ML18041A025

Annual Radiological Environ Operating Rept 1993 for Nine Mile Point Nuclear Station Units 1 & 2. W/940428 Ltr

ML18041A025
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1993
From:	Abbott R, Mueller J NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9405040061
Download: ML18041A025 (219)

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kCCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9405040061 DOC.DATE: 9$ )6~9+ 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 ABBOTT,R.B. Niagara Mohawk Power Corp.

MUELLER,J.H. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION e

"Annual Radiological Environ Operating Rept for

SUBJECT:

Mile Point Nuclear Station Units 1 6 2." W/ 4042 ltr.Nine D DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per Tech Specs) g ENCL ~ SIZE: /

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-1 LA 3 3 PD1-1 PD 1 1 BRINKMAN,D. 1 1 MENNING,J 1 1 D INTERNAL: AC 1 1 NRR/DRS S/PRPB1 1 2 2 R G FILE 01 1 1 RGN1 DRSS/RPB 1 1 R ILE 02 1 1 EXTERNAL EG&G AKERS E D 1 1 NRC PDR 1 1 g I( Phg~

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUIV!ENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL

0 7 NIAGAR~

U MOHAWK, .

NINE MILE POINT NUCLEAR STATION/P,O. BOX 63. LYCOMING. NEW YORK 13093/TELEPHONE (315) 343.21)0 April 28, 1994 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 RE: Nine Mile Point Nuclear Station Unit 1 Docket No. 50-220 Facility Operating License DPR-63 Nine Mile Point Nuclear Station Unit 2 Docket No. 50-410 Facility Operating License NPF-69

SUBJECT:

Transmittal of 1993 Annual Radiological Environmental Operating Report Gentlemen:

In accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2, we are enclosing the Annual Radi lo ical Environmental 0 eratin Re ort for the period January 1, 1993, through December 31, 1993.

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

Eui:w/ 98M~'

Richard B. Abbott J n H. Mueller Plant Manager, Unit 1 Plant Manager, Unit 2 ipse (ANNUALRP.93)

Enclosure pc: Mr. T. T. Martin, Regional Administrator, Region 1 Mr. B. S. Norris, Senior Resident Inspector Mr. R. A. Capra, Director, Project Directorate I-l, NRR Mr. D. S. Brinkman, Senior Project Manager, NRR Mr. J. E. Menning, Project Manager, NRR Records Management 9405040061: 931231 ',

PDR, ',ADQCK 05000220','

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NIAGARA. MOHAWKPOWER CORPORATION AI'PlUALRADIOLO I AL EIAMONMENTALOPERATING REPORT January 1, 1993 - December 31, 1993 for NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket Number 50-220 NIM': MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410 9405040061

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TABLE OF CONTENTS Pacae LIST OF TABLES LIST OF FIGURES

1.0 INTRODUCTION

2.0 AQUATIC SAMPLES I Shoreline Sediment II Fish III Surface Water 12 3.0 DIRECT RADIATION 16 4.0 TERRESTRIAL SAMPLES 23 I Air Particulate/Iodine 24 II Milk 30 III Food Product IV Land Use Census 35 5.0 INTERLABORATORY COMPARISON PROGRAM 37 6.0 HISTORICAL ENVIRONMENTAL SAMPLE DATA 39 7.0 CHANGES AND EXCEPTIONS TO THE PROGRAM 41

8.0 CONCLUSION

44 9.0 GENERAL REFERENCE MATERIAL 46 10.0 DATA TABLES 1993 49 11.0 FIGURES 143

.LIST OF TABLES Table No. Content . Pacae I Table 1 Sample Collection and Analysis, Site Radiological Environmental Monitoring i Program Aquatic Program and Direct Radiation 50 Table 2 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Terrestrial Program 51 Table 3 Environmental Sample Locations 52 Table 4 Radiological Environmental Monitoring Program Annual Summary 56 Table 5A Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/g-dry) 59 Table 5B Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/kg-dry) 60 Table 6A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 61 Table 6B Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet) 63 Concentration of Gamma Emitters in Surface Water Samples 65 Table 8 Concentration of Tritium in Surface Water Samples 70 Table 9A Direct Radiation Measurement Results-mrem/Standard Month 71 Table 9B Direct Radiation Measurement Results-mrem/Quarterly Period 75 Table 10 Environmental Airborne Particulate Samples-Offsite Stations, Gross Beta Activity 79 Table 11 Environmental Airborne Particulate Samples-Onsite Stations, Gross Beta Activity 81 Table 12 Concentration of Gamma Emitters in Air Particulate Samples 83 Table 13 Environmental Charcoal Cartridge Samples-Offsite Stations, I-131 Activity 98

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LIST OF TABLES (Continued)

Table No. Content Pacae t Table 14 Environmental Charcoal Cartridge Samples-Onsite Stations, I-131 Activity 100 Table 15 Concentration of Gamma Emitters in Milk 102 Table 16 Concentration of Iodine-131 in Milk 108 Table 17A Concentration of Gamma Emitters in Food Products (pCi/g-wet) 109 Tabl'e 17B Concentration of Gamma Emitters in Food Products (pCi/kg-wet) 110 Table 18 Milk Animal Census Table 19 1993 Residence Census 113 Table 20 Interlaboratory Comparison Program Results 114 Table 21 Historical Environmental Sample Data Shoreline Sediment (Control) 119 Historical Environmental Sample Data Shoreline Sediment (Indicator) 120 Table 23 Historical Environmental Sample Data Fish (Control) 121 Table 24 Historical Environmental Sample Data Fish (Indicator) 122 Table 25 Historical Environmental Sample Data Surface Water (Control) 123 Table 26 Historical Environmental Sample Data Surface Water (Indicator) 124 Table 27 Historical Environmental Sample Data Surface Water Tritium (Control) 125 Table 28 Historical Environmental Sample Data Surface Water Tritium (Indicator) 126

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LIST OF TABLES (Continued)

Table No. Content Pacae Table 29 Historical Environmental Sample Data Environmental TLD (Control) 127 Table 30 Historical Environmental Sample Data (A- E) Environmental TLD (Indicator) 128 Table 31 Historical Environmental Sample Data Air Particulates Gross Beta (Control) 133 Table 32 Historical Environmental Sample Data Air Particulates Gross Beta (Indicator) 134 Table 33 Historical Environmental Sample Data Air Particulates (Control) 135 Table 34 Historical Environmental Sample Data Air Particulates (Indicator) 136 Table 35 Historical Environmental Sample Data Air Radioiodine (Control) 137 Table 36 Historical Environmental Sample Data Air Radioiodine (Indicator) 138 Table 37 Historical Environmental Sample Data Milk (Control) 139 Table 38 Historical Environmental Sample Data Milk (Indicator) 140 Table 39 Historical Environmental Sample Data Food Products (Control) 141 Table 40 Historical Environmental Sample Data Food Products (Indicator) 142

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I. 4 LIST OF F GURES le Figure 1 - . Nearest Residence, Content Food Product,

'Shoreline Sediment Sample Locations Fish and Pacae 144 Figure 2 Milk Animal Census, Milk Sample and 145 Surface Water Sample Locations Figure 3 Off-site Environmental Stations and TLD 146 Locations Figure 4 On-site Environmental Station and TLD 147 Locations Figure 5 New York State Map 148 l

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1.0 INTR D CTI N Le

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1~0 INTRODUCTION This report is submitted in accordance with Appendix A (Technical Specifications), Section 6.9.1.d to License DPR-63, Docket No. 50-220 for the Nine Mile Point, Nuclear Station Unit 1 and Section 6.9.1.7 to License NPF-69, Docket No. 50-410 for the Nine Mile Point Nuclear-Station Unit 2 for the calendar year 1993.

The Radiological Environmental Monitoring Program (REMP) is a joint program between the Nine Mile Point Nuclear Station (NMPNS) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP). The sample collections for the radiological programs are performed in large part by EA Engineering Science and Technology (EA). EA also performs the sampling required for the Station's SPDES Permit. The same staff from EA is utilized to perform the majority of terrestrial and aquatic sampling required for the REMP. In-plant canal water sampling, air sample collection, and environmental TLD collections are performed .-

jointly by the NMPNS and JAFNPP staffs.

The present sample collection and analysis schedule required by the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1 and 2 is listed in Table 1 and 2.

The REMP samples were analyzed by Teledyne Isotopes and by the Site Environmental Laboratory during 1993. The following samples were analyzed by the Site Environmental Laboratory:

Shoreline sediment (gamma spectral analysis)

Fish (gamma spectral analysis)

Lake water (monthly gamma spectral analysis only)

Air particulate filter (weekly gross beta analysis)

Air particulate filter (monthly gamma spectral analysis)

Airborne radioiodine cartridge (weekly gamma spectral analysis)

Milk (gamma spectral and radioiodine analysis)

Food products (gamma spectral analysis)

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

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

I There were four separate groups of radionuclides that were detected in the environment during 1993. Several radionuclides could possibly fal'l into two of the four groups. The first of these groups is naturally occurring radionuclides. It must be realized that the environment

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I.'0 INTRODUCTION 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 of thermonuclear devices in the earth's upper atmosphere. the'etonation The detonation frequency during the early 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on atmospheric weapons testing in 1963 which greatly reduced the inventory through the decay of short lived radionuclides, deposition, and the removal (by natural processes) of radionuclides from the food chain. Since 1963, several tests have been conducted by the People's Republic of China. In atmospheric'eapons each case, the usual radionuclides associated with nuclear detonations were detected several months afterwards, and after a peak detection period, diminished to a point where most could not be detected. The last such weapons test was conducted in October of 1980. The resulting fallout or deposition from this test had influenced the background radiation in the vicinity of the site and was very evident in many of the sample media analyzed during 1981. Calculations from 1981 of the resulting doses to man from fallout related radionuclides in the environment show that the contribution from such nuclides (such as Sr-90 i or Cs-137) was significant and second in intensity only to natural background radiation. Quantities of Nb-95, Zr-95, Ce-141, ,Ce-144, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and, Co-60 were typical in air particulate samples during 1981 and have a weapons test origin. During 1993, Cs-137 and H-3 were the only radionuclides detected in environmental samples that had a weapons testing origin.-

The third group of radionuclides includes those that were a result of the Chernobyl Nuclear Plant accident. These radionuclides were first detected in May of 1986 and were found in samples of air particulates, air radioiodine and milk. Applicable radionuclides include I-131, Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, and La-140. Cs-137 was the only radionuclide in this category that could have contributed to the total amount of Cs-137 detected during 1993.

The fourth group of radionuclides are those that could be related to.

operations at the site. Many of these radionuclides are a by-product of both nuclear detonations and the operation of light water reactors.

Therefore, making a distinction between the two sources can be difficult, if not impossible. During 1993, no radionuclides were detected at Technical Specification required locations that would fall into this category.

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 1993, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. It is important to note that detected concentrations of radionuclides that are possibly

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1' INTRODUCTION related to operations .at the site are very small and are not an indication of environmental significance. In regards to these very small quantities, concentrations it will be further noted that at such minute the assessment of the significance of detected radionuclides is very difficult. Therefore, concentrations in one sample that are two times the concentration of another, for example, are not significant overall. Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in another because of counting statistics at such low concentrations.

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

Background gamma radiation around the Nine Mile Point Site, as a result of radionuclides in the atmosphere and the ground, accounted for approximately 50 mrem during 1993. 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 50 mrem, as a i background dose, is significantly greater than any possible dose as a result of operations at the site during 1993.

Environmental Sam le Locations Table 3 Table 3 contains the locations of the environmental samples presented in the data tables. The locations are given in degrees and distance from the Nine Mile Point Nuclear Station Unit 2 reactor centerline.

Table 3 also gives the figure (map) number as well as the map designation for each sample location by sample medium type. The requirement for Table 3 is found in Section 6.9.1.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.

Radiolo ical Environmental Monitorin Pro ram Annual Summar Table 4 Table 4 contains a summary of basic statistics for environmental sample media as required by the Technical Specifications. Table 4 is in the format presented on Table 3 of the NRC Branch Technical Position (Revision 1 dated November 1979) to NRC Regulatory Guide 4;8 "Environmental Technical Specifications for Nuclear Power Plants". The table is presented to meet the requirements of Section 6.9.1.d and Section 6.9.1.7 of the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2 respectively.

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I ~, SHORELINE SEDIMENT A. 'am le Collection f'I Methodolo N

A UATIC 'SAMPLES and Anal sis Shoreline sediment samples are collected twice per year from one area of existing or potential recreational value and from one area beyond the 'nfluence 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 per year. All samples are shipped and analyzed for 'wice gamma emitters at the Site Environmental Laboratory. Optional samples may be collected from .other shoreline locations at. or-near the site. 'la Shoreline sediment locations are shown on Figure 1 (refer to Table 3 for location designations and descriptions).

B. Evaluation of Shoreline Sediment Data Tables 5A and 5B Shoreline sediment samples were obtained in April and October of 1993 at one off-site control location (near Oswego Harbor) and in May and October of 1993 at one indicator location (shoreline area with recreational value just east of the site) .

The results of the shoreline sediment samples collec'ted during 1993 at the indicator and control locations are shown on Tables 5A and 5B. Table 5A shows results in units of pCi/g (dry) for purposes of data evaluation. Table 5B shows results in units of pCi/kg (dry), as required by the Technical Specifications. Only the Sunset Beach location was required by the Technical Specifications during 1993.

Several radionuclides were detected in sediment samples using gamma spectral analysis. K-40 was detected at both the control location and indicator location for both collection periods during 1993. K-40 is a naturally occurring primordial radionuclide. In addition to K-40, Ra-226 and AcTh-228 were also detected in control and indicator samples and are also.

naturally occurring radionuclides.

Cs-137 was detected once at the control location during 1993 at a concentration of 0.03 pCi/g (dry). Cs-137 was detected twice at the indicator location at concentrations ranging from 0.17 to 0.49 pCi/g (dry). Cs-137 has been detected each year since 1989 at the indicator location at concentrations ranging from 0.10 to 0.34. Cs-137 had not been detected prior to 1989 I (1985 1988). Although the control location did not contain a detectable concentration of Cs-137 during 1992, it had been detected intermittently in the past (1979, 1980, and 1982).

Detectable control location quantities ranged from 0.05 to 0.22 pCi/g (dry).

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A UATIC SAMPLES.

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SHO RELINE SEDIMENT (Cont'd)

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Evaluation of Shoreline Sediment Data-Tables 5A and 5B(Ctat'd) n The source.; of Cs-137 in 1993 indicator shoreline sediment samples is difficult to determine. Possible sources are fallout from past weapons or from site operations; It is highly probable that the Cs-137 is from fallout. Cs-137 has been detected in the past at control locations beyond the influence of the site as well as from the control location during 1993. Due to the fact that few shoreline regions west of the site contain fine sediment and/or sand, it is difficult to obtain control samples which are comparable to the physical and chemical characteristics of the indicator samples. Other factors, which include changing lake level and. shoreline erosion, further complicate any consistency in shoreline sediment sampling. Soil samples in areas which are likely to be affected by plant operations, as well as soil beyond any influence from the site, all contain levels of Cs-137 at or greater than the concentration found in 1993 shoreline sediment. Cs-137 in soil samples has been attributed to weapons testing fallout. The indicator location, unlike the control location, is very close to eroding ground areas and is ie believed to contain soil residues. Therefore, any sample containing soil would reveal Cs-137.

factors support the likelihood that the trace amounts of Cs-137 detected in the indicator shoreline sediment samples is due to fallout from past weapons testing.

shoreline'ediment These Using Regulatory Guide 1.109 methodology, and conservatively assuming that the maximum exposed individual (adult or teenager) would spend approximately 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year at this location, a conservative dose due to Cs-137 was calculated to be 0.001 mrem to the whole body and 0.001 mrem to the skin.

These doses are very small when compared to average annual whole body doses due to natural background and may be considered insignificant. For the purpose of comparison, soil sampled at a location beyond any influence of the site contained Cs-137 at a concentration of 0.61 pCi/g. Using the.

same methodology and assumptions for that of sediment, an annual whole body and skin doses of 0.002 mrem were calculated. Thus, it is shown that a dose to an individual at the shoreline is less than an individual would receive from soil.. Both doses may be considered insignificant.

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

I Tables 21 and 22 show historical environmental data for shoreline sediment samples. Shoreline sediment samples at the indicator were not collected prior to 1985.

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2 ' A UATIC SAMPLES FISH Sam le Collection Methodolo and Anal sis Available fish species are obtained from collections during the spring and fall. Samples are collected from two of four possible on-site sample transects located in the vicinity of the site discharge points and one off-site sample transect.

Available species are selected under the following guidelines:

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

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

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

Fish sample transects are shown on Figure 1 (refer to Table 3 for location designations and descriptions).

Evaluation of Fish Data Tables 6A and 6B A total of twenty-seven fish samples were analyzed as a result of collections in the spring season (June 1993) and in the fall season (September 1993). 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

¹1 (02), and the James A. FitzPatrick (03) generating facilities. The Oswego Harbor samples (00) served as control samples while the NMP (02) and JAF (03) samples served as indicator samples. Samples were analyzed for gamma emitters..

Table 6A shows results in units of pCi/g (wet) for purposes of data evaluation. Table 6B shows results in units of pCi/kg (wet), as required by the Technical Specifications.

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

Cs-137 was detected in three of the eight indicator samples and in one of the five control samples collected during the

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'2 0 A VATIC SAMPLES FISH (Cont'd)

Evaluation of Fish Data - Tables 6A and 6B Cont'd spring. Cs-137 :concentrations in indicator and control samples were approximately equal, and are considered to be representative of background concentrations. The concentration in smallmouth bass was 0.026 pCi/g (wet) detected's-137 at one indicator sample, location. Cs-137 was not detected in control samples of smallmouth bass. Cs-137 in lake trout was 0.029 pCi/g (wet) at one indicator location. Cs-137 was not detected in the control sample of lake trout. Cs-137 was detected in- an indicator sample of walleye at a concentration of 0.035 pCi/g (wet) and in the control walleye sample at a ."

concentration of 0.041 pCi/g (wet). Cs-137 was not detected in any of the other indicator or control location fish samples.

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. Ra-226, also naturally occurring, was detected intermittently in both indicator and control samples. No other radionuclides were detected in the spring fish samples.

Fall fish sample collections were comprised of five separate species and fourteen individual samples. Brown trout, smallmouth bass, white sucker, walleye, and Chinook salmon samples were collected at indicator sampling locations (NMP and JAF). At the control location (Oswego Harbor), white sucker, brown trout, walleye, Chinook salmon, and smallmouth bass samples were collected.

Cs-137 was detected in six of the fourteen samples which included the control samples. Indicator samples showed an average Cs-137 concentration that was slightly greater than the control sample mean from the off-site location. The detected concentrations were not significantly different from one another because of the extremely small quantities detected. Cs-137 in samples at the indicator locations ranged.

from 0.021 to 0.038 pCi/g (wet) and was 0.023 pCi/g (wet) at a control location.

Cs-137 was detected in Chinook salmon sampled at NMP and JAF at concentrations of 0.021 and 0.038 pCi/g (wet) respectively.

Cs-137 was detected in Chinook salmon collected at the control location (Oswego Harbor) at a concentration of 0.023 pCi/g (wet). The concentration of Cs-137 in walleye sampled at NMP and JAF was 0.029 pCi/g (wet) at both locations. Cs-137 was not detected in the control sample of walleye. Smallmouth bass sampled at the JAF location contained a concentration of 0.032 pCi/g (wet). Cs-137 was not detected in the NMP or

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2 ' A UATIC SAMPLES FISH (Cont'd)

Evaluation of Fish Data Tables 6A and 6B Cont'd control samples of smallmouth bass. Brown trout samples collected at indicator and control locations did not reveal any detectable concentrations of Cs-137.

Naturally occurring K-40 was detected in all of the fall samples collected. Ra-226, also naturally occurring, was detected intermittently in the control samples and in all of the indicator samples. -No other radionuclides were detected in the fall fish samples.

Review of past environmental data indicates that the mean annual Cs-137 concentration has decreased significantly from the 1976 through 1993 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 0.026 pCi/g (wet) in 1992.

The mean concentration of Cs-137 in indicator samples during 1993 was 0.030 pCi/g (wet). Control sample results have also decreased from a level of 1.2 pCi/g (wet) in 1976 to a level of 0.022 pCi/g (wet) in 1992. The mean concentration of Cs-137 in control samples during 1993 was 0.032 pCi/g (wet).

Results from 1980 to 1986 have shown a fairly consistent decreasing trend for control and indicator samples. During 1987 through 1993, control and indicator mean results increased slightly when compared to 1986.

The general decreasing trend for Cs-137 is most probably a result of ecological cycling. The concentrations of Cs-137 detected since 1976 in fish are a result of weapons testing fallout, and the general downward trend in concentrations will continue as a function of ecological cycling and nuclear decay. There was no significant effect from the 1986 Chernobyl Nuclear Plant accident during 1986 relative to Cs-137 results in fish samples although an effect may have been detected during the period of 1987 through 1991 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 fish in the local diet, a reasonable conservative estimate of dose to man can be calculated. Assuming that an adult consumes 21.0 kg of fish per year (Regulatory Guide 1.109 maximum exposed age group) 10

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

B. Evaluation of Fish Data Tables 6A and 6B Cont'd and the fish consumed contains an average Cs-137 concentration of 0.030 pCi/g (wet) (annual mean result of indicator samples for 1993), the adult whole body dose received would be 0.045 mrem per year. The critical organ, in this case, is the teen liver which would receive a calculated dose of 0.072 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 (16 kg per year for a teen and 21 kg per year for an adult) but the average annual Cs-137 concentration for the control samples is 0.032 pCi/g (wet).

The calculated Cs-137 adult whole body dose is 0.076 mrem per I year and the associated dose to the teen liver is 0.048 mrem per year. In this case, the fish from the control location i resulted in doses which were higher than that from the indicator location (near the nuclear facilities). The control location is located beyond any influence of the site. This strongly suggests that any Cs-137 detected in fish samples is due to weapons testing fallout and not due to plant operations. i 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 control sample fish are slightly greater, although well within natural variability. For example, the whole body and organ doses from the indicator samples were greater during 1990 and 1992.

Doses from both sample groups are considered background doses and negligible.

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I 2 ' "A VATIC 8AMPLE8 III SURFACE WATER A. Sam le Collection Methodolo and Anal sis Surface water samples are taken from the respective inlet canals of the J.A. FitzPatrick facility and Niagara Mohawk s Oswego Steam Station'. The FitzPatrick facility removes water from Lake Ontario on a continuous basis and generally represents a "down-current" sampling point from the Nine Mile Point Unit 1 and Unit 2 facilities. The Oswego Steam Station inlet canal removes water from Lake Ontario at a point 7.6 miles west of the site. This "up-current" 'pproximately 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 nearby (see Figure 2).

River..'ocated Samples from the FitzPatrick facility are composited from automatic sampling equipment which discharges into a compositing tank. Samples are obtained from the tank monthly and analyzed for gamma emitters. Samples from the Oswego Steam Station are also composited from automatic sampling equipment which discharge to a compositing tank. Samples from this location are obtained weekly and are composited to form monthly composite samples. Monthly samples are analyzed for gamma emitters.

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

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

Sampling for ground water and drinking water, as found in Section 3.12.1 of the Nine Mile Point Unit 2 Technical Specifications, was not required during 1993 because these pathways were not applicable to the Site during the year.

Applicable sampling requirements and conditions are presented in the Unit 2 Off-Site Dose Calculation Manual.

Surface water sample locations are shown on Figure 2 (refer to ie Table 3 for location designations and descriptions).

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III SURFACE WATER 4

(Cont'd) ......:,-~; a i

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.B. Evaluatio of'ata Tables 7 and 8

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Surface water samples were analyzed monthly for gamma emitters (using gamma spectral analysis) 'during 1993;=

Tritium analyses wer'e performed quarterly. Quarterly =

samples (i.e., analysis for tritium) were composite samples.

The analytical results for the 1993 surface water samples showed no evidence of plant related radionuclide buildup in the surface water in the vicinity of the site. Indicator samples were collected from the inlet canal at the James A.

FitzPatrick facility. The control location samples were collected at the inlet canal of Niagara Mohawk's Oswego Steam Station. These two locations are required to be sampled by the Technical Specifications. Tables 7 and 8 show the results of surface water s'amples analyzed during 1993.

Gamma spectral analysis was performed on twenty four monthly composite samples (two locations) required 'by the Technical Specifications. .In addition, three optional sample locations were evaluated. These included the Nine Mile Point Nuclear Station Unit 1 and Unit 2 inlet canals and the City of Oswego drinking water supply. The drinking water supply composite samples consisted of twice per week grab samples. Only two radionuclides were detected in samples from the five locations over the course of 1993. Both radionuclides were naturally occurring. K-40 was detected consistently in both indicator and control samples. Ra-226 was detected intermittently in samples from all five locations.

Tritium samples are quarterly samples that are a composite of the appropriate calendar months. Tritium was detected in all samples taken at all five locations. The City of Oswego drinking water showed tritium concentrations ranging from 180 to 230 pCi/liter with a mean of 212 pCi/liter. Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 200 to 280 pCi/liter and showed a mean concentration of 242 pCi/liter. Inlet canal samples taken at Nine Mile Point Unit 1 and Unit 2 showed tritium concentrations ranging from 160 to 320 pCi/liter and 200 to 330 pCi/liter respectively. The annual mean concentration was 212 pCi/liter and 242 pCi/liter respectively. At the Technical Specification control location (Oswego Steam Station inlet canal), tritium was detected at concentrations ranging from 160 to 230 pCi/liter and a mean of 188 I pCi/liter.

Previous annual mean results for tritium at the indicator sample location (FitzPatrick inlet canal) have generally decreased since 1976. Mean sample results reviewed from 13

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2 '

t III SURFACE WATER (Cont'd)

Evaluation of Data Tables 7 and (Cont'd) t B.

1976 through 1992 showed a peak 8

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 1993 was 242 pCi/liter.

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

Historical mean annual tritium results from previous city water samples (1976-1984) and Oswego Steam Station samples (1985-1991) show that the tritium concentrations have decreased. The maximum annual average was found in 1976 (652 pCi/liter) and the minimum in 1982 (165 pCi/liter).

s Mean annual results from 1979 to 1991 have remained relatively consistent. The Oswego Steam Station annual mean result for 1993 was 188 pCi/liter.

The impact of tritium in water to members of the public is minimal. This can be evaluated by calculating a dose to the whole body and maximum organ. Using Regulatory Guide 1.109 methodology, ingestion of water at the indicator location would result in a dose of 0.025 mrem to the whole body and 0.025 mrem to the child liver. The doses at the control location were 0.019 mrem whole body and '0.019 mrem to the child liver. Drinking water sampled in Oswego is drawn from Lake Ontario at a location more distant that the control location. Doses from tritium at this location were 0.022 mrem to the whole body and 0.022 mrem to the child liver.

Doses received as a result of water ingestion are approximately the same. The theoretical dose received from the indicator location was slightly higher, although well within natural variability. For example, the whole body and organ doses from control samples were greater during 1991.

Doses from all water sampled are considered background doses and are negligible.

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

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2. D A VATIC SAMPLES III SURFACE WATER (Cont'd) i B. Evaluation of Data Tables 7 and 8 (Cont'd)

Review of past environmental data for Cs-137 from 1979 through 1992 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 1982 at a inlet canal) was detected only once during control concentration of 0.43 pCi/liter. The 1979 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 1993 in surface water samples.

Other plant related radionuclides detected during a review period of 1979 1992 include only Co-60. The control sample location results'howed that Co-60 was detected once in 1981 (the May composite sample). This result is suspect and, as noted above, may be a result of contamination during handling or may be instrument background. This result was 1.4 pCi/liter. Results from the indicator location showed that Co-60 was detected three times during 1982 and averaged 1.9 pCi/liter. These positive results were attributed to inlet canal tempering and instrument background. Co-60 was not detected during 1993 in surface water samples.

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

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3.0 DIRECT RADIATION 16

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

Control TLD's accompany the TLD's when they are being placed or collected and are shielded by lead when they are not being used.. TLD data results are corrected for a transit dose by use of the data from shipment control TLD's.

Five different types of areas are evaluated by environmental TLD's. These areas include on-site areas (areas within the site boundary not required by the Technical Specifications),

the site boundary area in each of the sixteen meteorological sectors, an outer ring of TLD's located four to.five miles from the site in eight available land based meteorological sectors, special interest TLD's located at. sites of high population density and control TLD's located at sites beyond significant influence of the site. Special interest TLD s are located at or near large industrial sites, schools, proximal towns or communities or other special activity areas. Control TLD's are located to the southwest, south, south-southeast and northeast of the site at distances of 12.6 to 26.4 miles.

TLD's used during 1993 were composed of rectangular teflon wafers impregnated with 25% 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 3 and 4 (refer to Table 3 for location designations and descriptions).

Evaluation of TLD Data Tables 9A and 9B TLD's were collected and read once per quarter during the 1993 sample year. The TLD results are, for the most part, an average of eight independent readings at each location and are reported in mrem per standard month (Table 9A) and in mrem per quarterly period (Table 9B).

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

TLD results included on Tables 9A and 9B are comprised of TLD's required by the Technical Specifications and special interest TLD s not required by the Technical Specifications.

During 1993, TLD's were collected during the weeks of March 29, 1993, June 28, 1993, September 27, 1993, and December 27, 1993.

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3. ~ 0 'DXRECT RAD1ATION.

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

Overall TLD results are evaluated by organizing environmental

.TLD'.s into five different groups. These groups include: (1) .

on-site TLD's (TLD's within the site boundary not required by the Technical Specifications), (2) site boundary TLD s (one in each of the sixteen 22 1/2 degree meteorological sectors), (3) a ring of TLD's four to five miles from the site in each of the land based 22 1/2 degree meteorological sectors, (4) special .interest TLD s in areas of high population density, and (5) control TLD's in areas beyond any significant influence of the generating facilities. Special interest TLD's are located at or near large industrial sites, schools, or proximal towns or communities. Control TLD's are located, to the southwest, south, south-southeast, and northeast at distances of 12.6 to 26.4 miles from the site.

of'the..'ite Most of the TLD locations required by the Technical Specifications during 1993 were initiated in 1985 as a result of the issuance of new Technical Specifications by the NRC.

Therefore, these TLD results can only be compared to 1985 1992 results. Other TLDs, which include a few TLDs required by the Technical Specifications,(i.e., numbers 7, 14, 15, 18, 23, 49, 56, and 58) and other optional TLDs, can be compared to results prior to 1985 since these TLDs were established prior to 1985.

On-site TLD's are TLD's at special interest areas and, with the exception of TLD numbers 7 and 23, are not required by the Technical Specifications. These are located near the generating facilities and at previous or existing on-site air sampling stations. TLD s located at the air sampling stations include numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26. The results for these TLD's are generally consistent with previous years results. These results ranged from 3.1 to 13.6 mrem per standard month and up to three times control TLD results.

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 1993 were variable and ranged from 5.3 to 33.7 mrem per standard month as a result of activities at the radwaste facilities and the operating modes of the generating facilities. Results for 1993 are consistent with the ranges of variability. noted in 1992 for TLD's at or near these locations. TLD's in this group ranged up to approximately six times control TLD results.

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'3 0 'IRECT 'ADIATION t B.

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

Additional on-site TLD's are located near the on-site Energy t Center and the associated northeast, shoreline.

These TLD's" include numbers 18, 103, 106 and 107. TLD's 103, 106 and 107 are .located to the east of the Energy Center and to the west of the Unit -1 facility.',-TLD number 18 is located on the west side of the Energy Center.. Results during 1993 showed these TLD's ranged from 3.8 6.0 mrem per standard month and were consistent with the 1992 results.

Site boundary TLD's are required* by'he Technical Specifications and are located in the approximate area of the site boundary with one in each of the sixteen 22 1/2 degree .

meteorological sectors. These TLD's include numbers 75, 76 ..",

77, 23, 78, 79, 80, 81, 82, 83, 84', 7, 18, 85, 86 and 87. "TLD numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18 showed results that were consistent with control TLD results and ranged from 3.3 to 6.0 mrem per standard month. Site boundary TLD's during .1993 were consistent with 1985-1992 results. TLD numbers 75, 76, 77, 23, 85, 86, and 87 showed results that ranged up to three times the results of control TLD's. These results ranged from 3.8 to 11.6 mrem per standard month. This latter group of -TLD's are located near the lake shoreline (approximately 100 feet from the shoreline), but are also located in close proximity of the reactor building and radwaste facilities of Unit 1 and Unit 2 and the radwaste facilities of the FitzPatrick facility.

A net site boundary dose can be estimated from available TLD results and control TLD results. TLD results from TLD's located near the site boundary in sectors facing the land occupied by members of the public (excluding TLD's near the generating facilities and facing Lake Ontario) are compared to control TLD results. The site boundary TLD's include numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18. Control TLD's include numbers 8, 14, 49, 111 and 113. Net site boundary doses for each quarter in mrem per standard month are as follows:

Quarter et Site Bounder Dose*

1 -0.4 2 +0.0 3 +0.2 4 +0. 0

• Dose in mrem per standard month Site boundary TLD numbers 75, 76, 77, 23, 85, 86, and 87 were excluded from the net site boundary dose calculation since these TLD's are not representative of doses at areas where a member of the public may be located. These areas are near the north shoreline which are in close proximity to the generating facilities and are not accessible to members of the public.

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

The third group of environmental TLD's are those TLD's located four to five miles from the site in each of the land based 22.5 degree meteorological sectors. These TLDs are required by the Technical Specifications. At this distance, TLD s are not present in eight of the sixteen meteorological sectors that are located over Lake Ontario.

Results for this group of TLD's during 1993 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 3.4 to 6.3 mrem per standard month. These results are generally consistent with control TLD results during 1993.

Results for this group of TLDs were consistent with the 1985 1992 results. Results were also consistent with other off-site TLD results during 1993 and previous to 1993.

The fourth group of environmental TLD's are those TLD's located near the site boundary and at special interest areas such as industrial sites, schools, nearby communities, towns, off-site air sampling stations, the closest residence to the site, and the off-site environmental laboratory. Many of these TLDs are required by the Technical Specifications.

Others are optional. This group of TLD's include numbers 9, 10( 11/ 12( 13( 15/ 19( 51/ 52/ 53/ 54/ 55/ 56/ 58/ 96/ 97/

98, 99, 100, 101, 102, 108 and 109. TLD numbers 108 and 109 are TLD locations that were established to assist in the evaluation of the critical residence. Results ranged from 3.2 to 5.8 mrem per standard month. All the TLD results from this group were within the general variation noted for the control TLD's. Results during 1993 for TLD's established during previous years were consistent with results noted for those years.

The fifth group of TLD's include those TLD's considered as control TLD's. These TLD's are required by the Technical Specifications and include numbers 14 and 49. Optional control locations are TLD numbers 8, 111, and 113 and were added to the program to expand the data base for control TLD's. Results for 1993 ranged from 3.4 to 5.6 mrem per standard month. Results from 1993 were consistent with previous years results. However, an annual average increase was noted in 1986. This increase may have been a result of the Chernobyl Nuclear Plant accident and was not noted during 1987-1993.

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

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 1993.

Technical Specification TLDs located at the site boundary averaged 6.2 mrem per standard month during 1985. During the period of 1986 1992 site boundary TLDs ranged from 4.8 7.0 mrem per standard month. As noted previously, this group of TLDs can fluctuate because several of these TLDs are located in close proximity to the generating facilities. An increase was noted during 1986 although such an increase was noted for all TLDs including control TLDs. During 1993, site boundary TLDs averaged 5.3 mrem per standard month.

Technical Specification TLDs located off-site at a distance of 4 to 5 miles from the site in each of the land based meteorological sectors averaged 5.0 mrem per standard month during 1985. During the period of 1986 1992 off-site sector TLDs ranged from 4.1 6.0 mrem per standard month. The 1986 results demonstrated an increase for this group of TLDs.

Results for 1993 for the group averaged 4.5 mrem'per standard month. This is generally consistent with previous years results.

Special interest Technical Specification TLDs are located at areas of high population density, such as major work sites, communities, schools, etc. and at residences near the site (critical receptor areas). This group of TLDs averaged 5.3 mrem per standard month during 1985. During 1986, this same group of TLDs averaged 6.1 mrem. During the period of 1987 1992 these TLDs averaged between 4.1 5.3 mrem per standard month. 1993 results for these locations averaged 4.5 mrem per standard month.

The final group of TLDs required by the Technical Specifications is the control group. This group utilizes two TLD locations positioned well beyond the site. Results from 1985 for the control group averaged 5.4 mrem per standard month. During 1986, this same group of TLDs averaged 6.3 mrem per standard month. A marked increase was noted in the second quarter of 1986. The increase may have been a result of the Chernobyl Nuclear Plant accident. Results for 1987 1992 ranged from 3.9 5.4 mrem per standard month. Results for 1993 averaged 4.3 mrem per standard month.

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

Tables 29 and 30A-30E show the historical environmental sample data for environmental TLD's.

During 1993, all environmental TLD groups required by the Technical Specifications were generally consistent with the results observed during 1992. Overall, environmental TLD results for 1993 showed no significant impact from direct radiation measured outside the site boundary.

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23

I 4~0 TERRESTRIAL SAMPLES I "<<'IR PARTICULATE/IODINE A. Sam le Collection and Methodolo f

The air sampling stations required by the Technical Specifications are located in the general area of the .site boundary (within 0.7 miles) in sectors of highest calculated meteorological deposition factors (D/Q) based on historical meteorological data. These stations (R-l, R-2, and R-3) are located in the east, east-southeast, and southeast sectors as measured from the center of the Nine Mile Point Nuclear Unit 2 reactor building. The Technical Specifications 'tation also require that a fourth air sampling station be located in the vicinity of a year round community having the highest calculated deposition factor (D/Q) based on historical..'.

meteorological data. This station is located in the southeast sector (R-4). A fifth station required by the Technical Specifications is located at a site 16.4 miles from the site in a northeast direction (R-5). This location is considered a control location.

In addition to the Technical Specification required locations, there are six sampling stations located within the site boundary (D1, G, H, I, J, and K). These locations generally surround the area occupied by the three generating facilities, but are well within the site boundary.. One other air sampling station is located off-site in the southwest sector and is in the vicinity of the City of Oswego. Three remaining air sampling stations (D2, E and F) are located in the east southeast, south-southeast and south sectors and range in distance from 7.2 to 9.0 miles.

At each station, airborne particulates are collected by glass fiber filters and radioiodine by charcoal filters. Air particulate glass fiber filters are approximately two inches (47 millimeters) in diameter and are placed in sample holders in the intake line of a vacuum sampler. Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to absorb airborne radioiodine. The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis, or as required by dust loading. Gross beta analysis is performed for the individual particulate filters on a weekly basis. Charcoal cartridges are analyzed weekly for radioiodine by GeLi detector.

The particulate filters are composited by location for gamma analyses on a monthly basis after all weekly particulate filters have been counted for gross beta activity.

Air sampling stations are shown in Figures 3 and 4 (refer to Table 3 for location designations and.descriptions).

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

B. Evaluation of Air Particulate Gross Beta Tables 10 and 11 Tables 10 and 11 contain the results for the weekly air particulate gross beta analysis for a total of nine off-site and six on-site sample locations. Five of the nine off-site locations are required by the Technical Specifications. These sample locations are R-1, R-2, R-3, R-4 (all located near the site boundary) and R-5 (located at a control location beyond any significant influence from the site). Data contained on Tables 10 and 11 also shows the results'rom other air sampling locations not required by the Technical Specifications. These locations are designated as D1 on-site,,

G on-site, H on-site, I on-site, off-site J on-site, K on-site,' D2..-

off-site locations.

off-site, E off-site, F and G A total of 53 control samples from location R-.5 and 212 indicator samples from locations R-'1, R-2, R-3, and R-4 were collected and analyzed during 1993.

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

Location** Minimum* Maximum* AveracVe*

N R-1 0. 007 0. 021 0. 014 R-2 0. 006 0. 023 0.015 R-3 0.005 0.025 0.014 R-4 0. 007. 0.021 0.014 R-5 (control) 0. 007 0.022 0.013

• Concentration in pci/m3

• • Locations required by the Technical Specifications The observed- small increases and decreases in general gross beta activity can be attributed to changes in the environment, especially seasonal changes. The concentration of naturally occurring radionuclides in the lower limits of the atmosphere directly above land areas are affected by processes such as wind direction, snow cover, soil temperature and soil moisture content. Little change was noted in gross beta activity which corresponded with weapons testing as has been observed in past years. Review of air particulate gross beta concentrations shows that no significant increases in concentration occurred during 1993.

In general, the trend in air particulate gross beta activity has been one of decreasing activity since 1977 (extent of the review period). The mean gross beta concentration at control locations has decreased from a level of 0.165 pCi/m3 in 1981 to 0.012 in 1992. Results from indicator air sampling locations ranged from 0.151 pCi/m'n 1981 to 0.012 pCi/m'n .

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

B. Evaluation of Air Particulate Gross Beta Tables 10 and 11 1992. For both indicator locations and control location, the gross beta concentration during 1977 to 1987 fluctuated with the detonation of thermonuclear weapons.

Tables 31 and 32 show historical environmental sample data for air particulate gross beta levels.

C. Evaluation of Monthl Air Particulate Com osites Table 12 Weekly air particulate samples were composited by location to form monthly composite samples. The monthly composite by the Technical Specifications include R-1, R-2, samples'equired R-3, R-4, and R-5. Other sample locations not required by the Technical Specifications include D1 on-site, G on-site, H on-site, I on-site, J on-site, K on-site, D2 off-site, E off-site, F off-site and G off-site locations. The results of all monthly composite samples are included on Table 12.

The results for the monthly composite samples showed positive results for Be-7, K-40, and Ra-226. All three of these radionuclides are naturally occurring. Be-7 was found in all of the monthly composite samples from the locations required by the Technical Specifications. K-40 was found intermittently in the monthly composite samples required by the Technical Specifications. Ra-226 was also detected intermittently in both indicator and control samples. No other radionuclides were detected at Technical Specification or optional locations using gamma spectral analysis during 1993.

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

Detectable radionuclides included Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, La-140 and I-131. These radionuclides were not detected during 1993.

Co-60 concentrations in air particulate samples have shown a general decrease in both indicator and control samples. The Co-60 detected has primarily been attributed to past weapons testing fallout. The general decrease in Co-60 is due to ecological cycling and nuclear decay of the Co-60 initially produced by weapons tests. In 1977, Co-60 concentrations in control samples averaged 0.0172 pCi/m . A general decrease was observed in the years subsequent to 1977 until 1985 when no Co-60 was detected. From the period 1985-1993 no Co-60 was detected in control samples. Co-.60 concentrations in indicator samples have shown a similar decrease. In 1977, the 26

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4 "0 TERRESTRIAL SAMPLES AIR PARTICULATE/IODINE (Contend)

C. Evaluation of Monthl Air Particulate Com osites Table 12 (Cont'd) average concentration of Co-60 in indicator samples. was 0.0179 pCi/m'. By 1982, this value had decreased to 0.0005 pCi/m'. Slight increases were observed in 1983 and 1984, but these anomolies were due to contamination during handling of the unused samples and not due to plant operations (this has been previously documented in the 1984 annual report). Since 1984, no Co-60 has been detected in any Technical Specification indicator location.

During 1987, Co-60 was detected once at a concentration of, 0.0017 pCi/m3 at an optional air monitoring station. However, the Co-60 detected during 1987 was a result of contamination from improper handling of the sample, and not as a result of effluents from the site. This evaluation is contained in the 1987 annual report. Co-60 was not detected during 1988..

During 1989 Co-60 was detected at one on-site optional location during November at a concentration of 0.009 pCi/m3.

The Co-60 was attributed to. operations at the FitzPatrick facility and was presented inCo-60 the 1989 annual report. Results from 1990-1993 showed that was not detected from any optional indicator sample locations.

Historically, the presence of Cs-137 has been variable and has been present in air particulate samples since 1977. During 1977, both indicator and control Cs-137 average concentrations were approximately equal and averaged 0.0038 pCi/m . Since that time the concentration in both control and indicator samples has been steadily decreasing. As noted above for Co-60, the decreasing concentrations of Cs-137 are due to ecological cycling and nuclear decay of Cs-137 which was produced during weapons testing. 1978 concentrations of Cs-137 in control and indicator locations both averaged 0.0017 pCi/m, and steadily decreased to 0.0002 pCi/m in 1983. Cs-137 was not detected during 1984 and 1985. In 1986, Cs-137 was detected as' result of the Chernobyl accident in April 1986. Average concentrations during that year for in'dicator and control samples were 0.0183 and 0.0193 pCi/m3 respectively. During the period of 1987-1993 Cs-137 was not detected at any indicator or control location.

Prior to 1984, several radionuclides were detected that were associated with the 1980 Chinese weapons test and other weapons tests prior to 1980. These radionuclides were not detected after 1983 as a result of nuclear decay and ecological cycling. These include Zr-95, Ce-141, Nb-95, Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140. In addition, La-140 was detected once during 1983 and infrequently during 1978 and 27

~l 4 '0 TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont'd)

C. Evaluation of Monthl Air Particulate Com osites Table 12 (Cont'd) 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 These included Cs-134, Cs-137, Nb-95, Ru-103, Plant'ccident.

Ru-106, La-140 and I-131. All of these, with the exception of Cs-134 and particulate I-131, were detected subsequent to the 1980 Chinese weapons test (1981 1983). These radionuclides were not detected during 1984 1985. The concentrations detected during 1986 as a result of the Chernobyl accident were generally greater than the concentrations detected as a result of the 1980 Chinese weapons test. The presence of the radionuclides from the Chernobyl facility, however, extended over a very brief period (two months) while many of the radionuclides from the 1980 Chinese weapons test were present for approximately two years. During 1987 through 1993, none of the radionuclides associated with the 1986 Chernobyl accident or past weapons testing were detected in air particulate samples.

During 1991, Zn-65 was detected at one of the optional on-site locations. Zn-65 was detected at the H-onsite location at a concentration of 0.0046 pCi/m'uring the analysis of the February air particulate composite sample. The air particulate filters were then analyzed separately and determined that the Zn-65 was deposited during week 5 of 1991 it was (1/28/91 2/4/91) at a concentration of 0.0283 pCi/m3. The presence of Zn-65 in the sample was due to operations at the James A. Fitzpatrick facility. Zn-65 was not detected at any of the sample locations during 1992 or 1993.

During 1993, no radionuclides were detected in monthly air particulate composite samples that could have been attributed to plant operations. Therefore, no dose calculations were performed.

Tables 33 and 34 show historical environmental sample data for.

air particulate composites.

During the 1993 sampling program, airborne radioiodine was not found in any .of the fifty-three weekly samples from the control location required by the Technical Specifications.

LLD values at the control location ranged from 0.008 0.021 pCi/m'.

I-131 has been detected in the past at control locations and was attributed to past weapons testing and the Chernobyl accident. 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 28

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4~0 TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont'd)

D. Evaluation of Airborne Radioiodine Tables 13 and 14 factor of ten to 0.03 pCi/m'. During 1979 1981 and 1983 1985,'-131 was not detected. I-131 was detected once during 1982 at a concentration of 0.039 pCi/m'. Results from 1986 showed that I-131 was detected at the control location. This was a result of the 1986 Chernobyl Nuclear Plant accident.

The I-131 mean result was 0.151 pCi/m'. I-131 was not detected at the control location during the period 1987 through 1993.

During 1993, the indicator locations required by the Technical Specifications (approximate site boundary locations) showed no detectable levels of I-131. LLD values for I-131 ranged from 0.005 0.031 pCi/m3. I-131 was also not detected at any of the optional monitoring locations'not required by the Technical Specifications) during 1993.

0 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/m3 during 1976 and 1977. The average concentration decreased to 0.04 pCi/m during 1978 and was not detected during 1979. The 1980-1982 average concentrations were 0.013, 0.029, and 0.016 pCi/m~ which were reductions in view of previous I-131 concentrations. During 1983, the mean I-131 concentration was 0.028 pCi/m~ which represented a slight increase compared to 1982. For the most part, I-131 in indicator and control samples was a result of I-131 from weapons testing. A small portion of the concentrations detected for a few isolated instances 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/m's a result of the Chernobyl Nuclear Plant accident. I-131 was found at a mean concentration of 0.014 pCi/m'uring 1987 and was a result of operations at the site. I-131 was not found at the Technical Specification required indicator locations during 1988 through 1993.

Since I-131 was not detected at any of the indicator or control locations during 1993, no dose calculations are presented.

Tables 35 and 36 show the historical environmental sample data for airborne radioiodine.

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4 0 TERRESTRIAL SAMPLES I AIR PARTICULATE/IODINE (Cont'd)

II MILK A. Sam le Collection Methodolo and Anal sis Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat.

gallons are collected during the first half and second 'wo half of each month from each of the selected locations within ten miles of the site and from a control location. The samples are chilled and shipped fresh to the analytical.'.

laboratory within thirty-six hours of collection in insulated shipping containers.

The selection of milk sample locations is based on maximum deposition factors (D/Q). Deposition factors are generated from average historical meteorological data based on all licensed reactors. The Technical Specifications require three sample locations within 5.0 miles of the site with the highest calculated deposition factors. During 1993, 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 2. (refer to Table 3 for location designations and descriptions).

B. Evaluation of Milk Data - Tables 15 and 16 Milk samples were collected from a total of five indicator locations (within 10 miles of the site) and one control location (beyond 10 miles from the site) during 1993. The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site. During 1993, there were no milk sample locations within 5.0 miles of the site. The locations that were sampled during 1993 are located 30

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. 'ERRESTRIAL 'AMPLES MILK (Cont! d)

I B. Evaluation of Milk Data Tables 15 and 16 P from 5.5 to 9.5 miles from the site. The only sample location required by the Technical Specifications during 1993 was the ii control location. -During 1993, two control locations were utilized in order to satisfy the Technical'pecification requirement. Location number 65 was utilized from April through mid August and location number 73 was utilized from mid August through December. The reason two locations were was that the original control location (number 65) 'tilized had sold its herd during the sampling period. Sample location descriptions for all milk sample locations utilized during 1993 are listed as follows:

Location No. Direction From Site Distance From Site miles 7 ESE (107 o ) 5.5 50 E ( 930) 9.3 55 E ( 950) 9.0 60 E ( 90O) 9.5 4 ESE (113') 7.8 65 (Control) SW (220 ) 17.0 73 (Control) SW (234 o) 13 '

During 1993, milk samples were collected at each of the five 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 1993. Since I-131 was not detected during November and December of 1992, no additional samples were collected in January through March of 1993. For each sample, analyses were performed for gamma emitters (analysis by GeLi detector) and for I-131 using a resin extraction. Sample analysis results for gamma emitters are found on Table 15 and for I-131 on Table 16.

Gamma spectral analyses of the bimonthly samples showed only naturally occurring radionuclides such as K-40 and Ra-226 to be detected in milk samples during 1993. K-40 was detected in all indicator and control samples. Ra-226 occurred intermittently in milk samples. K-40 and Ra-226 are naturally occurring radionuclides and are found in many of the environmental media sampled.

During 1993, Cs-134 or Cs-137 were not detected in any control or indicator location milk samples. Cs-137 had been detected once in 1988 and was attributed to the, use of silage containing trace amounts of Cs-137 from the 1986 Chernobyl Nuclear Plant accident.

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4 ' TERRESTRIAL SAMPLES II MILK (Cont'd)

Evaluation of Milk Data - Tables 15 and 16 t B.

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

Milk samples were collected and analyzed twice per month I-131 was not detected during 1993 in any of the for'-131.

indicator or control samples. All 1993 I-131 milk sample results are reported as the lower limit of detection (LLD).

The LLD results for 1993 milk samples ranged from <0.33 pCi/liter to <0.78 pCi/liter.

Evaluation of site historical milk data shows that Cs-137 has been detected in environmental milk samples at both indicator (within 10 miles) and control locations (beyond .10 miles).

Mean Cs-137 concentrations for 1976 1981 remained fairly consistent and ranged from 8.1 (1980) to 17.1 pCi/liter (1977) at the indicator locations. The 1982 indicator mean was 5.7 pCi/liter which showed a decrease when compared to 1976 1981. Cs-137 in milk during 1983 yielded a mean of 7.2 pCi/liter which was slightly greater than the 1982 mean but was less than the 1976 1981 mean range. During 1983, however, Cs-137 was detected in only 3 of the 66 samples, while in 1982, Cs-137 was detected in 10 of the 54 samples analyzed. Cs-137 was not detected during 1984 or 1985 in indicator milk samples. Results from 1986 showed a mean Cs-137 concentration of 8.6 pCi/liter at the .indicator locations. Cs-137 in 1986 milk samples was a result of the

- 1986 Chernobyl Nuclear Plant accident. During 1987, Cs-137 was found in two indicator samples only at a mean concentration of 6.8 pCi/liter and was also a result of the Chernobyl accident. The 1988 results showed Cs-137 was detected only once at a concentration of 10.0 pCi/liter and was attributed to the Chernobyl accident. No Cs-137 was detected in milk samples during 1989 through 1993.

At the control location, Cs-137 has remained fairly consistent for all years from 1978 1982 except for 1979 and 1982. For these years, this radionuclide was not detected. Control.

samples were not obtained prior to 1978. Cs-137 ranged from 3.9 5.8 pCi/liter during 1978 1981. Cs-137 was not detected at the control location during 1982 1985. The absence of Cs-137 during 1982 through 1985 may be a result of a two to five year time interval since the last weapons test.

Results from 1986 showed a mean Cs-137 concentration, of 8.4 pCi/liter at the control location. The positive Cs-137 results during 1986 were a result of the Chernobyl Nuclear Plant accident. Cs-137 was not detected during 1987 through 1993 at the control location.

Past Cs-137 in milk samples is, for the most part, a result of previous weapons testing and more recently, the Chernobyl 32

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4 ' TERRESTRIAL SAMPLES Ie II MILK (Cont'd)

B. Evaluation of Milk Data Tables 15 and 16 accident. The continued reduction of Cs-137 levels is a result of nuclear decay and ecological cycling.

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

I-131 during these years is a result of intermittent weapons testing. During 1979 1985, I-131 in milk samples at the indicator locations was not detected except during 1980. The mean result during 1980 was 3.8 pCi/liter and was a result of the 1980 Chinese Weapons Test. Results from 1986 showed that I-131 was detected at a mean concentration 'of 5.2 pCi/liter as a result of the Chernobyl accident. I-131 was not detected during the period 1987 through 1993 in milk samples.

Historical data for I-131 from the control location showed t that I-131 was detected during 1980 at a mean concentration of 1.4 pCi/liter. There was no detectable I-131 during the l 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 i accident. I-131 was not detected during the period 1987 through 1993 at the control location.

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

Cs-134, Cs-137, and I-131 were not detected in the bi-monthly milk samples analyzed for 1993. Only naturally occurring radionuclides such as Ra-226 and K-40 were detected.

Therefore, no doses to man have been calculated.

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TERRESTRIAL'SAMPLES ZZI FOOD PRODUCTS i A. Sam le Collection Methodolo and Anal sis

'I Food products are collected once per year during the late summer at the approximate height of the harvest season.

Approximately one kilogram of a broadleaf vegetable or other broadleaf vegetation is collected from garden locations with the highest deposition factors (D/Q) based on average historical meteorological data. Five sample locations were utilized from at least two sectors. Additional samples may also be obtained. Control samples are also collected from available off-site locations 9 to 20 miles distant in a least prevalent wind direction. Control samples are of the same or of a similar type of vegetation. All samples are shipped fresh as soon as possible after collection.

Food product samples are analyzed for gamma emitters (gamma isotopic analysis). The gamma isotopic analysis also includes I-131-Food product locations are shown on Figure 1 (refer to Table 3 for location designations and descriptions).

B. Evaluation of Food Product Data Tables 17A and 17B Food product samples collected during 1993 were comprised of garden vegetables and other types of vegetation. Samples were collected from five 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, lettuce, tomatoes, collard greens, squash leaves, and swiss chard, which are all (except tomatoes) considered broadleaf vegetables. Other broadleaf vegetation consisted of beet leaves, pepper leaves, bean leaves, grape leaves, and cucumber leaves. At the control location, one sample of each of the same or of a similar type of vegetable or vegetation was.

collected. Vegetables and vegetation were collected in the late summer harvest season (mid-September 1993).

Results for food products are shown on Tables 17A and 17B.

Table 17A shows results in pCi/g (wet) while Table 17B results are in units of pCi/kg (wet). Only naturally occurring radionuclides were detected in indicator samples during 1993.

K-40 was detected in all food product samples. Be-7 was also found in all but two of the vegetation samples. AcTh-228 and Ra-226 were detected intermittently.. K-40, Be-7, Ra-22'6 andAcTh-228 are all naturally occurring radionuclides. Cs-137 was detected in one control sample of cucumber leaves during

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4.0 TERRESTRIAL SAMPLES III FOOD PRODUCTS (Cont d)

A. Evaluation of Food Product Data Tables 17A and 17B (Cont'd) 1993. Cs-137 was not detected in any of the indicator samples. It is likely the Cs-137 was present due to weapons testing fallout on -the soil and subsequent uptake by the plant. The concentration of Cs-137 in the control sample pCi/g (wet). No other radionuclides were detected in was'.007 the 1993 samples of food products.

Review of past environmental data indicates that Cs-137 has been detected intermittently during the years of 1976 1992 at the indicator locations and during the years of 1980 1992 at the control locations (control samples were not obtained prior to 1980). Review of indicator sample results from 1976 1992 showed that Cs-137 was not detected during 1976 1978, 1981 1984, 1986 - 1987, or 1990 and 1992. During 1979 and 1980, Cs-137 in fruits and/or vegetables showed annual mean concentrations of 0.004 and 0.036 pCi/g (wet) respectively.

Cs-137 was found at an indicator location during 1985 at. a concentration of 0.047 pCi/g (wet). During 1988 and 1989 Cs-137 was found at a concentration of 0.008 and 0.009 pCi/g (wet). Cs-137 was detected at a concentration of 0.040 pCi/g (wet) at an indicator location during 1991. Control sample results during 1980-1990 showed Cs-137 detected only once during 1980 at a concentration of 0.02 pCi/g (wet). Cs-137 was not detected in indicator samples during 1992 or 1993. As stated previously, Cs-137 was detected in one control sample at a concentration of 0.007 pCi/g (wet) in 1993.

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

IV LAND USE CENSUS A.

A land use census is conducted to determine the utilization of land in the vicinity of the site. The land use census actually consists of two types of census. A milk animal.

census is conducted to identify all milk animals within a distance of 10 miles from the site. A residence census is conducted to identify the closest residence in each of the meteorological sectors.

The milk animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site. A census is initiated once per year in the spring. The census is conducted by sending questionnaires to previous milk animal owners and also by. road surveys to locate any possible new owners. In the event questionnaires are not answered, then the owners are contacted by telephone or in person. The local agricultural agency was also contacted.

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4~0 TERRESTRZAL SAMPLES IV ~ LAND USE CENSUS (Cont'd)

~O A.

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

During 1993, a residence census was conducted to identify the nearest residence in each of the sixteen 22.5 de'gree meteorological sectors within a distance of five miles from the site in order to provide more comprehensive census data.

At this distance, some of the meteorological sectors are over water. These sectors include: N, NNE, NE, ENE, Wg WNW/ NW, and NNW.

I B. Evaluation of Data Tables 18 and 19 iO The number of milk animals located vithi an approximate ten mile radius of the site was estimated to be 1036 cows and 10 goats for the 1993 census. The number of cows decreased by 84 and the number of goats increased by 3 with respect to'he 1992 census. One new milk location and several locations where milk animals were no longer present were identified during the 1993 census. One control sampling location was discontinued approximately half-way through the grazing season because the herd was sold off. However, a new control location was identified and added to the 1993 sampling program. There were no other changes made to the milk sampling program. Most of the goats found on the census were milking goats. However, any milk produced was utilized by the owners and was not available for the sampling program. The results of the milk animal census are found on Table 18. Milk animal locations are shown on Figure 2.

The results of the 1993 residence census showing the applicable sectors and degrees and distance of each of the nearest residences are found on Table 19. The nearest residences are shown in Figure 1. No changes were noted in 1993.

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INTF<.RLAB RAY RY MPARI N PR RAM 37

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

Specifications and for which intercomparison samples are available from the EPA. Where many samples are available from the EPA, a QC sample to program sample ratio of ten percent is utilized, where applicable.

Results from the EPA are presented in terms of normalized deviations from.a known value (NDKV). Laboratory results are considered acceptable by EPA if the NDKV for each sample is between plus or minus 3 NDKV. All analyses but one performed by the Site Environmental Laboratory during 1993 were within 3NDKV. One sample analyzed by the Site Environmental Laboratory was outside three normalized deviations. The sample QA-93-078 was a water sample analyzed for mixed gamma.

The sample was analyzed for Co-60, Zn-65, Ru-106, Cs-134, Cs-137, and Ba-133. Five of the radionuclide activities were within 1.0 normalized deviations, while the Ru-106 activity was -3.13 from the normalized deviations.

The USEPA known activity for Ru-106 was 119 + 12 pCi/1. The Site Environmental Laboratory reported a mean result of 97 + 9 pCi/1. The Environmental Laboratory staff routinely uses a factor of 1.13 to correct an i+consistency in the published gamma yield factor. However, in this case, the results were not corrected prior to submittal to the EPA for evaluation. As noted, the other five radionuclides measured in this sample were within one standard deviation from the known, indicating no systematic error. All other analyses performed by the Site Environmental Laboratory and the vendor laboratory during 1993 were acc'eptable.

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6.0 HIST RICAL EMIR M4ENTAL SAMPLE DATA 39

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6~0 HISTORICAL ENVIRONMENTAL SAMPLE DATA Tables 21 40 show historical environmental sample data for critical radionuclides or radionuclides routinely detected in environmental sample media. Data show the minimum, maximum, and mean for each year evaluated. The data only consider detectable quantities and do not consider lower limit of detection (LLD) quantities. Data on Tables 21 40 were obtained from previous Annual Radiological Environmental Operating Report tables.

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I HAN ES AND EX EPTI N T THE PR RAIVI 41

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'-.70 'HANGES AND EXCEPTIONS"TO THE PROGRAM A. . Chan es to the 1993 Sam le Pro ra

.1.'. During 1993, milk sampling location 65 was discontinued

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after the first collection in August 1993. The herd at

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this location was sold off by the owner. Location 65 was the control location and the Technical Specification

..required location. It was replaced with location number

73. Location number 73 meets the requirements of a control location as defined in Technical Specifications, and was utilized beginning with the second coll'ection I during August 1993.

B. Exce tions to the 1993 Sam le Pro ram Exceptions to the 1993 sample program concerns those samples..~...

or monitoring requirements which are required by the Technical Specifications. This section implements section 3.6.20 of the Nine Mile Point Nuclear Station Unit 1 Technical Specifications and Section 3.12.1 of the Nine Mile Point Nuclear Station Unit 2 Technical Specifications.

I ~ Air radioiodine and particulate sampling required by the Technical Specifications 1~ Environmental air sample equipment at R-4 off-site sampling station was found to be inoperable from 7/6/93

> at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> to 7/7/93 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />. It was determined that during the monthly thermostat and operability check of this station the pump was left off. The pump was restarted at the time of discovery.

2 ~ Environmental air sample equipment at R-4 off-site station was inoperable from 10/14/93 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> to 10/14/93 at 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br /> due to a power interruption. The power interruption was necessary in order to relocate a pole from private property to a nearby right-of-way within 50 feet.

No other sample downtime was observed during 1993 for any Technical Specification required air radioiodine and particulate sampling locations. Other occurrences of downtime for optional air sampling stations were documented for 1993. However, these occurrences were minimal and are not presented here because optional air sampling stations are not required by the Technical Specifications.

~ Direct Radiation Measurements During the fourth quarter TLD readout. of TLDs supplied I and analyzed by the vendor, it was noted that the results for TLDs numbered 3 through 19 were unreliable. The cause of the problem was TLD reader malfunction at the 42 i

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CHANGES AND EXCEPTIONS TO THE PROGRAM Exce tions to the 1993 Sam le Pro ram (Cont'd)

~ Direct Radiation Measuiements'Cont'd)

F vendor, laboratory. This 'affected the fourth for Technical Specification required TLDs 7, 14,

.quarter.'esults 15, and 18. 'owever, concurrent with the vendor TLDs, the site environmental laboratory had supplied site were placed and collected at the same locations.

TLDs'hich These TLDs were placed and collected at the same time as'-,.

the vendor TLDs but analyzed separately by the site. The data from these TLDs is considered reliable and is presented in the TLD tables (9A and 9B) in lieu of the vendor supplied data. No other loss of TLD data was .

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noted during 1993.

Lower Limit of Detection for Environmental Sam les The Technical Specifications require that environmental .

samples analyzed for the Radiological Environmental Monitoring Program meet the lower limits of detection (LLD) found on Table 4.6.20-1 of the Nine Mile Point Unit 1 Technical Specifications and Table 4.12.1-1 of the Nine Mile Point Unit 2 Technical Specifications. All of the 1993 environmental samples required by the Technical Specifications which activity showed'o net were less than the required values found on Table 4.6.20-1 and Table 4.12.1-1.

Deviations from the Interlaborator Com arison Pro ram Section 3.6.21 of the Nine Mile Point Unit 1 Technical Specifications and Section 3.12.3 of the Nine Mile Point Unit 2 Technical Specifications require the site to conduct an Interlaboratory Comparison Program utilizing QC samples from the Environmental Protection Agency (EPA). This section also requires that deviations from the sample schedules be reported in the Annual Radiological Environmental Operating Report. The sample schedule is set by the EPA and includes media for'hich environmental samples are routinely collected and for which interlaboratory comparison samples are available from the EPA..

During 1993, 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. There were no deviations from the established schedule for the Interlaboratory Comparison Program.

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8 0 CONCLUSION CONCLUSION The Radiological Environmental Monitoring Program (REMP) was established to detect and evaluate any possible impact to the environment surrounding the Nine Mile Point area resulting from operations at the site.

Samples representing food sources consumed at higher such as fish and milk, were reviewed closely to evaluate trophic'evels, any impact to the general environment or to man. In addition, the data was reviewed for any possible historical trophic level bioaccumulation trends. Little or no impact could be determined resulting from radionuclide deposition considering all sources (natural, weapons testing, etc.). In regards to doses as a result of man-made radionuclides, a significant portion of the small doses',

received by a member of the public was from past nuclear weapons testing. Doses as a result of naturally occurring radionuclides, such as K-40, contributed a major portion of the total annual dose to members of the public.

Any possible impact as a result of site operations is extremely minimal when compared to the impact from natural background levels or weapons testing. It has been demonstrated that almost all environmental samples contain traces of radionuclides which are a result of weapons testing or naturally occurring sources (primordial and/or cosmic related). Whole body doses to man as a result of natural sources (naturally occurring radionuclides in the soil and lower atmosphere) in Oswego County account for approximately 50 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 1993, the presence of one fission product radionuclide was noted in two different sample media. These media included sediment and fish samples. The most likely source of this fission product is past weapons testing. The impact, expressed as a dose to man, from this radionuclide is minimal and insignificant when compared to the natural background dose.

Therefore, as determined by review of the data presented herein, no impact due to operations at the Nine Mile Point Nuclear Station was, detected that would affect the health and safety of the public.

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ENERAL REFEREN E MATERIAL 46

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

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.

U.S. Nuclear Regulatory Commission Branch Technical Position to 4 ~

Regulatory Guide 4 ') "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),

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

45( 1975 7 ~

'ational 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),

adiation 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

~an, ICRP Publication 29, 1979.

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

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

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

13. 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.

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GENERAL REFERENCE MATERIAL Samuel and Jordan, Walter H., Nuclear Power and Its

,) 14 'lasstone, Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ill., 1980.- 11 15 U.S. Department of Health, Education, and Welfare. Radiolo ical Health Handbook. Bureau of Radiological Health, Rockville, Maryland 20852. January 1970.

16. 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.

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

Ionizin Radiation Ex osure of the Po ulation of the United States,'..~-,.

NCRP Report No. 93, 1987.

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10. DATA TABL -1 49

TABLE 1 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

• A. AQUATIC PROGRAM MEDIA ANALYSIS FREQUENCY 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 Monthly Composite 1 Indicator (4), 1 Control H-3 Quarterly Composite 1 Indicator (4), 1 Control BE DIRECT RADIATION

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

NOTES:

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

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

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

(3) Indicator samples from an area near the vicinity of a site discharge point. Control samples of the same species or of species of similar feeding habits.

(4) 'ndicator sample from the J.A. Fitzpatrick inlet canal. from the site, special (5) Indicator samples from the site boundary, four-five miles interest areas and control areas (greater than ten miles from the site).

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

Co TERRESTRIAL PROGRAM MEDIA ANALYSIS FREQUENCY LOCATIONS

1. Air Particulates GB Weekly 4 Indicator, 1 Control (1)

GSA Monthly Composite

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

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

GSA 2/Month

4. Human Food Crops GSA, I-131 (4) Annually (3)

NOTES:

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

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

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

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

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

TABLE 3 ENVIRONMENTAL SAMPLE LOCATIONS AMPLE MAP FIGURE DEGREES & DISTANCE EDIUM DESIGNATION NUMBER LOCATION DESCRIPTION (I) horeline Sediment 5g Figure 1 unset Bay 800 at 1.5 miles 6 Figure 1 Langs Beach, Control 300 at 5.8 miles ish 2* Figure 1 ine Mile Point Transect 150 at 0.3 miles 3Q Figure 1 FitzPatrick Transect 55> at 0.6 miles Figure 1 Oswego Transect 350 at 6.2 miles urface Water Figure 2 FitzPatrick Inlet 700 at 0.5 miles Figure 2 swego Steam Station Inlet 35< at 7.6 miles Figure 2 NMP Unit 1 Inlet 050 at 0.3 miles 10 Figure 2 Oswego City Water 40> at 7 8 miles ll Figure 2 NMP Unit 2 Inlet 340 at 0.1 miles Air Radioiodine and R-1" Figure 3 R-1 Station, Nine Mile Point Road 880 at 1.8 miles Particulates R-2* Figure 4 R-2 Station, Lake Road 1040 at 1.1 miles R-3* Figure 4 R-3 Station, Co. Rt. 29 1320 at 1.5 miles R-4"'-5* Figure 4 R-4 Station, Co. Rt. 29 143< at 1.8 miles Figure 3 R-5 Station, Montario Point Road 420 at 16.4 miles Dl Figure 4 D 1 On-Site Station 690 at 0.2 miles G Figure 4 G On-Site Station 500 at 0.7 miles Figure 4 H On-Site Station 700 at 0.8 miles Figure 4 On-Site Station 980 at 0.8 miles Figure 4 On-Site Station 1100 at 0.9 miles Figure 4 K On-Site Station 1320 at 0.5 miles Figure 3 G Off-Site Station, Saint Paul Street 25< at 5.3 miles Figure 3 D2 Off-Site Station, Rt. 64 1170 at 9.0 miles Figure 3 E Off-Site Station, Rt. 4 1600 at 7.2 miles Figure 3 Off-Site Station, Dutch Ridge Road 1900 at 7.7 miles 52

TABLE 3 (Continued)

ENVIRONMENTALSAMPLE LOCATIONS AMPLE AP IGURE EGREES & DISTANCE EDIUM ESIGNATION UMBER OCATION DESCRIPTION (1) ermoluminescent igure 4 1 On-Site Station 690 at 0.2 miles osimeters (TLD) igure 4 2 On-Site Location 1400 at 0.4 miles igure 4 E On-Site Location 1750 at 0.4 miles igure 4 On-Site Location 100 at 0.5 miles igure 4 On-Site Station 500 at 0.7 miles igure 3 R-5 Off-Site Station 42< at 16.4 miles igure 3 1 Off-Site Location 800 at 11.4 miles 10 igure 3 2 Off-Site Station 1170 at 9.0 miles igure 3 Off-Site Station 1600 at 7.2 miles 12 igure 3 Off-Site Station 1900 at 7.7 miles 13 igure 3 Off-Site Station 250 at 5.3 miles 14* igure 3 outhwest Oswego - Control 260 at 12.6 miles 15* Igure 3 est Site Boundary 370 at 0.9 miles 18* igure 4 nergy Information Center 650 at 0.4 miles 19 figure 3 t Site Boundary 810 at 1.3 miles 3' igure 4 On-Site Station 700 at 0.8 miles igure 4 On-Site Station 980 at 0.8 miles 5 igure 4 On-Site Station 110> at 0.9 miles 6 igure 4 On-Site Station 1320 at 0.5 miles 7 igure 4 orth Fence, JAFNPP 600 at 0.4 miles 8 igure 4 orth Fence, JAFNPP 680 at 0.5 miles 9 igure 4 orth Fence, JAFNPP 650 at 0.5 miles 0 igure 4 orth Fence, JAFNPP 570 at 0.4 miles 1 igure 4 orth Fence, NMP-1 76> at 0.2 miles 9 igure 4 orth Fence, NMP-1 920 at 0.2 miles 7 igure 4 orth Fence, JAFNPP 690 at 0.6 miles 9g Igure 3 hoenix, NY - Control 1700 at 19.8 miles 1 igure 3 swego Steam Station, East 330 at 7.4 miles figure 3 itzhugh Park Elementary School, East 270 at 5.8 miles igure 3 ulton High School 1830 at 13.7 miles igure exico High School 1150 at 9.3 miles igure 3

3 ulaski Substation, Rt. 5 750 at 13.0 's

TABLE ntinued)

ENVIRONMENTALSAMPLE LOCATIONS AMPLE MAP IGURE EGREES & DISTANCE MEDIUM DESIGNATION UMBER OCATION DESCRIPTION (1) hermoluminescent 6* igure 3 ew Haven Elementary Sch 123> at 5.3 miles Dosimeters PLD) 8* igure 3 ounty Route 1 and Alcan 200 at 3.1 miles (Continued) 54 igure 4 orth Fence, NMP-2 50 at 0.1 miles 6* Figure 4 North Fence, NMP-2 250 at 0.1 miles 70k Figure 4 North Fence, NMP-2 450 at 0.2 miles 8+ igure 4 East Boundary, JAFNPP 90> at 1.0 miles 9g igure 4 ounty Route 29 1150 at 1.1 miles igure 4 ounty Route 29 1330 at 1.4 miles 80'1*

igure 4 incr Road 1590 at 1.6 miles 82+ igure 4 Miner Road 1810 at 1.6 miles 83+ igure 4 Lakeview Road 000 at 1.2 miles 84+ )gure 3 keview Road 250 at 1.1 miles 85~ igure 4 orth Fence, NMP-1 94< at 0.2 miles 86+ igure 4 orth Fence, NMP-2 150 at 0.1 miles 87* igure 4 orth Fence, NMP-2 410 at 0.1 miles 88* Figure 3 Hickory Grove Road 970 at 4.5 miles 89* igure 3 vitt Road 1110 at 4.1 miles 0 >Ic igure 3 Route 104 and Keefe Road 1350 at 4.2 miles igure 3 County Route 51A 156< at 4.8 miles 2x igure 3 aiden Lane Road 183> at 4.4 miles 3'A 3 ounty Route 53 050 at 4.4 miles figure 4w igure 3 County Route 1 and Kocher Road- 230 at 4.7 miles 5w igure 3 Lakeshore Camp Site 370 at 4.1 miles 6* igure 3 reamery Road 1990 at 3.6 miles 7Q igure 4 ounty Route 29 143> at 1.8 miles 8* igure 3 Lake Road 1010 at 1.2 miles 9 igure 3 ine Mile Point Road 880 at 1.8 miles 100 igure 4 ounty Route 29 and Lake Road . 1040 at 1.1 miles 101 igure 4 ounty Route 29 1320 at 1.5 miles 102 igure 3 Oswego County Airport 1750 at 11.9 miles 103 igure 4 Energy Center, East 67> at 0.4 miles 104 figure 3 Parkhurst Road 1020 at 1.4 miles 54

TABLE 3 (Continued)

ENVIRONMENTALSAMPLE LOCATIONS AMPLE MAP FIGURE DEGREES & DISTANCE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION (1) hermoluminescent 105 Figure 4 Lakeview Road 1980 at 1.4 miles Dosimeters (TLD) 106 Figure 4 horeline Cove, West of NMP-1 740 at 0.3 miles (Continued) 107 Figure 4 horeline Cove, West of NMP-1 72< at 0.3 miles 108 Figure 4 Lake Road 1040 at 1.1 miles 109 Figure 4 Lake Road 1030 at 1.1 miles 111 Figure 3 terling, NY - Control 140 at 21.8 miles 113 igure 3 Baldwinsville, NY - Control 178't 24.7 miles ows Milk Figure 2 ndicator Location 1070 at 5.5 miles 0 Figure 2 Indicator Location 93< at 9.3 miles 5 Figure 2 Indicator Location 950 at 9.0 miles 0 Figure 2 Indicator Location 900 at 9.5 miles Figure 2 ndicator Location 1130 at 7.8 miles 5g Figure 2 ontrol Location 20> at 17.0 miles 3Q igure 2 ontrol Location 34't 13.9 miles ood Products Figure 1 Indicator Location 840 at 1.6 miles Figure 1 ndicator Location 101< at 1.9 miles Figure I Control Location 25< at 15.6 miles Figure 1 ndicator Location 960 at 1.7 miles L Figure I Indicator Location 115't 1 9 miles ZQ Figure 1 ndicator Location 95> at 1.9 miles

- Technical Specification location.

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

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 N00 50-410 OSWEGO COUNTY'TATE OF NE'R YORK'ANUARY DECEMBER 1993*

~

INDICATOR LOCATION (b) OF HIGHEST CONTROL NUMBER OF TYPE AND NUMBER LOCATIONS: NUAL MEAN: LOCATION & LOCATION: MEAN ONROUTINE EDIUM (UNITS) OF ANALYSES* LLD(a) f EAN ( ) RANGE f EAN ( ) RANGE f

( ) RANGE EPORTS Shoreline GSA 4 Sediment* Cs-134 150 <LLD <LLD <LLD (pci/kg-dry) Cs-137 180 330 2 2 y: 28 1 2 172-489 1;5 at 80 172-489 28-28 Fish* GSA 27: (h)

(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 30 8 17 SS 32 2 10 21-38 6.2 at 235'3-41 23-41 Surface Water* H-3 8 242 4 4 AF: 188 4 4 (pci/liter) H-3 3000(c) 200-280 0.5 at 70'00-280 160-230 GSA 24 Mn-54 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0 Co-58 15 <LLD <LLD <LLD 0 Co-60 15 <LLD <LLD <LLD 0 Zn-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 <LLD <LLD <LLD 0 I-131 15 (c) <LLD <LLD <LLD 0 Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 56

TABLE 4 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POZNT 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 1993*

INDICATOR OCATION (b) OF HIGHEST CONTROL NUMBER OF TYPE AND NUMBER LOCATIONS: NUAL MEAN: LOCATION & LOCATION: MEAN NONROUTINE EDIUM (UNITS) OF ANALYSES* LLD(a) f EAN ( ) RANGE f EAN ( ) RANGE (f) RANGE REPORTS LD* (mrem per Gamma Dose 128 : (d) 15.0 120 120 12.8 8 8 uarterly 9.2-37.2 0.2 at 294 25.6-37.2 9.6-16 F 1 eriod) 11 Gross Beta 265 : 0.01 0.014 212 212 -2 0. 013 53 53 Particulates 0.005-0.025 1.1 at 104 0.006-0.023 0.007-0.022 Ci/m'-131 and Gases*

265 0. 07 <LLD <LLD <LLD GSA 60 0 Cs-134 0. 05 <LLD <LLD <LLD Cs-137 0. 06 <LLD <LLD <LLD ilk* GSA 108: (e) (h)

(pCi/liter) Cs-134 15 <LLD <LLD <LLD

<LLD Cs-137 18 <LLD <LLD Ba/La-140 15 <LLD <LLD <LLD I-131 108 <LLD <LLD <LLD I-131 Food Products* GSA 20 :(h)

(pCi/kg-wet) I-13 1 60 <LLD <LLD <LLD (broadleaf Cs-134 60 <LLD <LLD <LLD egetation) Cs-137 80 <LLD ~7.O 1 6 7.0 1 6 15.6 at 225 . 7.0-7.0 7.0-7.0

TABLE 4 ntinued)

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 1993*

TABLE NOTES:

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

(a) = LLD values as required by the 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 center-line. Units for sample results in 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 to environmental TLDs. The NMP-1 and NMP-2 Off-Site Dose Calculation Manuals contain 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. There were five optional indicator locations during 1993.

(f) = 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 ¹85 must be evaluated with the knowledge that this TLD is in close proximity (300-500 feet) of the Nine Mile Point Unit 1 reactor building and the radwaste buildings. This TLD, as well as other TLDs in this area, are adjacent to the lake shoreline which is a restricted area to members of the public. There are no residences or private property near this area.

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

58

TABLE 5A CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/g (dry) + 1 sigma SAMPLE COLLECTION LOCATION DATE Be-7 K-40 Co-60 Cs-134 Cs-137 Ra-226 AcTh-228 Other Langs Beach 4-27-93 <0.27 10.7+0.42 <0.037 <0.056 0.028+0.010 0.49+0.16 0 '5+0.06 <LLD (Control) 10-25-93 <0.32 12.7+0.50 <0.050 <0.060 <0.038 0.98+0.28 0.46+0.07 <LLD Sunset Beach 5-26-93 <0. 48 20.0+0.69 <0.082 <0.086 0.489+0.032 1.75+0.50 0.74+0.11 <LLD (Off-Site)* 10-25-93 <0.40 22.1+0.50 <0.056 <0.058 0.172+0.018 2.42+0.39 1.00+0.08 <LLD

• Sample required by the Technical Specifications Results in units of activity peer ram dry weight.

59

TABLE SB CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) + 1 sigma SAMPLE COLLECTION LOCATION DATE Be-7 -40 Co-60 Cs-134 Cs-137 a-226 cTh-228 THERS Langs Beach 4-27-93 <266 10700+424 <37 <56 28+10 487+162 346+56 <LLD (Control) 10-25-93 <316 12700+498 <50 <60 <38 985+284 464+74 <LLD Sunset Beach 5-26-93 <483 20000+690 <82 <86 489+32 1750+497 741+108 <LLD (Off-Site)

• 10-25-93 <395 22100+501 <56 <58 172+18 2420+390 1000+82 <LLD

• Sample required by the Technical Specifications Results in units of activity er kilo ram dry weight 60

TABLE 6A CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/g (wet) + 1 sigma GAMMA EMITTERS SAMPLE DATESAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 .

a-226 THER OSWEGO (CONTROL) 00 6/15/93 hitesucker <0. 06 <0.03 3. 25+0. 18 <0.02 <0.03 <0.02 <0.021 <0.05 0. 50+0. 12 <LLD 6/17/93 Lake Trout <0. 08 <0.04 4.05+0.25 <0.03 <0.05 <0.03 <0.029 <0.10 <0.41 <LLD 6/08/93 Brown Trout <0.11 <0.04 3.87+0.26 <0.03 <0.04 <0.03 <0.030 <0.10 <0.38 <LLD 6/17/93 alleye <0.06 <0.03 4.65+0.21 <0.03 <0.03 <0.02 0.041+0.010 <0.07 0. 45+0. 17 <LLD 6/17/93 Smallmouth Bass <0.14 <0.05 5.46+0.38 <0.05 <0.06 <0.05 <0.047 <0.13 <0.59 <LLD 9/17/93 Whitesucker <0. 09 <0.03 4.93+0.22 <0. 03 <0.02 <0. 03 <0.024 <0.- 09 0.40+0.15 <LLD 9/14/93 Chinook Salmon <0.10 <0.04 3.90+0.21 <0. 03 <0.03 <0. 02 0.023+0.009 <0.08 0.40+0.16 <LLD 9/14/93 Brown Trout <0.09 <0.04 3.60+0.21 <0. 03 <0.03 <0. 03 <0.023

<0.026

<0.07

<0.08 0-30+0

<0.44

'3 <LLD 9/17/93 alleye <0.09 <0.04 4.97+0.23 <0. 03 <0.04 <0. 03 <LLD 9/17/93 Smallmouth Bass <0.10 <0.04 3.55+0.22 <0. 04 <0.03 <0.03 <0.026 <0.06 0.33+0.15 <LLD NINE MILE POINT 02 6/15/93 hitesucker '0.08 <0.03 10.0+0.24 <0.03 - <0;03= <0.04 <0.030 <0. 09- <0.55 <LLD 6/17/93 Lake Trout <0.05 <0.03 3.19+0.18 <0.02 <0.03 <0.02 0.029+0.006 <0.07 0 '5+0 '6<LLD 6/08/93 Brown Trout <0.08 <0.03 3.37+0.20 <0.02 <0.03 <0.02 <0.025 <0.07 0.41+0.12<LLD 6/17/93 alleye <0.06 <0.03 3.18+0.19 <0.02 <0.03 <0.02 0.035+0.008 <0.06 0.65+0.10<LLD 9/14/93 hitesucker <0.11 9.12+0.25 <0. 03 <0. 03 <0. 03 <0.028 <0.09 1.05+0.21 <LLD 9/21/93 Brown Trout <0.07 <0.03 5.24+0.22 <0.03 <0.03 <0.02 <0.023 <0.08 0.43+0.15 <LLD 9/21/93 Chinook Salmon <0.08 <0.03

<0.09'0.04 4.42+0.24 <0.03 <0.03 <0.02 0.021+0.009 <0.08 0.38+0.18 <LLD 9/14/93 Smallmouth Bass <0.10 <0.04 3.82+0.21 <0.03 <0.03 <0.03 <0.024 <0.07 0.45+0.16 <LLD 9/21/93 alleye <0.03 4.42+0.24 <0.03 <0. 04 <0.03 0.029+0.011 <0.07 0.51+0.19 <LLD 61

TABLE 6A (Continued)

CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/g (wet) + 1 sigma GAMMA EMITTERS SAMPLE DATE SAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 a-226 THER JA FITZPATRICK 03 6/18/93 itesucker <0. 07 <0. 03 9.23+0.24 <0.03 <0.03 <0.04 <0. 030 <0. 08 0.73+0.20<LLD 6/08/93 .

Lake Trout <0.07 <0.02 3.15+0.18 <0.02 <0.03 <0.02 <0.023 <0.06 0.46+0 '4<LLD 6/08/93 Brown Trout <0.07 <0.03 4. 76+0. 21 <0. 03 <0.03 <0.02 <0.022 <0.07 0.37 <LLD 6/15/93 Smallmouth Bass <0.08 <0.03 10.4+0.25 <0.03 <0.03 <0.04 0. 026+0. 011 <0 09 0.69+0.22<LLD

~

9/14/93 Brown Trout <0. 08 <0.04 3. 65+0. 21 <0. 02 <0.04 <0.02 <0.022 <0.07 0. 54+0. 14 <LLD 9/14/93 Chinook Salmon <0.09 <0.04 4.46+0.23 <0.03 <0.03 <0.03 0.038+0.009 <0.07 0 48+0.15<LLD 9/14/93 alleye <0.09 <0.03 3.47+0.19 <0.02 <0.03 <0.02 0.029+0.008 <0.06 0. 32+0. 14 <LLD 9/14/93 Smallmouth Bass <0.12 <0.04 4.71+0.24 <0.02 <0.03 <0.03 0.032+0.008 <0.08 0. 38+0. 20 <LLD 62

TABLE 6B CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) + 1 sigma GAMMA EMITTERS SAMPLE DATA SAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 a-226 OTHER OSWEGO( CONTROL)-00 6/15/93 hitesucker <59 <27 3250+175 <24 <26 <21 <21 <55 505+124 <LLD 6/17/93 Lake Trout <83 <40 4050+253 <34 <48 <30 <29 <100 <411 <LLD 6/08/93 Brown Trout <112 <44 3870+255 <34 <43 <35 <30 <102 <375 <LLD 6/17/93 alleye <57 <28 4650+206 <26 <29 <22 41+10 <71 448+170 <LLD 6/17/93 Smallmouth Bass <135 <54 5460+376 <54 <64 <47 <47 <129 <587 <LLD 9/17/93 hitesucker <90 <34 4930+220 <28 <24 <26 <24 <87 396+151 <LLD 9/14/93 Chinook Salmon <98 <42 3900+206 <28 <33 <25 23+9 <78 402+159 <LLD 9/14/93 Brown Trout <93 <39 3600+210 <28 <29 <28 <23 <67 296+126 <LLD 9/17/93 alley.e <92 <35 4970+226 <32 <38 <26 <26 <80 <439 <LLD 9/17/93 Smallmouth Bass <99 <36 3550+216 <35 <34 <27 <26 <64 333+152 <LLD NINE MILE POINT -02 6/15/93 hitesucker <76 '"

<33 10000+24 <30 <31 <40 <30 <91 <547 <LLD 6/17/93 Lake Trout <50 <26 4 <24 <28 <21 29+6 <66 453+158 <LLD 6/08/93 Brown Trout <79 <35 3 190+176 <25 <28 <24 <25 <71 414+122 <LLD 6/17/93 alleye <60 <25 3370+199 <25 <30 <24 35+8 <57 654+98 <LLD 3180+192 9/14/93 hitesucker <107 <42 <34 <34 <34 <28 <88 '050+210 <LLD 9/21/93 Brown Trout <69 <32 9120+249 <27 <31 <24 <23 <78 434+152 <LLD 9/21/93 Chinook Salmon <81 <29 5240+220 <26 <33 <25 2 1+9 <75 380+182 <LLD 9/14/93 Smallmouth Bass <101 <39 4420+236 <29 <31 <27 <24 <66 448+163 <LLD 9/21/93 alleye <86 <33 3820+211 <26 <38 <30 29+11 <68 514+194 <LLD 4420+243 63 W

TABLE 6B (Continued)

CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) + 1 sigma GAMMA EMITTERS SAMPLE DATESAMPLE TYPE Fe-59 Co-58 -40 n-54 Co-60 Cs-134 Cs-137 Zn-65 a-226 OTHER J. A. FITZPATRICK 03 6/18/93 hitesucker <70 <32 9230+235 <29 <35 <38 <30 <84 732+196 <LLD 6/08/93 Lake Trout <68 <24 3150+177 <24 <30 <22 <23 <63 463+144 <LLD 6/08/93 Brown Trout <71 <31 4760+206 <26 <28 <24 <22 <72 <369 <LLD 6/15/93 Smallmouth Bass <82 <32 10400+246 <31 <30 <36 26+11 <86 690+217 <LLD 9/14/93 Brown Trout <78 <36 3650+209 <25 <35 <25 <22 <67 539+144 <LLD 9/14/93 Chinook Salmon <90 <37 4460+231 <27 <29 <26 38+9 <68 485+151 <LLD 9/14/93 alleye <88 <29 3470+193 <24 <31 <24 29+8 <64 316+145 <LLD 9/14/93 Smallmouth Bass <118 <35 4710+243 <24 <33 <29 32+8 <77 378+198 <LLD 64

TABLE 7 CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 1 sigma 1993 OCATION NUCLIDE JANUARY FEBRUARY CH PRIL JUNE SWEGO CITY K-40 62+ 14 193 + 17 1150 + 31 44+ 14 78 + 15 60 + 15 ATER** Ra-226 95 + 25 <70 64 + 38 64+ 25 98 + 24 99 + 20 Cs-134 <3.22 <3.50 <5.81 <3.47 <3.17 <4.03 Cs-137 <3.05 <3. 12 <4.84 <3.14 <3.55 <3.37 Zr-95 Nb-95

<7 '2

<4.59

<7. 46

<4.97

<9.10

<5.61

<6.. 13

<4. 16

<6.56

<4.43

<5.94

<4.10 Co-58 <3.93 <3.79 <5.01 <4. 14 <3.94 <4.45 n-54 <2.93 <3.84 <4.40 <3.71 <3.34 <3.84 Fe-59 Co-60

<7 '2

<4.08

<8.28

<3.81

<11.7

<4.50

<7.47

.<4.00

<9.05

<3.65

<8.93

<4.79 Zn-65 <7.90 <9.74 <13 ' <7.99 <7.78 <9.74 I-131 <10 ' <11 ' <13.4 <7.1 <9.8 <8.6 Ba/La-140 <10.7 <11.9 <9.5 <10.6 <9.0 <12.4 INE MILE K-40 50 + 12 46 + 15 68 + 13 1040 + 29 60 + 12 72 + 14 POINT UNIT I Ra-226 89 + 24 76 + 23

<2.99 76 + 27

<3.36 144 + 46

<5.68 124 + 28

<3.18 75 + 23

<3.80

<2.97 (INLET) Cs-134 Cs-137 <3.11 <3.13 <3 '6 <4.61

<8.29

<3.25

<6.87

<3 '1

<5.76 Zr-95 <6.62 <5.77 <6.43 Nb-95 <4.31 <3.85 <4.44 <5.'59 <4.31 <4.15 Co-58 <3.66 <3.30 <3.68 <5.09 <3.54 <4.34 n-54 <3.03 <3.09 <3.54 <4.24 <3.24 <4.03 Fe-59 <7.28 <8.40 <7.99 <10.8 <8.86 <8.90 Co-60 <3.71 <4.41 <3.98 <4.57 <3.72 <5.27 Zn-65 <6.77 <8.01 <8.82 <13.2 <9.47 <9.03 I-131 <9.8 = <10.'1 <9 ' <12.1 <9.7 <7 '

Ba/La-140 <11.0 <11.4 <11.9 <8.7 <12.7 <10.4

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

TABLE 7 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 1 sigma 1993 LOCATION NUCLIDE JANUARY FEBRUARY CH RIL JUNE INE MILE K-40 55 + 12 231 + 20 58 + 15 226 + 18 138 + 26 1080 + 30 POINT UNIT 2 Ra-226 113 + 16 <70 87 + 20 89+ 31 <103 112 + 38 (INLET) Cs-134 <3.35 <3.49 <3.63 <3.45 <4.95 <5.90 Cs-137 <3.27 <3. 31 <3.45 <3.04 <4.82 <4.54 Zr-95 <5.93 <7.25 <6.36 <7.37 <11.2 <8.95 Nb-95 <3.82 <4.90 <4.14 <5.15 <7.32 <5.60 Co-58 n-54

<3 '2

<3.21

<3.95

<3.59

<4.18

<3.85

<4.56

<3.45

<6.47

<5.86

<4.91

<4.52 Fe-59 <9.48 <7.41 <9.41 <7.78 <14.7 <11.5 Co-60 <4.02 <4.13 <3.83 <4.67 <7.63 <5.05 Zn-65 <7.40 <8.91 <8.41 <9.31 <14.6 <14. 1 I-131 <10.9 <11.9 <8.5 <12.7 <14 ' <12.5 Ba/La-140 <11.8 <9.26 <10.3 <13.2 <12.9 <9.5 FITZPATRICK K-40 1020 + 28 44 + 13 246 + 20 1050 + 23 220 + 18 1150 + 31 (INLET) Ra-226 123 + 34 105 + 29 45 + 26 129 + 33 70 + 35 171 + 38 Cs-134 <4.34 <3.09 <3.80 <4.44 <3.45 <5.96 Cs-137 <3.59 <3.30 <3.20 <3.72 <3.29 <4.54 Zr-95 Nb-95

<6.36

<4.00

<6 '1

<4.32

<7.40

<4.48

<7.33

<4.72

<6.89

<4.49

<8.84

<5.87 Co-58 <4.02 <3.52 <3.80 <3.88 <3.91 <5.11 n-54 <4.12 <3.50 <3.75 <3.42 <3.59 <4.54 Fe-59 <9.20 <8.65 <8.43 <9.20 <8.29 <12.4 Co-60 <4.33 <3.57 <3.75 <3.41 <3.97 <3.97 Zn-65 . <10.0 <8.10 <10.2 <10.1 <8.54 <12.2 I-131 <0.8 <1.0 <1.0 <1.0 <1.0 <0.4 Ba/La-140 <8.0 <8.9 <10.2 <9.3 <9.7 <8.6

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

• Sample required by the Technical Specifications.

66

TABLE 7 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 1 sigma 1993 LOCATION NUCLIDE JANUARY FEBRUARY RCH PRIL JUNE SWEGO K-40 54 + 12 33 + 14 57 + 12 185 + 18 62 + 16 57 + 15 STEAM Ra-226 76 + 27 99 + 28 67+ 31 <68 69 + 23 52 + 27 STATION Cs-134 <2.74 <3.92'3.34

<3.21 <3.52 <3.53 <2.90 (CONTROL) Cs-137 <3.27 <3.38 <2.92 <3.47 <3.56 Zr-95 <6.48 <6.41 <6.10 <6.80 <7.47 <6.44 Nb-95 <4.08 <4.37 <3.99 <4.26 <4.58 <4.09 Co-58 n-54

<3 '6

<3.18

<4.10

<3.75

<3.55

<3.05

<4.16

<3 '3 <5.16

<3.86

<3.51

<3.05 Fe-59. <7.88 <7.94 <8.43 <8.43 <8.90 <8.20 Co-60 <4.02 <4.42 <4.04 <3.25 <4.50 <4.04 Zn-65 <8.39 <8.52 <8.36 <9.09 <8.23 <8.11 I-131 <0.7 <1.0 <1.0 <0.5 <1 ' <0.4 Ba/La-140 <10.9 <12.6 <9.2 <10.1 <12.2 <10.9 LOCATION NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SWEGO CITY -40 81 + 14 284 + 20 216 + 24 86 + 25 944 + 26 208 + 15 ATER Ra-226 97+ 32 53 + 26 82 + 31 160 + 36 <88 53+ 21 Cs-134 <3. 14 <3.57 <4.23 <4.15 <4.34 <2.89 Cs-137 Zr-95

<3.29

<6.80

<3.16

<7.49

<4.10

<7.92

<3.59

<8.32

<3.55

<7.79

<2 '5

<5.64 Nb-95 <4.32 <4.75 <5.00 <5.65 <4.78 <3 '9 Co-58 n-54

<4.29

<3.21

<4.01

<4.06

<4 '8

<3.70

<4.52

<3.95

<4.55

<3.86

<3.10

<2.68 Fe-59 <8.79 <9.42 <9.25 <9.12 <8.41 <8.21 Co-60 <3.79 <4.48 <4.22 <3.76 <4.03 <3.55 Zn-65 <7.98 <9.74 <9.41 <10.6 <10.0 <6.70 I-131 <12.3 <11.7 <10.8 <13.6 <13.1 <13.8 Ba/La-140 <12 ' <11.2 <11.6 <9.3 <7.9 <11.6

~* Optional sample location. Sample not required by the Technical Specifications.

• Sample required by the Technical Specifications.

TABLE 7 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 1 sigma 1993 LOCATION NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER INE MILE K-40 35+ 13 232 + 19 244 + 19 247 + 19 908 + 26 68 + 12 POINT UNIT Ra-226 83 + 24 <74 60 + 22 52+ 26 171 + 36 111 + 23 (INLET) Cs-134 <3.08 <3.20 <3.30 <3.39 <4.39 <2.91 Cs-137 <3.28 <3.01 <3.11 <3.19 <3.23 <2.86 Zr-95 <6.15 <7.60 <5.95 <7.22 <7.66 <5.58 Nb-95 <3.93 <4. 86 <4.28 <4.34 <5.06 <4.11 Co-58 <3. 38 <4. 50 <3.99 <4.04 <4.47 <3.00 n-54 <3.39 <3.80 <3.65 <3.95 <4.08 <2.64 Fe-59 <7.98 <8.67 <8.63 <9.19 <8.88 <8.08 Co-60 <4.52 <4.08 <3.92 <3.75 <3.78 <3.54 Zn-65 <8.05 <10.5 <9.04 <9.99 <10.0 <6.64 I-131 <8 ' <12.4 <10.1 <11.0 <12.2 <13.1 Ba/La-140 <10.7 <11.5 <9.6 <10.8 <8.2 <12 '

INE MILE K-40 200 + 18 1190 + 28 41 + 12 87 + 26 55 + 8 217 + 13 POINT UNIT Ra-226 96 + 29 144 + 43 106 + 23 131 + 28 96 + 16 84 + 18 (INLET) Cs-134 <3.52 <5.52 <3.43 <4.10 <2.00 <2.29 Cs-137 <3.31 <4.26 <3.34 <3.69 <1.98 <2.17 Zr-95 <6.80 <8.43 <6.54 <8.05 <5.50 <5.41 Nb-95 <4.79 <5.72 <4.04 <5.07 <4.32 <3.83 Co-58 <4.00 <4.66 <3.64 <4.49 <2.91 <3.04 n-54 Fe-59

<3.50

<8.35

<4.08

<11.1

<3.19

<8.83

<3.94

<9.16

<2. 14

<7.54

<2 '5

<6.79 Co-60 <4.38 <4.36 <3.78 <3.60 <2.60 <2.58 Zn-65 <8.55 <12.6 <8.75 <9.80 <5.57 <6.67 I-131 <9.5 <14.2 <9.2 <13. 1 <9.1 <13.9 Ba/La-140 <9.0 <9.0 <9.8 <7. 1 <10.6 <9.8 4* Optional sample location. Sample not required by the Technical Specifications.

• Sample required by the Technical Specifications.

68

TABLE 7 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 1 sigma 1993 LOCATION NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER FITZPATRICK K-40 54 + 13 86+ 15 273 + =20 213 + 23 57 + 14 768 + 24 (INLET) Ra-226 87 + 27 125 + 28 56 + 32 <86 84 + 26 106 + 35 Cs-134 <3.26 <3.90 <3.44 <4.52 <3.22 <4.28 Cs-137 <3.08 <3.23 <3.22 <3.93 <2.89 <3.63 Zr-95 <6.43 <6.37 <6.85 <8.07 <6.36 <7.85 Nb-95 <4.70 <4.51 <4.64 <4.90 <3.97 <4.98 Co-58 <3.42 <4.26 <4.06 <4.15 <3. 69 <4.25 n-54 <3.37 <4.05 <3.89 <3.95 <3. 19 <3.97 Fe-59 <9.07 <9.94 <8.00 <9.96 <8.30 <8.18 Co-60 <3.92 <4.18 <4.02 <6.03 <4.17 <4.34 Zn-65 <8.27 <9.78 <9.09 <9.60 <7.85 <9.56 I-131 <0 ' <0.2 <0.4 <0.9 <0.4 <0.4 Ba/La-140 <10.3 <12.9 <10.1 <12 1 F <10.3 <7.6 SHEGO K 240 + 20 55 + 15 65 + 13 214 + 19 197 + 19 240 + 17 STEAM Ra-226 94 + 34 <62 91+ 27 <66 <72 82 + 28 STATION Cs-134 <3.80 <2.85 <2.91 <3.23 <4.25 <2.98 (CONTROL) Cs-137 <3.23 <2.93 <3. 19 <2.80 <3.32 <3.05 Zr-95 <6.96 <7.60 <5. 76 <7.24 <7.84 <6.19 Nb-95 <4.82 <4.22 <3. 43 <4.95 <5.00 <4.41 Co-58 <4.32 <3.48 <3.33 <4.27 <4.30 <3.70 n-54 <3.50 <3.04 <3.39 <3.66 <3.53 <2.90 Fe-59 <8.50 <8.13 <8.44 <8.05 <8.71 <8.55 Co-60 <3.57 <3.85 <3.57 <4.43 <4.84 <3.94 Zn-65 <9.74 <7.85 <8.05 <7.67 <9.88 <7.63 I-131 <0.9 <0.3 <0.3 <0.8 <0.3 <0.4 Ba/La-140 <11.4 <12.3 <9.5 <11..1 <8.6 <11.4

• Sample required by the Technical Specifications.

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

TA 8 CONCENTRATION OF TRITIUM IN SURFACE WATER SAMPLES (QUARTERLY COMPOSITE SAMPLES)

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

• First Quarter 01/04/93 03/31/93 280 +

+

110 Second Quarter 03/31/93 06/30/93 200 100 Third Quarter 06/30/93 09/30/93 230 + 100 Fourth Quarter 09/30/93 12/29/93 260 + 100 P-1 INLET ** First Quarter 12/31/92 03/31/93 320 + 110 Second Quarter 03/31/93 06/30/93 200 + 100 Third Quarter 06/30/93 09/30/93 170 + 100 Fourth Quarter 09/30/93 12/30/93 160 + 100 MP-2 INLET ** First Quarter 12/31/92 03/31/93 220 + 110 Second Quarter 03/31/93 06/30/93 220 + 100 Third Quarter 06/30/93 09/30/93 330 + 100 Fourth Quarter 09/30/93 12/30/93 200 + 90 SWEGO CITY WATER ** First Quarter 12/31/92 03/31/93 220 + 110 Second Quarter 03/31/93 06/30/93 220 + 100 Third Quarter 06/30/93 09/30/93 180 + 100 Fourth Quarter 09/30/93 12/30/93 230 + 100 SWEGO STEAM First Quarter 01/04/93 03/31/93 230 +

+

110 STATION

• Second Quarter 03/31/93 06/30/93 180 100 (CONTROL) Third Quarter 06/30/93 09/30/93 180 + 100 Fourth Quarter 09/30/93 12/30/93 160 + 100

• Samples required by the Technical Specifications.

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

70

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

UMBER LOCATION CH UNE  : SEPTEMBER DECEMBER DISTANCE) (2) 1993 3 D1 On Site 7.6+1.0 10 '+1.0 13.6+1.1 12 ~ 5+1. 6 (1) 0.2 miles 9 69O 4 D2 On Site 4.6+0.7 4.4+0.2 7.1+3.2 5.2+0.5 (1) 0.4 miles 9 4.6+0.2 5.9+0.9 4.0+0.4 (1) miles 140'.4 5 E On Site 4.3+0.6 9 1754 6 F On Site 3.4+0.1 3.5+0.3 5.8+0.6 4.0+0.6 (1) 0.5 miles 9 4.8+0.4 3.5+0 ' (1) miles 9 2504 210'.7 7* G On Site 3.6+0.3 3.3+0.2 8 R-5 Off Site-Control 4.4+0.3 4.4+0.1 5.6+0.2 4.4+0.6 (1) 16.4 miles 9 9 D1 Off-Site 4.0+0.2 3.7+0.3 5.2+0.2 4.2+0 ' (1) miles 9 804 42'1.4 10 D2 Off Site 3.4+0.2 3.2+0.2 4.7+0.3 4.2+0 ' (1) 9.0 miles 6 1174 11 E Off Site 3.5+0.2 3.3+0.2 5.6+0.2 4.4+0.5 (1) 7.2 miles 9 1604 12 F Off Site 3.8+0.2 3.5+0.1 5.4+0.3 4.3+0 ' (1) 7.7 miles 9 1904 13 G Off Site 4.4+0.4 4.2+0.5 5.6+0.5 4.4+0.5 (1) 5.3 miles 9 14* DeMass Rd., SW Oswego-Control 4.2+0.5 4.2+0 3 5.2+0.2 4.7+1.0 (1) miles 9 225'2.6 5.2+0.5 3.9+0.4 (1) miles 9 226'.9 15* Pole 66, W. Boundary-Bible Camp 4.2+0.3 3.2+0.1 5.2+0.3 4.6+0 ' (1) miles 9 237'.4 18* Energy Center Lamp Post, SW. 4.0+0.4 3.8+0.2 265'.

19 East Boundary-JAF, Pole 9 4.4+0.2 3.9+0.4 5.8+0.3 4.7+0.5 (1) 3 miles 9 814 23* H On Site 3.8+0.4 4.2+0.2 6.5+0.8 5.2+0.6 0.8 miles 9 24 I On Site 3.8+0.5 3.8+0.7 5.8+0 ' 3.9+0.5 miles 9 70'.8 3.1+0.5 3.5+0.2 4.6+0.3 3.8+0.4 miles 9 98'.9 25 J On Site 3.5+0.5 miles 9 110'.5 26 K On Site 3.8+0.3 4.0+0.6 5.7+0.9 miles 9 132'.4 27 N. Fence, N. of Switchyard, JAF 11.0+1.2 16.8+2.3 21.0+2-5 16.2+2 '

28 N. Light Pole, N. of Screenhouse, JAF 17.2+F 0 21.6+4 ' 33.7+7.6 24.1+5.0 miles 9 684 60'.5 29 N. Fence, N. of W. Side Screenhouse, JAF 14.1+2.9 19.7+4.4 27.6+6.0 20.5+4.1 0. 5 miles 9 65'1

TABLE 9A (Continued)

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

UMBER LOCATION RCH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 30 N Fence (NW) JAF 8.8+0.9 13.4+1.5 17.8+F 0 12.6+1.3 0.4 miles 9 8.2+0.9 6.6+0.8 miles 9 57'.2 31 N Fence (NW) NMP-1 7.0+0.8 5.8+0.4 8.7+1.0 miles 9 292~

276'.2 39 N Fence, Rad Waste, NMP-1 9.2+1.5 8.6+1.0 9.8+1.0 47 N Fence, NE, JAF 5.3+0.7 5.5+0.9 7.3+0.8 6.2+0.8 0.6 miles 9 3.4+0.1 5.0+0.2 3.6+0.2 8 miles 9 69'9.

49* Phoenix, NY-Control 4.0+0.4 4.8+0.3 miles 9 170'.4 51 Liberty & Bronson Sts., E. of OSS 4.5+0.5 3.8+0.3 5.1+0 '

3.9+0.3 miles 9 233'.8 52 East 12th & Cayuga Sts., Osw. School 4.3+0.2 3.4+0.1 5.0+0.2 53 Broadwell & Chestnut Sts., Fulton H.S. 3.9+0.1 4.3+0.2 5.7+0.4 4.6+0.3 miles 9 183' 227'3.7 54 Liberty St., & Co Rt 16, Mexico H.S. 4.2+0.6 3.8+0.3 4.8+0.3 4.4+0.6 ' miles 9 55 Gas Substation & Co Rt 5 Pulaski 4.3+0.5 3.6+0.2 5.2+0.4 4.0+0.4 miles 9 115'3.0 3.8+0.2 5.7+0.5 4.0+0.2 miles 9 75'.3 56* Rt 104 New Haven School (SE Corner) 4.2+0.2 3.9+0.2 miles 9 123'.1 58* Co Rt lA Alcan (E. of E. Entrance Rd.) 4.2+0.2 4.3+0.2 5.8+0.3 7.7+0.6 miles 9 5~

220'.1 75* - Unit 2, N. Fence, N. of Reactor Bldg. 5.6+0.4 5.5+0.5 7.5+0.7 76* Unit 2, N. Fence, N. of "N" Building 4.6+0.2 5.2+0.4 6.4+0.2 4.9+0.5 0.1 miles 9 7.6+0.6 5.8+0.6 miles 9 25'.2 77* Unit 2, N. Fence, N. of Warehouse, W. 5.6+0.2 5.6+0.4 6.0+0.4 4.6+0.4 miles 9 45'.0 78* JAF, E. of E. Old Lay Down Area 4.2+0.4 4.5+0.2 79* Co Rt 29, Pole ¹63, 0.2 mi. S. of Lake Rd 3.6+0.2 4.3+0.5 5.0+0.2 4.8+0.2 miles 9 90'.1 4.0+0.5 miles 9 115'.4 80* Co Rt 29, Pole ¹54, 0.7 mi. S. of Lake Rd 4.0+0.3 3.8+0.4 5.5+0.7 4.4+0.2 miles 9 133'.6 81* incr Rd., Pole ¹16, 0.5 mi. W. of Rt 29 3.6+0.2 4.1+0.3 5.7+0.2 159'.

82* incr Rd., Pole ¹1 1/2, 1.1 mi. W of Rt 29 3.8+0.2 3.9+0.2 5.1+0.4 3.8+0.3 6 miles 9 3.9+0.3 miles 9 181'.2 83* Lakeview Rd, Tree, 0.45 mi. N. of Miner Rd 3.6+0.4 4.2+0.1 5.4+0.2 200'2

TABLE 9A (Continued)

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

UMBER LOCATION RCH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 84* Lakeview Rd. N, Pole ¹6117, 200 Ft. N. of Lake Rd. 3.7+0.2 4.0+0.3 5.2+0.4 4.0+0.2 1.1 miles 9 85* Unit 1,.N. Fence, N. of W. Side of Screen 225'.2 House 9.6+1.3 9.2+1.2 11.6+1.3 9.0+0.8 miles 9 86* Unit 2, N. Fence, N. of W. Side of Screen 294'.1 House 6.4+0 8

~ 6.4+1.1 7.5+1.6 6.4+1.0 miles 9 87* Unit 2, N Fence, N. of E. Side of Screen 315'.1 House 5.9+0.8 6.4+0.7 8.1+1.3'.8+0.8 miles 9 88* Hickory Grove Rd., Pole ¹2, 0.6 mi. N. of 341'.5 Rt. 1 4.0+0.1 3.7+0.2 5.8+0.9 4.2+0.6 miles 9 97~

89* Leavitt Rd., Pole ¹16, 0.4 mi. S. of Rt 1 3.8+0.1 4.3+0.2 6.2+1.1 4.4+0.6 4.1 miles 9 5.0+0.4 5.0+0.5 miles 111'.2 90* Rt. 104, Pole ¹300, 150 Ft. E of Keefe Rd. 3.5+0.2 3.8+0.3 9 5.4+0.4 4.2+0.5 miles 135'.8 91* Rt. 51A, Pole ¹59, 0.8 mi. W. of Rt. 51 3.8+0 1.

~ 3.8+0.2 9 92* aiden Lane Rd., Power Pole, 0.6 mi., S of 156'.4 Rt. 104 4.2+0.3 5.2+0.5 6.3+0.5 miles 9 1834 93* Rt; 53, Pole 1-1, 120 Ft. S. of 104 4.6+0.2 5.0+0.4 5.1+1.0 5.1+0.4'.4+0.9 4.4 miles 9 4.2+0.2 4.0+0.3 miles 205'.7 94* Rt. 1, Pole ¹82, 250 Ft. E. of Kocher Rd. 3.4+0.1 3.7+0.3 9 95* Lakeshore Camp Site, from Alcan W. Access 223'.1 Rd., Pole ¹21, 1.2 mi. N. of Rt. 1 3.8+0.3 3.8+0.2 5.0+0.5 3.8+0.2 miles 9 96* Creamery Rd., 0.3 mi. S. of Middle Rd.,

237'.6 Pole 1 1/2 4.4+0.2 4.2+0.1 5.0+0.3 5.0+0.8 miles 9 Rt. 29, Env. Station R4, 200 Ft. N. of 199'.8 97*

incr Rd. 4.6+0.3 3.7+0.2 ~ 5.4+0.5 3.9+0.4 miles 9 4.4+0.4 miles 101' 143'.2 98* Lake Rd., Pole ¹145, 0. 15 mi. E. of Rt. 29 4.3+0.2 4.2+0.3 5.6+0.8 9

TABLE 9A (Continued)

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

UMBER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 99 NMP Rd., 0.4 miles N. of Lake Rd., Env.

Station R1 Off-Site 3.5+0.4 3.6+0.2 5.0+0.2 1.8 miles 9 88'.:

100 Rt. 29 and Lake Rd., Env. Station R2 Off-Site 4.4+0.4 3.9+0.3 4.4+0.3 4.2+0.2 1.1 miles 9 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env.

Station R3 Off-Site 4.5+0.1 3.8+0.3 4.8+0.4 3.7+0.2 1.5 miles 9 102 EOF/Env. Lab, Oswego Co. Airport (Fulton irport), 11.9 miles 132'.4+0.2 Rt. 176, E. Driveway Lamp Post 4.1+0.2 4.2+0.5 4.5+0.2 9 EIC, East Garage Rd., Lamp Post 4.3+0.2 4.3+0.4 6.0+0.3 4.0+0.2 miles 175'.4 103 9 104 Parkhurst Road, Pole 148 1/2-A, 0.1 mi. S. 178'.4+0.2 of Lake Rd. 1.4 miles 267'.4+0.2 4.4+0.2 3.8+0.3 5.0+0.2 9 104'1) 105 Lakeview Road, Pole 6125, 0.6 mi. S. of 102'.7+0.2 Lake Rd. 4.1+0.2 4.4+0.1 5.7+0.6 1.4 miles 9 Shoreline Cove, E of NMP-1, Tree on W Edge 4.6+0.4 4.6+0.5 6.0+0.2 4.7+0.5 miles 198'.3 106 9 107 Shoreline Cove, E of NMP-1, Tree 30 Ft. S. 274'.6+0.3 of.TLD g106 5.0+0.3 4.6+0.3 5.4+0.5 0.3 miles 9 108 Lake Rd. Pole g142 300'ast of Co. Rt. 272'.0+0.3 29 (S) 4.8+0.2 4.0+0.3 5. 4+0. 4 1. 1 miles 9 109 Lake Rd. Tree 300'. of Co. Rt. 29 (N) 4.0+0.3 4.0+0.2 5.4+0.3 3.8+0.2 miles 9 104'.1 Sterling, NY Control Blasiak Residence 4.6+0.2 4.0+0.3 5.3+0.2 4.2+0.4 8 miles 103'1.

111 9 113 Baldwinsville, NY Control Coates 214'.6+0.3 Residence 3.8+0.3 3.9+0.3 4.6+0.2 24.7 miles 9 Site Environmental Laboratory supplied TLD results utilized in lieu of vendor TLD data.

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

• - Technical Specification location 74

TABLE 9B DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma ANVARY PRIL ULY CTOBER LOCATION, OCATION HROUGH HROUGH THROUGH - HROUGH (DIRECTION &

UMBER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 3 Dl On Site 24.0+1.6 30.6+1.5 42.0+1.6 42.2+1.6 0.2 miles g 69o 4 D2 On Site 14. 6+1. 1 12.3+0.3 22.1+4.9 18.3+0.5 0.4 miles g 140o 5 E On Site 13.8+1.0 13.0+0.2 18 '+1.5 14.1+0.4 0.4 miles g 175o-6 F On Site 10.7+0.2 9.9+0.4 17.8+0.9 14.1+0.6 (1) 0.5 miles g 210o 7* G On Site 11.4+0.4 9.2+0.2 14.9+0.6 12.5+0.8 (1) 0.7 miles 9 250o 8 R-5 Off Site-Control 13.0+0.5 12.0+0.2 18.2+0.3 15.2+0.6 (1) 16.4 miles Q 42o 9 D1 Off Site 11.8+0.3 10.4+0.4 16.8+0.4 13.7+0.4 11.4 miles g 80o 10 D2 Off Site 10.2+0.4 9.2+0.3 14.6+0.4 13.6+0.5 (1) 9.0 miles 6 1170 11 E Off Site 10.7+0.3 9.4+0.3 16.8+0.3 14.4+0.8 (1) 7.2 miles g 160o 12 F Off Site 11.4+0.3 10.1+0.2 16.2+0.5 14.1+0.6 (1) 7..7 miles 190o 13 G Off Site 13.4+0.6 12.0+0.7 17.0+0.8 14.5+0.5 5.3 miles g 225o 14* DeMass Rd., SW Oswego-Control 11.8+0.7 12.2+0.4 16.1+0.4 15. 2+1. 0 (1) 12.6 miles 9 226o 15* Pole 66, W. Boundary-Bible Camp 12.5+0.5 9.2+0.2 16.4+0.8 12.7+0.4 (1) 0.9 miles 6 237 18* Energy Center-Lamp Post, SW. 12.9+0.6 10.8+0.2 16.1+0.5 16.0+1.0 (1) 0.4 miles g 265o 19 East Boundary-JAF, Pole 9 13.4+0.3 11.2+0.5 18.3+0.4 15.0+0.5 (1) 1.3 miles g 81o 23* H On Site 12.2+0.6 11.8+0.3 20.0+1.2 17.2+1.0 0.8 miles 9. 70o 24 I Site On 12.2+0.8 10.7+0.9 17.8+1.0 12.8+0.8 0.8 miles g 98o 25 J On Site 10.0+0.8 9.8+0.3 14.2+0.5 12.6+0.7 0.9 miles 6 110 26 K On Site 12.1+0.4 11.3+0.8 17.6+1.4 11.5+0.8 0.5 miles 9 132.

27 N. Fence, N. of Switchyard, JAF 31.2+1.7 51.0+3.4 65.8+3 ' 50.2+3.6 0.4 miles g 60o 28 N Light Pole, N. of Screenhouse, JAF 48.6+5.7 65.4+7.0 105.4+11.8 74.7+7.7 0.5 miles 9 68o 75

W W W W W W W W W W W W W TABLE 9B (Continued)

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

UMBER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 29 N Fence, N of W Side Screenhouse, JAF 39.9+4.1 59.6+6.6 86.3+9.4 63.4+6.4 0.5 miles 9 25.0+1.3 40.8+2.2 55.5+3.1 39.1+2.1 miles 9 65'.4 30 N Fence (NW) JAF 2 miles 9 276 57'.

31 N Fence (NW) NMP-1 22.4+1.3 16.2+0.6 26.1+1.4 20.4+1.2 39 N Fence, Rad Waste, NMP-1 29.2+2.4 23.8+1.4 31.4+1.6 26.9+1.6 0.2 miles 9 292~

47 N Fence, NE, JAF 15.0+1.0 16.6+1.3 22.7+1.3 19.0+1.3 0.6 miles 9 694 49* Phoenix, NY-Control 11.3+0.5 9.6+0.2 15.2+0.4 10.6+0.4 19.8 miles 9 Liberty Sts., E of OSS 12.5+0.6 11.0+0.4 15.6+0.7 14.2+0.4 miles 9 233~

170'.4 51 & Bronson 52 East 12th & Cayuga Sts., Oswego School 12.0+0.3 9.9+0.1 15.4+0.3 11.8+0.6 5. miles 9 8

53 Broadwell & Chestnut Sts., Fulton H.S. 11.1+0.2 12.5+0.4 17.4+0.6 13.9+0.5 miles 9 227'3.7 Liberty St., 13.0+0.9 10.9+0.4 14.8+0.5 12.9+0.9 miles 9 183'.3 54 & Co Rt 16, Mexico H.S.

Gas Substation & Co Rt 5 Pulaski 13.0+0.8 10.2+0.4 16.8+0.6 11.2+0.5 0 miles 9 75~

115'3.

55 56* Rt 104 New Haven School (SE Corner) 12.9+0.3 11.4+0.3 17.2+0.8 11.8+0.2 5.3 miles 9 Co Rt 1A Alcan (E. of Entrance Rd.) 13.6+0.2 11.8+0.3 17.9+0.6 11.4+0.2 miles 9 123'.1 58*

Unit 2, N. Fence, N. of Reactor Bldg. 17.6+0.6 15.4+0.7 24.0+1.2 23.8+0 ' miles 9 220'.1 75*

76* Unit 2, N. Fence, N. of "N" Building 14.4+0.4 14.3+0.6 20.6+0.3 15.2+0.8 miles 6 5'.1 77* Unit 2, N. Fence, N. of Warehouse, W. 17.8+0.4 15.8+0.6 23.6+0.9 18 '+0 ' miles 9 25'.2 78* JAF, E. of E. Old Laydown Area 13.4+0.7 12.5+0.4 18.5+0.6 15.2+0.7 miles 9 45'.0 79* Co Rt 29, Pole g63, 0.2 mi. S. of Lake Rd 11.2+0.3 12.4+0.8 15.6+0.3 14.2+0.4 miles 9 90'.1 80* Co Rt 29, Pole g54, 0.7 mi. S. of Lake Rd 12.2+0.4 11.0+0.5 17 '+F 1 11.6+0.7 miles 9 133~

115'.4 81* incr Rd, Pole gl6, 0.5 mi. W. of Rt 29 11.0+0.3 11.8+0.5 17.8+0.4 13.4+0.4 1.6 miles 9 159 82* incr Rd, Pole g1 1/2, 1.1 mi.- W of Rt 29 11.6+0.3 11.3+0.3 15.8+0.7 11.8+0 ' 1.6 miles 9 181 76

TABLE 9B (Continued)

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

UMBER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 83* Lakeview Rd., Tree, 0.45 mi. N of Miner Rd 11.6+0.6 11.6+0.2 17.0+0.4 12.0+0.4 1.2 miles 9 84* Lakeview Rd. N, Pole g6117, 200 Ft. N. of 11.6+0.4 16 '+0.6 1.1 miles 200'1.6+0.4 Lake Rd. 11.2+0.3 9 85* Unit 1, N. Fence, N. of W. Side of Screen 25.6+1.7 37.2+2.1 0.2 miles 225'7.5+1.,3 House 30.4+2.0 9 86* Unit 2, N. Fence, N. of W. Side of Screen 0.1 miles 294'0.0+1.5 House 20.3+1.3 18.0+1.6 23.9+2 ' 9 87* Unit 2, N. Fence, N. of E. Side of Screen 0.1 miles 315'3.8+1.3 House 18.6+1.2 17.8+1.0 25.8+2.1 9 88* Hickory Grove Rd., Pole g2, 0.6 mi. N. of 341'2.4+0

t. 1 12.4+0.2 11.0+0.2 17.7+1.4 12.8+0.4 18 '+1.7 '+0 4.5 miles 4.1 miles 9 97~

6 111~

89* Leavitt Rd., Pole g16, 0.4 mi. S. of- Rt 1 11.7+0.1 12 14.8+0 ' 4.2 miles 135~

90* Rt. 104, Pole g300, 150 Ft. E of Keefe Rd. 10.6+0.2 11.4+0.4 15.2+0.6 6 91* Rt. 51A, Pole g59, 0.8 mi. W-. of Rt. 51 11.5+0.2 10.6+0.3 16.5+0.6 12.6+0.7 4.8 maples 9 156o 92* aiden Lane Rd., Power Pole, 0.6 mi., S.

of Rt. 104 12.8+0.5 14 '+0.6 19 '+0.8 15.0+0.5 4.4 miles 9 93* Rt. 53, Pole 1-1; 120 Ft. S. of 104 14.0+0.3 13.4+0.6 16.8+1.5 4.4 miles 9 183'5.0+1.5 94* t. 1, Pole g82, 250 Ft. E. of Kocher Rd. 10.8+0.2 10.1+0.4 12.9+0.4 4.7 miles 9 205'1.6+0.4 95* Lakeshore Camp Site, from Alcan W. Access 4.1 miles 223'1.2+0.4 d., Pole f21, 1.2 mi. N. of Rt. 1 12.2+0.4 10.4+0.2 15.6+0.8 9 96* Creamery Rd., 0.3 mi. S. of Middle Rd.,

3.6 miles 237'4.8+1.3 Pole 1 1/2 14.2+0.4 11.6+0.1 15.4+0.4 9 199'7

• W

TABLE 9B (Continued)

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

UMBER LOCATION CH UNE SEPTEMBER DECEMBER DISTANCE) (2) 1993 97* Rt. 29, Env. Station R4, 200 Ft. N. of incr Rd. 14.2+0.4 10.7+0.4 16.8+0.8 1.8 miles 9 98* Lake Rd., Pole gl45, 0.15 mi. E. of Rt. 29 13.2+0.3 12.2+0.4 17.6+1.2 1.2 miles 9 143'2.8+0.5 99 NMP Rd., 0.4 miles N. of Lake Rd., Env.

1.8 miles 101'3.4+0.4 Station Rl Off-Site 10.7+0.6 10.5+0.2 15.1+0.4 9 100 Rt. 29 and Lake Rd., Env. Station R2 Off-Site 13.4+0.6 11.2+0.4 13.6+0.4 1.1 miles 9 104 88'2.5+0.3 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env.

Station R3 Off-Site 13.6+0.2 11.0+0.5 14.6+0.6 11.0+0.4 1.5 miles 9 EOF/Env. Lab, Oswego Co. Airport (Fulton 132'4.

102 178'1.8+0.6 irport), Rt. 176, E. Driveway Lamp Post 11.8+0.3 12.6+0.8 13.8+0.3 6+0. 4 11. 9 miles 9 13.5+0.'3 12.0+0.5 18.4+0.4 4+0. 4 0. 4 miles 9 175'3.

103 EIC, East Garage Rd., Lamp Post 104 Parkhurst Rd., Pole 148 1/2-A, 0.1 mi. S.

of Lake Rd. 13.6+0.3 10.8+0.5 15.6+0.3 12.8+0.4 1.4 miles 9 105 Lakeview Rd., Pole 6125, 0. 6 mi. S of Lake 1.4 miles 102'2.4+0.3 Rd. 12.6+0.3 12.9+0.2 17.8+0.9 9 106 Shoreline Cove, E of NMP-1, Tree on W Edge 14.8+0.6 12.9+0.6 18.5+0.4 0.3 miles 9 267'1) 198'5.0+0.9 107 Shoreline Cove, E of NMP-1, Tree 30 Ft. S.

0.3 miles 274'4.5+0.5 of TLD f106 16.0+0.5 12.8+0 ' 16.7+0.8 9 272'.

108 Lake Rd Pole gl42 300' of Co Rt 29 (S) 14.6+0 ' 11.7+0-4 16.8+0.5 11.9+0.5 1 miles 9 109 Lake Rd Tree, 300'. of Co. Rt. 29 (N) 12-4+0 ' 11.4+0 ' 17.0+0.4 11.3+0-4 miles 9 104'.1 Control Blasiak Residence 13 '+0 ' 11.2+0.4 16.8+0.3 13.0+0-6 miles 103'1.8 111 Sterling, NY 9 113 Baldwinsville, NY Control Coates 24.7 miles 214'1.3+0.5 Residence 11.4+0.4 11.4+0.5 14.0+0.4 9 Sate Environmental Laboratory supplied TLD results utxlxzed xn lieu of vendor TLD data.

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

• Technical Specification location.

78

TABLE 10 NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFF-SITE STATIONS GROSS BETA ACTIVITYpCI/I a 1 SIGMA LOCATION 0.01010.001 0.011i0.001 0.01010.001 0.00910.001 0.00910.001 0.00910.001 0.01010.001 0.00910.001 0.008&.001 01/05/93 0.02110.001 0.02110.001 0.020 j0.001 0.02210.001-. 0.02210.001 0.02310.001 0.021%0.001 0.022%0.001 01/12/93 0.02010.001 0.01610.001 0.017%0.001 0.01610.001 0.01810.001 0.01410.001 0.00910.001 0.01810.001 0.015%0.001 0.014%0.001 01/19/93 0.013i0.001 0.01210.001 0.01210.001 0.012%0.001 0.01110.001 0.011k 0.001 0.010i0.001 0.012i0.001 0.00920.001 01/26/93 0.016i0.001 0.01610.001 0.01510.001 0.01710.001 0.01510.001 0.01610.001 0.01210.001 0.015%0.001 0.01410,001 02/02/93 0.01810.001 0.01910.001 0.02010.001 0.01810.001 0.01810.001 0.02010.001 0.01610.001 0.01710.001 0.015i0.001 02/09/93 0.01410.001 0.01410.001 0.01310.001 0.01210.001 0.01210.001 0.01610.001 0.014i0.001 0.01310,001 02/16/93 0.01210.001 0.017 j0.001 0.01410.001 0.01510.001 0.01310.001 0.01410.001 0.016i0.001 0.01410.001 0.015%0.001 02/23/93 0.013 j0.001 0.016 j0.001 0.016 j0.001 0.01510.001 0.015i0.001 0.01610.001 0.014%0.001 0.01510.001 0.013%0.001 03/02/93 0.01510.001 0.022i0.001 0.01810.001 0.021%0.001 0.01820.001 0.01810.001 0.020i0.001 0.021i0.001 0.01610.001 03/09/93 0.021%0.001 0.01010,001 0.01710.001 0.012 j0.001 0.01210.001 0.01310.001 0.01210.001 0.015i0.001 0,012i0.001 0.017%0.001 03/16/93 0.01510.001 0.01610.001 0.016 10.001 0.01510.001 0.017i0.001 0.01510.001. 0.017i0.001 0.013i0.001 03/23/93 0.01610.001 0.00910.001 0.00710.001 0.00710.001 0.006%0.001 0.00910.001 0.00820.001 0.006%0,001 03/30/93 0.00810.001 0.00910.001 0.01110.001 0.00910.001 0.00910.001 0.00910.001 0.00810.001 0.00910.001 0.00920.001 0.008i0.001 04/06/93 0.00910.001 0.00510.001 0.00710,001 0.00710.001 0.006%0.001 0.00710.001 0.00610.001 0.00510.001 04/13/93 0.00710.001 0.006 j0.001 0.01210.001 0.01410.001 0.012i0.001 0.01320.001 0.011%0.001 0.012%0.001 0.01110.001 04/20/93 0.013i0.001 0.013i0.001 0.014 j0.001 0.01210.001 0.01010.001 0.01110,001 0.01210.001 0.01220.001 0.011%0,001 04/27/93 0.012%0.001 0.01410.001 0.01310.001 0.01510.001 0.01310.001 0.01310.001 0.01410.001 0.015i0.001 0.014i0.001 0.010%0.001 05/04/93 0.01220,001 0.01310.001 0.01410.001 0.01210.001 0.01210.001 0.015i0.001 0.012%0.001 0.01110.001 05/11/93 0.012t0.001 0.01410.001 0.01110.001 0.011i0.001 0.008i0.001 0.011%0.001 0.01210.001 0.011%0.001 0.008%0.001 05/18/93 0.01210.001 0.01010.001 0.011%0.001 0.01110.001 0.00910,001 0.01310.001 0.012%0,001 0.00920.001 0.01010.001 05/25/93 0.01010.001

• 0.01310.001 0.00710.001 0.00810.001 0.00710.001 0.00720.001 0.00810.001 0.00610.001 0.005i0.001 06/01/93 0.00710.001 0.00810.001 0.00810.001 0.01010.001 0.00910.001 0.00910.001 0.011%0.001 0.011%0.001 0.00810.001 06/08/93 0.01010.001 0.01210.001 0.01210.001 0.01210.001 0.012i0.001 0.01210.001 0.012%0.001 0.012i0.001 0.008i0.001 0.012%0.001 06/15/93 0.01210.001 0.00910.001 0.01010.001 0.01010.001 0.00910.001 0.011t0,001 0.00810.001 0.00810.001 06/22/93 0.01010.001 0.01120.001 0.01210.001 0.012%0.001 0.01310.001 0,01010.001 0.01310.001 0.011%0,001 06/29/93 0.01010.001 0.01510.001 0.012%0.001

" Sample loc required by Technical Specifications m m m m m m m m m'A m m m m m m m m m

TABLE 10 (CONTINUED)

NMP/DAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFF-SITE STATIONS GROSS BETA ACTIVITYpCi/m a 1 SIGMA LOCATION 07/06/93 0.013&.001 0.013%0.001 0.012&.001 0.012 j0.001 0.013&.001 0.011%0.001 0.012%0.001 0.012&.001 0.011&.001 07/13/93 0.018+0.001 0.01920.001 0.02010.001 0.017&.001 0.01510.001 0.02110.001 0.02310.001 0.023&.001'. 0.016&.001 07/20/93 0.011%0.001 0.01010.001 0.011%0.001 0.009 j0.001 0.00810.001 0.010%0.001 0.01010.001 0.00810.001 0.00910.001 07Q7/93 0.013&.001 0.013%0.001 0.01310.001 0.010%0.001 0.011%0.001 0.01010.001 0,011%0.001 0.009&.001-- 0.011&.001 08/03/93 0.012&.001 0.012%0.001 0.013%0.001 0.011%0.001 0.013%0.001 0,012%0.001 0,01310.001 0.012&.001 0.01lE0.001 08/10/93 0.016&,001 0.02020.001 0.01610.001 0.01410.001 0.014%0.001 0.01710.001 0.01710.001 0.016&,001 0.014&.001 08/17/93 0.01910.001 0.02310.001 0.02310.001 0.01810.001 0.02010.001 0.01910.001 0.01910.001 0.016%0.001 0.01720.001 08/24/93 0.01720.001 0.02010.001 0.01710.001 0.01610.001 0.01810.001 0.01610,001 0.02IE0.001 0.01~.001 0.01710.001 08/31/93 0.02010.001 0.018 j0.001 0.02510.001 0.021%0.001 0.02120.001 0.021%0.001 0.02020.001 0.021&,001 0.01920.001 09/07/93 0.015%0.001 0.018%0.001 0.014 j0.001 0.01710.001 0.012%0.001 0.01910.001 0.016%0.001 0.014&.001 0.01320.001 09/14/93 0.014&.001 0.01510.001 0.01610.001 0.01420.001 0.01410.001 0.016+0.001 0.01510.001 0.013&.001 0.014&.001 09Q1/93 0.013%0.001 0.01410.001 0.01220.001 0.012%0.001 0.01020.001 0.014%0.001 0.01110.001 0.01310.001 0.011%0.001 09/28/93 0.01310.001 0.013t0.001 0,012%0.001 0.012%0.001 0.012%0.001 0.012%0.001 0,011%0.001 0.01320.001 0.012%0.001 10/05/93 0.00910.001 0.011%0.001 0.011%0.001 0.011%0.001 0.01010.001 0.011%0.001 0.012%0.001 0.011&.001 0.01020.001 10/12/93 0.016%0.001 0.01720.001 0.01810.001 0.01910.001 0.019%0,001 0.01610.001 0.015%0.001 0.01810,001 0.01510.001 0.01810.001 0.01810.001 0.01610.001 0.01910.001 0.018%0.001 0.021%0.001 0.01810.001 0,019%0.001 0.016%0.001 10/19/93 0.013%0.001 0.01410.001 0.01310.001 0.01110.001 0.01010.001 0.014%0.001 0.01510.001 0.012%0.001 0.011%0.001 10/26/93 0.011%0.001 0.01010.001 '0.01010.001 0.01010.001 0.012%0.001 0.012%0.001 0,01010.001 0.010%0.001 11/02/93 0.011%0.001 0.01710.001 0.01610.001 0.014&.001 0.01710.001 0.016%0.001 0.01610,001 0.016%0.001 0.013%0.001 11/09/93 0.016+0.001 11/16/93 0.019&.001 0.021%0.001 0.020 j0.001 0.017%0,001 0.01720.001 0.021%0.001 0,020&.001 0.017&.001 0.018%0.001 0.01510.001 0.016%0.001 0.01410.001 0,015%0,001 0.017%0,001 0.01520.001 0.016%0.001 0.012%0.001 11/23/93 0.013%0.001 0.016%0.001 0.016%0.001 0.015%0.001 0.015&.001 0.01510.001 0.014%0.001 11/30/93 0.014%0.001 0.013 j0.001 0.01610.001 0.01610.001 0.01720.001 0.018 j0.001 0.017%0.001 0.01920.001 0.018%0.001 0.01710.001 0.01710,001 12/07/93 0.01710.001 0.01910.001 0.018&.001 0.01810.001 0.01920.001 0.01920,001 0.01910.001 0.01710.001 0.01720.001 12/12/93 0.01910.001 12Q1/93 0.01510.001 0.01410.001 0.014k%.001 0.015 j0.001 0.01610.001 0,01710.001 0.017%0.001 0.015&.001 0.014%0.001 0.011%0.001 0.01310.001 0.012%0.001 0.013%0.001 0.01310.001 0.01610.001 0.011%0.001 0.01510,001 12/28/93 0.01320,001 0.013%0.001 0.01310.001 0.01310.001 0.01510.001 0.01510.001 0.011%0.001 0.01410.001 0.01220.001 01/04/94 0.013%0.001

~ Sample locations required by Technical Specifications 80

TABLE 11 NMP/JAF-SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE STATIONS GROSS BETA ACTIVITYpCI/m3 a 1 SIGMA LOCATION 01/04/93 0.01020.001 0.00910.001 0.009%0.001 0.00920.001 0.008%0.001 0.01010.001 01/11/93 0.022%0.001 0.023%0.001 0.02310.001 0.019%0.001 0.018%0.001 0.01920.001 01/18/93 0.018 10.001 0.01720.001 0.014%0.001 0.016%0.001 0.012%0.001 0.014%0.001 01/25/93 0.01320.001 0.013%0.001 0.011%0.001 0.01320.001 0.01010.001 0.013%0.001 02/01/93 0.01320.001 0.012%0.001 0.012%0.001 0.014%0.001 0.012%0.001 0.012%0.001 02/08/93 0.018%0.001 0.018%0.001 0.018%0.001 0.018%0.001 0.015%0.001 0.01820.001 02/16/93 0.017%0.001 0.01310.001 0.012%0.001 0.013%0.001 0.011%0.001 0.012%0.001 02/22/93 0.01620.001 0.014%0.001 0.013%0.001 0.014%0.001 0.01310.001 0.01520.001 03/01/93 0.01720.001 0.01520.001 0.01610.001 0.01720.001 0.011%0.001 0.014%0.001 03/08/93 0.02510.001 0.02510.001 0.024%0.001 0.02510.001 0.022%0.001 0.024%0.001 03/15/93 0.012%0.001 0.011%0.001 0.01520.001 0.014%0.001 0.01020.001 0.014%0.001 03/22/93 0.01920.001 0.018%0.001 0.018%0.001 0.01720.001 0.012%0.001 0.017%0.001 03/29/93 0.009X0.001 0.008%0.001 0.00820.001 0.00920.001 0.007%0.001 0.008%0.001 04/05/93 0.01020.001 0.01010.001 0.011%0.001 0.00920.001 0.008%0.001 0.01010.001 04/12/93 0.00920.001 0.008%0.001 0.010%0.001 0.00920.001 0.007%0.001 0.00820.001 04/19/93 0.01220.001 0.01020.001 0.01320.001 0.011%0.001 0.00920.001 0.01220.001 04/26/93 0.013%0.001 0.013%0.001 0.012+0.001 0.012%0.001 0.01120.001 0.011%0.001 05/03/93 0.014%0.001 0.014%0.001 0.014%0.001 0.015%0.001 0.01120.001 0.01320.001 05/10/93 0.01420.001 0.013%0.001 0.011%0.001 0.01320.001 0.01320.001 0.011%0.001 05/17/93 0.011%0.001 0.011%0.001 0.01010.001 0.010%0.001 0.010%0.001 0.012%0.001 05/24/93 0.01020.001 0.00910.001 0.011%0.001 0.01120.001 0.006%0.001 0.005%0.001 06/01/93 0.008%0.001 0.00820.001 0.008%0.001 0.00920.001 0.00420.001 0.00610.001 06/07/93 0.00910.001 0.008%0.001 0.00920.001 0.00920.001 0.006%0.001 0.00710.001

. 06/14/93 0.01610.001 0.013%0.001 0.046%0.001 . 0.010%0.001 0.012%0.001 0.011%0.001 06/21/9 0.012%0.001 0.01120.001 0.01440.001 0.01020.001,. 0.01120.001 0.01020.001 06/28 0.01320.001 0.013%0.001 0. 001 0.013%0.001 0.00920.001 0.001

TABLE ll (CONTINUED)

NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE STATIONS GROSS BETA ACTIVITYpCi/m a 1 SIGMA LOCATION 07/06/93 0.01520.001 0.013%0.001 0.013%0.001 0.010%0.001 0.013+0.001 07/12/93 0.020%0.001 0.020 j0.001 0.02120.001 0.018%0.001 0.018%0.001 0.016%0.001 07/19/93 0.01320.001 '.013%0.001 0.011%0.001 0.00920.001 0.012%0.001 0.013%0.001 0.00920.001 07/26/93 0.011%0.001 0.01210.001 0.012%0.001 0.014%0.001 0.01220.001 0.011%0.001 08/02/93 0.012%0.001 0.014%0.001 0.01520.001 0.01220.001 0.01320.001 0.012%0.001 08/09/93 0.013%0.001 0.014%0.001 0.018%0.001 0.02010.001 0.014%0.001 0.01320.001 08/16/93 0.021%0.001 0.02320.001 0.02420.001 0.025%0.001 0.01920.001 0.021%0.001 08/23/93 0.01520.001 0.01720.001 0.014%0.001 0.015%0.001 0.01420.001 0.01420.001 08/30/93 0.024%0.001 0.02210.001 0.023%0.001 0.021%0.001 0.01820.001 0.021%0.001 09/07/93 0.01320.001 0.01610.001 0.017%0.001 0.017%0.001 0.011%0.001 0.01320.001 09/13/93 0.01320.001 0.01520.001 0.01220.001 0.013%0.001 0.01420.001 '.012%0.001 09/20/93 0.01320.001 0.016+0.001 0.015%0.001 0.014%0.001 0.012%0.001 0.01520.001 09/27/93 0.011%0.001 0.01320.001 0.014%0.001 0.014%0.001 0.011%0.001 0.01320.001 10/04/93 0.011%0.001 0.011%0.001 0.01120.001 0.011+0.001 0.00920.001 0.01020.001.

10/11/93 0.01820.001 0.01710.001 0.016%0.001 0.015%0.001 0.01420.001 0.01520.001 10/18/93 0.016%0.001 0.017%0.001 0.016%0.001 0.01520.001 0.01410.001 0.016%0.001 10/25/93 0.011%0.001 0.012%0.001 0.01320.001 0.015%0.001 0.012%0.001 0.012%0.001 11/01/93 0.00910.001 0.00810.001 0.01020.001 0.01120.001 0.01020.001 0.012%0.001 11/08/93 ~

0.01510.001 0.015%0.001 0.012%0.001 0.014%0.001 0.01320.001 0.015%0.001 11/15/93 0.022%0.001 0.02320.001 0.02020.001 0.02420.001 0.021%0.001 0.02020.001 11/22/93 0.01320.001 0.014%0.001 0.01620.001 0.014%0.001 0.01320.001 0.014%0.001 11/29/93 0.01420.001 0.01010.001 0.01610.001 0.012%0.001 0.012%0.001 0.01420.001 12/06/93 0.01920.001 0.02020.001 0.023+0.001 0.01920.001 0.01920.001 0.020%0.001 12/11/93 0.019%0.001 0.020 10.001 0.023%0.001 0.01920.001 0.01920.001 0.020%0.001 12/20/93 0.017%0.001 0.01710.001 0.01520.001 0.01720.001 0.014%0.001 0.017%0.001 12/27/93. 0.01320.001 0.014 %0.001 0.013%0.001 0.01320.001 0.012%0.001 0.01240.001 01/03/94 0.014%0.001 0.01610.001 0.014%0.001 0.01620.001 0.00910.001 '.016%0.001

TABLE 12 CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF AIR PARTICULATE SAMPLES 4

R-1 OFF-SITE STATION

• 7 Results in units of 1o- p'cpm + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL 1993 Co-60 <1.2 <2. 4 <2.4 <1.9 <2. 0 <3.2 n-54 <1.1 <1.6 <2.2 <1. 7 <1. 9 <2. 1 Cs-134 <1.4 <1.8 <2.7 <2.1 <1. 5 <1.8 Cs-137 <0.8 <1.5 <1 7 <1.7 <1. 0 <1. 6 b-95 <1.8 <2.4 <2.2 <2.5 <2.6 <2.8 Zr-95 <2.2 <3.1 <4 ' <3 ' <3.9 <4.0 Ce-141 <0.9 <1.7 <2.7 <2.6 <1.9 <1.8 Ce-144 <3.0 <6.1 <8 8 <7 ' <5.2 <5.4 u-106 <8,. 0 <12.5 <18.8 <16.0 <11 ' <14.3 u-103 <1. 0 <1.8 <2.4 <2.1 <1.9 <2.0 Be-7 60 + 92+8 54+8 109 + 8 69+8 89 + 10

-40 <14 16+8 239 + 15 209 + 12 54+ 8 <36 BaLa-140 <0.9 <6.9 <4.6 <4.9 <6.2 <6. 0 a-226 <10 <22 14+7 <16 + 7 <19 <19 I-131 <2.7 <3.8 <8 ~ 1 <8.3 <5.6 <7. 0 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.4 <2 ~ 0 <1. 7 <2.1 <2.4 <1.6 n-54 <1.3 <1. 6 <1. 3 <1.4 <1.2 <1.3 Cs-134 <1.2 <1. 4 <1. 5 <1.2 <1.6 <1.2 Cs-137 <1. 2 <1. 2 <1 4~ <1.2 <1.4 <0.9 Nb-95 <1.7 <2.6 <2.3 <1.9 <2.4 <1.9 Zr-95 <2.8 <3.2 <2.8 <2.4 <2.6 <1 '

Ce-141 <1.6 <1.8 <1.9 <1.3 <1. 8 <1.6 Ce-144 <4.3 <5.0 <4.7 <4.2 <4.8 <4.0 u-106 <9.9 <11.6 <12.6 <10.3 <11.7 <10.9 u-103 <1.4 <1.9 <1.7 <1.5 <1.6 <1.4 Be-7 74 + 86+ 8 94 + 9 88+ 6 80+ 7 59+ 7 K-40 28 + <27 <26 <12 9 + 5 14+5 BaLa-140 <3.8 <8.7 <10.4 <4.3 <8.0 <7.2 a-226 13 + <20 <18 7 + 5 <18 <14 I-131 <4.3 <6.3 <6.7 3.8 <4.8 <5.8 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• Location required the Technical Specifications.

• • - 'Other plant relatedby radionuclides.

83

TABLE 12 (Continued)

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

• Results in units of ao-3~ci m~ + 1 sigma NUCLIDES, JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1 ' <2.0 <2 ' <1.7 <2.0 <3 '

n-54 <1 ' <1.3 <1.2 <1.0 <2.2 <2.3 Cs-134 <1 ' <1.9 <1.5 <1.2 <2.8 <2.0 Cs-137 <1.3 <1.4 <1.6 <1.2 <2.0 <1.8 b-95 <1.7 <1.6 <1.8 <1.6 <3 ' <3.2 Zr-95 <2 ' <3.1 <2.8 <2.8 <4.6 <3 '

Ce-141 <1.8 <1.6 <1.7 <1.4 <3 ' <2.0 Ce-144 <4.6 <4.0 <5.0 <3.5 <9.8 <5.8 u-106 <13.6 <9.8 <12.9 <12.4 <18.8 <21.1 u-103 <1.7 <1.6 <1.7 <1.7 <2.7 <2.3 Be-7 73 + 8 87+8 73 + 8 96+7 83 + 9 106 + 11

-40 <26 <26 16+ 7 9+5 267 + 16 37 + 9 aLa-140 <1 3

~ <7.0 <7. 2 <7.7 <6. 1 <13 '

-226 <20 <10 + 6 <18 <13 <30 <23

-131 <6.0 <3.5 <5.2 <5.7 <8.2 <6.5 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES, JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1 ' <1.7 <1. 6 <1.6 <2. 2 <1.9 n-54 <1.3 <2.0 <1.6 <1.3 <1. 6 <1. 3 Cs-134 <1.4 <1.5 <1.5 <1.1 <1.4 <1. 0 Cs-137 <1.6 <1.2 <1.3 <1.0 <1.5 <1.2 Nb-95 <1.4 <2.2 <2.2 <1.7 <1.7 <2.0 Zr-95 <2 ' <3.9 <2.7 <2.7 <2.5 <2.7 Ce-141 <1-4 <2 ' <1 ' <1.4 <1.4 <1 6

~

Ce-144 <4.0 <5.5 <4.7 <3.8 <4.1 <4.2 Ru-106 <10.5 <11.3 <11.9 <10.3 <11.5 <11.0 u-103 <1.5 <2.1 <1.8 <1.4 <1.5 <1.5 Be-7 87+ 8 80+ 8 85+ 8 75+ 6 73 + 7 66+ 6 K-40 <11 37+ 8 46+ 8 36+ 6 15+ 6 47+ 6 BaLa-140 <6 ' <9.5 <6.2 <4. 2 <6.3 <5.2 a-226 11+4 <21 <19 <15 <17 <14 I-131 <3 4~ <7.0 <6. 5 <4.0 <5.4 <5.1 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Location required by the Technical Specifications.

• Other plant related radionuclides.

84

TABLE 12 (Continued)

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

• Results in units of 10-'@cia' 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1. 6 <2.5 <1.5 <1.0 <1.7 <3.5 n-54 <1 ' <2.0 <2.0 <1. 5 <1. 5 <2.3 Cs-134 <0.9 <2. 6 <1. 6 <1.2 <1.2 <2.2 Cs-137 <1i1 <1. 8 <1.6 <1.0 <1.5 <1.9 Nb-95 <1 5

~ <2. 0 <1.9 <1.4 <2 ' <3.2 Zr-95 <2.4 <3.6 <2.8 <2. 6 <2.9 <5.0 Ce-141 <1.2 <2.5 <1.5 <1.6 <1 8

~ <1.9 Ce-144 <4.0 <8. 0 <4.3 <4.7 <5. 1 <5.3 Ru-106 <9.7 <16.2 <14.9 <12.2 <11.8 <15.0 RU-103 <1.3 <2.1 <1.6 <1.5 <1. 5 <2.7 Be-7 69+ 6 73 + 8 77 + 7 85+ 7 68+8 84 + 10 K-40 11+ 4 210 + 13 <20 31+ 6 <21 52 + 11 BaLa-140 <4. 4 <4. 8 <7.5 <5.4 <6.8 <10.9 Ra-226 21+ 6 <28 12+7 <15 10+ 5 <22 I-131 <4. 6 <5.3 <5.3 <6.8 <4.9 <8.4 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.4 <2.4 <1.9 <1.7 <1.3 <1. 5 n-54 <1.9 <2 ' <1.7 <1.6 <1,7 <1.7 Cs-134 <1.5 <2.7 <1.5 <1.0 <1.7 <1.4 Cs-137 <1.3 <2.3 <1.7 <1.1 <1.4 <1.0 Nb-95 <2.5 <2.9 <1.8 <1.6 <1.6 <2.4 Zr-95 <3.6 <4.9 <4. 1 <2.8 <3.3 <3.0 Ce-141 <1.5 <3 ' <2. 0 <1 ' <1.8 <1.3 Ce-144 <4 ' <9.3 <4. 6 <3.6 <5.2 <3.8 Ru-106 <13.7 <20.7 <11. 1 <12.5 <13.6 <12.8 Ru-103 <1.7 <2.6 <1.9 <1.1 <2.0 <1.6 Be-7 70+ 8 91 + 10 68,+ 7 80+ 7 78+ 8 76+ 7 K-40 <27 225 + 15 13+7 <10 38 + 8 <15 BaLa-140 <7.7 <5.6 <6.6 <1.0 <9.3 <8. 6 Ra-226 <17 29 + 10 14+8 <16 <20 10+ 6 I-131 <4.3 <10.0 <7. 0 <3.5 <4. 8 <5.0 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Location required by the Technical Specifications.

• • Other plant related radionuclides.

,85

TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES 8

R-4 OFF-SITE STATION

• V Results in units of 10-~Cia +,1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE Co-60 <2. 2 <1. 6 <1.8 <1.5 <1.7 <2.1 n-54 <1. 1 <2 ~ 1 <1.6 <0.9 <1.8 <2.1 Cs-134 <1.3 <1. 4 <1.4 <1 ' <1.4 <2.4 Cs-137 <1.0 <1. 5 <1.4 <1.0 <1.4 <2.1 b-95 <1.8 <2. 0 <1.7 <1.7 <1.6 <2.8 Zr-95 <2.5 <3. 1 <3.0 <2 ' <1.8 <3.6 Ce-141 <1.2 <1.5 <1.7 <1.3 <1.5 <3.2 Ce-144 <3 7 <5.6 <4.4 <3.6 <4.3 <9.0 u-106 <8.9 <12.3 <11.1 <9.8 <11.9 <19.3 Ru-103 <1.6 <1 ' <1.7, <1.4 <1.6 <2 '

Be-7 54+6 73 + 7 71+7 84+7 59+7 76+9

-40 <18 17+7 <20 <18 <4 239 + 15 BaLa-140 <3. 9 <0.9 <13. 1 <5.3 <5.4 <5.8 a-226 <16 <20 <16 <13 8 + 5 <29

-131 <4.0 <3.4 <8.1 <4.4 <4.1 <10.1 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.4 <2 ' <2.4 <1.7 <2 ' <1.4 n-54 <1.3 <1 ' <1.6 <1.1 <1.6 <1 '

Cs-134 <1.3 <1 ' <1.4 <0.9 <1.4 <1 '

Cs-137 <1.1 <1.5 <1.5 <1.2 <1.2 <0.9 b-95 <1.5 <2.1 <2.2 <1 ' <2.3 <1. 6 Zr-95 <2.6 <2.3 <3.9 <2.6 <3.2 <2 ~ 0 Ce-141 <1 ' <1.7 <2.1 <1.4 <1.6 <1. 6 Ce-144 <4.2 <4.2 <5.1 <4. 1 <5.0 <4. 0 u-106 <10.7 <8.7 <14.4 <9.5 <12.4 <10.3 u-103 <1.6 <1.8 <1.7 <1.2 <1.8 <1.5 Be-7 66+ 6 87+ 8 92+ 8 61+ 6 75+7 61+ 7

-40 36+7 <24 31+ 7 25+ 6 52 + 9 29+ 6 BaLa-140 <4. 4 <4.8 <7. 0 <4.7 <6.2 <5.8 a-226 6+4 10+ 5 14 + 7 <14'3.

<20 8 + 4 I-131 <3. 8 <5.0 <7.5 6 <5.0 <4.4 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• Location required the Technical Specifications.

• • - Other plant relatedby radionuclides.

86

TABLE 12 (Continued)

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

• Results in units of 10- gCi~m + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1.8 <1.5 <1.6 <1. 5 <1 6~ <1. 6 n-54 <1.1 <1.4 <1.1 <1. 6 <1. 8 <2. 0 Cs-134 <1.0 <1.5 <1.2 <2. 0 <1.3 <1. 6 Cs-137 <0.8 <1.2 <1.2 <1. 4 <1.3 <1.4 b-95 <1.9 <1.6 <1.9 <2. 2 <2. 0 <2.2 Zr-95 <2.2 <2.2 <2.2 <3. 6 <3.2 <3 '

Ce-141 <1.2 <1.3 <1.4 <2.5 <1.6 <1.8 Ce-144 <3.0 <3.6 <4.3 <6.7 <5 1~ <4.7 u-106 <9.3 <11.4 <9.7 <13.8 <12.5 <10.1 u-103 <1.5 <1.5 <1.4 <2.1 <1.4 <1.8 Be-7 44 + 5 66+ 86+7 97 + 7 70+7 90+ 8

-40 BaLa-140 28+

<4.7 6 <13

<3.1 7

13+5

<6 ~ 1 184 +

<5.6 ll, 44 + 8

<0.9 44+8

<3. 8 a-226 7 + 4 11+ 5 <15 <22 <18 <20 I-131 <4. 0 <2.9 <4.7 <7 ' <5.1 <6.2 thers ** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1. 1 <2. 0 <2 ~ 0 <1. 6 <2.6 <1 ~ 3 n-54 <1.3 <1.8 <1.4 <1-6 <1.7 <F 1 Cs-134 <1 0

~ <1 5 <1 2

~ <1.5 <1 ~ 3 <1 1

~

Cs-137 <1.3 <1. 1 <1.2 <1.3 <1 ~ 6 <0.8 Nb-95 <1.3 <2.3 <1.9 <1.9 <2 ' <1.8 Zr-95 <2.2 <2.6 <2.5 <2.9 <2.7 <2.1 Ce-141 <1.4 <1.6 <1.8 <2.0 <1.4 <1.4 Ce-144 <4.2 <3 ' <5.0 <5.7 <4 ' <3.7 u-106 <8.8 <12.5 <10.7 <12.3 <13.5 <9.8 Ru-103 <1.2 <1.6 <1.7 <1.7 <1.6 <1.2 Be-7 77 + 7 85+ 8 74+ 7 78+ 6 70+ 7 61+ 6 K-40 16+ 4 19 + 6 <14 139 + 10 10+ 5 <17 BaLa-140 <4. 7 <7.4 <8.9 <4.8 <7. 5 <5.9 a-226 <13 <18 <17 <20 <18 17 + 4 I-131 <3.4 <5.2 <6.1 <5.0 <4.2 <5.6 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• Location required by the Technical Specifications.

• • Other plant related radionuclides.

87

TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES D2 OFF-SITE STATION

• Results in units of 10-~~ci m3 ii sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL 1993 Co-60 <1.8 <2 ' <1. 4 <1.5 <2.7 <2. 1 n-54 <1.2 <1.8 <1.7 <1. 6 <2.4 <1. 6 Cs-134 <1 ' <2.5 <1.7 <1. 0 <2 ' <1. 6 Cs-137 <0.9 <1.8 <1.4 <1.2 <2.4 <1. 4 Nb-95 <1.2 <2.3 <1 ' <1.8 <2.8 <2.0 Zr-95 <1.8 <3.6 <2.9 <2.8 <4.4 <3.0 Ce-141 <1.2 <2.5 <1.6 <1.6 <2.9 <1.6 Ce-144 <3.6 <8.0 <4.2 <3. 6 <9.6 <4.9 RQ-106 <8.2 <18.1 <11.3 <10. 1 <19.2 <14.4 RQ-103 <1.4 <2.0 <1.5 <1.3 <2.7 <2.0 Be-7 51+ 5 82+7 74 + 7 97 + 7 96+ 8 96+ 9 K-40 <8 216 + 14 <11 13+ 5 251 + 16 24+7 aLa-140 <4. 9 <4.1 <5.6 <6. 1 <7. 0 <8.7 x-226 <12 <25 <17 <14 <29 <17

-131 <5.1 <5.2 <4.0 <5.4 <7.8 <5.2 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1. 3 <1. 6 <2.8 <1.7 <1.9 <1.9 n-54 <1. 3 <1.4 <1-6 <1.3 <2. 0 <1.3 Cs-134 <1.5 <1. 3 <1.3 <1.0 <1. 3 <1.3 Cs-137 <1.2 <1.3 <1.6 <1.2 <1. 1 <1.1 Nb-95 <1.4 <1.5 <3 3 <1.9 <2.4 <2.4 Zr-95 <1.7 <2.5 <3.7 <2.4 <3.0 <3. 0 Ce-141 <1.3 <2.1 <2. 1 <1.4 <1. 8 <1.8 Ce-144 <3.5 <5.3 <5.7 <4.5 <4.3 <4.3 RQ-106 <10.5 <10.6 <11.8 <7.9 <9.14 <9.1 RQ-103 <1.4 <2.2 <1.8 <1.5 <1.7 <1.7 Be-7 86+ 7 91+ 9 74+ 8 80+ 7 70+7 70+ 7 K-40 <17 30+ 8 42+9 10+ 4 26+7 26+7 BaLa-140 <6.2 <10.1 <4. 6 <3 3

~ <7.5 <7.5 Ra-226 <14 <19 <19 <15 <16 <16 1-131 <3.4 <7.0 <7. 6 <4.2 <6.1 <6.1 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• Other plant related radionuclides.

88

TABLE 12 (Continued)

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

• Results in units of 10-gCQm + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1.4 <1. 6 <2 ' <1.4 <2. 0 <2.3 n-54 <1.2 <2.0 <2.0 <1.4 <1.6 <2.4 Cs-134 <1.1 <2.2 <2.6 <1.1 <1 ' <2.5 Cs-137 <0 ' <2.0 <2 ' <1 ' <1.5 <1.8 b-95 <1.3 <2.3 <3.0 <1 ' <1.9 <3.1 Zr-95 <2.2 <3 ' <4.0 <2.3 <3.1 <4.4 Ce-141 <1.4 <2.6 <3.4 <1 ' <1.6 <3 '

Ce-144 <3.6 <8.0 <9 ' <4.1 <4.6 <8.6 u-106 <8.7 <19.1 <19.0 <9.4 <13.3 <20.6 u-103 <1 ' <2 ' <2 ' <1 7

~ <1.7 <2.6 Be-7 61 + 93+8 87+ 9 94+7 91 + 8. 102 + 9

-40 15 + 216 + 14 233 + 14 36+ 6 <20 231 + 15 BaLa-140 <0.9 <5.7 <6.6 <5.9 <6.9 <8.7 a-226 <14 <27 <29 <16 <17 <31 I-131 <5.2 <6 ' <13.7 <6.4 <5.8 <10.5 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <2 ~ 3 <1. 6 <2. 0 <1.0 <1.6 <1.2 n-54 <2.1 <2.1 <1.9 <0.8 <1 ' <1.2 Cs-134 <1.7 <1.8 <1.6 <1.1 <1.6 <1.3 Cs-137 <1.1 <1.5 <1.3 <1.2 <1.3 <1.0 Nb-95 <2 ' <2.5 <1 ' <1.8 <2 ' <1.6 Zr-95 <2 ' <2.6 <2.3 <2.6 <3 ' <1.8 Ce-141 <1.4 <1.8 <1.8 <1.4 <1.6 <1.3 Ce-144 <4.4 <5.2 <4.6 <4.0 <4 ' <3.5 Ru-106 <14.1 <16.0 <15.8 <10.2 <11.2 <10.4 u-103 <1 ' <1 ' <1.5 <1.5 <1.4 <1 '

Be-7 76+ 8 125 + 10 105 + 8 80+ 6 69+7 69+7

-40 <21 <4 18 + 6 33+ 6 <20 12+4 BaLa-140 <7.4 <1.9 <7. 0 <4.9 <8.1 <5.6 a-226 <17 <19 <17 10+ 5 <18 <13 I-131 <4.5 <8.7 <5 ' <4.3 <5.7 <5.2 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• • - Other plant related radionuclides.

89

TABLE 12 (Continued)

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

• Results in units of 10-'~ci m + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1.5 <1. 2 <1. 7 <0. 8 <1. 4 <2.0 n-54 <1.4 <1.4 <1 ' <1.2 <1. 5 <1.9 Cs-134 <1.1 <1.2 <1.2 <1.0 <1.2 <2.3 Cs-137 <1 ' <1.4 <1.4 <1.0 <1.1 <2.0 b-95 <2 ' '<1. 8 <1.6 <1.3 <1.8 <2-8 Zr-95 <2 ' <2.9 <2.8 <1.6 <3.0 <3 '

Ce-141 <1.6 <1.3 <1.3 <1.3 <1.6 <2.9 Ce-144 <4.4 <4.4 <4. 0 <3.2 <4.8 <7 '

u-106 <10. 1 <10.1 <10.8 <9.7 <11.3 <17.5 u-103 <1. 6 <1.4 <1.6 <1.3 <1.4 <2.1 Be-7 61 + 96+7 69+ 6 110 + 8 72+7 94+ 9

-40 22 + <12 <16 11+ 4 28 + 7 216 + 14 aLa-140 <7. 2 <0.9 <4 ' <5. 0 <5.5 <5.0

.a-226 <15 <17 <16 <13 <17 <27

-131 <5.6 <3. 7 <3.8 <4. 5 <4. 8 <10.2 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1. 6 <1.8 <1 ~ 6 <1. 6 <1.8 <1.4 n-54 <1 ' <1.6 <1 ' <1.2 <1.4 <1.2 Cs-134 <0.9 <1.2 <1.4 <1. 1 <1.2 <0.9 Cs-137 <1.0 <1.2 <1.3 <1.0 <1.2 <1. 0 b-95 <1.3 <2.4 <1.7 <1.3 <2.0 <1.8 Zr-95 <1.8 <3.0 <2.1 <1.8 <2.8 <2.4 Ce-141 <1 ' <2.0 <1.5 <1.0 <1.6 <1.4 Ce-144 <3.5 <4.6 <3.9 <3 ' <4.6 <3.4 Ru-106 <7.9 <10.4 <10.7 <10.1 <10.2 <8.1 u-103 <1.3 <1.6 <1.5 <1.1 <1.4 <1.4 Be-7 72 + 87+ 8 97 + 8 69+ 6 69+ 7 60+ 6

-40 <8 9+5 <14 <8 41+7 9 + 4 BaLa-140 <5.4 <8.6 <4. 8 <5.4 <7. 1 <8.2 a-226 <13 <15 11+5 <14 <16 11+4 I-131 <4.9 <5.9 <6. 1 <3.4 <4.9 <4.9 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• • - Other plant related radionuclides.

r 90

TABLE 12 (Continued)

CONCENTRATZON OF GAMMA EMZTTERS ZN MONTHLY COMPOSZTES OF NMP AZR PARTZCULATE SAMPLES G OFF-SITE STATION

• Results in units of 10- pCifm + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL 1993 Co-60 <1.2 <1. 5 <2. 0 <2. 0 <2. 1 <2. 1 n-54 <1.1 <1.7 <1 ' <1.5 <1. 6 <1.9 Cs-134 <1.0 <1.5 <2.3 <1.9 <2.4 <2.2 Cs-137 <0.7 <1 ' <1.6 <1.5 <1.9 <1.8 Nb-95 <1.4 <2 ' <2.5 <2 ' <2.8 <2.8 Zr-95 <2.2 <2.8 <3.4 <2.9 <4.5 <4.0 Ce-141 <1.1 <1.6 <2.4 <2.3 <2.7 <3.0 Ce-144 <3.0 <5.2 <7.3 <6.2 <8.1 <8.1 Ru-106 <6.9 <15.5 <17.8 <13.4 <16.9 <18.2 Ru-103 <1.2 <1.7 <2.0 <1.9 <2 ' <2.5 Be-7 58+ 5 74+7 62+ 7 94 + 7 61+ 8 92+ 9 K-40 <15 31+ 6 205 + 13 166 + 10 222 + 14 186 + 13 BaLa-140 <5.9 <8.4 <5.0 <5.6 <5.7 <5.4 Ra-226 <13 9 + 6 <26 <21 17 + 10 27+1 I-131 <2.7 <4.1 <7.2 <8. 6 <7 ~ 3 <9.8 Others** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.3 <2.2 <2.0 <0.8 <2.0 <1 7

~

n-54 <1.2 <2.0 <1.5 <0.9 <1.6 <0.9 Cs-134 <1 ' <2.2 <1-2 <1.0 <1 ' <1. 1 Cs-137 <0.8 <1.8 <1.2 <0.8 <1.4 <1. 0 Nb-95 <1 ' <3.0 <1.9 <1.2 <2.0 <1.7 Zr-95 <1.6 <3.9 <2.6 <2.1 <2.9 <2.0 Ce-141 <1.2 <3 ~ 1 <1.8 <1.3 <2.2 <1.5 Ce-144 <3.5 <8.3 <5.0 <3.6 <6.5 <3.4 Ru-106 <9.0 <21.0 <11.8 <8.1 <15.2 <7.4 Ru-103 <F 1 <2.6 <1.8 <0.9 <1.9 <1.5 Be-7 78 + 6 79+8 70 + 7 60+ 5 60+ 6 58+ 5 K-40 6 + 3 216 + 14 48 + 7 34 + 6 180 + 11 29+ 6 BaLa-140 <4. 2 <5.3 <7. 4 <3. 4 <4. 1 <4. 2 Ra-226 <13 <27 <18 7 + 4 <22 <12 I-131 <3 ' <12.5 <6.5 <3 ~ 2 <5.7 <5.5 thers** <LLD <LLD <LLD <LLD <LLD, <LLD

• Optional sample location.

• • - Other plant related radionuclides.

91

TABLE 12 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF AIR PARTICULATE SAMPLES t'1 ON-SITE STATION

• Results in units of 10-~~ci m3 + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1.5 <1.8 <2 ' <1.4 <1. 4 <2 '

n'-54 <1. 5 <1.6 <1.5 <1 ' <1.4 <2.3 Cs-134 <1. 2 <1.3 <1.3 <1.1 <1 ' <2.2 Cs-137 <1.1 <1 ' <1.4 <1.0 <1.4 <1.7 b-95 <1.7 <1.7 <2.2 <1.5 <1.9 <3.1 Zr-95 <2.4 <3.1 <2.6 <2.4 <2.7 <5.2 Ce-141 <1.4 <1.3 <1.8 <1.5 <1. 6 <2.0 Ce-144 <3.8 <4.4 <5.0 <4.0 <4. 5 <5.7 u-106 <10.4 <12.6 <12.1 <10.0 <14 ~ 6 <18 '

u-103 <1.3 <1 ' <1 ' <1.8 <1.4 <2.3 Be-7 55+ 6 102 + 8 82+ 8 96+7 76+7 95 + 11

-40 23+7 <16 46+8 8 + 5 <20 20+ 8 aLa-140 <3. 6 <4.2 <4.8 <6.3 <5. 1 <6. 1

-226 <17 12+ 6 <18 <14 10+5 <18

-131 <3.7 <3.8 <6.7 <5.1 <4.0 <5.8 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1 ' <1.5 <1 4

~ <1. 4 <1.2 <1.2 n-54 <1.0 <1.2 <1.0 <0.8 <1.2 <1.1 Cs-134 <1.0 <1.4 <1.0 <1 ' <1.0 <1.1 Cs-137 <0.8 <1.3 <1.0 <1 ' <1.1 <1.0 Nb-95 <1.5 <1.8 <1.2 <1.4 <1.5 <1.2 Zr-95 <2.0 <1.9 <1 ' <2.0 <2.4 <1.6 Ce-141 <1.2 <1.5 <1.7 <1.2 <1.4 <1.3 Ce-144 <3.8 <3.4 <4.5 <3.5 <4.4 <3.5 u-106 <8.4 <9.3 <12.7 <7.0 <9.9 <10.7 u-103 <1.5 <1.4 <1 ' <1.2 <1.3 <1.4 Be-7 92+7 99+ 8 76+7 72+ 6 69+ 6 65+ 6

-40 <11 11+5 35+ 7 <12 23 + 7 <13 BaLa-140 <4.0 <7. 0 <5.2 <2.5 <5.3 <6.9 a-226 <11 <15 <14 <11 <13 <12 I-131 <3.6 <4.4 <4.6 <2 ' <4.5 <5.3 Others** <LLD <LLD <LLD <LLD <LLD <LLD sample location.

• - Optional Other plant related radionuclides.

92

TABLE 12 (Continued)

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

• Results in units of 10- @Cia + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1 ~ 1 <1. 1 <2 ' <1.2 <2. 1 <2.4 n-.54 <1 0

~ <1.4 <1.5 <1.3 <1. 9 <1 '

Cs-134 <1. 1 <1.5 <1.1 <1.2 <2.4 <1.4 Cs-137 <0. 8 <1.2 <1 ' <1.0 <2.0 <1.5 b-95 <1.4 <1.7 <2 ' <1.9 <2.6 <2 '

Zr-95 <1.9 <2-8 <2.9 <2.4 <3.8 <2 '

Ce-141 <1.0 <1.3 <1-9 <1.6 <2.6 <1.7 Ce-144 <2.9 <4. 1 <3.9 <4.0 <8.6 <5.3 u-106 <8.2 <10.2 <12.3 <10.4 <16.1 <9.2 u-103 <1.2 <1.0 <1 ' <1.5 <2.2 <1.6 Be-7 74+ 6 79+7 73+7 96+7 74+7 100 + 8

-40 <13 <16 <17 35+ 6 218 + 14 <18 BaLa-140 <0.9 <4.3 <8.7 <5.4 <5.7 <6.4 a-226 <10 <16 14+7 <14 17 + 10 <17 I-131 <3.3 <3.3 <8.8 <6.0 <6.0 <4.9 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <2.4 <2.2 <1.8 <1.4 <1.9 <1.2 n-54 <1.6 <2.3 <1.3 <1.3 <1 ' <1.5 Cs-134 <1.3 <2.7 <1 ' <1.2 <1.7 <1 '

Cs-137 <1.5 <2.1 <1.1 <0.9 <1.7 <0.9 Nb-95 <1.7 <3 ' <1-9 <1 ' <2.7 <1.7 Zr-95 <3.5 <4 ' <2.4 <2.6 <3.9 <2.7 Ce-141 <1.4 <3.0 <1. 6 <1.3 <2.6 <1.7 Ce-144 <4.4 <8.8 <5. 0 <3.8 <7.2 <3.9

'u-106

<10.9 <20. 1 <14. 0 <10.0 <16.2 <9.6 Ru-103 <1-8 <2.7 <1. 9 <1.4 <2.1 <1.4 Be-7 62 + 8 104 + 9 72 + 7 67+ 6 57+7 68+ 6

-40 28 + 7 214 + 14 42+ 9 51+7 168 + 12 43 + 7 BaLa-140 <6.3 <4.8 <4.6 <3.4 <5.5 <1. 1 a-226 <14 <27 <19 <14 <24 <16 I-131 <3.8 <9.2 <5.7 <4. 0 <6.7 <7.3 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• • -Other plant related radionuclides.

93

TABLE 12 (Continued)

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

• Results in units of 10- ~ci m + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1. 2 <l. 6 <1.2 <1.9 <1.9 <1.5 n-54 <1 ~ 3 <1. 0 <1.5 <1 ~ 8 <1.6 <1 ~ 9 Cs-134 <1. 1 <1. 3 <1.4 <2.3 <1.4 <1.5 Cs-137 <1. 2 <1-4 <1.4 <1.8 <1.4 <1.4 Nb-95 <1.5 <1.7 <2.2 <2.8 <1.4 <2.0 Zr-95 <1.9 <2.8 <3.2 <4.3 <2.6 <3.7 Ce-141 <1.0 <1.4 <1.8 <2.8 <1.6 <1.9 Ce-144 <3.1 <4.6 <4.3 <7.7 <4.8 <6.1 Ru-106 <7.1 <11.8 <13.5 <19.2 <11.5 <15.6

<1.2 <1.2 <2.0 <2.3 <1.4 <1.7 Ru-103 Be-7 K-40 50+

9 + 5 6 60+

<18 6 85+

13+

9 6

ill 202

+ 9

+ 12 68+

<19 7 56+7

<20 aLa-140 <1.0 <6 0

~ <11.4 <8 ' <5.2 <6.8

-226 10+ 5 <18 17+7 <23 11+ 6 15+ 6

-131 <3 ~ 7 <4.1 <9.5 <9 ' <5. 6 <5. 6 Others** <LLD. <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.5 <1.5 <2.3 <1. 5 <1. 6 <1.8 n-54 <1.1 <1.8 <1.6 <1.0 <1.6 <1.2 Cs-134 <1.1 <1.4 <1.5 <1.2 <1.6 <1.1 Cs-137 <1 ~ 1 <1.4 <1.5 <0.9 <1 5

~ <0.7 Nb-95 <1.7 <2 ' <2 ' <1.5 <1.5 <1-9 Zr-95 <2.6 <3.1 <2.5 <2.2 <2.8 <2.4 Ce-141 <1.5 <1.7 <2 ' <1.4 <1.7 <1.7 Ce-144 <4 1~ <5.6 <5.5 <4.5 <4.6 <3.9 RU-106 <10.5 <13.0 <12.7 <8.1 <10.9 <11.6 Ru-103 <1.4 <1.7 <1.9 <1.4 <1.7 <1.7 Be-7 83 + 6 67 + 8 82 + 8 74+ 6 69 + 7 73 + 7 K-40 24+ 6 <22 23 + 8 18+ 6 19+ 6 35+7 BaLa-140 <5.2 <4.5 <7.4 <3. 8 <7. 4 <7.3 Ra-226 <16 <18 <16 <15 21+7 <14 I-131 <4.5 <5.9 <6.1 <3. 1 <5.2 <5.7 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• Other plant related radionuclides.

94

TABLE 12 (Continued)

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

• Results in units of 1o- pci~m + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL zmE 1993 Co-60 <2.2 <2. 0 <1 ' <1.7 <1 ' <2.3 n-54 <1.7 <1.6 <1.5 <1.8 <1. 5 <1.5 Cs-134 <1.2 <1.5 <1.6 <2.0 <1.3 <1.5 Cs-137 <1 ' <1.4 <1.5 <1.7 <1.2 <1.1 Nb-95 <1.4 <2.1 <1.5 <2.8 <2.2 <2.5 Zr-95 <1.8 <4.2 <3.2 <3.4 <3.4 <3.1 Ce-141 <1.5 <2.0 <1 ' <2.7 <1.7 <1.9 Ce-144 <4.1 <5.4 <4.6 <7.2 <5.0 <5.4 u-106 <12.1 <13.7 <12.0 <15.8 <13.0 <12.6 Ru-103 <1.4 <1.9 <2 ' <2.1 <1.6 <2.0 Be-7 55+ 6 68+7 60+ 8 102 + 8 61+ 6 98+8

-40 19+ 6 38 + 7 17 + 6 198 + 12 51+9 42+ 8 BaLa-140 <4.4 <7. 5 <1.4 <6.7 <5.4 <5. 1 Ra-226 14+ 6 <20 <16 <25 <19 <18 I-131 <5.4 <3.8 <9.6 <9.0 <5.7 <6.3 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.7 <2.3 <1.8 <1. 1 <2.0 <2.0 n-54 <2.0 <1.6 <1. 2 <1.3 <1.7 <1.6 Cs-134 <2.1 <1 ' <1. 3 <1. 3 <1.5 <1.4 Cs-137 <1.9 <1. 4 <1. 3 <1. 2 <1.3 <1. 3 b-95 <2.5 <2. 3 <2. 3 <1.7 <2.1 <1. 0 Zr-95 <3.5 <3.6 <2. 8 <2. 6 <3.7 <1.6 Ce-141 <2.5 <1.9 <2.0 <1.4 <2.0 <1.4 Ce-144 <7.5 <4.9 <5.1 <3.8 <5.4 <3.9 u-106 <15.1 <13.7 <10.7 <9.5 <12.7 <8.8 u-103 <2.1 <1.9 <1.8 <1.3 <1.9 <1.5 Be-7 73+7 69+ 7 82 + 8 72+ 6 57+7 66+ 7

-40 178 + 12 53 + 9 37+ 8 17+ 4 55+ 9 <13 BaLa-140 <4. 4 <5.3 <6.4 <8. 3 <7. 6 <8.8 a-226 <25 <18 <17 <14 <19 <14 I-131 <6.4 <6 ' <7.0 <3.8 <6. 1 <6.3 thers** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• • Other plant related radionuclides.

95

TABLE 12 (Continued)

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

• Results in units of 10- @Cia + 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL JUNE 1993 Co-60 <1. 6 <2.0 <1.5 ~ <1.4 <1.9 <2.0 n-54 <1 ' <1 ' <1. 7 <1.3 <1.6 <1.6 Cs-134 <1.1 <1.3 <1.4 <1.3 <1. 5. <1.4 Cs-137 <0.9 < 1.'4 <1.4 <1.1 <1. 5 <1.1 b-95 <1.5 <2.0 <2.2 <1.7 <2. 0 <1.8 Zr-95 <1.8 <3.1 <3.6 <2.9 <2.7 <2.5 Ce-141 <0.9 <1.4 <1.5 <1.6 <1.7 <1. 4 Ce-144 <2.4 <4.8 <4.7 <4.5 <4.5 <4.5 u-106 <8.7 <10-7 <14.6 <9.9 <10.8 <9.2 Ru-103 <1 ' <1.4 <1.6 <1.6 <1.5 <1.5 Be-7 44+6 69+ 7 66+8 78 + 49+ 7 73 + 8

-40 <12 19+ 6 <26 <14 <19 17+ 6 aLa-140 <6.0 <6.5 <7. 3 <5.6 <6. 2 <4.6 a-226 <12 <18 8 + 5 <14 <19 <19

-131 <3.1 <3.7 <4. 0 <5.8 <4. 6 <4.1 thers** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.9 <2.1 <2.0 <1 1

~ <2. 0 <1.3 n-54 <1.0 <1.5 <2.0 <1.6 <1.8 <1.0 Cs-134 <1.6 <1.5 <1 ' <1 ' <1.7 <1.2 Cs-137 <1.2 <1.6 <1 ' <1.1 <1.2 <1. 2 Nb-95 <1.8 <2.3 <2.0 <2.1 <2.4 <2. 0 Zr-95 <2.4 <2.6 <3 ' <3.0 <3.3 <2.8 Ce-141 <1.3 <1.6 <2.0 <1.6 <1.6 <1 '

Ce-144 <3.9 <4.4 <4.8 <4.5 <5.1 <4.2 RU-106 <10.1 <11.6 <14.9 <8.4 <12.6 <12.6 u-103 <1.2 <2.1 <2 ' <1.4 <1.8 <1.2 Be-7 76+ 7 73 + 8 74 + 8 78 + 76+ 8 62+ 6 K-40 <22 <26 14 + 7 36 + 16+ 6 <17 BaLa-140 <7. 1 <10.4 <6.1 <7. 5 <6.3 <6.9 Ra-226 <15 <16 <19 <15 <17 6 + 4 I-131 <4.1 <5.2 <6.4 <5.2 <5.4 <6.6 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location

• • - Other plant related radionuclides 96

TABLE 12 (Continued)

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

• Results in units of 10- @Cia + 1 sigma NUCLIDES ANUARY FEBRUARY RCH PRIL UNE 1993 Co-60 <1. 1 <2 ' <2. 1 <1 ' <2. 0 <2. 1 n-54 <0.9 <1. 6 <1.7 <1-2 <1.7 <1.7 Cs-134 <1. 0 <1.5 <2.3 <0.9 <2.5 <1. 5 Cs-137 <1. 1 <1.3 <1.8 <1 ' <1.7 <1.5 Nb-95 <1.5 <2.0 <2.7 <1.6 <2.7 <2. 1 Zr-95 <2.4 <2.8 <3.8 <1.9 <3.8 <3 ~ 7 Ce-141 <1.2 <1.5 <2.7 <1.4 <2. 6 <1 9

~

Ce-144 <3.1 e

<4.6 <7.7 <3.6 <8. 0 <5.3 Ru-106 <9.0 <11.2 <17.2 <6.7 <17. 1 <11.7 Ru-103 <1.0 <1.3 <2.2 <1 ' <2.2 <1.6 Be-7 47 + 5. 63+ 6 79 + 7 90 + 60+ 7 73 + 8 K-40 19 + 5 10+ 6 189 + 13 35 + 194 -+ 13 48+7 BaLa-140 <1. 0 <7.2 <5.7 <5.0 <5. 1 <7. 2 Ra-226 <16 <19 17+7 <13 <27 <20 I-131 <4.5 <3 3 <7.9 <5.4 <7.0 <6. 0 Others*+ <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES ULY UGUST SEPTEMBER CTOBER OVEMBER DECEMBER Co-60 <2.5 <1.9 <1. 6 <1.2 <1. 6 <1.6 n-54 <1 3 <2.0 <1.2 <1.1 <1. 0 <1.2 Cs-134 <1.4 <2.4 <1.2 <1.1 <1. 1 <0.9 Cs-137 <1 ' <1.8 <1.3 <0.9 <1.3 <0.9 Nb-95 <2.6 <2.8 <2.2 <1.2 <1.8 <1 '

Zr-95 <3.0 <4.1 <2.9 <2.4 <2.6 <1.7 Ce-141 <1 ' <2.8 <1.6 <1.2 <1.6 <1.4 Ce-144 <4.0 <8.0 <4.5 <3.5 <4,. 6 <4.0 Ru-106 <11. 6 <18.9 <11.3 <8.7 <11.2 <8.6 RU-103 <1.2 <2.4 <1. 6 <F 1 <1.4 <1.5 Be-7 78 + 90+ 8 71+7 59 + 49 + 6 60+ 6 K-40 21 + 232 + 14 77 + 4 18 + 40+ 7 46+ 6 BaLa-140 <1.2 <6. 6 <4.5 <2.7 <6.6 <6.7 Ra-226 <14 <26 <16 <13 8 + 5 <13 I-131 <4.0 <F 1 <6.0 <2.7 <4 ' <6. 5 Others** <LLD <LLD <LLD <LLD <LLD <LLD

• Optional sample location.

• • Other plant related radionuclides.

97

TABLE 13 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF-SITE STATIONS I-131 ACTIVITYpCI/m a 1 SIGMA LOCATION 01/05/93 <0.012 <0.014 <0.013 <0.009 <0.010 <0.011 <0.009 <0.009 <0.009 01/12/93 <0.016 <0.017 <0.014 <0.012 <0.014 <0.015 <0.010 <0.013 <0.011 01/19/93 <0.010 <0.012 <0.008 <0.013 <0.010 <0.015 <0.009 <0.008 <0.009 01/26/93 <0.011 <0.016 <0.015 <0.012 <0.011 <0.015 <0.009 <0.010 <0.009 02/02/93 <0.015 <0.017 <0.011 <0.014 <0.010 <0.012 <0.014 <0.014 <0.012 02/09/93 <0.014 <0.012 <0.013 <0.012 <0.009 <0.011 <0.014 <0.010 <0.010 02/16/93 <0.012 <0.014 <0.013 <0,010 <0.008 <0.010 <0.012 <0.008 <0.010 02/23/93 <0.015 <0.012 <0.011 <0.012 <0.012 <0.014 <0.012 <0.012 <0.011 03/02/93 <0.016 <0.009 <0.014 <0.010 <0.013 <0.011 <0.012 <0.010 <0.015 03/09/93 <0.011 <0.013 <0.020 <0.010 <0.009 <0.017 <0.010 <0.012 <0.016 03/16/93 <0.012 <0.014 <0.014 <0.013 <0.010 <0.014 <0.014 <0.013 <0.009 03/23/93 <0.012 <0.015 <0.010 <0.014 <0.013 <0.013 <0.010 <0.010 <0.012 03/30/93 <0.014 <0.020 <0.011 <0.013 <0.017 <0.014 <0.011 <0.018 <0.011 04/06/93 <0.016 <0.019 <0.012 <0.012 <0.017 <0.011 <0.013 <0.018 <0.011 04/13/93 <0.011 <0.013 <0.015 <0.011 <0.012 <0.019 <0.012 <0.011 <0.017 04/20/93 <0.013 <0.011 <0.010 <0.014 <0.010 <0.016 <0.013 <0.013 <0.009 04/27/93 <0.013 <0.012 <0.013 <0.014 <0.015 <0.019 <0.010 <0.017 <0.012 05/04/93 <0.013 <0.012 <0.014 <0.011 <0.012 <0.009 <0.012 <0.009 <0.012 05/11/93 <0.018 <0.011 <0.011 <0.015 <0.011 <0.016 <0.010 <0.018 <0.014 05/18/93 <0.011 <0.020 <0.009 <0.019 <0.010 <0.021 <0.013 <0.010 <0.008 05/25/93 <0.014 <0.014 <0.015 <0.012 <0.014 <0.016 <0.013 <0.011 <0.016 06/01/93 <0.011 <0.014 <0.019 <0.012 <0.008 <0.012 <0.017 <0.011 <0.018 06/08/93 <0.014 <0.011 <0.015 <0.017 <0.015 <0.016 <0.019 <0.013 <0.010

<0.020 <0.016 <0.015 <0.009 <0.017 <0.013 <0.012 <0.018 <0.'011 06/15/93 06/22/93 <0.011 <0.025 <0.012 <0.019 <0.012 <0.022 <0.011 <0.020 <0.011 06/29/93 <0.015. <0.024 <0.011 <0.021 <0.012 <0.022 <0.013 <0.017 <0.015

~ Sample locations required by Technical.Specifications 98

TABLE 13 (CONTINUED)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFF-SITE STATIONS I-131 ACTIVITYpCI/m3 a 1 SIGMA LOCATION 07/06/93 <0.022 <0.018 <0.013 '0.013 <0.021 <0.013 <0.014 <0.011 <0.017 07/13/93 <0.009 <0.012 <0.018 <0.031 <0.015 <0.018 <0.022 <0.012 <0.012 07/20/93 <0.017 <0.017 <0.022 <0.016 <0.018 <0.016 <0.016 <0.008 <0.018 07/27/93 <0.018 <0.015 <0.021 <0.015 <0.012 <0.018 <0.016 <0.014 <0.014 08/03/93 <0.013 <0.015 <0.015 <0.019 <0.017 <0.016 <0.014 <0.017 <0.012 08/10/93 <0.019 <0.022 <0.019 <0.017 <0.013 <0.024 <0.015 <0.013 <0.013 08/17/93 <0.017 <0.019 <0.014 <0.012 <0.015 <0.017 <0.013 <0.011 <0.014 08/24/93 <0.017 <0.013 <0.022 <0.015 <0.010 <0.014 <0.012 <0.019 <0.018 08/31/93 <0.016 <0.017 <0.015 <0.014 <0.012 <0.014 <0.010 <0.013 <0.012 09/07/93 <0.012 <0.011 <0.010 <0.017 <0.008 <0.014 <0.016 <0.020 <0.012 09/14/93 <0.014 <0.012 <0.021 <0.013 <0.014 <0.016 <0.014 <0.019 <0.009 09/21/93 <0.014 <0.012 <0.013 <0.014 <0.012 <0.017 <0.013 <0.012 <0.011 09/28/93 <0.012 <0.013 <0.015 <0.010 <0.014 <0.015 <0.011 <0.011 <0.010, 10/05/93 <0.013 <0.016 <0.013 <0.015 <0.013 <0.019 <0.008 <0.012 <0.010 10/12/93 <0.015 <0.014 <0.013 <0.015 <0.012 <0.016 <0.011 <0;011 <0.010

<0.017 <0.011 <0.014 <0.014 <0.015 <0.014 <0.014 <0.012 <0.011 10/19/93

<0.014 <0.013 <0.013 <0.015 <0.014 <0.011 <0.017 <0.014 <0.011 10/26/93

<0.011 <0.011 <0.014 <0.016 <0.013 <0.013 <0.016 <0.011 <0.010 11/02/93

<0.018 <0.017 <0.014 <0.012 <0.014 <0.015 <0.012 <0.012 11/09/93 <0.015

<0.017 <0.011 <0.020 <0.012 <0.012 <0.019 <0.012 <0.012 11/16/93 <0.013

<0.016 <0.013 <0.020 <0.014 <0.017 <0.011 <0.017 <0.012 11/23/93 <0.014

<0.008 <0.013 <0.022 <0.014 <0.013 <0.016 <0.016 <0.009 11/30/93 <0.016

<0.014 <0.015 <0.014 <0.019 <0.012 <0.015 <0.012 <0.012 12/07/93 <0.014

<0.014 <0.015 <0.014 <0.016 <0.014 <0.014 <0.012 <0.011 12/12/93 <0.012

<0.012 <0.015 <0.014 <0.018 <0.013 <0.013 <0.009 <0.018 12/21/93 <0.013

<0.014 <0.011 <0.014 <0.012 <0.015 <0.010 <0.015 <0.014 12/28/93 <0.013

<0.013 <0.014 <0.013 <0.012 <0.016 <0.012 <0.012 <0.017 01/04/94 <0.005 ggf a~+cat rec~by Qgplceggclfirggpe W W W M

TABLE 14 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE STATIONS I-131 ACTIVITYpCi/m a 1 SIGMA LOCATION 01/04/93 <0.014 <0.010 <0.017 <0.012 <0.017 <0.013 01/11/93 <0.013 <0.015 <0.009 <0.010 <0.016 <0.007 01/18/93 <0.015 <0.008 <0.015 <0.014 <0.015 <0.014 01/25/93 <0.010 <0.013 <0.012 <0.015 <0.010 <0.012 02/01/93 <0.012 <0.014 <0.010 <0.014 <0.016 <0.008 02/08/93 <0.012 <0.012 <0.010 <0.011 <0.009 <0.009 02/16/93 <0.012 <0.012 <0.011 <0.012 <0.009 <0.009 02/22/93 <0.017 <0.011 <0.014 <0.012 <0.015 <0.014 03/01/93 <0.017 <0.011 <0.010 <0.022 <0.013 <0.012 03/08/93 <0.019 <0.009 <0.014 <0.018 <0.012 <0.010 03/15/93 <0.010 <0.018 <0.021 <0.019 <0.016 <0.015 03/22/93 <0.008 <0.011 <0.013 <0.011 <0.012 <0.009 03/29/93 <0.012 <0.014 <0.011 <0.018 <0.014 <0.009 04/05/93 <0.010 <0.016 <0.014 <0.018 <0.014 <0.011 04/12/93 <0.014 <0.019 <0.013 <0.012 <0.013 <0.015

<0.018 <0.010 <0.014 <0.013 <0.012 <0.010 04/19/93

<0.018 <0.012 <0.012 <0.018 <0.012 <0.011 04/26/93

<0.010 <0.013 <0.010 <0.018 <0.010 <0.018 05/03/93

<0.010 <0.019 <0.012 <0.015 <0.012 <0.008 05/10/93 -

<0.014 <0.013 <0.009 <0.019 <0.015 <0.013 05/17/93

<0.012 <0.009 <0.019 <0.013 <0.016 <0.012 05/24/93

<0.011 <0.010 <0.011 <0.014 <0.020 <0.011 06/01/93

<0.016 <0.010 <0.024 <0.015 <0.010 <0.021 06/07/93

<0.022 <0.011 <0.022 <0.014 <0.014 <0.013 06/14/93

<0.008 <0.016 <0.015 <0.013 <0.018 <0.012 06/21/93

<0.013 <0.020 <0.011 <0.022 <0.010 <0.023 06/28/93 ann

TABLE 14 (CONTINUED)

NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE STATIONS I-131 ACTIVITYpCi/m a 1 SIGMA LOCATION 07/06/93 <0.022 <0.013 <0.014 <0.013 <0.014 <0.015 07/12/93 <0.016 <0.017 <0.016 <0.016 <0.021 <0.012 07/19/93 <0.014 <0.016 <0.012 <0.014 <0.014 <0.015 07/26/93 <0.010 <0.019 <0.013 <0.016 <0.012 <0.013 08/02/93 <0.013 <0.015 <0.010 <0.015 <0.011 <0.018 08/09/93 <0.008 <0.020 <0.017 <0.019 <0.017 <0.020 08/16/93 <0.011 <0.017 <0.019 <0.016 <0.014 <0.015 08/23/93 <0.009 <0.011 <0.022 <0.012

<0.018'0.016 <0.013'0.013 08/30/93 <0.012 <0.014 <0.023 <0.012 09/07/93 <0.012 <0.012 <0.012 <0.019 <0.015 <0.015 09/13/93 <0.013 <0.013 <0.012 <0.023 <0.017 <0.010 09/20/93 <0.012 <0.013 <0.015 <0.016 <0.020 <0.013 09/27/93 <0.009 <0.013 <0.016 <0.012 <0.011 <0.012 10/04/93 <0.009 <0.013 <0.013 <0.014 <0.011 <0.011 10/11/93 <0.013 <0.015 <0.012 <0.016 <0.016 <0.014 10/18/93 <0.013 <0.016 <0.009 <0.010 -

<0.013 <0.010 10/25/93 <0.007 <0.012 <0.015 <0.016 <0.013 <0.009

<0.010 <0.010 <0.019 <0.012 <0.014 <0.016 11/01/93

<0.011 <0.011 <0.012 <0.018 <0.014 <0.014 11/08/93

<0.011 <0.009 <0.014 <0.019 <0.013 <0.013 11/15/93

<0.013 <0.017 <0.014 <0.021 <0.014 <0.018 11/22/93

<0.011 <0.013 <0.010 <0.012 <0.016 <0.010 11/29/93

<0.012 <0.016 <0.012 <0.015 <0.015 <0.013 12/06/93

<0.012 <0.016 <0.012 <0.015 <0.015 <0.013 12/11/93 12/20/93 <0.013 <0.015 <0.013 <0.015 <0.016 <0.014'0.012 12/27/9 <0.013 <0.015 <0.011 <0.013 <0.019

<0.011 <0.013 08 <0.013 <0.018 0.010, 01/0

TABLE 15 CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 1 sigma LOCATION NUCLIDES 4-05-93 4-19-93 5-03-93 5-17-93 6-07-93 6-2 1-93 60 -40 1580 + 68 1590 + 69 2680 + 73 2720 + 73 1540 + 75 1770 + 72 Cs-134 <6.5 <6.2 <10.6 <10.6 <7.6 <6.0 Cs-137 <6.9 <6.5 <8.2 <8 ' <6.8 <5.8 Ba/La-140 <6.4 <8.6 <7.6 <7-1 <12.1 <9.0 a-226 <126 <127 <172 145 + 72 <140 <131 thers <LLD <LLD <LLD <LLD <LLD <LLD 55 -40 2620 + 72 1440 + 68 1450 + 73 1520 + 67 1490 + 76 1620 + 78 Cs-134 <9.9 <5.8 <7. 0 <6.3 <7.3 <8.0 Cs-137 <8. 1 <6.3 <7. 2 <6.8 <5.9 <6.6 Ba/La-140 <8.7 <8.7 <11. 5 <4.6 <9.9 <7.4 a-226 <179 111 + 45 <120 <116 71 + 44 <123 thers <LLD <LLD <LLD <LLD <LLD <LLD

-40 1710 + 71 2560 + 72 1550 + 75 1600 + 69 2730 + 75 2680 + 72 Cs-134 <5. 2 <9.4 <6.7 <6.2 <10. 1 <10.3 Cs-137 <6.8 <8.1 <7.2 <6.3 <8.3 <8.7 Ba/La-140 <7.8 <7 ' <8.7 <8.5 <7.8 <6.6 a-226 <121 <176 <114 <124 <177 <179 thers <LLD <LLD <LLD <LLD <LLD <LLD 102

TABLE 15 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 1 sigma LOCATION NUCLIDES 4-05-93 4-19-93 5-03-93 5-17-93 6-07-93 6-21-93

-40 1480 + 76 1270 + 71 1540 + 67 1560 + 77 1490 + 68 1410 + 63 Cs-134 <7.1 <7. 1 <6.1 <7.2 <5.6 <5.8 Cs-137 <6.9 <7. 0 <6.5 <6.3 <6.8 7.0 Ba/La-140 <8.9 <7 ' <6.9 <12.9 <7.1 <8.8 a-226 <120 <119 <129 <126 <120 112 + 54 thers <LLD <LLD <LLD <LLD <LLD <LLD

-40 1570 + 67 2610 + 72 1490 + 66 1650 + 69 1530 + 67 1790 + 72 Cs-134 <5. 6 <10.1 <5. 6 <6.2 <5.7 6.6 Cs-137 <6.2 <8.4 <6.8 <6. 3 <6.3 <6.4 Ba/La-140 <7.4 <7.4 <10.3 <6.8 <10.1 <8.2 a-226 141 + 55 218 + 64 <127 <130 88 + 48 <125 thers <LLD <LLD <LLD <LLD <LLD <LLD 65* -40 1190 + 58 1700 + 71 1590 + 71 2450 + 70 1790 + 73 1370 + 65 (Control) Cs-134 <5.6 <6. 6 <6. 5 <10.1 <5.9 <6. 5 Cs-137 <5.9 <6.5 <6.3 <8.0 <6.2 <6.1 Ba/La-140 <10.1 <6.5 <8.6 <7.3 <6.7 <9.1 a-226 101 + 56 <127 <125 165 + 64 <124 129 + 54 thers <LLD <LLD <LLD <LLD <LLD <LLD

• Technical Specification location.

TABLE 15 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 1 sigma LOCATION NUCLIDES 7-06-93 7-19-93 8-02-93 8-16-93 9-07-93 9-20-93 60 -40 1320 + 62 1450 + 74 2650 + 73 1720 + 71 1420 + 64 1580 + 83 Cs-134 <7.4 <7 ' <10 ' <8. 4 <5.6 <7.6 Cs-137 <7.0 <5.1 <8.0 <6.0 <5.9 <7 '

Ba/La-140 <9.6 <9.5 <9.1 <9.9 <6.2 <11.6 a-226 117 + 50 <103 <181 127 + 54 <118 <151 thers <LLD <LLD <LLD <LLD <LLD <LLD 55 -40 1600 + 68 2530 + 71 1470 + 74 1410 + 78 2690 + 73 1400 + 64 Cs-134 <6.0 <10.3 <7.5 <8.4 <10.1 <5.6 Cs-137 <6.5 <7.5 <7.3 <8.1 <8.1 <6.4 Ba/La-140 <9.6 <6.3 <9.3 <13 ' <9.2 <11.0 a-226 <115 91 + 57 56 + 37 112 + 54 163 + 42 60 + 37 thers <LLD <LLD <LLD <LLD <LLD <LLD 50 -40 1350 + 71 1400 + 64 1360 + 64 1440 + 65 1630 + 69 1430 + 75 Cs-134 <7.2 <6. 5 <5.3 <5.6 <6.2 <6. 1 Cs-137 <6..4 <6. 0 <6.4 <5.8 <6.3 <6.9 a/La-140 <10.9 <6.9 <7.8 <10.1 <7.4 <7 '

a-226 <121 124 + 53 148 + 49 <124 <130 <112 thers <LLD <LLD <LLD <LLD <LLD <LLD 104

TABLE 15 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 1 sigma LOCATION NUCLIDES 7-06-93 7-19-93 8-02-93 8-16-93 9-07-93 9-20-93

-40 1490 + 67 1630 + 70 2700 + 73 1540 + 68 1420 + 63 1480 + 66 Cs-134 <5.6 <7.0 <9.9 <6. 2 <5.3 <5.6 Cs-137 <6.5 <6.5 <7.8 <6.5 <6.5 <7.2 Ba/La-140 <9.4 <7.0 <7.8 <8.9 <7.9 <14.7 a-226 <121 <126 203 + 65 112 + 41 132 + 49 114 + 48 thers <LLD <LLD <LLD <LLD <LLD <LLD

-40 2720 + 73* 1440 + 64 1530 + 67 1390 + 63 1640 + 70 1670 + 71 Cs-134 <10.0 <6.7 <6.4 <6.4 <6.4 <6.1 Cs-137 <8.1 <7.5 <6.1 <5.9 <6.4 <5.2 Ba/La-140 <8.4 <10.9 <6.9 <5 ' <8.6 <9.3 a-226 189 + 86 97 + 49 <131 78 + 33 <130 <115 thers <LLD <LLD <LLD <LLD <LLD <LLD 65*/73* -40 1750 + 71 2380 + 68 1570 + 71 1490 + 66 1560 + 83 1720 + 71 (Control) Cs-134 <6.2 <9.7 <7. 1 <6.8 <8.4 <5.9 Cs-137 <6.4 <8.3 <7.4 <6.8 <6.2 <6.5 a/La-140 <6.5 <7 ' <12.0 <8.2 <9.9 <8.2 a-226 <123 189 + 46 76 + 48 106 + 49 121 + 67 <125 thers <LLD <LLD <LLD <LLD <LLD <LLD

• Technical Specification location.

TABLE 15 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 1 sigma LOCATION NUCLIDES 10-04-93 10-18-93 11-01-93 11-16-93 12-06-93 12-20-93 60 -40 1510 + 66 2380 + 65 1630 + 68 1610 + 70 1570 + 75 1390 + 72 Cs-134 <5.4 <6.8 <6.8 <6. 6 <6.5 <6.6.

Cs-137 <6.4 <6.4 <6 ' <5. 8 <6.9 <7. 2 Ba/La-140 <9.2 <6.8 <9.2 <7. 0 <8.4 <8.9 a-226 <125 <151 <126 <125 133 + 38 <116 thers <LLD <LLD <LLD <LLD <LLD <LLD 55 -40 1480 + 74 1470 + 80 1460 + 74 1520 + 66 2280 + 64 1560 + 77.

Cs-134 <6.8 <8.3 <6.9 <5.6 <7.4 <7.0 Cs-137 <5.6 <7.3 <5.5 <5.8 <6.5 <6.2 Ba/La-140 <12.3 <10.4 <9.9 <8.3 <7.0 <9.4 a-226 <116 113 + 39 87 + 42 120 + 38 <152 96 + 38 thers <LLD <LLD <LLD <LLD <LLD <LLD 50 -40 1480 + 82 1420 + 65 1690 + 71 1490 + 66 2100 + 62 1290 + 75 Cs-134 <8. 5 <5.9 <6. 6 <6. 6 <7.1 <8. 0 Cs-137 <7. 2 <7.1 <5.7 <6. 1 <6.2 <8.6 Ba/La-140 <9.4 <8.6 <4.8 <6.4 <6.9 <7.4 a-226 191 + 74 159 + 48 <125 <117 131 + 48 130 + 61 thers <LLD <LLD <LLD <LLD <LLD <LLD 106

TABLE 15 (Continued)

CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 1 sigma OCATION NUCLIDES 10-04-93 10-18-93 11-01-93 11-16-93 12-06-93 12-20-93

-40 1470 + 65 1630 + 69 1390 + 65 1600 + 69 1550 + 76 1790 + 72 Cs-134 <5.6 <6. 1 <5.5 <5.7 <7.4 <6.4 s-137 <6.3 <5.3 <6.2 <6.2 <6.5 <6.3 Ba/La-140 <8.7 <8.5 <10.1 <8.2 <11.3 <9.0 a-226 87 + 48 <132 <118 <124 122 + 51 <130 thers <LLD <LLD <LLD <LLD <LLD <LLD

-40 1640 + 70 1520 + 75 2300 + 64 1550 + 81 1590 + 86 2400 + 67 Cs-134 <6. 6 <7+7 <6.5 <7 ' <7.2 <6.9 .

Cs-137 <6.8 <6.0 <6.1 <8 ' <8.0 <6 1

~

Ba/La-140 <9.6 <9.9 <6.3 <7.4 <10.4 <7.0 a-226 <127 75 + 29 234 + 79 108 + 60 <158 128 + 67 thers <LLD <LLD <LLD <LLD <LLD <LLD 65*/73* -40 1470 + 79 1350 + 71 1380 + 64 2190 + 63- 1730 + 86 2230 + 64 (Control) Cs-134 <7.5 <6.7 <6.0 <7 ' <7 ~ 7 <7.5 Cs-137 <7.4 <6.4 <7.4 <6.0 <7 ' <6.4 Ba/La-140 <8.5 <8.3 <10.1 <6 ' <10.4 <7.2 a-226 131 + 60 <120 <114 132 + 61 <154 <153 thers <LLD <LLD <LLD <LLD <LLD <LLD

• Technical Specification location.

M W W W W W

TABLE 16 CONCENTRATION OF ZODZNE - 131 ZN MILK (1)

Results in units of pCi/liter LOCATION 4-05-93 5-03-93 5-17-93 6-07-93 6-2 1-93 4-19-93'0.37 60 <0.50 <0.40 <0.45 <0.36 <0.66 55 <0.42 <0.57 <0.60 <0.40 <0.54 <0.38 50 <0.34 <0.34 <0.37 <0.38 <0.49 <0.45 7 <0.46 <0.44 <0.50 <0.60 <0.45 <0.35 4 <0.60 <0.44 <0.78 <0.37 <0.74 <0.47 65* <0.38 <0.37 <0.65 <0.35 <0.40 <0.61 LOCATION 7-06-93 7-19-93 8-02-93 8-16-93 9-07-93 9-20-93 60 <0.33 <0.61 <0.44 <0.37 <0. 33 <0.43 55 <0.36 <0.66 <0.36 <0.49 <0.43 <0.51 50 <0.39 <0.44 <0.46 <0.52 <0.41 <0.54 7 <0.44 <0.35 <0.36 <0.43 <0.38 <0.45 4 <0.41 <0.39 <0.49 <0.72 <0.66 <0.52 65*/73* <0.60 <0.52 <0.64 <0. 68 <0.61 <0.46 LOCATION 10-04-93 10-18-93 11-01-93 11-16-93 12-06-93 12-20-93 60 <0.49 <0.41 <0.45 <0.42 <0. 58 <0.37 55 <0.40 <0.36 <0.40 <0.51 <0.39 <0.39 50 <0.44 <0.34 <0.45 <0.46 <0.45 <0.58 7 <0.38 <0.44 <0.40 <0.37 <0.37 <0.39 4 <0.37 <0.40 <0.57 <0.38 <0.37 <0.44 65*/73* <0.34 <0.55 <0.34 <0.59 <0.34 <0.34

• Control Result. Technical Specification location.

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

108

TABLE 17A CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units of pCi/g (wet) + 1 sigma LOCATIO DATE SAMPLE TYPE Be-7 -40 I-131 Cs-134 Cs-137 a-226 AcTh-228 OTHER 9-13-93 Cabbage 0.16+0.03 2.99+0.ll <0.01 <0.01 <0. 01 0.20+0.08 <0.04 <LLD 9-13-93 Bean Leaves 1.33+0.04 6.95+0.12 <0.01 <0.02 <0.01 0.51+0.10 0.11+0.02 <LLD 9-13-93 Squash Leaves 0.96+0.04 2.90+0.09 <0.01 <0.01 <0.01 0.31+0.04 <0.03 <LLD 9-13-93 Tomatoes <0.05 2.28+0.07 <0.02 <0.01 <0.01 0.14+0.04 <0.02 <LLD 9-13-93 Squash Leaves 0.63+0.03 2.11+0.06 <0.01 <0.01 <0.01 <0.10 <0.02 <LLD P 9-13-93 Cabbage

• 0.19+0.04 1.92+0.09 <0. 02 <0.01 <0.01 0.28+0.06 <0.04 <LLD P 9-13-93 Swiss Chard 0.31+0.04 4.02+0.12 <0.02 <0.01 <0.01 0.20+0.06 <0.05 <LLD P 9-13-93 Collard Greens 0.42+0.04 4.04+0.13 <0.03 <0.01 <0.01 0.20+0.09 <0.05 <LLD L 9-13-93 Squash Leaves 0.85+0.03 1.93+0.06 <0.02 <0.01 <0.01 0.17+0.04 <0.02 <LLD L 9-13-93 Bean Leaves 0.84+0.03 2.00+0.06 <0.'01 <0.01 <0.01 0.16+0.05 <0.02 <LLD L 9-13-93 Pepper Leaves 0.42+0.03 4.70+0.09 <0.02 <0.01 <0.01 0.11+0.04 <0.03 <LLD Z 9-12-93 Grape Leaves 1.32+0.05 2.96+0.09 <0.02 <0.01 <0.01 0.15+0.08 <0.04 <LLD 9-13-93 Lettuce 0.61+0.07 4.80+0.20 <0.03 <0.03 <0.02 0.71+0.16 <0.09 <LLD Z

Z 9-13-93 Squash Leaves 0.85+0.03 3.50+0.08 <0.01 <0.01 <0.01 <0.12 0 '2+0 '1 <LLD 9-13-93 Beet Leaves 0.20+0.03 5.94+0.13 <0.02 <0.01 <0.01 0.22+0.08 <0.04 <LLD 9-13-93 Squash Leaves 1.70+0.04 3.35+0.09 <0.01 <0.01 <0.01 0.28+0.06 <0.03 <LLD 9-13-93 Grape Leaves 1.21+0.05 2.01+0.10 <0.01 <0.01 <0.01 0.25+0.06 <0.05 <LLD 9-13-93 Cabbage 0.09+0.04 2.23+0.11 <0.02 <0.01 <0.01 0.35+0.06 <0.05 <LLD 9-13-93 Cucumber Leaves 2.48+0.06 3.13+0.10 <0.01 <0.01 .007+.003 0.20+0.08 0.02+0.01 <LLD 9-13-93 Tomatoes <0.04 2.00+0.06 <0.01 <0.01 <0.01 0.14+0.03 <0 '2 <LLD

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

TABLE 17B CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) + 1 sigma LOCATXO DATE SAMPLE TYPE Be-7 -40 I-131 Cs-134 Cs-137 a-226 AcTh-228 OTHER 9-13-93 Cabbage 161+32 2990+109 <13 <12 <11 205+82 <45 =

<LLD 9-13-93 Bean Leaves 1330+45 6950+117 <15 <16 <12 507+96 108+18 <LLD 9-13-93 Squash Leaves 964+39 2900+91 <9 <9 <8 314+39 <28 <LLD 9-13-93 Tomatoes <51 2280+66 <19 <6 <7 141+40 <25 <LLD 9-13-93 Squash Leaves 632+26 2110+60 <12 <7 <6 <105 <23 <LLD 9-13-93 Cabbage 188+38 1920+91 <19 <13 <9 280+58 <39 <LLD 9-13-93 Swiss Chard 313+38 4020+123 <23 <12 <9 202+64 <46 <LLD 9-13-93 Collard Greens 421+45 4040+128 <30 <12 <12 199+87 <48 <LLD 9-13-93 Squash Leaves 851+29 1930+58 <18 <6 <6 167+38 <19 <LLD 9-13-93 Bean Leaves 844+29 2000+64 <8 <6 <6 164+47 <21 <LLD 9-13-93 Pepper Leaves 422+27 4700+92 <22 <7 <7, 106+42 <29 <LLD Z 9-12-93 Grape Leaves 1320+48 2960+94 <15 <10 <9 146+76 <40 <LLD Z 9-13-93 Lettuce 609+72 4800+204 <26 <26 <25 707+163 <95 <LLD Z 9-12-93 Squash Leaves 849+31 3500+82 <8 <7 <7 <121 23+9 <LLD 9-13-93 Beet Leaves 200+33 5940+133 <18 <11 <10 225+79 <44 <LLD 9-13-93 Squash Leaves 1700+45 3350+88 <13 <8 <8 278+59 <32 <LLD 9-13-93 Grape Leaves 1210+54 2010+99 <13 <13 <11 249+58 <49 <LLD 9-13-93 Cabbage 86+37 2230+108 <16 <13 <11 347+65 <52 <LLD 9-13-93 Cucumber Leaves 2480+61 3130+99 <15 <9 7+3 204+77 25+12 <LLD 9-13-93 Tomatoes <42 200+56 <11 <6 <5 136+33 <21 <LLD

• Control 'result All results in units of activity er kilo ram wet weight 110

TABLE 18 MILK ANIMAL CENSUS 1993 OWN OR AREA(a) O. ON CENSUS MAP(1) EGREES(3) DISTANCE (3) O. OF MILK ANI Scriba 16* 190o 5.9 None 2 195o 8.0 None 3 190o 4.5 3C 6 162o 2.2 1C 26 114o 1.5 None 61 140o 3.0 None 62 183o 6.7 2G 63 185o 8.0 35C ew Haven 9 95o 5.2 40C 4* 1130 7.8 100C 45 125 8.0 ND 10 130o 2.6 30C 5 146'30o 7 ' '1C 11 8.5 None 7* 107o 5.5 63C 64 107o 7.9 53C 71 111o 4.2 None exico 12 1070 11.5 21C 14 120o 9.8 56C 17 115o 10.2 2C 19 1320 10.5 40C 60* 90o 9.5 40C 50* 93o 8.2 140C 55* 95o 9.2 50C 21 112o 10.5 75C 68 108 11.6 None 49 88o 7.9 8G 72 98o 9.9 33C ichland 22 85 10.2 46C Pulaski 23 92o 10.5 None 69 850 11.6 60C Sterling 65** 220 17.0 25C olney 25 182 o 9.5 None 70 147 o 9.4 27C 66 156o 7..8 70C swego 7 3*** 234o 13.9 46C MILKING ANIMAL TOTALS: 1107 Cows 10 Goats MILKING ANIMAL TOTALS: 1036 Co 10 Goa 111

TABLE 18 (Continued)

MILK ANIMAL CENSUS I 1993 NOTES C Cows G Goats

• Milk sample location

• • Milk sample control location (4/93 8/93)

• • • Milk sample control location (8/93 12/93)

ND Did not wish to participate in the survey (1) References Figure 4 (2) Goat is not currently producing milk or any milk produced is utilized by the owner (3) Degrees and distance are based on NMP-2 reactor building centerline 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.

I 112

TABLE 19 1993 RESIDENCE CENSUS MAP METEOROLOGICAL LOCATION LOCATION (1) SECTOR DEGREES (2) DISTANCE (2)

N NNE NE ENE Lake Road A E 99~ 1~3 miles Lake Road B ESE 102 1.' miles County Route 29 C SE 130o 1.4 miles Miner Road D SSE 163o 1.6 miles Miner Road E S 170o 1.6 miles Lakeview Road F SSW 207o 1.2 miles Bible Camp Retreat G SW 234o 0.9 miles Bible Camp Retreat H WSW 238o 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.

113

TABLE 20 INTERLABORATORY COMPARISON PROGRAM RESULTS SITE REFERENCE NALYSIS DATE EDIUM O. EPA RESULT (1) SITE RESULT (2)

Beta 8/93 ir Filter A 93-123 47+5 52+1 (3)

(pCi/filter) 52+1 50+1 ritium 6/93 ater A 93-068 9844+984 9800+300 (4)

(pCi/liter) 9800+300 9800+300 ritium 11/93 ater A 93-185 7398+470 6900+300 (4)

(pCi/liter) 7000+300 6800+300 Beta 1/93 ater A 93-005 44+5 45+1 (3)

(pCi/liter) 41+1 42+1 Beta 4/93 ater A 93-045 177+27 151+2 (3)

(pCi/liter) 149+2 145+2 I-131 9/93 ilk A 93-154 120+12 117+2 (3)

(pCi/liter) 115+2 118+2 I-131 2/93 ater A 93-020 110+10 99+2 (3)

(pCi/liter) 98+2 98+2 I-131 10/93 ater A 93-066 117+12 120+2 (3)

(pci/liter) 120+2 119+2 114

TABLE 20 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS SITE REFERENCE NALYSIS DATE EDIUM O. EPA RESULT (1) SITE RESULT (2) amma 8/93 ir Filter A 93-123 9+5 8+2 (3)

(Cs-137) (pCi/filter) 7+2 9+2 amma 9/93 ilk A 93-154 49+5 49+4 (3)

(Cs-137) (pCi/liter) 48+4 44+4 Beta 7/93 ater A 93-099 43+7 38+1 (3)

(pCi/liter) 40+1 38+1 Beta 10/93 ater A 93-167 58+10 51+1 (3)

(pCi/liter) 50+1 53+1 amma 4/93 ater A 93-045 27+5 23+1 (3)

(Cs-134) (pCi/liter) 25+1 23+2 amma 4/93 ater A 93-045 32+5 31+2 (3)

(Cs-137) (pCi/liter) 32+2 30+2 Gamma 4/93 ater A 93-045 39+5 40+2 (3)

(Co-60) (pCi/liter) 38+2 37+2

TABLE 20 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS SITE REFERENCE ALYSIS DATE EDIUM O. EPA RESULT (1) SITE RESULT (2) amma 11/93 ater A 93-186 10+5 9+1 (3)

(Co-60) (pCi/liter) 10+1 11+1 amma 11/93 ater A 93-186 12+5 9+1 (3)

(Cs-134) (pCi/liter) 9+1 10+1 amma 11/93 ater A 93-186 10+5 11+1 (3)

(Cs-137) (pCi/liter) 11+1 10+1 amma 6/93 ater A 93-078 15+5 13+1 (3)

(Co-60) (pCi/liter) 14+1 13+1 amma 6/93 ater A 93-078 103+10 109+5 (3)

(Zn-65) (pCi/liter) 106+5 98+5 amma 6/93 ater A 93-078 119+12 76+14 (3)

(RQ-106) (pCi/liter) 114+17 102+16 amma 6/93 ater A 93-078 5+5 4+1 (3)

(Cs-134) (pCi/liter) 4+1 5+1 116

TABLE 20 (Continued)

INTERLABORATORY COMPARISON PROGRAM RESULTS SITE REFERENCE NALYSIS DATE EDIUM O. EPA RESULT (1) SITE RESULT (2) amma 6/93 ater A 93-078 5+5 6+1 (3)

(Cs-137) (pCi/liter) 5+2 5+2 amma 6/93 ater A 93-078 99+10 99+3 (3)

(Ba-133) (pCi/liter) 97+3 90+3 amma 11/93 ater A 93-186 201+20 172+20 (3)

(Ru-106) (pCi/liter) 177+22 188+16 amma 11/93 ater A 93-186 59+5 55+2 (3)

(Cs-134) (pCi/liter) 54+2 56+2 amma 11/93 ater A 93-186 40+5 39+2 (3)

(Cs-137) (pCi/liter) 41+2 42+2 amma 11/93 ater A 93-186 79+8 80+3 (3)

(Ba-133) (pCi/liter) 81+3 82+3 amma 11/93 ater A 93-186 30+5 30+2 (3)

(Co-60) (pCi/liter) 29+2 30+1 amma 11/93 ater A 93-186 150+5 154+7 (3)

(Zn-65) (pCi/liter) 157+8 158+6

TABLE 20 (Continued)

INTERLABORATORX COMPARISON PROGRAM RESULTS NOTES (1) Results reported as activity + the standard deviation of the error.

(2) Results reported as activity + the error (1 sigma).

(3) Analyzed at the site environmental laboratory.

(4) Analyzed at a vendor laboratory.

118

TABLE 21 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 LOCATION: CONTROL ~'i YEAR IN. X. IN. X. IN.

1979 (2) 1980 LLD LLD LLD LLD LLD LLD 0 '2 0.07 0 '2 0.09 0.22 0.08 LLD LLD LD LLD LLD LD 1981 LLD LLD LLD LLD LLD LLD LD LD LLD 1982 LD LLD LLD 0.05 0.05 0.05 LD LD LD 1983 LD LLD LLD LLD LLD LD LLD LD LLD 1984 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LD LLD LLD LD LD LD 1986 LLD LLD LLD LLD LLD LLD LD LD LD 1987 LD LLD LLD LLD LLD LD LLD LD LLD 1988 LD LLD LLD LLD LLD LD LLD LLD LD 1989 LLD LLD LLD LLD LLD LD LD LD LD 1990 LD LD LLD LD LD LLD LD D LD 1991 LD LLD LLD LD LLD LLD LD LD LD 1992 LD LLD LD LD LD LD LD LD LD 1993 LD LLD LD 0. 03 0. 03 0. 03 LLD LD LD esults in pCi/g (dry)

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

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

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

YEAR IN. X. EAN IN. X. IN. X. EAN 1979 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1980 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1981 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1982 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1983 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1984 (2) (2) (2) (2) (2) (2) (2) (2) (2) 1985 LLD LLD LLD LLD LD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1989 LD LLD LLD 0.25 0.34 0.30 LLD LLD LLD 1990 LD LLD LLD 0.28 0.28 0.28 LLD LLD LLD 1991 1992 LLD LLD LLD LD LLD LLD 0.11 0.10 0.16

0. 16 0 '4 0.13 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD 0.17 0. 49 0.33 LLD LD LLD esults in pCi/g (dry)

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

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

120

TABLE 23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 LOCATION: CONTROL YEAR IN. X.

1976 1.2 1.2 1.2 1977 0. 13 0. 13 0.13 1978 0.04 0.20 0.09 1979 0.03 0.06 0.04 1980 0.03 0.11 0.06 1981 0.028 0.062 0.043 1982 0.027 0.055 0.046 1983 0.041 0.057 0.049 1984 0.015 0.038 0 '32 1985 0.026 0.047 0.034 1986 0.021 0.032 0.025 1987 0.017 0.040 0.031 1988 0.023 0.053 0.033 1989 0.020 0.033 0.029 1990 0.025 0.079 0.043 1991 0.016 0.045 0.030 1992 0.019 0.024 0.022 1993 0.023 0 '41 0.032 esults in pCi/g (wet)

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

TABLE 24 HZSTORZCAL ENVZRONMENTAL SAMPLE DATA FISH Cs-137 LOCATION: INDICATOR (NMP/JAF)

YEAR IN. X.

1976 0.5 3.9 1.4 1977 0. 13 0.79 0.29 1978 0.03 0.10 0.08 1979 0.02 0.55 0. 10 1980 0.03 0.10 0. 06 1981 0.03 0.10 0.06 1982 0.034 0.064 0.048 1983 0.033 0.056 0.045 1984 0.033 0.061 0.043 1985 0.018 0.044 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 1988 0.020 0.074 0.034 1989 1990 0.020 0.024 0.043 0 '35 0.115 0.044 1991 1992 0.021 0 '35 0.027 0.013 0.034 0.026 1993 0. 021 0.038 0.030 esults in pCi/g (wet)

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

122

TABLE 25 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Cs-137 Co-60 LOCATION: CONTROL +

MIN.

1976 (1) (1) (1) (1) (1) (1) 1977 (2) (2) (2) (2) (2) (2) 1978 LLD LLD LLD (2) (2) (2) 1979 2.5 2.5 2.5 LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD 1.4 1.4 1.4 1982 LLD LLD LLD LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) No gamma analyses performed (not required).

(2) Data showed instrument background results.

(3) Location was the City of Oswego Water Supply for 1976 1984 and the Oswego Steam Station inlet canal= for 1985 1993.

W W W W W W W TABLE 26 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Cs-137 Co-60 LOCATION: INDICATOR +

YEAR MIN. X. EAN MAX.

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 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) No gamma analyses performed (not required).

(2) Data showed instrument background results.

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

124

TABLE 27 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM TRITIUM LOCATION: CONTROL IN.

1976 440 929 652 1977 300 530 408 1978 215 490 304 1979 174 308 259 1980 211 290 257 1981 211 328 276 1982. 112 307 165 1983 230 280 250 1984 190 220 205 1985 230 370 278 1986 250 550 373 1987 140 270 210 1988 240 460 320 1989 180 660 373 1990 260 320 290 1991 180 200 190 1992 190 310 242 1993 160 230 188 esults in pCi/liter (1) Control location is the City of Oswego drinking water for 1976 1984 and the Oswego Steam Station inlet canal for 1985 1993.

28 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM TRITIUM LOCATION: INDICATOR YEAR IN. X. EAN 1976 365 889 627 1977 380 530 455 1978 377 560 476 1979 176 276 228 1980 150 306 227 1981 212 388 285 1982 194 311 266 1983 249 560 347 1984 110 370 280 1985 250 1200 (2) 530 1986 260 500 380 1987 160 410 322 1988 430 480 460 1989 210 350 280 1990 220 290 250 1991 250 390 310 1992 240 300 273 1993 200 280 242 esults in pCi/liter (1) Indicator location is the FitzPatrick inlet canal.

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

126

TABLE 29 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: CONTROL ~~

YEAR IN. X.

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 7.2 5.4 1977 4.0 8.0 5.3 1978 3.3 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) *

~

1986 5.3 (5.5)

• 7.5 (7.2)

• 6.3 (6 ~ 3)

• 1987 4.6 (4.6)

• 6.6 (5.8)* 5' (5 2) *

~

1988 4.4 (4.8)

• 6.8 (6.8)

• 5.6 (5 4) *

~

1989 2.9 (2.9)* 6.4 (5.6)

• 4.7 (4 6) *

~

1990 3.7 (3.7)

• 6. 0 (5.9)

• 4.7 (4 6)*

1991 3.8 (3.8)* 5.4 (5.3)

• 4.5 (4 3)

• 1992 2.6 (2 ')*

3.4 (3.4)*

5.0 (4.7)

• 5.6 (5.2)

• 4.1

~

(3 ~ 9)

• 1993 4 ' (4.3)

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

(2) TLD g8 / 14 g 49 g 1 1 1 and 113 where applicable.

()* TLD result based on the Technical Specification required locations (TLD g14 and 49).

30A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: SITE BOUNDARY +

IN. X.

Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.1 12. 6 6.2 1986 4 ' 18.7 7.0 1987 4.4 14.3 6.1 1988 3.4 17.9 6.4 1989 2.8 15.4 5.9 1990 3.6 14.8 5.8 1991 3.2 16.7 5 '

1992 3.2 10.4 4.8 1993 3.3 11.6 5.3 esults in mrem per standard month (1) No data available (not required prior to 1985).

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

128

TABLE 30B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: OFF-SITE SECTORS @

YEAR Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.0 7.1 5.0 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 1988 3.8 7.0 5.3 1989 2.5 6.8 4.9 1990 3.6 6.3 4..7 1991 3.6 5.6 4.5 1992 2.9 5.0 4.1 1993 3.4 6.3 4.5 esults in mrem per standard month (1) No data *available (not required prior to 1985).

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

T 30C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION'PECIAL INTEREST YEAR IN. X. EAN Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 3.9 6.8 5.3 1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 7.0 4.8 1990 3.2 6.3 4.7 1991 2.9 5.6 4.4 1992 3.0 4.8 4.1 1993 3.2 5.8 4.5 esults in mrem per standard month (1) No data available (not required prior to 1985).

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

130

TABLE 30D HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: ON-SITE INDICATOR ~

YEAR IN. X. EAN reop (1) (1) (1) 1970 4 ' 9.0 6.0 1971 1.5 7.7 4.7 1972 2.3 8.2 4.9 1973 3.0 24.4 6.6 1974 3.1 10.6 5.7 1975 4.6 16 ' 7.3 1976 3 ' 18.8 6.9 1977 3.0 15.3 5.7 1978 3' 9.0 4 '

1979 2 ' 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' 15 ' 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 5.8 1988 4 ' 11.9 6.0 1989 2 ' 14 ~ 5 6.0 1990 3.6 12 ' 5.5 1991 3.2 11.6 5.1 1992 3.2 5.6 4.3 1993 3 ' 13.6 5.2 esults in mrem per standard month (1) No data available.

(2) Includes TLD numbers 3, 4, 5, 6, and 7 (1970 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25, and 26 (1974 1993). Locations are existing or previous on-site environmental air monitoring locations.

T 30E HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)

LOCATION: OFF-SITE INDICATOR ~i YEAR IN. X.

Preop (1) (1) (1) 1970 5.0 8.0 6.7 1971 1~1 7.7 4.5 1972 1.8 6.6 4 '

1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 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 3.6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 3.8 6.0 4.8 1991 3.4 5.4 4.3 1992 3.1 5.2 4.1 1993 3.2 5.6 4.3 esults 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).

132

TABLE 31 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA GPSS BETA LOCATION: CONTROL YEAR IN.

1977 0.001 0. 484 0 ~ 125 1978 0.01 0. 66 0. 16 1979 0.010 0. 703 0. 077 1980 0.009 0.291 0.056 1981 0.016 0.549 0.165 1982 0.011 0.078 0.033 1983 0.007 0.085 0.024 1984 0.013 0.051 0.026 1985 0. 013 0.043 0.024 1986 0. 008 0.272 0.039 1987 0. 009 0.037 0.021 1988 0. 008 0.039 0.018 1989 0. 007 0.039 0.017 1990 0. 003 0.027 0.013 1991 0. 006 0.028 0 '14 1992 0. 006 0.020 0.012 1993 0. 007 0.022 0 '13 esults in pCi/m3 (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 1993 (formerly C off-site location).

32 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA GROSS BETA LOCATION: INDICATOR YEAR IN. X.

1977 0. 002 0.326 0. 106 1978 0. 01 0.34 0 ~ 11 1979 0.001 0.271 0. 058 1980 0.002 0.207 0. 044 1981 0.004 0.528 0 ~ 151 1982 0.001 0.113 0 ~ 031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0 F 044 0.023 1986 0.007 0.289 0.039 1987 1988 0.009 0.007

0. 040 0 '21

0. 040 0.018 1989 0.007 0 ~ 041 0.017 1990 1991 0.005 0.007 0.023 0 '14 0.033 0.015 1992 0.005 0.024 0 '12 1993 0.005 0 '25 0.014 esults in pCi/m'1)

Locations used for 1977 1984 were Dl on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, Z on-site, and K on-site as applicable. 1985 1993 locations were R-1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

134

TABLE 33 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 LOCATION: CONTROL YEAR MIN. X. IN. X.

1977 0.0002 0. 0112 0.0034 0.0034 0.0347 0. 0172 1978 0.0008 0.0042 0.0018 0.0003 0.0056 0.0020 1979 0.0008 0.0047 0.0016 0.0005 0.0014 0.0009 1980 0.0015 0.0018 0.0016 LLD LLD LLD 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 0.0002 0.0009 0.0004 0.0004 0.0007 0.0006 1983 0.0002 0.0002 0.0002 0.0007 0.0007 0.0007 1984 LLD LLD LLD 0.0004 0.0012 0.0008 1985 LLD LLD LLD LD LLD LLD 1986 0.0075 0 '311 0.0193 LD LLD LL'D 1987 LLD LLD LLD LD LLD LLD 1988 LLD LLD LLD LD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LD LLD LLD esults in pCi/m'1)

Locations included composites of C, D1, E, F, and G off-site air monitoring locations for 1977 1984.. Sample location included only R-5 air monitoring location for 1985 1993.

HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 LOCATION'NDICATOR ~'i MIN. X. IN. MAX.

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 1985 LLD LLD LLD LLD LLD LLD 1986 0.0069 0.0364 0.0183 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD esults in pCi/m~

(1) Locations included composites of Dl, D2, E, F, G, H, I, J, and K on-site air monitoring locations for 1977 1984. Locations included R-1 through R-4 air monitoring locations for 1985 1993.

136

TABLE 35 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE IODINE-131 LOCATION: CONTROL IN. X.

1976 0. 01 5.88 0. 60 1977 0. 02 0.82 0. 32 1978 0.03 0.04 0.03 1979 LLD LLD LD 1980 LLD LLD LD 1981 LLD LLD LD 1982 0.039 0.039 0. 039 1983 LD LLD LD 1984 LD LLD LD 1985 LLD LLD LD 1986 0 '41 0.332 0 ~ 151 1987 LLD LD LD 1988 LLD LLD LD 1989 LLD LD LD 1990 LLD LLD LD 1991 LLD LD LD 1992 LD LLD LD 1993 LLD LLD LD esults in pCi/m~

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

Location R-5 off-site used for 1985 1993.

9 36 HIGTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE IODINE-131 LOCATION: INDICATOR IN. X.

1976 1977 0.01 0.02 2 '9 0.73 0.33 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 '.119 1987 0.011 0.018 0.014 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD LLD 1993 LLD LLD LLD esults in pCi/m~

(1) Locations used for 1976 1984 were D1 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site, and K on-site, as applicable. Locations used for 1985 1993 were R1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

138

TABLE 37 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 LOCATION: CONTROL +

YEAR MIN. X. EAN IN. MAX.

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 LD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 5.3 12.4 8.4 0.8 29.0 13.6 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) No data available (samples not required).

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

38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131 LOCATION INDICATOR MIN. X. IN. MAX.

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 ' 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 1988 10.0 10.0 10.0 LD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD esults in pCi/liter (1) Locations sampled were available downwind locations within ten miles with high radionuclide deposition potential.

140

TABLE 39 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 LOCATION: CONTROL Q YEAR X.

1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1). (1) (1) 1979 (1) (1) (1) 1980 (3) 0. 02 0. 02 0. 02 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (4) LLD LLD LLD 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD LLD 1993 0.07 0.07 0. 07 esults in pCi/g (wet)

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

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

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

(4) Data comprised of broadleaf vegetation only (1985 1993).

40 HISTORICAL ENVIRONMENTAL SAMPLE DATA POOD PRODUCTS Cs-137 LOCATION INDICATOR IN. X.

1976 (2) LLD LLD LD 1977 LLD LLD LLD 1978 LLD LLD LLD 1979 0.004 0.004 0.004 1980 0.004 0.060 0.036 1981 LLD LLD LLD 1982 LD LLD LD 1983 LLD LD LLD 1984 LLD LD LLD 1985 (3) 0.047 0. 047 0.047 1986 LD LLD LD 1987 LD LLD LLD 1988 0. 008 0.008 0.008 1989 0.009 0.009 0.009 1990 LLD LD LD 1991 0.040 0. 040 0. 040 1992 LD LLD LLD 1993 LLD LLD LD esults in pCi/g (wet)

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

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

(3) Data comprised of broadleaf vegetation only (1985 1993).

142

11.0 FIGURES 143

OSWEGO COUNTY New York FIGURE 1 NEAREST RESIDENCE, FOOD PRODUCT, FISH AND SHORELINE SEDINENT SAHPLE LOCATIONS KEY: ORESIDENCE - NNP L AISLE Q FISH ORESIDENCE - JAF

~ SHORELINE SEDINENT OFOOD PRODUCT ONTARIO eaa asa

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t OSWEGO COUNTY New York

<<s E IFIGURE 2 MILK ANI)IAL CENSUS, MILK SAMPLE, AND SURFACE WATER SAMPLE LOCATIONS ttv!

i PI MILK ANIMAL CENSUS Qi'IILK SAMPLE

$ P Mi~

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OSWEGO COUNTY New York FIGURE 3 OFF-SITE ENVIRONHENTAL STATION AND TLD LOCATIONS KEY:

Ll AICL O ENVIRONHENTAL STATION 1 Ie>>a

'I QTLD LOCATION ON2'ARI 0 SC4LE OF MILES Paeatv Oeeta 5~L aeue4e 4Ffffa a leaf fu faOF tf u O>>sat Oaaf Otaa. Oaafa ut  !

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