ML031470800

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2002 Annual Radiological Environmental Operating Report. Table of Contents Through Section 3
ML031470800
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 12/31/2002
From: Montgomery B
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031470800 (56)
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Constellation I Energy Group Nine Mile Point Nuclear Station NINE MILE POINT NUCLEAR STATION, LLC 2002 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

NINE MILE POINT NUCLEAR STATION, LLC ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2002 - December 31, 2002 For NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket Number 50-220 And NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50410

TABLE OF CONTENTS Page 1.0 EXECUIIVE

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 DESCRPION 3-1 3.1 Sample Collection Methodology 3-13 3.2 Analyses Performed 3-19 3.3 Sample Locations 3-19 3.4 Land Use Census 3-30 3.5 Changes to the REMP Program 3 3.6 Deviation and Exceptions to the Program 3-32 3.7 Statistical Methodology 3-34 3.8 Compliance with Required Lower irmits of Detection (LLD) 3-39 3.9 Regulatory Dose Limits 341 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 5-20 5.3 Conclusion 5-43 5.4 References 5-45 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 84 8.5 References 8-27 ii

LIST OF TABLES Page Table 3.0-1 Required Sample Collection and Analysis, Nine Mile Point Unit 1 3-2 Table 3.0-2 Required Sample Collection and Analysis, Nine Mile Point Unit 2 3-6 Table 3.3-1 Environmental Sample Locations 3-21 Table 3.8-1 Required Detection Capabilities For Environmental Sample Analysis, 3-40 Lower Limit of Detection (LLD)

Table 6-1 Concentrations of Gamma Emitters in Shoreline Sediment Samples 6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples 6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples 6-6, Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples 6-7 Table 6-5 Environmental Airborne Particulate Samples - Off-site Stations 6-12 Table 6-6 Environmental Airborne Particulate Samples - On-site Stations 6-14 Table 6-7 Environmental Charcoal Cartridge Samples -- Off-site Stations 6-16 Table 6-8 Environmental Charcoal Cartridge Samples - On-site Stations 6-18 Table 6-9 Concentrations of Gamma Emitters in Monthly Composites of JAF/NMPNS 6-20 Site Air Particulate Samples Table 6-10 Direct Radiation Measurement Results 6-35 Table 6-11 Concentrations of iodine-131 and Gamma Emitters in Milk 6-38 Table 6-12 Concentrations of Gamma Emitters in Food Products 6-41 Table 6-13 Milk Animal Census 6-42 Table 6-14 2002 Residence Census 6-43 Table 7-1 Historical Environmental Sample Data, Shoreline Sediment (Control) 7-1 Table 7-2 Historical Environmental Sample Data, Shoreline Sediment (Indicator) 7-2 Table 7-3 Historical Environmental Sample Data, Fish (Control) 7-3 Table 7-4 Historical Environmental Sample Data, Fish (Indicator) 7-4

.i.i

LIST OF TABLES (continued)

Page Table 7-5 Historical Environmental Sample Data, Surface Water (Control) 7-5 Table: 7-6 Historical Environmental Sample Data, Surface Water (indicator) 7-6 Table 7-7 Historical Environmental Sample Data, Surface Water Tritium (Control) 7-7 Table 7-8 Historical Environmental Sample Data, Surface Water Tritium (Indicator) 7-8 Table 7-9 Historical Environmental Sample Data, Air Particulate Gross Beta (Control) 7-9 Table 7-10 Historical Environmental Sample Data, Air Particulate Gross Beta (Indicator) 7-10 Table 7-11 Historical Environmental Sample Data, Air Radioiodine (Control) 7-11 Table 7-12 Historical Environmental Sample Data, Air Radioiodine (Indicator) 7-12 Table 7-13 Historical Environmental Sample Data, Air Particulates (Control) 7-13 Table 7-14 Historical Environmental Sample Data,. Air Particulates (Indicator) 7-14 Table 7-15 Historical Environmental Sample Data, Environmental TLID (Control) 7-15 Table 7-16 Historical Environmental Sample Data, Environmental TLD (Site Boundary) 7-16 Table 7-17 Historical Environmental Sample Data, Environmental TID (Off-site Sectors) 7-17 Table 7-18 Historical Environmental Sample Data, Environmental TLD (Special Interest) 7-18 Table 7-19 Historical Environmental Sample Data, Environmental TID 7-19 (On-site Indicator)

Table 7-20 Historical Environmental Sample Data, Environmental TLD 7-20 (Off-site Indicator)

Table 7-21 Historical Environmental Sample Data, Milk (Control) 7-21 Table 7-22 Historical Environmental Sample Data, Milk (Indicator) 7-22 Table 7-23 Historical Environmental Sample Data, Food Products (Control) 7-23 Table 7-24 Historical Environmental Sample Data, Food Products (Indicator) 7-24 Table 8-1 Interlaboratory Intercomparison Program (Gross Beta, Tritium, Iodine 8-10

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

LIST OF FIGURES Page Figure 3.3-1 New York State Map 3-25 Figure 3.3-2 Off-site Environmental Station and TLD Location Map 3-26 Figure 3.3-3 On-site Environmental Station and TID Location Map 3-27 Figure 3.3-4 Milk Animal Census, Milk Sample Location and Surface 3-28 Water Sample Location Map Figure 3.3-5 Nearest Residence, Food Product, Shoreline Sediment, 3-29 Fish Sample, Location Map V

~~~~~~~~~~~~~~~~~~

SECTION 1.0 EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

The Annual Radiological Environmental Operating Report is published pursuant to Section 6.9.1.d of the Nine Mile Point Unit 1 Technical Specifications, Section 5.6.2 of the Nine Mile Point Unit 2 Technical Specifications and 10 CFR 50.4.

This report describes the Radiological Environmental Monitoring Program (REMP), the implementation, 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 Unit 1 and Unit 2 ODCM.

The REMP is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 10CFR20 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 2002, samples collected as part of the required monitoring program demonstrated that there is no significant radiological impact from the operation of either the Nine Mvile Point Unit 1 (NNTv1) or Nine Mile Point Unit 2 (NMP2) facilities. Cesium-137 was detected in several aquatic pathways at low levels and is directly attributed to fallout from past weapons testing. Tritium was detected in two surface water samples near the detection limit and are not considered to be plant related. The 2002 results for all pathways sampled are consistent with the previous five year historical results and exhibit no adverse trends.

In summary, the analytical results from the. 2002 REMP demonstrate that the routine operation of the 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 continue 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 continues to demonstrate that the dose to a member of the public as a result of the operation of NMP1 and 1-1

NMP2 remains significantly below the federally required dose linits specified in 10CFR20 and 40CFRl90.

1-2

SECTION

2.0 INTRODUCTION

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 6.9.1.d to License DPR-63, Docket No. 50-220 for the Nine Mile Point Nuclear Station Unit 1 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 2002.

Nuclear Regulatory Commission (NRC) amendment #176 to the Niie Mile Point Unit 1 (NMP1) Technical Specifications, implemented on November 07, 2002, resulted in the relocation of the Radiological Environmental Monitoring Program (REMP) requirements from the NMP1 Technical Specifications to the NMP1 Offsite Dose Calculation Manual (ODCM). Nine Mile Point Unit 2 (NMP2) REMP requirements also reside within the NMP2 Offsite Dose Calculation Manual (ODCM). Throughout this report references will be made to TS/ODCM. This refers to the NMP1 Technical Specifications (TS) REMP requirements in effect from January 01, 2002 through November 06, 2002, the subsequent NMP1 TS amendment #176., effective November 07, 2002 and the NMP2 ODCM REMP requirements.

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, Nine Mile Point Unit 1, a 615 Megawatt Boiling Water Reactor (BWR) began full power operation. In 1975, the James A. FitzPatrick Nuclear Power Plant, a 883 Megawatt Boiling Water Reactor (BWR), currently owned and operated by Entergy, began full power operation. In 1985, the individual station Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which is common to both plants.

Data generated by the Radiological Environmental Monitoring Program (REMP) is shared, but each utility reviews and publishes their own annual report. In 1988, the Nine Mile Point Unit 2 reactor, a 1080 Megawatt BWR located between Unit 1 and Fitzpatrick, began full power operation. In 1995 Nine Mile Point Unit 2 was uprated to 1207 megawatts.

In summary, three Boiling Water Reactors, which generate approximately 2705 megawatts, have operated collectively at the Nine Mile Site since 1988. A large data base of 2-1

environmental results for the exposure pathways has been collected and analyzed to determine the effect from reactor operations.

2.2 SITE DESCRIPTION The Nine Mile Point Site is located on the southeast shore of Lake Ontario in the town of Scriba, approximately 7 miles east of the city of Oswego. The nearest metropolitan area is located approximately 23.8 miles southeast of the site. The reactors and support buildings occupy a small shoreline portion of the 900 acre site, which is partially wooded. 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 The objectives of the Radiological Environmental Program are to:

1. Measure and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls of radioactive material sources.
2. Monitor natural radiation levels in the environs of the NMPNS site.
3. Demonstrate compliance with the various environmental conditions and requirements of applicable state and federal regulatory agencies, including Technical Specifications and 40CFR Part 190.

2-2

SECTION 3.0 PROGRAM DESCRITON

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

.conducted every year. The NMPNS REMP consists of sampling and analysis of vaious media that include:

  • Shoreline Sediment
  • Fish
  • Surface Waters
  • Air
  • Milk
  • Food Products In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TIDs). 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 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).

3-1

TABLE 3.0-1 OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway Sampling and Collection Type-of Analysis and Number of Samples (a) and Locations and/or sample Frequency (a) Frequency AIRBORNE

a. Radioiodine and Samples from five locations; Continuous sampler operation Radioiodine Canisters Particulates with sample collection weekly analyze once/week for Three samples from off-site locations in different or as required by dust loading, I-131.

sectors of the highest calculated site average D/Q (based whichever is more frequent.

on all site licensed reactors). Particulate Samplers Gross beta radioactivity One sample from the vicinity of an established year following filter change (.

round community having the highest calculated site Composite (by location) average D/Q (based on all site licensed reactors). for gamma isotopic analysis (c)once per 3 One sample from a control location 10-17 miles distant months, (as a minimum).

and in a least prevalent wind direction (d).

b. Direct Radiation () 32 stations with two or more dosimeters to be placed as Once per 3 months Gamma dose once per 3 follows: an inner ring of stations in the general area of months.

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.

(1) At this distance, 8 wind rose sectors are over Lake Ontario 3-2

[.'. . I I t t t. lt I . I lII , I I[ I t I I

TABLE 3.0-1 (Continued)

OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples (a) and Locations and/or sample Frequency (a) Frequency WATERBORNE

a. Surface (0 One sarmple upstream Composite sam?le over 1 Gamma isotopic analysis (c) month period g once/month. Composite One sample from the site's downstream cooling water for once per 3 months intake . , tritium analysis.
b. Sediment from One sample from a downstream area with existing or Twice per year Gamma isotopic analysis (c)

Shoreline potential recreational value.

INGESTION

a. Milk Samples from milk sampling locations in three locations Twice per month, April -, Gamma isotopic (c)and within 3.5 miles distance having the highest calculated December (samples will be I-131 analysis twice per site average D/Q. If there are none, then one sample collected in January - March month when animals are on from milking animals in each of 3 areas 3.5 - 5.0 miles if I-131 is detected in pasture (April-distant having the highest calculated site average D/Q November and December of December); once/month at (based on all site licensed reactors) the preceding year) other times (January -

I . . .

I March) if required Qne sample from a milk sampling location at a control location (9-20 miles distant and in a least prevalent wind direction) d)

  • ~~~~~~~~ I - I f -- - I

TABLE 3.0-1 (Continued)

OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples (a)and Locations and/or sample Frequencv (a) Freauencv

b. Fish One sample each of two commercially or recreationally Twice per year Gamma isotopic analysis (c) important species in the vicinity of a plant discharge on edible portions twice area ) 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 Once per year during harvest Gamma isotopic (c)analysis (such as vegetables) grown nearest to each of two season of edible portions (Isotopic different off-site locations of highest calculated site to includelI-131 or a average D/Q (based on all licensed site reactors) separate I-131 analysis may be performed) once One sample of each of the similar broad leaf vegetation during the harvest season grown at least 9.3 - 20 miles distant in a least prevalent wind direction 3-4 I I I I I I I I I I I . I I

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

(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.

3-5

TABLE 3.0-2 OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or sample Frequency Frequency AIRBORNE

a. Direct Radiation ( 32 routine monitoring stations either with 2 or more Once per 3 months Gamma dose once per 3 dosimeters or with 1 instrument for measuring and months recording dose rate continuously, placed as follows:

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 (1) 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.

3-6 I I I I I I I I I I I I . I. I i

( ( ( I ( f I I I I TABLE 3.0-2 (Continued)

OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or sample Frequencv Freauencv

b. Airborne Samples from five locations: Continuous sampler operation Radioiodine Canister Radioiodine and with sample collection I-131 analysis weekly Particulates Three samples from offsite locations close to the site weekly, or more frequently if boundary (within one rmile) in different sectors of the required by dust loading Particulate Sampler highest calculated annual site average ground-level D/Q Gross beta radioactivity (based on all site licensed reactors). analysis following filter change (d)and gamma One sample from the vicinity of an established year- isotopic analysis (e)of round community having the highest calculated annual composite (by location) at site average ground-level D/Q (based on all site licensed least quarterly.

reactors).

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

a. Surface One sample upstream (C)f one sample from the site's Composite sample over 1- Gamma isotopic analysis' downstream cooling water intake (. month period . (e) once per month and tritium analysis quarterly.

3-7

TABLE 3.0-2 (Continued)

OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and. Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or sample Frequency Frequency

b. Ground Samples from one or two sources if likely to be Quarterly grab sample Gamma isotopic (e) and affected (h), tritium analysis quarterly
c. Drinking One sample each of one to three of the nearest water Composite sample over a 2- 1-131 analysis on each supplies that could be affected by its discharge ( week period(g when I-131 composite when the dose analysis is performed; calculated for the monthly composite otherwise. consumption of the water is greater than 1 mrem per year. ° Composite for gross beta and gamma isotopic analyses ()

monthly. Composite for tritium analysis quarterly.

d. Sediment from One sample from a downstream area with existing or Twice per year Gamma isotopic analysis(c)

Shoreline potential recreational value.

3-8 t I I I I I I I I . I

( - I(II ( ( l ( ( ( ( ( l ( l ( ( I TABLE 3.0-2 (Continued)

OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or sample Freciuencv Freauency INGESTION

a. Milk Samples from Milk Sampling Locations in three Twice per month, April - Gamma isotopic (e)and locations within 3.5 miles distance having the highest December (samples will be 1-131 analysis twice/month calculated site average D/Q (based on all licensed site collected January - March if when animals are on reactors). If there are none, then 1 sample from Milk I-131 is detected in November pasture (April -

Sampling Locations in each of three areas 3.5 - 5.0 and December of the December); once per miles distant having the highest calculated site average preceding year). month at other times D/Q (based on all licensed site reactors). (January - March if required).

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

b. Fish One sample each of two commercially or recreationally Twice per year Gamma isotopic analysis ()

important species in the vicinity of a plant discharge on edible portions twice area . per year.

One sample of the same species in areas not influenced by station discharge (c) 3-9

TABLE 3.0-2 (Continued)

OPERATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or sample Frequency Frequency

c. Food Products One sample of each principal class of food products At time of harvest (m) Gamma isotopic (e) analysis from any area that is irrigated by water in which liquid of edible portions (isotopic plant wastes have been discharged (). to include I-13 1).

Samples of three different kinds of broad leaf vegetation Once per year during the (such as vegetables) grown nearest to each of two harvest season.

different offsite locations of highest calculated site average D/Q (based on all licensed site reactors).

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

3-10 3-10 I I I I lI I I I I I I I I I I I

NOTES FOR TABLE 3.0-2 (a) Deviations are permitted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unavailability* or malfunction of automatic sampling equipment. If specimens are. unobtainable because sampling equipment malfunctions, effort shall be made to complete corrective action before the end of the next sampling period. All deviations from'-the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times it may'not be possible or practical to continue 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 appropriate substitutions may be made within 30 days in the Radiological Environmental Monitoring Program.

(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, integiating dosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one-phosphor, and two or m'iore 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the previous yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(e) 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 contanination.

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

  • Seasonal unavailability is meant to include theft and uncooperative residents.

3-11

NOTES FOR TABLE 3.0-2 (j) Analysis for 1-131 may be accomplished by Ge-Li analysis provided that the lower limit of detection (LLD) for 1-131 in water samples can be met. Doses shall be calculated for the maximum organ and age group.

(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.

(1) This Control applies only to major irrigation projects within 9 niles of the site in the general "downcurrent' direction.

(m) If harvest occurs more than once a 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.

3-12

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 1 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 four 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 immediately 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.

3-13

3.1.3 SURFACE WATER Surface water samples are taken from the respective inlet canals of the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) and the NRG'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 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.

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 is presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canal samples and from the City of Oswego drinking water supply. The latter three locations are not required by the TS/ODCM. These locations are optional sample points which are collected and analyzed to enhance the surface water sampling program. Monthly composite samples from these three locations are analyzed for gamma enitting nuclides and quarterly composite samples are analyzed for tritium.

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

Sampling for ground water and drinking water, as found in Section D.3.5.1 of the Nine Mile Point Unit 2 Offsite Dose Calculation Manual (ODCM), was not required during 2002. There was no Groundwater Source in 2002 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties were suitable for Contamination; therefore, Drinking Water was not a dose pathway during 2002.

3-14

3.1.4 AIR PARTICULATE / IODINE The air sampling stations required by the TS/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 Nine Mile Point Nuclear Station Unit 2 Reactor Building. The TS/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 TS/ODCM is a 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 TS/ODCM required locations, there are ten additional -sampling stations. Six of these sampling stations are located within the site boundary and are designated as On-Site Stations Dl, G, H, I, J, and K. These locations are within the site boundary of the NMPNS and JAFNPP. One air sampling station is located Off-Site in the southwest sector in the vicinity of the City of Oswego and is designated as Station G Off-Site.

Three remaining air sampling stations are located in the ESE, SSE, and S sectors and range in distance from 7.2 to 9.0 miles. These are designated as Off-Site Stations D2, E and F respectively.

Each station collects airborne particulates using glass fiber filters (47 millimeter diameter) and radioiodine using charcoal cartridges (2x1 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.

3-15

3.1.5 TLD (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamna 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 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:

TLD Geographical Category Description On-site TLDs placed at various locations within the Site Boundary and are not required by the TS/ODCM. (TLD locations comprising this group are: 3, 4, 5, 6, 7*, 23*, 24, 25, 26, 27, 28, 29, 30, 31, 39, 47, 18*, 103, 106 and 107)

Site Boundary 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 TSIODCM. (TLD locations comprising this group are: 75*, 76*, 77*, 78*, 79*, 80*, 81*, 82*, 83*, 84, 7*, 18*,

85*, 86*, 87* and 23*)

Off-site Sector 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 TS/ODCM. (TLD locations comprising this group are 88*, 89*,

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

3-16

TLD Geographical Category Description Special Interest TLDs placed in Special Interest areas of high population density and use. These TLDs are located at or nearlarge industrial sites, schools, or nearby towns or communities. This category is required by the TS/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)

Control 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 TS/ODCM. (TLD locations comprising this group are 14*, 49*, 8, 111, 113)

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

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 ILK Milk samples are routinely collected from six farms during the year. These farms include five indicator locations and one control location. Samples are collected twice per month, April through December, and each sariple is analyzed for gamma emitting radionuclides-and I-131.

Samples are collected in January, February and March in-the event that I-131 is detected in November and December of the preceding year.

3-17

The selection of milk sample locations is based on maximum deposition calculations (D/Q).

Deposition values are generated using average historical meteorological data for the site. The TS/ODCM require three sample locations within 5.0 miles of the site with the highest calculated deposition value. During 2002 there were no milk sample locations within 5.0 miles that were suitable for sampling based on production capabilities. There were however, five optional locations beyond five miles that were sampled as indicator locations for the 2002 routine milk sampling program.

The TS/ODCM also requires that a sample be collected from a location nine to twenty miles from the site and in the least prevalent wind direction. This location is in the SSW sector and serves as the control 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 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.)

3.1.7 FOOD PRODUCTS (VEGETATION)

Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broad leaf vegetation (edible or inedible) are collected from two different indicator garden locations. Sample locations are selected from gardens identified in the annual 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.

3-18

3.2 ANALYSES PERFORMED The majority of environmental sample, analyses are performed by the James A. FitzPatrick

Nuclear Power Plant (JAFNPP) Environmental Laboratory. Tritium analyses for samples collected during 2002 were performed by Framatome ANP Environmental Laboratory. The following samples are analyzed at the JAFNPP Environmental Lab:
  • Shoreline Sediment - gamma spectral analysis
  • Fish - gamma spectral analysis
  • Surface Water Monthly Composites - gamma spectral analysis /I-131
  • Air Particulate Filter - gross beta
  • Air Particulate Filter Composites - gamma spectral analysis
  • Airborne Radioiodine - gamma spectral analysis
  • Direct Radiation - Thermoluminescent Dosimeters (ILDs)
  • Milk- gamma spectral analysis and l-131
  • Food Products (Vegetation) - gamma spectral analysis
  • Special Samples (soil, food products, bottom sediment, etc.) - gamma spectral analysis 3.3 SAMPLE LOCATIONS Section 3.3 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.

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

This table contains the following information:

  • Sample Medium
  • Location 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).
  • Location description
  • Degrees and distance of the sample location from the site.

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3.3.1 LIST OF FIGURES

  • Figure 3;3 Off-Site Environmental Station and TLD Locations Map
  • Figure 3.3 On-Site Environmental Station and TID Locations Map
  • Figure 3.34 - Milk Animal Census, Milk Sample, and Surface Water Locations Map
  • Figure 3.3 Nearest Residence, Food Product, Fish and Shoreline Sediment Sample Locations Map 3-20

( ( r '( I F ( f I I ( I I I I TABLE 3.3-1 2002 ENVIRONMENTAL SAMPLE LOCATIONS "1 I ~: 1 "'~"~ DEGUES1&

Shoreline Sediment 05* Figure 3.3-5 Sunset Bay - - 800 at 1.5 miles 06 Figure 3.3-5 Langs Beach,' Control 2300 at 5.8 miles Fish 02* Figure 3.3-5 Nine Mile Point Transect 3150 15 0.3 miles 03* Figure 3.3-5 FitzPatrick Transect '. 550 at 0.6 niles 00* Figure 3.3-5 Oswego Transect 235° at 6.2 miles Surface Water 03* Figure 3.3-4 FitzPatrick Inlet 70 at 0.5 riles 08* Figure 3.34 Oswego Steam Station Inlet 235 'at 7.6 miles 09 Figure 3.3-4 NMP Unit 1 Inlet 275 0 at 0.3 miles 10 Figure 3.3-4 Oswego City Water 240 0 at 7.8 miles 11 Figure 3.3-4 NMP Unit 2 Inlet' 304 0 at 0.1 miles Air Radioiodine and Particulates R-1* Figure 3.3-2 R-1 Station, Nine Mile Point Road 880 at 1.8 miles R-2* Figure 3.3-3 R-2 Station, Lake Road 104 at 1.1 miles R-3* Figure 3.3-3 R-3 Station, Co. Rt. 29 132 'at 1.5 miles R-4*' Figure 3.3-3 R-4 Station, Co. Rt. 29 143 0 at 1.8 miles,'

R-5* Figure 3.3-2 R-5 Station, Montario Point 42 0at 16.4 miles Dl Figure 3.3-3 DI On-Site Station 69 at 0.2 miles G Figure 3.3-3 G On-Site Station 250 0 at 0.7 miles' Figure 3.3-3 Figure 3.3-3 H On-Site Station. 70 0 at 0.8 miles I Figure 3.3-3 I On-Site Station 98 °at 0.8 miles Figure 3.3-3 J On-Site Station 110 at 0.9 miles K Figure 3.3-3 K On-Site Station 132 at 0.5 miles G Figure 3.3-2 O Off-Site Station, Saint Paul Street 225 0 at 5.3 miles D2 Figure 3.3-2 D2 Off-Site Station, Rt. 64 117 0 at 9.0 niles E Figure' 3.3-2 E Off-Site Station, Rt.'4 160 0 at 7.2 miles F PiAure 3.3-2 F Off-site Station, Dutch Ridge Road 190 at 7.7 miles 3-21

TABLE 3.3-1 (Continued) 2002 ENVIRONMENTAL SAMPLE LOCATIONS U.6 Ql M, I1"i 3 iRINT WS Figure 3.3-3

-K'04Q'W Dl On-Site Station ON MS ic'. -Fff W OW z' DEGREES&,E_,'

690 at 0.2 miles Thermoluminescent Dosimeters (TLD) 4 Figure 3.3-3 D2 On-Site Station 1400 at 0.4 miles 5 Figure 3.3-3 E On-Site Station 175° at 0.4 miles 6 Figure 3.3-3 F On-Site Station 2100 at 0.5 miles 7* Figure 3.3-3 G On-Site Station 250° at 0.7 miles 8 Figure 3.3-2 R-5 Off-Site Station 420 at 16.4 miles 9 Figure 3.3-2 DI Off-Site Station 800 at 11.4 miles 10 Figure 3.3-2 D2 Off-Site Station 1170 at 9.0 miles 11' Figure 3.3-2 E Off-Site Station 1600 at 7.2 miles 12 Figure 3.3-2 F Off-Site Station 1900 at 7.7 miles 13 Figure 3.3-2 G Off-Site Station 2250 at 5.3 miles 14* Figure 3.3-2 Southwest Oswego - Control 2260 at 12;6 miles 15* Figure 3.3-2 West Site Boundary 2370 at 0.9 miles 18* Figure 3.3-3 Energy Information Center 2650 at 0.4 miles 19 Figure 3.3-2 East Site Boundary 810 at 1.3 miles 23* Figure 3.3-3 H On-Site Station 70° at 0.8 miles 24 Figure 3.3-3 I On-Site Station 980 at 0.8 miles 25 Figure 3.3-3 J On-Site Station 1100 at 0.9 miles 26 Figure 3.3-3 K On-Site Station 1320 at 0.5 miles 27 Figure 3.3-3 North Fence, JAFNPP 600 at 0.4 miles 28 Figure 3.3-3 North Fence, JAFNPP 680 at 0.5 miles 29 Figure 3.3-3 North Fence JAFNPP 650 at 0.5 miles 30 Figure 3.3-3 North Fence JAFNPP 570 at 0.4 miles 31 Figure 3.3-3 North Fence NMP-1 276° at 0.2 miles 39 Figure 3.3-3 North Fence NMP-1 2920 at 0.2 rniles 47 Figure 3.3-3 North Fence JAFNPP 690 at 0.6 miles 49* Figure 3.3-2 Phoenix, NY - Control 1700 at 19.8 miles 51 Figure 3.3-2 Oswego Steam Station, East 2230 at 7.4 miles 52 Figure 3.3-2 Fitzhugh Park Elementary School, East 2270 at 5.8 miles 53 Figure 3.3-2 Fulton High School 1830 at 13.7 miles 54 Figure 3.3-2 Mexico High School 1150 at 9.3 miles 55 Figure 3.3-2 Pulaski Gas Substation, Rt. 5 750 at 13.0 miles 3-22 I I I I I - _ [ 1. . [., t I I I [ I I I I I

( I I I [ I ( I l I I I I I I II I TABLE 3.3-1 (Continued) 2002 ENVIRONMENTAL SAMPLE LOCATIONS

'jlNiEMP I' 4 jG Thermoluminescent 56* Figure 3.3-2 New Haven Elementary School 1230 at 5.3 miles Dosimeters (TLD) 58* Figure 3.3-2 County Route 1 and Alcan 2200 at 3.1 miles (Continued) 75* Figure 3.3-3 North Fence, NMP-2 50 at 0.1 miles 76* Figure 3.3-3 North Fence, NMP-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, JAFNPP 90° at 1.0 miles 79* Figure 3.3-3 County Route 29 1150 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-1 3150 at 0.1 miles 87* Figure 3.3-3 North Fence, NMP-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 -: 111° 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 51A 156 0 at 4.8 miles 92* Figure 3.3-2 Maiden Lane Road 1830 a 4.4 miles 93* Figure 3.3-2 County Route 53 2050 at 4.4 miles 94* Figure 3.3-2 Country Route 1 and Kocher Road 2230 at 4.7 miles 95* Figure 3.3-2 Lakeshore Camp Site 237° at 4.1 miles 96* Figure 3.3-2 Creamery Road 199° 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 3-23

TABLE 3.3-1 (Continued) 2002 ENVIRONMENTAL SAMPLE LOCATIONS mr*

Thermolurninescet 0x4 tv,~ ~~~ ~ ~ ~ ~ ~ ~~~~~~~~~ DSACi1 Thermoluminescent 105 Figure 3.3-3 Lakeview Road 198° at 1.4 miles Dosimeters (TLD) 106 Figure 3.3-3 Shoreline Cove, West of NMP-1 2740 at 0.3 miles (Continued) 107 Figure 3.3-3 Shoreline Cove, West of NMP-1 2720 at 0.3 miles 108 Figure 3.3-3 Lake Road 104° at 1.1 miles 109 Figure 3.3-3 Lake Road 1030 at 1.1 miles 111 Figure 3.3-2 Sterling, NY - Control 2140 at 21.8 miles 113 Figure 3.3-2 Baldwinsville, NY - Control 1780 at 24.7 niles Cows Milk 76 Figure 3.3-4 Indicator Location 1320 at 5.2 miles 50 Figure 3.34 Indicator Location 930 at 8.2 miles 55 Figure 3.34 Indicator Location 950 at 9.0 rniles 60 Figure 3.34 Indicator Location 90° at 9.5 miles 4 Figure 3.34 Indicator Location 1130 at 7.8 miles 77* Figure 3.3-4 Control Location 1910 at 13.9 miles Food Products 133* Figure 3.3-5 Indicator Location 960 at 1.7 miles 132* Figure 3.3-5 Indicator Location 1150 at 1.9 miles 143 Figure 3.3-5 Indicator Location 1360 at 1.7 mniles 342 Figure 3.3-5 Indicator Location 960 at 1.7 miles 145* Figure 3.3-5 Control Location 2250 at 15.6 rniles Table Notes:

(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline

  • Sample location required by TS/ODCM 3-24 I [ I I [ I [ I I I I I I I I I

Figure 3.3.-4 NEW YORK STATE MAP NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit -I Nine Mile Point Nuclear Station Unit -2 James A. FitzPatriek Nuclear Power Plant c-( )

MAP OF OSWEGO COUNTY New York SCALEor MILS FIGURE 3. 3 - 2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS C02

I I I I , ,1 I I I I I ,

II I I I ENE Sunset WSW Northeast FIGURE 3.3-3 /, I . SE ONSITE ENVIRONMENTAL STATION AND TLD LOCATIONS l I l l KEY: l C ENVIRONMENTAL STATIONS 1U'

MAP OF OSWEGO COUNTY New York SCAL Or NILE" L -

I }<

_S,i 1 W U ./ 177 L r j s-ifO __

E t s y!tt -

MAP OF OSWEGO COUNTY 4 New York scALE or MILES 7

I I

I m

I It E! -iS=UF1l R 81--

I -

K

~~_

CA' ia I

v l-_

.-. ~~~~~~~~~~~~~~...

1 1 1

3.4 LAND USE CENSUS The TS/ODCM require that a milch animal census and a residence census be conducted annually. Mlch 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. The census is done once per year in the summer. It is conducted 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 Service was also contacted 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 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 TS/ODCM if broadleaf vegetation sampling and analysis is performed.

3-30

3.5 CHANGES TO THE REhlP PROGRAM The following changes were implemented during the 2002 sampling program:

A. Food Product/Vegetation The food product/vegetation sample locations are evaluated each sampling season based on meteorology and product availability. The following sample location changes were implemented in 2002:

  • The sampling program did not utilize food product vegetation locations (Battles, Hail, Lee, and Vitullo) sampled in 2001 for the 2002 sampling program. These locations were not sampled due to the general unavailability of samples.
  • The 2002 Land Use Census identified a new garden location that was sampled as an optional location due to limited produce availability. The garden is located in the east sector (96°) at a distance of 1.7 miles.

There were no changes to the program outlined by the TS/ODCM.

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3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM Exceptions to the 2002 sample program concern those samples or monitoring requirements

'which are required by the TS/ODCM. This section satisfies the reporting requirements of Section D6.9.1.d of the Nine Mile Point Unit 1 Offsite Dose Calculation Manual and Section D4.1.2 of the Nine Mile Point Unit 2 Offsite Dose Calculation Manual.

A. TS/ODCM PROGRAM DEVIATIONS The following are deviations from the program specified by the TS/ODCM:

I

1. The air sampling pump at the R-1 Environmental Sampling Station was inoperable for approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the sample period of 2/5/02 through 2/12/02. The inoperability of the smpling pumps was caused by a power outage which was weather related. No corrective action was implemented.
2. The air sampling pumps at the R-1 and R-2 Environmental Sampling Stations were inoperable for approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on 5/9102. The inoperability of the sampling pumps was caused by an electrical power outage initiated by Niagara Mohawk Power for line maintenance as a result of a fallen tree. No corrective action was implemented.
3. The air sampling pumps at the R-1 and R-2 Environmental Sampling Stations were inoperable for approximately 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> on 11/2/02. The inoperability of the sampling pumps was caused by a power outage which was weather related.

No corrective action was implemented.

4. Thermoluminscent Dosimeter (TLD) number 91 which is required by the TS/ODCM was discovered to be missing during the 2002 first quarter changeout. A new TLD was placed at that location.

B. AIR SAMPLING STATION OPERABILITY ASSESSMENT The TS/ODCM required air sampling program consists of 5 individual sampling locations. The collective operable time period for the air monitoring stations was 3-32

43,787 hours0.00911 days <br />0.219 hours <br />0.0013 weeks <br />2.994535e-4 months <br /> out of a possible 43,800. The air sampling availability factor for the report period was 99.97%.

3-33

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 JAFNPP Radiological Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean (X) and the standard deviation (s):

A. Mean n

Xi

.; ~i=l 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.

3-34

B. Standard Deviation S=E(Xi-)2M (N -1)

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

3.7.2 ESTINATION OF THE MEAN AND THE ESTIMATED ERROR FOR THE 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 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

X= Xi i=

N 3-35

Where, X = estimate of the mean.

i = individual sample, i.

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

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

B. Error of the Mean (Reference 18) 11/2 n

ERROR MEAN = I (ERROR) 2 i=1 N

Where, ERROR MEAN = propagated error i = individual sample ERROR = 1 sigma* error of the individual analysis N,n = number of samples with positive indications

  • Sigma (ca)

Sigma 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.

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1 3.7.3 LOWER LIMIT OF DETECTION (LLD)

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

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

4.66 Sb LLD-(E) (V) (2.22) (Y) exp (-XAt)

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);

E = the counting efficiency (in counts per disintegration);

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

2.22 = the number of disintegrations per minute per picocurie; Y = the fractional radiochemical yield (when applicable);

X = 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.

3-37

The TS/ODCM ILD formula assumes that:

  • 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 TS/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 TS/ODCM program required LLDs for specific media and radionuclides as specified by the NRC.

The LLDs actually achieved are routinely much lower than those specified by the TS/ODCM.

3-38

3.8 COMlPLIANCE WITH REQUIRED LOWER LIrvllS OF DETECTION (LLD)

Tables D 4.6.20-1 and D 3.5.1-3 of the Nine Mile Point Unit 1 Offsite Dose Calculation Manual and Nine Mile Point Unit2 Offsite Dose Calculation Manual, respectively, specify the detection capabilities for environmental sample analysis (See Report Table 3.8-1). The reporting requirements of Nine Mile Point Unit 1 Offsite Dose Calculation Manual, Section D 6.9.1.d and Nine Mite Point Unit 2 Offsite Dose Calculation Manual 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 achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement.

All sample analyses performed in 2002, as required by the TS/ODCM, achieved the Lower Limit of Detection (LLD) specified by ODCM Tables D 4.6.20-1 and D 3.5.1-3.

3-39

I r- I I- 1' r- F- . rI r- ( - rf I IF ( ( r (

TABLE 3.8-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Analysis Water Airborne Particulate or Fish Milk Food Products Sediment (Pci/i) Gases (pCi/m 3 ) (pCi/kg, wet) (pCi/) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 3000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58, Co-60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 I-131 15 (a) - 0.07 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 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 pCi/liter is used for H-3 and an LLD value of 15 pCi/liter is used for I-13 1.

3-40

3.9 REGULATORY DOSE LIMITS The Nuclear Regulatory Commission and the Environmental Protection Agency, two federal agencies, have responsibility for regulations promulgated for protecting the public from radiation and radioactivity beyond the site boundary.

3.9.1 The Nuclear Regulatory Connission (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 timit, 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 10CFR50, Appendix I, 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.

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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.

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