ML18038A297

Annual Radiological Environ Operating Rept 1989. W/900427 Ltr

ML18038A297
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1989
From:	Joseph Willis NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NMP62200, NUDOCS 9005030280
Download: ML18038A297 (193)

Text

Pi,".CELERATED DISTRIBUTION DEMONSTjWTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION WILLIS,J.L. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Annual Radiological Environ Operating Rept 198 ." W/900427 ltr.

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)$ Og PD1-1 PD g INTERNAL: ACRS 1 AEOD/DSP/TPAB 1 IRM TECH ADV 1 NRR ROTHMAN,R 1 1 PB11 2 2 NUDOCS-ABSTRACT 1 1 REG FILE 01 1 3: RGN1 DRSS/RPB 1 RG LE 02 1 1' EXTERNAL EGGG S IMPSON F F 2 LPDR NRC PDR 1 1 1'OTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE W~t CONTACI'HE,DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL

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g g $]QPP+,g NMP62200 NINE MILE POINT NUCLEAR STATION/P.O. BOX 32 LYCOMING, NEW YORK 13093/TELEPHONE (315) 343-2110 April 27, 1990 United States Nuclear Regulatory Commission Document Control Desk Hashington, 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 wi th the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2, we are enclosing the Ann al Radiol i al Environmental 0 ratin Re ort for the period January, 1989 through December, 1989.

Any questions concerning the enclosed report should be directed to Hugh J.

Flanagan at Nine Mile Point (315/349-2428) .

Very truly yours, General Superintendent Nuclear Generation 3LN:H3F:jg (2179X)

Enclosure (18 copies) xc: USNRC Region I Resident Inspector (Unit 1/Unit 2)

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NIAGARA MOHAWK POWER CORPORATION R RT January 1, 1989 - December 31, 1989 for NINE NILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket Number 50-220 and NINE NILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

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List of Tables List of Figures 1.0 Introduction 2.0 AQUATIC SAMPLES I Shoreline Sediment II Fish III Surface Hater 13 3.0 DIRECT RADIATION 17 4.0 TERRESTRIAL SAMPLES 24 I Air Particulate/Iodine 25 II MilIR III Food Product 37 IV Land Use Census 40 5.0 INTERLABORATORY COMPARISON PROGRAM 42 6.0 CHANGES AND EXCEPTIONS TO THE PROGRAM 44

7.0 CONCLUSION

47 8.0 GENERAL REFERENCE MATERIAL 49 9.0 DATA TABLES 1989 52

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Table 1 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program - Aquatic Program and Direct Radiation 53 Table 2 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Terrestrial Program 54 Table 3A Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/g-dry) 55 Table 3B Concentration of Gamma Emitters in Shoreline Sediment Samples (pCt/kg-dry) 56 Table 4A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 57 Table 4B Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet) 59 Table 5 Concentration of Gamma Emitters in Surface Water Samples 61 Table 6 Concentration of Tritium in Surface Water Samples 65 Table 7 Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity 66 Table 8 Environmental Airborne Particulate Samples-On-Site Stations, Gross Beta Activity 70 Table 9 Concentration of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples 72 Table 10 Environmental Charcoal Cartridge Samples-Off-Site Stations, I-131 Activity 87 Table 11 Environmental Charcoal Cartridge Samples-On-Site Stations, I-131 Activity , 89 Table 12A Direct Radiation Measurement Results (mrem per standard month) 91 Table 12B Direct Radiation Measurement Results (mrem per quarterly period) 95

(Continued)

Table 13 Concentration of Gamma Emitters in Milk 99 Table 14 Concentration of Iodine-131 in Milk 105 Table 15 Milk Animal Census 107 Table 16 1989 Residence Census 109 Table 17A Concentration of Gamma Emitters in Food Products (pCi/g-wet) 110 Table 178 Concentration of Gamma Emitters in Food Products (pCi/kg-wet)

Table 18 Interlaboratory Comparison Program Results 112 Table 19 Environmental Sample Locations 119 Table 20 Radiological Environmental Monitoring Program Annual Summary 128 Table 21 Historical Environmental Sample Data Shoreline Sediment (Control) 133 Table 22 Historical Environmental Sample Data Shoreline Sediment (Indicator) 134 Table 23 Historical Environmental Sample Data Fish (Control) 135 Table 24 Historical Environmental Sample Data Fish (Indicator) 136 Table 25 Historical Environmental Sample Data Surface Hater (Control) 137 Table 26 Historical Environmental Sample Data Surface Hater (Indi cator) 138 Table 27 Historical Environmental Sample Data Surface Hater Tritium (Control) 139 Table 28 Historical Environmental Sample Data Surface Hater Tritium (Indicator) 140

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Table 29 Historical Environmental Sample Data Air Particulate Gross Beta (Control) 141 Table 30 Historical Environmental Sample Data Air Particulate Gross Beta (Indicator) 142 Table 31 Historical Environmental Sample Data Air Particulates (Control) 143 Table 32 Historical Environmental Sample Data Air Particulates (Indicator) 144 Table 33 Historical Environmental Sample Data Air Radioiodine (Control) 145 Table 34 Historical Environmental Sample Data Air Radioiodine (Indicator) 146 Table 35 Historical Environmental Sample Data Environmental TLD (Control) 147 Table 36 Historical Environmental Sample Data (A E) Environmental TLD (Indicator) 148 Table 37 Historical Environmental Sample Data Milk (Control) 153 Table 38 Historical Environmental Sample Data Milk (Indicator) 154 Table 39 Historical Environmental Sample Data Food Products (Control) 155 Table 40 Historical Environmental Sample Data Food Products (Indicator) 156

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Figure lA Off-Site Environmental Station and 157 TLD Locations Figure 1B Off-Site Environmental Station and TLD 158 Locations (Southern)

Figure 2 On-Site Environmental Station and TLD 159 Locations Figure 3 Nearest Residence and Food Product Locations 160 Figure 4 Milk Animal Census and Milk Sample 161 Locations Figure 5 New York State Map 162

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1.0 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 1989.

The Radiological Environmental Monitoring Program (REMP) is a joint program between the Nine Mile Point Nuclear Station (NMPNS) and the James A. FitzPatrick 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 Environmental Laboratory during 1989. 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)

The 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 Technical Specifications. Data from optional locations are not evaluated unless indicated otherwise.

1.0 LJULalL There were four separate groups of radionuclides that were detected in the environment during 1989. Several radionuclides could possibly fall into two of the four groups. The first of these groups is naturally occurring radionuclides. It must be realized that the environment contains a broad inventory of naturally occurring radioactive elements. Background radiation, as a function of primordial radioactive elements and cosmic radiation of solar origin, offers a constant exposure to the environment and man. These radionuclides, such as Ra-226, Be-7 and especially K-40, account for a majority of the annual per capita background dose.

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 radtonuclides 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 198'I 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 1989, Cs-137 was the only radionuclide detected in environmental samples that has a weapons testing origin.

The third group of radionuclides includes those detected at the site 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.

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, impossible.

if The radionuclides falling into this category (as applicable not to the 1989 Nine Mile Point Radiological Environmental Monitoring Program) includes Zn-65, Co-60 and Cs-137. The dose to man as a result of these radionuclides is small and significantly less than the radiation exposure from naturally occurring sources of radiation and from fallout.

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1.0 Thus, 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 1989, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. It is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are very small and are not 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 concentra-tion 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.

The 1989 average annual dose equivalent to individuals in the United States has been estimated to be 360 mrem (NCRP 93, 1987). The majority of this dose (300 mrem) is attributed to natural background of which radon and daughter products contributed 200 mrem. Of man-made sources, medical diagnosis was the highest, contributing approximately 50 mrem. Consumer products added the remaining 10 mrem. The annual dose from the nuclear fuel cycle (including the operation of nuclear power facilities) is considered essentially negligible.

Background gamma radiation around the Nine Mile Point Site, as a result of radionuclides in the atmosphere and the ground, accounted for approximately 56 mrem per year during 1989. 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 56 mrem per year, as a background dose, is significantly greater than any possible doses as a result of operations at the site during 1989.

Table 19 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 19 also gives the figure (map) number as well as the map designation for each sample location by sample medium type. The requirement for Table 19 is found in section 6.9.1.d of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1 and section 6.9.1.7 of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 2.

1 v p 1 Table 20 contains a summary of basic statistics for environmental sample media as required by the Technical Specifications. Table 20 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. l.d and section 6.9.1.7 of the Technical Specifications for Nine Nile Point Nuclear Station Unit 1 and Unit 2 respectively.

v D 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 quantities. Data on Tables 21 - 40 were obtained from previous Annual Radiological Environmental Operating Report tables.

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T 2.0 I SHORELINE SEDIMENT A. 1 1 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 19 for location designations and descriptions).

Shoreline sediment samples were obtained in April and October of 1989 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 1989 at the indicator and control locations are shown on Table 3. Table 3A shows results in units of pCi/g (dry) for purposes of data evaluation.

Table 3B shows results in units of pCi/kg (dry), as required by the Technical Specifications. Only the Sunset Bay location was required by the Technical Specifications during 1989.

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 1989. K-40 ranged in concentration from 13.3 pCi/g (dry) to 13.7 pCi/g (dry) at the control location and 16.6 pCi/g (dry) to 18.0 pCi/g (dry) at the indicator location. K-40 is a naturally occurring primordial radionuclide.

Ra-226, AcTh-228, and Be-7, in addition to K-40, 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 2.34 pCi/g (dry) to 2.54 pCi/g (dry) at the indicator locations and 1.17 pCi/g (dry) to 1.25 pCi/g (dry) at the control location. The AcTh-228 was detected once at the control location at a concentration 0.42 pCi/g (dry).

AcTh-228 concentration ranged from 0.67 pCi/g (dry) to 0.80 pCi/g (dry) at the indicator location. Be-7 was detected in one control sample at a concentration of 0.12 pCi/g (dry). Be-7 is a naturally occurring radionuclide and has been detected intermittently during the past.

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2.0 I SHORELINE SEDIMENT (Cont ')

B. v (Cont'd)

Cs-137 was not detected at the control location during 1989. Cs-137 was detected at the indicator location at concentrations ranging from 0.25 pCi/g (dry) to 0.34 pCi/g (dry). Cs-137 has not been detected at this location in the past (1985 - 1988).

The source of Cs-137 in 1989 indicator shoreline sediment samples is difficult to determine. Possible sources are fallout from past weapons, or much less likely, 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 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'o be affected by plant operations, as well as soil beyond any inf'luence from the site, all contain levels of Cs-137 at or greater than the concentration found in 1989 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 0.001 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 also contained Cs-137 at a concentration of 0.63 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.

2.0 II FISH A. 1 1 Available fish species are obtained from collections during the spring and fal 1. Samples are col ected from two of four possible on-si te 1

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. Nhen 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 19 for location designations and descriptions).

B. T 4 A total of twenty-four fish samples were analyzed as a result of collections in the spring season (June 1989) and in the fall season (September-October 1989). Collections were made utilizing gill nets at one location greater than five miles from the site (Oswego Harbor area), and at two locations in the vicinity of the lake discharges for the Nine Nile Point Unit ¹1 (02), and the James A. FitzPatrick (03) generating facilities. The Oswego Harbor samples served as control samples while the NHP (02) and JAF (03) samples served as indicator samples. Samples were analyzed for gamma emitters. Table 4A shows results in units of pCi/g (wet) for purposes of data evaluation. Table 48 shows results in units of pCi/kg (wet), as required by the Technical Specifications.

Spring fish collections were comprised of three separate species. The three species represented two feeding types. Lake trout and brown trout are highly predacious and feed on significant quantities of smaller fish such as smelt, alewife, and other smaller predacious species. The second feeding type is represented by white sucker which are bottom feeders that consume bottom dwelling organisms and decaying organic matter.

II FISH (Cont'd)

B. v 1 f 4 4 (Cont'd)

Cs-137 was detected in four of the six indicator samples and in one of the three 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 lake trout ranged from 0.039 pCi/g (wet) to 0.043 pCi/g (wet) for the indicator samples. The detected Cs-137 concentration in control samples was 0.032 pCi/g (wet) for lake trout.

Cs-137 in brown trout samples ranged from 0.020 to 0.030 pCi/g (wet) at the indicator locations. Cs-137 was not detected in the control sample. Cs-137 was not detected in white sucker samples at the indicator or control locations.

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'etectable concentrations of K-40 in the indicator samples ranged from 3.99 to 5.26 pCi/g (wet) and 3.99 to 5.14 pCi/g (wet) for the control samples. Ra-226, also naturally occurring, was found at levels that ranged from 0.48 to 1.08 pCi/g (wet) at the indicator locations and was not detected at the control location. AcTh-228, another naturally occurring radionuclide, was detected in two indicator fish samples and ranged from 0.068 - 0.088 pCi/g (wet). AcTh-228 was not detected in the control samples. No other radionuclides were detected in the spring fish samples.

Fall fish sample collections were comprised of four separate species and fifteen individual samples. Halleye, brown trout, smallmouth bass, white sucker, and two separate lake trout samples were collected at each sampling location (NMP, JAF, and Oswego Harbor).

Cs-137 was detected tn nine of the fifteen samples which included the control samples. Indicator samples showed an average Cs-137 concentration that was approximately equal to 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 walleye samples at the indicator locations ranged from 0.030 to 0.042 pCi/g (wet) and was 0.020 pCi/g (wet) at the control location. Lake trout sampled at the control location had Cs-137 concentrations of 0.030 to 0.033 pCi/g (wet).

Indicator samples of lake trout ranged from 0.024 to 0.041 pCi/g (wet).

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2.0 II FISH (Cont'd)

B. Ev in f FihD -T (Cont'd)

Cs-137 was detected in one indicator sample of smallmouth bass at a concentration of 0.042 pCi/g (wet). A smallmouth bass sample was not available at the control location. White sucker and brown trout samples were available at both indicator and control locations. Cs-137 was not detected in these samples. The one species of bottom feeder collected during the fall season (white sucker) showed no detectable Cs-137 because of different feeding habits and because this species is not in the same position on the food chain as the other predacious species.

Naturally occurring K-40 was detected in all of the fall samples collected. Detectable concentrations of K-40 in the indicator samples ranged from 3.84 to 6.25 pCi/g (wet) and 3.38 to 5.12 pCi/g (wet) for the control samp'les. Ra-226, also naturally occurring, was detected at concentrations which ranged from 0.39 to 1.27 pCi/g (wet) for the indicator samples and from 0.42 to 0.60 pCi/g (wet) for the control samples. Another naturally occurring radionuclide, AcTh-228, was detected in one indicator sample of lake trout at a concentration of 0.143 pCi/g (wet) and in one control sample of walleye at a concentration of 0.079 pCi/g <wet). 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 1989, 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 1989 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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2.0 II fISH (Cont ')

B. i n f 4 (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 0.035 pCi/g (wet) (annual mean result of indicator samples for 1989), the whole body dose received would be 0.052 mrem per year. The critical organ in this case is the liver which would receive a calculated dose of 0.080 mrem per year. The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mile Point area (indicator samples). No radiological decay is assumed for the calculation of doses.

Conservative whole body and critical organ doses can be calculated for the consumption of fish from the control location as well. In this case the consumption rate is assumed to remain the same (21.0 kg per year ) but the average annual Cs-137 concentration for the control samples is 0.029 pCi/g (wet). The calculated Cs-137 whole body dose is 0.044 mrem per year and the associated dose to the liver is 0.066 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.

Ooses from both sample groups are considered background doses.

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2.0 III SURFACE WATER A.

Surface water samples are taken from the respective inlet canals of the J.A. FitzPatrick facility and Niagara Mohawk's Oswego Steam Station.

The FitzPatrick facility removes water from Lake Ontario on a continuous basis and generally represents a "down-current" sampling point from the Nine Mile Point Unit 1 and Unit 2 facilities. The Oswego Steam Station inlet canal removes water from Lake Ontario at a point approximately 7.6 miles west of the site. This "up-current" location is considered a 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 1989 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 lA (refer to Table 19 for location designations and descriptions).

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2.0 III SURFACE WATER (Cont'd)

B.

Surface water samples were ana'lyzed monthly for gamma emitters (using gamma spectral analysis) during 1989. Tritium analyses were performed quarterly. quarterly sampl es (i .e., analys i s for tri tium) were composite samples.

The analytical results for the 1989 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 5 and 6 show the results of surface water samples analyzed during 1989.

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 1989. Hoth 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 48 to 310 pCi/liter. K-40 in the Oswego Steam Station inlet canal ranged from 33 to 334 pCi/liter. The Nine Mile Point Unit 1 inlet canal, Unit 2 inlet canal and the city water samples showed K-40 detected in all of the twelve monthly samples for each location.

For these samples, K-40 concentrations ranged from 32 to 234 pCi/liter, from 46 to 262 pCi/liter and from 57 to 275 pCI/liter respectively.

Ra-226 was detected intermittently in samples from all five locations.

Ra-226 was detected in eleven of the twelve monthly samples from the Nine Mile Point Unit ¹1 inlet canal and ranged from 45 to 149 pCi/liter. The Nine Mile Point Unit 2 inlet canal showed Ra-226 detected in eleven of the twelve samples and ranged from 61 to 110 pCi/liter. Samples from the FitzPatrick location showed Ra-226 in eleven of the twelve monthly samples and ranged from 76 to 160 pCi/liter. The control sample location (Oswego Steam Station) showed Ra-226 in eleven of the twelve monthly samples and ranged in concentration from 58 to 155 pCi/liter. The city water samples results showed Ra-226 detected in ten of the twelve monthly samples and ranged from 47 to 158 pCi/liter.

-14

2.0 III SURFACE WATER (Cont'd)

B. v i n f D - T (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. Five 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 200 to 310 pCI/liter with a mean of 253 pCI/liter. Tritium concentrations for the James A, FitzPatrick inlet canal ranged from 210 to 350 pCi/liter and showed a mean concentration of 280 pCi/liter.

Inlet canal samples taken at Nine Nile Point Unit and Unit 2 showed 1

tritium concentrations ranging from 160 to 220 pCi/liter and 160 to 280 pCi/liter respectively. The annual mean concentration was 187 pCi/liter and 210 pCi/liter respectively. The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from 180 to 660 pCi/liter with a mean of 373 pCi/'liter.

As noted above, the Technical Specification control location (Oswego Steam Station inlet canal) mean results for tritium were greater than indicator locations. The maximum concentration of tritium at the control location was found in the fourth quarter of 1989 and was 660 z 90 pCi/liter. This value is more than twice the detected concentration of tritium at any other location. The Technical Specification control location is located at an "up current", distant location beyond any influence from the station. Elevated levels of tritium in water samples have been observed in the past. Weapons testing in previous years and other natural sources have contributed to the tritium detected in surface water.

Review of past environmental data for Cs-137 from 1979 through 1988 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 1989 in surface water samples.

Other plant related radionuclides detected during a review period of 1979 1988 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

-15

2.0 III SURFACE HATER (Cont'd)

B. v 1 (Cont'd) 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 1989 in surface water samples.

Tables 25 and 26 show historical environmental sample data for surface water using gammas 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 1989 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 1989 was 280 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 (1985-1989) 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 1988 have remained relatively consistent. The annual mean result for 1989 was 373 pCi/liter.

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

-16

t \

4 hW w 14

~~

I(-.

D T P

T I

-17 h

I' i ',",V r ) %5>, chf hiPvhv)gn,';t rPV ( g,~ 'gtfh vt e)<Vf%w ~P P Jv v r w>>=pezt1t ~ Y n;, t, rH, S+,'t,W

I

~ a ss>r s n mv~~

~ ay~<, ~ wg .z ~~q; ~s ~m r,,w;r~vsmi, igr~c;,. g>> y' r. " r e' ~,;, y"~el ~v w>,~~ ~ saon~> pw ~w.~ ~

e,p, ~

"h w) 4~ 4I I ~ E 3.0 A.

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 Hestwood, New Jersey. Shipment control TLD's (at least two) accompany each shipment to and from the vendor's laboratory. Shipment control TLD's also accompany the TLD's when they are being placed or collected and are shielded by lead when they are not being used. TLD data results are corrected for a transit dose by use of the data from the shipment control 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 communities 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 1989 were composed of rectangular teflon wafers impregnated with 251. CaS04. 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.

fnvironmental TLD locations are shown on Figures lA, 1B, and 2 (refer to Table 19 for location designations and descriptions).

B.

TLD's were collected and read once per quarter during the 1989 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 12A) and in mrem per quarterly period (Table 128).

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 12A and 128 are comprised of TLD's required by the Technical Specifications and special interest TLD's not required by the Technical Specifications. 'uring 1989, TLD's were collected during the weeks of March 26, 1989, June 2S, 1989, September 24, 1989 and December 24, 1989.

-18

~ - ~

3.0 D B. v 1 DD -T 1 (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 TLDs required by the Technical Specifications during 1989 were initiated in 1985 as a result of the issuance of new Technical Specifications by the NRC. Therefore, these TLDs can only be compared to 1985 - 1988 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 2.7 to 14.5 mrem per standard month. TLD ¹3 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 ¹3 were approximately double the results of the other TLD's during 1989 because of the effects from the Unit 2 and the FitzPatri ck facility.

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 1989 were variable and ranged from 6.0 to 42.1 mrem per standard month as a result of activities at the radwaste facilities and the operating modes of the generating facilities, Results for 1989 are consistent with the ranges of variability noted in 1988 for TLD's at or near these locations. TLD's in this group ranged up to approximately seven times control TLD results.

v 1 (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 1989 showed these TLD's ranged from 3.8 6.8 mrem per standard month and were slightly less than the 1988 results. Slight increases were noted in the second and third quarter results as was noted for all TLD's, including control TLD's.

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 2.8 to 6.3 mrem per standard month. Site boundary TLD's during 1989 were consistent with 1985-1988 results. TLD numbers 75, 76, 77, 23, 85, 86, and 87 showed results that ranged up to three times the results of control TLD's. These results ranged from 4.0 to 15.4 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 and Unit 2 and the radwaste facilities of the 1

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 each quarter in mrrg gus ~~

include numbers 8, 14, 49, 110 and 111. Net site boundary doses for mzLtll are as follows:

Q3hU~r

+0.4

+0.1

+0.3

-0.6

• 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.

-20

~ 0 ~

B. v T 1 (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 meteoro'logical sectors that are located over Lake Ontario.

Results for this group of TLD's during 1989 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, 91, 92, 93, 94 and 95. Results fluctuated from 2.5 to 6.8 mrem per standard month. These results are generally consistent with control TLD results during 1989. Results for this group of TLDs were consistent with the 1985 - 1988 results. Results were also consistent with other off-site TLD results during 1989 and previous to 1989. Again, second and third quarter TLD results were slightly elevated along with all other groups of TLD's, including control groups.

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, 52, 53, 54, 55, 56, 58, 96, 97, 98, 99 100, 101, 102, 108 and 109. TLD numbers 108 and 109 are new TLD locations that were established during 1988 and were added to assist in the evaluation of the critical residence. Results ranged from 2.1 to 7.0 mrem per standard month. All the TLD results from this group were within the general variation noted for the control TLD's.

Results during 1989 for TLD's established during previous years were consistent with results noted for those years. Overall, second and third quarter TLD results for this group were slightly elevated as were other TLD groups, including the control group.

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 ill. TLD numbers 110 and 111 were added to the program during 1988 to expand the data base for control TLD's. Results for 1989 ranged from 2.9 to 6.4 mrem per standard month. Results from 1989 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 1987-1989. Control TLD's results in 1989 (second and third quarter) were slightly elevated as were other TLD groups.

-21

3.0 D D T B. v i n T D (Cont'd)

Review of past TLD results T fi n 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 1989.

TLDs located at the site boundary averaged 6.2 mrem per standard month during 1985. During 1986, 1987, and 1988 site boundary TLDs averaged 7.0, 6.1, and 6.4 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 1989, site boundary TLDs averaged 5.9 mrem per standard month.

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, and 1988 off-site sector TLDs averaged 6.0, 5.2, and 5.3 mrem per standard month respectively. The 1986 results demonstrated an increase for this group of TLDs. Results for 1989 for the group averaged 4.9 mrem per standard month. This is fairly consistent with previous years results. Again, 1989 second and third quarter TLD's showed a slight increase.

Special interest 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 results averaged 5.3 mrem per standard month.

1989 results for this location averaged 4.8 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 Nuclear Plant accident. Results for 1987 and 1988 averaged 5.2 and 5.4 mrem per standard month respectively. Results for 1989 averaged 4.6 mrem per standard month and showed levels slightly less than previous years. Slight increases were noted in second and third quarter results.

-22 gg  %

f =

gg 'hl ' '

I'% Q), 1 g g g ~

~ ~ 'I A 'h ~ ~ 0~ 'A ' ~

B. v 1 i fT 0 1 A 1 (Cont'd)

During 1989, all environmental TLD groups required by the Technical Specifications were consistent with results observed during 1988.

However, all TLD groups (including control TLD's) showed decreased levels for the fourth quarter of 1989. In general, the second and third quarter results were higher than the first and fourth quarter results. This may be explained. by the fact that the second and third quarters are primarily dry, with little ground water from rain or snow precipitation to prevent naturally occurring radionuclides (from radon and thoron decay) from diffusing from the ground. This, in particular, may explain why the fourth quarter of 1989 results were tn fact, less than any fourth quarter results observed since 1985. The fourth quarter of 1989 experienced record snowfall in the month of December and a subsequent decrease in TLD results for that period.

Tables 35 and 36 show the historical environmental sample data for environmental TLD's.

Overall, environmental TLD results for 1989 showed no significant impact from direct radiation measured outside the site boundary.

-23

-24

~( 4.0 I AIR PARTICULATE/IODINE A.

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 Nile 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 least prevalent wind direction of northeast (R-5). This location is considered a control location.

In addition to the Technical Specification required locations, there are six other sampling stations located within the site boundary (01, G, H, I, J, and K). These locations generally surround the area occupied by the three generating facilities, but are well within the site boundary. One other air sampling station is located off-site in the southwest sector and is in the vicinity of the City of Oswego.

Three remaining air sampling stations (D2, E and F) are located in the east-southeast, south-southeast and south sectors and range in distance from 7.2 to 9.0 miles.

At each station, 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 19 for location designations and descriptions).

-25 vs *+v> ~ ~ 'r ~ ,;p ~ . ~< r ~ >'y *, ~

8 e; y ~ e a; a Wpv'~Osyae'

4.0 I AIR PARTICULATE/IODINE (Cont')

B. v Tables 7 and 8 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 7 and 8 also shows the results from other air sampling locations not required by the Technical Specifications. These locations are designated as Dl on-site, G on-site, H on-site, I on-site, J on-site, K on-site, D2 off-site, E off-site, F off-site and G off-site locations. A total of 52 control samples from location R-5 and 208 indicator samples from locations R-l, R-Z, R-3, and R-4 were collected and analyzed during 1989.

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

Location ** Minimum* Maximum* Average*

R-1 0.007 0.041 0. 017 R-2 0.008 0.033 0.017 R-3 0.007 0.041 0. 017 R-4 0.009 0.038 0.018 R-5 (control) 0.007 0.039 0.017

• Concentration in pCi/m3

• • 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 1989.

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/m3 in 1981 to 0.021 in 1987. Results from indicator air sampling locations ranged from 0.151 pCi/m3 in 1981 to 0.017 pCi/m3 in 1989. For both indicator locations and control locations, the gross beta concentration during 1977 to 1987 fluctuated

-26

4.0 T R I I AIR PARTICULATE/IODINE (Cont ')

B. v i (Cont'd) with the detonation of thermonuclear weapons. The Technical Specification control and indicator results during 1989 both averaged 0.017 pCi/m3 which represented the lowest level recorded to date.

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

C.

Weekly air particulate samples were composited by location to form monthly composite samples. The monthly composite samples required by the Technical Specifications include R-l, R-2, R-3, R-4, and R-5.

Other sample locations not required by the Technical Specifications include Dl 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 9.

The results for the monthly composite samples showed positive results for Be-7, K-40, and Ra-226. All three of these radionuclides are naturally occurring. Be-7 was found in all of the monthly composite samples from all locations required by the Technical Specifications.

Be-7 ranged from 0.052 to 0.103 pCi/m3 for the Technical Specification indicator locations (R-l, R-2, R-3, and R-4). The Technical Specification control location (R-5) results showed Be-7 ranging from 0.061 to 0.101 pCi/m3. K-40 was found intermittently in the monthly composite samples required by the Technical Specifications. K-40 ranged from 0.010 to 0.047 pCi/m3 at the control location (R-5) and 0.009 to 0.046 pCi/m3 at the indicator locations. Ra-226 ranged from 0.012 to 0.027 pCi/m3 at the indicator locations required by the Technical Specifications. The Technical Specification control location results showed no detectable Ra-226.

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 1989.

No other radionuclides were detected at Technical Specification locations using gamma spectral analysis during 1989

'27

r r \ &F4 ~ 9 I ~ F Fl ~ F I ~ LA C 4 4, ~ C 8 - ~ ) I I

4.0 I AIR PARTICULATE/IODINE (Cont')

C. v 1 1 n f (Cont'd)

The location, concentration range and mean, and frequency of occurrence of each radionuclide detected during 1989 if1 are included below.

Lm~n )ham" II F Ra-226 Indicator 0. 012 0. 027 0. 018 9/48 Ra-226 Control ND ND ND K-40 Ind1cator 0.009 0.046 0.028 40/48 K-40 Control 0.010 - 0.047 0.028 9/12 Be-7 Indicator 0.052 - 0.103 0.078 48/48 Be-7 Control 0.061 0.101 0.079 12/12

• Results in units

• • Frequency is the of pC1/m3.

number of times detected over the number of samp'les.

ND Not detected Historically, the naturally occurring radionuclides Ra-226, K-40 and Be-7 have shown fluctuations that are representative of natural changing cond1tions. No significant trends were noted during 1989.

Two plant related activation product radionuclides were detected at optional on-site air sampling stations during 1989. Zn-65 was detected at the H on-site and I on-site sampling locations in October and November at optional stations H on-site, I on-site, and J on-site.

Co-60 was also detected tn the H on-site November composite. The detected concentrations are summarized below:

Air Sampling Location Concentration in 10-3pCi/m3 lin P October Zn-65 2.77 2.90 <2.57 Co-60 <1.0 <1.7 <1.0 November Zn-65 24.9 4.63 2.17 Co-60 0.9 <0.9 <0.9 Zn-65 and Co-60 were not detected in any of the other air monitoring stations, including the control station during 1989.

An evaluation of the presence of Zn-65 in the monthly air composite sample was made. The weekly samples which make up the monthly composites were analyzed separately. It was determined that the detected activity was present in the October composite which represents the sample period designated as week No. 41 (10/9/89 10/16/89). The

-28 r rl r ~, ~,,I rI IF@fr F t .r ~

FI 'l+r ~

4 V ~ ~ ~

4.0 I AIR PARTICULATE/IODINE (Cont')

v 1 i n T 1 (Cont'd) detected activity in the November composite was on two filters which represent the sample periods designated as week No. 46 (ll/13/89 11/20/89) and week 47 (ll/20/89 - ll/27/89). Meteorological data was reviewed for these sample periods and it was determined that wind patterns during this time were such that the H, I, and J on-site sampling locations could be affected by plant effluents.

Based on the evaluation of meteorological data and plant effluents, it can be concluded the presence of Zn-65 and Co-60 in the October and November air particulate composite samples summarized above are the result of operations at the James A. FitzPatrick Nuclear Power Plant.

Due to the fact that Zn-65 and Co-60 were not detected in areas occupied by members of the public (outside the site boundary) the dose to man is not significant. The dose to man can be calculated based on the measured concentrations of Zn-65 and Co-60 using the methodology found in Regulatory Guide 1.109 at the two on-site sampling locations.

This calculated dose is conservative and is not representative of the dose to man beyond the si te boundary, but can be used to illustrate the significance of the resulting dose relative to background radiation.

Using inhalation rates, dose factors and the maximum observed concentrations of Co-60 and Zn-65 the following dose to man was calculated:

AAP~QEl I Eu.~adx Luna Adult 0.000198 0.00592 Child 0.000300 0.00475 The conservative whole body and critical organ (lung) dose calculated as a result of the Zn-65 and Co-60 air concentrations measured on-site are very low when compared to natural background. Whole body dose to man measured by the 1989 control TLDs was 56 mrem per year. In any case, no airborne concentrations of Zn-65 or Co-60 were detected at off-site locations and actual doses to individuals off-site are zero or much less than those calculated due to facility effluents.

Zn-65 has not been detected in the past. However, Co-60 has fluctuated in air particulate samples as a result of previous weapons testing.

Co-60 average concentrations from 1977 to 1978 decreased at the indicator ~ control locations from approximately 0.0176 to 0.0022 pCi/m3. Average concentrations decreased significantly during 1979 and 1980 when compared to 1977. These results where 0.007 to 0.0016 pCi/m3 respectively. 1981 and 1982 average Co-60 concentrations decreased to 0.0007 and 0.0006 pCi/m3. Average indicator and control

-29

4.0 I AIR PARTICULATE/IODINE (Cont')

C. 1 n (Cont'd) concentrations were approximately equal during 1979 to 1982. The 1983 indicator mean Co-60 concentration was 0.0007 pCi/m3 or slightly greater than the 1982 concentration. The 1983 control mean Co-60 concentration was also 0.0007 pCt/m3 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/m3 at the control stations and 0.0012 pCi/m3 at the indicator stations. However, the 1984 Co-60 positive results were a result of contamination during handling and not a result of operations at the site. The general reduction in previous indicator and control Co-60 concentrations (1981 - 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 locations. During 1987, Co-60 was detected once at a concentration of 0.0017 pCi/m3 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. Results from 1989 showed that Co-60 was not detected from either Technical Specification control or indicator sample locations.

Historically, Cs-137 has been variable during the past 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/m3. Cs-137 average concentrations at indicator and control locations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCi/m3 respectively. Average concentrations during 1980 and 1981 were approximately equal at control and indicator locations. Cs-137 during 1980 was approximately equal to 1979 and increased slightly in '1981 from 1979. The 1980 and 1981 average concentrations were 0.0014 and 0.0016 pCi/m3 respectively. The mean 1982 concentration for Cs-137 decreased to 0.0004 pCi/m3. The 1983 mean Cs-137 concentration for the indicator and control composite samples were 0.0002 and 0.0002 pCi/m3 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/m3 respectively. During 1987, 1988, and 1989 Cs-137 was not detected.

-30

4.0 I AIR PARTICULATE/IODINE (Cont')

C. v 1 f p 1 (Cont'd)

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 was 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 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 1989, 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.

During the 1989 sampling program, airborne radioiodine was not found in any of the fifty-two weekly samples from the control location required by the Technical Specifications. LLD values at the control location ranged from 0.006 0.013 pCi/m3.

I-131 has been detected in the past at control locations. During 1976, the mean off-site I-131 concentration was 0.60 pCi/m3. 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/m3. 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/m3. 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/m3. I-131 was not detected at the control location during the period 1987 through 1989.

-31

(~ ~

4.0 I AIR PARTICULATE/IODINE (Cont ')

D. v (Cont'd)

During 1989, 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 0.005 0.039 pCi/m3. During 1989, I-131 was not detected at any of the optional monitoring locations that were not required by the Technical Specifications.

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/m3 during 1978 and was not detected during 1979. The 1980-1982 average concentrations were 0.013, 0.029, and 0.016 pCi/m3 which were reductions in view of previous I-131 concentrations. During 1983, the mean I-131 concentration was 0.028 pCi/m3 which represented a slight increase compared to 1982. For the most part, I-131 in indicator and control samples was a resu'lt 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 sample stations 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/m3 as a result of the Chernobyl Nuclear Plant accident.

I-131 was found at a mean concentration of 0.014 pCi/m3 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 or 1989.

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

0

-32

~ 1 ~ ~

4.0 II MILK A. ll inM 1 n Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample i s 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 1989, 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' 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 19 for location designations and descriptions).

B. v 1 D - T 1 Milk samples were collected from a total of six indicator locations (wi thi n 10 miles of the site) and one control location (beyond 10 miles from the site) during 1989. The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site.

During 1989, there were no milk sample locations within 5.0 miles of the site. The locations that were sampled during 1989 are located from 5.5 to 9.5 miles from the site. The only sample location required by the Technical Specifications during 1989 was the control location which was located 17.0 miles to the southwest of the site ( location ¹65) .

Sample location descriptions for all milk sample locations utilized during 1989 are listed below.

-33

4.0 TR II MILK

8. v 1 (Cont'd)

F 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 1989, 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 1989. Since I-131 was not detected during November and December of 1988, no additional samples were collected in January through March of 1989. 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 13 and for I-131 on Table 14.

Gamma spectral analyses of the bimonthly samples showed K-40, Ra-226 and AcTh-228 to be the only naturally occurring radionuclides detected in the milk samples collected during 1989. K-40 was detected in all but one indicator sample. Indicator sample location concentrations ranged from 1360 pCi/liter to 1970 pCi/liter while K-40 concentrations at the control location ranged 1370 pCi/liter to 1790 pCi/liter.

Ra-226 ranged from 87 to 283 pCi/liter at the indicator locations and 97 to 284 pCi/liter at the control location. Ra-226 occurred intermittently in milk samples. AcTh-228 was found on one occasion for milk samples collected from the indicator locations at a concentration of 23.9 pCi/liter. AcTh-228 was also detected in one control location sample at a concentration of 24.8 pCI/liter. K-40, Ra-226 and AcTh-228 are naturally occurring radionuclides and are found in many of the environmental media sampled.

During 1989, no Cs-134 or Cs-137 was 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.

Milk samples were collected and analyzed twice per month for I-131.

I-131 was not detected during 1989 in any of the indicator or control samples. All 1989 I-131 milk sample results are reported as the lower limit of detection (LLD). The LLD results for 1989 milk samples ranged from <0.10 pCi/liter to <0.50 pCi/liter.

-34

4.0 II MILK B. v 1 1 1 (Cont'd)

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 than 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.

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 1989 at the control location.

Cs-137 in milk samples is, for the most part, a result of previous weapons testing and more recently, the Chernobyl accident. The continuing reduction of Cs-137 levels is a result of nuclear decay and ecological cycling.

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 mi'lk 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 1989 in milk samples.

-35

II MILK B. v 1 1 D T 14 (Cont'd)

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 1987, 1988, or 1989 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 1989. Only naturally occurring Ra-226, K-40, and AcTh-228 were detected. Therefore, no doses to man have been calculated.

1

-36 1

,'I

~ -~

4.0 III FOOD PRODUCTS A.

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 19 for location designations and descriptions).

B.

Food product samples collected during 1989 were comprised of garden vegetables, fruit 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, beet greens, squash leaves, collard greens, and swiss chard which are all considered broadleaf vegetables. Other broadleaf vegetation consisted of eggplant leaves, bean leaves, strawberry leaves, pepper leaves and cucumber leaves't the control location, one sample of each of the same or of a similar type of fruit, vegetable or vegetation was collected. Fruits, vegetables and vegetation were collected in the late summer harvest season.

K-40 was detected in food product samples. Vegetation sampled showed concentrations of K-40 ranging from 2.96 pCi/g to 7.42 pCi/g (wet).

Be-7 was also found intermittently in vegetation samples. This radionuclide ranged from 0.08 pCi/g to 1.56 pCi/g (wet). Ra-226 was detected at concentrations that ranged from 0.14 to 0.40 pCf/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 0.041 to 0.080 pCi/g (wet) for both indicator and control locations. K-40, Be-7, Ra-226 and AcTh-228 are naturally occurring radionuclides.

-37

4.0 III FOOD PRODUCTS B. Ev 1 1 1 B (Cont'd)

Cs-137 was detected in one broadleaf sample (squash leaves) from the indicator locations. The detected quantity was slightly below the limit of detection and was 0.009 pCi/g (wet). LLD values for all broadleaf samples ranged from 0.011 pCi/g to 0.018 pCi/g (wet). The presence of Cs-137 was not detected in any of the other samples. It is likely that the quantity of Cs-137 found is a result of uptake by the squash plant or from deposition. The ultimate source of Cs-137 is from weapons testing, operations at the site or both. Cs-137 has been detected in soil samples from areas at the site and at areas well beyond the site as a result of past weapons testing. Cs-137 was not detected at the control location nor was it detected at other indicator locations near the site.

No other radionuclides were detected in the 1989 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 - 'l988 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).

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

The impact of detectable Cs-137 in food product samples can be evaluated by calculating a dose to the maximum exposed individual as a result of consumption. Using standard methodology from NRC Regulatory Guide 1.109, the maximum exposed organ is the bone of a child. The maximum whole body dose would be to an adult. The Cs-137 concentration is 0.009 pCi/g (wet) and is conservatively assumed to be a result of operations at the site and is assumed to remain consistent throughout the year. The consumption rate is assumed to be a maximum consumption rate of 26 kg per year for a child. The calculated doses are 0.07 mrem per year to a child's bone tissue (maximum organ dose) and 0.01 mrem per year to the whole body. The maximum whole body dose, however, occurs to the adult. Assuming a Regulatory Guide 1.109 maximum consumption rate of 64 kg per year for an adult, the maximum organ dose is 0.06 mrem to the liver and 0.04 mrem to the whole body .

-38

4.0 III FOOD PRODUCTS B. v 1 fF Pr T 1 (Cont'd)

A maximum child organ dose of 0.07 mrem per year and adult whole body dose of 0.04 mrem per year are small when compared to doses from non man-made sources. A maximum organ dose of 0.07 mrem is small when compared to a dose of 20 mrem per year to the gonads and other soft tissues of an adult from naturally occurring K-40. A maximum whole body dose of 0.04 mrem per year can be compared to the increase in dose from increasing altitude. As one proceeds from one location to another location higher in altitude, the dose rate wi 1 1 increase slightly as a result of solar radiation. A whole body dose of 0.04 mrem per year is equivalent to proceeding from one area to another of 100 meters (328 feet) higher in altitude and remaining at that altitude for 7.3 days.

An occasion, such as moving to a location 100 meters (328 feet) higher in altitude, is a common occurrence. Any dose that may be received as a result of such an occurrence is considered sma'll and insignificant.

-39

4.0 IV LAND USE CENSUS A.

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 order to identify the closest residence 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 mi les.

A residence census was conducted during 1989 to identify the nearest residence in each of the sixteen 22.5 degree meteorological sectors within a distance of five miles from the site. At this distance, some of the meteorological sectors are over water. These sectors include:

N, NNE, NE, ENE, W, WNW, NW, and NNW.

B. v i fD In accordance with the Technical Specifications, a land use census was conducted during 1989 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.

-40

4.0 IV LAND USE CENSUS B. v 1 T 1 (Cont'd)

The number of milk animals located ~JQn the ten mile radius of the site was estimated to be 1165 cows and 27 goats for the 1989 census.

The number of cows decreased by 28 and the number of goats increased by 12 with respect to the 1988 census. One new milk location and one reactivated milk location were identified during the 1989 census.

However, no changes were made to the 1989 sampling program because the new locations did not meet criteria required to be a Technical Specification location, nor were they in such a location as to 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 15. Milk animal locations are shown on Figure 4.

.There are no residences in these sectors. The results of the 1989 residence census showing the applicable sectors and degrees and distance of each of the nearest residences are found on Table 16. The nearest residences are shown in Figure 3. No changes were noted in 1989.

-41

4

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Y A

-42

~ ~ e 5.0 NT PA N P - TABLE 18 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 18 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 and Table 3.12.1 1 of the Technical 1

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 uti lized, 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. The site laboratory's performance was acceptable for all but one analysis. The Site Environmental Laboratory results for gamma analysis of a water sample (reference QA-89-009) for Ru-106 exceeded three normalized deviations. The efficiency calibration for Ru-106 was evaluated and found to be correct. A review of the analytical results showed no discrepancies in the analysis. The other five radionuclides measured in this sample were within one standard deviation from the known, indicating no systematic error. The sample was re-analyzed using new calibration factors. The reanalysis results were consistent with the original results. No cause for the discrepancy was determined. The Ru-106 results for QA-89-058 (6/89), which was a similar sample, were acceptable. All results from the vendor laboratory were acceptable.

-43

F HA AND PTI N T TH P RAM 44

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6.0 HAN A D P RAH A.

1. Food product locations K, L, Q, Y, and H were added to the sample program during 1989. Locations K and L are located in the same sector and in close proximity to location T which was also sampled in 1987 and 1988. Location Q and Y were established as new sampling locations in different sectors due to their deposition potential and availability of samples. Location H was added as a new control location due to garden product availability.

2. Also during 1989, food product locations R, N, J, and X were deleted from the sampling program because of either sample unavailability or because the location had a low deposition potential as a result of the addition of locations K, L, Q, Y, and H.

1 Pr Exceptions to the 1989 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 Hile Point Nuclear Station Unit 1 Technical Specifications and Section 3.12.1 of the Nine Hile Point Nuclear Station Unit 2 Technical 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 2/16/89 (1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />) to 2/17/89 (1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />). The vacuum pump was found defective and was replaced.

2. Environmental air sample equipment at R-2 off-site air sampling station was inoperable from 3/9/89 (1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />) to 3/13/89 (1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br />). The vacuum pump was found defective and replaced.

3. Environmental air sample equipment at R-4 off-site air sampling station was inoperable from 3/20/89 (2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />) to 3/21/89 (0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />). The vacuum pump was found defective and was replaced.

4. Environmental air sample equipment at R-4 off-site air sampling station was inoperable from 3/21/89 (1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />) to 3/22/89 (0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />). Electrical maintenance was being performed at the station.

I

~ ( ~ r 6.0 B. (Cont'd)

5. Environmental air sample equipment at R-4 off-site air sampling station was inoperable from 9/12/89 (0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />) to 9/13/89 (0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />). The vacuum pump was restarted and was verified to be operating correctly.

6. Environmental air sample equipment at R-4 off-si te air sampling station was inoperable from ll/7/89 (1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />) to ll/14/89 (0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />). The vacuum pump was found defective and replaced.

Other occurrences of downtime for optional air sampling stations were documented for 1989. However, these occurrences are not presented here because optional air sampling stations are not required by the Technical Specifications.

Direct Radiation Monitoring Required by the Technical Specifications

l. TLD No. 83, a Technical Specification indicator TLD was lost during the second quarter of 1989. Results were obtained for the first, third, and fourth quarters. All other required TLDs were collected in 1989.

C. w inf vi 1 The Technical Spec ifications re q uire that environmental sam P les 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 1989 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.

Section 3.6.21 of the Nine Hile 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 1989, 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 gamma in milk sample was not sent out by EPA as previously scheduled and subsequently was not analyzed.

-46

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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 ma]or portion of the total annual dose to members of the public.

Any possible impact as a result of site operations is extremely minimal when compared to the impact from natural background levels or weapons testing. It has been demonstrated that almost all environmental samples contain traces of radionuclides which are a result of weapons testing or naturally occurring sources (primordial and/or cosmic related). Whole body doses to man as a result of natural sources (naturally occurring radionuclides in the soil and lower atmosphere) in Oswego County account for approximately 56 mrem per year as demonstrated by control environmental TLD's. Possible doses due to site operations are a minute fraction of this particular natural exposure.

During 1989, the presence of one fission product radionuclide and two activation product radionuclides was noted in several environmental sample media. These media included air, fish, and food product (garden vegetables). Possible sources of the fission product radionuclide is past weapons testing and/or facility operations. Activation products detected in air samples were determined to be a result of operations at the site (JAFNPP). The impact, expressed as a dose to man, is minimal and is insignificant when compared to the natural background dose. In actuality, the impact from this sample medium (i,e. air samples) is not measurable because samples were obtained from an on-site location and no activity was measured at nearby, critical off-site locations.

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.

-48 C

i I I g 1

-49 0

8.0 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 10CFR Part 50, Appendix I", March 1976 (Revision 0).

2. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I", October 1977 (Revision 1).

3. U.S. Nuclear Regulatory Commission Regul atory Guide 4. 8, "Environmental Technical Specifications for Nuclear Power Plants", December, 1975.

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

Revision 1, November 1979.

National Council on Radiation Protection and Measurements (NCRP),

vir m 1 i , NCRP Report No. 50, 1976.

National Council on Radiation Protection and Measurements (NCRP), ~N ZLrrl r , NCRP Report No. 45, 1975.

7. National Council on Radiation Protection and Measurements (NCRP),

r i D , NCRP Report No. 52, 1977.

National Council on Radiation Protection and Measurements (NCRP),

NCRP Report No. 56, 1977.

9.

1 , ICRP Publication 29, 1979.

10 Eichholz, G.

Arbor Science Publishers, v

Inc., Ann f

Arbor, Michigan, 1976.

w, First Edi tion, Ann Ei senbud, Merri 1, 1 vi e 1 v' Second Edition, Academic Press, New York, NY 1973.

12. Thomas, C.W. etc al., i v F 1 f in N 1 r W

~T , September 26, 1976. (BNHL-2164) Battelle, Pacific Northwest Laboratories, U.S. ERDA, 1979.

13 Pochin, Edward E., im 1 r frm N 1 r Pwr Pr i a d Nuclear Energy Agency, Organization for Economic Co-Operation and Development, 1976.

-50

8.0 14 Glasstone, Samuel and Jordan, Walter H., 1 P w I vir 1 ff , First Edition, American Nuclear Society, La Grange Park, Ill., 1980.

15. U.S. Department of Health, Education, and Welfare.

f4ZgZ~. Bureau of Radiological Health, Rockville, Maryland 20852.

January 1970.

16. U.S. Department of Health and Human Services.

National Center for Devices and Radiological Health, Rockville, Maryland 20857. August 1983.

17. National Council on Radiation Protection and Measurements (NCRP), Lggi~ln

, NCRP Report No.

93, 1987.

-51

.0 DT B

-52

~, ~

1

R 0

1. Shoreline Sediment GSA 2/year 1 Indicator (2)

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

3. Surface Hater GSA H. Comp. 1 Indicator (4), 1 Control H-3 Qtr. Comp. 1 Indicator (4), 1 Control

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

NOTES:

Sampling and analysis program as required by the Technical Specifications.

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

-53

~ r

~ ri ri

,~

C.

l. Air Particulates GB Meekly 4 Indicator, 1 Control (1)

GSA M. Composite

2. Airborne I-131 GSA Meekly 4 Indicator, 1 Control (1)

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

GSA 2/Month I-131 (5) Annual ly r'.

4. Human Food Crops GSA, (3) site 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 . 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-si te locations of highest 0/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.

TABLE 3A CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/g (dry) g 2 sigma Sample Collection Langs Beach 4-24-89 <0.44 13.3tl.0 <0.040 <0.037 <0.041 1.1720.49 <0.26 <LLD (Control)* 10-30-89 0.12'.07 13.7%0.5 <0.053 <0.082 <0.047 1.25z0.32 0.42z0.07 <LLD Sunset Beach 4-24-89 <0.43 16.6tl.l <0.052 <0.035 0.342z0.051 2.34z0.91 0.6720.14 <LLD (Off-Site) 10-30-89 <0.50 18.0gl.3 <0.063 <0.051 0.254z0.047 2.5420.83 0.80z0.18 <LLD

'ample ~ required Results in units of by the Technical activity Specifications (Optional g~~jll dry weight sample location)

-55

TABLE 38 CONCENTRATION OF GAMMA EMITTERS IN SMORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) g 2 sigma Sample Collection D

Langs Beach 4-24-89 <438 13300z1050 <40 <37 <41 1170z487 <264 <LLD 10-30-89 119z69 13700i486 <53 <82 <47 1250z324 418z68 <LLD (Control)'unset Beach 4-24-89 <427 16600zl090 <52 <35 342t51 23402909 666z141 <LLD (Off-Site) 10-30-89 <504 18000gl290 <63 <51 254247 2540z834 800z184 <LLD

• Sample not required by the Technical Specifications tel

-56 0

TABLE 4A CONCENTRATION OF GAHMA EHITTERS IN FISH SAMPLES Results in units of pCi/g (wet) z 2 sigma GAHMA EMITTERS 6/08/89 Lake Trout <0.110 <0.047 4.57g0.24 <0.036 <0.038 <0.031 0.032~0.010 <0.075 <0.57 <LLD 6/06/89 Brown Trout <0.142 <0.054 5.14'.65 <0.037 <0.032 <0.035 <0.048 <0.094 <0.78 <LLD 6/06/89 White Sucker <0.077 <0.034 3.99z0.49 <0.032 <0.026 <0.028 <0.031 <0.056 <0.59 <LLD 9/19/89 Lake Trout ¹1 <0.122 <0.039 4.06z0.55 <0.037 <0.033 <0.030 0.030z0.016 <0.075 <0.62 <LLD 9/19/89 Lake Trout ¹2 <0.084 <0.034 3.38t0.43 <0.025 <0.021 <0.023 0.033z0.013 <0.046 0.42z0.20 <LLD 10/28/89 Walleye <0.048 <0.024 4.85z0.44 <0.023 <0.022 <0.024 0.020z0.154 <0.045 0.60z0.22 (1) 9/22/89 White Sucker <0.075 <0.039 4.90z0.52 <0.030 <0.025 <0.028 <0.030 <0.067 0.57z0.28 <LLD 9/22/89 Brown Trout <0.151 <0.048 5.12'.62 <0.043 <0.038 <0.035 <0.046 <0.102 0.5820.28 <LLD 6/07/89 Lake Trout <0.095 <0.040 4.5720.51 <0.030 <0.018 <0.025 0.043z0.015 <0.056 0.6820.32 <LLD 6/07/89 Brown Trout <0.110 <0.039 3.99z0.21 <0.035 <0.036 <0.032 0.020g0.010 <0.085 0.6120.23 <LLD 6/22/89 White Sucker <0.069 <0.028 5.26+0.49 <0.024 <0.025 <0.024 <0.028 <0.055 0.68z0.30 (2) 9/19/89 Lake Trout ¹1 <0.146 <0.060 4.49z0.58 <0.030 <0.039 <0.032 <0.039 <0.092 0.39z0.26 <LLD 9/19/89 Lake Trout ¹2 <0.122 <0.041 4.2520.51 <0.028 <0.032 <0.027 0.040g0.018 <0.070 0.9020.42 <LLD 10/23/89 Walleye <0.059 <0.024 5.88g0.51 <0.023 <0.022 <0.025 0.03020.015 <0.054 0.70z0.25 <LLD 9/19/89 Brown Trout <0.112 <0.043 5.64i0.60 <0.034 <0.024 <0.031 <0.039 <0.069 0.6220.27 <LLD 9/29/89 White Sucker <0.088 <0.040 6.05z0.58 <0.027 <0.032 <0.029 <0.032 <0.068 0.99i0.48 <LLD

( 1) AcTh-228 found at a concentration of 0.079z0.046 pCi /g (wet) . All others were <LLD.

(2) AcTh-228 found at a concentration of 0.088z0.048 pCi/g (wet). All others were <LLD.

-57

TABLE 4A (Continued)

CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/g (wet) z 2 sigma GAMMA EMITTERS 6/06/89 Lake Trout <0.091 <0.034 4.38i0.48 <0.024 <0.022 <0.024 0.039z0.024 <0.060 0.48z0.25 <LLD 6/08/89 Brown Trout <0.069 <0.030 4.6420.47 <0.023 <0.024 <0.024 0.030z0.015 <0.052 1.08z0.38 (3) 6/03/89 Hhite Sucker <0.122 <0.050 4.80z0.64 <0.037 <0.046 <0.035 <0.040 <0.092 <0.84 <LLD 9/19/89 Lake Trout ¹1 <0.132 <0.051 3.84z0.22 <0.039 <0.032 <0.033 0.024~0:009 <0.102 0.47t0.23 <LLD 9/19/89 Lake Trout ¹2 <0.115 <0.042 4.70g0.51 <0.031 <0.026 <0.026 0.04lz0.018 <0.061 0.84z0.33 (4) 9/19/89 Halleye <0.110 <0.040 6.25z0.60 <0.029 <0.029 <0.027 0.042z0.019 <0.074 1.27z0.41 <LLD 9/22/89 Smallmouth Bass <0.085 <0.037 4.64t0.49 <0.028 <0.028 <0.024 0.042z0.020 <0.056 0.60z0.31 <LLD 9/19/89 Hhite Sucker <0.102 <0.037 3.97t0.46 <0.027 <0.027 <0.023 <0.027 <0.061 0.51i0.22 <LLD (3) AcTh-228 found at a concentration of 0.068+0.040 pCi/g (wet). All others were <LLD.

(4) AcTh-228 found at a concentration of 0.143g0.089 pCi/g (wet). All others were <LLD.

-58

. 0

TABLE 48 CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) g 2 sigma GAMMA EMITTERS 6/08/89 Lake Trout <110 <47 45702236 <36 <38 <31 32gl 0 <75 <573 <LLD 6/06/89 Brown Trout <142 <54 51402650 <37 <32 <35 <48 <94 <784 <LLD 6/06/89 Hhite Sucker <77 <34 39902491 <32 <26 <28 <31 <56 <586 <LLD 9/19/89 Lake Trout ¹1 <122 <39 4060g550 <37 <33 <30 30zl 6 <75 <623 <LLD 9/19/89 Lake Trout ¹2 <84 <34 33802429 <25 <21 <23 33t13 <46 4242205 <LLD 10/28/89 Halleye <48 <24 48502436 <23 <22 <24 20zl5 <45 6052222 (1) 9/22/89 Hhi te Sucker <75 <39 4900z522 <30 <25 <28 <30 <67 5682282 <LLD 9/22/89 Brown Trout <151 <48 5120z625 <43 <38 <35 <46 <102 585i275 <LLD 6/07/89 Lake Trout <95 <40 45702511 <30

<18 <25 43tl5 <56 6852325 <LLD 6/07/89 Brown Trout <110 <39 39902209 <35 <36 <32 20z10 <85 608z232 <LLD 6/22/89 Hhi te Sucker <69 <28 5260z486 <24 <25 <24 <28 <55 6832303 (2) 9/19/89 Lake Trout ¹1 <146 <60 44902576 <30 <39 <32 <39 <92 3942259 <LLD 9/19/89 Lake Trout ¹2 <122 <41 42502507 <28 <32 <27 40zl8 <70 898z416 <LLD 10/23/89 Halleye <59 <24 58802509 <23 <22 <25 30zl5 <54 7042250 <LLD 9/19/89 Brown Trout <112 <43 5640g600 <34 <24 <31 <39 <69 615z274 <LLD 9/29/89 Hhite Sucker <88 <40 60502584 <27 <32 <29 <32 <68 987t476 <LLD

( 1) AcTh-228 found at a concentration of 79z46 pCi /kg (wet) . All other radionucli des were <LLD.

(2) AcTh-228 found at a concentration of 88z48 pCi /kg (wet). All other radionuclides were <LLD.

-59

TABLE 4B (Continued)

CONCENTRATION OF GAHMA EHITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) z 2 sigma GAMHA EHITTERS 6/06/89 Lake Trout <91 <34 4380g485 <24 <22 <24 39t24 <60 4832254 <LLD 6/08/89 Brown Trout <69 <30 46402467 <23 <24 <24 30zl5 <52 1080z384 (3) 6/03/89 Hhite Sucker <122 <50 4800z642 <37 <46 <35 <40 <92 <842 <LLD 9/19/89 Lake Trout ¹1 <132 <51 3840t223 <39 <32 <33 24z9 <102 472t226 <LLD 9/19/89 Lake Trout ¹2 <115 <42 4700z513 <31 <26 <26 4lzl 8 <61 837t331 (4) 9/19/89 Halleye <110 <40 62502595 <29 <29 <27 42zl 9 <74 1270z414 <LLD 9/22/89 Smallmouth Bass <85 <37 4640z486 <28 <28 <24 42t20 <56 599z308 <LLD 9/19/89 Hhlte Sucker <102 <37 3970z458 <27 <27 <23 <27 <61 509z215 <LLD (3) AcTh-228 found at a concentration of 68t40 pCi/kg (wet). All other radionuclides were <LLD.

(4) AcTh-228 found at a concentration of 143z89 pCi/kg (wet). All other radionuclides were <LLD.

-60 y

TABLE 5 CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma Location Nuclide January February March April May June 1

OSWEGO CITY K-40 101+30 237g42 65z13 175z45 222g41 66+14 WATER Ra-226 47z33 116g47 89z24 94g74 96+49 <76

• • Cs-134 <2.68 <3.43 <3.33 <3.86 <3.31 <3.97 Cs-137 <2.80 <3.71 <2.68 <4.28 <4.22 <3.25 Zr-9S <6.3 <8.7 <8.8 <9.5 <9.6 <8.7 Nb-95 <3.47 <4.20 <4.09 <5.54 <4.76 <5.30 Co-58 <2.84 <3.49 <3.38 <4.36 <3.71 <4.39 Mn-54 <2.86 <3.38 <3.14 <4.39 <3.95 <3.61 Fe-59 <6.0 <9.3 <8.2 <9.5 <10.3 <8.9 Co-60 <2.10 <3.34 <3 '6 <3.91 <3.88 <3.80

<9.1 Zn-65 <5.6 <7.2 <8.1 <8.6 <7.3 I-131 <8.4 <11.4 <8.5 <11.5 <12.7 <10.7 Ba/La-140 <6.6 <6.4 <11.2 <9.3 <8.1 <10.4 NINE MILE K-40 66+21 234z37 36zl2 203243 58g22 32+12 POINT UNIT I Ra-226 74g36 61g31 '5+25 143250 81+35 80+29 (INLET) Cs-134 <2.46 <2.78 <3.09 <3.58 <2.68 <4.38

• • Cs-137 <2.47 <3.04 <3.01 <4.18 <2.70 <3.48 Zr-95 <6,2 <7.2 <8.6 <9.5 <6.2 <8.4 Nb-95 <3.31 <3.59 <4.03 <4.53 <F 17 <5.40 Co-58 <2.70 <3.19 <3.17 <4.03 <3.14 <4.78 Mn-54 <2.64 <2.59 <2.97 <3.46 <2.56 <3.64 Fe-59 <6.4 <6.7 <7.7 <8.5 <7.7 <7.9 Co-60 <2.34 <3.09 <3.65 <3.09 <2.74 <4.25 Zn-65 <5.4 <5.4 <8.5 <7.5 <5.5 <11.3 I-131 <8.2 <8.8 <7 ' <11.0 <9.3 <11.6 Ba/La-140 <6.5 <7.0 <8.9 <7.4 <5.8 <12.3

• • Optional sample location. Sample Specifications.

~ required by the Technical

-61

TABLE 5 (Continued)

CONCENTRATION OF GAMMA EHITTERS IN SURFACE HATER SAMPLES Results in units of pCi/liter g 2 sigma Location Nuc 1 i de January February March April May June NINE MILE K-40 172g40 48gl 1 100+26 53g21 50+15 63+12 POINT UNIT 2 Ra-226 11.0279 96+22 61z33 108z4 62227 <75

( INLET) Cs-134 <4.30 <2.89 <2.41 <2.29 <4.87 <3.70

• • Cs-137 <4.44 <2.68 <2.62 <2.60 <2.88 <3.45 Zr-95 <11.1 <8.4 <6.0 <6.7 <8.8 <8.1 Nb-95 <6.09 <4.22 <3.02 <3.27 <5.06 <4.41 Co-58 <4.76 <3.62 <2.56 <2.83 <4.30 <4.11 Hn-54 <4.38 <3.17 <2.49 <2.32 <4.04 <3.95 Fe-59 <10.6 <7.5 <6.4 <5.4 <8.3 <6.7 Co-60 <4.28 <3.28 <2.77 <2.34 <4.54 <4.12 Zn-65 <10.2 <8.4 <5.2 <4.5 <10.7 <8.8 I-131 <13.6 <7.6 <7.8 <6.8 <9.8 <8.8 Ba/La-140 <11.3 <8.5 <6.1 <5.0 <11.3 <9.1 FITZPATRICK K-40 191g41 191+41 183+30 203+34 310+43 221+46 (INLET) Ra-226 95z47 322241 76x44 77g41 110+46 90+41 Cs-134 <3.07 <3.60 <2.50 <3.05 <2.89 <3.39 Cs-137 <3.56 <3.76 <2.75 <3.26 <3.01 <3.44 Zr-95 <9.6 <9.5 <7.0 <8.0 <7.6 <8.8 Nb-95 <4.83 <4.66 <3.46 <4.26 <3.79 <4.64 Co-58 <4.30 <4.00 <2.80 <3.21 <3.02 <3.96 Hn-54 <3.62 <3.97 <2.63 <2.84 <3.18 <4.08 Fe-59 <9.0 <8.7 <5.4 <6.9 <7.6 <8.6 Co-60 <4.15 <3.67 <2.28 <3.05 <2.98 <3.09 Zn-65 <7.6 <7.9 <5.2 <6.4 <6.4 <7.6 I-131 <0.5 <0.3 <0.3 <0.2 <0.5 <0.2 Ba/La-140 <8.6 <6.3 <5.9 <6.8 <5.2 <6.3 OSHEGO K-40 234+34 188+49 202+31 229+35 215+40 236+41 STEAM Ra-226 92z39 97g51 58z39 112+41 99z41 108+45 STATION Cs-134 <3.02 <3.61 <2.71 <2.72 <3.10 <2.82 (CONTROL) Cs-137 <F 15 <3.65 <3.01 <2.88 <3.24 <2.76 Zr-95 <8.8 <10.2 <8.4 <6.4 <8.9 <7.4 Nb-95 <3.91 <4.49 <3.75 <3.66 <4.53 <3.47 Co-58 <3.05 <4.70 <3.31 <2.73 <3.72 <2.83 Mn-54 <3.00 <3.88 <2.59 <2.61 <3.47 <2.58 Fe-59 <6.9 <7 ' <7.3 <5.6 <7.5 <6.5 Co-60 <2.93 <4.37 <2.76 <2.61 <3.75 <2.52 Zn-65 <6.0 <6.5 <5.6 <5.9 <7.0 <6.2 I-131 <0.5 <0.4 <0.4 <0.3 <0.4 <0.3 Ba/La-140 <5,1 <7 ' <6.9 <5.7 <7.7 <5.8

"* Optional sample location. Sample ~n required by the Technical Specifications.

• - Sample required by the Technical Specifications.

-62

4 TABLE 5 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE HATER SAMPLES Results in units of pCi/liter g 2 sigma Location Nuclide July August September October November December OSHEGO CITY K-40 169z48 185247 73+13 239z36 275+64 57+14 WATER Ra-226 158z68 149+54 105+31 89z35 <116 89+22

• • Cs-134 <3.98 <4.57 <3.98 <2.38 <4.17 <3.60 Cs-137 <4.41 <4.58 <2.88 <2.88 <4.50 <3.15 Zr-95 <12.1 <11.4 <9.2 <7.2 <11.0 <8.4 Nb-95 <5.79 <6.03 <5,03 <3.42 <5.35 <5.17 Co-58 <4.43 <5.62 <4.08 <3.06 <4.51 <4.42 Mn-54 <4.39 <4.43 <3.52 <2.63 <4.56 <3.78 Fe-59 <10.2 <11.5 <7.5 <F 1 <9.8 <8.3 Co-60 <3.66 <3.88 <4.31 <2.48 <4.69 <4.13 Zn-65 <9.4 <9.4 <9.5 <6.0 <8.4 <8.4 I-131 <14.3 <14.1 <10.7 <9.6 <13.2 <10.0 Ba/La-140 <10. 9 <10.3 <12.9 <5.4 <8.9 <11.1 NINE MILE K-40 160245 228+44 52222 73z24 177+52 69+26 POINT UNIT I Ra-226 87+45 149+58 78g29 58z28 <113 53+29 (INLET) Cs-134 <4.39 <3.70 <2.56 <F 51 <4.23 <3.00

• • Cs-137 <4.80 <3.79 <2.52 <2.64 <4.79 <3.06 2r-95 <11.6 <9.2 <6.7 <6.7 <10.8 <7.9 Nb-95 <6.04 <4.97 <3.01 <3.50 <4.89 <3.86 Co-58 <4.90 <3.96 <3.05 <3.33 <4.56 <2.91 Mn-54 <4.51 <4.00 <2.92 <2.86 <3.96 <3.15 Fe-59 <10.1 <9.1 <7.0 <6.8 <12.1 <6.3 Co-60 <4.09 <3.25 <3.01 <3.06 <3.45 <3.21 En-65 <9.3 <7.6 <5.5 <5.4 <9.4 <6.4 I-131 <12.9 <11.9 <7.8 <8.7 <13.5 <9.5 Ba/La-140 <7.6 <8.7 <5.9 <6.1 <10.1 <6.9

• • Optional sample location.

Specifications.

Sample ~ required by the Technical

-63

TABLE 5 (Continued)

CONCENTRATION OF GAMMA EHITTERS IN SURFACE HATER SAMPLES Results in units of pCi/liter z 2 sigma Location Nuclide July August September October November December NINE MILE K-40 101g29 49+14 46gl 3 84z14 262~38 259+36 POINT UNIT 2 Ra-226 73z30 78232 10lg28 72g28 68z33 68g34 (INLET) Cs-134 <2.80 <4.01 <4.07 <4. 11 <2.66 <3.09 Cs-137 <2.83 <2.95 <3.43 <2.98 <2.68 <3.25 Zr-95 <6.8 <8.8 <7.9 <9.1 <6.4 <8.3 Nb-95 <3.58 <4.67 <4.74 <4.61 <3.64 <4.26 Co-58 <3.12 <4.45 <4.09 <4.34 <2.71 <3.42 Hn-54 <2.95 <3.98 <3.50 <3.60 <2.80 <3.26 Fe-59 <7.4 <8.4 <9 ' <7.8 <5.8 <6.4 Co-60 <2.56 <4.86 <4.25 <4.31 <2.38 <3.09 Zn-65 <5.4 <9.6 <9.3 <8.9 <5.9 <6.5 I-131 <8.4 <9.1 <8.1 <9.9 <9.1 <11.6 Ba/La-140 <7.4 '<10. 6 <9.9 <10.8 <5.6 <6.2 FITZPATRICK K-40 182z30 48gl 4 214g46 257235 49' 2 239+35 (INLET) Ra-226 <87 117z29 160+77 84z35 83g24 99+39 Cs-134 <3.01 <4.60 <3.81 <2.79 <3.86 <3.09 Cs-137 <3.10 <3.08 <3.99 <3.32 <3.54 <3.19 Zr-95 <7.0 <8.7 <9.3 <6.8 <8.3 <8.5 Nb-95 <3.90 <4.22 <4.97 <3.63 <5.05 <3.64 Co-58 <3.11 <4.50 <4.09 <3.12 <4.38 <3.00 Hn <2.90 <3.41 <3.90 <2.49 <3.44 <2.82 Fe-59 <6.5 <8.4 <9.1 <6.5 <8.0 <7.0 Co-60 <3.16 <4.54 <3.40 <2.38 <4.36 <2.86 Zn-65 <6.8 <9.5 <7.1 <5.7 <9.9 <6.3 I-131 <0.2 <0.2 <0.3 <0.3 <0.4 <0.4 Ba/La-140 <6.1 <10 ' <7.5 <4.4 <10.2 <6.3 OSHEGO K-40 38gl 3 334g49 236+39 151g38 216+44 265+38 STEAM Ra-226 76z25 lllg41 <85 155+58 113255 87+40 STATION Cs-134 <3.87 <2.98 <2.70 <3.58 <3.66 <3.02 (CONTROL) Cs-137 <3.35 <3.02 <3.02 <4.29 <3.66 <2.94 Zr-95 <8.4 <7 ' <7.9 <9.8 <8.7 <8.0 Nb-95 <4.30 <3.84 <3.72 <4.88 <4.73 <4.29 Co-58 <4.46 <3.56 <3 '8 <3.76 <3.81 <3.26 Mn-S4 <3.59 <3.01 <2.64 <4 '8 <4.02 <3.14 Fe-59 <8.4 <7.0 <F 7 <9.7 <9.4 <6.3 Co-60 <3.87 <2.82 <2.65 <4.01 <3.82 <3.02 Zn-65 <10.0 <6.6 <5.3 <7.2 <7.1 <6.9 I-131 <0.2 <0.2 <0.4 <0.3 <0.4 <0.2 Ba/La-140 <9 ' <6.9 <4.7 <8.8 <7.5 <5.7 the Technical Specifications Sample reguired

• • Optional sample by Specifications.

location. Sample ~ reguired by the Technical

-64

TABLE 6 CONCENTRATION OF TRITIUM IN SURFACE WATER SAMPLES (QUARTERLY COMPOSITE SAHPLES)

Results in units of pCi /liter g 2 sigma Location Period Date Tritium JAF INLET

• First Quarter 12/29/88 03/31/89 350zllO Second Quarter 03/31/89 06/30/89 <150 Third Quarter 06/30/89 09/29/89 <110 Fourth Quarter 09/29/89 01/02/90 210g90

'c NHP-1 INLET ** First (}uarter 12/31/88 03/31/89 160290 Second Quarter 03/31/89 06/30/89 220z80 Third (}uarter 06/30/89 09/29/89 <160 Fourth Quarter 09/29/89 01/02/90 180z80 NMP-2 INLET " First Quarter 12/31/88 - 03/31/89 190290 Second Quarter 03/31/89 06/30/89 160z100 Third Quarter 06/30/89 09/29/89 280270 Fourth Quarter 09/29/89 01/02/90 210gl 10 OSWEGO CITY WATER First Quarter 12/31/88 03/31/89 310zl00 Second Quarter 03/31/89 06/30/89 200z60 Third Quarter 06/30/89 09/29/89 <200 Fourth (}uarter 09/29/89 01/02/90 250z80

~'SWEGO STEAH First Quarter 12/31/88 03/31/89 280gllO STATION

• Second Quarter 03/31/89 06/30/89 180t90 (CONTROL) Third Quarter 06/30/89 09/29/89 <140 Fourth Quarter 09/29/89 - 01/02/90 660z80 Samples required by the Technical Specifications.

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

-65

TABLE 7 NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES OFF SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 SIGMA LOCATION MEEK END DATE R-1 OFF* R-2 OFF* R-3 OFF* R-4 OFF* R-5 OFF*

89/01/09 0.020+0.002 0.018+0.002 0.018+0.002 0.017+0.002 0.020+0.002 89/01/16 0.019+0.002 0.019+0.002 0.018+0.002 0.021+0.002 0.018+0.002 89/01/23 0.021+0.002 0.018+0.002 0.018+0.002 0.018+0 '02 0.020+0.002 89/01/30 0.024+0.002 0.021+0.002 0.023+0.002 0.024+0.002 0.022+0.002 89/02/06 0.022+0.002 0.022+0.002 0.018+0.002 0.021+0.002 0.023+0.002 89/02/13 0.016+0.002 0.016+0.002 0.015+0.002 0.017+0.002 0.016+0.002 89/02/21 0.021+0.002 0.020+0.002 0.019+0.002 0.026+0.003 0.018+0 '02 89/02/27 0.019+0.002 0.017+0.002 0.019+0.002 0.018+0.002 0.019+0.002 89/03/06 0.020+0.002 0.017+0.002 0.016+0.002 0.018+0.002 0.018+0.002 89/03/13 0.021+0.002 0.023+0.004 0.017+0.002 0.015+0 '02 0.019+0.002 89/03/20 0.018+0.002 0.017+0.002 0.015+0.002 0.025+0.003 0.016+0.002 89/03/27 0.015+0.002 0.016+0.002 0.018+0.002 0.018+0.002 0.020+0.002 89/04/03 0.014+0.002 0.013+0.002 0.012+0.002 0.014+0.002 0.011+0.002 89/04/10 0.012+0.002 0.012+0.002 0.011+0.002 0.019+0.003 0.012+0.002 89/04/17 0.016+0.002 0.016+0.002 0.016+0.002 0.019+0.002 0.016+0.002 89/04/24 0.018+0.002 0.016+0.002 0.015+0.002 0.015+0.002 0.018+0.002 89/05/01 0.012+0.002 0.010+0.002 0.012+0.002 0.013+0.002 0.011+0.002 89/05/08 0.007+0.001 0.009+0.002 0.008+0.001 0.009+0.002 0.007+0.001 89/05/15 0.008+0.002 0.008+0.001 0.007+0.001 0.009+0.001 0.008+0.002 89/05/22 0.014+0.002 0.015+0.002 0.014+0.002 0.014+0.002 0.016+0.002 89/05/30 0.014+0.002 0.014+0.002 0.014+0.002 0.016+0.002 0.015+0.002 89/06/05 0.013+0.002 0.012+0.002 0.012+0.002 0.012+0.002 0.013+0.002 89/06/12 0.011+0.002 0.011+0.002 0.010+0.002 0.011+0.002 0.011+0.002 89/06/19 0.009+0.002 0.009+0.002 0.008+0.002 0.009+0.002 0.009+0.002 89/06/26 0.012+0.002 0.017+0.002 0.015+0.002 0.017+0.002 0.015+0.002 89/07/03 0.019+0.003 0.019+0.002 0.018+0.002 0.018+0.002 0.020+0.003 "AMPLE LOCATIONS REQUIRED BY TECHNICAL SPE CATIONS

'UMP INOPERATIVE

TABLE 7 (Continued)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES OFF SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 SIGMA LOCATION WEEK END DATE D-2 OFF E-OFF F-OFF G-OFF 89/01/09 0.016+0.002 0.018+0.002 0. 018+0. 002 0.018+0.002 89/01/16 0.016+0.002 0.024+0.003 0.018+0.002 0.020+0.002 89/01/23 0.018+0.002 0.017+0.002 0.020+0.002 0.018+0.002 89/01/30 0.023+0.002 0.023+0.002 0.024+0.002 0.016+0.002 89/02/06 0.022+0.002 0.021+0.002 0.025+0.002 0.019+0.002 89/02/13 0.016+0.002 0.017+0.002 0.017+0.002 0.016+0.002 89/02/21 0.020+0.002 0.020+0.002 0.017+0.002 0.017+0.002 89/02/27 0.018+0.002 0.020+0.002 0.020+0.002 0.018+0.002 89/03/06 0.017+0.002 0.019+0.002 0.020+0.002 0.016+0.002 89/03/13 0.022+0.003 0.019+0.002 0.020+0.002 0.017+0.002 89/03/20 0.011+0.002 0.018+0.002 0.014+0.002 0.015+0.002 89/03/27 0.022+0.003 0.018+0.002 0.020+0.002 0.017+0 '02 89/04/03 0.016+0.003 0.012+0.002 0.013+0.002 0.011+0.002 89/04/10 0.012+0.002 0.012+0.002 0.012+0.002 0.012+0.002 89/04/17 0.016+0.002 0.016+0.002 0.016+0.002 0.016+0.002 89/04/24 0.016+0.002 0. 014+0. 002 0.013+0.002 0.013+0.002 89/05/01 0.011+0.002 0.012+0.002 0.010+0.002 89/05/08 0.005+0.001 0.007+0.001 0.006+0.001 0.006+0.001 89/05/15 0.010+0.002 0.009+0.002 0.008+0.001 0.008+0.001 89/05/22 0.014+0.002 0.015+0.002 0.015+0.002 0.012+0.002 89/05/30 0.013+0.002 0.017+0.002 0.016+0.002 0.015+0.002 89/06/05 0.012+0.002 0.013+0.002 0.013+0.002 0.013+0.002 89/06/12 0.010+0.002 0.011+0.002 0.010+0.002 0.010+0.002 89/06/19 0.009+0.002 0.009+0.002 0.009+0.002 0.008+0.002 89/06/26 0.015+0.002 0 '14+0.002 0.018+0.002 0.015+0.002 89/07/03 0.017+0.002 0.019+0.003 0.019+0.002 0.017+0.002

• SAMPLE LOCATIONS REQUIRED BY TECHNICAL SPECIFICATIONS

• • PUMP INOPERATIVE

TABLE 7 (Continued)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES OFF SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 SIGMA LOCATION HEEK END DATE R-1 OFF* R-2 OFF* R-3 OFF* R-4 OFF* R-5 OFF*

89/07/10 0.015+0.002 0. 016+0. 002 0.015+0.002 0.015+0.002 0. 018+0. 002 89/07/17 0.017+0.002 0.015+0.002 0.014+0 '02 0.016+0.002 0.017+0.002 89/07/24 0.021+0.002 0.020+0.002 0.021+0.002 0.021+0.002 0.019+0.002 89/07/3 1 0.020+0.002 0.020+0.002 0.019+0.002 0.019+0.002 0.021+0.002 89/08/07 0.016+0.002 0.015+0.002 0.015+0.002 0.016+0.002 0.019+0 '02 89/08/14 0.018+0.002 0.019+0.002 0.018+0.002 0 021+0.002 0.020+0.002 89/08/21 0.015+0.002 0.016+0.002 0.012+0.002 0.015+0.002 0.016+0.002 89/08/28 0.019+0.002 0.017+0.002 0.019+0.002 0.015+0.002 0.016+0.002 89/09/05 0.020+0.002 0.018+0.002 0.021+0.002 0.018+0.002 0.019+0.002 89/09/11 0.026+0.003 0.022+0.002 0.022+0.002 0.026+0.003 0.022+0.002 89/09/18 0 '24+0.004 0.017+0.002 0.018+0.002 0.016+0.002 0.016+0.002 89/09/25 0.009+0.002 0.009+0.002 0.009+0.002 0.009+0.002 0.009+0.002 89/10/02 0.018+0.002 0.015+0 '02 0.016+0.002 0.018+0.002 0.013+0.002 89/10/09 0.015+0.002 0.013+0.002 0.013+0.002 0.015+0.002 0.014+0.002 89/10/16 0.020+0.002 0.019+0.002 0.021+0.002 0.019+0.002 0.021+0 '02 89/10/23 0.010+0.002 0 'il+0.002 0.010+0.002 0.009+0.002 0.009+0.002 89/10/3 0 0.041+0.003 0.033+0.003 0.041+0.003 0.037+0.003 0.039+0.003 89/11/06 0.018+0.002 0.016+0.002 0.015+0.002 0.017+0.002 0.014+0.002 89/11/13 0.014+0.002 0.015+0.002 0.015+0.002 0.038+0.015 0.014+0.002 89/11/20 0.016+0.002 0.017+0.002 0.019+0.002 0.018+0.002 0.017+0.002 89/11/27 0.017+0.002 0.018+0.002 0.018+0.002 0.021+0.002 0.017+0.002 89/12/04 0.016+0.002 0.019+0.002 0.016+0.002 0.018+0.002 0.019+0.002 89/12/11 0.022+0.002 0.019+0.002 0.021+0.002 0.019+0.002 0.022+0.002 89/12/18 0.022+0.002 0.022+0.002 0.020+0.002 0.021+0.002 0.023+0.002 89/12/2 6 0 '22+0.002 0.023+0.002 0.021+0.002 0.025+0.003 0.021+0.002 90/01/02 0.017+0.002 0.019+0.002 0.018+0.002 0.020+0.002 0.021+0.002

• SAMPLE LOCATIONS REQUIRED BY TECHNICAL SPECIFICATIONS

• UMP INOPERATIVE

TABLE 7 (Continued)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES OFF SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 SIGMA LOCATION HEEK END DATE D-2 OFF E-OFF F-OFF G-OFF 89/07/10 0.017+0.002 0.018+0.002 0.017+0.002 0.015+0.002 89/07/17 0.015+0.002 0.017+0.002 0.020+0.002 0.011+0.002 89/07/24 0.019+0.002 0.022+0.002 0.024+0.002 0.016+0.002 89/07/31 0.022+0.002 0.023+0.002 0.021+0.002 0.016+0.002 89/08/07 0.015+0.002 0.016+0.002 0.015+0.002 0.014+0.002 89/08/14 0.017+0.002 0.021+0.002 0.020+0.002 0.015+0.002 89/08/21 0.014+0.002 0.017+0.002 0.015+0.002 0.013+0.002 89/08/28 0.017+0.002 0.019+0.002 0.018+0.002 0.017+0.002 89/09/05 0.019+0.002 0.019+0.002 0.019+0.002 0.017+0.002 89/09/11 0.020+0.002 0.025+0.002 0.023+0.002 0.020+0.002 89/09/18 0.014+0.002 0.015+0.002 0.015+0.002 0.014+0.002 89/09/25 0.010+0.002 0.009+0.002 0.009+0.002 0.009+0.002 89/10/02 0.015+0.002 0.016+0.002 0.016+0.002 0.016+0.002 89/10/09 0.013+0.002 0.016+0.002 0,016+0.002 0.015+0.002 89/10/16 0.020+0.002 0.020+0.002 0.018+0.002 0.018+0.002 89/10/23 0.008+0.001 0.008+0.002 0.011+0.002 0.010+0.002 89/10/30 0.038+0.003 0.037+0.003 0.036+0.003 0.031+0.003 89/11/06 0.015+0.002 0.016+0.002 0.014+0.002 0.015+0.002 89/11/13 0.013+0.002 0.014+0.002 0.012+0.002 0.015+0.002 89/11/20 0.018+0.002 0.017+0.002 0.017+0.002 0.016+0.002 89/11/27 0.015+0.002 0.019+0.002 0.017+0.002 0.016+0.002 89/12/04 0.016+0.002 0.019+0.002 0.017+0.002 0.015+0.002 89/12/11 0.019+0.002 0.018+0.002 0.020+0.002 0.017+0.002 89/12/18 0.022+0.002 0.023+0.002 0.021+0.002 0.019+0.002 89/12/26 0.024+0.002 0.022+0.002 0.022+0.002 0.020+0.002 90/01/02 0.021+0.002 0.022+0.002 0.020+0.002 0.020+0.002

• SAMPLE LOCATIONS REQUIRED BY TECMNICAL SPECIFICATIONS

• • PUMP INOPERATIVE

TABLE 8 NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES ON SITE STATIONS GROSS BETA ACTIVITY pCi/m + 2 SIGMA LOCATION WEEK END DATE D1--ON G--ON H ON ION J--ON KON 89/01/10 0.015+0 .002 0.017+0.002 0.015+0.002 0.017+0.003 0.015+0.002 0.018+0.002 89/01/17 0.019+0 .002 0.019+0.002 0.019+0.002 0.023+0.003 0.018+0.002 0.020+0.002 89/01/24 0.017+0 .002 0.018+0.002 0.018+0.002 0.026+0.003 0.012+0.002 0 '17+0 '02 89/01/31 0.034+0 .006 0.023+0.002 0.024+0.002 0.024+0.002 0.019+0.002 0.026+0.003 89/02/07 0.018+0 .002 0.019+0.002 0.017+0.002 0.019+0.002 0.019+0.002 0.022+0.002 89/02/14 0.018+0 .002 0.020+0.002 0.018+0.002 0.019+0.002 0.019+0.002 0.019+0.002 89/02/21 0.019+0 .002 0.020+0.002 0.019+0.002 0.020+0.002 0.013+0.001 0.020+0.002 89/02/28 0.021+0 .002 0.021+0.002 0.021+0.002 0.019+0.002 0.016+0.002 0.020+0.002 89/03/07 0.018+0 .002 0.018+0.002 0.018+0.002 0.018+0.002 0.015+0.002 0.018+0.002 89/03/14 0.019+0 .002 0.022+0.002 0.021+0.002 0.019+0.002 0.016+0.002 0.017+0.002 89/03/21 0.017+0 .002 0.018+0.002 0.020+0.002 0.016+0.002 0.016+0.002 0.014+0.002 89/03/28 0.018+0 .002 0.017+0.002 0.017+0.002 0.019+0.002 0.018+0.002 0.017+0.002 89/04/04 0.014+0 .002 0.014+0.002 0.015+0.002 0.015+0.002 0.014+0.002 0.015+0.002 89/04/11 0.011+0 .002 0.010+0.002 0.013+0.002 0.012+0.002 0.012+0.002 0.013+0.002 89/04/18 0.017+0 .002 0.017+0.002 0.018+0.002 0.017+0.002 0.017+0.002 0-017+0.002 89/04/25 0.017+0 .002 0.019+0.002 0.014+0.002 0.017+0.002 0.017+0.002 0 '18+0.002 89/05/02 0.013+0 .002 0.015+0.002 0.012+0.002 0.012+0.002 0.013+0.002 0 '13+0.002 89/05/09 0.010+0 .002 0.011+0.002 0.007+0.001 0.011+0.002 0.010+0.002 0.010+0.002 89/05/16 0.008+0 .002 0.008+0.002 0.008+0.001 0.009+0.002 0.008+0.002 0.006+0.001 89/05/23 0.015+0 .002 0.015+0.002 0.015+0.002 0.014+0.002 0.011+0.002 0.014+0.002 89/05/30 0.016+0 .002 0.015+0.002 0.016+0.002 0.017+0.002 0.016+0.002 0.015+0.002 89/06/06 0.013+0 .002 0.016+0.005 0.014+0.002 0.014+0.003 0.012+0.002 0.012+0.002 89/06/13 0.011+0 .002 0.012+0.002 0.011+0.002 0.010+0.003 0.010+0.002 0.010+0.002 89/06/20 0.008+0 .002 0.009+0.002 0.009+0.002 0.008+0.002 0.008+0.002 0.008+0.002 89/06/26 0.014+0 .002 0.015+0.002 0.016+0.002 0.012+0.002 0.014+0.002 0.013+0.002 89/07/03 0.017+0 .002 0.017+0.002 0.016+0.002 0.015+0.002 0.020+0.002 0.016+0.002

C

'L*

TABLE 8 (Continued)

C I

NMP/JAF SITE

~

~

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES ON SITE STATIONS GROSS BETA ACTIVITY pCi/m + 2 SIGMA LOCATION WEEK END DATE D1--ON G--ON H ON I--ON J--ON KON 89/07/11 0.017+0.002 0.016+0.002 0.017+0 . 002 0.019+0.002 0.019+0.002 0.013+0.002 89/07/18 0.017+0.002 0.013+0.002 0.013+0 . 002 0.015+0.002 0.016+0 002 0.013+0.002 89/07/25 0.016+0.002 0.017+0.002 0.017+0 . 003 0.018+0.002 0.020+0.002 0.016+0.002 89/08/01 0.019+0.002 0.018+0.002 0.020+0 .002 0.022+0.002 0.024+0.003 0.018+0.002 89/08/08 0.016+0.002 0.015+0.002 0.014+0 .002 0.014+0.002 0.016+0.002 0.016+0.002 89/08/15 0.014+0.002 0.015+0.002 0.015+0 .002 0.016+0.002 0.016+0.002 0.016+0.002 89/08/22 0.016+0.002 0.017+0.002 0.019+0 .002 0.017+0.002 0.017+0.002 0.016+0.002 89/08/29 0.017+0.002 0.019+0.002 0.016+0 .002 0.018+0.002 0.016+0.002 0.014+0.002 89/09/05 0.018+0.002 0.019+0.002 0.018+0 .002 0.018+0.002 0.017+0 002 0.017+0.002 89/09/12 0.019+0.003 0.021+0.003 0.018+0 .002 0.017+0.002 0.018+0.002 0.018+0.002 89/09/19 0.014+0.002 0.014+0.002 0.012+0 .002 0.010+0.002 0.014+0 '02 0.013+0.002 89/09/26 0.010+0.002 0.008+0.002 0.008+0 .002 0.008+0.002 0.007+0.001 0.009+0.002 89/10/03 0.016+0.002 0.017+0.002 0.005+0 .001 0.016+0.002 0.018+0.002 0.017+0.002 89/10/10 0.013+0.002 0.013+0.002 0.012+0 .002 0.013+0.002 0.014+0.002 0.013+0.002 89/10/17 0.021+0.002 0.020+0.002 0.019+0 .002 0.022+0.002 0.016+0.002 0.017+0.002 89/10/24 0.010+0.002 0.009+0.002 0.011+0 .002 0.010+0.002 0.008+0.002 0.009+0.002 89/10/31 0.038+0.003 0.038+0.003 0.032+0 .003 0.040+0.003 0.038+0.003 0.034+0.003 89/11/07 0.021+0.002 0.022+0.002 0.021+0 .002 0.020+0.002 0.021+0.002 0.019+0.002 89/11/14 0.017+0.002 0.013+0.002 0.013+0 .002 0.014+0.002 0.012+0.002 0.012+0.002 89/11/21 0.015+0.002 0.020+0.002 0.023+0 .002 0.020+0.002 0.018+0.002 0.018+0.002 89/11/28 0.017+0.003 0.018+0.002 0.030+0 .002 0.019+0.002 0.018+0.002 0 '20+0.002 89/12/05 0.021+0.003 0.021+0.002 0.022+0 .002 0.018+0.002 0.018+0.002 0.017+0.002 89/12/12 0.016+0.002 0.022+0.002 0.024+0 .002 0.020+0.002 0.019+0.002 0.019+0.002 89/12/19 0.019+0.002 0.022+0.002 0.019+0 .002 0.021+0.002 0.019+0.002 0.022+0.002 89/12/26 0.007+0.001 0.022+0.002 0.025+0 .002 0.022+0.002 0.025+0.002 0.020+0.002 90/01/02 0.019+0.002 0.020+0.002 0.020+0 .002 0.015+0.002 0.018+0.002 0.016+0.002

TABLE 9 CONCENTRATION OF GAMMA EHITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-1 OFF-SITE STATION*

Results in units of 39-3gGUZ3 z 2 sigma Nuclides January February March April Hay June Co-60 <0.8 <0.8 <0.8 <1.0 <0.9 <0.9 Hn-54 <0.6 <0.9 <0.8 <1.2 <0:9 (1.2 Cs-134 <0.8 <0.9 <0.9 <1.0 <1.0 <1.0 Cs-137 <0.8 <1.0 <1.0 <1.3 <1.0 <1.2 Nb-95 <0.9 <1.4 <1.1 <1.4 (1.5 <1.2 Zr-95 <2.4 <2.5 (2.1 (2.8 <2.3 (2.6 Ce-141 <1.3 <1.4 <1.3 <1.5 (1.6 <1.9 Ce-144 <3.6 <4.6 <4.0 <5.2 <5.5 <6.4 Ru-106 <9.2 <9.7 <7.7 <9.8 (10.3 (11.5 Ru-103 <1.4 <1.3 <1.1 <1.4 <1.1 <1.7 Be-7 80zl3 67tl2 95gl3 63zl3 82+13 92+16 K-40 <19 13z9 <21 llg9 23+11 14+10 La-140 <2.7 <3.1 <2.5 <3.1 <2.2 <3.0 Ra-226 <18 <18 <18 12g9 22g12 <23 I-131 <3.0 <3.0 (3.1 <3.2 <2.9 <4.5 Others** (LLD <LLD (LLD <LLD (LLD (LLD Nuclides July August September October November December Co-60 <0.9 (1. 6 <2.5 (1.1 <1.4 <1.1 Mn-54 <0.9 <1.2 <2.1 <0.9 <1.1 <1.0 Cs-134 <0.9 <1.2 <3.6 <1.1 <1.0 <1.0 Cs-137 (1.1 <1.2 (1.5 <1.0 <0.9 <1 .2 Nb-95 <1.4 (1.0 <3.0 (1.5 <1.6 <1.8 Zr-95 <2.4 <1.9 <3.2 <2.5 <3.0 <2.7 Ce-141 <1.7 <1.7 <2.0 <1.9 <1.6 <1.9 Ce-144 <5.0 <5.5 <6.4 <4.9 <4.1 <5.2 Ru-106 <8.9 <9.0 <13.6 <7 ' (11.0 <9.5 Ru-103 <1.2 <1.5 <1.8 <1.2 <1.3 <1.6 Be-7 103gl4 81+15 , 90+8 76gl3 61+6 62+12 K-40 44+15 <29 <19 44g15 9+4 34+15 La-140 (1.8 (1.8 <4.7 <2.5 <5.3 (1. 8 Ra-226 <21 17gl0 <24 13z9 (16 <20 I-131 <3.0 <3.4 <4.7 <3.2 <2.9 <4.6 Others*" <LLD <LLD (LLD <LLD <LLD <LLD

• Location required Specifications.

by the Technical

"* Other plant related radionuclides.

-72

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-2 OFF-SITE STATION*

Results in units of M-3gGUm3 z 2 sigma Nuclides January February March April May June Co-60 <1.1 <1.0 <0.8 <0.7 <0.8 <0.8 Hn-54 <1.0 <1.1 <0.8 <1.2 <1.0 <0.9 Cs-134 <0.9 <1.0 <0.9 <1.3 <1.1 <0.8 Cs-137 <0.7 <1.0 <0.9 <1.2 <0.9 <0.7 Nb-95 <1.1 <1.2 <1,2 <1.7 <1.4 <0.8 Zr-95 <1.9 <2.8 <2.5 <3.3 <3.0 <1.6 Ce-141 <1.3 <1.6 <1.3 <1.7 <1.7 <1.4 Ce-144 <4.4 <4.4 <4.4 <6.0 <4.7 <4.0 Ru-106 <8.1 <9.5 <7.9 <6.9 <8.9 <6.6 Ru-103 <1.2 <1.2 <1.3 <1.1 <1 ~ 3 <0.8 Be-7 Blg12 72+12 80z13 78gl4 58zl2 94+13 K-40 31+12 32+14 <15 22g14 36+14 37+12 La-140 <2.3 <2.1 <1.6 <3.3 <4.4 <2.6 Ra-226 <18 <20 <19 <22 <21 <16 I-131 <2.4 <2.3 <3.5 <4.0 <3.4 <2.5 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.1 <1.4 <0.4 <0.8 <0.5 <1.7 Mn-54 <1.1 <0.6 <0.9 <1.3 <0.8 <1.0 Cs-134 <0.9 <1.0 <0.9 <1.0 <0.7 <1.4 Cs-137 <1.0 <1.0 <1.0 <1.0 <0.8 <1.5 Nb-95 <1.3 <1.6 <1.2 <2.0 <1.4 <2.6 Zr-95 <2.1 <2.4 <3.1 <2.4 <1.2 <3.2 Ce-141 <1.6 <1.6 <1.5 <1.8 <1.2 <2.2 Ce-144 <5.4 <4.8 <4.9 <5.5 <3.5 <6.6 RU-106 <11.1 <7.7 <8.4 <9.8 <7.5 <10.4 Ru-103 <1.2 <1.1 <1.2 <1.4 <0.9 <1.9 Be-7 98z15 85g13 73gl2 71+13 52+10 75+16 K-40 24+14 33+14 20+10 36+15 11+8 <25 La-140 <2.7 <1.8 <1.5 <2.6 <3.0 <2.6 Ra-226 <21 <20 <18 <22 <13 <26 I-131 <3.6 <3.1 <3.5 <4.0 <2.8 <5. 6 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Location required by the Technical Specifications.

"* Other plant related radionuclides.

-73

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-3 OFF-SITE STATION*

Resul ts in units of 3Q-3gGUZ3 z 2 sigma Nuclides January February March April May June Co-60 <0.9 <1.4 <1 ~ 0 <1.1 <1.0 <0.8 Mn-54 <1.1 <1.1 <0.6 <0.9 <1.2 <0.9 Cs-134 <0.9 <1.3 <0.7 <0.9 <1.3 <0.9 Cs-137 <0.7 <1.1 <0.8 <0.7 <1.5 <1.0 Nb-95 <0.9 <1.5 <1.0 <1.0 <1.9 <0.8 Zr-95 <2.4 <2.3 <1.8 <1.7 <4.0 <2.1 Ce-141 <1.3 <1.8 <1.3 <1.4 <2.1 <1.4 Ce-144 <3.8 <5.9 <3.5 <4.0 <6.8 <4.5 Ru-106 <7 ' <10.7 <6.4 <7.5 <9.2 <8.5 Ru-103 <1.0 <1.2 <1.0 <1.0 <1.7 <1.2 Be-7 68z12 64+14 78gll 68g11 87+17 82+13 K-40 <12 22zl4 30g10 39+12 18+13 25tl2 La-140 <1.4 <1.8 <1.8 <2.2 <5.6 <1.4 Ra-226 <17 <23 <14 19+9 <24 <19 I-131 <2.8 <4.0 <2.2 <2.5 <4.6 <3.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <0.8 <0.9 <1.5 <0.8 <1.3 <0.9 Hn-54 <0.7 <1.0 <1.5 <1.0 <'l. l <1.0 Cs-134 <1.0 <1.1 <2.1 <1.1 <1.1 <0.9 Cs-137 <1.0 <1.2 <1.2 <1.2 <1.2 <0.9 Nb-95 <1.0 <1.7 <2.2 <1.2 <1.6 <1.4 Zr-95 <2.0 <2.3 <3 ' <2.4 <3.0 <2.7 Ce-141 <1.5 <1.8 <1.6 <1.7 <1.4 <1.8 Ce-144 <4.7 <5.2 <5.2 <5.5 <4.3 <4.7 RU-106 <8.9 <11.6 <9.6 <9.2 <10.1 <9.2 Ru-103 <1 ~ 2 <1.2 <1.7 <1.4 <1.3 <1.1 Be-7 99+14 83z16 64+6 87+13 53+6 56+11 K-40 35+13 32gl3 12z5 32gl3 11+4 40+13 La-140 <1.7 <4.2 <2.8 <3.5 <4.2 <3.3 Ra-226 <18 <22 <16 <21 25+7 <19 I-131 <2.6 <3.5 <4.1 <3.8 <2.9 <3.4 Others"* <LLD <LLD <LLD <LLD <LLD <LLD

• Location required by the Technical Specifications.

• • - Other plant related radionuclides.

74

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-4 OFF-SITE STATION*

Results in units of M-3gQLz3 ~ 2 sigma Nuclides January February March April May June Co-60 <0.7 <0.6 <1.1 <0.8 <1.3 <1 .5 Mn-54 <1.1 <0.6 <1.0 <0.9 <1.3 <1.0 Cs-134 <0.8 <0.9 <0.9 <0.8 <0.9 <0.9 Cs-137 <1.3 <1.0 <0.8 <0.7 <0.9 <1.3 Nb-95 <1.4 <1.2 <1.3 <1.1 <1.8 <0.9 Zr-95 <2.2 <2.5 <2.8 <2.1 <3 ' <3.3 Ce-141 <1.9 <1.5 <1.7 <1.6 <2.3 <2.0 Ce-144 <5,8 <4.3 <4.7 <4.5 <6.4 <5.2 Ru-106 <9.8 <10.6 <9.3 <7.6 <13.1 <9.1 Ru-103 <1.4 <1.4 <1.4 <1.1 <2.0 <1.4 Be-7 93z16 78+13 85zl5 82g14 78z16 98+16 K-40 30zl5 46gl6 23g12 41gl6 39z16 16+11 La-140 <3.4 <2.6 <1.9 <3 ' <4.3 <4.5 Ra-226 <21 27gl 4 <20 19g10 <22 12+8 I-131 <3.5 <2.9 <3.5 <2.9 <5.5 <4.5 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.1 <1.2 <1.6 <0.5 <0.8 <1.2 Mn-54 <0.9 <0.9 <1.2 <1.1 <1.0 <1.1 Cs-134 <1.2 <1.0 <1.3 <1.2 <1.0 <1.1 Cs-137 <1.1 <1.1 <1.2 <1.0 <0.9 <1.4 Nb-95 <1.4 <1.3 <2.1 <1.5 <1.7 <1.8 Er-95 <2.5 <2.0 <3.2 <2.9 <2.7 <2.9 Ce-141 <1.8 <1.7 <2.4 <1.8 <1.9 <2.1 Ce-144 <5.6 <6.0 <6.3 <5.3 <5.0 <5.0 Ru-106 <10.0 <7.0 <11.7 <8.8 <8.3 <11.1 Ru-103 <1.2 <0.9 <1.7 <1.2 <1.4 <1.4 Be-7 99+15 81+13 83gl5 69gl3 70zl4 77+15 K-40 <27 36+15 22gl3 28gl4 44+16 32+14 La-140 <2.2 <1.8 <2.1 <3.1 <2.1 <3.5 Ra-226 <20 <21 <21 <22 <19 <23 I-131 <3.6 <2.8 <4.6 <3.9 <6.6 <4.7 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• - Location required by the Technical Specifications.

• • Other plant related radionuclides.

-75

~

'l'g pl&"Pl V

TABLE 9 <Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NHP AIR PARTICULATE SAMPLES R-5 OFF-SITE STATION (CONTROL)*

Results in units of M-3~i3 z 2 sigma Nuclides January February March April Hay June Co-60 <1.4 <1.6 <0.9 <0.9 <1.1 <1.2 Hn-54 <0.9 <1.4 <0,8 <1.2 <0.8 <1.5 Cs-134 <0 ' <1.0 <0.9 <1.0 <0.9 <l.l Cs-137 <1.0 <1.5 <0.9 <0.9 <0.8 <1.1 Nb-95 <1.2 <1.6 <1.1 <1.5 <1.2 <1.6 Zr-95 <2.5 <3.4 <2.1 <3.0 <2.2 <2.3 Ce-141 <1.6 <1 ~ 8 <1.2 <1.6 <1.5 <1.6 Ce-144 <4.9 <5.8 <3.5 <4.8 <4.7 <4.6 Ru-106 <6.8 <7.4 <7;6 <11.7 <8.4 <10.7 Ru-103 <1.2 <1.4 <0.9 <1.3 <1.2 <1.3 Be-7 86gl3 65z13 70+11 76z13 95z14 84+7 K-40 34g15 24tl4 T2g8 10'3.0 47g15 <14 La-140 <2.1 <3.2 <3.7 <1.8 <4.4 Ra-226 <20 <21 <14 <18 <19 <16 I-131 <3.2 <3.4 <3.3 <2.8 <2.7 <3.8 Others** <LLD <LLD <LLO <LLD <LLO <LLD Nuclides July August September October November December Co-60 <1.2 <1.9 <1.1 <1.0 <0.8 <1.9 Hn-54 <1.1 <1.7 <1.0 <0.8 <0.8 <1.1 Cs-134 <1.0 <1.8 <1.0 <1.0 <0.7 <1.3 Cs-137 <1.1 <1.6 <1.1 <1.2 <0.8 <1.3 Nb-95 <1.4 <2.3 <1.6 <1.2 <1 ~ 0 <2.0 Zr-95 <2.2 <4,5 <2.9 <2.7 <2.2 <3.0 Ce-141 <1 ~ 6 <1.9 <1.7 <1.8 <1.3 <2.3 Ce-144 <4.9 <5.7 <5.1 <5.2 <4.3 <5.7 Ru-106 <11.3 <12.5 <8.0 <10.3 <7.7 <13.5 Ru-103 <1.5 <1.6 <1.2 <1.6 <1.2 <1.7 Be-7 101gl6 87z8 68g12 88zl4 66gll 61+14 K-40 <19 18z5 31gl3 41zl4 35gll <34 La-140 <3.4 <4.0 <3.0 <2.9 <2.3 <4.2 Ra-226 <21 <21 <19 <21 <16 <25 I-131 <3.9 <4.0 <3.8 <5.0 <3.2 <4.5 Others** <LLO <LLD <LLD <LLD <LLD <LLD

• Location required

• • Other plant related radionuclides. Specifications.

by the Technical

-76

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NHP AIR PARTICULATE SAMPLES Dl ON-SITE STATION

• Results in units of M-3g@gm3 g 2 sigma Nuclides January February March April Hay June 1

Co-60 <1.6 <1.1 <0.9 <1.1 <0.8 <1.4 Hn-54 <1.1 <1.2 <0.8 <1.2 <1.0 <1.1 Cs-134 <1.5 <1.1 <0.8 <0.9 <1.0 <1.1 Cs-137 <1.0 <1.1 <0.7 <1.0 <0.9 <1.1 Nb-95 <1.6 <1.6 <1.1 <1.7 <1.2 <2.0 Er-95 <3;5 <3 ' <2.2 <2.3 <2.8 <3.0 Ce-141 <2.2 <1.1 <1.6 <1.7 <1.7 <2.0 Ce-144 <5.3 <3.4 <4.6 <5.4 <5.0 <5.8 Ru-106 <14.7 <9;6 <8.2 <9.1 <8.1 <13.1 Ru-103 <1.0 <1.2 <1.1 <1.1 <1.0 <1.7 Be-7 77gl5 66+6 85gll 63g12 80gl3 98z17 K-40 26gl4 13g5 41+12 4lgl5 30z13 19+13 La-140 <3.9 <2.6 <2.7 <2.3 <2.3 <4.4 Ra-226 20g12 <14 <17 <21 <20 <23 I-131 <2.5 <2.7 <3.4 <3 ' <3.2 <4.5 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.3 <1.3 <1.2 <1.3 <0.9 <0.9 Mn-54 <1.3 <0.9 <0.8 <1.0 <1.1 <0.4 Cs-134 <1.0 <1.2 <1.1 <0.9 <0.8 <0.9 Cs-137 <1.1 <1.2 <1.1 <1.0 <0.7 <0.6 Nb-95 <1.5 <1.5 <1.9 <1.3 <1.3 <1.0 Zr-95 <3.0 <3.1 <1.7 <2.6 <2.7 <2.6 Ce-141 <2.0 <2.0 <1.8 <1.5 <1 ~ 8 <1.4 Ce-144 <5.8 <5.8 <5.1 <5.2 <4.9 <3.7 Ru-106 <10.2 <10.5 <12.5 <7.1 <7.9 <8.1 Ru-103 <1.3 <'1.6 <1.6 <1.3 <1.1 <1.0 Be-7 87+14 83+14 89+16 63gl 2 68zl 2 47+10 K-40 57g18 54+17 27+14 50p15 30+12 17+10 La-140 <3.0 <3.4 <2.2 <1.3 <1.9 <2.2 Ra-226 <24 25g12 <19 <20 <17 <15 I-131 <3.3 <3.5 <4.2 <3.4 <3.4 <3.4 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location

• • - Other plant related radionuclides.

-77

~

' C "~

I * ,~

>~ " ~ a ~z ~ ~ rr ~

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G ON-SITE STATION

• Results in units of M-3g@lm3 z 2 sigma Nuclides January February March April May June Co-60 <1.2 <2.3 <0.8 <1.0 <0.9 <1.1 Mn-54 <1.0 <1.1 <1.0 <0.8 <1.1 <0.7 Cs-134 <1.0 <1.0 <0.7 <0.9 <1.0 <1.0 Cs-137 <0.9 <0.9 <0.7 <1.0 <1.0 <1.3 Nb-95 <1.2 <1.0 <1.0 <1.4 <1.3 <1.4 Zr-95 <2.4 <2.8 <2.2 <2.1 <1.7 <2.8 Ce-141 <1.4 <1.0 <1.1 <1.6 <1.7 <1.7 Ce-144 <4,4 <3.2 <3.6 <4.8 <5.1 <5.0 Ru-106 <8.6 <8.5 <8.6 <8.8 <6.6 <10.4 Ru-103 <1.2 <1.3 <1.2 <1.1 <1.3 <1.3 Be-7 94gl4 82g6 83+13 72zl2 86gl4 92+15 K-40 2lzll 15t5 12'2.4 39g14 29gl2 <21 La-140 <2.6 <3.7 <1.9 <2.7 <2.5 Ra-226 <17 9g5 <13 <19 <19 <20 I-131 <2.7 <2.5 <3.2 <3.5 <3.4 <4.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD

~,

Nuclides July August September October November December Co-60 <0.8 <1.1 <0.5 <0.9 <0.9 <0.7 Mn-54 <1 .2 <0.5 <0.8 <1.1 <0.9 <0.9 Cs-134 <1.0 <1.2 <0.7 <0.9 <0.8 <1.0 Cs-137 <1.1 <1.2 <0.8 <1.0 <0.8 <1.0 Nb-95 <1.4 <1.4 <1.3 <1.3 <1.3 <1.1 Zr-95 <3.1 <2.8 <1.8 <2 ' <2.5 <2.7 Ce-141 <1.6 <1.9 <1.2 <1.6 <1.4 <1.8 Ce-144 <5.4 <4.7 <3.4 <5,0 <3.9 <4.5 Ru-106 <10.6 <8.6 <8.2 <9.2 <7.0 <8.2 Ru-103 <1.3 <1.4 <1.1 <1.3 <1.1 <1.2 Be-7 76g14 88+14 73gll 70gl3 71+12 75+12 K-40 41+15 38gl5 39+12 30zl3 20+10 30+12 La-140 <2.2 <2.2 <2.3 <3.1 <2.6 <2.0 Ra-226 <23 <20 <16 <22 <17 <18 I-131 <3 ' <3.5 <2.9 <3.2 <3 ' <4.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD

" - Optional sample location

• • - Other plant related radionuclides.

-78

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES H ON-SITE STATION

• Results in units of M-3gCUZ3 z 2 sigma Nuclides January February Harch April Hay June 1

Co-60 <1.1 <1.1 <0.6 <1.4 <0.7 <0.9 Mn-54 <1.0 <1.2 <0.8 <1.0 <0.9 <0.7 Cs-134 <0.9 <1.1 <0.9 <0.9 <1.0 <0.9 Cs-137 <1.0 <1.3 <0.5 <1.0 <0.7 <0.8 Nb-95 <1.7 <1.9 <1.2 <1.2 <1.1 <1.1 Zr-95 <2.5 <2.9 <2.0 <3.0 <2. <2.3 Ce-141 <1.6 <1.6 <1.2 <1.6 7'1.6

<1.3 Ce-144 <5.0 <5.6 <3.5 <5.1 <4.1 <4.2 Ru-106 <9 ' <8.4 <8.1 <11.8 <7 ' <7.2 Ru-103 <1.2 <1.4 <0.8 <1.3 <1.2 <1.0 Be-7 78+13 61gl 3 78+13 64+12 79+12 85+13 K-40 31+12 14gl 2 <17 37zl 4 36g14 35gll La-140 <2.5 <3.2 <2.1 <2.2 <1.2 <1 ~ 6 Ra-226 <19 <24 <16 <20 <18 <15 I-131 <2.7 <3 ' <3.2 <2.4 <2.4 <2.5 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <0.8 <2.3 <0.9 <1.0 0.9'.7 <1.5 Mn-54 <1.4 <1.8 <1.0 <0.8 <1.1 <1.3 Cs-134 <1.1 <2.3 <0.9 <0.8 <0.9 <1.6 Cs-137 <1.2 <1.5 <0.8 <0.9 <0.6 <1.2 Nb-95 <2.0 <2.3 <1.2 <1.2 <1.4 <1.8 Zr-95 <3.5 <3.5 <2.9 <2.7 <2.3 <3.4 Ce-141 <2.0 <1 ~ 8 <1.4 <1.4 <1.5 <1.8 Ce-144 <7.6 <6.5 <4.3 <5.1 <3.9 <4.9 Ru-106 <11.8 <12.8 <8.4 <9.5 <7.7 <12.2 Ru-103 <2.2 <1.7 <1.3 <1.2 <1.0 <1.4 Be-7 75zl7 70z7 57+11 49gll 55+9 54g6 K-40 46+21 14+6 33+12 54g16 23+10 <17 La-140 <4.6 <4.1 <2.6 <2.7 <1.9 <5.0 Ra-226 <29 17g12 <19 <15 <18 12'3.8 <3.0 <3.7 I-131 <4.4 <3.6 <3.2 Others** <LLD <LLD <LLD (1) (2) <LLD

• - Optional sample location

• • Other plant related radionuclides.

(1) Zn-65 detected at a concentration of 2.77+2.02 E-03 pCi/m3.

(2) Zn-65 detected at a concentration of 24.9z3.71 E-03 pCi/m3.

-79

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EHITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES I ON-SITE STATION

• Resul ts in units of M-3gQlm3 z 2 sigma Nuclides January February March April May June Co-60 <1.8 <1.5 <1.2 <0.8 <1.2 <1.5 Hn-54 <1.5 <0.8 <0.6 <0.8 <1.3 <0.8 Cs-134 <1.2 <0.9 <0.8 <1.0 <0.9 <1.2 Cs-137 <1.4 <0.9 <0.6 <0.8 <1.2 <1.1 Nb-95 <2.1 <1.1 <1.1 <1.0 <1.3 <1.5 Zr-95 <3 ' <1.6 <2.8 <2.2 <2.2 <3.0 Ce-141 <1.9 <1.2 <1.4 <1.7 <1.5 <1.8 Ce-144 <5.6 <3.8 <4.0 <4.8 <4.2 <5.6 RU-106 <9.6 <9.4 <8.2 <6.6 <8.7 <9.3 Ru-103 <1.4 <1.0 <1.2 <1.1 <1.3 <'1.6 Be-7 88g16 65gl 2 90+13 61gl 1 73g14 74+13 K-40 <14 22gl0 45gl 4 <18 29+13 La-140 <1.9 8'1.4 <2.9 <2.3 <1.7 <2.5 Ra-226 31zl3 <16 <16 <18 <21 <24 I-131 <3.4 <2.8 <3.1 <2.9 <3.4 <3.8 Others"* <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.5 <1.0 <1.4 <1.7 <0.9 <1.1 Mn-54 <1.1 <1.1 <1.1 <1.0 <0.9 <1.4 Cs-134 <1.5 <1.1 <1.3 <1.1 <0.8 <0.9 Cs-137 <1.1 <0.9 <0.9 <1.1 <0.9 <1.1 Nb-95 <1.6 <1.2 <1.4 <1.2 <1.2 <1.1 Zr-95 <3.2 <2.6 <2.9 <3.0 <2.6 <2.8 Ce-141 <1.7 <1.9 <1.4 <1 ~ 7 <1.5 <1.6 Ce-144 <5.0 <5.8 <4.2 <5.3 <4.1 <4.3 Ru-106 <14 <9.9 <9.5 <11.1 <8.1 <10.2 Ru-103 <1.5 <1.1 <1.4 <1 ~ 2 <1.3 <0.9 Be-7 86z16 68+12 65z6 52zll 52g10 45+11 K-40 26gl 5 50zlS <14 49zl6 30gll <12 La-140 <3.0 <3.1 <4.9 <3.2 <1.7 <3.3 Ra-226 <23 15g9 <16 <22 <16 <19 I-131 <2.7 <3.4 <3.6 <3.2 <3.4 <4.2 Others** <LLD <LLD <LLD (1) (2) <LLD

• Optional sample location

• • Other plant related radionuclides.

(1) - Zn-65 detected at a concentration of 2.90z1.90 E-03 pCi/m3.

(2) Zn-65 detected at a concentration of 4.63g2.10 E-03 pCi/m3.

-80

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EHITTERS IN MONTHLY COMPOSITES OF NHP AIR PARTICULATE SAMPLES J ON-SITE STATION

• Results in units of 39-3gCUm3 z 2 sigma Nuclides January February March April May June Co-60 <1.3 <1.1 <0.6 <1.6 <1.7 <2.0 Hn-54 <0.8 <1.0 <0.8 <1.2 <1.2 <1.4 Cs-134 <1.1 <1.0 <0.7 <0.8 <1.0 <1.5 Cs-137 <1.1 <1.0 <0.8 <0.8 <1.2 <1.3 Nb-95 <1.4 <1.1 <0.9 <1.3 <1,4 <1.7 Zr-95 <2.7 <2.3 <1 ~ 8 <2.8 <3.4 <3.7 Ce-141 <1.5 <1.0 <1.3 <1.8 <1.7 <1.8 Ce-144 <4.6 <3.2 <3.7 <5.3 <5.6 <5.1 Ru-106 <8.8 <7 ' <6.0 <11.2 <11.3 <8.8 Ru-103 <1.1 <1.0 <0.9 <1.5 <1.5 <1.4 Be-7 61gl2 53z5 68zll 52g12 50+12 85g7 K-40 33+14 34+11 35+14 43+16 11+5 14'0.6 <4.0 <3.7 <3.0 La-140 <2.5 <3.2 Ra-226 <19 <13 <15 <20 <22 <17 I-131 <2.8 <2.2 <2.9 <3.0 <4.0 <3.5 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.1 <1.3 <1.5 <1.0 <0.9 <1.6 Mn-54 <1.0 <1.3 <1.1 <1.1 <0.9 <1.4 Cs-134 <1.2 <1.1 <0.9 <1.0 <0.8 <1.0 Cs-137 <1.2 <1.5 <0.7 <1.0 <0.7 <0.9 Nb-95 <1.8 <1.9 <1.1 <0.8 <1.1 <1.4 Zr-95 <3.4 <3.4 <2.8 <3.1 <1.9 <2.9 Ce-141 <1.9 <1.8 <1.6 <1.6 <1.6 <1.9 Ce-144 <6.0 <6.1 <3.9 <5.1 <3 ' <4.9 Ru-106 <11.0 <10.2 <8.8 <9.6 <7.9 <9.9 Ru-103 <1.5 <1 ~ 7 <1.1 <1.3 <1.0 <1.5 Be-7 88+14 57gl5 72+13 69+13 61+11 54+'I 4 K-40 47+16 52g19 14+10 57zl7 46gl4 29+14 La-140 <3.4 <3.0 <2.2 <2.3 <2.9 <1.9 Ra-226 <22 <25 <11+9 16+9 <14 <21 I-131 <3.6 <3.4 <2.6 <3.0 <5.4 <4.5 Others** <LLD <LLD <LLD <LLD (1) <LLD

• Optional sample location

"* - Other plant related radionuclides.

(1) Zn-65 detected at a concentration of 2.17+1.32 E-03 pCi/m3.

-81 Lgt g( ~ ~ 'lac* 'tATg'll tW g( ~ -il ) 4). ' ~

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES K ON-SITE STATION

• Results in units of 39-3gQlm3 z 2 sigma Nuclides January February March April May June Co-60 <1.4 <1.2 <0.8 <0.7 <1.7 <0.9 Mn-54 <1 ~ 3 <1.3 <1.0 <1.2 <1.9 <1.3 Cs-134 <1.2 <1.1 <1.1 <1.1 <1.2 <1.3 Cs-137 <1.2 <1.2 <1.1 <0 ' <1.6 <1.3 Nb-95 <1.9 <2.2 <1.1 <1.1 <1.8 <1.3 Zr-95 <2.8 <4.1 <2.0 <2.7 <2.9 <3.0 Ce-141 <2.1 <1.9 <1.6 <1.6 <2.2 <1.8 Ce-144 <5.0 <6.2 <4.8 <5.2 <7.1 <5.4 Ru-106 <12.2 <10.0 <8.8 <8.1 <10.1 <10.3 RU-103 <1.4 <1.2 <1.5 <1.3 <1.8 <2.0 Be-7 83+14 74+15 74+13 62z11 82+16 100+16 K-40 40gl6 40gl6 26z12 33zl2 <26 23g14 La-140 <4.4 <2.0 <3.2 <2.7 <2.2 <2.1 Ra-226 <19g12 <23 <17 16z8 <23 <25 I-131 <3.9 <3.8 <3.9 <3.4 <3.7 <4.3 Others** <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <0.6 <1.5 <0.7 <0.8 <0.9 <1.2 Mn-54 <0.9 <1.1 <0.7 <1.0 <0.8 <1.3 Cs-134 <1.0 <1.2 <0.7 <1.1 <1.0 <0.9 Cs-137 <1.1 <0.8 <0.9 <1.1 <1.2 <1.2 Nb-95 <1.7 <1.3 <1.1 <1.6 <1.2 <1.9 Zr-95 <2.3 <3.1 <2.6 <3.1 <1.9 <3.2 Ce-141 <1.6 <1.8 <1.6 <1.8 <1.4 <2.1 Ce-144 <5.6 <5.0 <4.1 <5.3 <4.0 <5.5 Ru-106 <9.9 <5.2 <7 ' <9.8 <7.7 <10.3 Ru-103 <1.3 <1.3 <1.2 <1.7 <1.2 <1.5 Be-7 74g14 85g18 70+11 44gl 2 49+10 51+13 K-40 27zl3 <14. 3 34+12 38+16 21+10 <33 La-140 <3.2 <3.4 <2.4 <2.8 <1.5 <2.3 Ra-226 <19 <22 <18 <24 <16 <20 I-131 <3.4 <3.2 <2.4 <3.5 <3.0 <4.3 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• - Optional sample location

"* Other plant related radionuclides.

-82

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NHP AIR PARTICULATE SAMPLES D2 OFF-SITE STATION Resul ts in units of ~1-3~i3 z 2 sigma Nuclides January February March April May June 1

Co-60 <1.0 <1.0 <1.3 <1.6 <0.9 <0.8 Hn-54 <1.4 <0.9 <1.2 <1.0 <1.1 <0.5 Cs-134 <1.0 <1.0 <1.2 <1.2 <1.0 <0.8 Cs-137 <1.0 <1.0 <1.1 <1.3 <1.1 <0.7 Nb-95 <1.4 <1.3 <1.3 <1.8 <1.3 <1.2 lr-95 <2.0 <1.7 <2.3 <3.2 <2.2 <2.9 Ce-141 <1.8 <1.4 <1.6 <1.6 <1.6 <1.5 Ce-144 <5.3 <4.8 <5.8 <5.6 <5.0 <4.5 Ru-106 <8.5 <8.7 <11.1 <9.4 <11.3 <7.1 Ru-103 <1.2 <1.1 <1.2 <1.4 <1.3 <0.9 Be-7 94gl5 68+12 78+14 70gl4 79+13 99+14 K-40 24gl 2 33g14 <32 25gl3 28+13 <18 La-140 <3.2 <2.8 <2.7 <2.6 <1.5 <1.5 Ra-226 <21 <18 <22 <23 <19 <18 I-131 <3. 1 <2.3 <4.0 <3.1 <3.3 <3.1 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <0.7 <0.8 <1.8 <1.8 <0.6 <1.2 Hn-54 <0.9 <1.0 <1.3 <1.2 <0.8 <1.0 Cs-134 <0.8 <1.1 <2.1 <1.4 <0.8 <0.9 Cs-137 <0.9 <0.9 <1.2 <1.4 <0.7 <1.1 Nb-95 <1.3 <0 ' <1.4 <2.0 <1.0 <1.4 Zr-95 <2.1 <2.7 <3.6 <3.5 <2.0 <3.0 Ce-141 <1.5 <1.7 <1.7 <2.0 <1.4 <1.6 Ce-144 <4.7 <5.0 <5.1 <6.2 <4.1 <4.9 Ru-106 <7.6 <11 ' <8.6 <11.4 <7.5 <8.1 Ru-103 <1.0 <1.3 <1.3 <1.7 <0.8 <1.3 Be-7 103213 84gl4 74g6 70gl4 57+10 67+12 K-40 31gl2 25gl3 10+5 <25 34+10 27+12 La-140 <2.1 <2.6 <3.5 <6.1 <3.2 <1.7 Ra-226 <18 <21 <17 <26 <16 <16 I-131 <3.0 <3.3 <3.2 <4.7 <3.4 <3.2 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location

• • Other plant related radionuclides.

-83

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES E OFF-SITE STATION

• Results in units of M-3~3 z 2 sigma Nuclides January February March April May June Co-60 <1.6 <0.6 <0.3 <1.2 <0.6 <1.0 Mn-54 <1.3 <0.9 <0.7 <1.1 <1.2 <0.7 Cs-134 <1.2 <0.9 <0.8 <1.1 <1.2 <0.7 Cs-137 <1.2 <0.9 <0.8 <0.8 <1.1 <0.9 Nb-95 <1.2 <1.1 <1.1 <1.7 <1.4 <0.9 Zr-95 <2.7 <1.5 <1.9 <2.1 <2.5 <2.4 Ce-141 <1.9 <1.5 <1.2 <1.7 <1 ~ 6 <1.4 Ce-144 <5.6 <4.2 <3.9 <5.7 <4.6 <4.2 Ru-106 <10 ' <8.4 <5.4 <9.0 <8.8 <8.7 Ru-103 <1 ~ 7 <1.2 <0.8 <1.3 <1.1 <1.2 Be-7 77g15 69gll 82zll 76g14 76+12 85+12 K-40 <30 31gl 3 27zl0 34zl 5 48gl 4 38gl 2 La-140 <4.2 <3.0 <2.4 <3 ' <1.8 <2.9 Ra-226 <24 14~8 16g8 <23 <18 <16 I-131 <3.8 <2.5 <3.1 <3.4 <3.2 <3.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.2 <1.3 <0.6 <1.3 <1.0 <1.9 Mn-54 <1.1 <1.2 <1.5 <1.1 <1.0 <1.3 Cs-134 <0.9 <1.0 <1.1 <1.0 <0.8 <1.2 Cs-137 <1.0 <1.0 <1 ~ 3 <1.2 <0.9 <1.5 Nb-95 <1.0 <1.1 <2.0 <1.7 <1.2 <2.0 Zr-95 <2.9 <2.3 <3.1 <3.3 <2.1 <2.8 Ce-141 <1.6 <1.6 <1.9 <1.9 <1.4 <2.1 Ce-144 <5.6 <5.7 <5.4 <5.2 <3.8 <6.2 Ru-106 <12.2 <9.3 <10.0 <10.8 <7.9 <13.1 RU-103 <1.5 <1.5 <1.2 <1.3 <1.2 <1.5 Be-7 98zl5 74zl2 86zl5 76zl4 66+12 51+13 K-40 24zl2 47g15 25+14 25zl2 9+7 <22 La-140 <1.6 <3.2 <3.6 <2.7 <3.9 <3.4 Ra-226 <21 <21 <24 <22 <24 12'4.3 I-131 <3.5 <3.0 <4.3 <4.4 <4.4 Others"* <LLD <LLD <LLD <LLD <LLD <LLD

• - Optional sample location

• • Other plant related radionuclides.

-84 Pf 'll,

) 0 p,)we t Pg ~ '. '

I p H ~ V ~ >> P,I/i

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES F OFF-SITE STATION

• Results in units of JQ-3gGUm3 z 2 sigma Nuclides January February March April Hay June Co-60 <1.2 <1.4 <0.9 <0.9 <1.2 <1.0 Hn-54 <0.4 <1.1 <1.1 <0.8 <1.0 <0.7 Cs-134 <0.7 <1.1 <0.9 <0.9 <F 1 <1.0 Cs-137 <0.7 <1,3 <0.9 <0.8 <0.9 <1 ~ 0 Nb-95 <1.1 <1.7 <1.3 <1.2 <1.5 <1.1 lr-95 <2.1 <2.6 <2.7 <2.2 <3.0 <2.6 Ce-141 <1.4 <1.8 <1.9 <1.5 <1.8 <1.6 Ce-144 <4.4 <5.5 <5.0 <3.6 <5.3 <4.4 Ru-106 <6.6 <10.0 <10.6 <8.7 <7.6 <9.4 Ru-103 <1.0 <1.6 <1.1 <1.1 <1.4 <1.3 Be-7 70g12 75g15 79gl3 60+11 88+14 79+12 K-40 32gl2 <29 32g14 12'2.3 Slzl6 29+12 La-140 <2.0 <2.0 <1.8 <2.9 <1.5 Ra-226 <17 <23 <18 <15 <21 <18 I-131 <2.7 <4.0 <4.0 <2.3 <3.8 <3.6 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October November December Co-60 <1.2 <0.6 <0.5 <0.8 <0.7 <1.3 Hn-54 <0.6 <0.9 <0.7 <0.9 <0.6 <1 ~ 1 Cs-134 <1.2 <1.2 <0.7 <0.8 <0.8 <1.0 Cs-137 <1.1 <1.4 <0.7 <0.9 <0.7 <1.2 Nb-95 <1.8 <1.4 <1.3 <1.2 <1.1 <1.3 Zr-95 <2.9 <3.0 <2,6 <2.6 <2.4 <3.1 Ce-141 <1.6 <1.6 <1.4 <1.8 <1.5 <1.7 Ce-144 <4.5 <4.9 <3.9 <5.6 <4.3 <3.5 Ru-106 <10.4 <11.0 <7.9 <12.0 <7.8 <11.7 Ru-103 <1.4 <1.2 <1.1 <1.1 <1.2 <1.3 Be-7 105+16 84+15 69gll 75gl4 64+11 72g14 K-40 21+14 <22 34gl 2 58g19 43+13 <22 La-140 <2.5 <3.5 <3.8 <1.9 <2.7 <1.9 Ra-226 <21 25+13 <15 <23 <17 <22 I-131 <3.6 <3 ' <3 ' <4.2 <3.8 <4.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• - Optional sample location

• • Other plant related radionuclides.

-85

I

\

\

~ r r r ~ 'I' ~~ ~ Nr \ ~ <<1 ~ r TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NHP AIR PARTICULATE SAMPLES G OFF-SITE STATION

• Results in units of M-3gQlm3 z 2 sigma Nuclides January February March April May June Co-60 <0.6 <1.4 <0.9 <1.8 <1.0 <1.4 Hn-54 <0.8 <1.2 <0.8 <1.0 <0.9 <1.1 Cs-134 <1.2 <1.3 <0.9 <1.3 <0.8 <1.0 Cs-137 <1.2 <1.3 <0.7 <1.1 <1.1 <0.8 Nb-95 <1.4 <1.9 <1.3 <1.3 <1.1 <1.4 Zr-95 <3.0 <3.0 <1.9 <2.8 <2.4 <2.9 Ce-141 <1.7 <2.0 <1.1 <1.7 <1.6 <1.6 Ce-144 <5.4 <4.9 <3.4 <5.6 <4.6 <5.0 Ru-106 <8.1 <10.0 <8.3 <12.1 <7 ' <10.5 Ru-103 <1.4 <1.3 <1.0 <1.6 <1.1 <1.3 Be-7 87+14 56+12 70zll 76gl 4 88zl3 94+7 K-40 32g14 22gl 4 20g9 2lgl 4 32g13 10+4 La-140 <2.2 <2.6 <2.8 <3 ' <3.2 <4.8 Ra-226 <20 <21 <14 <20 <18 <16 I-131 <3.6 <3.4 <2.7 <3.5 <2.6 <3.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD Nuclides July August September October Co-60 <1.0 <1.3 <1.5 <0.5 <1.2 <1 ~ 2 Hn-54 <0.7 <1.8 <1.2 <1.2 <1.1 <0.9 Cs-134 <0.9 <1 ~ 8 <1.4 <1.2 <1.0 <1.3 Cs-137 <1.1 <1.2 <1.3 <1.3 <1.0 <1.1 Nb-95 <1.4 <2.1 <2.2 <1.7 <1.7 <1.3 Kr-95 <2.3 <4.7 <2.9 <2.3 <2.9 <2.3 Ce-141 <1.6 <1.9 <1.7 <2.0 <2.1 <1.6 Ce-144 <4.7 <5.7 <4.2 <5.5 <4.9 <5.0 Ru-106 <9.4 <11.7 <10.3 <9.3 <10.7 <7.7 Ru-103 <1.2 <1.7 <1.4 <1.4 <1.4 <0.9 Be-7 98214 82z8 82z7 69zl3 66g13 45+12 K-40 31gl3 <18 54+17 <25 <14 10'5.4 La-140 <1-8 <5.7 <1.6 <3 ' <2.9 Ra-226 <18 22g7 <17 <22 <19 <17 I-131 <3.2 <3.4 <4.9 <4.0 <5.4 <4.5 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location

• • Other plant related radionuclides.

-86

TABLE 10 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES OFF SITE STATIONS I-131 ACTIVITY pCi/m~3 + 2 SIGMA LOCATION WEEK END DATE R-1* R-2* R-3* R-4* R-5* D-2 E 89/01/09 <0.009 <0.007 <0.008 <0.010 <0.010 <0.008 <0. 008 <0.007 <0.006 89/01/16 <0.008 <0.007 <0.007 <0.009 <0.009 <0.008 <0.012 <0.006 <0.007 89/01/23 <0.008 <0.006 <0.008 <0.010 <0.007 <0.009 <0.006 <0.010 <0 '12 89/01/30 <0.010 <0.009 <0.008 <0.008 <0.008 <0.009 <0.008 <0.011 <0.009 89/02/06 <0.012 <0.007 <0.007 <0.010 <0.007 <0.007 <0.010 <0.004 <0.008 89/02/13 <0.009 <0.007 <0.006 <0.008 <0.009 <0.006 <0.008 <0.007 <0.007 89/02/21 <0.010 <0.011 <0.007 <0.015 <0.008 <0.010 <0.007 <0.006 <0.009 89/02/27 <0.013 <0.007 <0.008 <0.006 <0.010 <0.007 <0.009 <0.007 <0.009 89/03/06 <0.011 <0.011 <0.007 <0.008 <0.007 <0.013 <0.007 <0.007 <0.009 89/03/13 <0.008 <0.019 <0.008 <0.005 <0.010 <0.011 <0.007 <0.011 <0.008 89/03/20 <0.009 <0.006 <0.008 <0.010 <0.007 <0.009 <0.008 <0.008 <0 '08 89/03/27 <0.011 <0.007 <0.008 <0.008 <0.010 <0.012 <0.010 <0.010 <0.011 89/04/03 <0.007 <0 008 F <0.007 <0.008 <0.006 <0.016 <0.007 <0.010 <0.008 89/04/10 <0.008 <0.006 <0.006 <0.013 <0.012 <0.008 <0.007 <0.009 <0.009 89/04/17 <0.009 <0.009 <0.008 <0.007 <0.007 <0.007 <0.007 <0.010 <0 '11 89/04/24 <0.009 <0.009 <0.010 <0.008 <0.008 <0.008 <0.009 <0.007 <0.008 89/05/01 <0.010 <0.008 <0.010 <0.005 <0.009 <0.007 <0.010 <0.008 89/05/08 <0.007 <0.009 <0.009 <0.006 <0.009 <0.008 <0.006 <0.008 <0.009 89/05/15 <0.012 <0.009 <0.008 <0.009 <0.011 <0.008 <0.007 <0.007 <0.014 89/05/22 <0.011 <0.010 <0.005 <0.013 <0.008 <0.010 <0.009 <0.014 <0.009 89/05/30 <0.009 <0.010 <0.007 <0.009 <0.012 <0.010 <0.009 <0.009 <0.011 89/06/05 <0.009 <0.011 <0.008 <0.009 <0.009 <0.013 <0.007 <0.009 <0.011 89/06/12 <0.012 <0.012 <0.009 <0.009 <0.010 <0.008 <0.010 <0.008 <0.013 89/06/19 <0.008 <0.008 <0.011 <0.007 <0.009 <0.011 <0.006 <0.011 <0.009 89/06/26 <0.011 <0.008 <0.010 <0.010 <0.007 <0.013 <0.007 <0.006 <0.007 89/07/03 <0.008 <0.010 <0.006 <0.009 <0.009 <0.008 <0.010 <0.008 <0.008

• SAMPLE LOCATIONS REQUIRED BY TECHNICIAL SPECIFICATIONS

• • PUMP INOPERATIVE

TABLE 10 (Continued)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES OFF SITE STATIONS I-131 ACTIVITY pCi/m~3 + 2 SIGMA LOCATION WEEK END DATE R-1* R-2* R-3* R-4* R-5* D-2 E 89/07/10 <0.007 <0.007 <0 ~ 007 <0.011 <0.008 <0.006 <0.006 <0.011 <0.009 89/07/17 <0.008 <0.012 <0.006 <0.010 <0.009 <0.007 <0.012 <0.012 <0.010 89/07/24 <0.014 <0.009 <0.010 <0.011 <0.012 <0.006 <0.009 <0.011 <0.008 89/07/31 <0.008 <0.011 <0.008 <0.008 <0.007 <0.009 <0.008 <0.010 <0.010 89/08/07 <0.010 <0.008 <0.010 <0.009 <0.013 <0.009 <0.008 <0.008 <0.009 89/08/14 <0.008 <0.008 <0.010 <0.013 <0.010 <0.010 <0 '10 <0.009 <0.007 89/08/21 <0.009 <0.013 <0.010 <0.008 <0.013 <0.008 <0.009 <0.012 <0.007 89/08/28 <0.009 <0.010 <0.010 <0.010 <0.011 <0.011 <0 '13 <0.010 <0.013 89/09/05 <0.014 <0.012 <0 '09 <0 013 <0.009 <0.009 <0.010 <0.009 <0.008 89/09/11 <0.022 <0.008 <0.010 <0.016 <0.012 <0.009 <0.008 <0.010 <0.009 89/09/18 <0.030 <0.011 <0.007 <0.009 <0.011 <0.009 <0.010 <0.007 <0 '12 89/09/25 <0.010 <0.009 <0.009 <0.009 <0.010 <0.011 <0.011 <0.008 <0.011 89/10/02 <0.012 <0.008 <0.012 <0.007 <0.012 <0.012 <0.007 <0.008 <0.009 89/10/09 <0.010 <0.011 <0.009 <0.009 <0.012 <0.006 <0.008 <0.007 <0.011 89/10/16 <0.011 <0.010 <0.013 <0.008 <0.008 <0.007 <0.011 <0.009 <0.007 89/10/23 <0.008 <0.008 <0.008 <0.010 <0.007 <0.007 <0.006 <0.009 <0.007 89/10/30 <0.008 <0.010 <0.008 <0.007 <0.009 <0.009 <0.009 <0.014 <0.008 89/11/06 <0.008 <0.011 <0.011 <0.012 <0.010 <0.010 <0.009 <0.010 <0.011 89/11/13 <0.011 <0.008 <0.010 <0.039 <0.013 <0.009 <0.008 <0.011 <0.009 89/11/20 <0.006 <0.007 <0.010 <0.007 <0.008 <0.011 <0.009 <0.007 <0.009 89/11/27 <0.011 <0.011 <0.011 <0.009 <0.010 <0.011 <0.012 <0.009 <0.011 89/12/04 <0.008 <0.011 <0.009 <0.010 <0.012 <0.008 <0.009 <0.010 <0.009 89/12/11 <0.012 <0.015 <0.013 <0.015 <0.011 <0.011 <0.009 <0.012 <0.015 89/12/18 <0.013 <0.012 <0.013 <0.014 <0.013 <0.008 <0.011 <0.010 <0.016 89/12/26 <0.012 <0.010 <0.008 <0.011 <0.011 <0.012 <0.010 <0.015 <0.011 90/01/02 <0.012 <0.011 <0.010 <0.013 <0.011 <0.009 <0.012 <0.011 <0.013

• SAMPLE LOCATIONS REQUIRED BY TECHNICAL SPECIFICATIONS

TABLE ll NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES ONSITE STATIONS I-131 ACTIVITY pCi/m"3 + 2 SIGMA LOCATION WEEK END Dl ON G ON H ON ION J ON KON 89/01/10 <0.009 <0.011 <0.012 <0. 012 <0. 008 <0.014 89/01/17 <0.011 <0.008 <0.006 <0.009 <0.007 <0.008 89/01/24 <0.008 <0.009 <0.007 <0.013 <0.008 <0.010 89/01/3 1 <0.028 <0.006 <0.006 <0.008 <0 '07 <0.011 89/02/07 <0.008 <0.007 <0.007 <0.007 <0.008 <0.008 89/02/14 <0.010 <0.008 <0.007 <0.006 <0.010 <0.008 89/02/2 1 <0.012 <0.006 <0.006 <0.008 <0.006 <0.007 89/02/28 <0.013 <0.007 <0.010 <0.008 <0.006 <0.014 89/03/07 <0.006 <0.009 <0.011 <0.007 <0.009 <0.008 89/03/14 <0.011 <0.008 <0.009 <0.010 <0.011 <0.011 89/03/21 <0.011 <0.009 <0.008 <0.008 <0.012 <0.007 89/03/28 <0.008 <0.006 <0.009 <0.008 <0.008 <0.009 89/04/04 <0.010 <0.008 <0.009 <0.011 <0.008 <0.007 89/04/11 <0.007 <0.007 <0.009 <0.007 <0.008 <0.009 89/04/18 <0.009 <0.005 <0.013 <0.009 <0 '15 <0.009 89/04/25 <0.013 <0.006 <0.008 <0.009 <0.009 <0.008 89/05/02 <0.009 <0.008 <0.004 <0.009 <0.006 <0.010 89/05/09 <0.009 <0.011 <0.008 <0.011 <0.012 <0.009 89/05/16 <0.006 <0.007 <0.010 <0.007 <0.009 <0.012 89/05/23 <0.012 <0.008 <0.008 <0.010 <0.010 <0.009 89/05/30 <0.012 <0.008 <0.008 <0.009 <0.009 <0.007 89/06/06 <0.010 <0.042 <0.009 <0.015 <0.012 <0.013 89/06/13 <0.013 <0.007 <0.008 <0.015 <0.013 <0.008 89/06/20 <0 008

~ <0.010 <0.009 <0.008 <0.009 <0.011 89/06/26 <0.010 <0.009 <0.008 <0.011 <0.009 <0.007 89/07/03 <0.012 <0.011 <0.014 <0.009 <0.011 <0.010

'IC TABLE 11 (Continued)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES ONSITE STATIONS I-131 ACTIVITY pCi/m"3 + 2 SIGMA LOCATION WEEK END D1 ON G--ON H--ON ION J ON KON

~ 4 ~

,C 89/07/11 <0.011 <0.010 <0.011 <0.010 <0.014 <0.011 1

89/07/18 <0.007 <0.009 <0.008 <0.007 <0.010 <0.008 89/07/25 <0.008 <0.011 <0.017 <0.008 <0.011 <0.011 89/08/01 <0.015 <0.009 <0.011 <0.011 <0.011 <0.012 89/08/08 <0.013 <0.010 <0.013 <0.011 <0.013 <0.010

'I 89/08/15 <0.010 <0.009 <0.008 <0.007 <0.009 <0.008 P

~

89/08/22 <0.013 <0.010 <0.014 <0.009 <0.011 <0.008 I ". 89/08/29 <0.012 <0.005 <0.010 <0.010 <0.009 <0.009 89/09/05 <0.013 <0.006 <0.008 <G.009 <0.009 <0.010 89/09/12 <0.011 <0.009 <0.009 <0.008 <0.009 <0.010 89/09/19 <0.009 <0.009 <0.010 <0.009 <0.009 <0.014 89/09/26 <0.012" <0.007 <0.007 <0.009 <0 F 008 <0 '12 89/10/03 <0.011 <0.011 <0.012 <0.012 <0.009 <0.011 89/10/10 <0.006 <0.009 <0.008 <0.012 <0.009 <0.011 89/10/17 <0.010 <0.007 <0.007 <0.009 <0.010 <0.008 89/10/24 <0.007 <0.009 <0.010 <0.008 <0.011 <0.007 89/10/31 <0.007 <0.008 <0.010 <0.010 <0.011 <0.008 89/11/07 <0.009 <0.009 <0.009 <0.008 <0.011 <0.006 89/11/14 <0.012 <0.008 <0.007 <0.006 <0.008 <0.009 89/11/21 <0.006 <0.011 <0.008 <0.009 <0.008 <0.009 89/11/28 <0.015 <0.006 <0.007 <0.009 <0.011 <0.008 89/12/05 <0.010 <0.010 <0.012 <0.008 <0.011 <0.007 89/12/12 <0.013 <0.010 <0.014 <0.013 <0.015 <0.011 89/12/19 <0.012 <0.008 <0.010 <0.011 <0.009 <0.013 89/12/26 <0.012 <0.010 <0.008 <0.012 <0.009 <0.012 90/01/02 <0.011 <0.010 <0.011 <0.012 <0.013 <0.012

TABLE 12A DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/standard month g 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location Harch June September December (Distance)(2) 3 Dl On Site 12.0z0.6 14. 5i2. 9 13.lz2.0 9.1gl.0 0.2 miles 8 4 D2 On Site 6.2'.6 5.9'.5 6.8'.6 4.8%0.7 miles 9 69'.4 E On Site 4.9'.6 5.4'.5 6.6'.5 4.8'.5 140'.4 5 miles 8 175 6

7' F On Site 4.4'.9 4.8t0.4 5.720.8 3.7'.6 0.5 miles 8 On Site 5.8'.2 210'.7 4.620.3 5.020.2 3.8t0.5 miles 8 8 R-5 Off S/te-Control 4.820.4 5.2'.3 6.'4'.4 4.7'.6 miles 9 250'6.4

. 9 Dl Off Site 4.6'.4 5.4'.3 5.3'.2 4.0'.5 miles 8 42'1.4 10 D2 Off Site 4.4'.3 5.0z0.3 S.Og0.2 3.4'.4 miles 8 117 80'.0 11 E Off Site 3.2'.2 5.2'.3 5.440.2 3.220.6 7.2 miles 8 Off Site 4.8'.3 160'.7 12 F 4.220.2 4.8z0.2 2.8z0.2 miles 8 190 13 G Off Site 4.7'.3 5.1g0.2 4.8z0.2 3.7'.5 5.3 miles 8 14'eHass Rd., SW Oswego-Control 4.8z0.5 5.6'.4 5.4'.4 2.9'.4 miles 8 225'2.6 15* Pole 66, W. Boundary-Bible Camp 4.2'.l 4.420.2 5.2'.1 2.lz0.3 miles 8 226'.9 18* Energy Info. Center Lamp Post, 5.6'.4 5.6'.2 3.8'.4 237'.4 SW. 3.8i0.3 miles 9 5.2'.3 6.3'.5 3.3'.3 265'.3 19 East Boundary-JAF, Pole 9 5.1t0.2 miles 9 23' On Site 6.220.5 6.6'.4 7.7z0.4 4.0z0.4 miles 6 81'.8 24 I On Site 5.lz0.4 5.4'.5 6.2'.5 5.2'.7 miles 8 70'.8 25 J On Site 4.9'.5 6.lt0.2 5.2'.5 4.2'.7 miles 8 110 98'.9 26 K On Site 4.5'.4 5.8t0.5 6.0z0.6 2.720.6 0.5 miles 8 of Switchyard, JAF 132'.4 27 N. Fence, N. 22.2t3.8 25.0g4.1 22.8t3.5 14.923.5 miles 8 N. Light Pole, N. of Screenhouse, JAF 42.lz6.1 60'.5 28 38.6t7.6 41.2z6.8 32.5z4.2 miles 8 68 29 N. Fence, N. of W. Side Screenhouse, JAF 26.8z6.7 29.2z8.2 29.2z6.0 21.3z4.6 0.5 miles 9 65'91

TABLE 12A (Continued).

DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/standard month t 2 sigma January April July ~

October Location Location 1989 Through Through Through Through (Direction and Number Location Harch June September December (Distance)(2) 30 N. Fence (NH) JAF 17.4tl .7 18.7'.2 17.F1.8 11.8zl.6 0.4 miles 8 57

.31 N. Fence (NH) NHP-1 6.9'.8 7.5i0.6 8.420.8 6.0z0.6 0.2 miles 8 Rad Haste, 10.6t1.4 11.6'.1 13.0zl.2 276'.2 39 N. Fence, NHP-1 10.2zl.4 miles 8 10.F1.9 7.0zl.5 292'.6 47 N. Fence, NE, JAF 10.5z1.4 70.3zl.4 miles 8 49'hoenix, NY-Control 3.7'.2 5.020.2 5.2'.4 4.2'.4 miles 8 69'9.8 Liberty Sts., E of OSS 4.0t0.2 6.2'.5 170'.4 51 & Bronson 5.0g0.3 4.0z0.7 miles 8 52 East 12th & Cayuga Sts., Osw. School 4.6'.4 4.8'.2 5.4'.7 3.3'.3 miles 8 233'.8 53 Broadwell & Chestnut Sts., Fulton H.S. 4.4'.3 5.4'.4 5.5'.3 3.6'.4 miles 8 227'3.7 54 Liberty St., & Co. Rte. 16, Hexico H.S. 4.4'.2 4.8z0.3 5.3i0.2 3.020.2 miles 8 183'.3 Substation & Co. Rt. 5 Pulaski 5.6'.2 3.0'.3 56't.

55 3.420.2 4.8z0.2 miles 115'3.0 Gas 8 104 New Haven Sch. (SE Corner) 4.6'.3 4.8t0.2 5.4'.3 4.5'.5 miles 8 75'.3 58* Co. Rt. 1A Alcan (E. of E. Entrance Rd.) 4.3'.2 5.0z0.4 5.4'.2 3.4'.5 miles 8 123'.1 75* Unit 2, N. Fence, N. of Reactor Bldg. 4.920.2 6.lz0.6 7.3'.6 4.6'.5 miles 220'.1 76'nit 77'nit 2, N. Fence, N. of Change House 4.6'.3 6.620.4 6.6'.3 4.5'.5 miles 8

8 5'.1 2, N. Fence, N. of Pipe Bldg. 6.4'.5 8.2'.6 8.lz0.9 5.6'.8 miles 8 25'.2 78* JAF, E. of E. Old Lay Down Area 5.2'.3 6.0z0.4 6.020.5 3.6'.6 miles 45'.0 79'o. Rt. 29, Pole ¹63, 0.2 mi. S. of Lake Rd. 4.420.2 5.0z0.3 5.8'.5 2.8z0.6 1 miles 8

8 90'.

4.6'.4 5.6'.4 81'iner Rd., Pole ¹16, 0.5 mi. H. ofofRt.Lake29 Rd. 4.420.2 80* Co. Rt. 29, Pole ¹54, 0.7 mi. S.

115'.4 5.620.3 3.220.4 miles 8 5.4'.5 5.2'.2 3.0z0.5 miles 8 133'.6 82* Hiner Rd., Pole ¹1 1/2, 1.1 mi. H. of Rt. 29 4.620.3 4.8'.2 6.0i0.4 2.9'.5 159'.6 miles 8 83* Lakeview Rd., Tree, 0.45 mi. N. of Hiner Rd. 4.620.2 (1) 4.2'.3 181'.2 6.320.4 miles 8 200'

TABLE 12A (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month % 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location March June September December (Distance)(2) 84>> Lakeview Rd. N., Pole ¹6117, 200 Ft. N. of Lake Rd. 4.5%0.2 5.7%0.3 6.0%0.3 3.2%0.4 1.1 miles 8 85>> Unit 1, N. Fence, N. of W. Side of 225'.2 Screen House 14.4%1.6 14.2%1.4 15.4%1.9 12.0%1.2 miles 8 86* Unit 2, N. Fence, N. of W. Side of 294'.1 Screen House 6.0%0.4 7.4%1.0 8.4%0.8 6.2%1.1 miles 8 315 Unit 2, N. Fence, N. of E. Side of 87'&>>

Screen House 5.6%0.4 6.4%0.8 7.8%1.0 4.6%0.7 0.1 miles 8 Hickory Grove Rd., Pole ¹2, 0.6 mi. 341'.8 N. of Rt. 1 4.4%0.2 5.0%0.3 6.2%0.4 5.2%0.7 miles 8 Leavitt Rd., Pole ¹16, 0.4 mi. of Rt.

97'.1 89* S. 1 4.8%0.3 5.6%0.2 6.4%0.5 3.7%0.5 miles 8 Rt. 104, Pole ¹300, 150 Ft. E. of Keefe Rd.

ill'.2 90* 4.8%0.2 4.9%0.3 6.0%0.2 3.5%0.5 miles 8 135'.8 91>> Rt. 51A, Pole ¹59, 0.8 mi. W. of Rt. 51 4.4%0.2 4.8%0.3 5.8%0.2 2.5%0.2 miles 8 92>> Maiden Lane Rd., Power Pole, 0.6 mi., 156'.4 S. of Rt. 104 4.8%0.4 6.3%0.4 6.8%0.3 4.0%0.5 miles 8 93* Rt. 53, Pole l-l, 120 Ft. S. of 104 4.6%0.2 5.3%0.2 6.0%0.2 3.0%0.3 mi les 8 183'.4 Rt. 1, Pole ¹82, 250 ft. E. of Kocher Rd.

205'.7 4.2%0.4 5.8%0.4 5.8%0.3 2.7%0.2 miles 8 94'5'6* Lakeshore Camp Site, From Alcan W. 223'.1 Access Rd., Pole ¹21, 1.2 mi. N. of Rt. 1 4.4%0.2 6.0%0.2 5.9%0.2 2.6%0.2 miles 8 Creamery Rd., 0.3 mi. S of Middle Rd., 237'.6 Pole 1 1/2 4.5%0.4 6.0+0.3 6.2%0.4 3.6%0.2 miles 8 97* Rt. 29, Env. Station R4, 200 Ft. N. 199'.8 of Miner Rd. 4.8%0.2 5.5%0.2 6.4%0.3 3.6%0.2 miles 8 143 98* Lake Rd., Pole ¹145, 0.15 mi. E. of Rt. 29 5.0%0.3 5.4%0.3 7.0%0.2 3.6%0.3 1.2 miles 8 101'93

TABLE 12A (Continued)

DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/standard month g 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location March June September December (Distance)(2) 99 NMP Rd., 0.4 miles N. of Lake Rd ., Env.

Station Rl Off-Site 4.4'.3 5.8z0.3 6.4i0.3 4.0z0.4 1.8 miles 8 100 Rt. 29 and Lake Rd., Env. Station R2 88'.

Off-Site 4.320.2 6.0g0.3 5.8'.2 3.8z0.3 1 miles 8 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env. 104'.5 Station R3 Off-Site 3.8'.3 5. lz0. 4 6.0'.4 3.9'.1 miles 6 102 EOF/Env. Lab, Oswego Co. Airport (Fulton 132'1.9 Airport), Rt. 176, E. Driveway Lamp Post 3.6'.2 5.5'.3 6.0z0.2 4.0z0.5 miles 8 103 EIC, East Garage Rd., Lamp Post 3.9'.2 6.2'.3 6.020.2 4.lz0.6 miles 8 175'.4 104 Parkhurst Road, Pole 148 1/2-A, 0.1 mi. 267'.4 S. of Lake Rd. 4.5'.1 5.4'.2 5.020.2 3.8z0.5 miles 8 105 Lakeview Road, Pole 6125, 0.6 mi. S. of 102'.4 Lake Rd. 4.420.2 6.020.4 5.4'.3 4.2'.4 miles 8 198 106 Shoreline Cove, E. of NHP-l, Tree on H.

Edge .5.0z0.2. 5.6'.4 6.7'.4 4.620.6 0.3 miles 8 107 Shoreline Cove, E. of NHP-l, Tree 30 274'.3 ft. South of TLD ¹106 5.4'.4 6.2'.3 6.820.3 4.8z0.5 miles 6 108 Lake Rd. Pole ¹142 300'ast of 272'.1 County Route 29 (S) 4.720.5 5.8z0.4 6.4'.4 4.4'.5 miles 8 Lake Rd. Tree 300'ast of County Route 29(N) 3.9'.3 5.6'.2 6.2'.7 104'.1 109 4.0z0.5 miles 8 103 110 Baldwinsville, NY Control Volza Residence 3.4'.1 5.220.5 5.2'.2 4;4'.5 26.4 miles 8

~ ~

ill Sterling, NY - Control Blasiak Residence 3.620.2 5.4'.7 5.2'.3 3.7'.5 miles 8 214 166'1.8 (1) TLD lost in field.

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

Technical Specification location.

TABLE 12B DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/quarterly period % 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location Harch June September December (Distance)(2) 3 Dl On Site 36.1%0.8 44.3%4.5 38.7%2. 9 26.8%1.5 0.2 miles 8 69 4 D2 On Site 18.1%0.9 18. 1%0.7 20.1%0.9 14.7%1.1 0.4 miles 8 E On Site 140'.4 5 14.4%0.8 16.5%0.7 19.0%0.7 14.4%0.7 miles 8 175 6 F On Site 13.0%1.3 14.7%0.6 17.0%1.1 10.8%0.9 0.5 miles 9 7f G On Site 13.3%0.5 15.7%0.3 16.8%0.3 11.3%0.7 miles 8 210'.7 250 8 R-5 Off Site-Control 14.3%0.6 15.4%0.5 19. 1%0.7 14.0%0.9 16.4 miles 8 42 9 Dl Off Site 13.6%0.5 16.2%0.4 15.8%0.4 12.0%0.8 11.4 miles 9 10 D2 Off Site 13.0%0 4 14.9%0.5 15. 1%0.3 10.0%0.6 miles 8 80'.0 ll

~

Off Site 117'.2 E 9.3%0.4 15.4%0.4 16.0%0.4 9.6%0.9 miles 8 160 12 F Off Site 12.4%0.4 14.2%0.4 14.2%0.4 8.2%0.3 7.7 miles 9 Off Site 190'.3 13 G 13.9%0.4 15.2%0.4 14.6%0.4 11.2%0.7 miles 8 225 14* DeHass Rd, SH Oswego-Control 14.2%0.7 17.0%0.5 15.0%0.6 8.6%0.5 12.6 miles 8 15* Pole 66, H. Boundary-Bible Camp 226'.9 12.4%0.2 13.6%0.4 15.4%0.2 6.4%0.5 miles 8 237 18* Energy Info. Center-Lamp Post, SH 11.2%0.4 17.5%0.6 16.6%0.4 11.%0.6 0.4 miles 8 265'.3 19 East Boundary-JAF, Pole 9 15.2%0.5 15.6%0.3 18.8%0.7 9.8%0.5 miles 8 81 23* N On Site 18.0%0.8 20.6%0.7 22.3%0.6 12.4%0.7 0.8 miles 8 70 24 I On Site 14.9%0.6 16.6%0.7 18.1%0.7 15.9%1.1 0.8 miles 8 98 25 J On Site 14.2%0.7 18.9%0.3 15.2%0.7 12.6%1.0 0.9 miles 6 110 26 K On Site 13.3%0.6 18.0%0.8 17.6%0.8 8.3%0.8 0.5 miles 8 132 27 N. Fence, N. of Switchyard, JAF 61.4%5.2 74.6%6.2 68.3%5.3 44.6%5.3 0.4 miles 8 28 N. Light Pole, N. of 60'.5 Screenhouse,JAF 116.4%8.4 115.4%11.3 123.2%10.1 97.4+6.3 miles 8 68

-95

TABLE 128 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period 2 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location March June September December (Distance)(2) 29 N. Fence, N. of H. Side Screenhouse, JAF 74.229.3 87.3212.2 87 .S29 .0 63.826.7 0.5 miles 8 N Fence 48.022.4 55.823.4 65'.4 30 (NH) JAF 53.022.6 35.622.4 miles 8 N. Fence (NW) NMP-1 20.421.2 22.820.9 57'.2 31 24.821,1 17.921.0 miles 8 276'.2 39 N. Fence, Rad. Haste, NMP-1 31.622.2 35.122.3 38.021.8 30.322.1 miles 8 292'.6 47 N. Fence, NE, JAF 29.021.9 32.522.9 30.822.1 20.922.2 miles 8 49>> Phoenix, NY-Control 11.020.3 14.620.3 15.620.S 12.820.5 miles 8 69'9.8 Liberty & Bronson Sts., E. of OSS 170'.4 51 11.820.4 15.020.3 18.620.7 12.021.1 miles e East 12th & Cayuga Sts., Osw. School 233'.8 52 13.720.6 14.420.3 16.121.0 10.020.5 miles 8 53 Broadwell & Chestnut Sts., Fulton H.S. 12.920.4 16.020.6 16.620.5 10.520.7 miles 8 227'3.7 Liberty St. & Co. Rt. 16, Mexico H.S.

183'.3 54 13.020.5 14.620.4 15.820.3 8.920.4 miles 8 55 Gas Substation, Co. Rt. 5, Pulaski 9.620.2 14.420.3 16.820.3 9.220.5 miles 115'3.0 8

Rt. 104 New Haven Sch. (SE Corner) 13.620.5 75'.3 56'8* 14.620.4 16.020.4 13.820.7 miles 8 Co. Rt. 1A Alcan (E. of Entrance Rd.)

123'.1 12.820.4 15.320.5 15.820.3 10.320.8 miles 8 75* Unit 2, N. Fence, N. of Reactor Bldg.

220'.1 14.620.3 18.520.9 21.420.9 13.620.7 miles 8 76* Unit 2, N. Fence, N. of Change House 5'.

13.720.5 20.020.6 19.520.5 13.420.7 1 miles 8 77* Unit 2, N. Fence, N. of Pipe Bldg.

25'.2 18.820.8 24.620.8 23.721.3 16.621.2 miles 8 JAF, E. of E. Old Laydown Area 45'.0 78'9* 15.720.4 18.220.5 17.520.8 11.021.0 miles 8 Co. Rt. 29, Pole ¹63, 0.2 mi. S. of Lake Rd.

90'.

13.020.2 15.020.4 17.020.6 8.420.9 1 miles 8 80* Co. Rt. 29, Pole ¹54, 0.7 mi. S. of Lake Rd.

115'.4 13.420.6 16.620.5 16.420.4 9.720.6 miles 8 Miner Rd., Pole ¹16, 0.5 mi. W. of Rt. 29 133'.6 81'2* 13.020.4 16.220.7 15.520.4 9.420.8 miles e Miner Rd., Pole ¹ 1 1/2, 1. mi . H. of Rt. 29 13.420.4 159'.6 1 14.620.3 17.920.6 8.820.7 miles 8 181'

TABLE 12B (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period z 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location March June September December (Distance)(2)

Rd., Tree, 0.45 mi. N. of Miner Rd. 13.4'.3 18.2'.5 12.920.5 1.2. mi les 8 200' 83'4'5* Lakeview Rd., N., Pole ¹ 6117, 200 Ft.

N. of Lake Rd. 13.3'.4 17.120.4 17.8'.6 9.6'.5 1.1 mi les Unit 1, N. Fence, N. of W. Side of Screen 225'.2 House 42.8g2.4 43.0z2.2 45.022.9 35.7zl.7 miles 8 86* Unit 2, N. Fence, N. of W. Side of Screen 294'.l 96'akeview House 17.6'.7 22.3zl.5 24.S'il.2 18.6zl.6 miles 6 87* Unit 2, N. Fence, N. Of E. Side of Screen 315'.1 House 16.6'.7 19.2zl.2 22.8z1.5 13.8gl.O miles 8 88>> Hickory Grove Rd., Pole ¹2, 0.6 mi. N. 341'.8 of Rt. 1 13.0g0.3 15.0g0.4 18.020.5 15.8z1.0 miles 8 Leavitt Rd., Pole ¹16, 0.4 mi. S. of Rt. 1 14.3'.5 11.3'.8 97'.1 89>> 16.8z0.3 18.920.6 miles 8 111 90* Rt. 104, Pole ¹300, 150 Ft. E. of Keefe Rd. 14.020.4 14.6'.3 17.5+0.3 10.720.9 4.2 miles 8 14.6'.4 135'.8 91* Rt. 51A, Pole ¹59, 0.8 mi. W. of Rt. 51 13.020.4 17.0z0.3 7.7z0.4 miles 8 Maiden Lane Rd., Power Pole, 0.6 mi. S.

156'.4 92'3*

of Rt. 104 14.2'.5 19. 2io. 5 19.620.4 12.0'.8 miles 6 183 Rt. 53, Pole l-l, 120 Ft. S. of Rt. 104 13.6'.2 15.8'.3 17.620.4 9.2%0.4 4.4 miles 8 12.6'.6 17.2'.6 8.2'.4 205'.7 94>> Rt. 1, Pole ¹82, 250 Ft. E. of Kocher Rd. -

17.lz0.5 miles 8 95>> Lakeshore Camp Site, From Alcan W. Access 223'.1 Rd., Pole ¹21, 1.2 mi. N. of Rt. 1 13.0g0.3 17.920.3 17.3'.3 8.0z0.2 miles 8 Creamery Rd., 0.3mi. S. of Middle Rd.,

237'.6 Pole 1 1/2 13.4'.6 16.8'.4 18.6'.6 11.0g0.4 miles 8 199'97

TABLE 12B (Continued)

DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/quarterly period z 2 sigma January April July October Location Location 1989 Through Through Through Through (Direction and Number Location March June September December (Distance)(2) 97* Rt. 29, Env. Station R4, 200 Ft. N.

of Hiner Rd. 14.2'.3 16.620.3 19.0z0.4 10.8'.4 1.8 miles 6 98* ¹145, 0.15 mi. E. of Rt. 29 20.4'.2 10.7'.4 143'.2 Lake Rd., Pole 15.1t0.4 16.3i0.5 miles 6 99 NHP Rd., 0.4 miles N. of Lake Rd., Env. 101'.8 Station Rl Off-Site 13.2'.5 17.2'.4 19.3'.4 12.2'.6 miles 8 100 Rt. 29 and Lake Rd., Env. Station R2 88'.1 Off-Si te 12.720.4 18.2'.5 17.5'.3 11.3'.4 miles 8 101 Rt. 29, 07 mi. S. of Lake Rd., Env. Station 104'.5 R3 Off-Site 11.0z0.4 15.lz0.6 18.0'.6 11.7'.2 miles 8 102 EOF/Env. Lab, Oswego Co. Airport (Fulton 132'1.9 Airport), Rt. 176, E. Driveway Lamp Post 10.5'.2 16.4'.4 18.lz0.3 11.8z0.8 miles 8 11.6'.4 18.2'.4 17.4'.3 175'.4 103 EIC, East Garage Rd., Lamp Post 12.220.9 miles 6 104 Parkhurst Road, Pole 148 1/2-A, O.l mi. 267'.4 S. of Lake Rd. 13.4'.2 16.420.2 15.0z0.4 11.2'.8 miles 8 102 105 Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd. 13.0g0.2 18.2'.6 16.420.5 12.4'.6 1.4 miles 8 106 Shoreline Cove, E. of NHP-l, Tree on Hest 198'.3 Edge 14.720.4 17.3'.6 19.8%0.7 13.720.8 miles 8 107 Shoreline Cove, E. of NMP-l, Tree 30 274'.3 ft. South of TLD ¹106 15.820.4 19.210.5 20.0t0.5 14.4'.7 miles 8 108 Lake Rd. Pole ¹142 300'ast of County 272'.1 Route 29 (S) 14.0z0.7 17.8z0.6 19.3'.6 13.4'.7 miles 8 104 109 Lake Rd. Tree 300'ast of County Route 29(N) 11.420.5 16.6'.4 18.6zl.l 12.2'.8 1.1 miles 8 103 110 Baldwinsville, NY Control Volza Residence 10.lz0.2 15. 410. 7 15.8'.4 13.2'.7 26.4 miles 8 ill Sterling, NY Control Blasiak Residence 10.7'.4 16.0zl.l 15.820.4 11.2'.8 miles 8 166'1.8 214'1)

TLD lost in the field.

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

Technical Specification location

TABLE 13 CONCENTRATION OF GAHHA EHITTERS IN HILK Results in units of pCi/liter g 2 sigma Location Nuclides 4-3-89 4-17-89 5-8-89 5-22-89 6-5-89 6-19-89 60 K-40 14502134 1440i156 14902184 15502144 1610z166 1510i66 Cs-134 <3.9 <7.5 <7.4 <4.,1 <5.& <7.6 Cs-137 <4.3 <7.1 <9.4 <6.1 <6.6 <6.0 Ba/La-140 <3 ' <5. 4 <9.1 <3.6 <5.7 <10.0 Ra-226 93i50 <184 <218 <146 132%75 <134 Others <LLD <LLD <LLD <LLD <LLD <LLD 55 K-40 1650zl67 1580gl61 1680z201 1620il 71 <312 1430i140 Cs-134 <6 ' <6.4 <9.0 <7.1 <5.1 <5.0 Cs-137 <8.3 <6.9 <7.6 <7.1 <6.2 <6.1 Ba/La-140 <4.5 <7.1 <8.5 <6.6 <5.9 <4.4 Ra-226 <1&0 <182 <220 <191 <166 <141 Others <LLD <LLD <LLD <LLD <LLD <LLD 50 K-40 1540il&5 1400i60 1570i137 15&Oil&8 1670i192 1650z168 Cs-134 <7.1 <5.9 <5.4 <7.7 <7.3 <6.4 Cs-137 <8.0 <5.6 <5.9 <9.7 <8.2 <6.5 Ba/La-140 <8.0 <6.0 <3.1 <8.5 <9.5 <4.7 Ra-226 <203 11&i32 <150 <221 <218 <178 Others <LLO <LLD <LLD <LLD <LLD <LLD K-40 1390i131 15802134 1570i164 16&0z141 1650il38 1640zl 37 Cs-134 <4.8 <5.3 <6.0 <5.4 <5.0 <5.2 Cs-137 <5.4 <6.2 <7.4 <5.7 <6.0 <6.2 Ba/La-140 <3.4 <4.1 <5.7 <3.8 <5.6 <4.7 Ra-226 88+58 <149 <174 <156 <160 <156 Others <LLO <LLD <LLD <LLD <LLD <LLD

-99

TABLE 13 (Continued)

\

~ .\

CONCENTRATION OF GAMMA EHITTERS IN MILK Results in units of pCi/liter z 2 sigma C'ocation Nucl ides 4-3-89 4-17-89 5-8-89 5-22-89 6-5-89 6-19-89 K-40 1520zl 77 1720t191 1460zl39 1440zl76 15902136 14&0zl80 Cs-134 <7.7 <7.2 <4.9 <7 ~ 3 <5.4 <8.2 Cs-137 <7.2 <8.9 <5.7 <9.8 <6.3 <8.4 Ba/La-140 <9.5 <7;0 <4.0 <8.0 <4.3 <9.0 Ra-226 <214 <1&8 <143 <210 121z73 <217 Others <LLD <LLD <LLD <LLD <LLD <LLD 16 K-40 1480gl29 1530zl 81 1600gl65 1520z66 173021 74 1660zl48 Cs-134 <4.8 <7.4 <5.4 <5.8 <6.6 <5.0 Cs-137 <5.5 <9.5 <6.2 <5.5 <7.1 <5.8 Ba/La-140 <4.3 <7.4 <6.5 <7.2 <5.4 <5.1 Ra-226 169g68 206zl01 182z98 108z48 .lllzl01 <137 Others <LLD <LLD <LLD <LLD <LLD <LLD 65* K-40 1570z161 1440tl 25 16302145 1650zl39 1460zl83 1500265 (Control) Cs-134 <6.3 <4.8 <5.8 <4.8- <8.7 .<6. 4 Cs-137 <7.4 <5.2 <6.2 <6-0 <10.0 <6.4 Ba/La-140 <5.0 <3.8 <5.8 <5.4 <7.0 <8.3 Ra-226 <180 118z72 <147 129i72 284zl54 163<4.6 Others <LLD <LLD <LLD <LLD <LLD <LLD

• -Techni cal Specification location

TABLE 13 (Continued)

CONCENTRATION Of GAHHA EHITTERS IN HILK Results in uni ts of pCi /liter z 2 sigma Location Nuclides 7-5-89 7-17-89 8-7-89 8-21-89 9-5-89 9-18-89 60 K-40 1720zl71 1620zl91 1530z161 15402145 1600zl90 1470z66 Cs-134 <6.7 <6.4 <6.6 <4.7 <7.9 <6.1 Cs-137 <6.6 <8.7 <7.9 <6.4 <7.9 <5.9 Ba/La-140 <7.3 <6.7 <4.0 <3.6 <6.8 <5.8 Ra-226 174g87 <220 <200 <137 <210 <123 Others <LLD <LLD <LLD <LLD <LLD <LLD 55 K-40 1480i67 1550zl66 1670zl47 1520gl38 14902144 1470z140

%J Cs-134 <6.5 <6.3 <4.1 <5.2 <4.6 <5.2

~ 1 Cs-137 <7.0 <7.7 <6.4 <5.4 <6.6 <6.3 Ba/La-140 <7.4 <6.1 <5.1 <5.0 <4.7 <5.2

'I Ra-226 <142 153z88 <141 <139 <124 10lg56

~ w Others <LLD <LLD <LLD <LLD <LLD <LLD 50 K-40 1510z184 1450i139 1680z70 1500i66 1560zl88 1620z169 Cs-134 <6.4 <5.0 <7.4 <7.0 <8.1 <6.8 Cs-137 <8.2 <5.6 <6.8 <6.2 <8.8 <7.1 Ba/La-140 <4.3 <5.4 <5.8 <7.9 <6.8 <5.2 Ra-226 <195 99z55 119257 <142 <207 <185 Others <LLD <LLD <LLD <LLD <LLD <LLD 7 K-40 1720zl41 1540z68 15402134 1520g165 15502165 1470zl83 Cs-134 <4.6 <7.3 <5.8 <6.5 <7.4 <7.3 Cs-137 <5.3 <6.4 <6.5 <8.0 <8.0 <8.9 Ba/La-140 <5.1 <6.4 <5.6 <6.1 <7.3 <6.0

~ ~

Ra-226 132gll3 90i48 <161 171+109 <190 193g147 s

Others <LLD <LLD <LLD <LLD <LLD <LLD

-101

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter g 2 sigma Location Nucl ides 7-5-89 7-17-89 8-7-89 8-21-89 9-5-89 9-18-89 K-40 1550z65 1600zl87 14902141 17402142 1460zl40 1590z68 Cs-134 <6.5 <6.8 <4.6 <5.6 <5.2 <7.3 Cs-137 <6.8 <9.3 <5.9 <6.2 <5.9 <6.2 Ba/La-140 <6.4 <9.0 <2.7 <5.3 <3.2 <9.0 Ra-226 <136 <212 <128 120z60 <135 87g33 Others <LLD <LLO <LLD <LLD (1) <LLD 16 K-40 1620gl68 1970g151 1580z67 16402139 1810g143 1530t66 Cs-134 <7.1 <4.2 <6.6 <5.8 <5.4 <6.3 Cs-137 <7.9 <5.6 <7.0 <6.0 <6.2 <5.5 Ba/La-140 <6.5 <4.8 <7.9 <5.6 <4.0 <8.3 Ra-226 <193 <147 96z49 <171 <156 <137 Others <LLD <LLD <LLD <LLD <LLO <LLD 65* K-40 1440gl 81 1570267 14402178 13802174 1370zl34 1610tl37 (Control) Cs-134 <7.3 <6.9 <7.8 <7.7 <7.2 <5.0 Cs-137 <7.2 <5.6 <9.0 <I0.2 <9.3 <5.7 Ba/La-140 <6.0 <9.1 <10.5 <6.3 <7.7 <5.3 Ra-226 Others

<192

<LLD 97z36

<LLD

/liter

<226 129z82 191 tl 34 <156

<LLD <LLD <LLD <LLD

'-Technical Specification location.

( 1) AcTh-228 found at a concentration of 23.9z12 .7 pCi . All other radionuclides were less than LLD for this sample.

%J

~~

TABLE 13 (Continued)

~ 1 f

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter -g 2 sigma t

Location Nuclides 10-2-89 10-16-89 11-6-89 11-20-89 12-4-89 12-18-89 60 K-40 1660zl39 16102144 1610zl 37 15502191 1750zl 42 1610zl 69 Cs-134 <4.7 . <5.8 <4.8 <8.8 <5.3 <7.2 Cs-137 <6.1 <6.2 <7.1 <9.4 <5.7 <6.0 Ba/La-140 <5 ' <5.7 <3.2 <11.4 <4.3 <6.1 Ra-226 174i74 <146 <159 <238 <154 <189 Others <LLD <LLD <LLD <LLD <LLD <LLD K-40 15302139 1670gl39 1620zl69 1730tl 42 1440zl88 1600zl96 Cs-134 <4.6 <5.1 <6.9 <5.6 <8.1 <9.3 Cs-137 <5.9 <5.7 <6.7 <4.9 <9.3 <9.4 Ba/La-140 <4.2 <6.0 <5.5 <4.7 <8.3 <9.4

~ 9 Ra-226 <126 <153 158zl00 <150 <229 <222 Others <LLD <LLD <LLD <LLD <LLD <LLD 50 K-40 1520il34 1570zl91 1470zl38 1670zl71 14502189 1550gl91 Cs-134 <4.2 <7.0 <5.9 <6.4 <8.4 <8.1 Cs-137 <5.8 <8.9 <5.6 <7.9 <7.7 <8.8 Ba/La-140 <4.1 <5.4 <4.6 <6.2 <7.4 <8.0 Ra-226 <146 <211 <138 <202 <223 <224 Others <LLD <LLD <LLD <LLD <LLD <LLD 7 K-40 1560i143 1470z187 1560tl38 1460il 39 1590zl91 1690gl41

'I Cs-134 <5.7 <8.3 <4.4 <5.1 <9.2 <5.0 Cs-137 <6.0 <9.6 <6.2 <5.7 <10.0 <4.2 Ba/La-140 <6.0 <9.9 <6.4 <5.4 <10.0 <3.1 Ra-226 <145 <213 <161 <140 <227 132259 Others <LLD <LLD <LLD <LLD <LLD <LLD

-103

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter z 2 sigma Location Nuclides 10-2-89 10-16-89 11-6-89 11-20-89 12-4-89 12-18-89 K-40 1360zl75 15302143 1730zl72 1590i144 1510z141 1530zl63 Cs-134 <7.8 <4.8 <6.9 <4.8 <5.9 <7.2 Cs-137 <8.3 <5.4 <8.2 <5.6 <6.2 <7.7 Ba/La-140 <7.4 <4.7 <5.9 <5.2 <5.4 <4.6 Ra-226 <209 <135 <196 <130 <136 283tl51 Others <LLD <LLD <LLD <LLD <LLO <LLD 16 K-40 1820zl74 1640zl69 1760zl52 1670g197 1610z146 1520z68 Cs-134 <6.2 <6.3 <5.0 <9.0 <5.0 <7.6 Cs-137 <7.1 <6.8 <7.5 <10.5 <5.0 <6.1 Ba/La-140 <7.4 <3.4 <5.1 <6.3. <4.6 <10.1 Ra-226 145z76 <190 <148 <229 105t63 <135 Others <LLD <LLO <LLD <LLD <LLD <LLD K-40 1610t143 1670zl 74 1510zl&6 1790zl47 1760z142 15&02144 65'Control) Cs-134 <5.2 <6.0 <8.0 <5.3 <4.7

<5.2 Cs-137 <5.9 <8.0 <10.7 <5.7 <5.2 <5.9 Ba/La-140 <5.2 <6.2 <6.6 <5.1 <2.7 <6.0 Ra-226 <145 <200 <229 <151 1&lz&1 <145 Others <LLO <LLD <LLO <LLD (2) <LLD

• -Technical Specification location.

(2) AcTh-228 found at a concentration of 24.&zl3.1 pCi/liter. All other radionuclides were less than LLD for this sample.

TABLE 14 CONCENTRATION OF IODINE 131 IN HILK (1)

Results in units of pCi/liter z 2 sigma Location 4-3-89 4-17-89 5-8-89 5-22-89 6-5-89 6-19-89 60 <0.18 <0.19 <0.15 <0.13 <0.14 55 <0.26 <0.16 <0.19 <0.15 <0.13 <0.16 65'0.15 50 7

<0.13

<0.16

<0.15

<0.16

<0.30

<0.28

<0.16

<0.14

<0.19

<0.13

<0.19

<0.16 4 <0.14 <0.17 <0.31 <0.20 <0.12 <0.20 16 <0.17 <0.16 <0.17 <0.16 <0.14 <0.18

<0.13 <0.16 <0.17 <0.22 <0.14 <0.21 Location 7-5-89 7-17-89 8-7-89 8-21-89 9-5-89 9-18-89 60 <0.13 <0.13 <0.23 <0.19 <0.16 <0.15 55 <0.12 <0.12 <0.15 <0.11 <0.15 <0.14 50 <0.15 <0.15 <0.18 <0.12 <0.18 <0.15 7 <0.18 <0.11 <0.15 <0.10 <0.19 <0.15 4 <0.26 <0.13 <0.22 <0.11 <0.17 <0.13 16 <0.20 <0.15 <0.15 <0.12 <0.18 <0.21 65* <0.29 <0.11 <0.15 <0.10 <0.15 <0.17

• Control result. Technical Specification location.

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

-105

TABLE 14 (Continued)

CONCENTRATION OF IODINE 131 IN MILK (1)

Results in units of pCi/liter g 2 sigma r

~ ~

Location 10-2-89 10-16-89 11-6-89 11-20-89 '12-4-89 12-18-89 60 <0.15 <0.14 <0.41 <0.33 <0.50 <0.34 55 <0.17 <0.18 <0.40 <0.37 <0.29 <0.22 r 'C 50 <0.19 <0.19 <0.42 <0.19 <0.50 <0.17

'C 7 <0.16 <0.17 <0.21 <0.38 <0.49 <0.32 4 <0.13 <0.15 <0.40 <0.44 <0.21 <0.19 16 <0.15 <O.I5 <0.31 <0.50 <0.23 <0.26 65* <0.14 <O.I5 <0.35 <0.30 <0.20 <0.36 Control result. Technical Specification location.

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

TABLE 15 MILK ANIMAL CENSUS 1989 Number on Number of (a) g~r~~(1 ) gp(~(3) pi c~~(3)

Scriba 1 3.0 miles None 16* 5.9 39C 2 8.0 ND 3 220'90'95'90'62'14'40'83' 4.5 4C 6 2.2 1C 26 1.5 ND 61 3.0 1C,12G 62 6.7 6G New Haven 8 9.2 None 9 5.2 40C 4* 7.8 100C 45 130'5'13'25'30'46'30'07' 8.0 10C 10 2.6 28C 5 7.2 49C ll7* 8.5 30C 5.5 62C 4

Mexico 12 11.5 20C 13 11.2 None 14 9.8 68C 15 10.8 None 17 10.2 1C 18 10.0 None 10.5 107'14'20'00'15'10'32'23'0'3'5'12'08' 19 40C 20 11.2 None 60* 9.5 30C 50* 8.2 I65C 55* 9.0 55C 21 10.5 72C 68 11.6 28C Richland Pulaski Oswego (SW)

Hannibal Sterling 17.

Volney 25 14'82'47'56' 9.5 None 70 9.4 25C;2G 66 7.8 70C;1G MILKING ANIMAL TOTALS: 1,210 Cows (including control locations)

MILKING ANIMAL TOTALS: 1,165 Cows (b)

(excluding control locations) 27 Goats (b)

-107 A

~ a% '( i ~ ~ ~

TABLE 15 (Continued)

MILK ANIMAL CENSUS 1989 NOTES:

C Cows G Goats ND s Milk sample ~~

Milk sample location location Did not wish to participate in the survey (1)

(2)

(3)

Goat is ~

References Figure 4 currently producing milk or any milk produced Degrees and distance are based on NHP-2 Reactor Building is utilized by the owner centerline.

None No cows or goats at that location. Location was a,previous location with cows and/or goats.

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

(b) Totals excluding control location results.

-108

TABLE 16 1989 RESIDENCE CENSUS Hap(1) Meteorological i n i n r <~>~D> an e~~~

N NNE NE ENE Lake Road A E 99' miles Lake Road B ESE 1.1 mi les County Route 29 C SE 1.4 miles Miner Road D SSE 1.6 102'30'63'70'07'34'38'.3 miles Miner Road E S 1.6 miles Lakeview Road F SSH 1.2 miles Bible Camp Retreat G SH 0.9 miles Bible Camp Retreat H HSH 0.9 miles H

HNH NH NNH This meteorological sector is over Lake Ontario. There is no residence within five miles.

(1) Corresponds to,Figure 3.

(2) Based on NMP-2 reactor centerline.

-109

TABLE 17A CONCENTRATION OF GAMHA EHITTERS IN FOOD PRODUCTS Results in units of pCi/g (wet) z 2 sigma Location Date Sample Type Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 AcTh-228 Others T 8-28-89 Beet Greens 0.19'.04 5.43z0.16 <0.013 <0.019 <0.017 0.37zO.ll <0.070 <LLD T 8-28-89 Squash Leaves 0.32z0.08 5.03z0.31 <0.014 <0.014 <0.014 0.25t0.15 0.080z0.030 <LLD T 8-28-89 Cabbage <0.13 3.40z0.31 <0.015 <0.014 <0.016 0.30z0.13 <0.064 <LLD K 8-28-&9 Strawberry Leaves 0.7&F0.12 4.42z0.35 <0.018 <0.015 <0.017 0.37t0.20 0.072z0.034 <LLD K 8-28-89 Squash Leaves 0.54z0.06 3.9&F0.22 <0.010 <0.009 0.009z0.007 0.22z0.10 0.041t0.020 <LLD L 8-28-89 Bean Leaves 0.36g0.07 3.02z0.25 <0.012 <0.011 <0.012 0.14'.ll <0.051 <LLD L 8-28-89 Cucumber Leaves 0.76t0.04 2.97z0.11 <0.011 <0.013 <0.011 0.3020.09 <0.047 <LLD L 8-28-89 Squash Leaves 0.6)g0.11 5.77z0.42 <0.018 <0.018 <0.018 0.35z0.16 0.06&z0.031 <LLD P 8-28-89 Collard Greens 0.1&F0.04 4.4420.16 <0.014 <0.019 <0.016 0.34z0.12 <0.064 <LLD P 8-28-89 Swiss Chard 0.10'.04 6.40zO 35 <0.011 <0.010 <0.012 0.17'.10 0.065z0.029 <LLD P 8-29-89 Beet Greens 0.1&F0.07 3.9220.31 <0.014 <0.015 <0.015 0.3320.14 0.069z0.040 <LLD e 9-05-89 Cabbage <0.09 3.4&F0.24 <0.010 <0.012 <0.012 0.26z0.10 0.05&z0.030 <LLD 0 9-05-&9 Squash Leaves 0.43z0.10 4.37z0.36 <0.015 <0.015 <0.016 0,,40t0.17 <0.066 <LLD 0 9-05-89 Cucumber Leaves 1.56z0.12 5.15'.31 <0.014 <0.013 <0.014 0.32z0.19 0.064z0.039 <LLD Y 9-05-89 Squash Leaves 0.54t0.05 4.39z0.15 <0.013 <0.018 <0.014 0.34z0.12 <0.067 <LLD Y 9-05-89 Pepper Leaves . 0.0&F0.04 7.4220.38 <0.011 <0.011 <0.011 0.30z0.15 <0.057 <LLD Y 9-05-89 Eggplant Leaves 0.2&F0.07 5.84g0.38 <0.015 <0.013 <0.016 0.40z0.16 0.043z0.02& <LLD H* 8-30-89 Swiss Chard <0.10 5.49+0.33 <0.013 '<0.012 <0.014 0.22g0.12 <0.051 <LLD H'* &-30-89 Squash Leaves 0.22t0.06 4.35z0.28 <0.013 <0.011 <0.012 0.2&F0.15 <0.050 <LLD

&-30-89 Cabbage <0.12 2.96z0.13 <0.013 <0.017 <0.016 0.3&F0.12 0.048<0.016 <LLD

' Control result All results in units of activity ~~ wet weight

-110

TABLE 178 CONCENTRATION OF GAMMA EHITTERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) t 2 sigma 1

Location Date Sample Type Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 AcTh-228 Others T 8-28-89 Beet Greens 187z45 5430zl62 <13 <19 <17 372+111 <70 <LLD T. 8-28-89 Squash Leaves 324g77 5030z313 <14 <14 <14 250gl46 80z30 <LLD T 8-28-89 Cabbage <126 3400z310 <15 <14-,. <16 <64 <LLD K 8-28-89 Strawberry Leaves 779zl21 4420z352 <18 <15 <17 3032133'672200 72z34 <LLD K 8-28-89 Squash Leaves 540263 39&oi223 <10 <9 220zl00 41g20 <LLD L 8-28-89 Bean Leaves 361t73 9'12 3020g252 <12 <11 139zllO <51 <LLD L 8-28-89 Cucumber Leaves 765t45 2970gl08 <1'1 <13 <11 29&t90 <47 <LLD L 8-28-89 Squash Leaves 614zl09 5770i424 <18 <.1 8 <18 3502156 6&z31 <LLD P 8-28-89 Collard Greens 185z44 4440zl56 <14 <19 <16 344gl 1 9 <64 <LLD P 8-28-&9 Swiss Chard 105245 64002347 <11 <10 <12 174g96 65229 <LLD P 8-29-89 Beet Greens 176t70 39202314 <14 <15 <15 32&zl35 69z40 <LLD Q 9-05-&9 Cabbage <87 3480z242 <10 <12 <12 265gl00 5&z30 <LLD Q 9-05-89 Squash Leaves 42&tl02 4370z355 <15 <15 <16 39&t173 <66 <LLD Q 9-05-89 Cucumber Leaves 1560zl18 51502311 <14 <13 <14 322gl92 64z39 <LLD Y 9-05-89 Squash Leaves 539z49 43902149 <13 <18 <14 336zl15 <67 <LLD Y 9-05-89 Pepper Leaves 80245 74204377 <11 <11 <11 229zl51 <57 <LLD Y 9-05-89 Eggplant Leaves 283t74 584023&0 <15 <13 <16 403tl56 43z28 <LLD M*

8-30-89 Swiss Chard <97 5490z328 <13 <12 <14 21&tl19 <51 <LLD 8-30-89 Squash Leaves 215t64 43502277 <13 <11 <12 284tl51 <50 <LLD 8-30-89 Cabbage <119 2960zl30 <13 <17 <16 382z115 4&zl6 <LLD

• Control result All results in units of activity wet weight

-111

, ~

TABLE 18 INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference Ho. EPA Result (1) Site Result (2)

Beta 3/89 Air Filter QA 89-031 62t5 6lz2 (3)

(pCi/filter) 60t2 60t2 Beta 8/89 Air Filter QA 89-090 Invalid (5)

(pCi/filter)

Tritium 2/89 Hater QA 89-012 27542356 3300zl00 (4)

(pCi/liter) 2900zl00 2800zl00 Tritium 6/89 Hater QA 89-063 4053z450 43002100 (4)

(pCi/liter) 4400z100 4300tl00 Tritium 10/89 Hater QA 89-119 3496g364 35002200 (4)

(pCi/liter) 3400z100 3400z100 Beta 4/89 Hater QA 89-032 57z5 50t2 (3)

~ p (pCi/liter) 52t3 48t2 Beta 10/89 Water QA 89-129 32t5 32tl (3)

(pCi/liter) 30zl 3lzl

-112

TABLE 18 (Continued)

INTERLABORATORY COHPARISON PROGRAH RESULTS S

Analysis Date Hedi um Site Reference No. EPA Result ( 1) Site Result (2)

I-131 2/89 Water QA 89-011 7.5'.05 8.0z0.8 (3)

(pCi /liter) 8.0z0.7 8.0z0.8 I-131 8/89 Water QA 89-082 83z8 8721 (3)

(pCi/liter) 88z3 90z3 Gamma (Cs-137) 8/89 Air Filter (pCi/filter)

QA 89-090 10z5 10'3) 12t4 llz5 Gamma 3/89 Air Filter QA 89-031 20z5 27z5 (3)

(Cs-137) (pCi/filter) 26z6 26z6 Gamma 4/89 Hilk QA 89-033 50z5 50z8 (3)

(Cs-137) (pCi/liter) 50z8 49z9 Beta 5/89 Water QA 89-042 50z5 5lz3 (3) 47z3 48z3 Beta 9/89 Water QA 89-105 6zl (3) 6zl 5tl

-113

TABLE 18 (Continued)

INTERLABORATORY COHPARISON PROGRAM RESULTS Ana1ys i s Date Medium Site Reference No. EPA Result (1) Site Result (2) r Gamma 2/89 .Hater QA 89-009 235z24 216zl8 (3)

(Cr-51) (pCi/liter) 225z35 1

225t27

• -I Gamma 2/89 Hater QA 89-009 159zl 6 14926 (3)

(Zn-65) (pCi/liter) 154t11 15lzl2 Gamma 2/89 Hater QA 89-009 178<18 143216 (3)

(Ru-106) (pCi/liter) 143t24 137z24 Gamma 2/89 Hater QA 89-009 10z5 8tl (3) I (pCi/liter)

(Cs-134) 9z2 10z2 Gamma 2/89 Hater QA 89-009 10z5 9z2 (3)

I (Cs-137) (pCi/liter) 10z3 8g2 Gamma 2/89 Water QA 89-009 10z5 10zl (3)

(Co-60) (pCi/liter) 10z3 9t3

~ ~

-114

lJ

~

TABLE 18 (Continued)

INTERLABORATORY COHPARISON PROGRAM RESULTS Analysis Date Hedium Site Reference No. EPA Result (1) Site Result (2)

I Gamma 6/89 Hater QA 89-058 3lz5 34z4 (3)

(Co-60) (pCi/liter) 33j:2

~ ~ 29z4 rl Gamma 6/89 Hater QA 89-058 16521 7 172t6 (3)

(Zn-65) (pCi/liter) 19&g14 175zl3 Gamma 6/89 Water QA 89-058 128zl3 127217 (3)

(Ru-106) (pCi/liter) 127z28 122~27 Gamma 6/89 Hater QA 89-058 39z5 37z2 (3) l (Cs-134) (pCi/liter) 38i4 37z4 Gamma 6/89 Hater QA 89-058 20z5 18i2 (3)

(Cs-137) (pCi/liter) 20z4 22+3 Gamma 10/89 Hater QA 89-106 59z6 64z6 (3)

(Ba-133) (pCi/liter) 55z6 58z7

-115

TABLE 18 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No. EPA Result (1) Site Result (2)

Gamma 10/89 Water QA 89-106 30z5 28z5 (3)

(Co-60) (pCi/liter) 29z5 32t5 Gamma 10/89 Hater QA 89-106 129tl 3 134232 (3)

(Zn-65) (pCi/liter) 136z36 135t43 Gamma 10/89 Hater QA 89-106 16lzl6 138t32 (3)

(Ru-106) (pCi/liter) 138236 155z43 Gamma 10/89 Hater QA 89-106 29z5 26z4 (3)

(Cs-134) (pCi/liter) 26t4 25t5 Gamma 10/89 Hater QA 89-106 59z5 59z6 (3)

(Cs-137) (pCi/liter) 59z6 60z6

-116

TABLE 18 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Oate Medium Site Reference No. EPA Result (1) Site Result (2)

Gamma 4/89 Water QA 89-032 20z5 18z2 (3)

(Cs-134) (pCi/liter) 16z4 18z4 Gamma 4/89 Water QA 89-032 20z5 19z4 (3)

(Cs-137) (pCi /liter) 19z4 20z5 Gamma 10/89 Hater QA 89-129 Sz5 5z2 (3)

(Cs-134) (pCi /liter) 4t2 5t2 Gamma 10/89 Hater QA 89-129 St5 5tl (3)

(Cs-137) (pCi/liter) 4g2 5g2

-117

TABLE 18 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS

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

(2)-Results reported as activity z the error (2 sigma).

(3)-Analyzed at the site environmental laboratory.

(4)-Analyzed at a vendor laboratory.

(5)-Intercompari son study determined to be invalid by EPA due to a problem with the I-131 deposited on the filter.

-118

TABLE 19 ENVIRONMENTAL SAHPLE LOCATIONS Sample Hap Figure Location Degrees and Medium Designation Number Description Distance ( 1)

Shoreline 05* Figure lA Sunset Bay 80't 1.5 miles Sediment 06 Figure lA Langs Beach, Control 230't 5.8 miles Fish 02* Figure lA Nine Hile Point Transect 315 at 0.3 miles 03'0*

Figure lA FitzPatrick Transect 55't 0.6 miles Figure lA Oswego Transect 235 at 6.2 miles Surface Water 03'8*

Figure lA FitzPatrick Inlet 70't 0.5 miles Figure 1A Oswego Steam Station Inlet 235't 7.6 miles 09 Figure lA NHP Unit 1 Inlet 305't 0.3 miles 10 Figure lA Oswego City Water 240't 7.8 miles

~, ~

Figure lA NMP Unit 2 Inlet 304't O.l miles

-119

TABLE 19 (Continued)

ENVIRONHENTAL SAHPLE LOCATIONS Sample Hap Figure Location Degrees and Hedium Designation Number Description Distance (1)

Air R-1* Figure 1A R-1 Station, Nine Hile Point Road 88 at 1.8 miles Radioiodine and Figure 2 R-2 Station, Lake Road 104 at 1.1 miles Particulates R-2'-3'-4*

Figure 2 R-3 Station, Co. Rt. 29 132't 1.5 miles Figure 2 R-4 Station, Co. Rt. 29 143't 1.8 miles R-5* Figure lA R-5 Station, Hontario Point Road 42't 16.4 miles Dl Figure 2 Dl On-Site Station 69't 0.2 miles

~ Figure 2 G On-Site Station 250 at 0.7 miles Figure 2 N On-Site Station 70't 0.8 miles Figure 2 I On-Site Station 98't 0.8 miles Figure 2 J On-Site Station 110 at 0.9 miles Figure 2 K On-Site Station 132't 0.5 miles Figure lA G Off-Site Station, Saint Paul Street 225't 5.3 miles

'120

TABLE 19 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS Sample Map Figure Location Degrees and Medium Designation Number Description Distance (1)

Air D2 Figure lA D2 Off-Site .Station, Rt. 64 117 at 9.0 miles Radioiodine And Figure lA E Off-Site Station, Rt. 4 160 at 7.2 miles Particulates Continued Figure lA F Off-Site Station, Dutch Ridge Rd. 190't 7.7 miles Thermo- Figure 2 Dl On-Site Station 69't 0.2 miles luminescent Dosimeters Figure 2 D2 On-Site Location 140't 0.4 miles (TLD)

Figure 2 E On-Si te Location 175't 0.4 miles Figure 2 F On-Si te Location 210't 0.5 miles Figure 2 G On-Site Station 250 at 0.7 miles Figure lA R-5 Off-Site Station 42 at 16.4 miles Figure lA Dl Off-Site Location &0't 11.4 miles 10 Figure lA D2 Off-Site Station 117't 9.0 miles

-121

TABLE 19 (Continued)

~ ~

ENVIRONMENTAL SAMPLE LOCATIONS g A.

Sampl e Map Figure Location Degrees and Medium Designation Number Description Distance (1)

Thermo- Figure lA E Off-Site Station 160't 7.2 miles luminescent Dosimeters 12 Figure lA F Off-Site Station 190't 7.7 miles (TLD)

Continued 13 Figure lA G Off-Site Station 225 at 5.3 miles 14* Figure 1A Southwest Oswego Control 226't 12.6 miles 15* Figure 1A West Site Boundary 237't 0.9 miles 18'9 Figure 2 Energy Information Center 265't 0.4 miles Figure lA East Site Boundary 81't 1.3 miles 23'4 Figure 2 H On-Site Station 70't 0.8 miles Figure 2 I On-Site Station 98't 0.8 miles 25 Figure 2 3 On-Site Station 110't 0.9 miles 26 Figure 2 K On-Site Station 132't 0.5 miles 27 Figure 2 North Fence, JAFNPP 60't 0.4 miles 28 Figure 2 North Fence, JAFNPP 68't 0.5 miles

TABLE 19 (Continued)

ENVIRONHENTAL SAHPLE LOCATIONS Sample Hap Figure Location Degrees and Hedium Designation Number Description Distance (1)

Thermo- 29 Figure 2 North Fence, JAFNPP 65't 0.5 miles luminescent Dosimeters 30 Figure 2 North Fence, JAFNPP 57 at 0.4 miles (TLD)

Continued 31 Figure 2 North Fence, NHP-1 276 at 0.2 miles 39 Figure 2 North Fence, NHP-1 292't 0.2 miles 47 Figure 2 North Fence, JAFNPP 69 at 0.6 miles 49'1 Figure 18 Phoenix, NY Control 170 at 19.8 miles Figure lA Oswego Steam Station, East 233 at 7.4 miles Figure lA Oswego Elementary School, East 227 at 5.8 miles 53 Figure 1B Fulton High School 183 at 13.7 miles 54 Figure 1A Hexico High School 115't 9.3 miles 55 Figure lA Pulaski Gas Substation, Rt. 5 75't 13.0 miles 56* Figure lA New Haven Elementary School 123't 5.3 miles 58>> Figure lA Co. Rt. 1 and Alcan 220't 3.1 miles

-123

TABLE 19 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS Sample Hap Figure Location Degrees and Hedium Designation 'Number Description Distance ( 1)

Thermo-luminescent 75>> 2 North Fence, NHP-2 5't O.l miles Dosimeters (TLD) 76* Figure 2 North Fence, NMP-2 25't 0.1 miles Continued 77* Figure 2 North Fence, NHP-2 45't 0.2 miles 78* Figure 2 East Boundary, JAFNPP 90 at 1.0 miles 79'0*

Figure 2 County Route 29 115't l. 1 miles 85'6'igure Figure 2 County Route 29 133 at 1.4 miles 81* Figure 2 Hiner Road 159 at 1.6 miles Figure 2 Hiner Road 181 at 1.6 miles 82'3*

Figure 2 Lakeview Road 200't 1.2 miles 84* Figure lA Lakeview Road 225't 1.1 miles Figure 2 North Fence, NMP-1 294't 0.2 miles Figure 2 North Fence, NMP-1 315't 0.1 miles

TABLE 19 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS Sampl e Hap Figure Location Degrees and Hedium Designation Number Description Dl'stance (1)

Thermo- Figure 2 North Fence, NHP-2 341't 0.1 miles luminescent Dosimeters Figure lA Hickory Grove Road 97't 4.5 miles (TLD)

Continued 87'8'9'0'1>>

Figure lA Leavitt Road 1 1 1't 4. 1 miles Figure 1A Route 104 and Keel'e Road 135't 4.2 miles Figure lA County Route 51A 156't 4.8 miles 92'3*

Figure lA Haiden Lane Road 183't 4.4 miles Figure lA County Route 53 205't 4.4 miles 94* Figure lA County Route 1 and Kocher Road 223't 4.7 miles 95'6*

Figure lA Lakeshore Camp Site 237't 4.1 miles Figure 1A Creamery Road 199't 3.6 miles 97* Figure 2 County Route 29 143't 1.8 miles 98* Figure lA Lake Road 101't 1 ~ 2 miles 99 Figure 1A Nine Nile Point Road 88't 1.8 miles

-125

TABLE 19 (Continued)

ENVIRONMENTAL SAHPLE LOCATIONS Sample Hap Figure Location Degrees and Hedium Designation Number Description Distance ( 1)

Thermo-luminescent 100 Figure 2 County Route 29 and Lake Road 104't 1.1 miles Dos)meters (TLD) 101 Figure 2 County Route 29 132't 1.5 miles Continued 102 Figure 1B Oswego County Airport 175't 11.9 miles 103 Figure 2 Energy Information Center, East 267't 0.4 miles 104 Figure 1A Parkhurst Road 102't 1.4 miles 105 Figure 2 Lakeview Road 198't 1.4 miles 106 Figure 2 Shoreline Cove, West of NHP-1 274't 0.3 miles 107 Figure 2 Shoreline Cove, West of NMP-1 272't 0.3 miles 108 Figure lA Lake Road 104't 1.1 miles 109 Figure 1A Lake Road 103 at 1.1 miles 110 Figure 1B Baldw)nsvi lie, New York Control 166't 26.4 miles Figure lA Sterling, New York Control 214't 21.8 miles Cows Milk Figure 4 Indicator Location 107't 5.5 miles 16 Figure 4 Indicator Location 190 at 5.9 miles 126

TABLE 19 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS Sample Hap Figure Location Degrees and Hedium Designation Number Description Distance (1)

Cows Hi 1k 50 Figure 4 Indicator Location 93 at 9.3 miles Continued 55 Figure 4 Indicator Location 95't 9.0 miles 60 Figure 4 Indicator Location 90 at 9.5 miles Figure 4 Indicator Location 113't 7 .8 miles 65* Figure 4 Control Location 220't 17.0 miles Food Products Figure 3 Indicator Location 84't 1.6 miles Figure 3 Indicator Location 101't 1.9 miles L* Figure 3 Indicator Location 82't 1.7 miles Figure 3 Control Location 225't 15.6 miles Figure 3 Indicator Location 96't 1.7 miles Figure 3 Indicator Location 136't 1.7 miles Figure 3 Indicator Location 110 at 2. 1 miles

'-Technical Specification location.

( 1) Degrees and distance based on Nine'ile Point Unit 2 reactor centerline .

-127 i

TABLE 20 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE HILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE HILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSHEGO COUNTY, STATE OF NEH YORK, JANUARY - DECEHBER 1989'ocation (b) of Hedium Qlni~

Type and Number of

• llaw&

than ~

Indicator Locations: Highest Annual Hean:

Location & Hhu}~

Control Location:

HhUL~

Number of Nonroutine Haua~

Shoreline GSKQ.-

Sediment *

(pCi/kg-dry) Cs-134 150 <LLD <LLD <LLD 0 Cs-137 180 ?9LL?l?l Sunset Bay: ?5~~+ <LLD 0 254-342 1.5 at 80'54-342 Fish *

(pCi/kg-wet)

~~) (h) ~

Hn-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 2n-65 260 <LLD <LLD <LLD 0 Cs-134 130 <LLD <LLD <LLD 0 Cs-137 150 NMP: 0 20-43 0.3 at 315'0-43 20-33

-128

TABLE 20 (Continued)

RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE HILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER Location (b) of 1989'edium Type and Indicator Locations: Highest Annual Mean: Control Location: Number of Number of ~~( Location & Haul~ hlLLD Nonroutine QJaRQ km~~* LLD~ fh@xi~

Surface Water *

(pCi/liter) H-3 3000(c) ?S~~U. JAF: 323 QLQ 0

>>,f 210-350 0.5 at 70'10-350 180-660 G5~~:

Hn-54 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0 Co-58 15 <LLD <LLD <LLD 0 Co-60 15 <LLD <LLD <LLD 0 Zn-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 <LLD <LLD <LLD 0 I-131 15(c) <LLD <LLD <LLD 0

>>)

-129 a t

• g C ~

TABLE 20 (Continued)

RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM ANNUAL

SUMMARY

NINE HILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 h

NINE HILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410

~

r

~ ~

OSHEGO COUNTY, STATE OF NEW YORK, JANUARY DECEHBER

~ h 1989'ocation (b) of Type and Indicator Locations: Highest Annual Hean: Control Location: Number of Hedium QlsMQ Number of 8243ZMi ~LD~

Ha~ Location 5 H~~ Nonroutine 4

Raauris.

Surface Cs-134 15 <LLD <LLD <LLD 0 Hater

'pCi/liter) Cs-137 18 <LLD <LLD <LLD 0 (Continued)

Ba/La-140 15 <LLD <LLD <LLD 0 If

, i Air Gross Beta: 0.01 0.007-0.041 1.8 at IIIIIIIIII 143'.009-0.038 tlllulllf 0.007-0.039 0

Particulates'pCi/m3) h' h

LQRU.: 0 07 <LLD <LLD <LLD 0 f ~ ~

65k KQ2 Cs-134 0.05 <LLD <LLD <LLD 0 Cs-137 0.06 <LLD <LLD <LLD 0

~ I

~ 4P C

C r -130

I".

)~

~

'%ABLE

~

20 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSHEGO COUNTY, STATE OF NEH YORK, JANUARY DECEHBER Location (b) of

~~

1989'edium Type and Indicator Locations: Highest Annual Mean: Control Location: Number of Number of Haa~ Location 5 Nonroutine QlniLtt) LLEW Resorts.

TLDA Gamma (d) TLD¹ 85 '~4. (3LQ (g) ~ljiQUID. 0 (mrem per Qme Q?D: 6.4-45.0 0.2 at 294'5.7-45.0 8.6-17.0 quarterly period)

I Hi lk'pCi/liter)

~i~ (e)(h)

Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 Ll33~2Q.:

I-131 <LLD <LLD <LLD 0 Food Products'~:(h)

(pCi/kg-wet)

(broadleaf I-131 60 <LLD <LLD <LLD 0 vegetation)

Cs-134 60 <LLD <LLD <LLD 0 Cs-137 80 Loca. K 1.7 at 96'

~~ <LLD 0

-131

TABLE 20 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

.,FF NINE HILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE HILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 F. 3 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEHBER 1989*

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3 Data for Table 20 is based on Technical Specification required samples unless otherwise indicated .

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

(b) Location is distance in miles and direction in compass degrees based on NHP-2 reactor centerline. Units for F

this column are specified in medium column.

(c)- 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.

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(d) The Technical Specifications do not specify a particular LLD value for environmental TLDs. The NHP-1 and t NHP-2 Off-Site Dose Calculation Hanuals contains specifications for environmental TLD sensitivities. ~

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.i j (e) 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.

Ftj (f) Fraction of number of detectable measurements to total number of buildings measurements. Mean and range results are based on detectable measurements only.

F (g) The results for TLD ¹85 must be evaluated with the knowledge that this TLD is in close proximity (300-500 3

feet) of the Nine Mile Point Unit reactor building and the radwaste 1 . 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.

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There are no residences or private property near this area.

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

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TABLE 21 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 Y r i . M in. M . M 1979 (2) LLD LLD LLD 0.22 0.22 0.22 LLD LLD LLD 1980 LLD LLD LLD 0.07 0.09 0.08 LLD 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 Results 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.

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TABLE 22 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 Y r M . e 1979 (4) (4) (4) (4) (4) (4) (2) (2) <2) 1980 (4) (4) (4) (4) (4) (4) (2) (2) (2) 1981 (4) (4) (4) (4) (4) (4) (2) (2) (2) 1982 (4) (4) (4) (4) (4) (4) (2) (2) (2) 1983 (4) (4) (4) (4) (4) (4) (2) (2) (2) 1984 (4) (4) (4) (4) (4) (4) (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 LLD LLD LLD 0.25 0.34 0.30 LLD LLD LLD Results in pCi/g -dry (1) Location was off-site at Sunset Bay (closest location with recreational value).

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

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TABLE 23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 1976 1.2 1.2 1.2 1977 0.13 0.13 0.13 1978 0.04 0.20 0.09 1979 0.03 0.06 0.04 1980 0.03 0.11 0.06 1981 0.028 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 0.025 1987 0. 017 0.040 0.031 1988 0.023 0.053 0 '33 1989 0.020 0.033 0.029 Results in pCi/g (wet)

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

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TABLE 24 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 1976 0.5 3.9 1.4 1977 0.13 0.79 0.29 1978 0.03 0.10 0.08 1979 0.02 0.55 0.10 1980 0.03 0.10 0.06 1981 0.03 0.10 0.06 1982 0.034 0.064 0.048 1983 0.033 0.056 0.045 1984 0.033 0.061 0.043 1985 0.018 0.044 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 1988 0 020 F 0.074 0.034 1989 0.020 0.043 0.035 Results in pCi/g (wet)

Indicator locations are in the general area of the NMP-1 and J. A.

FitzPatrick cooling water discharge structures.

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TABLE 25 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE NATER Cs-137 Co-60 1976 (3) (1) (1) <1) (1) (1) (1)

'l 977 (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 Resul ts in pCi/liter (1) No gamma analyses performed (not required)

(2) Data showed instrument background results (3) Location was the City of Oswego Hater Supply for 1976 - 'l984 and the Oswego Steam Station inlet canal for 1985 - 1989

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TABLE 26 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE NTER Cs-137 Co-60 (3) 1976 (1) (1) (1) (1) (1) (1) 1977 (2) (2) (2) (2) (2) (2) 1978 LLO LLD LLD (2) (2) (2)

'l 979 LLD LLD LLD LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLO 1981 LLD LLD LLD LLD LLD LLD 1982 0.43 0.43 0.43 1.6 2.4 1.9 1983 LLD LLO LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLO LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLO LLD Resul ts in pCi/liter (1) No gamma analyses performed (not required).

(2) Data showed instrument background results.

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

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TABLE 27 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE NTER TRITIUM Tritium 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 Results 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 - 1989.

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TABLE 28 HISTORICAL ENVIRONMENTAL SAMPLE OATA SURFACE HATER TRITIUM Tr)tlum 1976 365 &89 627 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 Results 1n pCI/1)ter (1) Indicator'ocat]on 1s the FltzPatrlck tnlet canal.

(2) Suspect samp'le contamination. Recollected samples showed normal levels of tritium.

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TABLE 30 HISTORICAL ENVIRONHENTAL SAHPLE DATA AIR PARTICULATE GROSS BETA Gross Beta 1977 0.002 0.326 0.106 1978 0.01 0.34 0.11 1979 0.001 0.271 0.058 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 Results in pCi/m3

( 1) Locations used for 1977 - 1984 were Dl 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 - 1989 locations were R-1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

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TABLE 32 HISTORICAL ENVIRONHENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 (2)

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)

(1) (1) (1) (1) (1) (1) 1973 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 '.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 0.0002 0.0045 0.0014 0.0002 0.0017 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'LD 0.0007 0.0017'LD 0.0012 1985 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 Results in pCi/m3 (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 - 1989.

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TABLE 34 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Iodine 131 1976 0.01 2.09 0 '3 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 1979 LLD LLD LLD 1980 0. 013 0. 013 0.013 1981 0.016 0.042 0;029 1982 0.002 0.042 0.016 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 0.014 1988 LLD LLD LLD 1989 LLD LLD LLD Results in pCi/m3

( 1) Locations used for 1976 1984 were Dl on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site, and K on-site, as applicable. Locations used for 1985 1989 were Rl off-site, R-2 off-site, R-3 off-site and R-4 off-site.

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

(2)

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 6.2

'986 4.4 6'8.7 7.0 1987 4.4 14.3 6.1 1988 3.4 17.9 6.4 1989 2.8 15.4 5.9 Results in mrem per standard month (1) No data available (not required prior to 1985)

(2) TLD locations initiated in 1985 as required by the new Technical Specitications. 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 368 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)

(2)

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-. 2 1988 3.8 7.0 5.3 1989 2.5 6.8 4.9 Results in mrem per standard month (1) No data 'available (not required prior to 1985)

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

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TABLE 36C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose <mrem)

(2)(3)

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 3.9 6.8 5.3 1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 7.0 4.8 Results in mrem per standard month (1) No data available (not required prior to 1985).

(2) TLD locations initiated in 1985 as required by the new 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)

(2)

Preop (1) (1) (1) 1970 4.7 9.0 6.0 1971 1.5 7.7 4.7 1972 2.3 8.2 4.9 1973 3.0 24.4 6.6 1974 3.1 10. 6 5.7 1975 4.6 16.0 7.3 1976 3.7 18.8 6.9 1977 3.0 15'. 3 5.7 1978 3.0 9.0 4.3 1979 2.7 8.3 4.3 1980 3.9 12.0 5.3 1981 4.1 11.8 5.8 1982 3.9 13.0 6.3 1983 5.0 16.5 6.9 1984 4.6 13.2 7.0 1985 4.7 15.9 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 5.8 1988 4.4 11.9 6.0 1989 2.7 14.5 6.0 Results 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 1989). Locations are existing or previous on-site environmental air monitoring locations.

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~ . TABLE 36E HISTORICAL ENVIRONHENTAL SAHPLE DATA ENVIRONHENTAL TLD Dose (mrem)

(2)

Preop (1) (1) (1) 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.'5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 1978 ~ Zo7 4.7 3.7 1979 3.0 5.7 4.0 1980 3.1 5.8 4.6 1981 3.6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 Results in mrem per standard month (1) No data available.

(2) Includes TLD numbers 8, 9, 10, 11, 12 and 13 (off-site environmental air monitoring locations.

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TABLE 37 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131

<2) 1 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 LL'D LLD LLD LLO LLD LLD 1980 3.6 5.6 4.5 1.4 1.4 1.4 1981 3.9 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 LLO LLD LLD LLD LLD LLO 1989 LLD LLD LLD LLD LLD LLD Results in pCf/liter (1) No data available (samples not required).

<2) Location used was an available milk sample location in a least prevalent wind direction greater than ten miles f'rom the site.

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TASLE 38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 1'l .0 22.0 17.1 0.01 49.00 6.88 1978 3.4 33.0 9' 0.19 0.19 0.19 1979 3.2 53.0 9.4 LLO LLD LLD 1980 3.2 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1983 3.3 10.9 7.2 LLD LLD LLD 1984 LLO LLD LLO 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 Results tn pCf/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 (2) 1976<3) <1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 ('l ) (1) (1) 1980 0.02 0.02 0.02 1981 LLD LLD LLD 1982 LLD LLD LLO 1983 LLO LLD LLD 1984 LLD LLD LLD 1985<4) LLO LLD LLO 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LLD Results tn pCt/g (wet)

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

(2) Location was an avatlable Food product sample location tn a least prevalent wind direction greater than ten mtles from the site (3) Data comprised of broadleaf and non-broadleaf vegetation (1980-1984).

(4) Data comprised of broadleaf vegetation only (1985-1989).

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TASLE 40 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 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 LLD 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 Results in pCi/g (wet)

( 1) Indicator locations were available downwind'ocations 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 ('l985-1989) ~

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