Text

Annual Radiological Environ Operating Rept for 1987. W/880428 Ltr
	ML18038A394
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1987
From:	Perkins T; NIAGARA MOHAWK POWER CORP.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NMP33241, NUDOCS 8805040404
	Download: ML18038A394 (167)
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~Cl.ZmmTZn DIS 1BUT'ON" DEMONSTRA. 'ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

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H ov 87/12/3I PZ'CCESSION NOTARIZED: NO DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION PERKINS,T.J. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Annual Radiologicial Environ Operating Rept for 1987."

W/880428 ltr.

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2)

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V NIASARA 0 MOHANK NIAGARAMOHAWK POWER CORPORATION/301 PLAINFIEI.DRQAQ, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 NMP33241'pril 28, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 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

Dear Mr. Russell:

In accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2, we are enclosing the Annual Radiological Environmental Operatin Report for the period January, 1987 through December, 1987.

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

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

Very truly yours,

,c,64~

Thomas J. Perkins Vice President Nuclear TJP/HJF/bls Enclosure (3 copies) xc: USNRC Region I Resident Inspector (Unit 1/Unit 2)

NIAGARA MOHAWK POWER CORPORATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 1987 December 31, 1987 for NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket Number 50-220 and NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

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TABLE OF CONTENTS

~Pa e List of Tables List of Figures vl Introduction II. Description

1) Sample Collection Methodology and Analysis

2) Analyses Performed

3) Changes to the 1987 Sample Program 4J Exceptions to the 1987 Sample Program III. Evaluation of Environmental Data 10 A) Aquatic Program 12

1) Shoreline Sediment 13

2) Fish 16

3) Surface Water 19 B) Terrestrial Program 22

1) Air Particulates Gross Beta 22

2) Monthly Air Particulate Composites 23

3) Airborne Radioiodine 27

4) TLD (Environmental Dosimetry) 29

5) Milk 34

6) Land Use Census 39

7) Food Products 40

8) Interlaboratory Comparison Program 42

9) Environmental Sample Locations 42

10) Radiological Environmental Monitoring Program Annual Summary 43

11) Historical Environmental Sample Data 43

TABLE OF CONTENTS (Continued)

~Pa e C) Conclusion 43 D) General Reference Material 45 E) Data Tables 1987 47

LIST OF TABLES Table No. Content P~ae .

Table 1 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program A. Aquatic Program 48 Table 2 Sample Collection and Analysis, Site Radiological Environmental Moni toring Program B. Terrestrial Program 49 Table 3A Concentration of Gamma Emitters in Shoreline Sediment, Samples (PCilg-dry) 50 Table 3B Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/kg-dry) 51 Table 4A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 52 Table 4B Concentration of Gamma Emitters in Fish Samples (pCilkg-wet) 54 Table 5 Concentration of Gamma Emitters in Surface Water Samples 56 Table 6 Concentration of Tritium in Surface Water Samples 60 Table 7 Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity 61 Table 8 Environmental Airborne Particulate Samples-On-Site Stations, Gross Beta Activity 63 Table 9 Concentration of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples 64 Table 10 Environmental Charcoal Cartridge Samples-Off-Si te Stations, I-131 Activity 79 Table ll Environmental Charcoal Cartridge Samples-On-Site Stations, I-131 Activity 81 Table 12A Direct Radiation Measurement Results (mrem per standard month) 82 Table 12B Direct Radiation Measurement Results (mrem per quarterly period) 86

LIST OF TABLES (Continued)

Table No. Content ~Pa e Table 13 Concentration of Gamma Emitters in Milk 90 Table 14 ~ Concentration of Iodine-131 in Milk 96 Table 15 Milk Animal Census 98 Table 16 1987 Residence Census 100 Table 17A Concentration of Gamma Emitters in Food Products (pCi/g-wet) 101 Table 17B Concentration of Gamma Emitters in Food Products (pCi/kg-wet) 103 Table 18 Interlaboratory Comparison Program Results 105 Table 19 Environmental Sample Locations 113 Table 20 Radiological Environmental Monitoring Program Annual Summary Table 21 Historical Environmental Sample Data Shoreline Sediment (Control) 127 Table 22 Historical Environmental Sample Data Shoreline Sediment (Indicator) 128 Table 23 Historical Environmental Sample Data Fish (Control) 129 Table 24 Historical Environmental Sample Data Fish (Indicator) 130 Table 25 Historical Environmental Sample Data Surface Water (Control) 131 Table 26 Historical Environmental Sample Data Surface Water (Indicator) 132 Table 27 Historical Environmental Sample Data Surface Water Tritium (Control) 133 Table 28 Historical Environmental Sample Data Surface Water Tritium (Indicator) 134

LIST OF TABLES (Continued)

Table No. Content ~Pa e Table 29 Historical Environmental Sample Data Air Particulate Gross Beta (Control) 135 Table 30 Historical Environmental Sample Data Air Particulate Gross Beta (Indicator) 136 Table 31 Historical Environmental Sample Data Air Particulates (Control) 137 Table 32 Historical Environmental Sample Data Air Particulates (Indicator) 138 Table 33 Historical Environmental Sample Data Air Radioiodine (Control) 139 Table 34 Historical Environmental Sample Data Air Radioiodine (Indicator) 140 Table 35 Historical Environmental Sample Data Environmental TLD (Control) 141 Table 36 Historical Environmental Sample Data Environmental TLD (Indicator) 142 Table 37 Historical Environmental Sample Data Milk (Control) 147 Table 38 Historical Environmental Sample Data Milk (Indicator) 148 Table 39 Historical Environmental Sample Data Food Products (Control) 149 Table 40 Historical Environmental Sample Data Food Products (Indicator) 150

LIST OF FIGURES

~Pi ux'e No Content ~Pa e Figure lA Off-Site Environmental Station and 151 TLD Locations Figure 1B Off-Site Environmental Station and TLD 152 Locations (Southern)

Figure 2 On-Site Environmental Station and TLD 153 Locations Figure 3 Nearest Residence and Food Product Locations 154 Figure 4 Milk Animal Census and Milk Sample 155 Locations Figure 5 New York State Map 156

NINE MILE POINT NUCLEAR STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I. INTRODUCTION This report is submitted in accordance with Appendix A (Technical Specifications), Section 6.9.1.d to License DPR-63, Docket No. 50-220 for the Nine Mile Point Nuclear Station Unit 1 and Section 6.9.1.7 to License NPF 69, Docket No. 50-410 for the Nine Mile Point Nuclear Station Unit 2 for the calendar year 1987.

II. DESCRIPTION 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 sample collections for the radiological program are performed by two groups. EA Science and Technology Inc. (EA) performs much of the environmental sampling. EA is presently performing the Nine Mile Point Biological Monitoring Program required by the Station s SPDES Permit.

The staff required by EA to perform this program is used to perform the terrestri'al sampling required for the site Radiological Environmental

,Monitoring Program (REMP). In-plant canal sampling and remaining terrestrial sampling is performed jointly by the NMPNS and the James A.

FitzPatrick Nuclear Power Plant (JAFNPP) staffs.

Sam le Collection Methodolo and Anal sis A. Shoreline Sediment 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. Optional samples may be collected from other shoreline locations at or near the site.

Shoreline sediment locations are shown on Figure 1A (refer to Table 19 for location designations and descriptions).

B. Fish Samples Available fish species are obtained from collections during the spring and fall. Samples are collected from two of four possible on-site sample transects located in the vicinity of the site discharge points and one off-site sample transect.

Available species are selected under. the following guidelines:

II. DESCRIPTION (Cont'd)

1. Sam le Collection Methodolo and Anal sis (Cont'd)

B. Fish Samples (Cont'd)

Samples of 0.5 to 1 kilogram of edible portions for a minimum of two species per location.

2~ When two independent 'species are not available at all sample locations, a species may be divided into two samples for each location. This procedure may be accomplished provided that a sufficient sample size is available for the species in question at all three locations.

Selected fish samples are segregated by species and location and are processed immediately after collection. Samples are shipped frozen in insulated containers. Edible portions of samples are analyzed for gamma emitting radionuclides.

Fish sample transects are shown on Figure 1A (refer to Table 19 for location designations and descriptions).

C. Surface Water Surface water samples're 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 large 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.

II. DESCRIPTION (Cont'd)

1. Sam le Collection Methodolo and Anal sis (Cont'd)

C. Surface Water (Cont'd)

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 1987 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 Manuals Surface water sample locations are shown on Figure 1A (refer to Table 19 for location designations and descriptions).

'. Air Particulate/Iodine 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/g) based'n historical meteorological data. These stations (R-l, R-2, and R-3) are located in the east, east-southeast, and southeast sectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2 reactor building. The Technical Specifications also require that, a fourth air sampling station be located in the vicinity of a year round community having the highest calculated deposition factor (D/g) 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 (D1, G, H, I, J, and K). These locations generally surround the area occupied by the three generating facilities, but are well within the site boundary. One other 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 ESE, SSE and S sectors and range in distance from 7.2 to 9.0 miles.

II. DESCRIPTION (Cont'd)

1. Sam le Collection Methodolo and Anal sis (Cont'd)

D. Air Particulate/Iodine (Cont'd)

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 for gamma analyses on a monthly basis by location 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 Eor location designations and descriptions).

E. TLD (direct radiation)

Thermoluminescent'osimeters (TLD's) are used to measure direct radiation (gamma dose) in the environment. TLD's are obtained from Teledyne Isotopes on a quarterly basis and are read at Teledyne Isotopes'acility in,Westwood, New Jersey. Shipment control TLD's (at least two) accompany each shipment to and Erom 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 indus trial sites, schools, proximal towns or commun i ties or other special activity areas. Control TLD's are located to the southwest, south and northeast of the site at distances of 12.6 to 19.8 miles.

II. DESCRIPTION (Cont'd)

1. Sam le Collection Methodolo and Anal sis (Cont'd)

E. TLD (direct radiation) (Cont'd)

TLD's used during 1987 were composed oE rectangular teflon wafers impregnated with 251. CaSO4. Dy Phosphor. These were placed in polyethylene packages to ensure dosimeter integrity.

TLD packages were placed in open webbed plastic holders and were attached to supporting structures, usually trees or utility poles.

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

F. Milk Milk samples are collected in polyethylene bottles from the bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat. Two gallons are collected during the first halE 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.'ilk sample location selection is based on maximum deposition factors (D/g). 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 1987, there were no milk sample locations within 5.0 miles that could be sampled. However, there were several optional locations beyond five miles that were sampled.

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

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

The milk sample locations are found on Figure 4. (refer to Table 19 for location designations and descriptions).

II. DESCRIPTION (Cont'd)

1. Sam le Collection Methodolo and Anal sis (Cont'd)

G. Land Use Census A land use census is conducted to determine the utilization of land in the vicinity of the site. The land use census actually consists of two types of census. , A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. A census covering areas out to a distance of 10 miles exceeds the distance required by the Technical Specifications. This census is conducted during the beginning of the grazing season using road surveys, contacting local agricultural authorities, post cards, and investigating references from other owners.

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 sunder 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 s'ectors over land where residences are located within 3 miles.

The results of the two land use census are shown on Tables 15 and 16 and on Figures 3 and 4.

Food Products Food products are collected once per year during the late sunder at the approximate height of the harvest season. Approximately one kilogram of broadleaf vegetables 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 emit ters (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).

II. DESCRIPTION (Cont'd)

2. Anal ses Performed The Radiological Environmental Monitoring, Program (RFMP) samples were analyzed by Teledyne Isotopes and by the Site Environmental Laboratory during 1987. The following samples were analyzed by the site:

Air particulate filter (weekly gross beta analysis)

Air particulate filter (monthly gamma spectral analysis)

Airborne radioiodine cartridge (weekly gamma spectral analysis)

Lake water (monthly gamma spectral analysis only)

Pish (gamma spectral analysis)

Shoreline sediment (gamma spectral analysis)

~

Milk (gamma spectral analysis only)

The remainder of the sample analyses, as outlined in Table 1 and 2, were analyzed by Teledyne Isotopes.

3. Chan es to the 1987 Sam le Pro ram A. Program TLD f1107 was added to the monitoring program on April 2, 1987. TLD iP107 was added to the program as a backup for. TLD

$1106 which is used to evaluate any possible doses to members of the public involved in activities within the site boundary.

B. An additional food product location (J) was added to the monitoring program during 1987. This location was utilized during 1987 for garden fruits and vegetables. Location J was added because of'ts proximity to the site and represents one location of several program locations that may be utilized for food product samples dependent upon sample availability.

C. The Nine Mile Point Nuclear Station Unit 2 inlet canal was added to the sampling program during 1987. The Unit 2 inlet canal removes cooling water from Lake Ontario. This location was added to the sampling program to be 'consistent with the sampling program at the other generating facilities and to assess any possible impact from. the operation of the generating facilities in the immediate area of Lake Ontario.

II. DESCRIPTION (Cont'd)

3. Chan es to the 1987 Sam le Pro ram (Cont'd)

D. Three on-site (within the site boundary) air sampling stations were moved to former off-site air sampling locations. The three air, sampling stations were D2 on-site (moved 1/14/87), E on-site (moved 1/14/87) and F on-site (moved 1/15/87). These stations were moved to previous air sampling locations D2 off-site,'

off-site, and F off-site which were utilized prior to 1985.

None of the on-site or off-site locations are required by the Technical Specifications. The on-site locations were moved because of the importance of locating monitoring stations between the site and populated areas. The data from such locations would be of great importance in the event of a radiological release incident. The D2 off-site location is in line with Mexico, N.Y., the E off-site location is in line with Phoenix, N.Y. and" the F off-site location is in line with Fulton, N.Y. The three on-site locations were not considered as critical as the off-site locations when considering the fact that air monitoring stations are already located at the site boundary in critical downwind areas.

4. Exce tions to the 1987 Sam le Pro ram Exceptions to the 1987 sample program concerns those samples or monitoring, requirements whic'h are required by the Technical Specifications. This section implements section 3.6.20 of the Nine Mile Point Nuclear Station Unit 1 Technical Specifications and Section 3.12.1 of the Nine Mile Point Nuclear Station Unit 2 Technical Specifications.

A. Air Radioiodine and Particulate Sampling Required by the Technical Specifications Environmental air sample equipment at R-3 off-site air sampling station was inoperable from 4/14/87 (1550 hours0.0179 days 0.431 hours 0.00256 weeks 5.89775e-4 months ) to 4/16/87 (0919 hours0.0106 days 0.255 hours 0.00152 weeks 3.496795e-4 months ). The vacuum pump was found defective and was replaced.

2. Environmental air sample equipment at R-5 off-site air sampling station was inoperable from 6/23/87 (1057 hours0.0122 days 0.294 hours 0.00175 weeks 4.021885e-4 months ) to 6/23/87 (1329 hours0.0154 days 0.369 hours 0.0022 weeks 5.056845e-4 months ). The vacuum pump was found defective and was replaced.

3. Environmental air sample equipment at R-5 off-site air sampling location was inoperable from 6/27/87 (2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months ) to 6/30/87 (1504 hours0.0174 days 0.418 hours 0.00249 weeks 5.72272e-4 months ). The vacuum pump fuse was blown and the pump was found defective. The pump was replaced.

4. Environmental air sample equipment at R-2 off-site air sampling location was inoperable from 9/4/87 (0550 hours0.00637 days 0.153 hours 9.093915e-4 weeks 2.09275e-4 months ) to 9/4/87 (0855 hours0.0099 days 0.238 hours 0.00141 weeks 3.253275e-4 months ). The vacuum pump was found defective and was replaced.

II. DESCRIPTION (Cont'd) 4.A. Exce tions to the 1987 Sam le Pro ram (Cont'd)

5. Environmental air sample equipment at R-4 off-site air monitoring station was inoperable from 9/10/87 (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ) to 9/11/87 (1340 hours0.0155 days 0.372 hours 0.00222 weeks 5.0987e-4 months ). The vacuum pump was found defective and was replaced.

6. Environmental air sample equipment at R-5 off-site air monitoring station was inoperable from 10/31/87 (1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months ) to 11/3/87 (1056 hours0.0122 days 0.293 hours 0.00175 weeks 4.01808e-4 months ). The vacuum pump was found defective and was replaced.

7. Environmental air sample equipment at R-1 and R-2 off-site air monitoring stations was inoperable from ll/6/87 (2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months ) to 11/7/87 (0510 hours0.0059 days 0.142 hours 8.43254e-4 weeks 1.94055e-4 months ). The vacuum pumps in both of these monitoring stations were inoperable due to an off-site power loss. All monitoring equipment was operable once off-site power was restored.

Other occurrences of downtime for optional air sampling stations were documented for 1987. However, these occurrences are not presented here because optional air sampling stations are not required .by the Technical Specifications. Documentation includes downtime for air sampling equipment as well as environmental radiation monitoring equipment.

B. Lower Limit of Detection for Environmental Samples The Technical Specifications require that environmental samples analyzed for the Radiological Environmental Monitoring Program meet the lower limits of detection (LLD) found on Table 4.6.20-1 of the Nine Mile Point Unit 1 Technical Specifications and Table 4.12.1-1 of the Nine Mile Point Unit 2 Technical Specifications. All of the 1987 environmental sample" 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.

C. Deviations from the Interlaboratory Comparison Program Section 3.6.21 of the Nine Mile Point Unit 1 Technical Specifications and Section 3.12.3 of the Nine Mile Point Unit 2 Technical Specifications requires 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.

I1. DESCRIPTION (Cont'd) 4.C. Exce tions to the 1987 Sam le Pro ram (Cont'd)

During 1987, 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. The amount of samples obtained from the EPA program was based on the maximum amount available per participant or on a ten percent or better level (percent of the ratio of EPA samples to the total required sample volume).

A review of the 1987 results showed that one EPA sample, which was scheduled during October, was not received. This =sample was a spiked milk sample. Since the sample was not received, it could not be analyzed and the data are not included on Table 18 (Interlaboratory Comparison Program Results) ~ Subsequent investigation of the missing spike sample and written correspondence from the EPA showed that the sample was never sent by the EPA to the program participants.

III. EVALUATION OF ENVIRONMENTAL DATA There wore four separate groups . of radionuclides that were detected in the environment during 1987. A few of these 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 such as by the process of sedimentation. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China. In each case, the usual radionuclides associated with nuclear detonations were detected several months afterwards, and after a peak detection period, diminished to a point where most could not be detected. The last such weapons test was conducted in October of 1980. The resulting fallout or deposition from this test had influenced the background radiation in the

-10

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd) vicinity of the site and was very evident in many of the sample media analyzed during 1981. Calculations from 1981 of the resulting doses to man from fallout related radionuclides in the environment show that the contribution from such nuclides (such as Sr-90 or Cs-137) is significant and second in intensity only to natural background radiation. Quantities oE 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 1987, 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 Station 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. During 1987, Cs-137 was detected in a Eew milk samples collected during the first half of the grazing season and was a result of the Chernobyl accident.

The fourth group of radionuclides detected in the environment during 1987 were those that could be related to operations at the site. These select radionuclides were detected in a Eew of the sample media collected and at very low concentrations, Many of these radionuclides are a by-product of both nuclear detonations and the operation of light water reactors thus making a distinction between the two sources difficult, if not impossible. Radionuclides Ealling into this category (as applicable to the 1987 Nine Mile Point Radiological Environmental Monitoring Program) include I-131, Cs-137 and Co-60. The dose to man as a result of these radionuclides is small and signiEicantly less than the radiation exposure from naturally occurring sources oE radiation and from fallout.

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 1987, but also ta assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. It is important to note that of. radionuclides that are possibly detected concentrations 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 Eurther noted that at such minute concentrations the assessment of the significance of detected radionuclides is very difficult. Therefore, concentrations in one sample that are two times the concentration of another, for example, are not significant overall. Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in another because of counting statistics.

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

The 1970 per capita dose rate (Eisenbud) was determined to be 209 mrem per year from all sources. This average dose includes such exposure sources as natural, occupational, weapons testing, consumer products, medical, etc. The 1970 per capita dose rate due to natural sources was 130 mrem per year. Of this dose, approximately 20 mrem per year is received by the gonads and other soft issues and an additional 15 mrem per year is received by the bone tissue for a 70 kg (155 lb) man. These doses (ie.

20 mrem and 15 mrem) are the result of just K-40 alone, a naturally occurring relatively high energy beta emitter (1.3 Mev). The 1970 per capita dose rate due to the nuclear fuel cycle was 0.028 mrem per year. More recently, the nuclear fuel cycle dose was estimated by a USEPA study to be less than 0.6 mrem per year by the year 2000 (Glasstone).

Background gamma radiation around the Nine Mile Point Site, as a result of radionuclides in the atmosphere and the ground, accounts for approximately 64 mrem per year during 1987. 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 64 mrem per year, as a background dose, is significantly greater than any possible doses as a result of operations at the site during 1987.

A uatic Pro ram Tables 3 through 6 show the analytical results for the aquatic media collected during the 1987 sampling program. Aquatic samplea were collected at four possible ,indicator locations.

The locations (on-site transect designations) used for on-site sampling were NMPW, NMPP (02), JAF (03), and NMPE., Because of the, unavailability of various sample media, on-site samples may be collected from combinations of the above listed locations, when required. NMPW and NMPP may be combined into location NMPP. NMPE and JAF may be combined into location JAF. Off-site samples were collected at the Oswego Harbor area or further to the west (or east) and therefore served as control samples.

Refer to Figure 1A for the location of sample transects.

Data are evaluated only from locations required by the Technical Specifications. Data from optional sample locations are not evaluated unless indicated otherwise.

III'VALUATIONOF L'NVIRONMENTAL DATA (Cont'd)

A. 1. Shoreline Sediment Table 3 Shoreline sediment samples were collected twice during 1987.

Collections were made in April and October at one oEE-site or control location (near Oswego Harbor) and at one indicator location (shoreline area just east oE the site with recreational value). In addition to the two locations noted above, another shoreline location at the site was sampled. This optional location was the location required by the previous Technical Specifications; This location was sampled during 1987 because plant related radionuclides had been detected during previous years and because this location had been evaluated in previous Annual Radiological Environmental Operating Reports.

The results oE the shoreline sediment samples collected during 1987 at the indicator and control locations are shown on Table

3. Only the Sunset Bay location was required by the Technical Specifications during 1987.

Several radionuclides were detected in sediment samples using gamma spectral analysis. These radionuclides ranged from naturally occurring primordial radionuclides to man-made radionuclides. K-40 was detected at both the control location and indicator locations for both '.collection periods during, 1987. K-40 ranged in concentration from 8.1 pCi/g (dry) to 14.7 pCi/g (dry) at the control location and 10.6 pCi/g (dry) to 15.7 pCi/g (dry) at the indicator locations.

Ra-226 and AcTh-228, 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 0.46 pCi/g (dry) to 2.44 pCi/g (dry) at the indicator locations and 0.76 pCi/g (dry) to 1.11 pCi/g (dry) at the control location.

AcTh-228 was found at all indicator locations and ranged from 0.33 pCi/g (dry) to 0.93 pCi/g (dry) and 0.21 pCi/g (dry) to 0.67 pCi/g (dry) at the control location. Be-7 was not detected in any of the indicator or control samples. Be-7 is a naturally occurring radionuclide and has been detected intermittently during the past.

Cs-137 was detected in the optional Nine Mile Point samples collected during the year. Cs-137 was detected in the optional indicator samples only and none of the normal program samples.

The concentration detected was small and was, for the most part, indicative of operations at the site. Cs-137, was detected at concentrations ranging from 0.14 pCi/g (dry) to 0.59 pCi/g (dry). As noted above, Cs-137 was not detected in any of the control samples, although Cs-137 has been routinely observed in the past in control samples (prior to 1981). Cs-137 was not detected at the Sunset Bay indicator location.

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 1, Shoreline Sediment Table 3 (Cont'd)

Co-60 was detected in one of the optional Nine Mile Point indicator samples collected during 1987. Co-60 was detected at a concentration of 0.06 pCi/g (dry) in the October sample. The control 'location samples showed no detectable Co-60. Co-60 has not been noted in previous years at the control location. Co-60 detected during 1987 at this location is a result of operations at the site. Co-60 was not detected at the Sunset Bay indicator location during 1987.

Cs-134 was not detected in any of the indicator or control samples during 1987. Cs-134 had been detected once during 1983 in a Nine Mile Point sample at a concentration of 0.09 pCi/g (dry) which was greater than the LLD values for the 1987 samples.

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

Evaluation of average historical data (1979-1987) shows that Cs-137 has ranged from 0.05 pCi/g (dry) in 1982 to 0.22 pCi/g (dry) in 1979 at the control location. Cs-137 at the Nine Mile Point indicator location has ranged from 0.11 pCi/g (dry) in 1981 to 1.58 pCi/g (dry) in 1984. The 1987 results ranged from 0.14 pCi/g (dry) to 0.59 pCi/g (dry) at . the Nine Milch Point indicator location. Cs-137 was not detected at the control location during 1983 1986 or 1987. Overall, the control location results have decreased since 1979, while the Nine Mile Point indicator results have increased starting with the one 1982 maximum sample result for Cs-137 of 0.80 pCi/g (dry) ~

Indicator sample results at Nine Mile Point have remained fairly consistent since the fall of 1983 through 1985 and appear to be decreasing in 1986 and 1987.

Since the new Technical Specification location was initiated in 1985, there is no previous data to compare the 1985 1987 results to. As noted above, however, Cs-137 was not detected at the Technical Specification indicator location during 1985 1987. Cs-137 LLDs values ranged from <0.04 pCi/g (dry) to <0.05 pCi/g (dry) during 1987.

The evaluation of past Co-60 data indicates that Co-60 has not been detected during the period of 1979 1981 at either the Nine Mile Point indicator or control locations. During 1982, Co-60 was detected at an average concentration of 0.16 pCi/g (dry) at the Nine Mile Point location. Co-60 increased to an average concentration of 0.25 pCi/g (dry) during 1983 and subsequently decreased to 0,10 pCi/g (dry) during 1986. During 1987, Co-60 was detected only once at a concentration of 0.06

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 1. Shoreline Sediment Table 3 (cont'd) pCi/g dry. Co-60 has not been detected in any of the control samples from 1979 1987. It appears that Co-60 concentrations at the Nine Mile Point indicator location have increased (from not previously detected), remained somewhat consistent through 1984 and decreased during 1985 1987.

As noted previously, the new Technical" Specification location was initiated in 1985. Therefore, there is no previous data to compare the 1985 1987 Co-60 results to. Co-60 was not found at this location during 1985 1987. Co-60 LLDs values ranged from < 0.04 pCi/g (dry) to < 0.05 pCi/g (dry) during 1987.

Tables 21 and 22 show historical environmental data for shoreline sediment samples. Shoreline sediment samples were not collected prior to 1979.

Shoreline sediment samples, as required by the Technical Specifications, as well as optional samples of the Nine Mile Point location, will continue to be collected and analyzed.

These samples may be supplemented with additional samples, if necessary, in an effort to assess any trends and any possible impacts.

The impact of the 1987 shoreline sediment sample results is minimal and can be evaluated by projecting a dose to man using standard Regulatory Guide 1.109 methodology. The critical pathway, in this case, is direct radiation to the whole body.

The presence of Co-60 and Cs-137 at the optional Nine Mile Point location, is a result of operations at the site. Although the shoreline area is controlled by NMPC personnel, a dose may be calculated assuming that the area in question is utilized as a beach area. Assuming that a teenager spends 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at the beach area or shoreline (Regulatory Guide 1.109), and the sediment has a mass of 40 kg/m (dry) to a depth of 2.5 cm, then the associated dose to the whole body in mrem per year can be calculated.

Further assumptions must be made and include: no radiological decay of the detected radionuclides, the shoreline width factor is 0.3 (Regulatory Guide 1 109), the average Co-60 and Cs-137

~

concentrations detected are constant for the year and the detected quantities are a result of site operations. Whole body and skin doses are as follows.

Radionuclide Concentration << Whole Bod Dose< Skin Dose<

Co-60. 0.06 0.0008 0.0010 Cs-137 0.36 0.0012 0.0014

~Dose in mrem

<<Average concentration in pCi/g (dry)

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 1, Shoreline Sediment Table 3 (cont'd)

The radionuclide concentrations used are 0.06 pCi/g (dry) for Co-60 and 0.36 pCi/g (dry) for Cs-137. The whole body dose from Co-60 is 0.0008 mrem per year and 0.0012 mrem per year from Cs-137 or a total whole body dose of 0.0020 mrem per year.

A whole body dose from Co-60 and Cs-137 can not be calculated for shoreline sediment samples collected at the 1987 Technical Specification location since no gamma emitting radionuclides, with the exception of naturally occurring radionuclides, were found.

A whole body dose of 0.0020 mrem per year at the Nine Mile Point location is very small and can be compared to the whole body dose from natural background radiation in the area surrounding the site. The natural background dose as a result of parameters such as cosmic radiation and naturally occurring radionuclides in the atmosphere and the ground, has been demonstrated by environmental dosimeters (TLD's) to be approximately 5.3 mrem per month or 64 mrem per year. The calculated dose of 0.0020 mrem per year as a result of Co-60 and Cs-137 in shoreline sediment is conservative in the sense that it is a high dose estimate and the shoreline area is not a beach area. Even in view of this conservatism, this dose is extremely small and is 0.00003 of the annual natural backgro'und dose of 64 mrem per year.

A. 2. Fish Table 4A, 4B P

A total of twenty-four fish samples were analyzed as a result of collections in the spring season (June July 1987) and in the fall season (October-November 1987). Collections were made utilizing gill nets at one location greater than five miles from the site (Oswego Harbor area), and at two locations in the vicinity of the lake discharges for the Nine Mile Point Unit tP1 (02), and the James A. FitzPatrick (03) generating, facilities.

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

Samples were analyzed for gamma emitters. Table 4A shows results in units of pCi/g (wet) for purposes of data evaluation. Table 4B shows results in units of pCi/kg (wet), as required by the Technical Specifications.

Analysis of the spring 1987 fish samples indicated detectable concentrations of radionuclides related to past weapons testing and natural origins (naturally occurring). Small detectable concentrations of Cs-137 were found in all fish samples (including control samples) with the exception of two samples.

Spring fish collections were comprised of three separate species and ten individual samples. The three species represented one feeding, type. Lake trout, brown trout and smallmouth bass are highly predacious and feed on significant quantities of smaller

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 2. Fish Table 4A, 4B (Cont'd) fish such as smelt, alewife, and other smaller predacious species. Because of the limited availability of species present in the catches, no bottom feeding specimens were collected in the spring samples.

Cs-137 was detected in five of the seven indicator samples and in all of the 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. Cs-137 in lake trout samples ranged from 0.026 to 0.032 pCi/g (wet) for the indicator samples. Cs-137 in control samples ranged from 0.017 to 0.022 pCi/g (wet) for lake trout. Cs-137 in brown trout samples ranged from 0.032 to 0.036 pCi/g (wet) at the indicator locations. Cs-137 in the control sample was 0.039 pCi/g (wet) (one sample collected).

K-40 was detected in all of the spring samples collected. K-40 is a naturally occurring radionuclide and is not related to power plant operations. Detectable concentrations of K-40 in the indicator samples ranged from 1.95 to 3.85 pCi/g (wet) and 3.62 to 4.02 pCi/g (wet) for the control samples. No other radionuclides were detected in the spring fish samples.

Fall fish sample collections were comprised 'of five separate species and fourteen individual samples. Six samples of lake trout, two samples of chinook salmon, three samples of walleye, one sample of smallmouth bass, and two samples of sucker were collected at a combination of two indicator sample locations (NMP and JAF) and one control sample location (Oswego Harbor area). Samples were collected by gill net in October November.

Cs-137 was detected in ten of the fourteen samples including all four of the control samples. Indicator samples showed an average Cs-137 concentration that was 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 lake trout samples at the indicator locations ranged from 0.024 to 0.032 pCi/g (wet) and 0.034 to 0.040 pCi/g (wet) at the control location. Chinook salmon samples showed Cs-137 concentrations of 0.037 pCi/g (wet) for the control sample and 0.063 pCi/g (wet) for the indicator sample (only one sample collected at both locations). Walleye samples showed a concentration of 0.030 pCi/g (wet) at the control location.

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 2. Fish Table 4A, 4B (Cont'd)

Cs-137 was not detected in the walleye samples from the indicator locations. Only one sample of smallmouth bass was available during the fall season (Nine Mile Point indicator location). The associated Cs-137 concentration was 0.036 pCi/g (wet). White sucker samples were available only't the indicator 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 oE different feeding habits and because this species is not in the same position on the food chain as the other predacious species.

K-40 was detected in all of the fall samples collected.

Detectable concentrations of K-40 in the indicator samples ranged from 2.48 to 6.19 pCi/g (wet) and 3.19 to 4.28 pCi/g (wet) for the control samples. No other radionuclides were detected in the fall fish samples.

Review oE past environmental data indicates that the mean 1985.-1986 Cs-137 concentration has decreased from 1984 sample results and 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, control and indicator mean results increased slightly.

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 Eallout, 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 Eish samples although an effect may have been detected during 1987 since both indicator and control location mean results increased slightly.

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

Lake Ontario fish are considered an important food source by many. Therefore, fish are an integral part of the human food chain. Based on the importance of Eish 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 0.033 pCi/g (wet) (annual mean result of indicator samples for 1987),

the whole body dose received would be 0.049 mrem per year. The

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 2. Fish Table 4A, 4B (Cont'd) critical organ in this case is the liver which would receive a calculated dose of 0.076 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 0.031 pCi/g (wet). The calculated Cs-.137 whole body dose is 0.046 mrem per year and the.

associated dose to the liver is 0.071 mrem per year.

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

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

'are considered backgrou'nd doses.

A. 3 Surface Water Tables 5 and 6 Surface water samples were analyzed monthly for gamma emitters (using'amma spectral analysis) during 1987. Tritium analyses were performed quarterly. Quarterly samples (i.e., analysis for tritium) were composite samples.

The analytical results for the 1987 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 1987.

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'nly two radionuclides were detected in samples from the five locations over the course of 1987. 'hese radionuclides were naturally occurring.

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III. EVALUATION OF RNVIRONMFNTAL DATA (Cont'd)

A. 3 Surface Water Tables 5 and 6 (Cont'd)

K-40 was detected intermittently in both Technical Specification required intake canal samples. The James A. Fitzpatrick inlet canal samples showed K-40 detected in ten of the twelve monthly samples and ranged from 33 to 272 pCi/liter. K-40 in the Oswego Steam Station inlet canal was detected in nine of the twelve samples and ranged from 49 to 267 pCi/liter. The Nine Mile Point Unit 1 inlet canal, Unit 2 inlet canal and the city water samples showed K-40 detected in five, nine and seven respectively, of the twelve monthly samples for each location.

For these samples, K-40 concentrations ranged from 54 to 227 pCi/liter, from 32 to 292 pCi/liter and from 85 to 292 pCi/liter respectively.

Ra-226 was detected intermittently in samples from all five locations'a-226 was detected in Eour of the twelve monthly samples from the Nine Mile Point Unit 81 inlet canal and ranged from 88 to 137 pCi/liter. The Nine Mile Point Unit 2 inlet canal showed Ra-226 detected in seven of the twelve samples and ranged from 50 to 174 pCi/liter. Samples from the FitzPatrick location showed Ra-226 in nine of the twelve monthly samples and ranged Erom 54 to 130 pCi/liter. The control sample location (Oswego ~

Steam Station) showed Ra-226 . in seven of the twelve monthly samp'les and ranged in concentrations from 76 go 127 pCi/liter. The city water samples results showed Ra-226 ~

detected in nine of the twelve monthly samples and ranged from 77 to 153 pCi/liter.

Tritium samples are quarterly samples that are a composite of the appropriate calendar months. Tritium was detected in samples taken at all five locations. One 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 210 to 320 pCi/li'ter with a mean oE 275 pCi/liter. Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 160 to 410 pCi/liter and showed a mean concentration of 322 pCi/liter.

Inlet canal samples taken at Nine Mile Point Unit 1 and Unit 2 showed tritium concentrations ranging from 210 to 390 pCi/liter and 260 to 310 pCi/liter respectively.'he annual mean concentration was 283 pCi/liter and 292 pCi/liter respectively.

The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from 140 to 270 pCi/liter with a mean of 210 pCi/liter.

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 3 Surface Water Tables 5 and 6 (Cont'd)

Review of past environmental data for Cs-137 from 1979 through 1987 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'uring 1982 at a concentration oE 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 1987 in surface water samples.

Other plant related radionuclides detected during a review period of 1979 1986 include only Co-60 'he location results showed that Co-60 was detected once in 1981 control sample (the May composite sample). This . result is suspect and, as noted above, may be a result of contamination during handling or may be instrument background. This result was 1.4 pCi/liter.

Results from the indicator location showed that Co-60 was detected. three . times during 1982 and averaged 1.9 pCi/liter.

These positive results were attributed to inlet canal'empering and instrument background. Co-60 was not detected during 1987 in surface water samples.

Tables 25 and 26 'show historical environmental sample data Eor surface water.

Previous annual mean results for tritium at the indicator sample location (Fitzpatrick inlet canal) has decreased since 1976.

Mean sample results were reviewed from 1976 through 1987 and 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 1987 was 322 pCi/liter.

Mean tritium results for the control location (Oswego Steam Station) can not be evaluated with regard to 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 efEects 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.

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

A. 3. Surface Water Tables 5 and 6 (Cont'd)

Mean annual tritium results from previous city water samples and Oswego Steam Station samples from 1976 to 1987 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 1987 have remained relatively consistent. The 1985, 1986 and 1987 annual mean tritium results for the Oswego Steam Station were 278, 373 and 210 pCi/liter respectively.

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

The impact, as expressed as a dose to man, can not be evaluated because no plant related radionuclides were detected, in surface water samples with the exception of tritium. Plant related radionuclides were not found in the optional drinking water samples either. Any impact associated with the fluctuation of tritium levels are considered to be background and are not considered to be a result of operations at the site.

B. Terrestrial Pep ram Tables 7 through 14 and 17 r'epresent the analytical results for the terrestrial samples collected for the 1987 reporting period.

Data are evaluated only from locations required by the Technical Specifications. Data from optional sample locations are not evaluated unless indicated otherwise.

1. Air Particulate Gross Beta Tables 7 and 8 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 lo'cated 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-1, R-2, R-3, and.

R-4 were collected'nd analyzed during 1987.

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

1. Air Particulate Gross Beta Tables 7 and 8 The minimum, maximum, and average gross beta results for sample locations required by the Technical Specifications are presented below.

Location << Minimum~ Maximum" Average" R-1 0.009 0.040 0.021 R-2 0.009 0.037 0.021 R-3 0.010. 0.036 0.021 R-4 0.009 0.039 0.021 R-5 (control) 0.009 0.037 0.021 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 particulat'e gross beta concentrations shows that no significant increases in concentration occurred during 1987.

In general, the trend in air particulate gross beta activity has been one of decreasing activity since 1977 (extent of the review period). The mean gross beta concentration at control locations has decreased from a level of 0.165 pCi/m in 1981 to 0.021 in 1987. 'Results from indicator air sampling locations ranged from 0.151 pCi/m in 1981 to 0.021 pCi/m in 1987. For both indicator locations and control locations, the gross beta concentration during 1977 to 1987 fluctuated with the detonation of thermonucleax. weapons. The Technical Specification indicator and control results during 1987 were 0.021 pCi/m3 and 0.021 pCi/m respectively which represented the lowest level recorded to date.

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

2. Monthl Air Particulate Com osites Table 9 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 tI

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III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd) 2 ~ Monthl Air Particulate Com osites Table 9 (Cont'd) 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 oE 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 each of the monthly composite samples from all locations required by the . Technical Specifications. Be-7 ranged from 0.048 to 0.196 pCi/m 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 0.069 to 0.169 pCi/m . K-40 was found intermittently in the monthly composite samples required by the Technical Specifications.

K-40 ranged from 0.018 to 0.054 gCi/m at the control location (R-5) and 0.015 to 0.064 pCi/m at the indicator locations.

Ra-226 ranged from 0.015 to 0.051 pCi/m at the indicator locations required by the Technical Specifications. The Technical Specification control location ranged from 0.020 to 0.031 pCi/m3.

As a result oE 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 1987.

Two fission product radionuclides were detected during 1987 at an optional sample location. The two radionuclides were detected at the G off-site air monitoring station during the month of July. The detected quantities were small and were at or near the lower limit of detection. Co-60 was detected at a concentration oE 0.0017 pCi/m . Mn-54 was detected at 0.0032 pCi/m . These two radionuclides were not detected at any of the other Technical Specification or optional sample locations including the control location.

The presence of these radionuclides is suspect and is believed to be a result of contamination of the sample rather than a result of a release from the site for several reasons. First, the sample location is at a distant location from the site.

Other monitoring locations closer to the site and in the same direction as G off-site did not reveal Mn-54 or Co-60 as would be expected if it originated from the site. Also, the release rate oE Co-60 and Mn-54 from the'ite would have had to have been significantly above what would normally be expected or what was observed due to the dispersion and'eposition factors associated with this location. Additionally, the weekly samples that make up the monthly composites were analyzed separately to determine the exact week that the

-24

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

2. Monthl Air Particulate Com osites Table 9 (Cont'd) radionuclides were detected. Meterological data for the determined period when the nuclides were detected indicated that the wind direction was toward the G off-site location for a period of less than one hour. Further, no other radionuclides, such as Cs-137, were detected in the monthly air particulate sample. If the presence of the Mn-54 and Co-60 were due to plant effluents, these other radionuclides would also be expected to be present. Therefore, it may be concluded that the presence of Mn-54 and Co-60 at the G off-site location is attributabld to contamination of the particulate filter due to improper handling.

No other naturally occurring or plant related radionuclides were detected using gamma spectral analysis during 1987.

The location, concentration range and mean, and frequency of occurrence of each radionuclide detected during 1987 at the Technical S ecification re uired locations are included below.

Radionuclide Location ~Ran e< Mean~ Fre uenc <<

Ra-226 Indicator 0.015 0.051 0.022 10/48 Ra-226 Control 0.020 0.031 0 '25 2/12 K-40 Indicator 0.015 0.064 0.041 23/48 K-40 Control 0,018 0.054 0.033 5/12 Be-7 Indicator 0.048 0.196 0.129 48/48 Be-7 Control 0.069 0.169 0.129 12/12 Mn-54<<< Indicator 0.003 0.003 1/12%'<<

54<<R Control ND ND ND C0-60<<< Indicator 0.002 0 '02 ] /] 2'A<<

Co-60<<< Control ND ND ND Results in units of pCi/m

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

<<"- Location is optional location G off-site.

ND Not detected Historically, the naturally occurring radionuclides Ra-226, K-40 and Be-7 have shown fluctuations that are representative of natural changing conditions. No significant trends were noted during 1987.

In the past,. Co-60 has fluctuated in air particulate samples as a result of previous weapons testing. Co-60 average concentrations at the indicator 'and control locations from 1977 to 1978 decreased from approximately 0.0176 to 0.0022 pCi/m .

Average concentrations decreased significantly during 1979 and 1980 when compared to 1977. These results where 0.007 to 0.0016

-25

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd) 2 ~ Monthl Air Particulate Com osites Table 9 (Cont'd) pCi/m respectively. 1981 and 1982 average Co-60 concentrations decreased to 0.0007 and 0.0006 pCi/m . Average indicator and control concentrations were approximately equal during 1977 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 pCi/m which was slightly greater than 1982 control results. As noted in previous annual reports, however, a portion of the Co-60 detected during 1983 was attributed to contamination during handling of the unused filters prior to installation. Co-60 was detected during the first quarter of 1984 and averaged 0.0008 pCi/m at the control stations and 0.0012 pCi/m at the indicator stations. However, the 1984 Co-60 positive results were a result of contamination during handling and not a result of operations at the site. 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/m at an optional air monitoring station. However, Co-60 during 1987 was a result of contamination from improper handling of the sample, and not as a result of effluents from the site.

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/m . Cs-137 average concentrations at indicator and control locations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCi/m respectively. Average concentrations during 1980 and 1981 were approximately equal at control and indicator locations. Cs-137 concentrations

'he during 1980 was approximately equal to 1979 and increased slightly in 1981 from 1979 were 0.0014 and 0.0016 pCi/m 1980 and 1981 average respectively.

The mean 1982 concentration for Cs-137 decreased to 0..0004 pCi/m . The 1983 mean Cs-137 concentration for the indicator and control composite samples were 0.0002 and 0.0002 pCi/m which was a reduction from 1982 results. Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite samples. As noted above for the average annual Co-60 results, the reduction in Cs-137 results since 1981 is attributed to nuclear decay and ecological cycling of Cs-137 initially produced by 'the 1980 Chinese weapons test. Cs-137 was not detected during 1985 in air particulate samples. Cs-137 was detected during 1986 as a result of the Chernobyl Nuclear Plant

-26

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

2. Monthl Air Particulate Com osites Table 9 (Cont'd) accident in April 1986. Mean Cs-137 concentrations for indicator and control sample locations were 0.0183 and 0.0193 pCi/m respectively. During 1987, Cs-137 was not detected.

Prior to 1984, several radionuclides were detected that were associated with the 1980 Chinese weapons test and other weapons tests prior to 1980. These radionuclides were not'etected 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, none of the radionuclides associated with the 1986 Chernobyl accident were detected in air particulate samples.

Detectable radionuclides in air particulate samples during 1987 were a result of improper handling of one of the air particulate filters. Since the contamination of this filter was not a result of effluents from the site, no assessment of the impact to man is presented here.

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

B.3. Airborne Radioiodine Tables 10 and 11 During the 1987 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 0.004 0.026 pCi/m .

-27

IIX. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B.3. Airborne Radioiodine Tables 10 and 11 (Cont'd)

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

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

During 1987, the indicator locations required by the Technical Specifications (approximate site boundary locations) showed sample results with detectable levels of I-131. Detectable levels were found at locations R-1 off-site and R-2 off-site

.only during the period of September 1-8, 1987. The levels found were 0.011 and 0.018 pCi/m . The mean was 0.014 pCi/m I-l.31 was only detected on these two occasions at the Technical Specification required locations. LLD values for I-131 during other periods ranged from 0.004 0.017 pCi/m .

During 1987, I-131 was also detecte'd at two other on-site monitoring locations that were not required by the Technical Specifications. These two locations are optional sampling locations that are not required .by the Technical Specifications and are in close proximity to the generating facilities on the eastern end of the site. Detectable levels of 0.016 and 0.061 pCi/m were found at on-site monitoring locations I and J during the week of September 1 8, 1987. I-131 was also found on a third occasion. A detectable concentration was found at the I on-site monitoring location during the week of September 21 28, 1987. The result was 0.008 pCi/m .. The mean concentration for the three occasions when I-131 was found at the on-site locations was 0.028 ,pCi/m . The two initial results found at the I and J on-site locations occurred during the same week of September 1-8, 1987 as the two results from the R-1 and R-2 off-site (approximate site boundary) locations.

I-131 at indicator locations has been detected in the past and was detected at a mean concentration of 0.33 and 0.31 pCi/m during 1976 and 1977. The average concentration decreased to 0.04 pCi/m during 1978 and was not detected during 1979. The 1980-1982 average concentrations were 0.013, 0.029, and 0.016 pCi/m3 which were reductions in . view of previous I-131 concentrations. During 1983, the mean. I-131 concentration was 0.028 pCi/m which represented a slight increase compared to

-28

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B.3. Airborne Radioiodine Tables 10 and 11 (Cont'd) 1982. For the most part, I-131 in indicator and control samples was a result of I-131 from weapons testing. A small portion of the concentrations detected may have been a result of operations at the site. The concentrations detected during 1983 at the on-site 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. As noted previously, I-131 was found at a mean concentration of 0.014 pCi/m3 during 1987 and was a result of operations at the site ~

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

The impact of the measurable concentration of I-131 at the Technical Specification indicator locations can be assessed by projecting a dose to the maximum exposed organ (thyroid) and the whole body as a result of inhalation. The maximum exposed age group is the child. Using Standard Regulatory Guide 1.109 methodology, an inhalation rate of 3700 m3 per year and the average indicator location I-131 concentration, conservative doses can be calculated. In order to be conservative and to simplify the computations, no radiological decay is assumed and the maximum exposed individual is assumed to remain at the site boundary for one week. Maximum child thyroid and whole body doses are presented below.

Sample Mean Weeks Thyroid Whole Body Locations(s) Concentration(1) Detected Dose Dose Indicator 0.014 0.004 0.000007 Control (LLD (1) Concentration in pci/m3 (2) Dose in mrem for 1987 The calculated total dose for the critical individual (child) would be 0.004 mrem to the thyroid and 0.000007 mrem to the whole body. These doses are very small and are of no significance.

B. 4. TLD (Environmental Dosimetr ) Table 12 TLD's were collected and read once per quarter during the 1987 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 and in mrem per quarterly period.

-29

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 4. TLD (Environmental Dosimetr ) Table 12 (Cont'd)

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 12B are comprised of TLD's required by the Technical Specifications and special interest TLD's not required by the Technical Specifications.

During 1987, TLD's were collected on approximately April 1, 1987, June 30, 1987, September 30, 1987 and December 30, 1987.

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, and northeast of the site at distances of 12..6 to 19.8 miles from the site.

Most of the TLDs required by the Technical Specifications during 1987 were initiated in 1985 as a result of the issue of new Technical Specifications by the NRC. Therefore, these TLDs can only be compared to 1985 1987 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 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 although a slight decrease was noted when compared to 1986. These results ranged from 4.0 to 11.4 mrem per standard month. TLD tP3 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 ft3 were approximately double the results of the other TLD's during the third and fourth guarters because of the effects from Unit 1 and the Fitzpatrick facility as. well as the startup and testing program at Unit 2.

-30

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 4. TLD Environmental Dosimetr Table 12 (Cont'd)

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 1987 were variable and ranged from 5.0 to 32.8 mrem per standard month as a r'esult of activities at, the radwaste facilities and the operating modes of the generating facilities. Results for 1987 are significantly less than the ranges of variability noted in previous years for TLD's at or near these locations. TLD's in this group ranged up to approximately six times control TLD results.

Additional on-site TLD's are located near the on-site Energy Information Center and the associated northeast shoreline.

These TLD's include numbers 18, 103, 106 and 107, TLD number 107 is a new TLD and was established in the second quarter of 1987. Therefore, no previous results for this TLD exist, although results were slightly greater than control TLD results and ranged from 5.7 to 6.7 mrem per standard month. TLD number 18 results during 1987 were fairly consistent with previous years and ranged from 5.7 to 6.2 mrem per standard month. TLD number 103 was established during the second 'quarter of 1985.

This TLD is located on the east side of the Energy Information Center. Results were consistent with the results from 1985 and ranged from 5.4 to 6.2 mrem per standard month. TLD number 106 was established during the second quarter of 1986 and is in close proximity to TLD iP107. Results for f1106 ranged from 6.0 to 6.6 mrem per standard month and were slightly less than 1986 results. TLD numbers 18, 106 and 107 (noted above) are located to the east of the Energy Information Center and to the west of the Unit 1 facility.

Site boundary TLD's are required by the Technical Specifications and are located in the approximate area of the site boundary with one in'ach 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 4.4 to 6.2 mrem per standard month. TLD numbers 75, 76, 77, 23, 85, 86, and 87 showed results that ranged up to twice the results of control TLD's. These results ranged from 4.4 to 14.3 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. TLD number 78 was

III. TDTALUATION OF RNVIRONMENTAL DATA (Cont'd)

B. 4 ~ TLD (Environmental Dosimetr ) Table 12 (Cont'd) slightly greater than the other site boundary TLD's not affected by facility reactor buildings or radwaste buildings. This TLD is located closer to the Fitzpatrick facility and is at least 500 feet within the site boundary or site property.

A net, site boundary dose can be estimated from available TLD re'suits 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 and 49. Net site boundary doses for each quarter in mrem per standard month are as follows:

guartsr Net Site Boundar Dose<

1 +0.1 2 -0.1 3 -0.3 4 +0.2 "Dose in mrem per standard month'ite 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 public may be located. These areas are near the north of'he shoreline which are in close proximity to the generating facilities and are not accessible to members of the public.

The third group of environmental TLD's are those TLD's located four to five miles from the site in each of the land based 22.5 degree meteorological sectors. These TLDs are required by the

-Technical Specifications. At this distance, TLD's are not present in eight of the sixteen meteorological sectors that are located over Lake Ontario.

Results for this group of TLD's during 1987 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 4.3 to 6.0 mrem per standard month. These results are generally consistent with control TLD results during 1987. Results for this group of TLDs were consistent with the 1985 and 1986 results. Results were also consistent with other off-site TLD results during 1987 and previous to 1987. ~

-32

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 4. TLD (Environmental Dosimetr Table 12 (Cont'd)

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, and 102.

Results ranged from 3.5 to 6.8 mrem per standard month. All the TLD results from this group were within the general variation noted for the control TLD's. Results during 1987 for TLD's established during previous years were consistent with results noted for those years.

The fifth group of TLD's include those TLD's considered as control TLD's. These TLD's are required by the Technical Specifications and include numbers 14 and 49. An optional control location is TLD number 8. Results for 1987 ranged from 4.6 to 6.6 mrem per standard month. Results from 1987 were consistent with previous years results. However, a slight increase was noted in the second quarter of 1986. This increase may have been a .result'f the Chernobyl Nuclear Plant accident and was not noted during 1987.

Review of past TLD results re uired b the Technical S ecifications show that these TLDs can be separated into four groups. These groups include site boundary TLDs in each meteorological sector (16 TLDs total), TLDs located off-site in each land based sector at a distance of 4 to 5 miles (8 TLDs total), TLDs located at special interest areas (6 TLDs total) and TLDs located at control locations (2 TLDs total) ~ As noted previously, since the present Technical Specifications became effective in 1985, these TLDs, for the most part, can only be evaluated for 1985 1987.

TLDs located at the site boundary averaged 6.2 mrem per standard month during 1985. During 1986, site boundary TLDs averaged 7.0 mrem per standard month. 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 1987, site boundary TLDs averaged 6.1 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" off-site sector TLDs averaged 6.0 mrem and 5.2 mrem per standard month. 1986 results demonstrated an increase for this group of TLDs.

-33

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 4. TLD (Environmental Dosimetr ) Table 12 (Cont'd)

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.

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 avera'ged 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 averaged 5.2 mrem per standard month and showed levels that were typical of 1985 levels.

During 1987,. all environmental TLD groups required by the Technical Specifications showed a decrease when compared to 1986 result's. The average percentage decrease was 15'I.. The smallest decrease (13%) was noted 'for. the site boundary TLDs and the off-site sector TLD located 4.5 miles from the site. The greatest decrease (17%) was noted for the control TLD group.

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

Overall, environmental TLD results for 1987 showed no significant impact from direct radiation measured outside the site boundary.

B. 5 Milk-Tables 13 and 14 Milk samples were collected from a total of six indicator locations (within 10 miles of the site) and one control location (beyond 10 miles from the site) during 1987. The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site. During 1987, there were no milk sample locations within 5.0 miles of the site. The locations that were sampled during 1987 are located from 5.5 to 9.5 miles from the site. The only sample location required by the Technical Specifications during 1987 was the control location which was located 17.0 miles to the southwest of the site

-34

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 5 Milk-Tables 13 and 14 (Cont'd)

(location (165). Sample location descriptions for all milk sample locations utilized during 1987 are listed below.

Location No. Direction From Site Distance From Site (miles) 7 ESE 5.5 16 S 5.9 50 E 8.2 55 E 9.0 60 E 9.5 4 ESE 7.8 65 SW 17.0 During 1987, 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 1987. Since I-131 was not detected during November and December of 1986, no additional samples were collected in January through March of 1987. 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.

The gamma spectral analyses of the bimonthly samples showed K-40 to be the only naturally occurring radionuclide detected in the milk samples collected during 1987. K-40 was detected in every sample analyzed and ranged in concentration from 744 pCi/liter to 1,820 pCi/liter at the indicator locations and 1,190 pCi/liter to 1,790 pCi/liter at the control location. K-40 is a naturally occurring radionuclide and is found in many of the environmental media sampled.

Cs-137 was detected a total of two times in milk samples during 1987. Cs-137 was found at low concentrations of 5.5 pCi/liter (location fP7) and 8.1 pCi/liter (location (155). Both results were found on May 4, 1987. Location F7 is 5.5 miles from the site and location fP55 is 9.0 miles from the site. Cs-137 was not detected at the control location during 1987.

The cause of the low concentration of Cs-137 found during May is a result of the 1986 Chernobyl Nuclear Plant accident. During 1986, Cs-137 was detected fifteen times and was found at both indicator and control locations. Cs-137 was not detected after September 1986 which corresponds to the end of the grazing season. A monthly questionnaire showed that there were no milk

J III. EVALUATION OF ENV1RONMENTAL DATA (Cont'd)

B. 5 Milk-Tables 13 and 14 (Cont'd) animals released for pasturing during May of 1987 at locations 117 and f555. Therefore, these animals were Eed stored feed from 1986. Animals at other locations were released Eor pasturing during May except Eor one location. In addition, information relative to other nuclear sites on the East Coast showed that Cs-137 was also detected during the first half of 1987 and, at some sites, during the entire year.

It is felt that stored feed consumed during May 1987 at locations 7 and 55 contained enough Cs-137 fallout from the 1986 Chernobyl accident that analyses showed detectable levels of Cs-137. The amount of stored feed consumed at the other locations was considerably less than at locations F7 and 855 except for one location. In addition, the greatest of the two detectable levels was found at location f155 which is 9.0 miles from the site.. In the event Cs-137 in the May milk samples was a result of activities at the site, it would seem unlikely that the greatest detected quantity would be Eound at a distance of 9.0 miles from the site. In addition, Cs-137 release levels 'from the site during April and May 1987 were normal.

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 1987 in any of the indicator or control samples. All 1987 I-131 milk sample results are reported as the lower limit of detection (LLD). The LLD results for 1987 milk samples ranged from <0.1 pCi/liter to <0.5 pCi/liter.

Evaluation of site historical milk data shows that Cs-137 has been detected in envi:ronmental milk samples at both indicator (within 10 miles) and control locations (beyond 10 mile's). 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 oE 6.8 pCi/liter and was also a result of the Chernobyl accident.

-36

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 5 Milk-Tables 13 and 14 (Cont'd)

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 1982. Cs-137 was not detected at the control location during 1983, 1984, or 1985. The absence of Cs-137 during 1983 through 1985 may be a result of a three 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 accidents Cs-137 was not detected during 1987 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 '-131 during these years is a result of intermittent weapons testing.

During 1979 1985, I-131 in milk samples at the indicator locations was not detected except during 1980. The mean result during 1980 was 3.8 pCi/li:ter 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 1987 in milk samples.

Historical data for I-131 from the control location showed that I-131 was detected during 1980 at a me'an 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 at the control location.

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

The impact as a result of Cs 137 in 1987 milk samples can be assessed by calculating conservative doses to man from the consumption of milk with detectable quantities of Cs-137. The calculated doses are a result of the Chernobyl accident. In order to calculate doses, several assumptions are made. These include: a mean Cs-137 concentration of 6.8 pCi/liter for indicator sample results, a consumption rate of 330 liters (87 gallons) per year for an infant (the maximum exposed individual),

-37

III. . EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 5 Milk-Tables 13 and 14 (Cont'd) an applicable time period of 1 month of the year (Cs-137 was not detected consistently throughout the year) and no radiolo'gical decay. Dose factors are taken from Table E-14 of Regulatory Guide'.109.

The infant whole body dose is calculated as 0.008 mrem. The infant critical organ is the liver. The dose to the liver is 0.114 mrem. These doses are- from consuming milk from the indicator locations.

The maximum organ dos'e is the liver of an infant. The maximum whole body dose, however, is to an adult. Using the same

.criteria as above, except for a new consumption rate of 310 liters (80 gallons) per year for an adult, the maximum exposed organ (liver) dose to an adult is 0.019 mrem for indicator samples. The adult whole body dose is 0.012 mrem. The adult liver dose is less than the infant dose. The adult whole body dose is greater than the infant whole body dose.

For the purpose of illustration, the significance of the above doses can be brought into perspective by comparison to background doses due to the cosmic radiation with changes in altitude. The whole body dose to an adult is 0.012 mrem as a result of consuming milk from indicator sample locations with detectable Cs-137 during 1987. A dose

~

of 0.012 mrem is equal to the increase in dose as a result of residing at a location that is 100 meter (328 feet) higher in altitude for 2.2 days. The increase in dose is for a sea level elevation. Because the dose due to cosmic radiation is greater at higher altitudes, a whole body dose from milk consumption of 0,012 mrem is equal to residing in the city of Denver, Colorado for only 2.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (NCRP Report No. 45).

An additional comparison can be made to naturally occurring K-40. K-40 has been noted in almost all environmental samples at significant levels. A 70 kilogram adult weighs approximately 154 pounds and contains approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation, consumption, etc.). The dose to the bone tissue is about 20 mrem per year as a result of internally deposited K-40 (Eisenbud). For comparison purposes, an adult bone dose can be calculated that results from the consumption of milk with an average 1987 concentration of Cs-137. Using the same criteria used for calculating the preceding doses, the adult bone dose is 0.014 mrem per year.

This calculated dose is small and is only 0.0007 of the annual bone dose received from naturally occurring K-40.

-38

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 5. Milk-Tables 13 and 14 (Cont'd)

The whole body doses calculated from the indicator samples are small. The adult and infant liver/whole body doses are well below criteria utilized by the Federal Public Health Service and Food and Drug Administration to protect the health and safety of the general population (U. S. Department of Health and Services). The guide used by these federal health agencies for Cs-137 in milk is 240,000 pCi/liter. The maximum Cs-137 concentration observed during the 1987 sampling program was 8.1 pCi/liter. The observed Cs-137 concentrations are well below the protective action criteria.

Iodine-131 was not detected in the bi-monthly milk samples analyzed for 1987. Therefore, no doses to man have been calculated because of the lack of detectable I-131.

B. 6 Land Use Census Tables 15 and 16 In accordance with the Technical Specifications, a land use census was conducted during 1987 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.

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 is also contacted.

The number of milk animals located within the ten mile radius of the site was estimated to be 1245 cows and 30 goats for the 1987 census. No new locations-were added since the 1986 census. The number of cows decreased by 8 and the number of goats increased by 20 with respect to the 1986 census. The results of the milk animal census are found on Table 15. Milk animal locations are shown on Figure 4.

A residence census was conducted during 1987 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. There are no residences in these sectors. The results of the 1987 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.

-39

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 7 Food Products -Table 17 Food product samples collected during 1987 were comprised of garden vegetables, fruit and other types of vegetation. Samples were collected from seven 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, lettuce and swiss chard which are all considered broadleaf vegetables. Other broadleaf vegetation consisted of grape leaves, pumpkin leaves, green bean leaves and cucumber leaves. In addition, non broadleaf fruits or vegetables were collected. Non broadleaf fruits or vegetables collected in 1987 consisted of tomatoes. At the control location, one sample of each 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 all broadleaf and non-broadleaf vegetation.. Broadleaf vegetation (Swiss chard, beet greens, cabbage, lettuce, pumpkin leaves, green bean leaves, cucumber leaves, squash leaves and grape leaves) showed concentrations of K-40 ranging from 1.06 pCi/g to 5.81 pCi/g (wet). Non-broadleaf fruits (tomatoes) showed concentrations of K-40 ranging from 1.84 pCi/g to 2.95 pCi/g (wet). Be-7 was found intermittently in broadleaf vegetation samples. This radionuclide ranged from 0.10 pCi/g to 1.88 pCi/g (wet). Non-broadleaf vegetation (tomatoes) show no detectable Be-7. K-40 and Be-7 are both naturally occurring radionuclides.

Cs-137 was detected in one non-broadleaf sample (tomato) from the indicator locations. The detected quantity was at the limit of detection and was 0.016 pCi/g (wet). LLD values for all samples ranged from 0.009 pCi/g to 0.020 pCi/g (wet). The detected quantity of Cs-137 was not detected in any of the broadleaf samples, as would be expected. It is likely that the quantity of Cs-137 found is a result of uptake by the tomato plant. The source of the cesium is most likely from the soil.

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. A portion of the detected quantity may be from operations at the site. Cs-137 was not detected at the control location.

No other radionuclides were detected in the 1987 samples of fruits, vegetables, or other vegetation.

-40

III. EVALUATION OF FNVIRONMENTAL DATA (Cont'd)

B. 7 Food Products -Table 17 (Cont'd)

Review of past environmental data indicates that K-40 has been consistently detected in Eood crop samples. K-40 concentrations have fluctuated from one sample to another but the annual ranges have remained relatively consistent from year to year. Be-7 has been detected occasionally during the past on leafy vegetables (1978 1982, and 1984).

-Cs-137 has been detected intermittently during the years of 1976 1986 at the indicator locations and during the years of 1980 1986 at th'e control locations (control samples were not obtained prior to 1980). Review of indicator sample results from 1976 1986 showed that Cs-137 was not detected during 1976 1978 and 1981 1984. During 1979 and 1980, Cs-137 in fruits and/or vegetables showed annual mean concentrations oE 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).

Control sample results during 1980-1986 showed Cs-137 detected only during 1980 at a concentration of 0.02 pCi/g (wet). During 1987, Cs-137 was found in a non-broadleaf fruit sample (tomato) at an optional indicator location. The detectable concentration was 0.016 pCi/g (wet). Cs-137 was not detected at the control location during 1987.

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

The impact of detectable Cs-137 in Eood 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 bono of a child, The maximum whole body dose would be to an adult. The Cs-137 concentration is 0.016 pCi/g (wet) and is conservatively assumed to be a result oE 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 0.14 mrem per year to a child's bone tissue (maximum organ dose) and 0.02 mrem per year to the whole body. The maximum whole body dose 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 0.11 mrem to the liver and 0.07 mrem to the whole body.

A maximum child organ dose of 0.14 mrem per year and adult whole body dose of 0.07 mrem per year are small when compared to doses from non man-made sources. A maximum organ dose of 0.14 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 0.07 mrem per year can be

-41

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 7 Food Products -Table 17 (Cont'd) compared to the increase in dose from increasing altitude. As one proceeds from one location to another location higher in altitude, the dose rate will increase slightly as a result of solar radiation. A whole body dose of 0.07 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 13 days.

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

B. 8 Interlaborator Com arison Pro ram-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 utilized, where applicable.

B. 9 Environmental Sam le Locations Table 19 Table 19 contains the locations of the environmental samples presented in the data tables (Section E). The locations are given in degrees and distance from the Nine Mile Point Nuclear Station Unit 2 'eactor 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.

-42

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

B. 10 Radiolo ical Environmental Monitorin Pro ram Annual

~Semmae -Table 20 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 6.9.1.d and section 6.9.1.7 of the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit, 2 respectively.

B.11 Historical Environmental Sam le Data Tables 21 40 Tables 21 40 show historical environmental sample data for critical radionuclides or radionuclides routinely detected in environmental sample media. Data show the minimum, maximum, and mean for each year evaluated. The data only consider detectable quantities and do not consider lower limit of detection quantities. Data on Tables 21 40 were obtained from previous Annual Radiological Environmental Operating Report tables.

C. Conclusion The Radiological Environmental Monitoring Program (REMP) was ~

established to detect and evaluate any possible impact to the environment surrounding the Nine Mile Point area resulting from operations at the site.

Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the general environment or to man. In addition, the data was reviewed for any possible historical trophic level bioaccumulation trends. Little or no impact could be determined resulting from radionuclide deposition considering all sources (natural, weapons testing, etc.). 'n regards to doses as a result of man-made radionuclides, a significant portion of the small doses received by a member of the public was from past nuclear weapons testing. Doses as a result of naturally occurring radionuclides, such as K-40, contributed a major portion of the total annual dose to members of the public.

Any possible impact as a result of site operations is extremely minimal when compared to the impact from natural background levels or weapons testing. It has been demonstrated that almost all environmental samples contain traces of radionuclides which are a result of weapons testing or naturally occurring sources

-43

III. EVALUATION OF ENVIRONMENTAL DATA (Cont'd)

(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 64 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 1986, the presence of fission product radionuclides was noted in several environmental sample media. These media included air particulate samples, airborne radioiodine samples and milk samples. The source of the fission product radionuclides was attributed to the April 26, 1986 accident at the Chernobyl Nuclear Plant. Samples results from 1987 showed that only two isolated cases were found where Cs-137 from the Chernobyl accident was detected. The two cases concerned milk samples obtained during May of the year. The impact of the detected quantities was insignificant.

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.

-44

DE GENERAL REFERENCE MATERIAL

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

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

3. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", December, 1975.

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

Revision 1, November 1979.

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

Environmental Radiation Measurements, NCRP Report No 50, 1976.

~

6. National Council on Radiation Protection and Measurements (NCRP), Natural Back round Radiation in the United States, NCRP Report No. 45, 1975.

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

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

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

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

9. International Commission on Radiological Protection (ICRP), Radionuclide Release into the Environment. Assessment of Doses to Man, ICRP Publication 29, 1979.

10. Ei'chholz, G. Environmental As ects of Nuclear Power, First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan, 1976.

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

12. Francis, C.W., Radiostrontium Movement in Soils and U take in Plants.

Environmental Sciences Division, Oak Ridge National Laboratory, U.S.

Department of Energy, 1978.

13. Thomas, C.W. etc al., Radioactive Fallout from Chinese Nuclear Wea ons Tes't, September 26, 1976. (BNWL-2164) Battelle, Pacific Northwest Laboratories, U.S. ERDA, 1979.

-45

D. GENERAL REFERENCE MATERIAL (Cont'd)

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

15 Glasstone, Samuel and Jordan, Walter H., Nuclear Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ill., 1980.

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

January 1970.

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

-46

E. DATA TABLES 1987

-47

TABLE 1 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM >

A. A VATIC PROGRAM MEDIA ANALYSIS FRE UENCY LOCATIONS 1

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

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

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

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

B. TERRESTRIAL PROGRAM MEDIA ANALYSIS FRE UENCY LOCATIONS

l. Air Particulates GB Weekly 4 Indicator, 1 Control GSA M. Composite

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

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

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

GSA 2/Month

5. Human Food Crops GSA, I-131 (5) Annually (4)

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

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

(4) Six samples total utilizing at least two meteorological sectors in areas of highest D/Q. One sample of each of similar food product in a least prevalent wind direction.

(5) Gamma spectral analysis to include I-131

'49

TABLE 3A CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/g (dry) + 2 sigma Sample Collection Location Date Be-7 K-40 Co-60 Cs-134 Cs-137 Ra-226 AcTh-228 Others Langs Beach 4-24-87 <0.39 14.7+1.2 <0.05 <0.04 <0.05 1.11+0.49 0.67+0.15 <LLD (Control)~ 10-23-87 <0.19 8.1+0.6 <0.01 <0.02 <0.02 0.76+0.27 0.21+0.07 <LLD Sunset Beach 4-24-87 <0.46 15.7+1.2 <0.05 <0.04 <0.05 2.16+0.58 0.93+0.17 <LLD (Off-Site) 10-23-87 <0.41 15.4+1.0 <0.04 <0.04 <0.04 1.84+0.60 0.83+0.16 <LLD Nine Mile Point 4-27-87 <0.53 12.0+1.4 <0.08 <0. 06 0.14+0.05 2.44+0.70 0.89+0.22 <LLD (On-Site)" 10-23-87 <0.39 10.6+0.9 0.06+0.03 <0.03 0.59+0.05 0.46+0.32 0.33+0.10 <LLD iii Sample not required by the Technical Specifications (Optional sample location)

Results in units of activity ~er ram dry woidht

-50

TABLE 3B CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) + 2 sigma Sample Collection Location Date Be-7 K-40 Co-60 Cs-134 Cs-137 Ra-226 AcTh-228 Others Langs Beach 4-24-87 <391 14700+1160 <49 <36 <49 1110+493 669+152 <LLD (Control)~ .10-23-87 <194 8100+586 <13 <20 <20 757+270 213+72 <LLD Sunset Beach 4-24-87 <456 15700+1150 <51 <42 <51 2160+576 927+171 <LLD (Off-Site) 10-23-87 <412 15400+1020 <40 <38 <43 1840+603 827+160 <LLD Nine Mile Point 4-27-87 <527 12000+1360 <77 <55 144+49 2440+704 886+221 <LLD (On-Site)> 10-23-87 <389 10600+868 64+25 <26 586+52 463+317 329+100 <LLD

>Sample not required by the Technical Specifications

-51

TABLE 4A CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of PCi/g (wet) + 2 sigma GAMMA EMITTERS Sam le Date Sam le T e Fe-59 Co-5& K-40 Mn-54 Co-60 Cs-134 Cs-137 Zn-65 Others OSWEGO CONTROL 00 6/25/87 Lake Trout fPl <0.066 <0.029 3.62+0.44 '<0.026 <0.021 <0.025 0.022+0.015 <0.054 (LLD 6/25/87 Lake Trout 82 <0.057 <0.026 3.87+0.42 <0.023 <0.024 <0.020 0.017+0.010 (0.042 <LLD 6/05/87 Brown Trout <0..075 (0.032 4.02+0.45 <0.024 <0.026 (0.024 0.039+0.015 <0.065 <LLD 10/06/87 Lake 'Trout 81 <0.100 <0.036 4.28+0.47 <0.025 (0.025 (0.025 0.040+0.018 (0.062 <LLD 10/06/87 Lake Trout 82 <0.065 <0.030 4.05+0.38 <0.019 (0.018 <0.020 0.034+0.011 <0.048 <LLD 11/05/87 Chinook Salmon <0.043 <0.020 4.13+0.36 <0.018 <0.021 <0.017 0.037+0.011 <0.041 <LLD 10/20/87 Walleye <0.074 <0.025 3.19+0.45 <0.023 <0.028 <0.020 0.030+0.014 <0.054 <LLD NINE MILE POINT 02 6/02/87 Lake Trout /Pl <0.063 <0.022 1.95+0.28 <0.017 <0.018 <0.016 0.026+0.010 (0.038 <LLD 6/02/87 Lake Trout tt2 <0.082 <0.026 3.80+0.42 <0.023 (0.022 <0.022 <0.027 (0.052 <LLD 7/02/87 Brown Trout <0.050 (0.024 3.69+0.44 <0.019 <0.020 <0.021 0 '36+0.016 <0.045 <LLD 7/02/87 Smallmouth Bass <0.047 (0.023 3.81+0.52 <0.018 <0.021 <0.019 0.026+0.014 <0.054 (LLD 10/14/87 Lake Trout Sl <0.050 <0.019 3.08+0.34 <0.018 <0.022 <0.017 0.032+0.013 <0.039 <LLD 10/14/87 Lake Trout 82 <0.064 <0.027 2.90+0.42 .<0.023 <0.023 <0.021 0.024+0.012 <0.052 <LLD 11/04/87 Chinook Salmon <0.079 <0.033 4.04+0.60 <CI. 029 <0.034 <0.031 0.063+0.021 <0.074 <LLD 10/07/87 Smallmouth Bass (0.093 <0.030 4.07+0.45 <0.025 <0.019 <0.022 0.036+0.014 <0.057 <LLD

.10/07/87 Walleye <0.094 <0.032 4.24+0.48 <0.022 <0.024 <0.026 <0.030 -<0.058 <LLD 10/07/87 White Sucker <0.075 <0.028 4.64+0.41 <0.021 (0.021 (0.019 <0.024 <0.047 <LLD

-52

TABLE 4A (Cont'd)

CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of PCi/kg (wet) + 2 sigma GAMMA EMITTERS Sam le Date Sam le T e Fe-59 Co-58 K-40 Mn-54 Co-60 Cs-134 Cs-137 Zn-65 Others JA FITZPATRICK 03 6/02/87 Lake Trout 81 <0.076 <0.032 3.04+0.42 <0.024 <0.024 <0.023 0.032+0.015 <0.051 <LLD 6/02/87 Lake Trout /P2 <0.076 <0.028 3.85+0.40 <0.022 <0.023 <0.022 <0.025 <0.050 <LLD 6/05/87 Brown Trout <0.081 <0.028 3.67+0.44 <0.021 <0.020 <0.022 0.032+0.014 <0.056 <LLD 10/14/&7 Lake Trout Sl <0.081 <0.028 2.48+0.39 <0.020 <0.026 <0.020 0.030+0.013 <0.055 : <LLD 10/14/87 Lake Trout 82 <0.078 <0.029 4.14+0.42 <0.021 <0.018 <0.022 0.026+0.012 <0.054 <LLD 10/20/87 Malleye <0.114 <0.053 6.19+0.58 <0.038 <0.041 <0.043 <0.043 <0.089 <LLD 10/07/87 White Sucker <0.064 <0.024 3.03+0.34 <0.017 <0.020 <0.018 <0.019 <0.040 <LLD

-53

TABLE 4B CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of PCi/kg (wet) + 2 sigma GAMMA EMITTERS Sam le Date Sam le T e Fe-59 Co-5& K-40 Mn-54 Co-60 Cs-134 Cs-137 Zn-65 Others r

OSWEGO CONTROL -00 6/25/87 Lake Trout foal <66 <29 3,620+440 <26 <21 <25 22+15 <54 <LLD 6/25/87 Lake Trout 82 <57 <26 3i&70+424 <23 <24 <20 17+10 <42 <LLD 6/05/87 Brown Trout <75 <32 4,020+44& <24 <26 <24 39+15 <65 <LLD 10/06/87 Lake Trout 1Pl <100 <36 4,280+472 <25 <25 <25 40+18 <62 <LLD 10/06/87 Lake Trout 82 65 <30 4,050+376 <19 <18 <20 34+11 <48 <LLD 11/05/87 Chinook Salmon < 43 <20 4,130+363 <18 (21 <17 37+11 <41 <LLD 10/20/87 Walleye 74 <25 3%190+449 <23 <28 <20 30+14 <54 <LLD NINE MILE POINT-02 6/02/87 Lake Trout Sl <63 <22 1%950+284 <17 <18 <16 26+10 <38 <LLD 6/02/87 Lake Trout S'2 <82 <26 3,800+421 <23 <22 <22 <27 <52 <LLD 7/02/87 Brown Trout <50 <24 3,690+442 <19 <20 <21 36+16 <45 <LLD 7/02/87 Smallmouth Bass <47 <23 3,810+522 <18 <21 <19 26+14 <54 <LLD

TABLE 4B (Cont'd)

CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of PCi/kg (wet) + 2 sigma GAMMA EMITTERS Sam le Date Sam le T e Fe-59 Co-58 K-40 Mn-54 - Co-60 Cs-134 Cs-137 Zn-65 Others NINE MILE POINT-02 (Cont'd) 10/14/87 Lake Trout 81 <50 <19 3,080+342 <18 <22 <17 32+73 <39 <LLD 10/14/87 Lake Trout <64 <27 2,900+422 <23 <23 <21 24+12 <52 <LLD 11/04/87 Salmon i'hinook

<79 <33 4,040+596 <29 <34 <31 63+21 <74 <LLD 10/07/87 Smallmouth Bass <93 <30 4,070+448 <25 <19 <22 36+14 <57 <LLD 10/07/87 Walleye <94 <32 4,240+475 <22 <24 <26 <30 <58 <LLD

'10/07/87 White Sucker <75 <28 4,640+407 <21 <21 <19 <24 <47 <LLD JA FITZPATRICK 03 6/02/87 Lake Trout 81 <76 <32 3,040+424 <24 <24 <23 32+15'25

<51 <LLD 6/02/87 Lake Trout 82 <76 <28 3,&50+403 <22 <23 <22 <50 <LLD 6/05/87 Brown Trout <81 <28 3,670+440 <21 <20 <22 32+14 <56 <LLD-10/14/87 Lake Trout 81 <81 <28 2,480+389 <20 <26 <20 30+13 <55 <LLD 10/14/87 Lake Trout 82 <78 <29 4,140+417 <21 <18 <22 2&+12 <54 <LLD 10/20/87 Walleye <ll <53 6,190+575 <38 <41 <43 <43 <89 <LLD 10/07/87 White Sucker <64 <24 3,030+337 <17 <20 <18 <19 <40 <LLD

-55

TABLE 5 CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma Station Nuclide January February March April May June 1987 OSWEGO CITY K-40 292+61 <54 <50 <60 227+52 85+42 WATER Ra-226 101+54 <114 111+65 86+43 153+60 <85 Cs-134 <4.62 73

'4.

<4.23 <4.28 <4.57 <3.05 Cs-137 <5.08 <5.25 <4.23 <4.91 <4.03 <3.07 Zr-95 <12.40 <12.70 <11.50 <12.00 <12.70 <10.10 Nb-95 <5.75 <6.33 <6.14 <5.56 <6.33 <5.03 Co-58 <5.39 <5.53 <4.77 <5.06 <5.13 <4.34 Mn-54 <5.04 <5.05 <3.95 <4.59 <4.41 <3.38 Fe-59 <11.30 <10.60 <10.60 <10.00 <12.80 <8.37 Co-60 <4.18 <5.72 <5.72 <6.06 <4,21 <4.16 Zn-65 <8.17 <10.20 <12.20 <9.94 <9.27 <6.68 I-131 <16.1 <12+7 <14.6 <13.1 <16.0 <16.8 Ba/La-140 <10.6 <14.1 <5.6 <12.6 <11.2 <9.4 NINE MILE K-40 212+42 <60 <46 <70 54+38 <60 POINT UNIT I Ra-226 137+58 98+43 <107 <117 <119 117+48 Cs-134 'INLET)

<3.37 <4.34 <4.4l <4.99 <4.65 <3.91 Cs-137 <3.50 <4.47 <4.77 <4.55 <4,91 <4.46 Zr-95 <10.00 <12.90 <11.40 <12.90 <10.60 <11.70 Nb-95 <4.29 <5,67 <5.88 <7ell <6 '2 <3.07 Co-58 <3.85 <F 00 <5.15 <5+12 <6 '3 <4.74 Mn-54 <3.48 <4.58 <4.08 <5.23 <4.73 <4.82 Fe-59 <8.20 <11.80 <9.94 <11.80 <12.60 <10.70 Co-60 <2.69 <4.52 <4.52 <5.15 <5.52 <5.88 Zn-65 <6.96 <9.59 <9.67 <9.91 <12.70 <8.61 I-131 <11.5 <12.9 <15.8 <13.0 <14.1 <13.8 Ba/La-140 <7.0 <10.8 <10.9 <15.3 <11.2 <12.2

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

-56

TABLE 5 (Continued)

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

Stati,on Nuclide January February March April May June 1987 NINE MILE K-40 252+46 <64 143+46 <48 245+51 292+59 POINT UNIT 2 Ra-226 142+68 <1 12 <124 <104 174+70 100+51 (INLET) Cs-134 <3.56 <3.76 <4.90 <3.72 <4.60 <4.48 Cs-137 <3.47 <3.59 <4.81 <3.46 <4.94 <5.00 Zr-95 "

<9.91 <9.99 <12.00 <9,60 <11:90 <12.70 Nb-95 <4.39 <4.41 <5.95 <5.30 <5. 31

~ <5.68 Co-58 <4.04 <5.32 <5.50 <5.57 <4.76 <5.11 Mn-54 <3.50 <3 '2 <S.13 <3.99 <4.30 <4.35 Fe-59 <8.53 <8. 80 ~ <11.10 <10.10 <11.10 <11.30 Co-60 <3.35 <4.94 <4.34 <4.28 <4.79 <3.64 Zn-6S <7.48 <9.90 <10.90 <9.54 <11.40 <8.93 I-131 <13 1 F <12.3 <15.5 <12.7 <14.8 <14.9 Ba/La-140 <8.9 <8.3 <12.0 <8.2 <11.4 <8.4 FITZPATRICK K-40 236+43 <64 272+54 33+32 <64 77+45 (INLET) Ra-226 130+54 <112 127+62 <118 101+47 107+69 Cs-134 <3.72 <5.23 <4.75 <4.33 <4.41 <3.84.

Cs-137 <3.56 <4.69 <4.94 <4.69 <4.98 <4.98 Zr-95 <9.31 <10.70 <13.60 <12.10 <10.20 <10.60 Nb-95 <4.77 <4.60 <5.89 <6.71 <6,43 <5.65 Co-58 <3.90 <6.12 <5.13 <4.67 <4.06 <4.14 Mn-54 <3.75 <5.79 <4.69 <4.37 <4.90 <5.46 Fe-59 <8.14 <11.60 <10.20 <12.90 <11.10 <10.10 Co-60 <3.13 <6.06 <4.50 <5.15 <5.14 <5.52 Zn-65 <6.84 <7.41. <10.60 <11.30 <9.91 <10.30 I-131 <0.29 <0.33 <0.33 <0.20 <0.47 <0.27 Ba/La-140 <6.5 <10.3 <10.7 <8.8 <11.0 <10.7 OSWEGO K-40 267+60 <54 <53 <70 115+45 49+32 STEAM Ra-226 112+62 <107 <103 <113 127+75 76+49 STATION Cs-134 <4.49 <4.11 <3.78 <3.57 <4.71 <4.24 (CONTROL) Cs-137 <4.64 <3.65 <4.76 <4.47 <4.63 <3.94 Zr-9S <12.20 <8.88 <10.30 <10.70 <11.70 <12.50 Nb-9S <6.15 <3.83 <5.64 <5.04 <5.29 <5.86 Co-58 <5.23 <5.07 <4.51 <4.59 <4.65 <4.12 Mn-54 <5,19 <4.25 <4.88 <4.88 <4.77 <4.38 Fe-59 <11.80 <8.68 <9.00 <8.88 <13.00 <8.51 Co-60 <4.18 <5.73 <6.39 <4.74 <4.63 <4.44 Zn-6S <8.64 <7.99 <8.97 <8.96 <10.20 <8.09 I-131 <0,25 <0.37 <0.31 <0.30 <0.36 <0.26 Ba/La-140 <13.0 <7.5 <14.1 <11.3 <9.0 <12.5

<-Optional sample location. Sample not required by the Technical Specifications.

<<-Sample required by the Technical Specifications.

-57

TABLE 5 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma Station Nuclide August September October November December 1987 OSWEGO CITY K-40 250+21 195+42 257+45 233+44 <46 <40 WATER Ra-226 88+26 100+74 108+48 119+52 77+40 <74 Cs-134 <1.51 <3.92 <3.24 <3.62 <3.27 <3.42 Cs-137 <1.57 <4.22 <3.33 <3.59 <3.28 <2.69 Zr-95 <4.36 <11.10 <8.43 <9:49 <7.29 <9.23 Nb-95 <2.20 <5.37 <3.81 <4.41 <4.23 <3.96 Co-58 <1.79 <4.79 <3.26 <4.16 <3.40 <3.79 Mn-54 <1.55 <4.49 <3.05 <3.13 <3.36 <3.18 Fe-59 <4. 01. <10.40 <6.44 <7.83 <6.90 <7.39 Co-60 <1.57 <3.84 <2.78 <3.04 <3.61 <3.72 Zn-65 <3.19 <8.53 <7.20 <5.74 <4.97 <6.87 I-131 <7.7 <13+1 <11.7 <10.6 <9.5 <11.5 Ba/La-140 <4.5 <9.7 <7.6 <7.6 <6.5 <8.4 NINE MILE K-40 227+39 <67 <54 <63 174+42 63+25 POINT UNIT I Ra-226 88+39 <116 <118 <115 <126

<4. 04..

<85

<2.86 (INLET) Cs-134 <2.91 <4.04 <4.78 <4.43 Cs-137 <3.16 <5.06 <4.69 <4.61 <4.41 <2.90 Zr-95 <8.50 <12.70 <11.10 <13.70 <12.10 <7.62 Nb-95 <4.62 <5.53 <7.01 <5.23 <6.37 <3.94 Co-58 <3.23 <4.94 <6.16 <4.26 <5.15 <3.68 Mn-54 <3.28 <5.37 <4.69 <5.02 <3 '1 <2.88 Fe-59 <7.58 <10.50 <9,32 <11.90 <11.60 <8.52 Co-60 <3.04 <3.54 <5.78 <5.61 <4.06 <3.07 Zn-65 <5.90, <10.40 <8.73 <8.42 <10.30 <6.97 I-131 <13.0 <13.1 <14.5 <16.8 <13.9 <11.4 Ba/La-140 <8.6 <10.5 <9.6 <12.6 <10.3 <8.8 NINE MILE K-40 32+16 52+23 <50 224+42 177+46 250+43 POINT UNIT 2 Ra-226 90+41 50+40 <100 70+46 <126 76+38 (INLET) Cs-134 <2o37 <3.24 <4.14 <3.46 <4.11 <3.44 Cs-137 <2.48 <3.11 <4.41 <3.59 <4.41 <3.30 Zr-95 <6.17 <6.65 <11.20 <9.86 <10.10 <9.57 Nb-95 <3.41 <4.40 <5.43 <4.97 <5.90 <4.38 Co-58 <2.86 <4.08 <4.47 <3:29 <4.88 <4.01 Mn-54 <2.62 <2.99 <3.81 <3.62 <4.05 <3.21 Fe-59 <6.16 <8.72 <9.36 <7,91 <11.30 <8,16 Co-60 <2.55 <3.61 <4.26 <3.73 <3.84 <3.30 Zn-65 <5.32 <7 '6 <9.00 <7.30 <9.45

<14.3

<7.42

<14.6 I-131 <10.4 <9.5 <14.4 <14.2 Ba/La-140 <7.2 <7.0 <11.0 <8.0 <11.0 <9.6

< Optional sample location. Sample not required by the Technical Specifications'58

TABLE 5 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma Station Nuclide July August September October November December 1987 FITZPATRICK K-40 233+46 253+39 263+45 258+57 196+37 54+43 (INLET) Ra-226 117+47 110+46 54+38 109+56 113+41 <112 Cs-134 <3.60 <3.06 <3.22 <4.28 <3.45 <4.54 Cs-137 <3.50 <3.29 <3.40 <4.10 <3.45 <4.69 Zr-95 <9.63 <8.08 <8.12 <11.50 <9,10 <10.90 Nb-95 <5.21 <3.92 <3.67 <5.26 <4.69 <5.34 Co-58 <3.96 <3.63 <3.62 <4.81 <4.03 <4.79 Mn-54 <4.00 <3.17 <3.29 <3.88 <3.66 <4.26 Fe-59 <9.92 <6.28 <6.78 <10.90 <9.41 <9.68 Co-60 <3.49 <3.28 <3.04 <4.06 <3.23 <4.34 Zn-6S <8.41 <7.08 <7.41 <8.03 <7.16 <10.40 I-131 <0.32 <0.28 <0.35 <0.32 <0.32 <0.44 Ba/La-140 <8.42 <5.4 <6.5 <8.6 <8.2 <14.0 OSWEGO K-40 223+43 206+36 259+59 230+51 210+40 100+33 STEAM Ra-226 ~

97+44 87+39 106+79 83+48 <103. <84 STATION Cs-134 <2.96 <3.35 <4.50 <3.82 <3.54 <2.53 (CONTROL) 's-137 Zr-95

<3.40

<8.29

<3.54 <4,10 <5.01 <3.69 <3 '1

<7.81 <12.70 <12.20 <10.10 <9.03 Nb-95 <4.04 <4.28 <5+27 <6.50 <4,55 <3.66 Co-58 <3.46 <3.46 <5.64 <5.08 <3.79 <3.57 Hn-54 <3.23 <3.47 <4.34 <4.25 <3.66 <3.02 Fe-59 <7.33 <7.70 <12.30 <9.43 <7.23 <7.72 Co-60 <3.17 <2,71 <4.47 <3.95 <3.51 <2.80 Zn-65 <6.54 <6.35 <10.10 <8 '0 <6.45 <6.08 I-131 Ba/La-140

<0.28 <0.28 <0 '5 <0.29 <0.25 <0.46

<6.0 <7.3 <9.2 <8.3 <8.5 <8.6

<<-Sample required by the Technical Specifications

-59

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

Results in units of pCi/liter + 2 sigma Station Period Date Tritium JAF INLET > First Quarter 1/2/87 3/31/87 160 + 80 Second Quarter 3/31/87 7/1/87 350 + 100 Third Quarter 7/1/87 9/30/87 410 + 80 Fourth Quarter 9/30/87 12/30/87 370 + 60 NMP-1 INLET >< First Quarter 12/31/86 3/31/87 (170 Second Quarter 3/31/87 6/30/87 210 + 70 Third Quarter 6/30/87 9/30/87 390 + 100 Fourth Quarter 9/30/87 1/4/88 250 + 100 NMP-2 INLET "~ First Quarter 12/31/86 - 3/31/87 300 w 110 Second Quarter 3/31/87 6/30/87 310 + 70 Third Quarter 6/30/87 9/30/87 300 + 70 Fourth Quarter 9/30/87 1/4/88 260 + 80 OSWEGO CITY WATER >> First Quarter 12/31/86 3/31/87 210 + 70 Second Quarter 3/31/87 .6/30/87 310 + 100 Third Quarter 6/30/87 9/30/87 260 + 80

'Fourth Quarter 9/30/87 1/4/88 320 + 80 OSWEGO STEAM First Quarter 12/31/86 3/31/87 170 + 90 STATION Second Quarter 3/31/87 6/30/87 260 + 90 (CONTROL) Third Quarter 6/30/87 . 9/30/87 270 + 90 Fourth Quarter 9/30/87 1/4/88 140 + 90 Samples required by the Technical Specifications.

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

-60

TABLE 7 NIP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES OFF SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 Sigma LOCATION MEEK END DATE R2 R4 87/91/86 8.828+8.883 8.925+8.883 8 928+8 883

~ ~ 8.818+8.883 8.823+8.883 87/81/13 8.828+8.883 8.818+8 883~ 8.823+8.883 8.815+8.983 8.919+8.883 87/81/28 8 822+8 883

~ ~ 8 825+8.883

~ 8.824+8.883 8.823+8 883

~ 8.825+8 983

~

87/81/27 8.828+8.883 8.824+8 883~ 8 819+8.883

~ 8 824+8.883

~ 8.914+8.883 87/82/83 8.832+8.884 8.838+8.884 8.838+8.884 8.827+8 884

~ 8 833+8 884

~ ~

87/82/18 8.824+8.883 8.821+8 883~ 8.822+8.883 8.823+8.883 8.825+8.883 87/82/17 8.825+8.883 8.827+8.883 8.827+8.883 8.825+8 883

~ 8.826+8.883 87/82/24 8.818+8.883 8.828+8 883~ 8.822+8 883

~ 8 821+8.883

~ 8.822+8.883 87/83/83 8.889+8 882

~ 8.811+8.883 8 818+8.882

~ 8 812+8.883

~ 8.813+8.883 87/83/18 8.825+8.883 8 823+9.883

~ 8.826+8 883

~ 8 828+8.883

~ 8.928+8.883 87/83/17 8,828+8,884 8,828+8.884 8.829+8.884 8.828+8.884 9.829+8.884 87/83/24 8.828+8.883 8.819+8.883 8.818+8.883 8.81S+8.883 8 812+8.882

~

87/83/31 8.819+8.883 8.828+8.883 8.817+8.883 8 819+8.883

~ 9 818+8.883

~

87/84/87 8 813+8 883

~ ~ 8.813+8.883 8.818+8.882 8.812+8.882 8 814+8.883

~

87/84/14 8.821+8 883

~ 8.822+8.883 8.821+8.883 8 822+9.883

~ 8.824+8.883 87/94/21 8.816+8.883 8 815+8.883

~ 8.814+8.883 8 815+8.883

~ 8.916+8.883 87/84/28 8.816+8.883 9.915+8.983 8.818+8.883 8.814+8.883 8.917+8.883 87/85/QS 8.828+8 883

~ 8.818+8.883 8 928+8.883

~ 8 821+8.883

~ 8 822+8.883

~

87/85/12 8.838+8.983 8 828+8 ~ 883

~ 8.829+8 883

~ 8.828+8.883 8.829+8.883 87/QS/19 8,815+8.883 8.816+8.883 8.818+8.883 8.816+8.883 8.819+8 883

~

87/85/26 8.813+8.882 8.811+8.882 8 814+8.883

~ 8.813+8.882 8.815+8 883

~

87/86/82 8.834+8.884 8.836+8.884 8.835+8.884 8.835+8.884 8.834+8.884 87/86/89 8.822+8.883 8 822+8.883

~ 8.821+8 883

~ 8.828+8 883

~ 8.819+8 883

~

87/86/16 8.827+8 883

~ 8.827+8.883 8.823+8.883 8.826+8.983 8.922+8.883 87/86/23 8.818+8.883 8.828+8.883 8.819+8.883 9.819+8 883

~ , 8.919+8.983 87/86/38 8.826+8.883 8 825+8.883

~ 8.838+8.883 8 826+8.983

~ 8.828+8.896 87/87/87 8.817+8 884

~ 8.815+8.884 8.817+8.984 8.815+8 884

~ 8.815+9.QQS 87/87/14 8.826+8.883 8.828+8.883 8.825+8.893 8 825+8.883

~ 8.828+8.884 87/87/22 8.819+8 883

~ 8.817+8.882 8.819+8.883 8.816+8.882 8.919+8.883 87/87/28 8.825+8.883 8.829+8 884

~ 8.826+8.883 8 828+8.884

~ 8.831+8.884 87/88/84 8 828+8.883

~ 8.818+8.983 8.817+8.883 8.828+8.883 8.814+8.883 87/88/11 8.819+8.883 8.828+8.883 8.818+8 883

~ 8.819+8.883 8.822+8.883 87/88/18 8 826+8.883

~ 8.823+8.883 8.824+8.883 8.824+8.88~ 8.825+8.883 87/88/25 8.816+8.883 8.818+8.883 8.821+8 883

~ 8.819+8 883

~ 8 917+8.883

~

87/89/81 8.816+8.882 8.816+8.883 8.817+8.883 8.817+8.883 8.914+8 882

~

87/99/88 8.817+8.883 8.817+8.883 8.828+8 883

~ 8.816+8.883 8.918+8.883 87/89/IS 8 817+8.883

~ 8.918+8.883 8 928+8.883

~ 8.816+8.983 8.816+8.883 87/89/22 9.811+8.882 8.812+8.882 8.811+8.882 8.814+8.983 8.812+8.882 87/89/29 8 822+8 883

~ ~ 8.922+8.883 8 822+8.883 8.824+8 883 8.823+8.883

'.822+8.983

~ ~

87/18/86 8 821+8 883

~ ~ 8.822+8.893 8.818+8.983 8.819+8.883 87/18/13 8.828+9.883 8.823+8.983 8.828+8.883 8.829+8 883

~ 8 819+8.883

~

87/18/28 8 848+8.884

~ 8.937+8.884 8.836+8.884 8 839+8.884

~ 8.837+8.984 87/18/27 8.824+8 883

~ 8.826+8.983 8.826+8.883 8.827+8.883 8.823+8.883 87/ll/83 8.822+9.983 8.823+8.883 8.821+8.883 8.824+8.883 8.917+8.984 87/11/18 8,828+8.893 8.832+8.883 8.829+8.883 8,828+8.883 8.826+8.883 87/11/17 8.826+8,883 8.827+9.883 8.824+8 883

~ 8 827+8.883

~ 8.827+8.883 87/11/24 8.818+8.883 8.817+8.883 8.816+8.883 8 815+8.883

~ 8.829+8.883 87/12/81 8.81S+8.882 8 816+8.882

~ 8.81S+8.882 8,815+8.882 8.812+8.882 87/12/88 8 811+8.882

~ 8 889+8,.882

~ 8.818+8.882 8.889+8.882 8 889+8 882

~ ~

87/12/15 8.819+8.882 8.817+8.882 8.816+8.882 8,816+8.882 8.817+8 882

~

87/12/22 8 '16+8.882 8.815+8.882 8.815+8.882 8 816+8.882

~ 8.814+8.882 87/12/29 8.823+8.883 9.823+8.883 8 823+8.883

~ '.824+8.883 8.823+8.883

-61

TABLE 7 '(Cont'd)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES " OFF SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 Sigma LOCATION WEEK END DATE D2 87/81/86 8 '26+8.884 8.827+8.883 8.827+8.883 8.828+8.884 87/81/13 8.822+8.884 8.822+8.883 8.828+8.883 8.819+8.883 87/81/28 8.818+8,883 8,828+8.883 8.819+8.883 8.827+8.884 87/81/27 8.828+8 '83 8.821+8.883 8 '25+8.883 8.819+8.883 87/82/83 8.82S+8.884 8.827+8.883 8.82S+8.883 8.826+8.884 87/82/18 8.822+8.883 8,818+8.883 8.828+8.883 8.825+8.883 87/82/17 8 '21+8 '83 8.825+8.883 8 '22+8.883 8.825+8 883 8.822+8 '83 8.822+8 '83

~

87/82/24 8.828+8.883 8 '24+8.883 87/83/83 8.812+8 '83 8 818+8.882 F 8.818+8 882 F 8.811+8.883 87/83/18 8.824+8.883 8 '25+8.883 8.827+8.883 8.823+8.883 87/83/17 8.825+8.884 8 '26+8.883 8.838+8.884 8.828+8.884 87/83/24 8.813+8 883 F 8.813+8,882 8.815+8.883 8.814+8 883 F 87/83/31 8.817+8.883 8.819+8.883 8.821+8.883 8.821+8.883 87/84/87 8.812+8.883 '

'13+8.883 8.813+8.882 8.814+8.883 87/84/14 8.815+8.883 8.821+8.883 8.821+8.883 8.822+8.883 87/84/21 8.811+8.882 8 '16+8.883 8.815+8.883 8.814+8.883 87/84/28 8.813+8.883 8.816+8.883 8.828+8 '83 8.812+8.883 87/85/QS 8.824+8.883 8.821+8.883 8.823+8.883 8.821+8.883 87/85/12 8.826+8.883 8.826+8.883 '8.838+8 '84 8,828+8.884 87/85/19 8.816+8.883 8.814+8 '82 8.816+8.883 Q.819+8.883 87/85/26 8.814+8.882 8 QIS+8.883

~ 8.812+8.882 8.815+8.883 87/86/82 8 '37+8.884 8.832+8.884 8.831+8.883 8.834+8.884 87/86/89 8.821+8.883 8.828+8.883 8.819+8.883 8.828+8.883 87/86/16 8.827+8.883 8.826+8.883 8.824+8.883 8.823+8.883 87/86/23 8.828+8.883 8.819+8.883 8.821+8;883 8.822+8.883 87/86/38 8.825+8.883 .8.828+8.883. 8.826+8.883 8.829+8.883~

'.816+8.884 8.812+8..884 8.814+8.884 8.816+8.884 87/87/87'7/87/14 8.826+8 '83 8.827+8.883 8.826+8.883 8.826+8.883 87/87/22 8.818+8.882 8 819+8.883 F 8.81-8+8.882 8.822+8.883 87/87/28 8 '27+8.883 8.827+8.883 8 '38+8.884 8.829+8.884 87/88/84 8.818+8.883 8 819+8.883 8.822+8.883 8.828+8.883 8.819+8 '83 8.819+8 '83 F

87/88/ll 8 '19+8.883 8.819+8.883 87/88/18 8.827+8.883 8.825+8.883 8.822+8.883 8.822+8.883 87/88/25 8.823+8 '83 8 '21+8 '83 8 '21+8.883 8.828+8.883 87/89/81 8.828+8.883 8.817+8.883 8.815+8.882 8.815+8.882 87/89/88 8.815+8 '82 8.813+8 '82 8 816+8.882 8.816+8.883 8.818+8 '83 F

87/89/15 8.828+8.883 8.828+8.883 8.816+8.883 87/89/22 8.818+8.882 8.811+8.882 8.818+8.882 8.812+8.882 87/89/29 8.824+8.883 8.821+8.883 8.824+8.883 .8.822+8.883 87/IQ/86 8.819+8.883 8.828+8.883 8.818+8.883 8.828+8.883 87/18/13 8.821+8.883 8.828+8.883 8.817+8.883 8.822+8.883 87/18/28 8.841+8.884 8.834+8.883 8.835+8.884 8.837+8.884 87/18/27 8.826+8.883 8.828+8 '83 8 '24+8.883 8.828+8.88'.822+8.883 87/11/83 8.822+8.883 8.818+8.883 8.821+8.883 87/ll/18 8.829+8.883 8.828+8.883 8.826+8.883 8.828+8.883 87/11/17 8.826+8.883 8.827+8.883 8 '26+8 '83 '.828+8.883 87/11/24 8 818+8.883 F 8 816+8.883 F 8.818+8.883 Q.QIS+8.883 87/12/81 8 '14+8.882 Q.QIS+8.882 8.816+8.882 8.813+8.882 87/12/88 8 818+8.882 F 8 889+8.882 F Q.QQS+8.882 8.888+8.882 87/12/15 8 '15+8.882 8.816+8.882 8.816+8.882 8.814+8.882 87/12/22 8 815+8.882 F 8.815+8.882 8.813+8.882 8.814+8.882 87/12/29 8 '23+8,882 8.828+8.882 8 '22+8.882 8.822+8.882

-62

TABLE 8 NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES ON SITE STATIONS GROSS BETA ACTIVITY pCi/m"3 + 2 Sigma LOCATION MEEK END OATE DI 87/81/85 ~ 823+.883 .825+.883 .825+.883 .824+.883 .824+.883 .824+.883 87/81/12 .828+.883 .821+.883 .828+.883 F 821+.883 .816+.883 .821+.883 87/81/19 .QZZ+.883 ,824'83 828+.883 819+.883 .828+.883 .819+.883

.828'83 .822'83

~ F 87/81/26 .828+.884 .818+.883 ~ 821+.883 .823+ 883 F

87/82/82 .829+.883 .831+.884 .SZ9+.883 .829+.884 .822+.883 .836+.884 87/QZ/89 .822+.883 .828+.883 .823+.883 .825+.883 ~ 822+.883 .824+.883 87/82/17 .824+.883 .826+.883 .QZ6+.884 .857+.823 .826+.884 .838+.884 87/82/23 .817+.883 .828+.883 .828+.884 .82o+.884 ~ 82'8+.884 ~ 827+.885 87/83/82 .813'82 .811+.882 ~ 811+ 882

~ ~ 812+.882 .818+.882 .815+.883 87/83/89 .825+.883 .827+.883 .822+.883 825+.883 ~ 821'83 828+.883 825+.883 .831'84

~ ~

87/83/16 ~ 827+.883 ~ 832+.884 .824+.883 ~ .GZ5+.883 87/83/23 .828+.883 .822+.883 .817+.883 F 817+.883 .816+.883 ~ 817+.883 87/83/38 .828+.883 ~ 817+.883 .818'83 F 818+.884 .818+.883 .817+.883 87/84/86 .812+.882 ~ 813'83 .814+'.883 .819+.883 .815+.883 .813+.882 87/84/13 .819+.883 F 819+.883 ~ 818'83 ~ 817+.883 F 818+.883 .815+.882 87/84/28 .828+.883 .819+.883 819+.883 .819+.883 .819+.883 .818+.883

.817+.883 .817'83

~

87/84/27 .817+.883 .816+.883 ~ 813+.883 .819+.883 87/85/84 .823+.883 .819+.883 .821+.883 .822+.883 .823+.883 .824+.883 87/85/11 .826+.883 .825+.883 .826'83 .828+.885 .822+.883 .824+.883 87/85/18 .823+.883 .822+.883 ~ 817'83 .822+.884 .819+.883 .821+.883 87/85/26 .813+.882 .812+.882 .813+.882 .811+.882 .814+.882 .Gll+.882 87/86/81 .831+.884 .824+.884 ~ 812'83 .827+.884 .831+.884 .838+.884 87/86/88 ~ 825+.883 .828+.883 ~ 823+.883 .821+.883 .822'83 ~ 823+.883 87/86/.15 ~ .827+.883 .823'83 F 888+.882 .823+.883 .816+.882 .822+.883 87/86/22 .823+.883 .823+.883 .823+.883 ~ 823+.883 .823+.883 .818+.883 87/86/29 .821+.883 .818+.883 .823+.883 .81 9+.883 '.821+.883 .821+.883 87/87/86 828+,884 .811'84 .818+.885 .817+.884 .816+.884 818+.884

.817+.882 .819'83

~ F 87/87/13 .821+.883 F 819+.883 .824+.883 ,816+.882 87/87/28 ~ 823+.883 .821+.883 .822+.883 .819+.883 .828+.883 .818+.883 87/87/27 .827+.883 ~ 826+.883 ~ 826+.883 .831'84 .829+.883 .828+.883 87/88/83 .818+.883 .818'83 F 816+.883 .817+.883 .816+.883 .815+.882 87/88/18 .821+.883 .816'83 .818+.883 F 818+.883 ~ 822+.883 .817+.882 87/88/17 ~ 827+.883 ~ 824+.883 .823'83 .825+.883 .826'83 .826+.883 87/88/24 .828+.883 .828+.883 .818+.883 .819+.883 ~ 819+.883 .828+ 883

.816'82 F

87/88/31 .818+.883 ~ 816'83 .889+.887 ~ 813+.882 ~ QI8+.883 87/89/88 .818+.882 .817+.882 .816+.883 .815+.882 .816+.882 .814+.882 87/89/14 .815+.883 .813+.883 .814+.883 F 815+.883 .816+ 883

~ .812+.882 87/89/21 .816+.882 .813+.882 .813+.882 .812+.882 .814+.882 .812+ 882

.816'83 F

87/89/28 .817+.883 .816+.883 .828+.883 .816+.883 .815+.882 87/IS/85 .825+.883 ~ 822'83 .824+.883 .822+.883 .824+.883 .822+.883 87/18/13 .821+.883 .821+.883 .818+.883 .821+.883 .818+.882 .818+.882 87/IS/19 .835+.884 ~ 837+.884 .835'84 .848+.884 .835'84 ~ 836+.884 87/18/26 .829+.883 .827+.883 .828+.883 .827+.883 .827+.883 .822+.883 87/11/82 ~ 819+.88o .819'83 .818+.883 .824+.883 .821+.883 .828+.883 87/ll/89 .835+.883 .836+.884 .831'83 .836+.884 .831+.883 .834+.883 87/11/16 .825+.883 ~ 824'83 .825+.883 ~ 824+.883 .824+.883 :824+'.883 87/II/23 ~ 819+.883 ~ 819+.883 ~ 828+.883 .819+.883 .818+.883 .818+.883 87/11/38 818+.882 819+.882 .818+.882 .817+.882 .816+ 882 .819+.882

.814+.882 .811'82 F F F 87/12/87 .889+.882 .889+.882 .811+ 882 F F 811+.882 87/12/14 ~ 814+.882 .815+.882 .818+.882 .817+.882 .815+.882 .814+.882 87/12/21 ~ QIZ+.882 .815+,882 .814+.882 .815+.882 .814+.882 .816+.882 87/12/28 ~ 821'82 .821+.883 .823+.883 .826+.884 .817+.882 .824+.883

-63

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

Results in units of 10 ~Ci/m + 2 sigma Nuclides January February March April May June 1987 Co-60 <1.4 ,<2s 7 <2.1 <1.8 <2.2 <1.6 Mn-54 <1 ~ 3 <1.7 <1.4 <1 3

~ <1.0 <0.9 Cs-134 <1.5 <ls3 <1.5 <1.1 <1.3 <1.6 Cs-137 <1.2 <1 3

~ <0.9 <1.4 <1.5 <1.4 Nb-95 <1.5 <2.1 <1.7 <ls3 <2s2 <F 1 Zr-95 <2.6 <4.2 <3.8 <3 ' <2.2 <4.6 Ce-141 <2 ' <1.9 <2 ' <2.1 <1. 9 <2.8 Ce-144 <6.5 <6.1 <6.4 <5.9 <5.7 <8.1 Ru-106 <10.5 <8.7 <15.3 <9.9 <13.1 <15.8 RQ-103 <1.5 <2.4 <2.0 <1.6 <2s2 <2.6 Be-7 93.3+16.8 132.0+23.1 131.0+21.8 157.0+21.8 162.0+24.9 188.0+27.2 K-40 53.7+19.2 <26.3 <31.6 15.2+11.3 <26.2 <36.4 La-140 <3.0 <5.8 <4.4 <3.3 <6.3 <3s2 Ra-226 <24.2 <25.9 <31.3 <21.6 <25.8 <35.4 Ig-131 <4.5 <4.9 <4.2 <8./4 <3.8 <6.4 Nuclides July August September October November December Co-60 <1.1 <1.0 <0.7 <1.6 <1.0 <1.1 Mn-54 <1.4 <1.6 <1.5 <1.3 <0.6 <0.6 Cs-134 <lsl <1.8 <1.1 <1.3 <1.3 <1.1 Cs-137 <1.2 <1.5 <1.4 <1.5 <1.4 <1.3 Nb-95 <2 ' <1.1 <1 ' <1.4 <1.8 <1.7 Zr-95 <F 1 <3.0 <3.6 <2.9 <2.8 <2.4 Ce-141 <2.1 <2.0 <2.3 <1.8 <1.7 <1.7 Ce-144 <6.2 <6.6 <5 ' <5.6 <5.0 <5.7 Ru-106 <11.1 <11.6 <12.9 <9.1 <11.7 <13 '

Ru-103 <1.5 <2.0 <1.6 <ls3 <1.4 <1.8 Be-7 154.0+19.8 151.0+23.1 91.3+17.9 133.0+19.5 73.3+17.3 73.9+14.4 K-40 35.7+17.0 <35.5 20.5+12.8 <24.7 <23.4 27.9+14.0 La-140 <3 ~ 5 <3.0 <2.7 <2 ' <4.0 <2.1 Ra-226 22.1+13.9 <26.3 <27.5 <18.8 <21s7 16.1+9.3 I-131 <5.3 <5.0 <6.5 <4.3 <3.8 <4.9

< Location required by the Technical Specifications.

-64

TABLE 9 (Continued)

CONCENTRATION OF CiAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICHLATE SAMPLES.

R-2 OFF-SITE STATIONlt'esults in units of 20 RRCi/mg 2 2 sigma Nuclides January February March April May June 1987 Co-60 (l. 4 <2.7 <1.6 <0.9 <2 ' <1.1 Mn-54 <1.4 <1.9 <1.6 <1.6 <1.6 <1.8 Cs-134 (1.3 (1.7 <1.5 <1.2 <1.6 <1.6 Cs-137 <1.4 <1.7 <1.0 <1.3 <1 ~ 7 <1.4 Nb-95 <1.6 <1.8 <3.0 <1.8 <2.0 <2.4 Zr-95 (3.5 <3.9 <4.5 <4.0 <3.6 (2.4 Ce-141 (2 2 <2.6 <2.7 <1.9 <2.5 <2.9 Ce-144 <6.5 <6.3 <7.0 <5.3 <6.9 (8.0 Ru-106 (10.6 <15.1 <16.0 <13.2 <17.2 <13.7 Ru-103 <1.7 <2.0 <2.2 <1.5 <2.0 <1.8 Be-7 101.0+16.0 122.0+22.4 136.0+25.'7 169.0+24.3 133.0+22.8 153.0+22.8 K-40 63.9+18.4 20.7+15.6 23.3+17.5 <27.8 36 '+22.4 58.3+23.5 La-140 <3.0 <5.2 <11.5 <7.2 <2.6 <5.3 Ra<<226 . 22.5+12.5 <29.8 (28.5 <22.1 ., (29.9 <31.4 I-131 <4.6 <4.7 <11. 6 <6.2 <5.9 (6.7 Nuclides July August September October November December Co-60 (1. 3 <1.5 <1.4 <1.4 <1 ~ 7 <1 2

~

Mn-54 <0.7 <2.0 <1.4 <1.6 <le2 <1.2 Cs-134 <0.9 <1.6 <1 2

~ <1 2

~ <1 e'3 <1.2 Cs-137 <1.1 <1.6 <1.4 <0.7 <1.1 (1.1 Nb-95 <1.3 <1.8 <2.6 <le3 <1.6 (1.6 Zr-95 <2.6 <3 ' <5.1 <3.8 <3.0 <3.0 Ce-141 (2.1 <2el <2e2 <1.6 <1.6 <1.6 Ce-144 (5.6 <7.1 <4.7 <4.9 <5.0 <4.8 Ru-106 <9.4 <10.9 <13.0 <8.8 <13.0 <10.3 Ru-103 (1 2 <2.0 <2.4 <1 3

~ <1.6 <1.4 Be-7 154.0+18.6 154.0+24.6 117.0+21.9 115.0+18.6 95.8+18.4 62.3+13.4 K-40 58.9+19.7 <30.5 <24.0 <17.0 <14.5 <17 ..6 La-140 (2.8 <4.4 <4.2 <2.6 <2.8 <3.9 Ra-226 15.3+11.5 <23.2 <21.9 <21.8 <23e3 18.9+13.8 I-131 <4.8 <4 ' <7.8 <4.2 <3.9 <4.8 lg' Location required by the Technical Specifications.

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-3 OFF-SITE STATION%'esults in units of 10 pCi/m + 2 sigma Nuclides January February March April May June 1987 Co-60 <1.6 <2.0 <2.0 <0.7 <0.8 <2e2 Mn-54 <1.4 <1.5 <1.9 <1.7 <1.8 <lo3 Cs-134 <1.5 <l. 7 <1e2 <1.7 <1.9 <1.4 Cs-137 <1 ~ 3 <l. 4 <1.4 <le7 <1.6 <le5 Nb-95 <2.0 <2.0 <1.4 <2ol <2.2 <2e2 Zr-95 <4.3 <3.4 <4.5 <4.0 <3,9 <4.9 Ce-141 <2 ' <2.4 <2 ' <2.6 <2.7 <3+1 Ce-144 <6.9 <7.1 <6.8 <7.4 <8.6 <8.8 Ru-106 <11.8 <14.3 <11.8 <11.1 <18.7 <14.2 RU-103 <1.8 <2.3 <1.5 <2.0 <1.9 <2+1 Be-7 102.0+17.2 127.0+23.2'33.4 143.0+23.9 171.0+24.1 135.0+21.9 170.0+24.1 K-40 50.5+21.4 <28.8 52.3+20.7 46.2+21.5 57.3+22.7 La-140 <5.1 <6.2 '2.9

<4.0 <4.1 <7.1 Ra-226 18.4+11.3 <27.8 <31.7 21.0+13.1 <34.6 <37.1 I-131 <4.6 <3.7 <4.8 <8.1 <4.6 <8.6 Nuclides July August September October November December Co-60 <1 ~ 7 <1.8 <1. 5 <0.8 <1.5 <1.4 Mn-54 <1.5 <1.8 <2.0 <0.9 <1.7 <1.3 Cs-l.34 <1+3 <1.4 <1.5 <1.6'lo2

<1.6 <i+3 Cs-137 <1.4 <1.7 <1.3 <1.6 <0.8 Nb-95 <2e3 <1.9 <2,0 <1.6 <1.3 <2.3 Zr-95 <3 ' <4.4 <4.0 <3.7 <4.1 <3 '

Ce-141 <2.1 <2.5 <2.2 <2.0 <1.9 <2.1 Ce-144 <5.7 <7.7 <6.2 <5.1 <5.5 <6.5 Ru-106 <10.8 <14.7 <15.4 <14.4 <10.5 <12.8 RQ-103 <1.9 <2.0 <1.6 <1.5 <1.6 <1.6 Be-7 158.0+20.7 148.0+21.9 110.0+22.0 128.0+19.7 66.9+14.6 48.1+13.2 K-40 38.2+18.1 53.0+22.0 <30.1 <22.1 <17 e3 ~ 29.5+14.8 La-140 <3.7 <2.3 <4.5 <4.8 <3.6 <5.6 Ra-226 <23.3 <31.6 <24.2 <22.2 <24.6 <23.8 I-131 <4.9 <5.2 <7.6 <4.0 <4.4 <4.6

" Location required by the Technical Specifications.

-66

TABLE 9 (Continued)

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

Results in units of 10 pCi/'m + 2 sigma Nuclides January February March April May June 1987 Co-60 <1. 1 <2.0 <1.2 <1.4 <2.0 <1.0 Mn-54 <1.1 <1.9 <1.6 <1.3 <1.6 <1.4 Cs-134 <1 3

~ <1.4 <1.8 <1.2 <1.6 <1.8 Cs-137 <l. 1 <1. 3 <1.9 <1 2~ <1.3 <1.3 Nb-95 <1.7 <2 ' <2.0 <1.9 <l. 7 <2.4 Zr-95 <3.8 <5.4 <4,4 <4.5 <3.6 <4.0 Ce-141 <2.1 <2.2 <2.5 <2.4 <2.0 <2.9 Ce-144 <6.6 <6.4 <7.4 <6.4 <4.8 <8.9 Ru-106 <13.7 <14.2 <12.0 <12.6 <15.4 <13.5 Ru-103 <1.6 <1.9 <2 ..0 <1.8 <2.0 <1.6 Be-7 107.0+17.1 100.0+20.3 147.0+24.2 159.0+24.0 161.0+25.2 196.0+30.2 K-40 41.2+15.9 <30.2 <17.8 38.4+18.2 <32.2 40.7+23.1 La-140 <4.4 <4.3 <3.4 <5.6 <4.6 <6.1 Ra-226 15.1+9.7 <27.7 24.7+14.9 50.9+24.5 <29.6 <34.2 I-131 <5.6 <5.4 <4.7 <7.3 <4.3 <6.0 Nuclides July August September October November December Co-60 <le3 <1.1 <2.0 <1. 8 <1.9 <1.9 Mn-54 <1.2 <1.2 <1.7 <1.3 <1.5 <1.2 Cs-134 <le2 <1 3

~ <1.4 <1.3 <1.5 <1.2 Cs-137 <1.2 <1.1 <1.5 <1 ' <1.4 <1.2 Nb-95 <2.0 <1.7 '2.6

<2.0 <1.8 <2.0 Zr-95 <3.4 <4.7 <4.6 <2.8 <4.5 <2.2 Ce-141 <2 ' <2.1 <2.4 <2.3 <2.2 <1.4 Ce-144 <5 ' <7 3~ <6.8 <6.4 <6.6 <5.6 Ru-106 <12.1 <18.6 <10.4 <10.8 <14.1 <9.6 RU-103 <1 ~ 7 <1.6 <2.3 <1 ~ 7 <1.8 <1.3 Be-7 143,0+21.6 177.0+26.3 133.0+25 .3 143.0+19.9 75.1+16.7 83.2+17.0 K-40 <2le2 <28.7 <21.0 42.3+16.9 39.2+16.7 <16.0 La-140 <6.6 <4.7 <4.8 <2.0 <3.5 <3.0 Ra-226 <24.3 <28.9 <25.9 <24.7 <29.8 <23.0 I-131 <4.3 <4.3 <10.0 <4.9 <4.3 <4.3

~ Location required by the Technical Specifications.

-67

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-5 OFF-SITE STATION (CONTROL)Jc Results in units of 10 g2Ci/mg + 2 sigma Nuclides January February March April May June 1987 Co-60 <1.8 <2. 2 <1.0 <2.0 <1. 4 <1.7 Mn-54 <1.4 <1.0 <1.7 <1.4 <1. 7 <1.4 Cs-l.34 <1.5 <1.5 <1.5 <1.2 <2.0 <1.4 Cs-137 <1.4 <1.3 <2.0 <1a2 <1.7 <1.3 Nb-95 %2 ' <2.4 <1.9 <1.8 <2.8 <1.8 Zr-95 <4.0 <3.7 <5.8 <6.2 <4.7 <3 '

Ce-141 <2e3 <2.4 <2.6 <2e2 <2.5 <3.0 Ce-144 <6.5 <6.0. <6.4 <5.5 <7.8 <5.6 Ru-106 <13a3 <11.5 <14.9 <10.4 <18.0 <14.5 Ru-103 <1 ' <1.8 <2.5 <2.0 <1.9 <2.5 Be-7 99.5+17.3 123.0023.4 140.0+23.1 168.0+26.4 169.0+27.3 154.0+27.0 K-40 54.5+19.8 <24:0 17.5+14.0 <15.3 <41.6 <23.5 La-140 <3.7 <5.4 <5.7 <6.0 <2;9 <6.1 Ra-226 20.0+10.9 <25.5 <30.7 <24.5 <29.6 <27.0 I-131 <6.0 <5.5 <4.5 <6.8 <4.3 <12.8 Nuclides July August September October November December Co-60 <1.4 <1.6 <1.5 <2.0 <1.8 <1.0 Mn-54 <1.0 <1.5 <1.6 <1.1 <1.4 <1 '

Cs-134 <1.6 <1.4 <1e7 <1.7 <1.6 <1.1 Cs-137 <1 ' <1.0 <1.6 <1.0 <1.7 <1 '

Nb-95 <2.6 <1.6 <2.3 <1.5 <2.2 <1.9 Zr-95 <4.0 <3.0 <3 ' <4.0 <3.9 <3.2 Ce-141 <2.2 <2a2 <2.6 <1.9 <2.3 <1.8 Ce-144 <7 1~ <5.4 <5.9 <5.2 <7,2 <6.1

'u-106

<12a7 <11.8 <14,2 <10.1 <13.8 <11.3 Ru-103 <1.6 <1.6 <2.3 <2.0 <2.0 <1.5 Be-7 138.0+21.8 167.0+23.1 111.0+20.6 143.0+22.1 72.0+18,1 68.6+15.1 K-40 21.6+13.7 <28.4 <17.6 <15.3 44.8+18.2 26.2+12.5 La-140 . <5.2 <3 ' <3.1 <5.8 <3.5 <3.4 Ra-226 <26.1 <26.9 30.8+18.7 <25.4 <29.2 <21.0 I-131 <5 ' <4 ' <6.0 <5.6 <3.9 <4.7

< Location required by the Technical Specifications.

-68

TABLE 9 (Continued)

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

Results in units of 10 3pCi/m + 2 sigma Nuclides January February March April May, June 1987 Co-60 <1.6 <2.4 <i+3 <le5 <1.6 <1.4 Mn-54 <1 2

~ <1 3

~ <lo3 <1.3. <1.0 <1.8 Cs-134 <0.9 <i+3 <1.6 <1 ' <1.2 <1.3 Cs-137 <1.4 <1.3 <1.2 <1.1 <1.7 <1.7 Nb-95 <2.2 <2.0 <2.2 <1.5 <1.2 <2+2 Zr-95 <1.4 <3.8 <4.5 <3.6 <3.2 <5.4 Ce-141 <2.0 <2.1 <2.0 <1.9 <2.0 <2.9 Ce-144 <5.9 <6.4 <6.0 <5.2 <6.2 <7.8 .

Ru-106 <7.4 <13.8 <13.2 <15.0 <10.4 <18.2 RU-103 <2.1 <2.0 <1.6 <1.6 <1.8 <2+1 Be-7 79.9+17.2 130.0+21.8 141.0+22.4 147.0+22.9 162.0+25.4 165.0+26.4 K-40 <14.1 <27.8 <28.1 <18.7 <34.8 46.0+23.1 La-140 <3 ' <2.7 <3.8 <3.8 <3.3 <6.0 Ra-226 <24.9 <25.2 <29.2 17.5+9.1 20.5+12.1 <36.2 I-131

~,

<4.7 <4.2 <4.4 <6.4 <4.5 '5 ~ 6 Nuclides July August September October November December Co-60 <1.2 <1.6 <1 5

~ <1.1 <1. 5 <1e2 Mn-54 <1.8 <1.4 <1.4 <1~3 <1.2 <1.0 Cs-134 <1.0 <1.6 <2,1 <1.2 <1.3 <1.1 Cs-137 <1.3 <1.4 <1.8 <1ol <1.1 <1.0 Nb-95 <1.9 <1.4 <2.4 <1.3 <1.4 <1.2 Zr-95 <3.2 <3.5 <2.9 <2.6 <3.5 <2.9 Ce-141 <1.8 <2.2 <1.8 <2.0 <2.3 <1.8 Ce-144 <5.2 <6.3 <6.7 <5.5 <5.6 <5.2 Ru-106 <15.0 <12.9 <16.9 <10.0 <12.4 <8.9 Ru-103 <1.5 <1.2 <li3 <1.4 <1.7 <1.5 Be-7 141.0+21.5 152.0+20.6 100.0+19.4 135.0+16.9 77.1+15.0 63.8+12.6 K-40 <18.9 51.6+19.7 <15e7 51.8+16.1 53.2+17.3 41.3+14.8 La-140 <2.9 <4.5 <4.2 <2 ' <1.5 <3>1 Ra-226 <24.0 16.3+10.6 <29.1 <21.0 <26.7 <21.3 I-131 <4.2 <3.5 <4.4 <4.8 <3.8 <5.4

"-Optional sample location

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G ON-SITE STATION Results in units of 10 pCi/m3 + 2 sigma Nuclides January February March April May June 1987 Co-60 <1 1

~ <1.6 <2.1 <1.7 <1.4 <2.3 Mn-54 <1.1 <2.0 <1.8 <1.5 <2.4 <1.9 Cs-134 <1.2 <1.8 <1. 7 <1.4 <1.6 <1.6 Cs-137 <1.1 <1.6 <1.4 <1.4 <1.8 <1.8 Nb-95 <1.8 <2e3 <2.2 <1.7 <1.3 <2.6 Zr-95 <3.4 <3.6 <3.0 <3.5 <3e3 <4.9 Ce-141 <2.0 <2.0 <2.4 <2.0 <2.5 <3el Ce-144 <4.6 <5.9 <6.7 <5.6 <7.5 <9.2 Ru-106 <13.1 <15.5 <18.2 <12.9 <15.7 <14.3 RQ-103 <lo7 <1.5 <1 3~ <2.1 <2 ' <2.4 Be-7 90.3+17.4 125.0+24 ' 137.0+22.7 129.0+19.8 144.0+23.3 166.0+26.3 K-40 <28.0 <27 ' <31.0 <29.3 <23.5 54.5+22.0 La-140 <2.6 <3 ' <5.9 <3 ' <2.8 <6.0 Ra-'226 <19.1 <27.7 <31.4 <21.3 <30.1 <34.9 1-1.31 <4.0 <4.4 <5.1 <6.4 <4.1 <8.4 Nuclides July August September October November December Co-60 <1.6 <1.9 <1.5 <0.6 <1.9 <1.5 Mn-54 <1.3 <1.5 <1.3 <1.5 <1.5 <1.0 Cs-134 <1.1 <1.8 <1.2 <1.1 <1.5 <1.4 Cs-137 <1 1

~ <1.4 <1.6 <1.0 <1.4 <lo2 Nb-95 <1.4 <2.2 <1.6 <1.3 <1.8 <1.5 Zr-95 <2.4 <3.5 <4.4 <2.4 <3.3 <3.8 Ce-141 <2.2 <2.9 <2.4 <2.0 <2o2 <2.2 Ce-144 <5.8 <8.3 <7 ' <6.0 <6.8 <6.3 Ru-106 <10.0 <16.1 <13.9 <12.1 <10.8 <12.2 Ru-103 <1.7 <1.7 <1.6 <1.4 <1.8 <1.4 Be-7 138.0+20.1 167.0+23.8 92.3+17.4 108.0+17.0 71.6+15.2 63.4+13.1 K-40 65.0+19.2 76.9+26.1 42.5+19.5 41.4+17.7 30.7+15.4 34.0+14.5 La-140 <3.6 <3.4 <3.7 <3 ' <4.0 <3.0 Ra-226 27.3+17.5 31.5+17.6 <29.8 <24.8 22.7+11.1 <22.2 I-131 <4.3 <5.6 <4.2 <5.2 <4.2 <4.3

<Optional sample location

-70

TABLE 9 (Continued)

CONCLNTRATION OF <rAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES H ON-SITE STATION +

Results in units of 10 r~cilm + 2 sinus Nuclides January February March April May June 1987 Co-60 <1.8 <2.5 <3el <2.1 <1.5 <1.6 Mn-54 <1.4 <2 ' <1.7 <1.2 <1.2 <2.2 Cs-134 <1. 1 <1.6 <le2 <1.7 <1.7 <2.1 Cs-137 <1. 4 <2.0 <1.7 <1.9 <1,6 <2.1 Nb-95 <2.0 <2.7 <1 3~ <2.2 <3.5 <2.6 Zr-95 <3e2 <3.6 <4.4 <4.6 <2.8 <4 '

Ce-141 <1 7

~ <2.4 <2.3 <2e2 <2.9 <2.8 Ce-144 <4.5 <7.8 <7 ' <7.4 <F 6 <10.5 Ru-106 <10.0 <17.3 <14 ' <12.6 <21.4 <18.3 Ru-103 <1.6 <2 ' <2 ' <1.4 <2.6 <2.2 Be-7 106.0+19.6 116.0+22.9 131.0+25.3 112.0+17.8 144.0+25.6 130.0+24.6 K-40 <19.0 26.5+17.7 26.8+19.8 60'.8+20.5 <41.8 <52.4 La-140 <4.2 <4.5 <3.6 <2.1 <4.4 <3.9 Ra-226 <22.0 <28.5 <32.4 <28.1 <38.2 <42.8 I-1.31 <3 ' <5.3 <4.6 .<2 ~ 7 <5.9 <7.4 Nuclides July August September October November December Co-60 <1.8 <1.4 <3 2

~ <1.2 <1.0 <1.4 Mn-54 <1.5 <1.6 <1 3

~ <1el <1 2

~ <1.2 Cs-134 <lel <1.9 <1.2 <1.5 <1.4 <1.5 Cs-137 <1.2 <1.8 <1 1

~ <0.9 <1 1

~ <1.3 Nb-95 <1.8 <2.1 <2.1 <1 ' <1.9 <1.6 Zr-95 <4.0 <4.2 <3.5 <4.0 <3.9 <4.4 Ce-141 <2.4 <2.4 <1 9

~ <1.8 <1.9 <2.1 Ce-144 <6 ' <9.0 <7.1 <4.6 <5.4 <5.6 Ru-106 <10.2 <18.1 <16.5 <8.8 <12.4 <12.8 RQ-103 <1.6 <2.0 <1.8 <1 2

~ <1.0 <1.5 Be-7 132.0+19.6 139.0+22.0 72.3+19.S 116.0+20.0 71.6+16.8 61.2+15.5 K-40 37.4+16 ' 73.2+25.5 <22.5 <9.2 <20 ' 19.3+13.5 La-140 <3.1 <4.4 <3 ' <4.0 <4.0 <9.3 Ra-226 <28.6 <34.2 <26.9 <19.4 <24.8 <23.1 I-131 <5.5 <5.2 <6.6 <4.6 <4.0 <6.0 "Optional sample location

-71

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTH Y COMPOSITES OF NMP AIR PARTICULATE SAMPLES I ON-SITE STATION Results in units of 10 g~Ci/mg + 2 sigma Nuclides January February March April May June 1987 Co-60 <1.6 <2a5 <2.0 <le7 <2.2 <1.1 Mn-54 <1.0 <1.3 <1.0 <1.8 <1.8 <1.9 Cs-134 <1.2 <2.1 <1.6 <1.3 <2.2 <1.8 Cs-137 <1.4 <1.8 <le7 <1.5 <2.0 <1.6 Nb-95 <1.3 <3.5 <2.9 <1.5 <2.9 <1 ~ 7 Zr-95 <3.0 <5.1 <5.0 <3.4 <5,0 <4.7 Ce-141 <1.7 <3.2 <2.4 <2.4 <3e3 <3.0 Ce-144 <5.3 <8.9 <7.9 <5.0 <10.5 <7.4 Ru-106 <11.4 <20.9 <16.1 <12.4 <15.6 <14.6 Ru-103 <1.0 <2.8 <2.0 <1.4 <2.7 <2.6 Be-7 82.7+16.7 108.0+24.8 105.0+22.3 145.0+24.0 140.0+24.4 151.0+22.4 K-40 <17.0 36.0+23.8 21.6+17.2 <17.7 62.6+26.8 77.8+24.9 La-140 <3 ' <4.4 <5.6 <10.3 <4 ' <2.8 Ra-226 <18.7 <35.0 <30.7 <21.6 <42.4 <35.2 I-131 <3.7 <6.5 <6,4 <8.7 .<6.8 <6 '

Nuclides July August September October November December Co-60 <1.5 <1.5 <2.5 <1.7 <1.4 <1.3 Mn-54 <1.6 <1.8 <le7 <1.0 <1.8 <1.6 Cs-134 <1.4 <1.4 <1.5 <1.1 <1.6 <1.3 Cs-137 <le2 <le7 <1.2 <0.9 <la3 <1.6 Nb-95 <le7 ,<2. 6 <1.9 <le7 <2.4 <2.3 Zr-95 <3.6 <4.2 <3.8 <2.1 <3.7 <3.8 Ce-141 <1 8

~ <3.0 <1.6 <1.6 <2 ' <2.4 Ce-144 <5.0 <7.4 <5.0 <5.5 <6 ' <5.5 Ru-106 <11.4 <17e2 <11.3 <12.8 <11.3 <12.0 Ru-103 <1.4 <2.5 <1.4 <1.4 <1.8 <1.8 Be-7 107.0+17.9 110.0+20.0 73.5+17.5 110.0+17.1 86.0+18.7 64.9+16.3 K-40 21.1+12.1 47.6+21.4 <28.8 10.1+9.4 18.9+13.3 24.2+15.0 La-140 <5.0 <4.8 <3 ' <2 ' <3.9 <6.9 Ra-226 <21.6 <35.3 <23.8 <21.7 <24.9 <26.8 I-131 <4.7 <5.2 <4.3 <4.2 <4.8 <7.3

"-Optional sample location.

-72

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES J ON-SITE STATION f Results in units of 10 RCi/m + 2 sigma Nuclides January February March April May June 1987 Co-60 <1.6 <1.5 <1.2 <2.5 <1.1 <1.5 Mn-54 <1.7 <2.2 <2.0 <1.3 <1.4 <1.5 Cs-134 <1.4 <1.6 <1.4 <1.2 <1.7 <1.6 Cs-137 <1.7 <1.7 <1.3 <lel <F 1 <1.8 Nb-95 <1.9 <2e7 <2el <2.0 <1.7 <2.2 Zr-95 <2.4 <4.7 <4.3 <2.9 <2e7 <4.6 Ce-141 <1.9 <2.5 <2.0 <2.0 <1.8 <2.4 Ce-144 <6.3 <7.1 <6.6 <5.0 <6.3 <6.6 Ru-106 <15.2 <18.2 <12.5 <8.7 <16.0 <13.0 Ru-103 <1.8 <2.1 <1.8 <1.8 <1.7 <2.3 Be-7 90.6+18,4 85.1+19.3 121.0+23.4 150.0+25.7 138.0+23.7 175.0+28.0 K-40 <28 ' <27.8 30.0+19.8 <30.4 <23.9 <34.4 La-140 <3 ' <F 1 <3.6 <6.8 <3.2 <8.6 Ra-226 <25.5 <27.8 <29.3 <23.9 <26.0 <26.5 I-131 <F 1 <4.9 <5.4 <6.4 <4.4 <7.7 Nuclides July August September October November December Co-60 <1.4 <1.4 <1.5 <1.2 <1.8 <le3 Mn-54 <le3 <1.5 <1.6 <1.7 <1.5 <1.6 Cs-134 <1. 2 <1.6 <1.5 *<1 2

~ <1 3

~ <1.0 Cs-137 <1.0 <1.4 <1.8 <1.4 <1.5 <F 1 Nb-95 <1 ' <2.2 <1.8 <1.8 <2.3 <1 7

~

Zr-95 <2.3 <4.0 <3.7 <3.8 <4.5 <3.4 Ce-141 <1.9 <2.2 <2.0 <1.7 <2.0 <2.4 Ce-144 <5.6 <6.1 <5.7 <4.2 <5.7 <5.4 Ru-106 <10.3 <12.5 <9.7 <7.5 <14.7 <15.4 Ru-1.03 <1.3 <1.5 <1.9 <1.4 <1.6 <1 ~ 7 Be-7 146.0+18.9 148.0+22.4 76.5+17.8 107.0+18.0 69.7+17.0 59.8+13.7 K-40 57.9+18.3 42.8+17.8 <22.8 <19.7 <22.6 53.3+16.9 La-140 <4.9 <3.8 <3 ' <2.7 <4.8 <2.6 Ra-226 <22.6 <31.3 <25.9 <19.2 <29.1 <24.5 I-131 <4.9 <4.7 <4.7 <4.2 <4.3 <5.1 lp'-Optional sample location

-73

TABLE 9 (Continued)

CONCENTRATlON OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES s

K ON-SITE STATION in units of 10 ggoi/mg4'esults

+ 2 sigma Nuclides January February March April May June 1987 Co-60 <0.5 <1.7" <2.4 <1.4 <0.9 "<2.1 Mn-54 <1.4 <1.8 <0.8 <1.4 <1.2 <1.9 CG-134 <1.5 <1. 9 <1.6 <1.2 <1.8 <1 2

~

Cs-137 <1.1 <1 5

~ <1.8 <1.6 <1.1 <1.4 Nb-95 <2.0 <2.0 <1.0 <2.0 <1.6 <2.0 Zr-95 <4.5 <3.4 <3.5 <4.6 <3.8 <5.0 Ce-141 <2el <2 ' <2.2 <2 ' <2.0 <2 '

Ce-144 <6 ' <6.5 <6.4 <4.9 <6.4 <8.0 RU-106 <13.0 <15.6 <15.4 <12.9 <8.7 <15.5 Ru-103 <1.5 <1 3

~ <2.0 <1.4 <2.0 <2.1 Be-7 89.9+15.2 124.0+24.7 110.0+20.7 123.0+19.1 133.0+22.3 137.0+21.5 K-40 53.9+17.7 <38 ' <19.3 <15.1 <27s3 49.3+20.6 La-140 <3.9 <6.1 <3 ' <4.3 <2.6 <3.9 Ra-226 <23 ' <29.2 <25.8 ,<22. 0 <28.2 ~ 26.5+17.9 I-131 <5.5 <4.0 <5.5 <6.0 <4.5 <8.0 Nuclides July August September October November December Co-60 <F 1 <1.0 <0. 6 <1.0 <1. 7 <0.7 Mn-54 <1.7 <1.1 <1.2 <1.3 <1.5 <1.4 Cs-134 <0.8 <1.1 <lsl <ls2 <1.4 <1.3 Cs-137 <1.2 <1.3 <F 1 <1.1 <1 ~ 5 <1.3 Nb-95 <2.0 <1 1

~ <1:6 <1.7 <1 ~ 7 <1.5 Zr-95 <4.3 <1.4 <3.1 <3 ' <3.4 <4.7 Ce-141 <1.9 <1.8 <2.2 <1.6 <2.0 <2.2 Ce-144 <5.2 <5.2 <6.3 <5.0 <6.3 <6.0 Ru-106 <10.2 <12.9 <11.8 <9.0 <13.5 <13.1 Ru-103 <1.3 <1.6 <la7 <1.3 <1.9 <1.9 Be-7 109.0+18.1 125.0+22.2 <34.1 119.0+17.6 81.9+17.6 63.6+15.0 K-40 <18.0 14.7+12.4 42.6+17.9 13.4+8.9 <23.8 26.1+14.1 La-140 <3.0 <2.9 <le7 <2.7 <6.4 <4.0 Ra-226 <20.7 <23.3 <25.6 19.9+11.9 <19.8 <28.7 I-131 <4.5 <4.0 <4.6 <4.6 <3.7 <5.5

<-Optional sample location

-74

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES D2 OFF-SITE STATION in units of JL'esults 10 grani/m a 2 sigma Nuclides January February March April May June 1987 Co-60 <0.9 <2.5 <3 ' <1.1 <1 el <1.0 Mn-54 <1.1 <2.4 <le5 <2.0 <le2 <2.2 Cs-134 <1.6 <1.8 <1.8 <1.3 <1.5 <1.8 Cs-137 <1.4 <1.8 <2 ' <1.2 <la7 <2al Nb-95 <le7 <2.7 <2.0 <2.5 <2.0 <2.7 Zr-95 <3.6 <5.6 <2.9 <3.2 <3.5 <4.5 Ce-141 <2.9 <2.4 <1,9 <2 ' <1.8 <2.7 Ce-144 <7.4 <7.4 <7.0 <7.7 <5.7 <7.7 Ru-106 <13.7 <18.3 <16.9 <13.5 <17.3 <17.4 Ru-103 <2.1 <2.1 <2.0 <2.0 <1.5 <2.2 Be-7 95.8+16.6 127.0+24.6 132.0+23.6 137.0+22.4 181.0+26.4 182.0+26.9 K-40 66.8+20.6 <35.5 <39 F 7 <29.7 <33.3 <38.5 La-140 <4.0 <3.7 <3.4 <3.3 <3.2 <4.9 Ra-226 31.2+19.8 <28.6 <32.5 <27.4 <26.3 <30.0 I-131. ~

<5.9 <7 e3 <4.6 <6.8 <4.4 <8.0 Nuclides July August September October November December Co-60 <1.4 <1.5 <1.4 <1 3

~ <1.8 <0.8 Mn-S4 <1.2 <1 ' <1.1 <1.3 <0.6 <1.0 Cs-134 <1.1 <1.1 <1.4 <lel <1.3 <F 1 Cs-137 <1.2 <1.0 <1.4 <0.9 <1.3 <1.0 Nb-95 <1.5 <1 ~ 7 <1.5 <1.4 <1.2 <la3 Zr-95 <2.6 <2.8 <3al <2.4 <3 ' <3.6 Ce-141 <1.8 <2.4 <2.4 <1,5 <1.8 <F 1 Ce-144 <5.5 <6.5 <5.8 <4.3 <4.3 <5.0 Ru-106 <10.1 <13.4 <10.3 <10.8 <10.2 <9.6 Ru-103 <1 3

~ <1 ' <1.6 <1.'2 <le2 <1.4 Be-7 132.0+17.6 141.0+19.2 112.0+19.5 123.0+17.9 88.4+17.1 66.6+13.3 K-40 44.1+14.6 42.6+16.8 <19.9 <10.4 <24.1 34.0+14.5 LG-140 <2.8 <2.9 <4.2 <3.2 <2.7 <2.6 Ra-226 <22e5 <24.7 <24.7 <19.7 <20.7 15.8+12.9 I-131 <4.0 <4.1 <6.2 <3 ' <3.4 <4.1

"-Optional sample location

TABLL' (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES E OFF-SITE STATION Results in units of 10 pCi/m + 2 sigma A'uclides January February March April May June 1987 Co-60 <i+3 <1.6 <2.1 <0.9 <2.2 <1.1 Mn-54 <0.8 <1.7 <1.6 <1.2 <1.0 <2.1 Cs-134 <1 3

~ <1.2 <1.4 <1.1 <1.4 <1.5 Cs-137 <1.1 <1.7 <1.5 <1.1 <1.7 <2.2 Nb-95 <2.2 <2.8 <1.8 <1.5 <2e3 <2.5 Zr-95 <3.0 <4.4 <2.8 <2 ' <4.4 <4.4 Ce-141 <2.3 <2.9 <2.1 <1.8 <1.7 <3el Ce-144 <6.3 <6.6 <6.9 <4.7 <6.3 <7.6 RU-106 <13.6 <18.4 <11.9 <9.1 <12.3 <12-1 Ru-103 <1.6 <1.8 <2.3 <2.1 <1.6 <2.4 Be-7 97.2+16 ' 103.0+21.2 129.0+21.7 116.0+20.5 188.0+26.8 162.0+23.9 K-40 51.7+18.6 22.9+16.6 20.6+13.6 <28.6 <11.8 64.7+22.4 La-140 <4.7 <4.0 <2.7 <3.7 <3.2 <4.9 Ra-226 15.0+9.9 17.3+10.8 <26.5 <23.2 <24.8 <34.2 I-131 <5.3 ~ <7.6 <4.8 <4.6 <3.4 ~

<7.4 Nuclides July August September October November December Co-60 <0.9 <1.3 ~

<1.0 <0.8 <2.0 <1.1 Mn-54 <1.8 <1.3 <1.4 <1.4 <1 ' <1.3 Cs-134 <1.3 <1.4 <1.4 <1.2 <1 ' <0.9 Cs-137 <0.6 <1.4 <1.2 <1.1 <1.2 <1.1 Nb-95 <1.7 <2.1 <2.0 <1.1 <1.5 <F 1 Zr-95 <3.8 <3.8 <3.6 <3.3 <3 ' <2.3 Ce-141 <1.7 <2.5 <2.6 <1.8 <2.0 <1.9 Ce-144 <5.7 <6.7 <6.3 <4.8 <5.4 <4.9 Ru-106 <7.9 <12.7 <11.9 <12.7 <14.0 <8.0 Ru-103 <1.4 <1.9 <1.9 <1.3 <1.6 <1.3 Be-7 123.0+19.9 146.0+21.8 105.0+19.0 126.0+19.1 78.7+16.6 65.6+12.6 K-40 <16.1 47.5+20.1 62.8+19.1 <2 1 1 ~ 28.2+14.4 44.3+15.1 La-140 <5.8 <2.3 <7.8 <2s7 <5.4 <2.4 Ra-226 <22+3 <28.4 <25.4 <21.4 <25.9 <21+7 I-131 <3.8 <4.8 <9.5 <4.4 <4.1 <5.0

<-Optional sample location

-76

TABLE 9 (Continued)

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

Results in units of 10 gggi/m e 2 sigma Nuclides January . February March April May June 1987 Co-60 <1.4 <1.9 <1.1 <1.8 <1.6 <1.6 Mn-54 <1.4 <1.0 <0.9 <1.4 <1.7 <1.5 CG-134 <1.1 <1.6 <1.8 <1.4 <1.5 <1.4 Cs-137 <1.3 <F 1 <1.6 <1 3

~ <0.8 <1.8 Nb-95 <1.8 <1.9 <2.8 <1.6 <1 ~ 7 <2.3 Zr-95 <3.5 <5.2 <3.4 <3.6 <3.2 <4.6 Ce-141 <2.2 <2.3 <2.1 <2e3 <2.0 <2.5 Ce-144 <6.7 <7 ' <6.7 <6.1 <6.1 <8.3 Ru-106 <11.5 <17.4 <13 ' <13.7 <8.8 <11.2 Ru-103 <1.4 <1.4 <1.6 <1.9 <1.6 <2.2 Be-7 103.0+15.9 120.0+22.2 148.0+23.4 145.0+20.2 144.0+23.9 160.0+25.5 K-40 47.0+17.4 <26.7 27.7+17.3 57.0+18.7 <29.5 <45.9 La-140 <4.0 <3.2 <3.1 <4.2 <4.6 <7.0 Ra-226 26 '9+15.3 <27.0 <26.2 <23.7 <23.4 <32.8 I-131 <4.1 <6:2 <5.4 <6.1 <4.3 <7.9 Nuclides July August September October November December Co-60 <1.2 <2.3 <1.6 <1.3 <1. 7 <0.6 Mn-54 <1.4 <1.6 <1 3

~ <0.6 <1.6 <1.0 Cs-134 <1.2 <1.5 <1.5 <1.3 <1.2 <F 1 Cs-137 <0.9 <1.3 <1 2

~ <0.8 <F 1 <0 '

Nb-95 <1 ' <1 ' <1 ' <1.4 <1.8 <1e7 Zr-95 <2.6 <5.1 <4.5 <3.3 <2.3 <3.2 Ce-141 <2.2 <2.3 <2.9 <1.7 <1.8 <1.6 Ce-144 <5.' <7.4 <7.3 <4.6 <5.2 <4.8 Ru-106 <10.0 <16.9 <11.2 <10.8 <12.2 <10.7 Ru-103 <1.7 <2.0 <2.0 <1.5 <1.3 <1.4 Be-7 122.0+18.1 136.0+21.8 108.0+20.3 118.0+17.2 90.5+17.9 63.9+13.6 K-40 41.3+17.0 15.0+11.2 43.5+17.9 16.0+9.8 <25.0 29.1+13.1 La-140 <4.0 <2.6 <3.7 <3 ' <2.8 <2.9 Ra-226 <24.8 12.3+11.8 <28.3 <20.0 <22.6 <22e7 I-131 <4.6 <5.3 <10 ' <4.2 <3.4 <3e3

"-Optional sample location

-77

TABLE 9 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G OFF-SITE STATION Results in units of 10 ~Ci/m + 2 sigma Nuclides .January February March April May June 1987 Co-60 <1.6 <2 ' <1. 9 <F 1 <1.3 <1.5 Mn-54 <1.9 <1.6 <1.6 <1.5 <1.1 <1.7 Cs-134 <1.6 <1,6 <1.8 <1.5 <2.0 <1.8 Cs-137 <1.4 <1.9 <1.6 <0.7 <1.3 <1.9 Nb-95 <2.3 <2.5 <2.3 <1.4 <1.0 <2.0 Zr-95 <3 ' <4.6 <5.9 <3.8 <3.7 <4.9 Ce-141 <2.5 <2.5 <2.2 <2.0 <2.5 <3.5 Ce-144 <8.1 <6.9 <8.3 <5.9 <5.6 <8.4 Ru-106 <12.9 <16.6 <19.0 <11.0 <16.7 <15.7 Ru-103 <2.2 <2.7 <1. 6 <2.0 <1.8 <2.8 Be-7 108.0+19.0 137.0+26.0 137.0+24.7 152.0+22.8 161.0+27.6 194.0+26.8 K-40 38.5+18.6 <27.4 23.7+16.1 <25.2 <37.0 79.1+28.5 La-140 <2o2 <4.4 <3.2 <4.6 <3.8 <6.4 Ra-226. <30.5 <27.9 <33.7 <26.7 <30.8 <38.2 I-131 <6.5 <6.0 <4 ..4 <F 1 <5.7 <7.5 Nuclides July August September October November December Co-60 1.7+1.0 <1.6 <1. 5 <1.5 <1.8 <1.1 Mn-54 3 '+1 1 <1.5 <1.4 <1.2 <1.0 <0.9 Cs-134 <1.1 <1.7 <1.2 <1.4 <1.4 <1.3 Cs-137 <1 3

~ <1.3 <le3 <1.1 <1.2 <1.2 Nb-95 <1.7 <1.6 <2.6 <2 ' <1.4 <1.7 Zr-95 <3.1 <4.0 <3.6 <3.0 <3.4 <3.0 Ce-141 <2.3 <2.5 <2.8 <2.2 <2.1 <2.0 Ce-144 <6.2 <6.8 <6.6 <6.6 <6.9 <5.5 Ru-106 <11 ' <14.0 <11.9 <9.4 <13.1 <10.0 Ru-103 <2.0 <2.0 <2.4 <1.5 <1.9 <1.4 Be-7 157.0+20.8 157.0+21.3 112.0+18.8 130.0+19.5 82.0+15.2 52.5+13.0 K-40 54.0+17.5 76.6+21.8 44.1+16.5 34.0+16.4 59.2+18.7 33.4+14.7 La-140 <2.2 <5.4 <4.3 <2.2 <4.2 <2.0 Ra-226 <24.4 <27.7 17.1+11.2 <26.5 <29.2 14.4+8.9 I-131 <7.5 <6.5 <10.7 <5.0 <4.2 <4.5

"-Optional sample location

-78

TABLE NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF SITE STATIONS I-131 ACTIVITY pCi/m"3 + 2 sigma LOCATION MEEK END DATE Rl R2 R3 87/81/86 <Q,QQS <8.812 <8.889 <8.814 <8.812 87/81/13 <8 '89 <8.888 <8 888 F <8.886 <8.814 87/81/28 <8.818 <8,816 <8.815 <8.818 <8.813 87/81/27 <8 '11 <8.811 <8.815 <8.813 <8 '14 87/82/83 <8.815 <8.814 <8.813 <8.813 <8.813 87/82/18 <8.812 <8.811 <8 '11 <8.888 <8.811 87/82/17 <8.814 <8,813 <8.814 <8.888 <8.889 87/82/24 <8.812 <8.813 <8.812 <8.812 <8.818 87/83/83 <8.889 <8.811 <8.812 <8 '16 <8.818 87/83/18 <8 889 F <8.813 <8.812 <8.818 <8.813 87/83/17 <8.885 <8.813 <8.811 <8.815 <8,813 87/83/24 <8.818 <8 '12 <8 '89 <8.889 <8 '18 87/83/31 <8.818 <8 '87 <8.811 <8.814 <8.818 87/84/87 <8.815 <8.889 <8 811 <8 888 <8.812 87/84/14 <8.888 <8.887 <8 '14 F F

<8.812 <8 '14 87/84/21 <8.812 <8.812 <8.815 <8.888 <8.813 87/84/28 <8.811 <8 '89 <8.888 <8.818

'11

<8.814

'87 87/QS/85 <8.811 <8.889 <8.889 <8 <8 87/85/12 <8 812 <8 889 <8.818 <8.813 <8.812

~

'13 F

87/85/1S <8. 812 <8.889 <8 ,,<8.812 <8.813 87/85/26 <8 818

~ <8.814 <8.886 <8 '84 <8 889 F

'87/86/82 <8.816 . <8 889 <8,888 <8.818 <.8. 889

'17 F

87/86/89 <8 812 <8 <8.813 <8.889 <8,812

'15 F

87/86/16 <8.818 <8.813 <8.816 <8 <8 812 F

87/86/23 <8.814 <8.814 <8 886 <8.814 <8.813 87/86/38 <8.888 <8.889 F

<8.886 <8.818 <8 '26 87/87/87 <8.814 <8.889 <8.889 <8.812 <8 '18 87/87/14 <8.889 <8.811 <8.814 <8.812 <8 '18 87/87/22 <8 811 <8.814 <8 '18 <8 '87 <8.815

'12 '12 <8 '16 F

87/87/28 <8 <8.816 <8.814 <8 87/88/84 87/88/11 87/88/18

<8.889

<8.813

<8 818 F

<8.813

<8.818

<8.889

<8.811

<8.812

<8.813

<8

<8 'll

'12

<8.888

<8.818

<8.889

<8.887 87/88/25 <8.811 <8.889 <8.818 <8.888 <8.812 87/QS/Ql <8 '12 <8.889 <8.811 <8.888 <8.887 87/89/88 8.811+8.886 8.818+8.888 <8.889 <8.811 <8.818 87/89/15 <8.818 <8.818 <8.818 <8.813 <8.818 87/89/22 <8.885 <8.889 <8.811 <Q.QQS <8 '18 87/89/29 <8 '12 <8.'813 <8.812 <8.813 <8.813 87/18/86 <8 '11 <8 '18 <8.813 <8.888 <8.818 87/18/13 <8.888 <8.889 <8.818 <8.888 <8.889 87/18/28 <8.811 <Q.QQS <8.888 <8.811 <8.812 87/18/27 <8.889 <8.811 <8.811 <8.812 <8.813 87/11/83 <Q.QQS <8.811 <8 '11 <8,818 <8.823 87/ll/18 <8.818 <8.818 <8.889 <8.818 <8.813 87/11/17 <8.888 <8.811 <8.887 <8.886 <8.818 87/11/24 <8.888 <8.889 <8.818 <8.818 <8 '12 87/12/81 <8.88S <8.886 <8.886 <8.888 <8.888 87/IZ/88 <8.885 <8.889 <8.818 <8.888 <8.818 87/12/15 <8.889 <8.887 <8.889 <8.818 <8.888 87/12/22 <8.818 <8.886 <8 '88 <8 '88 <8.889 87/12/29 <8 '89 <8.888 <8.888 <8.889 <8.884

-79

TABLE'10 (Cont'd)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES " OFF SITE STATIONS I-131 ACTIVITY pCi/m"3 + 2 sigma LOCATION MEEK END DATE 02 87/81/86 <8.885 <8 '12 <8 '12 <8. 811 87/81/13 <8.817 <8.813 <8.888 <8.811 87/81/28 <8.816 <8.818 <8.813 <8.814 87/81/27 <8.814 <8.889 <8.812 <8.816 87/82/83 <8.814 <8.812 <8 '13 <8.822 87/82/18 <8.814 <8.813 <8.88S <8.811 87/82/17 <8.813 <8.811 <8.818 <8.813 87/82/24 <8.812 <8.818 <8.818 <8.813 87/83/83 <8.818 <8.818 <8.889 <8.813 87/83/18 <8.813 <8 '12 <8.888 <8.813 87/83/17 <8.814 <8.812 <8.818 <8.811 87/83/24 <8.811 <8.812 <8 '88 <8.814 87/83/31 <8.818 <8.814 <8.811 <8.828 87/84/87 <8 '12 <8 '18 <8 '13 <8.889 87/84/14 <8 '11 <8.816 <8 '12 <8 '12 87/84/21 <8.888 <8.811 <8 '89 <8.811 87/84/28 <8.812 <8.886 <8 '11 <8.888 87/85/85 <8 '13 <8.88S <8.888 <8.818 87/85/12 <8 '89 <8.813 <8.811 <8.812 87/85/19 <8 '13 <8.818 <8.88S <8.811 87/85/26 <8 '88 <8 '18 <8.811 <8.813 8 //86/82 <8.811 <8.818 <8.811 <8.815 87/86/89 <8,889 <8.812 <8.813 <8.814 87/86/16 <F 811 <8.814 <8.886 <8.811 87/86/23 <8 '13 <8.811 <8 '13 <8.812 87/86/38 <8.887. <8.815 <8.811 <8.812 87/87/87 <8.811 <8.811 <8.818 <8.812 87/87/14 <8.888 <8.887 <8.811 <8.813 87/87/22 <8 '89 <8.812 <8.812 <8.811 87/87/28 <F 818 <8.812 <8.814 <8.813 87/88/84 <8.88S <8.818 <F 811 <8.811 87/88/ll <8.818 <8 '13 <8.812 <8.812 87/88/18 <8.88S <8.811 <8 '89 <8.88S 87/88/25 <8.813 <8.818 <8.811 <8.811 87/8S/81 <8.818 <8 '12 <8.818 <8.887 87/8S/88 <8.888 <8.888 <8 '8S <8.811

<8.818 <8.813 <8.889 <8.811

<8 '8S 87/89/15'7/89/22

<8.887 <8.811 <8.812 87/89/29 <8.818 <8.818 <8.888 <8 811 F

87/18/86 <8.811 <F 818 <8.814 <8.813 87/18/13 87/18/28

<8 '89

<8.818

<8.889

<8 '12

<8.811

<8 '18

<8.818

<8.812 87/18/27 <8.888 <8 '88 <8.812 <8.889 87/11/83 <8.887 <8 '12 <8.811 <8.816 87/11/18 <8.886 <8 '87 <8.818 <8.818 87/11/17 <8.888 <8 '18 <8 '12 <8.888 87/11/24 <8.818 <8.88S <8.888 <8.818 87/12/81 <8.888 <8 '89 <8 '85 <8.887 87/12/88 <8.887 <8 '88 <8.884 <8.889 87/12/15 <8.888 <8.888 <8 '88 <8.887 87/12/22 <8 '88 <8.887 <8.887 <8.888 87/12/29 <8.888 <8.887 <8.884 <8.889

-80

TABLE 11 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES ON SITE STATIONS I-131 ACTIVITY pCi/m" 3 + 2 sigma LOCATION MEEK END DATE 01 87/81/85 <F 811 <8 '14 <8.889 <8.813 <8.887 <8.818 87/81/12 <8.813 <8.818 <8 '18 <8 '11 <8 '18 <8; 814 87/81/IS <8.818 <8.815 <8.811 <8 '14 <8.817 <8.887 87/81/26 <8.822 <8.813 <8.811 <8.813 <8.889 <8 '15 87/82/82 <8.811 <8.814 <8.811 <8.813 <8.816 <8.817 87/82/89 <8.813 <8.886 <8.811 <8.811 <8.813 <8.8f2 87/82/17 <8 '89 <8.812 <8.815 <8 '38 <8.828 <8.818 87/82/23 <8.818 <8.811 <8.88S <8.813 <8.818 <8.812 87/83/82 <8.889 <8.812 <8.888 <8 '11 <8.812 <8.88S 87/83/89'7/83/I6

<8.889 <8.815 <8.812 <8.818 <8.811 <8 '11

<8.818 <8.889 <8.817 <8.889 <8.886 <F 811 87/83/23 <8.813 <8.812 <8 '11 <8.817 <8.818 <8.818 87/83/38 <8.815 <8.812 <8 '11 <8 '22 <8 '89 <8.811 87/84/86 <F 818 <8.818 <8 '14 <8.814 <8.811 <8.888 87/84/13 <8.886 <8.811 <8.813 <8.811 <8 '89 <8.813 87/84/28 <8.889 <8.813 <8.812 <8 '89 <8.813 <8.887 87/84/27 <8.889 <8.813 <8.816 <8.889 <8.889 <8.885 87/85/84 <8.888 <8.811 <8.889 <8.811 <8.818 <8.889 87/85/11 <8.814 <8.888 <8.818 <8.821 <8.813 <8.889 87/85/18 <8.812 <8 '88 <8.812 <8.828 <8.887 <8.889

'87 87/85/26 <8 '18 <8.888 <8.889 <8.818 <8.887

<8.815

<8 87/86/81 <8 889

~ <8.811 <8.812 <8.889 <8.811 87/86/88 <8.812 <8.813 <8.816 <8.812 <8 818 <8.812

'13

~

87/86/15 <8 <8.813 <8.818 <8.813 <8.813 <8.811 87/86/22 <8.813 <8 '12 <8.816 <8.889 <F 811 <8.818 87/86/2S <8.818 <8.814 <8.811 %8.818 <8.888 <8.889 87/87/86 <8 '12 <8 '18 .<8.814 <8.818 <8.889 <8.812 87/87/13 <8.818 <8.812 <8.818 <8.812 <8.813 <8.81

'88 1

87/87/28 <8.818 <8.811 <8.811 <8 <8.889 <8.813 87/87/27 <8.812 <8.811 <8 '12 <8.813 <8.889 <8.818 87/88/83 <8,818 <8.812 <8.818 <8.812 <8.811 <8.81 1 87/88/18 <8.886 <8.814 <8.812 <8.813 <F 818 <8.811 87/88/17 <8.811 <8.816 <8.818 <8.814 <8.811 <8.813 87/88/24 <8.812 <8 '13 <8.813 <8 '22 <8.884 <8.888 87/88/31 <8.811 <8.811 <8.845 <8.811 <8.889 <8.886 87/89/88 <8.818 <8.812 <8.828 F 816+.889 861+. 814 <8.814 87/89/14 <8.812 <8.881 <8.818 <8.815 <5.812 <8.814 87/89/21 <8.818 <8.811 <8.888 <8.888 <8.818 <8.818 87/89/28 <8.813 <8.889 <8.813 .888+.886 <8.812 <8.888 87/18/85 <8.887 <8.888 48.818 <9.889 <8.818 <8.818 87/18/13 <8.818 <8 '87 <8.888 <8.889 <8.818 <8.818 87/18/19 <8.812 <8.889 <8.813 <8.811 <8.813 <8.813 87/18/26 <F 811 <8 '18 <8.888 <8 '18 <8.812 <8.889 87/11/82 <8.818 <8.811 <F 811 <8.887 <8.818 <8.818 87/11/89 <8.888 <8.811 <8.813 <8.814 <8.889 <8.812 87/ll/16 <8.889 <8.888 <8.811 <8.818 <8.818 <8.815 87/11/23 <F 885 <8 '12 <8.811 <8.889 <F 811 <8.88S 87/II/38 <8.818 <8 '89 <8.88S <8.8I8 <8.88S <8.818 87/12/87. <8 '86 <8.888 <8.814 <8 '89 <8.813 <8 '86 87/12/14 <8.886 <8.887 <8 '12 <8.88S <8.818 <8.884 87/12/21 <8.887 <8 '89 <8.888 <8.811 <8.818 <8.889 87/12/28 <8.888 <8 '88 <8.889 <8.817 <8.813 <8.8.18

.-81

TABLE 12A DIRECT RADIATION'MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma January April July October Location Station 1987 Through ~

Through Through Through (Direction and Number Location March June September December (Distance)(3) 3 Dl On Site 6.4+1.1 ~ 8.8+0.9 11.3+1.2 11.4+1.4 0.2 miles Q &9o 4 D2 On Site 4.6+0.3 5.6+0.6 5.7+0.5 5.8+0.5 0.4 miles 9 140 5 E On Site 5.5+0.2 5.2+0.4 6.3+0.4 6.1+0.4 0.4 miles Q 175~

6 F On Site 4.0+0.3 4.7+0.4 5.7+0.3 4.0+1.1 0.5 miles 8 2100 7 Jf G On Site 4.4+0.2 4.4+0.2 5.5+0.2 '.6+0.2 0.7 miles 8 2500 8 R-5 Off Site-Control 5.3+0.4 5.6+0.4 6.6+0.5 5.4+0.5 16.4 miles Q 42o 9 Dl Off Site 5.1+0.2 4.8+0.9 5.7+0.4 5.2+0.4 11.4 miles Q 80 10 D2 Off Site 5.0+0.2 4.8+0.2 5.2+0.4 5.0+0.4 9.0 miles Q 1174 ll 12 E Off Site F Off Site 5.1+0.3 5.0+0.6

. 4.4+0.3 4.5+0.4 5.7+0.3 5.8+0.4 5.2+0.4 5.0+0.4 7.2 7.7 miles miles Q 160 1904 Q

13 G Off Site 5.2+0.4 4.6+0.2 5.6+0.3 5.2+0.4 5.3 miles 8 2250 14> DeMass Rd., SW Oswego-Control 5.2+0.3 5.4+0.6 5.8+0.4 5.0+0.4 12.6 miles 9 226 15> Pole 66, W. Boundary-Bible Camp 4.8+0.4 ~

4.2+0.3 5.2+0.4 5.0+0.4 0.9 miles 8 2370 18> Energy Info. Center Lamp Post, SW. 5.7+0.2 5.8+0.4 6.2+0.4 5.8+0.4 0.4 miles 8 2650 19 East Boundary-JAF, Pole 9 5.4+0.6 5.2+0.5 6.0+0.4 5.2+0.2 1.3 miles Q 81 H On Site 6.2+0.5 5.8+0.4 7.0+0.4 6.4+0.5 0.8 miles Q 704 23'4 I On Site 5.5+0.5 4.9+0.4 6.2+0.5 5 F 8+0.5 . 0.8 miles Q 98o 25 J On Site 5.4+0.6 4.8+0.3 4.9+0.3 5.1+0.4 0.9 miles 9 110 26 K On Site 5.6+0.4 5.0+0.3 4.9+0.5 5.1+0.3 0.5 miles 8 1320 27 N. Fence, N. of Switchyard, JAF 9.8+2.4 13.6+3.0 16.4+3.0 18.2+4.0 0.4 miles Q 60 28 N. Light Pole, N. of Screenhouse, JAF 14.4+4.8 18.1+5.2 21.1+5.8 23.0+8.4 0.5 miles Q 68 29 N. Fence, N. of W. Side Screenhouse, JAF .30.8+5.4 32.8+6.8 31.0+8.0 31.8+9.7 0.5 mlles Q 65

TABLE 12A. (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma January April July October Location Station 19&7 Through Through Through Through (Direction and Number Location March June September December (Distance)(3) 30 N. Fence (NW) JAF 9.1+1. 8 11.6+2.0 13.6+1.6 14.6+2.6 0.4 miles 9 57o 31 N. Fence (NW) NMP-1 (1) 8.4+1.2 &.1+1.2 7.9+1.1 0.2 miles Q 276 39 N. Fence, Rad Waste, NMP-1 12.2+1.8 11.0+1.6 11.1+1.2 11.4+2.2 0.2 miles 9 292 47 N. Fence, NE, JAF 8.6+1.2 10.6+1.5 11.8+1.9 11.4+1.6 0.6 miles 9 69 49k Phoenix, NY-Control 5.0+0.2 4.6+0.2 5.4+0.2 5.1+0.6 19.8 lllileS 9 170 51 Liberty 6 Bronson Sts., E of OSS 5.8+0.3 4.7+0.2 5.4+0.2 5.8+0.5 7.4 miles Q 233 52 East 12th 6 Cayuga Sts., Osw. School 5.6+0.4 4.840.2 5.6+0.2 5.3+0.4 5.8 miles 9 227 53 Broadwell S Chestnut Sts., Fulton H.S. 5.7+0.3 4.8+0.3 6.0+0.4 5.4+0.4 13.7 miles Q 183o 54 Liberty St., 6 Co. Rte. 16, Mexico H.S. 5.6+0.6 4.8+0.2 5.3+0.3 4.6+0.4 9.3 nli les 9 115 55 Gas Substation 6 Co. Rt. 5 Pulaski 5.4+0.6 4.6+0.2 5.5+0.2 5.1+0.2 13.0 miles 9 75 56% Rt. 104 New Haven Sch. (SE Corner) 5.5+0.4 4.5w0.2 '5.8+0.6 5.1+0.3 5.3 miles Q 123 5 8'4 Co. Rt. 1A Alcan (E. of E. Entrance Rd.) 5.2+0.3 4.1+1.2 4.8+0.4 5.4+0.4 3.1 miles 9 220 5.0+0.4 5.6+0.4 5.1+0.4 0.1 illil.eS 9 5o 75k Unit 2, N. Fence, N. of Reactor Bldg. 5.9+0.4 76> Unit 2, N. Fence, N. of Change Houso 4.4+0.4 5.4+0.6 5.6+0.4 5.5+0.4 0.1 miles 9 25o 7 7'Jf Unit 2, N. Fence, N. of Pipe Bldg. 5.8+0.4 7.6+0.5 7.6+1.2 6.0+0.6 0.2 miles Q 45 78> JAF, E. of E. Old Lay Down Area 6.0+0.5 6.0+0.4 6.0+0.4 5.5+0.4 1.0 miles Q 90 79% Co. Rt. 29, Pole ft63, 0.2 mi. S. of Lake Rd. 5.0+0.3 5.4+0.2 5.5+0.4 5.2+0.2 1.1 miles 9 115 80 Co. Rt. 29, Pole it54, 0.7 mi.'. of Lake Rd. 5.0+0.3 4.6i0.2 5.4+0.2 5.0+0.2 1.4 miles Q 133

&l> Miner Rd., Pole 816, 0.5 mi. W. of Rt. 29 5.4+0.2 4.640.2 5.8+0.3 5.6+0.5 1.6 miles Q 159 82a Miner Rd., Pole ill 1/2, 1.1 mi. W. of Rt. 29 5.3+0.3 4.440.2 4.8+0.3 5.6+0.4 1.6 miles 9 181 83< Lakeview Rd., Tree, 0.45 mi. N. of Miner Rd. 5.4+0.6 5.2+0.9 5.6+0.3 5.4+0 4

~ 1.2 miles 9 200

-83

TABLE 12A (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma January April July October :

Location Station 1987 Through Through Through Through (Direction and Number Location March June September December (Distance)(3) 84" Lakeview Rd. N., Pole it6117, 200 Ft. N. of Lake Rd. 5.8+0.5 5.'8+1.0 5.6+0.4 5.6+0.5 1.1 miles Q 225 85> Unit 1, N. Fence, N. of W. Side of Screen House 13.2+2.6 12.0+3.4 12.0+1.6 14.3+2.0 0.2 miles 9 294 86> Unit 2, N. Fence, N. of W. Side of Screen House 6.8+1.0 7.3+1.6 7.0+0.6 6.4+0.9 O.l miles Q 315 87> Unit 2, N. Fence, N. of E. Side of Screen House 6.0+0.4 5.6+0.5 6.1+0.5 6.0+0.6 0.1 miles Q 341 88> Hickory Grove Rd., Pole "112, 0.6 mi.

N. of Rt. 1 6.0+1.2 4.6+0.3 5.8+0.3 5.0+0.4 4.8 miles 97 Leavitt Rd., Pole itl6, 0.4 mi. S. of Rt. 1 5.7+0.2 5.4+0.2 6.0+0.3 5.2+0.4 4.1 miles Q

Q ill 89%'0%'1" Rt. 104, Pole S'300, 150 Ft. E. of Keefe Rd. 5.4+0.4 4.8+0.3 5.5+0.4 5.0+0.3 4.2 males 9 135 Rt. 51A, Pole 859, 0.8 mi. W. of Rt. 51 5.0+0.2 4.3+0.4 5.0+0.2 4.8+0.5 4.8 miles Q 156 92" Maiden Lane Rd., Power Pole, 0.6 mi.,

S. of Rt. 104 5.4+0.2 5.1+0.3 6.0+0.4 5.6+0.3 4.4 miles Q 183 93'A Rt. 53, Pole l-l, 120 Ft. S. of 104 4.5+0.2 5.2+0.4 5.8+0.6 5.0+0.2 4.4 miles 9 205 94k Rt. 1, Pole 882, 250 ft. E. of Kocher Rd. 5.0+0.4 5.5+0.5 5.0+0.4 5.0+0.2 4.7 miles Q 223 95 J( Lakeshore Camp Site, From Alcan W.

Access Rd., Pole 821, 1.2 mi. N. of Rt. 1 4.6+0.2 4 ..690.2 5.2+0.2 4.4+0.1 4.1 miles Q 237 96% Creamery Rd., 0.3 mi. S of Middle Rd.,

Pole 1 1/2 5.5+0.6 4.630.2 5.2+0.3 5.4+0.4 3.6 miles Q 199 97)k Rt. 29, Env. Station R4, 200 Ft. N.

of Miner Rd. 5.6+0.4 3. 5+1. 2 5.7+0.2 4.8+0.2 1.8 miles Q 143 98'A Lake Rd., Pole 8145, 0.15 mi. E. of Rt. 29 6.0+0.2 4.9+0.3 6.0+0.4 6.0+0.4 1.2 miles Q 101

TABLE 12A (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month + 2 sigma January April July October Location Station 1987 Through Through Through Through (Direction and Number Location March June September December (Distance)(3) 99 NMP Rd., 0.4 miles N. of Lake Rd., Env.

Station Rl Off-Site 4.9+0.2 5.0+0.2 5.6+0.4 5.6+0.4 1.8 miles 9 88 100 Rt. 29 and Lake Rd., Env. Station R2 Off-Site 5.0+0.2 4.6+0.3 6.1+0.2 5.2+0.4 1.1 miles Q 104 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env.

Station R3 Off-Site 5.3+0.2 4.4+0.6 5.7+0.2 5.4+0.3 1.5 miles 9 132 102 EOF/Env. Lab, Oswego Co. Airport (Fulton Airport), Rt. 176, E. Driveway Lamp Post 6.8+0.5 4.8+0.3 5.8+0.3 5.8+0.2 11.9 miles 9 175 103 EIC, East Garage Rd., Lamp Post 5.8+0.2 5.4+0.4 5.5+0.4 6.2+0.4 0.4 males 9 267 104 Parkhurst Road, Pole 148 1/2-A, 0.1 mi.

S. of Lake Rd. 5.4+0.5 4.9+0.2 5.2+0.4 '5.2+0.4 1.4 miles 9 102 105 Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd. 5.4+0.3 5.0+0.2 5.8+0.3 5.0+0.4 1.4 miles 9 198 106 Shoreline Cove, E. of NMP-l, Tree on W.

Edge 6.4+0.5 6.0+0.6 6.6+0.5 6.2+0.4 0.3 miles Q 274 107 Shoreline Cove, E. of NMP-l, Tree 30 ft. South of TLD ftl06 (2) 6.5+0. 6 6.7+0.6 5.7+0.5 0.3 miles 9 272 (1) TLD lost in field.

(2) TLD not established during the quarterly period.

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

.(4) TLD deleted.

Technical Specification location.

-85

TABLE 12B DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma January April July October Location Station 1987 Through Through Through Through (Direction and Number Location March June September .December (Distance)(3) 3 Dl On Site 19.9+1.7 25. 4+1.3 34.8+1.8 33 0+2.0 F 0.2 miles 69 4 D2 On Site 14.2+0.5 16. 5+0.8 17.6+0.7 17.0+0.8 0.4 miles 140 5 E On Site 16.7+0.3 15. 3+0.6 19.3+0.6 17.8+0.6 0.4 miles 175 6 F On Site 12.3+0.5 13. 7+0.6 17.3+0.5 11.7+1.6 0.5 miles 210 7A G On Site 13.8+0.4 12. 9+0.4 16.8+0.3 13.3+0.4 0.7 miles 250o 8 R-5 Off Site-Control 15.8+0.6 16. 6+0.6 19.8+0.8 16.2+0.7 16.4 miles 42 9 Dl Off Site 15.4+0.2 14. 3+1.4 17.2+0.6 15.4+0.6 11.4 miles 80o 10 D2 Off Site 15.0+0.2 14. 5+0.4 15.5+0.5 15.1+0.5 9.0 miles 117 ll E Off Site Off Site 15.2+0.4 15.2+0.8

13. 3+0.4

13. 6+0.5 17.0+0.4 17.4+0.6 15.5+0.6 15.0+0.6 7.2 7.7 miles miles 160 190 12 F 13 G Off Site 15.6+0.5 13. 840.4 16.8+0.5 15.6+0.6 5.3 miles 225 14>. DeMass Rd, SW Oswego-Control 15.4+0.5 16. 1+0.8 17.4+0.5 15.1+0.6 12.6 miles 226~

15% Pole 66, W. Boundary-Bible Camp 14.4+0.6 12.. 2+0.4 15.8+0.6 14.0+0.6 0.9 miles 237 18" Energy Info. Center-Lamp Post, SW 17.3+0.3 17. 1+0.5 18.6+0.5 17.2+0.6 0.4 miles 265 19 East Boundary-JAF, Pole 9 16.6+1.0 15. 2+0.8 18.4+0.6 15.5+0.4 1.3 miles 81~

23~ H On Site 18.8+0.8 16. 8+0.6 21.4+0.6 18.5+0.7 0.8 miles 70

'4 I On Site 16.8+0.8 14. 4+0.6 19.0+0.8 16.8+0.8 0.8 miles 98 25 J On Site 16.6+0.9 14. 2+0.5 14.9+0.4 14.9+0.5 0.9 miles 110 26 K On Site 17.2+0.6 14. 6+0.5 15.1+0.7 14.8+0.5 0.5 miles 132 27 N. Fence, N. of Switchyard, JAF 29.6+3.6 40. 2+4.4 50.5+4.6 53.8+6.0 0.4 miles 60 28 N. Light Pole, N. of Screenhouse,JAF 43.4+7.2 53.5+7.7 65.0+9.0 6&.1+12.4 0.5 miles Q 68

-86

TABLE 12B (Continued)

DIRECT RADIATION'MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma January April July October Location Station 1987 Through Through Through Through (Direction and Number Location March June September December (Distance)(3) 29 N. Fence, N. of W. Side Screenhouse, JAF 92.5+8.0 97.0+10.2 95.5+12.4 94.0+14.4 0.5 miles Q 65 30 N Fence (NW) JAF 27.4+2.8 34.1+3.0 41.9+2.6 43.2+3.9 0.4 miles Q 57~

31 N. Fence (NW) NMP-1 (1) 24.8+1.8 24.5+1 8

~ 23.4+1.6 0.2 miles Q 276 39 N. Fence, Rad. Waste, NMP-1 37.2+2.8 32.6+2.2 33.5+1.9 33.9+3.2 0.2 miles Q 292 47 N. Fence, NE, JAF 26.0+1.8 31.6+2.2 36.0+2.9 33.8+2.4 0.6 miles Q 69o 49~ Phoenix, NY-Control 14.6+0.3 13.8+0.4 16.4+0.2 15.4+0.8 19.8 miles Q 170 51 Liberty 6 Bronson Sts., E. of OSS 17.3+0.4 14.0+0.4 16.0+0.4 17.5+0.8 7.4 miles Q 233 52 East 12th 6 Cayuga Sts., Osw. School 16.6+0.5 14.4+0.4 16.6+0.4 15.8+0.6 5.8 miles Q 227o 53 Broadwell S Chestnut Sts., Fulton H.S. 17.2+0.4 14.4+0.4 18.0+0.6 16.2+0.6 13.7 miles Q 183 54 Liberty St. 6 Co. Rt. 16, Mexico H.S. 16.6+0.8 14.2+0.4 15.9+0.4 13 8+0.6 F 9.3 miles Q 115 Gas Substation, Co. Rt. 5, Pulaski 16.2+0.8 13.8+0.3 16.6+0.4 15.4+0.4 13.0 miles 75 56't.

55 58<

104 New Haven Sch. (SE Corner)

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

16.7+0.4 15.9+0.4 13.4+0.4 12.2+1.8 17.0+0.8 14.3+0.6 15.5+0.5 16'.4+0.5 5.3 3.1 miles miles Q

Q Q

123 220 75> Unit 2, N. Fence, N. of Reactor Bldg. 17.8+0.6 14.S+0. 6 17.0+0.5 15.2+0.6 0.1 miles Q 5o 76> Unit 2, N. Fence, N. of Change House 13.5+0.5 16;0+0.8 17.2+0.5 16.4+0.6 0.1 miles Q 25 77~ Unit 2, N. Fence, N. of Pipe Bldg. 18.2+0.6 22.4+0.7 22.7+1.7 17.6+0.8 0.2 miles Q '45 78'AF, E. OF E. Old Laydown Area 18.2+0.8 17.4+0.6 18.4+0.6 16.8+0.6 16.1+0.6 15.4+0.4 1.0 1.1 miles miles Q 90 79~ Co. Rt. 29, Pole 863, 0.2 mi. S. of Lake Rd. 15.5+0.4 15.6+0.3 Q 115 80~ Co. Rt. 29, Pole it54, 0.7 mi. S. of Lake Rd. 15.4+0.4 13.3+0.4 16.6+0.4 14.8+0.3 1.4 miles Q 133 81" Miner Rd., Pole it16, 0.5 mi. W. of Rt. 29 16.6+0.4 13.2+0.4 17.4+0.4 16 '+0.6 1.6 miles Q 159 82~ Miner Rd., Pole tt 1 1/2, 1.1 mi. W. of Rt. 29 16.2+0.4 13.0+0.3 14.8+0.4 16.2+0.6 1.6 miles Q 181

-87

TABLE 12B (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma January April July October Location Station 1987 Through Thro'ugh Through Through (Dxrectxon and Number'ocation March June September December (Distance)(3) 83> Lakeview Rd., Tree, 0.45 mi. N. of Miner Rd. 16.4+0.9 15.2+1.3 17.0+0.4 15.6+0.6 1.2 miles 9 200 84> Lakeview Rd., N., Pole 8 6117, 200 Ft.

N. of Lake Rd. 17.8+0.8 16.9+1.4 17.0+0.6 16.6+0.7 1.1 miles 9 225 85~ Unit 1, N. Fence, N. of W. Side of Screen House 39.6+3.9 35.6+5.0 36.4+2.5 42.4+3.1 0.2 miles 9 294 86> Unit 2, N. Fence, N. of W. Side of Screen House 20.4+1.4 21.6+2.2 21.0+1.0 19.0+1.4 O.l miles 9 315 87> Unit 2, N. Fence, N. Of E. Side of Screen

.House 18.4+0.6 16.6+0.8 18.4+0.8 17.'6+1.0 O.l miles 9 341

&8< Hickory Grove Rd., Pole it2, 0.6 mi. N.

of Rt. 1 18.3+1.8 13.4+0.4 17.6+0.4 14.8+0.6 4.8 miles Q 97 89~ Leavitt Rd., Pole tl6, 0.4 mi. S. of Rt. 1 17.2+0.4 16.0+0.4 18.2+0.4 15.8+0.6 4.1 4.2 miles 9 miles Q ill 904 Rt. 104, Pole tt300, 150 Ft. E. of Keefe Rd. 16.6+0.6 14.3+0.4 16.4+0.6 15.0+0.5 135 91< Rt. 51A, Pole ft59, 0.8 mi. W. of Rt. 51 15.2+0.3 12.7+0.6 15.1+0.4 14.4+0;7 4.8 miles 9 156 92" Maiden Lane Rd., Power Pole, 0.6 mi. S.

of Rt. 104 16.4+0.4 15.0+0.5 18.2+0.6 16.8+0.4 4.4 miles 9 183 93 Jt Rt. 53, Pole l-l, 120 Ft. S. of Rt. 104 13.5+0.4 15.7+0.6 17.1+0.8 15.2+0.4 4.4 males 9 205 Rt. 1, Pole 882, 250 Ft. E. of Kocher Rd. 15..0+0.6 16.4+0.8 15.1+0.5 15.0+0.4 4.7 miles 9 223 ~

94%'5k'6% Lakeshore Camp Site, From Alcan W. Access Rd., Pole it21, 1.2 mi. N. of Rt. 1 13.7+0.3 13.8+0.4 15.6+0.3 13.2+0.2 4.1 miles Q 237 Creamery Rd., 0.3mi. S. of Middle Rd.,

Pole 1 1/2 16.7+0.8 13.6+0.4 15.640;4 16.6+0.6 3.6 miles Q 199

-88

TABLE 12B (Continued)

DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma January April July October Location Station 1987 Through Through Through Through (Direction and Number Location March June September December (Distance)(3) 97* Rt. 29, Env. Station R4, 200 Ft. N.

of Miner Rd. 16.6+0.4 10.4+3.7 17.2+0.4 14.4+0.4 1.8 miles 9 143 98)k Lake Rd., Pole 8145, 0.15 mi. E. of Rt. 29 18.2+0.4 14.4+0.5 18.4+0.6 17.8+0.6 1.2 miles 9 101 99 NMP Rd., 0.4 miles N. of Lake Rd., Env.

Station Rl Off-Site 14.8+0.2 14.7+0.4 16.7+0.4 16.5+0.6 1.8 miles 9 88 100 Rt. 29 and Lake Rd., Env. Station R2 Off-Site 15.1+0.4 14.0+0.4 18.2+0.4 15.6+0.5 1.1 miles Q 104 101 Rt. 29, 07 mi. S. of Lake Rd., Env. Station R3 Off-Site 16.0+0.3 13.2+0.9 17.0+0.4 15.8+0.4 1.5 miles 9 132 102 EOF/Env. Lab, Oswego Co. Airport (Fulton Airport), Rt. 176, E. Driveway Lamp Post 20.7+0.8 14.2+0.4 17.3+0.4 17.0+0.4 11.9 males 9 175 103 EIC, East Garage Rd., Lamp Post 17.2+0.4 ~ 16.2+0.6 16.6+0.5 18.5+0.4 0.4 miles 9 267 104 Parkhurst Road, Pole 148 1/2-A, O.l mi.

S. of Lake Rd. 16.6+0.8 14.4+0.4 16.0+0.6 15.2+0.6 1.4 milos Q 102 105 Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd. 16.6+0.6 15.0+0.4 17.6+0.4 14.8+0.4 1.4 miles Q 198 106 Shoreline Cove, E. of NMP-l, Tree on West Edge 20.0+0.8 17.8+0.8 19.9+0.8 18.0+0.7 0.3 miles 9 274 107 Shoreline Cove, E. of NMP-l, Tree 30 ft. South of TLD 8106 (2) 19.2+1.0 20.2+0.8 16.6+0.8 0.3 miles Q 272 (1) TLD lost in the field.

(2) TLD not established during the quarterly period.

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

(4) TLD deleted.

Technical Specification location

-89

TABLE 13 CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Station Nucli des 4-6-87 4-20-87 5-4-87 5-18-87 6-1-87 6-15-87 K-40 1450+203 1530+241 1490+170 1590+167 1540+189 1630+189 Cs-134 <9.4 <10.6 <6.9 <7.8 <6.6 <6.2 Cs-137 <8.3 <11.1 5.5+4.0 <7.9 <7.8 <8.1 Ba/La-140 <9.8 <4.9 <6.0 <4.8 <7.4 <7.5 Others <LLD <LLD <LLD <LLD <LLD <LLD 16 K-40 1390+196 1550+286 1650+172 1740+194 1380+181 1730+173 Cs-134 <8.3 <10.6 <7.2 <7.0 <6.4 <7.1 Cs-137 <9.7 <15.4 <8.0 . <9.2 <8.8 <9.0 Ba/La-140 <7.7 <12.9 <7.2 <9.0 <6.0 <6.8 Others <LLD <LLD <LLD <LLD <LLD <LLD 50 K-40 1410+174 1670+271 1330+159 1740+181 1400+189 1730+172 Cs-134 <8.0 <9.0 <6.6 <7.0 <8.2 <6.4 Cs-137 <8.3 <12.0 <8.1 <8.9 <8.4 <8.3 Ba/La-140 <7 7 <8.5 <8.0 <8.5 <6.4 <5.1 Others <LLD <LLD ~

<LLD <LLD <LLD <LLD 55 K-40 1710+205 1440+262 1640+168 1510+173 1660+169 1270+183 Cs-134 <8.4 <10.7 <8.4 <7.7 <6.3 <6.6 Cs-137 <8.8 <13.3 8.li4.6 <9.0 <8.2 <6.1 Ba/La-140 <7.0 <13.5 <7 3 <8.6 <7.7 <8.3 Others <LLD <LLD (I LD <LLD <LLD <LLD

-90

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Station Nuclides 4-6-&7 4-20-87 5-4-87 5-18-87 6-1-87 6-15-87.

60 K-40 1300+197 1430+224 1420+190 1590+189 1400+165 1530+188 Cs-134 <8.4 <9.5 <7.6 <8.4 <7.6 <6.7 Cs-137 <8.9 <13.6 <9.8 <8.3 <7.8 <8.1 Ba/La-140 <8.6 <9.8 <6.5 <7.4 <7.5 <6.7 Others <LLD <LLD <LLD <LLD <LLD <LLD K-40 1470+178 1730+250 1730+196 1570+198 1510+197 1590+188 Cs-134 <6.6 <9.3 <7.2 <8.6 <8.9 <7.4 Cs-137 <8.6 <11.7 <9.7 <10.5 <8.6 <8.0 Ba/La-140 <7.5 <9.4 <7.0 <11.1 <6.4 <5 5 Others <LLD <LLD <LLD . <LLD <LLD <LLD 65" K-40 1490+263 1370+225 1670+192 1710+174 1530+164 1610al66 (Control) Cs-134 <11.8 <9.0 <7.8 <7 7 <6.3 <7.0 Cs-137 <11.3 <11.4 <6.8 <8.5 <7.4 <7.4 Ba/La-140 <9.0 <13.5 <6.0 <2.4 <5.9 <5.6 Others <LLD <LLD <LLD <LLD <LLD <LLD

~-Technical Specification location

-91

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Station Nuclides 7-6-87 7-20-87 8-3-87 8-17-87 9-8-87 9-21-87 K-40 1430+194 1740+173 1450+198 '1580+169 17&0+147 16704144 Cs-134 <7.8 <5.7 <8.4 <5.9 <4.9 <4.7 Cs-137 <9.7 <8.7 <8.0 <7.7 <5.7 <5.4 Ba/La-140 <9.8 <7 7 <10.0 <4.& <5.1 <4.8 Others <LLD <LLD <LLD <LLD <LLD <LLD 16 K-40 1820+176 1570+183 1430+191 1570+201 1340+188 16404-1 75 Cs-134 <6.3 <5.5 <7.4 <7.8 <8.4 <6.6 Cs-137 <9.2 <7.5 <9.8 <10.7 <7.0 <7.5 Ba/La-140 <8.0 <6.1 <5 7 <7.5 <8.4 <3.6 Others <LLD <LLD <LLD <LLD <LLD <LLD 50 K-40 1690+72 1370+163 1680+173 1610+134 1470+139 1270+148 Cs-134 <2.6 <6.8 <7.0 <4.8 <4.5 <7.1 Cs-137 <2.8 <7.2 <7.0 <5.2 <5.9 <6.3 Ba/La-140 <3.0 <7.7 <7.1 <6.1 <4.9 <6.1 Others <LLD <LLD <LLD <LLD <LLD <LLD 55 K-40 1260+185 1540+185 1640+135 1810+143 1600+142 1530+142 Cs-134 <6.2 <7.4 <4.8 <5.1 <4.9 <4.7 Cs-137 <9.2 <8.5 <5.4 <5.3 <5.5 <5.5 Ba/La-140 <9.7 <5*. 0 <5.8 <5.3 s <3.8 <3.7 Others <LLD <LLD <LLD <LLD <LLD <LLD

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Station Nuclides 7-6-87 7-20-87 8-3-87 8-17-87 9-8-87 9-21-87 60 K-40 1660+61 744<94 15'20+167 1580+165 1500+166 1490+136 Cs-134 <2.4 <4.2 <7.2 <6.0 <6.4 <4.1 Cs-137 <2.8 <4.6 <7 7 <7.4 <6.8 <5.5 Ba/La-140 <2.6 <2.9 <5.1 <4.2 <5.1 <4 '

Others <LLD <LLD <LLD <LLD <LLD <LLD K-40 1360+165 1400+157 1430+193 1440+139 1440+137 1570+201 Cs-134 <6.5 <7.1 <5.2 <3.8 <5.0 <7.8 Cs-137 <8.1 <8.2 <9.2 <6.6 <5.5 <7.8 Ba/La-140 <9. 0 <6.1 <7;9 <4.9 <5.6 <9.2 Others <LLD <LLD <LLD <LLD <LLD <LLD 65k K-40 1610+177 1190+176 1360+191 1720+140 1640+172 1610+142 (Control) Cs-134 <6. 8 <7.2 <6.5 <4.5 <6.6 <4.8 Cs-137 <8.0 <8.9 <8.9 <5.3 <8.2 <5.2 Ba/La-140 <7.2 <8.0 <10.7 <5 ' <7.3 <5.6 Others <LLD <LLD <LLD <LLD <LLD <LLD

>-Technical Specification location.

-93

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units bf pCi/liter + 2 signa Station Nuclides 10-5-87 10-19-87 11-2-87 11-16-87 12-7-87 12-21-87 K-40 1180+41 1370+133 1620+167 1690+170 1320+132 1550+140 Cs-134 <1.6 <5.2 <6.3 <6.3 <5.1 <5.5 Cs-137 <1.8 <5 ' <7.7 <7.4 <5.1 '5.5 Ba/La-140 <1.9 <3.1 <4.0 <5.1 <3.9 <6.4 Others <LLD <LLD <LLD <LLD <LLD <LLD 16 K-40 1560+165 1430+192 1820+143 1680+137 1400+134 Cs-134 <6.4 <6.6 <7.0 <5.4 <5.0 <5.0 Others'700+177 Cs-137 <7.6 <8.4 <10.4 <6.3 <5.7 <5.9 Ba/La-140 <7.6 <7.2 <11.9 <5.0 <6.2 <5.3

<LLD <LLD <LLD <LLD <LLD <LLD 50 K-40 1620+135 1550+134 1670+174 1450+135 1720+141 1450 1-193 Cs-134 <4.4 <5.6 <7.0 <4.8 <5.3 <6.3 Cs-137 <5.1 <6.0 <7.5 <5.4 <5.4 <8.7 Ba/La-140 <5.3 <5.0 <8.7 <3.0 <4.8 <11.2 Others <LLD <LLD <LLD <LLD <LLD <LLD 55 K-40 1520+165 1440+197 1660+138 1550+203 1560+204 1630+136 Cs-134 <6.9 <7.8 <4 ' <7 7 <7.3 <5.2 Cs-137 <7.4 <8.2 <5.5 <7.8 <8.7 <5.3 Ba/La-140 <4.8 <7.2 <5.8 <9.6 <6.2 <4.8 Others <LLD <LLD <LLD <LLD <LLD <LLD

-94

TABLE 13 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Station Nucli des 10-5-87 10-19-87 11-2-87 11-16-87 12-7-87 12-21-87 60 K-40 1400+156 1500+161 1400+134 1350+190 1450+189 1640+169 Cs-134 <6.9 <6.6 <5.3 <7 3 <5.6 <6.1 Cs-137 <7 3 <7.8 <5.4 <8.2 <9.2 <7.9 Ba/La-14$ <7 7 <8.0 <5.3 <8.0 <10.2 <5.1 Others <LLD <LLD <LLD . <LLD <LI D <LLD K-40 1340+187 1370+189 1620+141 1540+165 1770+145 1820+144 Cs-134 <6.7 <7.1 <5.8 <5.9 <5.3 <4.6 Cs-137 <10.1 <9.5 <6.0 ~ <7.7 <6.1 <5.3 Ba/La-140 <8.0 <8.4 <5.5 <9.1 <5.0 <5.4 Others <LLD <LLD <LLD <LLD <LLD <LLD 65~ K-40 1790+144 1410+197 1350+186 1450+136 1670+169 14704.198 (Control) Cs-134 <5.0 <7.8 <7.7 <5 3 <6.7 <8.5 Cs-137 <6.1 <7.4 <8:4 <5.2 <7.8 <8.0 Ba/La-140 <5 3 <5.1 <6.5 <5.9 <6.9 <5.1 Others <LLD <LLD <LLD <LLD <LLD <LLD

>-Technical Specification location.

-9'5

TABLE 14 CONCENTRATION OF IODINE 131 IN MILK (1)

Results in units of pCi/liter + 2 sigma Station 4-6-87 4-20-87 5-4-87 5-18-87 6-1-87 6-15-87

\

7 <0.3 <0.2 <0.3 <0.4 <0.4 <0.2 16 <0.3 <0.3 <0.3 <0.2 <0.3 <0.2 50 <0.3 <0.4 <0.3 <0.4 <0.5 <0.2 55 <0.4 <0.3 <0.2 <0.3 <0.3 <0.2 60 <0.4 <0.3 <0.3 <0.5 <0.4 <0.3 4 <0.5 <0.3 <0.3 <0.2 <0.4 <0.2 65> <0.2 <0.3 <0.2 <0.2 <0.4 <0 '

Station 7-6-87 7-20-87 8-3-87 8-17-87 9-8-87 9-21-87 7 <0.3 <0.3 <0.3 <0.4 <0.3 <0.1 16 <0.3 <0 <0.2 <0.4 <0.3 <0.3 50 <0.4 <0.3 <0.2 <0.3'0.4

<0.5 <0.1 55 <0.4 <0.2 <0.2 <0.2 <0.3 60 <0.3 <0.2 <0.3 <0.3 <0.5 <0.4 4 <0.4 <0.4 <0.3 <0.4 <0.3 <0.3 65" <0.4 <0.4 <0.3 <0.4 <0.2 <0.3 Control result. Technical Specification location.

Original sample could not be analyzed at the laboratory. A sample for this location was recollected on 7/27/87 and analyzed.

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

-96

TABLE 14 (Continued)

CONCENTRATION OF IODINE 131 IN MILK (1)

Results in units of pCi/liter + 2 sigma Station 10-5-87 10-19-87 11-2-87 11-16-87 12-7-87 12-21-87 7 <0.3 <0.3 <0.4 <0.2 <0.2 16'0 <0.3 <0.3 <0.2 <0.2 <0.3 <O.l

<0.2 <0.3 <0.2 <0.4 <0.2 <0.2 65%'0.2 55 60

<0.2

<0.3

<0.2

<0.3

<0.2

<0.3

<0.4

<0.3

<0.2

<0.4 4 <0.2 <0.4 <0.2 <0.2 <0.2 <0.2

<0.3 <0.2 <0.2 <0.3 <0.2 <0.2 Control result. Technical Specification location.

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

-97

TABLE 15 MILK ANIMAL CENSUS 1987 Number on Number of Town or Area(a) ~Census Me ~<>e rees<3> Distance( Milk Animals Scriba 1(b) 220 3,0 miles None 16< 190 "5.9 40C 2 195 8.0 ND 3 (b) 190 4.5 2C 6 (b) 162 2 ' 1C 26 (b) 114 1.5 ND 61 (b) 140 3.0 15G(2) 62 183 6.7 5G 63 185 8.0 39C New Haven 8 130 9.2 32C 9 95 5.2 40C 4A'5 113 7 ' 95C 125 8,0 None 10(b) 130 2.6 32C 5 146 7.2 52C 11 130 8.5 36C 7 )L'4 107 5.5 67C 107 7.9 50C Mexico 12 107 11.5 22C 13 114 11.2 1C 14 120 9.8 57C 15 100 10.8 None 17 115 10.2 45C 18 110 10.0 42C 19 1320 10.5 40C 20 123 11.2 None 60~ 90 9.5 40C 50><l 93 8.2 170C 55K 950 9.0 55C 21 1120 10.5 80C 49 88 7.9 6G(2)

Richland 22 850 10.2 42C Pulaski 23 920 10.5 55C Oswego 24 2140 8.8 None Hannibal 40 220 15.0 None Sterling 65RR 220 17.0 42C Volney 25 182 9.5 None 70 1470 9.4 17C 66 1560 7.8 90C, 1G(2) 67 1520 8.3 3G(2)

MILKING ANIMAL TOTALS: 1,287 Cows (including control locations) 30 Goats 1,245 Cows (c) 30 Goats (c)

-98

TABLE 15 (Continued)

MILK ANIMAL CENSUS 1987 NOTES:

C = Cows G Goats Milk sample location Milk sample control location New location ND = Did not wish to participate in the survey (1) References Figure 4 (2) Goat is not currently producing milk (3) Degrees and distance are based on NMP-2 Reactor Building centerline.

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

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

(b) Location within five miles (Technical Specification requirement).

(c) Totals excluding. control location results.

-99

TABLE 16 1987 RESIDENCE CENSUS Map(1) Meteorological Location Location Sector De rees(2) Distance(

N NNE NE ENE Lake Road A E 99 1.3 miles Lake Road B ESE 102 1.1 miles County Route 29 C SE 130 1.4 miles Miner Road D SSE 163 1.6 miles Miner Road E S 1700 1.6 miles Lakeview Road F SSW 2070 1.2 miles Bible Camp Retreat G SW 2340 0.9 miles Bible Camp Retreat H WSW 238 0.9 miles W

WNW NW NNW 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.

-100

TABLE 17A CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units .of pCi/g (wet) + 2 sigma Collection Sample Site Date Description Be-7 K-40 I-131 Cs-134 Cs-137 Others T 9-14-87 Beet Greens 0.47+0.15 4.87+0.49 <0.037 <0.018 <0.017 <LLD T 9-14-87 Squash Leaves 1.88+0.19 2.22+0.22 <0.019 <0.011 <0.012 <LLD T 9-14-87 Cabbage <0.14 2.66+0.27 <0.027 <0.014 <0.016 <LLD P 9-15-87 Cabbage <0.15 2.02+0.25 <0.028 <0.015 <0.016 <LLD P 9-15-87 Green Bean Leaves 1.46+0.15 1.16+0.12 <0.026 <0.011 <0.013 <LLD P 9-15-87 Squash Leaves 1.47+0.15 2.0540.20 <0.024 <0.012 <0.012 <LLD N 9-15-87 Squash Leaves 1.74+0.17 2.21+0.22 <0.025 <0.014 <0.014 <LLD R 9-15-87 Squash Leaves 0.97+0.ll 2.37+0.24 <0.019 <0.012" <0.012 <LLD R 9-15-87 Green Bean Leaves 0.94+0.12 1.06+0.12 <0.027 <0.011 <0.013 <LLD R 9-15-87 Cucumber Leaves 1.81+0.18 1.33+0.15 <0.020 <0.010 <0.011 <LLD V 9-15-87 Cabbage <0.12 2.85+0.29 <0.025 <0.013 <0.012 <LLD W" 9-15-87 Swiss Chard <0.12 5.01+0.50 <0.028 <0.013 <0.012 <LLD 9-15-87 Squash Leaves 1.69+0.17 2.43+0.24 <0.020 <0.009 <0.009 <LLD W> 9-15-87 Beet Greens 0.34+0.12 5.81+0.58 <0.032 <0.014 <0.013 <LLD WA 9-15-87 Cabbage 0.10+0.06 2.55+0.25 <0.021 <0.009 <0.009 <LLD

> Control result.

Results in units uy activity ~er ran wet weight.

-101

TABLE 17A (Continued)

CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units of pCi/g (wet) + 2 sigma Collection Sample Site Date Description Be-7 K-40 I-131 Cs-134 Cs-137 Others J Swiss Chard 0.26+0.10 5.22+0.52 <0.026 <0.010 <0.011 <LLD J 9-14-87 Lettuce 0.54+0.18 1.85+0.27 <0.036 <0.016 <0.018 <LLD J 9-14-87 Pumpkin Leaves 1.23+0.14 2.51+0.25 <0.023 <0 011 F <0.013 <LLD QA'-14-87 S 9-15-87 9-14-87 Grape Leaves Tomatoes 0.75+0.10

<0.08 1.18+0.14 2.35+0.24

<0.020

<0.018

<0.010

<0.009

<LLD

<LLD Pyiik 9-15-87 Tomatoes <0.10 2.61+0.26 <0.020 <0.013 <0.012 <LLD Ra% 9-15-87 Tomatoes <0.08 2.62+0.26 <0.016 <0.010 <0.009 <LLD 9-15-87 Tomatoes <O.ll 1.91+0.20 <0.025 <0.011 <0.011 <LLD Naa 9-15-87 Tomatoes <0.07 1.84+0.19 <0.018 <0.009 <0.010 <LLD JAR 9-14-87 Tomatoes <0.09 2.4840.25 <0.020 <0 '11 <0.011 <LLD 9-15-86 Tomatoes <0.20 2.95+0.29 .<0.049 <0.019 <0.020 <LLD 9-15-87 Tomatoes <0.08 2.17+0.22 <0.018 <0.009 0 '16+0.008 <LLD

> Control result.

>> Optional sample (non-broadleaf vegetation).

'Results in. units of activity ~er ram wet woight.

-102

TABLE 17B CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units of PCi/kg (wet) + 2 sigma Collection Sample Others Site Date Description Be-7 . K-40 I-131 Cs-134 Cs-137 9-14-87 Beet Greens 469+152 4870+490 <37 <18 <17 <LLD T

T 9-14-87 Squash Leaves 1880+190 2220+220 <19 <ll <12 <LLD 9-14-87 Cabbage <140 2660+270 <27 <14 <16 <LLD T

9-15-87 Cabbage <150 2020+250 <28 <15 <16 <LLD P

P 9-15-87 Green Bean Leaves 1460+150 1160+120 <26 <ll <13 <LLD 9-15-87 Squash Leaves 1470+150 2050+200 <24 <12 <12 <LLD P

9-15-87 Squash Leaves 1740+170 2210+220 <25 <14 <14 <LLD N

9-15-87 Squash Leaves 966+106 2370+240 <19 <12 <12 <LLD R

R 9-15-87 Green Bean Leaves 940+115 1060+120 <27 <ll <13 <LLD 9-15-87 Cucumber Leaves 1810+180 1330+150 <20 <10 <11 <LLD R ~

9-15-87 Cabbage <120 2850+290 <25 <13 <12 <LLD V

W~ 9-15-87 Swiss Chard <120 5010+500 <28 <13 <12 <LLD 9-15-87 Squash Leaves 1690+170 2430+240 <20 <9 ~ <9 <LLD 9-15-87 Beet Greens 341+125 5810+580 <32 <14 <13 <LLD W* 9-15-87 Cabbage 104+61 2550+250 <21 <9 <9 <LLD J 9-14-87 Swiss Chard 265+95 5220+520 <26 <10 <ll <LLD 9-14-87 Lettuce 537+176 1850+270 <36 <16 <18 <LLD J

~ Control result

-103

TABLE 17B (Continued)

CONCENTRATION OF GAMMA EHITTERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) + 2 sigma Collection: 'ample Site Date Description Be-7 K-40 I-131 Cs-134 Cs-137 Others 9-14-87 Pumpkin Leaves 1230+140 2510+250 <23 <ll <13 <LLD 9-15-87 Grape Leaves 753+99 1180+140 <20 <10 <9 <LLD 9-14-87 Tomatoes <82 2350+240 <18 <10 <9 <LLD 9-15-87, Tomatoes <95 2610+260 <20 <13 <12 <LLD 9-15-87 Tomatoes <80 '2620+260 <16 <10 <9 <LLD 9-15-87 Tomatoes <110 1910+200 <25 <11 <11 <LLD 9-15-87 Tomatoes <73 1&40+190 <18 <9 <10 <LLD 9-14-87 Tomatoes <89 2480+250 <20 <11 <ll <LLD 9-15-87 Tomatoes <200 2950+290 <49 <19 <20 <LLD 9-15-87 Tomatoes <84 2170+220 <18 <9 16+8 <LLD

> Control result

>> Optional sample (non-broadleaf vegetation).

-104

TABLE 18 INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis 'Date Medium Site Reference No. EPA Result (1) Site Result (2)

Beta 4/87 Air Filter QA 87-35 43+5 54+4 (3)

(pCi/filter) 54+4 55+4 Beta 8/87 Air Filter QA 87-96 30+5 36+3 (3)

(pCi/filter) 36+3 36+3 Tritium 2/87 Water QA 87-14 4209+421 4000+200 (4)

(pCi/liter) 3800+100 4000+100 Tritium 6/87 Water QA 87-68 2895+357 2800+100 (4)

(pCi/liter) 2700+200 3000+200 Tritum 10/87 Water QA 87-117 4492+449 4700+100 (4)

(pCi/liter) 4500+100 4800+100 I-131 2/87 Milk QA 87-20 9+1 9+1 (4)

(pCi/liter) 9+1 9+1

-105

TABLE 18 (Continued)

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

I-131 4/87 Water QA 87-28 7+1 8+2 (3)

(pCi/liter) 8+2 8+3 I-131 8/87 Water QA 87-88 48+6 46+9 (3)

(pCi/liter) 52+12 45+12 I-131 12/87 Water QA 87-160 26+6 30+2 (3)

(pCi/liter) 30+2 30+3 Gamma 1/87 Food QA 87-6 78+8 72+3 (4)

(I-131) (pCi/kg) 76+3 75+2 Gamma 1/87 Food QA 87-6 84+5 88+9 (4)

(Cs-137) (pCi/kg) 96+10 97+10 Gamma 1/87 Food QA 87-6 980+49 775+78 (4)

(K-40)% (pCi/kg) 76&+77 870+87 Gamma 7/87 Food QA 87-82 80+8 89+13(4)

(I-131) (pCi/kg) 83+14 100+15

-106

TABLE 18 (Continued)

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

Gamma 7/87 Food QA 87-82 50+5 55+6 (4)

(Cs-137) (pCi/kg) 56+6 57+6 Gamma 7/87 Food QA 87-82 1680+84 1610+160 (4)

(K-40)A (pCi/kg) 1630+160 1410+140 Gamma 2/87 Mater QA 87-12 50+5 62+15 (3)

(Co-60) (pCi/liter) 51+13 50+16 Gamma 2/87 Water QA 87-12 91+5 97+24 (3)

(Zn-65) (pCi/liter) 103+37 112+29 Gamma 2/87 Mater QA 87-12 100+5 136+77 (3)

(RU-106) (pCi/liter) 137+83 137+71 Gamma 2/87. Mater qA 87-12 59+5 51+12 (3)

(Cs-134) (pCi/liter) 52+14 53+12 Gamma 2/87 Water QA 87-12 87+5 75+14 (3)

(Cs-137) (pCi/liter) 77+19 79+14

-107

TABLE 18 (Continued)

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

Gamma 6/87 Water QA 87-61 41+5 35+19 (3)

(Cr-51) (pCi/liter) 50+19'9+19 Gamma 6/87 Water QA 87-61 64+5 60+4 (3)

(Co-60) (pCi/liter) 64+4 68+4 Gamma 6/87 Water QA 87-61 10+5 7+5 (3)

(Zn-65) (pCi/liter) 12+5 16+5 Gamma 6/87 Water QA 87-61, 75+5 76+6 (3)

(RU-106) (pCi/liter) 77+6 87+6 Gamma 6/87 Water QA 87-61 40+5 36+3 (3)

(Cs-134) (pCi/liter) 40+3 41+3 Gamma 6/87 Water QA 87-61 80+5 72+4 (3)

(Cs-137) (pCi/liter) 76+4 79+4 Gamma 10/87 Water QA 87-116 70+5 197+75 (3)

(Cr-51) (pCi/liter) LLD 84+43

-108

TABLE 18 (Continued)

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

Gamma 10/87 Water QA 87-116 15+5 18+3 (3)

(Co-60) (pCi/liter) 15+5 16+5 Gamma 10/87 Water QA 87-116 46+5 41+6 (3)

(Zn-65) (pCi/liter) 50+13 48+13 Gamma 10/87 Water QA 87-116 61+5 52+16 (3)

(RU-106) (pCi/liter) 46+30 57+32 Gamma 10/87 Water QA 87-116 25+5 27+3 (3)

(Cs-134) (pCi/liter) 27+5 29+6 Gamma 10/87 Water QA 87-116 51+5 46+3 (3)

(Cs-137) t (pCi/liter) 42+6 48+7 Gamma 4/87 Water QA 87-36 8+5 10+5 (3)

(Co-60) (pCi/liter) 10+5 10+5

-109

TABLE 18 (Continued)

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

Gamma 4/87 Mater QA 87-36 20+5 18+8 (3)

(Cs-134) (pCi/liter) 20+6 20+6 Gamma . 4/87 Mater QA 87-36 15+5 12+5 (3)

(Cs-137) (pCi/liter) 12+5 13+6 Gamma 10/87 Mater QA 87-118 16+5 14+5 (3)

(Co-60) (pCi/liter) 16+2 16+2 I

Gamma 10/87 Mater QA 87-118 16+5 20+6 (3)

(Cs-134) (pCi/liter) 17+3 19+3 Gamma 10/87 Water QA 87-118 24+5 26+5 (3)

(Cs-137) (pCi/liter) 24+2 22+5 Gamma 4/87 Air Filter QA 87-35 8+5 11+4 (3)

(Cs-137) (pCi/filter) 11+4 12+4

TABLE 18 (Continued)

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

Gamma 8/87 Air Filter QA 87-96 10+5 12+5 (3)

(Cs-137) (pCi/filter) 12+4 ll+4 Gamma 6/87 Milk QA 87-71 59+6 55+2 (3)

(I-131) (pCi/liter) 58+2 51+2 Gamma 6/87 Milk QA &7-71 74+5 82+8 (3)

(Cs-137) (pCi/liter) 82+8 81+8 Milk 87-71 1525+76 1538+154 (3)

(K-40)A'/87 Gamma (pCi/liter)

QA 1593+159 1443+144.

Gamma 10/87 Milk QA 87-N/A NS NS (I-131) (pCi/liter) NS NS Gamma 10/87 Milk QA 87-N/A NS NS (Cs-137) (pCi/liter) NS NS

-111

TABLE 18 (Continued)

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

Milk 87-NA NS NS (K-40)A'0/87 Gamma (pCi/liter)

QA NS NS a-EPA K-40 results reported as mg per unit of total potassium.. Site results reported as K-40 only.

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

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

(3)-Analyzed at the site environmental laboratory.

(4)-Analyzed at a vendor laboratory.

N/A Not applicable. No sample available.

NS No sample sent by USEPA.

-112

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

Shoreline 05% Figure lA Sunset Bay 80 at 1'.5 miles Sediment 06 Figure 1A Langs Beach, Control 230 at 5.8 males 07 Figure lA Nine Mile Point 275 at 0.3 mxles Fish 02k Figure lA Nine Mile Point Transect 315 at 0.3 miles 03%'0<

Figure lA FitzPatrick Transeot 55 at 0.6 miles Figure 1A Oswego Transect 235 at 6.2 miles Surface Mater 03% Figure lA FitzPatrick Inlet 70 at 0.5 miles 08" Figure lA Oswego Steam Station Inlet 235 at 7.6 miles 09 Figure lA NMP Unit 1 Inlet 305 at 0.3 miles 10 Figure lA Oswego City Mater 240 at 7.8 miles Figure lA NMP Unit 2 Inlet 304 at O.l miles

-113

TABLE 19 (Continued)

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

Air R-1> Figure 1A R-1 Station, Nine Mile Point Road 88 at 1.8 miles Radioiodine and Figure 2 R-2 Station, Lake Road 104 at 1.1 miles Particulates R-3> Figure 2 R-3 Station, Co. Rt. 29 132 at 1.5 miles Figure 2 R-4 Station, Co. Rt. 29 143 at 1.8 miles R-5~ - Figure lA R-5 Station, Montario Point Road 42 at 16 ' miles Dl Figure 2 Dl On-Site Station 69 at 0.2 miles Figure 2 G On-Site Station 250 at 0.7 miles H Figure 2 H On-Site Station 71 at 0.8 miles Figure 2 I On-Site Station 98 at 0.8 miles Figure 2 J On-Site Station 110 at 0.9 miles Figure 2 K On-Site Station 132 at 0.5 miles Figure lA G Off-Site Station, Saint Paul Street 225 at 5.3 miles

-114

TABLE 19 (Continued)

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

Air D2 Figure 1A D2 Off-Site Station, Rt. 64 117 at 9.0 miles

- Radioiodine And E Figure lA E Off-Site Station, Rt. 4 160 at 7.2 miles Particulates Continued Figure 1A F Off-Site Station, Dutch Ridge Rd. 190 at 7.7 miles Thermo- Figure 2 Dl On-Site Station 69 at 0.2 miles luminescent Dosimeters Figure 2 D2 On-Site Station 140 at 0.4 miles (TLD)

Figure 2 E On-Site Station 175 at 0.4 miles Figure 2 F On-Site Station 210 at 0.5 miles Figure 2 G On-Site Station 250 at 0.7 miles Figure lA R-5 Off-Site Station 42 at 16.4 miles Figure lA Dl Off-Site Location 80 at 11.4 miles 10 Figure lA D2 Off-Site Location, 117 at 9.0 miles

-115

TABLE 19 (Continued)

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

Thermo- Figure lA E Off-Site Location 160 at 7.2 miles luminescent Dosimeters 12 Figure 1A F Off-Site Location 190 at 7.7 miles (TLD)

Continued 13 Figure 1A G Off-Site Station 225 at 5.3 miles 14> Figure 1A Southwest Oswego Control 226 at 12.6 miles 15" Figure lA West Site Boundary 237 at 0.9 miles 18" Figure 2 Energy Information Center 265 at 0.4 miles 19 Figure lA East Site Boundary 81 at 1.3 miles 23+ Figure 2 H On-Site Station 70 at 0.8 miles 24 Figure 2 I On-Site Station 98 at 0.8 miles 25 Figure 2 J On-Site Station 110 at 0.9 miles 26 Figure 2 K On-Site Station 132 - at 0.5 miles 27 Figure 2 North Fence, JAFNPP 60 at 0.4 miles 28 Figure 2 North Fence, JAFNPP 68 at 0.5 miles

TABLE 19 (Continued)

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

Thermo- 29 Figure 2 North Fence, JAFNPP 65 at 0.5 miles luminescent Dosimeters 30 Figure 2 North Fence, JAFNPP 57 at 0.4 miles (TLD)

Continued 31 Figure 2 North Fence, NMP-1 276 at 0.2 miles 39 Figure 2 North Fence, NMP-1 292 at 0.2 miles Figure 2 North Fence, JAFNPP 69 at 0.6 miles 49K Figure 1B Phoenix, NY Control 170 at 19.8 miles 51 Figure lA Oswego Steam Station, East 233 at-7.4 miles

'52 Figure lA Oswego Elementary School, East 227 at 5.8 miles 53 Figure 1B Fulton High School 183 at 13.7 miles 54 Figure 1A Mexico High School 115 at 9.3 miles 55 Figure lA Pulaski Gas Substation, Rt. 5 75 at 13.0 miles 56~ Figure lA New Haven Elemontary School 123 at 5.3 miles 58" Figure lA Co. Rt. 1 and Alcan 220 at 3.1 miles

-117

TABLE 19 (Continued)

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

Thermo- 75% 2 North Fence, NMP-2 5 at 0.1 miles luminescent Dosimeters 76~ Figure 2 North Fence, NMP-2 25 at O.l miles (TLD)

Continued 77% Figure 2 North Fence, NMP-2 45 at 0.2 miles 83'igure 78~ Figure 2 East Boundary, JAFNPP 90 at 1.0 miles 79%'0<

Figure 2 County Route 29 115 at 1.1 miles Figure 2 County Route 29 133 at 1.4 miles 81> Figure 2 Miner Road 159 at 1.6 miles 82~ Figure 2 Miner Road 181 at 1.6 miles Figure 2 Lakeview Road 200 at 1.2'miles 84> Figure lA Lakeview Road 225 at 1.1 miles 85> Figure 2 North Fence, NMP-1 294 at 0.2 miles 86> Figure 2 North Fence, NMP-1 315 at 0.1 miles

TABLE 19 (Continued)

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

Thermo- 87> Figure 2 North Fence, NMP-2 341 at O.l miles luminescent Dosimeters 88" Figure lA Hickory Grove Road 97 at 4.5 miles (TLD)

Continued 89k'OA Figure lA Leavitt Road ill at 4.1 miles Figure lA Route 104 and Keefe Road 135 at 4.2 miles 91> Figure lA County Route 51A. 156 at 4.8 miles 92* Figure lA Maiden Lane Road 183 at 4.4 miles Figure 1A County Route 53 205 at 4.4 miles 93k'4)R Figure 1A County Route 1 and Kocher Road 223 at 4.7 miles 95%'6" Figure lA Lakeshore Camp Site 237 at 4.1 miles Figure lA Creamery Road 199 at 3.6 miles 97%'8~

Figure 2 County Route 29 143 at 1.8 miles Figure lA Lake Road 101 at 1.2 miles 99 Figure lA Nine Mile Point Road 88 at 1.8 miles

-119

TABLE 19 (Continued)

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

Thermo- 100 Figure 2 County Route 29 and.Lake Road 104 at 1.1 miles luminescent Dosimeters 101 Figure 2 County Route 29 132 at 1.5 miles (TLD)

Continued 102 Figure 1B Oswego County Airport 175 at 11.9 miles 103 Figure 2 Energy Information Center, East 267 at 0.4 miles 104 Figure lA Parkhurst Road 102 at 1.4 miles 105 Figure 2 Lakeview Road 198 at 1.4 miles 106 Figure 2 Shoreline Cove, East of NMP-1 274 at 0.3 miles 107 Figure 2 Shoreline Cove, East of NMP-1 272 at 0.3 miles Cows Milk Figure 4 Indicator Location 107 at 5.5 miles 16 Figure 4 Indicator Location 190 at 5.9 miles 50 Figure 4 Indicator Location 93 at 8.2 miles 55 Figure 4 Indicator Location 95 at 9.0 miles 60 Figure 4 Indicator Lbcation 90 at 9.5 miles Figure 4 Indicator Location 113 at 7.8 miles 65~ Figure 4 Control Location 220 at 17.0 miles I

-120

TABLE 19 (Continued)

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

Food Products Figure 3 Indicator Location 84 at 1.6 miles Figure 3 Indicator Location 101 at 1.9 miles Figure 3 Indicator Location 114 at 1.5 miles Figure 3 Indicator Location 112 at 2.0 miles Figure 3 Control Location 225 at 12.6 miles N* Figure 3 Indicator Location 171 at 1.6 miles Figure 3 Indicator Location 141 at 1.9 miles Figure 3 Indicator Location 103 at 1.9 miles

-Technical Specification location.

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

-121

TABLE 20 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1987>

Location (b) of Type and Indicator Locations: Highest Annual Mean: Control Location: Number of Medium Number of M~ean f Location 0 M~ean f Masanf Nonroutine

~Un i ts A~nal ses L~LU a Ran e Ran e Ran e ~Re orts Shoreline G~SA 4 Sediment "

(pCi/kg-dry) Cs-134 150 <LLD <LLD <LLD Cs-137 180 <LLD <LLD <LLD Fish > G~SA 24 (pCi/kg-wet)

Mn-54 130 <LLD <LLD <LLD Fe-59 260 <LLD <LLD <LLD Co-58 130 <LLD <LLD <LLD Co-60 130 <LLD <LLD <LLD Zn-65 260 <LLD <LLD <LLD Cs-134 130 <LLD <LLD <LLD Cs-137 150 33 11/17 NMP: ~33 7/10 ~31 7/7 24-63 0.3 at 315 24-63 17-40

-122

TABLE 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 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1987>

Location (b) of Type and Indicator Locations: Highest Annual Mean: Control Location: Number of Medium Number of Masanf Location R M~ean f M~ean F Nonroutine

~no i ts A~nal ses LLD~a Ran e Ran e Ran e ~Re orts Surface S~SS Water "

(pCi/liter) H-3 2000(c) 322 4/4 SAR: ~322 4/4 210 4/4 160-410 0.5 at 70 160-410 140-270 G~SA 24 Mn-54 <LLD <LLD <LLD Fe-59 30 <LLD <LLD <LLD Co-58 <LLD <LLD <LLD Co-60 15 <LLD <LLD <LLD Zn-65 30 <LLD <LLD <LLD Zr-95 15 <LLD <LLD <LLD .0 Nb-95 15 <LLD <LLD <LLD I-131 15(c) <LLD <LLD <LLD

-123

TABLE 20 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 'ANNUAL

SUMMARY

NINE MII E POINT NUCLEAR STATION UNIT 1'OCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1987>

Location (b) of Type and Indicator Locations: Highest Annual Mean: Control Location: Number of Medium Number of M~ean f Location 6 M~ean f M~ean f Nonroutine

~Unite A~nal ses LLD a Ran e Ran e Ran e ~Re orts Surface Cs-134 15 <LLD <LLD <LLD Water >

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

Ba/La-140 15 <LLD <LLD <LLD Air Gross Beta: 0.01 0.021 52/52 0.021 52/52 Particolates* ~260 0.009-0.040 1.1 at 104 0.009-0.037 0.009-0.037 (pCi/m )

~I-131 260: 0.07 0.014 2/208 R-2 0.018 1/52 <LLD 0.011-0.018 1.1 at 104 0.018 GSA 60 Cs-134 0,05 <LLD <LLD <LLD Cs-137 0.06 <LLD <LLD <LLD

-124

TABLE 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 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 19&7>

Location (b) of Type and Indicator Locations: Highest Annual Mean: Control Location: Number oF Medium Number of M~ean f Location & M~ean f M~ean f Nonroutine

~un( ts A~nal ses L~LD a Ran e Ran e Ran e ~Re orts TLDA'mrem Gamma (d) 16.9 120/120 TLD// 85 ~38.5 4/4 (8) ~15.5 8/8 per D~ose 12S 10.4-42.4 0.2 at 294 35.6-42.4 13.8-17.4 quarterly period)

Milk" G~SA 126 (pCi/liter)

Cs-134 15 (e) (e) <LLD Cs-137 18 ~6.8 2/108 (i( Loca. 1t55 8.5(11/1& <<LLD 5.5-8.1 9.0 at 95 8.1 Ba/La-140 15 (e) (e) <LLD I-131 126 I-131 (e) (e) <LLD Food Frodncts* G~SA 19 (pCi/kg-wet)

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

Cs-134 60 <LLD <LLD <LLD Cs-137 80 <LLD <LLD <LLD

-125

TABLE 20 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAf

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1987>

Table Notes:

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.

(b) Location is distance in miles and direction in compass degrees based on NMP-2 reactor centerline. Units for this column are specified in medium column.

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

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

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

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

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

(g) = The results for TLD 1185 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.

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

(i) = All indicator locations had the same mean result. Location R-2 was used because this location had the highest mean result during 1986.

Cs-137 values are a result of the 1986 Chernobyl Nuclear Plant accident.

-126

TABLE 21 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHOREI INE SEDIMENT Cs-134 Cs-137 Co-60 Year (Min. Max. Mean) (Hin. Hax. Mean) (Min. Hax. Mean)

Location: Control(1) 1979 (2) LLD LLD LLD 0.22 0.22 0.22 LLD LLD LLD 1980 LLD LLD LLD 0.07 0.09 0.08 LLD LLD LLD 1981 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1982 LLD LLD LLD 0.05 0.05 0.05 LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD .LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD LLD LLD LLD 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.

-127

TABLE 22 HISTORICAL ENVIRONMENTAL SAMPf E DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 Year (Min. Max. Mean) (Min. Max. Mean) (Min. Max. Mean)

Location: Indicator (NMP)<1) 1979 LLD LLD LLD 0.15 0.15 0.15 LLD LLD LLD 1980 LLD LLD LLD 0.20 0.20 0.20 LLD LLD LLD 1981 LLD 'LD LLD 0.11 0.11 0.11 LLD LLD LLD 1982 LLD LLD LLD 0.07 .0.80 0.43 0.16 0.16 0.16 1983 0.09 0.09 0.09 0.16 1.81 0.94 0.14 0.36 0.25 1984 LLD LLD LLD 1.54 1.61 1.58 0.21 0.26 . 0.24 1985 LLD LLD LLD 1.00 1.81 1.40 0.11 0.18 0.15 1986 LLD LLD LLD 1.07 .1.07 1.07 0.10 0.10 0.10 1987 LLD LLD LLD 0.14 0.59 0.36 0,06 0.06 0.06 Location: Indicator (Sunset Ba )<2) 1979 (4) (4) (4) (4) (4) (4) (4) (4) (4) 1980 (4) (4) (4) (4) (4) (4) (4) (4) (4) 1981 (4) (4) (4) (4) (4) (4) (4) (4) <4) 1982 (4) (4) (4)'4)

(4) <4) (4) (4) (4) '4) 1983 (4) (4) <4) (4) (4) (4) (4) (4) 1984 (4) (4) (4) (4) (4) (4) (4) (4) (4) 1985 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD LLD LLD LLD Results in pCi/g -dry (1) Location was shoreline area near NMP-l.

(2) Location was off-site at Sunset Bay (closest location with recreational value).

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

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

-128

TABLE 23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 Year (Min. Max. Mean)

Location: Control(1) 1976 1.2 1.2 1.2 1977 0.13 0.13 0.13 1978 0.04 0.20 0 '9 1979 0.03 0.06 0.04 1980 0.03 0.11 0.06 1981 0.028 0.062 0.043 1982 0,027 0.055 0.046 1983 0.041 0.057 0.049 1984 0.015 0.038 0.032 1985 0.026 0.047 0.034 1986 0.021 0.032 0.025 1987 0.017 0.040 0.031 Results in pCi/g -wet (1) Control location was at an area beyond the influence of the site (westerly direction).

-129

TABLE 24 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 Year (Min. Max. Mean)

Location: Indicator (NMP/JAF) 1976 0.5 3.9 1.4 1977 0.13 0. 79 0.29 1978 0.03 0.10 0.08 1979 0.02 0.55 0.10 1980 0.03 0.10 0.06 1981 0.03 0.10 0.06 1982 0.034 0.064 0.048 1983 0.033 0.056 0.045 1984 0.033 0.061 0.043 1985 0.018 0.044 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 Results in pCi/g -wet Indicator locations are in the general area of the NMP-1 and J. A.

FitzPatrick cooling water discharge structures.

-130

TABLE 25 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE'ATER Cs-137 Co-60 Year (Min. Max. Mean) (Min. Max. Mean)

Location: . Control 1976 (3) (1) (1) (1) (1) (1) (1) 1977 (2) (2) (2) (2) (2) (2) 1978 LLD LLD LLD (2) (2) (2) 1979 2.5 2.5 2.5 LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD 1.4 1.4 , 1.4 1982 'LD LLD LLD LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD Results in pCi/liter (1) No gamma analyses performed (not required)

(2) Data showed instrument background results (3) Location was the City of Oswego Water Supply for 1976 1984 and the Oswego Steam Station inlet canal for 1985 1987

-131

TABLE 26 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Cs-137 Co-60 Year (Min. Max. Mean) (Min. Max. Mean)

Location: Indicator 1976 (1) (1) (1) (1) (1) (1) 1977 (2) (2) (2) (2) (2) (2) 1978 LLD LLD LLD (2) (2) (2) 1979 LLD LLD LLD LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD LLD LLD LLD 1982 0.43 0.43 0.43 1.6 2.4 1.9 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD Results in pCi/liter (1) No gamma analyses performed (not required)

(2) Data showed instrument background results (3) Location was J. A. FitzPatrick inlet canal

-132

TABl E 27 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Tritium Year (Min. Max. Mean)

Location: Control 1976 440 929 652 1977 300 530 408 1978 215 490 304 1979 174 308 259 1980 211 290 257 1981 211 328 276 1982 112 307 165 1983 230 280 250 1984 190 220 205 1985 230 370 278 1986 250 550 373 1987 140 270 210 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 1987

-133

TABLE 28 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Tritium Year (Min. Max. Mean)

Location: Indicator 1976 365 889 627 1977 380 530 455 1978 . 377 560 476 1979 ~

176 276 228 1980 150 306 227 1981 212 388 285 1982 194 311 266 1983 249 560 347 1984 110 370 280 1985 250 1200(2) 530 1986 260 500 380 1987 160 410 322 Results in pCi/liter (1) Indicator location is the FitzPatrick inlet canal.

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

-134

TABLE 29 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Gross Beta Year (Min. Max. Mean)

Location: Control 1977 0.001 0,484 0.125 1978 0.. 01 0.66 0.16 1979 0.010 0,703 0.077 1980 0.009 0.291 0.056 1981 0.016 0.549 0.165 1982 0.011 0.078 0 '33 1983 0.007 0.085 0.024 1984 0.013 0.051 0.026 1985 0.013 0.043 0.024 1986 0.008 0.272 0:039 1987 0.009 0.037 0.021 Results in pCi/m 1 (1) Locations used for 1977 1984 were C off-site, Dl off-site, D2 off-site, E off-site, F off-site and G off-site. Control location R-5 off-site was used for 1985 1987 (formerly C off-site location)

-135

TABLE 30 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Gross Beta Year (Min. Max. Mean)

Location: Indicator 1977 0.002 0.326 0.106 1978 0.01 0.34 0.11 1979 0.001 0.271 0.058 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0 '13 0.031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 Results in pCi/m (1) Locations used for 1977 1984 were D1 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site and K on-site, as applicable. 1985 1987 locations were R-1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

-136

TABLE 31 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 Year (Min. Max. Mean) (Min. Max. Mean)

Location: Control (2)

Preop. (1) (1) (1) (1) (1) (1) 1970 (1) (1) (1) (1) (1) (1) 1971 (1) .(1) (1) (1) (1) (1) 1972 (1) (1) (1) (1) (1) (1) 1973 (1) (1) (1) (1) (1) (1) 1974 (1) (1) (1) (1) (1) (1) 1975 (1) (1) (1) (1) (1) (1) 1976 (1) (1) (1) (1) (1) (1) 1977 0.0002 0.0112 0.0034 0.0034 0.0347 0.0172 1978 0.0008 0.0042 0.0018 0.0003 0.0056 0.0020 1979 0.0008 0.0047 0.0016 0.0005 0,0014 0 '009 1980 0.0015 0.0018 0.0016 LLD LLD LLD 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 0.0002 0.0009 0.0004 0.0004 0.0007 0.0006 1983 .0.0002 0.0002 0.0002 0.0007 0.0007 A) . 0007 1984 LLD LLD LLD 0.0004 0 '012 '0.0008 1985 'LD LLD LLD LLD LLD LLD 1986 0.0075 0.0311 0.0193 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD Results in pCi/m (1) No data available (not required prior to 1977)

(2) Locations included composites of off-site air monitoring locations for 1977 1984. Locations included R-5 air monitoring location for 1985 1987

-137

TABLE 32 NISTORXCAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 Year (Min. Max. Mean) (Min. Max. Mean)

Location: Indicator(

Preop. (1) (1) (1) (1) (1) (1) 1970 (1) (1) (1) (1) (1) (1) 1971 ,(1) (1) (1) (1) (1) (1) 1972 (1) (1) (1) (1) (1) (1) 1973 (1) (1) (1) (1) (1) (1) 1974 (1) (1) (1) (1) (1) (1) 1975 (1) (1) (1) (1) (1) (1) 1976 (1) (1) (1) (1) (1) (1) 1977 0.0001 0.0105 0.0043 0.0003 0.0711 0.0179 1978 0.0003 0.0026 0.0016 0.0003 0.0153 0.0023 1979 0.0003 0.0020 0.0010 0.0003 0.0007 0.0005 1980 0.0005 0.0019 0.0011 0.0016 0.0016 0.0016 1981 0.0002 0.0045 0.0014 0.0002 0.0017 0.0006 1982 0.0001 0.0006 0.0004 0.0003 0.0010 0.0005 1983 0.0002 0.0003. 0.0002 0.0003 0:0017 0.0007 1984 LLD LLD LLD 0.0007 0;0017 0.0012 LLD LLD ~

LLD LLD LLD LLD 1985'986 0.0069 0.0364 0.0183 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD Results in pCi/m3 (1) No data available (not required prior to 1977)

(2) Locations included composites of on-site air monitoring locations for 1977 1984. Locations included R-1 through R-4 air monitoring locations for 1985 1987.

-138

TABLE 33 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Iodine-131 Year (Min. Max. Mean)

Location: Control (1) 1976 0.01 5.88 ~ 0.60 1977 0.02'.03 0.82 0.32 1978 0.04 0.03 1979 LLD LLD LLD 1980 LLD LLD LLD 1981 LLD LLD LLD 1982 0.039 0.039 0.039 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0,041 0.332 0,151 1987 LLD LLD LLD Results in pCi/m (1) Locations Dl off-site, D2 off-site, E off-site, F off-site and G off-site used for 1976 1984. Location R-5 off-site used for 1985 1987.

TABLE 34 HISTORICAL ENVIRONMENTAL. SAMPLE DATA AIR RADIOIODINE Iodine 131 Year (Min. Max. Mean)

Location: Indicator(

1976 0.01 2.09 0.33 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 1979 LLD LLD LLD 1980 0.013 0,013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.042 0.016 1983 0.022 0.035 0.028 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0.023 0.360 0 '19 1987 0.011 0.018 0.014 Results in pCi/m (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 1987 were Rl off-site, R-2 off-site, R-3 off-site and R-4 off-site.

-140

TABLE 35 HISTORICAl. ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)

Year (Min. Max. Mean)

Location: Control(2)

Preop (1) (1) (1) 1970 6.0 7.3 6.7 1971 2.0 6.7 4.3 1972 2.2 6.2 4,4 1973 2.2 6.9 4.7 1974 2.7 = 8.9 5.6 1975 4.8 6.0 5.5 1976 3.2 7' 5.4 1977 4.0 8.0 5,3 1978 3' 4.7 4.3 1979 3.3 5.7 4.7 1980 3.8 5.8 4.9 1981 3.5 5.9 4.8 1982 3.8 6.1 5.1 1983 4.9 7.2 5.8 1984 4.7 8.2 6.2 1985 4.5 (4.4)< 7.6 (6.8)" 5.6 (5.4)'4 1986 5.3 (5.5)< 7.5 (7.2)" 6.3 (6.3)A'.4 1987 4.6 (4.6)< 6.6 (5.8)A (5.2)'4 Results in mrem per standard month (1) Data not available r (2) TLD 88, 14, and 49, where applicable

( )< TLD result based on the Technical Specification required locations (TLD fC14 and 49).

-141

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

Year (Min. Max. Mean)

Location: Site Boundar Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) <1) (1) 1980 (1) (1) (1) 1981 (1) <1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.1 12.6 6.2 1986 4.4 18.7 7.0 1987 4 ~4 14.3 6.1 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 75, 76, 77, 23, 78, 79, 80, 81, 82, 83, 84, 7, 18, 85, 86 and 87

-142

TABLE 36B

'HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)

Year (Min. Max. Mean)

Location: Off-Site Sectors(2)

Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 19.76 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.0 7.1 5,0 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 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.

-143

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

Year (Min. Max. Mean)

Location: S ecial Interest(2)(

Preop (1) (1) (1) 1970 (1) (1) (1)

~

1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) ~

(1) 1983 (1) (1) (1)

'1984 (1) (1) ~ (1) 1985 3.9 6.8 5.3 1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 Results in mrem per standard month (1) No data available (not required prior to 1985).

(2) TLD locations initiated in 1985 as required by 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.

-144

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

Year (Min. Max. Mean)

Location: On-Site Indicator(

Preop (1) (1) (1) 1970 4.7 9.0 6.0 1971 1.5 7.7 4.7 1972 2' 8.2. 4.9 1973 3.0 24.4 6.6 1974 3.1 10.6 5.7 1975 4.6 16.0 7.3 1976 3.7 18.8 6.9 1977 3.0 15.3 5.7 1978 3.0 9.0 4.3 1979 2.7 8.3 4.3 1980 3.9 12.0 5.3 1981 4.1 11.8 5.8 1982 3.9 13.0 6.3 1983 5.0 16.5 6.9 1984 4.6 13.2 7.0 1985 4.7 15.9 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 .5.8 Results in mrem per standard month (1) No data available.

(2) Includes TLD numbers 3, 4, 5, 6, and 7 only (1970 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26 (1974 1987) ~

(on-site environmental air monitoring locations).

/

-145

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

Year (Min. Max. Mean)

Location: Off-Site Indicator(2)

Preop (1) (1) (1) 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974 2.4 8.9 5,3 4.5 7.1 5 .'5 1975 1976 3.4 7.2 5.2 1977 3.7 8,0 5.3 1978 2.7 4.7 3,7 1979 3.0 5.7 4.0 1980 3.1 5.8 4.6 1981 F 6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 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.

-146

TABLE 37 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 Year (Min. Max. Mean) (Min. Max. Mean)

Location: Control(2) 1976 (1) (1) (1) (1) (1) (1) 1977 (1) (1) (1) (1) (1) (1) 1978 2.4 7.8 5.8 LLD LLD LLD 1979 LLD LLD LLD LLD LLD LLD 1980 3.6 5.6 4.5 1.4 1.4 1.4 1981 3.9 3.9 3.9 LLD LLD LLD 1982 LLD LLD LLD LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD 'LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 5.3 12.4 8.4 0.8 29.0 13.6 1987 J LD LLD LLD LLD LLD LLD Results in pCi/liter (1) No data available (no samples collected)

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

-147

TABLE 38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 Year (Min. Max. Mean) (Min. Max. Mean)

Location: Indicator(1) 1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 11.0 22.0 17.1 0.01 49.00 6.88 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 3.2 53.0 9.4 LLD LLD LLD 1980 3.2 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1983 3.3 10.9 7.2 LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 8.1 6.8 LLD LLD LLD Results in pCi/liter (1) Locations were available downwind locations within ten miles with high deposition potential.

-148

TABLE 39 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 Year (Min. Max. Mean)

Location: Control(

1976(3> (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1> (1) 1980 0.02 0.02 0.02 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985(4> LLD LLD LLD 1986 LLD LLD LLD 1987 LLD LLD LLD Results in pCi/g (wet)

(1) No data available (control samples not collected)

(2) Location was an available food product sample location in a least prevalent wind direction greater than ten miles from the site (3) Data comprised of broadleaf and non-broadleaf vegetation.

(4) Data comprised of broadleaf vegetation only.

-149

TABLE 40 HlSTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 Year (Min. Max. Mean)

Location: Indicator(

1976(2) LLD LLD LLD 1977 LLD LLD LLD 1978 LLD LLD LLD 1979 0.004 0.004 0.004 1980 0 '04 0.060 0.036 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985(>> 0.047 0.047 0.047 1986 LLD LLD LLD 1987 LLD LLD LLD Results in pCi/g (wet)

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

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

(3) Data comprised of broadleaf vegetation only.

-150

QSRs 24 WENO

~

. JEEFEEEC J

~ \ andy C tools FIGURE IA OFF-SITE ENVIRONMENTAL STATION AND TLD MCATIONS Y A N D J

C R E 9 9

4 SCALK OF MILKS LEO END LA R'E 10 MI 55 Plalteal o ENVIRONMENT STATION AND TLD LOCATION 09 ONTARIO 5cee tpe nep TLD LOCATION 07 05 0 ldemos emote n ~I 0 H 0 1

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6 fIGURE 2 WIN, ~III II'p OiV-SITE EIIVIROliblETVTAL STATIOiV AiVD TLD SII LOCATIOiVS Environ60enta1 Station TLD Location III%00.000IT 000 I 000 Ihhll 0 000 I ~ H!I A

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-153

SCALE OF MILES Senal Saaeel Stare Pwa

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I h(ILK ANlh!AL CFNSUS AND II ~ MW Nl Lk SAhUILE LOCATIONS NMP wnso Pass WM;O dey doesn Wse deal

~ leasaal iss4so (ll~ (Oe IES I

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R ~~A~N I ~~

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FIGURE 5 NEi'$ YORK STATE MAP Lake Qnta<'o U~

ROCHESTER ~ UTICA SYRACUSE BUFFALO ALBANY'EW YORK Nine Mile Point Nuclear Station Unit I Nine Mile Point Nuclear Station Unit 2 James A'. FitzPatrick Nuclear Pov or Plant NEW YORK CITY

-156

ML18038A394

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