ML18038A297

Annual Radiological Environ Operating Rept 1989

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)

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

Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000220 05000410

SUBJECT:

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

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TITLE: Environmental Monitoring Rept (per Tech Specs)

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1'OTE TO ALL"RIDS" RECIPIENTS:

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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 with 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 3.0 DIRECT RADIATION 4.0 TERRESTRIAL SAMPLES I

Air Particulate/Iodine II MilIR III Food Product IV Land Use Census 5.0 INTERLABORATORY COMPARISON PROGRAM 6.0 CHANGES AND EXCEPTIONS TO THE PROGRAM

7.0 CONCLUSION

8.0 GENERAL REFERENCE MATERIAL 9.0 DATA TABLES 1989 13 17 24 25 37 40 42 44 47 49 52

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Table 1

Sample Collection and Analysis, Site Radiological Environmental Monitoring Program -

Aquatic Program and Direct Radiation 53 Table 2

Table 3A Table 3B Table 4A Table 4B Table 5

Table 6

Table 7

Table 8

Table 9

Table 10 Table 11 Table 12A Table 12B Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Terrestrial Program Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/g-dry)

Concentration of Gamma Emitters in Shoreline Sediment Samples (pCt/kg-dry)

Concentration of Gamma Emitters in Fish Samples (pCi/g-wet)

Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet)

Concentration of Gamma Emitters in Surface Water Samples Concentration of Tritium in Surface Water Samples Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity Environmental Airborne Particulate Samples-On-Site Stations, Gross Beta Activity Concentration of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples Environmental Charcoal Cartridge Samples-Off-Site Stations, I-131 Activity Environmental Charcoal Cartridge Samples-On-Site Stations, I-131 Activity,

Direct Radiation Measurement Results (mrem per standard month)

Direct Radiation Measurement Results (mrem per quarterly period) 54 55 56 57 59 61 65 66 70 72 87 89 91 95

(Continued)

Table 13 Table 14 Table 15 Table 16 Table 17A Table 178 Table 18 Table 19 Table 20 Table 21 Table 22 Table 23 Table 24 Table 25 Table 26 Table 27 Table 28 Concentration of Gamma Emitters in Milk Concentration of Iodine-131 in Milk Milk Animal Census 1989 Residence Census Concentration of Gamma Emitters in Food Products (pCi/g-wet)

Concentration of Gamma Emitters in Food Products (pCi/kg-wet)

Interlaboratory Comparison Program Results Environmental Sample Locations Radiological Environmental Monitoring Program Annual Summary Historical Environmental Sample Data Shoreline Sediment (Control)

Historical Environmental Sample Data Shoreline Sediment (Indicator)

Historical Environmental Sample Data Fish (Control)

Historical Environmental Sample Data Fish (Indicator)

Historical Environmental Sample Data Surface Hater (Control)

Historical Environmental Sample Data Surface Hater (Indicator)

Historical Environmental Sample Data Surface Hater Tritium (Control)

Historical Environmental Sample Data Surface Hater Tritium (Indicator) 99 105 107 109 110 112 119 128 133 134 135 136 137 138 139 140

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Table 29 Table 30 Table 31 Table 32 Table 33 Table 34 Table 35 Table 36 (A E)

Table 37 Table 38 Table 39 Table 40 Historical Environmental Sample Data Air Particulate Gross Beta (Control)

Historical Environmental Sample Data Air Particulate Gross Beta (Indicator)

Historical Environmental Sample Data Air Particulates (Control)

Historical Environmental Sample Data Air Particulates (Indicator)

Historical Environmental Sample Data Air Radioiodine (Control)

Historical Environmental Sample Data Air Radioiodine (Indicator)

Historical Environmental Sample Data Environmental TLD (Control)

Historical Environmental Sample Data Environmental TLD (Indicator)

Historical Environmental Sample Data Milk (Control)

Historical Environmental Sample Data Milk (Indicator)

Historical Environmental Sample Data Food Products (Control)

Historical Environmental Sample Data Food Products (Indicator) 141 142 143 144 145 146 147 148 153 154 155 156

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Figure lA Figure 1B Figure 2

Figure 3

Figure 4

Figure 5

Off-Site Environmental Station and TLD Locations Off-Site Environmental Station and TLD Locations (Southern)

On-Site Environmental Station and TLD Locations Nearest Residence and Food Product Locations Milk Animal Census and Milk Sample Locations New York State Map 157 158 159 160 161 162

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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, if not impossible.

The radionuclides falling into this category (as applicable 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.

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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.

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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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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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SHORELINE SEDIMENT (Cont')

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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 1 ected from two of four possible on-si te 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.

B.

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).

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.

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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.

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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')

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(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).

-13

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 tritium) 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 1

and Unit 2

showed 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.

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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.

B.

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).

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 1

and Unit 2

and the radwaste facilities of the FitzPatrick facility.

A net site boundary dose can be estimated from available TLD results and control TLD results.

TLD results from TLD's located near the site boundary in sectors facing the land occupied by members of the public (excluding TLD's near the generating facilities and facing Lake Ontario) are compared to control TLD results.

The site boundary TLD's include numbers 78, 79, 80, 81, 82, 83, 84, 7

and 18.

Control TLD's include numbers 8,

14, 49, 110 and 111.

Net site boundary doses for each quarter in mrrg gus ~~ 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

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~

B.

v 1

i f T 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).

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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 R-2 R-3 R-4 R-5 (control) 0.007 0.008 0.007 0.009 0.007 0.041 0.033 0.041 0.038 0.039

0. 017 0.017

0. 017 0.018 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)

C.

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.

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

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~

)

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.

Ra-226 Ra-226 K-40 K-40 Be-7 Be-7 Lm~n Indicator Control Ind1cator Control Indicator Control

)ham"

0. 012

0. 027 ND 0.009 0.046 0.010 - 0.047 0.052 - 0.103 0.061 0.101 II F

0. 018 9/48 ND ND 0.028 40/48 0.028 9/12 0.078 48/48 0.079 12/12 Results in units of pC1/m3.

• • Frequency is the 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:

lin P

Air Sampling Location Concentration in 10-3pCi/m3 October November Zn-65 Co-60 Zn-65 Co-60 2.77

<1.0 24.9 0.9 2.90

<1.7 4.63

<0.9

<2.57

<1.0 2.17

<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 Adult Child I

Eu.~adx Luna 0.000198 0.00592 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 at the indicator ~

control locations from 1977 to 1978 decreased 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.

B.

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).

v 1

D

- T 1

Milk samples were collected from a total of six indicator locations (withi 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')

16 S

(190')

50 E

( 93')

55 E

( 95')

60 E

( 90')

4 ESE (113')

65 (Control)

SW (220

)

5.5 5.9 9.3 9.0 9.5 7.8 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.

-36 1

1

,'I

~

- ~

4.0 III FOOD PRODUCTS A.

B.

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).

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 pl I

'i t

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

1 and Table 3.12.1

1 of the Technical Specifications and for which intercomparison samples are available from the EPA.

Where many samples are available from the

EPA, a

QC sample to program sample ratio of ten percent is 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

/-

C 0) 0

~

E 1

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, deleted from the sampling program because of unavailability or because the location had a

potential as a result of the addition of locations H.

J, and X

were either sample low deposition K, L, Q,

Y, and 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-site 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

ifications re uire that environmental sam les The Technical Spec q

P 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

.0

-47

P Wp 0,

4 I

~

a~

v Y

p C

~

L l.

~

~

~

+

~

~ I ~,

8 IV 4

4

~

1

~

4

~

7-0 GQHGLI585 QQN(~l~

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.

C

-48

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.

4, U.S.

Nuclear Regulatory Commission Regul atory Guide

4. 8, "Environmental Technical Specifications for Nuclear Power Plants",

December, 1975.

U.S.

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

Revision 1,

November 1979.

National Council vir m

1 i

National Council on r

on Radiation Protection and Measurements (NCRP),

NCRP Report No. 50, 1976.

Radiation Protection and Measurements (NCRP),

~N ZLrrl NCRP Report No. 45, 1975.

7.

9.

National Council r

No. 52, 1977.

National Council Report No.

56, 1977.

on Radiation Protection on Radiation Protection and Measurements (NCRP),

i D

NCRP Report and Measurements (NCRP),

NCRP 10 12.

13 1

ICRP Publication 29, 1979.

Eichholz, G.

v f

w, First Edi tion, Ann Arbor Science Publishers, Inc.,

Ann Arbor, Michigan, 1976.

Ei senbud, Merri 1 1, vi e

1 v'

Second

Edition, Academic

Press, New York, NY 1973.

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.

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 2.

Fish 3.

Surface Hater GSA GSA GSA H-3 2/year 2/year H.

Comp.

Qtr.

Comp.

1 Indicator (2) 2 Indicator (3),

1 Control 1 Indicator (4),

1 Control 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

~ r i ri

, ~

C.

r'.

l.

Air Particulates 2.

Airborne I-131 3.

Milk 4.

Human Food Crops GB GSA GSA I-131 GSA GSA, I-131 (5)

Meekly M. Composite Meekly 2/Month 2/Month Annual ly 4 Indicator, 1 Control (1) 4 Indicator, 1 Control (1) 3 Indicator, 1 Control (2)

(3)

NOTES:

Sampling and analysis program as required by the Technical Specifications.

( 1)

Three indicator samples from near the site boundary in three of the highest D/Q meteorological

sectors, one indicator sample from near a year round community, and one control sample from an area of least prevalent wind direction.

(2)

Three indicator samples from areas within 5.0 miles of the site

Control sample from an area of least prevalent wind direction.

(3)

Samples of three different kinds of broadleaf vegetation nearest to each of two different off-site locations of highest 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 (Control)*

Sunset Beach (Off-Site) 4-24-89 10-30-89 4-24-89 10-30-89

<0.44 0.12'.07

<0.43

<0.50 13.3tl.0 13.7%0.5 16.6tl.l 18.0gl.3

<0.040

<0.053

<0.052

<0.063

<0.037

<0.082

<0.035

<0.051

<0.041

<0.047 0.342z0.051 0.254z0.047 1.1720.49 1.25z0.32 2.34z0.91 2.5420.83

<0.26 0.42z0.07 0.6720.14 0.80z0.18

<LLD

<LLD

<LLD

<LLD

'ample ~ required by the Technical Specifications (Optional sample location)

Results in units of activity g~~jll dry weight

-55

TABLE 38 CONCENTRATION OF GAMMA EMITTERS IN SMORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) g 2 sigma Sample Langs Beach (Control)'unset Beach (Off-Site)

Collection D

4-24-89 10-30-89 4-24-89 10-30-89

<438 119z69

<427

<504 13300z1050

<40 13700i486

<53 16600zl090

<52 18000gl290

<63

<37

<82

<35

<51

<41

<47 342t51 254247 1170z487 1250z324 23402909 2540z834

<264 418z68 666z141 800z184

<LLD

<LLD

<LLD

<LLD

• Sample not required by the Technical Specifications tel 0

-56

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 6/06/89 Brown Trout 6/06/89 White Sucker

<0.110

<0.047

<0.142

<0.054

<0.077

<0.034 4.57g0.24 5.14'.65 3.99z0.49

<0.036

<0.037

<0.032

<0.038

<0.032

<0.026

<0.031

<0.035

<0.028 0.032~0.010

<0.048

<0.031

<0.075

<0.094

<0.056

<0.57

<LLD

<0.78

<LLD

<0.59

<LLD 9/19/89 9/19/89 10/28/89 9/22/89 9/22/89 Lake Trout ¹1 Lake Trout ¹2 Walleye White Sucker Brown Trout

<0.122

<0.039

<0.084

<0.034

<0.048

<0.024

<0.075

<0.039

<0.151

<0.048 4.06z0.55 3.38t0.43 4.85z0.44 4.90z0.52 5.12'.62

<0.037

<0.025

<0.023

<0.030

<0.043

<0.033

<0.021

<0.022

<0.025

<0.038

<0.030

<0.023

<0.024

<0.028

<0.035 0.030z0.016 0.033z0.013 0.020z0.154

<0.030

<0.046

<0.075

<0.046

<0.045

<0.067

<0.102

<0.62

<LLD 0.42z0.20

<LLD 0.60z0.22 (1) 0.57z0.28

<LLD 0.5820.28

<LLD 6/07/89 Lake Trout 6/07/89 Brown Trout 6/22/89 White Sucker

<0.095

<0.040

<0.110

<0.039

<0.069

<0.028 4.5720.51 3.99z0.21 5.26+0.49

<0.030

<0.035

<0.024

<0.018

<0.036

<0.025

<0.025

<0.032

<0.024 0.043z0.015 0.020g0.010

<0.028

<0.056

<0.085

<0.055 0.6820.32

<LLD 0.6120.23

<LLD 0.68z0.30 (2) 9/19/89 9/19/89 10/23/89 9/19/89 9/29/89 Lake Trout ¹1 Lake Trout ¹2 Walleye Brown Trout White Sucker

<0.146

<0.060

<0.122

<0.041

<0.059

<0.024

<0.112

<0.043

<0.088

<0.040 4.49z0.58 4.2520.51 5.88g0.51 5.64i0.60 6.05z0.58

<0.030

<0.028

<0.023

<0.034

<0.027

<0.039

<0.032

<0.022

<0.024

<0.032

<0.032

<0.027

<0.025

<0.031

<0.029

<0.039 0.040g0.018 0.03020.015

<0.039

<0.032

<0.092

<0.070

<0.054

<0.069

<0.068 0.39z0.26

<LLD 0.9020.42

<LLD 0.70z0.25

<LLD 0.6220.27

<LLD 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 9/19/89 9/19/89 9/19/89 9/22/89 9/19/89 Lake Trout ¹1 Lake Trout ¹2 Halleye Smallmouth Bass Hhite Sucker 6/06/89 Lake Trout 6/08/89 Brown Trout 6/03/89 Hhite Sucker

<0.091

<0.034

<0.069

<0.030

<0.122

<0.050

<0.132

<0.051

<0.115

<0.042

<0.110

<0.040

<0.085

<0.037

<0.102

<0.037 4.38i0.48 4.6420.47 4.80z0.64 3.84z0.22 4.70g0.51 6.25z0.60 4.64t0.49 3.97t0.46

<0.024

<0.023

<0.037

<0.039

<0.031

<0.029

<0.028

<0.027

<0.022

<0.024

<0.046

<0.032

<0.026

<0.029

<0.028

<0.027

<0.024

<0.024

<0.035

<0.033

<0.026

<0.027

<0.024

<0.023 0.039z0.024 0.030z0.015

<0.040 0.024~0:009 0.04lz0.018 0.042z0.019 0.042z0.020

<0.027

<0.060

<0.052

<0.092

<0.102

<0.061

<0.074

<0.056

<0.061 0.48z0.25

<LLD 1.08z0.38 (3)

<0.84

<LLD 0.47t0.23

<LLD 0.84z0.33 (4) 1.27z0.41

<LLD 0.60z0.31

<LLD 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 9/19/89 9/19/89 10/28/89 9/22/89 9/22/89 Lake Trout ¹1 Lake Trout ¹2 Halleye Hhi te Sucker Brown Trout 6/08/89 Lake Trout 6/06/89 Brown Trout 6/06/89 Hhite Sucker

<110

<47

<142

<54

<77

<34

<122

<39

<84

<34

<48

<24

<75

<39

<151

<48 4060g550 33802429 48502436 4900z522 5120z625

<37

<25

<23

<30

<43 45702236

<36 51402650

<37 39902491

<32

<38

<32

<26

<33

<21

<22

<25

<38

<31

<35

<28

<30

<23

<24

<28

<35 32gl 0

<48

<31 30zl 6 33t13 20zl5

<30

<46

<75

<573

<LLD

<94

<784

<LLD

<56

<586

<LLD

<75

<623

<LLD

<46 4242205

<LLD

<45 6052222 (1)

<67 5682282

<LLD

<102 585i275

<LLD 6/07/89 Lake Trout 6/07/89 Brown Trout 6/22/89 Hhi te Sucker

<95

<40

<110

<39

<69

<28 45702511 39902209 5260z486

<30

<18

<35

<36

<24

<25

<25

<32

<24 43tl5 20z10

<28

<56

<85

<55 6852325 608z232 6832303

<LLD

<LLD (2) 9/19/89 9/19/89 10/23/89 9/19/89 9/29/89 Lake Trout ¹1 Lake Trout ¹2 Halleye Brown Trout Hhite Sucker

<146

<60

<122

<41

<59

<24

<112

<43

<88

<40 44902576 42502507 58802509 5640g600 60502584

<30

<39

<28

<32

<23

<22

<34

<24

<27

<32

<32

<27

<25

<31

<29

<39 40zl8 30zl5

<39

<32

<92

<70

<54

<69

<68 3942259 898z416 7042250 615z274 987t476

<LLD

<LLD

<LLD

<LLD

<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 6/08/89 Brown Trout 6/03/89 Hhite Sucker

<91

<34

<69

<30

<122

<50 4380g485 46402467 4800z642

<24

<23

<37

<22

<24

<46

<24

<24

<35 39t24 30zl5

<40

<60

<52

<92 4832254 1080z384

<842

<LLD (3)

<LLD 9/19/89 9/19/89 9/19/89 9/22/89 9/19/89 Lake Trout ¹1 Lake Trout ¹2 Halleye Smallmouth Bass Hhlte Sucker

<132

<51

<115

<42

<110

<40

<85

<37

<102

<37 3840t223 4700z513 62502595 4640z486 3970z458

<39

<31

<29

<28

<27

<32

<26

<29

<28

<27

<33

<26

<27

<24

<23 24z9 4lzl 8 42zl 9 42t20

<27

<102

<61

<74

<56

<61 472t226 837t331 1270z414 599z308 509z215

<LLD (4)

<LLD

<LLD

<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.

-60y

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

May June OSWEGO CITY K-40 WATER Ra-226 Cs-134 Cs-137 Zr-9S Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 NINE MILE K-40 POINT UNIT I Ra-226 (INLET)

Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 101+30 47z33

<2.68

<2.80

<6.3

<3.47

<2.84

<2.86

<6.0

<2.10

<5.6

<8.4

<6.6 66+21 74g36

<2.46

<2.47

<6,2

<3.31

<2.70

<2.64

<6.4

<2.34

<5.4

<8.2

<6.5 237g42 116g47

<3.43

<3.71

<8.7

<4.20

<3.49

<3.38

<9.3

<3.34

<7.2

<11.4

<6.4 234z37 61g31

<2.78

<3.04

<7.2

<3.59

<3.19

<2.59

<6.7

<3.09

<5.4

<8.8

<7.0 65z13 89z24

<3.33

<2.68

<8.8

<4.09

<3.38

<3.14

<8.2

<3'6

<8.1

<8.5

<11.2 36zl2

'5+25

<3.09

<3.01

<8.6

<4.03

<3.17

<2.97

<7.7

<3.65

<8.5

<7 '

<8.9 175z45 94g74

<3.86

<4.28

<9.5

<5.54

<4.36

<4.39

<9.5

<3.91

<8.6

<11.5

<9.3 203243 143250

<3.58

<4.18

<9.5

<4.53

<4.03

<3.46

<8.5

<3.09

<7.5

<11.0

<7.4 222g41 66+14 96+49

<76

<3.31

<3.97

<4.22

<3.25

<9.6

<8.7

<4.76

<5.30

<3.71

<4.39

<3.95

<3.61

<10.3

<8.9

<3.88

<3.80

<7.3

<9.1

<12.7

<10.7

<8.1

<10.4 58g22 32+12 81+35 80+29

<2.68

<4.38

<2.70

<3.48

<6.2

<8.4

<F 17

<5.40

<3.14

<4.78

<2.56

<3.64

<7.7

<7.9

<2.74

<4.25

<5.5

<11.3

<9.3

<11.6

<5.8

<12.3

• • Optional sample location.

Sample ~ required by the Technical Specifications.

-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 FITZPATRICK (INLET)

K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 NINE MILE K-40 POINT UNIT 2 Ra-226

( INLET)

Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 172g40 11.0279

<4.30

<4.44

<11.1

<6.09

<4.76

<4.38

<10.6

<4.28

<10.2

<13.6

<11.3 191g41 95z47

<3.07

<3.56

<9.6

<4.83

<4.30

<3.62

<9.0

<4.15

<7.6

<0.5

<8.6 48gl 1 96+22

<2.89

<2.68

<8.4

<4.22

<3.62

<3.17

<7.5

<3.28

<8.4

<7.6

<8.5 191+41 322241

<3.60

<3.76

<9.5

<4.66

<4.00

<3.97

<8.7

<3.67

<7.9

<0.3

<6.3 100+26 61z33

<2.41

<2.62

<6.0

<3.02

<2.56

<2.49

<6.4

<2.77

<5.2

<7.8

<6.1 183+30 76x44

<2.50

<2.75

<7.0

<3.46

<2.80

<2.63

<5.4

<2.28

<5.2

<0.3

<5.9 53g21 108z4

<2.29

<2.60

<6.7

<3.27

<2.83

<2.32

<5.4

<2.34

<4.5

<6.8

<5.0 203+34 77g41

<3.05

<3.26

<8.0

<4.26

<3.21

<2.84

<6.9

<3.05

<6.4

<0.2

<6.8 50+15 62227

<4.87

<2.88

<8.8

<5.06

<4.30

<4.04

<8.3

<4.54

<10.7

<9.8

<11.3 310+43 110+46

<2.89

<3.01

<7.6

<3.79

<3.02

<3.18

<7.6

<2.98

<6.4

<0.5

<5.2 63+12

<75

<3.70

<3.45

<8.1

<4.41

<4.11

<3.95

<6.7

<4.12

<8.8

<8.8

<9.1 221+46 90+41

<3.39

<3.44

<8.8

<4.64

<3.96

<4.08

<8.6

<3.09

<7.6

<0.2

<6.3 OSHEGO STEAM STATION (CONTROL)

K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 234+34 92z39

<3.02

<F 15

<8.8

<3.91

<3.05

<3.00

<6.9

<2.93

<6.0

<0.5

<5,1 188+49 97g51

<3.61

<3.65

<10.2

<4.49

<4.70

<3.88

<7 '

<4.37

<6.5

<0.4

<7 '

202+31 58z39

<2.71

<3.01

<8.4

<3.75

<3.31

<2.59

<7.3

<2.76

<5.6

<0.4

<6.9 229+35 112+41

<2.72

<2.88

<6.4

<3.66

<2.73

<2.61

<5.6

<2.61

<5.9

<0.3

<5.7 215+40 99z41

<3.10

<3.24

<8.9

<4.53

<3.72

<3.47

<7.5

<3.75

<7.0

<0.4

<7.7 236+41 108+45

<2.82

<2.76

<7.4

<3.47

<2.83

<2.58

<6.5

<2.52

<6.2

<0.3

<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 WATER Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 NINE MILE K-40 POINT UNIT I Ra-226 (INLET)

Cs-134 Cs-137 2r-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 En-65 I-131 Ba/La-140 169z48 158z68

<3.98

<4.41

<12.1

<5.79

<4.43

<4.39

<10.2

<3.66

<9.4

<14.3

<10. 9 160245 87+45

<4.39

<4.80

<11.6

<6.04

<4.90

<4.51

<10.1

<4.09

<9.3

<12.9

<7.6 185247 149+54

<4.57

<4.58

<11.4

<6.03

<5.62

<4.43

<11.5

<3.88

<9.4

<14.1

<10.3 228+44 149+58

<3.70

<3.79

<9.2

<4.97

<3.96

<4.00

<9.1

<3.25

<7.6

<11.9

<8.7 73+13 105+31

<3.98

<2.88

<9.2

<5,03

<4.08

<3.52

<7.5

<4.31

<9.5

<10.7

<12.9 52222 78g29

<2.56

<2.52

<6.7

<3.01

<3.05

<2.92

<7.0

<3.01

<5.5

<7.8

<5.9 239z36 89z35

<2.38

<2.88

<7.2

<3.42

<3.06

<2.63

<F 1

<2.48

<6.0

<9.6

<5.4 73z24 58z28

<F 51

<2.64

<6.7

<3.50

<3.33

<2.86

<6.8

<3.06

<5.4

<8.7

<6.1 275+64 57+14

<116 89+22

<4.17

<3.60

<4.50

<3.15

<11.0

<8.4

<5.35

<5.17

<4.51

<4.42

<4.56

<3.78

<9.8

<8.3

<4.69

<4.13

<8.4

<8.4

<13.2

<10.0

<8.9

<11.1 177+52 69+26

<113 53+29

<4.23

<3.00

<4.79

<3.06

<10.8

<7.9

<4.89

<3.86

<4.56

<2.91

<3.96

<3.15

<12.1

<6.3

<3.45

<3.21

<9.4

<6.4

<13.5

<9.5

<10.1

<6.9

• • Optional sample location.

Sample ~ required by the Technical Specifications.

-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 POINT UNIT 2 (INLET)

FITZPATRICK (INLET)

OSHEGO STEAM STATION (CONTROL)

K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn Fe-59 Co-60 Zn-65 I-131 Ba/La-140 K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-S4 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 101g29 73z30

<2.80

<2.83

<6.8

<3.58

<3.12

<2.95

<7.4

<2.56

<5.4

<8.4

<7.4 182z30

<87

<3.01

<3.10

<7.0

<3.90

<3.11

<2.90

<6.5

<3.16

<6.8

<0.2

<6.1 38gl 3 76z25

<3.87

<3.35

<8.4

<4.30

<4.46

<3.59

<8.4

<3.87

<10.0

<0.2

<9 '

49+14 78232

<4.01

<2.95

<8.8

<4.67

<4.45

<3.98

<8.4

<4.86

<9.6

<9.1

'<10. 6 48gl 4 117z29

<4.60

<3.08

<8.7

<4.22

<4.50

<3.41

<8.4

<4.54

<9.5

<0.2

<10 '

334g49 lllg41

<2.98

<3.02

<7 '

<3.84

<3.56

<3.01

<7.0

<2.82

<6.6

<0.2

<6.9 46gl 3 10lg28

<4.07

<3.43

<7.9

<4.74

<4.09

<3.50

<9 '

<4.25

<9.3

<8.1

<9.9 214g46 160+77

<3.81

<3.99

<9.3

<4.97

<4.09

<3.90

<9.1

<3.40

<7.1

<0.3

<7.5 236+39

<85

<2.70

<3.02

<7.9

<3.72

<3'8

<2.64

<F 7

<2.65

<5.3

<0.4

<4.7 84z14 72g28

<4. 11

<2.98

<9.1

<4.61

<4.34

<3.60

<7.8

<4.31

<8.9

<9.9

<10.8 257235 84z35

<2.79

<3.32

<6.8

<3.63

<3.12

<2.49

<6.5

<2.38

<5.7

<0.3

<4.4 151g38 155+58

<3.58

<4.29

<9.8

<4.88

<3.76

<4'8

<9.7

<4.01

<7.2

<0.3

<8.8 262~38 68z33

<2.66

<2.68

<6.4

<3.64

<2.71

<2.80

<5.8

<2.38

<5.9

<9.1

<5.6 49' 2

83g24

<3.86

<3.54

<8.3

<5.05

<4.38

<3.44

<8.0

<4.36

<9.9

<0.4

<10.2 216+44 113255

<3.66

<3.66

<8.7

<4.73

<3.81

<4.02

<9.4

<3.82

<7.1

<0.4

<7.5 259+36 68g34

<3.09

<3.25

<8.3

<4.26

<3.42

<3.26

<6.4

<3.09

<6.5

<11.6

<6.2 239+35 99+39

<3.09

<3.19

<8.5

<3.64

<3.00

<2.82

<7.0

<2.86

<6.3

<0.4

<6.3 265+38 87+40

<3.02

<2.94

<8.0

<4.29

<3.26

<3.14

<6.3

<3.02

<6.9

<0.2

<5.7 Sample reguired by the Technical Specifications

• • Optional sample location.

Sample ~ reguired by the Technical Specifications.

-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

• NHP-1 INLET **

NMP-2 INLET "

OSWEGO CITY WATER

~'SWEGO STEAH STATION *

(CONTROL)

First Quarter Second Quarter Third Quarter Fourth Quarter

'c First (}uarter Second Quarter Third (}uarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth (}uarter First Quarter Second Quarter Third Quarter Fourth Quarter 12/29/88 03/31/89 03/31/89 06/30/89 06/30/89 09/29/89 09/29/89 01/02/90 12/31/88 03/31/89 03/31/89 06/30/89 06/30/89 09/29/89 09/29/89 01/02/90 12/31/88 - 03/31/89 03/31/89 06/30/89 06/30/89 09/29/89 09/29/89 01/02/90 12/31/88 03/31/89 03/31/89 06/30/89 06/30/89 09/29/89 09/29/89 01/02/90 12/31/88 03/31/89 03/31/89 06/30/89 06/30/89 09/29/89 09/29/89 - 01/02/90 350zllO

<150

<110 210g90 160290 220z80

<160 180z80 190290 160z100 280270 210gl 10 310zl00 200z60

<200 250z80 280gllO 180t90

<140 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 89/01/16 89/01/23 89/01/30 89/02/06 89/02/13 89/02/21 89/02/27 89/03/06 89/03/13 89/03/20 89/03/27 89/04/03 89/04/10 89/04/17 89/04/24 89/05/01 89/05/08 89/05/15 89/05/22 89/05/30 89/06/05 89/06/12 89/06/19 89/06/26 89/07/03 0.020+0.002 0.019+0.002 0.021+0.002 0.024+0.002 0.022+0.002 0.016+0.002 0.021+0.002 0.019+0.002 0.020+0.002 0.021+0.002 0.018+0.002 0.015+0.002 0.014+0.002 0.012+0.002 0.016+0.002 0.018+0.002 0.012+0.002 0.007+0.001 0.008+0.002 0.014+0.002 0.014+0.002 0.013+0.002 0.011+0.002 0.009+0.002 0.012+0.002 0.019+0.003 0.018+0.002 0.019+0.002 0.018+0.002 0.021+0.002 0.022+0.002 0.016+0.002 0.020+0.002 0.017+0.002 0.017+0.002 0.023+0.004 0.017+0.002 0.016+0.002 0.013+0.002 0.012+0.002 0.016+0.002 0.016+0.002 0.010+0.002 0.009+0.002 0.008+0.001 0.015+0.002 0.014+0.002 0.012+0.002 0.011+0.002 0.009+0.002 0.017+0.002 0.019+0.002 0.018+0.002 0.018+0.002 0.018+0.002 0.023+0.002 0.018+0.002 0.015+0.002 0.019+0.002 0.019+0.002 0.016+0.002 0.017+0.002 0.015+0.002 0.018+0.002 0.012+0.002 0.011+0.002 0.016+0.002 0.015+0.002 0.012+0.002 0.008+0.001 0.007+0.001 0.014+0.002 0.014+0.002 0.012+0.002 0.010+0.002 0.008+0.002 0.015+0.002 0.018+0.002 0.017+0.002 0.021+0.002 0.018+0 '02 0.024+0.002 0.021+0.002 0.017+0.002 0.026+0.003 0.018+0.002 0.018+0.002 0.015+0 '02 0.025+0.003 0.018+0.002 0.014+0.002 0.019+0.003 0.019+0.002 0.015+0.002 0.013+0.002 0.009+0.002 0.009+0.001 0.014+0.002 0.016+0.002 0.012+0.002 0.011+0.002 0.009+0.002 0.017+0.002 0.018+0.002 0.020+0.002 0.018+0.002 0.020+0.002 0.022+0.002 0.023+0.002 0.016+0.002 0.018+0 '02 0.019+0.002 0.018+0.002 0.019+0.002 0.016+0.002 0.020+0.002 0.011+0.002 0.012+0.002 0.016+0.002 0.018+0.002 0.011+0.002 0.007+0.001 0.008+0.002 0.016+0.002 0.015+0.002 0.013+0.002 0.011+0.002 0.009+0.002 0.015+0.002 0.020+0.003 "AMPLE LOCATIONS REQUIRED BY

'UMP INOPERATIVE TECHNICAL SPE CATIONS

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 89/01/16 89/01/23 89/01/30 89/02/06 89/02/13 89/02/21 89/02/27 89/03/06 89/03/13 89/03/20 89/03/27 89/04/03 89/04/10 89/04/17 89/04/24 89/05/01 89/05/08 89/05/15 89/05/22 89/05/30 89/06/05 89/06/12 89/06/19 89/06/26 89/07/03 0.016+0.002 0.016+0.002 0.018+0.002 0.023+0.002 0.022+0.002 0.016+0.002 0.020+0.002 0.018+0.002 0.017+0.002 0.022+0.003 0.011+0.002 0.022+0.003 0.016+0.003 0.012+0.002 0.016+0.002 0.016+0.002 0.011+0.002 0.005+0.001 0.010+0.002 0.014+0.002 0.013+0.002 0.012+0.002 0.010+0.002 0.009+0.002 0.015+0.002 0.017+0.002 0.018+0.002 0.024+0.003 0.017+0.002 0.023+0.002 0.021+0.002 0.017+0.002 0.020+0.002 0.020+0.002 0.019+0.002 0.019+0.002 0.018+0.002 0.018+0.002 0.012+0.002 0.012+0.002 0.016+0.002

0. 014+0. 002 0.007+0.001 0.009+0.002 0.015+0.002 0.017+0.002 0.013+0.002 0.011+0.002 0.009+0.002 0 '14+0.002 0.019+0.003

0. 018+0. 002 0.018+0.002 0.020+0.002 0.024+0.002 0.025+0.002 0.017+0.002 0.017+0.002 0.020+0.002 0.020+0.002 0.020+0.002 0.014+0.002 0.020+0.002 0.013+0.002 0.012+0.002 0.016+0.002 0.013+0.002 0.012+0.002 0.006+0.001 0.008+0.001 0.015+0.002 0.016+0.002 0.013+0.002 0.010+0.002 0.009+0.002 0.018+0.002 0.019+0.002 0.018+0.002 0.020+0.002 0.018+0.002 0.016+0.002 0.019+0.002 0.016+0.002 0.017+0.002 0.018+0.002 0.016+0.002 0.017+0.002 0.015+0.002 0.017+0 '02 0.011+0.002 0.012+0.002 0.016+0.002 0.013+0.002 0.010+0.002 0.006+0.001 0.008+0.001 0.012+0.002 0.015+0.002 0.013+0.002 0.010+0.002 0.008+0.002 0.015+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 89/07/17 89/07/24 89/07/3 1 89/08/07 89/08/14 89/08/21 89/08/28 89/09/05 89/09/11 89/09/18 89/09/25 89/10/02 89/10/09 89/10/16 89/10/23 89/10/3 0 89/11/06 89/11/13 89/11/20 89/11/27 89/12/04 89/12/11 89/12/18 89/12/2 6 90/01/02 0.015+0.002 0.017+0.002 0.021+0.002 0.020+0.002 0.016+0.002 0.018+0.002 0.015+0.002 0.019+0.002 0.020+0.002 0.026+0.003 0 '24+0.004 0.009+0.002 0.018+0.002 0.015+0.002 0.020+0.002 0.010+0.002 0.041+0.003 0.018+0.002 0.014+0.002 0.016+0.002 0.017+0.002 0.016+0.002 0.022+0.002 0.022+0.002 0 '22+0.002 0.017+0.002

0. 016+0. 002 0.015+0.002 0.020+0.002 0.020+0.002 0.015+0.002 0.019+0.002 0.016+0.002 0.017+0.002 0.018+0.002 0.022+0.002 0.017+0.002 0.009+0.002 0.015+0 '02 0.013+0.002 0.019+0.002 0 'il+0.002 0.033+0.003 0.016+0.002 0.015+0.002 0.017+0.002 0.018+0.002 0.019+0.002 0.019+0.002 0.022+0.002 0.023+0.002 0.019+0.002 0.015+0.002 0.014+0 '02 0.021+0.002 0.019+0.002 0.015+0.002 0.018+0.002 0.012+0.002 0.019+0.002 0.021+0.002 0.022+0.002 0.018+0.002 0.009+0.002 0.016+0.002 0.013+0.002 0.021+0.002 0.010+0.002 0.041+0.003 0.015+0.002 0.015+0.002 0.019+0.002 0.018+0.002 0.016+0.002 0.021+0.002 0.020+0.002 0.021+0.002 0.018+0.002 0.015+0.002 0.016+0.002 0.021+0.002 0.019+0.002 0.016+0.002 0 021+0.002 0.015+0.002 0.015+0.002 0.018+0.002 0.026+0.003 0.016+0.002 0.009+0.002 0.018+0.002 0.015+0.002 0.019+0.002 0.009+0.002 0.037+0.003 0.017+0.002 0.038+0.015 0.018+0.002 0.021+0.002 0.018+0.002 0.019+0.002 0.021+0.002 0.025+0.003 0.020+0.002

0. 018+0. 002 0.017+0.002 0.019+0.002 0.021+0.002 0.019+0 '02 0.020+0.002 0.016+0.002 0.016+0.002 0.019+0.002 0.022+0.002 0.016+0.002 0.009+0.002 0.013+0.002 0.014+0.002 0.021+0 '02 0.009+0.002 0.039+0.003 0.014+0.002 0.014+0.002 0.017+0.002 0.017+0.002 0.019+0.002 0.022+0.002 0.023+0.002 0.021+0.002 0.021+0.002

• SAMPLE LOCATIONS REQUIRED BY UMP INOPERATIVE TECHNICAL SPECIFICATIONS

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 89/07/17 89/07/24 89/07/31 89/08/07 89/08/14 89/08/21 89/08/28 89/09/05 89/09/11 89/09/18 89/09/25 89/10/02 89/10/09 89/10/16 89/10/23 89/10/30 89/11/06 89/11/13 89/11/20 89/11/27 89/12/04 89/12/11 89/12/18 89/12/26 90/01/02 0.017+0.002 0.015+0.002 0.019+0.002 0.022+0.002 0.015+0.002 0.017+0.002 0.014+0.002 0.017+0.002 0.019+0.002 0.020+0.002 0.014+0.002 0.010+0.002 0.015+0.002 0.013+0.002 0.020+0.002 0.008+0.001 0.038+0.003 0.015+0.002 0.013+0.002 0.018+0.002 0.015+0.002 0.016+0.002 0.019+0.002 0.022+0.002 0.024+0.002 0.021+0.002 0.018+0.002 0.017+0.002 0.022+0.002 0.023+0.002 0.016+0.002 0.021+0.002 0.017+0.002 0.019+0.002 0.019+0.002 0.025+0.002 0.015+0.002 0.009+0.002 0.016+0.002 0.016+0.002 0.020+0.002 0.008+0.002 0.037+0.003 0.016+0.002 0.014+0.002 0.017+0.002 0.019+0.002 0.019+0.002 0.018+0.002 0.023+0.002 0.022+0.002 0.022+0.002 0.017+0.002 0.020+0.002 0.024+0.002 0.021+0.002 0.015+0.002 0.020+0.002 0.015+0.002 0.018+0.002 0.019+0.002 0.023+0.002 0.015+0.002 0.009+0.002 0.016+0.002 0,016+0.002 0.018+0.002 0.011+0.002 0.036+0.003 0.014+0.002 0.012+0.002 0.017+0.002 0.017+0.002 0.017+0.002 0.020+0.002 0.021+0.002 0.022+0.002 0.020+0.002 0.015+0.002 0.011+0.002 0.016+0.002 0.016+0.002 0.014+0.002 0.015+0.002 0.013+0.002 0.017+0.002 0.017+0.002 0.020+0.002 0.014+0.002 0.009+0.002 0.016+0.002 0.015+0.002 0.018+0.002 0.010+0.002 0.031+0.003 0.015+0.002 0.015+0.002 0.016+0.002 0.016+0.002 0.015+0.002 0.017+0.002 0.019+0.002 0.020+0.002 0.020+0.002

• SAMPLE LOCATIONS

• • PUMP INOPERATIVE REQUIRED BY TECMNICAL SPECIFICATIONS

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 I

ON J--ON K

ON 89/01/10 89/01/17 89/01/24 89/01/31 89/02/07 89/02/14 89/02/21 89/02/28 89/03/07 89/03/14 89/03/21 89/03/28 89/04/04 89/04/11 89/04/18 89/04/25 89/05/02 89/05/09 89/05/16 89/05/23 89/05/30 89/06/06 89/06/13 89/06/20 89/06/26 89/07/03

.002

.002

.002

.006

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002

.002 0.015+0 0.019+0 0.017+0 0.034+0 0.018+0 0.018+0 0.019+0 0.021+0 0.018+0 0.019+0 0.017+0 0.018+0 0.014+0 0.011+0 0.017+0 0.017+0 0.013+0 0.010+0 0.008+0 0.015+0 0.016+0 0.013+0 0.011+0 0.008+0 0.014+0 0.017+0 0.017+0.002 0.019+0.002 0.018+0.002 0.023+0.002 0.019+0.002 0.020+0.002 0.020+0.002 0.021+0.002 0.018+0.002 0.022+0.002 0.018+0.002 0.017+0.002 0.014+0.002 0.010+0.002 0.017+0.002 0.019+0.002 0.015+0.002 0.011+0.002 0.008+0.002 0.015+0.002 0.015+0.002 0.016+0.005 0.012+0.002 0.009+0.002 0.015+0.002 0.017+0.002 0.015+0.002 0.019+0.002 0.018+0.002 0.024+0.002 0.017+0.002 0.018+0.002 0.019+0.002 0.021+0.002 0.018+0.002 0.021+0.002 0.020+0.002 0.017+0.002 0.015+0.002 0.013+0.002 0.018+0.002 0.014+0.002 0.012+0.002 0.007+0.001 0.008+0.001 0.015+0.002 0.016+0.002 0.014+0.002 0.011+0.002 0.009+0.002 0.016+0.002 0.016+0.002 0.017+0.003 0.023+0.003 0.026+0.003 0.024+0.002 0.019+0.002 0.019+0.002 0.020+0.002 0.019+0.002 0.018+0.002 0.019+0.002 0.016+0.002 0.019+0.002 0.015+0.002 0.012+0.002 0.017+0.002 0.017+0.002 0.012+0.002 0.011+0.002 0.009+0.002 0.014+0.002 0.017+0.002 0.014+0.003 0.010+0.003 0.008+0.002 0.012+0.002 0.015+0.002 0.015+0.002 0.018+0.002 0.012+0.002 0.019+0.002 0.019+0.002 0.019+0.002 0.013+0.001 0.016+0.002 0.015+0.002 0.016+0.002 0.016+0.002 0.018+0.002 0.014+0.002 0.012+0.002 0.017+0.002 0.017+0.002 0.013+0.002 0.010+0.002 0.008+0.002 0.011+0.002 0.016+0.002 0.012+0.002 0.010+0.002 0.008+0.002 0.014+0.002 0.020+0.002 0.018+0.002 0.020+0.002 0 '17+0 '02 0.026+0.003 0.022+0.002 0.019+0.002 0.020+0.002 0.020+0.002 0.018+0.002 0.017+0.002 0.014+0.002 0.017+0.002 0.015+0.002 0.013+0.002 0-017+0.002 0 '18+0.002 0 '13+0.002 0.010+0.002 0.006+0.001 0.014+0.002 0.015+0.002 0.012+0.002 0.010+0.002 0.008+0.002 0.013+0.002 0.016+0.002

C

'L*

C

~I

~

TABLE 8 (Continued)

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 K

ON 89/07/11 89/07/18 89/07/25 89/08/01 89/08/08 89/08/15 89/08/22 89/08/29 89/09/05 89/09/12 89/09/19 89/09/26 89/10/03 89/10/10 89/10/17 89/10/24 89/10/31 89/11/07 89/11/14 89/11/21 89/11/28 89/12/05 89/12/12 89/12/19 89/12/26 90/01/02 0.017+0.002 0.017+0.002 0.016+0.002 0.019+0.002 0.016+0.002 0.014+0.002 0.016+0.002 0.017+0.002 0.018+0.002 0.019+0.003 0.014+0.002 0.010+0.002 0.016+0.002 0.013+0.002 0.021+0.002 0.010+0.002 0.038+0.003 0.021+0.002 0.017+0.002 0.015+0.002 0.017+0.003 0.021+0.003 0.016+0.002 0.019+0.002 0.007+0.001 0.019+0.002 0.016+0.002 0.013+0.002 0.017+0.002 0.018+0.002 0.015+0.002 0.015+0.002 0.017+0.002 0.019+0.002 0.019+0.002 0.021+0.003 0.014+0.002 0.008+0.002 0.017+0.002 0.013+0.002 0.020+0.002 0.009+0.002 0.038+0.003 0.022+0.002 0.013+0.002 0.020+0.002 0.018+0.002 0.021+0.002 0.022+0.002 0.022+0.002 0.022+0.002 0.020+0.002 0.017+0 0.013+0 0.017+0 0.020+0 0.014+0 0.015+0 0.019+0 0.016+0 0.018+0 0.018+0 0.012+0 0.008+0 0.005+0 0.012+0 0.019+0 0.011+0 0.032+0 0.021+0 0.013+0 0.023+0 0.030+0 0.022+0 0.024+0 0.019+0 0.025+0 0.020+0

. 002

. 002

. 003

.002

.002

.002

.002

.002

.002

.002

.002

.002

.001

.002

.002

.002

.003

.002

.002

.002

.002

.002

.002

.002

.002

.002 0.019+0.002 0.015+0.002 0.018+0.002 0.022+0.002 0.014+0.002 0.016+0.002 0.017+0.002 0.018+0.002 0.018+0.002 0.017+0.002 0.010+0.002 0.008+0.002 0.016+0.002 0.013+0.002 0.022+0.002 0.010+0.002 0.040+0.003 0.020+0.002 0.014+0.002 0.020+0.002 0.019+0.002 0.018+0.002 0.020+0.002 0.021+0.002 0.022+0.002 0.015+0.002 0.019+0.002 0.016+0 002 0.020+0.002 0.024+0.003 0.016+0.002 0.016+0.002 0.017+0.002 0.016+0.002 0.017+0 002 0.018+0.002 0.014+0 '02 0.007+0.001 0.018+0.002 0.014+0.002 0.016+0.002 0.008+0.002 0.038+0.003 0.021+0.002 0.012+0.002 0.018+0.002 0.018+0.002 0.018+0.002 0.019+0.002 0.019+0.002 0.025+0.002 0.018+0.002 0.013+0.002 0.013+0.002 0.016+0.002 0.018+0.002 0.016+0.002 0.016+0.002 0.016+0.002 0.014+0.002 0.017+0.002 0.018+0.002 0.013+0.002 0.009+0.002 0.017+0.002 0.013+0.002 0.017+0.002 0.009+0.002 0.034+0.003 0.019+0.002 0.012+0.002 0.018+0.002 0 '20+0.002 0.017+0.002 0.019+0.002 0.022+0.002 0.020+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 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.8

<0.6

<0.8

<0.8

<0.9

<2.4

<1.3

<3.6

<9.2

<1.4 80zl3

<19

<2.7

<18

<3.0 (LLD

<0.8

<0.9

<0.9

<1.0

<1.4

<2.5

<1.4

<4.6

<9.7

<1.3 67tl2 13z9

<3.1

<18

<3.0

<LLD

<0.8

<0.8

<0.9

<1.0

<1.1 (2.1

<1.3

<4.0

<7.7

<1.1 95gl3

<21

<2.5

<18 (3.1 (LLD

<1.0

<1.2

<1.0

<1.3

<1.4 (2.8

<1.5

<5.2

<9.8

<1.4 63zl3 llg9

<3.1 12g9

<3.2

<LLD

<0.9

<0:9

<1.0

<1.0 (1.5

<2.3 (1.6

<5.5 (10.3

<1.1 82+13 23+11

<2.2 22g12

<2.9 (LLD

<0.9 (1.2

<1.0

<1.2

<1.2 (2.6

<1.9

<6.4 (11.5

<1.7 92+16 14+10

<3.0

<23

<4.5 (LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others*"

<0.9

<0.9

<0.9 (1.1

<1.4

<2.4

<1.7

<5.0

<8.9

<1.2 103gl4 44+15 (1.8

<21

<3.0

<LLD (1. 6

<1.2

<1.2

<1.2 (1.0

<1.9

<1.7

<5.5

<9.0

<1.5 81+15

<29 (1.8 17gl0

<3.4

<LLD

<2.5

<2.1

<3.6 (1.5

<3.0

<3.2

<2.0

<6.4

<13.6

<1.8

, 90+8

<19

<4.7

<24

<4.7 (LLD (1.1

<0.9

<1.1

<1.0 (1.5

<2.5

<1.9

<4.9

<7 '

<1.2 76gl3 44g15

<2.5 13z9

<3.2

<LLD

<1.4

<1.1

<1.0

<0.9

<1.6

<3.0

<1.6

<4.1 (11.0

<1.3 61+6 9+4

<5.3 (16

<2.9

<LLD

<1.1

<1.0

<1.0

<1.2

<1.8

<2.7

<1.9

<5.2

<9.5

<1.6 62+12 34+15 (1. 8

<20

<4.6

<LLD

• Location required by the Technical Specifications.

"* 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 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.1

<1.0

<0.9

<0.7

<1.1

<1.9

<1.3

<4.4

<8.1

<1.2 Blg12 31+12

<2.3

<18

<2.4

<LLD

<1.0

<1.1

<1.0

<1.0

<1.2

<2.8

<1.6

<4.4

<9.5

<1.2 72+12 32+14

<2.1

<20

<2.3

<LLD

<0.8

<0.8

<0.9

<0.9

<1,2

<2.5

<1.3

<4.4

<7.9

<1.3 80z13

<15

<1.6

<19

<3.5

<LLD

<0.7

<1.2

<1.3

<1.2

<1.7

<3.3

<1.7

<6.0

<6.9

<1.1 78gl4 22g14

<3.3

<22

<4.0

<LLD

<0.8

<1.0

<1.1

<0.9

<1.4

<3.0

<1.7

<4.7

<8.9

<1

~ 3 58zl2 36+14

<4.4

<21

<3.4

<LLD

<0.8

<0.9

<0.8

<0.7

<0.8

<1.6

<1.4

<4.0

<6.6

<0.8 94+13 37+12

<2.6

<16

<2.5

<LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RU-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.1

<1.1

<0.9

<1.0

<1.3

<2.1

<1.6

<5.4

<11.1

<1.2 98z15 24+14

<2.7

<21

<3.6

<LLD

<1.4

<0.6

<1.0

<1.0

<1.6

<2.4

<1.6

<4.8

<7.7

<1.1 85g13 33+14

<1.8

<20

<3.1

<LLD

<0.4

<0.9

<0.9

<1.0

<1.2

<3.1

<1.5

<4.9

<8.4

<1.2 73gl2 20+10

<1.5

<18

<3.5

<LLD

<0.8

<1.3

<1.0

<1.0

<2.0

<2.4

<1.8

<5.5

<9.8

<1.4 71+13 36+15

<2.6

<22

<4.0

<LLD

<0.5

<0.8

<0.7

<0.8

<1.4

<1.2

<1.2

<3.5

<7.5

<0.9 52+10 11+8

<3.0

<13

<2.8

<LLD

<1.7

<1.0

<1.4

<1.5

<2.6

<3.2

<2.2

<6.6

<10.4

<1.9 75+16

<25

<2.6

<26

<5. 6

<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 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.9

<1.1

<0.9

<0.7

<0.9

<2.4

<1.3

<3.8

<7 '

<1.0 68z12

<12

<1.4

<17

<2.8

<LLD

<1.4

<1.1

<1.3

<1.1

<1.5

<2.3

<1.8

<5.9

<10.7

<1.2 64+14 22zl4

<1.8

<23

<4.0

<LLD

<1

~ 0

<0.6

<0.7

<0.8

<1.0

<1.8

<1.3

<3.5

<6.4

<1.0 78gll 30g10

<1.8

<14

<2.2

<LLD

<1.1

<0.9

<0.9

<0.7

<1.0

<1.7

<1.4

<4.0

<7.5

<1.0 68g11 39+12

<2.2 19+9

<2.5

<LLD

<1.0

<1.2

<1.3

<1.5

<1.9

<4.0

<2.1

<6.8

<9.2

<1.7 87+17 18+13

<5.6

<24

<4.6

<LLD

<0.8

<0.9

<0.9

<1.0

<0.8

<2.1

<1.4

<4.5

<8.5

<1.2 82+13 25tl2

<1.4

<19

<3.0

<LLD Nuclides July August September October November December Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RU-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others"*

<0.8

<0.7

<1.0

<1.0

<1.0

<2.0

<1.5

<4.7

<8.9

<1

~ 2 99+14 35+13

<1.7

<18

<2.6

<LLD

<0.9

<1.0

<1.1

<1.2

<1.7

<2.3

<1.8

<5.2

<11.6

<1.2 83z16 32gl3

<4.2

<22

<3.5

<LLD

<1.5

<1.5

<2.1

<1.2

<2.2

<3 '

<1.6

<5.2

<9.6

<1.7 64+6 12z5

<2.8

<16

<4.1

<LLD

<0.8

<1.0

<1.1

<1.2

<1.2

<2.4

<1.7

<5.5

<9.2

<1.4 87+13 32gl3

<3.5

<21

<3.8

<LLD

<1.3

<'l. l

<1.1

<1.2

<1.6

<3.0

<1.4

<4.3

<10.1

<1.3 53+6 11+4

<4.2 25+7

<2.9

<LLD

<0.9

<1.0

<0.9

<0.9

<1.4

<2.7

<1.8

<4.7

<9.2

<1.1 56+11 40+13

<3.3

<19

<3.4

<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 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.7

<1.1

<0.8

<1.3

<1.4

<2.2

<1.9

<5,8

<9.8

<1.4 93z16 30zl5

<3.4

<21

<3.5

<LLD

<0.6

<0.6

<0.9

<1.0

<1.2

<2.5

<1.5

<4.3

<10.6

<1.4 78+13 46gl6

<2.6 27gl 4

<2.9

<LLD

<1.1

<1.0

<0.9

<0.8

<1.3

<2.8

<1.7

<4.7

<9.3

<1.4 85zl5 23g12

<1.9

<20

<3.5

<LLD

<0.8

<0.9

<0.8

<0.7

<1.1

<2.1

<1.6

<4.5

<7.6

<1.1 82g14 41gl6

<3 '

19g10

<2.9

<LLD

<1.3

<1.3

<0.9

<0.9

<1.8

<3 '

<2.3

<6.4

<13.1

<2.0 78z16 39z16

<4.3

<22

<5.5

<LLD

<1.5

<1.0

<0.9

<1.3

<0.9

<3.3

<2.0

<5.2

<9.1

<1.4 98+16 16+11

<4.5 12+8

<4.5

<LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Er-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.1

<0.9

<1.2

<1.1

<1.4

<2.5

<1.8

<5.6

<10.0

<1.2 99+15

<27

<2.2

<20

<3.6

<LLD

<1.2

<0.9

<1.0

<1.1

<1.3

<2.0

<1.7

<6.0

<7.0

<0.9 81+13 36+15

<1.8

<21

<2.8

<LLD

<1.6

<1.2

<1.3

<1.2

<2.1

<3.2

<2.4

<6.3

<11.7

<1.7 83gl5 22gl3

<2.1

<21

<4.6

<LLD

<0.5

<1.1

<1.2

<1.0

<1.5

<2.9

<1.8

<5.3

<8.8

<1.2 69gl3 28gl4

<3.1

<22

<3.9

<LLD

<0.8

<1.0

<1.0

<0.9

<1.7

<2.7

<1.9

<5.0

<8.3

<1.4 70zl4 44+16

<2.1

<19

<6.6

<LLD

<1.2

<1.1

<1.1

<1.4

<1.8

<2.9

<2.1

<5.0

<11.1

<1.4 77+15 32+14

<3.5

<23

<4.7

<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 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.4

<0.9

<0 '

<1.0

<1.2

<2.5

<1.6

<4.9

<6.8

<1.2 86gl3 34g15

<2.1

<20

<3.2

<LLD

<1.6

<1.4

<1.0

<1.5

<1.6

<3.4

<1

~ 8

<5.8

<7.4

<1.4 65z13 24tl4

<3.2

<21

<3.4

<LLD

<0.9

<0,8

<0.9

<0.9

<1.1

<2.1

<1.2

<3.5

<7;6

<0.9 70+11 T2g8

<3.7

<14

<3.3

<LLO

<0.9

<1.2

<1.0

<0.9

<1.5

<3.0

<1.6

<4.8

<11.7

<1.3 76z13 10'3.0

<18

<2.8

<LLD

<1.1

<0.8

<0.9

<0.8

<1.2

<2.2

<1.5

<4.7

<8.4

<1.2 95z14 47g15

<1.8

<19

<2.7

<LLO

<1.2

<1.5

<l.l

<1.1

<1.6

<2.3

<1.6

<4.6

<10.7

<1.3 84+7

<14

<4.4

<16

<3.8

<LLD Nuclides July August September October November December Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.2

<1.1

<1.0

<1.1

<1.4

<2.2

<1

~ 6

<4.9

<11.3

<1.5 101gl6

<19

<3.4

<21

<3.9

<LLO

<1.9

<1.7

<1.8

<1.6

<2.3

<4,5

<1.9

<5.7

<12.5

<1.6 87z8 18z5

<4.0

<21

<4.0

<LLD

<1.1

<1.0

<1.0

<1.1

<1.6

<2.9

<1.7

<5.1

<8.0

<1.2 68g12 31gl3

<3.0

<19

<3.8

<LLD

<1.0

<0.8

<1.0

<1.2

<1.2

<2.7

<1.8

<5.2

<10.3

<1.6 88zl4 41zl4

<2.9

<21

<5.0

<LLD

<0.8

<0.8

<0.7

<0.8

<1

~ 0

<2.2

<1.3

<4.3

<7.7

<1.2 66gll 35gll

<2.3

<16

<3.2

<LLD

<1.9

<1.1

<1.3

<1.3

<2.0

<3.0

<2.3

<5.7

<13.5

<1.7 61+14

<34

<4.2

<25

<4.5

<LLD

• Location required by the Technical Specifications.

• • Other plant related radionuclides.

-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 Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Er-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

January

<1.6

<1.1

<1.5

<1.0

<1.6

<3;5

<2.2

<5.3

<14.7

<1.0 77gl5 26gl4

<3.9 20g12

<2.5

<LLD February

<1.1

<1.2

<1.1

<1.1

<1.6

<3 '

<1.1

<3.4

<9;6

<1.2 66+6 13g5

<2.6

<14

<2.7

<LLD March 1

<0.9

<0.8

<0.8

<0.7

<1.1

<2.2

<1.6

<4.6

<8.2

<1.1 85gll 41+12

<2.7

<17

<3.4

<LLD April

<1.1

<1.2

<0.9

<1.0

<1.7

<2.3

<1.7

<5.4

<9.1

<1.1 63g12 4lgl5

<2.3

<21

<3 '

<LLD Hay

<0.8

<1.0

<1.0

<0.9

<1.2

<2.8

<1.7

<5.0

<8.1

<1.0 80gl3 30z13

<2.3

<20

<3.2

<LLD June

<1.4

<1.1

<1.1

<1.1

<2.0

<3.0

<2.0

<5.8

<13.1

<1.7 98z17 19+13

<4.4

<23

<4.5

<LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.3

<1.3

<1.0

<1.1

<1.5

<3.0

<2.0

<5.8

<10.2

<1.3 87+14 57g18

<3.0

<24

<3.3

<LLD

<1.3

<0.9

<1.2

<1.2

<1.5

<3.1

<2.0

<5.8

<10.5

<'1.6 83+14 54+17

<3.4 25g12

<3.5

<LLD

<1.2

<0.8

<1.1

<1.1

<1.9

<1.7

<1.8

<5.1

<12.5

<1.6 89+16 27+14

<2.2

<19

<4.2

<LLD

<1.3

<1.0

<0.9

<1.0

<1.3

<2.6

<1.5

<5.2

<7.1

<1.3 63gl 2 50p15

<1.3

<20

<3.4

<LLD

<0.9

<1.1

<0.8

<0.7

<1.3

<2.7

<1

~ 8

<4.9

<7.9

<1.1 68zl 2 30+12

<1.9

<17

<3.4

<LLD

<0.9

<0.4

<0.9

<0.6

<1.0

<2.6

<1.4

<3.7

<8.1

<1.0 47+10 17+10

<2.2

<15

<3.4

<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 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.2

<1.0

<1.0

<0.9

<1.2

<2.4

<1.4

<4,4

<8.6

<1.2 94gl4 2lzll

<2.6

<17

<2.7

<LLD

<2.3

<1.1

<1.0

<0.9

<1.0

<2.8

<1.0

<3.2

<8.5

<1.3 82g6 15t5

<3.7 9g5

<2.5

<LLD

<0.8

<1.0

<0.7

<0.7

<1.0

<2.2

<1.1

<3.6

<8.6

<1.2 83+13 12'2.4

<13

<3.2

<LLD

<1.0

<0.8

<0.9

<1.0

<1.4

<2.1

<1.6

<4.8

<8.8

<1.1 72zl2 39g14

<1.9

<19

<3.5

<LLD

<0.9

<1.1

<1.0

<1.0

<1.3

<1.7

<1.7

<5.1

<6.6

<1.3 86gl4 29gl2

<2.7

<19

<3.4

<LLD

<1.1

<0.7

<1.0

<1.3

<1.4

<2.8

<1.7

<5.0

<10.4

<1.3 92+15

<21

<2.5

<20

<4.0

<LLD

~,

Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.8

<1.2

<1.0

<1.1

<1.4

<3.1

<1.6

<5.4

<10.6

<1.3 76g14 41+15

<2.2

<23

<3 '

<LLD

<1.1

<0.5

<1.2

<1.2

<1.4

<2.8

<1.9

<4.7

<8.6

<1.4 88+14 38gl5

<2.2

<20

<3.5

<LLD

<0.5

<0.8

<0.7

<0.8

<1.3

<1.8

<1.2

<3.4

<8.2

<1.1 73gll 39+12

<2.3

<16

<2.9

<LLD

<0.9

<1.1

<0.9

<1.0

<1.3

<2 '

<1.6

<5,0

<9.2

<1.3 70gl3 30zl3

<3.1

<22

<3.2

<LLD

<0.9

<0.9

<0.8

<0.8

<1.3

<2.5

<1.4

<3.9

<7.0

<1.1 71+12 20+10

<2.6

<17

<3 '

<LLD

<0.7

<0.9

<1.0

<1.0

<1.1

<2.7

<1.8

<4.5

<8.2

<1.2 75+12 30+12

<2.0

<18

<4.0

<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 1

April Hay June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.1

<1.0

<0.9

<1.0

<1.7

<2.5

<1.6

<5.0

<9 '

<1.2 78+13 31+12

<2.5

<19

<2.7

<LLD

<1.1

<1.2

<1.1

<1.3

<1.9

<2.9

<1.6

<5.6

<8.4

<1.4 61gl 3 14gl 2

<3.2

<24

<3 '

<LLD

<0.6

<0.8

<0.9

<0.5

<1.2

<2.0

<1.2

<3.5

<8.1

<0.8 78+13

<17

<2.1

<16

<3.2

<LLD

<1.4

<1.0

<0.9

<1.0

<1.2

<3.0

<1.6

<5.1

<11.8

<1.3 64+12 37zl 4

<2.2

<20

<2.4

<LLD

<0.7

<0.9

<1.0

<0.7

<1.1

<2.

7'1.6

<4.1

<7 '

<1.2 79+12 36g14

<1.2

<18

<2.4

<LLD

<0.9

<0.7

<0.9

<0.8

<1.1

<2.3

<1.3

<4.2

<7.2

<1.0 85+13 35gll

<1

~ 6

<15

<2.5

<LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.8

<1.4

<1.1

<1.2

<2.0

<3.5

<2.0

<7.6

<11.8

<2.2 75zl7 46+21

<4.6

<29

<4.4

<LLD

<2.3

<1.8

<2.3

<1.5

<2.3

<3.5

<1

~ 8

<6.5

<12.8

<1.7 70z7 14+6

<4.1 12'3.8

<LLD

<0.9

<1.0

<0.9

<0.8

<1.2

<2.9

<1.4

<4.3

<8.4

<1.3 57+11 33+12

<2.6 17g12

<3.6

<LLD

<1.0

<0.8

<0.8

<0.9

<1.2

<2.7

<1.4

<5.1

<9.5

<1.2 49gll 54g16

<2.7

<19

<3.2 (1) 0.9'.7

<1.1

<0.9

<0.6

<1.4

<2.3

<1.5

<3.9

<7.7

<1.0 55+9 23+10

<1.9

<15

<3.0 (2)

<1.5

<1.3

<1.6

<1.2

<1.8

<3.4

<1.8

<4.9

<12.2

<1.4 54g6

<17

<5.0

<18

<3.7

<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 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RU-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others"*

<1.8

<1.5

<1.2

<1.4

<2.1

<3 '

<1.9

<5.6

<9.6

<1.4 88g16

<14

<1.9 31zl3

<3.4

<LLD

<1.5

<0.8

<0.9

<0.9

<1.1

<1.6

<1.2

<3.8

<9.4

<1.0 65gl 2 8'1.4

<16

<2.8

<LLD

<1.2

<0.6

<0.8

<0.6

<1.1

<2.8

<1.4

<4.0

<8.2

<1.2 90+13 22gl0

<2.9

<16

<3.1

<LLD

<0.8

<0.8

<1.0

<0.8

<1.0

<2.2

<1.7

<4.8

<6.6

<1.1 61gl 1 45gl 4

<2.3

<18

<2.9

<LLD

<1.2

<1.3

<0.9

<1.2

<1.3

<2.2

<1.5

<4.2

<8.7

<1.3 73g14

<18

<1.7

<21

<3.4

<LLD

<1.5

<0.8

<1.2

<1.1

<1.5

<3.0

<1.8

<5.6

<9.3

<'1.6 74+13 29+13

<2.5

<24

<3.8

<LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.5

<1.1

<1.5

<1.1

<1.6

<3.2

<1.7

<5.0

<14

<1.5 86z16 26gl 5

<3.0

<23

<2.7

<LLD

<1.0

<1.1

<1.1

<0.9

<1.2

<2.6

<1.9

<5.8

<9.9

<1.1 68+12 50zlS

<3.1 15g9

<3.4

<LLD

<1.4

<1.1

<1.3

<0.9

<1.4

<2.9

<1.4

<4.2

<9.5

<1.4 65z6

<14

<4.9

<16

<3.6

<LLD

<1.7

<1.0

<1.1

<1.1

<1.2

<3.0

<1

~ 7

<5.3

<11.1

<1

~ 2 52zll 49zl6

<3.2

<22

<3.2 (1)

<0.9

<0.9

<0.8

<0.9

<1.2

<2.6

<1.5

<4.1

<8.1

<1.3 52g10 30gll

<1.7

<16

<3.4 (2)

<1.1

<1.4

<0.9

<1.1

<1.1

<2.8

<1.6

<4.3

<10.2

<0.9 45+11

<12

<3.3

<19

<4.2

<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 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.3

<0.8

<1.1

<1.1

<1.4

<2.7

<1.5

<4.6

<8.8

<1.1 61gl2 33+14

<2.5

<19

<2.8

<LLD

<1.1

<1.0

<1.0

<1.0

<1.1

<2.3

<1.0

<3.2

<7 '

<1.0 53z5 14'0.6

<13

<2.2

<LLD

<0.6

<0.8

<0.7

<0.8

<0.9

<1

~ 8

<1.3

<3.7

<6.0

<0.9 68zll 34+11

<3.2

<15

<2.9

<LLD

<1.6

<1.2

<0.8

<0.8

<1.3

<2.8

<1.8

<5.3

<11.2

<1.5 52g12 35+14

<4.0

<20

<3.0

<LLD

<1.7

<1.2

<1.0

<1.2

<1,4

<3.4

<1.7

<5.6

<11.3

<1.5 50+12 43+16

<3.7

<22

<4.0

<LLD

<2.0

<1.4

<1.5

<1.3

<1.7

<3.7

<1.8

<5.1

<8.8

<1.4 85g7 11+5

<3.0

<17

<3.5

<LLD Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.1

<1.0

<1.2

<1.2

<1.8

<3.4

<1.9

<6.0

<11.0

<1.5 88+14 47+16

<3.4

<22

<3.6

<LLD

<1.3

<1.3

<1.1

<1.5

<1.9

<3.4

<1.8

<6.1

<10.2

<1

~ 7 57gl5 52g19

<3.0

<25

<3.4

<LLD

<1.5

<1.1

<0.9

<0.7

<1.1

<2.8

<1.6

<3.9

<8.8

<1.1 72+13 14+10

<2.2

<11+9

<2.6

<LLD

<1.0

<1.1

<1.0

<1.0

<0.8

<3.1

<1.6

<5.1

<9.6

<1.3 69+13 57zl7

<2.3 16+9

<3.0

<LLD

<0.9

<0.9

<0.8

<0.7

<1.1

<1.9

<1.6

<3 '

<7.9

<1.0 61+11 46gl4

<2.9

<14

<5.4 (1)

<1.6

<1.4

<1.0

<0.9

<1.4

<2.9

<1.9

<4.9

<9.9

<1.5 54+'I 4 29+14

<1.9

<21

<4.5

<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 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 RU-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.4

<1

~ 3

<1.2

<1.2

<1.9

<2.8

<2.1

<5.0

<12.2

<1.4 83+14 40gl6

<4.4

<19g12

<3.9

<LLD

<1.2

<1.3

<1.1

<1.2

<2.2

<4.1

<1.9

<6.2

<10.0

<1.2 74+15 40gl6

<2.0

<23

<3.8

<LLD

<0.8

<1.0

<1.1

<1.1

<1.1

<2.0

<1.6

<4.8

<8.8

<1.5 74+13 26z12

<3.2

<17

<3.9

<LLD

<0.7

<1.2

<1.1

<0 '

<1.1

<2.7

<1.6

<5.2

<8.1

<1.3 62z11 33zl2

<2.7 16z8

<3.4

<LLD

<1.7

<1.9

<1.2

<1.6

<1.8

<2.9

<2.2

<7.1

<10.1

<1.8 82+16

<26

<2.2

<23

<3.7

<LLD

<0.9

<1.3

<1.3

<1.3

<1.3

<3.0

<1.8

<5.4

<10.3

<2.0 100+16 23g14

<2.1

<25

<4.3 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.6

<0.9

<1.0

<1.1

<1.7

<2.3

<1.6

<5.6

<9.9

<1.3 74g14 27zl3

<3.2

<19

<3.4

<LLD

<1.5

<1.1

<1.2

<0.8

<1.3

<3.1

<1.8

<5.0

<5.2

<1.3 85g18

<14. 3

<3.4

<22

<3.2

<LLD

<0.7

<0.7

<0.7

<0.9

<1.1

<2.6

<1.6

<4.1

<7 '

<1.2 70+11 34+12

<2.4

<18

<2.4

<LLD

<0.8

<1.0

<1.1

<1.1

<1.6

<3.1

<1.8

<5.3

<9.8

<1.7 44gl 2 38+16

<2.8

<24

<3.5

<LLD

<0.9

<0.8

<1.0

<1.2

<1.2

<1.9

<1.4

<4.0

<7.7

<1.2 49+10 21+10

<1.5

<16

<3.0

<LLD

<1.2

<1.3

<0.9

<1.2

<1.9

<3.2

<2.1

<5.5

<10.3

<1.5 51+13

<33

<2.3

<20

<4.3

<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 1

April May June Co-60 Hn-54 Cs-134 Cs-137 Nb-95 lr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

Nuclides

<1.0

<1.4

<1.0

<1.0

<1.4

<2.0

<1.8

<5.3

<8.5

<1.2 94gl5 24gl 2

<3.2

<21

<3.

1

<LLD July

<1.0

<0.9

<1.0

<1.0

<1.3

<1.7

<1.4

<4.8

<8.7

<1.1 68+12 33g14

<2.8

<18

<2.3

<LLD August

<1.3

<1.2

<1.2

<1.1

<1.3

<2.3

<1.6

<5.8

<11.1

<1.2 78+14

<32

<2.7

<22

<4.0

<LLD September

<1.6

<1.0

<1.2

<1.3

<1.8

<3.2

<1.6

<5.6

<9.4

<1.4 70gl4 25gl3

<2.6

<23

<3.1

<LLD October

<0.9

<1.1

<1.0

<1.1

<1.3

<2.2

<1.6

<5.0

<11.3

<1.3 79+13 28+13

<1.5

<19

<3.3

<LLD November

<0.8

<0.5

<0.8

<0.7

<1.2

<2.9

<1.5

<4.5

<7.1

<0.9 99+14

<18

<1.5

<18

<3.1

<LLD December Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.7

<0.9

<0.8

<0.9

<1.3

<2.1

<1.5

<4.7

<7.6

<1.0 103213 31gl2

<2.1

<18

<3.0

<LLD

<0.8

<1.0

<1.1

<0.9

<0 '

<2.7

<1.7

<5.0

<11 '

<1.3 84gl4 25gl3

<2.6

<21

<3.3

<LLD

<1.8

<1.3

<2.1

<1.2

<1.4

<3.6

<1.7

<5.1

<8.6

<1.3 74g6 10+5

<3.5

<17

<3.2

<LLD

<1.8

<1.2

<1.4

<1.4

<2.0

<3.5

<2.0

<6.2

<11.4

<1.7 70gl4

<25

<6.1

<26

<4.7

<LLD

<0.6

<0.8

<0.8

<0.7

<1.0

<2.0

<1.4

<4.1

<7.5

<0.8 57+10 34+10

<3.2

<16

<3.4

<LLD

<1.2

<1.0

<0.9

<1.1

<1.4

<3.0

<1.6

<4.9

<8.1

<1.3 67+12 27+12

<1.7

<16

<3.2

<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 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

Nuclides

<1.6

<1.3

<1.2

<1.2

<1.2

<2.7

<1.9

<5.6

<10 '

<1

~ 7 77g15

<30

<4.2

<24

<3.8

<LLD July

<0.6

<0.9

<0.9

<0.9

<1.1

<1.5

<1.5

<4.2

<8.4

<1.2 69gll 31gl 3

<3.0 14~8

<2.5

<LLD August

<0.3

<0.7

<0.8

<0.8

<1.1

<1.9

<1.2

<3.9

<5.4

<0.8 82zll 27zl0

<2.4 16g8

<3.1

<LLD

<1.2

<1.1

<1.1

<0.8

<1.7

<2.1

<1.7

<5.7

<9.0

<1.3 76g14 34zl 5

<3 '

<23

<3.4

<LLD September October

<0.6

<1.2

<1.2

<1.1

<1.4

<2.5

<1

~ 6

<4.6

<8.8

<1.1 76+12 48gl 4

<1.8

<18

<3.2

<LLD November

<1.0

<0.7

<0.7

<0.9

<0.9

<2.4

<1.4

<4.2

<8.7

<1.2 85+12 38gl 2

<2.9

<16

<3.0

<LLD December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 RU-103 Be-7 K-40 La-140 Ra-226 I-131 Others"*

<1.2

<1.1

<0.9

<1.0

<1.0

<2.9

<1.6

<5.6

<12.2

<1.5 98zl5 24zl2

<1.6

<21

<3.5

<LLD

<1.3

<1.2

<1.0

<1.0

<1.1

<2.3

<1.6

<5.7

<9.3

<1.5 74zl2 47g15

<3.2

<21

<3.0

<LLD

<0.6

<1.5

<1.1

<1

~ 3

<2.0

<3.1

<1.9

<5.4

<10.0

<1.2 86zl5 25+14

<3.6

<24

<4.3

<LLD

<1.3

<1.1

<1.0

<1.2

<1.7

<3.3

<1.9

<5.2

<10.8

<1.3 76zl4 25zl2

<2.7

<22

<4.4

<LLD

<1.0

<1.0

<0.8

<0.9

<1.2

<2.1

<1.4

<3.8

<7.9

<1.2 66+12 9+7

<3.9 12'4.3

<LLD

<1.9

<1.3

<1.2

<1.5

<2.0

<2.8

<2.1

<6.2

<13.1

<1.5 51+13

<22

<3.4

<24

<4.4

<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 Hn-54 Cs-134 Cs-137 Nb-95 lr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.2

<0.4

<0.7

<0.7

<1.1

<2.1

<1.4

<4.4

<6.6

<1.0 70g12 32gl2

<2.0

<17

<2.7

<LLD

<1.4

<1.1

<1.1

<1,3

<1.7

<2.6

<1.8

<5.5

<10.0

<1.6 75g15

<29

<2.0

<23

<4.0

<LLD

<0.9

<1.1

<0.9

<0.9

<1.3

<2.7

<1.9

<5.0

<10.6

<1.1 79gl3 32g14

<1.8

<18

<4.0

<LLD

<0.9

<0.8

<0.9

<0.8

<1.2

<2.2

<1.5

<3.6

<8.7

<1.1 60+11 12'2.3

<15

<2.3

<LLD

<1.2

<1.0

<F 1

<0.9

<1.5

<3.0

<1.8

<5.3

<7.6

<1.4 88+14 Slzl6

<2.9

<21

<3.8

<LLD

<1.0

<0.7

<1.0

<1

~ 0

<1.1

<2.6

<1.6

<4.4

<9.4

<1.3 79+12 29+12

<1.5

<18

<3.6

<LLD Nuclides July August September October November December Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.2

<0.6

<1.2

<1.1

<1.8

<2.9

<1.6

<4.5

<10.4

<1.4 105+16 21+14

<2.5

<21

<3.6

<LLD

<0.6

<0.9

<1.2

<1.4

<1.4

<3.0

<1.6

<4.9

<11.0

<1.2 84+15

<22

<3.5 25+13

<3 '

<LLD

<0.5

<0.7

<0.7

<0.7

<1.3

<2,6

<1.4

<3.9

<7.9

<1.1 69gll 34gl 2

<3.8

<15

<3 '

<LLD

<0.8

<0.9

<0.8

<0.9

<1.2

<2.6

<1.8

<5.6

<12.0

<1.1 75gl4 58g19

<1.9

<23

<4.2

<LLD

<0.7

<0.6

<0.8

<0.7

<1.1

<2.4

<1.5

<4.3

<7.8

<1.2 64+11 43+13

<2.7

<17

<3.8

<LLD

<1.3

<1

~

1

<1.0

<1.2

<1.3

<3.1

<1.7

<3.5

<11.7

<1.3 72g14

<22

<1.9

<22

<4.0

<LLD

• - Optional sample location

• • Other plant related radionuclides.

-85

\\

~

r r r

~

'I'

~ ~

~ Nr

\\

~ <<1

~ r I

\\

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 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<0.6

<0.8

<1.2

<1.2

<1.4

<3.0

<1.7

<5.4

<8.1

<1.4 87+14 32g14

<2.2

<20

<3.6

<LLD

<1.4

<1.2

<1.3

<1.3

<1.9

<3.0

<2.0

<4.9

<10.0

<1.3 56+12 22gl 4

<2.6

<21

<3.4

<LLD

<0.9

<0.8

<0.9

<0.7

<1.3

<1.9

<1.1

<3.4

<8.3

<1.0 70zll 20g9

<2.8

<14

<2.7

<LLD

<1.8

<1.0

<1.3

<1.1

<1.3

<2.8

<1.7

<5.6

<12.1

<1.6 76gl 4 2lgl 4

<3 '

<20

<3.5

<LLD

<1.0

<0.9

<0.8

<1.1

<1.1

<2.4

<1.6

<4.6

<7 '

<1.1 88zl3 32g13

<3.2

<18

<2.6

<LLD

<1.4

<1.1

<1.0

<0.8

<1.4

<2.9

<1.6

<5.0

<10.5

<1.3 94+7 10+4

<4.8

<16

<3.0

<LLD Nuclides July August September October Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Kr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131 Others**

<1.0

<0.7

<0.9

<1.1

<1.4

<2.3

<1.6

<4.7

<9.4

<1.2 98214 31gl3

<1-8

<18

<3.2

<LLD

<1.3

<1.8

<1

~ 8

<1.2

<2.1

<4.7

<1.9

<5.7

<11.7

<1.7 82z8 10'5.4 22g7

<3.4

<LLD

<1.5

<1.2

<1.4

<1.3

<2.2

<2.9

<1.7

<4.2

<10.3

<1.4 82z7

<18

<5.7

<17

<4.9

<LLD

<0.5

<1.2

<1.2

<1.3

<1.7

<2.3

<2.0

<5.5

<9.3

<1.4 69zl3 54+17

<1.6

<22

<4.0

<LLD

<1.2

<1.1

<1.0

<1.0

<1.7

<2.9

<2.1

<4.9

<10.7

<1.4 66g13

<25

<3 '

<19

<5.4

<LLD

<1

~ 2

<0.9

<1.3

<1.1

<1.3

<2.3

<1.6

<5.0

<7.7

<0.9 45+12

<14

<2.9

<17

<4.5

<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 89/01/16 89/01/23 89/01/30 89/02/06 89/02/13 89/02/21 89/02/27 89/03/06 89/03/13 89/03/20 89/03/27 89/04/03 89/04/10 89/04/17 89/04/24 89/05/01 89/05/08 89/05/15 89/05/22 89/05/30 89/06/05 89/06/12 89/06/19 89/06/26 89/07/03

<0.009

<0.008

<0.008

<0.010

<0.012

<0.009

<0.010

<0.013

<0.011

<0.008

<0.009

<0.011

<0.007

<0.008

<0.009

<0.009

<0.010

<0.007

<0.012

<0.011

<0.009

<0.009

<0.012

<0.008

<0.011

<0.008

<0.007

<0.007

<0.006

<0.009

<0.007

<0.007

<0.011

<0.007

<0.011

<0.019

<0.006

<0.007

<0 F 008

<0.006

<0.009

<0.009

<0.008

<0.009

<0.009

<0.010

<0.010

<0.011

<0.012

<0.008

<0.008

<0.010

<0.008

<0.007

<0.008

<0.008

<0.007

<0.006

<0.007

<0.008

<0.007

<0.008

<0.008

<0.008

<0.007

<0.006

<0.008

<0.010

<0.010

<0.009

<0.008

<0.005

<0.007

<0.008

<0.009

<0.011

<0.010

<0.006

<0.010

<0.009

<0.010

<0.008

<0.010

<0.008

<0.015

<0.006

<0.008

<0.005

<0.010

<0.008

<0.008

<0.013

<0.007

<0.008

<0.005

<0.006

<0.009

<0.013

<0.009

<0.009

<0.009

<0.007

<0.010

<0.009

<0.010

<0.009

<0.007

<0.008

<0.007

<0.009

<0.008

<0.010

<0.007

<0.010

<0.007

<0.010

<0.006

<0.012

<0.007

<0.008

<0.009

<0.009

<0.011

<0.008

<0.012

<0.009

<0.010

<0.009

<0.007

<0.009

<0.008

<0.008

<0.009

<0.009

<0.007

<0.006

<0.010

<0.007

<0.013

<0.011

<0.009

<0.012

<0.016

<0.008

<0.007

<0.008

<0.007

<0.008

<0.008

<0.010

<0.010

<0.013

<0.008

<0.011

<0.013

<0.008

<0. 008

<0.012

<0.006

<0.008

<0.010

<0.008

<0.007

<0.009

<0.007

<0.007

<0.008

<0.010

<0.007

<0.007

<0.007

<0.009

<0.006

<0.007

<0.009

<0.009

<0.007

<0.010

<0.006

<0.007

<0.010

<0.007

<0.006

<0.010

<0.011

<0.004

<0.007

<0.006

<0.007

<0.007

<0.011

<0.008

<0.010

<0.010

<0.009

<0.010

<0.007

<0.010

<0.008

<0.007

<0.014

<0.009

<0.009

<0.008

<0.011

<0.006

<0.008

<0.006

<0.007

<0'12

<0.009

<0.008

<0.007

<0.009

<0.009

<0.009

<0.008

<0'08

<0.011

<0.008

<0.009

<0'11

<0.008

<0.008

<0.009

<0.014

<0.009

<0.011

<0.011

<0.013

<0.009

<0.007

<0.008

• SAMPLE LOCATIONS REQUIRED

• • PUMP INOPERATIVE BY TECHNICIAL SPECIFICATIONS

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 89/07/17 89/07/24 89/07/31 89/08/07 89/08/14 89/08/21 89/08/28 89/09/05 89/09/11 89/09/18 89/09/25 89/10/02 89/10/09 89/10/16 89/10/23 89/10/30 89/11/06 89/11/13 89/11/20 89/11/27 89/12/04 89/12/11 89/12/18 89/12/26 90/01/02

<0.007

<0.008

<0.014

<0.008

<0.010

<0.008

<0.009

<0.009

<0.014

<0.022

<0.030

<0.010

<0.012

<0.010

<0.011

<0.008

<0.008

<0.008

<0.011

<0.006

<0.011

<0.008

<0.012

<0.013

<0.012

<0.012

<0.007

<0.012

<0.009

<0.011

<0.008

<0.008

<0.013

<0.010

<0.012

<0.008

<0.011

<0.009

<0.008

<0.011

<0.010

<0.008

<0.010

<0.011

<0.008

<0.007

<0.011

<0.011

<0.015

<0.012

<0.010

<0.011

<0 ~ 007

<0.006

<0.010

<0.008

<0.010

<0.010

<0.010

<0.010

<0'09

<0.010

<0.007

<0.009

<0.012

<0.009

<0.013

<0.008

<0.008

<0.011

<0.010

<0.010

<0.011

<0.009

<0.013

<0.013

<0.008

<0.010

<0.011

<0.010

<0.011

<0.008

<0.009

<0.013

<0.008

<0.010

<0 013

<0.016

<0.009

<0.009

<0.007

<0.009

<0.008

<0.010

<0.007

<0.012

<0.039

<0.007

<0.009

<0.010

<0.015

<0.014

<0.011

<0.013

<0.008

<0.009

<0.012

<0.007

<0.013

<0.010

<0.013

<0.011

<0.009

<0.012

<0.011

<0.010

<0.012

<0.012

<0.008

<0.007

<0.009

<0.010

<0.013

<0.008

<0.010

<0.012

<0.011

<0.013

<0.011

<0.011

<0.006

<0.007

<0.006

<0.009

<0.009

<0.010

<0.008

<0.011

<0.009

<0.009

<0.009

<0.011

<0.012

<0.006

<0.007

<0.007

<0.009

<0.010

<0.009

<0.011

<0.011

<0.008

<0.011

<0.008

<0.012

<0.009

<0.006

<0.012

<0.009

<0.008

<0.008

<0'10

<0.009

<0'13

<0.010

<0.008

<0.010

<0.011

<0.007

<0.008

<0.011

<0.006

<0.009

<0.009

<0.008

<0.009

<0.012

<0.009

<0.009

<0.011

<0.010

<0.012

<0.011

<0.012

<0.011

<0.010

<0.008

<0.009

<0.012

<0.010

<0.009

<0.010

<0.007

<0.008

<0.008

<0.007

<0.009

<0.009

<0.014

<0.010

<0.011

<0.007

<0.009

<0.010

<0.012

<0.010

<0.015

<0.011

<0.009

<0.010

<0.008

<0.010

<0.009

<0.007

<0.007

<0.013

<0.008

<0.009

<0 '12

<0.011

<0.009

<0.011

<0.007

<0.007

<0.008

<0.011

<0.009

<0.009

<0.011

<0.009

<0.015

<0.016

<0.011

<0.013

• SAMPLE LOCATIONS REQUIRED BY TECHNICAL SPECIFICATIONS

TABLE ll NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES ONSITE I-131 ACTIVITY pCi/m"3 +

2 SIGMA LOCATION STATIONS WEEK END Dl ON G

ON H

ON I

ON J

ON K

ON 89/01/10 89/01/17 89/01/24 89/01/3 1 89/02/07 89/02/14 89/02/2 1 89/02/28 89/03/07 89/03/14 89/03/21 89/03/28 89/04/04 89/04/11 89/04/18 89/04/25 89/05/02 89/05/09 89/05/16 89/05/23 89/05/30 89/06/06 89/06/13 89/06/20 89/06/26 89/07/03

<0.009

<0.011

<0.008

<0.028

<0.008

<0.010

<0.012

<0.013

<0.006

<0.011

<0.011

<0.008

<0.010

<0.007

<0.009

<0.013

<0.009

<0.009

<0.006

<0.012

<0.012

<0.010

<0.013

<0 ~ 008

<0.010

<0.012

<0.011

<0.008

<0.009

<0.006

<0.007

<0.008

<0.006

<0.007

<0.009

<0.008

<0.009

<0.006

<0.008

<0.007

<0.005

<0.006

<0.008

<0.011

<0.007

<0.008

<0.008

<0.042

<0.007

<0.010

<0.009

<0.011

<0.012

<0.006

<0.007

<0.006

<0.007

<0.007

<0.006

<0.010

<0.011

<0.009

<0.008

<0.009

<0.009

<0.009

<0.013

<0.008

<0.004

<0.008

<0.010

<0.008

<0.008

<0.009

<0.008

<0.009

<0.008

<0.014

<0. 012

<0.009

<0.013

<0.008

<0.007

<0.006

<0.008

<0.008

<0.007

<0.010

<0.008

<0.008

<0.011

<0.007

<0.009

<0.009

<0.009

<0.011

<0.007

<0.010

<0.009

<0.015

<0.015

<0.008

<0.011

<0.009

<0. 008

<0.007

<0.008

<0'07

<0.008

<0.010

<0.006

<0.006

<0.009

<0.011

<0.012

<0.008

<0.008

<0.008

<0 '15

<0.009

<0.006

<0.012

<0.009

<0.010

<0.009

<0.012

<0.013

<0.009

<0.009

<0.011

<0.014

<0.008

<0.010

<0.011

<0.008

<0.008

<0.007

<0.014

<0.008

<0.011

<0.007

<0.009

<0.007

<0.009

<0.009

<0.008

<0.010

<0.009

<0.012

<0.009

<0.007

<0.013

<0.008

<0.011

<0.007

<0.010

C'I TABLE 11 (Continued)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES ONSITE I-131 ACTIVITY pCi/m"3 + 2 SIGMA LOCATION STATIONS

~ 4

~

,C 1

'I

~

P I ".

WEEK END 89/07/11 89/07/18 89/07/25 89/08/01 89/08/08 89/08/15 89/08/22 89/08/29 89/09/05 89/09/12 89/09/19 89/09/26 89/10/03 89/10/10 89/10/17 89/10/24 89/10/31 89/11/07 89/11/14 89/11/21 89/11/28 89/12/05 89/12/12 89/12/19 89/12/26 90/01/02 D1 ON

<0.011

<0.007

<0.008

<0.015

<0.013

<0.010

<0.013

<0.012

<0.013

<0.011

<0.009

<0.012"

<0.011

<0.006

<0.010

<0.007

<0.007

<0.009

<0.012

<0.006

<0.015

<0.010

<0.013

<0.012

<0.012

<0.011 G--ON

<0.010

<0.009

<0.011

<0.009

<0.010

<0.009

<0.010

<0.005

<0.006

<0.009

<0.009

<0.007

<0.011

<0.009

<0.007

<0.009

<0.008

<0.009

<0.008

<0.011

<0.006

<0.010

<0.010

<0.008

<0.010

<0.010 H--ON

<0.011

<0.008

<0.017

<0.011

<0.013

<0.008

<0.014

<0.010

<0.008

<0.009

<0.010

<0.007

<0.012

<0.008

<0.007

<0.010

<0.010

<0.009

<0.007

<0.008

<0.007

<0.012

<0.014

<0.010

<0.008

<0.011 I

ON

<0.010

<0.007

<0.008

<0.011

<0.011

<0.007

<0.009

<0.010

<G.009

<0.008

<0.009

<0.009

<0.012

<0.012

<0.009

<0.008

<0.010

<0.008

<0.006

<0.009

<0.009

<0.008

<0.013

<0.011

<0.012

<0.012 J

ON

<0.014

<0.010

<0.011

<0.011

<0.013

<0.009

<0.011

<0.009

<0.009

<0.009

<0.009

<0 F 008

<0.009

<0.009

<0.010

<0.011

<0.011

<0.011

<0.008

<0.008

<0.011

<0.011

<0.015

<0.009

<0.009

<0.013 K

ON

<0.011

<0.008

<0.011

<0.012

<0.010

<0.008

<0.008

<0.009

<0.010

<0.010

<0.014

<0'12

<0.011

<0.011

<0.008

<0.007

<0.008

<0.006

<0.009

<0.009

<0.008

<0.007

<0.011

<0.013

<0.012

<0.012

TABLE 12A DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/standard month g 2 sigma Location Number Location 1989 January April Through Through Harch June July October Location Through Through (Direction and September December (Distance)(2) 3 Dl On Site 4

D2 On Site 5

E On Site 6

F On Site 7'

On Site 8

R-5 Off S/te-Control 9

Dl Off Site 10 D2 Off Site 11 E Off Site 12 F Off Site 13 G Off Site 14'eHass Rd.,

SW Oswego-Control 15*

Pole 66, W. Boundary-Bible Camp 18*

Energy Info. Center Lamp Post, SW.

19 East Boundary-JAF, Pole 9

23' On Site 24 I On Site 25 J

On Site 26 K On Site 27 N. Fence, N. of Switchyard, JAF 28 N. Light Pole, N. of Screenhouse, JAF 29 N. Fence, N. of W. Side Screenhouse, JAF 12.0z0.6 6.2'.6 4.9'.6 4.4'.9 4.620.3 4.820.4 4.6'.4 4.4'.3 3.2'.2 4.220.2 4.7'.3 4.8z0.5 4.2'.l 3.8i0.3 5.2'.3 6.220.5 5.lz0.4 4.9'.5 4.5'.4 22.2t3.8 42.lz6.1 26.8z6.7

14. 5i2. 9 5.9'.5 5.4'.5 4.8t0.4 5.020.2 5.2'.3 5.4'.3 5.0z0.3 5.2'.3 4.8'.3 5.1g0.2 5.6'.4 4.420.2 5.6'.4 5.1t0.2 6.6'.4 5.4'.5 6.lt0.2 5.8t0.5 25.0g4.1 38.6t7.6 29.2z8.2 13.lz2.0 6.8'.6 6.6'.5 5.720.8 5.8'.2 6.'4'.4 5.3'.2 S.Og0.2 5.440.2 4.8z0.2 4.8z0.2 5.4'.4 5.2'.1 5.6'.2 6.3'.5 7.7z0.4 6.2'.5 5.2'.5 6.0z0.6 22.8t3.5 41.2z6.8 29.2z6.0 9.1gl.0 4.8%0.7 4.8'.5 3.7'.6 3.8t0.5 4.7'.6 4.0'.5 3.4'.4 3.220.6 2.8z0.2 3.7'.5 2.9'.4 2.lz0.3 3.8'.4 3.3'.3 4.0z0.4 5.2'.7 4.2'.7 2.720.6 14.923.5 32.5z4.2 21.3z4.6 0.2 miles 8

69'.4 miles 9

140'.4 miles 8

175 0.5 miles 8

210'.7 miles 8

250'6.4 miles 9

42'1.4 miles 8

80'.0 miles 8 117 7.2 miles 8

160'.7 miles 8 190 5.3 miles 8

225'2.6 miles 8

226'.9 miles 8

237'.4 miles 9

265'.3 miles 9

81'.8 miles 6

70'.8 miles 8

98'.9 miles 8 110 0.5 miles 8

132'.4 miles 8

60'.5 miles 8 68 0.5 miles 9

65'91

TABLE 12A (Continued).

DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/standard month t 2 sigma Location Number Location 1989 January Through Harch April Through June July

~ October Through Through September December Location (Direction and (Distance)(2) 30 N.

Fence (NH) JAF

.31 N.

Fence (NH) NHP-1 39 N. Fence, Rad Haste, NHP-1 47 N. Fence, NE, JAF 49'hoenix, NY-Control 51 Liberty & Bronson Sts.,

E of OSS 52 East 12th

& Cayuga Sts.,

Osw.

School 53 Broadwell

& Chestnut Sts.,

Fulton H.S.

54 Liberty St.,

& Co. Rte.

16, Hexico H.S.

55 Gas Substation

& Co. Rt.

5 Pulaski 56't.

104 New Haven Sch.

(SE Corner) 58*

Co. Rt.

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

75*

Unit 2, N. Fence, N. of Reactor Bldg.

76'nit 2, N. Fence, N. of Change House 77'nit 2, N. Fence, N. of Pipe Bldg.

78*

JAF, E. of E. Old Lay Down Area 79'o.

Rt. 29, Pole ¹63, 0.2 mi. S. of Lake Rd.

80*

Co. Rt. 29, Pole ¹54, 0.7 mi. S. of Lake Rd.

81'iner Rd., Pole ¹16, 0.5 mi.

H. of Rt.

29 82*

Hiner Rd., Pole ¹1 1/2, 1.1 mi. H. of Rt.

29 83*

Lakeview Rd., Tree, 0.45 mi.

N. of Hiner Rd.

17.4tl.7 6.9'.8 10.6t1.4 10.5z1.4 3.7'.2 4.0t0.2 4.6'.4 4.4'.3 4.4'.2 3.420.2 4.6'.3 4.3'.2 4.920.2 4.6'.3 6.4'.5 5.2'.3 4.420.2 4.6'.4 4.420.2 4.620.3 4.620.2 18.7'.2 7.5i0.6 11.6'.1 10.F1.9 5.020.2 5.0g0.3 4.8'.2 5.4'.4 4.8z0.3 4.8z0.2 4.8t0.2 5.0z0.4 6.lz0.6 6.620.4 8.2'.6 6.0z0.4 5.0z0.3 5.6'.4 5.4'.5 4.8'.2 (1) 17.F1.8 8.420.8 13.0zl.2 70.3zl.4 5.2'.4 6.2'.5 5.4'.7 5.5'.3 5.3i0.2 5.6'.2 5.4'.3 5.4'.2 7.3'.6 6.6'.3 8.lz0.9 6.020.5 5.8'.5 5.620.3 5.2'.2 6.0i0.4 6.320.4 11.8zl.6 6.0z0.6 10.2zl.4 7.0zl.5 4.2'.4 4.0z0.7 3.3'.3 3.6'.4 3.020.2 3.0'.3 4.5'.5 3.4'.5 4.6'.5 4.5'.5 5.6'.8 3.6'.6 2.8z0.6 3.220.4 3.0z0.5 2.9'.5 4.2'.3 0.4 miles 8

57 0.2 miles 8

276'.2 miles 8

292'.6 miles 8

69'9.8 miles 8

170'.4 miles 8

233'.8 miles 8

227'3.7 miles 8

183'.3 miles 8

115'3.0 miles 8

75'.3 miles 8

123'.1 miles 8

220'.1 miles 8

5'.1 miles 8

25'.2 miles 8

45'.0 miles 8

90'.

1 miles 8

115'.4 miles 8

133'.6 miles 8

159'.6 miles 8

181'.2 miles 8 200'

TABLE 12A (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month

% 2 sigma Location Number Location January 1989 Through March April Through June July October Through Through September December Location (Direction and (Distance)(2) 84>>

85>>

86*

87'&>>

89*

90*

91>>

92>>

93*

94'5'6*

97*

98*

Lakeview Rd. N., Pole ¹6117, 200 Ft.

N. of Lake Rd.

Unit 1, N. Fence, N. of W. Side of Screen House Unit 2, N. Fence, N. of W. Side of Screen House Unit 2, N. Fence, N. of E. Side of Screen House Hickory Grove Rd., Pole ¹2, 0.6 mi.

N. of Rt.

1 Leavitt Rd.,

Pole ¹16, 0.4 mi. S. of Rt.

1 Rt.

104, Pole ¹300, 150 Ft.

E. of Keefe Rd.

Rt.

51A, Pole ¹59, 0.8 mi.

W. of Rt.

51 Maiden Lane Rd.,

Power Pole, 0.6 mi.,

S. of Rt.

104 Rt. 53, Pole l-l, 120 Ft.

S. of 104 Rt.

1, Pole ¹82, 250 ft. E. of Kocher Rd.

Lakeshore Camp Site, From Alcan W.

Access Rd., Pole ¹21, 1.2 mi.

N. of Rt.

1 Creamery Rd., 0.3 mi.

S of Middle Rd.,

Pole 1 1/2 Rt. 29, Env. Station R4, 200 Ft.

N.

of Miner Rd.

Lake Rd., Pole ¹145, 0.15 mi.

E. of Rt.

29 4.5%0.2 14.4%1.6 6.0%0.4 5.6%0.4 4.4%0.2 4.8%0.3 4.8%0.2 4.4%0.2 4.8%0.4 4.6%0.2 4.2%0.4 4.4%0.2 4.5%0.4 4.8%0.2 5.0%0.3 5.7%0.3 14.2%1.4 7.4%1.0 6.4%0.8 5.0%0.3 5.6%0.2 4.9%0.3 4.8%0.3 6.3%0.4 5.3%0.2 5.8%0.4 6.0%0.2 6.0+0.3 5.5%0.2 5.4%0.3 6.0%0.3 15.4%1.9 8.4%0.8 7.8%1.0 6.2%0.4 6.4%0.5 6.0%0.2 5.8%0.2 6.8%0.3 6.0%0.2 5.8%0.3 5.9%0.2 6.2%0.4 6.4%0.3 7.0%0.2 3.2%0.4 12.0%1.2 6.2%1.1 4.6%0.7 5.2%0.7 3.7%0.5 3.5%0.5 2.5%0.2 4.0%0.5 3.0%0.3 2.7%0.2 2.6%0.2 3.6%0.2 3.6%0.2 3.6%0.3 1.1 miles 8

225'.2 miles 8

294'.1 miles 8 315 0.1 miles 8

341'.8 miles 8

97'.1 miles 8

ill'.2 miles 8

135'.8 miles 8

156'.4 miles 8

183'.4 mi les 8

205'.7 miles 8

223'.1 miles 8

237'.6 miles 8

199'.8 miles 8

143 1.2 miles 8

101'93

TABLE 12A (Continued)

DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/standard month g 2 sigma Location Number Location January April 1989 Through Through March June July Through September October Through December Location (Direction and (Distance)(2)

~ ~

99 100 101 102 103 104 105 106 107 108 109 110ill NMP Rd., 0.4 miles N. of Lake Rd.,

Env.

Station Rl Off-Site Rt.

29 and Lake Rd.,

Env. Station R2 Off-Site Rt. 29, 0.7 mi. S. of Lake Rd.,

Env.

Station R3 Off-Site EOF/Env.

Lab, Oswego Co. Airport (Fulton Airport), Rt.

176, E. Driveway Lamp Post EIC, East Garage Rd.,

Lamp Post Parkhurst

Road, Pole 148 1/2-A, 0.1 mi.

S. of Lake Rd.

Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd.

Shoreline

Cove, E. of NHP-l, Tree on H.

Edge Shoreline

Cove, E. of NHP-l, Tree 30 ft. South of TLD ¹106 Lake Rd. Pole ¹142 300'ast of County Route 29 (S)

Lake Rd. Tree 300'ast of County Route 29(N)

Baldwinsville, NY Control Volza Residence

Sterling, NY - Control Blasiak Residence 4.4'.3 4.320.2 3.8'.3 3.6'.2 3.9'.2 4.5'.1 4.420.2

.5.0z0.2.

5.4'.4 4.720.5 3.9'.3 3.4'.1 3.620.2 5.8z0.3 6.0g0.3

5. lz0. 4 5.5'.3 6.2'.3 5.4'.2 6.020.4 5.6'.4 6.2'.3 5.8z0.4 5.6'.2 5.220.5 5.4'.7 6.4i0.3 5.8'.2 6.0'.4 6.0z0.2 6.020.2 5.020.2 5.4'.3 6.7'.4 6.820.3 6.4'.4 6.2'.7 5.2'.2 5.2'.3 4.0z0.4 3.8z0.3 3.9'.1 4.0z0.5 4.lz0.6 3.8z0.5 4.2'.4 4.620.6 4.8z0.5 4.4'.5 4.0z0.5 4;4'.5 3.7'.5 1.8 miles 8

88'.

1 miles 8

104'.5 miles 6

132'1.9 miles 8

175'.4 miles 8

267'.4 miles 8

102'.4 miles 8 198 0.3 miles 8

274'.3 miles 6

272'.1 miles 8

104'.1 miles 8 103 26.4 miles 8

166'1.8 miles 8 214 (1)

(2)

TLD lost in field.

Direction and distance based on NMP-2 reactor Technical Specification location.

centerline and sixteen-22.5'ector grid.

TABLE 12B DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/quarterly period

% 2 sigma Location Number Location 1989 January Through Harch April Through June July October Through Through September December Location (Direction and (Distance)(2) 3 4

5 67f 8

9 10ll 12 13 14*

15*

18*

19 23*

24 25 26 27 28 Dl On Site D2 On Site E On Site F On Site G On Site R-5 Off Site-Control Dl Off Site D2 Off Site E Off Site F Off Site G Off Site DeHass Rd, SH Oswego-Control Pole 66, H. Boundary-Bible Camp Energy Info. Center-Lamp

Post, SH East Boundary-JAF, Pole 9

N On Site I On Site J

On Site K On Site N. Fence, N. of Switchyard, JAF N. Light Pole, N. of Screenhouse,JAF 36.1%0.8 18.1%0.9 14.4%0.8 13.0%1.3 13.3%0.5 14.3%0.6 13.6%0.5 13.0%0

~ 4 9.3%0.4 12.4%0.4 13.9%0.4 14.2%0.7 12.4%0.2 11.2%0.4 15.2%0.5 18.0%0.8 14.9%0.6 14.2%0.7 13.3%0.6 61.4%5.2 44.3%4.5

18. 1%0.7 16.5%0.7 14.7%0.6 15.7%0.3 15.4%0.5 16.2%0.4 14.9%0.5 15.4%0.4 14.2%0.4 15.2%0.4 17.0%0.5 13.6%0.4 17.5%0.6 15.6%0.3 20.6%0.7 16.6%0.7 18.9%0.3 18.0%0.8 74.6%6.2 38.7%2. 9 20.1%0.9 19.0%0.7 17.0%1.1 16.8%0.3

19. 1%0.7 15.8%0.4

15. 1%0.3 16.0%0.4 14.2%0.4 14.6%0.4 15.0%0.6 15.4%0.2 16.6%0.4 18.8%0.7 22.3%0.6 18.1%0.7 15.2%0.7 17.6%0.8 68.3%5.3 26.8%1.5 14.7%1.1 14.4%0.7 10.8%0.9 11.3%0.7 14.0%0.9 12.0%0.8 10.0%0.6 9.6%0.9 8.2%0.3 11.2%0.7 8.6%0.5 6.4%0.5 11.%0.6 9.8%0.5 12.4%0.7 15.9%1.1 12.6%1.0 8.3%0.8 44.6%5.3 116.4%8.4 115.4%11.3 123.2%10.1 97.4+6.3 0.2 miles 8

69 0.4 miles 8

140'.4 miles 8 175 0.5 miles 9

210'.7 miles 8 250 16.4 miles 8 42 11.4 miles 9

80'.0 miles 8

117'.2 miles 8 160 7.7 miles 9

190'.3 miles 8 225 12.6 miles 8

226'.9 miles 8 237 0.4 miles 8

265'.3 miles 8 81 0.8 miles 8 70 0.8 miles 8 98 0.9 miles 6 110 0.5 miles 8 132 0.4 miles 8

60'.5 miles 8 68

-95

TABLE 128 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period 2 2 sigma Location Number Location 1989 January Through March April Through June July October Through Through September December Location (Direction and (Distance)(2) 29 30 31 39 47 49>>

51 52 53 54 55 56'8*

75*

76*

77*

78'9*

80*

81'2*

N. Fence, N. of H. Side Screenhouse, JAF N Fence (NH) JAF N. Fence (NW) NMP-1 N. Fence, Rad.

Haste, NMP-1 N. Fence, NE, JAF

Phoenix, NY-Control Liberty & Bronson Sts.,

E. of OSS East 12th

& Cayuga Sts.,

Osw.

School Broadwell

& Chestnut Sts.,

Fulton H.S.

Liberty St.

& Co. Rt.

16, Mexico H.S.

Gas Substation, Co. Rt. 5, Pulaski Rt.

104 New Haven Sch.

(SE Corner)

Co. Rt.

1A Alcan (E. of Entrance Rd.)

Unit 2, N. Fence, N. of Reactor Bldg.

Unit 2, N. Fence, N. of Change House Unit 2, N. Fence, N. of Pipe Bldg.

JAF, E. of E. Old Laydown Area Co. Rt. 29, Pole ¹63, 0.2 mi. S. of Lake Rd.

Co. Rt. 29, Pole ¹54, 0.7 mi.

S. of Lake Rd.

Miner Rd.,

Pole ¹16, 0.5 mi.

W. of Rt.

29 Miner Rd.,

Pole ¹ 1 1/2, 1.

1 mi.

H. of Rt.

29 74.229.3 48.022.4 20.421.2 31.622.2 29.021.9 11.020.3 11.820.4 13.720.6 12.920.4 13.020.5 9.620.2 13.620.5 12.820.4 14.620.3 13.720.5 18.820.8 15.720.4 13.020.2 13.420.6 13.020.4 13.420.4 87.3212.2 55.823.4 22.820.9 35.122.3 32.522.9 14.620.3 15.020.3 14.420.3 16.020.6 14.620.4 14.420.3 14.620.4 15.320.5 18.520.9 20.020.6 24.620.8 18.220.5 15.020.4 16.620.5 16.220.7 14.620.3 87.S29.0 53.022.6 24.821,1 38.021.8 30.822.1 15.620.S 18.620.7 16.121.0 16.620.5 15.820.3 16.820.3 16.020.4 15.820.3 21.420.9 19.520.5 23.721.3 17.520.8 17.020.6 16.420.4 15.520.4 17.920.6 63.826.7 35.622.4 17.921.0 30.322.1 20.922.2 12.820.5 12.021.1 10.020.5 10.520.7 8.920.4 9.220.5 13.820.7 10.320.8 13.620.7 13.420.7 16.621.2 11.021.0 8.420.9 9.720.6 9.420.8 8.820.7 0.5 miles 8

65'.4 miles 8

57'.2 miles 8

276'.2 miles 8

292'.6 miles 8

69'9.8 miles 8

170'.4 miles e

233'.8 miles 8

227'3.7 miles 8

183'.3 miles 8

115'3.0 miles 8

75'.3 miles 8

123'.1 miles 8

220'.1 miles 8

5'.

1 miles 8

25'.2 miles 8

45'.0 miles 8

90'.

1 miles 8

115'.4 miles 8

133'.6 miles e

159'.6 miles 8 181'

TABLE 12B (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period z 2 sigma Location Number Location January 1989 Through March April Through June July Through September October Through December Location (Direction and (Distance)(2) 83'4'5*

86*

87*

88>>

89>>

90*

91*

92'3*

94>>

95>>

96'akeview Rd., Tree, 0.45 mi.

N. of Miner Rd.

Lakeview Rd., N., Pole ¹ 6117, 200 Ft.

N. of Lake Rd.

Unit 1, N. Fence, N. of W. Side of Screen House Unit 2, N. Fence, N. of W. Side of Screen House Unit 2, N. Fence, N. Of E. Side of Screen House Hickory Grove Rd., Pole ¹2, 0.6 mi. N.

of Rt.

1 Leavitt Rd.,

Pole ¹16, 0.4 mi. S. of Rt.

1 Rt.

104, Pole ¹300, 150 Ft.

E. of Keefe Rd.

Rt.

51A, Pole ¹59, 0.8 mi.

W. of Rt.

51 Maiden Lane Rd.,

Power Pole, 0.6 mi.

S.

of Rt.

104 Rt.

53, Pole l-l, 120 Ft.

S. of Rt.

104 Rt.

1, Pole ¹82, 250 Ft.

E. of Kocher Rd.

Lakeshore Camp Site, From Alcan W. Access Rd.,

Pole ¹21, 1.2 mi.

N. of Rt.

1 Creamery Rd., 0.3mi.

S. of Middle Rd.,

Pole 1 1/2 13.4'.3 13.3'.4 42.8g2.4 17.6'.7 16.6'.7 13.0g0.3 14.3'.5 14.020.4 13.020.4 14.2'.5 13.6'.2 12.6'.6 13.0g0.3 17.120.4 43.0z2.2 22.3zl.5 19.2zl.2 15.0g0.4 16.8z0.3 14.6'.3 14.6'.4

19. 2io. 5 15.8'.3 17.2'.6 17.920.3 13.4'.6 16.8'.4 18.2'.5 17.8'.6 45.022.9 24.S'il.2 22.8z1.5 18.020.5 18.920.6 17.5+0.3 17.0z0.3 19.620.4 17.620.4

- 17.lz0.5 12.920.5 9.6'.5 35.7zl.7 18.6zl.6 13.8gl.O 15.8z1.0 11.3'.8 10.720.9 7.7z0.4 12.0'.8 9.2%0.4 8.2'.4 18.6'.6 11.0g0.4 17.3'.3 8.0z0.2 1.2. mi les 1.1 mi les 8 200' 225'.2 miles 8

294'.l miles 6

315'.1 miles 8

341'.8 miles 8

97'.1 miles 8

111 4.2 miles 8

135'.8 miles 8

156'.4 miles 6 183 4.4 miles 8

205'.7 miles 8

223'.1 miles 8

237'.6 miles 8

199'97

TABLE 12B (Continued)

DIRECT RADIATION HEASUREHENT RESULTS Results in units of mrem/quarterly period z 2 sigma Location Number Location January April 1989 Through Through March June July October Through Through September December Location (Direction and (Distance)(2) 97*

98*

99 100 101 102 103 104 105 106 107 108 109 110ill Rt. 29, Env. Station R4, 200 Ft.

N.

of Hiner Rd.

Lake Rd., Pole ¹145, 0.15 mi.

E. of Rt.

29 NHP Rd., 0.4 miles N. of Lake Rd.,

Env.

Station Rl Off-Site Rt.

29 and Lake Rd.,

Env. Station R2 Off-Site Rt. 29, 07 mi. S. of Lake Rd.,

Env. Station R3 Off-Site EOF/Env.

Lab, Oswego Co. Airport (Fulton Airport), Rt.

176, E. Driveway Lamp Post EIC, East Garage Rd.,

Lamp Post Parkhurst

Road, Pole 148 1/2-A, O.l mi.

S. of Lake Rd.

Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd.

Shoreline

Cove, E. of NHP-l, Tree on Hest Edge Shoreline

Cove, E. of NMP-l, Tree 30 ft. South of TLD ¹106 Lake Rd.

Pole ¹142 300'ast of County Route 29 (S)

Lake Rd.

Tree 300'ast of County Route 29(N)

Baldwinsville, NY Control Volza Residence

Sterling, NY Control Blasiak Residence 14.2'.3 15.1t0.4 13.2'.5 12.720.4 11.0z0.4 10.5'.2 11.6'.4 13.4'.2 13.0g0.2 14.720.4 15.820.4 14.0z0.7 11.420.5 10.lz0.2 10.7'.4 16.620.3 16.3i0.5 17.2'.4 18.2'.5 15.lz0.6 16.4'.4 18.2'.4 16.420.2 18.2'.6 17.3'.6 19.210.5 17.8z0.6 16.6'.4

15. 410. 7 16.0zl.l 19.0z0.4 20.4'.2 19.3'.4 17.5'.3 18.0'.6 18.lz0.3 17.4'.3 15.0z0.4 16.420.5 19.8%0.7 20.0t0.5 19.3'.6 18.6zl.l 15.8'.4 15.820.4 10.8'.4 10.7'.4 12.2'.6 11.3'.4 11.7'.2 11.8z0.8 12.220.9 11.2'.8 12.4'.6 13.720.8 14.4'.7 13.4'.7 12.2'.8 13.2'.7 11.2'.8 1.8 miles 6

143'.2 miles 6

101'.8 miles 8

88'.1 miles 8

104'.5 miles 8

132'1.9 miles 8

175'.4 miles 6

267'.4 miles 8 102 1.4 miles 8

198'.3 miles 8

274'.3 miles 8

272'.1 miles 8 104 1.1 miles 8 103 26.4 miles 8

166'1.8 miles 8

214'1)

(2)

TLD lost in the field.

Direction and distance based on NMP-2 reactor Technical Specification location centerline and sixteen 22.5'ector grid.

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 55 50 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 14502134

<3.9

<4.3

<3 '

93i50

<LLD 1650zl67

<6 '

<8.3

<4.5

<1&0

<LLD 1540il&5

<7.1

<8.0

<8.0

<203

<LLO 1390i131

<4.8

<5.4

<3.4 88+58

<LLO 1440i156

<7.5

<7.1

<5. 4

<184

<LLD 1580gl61

<6.4

<6.9

<7.1

<182

<LLD 1400i60

<5.9

<5.6

<6.0 11&i32

<LLD 15802134

<5.3

<6.2

<4.1

<149

<LLD 14902184

<7.4

<9.4

<9.1

<218

<LLD 1680z201

<9.0

<7.6

<8.5

<220

<LLD 1570i137

<5.4

<5.9

<3.1

<150

<LLD 1570i164

<6.0

<7.4

<5.7

<174

<LLD 15502144

<4.,1

<6.1

<3.6

<146

<LLD 1620il 71

<7.1

<7.1

<6.6

<191

<LLD 15&Oil&8

<7.7

<9.7

<8.5

<221

<LLD 16&0z141

<5.4

<5.7

<3.8

<156

<LLD 1610z166

<5.&

<6.6

<5.7 132%75

<LLD

<312

<5.1

<6.2

<5.9

<166

<LLD 1670i192

<7.3

<8.2

<9.5

<218

<LLD 1650il38

<5.0

<6.0

<5.6

<160

<LLD 1510i66

<7.6

<6.0

<10.0

<134

<LLD 1430i140

<5.0

<6.1

<4.4

<141

<LLD 1650z168

<6.4

<6.5

<4.7

<178

<LLD 1640zl 37

<5.2

<6.2

<4.7

<156

<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 16 65*

(Control)

K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1520zl 77

<7.7

<7.2

<9.5

<214

<LLD 1480gl29

<4.8

<5.5

<4.3 169g68

<LLD 1570z161

<6.3

<7.4

<5.0

<180

<LLD 1720t191

<7.2

<8.9

<7;0

<1&8

<LLD 1530zl 81

<7.4

<9.5

<7.4 206zl01

<LLD 1440tl 25

<4.8

<5.2

<3.8 118z72

<LLD 1460zl39

<4.9

<5.7

<4.0

<143

<LLD 1600gl65

<5.4

<6.2

<6.5 182z98

<LLD 16302145

<5.8

<6.2

<5.8

<147

<LLD 1440zl76

<7 ~ 3

<9.8

<8.0

<210

<LLD 1520z66

<5.8

<5.5

<7.2 108z48

<LLD 1650zl39

<4.8-

<6-0

<5.4 129i72

<LLD 15902136

<5.4

<6.3

<4.3 121z73

<LLD 173021 74

<6.6

<7.1

<5.4

.lllzl01

<LLD 1460zl83

<8.7

<10.0

<7.0 284zl54

<LLD 14&0zl80

<8.2

<8.4

<9.0

<217

<LLD 1660zl48

<5.0

<5.8

<5.1

<137

<LLD 1500265

.<6. 4

<6.4

<8.3 163<4.6

<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 55

%J

~ 1

'I

~ w 50 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1720zl71

<6.7

<6.6

<7.3 174g87

<LLD 1480i67

<6.5

<7.0

<7.4

<142

<LLD 1510z184

<6.4

<8.2

<4.3

<195

<LLD 1620zl91

<6.4

<8.7

<6.7

<220

<LLD 1550zl66

<6.3

<7.7

<6.1 153z88

<LLD 1450i139

<5.0

<5.6

<5.4 99z55

<LLD 1530z161

<6.6

<7.9

<4.0

<200

<LLD 1670zl47

<4.1

<6.4

<5.1

<141

<LLD 1680z70

<7.4

<6.8

<5.8 119257

<LLD 15402145

<4.7

<6.4

<3.6

<137

<LLD 1520gl38

<5.2

<5.4

<5.0

<139

<LLD 1500i66

<7.0

<6.2

<7.9

<142

<LLD 1600zl90

<7.9

<7.9

<6.8

<210

<LLD 14902144

<4.6

<6.6

<4.7

<124

<LLD 1560zl88

<8.1

<8.8

<6.8

<207

<LLD 1470z66

<6.1

<5.9

<5.8

<123

<LLD 1470z140

<5.2

<6.3

<5.2 10lg56

<LLD 1620z169

<6.8

<7.1

<5.2

<185

<LLD

~

~

s 7

K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1720zl41

<4.6

<5.3

<5.1 132gll3

<LLD 1540z68

<7.3

<6.4

<6.4 90i48

<LLD 15402134

<5.8

<6.5

<5.6

<161

<LLD 1520g165

<6.5

<8.0

<6.1 171+109

<LLD 15502165

<7.4

<8.0

<7.3

<190

<LLD 1470zl83

<7.3

<8.9

<6.0 193g147

<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 16 65*

(Control)

K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1550z65

<6.5

<6.8

<6.4

<136

<LLD 1620gl68

<7.1

<7.9

<6.5

<193

<LLD 1440gl 81

<7.3

<7.2

<6.0

<192

<LLD 1600zl87

<6.8

<9.3

<9.0

<212

<LLO 1970g151

<4.2

<5.6

<4.8

<147

<LLD 1570267

<6.9

<5.6

<9.1 97z36

<LLD 14902141

<4.6

<5.9

<2.7

<128

<LLD 1580z67

<6.6

<7.0

<7.9 96z49

<LLD 14402178

<7.8

<9.0

<10.5

<226

<LLD 17402142

<5.6

<6.2

<5.3 120z60

<LLD 16402139

<5.8

<6.0

<5.6

<171

<LLD 13802174

<7.7

<I0.2

<6.3 129z82

<LLD 1460zl40

<5.2

<5.9

<3.2

<135 (1) 1810g143

<5.4

<6.2

<4.0

<156

<LLO 1370zl34

<7.2

<9.3

<7.7 191tl34

<LLD 1590z68

<7.3

<6.2

<9.0 87g33

<LLD 1530t66

<6.3

<5.5

<8.3

<137

<LLD 1610tl37

<5.0

<5.7

<5.3

<156

<LLD

'-Technical Specification location.

( 1)

AcTh-228 found at a concentration of 23.9z12

.7 pCi

/liter

All other radionuclides were less than LLD for this sample.

%J

~ ~

~ 1 f

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter -g 2 sigma Location Nuclides 10-2-89 10-16-89 11-6-89 11-20-89 12-4-89 t

12-18-89

~ 9 60 50 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1660zl39

<4.7.

<6.1

<5 '

174i74

<LLD 15302139

<4.6

<5.9

<4.2

<126

<LLD 1520il34

<4.2

<5.8

<4.1

<146

<LLD 16102144

<5.8

<6.2

<5.7

<146

<LLD 1670gl39

<5.1

<5.7

<6.0

<153

<LLD 1570zl91

<7.0

<8.9

<5.4

<211

<LLD 1610zl 37

<4.8

<7.1

<3.2

<159

<LLD 1620zl69

<6.9

<6.7

<5.5 158zl00

<LLD 1470zl38

<5.9

<5.6

<4.6

<138

<LLD 15502191

<8.8

<9.4

<11.4

<238

<LLD 1730tl 42

<5.6

<4.9

<4.7

<150

<LLD 1670zl71

<6.4

<7.9

<6.2

<202

<LLD 1750zl 42

<5.3

<5.7

<4.3

<154

<LLD 1440zl88

<8.1

<9.3

<8.3

<229

<LLD 14502189

<8.4

<7.7

<7.4

<223

<LLD 1610zl 69

<7.2

<6.0

<6.1

<189

<LLD 1600zl96

<9.3

<9.4

<9.4

<222

<LLD 1550gl91

<8.1

<8.8

<8.0

<224

<LLD 7

'I K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1560i143

<5.7

<6.0

<6.0

<145

<LLD 1470z187

<8.3

<9.6

<9.9

<213

<LLD 1560tl38

<4.4

<6.2

<6.4

<161

<LLD 1460il 39

<5.1

<5.7

<5.4

<140

<LLD 1590zl91

<9.2

<10.0

<10.0

<227

<LLD 1690gl41

<5.0

<4.2

<3.1 132259

<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 16 65'Control)

K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1360zl75

<7.8

<8.3

<7.4

<209

<LLD 1820zl74

<6.2

<7.1

<7.4 145z76

<LLD 1610t143

<5.2

<5.9

<5.2

<145

<LLO 15302143

<4.8

<5.4

<4.7

<135

<LLD 1640zl69

<6.3

<6.8

<3.4

<190

<LLO 1670zl 74

<6.0

<8.0

<6.2

<200

<LLD 1730zl72

<6.9

<8.2

<5.9

<196

<LLD 1760zl52

<5.0

<7.5

<5.1

<148

<LLD 1510zl&6

<8.0

<10.7

<6.6

<229

<LLO 1590i144

<4.8

<5.6

<5.2

<130

<LLD 1670g197

<9.0

<10.5

<6.3.

<229

<LLD 1790zl47

<5.3

<5.7

<5.1

<151

<LLD 1510z141

<5.9

<6.2

<5.4

<136

<LLO 1610z146

<5.0

<5.0

<4.6 105t63

<LLD 1760z142

<5.2

<5.2

<2.7 1&lz&1 (2) 1530zl63

<7.2

<7.7

<4.6 283tl51

<LLD 1520z68

<7.6

<6.1

<10.1

<135

<LLD 15&02144

<4.7

<5.9

<6.0

<145

<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 55 50 7

4 16 65'0.15

<0.26

<0.13

<0.16

<0.14

<0.17

<0.13

<0.18

<0.16

<0.15

<0.16

<0.17

<0.16

<0.16

<0.19

<0.19

<0.30

<0.28

<0.31

<0.17

<0.17

<0.15

<0.15

<0.16

<0.14

<0.20

<0.16

<0.22

<0.13

<0.13

<0.19

<0.13

<0.12

<0.14

<0.14

<0.14

<0.16

<0.19

<0.16

<0.20

<0.18

<0.21 Location 7-5-89 7-17-89 8-7-89 8-21-89 9-5-89 9-18-89 60 55 50 7

4 16 65*

<0.13

<0.12

<0.15

<0.18

<0.26

<0.20

<0.29

<0.13

<0.12

<0.15

<0.11

<0.13

<0.15

<0.11

<0.23

<0.15

<0.18

<0.15

<0.22

<0.15

<0.15

<0.19

<0.11

<0.12

<0.10

<0.11

<0.12

<0.10

<0.16

<0.15

<0.18

<0.19

<0.17

<0.18

<0.15

<0.15

<0.14

<0.15

<0.15

<0.13

<0.21

<0.17 Control result.

Technical Specification location.

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

-105

r

~

~

TABLE 14 (Continued)

CONCENTRATION OF IODINE 131 IN MILK (1)

Results in units of pCi/liter g 2 sigma Location 10-2-89 10-16-89 11-6-89 11-20-89

'12-4-89 12-18-89 r 'C

'C 60 55 50 7

4 16 65*

<0.15

<0.17

<0.19

<0.16

<0.13

<0.15

<0.14

<0.14

<0.18

<0.19

<0.17

<0.15

<O.I5

<O.I5

<0.41

<0.40

<0.42

<0.21

<0.40

<0.31

<0.35

<0.33

<0.37

<0.19

<0.38

<0.44

<0.50

<0.30

<0.50

<0.29

<0.50

<0.49

<0.21

<0.23

<0.20

<0.34

<0.22

<0.17

<0.32

<0.19

<0.26

<0.36 Control result.

Technical Specification location.

( 1)

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

(a)

TABLE 15 MILK ANIMAL CENSUS 1989 Number on g~r~~(1 )

gp(~(3) pic~~(3)

Number of Scriba New Haven Mexico Richland Pulaski Oswego (SW)

Hannibal Sterling Volney 1

16*

2 3

6 26 61 62 8

9 4*

45 10 5ll 7*

4 12 13 14 15 17 18 19 20 60*

50*

55*

21 68 25 70 66 220'90'95'90'62'14'40'83' 130'5'13'25'30'46'30'07' 107'14'20'00'15'10'32'23'0'3'5'12'08' 14'82'47'56' 3.0 miles 5.9 8.0 4.5 2.2 1.5 3.0 6.7 9.2 5.2 7.8 8.0 2.6 7.2 8.5 5.5 11.5 11.2 9.8 10.8 10.2 10.0 10.5 11.2 9.5 8.2 9.0 10.5 11.6 17.

9.5 9.4 7.8 None 39C ND 4C 1C ND 1C,12G 6G None 40C 100C 10C 28C 49C 30C 62C 20C None 68C None 1C None 40C None 30C I65C 55C 72C 28C None 25C;2G 70C;1G MILKING ANIMAL TOTALS:

(including control locations)

MILKING ANIMAL TOTALS:

(excluding control locations) 1,210 Cows 1,165 Cows (b) 27 Goats (b)

-107 A

~

a%

'(

i ~

~

~

TABLE 15 (Continued)

MILK ANIMAL CENSUS 1989 NOTES:

C G*

ND s (1)

(2)

(3)

None (a)-

(b)

Cows Goats Milk sample location Milk sample ~~ location Did not wish to participate in the survey References Figure 4

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

No cows or goats at that location.

Location was a,previous location with cows and/or goats.

Census performed out to a distance of approximately ten miles.

Totals excluding control location results.

-108

i n

TABLE 16 1989 RESIDENCE CENSUS Hap(1)

Meteorological i

n r

<~>~D>

an e~~~

Lake Road Lake Road County Route 29 Miner Road Miner Road Lakeview Road Bible Camp Retreat Bible Camp Retreat A

B C

D E

F G

H N

NNE NE ENE E

ESE SE SSE S

SSH SH HSH H

HNH NH NNH 99' 102'30'63'70'07'34'38'.3 miles 1.1 mi les 1.4 miles 1.6 miles 1.6 miles 1.2 miles 0.9 miles 0.9 miles 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

T T

K K

L L

L P

P P

e 0

0 Y

Y Y

H*

H'*

8-28-89 8-28-89 8-28-89 8-28-&9 8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-29-89 9-05-89 9-05-&9 9-05-89 9-05-89 9-05-89 9-05-89 8-30-89

&-30-89

&-30-89 Beet Greens Squash Leaves Cabbage Strawberry Leaves Squash Leaves Bean Leaves Cucumber Leaves Squash Leaves Collard Greens Swiss Chard Beet Greens Cabbage Squash Leaves Cucumber Leaves Squash Leaves Pepper Leaves Eggplant Leaves Swiss Chard Squash Leaves Cabbage 0.19'.04 0.32z0.08

<0.13 0.7&F0.12 0.54z0.06 0.36g0.07 0.76t0.04 0.6)g0.11 0.1&F0.04 0.10'.04 0.1&F0.07

<0.09 0.43z0.10 1.56z0.12 0.54t0.05 0.0&F0.04 0.2&F0.07

<0.10 0.22t0.06

<0.12 5.43z0.16 5.03z0.31 3.40z0.31 4.42z0.35 3.9&F0.22 3.02z0.25 2.97z0.11 5.77z0.42 4.4420.16 6.40zO 35 3.9220.31 3.4&F0.24 4.37z0.36 5.15'.31 4.39z0.15 7.4220.38 5.84g0.38 5.49+0.33 4.35z0.28 2.96z0.13

<0.013

<0.014

<0.015

<0.018

<0.010

<0.012

<0.011

<0.018

<0.014

<0.011

<0.014

<0.010

<0.015

<0.014

<0.013

<0.011

<0.015

<0.013

<0.013

<0.013

<0.019

<0.014

<0.014

<0.015

<0.009

<0.011

<0.013

<0.018

<0.019

<0.010

<0.015

<0.012

<0.015

<0.013

<0.018

<0.011

<0.013

'<0.012

<0.011

<0.017

<0.017

<0.014

<0.016

<0.017 0.009z0.007

<0.012

<0.011

<0.018

<0.016

<0.012

<0.015

<0.012

<0.016

<0.014

<0.014

<0.011

<0.016

<0.014

<0.012

<0.016 0.37zO.ll 0.25t0.15 0.30z0.13 0.37t0.20 0.22z0.10 0.14'.ll 0.3020.09 0.35z0.16 0.34z0.12 0.17'.10 0.3320.14 0.26z0.10 0,,40t0.17 0.32z0.19 0.34z0.12 0.30z0.15 0.40z0.16 0.22g0.12 0.2&F0.15 0.3&F0.12

<0.070 0.080z0.030

<0.064 0.072z0.034 0.041t0.020

<0.051

<0.047 0.06&z0.031

<0.064 0.065z0.029 0.069z0.040 0.05&z0.030

<0.066 0.064z0.039

<0.067

<0.057 0.043z0.02&

<0.051

<0.050 0.048<0.016

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<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 Location Date Sample Type 1

Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 AcTh-228 Others T

T.

T K

K L

L L

P P

P Q

Q Q

Y Y

Y M*

8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-28-89 8-28-&9 8-29-89 9-05-&9 9-05-89 9-05-89 9-05-89 9-05-89 9-05-89 8-30-89 8-30-89 8-30-89 Beet Greens Squash Leaves Cabbage Strawberry Leaves Squash Leaves Bean Leaves Cucumber Leaves Squash Leaves Collard Greens Swiss Chard Beet Greens Cabbage Squash Leaves Cucumber Leaves Squash Leaves Pepper Leaves Eggplant Leaves Swiss Chard Squash Leaves Cabbage 187z45 324g77

<126 779zl21 540263 361t73 765t45 614zl09 185z44 105245 176t70

<87 42&tl02 1560zl18 539z49 80245 283t74

<97 215t64

<119 5430zl62 5030z313 3400z310 4420z352 39&oi223 3020g252 2970gl08 5770i424 4440zl56 64002347 39202314 3480z242 4370z355 51502311 43902149 74204377 584023&0 5490z328 43502277 2960zl30

<13

<14

<15

<18

<10

<12

<1'1

<18

<14

<11

<14

<10

<15

<14

<13

<11

<15

<13

<13

<13

<19

<14

<14-,.

<15

<9

<11

<13

<.1 8

<19

<10

<15

<12

<15

<13

<18

<11

<13

<12

<11

<17

<17

<14

<16

<17 9'12

<11

<18

<16

<12

<15

<12

<16

<14

<14

<11

<16

<14

<12

<16 372+111 250gl46 3032133'672200 220zl00 139zllO 29&t90 3502156 344gl 1 9 174g96 32&zl35 265gl00 39&t173 322gl92 336zl15 229zl51 403tl56 21&tl19 284tl51 382z115

<70 80z30

<64 72z34 41g20

<51

<47 6&z31

<64 65229 69z40 5&z30

<66 64z39

<67

<57 43z28

<51

<50 4&zl6

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<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 Beta 3/89 8/89 Air Filter (pCi/filter)

Air Filter (pCi/filter)

QA 89-031 QA 89-090 62t5 Invalid (5) 6lz2 (3) 60t2 60t2 Tritium Tritium Tritium Beta

~ p Beta 2/89 6/89 10/89 4/89 10/89 Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Water (pCi/liter)

QA 89-012 QA 89-063 QA 89-119 QA 89-032 QA 89-129 27542356 4053z450 3496g364 57z5 32t5 3300zl00 (4) 2900zl00 2800zl00 43002100 (4) 4400z100 4300tl00 35002200 (4) 3400z100 3400z100 50t2 (3) 52t3 48t2 32tl (3) 30zl 3lzl

-112

TABLE 18 (Continued)

INTERLABORATORY COHPARISON PROGRAH RESULTS Analysis S

Date Hedi um Site Reference No.

EPA Result

( 1)

Site Result (2)

I-131 I-131 Gamma (Cs-137)

Gamma (Cs-137)

Gamma (Cs-137)

Beta Beta 2/89 8/89 8/89 3/89 4/89 5/89 9/89 Water (pCi /liter)

Water (pCi/liter)

Air Filter (pCi/filter)

Air Filter (pCi/filter)

Hilk (pCi/liter)

Water Water QA 89-011 QA 89-082 QA 89-090 QA 89-031 QA 89-033 QA 89-042 QA 89-105 7.5'.05 83z8 10z5 20z5 50z5 50z5 8.0z0.8 (3) 8.0z0.7 8.0z0.8 8721 (3) 88z3 90z3 10'3) 12t4 llz5 27z5 (3) 26z6 26z6 50z8 (3) 50z8 49z9 5lz3 (3) 47z3 48z3 6zl (3) 6zl 5tl

-113

TABLE 18 (Continued)

INTERLABORATORY COHPARISON PROGRAM RESULTS Ana1ys i s r

Gamma (Cr-51) 1

• -I Gamma (Zn-65)

Gamma (Ru-106)

Gamma (Cs-134)

Gamma (Cs-137)

I Gamma (Co-60)

Date 2/89 2/89 2/89 2/89 2/89 2/89 Medium

.Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Water (pCi/liter)

Site Reference No.

QA 89-009 QA 89-009 QA 89-009 QA 89-009 QA 89-009 QA 89-009 EPA Result (1) 235z24 159zl 6 178<18 10z5 10z5 10z5 Site Result (2) 216zl8 (3) 225z35 225t27 14926 (3) 154t11 15lzl2 143216 (3) 143t24 137z24 8tl (3) 9z2 10z2 9z2 (3) 10z3 8g2 10zl (3) 10z3 9t3 I

~

~

-114

~ Jl TABLE 18 (Continued)

INTERLABORATORY COHPARISON PROGRAM RESULTS Analysis I

Date Hedium Site Reference No.

EPA Result (1)

Site Result (2)

~

~rl Gamma (Co-60)

Gamma (Zn-65)

Gamma (Ru-106) 6/89 6/89 6/89 Hater (pCi/liter)

Hater (pCi/liter)

Water (pCi/liter)

QA 89-058 QA 89-058 QA 89-058 3lz5 16521 7 128zl3 34z4 (3) 33j:2 29z4 172t6 (3) 19&g14 175zl3 127217 (3) 127z28 122~27 Gamma (Cs-134) l Gamma (Cs-137)

Gamma (Ba-133) 6/89 6/89 10/89 Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

QA 89-058 QA 89-058 QA 89-106 39z5 20z5 59z6 37z2 (3) 38i4 37z4 18i2 (3) 20z4 22+3 64z6 (3) 55z6 58z7

-115

TABLE 18 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No.

EPA Result (1)

Site Result (2)

Gamma (Co-60)

Gamma (Zn-65)

Gamma (Ru-106)

Gamma (Cs-134)

Gamma (Cs-137) 10/89 10/89 10/89 10/89 10/89 Water (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

Hater (pCi/liter)

QA 89-106 QA 89-106 QA 89-106 QA 89-106 QA 89-106 30z5 129tl 3 16lzl6 29z5 59z5 28z5 (3) 29z5 32t5 134232 (3) 136z36 135t43 138t32 (3) 138236 155z43 26z4 (3) 26t4 25t5 59z6 (3) 59z6 60z6

-116

TABLE 18 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Oate Medium Site Reference No.

EPA Result (1)

Site Result (2)

Gamma (Cs-134)

Gamma (Cs-137)

Gamma (Cs-134)

Gamma (Cs-137) 4/89 4/89 10/89 10/89 Water (pCi/liter)

Water (pCi /liter)

Hater (pCi/liter)

Hater (pCi/liter)

QA 89-032 QA 89-032 QA 89-129 QA 89-129 20z5 20z5 Sz5 St5 18z2 (3) 16z4 18z4 19z4 (3) 19z4 20z5 5z2 (3) 4t2 5t2 5tl (3) 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 Medium Hap Designation Figure Number Location Description Degrees and Distance

( 1)

Shoreline Sediment 05*

06 Figure lA Sunset Bay Figure lA Langs

Beach, Control 80't 1.5 miles 230't 5.8 miles Fish 02*

03'0*

Figure lA Nine Hile Point Transect Figure lA FitzPatrick Transect Figure lA Oswego Transect 315 at 0.3 miles 55't 0.6 miles 235 at 6.2 miles Surface Water 03'8*

09 10 Figure lA FitzPatrick Inlet Figure 1A Oswego Steam Station Inlet Figure lA NHP Unit 1 Inlet Figure lA Oswego City Water Figure lA NMP Unit 2 Inlet 70't 0.5 miles 235't 7.6 miles 305't 0.3 miles 240't 7.8 miles 304't O.l miles

~,

~

-119

TABLE 19 (Continued)

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

Air Radioiodine and Particulates R-1*

R-2'-3'-4*

R-5*

Dl Figure 1A R-1 Station, Nine Hile Point Road Figure 2

R-2 Station, Lake Road Figure 2

R-3 Station, Co. Rt.

29 Figure 2

R-4 Station, Co. Rt.

29 Figure lA R-5 Station, Hontario Point Road Figure 2

Dl On-Site Station

~ Figure 2

G On-Site Station Figure 2

N On-Site Station Figure 2

I On-Site Station Figure 2

J On-Site Station Figure 2

K On-Site Station 88 at 1.8 miles 104 at 1.1 miles 132't 1.5 miles 143't 1.8 miles 42't 16.4 miles 69't 0.2 miles 250 at 0.7 miles 70't 0.8 miles 98't 0.8 miles 110 at 0.9 miles 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 Medium Map Figure Designation Number Location Description Degrees and Distance (1)

Air Radioiodine And Particulates Continued D2 Figure lA D2 Off-Site.Station, Rt.

64 Figure lA E Off-Site Station, Rt.

4 Figure lA F Off-Site Station, Dutch Ridge Rd.

117 at 9.0 miles 160 at 7.2 miles 190't 7.7 miles Thermo-luminescent Dosimeters (TLD) 10 Figure 2

Dl On-Site Station Figure 2

D2 On-Site Location Figure 2

E On-Si te Location Figure 2

F On-Si te Location Figure 2

G On-Site Station Figure lA R-5 Off-Site Station Figure lA Dl Off-Site Location Figure lA D2 Off-Site Station

&0't 117't 11.4 miles 9.0 miles 69't 0.2 miles 140't 0.4 miles 175't 0.4 miles 210't 0.5 miles 250 at 0.7 miles 42 at 16.4 miles

-121

~ - ~

g A.

Sampl e Medium Map Designation Figure Number TABLE 19 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS Location Description Degrees and Distance (1)

Thermo-luminescent Dosimeters (TLD)

Continued 12 13 14*

15*

18'9 23'4 25 26 27 28 Figure lA E Off-Site Station Figure lA F Off-Site Station Figure lA G Off-Site Station Figure 1A Southwest Oswego Control Figure 1A West Site Boundary Figure 2

Energy Information Center Figure lA East Site Boundary Figure 2

H On-Site Station Figure 2

I On-Site Station Figure 2

3 On-Site Station Figure 2

K On-Site Station Figure 2

North Fence, JAFNPP Figure 2

North Fence, JAFNPP 160't 7.2 miles 190't 7.7 miles 225 at 5.3 miles 226't 12.6 miles 237't 0.9 miles 265't 0.4 miles 81't 1.3 miles 70't 0.8 miles 98't 0.8 miles 110't 0.9 miles 132't 0.5 miles 60't 0.4 miles 68't 0.5 miles

TABLE 19 (Continued)

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

Thermo-luminescent Dosimeters (TLD)

Continued 29 30 31 39 47 49'1 53 54 55 56*

58>>

Figure 2

North Fence, JAFNPP Figure 2

North Fence, JAFNPP Figure 2

North Fence, NHP-1 Figure 2

North Fence, NHP-1 Figure 2

North Fence, JAFNPP Figure 18

Phoenix, NY Control Figure lA Oswego Steam Station, East Figure lA Oswego Elementary School, East Figure 1B Fulton High School Figure 1A Hexico High School Figure lA Pulaski Gas Substation, Rt.

5 Figure lA New Haven Elementary School Figure lA Co. Rt.

1 and Alcan 65't 0.5 miles 57 at 0.4 miles 276 at 0.2 miles 292't 0.2 miles 69 at 0.6 miles 170 at 19.8 miles 233 at 7.4 miles 227 at 5.8 miles 183 at 13.7 miles 115't 9.3 miles 75't 13.0 miles 123't 5.3 miles 220't 3.1 miles

-123

TABLE 19 (Continued)

ENVIRONMENTAL SAMPLE LOCATIONS Sample Hedium Hap Figure Designation

'Number Location Description Degrees and Distance

( 1)

Thermo-luminescent Dosimeters (TLD)

Continued 75>>

76*

77*

78*

79'0*

81*

82'3*

84*

85'6'igure 2

North Fence, NHP-2 Figure 2

North Fence, NMP-2 Figure 2

North Fence, NHP-2 Figure 2

East Boundary, JAFNPP Figure 2

County Route 29 Figure 2

County Route 29 Figure 2

Hiner Road Figure 2

Hiner Road Figure 2

Lakeview Road Figure lA Lakeview Road Figure 2

North Fence, NMP-1 Figure 2

North Fence, NMP-1 5't O.l miles 25't 0.1 miles 45't 0.2 miles 90 at 1.0 miles 115't l. 1 miles 133 at 1.4 miles 159 at 1.6 miles 181 at 1.6 miles 200't 1.2 miles 225't 1.1 miles 294't 0.2 miles 315't 0.1 miles

TABLE 19 (Continued)

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

Thermo-luminescent Dosimeters (TLD)

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

92'3*

94*

95'6*

97*

98*

99 Figure 2

North Fence, NHP-2 Figure lA Hickory Grove Road Figure lA Leavitt Road Figure 1A Route 104 and Keel'e Road Figure lA County Route 51A Figure lA Haiden Lane Road Figure lA County Route 53 Figure lA County Route 1 and Kocher Road Figure lA Lakeshore Camp Site Figure 1A Creamery Road Figure 2

County Route 29 Figure lA Lake Road Figure 1A Nine Nile Point Road 341't 0.1 miles 97't 4.5 miles 1 11't 4. 1 miles 135't 4.2 miles 156't 4.8 miles 183't 4.4 miles 205't 4.4 miles 223't 4.7 miles 237't 4.1 miles 199't 3.6 miles 143't 1.8 miles 101't 1

~ 2 miles 88't 1.8 miles

-125

TABLE 19 (Continued)

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

( 1)

Thermo-luminescent Dos)meters (TLD)

Continued 100 101 102 103 104 105 106 107 108 109 110 Figure 2

County Route 29 and Lake Road Figure 2

County Route 29 Figure 1B Oswego County Airport Figure 2

Energy Information Center, East Figure 1A Parkhurst Road Figure 2

Lakeview Road Figure 2

Shoreline

Cove, West of NHP-1 Figure 2

Shoreline

Cove, West of NMP-1 Figure lA Lake Road Figure 1A Lake Road Figure 1B Baldw)nsvi lie, New York Control Figure lA

Sterling, New York Control 104't 1.1 miles 132't 1.5 miles 175't 11.9 miles 267't 0.4 miles 102't 1.4 miles 198't 1.4 miles 274't 0.3 miles 272't 0.3 miles 104't 1.1 miles 103 at 1.1 miles 166't 26.4 miles 214't 21.8 miles Cows Milk 16 Figure 4

Indicator Location Figure 4

Indicator Location 107't 5.5 miles 190 at 5.9 miles 126

TABLE 19 (Continued)

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

Cows Hi 1k Continued 50 55 60 65*

Figure 4

Indicator Location Figure 4

Indicator Location Figure 4

Indicator Location Figure 4

Indicator Location Figure 4

Control Location 93 at 9.3 miles 95't 9.0 miles 90 at 9.5 miles 113't 7.8 miles 220't 17.0 miles Food Products L*

Figure 3

Indicator Location Figure 3

Indicator Location Figure 3

Indicator Location Figure 3

Control Location Figure 3

Indicator Location Figure 3

Indicator Location Figure 3

Indicator Location 84't 1.6 miles 101't 1.9 miles 82't 1.7 miles 225't 15.6 miles 96't 1.7 miles 136't 1.7 miles 110 at 2. 1 miles

'-Technical Specification location.

( 1)

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

-127 i

Hedium Qlni~

Type and Number of*

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 Indicator Locations:

Highest Annual Hean:

Control Location:

than ~

Location

& Hhu}~

HhUL~

llaw&

Number of Nonroutine Haua~

Shoreline Sediment (pCi/kg-dry)

GSKQ.-

Cs-134 Cs-137 150 180

<LLD

?9LL?l?l 254-342

<LLD Sunset Bay: ?5~~+

1.5 at 80'54-342

<LLD

<LLD 0

0 Fish *

(pCi/kg-wet) ~~)

~ (h)

Hn-54 Fe-59 Co-58 Co-60 2n-65 Cs-134 Cs-137 130 260 130 130 260 130 150

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 20-43

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD NMP:

0.3 at 315'0-43

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 20-33 0

0 0

0 0

0 0

-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 1989'edium QJaRQ Type and Number of km~~*

LLD~

Indicator Locations:

~~(

Location (b) of Highest Annual Mean:

Control Location:

Location

& Haul~

hlLLD Number of Nonroutine fh@xi~

>>,f Surface Water *

(pCi/liter)

H-3 G5~~:

Hn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 3000(c) 15 30 15 15 30 15 15 15(c)

?S~~U.

210-350

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD JAF:

0.5 at 70'10-350

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 323 QLQ 180-660

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0 0

0 0

0 0

>>)

a t

-129

• g C

~

TABLE 20 (Continued)

~

h r

~ ~

~ h 4

If

, i h'

h f

~

~

~ I

~4P C

Cr Hedium QlsMQ Surface Hater

'pCi/liter)

(Continued)

Air Particulates'pCi/m3)

RADIOLOGICAL ENVIRONMENTAL HONITORING 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 NEW YORK, JANUARY DECEHBER 1989'ocation (b) of Indicator Locations:

Highest Annual Hean:

Control Location:

Ha~

Location 5 H~~

Type and Number of 8243ZMi

~LD~

Cs-134 Cs-137 Ba/La-140 15

<LLD

<LLD

<LLD 18

<LLD

<LLD

<LLD 15

<LLD

<LLD

<LLD IIIIIIIIII tlllulllf 1.8 at 143'.009-0.038 0.007-0.039 Gross Beta:

0.01 0.007-0.041 LQRU.:

0 07

<LLD

<LLD

<LLD 65k KQ2 Cs-134 0.05

<LLD

<LLD

<LLD Cs-137 0.06

<LLD

<LLD

<LLD

-130 Number of Nonroutine Raauris.

0 0

0 0

0 0

0

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 1989'edium QlniLtt)

Type and Number of Indicator Locations:

Haa~

LLEW Location (b) of Highest Annual Mean:

Control Location:

Location 5 ~~

Number of Nonroutine Resorts.

TLDA (mrem per quarterly period)

Gamma Qme Q?D:

(d) 6.4-45.0 TLD¹ 85

'~4. (3LQ (g)

~ljiQUID.

0.2 at 294'5.7-45.0 8.6-17.0 0

I Hi lk'pCi/liter)

~i~ (e)(h)

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

I-131

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0 Food Products'~:(h)

(pCi/kg-wet)

(broadleaf I-131 vegetation)

Cs-134 60 60

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 Cs-137 80 Loca.

K

~~

<LLD 1.7 at 96' 0

-131

TABLE 20 (Continued)

F.

3 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 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEHBER 1989*

.,FF

~

~

i

'I

~3 Xah.'~~:

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

~

(a)

LLD values as required by the Radiological Technical Specifications.

LLD units are specified in the medium column.

F 5 ~

'0 j

.i j Ftj F

3 3

F 3

F (b)

(c)-

(d)

(e)

(f)

(g)

(h)

=

Data includes results from optional samples in addition to samples Specifications.

For food products, only broadleaf vegetation was evaluated.

required by the Technical Location is distance in miles and direction in compass degrees based on NHP-2 reactor centerline.

Units for this column are specified in medium column.

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

The Technical Specifications do not specify a particular LLD value for environmental TLDs.

The NHP-1 and NHP-2 Off-Site Dose Calculation Hanuals contains specifications for environmental TLD sensitivities.

The Technical Specification criteria for indicator milk sample locations includes locations within 5.0 miles of the site.

There are no milk sample locations within 5.0 miles of the site.

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

Fraction of number of detectable measurements to total number of measurements.

Mean and range results are based on detectable measurements only.

The results for TLD ¹85 must be evaluated with the knowledge that this TLD is in close proximity (300-500 feet) of the Nine Mile Point Unit 1 reactor building and the radwaste buildings

This TLD, as well as other TLDs in this area, are adjacent to the lake shoreline which is a restricted area to members of the public.

There are no residences or private property near this area.

t

~

~

-132

TABLE 21 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Y

r Cs-134 i

M Cs-137 Co-60 in.

M M

1979 (2) 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.22 0.22 0.07 0.09 LLD LLD 0.05 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD

, LLD LLD LLD LLD 0.22 0.08 LLD 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 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.

-133

TABLE 22 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Y r Cs-134 Cs-137 Co-60 M

e 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (4)

(4)

(4)

(4)

(4)

(4)

LLD LLD LLD LLD 0.25 (4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

(4)

LLD LLD LLD LLD LLD LLD LLD LLD 0.34 0.30 (2)

(2)

(2)

(2)

(2)

(2)

LLD LLD LLD LLD LLD (2)

(2)

(2)

(2)

(2)

(2)

LLD LLD LLD LLD LLD

<2)

(2)

(2)

(2)

(2)

(2)

LLD LLD 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.

-134

TABLE 23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1.2 0.13 0.04 0.03 0.03 0.028 0.027 0.041

0. 015

0. 026

0. 021

0. 017 0.023 0.020 1.2 0.13 0.20 0.06 0.11 0.062 0.055 0.057 0.038 0.047 0.032 0.040 0.053 0.033 1.2 0.13 0.09 0.04 0.06 0.043 0.046 0.049 0.032 0.034 0.025 0.031 0 '33 0.029 Results in pCi/g (wet)

(1)

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

-135

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

-136

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

'l 977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1)

(1)

<1)

(2)

(2)

(2)

LLD LLD LLD 2.5 2.5 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(1)

(2)

(2)

(2)

(2)

LLD LLD LLD LLD 1.4 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

<2)

(2)

LLD LLD 1.4 LLD LLD 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

-137

TABLE 26 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE NTER Cs-137 Co-60 1976 1977 1978

'l 979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1)

(1)

(1)

(2)

(2)

(2)

LLO LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.43 0.43 0.43 LLD LLO LLD LLD LLD LLD LLD LLD LLD LLD LLD LLO LLD LLD LLD LLD LLD LLD LLD LLD LLD (3)

(1)

(1)

(2)

(2)

(2)

(2)

LLD LLD LLD LLD LLD LLD 1.6 2.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLO (1)

(2)

(2)

LLD LLO LLD 1.9 LLD 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 J, A. FitzPatrick inlet canal.

-138

TABLE 27 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE NTER TRITIUM Tritium 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 440 300 215 174 211 211 112 230 190 230 250 140 240 180 929 530 490 308 290 328 307 280 220 370 550 270 460 660 652 408 304 259

~

257 276 165 250 205 278 373 210 320 373 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.

-139

~ >

~

TABLE 28 HISTORICAL ENVIRONMENTAL SAMPLE OATA SURFACE HATER TRITIUM Tr)tlum 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 365 380 377 176 150 212 194 249 110 250 260 160 430 210

&89 530 560 276 306 388 311 560 370 1200(2) 500 410 480 350 627 455 476 228 227 285 266 347 280 530 380 322 460 280 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.

-140

,<<w ~

a ~ ~-,

a a, Sgv

~.wq S q ',

~ '

"'AWPA;t 'V;

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

-142

~-

~

~

I

I

~

~ t 1

P

. l

TABLE 32 HISTORICAL ENVIRONHENTAL SAMPLE DATA

, AIR PARTICULATES Cs-137 Co-60 Preop.

1970 1971 1972 1973 1974

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 0.0001 0.0003 0.0003 0.0005 0.0002 0.0001 0.0002 LLD LLD 0.0069 LLD LLD LLD (1)

(1)

(1)

<1)

(1)

(1)

(1)

<1) 0.0105 0.0026 0.0020 0.0019 0.0045 0.0006 0.0003 LLD LLD 0.0364 LLD LLD LLD (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 0.0043

. 0.0016 0.0010 0.0011 0.0014 0.0004 0.0002 LLD'LD 0.0183 LLD LLD

, LLD (2)

(1)

(1)

(1)

(1)

, (1)

'1)

(1)

(1) 0.0003 0.0003 0.0003 0.0016 0.0002 0.0003 0.0003 0.0007 LLD

LLD, LLD LLD LLD (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

'.0711 0.0153 0.0007 0.0016 0.0017 0.0010 0.0017 0.0017'LD LLD LLD LLD LLD (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

0. 0179 0.0023 0.0005 0.0016 0.0006 0.0005 0.0007 0.0012 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.

-144

~

~ ~

~

TABLE 34 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Iodine 131 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 0.01 0.02 0.02 LLD

0. 013 0.016 0.002 0.022 LLD LLD 0.023 0.011 LLD LLD 2.09 0.73 0.07 LLD

0. 013 0.042 0.042 0.035 LLD LLD 0.360 0.018 LLD LLD 0'3 0.31 0.04 LLD 0.013 0;029 0.016 0.028 LLD LLD 0.119 0.014 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.

-146

~

~

I ~ p )(

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

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985

'986 1987 1988 1989 (1)

(1)

(1)

<1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 4.1 4.4 4.4 3.4 2.8 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 12 6'8.7 14.3 17.9 15.4 (2)

<1)

(1)

(1)

(1)

(1)

<1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 6.2 7.0 6.1 6.4 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.

-148

1

~

~

~

TABLE 368 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)

(2)

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1)

(1)

(1)

(1)

(1)

<1)

(1)

(1)

(1)

(1)

<1)

(1)

(1)

(1)

(1)

(1)

~

4.0 4.6 4.3 3.8 2.5

<1)

(1)

(1)

(1)

(1)

(1)

<1)

('1 )

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 7.1 8.6 6.0 7.0 6.8 (1)

(1)

(1)

(1)

(1)

(1)

(1)

<1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 5.0 6.0 5-. 2 5.3 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.

-149

TABLE 36C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose

<mrem)

(2)(3)

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1)

<1)

(1)

<1)

. (1)

(1)

<1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 3.9 4.8 3.5 3.9 2.1 (1)

(1)

(1)

(1)

<1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 6.8 8.2 6.0 6.6 7.0 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 5.3 6.1 5.1 5.3 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.

-150

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

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1) 4.7 1.5 2.3 3.0 3.1 4.6 3.7 3.0 3.0 2.7 3.9 4.1 3.9 5.0 4.6 4.7 4.7 4.0 4.4 2.7 (1) 9.0 7.7 8.2 24.4

10. 6 16.0 18.8 15'. 3 9.0 8.3 12.0 11.8 13.0 16.5 13.2 15.9 16.1 11.4 11.9 14.5 (2)

(1) 6.0 4.7 4.9 6.6 5.7 7.3 6.9 5.7 4.3 4.3 5.3 5.8 6.3 6.9 7.0 6.3 7.0 5.8 6.0 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.

-151

~

I

~

~

~

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

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 (1) 5.0 1.1 1.8 2.2 2.4 4.'5 3.4 3.7

~

Zo7 3.0 3.1 3.6 4.0 4.6 4.6 4.6 5.0 4.4 4.2 2.8 (1) 8.0 7.7 6.6 6.9 8.9 7.1 7.2 8.0 4.7 5.7 5.8 5.9 6.2 7.2 8.2 7.7 7.6 6.6 6.6 6.4 (2)

(1) 6.7 4.5 4.4 4.1 5.3 5.5 5.2 5.3 3.7 4.0 4.6 4.7 5.2 5.6 6.1 5.5 6.1 5.2 5.4 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.

-152

TABLE 37 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1

(1)

(1)

(1)

(1)

(1)

(1) 2.4 7.8 5.8 LL'D LLD LLD 3.6 5.6 4.5 3.9 3.9 3.9 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 5.3 12.4 8.4 LLD

'LLD LLD LLO LLD LLD LLD LLD LLD

<2)

(1)

(1)

(1)

(1)

(1)

(1)

LLD LLD LLD LLO LLD LLD 1.4 1.4 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.8 29.0 13.6 LLD LLD LLD LLD LLD LLO 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.

-153

TASLE 38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 4.0 1'l.0 3.4 3.2 3.2 3.5 3.5 3.3 LLO LLD 6.1 5.5 10.0 LLD 15.0 9.3 22.0 17.1 33.0 9 '

53.0 9.4 21.0 8.1 29.0 8.6 14.0 5.7 10.9 7.2 LLD LLO LLD LLD 11.1 8.6 8.1 6.8 10.0 10.0 LLD LLD 0.02 45.00 3.20 0.01 49.00 6.88 0.19 0.19 0.19 LLO LLD LLD 0.3 8.8 3.8 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.3 30.0 5.2 LLD LLD LLD LLD LLD LLD LLD LLD LLD Results tn pCf/liter (1)

Locations sampled were available downwind locations within ten miles with high deposition potential.

-154

S P 5

~, *+I

~,

~ ~

TABLE 39 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 1976<3) 1977 1978 1979 1980 1981 1982 1983 1984 1985<4) 1986 1987 1988 1989

<1)

(1)

(1)

('l )

0.02 LLD LLD LLO LLD LLO LLD LLD LLD LLD (1)

(1)

(1)

(1) 0.02 LLD LLD LLD LLD LLD LLD LLD LLD LLD (2)

(1)

(1)

(1)

(1) 0.02 LLD LLO LLD LLD LLO LLD 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).

-155

TASLE 40 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 1976(2) 1977 1978 1979 1980 1981 1982 1983 1984 1985(3) 1986 1987 1988 1989 LLD LLD LLD 0.004 0.004 LLD LLD LLD LLD 0;047 LLD LLD 0.008 0.009 LLD LLD

~ LLD 0.004 0.060 LLD LLD LLD LLD 0.047 LLD LLD 0.008 0.009 LLD LLD LLD 0.004 0.036 LLD LLD LLD LLD 0.047 LLD LLD 0.008 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)

~

-156

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