ML18038A350

Annual Radiological Environ Operating Rept for 1990. W/910426 Ltr

ML18038A350
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1990
From:	Firlit J NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NMP76356, NUDOCS 9105020211
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ACCESSION NBR:9105020211 DOC.DATE: ~+6~ NOTARIZED: NO FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe DOCKET 05000220 50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION FIRLIT,J.F. Niagara Mohawk Power Corp.

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"Ann Radiological Environ Operating Rept for 1990."

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T N(AGA A H V MOHAWK NMP76356 NINE MILK POINT NUCLEAR STATION /P.O. BOX 32 LYCOMING, NEW YORK 13093/TELEPHONE (315) 343-2110 Joseph F. Firlit Vice President Nuclear Generation April 26, 1991 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 RE: Nine Mile Point Nuclear Station Unit 1 Facility Operating License DPR-63 Docket No. 50-220 Nine Mile Point Nuclear Station Unit 2 Facility Operating License NPF-69 Docket No. 50-410 Gentlemen:

In accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2, we are enclosing the Annual Radiolo ical Environmental 0 eratin Re ort for the period January, 1990 through December, 1990.

Any questions concerning the enclosed report should be directed to Hugh J. Flanagan at Nine Mile Point (315/349-2428).

Very ruly ours, C

Jo ph F. Firlit Vice President-Nuclear Generation JFF: HJF: caf (89RADPT1. HJF)

Enclosure (18 copies)

XC: USNRC Region I Resident Inspector (Unit 1/Unit 2) 9105020211 901231 PDR, ADOCK 05000220 PDR

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9105020211 NINE MILE POINT NUCLEAR STATION

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NIAGARA MOHAWK POWER CORPORATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 1990 - December 31, 1990 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

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so TABLE OF CONTENTS Pacae List of Tables List of Figures 1.0 Introduction 2.0 AQUATIC SAMPLES I Shoreline Sediment II Fish III Surface Water 12 3.0 DIRECT RADIATION 16 4.0 TERRESTRIAL SAMPLES 23 I Air Particulate/Iodine 24 II Milk 31 III Food Product 35 IV Land Use Census 37 5.0 INTERLABORATORY COMPARISON PROGRAM 39 6.0 HISTORICAL ENVIRONMENTAL SAMPLE DATA 41 7.0 CHANGES AND EXCEPTIONS TO THE PROGRAM 43

8.0 CONCLUSION

46 9.0 GENERAL REFERENCE MATERIAL 48 10.0 DATA TABLES 1990 51 11.0 FIGURES 147

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LIST OF TABLES Table No. Content ~acae Table 1 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Aquatic Program and Direct Radiation 52 Table 2 Sample Collection and Analysis, Site Radiological .Environmental Monitoring Program Terrestrial Program 53 Table 3 Environmental Sample Locations 54 Table 4 Radiological Environmental Monitoring 58 Program Annual Summary Table 5A Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/g-dry) 61 Table 5B Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/kg-dry) 62 Table 6A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 63 Table 6B Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet) 65 Table 7 Concentration of Gamma Emitters in Surface Water Samples 67 Table 8 Concentration of Tritium in Surface Water Samples 72 Table 9A Direct Radiation Measurement Results (mrem per standard month) 73 Table 9B Direct Radiation Measurement Results (mrem per quarterly period) 77 Table 10 Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity 81 Table 11 Environmental Airborne Particulate Samples-On-Site Stations, Gross Beta Activity 83 Table 12 Concentration of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples 85 Table 13 Environmental Charcoal Cartridge Samples-Off-Site Stations, I-131 Activity 100 Table 14 Environmental Charcoal Cartridge Samples-i On-Site Stations, I-131 Activity 102

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LIST OF TABLES (Continued)

Table No. Content Pacae Table 15 Concentration of Gamma Emitters in Milk 104 Table 16 Concentration of Iodine-131 in Milk 110 Table 17A Concentration of Gamma Emitters in Food Products (pCi/g-wet)

Table 17B Concentration of Gamma Emitters in Food Products (pCi/kg-wet) 112 Table 18 Milk Animal Census 113 Table 19 1990 Residence Census 115 Table 20 Interlaboratory Comparison Program Results 116 Table 21 Historical Environmental Sample Data Shoreline Sediment (Control) 123 Table 22 Historical Environmental Sample Data Shoreline Sediment (Indicator) 124 Table 23 Historical Environmental Sample Data Fish (Control) 125 Historical Environmental Sample Data Fish (Indicator) 126 Table 25 Historical Environmental Sample Data Surface Water (Control) 127 Table 26 Historical Environmental Sample Data Surface Water (Indicator) 128 Table 27 Historical Environmental Sample Data Surface Water Tritium (Control) 129 Table 28 Historical Environmental Sample Data Surface Water Tritium (Indicator) 130

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LIST OF TABLES (Continued)

Table No. Content Pacae Table 29 Historical Environmental Sample Data Air Particulate Gross Beta (Control) 131 Table 30 Historical Environmental Sample Data Air Particulate Gross Beta (Indicator) 132 Table 31 Historical Environmental Sample Data Air Particulates (Control) 133 Table 32 Historical Environmental Sample Data Air Particulates (Indicator) 134 Table 33 Historical Environmental Sample Data Air Radioiodine (Control) 135 Table 34 Historical Environmental Sample Data Air Radioiodine (Indicator) 136 Table 35 Historical Environmental Sample Data Environmental TLD (Control) 137 Table 36 Historical Environmental Sample Data (A E) Environmental TLD (Indicator) . 138 Table 37 Historical Environmental Sample Data Milk (Control) 143 Table 38 Historical Environmental Sample Data Milk (Indicator) 144 Table 39 Historical Environmental Sample Data Food Products (Control) 145 Table 40 Historical Environmental Sample Data Food Products (Indicator) 146

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LIST OF FIGURES Fi ure No. Content Pacae Figure 1A Off-Site Environmental Station and 148 TLD Locations Figure 1B Off-Site Environmental Station and TLD 149 Locations (Southern)

Figure 2 On-Site Environmental Station and TLD 150 Locations Figure 3 Nearest Residence and Food Product Locations 151 Figure 4 Milk Animal Census and Milk Sample 152 Locations Figure 5 New York State Map 153

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1~0 INTRODUCTION This report is submitted in accordance with Appendix A (Technical Specifications), Section 6.9.1.d to License DPR-63, Docket No. 50-220 for the Nine Mile Point Nuclear Station Unit 1 and Section 6.9.1.7 to License NPF 69, Docket No. 50-410 for the Nine Mile Point Nuclear Station Unit 2 for the calendar year 1990.

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 Science and Technology (EA). EA also performs the sampling required for the Station's SPDES Permit. The same staff from EA is utilized to perform the majority of 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 present sample collection and analysis schedule required by the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1 and 2 (NMPNS) is listed in Table 1 and 2.

The REMP samples were analyzed by Teledyne Isotopes and by the Site Enviranmental Laboratory during 1990. The following samples were analyzed by the Site Environmental Laboratory:

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 analysis only)

Food products (gamma spectral analysis)'he remainder of the sample analyses, as outlined in Table 1 and 2, were analyzed 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 1990. Several radionuclides could possibly fall t into two of the four groups. The first of these groups is naturally t

~ 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 2

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INTRODUCTION 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.

A second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's upper atmosphere.

The detonation frequency during the early 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on 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 vicinity of the site and was very evident in many of the sample media analyzed during 1981. Calculations from 1981 of the resulting doses to man from fallout related radionuclides in the environment show that the contribution from such nuclides (such as Sr-90 or Cs-137) is significant and second in intensity only to natural background radiation. Quantities of Nb-95, Zr-95, Ce-141, Ce-144, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and Co-60 were typical in air particulate samples during 1981 and have a weapons test origin.

During 1990, Cs-137 was the only radionuclide detected in environmental samples that has 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 particulates, air radioiodine and milk. Applicable radionuclides include I-131, Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, and La-140. Cs-137 was the only radionuclide in this category detected during 1990.

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 and therefore, make a distinction between the two sources difficult, not impossible. The only radionuclide falling into this category (as if applicable to the 1990 Nine Mile Point Radiological Environmental Monitoring Program) was Cs-137. The dose to man as a result of this radionuclide is small and significantly less than the radiation exposure from naturally occurring sources of radiation and from fallout.

The evaluation and interpretation of environmental data must be made at several levels including trend analysis, dose to man, etc. An attempt has been made not only to report the data collected during 1990, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. It is

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INTRODUCTION 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, concentrations in one sample that are two times the concentration of another, for example, are not significant overall. Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in another 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 57 mrem during 1990. This dose is a result of radionuclides of cosmic origin (for example, .Be-7), of a primordial origin (Ra-226, K-40, and Th-232) and, to a much smaller extent, of a

> man-made origin from weapons testing. A dose of 57 mrem, as a background dose, is significantly greater than any possible dose as a result of operations at the site during 1990.

Environmental Sam le 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 Station 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.l.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.

Radiolo ical Environmental Monitorin Pro ram Annual Summar Table 4 Table 4 contains a summary of basic statistics for environmental sample media as required by the Technical Specifications. Table 4 is in the format presented on Table 3 of the NRC Branch Technical Position (Revision 1 dated November 1979) to NRC Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants". The table is presented to meet the requirements of section 6.9.1.d and section 6.9.1.7 of the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2 respectively.

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2 0 A UATXC SAMPLBS I

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A VATIC SAMPLES SHORELINE SEDIMENT Sam le Collection Methodolo and Anal sis 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. 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 shipped and 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 lA (refer to Table 3 for location designations and descriptions).

Evaluation of Shoreline Sediment Data Tables 5A ahd 5B Shoreline sediment. samples were obtained in April and October of 1990 at one off-site control location (near Oswego Harbor) and at one indicator location (shoreline area just east of the site with recreational value).

The results of the shoreline sediment samples collected during 1990 at the indicator and control locations are shown on Table

5. Table 5A shows results in units of pCi/g (dry) for purposes of data evaluation. Table 5B shows results in units of pCi/kg (dry), as required by the Technical Specifications. Only the Sunset Beach location was required by the Technical Specifications during 1990.

Several radionuclides were detected in sediment samples using gamma spectral analysis. K-40 was detected at both the control location and indicator locations for both collection periods during 1990.. K-40 ranged in concentration from 13.6 pCi/g (dry) to 15.0 pCi/g (dry) at the control location and 16.1 pCi/g (dry) to 17.8 pCi/g (dry) at the indicator location. K-40 is a naturally occurring primordial radionuclide.

In addition to K-40, Ra-226 and AcTh-228 were also detected and are also naturally occurring radionuclides. Ra-226 was detected at-concentrations that. were representative of normal background level fluctuations. Ra-226 was found at concentrations of 1.70 pCi/g (dry) to 2.06 pCi/g (dry) at the indicator location and 0.84 pCi/g (dry) to 1.51 pCi/g (dry) at the control location.

AcTh-228 was detected twice at the control location at a concentration 0.44 pCi/g (dry). The AcTh-228 concentration ranged from 0.62 pCi/g (dry) to 0.68 pCi/g (dry) at the indicator location.

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2 ' A UATIC SAMPLES SHORELINE SEDIMENT (Cont'd)

B. Evaluation of Shoreline Sediment Data-Tables 5A and 5B (Cont'd)

Cs-137 was not detected at the control location during 1990.

Cs-137 was detected twice at the indicator location at a concentration of 0.28 pCi/g (dry). Cs-137 was detected in 1989 but had not been detected at this location in the past (1985 1988) .

The source of Cs-137 in 1990 indicator shoreline sediment samples is difficult to determine. Possible sources are fallout from past weapons or from site operations. It is highly probable that the Cs-137 is from fallout. Cs-137 has been detected in the past at control locations beyond the .influence of the site. 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 and chemical characteristics of the indicator samples. Other factors, which include changing lake level and. shoreline erosion, further complicate any consistency in 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 levels of Cs-137 at or greater than the concentration found in 1990 shoreline sediment.

Cs-137 in soil samples has been attributed to weapons testing fallout. Therefore, any shoreline sediment sample containing soil would reveal Cs-137. These factors support the likelihood that the trace amounts of Cs-137 detected in the indicator shoreline sediment samples is 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 0.0009 mrem to the same individual. This dose is very small when compared to average annual whole body doses due to natural background and may be considered insignificant. For the purpose of comparison, soil sampled at a location beyond any influence of the site contained Cs-137 at a concentration of 0.74 pCi/g. Using the same methodology and assumptions for that of sediment, an annual whole body dose of 0.002 mrem was calculated. Thus, it is shown that a dose to an individual at the shoreline is less than an individual would receive from soil. 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 this location were not collected prior to 1985.

2 ' A VATIC SAMPLES FISH A. Sam le Collection Methodolo and Anal sis 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 1 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 1A (refer to Table 3 for location designations and descriptions).

J B. Evaluation of Fish Data Tables 6A and 6B A total of thirty fish samples were analyzed as a result of collections in the spring season (June 1990) and in the fall season (September-October 1990). 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 oi'he lake discharges for the Nine Mile Point Unit N1 (02), and the James A. FitzPatrick (03) generating facilities.

The Oswego Harbor samples served as control samples while the NMP (02) and JAF (03) samples served as indicator samples.

Samples were analyzed for gamma emitters. 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 the Technical Specifications.

Spring fish sample collections were comprised of six separate species and fourteen individual samples. Brown trout, white sucker, lake trout, smallmouth bass and white perch were collected at the indicator locations (NMP and JAF). At the control location (Oswego Harbor) brown trout, white sucker, lake trout and yellow and white perch were collected.

A 2 ' A VATIC SAMPLES FISH (Cont'd)

Evaluation of Fish Data - Tables 6A and 6B (Cont'd)

Cs-137 was detected in four of the nine indicator samples and in three of the five control samples collected during the spring.

Indicator samples showed Cs-137 concentrations to be slightly greater than control results for some samples and slightly less than or equal to control results for other samples. The average indicator Cs-137 concentration was slightly greater than the average control concentration. The indicator results, however, are not significantly different from the control results and are therefore considered to be representative of background concentrations. The detected Cs-137 concentration in 3,ake trout was 0.035 pCi/g (wet) at one indicator sample location. The detected Cs-137 concentration in control samples was 0.033 pCi/g (wet) for lake trout. Cs-137 in brown trout was 0.035 pCi/g (wet) at one indicator location. Cs-137 was detected at the control sample location at the same concentration. .Cs-137 was not detected in white sucker samples at the indicator or control locations. Cs-137 was detected in a white perch sample at an indicator location at a concentration of 0.115 pCi/g (wet) and in a white perch sample at the control location at a concentration of 0.079 pCi/g (wet).

K-40 was detected in all of the spring samples collected. K-40 is a naturally occurring radionuclide and is not related to power plant operations. Detectable concentrations of K-40 in the indicator samples ranged from 4.00 to 8.78 pCi/g (wet) and 3.81 to 7.50 pCi/g (wet) for the control samples. Ra-226, also naturally occurring, was found at levels that ranged from 0.51 to 1.31 pCi/g (wet) at the indicator locations. Ra-226 was detected in all control samples and ranged in concentration from 0.31 to 1.45 pCi/g (wet). No other radionuclides were detected in the spring fish samples.

Fall fish sample collections were comprised of six separate species anl sixteen individual samples. Lake trout, brown trout, smallmouth bass, white sucker, and either white or yellow perch samples were collected at indicator sampling locations (NMP and ZAF). All six species were collected at the control location (Oswego Harbor).

Cs;137 was detected in six of the sixteen samples which included the control samples. Indicator samples showed an average Cs-137 concentration that was slightly greater than the control sample mean from the off-site location. The detected concentrations were not significantly different from one another because of the extremely small quantities detected. Cs-137 in lake trout samples at the indicator locations ranged from 0.032 to 0.036 pCi/g (wet) and was 0.025 pCi/g (wet) at the control location.

2 ' A VATIC SAMPLES FISH (Cont'd)

B. Evaluation of Fish Data Tables 6A and 6B (Cont'd)

Cs-137 was detected in white perch sampled at NMP at a concentration of 0.024 pCi/g (wet) and in yellow perch at the JAF location at a concentration of 0.036 pCi/g (wet). Cs-137 was not detected in either type of perch collected at the control location (Oswego Harbor). Cs-137 was detected in 1 of 2 brown trout samples from indicator locations at a concentration of 0.040 pCi/g (wet) and not detected at the control location. White sucker and smallmouth bass samples collected at indicator or control locations did not. reveal any detectable concentrations of Cs-137.

'Naturally occurring K-40 was detected in all of the fall samples collected. Detectable concentrations of K-40 in the indicator samples ranged from 4.87 to 6.75 pCi/g (wet) and 3.97 to 5.77 pCi/g (wet) for the control samples. Ra-226, also naturally occurring, was detected. intermittently at concentrations which ranged from 0.52 to 0.99 pCi/g (wet) for the indicator samples and from 0.37 to 0.77 pCi/g (wet) for the control 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 1979 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 0.028 pCi/g (wet) in 1986.

Control sample results have also decreased from a level of 1.2 pCi/g (wet) in 1976 to a level of 0.025 pCi/g (wet) in 1986.

Results from 1980 to 1986 have shown a fairly consistent decreasing trend for control and indicator samples. During 1987 through 1990, control and indicator mean results increased slightly when compared to 1986.

The general decreasing trend for Cs-137 is most probably a result of ecological cycling. The concentrations of Cs-137 detected since 1976 in fish are a result of weapons testing fallout, and the general downward trend in concentrations will continue as a function of ecological cycling and nuclear decay.

There was no apparent effect from the 1986 Chernobyl Nuclear Plant accident during 1986 relative to Cs-137 results in fish samples although an effect may have been detected during the period of 1987 through 1990 since both indicator and control location mean results increased slightly.

Tables 23 and 24 show historical environmental sample data for fish.

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2 ' A UATIC SAMPLES FISH (Cont'd)

B. Evaluation of Fish Data Tables 6A and 6B (Cont'd)

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 consumes 21.0 kg of fish per year (Regulatory Guide 1.109 maximum exposed age group) and the fish consumed contains an average Cs-137 concentration of 0.044 pCi/g (wet) (annual mean result of indicator samples for 1990),

the whole body dose received would be 0.066 mrem per year. The critical organ in this case is the liver which would receive a calculated dose of 0.10 mrem per year. The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mile Point area (indicator samples). No radiological decay is assumed for the calculation of doses.

. Conservative whole body and critical organ doses can be calculated for the consumption of fish from the control location as well. In this cas'e the consumption rate is assumed to remain the same (21.0 kg per year ) but the average annual Cs-137 concentration for the control samples is 0.043 pCi/g (wet). The calculated Cs-137 whole body dose is 0.064 mrem per year and the associated dose to the liver is 0.098 mrem per year.

In summary, the whole body and critical organ doses observed as a result of consumption of fish is small. Doses received from the consumption of indicator and control sample fish are approximately the same. The doses from indicator sample fish are slightly greater, although well within natural variability.

For example, the whole body and organ doses from the control samples were greater during 1985. Doses from both sample groups are considered background doses.

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2 ' A VATIC 8AMPLE8 SURFACE WATER A. Sam le Collection Methodolo and Anal sis

'urface 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 control location because of the distance from the site as well as the result of the lake current patterns and current patterns from the Oswego River located nearby (see Figure 1A) .

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 discharge 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 samples from each of the locations is saved and composited to form quarterly composite samples for each calendar quarter. Quarterly composite samples are analyzed for tritium.

In addition to the FitzPatrick and Oswego Steam Station facilities, data are presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canals and city water from the City of Oswego. The latter three locations are not required by the Technical Specifications, but are optional samples. Monthly composite samples from these three locations are analyzed for gamma emitters and quarterly composite samples are analyzed for tritium.

Sampling for ground water and drinking water, as found in Section 3.12.1 of the Nine Mile Point Unit 2 Technical Specifications, was not required during 1990 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.

Surface water sample locations are shown on Figure 1A (refer to Table 3 for location designations and descriptions).

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SURFACE WATER 2~0 A UATIC 8AMPLE8 (Cont d)

Evaluation of Data Tables 7 and 8 Surface water samples were analyzed monthly for gamma emitters (using gamma spectral analysis) during 1990. Tritium analyses were performed quarterly. Quarterly samples (i.e., analysis for tritium) were composite samples.

The analytical results for the 1990 surface water samples showed no evidence of plant related radionuclide buildup in the surface water in the vicinity of the site. Indicator samples were collected from the inlet canal at the James A. FitzPatrick facility. The control location samples were collected at the inlet canal of Niagara Mohawk's Oswego Steam Station. These two locations are required to be sampled by the Technical Specifications. Tables 7 and 8 show the results of surface water samples analyzed during 1990.

Gamma spectral analysis was performed on twenty four monthly composite samples (two locations) required by the Technical

. Specifications. In addition, three optional sample locations were evaluated. These included the Nine Mile Point Nuclear Station Unit 1 and Unit 2 inlet canals and the City of Oswego drinking water supply. The drinking water supply composite samples consisted of twice per week grab samples. Only two radionuclides were detected in samples from the five locations over the course of 1990. Both radionuclides were naturally occurring.

K-40 was detected consistently in both Technical Specification required intake canal samples. K-40 in James A. FitzPatrick inlet canal samples ranged from 50 to 283 pCi/liter. K-40 in the Oswego Steam Station inlet canal ranged from 38 to 263 pCi/liter. The Nine Mile Point Unit 1 inlet canal, Unit 2 inlet canal and the city water samples showed K-40 detected in nearly all of the twelve monthly samples for each location. For these samples, K-40 concentrations ranged from 58 to 262 pCi/liter, from 70 to 322 pCi/liter and from 45 to 304 pCi/liter respectively.

Ra-226 was detected intermittently in samples from all five locations. Ra-226 was detected intermittently in samples from the Nine Mile Point Unit 1 inlet canal and ranged from 63 to 135 pCi/liter. The Nine Mile Point Unit 2 inlet canal showed Ra-226 detected at concentrations that ranged from 73 to 148 pCi/liter.

Samples from the FitzPatrick location showed Ra-226 that ranged from 74 to 126 pCi/liter. The control sample location (Oswego Steam Station) showed Ra-226 that ranged in concentration from 70 to 154 pCi/liter. The city water samples results showed Ra-226 that ranged from 69 to 168 pCi/liter.

-13

2 ' A VATIC SAMPLES III SURFACE WATER (Cont'd)

B. Evaluation f Data Tables 7 and 8 (Cont'd)

Tritium samples are quarterly samples that are a composite of the appropriate calendar months. Tritium was detected in samples taken at all five locations. Six of the sample results showed that tritium was not detected within the analytical sensitivity of the analysis. The City of Oswego drinking water showed tritium concentrations ranging from 290 to 450 pCi/liter with a mean of 353 pCi/liter. Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 220 to 290 pCi/liter and showed a mean concentration of 250 pCi/liter.

Inlet canal samples taken at Nine Mile Point Unit 1'and Unit 2 showed tritium concentrations ranging from 190 to 320 pCi/liter

. and 140 to 260 pCi/liter respectively. The annual mean concentration was 255 pCi/liter and 210 pCi/liter respectively.

The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from 260 to 320 pCi/liter with a mean of 290 pCi/liter.

Review of past environmental data for Cs-137 from 1979 through 1989 shows that this radionuclide was detected only once at the control location during 1979 at a concentration of 2.5 pCi/liter. Cs-137 at the indicator location (JAF inlet canal) was detected only once during 1982 at a concentration of 0.43 pCi/liter. The 1979 control sample result is suspect and may have been a result of contamination during handling or instrument background since Cs-137 was not detected in the indicator inlet canal. The one result from the 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 1990 in surface water samples.

-14

2 0 A VATIC SAMPLES SURFACE WATER (Cont'd)

B. Evaluation of Data Tables 7 and 8 (Cont'd)

Other plant related radionuclides detected during a review period of 1979 1989 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 1990 in surface water samples.

Tables 25 and 26 show historical environmental sample data for surface water using gamma spectral analysis.

Previous annual mean results for tritium at the indicator sample

. location (FitzPatrick inlet canal) has decreased since 1976.

Mean sample results reviewed from 1976 through 1990 showed a peak average value of 627 pCi/liter (1976) and a minimum value of 227 pCi/liter (1980). The annual mean tritium result at the indicator location for 1990 was 250 pCi/liter.

Mean tritium results for the control location (Oswego Steam Station) can not be evaluated with regard to long term historical data since sampling was only initiated at this location in 1985. Some idea of the variability of control sample data can be obtained, however, by review of previous data from the City of Oswego drinking water samples. The drinking water samples are not likely to be affected by the station because of the effects of the distance, lake currents, and the discharge of the Oswego River. Therefore, this previous sample data represents acceptable control sample data for evaluation purposes.

Historical mean annual tritium results from previous city water samples (1976-1984) and Oswego Steam Station samples (1985-1990) 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 1990 have remained relatively consistent. The annual mean result for 1990 was 290 pCi/liter.

Tables 27 and 28 show historical environmental sample data for surface water tritium.

-15

3 0 DXRECT RADZATZOM

-16

3 ' DIRECT RADIATION A. Sam le Collection Methodolo and Anal sis Thermoluminescent dosimeters (TLD's) are used to measure direct radiation (gamma dose) in the environment. TLD's are obtained from Teledyne Isotopes on a quarterly basis and are read at Teledyne Isotopes'acility in Westwood, New Jersey. 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 for a transit dose by use of the data from shipment control TLD's.

Five different types of areas are evaluated by environmental TLD's. These areas include on-site areas (areas within the site boundary not required by the Technical Specifications); the site boundary area in each of the sixteen meteorological sectors, an outer ring of TLD's located four to five miles from the site in eight available land based meteorological sectors, special interest TLD's located at sites of high population density and control TLD's located at sites beyond significant influence of the site. Special interest TLD's are located at or near large

. industrial sites, schools, proximal towns or'ommunities or other special activity areas. Control TLD's are located to the southwest, south, south-southeast and northeast of the site at distances of 12.6 to 26.4 miles.

TLD's used during 1990 were composed of rectangular teflon wafers impregnated with 254 CaSO<. Dy Phosphor. 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.

Environmental TLD locations are shown on Figures 1A, 1B, and 2 (refer to Table 3 for location designations and descriptions).

B. Evaluation of TLD Data Tables 9A and 9B TLD's were collected and read once per. quarter during the 1990 sample year. The TLD results are, for the most part, an average of eight independent readings at each location and are reported in mrem per standard month (Table 9A) and in mrem per quarterly period (Table 9B).

TLD's required by the Technical Specifications include two TLD's at each location with four independent readings per TLD.

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 1990, TLD's were collected during the weeks of March 26, 1990, June 25, 1990, September 24, 1990 and December 24, 1990.

-17

i 3 0 DIRECT RADIATION Evaluation of TLD Data Tables 9A and 9B (Cont'd)

Overall TLD results are evaluated by organizing environmental TLD's into five different groups. These groups include: (1) on-site TLD's (TLD's within the site boundary not required by the Technical Specifications), (2) site boundary TLD s (one in each of the sixteen 22 1/2 degree meteorological sectors), (3) a ring of TLD's four to five miles from the site in each of the land based 22 1/2 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 26.4 miles from the site.

Most of the TLD locations required by the Technical Specifications during 1990 were initiated 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 - 1989

~

results. Other TLDs, which include a few TLDs required by the Technical Specifications (i.e., numbers 7, 14, 15, 18, 23, 49, 56, and 58) and other optional TLDs, can be compared to results prior to 1985 since these TLDs were established prior to 1985.

On-site TLD's are TLD's at special interest areas and, with the exception of TLD numbers 7 and 23, are not required by the Technical Specifications. These are located near the 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.

These results ranged from 3.6 to 12.9 mrem per standard month.

TLD N3 is located in the vicinity of Nine Mile Point Unit 2 and is between the Unit 1 facility and the FitzPatrick facility.

The results for TLD N3 were approximately double the results of the other TLD's during 1990 because of the effects from the Unit 1, Unit 2 and the FitzPatrick facilities.

Other on-site TLD's include special interest TLD's located near the north shoreline of the Unit 1, Unit 2 and FitzPatrick facilities, but in close proximity to radwaste facilities and the Unit 1 reactor building. These TLD's include numbers 27, 28, 29, 30, 31, 39, and 47. Results for these TLD's during 1990 were variable and ranged from 4.6 to 33.0 mrem per standard month as a result of activities at the radwaste facilities and the operating modes of the generating facilities. Results for 1990 are consistent with the ranges of variability noted in 1989 for TLD's at or near these locations. TLD's in this group ranged up to approximately seven times control TLD results.

-18

3 ' DIRECT RADIATION Evaluation of TLD Data Tables 9A and 9B (Cont'd)

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 107. TLD's 103, 106 and 107 are located to the east 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 1990 showed these TLD's ranged from 4.5 6.6 mrem per standard month and were consistent with the 1989 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 22 1/2 degree meteorological sectors. These TLD's include numbers 75, 76, 77, 23 78, 79, 80, 81, 82, 83, 84, 7, 18, 85, 86 and 87. TLD numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18 showed results that were consistent with control TLD results and ranged from 3.6 to 6.4 mrem per standard month. Site boundary TLD's during 1990 were consistent with 1985-1989 results. TLD numbers 75, 76, 77, 23, 95, 86, and 87 showed results that ranged up to three times the results of control TLD's. These results ranged from 4.4 to 14.8 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.

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, 110 and 111. Net site boundary doses for each quarter in mrem ger standard month are as follows:

guarter Net Site Bounda Dose*

1 -0.1 2 +0.2 3 +F 5 4 -0 '

• 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 proximity to the generating facilities and are not accessible to members of the public.

-19

3 ' DIRECT RADIATION B. Evaluation of TLD 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 Specifications. At this distance, TLD s are not present in eight of the sixteen meteorological sectors that are located over Lake Ontario.

Results for this group of TLD's during 1990 fluctuated slightly as a result of changing naturally occurring conditions and the different concentrations of naturally occurring radionuclides in the ground at each of the locations. These TLD's were established in 1985 and include numbers 88, 89, 90, 9X, 92, 93, 94 and 95. Results fluctuated from 3.6 to 6.3 mrem per standard month. These results are generally consistent with control TLD results during 1990. Results for this group of TLDs were consistent with the 1985 1989 results. Results were also consistent with other off-site TLD results during 1990 and previous to 1990.

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, and the off-site environmental laboratory. Many of these TLDs are required by the Technical Specifications. Others are optional.

This group of TLD's include numbers 9, 10, 11, 12, 13, 15, 19, 51'2i 53ITLD54'5I and 109.

56'8I 96I 97I 98i 99'00( 101i 102I 108 numbers 108 and 109 are TLD locations that were established to assist in the evaluation of the critical residence. Results ranged from 3.2 to 6.5 mrem per standard month. All the TLD results from this group were within the general variation noted for the control TLD's. Results during 1990 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 TLD's are required by the Technical Specifications and include numbers 14 and 49. Optional control locations are TLD numbers 8, 110, and 111 and were added to the program to expand the data base for control TLD's. Results for 1990 ranged from 3.7 to 6.0 mrem per, standard month. Results from 1990 were consistent with previous years results. However, an annual average increase was noted in 1986. This increase may have been a result of the Chernobyl Nuclear Plant accident and was not noted during 1987-1990.

-20

3 ' DIRECT RADIATION r

Evaluation of TLD Data Tables 9A and 9B (Cont'd)

Review of past TLD results re ired b the Technical S ecifications 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 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 1990.

Technical Specification TLDs located at, the site, boundary averaged 6.2 mrem per standard month during 1985. During 1986, 1987, 1988, and 1989 site boundary TLDs averaged 7.0, 6.1, 6.4g and 5.9 mrem per standard month respectively. As noted previously, this group of TLDs can fluctuate because several of these TLDs are located in close proximity to the .generating facilities. An increase was noted during 1986 although such an increase was noted for all TLDs including control TLDs. During 1990, site boundary TLDs averaged 5.8 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 during 1985. During 1986, 1987, 1988 and 1989 off-site sector TLDs averaged 6.0, 5.2, 5.3 and 4.9 mrem per standard month respectively. The 1986 results demonstrated an increase for this group of TLDs.

Results for 1990 for the group averaged 4.7 mrem per standard month. This is fairly consistent with previous years results.

Special interest Technical Specification TLDs are located at areas of high population density, such as major work sites, communities, schools, etc. and at residences near the site (critical receptor areas). This group of TLDs averaged 5.3 mrem per standard month during 1985. During 1986, this same group of TLDs averaged 6.1 mrem. The 1987 results showed a decrease when compared to the 1985 and 1986 results and averaged 5.1 mrem per standard month. 1988 and 1989 results averaged 5.3 and 4.8 mrem per standard month respectively. 1990 results for these locations averaged 4.7 mrem per standard month.

The final group of TLDs required by the Technical Specifications is the control group. This group utilizes two TLD locations positioned well beyond the site. Results from 1985 for the control group averaged 5.4 mrem per standard month. During 1986, this same 'group of TLDs averaged 6.3 mrem per standard month. A marked increase was noted in the second quarter of 1986. The increase may have been a result of the Chernobyl

-21

3 ' DIRECT RADIATION B. Evaluation of TLD Data Tables 9A and 9B (Cont'd)

Nuclear Plant accident. Results for 1987, 1988 and 1989 averaged 5.2, 5.4 and 4.6 mrem per standard month respectively.

Results for 1990 averaged 4.6 mrem per standard month and showed levels slightly less than previous years.

Tables 35 and 36A-36E show the historical environmental'ample data for environmental TLD's.

During 1990, all environmental TLD groups required by the Technical Specifications were consistent with results observed during 1989. Overall, environmental TLD results for 1990 showed no significant impact from direct radiation measured outside the site boundary.

-22

TBRRSSTRXAL SAMPLBS

-23

4 ' TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE A. Sam le Collection and Methodolo The air sampling stations required by the Technical Specifications are located in the general area of the site boundary (within 0.7 miles) in sectors of highest calculated meteorological deposition factors (D/Q) based on historical meteorological data. These stations (R-l, 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 community having the highest calculated deposition factor (D/Q) based on historical meteorological data.

This 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.

In addition to the Technical Specification required locations, there are six sampling stations located within the site boundary (D1, G, H, I, J, and K). These locations generally surround the area occupied by the three generating facilities, but are well within the site boundary. One other hir 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, airborne particulates 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 intake line of a vacuum sampler. Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to absorb airborne radioiodine. The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis, or as required by dust loading. Gross beta analysis is performed for the individual particulate filters on a weekly basis. Charcoal cartridges are analyzed weekly for radioiodine by GeLi detector.

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.

Air sampling stations are shown in Figures 1 and 2 (refer to Table 3 for location designations and descriptions).

-24

4 ' TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont'd)

B. Evaluation of Air Particulate Gross Beta Tables 10 and 11 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 sample locations. Five of the nine off-site locations are required by the Technical Specifications. These sample locations are R-l, 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 allocations samples from location R-5 and 208 indicator samples from R-l, R-2, R-3, and R-4 were collected and analyzed during 1990.

The minimum, maximum, and average gross beta results. for sample locations required by the Technical Specifications are presented below.

Location ** ~Minimu

• Maximum* AveracVe*

R-1 0. 005 0.022 0.014 R-2 0. 007 0.022 0.014 R-3 0.006 0.020 0.013 R-4 0.006 0.023 0.014 R-5 (control) 0.003 0.027 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. Review of air particulate gross beta concentrations shows that no significant increases in concentration occurred during 1990.

In general, the trend in air particulate gross beta activity has been one of decreasing activity since 1977 (extent of the review period). The mean gross beta concentration at control locations has decreased from a level of 0.165 pCi/m~ in 1981 to 0.013 in 1990. Results from indicator air sampling locations ranged from 0.151 pCi/m~ in 1981 to 0.014 pCi/m~ in 1990. For both indicator locations and control location, the gross beta concentration

-25

4 ' TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont'd)

B. Evaluation of Air Particulate Gross Beta (Cont')

Tables 10 and ll during 1977 to 1987 fluctuated with the detonation of thermonuclear weapons. The Technical Specification control and indicator results during 1990 averaged 0.013 pCi/m~ and .014 pCi/m~ respectively which represented the lowest level recorded to date.

Tables 29 and 30 show historical environmental sample data for air particulate gross beta levels.

C. Evaluation of Monthl Air Particulate Com osites 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 requiied 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 but one of the monthly composite samples from the locations required by the Technical Specifications. Be-7 ranged from 0.043 to 0.089 pCi/m~ for the Technical Specification indicator locations (R-1, R-2, R-3, and R-4). The Technical Specification control location (R-5) results showed Be-7 ranging from 0.049 to 0.080 pCi/m~.'-40 was found intermittently in the monthly composite samples required by the Technical Specifications.

K-40 ranged from 0.013 to 0.062 pCi/m~ at the control location (R-5) and 0.007 to 0.046 pCi/m at the indicator locations.

Ra-226 ranged from 0.010 to 0.028 pCi/m~ at the indicator locations required by the Technical Specifications. The Technical Specification control location results ranged from 0.016 to 0.024 pCi/m~.

As a result of the Chernobyl Nuclear Plant accident in April 1986, several radionuclides attributable to the fission process were detected in air particulate samples during 1986.

Detectable radionuclides included Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, La-140 and I-131. These radionuclides were not detected during 1990.

No other radionuclides were detected at Technical Specification locations using gamma spectral analysis during 1990.

-26

4 ' TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont ')

C. Evaluation of Monthl Air Particulate Com osites Table 12 (Cont'd)

The location, concentration range and mean, and frequency of occurrence of each radionuclide detected during 1990 at the Technical S ecification re ired locations are included below.

Radionuclide Location Rancae*

Ra-226 Indicator 0.010 0.028 0.018 8/48 Ra-226 Control 0.016 0.024 0.019 4/12 K-40 Indicator 0.007 0.046 0.026 34/48 K-40 Control 0.013 0.062 0.029 11/12 Be-7 Indicator 0.043 0.089 0.067 48/48 Be-7 Control 0.049 0.080 0.064 11/12

• Results in units of pCi/m~.

• • Frequency is the number of times detected over the number of samples.

Historically, the naturally occurring radionuclides Ra-226, K-40 and Be-7 have shown fluctuations that are representative of natural changing conditions. No significant trends were noted during 1990.

Co-60 has fluctuated in air particulate samples as a result of previous weapons testing. Co-60 average concentrations at the indicator and control locations from 1977 to 1978 decreased from approximately 0.0176 to 0.0022 pCi/m . Average concentrations decreased significantly during 1979 and 1980 when compared to 1977. These results were 0.007 to 0.0016 pCi/m respectively.

1981 and 1982 average Co-60 concentrations decreased to 0.0007 and 0.0006 pCi/m~. Average indicator and control concentrations were approximately equal during 1979 to 1982. The 1983 indicator mean Co-60 concentration was 0.0007 pCi/m~ or slightly greater than the 1982 concentration. The 1983 control mean Co-60 concentration was also 0.0007 pCi/m~ which was slightly greater than 1982 control results. As noted in previous annual reports, however, a portion of the Co-60 detected during 1983 was attributed to contamination, during handling of the unused filters prior to installation. Co-60 was detected during the first quarter of 1984 and averaged 0.0008 pCi/m~ at the control stations and 0.0012 pCi/m~ at the indicator stations. However, the 1984 Co-60 positive results were a result of contamination during handling and not a result of operations at the site.

This analysis was presented in the 1984 annual report. The general reduction in previous indicator and control Co-60 concentrations (1981 1983) was a result of nuclear decay and ecological cycling of Co-60 initially produced by the 1980 Chinese weapons test. Co-60 was not detected during 1985 1986 in air particulate samples from either indicator or control

-27

4 ' TERRESTRIAL SAMPLES

, I AIR PARTICULATE/IODINE (Cont'd)

C. Evaluation of Monthl Air Particulate Com osites Table 12 (Cont'd) locations. During 1987, Co-60 was detected once at a concentration of 0.0017 pCi/m~ at an optional air monitoring station. However, the Co-60 detected during 1987 was a result of contamination from improper handling of the sample, and not as a result of effluents from the site. This evaluation is contained in the 1987 annual report. Co-60 was not detected during 1988. During 1989 Co-60 was detected at one on-site optional location during November at a concentration of 0.009 pCi/m~. The Co-60 was attributed to operations at the FitzPatrick facility and was presented in the 1989 annual report. Results from 1990 showed that Co-60 was not detected from either Technical Specification control or indicator sample locations.

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~. Cs-137 average concentrations at indicator and control locations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCi/m respectively. Average concentrations during 1980 and 1981 were approximately equal at control and indicator locations. Cs-137 during 1980 was approximately equal to 1979 and increased slightly in 1981. The 1980 and 1981 average concentrations were 0.0014 and 0.0016 pCi/m~ respectively. The mean 1982 concentration for Cs-137 decreased to 0.0004 pCi/m~. The 1983 mean Cs-137 concentration for the indicator and control composite samples were 0.0002 and 0.0002 pCi/m~ which was a reduction from 1982 results. Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite samples. As noted above for the average annual Co-60 results, the reduction in Cs-137 results since 1981 is attributed to nuclear decay and ecological cycling of Cs-137 initially produced by the 1980 Chinese weapons test. Cs-137 was not detected during 1985 in air particulate samples. Cs-137 was detected during 1986 as a result of the Chernobyl Nuclear Plant accident in April 1986. Mean Cs-137 concentrations for indicator and control sample locations were 0.0183 and 0.0193 pCi/m respectively. During the period of 1987-1990, Cs-137 was not detected.

Prior to 1984, several radionuclides were detected that were associated with the 1980 Chinese weapons test and other weapons tests prior to 1980. These radionuclides were not detected during 1984 or 1985 as a result of nuclear decay and ecological cycling. These include Zr-95, Ce-141, Nb-95, Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140. In addition, La-140 was detected once during 1983 and infrequently during 1978 and 1981. La-140

-28

TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont'd)

C. Evaluation of Monthl Air Particulate Com osites - Table 12 (Cont'd) not detected during 1984 or 1985. 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. All of these, with the exception of Cs-134 and particulate I-131, were detected subsequent to the 1980 Chinese weapons test (1981

'as 1983). These radionuclides were not 'detected during 1984 1985. The concentrations detected during 1986 as a result of the Chernobyl accident were generally greater than the concentrations detected as a result of the 1980 Chinese weapons test. The presence of the radionuclides from the Chernobyl facility, however, extended over a very brief period (two months) while many of the radionuclides from the 1980 Chinese weapons test were present for approximately two years. During 1987 through 1990, none of the radionuclides associated with the 1986 Chernobyl accident or past weapons testing were detected in

. air particulate samples.

Tables 31 and 32 show historical environmental sample data for air particulate composites.

Evaluation of Airborne Radioiodine Tables 13 and 14 During the 1990 sampling program, airborne radioiodine was not found in any of the fifty-one weekly samples from the control location required by the Technical Specifications. LLD values at the control location ranged from 0.005 0.061 pCi/m~.

I-131 has been detected in the past at control locations.

Durinp 1976, the mean off-site I-131 concentration was 0.60 pCi/m . The 1977 mean I-131 concentration decreased to 0.32 pCi/m~ and for 1978 the concentration decreased by a factor of ten to 0.03 pCi/m~. During 1979 1981 and 1983 1985, I-131 was not detected. I-131 was detected once during 1982 at a concentration of 0.039 pCi/m~. Results from 1986 showed that I-131 was detected at the control location. This was a result of the 1986 Chernobyl Nuclear Plant accident. The I-131 mean result was 0.151 pCi/m~. I-131 was not detected at the control location during the period 1987 through 1990.

During 1990, the indicator locations required by the Technical Specifications (approximate site boundary locations) showed no detectable levels of I-131. LLD values for I-131 ranged from 0.006 0.037 pCi/m~. During 1990, I-131 was not detected at any of the optional monitoring locations that were not required by the Technical Specifications.

-29

4 0 TERRESTRIAL SAMPLES e

I AIR PARTICULATE/IODINE (Cont ')

D. Evaluation of Airborne Radioiodine Tables 13 and 14 (Cont'd)

I-131 at indicator locations has been detected in the past and was detected at a mean concentration of 0.33 and 0.31 pCi/m~

during 1976 and 1977. The average concentration decreased to 0.04 pCi/m~ during 1978 and was not detected during 1979. The 1980-1982 average concentrations were 0.013, 0.029, and 0.016 pCi/m which were reductions in view of previous I-131 concentrations. During 1983, the mean I-131 concentration was 0.028 pCi/m which represented a slight increase compared to 1982. For the most part, I-131 in indicator and control samples was a result of I-131 from weapons testing. A small portion of the concentrations detected may have been a result of operations at the site. The concentrations detected during 1983 at the on-site samplestations were a result of operations at the site.

I-131 was not detected in any of the 1984 or 1985 samples.

During 1986, I-131 was detected at the indicator locations at a mean concentration of 0.119 pCi/m~ as a result of thy Chernobyl Nuclear Plant accident. I-131 was found at a mean concentration of 0.014 pCi/m~ during 1987 and was a result of operations at the site. As noted previously, I-131 was not found at the Technical Specification required indicator locations during 1988 through 1990.

Tables 33 and 34 show the historical environmental sample data for airborne radioiodine.

-30

0 4 ' TERRESTRIAL SAMPLES II MILK A. Sam le Collection Methodolo and Anal sis 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 and shipped fresh to the analytical laboratory within thirty-six hours of collection in insulated shipping 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 Specifications require three sample locations within 5.0 miles of the site with the highest calculated deposition factors. During 1990, there were no milk sample locations within 5.0 miles that could be sampled.

However, there were several optional locations beyond five miles that were sampled.

A fourth sample location required by the Technical Specifications is located in a least prevalent wind direction from the site. This location is in the southwest sector and serves as a control location.

Milk samples are collected twice per month (April December) and analyzed for gamma emitters and I-131. Samples are collected and analyzed in January - March in the event I-131 is detected in November and December of the preceding year.

The milk sample locations are found on Figure 4. (refer to Table 3 for location designations and descriptions).

B. Evaluation of Milk Data Tables 15 and 16 Milk samples were collected from a total of six indicator locations (within 10 miles of the site) and one control location (beyond 10 miles from the site) during 1990. The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site. During 1990, there were no milk sample locations within 5.0 miles of the site. The locations that were sampled during 1990 are located from 5.5 to 9.5 miles from the site. The only sample location required by the Technical Specifications during 1990 was the control location which was located 17.0 miles to the southwest of the site (location N65). Sample location descriptions for all milk sample locations utilized during 1990 are listed below.

-31

4 ' TERRESTRIAL SAMPLES II MILK B. Evaluation of Milk Data Tables 15 and 16 (Cont'd)

Location No. Direction From Site Distance From Site miles 7 ESE (107 ' 5.5 16 S (190') 5.9 50 E (93) 9.3 55 ~ E ( 95 ) 9.0 60 E ( 90') 9.5 4 ESE (113') 7.8 65 (Control) SW (220') 17.0 During 1990, milk samples were collected at each of the six indicator locations and the control location in the first half and the second half of each month. Samples were collected during the months of April. through December 1990. Since I-131 was not detected during November and December of 1989, no .additional samples were collected in January through March of 1990. 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 1990. K-40 was detected in all indicator samples. Indicator sample location concentrations ranged from 1320 pCi/liter to 1860 pCi/liter while K-40 concentrations at the control location ranged from 1410 pCi/liter to 1770 pCi/liter. Ra-226 ranged from 50 to 204 pCi/liter at the indicator locations and 93 to 192 pCi/liter at the control location. Ra-226 occurred intermittently in milk samples. K-40 and Ra-226 are naturally occurring radionuclides and are found in many of the environmental media sampled.

During 1990, Cs-134 or Cs-137 was not detected in any control or indicator location milk samples. Cs-137 had been detected once in 1988 and was attributed to the use of silage containing trace amounts of Cs-137 from the 1986 Chernobyl Nuclear Plant accident.

No other radionuclides were detected in milk samples using gamma spectral analysis.

-32

TERRESTRIAL SAMPLES II MILK B. Evaluation of Milk Data Tables 15 and 16 (Cont'd)

Milk samples were collected and analyzed twice per month for I-131. I-131 was not detected during 1990 in any of the indicator or control samples. All 1990 I-131 milk sample results are reported as the lower limit of detection (LLD). The LLD results for 1990 milk samples ranged from <0.10 pCi/liter to

<0.50 pCi/liter.

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 1981 remained fairly consistent and ranged from 8.1 (1980) to 17.1 pCi/liter (1977) at the indicator locations. The 1982 indicator mean was 5.7 pCi/liter which showed a decrease when compared to 1976 1981. Cs-137 in milk during 1983 yielded a mean of 7.2 pCi/liter which was slightly greater than the 1982 mean but was less thon the 1976 1981 mean range. During 1983, however, Cs-137 was detected in only 3 of the 66 samples, while in 1982, Cs-137 was detected in 10 of the 54 samples analyzed. Cs-137 was not detected during 1984 or 1985 in indicator milk samples. Results from 1986 showed a mean Cs-137 concentration of 8.6 pCi/liter at the indicator locations. Cs-137 in 1986 milk samples was a result of the 1986 Chernobyl Nuclear Plant accident. During 1987, Cs-137 was found in two indicator samples only at a mean concentration of 6.8 pCi/liter and was also a result of the Chernobyl accident. The 1988 results showed Cs-137 was detected only once at a concentration of 10.0 pCi/liter and was attributed to the Chernobyl accident. No Cs-137 was detected in milk samples during 1989 or 1990.

At the control location, Cs-137 has remained fairly consistent for all years from 1978 1982 except for 1979 and 1982. For these years, this radionuclide was not detected. Control samples were not obtained prior to 1978. Cs-137 ranged from 3.9 5.8 pCi/liter during 1978 1981. Cs-137 was not detected at the control location during 1982, 1983, 1984, or 1985. The absence of Cs-137 during 1982 through 1985 may be a result of a two to five year time interval since the last weapons test.

Results from 1986 showed a mean Cs-137 concentration of 8.4 pCi/liter at the control location. The positive Cs-137 results during 1986 were a result of the Chernobyl Nuclear Plant accident-. Cs-137 was not detected during 1987 through 1990 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 result of nuclear decay and ecological cycling.

-33

4~0 TERRESTRIAL SAMPLES II MILK B. Evaluation of Milk Data - Tables 15 and 16 (Cont'd)

An evaluation of historical data for I-131 in milk samples shows that annual mean results ranged from 0.19 pCi/liter to 6.88 pCi/liter at the indicator locations during 1976 1978. I-131 during these years is a result of intermittent weapons testing.

During 1979 1985, I-131 in milk samples at the indicator locations was not detected except during 1980. The mean result during 1980 was 3.8 pCi/liter and -was a result of the 1980 Chinese Weapons Test. Results from 1986 showed that I-131 was detected at a mean concentration of 5.2 pCi/liter as a result of the Chernobyl accident. I-131 was not detected during the period 1987 through 1990 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 pCi/liter. There was no detectable I-131 during the period of 1978 1985 with the exception of 1980. During 1986, I-131 from

. the control location showed a mean concentration of 13.6 pCi/liter as a result of the Chernobyl accident. I-131 was not detected during the period 1987 through 1990 at the control location.

Tables 37 and 38 show the historical environmental sample data for milk.

Cs-134, Cs-137, and I-131 were not detected in the bi-monthly milk samples analyzed for 1990. Only naturally occurring radionuclides such as Ra-226 and K-40 were detected. Therefore, no doses to man have been calculated.

-34

4 ' TERRESTRIAL SAMPLES IlI A.

FOOD PRODUCTS Sam le Collection Methodolo and Anal sis 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 meteorological data. Six samples are collected 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 (gamma isotopic analysis). The gamma isotopic analysis also includes I-131.

Food product locations are shown on Figure 3 (refer to Table 3 for location designations and descriptions).

B. Evaluation of Food Product Data Tables 17A and 17B Food product, samples collected during 1990 were comprised of garden vegetables and other types of vegetation. Samples were collected from six indicator locations and one control location.

The indicator locations were represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and all site release points at operating facilities. The control location was represented by a garden location 9-20 miles distant in a least prevalent wind direction.

Garden vegetables were comprised of cabbage, squash leaves, and swiss chard which are all considered broadleaf vegetables.

Other broadleaf vegetation consisted of corn leaves, bean leaves, grape 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.

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). K-40 was detected in all food product samples. Vegetation sampled showed concentrations of K-40 ranging from 2.19 'pCi/g to 6.10 pCi/g (wet). Be-7 was also found in all vegetation samples. This radionuclide ranged from 0.08 pCi/g to 1.46 pCi/g (wet). Ra-226 was detected intermittently at concentrations that ranged from 0.19 to 0.68 pCi/g (wet) for all sample types at the indicator and control locations. AcTh-228 was also detected intermittently for all sample types at concentrations that ranged from 0.030 to 0.072 pCi/g (wet) for both indicator

-35

4 ' TERRESTRIAL SAMPLES III FOOD PRODUCTS B. Evaluation of Food Product Data Tables 17A and 17B (Cont'd) and control locations. K-40, Be-7, Ra-226 and AcTh-228 are naturally occurring radionuclides. No other radionuclides were detected in the 1990 samples of vegetables or other vegetation.

Review of past environmental data indicates that Cs-137 has been detected intermittently during the years of 1976 1988 at the indicator locations and during the years of 1980 1988 at the control locations (control samples were not obtained prior to 1980). Review of indicator sample results from 1976 1988 showed that Cs-137 was not detected during 1976 1978 and 1981 1984 or 1986 1987. During 1979 and 1980, Cs-137 in fruits and/or vegetables showed annual mean concentrations of 0.004 and 0.036 pCi/g (wet) respectively. Cs-137 was found at an indicator location during 1985 at a concentration of 0.047 pCi/g (wet). During 1988, Cs-137 was found at a concentration of 0.008 pCi/g (wet). Control sample results during 1980-1988 showed Cs-137 detected only during 1980 at a concentration of 0.02 pCi/g (wet). Cs-137 was detected in one broadleaf sample during 1989 at a concentration of 0.0009 pCi/g (wet).

Tables 39 and 40 show historical environmental sample data for food products.

-36

4 ' TERRESTRIAL SAMPLES IV LAND USE CENSUS A land use census is conducted to determine the utilization of land in the vicinity of the site. The land use census actually consists of two types of census. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site.

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 contacted by telephone or in person. The local agricultural agency was also contacted.

A second type of census is a residence census. This census is conducted in accordance with the Technical Specifications in order to identify the closest residence within three miles in each of the 22.5 degree meteorological sectors. A residence, for the purposes of this census, is a residence that is occupied on a part time basis (such as a summer camp), or on a full time, year round basis. For the residence census, several of the meteorological sectors are over Lake Ontario because the site is located at the shoreline. Therefore, there are only eight sectors over land where residences are located within 3 miles.

During 1990, a residence census was conducted to identify the nearest residence in each of the sixteen 22.5 degree meteorological sectors within a distance of five miles from the site in order to provide more comprehensive census data. At this distance, some of the meteorological sectors are over water. These sectors include: N, NNE, NE, ENE, W, WNW, NW, and NNW.

B. Evaluation of Data Tables 18 and 19 In accordance with the Technical Specifications, a land use census was conducted during 1990 to identify within a distance of five miles the location of all milk animals (cows and goats) and the location of the nearest residence in each of the sixteen 22.5 degree meteorological sectors. The milk animal census was actually conducted out to a distance of ten miles in order to provide a more comprehensive census.

-37

4 ' TERRESTRIAL SAMPLES IV LAND USE CENSUS B. Evaluation of Data Tables 18 and 19 (Cont'd)

The number of milk animals located within an approximate ten mile radius of the site was estimated to be 1086 cows and 30 goats for the 1990 census. The number of cows decreased by 79 and the number of goats increased by 3 with respect to the 1989 census. One new milk location and several deactivated milk locations were identified during the 1990 census. However, no changes were made to the 1990 sampling program because the new location did not meet milk sampling location criteria, nor did the location provide a higher D/Q value for optional samples.

Therefore, there were no changes made to the milk sampling program. 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 4.

The results of the 1990 residence census showing the applicable sectors and degrees and distance of each of the nearest residences are found on Table 19. The nearest residences are shown in Figure 3. No changes were noted in 1990.

-38

5 0 XHTBRLABORATORY COMPARZSOH PROGRAM

-39

5~0 ..INTERLABORATORY COMPARISON PROGRAM - TABLE 20 Section 3.6.21 and Section 3.12.3 of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1 and Unit 2, respectively, require that a summary of the results obtained as part of an Interlaboratory Comparison Program be included in the Annual Radiological Environmental Operating Report. Presently, the only NRC approved Interlaboratory Comparison .Program is the USEPA Cross Check Program. Table 20 shows the results of the EPA's reference results and the licensee's results. Some of the EPA reference samples have been analyzed by the site. Other EPA reference samples have been analyzed by a vendor who normally analyzes those types of sample media, for the site. Participation 'in the EPA Cross Check Program includes sample media for which environmental samples are routinely collected, as required by Table 3.6.20 1 and Table 3.12.1 1 of the Technical Specifications and "for which intercomparison samples are available from the EPA. Where many samples are available from the EPA, a QC sample to program sample ratio of ten percent is utilized, where applicable.

Results from the EPA are presented in terms of normalized

~

deviations from a known value (NDKV). Laboratory results are

. considered acceptable by EPA if the NDKV for each sample is between plus or minus 3 NDKV. All analyses performed by the Site Environmental Laboratory during 1990 were within 3NDKV.

One sample analyzed by the vendor was outside three normalized deviations. The sample QA-90-113 was a milk sample analyzed for I-131. The vendor laboratory uses a . chemical separation technique to analyze for I-131. Low separation yield is a possible explanation for the nonconformity. There have been no previous similar nonconformities by this vendor. The same sample analyzed by the Site Environmental Laboratory was acceptable.

-40

6 0 HTSTORZCAL BHVXRONMENTAL SAMPLB DATA

6 ' HISTORICAL ENVIRONMENTAL SAMPLE DATA 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.

-42

7 0 CHANGES AND BXCEPTXONS TO THE PROGRAM

-43

7~0 CHANGES AND EXCEPTIONS TO THE PROGRAM A. Chan es

~ to the 1990 Sam le Pro ram 1.~ Food product location Z was added to the sample program during 1990. Location Z is an optional sampling location.

2. Also during 1990, food product locations L and Y were not utilized by the sampling program because of either sample unavailability or because the location had a low deposition potential as a result of the addition of location Z.

B. Exce tions to the 1990 Sam le Pro ram Exceptions to the 1990 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 Te'chnical Specifications.

~ Air Radioiodine and Particulate Sampling Required by the Technical Specifications 1~ Environmental air sample equipment at R-4 off-site air

. sampling station was inoperable from 1/26/90 (1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />) to 1/30/90 (0830 hour0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />s}. The vacuum pump plug had vibrated loose, causing pump to be unplugged.

Pump restarted and preventative maintenance performed.

2. Environmental air sample equipment at R-5 off-site air sampling station was inoperable from 5/25/90 (0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />) to 5/29/90 (1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />). The vacuum pump was found defective and replaced.

3. Environmental air sample equipment at R-5 off-site air sampling station was inoperable from 7/18/90 (0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />) to 7/24/90 (1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />). The vacuum pump was found defective and was replaced.

4 ~ ErTvironmental air sample equipment at R-5 off-site air sampling station was inoperable from 8/07/90 (1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />) to 8/14/90 (1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />). The vacuum pump was restarted and was verified to be operating correctly.

5. Environmental air sample equipment at R-1 off-site air sampling station was inoperable from 9/06/90 (2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />) to 9/11/90 (0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />). The vacuum pump was found defective as a result of an inoperable cooling fan and was replaced.

7 9 CHANGES AND EXCEPTIONS TO THE PROGRAM B. Exce

~ tions to the

~

1990 Sam le Pro ram (Cont'd)

Other occurrences of downtime for optional air sampling stations were documented for 1990. However, these occurrences are not presented here because optional air sampling stations are not required by the Technical Specifications.

C. Lower Limit of Detection for Environmental Sam les The Technical Specifications require that environmental samples analyzed for the Radiological Environmental Monitoring Program meet the lower limits of detection (LLD) found on Table 4.6.20-1 of the Nine Mile Point Unit 1 Technical Specifications-and Table 4.12.1-1 of the Nine Mile Point Unit 2 Technical Specifications.

All of the 1990 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 Interlaborator Com arison Pro ram 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 utilizing QC samples from the Environmental Protection Agency (EPA).. This section also requires that deviations from the sample schedules be reported in the Annual Radiological Environmental Operating Report. The sample schedule is set by the EPA and includes media for which environmental samples are routinely collected and for which interlaboratory comparison .samples are available from the EPA.

During 1990, sample media offered by the EPA for the Interlaboratory Comparison Program, and for which environmental samples are routinely collected and analyzed, were obtained and analyzed. One iodine in water sample was not sent out by EPA as previously scheduled and subsequently was not analyzed.

-45

8.0 comer vsxos

-46

8 ' 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 radionuclide 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 57 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 1990, the presence of one fission product radionuclide was noted in two different sample media. These media included sediment and fish samples. The most likely source of the fission product radionuclide is past weapons testing. The impact, expressed as a dose to man, is minimal and is 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 effect the health and safety of the public.

-47

9 0

-48

9 ' GENERAL REFERENCE MATERIAL U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", March 1976 (Revision 0).

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).

U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",

December, 1975.

U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979.

National Council on Radiation Protection and Measurements (NCRP),

Environmental Radiation Measurements, NCRP Report No. 50, 1976.

National Council on Radiation Protection and Measurements (NCRP),

Natural Back round Radiation in the United States, NCRP Report No.

45, 1975.

National Council on Radiation Protection and Measurements (NCRP),

Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977.

National Council on Radiation Protection and Measurements (NCRP),

Radiation Ex osure from Consumer Products and Miscellaneous Sources, NCRP Report No. 56, 1977.

International Commission on Radiological Protection (ICRP),

Radionuclide Release into the Environment Assessment of Doses to Man, ICRP Publication 29, 1979.

Eichholz, G.. Environmental As ects of Nuclear Power, First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan, 1976.

Eisenbud, Merrill, Environmental Radioactivit , Second Edition, Academic Press, New York, NY 1973.

Thomas, C.W. etc al., Radioactive Fallout from Chinese Nuclear Wea ons Test, September 26, 1976. (BNWL-2164) Battelle, Pacific Northwest Laboratories, U.S. ERDA, 1979.

Pochin, Edward E., Estimated Po ulation Ex osure from Nuclear Power Production and Other Radiation Sources, Nuclear Energy Agency, Organization for Economic Co-Operation and Development, 1976.

-49

9 0 GENERAL REFERENCE MATERIAL Glasstone, Samuel and Jordan, Walter H., Nuclear Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ill., 1980.

U.S. Department of Health, Education, and Welfare. Radiolo ical Health Handbook. Bureau of Radiological Health, Rockville, Maryland 20852. January 1970.

U.S. Department of Health and Human Services. Pre aredness and Res onse in Radiation Accidents, National Center for Devices and Radiological Health, Rockville, Maryland 20857. August 1983.

National Council on Radiation Protection and Measurements (NCRP),

Ionizin Radiation Ex osure of the Po ulation of the United States, NCRP Report No. 93, 1987.

-50

10 0 DATA TABLBS %990

-51

TABLE 1 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

• A AQUATIC PROGRAM MEDIA ANALYSIS FREQUENCY LOCATIONS (1)

1. Shoreline GSA 2lYear 1 Indicator (2)

Sediment

2. Fish GSA 2/Year 2 Indicator (3), 1 Control

3. Surface Water GSA M. Comp 1 Indicator (4), 1 Control H-3 Qtr. Comp 1 Indicator (4), 1 Control B. DIRECT RADIATION

1. TLD Gamma Dose Quarterly 30 Indicator, 2 Control (5)

NOTES:

• Sampling and analysis program as required by the Technical Specifications.

(1) Aquatic program indicator samples collected in the vicinity of the site; control samples collected at a distance of at least five miles from the site.

(2) Indicator sample from an area of potential recreational value.

(3) Indicator samples from an area near the vicinity of a site discharge point.

Control samples of the same species or of species of similar feeding habits.

(4) Indicator sample from the J. A. Fitzpatrick inlet canal.

(5) Indicator samples from the site boundary, four-five miles from the site, special interest areas and control areas (greater than ten miles from the site) .

-52

TABLE 2 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*

Ce TERRESTRIAL PROGRAM MEDIA ANALYSIS FREQUENCY LOCATIONS 1~ Air GB Weekly 4 Indicator, 1 Control (1)

Particulates GSA M. Composite 2 ~ Airborne GSA Weekly 4 Indicator, 1 Control (1)

I-131 3 ~ Milk I-131 2/Month 3 Indicator, 1 Control (2)

GSA 2/Month 4~ Human Food GSA, I-131 (5) Annually (3)

Crops NOTES:

• Sampling and analysis program as required by the Technical Specifications.

(1) Three indicator samples from near the site boundary in three of the highest D/Q meteorological sectors, one indicator sample from near a year round community, and one control sample from an area of least prevalent wind direction.

(2) Three indicator samples from areas within 5.0 miles of the site. Control sample from an area of least prevalent wind direction.

(3) Samples of three different kinds of broadleaf vegetation nearest to each of two different off-site locations of highest D/Q and one sample of each of similar broadleaf vegetation at least 9.3-20 miles distant in a least prevalent wind direction.

(4) Gamma spectral analysis to include I-131.

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE P FIGURE DEGREES & DISTANCE EDIUM DESIGNATION BER LOCATION DESCRIPTION (1)

Shoreline Sediment p5* Figure 1A Sunset Bay 80'30't 1.5 miles 06 Figure 1A Langs Beach, Control at 5.8 miles Fish 02* Figure 1A ine Mile Point Transect 0.3 miles P3* Figure 1A FitzPatrick Transect 315'5'35't at 0.6 miles pp* Figure lA Oswego Transect at 6.2 miles Surface Water P3* Figure 1A FitzPatrick Inlet 0.5 miles 08* Figure lA Oswego Steam Station Inlet at 7.6 miles Figure 1A NMP Unit 1 Inlet at 0.3 miles 70'35'05'40 09 10 11 Figure 1A Oswego City Water Figure lA P Unit 2 Inlet 304'tat 7.8 miles at 0 1 miles

~

ir Radioiodine Particulates and 1*

2*

Figure lA -1 Station, Nine. Mile Point Road

-2 Station, Lake Road 1.8 miles Figure 2 at 1.1 miles 3* Figure 2 -3 Station, Co. Rt. 29 at 1.5 miles

-4* Figure 2 -4 Station, Co. Rt. 29 at 1.8 miles 5* Figure 1A -5 Station, Montario Point Road 88'04'32'43'2'9'50'0' at 16.4 miles Dl Figure 2 Dl On-Site Station at 0.2 miles G Figure 2 G On-Site Station at 0.7 miles H Figure 2 H On-Site Station at 0.8 miles I Figure 2 I On-Site Station at 0.8 miles Figure 2 On-Site Station at 0.9 miles K Figure 2 K On-Site Station at 0.5 miles G Figure 1A G Off-Site Station, Saint Paul Street 98'10'32'25'17'60'90't at 5.3 miles D2 Figure 1A D2 Off-Site Station, Rt. 64 at 9.0 miles E Figure 1A E Off-Site Station, Rt. 4 at 7.2 miles F Figure lA F Off-Site Station, Dutch Ridge Road at 7.7 miles

-54

TABLE 3 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE P FIGURE DEGREES & DISTANCE EDIUM DESIGNATION BER LOCATION DESCRIPTION (1) hermoluminescent 3 Figure Dl On-Site Station 0.2 miles Dosimeters (TLD) 4 Figure D2 On-Site Location at 0.4 miles 5 Figure E On-Site Location at 0.4 miles 6 Figure F On-Site Location at 0.5 miles 7* Figure 2 G On-Site Station at 0.7 miles 8 Figure 1A -5 Off-Site Station at 16.4 miles 9 Figure lA Dl Off-Site Location at 11.4 miles 10 Figure lA D2 Off-Site Station at 9.0 miles 11 Figure 1A E Off-Site Station at 7.2 miles 12 Figure 1A F Off-Site Station at 7.7 miles 13 Figure lA G Off-Site Station at 5.3 miles 1A Southwest Oswego Control at 69'40'75'10'50'2'0'17'60'90'25'26'37'65'1'0'8'10'32'0'8'5'57't 14* Figure 12.6 miles 15* Figure lA est Site Boundary at 0.9 miles 18* Figure 2 Energy Information Center at 0.4 miles 19 Figure 1A East Site Boundary at 1.3 miles 23* Figure 2 On-Site Station at 0.8 miles 24 Figure 2 I On-Site Station at 0.8 miles 25 Figure 2 On-. Site Station at 0.9 miles 26 Figure 2 K On-Site Station at 0.5 miles 27 Figure 2 orth Fence, JAFNPP at 0.4 miles 28 Figure orth Fence, JAFNPP at 0.5 miles 29 Figure 2 orth Fence, JAFNPP at 0.5 miles 30 Figure 2 orth Fence, JAFNPP at 0.4 miles 31 Figure 2 North Fence, NMP-1 276't 0.2 miles 39 Figure 2 orth Fence, NMP-1 292't 0.2 miles 47 Figure 2 orth Fence, JAFNPP 0.6 miles 49* Figure 1B Phoenix, NY - Control at 19.8 miles 51 Figure 1A Oswego Steam Station, East at 7.4 miles 52 Figure lA Fitzhugh Park Elementary Sc hool, East 69'70'33'27'83'15'5't at 5.8 miles 53 Figure 1B Fulton High School at 13.7 miles 54 Figure lA exico High School at 9.3 miles 55 Figure 1A Pulaski Gas Substation, Rt. at 13. 0 miles

TABLE 3 ( tinued)

ENVIRONMENTAL 8 E LOCATZON8 SAMPLE P FIGURE DEGREES & DISTANCE EDIUM DESIGNATION BER LOCATION DESCRIPTION (1)

Thermoluminescent 56* Figure 1A ew Haven Elementary School 123'20' 5.3 miles Dosimeters (TLD) 58* Figure 1A County Route 1 and Alcan at 3.1 miles (Continued) 75* Figure 2 orth Fence, NMP-2 0 at 0.1 miles 76* Figure 2 orth Fence, NMP-2 at 0.1 miles 77* Figure 2 orth Fence, NMP-2 at 0.2 miles 78* Figure 2 East Boundary, JAFNPP at 1.0 miles 79* Figure 2 County Route 29 at 1.1 miles 80* Figure 2 County Route 29 at 1.4 miles 81* Figure 2 incr Road at 1.6 miles 82* Figure 2 incr Road at 1.6 miles 83* Figure 2 Lakeview Road at 1.2 miles 84* Figure 1A Lakeview Road at 1.1 miles 85* Figure 2 orth Fence, NMP-1 at 0.2 miles 86* Figure 2 orth Fence, NMP-1 at 0.1 miles 87* Figure 2 orth Fence, NMP-2 at 0.1 miles 88* Figure 1A ickory Grove Road at 4.5 miles 89* Figure 1A Leavitt Road at 4.1 miles 90* Figure 1A Route 104 and Keefe Road at 25'5'0'15'33'59'81'00'25'94'15'41'7'11'35'56'83'05'23'37'99'43'01'8'04'32'75'67'02't 4.2 miles 91* Figure 1A County Route 51A at 4.8 miles 92* Figure lA aiden Lane Road at 4.4 miles 93* Figure 1A County Route 53 at 4.4 miles 94* Figure 1A County Route 1 and Kocher Road at 4.7 miles 95* Figure 1A Lakeshore Camp Site at 4.1 miles 96* Figure lA Creamery Road at 3.6 miles 97* Figure 2 County Route 29 at 1.8 miles 98* Figure lA Lake Road at 1.2 miles 99 Figure 1A Nine Mile Point Road at 1.8 miles 100 Figure 2 County Route 29 and Lake Road at 1.1 miles 101 Figure 2 County- Route 29 at 1.5 miles 102 Figure 1B Oswego County Airport at 11. 9 miles 103 Figure 2 Energy Center, East at. 0.4 miles 104 Figure lA Parkhurst Road at 1.4 miles

-56

TABLE 3 (Conti.nued)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE P FIGURE DEGREES & DISTANCE DIUM DESIGNATION BER LOCATION DESCRIPTION (1)

Thermoluminescent 105 Figure 2 Lakeview Road 1.4 miles Dosimeters (TLD) 106 Figure 2 Shoreline Cove, West of NMP-1 at 0.3 miles (Continued) 107 Figure 2 Shoreline Cove, West of NMP-1 198'74'72'04'03'66 at 0.3 miles 108 Figure 1A Lake Road at 1.1 miles 109 Figure 1A Lake Road at 1.1 miles 110 Figure 1B Baldwinsville, NY Control at 26.4 miles 111 Figure 1A Sterling, NY Control at 21.8 miles Cows Milk 7 Figure 4 Indicator Location at 5.5 miles 16 Figure 4 Indicator Location at 5.9 miles 50 Figure 4 Indicator Location at 9.3 miles 55 Figure 4 Indicator Location at 9.0 miles 60 Figure 4 Indicator Location at 9.5 miles 4 Figure 4 Indicator Location at 7.8 miles 214'07'90'3'5'0'13'20'4'01'25'6'36'5't 65* Figure 4 Control Location at 17.0 miles Food Products

• Figure 3 Indicator Location at 1.6 miles P* Figure 3 Indicator Location at 1.9 miles

• Figure 3 Control Location at 15. 6 miles K* Figure 3 Indicator Location at 1.7 miles

• Figure 3 Indicator Location at 1.7 miles Q* Figure 3 Indicator Location at 1.9 miles

• Technical Specification location.

(1) Degrees and'istance based on Nine Mile Point Unit 2 reactor centerline.

RADIOLOGICAL ENVIRONMENTAL MO ING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATI UNIT 1 DOCKET NO ~ 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO ~ 50-410 OSWEGO COUNTY'TATE OF NEW YORK~ JANUARY - DECEMBER 1990*

INDICATOR

~

LOCATION (b) OF HIGHEST CONTROL NUMBER OF YPE AND NUMBER LOCATIONS: NUAL MEAN: LOCATION & LOCATION: MEAN NONROUTINE DIUM (UNITS) OF ANALYSES* LLD (a) f EAN ( ) RANGE f EAN ( ) RANGE f

( ) RANGE REPORTS Shoreline GSA 4 Sediment* Cs-134 150 <LLD <LLD <LLD (pCi/kg-dry) Cs-137 180 277 2 2 'v: <LLD 277-277 1.5 at 80'77-277 Fish* GS'A 30: (h) 0 (pCi/kg-wet) -54 130 <LLD <LLD <LLD 0 Fe-59 260 <LLD <LLD <LLD 0 Co-58 130 <LLD <LLD <LLD 0 Co-60 130 <LLD <LLD <LLD 0 Zn-65 260 <LLD <LLD <LLD 0 Cs-134 130 <LLD <LLD <LLD 0 Cs-137 150 44 9 19 po 43 4 11 24-115 0.3 at 315'4-115 25-79 Surface Water* -3 8 250 4 4

• 290 2 4 (pCi/liter) 3000(c) 220-290 0.5 at 70'20-290 260-320 GSA 24

-54 15 <LLD <LLD <LLD Fe-59 30 <LLD <LLD <LLD Co-58 15 <LLD <LLD <LLD Co-60 15 <LLD <LLD <LLD Zn-65 30 <LLD <LLD <LLD Zr-95 15 <LLD <LLD <LLD Nb-95 15 <LLD <LLD <LLD I-131 15 (c) <LLD <LLD <LLD Cs-134 15 <LLD <LLD <LLD Cs-137 18 <LLD <LLD <LLD Ba/La-140 15 <LLD <LLD <LLD

-58

TABLE 4 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONZTORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO+ 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO ~ 50-410 OSWEGO COUNTYi STATE OP NER YORK'ANUARY - DECEMBER 1990*

INDICATOR LOCATION (b) OF HIGHEST CONTROL NUMBER OF YPE AND NUMBER LOCATIONS NUAL MEAN: LOCATION & LOCATION: MEAN NONROUTINE DIUM (UNITS) OF ANALYSES* LLD(a) f MEAN ( ) RANGE f EAN ( ) RANGE (F) RANGE REPORTS TLD* (mrem per Gamma Dose 128 (d) 15.8 120 120 II 13.9 8 8 quarterly 9.8-44.4 0.2 at 294 37.8-44.4 11.0-17.6 period) t ir Particulates*

Gross Beta 259 0. 01 0.014 208 208 0.005-0.023 R-4 1.8 at 0.013 51 51 143'.006-0.023 0.003-0.027 0

pci/m~

I-131 259 0.07 <LLD <LLD <LLD GSA 60 Cs-134 0. 05 <LLD <LLD <LLD Cs-137 0 ~ 06 <LLD <LLD <LLD ilk* GSA 126  : (e) (21) <LLD <LLD <LLD (pCi/liter) Cs-134 15 <LLD <LLD <LLD Cs-137 18 <LLD <LLD <LLD Ba/La-140 15 I-131 126 <LLD <LLD <LLD I-131 Food Products* GSA 20  :(?1) 60 <LLD <LLD <LLD (pCi/kg-wet) I-131 60 <LLD . <LLD <LLD (broadleaf Cs-134 80 <LLD <LLD <LLD egetation) Cs-137

TABLE 4 inued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO ~ 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO ~ 50-410 OSWEGO COUNTY'TATE OF NEW YORKi J'ANUARY - DECEMBER 1990*

TABLE NOTES:

Data for Table 4 is based on Technical Specification required samples unless otherwise indicated.

LLD values as required by the Radiological Technical Specifications. LLD units are specified in the medium column.

Location is distance in miles and direction in compass degrees based on NMP-2 reactor center-line. Units for this column are specified in medium column.

The Technical Specifications specify an I-131 and tritium LLD value for surface water analysis (non-drinking water) of 15 pCi/liter and 3000 pCi/liter respectively.

The Technical Specifications do not specify a particular LLD value to environmental TLDs. The NMP-1 and NMP-2 Off-Site Dose Calculation Manuals contain specifications for environmental TLD sensitivities.

The Technical Specification criteria for indicator milk sample locations includes locations within 5.0 miles of the site. There are no milk sample locations within 5.0 miles of the site.

Therefore, the only sample location required by the Technical Specifications is the control

-location.

Fraction of number of detectable measurements to total number of measurements. Mean and range results are based on detectable measurements only.

The results for TLD 585 must be evaluated with the knowledge that this TLD is in close proximity (300-500 feet) of the Nine Mile Point Unit 1 reactor building and the radwaste buildings. This TLD, as well as other TLDs in this area, are adjacent to the lake shoreline which is a restricted area to members of the public. There are no residences or private property near this area.

Data includes results from optional samples in addition to samples required by the Technical Specifications. For food products, only broadleaf vegetation was evaluated.

-60

TABLE 5A CONCENTRATION OP GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/g (Crjj) + 2 sigma SAMPLE COLLECTION LOCATION DATE Be-7 K-40 Co-60 Cs-134 Cs-137 Ra-226 AcTh-228 Other Langs Beach 04-24-90 <0.29 13 '+0.5 <0.052 <0.058 <0.040 0.84+0.30 0.44+0.06 <LLD (Control)

• 10-30-90 <0 49 15.0+1.4 <0.061 <0.053 <0.056 1.51+0.72 0 '4+0.18 <L'LD Sunset Beach 04-24-90 <0 ~ 41 16.1+0.5 <0.068 <0.076 0.28+0.03 1.70+0.39 0~ 62+0 08 'LLD (Off-Site) 10-30-90 <0.45 17.8+0.6 <0 '75 <0.085 0.28+0.03 2.06+0.49 0 '8+0 F 09 <LLD

• Sample not recpxired by the Technical Specifications (Optional sample location)

Results in units of activity ~er ram dry weight.

TABL CONCENTRATION OR GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) + 2 sigma SAMPLE COLLECTION LOCATION DATE Be-7 -40 Co-60 Cs-134 Cs-137 a-226 cTh-228 THERS Langs Beach 04-24-90 <292 13600+469 <52 <58 <40 842+300 445+61 <LLD (Control)

• 10-30-90 <486 15000+1410 <61 <53 <56 1510+723 435+183 <LLD Sunset Beach 04-24-90 <409 16100+547 <68 <76 277+26 1700+390 625+80 <LLD (Off-Site) 10-30-90 <447 17800+628 <75 <85 277+29 2060+487 683+87 <LLD

• Sample not recpxired by the Technical Specifications Results in units of activity er kilo ram dry weight

-62

TABLE 6A CONCENTRATION OR GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/g (wet) + 2 sigma GAMMA EMITTERS AMPLE DATE SAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 a-226 THER OSWEGO (CONTROL) 00 Trout <0.085 <0.041 5.27+0.59 <0.028 <0.032 '35+0.016 06/01/90 06/01/90 06/13/90 Brown ite Sucker Lake Trout

<0.106

<0.098

<0.043

<0.046 3.81+0 '2 <0.030 5.53+0.73 0

<0.031 <0.034 <0.026 <0.028

<0.046 <0.038 <0.042 0.033+0.023

<0.056

<0.085

<0.098 0.73+0.35 <LLD 0 '1+0.18 <LLD 0.57+0.34 <LLD 06/01/90 Yellow Perch <0.210 <0.075 7.50+0.30 <0.053 <0.060 <0.047 <0.048 <0.123 1.45+0,32 <LLD 06/01/90 ite Perch <0.158 <0.070 6.54+0.74 <0.049 <0.042 <0 '46 0.079+0.036 <0.104 1.15+0.80 <LLD 09/28/90 Brown Trout <0.069 <0.026 4.65+0.52 <0.024 <0.035 <0.031 <0. 031 <0.065 0.42+0.28 <LLD 09/28/90 ite Sucker <0.064 <0.032 3.97+0.50 <0.025 <0.026 <0.029 <0.030 <0.059 0.77+0.36 <LLD 09/28/90 Lake Trout <0.054 <0.028 4.97+0.49 <0.025 <0.024 <0.026 0.025+0.015 <0.054 0.52+0.26 <LLD 09/27/90 Yellow Perch <0 '91 <0.043 4.46+0.25 <0.037 <0.052 <0.034 <0.032 <0.085 0.37+0.21 <LLD 10/03/90 hite Perch <0.068 <0.035 5.77+0.63 <0.025 <0.029 <0.032 <0.037 <0.088 0.61+0.34 <LLD 10/03/90 Smallmouth Bass <0.089 <0.034 4.08+0.24 <0.027 <0.045 <0.029 <0.035 <0.095 0 '6+0.21 <LLD NINE MILE POINT 02 06/01/90 Lake Trout <0. 102 <0.039 5 '1+0 '0 <0.027 <0 '30 <0.032 0.035+0.017 <0.061 1.07+0.42 <LLD 06/13/90 ite Sucker <0. 070 <0.035 6.16+0.54 <0.023 <0.027 <0.028 <0.035 <0.063 0.69+0.27 <LLD 06/14/90 Brown Trout 0.098 <0.044 6.20+0.64 <0.034 <0.026 <0.035 <0.038 <0.086 0.76+0.34 <LLD 06/13/90 Smallmouth Bass <0.096 <0.045 4.00+0.24 <0.040 <0.045 <0.032 0.039+0,011 <0.082 0.73+0.19 <LLD 06/14/90 ite Perch <0.141 <0.059 4.92+0.80 <0.060 <0.051 <0.060 0.115+0.041 <0.104 1.11+0.49 <LLD 09/27/90 Lake Trout <0.088 <0.043 5. 17+0. 63 <0.037 <0.034 <0.035 0.036+0.025 <0.072 <0.80 <LLD 09/28/90 hite Sucker <0.091 <0.045 6.75+0.81 <0.041 <0.048 <0.035 <0.041 <0.079 <0.86 <LLD 09/28/90 Brown Trout <0.060 <0.030 5.33+0.59 <0.030 <0.034 <0.031 <0.035 <0.076 0.52+0.27 <LLD 09/28/90 Smallmouth Bass <0.060 <0.030 5.44+0.60 <0.025 <0.028 <0.030 <0;032 <0.069 0.62+0.29 <LLD 09/28/90 ite Perch <0.072 <0.036 5.46+0.63 <0.030 <0.032 <0.033 0.024+0.015 <0.069 0.76+0.34 <LLD

TABLE 6A tinued)

CONCENTRATION OR GAMMA EMITTERS IN PISH SAMPLES Results in units of pCi/g (wet) + 2 sigma GAMMA EMITTERS SAMPLE DATE SAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 a-226 THER JA FITZPATRICK 03 06/01/90 Lake Trout <0. 136 <0 045 4.09+0.58 <0.036 <0.033 <0.032 <0.044 <0.099 0.51+0.34 <LLD 06/12/90 Brown Trout <0.067 <0.024 4.47+0.49 <0.027 <0.025 <0.024 0.035+0.018 <0 '46 0.59+0.26 <LLD 06/13/90 ite Sucker <0.075 <0 '36 4.81+0.55 <0.031 <0.026 <0.030 <0.034 <0.076 0.72+0.27 <LLD 06/13/90 Smallmouth Bass <0.159 <0.065 8.78+1.09 <0.066 <0. 065 <0. 057 <0. 063 <0.162 1.31+0.54 <LLD 09/27/90 Lake Trout <0.069 <0.030 4.87+0.56 <0.030 <0.030 <0.030 0.032+0.022 <0.064 0.66+0.27 <LLD 09/27/90 Brown Trout <0.057 <0.027 6.20+0.57 <0.031 <0.025 <0 '28 0.040+0.018 <0.058 0.80+0.34 <LLD 09/27/90 ite Sucker <0.090 <0.055 5.68+0.79 <0.044 <0.040 <0.041 <0.051 <0.113 <0.96 <LLD 09/27/90 Smallmouth Bass <0.085 <0.038 5.42+0.69 <0.038 <0.040 <0.044 <0.052 <0.097 <0.88 <LLD 09/27/90 Yellow Perch <0.108 <0.053 6.02+0.36 <0.049 <0.068 <0.044 0.036+0.016 <0.121 0.99+0.36 <LLD

-64

TABLE 6B CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) + 2 sigma GAMMA EMITTERS SAMPLE DAT SAMPLE TYPE Fe-59 Co-58 -40 -54 Co-60 Cs-134 Cs-137 Zn-65 a-226 OTHER OSWEGO( CONTROL)-00 06/01/90 Brown Trout 85 <41 5270+593 <30 <28 <32 35+16 <56 728+351 <LLD 06/01/90 ite Sucker <106 <43 3810+218 <31 <34 <26 <28 <85 306+183 <LLD

.06/13/90 Lake Trout <98 <46 5530+727 <46 <38 <42 33+23 <98 573+339 <LLD 06/01/90 Yellow Perch <210 <75 7500+304 <53 <60 <47 <48 <123 1450+318 <LLD 06/01/90 ite Perch <158 <70 6540+738 <49 <42 <46 79+36 <104 1150+796 <LLD 09/28/90 Brown Trout <69 <26 4650+520 <24 <35 <31 <31 <65 425+284 <LLD 09/28/90 ite Sucker <64 <32 3970+501 <25 <26 <29 <30 <59 769+359 <LLD 09/28/90 Lake Trout <54 <28 4970+492 <25 <24 <26 25+15 <54 518+256 <LLD 09/27/90 Yellow Perch 91 <43 4460+249 <37 <52 <34 <32 <85 371+214 <LLD 10/03/90 ite Perch <68 <35 5770+627 <25 <29 <32 <37 <88 606+339 <LLD 10/03/90 Smallmouth Bass <89 <34 4080+244 <27 <45 <29 <35 <95 659+210 <LLD NINE MILE POINT -02 06/01/90 Lake Trout 102 <39 5010+498 <27 <30 <32 35+17 <61 1070+424 <LLD 06/13/90 ite Sucker <70 <35 6160+542 <23 <27 <28 <35 <63 686+266 <LLD 06/14/90 Brown Trout <98 <44 6200+643 <34 <26 <35 <38 <86. 762+340 <LLD 06/13/90 Smallmouth Bass <96 <45 4000+243 <40 <45 <32 39+11 <82 729+189 <LLD 06/14/90 ite Perch <141 <59 4920+797 <60 <51 <60 115+41 <104 1110+494 <LLD 09/27/90 Lake Trout <88 <43 5170+630 <37 <34 <35 36+25 <72 <803 <LLD 09/28/90 ite Sucker <91 <45 6750+807 <41 <48 <35 <41 <79 <865 <LLD 09/28/90 Brown Trout <60 <30 5330+591 <30 <34 <31 <35 <76 523+266 <LLD 09/28/90 Smallmouth Bass <60 <30 5440+605 <25 <28 <30 <32 <69 625+290 <LLD 09/28/90 ite Perch <72 <36 5460+634 <30 <32 <33 24+15 <69 755+338 <LLD

TABLE 6B (C ueC)

CONCENTRATION OP GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) + 2 sigma GAMMA EMITTERS SAMPLE DATESAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 a-226 OTHER J. A. FITZPATRICK 03 06/01/90 Lake Trout <136 <45 4090+58 <36 <33 <32 <44 <99 509+339 <LLD 06/12/90 Brown Trout <67 <24 4470+49 <27 <25 <24 35+18 <46 587+261 <LLD 06/13/90 ite Sucker <75 <36 4810+55 <31 <26 <30 <34 <76 724+271 <LLD 06/13/90 Smallmouth Bass <159 <65 8780+1090 <66 <65 <57 <63 <162 1310+544 <LLD 09/27/90 Lake Trout <69 <30 4870+561 <30 <30 '30 32+22 <64 658+273 <LLD 09/27/90 Brown Trout <57 <27 6200+567 <31 <25 <28 40+18 <58 805+341 <LLD 09/27/90 ite Sucker <90 <55 5680+789 <44 <40 <41 <51 <113 <965 <LLD 09/27/90 Smallmouth Bass <85 <38 5420+688 <38 <40 <44 <52 <97 <880 <LLD 09/27/90 Yellow Perch <108 <53 6020+357 <49 <68 <44 36+16 <121 989+359 <LLD

-66

TABLE 7 CONCENTRATION OF GAMMA EMITTERS IN SURFACE 'RATER SAMPLES Results in units of pCi/liter + 2 sigma 1990 LOCATION CLIDE FEBRUARY CH PRIL E SWEGO CITY K-40 247+56 300+41 226+37 225+32 45+2 0 <54 ATER** a-226 101+48 119+45 69+33 87+41 <73 110+44 Cs-134 <4.54 <2.84 <2.52 <2.57 <2.59 <3.08 Cs-137 <4.39 <3.75 <2.64 <3.29 <2.76 <3.27 Zr-95 <13 ' <7 ' <7.0 <7.8 <5 ' <5.2 b-95 Co-58

<6.06

<5.67

<4.35

<3.27

<3.57

<3.18

<3.94

<3.15

<3

<2

'7

'0 <3.83

<3.59 n-54 <4.51 <3.05 <2.65 <3.01 <2.52 <2.57 Fe-59 <12 2 <7.2 6.5 <7.4 <6.5 <7.2 Co-60 Zn-65

<4 '8

<10.5

<2.86

<6.6

<2.52

<5 '

<2.80

<6.1

<2.61

<4.6

<2.78

<6.6 I-131 <14 4 <10.0 <9.4 <10.4 <8.4 <9.6 Ba/La-140 <9.6 <6.3 .

<5.8 <6.5 <6.3 <6 '

INE MILE K-40 72+13 240+37 239+47 178+42 129+24 58+12 POINT UNIT I a-226 63+25 82+34 135+48 <122 77+29 71+28 (INLET) Cs-134 Cs-137

<4 ~ 31

<3.30

<3.09

<2.98

<3 37

<3 '1 <4.11

<4.89

<2 '1

<2.99

<2 '4

<3.34 Zr-95 <8 ' <7.4 <10.0 <13.7 <7 ' <5.8 b-95 Co-58

<4.63

<4.09

<3 '7

<3.45

<4.94

<3.72

<5.89

<5.37

<3.73

<3 '6 <3.97

<3.83 n-54 <3.94 <3.17 <3.21 <4.27 <2.80 <3.30 Fe-59 <7 7 <6.1 <9 ' <10.1 <7.4 <8.7 Co-60 Zn-65

<4.36

<10 '

<3.05

<6.3

<3.95

<7 '

<4 '6

<8 2

<2.72

<5.4

<4.20

<8.1 I-131 <7 ' <8.9 <12.1 <13. 8 <8.9 <8 '

Ba/La-140 <8 6 <6.0 <5 ' <9.4 <7.0 <9.6

• • Optional sample location. Sample not required by the Technical Specifications.

TABLE 7 (C ued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE RATER SAMPLES Results in units of pCi/liter + 2 sigma 1990

'LOCATION CLIDE FEBRUARY CH PRIL UNE NINE MILE K-40 228+44 225+46 322+12 23 1+49 18 1+3 8 178+48 POINT UNIT 2 a-226 97+41 144+56 131+25 138+56 88+42 <125 (INLET) Cs-134 Cs-137

<3.89

<3.89

<3.83

<3.81

<2.84

<2.93

<3.86

<3.91

<3 '6

<3.89

<4.22

<5.15 Zr-95 <9.6 <9.1 <7.9 <9.5 <8 ' <8.6 b-95 <4.54 <4.86 <3.88 <5.12 <5.37 <6.17 Co-58 n-54

<4 '1

<3.61

<4.28

<3.50

<3.39

<3.00

<4.25

<3.54

<4.30

<4.09

<5.36

<3.68 Fe-59 <8.1 <7.6 <8.8 <9.3 <8.7 <10.9 Co-60 <4.01 <3.32 <3.49 <3.93 <3.87 <4.56 Zn-65 <7 ' <7 ' <8.7 <8.9 <8 ' <9.4 I-131 <11.4 <11.5 <6.8 <13.3 <12.7 <13.9 Ba/La-140 <8.1 <6.8 <7.1 <7.2 <7 ' <10.6 FITZPATRICK K-40 283+41 107+32 195+36 205+31 230+40 62+23 (INLET) a-226 119+41 90+35 <79 112+39 126+42 97+55 Cs-134 <2.59 <2.51 <2.62 <2.85 <3.68 <2.44 Cs-137 <2.85 <2.34 <2.91 <3.16 <3.60 <2.46 Zr-95 <6.7 <6.4 <6.8 <7.4 <9.9 <4 '

b-95 <3.43 <3.52 <3.44 <3.86 <5.23 <3.18 Co-58 n-54

<3.40

<2.62

<2 '1

<2.81

<3.20

<2 83

<3.51

<2.89

<4.08

<3.43

<2.58

<2.45 Fe-59 <6.3 <6.2 <6.3 <6.8 <7.8 <6.5 Co-60 Zn-65

<2 '7

<5.7

<3.00

<5.8

<2.43

<5.2

<2.68

<6.5

<3

<7

'6

<2.66

<5.5 I-131 <0.49 <0.42 <0.46 <0.23 <0.20 <0.27 Ba/La-140 <5.8 <6.0 <5.6 <6.5 <6.9 <5.4

• • Optional sample location. Sample not required by the Technical Specifications.

• Sample required by the Technical Specifications.

-68

TABLE 7 (Continued)

CONCENTRATION OP GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma 1990 LOCATION CLIDE ANUARY FEBRUARY CH PRIL E SWEGO K-40 231+44 245+46 180+50 74+23 234+33 217+46 a-226 <107 154+56 ill+45 71+30 84+40 118+48 STEAM STATION Cs-134 Cs-137

<3.62

<3.66

<3.75

<3.47

<4.63

<4.62

<2.49

<3.08

<2 '0

<3 18

<3.70

<3.68 (CONTROL)

Zr-95 <9.2 <9.5 <10.9 <6.8 <7 ' <7.3 b-95 <5.20 <4.78 <6.60 <3.44 <4.10 <4.68 Co-58 n-54

<4.22

<3 '3 <4.70

<3.83

<5.53

<4.69

<2 '1

<3.02

<3 '1

<2.89

<4.39

<3.79 Fe-59 <8.2 <8.0 <11.8 <7.0 <6.0 <7.2 Co-60 <3.68 <3.61 <5.71 <2.48 <2 '6 <3.38 Zn-65 <8.3 <7 ' <9.6 <6.1 <6.0 <7.5 I-131 <0.46 <0.42 <0.43 <0.29 <0-29 <0.18 Ba/La-140 <4.5 <6 ' <8.9 <5.2 <5 ' <8.6

'LOCATION CLIDE LY UGUST EPTEMBER OCTOBER OVEMBER DECEMBER SWEGO CITY K-40 259+36 141+40 59+13 304+41 257+51 78+24 ATER a-226 93+46 <122 8 1+28 87+46 168+50 69+29 Cs-134 <2.57 <4.08 <3. 16 <2.84 <3.62 <2 52 Cs-137 <2 81 <4.58 <3.24 <2.95 <3.78 <2.78 Zr-95 <5.71 <8.62 <6.02 <5.23 <6.62 <5.88 b-95 Co-58

<3.95

<3.49

<6.19

<5.27

<4.05

<3.87

<3 '1

<2.90

<4.90

<4.03

<3.25

<3.19 n-54 <2.88 <4.66 <3.37 <2.86 <3.28 <3.00 Fe-59 <6.0 <9.2 <7.8 <6.2 <8.3 <7.'1 Co-60 Zn-65

<2.76

<4.8

<4 '6

<10.3

<4.60

<8.5

<2.80

<5.2

<3.48

<7 '

<2. 61

<5.7 I-131 <9.2 <13.8 <9.7 <8.7 <12 ' <9.6 Ba/La-140 <5 '8 <8.79 <11.3 <5.4 <8.6 <6.0

• • Optional sample location. Sample not required by the Technical Specifications.

• Sample required by the Technical Specifications.

TABLE 7 (C ued)

CONCENTRATION OP GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma 1990 LOCATION CLIDE LY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER INE MILE K-40 70+14 194+30 200+46 262+40 86+34 72+14 POINT UNIT I a-226 120+20 66+32 <122 <81 <71 <60 (INLET) Cs-134 <4. 12 <2.99 <4.54 <2.79 <2.55 <3.19 Cs-137 <3 ~ 37 <2.85 <4.82 <3.04 <2.55 <3 ~ 41 Zr-95 b-95

<7.08

<4.66

<5 '0

<3.60

<9.32

<5.63

<5.46

<2.94

<5.31

<3.59

<6.25

<4.18 Co-58 <3.80 <3.11 <5.41 <2.88 <2.59 <3.71 n-54 <3.09 <3.15 <4.81 <2.49 <2.83 <3.02 Fe-59 <8.8 <6.2 <11.9 <5.5 <5 ' <8.0 Co-60 Zn-65

<4.01

<10.4

<2 '6

<5.9

<5.13

<9.2

<2.37

<6.1

<2.54

<4.9

<3.48

<8.3 I-131 <10.1 <10.2 <14.5 <9.0 <8.2 <11.0 Ba/La-140 <11.9 <7.5 <12 ' <5.4 <6.4 <F 1 INE MILE K-40 182+42 70+22 203+31 74+29 157+45 164+38 POINT UNIT 2 a-226 95+41 128+48 103+39 73+36 148+55 80+46 (INLET) Cs-134 <3.96 <2.64 <3.04 <2.24 <4.25 <4.43 Cs-137 Zr-95

<4.25

<8.63

<2.65

<5.34

<2 '5

<6.22

<2.50

<6.23

<4.40

<9.96

<4.17

<8.49 b-95 <5.38 <3.82 <3.95 <3.25 <5.72 <5.97 Co-58 <5.04 <2.83 <3.50 <2.94 <5.24 <5.05 n-54 <4.02 <2.64 <2.92 <2.86 <4.91 <4.32 Fe-59 <9.8 <7.0 <6.4 <6.7 <8.8 <11.1 Co-60 <4.70 <2.22 <2.59 <2.54 <4.66 <3.84 Zn-65 <9.1 <5.5 <5.7 <5.9 <11.3 <9.1 I-131 <14.7 <8.9 <10.3 <8.8 <14.1 <14.9 Ba/La-140 <10.5 <5.5 <6.5 <6.4 <10.1 <10.1

• • Optional sample location. Sample not required by the Technical Specifications.

• Sample required by the Technical Specifications.

-70

TABLE 7 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE RATER SAMPLES Results in units of pCi/liter + 2 sigma 1990 CLIDE LY UGUST SEPTEMBER OCTOBER OVEMBER DECEMBER LOCATION FITZPATRICK K-40 214+33 56+12 181+44 50+13 59+14 254+36 a-226 74+32 94+23 104+55 110+30 80+24 94+41

( INLET)

Cs-134 <3.05

<3.00

<3 '7

<3.40

<3.57

<3.83

<3.14

<3 '6 <3.30

<3.10

<2.93

<3.07 Cs-137 Zr-95 b-95

<6

<3

'0

'6 <6.62

<4.13

<7.11

<4 '8 <6.30

<3.76

<6.93

<4.28

<6.20

<3.72 Co-58 <3.40 <3.57 <3 '4 <3 '9 <3.47 <3.31 n-54 <2.75 <3.04 <3.38 <3.38 <3.09 <2.80 Fe-59 <7 1 <8.4 <8 ' <8.1 <7.6 <6.7 Co-60 <2 96 <4.02 <3.67 <3 '5 <3.48 <2.99 Zn-65 <6. 0 <9.8 <8 0 <8 6 <8.3 <5 '

I-131 <0.24 <0.21 <0.39 <0.19 <0.16 <0 46 Ba/La-140 <F 1 <11.4 <6 ' <8 ' <12.0 <6 '

SWEGO K-40 144+42 171+38 43+14 97+30 38+12 263+43 a-226 122+68 96+49 100+28 <73 70+22 108+48 STEAM STATION Cs-134 <4 '9 <3.30 <3.11 <2 '2

<2.50

<3.01

<3.14

<3.63

<3.55 Cs-137 <4.62 <3.57 3.03

<4 '6 (CONTROL)

Zr-95 <9.47 <7.29 <6.16 <5.92 <7.93 Nb-95 <5.61 <4.83 <3.83 <3.50 <3.69 <4.71 Co-58 <5 32 <4.05 <3.49 <2.92 <3.61 <4.66 n-54 <4.02 <3 '4 <3.22 <2 '6 <3.05 <4.33

<6.8 <7.9 <6.6 <7 ' <9-6 Fe-59 Co-60

<10.9

<4.85 <3.46 <4.43 <3 '8 <3.48

<7.4

<3

<7 '

'1 Zn-65 <9.6 <6.7 <7.9 <5.0 I-131 <0.26 <0.20 <0.26 <0.20 <0.27 <0.49 Ba/La-140 <10.8 <8.2 <11.6 <5.3 <9.1 <F 9

• Sample required by the Technical Specifications.

• • Optional sample location. Sample not required by the Technical Specifications.

CONCENTRATION OP TRITIUM IN SURFACE WATER SAMPLES (QUARTERLY COMPOSITE SAMPLES)

Results in units of pCi/liter + 2 sigma LOCATION PERIOD DATE TRITIUM AF INLET

• First Quarter 01/02/90 03/3 0/90 220+120 Second Quarter 03/30/90 06/29/90 230+100 Third Quarter . 06/29/90 10/01/90 290+110 Fourth Quarter 10/01/90 01/02/91 260+110 P-1 INLET ** First Quarter 01/02/90 03/3 0/90 <200 Second Quarter 03/30/90 06/29/90 190+70 hird Quarter 06/29/90 10/01/90 <100 Fourth Quarter 10/01/90 12/3 1/90 320+120 P-2 INLET ** First Quarter 01/02/90 03/30/90 <200 Second Quarter 03/30/90 06/29/90 140+80 hird Quarter 06/29/90 10/01/90 230+80 Fourth Quarter 10/01/90 12/3 1/90 260+120 SWEGO CITY WATER ** First Quarter 01/02/90 03/30/90 <200 Second Quarter 03/30/90 06/29/90 290+110 hird Quarter 06/29/90 10/01/90 450+110 Fourth Quarter 10/01/90 12/3 1/90 320+120 SWEGO STEAM First Quarter 01/02/90 03/3 0/90 <200 STATION

• Second Quarter 03/30/90 06/29/90 <200 (CONTROL) bird Quarter 06/29/90 10/01/90 260+80 Fourth Quarter 10/01/90 12/31/90 320+120

• Samples

• • - Optional required samples.

by the Technical Specifications.

Oswego City Water samples are composites of twice per week grab samples.

-72

TABLE 9A DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma ANUARY PRIL LY CTOBER LOCATION LOCATION HROUGH HROUGH THROUGH HROUGH (DIRECTION &

BER LOCATION CH E SEPTEMBER DECEMBER DISTANCE) (2) 1990 3 Dl On Site 12 9+1.0 4.2+0.4

'+0.3

11. 6+0. 3 4.9+0.4 ll.1+1.

5.2+0.6 3 0.2 miles 0 miles 9 69'.4 4 D2 On Site 6.7+0.3 4 140'.

5 E On Site 5.8+0.2 4.4+0.3 5.1+0.8 4.7+0.4 4 miles 6 5.0+1.5 3.9+0.4 miles 9 175'.5 6 F On Site F 1+0.2 3.8+0.4 3.6+0.2 miles 9 210'.7 7* G On Site 5.4+0.4 4.0+0.2 5.0+0.5 8 -5 Off Site-Control 6.0+0.6 5.0+0.4 (1) 5.2+0.4 miles 6 250'6.4 9 Dl Off Site 5.8+0.2 4.7+0.5 5.2+0.5 4.2+0.3 miles 9 42'1.4 10 D2 Off Site 5.8+0.2 4 '+0 ' 4.6+0.2 4.5+0.2 miles 9 80'.0 4.4+0.4 3.9+0.3 miles 9 117'.2 11 E Off Site 4.5+0.3 4.2+0.3 4.6+0.3 miles 9 160'.7 12 F Off Site 5.6+0.1 4.0+0.2 3.8+0 '

4.9+0.3 4.2+0.2 miles 9 225 190'.3 13 G Off Site 6.0+0.5 4.2+0.2 14* DeMass Rd., SW Oswego-Control 5.9+0.3 4.2+0.2 5.0+0.2 4.6+0.3 12.6 miles 9 226 15* Pole 66, W. Boundary-Bible Camp 5.0+0.2 3 '+0.1 4.4+0.4 F 1+0 1 0.9 miles 9 237 18* Energy Info. Center Lamp Post, SW. 6.4+0.2 5.0+0.2 5.5+0.8 4.5+0.3 0.4 miles 9

'+0 '

265'.

19 East Boundary-JAF, Pole 9 6.5+0 ' 5.8+0.3 5.2+0.8 5 3 miles 9 7.6+0.7 4.4+0.2 6.0+0.9 6.1+0 ' miles 9 81'.8 23* On Site I 6 4+0.3 4.8+0.6 5.1+0.4 4.3+0.4 miles 9 70'.8 24 On Site 5.1+0 '= 4.8+0.4 5.4+0.5 4.2+0.4 miles 9 98'.9 25 On Site 4.1+0.4 miles 9 110'.5 26 K On Site 4.8+0.2 4.4+0.6 4.9+0.4 27 Fence, N. of Switchyard, JAF 22.6+3.8 6 '+0.8 19.3+3.1 18 '+1.9 miles 9 60 132'.4 28 Light Pole, N. of Screenhouse, JAF 33.0+7.0 19.4+2.5 28.6+6.4 26.8+5.1 0.5 miles 9 Fence, N. of W. Side Screenhouse, JAF 27.6+5.4 10 '+1.9 6+4.6 22.6+4.2 miles 9 65' 68'.5 29 23

TABLE 9A tinued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma ANUARY PRIL ULY CTOBER LOCATION LOCATION HROUGH HROUGH HROUGH HROUGH (DIRECTION &

BER LOCATION CH NE SEPTEMBER DECEMBER DISTANCE) (2) 1990 30 Fence (NW) JAF 18.2+2.4 4.9+0.4 14.6+1.6 14. 0+1. 1 0.4 miles 9 31 Fence (NW) NMP-1 8.3+0.9 7 1+0.8 7.6+1.3 7.2+0.8 miles 9 57'.2 39 Fence, Rad Waste, NMP-1 12 '+1 ' 11.3+1.7 11.0+1.8 10.4+0.9 miles. 9 276'.2 47 Fence, NE, JAF 10.7+1.5 4.6+0.4 8 '+1.3 7.8+0.8 miles 9 69 292'.6 49* Phoenix, NY-Control 5 '+0.5 3.7+0.2 4.1+0.3 4.0+0.3 19.8 miles 9 51 Liberty & Bronson Sts., E of OSS 5.8+0.4 4.2+0.2 4.7+0.3 (1) miles 9 170'.4 52 East 12th Cayuga Sts., Osw: School 4.8+0.2 4.0+0.2 4 7+0.2 F 0+0.3 miles 9 227 233'.8 53 Broadwell & Chestnut Sts., Fulton H.S. 6.2+0.2 4.4+0.4 5 '+0.3 5.6+0.3 13.7 miles 9 54 Liberty St., & Co Rt 16, Mexico H.S. 5.4+0.5 3.9+0.2 5.2+0.2 4.0+0.3 miles 9 183'.3 55 Gas Substation & Co Rt 5 Pulaski 4 '+0.2 '+0.3 3.8+0.4 3.9+0.2 miles 9 115'3.0 56* t 104 New Haven Sch. (SE Corner) 5.3+0.2 3

4.4+0.3 5.2+0.5 4.4+0.2 miles 9 75'.3 58* Co Rt 1A Alcan (E of E Entrance Rd.) 5.7+0.4 4.6+0.4 4.4+0.2 4.3+0.4 miles 9 123'.1 75* nit 2, N Fence, N of Reactor Bldg. 6.7+0.4 5.1+0.7 5.6+0.7 5.2+0.5 miles 9 220'.1 76* nit 2, N Fence, N of Change House 6.4+0.3 4.7+0.2 5.6+0.3 5.7+0.6 miles 9 5'.1 77* nit 2, N Fence, N of Pipe Bldg. 7.4+0.2 5.2+0.3 6.6+0.6 8.0+0.6 miles 9 45 25'.2 78* AF, E of E Old Lay Down Area 5.3+0.5 5.2+0.2 5.4+0.2 5'5+0,.3 1.0 miles 9 79* Co Rt 29, Pole f63, 0.2 mi. S of Lake Rd 5.6+0.2 3.9+0.2 4.4+0.4 4 '+0 ' miles 9 90'.1 80* Co Rt 29, Pole f54, 0.7 mi. S of Lake Rd 5.5+0.3 4.5+0.2 4.2+0.8 4.1+0.3 miles 9 115'.4 81* incr Rd., Pole gl6, 0.5 mi. W of Rt 29 5 6+0.1 5 '+0.6 4.4+0.2 F 1+0.2 miles 9 133'.6 82* incr Rd., Pole g1 1/2, 1.1 mi. W of Rt 29 5.5+0.3 4.4+0.2 4.7+0.3 4.0+0.3 miles 6 159'.6 83* Lakeview Rd, Tree, 0.45 mi. N of Miner Rd 5.8+0.4 4 '+0.3 5.2+0.2 5.0+0.4 miles 0 181'.2 200'74

TABLE 9A (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results i.n units of mrem/standard month + 2 sigma ANUARY PRIL LY CTOBER LOCATION LOCATION HROUGH HROUGH HROUGH HROUGH (DIRECTION &

BER LOCATION CH E SEPTEMBER DECEMBER DISTANCE) (2) 1990 84* Lakeview Rd. N, Pole f6117, 200 Ft. N of Lake Rd. 5.0+0.2 3.9+0.2 5.0+0.3 1.1 miles 9 85* nit 1, N. Fence, N of W Side of Screen ouse 14.8+2.3 12 '+1.3 12.8+1.6 0.2 miles 9 225'3.4+1.6 86* nit.2, N. Fence, N of W Side of Screen 294'.6+0.6 ouse 7.6+0.9 5.8+0.8 6.5+0.7 O.l miles 9 87* nit. 2, N Fence, N of E Side of Screen 341' 315'.4+0.4 ouse 7.3+0.5 6.2+0.6 6.8+0 ' 0.1 miles 6 88* ickory Grove Rd., Pole g2, 0.6 mi. N of

t. 1 5.9+0.2 4.2+0.2 5.0+0.3 4.8+0 ~ 5 4.8 miles 9 89* Leavitt Rd., Pole gl6, 0.4 mi. S of Rt 1 5.9+0.1 4.2+0.7 4.8+0.2 4.9+0.3 4.1 miles 9 101'.2+0.3 90* t. 104, Pole 4300, 150 Ft. E of Keefe Rd. 5.6+0.2 3.8+0.2

'+0 1 4.6+0.1 4.2+0.2

'+0 '

4.2 miles 9 91* t. 51A, Pole f59, 0.8 mi. W of Rt. 51 of 5.1+0.2 4 F 4.0+0.3 3 4.8 miles 9 97'11'35'56'.8+0.2 92* aiden Lane Rd., Power Pole, 0.6 mi., S 104 6.3+0.4 4 '+0.2 5.0+0.3 4.4 miles 9 183 93* t. 53, Pole 1-1, 120 Ft. S Of 104 6.0+0 ' 3.9+0.2 4.9+0.4 4'6+0'2 4.4 miles 9 94* t. 1, Pole 482, 250 Ft. E of Kocher Rd. 5.9+0.2 3 '+0.6 3.8+0.2 4. 6+0. 2 miles 6 205'.7 95* Lakeshore Camp Site, from Alcan W Access 223'.8+0.2 d., Pole 421, 1.2 mi. N of Rt. 1 6.0+0.4 4.0+0.4 4.3+0.2 4.1 miles 9 96* Creamery Rd., 0.3 mi. S of Middle Rd., 237'.8+0.3 Pole 1 1/2 6.0+0.3 3.8+0.2 4.6+0.2 3.6 miles 9 97* t. 29, Env. Station R4, 200 Ft. N of 1.8 miles 199'.4+0.3 incr Rd. 6.0+0.3 4.4+0.3 4.2+0.2 9 Lake Rd., Pole $ 145, 0.15 mi. E of Rt. 29 6.3+0.2 4.2+0.3 4.6+0.5 5.2+0.2 miles 143'.2 98* 9

TABLE 9A inued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma ANUARY PRIL LY CTOBER LOCATION LOCATION HROUGH HROUGH HROUGH HROUGH (DIRECT10N &

BER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1990 99 NMP Rd., 0.4 miles N of Lake Rd., Env.

Station R1 Off-Site 5.1+0.3 4.4+0.4 4.6+0.3 4.4+0.3 1.8 miles 9 100 t.-29 and Lake Rd., Env. Station R2 Off- 88'.1 Site 5.4+0.2 4.4+0.2 4.0+0.3 4.4+0.2 miles 6 104 101 Rt. 29, 0.7 mi. S of Lake Rd., Env.

Station R3 Off-Site 5.8+0.3 4.0+0.2 4.5+0.2 4.2+0.4 1.5 miles 9 102 EOF/Env. Lab, Oswego Co. Airport (Fulton 132'1.9 irport), Rt. 176, E. Driveway Lamp Post 5.9+0.2 5.0+0.3 5.1+0.2 4.9+0.2 miles 9 103 EIC, East Garage Rd., Lamp Post 5.8+0.2 5.0+0.3 5.3+0.3 4 '+0.2 miles 9 267 175'.4 104 Parkhurst Road, Pole 148 1/2-A, 0.1 mi. S of Lake Rd. 5.8+0.2 4.6+0.1 4.6+0.4 4.2+0.2 1.4 miles 9 105 Lakeview Road, Pole 6125, 0.6 mi. S of 102'.4 Lake Rd. 5 '+0.3 4.6+0.4 5.0+0.4 4 '+0.2 miles 9 Shoreline Cove, E of NMP-1, Tree on =-W Edge ' 5.7+0.4 5.2+0.5 miles 198'.3 106 5.8+0.4 5.1+0 9 107 Shoreline Cove, E of NMP-1, Tree 30 Ft. S 274'.3 of TLD f106 6.6+0.3 5.2+0.3 5.4+0.3 5.8+0.8 miles 9 108 Lake Rd. Pole f142 300'ast of Co. Rt. 272'.1 29 (S) 6. 0+0. 3 5.4+0.3 4.8+0.4 4.8+0.4 miles 6 of Rt. 5.6+0.3 4.0+0.3 4.8+0.4 4.0+0.6 miles 104'.1 109 Lake Rd. Tree 300' Co. 29 (N) 9 103 110 Baldwinsville, NY Control Volza esidence 5.6+0.2 4.0+0.3 4.0+0.2 4.2+0.1 26. 4 miles 9 Sterling, NY Control Blasiak 4.6+0.2 4.7+0.5 4.0+0.2 8 miles 166'1.

Residence 5.6+0.3 9 214 (1) TLD lost in the field.

(2) Direction and distance based on NMP-2 reactor centerline and sixteen 22.5'ector grid.

• Technical Specification location

-76

TABLE 9B DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/cpxarterly period + 2 sigma ANUARY PRIL LY CTOBER LOCATION LOCATION HROUGH HROUGH THROUGH HROUGH (DIRECTION &

BER LOCATION CH E SEPTEMBER DECEMBER DISTANCE) (2) 1990 3 Dl On Site 38.2+1.5 12.6+0.7 34.7+0.4 33.3+1.9 0.2 miles 9 69 4 D2 On Site 19.9+0.5 14.2+0.5 14.9+0.6 15.3+0.9 0.4 miles 9 15.7+1.3 13 '+0.6 miles 6 175 140'.4 5 E On Site 17.2+0.3 13.2+0.4 6 F On Site 15 0+0.3 11.3+0.6 15.2+2.3 11 4+0.6 0. 5 miles 9 10.9+0.4 miles 9 210'.7 7* G On Site 15.8+0.6 12.2+0.2 14.8+0.7 8 R-5 Off Site-Control 18.2+0.9 15.0+0.6 (1) 15.4+0.6 miles 9 42 250'6.4 9 Dl Off Site 17.2+0.2 14.0+0.7 15.8+0.7 12.6+0.5 11.4 miles 9 D2 Off Site 12.1+0.6 14.2+0.3 13 5+0 ' miles 9 80'.0 10 17.5+0.3 11.6+0.4 miles 9 117'.2

11. E Off Site 13.4+0.5 12.6+0.5 13.5+0.6 11.6+0.4 miles 9 160'.7 12 F Off Site 16.8+0.1 12.1+0.3 14.0+0.5 14.8+0.5 12.6+0.4 miles 6 190'.3 13 G Off. Site 18.2+0.7 12.6+0.2 14* DeMass Rd., SW Oswego-Control 17.6+0.4 12 '+0.4 15.2+0.3 13.8+0.5 miles 9 226 225'2.6 15* Pole 66, W. Boundary-Bible Camp 14.6+0.2 9 '+0.2 13.6+0 ' 11.8+0.2 0.9 miles 9 Energy Info. Center-Lamp Post, SW. 17.0+1.2 13.2+0.4 miles 9 237'.4 18* 19.0+0.4 14 F 8+0.4 15.8+1.2 14.9+0.3 miles 9 265'.3 19 East Boundary-JAF, Pole 9 18.9+0 ' 17.2+0 '

Site 22.6+1.0 13.4+0.3 17.9+1.3 18;2+0..9 miles 9 81'.8 23* On I 18.8+0.5 14.5+1.0 15.2+0.6 12.9+0.6 miles 9 98 70'.8 24 On Site 25 On Site 15.1+0.4 14.5+0 ' 16.0+0.8 12.7+0 ' 0. 9 miles 6 12.2+0.5 miles 9 110'.5 26 K On Site 14 1+0.4 13.1+0.9 F 14.8+0.6 55.6+2.9 miles 9 132'.4 27 Fence, N of Switchyard, JAF 66.7+5.7 18.8+1.2 59.2+4.8 Light Pole, N of Screenhouse, JAF 97.3+10.3 58.0+3.8 87.8+9.9 81.0+F 8 miles 9 68' 60'.5 28

TABLE 9B tinued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/cyxarterly period + 2 sigma ANUARY PRIL ULY CTOBER LOCATION LOCATION HROUGH HROUGH HROUGH HROUGH (DIRECTION &

BER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1990 29 Fence, N of W Side Screenhouse, JAF 81.6+8.0 30.6+2.8 72 3+7 1

~ ~ 68.5+6.4 0.5 miles 9 30 Fence (NW) JAF 53.6+3.5 14.7+0.6 44.8+2.4 42.1+1.7 miles 9 65'.4 31 Fence (NW) NMP-1 24.8+1.4 21 2+1.1 22.8+2.0 21-4+1.2 miles 9 57'.2 Fence, Rad Waste, NMP-1 36.8+1.9 33.9+2.5 33.5+2.7 30.6+1.4 miles 9 292 276'.2 39 47 Fence, NE, JAF 31.6+2.2 14.0+0 6 26.8+2.0 23.6+1.2 0.6 miles 9 49* Phoenix, NY-Control 16.6+0.7 11.0+0.3 12.6+0.5 12.0+0.4 8 miles 9 69'9.

51 Liberty & Bronson Sts., E of OSS 17.4+0.6 12.7+0 ' 14.1+0.5 14.8+0.4 miles 9 170'.4 East 12th & Cayuga Sts., Osw. School 233'.

52 14.4+0.3 11.9+0.4 14.0+0.4 (1) 8 miles 9 227 53 Broadwell & Chestnut Sts., Fulton H.S. 18.4+0.4 13 '+0 ' 16.5+0.4 16.7+0.4 13.7 miles 9 183 54 Liberty St., & Co Rt 16, Mexico H.S. 16.0+0.8 11 6+0.3 15 '+0.3 12.0+0.4 9.3 miles 9 55 Gas Substation & Co Rt 5 Pulaski 13.4+0.3 11.2+0.4 11.4+0.5 11.8+0.3 miles 9 115'3.0 56*

58*

t 104 New Haven Sch. (SE Corner)

Co Rt 1A Alcan (E of Entrance Rd.)

15.5+0.4 13.0+0 ' 15.9+0.7 12.8+0.3 miles 9 123'.

75'.3 17.0+0.5 13.8+0 6 13.8+0.3 12.4+0.6 1 miles 9 75* nit 2, N Fence, N of Reactor Bldg. 20.0+0.6 15.4+F 1 17.0+1.0 15.2+0.8 1 miles 9 220'.

76* nit 2, N Fence, N of Change House 19.2+0.5 14 0+0 3 17.0+0.6 F 16.8+0.8 miles 9 5'.1 77* nit 2, N Fence, N of Pipe Bldg. 22.0+0.3 15.6+0 ' 19.8+0.9 23.2+0.9 miles 9 25'.2 78* AF, E of E Old Laydown Area 14.2+0 ' 0 miles 9 45'.

15.4+0.8 16.4+0.4 16.5+0.5 79* Co Rt 29, Pole f63, 0.2 mi. S of Lake Rd 16.3+0.2 11.6+0.3 13.6+0.7 11.9+0.4 miles 9 90'.1 80* Co Rt 29, Pole $ 54, 0.7 mi. S of Lake Rd 15.9+0.5 13.5+0 ' 12.8+1.2 11.8+0.4 miles 9 115'.4 81* incr Rd, Pole 416, 0.5 mi. W of Rt 29 16.4+0.2 15.6+0 ' 12.8+0.3 11.8+0.4 miles 9 133'.6 82* incr Rd, Pole g1 1/2, 1.1 mi. W of Rt 29 16.2+0.4 13.0+0 ' 14.5+0.4 11.7+0.4 miles 9 159'.6 181'78

TABLE 9B (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/cpzarterly period + 2 sigma ANUARY PRIL LY CTOBER LOCATION LOCATION HROUGH HROUGH HROUGH HROUGH (DIRECTION BER LOCATION CH E SEPTEMBER DECEMBER DISTANCE) (2) 1990 83* Lakeview Rd., Tree, 0.45 mi. N of Miner Rd 17. 1+0 7 12 '+0 '

~ 15 '+0.3 14 5+0 F 6 1.2 miles 9 84* Lakeview Rd. N, Pole f6117, 200 Ft. N of 200'.1 Lake Rd. 14.6+0.3 11.6+0.4 15.4+0 4 12.1+0.5 miles 9 85* nit 1, N Fence, N of W Side of Screen 225'.2 ouse 44.4+3.5 37.8+2.0 38.6+2.4 40.0+2.5 miles 9 86* nit 2, N Fence, N of W Side of Screen 294'.1 ouse 23.0+1.3 17.3+1.1 19.8+1.0 16 '+0.9 miles 9 87* nit 2, N Fence, N of E Side of Screen 315'.1 ouse 21.8+0.7 18.6+1.0 20.4+0.9 16.0+0.6 miles 0 88* ickory Grove Rd., Pole g2, 0.6 mi. N of 341'.8

t. 1 17.2+0 ' 12.4+0.3 15 '+0 ' 14.0+0.8 miles 9 97 89* Leavitt Rd., Pole f16, 0.4 mi. S of Rt 1 17.2+0.2 12 '+1.1 14 '+0 ' 14 '+0.5 4.1 miles 0 90* t. 104, Pole $ 300, 150 Ft. E of Keefe Rd. 16.2+0.4 11.4+0.2 14.1+0.2 12.3+0.3 miles 9 111'.2 91* t. 51A, Pole $ 59, 0.8 mi. of Rt. 51 W 14 9+0.2 12 8+0.2 12 '+0 '

F F 10.4+0.2 miles 9 135'.8 92* aiden Lane Rd., Power Pole, 0.6 mi., S of 156'.4 104 18.4+0.5 13.8+0.3 15.2+0.5 13.7+0.3 miles 9 93* t. 53, Pole 1-1, 120 Ft. S Of 104 17 '+0 4 11.8+0.4 15.2+0.7 13.2+0.4 miles 9 183'.4 94* t. 1, Pole f82, 250 Ft. E of Kocher Rd. 17.4+0.4 11.0+1.0 12.0+0.3 13.4+0.3 miles 9 205'.7 95* Lakeshore Camp Site, from Alcan W Access 223'.1 d., Pole f21, 1.2 mi. N of Rt. 1 17. 5+0. 6 11.9+0 ' 13 '+0 ' 11.2+0.3 miles 9 96* Creamery Rd., 0.3 mi. S of Middle Rd., 237'.6 Pole 1 1/2 17.4+0 4 11.4+0.4 14-2+0.2 13 '+0.4 miles 6 199'

TABLE 9B (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/cpxarterly period + 2 sigma ANUARY PRIL ULY CTOBER LOCATION LOCATION HROUGH HROUGH THROUGH HROUGH (DIRECTION &

BER LOCATION CH NE SEPTEMBER DECEMBER DISTANCE) (2) 1990 97* t. 29, Env. Station R4, 200 Ft. N of incr Rd. 18.0+0.5 11.7+0.5 12.6+0.3 1.8 miles 9 98* Lake Rd., Pole gl45, 0.15 mi. E of Rt. 29- 18.4+0.4 12.8+0.4 14.2+0.7 1.2 miles 9 143'5.5+0.4 99 P Rd., 0.4 miles N of Lake Rd., Env.

Station R1 Off-Site 15.8+0.5 13.2+0.6 13.2+0.4 1.8 miles 9 101'3.0+0.5 100 t. 29 and Lake Rd., Env. Station R2 Off-Site 16 '+0 ' 13.0+0.4 12.0+0.4 1.1 miles 9 88'3.1+0.3 101 t. 29, 0.7 mi. S of Lake Rd., Env.

Station R3 Off-Site 17.2+0.4 11.8+0.2 13.5+0 ' 1.5 miles 9 104'2.4+0.5 102 EOF/Env. Lab, Oswego Co. Airport (Fulton irport), Rt. 176, E Driveway Lamp Post 214'3.0+0.4

17. 3+0. 3 15.0+0.4 15.7+0.3 11.9 miles 9 132'4.5+0.3 103 EIC, East Garage Rd., Lamp Post 17. 2+0. 4 14.8+0.4 16.2+0.4 0.4 miles 9 175'3.8+0.4 104 Parkhurst Rd., Pole 148 1/2-A, 0.1 mi. S of Lake Rd. 16.8+0.2 13 '+0.2 14.2+0.6 12 4+0 3 1.4 miles 9 105 Lakeview Rd., Pole 6125, 0.6 mi. S of Lake d- 17. 2+0. 4 14 F 0+0.5 15.2+0.6 1.4 miles 6 102'2.9+0.4 106 Shoreline Cove, E of NMP-1, Tree on W Edge 17. 2+0. 6 15 '+0 ' 17.4+0 ' 0.3 miles 267'1) 9 274 198'5.4+0.8 107 Shoreline Cove, E of NMP-1, Tree 30 Ft. S of TLD f106 19.4+0 ' 15.4+0.4 16.5+0 ' 17. 0+1. 1 0.3 miles 9 108 Lake Rd Pole f142 300' of Co Rt 29 (S) 17.6+0.4 15.8+0.4 14.9+0.6 14.0+0.6 miles 9 272'.1 109 Lake Rd Tree, 300' of Co. Rt. 29 (N) 16.4+0.5 11.6+0.5 14.8+0.6 14.6+0.9 miles 9 103 104'.1 110 Baldwinsville, NY Control Volza 16.4+0.4 12.0+0.4 12.3+0.4 12.3+0.1 26.4 miles 9 esidence Sterling, NY Control Blasiak Residence 16.1+0.4 13.4+0.4 14.5+0.8 21.8 miles 9 166'1.7+0.3 TLD lost in the field.

(2) Direction and distance based on NMP-2 reactor centerline and sixteen 22.5'ector grid.

• Technical Specification location.

-80

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFF-SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 a 2 SIGMA LOCATION 90/01/09 0.018%0.002 0.017%0.002 0.016a0.002 0.017%0.002 0.018%0.002 0.014%0.002 0.017a0.002 0-017%0 002 0.017a0.002 90/01/16 0.017a0.002 0.016%0.002 0.016%0.002 0.018%0.002 0.015%0.002 0.015%0.002 0.018%0.002 0.015~0.002 0.015%0.002 90/01/23 0.015%0.002 0.016%0.002 0.014a0.002 0.017%0.002 0.016a0.002 0.015%0.002 0.016%0.002 0.014%0.002 0.014%0.002 90/01/30 0.01140.002 0 012%0.002 0.011%0.002 0.015%0.002 0.013%0.002 0.011%0.002 0.013+0.002 0.012%0.002 0.011R0.002 90/02/06 0.014%0.002 0.013%0.002 0.012%0 ~ 002 0.014%0.002 0.014x0.002 0.012%0.002 0.012%0.002 0.014%0.002 0.012%0.002 90/02/13 0.01940.002 0.017%0.002 0.018%0.002 0.017%0.002 0.01610.002 0.01440.002 0.017%0.002 0.017a0.002 0.017%0.002 90/02/20 0.014%0.002 0.014%0.002 0.013%0.002 0.015%0.002 0.014a0.002 0. 012 10. 002 0.013a0.002 0. 01510. 002 0.015%0.002 90/02/27 0.011+0.002 0.016a0.002 0. 015 LO. 002 0.016%0.002 0.01540.002 0.014%0.002 0.015%0.002 0.016%0 002 0.014%0.002 90/03/06 0.01740.002 0.01710.002 0.018%0.002 0.019%0.002 0.017%0.002 0.015%0.002 0.018%0.002 0.017%0.002 0.015a0.002 90/03/13 0.015%0.002 0.013%0.002 0.011%0.002 0.015%0.002 0.012%0.002 0.012R0.002 0.014%0.002 0.014~0.002 0.012%0.002 90/03/20 0. 012 %0. 002 0.012%0.002 0.01240.002 0.013%0 ~ 002 0.009j0.002 0.01040.002 0.010a0.002 0.010%0.002 0.010%0.002 90/03/27 0.015%0.002 0 '15%0.002 0.013%0.002 0.015%0.002 0-015%0.002 0. 01310. 002 0.014t0.002 0.015%0.002 0.014%0.002 90/04/03 0.009x0.002 0.009%0.002 0.009%0.002 0.008%0.002 0. 00810.001 0.008%0.001 0.009%0.002 0.008%0.002 0.009%0.002 90/04/10 0.011%0.002 0.012%0.002 0 013%0 002 0.012%0.002 0.012%0.002 0.011%0.002 0.012R0.002 0.013%0.002 0.011R0.002 90/04/17 0.014%0.002 0.014%0.002 0.012%0.002 0.014%0.002 0.012%0.002 0.014%0.002 0.014%0.002 0.013%0.002 0.014%0.002 90/04/24 0.01610.002 0.01740.002 0.016%0.002 0.016%0.002 0.01640 002 0. 01610. 002 0.017%0.002 0. 01710.002 0.016%0.002 90/05/01 0.018%0.002 0.017%0.002 0.015x0.002 0.013+0.002 0.016%0.002 0.015%0.002 0.018%0.002 0.014%0.002 0.015%0.002 90/05/08 0.010%0.002 0.010%0.002 0.009a0.002 - 0.010%0.002 0.008%0.001 0.010%0.002 0.010%0.002 0.009%0.002 0.008%0.001 90/05/15 0.011%0.002 0.01240.002 0.013%0.002 0.011%0.002 0.01110.002 0.01040.002 0.012%0.002 0 011%0 002 0. 01110. 002 90/05/22 0.005a0.001 0.007%0.001 0.007~0.001 0.006%0.001 0.00610.001 0.006%0.001 0.006%0.001 0.007~0.001 0.006%0.001 90/05/29 0.009%0.002 0.010%0 ~ 002 0.00940.002 0.009%0.002 0.003%0.002 0.008%0.001 0.011%0.002 0.00910.002 0.007%0.001 90/06/05 0.010a0.002 0. 01010. 002 0.010%0.002 0.010~0.002 0.008%0.001 0.009%0.002 0.011%0.002 0.010%0.002 0.008%0.002 90/06/12 0.010%0.002 0.010%0.002 0.010a0.002 0.011%0.002 0.011%0.002 0.010%0.002 0.011%0.002 0.011%0.002 0.011%0.002 90/06/19 0.01640.002 0.015%0.002 0.014%0.002 0.015%0.002 0.013%0.002 0.014%0.002 0.016%0.002 0.014%0.002 0.013%0.002 90/06/26 0.009%0.002 0.01040.002 0.010%0.002 0 '0920.002 0.007%0.001 0. 008%0. 001 0.00910.002 0.010%0.002 0.010%0.002

• Sampl e l ocati ons required by Techni cal Speci fi cati ons.

• • Pump Inoperative

TABLE 10 wTzwuEo)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFF-SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 a 2 SIGMA LOCATION 90/07/03 0.012j0.002 0.010j0.002 0.009j0.002 0.012j0.002 0.010j0.002 0.010j0.002 0.010j0.002 0.012j0.002 0.010j0.002 90/07/10 0.011j0.002 0.013j0.002 0.011j0.002 0.012j0.002 0.011j0.002 0.012j0.002 0.012j0.002 0.012j0.002 0.011j0.002 90/07/17 0.011j0.002 0.012j0.002 0.011j0.002 0.010j0.002 0.009j0.002 0.009j0.002 0.011j0.002 0.011j0.002 0.009j0.002 90/07/24 0.017j0.002 0.016j0.002 0.014j0.002 0.018j0.002 0.027j0.009 0.015j0.002 0.016j0.002 0.017j0.002 0.017j0.002 90/07/31 0.013j0.002 0.013j0.002 0.013j0.002 0.016j0.002 0.013j0.002 0.012j0.002 0.015j0.002 0.011j0.002 0.012j0.002 90/08/07 0.011j0.002 0.011j0.002 0.010j0.002 0.011j0.002 0.010j0.002 0.009j0.002 0.010j0.002 0.013j0.002 0.012j0.002 90/08/14 0.014j0.002 0.012j0.002 0.014j0.002 0.015j0.002 0.016j0.002 0.015j0.002 0.013j0.002 0.010j0.002 90/08/21 0.019j0.002 0.020j0.002 0.019j0.002 0.021j0.002 0.018j0.002 0.020j0.002 0.019j0.002 0.019j0.002 0.018j0.002 90/08/28 0.012j0.002 0.013j0.002 0.013j0.002 0.012j0.002 0.012j0.002 0.014j0.002 0.013j0.002 0.012j0.002 0.010j0.002 90/08/04 0.014j0.002 0.017j0.002 0.014j0.002 0.019j0.002 0.015j0.002 0.019j0.002 0.018j0.002 0.018j0.002 0.016j0.002 90/09/ll 0.022j0.005 0.017jo 002

~ 0.014j0.002 0.017j0.002 0.011j0.002 0.018j0.002 0.015j0.002 0.013j0.002 0.014j0.002 90/09/18 0.013j0.002 0.016j0.002 0.014j0.002 0.016jo 002

~ 0.013j0.002 0.016j0.002 0.017j0.002 0.014j0.002 0.013j0.002 90/09/25 0.012j0.002 0.011j0.002 0.011j0.002 0.013j0.002 0.009j0.002 0.011j0.002 0.010j0.002 0.009j0.002 0.008j0.002 90/10/02 0.019j0.002 0.022j0.002 0.020j0.002 0.023j0.002 0.019j0.002 0.019j0.002 0.020j0.002 0.019j0.002 0.019j0.002 90/10/09 90/10/16 90/10/23

0. 014 jo. 002 0.006j0.001 0.015j0.002 0.017j0.002 0.007j0.001 0.014j0.002 0.015j0.002 0.006j0.001 0.015j0.002 0.014j0.002 0.008j0.002 0.013j0.002 0.015j0.002 0.007j0.001 0.012j0.002 0.014j0.002 0.007j0.001 0.015j0.002 0.015j0.002 0.007j0.001 0.015j0.002 0.014j0.002 009 jo. 002 0.015j0.002 0.012j0.002 0.006j0.001 0.012j0.002 90/10/30 0.010j0.002 0.012j0.002 0.011j0.002 0.011j0.002 0.010j0.002 0.011j0.002 0.012j0.002 0.011j0.002 0.009j0.002 90/11/06 0.020j0.002 0.020j0.002 0.018j0.002 0.021j0.002 0.020j0.002 0.020j0.002 0.021j0.002 0.020j0.002 0.019j0.002 90/11/13 0.012j0.002 0.013j0.002 0.013j0.002 0.013j0.002 0.012j0.002 0.014j0.002 0.014j0.002 0.012j0.002 0.012j0.002 90/11/20 0.018j0.002 0.020j0.002 0.018j0.002 0.021j0.002 0.017j0.002 0.016j0.002 0.020j0.002 0.016j0.002 0.015j0.002 90/11/27 0.019j0.002 0.020j0.002 0 017j0.002 0.019j0.002 0.019j0.002 0.018j0.002 0.018j0.002 0.020j0.002 0.018j0.002 90/12/04 0.016j0.002 0.017j0.002 0.014j0.002 0.018j0.002 0.015j0.002 0.009j0.002 0.016j0.002 0.013j0.002 0.018j0.002 90/12/11 0.016j0.002 0.018j0.002 0.016j0.002 0.019j0.002 0.016j0.002 0.016j0.002 0.018j0.002 0.016j0.002 0.013j0.002 90/12/18 0.017j0.002 0.018j0.002 0.015j0.002 0.017j0.002 0.017j0.002 0.018j0.002 0.019j0.002 0.015j0.002 90/12/25 0.014j0.002 0.013j0.002 0.016j0.002 0.017j0.002 0.013j0.002 0.015j0.002 0.014j0.002 0.015j0.002 0.012j0.002 91/01/01 0.017j0.0021 0.017j0.002 0.016j0.002 0.017j0.002 0.018j0.002 0.017j0.002 0.016j0.002 0.017j0.002 0.013j0.002

• Sample locations required by Technical Specifications.

• • Pump Inoperative

-82

TABLf ll NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE STATIONS GROSS BETA ACTIVITY pCi/m" i2 SIGMA LOCATION 90/01/08- 0.015x0.002 0.019%0.002 0.017%0.002 0.015i0.002 0.016%0.002 0.019i0.002 90/01/15 0.01610.002 0.020%0.002 0.02110.002 0.017i0.002 0.018%0.002 0.020%0.002 90/01/22 0.012%0.002 0.015+0.002 0.016i0.002 0.013%0.002 0.012i0.002 0.014%0.002 90/01/29 0.013%0.002 0.015+0.002 0.015%0.002 0.016%0.002 0.015%0.002 0.014%0.002 90/02/05 0.012%0.002 0.009+0.002 0.010~0.001 0.010%0.002 0.00920.002 0.01120.002 90/02/12 0.016i0.002 0.015%0.002 0.016%0.002 0.015%0.002 0.015%0.002 0.016%0.002 90/02/20 0.013i0.002 0.016z0.002 0.014+0.002 0.012%0.002 0.012a0.002 0.013%0.002 90/02/26 0.015+0.002 0.012i0.002 0.013%0.002 0.016%0.002 0.014a0.002 0.016%0.002 90/03/05 0.016%0.002 0.018%0.002 0.016%0.002 0.016%0.002 0.018%0.002 0.017i0.002 90/03/12 0.015i0.002 0.016%0.002 0.017x0.002 0.016%0.002 0.014%0.002 0.014+0.002 90/03/19 0.010i0.002 0.01220.002 . 0.012%0.002 0.011%0.002 0.013%0.002 0..010%0.002 90/03/26 0.013i0.002 0.0162.0002 0.014x0.002 0.01420.002 0.014%0.002 0.015i0.002 90/04/02 0.009%0.001 0.010a0.002 0.010i0.002 0.009x0.002 0.009i0.002 0.009a0.002 90/04/09 0.007%0.001 0.011%0.002 0.01110.002 0.009i0.002 0.009%0.002. 0.009~0.001 90/04/16 0.008%0.001 0.017i0.002 0.015i0.002 0.015a0.002 0.015%0.002 0.012i0.002 90/04/23 0.013a0.002 0.014+0.002 0.015+0.002 0.016%0.002 0.017%0.002 0.015%0.002 90/04/30 0.021%0.003 0.019i0.002 0.01720.002 0.01720.002 0.013i0.002- 0.018%0.002 90/05/07 0.00910.002 0.009i0.001 0.011%0.002 0.00920.002 0.009i0.002 0.009%0.002 90/05/14 0.012%0.002 0.012+0.002 0.012%0.002 0.013%0.002 0.010i0.002 0.011%0.002 90/05/21 0.007i0.001 0.007i0.001 0.00820.002 0.004i0.001 0.007i0.001 0.007%0.001 90/05/29 0.008%0.001 0.007i0.001 0.008%0.002 0.009i0.001 0.00820.002 0.005a0.001 90/06/04 ~

0.012+0.002 0.011%0.002 0.013a0.002 0.011%0.002 0.011%0.002 0.011%0.002 90/06/11 0.010%0.002 0.009%0.002 0.009i0.002 0.010%0.002 0.008%0.002 0.00820.001 90/06/18 0.015%0.002 0.016%0.002 0.017i0.002 0;017%0.002 0.01510.002 0.01520.002 90/06/25 0.008x0.002 0.010i0.002 0.01220.002 0.010%0.002 0.007%0.002 0.007i0.001

-83

TABLE 1 NTINUED)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE STATIONS GROSS BETA ACTIVITY pCi/m" i2 SIGMA LOCATION 90/07/02 0.009%0.002 0.009%0.002 0. 01220. 002 0.010%0.002 0.011%0.002 0.009%0.001 90/07/09 0.012%0.002 0.013%0.002 0.013%0.002 0.012%0.002 0.013%0.002 0.010%0.002 90/07/16 0.008%0.002 0.01020.002 0.010%0.002 0.010%0.002 0.010%0.002 0.008%0.001 90/07/23 0.017%0.002 0.018%0.002 0.01820.002 0.020%0.002 0.018i0.002 0.018%0.002 90/07/30 0.013%0.002 0.01020.002 0.016i0.002 0.016%0.002 0.01520.002 0.014i0.002 90/08/06 0.01120.002 0.011%0.002 0.010i0.002 0.012i0.002 0.011%0.002 0.011i0.002 90/08/13 0.015i0.002 0.012%0.002 0.017i0.002 0.016i0.002 0.015%0.002 0.016i0.002 90/08/20 -0.018%0.002 0.019%0.002 0.019%0.002 0.017t0.002 0.018i0.002 0.016%0.002 90/08/27 0.010a0.002 0.012%0.002 0.012i0.002 0.011%0.002 0.011%0.002 0.012i0.002 9O/O9/O4 0.016%0.002 0.018i0.002 0.018x0.002 0.017%0.002 0.018i0.002 0.016%0.002 90/09/10 0.013%0.002 0.014%0.002 0.014%0.002 0.016%0.002 0.015i0.002 0.013%0.002 90/09/17 0.014%0.002 0.017i.0002- 0.01820.002 0.017%0.002 0.014a0.002 0.01520.002 90/09/24 0.009a0.007 0.008%0.001 0.010%0.002 0.008%0.002 0.008i0.002 0.009t0.002 90/10/01 0.018%0.002 0.021%0.002 0.021%0.002 0.019a0.002 0.02020.002 0.019%0.002 90/10/08 0.012%0.003 0.016%0.002 0.017%0.002 0.017%0.002 0.019i0.002 0.016a0.002 90/10/15 0.006%0.001 0.006i0.001 0.006%0.001 0.006%0.001 0.005io.ool 0.005%0.001 90/10/22 0.013%0.002 0.016%0.002 0.017%0.002 0.015i0.002 0.017%0.002 0.01520.002 90/10/29 0.009a0.002 0.012%0.002 0.011%0.002 0.012%0.002 0.011i0.002 0.012%0.002 90/11/05 0.019%0.002 0.02220.002 0.022%0.002 0.020a0.002 0.021%0.002 0.021%0.002 90/11/13 0.012%0.002 0.013%0.002 0.016a0.002 0.012i0.002 0.014i0.002 0.011%0.002 90/11/19 0.018a0.002 0.021%0.002 0.021i0.003 0.019i0.002 0.019i0.002 0.019i0.002 90/11/26 0.018%0.002 0.01920.002 0.019%0.002 0.018%0.002 0.020%0.002 0.01810.002 90/12/03 0.016%0.002 0.018%0.002 0.016%0.002 0.014%0.002 0.015%0.002 0.00%0.002 90/12/10 0.013%0.002 0.016i0.002 0.013%0.002 0.013%0.002 0.014%0.002 0.016a0.002 90/12/17 0.015+0.002 0.016i0.002 0.01510.002 0.015%0.002 0.01420.002 0.017i0.002 90/12/25 0.014+0.002 0.016%0.002 0.014%0.002 0.014%0.002 0.013%0.002 0.015%0.002 91/01/01 0.018%0.002 0.021%0.002 0.016%0.002 0.017%0.002 0.01920.002 0.015%0.002

-84

TABLE 12 CONCENTRATION OP GAMMA EMZTTERS ZN MONTHLY COMPOSZTES OP NMP AZR PARTZCULATE SAMPLES R-1 OPP-SITE STATION*

Results in units of 10-~Cia + 2 sigma CLIDES FEBRUARY CH RIL 1990 Co-60 <1 ' 1.0 1.0 1.2 <0. 7 <2.3

-54 <0 ' 1~2 0.8 1.4 <0.8 1.4 Cs-134 <0 ' <1 ~ 0 <0.7 1.2 <0.7 <1.1 Cs-137 <0 ' 0~8 <1. 0 1.1 <0.7 1.0 b-95 <1 ' <1. 2 <1.2 1.7 <1. 0 1.4 Zr-95 <2 6 <3 ' 1.8 3.4 <1.4 <2. 6 Ce-141 <1.7 <1. 6 <1.4 2.0 <1.4 1' Ce-144 <5 ' <4 ' <4.3 5.9 <3. 8 <4.3 u-106 <7.8 10.3 <6.9 12.4 <6. 9 <11.6 u-103 <1-1 <1 3 0.9 1.8 <0 ~ 6 1.4 Be-7 43+10 64+13 69+12 5+15 63+10 57+6

-40 33+13 21 26+11 5+15 30+11 15 BaLa-140 <3.0 2.8 1.4 2.0 <2.4 5.3 a-226 <20 20 16 24 <14 15 I-131 <3 3 3 3 <3. 1 4.4 <3.0 2 '

thers** <LLD <LLD <LLD LLD <LLD LLD CLIDES LY UGUST SEPTEMBER CTOBER OVEMBER DECEMBER Co-60 <1. 2 1.2 <2. 0 1.4 <0.6 <0. 5

-54 <0. 8 1.0 <1. 1 1.2 <0.7 <1. 0 Cs-134 <1. 0 <1.0 1.6 1.1 <0.7 <0.9 Cs-137 <0.9 1.1 <1.2 1~2 <0.6 0.7 b-95 <1.5 0.9 1 8 1.7 <0.9 <1 0 Zr-95 <2.0 1.5 2.8 2.5 <1.2 <2 1 Ce-141 <1.7 1.6 2.3 1.3 <1.2 <1. 2 Ce-144 <4.4 4~4 7.4 4.2 <3.4 <3 ~ 8 u-106 <10.9 9.8 13 3 9.8 <6 ' <7 7 u-103 <1.3 <1.2 <1. 6 1.1 <1.0 <1-0 Be-7 66+14 76+12 70+16 52+6 56+10 55+12

-40 31+14 22+11 <31 <16 19+10 14+9 BaLa-140 <2.6 <2.7 4.0 5.0 <1.3 '.6 a-226 <22 <17 27 13 <16 <18 I-131 <3.6 3.4 3.8 3 ' <2.6 2.7 thers** <LLD LLD <LLD LLD <LLD LLD

• Location required by the Technical Specifications.

• • - Other plant related radionuclides.

-85

TABLE 12 (Continued)

CONCENTRATZON OF GAMMA,EMZTTERS ZN MONTHLY COMPOSITES OF NMP AZR PARTICULATE SAMPLES R 2 OFF-SITE STATION*

Results in units of 10-~Cpm + 2 sigma CLIDES FEBRUARY CH RIL .

1990 Co-60 <1 ~ 6 <0.9 <1 ~ 2 <1 9 <0.9 <1. 0

-54 <0 ' <1. 0 <1-3 <1-3 <0. <1. 1 Cs-134 <1 ~ 1 <0.8 <1.2 <1.2 7'li2

<1. 1 Cs-137 <1+1 <0.9 <0.9 <1-0 <0.9 <1. 6 b-95 <1 1

~ <1 ~ 3 <1-2 <1.5 <1-3 <1.4 Zr-95 <2 ' <2.7 <2.6 2.9 <1.7 <2.9 Ce-141 <1-6 <1.4 <1.2 1 3 <1.5 <1.8 Ce-144 <5.3 <4.6 <3.9 4.3 <4.2 <6. 1 u-106 <9.7 <7.6 <9.9 10.5 <7.5 <9.9 u-103 <1 ~ 3 <0.9 <1.2 1 3 <1.1 <1.7 Be-7 48+11 54+10 80+6 84+7 56+10 75+15

-40 41+15 24+10 <12 10 17+9 20+12 aLa-140 <2.7 <1 8 <5.3 2.8 <1.4 <5.0 a-226 <23 12+8 <12 17 <18 <23

-131 <3.1 <3.0 <2.7 2.5 <3 ' <3 '

thers** <LLD <LLD <LLD LLD <LLD <LLD CLIDES LY UGUST SEPTEMBER CTOBER OVEMBER DECEMBER Co-60 <1 3 <1-0 <1.7 1~7 <0.5 <0.9

-54 <1.4 <0.8 <1.5 1.5 <0.6 <1 ~ 0 Cs-134 <1 ~ 3 <1.0 <1.3 1.8 <0.7 <1.0 Cs-137 <1 ~ 6 <1 ~ 0 <1.4 1.3 <0.5 <0.9

-95 <1.9 <1.2 <2.0 <1.8 <0.9 <1.2 Zr-95 <2.7 <1.5 <2.8 2.7 <1 5 <1.8 Ce-141 <1 ~ 4 <1.4 <1.4 1.4 <1 4 <1.7 Ce-144 <4.9 <4.4 <4.7 4 7 <3.3 <5.3 u-106 <9 ' <7 7 <12.8 9.3 <7.5 <9.2 u-103 <1.2 <1 ~ 3 <1 3 1.3 <0 ' <1.3 Be-7 83+7 80+12 80+7 48+6 58+9 68+12

-40 <18 18+10 13+6 21 28+10 42+14 BaLa-140 <4 ' <2 ' <5.3 6.3 <2.7 <3.4 a-226 <16 <18 12+5 17 <15 <20 I-131 <2.9 <3.0 <3.8 3 2 <3.0 <4. 2 thers** <LLD <LLD <LLD LLD <LLD <LLD

• Location required by the Technical Specifications.

• • - Other plant related radionuclides.

-86

TABLE 12 (Continued)

CONCENTRATZON OF GAMMA EMZTTERS XN MONTHLY COMPOSXTES OF NMP AZR PARTICULATE'AMPLES R 3 OFF-SITE STATION*

Results in units of 10<<~Cia- + 2 sigma CLIDES EBRUARY CH NE 1990 Co-60 <1-6 1.2 <1-2 1 2 <1 1

~ 1.8

-54 <1 1 0' <1 ' 1 1 <0. 9 <1.5 Cs-134 <1-4 1 2 <1 1 1.0 <0.7 1.6 Cs-137 <1-1 0.8 <0 ' 1 3 <1 ' <1 '

b-95 <1 6

~ 1 3 <1 ~ 2 1.4 <1.1 <1 '

Zr-95 <2-8 2.9 <2-3 3 2 (2 ' 2.6 Ce-141 <2 ' 1.6 <1-6 1 6 <1 4 1.3 e-144 <6.4 5.2 <4.7 4.7 <4. 3 4.4 u-106 <11.7 9.6 <10 5 9 7 <6. 3 10 '

u-103 <1-6 1.5 <lo 1 1 3 <1 ~ 3 1.4 Be-7 49+12 56+16 77+14 9+13 62+12 60+6

-40 <29 21 32+13 6+13 19+10 20 BaLa-140 <F 1 2.9 <2- 1 2 6 <1 8 4.0 a-226 <26 20 <19 8+13 <16 10+6 I-131 <4.7 3.8 <3. 6 3 2 (3 ' 3 '

thers** <LLD LLD <LLD LLD <LLD LLD CLIDES LY UGUST SEPTEMBER CTOBER OVEMBER DECEMBER Co-60 <F 1 1~0 <1-7 0.9 <1 ~ 0 1.4

-54 <1.0 1.0 <1.5 0.9 0.8 0.9 s-134 <0 8 0.9 <1 ' 0.8 (0 ' 1.0 s-137 <1 1 0.9 <1 6 0.8 <0.8 1.0 b-95 <1-0 1~3 <2.0 1.2 <0.8 1.6 Zr-95 <1 6 1-7 <2 ' 1.7 <1 ' 1.8 Ce-141 <1 ' 1' <1 4 1.5 (1 1

~ 1.8 Ce-144 <4.8 5.1 <4.4 4.2 (3.8 4.6 u-106 <9. 0 9.9 <9.5 8 9 <7 ' <8.4 u-103 <1-3 1.0 <1 ' 1.0 (1 1

~ 1 '

Be-7 73+14 65+13 66+6 58+11 64+10 61+12

-40 25+12 17+10 14+6 6+15 27+11 27+12 BaLa-140 <1.5 2.0 <4.0 2-9 <1.9 2.5 a-226 <20 17 11+6 18 <16 21+13 I-131 <3 ' 4.3 <3 ' 2-9 <2 ' 4.5 thers** <LLD LLD <LLD LLD <LLD LLD

• Location required by the Technical Specifications.

• • - Other plant related radionuclides.

-87

TABLE 12 (Continued)

CONCENTRATZON OR GAMMA EMZTTERS ZN MONTHLY COMPOSITES OP NMP AZR PARTICULATE SAMPLES R-4 OPP-SITE STATION (CONTROL)

• Results in units of lo-~cpm~ + 2 sigma CLIDES EBRUARY CH PRIL NE Co-60 <2 ~ 5 <1 ~ 1 <1 ' 1 1"

~ <0. 9 <2 '

-54 <1. 8 1.0 <F 1 0.9 0.9 <1 '

Cs-134 1.8 1.3 <F 1 1' 0.9 <1 '

Cs-137 1.6 F 1 <1 ' 0.9 0.9 <1.6 b-95 2.2 1.8 1.8 1.2 1.2 <2 '

Zr-95 <5-1 3.2 <2-8 3 ~ 1 2.0 <2.0 Ce-141 2.1 1.9 1.4 1' 1.6 2.1 Ce-144 6.1 5.7 3.9 5.0 4.7 6.6 u-106 16.3 9.8 11.4 11.8 7.0 <12.3 u-103 1.8 1.4 1.2 1.2 1.3 <1.7 Be-7 72+8 70+14 88+7 74+13 57+11 75+15

-40 24+7 27+14 7+4 27+ 13 44+14 27+15 BaLa-140 <7 ' 1.8 4.5 2.5 2.2 2 '

a-226 23 27 14 21 24+11 <26

-131 3.6 3 ' 3.3 3 ' 3.4 4.9 thers** LLD LLD LLD LLD LLD <LLD CLIDES LY UGUST EPTEMBER CTOBER OVEMBER DECEMBER o-60 2.2 1.1 1.5 1-1 1.1 <1 ~ 1

-54 <1 ~ 1 0.9 1.0 1.5 1.0 <1 ~ 0 Cs-134 <1.7 1.0 1.1 1.1 0.7 <1.0 Cs-137 <1 ' 1.0 0.9 1~1 1.0 <1. 1 b-95 2 ' 1.8 <1 ' 1.6 0 8 1.4 Zr-95 2.6 1.8 2.0 2 3 <1.9 <1-9 Ce-141 <1 ' 1.6 <1 ' 2~0 <1 ' <1 8 Ce-144 4.2 <4 1 5' 5~6 3.9 <5.4 u-106 13.5 9.0 9.1 8.8 9.1 <9.4 u-103 1.5 1.3 1.4 1.3 1.3 <1.5 Be-7 86+7 5+13 3+13 59+12 69+14 71+13

-40 14 19 41+15 32+16 17 35+14 BaLa-140 4.4 1.9 2.3 F 1 2.3 2 '

a-226 16 18 18 22+ 13 16 <23 I-131 3.4 4.5 4.2 3 ' 3.0 <4.4 thers** LLD LLD LLD LLD LLD LLD

• Location required by the Technical Specifications.

• • - Other plant related radionuclides.

-88

TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMZTTERS ZN MONTHLY COMPOSITES OF NMP AZR PARTICULATE SAMPLES R-5 OFF-SITE STATION*

Results in units of 10-~Cia .+ 2 sigma CLIDES FEBRUARY CH RIL 1990 Co-60 <0.9 <1 ' <0.6 1~3 <1. 6 1.0 n-54 <0.8 <1.0 <0.9 1.0 <1 1 <0.7 Cs-134 <0.7 0 8 <0 ' 0 ' <1 2 0.9 Cs-137 <0.9 1.0 <0.9 0.7 <0 8 0.6 b-95 <1-0 <li2 <1.4 1.3 <1.3 1 1 Zr-95 <1.8 <2 ' <2.0 2.5 <2 1 1.5 Ce-141 <1.6 1.6 <1 ' 1.4 1.7 1.6 Ce-144 <4 ' <5.0 <4.0 4.0 <5.0 4.7 u-106 <10.4 <9.7 <7 7 8.2 <9.9 <8 '

u-103 <1.1 <F 1 <0.9 1.0 <1.2 <1.0 Be-7 51+11 72+12 68+12 6+12 58+12 21

-40 42+14 36+14 <11 37+13 13+10 30+13 BaLa-140 <1.2 2' <3 ' 1.2 <2 1 1 7 a-226 19+13 19 <14 4+10 <20 18 I-131 <2.9 3.1 <2 ' 2.5 <4.0 <2 '

thers ** <LLD LLD <LLD LLD LLD LLD CLIDES UGUST SEPTEMBER CTOBER OVEMBER DECEMBER Co-60 <1+2 1' <2 ' 1.0 0.6 1.2

-54 <1.1 0' <1.0 0.8 <0.6 1.4 Cs-134 <1.1 1 2 <1 ' 1.2 <0. 6 0.7 Cs-137 <1 ' 1 1 <1.2 1.2 <0 ~ 6 <0. 9 b-95 <1-2 1.4 <1.6 1.6 <1- 1 1 2 Zr-95 <2.4 2.6 <3+3 2 ' <1. 6 1.8 Ce-141 <1.8 1' <1 ' 1.8 <1.3 1.5 Ce-144 <5.0 4.8 <4.4 4.8 <3 ' 4.9 u-106 <9.3 11.9 <10 1 12.9 <6.6 <8.2 u-103 <1 ' 1.6 <1.4 1.6 <0.9 1.0 Be-7 80+14 68+14 66+6 9+12 63+9 52+12

-40 62+18 13+9 16+5 18+13 20+9 29+12 BaLa-140 <1.5 4.3 5.7 3.4 <1 8 3.0 a-226 18+12 21 16+7 20 <14 18 I-131 <3+2 4.3 <4.2 2.8 <2 3 4.1 thers** <LLD LLD <LLD LLD <LLD <LLD

• Location required by the Technical Specifications.

• • - Other plant related radionuclides.

-89

TABLE 12 (Continued)

CONCENTRATION OP GAMMA EMITTERS IN MONTHLY COMPOSITES OP NMP AZR PARTICULATE SAMPLES D2 OPP-SITE STATION*

Results in units of 10- Ziti + 2 m~ sigEa CLIDES EBRUARY CH PRIL- NE 1990 Co-60 1.2 1.2 1.0 1' 0.7 <1 '

-54 <1-2 1.0 1.0 1.0 0.7 <1.3 Cs-134 1.0 0.7 0' 0 ' 0.7 1~1 b-95 0 ' 1.1 1.0 0.7 0.8 <1 ~ 1 Zr-95 <1.1 1.3 1.5 1.2 1.2 1.4 Ce-141 <2 5 3.8 2 7 2 ' 1.2 <2.2 Ce-144 <1.6 1.8 1.6 1.6 1.2 <1-2 u-106 <5.0 5.8 4.8 4' 3.2 3.9 u-103 8.4 9.4 11 ' 9.1 6.7 <9.6 Be-7 0.9 1.3 <1 ' 0.9 1' <1 '

-40 57+11 49+12 61+12 63+12 65+12 61+6 BaLa-140 26+12 38+17 36+14 37+15 12+7 13+4 a-226 2.5 2.0 3 ' 2.0 2.4 <5.0

-131 20 26 20 15+13 10+6 9+5 thers** 2.7 3.8 3.6 2 ' 2.6 2.8 LLD LLD LLD LLD LLD LLD CLIDES LY UGUST EPTEMBER CTOBER OVEMBER DECEMBER o-60 1 2 1.1 <1. 1 1.5 1.0 <2.2

-54 0.6 1 2 1~1 <1.3 1.1 1 7 s-134 0.8 1 3 1 2 1 3 1.0 <1.6 Cs-137 <1.1 0.9 1~0 1 1 0.9 <1 2 b-95 1.1 1 3 1 3 1.8 1.5 <2 4 Zr-95 <1.9 1.8 2.4 2.6 2.0 2.3 Ce-141 1.6 1 3 1.9 1.6 1.7 2 1 e-144 <4.9 4.0 5.4 3.8 4.9 <5. 6 u-106 5.5 9.7 10.0 8.4 10.0 <14. 5 u-103 1 1 1 2 1.5 1.4 1.2 <2.0 Be-7 63+12 80+6 2+14 58+6 51+11 67+7

-40 33+14 15+6 30+14 16+6 23 <25 BaLa-140 1.5 6.6, <3.9 3 1 2.6 <7.2 a-226 13+8 12 22 16 19 15+8 I-131 2.6 4.0 5.0 3.0 3.4 <4 8 thers** LLD LLD LLD LLD LLD <LLD

• Optional sample location.

• • Other plant related radionuclides.

-90

TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMZTTERS ZN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES E OFF-SITE STATION

• Results in units of 10-~cpm~ + 2 sigma CLIDES EBRUARY CH PRIL'.3 1990 Co-60 <1.4 1.1 1.0 1 0 1.3

-54 1.4 <1.4 1.0 1.4 0.8 1 1 Cs-134 <1 ' '.2 0.9 0.9 0.9 1.0 Cs-137 1.4 1.0 1.0 1.0 0 7 1.0 b-95 <1. 1 1.5 0.4 1.7 0~8 1~1 Zr-95 2.6 2.5 2.0 3' 1.6 1.9 Ce-141 F 1 1.8 1.4 1' 1.5 1.5 Ce-144 <6.3 5.0 4.6 4' 3 ' 5.6 u-106 8.8 10. 0 8.0 9.4 8 ' 7.4 u-103 1.5 1.0 1.1 1.3 1 1 1 3 Be-7 70+14 66+12 66+12 85+7 8+11 9+15

-40 30 44+17 17+9 13 23+10 27+13 BaLa-140 2 ' 2.2 3 ' 5.6 2 0 3.1 a-226 17+13 26+13 9+7 12+6 18 15+12 I-131 <4.7 3.3 2.9 2.3 3 2 3.6 thers** <LLD LLD LLD LLD LLD LLD CLIDES LY UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 <F 7 0.8 1.7 0.7 0.7 1.3 .

-54 0.9 0.7 1.4 1.0 0.6 0.9 Cs-134 0.8 1.0 1.4 0' 0.6 1.1 Cs-137 0.9 0.9 1.4 0.8 0.7 1.1 b-95 1.0 1.6 1.8 1.3 0.8 1.6 Zr-95 <1.8 <1.7 1.9 1.1 2 1 <2. 0 Ce-141 1.5 1.4 2 1 1.4 1 2 1.6 Ce-144 4.8 3.9 5.4 4.4 3.9 4.9 u-106 8.5 F 1 13 8 8.5 6.5 7.3 u-103 1.0 1.2 1.8 1.1 1.0 <1.4 Be-7 75+12 79+14 69+15 56+10 61+10 63+13

-40 25+11 18 43+18 35+12 25+11 34+14 BaLa-140 2.4 1.8 4.3 2.6 2.7 3.5 a-226 19 18 23 15+9 16 14+9 I-131 2.6 4.3 4.5 3 ' F 1 4.0 thers** LLD LLD LLD LLD LLD LLD

• Optional sample location.

• • - Other plant related radionuclides.

-91

TABLE 12 (Continued)

CONCENTRATION OP GAMMA EMITTERS IN MONTHLY COMPOSITES OP NMP AIR PARTICULATE SAMPLES 7 OPP SITE STATION

• Results in units of 10-~Cia + 2 sigma CLIDES ANUARY EBRUARY CH PRIL 1990 Co-60 <F 7 1.7 1.1 1.6 0.6 1~1

-54 1.5 1.5 1 3 1.4 1.2 1 2 Cs-134 1 3 1.3 1.4 1.2 1~1 1.6 Cs-137 1.2 1.3 1.0 1~3 0.9 <1-3 b-95 1.9 2.0 1.4 F 1 1.3 <1-9 Zr-95 2 ' 2.6 2' 2.8 1.9 3.0 e-141 1.6 2 1 1~2 2.1 1.5 2.0 Ce-144 5.4 6.6 3.5 6.1 4.5 <6 '

u-106 10.8 13 ~ 7 9.4 12 2 9.8 10.0 u-103 1.6 1.4 <1.3 1.8 1.0 2.1 Be-7 58+6 74+16 61+5 9+16 59+12 65+14

-40 22 29 14 42+17 27+13 34+18 aLa-140 5.2 3.0 3.4 3.0 2.8 5.0 a-226 19+8 27 13 24 18 27 I-131 3 ' 4 ' 3.4 4.1 3.2 4.5 thers** LLD LLD LLD LLD LLD LLD CLIDES UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 1.2 1.4 1.0 0.8 0.8 <1 ~ 9

-54 1.7 1.2 <1. 0 0.7 0.8 1~2 Cs-134 0.9 1.3 0.8 0.9 0.8 1.4 Cs-137 1.3 0' 1.0 1.0 0.5 1.6 b-95 1.9 1~1 1~2 1 2 1~0 2.0 Zr-95 2.3 2.0 1.3 1 7 1.2 2.8 Ce-141 2.0 1.8 1.6 1.5 1~3 1~3 e-144 <6. 6 5.2 4.2 4.7 3.7 3.8 u-106 14. 0 11.2 8 ' 7.7 7.3 11.6 u-103 1.5 1.3 1.3 0.9 0.9 <1 ~ 4 Be-7 81+16 87+16 68+13 59+10 59+10 54+6

-40 54+21 28 47+15 40+14 26+10 11+4 BaLa-140 3.6 <2 ' <2.6 1.7 2.5 4.8 a-226 27 20 19 19 11+6 16 I-13 1 4.0 5.4 4.0 2 ' 2 3 4 ~ 1 thers** LLD LLD LLD LLD LLD LLD

• location.

• • - Optional sample Other plant related radionuclides.

-92

TABLE 12 (Continued)

CONCENTRATXON OP GAMMA EMITTERS ZN MONTHLY COMPOSXTES OP NMP AIR PARTXCULATE SAMPLES G OPP SZTE STATION

• Results in units of 10-~Cpm~ + 2 sigma CLIDES FEBRUARY CH PRIL 1990 o-60 <1.4 1' <0.7 1~1 1.4 <0. 9

-54 1.6 1.0 0' 1.1 0.8 1~2 s-134 <1 ~ 1 0.9 0.9 1.0 1.0 1.0 Cs-137 <1.2 1' 0.7 1.0 <0.8 1~2 b-95 1.9 1.5 0.7 1.0 1 2 1~1 Zr-95 3.0 3~2 2.6 2.3 1.4 1~8 Ce-141 <2.1 1.6 1.4 1.7 1 2 1.5 Ce-144 7.0 5.2 4.6 5.0 4.0 4.8 u-106 16.5 9.6 8.6 6.7 8.6 9 '

u-103 1.5 1.4 1 1 1.0 1.1 1 3 Be-7 43+12 54+12 60+12 4+12 54+11 56+11

-40 38+17 28+14 12+8 7+16 10+8 28+12 BaLa-140 2 2 2.9 2.8 3 ' 2 2 1' a-226 27 24 18 19+10 8+7 20 I-131 4.0 3.7 3.0 3.1 F 1 2~9 thers** LLD LLD LLD LLD LLD LLD CLIDES LY UGUST EPTEMBER CTOBER OVEMBER ECEMBER Co-60 <2.0 1.0 1.0 0.8 0.9 1.0

-54 1 1 0.9 1~0 1' 0.9 0.9 Cs-134 1.6 0.7 0.9 1 2 0.8 1.0 Cs-137 1.4 0' 1 ' 0.9 0.6 1.1 b-95 <1.5 1' 2 1 1.2 0.9 1.2 Zr-95 <2.9 1.6 2.0 2' 1.8 2.2 e-141 1' 1' 1.6 1.8 1.5 1.7 Ce-144 <4.8 4.3 4.0 4 ' 4 ' 5.1 u-106 11 ' 8 2 9.5 <11.2 7.8 10.4 u-103 <1 ' 1~1 1.4 1.4 1~1 1 2 Be-7 70+7 9+12 68+15 50+12 51+11 50+11

-40 19+6 41+13 20+11 13+10 15+10 29+13 BaLa-140 5.7 2.4 3 ~7 3.4 1.6 1.4 a-226 13+8 16 24 20 8+7 21 I-131 3~3 3.0 4.7 3.8 2.4 3.8 thers** LLD LLD LLD <LLD LLD LLD

• Optional sample location.

• • - Other plant, related radionuclides.

-93

TABLE 12 (Continued)

CONCENTRATZON OF GAMMA EMZTTERS ZN MONTHLY COMPOSITES OF NMP AZR PARTZCULATE SAMPLES D1 ON-SZTE STATZON*

Results in units of 10<<~c+m~ + 2 sigIRL CLZDES ANUARY FEBRUARY CH 1990 Co-60 <1 ~ 2 1.5 1~1 0.5 0.8 1'

-54 <0.9 <1-4 1.1 0.8 0.9 1.4 s-134 <0.9 1.2 1.0 0.9 0.8 1.0 Cs-137 <0.9 1.0 0 9 0.8 0.9 1.0 b-95 1' 1.5 1 3 1.1 1.4 1.8 Zr-95 <2.8 2 2 2.6 2 ' 2.0 2.5 Ce-141 1.5 1' 1.5 1.5 1.4 1 7 Ce-144 <5.0 5.2 4 ' 4.0 4.5 5.9 u-106 <9.0 9.4 9.2 6.9 8.4 <14 8 u-103 <1-4 1~1 1.1 1' 1.1 1.2 Be-7 57+12 57+14 54+11 55+10 56+11 75+19

-40 35+14 28+14 21+12 33+12 35+14 26+15 aLL-140 2 ' 3 ' 2.5 1~1 2.6 3.6 a-226 22 21 19 17 17 20+12 Z-131 3.5 2.8 3.9 2.8 3 ' 4.1 thers** LLD LLD LLD LLD LLD LLD CLZDES LY UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 <0.8 1.2 1.0 1.5 1.5 0.7

-54 <0 ' 1.0 1.4 1 2 0.9 1.0 Cs-134 <1.0 1.0 1.6 1.4 1.0 0 9 Cs-137 <0.9 0.9 1.3 1.3 1.0 0.9 b-95 <1 ' 1~3 1.7 1.9 1.5 1' Zr-95 <2 ' 2.5 2.7 1.9 2.0 1.3 Ce-141 1' 1.7 .2-3 2 ' 1.5 1.5 Ce-144 <4.4 5.3 6.7 6.2 4.9 4.7 u-106 7.9 11. 8 11.8 10.4 11 2 <9.4 u-103 <1 ' 1.5 1.8 1.4 1' 1.2 Be-7 70+12 59+12 65+15 54+12 87+14 54+12

-40 45+15 25+12 56+20 43+17 19+12 28+13 BaLa-140 <1 ' 3.7 2.0 3.4 3 ' 1.5 a-226 19 18 26 25+14 20 20 I-131 <2 ' 4.0 4.2 3.3 4.0 <3 ~ 1 thers** LLD LLD LLD LLD LLD LLD

• sample location.

• - Optional Other plant related radionuclides.

-94

TABLE 12 (Continued)

CONCENTRATZON OP GAMMA EMITTERS ZN MONTHLY COMPOSZTES OP NMP AZR PARTICULATE SAMPLES G ON-SITE STATZON

• Results in units oi XO-~Cpm + 2 sigma CLI DES ANUARY FEBRUARY PRIL 1990 o-60 <1 ' 1 2 1.0 1.0 0.9 <0.7

-54 <1.0 0' 0' 1.2 1.0 <0.7 C s-134 <1 ' 1' 0.7 1~1 0.8 1.0 C s-137 1.6 1 1 0' 1~1 1.0 1.1 b-95 <1.8 1.0 0' 1.6 1.1 1.4 r-95 3.0 2 9 1 6 3.5 2.2 1.9 e-141 (1. 4 1.5 1 2 2.0 1.4 1.7 e-144 4.8 4' 3 ' 6.7 4.8 4.7 u-106 <10.0 <8 ' 7 7 10.2 10.6 10.0 u-103 1~0 1 4 1.0 1.6 1.5 <1.2 e-7 45+11 61+13 86+13 104+19 0+12 62+11

-40 (20 13+10 3 1+12 52+20 15+11 40+15 aLa-140 3.4 2' 2 2 2.0 3.0 1.4 a-226 19 9+8 16+9 27 19 15+9

-131 3.2 3 5 3 0 3.9 3.4 3 3 thers** LLD LLD LLD LLD <LLD CLIDES LY UGUST EPTEMBER CTOBER DECEMBER o-60 1.0 0.7 0 9 1.5 0.9 1.2

-54 1.0 1 2 1-1 1.2 0.7 1 1 s-134 0.7 0.9 1.0 1.2 0.8 1.0 s-137 1.0 1.0 0<<8 1.0 0.8 0.9 b-95 1.4 1 4 1.0 1.4 1.1 1.2 2 r-95 <1 ' 2 ' 2 2 1.9 1-2 2.0 C e-141 <1 6 <1.6 1.6 2.1 1.0 <1.5 C e-144 <5.2 4 ' 5.1 6.5 4.0 4.7 u-106 10.5 9 ' 10.5 11.7 8.1 <5.9 u-103 <F 1 1 4 1 2 <1.5 1.0 1 1 e 7 72+12 9+13 69+12 60+13 66+11 69+12

-40 32+14 24+12 37+12 36+17 13+8 37+14 aLa-140 <2 ' 3 ' 1 6 4.6 1.4 <2 '

a-226 19 10+7 20 24 14 16

-131 3.0 3.6 2 8 3.8 3 ' 2.9 thers** <LLD LLD LLD LLD LLD LLD Optional sample location.

• -Other plant related radionuclides.

-95

TABLE 12 (Continued)

CONCENTRATION OP GAMMA EMZTTERS ZN MONTHLY COMPOSITES OP NMP AZR PARTICULATE SAMPLES H ON-SITE STATION

• Results in units of 10-QC~i g~ + 2 sigma CLZ DES FEBRUARY CH PRZL NE 1990 Co-60 1.9 1' 1.4 1.8 1.6 <1 8 n-54 1.2 1 3 1.0 1 3 1.0 <2.0 Cs-134 <0 ' 0.8 1.1 1.6 1.4 <1-4 s-137 <1.3 0.9 1.0 1.3 1.0 <1 9 b-95 1.5 1.5 1.3 <1 ' 1.8 <1.7 Zr-95 <2.6 1.8 2.8 2.6 2.8 <3.5 Ce-141 1 7 1.9 1.6 <2 ' 2.2 2 3 Ce-144 <5 ' <5 ' 4.8 F 1 6.7 7~2 Q-106 <11.7 8 ' 8.9 12.6 13.7 14.7 Q-103 1.6'4+11 1.4 1.4 1.5 2.0 1.8 Be-7 62+13 65+12 74+16 57+14 60+15

-40 33+15 29+15 21+11 28+16 32 53+20 aLa-140 4.9 3.2 3.9 3 ' 2.3 4.0

-226 22 21 20 27 26 26

-131 3.8 F 1 2.7 4.3 4.2 4.0 thers** LLD LLD LLD LLD LLD LLD CLZDES LY UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 <1.7 1~2 1.5 F 7 0.6

-54 1' 0.8 1.4 1.7 0.9 <1. 0 Cs-134 <1-3 <0.9 1.8 1.5 1.0 <0.9 Cs-137 0.9 0.6 1 3 1.4 0.9 <1.0 b-95 'i+3 1.3 2.0 2.0 1' <0.9 Zr-95 <2 ' 2~1 2.8 2.6 1.4 <2-0 Ce-141 <2 ' 1.5 1.6 2.1 1.5 1.5 Ce-144 <6.5 4.6 5.1 6 ' 4.7 <4.2 u-106 Q-103 12.8

<1.9 10.0 1.4 13 '

1.7 14.2 1.4 LLD'0.7 7 1 1.1

<6 '

<1+1 Be-7 62+14 72+12 56+7 58+14 53+10 45+9

-40 21+14 23 17+7 27+16 33+ 12 33+13 BaLa-140 3.8 3.4 6.6 4.3 1.2 <2 '

a-226 24 17 16+7 <26 17 <19 I-131 3.4 3.8 3 ' 3.8 3.4 3.2 thers** <LLD LLD LLD LLD <LLD

• Optional sample location.

• • Other plant related radionuclides.

-96

TABLE 12 (Continued)

CONCENTRATION OP GAMMA EMZTTERS ZN MONTHLY COMPOSITES OP NMP AIR PARTICULATE SAMPLES I ON-SITE STATZON

• Results in units of 10<<giCi~m~ + 2 sigma CLIDES EBRUARY CH PRIL 1990 Co-60 <1 5 1' 0~7 <0.9 <1-8 1' n-54 <1 4

~ 1.0 1~1 0 ' 1 2 1 0 Cs-134 <0 ' 1~1 0~8 1.1 0.9 1 1 Cs-137 <1.0 1~0 1~1 1.1 1 1 1' b-95 1.0 3 1-2 1.3 1.5 1.3 Zr<<95 2 2 2' 2' 2.6 2.3 1.8 Ce-141 <1 6 1~6 1' 1.6 1.9 1.5 Ce-144 F 1 <4 ~ 7 3' 4 ' 5.1 4.7 u-106 <10.0 <9 ~ 1 8' 9 ' 10.8 <10.1 u-103 1.5 1~0 1' 1.2 1.6 1 1 Be-7 58+13 56+12 62+5 64+11 45+11 68+13

-40 29+13 16+10 18 42+14 32+14 53+18 BaLa-140 3 ' 3.5 5.3 2 ~ 9, 3.2 1.5 a-226 18 21+12 13 18 20 14+9 I-131 2 4 3.0 2.4 3.0 3.8 2.9 thers** LLD LLD LLD LLD LLD LLD CLIDES LY UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 <1 ' 1~1 1~7 0 ' 0 ' <0.7

-54 <0.8 <0 ' 1.0 1.2 0.8 <F 1 Cs-134 <0 ' 0 ' 0.9 0' 0' 0.9 Cs-137 0.8 0.6 1.0 '

<0.9 0.8 0.8 b-95 <1 ' 1.0 ~ 5 1.2 1.0 <1 '

Zr-95 <1 ' 1.5 <2 ~ 2 <1.7 2 3 <1.6 Ce-141 <1 ' 1' 1~8 1.6 1~5 1 6 Ce-144 <4.4 3 8 5.2 4. 4~4 <5.3 u-106 7' 10.1 7' 10.6 5'.3 9 0 u-103 <1 ~ 0 0.8 1' 1.3 0.9 1 3 Be-7 62+11 66+10 54+12 57+11 55+10 50+11

-40 55+16 33+11 30+13 40+14 44+14 32+13 BaLa-140 3 2 1.6 2 ' F 1 2.0 1.5 a-226 <19 14 <20 18 9+8 20 I-131 <2 9 3 ' 2.6 2 ' 2.9 3 2 thers** <LLD LLD <LLD <LLD LLD LLD

• Optional sample location.

• • Other plant related radionuclides.

-97

TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMZTTERS IN MONTHLY COMPOSITES OF NMP AZR PARTZCULATE SAMPLES ON-SITE STATION

• Results in units of 10-~Cia~ + 2 sigma 1 =

CLIDES FEBRUARY CH PRZL 1990 Co-60 <1.7 2.1 1~3 <0.8 <1 2

~ 1~1

-54 <1 ~ 0 1.6 1.0 1.0 0' 1~3 Cs-134 <1 ~ 3 1 2 0.7 0.9 0.9 1.4 Cs-137 <1 ~ 4 1.7 0.8 0.8 1.0 1.4 b-95 <2 ' 1.4 1.1 1.4 <1 2 1.9 Zr-95 <2 ' 2.8 2.5 2.1 2.0 2.4 Ce-141 <F 1 <2.0 1.4 <1.6 <1.6 2' Ce-144 <6 ' 7.0 5.0 <4.7 <4 ' 6.7 u-106 <16.4 9.1 8.2 9.6 7.5 10.1 u-103 1 7 1.3 1.2 1.3 1 3 1.8 Be-7 50+13 57+14 64+11 1+13 48+10 2+15

-40 27+15 32+16 35+13 52+17 22+10 27+15 aLa-140 <3 ~ 6 2.4 2 2 2 ' 3.0 4.4 a-226 24 13+10 18 ll+9 16 20+12 I-131 3.8 4.3 3.0 3.1 3.6 4 '

thers** LLD LLD LLD LLD LLD LLD "

CLZDES UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 <1-0 <1 ~ 1 1.2 <1.3 1~3 1 2

~

n-54 <1.4 1.0 1.0 1.1 1 2 0.9 s-134 <1 ~ 2 0.9 1 2 1.0 1.0 1.0 Cs-137 1-3 0.9 1.0 1.0 1.0 0.9 b-95 1.3 1.5 1 7 1.4 1~4 1 2 Zr-95 2 ' 1.8 2.6 3.1 <2.5 <2.0 Ce-141 <1-7 1.5 1.8 <2.0 1~7 <1 ~ 7 Ce-144 5.8 4.6 5.9 <5.9 5.2 4 '

u-106 <8 ' 8.6 11.7 <11.2 10.2 <7.0 u-103 <1-0 1.2 1.4 1.3 <1 ~ 2 <1 ~ 2 Be-7 56+14 61+11 56+11 56+12 45+12 52+11

-40 35+16 3 1+14 44+15 35+15 14+10 42+14 BaLa-140 <3.0 2 2 4 ' 1.7 <2.7 <2 '

a-226 <20 16+10 24 <24 17 19 I-131 2 ' 3.2 3.7 3.0 3~3 3.0 thers** LLD LLD LLD LLD LLD LLD

• Optional sample location.

• • Other plant related radionuclides.

-98

, TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMZTTERS IN MONTHLY COMPOSZTES OF NMP AZR PARTICULATE SAMPLES K ON-SITE STATION

• Results in units of 10-~Cia + 2 sigma CLXDES FEBRUARY CH PRZL NE 1990 Co-60 <1. 0 <0 8 <0.9 <1. 5 <1.6 <1. 6 n-54 <0. 9 <1. 2 <1.2 <1.5 <1.4 <1.2 Cs-134 <1 0

~ <1. 0 <1.0 <1+2 <1.4 <1.2 Cs-137 <0.9 <0.9 <0.9 <1 ' <1.0 <0.8 b-95 <1.0 <1.5 <1.2 <1.8 <1.4 <1.9 Zr-95 <3.5 <F 1 <3.2 <3.5 <2.5 2.7 Ce-141 <1.5 <1.7 <1.2 <1.9 <2.0 <1.5

'e-144

<4.7 <4.6 <3 ' <5.5 <5.6 <4.1 u-106 <9.7 <8.4 <8.1 <12.2 <10. 1 <11.0 u-103 <1 ' <1.2 <1.0 <1.2 <1.5 <1.4 Be-7 58+12 47+11 58+5 79+15 63+13 52+6 E-40 <19 14+10 <8 31+15 <28 <15 BaLa-140 <3.7 <2 ' <3.2 2.8 <6.2 <4. 4 a-226 <21 <18 <13 <21 <24 11+6 I-131 <3. 0 <4.0 <2.3 <3.9 <4.0 <3.0 thers** <LLD <LLD <LLD <LLD <LLD <LLD CLIDES ULY UGUST EPTEMBER CTOBER OVEMBER DECEMBER Co-60 <0.5 <1 ' <0.8 <1. 0 <0.8 <1.2 n-54 <1.1 <0.7 <1.0 <1.1 0.8 <0.8 Cs-134 <0.9 <0.6 <0.9 <1 ' <0.9 <0.8 Cs-137 <1.0 <0.6 <1.0 1.0 <0.8 <1. 0.,

b-95 <1.0 <0.8 <1.6 <F 1 <0.8 <1.1 Zr-95 <2.0 <1.3 <2.5 <1.8 <1.9 <1.8 Ce-141 <1.5 <1 ' <1.8 <1.5 <1.2 <1.5 Ce-144 <5.5 <3 3 <F 1 <4.0 <3.8 <4.9 u-106 <8.4 <6.8 <9.6 8.1 <9.4 <9.0 u-103 1.2 0.8 1.2 1.2 <1.0 <1. 1 Be-7 50+11 56+9 54+11 56+12 55+11 56+10

-40 34+14 32+10 43+16 18 <17 38+13 BaLa-140 <1.5 <2 ' <2.1 <2 ' <2.5 <2.3 a-226 <17 <13 <19 21+12 <14 <20 I-131 <2 ' <3.9 <3.4 <3.1 <3 ~ 1 <3.5 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• - Optional sample location.

• • - Other plant related radionuclides.

-99

TAB 3 NMP/JA SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF-SITE STATIONS I-131 ACTIVITY pCi/m"3 a 2 SIGMA LOCATION 90/01/09 <0.014 <0.016 <0.010 <0.015 <0.012 <0.010 <0.010 <0.013 <0.012 09/01/16 <0.009 <0.011 <0.012 <0.010 <0.010 <0.012 <0.010 <0.012 <0.011 90/01/23 <0.012 <0.008 <0.007 (0.008 <0.009 <0.010 <0.010 <0.008 <0.007 90/01/30 <0.007 <0.010 <0.006 <0.019 <0.007 <0.011 <0.007 <0.011 <0.011 90/02/06 <0.009 <0.009 <0.007 <0.009 <0.008 <0.006 <0.011 <0.009 <0.011 90/02/13 <0.009 (0.008 <0.009 <0.010 <0.009 <0.007 (0.008 (0.006 <0.007 90/02/20 <0.010 (0.008 <0.008 <0.009 (0.007 <0.008 <0.011 <0.008 <0.007 90/02/27 <0.013 <0.011 <0.010 <0.011 <0.014 <0.011 (0.012 <0.013 <0.015 90/03/06 <0.010 <0.011 <0.009 <0.011 <0.008 (0.010 (0.011 <0.012 <0.010 90/03/13 <0.011 <0.008 <0.010 <0.010 <0.014 <0.012 <0.011 <0.014 <0.014 90/03/20 <0.007 <0.013 <0.012 <0.013 <0.010 (0.012 <0.013 <0.012 <0.012 90/03/27 <0.011 <0.009 <0.011 <0.015 <0.008 (0.011 <0.008 <0.013 <0.010 90/04/03 <0.012 <0.011 <0.015 <0.013 <0.012 <0.011 <0.009 <0.013 <0.009 90/04/10 <0.014 <0.010 <0;010 <0.009 <0.009 <0.012 <0.009 (0.012 <0.019 90/04/17 <0.012 <0.013 <0.008 <0.009 <0.011 <0.010 <0.009 <0.014 <0.019 90/04/24 <0.009 <0.009 <0.009 <0.008 <0.012 <0.008 <0.010 <0.016 <0.017 90/05/01 <0.010 <0.013 <0.015 <0.009 <0.012 <0.012 <0.011 (0.012 <0.011 90/05/08 <0.013 <0.009 <0.009 <0.010 <0.014 <0.010 (0.015 <0.011 <0.011 90/05/15 <0.010 <0.012 <0.008 <0.015 <0.009 <0.010 <0.012 <0.011 <0.009 90/05/22 <0.013 <0.009 <0.012 <0.018 <0.012 <0.011 <0.013 <0.014 <0.010 90/05/29 <0.010 <0.009 <0.011 <0.013 <0.028 <0.009 <0.011 <0.011 <0.014 90/06/05 <0.010 <0.011 <0.017 <0.010 <0.010 <0.011 <0.015 <0.011 <0.010 90/06/12 <0.012 <0.010 <0.011 <0.013 <0.011 <0.008 <0.012 <0.013 <0.012 90/06/19 <0.013 <0.011 <0.013 <0.011 <0.012 <0.010 <0.012 <0.013 <0.013 90/06/26 <0.015 <0.009 <0.012 <0.015 <0.007 <0.009 <0.011 <0.014 <0.012

• Sample locations required by Technical Specifications snn

TABLE 13 (C0NTINUED)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF-SITE STATIONS I-131 ACTIVITY pCi/m"3 a 2 SIGMA LOCATION 90/07/03 <0.012 (0. 013 <0.011 <0.012 <0.013 <0.010 <0.011 <0.013 <0.009 90/07/10 <0.018 <0.008 <0.012 <0.014 (0.014 <0.015 <0.012 <0.011 <0.016 90/07/17 <0.012 <0.010 <0.010 <0.016 <0.011 <0.010 <0.011 <0.013 <0.008 90/07/24 <0.013 <0.010 <0.009 <0.010 (0.061 (0.016 <0.009 <0.011 .<0.016 90/07/31 <0.015 <0.011 <0.013 <0.013 <0.011 <0.011 <0.012 <0.046 <0.012 90/08/07 <0.015 <0.011 <0.013 <0.015 <0.011 <0.018 <0.016 (0.014 <0.013 90/08/14 <0.014 <0.009 <0.013 <0.013 <0.012 (0.008 (0.018 <0.013 90/08/21 <0.013 <0.010 <0.012 (0.012 <0.010 <0.010 <0.013 <0.012 <0.014 90/08/28 <0.012 <0.011 <0.014 <0.012 <0.010 <0.011 <0.011 <0.011 <0.013 90/09/04 (0.018 <0.011 <0.010 (0.012 <0.012 <0.009 <0.009 <0.012 <0.009 90/09/11 <0.037 <0.014 <0.012 <0.013 <0.013 <0.017 (0.011 (0.012 <0.011 90/09/17 <0.012 <0.009 <0.011 <0.011 <0.010 <0.012 <0.011 <0.010 <0.012-90/09/25 <0.015 <0.012 <0.007 (0.012 <0.009 <0.020 <0.014 <0.010 <0.012 90/10/02 <0.007 <0.009 <0.009 <0.010 <0.008 <0.014 <0.010 <0.012 <0.012 90/10/09 <0.008 <0.011 <0.011 <0.011 <0.010 <0.007 (0.008 <0.010 <0.008 90/10/16 <0.010 <0.009 <0.009 <0.016 <0.007 <0.011 (0.010 <0.007 <0.012 90/10/23 <0.014 <0.007 <0.007 <0.012 <0.010 <0.013 <0.013 <0.008 <0.011 90/10/30 <0.009 <0.007 <0.008 <0.012 <0.011 <0.007 <0.007 <0.013 (0.008 90/11/06 <0.023 <0.007 <0.007 <0.010 <0.008 <0.011 (0.010 <0.009 <0.010 90/11/13 <0.009 <0.011 <0.010 <0.012 <0.009 <0.010 <0.009 <0.010 <0.011 90/11/20 (0.008 <0.008 <0.010 <0.014 <0.009 <0.009 <0.009 <0.012 (0.012 90/11/27 (0.012 <0.011 <0.008 <0.008 <0.012 <0.010 <0.008 <0.010 <0.009 90/12/04 <0.010 <0.011 <0.008 <0.009 <0.010 <0.011 <0.010 <0.012 <0.010 90/12/11 <0.012 (0.008 <0.009 <0.011 <0.005 <0.014 (0.008 <0.012 . <0.006 90/12/18 <0.012 (0.008 <0.009 <0.011 <0.013 <0.011 <0.011 <0.013 90/12/25 <0.009 <0.007 <0.011 <0.012 <0.007 (0.011 (0.011 <0.011 <0.015 91/01/01 <0.008 <0.009 <0.012 <0.010 <0.008 <0.007 <0.013 <0.010 <0.013

• Sampl cations required by Technical Specific

• • Pump erative

-101

TAB 4 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE STATIONS I-131 ACTIVITY pCi/m"3 ~ 2 SIGMA LOCATION 90/01/08 <0.010 <0.018 <0. 012 <0.011 <0.015 <0.012 90/01/15 <0.010 <0.009 <0.007 <0.011 <0.015 <0.008 90/01/22 <0.009 <0.009 <0.006 <0.006 <0.011 <0.005 90/01/29 <0.011 <0.007 <0.006 (0.008 <0.007 <0.008 90/02/05 <0.008 <0.007 <0.008 (0.008 <0.013 <0.009 90/02/12 <0.006 <0.007 <0.009 <0.008 <0.008 <0.009 90/02/20 <0.007 <0.010 <0.007 <0.008 <0.005 <0.008 90/02/26 <0.013 <0.009 <0.008 <0.011 <0.016 <0.011 90/03/05 (0.010 <0.008 <0.008 <0.013 <0.013 <0.012 90/03/12 <0.014 <0.012 <0.011 <0.015 <0.008 <0.010 90/03/19 <0.011 <0.010 <0.019 <0.011 <0.014 <0.014 90/03/26 <0.007 <0.010 <0.011 <0.010 <0.013 <0.007 90/04/02 <0.009 <0.009 <0.007 <0.011 <0.015 <0.011 90/04/09 <0.014 <0.011 <0.012 <0.010 <0.013 (0.012 90/04/16 <0.020 <0.007 <0.010. <0.015 <0.009 <0.013 90/04/23 <0.013 <0.068 <0.012 <0.009 <0.010 (0.011 90/04/30 (0.021 <0.012 <0.014 <0;014 <0.015 <0.012 90/05/07 <0.012 <0.011 <0.012 <0.010 <0.012 (0.012 90/05/14 <0.023 <0.011 <0.011 <0.012 <0.013 <0.014 90/05/21 <0.013 <0.010- <0.015 <0.012 <0.008 <0.011 90/05/29 (0.014 <0.011 <0.015 <0.010 <0.014 <0.010 90/06/04 <0.013 <0.009 <0.017 <0.011 <0.011 <0.011 90/06/11 <0.014 <0.010 <0.013 <0.010 <0.014 <0.012 90/06/18 <0.019 <0.011 <0.016 <0.011 <0.016 <0.009 90/06/25 <0.009 <0.011 <0.019 <0.009 <0.015 <0.012

-102

TABLE 14 (CONTINUED)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE STATIONS I-131 ACTIVITY pCi/m"3 a 2 SIGMA LOCATION 90/07/02 <0.013 <0.011 <0.012 (0.008 <0.010 <0.011 90/07/09 <0.009 <0.013 <0.013 <0.015 <0.013 <0.014.

90/07/16 <0.011 <0.010 <0.011 <0.011 <0.014 <0.012 90/07/23 <0.007 <0.008 <0.009 <0.013 <0.010 <0.014 90/07/30 <0.008 <0.010 <0.010 (0.008 <0.012 <0.013 90/08/06 <0.012 <0.008 (0.008 <0.009 <0.012 (0.012 90/08/13 <0.015 <0.009 (0.011 <0.009 <0.012 (0.015 90/08/20 <0.008 <0.008 <0.015 <0.012 <0.013 <0.011 90/08/27 <0.014 <0.011 <0.014 <0.011 <0.020 <0.008 90/09/04 <0.008 <0.012 <0.013 <0.009 <0.010 <0.014 90/09/10 <0.012 <0.012 <0.011'0.012

<0.012 <0.013 <0.016 90/09/17 <0.008 <0.009 <0.010 <0.009 <0.011 90/09/24 <0.060 <0.013 <0.010 <0.014 <0.011 <0.012 90/10/01 <0.009 <0.014 <0.010 <0.015 <0.008 . <0.010 90/10/08 <0.020 <0.010 <0.010 <0.011 <0.010 <0.010 90/10/15 <0.013 <0.009 <0.010 <0.009 <0.010 <0.011 90/10/22 <0.009 <0.010 <0.010 <0.006 <0.011 <0.008 90/10/29 <0.007 <0.009 <0.009 (0.012 <0.008 <0.009 90/11/05 <0.009 <0.007 <0.011 <0.009 <0.011 <0.007 90/11/13 <0.010 (0.008 <0.009 <0.007 <0.010 <0.006 90/11/19 <0.009 <0.011 <0.011 <0.008 (0.013 (0.012 90/11/26 (0.012 <0.009 <0.009 <0.007 <0.010 <0.011 90/12/03 <0.014 <0.009 <0.011 <0.012 (0.012 <0.010 90/12/10 <0.011 <0.009 <0.010 <0.008 <0.012 <0.008 90/12/17 <0.013 <0.008 <0.011 <0.016 (0.008 <0.007 90/12/25 <0.007 <0.014 <0.012 <0.009 <0.012 <0.012 91/01/01 <0.010 <0.010 <0.009 <0.013 <0.014 <0.009

TABLE 15 CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units af pCi/liter + 2 sigma LOCATION CLIDES 4-2-90 4-16-90 5-7-90 5-21-90 6-4-90 6-18-90 60 -40 1850+147 1500+66 1650+198 1550+144 1560+19 1 1640+169 Cs-134 <4.8 <5.1 <9.3 <4.5 <6.9 <6.1 Cs-137 <5.4 <4.8 <8.9 <4.5 <8.8 <7.4 Ba/La-140 <4.4 <7.5 <6.3 <5.2 <6.3 <6.1 a-226 <142 <112 164+90 <128 <188 <189 thers <LLD <LLD <LLD <LLD <LLD <LLD 55 -40 1580+66 1490+64 1550+163 1600+169 1610+170 1370+134 Cs-134 <5.9 <5.4 <6.4 <6.5 <7.4 <5.3 Cs-137 <5.4 <5.4 <7 ' <6.9 <7.6 <5.8 Ba/La-140 8.9 <7.8 <6.9 <4.0 <5.9 <4.0 a-226 92+44 <112 <197 <194 <191 <140 thers <LLD <LLD <LLD <LLD <LLD <LLD 50 -40 1640+198 1730+198 1490+189 1550+143 1520+136 1800+209 Cs-134 <6 ' <7.5 <9.2 <5.2 <4.8 <7 '

Cs-137 <8.4 <7.5 <9.3 <5.4 <5.5 <9.0 Ba/La-140 <7.6 <5.4 <9.4 <5.7 <6.0 <8.9 a-226 <226 <205 <218 130+72 <149 <218 thers <LLD <LLD <LLD <LLD <LLD <LLD

-40 1570+67 1660+146 1470+140 1510+162 1850+206 1560+134 Cs-134 <6.0 <4.7 <4.8 <6.9 <8.7 <5.4 Cs-137 <6.0 <5.3 <6.0 <6.8 <8.6 <6.0 Ba/La-140 <6.9 <4 ' <F 1 <6.6 <7.1 5.3 a-226 50+28 <146 <162+92 <181 <191 <153 thers <LLD <LLD <LLD <LLD <LLD <LLD

-104

TABLE 15 (Continued)

CONCENTRATION OP GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma LOCATION CLIDES 4-2-90 4-16-90 5-7-90 5-21-90 6-4-90 6-18-90

-40 1530+170 1510+144 1700+139 1320+176 1420+135 1540+189 Cs-134 <6.6 4 ~ 9. <5.3 <7.5 <4.7 <8.2 Cs-137 <7 ' <5.7 <5.4 <10.0 <4.8 <9.5 Ba/La-140 <4.6 <3.6 <3 ' <8.2 <4.8 <9.4 a-226 <193 <152 143+80 155+123 <133 <210 thers <LLD <LLD <LLD <LLD <LLD <LLD 16 -40 1460+65 1630+135 1560+144 1650+201 1670+171 1530+139 Cs-134 <6 ' <F 1 <5.2 <6.5 <6.2 <4.5 Cs-137 <5.8 <5.6 <5.4 <9.2 <6.5 <6.3 Ba/La-140 <7.4 4.6 <4.0 <8.4 <7.0 <4 '

a-226 104+38 <138 <127 <214 150+75 <144 thers <LLD LLD <LLD <LLD <LLD <LLD 65* -40 1530+66 1770+175 1560+165 1610+137 1590+172 1610+137 (Control) Cs-134 <6.3 7.0 <7.9 <4.6 <6.6 <4.4 Cs-137 <5.9 <7+1 <7 ' <5.4 <5.9 . <5 '

Ba/La-140 <8.7 <4 ' <6.2 <4.3 <6.5 <5.7 a-226 <115 <196 <190 93+58 <192 <157 thers <LLD <LLD <LLD <LLD <LLD <LLD

• Technical Specification location.

-105

TABLE 15 (ContinueC)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma LOCATION CLIDES 7-9-90 7-23-90 8-6-90 8-20-90 9-4-90 9-17-90 60 -40 1590+134 1860+146 1470+189 1620+202 1700+199 1750+140 Cs-134 <5.0 <5.4 <8.4 <8.5 <8.8 <4 ~ 7 Cs-137 6.3 <6.4 <9.4 <8.2 <10.0 <5.9 Ba/La-140 <4.9 <5.6 <8.8 <7.1 <9.4 <5.3 a-226 <151 <152 <216 <196 <229 <158 thers <LLD <LLD <LLD <LLD <LLD <LLD 55 -40 1560+192 1490+66 1650+197 1590+166 1570+144 1600+146 Cs-134 <8.6 <5.4 <8.8 <6.6 <5.1 <4.9 Cs-137 <10.2 <6.5 <9.0 <6.1 <4.7 <4.5 Ba/La-140 <7.1 <9.0 <7.0 <5 ' <5.1 <3.6 a-226 <217 125+55 <226 <148+99 <140 <132 thers <LLD <LLD <LLD <LLD <LLD <LLD 50 -40 1460+138 1560+165 1500+186 1690+139 1770+202 1530+143 Cs-134 <4.5 <6.6 <7 ' <4.8 <8 ' <4.7 Cs-137 <4.9 <7.9 <9.3 <6.0 <8.4 <5 '

Ba/La-140 <3.6 <6.5 <8.7 <3.4 <8 ' <6.3 a-226 <133 137+74 <210 137+83 <217 <142 thers <LLD <LLD <LLD <LLD <LLD <LLD

-40 1530+163 1520+140 1640+169 1460+64 1650+140 1530+193 Cs-134 <6.7 <4.9 <6.6 <5.4 <5.2 <6 ~ 1 Cs-137 <8.5 <5.2 <8.4 <5.9 <5.6 <8.2 Ba/La-140 <6.5 <4.1 <7.6 <6.3 <4.6 <4.4 a-226 1 17+7 1 <129 <202 <115 <154 <193 thers <LLD <LLD <LLD <LLD <LLD <LLD

-106

TABLE 15 (ContinueC)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma LOCATION CLIDES 7-9-90 7-23-90 8-6-90 8-20-90 9-4-90 9-17-90

-40 1440+64 1620+195 1520+66 1470+186 1380+63 1570+143 Cs-134 <5 ' <7 2 <5.8 <7 ' <5.6 <4.7 Cs-137 6.7 <8 2 <6 ' <8.6 6.4 <4.9 Ba/La-140 <7.4 <10 ' <9.3 <5.4 <8 ' <4.8 a-226 112 124+80 123+47 195+138 <136+44 <139 thers <LLD <LLD <LLD <LLD <LLD <LLD 16 -40 1740+140 1670+201 1740+145 1660+140 1750+142 1820+146 Cs-134 <5.4 <8.5 5.5 <5.7 <5.1 <5.5 s-137 <6.7 <9.0 <5.4 <6.3 <5.8 <6.5 Ba/La-140 5' <7 7 <5.1 <5.1 <5.1 <4 '

a-226 <155 <208 <156 <155 102+74 <158 thers <LLD <LLD <LLD <LLD <LLD <LLD 65* -40 1620+169 1470+160 1710+170 1430+64 1550+142 1500+66 (Control) Cs-134 6.8 <6.5 <7. 1 <5.7 <4.7 <6.3 Cs-137 <6 ' <F 1 <7 ~ 1 <5.5 <5.7 . <6.8 Ba/La-140 <5 ' <F 6 <5.8 <8.2 <4-1 <6.5 a-226 <188 <192 <195 <110 <137 167+43 thers <LLD <LLD <LLD <LLD <LLD <LLD

• Technical Specification location.

-107

TABLE 15 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma LOCATION CLIDES 10-1-90 10-15-90 11-5-90 11-19-90. 12-3-90 12-17-90 60 -40 1610+68 1770+153 1580+166 1650+193 1640+165 1510+184 Cs-134 <6.4 <4.9 <5.8 <7.7 <6.9 <7.6 Cs-137 <6.2 <5 ' <8.0 <8.5 <7+7 <9.4 Ba/La-140 <9 ' <2.6 <5.6 <10.0 <6.5 <9.4 a-226 73+43 <128 <189 <206 <186 <223 thers <LLD <LLD <LLD <LLD <LLD 'LLD 55 -40 1400+65 1630+138 1660+140 1850+176 1480+65 1690+140 Cs-134 <6.2 4.5 <5.3 <6.7 <5.9 <5.4 Cs-137 <6.3 <4.9 <6.3 <8.1 <6.1 <6.4 Ba/La-140 <6.3 <3 ' <4 ' <6 ' <4.3 <6.0 a-226 <119 <148 <154 <189 113+44 130+72 thers <LLD LLD <LLD <LLD <LLD <LLD 50 -40 1510+143 1480+139 1600+135 1540+164 1420+182 1630+146 Cs-134 <4.9 <4.7 <F 1 <7.0 <8.5 <5.6 Cs-137 <5.4 <5.8 <6.3 <6.1 <8.6 <5.9 Ba/La-140 <5.1 <5.8 <4.8 <5.4 <9.3 <5.1 a-226 <133 137 <158 <188 <209 <135 thers <LLD <LLD <LLD <LLD <LLD- <LLD

-40 1480+139 1490+161 1720+173 1420+136 . 1510+192 1460+159 Cs-134 <4.4 6.6 <6.8 <4 ~ 8 <8.2 <6.3 Cs-137 <5.6 <6.5 <8.7 <5.9 <10.1 <7.1 Ba/La-140 <4 ' <8.4 <6.6 <5.5 <5.4 <8.0 a-226 <133 165+76 204+91 <128 <211 199+128 thers <LLD <LLD <LLD <LLD <LLD <LLD

-108

TABLE 15 (Continued)

CONCENTRATION OP GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma LOCATION CLIDES 10-1-90 10-15-90 11-5-90 11-19-90 12-3-90 12-17-90

-40 1450+188 1620+192 1470+141 1780+142 1680+140 1550+136 Cs-134 <7.9 <8.1 <5.0 <4.8 <5.6 <F 1 Cs-137 <9 2 <9.5 <5.4 <5.5 <5.7 <6.6 Ba/La-140 <8.3 <10.4 <5.3 4.3 <5.3 <4.8 a-226 <226 -

<221 <137 <154

• 161+71 <151 thers <LLD <LLD <LLD <LLD LLD <LLD 16 -40 1700+138 1610+148 1680+198 1770+201 1710+140 1490+66 Cs-134 <5.0 <4 ' <6.8 <7.2 <4.7 <5.7 Cs-137 <5 ' <4.5 <10 ' <9.0 <6.6 <6.5 Ba/La-140 <3 6 <4.7 <6.3 <8.3 <5.9 <7 '

a-226 <153 <138 <228 <202 160 120 thers <LLD <LLD <LLD <LLD <LLD <LLD 65* -40 14 10+65 1630+137 1490+66 1690+139 1530+66 1570+67 (Control) Cs-134 <6.2 4.8 <5.7 <6.0 <5.2 <5.5 Cs-137 <6.3 5.8 <6.4 <6.5 <6 ' . <6.4 Ba/La-140 <9.4 <4.6 <9.8 <5.4 <5.7 7 '

a-226 <123 156+70 <109 <156 115+42 116 thers <LLD <LLD <LLD <LLD <LLD . <LLD

• Technical Specification location.

-109

TABLE 16 CONCENTRATION OP IODINE - 131 IN MILK (1)

Results in units of pCi/liter + 2 sigma LOCATION 4-2-90 4-16-90 5-7-90 5-21-90 6-4-90 6-18-90 60 <0.40 <0.16 <0.19 <0. 18 <0 49 <0.20 55 50

<0.39

<0.46

<0.38

<0.35

<0.37

<0.12

<0 10

<0.16

<0 '0

<0.30

<0 '4

<0.21 7

4

<0 32

<0.19

<0.41

<0 19

<0.20

<0.19 0 '4

<0.17

<0.25

<0 12

<0.21

<0 13 16 <0.37 <0.14 <0. 12 <0.17 <0.48 65* <0 '1 <0.13 <0. 14 <0.13 <0.29

<0.25

<0.23 LOCATION 7-9-90 7-23-90 8-6-90 8-20-90 9-4-90 9-17-90 60 <0.27 <0.44 <0.28 <0.19 <0.16 <0.10 55 50

<0.19

<0.34

<0.27

<0 '1 <0.24

<0.18

<0.12

<0.11

<0 '1

<0.20

<0.35

<0 '6 7 <0.18 <0 17 <0.14 <0.22 <0.20 <0.31 4 <0.24 <0.36 <0.26 <0.25 <0.16 <0.16 16 65*

<0.30

<0.37

<0.18

<0.13

<0.15

<0 '8 <0 '2

<0.13

<0.36

<0.29

<0.22

<0.16 LOCATION 10-1-90 10-15-90 11-5-90 11-19-90 12-3-90 12-17-90 60 <0.50 <0.16 <0.11 <0.20 <0.16 <0. 18 55 <0.19 <0.19 <0.15 <0.25 <0.19 50 7

<0

<0

'1

'1 <0

<0

'9

'0 <0.20

<0.13

<0.21 <0.14

<0.22

<0.14

<0 18 <0.15 <0.34 4 <0.14 <0.14 <0-13 <0-45 <0.18 <0.21 16 <0.44 <0 '8 <0.12 <0.20 <0.17 <0.13 65* <0 '9 <0 '9 <0.12 <0.15 <0.22 <0.13

• Control Result. Technical Specification location.

(1) Iodine 131 results are corrected for decay to the sample stop date.

TABLE 17A CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS

- Results in units of pCi/g (wet) + 2 sigma LOCATIO DATE SAMPLE TYPE Be-7 -40 I-131 Cs-134 Cs-137 a-226 cTh-228 OTHER 9-10-90 Bean Leaves 0.58+0.08 3.49+0.26 <0. 012 <0.010 <0.012 0.20+0.10 <0.046 <LLD 9-10-90 Squash Leaves 0.44+0.04 3.29+0.12 <0.011 <0.014 <0.013 0.23+0 09 <0.043

~ <LLD 9-10-90 Cabbage 0.11+0 08 3.82+0.27 <0.013 <0.011 <0.013 0.29+0.12 <0.049 <LLD K 9-10-90 9-10-90 Corn Leaves Squash Leaves 0 '7+0.15 4 '1+0 '3 <0 022 <0.020 0.67+0.07 2.85+0.22 <0.010 <0.008

<0 '21

<0.010 0.68+0.35 <0.096 0.22+0.11 <0.037

<LLD

<LLD K

K 9-10-90 Bean Leaves 0.39+0.11 3.37+0.34 <0.019 <0.017 <0.019 0.34+0.16 <0.077 <LLD P 9-10-90 Squash Leaves 0.89+0.76 2.82+0.20 <0.009 <0.008 <0.008 0.23+0.09 <0.032 <LLD P 9-10-90 Bean Leaves 0.73+0.08 2.19+0.21 <0.014 <0.010 <0.010 <0.24 <0.047 <LLD P 9-10-90 Swiss Chard 0.27+0.04 6.10+0.17 <0.013 <0.014 <0.014 0.22+0.09 <0.057 <LLD 9-10-90 9-10-90 Cabbage Bean Leaves 0.18+0 '6 3.74+0.27 <0.012 <0,.011 0.47+0.06 4.05+0.24 <0.010 <0.008

<0.013

<0.010 0.34+0.17 <0.051 0.23+0.10 <0.038

<LLD

<LLD 9-10-90 Cucumber Leaves 1.04+0.14 5.08+0.44 <0.022 <0.018 <0.022 0.30+0.19 <0.088 <LLD Z 9-10-90 Squash Leaves 0.36+0.07 3.61+0.28 <0.017 <0 '12 <0.012 0.30+0.16 <0.050 <LLD Z 9-10-90 rape Leaves 0.65+0.09 4.03+0.28 <0.016 <0.011 <0.012 0.26+0.12 <0.048 <LLD Z 9-10-90 Bean Leaves 0.56+0.10 3.14+0.31 <0.019 <0.014 <0.014 0 34+0.17 0.030+0.024 <LLD 9-10-90 Swiss Chard 0 '9+0.06 5.66+0.34 <0.016 <0.012 <0 014 0.19+0.10 0.072+0.058 <LLD 9-10-90 Squash Leaves 0.47+0.09 5.65+0.37 <0.025 <0 '15 <0.015 0.44+0.15 <0.065 <LLD 9-10-90 Cabbage 0.08+0.03 2.58+0.11 <0.014 <0.012 <0.012 0.19+0;08 <0.044 <LLD 9-10-90 9-10-90 Grape Leaves Bean Leaves 1.46+0.16 4 '6+0 '5 <0.025 <0.022 0.49+0.05 5.53+0.16 <0.015 <0.015

<0.023

<0 '14 0.54+0.20 <0.091 0.30+0.09 <0.055

<LLD

<LLD

• Control result All results in units cf activity ~er ram wet weight

TABL CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) + 2 sigma LOCATIO DATE SAMPLE TYPE Be-7 -40 I-131 Cs-134 Cs-137 a-226 cTh-228 OTHER 9-10-90 Bean Leaves 580+100 3490+258 <12 <10 <12 199+100 <46 <LLD 9-10-90 Squash Leaves 435+40 3290+119 <11 <14 <13 234+88 <43 <LLD 9-10-90 Cabbage 114+80 3820+269 <13 <ll <13 294+125 <49 <LLD 9-10-90 Corn Leaves 869+147 4310+427 <22 <20 <21 680+352 <96 <LLD 9-10-90 Squash Leaves 671+74 2850+219 <10 <8 <10 215+106 <37 <LLD K 9-10-90 Bean Leaves 393+106 3370+340 <19 <17 <19 337+165 <77 <LLD P 9-10-90 Squash Leaves 891+76 2820+199 <9 <8 <8 231+92 <32 <LLD P 9-10-90 Bean Leaves 731+84 2190+214 <14 <10 <10 <238 <47 <LLD P 9-10-90 Swiss Chard 274+38 6100+169 <13 <14 <14 224+87 <57 <LLD 9-10-90 Cabbage 177+64 3740+267 <12 <11 <13 340+170 <51 <LLD 9-10-90 Bean Leaves 468+60 4050+239 <10 <8 <10 228+104 <38 <LLD 9-10-90 Cucumber Leaves 1040+138 5080+440 <22 <18 <22 302+187 <88 <LLD Z 9-10-90 Squash Leaves 365+73 3160+281 <17 <12 <12 301+165 <50 <LLD Z 9-10-90 Grape Leaves 647+90 4030+284 <16 <11 <12 258+117 <48 <LLD Z 9-10-90 Bean Leaves 557+101 3140+308 <19 <14 <14 336+169 30+24 <LLD 9-10-90 Swiss Chard 87+55 5660+345 <16 <12 <14 194+98 72+58 <LLD 9-10-90 Squash Leaves 467+93 5650+374 <25 <15 <15 439+150 <65 <LLD 9-10-90 Cabbage 78+27 2580+109 <14 <12 <12 188+78 <44 <LLD 9-10-90 Grape Leaves 1460+165 4760+451 <25 <22 <23 544+201 <91 <LLD 9-10-90 Bean Leaves 494+47 5530+165 <15 <15 <14 296+89 <55 <LLD

• Control result All results in units of activity er kilo ram wet weight

-112

TABLE 18 MILK ANIMAL CENSUS 1990 OWN OR AREA(a) O. ON CENSUS MAP(1) DEGREES (3) (3 ) O. OF MILK ANIMALS Scriba 16* 5. 9. 40C 2 190'95'90'62 8.0 one 3 4.5 4C 6 2'. 2 1C 26 1.5 D 61

'14'40'83

3. 0- 9G (2) 62 6.7 6G (2) 63 8 ' 40C ew Haven 9 5.2 42C 4* 7.8 95C 45 8' D 10 2.6 30C 5 7.2 45C 11 8.5 one 7* 5.5 62C 64 7.9

'85'5'13'25'30'46'30'07'07'07'20'15'32'0'3'5'12'08'8'5'2'5'ISTANCE 50C exico 12 11.5 24C 14 9.8 65C 17 10.2 2C 19 10 ' 40C 60* ,9 ~ 5 30C 50* 8.2 160C, 1G (2) 55* 9~2 55C 21 10. 5 50C, 3G (2) 68 11.6 64C, 1G (2) 49 7.9 10G, (2) ichland 22 10.2 52C Pulaski 23 10 5 one 69 11.6 52C Sterling 65** 43C olney 25 220'82'47'56'52'7.0 9.5 one 70 9.4 23C 66 7.8 60C 67 8.3 one MILKING ANIMAL TOTALS: 1,129 Cows (including control locations) 30 Goats MILKING ANIMAL TOTALS 1,086 Cows (b)

(excluding control locations) 30 Goats (b)

-113

TABLE 18 (Continued)

MILK ANIMAL CENSUS 1990 NOTES C = Cows G = Goats

• = Milk sample location

• • = Milk sample control location ND = Did not wish to participate in the survey (1) = References Figure 4 (2) = Goat is not currently producing milk or any milk produced is utilized by the owner (3) = Degrees and distance are based on NMP-2 Reactor Building centerline one = No cows or goats at that location. Location was a previous location with cows and/or goats.

(a) = Census performed out to a distance of approximately ten miles.

(b) = Totals excluding control location results.

-114

TABLE 19 1990 RESIDENCE CENSUS P (1) TEOROLOGICAL LOCATION LOCATION ECTOR DEGREES (2 ) DISTANCE (2)

E E

NE Lake Road miles Lake Road B SE 99'02'30; 1.1 miles County Route 29 C E 1.4 miles incr Road D SE 1.6 miles incr Road 1.6 163'70'07'34'38'.3 miles Lakeview Road SW 1 2 miles Bible Camp Retreat W 0.9 miles Bible Camp Retreat SW 0.9 miles

• This meteorological sector is over Lake Ontario.

within five miles.

(1) 'Corresponds to Figure 3.

(2) Based on NMP-2 reactor centerline.

-115

TAB 0 INTERLABORATORY COMPARISON PROGRAM RESULTS ITE REFERENCE ALYSIS DATE EDIUM O. PA RESULT (1) ITE RESULT (2)

Beta 3/90 ir Filter A 90-024 31+5 33+3 (3)

(pCi/filter) 32+3 31+3 Beta 8/90 ir Filter A 90-097 62+5 63+2 (3)

(pCi/filter) 64+2 63+2 ritium 2/90 ater A 90-016 4976+498 5100+100 (4)

(pCi/liter) 5000+100 4800+100 ritium 6/90 ater A 90-070 2933+358 3000+200 (4)

(pCi/liter) 3100+200 2800+100 ritium 10/90 ater A 90-126 7203+720 7100+300 (4)

(pCi/liter) 7000+300 7400+300 Beta 4/90 ater A 90-034 52+5 50+2 (3)

(pCi/liter) 49+2 50+2 Beta 10/90 ater (pCi/liter)

A 90-127 53+5

'8+1 49+1 49+1 (3)

I-131 4/90 ilk A 90-035 99+10 96+10 (4)

(pCi/liter) 97+12 95+14

-116

TABLE 20 (Cantinued)

INTERLABORATORY COMPARISON PROGRAM RESULTS ITE REFERENCE ALYSIS DATE DIUM O. PA RESULT (1) ITE RESULT (2)

I-131 2/90 ater A 90-018 (5) (5)

(pCi/liter)

I-131 8/90 ater A 90-096 39+6 41+1 (3)

(pCi/liter) 41+2 41+2 amma 3/90 ir Filter A 90-024 10+5 12+4 (3)

(Cs-137) (pCi/liter) 12+4 12+5 amma 8/90 ir Filter A 90-097 20+5 23+5 (3)

(Cs-137) (pCi/liter) 23+5 24+6 amma 4/90 ilk A 90-035 24+5 25+3 (3)

(Cs-137) (pCi/liter) 24+6 25+5 Beta 1/90 ater A 90-016 12+5 12+1 (3) 10+1 10+1 Beta 5/90 ater A 90-056 15+5 13+1 (3) 13+1 12+ 1 Beta 9/90 ater A 90-111 10+5 11+1 (3) 11+1 12+1

TABLE 20 tinued)

XNTERLABORATORY COMPARISON PROGRAM RESULTS SITE REFERENCE ALYSIS DATE EDIUM O. PA RESULT (1) ITE RESULT (2) amma 2/90 ater A 90-017 74+7 75+3 (3)

(Ba-133) (pCi/liter) 74+3 78+6 amma 2/90 ater A 90-017 139+14 145+6 (3)

(Zn-65) (pCi/liter) 147+12 146+15 amma 2/90 ater A 90-017 139+14 131+16 (3)

(Ru-106) (pCi/liter) 130+13 144+30 amma 2/90 ater A 90-017 18+5 15+1 (3)

(Cs-134) (pCi/liter) 21+4 14+3 amma 2/90 ater A 90-017 18+5 23+2 (3)

(Cs-137) (pCi/liter) 24+3 25+3 amma 2/90 ater A 90-017 15+5 15+1 (3)

(Co-60) (pCi/liter) 15+4 15+3 I-13 1 9/90 ilk A 90-113 58+6 65+2 (4)

(pCi/liter) 64+3 62+4 amma 9/90 ilk A 90-113 20+5 20+3 (3)

(Cs-137) (pCi/liter) 2 1+5 18+6

-118

TABLE 20 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS ITE REFERENCE ALYSIS DATE DIUM O. PA RESULT (1) ITE RESULT (2) amma 6/90 ater A 90-065 24+5 27+2 (3)

(Co-60) (pCi/liter) 25+6 27+6 amma 6/90 ater A 90-065 148+15 158+6 (3)

(Zn-65) (pCi/liter) 152+15 164+15 amma 6/90 ater A 90-065 210+21 191+21 (3)

(RQ-106) (pCi/liter) 166+29 177+34 amma 6/90 ater A 90-065 24+5 20+2 (3)

(Cs-134) (pCi/liter) 23+3 27+5 amma 6/90 ater A 90-065 25+5 24+2 (3)

(Cs-137) (pCi/liter) 25+4 25+4 amma 6/90 ater A 90-065 99+10 105+3 (3)

(Ba-133) (pCi/liter) 99+7 102+7

TABLE 20 tinued)

INTERLABORATORY COMPARISON PROGRAM RESULTS ITE REFERENCE ALYSIS DATE DIUM O. PA RESULT (1) ITE RESULT (2) amma 10/90 ater A 90-114 20+5 22+3 (3)

(Co-60) (pCi/liter) 19+3 22+3 amma 10/90 ater A 90-114 115+12 117+12 (3)

(Zn-65) (pCi/liter) 118+12 114+12 amma 10/90 ater A 90-114 151+15 130+25 (3)

(Ru-106) (pCi/liter) 13 1+25 123+25 amma 10/90 ater A 90-114 12+5 10+3 (3)

(Cs-134) (pCi/liter) 11+3 12+3 amma 10/90 ater A 90-114 12+5 12+3 (3)

(Cs-137) (pCi/liter) 12+3 12+3 amma 10/90 ater A 90-114 110+11 108+6 (3)

(Ba-133) (pCi/liter) 105+6 105+6

-120

TABLE 20 (Cantinued)

INTERLABORATORY COMPARISON PROGRAM RESULTS ITE REFERENCE ALYSIS DATE DIUM O. PA RESULT (1) ITE RESULT (2) amma 4/90 ater A 90-034 15+5 14+4 (3)

(Cs-134) (pCi/liter) 15+3 12+4 amma 4/90 ater A 90-034 15+5 16+3 (3)

(Cs-137) (pCi/liter) 16+4 14+4 amma 10/90 ater A 90-127 7+5 7+3 (3)

(Cs-134) (pCi/liter) 8+2 9+3 amma 10/90 ater A 90-127 5+5 7+2 (3)

(Cs-137) (pCi/liter) 6+3 6+3

TABLE 20 tinued)

INTERLABORATORY COMPARISON PROGRAM RESULTS NOTES:

(1) Results reported as activity + the standard deviation of the error.

(2) Results reported as activity + the error (2 sigma).

(3) Analyzed at the site environmental laboratory.

(4) Analyzed at a vendor laboratory.

(5) No results. No sample sent by EPA;

-122

TABLE 21 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 LOCATION: CONTROL ~ii YEAR IN. IN. IN. EAN 1979 (2) LLD LLD LLD LLD 0 '2

0. 07 0.22 0.09 0 ~

0.08 22 LLD LLD LLD LLD LLD LLD 1980 LLD LLD 1981 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1982 LLD LLD LLD 0.05 0.05 0.05 LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD LLD LLD LLD esults in pCi/g (dry)

(1) Control location was at an area beyond the influence of the site (westerly direction).

(2) Sampling was initiated in 1979. Sampling was not required prior to 1979.

TABLE 22 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 LOCATION: INDICATOR (SUNSET BAY)

YEAR IN. IN. X. IN. X.

1979 (2) (2) (2) (2) (2) (2) (2) (2) (2.)

1980 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1981 (2) (2) (2) (2) (2) (2) (2)

'2)

(2) 1982 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1983 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1984 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1989 1990 LLD LLD LLD LLD LLD LLD 0.25 0.28 0

0

'4

'8 0.30 0.28 LLD LLD LLD LLD LLD LLD esults in pCi/g (dry)

(1) Location was off-site at Sunset Beach (closest location with recreational value).

(2) Sampling initiated in 1985 as required by the new Technical Specifications.

-124

TABLE 23 HZSTORZCAL ENVIRONMENTAL SAMPLE DATA PZSH Cs-137 LOCATION. CONTROL (1)

IN.

1976 1~2 1.2 1.2 1977 0. 13 0.13 0.13 1978 0. 04 0.20 0.09 1979 0 03 0.03 0.06 0.11 0 '4

'6 1980 0 1981 0 '28 0.062 0.043 1982 0.027 0.055 0.046 1983 0.041 0.057 0.049 1984 0.015 0.038 0.032 1985 0. 026 0.047 0.034 1986 0. 021 0.032 0 '25 1987 0 '17 0.040 0 '31 1988 0.023 0.053 0.033 1989 0.020 0.033 0.029 1990 0.025 0.079 0 '43 esults in pCi/g (wet)

(1) Control location was at an area beyond the influence of the site (westerly direction).

TABLE 24 HISTORICAL ENVIRONMENTAL SAMPLE DATA PISH Cs-137 LOCATION: INDICATOR (NMP/JAF)

IN.

1976 0.5 3.9 1.4 1977 1978 0.13 0 '3 0 '9 0.10 0.29 0.08 1979 1980 0 '2 0.03 0 '5 0.10 0.10 0.06 1981 1982 0 '3 0.034 0 '0 0.064 0 06

0. 048 1983 0.033 0.056 0.045 1984 0.033 0.061 0.043 1985 0.018 0 '44 0.030 1986 0.009 0 '51 0.028 1987 0.024 0.063 0.033 1988 0 '20 0.074 0.034 1989 0.020 0.043 0.035 1990 0.024 0.115 0.044 esults in pCi/g (wet)

Indicator locations are in the general area of the NMP-1 and Z. A. FitzPatrick cooling water discharge structures.

-126

TABLE 25 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE MATER Cs-137 Co-60 LOCATION: CONTROL YEAR IN. EAN IN.

1976 (1) (1) (1) (1) (1) (1) 1977 (2) (2) (2) (2) (2) (2) 1978 LLD LLD LLD (2) (2) (2) 1979 2.5 2.5 2.5 LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD 1.4 1.4 1.4 1982 LLD LLD LLD LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) No gamma analyses performed (not required).

(2) Data showed instrument background results.

(3) Location was the City of Oswego Water Supply for 1976 1984 and the Oswego Steam Station inlet canal for 1985 1990.

TABLE 26 HZSTORZCAL ENVZRONMENTAL SAMPLE DATA SURFACE WATER Cs-137 Co-60 LOCATION: INDICATOR ~ i YEAR IN. IN. AN 1976 (1) (1) (1) (1) (1) (1) 1977 (2) (2) (2) (2) (2) (2) 1978 LLD LLD LLD (2) (2) (2) 1979 LLD LLD LLD LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD LLD LLD LLD 1982 1983 0.43 LLD 0 '3 LLD 0.43 LLD 1.6 LLD 2.4 LLD 1.9 LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) No gamma analyses performed (not recpxired).

(2) Data showed instrument background results.

(3) Location was the J. A. FitzPatrick inlet canal.

-128

TABLE 27 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE MATER TRITIUM TRITIUM LOCATION'ONTROL (1)

YEAR IN.

1976 440 929 652 1977 300 530 408 1978 215 490 304 1979 174 308 259 1980 211 290 257 1981 211 328 276 1982 112 307 165 1983 230 280 250 1984 190 220 205 1985 230 370 278 1986 250 550 373 1987 140 270 210 1988 240 460 320 1989 180 660 373 1990 260 320 290 esults in pCi/liter (1) Control location is the City of Oswego drinking water for 1976 - 1984 and the Oswego Steam Station inlet canal for 1985 1990.

TABLE 28 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE RATER TRITIUM TRITIUM LOCATION: INDICATOR YEAR IN.

1976 365 889 627 1977 380 530 455 1978 377 560 476 1979 176 276 228 1980 150 306 227 1981 212 388 285 1982 194 '311 266 1983 249 560 347 1984 110 370 280 1985 250 1200 (2) 530 1986 260 500 380 1987 160 410 322 1988 430 480 460 1989 210 350 280 1990 220 290 250 esults in pCi/liter (1) Indicator location is the FitzPatrick inlet canal.

(2) Suspect sample contamination. Recollected samples showed normal levels of tritium.

-130

TABLE 29 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA GROSS BETA LOCATION: CONTROL ~ii IN.

1977 0. 001 0.484 0.125 1978 0. 01 0.66 0 16 1979 0. 010 0.703 0.077 1980 0.009 0.291 0.056 1981 0.016 0.549 0.165 1982 0.011 0.078 0.033 1983 0.007 0.085 0.024 1984 0.013 0.051 0 '26 1985 0.013 0.043 0.024 1986 0.008 0.272 0.039 1987 0.009 0.037 0.021 1988 0.008 0.039 0 '18 1989 0.007 0.039 0 '17 1990 0.003 0.027 0'013 esults in pCi/m~

(1) Locations used for 1977 1984 were C off-site, Dl off-site, D2 off-site, E off-site, F off-site, and G off-site. Control location R-5 off-site was used for 1985 1990 (formerly C off-site location).

TABLE 30 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA GROSS BETA LOCATION: INDICATOR <<ii YEAR IN. EAN 1977 0.002 0.326 0.106 1978 0.01 0.001 0 '4 0.271 0.11 0.058 1979 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 1983 0 '02 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 1986 0 '07 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 0.005 0.023 0; 014 esults in pCi/m~

(1) Locations used for 1977 - 1984 were D1 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site, and K on-site as applicable. 1985 1990 locations were R-1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

-132

TABLE 31 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 LOCATION: CONTROL ~ i IN. X. IN.

Preop. (1) (1) (1) (1) (1) (1) 1970 (1) (1) (1) (1) (1) (1) 1971 (1) (1) (1) (1) (1) (1) 1972 (1) (1) (1) (1) (1) (1) 1973 (1) (1) (1) (1) (1) (1) 1974 (1) (1) (1) (1) (1) (1) 1975 (1) (1) (1) (1) (1) (1) 1976 (1) (1) (1) (1) (1) (1) 1977 0.0002 0.0112 0.0034 0. 0034 0.0347 0.0172 1978 0.0008 0.0042 0.0018 0.0003 0.0056 0.0020 1979 0.0008 0.0047 0.0016 0.0005 0.0014 0.0009 1980 0.0015 0.0018 0.0016 LLD LLD LLD 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 0.0002 0.0009 0.0004 0.0004 0.0007 0.0006 1983 0.0002 0.0002 0.0002 0.0007 0.0007 0.0007 1984 LLD LLD LLD 0.0004 0.0012 0.0008 1985 LLD LLD LLD LLD LLD LLD 1986 0.0075 0.0311 0.0193 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD esults in pCi/m~

(1) No data available (not required prior to 1977).

(2) Locations included composites of off-site air monitoring locations for 1977 1984. Sample location included only R-5 air monitoring location for 1985 1990.

TABLE 32 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 LOCATION: INDICATOR ~ i YEAR IN. X. IN. X.

Preop. (1) (1) (1) (1) (1) (1) 1970 (1) (1) (1) (1) (1) (1) 1971 (1) (1) (1) (1) (1) (1) 1972 (1) (1) (1) (1) (1) (1) 1973 (1) (1) (1) (1) (1) (1) 1974 (1) (1) (1) (1) (1) (1) 1975 (1) (1) (1) (1) (1) (1) 1976 (1) (1) (1) (1) (1) (1) 1977 0.0001 0.0105 0.0043 0.0003 0.0711 0.0179 1978 0.0003 0.0026 0 0016 0.0003 0.0153 0.0023 1979 0.0003 0.0020 0.0010 0.0003 0.0007 0.0005 1980 0.0005 0.0019 0.0011 0.0016 0.0016 0.0016 1981 0 '002 0.0045 0.0014 0.0002 0 '017 0.0006 1982 0.0001 0.0006 0.0004 0.0003 0.0010 0.0005 1983 0.0002 0.0003 0.0002 0.0003 0.0017 0.0007 1984 LLD LLD LLD 0.0007 0.0017 0.0012 1985 LLD LLD LLD LLD LLD LLD 1986 0.0069 0.0364 0.0183 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD esults in pCi/m~

(1) No data available (not required prior to 1977).

(2) Locations included composites of on-site air monitoring locations for 1977 1984. Locations included R-1 through R-4 air monitoring locations for 1985 1990.

-134

TABLE 33 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE IODINE-131

~~~

LOCATION: CONTROL YEAR IN. X.

0.01 5.88 0. 60 1976 1977 0.02 0.82 0 '2 0.03 1978 0.03 0.04 1979 LLD LLD LLD 1980 LLD LLD LLD 1981 LLD LLD LLD 1982 0.039 0.039 0.039 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0.041 0.332 0.151 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD esults in pCi/m~

(1) Locations Dl off-site, D2 off-site, E- off-site, F off-site, and G off-site used for 1976 1984.

Location R-5 off-site used for 1985 1990.

TABLE 34 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE IODINE-131 LOCATION: INDICATOR i ~

YEAR IN. EAN 1976 0 01 2. 09 0.33 1977 0 02 0.73 0.31 1978 0. 02 0.07 0.04 1979 LLD LLD LLD 1980 0.013 0 013 0.013 1981 0.016 0.042 0 '29 1982 0 002 0.042 0.016 1983 0.022 0.035 0 028 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0 023 0.360 0.119 1987 0.011 0.018 0 '14 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD esults in pCi/m~

Locations used for 1976 1984 were D1 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, Z on-site, and K on-site, as applicable. Locations used for 1985 1990 were R1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

-136

TABLE 35 HI8TORICAL ENVIRONMENTAL 8AMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: CONTROL (2)

IN.

Preop (1) (1) (1) 1970 6.0 7 ' 6.7 1971 2.0 6.7 4.3 1972 2 ' 6.2 4 '

1973 2.2 6.9 4.7 1974 2 ' 8.9 5.6 1975 4.8 6'. 0 5.5 1976 3.2 7 ' 5' 1977 4.0 8.0 5' 1978 3.3 4.7 4 '

1979 3 ' 5.7 4 '

1980 3.8 5.8 4.9 1981 3.5 5.9 4.8 1982 3.8 6.1 5;1 1983 4' 7.2 5.8 1984 4.7 8.2 6 '

1985 4~5 (4 ~ 4)* 7.6 (6.8)

• 5.6 (5.4)*

1986 5.3 .(5.5)* 7.5 (7.2)

• 6.3 (6.3)

• 1987 4.6 (4. 6)

• 6.6 (5.8)* 5.4 (5.2)

• 1988 4 4 (4 8) *

~ ~ 6.8 (6.8)

• 5 6 (5.4) *

~

1989 2' (2.9)

• 6.4 (5.6)

• 4.7 (4.6)*

1990 3.7 (3 7) *

~ 6.0 (5.9)

• 4.7 (4.6)

• esults in mrem per standard month (1) Data not available.

(2) TLD 58, 14, 49, 100, and 111 where applicable.

( )* TLD result based on the Technical Specification required locations (TLD gl4 and 49).

TABLE 36A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: SITE BOUNDARY YEAR IN. EAN Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.1 12. 6 6.2 1986 4 ' 18.7 7.0 1987 4 ' 14 ' 6 1 1988 3.4 17 ' 6.4 1989 2.8 15.4 5' 1990 3.6 14.8 5.8 esults in mrem per standard month (1) No data available (not required prior to 1985);

(2) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 75, 76, 77, 23, 78, 79, 80, 81, 82, 83, 84, 7, 18, 85, 86, and 87.

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TABLE 36B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: OFF-SITE SECTORS ( )

IN.

Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.0 7.1 5.0 1986 4.6 8.6 6~0 1987 4.3 6.0 5' 1988 3.8 7-. 0 5.3 1989 2.5 6.8 4.9 1990 3.6 6 ' 4.7 esults in mrem per standard month (1) No data available (not required prior to 1985).

(2) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 88, 89, 90, 91, 92, 93, 94, and 95.

TABLE 36C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: SPECIAL INTEREST YEAR IN. X. EAN Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 3 ' 6.8 5.3 1986 4.8 8.2 6.1 1987 3 ' 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 7.0 4.8 1990 3 ' 6.3 4.7 esults in mrem per standard month (1) No data available (not required prior to 1985).

(2) TLD locations initiated in 1985 as required by the new Technical Specifications. TLD's included are numbers 96, 58, 97, 56, 15, and 98.

(3) TLD locations include critical residences and populated areas near the site.

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TABLE 36D HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: ON-SITE INDICATOR ~ i EAR IN.

Preop (1) (1) (1) 1970 4.7 9.0 6.0 1971 1.5 7 ' 4.7 1972 2.3 8.2 4.9 1973 3.0 24.4 6.6 1974 3.1 10.6 5.7 1975 4.6 16.0 7 '

1976 3 ' 18.8 6.9 1977 3.0 15.3 5.7 1978 3 ' 9.0 4 '

1979 2 7 8.3 4.3 1980 3.9 12 ' 5.3 1981 4.1 11.8 5.8 1982 3.9 13 ' 6.3 1983 5.0 16.5 6.9 1984 4~6 13 ' 7.0 1985 4 ' 15 ' 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 5.8 1988 4.4 11.9 6.0 1989 2.7 14.5 6.0 1990 3' 12.9 5' esults in mrem per standard month (1) No data available.

(2) Includes TLD numbers 3, 4, 5, 6, and 7 (1970 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25, and 26 (1974 1990). Locations are existing or previous on-site environmental air monitoring locations.

TABLE 36E HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: OFF-SITE INDICATOR ~~~

EAR IN.

Preop (1) (1) (1) 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4' 1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.5 7~1 5.5 1976 3.4 7.2 5.2 1977 F 7 8.0 5.3 1978 2.7 4.7 3 '

1979 3.0 5.7 4.0 1980 3 ' 5.8 4.6 1981 3 ' 5.9 4.7 1982 4 ' 6.2 5.2 1983 4.6 7.2 5,6 1984 4 ' 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 . 5.4 1989 2.8 6.4 4.6 1990 3' 6' 4.8 esults in mrem per standard month (1) No data available.

(2) Includes TLD numbers 8, 9, 10, locations).

ll, 12, and 13 (off-site environmental air monitoring

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TABLE 37 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 LOCATION: CONTROL ~ i EAR IN. IN. EAN 1976 (1) (1) (1) (1) (1) (1) 1977 (1) (1) (1) (1) (1) (1) 1978 2.4 7.8 5.8 LLD LLD LLD 1979 LLD LLD LLD LLD LLD LLD 1980 3.6 5.6 4.5 1.4 1.4 1.4 1981 3' 3.9 3.9 LLD LLD LLD 1982 LLD LLD LLD LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 5.3 12.4 8.4 0.8 29 0 13.6 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) No data available (samples not recpxired).

(2) Location used was an available milk sample location in a least prevalent wind direction greater than ten miles from the site.

TABLE 38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 LOCATION INDICATOR IN. IN.

1976 1977 4.0 11.0 15.0 22.0 9.3

17. 1 0 '2 0.01 45.00 49.00 3.20 6.88 1978 1979 3

3 33.0 53.0 9.9 9.4 0.19 LLD 0.19 LLD 0 '9 LLD 1980 3 ' 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1983 3 ' 10.9 7.2 LLD. LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 8.1 6.8 LLD LLD LLD 1988 10.0 10.0 10 0 LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) Locations sampled were available downwind locations within ten miles with high deposition potential.

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TABLE 39 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 LOCATION: CONTROL << i EAR IN 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (3) 0.02 0.02 0.02 1981 LLD LLD LLD 1982 LLD LLD LD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (4) LLD LLD LLD 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD esults in pCi/g (wet)

(1) No data available (control samples not required).

(2) Location was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.

(3) Data comprised of broadleaf and non-broadleaf vegetation (1980 1984).

(4) Data comprised of broadleaf vegetation only (1985 1990).

TABLE 40 HISTORICAL ENVIRONMENTAL SAMPLE DATA POOD PRODUCTS Cs-137 LOCATION: INDICATOR ~~i EAR IN.

1976 (2) LLD LLD LLD 1977 LLD LLD LLD 1978 LLD LLD LLD 1979 0.004 0.004 0.004 1980 0.004 0.060 0.036 1981 LLD LLD LD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (3) 0.047 0.047 0. 047 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 0.008 0.008 0.008 1989 0.009 0.009 0.009 1990 LLD LLD D esults in pCi/g (wet)

Indicator locations were available downwind locations within ten miles of the site and with high deposition potential.

(2) Data comprised of broadleaf and non-broadleaf vegetation (1976 1984).

(3) Data comprised of broadleaf vegetation only (1985 1990).

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PXGURBS

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-150

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-153