Text

Annual Radiological Environmental Operating Report
	ML051380529
Person / Time
Site:	Ginna
Issue date:	12/31/2004
From:	; Constellation Energy Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML051380529 (61)
	v • d • e

2004 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT R.E. Ginna Nuclear Power Plant Docket No. 50-244

TABLE OF CONTENTS Page 1.0

SUMMARY

1 2.0 PROGRAM DESCRIPTION 3 2.1 Program Objectives 3 2.2 Program Requirements 3 3.0 DATA

SUMMARY

13 3.1 Analytical Results 13 3.2 Air Samples 14 3.3 Water Samples 24 3.4 Milk Samples 34 3.5 Fish Samples 36 3.6 Sediment Samples 39 3.6 Vegetation Samples 41 3.7 External Penetrating Radiation 43 4.0 LAND USE CENSUS 45 5.0 EXTERNAL INFLUENCES 45 6.0 QUALITY ASSURANCE 47 7.0 DEVIATIONS FROM SCHEDULE 56

LIST OF TABLESIFIGURES Table/Figure Page 1-1 Environmental Radiological Monitoring 2 Program Summary 2-1 Radiological Environmental Monitoring Program 5 2-2 Maximum Values of LLD 7 2-3 Direction and Distance to Sample Points 9 3-1 A Onsite Samplers, January - June 15 3-1 B Onsite Samplers, July - December 16 3-2 A Offsite Samplers, January - June 17 3-2 B Offsite Samplers, July - December 18 3-4 A 13 Week Composite Gamma Isotopic Analyses First Quarter 19 3-4 B 13 Week Composite Gamma Isotopic Analyses Second Quarter 20 3-4 C 13 Week Composite Gamma Isotopic Analyses Third Quarter 21 3-4 D 13 Week Composite Gamma Isotopic Analyses Fourth Quarter 22 3-5 Charcoal Cartridges for Iodine 23 3-8 Environmental Water Samples Gross Beta Analysis 26 3-9 Russell Station Water Gamma Isotopic Analysis 27 3-10 Ontario Water District Water Gamma Isotopic Analysis 28 3-11 Circ-In Water Gamma Isotopic Analysis 29 3-12 Circ-Out Water Gamma Isotopic Analysis 30 3-13 Deer Creek Water Gamma Isotopic Analysis 31 3-14 Environmental Water Samples Tritium Analysis 32 3-15 Radioiodine in Water 33 3-16 Milk Samples Gamma Isotopic Analysis 35 3-17A Fish Samples Gamma Isotopic Analysis 37 3-17B Fish Samples Gamma Isotopic Analysis 38 3-18 Sediment Samples Gamma Isotopic Analysis 40 3-19 Vegetation Samples Gamma Isotopic Analysis 42 3-20 External Penetrating Radiation 44

LIST OF TABLESIFIGURES (continued)

Table/Figure Page 4-1 Land Use Census 45 6-1A Trend of Blind Spiked Water Samples 52 6-1 B Trend of Blind Spiked Milk Samples 52 6-1C Trend of Blind Spiked Filter Samples 53 6-1C Trend of QC Blind Spiked TLD's 54 6-2A Trend of Split TLD Samples 54 LIST OF MAPS Map No. Page 2-1 Onsite Sample Locations 10 2-2 Offsite Sample Locations 11 2-3 Water Sample and Milk Farm Locations 12

RADIOLOGICAL ENVIRONMENTAL SURVEY January 1, 2004 - December 31, 2004 1.0

SUMMARY

The Annual Radiological Environmental Operating Report is published in accordance with Section 5.0 of the Offsite Dose Calculation Manual, (ODCM).

This report describes the Radiological Environmental Monitoring Program, (REMP), and its implementation as required by the ODCM.

The REMP is implemented to measure radioactivity in the aquatic and terrestrial pathways. The aquatic pathways include Lake Ontario fish, Lake Ontario water, and Deer Creek water. Measurement results of the samples representing these pathways contained only natural background radiation or low concentrations of Cs-1 37 resulting from past atmospheric nuclear weapons testing.

Terrestrial pathways monitored included airborne particulate and radioiodine, milk, food products, and direct radiation. Analysis of terrestrial pathways demonstrated no detectable increase in radiation levels as a result of plant operation. The 2004 results were consistent with data for the past five years and exhibited no adverse trends.

The analytical results from the 2004 Radiological Environmental Monitoring program demonstrate that the operation of the R.E. Ginna Nuclear Power Plant had no measurable radiological impact on the environment. The results also demonstrate that operation of the plant did not result in a measurable radiation dose to the general population above natural background levels.

During 2004, 1236 samples were collected for analysis by gross beta counting and/or gamma spectroscopy. These included 936 air samples, 60 water samples, 17 fish samples, 6 sediment samples, 14 vegetation samples, 47 milk samples, and 156 thermoluminescent dosimeter measurements. During 2004 there were three deviations from the sampling schedule for air samples. The minimum number of samples required in ODCM Table 5-1 were collected for all pathways.

Samples were collected by Ginna Station chemistry personnel and analyzed by the J. A. Fitzpatrick Nuclear Power Plant Environmental Laboratory.

A summary of the data collected indicating the results of all data for indicator and control locations is given in Table 1-1.

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Table 1-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY SAMPLED TYPE AND TOTAL NUMBER OF INDICATOR LOCATIONS CONTROL LOCATION UNIT OF MEASUREMENT ANALYSES LLD MEAN (1) RANGE MEAN (1) RANGE NAME, DISTANCE MEAN (1) RANGE AND DIRECTION AIR: Particulate (pCI/M ) Gross Beta 628 0.003 0.016(4651468) Onsite Location #13 0.017 (52152) 0.016 (155/156) 0.006-0.031 292 230M 0.11 - 0.028 0.006 - 0.028902 (pCi/M3) Gamma Scan 48 (2) < LLD N/A N/A < LLD Iodine (pCI/M') Gamma Scan 258 0.006- < LLD N/A N/A < LLD 0.057 DIRECT RADIATION: TLD Gamma 156 5.0 11.5 (120/120) Onsite Location #7 15.9 (4/4) 10.6 (36/36)

(mrem/quarter) 8.8-17.0 257 220M 14.5-17.0 8.9-11.7 WATER: Drinking Gross Beta 12 0.2 2.62 (12/12) OWD 2.62 N/A (pCULiter) 1.29-3.84 70 1200M 1.29 - 3.84 Gamma Scan 12 (2) Ra-226 83 (10/12) OWD Ra-226 83 (10/12) N/A 44 -135 70 1200M 44 -135 Tritlum 12 (2) <LID N/A N/A N/A Iodine 12 0.47' < LLD NiA N/A N/A WATER: Surface Gross Beta 48 0.2 2.16 (12/12) Deer Creek 3.97 (12112) 2.23 (12/12)

(pCi/Liter) 1.18-3.74 105 260M 2.27 - 6.53 0.79 - 2.92 Gamma Scan 48 (2) Ra-226 101 (9/12) Circ-out Ra-226 101 (9/12) Ra-226 95 (12/12)58-153 15 130M 58 -153 41-165 Tritium 48 (2) <LLD N/A N/A N/A Iodine 48 0.46' < LLD N/A N/A < LLD MILK: Iodine 47 0.44' < LLD N/A N/A < LLD (pCI/LIter)

Gamma Scan 47 (2) < LLD N/A N/A < LLD FISH: Gamma Scan 17 (2) Ra-226 541 (9/10) Indicator Fish Ra-226 541 (9/10) Ra-226 540 (6/8)

(pCi/Kg) 252 - 726 015 130M 252 - 726 122 -391 VEGETATION: Gamma Scan 14 (2) Ra-226 251 (6/8) Indicator Vegetation. Ra-226 251 (6/8) Ra-226 242 (4/6)

(pCi/Kg) 155 - 358 155 - 358 128 - 495 SEDIMENT: Gamma Scan 6 (2) Ra-226 1028 (4/4) Indicator Sediment Ra-226 1028 (4/4) Ra-226 804 (2/2)

(pCi/Kg) 504 - 2410 504 - 2410 418 -1190 (1) Mean and range based on detectable measurements only. Fraction of detectable measurements at specified locations In parentheses.

(2) Table of LLD values attached for gamma scan and trltium measurements.

Average LLD 2

2.0 PROGRAM DESCRIPTION 2.1 Program Objectives The objectives of the Radiological Environmental Monitoring Program are:

Measure and evaluate the effects of plant operation on the environment.

Monitor background radiation levels in the environs of the Ginna site.

Demonstrate compliance with the environmental conditions and requirements of applicable state and federal regulations, including the ODCM and 40 CFR 190.

Provide information by which the general public can evaluate environmental aspects of the operation of Ginna Nuclear Power Station.

2.2 Program Requirements In order to achieve the objectives listed in section 2.1, a sampling and analysis program is implemented each year according to table 5-1 of the ODCM.

Following are the requirements from the ODCM:

Monitoring Program The radiological environmental monitoring program shall be conducted as specified in Table 5-1 at the locations given in the ODCM.

If the radiological environmental monitoring program is not conducted as specified in Table 5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for these deviations and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal availability, or to malfunction of automatic sampling equipment. If the latter, efforts shall be made to complete corrective action prior to the end of the next sampling period.

If milk or fresh leafy vegetable samples are unavailable for more than one sample period from one or more of the sampling locations indicated by the ODCM, a discussion shall be included in the Annual Radiological Environmental Operating Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. If a milk or leafy vegetable sample location becomes unavailable, the locations from which samples were unavailable may then be deleted from the ODCM, provided that comparable locations (if available) are added to the environmental monitoring program.

3

Land Use Census A land use census shall be conducted and shall identify the location of the nearest milk producing animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles.

An onsite garden located in either the meteorological sector having the highest historical D/Q, or in a location with a higher D/Q than the location of the maximally exposed individual, may be used for broad leaf vegetation sampling in lieu of a garden census. Otherwise the land use census shall also identify the location of the nearest garden of greater than 500 square feet in each of the 16 meteorological sectors within a distance of five miles. D/Q shall be determined in accordance with methods described in the ODCM.

Interlaboratorv Comparison Program Analyses shall be performed on applicable radioactive environmental samples supplied as part of an interlaboratory comparison program which has been approved by NRC, if such a program exists.

Specification The radiological environmental monitoring samples shall be collected pursuant to Table 5-1. Acceptable locations are shown in the ODCM. Samples shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.

A land use census shall be conducted annually between June 1 and October 1.

A summary of the results obtained as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

Deviations from the Sampling Schedule Deviations from the sampling schedule are allowed when samples are unavailable due to hazardous conditions, seasonal variations or malfunction of automatic sampling equipment.

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Table 2-1 Page 1 of 2 Offsite Dose Calculation Manual Table 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR NUMBER OF SAMPLES & SAMPLING AND COLLECTION - TYPE AND FREQUENCY OF ANALYSIS SAMPLE SAMPLE LOCATIONS FREQUENCY

1. AIRBORNE

a. Radioiodine indicator Continuous operation of sampler with Radioiodine canister. Analyze within 7 days of collection for Iodine-131.

1 control ample collection at least once per 10 days Particulate sampler. Analyze for gross beta radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following

b. Particulate Indicator Same as above ilter change. Perform gamma isotopic analysis on each sample for which control gross beta activity is > 10 times the mean of offsite samples. Perform gamma sotopic analysis on composite (by location) sample at least once per 92 days.

2. DIRECT 30 indicator TLDs at least quarterly amma dose quarterly.

RADIATION control 11 placed greater than 5 miles rom plant site.)

3. WATERBORNE

a. Surface 1 control (Russell Station) Composite sample collected over a Gross beta and gamma isotopic analysis of each composite sample. Tritium I indicator (Condenser Water period of < 31 days. analysis of one composite sample at least once per 92 days.

ischarge)

Drinking I indicator (Ontario Water District ame as above Same as above.

ntake)

c. Shoreline 1 Control (Russell Station) emi-annnually Gamma isotopic analysis of each sample Sediment I Indicator (Ontario Water istricl)

Composite sample to be collected by collecting an aliquot at Intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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Table 2-1 Page 2 of 2 Offsite Dose Calculation Manual Table 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY ANDIOR NUMBER OF SAMPLES & SAMPLING AND COLLECTION TYPE AND FREQUENCY OF ANALYSIS SAMPLE SAMPLE LOCATIONS FREQUENCY

4. INGESTION

a. Milk I control At least once per 15 days Gamma isotopic and 1-131 analysis of each sample.

3 indicator*

(June thru October)

I control At least once per 31 days Gamma Isotopic and 1-131 analysis of each sample.

1 Indicator November thru May)

b. Fish 4 control Twice during fishing season Including at Gamma Isotopic analysis on edible portions of each sample.

4 Indicator (Off shore at Ginna) east four species.

1 control nnual at time of harvest. Sample from Gamma isotopic analysis on edible portion of sample.

c. Food Products 2 Indicator (On site) two of the following:

1. apples 2 cherries 3 Other crops grown on site by contract farmer 1 control At time of harvest. One sample of: Gamma Isotopic analysis on edible portion of sample.

1 Indicator 1. broad leaf vegetation' (On site garden or nearest offsite 2. other vegetable garden within 5 miles in the highest D/0 meterological sector) leaves from 3 different plant species composited See Land Use Census, page 50 6

Table 2-2 Page 1 of 2 The maximum LLD values as defined by ODCM Table 5-3 Airborne I.Food Particulate

-Analyss Water Particulate Fish Milk (pCI/kg, wet)

(pCi/Liter) or Gas (pCi/kgwet) (pCILiter)

__ (pCi/m 3)

Gross Beta 4(a) 1 x 10-H-3 2000 (1000)(a)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 Zn-65 30 260 Zr-Nb-95 15D 1-131 1 7 x 10 1 60 Cs-134 15(10)(a), I x 10- 130 15 60 Cs-137 18 Ba-La-140 15(b) 15(b)

a. LLD for drinking water

b. Total for parent and daughter 7

Table 2-2 Page 2 of 2 LLD TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

The LLD is defined as an apriori (before the fact) limit representing the capability of a measurement system and not as an aposteriori (after the fact) limit for a particular measurement, the minimum detectable activity (MDA).

For a particular measurement system (which may include radiochemical separation):

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

LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) 4.66 establishes 95% confidence interval about LLD Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (in counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable)

Xis the decay constant for the particular radionuclide At is the elapsed time between sample collection, (or end of sample collection period), and time of counting 8

Table 2-3 DIRECTION AND DISTANCE TO SAMPLE POINTS All directions given in degrees and all distances given in meters Air Sample Stations Direction Distance TLD Direction 'Distance

. Locations

2 1 87 320 #2 87 320

3 1 110 420 #3 110 420

4 1 140 250 #4 140 250

5 1 185 160 #5 185 160

6 1 232 225 #6 232 225

7 1 257 220 #7 257 220

8 C 258 19200 #8 258 19200

9 1 235 11400 #9 235 11400

10 C 185 13100 #10 185 13100

11 1 123 11500 #11 123 11500

12 C 93 25100 #12 93 25100

13 1 194 690 # 13 292 230 Water Sample Locations Direction Distance ;- # 14 292 770 Russell Station C 270 25600 # 15 272 850 Ontario Water District I 70 2200 # 16 242 900 Circ Water Intake S 0 420 # 17 208 500 Circ Water Discharge I 15 130 #18 193 650 Deer Creek S 105 260 #19 177 400

20 165 680

21 145 600

22 128 810 Sediment Samples Direction Distance #23 107 680 OWD Shoreline I 70 2200 #24 90 630 Russell Shoreline C 270 25600 #25 247 14350 Lake Ontario Benthic S 70 2200 # 26 223 14800 Milk Sample Locations Direction Distance #27 202 14700 Farm A I 113 8270 # 28 145 17700 Farm B I 242 4680 # 29 104 13800 Farm C I 156 5230 #30 103 20500 Farm D C 132 21000 # 31 263 7280 Fish Samples # 32 246 6850 Indicator Samples Lake Ontario Discharge Plume # 33 220 7950 Background Samples Russell Station # 34 205 6850 Produce Samples #35 193 7600 Indicator Samples Grown on property surrounding Plant #36 174 5650 Background Samples Purchased from farms > 10 miles # 37 158 6000 I = Indicator Samples # 38 137 7070 C = Control Samples #39 115 6630 S = Supplemental Samples #40 87 6630 9

Map 2-1 Onsite Sample Locations

Key Glnna SfRllenn Strutictlueir TLDA s Air samplers (10)

Map 2-2 Offsite Sample Locations Location of TLDs and milk farms within 5 mile radius of Ginna Station *.

Onsite samples detailed on map 2-1.

(11)

Map 2-3 I

Water Sample and Milk Farm Locations Location of water samples, milk farms and TLDs *.

Station are detailed on maps 2-1 and 2-2.

Onsite samples and samples in close proximity to Ginna (12)

3.0 DATA

SUMMARY

3.1 Analytical Results The values listed on the following tables include the uncertainties stated as

+/- 1 standard deviation.

Definitions Curie (Ci): The quantity of any radionuclide in which the number of disintegrations per second is 37 billion.

Picocurie (pCi): One millionth of a millionth of a curie or 0.037 disintegrations per second Cubic meter (M3) Approximately 35.3 cubic feet Liter (L): Approximately 1.06 quarts Kilogram (Kg): Approximately 2.205 pounds Lower Limit of Detection The U.S. Nuclear Regulatory Commission has requested that reported values be compared to the Lower Limit of Detection (LLD) for each piece of equipment.

The LLD for the equipment is established by the measurement of a blank sample. These values are before correction for decay. Decay correction is applied from the end of the sampling period to the counting time, not from the midpoint of the sampling period. An explanation of the calculation of the LLD is included with Table 2-2, (page 8).

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3.2 Air Samples Radioactive particles in air are collected by drawing approximately one SCFM through a two inch diameter particulate filter. The volume of air sampled is measured by a dry gas meter and corrected for the pressure drop across the filter. The filters are changed weekly and allowed to decay for three days prior to counting to eliminate most of the natural radioactivity such as the short half-life decay products of radon.

The decay period is used to give a more sensitive measurement of long-lived man-made radioactivity.

A ring of 6 sampling stations is located on the plant site from 150 to 420 meters from the reactor centerline near the point of the maximum annual average ground level concentration, I more is located on-site at 690 meters, and 2 others offsite at approximately 7 miles. In addition, there are 3 sampling stations located approximately 7 to 16 miles from the site that serve as control stations.

Based on weekly comparisons, there was no statistical difference between the Control and Indicator radioactive particulate concentrations. The averages for the control samples were 0.016 pCi/M 3 , and the averages for the indicators were 0.016 pCi/M 3 for the period of January to December, 2004. Maximum weekly concentrations for each station were less than 0.033 pCi/M 3 .

The major airborne species released from the plant are noble gases, tritium and radioiodines. Most of this activity is released in a gaseous form, however, some radioiodine is released as airborne particulate and some of the particulate activity is due to short lived noble gas decay products.

Tables 3-1A, 3-1 B are a list of gross beta analysis values for the on-site sample stations. Tables 3-2A, 3-2B are a list of gross beta analysis values for the off-site sampler stations.

The particulate filters from each sampling location were saved and a 13 week composite was made. A gamma isotopic analysis was performed for each sampling location and corrected for decay. The results of these analyses are listed in Tables 3-4 A to D, and indicate only the naturally occurring radioisotopes, Be-7 and K-40.

Radioiodine cartridges are placed at six locations. These cartridges are changed and analyzed each week. No positive analytical results were found on any sample. A list of values for these cartridges is given in Table 3-5.

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R.E. Ginna Nuclear Power Plant Table 3-1A On-Site Air Particulate Samplers Gross Beta Results In pCilm3 Collection Station Station Station Station Station Station Station Date #2 (I) #3 (l) #4 (i) #5 (l) #6 (I) #7 (1) #13 (1) Average 5-Jan 0.022 +/- 0.004 0.020 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.020 +/- 0.004 0.021 +/- 0.004 0.020 12-Jan 0.016 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.000 0.018 +/- 0.003 0.018 +/- 0.003 0.015 +/- 0.003 0.022 +/- 0.005 0.018 20-Jan 0.015 +/- 0.003 0.012 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.012 +/- 0.003 0.012 +/- 0.003 0.012 26-Jan 0.017 +/- 0.004 0.015 +/- 0.003 0.013 i 0.003 0.015 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.004 0.016 +/- 0.004 0.015 2-Feb 0.021 +/- 0.004 0.017 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.004 0.017 9-Feb 0.019 +/- 0.004 0.015 +/- 0.003 0.019 i 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.003 0.020 +/- 0.004 0.018 16-Feb 0.028 +/- 0.004 0.024 +/- 0.003 0.020 i 0.003 0.019 +/- 0.003 0.025 +/- 0.003 0.022 +/- 0.004 0.027 +/- 0.005 0.024 23-Feb 0.024 +/- 0.004 0.020 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.022 +/- 0.003 0.019 +/- 0.004 0.021 +/- 0.004 0.020 1-Mar 0.028 +/- 0.004 0.024 +/- 0.003 0.026 +/- 0.003 0.024 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.003 0.028 +/- 0.005 0.026 8-Mar 0.017 +/- 0.003 0.016 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.020 +/- 0.004 0.017 +/- 0.004 0.017 15-Mar 0.014 i 0.003 0.013 +/- 0.003 0.017 +/- 0.003 0.013 +/- 0.003 0.015 +/- 0.003 0.014 +/- 0.004 0.014 +/- 0.003 0.014 22-Mar 0.019 i .011(a) 0.015 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.003 0.017 29-Mar 0.023 +/- 0.004 0.017 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.004 0.019 +/- 0.003 0.019 6-Apr 0.012 +/- 0.003 0.010 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.003 0.008 +/- 0.002 0.010 12-Apr 0.013 +/- 0.003 0.011 +/- 0.003 0.011 i 0.003 0.010 +/- 0.003 0.012 +/- 0.003 0.009 +/- 0.003 0.013 +/- 0.003 0.011 20-Apr 0.019 i 0.003 0.014 +/- 0.003 0.012 +/- 0.002 0.014 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.004 0.012 +/- 0.003 0.015 26-Apr 0.009 i 0.003 0.008 +/- 0.003 0.012 +/- 0.003 0.007 +/- 0.002 0.009 +/- 0.003 0.010 +/- 0.003 0.011 +/- 0.002 0.009 4-May 0.013 +/- 0.003 0.010 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.003 0.011 +/- 0.002 0.011 +/- 0.003 0.012 +/- 0.003 0.012 11-May 0.019 i 0.003 0.017 +/- 0.003 0.018 +/- 0.003 0.015 +/- 0.004 0.019 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.003 0.018 18-May 0.019 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.017 +/- 0.003 0.014 +/- 0.003 0.015 24-May 0.012 i 0.003 0.010 +/- 0.003 0.011 i 0.003 0.010 +/- 0.003 0.011 +/- 0.003 0.012 +/- 0.003 0.012 +/- 0.003 0.011 2-Jun 0.015 +/- 0.003 0.012 +/- 0.002 0.012 i 0.002 0.012 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.003 0.014 +/- 0.003 0.013 8-Jun 0.014 +/- 0.003 0.011 +/- 0.003 0.012 i 0.003 0.015 +/- 0.003 0.014 +/- 0.003 0.012 +/- 0.003 0.018 +/- 0.004 0.014 15-Jun 0.017 +/- 0.003 0.014 +/- 0.003 0.016 +/- 0.004 0.016 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.018 +/- 0.004 0.016 22-Jun 0.015 +/- 0.003 0.010 +/- 0.002 0.012 +/- 0.004 0.012 +/- 0.002 0.014 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.003 0.013 29-Jun 0.027 i 0.004 0.022 +/- 0.003 0.027 +/- 0.005 0.013 +/- 0.003 0.014 +/- 0.003 0.016 +/- 0.004 0.012 +/- 0.003 0.019

.Maximum 0.028 +/- 0.004 0.024 +/- 0.003 0.027 +/- 0.005 0.024 +/- 0.004 0.026 +/- 0.003 0.027 +/- 0.004 0.028 +/- 0.005 Average 0.018 0.015 0.016 0.015 0.016 0.016 0.017 Minimum 0.009 +/- 0.003 0.008 +/- 0.002 0.009 +/- 0.000 0.007 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.003 0.008 +/- 0.002 (a) Sample collected for <84 hours in sample period I = Indicator (15)

C = Control

R. E.Ginna Nuclear Power Plant Table 3-1 B On-Site Air Particulate Samplers Gross Beta Results In pCiImr3 Collection Station Station Station Station Station Station Station Date #2 (l) #3 (I) #4 (l) #5 (1) #6 (I) #7 (l) #13 (I) Average 6-Jul 0.016 +/- 0.003 0.013 +/- 0.003 0.014+/- 0.004 0.013 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.003 0.014 +/-0.003 0.013 12-Jul 0.013 +/- 0.003 0.010 +/- 0.003 0.007+/- 0.004 0.009 +/- 0.003 0.011 +/- 0.003 0.010 +/- 0.003 0.011 +/-0.003 0.010 19-Jul 0.008 +/- 0.003 0.010 +/- 0.003 0.011+/- 0.004 0.009 +/- 0.003 0.010 +/- 0.002 0.010 +/- 0.003 0.010 +/-0.003 0.010 27-Jul 0.021 +/- 0.003 0.019 +/- 0.003 0.021+/- 0.004 0.019 +/- 0.003 0.018 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.020 3-Aug 0.011 +/- 0.003 0.010 +/- 0.003 0.010+/- 0.004 0.012 +/- 0.003 0.010 +/- 0.003 0.011 +/- 0.003 0.011 +/- 0.003 0.011 9-Aug 0.011 +/- 0.003 0.013 +/- 0.003 0.015+/- 0.004 0.014 +/- 0.003 0.015 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.015 16-Aug 0.016 +/- 0.003 0.021 +/- 0.003 0.019 0.004 0.020 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.003 0.019 23-Aug 0.026 +/- 0.004 0.031 +/- 0.004 0.023+/- 0.004 0.023 +/- 0.003 0.025 +/- 0.003 0.024 +/- 0.003 0.024 +/-0.003 0.025 30-Aug 0.018 +/- 0.003 0.017 +/- 0.003 0.017+/- 0.004 0.016 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.018 +/-0.003 0.018 7-Sep 0.018 +/- 0.003 0.018 +/- 0.003 0.014 +/- 0.004 0.017 +/- 0.003 0.017 +/- 0.002 0.014 +/- 0.003 0.018 +/-0.003 0.017 14-Sep 0.010 +/- 0.003 0.010 +/- 0.003 0.009 +/- 0.004 0.009 +/- 0.003 0.010 +/- 0.003 0.011 +/- 0.003 0.012 +/-0.003 0.010 21-Sep 0.017 +/- 0.003 0.024 +/- 0. 151 (a) 0.012 +/- 0.004. 0.014 +/- 0.003 0.014 +/- 0.003 0.012 +/- 0.003 0.018 +/- 0.003 0.016 28-Sep 0.030 +/- 0.004 0.031 +/- 0.004 0.027+/- 0.005 0.025+/- 0.004 0.028 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.003 0.019 4-Oct 0.013 +/- 0.003 0.012 +/- 0.003 0.015+/- 0.004 0.020+/- 0.003 0.016 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0.015 1`1-Oct 0.020 +/- 0.003 0.021 +/- 0.003 0.020+/- 0.004 0.023 +/- 0.004 0.020 +/- 0.003 0.021 +/- 0.003 0.023 +/-0.003 0.021 18-Oct 0.009 +/- 0.003 0.012 +/- 0.003 0.011 +/- 0.004 0O.013 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.003 0.014 +/-0.003 0.012 25-Oct 0.008 +/- 0.003 0.007 +/- 0.002 0.008 +/- 0.003 0.009 +/- 0.003 0.005 +/- 0.002 0.008 +/- 0.002 0.007 +/-0.002 0.007 2-Nov 0.013 +/- 0.003 0.017 +/- 0.004 0.014 +/- 0.004 0.017 +/- 0.003 0.013 +/- 0.002 0.016 +/- 0.003 0.014 +/-0.003 0.015 8-Nov 0.013 +/- 0.003 0.014 +/- 0.003 0.013 +/- 0.004 0.018 +/- 0.004 0.014 +/- 0.003 0.017 +/- 0.003 0.014 +/- 0.003 0.015 16-Nov 0.013 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.004 0.017 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.016 22-Nov 0.023 +/- 0.004 0.025 +/- 0.004 0.027 +/- 0.005 0.024 +/- 0.004 0.025 +/- 0.004 0.024 +/- 0.004 0.026 +/- 0.004 0.025 29-Nov 0.014 +/- 0.003 0.013 +/- 0.003 0.017 +/- 0.004 0.010+/- 0.003 0.005 +/- 0.002 0.011 +/- 0.002 0.012 +/- 0.003 0.012 6-Dec 0.018 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.005 0.020 +/- 0.003 0.018 +/- 0.003 0.021 +/- 0.003 0.018 +/-0.003 0.020 13-Dec 0.006 +/- 0.002 0.008 +/- 0.020 0.010 +/- 0.003 0.008 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.008 20-Dec 0.017 +/- 0.004 0.015 +/- 0.003 0.017 +/- 0.005 0.015 +/- 0.004 0.014 +/- 0.003 0.013 +/- 0.003 0.017 +/- 0.003 0.015 27-Dec 0.020 +/- 0.003 0.014 +/- 0.003 0.020 +/- 0.005 0.015 +/- 0.003 0.007 +/- 0.002 0.013 +/- 0.003 0.013 +/- 0.003 0.015 Maximum 0.030 +/- 0.004 0.031 +/- 0.020 0.027 +/- 0.005 0.025 +/- 0.004 0.028 +/-' 0.004 0.025 +/- 0.004 0.026 +/- 0.004 Average 0.015 0.016 0.016 0.016 0.015 0.016 0.016 Minimum 0.006 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.003 0.008 +/- 0.002 0.005 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 (a) Sample collected for <84 hours in sample period I= Indicator (16)

C = Control

R. E. Ginna Nuclear Power Plant Table 3-2A Off-Site Air Particulate Samplers Gross Beta Results in pCilm3 Collection Station Station Station Station Station Date #8 (C) #9 (I) #10 (C) #11 (I) #12 (C) Average 5-Jan 0.021 +/- 0.003 0.019 +/- 0.005 0.023 +/- 0.004 0.023 +/- 0.003 0.020 +/- 0.003 0.021 12-Jan 0.017 +/- 0.003 0.016 +/- 0.005 0.022 +/- 0.003 0.019 +/- 0.003 0.017 i 0.003 0.018 20-Jan 0.009 +/- 0.002 0.013 +/- 0.004 0.014 +/- 0.003 0.014 +/- 0.003 0.014 i 0.003 0.013 26-Jan 0.014 +/- 0.003 0.012 +/- 0.005 0.020 +/- 0.004 0.019 +/- 0.003 0.016 i 0.003 0.016 2-Feb 0.017 +/- 0.003 0.020 +/- 0.005 0.017 +/- 0.003 0.020 +/- 0.003 0.017 i 0.003 0.018 9-Feb 0.015 +/- 0.003 0.017 +/- 0.005 0.019 +/- 0.003 0.014 +/- 0.003 0.015 i 0.003 0.016 16-Feb 0.021 +/- 0.003 0.025 +/- 0.005 0.026 +/- 0.004 0.024 +/- 0.003 0.021 i 0.003 0.023 23-Feb 0.024 +/- 0.003 0.020 +/- 0.005 0.023 +/- 0.004 0.020 +/- 0.003 0.018 i 0.003 0.021 1-Mar 0.025 +/- 0.003 0.026 +/- 0.004 0.024 +/- 0.004 0.025 +/- 0.003 0.029 +/- 0.004 0.026 8-Mar 0.019 +/- 0.003 0.013 + 0.005 0.019 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.017 15-Mar 0.014 +/- 0.003 0.006 +/- 0.004 0.013 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.013 22-Mar 0.016 +/- 0.003 0.013 +/- 0.005 0.016 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.015 29-Mar 0.018 +/- 0.003 0.015 +/- 0.005 0.016 +/- 0.003 0.022 +/- 0.003 0.016 +/- 0.003 0.017 6-Apr 0.010 +/- 0.002 0.011 +/- 0.004 0.009 +/- 0.003 0.009 +/- 0.002 0.008 _ 0.002 0.009 12-Apr 0.012 +/- 0.003 0.011 +/- 0.005 0.015 +/- 0.003 0.013 +/- 0.003 0.014 + 0.003 0.013 20-Apr 0.016 +/- 0.003 0.013 + 0.005 0.016 +/- 0.005 0.016 + 0.003 0.017 i 0.003 0.016 26-Apr 0.011 +/- 0.002 0.010 + 0.002 0.008 +/- 0.002 0.010 +/- 0.002 0.010 i 0.002 0.010 4-May 0.013 +/- 0.003 0.010 +/- 0.005 0.014 +/- 0.003 0.011 +/- 0.003 0.010 i 0.003 0.012 11-May 0.018 +/- 0.003 0.015 +/- 0.004 0.017 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.017 18-May 0.018 +/- 0.003 0.033 +/- 0.008 0.017 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.020 24-May 0.015 +/- 0.003 0.029 + 0.009 0.011 +/- 0.003 0.012 +/- 0.003 0.011 +/- 0.030 0.016 2-Jun 0.012 +/- 0.002 0.010 +/- 0.003 0.011 +/- 0.003 0.012 +/- 0.003 0.012 +/- 0.002 0.011 8-Jun 0.013 +/- 0.003 0.011 +/- 0.005 0.014 +/- 0.003 0.011 +/- 0.013(a) 0.011 +/- 0.003 0.012 15-Jun 0.020 +/- 0.003 0.017 +/- 0.005 0.019 +/- 0.003 0.017 +/- 0.003 0.016 _ 0.003 0.018 22-Jun 0.013 +/- 0.003 0.009 +/- 0.004 0.015 +/- 0.003 0.014 +/- 0.004 0.012 i 0.003 0.013 29-Jun 0.016 +/- 0.003 0.014 +/- 0.004 0.016 +/- 0.003 0.011 +/- 0.003 0.015 i 0.003 0.014 Maximum 0.025 +/- 0.003 0.033 +/- 0.009 0.026 +/- 0.005 0.025 +/- 0.004 0.029 +/- 0.030 Average 0.016 0.016 0.016 0.016 0.015 Minimum 0.009 +/- 0.002 0.006 +/- 0.002 0.008 +/- 0.002 0.009 _ 0.002 0.008 +/- 0.002 (a) Sample collected for <84 hours in sample period I = Indicator C = Control (17)

R. E. Ginna Nuclear Power Plant Table 3-2B Off-Site Air Particulate Samplers Gross Beta Results in pCilm3 Collection Station Station Station Station Station Date #8 (C) #9 (l) #10 (C) #11 (I) #12 (C) Average 6-Jul 0.015 +/- 0.003 0.011 +/- 0.004 0.012 +/- 0.003 0.012 +/- 0.003 0.012 +/- 0.003 0.012 12-Jul 0.009 +/- 0.003 0.012 +/- 0.005 0.009 +/- 0.003 0.010 +/- 0.003 0.010 + 0.003 0.010 19-Jul 0.015 +/- 0.003 0.007 + 0.004 0.010 +/- 0.003 0.010 +/- 0.003 0.011 +/- 0.003 0.011 27-Jul 0.016 +/- 0.003 0.020 +/- 0.004 0.018 +/- 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.018 3-Aug 0.016 +/- 0.003 0.013 +/- 0.005 0.010 +/- 0.006(a) 0.015 +/- 0.003 0.014 +/- 0.003 0.014 9-Aug 0.015 i 0.003 0.016 +/- 0.005 0.019 +/- 0.003 0.014 +/- 0.004 0.013 +/- 0.003 0.015 16-Aug 0.016 i 0.003 0.017 +/- 0.005 0.017 +/- 0.003 0.018 +/- 0.004 0.016 +/- 0.003 0.017 23-Aug 0.022 i 0.004 0.023 +/- 0.005 0.027 +/- 0.004 0.023 +/- 0.004 0.022 +/- 0.003 0.023 30-Aug 0.018 +/- 0.040 0.017 + 0.005 0.016 +/- 0.004 0.017 +/- 0.004 0.013 +/- 0.003 0.016 7-Sep 0.017 +/- 0.003 0.013 + 0.004 0.017 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.003 0.015 14-Sep 0.011 + 0.003 0.008 +/- 0.005 0.011 +/- 0.003 0.010 +/- 0.003 0.008 +/- 0.030 0.010 21-Sep 0.016 +/- 0.003 0.011 +/- 0.004 0.013 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.014 28-Sep 0.032 +/- 0.004 0.021 +/- 0.005 0.027 +/- 0.004 0.031 +/- 0.004 0.026 +/- 0.004 0.027 4-Oct 0.015 +/- 0.003 0.016 +/- 0.005 0.019 +/- 0.004 0.012 +/- 0.004 0.015 + 0.003 0.015 11-Oct 0.024 + 0.004 0.020 +/- 0.005 0.018 +/- 0.004 0.019 +/- 0.004 0.017 +/- 0.003 0.020 18-Oct 0.016 i 0.003 0.010 + 0.020 0.012 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.003 0.013 25-Oct 0.007 +/- 0.003 0.007 +/- 0.003 0.004 +/- 0.002 0.010 +/- 0.003 0.008 +/- 0.002 0.007 2-Nov 0.016 + 0.003 0.017 +/- 0.005 0.014 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.015 8-Nov 0.013 + 0.003 0.016 +/- 0.005 0.015 +/- 0.004 0.017 +/- 0.004 0.015 +/- 0.003 0.015 16-Nov 0.020 + 0.003 0.015 +/- 0.005 0.015 +/- 0.003 0.018 +/- 0.004 0.017 +/- 0.003 0.017 22-Nov 0.026 + 0.004 0.017 +/- 0.005 0.024 +/- 0.004 0.020 +/- 0.004 0.024 +/- 0.004 0.022 29-Nov 0.017 +/- 0.003 0.029 + 0.006 0.017 +/- 0.003 0.010 +/- 0.003 0.014 +/- 0.003 0.017 6-Dec 0.022 + 0.004 0.013 +/- 0.005 0.021 +/- 0.004 0.023 +/- 0.004 0.016 + 0.003 0.019 13-Dec 0.009 + 0.003 0.005 +/- 0.004 0.007 +/- 0.003 0.009 +/- 0.003 0.008 +/- 0.003 0.008 20-Dec 0.015 i 0.004 0.013 +/- 0.005 0.016 +/- 0.003 0.017 +/- 0.004 0.013 +/- 0.003 0.015 27-Dec 0.021 + 0.004 0.029 +/- 0.006 0.019 +/- 0.004 0.017 +/- 0.004 0.017 +/- 0.003 0.021 Maximum 0.032 +/- 0.040 0.029 +/- 0.020 0.027 +/- 0.004 0.031 +/- 0.004 0.026 +/- 0.030 Average 0.017 0.015 0.016 0.016 0.015*

Minimum 0.007 +/- 0.003 0.005 +/- 0.003 0.004 +/- 0.002 0.009 +/- 0.003 0.008 +/- 0.002 (a) Sample collected for <84 hours in sample period I = Indicator C = Control (18)

Table 3-4 A 13 Week Composite Air Sample Analysis 1st Quarter 2004 S I'i ' " ' --- I I Ra-226 NA <1.77F,02 <9.91 E-03 <9.68E-03 <8.91 E-03 <1.20E-02 <1.70E02 <.41E02 <20 2 98E3 <1.06E-02 l<1.26E-02 <1.75E-02 Cr-51 NA <2.09E-02 <1.37E-02 <1.53E-02 <1.40E-02 <1.64E-02 <2.28E-02 <2.48E-02 <2.79E-02 15E0 l16E0 17E0 <2.36E-02 1-1 31 7.OOE-01 <1.42E-02 <9.52E-03 <7.49E-03 <1 .19E-02 <9.85E-03 <1 .99E-02 <1 .23 E-02 <2.39E-02 <8.93E-03 <1.14E-02 <1.14E-02 <1 .78E-02 Be-7 NA 0.1 1310.0 12 0.085+0.008 0.07610.008 0.094+0.009 0.10 7.+0.009 0.081+/-0o.009 0.094:LO.0 10o0.1081Bo.04 0.098+0.009 0.095+0.008 0.109+0.009 0.09610.010o Cs- 134 L.OOE-02 <1.35F,03 <7.06E-04 <7.70E-04 <7.99E-04 <7.53E-04 <1l35E-03 <1.08E-03 <l .91lE-03 <1.07F,03 <7.90E-04 <l1.11lE-03 <8.57E-04 Cs-137 L.OOE_02 <1.17E-02 <7.13F,-04 <7.24 E-04 <7.04E-04 <9.36E-04 <1.16GE-03 <1.1OE-03 <1.46E-03 <9.36E-04 a3.63E-04 <1 .08E-03 <1.42 E-02 Zr-95 NA <4.46E-03 <1.27E-03 a2.50E-03 <2.42E-03 <2.47E-03 a3.99E-03 a332E-03 <s.88E-03 <2.14E-03 <1 .56fi,3 a2.50E-03 a3.78E-Nb-95 NA a3.72E-03 <1.91 E-03 <1.77E-03 <1.53E-03 <2.32E-03 <2.88E-03 <2.09E-03 <4.60E-03 <2.35E-03 <2.25E-03 <2.34E-03 a337E-03 Co-58 NA <2.74E-03 <9.39E-04 <1 32E-03 <1.27E-03 <l .49E-03 <2.27E-03 <1.86E-03 <1.45F,03 <1 .19 F-3 <8.85&04 <1.41 E-03 <1.80F,03 Mn-54 NA <I.F3E,-03 <7.91E-04 <8.07E-04 <8.88E-04 <1.04E-03 <1.49E-03 <1.63E-03 <1.91E-03 <9.76E-04 <7.19E-04 <1.16E-03 <1.75E-02 Ru-103 NA <2.29E-O3 <l.31E-03 <1.7153E- <1.20E-03 <1.53E-03 <2.23E-02 <2.26E-03 <2.93E-03 <1.60E-03 <1.47E-03 <2.07E-03 <2.7E-03 Ru-106 NA <1.26E-02 <7.6sE-03 <7.24E-03 <8.07E-03 <6.80E-03 <1.30E-02 <1.18E-02 <1.93E-02 <.935E-03 <1.04E-02 <1.12E-02 <1.29E-02 Ce-141 NA <2.68E-03 <.7506-03 <1.94E-03 <1.29E-03 <2.35E-03 <3.15E-03 <1.73E-03 <4.OOE-03 1.07E-03 <1.42E-02 <2.28E-03 <.45E-03 Ce-144 NA <5.15E-03 <a.7sE-03 <2.75E-03 <2.09E-03 <a.7sF-03 <5.1E-03 <4.28E-03 <1.32E-03 <2.92E-03 <.27E-03 <3.66E-03 <6.SOE-03 Fc-59 NA <6.54E-03 <1.40E-03 <4.SOE-03 <4.S3E-03 <a.42E-03 <6.40F,03 <7.66R-03 <7.61 E-03 <6.41 E-03 <1.24E-03 <3.46E-03 <3.52E-03 Zn-65 NA <9.47E-04 <4.75 E-04 <2.S2E-03 <1.83E-03 <l1.9R03 <2.45E-03 <2.02E-03 <4.99E-03 <.o I E-03 <2.37E-03 <2.83E-03 <3.45E-03 Co-60 NA <5.09E-04 <1.07E-03 <1.08E-03 <8.78E-04 <7.23E-04 <1.73E-03 <4.08E-04 <1.47E-03 <1.48E-03 <8.O8E-03 <1.41E-02 <1.30E-03 K-40 NA <5.15E-03 <8.71 E-03 <6.72E-03 <1.2 03 0.0290.006 0.0293+0.006 <1.4E-02 <5.67E-03 <9.51 E-03 <2.41E-03 0.022+0-005 0.053+0.

Ru-10 NA <1.69E-02 <2.53E-03 <1.24E-02 I<6.7E-03 <9.850E03 <1.39E-02 <1.72E-02 <1.54E-02 <1.15E-02 <6.51E-03 <1.16E-02 <1.46E-02

( 1 9)

Table 3-4 B 13 Week Composite Air Sample Analysis 2nd Quarter 2004 Radionuclide LLD pClm3 Ra-226 NA <1.61E-02 <1.41E-02 <1.15E-02 <I.OIE-02 <1.75E-02 <1.43E-02 <1.93E-02 .007+004 .013+ 006 <1.18F-02 <1.20E-02 Cr-SI NA <2.65E-02 <2.32E-02 <1.82E-02 <1.88E-02 <2.56E-02 <2.02E-02 <3.59E-02 <1.44E-02 <2.53E-02 <2.41 E-02 <1.98E-02 1-131 7.OOE-01 <2.13E-02 <2.20E-02 <1.67E-02 <1.47E-02 <1.83E-02 <1.91E-02 <2.89E-02 <1.41E-02 <2.14E-02 <2.06E-02 <1.82E-02 Be-7 NA .097 .010 .108A.009 .096+011 .095+.085 .105+.011 .110011 .119.I015 .125O 10 .090+ 010 .106+O009 .111. 011 Cs-134 I.OOE-02 <1.41E-03 <1.44E-03 <1.12E-03 <9.37E-04 <1.66E-03 <1.18E-03 <1.43E-03 <7.12E-04 <I.31E-03 <1.21E-03 <I.37E-03 Cs-137 I.OOE-02 <1.05E-03 <1.03E-03 <1.06E-03 <5.21 E-04 <1.17E-03 <9.49E-04 <1.44E-03 <6.65E-04 <1.03E-03 <7.33E-04 <1.15E-03 Zr-95 NA <2.47E-03 <2.56E-03 <1.89E-03 <1.77E-03 <3.43E-03 <2.52E-03 <3.76E-03 <2.84E-03 <2.47E-03 <2.77E-03 <2.59E-03 Nb-95 NA <2.OOE-03 <2.45E-03 <2.58E-03 <1.80E-03 <3.96E-03 <235E-03 <5.37E-03 <2.11 E-03 <3.o1E-03 <2.50E-03 <1.90E-03 Co-58 NA <1.57E-03 <1.67E-03 <1.88E-03 <7.09E-03 <1.96E-03 <1.77E-03 <2.18E-03 <1.05E-03 <1.55E-03 <1.46E-03 <1.57E-03 Aln-54 NA <1.32E-03 <1.21E-03 <1.67E-03 <8.99E-04 <1.37E-03 <1.33E-03 <2.25E-03 <8.15E-04 <1.22E-03 <9.78E-04 <1.50E-03 Ru-103 NA <2.49E-03 <2.19E-03 <1.79E-Oi <1.99E-03 <2.45E-03 <2.16E-03 <3.56E-03 <1.46E-03 <1.66E-03 <2.OOE-03 <2.22E-03 Ru-106 NA <1.28E-02 <1.06E-02 <7.52E-03 <9.53E-03 <1.31E-02 <1.12E-02 <1.71E-02 <7.23E-03 <1.26E-02 <9.05E-03 <1.15E-02 Ce-141 NA <2.93E-03 <2.76E-03 <2.09E-03 <1.79E-03 <3.43E-03 <2.32E-03 <3.90E-03 <1.89E-03 <3.01 E-03 <2.59E-03 <2.44F,-03 Ce-144 NA <4.74E-03 <5.18E-03 <3.77E-03 <3.09E-03 <5.55E-03 <4.06E-03 <6.56E-03 <3.16E-03 <4.17E-03 <4.28E-03 <4.09E-03 Fc-59 NA <6.89E-03 <5.95E-03 <7.95E-03 <4.87E-03 <4.59E-03 <2.11 E-03 <1.03E-02 <3.94E-03 <9.38E-03 <4.63E-03 <8.65E-03 Zn-65 NA <2.89E-03 <2.66E-03 <2.53E-03 <1.81E-03 <3.39E-03 <7.78E-04 <3.84E-03 <2.30E-03 <3.69E-03 <2.64E-03 <3.55E-03 Co-60 NA <1.07E-03 <d.84E-04 <1.IIE-03 <1.11E-03 <136E-03 <1.74E-03 <1.83E-03 <I.39E-03 <1.46E-03 <8.08E-04 <1.21E-03 K-40 NA .029+o006 .041t.006 <3.95E-03 .024+0O5 .0451.007 <1.19E-02 <1.52E-02 .020L005 .043+008 .036+006 <4.29E-03 Ba/La-140 NA <I.11 E-02 <1.02E-02 <1.70F,-02 <9.38E-03 <1.39E.02 <232E-02 <1.99E-02 <1.56E-02 <1.26E-02 <1.09E-02 <2.14E-02 (20)

Table 3-4 C 13 Week Composite Air Sample Analysis 3rd Quarter 2004 iRadionuclide lLLD l - I I I 11 I Ra-226 NA 1.79E-02 1.86E-02 3.60E-02 2.12E-02 2.03E-02 1.48E-02 2.31E-02 3.40E-02 2.12E-02 1.59E-02 1.25E-02 1.89E-02 Cr-Si NA 2.58E-02 2.70E-02 4.74E-02 2.14E-02 2.37E-02 2.25E-02 3.27E-02 5.93E-02 3.26E-02 2.31E-02 1.46E-W2 2.73E-02 1-131 7.OOE-01 1.75E-02 1.68E-02 1.75E-02 1.85E-02 1.24E-02 1.32E-02 1.57E-02 1.97E-02 1.50E-02 1.99E-02 1.01E-02 1.65E-02 Be-7 NA 0.089:0.Oi1 0.09710.015 0.109LO.015 0.075+0.014 0.097+/-0.010 0.0820.013 0.11040.012 0.078LO.018 0.08910.012 0.08410.013 0.093IO.O11 O.1I8.0.O12 Cs-134 1.OOE-02 2.05E-03 1.59E-03 2.87E-03 1.9OE-03 1.41E-03 2.16E-03 2.32E-03 2.91E-03 23IE-03 1.98E-03 l.19E-03 1.48E-03 Cs-137 1.OOE-02 1.OSE-03 1.38E-03 2.27E-03 1.02E-03 1.09E-03 3.87E-04 I.98F,03 2.OOE-03 I.05E-03 1.20F,03 2.59E-04 1.39E-03 Zr-95 NA 3.81 E-03 4.39E-03 7.61 E-03 1.19E-03 3.37E-03 3.37E-03 3.71 E-03 9.38E-03 4.32F,03 3.81 E-03 3.50E-03 3.74E-03 Nb-95 NA 2.90E-03 2.85E-03 5.52E-03 3.35E-03 2.41E-03 1.02E-03 3.06E-03 5.29E-03 4.39E-03 2.47E-03 1.95E-03 2.89E-03 Co-58 NA 1.73F,03 2.1OE-03 4.57E-03 3.24R,03 2.34E-03 7.07F,04 2.39E-03 4.92E-03 3.05F,03 1.92F,03 1.52E-03 1.60E-03 5ln-54 NA 1.61E-03 1.90E-03 3.11 E-03 1.77E-03 1.24E-03 2.38E-03 1.98E-03 4.52E-03 1.81E-03 135E-03 1.71E-03 137E-03 Ru-103 NA 2.71E-03 2.25E-03 3.73E-03 2.69E-03 2.57E-03 2.19E-03 2.22E-03 3.32E-03 2.06E-03 1.60E-03 2.06E-03 2.20E03 Ru-106 NA I.57E-02 1.47E-02 2.34E-02 1.09E-02 1.02E-02 1.42E-02 1.38E-02 7.87E-03 1.59E-02 1.21 E-02 1.23E-02 1.43E-02 Ce-141 NA 3.43E-03 3.27E-03 4.25E-03 2.61 E-03 2.96E-03 2.61E-03 3.88E-03 6.44E-03 4.06E-03 2.63E-03 2.28E-03 2.86E-03 Ce-144 NA 5.31E-03 6.31 E-03 1.01E-02 4.41 E-03 4.41 E-03 5.89E-03 5.69E-03 9.62E-03 736E-03 6.47E-03 4.34E-03 6.42E-03 Fe-59 NA 7.36R,03 1.22F,02 1.34E-02 3.32R03 7.45E-03 3.46E-03 8.63F,03 6.58E-03 8.36E-03 2.81 R03 631E-03 7.60E-03 Zn-65 NA 3.04R03 5.71EF03 5.09E-03 1.34E-03 3.32E-03 3.76F,03 5.35E-03 1.05F,02 3.83E-03 3.08O03 8.93E-04 3.90E-03 Co-60 NA 1.60E-03 7.76E-04 2.06E-03 7.22E-04 1.48E-03 2.97E-03 1.43E-03 3.86E-03 1.55R03 6.04E-04 1.36E-03 1.26E-02 K-40 NA 0.0340.008 2.24E-02 0.058:0.011 2.08E-02 0.027&O.006 2.14E-02 0.045A0.009 1.44E-02 0.053M0.011 1.58E-02 4.79E-03 1.69E-02 Ba/La-140 NA 3.55E-03 7.09E-03 1.91 E-02 6.61 E-03 8.35E-03 2.32E-02 1.08E-02 3.52E-02 1.73E-02 5.67E-03 4.47E-03 9.55E-03 (21 )

Table 3-4 D 13 Week Composite Air Sample Analysis 4th Quarter 2004

. . . . . . . . .-. . I Ra-226 NA 2.54E-02 1.22E-02 237E-02 1.87E-02 1.64E-02 1.96E-02 1.42E-02 3.11E-02 1.82E-02 2.73E-02 I.90E-02 I.01 F-02 Cr-51 NA 2.53F,02 3.01E-02 3.92E-02 3.85E-02 2.98E-02 2.52E-02 3.68E-02 4.65F-O2 2.50E-02 3.24E-02 2.47F-02 2.69E-02 1.131 7.OOF-01 3.95E-02 1.95E-02 2.73E-02 2.91 R,02 2.95E-02 2.80E-02 2.93E-02 5.73E-02 3.92E-02 3.40E-02 2.63E-02 2.40E-02 lle-7 NA 6.94E-2 +.0141 7.17R-2 4.0112 7.24F,2 .014( 1.05E-1 +.0135 7.71E-21.0123 1.06E-1 i.0134 7.80F-2 +/-.0125 7.45E-2 +.0159 8.52E-2 E.0132 1.03E-I1 .0145 6.52E-2 +/- .0126 1.14E .0124 Cs-134 I.OOE-02 1.63E-03 I.57E-03 1.31E-03 2.1OE-03 1.56F-03 I.OOF,03 1.85E-03 2.68E-03 1.97E-03 1.84E-03 2.01E-03 1.53E-03 Cs-137 1.OOE-02 1.63F,03 1.I1E-03 2.28E-03 1.28E-03 1.35E-03 1.59E-03 1.39E-03 2.21 F,03 1.21 E-03 I.57E-03 1.06E-03 I.OOE-03 Zr-95 NA S.61 E-03 1.03E-03 1.40E-03 4.07E-03 3.20E-03 4.96E-03 4.79F-03 8.49E-03 3.81 E-03 659E-03 3.70E-03 3.16E-03 Nb-95 NA 4.93E-03 3.86E-03 4.48E-03 3.57E-03 2.83E-03 1.IOE-03 2.87E-03 7.50E-03 4.78E-03 4.96E-03 3.27E-03 3.25E-03 Co-58 NA 2.92E-03 1.89E-03 3.74E-03 2.79E-03 1.92E-03 2.58F-03 2.38E-03 4.58E-03 2.49E-03 1.93E-03 2.22E-03 I.OOE-03 NMn-54 NA 1.54E-03 1.27E-03 2.SOE-03 1.53E-03 1.OOE-03 1.72F-03 2.07E-03 1.73E-03 1.42E-03 2.IOE-03 1.48E-03 1.48E-03 Ru-103 NA 3.01 E-03 2.44E-03 3A6E 03 3.22E-03 2.52E-03 3.24E-03 2.31 E-03 3.65E-03 1.61 E-03 4.OOE-03 2.53E-03 1.77E-03 Ru-106 NA I.52E-02 1.13E-02 1.21E-02 1.39E-02 1.63E-02 2.03E-02 1.58E-02 1.93E-02 1.47E-02 1.71E-02 1.45E-02 7.42E-03 Ce-141 NA 2.85E-03 3.23E-03 3.75E-03 3.85E-03 2.94E-03 2.84E-03 4.53E-03 S.58E-03 2.81E-03 S.79E-03 2.94E-03 2.41E-03 Ce-144 NA 5.44E-03 S.83E-03 5.72E-03 6.17E-03 4.89E-03 5.74E-03 6.32E-03 7.74E-03 4A2E-03 8.60E-03 5.65E-03 4A3E-03 Fe-S9 NA 4.07E-03 1.09E-02 3.82E-03 7.58E-03 9.26E-03 9.81 E-03 3.151-03 1.80E-02 8.13E-03 138E-02 1.07F,02 6.31IE-03 Zn-65 NA 5.12E-02 4.47E-03 5.65E-03 3.40E-03 4.24E-03 356R-03 1.1 5E-03 4.97E-03 4.18E-03 4.18E-03 4.90E-03 1.OOE-03 Co-60 NA 7.91 E-04 1.46E-03 7.40E-04 1.86E-03 1.78F,03 2.38E-03 I.OOE-03 2.72E-03 1.43E-03 1.80E-03 2.06E-03 1.21 E-03 K-40 NA 7.98E-03 S.60E-03 2.02-02 153E-02 2.38E-02 6.99E-03 6.06E-03 2.50E-02 5.47F,03 1.87E-02 7.62E-03 1.26E-02 Ba/IL-140 NA 3.59E-02 3.04E-02 2.74E-02 2.74E-02 2.46E-02 1.00F,02 2.34F,02 6.05E-02 7.76E-03 2.75E-02 1.09E-02 6.62E-03 (22)

Table 3-5 Charcoal Cartridges Gamma Analysis for Iodine Results in pCi/IM3 Collection Station #2 Station #4 Station #7 Station #8 Station #9 Station #11 Date 5-Jan <0.022 <0.021 <0.018 <0.020 <0.039 <0.015 12-Jan <0.017 <0.021 <0.023 <0.024 <0.041 <0.016 20-Jan <0.023 <0.014 <0.013 <0.013 <0.035 <0.018 26-Jan <0.034 <0.023 <0.024 <0.018 <0.053 <0.019 2-Feb <0.030 <0.017 <0.026 <0.023 <0.046 <0.021 9-Feb <0.033 <0.021 <0.021 <0.021 <0.053 <0.022 16-Feb <0.025 <0.019 <0.026 <0.016 <0.041 <0.017 23-Feb <0.025 <0.013 <0.023 <0.021 <0.044 <0.018 1-Mar <0.021 <0.013 <0.017 <0.017 <0.029 <0.021 8-Mar <0.022 <0.024 <0.027 <0.019 <0.035 <0.016 15-Mar <0.026 <0.014 <0.016 <0.013 <0.030 <0.021 22-Mar <0.062 <0.015 <0.027 <0.022 <0.032 <0.019 29-Mar <0.030 <0.016 <0.016 <0.019 <0.044 <0.021 6-Mar <0.013 <0.016 <0.019 <0.016 <0.039 <0.010 12-Apr <0.022 <0.022 <0.023 <0.025 <0.025 <0.020 20-Apr <0.026 <0.013 <0.015 <0.020 <0.037 <0.017 26-Apr <0.035 <0.017 <0.011 <0.016 <0.035 <0.019 4-May <0.021 <0.015 <0.022 <0.021 <0.035 <0.019 11-May <0.015 <0.016 <0.017 <0.020 <0.043 <0.023 18-May <0.019 <0.013 <0.017 <0.028 <0.051 <0.024 24-May <0.025 <0.022 <0.029 <0.016 <0.048 <0.023 2-Jun <0.016 <0.013 <0.019 <0.016 <0.019 <0.021 8-Jun <0.034 <0.017 <0.026 <0.015 <0.040 <0.062 15-Jun <0.006 <0.023 <0.017 <0.013 <0.031 <0.023 22-Jun <0.021 <0.039 <0.029 <0.016 <0.036 <0.025 29-Jun <0.018 <0.022 <0.029 <0.012 <0.027 <0.029 6-Jul <0.017 <0.026 <0.024 <0.012 <0.034 <0.020 12-Jul <0.026 <0.041 <0.030 <0.026 <0.041 <0.025 19-Jul <0.017 <0.034 <0.026 <0.029 <0.029 <0.041 27-Jul <0.019 <0.017 <0.014 <0.016 <0.025 <0.020 3-Aug <0.023 <0.035 <0.027 <0.023 <0.050 <0.017 9-Aug <0.019 <0.008. <0.018 <0.021 <0.029 <0.025 16-Aug <0.020 <0.033 <0.018 <0.025 <0.044 <0.032 23-Aug <0.022 <0.025 <0.018 <0.022 <0.041 <0.025 30-Aug <0.027 <0.043 <0.028 <0.039 <0.054 <0.031 7-Sep <0.020 <0.005 <0.013 <0.020 <0.036 <0.004 14-Sep <0.011 <0.032 <0.017 <0.029 <0.050 <0.025 21-Sep <0.019 <0.024 <0.025 <0.034 <0.027 <0.015 28-Sep <0.024 <0.029 <0.015 <0.017 <0.030 <0.021 4-Oct <0.026 <0.026 <0.017 <0.020 <0.030 <0.023 11-Oct <0.021 <0.024 <0.021 <0.028 <0.036 <0.016 18-Oct <0.017 <0.028 <0.012 <0.020 <0.041 <0.029 25-Oct <0.024 <0.034 <0.017 <0.015 <0.030 <0.032 2-Nov <0.018 <0.037 <0.015 <0.023 <0.049 <0.027 8-Nov <0.019 <0.039 <0.02 <0.030 <0.058 <0.028 16-Nov <0.024 <0.043 <0.012 <0.013 <0.028 <0.024 22-Nov <0.022 <0.032 <0.018 <0.021 <0.043 <0.028 29-Nov <0.016 <0.020 <0.015 <0.025 <0.034 <0.021 6-Dec <0.018 <0.016 <0.019 <0.027 <0.046 <0.015 13-Dec <0.017 <0.027 <0.014 <0.015 <0.038 <0.018 20-Dec <0.020 <0.028 <0.022 <0.019 <0.037 <0.024 27-Dec <0.023 <0.029 <0.012 <0.018 <0.043 <0.025 (23)

3.3 Water Samples Water samples are collected on a schedule specified in the ODCM, from locations surrounding the plant to assess ifthere is any measurable influence upon, or contamination of, drinking or irrigation water from liquid effluent releases, or deposition from gaseous effluent releases.

Samples are collected weekly from Lake Ontario, upstream (Russell Station or Monroe County Water Authority - Shoremont) and downstream (Ontario Water District Plant - OWD), composited monthly, and analyzed for gross beta activity, Table 3-8.

There was no statistically significant difference between the upstream and downstream sample concentrations. The 2004 averages were 2.23 pCiAiter and 2.62 pCi/liter for the upstream and downstream samples respectively. Gamma isotopic analysis of the monthly composite samples showed no statistically significant difference in activity between the upstream and downstream samples.

Gross beta peaks of up to 10 pCilliter can occur when the lake is stirred up by wind and the weekly sample includes large quantities of suspended silt.

Weekly samples are taken from the plant circulating water intake (Circ In) and discharge canal (Circ Out), and composited monthly. The 2004 averages were 2.23 pCi/liter and 2.16 pCi/liter for the intake and discharge canal respectively. These are essentially the same as the upstream and downstream values as they fall within the

+ 1 sigma error band and range of the measurement.

Results for all water beta analyses are listed in Table 3-8 .

Samples of the creek which crosses the site are collected and analyzed monthly.

Deer Creek gross beta values are typically higher than other surface water samples due to Radon progeny in the soils from which the creek recharges and over which the creek flows.

24

Isotopic Analysis Gamma isotopic analysis is performed on each monthly composite sample. These are listed in Tables 3-9 to 3-14 and are separated by source of sample. No anomalous results were noted.

Tritium Analysis Tritium analysis was performed on all water samples on a monthly basis.

Composites are made from the weekly samples and a portion filtered to remove interferences for analysis by beta scintillation. Tritium data is given in Table 3-14.

Radioiodine analysis All monthly composite water samples are analyzed for lodine-1 31. The analysis allows the determination of lodine-1 31 activity of <1 pCi/liter. Radioiodine data is given in Table 3-15. Any positive counts and the 1 sigma error are reported. During 2004, no sample results indicated 1-1 31 activity in excess of the LLD for the analysis.

25

R. E. Ginna Nuclear Power Plant Table 3-8 Environmental Water Samples Gross Beta Analysis Results in pCiLliter Month Control O.W.D. Circ In Circ Out Deer Creek January 2.31 +/- 0.46 3.84 +/- 0.52 3.27 +/- 0.50 3.74 +/- 0.51 3.62 +/- 0.58 February 2.27 +/- 0.48 3.24 +/- 0.52 1.53 +/- 0.48 2.58 +/- 0.49 4.37 +/- 0.64 March 2.74 +/- 0.53 2.37 +/- 0.53 2.67 +/- 0.53 2.10 +/- 0.51 3.32 +/- 0.54 April 2.36 +/- 0.50 1.66 +/- 0.49 2.58 +/- 0.51 2.10 +/- 0.50 2.27 +/- 0.58 May 1.93 +/- 0.50 1.29 +/- 0.48 1.74 +/- 0.49 1.46 +/- 0.48 3.74 +/- 0.64 June 0.79 +/- 0.45 2.17 +/- 0.48 1.51 +/- 0.47 1.18 +/- 0.47 4.05 +/- 0.60 July 2.43 +/- 0.50 3.52 +/- 0.52 2.50 +/- 0.48 1.91 +/- 0.46 3.40 +/- 0.52 August 2.92 +/- 0.47 2.45 +/- 0.46 1.86 +/- 0.44 2.39 +/- 0.43 4.14 +/- 0.56 September 2.86 +/- 0.54 2.11 +/- 0.51 2.38 +/- 0.50 1.76 +/- 0.49 5.23 +/- 0.59 October 2.42 +/- 0.48 3.06 +/- 0.51 2.06 +/- 0.47 2.72 +/- 0.49 5.43 +/- 0.66 November 1.49 +/- 0.48 3.15 +/- 0.53 2.41 +/- 0.52 1.87 +/- 0.48 4.12 +/- 0.62 December 2.73 +/- 0.47 2.22 +/- 0.44 2.72 +/- 0.48 1.47 +/- 0.55 6.53 +/- 0.64 Maximum 2.92 +/- 0.54 3.84 +/- 0.53 3.27 +/- 0.53 3.74 +/- 0.55 6.53 +/- 0.66 Average 2.23 2.62 2.23 2.16 3.97 Minimum 0.79 +/- 0.45 1.29 +/- 0.44 1.51 +/- 0.44 1.18 +/- 0.43 2.27 +/- 0.52 (26)

R. E. Ginna Nuclear Power Plant Table 3-9 Control Water Gamma Isotopic Analysis Results In pCilLiter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 60Co 140Ba 226Ra January <22 <29 <2 <2 <5 <4 <2 <2 <3 < 25 <6 <15 <7 <5 < 2 <9 79*20 February <29 <34 <2 <3 <6 <4 <3 <3 <4 < 31 <6 < 18 <8 <4 <4 < 11 121+/-22 March <25 <30 <1 <3 <5 <4 <3 <2 <3 < 24 <6 < 18 <9 <5 < 3 <8 70+/-20 April <36 <48 <3 <4 <7 .< 5 <4 <3 <6 < 34 <8 < 25 < 12 < 10 <3 < 14 68+/-32 May <26 <32 <3 <3 <6 <4 <3 <2 <4 < 27 <6 <19 <9 <6 <3 <8 71+/-22 June <30 <36 <4 <3 <7 <5 <4 <3 <4 < 37 <6 <21 <10 <8 < 5 <9 80+/-30 July <41 <46 <3 <4 <8 <5 <5 <4 <5 < 51 <9 <28 <12 <9 < 4 < 13 95+/-32 August <48 <56 <6 <6 <10 <6 <7 <5 <6 < 57 <11 < 37 < 16 < 12 < 7 < 15 87+/-36 September <41 <42 <3 <4 <8 <5 <5 <5 <5 < 38 <7 < 24 < 14 < 10 <4 < 12 118+/-29 October <25 <35 <4 <3 <6 <5 <4 <3 <4 < 30 <5 < 18 < 10 <8 < 3 <9 155+/-24 November <35 <43 <5 <4 <9 <5 <5 <4 <6 < 41 <8 <26 <11 <6 <4 < 11 109+/-31 December <30 <40 <4 <4 <6 <5 <4 <4 <5 < 33 <8 <23 <11 <9 < 4 < 11 60+/-31 (27)

R. E. Ginna Nuclear Power Plant Table 3-10 Ontario Water District Water Gamma Isotopic Analyses Results In pClILlter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 60Co 14OBa 226Ra January <37 <40 <3 <4 <7 <5 <4 <3 <5 <40 <8 <22 < 10 <9 < 4 < 10 69+/-29 February <28 <31 <3 <3 <5 <4 <2 <3 <4 <28 <6 < 18 <9 <8 <3 <6 53+/-22 March <29 <33 <2 <3 <6 <4 <3 <3 <4 <34 <6 < 21 < 9 <7 <3 <8 105+/-26 April <32 <45 <4 <4 <7 <5 <4 <3 <5 <32 <5 < 25 < 9 <8 <3 <8 66+/-27 May <48 <59 <4 <6 <9 <7 <5 <5 <6 <54 <10 <29 <17 <12 <5 <15 83+/-44 June <23 <29 <3 <3 <5 <3 <3 <3 <3 <27 <4 < 15 <7 <6 < 3 <7 115+/-21 July <36 <44 <2 <4 <8 <5 <5 <3 <5 <35 <8 <28 <13 <8 < 3 <10 <92 August <49 <47 <6 <6 <9 <6 <6 <5 <7 <49 <9 <29 <17 <12 < 4 <13 < 101 September <23 <31 <2 <2 <5 <3 <3 <3 <2 <27 <6 < 19 <7 <3 < 2 <6 69+/-20 October <29 <25 <4 <3 <7 <5 <4 <3 <5 <31 <7 <23 < 10 <7 <4 <7 44+/-27 November <24 <32 <4 <3 <6 <4 <4 <4 <4 <32 <5 < 17 < 11 <8 <3 <8 135+/-23 December <35 <39 <5 <4 <8 <6 <5 <4 <6 <42 <8 <24 <13 <10 <4 <12 88+/-30 (28)

R. E. Ginna Nuclear Power Plant Table 3-11 Circ-In Water Gamma Isotopic Analyses Results in pCilLiter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 6OCo 140Ba 226Ra January <29 <38 <2 <3 <5 <4 <3 <3 <4 <32 <7 < 21 <7 <7 <3 <7 92+/-26 February <21 <28 <I <2 <4 <3 <3 <2 <3 <24 <5 < 18 <6 <3 < 2 <5 71+/-19 March < 24 < 27 <1 <2 <5 <3 <3 <2 <3 <23 <5 < 17 <8 <6 < 3 <5 72+/-23 April <30 <37 <4 <4 <7 <5 <4 <4 <5 <35 <7 < 22 < 11 <8 < 4 < 11 < 66 May <35 <44 <4 <3 <9 <5 <4 <4 <5 <36 <7 < 21 <13 <8 < 4 < 10 131+/-31 June <26 <31 <3 <3 <5 <3 <3 <3 <4 <28 <6 < 19 <9 <6 <3 < 8 < 54 July <47 <50 <5 <5 <9 <7 <6 <5 <7 <51 <9 <30 < 16 < 15 <4 < 15 148+/-41 August <39 <50 <6 <4 <9 <6 <5 <4 <5 <45 <10 < 32 < 16 < 13 <5 <14 <96 September <29 <33 <3 <3 <6 <4 <3 <2 <4 <35 <6 < 20 <10 <7 < 3 < 8 62+/-22 October <38 <44 <5 <4 <8 <6 <5 <5 <6 <40 <8 < 26 < 17 < 10 < 5 < 10 88+/-39 November <26 <34 <2 <3 <5 <4 <4 <3 <4 <30 <7 < 23 <9 <7 < 3 < 7 69+/-26 December <30 <40 <4 <4 <6 <5 <4 <4 <5 <33 <8 < 23 < 11 <9 < 4 < 11 < 76 (29)

R. E. Ginna Nuclear Power Plant Table 3-12 Circ-Outlet Water Gamma Isotopic Analyses Results In pCI/Liter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 60Co 1401a 226Ra January <31 <41 <3 <3 <7 <4 <4 <3 <4 <35 <7 <22 < 11 *< 8 <3 <9 153+/-31 February <27 <28 <3 <3 <5 <3 <3 <3 <4 <26 <6 < 19 <8 <6 <3 <6 <62 March < 21 < 25 <3 <2 <5 <3 <3 <3 <3 <24 <3 <14 <8 <5 <3 <5 145+/-19 April <23 <31 <2 <3 <5 t4 <3 <3 <3 <25 <6 < 19 <7 <3 <3 <6 76+/-22 May <34 <42 <2 <3 <6 <4 <4 <3 <4 <33 <7 <25 <10 <8 <3 <8 58+/-28 June <26 <28 <1 <3 <5 <3 <3 <2 <4 <26 <5 <19 <9 <5 <3 <8 70+/-25 July <47 <49 <4 <5 <8 <7 <5 <6 <5 <40 <9 <27 < 14 <9 <5 <14 138+/-36 August <41 <47 <5 <5 <10 <5 <5 <4 <6 <42 <8 < 32 < 14 < 10 <5 <11 76+/-33 September <31 <39 <3 <3 <7 <5 <4 <3 <4 < 40 <7 <23 < 12 <9 <4 < 10 96+/-27 October < 33 < 36 <4 <4 <7 <4 <4 <4 <5 <29 <7 <22 <11 <8 <5 <9 <66 November <45 <41 <3 <4 <7 <6 <6 <5 <6 <41 <8 <27 < 16 <10 <5 <12 93+/-34 December <33 <38 <4 <4 <8 <5 <4 <3 <5 <33 <8 <22 <11 <7 <4 <8 <76 (30)

R. E. Ginna Nuclear Power Plant Table 3-13 Deer Creek Water Gamma Isotopic Analyses Results in pCilLiter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 6OCo 140Ba 226Ra January <39 <46 <3 <5 <7 <5 <5 <6 <5 <42 <8 <38 <11 <12 <5 <5 <117 February <34 <48 <6 <5 <6 <6 <5 <5 <5 <49 <9 <31 < 17 < 14 <7 < 8 129+/-44 March <40 <42 <6 <6 <8 <5 <6 <7 <5 <59 <7 <34 <17 <14 <6 < 10 < 109+/-46 April <38 <44 <3 <5 <8 .~5 <5 <5 <5 <48 <9 <36 <11 <11 <5 <4 < 113 May <37 <39 <6 <5 <8 <4 <5 <5 <5 <52 <8 <36 <12 <10 <5 <6 < 109 June <34 <42 <3 <5 <7 <4 <5 <4 <5 <49 <8 <36 <12 <12 <4 <5 101+/-44 July <44 <46 <6 <6 <9 <6 <6 <5 <6 <60 <9 <37 <15 <15 <5 <7 < 128 August <40 <36 <5 <5 <10 <5 <4 <6 <6 <49 <7 <28 <14 <11 <8 < 8 139+/-44 September <34 <34 <4 <4 <8 <4 <4 <5 <4 <39 <6 <24 <12 <11 <3 < 4 167+/-34 October <35 <32 <5 <5 <8 <5 <4 <5 <5 <51 <8 <36 <11 <11 <5 <6 <113 November <37 <44 <4 <5 <9 <5 <5 <5 <4 <49 <9 <34 <13 <13 <5 <5 86+/-39 December <38 <37 <4 <4 < 10 <6 <5 <5 <5 <46 <8 <33 <14 <13 <6 <6 < 119 (31)

R.E. Ginna Nuclear Power Plant Table 3-14 2004 Environmental Water Samples Tritium Analysis Results in pCi/Liter Month Control O.W.D. Circ In Circ Out Deer Creek January <215 <214 <215 <215 <225 February <220 <219 <223 <218 <226 March <221 <225 <222 <221 <225 April <213 <212 <213 <211 <221 May <214 <212 <214 <212 <226 June <217 <218 <219 <226 <227 July <206 <208 <214 <209 <221 August <207 <200 <207 <204 <210 September <631 <643 <628 <624 <649 October <221 <223 <237 <221 <643 November <609 <612 <616 <614 <639 December <220 <220 <221 <218 <229 (32)

R. E. Ginna Nuclear Power Plant Table 3-15 Radiolodine In Water Results in pCiLliter Month Control O.W.D. Circ In Clrc Out Deer Creek January <0.67 <0.44 <0.56 <0.52 <0.45 February <0.64 <0.49 <0.42 <0.49 <0.46 March <0.91 <0.52 <0.41 <0.52 <0.44 April <0.62 <0.51 <0.42 <0.47 <0.44 May <0.59 <0.55 <0.41 <0.45 <0.40 June <0.40 <0.52 <0.54 <0.41 <0.52 July <0.51 <0.34 <0.40 <0.39 <0.41 August <0.41 <0.51 <0.54 <0.45 <0.55 September <0.58 <0.41 <0.48 <0.41 <0.48 October <0.58 <0.43 <0.39 <0.39 <0.38 November <0.73 <0.51 <0.54 <0.62 <0.34 December <0.52 . <0.42 <0.38 <0.42 <0.39 (33)

3.4 Milk Samples There were two indicator dairy herds located three to five miles from the plant on 1/1/04. The owner of previous indicator farm C retired early In 2002, and a change to the ODCM was submitted to reflect this. Milk samples are collected monthly during November through May from one of the indicator farms and biweekly during June through October from each. A control farm sample is taken for each monthly sample and once during each biweekly period. The milk is analyzed for lodine-131 and also analyzed by gamma spectroscopy for major fission products.

All positive counts and the +/-1 sigma error are reported. During 2004, no samples indicated 1-131 activity that exceeded the LLD for the analysis.

Table 3-16 is a listing of all samples collected during 2004 with analytical results.

34

Table 3-16 Milk Results in pClILlter Farm Date K-40 Cs-134 Cs-137 Ba-140 1-131 FARM B 01/13/04 1463i81 <7 <7 <9 <0.37 FARM C 01/13/03 1577i67 <5 <5 <5 <0.37 FARM A 02/11/04 1470i90 <7 <8 <7 <0.54 FARM C 02/11/04 1690+/-76 <6 <6 <6 <0.42 FARM B 03/09/04 1450+/-80 <7 <6 <8 <0.53 FARM C 03/09/04 1460+/-64 <6 <6 <6 <0.45 FARM A 04/13/04 1590+/-82 <4 <8 <9 <0.37 FARM C 04/13/04 1500+/-80 <6 <7 <8 <0.36 FARM B 05/11/04 1440+/-83 <7 <8 <7 <0.47 FARM C 05/11/04 1500+/-68 <6 <7 <6 <0.41 FARM A 06/08/04 1710+/-80 <8 <7 <9 <0.41 FARM B 06/08/04 1490+/-101 <8 <9 <11 <0.46 FARM C 06/08/04 1500+/-79 <6 <7 <8 <0.53 FARM A 06/22/04 1570+/-104 <8 <7 <11 <0.52 FARM B 06/22/04 1490+/-80 <6 <7 <6 <0.42 FARM C 06/22/04 1520+/-79 <7 <7 <7 <0.38 FARM A 07/06/04 1500+/-71 <6 <5 <6 <0.36 FARM B 07/06/04 1720+/-81 <5 <7 <8 <0.48 FARM C 07/06/04 1690+/-57 <3 <5 <5 <0.38 FARM A 07/20/04 1780+/-101 <9 <9 <12 <0.41 FARM B 07/20/04 1660+/-69 <4 <5 <7 <0.35 FARM C 07/20/04 1620+/-115 <10 <9 <8 <0.37 FARM A 08/03/04 1400+/-80 <7 <6 <8 <0.45 FARM B 08/03/04 1570+/-93 <7 <7 <8 <0.53 FARM C 08/03/04 1450+/-84 <7 <7 <7 <0.41 FARM A 08/17/04 1560+/-92 <7 <9 <8 <0.39 FARM B 08/17/04 1440+/-79 <6 <7 <7 <0.36 FARM C 08/17/04 1380+/-78 <6 <8 <5 <0.40 FARM A 08/31/04 1470+/-103 <9 <10 <11 <0.48 FARM B 08/31/04 1590+/-84 <7 <7 <7 <0.36 FARM C 08/31/04 1660+/-61 <3 <5 <3 <0.34 FARM A 09/13/04 1540+/-81 <7 <6 <10 <0.57 FARM B 09/14/04 1320+/-75 <6 <7 <8 <0.44 FARM C 09/13/04 1520+/-77 <6 <7 <6 <0.37 FARM A 09/28/04 1510+/-79 <7 <8 <8 <0.48 FARM B 09/28/04 1410+/-76 <7 <6 <7 <0.37 FARM C 09/28/04 1700+/-88 <9 <8 <9 <0.33 FARM A 10/12/04 1560+/-102 <10 <9 <8 <0.43 FARM B 10/12/04 1410+/-77 <7 <7 <7 <0.37 FARM C 10/12/04 1560+/-82 <7 <7 <9 <0.53 FARM A 10/26/04 1370+/-96 <9 <9 <11 <OA9 FARM B 10/26/04 1660+/-83 <6 <6 <7 <0.34 FARM C 10/26/04 1480+/-78 <7 <6 <7 <0.34 FARM B 11/10/04 1390+/-81 <7 <8 <10 <0.79 FARM C 11/10/04 1430+/-62 <5 <5 <6 <0.68 FARM A 12/14/03 1580+/-86 <8 <7 <8 <0.37 FARM C 12/14/03 1760+/-73 <6 <6 <6 <0.39 (35)

3.5 Fish Samples Indicator fish are caught in the vicinity of the Discharge Canal and analyzed for radioactivity from liquid effluent releases from the plant. The fish are filleted to represent that portion which would normally be eaten. Additional fish are caught more than 15 miles away to be used as control samples and are prepared in the same manner.

Four different species of fish are analyzed during each half-year from the indicator and background locations if they are available. There was no statistically significant difference in the activity of the fish caught between the indicator and control locations.

Fish are caught by R. E. Ginna Nuclear Power Plant environmental staff and are analyzed by gamma spectroscopy after being held for periods of less than one week to keep the LLD value for the shorter half-life isotopes realistic. Detection limits could also be affected by small mass samples, (c 2000 grams), in some species.

Gamma isotopic concentrations (pCi/kilogram wet) are listed in Tables 3-17A, and 3-17B.

36

3.5 Fish Samples Indicator fish are caught in the vicinity of the Discharge Canal and analyzed for radioactivity from liquid effluent releases from the plant. The fish are filleted to represent that portion which would normally be eaten. Additional fish are caught more than 15 miles away to be used as control samples and are prepared in the same manner.

Four different species of fish are analyzed during each half-year from the indicator and background locations if they are available. There was no statistically significant difference in the activity of the fish caught between the indicator and control locations.

Fish are caught by R. E. Ginna Station environmental staff and are analyzed by gamma spectroscopy after being held for periods of less than one week to keep the LLD value for the shorter half-life isotopes realistic. Detection limits could also be affected by small mass samples, (< 2000 grams), in some species.

Gamma isotopic concentrations (pCi/kilogram wet) are listed in Tables 3-17A, and 3-17B.

36

R. E. Ginna Nuclear Power Plant Table 3-17A Fish Samples Gamma Isotopic Analysis Results in pCl/kgm Wet Description 226Ra 51Cr 131 1 134Cs 137Cs 103Ru 106Ru 141Ce 144Ce Indicator Fish First Half 2004 Chinook Salmon 252+/-98 < 1570 < 1260 < 17 < 16 < 91 < 176 < 159 < 96 Carp <520 < 426 < 350 < 31 < 29 < 37 < 300 < 62 < 164 BrownTrout 406+190 < 341 < 222 < 32 < 27 < 43 < 284 < 53 <148 Small Mouth Bass 484+/-216 < 534 < 419 < 39 < 35 < 60 < 444 < 73 <186 Small Mouth Bass 726+/-210 < 419 < 200 < 21 < 31 < 39 < 337 < 66 < 186 Second Half 2004 Chinook Salmon 705+/-217 < 304 < 56 < 35 < 31 < 30 < 306 < 47 < 185 Lake Trout 726+/-156 < 201 < 43 < 26 < 25 < 24 < 268 < 27 <100 BrownTrout 599+/-195 < 255 < 53 < 33 < 40 < 36 < 365 < 42 <164 Small Mouth Bass 432+/-156 < 202 < 40 < 17 < 26 < 27 < 271 < 36 < 120 Background (Control) Fish First Half 2004 Smallmouth Bass <488 < 236 < 91 < 25 < 26 < 31 < 295 < 37 < 121 White Sucker 660+/-214 < 253 < 44 < 27 < 29 < 30 < 275 < 41 < 162 Freshwater Drum 418+/-1130 < 2620 < 5280 < 12 < 128 < 220 < 271 < 123 < 95 Carp 702+/-194 < 829 < 5570 < 27 < 25 < 65 < 289 < 102 < 150 Second Half 2004 <494 < 208 < 34 < 32 < 33 < 30 < 287 < 36 < 144 Chinook Salmon 411+/-135 < 188 < 37 < 17 < 20 < 21 < 194 < 27 < 99 Freshwater Drum 484+/-102 < 241 < 151 < 16 21+/-7 < 21 < 164 < 27 < 75 Brown Trout 394+/-115 < 150 < 33 < 18 < 19 < 19 < 188 < 25 < 85 White Sucker 703+/-168 < 233 < 81 < 31 < 24 < 29 < 332 < 36 < 107 (37)

R. E. GInna Nuclear Power Plant Table 3-17B Fish Samples Gamma Isotopic Analysis Results In pCi/kgm Wet Description 95Zr 95Nb 58Co 54Mn 59Fe 65Zn 6OCo 40K 140Ba Indicator Fish First Half 2004 Chinook Salmon < 88 < 114 < 38 < 19 < 238 < 51 < 18 4700+/-158 < 4610 Carp < 66 < 49 < 39 < 34 < 126 < 86 < 36 4590+/-308 < 198 BrownTrout < 59 < 44 < 33 < 33 < 132 < 78 < 34 3680*266 < 150 Small Mouth Bass < 86 < 56 < 52 < 37 < 169 < 108 < 48 5930+/-424 < 142 Small Mouth Bass < 63 < 41 < 37 < 32 < 107 < 78 < 29 5630+/-270 < 88 Second Half 2004 ChinookSalmon < 52 < 37 < 37 < 35 < 90 < 75 < 31 6160+/-288 < 36 LakeTrout < 47 < 28 < 25 < 28 < 73 < 57 < 26 4030+/-239 < 51 Brown Trout < 60 < 41 < 31 < 36 < 107 < 92 < 46 6280+/-361 < 34 SmallMouth Bass < 48 < 29 < 28 < 26 < 76 < 67 < 31 5250+/-253 < 53 Control (Background) Fish First Half 2004 Smallmouth Bass < 54 < 37 < 30 < 30 < 98 < 69 < 34 4780+/-261 < 68 WhiteSucker < 50 < 31 < 28 < 30 < 70 < 70 < 29 5410+/-233 < 35 FreshwaterDrum < 95 < 161 < 53 < 22 < 241 < 31 < 17 4680+/-135 < 9910 Carp < 95 < 85 < 40 < 31 < 177 < 48 < 30 5300+/-242 < 1050 Second Half 2004 Chinook Salmon < 37 < 23 < 20 < 18 < 61 < 44 < 21 4660+/-204 < 34 Freshwater Drum < 30 < 28 < 18 < 19 < 65 < 41 < 19 3400+/-165 < 79 Brown Trout < 34 < 24 < 19 < 19 < 61 < 43 < 18 4070+/-184 < 33 White Sucker < 49 < 31 < 32 < 32 < 92 < 76 < 30 3300+/-260 < 56 (38)

3.6 Sediment Samples Samples of shoreline sediment are taken upstream (Russell Station or Monroe County Water Authority - Shoremont) and downstream (Ontario Water District) of Ginna Station.

Results of the gamma isotopic analysis for sediment are included in Table 3-18, along with benthic sediment and cladaphora from Lake Ontario.

39

Rochester Gas and Electric Table 3-18 Sediment Samples Gamma Isotopic Analysis Results in pCilkg (wet)

Description Collection Date 226Ra 51Cr 131 1 134Cs 137Cs 103 Ru Ru 106 141 Ce 144Ce Shoreline Sediment (I) 04/22/04 562+/-232 <286 <77 <36 22+/-12 <36 <43 <52 <182 Shoreline Sediment (C) 04/21/04 418+/-224 <300 <78 <34 <40 <33 <261 <186 <50 Shoreline Sediment (I) 09/17/04 637+/-26 <30 <61 <40 <40 <35 <301 <52 <197 Shoreline Sediment (C) 09/17/04 1190+/-249 <336 <59 <42 <33 <30 <288 <48 <156 Benthic Sediment (I) 09/25/04 2410+/-583 <815 <316 <79 131+/-34 <69 <781 <126 <384 Cladaphora (I) 10/7/2004 504+/-74 <78 <13 <6 11+/-4 <9 <84 <12 <45 95Zr 95Nb 58Co 54Mn 59Fe 65Zn 6OCo 40K 140Ba Shoreline Sediment (I) 04/22/04 <68 <49 <43 <32 <116 <61 <45 11700+/-448 <67 Shoreline Sediment (C) 04/21/04 <68 <51 <49 <37 <119 <91 <38 7630+/-438 <89 Shoreline Sediment (I) 09/17/04 <81 <41 <36 <36 <119 <103 <45 11800+/-531 <55 Shoreline Sediment (C) 09/17/04 <56 <53 <35 <35 <120 <108 <38 9400+/-461 <65 Benthic Sediment (I) 09/25/04 <132 <120 <93 <77 <263 <141 <101 19200+/-976 <286 Cladaphora (I) 10/7/2004 <16 <11 <9 <9 <26 <13 <9 3160+/-108 <12 (I) = Indicator (C) = Control (40)

3.6 Vegetation Samples Crops are grown on the plant property in a location with a highest off-site meteorological deposition parameter, and samples of the produce are collected at harvest time for analysis.

Control samples are purchased from farms greater than ten miles from the plant, (Gro-Moore Farm Market in Henrietta, New York).

There was no indication in the samples of any measurable activity other than naturally occurring K-40 and Ra-226.

Gamma isotopic data is given in Table 3-19.

41

Table 3-19 Vegetation Samples Gamma Isotopic Analysis Results in pCilkg (wet)

Collection Description Date Indicator Vegetation 226Ra 51Cr 131 1 134Cs 137Cs 103 Ru Ru 106 141 Ce 144Ce Cherries 07/09/04 235+/-45 <58 <16 <4 <6 <7 <61 <11 <39 Tomatoes SSE 09/07/04 209+/-49 <49 <9 <7 <8 <8 <69 <9 <36 Lettuce SSE 07/26/04 155+/-72 <83 <12 <8 <10 <10 <116 <14 <72 Lettuce ESE 07/26(04 358+/-119 <112 <17 <16 <18 <14 <192 <19 <80 Tomatoes ESE 09/07/04 <115 <47 <7 <7 <7 <6 <64 <8 <36 Apples S 09/15/04 <112 <54 <11 <5 <7 <7 <57 <10 <36 Apples SSE 09/15/04 194+/-57 <72 <15 <9 <9 <10 <82 <11 <45 Squash ESE 08/16(04 352+/-115 <111 <17 <19 <16 <15 <155 <19 <82 Control (Background) Vegetation Squash 08/10/04 <254 <1 00 <12 <17 <17 <15 <131 <19 <84 Cherries 07/19/04 128+/-42 <43 <7 <6 <7 <6 <59 <7 <31 Lettuce 08/10/04 495+/-255 <219 <34 <45 <42 <32 <393 <38 <167 Tomatoes 08/10/04 <197 <66 <10 <11 <11 <11 <105 <12 <55 Apples 09/17/04 189+/-50 <53 <10 <4 <6 <6 <59 <10 <39 Tomatoes 09/07/04 155+/-51 <46 <8 <5 <7 <7 <73 <9 <33 Indicator Vegetation 95Zr 95Nb 58Co 54Mn 59Fe 65Zn 6OCo 40K 140Ba Cherries 07/09/04 <1 <8 <7 <7 <17 <8 <6 2680+/-61 <12 Tomatoes SSE 09/07/0,4 <12 <8 <7 <7 <27 <19 <9 2360+/-84 <9 Lettuce SSE 07/26/0 4 <18 <10 <12 <12 <26 <29 <13 3420+/-122 <14 Lettuce ESE 07/26/0,4 <34 <16 <18 <18 <51 <47 <15 5130+/-215 <20 Tomatoes ESE 09/07/0 4 <10 <7 <6 <6 <16 <19 <7 2220+/-78 <8 Apples S 09/15/0,4 <11 <8 <8 <7 <21 <17 <7 938+/-57 <12 Apples SSE 09/15/0,4 <15 <8 <8 <7 <25 <20 <10 1017+/-76 <18 Squash ESE 08/16/0, 4 <29 <17 <14 <17 <51 <41 <19 2800+/-175 <29 Control (Background) Vegetation Squash 08/10/04 <32 <17 <11 <16 <50 <47 <17 2260+/-156 <17 Cherries 07/19/04 <10 <7 <6 <7 <19 <15 <7 2050+/-72 <9 Lettuce 08/10/04 <65 <37 <39 <46 <109 <108 <46 3950+/-367 <11 Tomatoes 08/10/04 <21 <12 <11 <11 <35 <26 <10 2420+/-128 <11 Apples 09/17/04 <11 <7 <6 <6 <16 <9 <5 1180+/-51 <8 Tomatoes 09/07/04 <11 <7 <7 <7 <21 <18 <8 2020+/-74 <10 (42)

3.7 External Penetratinq Radiation Thermoluminescent dosimeters, (TLD's), with a sensitivity of 5 millirem/quarter are placed as part of the environmental monitoring program. Thirty-nine TLD badges are currently placed in four rings around the plant. These rings range from less than 1000 feet to 15 miles and have been dispersed to give indications in each of the nine land based sectors around the plant should an excessive release occur from the plant.

Badges are changed and read after approximately 3 months exposure.

TLD locations #7 and #13 are influenced by close proximity to radioactive equipment storage areas and will normally read slightly higher than other locations. For the year of 2004, on-site exposure ranged between 8.8 - 17.0 mrem/quarter, with an average exposure of 12.0 mrem/quarter and off-site exposure ranged between 8.9 - 13.7 mrem/quarter with an average exposure of 10.7 mrem/quarter.

40 CFR 190 requires that the annual dose equivalent not exceed 25 millirems to the whole body of any member of the public. Using the annual average of control TLD stations as background and the highest site boundary TLD, leads to 6.4 millirem direct radiation dose to the hypothetical maximally exposed member of the public, off-site.

Table 3-20 gives TLD readings for each quarter.

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Rochester Gas and Electric Table 3-20 External Penetrating Radiation Thermoluminescent Dosimetry 2004 Units mrem/91 Day Quarter Location Type 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

2-#7plus #13 are 2 1 11.1 t 2.8 11.1 +/- 2.8 12.0 +/- 3.0 12.9 +/- 3.2 on-site near the line 3 1 10.7 +/- 2.7 11.5 +/- 2.9 11.9 +/- 3.0 13.2 +/- 3.3 ofthehighestannual 4 1 11.7 +/- 2.9 11.4 +/- 2.9 12.1 +/- 3.0 12.9 +/- 3.2 average ground level 5 1 12.1 +/- 3.0 13.4 +/- 3.4 13.4 +/- 3.4 13.5 +/- 3.4 concentration. 6 1 8.8 +/- 2.2 10.3 +/- 2.6 12.0 +/- 3.0 10.7 +/- 2.7 7 1 14.5 +/- 3.6 16.3 +/- 4.1 17.0 +/- 4.3 15.7 +/- 3.9

8-#12areoffsiteat 8 C 10.7 +/- 2.7 10.9 +/- 2.7 11.4 +/- 2.9 11.5 +/- 2.9 adistanceof8to15miles. 9 1 9.9 +/- 2.5 10.6 +/- 2.7 10.6 +/- 2.7 11.2 +/- 2.8 10 C 10.0 +/- 2.5 10.5 +/- 2.6 10.2 +/- 2.6 10.5 +/- 2.6 11 1 10.1 +/- 2.5 10.7 +/- 2.7 10.7 +/- 2.7 10.8 +/- 2.7 12 C 9.1 +/- 2.3 10.1 +/- 2.5 10.0 +/- 2.5 11.7 +/- 2.9 13 1

10.7 +/- 2.7 12.7 +/- 3.2 13.6 +/- 3.4 13.5 +/- 3.4

14-#16arelocated 14 1 13.7 +/- 3.4 11.5 +/- 2.9 12.4 +/- 3.1 12.4 +/- 3.1 alongaline3000HR.west 15 1 11.6 +/- 2.9 12.6 t 3.2 13.0 +/- 3.3 13.1 +/- 3.3 oftheplant. 16 1 10.9 +/- 2.7 11.2 +/- 2.8 12.3 +/- 3.1 12.8 +/- 3.2

17-#21 arelocated 17 1 9.9 +/- 2.5 11.2 +/- 2.8 11.5 +/- 2.9 11.8 +/- 3.0 alongLakeRoad. 18 1 11.8 +/- 3.0 12.4 +/- 3.1 11.9 +/- 3.0 11.4 +/- 2.9 19 1 9.5 +/- 2.4 11.4 +/- 2.9 10.3 +/- 2.6 10.7 +/- 2.7 20 1 9.8 +/- 2.5 11.9 +/- 3.0 11.5 +/- 2.9 12.3 +/- 3.1 21 1 10.8 +/- 2.7 12.3 +/- 3.1 11.9 +/- 3.0 12.1 +/- 3.0

22-#24arelocated 22 1 10.3 +/- 2.6 11.0 +/- 2.8 10.9 +/- 2.7 11.5 +/- 2.9 alongtheeastsite 23 1 10.8 +/- 2.7 11.8 +/- 3.0 12.2 +/- 3.1 12.7 +/- 3.2 boundaryline. 24 1 10.8 +/- 2.7 11.7 +/- 2.9 12.3 +/- 3.1 12.4 +/- 3.1

25-#30areoffsite 25 C 10.0 +/- 2.5 11.2 +/- 2.8 11.0 +/- 2.8 11.1 +/- 2.8 atadistanceof8 26 C 9.9 +/- 2.5 10.4 +/- 2.6 10.9 +/- 2.7 11.2 +/- 2.8 to 15 miles. 27 C 10.1 +/- 2.5 11.0 +/- 2.8 10.6 +/- 2.7 11.3 +/- 2.8 28 C 9.8 +/- 2.5 11.2 +/- 2.8 11.4 +/- 2.9 11.2 +/- 2.8 29 C 9.5 +/- 2.4 10.7 +/- 2.7 10.7 +/- 2.7 11.1 +/- 2.8 30 C 8.9 +/- 2.2 9.7 +/- 2.4 10.2 +/- 2.6 10.4 +/- 2.6

31 -#40 are located 31 1 9.5 +/- 2.4 11.8 +/- 3.0 12.4 +/- 3.1 12.2 +/- 3.1 inanarcatadistance 32 1 9.4 +/- 2.4 10.2 +/- 2.6 10.3 +/- 2.6 10.5 +/- 2.6 of 4-5 miles. 33 1 9.3 +/- 2.3 10.7 +/- 2.7 11.4 +/- 2.9 11.2 +/- 2.8 34 1 9.8 +/- 2.5 12.1 +/- 3.0 12.6 +/- 3.2 12.4 +/- 3.1 35 1 10.7 +/- 2.7 12.2 +/- 3.1 12.7 +/- 3.2 12.4 +/- 3.1 36 1 9.3 +/- 2.3 10.3 +/- 2.6 10.7 +/- 2.7 11.0 +/- 2.8 37 1 9.0 +/- 2.3 10.2 +/- 2.6 10.3 +/- 2.6 10.3 +/- 2.6 38 1 10.2 +/- 2.6 12.3 +/- 3.1 12.1 +/- 3.0 12.0 +/- 3.0 39 1 9.5 +/- 2.4 12.3 +/- 3.1 11.9 +/- 3.0 11.8 +/- 3.0 40 1 9.5 +/- 2.4 10.5 +/- 2.6 10.7 +/- 2.7 9.4 +/- 2.4 (44)

4.0 LAND USE CENSUS A land use census is performed each year to determine any major changes in the use of the land within 5 miles of the plant. There were no major changes in 2004. The land use remains mainly agricultural in nature, although the long term trend is away from agriculture and towards residential use. There were several new private home developments of substantial size. The two dairy operations nearest to the plant began the year in operation with 40 to 50 milk cows. (Molino Farm ceased commercial operation early in 2002). There are no goats raised for human consumption of milk or meat within the five mile radius. Beef cattle are still raised on 3 farms within 5 miles of the plant as in past years.

An on-site garden is used for broad leaf vegetation and on-site crops are collected for indicator samples when available.

A copy of the Land Use Census that was completed in September 2004 is attached.

Detailed land use census data is available on file at Ginna Station.

5.0 EXTERNAL INFLUENCES During 2004, there were no external influences such as atmospheric weapons testing or accidents at other nuclear facilities which had an impact on the data.

45

Attachment I Land Use Census ector f Din-de61o"'N i i Nearesf +. Ditnetoik

. ' p ,4Residene E 1260 m N/A N/A ESE 1050 m N/A N/A SE 610 m N/A 8270 m SSE 660 m N/A N/A S 1560 m N/A N/A SSW 760 m N/A N/A SW 660 m N/A 4680 m WSW 1350 m N/A N/A W 1160 m N/A N/A Changes from previous year:

Development of single family homes is increasing over past years.

Interviews with area farmers indicates that the number of acres farmed will continue to decrease.

No new agricultural land use was noted.

No new food processing facilities were noted.

Milk animal locations:

No new milk producing animals were identified in the 2004 Census.

UFSAR change request: Y. N X Land Use Census Completed by: -i / 4 Date: _ __ __

Reviewed by: )29---7 Date: __ _ _ _

46

6.0 QUALITY ASSURANCE 6.1 INTERLABORATORY BLIND SAMPLE COMPARISON A Laboratory's participation in an interlaboratory comparison program provides a means for verifying the measurement accuracy of radioactive material in environmental sample media with another laboratory. The ODCM requires participation in an interlaboratory comparison program that is approved by the NRC, if such a program exists. Until 1996 the United States Environmental Protection Agency (EPA), Office of Research and Development, National Exposure Research Laboratory, Las Vegas, Nevada, was the NRC approved program. Since the NRC has not approved a replacement for the EPA's program, Ginna Station has engaged the services of Analytics, Inc., Atlanta, Georgia for quality control blind spiked environmental sample media for interlaboratory comparison. Ginna Station submits blind spiked to our contract laboratory, James A. Fitzpatrick Environmental Laboratory (JAFEL), for analysis with field samples. JAFEL engages the services of Analytics and Environmental Measurements Laboratory (EML) for environmental sample media as blind sample spikes that are in addition to those submitted by Ginna Station. It should be noted that 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.

However, JAFEL was eligible to participate in the first of two annual quality assessment quality programs in 2004 before the program was restructured.

An assessment of the blind spiked sample media for accuracy was performed, using the acceptance test generally referred to as the "NRC" method. This method is contained in NRC Procedure DVP-04.01 and was taken from the Criteria of Comparing Analytical Results (USNRC) and Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). The Laboratory's accuracy is evaluation by comparison to a reference as follows:

Error Resolution = Reference Value Reference Uncertainty Comparison Ratio = Laboratorv Analysis Reference Value 47

The reference value and uncertainty are Analytics values. Using Table 6.1A, the interval for the RATIO OF AGREEMENT is determined by the appropriate row under the ERROR RESOLUTION column. The RATIO OF AGREEMENT provides criteria for evaluating the comparison ratio as to being in agreement or disagreement. When the comparison ratio is found to be in agreement with the reference value a Laboratory's analysis does not have a statistically significant analysis error, either systematic or programmatic. If the comparison ratio is found to be in disagreement with the reference value the Laboratory's analysis has a statistically significant analysis error, which may be either systematic or programmatic.

Table 6.1A ERROR RATIO OF RESOLUTION AGREEMENT

<3 0.4 to 2.5 3.1 to 7.5 0.5 to 2.0 7.6 to 15.5 0.6 to 1.66 15.6 to 50.5 0.75 to 1.33 50.6 to 200 0.8 to 1.25

<200 0.85 to 1.18 A 5% reference uncertainty was applied to the reference value. According to ANSI N42.23-1996, 5% is the maximum acceptable bias for a reference laboratory that prepares blind spiked samples. The ERROR RESOLUTION for all the Analytics' spiked samples was determined to fall between 15.6 and 50.5 which correlates to RATIO OF AGREEMENT OF 0.75 to 1.33.

Comparison ratios are displayed in Figures 6.1A, 6.1B, 6.1C and 6.1D along with a lower control limit (LCL) of 0.75 and an upper control limit (UCL) of 1.33.

48

6.2 ANALYTICS SAMPLE NON-CONFORMITIES For 2004, two nuclides fell outside of the LCL and UCL, based on JAFEL acceptance criteria. Cs-137 (Figure 6.1B, QC-4) and Zn-65 (Figure 6.1E, QC-1). JAFEL investigation of these two non-conformities is discussed below.

Cs-137 Non-conformitv A spiked mixed gamma and 1-131 milk sample supplied by Analytics, Inc. was submitted to the laboratory for analysis by Constellation/Ginna. The sample was analyzed in accordance with standard laboratoryprocedures. 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 Cs-137 was determined to be outside the QA Acceptance Criteria resulting in a sample nonconformity. The known result for the sample was 126 pCi/L as determined by the supplier. The reported mean result for the sample was 191 pCi/L. The reported laboratory results when compared to the reference or known value produced a ratio of 1.51.

Discussions with the supplier indicated that the reference value was correct as reported and confirmed by the overall accuracy of the reported values from the other participating laboratories.

An evaluation of the Cs-137 result was performed. The spectrum and peak search results were examined with no anomalies identified. The 4 individual laboratory results had good precision with a range of 199 pCi/L for the high to 181 pCi/L for the low result. The results had a spread of 18 pCi/L or approximately 9.4% of the reference results. Based on the evaluation of the 4 results and corresponding analytical data it was determined that the result for Cs-137 were correct as reported with no identified deficiencies. In addition to Cs-137, the Co-60 results for this sample showed a relatively high result with a ratio of 1.21 in comparison with the reference value. The overall evaluation of the sample results indicated that the high result for Cs-137 and Co-60 was the result of contamination in the counting beaker from a previous spiked QA sample. This assessment is supported by the historical performance for laboratory analysis of spiked QA samples.

A review of the 5 year historical performance for Cs-137 spiked QA sample results showed very good performance with no non-conformities. As with Cs-137, Co-60 historical performance of QA samples is very good with no non-conformities or quality related problems.

As a corrective action, the laboratory technicians were briefed on the importance of not reusing counting containers for the analysis of spiked QA samples. The QA check sheet was revised to include verification that new counting containers are being used.

49

Zn-65 Non-conformity 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 and resulted in an agreement when compared to the known 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 gamma 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 sample spectrums, there was a low number of total counts in the 1110 to 1130 KeV area. The low count rate and subsequent poor peak shape made it difficult for the algorithm to select an exact background for determining the total counts in the peak. In addition, low 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 media in the counting geometry may have effected the homogeneity of the sample and produced a positive bias in the collective sample results. To determine if this was a programmatic or systematic error inherent to the software/analysis system, an extent of condition was performed using another spiked sample result for any similar nonconformities. 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.

50

The results are as follows:

2004 Zn-65 Results Sample ID Medium JAF Supplier Ratio E-4053-05 Water pCi/L 146+/-6 143+/-5 1.03 E-4319-05 Water pCi/L 165+/-6 178+/-6 0.93 E-4054-05 Filter pCi/filter 98+/-5 95+3 1.03 E-4320-05 Filter pCi/filter 1 141+/-6 120+/-4 1.18 E-4321-05 Milk pCi/L 155+/-7 167+/-6 0.93 E-4165-05 Milk pCi/L 94+/-5 99+/-3 0.94 E-4168-05 Vegetation pCi/kg 260+/-17 232+/-8 1.12 E-4159-09 Soil pCi/kg 289+/-20 262+/-5 1.10 E-4051-09 Soil pCi/kg 289+/-17 252+/-6 1.15 E-4253-09 Soil pCi/kg 239+/-12 248+/-6 0.96 E-4373-09 Soil pCi/kg 336+/-22 329+/-6 1.02 A duplicate sample of this sample (E-4166-05) was submitted to the laboratory as a blind spike (E-4154-09). 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 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-conformity.

51

Figure 6.1A Trend of Blind Spiked Water Sam ples 1.50 1.40 1.30 S2 1.20

0 1.10

A=

1.00=

0. 0.90 - -

E 0.70 0.60 1 beta Itritium Ce-141 l Cr-511 Cs-134 Cs-137 lMn-54 Fe-59 Zn.65 Co.60 Co.58 1-131

-ICL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1;33

CC-1 0.94 1.25 0.97 0.98 A CC-2 0.99 1.00 0.99 1.09 0.94 0.95 1.02 1.15 1.02 0.97 1.03 1.03

QC-3 0.99 1.00 1.05 1.25 0.93 0.99 0.94 1.13 0.95 0.96 1.03 1.04

[ QC.4 1.00 0.90 aCC5_ 1.02 0.81 0.97 0.98 0.97 1.02 0.93 0.98 0.99 0.98

- LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 Figure 6.1B Trend of Blind Spiked Milk Sam pies 1.50 e 1.30 1.10 U L 0.70 0.50 Ce-141 Cr-51 Cs-134 I Cs-137 Mn-54 Fe.59 I Zn65 I Co.60 I Co.58 1 1.131

- UCL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33

OC-1 1.05 0.96 0.88 0.97 1.01 1.01 0.97 1.03 0.97 A QC-2 0.99 0.95 0.96 0.92 0.97 1.12 0.94 1.00 0.94 0.95

QCC3 0.96 0.97 0.89 0.92 1.04 1.09 0.93 0.98 0.95 0.89

QC-4 0.95 1.10 1.16 1.52 1.05 1.03 1.04 1.21 1.02

-LC L 0.75 0.75 0.75 0.75 0.75 0 0.75 00.75 0.75 0.75 0.75 52

Figure 6.1C Trend of Blind Spiked Filter Sam pies 1.50 1.40 1.30

°2 1.20 X E 1.10 X-

° 1.00 x

e. 0.90 _l*

o 0.80 0.70 0.60 0.50 beta Ce.141 Cr-51 Cs.134 Cs-137 Mn-54 Fe.59 Zn.65 Co-60 Co-58

- UCL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33

QC.1 0.95 1.06 1.10 1.01 A QCC2 0.95 0.95 0.92 0.88 0.98 1.02 0.98 1.03 0.95 0.99 x QC-3 0.97 1.03 1.16 1.05 1.00 1.11 1.10 1.08 0.99

QC-4 0.99 0.90 0.93 1.05 0.99 1.11 1.05 1.03 0.96 x C-5 1.09 0.89 1.08 1.04 1.18 1.25 1.18 0.96 1.10

OC-6 0 0.93 1.05 0.99 1.11 1.05 1.03 0.96 0.98 LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 Figure 6.IDTrend of Blind Spiked Filter Samples 1.50 1.40 1.30 1.20 1.10 0 1.00 E 0.90 0

0.80 0.70 0.60 0.50 1-131 1-131 1-131 1-131

- UCL 1.33 1.33 1.33 1.33

CC-1 1.02

QC2 0.97

QC3 0.96

QC-4 1.04 I- LCL 0.75 0.75 0.75 0.75 53

Figure 6.1ETrend of Blind Spiked SoliNegetatlon Samples

1. 50, 1.40 1.30 U 1.20 -

1.10 * * *A 0 1.00 A A A

0. 0.90 U

0.80 i 0.70 -

0.60 0.50n Ce.141 I Cr.51 I Cs-134 I Cs.137 I Mn-54 I Fe.59 I Zn-65 Co-60 I Co.58

- UCL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 a QC1 1.09 1.20 1.11 1.02 1.08 1.08 1.27 1.08 0.93 A QC-2 0.97 1.07 1.07 1.01 1.07 1.06 1.12 1.01 1.03 I- LCL 0.75 1 0.75 0.75 1 0.75 0.75 I 0.75 0.75 1 0.75 0.75 Figure 6.2A Trend of QC Blind Spiked TLDs 0.25 0.20 0.15 E0.10 0.05

0.00 m rem

- UCL 0.20 0.20 0.20 0.20

QC-1 0.02 A QC.2 0.06

QC-3 0.04 QC-4 0.07 54

6.3 INTRALABORATORY BLIND SAMPLE COMPARISON A Laboratory's use of in-house quality control spiked samples provides a means for verifying measurement accuracy for analyzing environmental sample media. In 2004, Ginna Station implemented field spiked environmental TLDs by irradiating TLDs with a Cs-137 source to a known dose. The spiked TLDs were placed in the field and processed with each quarter's environmental TLDs. The reported dose was background corrected, using the average of the field control TLDs. The reported dose and delivered dose are used to calculate a performance quotient ((reported - delivered)/delivered) for each TLD within the set of spiked TLDs. The performance bias is the average of the performance quotients. The standard deviation of bias is the standard deviation of the performance quotients. For the set of spiked TLDs a performance criteria is calculated by adding the performance bias and standard deviation of the bias. The performance criteria limit was established to be 0.20. Spike performance criteria of less than 0.20 validate the TLD processing at Ginna Station. All blind TLD performance criteria for year 2004 were less than 0.20. Figure 6.2A displays the spike TLD performance criteria.

6.4 AUDIT OF CONTRACT LABORATORY Ginna Station Quality Assurance personnel conducted audits of the ODCM and REMP during 2004. Report #AINT-2004-0002-BKS. In those audits, they examined the data and results from JAFEL to ensure that the information was properly gathered, validated and reviewed by Ginna personnel in accordance with the ODCM and REMP programs. There were no external surveillances done at JAFEL in 2004.

55

7.0 DEVIATIONS FROM SCHEDULE Five items reportable in the Annual Environmental Radiological Operating Report under procedure CHA-RETS-VARIATION were reported as follows:

1. Environmental Air Sample Station (ES) # 2 found off 3/22/04. GFI reset, no further failure. Sample period was 34.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

2. ES #11 found off 6/9104. GFI reset. Sample period was 27.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

3. Weekly OWD water sample was missed due to suction tubing pulled away from sample bottle, reconnected 7/6104.

4. ES #10 found off 8/4/04. Reset with no subsequent indications of problem. Sample period was 57.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

5. ES #3 found off. Reset successfully. Bees nest removed from breaker and breaker covered in plastic. Sample period was 1.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

56

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