Text

Annual Radiological Environmental Operating Report
	ML051400270
Person / Time
Site:	Nine Mile Point
Issue date:	05/12/2005
From:	Spina J; Constellation Energy Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NMP1L 1949
	Download: ML051400270 (191)
	v • d • e

Q Constellation Energy-Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 May 12, 2005 NMP1L 1949 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Nine Mile Point Units 1 and 2 Docket Nos. 50-220 and 50-410 Facility Operating License Nos. DPR-63 and NPF-69 2004 Annual Radiological Environmental Operating Report Gentlemen:

In accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit I and Unit 2, we are enclosing the 2004 Annual Radiological Environmental Operating Report for the period January 1, 2004 through December 31, 2004.

Any questions concerning the enclosed report should be directed to Kent Stoffle, Principal Engineer, Environmental Protection at 315-349-1364.

Very truly yours, es A. Spina Vice President Nine Mile Point JAS/CWP/sac Enclosure cc:

Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Mr. P. S. Tam, Senior Project Manager, NRR (2 copies)

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Constellation Energy&

Nine Mile Point Nuclear Station NINE MILE POINT NUCLEAR STATION, LLC 2004 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I i j

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NINE MILE POINT NUCLEAR STATION, LLC

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2004 - December 31, 2004 For NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63.

Docket No. 50-220 And NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Program History 2-1 2.2 Site Description 2-2 2.3

' Program Objectives 2-2 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection Methodology 3-13 3.2 Analyses Performed 3-18 3.3 Sample Locations 3-18 3.4 Land Use Census 3-29 3.5 Changes to the REMP Program 3-29 3.6 Deviation and Exceptions to the Program 3-30 3.7 Statistical Methodology 3-31 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-34 3.9 Regulatory Dose Limits 3-36 4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL 4-1 POSITION FORMAT 5.0 DATA EVALUATION AND DISCUSSION 5-1 5.1 Aquatic Program 5-7 5.2 Terrestrial Program 5-17 5.3 Conclusion 5-35 5.4 References 5-37 i

TABLE OF CONTENTS (Continued)

Page 6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6-1 7.0 HISTORICAL DATA TABLES 7-1 8.0 QUALITY ASSURANCE/QUALITY CONTROL PROGRAM 8-1 8.1 Program Description 8-1 8.2

'Program Schedule 8-2 8.3 Acceptance Criteria 8-2 8.4 Program Results Summary 8-4 8.5 References 8-24 ii

LIST OF TABLES Table 3.0-1 Table 3.0-2 Table 3.3-1 Table 3.8-1 Table 4.0-1 Table 6-1 Table 6-2 Table 6-3 Table 6-4 Table 6-5 Table 6-6 Table 6-7 Table 6-8 Table 6-9 Table 6-10 Table 6-11 Table 6-12 Table 6-13 Table 6-14 Table 7-1 Table 7-2 Required Sample Collection and Analysis, Nine Mile Point Unit 1 Required Sample Collection and Analysis, Nine Mile Point Unit 2 Environmental Sample Locations Required Detection Capabilities for Environmental Sample Analysis, Lower Limit of Detection (LLD)

Radiological Environrniental Monitoring Program Annual Summary Concentrations of Gamma Emitters in Shoreline Sediment Samples Concentrations of Gamma Emitters in Fish Samples Concentrations of Tritium in Surface Water Samples Concentrations of Gamma Emitters in Surface Water Samples Environmental Airborne Particulate Samples - Offsite Stations Environmental Airborne Particulate Samples - Onsite Stations Environmental Charcoal Cartridge Samples - Offsite Stations Environmental Charcoal Cartridge Samples - Onsite Stations Concentrations of Gamma Emitters in Monthly Composites of JAF/NMPNS Site Air Particulate Samples Direct Radiation Measurement Results Concentrations of Iodine-131 and Gamma Emitters in Milk Concentrations of Gamma Emitters in Food Products Milk Animal Census Residence Census Historical Environmental Sample Data, Shoreline Sediment (Control)

Historical Environmental Sample Data, Shoreline Sediment (Indicator) 3-2 3-6 3-20 3-35 4-2 6-2 6-3 6-6 6-7 6-12 6-14 6-16 6-18 6-20 6-35 6-38 6-40 6-41 6-42 7-1 7-2 iii

LIST OF TABLES (continued)

Table 7-3 Table 7-4 Table 7-5 Table 7-6 Table 7-7 Table 7-8 Table 7-9 Table 7-10 Table 7-11 Table 7-12 Table 7-13 Table 7-14 Table.7-15 Table 7-16 Table 7-17 Table 7-18 Table 7-19 Table 7-20 Table 7-21 Table 7-22 Table 7-23 Historical Environmental Sample Data, Fish (Control)

Historical Environmental Sample Data, Fish (Indicator)

Historical Environmental Sample Data, Surface Water (Control)

Historical Environmental Sample Data, Surface Water (Indicator)

Historical Environmental Sample Data, Surface Water Tritium (Control)

Historical Environmental Sample Data, Surface Water Tritium (Indicator)

Historical Environmental Sample Data, Air Particulate Gross Beta (Control)

Historical Environmental Sample Data, Air Particulate Gross Beta (Indicator)

Historical Environmental Sample Data, Air Radioiodine (Control)

Historical Environmental Sample Data, Air Radioiodine (Indicator)

Historical Environmental Sample Data, Air Particulates (Control)

Historical Environmental Sample Data, Air Particulates (Indicator)

Historical Environmental Sample Data, Environmental TLD (Control)

Historical Environmental Sample Data, Environmental TLD (Site Boundary)

Historical Environmental Sample Data, Environmental TLD (Offsite Sectors)

Historical Environmental Sample Data, Environmental TLD (Special Interest)

Historical Environmental Sample Data, Environmental TLD (Onsite Indicator)

Historical Environmental Sample Data, Environmental TLD (Offsite Indicator)

Historical Environmental Sample Data, Milk (Control)

Historical Environmental Sample Data, Milk- (Indicator)

Historical Environmental Sample Data, Food Products (Control)

Page 7-3 7-4 7-5 7-6 7-7 7-8 7-9 7-10 7-11 7-12 7-13 7-14 7-15 7-16 7-17 7-18 7-19 7-20 7-21 7-22 7-23 iv

I LIST OF TABLES (continued)

Table 7-24 Table 8-1 Historical Environmental Sample Data, Food Products (Indicator)

Interlaboratory Intercomparison Program (Gross Beta, Tritium, Iodine

& Gamma Analysis of Air, Water, Milk, Soil, Filter & Food Products)

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7-24 8-10 v

LIST OF FIGURES Figure 3.3-1 Figure 3.3-2 Figure 3.3-3 Figure 3.3-4 Figure 3.3-5 New York State Map Off-site Environmental Station and TLD Locations On-site Environmental Station and TLD Locations Milk and Surface Water Sample Locations Nearest Residence, Food Product, Fish and Shoreline Sediment Sample Locations Page 3-24 3-25 3-26 3-27 3-28 vi

1.0 EXECUTIVE

SUMMARY

The Annual Radiological Environmental Operating Report is published pursuant to Section 6.6.2 of the Nine Mile Point Unit 1 (NMP1) Technical Specifications,-Section 5.6.2 of the Nine Mile Point Unit 2 (NMP2) Technical Specifications and 10 CFR 50.4.

This report describes the Radiological Environmental Monitoring Program (REMP), the implemIentation, and the results obtained as required by Technical Specifications (TS) and the Offsite Dose Calculation Manuals (ODCM). The report also contains the analytical results tables, data evaluation, dose assessment, and data trends for each environmental sample media. Also included are results of the land use census, historical data and the Environmental Laboratory's performance in the Quality Assurance Intercomparison Program required by the NMP I and NMP2 ODCM.

The REMP is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with IOCFR20 and 40CFR190. Samples are collected from the aquatic and terrestrial pathways applicable to the site. The aquatic pathways include Lake Ontario fish, surface waters and lakeshore sediment.

The terrestrial pathways include airborne particulate and radioiodine, milk, food products and direct radiation.

During 2004 there were 2310 analyses performed on environmental media collected as part of the required monitoring program.

These results demonstrated that there was no significant or measurable radiological impact from the operation of either the NMP1 or NMP2 facilities.

Cesium-137 was detected in one aquatic pathway (shoreline sediment) at very low levels and was attributed to fallout from past weapons testing. The 2004 results for all pathways sampled were consistent with the previous five year historical results and exhibited no adverse trends.

In summary, the analytical results from the 2004 REMP demonstrate that the routine operation of both facilities at the Nine Mile Point Site had no significant or measurable radiological impact on the environment. No elevated radiation levels were detected in the off-site environment as a result of either the NMPI or NMP2 hydrogen injection programs. The results of the REMP continued to demonstrate that the operation of the plants did not result in a significant measurable dose to a member of the general population, or adversely impact the environment as a result of radiological effluents. The environmental program continued to demonstrate that the dose to a member of the public as a result of the operation of NMP1 and NMP2 remained significantly below the federally required dose limits specified in 10CFR20 and 40CFRI9O.

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2.0 INTRODUCTION

Nine Mile Point Units 1 and 2.are operated by Nine Mile Point Nuclear Station, LLC. This report is submitted in accordance with Appendix-A (Technical Specifications) Section 6.6.2 to License DPR-63, Docket No. 50-220 for the Nine Mile Point Nuclear Station Unit I and Appendix A (Technical Specifications) Section 5.6.2 to License NPF-69, Docket No. 50-410 for the Nine Mile Point Nuclear Station Unit 2 for the calendar year 2004.

Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2) Radiological Environmental Monitoring Program (REMP) requirements reside within the NMP1 Offsite Dose Calculation Manual (ODCM) and NMP2 ODCM, respectively.

Throughout this report references will be made to the ODCM. This refers to both the NMP1 ODCM and NMP2 ODCM.

2.1 PROGRAM HISTORY Environmental monitoring of the Nine Mile Point site has been on-going since 1964.

The program includes five years of pre-operational data which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required pre-operational environmental site testing program.

This pre-operational data serves as a reference point to' compare later data obtained during.reactor operation.

In 1969, NMP1, a 1850 Megawatts -

Thermal (MWt) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A.

FitzPatrick Nuclear Power Plant (JAFNPP), a 2536 MWt BWR, currently owned and operated by Entergy, began full power operation.

In 1988, the NMP2 reactor, a 3323 MWt BWR located between NMP1 and JAFNPP, began full power operation. In 1995, NMP2 was uprated to 3467 MWt.

In 1985, individual station Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which is common to both NMP1 and JAFNPP, and subsequently NMP2. Subsequent Technical Specification amendments relocated the REMP requirements to the ODCM for all three plants. Data generated by the REMP is shared, but each operating company reviews and publishes their own annual report.

In summary, three BWRs, which together generate approximately 7853 Megawatts - Thermal, have operated collectively at the Nine Mile Point Site since 1988.

A large database of environmental results for the exposure pathways has been collected and'analyzed to determine the effect from reactor operations.

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2.2 SITE DESCRIPTION The Nine Mile Point Site is located on the southeast shore of Lake Ontario in the town of Scriba, approximately 6.2 miles northeast of the city of Oswego. The nearest metropolitan area is located approximately 36 miles south southeast of the site. The reactors and support buildings occupy a l

small shoreline portion of the 900 acre site. The land, soil of glacier deposits, rises gently from the lake in all directions. Oswego County is a rural environment, with about 34% of the land devoted to agriculture.

2.3 PROGRAM OBJECTIVES l

The objectives of the Radiological Environmental Monitoring Program are to:

1. Measure and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material sources.

2. Monitor natural radiation levels in the environs of the NMPNS site.

3. Demonstrate compliance with the requirements of applicable federal regulatory agencies, including Technical Specifications and the Offsite Dose Calculation Manuals.

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3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.3, an extensive sampling and analysis program is conducted every year.

The Ninee Mile Point Nuclear Station (NMPNS) Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

Shoreline Sediment Fish

Surface Waters Air

Milk

Food Products In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1 and Table 3.0-2. The NMPNS REMP sampling locations are selected and verified by an annual land use census. The accuracy and precision of the analysis program is assured by participation in an Interlaboratory Comparison Quality Assurance Program (ICP). In addition to the participation in the ICP Program; sample splits are provided to the New York State Department of Health for cross checking purposes.

Sample collections -for the radiological program are accomplished, by a. dedicated site environmental staff from both the NMPNS and James A. FitzPatrick. Nuclear Power Plant (JAFNPP). The site staff is assisted by a contracted environmental engineering company, EA Engineering, Science and Technology, Inc. (EA).

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TABLE 3.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION ANI) ANALYSIS Nine Mile Point Unit I Exposure Pathway and/or Sample Number of Samples (a) and Locations Sampling and Collection Frequency (a)

Type of Analysis and Frequency AIRBORNE

a. Radioiodine and Particulates Samples from five locations; Continuous sampler operation with sample collection weekly or as required by dust loading, whichever is more frequent.

Three samples from offsite locations in different sectors of the highest calculated site average D/Q (based on1 all site licensed reactors).

Radioiodine Canisters -

analyze once/week for 1-131.

Particulate Samplers -

Gross beta radioactivity following filter change (b)

Composite (by location) for gamma isotopic analysis (c) once per 3 months, (as a minimum).

One sample from the vicinity of an established year round community having the highest calculated site average D/Q (based on all site licensed reactors).

One sample from a control location 10-17 miles distant and in a least prevalent wind direction (d).

b. Direct Radiation (c) 32 stations with two or more dosimeters to be placed as follows: an inner ring of stations in the general area of the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each land based sector. (1) The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools and in 2 or 3 areas to serve as control stations.

Once per 3 months Gamma dose once per 3 months.

(1)

At this distance, 8 wind rose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario 3 - 2

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 I

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Exposure Pathway and/or Sample '

Number of Samples (a) and Locations Sampling and Collection Frequency (a)

Type of Analysis and Frequency WATERBORNE

a. Surface M

b. Sediment from Shoreline' One sample upstream.,

Composite sample over I month period (g One sample from the site's downstream cooling water intake..

One sample from a downstream area with' existng or potential recreational value.

Gamma isotopic analysis (C) once/month. Composite for once per 3 months tritinur analysis.

Gamma' isotopic analysis (c)

Twice'per year INGESTION

a. Milk Samples from milk sampling locations in three locations within 3.5 miles distance having the highest calculated site average D/Q. If there are' none, then one sample from milking animals in each of 3 areas 3.5 - 5.0 miles distant having the highest calculated site average D/Q (based on all site licensed reactors). -

Twice per month, April -

December (samples will be collected in January - March if 1-131 is detected in November and December of the preceding year).

Gamma isotopic (c) and I-131 analysis tvice per month when animals are on pasture (April -

December); once/month at other times (January -

March) if required.

One sample 'from a milk sampling location at a control location (9-20 miles distant and in a least prevalent wind direction) (d) 3 - 3

TABLE 3.0-1 (Continuied)

RADIOLOGICAL ENVIRONMENTAL MIONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway and/or Sample Number of Samples (a) and Locations Sampling and Collection Frequency (a)

Type of Analysis and Frequency

b. Fish One sample each of two conmnercially or recreationally important species in the vicinity of a plant discharge (h) area Twice per year Gamma isotopic analysis (C) on edible portions twice per year.

One sample each of the same species from an area at least 5 miles distant from the site (d).

c. Food Products Samples of three different kinds of broad leaf vegetation (such as vegetables) grown nearest to each of two different off-site locations of highest calculated site average D/Q (based on all licensed site reactors).

Once per year during harvest season Gamma isotopic (C) analysis of edible portions (Isotopic to include I-131 or a separate 1-131 analysis may be performed) once during the harvest season.

One sample of each of the similar broad leaf vegetation grown at least 9.3 - 20 miles distant in a least prevalent wind direction.

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NOTES FOR TABLE 3.0-1 (a)

It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and may be substituted. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Highest D/Q locations are based on historical meteorological data for all site licensed reactors.

(b)

Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If the gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(c)

Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.

(d)

The purpose of these samples is to obtain background information.

If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites, such as historical control locations which provide valid background data may be substituted.

(e)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may by considered to be one phosphor, and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation..

(f)

The "upstream sample" should be taken at a distance beyond significant influence of the discharge. The "downstream sample" should be taken in an area beyond but near the mixing zone, if possible.

L (g)

Composite samples should be collected with equipment (or equivalent). which is capable of collecting an aliquot at time intervals which are :very short (e.g. hourly) relative to the compositing period (e.g. monthly) in order to assure obtaining a representative sample.

(h)

In the event commercial or recreational important species are not available as a result of three attempts, then other species may be utilized as available. -

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TABLE 3.0-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and Frequency AIRBORNE

a. Direct Radiation 32 routine monitoring stations (b) either with 2 or more dosimeters or with I instrument for measuring and recording dose rate continuously, placed as follows:

Once per 3 months Gamma dose once per 3 months An inner ring of stations, one in each meteorological sector in the general area of the Site Boundary.

An outer ring of stations, one in each land base meteorological sector in the 4 to 5 mile (I) range from the site.

The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools, and in one of two areas to serve as control stations (C)

(1) At this distance, 8 wind rose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RE QUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample

b. Airborne Radioiodine and Particulates Number of Samples and Sample Locations (

Samples from five locations:

Three samples from offsite locations close to the site boundary (within one mile) in different sectors of the highest calculated annual site average ground-level D/Q (based on all site licensed-reactors).

Sampling and Collection Frequency Type of Analysis and Frequency S

f Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading One sample from the vicinity of an established year-round community having the highest calculated annual site average ground-level D/Q (based on all site licensed reactors).

One sample from a control location at least 10 miles distant and in a least prevalent wind direction (c)

Radioiodine Canister I-13 1 analysis weekly Particulate Sampler-Gross beta radioactivity analysis:LŽ24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change (d),

Gamma isotopic analysis on each sample where gross beta activity is >10 times the previous yearly mean of control samples and gamma isotopic analysis (') of composite sample (by location) once per 3 months.

WATERBORNE

a. Surface One sample upstream (c) (0 Composite sample over 1-month period (g.

Gamma isotopic analysis (e) once per month and tritium analysis once per 3 months.

One sample from the site's downstream'cooling water intake~.-

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TABLE 3.0-2 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and Frequency

b. Ground

c. Drinking

d.

Sediment from Shoreline Samples from one or two sources if likely to be affected (h)

One sample each of one to three of the nearest water supplies that could be affected by its discharge (i One sample from a downstream area with existing or potential recreational value.

Grab sample once per 3 months.

Composite sample over a 2-week period(g) when 1-13 1 analysis is performed; monthly composite otherwise.

Twice per year Gammna isotopic (e) and tritium analysis once per 3 months.

I-13 1 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mremn per year. (i) Composite for gross beta and gamma isotopic analyses (e) monthly. Composite for tritium analysis once per 3 months.

Gamma isotopic analysis(e) 3 - 8 i

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS.

Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (3)

Sampling and Collection Frequency Type of Analysis and Frequency INGESTION

a.

Milk

b.

Fish Samples from Milk Sampling Locations in three locations within 3.5 miles distance having the highest calculated annual site average D/Q (based on all; licensed site reactors). If there are none, then 1 sample from' Milk Sampling Lboc'ti6is' in each'oftthfee'areas 3:5 5.0'miles distant having the highest calculated annual site average D/Q (based on all licensed site reactors).

One sample`from a Milk Sample Location at a'control location 9 - 20 miles distant and in a least prevalent wind direction (c).

One sample each of two commercially or recreationally important species in the vicinity of a plant discharge area Twice per month, April -.

December (samples will be collected January - March if I-131 is detected in November and December of the preceding year).

Twice per year Gamma isotopic (e) and 1-131 analysis tvice/month when animals are on pasture (April -

December); once per month at other times (January - March if required).

Gamma isotopic analysis (

on edible portions tvice per year.

One sample of the same species in areas not influenced by station discharge (C).

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TABLE 3.0-2 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and Frequency

c. Food Products One sample of each principal class of food products from any area that is irrigated by water in w~hich liquid plant wastes have been discharged (1).

At time of harvest (nm)

Gamma isotopic (c and I-131 analysis of each sample of edible portions.

Samples of three different kinds of broad leaf vegetation (such as vegetables) grown nearest to each of two different offsite locations of highest calculated annual site average D/Q (based on all licensed site reactors).

Once per year during the harvest season.

One sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least prevalent wind direction.

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NOTES FOR TABLE 3.0-2 (a)

Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent; shall be'provided for each and every sample location in Table 3.0-2.

Refer to NUREG-0I33, 6"Preparation of Radiological Effluent" Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.' Deviations are permitted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unavailability (which includes theft and uncooperative residents), or malfunction of automatic sampling equipment.

(b)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Each of the 32 routine monitoring stations shall be equipped with 2 or more dosimeters or with I instrument for L

measuring and recording dose rate continuously.

For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(c)

The purpose of these samples is to obtain background information.

If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites, which provide valid background data, may be substituted.

(d)

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.

L

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Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(f)

The "upstream" sample shall be taken at a distance beyond significant influence of the'discharge.

.The "downstream" sample shall be taken in an area beyond but near the mixing zone.

(g)

In this program, representative composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(h)

Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(i)

Drinking water samples shall be taken only when drinking water is a dose pathway.

-(j)

Analysis for I-131 may be accomplished by Ge-Li analysis provided that the lower limit of detection (LLD) for I-131 in water samples found on Table 3.8-1 can be met.

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NOTES FOR TABLE 3.0-2 (Continued)

(k)

In the event two commercially or recreationally important species are not available after three attempts of collection, then two samples of one species or other species not necessarily commercially or recreationally important may be utilized.

(I)

Applicable only to major irrigation projects within 9 miles of the site in the general downcurrent direction.

(m)

If harvest occurs more than once/year, sampling shall be performed during each discrete harvest.

If harvest occurs continuously, sampling shall be taken monthly.

Attention shall be paid to including samples of tuberous and root food products.

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3.1 SAMPLE COLLECTION METHODOLOGY 3.1.1 SHORELINE SEDIMENTS One kilogram of shoreline sediment is collected at one area of existing or potential recreational value. One sample is also collected from a location beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately-I inch. The samples are placed in plastic bags, sealed and shipped to the lab for analysis. Sediment samples are analyzed for gamma emitting radionuclides.

Shoreline sediment sample locations are shown in Section 3.3, Figure 3.3-5.

3.1.2 FISH Samples of available fish species that are commercially or recreationally important to Lake Ontario, such as lake trout, salmon, -walleye and smallmouth bass, are collected twice per year, once in the spring and again in the fall., Indicator samples are collected from a combination of the two on-site sample transects located off.shore; from the site.:- One set of control samples are collected at an off-site sample-transect located off shore 8 - 10 miles west of the site. Available species are selected using the following guidelines:

a.

A minimum of two species that are commercially or recreationally important are to be collected from each sample location. Samples selected are limited to edible and/or sport species when available.

b.

Samples are composed of 0.5 to 1 kilogram of the edible portion only.

Selected fish samples are frozen after collection and segregated by species and location. Samples are shipped frozen in insulated containers for analysis.

Edible portions of each sample are analyzed for gamma emitting radionuclides.

- Fish collection locations are shown in Section 3.3, Figure 3.3-5.

3.1.3 SURFACE WATER Surface water samples are taken from the respective inlet canals of the JAFNPP and the NRG Energy's Oswego Steam Station.. The JAFNPP facility draws water from Lake Ontario on a continuous basis. This is used for the "downstream" or indicator sampling point for the Nine Mile Point site. The Oswego Steam Station inlet canal removes water from Lake Ontario at a point 3 - 13

approximately 7.6 miles west of the site. This "upstream" location is considered a control location because of the distance from the site as well as the result of the lake current patterns and current patterns from the Oswego River located nearby.

Samples from the JAFNPP facility are composited from automatic sampling equipment, which discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitters. Samples from the Oswego Steam Station are also obtained using automatic sampling equipment and collected in a holding tank.

Representative samples from this location are obtained weekly and are composited to form a monthly composite sample.

The monthly samples are analyzed for gamma emitting radionuclides.

I A portion of the monthly sample from each of the locations is saved and composited to form quarterly composite samples, which are analyzed for tritium.

In addition to the sample results for the JAFNPP and Oswego Steam Station collection sites, data l

is presented for the Nine Mile Point Unit I (NMPI) and Nine Mile Point Unit 2 (NMP2) facility inlet canal samples and from the City of Oswego drinking water supply. The latter three locations are not required by the ODCM. These locations are optional sample points which are collected and analyzed to enhance the surface water sampling program. MIonthly composite samples from these three locations are analyzed for gamma emitting nuclides and quarterly composite samples are analyzed for tritium.

Sampling for groundwater and drinking water, as found in Section D 3.5.1 of the NMiP2 ODCM, was not required during 2004. There was no groundwater source in 2004 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties were l

suitable for contamination; therefore, drinking water was not a dose pathway during 2004.

Surface water sample locations are shown in Section 3.3 on Figure 3.3-4.

3.1.4 AIR PARTICULATE / IODINE The air sampling stations required by the ODCM are located in the general area of the site boundary. The sampling stations are sited within a distance of 0.2 miles of the site boundary in sectors with the highest calculated deposition factor (D/Q) based on historical meteorological data.

These stations (R-1, R-2, and R-3) are located in the E, ESE, and SE sectors as measured from the center of the NMIP2 Reactor Building. The ODCM also require that a fourth air sampling station be located in the vicinity of a year round community. This station is located in the SE sector at a distance of 1.8 miles and is designated as Station R-4. A fifth station required by the ODCMI is a 3 - 14

control location designated as Station R-5. Station R-5 is located 16.4 miles from the site in the NE meteorological sector.

In addition to the five ODCM required locations, there are ten additional sampling stations. Six of these sampling stations are located within the site boundary and are designated as Onsite Stations DI, G, H; I, J, and K. These locations are within the site boundary of the NMPNS and JAFNPP.

One air sampling station is located'Offsite'in the SW sector in the vicinity of the City of Oswego and is designated as Station G Offsite. Three remaining air sampling stations are located in the ESE, SSE, and SSW sectors and range in'distance from 7.2 to 9.0 miles. These are designated as Offsite Stations D2, E and F, respectively.

Each station collects airborne particulates using glass fiber filters (47 millimeter diameter) and radioiodine using charcoal sample cartridges (2 x 1 inch). The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis.

Sample volume is determined by use'of calibrated gas -flow meters located at the sample discharge.

Gross beta' analysis is performed on each particulate filter. Charcoal cartridges are analyzed for radioiodine using gamma spectral analysis. The particulate filters are composited monthly by location and analyzed for gamma emitting radionuclides.;-

Air sampling station locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.-

3.1.5 TLD (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment.

Environmental TLDs are supplied and processed quarterly by the JAFNPP Environmental Laboratory.. The laboratory utilizes a Panasonic based system using UD-814

'dosimeters which are constructed of rectangular teflon wafers impregnated with 25% CaSO 4:Dy phosphor. Each dosimeter contains three calcium sulfate elements and one lithium borate element.

Environmental TLDs are placed in five different geographical regions around the site to evaluate' effects of Direct Radiation as a result of Plant Operations. The following is a description of the five TLD geographical categories used in the NMPNS and JAFNPP Environmental Monitoring Program and the TLDs that make up' each region:

3-15

TLD Geographical Category Description Onsite TLDs placed at various locations within the Site Boundary and are not required by the ODCM, with the exception of TLD # 7, 23 and

18. (TLD locations comprising this group are: 3, 4, 5, 6, 7*, 18*,

23*, 24, 25, 26, 27, 28, 29, 30, 31, 39, 47, 103, 106 and 107)

I Site Boundary Offsite Sector Special Interest Control An inner ring of TLDs placed in the general area of the Site Boundary in each of the sixteen meteorological sectors.

This category is required by the ODCM.

(TLD locations comprising this group are: 7*, 18*, 23*, 75*, 76*, 77*, 78*, 79*, 80*, 81*,

82*, 83*, 84*, 85*, 86*, and 87*)

An outer ring of TLDs placed 4 to 5 miles from the site in each of the 8 land based meteorological sectors. This category is required by the ODCM. (TLD locations comprising this group are 88*, 89*,

90*, 91*, 92*, 93*, 94*, and 95*)

TLDs placed in Special Interest areas of high population density and use. These TLDs are located at or near large industrial sites, schools, or nearby towns or communities. This category is required by the ODCM. (TLD locations comprising this group are: 9, 10, 11, 12, 13, 15*, 19, 51, 52, 53, 54, 55, 56*, 58*, 96*, 97*, 98*, 99, 100, 101, 102, 108, and 109)

I TLDs placed in areas beyond significant influence of the site and plant operations. These TLDs are located to the SW, S and NE of the site at distances of 12.6 to 24.7 miles. This category is also required by the ODCM. (TLD locations comprising this group are 8, 14*,49*, 111, 113)

I TLD location required by ODCM Although the ODCM require a total of 32 TLD stations, environmental TLDs are also placed at additional locations, not required by the ODCM, within the Onsite, Special Interest and Control TLD categories to supplement the ODCM required direct radiation readings.

3-16

Two dosimeters are placed at each TLD monitoring location.

The TLDs are sealed in polyethylene packages to ensure dosimeter integrity and placed in open webbed plastic holders and attached to supporting structures, such as utility poles.

Environmental TLD locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.

3.1.6 MILK Milk samples are routinely collected from four farms during the sampling 'year. These farms include three indicator locations and one control location. Samples are normally collected April through December of the sample year.

If plant related radionuclides are detected during November and December of the previous year, milk collections are continued into the following year, starting in January. ' If plant related radionuclides are not detected in the November and December samples, then milk collections do not commence until April of the next sampling year.

Milk samples were not collected in January through March of 2004 as there were no positive detections of plant related radionuclides in samples collected during November and December 2003.

In 2004, samples were collected from indicator location 76 and control location 77 twice per month, April through December.

Samples from indicator locations 4 and 55 were initially collected once per month starting in April. The sampling frequency was increased for locations 4 and 55 to twice per month in July and continued through December.

The: increased sample frequency at locations 4 and 55 was implemented to heighten monitoring to detect a possible environmental impact as a result of the increased effluent release rate resulting from the fuel

.failure that was experienced at JAFNPP starting in February of 2004. The failed fuel bundles were removed from the core during the 2004 refueling outage conducted in October.

The ODCM also requires that a sample' be collected from a control location nine to twenty miles from the site and in a less prevalent'wiid'directidn.' This location is in the south sector at a distance of 14 miles and serves as the contrtol location.

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 to assure a homogenous mixture of milk L

and butterfat. Two gallons are collected from each indicator and control location during the first half and second half of each month. The 'samples are chilled, preserved and shipped fresh to the analytical laboratory within thirty-six hours of collection, in insulated shipping containers.

The milk sample locations are shown in Section 3.3, Figure.3.3-4. (Refer to Section 3.3, Table 3.3-1 for location designation and descriptions.)

3 - 17

3.1.7 FOOD PRODUCTS (VEGETATION)

Food products are collected once per year during the late summer harvest season. A minimum of l

three different kinds of broadleaf vegetation, edible or inedible, is collected from two different indicator garden locations. Sample locations are selected from gardens identified in the annual l

census that have the highest estimated deposition values (D/Q) based on historical site meteorological data. Control samples are also collected from available locations greater than 9.3 miles distant from the site in a less prevalent wind direction. Control samples are of the same or similar type of vegetation when available.

Food product samples are analyzed for gamma emitters using gamma isotopic analysis.

Food product locations are shown in Section 3.3, Figure 3.3-5.

3.2 ANALYSES PERFORMED The following environmental sample analyses are performed by the JAFNPP Environmental Laboratory:

Shoreline Sediment - gamma spectral analysis

Fish - gamma spectral analysis

]

Surface Water Composites - gamma spectral analysis, 1-131 and tritium o

Air Particulate Filter - gross beta

Air Particulate Filter Composites - gamma spectral analysis Airborne Radioiodine - gamma spectral analysis

Direct Radiation - Thermoluminescent Dosimeters (TLDs) l

Milk-gamma spectral analysis and I-131

Food Products (Vegetation) - gamma spectral analysis

Special Samples (soil, food products, bottom sediment, etc.) - gamma spectral analysis 3.3 SAMPLE LOCATIONS I

Section 3.3, Figures 3.3-1 through 3.3-5 provides maps illustrating sample locations.

Sample locations referenced as letters and numbers on the report. period data tables are consistent with designations plotted on the maps.

3-18

This section also contains an environmental sample location reference table (Table 3.3-1). This table contains the following information:

Sample medium

Map designation, (this column contains the key for the sample location and is consistent with the designation on the sample location maps and on the sample results data tables).

Figure number

. Location description Degrees and distance of the sample location from the site.

3.3.1 LIST OF FIGURES Figure 3.3 New York State Map Figure 3.3 Off-Site Environmental Station and TLD Locations Map

Figure 3.3 On-Site Environmental Station and TLD Locations Map

-Figure 3.3 Milk Sample and Surface Water Locations Map Figure 3.3 Nearest Residence, Food Product, Fish and Shoreli Locations Map tine Sediment Sample A.

k I

I I

3 -19

.. TABLE 3.3-1 2004 ENVIRONMENTAL SAMPLE LOCATIONS MEDIUM~

_DESIGNATION l

LOCATION DESCRIPTION l

DENGE

&i)

Shoreline Sediment 5*

6 Figure 3.3-5 Figure 3.3-5 Sunset Bay Langs Beach, Control 800 at 1.5 miles 2300 at 5.8 miles Fish 02*

03*

00*

Surface Water 03*

08*

09 10 11 Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Figure 3.3-4 Figure 3.34 Figure 3.3-4 Figure 3.3-4 Figure 3.3-4 Nine Mile Point Transect FitzPatrick Transect Oswego Transect 3150 550 2350 FitzPatrick Inlet Oswego Steam Station Inlet NMP Unit I Inlet Oswego City Water NMI' Unit 2 Inlet 700 235° 2750 2400 3040 at 0.3 miles at 0.6 miles at 6.2 miles at 0.5 miles at 7.6 miles at 0.3 miles at 7.8 miles at 0.1 miles Air Radioiodine and Particulates R-1*

R-2*

R-3*

R14*

R-5*

Dl G

11 I

J K

G D2 E

F Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Fignure 3.3-2 R-l Station, Nine Mile Point Road R-2 Station, Lake Road R-3 Station, Co. Rt. 29 R-4 Station, Co. Rt. 29 R-5 Station, Montario Point Dl On-Site Station G On-Site Station H-I On-Site Station I On-Site Station J On-Site Station K On-Site Station G Off-Site Station, Saint l'aul Street D2 Off-Site Station, Rt. 64 E Off-Site Station, Rt. 4 F Off-site Station, Dutch Ridge Road 880 1040 1320 1430 420 690 2500 700 980 110 0 1320 225 0 1170 1600 1900 at 1.8 miles at 1.1 miles at 1.5 miles at 1.8 miles at 16.4 miles at 0.2 miles at 0.7 miles at 0.8 miles at 0.8 miles at 0.9 miles at 0.5 miles at 5.3 miles at 9.0 miles at 7.2 miles at 7.7 miles 3 - 20

V-F___

F,-

(,-

r-, r --

(

f -,. F___

I--

f-I r I

[-- -

I TABLE 3.3-1 (Continued) 2004 ENVIRONMENTAL SAMPLE LOCATIONS

~--~AP-Tj

~

GREES*riv;'

ESIGN Thermoluminescent Dosimeters (TLD) 3 4

.5 6 -

7*

8 9

10

11 12 13 14*.

15*

18*

19 23*.

24 25 26 27 28 29 30 31 39 47 49*

51 52 53 54 55.

Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-3 Figure 3.3-2 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2' Figure 3.3-2 Dl On-Site Station D2 On-Site Station E On-Site Station F On-Site Station G On-Site Station R-5 Off-Site Station Dl Off-Site Station D2 Off-Site Station E Off-Site Station F Off-Site Station G Off-Site Station Southwest Oswego - Control West Site Boundary Energy Information Center East Site Boundary H On-Site Station I On-Site Station J On-Site Station K On-Site Station North Fence, JAFNPP North Fence, JAFNPP.

North Fence JAFNPP North Fence JAFNPP North Fence NMP-I North Fence NMP-I North Fence JAFNPP Phoenix, NY - Control Oswego Steam Station, East Fitzhugh Park Elementary School, East Fulton High School Mexico' High School Pulaski Gas Substation, Rt. 5 690 1400 1750 2100 250° 420 800 1170 1600 1900 2250 226° 237° 2650 810 700 980 1100 1320 600 68° 650 570 2760 2920 690 1630 223°,

2270 183° 1150 750 at 0.2 miles at 0.4 miles at 0.4 miles at 0.5 miles at 0.7 miles at 16.4 miles at 11.4 miles at 9.0 miles at '7.2 miles at 7.7 miles at 5.3 miles at 12.6 miles at 0.9 miles at 0.4 miles at 1.3 miles at 0.8 miles at 0.8 miles at 0.9 miles at 0.5 miles at 0.4 miles at 0.5 miles at 0.5 miles at 0.4 miles at 0.2 miles at 0.2 miles at 0.6 miles at 19.8 miles at,. 7.4 miles at 5.8 miles at 13.7 miles at 9.3 miles at 13.0 miles 3 2 ' ' I 1.

f

-i T ' m 3 -21

TABLE 3.3-1 (Continitued) 2004 ENVIRONMENTAL SAMPLE LOCATIONS GURLE-

'AP

~~LOCATION DESCRIPTION DERS&

MEDI I DESIGNATION iDISTANCE (1)

Thermoluminescent 56*

Figure 3.3-2 New Haven Elementary School 123° at 5.3 miles Dosimeters (TLD) 58*

Figure 3.3-2 County Route lA and Alcan 2200 at 3.1 miles (Continued) 75*

Figure 3.3-3 North Fence, NMI)-2 50 at 0.1 miles 76*

Figure 3.3-3 North Fence, NMIP-2 250 at 0.1 miles 77*

Figure 3.3-3 North Fence, NMP-2 450 at 0.2 miles 78*

Figure 3.3-3 East Boundary, JAFNIPIP 900 at 1.0 miles 79*

Figure 3.3-3 County Route 29 115° at 1.1 miles 80*

Figure 3.3-3 County Route 29 133° at 1.4 miles 81*

Figure 3.3-3 Miner Road 1590 at 1.6 miles 82*

Figure 3.3-3 Miner Road 1810 at 1.6 miles 83*

Figure 3.3-3 Lakeview Road 2000 at 1.2 miles 84*

Figure 3.3-2 Lakeview Road 2250 at 1.1 miles 85*

Figure 3.3-3 North Fence, NMP-1 2940 at 0.2 miles 86*

Figure 3.3-3 North Fence, NMP-I 315° at 0.1 miles 87*

Figure 3.3-3 North Fence, NMIP-2 3410 at 0.1 miles 88*

Figure 3.3-2 Hickory Grove Road 970 at 4.5 miles 89*

Figure 3.3-2 Leavitt Road 1110 at 4.1 miles 90*

Figure 3.3-2 Route 104 and Keefe Road 1350 at 4.2 miles 91*

Figure 3.3-2 County Route SIA 156° at 4.8 miles 92*

Figure 3.3-2 Maiden Lane Road 1830 at 4.4 miles 93*

Figure 3.3-2 County Route 53 2050 at 4.4 miles 94*

Figure 3.3-2 Country Route I and Kocher Road 2230 at 4.7 miles 95*

Figure 3.3-2 Lakeshore Camp Site 2370 at 4.1 miles 96*

Figure 3.3-2 Creamery Road 1990 at 3.6 miles 97*

Figure 3.3-3 County Route 29 1430 at 1.8 miles 98*

Figure 3.3-2 Lake Road 1010 at 1.2 miles 99 Figure 3.3-2 Nine Mile Point Road 880 at 1.8 miles 100 Figure 3.3-3 Country Route 29 and Lake Road 1040 at 1.1 miles 101 Figure 3.3-3 County Route 29 1320 at 1.5 miles 102 Figure 3.3-2 Oswego County Airport 1750 at 11.9 miles 103 Figure 3.3-3 Energy Center, East 2670 at 0.4 miles 104 Figure 3.3-2 Parkhurst Road 1020 at 1.4 miles 3 - 22

I--

17 r__

[-

Ir-I

-Irt-

[F r([

(-

TABLE 3.3-1 (Continued) 2004 ENVIRONMENTAL SAMPLE LOCATIONS 111m:

_DEGREES Thermoluinescen Thermnoluminescent Dosimeters (TLD)

(Continued) 105 106 107 108 109 111 112 113 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-3 Figure 3.3-2 Figure 3.3-2 Figure 3.3-2 Lakeview Road Shoreline Cove, West of NMP-I Shoreline Cove, \\Vest of NMP-I Lake Road Lake Road Sterling, NY-Control EOF/Env. Lab, Oswego County Airport Baldwinsville, NY - Control 1980 2740 2720 1040 1030 2140 1750 1780 at 1.4 miles at 0.3 miles at 0.3 miles at 1.1 miles at 1.1 miles at 21.8 miles at 11.9 miles at 24.7 miles at 5.2 miles at 9.0 miles at 7.8 miles at 13.9 miles Cows Milk 76 55 4

77*

Figure 3.3-4 Figure 3.3-4

. Figure 3.3-4 Figure 3.3-4 Indicator Location Indicator Location Indicator Location Control Location 1320 950 1130 1910 Food Prod~ucts 133*

132*

144 134 145*

Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Figure 3.3-5 Indicator Location Indicator Location*

Indicator Location Indicator Location Control Location 960 1150 1360 960 2250 at 1.7 miles at 1.9 miles at 1.7 miles at 1.7 miles at 15.6 miles Table Notes:

(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline Sample location required by ODCM 3 - 23

m m

m M

M

=

m

-M FIGURE 3.3-1 NEW YORK STATE MAP A_

NEV YORK A-'

/

ROCIMMW

)

Se5 I

unMc I

I

\\

MUsSCUE POUMMLVM CO4NDO C

NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1 Nine Mile Point Nuclear Station Unit - 2 James A. FitzPatrick Nuclear Power Plant

FIGURE 3. 3 -2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS KEY O ENVIRONMENTAL STATION TLD LOCATION

m m

pi"w 0 Yow k

wq¢ w R

t V,

~

6}_1 4 o

-II=00 FIGURE 3.3-4 MILK AND SURFACE WATER SAMPLE LOCATIONS KEY:

MILK SAMPLE LOCATION SURFACE WffER LOCATION

400 or OSWIGO U"NTY tbwr Ye FISHJNI00000!0So" SHE LOWINGMM A

r Lssw C. e k e -

3.4 LAND USE CENSUS The ODCM require that a milch animal census and a residence census be conducted annually out to.a distance of five miles. Milch animals are defined as any animal that is routinely used to provide milk for human consumption.

The milch animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site. This census is performed once per year in the summer by sending questionnaires to previous milch animal owners, and by. road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Seryice was also contacted X -

to provide any additional information.

The residence census is conducted each year to identify the closest residence in each of the 22.5 degree meteorological sectors out to'a distance of five miles. A residence, for the purposes of this census, is a residence that is occupied on a part time basis (such as a summer camp), or on a full time, year round basis. Several of the'site meteorological sectors are located over Lake Ontario, therefore, there are only eight sectors over land where residences-are located within five miles.

In addition to the milch animal and residence census, a garden census is performed. The census is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the ODCM if broadleaf vegetation sampling and analysis is performed.

3.5 CHANGES TO THE REMP PROGRAM, The following changes were implemented during the 2004 sampling program:

A.

Milk Sampling Program Milk sampling location number 50 was deleted from\\e samping program in 2004. This farm is located at'a 'distance of 8.2 mriles fromn the site' in the' east sector. The sample location was an optional location' as it was beyond-the five mile distance for required sampling. Location'50 was removed from the program because the owner retired from active dairy farming and the milking herd was sold off.

3-29

I -

3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM I.

The noted exceptions to the 2004 sample program address only those samples or monitoring I

requirements which are required by the ODCM. This section satisfies the reporting requirements of Section D 6.9..d of the NMIP1 ODCMI and Section D 4.1.2 of the NNIP2 ODCM.

A.

ODCMN PROGRAM DEVIATIONS The following are deviations from the program specified by the ODCM:

I

1.

RI, R3 and R4 Environmental Sampling Stations were inoperable for varying lengths of times as described below during the sample period of 5/18/04 through 5/25/04. The inoperability was caused by power outages as a result of a series of thunderstorms occurring during the sample period. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

[

Environmental Air Sample Station Power Loss l

l Station Location I

Loss of PoNver (hours)

RI 22.4 R3 6.1 R4 6.1 I

2.

The air sampling pump at the R5 Environmental Sampling Station was inoperable for approximately 1.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during the sample period of 8/10/04 through 8/17/04.

The air sample pump was running at the time of sample collection. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was likely due to a short power outage as severe thunderstorms were experienced in the area of the monitoring station during the sample period. No corrective action was implemented

3.

The air sampling pumps at the R3 and R4 Environmental Sampling Stations were temporarily inoperable during the sample period of 9/28/04 through 10/5/04. The inoperability was caused by a power outage in the local electrical power distribution system The following lengths of inoperability were observed: R-3 (1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ) and R-4 (1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ). Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

3 - 30

4.

The air sampling pump integrator at the R5 Environmental Sampling Station indicated 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of sample pump inoperability over the 7 day sample period of 10/12/04 through 10/19104. The sample p'ump was running at the time of sample collection and there was no indication of equipment damage. Loss of sample time was the result of a power outage required for power line maintenance.

No corrective action was implemented.

B.

AIR SAMPLING STATION OPERABILITY ASSESSMENT The ODCM required air sampling program consists of 5 individual sampling locations.

The collective operable time period for the air monitoring stations was 43,878 hours0.0102 days 0.244 hours 0.00145 weeks 3.34079e-4 months out of a possible 43,920. The air sampling availability factor for'the report period was 99.90%.

3.7 STATISTICAL METHODOLOGY There are a number of statistical 'calculation methodologies used in evaluating the data from the environmental monitoring program.

These methodologies include determination of standard deviation, the mean and associated error for the mean and the lower limit of detection (LLD).-

3.7.1 ESTIMATION OF THE MEAN AND STANDARD DEVIATION The mean, (X), and standard deviation, (s), were used in the reduction of the data generated by the sampling and analysis of the various media in the NMPNS Radiological' Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean (X) and the standard deviation (s):

A.

Mean

.N.

n

Where, X

= estimate of the mean'.

i

=individual sample, i.

N, n = total number of samples with positive indications.

Xi '

= value for sample i above the lower limit of detection.

3 -31

I.

B.

Standard Deviation

[

1l/21

=

(C;_X, -)2 i=l (N - )

Where, X = mean for the values of X s = standard deviation for the sample population.

3.7.2 ESTIMATION OF THE MEAN AND THE ESTIMATED ERROR FOR THIE MEAN In accordance with program policy, two recounts of samples are performed when the initial count indicates the presence of a plant related radionuclide(s). When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive I

detections and the associated propagated error for that mean. In cases where more than one positive sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report.

The following equations were utilized to estimate the mean (X) and the associated propagated error.

A.

Mean n

I xiI N

Where, X

=estimate of the mean.

i

= individual sample, i.

N,n

= total number of samples with positive indications.

Xi

= value for sample i above the lower limit of detection.

3 - 32

B.

Error of the Mean (Reference 18),

ERROR MEAN = [K (ERROR)

-N

Where, i

ERROR MEAN

= propagated error

= individual sample ERROR

= 1 sigma* error of the individual analysis N, n

= number of samples with positive indications Sigma (C)

Sigmna is the greek letter used to represent the mathematical term Standard Deviation.

Standard Deviation is a measure of dispersion from the arithmetic mean of a set of numbers.

3.7.3 LOWVER LIMIT OF DETECTION (LLD)-

The LLD is the predetermined concentration or activity level used to establish a detection limit for the analytical procedures.

The LLDs are specified by the ODCM for.radionuclides in specific media and are determined by taking into account the overall measurement methods. The equation used to calculate the LLD is:

4.66 Sb

\\

1 ;-

LLD=

(E) (V) (2.22) (Y) exp (-2At)

Where:

LLD = the a priori lower limit of detection, as defined above (in picocuries per unit mass or volume);

Sb =

the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute);

I -

I E

=

the counting efficiency (in counts per disintegration);

I V

=

the sample size (in units of mass or volume);

2.22 = the number of disintegrations per minute per picocurie; l

Y

=

the fractional radiochlemical yield (when applicable);

l A

the radioactive decay constant for the particular radionuclide; At the elapsed time between sample collection (or end of the sample collection period) and time of counting.

J The ODCMI LLD formula assumes that:

I

The counting times for the sample and background are equal.

The count rate of the background is approximately equal to the count rate of the sample.

In the ODCM program, LLDs are used to ensure that minimum acceptable detection capabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative).

Table 3.8-1 lists the ODCM program required LLDs for specific media and l

radionuclides as specified by the NRC. The LLDs actually achieved are routinely much lower than those specified by the ODCM.

l 3.8 COMPLIANCE WITH REQUIRED LOWVER LIMITS OF DETECTION (LLD) l Tables D 4.6.20-1 and D 3.5.1-3 of the NMPI ODCMI and NiP2 ODCM, respectively, specify the detection capabilities for environmental sample analysis (See Report Table 3.8-1). The reporting requirements of NMPI ODCM, Section D 6.9.1.d and NMIP2 ODCM, Section D 4.1.2 require that a discussion of all analyses for which the LLDs required by Tables D 4.6.20-1 and D 3.5.1-3 were not j

achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement.

I All sample analyses performed in 2004, as required by the ODCM, achieved the Lower Limit of Detection (LLD) specified by ODCM Tables D 4.6.20-1 and D 3.5.1-3.

3-34

f, __

V__

r-_

r i

I-F-

rF TABLE 3.8-1 I-- -- --.

REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL LOWER LIMIT OF DETECTION (LLD)

SAMPLE ANALYSIS Analysis Water I(pCi/I)

Airborne Particulate or Gases (pCi/M3 ),

Fish (PCi/k-R, wet).

Milk (pCi/1)

Food Products (pCi/kg, wet)

Sediment (pCi/kg, dry)

Gross Beta 4

0.01 H-3 Mn-54 Fe-59 Co-58, Co-60 Zn-65 Zr-95, Nb-95 1-131 3000 (a) 15 30 15 130 Den ou 130 I.

260 I

30 15 15 (a)

Cs-134 Cs-137 15 -

18.

0.07 0.05 0.06 1

60 60 150 130 15

- 18 150 80 180 Ba/La 15 15 (a)

No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore an LLD value of 3000 pCiAiter is used for H-3 and an LLD value of 15 pCi/liter is used for 1-13 1.

3 - 35

I -

3.9 REGULATORY DOSE LIMITS Two federal agencies, the Nuclear Regulatory Commission and the Environmental Protection j

Agency have responsibility for regulations promulgated for protecting the public from radiation and radioactivity beyond the site boundary.

3.9.1 The Nuclear Regulatory Commission (NRC)

The NRC, in 10CFR20.1301, limits the levels of radiation in unrestricted areas resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:

less than or equal to 100 mrem per year to the total body.

In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees.

Conformance to these guidelines ensures that nuclear power reactor effluents are maintained as far below the legal limits as is reasonably achievable.

The NRC, in IOCFR50, Appendix 1, establishes design objectives for the dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:

less than or equal to 3 mrem per year to the total body, and less than or equal to 10 mrem per year to any organ.

The air dose due to release of noble gases in gaseous effluents is restricted to:

less than or equal to 10 mrad per year for gamma radiation, and less than or equal to 20 mrad per year for beta radiation.

The dose to a member of the general public from iodine-131, tritium, and all particulate radionuclides with half-lives greater than 8 days in gaseous effluents is limited to:

less than or equal to 15 mrem per year to any organ.

3 - 36

3.9.2 Environmental Protection Agency (EPA)

The EPA, in 40CFR190.10 Subpart B, sets forth the environmental standards for the uranium fuel cycle. During normal operation, the annual dose to any member of the public from the entire uranium fuel cycle shall be limited to; less than or equal to 25 mrem per year to the whole body, less than or equal to 75 mrem per year to the thyroid, and less than or equal to 25 mrem per year to any other organ.

3 -37

0

4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL POSITION FORMAT All sample data is summarized in table form'. The tables are titled "Radiological Environmental Monitoring Program Annual Summary" and use the following format as specified in the NRC Branch Technical Position:

Column I

1.

Sample'medium

2.

Type and number of analyses performed

3.

Required Lower Limits of Detection (LLD), see Section 3.8, Table 3.8-1. This wording indicates that inclusive data is based on 4.66 Sb (sigma) of background (See Section 3.7).

4.

The mean and range of the positive measured values of the indicator locations.:

5.

The mean, range, and location of the highest indicator annual mean.' Location designations are keyed to Table 3.3-1 in Section 3.3.

6.

The mean and range of the positive'measured values of the control locations.

7.

The number of nonroujtine reports sent to the Nuclear Regulatory Commission.

NOTE:

Only positive measured values are used in statistical calculations.

4 - 1

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT I I)OCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBEIR 2004*

-- o;;

4 w;-W-

~.

P

-'n' INDICATOR

'LOCATION (b) OF HIGHEST

-_NUMBEROF' Ty TEND NUMBE'LJOAIN

~

NULMA:

CONTROL LOCATIOW:NNOTN MEDU LL~a 4!O:WANATILS`YSES*.ANUAMAN NNRUTN (UNIT)A-DSa)S,

.MEAN (t) I RANGE; lRANGE LOCATION &MEANEA

)

ARANGE

-:E

, ;:REPORTS Shoreline Sediment GSA (4):

(pCi/k- -dry)

Cs-134 150

<LLD

<Ll.D

<LLD 0

Cs-137 180 39 (1/2)

No. 5:

39 (1/2)

<LLD 0

39 - 39 1.5 at 800 39 - 39 Fish GSA (20): (Ii)

(pCi/k-g-wet)

Mn-54 130

<LLD

<LLD 0

Fe-59 260

<LLD

<LLI)

<LLD 0

Co-58 130

<LLD

<LLD 0

Co-60 130

<LLD

<LLD 0

ZC-65 260

<LLD

<LLD 0

Cs-134 130

<LLD

<LLD 0

Cs-137 150

<LLD

<LLD 0

4 -2

r---

r_

r r---

F--V

-r r

r---

r-(

TABLE 4.0-1 (iontinucd)'

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 - DECE MBER 2004*

T (pCi/liter).

.,~: :::1 I

I.:

I..

I

--H-3.-

GSA (24):

-Mn-54 Fe-59

<LLD I

<LLD

-<LLD.

<LLD 0

<LLD

': <LLD:

<LLD 0

O

<LLD

- <LLD Co-58

,<LLD Co-60

<LLD

<LLD 0

0 Zn-65 Zr-95

<LLD

.0 0

<LLD

<LLD Nb-95 1-131 Cs-134 Cs-137

<LLD I

I

. I

. I<L D,

.<LLD

<LLD

-LDi

~ <LLD

<LLD

<LLD 0

0

-:-<LLD 0

<LLD

<LLD 0

Ba/La-140

<LLD

.- <LLD

<LLD -

0 4-3 3

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT I I)OCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT2 I)OC%'ET NO. 50-4 10 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2004*

TPjADNJER NCAOR

.LOCATION (b)

OF HIGHEST NUCNRO OATO MBER OF MEDIUM (

LDa)

.. LOFATIONSE

-ANNUAL MEAN:

EANONROUTINE

f)

'A.LOCATION MEAN

( -

RANGE,

REPORTS TLD (nurem per Ganmmia Dose (128)

(d) 5.0 (120/120) (i)

TLD #85 (g):

8.6 (4/4) 4.5 (8/8) 0 standard month) 3.0- 10.8 0.2 at 2940 7.5 - 10.8 3.3 - 5.9 Air particulates Gross Beta (205):

0.01 0.016 (212/212)

R-2 0.017 (53/53) 0.016 (53/53) 0 (pci/m 3 )

0.003 - 0.036 1.1 at 1040 0.008 - 0.036 0.008 - 0.032 1-131 (265):

0.07

<LLD

<LLD 0

GSA (60):

Cs-134 0.05

<LLD

<LLD 0

Cs-137 0.06

<LLD

<LLD 0

Milk GSA (66): (e) (h)

(pCi/liter)

Cs-134 15

<LLD

<LLD 0

Cs-137 I 8

<LLD

<LLD 0

Ba/La-140 15

<LLD

<LLD 0

1-131 (66):

1-131 1

<LLD

<LLD 0

4 - 4

FV

[--

F-V_

V

(

U-V

[_

I r--

F--

Frev-or- - m I -," -

[-----

f---- -

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2004*

Food Products (pCilkg-wet)

GSA (16): (h) 1-131 Cs-134 r

.Cs-137-:

I 60 60.

'I0; I f

. \\ -80,

<LLD

<LLD 0 0

!i 1: ;

, :1 -,!,

I

<LLD

- <LLD 0"

I- "

0'

<LLD.

,, a.

-i

<LLD, I':

1"'

!,~

I

5.

4 - 5

TABLE NOTES:

ITABLEI NOTlElS:

=

Data for Table 4.0-1 is based on Unit I and Unit 2 ODCM required samples unless otherwise indicated.

(a)

=

LLD values as required by the ODCMs. LLD units are specified in the medium colunmn.

(b)

=

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

(c)

=

The ODCMs specify an 1-13 1 and trilium LLD value for surface water analysis (non-drinking water) of 15 pCi/liter and 3000 pCi/liter respectively.

(d)

=

The ODCMs do not specify a particular LLD value to environmental TLDs. The NMP-I and NMP-2 Offsite Dose Calculation Manuals contain specifications for environmental TLD sensitivities.

(e)

=

The ODCM's criteria for indicator milk sample locations include 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 ODCMs is the control location. There were three optional locations during 2004.

(f)

=

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

(g)

=

This dose is not representative of doses to a member of the public since this area is located near the north shoreline which is in close proximity to the generating facility and is not accessible to members of the public (See Section 5.2.4, TLDs).

(h)

=

Data includes results from optional samples in addition to samples required by the ODCMs.

(i)

Indicator TLD locations are: #7, 15, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, 94, 95, 96, 97, 98, 18, 56, and 58. Control TLDs are all TLDs located beyond the influence of the site (TLD 1: 14, 49).

4 -6 L;

5.0 DATA EVALUATION AND DISCUSSION A.

Introduction

.Each year the results of the Annual 'Radiological Environmental Monitoring Program

-- (REMP) are evaluated considering'plant operations at the site, the natural processes in the environment and the archive of historical environmental radiological data. A number of

' factors. are' considered in the' course of evaluating 'andr interpreting the-Annual Envirdnmental Radiological Data. This interpretation can be made using several methods including trend analysis, population dose estimates, risk estimates to the general population based on significance of environmental concentrations, effectiveness' of plant effluent controls and specific research areas. 'The report not only presents the data collected during the 2004 sample program but also assesses the'significance of radionuclides detected in the environment. It is important to note that detection of a radionuclide is not, of itself, an indication of environmental significance; Evaluation of the impact of the radionuclide in'

'terms of potential increased dose to man, in relation to natural background, is necessary to determine the true significance of any detection.

B.

Units of Measure Some of the units of measure used in this report are explained below.

Radioactivity is the number of atoms'in a material that decay per unit of time. Each time an atom decays, radiation is emitted: The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second.

Smaller units of the curie,are used in this report. Two common units are the microcurie (uCi), one millionth '(0.000001). of a!'curie, and' the picocurie (pCi), one trillionth l

(0.000000000001) of a curie. The picocurie is the unit of radiation that is routinely used in this report. The mass, or weight, of radioactive material that would result in one curie of activity depends on the disintegration rate or half-life. For example, one gram of radium-226 contains one curie of activity, but it would require about 1.5 million grams of natural uranium to equal one curie. Radium-226 is more radioactive than natural uranium on a L

weight or mass basis.

5 - 1

C.

Dose/Dose to Man The dose or dose equivalent, simply put, is the amount of ionizing energy deposited or absorbed in living tissue.

The amount of energy deposited or ionization caused is dependent on the type of radiation. For example, alpha radiation can cause dense localized l

ionization that can be up to 20 times the amount of ionization for the same energy imparted as from gamma or x-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of radiation.

When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation.

l The dose equivalent is measured in rem (roentgen equivalent man).

In terms of environmental radiation, the rem is a large unit. Therefore, a smaller unit, the milliremr (mrem) is often used. One millirem is equal to 0.001 of a rem.

The term "dose to man" refers to the dose or dose equivalent that is received by members l

of the general public at or beyond the site boundary. The dose is calculated based on concentrations of radioactive material measured in the environment.

The primary pathways that contribute to the dose to man are the inhalation pathway, the ingestion pathway and direct radiation.

l D.

Discussion There are three separate groups of radionuclide that were measured in the environment in the media analyzed for the 2004 sampling program. The first of these groups consists of those radionuclide that are naturally occurring. The environment contains a significant inventory of naturally occurring radioactive elements.

The components of natural or background radiation include the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space called cosmic radiation, naturally-occurring radioactive isotopes in the human body like potassium-40, medical procedures, man-made phosphate fertilizers (phosphates and uranium are often found together in nature), and household items like televisions.

In the United States, a person's average annual exposure from background radiation is 360 mrem, as illustrated on the following Background Radiation Chart.

5-2

---Background Radiation ALL SOURCES RADIATION EXPOSURE

. 360 mromlyr.

I.

I MAN-MADE SOURCES MElCALX-RAYS11%

lINT8iRNAL;_

ERETIAL 8%.

S ii-COSmIC 8%

NUCLEAR MED!iE 4%,

PROOUiCTS 3%

OTHERt m MAN-Occupational 0.3%

MADE18%

Fallout 0.3%Y

.5.

iiujclea rPower 0.1%

Dose)

Miscellaneous 0.1%

Radiation Exposure In the U (Percent of Total Effective I NCRP 93, 1987 A number of radionuclides'are present in the environment due 'to sources such as cosmic radiation and fallout from nuclear weapons testing. 'These radionuclides are' expected to be present in many of the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of the radiojuiclideshnormally present include:

- Tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere, Beryllium - 7, present as a result of the interaction of cosmic radiation with the upper atmosphere,

Potassium -40 and radium'-226, naturally occurring radionuclides found in the human body 'and throughout the environment, and Fallout radionutlide& from' nuclear weapons'testing,' including cesium-137,

' strontium-89, and strontium-90.

Beryllium'-7 and potassium-40 are especially common in REMP samples." Since they are naturally occurring and are abundant, positive results for these 'radionuclides are reported in some cases in Section 6.0 of this report. Comparisons of program samples to natural background radiation are made thioughoiit this 'section to help put program results into perspective 'and to aid the' readier in' determining what, if any, significant impact is demonstrated by the REMP results. "

5 - 3

The second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's atmosphere. Atmospheric nuclear testing during the early 1950s produced a measurable inventory of radionuclides presently found in the lower I

atmosphere as well as in ecological systems. In 1963 an Atmospheric Test Ban Treaty was signed.

Since the treaty, the global inventory of man-made radioactivity in the l

environment has been greatly reduced through the decay of short lived radionuclides and the removal of radionuclides from the food chain by such natural processes as weathering and sedimentation. This process is referred to in this report as ecological cycling. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China.

In each case, the usual radionuclides associated with nuclear detonations were detected for several months following the test, and then after a peak detection period, diminished to a point where most could not be detected. Although reduced in frequency, atmospheric testing continued into the 1980's. The resulting fallout or deposition from these most recent tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample media analyzed over the years.

The highest l

weapons testing concentrations were noted in samples collected for the 1981 RENIP. Cs-137 was the major byproduct of this testing and is still occasionally detected in a fewv select l

number of environmental media.

The third group of radionuclides that may be detected in the environment are those that are related to nuclear power technology.

These radionuclides are the byproduct of the operation of light water reactors. These byproduct radionuclides are the same as those produced in atmospheric weapons testing and found in the Chernobyl fallout.

This commonality makes a determination of the source of these radionuclides that may be detected in environmental samples difficult to determine. During 2004, Cs-137 was the only potential plant-related radionuclide detected in the REMP samples.

A number of factors must be considered in performing radiological sample data evaluation and interpretation.

The evaluation is made using several approaches including trend analysis and dose to man. An attempt has been made not only to report the data collected during 2004, but also to assess the significance of the radionuclides detected in the environment as compared to natural and other man-made radiation sources. It is important to note that detected concentrations of radionuclides in the local environment as a result of man's technology are very small and are of no or little significance from an environmental or dose to man perspective.

The 1987 per capita average dose was determined to be 360 mrem per year from all sources, as noted in NCRP Report No. 93 (Reference 14). This average dose includes such exposure sources as natural radiation, occupational exposure, weapons testing, consumer products and nuclear medicine. The 1987 per capita dose rate due to natural sources was 5 - 4

295 mrem per year.

The per capita radiation dose from nuclear power production nationwide is less than one mrem'per year.

The natural background 'gammra radiation' in the environs of the -Nine' Mile Point site, resulting from radionuclides in the' atmosphere and in the ground,; accounts for approximately 60-65 'mrem per" year.

This dose is a result of radionuclides of cosmic origin (for example, Be-7) and of primordial origin (Ra-226, K-40,"and Th-232). A dose of 60 mrem per year, as a background dose, is significantly greater than any possible doses as a result of routine operations at the site during 2004.

The results of each sample medium are discussed in detail in Sections 5.1 and 5.2. This includes a summary of the results, the estimated environmental impact, a detailed review of any relevant detections with a dose to man estimate where appropriate, and an analysis of possible long term and short term trends.

During routine implementation of the REMP, additional or optional environmental pathway media are sampled and analyzed. These samples are obtained to:

Expand the area covered by the program beyond that required by the ODCM.

Provide more comprehensive monitoring than is currently required,

Monitor the secondary dose to main pathways, and Maintain the analytical data base established when the plants began commercial operation.

The optional samples that are collected will vary from year to year. In addition to the optional sample media, additional locations are sampled and analyzed for those pathways required by the ODCM. These additional sample locations are obtained to ensure that a variety of environmental pathways are monitored in a comprehensive manner. Data from additional sample locations that are associated with the required ODCM sample media are included in the data presentation and evaluation. When additional locations are included,'

the use of this data is specifically noted in Sections 5.1 and 5.2.

Section 6.0 contains the analytical results for the sample media addressed in the report.

Tables are provided for each required sample medium analyzed during the 2004 program.

5s - Is

Section 7.0, titled Historical Data, contains statistics from previous years environmental I

sampling. The process of determining the impact of plant operation on the environment includes the evaluation of past analytical data to determine if trends are changing or developing. As state-of-the-art detection capabilities improve, data comparison is difficult in some cases.

For example, Lower Limits of Detections (LLDs) have improved significantly since 1969 due to technological advances in laboratory procedures and analytical equipment.

5 - 6

5.1 AQUATIC PROGRAM The aquatic program consists of samples collected from three environmental pathways. These pathways are:.

Shoreline Sediment

-Fish L.

Surface Waters L

.Section 6.0, Tables 6-1 through 6-4 present the analytical results for the aquatic samples collected for the 2004 sampling period.

5.1.1 SHORELINE SEDIMENT RESULTS A.

Results Summary Shoreline sediment samples were obtained in A'pril and October of 2004 at one offsite control location (Lang's Beach located near Oswego Harbor) and at one indicator location (Sunset Bay) which is an area east of the site considered to have recreational value.

A total of four sediment samples were' collected for the 2004 sample program, two indicator and two control. Cs-137 was detected in only one of the samples collected from the Sunset Bay indicator location in 2004, measuring 0.039 pCi/g (dry). This is considered L

a 50% decrease in the number of positive Cs-137 detections made in indicator sample collections compared to the number of samples collected during 2003.

These results continue to show a downward trend over the last 10 years. '.Cs-137 was not detected in samples collected from the control location during 2004; however, Cs-137 has been detected in past control samples.. Cs-137 was detected in control samples collected in 1993 at an average concentration of 0.03 pCi/g.

L The general lack of Cs-137 at the control location is attributed.to the differences in the

-sediment types between the two sample locations (See Data'Evaluation and Discussion).

The source of the' Cs-137 detected in the indicator shoreline sediment is considered to be the result of fallout from atmospheric nuclear weapons testing and not from operations at the site. The mean concentration of Cs-137 measured in the 2004 indicator sample is the lowest measured concentration since shoreline sediment sampling began in 1985.

Historical mean concentrations measured at the indicator location ranged from a maximum 5 -7

.1.

I of 0.33 pCi/g in 1993 to a minimum of 0.04 pCi/- (dry) in 2004. The results for the 2004 control location were less than the detection limit. No other plant-related radionuclides were detected in the 2004 shoreline sediment samples.

The calculated potential whole body and skin doses which may result from the measured Cs-137 concentrations are extremely small and are insignificant when compared to natural background doses.

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over the previous ten years. This graph illustrates a general downward trend in the Cs-137 concentrations since 1994.

I 0.3 0.25 0.2 i,, 0.15 0

a 0.1 0.05 0

Shoreline Sediment I I Control Indicatorl

_ 1 None

_ l detected

- j.

I1 I I I

1 1

l 0I0D 0n to

(-

co0

0) 0

0)

0) 0 0M

0) 0 a) 0

0)

C) a)

0 Year

( '4

( N I

( N J

( N4

.1 B.

Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from the shoreline of Lake Ontario. Samples are collected from one indicator location (Sunset Bay), and one control location (Lang's Beach).

Samples were collected from both the indicator and control locations in April and October 2004. The results of these sample collections are presented in Section 6.0, Table 6-1, "Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2004". Cesium-137 (Cs-137) and Potassium-40 (K-40) were the significant radionuclides detected in the sediment samples.

'I I

I 5 - 8

Cs-137 was detected in the indicator sample collected in April for the 2004 program. The measured concentration for this sample was 0.039 pCi/g (dry). The presence of Cs-137 in certain environmental sample media such as soil, shoreline sediment and fish is historically common. Cs-137 is a fission product that is produced in nuclear power reactors and during atmospheric weapons testing. In addition to the Cs-137 found in the environment as a result of past weapons testing, a significant'inventory of Cs-137 was also introduced globally as a result of the Chernobyl accident in 1986.

Because Cs-137 is found in environmental samples as a result of weapons testing and Chernobyl, it is difficult to accurately determine the source of Cs-137 measured in the sediment sample. It is highly probable that the source of the cesium is from sources other than the operation of plants at the Nine Mile Point Site. It is likely that any sediment sample containing Cs-137 which was the result of plant operation would also contain other plant related isotopes such as Co-60 and Cs-134. The absence of corroborating radionuclides would indicate that the source of Cs-137 in sediment samples is from the existing background Cs-137 which is attributed to weapons testing and the Chernobyl accident., This assessment is further substantiated by the fact that Cs-137 was detected in the 1993 sediment control sample.

Historically, Cs-137 has been routinely measured in the control samples of other environmental media such as fish and soil.

Thegeneral absenceof Cs-137 in the control samples is attributed to the differences in the sediment types between the two sample locations. Few shoreline regions west of the site contain fine sediment and/or sand which would be representative of the indicator location.

It is difficult to obtain control samples that are comparable in physical and chemical characteristics to the indicator samples. Other factors, which includechanging lake level and shoreline erosion, further complicate attempts at consistencyin shoreline sediment sampling. Recent soil samples from locations beyond any expected influence from the site have contained levels of Cs-137 equal to or greater than the concentrations found in the 2004 shoreline sediment samples. The Cs-137 is commonly found in soil samples and is attributed to weapons testing fallout. Shoreline samples containing soil or sediment are likely to contain Cs-J137.,

C.

Dose Evaluation The radiological impact of Cs-137 measured in the shoreline sediment can be evaluated on the basis of dose to man. In the case of shoreline sediments, the critical pathway is direct radiation to the whole body and skin.. Using the parameters provided in Regulatory Guide 1.109, the potential dose to man in mrem per year can be calculated.

The following regulatory guide values and the maximum 2004 shoreline sediment indicator Cs-137 concentration were used in calculating the dose to man:

.5-9

I --

I.

A teenager spends 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at the beach area or on the shoreline,

The sediment has a mass of 40 kg/mr2 (dry) to a depth of 2.5 cm,

The shoreline width factor is 0.3, and

The maximum measured Cs-137 concentration of 0.039 pCi/g (dry).

Using these conservative parameters, the potential dose to the maximum exposed individual (teenager) would be 0.00013 mremlyear to the whole body and 0.00015 I

mrem/year to the skin.

This calculated dose is very small and is insignificant when compared to the natural background annual exposure of approximately 60 mrem as measured by control TLDs in the vicinity of the site.

D.

Data Trends I

The mean Cs-137 concentration for the shoreline sediment indicator sample for 2004 was 0.04 pCi/g (dry). This is the lowest mean concentration measured at the indicator location since shoreline sediment sampling was initiated in 1985.

The previous five years of data show a steady decline in mean concentration values measured at the indicator locations. Over the five year period, mean concentrations ranged from a high of 0.08 pCi/g (dry) in 1999 to a low value of 0.05 pCi/g (dry) measured in both 2002 and 2003. Cesium-137 was not detected in the control location samples over this same five year period.

J The previous ten year data trend for indicator shoreline samples showed a similar downward trend in concentration measured at the indicator sample locations. Over the ten year period of 1994 through 2003, mean concentrations at the indicator location ranged from a maximum of 0.24 pCi/g (dry) in 1994 to a minimum of 0.05 pCi/g (dry) measured I

in 2002 and 2003. The mean indicator concentration measured in 2004 of 0.04 pCi/g (dry) continues to support the long term decreasing trend in Cs-137 concentration in shoreline I

sediment samples. Cesium-137 was not detected in the control samples collected over the previous ten years.

Shoreline sediment sampling at the indicator location commenced in 1985. Prior to 1985, no data was available for long term trend analysis.

Sectopm 7.0, Tables 7-1 and 7-2 illustrate historical environmental data for shoreline sediment samples.

5-10

5.1.2 FISH SAMPLE RESULTS A.

Results Summary A total of 20 fish samples were collected for the 2004 sample program. Species collected were: smallmouth bass, brown trout, walleye and chinook salmon. The analytical results for the 2004 fish samples showed no detectable concentration of radionuclide that would be attributable to plant 'operations at the site or past atmospheric weapons testing. The absence'. of Cs-137 in the 2004:fish samples is significant in the fact that it continues to validate the absence of Cs-137 in fish samples'observed.. With the exception of 2001, 2003 and 2004, positive concentrations of Cs-137 have been measured in fish samples collected

. in the previous 20 years at a combination of both the. indicator and/or control locations.

(Refer-to Tables 7-3 and 7-4).,-These low levels of Cs-137 represented no significant dose to man or impact on the environment.

The 2004 fish sample results demonstrate that plant operations at the Nine Mile Point Site have no measurable radiological environmental impact on the upper levels of the Lake i

Ontario'food chain. The 2004 'results are consistent with previous year's results in that they -continue to support the :.general long-term downwardi trend in fish Cs-137 concentrations over the last 24 years.. Cs-137 was not detected in fish samples collected in 2000, 2001, 2003 and 2004 from indicator locations. The period 'of 2000 through 2004 as a group are the lowest results measured since the beginning of the Site Environmental Monitoring Program in 1969.

B.

Data Evaluation and Discussion Fish 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 NMPNS and the JAFNPP facilities. The Oswego Harbor samples served as control samples while the NMPNS and JAFNPP samples served as indicator samples. All samples were analyzed for gamma emitters. Section 6.0, Table 6-2 shows individual results for all the samples collected in 2004 in units of pCi/g (wet).

The spring fish collection was made up 'of 9 individual'samples representing three separate species.

Walleye, smallrmouth.bass and brown trout were collected from all three locations.

The total fall fish collection was comprised of 11 individual samples representing four individual species. Brown trout, chinook salmon and walleye were collected from all three 5 Jo-11

I -

sampling locations. Smallmouth bass were collected at the control and JAFNPP indicator locations.

Cs-137 was not detected in any of the fish species collected for the 2004 sample program C.

Dose Evaluation Fish represent the highest level in the aquatic food chain and have the potential to be a contributor to the dose to man from the operations at the site. The lack of detectable concentrations of plant-related radionuclides in the 2004 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic pathway. Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry. Therefore, these fish are an integral part of the human food chain.

D.

Data Trends The Cs-137 data for fish samples over the previous five years (1999 through 2003) show

]

that the number of positive detections has decreased over this period. There are no positive detections in either 2001 or 2003 and only intermittent detections in the remaining years of l

this period. The general lack of positive detections was continued in the 2004 sample year.

The graph below illustrates the mean control and indicator Cs-137 concentrations for 2004 and the previous ten years.

Annual Mean Fish Cs-137 Concentrations 0.035 0.03 0 Control

Indicator I

None Detected 0.025

__0.02 0.015 0.01 D1, 0.005--

5

-I 0.

Ca 0'

0S0 0

0 CS C,

C, Cue 0

0 0

0 Year 5-12

The ten year data trend shows a consistent level of Cs-137 measured in fish between 1994 and 2000. After 2000, the number of positive detections drops off as noted in the five year trend. The 1994 through 2004 results, as a group, are the lowest Cs-137 concentrations measured over the existence of the sample program.

The general long-term decreasingirend for Cs-137, illustrated in the graph below, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay. The concentrations of Cs-137 detected in fish since 1976 are considered to be the result of weapons testing fallout. The general downward trend in concentrations will continue as a function of additional ecological cycling and radiological decay.

-j Fish Cs-137 1.6 O Control -

Indicator 1.4 -

1.2-

.None Detected E 0.8 -

U 0.6 0.4-0.2 0

Iri =P P-P_

W)

W W

M 0+ o W° W-C° V~

0~

C CYar C4 V

Va V) 9 a

)5

>V r

V,> V> 0V V V V V) 90 4

CD CDE Year 0

.. a, 1..

j,,,

-Section 7.0, Tables 7-3 and 7-4 showv historical environmental sample data for fish.

t {

-

i:..

5 -13

5.1.3 SURFACE WATER (LAKE)

A.

Results Summary The ODCMv requires that monthly surface water samples be taken from the respective inlet water supplies of the JAFNPP and NRG Energy's Oswego Steam Station. In conjunction with the required samples, three additional Lake Ontario surface water locations are sampled and analyzed.

These additional locations are the Oswego City Water Intake, the NMIP1 Intake and the NMIP2 Intake.

Gamma spectral analysis was performed on 24 monthly composite samples from the ODCM locations and on 36 monthly composite samples collected from the additional sample locations. The results of the gamma spectral analyses showed that only naturally-occurring radionuclides were detected in the 60 samples from the five locations collected for the 2004 Sampling Program.

The two naturally-occurring radionuclide detected were K-40 and Ra-226 and were not related to plant operations.

Monthly composite samples showed no presence of plant-related gamma emitting isotopes in l

the waters of Lake Ontario as a result of plant operations.

The monthly surface water samples are composited on a quarterly basis and are analyzed for tritium. A total of 20 samples were analyzed for tritium as part of the 2004 RENIP program.

The results for the 2004 samples showed no positive detections of tritium. All results for 2004 were below the established measurement sensitivity and are reported as less than the lower limit of detection (<LLD). There is no indication of a long-term buildup of tritium concentrations in the surface waters adjacent to the site.

B.

Data Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples from five Lake Ontario sampling locations. No plant-related radionuclide were detected in 2004 samples.

This is consistent with historical data, which has not shown the presence of plant-related radionuclides in surface water samples.

Tritium samples are quarterly samples that are a composite of the applicable monthly samples for a given location. Tritium samples analyzed for the 2004 sample program were analyzed to an instrument detection level of 500 pCi/l.

The tritium results for the JAFNPP inlet canal samples contained no positive detections. The 2004 results had LLD values that ranged from <408 pCi/i to <439 pCi/l. The ODCM Control location (Oswego Steam Station inlet canal) results showed no positive detections and the sample results had LLD values in the range of <421 pCi/I to <439 pCi/l.

5 - 14

Tritium was not detected in any of the twelve optional Lake Ontario samples collected in the 2004 program. The Oswego City Water inlet is sampled to monitor drinking water quality and is representative of a control location due to its distance from the site. The city water inlet' is located 7.8 miles west of the site in an "up-stream' direction based on the current patterns in the lake.,

No positive detections of tritium were identified in 2004. The following is a summary of LLD results for the 2004 sample program:

Sample Tritium Concentration pCi/liter Location inimum Maximu Mean (Annual)

JAF Inlet (Indicator)*

<408

<439

<425 Oswego Steam Inlet (Control)*

<421

<439

<429

-NMP #1 Inlet

<421

<439

<429 NMPi#2Inlet.

<421

<439

<429 Oswego City Water Supply.

<421

<439

<429

Sample location required by ODCM The above LLD values are far below the ODCM required LLD value of 3000 pCi/l.

Analytical results for surface water samples are found in Section 6.0, Tables 6-3 through 6-4.

C.

Dose Evaluation The radiological impact to members of the public from low levels of tritium in water is insignificant. This can be illustrated by calculating a dose to the whole body and maximum organ using the maximum LLD value and Regulatory Guide '1.109 methodology. Based on a water ingestion rate of510 liters/yr and the maximum 2004 LLD concentration of<439 pCi/l, the calculated dose would be less than 0.045 mrem to the child whole body and less than 0.045 mrem to the child liver (critical age group/organ).

D.

Data Trends There are no data trends for gamma emitters such as Cs-137 and Co-60 as historically these radionuclides have not been detected in lake water samp'les.

5,- 15

'I.

Tritium results for the 2004 lake water samples were consistent with results from the previous five years for both the indicator and control locations.

The mean measured tritium concentrations for the previous five year period of 1999 - 2003 ranged from 212 pCi/l to 337 pCi/I for the control and 185 pCi/I to 297 pCi/I for the indicator location. By comparison, the mean 2004 tritium concentrations were < 429 pCi/I and < 425 pCi/l for the control and indicator locations respectively. The previous five year data indicates no significant trends in either the indicator or the control mean concentrations. This previous five year data set is consistent with long term tritium results measured at the site. The indicator data from the previous ten year period, 1994 through 2003, is representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured.

The 1999 mean control value of 337 pCi/I is the highest concentration measured since 1989 and is within the variability of results measured over the life of the program. The ten year historical results are consistent between the control and indicator locations with no large variation in the measured results.

The following graph illustrates the concentrations of tritium measured in Lake Ontario over the past 20 years at both an indicator and control location. Prior to 1985, the Oswego City Water Supply results were used as control location data as this location closely approximates the Oswego Steam Station, the current control location.

1.

Surface W'aterTritium 600 6

' None Detecced 0

Ocont 500 400 S

301 0

-h y

200 100 0

I

I I1 v7 V^

a 0

rO 00 0a 0

=

g

'4r m

la r-M so 0

'r 00 0

00 00 00 00 o

0 C%

0%

s C

0%

0D 0

C 0

0D 0

0%

as 0%

0%

a, E.

C Cal 0s Cal 0%

0%

E%

0%

0 0o0 0

0 Year Historical data for Surface Water Tritium is presented in Section 7.0, Tables 7-7 and 7-8.

5 - 16

5.2 TERRESTRIAL PROGRAM The terrestrial program consists of samples collected from four environmental pathways. These pathways are:

Airborne particulate and radioiodine,

-Direct Radiation,

Milk, and L

'Food Products' I

Section 6.0, Tables 6-5 through 6-12 present the collected for the 2004 reporting period. -

5.2.1 AIR PARTICULATE GROSS BETA, A.

Results Summary analytical results for the terrestrial samples A.

Weekly air samples were collected and analyzed for particulate gross beta particulate activity. 'For the 2004 program, a total of 53 samples were collected from control location'-

R-5 and 212'samples were collected from indicator locations R-1, R-2, R-3, and R-4.

These five locations are required by the ODCM. Additional air sampling locations are maintained and are discussed in Sectiohn!5.2.1.B below. The mean gross beta concentration for samples collected from the control location (R-5) in 2004 was 0.016 pCi/m3. The mean gross beta concentration for the samples collected from the indicator locations (R-1, R-2, R-3, and R-4) in 2004 was 0.016 pCi/fr.

.The mean gross beta results for the indicator and the control stations were equal in 2004. The consistency between-the indicator and control mean values, demonstrates that there are no increased airborne radioactivity levels in the general 'vicinity of the site: ::-The indicator results are consistent with concentrations measured over the last fifteen years.

This consistency demonstrates that the natural baseline.gross beta activity has' been reached. The man-made radionuclide contribution to the natural background from atmospheric weapons testing and Chemobyl can no longer be detected above the background-concentrations of naturally occurring beta emitting radionuclides.

5 - 17

Il B.

Data Evaluation and Discussion l

The air monitoring system consists of fifteen sample locations, six onsite and nine offsite.

l Each location is sampled weekly for particulate gross beta activity. A total of 795 samples were collected and analyzed as part of the 2004 program. Five of the nine offsite locations l

are required by the ODCNI. These locations are designated as R-l, R-2, R-3, R-4, and R-5.

R-5 is a control location required by the ODCM and is located beyond any local influence from the site. [n addition, optional offsite and onsite air sample locations are maintained from which weekly samples are collected. The optional offsite locations are designated as D-2, E, F and G. The optional onsite locations are designated as D-1, G, H, I, J and K.

I Gross beta analysis requires that the samples be counted no sooner than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after collection. This allows for the decay of short half-life naturally-occurring radionuclides, thereby increasing the sensitivity of the analysis for plant-related radionuclides.

Section 6.0, Tables 6-5 and 6-6 present the weekly gross beta activity results for samples collected from the offsite and onsite locations.

j The average annual gross beta indicator concentrations for the ODCNI indicator stations (R-l, R-2, R-3 and R-4) was 0.016 pCi/mr3.

The offsite ODCNI control station (R-5) annual mean gross beta concentration was 0.016 pCi/mi3. The minimum, maximum and average gross beta results for sample locations required by the ODCMI were:

Concentration pCi/mi3 Location Minimum NMaximum Mean I

R-1 0.003 0.036 0.014 R-2 0.008 0.036 0.017 R-3 0.007 0.035 0.017 R-4 0.008 0.036 0.016 R-5 0.008 0.032 0.016 The mean weekly gross beta concentrations measured in 2004 are illustrated in the following graphs:

5 - 18

I Air PartlculateFilter-Gross Beta I

X 4

S 6

1 3

lo. 1la 12 13 14 II 16 17 Is 99 26 21 2

23 24 23 26 Week #

Air Particulate Filter - Gross Beta Indicator Control WHS M. Ike Ax The fluctuations observed in the gross beta activity over the year. can be attributed to changes in the environment, especially seasonal changes. The concentrations of naturally-occurring radionuclides in the loWer levels of the atmosphere directly above the land are affected by time-related processes such as wind direction, precipitation, snow cover, soil temperature and soil moisture content.

C.

Dose Evaluation Dose calculations are not performed based on gross beta concentrations. Dose to man as a result of radioactivity in air is calculated using the specific radionuclide and the associated 5:-.19

dose factor. See Section 5.2.2.C for dose calculations from air concentrations. The dose received by man from air gross beta concentration is a component of the natural background.

D.

Data Trends With the exception of the 1986 sample data, which was affected by the Chernobyl accident, the general trend in air particulate gross beta activity has been one of decreasing I

activity since 1981, when the mean control value was 0.165 pCi/mi3. The 1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.

0.18 Air Particulate Filter-Gross Beta 018-l 0 Series I a Series2 L

0.14 1980: Atmospheric 0.12 0.1 U 0.08 0.06-0.04 1jj Chernobyl 0.02 i!

IflIIn ul 0

0 0

Year The trend for the previous five years represents a base line concentration or natural background level for gross beta concentrations.

This trend is stable with minor fluctuations due to natural variations. The change in concentrations over the period of 1994 through 2004 is very small. This is illustrated by the following graph.

5-20

AirParticulate Filter-Gross Beta 0.0180 01 l

Indicator

Control 0.016-0.0 14--

0.0 12 i

u0.0!

0.008.

0.006-0.0104 0.002,-

0 "IS 0

CI 0

0 0

0 00 0

0 0

0 V

e 0

0 0

Yea Cd cm CIA C

.,. 1 1 For the operational period of 1994 - 2004, the mean annual gross beta concentration at the control station (R-5) has remained steady with a narrow range of 0.013 pCi/rn3 to 0.017 pCi/rn 3.

The mean annual concentrations for the indicator stations for this same time period were similar to the control and ranged from a maximum mean of 0.017 pCi/m3 in 1999 to a minimum mean of 0.010 pCi/m3 in 1997.

Historical data of air particulate gross beta activity are presented in Section 7.0, Tables 7-9 and 7-10.

5.2.2 MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS)

A.

Results Summary Fifteen air monitoring stations are maintained around the Nine Mile Point Site. Five of the 15 air monitoring stations are required by the ODCM and are located offsite near the site boundary and offsite as a control location. Ten additional air sampling stations are also maintained as part of the sampling program.

Together, these fifteen continuous air sampling stations make up a comprehensive environmental' monitoring network for measuring radioactive air particulate concentrations in the environs of the site. Annually, the air monitoring stations provide 795 individual air particulate samples which are assembled by location into 180 monthly composite samples. The monthly composites are analyzed using gamma spectroscopy.

No plant-related gamma emitting ridionuclides were detected in any of the air particulate filter samples collected during 2004.

5-21

'UL-The gamma analysis results for the monthly composite samples routinely showed positive detections of Be-7, K-40, and Ra-226. Each of these radionuclides is naturally occurring.

B.

Data Evaluation Discussion A total of fifteen air samnplinga stations are in continuous operation and located both onsite and in the offsite sectors surrounding the Nine Mile Point Site.

Five of the fifteen M

monitoring stations are required by the ODCM and the remaining ten are optional to provide an effective monitoring network. Composite air filter samples are assembled for each of the fifteen sampling locations. Each of the weekly air particulate filters collected i

for the month is assembled by location to form monthly composite samples. The monthly composite samples required by the ODCM are composite samples assembled for R-1, R-2, R-3, R-4 and R-5. Other sample locations not required by the ODCM, for which analytical results have been provided, include six onsite locations and four offsite locations. The analytical results for the 180 air particulate filter composites in 2004 showed no detectable l

activity of plant related radionuclides.

The results of the monthly composite samples are presented in Section 6.0, Table 6-9.

C.

Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no J

plant related radionuclides were detected in 2004. The monthly air particulate sampling program demonstrated no offsite dose to man from this pathway as a result of operations of the plants located at the Nine Mile Point Site.

D.

Data Trends No plant related radionuclides were detected during 2004 at the off-site air monitoring locations.

The ten year database of air particulate composite analysis shows that there is no buildup

[

or routine presence of plant related radionuclides in particulate form in the atmosphere around the site.. Historically Co-60 was detected in each of the years from 1977 through

'l 1984 at both the indicator and control locations, with the exception of 1980 when Co-60 was not detected at the control location.

The presence of Co-60 in the air samples collected during these years was the result of atmospheric weapons testing. Co-60 was again detected in an offsite 2000 indicator sample and was the only positive detection of Co-60 since 1984. The detection of Co-60 in the one 2000 sample was an isolated event 4

5-22

associated with effluents from the :NMP1 facility.

There have been no subsequent measurable concentrations of Co-60 in the environment surrounding the NMP site.

Historical data shows that Cs-137-is the fission product radionuclide most frequently detected in the air particulate filter composites. Cs-137 was detected in each of the years from 1977 through 1983 at both the control and indicator sampling locations.

The presence of Cs-137 in the air samples collected during these years was the result of atmospheric weapons testing.

Cs-137 was again detected in 1986 as :a result of the Chernobyl accident.

Since 1986 there have been no detections of Cs-137 in the environment surrounding the NMP site.

After 1986, no plant related or fallout radionuclides were detected in any of the offsite air particulate composite samples with the exception of the isolated detection.of Co-60 in 2000 in a single sample. A review of the past five year's data for air, particulate filter composites indicates no plant related radiological impact on the environment. All previous historical positive detections of fission product radionuclides were associated with atmospheric weapons testing or the Chernobyl accident, with the exception of the 2000 detection noted above.

Historical data for air particulate results are presented in Section 7.0, Tables.7-13 and 7-14.

5;2.3 AIRBORNE RADIOIODINE (1-131)

A.

Results Summary Iodine-131 (1-131) was not detected in any of the 795 samples analyzed for the 2004 program. No radioiodine has been measured off-site at the constant air monitoring stations since 1987.

B.

Data Evaluation and Discussion Airborne radioiodine is monitored at the fifteen air sampling stations also used to collect air particulate samples. There are nine offsite locations, five of which are required by the ODCM. The offsite locations required by the ODCM are designated as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influence from the plant. Ten air sampling locations are also maintained in addition to those required by the ODCM. Six of these stations D-l, G, H, I, J andK are located onsite. D-2, E, F and G are the optional stations located offsite.

5 - 23

I L.

11 11 Samples are collected using activated charcoal cartridges. They are analyzed weekly for I-131. 1-131 was not detected in any of the 2004 samples collected.

1 The analytical data for radioiodine are presented in Section 6.0, Tables 6-7 and 6-8.

C.

Dose Evaluation The calculated dose as a result of 1-131 was not evaluated due to the fact 1-131 was not detected during 2004. The I-131 sampling program demonstrated no off-site dose to man from this pathway as a result of operation of the plants located at Nine Mile Point.

D.

Data Trends No radioiodine has been detected in samples collected from the air sampling locations required by the ODCM since 1987.

11 There has been no positive detection of 1-131. in air samples collected over the last ten years. This demonstrates that there is no measurable environmental impact or positive trend for iodine buildup due to plant operations during the period from 1994 through 2004.

I-131 has previously been detected in samples collected during the last eighteen year period in 1986 and 1987. The 1986 detection of I-131 was the result of the Chernobyl accident and the 1987 detection was the result of plant operations.

D Iodine-131 has been detected in the past at control locations. Control samples collected during 1976 had a mean 1-131 concentration of 0.60 pCi/M3.

During 1977 this mean decreased to 0.32 pCi/m.3, and further decreased by a factor of ten to 0.03 pCi/M3 in 1978.

I-131 was not detected in samples collected from the control location during 1979 - 1981 X

and 1983 - 1985.

I-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/rn3.

Iodine-131 has been detected in samples collected from the on-site indicator locations during 1980 - 1983 and 1986 - 1987. The mean concentrations ranged from 0.013 pCi/m3 in 1980 to a maximum of 0.119 pCi/m.3 in 1986. The maximum mean indicator 1-131 concentration of 0.119 pCi/i 3 was the result of the Chernobyl accident.

1-131 was detected in a total of 75 weekly samples collected duiring the 1986 sample program. The 1986 measured concentrations ranged from a minimum of 0.023 pCi/m3 to a maximum of 0.36 pCi/m3. Each positive detection of I-131 in samples collected in 1986 was the direct result of the Chernobyl Nuclear accident.

Historical data for 1-131 are presented in Section 7.0, Tables 7-11 and 7-12.

5-24 II

5.2.4 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD)

A.

Results Summary Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. As part of the 2004 environmental monitoring program, TLDs were placed at a total of 72 different environmental TLD locations (32 required by the ODCM and 40 optional locations). These TLDs were placed, collected and read each quarter of 2004. As a result of placing two TLDs at each location, the results presented in this report are the average of two TLD readings obtained for a given location.

The 72 TLDs were placed in the following five geographical locations around the site boundary:

Onsite (areas within the site boundary),

Site Boundary (area of the site boundary in each of the 16 meteorological sectors),

Offsite Sector (area four to five -miles from the site in each of the eight land based meteorological sectors),

.Special Interest (areas of high population density and use), and

Control (areas beyond significant influence of the site).

All geographical locations are required by the ODCM with the 'exception of the Onsite area which was optional. Description of the five geograpical categories and the designation of specific TLD locations that make up each category is presented in Section 3.1.5, TLD (Direct Radiation) of this report.'

A summary of the 2004 dose rates for each of the five geographical locations is as follows:

Dose in mrem per standard month Geographic Category '

Mm Max Mean Onsite (Optional) 3.3 13.2 5.4 Site Boundary (Inner Ring)

3.3 6.4 4.4 Offsite Sectors (Outer Ring)

3.2' 6.7 4.4 Special Interest * (2) 3.0 5.9 4.2 Control*(3)

A:

3.3 5.9 4.5 Geographical locations required by the ODCI.

1 Only includes TLD results that are not affected by radwaste direct shine (TLD #s. 78, 79, 80, 81, 82, 83,84,7,18) 2 Only includes TLD results required by the ODCM (TLD #s. 15, 56, 58, 96, 97, 98) 3 Only includes TLD results required by the ODCM (TLD. #s. -14, 49) 5 -25

Comparison of annual mean dose rates associated with each geographical location indicate that there is no statistical difference in annual dose as a function of distance from the site boundary. The measured annual dose rate at the nearest resident to the site was consistent III with the dose rates measured at the site boundary and control locations. The results for the Site Boundary, Offsite Sectors and Special Interest (Offsite) were well within expected normal variation when compared to the Control TLD results.

The results for the 2004 environmental TLD monitoring program indicate that there was no II significant increase in dose rates as a result of operations at the site. The Hydrogen Water Chemistry systems used at NMPNS did not measurably increase the ambient radiation exposure rate beyond the site boundary.

B.

Data Evaluation and Discussion Direct Radiation (Gamma Dose) measurements were taken at 72 different environmental locations during 2004, 32 of which are required by the ODCM. These locations are grouped into five geographical location categories for evaluation of results.

The five categories include: Onsite, Site Boundary, Offsite Sector, Special Interest and Control locations. All categories are required by the ODCM with the exception of the Onsite TLDs. Onsite TLDs are placed at various locations within the site boundary to provide Ill additional information on direct radiation levels at and around the NMIPI, NNIP2 and JAFNPP facilities.

Onsite TLDs are optional and are subdivided into three categories for which direct radiation results are evaluated. The 2004 direct radiation results for Onsite TLD locations were as follows:

1.

Results for TLDs located near the NMPI, NMP2 and JAFNPP generating facilities and at previous or existing on-site air monitoring stations ranged from 3.3 to 13.2 mrem per standard month.

2.

Results for TLDs located near the north shoreline ofNMP I, NMP2 and Fitzpatrick facilities in close proximity to the Radwaste and Unit I Reactor Building ranged from 3.3 to 37.6 mrem per standard month.

[I

3.

Results for TLDs located onsite near the Energy Information Center and its associated shoreline ranged from 3.9 to 6.8 mrem per standard month.

iJ Site Boundary TLD results ranged from 3.3 to 10.8.mrem per standard. month in 2004.

This range included all TLDs placed in each of the 16 meteorological sectors in the general 5-26

area of the site boundary. The highest dose rate measured at a location required by the ODCM was 10.8 mrem per standard month.

This TLD, (TLD 85) represents the site boundary maximum dose and is located in the WNW sector along the lake shore in close proximity to the NMP1 plant. The TLD locations along the lakeshore close to the plants (TLD #s 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildings and radwaste shipping activities. These locations and are not accessible to members of the public and the TLD results for these areas are not representative of dose rates measured at the remaining site boundary locations. The remaining Site Boundary TLD locations, which are located away from the plant ranged from 3.3 to 6.4 mrem per standard month resulting in an average dose rate of 4.4 mrem per standard month.

Offsite Sector TLDs, required by the ODCM, located 4 to 5 miles from the site in each of the 8 land based meteorological sectors ranged from 3.2 to 6.7 mrem per standard month with an average dose rate of 4.4 mrem per standard month.

Special Interest TLDs from all locations ranged from 3.0 to 6.8 mrem per standard month with a 2004 annual average dose rate of 4.4 mrem per standard month.-

The Control TLD group required by the ODCM utilizes locations positioned well beyond the site. -2004 Control TLD results ranged from 3.3 to 5.9 mrem per standard month with an annual average dose rate of 4.3 mrem per standard month. These results include both the ODCM required control TLDs and the three additional control TLDs.

TLD analysis results are presented in Section 6.0, Table 6-10.

C.

Dose evaluation 2004 annual mean dose rates 'for each geographic location required by the ODCM are as follows:

Site Boundary:.

4.4 mrem jer standard month (TLD #s: 78, 79, 80, 81, 82, 83, 84, 7, 18)

Offsite Sectors:

4.4 mrem per standard month (TLD #s: 88, 89, 90, 91, 92, 93, 94,

.9.5)

Special Interest:

4.2 mrem per standard month (TLD #s: 15, 56, 58, 96, 97, 98)

Control:

4.5 mrem per standard month (TLD #s 14,49) 5 -27

The measured mean dose rate in the proximity of the closest resident was 4.2 mrem per standard month (TLD #s: 108, 109) which is consistent with the control measurements of 4.5 mrem per standard month.

The mean annual dose for each of the geographic location categories demonstrates that there is no statistical difference in the annual dose as; a function of distance from the site.

The TLD program verifies that operations at the site do not measurably contribute to the J

levels of direct radiation present in the offsite environment.

D.

Data Trends A comparison of historical TLD results can be made using the different geographical l

categories of measurement locations. These include Site Boundary TLDs located in each of the 16 meteorological sectors, TLDs located offsite in each land based sector at a distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDs 11!

located at control locations.

Site Boundary, Offsite Sector and Special Interest TLD locations became effective in 1985; therefore, trends for these results can only be evaluated l

from 1985 to the present.

The following graph illustrates TLD results for the Control, Site Boundary, Offsite Sectors i

and Special Interest groups from 1991 through 2004:

TLD Data a Control a Site Boundary

OMfsite Sector El Special Interest 5

3 L I 2

i 0

-s co s-co 0

0o a

o4 en o

Year e

(

4 C 4 LI TLDs located at the site boundary averaged 4.4 mrem per standard month during 2004 L

(Site Boundary average results do not include TLDs influenced by radwaste buildings and radwaste shipping activities). This result is consistent with the previous five year average of 4.5 mrem per standard month.

5-28

Offsite Sector TLDs averaged 4.4 mrem per standard month during 2004. This result is also consistent with the previous five year average of 4.3 mrem per standard month for offsite sectors.

Special Interest TLD locations averaged 4.2 mrem per standard month during 2004 which is consistent with the previous five year average of 4.3 mrem per standard month.

The last group of TLD locations required by the ODCM is the Control Group. This group utilized.TLD locations positioned well beyond the site. 2004 control results from all Control TLDs averaged 4.3 mrem per standard month, consistent with the previous five year average of 4.4 mrem per standard month. The 2004 TLD program results, when compared to the previous seventeen years, showed no significant trends relative to increased dose rates in the environment-Section 7.0, Tables 7-15 through 7-20'show the historical environmental sample data for environmental TLDs.

5.2.5 MILK' A.

Results Summary A total of 66 milk samples were collected during the 2004 program and analyzed for gamma emitting radionuclides using, gamnma'spectroscopy.

In. addition, each sample

' undergoes an iodine extraction procedure to determine the presence of Iodine-131 (I-13 1).

I-131, a possible plant related radionuclide, is measured to.evaluate the cow/milk dose pathway to man. 1-131 was not detected in any of the 66 milk samples collected in 2004 from the four milk sample locations.,

Gamma spectral analyses 'of the imilk samples showed only naturally occurring radionuclides, such as K-40, were detected in milk samples collected during'2004. K-40 was detected in all indicator and control samples.

K-40 is a naturally occurring radionuclide and is found in many environmental sample media.

Vo.

The 2004 results demonstrate that routine operations of the Nine Mile Point Site resulted in no measurable contribution to the "dose to the public" from the cow/milk pathway.

5 - 29

B.

Sampling Overview l

Milk samples were collected from three indicator locations and one control location. The ODCM requires that three sample locations be within five miles of the site. Based on the j

milk animal census, there were no adequate milk sample locations within five miles of the site in-2004.

Samples were collected from four farms located beyond the five-mile requirement to ensure the continued monitoring of this important pathway.

The three indicator locations ranged from 5.2 to 9.0 miles from the site. The control samples were collected from a farm located 15.6 miles from the site and in a low frequency wind sector (upwind). The geographic location of each sample location is listed below:

Location No.

Direction From Site Distance (Miles) 76 SE 5.2 55 E

9.0 4

ESE 7.8 77 (Control)

SSW 13.9 1

Samples were collected from Indicator location # 76 and Control location #77 from April l

through December, during the first and second half of each month. The remaining optional sample locations (4 and 55) were sampled once each during April through June and twice per month July through December. Samples were not required to be collected during January through March of 2004 as a result of 1-131 not having been detected in samples collected during November and December of 2003, as stipulated in the ODCM.

C.

Data Evaluation and Discussion l

Each milk sample is analyzed for gamma emitters using gamma spectral analysis. The I-131 analysis is performed using resin extraction followed by spectral analysis for each sample.

1-131 and gamma analysis results for milk samples collected during 2004 are provided in Section 6.0, Table 6-11.

[I Iodine-131 was not detected in any indicator or control milk samples analyzed during 2004. All 1-131 milk results were reported as Lower Limits of Detection (LLD). The LLD results for all samples ranged from < 0.30 to < 0.83 pCi/liter.

No plant-related radionuclides were detected in any milk sample collected in 2004. K-40 was the most abundant radionuclide detected, and found in every indicator and control sample collected.

K-40 is a naturally-occurring radionuclide and is found in many of the environmental media samples. The K-40 concentration for all milk samples analyzed ranged from 980 to 5-30 A

1990 pCi/liter. Cs-137 was not detected in any indicator or control milk sample collected in 2004.

D.

Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected.

The' dose to' man from naturally occurring concentrations of K-40 in milk and other environmental media can be calculated. This calculation illustrates that the dose received due to exposure from plant effluents is 'negligible compared to the dose received from naturally occurring radionuclides.. Significant levels of K-40 have been measured in environmental samples.

A 70 kilogram (154 pound) adult contains' approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation, consumption, etc.).

The dose to bone tissue is about 20 mrem per year as a result of internal deposition of naturally-occurring K-40.

E.

Data Trends Man-made radionuclides are not routinely detected in milk samples. In the past nineteen years, Cs-137 was only detected in 1986, 1987, and 1988. -The mean Cs-137 indicator activities for those years were 8.6, 6.8 and 10.0 pCi/liter, respectively.'

I-131 was measured in two milk samples collected in 1997 from a'single sample location, having a mean concentration of 0.50 pCi/liter and was of undetermined origin.- The previous detection was in 1986 with a mean concentration of 13.6 pCi/liter. The 1986 activity was a

result of the Chernobyl accident. '

The comparison of 2004 data. to historical results over the operating life of the plants shows that Cs-137 and 1-131 levels have decreased significantly since 1983.

Historical data of milk sample'results for Cs-137 and I-131 are presented in Section 7.0, Tables 7-21 and 7-22.

1-l 5.2.6 FOOD PRODUCTS (VEGETATION)

A.

Results Summary There were no plant-related radionuclides detected in the 16 food product samples collected and analyzed for the 2004 program.

5 -31

I l" IL Detectable levels of naturally occurring K-40 were measured in all control and indicator samples collected for the 2004 program.

Ra-226, Be-7 and AcTh-228, all naturally-occurring radionuclide, were also detected intermittently in samples collected in 2004.

These results are consistent with the levels measured in 2003 and previous years.

The results of the 2004 sampling program demonstrate that there is no measurable impact on the dose to the public from the garden pathway as a result of plant operations.

B.

Data Analysis and Discussion Food product samples were collected from four indicator locations and one control location. The indicator locations are represented by nearby gardens in areas of highest D/Q (deposition -factor). values based on historical meteorology and an annual garden census. The control location was a garden 15 miles* away. in a predominately upwind direction.

11 Food product samples collected during 2004 included two varieties considered to be an edible broadleaf vegetable. Cabbage, an edible broadleaf vegetable, was collected from one indicator location. Collards were collected from another indicator location. Neither of these edible broadleaf varieties were available from the control location. The general lack l

of edible broadleaf vegetation samples was the result of grower preference and such varieties were not available in local gardens.

Where broadleaf vegetables were not available, non-edible broadleaf vegetation was collected. Non-edible vegetation consisting of squash leaves, grape leaves, zucchini leaves, and cucumber leaves were collected for the 2004 program. The leaves of these plants were sampled as representative of broadlieaf i

vegetation which is a measurement of radionuclide deposition. In addition to the broadleaf vegetation, tomato samples were collected from four locations. Samples were collected during the late summer/fall harvest season. Each sample was analyzed for gamma emitters using gamma spectroscopy.

The analysis of food product samples collected during 2004 did not detect any plant-related radionuclides.

Results for the past five years also demonstrate that there is no buildup of plant-related radionuclides in the garden food products grown in areas close to the site.

Naturally-occurring Be-7, K-40, Ra-226 and AcTh-228 were detected in food product samples. The concentration of Be-7 in vegetation samples ranged from 0.23 to 1:62 pCi/g (wet). The concentration of K-40 in indicator and control samples ranged from 2.03 to 4.59 pCi/g (wet). Ra-226 and AcTh-228 were detected intermittently in the samples. The results for naturally-occurring radionuclides are consistent with the data of prior years.

5-32

Analytical results for food products are found in Section 6.0, Table 6-12.

C.

Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant-related radionuclides were' detected.

The food product sampling program demonstrated no measurable offsite'dose to man from this pathway as a result of operations of the plants located at Nine Mile Point.

D.

Data Trends Food product/vegetation sample results for the last five years demonstrate that there is no chronic deposition or buildup of plant-related radionuclides in the garden food products in the environs near the site.

The last positive indication was for Cs-137 which was detected at one indicator location in 1999 with a concentration of 0.008 pCi/g (wet).

-137 had been d!t'cted intnspre Historically, Cs-137 had been detected in ten separate years since 1976 ranging from a maximum mean concentration of 0.047 pCi/g (wet) in 1985 to a minimum of 0.008 pCi/g v(wet) in 1999.

The trend for'Cs437 is a general 'reduction in concentration to non detectable levels in samples collected during the 2000 through 2004 sample'programs.

Historical data of food product results are presented in Section 7.0, Tables 7-23 and 7-24.

5.2.7 LAND USE CENSUS RESULTS A.

Results Summary The ODCM requires that an annual land use census be performed to identify potential new locations for milk sampling and for calculating the dose to man from plant effluents. In 2004, a milk animal census, a nearest resident census and a garden survey were performed.

Based on the 2004 milk census milk sampling location X50 was deleted from the sampling program in 2004. This farm was sampled during the 2003 sampling program; however, it was an optional location as it was beyond the five mile distance for required sampling.

Location # 50 was removed from the program because the owner retired from active dairy farming and the milking herd was sold off.

5 - 33

The results of the closest residence census conducted in 2004 required no change to either the NMIP I or NMP2 ODCMs' closest resident location.

i A garden census, not required by the ODCM, is performed to identify appropriate garden sampling locations and dose calculation receptors. Garden samples were collected from a number of locations listed in Table 5-1 of the NMP1 and NMP2 ODCMs and identified in the census as active for 2004. See Table 3.3-1 for 2004 sampling locations.

B.

Data Evaluation and Discussion A land use census is conducted each year to determine the utilization of land in the vicinity of the Nine Mile Point site. The land use census consists of two types of surveys. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. The census, covering areas out to a distance of 10 miles exceeds the 5 mile distance required by the ODCM.

A resident census is conducted and is designed to identify the nearest resident in each meteorological sector out to a distance of 5 miles.

The milk animal census is an estimation of the number of cows and goats within an approximate 10 mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by sending questionnaires to previous milk l

animal owners and also by road surveys to locate any possible new locations. In the event the questionnaires are not answered, the owners are contacted by telephone or in person. '

The local county agricultural extension service is also contacted as an additional source of information concerning new milk animal locations in the vicinity of the site.

The number of milk animals located within an approximate 10 mile radius of the site was estimated to be 500 cows and 10 goats based on the 2004 land use census. The number of

[jj cows has decreased by 140 and the number of goats has increased by 4 when compared to the 2003 census. The goats identified during the census were not milking goats. The results of the milk animal census are found in Section 6.0, Table 6-13.

The second type of census conducted is a residence census. The census is conducted in

[

order to identify the closest residence within 5 miles in each of the 22.5 degree land-based meteorological sectors. There are only eight sectors over land where residences are located within 5 miles. The water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW.

.1 The results of the residence census, showing the applicable sectors and degrees and distance of each of the nearest residence, are found in Section 6.0, Table 6-14. No changes were identified in the 2004 census for the closest resident in the land based meteorological sectors.

The nearest resident locations are illustrated in Section 3.3, Figure 3.3-5.

5-34 L

5.3 CONCLUSION

The Radiological Environmental Monitoring.Program (REMP) is an ongoing program implemented to measure and document the radiological impact of NMPNS operations on the local environment. The program is designed to detect and evaluate small changes in the radiological environment surrounding the site. Environmental media representing food sources consumed at the higher levels of the food chain,, such as fish, food products and milk, are part of a comprehensive sampling program. Results of all samples are reviewed closely to determine any possible impact to the environment or to man.

In addition, program results are evaluated for possible short and long term historical trends.

The federal government has established dose limits to protect the public from radiation and radioactivity. The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10 of the U.S. Code of Federal Regulations (10CFR20).

The Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40CFRI90). Radiation exposure to members of the public, calculated based on the results of the REMP, is extremely small. The dose to members of the public from operations at the Nine Mile Point site, based on environmental measurement and calculations made from effluent releases, is determined to be a fraction of limits set forth by the NRC and EPA.

The results of the 2004 Radiological Environmental Surveillance Program continue to clearly demonstrate that there is no significant short term or chronic long term radiological impact on the environment in the vicinity of the Nine Mile Point site. No unusual radiological characteristics were measured or observed in the local environment. The Environmental Monitoring Program continues to demonstrate that the effluents from the site to the environment contribute no significant or even measurable radiation exposures to the general public as confirmed by the sampling and analysis of environmental media from recognized environmental pathways: Based on TLD results there was no measurable increase in radiation levels beyond the site boundary as a result of the hydrogen water chemistry programs. Environmental radiation levels measured at the nearest residence are at the background level based on control station TLD results. The only measurable radiological impact on the environment continues to be the result of atmospheric weapons testing conducted in the early 1980s and the 1986 accident at the Chernobyl Nuclear Power Plant. Both of these source terms have contributed to a measurable inventory of Cs-137 in the environment. The results for the 2004 sample program demonstrate that the concentrations of man-made radionuclides continue to decline.

This reduction in environmental background concentrations will allow for the site environmental program to become more sensitive to the measurable impact of plant operations on the environment as time goes on.

5 - 35

The environmental monitoring program detected one potential plant-related radionuclide in the sample media collected during 2004. Cs-137 was detected in one shoreline sediment sample. The source of the Cs-137 measured in this sample is considered to be fallout from past atmospheric t

nuclear weapons testing. The measured concentration of Cs-137 in the sample was small and consistent with historical results for shoreline sediment.

The impact of these Cs-137 concentrations are minimal in terms of dose to man.

Dose from man-made sources in the environment is very small when compared to the dose originating from naturally-occurring sources of radioactivity.

Radiation from naturally-occurring radionuclides such as K-40 and Ra-226 contributed the vast majority of the total annual dose to members of the general public. The dose to members of the public, resulting from plant operations, is extremely small in comparison to the dose contribution from natural background levels and sources other than the plants.

The whole body dose in Oswego County due to natural sources is approximately 50 - 60 mrem per. individual per year as demonstrated by control environmental TLDs. The fraction of the annual dose to man, attributable j

to site operation, remains insignificant.

Based upon the overall results of the 2004 Radiological Environmental Monitoring Program, it can be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that would be expected for the lakeshore environment of the J l site.

1I i3

All L

lI L

5-36 L

5.4 REFERENCES

1.

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.

2.

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

3.

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

4.

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

5.

National Council on Radiation Protection and Measurements (NCRP), Environmental Radiation Measurements, NCRP Report No. 50, 1975.

6.

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

7.

National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977.

8.

National Council on Radiation Protection and Measurmnents (NCRP), Radiation Exposure from Consumer Products and Miscellaneous Sources. NCRP Report No. 56, 1977.

9.

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

10.

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

11.

Schleien, Bernard. The Health Physics and Radiological Health Handbook. Scinta, Inc.,

Silver Spring, Maryland, 1992.

5 - 37

12.

U.S. Department of Health and Human Services. Preparedness and Response in Radiation Accidents, National Center for Devices and Radiological Health, Rackville, Maryland 20857, August 1983.

13.

National Council on Radiation Protection and Measurments (NCRP), Ionizing Radiation Exposure of the Population of the United States NCRP Report'No. 93, 1987.

14.

National Council on Radiation Protection and Measurements (NCRP), Exposure of the l

Population in the United States and Canada from National Background Radiation, NCRP Report No. 94, 1987.

-I III A

L L

5 I

6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6.1 Environmental sample data is summarized in table format. Tables are provided for select sample media and contain data based on actual values obtained over the year. These values are comprised of both positive Values and LLD values where applicable.

6.2 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "real" signal (See Section 3.7.3 for detailed explanation).

6.3 When the initial count of a sample indicates the presence of radioactivity, two recounts are normally performed. When aradionuclide is positively identified in two or more counts, the analytical results for that radionuclide is reported as the mean of the positive detections and the associated error for that mean (see Section 3.7.2 for methodology).

6.4 Many of the tables are footnoted with the term "Plant Radionuclides".

Plant related radionuclides are radionuclides that are produced in the reactor as a result of plant operation either through the activation or fission process.

.,6-lI

TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 2004 Results in Units of pCi/g (dry) + 1 Signia SAMPLE-',

COLLECTION.-

. GAMMA EMITTERS LOCATION DATE K-40 ;

Co-60 i

Cs-134 Cs-137 l l

Zn-65

Otherst 04/21/04 17.3 +/- 0.465

<0.035

<0.026 0.039 1 0.014

<0.058

<LLD Sunset Bay (05)***

10/20/04 17.4 + 0.737

<0.044

<0.065

<0.060

<0.095

<LLD 04/21/04 9.00 +/- 0.385

<0.029

<0.031

<0.094

<LLD Lang's Beach (06, Control) ***

10/20/04 11.7 + 0.380

<0.036

<0.023

<0.031

<0.048

<LLD t

Plant related radionuclides

+

Corresponds to samnple-locations noted on Figure 3.3-5 6-2

~

i~-

(--- --

(--- "

F- "

f -----

V.

(

r

(

F r

-F F----

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2004 Results in Units of pCilg (wet) +/- 1 Sigma

(

I I rI DATE l

TYPE-l K-40 l-Mn Co-58:l

.Fe-59.-

I -Co-60 -;

Zn-65 I

Cs-434 Cs-137.

Otherst FITZPATRICK (03)***

06/09/04 Brown-Trout - 5.24+/-0.357

<0.034

<0.036

<0.115

<0.036

<0.011

<0.033

<0.036

<LLD 06/08/04 Wallcye 4.84+/-0.342

<0.038

<0.118

<0.036

<0.077

<0.036

<0.029

<LLD 06/08/04 Walleye 4.84+/-0.342

<0.038

<0.118

<0.036

<0.077

<0.030

<0.029

<LLD

,Ch i

.noo 09/17/04 Browni Trout 4.56+/-0.296

<0.023

<0.032

-<0.077

-<0.030

<0.061

<0.029

<0.025

<LLD 09/17/04 Chinook 6.19+/-0.299

<0.031

<0.035

<0.080

<0.031

<0.072

<0.023

<0.030

<LLD Salmon 09/17/04 Walleye 3.74+0.367

<0.042

<0.056

<0.139

<0.045

<0.107

<0.037

<0.042

<LLD 09/17/04 Smallmouth 5.27+/-0.337

<0.030

<0.125

<0.039

<0.079

<0.040

<0.032

<LLD Bass Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides

t.

v 6-3

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2004 Results in Units of pCi/g (wvet) + 1 Sigma DATE I

TYPE I

K-40 I

Mn-54 1,-Co-58.-

I Fe-59 I Co-60 I

Zn-65 I Cs-134 -

Cs-137 Others NINE MILE POINT (02)***

06/08/04 Brown Trout 6.13 + 0.298

<0.036

<0.037

<0.088

<0.035

<0.081

<0.037

<0.030

<LLD 06/08/04 Walleye 4.81 + 0.304

<0.034

<0.060

<0.044

<0.073

<0.026

<LLD 06/14/04 Smallmouth 5.82 0.373

<0.035

<0.040

<0.110

<0.044

<0.098

<0.042

<0.040

<LLD Bass 09/17/04 Brown Trout 4.28 + 0.285

<0.030

<0.031

<0.098

<0.038

<0.054

<0.031

<LLD 09/17/04 C

4.42 0.289

<0.034

<0.031

<0.105

<0.022

<0.067

<0.026

<LLD Salmon 09/17/04 Walleye 4.67 + 0.377

<0.043

<0.026

<0.095

<0.036

<0.085

<0.029

<0.035

<LLD

- - Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides 6 -4

-i

-_=

L_.;

i i; i.

1

.1 -

I L

r

-" r--

(f flr -

Jf f

Vr--

[F[***- I ---- V, -

1- -

F--

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2004 Results in Units of pCi/g (wet) + 1 Sigma DATE..-

I TYPE K-40 Mn-54 Co-58 Fe-59-. l Co-60 I Zn-65 I Cs-134 l Cs-137 I Otherst OSWVEGO HARBOR (CONTROL) (00)***

06/10/04 Brown Trout 4.28+0.279

<0.030

<0.028

<0.079

<0.034

<0.069

<0.027

<0.032

<LLD 06/10/04 Walleye 4.97+0.338

<0.033

<0.034

<0.116

<0.029

<0.075

<0.033

<0.035

<LLD 06/14/04 Smallbouth 06/14/04a 6.12+0.367

<0.040

<0.039

<0.100

<0.047

<0.091

<0.039

<0.032

<LLD

.Bass.

09/15/04

Brown Trout; 5.06+0.177

<0.021

<0.023

<0.058

<0.021

<0.050

<0.014

<0.021

<LLD 09/15/04 5.16+0.269

<0.037

-<0.029

<0.094

--- <0.034-

<0.072

<0.020

<0.027

<LLD Salmon 09/15/04.

Walleye 4.88+0.272

<0.023

<0.026

<0.075

<0.034

<0.066

<0.025

<0.027

<LLD 09/15/04 Smallmouth 5.30+0.222

<0.024

<0.073

< 0.022

<0.057

<0.022

<0.023

<LLD Bass Corresponds to sample location noted on Figure 3.3-5 t Plant related radionuclides

j 6-5,

TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2004 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l + 1 Sigma STATION CODE:

PERIOD i.;::-

DATE TRITUM First Quarter 01/02/04 - 04/01/04

< 432 FITZPATRICK*

Second Quarter 04/01/04 - 07/01/04

< 439 (03, INLET)***

Third Quarter 07/01/04 - 10/02/04

< 421 Fourth Quarter 10/02/04 - 01/03/05

< 408 First Quarter 12/29/03 - 04/02/04

< 432 OSWEGO STEAM STATION*

Second Quarter 04/02/04 - 07/01/04

< 439 (08, CONTROL)***

Third Quarter 07/01/04 - 09/30/04

< 421 Fourth Quarter 09/30/04 - 12/29/04

< 425 First Quarter 12/29/03 - 04/02/04

< 432 NINE MILE POINT UNIT 1**

Second Quarter 04/02/04 - 07/01/04

< 439 (09, INLET)***

Third Quarter 07/01/04 - 09/30/04

< 421 Fourth Quarter 09/30/04 - 12/29/04

< 425 First Quarter 12/29/03 - 04/02/04

< 432 NINE MILE POINT UNIT 2**

Second Quarter 04/02/04 - 07/01/04

< 439 (11, INLET)*-*

Third Quarter 07/01/04 - 09/30/04

< 421 Fourth Quarter 09/30/04 - 12/29/04

< 425 First Quarter 12/29/03 - 04/02/04

< 432 OSWEGO CITY WATER**

Second Quarter 04/02/04 - 07/01/04

< 439 (10)***

Third Quarter 07/01/04 - 09/30/04

< 421 Fourth Quarter 09/30/04 - 12/29/04

< 425 Sample location required by ODCM Optional sample location Corresponds to sample location noted on Figure 3.3-4 6-6 6

i--

6 -- -_

i--

"

--

.1I

F- -,

I ----

I- -,-

F ---,

F---,

F --

r

(

r-F[ -

I ---

I F-

[-- -

r- -

TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2004 Results in Units of pCi/liter 4 1 Sigma OSWEGO STEAM STATION* (08, CONTROL)***

NUCLIDE

-:JANUARY.-- -.-. : FEBRUARY

.,MARCH -

APRIL '

MAY JUNE 1-131

<12.2

<8.96

<12.7

<13.9

<11.9

<10.6 Cs-134

<2.57

<2.38

<1.58

<4.82

<2.24

<3.68 Cs-137

'<2A4

<2.42

<2.55

<4.11

<3.83

<3.23 Zr-95

<5.46

<5.14

<5.76

<7.38

<7.82

<5.79 Nb-95

<3.90

<3.67

<3.25

<6.03

<5.00

<5.10 Co-58

<3.10

<2.93

<3.36

<5.23

<4.13

<4.29 Mn-54

<2.86

<2.65

<2.62,

<4.41

<3.76

<3.69.

' Zn-65

<3.86

<5.94'

- -<6.51'-'

<11.4

<9.35

<8.89 Fe-59

<8.40

<8.79

<9.25

<15.4

'<13.9

<10.4 Co-60

<2.58

<2.62

<2.68

<4.77

<4.85

<4.11 K-40 164 + 14.4 175 + 15.6 180 i 15.3 344 + 29.4 271 + 24.4 187 21.5 Ba/La-140

<8.63

<7.27

<8.91

<10.4

<14.8

<7.60 NUCLIDE.

JUY

!.: J -AUGUS

-- A I ;:SEPTEMBER.. -

OCTOBER

.I- :-NOVEMBER --

DECEMBER

'I-131

<15.0

<11.0

<11.3

<8.41

<11.1

<8.93 Cs-134

<3.08

<1;57

<3.48

<1.80

<4.22

<3.85 Cs-137

<4.64

<2.26

<3.42

<2.41

<3.30

<3.60 Zr-95

<9.47

<4.45

<6.74

<4.96

<6.96

<7.22 Nb-95

<5.88

<3.20

<4.00

<3.30

<5.02

<4.39 Co-58

<5.46

<2.68

<3.58

<2.89

<4.32

<4.31 Mn-54

<5.25.

<2.31

<3.45

<2'44

<3.86 -<4.04 Zn-65

<10.6

<5.11

<7.60

<5.75

<8.11-

<9.29 Fe-59

<14.1

<6.48

<10.6

<7.84

<11.7

<11.6 Co-60

<5.22

<2.05

<3.21

<2.50"

<3.16

<3.82 K-40 333 29.5 238 +/- 13.0, 356 + 21.6-

+281+/-j6.1 269 + 22.9 406 + 26.6 Ba/La-140

<13.1

<6.36

<10.5

<6.38

<10.3

<10.8 Sample location requireo by Fgr..

- Corresponds to sample location noted on Figure 3.3-4

- 6 = 7

TABLE 6-4 (continued)

- CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2004 Results in Units of pCilliter +/- 1 Sigma FITZPATRICK* (03, INLET)***

NUCLIDE JANUARY---- IFEBRUARY=-

1-MARCH APRIL I

MAY JUNE 1-131

<10.3

<5.85

<11.9

<8.61

<8.68

<10.9 Cs-134

<4.26

<1.46

<3.27

<2.93

<3.50

<2.66 Cs-137

<3.96

<2.15

<3.42

<2.92

<3.66

<4.28 Zr-95

<9.96

<4.20

<6.73

<5.72

<7.20

<9.22 Nb-95

<5.46

<2.58

<4.50

<3.84

<4.75

<5.58 Co-58

<4.96

<2.42

<4.25

<3.04

<3.94

<4.51 Mn-54

<3.10

<2.26

<3.61

<2.31

- <4.16

<3.97 Zn-65

<9.62

<4.86

<4.81

<6.12

<9.71

<9.37 Fe-59

<13.9

<6.31

<11.4

<9.07

<13.6

<14.5 Co-60

<4.62

<2.35

<3.09

<2.90

<5.08

<4.75 K-40 161 +/- 23.2 231 +/- 12.8 338 +/- 21.5 133 +/- 13.9 199 +/- 23.0 137 22.1 Ba/La-140

<10.3

<4.25

<10.9

<8.04

<12.8

<11.3

NUCLIDE.

JULY i

AUGUST'.-.

SEPTEMBER

-OCTOBER;-..

NOVEMBER-.1 DECEMBER I-131

<13.8

<12.9

<9.19

<7.08

<13.8

<7.95

-Cs-134

<5.32

<4.55

<2.55

<2.93

<3.36

<1.67 Cs-137

<5.09

<4.91

<2.67

<2.80

<2.90

<2.51 Zr-95

<9.75

<10.2

<4.92

<5.45

<6.67

<4.38 Nb-95

<6.06

<7.00

<3.43

<3.49

<3.63

<2.85 Co-58

<5.11

<5.51

<2.93

<2.81

<3.93

<2.71 Mn-54

<4.86

<5.27

<2.49

<2.78

<3.00

<2.70 Zn-65

<11.9

<12.0

<6.24

<5.88

<6.71

<2.77 Fe-59

<16.2

<14.6

<8.61

<8.80

<10.8

<7.13 Co-60

<5.79

<4.02

<2.65

<2.54*-

<4.04

<2.36 K-40 332 +/- 33.8 208 +/- 25.7 142 +/- 14.5 126 +/- 14.0 167 +/- 19.2 264 +/- 14.2 Ba/La-140

<14.8

<12.0

<8.07-

<6.43

<11.3

<6.89 Sample location required by UOUM.

- - Corresponds to sample location noted.on Figure 3.34 6-8

=

-~

I j-FE _:

Fi

iE

e_ ----

t l

r_

r-__

F-F

~

I F-(_

r-_

i---

I_- - r

'V

-I TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURrIFACE WATER SAMPLES - 2004 Results in Units of pCi/liter + 1 Sigma NINE MILE POINT UNIT 1** (09, INLET)***

NUCLIDE -;

,JANUARY-

-FEBRUARY -,

MARCH '--

APRIL - '

.MAY JUNE I-1'31

<14.4

<12.2

<14.6

<13.2

<14.0

<8.14 Cs-134

<3.33

<3.49

<3.50

<3.72

<3.08

<2.54 Cs-137

<332

<3.59

<3.57

<3.96'

<3.09

<2.58 Zr-95'

<6.28

<6.94

<7.69.

<7.70

<5.73

<5.43 Nb-95

<4.30

<3.52

<4.56

<4.68

<4.80

<3.53 Co-58

'<3.92

<3.94

<4.17

<4.68

<3.59

<3.03 Mn;-54

<3.33

<3.99

<3.41

<3.85

<3.64

<2.66 Zn-65' "7.34

<8.65

<8.04

<9.54

<<.68

<6.03 Fe-59

-,<11.5,

<12.2-

<10.5

<15.4,

<1 1.6

<10.0 Co-60

<3.66

<3.03

<4.07

<3.74

<3.53

<3.10 K-40 179 +-19.7 177 + 21.3 203 +/- 21.2 192 23.8 165 +/-,19.6 176 16.5 Ba/La-140

<9.06

<8.54

<12.5

<11.4

<12.3

<7.54 OTBR

.',j,-DCME NUCLIDE '

,Y--

TF-AUGUSTX.;

SEPTEMBER-:

OCTOBER-NOVEMBER' D

1-131

<11.9

<10.6

<9.49

<13.1

<7.74

<10.4 Cs-134

<3.72

<2.70

<2.69

<3.80.!

<2.83

<4.37 Cs-137

<3.59

<2.20

<2.73

<3.40

<2.88

<3.86 Zr-95

<7.08

<5.68

<5.69.

<6.66

<5.30

<7.78 Nb-95

<5.52

<3.45

<3.80

<4.68

<3.45

<4.75 Co-58

<4.70

<2.76-

<2.87

<3.85

<2.90

<4.90 Mn-54

<3.81

<2.40

<2;6i

<3.87

<2.53

<4.94 Zn-65

<9.06

<4.76 '

<6.30'

<7.88

<6.30

<1 1.3 Fe-59

<13.2

<8.91

<7.99

<10.8

<9.06

<11.9 Co-60

<4.30

<2.36

<2.90

<3.53"

<2.74

<4.64 K-40 173 +/- 22.4 83.3 +/- 12.4, 120 13.5 155+/- 19.0 170 + 15.2.

246+/-25.0 Ba/La-140

- <10.3 -

- <9.38-

<8.31

<10.2.

<7.39

<9.06

- Optional sample location.

- - Corresponds to sample location noted on Figure 3.3A4

6.

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2004 Results in Units of pCi/liter 1 Sigma NINE MILE POINT UNIT 2** (11, INLET)***

NUCLIDE'-

'- ;1JANUARY. -

FEBRUARY - '--

MARCH APRIL MAY JUNE I-131

<12.5

<12.6

<10.6

<11.8

<10.3

<9.32 Cs-134

<2.50

<3.35

<2.90

<3.84

<1.63

<2.10 Cs-137

<2.90

<3.12

<3.14

<3.59

<2.94

<3.42 Zr-95

<5.96

<7.59

<6.63

<7.44

<5.34

<5.61 Nb-95

<3.82

<4.80

<3.51

<5.25

<3.55

<4.41 Co-58

<3.11

<3.92

<3.10

<4.32

<3.14

<3.53 Mn-54

<2.55

<3.82

<2.59

<3.60

<2.77

<3.10 Zn-65

<6.70

<7.88

<6.48

<8.43

'<5.88

<7.83 Fe-59

<9.23

<13.7

<10.1

<13.9

<9.63

<10.0 Co-60

<3.13

<3.37

<3.33

<4.29

<3.08

<3.29 K-40 150+/- 14.5 182 +/- 21.1 126'+/- 14.5 108 +/- 17.6 126 +/- 14.0 368 +/- 21.7 Ba/La-140

<7.06

<11.0

<8.30

<10.3

<8.62

<8.18 NUCLLDE' JULY-

- l -;-

AUGUST 4.: SEPTEMBER ' -

OCTOBER

-' - NOVEMBER; ' ' DECEMBER I-131

<13.9

<14.7

<8.95

<8.09

<7.68

<7.31 Cs-134

<3.98

<3.53

<1.60

<2.81

<1.86

<3.17 Cs-137

<3.45

<2.69

<2.15

<2.88

<2.90

<2.99 Zr-95

<8.15

<6.09

<4.46

<5.61

<5.73

<6.25 Nb-95

<6.26

<4.01

<3.06

<3.45

<3.21

<4.59 Co-58

,<4.14

<3.65

<2.57

<2.65

<3.29

<3.24 Mn-54

<4.39

<3.47

<2.24

<2.55

<2.82

<3.06 Zn-65

<9.30

<6.76

<2.96

<7.32

<5.73

<6.92 Fe-59

<14.8

<10.5

<6.40

<8.59

<8.98

<8.56 Co-60

<4.81

<3.21

<2.17

<2.74"

<2.75

<3.16 K-40 82.4 +/- 18.6 200 +/- 17.9 239 +/- 13.2 198 I 16.6 153 +/- 16.4 156 +/- 16.9 Ba/La-140

<14.7

<10.2

- <5.18-

<7.37

<7.42

<8.08

- Optional sample location

- - Corresponds to sample location noted on Figure 3.34 6 ' -10 g

- i

=-

~---

I r

r__

I __

F _

r -

i V, r--

r

r F,

F-- -

I-F__'

F_'

(-'

F-I TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2004 Results in Units of p'Ci/liter +/-+ 1 Sigma OSWVEGO CITY-NVATER** (10)**

--.NUCLIDE

. I,tJANUARY..

FEBRUARYtJ' :.-~-MARCHV J

APRIL I

MY 4JN I-131

<13.8

<9.97

<1 1.7

<12.2

<14.6

<7.93.

Cs-134

<2.02'

<2.62

<3.25

<2.09

<2.87

<1.48 Cs-137

<3.01-

<2.74

<3.29

<3.13

<2.83

<2.28 Zr-95 69 46 60

<5.79

<6.09

<4.46 Nb-95:

<4.79

<3.81

<4.62

-~i3.56

<3.91

~

<3.07 Co-58

<3.75

<2.90

'<3.90

<3.49

<.2<2.73 Mn-54'

<3.24

<2.73

<3.37

<3.39

<2.95

<2.36 Zn-65t 45

,.56.01,~_

<5.00

<3.4<69

<3.12 Fe-59

<i:9.66~ ",

<8.65,.

<11..

1.

<8.43,

<6.64'

C-0<3.61:

-,<2.63

<.4<3.23,

<2.85

.<.31'..

'K-40 3-"81 &22.3

~

173 +15.1 338 +/-E22.5 247 +17.6 372 +19.9'"

272 14.1-Ba/La-140.:

<;9.58

<769<0.8.00

<10.5

~

<5.05

.-NUCLIDE-,r f.~

UL~~

AUGUST,,'7 7. [

4SEP.T EMBER+/- ~

-OCTOBER. T. J,NOvEMl3ERI.;

DCMER:.

1-131

<12.8

<12.9

<13.9

<8.49

<8.02

<7.25

Cs4'34

<2.17

<3.10

<3.40

<2.61

<2.93

<3.19 Cs-137

<~3.76

.<2.88

<3.53

<2.32

<'2.52

<2.62

Zr-95

<8.09.

<5.5 7

<6.86

,<4.74.

<5.27

<5.44-Nb-95

<4.79

<3.47

<c4.4 8

<3.37

<3.52,

<3.37

C6-58

.<4.06

<2.99

'<4.40

<3.20

<2.76'

<3.47 Mn-54

<3.39

<2.82

<4.21

<2.51

<2.74

<~2.45 Zn-65

<9.47

.<7.13

<8.89

<5.38

<5.25

<5.70 Fe-59

<1 0.5

<8.98

<12.5

<7.95

<7.64

<8.94 Co-60

<4.71

<2.67

<3.35

<2.36"

<2.51

<2.79 K-40 105 +18.3

.186+/-+15.9 194+/-+20.4 95.2:~12 5 10 +/- 13.8 91.9 +/- 15.3 BaILa-140

<12.1

<9.91

.-<10.3

'<7.05

<6.83

<6.30

- Optional Sample location i

- Cbrresponds to sample location noted on Figure 3.3-4

.. 6-11>-

TABLE 6-5 NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE STATIONS - 2004 GROSS BETA ACTIVITY pCi/f 3 i I Signia LOCATION W eek S tart R-14

R 5

l D -2**

I

_l

_ _l G **

- Date -

OFF SITE

^

F S IT E: '

OFFSITE-. l FFS1TE:-. l:'.OFFS1TE OFFSITE l-OFFSITE!

OFFSITE lOFFSITE 12/30/04 0.0189 +/- 0.002 0.0214 +/- 0.002 0.0173 +/- 0.002 0.0177 +/- 0.002 0.0222 +/- 0.002 0.0194 +/- 0.002 0.0183 +/- 0.002 0.0196 +/- 0.002 0.0157 +/- 0.001 01/06/04 0.0173 +/- 0.002 0.0197 +/- 0.002 0.0162 +/- 0.002 0.0153 +/- 0.002 0.0202 +/- 0.002 0.0202 +/- 0.002 0.0219 +/- 0.002 0.0213 +/- 0.002 0.0183 +/- 0.002 01/13/04 0.0139 0.001 0.0197 +/- 0.002 0.0141+/- 0.001 0.0116+/- 0.001 0.0106 +/- 0.001 0.0135 +/- 0.001 0.0104 +/- 0.001 0.0125 +/- 0.001 0.0114 +/- 0.001 01/20/04 0.0120 +/- 0.001 0.0141 +/- 0.001 0.0158 +/- 0.002 0.0142 +/- 0.001 0.0172 + 0.002 0.0136 +/- 0.002 0.0155 +/- 0.002 0.0160 +/- 0.002 0.0141 +/- 0.001 01/27/04 0.0121 +/- 0.001 0.0162 +/- 0.002 0.0120 +/- 0.001 0.0121 +/- 0.001 0.0144 +/- 0.001 0.0112 +/- 0.001 0.0136 +/- 0.001 0.0121 +/- 0.001 0.0146 +/- 0.001 02/03/04 0.0174 i 0.002 0.0158 +/- 0.002 0.0148 +/- 0.002 0.0152 +/- 0.002 0.0178 +/- 0.002 0.0179 +/- 0.002 0.0180 +/- 0.002 0.0183 +/- 0.002 0.0155 +/- 0.002 02/10/04 0.0178 +/- 0.001 0.0210 +/- 0.002 0.0195 +/- 0.002 0.0174 +/- 0.001 0.0203 +/- 0.002 0.0168 +/- 0.001 0.0195 +/- 0.002 0.0195 +/- 0.002 0.0187 +/- 0.002 02/18/04 0.0260 +/- 0.002 0.0222 +/- 0.002 0.0235 +/- 0.002 0.0232 +/- 0.002 0.0235 +/- 0.002 0.0234 +/- 0.002 0.0221 +/- 0.002 0.0230 +/- 0.002 0.0199 +/- 0.002 02/24/04 0.0192 +/- 0.002 0.0227 +/- 0.002 0.0221 +/- 0.002 0.0188 +/- 0.002 0.0179 +/- 0.002 0.0208 +/- 0.002 0.0207 +/- 0.002 0.0198 +/- 0.002 0.0193 +/- 0.002 03/02/04 0.0170 +/- 0.002 0.0169 +/- 0.002 0.0173 +/- 0.002 0.0145 +/- 0.002 0.0151 +/- 0.002 0.0141 +/- 0.001 0.0149 +/- 0.002 0.0193 +/- 0.002 0.0171 +/- 0.002 03/09/04 0.0129 +/- 0.002 0.0139 +/- 0.001 0.0141 +/- 0.002 0.0135 +/- 0.002 0.0124 +/- 0.001 0.0141 +/- 0.001 0.0155 +/- 0.002 0.0153 + 0.001 0.0150 +/- 0.002 03/16/04 0.0188 +/- 0.002 0.0167 +/- 0.002 0.0153 +/- 0.002 0.0137 +/- 0.001 0.0154 +/- 0.002 0.0163 +/- 0.001 0.0162 +/- 0.002 0.0164 +/- 0.002 0.0133 +/- 0.001 03/23/04 0.0138 +/- 0.001 0.0130 +/- 0.001 0.0141 +/- 0.002 0.0139 +/- 0.001 0.0149 +/- 0.002 0.0137 +/- 0.001 0.0113 +/- 0.001 0.0141 +/- 0.001 0.0151 +/- 0.002 03/30/04 0.0058 +/- 0.001 0.0078 +/- 0.001 0.0070 +/- 0.001 0.0092 +/- 0.001 0.0085 +/- 0.001 0.0057 +/- 0.001 0.0071 +/- 0.001 0.0089 +/- 0.001 0.0088 +/- 0.001 04/06/04 0.0087*4 0-001 0.0101 +/- 0.001 0.0124 +/- 0.002 0.0084 +/- 0.001 0.0116 +/- 0.001 0.0117 +/- 0.001 0.0112 + 0.001 0.0082 +/- 0.001 0.0118 0.001 04/13/04 0.0082 +/- 0.001 0.0152 +/- 0.002 0.0164 +/- 0.002 0.0127 +/- 0.001 0.0137 +/- 0.001 0.0147 +/- 0.001 0.0113 +/- 0.001 0.0124 +/- 0.001 0.0145 +/- 0.002 04/20/04 0.0035 +/- 0.001 0.0116 +/- 0.001 0.0097 +/- 0.001 0.0101 +/- 0.001 0.0093 +/- 0.001 0.0081 +/- 0.001 0.0105 +/- 0.001 0.0105 +/- 0.001 0.0105 +/- 0.001 04/27/04 0.0037 +/- 0.001 0.0120 +/- 0.001 0.0138 +/- 0.001 0.0113 +/- 0.001 0.0115 +/- 0.001 0.0145 +/- 0.001 0.0133 +/- 0.001 0.0134 +/-+0.001 0.0139 +/- 0.002 05/04/04 0.0041 +/- 0.001 0.0152 +/- 0.002 0.0151 +/- 0.002 0.0145 +/- 0.001 0.0167 +/- 0.002 0.0151 +/- 0.002 0.0144 +/- 0.002 0.0172 +/- 0.002 0.0150 +/- 0.002 05/11/04 0.0063 +/- 0.001 0.0126 +/- 0.002 0.0157 +/- 0.002 0.0135 +/- 0.001 0.0118 +/- 0.001 0.0156 +/- 0.002 0.0132 +/- 0.001 0.0169 +/- 0.002 0.0186 +/- 0.002 05/18/04 0.0042 + 0.001 0.0094 +/- 0.001 0.0138 +/- 0.002 0.0099 +/- 0.001 0.0087 +/- 0.001 0.0102 +/- 0.001 0.0105 +/- 0.001 0.0102 +/- 0.001 0.0096 +/- 0.001 05/25/04 0.0039 +/- 0.001 0.0099 +/- 0.001 0.0106 +/- 0.001 0.0082 +/- 0.001 0.0085 +/- 0.001 0.0126 +/- 0.001 0.0120 +/- 0.001 0.0107 +/- 0.001 0.0118 +/- 0.001 06/02/04 0.0030 +/- 0.001 0.0100 +/- 0.002 0.0086 +/- 0.001 0.0091 4- 0.001 0.0081 +/- 0.001 0.0107 +/- 0.001 0.0109 +/- 0.002 0.0099 +/- 0.002 0.0093 +/- 0.001 06/08/04 0.0065 +/- 0.001 0.0132 +/- 0.002 0.0148 +/- 0.002 0.0148 +/- 0.001 0.0139 +/- 0.002 0.0169 +/- 0.002 0.0145 +/- 0.002 0.0164 +/- 0.002 0.0176 +/- 0.002 06/15/04 0.0036 +/- 0.001 0.0105 +/- 0.001 0.0098 +/- 0.001 0.0107 +/- 0.001 0.0107 +/- 0.001 0.0124 4- 0.001 0.0118 +/- 0.001 0.0130 +/- 0.002 0.0127 +/- 0.002 06/22/04 0.0056 +/- 0.001 0.0145 +/- 0.002 0.01 50 0.002 0.0160 +/- 0.002 0.0116 +/- 0.001 0.0163 +/- 0.002 0.0177 +/- 0.002 0.0154 +/- 0.002 0.0152 +/- 0.002

Sample location required by ODCM Optional sample location 6 - 12 FL S~

Is~

ILi tWE.

f i.~

iE-.

bff.

L.--

l v7--

k_

=

-::f

I l

I

(

I--

F-I FU--

(

I_

(_ _

I--

( -

. TABLE 6-5 (Continued)

NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE STATIONS - 2004

'\\

.I GROSS BETA ACTIVITY pCi/m3 + 1 Sigma, LOCATION i

We ta.l Rl--;l-S.R2

l' R-3*cl1 R,4* -i l

-5*

-.D^2**

l:

E**

l F** :-l Week Start R71*

I7 G*R.*_1

>R3*jR-~

1ID2" j

Date' -

IOFFSTE OFFSITE -J_ OFFSlTE :OFFSITE I-OFFSTE-J-.OFFSITE. _OFFSITE

-,'-OFFSITE: _

OFFSITE 06/29/04 0.0030 i: 0.001 0.0114 +/- 0.001 0.0104 +/- 0.001 0.0104 +/- 0.001 0.0123 +/- 0.001 0.0091 +/- 0.001 0.0125 +/- 0.001 0.0105 +/- 0.001 0.0131 +/- 0.001 07/07/04 0.0027 +/- 0.001 0.0120'+ 0.002 0.0118 +/- 0.002 0.0093 +/- 0.001 0.0085 +/- 0.001 0.0100 +/- 0.001 0.0089 +/- 0.001 0.0104 +/- 0.002 0.0083 + 0.001 07/13iO4 0.0084 +/- 0.001 0.0140 4 0.002 0.0183 +/- 0.002 0.0155 40.002 0.0200 +/- 0.002

.01064 0.002 0.0205 +/- 0.002 0.0193 +/- 0.002 0.0181. 0.002 07/20/04 0.0145 +/- 0 001 0.0273 + 0.002 0.0260 I 0.002 0.0212'+/- 01002 0.0260 +/- 0.002 0.0257 +/- 0.002 0.0221 +/- 0.002 0.0240 +/- 0.002 0.0229 +/- 0.002 07/27/04 0.0124 + 0.002 0.0210 +/- 0.002 0.0188 +/- 0.002 0.0193 + 0.002 0.0205 +/- 0.002 0.0200 i 0.002 0.0207 +/- 0.002 0.0231 +/- 0.002 0.0172 +/- 0.002 08/03/04 0.0150+0.001' 0.0183 +/- 0.002 0.0140 +/-0.001 0.015340.002 0.0126 0.001' 0.0151 0.002 0.017010.002 '0.0151 +/- 0.001 0.01864 0.002 08/10/04 -

0.0365 4 0.002 0.0i60 4 0.002 0.0352 +/-+'0.002 0.0362 4 0.002 0.0324 +/- 0.002 0.0354 +/- 0.002 0.0408 +/-:t 0.002 0.0404 +/- 0.002 0:0310 +/- 0.002 08/i7/64 "

0.02iS 0.002 0.0230+/- 0.002 0.0212+/- 0.002 0.0209-0.002 0.0199+/-0.002 0.00.0020.002 0.019940.002' -0.0216+/- 0.002 '0.0222 +/- 0.002 08/24/04 0.0204 +/- 0.002 0.0209 +/- 0.002 0.0182 +/- 0:002 0.0184 +/- 0.002 0.0173 +/- 0.002 0.0222 + 0.002 0.0i81+/-_:0.002 0.0161 + 0.001 0.0160 b 0.002 08/31/04 '

0.0183 +/- 0.002 0.0211 0.002 0.0201 + 0.002 0.0187 +/- 0.002 0.0205 +/-;0.002 0 0225 0.002 0.014 -0002 0.0180 +/- 0.001 0.0173 +/- 0.002 09/08/04 '

0.0150 + 0.002 0.0125 +/- 0.002 0.01il + 0.001 010131 +/- 0.002 0.0105 +/-0.001 0.0114 +/- 0.001 0.01071 0.001 0.0144 +/- 0.002 0.0154 4 0.002 09/14/04 0.0206 + 0.002 0.0215+/- o.do2 0.0205 +/- 0.002 0.0181 +/- 0.002 0.0181 +/- 0.002 0.0202 +/- 0.002 0.0220 +/- 0.002 0.0179 + 0.002 0.0197 + 0.002 09/21/04 0.0303 + 0.002 0.0300 +/- 0.002 0.0278 +/- 0.002 0.0291 +/- 0.002 0.0264 +/- 0.002 0.0297 +/- 0.002 0.0253 +/- 0.002 0.0268 +/- 0.002 0.0300 + 0.002 09i28/04 0:0181 +/- 0.002 0.0170 + 0.002 0.091 + 0.002 0.0173 +/- 0.002 0.0162 +/- 0.001 0.0166 +/- 0.002 0.0169 +/- 0.002 0.0162 + 0.002 0.0165 + 0.002 10/05/04 0.0218 +/-.0,002 0.0220 +/- 0.002 0.0199 + 0.002 0.0231 +/- 0.002 0.0184 +/- 0.002 0.0197 +/- 0.002 0.0236 +/- 0.002 0.0212 +/- 0.002 0.0228 + 0.002 10/12/04 0.0137 +/- 0.001 0.0159+/- 0.002 0.0139 0.001 0.0169 0.002 0.0111 I.00' 0.0128 +/- 0.001 0.0132 +/- 0.001 0.0134 +/- 0.001 0.0179 +/- 0.002 10/19/04 0.0139 +/- 0.001 0.0162 +/- 0.002 0.0108 : 0.001 0.0124 0.001 0.0096 +/- 0.001.

0.0142 +/- 0.002 0.0129 + 0.001 0.0127 + 0.001 0.0119 +/- 0.001 10/26/04 0.0157 +/- 0.002 0.0149 +/- 0.002 0.0190 +/- 0.002 0.0177 +/- 0.002 0.0132 +/- 0.001.0.0168 +/- 0.002 0.0155 +/- 0.002 0.0153 +/- 0.001 0.0146 +/- 0.002 11/02/04 0.0173 +/- 0.002 0.0167 +/- 0.002 0.0134 +/- 0.001 0.0143 +/- 0.001 0.0211 +/- 0.002 0.0172 +/- 0.002 0.0134 +/- 0.001 0.0177 +/- 0.002 0.0175 1 0.002

'11/09/04 0.0191 + 0.002' 0.0194 +/- 0.002 0.0198 +/- 0.002 0.0188 +/- 0.002 0.0173 +/- 0.002 0.0209 +/- 0.002 0.0259 +/- 0.002 0.0208 +/- 0.002 0.0176 +/- 0.002 11/16/04 0.0220 +/- 0.002 0.0238 +/- 0.002 0.0248 +/- 0.002 0.0256 0.002 0.0253 +/- 0.002 0.0265 +/- 0.002 0.0225 +/- 0.002 0.0218 +/- 0.002 0.0269 +/- 0.002 11/23/04 0.0151 + 0.002 0.0179 +/- 0.002 0.0169 +/- 0.002 0.0156 +/- 0.002 0.0120 +/- 0.001 0.0163 +/- 0.002 0.0127 +/- 0.001 0.0148 +/- 0.002 0.0166 +/- 0.002 11/30/04 0.0200 4:0.002 0.0185 +/- 0.002 0.0200 +/- 0.002 0.0191 +/- 0.002 0.0169 +/- 0.002 0.0184 +/- 0.002 0.0197 +/- 0.002 0.0166 +/- 0.002 0.0190 +/- 0.002 12/07/04 0.0103 +/- 0.001 0.0174 + 0.002 0.0113 +/- 0.001 0.0100 +/- 0.001 0.0099 +/- 0.001 0.0093 +/- 0.001 0.0105 +/- 0.002 0.0111 +/- 0.001 0.01 16 +/- 0.001 12/14/04 0.0234 +/- 0.002.0.0232 +/- 0.002 0.0203 +/- 0.002 0.0189 +/- 0.002 0.0206 +/- 0.002 0.0183 0:002 0.0239 +/- 0.002 0.0206 +/- 0.002 0.0238 +/- 0.002 12/21/04 0.0170 + 0.002' 0.0182 +/- 0.002 0.0167+/-4 0.002 0.0189 +/- 0.002 0.0i86+/-0.002 0.0188 1 0.002 0.0192 +/- 0.002 0.0184 + 0.001 0.0170 +/- 0.002 12/28/04 0.0223 +/- 0.002 0.0252 + 0.002 0.0247 +/- 0.002 0.0266 +/- 0.002.0.0254 +/- 0.002 0.0259 + 0.002 0.0293 +/- 0.002 0.0278 +/- 0.002 0.0275 +/- 0.002 S Sample location required by ODCM

-* Optional sample location 6-13

TABLE 6-6 NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE STATIONS - 2004 GROSS BETA ACTIVITY pCilm3 i 1 Siginia LOCATION WeekStart H**

K l

I

'Date

-. l ONSITE ONSITE ONSITE ONS1NSI-ON-ST ONSITE 12/29/04 0.0187 +/- 0.002 0.0204 +/- 0.002 0.0192 +/- 0.002 0.0210 I 0.002 0.0205 +/- 0.002 0.0174 +/- 0.002 01/05/04 0.0220 +/- 0.002 0.0203 +/- 0.002 0.0161 +/- 0.001 0.0154 +/- 0.002 0.0192 +/- 0.002 0.0171 +/- 0.002 01/12/04 0.0162 + 0.002 0.0127 +/- 0.001 0.0130 +/- 0.001 0.0143 +/- 0.001 0.0142 +/- 0.001 0.0126 +/- 0.001.

01/19/04 0.0148 +/- 0.002 0.0099 +/- 0.001 0.0136 +/- 0.001 0.0128 +/- 0.001 0.0146 +/- 0.001 0.0167 +/- 0.002 01/26/04 0.0162 +/- 0.002 0.0122 +/- 0.001 0.0151

0.001 0.0175 0.002 0.0133 +/- 0.001 0.0152 +/- 0.001 02/02/04 0.0160 +/- 0.002 0.0157 +/- 0.002 0.0157 +/- 0.001 0.0169

0.002 0.0131 +/- 0.001 0.0137 +/- 0.002 02/09/04 0.0262 +/- 0.002 0.0202 +/- 0.002 0.0223 +/- 0.002 0.0206

0.002 0.0 194

0.001 0.0241 +/- 0.002 02/17/04 0.0227

0.002 0.0241

0.002 0.0247

0.002 0.0246

0.002 0.0228

0.002 0.0239

0.002 02/23/04 0.0258 +/- 0.002 0.0245 +/- 0.002 0.0258 +/- 0.002 0.0231 i 0.002 0.0243 +/- 0.002 0.0238 +/- 0.002 03/01/04 0.0186 +/- 0.002 0.0166

0.002 0.0154

0.002 0.0165

0.002 0.0154

0.002 0.0177 +/- 0.002 03/08/04 0.0151 +/- 0.002 0.0142 +/- 0.001 0.0157 +/- 0.001 0.0156

0.002 0.0171 +/- 0.002 0.0143

0.002 03/15/04 0.0112

0.001 0.0135

0.001 0.0149

0.001 0.0151 +/- 0.002 0.0140 +/- 0.001 0.0126

0.001 03/22/04 0.0159

0.002 0.0156 +/- 0.002 0.0166 +/- 0.002 0.0169

0.002 0.0183 +/- 0.002 0.0157

0.002 03/29/04 0.0076

0.001 0.0085

0.001 0.0099

0.001 0.0080

0.001 0.0058

0.001 0.0070 +/- 0.001 04/05/04

. 0.0136

0.002 0.0118

0.002 0.0122 + 0.002 0.0133

0.002 0.0106

0.001 0.0119

0.001 04/12/04 0.0133 0.002 0.0106* 0.001 0.0135 +/- 0.001 0.0107

0.001 0.0129 0.001 0.0134 0.001 04/19/04 0.0109 0.001 0.0088 0.001 0.0118

0.001 0.0112

0.001 0.0095 0.001 0.0090

0.001 04/26/04 0.0130

0.002 0.0149

0.002 0.0124 +/- 0.001 0.0125

0.001 0.0123

0.001 0.0123 +/- 0.001 05/03/04 0.0137 0.002 0.0123 0.002 0.0137 0.001 0.0161

0.002 0.0141

0.002 0.0119

0.001 05/10/04 0.0178 0.002 0.0131 0.002 0.0155 0.002 0.0163

0.002 0.0178

0.002 0.0146

0.002 05/17/04 0.0126

0.002 0.0096

0.001 0.0102

0.001 0.0094 +/- 0.001 0.0090

0.001 0.0123

0.001 05/24/04 0.0094

0.001 0.0103

0.001 0.0075

0.001 0.0106

0.001 0.0083

0.001 0.0095

0.001 06/01/04 0.0069

0.002 0.0054

0.001 0.0085

0.001 0.0073

0.001 0.0084 +/- 0.001 0.0049

0.001 06/07/04 0.0177 +/- 0.002 0.0143

0.002 0.0145 +/- 0.001 0.0170

0.002 0.0182

0.002 0.0163

0.002 06/14/04 0.0103

0.001 0.0104

0.001 0.0105

0.001 0.0128

0.002 0.0096

0.001 0.0100

0.001 06/21/04 0.0088* 0.001 0.0135 0.001 0.0104

0.001 0.0113

0.001 0.0112

0.001 0.0140

0.002 Optional sample location 6-14

LL

"

F==-

H---

P--

r---

Pf=

F

I --

r -

(..-.-

n T

.r(-,

1 1

(

I-1 TABLE 6-6 (Continued)

NMPNS/.JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE STATIONS - 2004 GROSS BETA'ACTIVITY pCi/m 3 + 1 Sigma

_.LOCATION

. *~Week Start.-j - E--I*t'--

7r

- G**~ 1 ~

ji

-H*

J*-:

Date ONSTE J

ONSIEJ.

ONSTEr.

ONSITE ' j-..ONSITE; ON STE-06/28/04 0.0117+/-0.001 0.0104 +/- 0.001 0.0105 0.001 0.0109 +/- 0.001 0.0128 +/- 0.001 0.0107+/-0.001

'07/06/04 0.0096 +/- 0.001 0.0064 +/- 0.001 0.0111 +/- 0.002' 0.0095 +/- 0.001 0.0091 +/- 0.001 0.0096 +/- 0.001 07/12/04

,0.0103

+/- 0.001 0.0097 4 0.001 0.0091 & 0.001 0.0092 : 0.001 0.0074 +/- 0.001 0.0095 +/- 0.001.

07/19/04 0.0184 +/- 0.002 0.014740.001 0.0227 +/- 0.002 0.0191 + 0.002 0.0260 +/- 0.002 0.0200 +/- 0.002 07/26/04 0.0159 + 0.002 0.0181 4 0.002, 0.0196 + 0.002 0.0189 f 0.002 0.0168 + 0.001 0.0174 + 0.002 08/02/04 0.01710.6002 0.0 1 16oo t

0.001, 0.0160 0.002 0.0156 + 0.002 0.0153 +/- 0.002 0.0146 +/- 0.002

'08/9/04 0.0239 + 0.002' 0.0240

0.002 0.0269 I 0.002 0.0266 +/- 0.002

'0.0248 + 0.002 0.0265 +/- 0.002 08/16/04 0.0212 +/- 0.002 0.0172Y' 0;002' 0.0229

0.002 0.0 0.00 0.002

0.0200 I 0.002 0.0204 + 0.002 08/23/04 0.021340 6.00 0.010ii1 60.002 0.0183 0.002 0.0201 +/- 0.002 0.0172 + 0.002 0.0184 + 0.002 08/30/04 0.0156 + 0.001; 0.016'5+/-0.001:

' 0.0'153 0.001 0.0170-E0.001 0.0170 +/- 0.002 0.0153 + 0.001 09/07/04 0.0137 0.002 0.013i7 6.001 0.0159 + 0.002 :

0.0157 + 0.002 0.0146 +/- 0.002 0.0133 +/- 0.002' 09/13/04 0.0169 + 0.002 0.0155 0.001 0.0150*0.001 0.0157 +/- 0.002 0.0175 +/- 0.002 0.0173 + 0.002 09/20/04 0.0281 + 0.002 0.0283 +/- 0.002 0.0290 + 0.002, 0.0271 +/- 0.002 0.0289 +/- 0.002 0.0265 +/- 0.002 09/27/04 0.0183 + 0.002 0.0189 +/- 0.002 0.0142 4 0.001 0.0190 +/- 0.002 0.0170 +/- 0.002 0.0193 4+/- 0.002 10/04/04

. 0.0204 0.002 0.0185 + 0.002 0.0224 +/- 0.002 0.0249 +/- 0.002 0.0199 +/- 0.002 0.0201 +/- 0.002 10/11/04 0.0145 0.002" 0.0166 ++/-0.002' 0.0143 0.001.

0.0157 + 0.002 0.0144 +/- 0.002 0.0139 +/- 0.001 10/18/04 0.0120 0.001 0.0092: b0.001

-0.0090 + 0.001 0.0117+/- 0.001 0.0120 +/- 0.001 0.0108 0.001 10/25/04 0.0176 + 0.002 0.0145+/- 0.002 0.0182 + 0.002.

0.0164 +/- 0.002 0.01600.002 0.0158 0.002 11/02/04

0.0164 +/- 0.002 0.0171 0.002 0.0177 +/- 0,002 0.0203 +/- 0.002 0.0176 0.002 0.0139 +/- 0.001 11/08/04 0.0121 +/- 0.001 0.0160 0.002 0.0130 +/- 0.001 0.0179 + 0.002.

0.0179 0.002 0.0166 +/- 0.002 11/15/04 0.0292 +.0.002 0.0269 4 0.002

'0.0258*+/- 0.002 0.0256 I 0.002 0.0273 +/- 0.002 0.0234 +/- 0.002 11/22/04 0.0188 +/- 0.002 0.0165 +/- 0.002 0.0152+/-i 0.002 0.0167 +/- 0.002 0.0178 +/- 0.002 0.0169 £'0.002 11/29/04 0.0264 +/- 0.003 0.0195 +/-:0.002

0.0195 +/- 0.002 0.0219 +/- 0.002 0.0192 +/- 0.002 0.0184 +/- 0.002 12/06/04 0.0131 ++/-0.002 0.0108 + 0.001 0.0114 + 0.001 0.0137 + 0.002 0.0131 +/- 0.001 0.0082 +/- 0.001 12/13/04 0.0199 +/- 0.002 0.0209 +/- 0.002 0.0219 + 0.002 0.0248 + 0.002 0.0199 +/- 0.002 0.0213 +/- 0.002 12/20/04 0.0209 + 0.002

.0.0222 +/- 0.002

'0.0213 4- 0.002 0.0186 + 0.002 0.0177 + 0.002 0.0169 +/- 0.002 12/27/04 0.0285 +/- 0.002 0.0283 +/- 0.002

,. 0.0266 +/- 0.002 0.0292 + 0.002.

0.0281 + 0.002 0.0251 +/- 0.002

- Optional sample location 6 - 15

TABLE 6-7

-NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFS1TE STATIONS - 2004 1-131 ACTIVITY pCUM3 4 1 Sigma LOCATION WeekStart Rl*-

-; RG3

l-R4*

l R*

l l..,E** -

G**

Date OFFSITE-1 lOFFSIT OF TE-OFFSITE-

. jOFFSITE I.- OFFSITE I OFFSITE:.. I -OFFSITE I OFFSITE 12/30/04

< 0.0186

< 0.0177

< 0.0220

< 0.0244

< 0.0205

< 0.0247

< 0.0199

< 0.0158

< 0.0183-01/06/04

< 0.0143

< 0.0159

< 0.0118

< 0.0203

< 0.0173

< 0.0174

< 0.0146

< 0.0185

< 0.0198 01/13/04

< 0.0216

< 0.0212

< 0.0136

< 0.0178

< 0.0208

< 0.0136

< 0.0164

< 0.0034

< 0.0149 01/20/04

< 0.0162

< 0.0185

< 0.0165

< 0.0195

< 0.0176

< 0.0189

< 0.0166

< 0.0225

< 0.0098 01/27/04

< 0.0214

< 0.0178

< 0.0204

< 0.0179.

< 0.0270

< 0.0126

< 0.0165

< 0.0180

< 0.0218 02/03/04'

< 0.0195

< 0.0132

< 0.0108

< 0.0127

< 0.0224

< 0.0211

< 0.0168

< 0.0179

< 0.0169 02/10/04

< 0.0281

< 0.0167

< 0.0166

< 0.0191

< 0.0176

< 0.0198

< 0.0086

< 0.0168

< 0.0206 02/18/04

< 0.0283

< 0.0245

< 0.0218

< 0.0206

< 0.0221

< 0.0290

< 0.0135

< 0.0105

< 0.0210 02/24/04

< 0.0184

< 0.0213

< 0.0207

< 0.0149

< 0.0163

< 0.0125

< 0.0187

< 0.0209

< 0.0208 03/02/04

< 0.0225

< 0.0151

< 0.0146

< 0.0228

< 0.0212

< 0.0137

< 0.0131

< 0.0211

< 0.0218 03/09/04

< 0.0196

< 0.0156

< 0.0260

,< 0.0203

< 0.0220

< 0.0179

< 0.0135

< 0.0147 03/16/04

< 0.0192

< 0.0153

< 0.0037

< 0.0158

< 0.0169

< 0.0143

< 0.0255

< 0.0133

< 0.0221 03/23/04

< 0.0195

< 0.0189

< 0.0226

< 0.0136

< 0.0267

< 0.0161

< 0.0238

< 0.0155

< 0.0200 03/30/04

< 0.0193

< 0.0124

< 0.0143

< 0.0203

< 0.0177

< 0.0148.

< 0.0197

< 0.0160

< 0.0199 04/06/04

< 0.0217

< 0.0176

< 0.0197

< 0.0216

< 0.0,35

< 0.0153

< 0.0272

< 0.0169

< 0.0283 04/13/04

< 0.0226

< 0.0121

< 0.0116

< 0.0202

< 0.0239

< 0.0214

< 0.0155

< 0.0170

< 0.0211 04/20/04

< 0.0170

< 0.0243

< 0.0201

< 0.0135,

< 0.0188

<0.0117

< 0.0197

< 0.0233

< 0.0190 04/27/04

< 0.0259

< 0.0204

<0.0131

< 0.0132

< 0.0197

< 0.0186

< 0.0196

< 0.0207

< 0.0177 05/04/04

< 0.0233

< 0.0192

< 0.0112

< 0.0195

<0.0113

< 0.0221

< 0.0272

< 0.0183

< 0.0160 05/11/04

< 0.0259

< 0.0156

< 0.0125

< 0.0167

< 0.0166

< 0.0176

< 0.0196

<0.0181

<0.0187 05/18/04

< 0.0202

< 0.0229

< 0.0168

< 0.0129

< 0.0211

< 0.0177

< 0.0208

< 0.0257

< 0.0208 05/25/04

< 0.0147.

< 0.0168

< 0.01 15

< 0.0188

< 0.0131

< 0.0161

< 0.0171

< 0.0084

< 0.0173 06/02/04

< 0.0170

< 0.0284

< 0.0189

< 0.0231

< 0.0280

< 0.0208

< 0.0227

< 0.0174

< 0.0233 06/08/04

< 0.0206

< 0.0200

< 0.0143

< 0.0192

< 0.0190

< 0.0205

< 0.0177

< 0.0252 06/15/04

< 0.0180

< 0.0162

< 0.0231

< 0.0169

< 0.0174

< 0.0142

< 0.0199

< 0.0207

< 0.0152 06/22/04

<0.0161

<0.0144

<0.0158

< 0.0184

< 0.0132

< 0.0198

< 0.0168

< 0.0187

< 0.0181 4*

Sample location required by ODCM Optional sample location 6-16 6-L-Lz F--

---_0 iii--

~

W-I l -

1,

F---

ha rho r-t

[--

t---

r' F---

(----

r----

(

TABLE 6-7 (Continued)

NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES'- OFFSITE STATIONS - 2004 1-131 ACTIVITY pC IS 3

, 1 sigma I "

l e F-LOCATION ;

WeekStart R-1*

-2*-4

]

R3*-

l:-R-4 l

R-5 l

D-2**

E**.

Date OFFSITE, JOFFSITE I OFFSITEI OFFSITE j OFFSITE -J OFFSITE OFFSITE 06/29/04

< 0.0186

< 0.0149

< 0.0220

< 0.0172

< 0.0139

< 0.0133

< 0.0229

< 0.0181

<0.0185 07/07/04

< 0.0204

.< 0.0197

< 0.0208

< 0.0179

< 0.0239

<0.0202

< 0.0177

< 0.0200

< 0.0189 07/13/04

<0.0238

< 0.0191

< 0.0159

<0.0196

<'0.0235

<0.0210

< 0.0147

<0.0179

< 0.0211 07/20/04

< 0.0146

< 0.0140

< 0.0153

< 0.0239 0.0126

< 0.0167

< 0.0143'

< 0.0159

< 0.019'8 07/27/04

< 0.0266

'< 0.0037

< 0.0154

< 0.0094

< 0.0258

< 0.0234

< 0.0198

< 0.0145

< 0.0151 08/03/04

< 0.0169

< 0.0242

<.0.0269

< 0.0252'

< 0.01'67

< 0.0209

<'0.0149

< 0.0163

<'0.0218 08/10/04

<0.0169

< 0.0167

<0.0143

-< 0.0187

- < 0.0176

<0.0169

<0.0111:

< 0.0159

<0.0169 08/17/04

<0.0182

'<0;'

'<0.01 84 8

'0.0121

<0.0196

<0.0245

<0.0158

<0.0145

<0.0240 08/24/

< 0.0278

<0.0198

< 0.0207

<0.0186'

< 0.0156

<0.0235

<0.0221

<0.0152

'<<0.0149 08/31/04

< 0.0139

<0.0125

< 0.0191

<0.0198'

< 0.0155

<0.0095

<0.0154'

< 0.0140

< 0.0129 09/08/04'

< 0.0253

'< 0.0264'

< 0.0177

< 0.0133'

< 0.0233

< 0.0187

< 0.0305

< 0.0182

< 0.0168 09/14/04

< 0.0159

< 0.0332

< 0.0268

< 0.0226

< 0.01'20

<0.0314

-< 0.0198 7

< 0.0191

< 0.0327 09/21/04

< 0.0133

< 0.0190

< 0.01 16

<0.0161

< 0.0138

<0.0146

< 0.0179

< 0.0150

< 0.0181 09/28/04

< 0.0150

< 0.0133

< 0.0204

<0.0149

< 0.01'84

<0.0133

< 0.0226

< 0.0148

< 0.0146 10/05/04

< 0.0225

< 0.0214

< 0.0135

< 0.0137

<0;0161

< 0.0227

< 0.0207

< 0.0151

< 0 0155 10/12/04

< 0.0176

< 0.0151'

. < 0.0149

<0.0185'

< 0.0202

< 0.0229

< 0.0178

< 0.0125

< 0.0113

10/19/04

< 0.0176

< 0.0254

< 0.0256.

< 0.0226

< 0.0253.

<0.0204

< 0.0206

< 0.0269

< 0.0191 10/26/04

< 0.0225

< 0.0171

< 0.0238

< 0.0289

< 0.0201

< 0;0162

< 0.0253

< 0.0180

< 0.0228 11/02/04

< 0.0158

< 0.0200'

< 0.0122

< 0.0222

< 0.0218

< 0.0036

< 0.0155

< 0.0119

< 0.0220

-11/09/04

< 0.0135'

< 0.0136

-< 0.0149

< 0.0209

<0.0197

< 0.0191-

< 0.0168-

-- < 0.0109

< 0.0181 11/16/04

< 0.0281

< 0.0206

<0.0186

<0.0177 0.0186

< 0.0246

< 0.0189

< 0.0207

< 0.0192 11/23/04

< 0.0232

< 0.0259

< 0.0200

< 0.0250

< 0.0158

< 0.0204

< 0.0238

< 0.0192

< 0.0253 11/30/04

< 0.0285

< 0.0257

< 0.0181

< 0.0200

' < 0.0227,

' < 0.0244

< 0.0208

< 0.0161

< 0.0180 12/07/04

< 0.0265

< 0.0214

< 0.0252

< 0.0189

< 0.0152

< 0.0256

< 0.0236

< 0.0166

< 0.0215 12/14/04

< 0.0160

< 0.0244

< 0.0212

< 0.0175

< 0.0186

< 0.0179

< 0.0256

< 0.0166

< 0.0143 12/21/04

< 0.0367

<0.01 77

< 0.0440

<0.0157

< 0.0156 '.-'<0:0137

< 0.0270

< 0.0191

< 0.0144 12/28/04

< 0.0182

<0.0129

< 0.0223

<O.Q240

<0.0260

< 0:0290

<0.0196

<0.0171

< 0.0136 l

Sample location required

- Optional sample location byODCM

.6-:17-

TABLE 6-8 NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE STATIONS - 2004 1-131 ACTIVITY pCi/iu3 4 1 Sigmia LOCATION

OtDate-.:

ONSfE'

__TE_--

ONSI l

'-.-. SIONSITE

-i

ONSITE, 12/29/03

< 0.0163

< 0.0215

< 0.0175

< 0.0102

< 0.0169

< 0.0208 01/05/04

< 0.0274

< 0.0293

< 0.0190

< 0.0145

< 0.0184

< 0.0230 01/12/04

< 0.0325

< 0.0180

< 0.0146

< 0.0186

< 0.0207

< 0.0217 01/19/04

< 0.0199

< 0.0178

< 0.0120

< 0.0152

< 0.0173

< 0.0200 01/26/04

< 0.0347

< 0.0160

< 0.0189

< 0.0127

< 0.0186

< 0.0243 02/02/04

< 0.0057

< 0.0217

< 0.0151

< 0.0128

< 0.0221

< 0.0236 02/09/04

< 0.0177

< 0.0103

< 0.0136

< 0.0158

< 0.0204 02/17/04

< 0.0289

< 0.0218

< 0.0158

< 0.0191

< 0.0203

< 0.0223 02/23/04

'< 0.0151

< 0.0187

< 0.0177

< 0.0247

< 0.0242

< 0.0153 03/01/04

< 0.0198

< 0.0172

< 0.0165

< 0.0190

< 0.0239

< 0.0214 03/08/04

< 0.0269

< 0.0134

< 0.0072

< 0.0238

< 0.0195

< 0.0213 03/15/04

< 0.0274

< 0.0209

< 0.0125

< 0.0199.

< 0.0208

< 0.0281 03/22/04

< 0.0206

< 0.0159

< 0.0161

< 0.0206

< 0.0142

< 0.0226 03/29/04

< 0.0339

< 0.0289

< 0.0178

< 0.0250

< 0.0152

< 0.0166 04/05/04

< 0.0195

< 0.0102

< 0.0251

< 0.0202

< 0.0201

< 0.0141 04112104

< 0.0171

< 0.0193

< 0.0134

< 0.0235

<0.0128

< 0.0233 04/19/04

< 0.0243

< 0.0214

< 0.0290

< 0.01,88

< 0.0159

< 0.0284 04/26/04

< 0.0196'

< 0.0258

< 0.0189

< 0.0205

< 0.0254

< 0.0212 05/03/04

< 0.0236

< 0.0169

< 0.0146

< 0.0225

< 0.0198

< 0.0173 05/10/04

< 0.0205

< 0.0184

< 0.0204,

< 0.0144

< 0.0150

< 0.0217 05/17/04

< 0.0332

< 0.0184

< 0.0135

< 0.0174

< 0.0243

< 0.0244 05/24/04

< 0.0190

< 0.0159

< 0.0125

< 0.0172

< 0.0270

< 0.0163 06/01/04

< 0.0231

< 0.0252

< 0.0151

< 0.0233

< 0.0234

< 0.0259 06/07/04

< 0.0271

< 0.0199

< 0.0142

< 0.0206

< 0.0247

< 0.0248 06/14/04

< 0.0200

< 0.0209

< 0.0131

< 0.0166

< 0.0196

< 0.0223 06/21/04

< 0.0205

< 0.0223

<0.0219

<0.0146

< 0.0164

< 0.0130 POptional sample location 6-18

i i

ii i

l I,-

-~'~

~

r

F- --

I---- -

I F-

[-,-"

F-.- (

F F

[

I F---

fl-*-

w I

F-.--

F F

1 I 1-F--- -

F 1-F TABLE 6-8 (Continued)

NMPNS/.JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE STATIONS - 2004 1-131 ACTIVITY pCi/m3 i i Sigma L O C A T IO N Week.Start DI**

j

.Date

- ONS1E

.1 O;-.T, ONSUE ONSITE, -

ONSITE ONSrTE 06/28/04

< 0.0151

< 0.0032

, < 0.0222

<0.0140

< 0.0212

< 0.0150 07/06/04

<0.0192

< 0.0267

< 0.0285

< 0.0211

< 0.0153

< 0.0236 07/12/04

< 0.0143

<0.0142

< 0.0259

< 0.'0176

< 0.0264

<0.0186.

07/19/04

<'0.0260--

<0.0122

<0.0209...

< 0.0165

< 0.0187

<.0.0097 07/26/04

< 0.0319

< 0.0172

,<0.0181

< 0.0207

< 0.0178

< 0.0254 08/02/04

< 0.0235

<0.0132

< 0.0144

< 0.0238-

< 0.0132

< 0.0183 08/09/04

< 0.0172

<0.0183

<0.0170

< 0.0219

< 0.0179

< 0.0i35 08/16/04

< 0.0232

< 0.0136

< 0.0196'

< 0.0097

<0.0181

< 00258 08/23/04

< 0.0130

< 0.01 15

< 0.0226

< 0.0177

< 0.0126

<0.0163 08/30/04

< 0.0239

< 0.'0174

< 0.01'19

<0.0172

< 0.0239

<0.0186 09/07/04

< 0.0268

< 0.0135

< 0.0200

<0.0183

<0.0212

<0.0254 09/13/04

<0.0188

< 0.0182

< 0.0150

< 0.0186

< 0.0149

< 0.0203 09/20/04

<0.0178

< 0.0134

<0.0164.

< 0.0170

< 0.0162

< 0.0200 09/27/04

< 0.0157

'< 0.0181

< 0.0211

< 0.0167

< 0.0149

< 0.0153 10/04/04

< 0.0165

< 0.0184

< 0.0227

<0.0111

< 0.0238

< 0.0232 10/11/04

< 0.0289

<0.0137

< 0.0152

< 0.0218

< 0.0162

< 0.0186 10/18/04

<0.0180

<0.0153

< 0.0232

< 0.0217

< 0.0149

< 0.0172 10/25/04

< 0.0181'

< 0.0250

< 0.0142'

< 0.0266

< 0.0200

< 0.0218 11/02/04

< 0.0246

< 0.0201

< 0.0155

<0.0197

< 0.0099

< 0.0195 11/08/04'

< 0.0289-

< 0.0125

< 0.0161 -

-<0.0126

<0.0243

<0.0206 11115104

< 0.0150

< 0.0155

< 0.01 '

59

< 0.0184

< 0.0142

< 0.0169 11/22/04

< 0.0158

< 0.0227

< 0.0234

< 0.0131

< 0.0193

< 0.0268 11/29/04

< 0.0671

< 0.0220

-L

< 0.0170

< 0.0199

< 0.0135

< 0.0216 12/06/04

< 0.0198

< 0.0182

< 0.0247

< 0.0143

< 0.0201

< 0.0224 12/13/04

< 0.0213

< 0.0203

< 0.0212

< 0.0247

< 0.0264

< 0.0189 12/20/04

< 0.0176

<0.0160

<0.0331

< 0.0225

,< 0.0192

< 0.0204 12/27/04

< 0.0290

< 0.0282

.< 0.0142

< 0.0185

< 0.0269

< 0.0240 Optional sample location

6 19.

TABLE 6-9 CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10-3 pCi/m3 + 1 Sigma R1 OFFSITE COMPOSITE*

.. :.NUCLIDES

. JANUARY.-

-FEBRUARY-MARCH APRIL -.

-MAY JUNE Be-7 76.4 +/- 17.9 110+/- 14.5 105+/- 16.5 89.0 +/- 14.6 29.7 +/- 9.68

<33.1 Zn-65

<12.2

<6.97

<9.56

<8.54

<4.89

<12.8 Cs-134

<2.66

<3.36

<3.38

<2.53

<3.19

<3.28 Cs-137

<2.57

<2.43

<2.50

<2.21

<3.09

<4.03 Zr-95

<9.07

<5.17

<6.89

<4.59

<10.4 Nb-95

<4.26

<4.60

<4.57

<5.34

<3.35

<7.16 Co-58

<1.33

<2.06

<3.43

<3.76

<2.25

<1.53 Mn-54

<4.16

<2.72

<2.84

<2.38

<3.75

<5.08 Co-60

<6.35

<3.25

<2.25

<3.61

<2.95

<2.18 K-40

<17.9

<34.7 100+/- 19.0

<8.71

<10.5

<63.3 Others t

<LLD

-NUCLIDES -

-r AUGUSTUT5.-.

SEPTEMBER

--OCTOBER

'- NOVEMBER

-DECEMBER Be-7 26.5+/- 11.0 94.4+/- 16.4 102+/- 18.4 56.4+/- 11.9 59.4+/- 16.0 84.0+/- 18.9 Zn-65

<7.13

<5.24

<1;1.7

'<7.73

<10.2

<3.01 Cs-134

<2.96

<3.96

<4.28

<3.03

<4.80

<2.86 Cs-137

<2.36

<2.06

<3.34

<1.74'

<2.79

<5.16 Zr-95

<6.62

<4.85

<7.85

<1.45

<9.17

<7.71 Nb-95

<4.55

<3.28

<6.51

<4.76

<4.81

<4.21 Co-58

<4.98

<2.38

<3.49

<2.19

<4.77

<3.77 Mn-54

<3.24

<3.05

<3.03

<2.79

<4.09 Co-60

<4.30

<1.11

<3.75

<3.17

<1.47

<4.70 K-40

<39.9

<32.3

<14.6

<29.6

<40.8

<17.6 Others t

<LLD

<LLD Sample location required by ODCM t Plant related radionuclides 6-20 E__=

F___

:__

PE

ii_

E=

i=__Z=

i__

i

I _ __.

r__

w___

6K___

(

r -,

r U,-,

IU

--- I-f-- rI

(

I I

f

(

II 1--

I.- -

I I

I TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10- pCim 3 + I sigma R2 OFFSITE COMPOSITE*

NUCLIDES~

JANUARY

.ERUARY:

- MARCH J

PI A

~

JN Be-7 79.6 + 13.8 96.64+ 14.1 95.1 +/- 13.9 93.0+/-21.4 73.2 +/- 10.4 114 +17.0 Zn-65

<5.18

<8.34

<9.48

<8.65

<7.08

<10.6 Cs-134

<3.46

<3.13

<2.26

<2.64

<1.88

<3.85 Cs-137

<2.39

<2.49

<2.86

<3.76

<2.11

<3.08 Zr-95

<6.13

<6.50

<4.21

<7.87

<4.28

<6.84 Nb-95

<4.22

<2.95

<352

<6.67

<3.69

<4.41 Co-58

<3.07

<3.37

<4.04

<3.94

<3.02

<3.56 Mn-54

<3.41

<3.32

<1.90

<3.11

<1.88

<3.23 Co-60

<3.93

<3.59

<2.59

.<4.05

<2.61

<4.42 K-40

<36.2 98.5 : 19.4 88.4 4-18.3

<61.0

<7.00

<15.8 Others t

<LLD

-NUCLDES --

-TY: :-

'-:~1~

AUGUST" L-SEPTE BER J -- OCTOBER NOVEMBER [

DECEMBER Be-7.

55.9+/- 13.0 83.0+/- 13.3 74.6+/- 18.1 45.6+/- 13.2 57.2+/- 16.9 68.4+/- 13.3 Zn-65

<5.64

<6.21

<11.7

<1.93

<9.26

<7.43 Cs-134

<3.23

<5.18

<0.69

<4.91

<1.81 Cs-137

<2.74

<2.42

<5.25

<0.61

<2.66

<3.27 Zr-95

<6.60

<4.65

<10.0

<6.21

<10.6

<1.41 Nb-95

<3.90

<3.15

<5.57

<2.89

<5.48

<3.57 Co-58

<2.93

<0.64

<4.78

<3.61

<5.79

<3.91 Mn-54

<3.23

<2.31

-<3.57.

<2.09

<4.23

<3.34 Co-60

<1.19

<2.22

<6.29

<2.88

<3.56

<1.06 K40

<12.1

<23.6 148 + 29.7.

<30.5.

114 +/- 26.6

<29.4 Others t

<LLD

Sample location required by ODCM t Plant related radionuclides 6-221

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3 pCi/ni3 i 1 Sigma R3 OFFSITE COMPOSITE*

NUCLIDES->I JANUARY-.lI FEBRUARY

-l MARCH APRI MAY JUNE Be-7 58.0+ 11.6 107+/- 16.7 1101 13.7 130+/- 18.4-98.1 +12.3 46.7+/- 15.8 Zn-65

<6.09

<8.46

<6.73

<9.51

<3.01

<14.5 Cs-134

<3.84.

<3.31

<2.51

<3.48

<1.42

<3.91 Cs-137

<3.99

<2.64

<2.41

<3.33

<1.79

<3.26 Zr-95

<5.88

<6.86

<4.61

<4.62

<3.93

<7.83 Nb-95

<3.18

<5.80

<4.61

<6.00

<3.38

<7.04 Co-58

<3.04

<4.70

<2.99

<4.29

<2.19

<5.58 Mn-54

<3.91

<2.28

<2.71

<3.18

<1.55

<2.84 Co-60

<4.02

<4.45

<2.84

<3.77

<2.67

<1.60 K-40

<33.8

<35.8

<26.1 87.7 +/- 17.2

<21.2

<75.8 Others t

<LLD

- NUCLIDES

[.

JULY"

'-J4 AUGUS T.

-OC-SEPTEMBER

[

OCTOBER-:

-J. NOVE ER. -.DECEBR Be-7 85.8+/- 13.3 71.8+/- 11.9 81.3+/- 14.7 63.7+/- 15.4 42.4+/- 15.1 76.0+/- 17.6 Zn-65

<1.82

<4.60

<11.9

<2.12

<9.39

<8.11 Cs-134

<2.64

<2.47

<3.96

<4.67

<5.04 Cs-137

<2.28

<1.79

<3.76

<3.49

<2.46

<3.66 Zr-95

<6.56

<5.14

<1.69

<7.79

<2.03

<9.88 Nb-95

<4.04

<3.48

<4.20

<5.76

<7.21

<6.10 Co-58

<3.81

<2.62

<2.84

<3.21

<4.44

<3.73 Mn-54

<2.91

<3.26

<4.46

<2.74

<3.32

<4.05 Co-60

<2.96

<2.20

<4.28

<3.29

<1.58

<1.71 K40

<36.2 42.4 + 14.8

<36.1

<51.2

<60.8

<17.4 Others t

<LLD.

<LLD

Sample location required by ODCM t Plant related radionuclides 6 -22 6___

=

:=

K___ ----

P___

PE__

ff_ _

r

F',

[,---

I----

(____

F_

(

( F

(

I (I

(

~

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004**

Results in Units of 10 ' pCi/mr

+/- 1 Sigma R4 OFFSITE cCmpOSITE*

NUCLIDES -

JANUARY-7 l FEBRUARY' :

MARCH APRIL MAY JUNE Be-7 42.3+/- 12.2 79.6+/- 12.6 105+/- 17.1 153+/- 18.1 97.5+/- 13.3 103+/- 18.1 Zn-65

<6.94

<7.32

<9.33

<7.59

<6.32

<8.68 Cs-134

<3.15

<3.27

<3.46

<4.24

<2.29

<4.25 Cs-137

<2.99

<2.29

<2.81

<2.95

<2.23

<3.68 Zr-95

-. 51

<5.33

<5.55

<6.80

<6.32,

<9.31 Nb-95

<4.96

<3.27'

<5.74

<5.76

<2.13

<5.74 Co-58

<2.86

<1.94

<4.24

<3.75

<1'.82

<4.96 Mn-54

. <3.15

<1.97

<3.33

<3.63

<2.55

<4.47

,Co-60

<1.16

<2.31

<4.20

<2.99

<3.86

<3.04 K40

<11.8

<21.6 98.6 t 20.3 73.2+/- 16.4

<26.9 98.9 25.6 Others t

<LLD.

<LLD

<LLD NUCLIDES -

J,.LY t-: '

'-AUGUST;'; j:: SEPTEMBER - -

OCTOBER

-. i NOVEMBER

- -[DECEMBER Be-7 84.0 +/- 14.0 90.2 4:12.4 82.0+/-L 17.0 57.5 +/- 13.1 72.3 +/- 15.6 50.6 +/- 13.5 Zn'-65

<8.93

<6.18

<13.5

<10.5

<10.1

<2.27 Cs-134

<4.28

<3.18

<4.41

<3.98

<4.05

<3.89 Cs-137

<2.78

<2.60

<2.99

<3.20

<3.21

<2.04 Zr-95

<5.61

<3.47

<7.64

<5.96

<8.12'

<4.92 Nb-95 '<5.09

<2.35'

<6.30'

<6.28

<4.77

<3.39 Co-58

<3.43

<2.35

<3.84

<3.93

<4.06

<4.53 Mn-54

<2.61

<1.75

<3.32

<3.35

<3.50

<2.20 Co-60

<3.59

<2.40

<4.00

<3.90

<3.81

<1.30 K40 92.1 +/- 19.3

<20.2

<14.9 87.8 +/- 16.9

<40.4

<45.4 Others t

<LLD

<LLD,

<LLD

<LLD.<LLD

<LLD ampla rlaterion requirea by DUi t Plant related radionuclides I -

6 -23D'.."

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3 pCi/m3 +/- 1 Sigma R5 OFFSITE COMPOSITE*

NUCLIDES

-JANUARY-

FEBRUARY

-MARCH -

-APRIL MAY JUNE' Be-7 69.5+/- 18.1 109+/- 12.6 70.5+/- 14.3 135+/- 18.9 118+/- 11.9 88.0+/- 17.1 Zn-65

<8.91

<3.48

<8.48

<5.96

<4.68

<13.4 Cs-134

<4.40

<2.71

<3.57

<2.73

<1.80

<4.71 Cs-137

<3.23

<2.12

<2.41

<2.92.

<1.61

<4.17 Zr-95

<6.76

<4.48

<6.87

<4.84

<2.29

<6.65 Nb-95

<4.01

<2.69

<4.89

<5.75

<3.62

<6.51 Co-58

<4.38

<2.01

<3.64

<6.12

<2.59

<5.03 Mn-54

<3.74

<3.61

<2.74

<2.96

<1.89

<3.52 Co-60

<5.32

<3.45

<3.72

<1.23

<2.83

<5.41 K-40 89.3 +/- 22.3

<28.3 100 +/- 16.3

<35.4 33.3 +/- 10.5

<57.4 Others t

<LLD

<LLD.

<LLD

<LLD NUCLIDES' I

- JULY AUGUST-SEPTEMBER:- I OCTOBER' 1:'.

NOVEMBER DECE ER Be-7 61.2 12.6 76.1 +/- 13.5 71.5 +/- 16.2 52.8 +/- 13.3

<33.1 63.0 +/- 13.1 Zn-65

<9.71

<8.53

<13.0

<8.32

<15.3

<6.29 Cs-134

<3.92

<3.15

<5.31

<3.10

<6.76

<1.78 Cs-137

<3.07

<2.61

<3.37

<1.78

<4.06

<2.30 Zr-95

<7.39

<4.84

<7.81

<1.49

<7.59

<5.08 Nb-95

<4.55

<3.57

<5.95

<3.75

<5;18

<4.07 Co-58

<0.90

<3.72

<4.45

<2.81

<4.15

<2.95 Mn-54

<3.52

<3.55

<4.67

<2.40

<3.07

<1.98 Co-60

<4.49

<2.87

<4.85

<1.13

<5.99

<1.05 K-40

<12.1 63.9 +/- 16.2 161 26.6

<11.5, 118 4 24.7

<10.6 Others t

-<LLD

<LLD

<LLD Sampic location required by ODCM t Plant related radionuclides 6 -24

.i---

I'

['--

F-'

fr _

r

(

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF.JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3 pCi/r 3

I Sigma D2 OFFSITE COMPOSITE**

NUCLIDES l.

JANUARY -' -FEBRUARY.

'MARCH APRIL JUNE Be-7 72.9+/-,16.0 108k 16.8 92.9k 12.4 165+/- 17.5 108d 12.8 73.9b 16.0 Zn-65

<8.34

<8.51

<5.01

<6.02'

<6.00

<8.67 Cs-134

<5.43

<2.74

<2.27

<2.66

<2.60

<2.24 Cs-137

<4.59

<2.66

<1.91

<1.85

<2.28

<2.31 Zr-95

<2.29

<6.18

<4.18

<7.78

<3.83

<9.26

- Nb,95

<4.28

<5.58

<4.43

<4.63

<3.08 -

<4.20 Co-58

<1.33

<2.98

<2.08

<3.07

<2.78

<2.71 Mn-54

<3.28

<3.04

<2.65

<2.42

<2.24

<3:55 Co-60

<6.36

<3.16

<3.35

<3.37

<2.23

<4.21 K-40

<51.0

<47.6

<27.4

<22.0 69.4 +/- 14.2

<15.1 Others f

<LLD

<LLb

<LLD

UCLDES i

JULY:7

'.-J,AUGUST'V SEPTEMBER-

'--OCTOBER

.NOVEMBER'4

-'DECEMBER.

Be-7.

84.9 +/- 13.6 86.7 + 13.2 58.5 + 15.8 62.5 + 13.3

<46.8 49.0 : 14.3 Zn:65

<8.73

<8.36

<13.3

<2.03

<11.4

<3.00 Cs-134

<3.50

<3.56

<4.46

<3.71

<5.02

<5.80 Cs-137

<2.37

<2.88

,<4.24:

<0.63

<3.53

<4.11 Zr-95

<6.64

<6.66

<7.02,

<1.52

<13.7

,2.24 Nb-95 '

<3.93

- <4.37'

<5.54

<5.43

<8.40

'-6.13 Co-58

<3.41

<3.13

<3.63

<3.69

<6.60

<3.75 Mn-54

<2.52

<2.71

<3.15

<2.83

<1.56

<4.08 Co-60

<3.90

<2.18

<4.90'

<4.20

<6.56

<5.91 K-40

<12.1 149+/- 18.7

<60.4

<38.7.

<24.7

<17.5 Others t

<LLD

'<LLD

.LLD

<LLD

<LLD Optional sample location t Plant related radionuclides 6-25'

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results iu Units of 10- pCi/m3 +/- 1 Signia E OFFSITE COMPOSITE**

NUClDES:

JANUARY

':FEBRUARY.

MARCH APRIL.

MAY JUNE Be-7 59.2 + 14.9 88.7 +/- 12.8 104+/- 16.4 128+/- 16.6 104+/- 12.2 91.7+/- 16.8 Zn-65

<9.12

<8.25

<7.96

<4.07

<6.97

<10.1 Cs-134

<3.40

<2.16

<3.65

<3.04

<2.87

<3.84 Cs-137

<1.95

<2.64

<2.83

<2.15

<1.95

<2.82 Zr-95

<5.97

<3.15

<7.38

<4.46

<4.59

<9.05 Nb-95

<5.84

<4.37

<4.98

<5.20

<3.52

<4.41 Co-58

<2.46

<2.39

<3.23

<3.66

<1.93

<4.61 Mn-54

<2.64

<2.91

<3.35

<3.20

<2.07

<4.16 Co-60

<3.25

<3.27

<3.78

<3.51

<2.27

<1.19 K40

<34.4

<30.1 90.7 +/- 18.6

<8.47 93.5 +/- 14.4 100 +/- 24.4 Others t

<LLD

<LLD NUCLIDES' JULY-.

AUGUST3/4>.-:

- SEPTEMBER:.'.'

'OCTOBER

- '--NOVE DECEMBER--.

Be-7 60.8 +/- 12.3 46.2 +/- 13.1 77.6 +/- 16.2 64.4 +/- 13.1 74.0 15.8 82.8 15.8 Zn-65

<7.97

<9.07

<2.49

<5.14

<11.3

<7.03 Cs-134

<0.64

<3.18

<3.89

<0.68

<3.96

<3.87 Cs-137

<1.79

<2.82

<3.70

<1.62

<4.20

<2.82 Zr-95

<7.13

<1.50

<6.70

<6.08

<7.67

<1.86 Nb-95

<5.37

<4.92

<6.96

<0.98

<4.12

<3.68 Co-58

<2.26

<4.55

<3.47

<3.54

<3.16

<2.80 Mn-54

<0.75

<2.78

<3.01

<2.60

<4.80

<3.00 Co-60

<3.27

<1.18

<5.18

<2.82

<5.88

<1.41 K-40

<11.7

<34.2

<55.3

<37.6

<43.4

<14.3 Others t

<LLD

<LLD Optional sample location t

Plant related radionuclides 6 -26

?

-*~'~

~

Jz

=~

rI

r r

r---

r--

r-r -

r--1

[--

r-r--

r---1 1-TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10-3 pCi/m 1 Sigina F OFFSITE COMPOSITE**

( __

(.-.

NUCLIDES,.1.^

I...

JANUARY FEBRUARY

MARCH

[

APRIL-'-

JUNE Be-7 Zn-65 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Co-60 K-40 Others t 53.7+/-+ 12.7

<6.66

<2.48

<2.87

.<5.31

<3.66

<2.75

<2.35

<3.17

<37.1

<LLD 90.3 +/- 11.6

<5.45

<2.60

<2.72 I<5.60

<2.45

<2.66

<1.92

.<2.86

<26.5

<LLD 97.9 + 13.9

<7.61..

<4.20

<2.68

<5.39

<4.72.

<4.44

<3.00

<4.06 91.3 +/- 16.3

<LLD.

114+/- 19.5

<11.5

<3.49

<2.90

<8.28

<7.87

<3.71

<2.93

<4.84

<49.5

<LLD 93.9+/- 14.2

<5.62

<2.73

<2.81

<3.31

<2.40

<3.998

<3.17

<0.94

<9.59

<LLD

<45.0

<10.5

<5.00

<5.44

<13.2.-

<5.06

<4.60

<1.45

<6.47

<23.2

<LLD UCLIDES mLYi.> J -'* AUGUST<: '

SEPTEMBER OCTOBER;'- :-: NOVEMBER; i-. DECEMBER Be-7 90.3+/- 13.6 73.7+/- 10.6 57.8+/- 14.6 60.5+/- 14.1 67.9+/- 16.2 89.5+/- 13.6 Zn-65

<8.48

<6.23

<7.53.

<7.87.

<7.01

<5.03 Cs-134

<3.26

<2.61

<3.81

<3.54

<4.81

<2.93 Cs-137

<0.60

<2.17 -<1.89

<3.42

<3.25

<2.32 Zr-95.

- <6.15

<5.49

<4.71

<5.40

<1.93

<5.13 Nb-95

<2.86

<3.96-

<4.06

<3.72

<6.28 -

<2.78 Co-58

<3.58

<2.39

<4.53

<3.64

<3.24

<2.98 Mn-54

<0.72

<2.07

<0.83

<4.07

<3.55

<2.00 Co-60

<1.09

<3.51

<3.29

<3.22

<3.86

<1.06 K-40

<30.1

<21.1

<12.8 107 +/- 21.8

<51.6

<42.7 Others t

<LLD

- Optional sample location t

Plant related radionuclides

. ' 6-27'

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3 pCi/m3 1 Sigma G OFFSITE COMPOSITE**

NUCLIDES JANUARY

, 4FEBRUARY

.-MARCH' -

APRIL MAY

' JUNE Be-7 55.1 +/- 14.1 94.4 +/- 13.2 90.1 + 16.4 134 +/- 16.0 111 +/- 12.4 98.1 + 18.7 Zn-65

<10.6

<6.39

<7.34

<6.82

<7.22

<12.4 Cs-134

<3.42

<2.55

<3.01

<3.02

<1.82

<7.09 Cs-137

<3.39

<2.19

<3.63

<2.39

<1.88

<5.68 Zr-95

<1.66

<6.46

<5.64

<5.53

<4.86

<8.35 Nb-95

<4.54

<3.89

<6.58

<3.75

<3.33

<5.38 Co-58

<3.84

<2.08

<4.06

<4.22

<2.11

<5.95 Mn-54

<4.29

<1.82

<3.38

<3.49

<2.50

<3.81 Co-60

<4.47

<3.19

<3.47

<3.68

<2.18

<4.64 K-40

<45.3

<35.5

<52.0

<25.9

<18.3 119 +/- 31.5 Others t

<LLD

-NCIE JLi7~~jcAUGUST:` ~1 SPEBR CTOBER 1 NOVEMBER. I DECENMER Be-7 67.9 + 15.4 70.1 +/- 12.8 65.8 18.5 68.4 I 13.2 100 +/- 19.8 74.7 +/- 15.9 Zn-65

<8.94

<5.86

<7.52

<9.81

<11.5

<7.38 Cs-134

<4.56

<2.88

<6.89.

<5.14

<6.08

<5.10 Cs-137

<3.16

<2.40

<0.92

<2.89

<5.32

<4.73 Zr-95

<6.54

<4.62

<7.39.

<5.23;

<10.9

<7.58 Nb-95

<3.69

<3.13

<7.07

<5.57

<6.60

<5.70 Co-58

<3.27

<2.38

<1.25

<3.90

<5.93

<2.70 Mn-54

<4.73

<2.69

<3.73

<3.81

<4.33

<0.85 Co-60

<3.83

<3.07

<1.65.

<4.16

<6.50

<3.48 K-40 73.8 + 20.5

<32.8

<69.7 92.6 +/- 20.4 138 +/- 27.8

<46.5 Others t

<LLD

<LLD'

<LLD

+ Optional sample location t

Plant related radionuclides

, i 6-28 I S_.~~~~r

,,j,,;,

6-

6----

6 -

V- --.

r t

, r-r- -- (7 r

r r-r---

(7--

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE:AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3pCi/mr'

+/- 1 Sigma I

(I D1 ONSITE COMPOSITE**

-NUCLIDES -

JANUARY-7 C'FEBRUARY

l.

MARCH l

APRIL J

-- MJUNE.

Be-7 59.1 + 16.0 79.1 1 15.6 76.3 :1:16.6 119 +/- 16.5 94.7 + 15.2 97.0 +/- 19.1 Zn-65

<10.5

<7.78

<7.59:

<7.88

<6.31

<7.18 Cs-134

<4.88

<3.79

<3.29

<3.15

<3.61

<2.34 Cs-137

<'3.04

<3.68

<2.69

<2.33

<2.52

<4.69 Zr-95

<8.80

<5.69

<5.73,<4.89

<7.18

<7.98

- -Nb-95 '

-4.62"

<3.23'

<4.10

'<3.74

<4.96

<3.51 Co-58

<5.10

<5.04

<2.56

<4.00

<2.94

<5.72 Mn-54

<4.79

<3.09

<3.81

<2.74

<3.25

<3.21 Co-60

<4.21

<1.31

<2.63

<4.25

<3.81

<4.39

'.K-40

<49.5

<38.1 115 + 22.7

<34.8

<10.7

<41.1 Others t

<LLD

' NUCLIDES

- ' ::JULY-r'-

' AUGUST:

'j--t-SEPTEMBER-- [...OCTOBER NOVEMBER [

-DECEMBER Be-7 71.4+/- 12.1 104 +/- 15.8 71.4 + 17.2 90.0 + 14.9 83.7 I 16.2 75.4 +/- 24.9 Zn-65

<5.13

<7.14

<10.5

<7.80

<2.91

<14.4 Cs-134

<2.73

<2.89

<4.51

<3.38

<4.54

<5.81 Cs-137

<2.63

<2.2'2

<3.51

<2.46

<3.32'

<4.44 Zr-95

<6.85

<7.45

<8.75

<1.63

<7.96

<10.8 Nb-95

<2.87

<4.66

<6.63

<6.77

<5.48

<5.95 Co-58

<4.35

<3.28

<5.37

<3.57

<5.30

<7.82 Mn-54

<3.97

<2.83

<3.68

<3.37

<3.53

<1.56 Co-60

<3.06

<1.20

<3.90

<1.23

<6.04

<2.40 K-40

<29.6

<57.3 124 + 26.0

<12.5

<64.7

<24.5 Others t

<LLD

. <LLD

<LLD

<LLD Optional sample location t

Plant related radionuclides I ; 6-29

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10-3 pCi/ni3 1 Sigma G ONSITE COMPOSITE**

.: NUCLIDES.-

-JAARY..

FEBRUARY MARCH APRIL

- MAY

...'JUNE Be-7 59.9+/- 12.5 105+/- 13.8 98.2+/- 14.4 133+/- 17.7 110+/- 13.0 69.7 +/- 16.7 Zn-65

<6.24

<7.05

<7.13

<7.54

<5.71

<11.8 Cs-134

<2.36

<3.14

<3.26

<2.74

<2.05

<3.94 Cs-137

<1.96

<2.01

<2.23

<3.17

<1.97

<3.82 Zr-95

<5.07

<5.76

<1.18

<8.41

<4.77

<8.89 Nb-95

<0.96

<5.20

<4.06

<7.52

<2.32

<5.78 Co-58

<2.95

<2.70

<3.36

<4.08

<2.23

<4.66 Mn-54

<3.25

<2.11

<2.77

<3.40

<1.70

<3.61 Co-60

<2.95

<0.87

<0.86

<4.22

<2.63

<7.16 K40

<10.5

<35.0

<23.7 115 +/- 19.7

<34.2

<46.3 Others t

<LLD

<LLD NUCLIDES

[;

JUY

-I AUGUST-.z

.[-;SEPTEMBER-4.OCTOBER.

.l ;-NOVEMBER I l DECEMBER Be-7 78.0 +/- 14.1 101 +/- 12.8 73;0+/- 15.3 67.6 + 13.8 85.2 +/- 17.4 67.7 +/- 13.8 Zn.65

<6.33

<6.32

<11.3

<5.34

<7.88

<5.16 Cs-134

<3.24

<2.93

<2.92

<2.74

<4.59

<3.00 Cs-137

<3.80

<1.79

<3.91

<2.90

<3.64

<2.05.

Zr-95

<6.11 i

<3.66

<6.61

<5.41

<12:2

<7.53 Nb-95

<4.55

<2.91

<3.59

<4.37

<1.50

<2.89 Co-58

<3.73

<1.51

<3.42

<4.21

<5.41

<3.58 Mn-54

<2.22

<2.62

<4.41

<2.37

<3.98

<3.71 Co-60

<3.54

<2.53

<3.60

<1.12

<6.99

<3.54 K-40 84.3 +/- 18.4

<21.4

<38.1

<11.4

<67.0

<11.0 Others t

<LLD

- Optional sample location t Plant related radionuclides 6-30 F---

Ir-1--

1-r f--

r--

I--

[

~~

I.

f Ut

[

~~1 1-

-~

TABLE 6-9 (confinued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAFINMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 pCi/rn3 I Sigma I

I H ONSITE COMPOSITE**

NUCLIDES

-JANUARY.

l 'FEBRUARY

-MARCH APRIL

-MAY JUNE Be-7 66.2+ 13.9 75.8+/- 11.6 98.1 + 13.7 156+ 18.1 98.1 + 12.0 127+/- 18.5 Zn-65

<8.76

<8.15

<6.52

<8.04

<4.26

<10.7 Cs-134

<4.50

<3.46

<2.23

<2.62

<1.79

<5.83 Cs-137

<2.74

<2.66

<1.51

<2.09

<1.86

<3.61 Zr-95

<5.25

<6.69

<3.83

<5.71

<4.81

<7.95 Nb-95

<3.98

<4.12

<3.21

<4.78

<2.37

<4.40 Co-58

<3.21

<2.69

. <2.97

<3.38

<2.83

<5.22 Mn-54

<3.78

<2.74

<2.28

<2.03

<1.82

<4:68 Co-60

<0.84

<3.33

<2.17

<2.11

<3.15

<4.00 K40

<8.39 93.1 + 19.1

<25.4

<36.3

<23.6 143 + 24.9 Others t

<LLD

-NUCLIDES Y

- j -- AUGUST.';I~.SEPTEMBER: [

OCTOBER

- J NOVEMBER -

DECEMBER Be-7 59.1 k 13.4 101 + 13.7 74.7 + 16.1 61.9 + 11.6 78.4 + 18.2

<34.6 Zn-65

<5.16

<6.67

<8.19

<5.30

<12.6

<3.03 Cs-134

<2.75

<3.12

<2.88

<4.47

<6.21

<3.61 Cs-137

<2.05

<2.57

<3.17

<2.97

<4.19.

<3.71 Zr-95

<4.16

<5.72

<7.54

<4.28

<6.11

<7.81 Nb-95

<4.27

<2.97

<4.44

<5.36

<6.80

<1.58 Co-58

<4.37

<2.71

<3.36

<2.49

<5.28

<3.81 Mn-54

<3.71

<2.67

<3.72

<3.11

<5.47

<4.78 Co-60

<3.07

<2.26

<496

<1.11

<5.07

<4.71 K40

<29.8

<8.06

<45.8

<30.6 114 + 23.3

<50.4 Others t

<LLD

<LLD.:.

<LLD

'<LLD

<LLD

- Optional sample location:

t Plant related radionuclides

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMVPLES - 2004 Results in Units of 103 pCi/mn3 + 1 Sigma I ONSITE COMPOSITE**

NUCLIDES.- l

-JANUARY 7.7.7..7 l---FEBRUARY--

l MARCH' APRIL MAY

' JUNE Be-7 54.9 +/- 16.5 97.0 +/- 13.0 97.3 +/- 16.8 96.9 +/- 18.0 105 +/- 14.4 69.8 +/- 17.3 Zn-65

<12.2

<5.84

<9.10

<7.31

<8.04

<2.65 Cs-134

<2.67

<3.18

<2.27

<3.69

<2.00

<4.18 Cs-137

<2.58

<2.75

<2.44

<3.93

<1.54

<3.07 Zr-95

<2.31

<4.59

<7.57

<8.45

<6.83

<8.95 Nb-95

<1.61

<4.09

<5.73

<4.89

<3.61

<5.21 Co-58

<3.88

<2.36

<2.97

<2.89

<4.50

<5.02 Mn-54

<1.14

<2.68

<2.45

<0.79

<2.91

<5.16 Co-60

<17.6

<2.41

<4.69

<5.58

<3.78

<1.55 K-40

<5 1.1

<22.5 84.0+/- 19.1

<34.3

<10.8

<51.7 Others t

<LLD

<LLD NUCLIDES

-- :. :. -AUGUST.

l

°SEPTEMBER

" OCTOBER -

-..-NOVEMBER -'

DECEMBER Be-7 100 + 15.0 98.4+/- 12.7 63.9 + 14.3 67.7 +/- 15.7 74.4 + 18.0 71.8+/-h 13.5 Zn-65

<9.25

<6.44

<2.31

<9.72

<14.5

<7.60 Cs-134

<4.42

<2.93

<3;30

<4.29

<3.90

<3.02 Cs-137

<3.40

<1.67

<0.73

<3.46

<3.18

<2.06 Zr-95

<6.39

<4.24

<9.04

<6.04

<2.08

<4.20 Nb-95

<4.43

<3.81

<5.06

<6.36

<1.43

<4.31 Co-58

<4.48

<1.67

<1.01

<4.06

<5.94

<3.10 Mn-54

<3.02

-<2.80

<0.87

<3.84

<2.69

<2.62 Co-60

<3.20

<2.89

<3.46

<5.20

<1.60

<3.56 K-40 77.3 +/- 18.5

<26.5

<36.6

<37.5

<16.3

<11.0 Others t

<LLD

.<LLD

<LLD Optional sample localion t

Plant related radionuclides 6-32 L,

6: __

L_ L -

I b

1--

l.

7

(' - -

F - -

F --

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3 pCi/m3 i I Sigma, J ONSITE COMPOSITE**

-NUCLIDES l

3

-JANUARY

-FEBRUARY.

MARCH

' l Y

JUNE Be-7 72.5 i 15.6 89.8 13.3 111 4 15.6 122+/- 17.2 95.4+/- 11.6 84.6 i 18.4 Zn-65

<7.49

<4.49

<7.83

<8.20

<3.73

<11.1 Cs-134

<3.71

<2.77

<3.86

<3.36

<2.72

<4.65 Cs-137'

-<0.65,

<2.31

<2.46

<3.01

<2.00

<5.99

-Zr-95

<1.57

'<4.63

<5.59 '

<7.08

<4.30

<5.75

, Nb-95

<4.64

<2.80'

<5.10'

<5.20 '

<3.41

<6.10 Co-58

<3.43

<2.07

<4.47

<3.75

<2.04

<4.24 Mn-54

<2.52

,<1.80

<2.95

<3.35

<1.94

<1.11 Co-60

<3.09

<3.16

<2.87

<2.29

<2.60

<5.84 K-40

<12.0 50.8i 15.3 109+/- 19.0 98.8i 17.7

<16.4

<17.3 Others t

<LLD

<LLD NUCLIDES 47 'JUL-Y.

c :; ' AUGUST.v->

lSEPTEMBER:

OCTOBER -;.- "NOVEMBER

[

DECEMBER--

Be-7 72.3,+/- 12.4 113+/- 14.8 81.7+/- 17.8 56.9+/- 15.0 59.1 i 16.5 81.2+/- 16.5 Zn-65

<8.51

<9.56

<11.2

, <8.49,

<9.08

<12.1 Cs-134

' <2.78

<2.31

<6.54'

<4.86

<4.20

<3.63 Cs-137

<2.07

<2.49

<4.52

<3.32

<0.94 Zr-95

<4.21

<5.49

<8.23

<5.13

<5.75

<9.10 Nb-95

<4.83

<3.75

<5.62

<3.56'

<5.85

<1.59 Co-58

<3.11

<4.24

<4.68

<3.82

<1.16

<3.83 Mn-54

<3.06

<3.15,

<4.02

<3.92

<4.23

<3.25 Co-60

<3.11

<4.17

<'310'

<2.48

<1.51

<1.74 K40

<11.1 116 21.7 79.1 +/- 20.6

<42.6

<41.8

<50.5 Others t

<LLD,.

<LLD

- Optional sample location

<L'.

<LLD

t. Plant related radionuclides 6 ~33`

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2004 Results in Units of 10 3 pCi/nm3 i 1 Sigma K ONSITE COMPOSITE**

NUCLIDES

[

JANUARY'.'-;

lFEBRUARY --

MARCH APRIL

- MAY

-: JUNE Be-7 51.5 +/- 13.7 84.1 +/- 15.0 80.8 +/- 16.3 146+/-1,9.3 107+/- 13.0 92.5 20.4 Zn-65

<5.64

<7.31

<8.81

<7.48

<5.60

<13.1 Cs-134

<2.96

<2.72

<3.11

<2.34

<2.38

<5.37 Cs-137

<2.74

<3.46

<3.96

<2.89

<2.43

<3.98 Zr-95

<4.51

<6.20

<7.62

<10.5

<3.69

<8.76 Nb-95

<3.98

<5.49

<5.26

<1.37

<3.55

<4.55 Co-58

<3.42

<5.11

<4.24

<4.37

<2.61

<3.86 Mn-54

<2.90

<3.49

<3.83

<1.82

<4.54 Co-60

<3.38

<6.32

<5.91

<5.11

<2.37

<5.36 K-40

<39.6

<52.7

<36.4

<12.3 66.1 +/- 16.9 82.5 +/- 22.3 Others t

<LLD

-NUCLIDES.

- JULY I

AUGUST' _l-SEPTEMBER [

OCTOBER-I NOVEMBER :l-.DECEMBER Be-7 93.6 +/- 15.3 87.5 i 13.1

<46.6 52.3+/-+ 15.0 77.1 +/- 17.3 62.4 +/- 12.3 Zn-65

<9.13

<8.38

<10.1

<9.76

<11.0

<1.92 Cs-134

<3.67

<3.96

<6.77

<2.91

<5.98

<3.57 Cs-137

<3.19

<2.79

<4.59

<2.37

<2.58

<2.68 Zr

<6.31

<6.11

<2.75

<7.48

<9.85

<4.22 Nb-95

<4.71

<3.32

<5.12

<3.14

<4.19

<2.93 Co-58

<4.43

<2.99

<1.60

<4.76

<5.66

<4.77 Mn-54

<2.67

<3.45

<5.06

<3.53

<3.68

<0.72 Co-60

<3.66

<3.72

<5.82

<3.10

<4.36

<2.86 K-40 66.6 +/- 17.8 144 + 21.0

<21.8

<32.8 128 +/- 24.6

<11.1 Others t

<LLD

<LLD Optional sample localion t

Plant related radionuclides

'6-34 i.I_

F1I

=--

lts

-__!l..'

F -

F -, -

F- -

F__

1___,

IU F_-

F-F F

I

(..-.

TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS - 2004 Rcsults in Units of mrem/std. Month 1 1 Sigma I

LOCATION FIRST- -',

SCON T

T.IRD FOURTH -

CA(

IMER LOCATIONU j-.

(DISTANCE AND NU.

.ER-.....

.,QUARTER-QUARTER,.-

'QUARTE-R QUARTE

_v 1--

'_-DIRECTION)(I) 3 Dl Onsite 9.8+/-0.2.

13.2 1.2

- 12.6+/- 1.1 11.8+/-0.6 0.2 miles @ 69°.

4 D2 Onsite 4.3+/- 0.4 4.1 +/- 0.2

.5.5 +/- 0.8 4.1 +/- 0.2 0.4 miles ( 1400 5

.E Onsite 4.1 +/- 0.3 4.9 +/- 0.4. -.

6.9 +/- 0.5 4.5 +/- 0.2 0.4 miles @ 175° 6

F Onsite 3.5 +/-0.2 4.1 +/- 0.3 5.4+/-0.5 3.7+/-0.3 0.5 miles @ 2100 7*

G Onsite

-3.3 +/-0.1

-40+/-020.2 4.7+/-0.3 3.5 +/-0.1 0.7 miles @ 250° 8

R-5 Offsite Control 4.4 +/- 0.2 -

5.0

0.4

. 5.8 +/- 0.4.

4.4 +/- 0.1 16.4 miles ( 42° 9

DI Offsite-3.5 +/- 0.2 -

4.1 0.3 5.4 +/- 0.6 3.4 +/- 0.2 11.4 miles @80°

.10-

D2Offsite,-----

-- 3.6+/-0.2 4.3+/-0.4 5

1

.3.6+/-0.3 9.0miles 117° 11 EOffsite - -

3.6+/- 0.2.

4.4 0.3 5.6 +/- 0.6 3.9+/-0.2 7:2 miles 1600 12

.ji-

-F-Offsite 3.2 +/- 0.2 4.2 + 0.3 6.0 +/- 0.8 4.6 +/- 0.1 7.7 miles @ 1900

.13

-G Offsite 3.8 +/- 0.2 4.3 +/- 0.1.

6.0+/- 0.7.

4.7 +/- 0.1 5.3 miles @225 14* -

DeMass Rd., SW Oswego Control

-3.8 0.2 4.8 +/- 0.2 5.9 +/- 1.0 4.6 +/- 0.2 12.6 miles @ 226° 15*

Pole 66, WV. Boundary - Bible Camp 3.5 +/- 0.2 3.8 +/--0.2 5.1 1 0.1 4.01 0.2 0.9 miles @ 2370

.18*

Energy Info. Center - Lamp Post; SW-

- 3.9 +/- 0.2 4.5 +/- 0.2 6.0 +/- 0.2 4.7 +/- 0.3 0.4 miles @ 265° 19 *

EastBoundary-JAFPole9 3.8 +/- 0.2 4.7 +/- 0.7 5.8 +/- 0.8 4.8 +/- 0.1 1.3 miles na, 81° 23*

- HOnsite

4.7 +/- 0.3--

5.0 +/- 0.4

-. 6.9 +/- 0.9 5.3 +/- 0.2 0.8 miles @ 70°

..24 I Onsite 3.90.3 4.5 + 0.5 5.8 +/- 0.5.

.4.4 +/- 0.2 0.8 miles @ 980 25 J Onsite--

.3.4 +/- 0.1.

4.5 +/- 0.2 5.3 +/- 0.2 4.5 +/- 0.3 0.9 miles@ 1100 26 Onsite 13.5 +/- 0.3 4.2+/- 0.2 -

6.0 0.5 4.5 +/- 0.3 0.5miles @ 1320 27 N. Fence, N. of Switchyard, JAF 14.6+/- 0.5 19.0+/- 0.6 19.3 +/- 1.3 18.3 + 1.2 0.4 miles @ 60° 28 N. Light PoleN. of Screenhouse, JAF.

24.0 +/- 1.8 29.61 0.5 33.4+/-h 3.4 37.6 +/- 1.8

.0.5 miles @ 68° 29 N. Fence, N. of W. Side 21.1 +/- 1.7 25.8 +/- 1.4 23.3

3.1 25.1 +/- 2.4 0.5 miles @ 650 30 N. Fence, (NW) JAF 12.4 +/- 0.4;-:.<-

13.4 0.8 14.8 +/- 1.2 13.9 +/- 1.1 0.4 miles @ 57° 31 N. Fence, (NW)NMP-6.1 0.3 7.3 0.5 8.9 1.3 7.2 +/- 0.3 0.2 miles @ 276°

I

6-35.

TABLE 6-10 (continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2004 Results in Units of nireifi/std. Mouth -+/- 1 Signiia T

T LOCATION LOCATION FIRST:

SECOND-THIRD FOURTH (ITNEA]

NUBRLOCATION.

(D________

_ ISTANC NU;QUA TER Q-T QUARTER QUARTER QURTR QURE

)()k~

39 N. Fence, Rad. Waste-NMP-I 8.3 +/- 0.4

.8.4 +/- 0.5 10.4 +/- 0.9 10.0 i 0.8 0.2 miles @ 2920 47 N. Fence, (NE) JAF 6.3 +/- 0.2 6.8 + 0.3 7.8 +/- 1.1 7.4 +/- 0.4 0.6 miles @ 690 49*

Phoenix, NY-Coiltrol 3.3 +/- 0.2 3.8

0.2 5.7 +/- 1.0 4.0 +/- 0.3 19.8 miles (a 163" 51 Liberty & Bronson Sts., E of OSS 3.7 +/- 0.2 --

4.3 0.4 5.8* 0.7 4.2 +/- 0.4 7.4 miles (CD 233" 52 E. 12th & Cayuga Sts., Oswego School 3.6 - 0.3.

4.4 +/- 0.1 6.8 +/- 0.7 4.3 +/- 0.2 5.8 miles na, 2270 53 Broadwell & Chestnut Sts. Fulton 11.S.

3.6 +/- 0.2 4.8 +/- 0.3 6.6 +/- 1.2 4.4 +/- 0.3 13.7 miles (6 1830 54 Liberty St. & Co. Rt. 16 Mexico I1.S.

3.8 +/- 0.2 3.9.+ 0.2 5.2 +/- 0.3 4.2 +/- 0.2 9.3 miles (a) 1150 55 Gas Substation Co. Rt. 5-Pulaski 4.3 F 0.4 4.1 + 0.2 5.5

0.4 3.9

0.3 13.0 miles (a 75' 56-Rt. 104-New Haven Sch. (SE Comer) 3.0 +/- 0.5 3.7 +/- 0.2 5.3 +/- 0.4 3.7 +/- 0.1 5.3 miles @ 123° 58*

Co Rt. IA-Alcan (E. of E. Entrance Rd.)

3.9 +/- 0.2 4.5 +/- 0.1 5.8 +/- 0.4 4.1 +/- 0.3 3.1 miles (2 220° 75*

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

7.0 +/- 0.3 7.5 +/- 0.6 8.6 +/- 0.7 7.1 : 0.3 0.1 miles @ 5° 76*

Unit 2, N. Fence, N. of Change House 5.2 +/- 0.4 5.9

0.3 6.8 +/- 0.5 5.4 +/- 0.2 0.1 miles @25°

-77*

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

5.7 +/- 0.5 6.7 +/-0.8 8.6 +/- 1.4 6.2 +/- 0.2 0.2 miles

), 45' 78*

JAF. E. of E. Old Lay Down Area 4.0 +/- 0.3 4.5 + 0.2 6.3 +/- 1.0 4.4 +/- 0.2 1.0 iniles 61 90° 79*.

Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd.

3.6 +/- 0.2.-

3.8 +/- 0.3 5.1 +/- 0.5 3.7 +/- 0.3 1.1 miles @ 115° 80*

Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd.

3.6 +/- 0.2 4.1 +/- 0.2 6.0 +/- 0.8 4.1 +/- 0.2 1.4 miles (ki 1330 81*

MinerRd.,Pole#16,0.5 mi.W.ofRt.29 3.5 i 0.2 4.0 i 0.1 6.4

0.7 3.8 i 0.2 1.6 miles @ 1590 82*

Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29 3.4 +/- 0.2 4.0 i 0.2 5.2 +/- 0.2 3.7 i 0.4 1.6 miles (Q 181° 83*

Lakeview Rd., Tree 0.45 mi. N. of Miner Rd. -

3.6 +/- 0.2 4.0+/- 0.3 5.8 +/- 0.7 4.1 +/- 0.4 1.2 miles @ 200° 84*

Lakeview Rd., N., Pole #6117, 200a. N. of Lake Rd.

3.7

0.1 4.2 i 0.3 6.1 +/- 0.8 4.2 +/- 0.2 1.1 miles @225° 85*

Unit 1, N. Fence, N. of W. Side of Screen House 7.6 +/- 0.5 7.5 +/- 0.5 10.8 i 0.6 8.3 +/- 0.7 0.2 miles @ 294° 86*

Unit 2, N. Fence, N of W. Side of Screen I louse 6.9

0.3 6.7 i 0. I 9.9 i 1.1 7.4 i 0.3 0.1 miles @315° 87*

Unit 2, N. Fence, N. of E. Side of Screen House 7.4 i 0.2 7.1 i 0.3 9.5 i 1.5 7.6 i 0.7 0.1 miles @ 341° 88*

Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 1 3.4

0.1 4.2 +/- 0.3 5.7 i 0.8 4.2 +/- 0.3 4.8 miles (a), 970 6 -36:

-e--I:

1~

~

i l~-6--

t---

F

(- ---

F- --

F",

F -

r-F

(.

F

(

[

0 w

(

I f.....---

TABLE 6-10 (continued)

DIRECT RADIATION MEASUREM ENT RESULTS - 2004 Results in Units of mrem/std. Month : I Sigrna lNUMER Nl

,- ~LOCATION:,I.

l QUARTER<

AlE RT QA (DISAN LOCATION

--. -: -SECOND.

THIRD' FOURTH LCTO DIRECON(1 89*

Leavitt Rd., Pole #16, 0.4 mi. S. of Rt. I 3.8 +/-0.2 5.0+/-0.3 5.4 0.4 4.4 : 0.3

4. i miles@ 1110 90*

Rt. 104, Pole #300, 150 ft. E. of Keefe Rd.

3.4+/-0.3 4.3+/-0.3 6.7I0.7 4.5+/-0.2 4.2 miles () 1350 91*

Rt SI A, Pole #59, 0.8 mi. W. of Rt. 51 3.2 +/- 0.2 3.8 +/- 0.2 5.6 +/- 0.5 4.2 +/- 0.1; 4.8 miles i) 156° 92*

Maiden Lane Rd., PoWer Pole, 0.6 mi. S. of Rt. 104 3.7 - 0.2 4.4 +/- 0.1 5.8 +/- 0.7 4.8 +/- 0.2 4.4 miles @ 1830 93*

Rt. 53 Pole 1-, 120 R. S. of Rt. 104 3.5 +/- 0.2 4.4 4 0.3 5.1 +/- 0.3 4.4 +/- 0.2 4.4 miles @ 2050 94*

Rt. 1, Pole #82, 250 fl. E. of Kocher Rd. (Co. Rt. 63).

3.3 +/- 0.2 4.0+/- 0.3 4.8 +/- 0.3 4.3 +/- 0.1 4.7 miles @ 223o 95*

Alcan W access Rd., Joe Fultz Blvd, Pole #21 3.3 +/- 0.1 3.6 + 0.2 4.6 +/- 0.2 3.8 +/- 0.2 4.1 miles (@ 2370 96*

Creamery Rd., 0.3 mi. S. 6f Middle Rd., Pole 1-1/2 1

3.5 +/-0.2' 4.1 +/- 0.3 4.9 0.4 4.2 +/- 0.2 3.6 miles @ 199° 97*

Rt.29,Pole#50,20Oft.N.ofMinerRd..'

.6+/- 0.3.

3.9+/- 0.1 5.2 +/- 0.3 4.2 + 0.2' 1.8 miles @ 1430 98*

Lake Rd., Pole #145, 0.15 mi. E. of Rt 29 3.7 + 0.2 4.2 0.2

.. 5.9 +/- 0.7 4.1 0.1

1.2 miles @ 1010 99 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station Rl 3.8 +/- 0.3 4.4 + 0.2 5.6 +/- 0.6 4.4 + 0.1 i.8 nmiles 88 0 100 Rt. 29 & Lake Rd., Env. Station R2 3.7+/-0.2' 4.040.2 5.5+/-0.6 4.1 +/-0.2 1.i miles@ 1040 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 3.5 +/-'0.2 -

3.6 +-0.3 5.0 +/- 0.9

.3.6 +/- 0.1 1.5 miles @i, 132° 102 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post 3.4 +/-0.1 3.9 : 0.3 5.1 +/- 0.5 3.8 +/- 0.4 11.9 miles @, 175' 103.

. ETC, East Garage Rd., Lamp Post 4.2 +/- 0.2 4.5 + 0.2.

6.2 +/- 0.4 4.1 +/- 0.2 0.4 miles @ 267° 104

-'Parkhurst Rd., Pole #23,;0.1 ri~. S. of Lake rd. -

3.6 +/- 0.2 4.10.2 5.3 0.5 4.5+/- 0.1 1.4 miles na, 102° 105 LakeviewRd. Pole #36, 0.5 mi. S. of Lake Rd.

3.7+/-0.2 4.0 0.2 5.1+/-0.3 3.6+/-0.2:

1.4miles@ 1980 106 Shoreline Cove, W. of NMP-I, Tree on W. Edge 4.4 +/- 0.3 4.8 + 0.2 6.8 +/- 0.6 4.8 +/- 0.2 0.3 miles @ 2740 107 Shoreline Cove, W. of NMP-l, 30 ft SSW of #106 4.2 +/- 0.2 4.7 +/- 0.2 6.2 +/- 0.2 4.5 +/- 0.2 0.3 miles @ 2720 108 LakeRd.,Polet#142,300ftE.ofRt.29S.

3.7 +/- 0.3

.4.3 h 0.2 5.0 +0.1 3.9 +/- 0.4 1.1 miles ( 104" 109 Tree North of Lake Rd.,300 ft E. of Rt. 29 N 3.8 +/- 0.3 3.8 +/- 0.2 5.3+/- 0.7 3.9 +/- 0.3 1.1 miles @ 1030 1ll Control, State Route 38, Sterling NY 3.3 +/-0.2 3.6+/- 0.2 4.6 +/- 0.3 3.4 +/- 0.3 26.4 miles @ 1660 112 EOF/Env. Lab, Oswego County Airport 3.9 +/- 0.3 4.0 +/- 0.3 l

5.3 +/- 0.5 3.5 +/- 0.2 11.9 miles ! 175° 113 Control, Baldwinsville, NY 3.4 +/- 0.2 3.6+/-0.1 4.4+/-0.4 3.4 0.1 21.8miles@214 (1) Direction and distance based on NMP-2 reactor centerline and sixteen 22.50 sector grid TLD required by ODCM 637 7

. I

l l a.,

I TABLE 6-11 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2004 I

Results in Units of pCi/liter 1 1 Sigma

-SAMPLE LOCATION*** No.55**, '.__.___.______;,__,

CollectionDatel.

I-131

.. l.:

K 1t;-' *Cs-134 l

Cs-137.

l Ba/La "1 i'Otherst 04/05/04

<0.441 1570* 84

<5.35

<5.58

<5.51

<LLD 05/03/04

<0.420 1500 84

<6.56

<6.82

<7.64

< LLD 06/07/04

<0.450 1340 67

<5.30

<6.55

<5.98

< LLD 07/12/04

<0.404 1540* 79

<5.74

<5.52

<7.27

< LLD 07/26/04

<0.311 1490 +/- 89

<6.93

<8.55

<8.49

<LLD 08/09/04

<0.444 1430

77

<6.84

<5.42

<7.59

< LLD 08/23/04

<0.382 1510 +/- 79

<6.00

<6.55

<8.08

< LLD 09/13/04

<0.347 1430* 77

<5.85

<6.55

<5.16

< LLD 09/27/04

<0.430 1460

80

<6.72

<6.83

<8.10

<LLD 10/11/04

<0.328 1620 104

<9.08

<7.11

<6.78

<LLD 10/25/04

<0.381 1520 78

<4.03

<5.63

<5.51

<LLD 11/08/04 -

<0.323 1570 84

<4.98

<7.22

<7.88

< LLD 11/22/04

<0.584 1880 90

<9.28

<7.77

<9.37

< LLD 12/06/04

<0.359 1990 +/- 109

<9.30

<9.63

<9.30

<LLD 12/20/04

<0.364 1510 63

<4.62

<4.16

<4.86

< LLD

'-_'_'_'-_-_t' SAMPLE LOCATION*** No.4*,*'.

CollectioniDatel:

I-131.'

K-40>

C. i:Cs-134 -'7^

Cs4137 ;,

Ba/La I

7 Othe st 04/05/04

<0.351.

1530 + 64

<4.77

<4.69

<5.34

< LLD 05/03/04

<0.369 1770: *74

<5.90

<6.38

<7.15

< LLD 06/07/04

<0.330 1510 L 84

<7.69

<7.91

<8.77

< LLD 07/12/04

<0.380 1860

93

<8.87

<6.94

<8.42

<LLD 07/26/04

<0.331

.1680 97

<6.07

<9.87

<11.7

< LLD 08/09/04

<0.419 1600 87

<8.09

<8.39

<5.98

< LLD 08/23/04

<0.335 1340

74

<6.94

<5.60

<8.01

< LLD 09/13/04

<0.393

,1500 76

<6.29

<5.36

<6.45

< LLD 09/27/04

<0.642 1480* 100

<8.45

<8.13

<9.54

< LLD 10/11/04

<0.328 1560

80

<6.24

<6.70

<6.28

< LLD 10/25/04

<0.315 1760

89

<7.92

<6.63

<7.99

< LLD 11/08/04

<0.827 1390 + 74

<5.30

<6.47

<6.88

< LLD 11/22/04

<0.469 1540

79

<5.99

<7.50

<7.98

< LLD 12/06/04

<0.309 1460

94

<8.67

<7.53

<9.36

< LLD 12/20/04

<0.474 1630 *70

<6.91

<5.09

<6.57

< LLD t

Plant related radionuclides Optional sample location Corresponds to sample location noted on Figure 3.3-4 11 II

'111 illA L.1

[II I.U 6 -38

CONCENTRATIONS TABLE-6-11 (Continued)

OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2004 Results in Units of pCi/liter +/- 1 Sigma

- uSAMPLE LOCATIONNo.*** 76**-

Collection Date I-131 K-40

] K:Cs-134:.

--Cs-137:

-: Ba/La r Others t 04/05/04

<0.349 1580 1 49

<2.86

<4.05

<3.78

<LLD 04/19/04

<0.529 1400 +/- 65

<4.81

<5.38

<6.92

<LLD 05/03/04

<0.409 1500 +/- 67

<5.31

<5.46

<6.83

< LLD 05/17/04

<0.340 1470 +/- 75

<5.45

<5.99

<6.76

< LLD 06/07/04

<0.407 1720 + 93

<6.96

<8.71

<10.2

< LLD 06/21/04

<0.481 1360,61

<5.03

<4.59

<6.03

<LLD 07/12/04

<0.454 1560 82

<6.12

<7.50

<7.21

< LLD 07/27/04

<0.441 1420 +/- 78

<5.89

<6.98

<6.74

< LLD 08/09/04

<0.335 1500+/- 102

<7.82

<8.13

<10.2

< LLD 08/23/04

<0.399 1520 100

<8.40

<7.89

<7.86

< LLD 09/13/04

<0.494 1370 76

,8.26

<5.41 -

8.08

< LLD 09/27/04

<0.499 980 +/- 67

<7.40

<7.22

<7.35

<LLD 10/11/05

<0.384 1470+/ - --<7.05

<5.93

<9.13

< LLD 10/25/04

<0.303 1630 + 60

<3.45

<4.84

<5.22

< LLD 11/09/04.

<0.400 1320 63

<4.59

<5.12

<5.84

-< LLD 11/21/04

<0.623 i1320 93

- <10.9

<5.89

<9.93

<LLD 12/05/04

<0.394 1390 91

<7.32

<10.2

<11.2-

<LLD 12/20/04

<0.335 131062

<6.04

<5.48

<5.05

<LLD SAMPLE LOCATION No277*** (Control)t-, !:

CollectionDate' 131 : l.I K-40;- A'

-Cs-134';! 4l £-.Cs-1371Al Ba/La lKOthet t 04/05/04

<0.318 1520+/- 65

<4.49

<5.55

<3.67

< LLD 04/19/04

<0.408 1520 68

<5.32

<5.30

<6.84

< LLD 05/03/04

<0.547 1660 +/- 67

<5.92

<5.10

<6.25

< LLD 05/17/04

<0.398 1610+/- 95

_<7.09

<6.95

<9.80

< LLD 06/07/04

<0.368 1680 +/- 67

<4.79

<4.82

<7.47

< LLD 06/21/04

<0.427 1710 72

<6.03

<5.83

<8.42

< LLD 07/12/04

<0.477 1670 +/- 62

<5.53

<5.35

<5.56

< LLD 07/26/04

<0.43 8 1720+/-A 68

<3.52

<5.70

<5.87

< LLD 08/09/04

<0.313 1570 60

-. <3.40

<5.20

<5.86

< LLD 08/23/04

<0.684 1580 60 c<5.80

<4.99

<4.68

< LLD 09/13/04

<0.333 1520+/- 101-

-- <8.66

<8.81-

<9.52

< LLD 09/27/04

<0.427 1670 62

<3.51

<5.10

<4.86

<LLD 10/11/04

<0.452 1310 72

<6.06

<5.22

<5.97.

< LLD 10/25/04

<0.347.

1340 +/- 77

<5.85

<625

<6.35

< LLD 11/08/04

<0.346-1540 59

<3.27

<5.25

<4.88

< LLD 11/22/04

<0.462

-1660+/- 62

<-c3:27

<4.72

<3.78.

< LLD 12/06/04

<0.448 1460+/-h 117

<6.44

<9.88

<9.45

< LLD 12/20/04

<0.405 1470 4 65

-<5.80

<5.24

<6.35

< LLD ies t

Plant related radionuclid Sample location required 11 Optional sample location Cs Iby C)DCM 6 6-39

- - Corresponds'to sample location noted on Figure 3.3-4

TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2004 Results in Units of pCi/g (wet) + 1 sigma COLLECTION J SA LE 1 -3 1

STE DATE-K Cs-134 ZCn-137 I Zn-65.

Squash Leaves 1.62 + 0.057.

4.36 +/- 0.130

<0.012

<0.008

<0.010

<0.017 133

09/20/04 Tomatoes

<0.060 2.27 +/- 0.091

<0.007

<0.008

<0.016 Collards 0.228 +/- 0.055 4.59 +/- 0.203

<0.018

<0.019

<0.017

<0.047 Tomatoes

<0.060 2.03 +/- 0.087

<0.007

<0.005

<0.007

<0.021 132

09/20/04 Squash Leaves 1.40 +/- 0.073 3.16 +/- 0.150

<0.015

<0.020

<0.013

<0.034 Zucchini Leaves 0.442 +/- 0.057 4.18 0.190

<0.020

<0.013

<0.020

<0.050 134.**

09/20/03 Grape Leaves 1.79 +/- 0.140 4.52 +/- 0.302

<0.030.

<0.034

<0.030

<0.090 Tomatoes

<0.090 3.49 +/- 0.150

<0.012

<0.015

<0.014

<0.032 Cucumber Leaves 1.45 +/- 0.072 3.10 +/- 0.150

<0.015

<0.017

<0.013

<0.042 Whaley 09/20/04 Tomatoes

<0.051 2.80 +/- 0.100

<0.007

<0.005

<0.008

<0.018 144 Squash Leaves 0.929 +/- 0.073 4.57 +/- 0.229

<0.019

<0.021

<0.016

<0.052 Cabbage 0.243 +/- 0.048 4.55 +/- 0.163

<0.019

<0.013

<0.017

<0.039 Squash Leaves 0.845 +/- 0.050 3.68 +/- 0.135

<0.0 12

<0.010

<0.011

<0.028 145

09/16/04 Cucumber Leaves 1.46 +/- 0.075 2.42+/- 0.149

<0.017

<0.012

<0.030 (Control)

Tomatoes

'*0.055 2.62 +/- 0.097

<0.008

<0.007

<0.017 Grape Leaves.

1.61+/- 0.069 2.93 0.120

<0.019

<0.011

<0.014

<0.035

Sample Location required by ODCM

- Optional sample location Note: Other plant related radionuclides <LLD 6 -40

-=

i I r

= _

r~ ;

r---

im*

-~ _

r

TABLE 6-13 MILK ANIMAL CENSUS - 2004 6TW R RA() >~!j§NUMBEI ON

2)

(2

'- 'NUMBER OF'MlLK,;

TOWNOR REA'.-!~KiY R DEGREES,'

1ITNE 2 mieY

¶-,

Sciba62 1830 6.7 1G(3 New Haven 75 146° 7.5 9G 9

950 5.2 40C 4*

1130 7.8 90C 64 1070 7.9 51C Mexico 14 1200 9.8 55C 60 90° 9.5 20C 76*

1320 5.2 30C 50*

930 9.1 NONE 55*

95o 9.0 51C 21 1120 10.5 60C 72 980 9.9 38C Sterling 73*

2340 13.9 NONE Richland 22 850 13.9 NONE Volney 25 1820 9.5 NONE Granby Control) 77**

1910 13.9 65C MILKING ANIMAL TOTALS:

500 Cows (including control locations) 10 Goats MILKING ANIMAL TOTALS:

435 Cows (excluding control locations) 10 Goats NOTES:

C

= Cows G = Goats

= Milk sample location

= Milk sample control location (1)

= Reference Figure 3.3-4 (2)

= Degrees and distance are based on NMP-2 reactor building centerline (3)

= Goat is not currently producing milk or any milk produced is utilized by the owner 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 10 miles 6 -41

Ian II TABLE 6-14 RESIDENCE CENSUS - 2004

~MAP LOCATION,'-DEGREES:(2)

(

-bEGREE&,

D1/2i

STANCElf, 2 ~;.

NNE

~NE

~ENE Lake Road A

E 970 1.3 miles Lake Road B

ESE 1020 1.1 miles County Route 29 C

SE 1300 1.4 miles Miner Road D

SSE 1630 1.7 miles Miner Road E

S 1700 1.6 miles Lakeview Road F

SSW 2070 1.2 miles Bible Camp Retreat G

SW 2340 0.9 miles Bible Camp Retreat H

WSW 2380 0.9 miles W

WNW NW NNW NOTES:

This meteorological sector is over Lake Ontario. There is no residence within five miles (1)

Corresponds to Figure 3.3-5 (2)

Based on NMP2 reactor centerline Il Il Il Il A

1I 1'I I

I,.

ii I

6 -42

TABLE 7-1 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (CONTROL) (1)

Cs-137 (pCig (dry)

Co-60 (pCi/g (d))

1979 (2) 0.22 0.22 0.22 LLD LLD LLD

1980

.0.07 0.09 0.08 LLD LLD LLD

.1981 LLD LLD LLD LLD LLD' LLD 1982 0.05 0.05

.0.05 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

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 0.03 0.03 0.03 LLD LLD LLD 1994 LLD LLD LLD

'LLD LLD

.LLD 1995 LLD LLD

-LLD LLD LLD LLD 1996 LLD

. LLD

-LLD LLD LLD LLD 1997 LLD LLD

,LLD LLD.

LLD LLD 1998

LLD LLD LLD LLD LLD

. 1999 LLD LLD LLD LLD LLD LLD

.2000

-LLD LLD

.LLD LLD LLD LLD

.2001 LLD LLD LLD LLD LLD LLD

.2002

.LLD LLD LLD LLD LLD LLD 2003 LLD LLD

.LLD LLD LLD LLD 2004

'LLD LLD LLD LLD LLD LLD (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.

7-1

-I -

I TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDENIENT (INDICATOR) '

Cs-137 (pCi/g dry))

Co-60 (pCi/g (dry))

1979 (2)

(2)

(2) 1980 (2)

(2)

(2) 1981 (2)

(2)

(2) 1982 (2)

(2)

(2) 1983 (2)

(2)

(2) 1984 (2)

(2)

(2) 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 0.25 0.34 0.30 LLD LLD LLD 1990 0.28 0.28 0.28 LLD LLD LLD 1991 0.11 0.16 0.14 LLD LLD LLD 1992 0.10 0.16 0.13 LLD LLD LLD 1993 0.17 0.49 0.33 LLD LLD LLD 1994.

0.08 0.39 0.24 LLD LLD LLD 1995 0.16 0.17 0.16 LLD LLD LLD 1996 0.13 0.18 0.16 LLD LLD LLD 1997 0.13 0.18 0.16 LLD LLD LLD 1998 0.07 0.07 0.07 LLD LLD LLD 1999 0.06 0.09 0.08 LLD LLD LLD 2000 0.06 0.08 0.07 LLD LLD LLD 2001 0.06 0.07 0.07 LLD LLD LLD 2002 0.05 0.05 0.05 LLD LLD LLD 2003 0.04 0.05 0.05 LLD LLD LLD 2004 0.04 0.04 0.04 LLD LLD LLD (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.

1, 1

1I I

1 1i Il I

I ii 1

J.

7 -2

TABLE 7-3 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (CONTROL) (1)

Cs-137 (pCi/g (wet))

YEAw~R-gx ME &M}

F 1976 1.2 1.2 1.2 1977 0.13 0.13 0.13 1978 0.04 0.20 0.09 1979 0.03 0.06 0.04 1980 0.03 0.11 0.06 1981-0.028 0.062 0.043 1982

'0.027 0.055

' 0.046 1983

0.041 0.057 0.049 1984 0.015 0.038 0.032 1985 0.026 0.047 0.034

- 1986

.0.021 0.032 0.025 1987 0.017 0.040 0.031

-1988 0.023 0.053 0.033 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 0.041 0.032 1994 0.012 0.035 0.024

'1995 0.014 0.020

0.016 1996 0.014 0.018 i0.016 1997

'0.019 0.043 0.031 1998 0.013 0.013

-0.013 1999 LLD LLD.

LLD 2000

' 0.02 0.02 0.02 2001 LLD LLD LLD 2002

.LLD LLD LLD 2003 LLD LLD LLD 2004 LLD

LLD LLD.

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

L.-

II TABLE 74 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (INDICATOR) (1)

Cs-137 (pC~ig (wet))

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 0.06 1 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 0.020 0.043.

0.035 1990 0.024 0.115 0.044 1991 0.021 0.035 0.027 1992 0.013 0.034 0.026 1993 0.021 0.038 0.030 1994 0.011 0.028 0.020 1995 0.016 0.019 0.018 1996 0.014 0.016 0.015 1997 0.015.

0.017 0.016 1998 0.021 0.021 0.021 1999 0.016 0.018 0.017 2000 LLD LLD

LLD 2001 LLD LLD LLD 2002 0.016 0.016 0.016 2003 LLD LLD LLD 2004 LLD LLD LLD J

I1 (1) Indicator locations are in the general area of the NMP-I and J. A. FitzPatrick cooling water discharge structures.

1.

I1 d

7-4

TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (CONTROL) (3)

Cs-137_(pCilfiter)

Co-60 (pCi/liter)

_'YEA r

1 12

MX!~~~E~K YM AX.

%_-~v 1976 (1)

(1)(1)

(1)

(1) 1977 (2)

(2)

-(2)

,1978 LLD LLD LLD (2)

(2)

(2) 1979 2.5 2.5 2.5 LLD LLD LLD

,1980 LLD LLD iLLD 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

- 1990 LLD LLD LLD LLD

,LLD LLD 1991 LLD LLD LLD LLD LD LLD

,1992 LLD LLD

,LLD LLD

.LLD LLD 1993 LLD LLD

,LLD LLD LLD LLD

, 1994 LLD

.LLD

-LLD LLD LLD LLD 1995

.LLD LLD

.LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD.

LLD LLD LLD LLD LLD 1998 LLD LLD

'LLD LLD LLD

,LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001.

LLD

LLD (LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD

.2003 LLD LLD :

-LLD.

LLD LLD LLD 2004

-LLD L

,LLD LLD LLD LLD I

i r

(1)

No garmma analyses performed (not requr ed).

(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 1985-2004.

.>7-5

I I

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMNIPLE DATA SURFACE WATER (INDICATOR) (3)

I 1

Cs-137 (pCi/liter)

Co-60 (pi/liter) te r

. t*

-:1 a>-0\\47 c¢ %4O Bu l n g 1976 (1)

(1)(1()()()

1977 (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 LLLD LD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD LLD LLD LLD LLD LLD 1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD 2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD (1)

No gamma analyses performed (not required).

(2)

Data showed instrument background results.

(3).

Location was the J. A. FitzPatrick inlet canal.

I 1 I

I I

1 7-6

TABLE 7-7 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (CONTROL) (

-__.TRITIUM (pCi/liter) 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 190g.

310 242 1993 160 230

'188 1994 250 250 250 1995

230 230 230 1996 LLD LLD LLD 1997 LLD LLD

.LLD

.1998 190 190 190 1999 220 510 337 2000 196 237 212 2001 LLD LLD

.LLD

.2002 LLD LLD.

LLD 2003

'LLD LLD LLD 2004 LLD LLD LLD (1)

Control location is the City of Oswego drinking water for 1976 - 1984 and the Oswego Steam Station inlet canal for 1985 - 2004.

..7-7

I TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITLTUM (INDICATOR)(1 TRITIUM (pCi/liter) 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 1994 180 260 220

1995 320 320 320 1996 LLD LLD LLD 1997 160 160 160

1998 190 190 190 1999 180 270 233 2000 161 198 185 2001 LLD LLD LLD 2002 297

.297 297 2003 LLD LLD LLD 2004 LLD LLD LLD (1). Indicator location is the FitzPatrick inlet canal.

(2) Suspect sample'contamnination. Recollected samples showed normal levels of tritiuzn.

I1

.1 II Ii 7-8

TABLE 7-9 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (CONTROL)

GROSS BETA (pCi/m3) 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 199i

.0.006 0.028 0.014 1992 0.006 0.020 0.012 1993 0.007 0.022

-0.013 1994 0.008 0.025 0.015 1995 0.006 0.023 0.014

.1996 0.008 0.023 0.014 1997 0.006 0.025 0.013 1998

.0.004 0.034 0.014 1999 0.010 0.032 0.017 2000

,0.006 0.027 0.015

- 2001

-,0.006 0.034 0.016 2002 0.008 0.027 0.016 2003 0.004 0.032 0.015 2004 0.008 0.032 0.016 (1),. Locations used for 1977. 1984 were C offsite, Dl.offsite; D2 offsite, E offsite, F offsite, and G offsite.

Control location R-5 offsite was used for 1985--2004 (formerly C offsite location).

}7 - 9

I AL-1' TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (INDICATOR) (

_______ _GROSS BETA (pCi/m3) 1977 0.002 0.326 0.106 1978 0.01 0.34 0.11 1979 0.001 0.271 0.058 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 0.005 0.023 0.014 1991 0.007 0.033 0.015 1992 0.005 0.024 0.013 1993 0.005 0.025 0.014

-1994 0.006 0.025 0.015 1995 0.004 0.031 0.014 1996 0.006 0.025 0.013 1997 0.001 0.018 0.010 1998 0.002 0.040 0.015 1999 0.009 0.039 0.017 2000 0.005 0.033 0.015 2001 0.004 0.037 0.016 2002 0.006 0.026 0.016 2003 0.005 0.035 0.015 2004 0.003 0.037 0.016 (1)

Locations used for 1977 - 1984 were Dl onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite as applicable. 1985 - 2004 locations were R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

1 I

I 1I 1Il 1

I

.1 I

I.

J 7 - 10 I

TABLE 7-11 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (CONTROL) (1)

.~V IODINE-131 (pCi/Mi) 1976 0.01 5.88 0.60 1977 0.02 0.82

'0.32 1978 0.03 0.04 0.03 1979 LLD LLD LLD 1980 LLD LLD LLD 1981 LLD LLD LLD

.1982 0.039 -

0.039

.0.039 1983 LLD LLD LLD 1984 LLD LLD

.LLD 1985 LLD LLD LLD

.1986 0.041 0.332 0.151

-1987 LLD LLD LLD

1988 LLD

.LLD LLD

1989 LLD LLD

.LLD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD

.LLD

.1993 LLD LLD LLD 1994

. LLD LLD

.LLD 1995 LLD LLD LLD

'1996 LLD LLD LLD

.1997

.LLD LLD LLD

.-1998 LLD LLD LLD

.1999 LLD LLD LLD 2000 LLD LLD -

LLD

'2001 LLD LLD.

LLD

.2002 LLD LLD LLD

-.2003 LLD LLD LLD

.2004

LLD LLD LLD (I)

Locations Dl offsite, D2 offsite, E offsite, F offsite, and G offsite used for 1976.- 1984. Location R:5 offsite used for 1985 -2004.

.7-:11

1 TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (INDICATOR) (1)

IODI NE-131 (pC~im 3 )

1976 0.01 2.09 0.33 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 1979 LLD LLD LLD 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.042 0.016 1983 0.022 0.035 0.028 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0.023 0.360 0.119 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 1994 LLD LLD LLD 1995 LLD LLD LLD 1996 LLD LLD LLD 1997 LLD LLD LLD 1998 LLD LLD LLD 1999 LLD LLD LLD 2000 LLD LLD LLD 2001 LLD LLD LLD 2002 LLD LLD LLD 2003 LLD LLD LLD 2004 LLD LLD LLD (1)

Locations used for 1976 - 1984 were Dl onsite, D2 onisite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite, as applicable. Locations used for 1985 - 2004 were RI offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

I I

11I' 1

1 I

1 1

I I

.1 I

'I 7-12

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (CONTROL) (1)

Cs-137 (pCi/rm)

.__ 'Co-60 (pCi/mn)

[ YEA

.isMI.;..,AX.

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 1984 LLD LLD LLD 0.0004 0.0012 0.0008 1985 LLD LLD LLD LLD LLD LLD 1986 0.0075 0.0311

,0.0193 LLD LLD LLD

-'1987 LLD LLD fLLLD LD

-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 K LLD LLD 1993 LLD LLD

-LLD LLD LLD

.LLD.

1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLLD LD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD LLD LLD LLD LLD LLD 1998 L

LLD LLD LLD

.1999 LLD LLD :

LLD LLD LLD

.LLD 2000 LLD

.LLD

-LLD LLD LLD

, LLD 2001 LLD

,LLLD LD LLD

LLD,

-LLD 2002 LLD LLD "LLD' LLD LLD LLD 2003 LLD LLD D

. LLD LLD LLD 2004 LLD LLD

-LLD LLD '

LLD LLD (1)

Locations included composites of C, DI, E, F, and G offsite air monitoring locations for 1977 -1984. Sample location included only R-5,air monitoring location for 1985 - 2004.

7.- 13

- ml TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA l

AIR PARTICULATES (INDICATOR) (1)

,il1 Cs-137 (pCi/M3)

Co-60 (pCrm3) 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 L

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 I

jJ 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

.11 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD

-LLD LLD LLD LLD LLD

.1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD 0.0048 0.0048 0.0048 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD L

2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD (1)

Locations included composites of DI, D2, E, F, G, H, I, J, and K onsite air monitoring locations for 1977 -

1984. Locations included R-l through R4 air monitoring locations for 1985 - 2004..

L 14 L

TABLE 7-15 HISTORICAL ENVIRONMENTAL SAMPLE DATA

'ENVIRONMENTAL TLD (CONTROL) (2)

DOSE (mrem per standard month)

_"9i

'.~

)4 Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986' 1987 1988 1989 1990 1991 1992

'1993 1994 1995 1996 -

1997 1998 1999 2000 2001 2002 2003

.2004

' (1) 6.0 2.0 2.2 2.2 2.7 4.8 3.2 4.0 3.3

,3.3 3.8 3.5

.3.8 4.9 4.7 4.5 (4.4)*

5.3 (5.5)*

4.6 (4.6)*

4.4 (4.8)*

-2.9 (2.9)*

3.7 (3.7)*

-3.8 (3.8)*

2.6 (2.6)*

3.4 (3.4)*

3.1 (3.1)*

3.4 (3.4)*

3.7 (3.9)*

3.7 (3.7)*

3.6 (3.7)*

3.7 (3.7)*

3.6 (3.9)*

3.4 (3.4)*

3.3 (3.3)*

'(1) 7.3 6.7 6.2 6.9 8.9 6.0 7.2

- 8.0 4.7 5.7 5.8 5.9 6.1 7.2 8.2 7.6 (6.8)*

7.5 (7.2)*

6.6 (5.8)*

6.8 (6.8)*

6.4 (5.6)*

6.0 (5.9)*

5.4 (5.3)*

.5.0 (4.7)*

5.6 (5.2)*

5.0 (4.6)*

5.7 (4.9)*

5.6 (5.6)*

6.2 (5.2)*

5.6 (4.8)*

7.1 (4.7)*

7.3 (5.5)*

5.4 (5.0)*

5.5 (5.2)*

5.5 (4.'8)*

5.9 (5.9)*

, (1) 6.7 4.3 4.4 4.7 5.6

'5.5

.5.4 5.3 4.3 4.7 4.9 4.8 5.1 5.8 6.2 5.6 (5.4)*

6.3 (6.3)*

5.4 (5.2)*

5.6 (5.4)*

4.7 (4.6)*

4.8 (4.6)*

4.5,(4.3)*

4.1 (3.9)*

4.4,(4.3)*

4.1 (3.9)*

4.4 (4.2)*

4.3 (4.2)*

4.7 (4.6)*

.44 (4-2)*

4.6 (4.4)*

4.7 (4.3)*

4.4 (4.4)*

4.3 (4.1)*

4.2 (4.2)*

'4.3 (4.5)*

7 i

I I

i i

i I

(1)

Data not available.

(2). TLD #8, 14, 49, 111 and 113.where applicable.

( )* TLD result based 'on the ODCM required locations' (TLD #14 and 49).

,7-15

1 TABLE 7-16 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SITE BOUNDARY) (2)

DOSE (mrem per standard month)

,\\,S, t

'.'.~~~~~~4

^; Zg"} ,:

;+'i'M:'

3 I

1 1

1 L

Il Il Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 (1)

(1)

(1) 4.1 4.4 4.4 3.4 2.8 3.6 3.2 3.2 3.3 2.8 3.5 3.2 3.5 3.7 3.3 3.6 3.6 3.5 3.2 3.3 (1)

(1)

(1),

(1)

(1) 12.6 18.7 14.3 17.9 15.4 14.8 16.7 10.4 11.6

12.4 9.6 9.1 10.2 9.4 12.3.

10.0 10.3 9.4 8.9 10.8 (1)

(1)

(1) 6.2 7.0 6.1 6.4 5.9 5.8 5.7 4.8 5.3 5.2 5.4 5.9 5.4 5.8 5.5 5.7 5.4 5.4 5.6 I

I

-I L

A dL L

(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.

7 - 16 U

TABLE 7-17 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFFSITE SECTORS) (2)

-:DOSE (mrem per standard month) -

,1 TM.i tw

'ii.

-i

.§ M

V

..J.

zL LC1,.

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987

,1988

,1989 1990

.1991 1992 1993

1994 1995 1996 1997 1998 1999

,2000 2001

'2002 2003 2004 (1)

(1)

.(1)

(1)

(1)

(1)

(1)

,4.0 4.6 4.3 3.8 2.5 3.6 3.6 2.9 3.4 3.0 3.2 3.2 3.5 3.5

.6 3.4 3.6

-3.1 3.4 3.2 (1)

(1)

(1)

(1)

(1) 7.1

8.6 6.0 7.0 6.8 6.3 5.6 5.0 6.3 5.1 5.2 5.3

' 5.8 5.0 5.6

',6.6 5.4 5.3-4.8 6.7 (1)

(1)

(1)

(1)

'(1)

(1)

,(1)'

is(1) 5.0 6.0

, 5.2 5.3 4.9 4.7 4.5 4.1 4.5 4.0 4.2 4.2 4.5 4.2 4.4 4.5 4.4 4.2 4.1 4.4

-- Z i

..1 (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.

'7 -17

I ML_

1 TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SPECIAL INTEREST) (2) (3)

DOSE (mrem per standard month) f-..Y EA R.

byxv4; : i 1

.1 L

Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 (1)

(1)

(1)

(1)

(1) 3.9 4.8 3.5 3.9 2.1 3.2

.2.9 3.0 3.2 2.9 3.4 3.2 3.5 3.7 3.6 3.6 3.8 3.5 3.4 3.0 (1)

(1)

(1) 6.8 8.2 6.0 6.6 7.0 6.3 5.6 4.8 5.8 4.8 4.9 5.3 5.4 4.9 5.5 6.3 5.0 4.7 5.0:

5.9 (1)

(1)

(1) 5.3 6.1 5.1 5.3 4.8 4.7 4.4 4.1 4.5 4.0 4.3 4.2 4.5 4.3 4.4 4.5 4.3 4.1 4.2 4.2 11 I,

I ii II L

(1)

No data available (not required prior to 1985).

(2)

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

(3)

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

7-18 I]

-TABLE 7-19 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (ONSITE INDICATOR) (2)

-.DOSE (mrem per standard month)

. yEAdPCi'>;'vr

i r\\

-7 j

.A Preop(1)

(1)

(1) 1970 4.7 9.0 6.0 1971 1.5 7.7 4.7 1972 2.3 8.2 4.9 1973 3.0 24.4 6.6 1974 3:1 10.6 5.7 1975 4.6 16.0 7.3 1976 3.7 18.8 6.9 1977 3.0 15.3 5.7 1978 3.0 9.0 4.3 1979 2.7

)

8.3 4.3

-1980 3.9 12.0 5.3 1981 4.1 11.8 5.8 1982 3.9 13.0 6.3

-1983 5.0 16.5 6.9 1984 4.6 13.2 7.0

-1985 4.7 15.9 6.3 1986 4.7 16.1 7.0.

-1987 4.0 11.4 5.8

1988

- 4.4 11.9 6.0 1989 2.7 14.5 6.0 1990 3.6 12.9 5.5

'1991 3.2 11.6 5.1 1992 3.2 5.6 4.3

1993 3.1 13.6 5.2 1994 2.8 14.3 5.1 1995 3.5 28.6 6.2

-1996 3.1 32.6

.6.4 1997 3.5

-28.8

.7.7.

1998 3.6 28.8 6.2 1999 3.3

-28.4 6.6 2000 3.7 16.5 5.6 2001

¶ 3.8 14.5 5.6 2002 3.5 13.6 5.3 2003 3.2 12.9

,5.3 2004 3.3 13.2

5.4 (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 - 2004). Locations are existing or previous onsite environmental air monitoring locations.

7.-'19

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFFSITE INDICATOR) (2)

DOSE (mrem per standard month)

(;t

?

a.

i' In e-X~'....

g. A tgtag Ik KE 09!,,.';

Preop (1)

(1)

(1) 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 1978 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 1994 3.0 5.0 4.1 1995 3.9 5.7 4.4 1996 3.3 5.5 4.1 1997 3.7 6.2 4.7 1998 3.9 5.6 4.4 1999 3.8 7.1 4.6 2000 3.8 7.3 4.6 2001 3.7 5.9 4.5 2002 3.6 5.5 4.4 2003 3.1 5.5 4.4 2004 3.2 6.5 4.5 (1)

No data available.

(2)

Includes TLD numbers 8, 9, 10, 11, 12, and 13 (offsite environmental air monitoring locations).

7 - 20

TABLE 7-21 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (CONTROL) (2)

Cs-137 (pCi/liter)

' I-131 (pCi/liter)

,.', YEA

,i, 1.gi>.>2.; >,A2*

1f.______

IN'. W-1 }: MA.......

tu~EAN 1976 7.(1)

(1)

(1) 1978 2.4 7.8

-5.8 LLD LLD LLD 1979 LLD LLD LLD LLD LLD LLD

,1980 3.6

.5.6

.'4.5 1.4 1.4 1.4 1981 3.9 3.9.

3.9 LLD LLD '

LLD 1982 LLD LLD LLD LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD

,1984 LLD LLD

,LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD.

.LLD

-1986 5.3 12.4

'8.4 0.8 29.0 13.6 1987 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 1994 LLD LLD

LLD LLD LLD LLD 1995

LLD, LLD LLD LLD LLD,

LLD 1996 LLD LLD

.LLD.

,LLD

LLD

.LLD 1997

' LLD LLD

-,LLD LLD

LLD LLD 1998 LLD LLD :

..LLD LLD LLD

.LLD 1999 LLD.

LLD

'LLD

.LLD

,LLD

,LLD 2000 LLD LLD

-,,LLD

,,LLD LLD

. LLD 2001

LLD, LLD,

LLD

.-LLD

LLD

,; LLD 2002 LLD LLD

. LLD LLD LLD LLD 2003 L

LLD.

LLD

. LLD LLD LLD 2004 LLD LLD '

!LLD LLD.

LLD LLD (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.

7-21

TABLE 7-22 HISTORICAL ENVIROMNIENTAL SAMPLE DATA MIILK (INDICATOR) (1) 1.

I Cs-137 (pCi/liter)

I-131 (pCiliter)

"YEAR

.,MN, M

M M

4E.

vfAX.

1 'vE Ai.

1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 11.0 22.0 17.1 0.01 49.00 6.88 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 3.2 53.0 9.4 LLD LLD LLD 1980 3.2 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1983 3.3 10.9 7.2 LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 8.1 6.8 LLD LLD LLD 1988 10.0 10.0 10.0 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 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD LLD LLD 0.50 0.50 0.50 1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD 2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD (1)

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

1 I

I Il I

7-22 I

TABLE 7-23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (CONTROL) (

C s -1 3 7 (p C i lg (w e t))

1976

~E N -,...

()...-1

",)YEAR

~

EA'i~>

1977 (1)

(1)

.1978 (1)

-(1)

(1) 1979 (1)

(1)

(1) 1980 (3) 0.02 0.02 0.02 1981 LLD LLD LLD 1982 LLDLLD

.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 LLD 1990 LLD LLD LLD 1991

LLD LLD LLD 1992 LLD LLD LLD 1993 0.007 0.007 0.007 1994 LLD LLD LLD 1995 LLD LLD LLD 1996 LLD LLD LLD 1997 LLD LLD

LLD 1998 LLD LLD LLD 1999 LLD LLD LLD 2000 LLD LLD LLD 2001 LLD LLD LLD 2002 LLD LLD LLD 2003 LLD LLD LLD 2004 LLD LLD LLD (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 - 2004).

7

-23

I Il TABLE 7-24 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (INDICATOR) (1)

Cs-137 (pCilg (wet))

1976 (2)

LLD LLD LLD 1977 LLD LLD LLD 1978 LLD LLD LLD 1979 0.004 0.004 0.004 1980 0.004 0.060 0.036 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (3) 0.047 0.047 0.047 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 0.008 0.008 0.008 1989 0.009 0.009 0.009 1990 LLD LLD LLD 1991 0.040 0.040 0.040 1992 LLD LLD LLD 1993 LLD LLD LLD 1994 0.004 0.011 0.008 1995 0.010 0.012 0.011 1996 LLD LLD LLD 1997 0.012 0.012 0.012 1998 LLD LLD LLD 1999 0.008 0.008 0.008 2000 LLD LLD LLD 2001 LLD LLD LLD 2002 LLD LLD LLD 2003 LLD LLD LLD 2004 LLD LLD LLD (1)

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 - 2004).

I I

,1 11il I,

I iiI 1

A ii' 24

8.0 QA/QC PROGRAM 8.1 PROGRAM DESCRIPTION The Nine Mile Point Unit 1 (NMP1) Offsite Dose Calculation Manual (ODCM), Part 1, Section DSR 4.6.21 and the Nine Mile Point Unit 2 (NMP2) ODCM, Part 1, Section D 3.5.3 requires that the licensee participate in an Interlaboratory Comparison Program.

The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected'and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures-that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the ODCM requirements for an Interlaboratory Comparison Program, NMP utilizes the James A. Fitzpatrick Nuclear Power Plant (JAFNPP)

Environmental Laboratory, who has engaged the services of two independent laboratories to provide quality assurance comparison samples. -The two laboratories are Analytics, Incorporated (Analytics) in Atlanta, Georgia and the U.S. Department of Energy's Environmental Measurements Laboratory (EML) in New York City.

-Analytics supplies sample media as blind -sample spikes, -which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed using standard laboratory procedures. The results are submitted to Analytics, which issues a statistical summary report. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance for Analytic's sample results.

In addition to the Analytics program, the JAFNPP Environmental Laboratory participated in the EML Quality Assessment Program'(QAP). EML supplies sample media as blind sample spikes to approximately 127 laboratories worldwide'.- these samples, containing a spiked am6unt of low level activity, are analyzed using standard laboratory procedures. The results are submitted to the EML for statistical evaluation.

Reports are provided to each participating laboratory, which' provide an evaluation of the laboratory's performance.

In 2004, the program provided by EML was scaled back as a result of the laboratory'being reorganized under the 'Federal Department' of Homeland Security as part of the Science and Technology directorate. Under the reorganization; the laboratory no longer provided spiked cross check samples to commercial -laboratories. 'The fJAFNPP Environmental' lab was eligible to participate in the first of two annual quality assessment programs (QAP-0403) in 2004 'before the program was restructured.

8-1

I I

8.2 PROGRA"M SCHEDULE ala l[?SIPLEPROVIDER2

`

Y-?TPEARLY Water Gross Beta 0

1 Water Tritium I

1 2

Water 1-131 2

0 2

Water Mixed Gamma 2

1 3

Air Gross Beta 2

1 3

Air 1-131 2

0 2

Air:

Mixed Gamma 2

1 3

Milk 1-131 2

0 2

Milk Mixed Gamma 2

0 2

Soil Mixed Gamma 1

0 1

Vegetation Mixed Gamma I

0 1

TOTAL SA.MIPLE INVENTORY 17 5

22 I

ID

'I Ii I

8.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The evaluation method for the QA sample results is dependent on the supplier of the sample.

The sample evaluation methods are discussed below.

8.3.1 ANALYTICS SAMPLE RESULTS Samples provided by Analytics are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC Result) to the Vendor Laboratory Known value (Reference Result).

An Environmental Laboratory analytical result is evaluated using the following calculation:

The value for the error resolution is calculated.

I I

I

'I L

L 8-2

The error resolution =

Reference Result Reference Results Error Using the appropriate row under the Error Resolution column in Table 8.3.1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

L Ratio Q

OC Result L

of Agreement; Reference Result l

If the value falls within the agreement interval, the result is acceptable.

TABLE 8.3.1 L

[s---' :ERORRESOLIJTIONs4 :

nt'HRATIO.OFAiXREE'MENT !;':

i 3

.0.4-2.5 3.1 to 7.5 0.5-2.0 7.6 to 15.5 0.6-1.66 L

15.6 to 50.5 ; ; v0.75-1.33 50.6 to 200 0.8-1.25

>200 0.85-1.18 l

Again, this acceptance test'is generally referred to as the "NRC method". The acceptance criteria is contained in JAFNPP Procedure DVP-04.01 and was taken from the Criteria of Comparing Analytical Results (UiSNRC) and Bevington, P.R., Data Reduction and Error.Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). The NRC method generally results in an acceptance range of approximately 4 25% of the Known value when applied to sample results from L

the Analytics Inc. Interlaboratory Comparison Program. This method is used as the: procedurally required assessment method and requires the generation of a nonconformity report when results are L

unacceptable.

8.3.2 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

The laboratory's analytical performance is evaluated by EML based on the historical analytical capabilities for individual analyte/matrix pairs. The statistical criteria for Acceptable Performance, "A", has been chosen by EML-to be between the 15th and 85th percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements. The L

8-3

'ii-

.1 Acceptable With Waming criteria, "W", is between the 5th and 15th percentile and between the 85th and 95th percentile. In other words, the middle 70% of all reported values are acceptable, while the other 5th-15th (10%) and 85th-95th percentiles (10%) are in the warning area. The Not Acceptable criteria, "N", is established at less than the 5th percentile and greater than the 95th percentile, that is, the outer 10% of the historical data.

Using five years of historical analytical data, the EML, determined performance results using the percentile criteria summarized below:

Result Cumulative Normalized Distribution Acceptable ("A")

15% - 85%

Acceptable with Warning ("W")

5% - 15% or 85% - 95%

Not Acceptable ("N")

<5% or >95%

8.4 PROGRAM RESULTS

SUMMARY

]

The Interlaboratory Comparison Program numerical results are provided on Table 8-1.

8.4.1 ANALYTICS QA SAMUIPLES RESULTS Seventeen QA blind spike samples were analyzed as part of Analytics' 2004 Interlaboratory Comparison Program.

The following sample media were evaluated as part of the comparison I

program.

Air Charcoal Cartridge: I-131 Air Particulate Filter Mixed Gamma Emitters, Gross Beta Water: 1-131,MixedGammaEmitters,Tritium Soil: Mixed Gamma Emitters Milk: I-131,;Mixed Gamma Emitters

.1 Vegetation: Mixed Gamma Emitters The JAFNPP Environmental Laboratory performed 81 individual analyses on the seventeen QA samples. Of the 81 analyses performed, 80 were in agreement using the NRC acceptance criteria for a 98.8% agreement ratio.

I Sample non-conformities are discussed in Section 8.4.1.1.

[I

' I1 8-4

8.4.1.1 ANALYTICS SAMPLE NONCONFORMITIES Analytics Sample E4166-05, Zn-65 in Soil Nonconformity No. 2004-01 A spiked mixed' gamma in 'soil sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample'contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified. Eight of the nine'radionuclides were quantified within the acceptable range. The mean result for Zn-65 was determined to be outside the QA Acceptance Criteria resulting in a sample nonconformity. The soil sample was analyzed five times using four different detectors with the mean Zn-65 result reported as 334-pCi/kg. The known result for the sample was 262 pCi/kg as determined by the supplier. One of the five reported results was 292 pCi/kg that resulted in an agreement when compared to the known value of 262 pCi/kg with a ratio of 1.11. The remaining 4 individual results were outside the acceptance criteria and had ratios to the known value that ranged from 1.29 to' 1.34. All of the analysis had relatively high associated counting errors, which ranged from 8.3% to 18.3%.

An evaluation of the Zn-65 'result was performed. The spectrum and peak search results were examined with no anomalies identified. Zn-65 decays by electron capture with a 244 day half-life and'a gamma ray energy of 1115 KeV with a yield of 50.75%. No significant secondary gammna energies are produced in the Zn-65 decay scheme. The average net count rates of the five analyses were low and ranged from a high of 1.50 counts per minute to a low of 0.93 counts per minute. The low activity in the sample resulted in high associated counting errors as noted above.

In soil samples, Ra-226 is a naturally occurring radionuclide which produces a secondary peak at 1120 KeV. The.presence of Ra-226 (1120 KeV) and Zn-65 (1115 KeV) in the sample resulted in a doublet peak formation in this region of the spectrum. In most cases, the computer algorithm can differentiate the two adjacent peaks and correct for interferences from overlapping (doublet) peaks. 'In these sampl spectrums, there was a low number of total counts in the 1110 to 1130 KeV aiea' 'The low count rate and subsequent poor peak shape made it difficult for the algo'rithin to select an exact background for determining the total counts in the peak. Ini additio'n,'lowir 'count'rate-made it difficult to-define the two peaks contained in the doublet. In addition to'the complicated nature of the spectrum, the settling of the soil m'edia in ihe counting geormetry'may have effected the himi o'geneity of the sample and

'produced a positive bias in the collective sample results.

To determine if this was a programmatic or systematic error'inhrerent to the software/analysis system, an extent of condition was performed using anothler'spiked sample result for any similar. nonconformities.

8-5

I In 2004, eleven spiked samples were analyzed which contained certified concentrations of Zn-65 and other radionuclides. This sample set included four additional soil samples.

The results are as follows:

I Ib L

2004 Zn-65 Results E4053-05 Water pCi/liter 146+/-6 143+/-5 1.03 E-4319-05 Water pCi/liter 165+/-6 178+/-6 0.93 E-4054-05 Filter pCi/filter 98+/-5 95+/-3 1.03 E-4320-05 Filter pCi/filter 141+/-6 120+/-4 1.18 E-4321-05 Milk pCilliter 155+7 167+/-6 0.93 E-4 165-05 Milk pCilliter 94+/-5 9913 0.94 E4168-05 Vegetation 260+/-17 232+/-8 1.12 E-4154-09t Soil pCi/kg 289+/-20 262+/-5 1.10 E4051-09*

Soil pCi/kg 289+/-17 252+/-6 1.15 E4253-09*

Soil pCi/kg 239+/-12 248+6 0.96 E4373-09*

Soil pCi/kg 336+/-22 329+/-6 1.02 Mean Ration = 1.04 I

1L 1,

ID I

I Provided by laboratory client, NOT reported in Annual Report t

Duplicate sample of E4165-05 provided by laboratory client, NOT reported in Annual Report A duplicate sample of this sample (E-4166-05) was submitted to the laboratory as a blind spike (E4154-09).

This sample was made from the exact. supplier stock as the non-conformity sample. The Zn-65 result for this duplicate sample was in full agreement with the known value on all five of the analysis performed. The mean Zn-65. result for the duplicate sample was 289+/-20 pCi/Kg for a ratio to the known value of 1.10 (See results in the table above). The mean ratio for all eleven Zn-65 results was 1.04. The mean ratio for the four soil sample Zn-65 results was 1.06. The mean ratio value for the eleven samples noted above and each individual ratio values for, each of Zn-65 results are excellent indicators that the routine measurement of Zn-65 in environmental media is accurate. These results demonstrate that I

I LI1 liD 8-6 I

there is no systematic error or bias for the analysis of Zn-65 in soil or other environmental sample media. No corrective action was implemented as a result of this non-confornity.

8.4.2 ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

In 2004, JAFNPP Environmental Laboratory participated in the EML Quality Assessment Program, QAP-0403. Sample sets consisted of the followihg sample media:

Water: Gross Beta, Mixed Gamma Emitters Water: Tritium Air Particulate Filter: Mixed Gamima Emitters/Gross Beta A total of 5 samples containing 8 individual radionuclides were evaluated for the samples included in' QAP-0403. Using the EML acceptance criteria, 8 of 8 radionuclides analyses (100%) were evaluated to be acceptable. Results for the EML Quality Assessment Program are contained'in Table 8-1 and results for all participants can be viewed on-line at www.eml.doe.gov. A summary of the JAFNPP Environmental Laboratory results is as follows:

Air 4

4 0

Water 4

4 0

Total 8

8 0

Percentage 100%

0.0%

There were no sample nonconformities with samples analyzed for the EML program 8-7

I TABLE 8-1 INTERLABORATORY INTERCONIPARISON PROGRAM Gross Beta Analysis ofAir Particulate Filters (pCi/filter)

I~EDIUINE:.;

ANAYSIS

.>JAFRESUT()$

V IRATIOA(3)"

6/17/2004 E-4164-05 AIR 159.8 3.1 pCi/filter GROSS 158.5 t

3.1 166.0 X

5.5 0.95 A

BETA 155.7 3.1 160 55 09 Mean 158.0

1.8 12/9/2004 E4376-05 AIR 223.2 i

2.1 pCi/filter GROSS 219.7 2.1 225.0 7.5 99 A

BETA 222.4 t

2.1 Mean=

221.8 1.2 (1) Results reported as activity *1 sigma.

(2) Results reported as activity 42 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

I 1a Jt I1 II Il ill 11

.1 II 8-8

TABLE 8-1 (Continued)

LNTERLABORATORYINTERCOMPARISON PROGRAM_

Tritium Analysis Water (pCi/liter)

VAFRENERENCET lTE!2 ID N O' 2

,MEDlIJM ;

AJ E

T 3/25/2004 E-4052-05 WATER 4681 171 pCi/liter H-3 4699 171 4700 300 1.00 A

4716 171 Mean =

4699

99 I

(1) Results reported as activity I1 sigma. Sample analyzed by JAFNPP Environmental Laboratory l(2) Results reported as activity *2 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

.I, 8-9

1 TABLE 8-1 (Continued)

INTERLABORATORY INTERCONIPARISON PROGRANI Io ine Analysis of Water, Air and Milk DAE' INO MD1Mt

iWMALYSIS..

JFESL()i"R~A~i2ŽfAT1O(3Y' 3/25/2004 E-4053-05 WATER 92.9

+

1.9 pCi/liter 94.1

+

1.7 I-131**

90.7 L

I 8 90.2 t

3.0 1.03 A

Mean 92.6 +/-

1.0 6/17/2004 E-4167-05 AIR 83.8 4

5.6 pCi/cc 1-131 78.3 5.8 83.1

+/-

2.8 0.97 A

Mean 80.8

+/-

3.1 6/17/2004 E-4165-05 MILK 53.0 1

1.7 pCi/liter 1-131**

55.4 2.2 58.2 4

1.9 0.95 A

56.9

2.0 Mean=

55.1

+/- 0.8 9/16/2004 E-4322-05 AIR 72.4 4

5.2 pCi/cc 1-131 75.0 t

4.8 76.7 4

2.6 0.96 A

73.5

4.9 Mean 73.6 2.9 9/16/2004 E-4319-05 WATER 69.7

+/-

1.1 pCi/liter M31**

67.2

+/-

1.2 70.8

+/-

2.4 0.98 A

71.7 1.0 Mean =

69.5 +/- 0.6 9/16/2004 E-4321-05 MILK 74.1

+/-

1.2

~~~pCi/liter.7 1-131**

72.7 1 1.1 83.5 4

2.8 0.89 A

75.1

+/-

1.3 Mean 74.0 0.7 (1) Results reported as activity +/-I sigma.

(2) Results reported as activity 42 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(+) Sample provided by Analytics, Inc.

(*) Result determined by Resin Extraction/Gamma Spectral Analysis.

(A) Evaluation Results, Acceptable.

1 I

~11 IIn I

.I L

1L I

11 8-10

TABLE 8-i (Continued)

INTERL'ABORATORY INTERCONIPARISON PROGRAM Gamma nalisis sWater (pCilliter)

IT X7

,: REFERENr'v

-'AN.

X ATE AL RATI I I 4

3/25/2004 E-4053-05 WATER pCi/liter Ce-141 81.5 86.2 I.

89.0 80.4 Mean=' 84.3 10.4 1.1 I 9.4 7.8 4.0 85.0,

2.8 0.99 A

362.0 +/-

48.1-325.0

+/-

6.6 Cr-51 431.0 47.7 326.0 10.9 1.09 A

-- 305.0 35.8 Mean= 355.8 ;+19.2

.83.3 1.4 Cs-134 85 5 7 89.7 3.0 0.94 A

84.5 5.7 Mean=

84.6 +/-

3.1 -

174.0

+/- 9.3 Cs-137 178.0 1.1 185.0 6.2 0.95 A

174.0

+/-

9.0 Mean 175.3

+/-

4.3 116.0

+

7.9 116.0

+/-

1.0 Mn-54 116.0

+/-

7.8 114.0 3.8 1.02 A

-115.0

+/- 5.9 Mean 115.8

+

3.1 66.3 4

8.8 59.5 1.1 Fe 64.4 '

8.1 56.7 1.9 1.15 A

70.9 5.7 Mean 65.3 3.3 161.0 15.2 149.0 1.7 Zn-65 124.0 I 14.5 143.0 4.8 1.03 A

151.0 10.8 Mean 146.3 5.9 143.0 6.8 153.0 0.8 Co-60 145.0 6.6 153.0 5.1 0.97 A'

153.0 5.0 Mean= 148.5

2.7 Co-58

. I -

114.0 116.0

'118.0 I

'112.0 Mean= 115.0 4

8.3 4*

1.0

+

7.8

+

5.9

+

3.2 112.0 3.7 1.03, A L

(1) Results reported as activity *1sigma.

(2) Results reported as activity +2 sigma.

(3) Ratio'- Reported/Analytics (See Section 8.3).

L

(*)

Sample provided by Analytics, Inc.

I (A) Evaluation Results, Acceptable 8-11

I TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRA. I Gamma Analysis Water (pCi/liter) 1i IO-RA T I 0EFRC 9/16/2004 E-4319-05 WATER pCi/liter Ce-141 251.0 257.0 255.0 Mean = 254.3 9.1 8.6 7.8 4.9.

1.02 250.0

+/-

8.3 A

I 1

I 163.0 30.9 Cr-51 209.0 31.8 223.0 7.5 0.81 A

173.0 30.4 Mean= 181.7 t

17.9 91.6

+

5.8 Cs-134 90.0 +/-

9.2 96.4 3.2 0.97 A

97.9

+/-

5.4 Mean =

93.2 4.1 217.0 7.2 Cs-137 206.0 68 215.0 7.2 0.98 A

206.0 6.6 Mean = 209.7 4.0 182.0 6.9 Mn-54 169.0 4

6 181.0 6.1 0.97 A

175.0

+/-

6.3 Mean = 175.3 3.8 83.6 6.6 Fe-59 99.6 6.4 91.6 3.1 1.02 A

96.7 4*

6.1 Mean=

93.3

+/-

3.7 178.0 +/-

11.4 Zn-65 156.0

+

10.2 178.0 5.9 0.93 A

161.0

+

10.1 Mean = 165.0 6.1 117.0 4

4.4 Co-60 132.0 4.5 125.0 4.2 0.98 A

119.0 4.1 Mean = 122.7

+/-

2.5 I

L L

Co-58 100.0 89.4 90.2 Mean=

93.2

4 4*

5.6 5.2 5.0 3.1 94.6 4

3.2 0.99 A

J J. ____________

.L (1) Results reported as activity *1 sigma.

(2) Results reported as activity -L2 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

L A

L L

8-12

TABLE 8-1 (Continued)

INTERLABORATORY.INTERCOMIPARISON PROGRAAI Gamma Analysis otAir Particulate Filters (pCilfilter)

JAF.ENVI

, -iREFERENCL l it[

.iDAE ¢.3/4iID. NO~. 1 >MEDIUM

'JA.~

s*,

F

.RJMES LT (l) ^R ;:ss'; ri,*

()

44RAT1Oj.En0(3) '

7~YIATE~I

~

I

{AY S

~

i;~i' 3/25/2004 E-4054-05 FILTER -

pCi/filter Ce-141 51.1 52.8 57.2 Mean =

53.7 4

2.9

+

3.6 2.9 1.8 56.6 i

1.9 0.95 A

192.0

+

21.1 214.0. 4* 25.4 270 72 09 Cr-51 194.0 19.7 217.0 7.2 0.92 A

. Mean = 200.0 12.8 55.0 4.1 134 59.7 2.0 0.88 A

Cs1 450.3 4.0 Mean=

52.6 +/- 2.5 116.0

+

5.0 Cs-137 11.0 4

123.0 4.1 0.98 A

116.0

+

4.9 Mean= 121.0 +/-

3.1 -

79.2 +/-

4.6 Mn-54 7704 4

75.8 4

2.5 1.02 A

76.0*

4.3 Mean=

77.5 2.8 33.7 4.7 Fe-59

37.

5.7 37.8 1.3 0.98 A

40.2 4-4.7 Mean 37.0 2.9 87.7 8.6 Zn1090 11.1 95.1 3.2 1.03 A

Zn 65-97.7 8.3 Mean=

98.1

+/- 5.4 105.0

+/- 4.3 Co-60 95 3 5.0 102.0 3.4 0.96 A

91.3 4

4.0 M ean =

97.3

+/-

2.6 I__

Co-58 78.3 4

. 71.6 4

71.9 4.6.

5.5

.4.4 74.6 4

2.5 0.99 A

-Mean =

73.9 4

2.8 A.

a.

I (1) Results reported as activity *I sigma.

(2) Results reported as activity *2 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

7..

8-13

. 12L-1 TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRANI Gamma Analysis of Air Particulate Filters (pCi/filter) 1

]l DI L'

YI A.f 4

l1 sRATIO(3) 9/16/2004 l E-4320-05 FILTER pCi/filter 183.0

+

5.0 Ce-141 195.0

+

173.0' Mean = 183.7

+/-

5.7

5. 1 3.0 168.0 5.6 1.09 A

11 11 132.0 4

20.9 Cr-51 128.0 21.5 150.0 5.0 0.89 A

142.0 21.7 Mean = 134.0 i

12.3 60.4 X

8.4 Cs-134 74.8 L 5.3 64.9 i

2.2 1.08 A

76.0 4.8 Mean =

70.4

3.7 148.0 5.7 Cs-137 155.0 4 6.2 145.0 4.8 1.04 A

149.0

5.3 Mean = 150.7 3.3 154.0

+/-

6.0 Mn-54 135.0

+

5.3 122.0 4.1 1.18 A

Mean= 144.0

+/-

3.3 78.7

+

6.1 Fe-59 78.7 6.3 61.6 2.1 1.25 A

Mean =

76.9

+/-

3.4 144.0 10.4 Zn-65 145.0*

10.8 120.0 4.0 1.18 A

135.0

.9.1 Mean=

141.3

5.8 87.0

+/- 3.8 Co-60 73

+

84.3 2.8 0.96 A

82.3 3.5 M ean=

81.0 2.1 d

L

.L II

.[

Co-58 77.0 69.2 64.2 Mean =

70.1 4

4.8 4.9

+

4.2

+/-

2.7 63.7 2.1 1.10 A

(1) Results reported as activity *I sigma.

(2) Results reported as activity -2 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

ID 1

8-14

TABLE 8-1 (Continued)

INTERLABORATORY INTERCONIPARISON PROGRAM Gamma Analysis Mlilk (pCi/liter)

J ENV. 1 r:l-a;

l

~DA~jIi~N~J j&MDIM AALYIS~ ~1AFRESLT 11

, j~ LBvRE 2

FERENCE~o(3 6/17/2004 E-4165-05 MILK pCi/liter Ce-141 161.0 157.0 153.0

+/-.6.1 11.1 7.6.

Mean =

155.0 10.9 141.0 6.4 166.0

+/-

8.2 155.5 3S I57.0

+

5.2 0.99 A

274.0 30.6.

.143.0 47.8 239.0 31.3 Cr-51

.228.0 44.0 228.0 s

7.6 0.95 A

225.0 28.6 195.0 37.9 Mean =

217.3

+/-

153

_..~96.6 4.6 96.6 h

7.6 92.5 4.2 Cs-134 97.9 7.2 101.0

+

3.4 0.96 A

104.0.

4.6 93.6 5.8

-Meah=

96.9:

2.4 -

147.0 t

5.5 134.0 8.8 147.0 5.5 Cs-137 141.0 4

8.3 156.0 5.2 0.92 A

151.0 5.4 139.0 i

6.4

.Mean=

143.2 4

2.8 68.9 4.2 64.4 7.4 r

65.9 4.6

-Mn-54:-v-62.4 6.3 70.5 s

2.4 0.97 A 71.7 4.2 76.9 5.2 M ean =

68.4

k 2.2 37.5 5.1 45.3 9.1 53.6 -

6.3 Fe-59 50.3 7.9 44.5

+

1.5 1.12 A

.60.3 5.4

'51.8 5.8*

Mean 49.8 t

2.8 r

113.0 8.9 76.5 14.0

.n.65 95.4 9.4 Zn-65 88.2 13.5 99.3 4 3.3 0.94 A

90.6 8.5 99.2 10.3 Mean =. 93.8 4.5 172.0 I

4.7 172.0

.7.7 180.0 4.9 Co-60 160.0

k. 7.1 172.0 t

5.7 1.00 A 175.0 4.7 I -

-175.0 5.3 Mean =

172.3 4

2.4 Co-58 45.2 38.4,.

40.7 I

45.3 40.9 49.8

+/-

Mean =

43.4 3.8 -

6.3 3.7 5.9 -

3.7 4.6 1.9 46.2 1.5 0.94 A

. (I) Results reported as activity t1 sigma (3) Ratio = Reported/Analytics (See Section 8.3).

(A)

(2) Results reported as activity *2 sigma.

(*) Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

8-15

I TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAMNI Gamma Analysis Milk (pCi/liter) 1 Ri.'

1.1D IF lt.0' RSL RAT 1 l

-3 l

11 9/16/2004 E-4321-05 MILK pCi/liter Ce-141 226.0 220.0 230.0 Mean = 225.3 8.5

+ 9.1

+

8.6

+

5.0 235.0 4

7.8 0.96 A

I 256.0 4

35.5 Cr-51 212.0 +/-

32.7 210.0

7.0 0.97 A

Mean= 204.3 20.3 84.0

+/-

9.5 Cs-134 81.4 9.6 90.6 3.0 0.89 A

75.7

+/-

11.2 Mean=

80.4

+/-

5.9 193,0

+/-

6.6 Cs-137 188.0

+

6.8 202.0 6.7 0.92 A

179.0

+

7.9 Mean 186.7 4.1 180.0 6.5 Mn-54 185.0 6.9 171.0 5.7 1.04 A

169.0

7.9 Mean 178.0 4.1 90.6 6.4 92.6

7.2 Fe-59 86.1 2.9 1.09 A

97.5

8.6 Mean 93.6

4.3 173.0 11.4 Zn-65 150.0*

11.4 167.0

+/-

5.6 0.93 A

143.0

13.3 Mean=

155.3 7.0 108.0

+/- 4.2 Co-60 116.0

+/-

5 118.0 +/-

3.9 0.98 A

122.0

+/- 5.5 Mean= 115.3

+/-

2.8 1

I 11 d'

lI' I

I Co-58 83.7 88.4 81.5 Mean =

84.5 5.2

+ 5.7-

+/-

6.3

+

3.3 89.0

+/- 3.0 0.95 A

Ll (1)

Results reported as activity *I sigma.

(2) Results reported as activity +/-2 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

Ll LI LA LI 8-16

TABLE 8-1 (Continued)

INTERLABORATORY INTERCONIPARISON PROGRAM1 Gamma Analysis Soilf(pCi/gram)

ADTEw IO.

ASt.TLl 6/17/2004 E-4166-05

- SOIL pCi/gram Ce-141 0.378 0.493.

0.503 0.467

+/-

0.414

+/-

Mean =

0.451

k 0.034 0.025 0.043 0.022 0.032 0.015 1.09 A

0.413 A 0.014 0.502 +/-

0.162 0.617 0.110 Cr-51 0.825 +/-

0.110 0.601 A

0.020 1.20 A

0.932 +/-

0.183 Mean 0.719 +/-

0.054 0.302 +/-

0.028 0

244i +/-

0.032 Cs--134 0.370 0.033 0.267 A

0.009 1.11 A

0.286 0.016 0.279 +/-

0.262 Mean 0.296

. 0.012 0.568

+/-

0.034

.0.525

+/-

0.022 0.480' 0.041 Cs-137 0.516

+

0.017 1.02 A

.0.534 +/-

0.020 0.518 4-0.032 Mean 0.525 0.012 0.227.*.

0.025 0.215 0.016 0.178 0.032 Mn-54 0.186 1

0.006 1.08 A

0.203 0.015 0.183 0.024 Mean 0.201 0.011O 0.149' 4 0.049

.0.129

+/-

0.031 Fe-59 0.120

+/-

0.026 0.117

0.004 1.08 A

0.101 0.037 Mean 0.126 0.013 0.342 0.044 0292 0.029 0.338 0.062 Zn-65 0.262

+

0.009 1.27 D

0.348 0.029 0.352 '-

0.046 NC #2004-Mean'=

0.334 +/-

0.019 (ll 0.539 +/-

0.026 0.461 i

0.017 Co-60 0°466 0.01 0.453 '

0.015 1.08 A

.. ____0.500 n

0.0250.4

,.Mean

=

0.488 0 011

. I

I. -

Co-58 Mean =

0.127.*+ 0.022 0.140 0.016 0.112 +/-

0.028 0.112 +/-

0.014 0.079

.0.022 0.114 0.009 0.122 :

0.004 0.93 A

I I

I J.

J (1) Results reported as activity :1 sigma.

(2) Results reported as activity 42 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(NC) Non Conformity number

-.- (*) Sample provided by Analytics, Inc.

(A) 'Evaluation Results, Acceptable.

(D) Evaluation Results, Not Acceptable 8-17

I.9-li TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Vegetation (pCUgram)

I

~DATE~

-I O'

jEIM.

ANLSS

.JAF RESULT (1):{

4LB

)Z

~RAT1O(-3)-,

6/17/2004 1 E4168-05 VEGETATION pCi/gram Ce-141 0.371 0.370 +/-

0.346 4 0.330 :

Mean=

0.354

0.010 0.022 0.025

.0.020 0.010 0.365 0.012 0.97 A

I I

I 0.478

0.054 0.511 0.011 Cr-51 0.670

0.013 0.531 0.018 1.07 A

0.617 4

0.010 Mean =

0.569

0.051 0.234 0.007 0.256

0.020 Cs-134 0.278 0.025 0.235

+/-

0.008 1.07 A

0.238

0.019 Mean=

0.252

0.010 0.353

0.008 0.381

0.022 Cs-137 0.340

0.025 0.363 4

0.012 1.01 A

0.388

0.021 Mean=

0.366

0.010 0.179

0.006 0.200

0.018 Mn-54 0.154

0.023 0.164 0.005 1.07 A

0.170 +

0.017 Mean 0.176

0.009 0.085

0.010 0.108 0.025 Fe-59 0.140

0.028 0.104 4 0.003 1.06 A

0.107

0.022 Mean 0.110

0.011.

0.251 0.014 0.300

0.039 Zn-65 0.240 :L 0.047 0.232 0.008 1.12 A

0.249 +/-

0.031 Mean 0.260 +/-

0.017 0.405

0.007 0.390 0.019 Co-60 0.409

0.025 0.400 0.013 1.01 A

0.412 0.019 Mean 0.404 0.010 1I I

1 I

I ill1 Co-58 0.106

0.114 +/-.

0.121 *-

0.101

+/-

Mean =

0.111

0.006 0.016 0.022 0.016 0.008 0.108 0.004 I

1.03 A

1.

(1) Results reported as activity *1 sigma.,

(2) Results reported as activity -2 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-18 LI

TABLE 8-1 (Continued)

INTERLABORATORY INTERCONIPARISON PROGRAMI Gamma Analysis Water (Bq/liter) 14 1

DAE -ID-NO.:!~-.

I.EDIMU;C1 i~~ANALYS S~ ~

RSL I 7

~ AB,`(Y:'{ ~AAI(3) 3/1/2004 QAP-0403 WATER 52.5

+

2.9 Bq/liter 47.4

+

2.7 Cs50.0 2.8 52.0 e

2.7 0.972 A

Cs13 52.2

3.4 50.7

2.6 Mean 50.5 1.3 156.1

3.7 161.3 4

3.9 159.5 3.8 Co-60 163.2 i

5.9 A0975 A

159.. +4.7 159.5

.3.7

_______Mean~

159.2-1.8 (1) Results reported as activity.+/-1 sigma.

(2) Results reported as activity *2 sigma.

(3) Ratio = Reported/EML(See Section 8.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results,-Acceptable.

8-19

-1 1

TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (Bq/filter)

-,'AF-ENVL'

~;

-R ERI

_T

.IDNO.;

' MEDIUNI gANALYS1S

(`

JAFRESXMT(1)I L

RiATIO,(3)~

3/1/2004 QAP-0403 FILTER 35.0 1

0.5 Bq/filter Co-60 36.1 0.5 35.4 0.85 1.006 A

35.6

E 0.4

_Mean 35.6 0.3 19.4 0.4 Cs-134 20.3 0.4 18.2 4 0.40 1.104 W

20.2 0.4

_ Mean 20.1 0.2 27.9 0.5 Cs-137 28.0 0.5 26.4 0.86 1.057 A

27.8 0.4

_M ean =

27.9

0.3 Z

_i4 (1) Results reported as activity.*l sigma.

(2) Results reported as activity $2 sigma.

(3) Ratio = Reported/EML (See Section 8.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A) Evaluation Results, Acceptable.

(W) Acceptable with Warning.

I I

11 1

l 8-20

TABLE 8-1 (Continued)

INTERLABORATORY INTERCO0NIPARISON PROGRAM Gross Beta'Analysis of' Water (Bq/liter) i i

,",ENV,.:~

j'REFERENCE.-`r 3/1/2004 QAP-0403 WATER' GROSS 1109 1

30 Bqlliter BETA 9

1115 30 1170 117 0.944 A

1090 30 Mean=

1105 17 L

(1)

Results reported as activity *1 sigma.

(2) Results reported as activity +/-2 sigma:

(3) Ratio = Reported/EML (See Section 8.3).

(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.

K((A) Evaluation Results, Acceptable.

8-'21

I

- I IL -

I1 TABLE 8-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAMNI Tritium Analysis Water (Bq/llter).

f s 03~~;>QmS i-J X'~~

~~EERE NCMfl 2 @eDATE,^tls *lDNO.;.'.,~~

~~tz1MEDIU~~

~~'ANLYSIS~~

~~' Y~~

~~'JAF ESUT(1)4 j4 ; YLAE(2)I 1RATIQ(3);,~~

~~3/1/2004 QAP-0403 WATER H-3 233.4~~

+

~~7.8 Bq/liter 224.9 7.8 2382 0 0~~

~~79 186.6 3.3 1.25 A 232.0 t~~

~~7.9 235.3 8.0 Mean= 232.8 ** 3.5 (1) Results reported as activity +/-1 sigma.~~

~~(2) Results reported as activity *2 sigma.~~

~~(3) Ratio = Reported/EML (See Section 8.3).~~

~~(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.~~

~~(A) Evaluation Results, Acceptable.~~

~~I I~~

~~I J~~

~~Li L~~

~~I I~~

~~L L~~

~~IlL L~~

~~L 8-22~~

~~L TABLE 8-1 (Continued)~~

~~INTERLABORATORY INTERCONIPARISON PROGRAM Gross Beta Analysis of Air (Bq/filter)~~

~~[A ENV;-~~

~~RESUL T(1)~~

)

~~3/1/2004 QAP-0403 AIR GROSS 2.8~~

~~§ 0.08 Bq/filter BETA 2.6 0.08 2.7~~

~~0.08 2.6 0.08 2.85 0.28 0.94 A~~
2.6 0
0.08 2.7
~~0.08 M e a n =~~
2.7 0.0 5 L
(1) Results reported as activity *1 sigma.
L (2)
Results reported as activity -2 sigma.
(3) Ratio = Reported/EML (See Section 8.3).
(*) Sample provided by Environmental Measurements Lab., Dept. of Energy.
L (A) Evaluation Results, Acceptable.
8-23
-~
Al h
~~8.5 REFERENCES~~
8.5.1 Semi-Annual Report of the Department of Energy, Office of Environmental Management, Quality i
Assessment Program, EML 621, June 2004.
8.5.2 Radioactivity and Radiochemistry, The Counting Room: Special Edition, Caretaker Publications, Atlanta, Georgia, 1994.
1 8.5.3 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).
8IL 1-1.
L L
.8-24 LI

ML051400270

Contents

Text

Subject:

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

SUMMARY

8.5 REFERENCES

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ML051400270

Text

Subject:

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

SUMMARY

8.5 REFERENCES

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