Text

Part 2 of 2, R.E. Ginna Nuclear Power Plant - Annual Radioactive Effluent & Environmental Reports
	ML021440636
Person / Time
Site:	Ginna
Issue date:	05/15/2002
From:	Mecredy R; Rochester Gas & Electric Corp
To:	Clark R; NRC/NRR/DLPM/LPD1
References
	Download: ML021440636 (94)
	v • d • e

2001 Annual Radiological Environmental Operating Report rW R.E. Ginna Nuclear Plant Rochester Gas and Electric Docket No. 50-244

2001 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT R.E. Ginna Nuclear Station Rochester Gas & Electric Corporation 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 26 3.4 Milk Samples 38 3.5 Fish Samples 40 3.6 Vegetation Samples 44 3.7 External Penetrating Radiation 46 4.0 LAND USE CENSUS 49 5.0 EXTERNAL INFLUENCES 49 6.0 QUALITY ASSURANCE 52 7.0 DEVIATIONS FROM SCHEDULE 61

LIST OF TABLES/FIGURES Table/Figure Page 1-1 Environmental Radiological Monitoring Program Summary 2 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 3-3 Onsite vs Offsite Air Monitors 19 3-4 A 13 Week Composite Gamma Isotopic Analyses First Quarter 20 3-4 B 13 Week Composite Gamma Isotopic Analyses Second Quarter 21 3-4 C 13 Week Composite Gamma Isotopic Analyses Third Quarter 22 3-4 D 13 Week Composite Gamma Isotopic Analyses Fourth Quarter 23 3-5 Charcoal Cartridges for Iodine 24 3-6 Annual Trending of Air Activity 25 3-7 A 1999 Trending of Environmental Water Samples 28 3-7 B Annual Trending of Environmental Water Samples 29 3-8 Environmental Water Samples Gross Beta Analysis 30 3-9 Russell Station Water Gamma Isotopic Analysis 31 3-10 Ontario Water District Water Gamma Isotopic Analysis 32 3-11 Circ-ln Water Gamma Isotopic Analysis 33 3-12 Circ-Out Water Gamma Isotopic Analysis 34 3-13 Deer Creek Water Gamma Isotopic Analysis 35 3-14 Environmental Water Samples Tritium Analysis 36 3-15 Radioiodine in Water 37 3-16 Milk Samples Gamma Isotopic Analysis 39 3-17A Fish Samples Gamma Isotopic Analysis 41 3-17B Fish Samples Gamma Isotopic Analysis 42 3-18 Lake Samples Gamma Isotopic Analysis 43 3-19 Vegetation Samples Gamma Isotopic Analysis 45 3-20 External Penetrating Radiation 47 3-21 Two Year Trend of External Penetrating Radiation 48

LIST OF TABLES/FIGURES (continued)

Table/Figure Page 4-1 Land Use Census 50 6-1A Trend of Blind Spiked Water Samples 53 6-1 B Trend of Blind Spiked Milk Samples 54 6-1C Trend of Blind Spiked Filter Samples 54 6-2C Trend of QC Blind Spiked TLD's 55 6-3A Trend of Split TLD Samples 57 6-3B Trend of Split Milk Samples 57 6-3C Trend of Composite Air Particulate Filter Samples 58 6-3D Trend of Air Particulate Samples 59 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 2-4 Land Use Census 51

RADIOLOGICAL ENVIRONMENTAL SURVEY January 1 - December 31, 2001 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 2001 results were consistent with data for the past five years and exhibited no adverse trends.

The analytical results from the 2001 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 2001, 1185 samples were collected for analysis by gross beta counting and/or gamma spectroscopy. These included 936 air samples, 60 water samples, 16 fish samples, 18 vegetation samples, 57 milk samples, and 156 thermoluminescent dosimeter measurements. During 2001 there was one deviation from the sampling schedule for TLD's, 6 deviations for air samples, and 2 deviations for water 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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I I I I I I I I I I I I I I Table 1-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY SAMPLED TYPE AND TOTAL NUMBER OF INDICATOR LOCATIONS CONTROL UNIT OF MEASUREMENT ANALYSES LLD MEAN (1) RANGE LOCATIONS MEAN (1) RANGE NAME, DISTANCE MEAN (1) RANGE AND DIRECTION AIR: Particulate(pCi/M") Gross Beta 624 0.003 0.017 (468/468) Onsite Location # 5 0.019 (52/52) 0.017 (156/156) 0.006-0.043 185 160M 0.07- 0.034 0.004 - 0.034 (pCi/M3) Gamma Scan 48 (2) < LLD N/A N/A < LLD Iodine(pCi/M*) 0.006- <LLD N/A N/A Gamma Scan 260 0.054 < LLD DIRECT RADIATION: 12.5 (120/120)

TLD Gamma 156 5.0 9.6-20.3 Onsite Location #7 18.7 (4/4) 11.0 (36/36)

(mrem/quarter) 257 220M 17.7-20.3 9.4- 12.8 WATER: Drinking Gross Beta 12 0.2 2.51 (12/12) OWD 2.51 N/A (pCi/Liter) 0.86-3.29 70 1200M 0.86-3.29 Gamma Scan 12 (2) Ra-226 94 (12/12) OWD Ra-226 94,(12/12) N/A 56-176 70 1200M 56-176 Tritium 12 (2) <LLD N/A N/A N/A Iodine 12 0.56* < LLD N/A N/A N/A Surface Gross Beta 48 0.2 2.51 (12/12) Deer Creek 3.90 (12/12) 2.17 (12/12)

(pCi/Liter) 0.98- 3.64 105 260M 1.36- 5.64 1.44- 3.43 Gamma Scan 48 (2) Ra-226 99 (12/12) Circ-out Ra-226 99 (12/12) Ra-226 77 (12/12)63-145 15 130M 63-145 36-105 Tritium 48 (2) <LLD N/A N/A N/A Iodine 48 0.75* < LLD N/A N/A < LLD MILK: Iodine 58 0.54* < LLD N/A N/A < LLD (pCi/Liter)

Gamma Scan 58 (2) < LLD N/A N/A < LLD FISH: Gamma Scan 17 (2) Ra-226 745 (6/8) Indicator Fish Ra-226 745 (6/8) Ra-226 487 (4/6)

(pCi/Kg) 550-996 015 130M 550-996 324-835 VEGETATION: Gamma Scan 8 (2) Ra-226 265 (5/5) Indicator Vegetation Ra-226 265 (5/5) Ra-226 135 (3/4)

(pCi/Kg)94-506 94-506 65-204

~1 Ill andlI UdragU VII Uon UeUable measurements only. I-r2 ction ot detectable measurements at specified locations in parentheses.

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

(3) Single sample 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:

MonitorinQ Proqram 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 are added to the environmental monitoring program.

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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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I f I I I I I I I 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 5 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 hours following

b. Particulate 9 indicator Same as above ilter change. Perform gamma isotopic analysis on each sample for which 3 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 Gamma dose quarterly.

RADIATION 9 control (11 placed greater than 5 miles from 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 1 indicator (Condenser Water period of < 31 days. analysis of one composite sample at least once per 92 days.

Discharge)

Same as above.

b. Drinking 1 indicator (Ontario Water District Same as above Intake)

Gamma isotopic analysis of each sample C. Shoreline 1 Control (Russell Station) Semi-annnually Sediment 1 Indicator (Ontario Water District)

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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I f f r I ( I I I I I I I I I I Table 2-1 Page 2 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

4. INGESTION

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

3 indicator (June thru October) 1 control Gamma isotopic and 1-131 analysis of each sample.

1 indicator At least once per 31 days November thru May)

Gamma isotopic analysis on edible portions of each sample.

b Fish 4 control Twice during fishing season including at 4 indicator (Off shore at Ginna) -east four species. Gamma isotopic analysis on edible portion of sample.

1 control C Food Products 2 indicator (On site) Annual at time of harvest, Sample from wo of the following:

1. apples

2. cherries Gamma isotopic analysis on edible portion of sample.

3. Other crops grown on site by contract farmer 1 control 1 indicator At time of harvest. One sample of:

(On site garden or nearest offsite 1. broad leaf vegetation*

garden within 5 miles in the 2. other vegetable highest D/Q meterological sector)

leaves from 3 different plant species composited 6

I I I I I I I Table 2-2 Page 1 of 2 The maximum LLD values as defined by ODCM Table 5-3 Airborne Food Particulate Analysis Water Particulate Fish Milk (pCi/kg, wet)

(pCi/Liter) or Gas (pCilkg, wet) (pCi/Liter)

(pCi/m 3)

Gross Beta 4(a) 1 x 10z 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 10-2 1 60 Cs-134 15(10)(a), I x 10-2 130 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)

X is 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 I 87 320 #2 87 320

3 I 110 420 #3 110 420

4 I 140 250 #4 140 250

5 I 185 160 #5 185 160

6 I 232 225 #6 232 225

7 I 257 220 #7 257 220

8 C 258 19200 #8 258 19200

9 I 235 11400 #9 235 11400

10 C 185 13100 #10 185 13100

11 I 123 11500 #11 123 11500

12 C 93 25100 # 12 93 25100

13 I 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 DeerCreek S 105 260 # 19 177 400

20 165 680

21 145 600

22 128 810

23 107 680

24 90 630

25 247 14350

26 223 14800 Milk Sample Locations Direction Distance # 27 202 14700 Farm A I 113 9500 # 28 145 17700 Farm B I 242 5450 # 29 104 13800 Farm C I 156 4950 #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 = Inaicator Samples # 38 137 7070 C = Control Samples # 39 115 6630 S = Supplemental Samples # 40 87 6630 9

C-01

.2 CNI Cl 0 2!

0 C

C-0 7,

cn 01 0t N-C-03,

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.

One millionth of a millionth of a curie or 0.037 disintegrations Picocurie (pCi):

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 SCUM 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 progeny products of radon and thoron. 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, 1 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 17 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 0.018 pCi/m 3, and the averages for the indicators were 0.019 pCi/m 3 for the period of January to December, 2001. Maximum weekly concentrations for each station were less than 0.043 pCi/m 3 . These values represent a worst-case evaluation of the four environmental air sample gas meters which failed as-found testing on 6/27/01. The failed as-found flows varied between 106% and 127%, and included 3 indicator stations and 1 control station. See section 7.0.

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 4Ato D.

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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.

A trend plot of the 2001 Onsite vs. Offsite air filter data is included, Table 3-3.

Additionally, a trend plot of the annual averages measured since 1968, Table 3-6, is included to show the variation of data during the years that the R.E. Ginna Nuclear Power Plant has been operational. The peak activities measured correspond to the years when atmospheric tests of nuclear weapons were being conducted.

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Rochester Gas and Electric Table 3-1 A On-Site Air Particulate Samplers Gross Beta Results in pCi/m3 Collection Date Sta. #2 (I) Sta. #3 (I) Sta. #4 (I) Sta. #5 (I) Sta. #6 (I) Sta. #7 (I) Sta #13A (I) Average 8-Jan 0.018 +/- 0.005 0.018 +/- 0.004 0.022 0.007(a) 0.034 0.007(a) 0.020 +/- 0.004 0.019 +/- 0.003 0.020 +/- 0.004 0.022 16-Jan 0.021 +/- 0.005 0.021 +/- 0.003 0.021 0.003 0.021 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.025 +/- 0.004 0.021 22-Jan 0.016 +/- 0.005 0.021 +/- 0.004 0.020 0.004 0.022 0.004 0.019 +/- 0.003 0.020 +/- 0.003 0.026 +/- 0.005 0.021 29-Jan 0.021 +/- 0.005 0.019 +/- 0.003 0.021 0.004 0.029 0.004 0.021 +/- 0.003 0.018 +/- 0.003 0.026 +/- 0.004 0.022 5-Feb 0.023 +/- 0.005 0.020 +/- 0.003 0.019 0.004 0.025 0.004 0.020 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.004 0.021 12-Feb 0.020 +/- 0.005 0.022 +/- 0.004 0.022 0.004 0.025 0.004 0.009 +/- 0.003 0.021 +/- 0.003 0.024 +/- 0.004 0.021 20-Feb 0.020 +/- 0.005 0.024 +/- 0.003 0.021 0.003 0.026 0.003 0.028 +/- 0.004 0.023 +/- 0.003 0.028 +/- 0.004 0.024 26-Feb 0.017 +/- 0.005 0.016 +/- 0.003 0.018 0.004 0.022 0.004 0.016 +/- 0.003 0.015 +/- 0.003 0.021 +/- 0.004 0.018 5-Mar 0.021 +/- 0.005 0.018 +/- 0.003 0.019 0.004 0.023 0.004 0.021 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.004 0.020 12-Mar 0.011 +/- 0.004 0.015 +/- 0.003 0.014 0.003 0.018 0.003 0.013 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.004 0.014 19-Mar 0.014 +/- 0.005 0.015 +/- 0.003 0.013 0.003 0.017 0.003 0.017 +/- 0003 0.016 +/- 0.003 0.018 +/- 0.004 0.016 26-Mar 0.008 +/- 0.004 0.011 +/- 0.003 0.010 0.003 0.013 0.003 0.012 +/- 0.003 0.011 +/- 0.002 0.013 +/- 0.003 0.011 2-Apr 0.009 +/- 0.004 0.013 +/- 0.003 0.011 0.003 0.012 0.003 0.014 1 0.003 0.011 +/- 0.003 0.016 +/- 0.004 0.012 9-Apr 0.016 +/- 0.005 0.016 +/- 0.003 0.017 0.003 0.017 0.003 0.017 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.004 0.017 16-Apr 0.009 1 0.004 0.010 +/- 0.003 0.010 0.003 0.013 0.003 0.007 +/- 0.005(a) 0.008 +/- 0.002 0.008 +/- 0.003 0.009 23-Apr 0.019 +/- 0.005 0.019 +/- 0.003 0.020 0.004 0.028 0.004 0.023 +/- 0.004 0.020 +/- 0.003 0.021 +/- 0.004 0.021 30-Apr 0.018 +/- 0.005 0.020 +/- 0.003 0.023 0.004 0.026 0.004 0.027 +/- 0.004 0.022 +/- 0.003 0.028 +/- 0.005 0.023 7-May 0.019 +/- 0.005 0.025 +/- 0.004 0.024 0.004 0.033 0.004 0.025 +/- 0.004 0.020 +/- 0.003 0.025 +/- 0.004 0.024 14-May 0.012 +/- 0.004 0.016 +/- 0.003 0.018 0.003 0.021 0,003 0,016 +/- 0.003 0.016 +/- 0.003 0.023 +/- 0.004 0.017 21-May 0.010 +/- 0.004 0.011 +/- 0.003 0.011 0.003 0.013 0.003 0.013 +/- 0.003 0.010 +/- 0.002 0.013 +/- 0.004 0.012 29-May 0.007 +/- 0.003 0.006 +/- 0.002 0.006 0.002 0.008 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.003 0.007 4-Jun 0.012 +/- 0.008(a) 0.009 +/- 0.003 0.008 0.003 0.009 0.003 6.010 +/- 0.003 0.008 +/- 0.003 0.011 +/- 0.004 0.009 11-Jun 0.010 +/- 0.004 0.012 +/- 0.003 0.012 0.003 0.012 0.003 0.015 +/- 0.003 0.012 +/- 0.003 0.020 +/- 0.004 0.013 18-Jun 0.014 +/- 0.004 0.016 +/- 0.003 0.015 0.003 0.015 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.004 0.016 25-Jun 0.009 +/- 0.004 0.012 +/- 0.003 0.012 0.003 0.013 0.003 0.018 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.003 0.013 2-Jul 0.017 +/- 0.005 0.019 +/- 0.003 0.018 0.003 0.018 0.004 0.026 +/- 0.004 0.019 +/- 0.003 0.018 +/- 0.004 0.019 Maximum 0.023 +/- 0.005 0.025 +/- 0.004 0.024 +/- 0.004 0.034 +/- 0.007 0.028 +/- 0.004 0.023 +/- 0.003 0.028 +/- 0.004 Average 0.015 0.016 0.016 0.020 0.017 0.016 0.019 Minimum 0.007 +/- 0.003 0.006 +/- 0.002 0.006 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.003 (a) Sample collected for <84 hours in sample period.

I= Indicator C= Control (15)

I I I I I I I I I J I I I

Rochester Gas and Electric Table 3-1 B On-Site Air Particulate Samplers Gross Beta Results in pCi/m3 Collection Date Sta. #2 (I) Sta. #3 (I) Sta. #4 (I) Sta. #5 (I) Sta. #6 (I) Sta. #7 (I) Sta. #13A (I) Average 9-Jul 0.010 0.004 0.012 +/- 0.003 0.015 +/- 0.003 0.011 +/- 0.003 0.016 +/- 0.003 0.012 +/- 0.003 0.017 +/- 0.004 0.013 16-Jul 0.007 0.004 0.009 +/- 0.003 0.008 +/- 0.002 0.007 +/- 0.003 0.012 +/- 0.003 0.010 +/- 0.002 0.011 +/- 0.003 0.009 23-Jul 0.016 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.004 0.016 +/- 0.003 0.016 +/- 0.004 0.016 30-Jul 0.015 0.003 0.013 +/- 0.003 0.017 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.004 0.015 6-Aug 0.022 0.003 0.022 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.004 0.022 +/- 0.003 0.021 +/- 0.004 0.024 +/- 0.004 0.021 0.003 0.026 +/- 0.004 0.024 +/- 0.003 0.024 +/- 0.004 0.021 +/- 0.003 0.023 +/- 0.004 0.022 +/- 0.004 0.023 13-Aug 0.024 0.015 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.004 0.015 20-Aug 27-Aug 0.016 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.017 +/- 0.004 0.016 4-Sep 0.018 0.003 0.019 +/- 0.003 0.025 +/- 0.012(a) 0.015 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.018 10-Sep 0.022 0.004 0.021 +/- 0.004 0.022 +/- 0.004 0.020 +/- 0.004 0.020 - 0.004 0.023 +/- 0.004 0.024 +/- 0.005 0.022 17-Sep 0.016 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.018 +/- 0.004 0.016 24-Sep 0.020 0.003 0.022 +/- 0.003 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.004 0.021 +/- 0.004 0.020 +/- 0.004 0.022 1-Oct 0.009 0.003 0.008 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.003 0.010 1 0.003 0.007 +/- 0.003 0.008 +/- 0.003 0.008 9-Oct 0.018 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.017 +/- 0.004 0.019 15-Oct 0.018 0.004 0.016 +/- 0.003 0.016 +/- 0.003 0.020 +/- 0.004 0.019 +/- 0.004 0.018 +/- 0.004 0.021 +/- 0.005 0.018 23-Oct 0.017 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.004 0.017 29-Oct 0.010 0.003 0.012 +/- 0.003 0.011 +/- 0.003 0.011 +/- 0.003 0.011 +/- 0.003 0.011 +/- 0.003 0.010 +/- 0.004 0.011 5-Nov 0.018 0.003 0.019 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.004 0.019 +/- 0.003 0.023 +/- 0.004 0.021 +/- 0.004 0.020 12-Nov 0.013 0.003 0.014 +/- 0.003 0.016 +/- 0.003 0.012 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.004 0.015 19-Nov 0.038 0.005 0.036 +/- 0.004 0.043 +/- 0.005 0.033 +/- 0.005 0.035 +/- 0.004 0.035 +/- 0.004 0.038 +/- 0.005 0.037 26-Nov 0.015 0.004 0.021 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.004 0.018 +/- 0.004 0.020 +/- 0.004 0.021 +/- 0.004 0.020 3-Dec 0.011 0.013(a) 0.014 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.011 +/- 0.003 0.013 +/- 0.004 0.014 10-Dec 0.023 0.004 0.034 +/- 0.004 0.029 +/- 0.004 0.025 +/- 0.004 0.030 +/- 0.004 0.033 +/- 0.004 0.033 +/- 0.005 0.030 17-Dec 0.019 0.003 0.024 +/- 0.004 0.025 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.004 0.025 +/- 0.004 0.022 +/- 0.005 0.023 26-Dec 0.018 0.003 0.021 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.018 +/- 0.003 0.023 +/- 0.004 0.020 2-Jan 0.016 0.003 0.019 +/- 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.004 0.017 Maximum 0.038 +/- 0.005 0.036 +/- 0.004 0.043 +/- 0.005 0.033 +/- 0.005 0.035 +/- 0.004 0.035 +/- 0.004 0.038 +/- 0.005 Average 0.017 0.018 0.019 0.017 0.019 0.018 0.019 Minimum 0.007 +/- 0.004 0.008 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.003 0.010 +/- 0.003 0.007 +/- 0.003 0.008 +/- 0.003 (a) Sample collected for <84 hours in sample period.

I= Indicator C= Control p d..

(16)

II I 1 I 1 I 1I 1I I1 1

Rochester Gas and Electric Table 3-2 A Off-Site Air Particulate Samplers Gross Beta Results in pCi/m3 Collection Date Sta. #8 (C) Sta.#9 (I) Sta. #10 (C) Sta. #11 (I) Sta.#12 (C) Average 8-Jan 0.018 0.003 0.018 +/- 0.004 0.021 +/- 0.004 0.020 +/- 0.003 0.022 0.004 0.019 16-Jan 0.017 0.003 0.015 +/- 0.003 0.022 +/- 0.003 0.017 +/- 0.003 0.024 0.004 0.019 22-Jan 0.022 0.004 0.016 +/- 0.004 0.022 +/- 0.004 0.018 +/- 0.003 0.022 0.004 0.020 29-Jan 0.015 0.003 0.018 +/- 0.004 0.029 +/- 0.004 0.017 +/- 0.003 0.026 0.004 0.021 5-Feb 0.018 0.003 0.015 +/- 0.004 0.020 +/- 0.003 0.016 +/- 0.003 0.022 0.004 0.018 12-Feb 0.019 0.003 0.018 +/- 0.004 0.019 +/- 0.003 0.018 +/- 0.003 0.026 0.004 0.020 20-Feb 0.020 0.003 0.018 +/- 0.004 0.021 +/- 0.003 0.020 +/- 0.003 0.022 0.004 0.020 26-Feb 0.013 0.003 0.016 +/- 0.004 0.013 +/- 0.003 0.014 +/- 0.003 0.018 0.004 0.015 5-Mar 0.017 0.003 0.016 +/- 0.004 0.017 +/- 0.003 0.016 +/- 0.003 0.026 0.004 0.018 12-Mar 0.010 0.002 0.011 +/- 0.003 0.013 +/- 0.003 0.011 +/- 0.002 0.016 0.004 0.012 19-Mar 0.014 0.003 0,014 +/- 0.004 0.018 +/- 0.003 0.013 +/- 0.003 0.018 0.004 0.015 26-Mar 0.013 0.003 0.011 +/- 0.004 0.012 +/- 0.002 0.011 +/- 0.002 0.017 0.004 0.013 2-Apr 0.011 0.003 0.011 +/- 0.004 0.010 +/- 0.002 0.013 +/- 0.003 0.014 0.004 0.012 9-Apr 0.015 0.003 0.011 +/- 0.004 0.014 +/- 0.003 0.014 +/- 0.003 0.018 0.004 0.015 16-Apr 0.009 0.002 0.008 +/- 0.003 0.010 *+ 0.002 0.007 +/- 0.002 0.011 0.004 0.009 23-Apr 0.020 0.003 0.017 +/- 0.004 0.018 + 0.003 0.015 +/- 0.003 0.022 0.004 0.019 30-Apr 0.021 0.003 0.023 +/- 0.004 0.021 +/- 0.003 0.022 +/- 0.003 0.026 0.005 0.022 7-May 0.027 0.004 0.023 +/- 0.004 0.021 +/- 0.003 0.023 +/- 0.003 0.033 0.005 0.025 14-May 0.016 0.004 0.016 +/- 0.004 0.018 + 0.003 0.018 +/- 0.003 0.021 0.004 0.018 21-May 0.013 0.003 0.011 +/- 0.003 0.012 + 0,002 0.012 +/- 0.003 0.018 0.004 0.013 29-May 0.005 0.002 0.009 +/- 0.003 0.009 +/- 0.002 0.008 +/- 0.002 0.008 0.003 0.008 4-Jun 0.008 0.003 0.008 +/- 0.003 0.007 + 0.002 0.008 +/- 0.003 0.012 0.004 0.009 11-Jun 0.014 0.003 0.013 +/- 0.003 0.013 + 0.002 0.012 +/- 0.003 0.014 0.004 0.013 18-Jun 0.015 0.003 0.017 +/- 0.004 0.016 + 0.003 0.017 +/- 0.003 0.018 0.003 0.017 25-Jun 0.018 0.003 0.016 +/- 0.003 0.011 +/- 0.002 0.014 +/- 0.003 0.011 0.002 0.014 2-Jul 0.021 0.003 0.021 +/- 0.004 0.019 +/- 0.003 0.019 +/- 0.003 0.016 0.003 0.019 Maximum 0.027 +/- 0.004 0.023 +/- 0.004 0.029 +/- 0.004 0.023 +/- 0.003 0.033 +/- 0.005 Average 0.016 0.015 0.016 0.015 0.019 Minimum 0.005 +/- 0.002 0.008 +/- 0.003 0.007 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.003 I= Indicator C= Control (17)

Rochester Gas and Electric

Table 3-2 B Off-Site Air Particulate Samplers Gross Beta Results in pCi/m3 Collection Date Sta. #8 (C) Sta. #9 (I) Sta. #10 (C) Sta. #11 (I) Sta. #12 (C) Average 9-Jul 0.015 +/- 0.003 0.012 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.003 0.011 +/- 0.002 0.013 16-Jul 0.010 +/- 0.003 0.012 +/- 0.003 0.011 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 23-Jul 0.016 +/- 0.003 0.015 +/- 0.003 0.014 +/- 0.003 0.018 +/- 0.003 0.013 +/- 0.002 0.015 30-Jul 0.015 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.013 1 0.002 0.015 6-Aug 0.022 +/- 0.003 0.021 +/- 0.004 0.020 +/- 0.003 0.021 +/- 0.003 0.017 +/- 0.003 0.020 13-Aug 0.024 +/- 0.003 0.022 +/- 0.004 0.023 +/- 0.003 0.024 +/- 0.003 0.019 +/- 0.003 0.023 20-Aug 0.018 +/- 0.003 0.019 +/- 0.004 0.013 +/- 0.004 0.017 +/- 0.003 (b) 0.017 27-Aug 0.017 +/- 0.003 0.016 +/- 0.004 0.012 +/- 0.004 0.018 +/- 0.003 0.011 +/- 0.002 0.015 4-Sep 0.016 +/- 0.002 0.015 +/- 0.003 0.016 +/- 0.004 0.018 +/- 0.003 0.017 +/- 0.002 0.016 10-Sep 0.021 +/- 0.004 0.018 +/- 0.004 0.020 +/- 0.006 0.019 +/- 0.004 0.019 +/- 0.003 0.019 17-Sep 0.015 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.004 0.014 +/- 0.003 0.013 +/- 0.003 0.014 24-Sep 0.022 +/- 0.003 0.031 +/- 0.005 0.022 +/- 0.005 0.025 +/- 0.004 0.021 +/- 0.003 0.024 1-Oct 0.006 +/- 0.002 0.009 +/- 0.003 0.004 +/- 0.004 0.007 +/- 0.002 0.008 +/- 0.002 0.007 9-Oct 0.018 +/- 0.003 0.019 +/- 0.004 0.019 +/- 0.004 0.020 +/- 0.003 0.018 +/- 0.003 0.019 15-Oct 0.017 +/- 0.003 0.019 +/- 0.004 0.015 +/- 0.005 0.016 +/- 0.004 0.013 +/- 0.003 0.016 23-Oct 0.015 +/- 0.003 0.018 +/- 0.004 0.017 +/- 0.004 0.019 +/- 0.003 0.014 +/- 0.003 0.017 29-Oct 0.012 +/- 0.003 0.010 +/- 0.003 0.012 +/- 0.005 0.013 +/- 0.003 0.011 +/- 0.003 0.012 5-Nov 0.017 +/- 0.003 0.018 +/- 0.004 0.015 +/- 0.004 0.020 +/- 0.003 0.018 +/- 0.003 0.018 12-Nov 0.017 +/- 0.003 0.013 +/- 0.003 0.015 +/- 0.004 0.015 +/- 0.003 0.016 +/- 0.003 0.015 19-Nov 0.034 +/- 0.004 0.034 +/- 0.005 0.030 +/- 0.006 0.041 +/- 0.004 0.030 +/- 0.004 0.034 26-Nov 0.019 +/- 0.003 0.020 +/- 0.004 0.019 +/- 0.005 0.019 +/- 0.003 0.019 +/- 0.003 0.019 3-Dec 0.014 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.004 0.018 +/- 0.003 0.013 +/- 0.003 0.015 10-Dec 0.028 +/- 0.004 0.024 +/- 0.004 0.026 +/- 0.005 0.030 +/- 0.004 0.026 +/- 0.003 0.027 17-Dec 0.021 +/- 0.003 0.020 +/- 0.004 0.020 +/- 0.005 0.026 +/- 0.004 0.019 +/- 0.003 0.021 26-Dec 0.020 +/- 0.003 0.020 +/- 0.003 0.019 +/- 0.004 0.019 +/- 0.003 0.019 +/- 0.003 0.019 2-Jan 0.016 +/- 0.003 0.017 +/- 0.004 0.017 +/- 0.005 0.014 +/- 0.003 0.017 +/- 0.003 0.016 Maximum 0.034 +/- 0.004 0.034 +/- 0.005 0.030 +/- 0.006 0.041 +/- 0.004 0.030 +/- 0.004 Average 0.018 0.018 0.017 0.019 0.016 Minimum 0.006 +/- 0.002 0.009 +/- 0.003 0.004 +/- 0.004 0.007 +/- 0.002 0.008 +/- 0.002 (b) data rejected, statistical outlier I= Indicator C= Control (18)

(0

':o 0

CD)

-nCD CD cn CA) 0) m C) 0)

Rochester Gas and Electric Table 3-4A 13 Week Composite Gamma Isotopic Analysis Result in pCi/m3 First Qtr Station 7Be 40K 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce

2 0.092+/-0.017 <.009 <.003 <.013 <.004 <.001 <.009 <.006 <.005 <.006 <.015 <.002 <.001 <.028 <.005 <.007

3 0.078+/-0.013 <.018 <.001 <.005 <.003 <.002 <.005 <.003 <.001 <.003 <.020 <.002 <.002 <.024 <.004 <.007

4 0.090+/-0.013 0.041+/-0.010 <.001 <.007 <.002 <.001 <.006 <.004 <.004 <.003 <.018 <.002 <.002 <.023 <.005 <.008

5 0.081+/-0.012 <.024 <.002 <.005 <.002 <.001 <.004 <.003 <.001 <.003 <.012 <.002 <.001 <.018 <.003 <.005

6 0.060+/-0.010 <.014 <.001 <.016 <.002 <.001 <.004 <.004 <.003 <.001 <.020 <.002 <.001 <.005 <.003 <.006

7 0.080+/-0.011 <.013 <.001 <.004 <.002 <.002 <.002 <.004 <.002 <.002 <.013 <.001 <.001 <.013 <.002 <.003

8 0.078+/-0.012 <.016 <.002 <.006 <.003 <.002 <.004 <.003 <.004 <.003 <.016 <.001 <.001 <.017 <.004 <.006

9 0.080+/-0.014 0.046+/-0.01 <.002 <.009 <.004 <.002 <.006 <.006 <.004 <.004 <.021 <.003 <.002 <.026 <.006 <.009

10 0.093+/-0.011 <.005 <.001 <.006 <.002 <.002 <.003 <.004 <.001 <.003 <.011 <.001 <.001 <.005 <.003 <.005

11 0.084+/-0.010 <.004 <.001 <.005 <.001 <.002 <.001 <.003 <.002 <.002 <.010 <.002 <.001 <.005 <.002 <.004

12 0.120+/-0.015 <.018 <.002 <.005 <.002 <.003 <.004 <.003 <.003 <.002 <.013 <.002 <.001 <.007 <.003 <.005

13 0.120+/-0.016 <.007 <.002 <.008 <.002 <.003 <.005 <.005 <.005 <.004 <.018 <.002 <.001 <.034 <.005 <.008 (20)

Rochester Gas and Electric Table 3-4B3 13 Week Composite Gamma Isotopic Analysis Result in pCi/m3 Second Qtr Station 7Be 40K 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce

2 0.101+/-0.016 <.025 <.003 <.003 <.004 <.003 <.005 <.005 <.004 <.004 <.021 <.002 <.003 <.024 <.005 <.006

3 0.111+/-0.013 <.005 <.001 <.004 <.002 <.001 <.005 <.003 <.004 <.002 <.011 <.001 <.001 <.005 <.002 <.005

4 0.104+/-0.014 <.026 <.002 <.006 <.003 <.002 <.005 <.004 <.003 <.003 <.015 <.002 <.002 <.016 <.004 <.006

5 0.122+/-0.013 <.005 <.001 <.005 <.001 <.002 <.004 <.004 <.004 <.002 <.012 <.002 <.001 <.005 <.002 <.005

6 0.118+/-0.014 <.015 <.001 <.007 <.003 <.002 <.005 <.004 <.003 <.003 <.017 <.001 <.001 <.014 <.003 <.006

7 0.104+/-0.011 <.016 <.001 <.001 <.001 <.001 <.004 <.003 <.002 <.002 <.009 <.001 <.001 <.014 <.002 <.003

8 0.088+/-0.012 0.044+/-0.011 <.002 <.007 <.003 <.003 <.005 <.005 <.003 <.003 <.015 <.002 <.001 <.005 <.004 <.006

9 0.104+/-0.014 0.045+/-0.010 <.002 <.008 <.003 <.003 <.005 <.005 <.004 <.004 <.021 <.002 <.002 <.017 <.005 <.009

10 0.126+/-0.012 <.004 <.001 <.005 <.001 <.001 <.003 <.003 <.003 <.002 <.012 <.002 <.001 <.014 <.002 <.003

11 0.121+/-0.013 <.005 <.001 <.006 <.003 <.001 <.002 <.004 <.003 <.002 <.014 <.001 <.001 <.004 <.002 <.005

12 0.151+/-0.017 <.006 <.001 <.010 <.002 <.003 <.006 <.004 <.004 <.002 <.022 <.001 <.001 <.006 <.003 <.006

13 0.125+/-0.015 0.062+/-0.012 <.001 <.007 <.004 <.002 <.005 <.006 <.005 <.004 <.024 <.003 <.002 <.022 <.005 <.009 (21 )

I f Rochester Gas and Electric Table 3-4C 13 Week Composite Gamma Isotopic Analysis Result in pCi/m3 Third Qtr Station 7Be 40K 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce

2 0.128+/-0.014 <.023 <.001 <.003 <.002 <.001 <.001 <.004 <.003 <.002 <.016 <.001 <.001 <.021 <.002 <.006

3 0.093+/-0.012 <.023 <.002 <.006 <.002 <.001 <.004 <.003 <.003 <.002 <.002 <.002 <.001 <.006 <.003 <.004

4 0.096+/-0.012 <.014 <.001 <.009 <.002 <.000 <.003 <.004 <.004 <.003 <.016 <.001 <.001 <.015 <.003 <.005

5 0.099+/-0.014 <.006 <.002 <.011 <.002 <.003 <.007 <.005 <.003 <.004 <.014 <.002 <.002 <.031 <.005 <.008

6 0.107+/-0.014 0.038+/-0.008 <.002 <.002 <.003 <.002 <.004 <.005 <.004 <.003 <.019 <.002 <.002 <.017 <.004 <.009

7 0.096+/-0.011 0.018+/-0.005 <.001 <.008 <.002 <.001 <.003 <.003 <.003 <.003 <.011 <.001 <.001 <.005 <.003 <.004

8 0.097+/-0.011 0.029+/-0.006 <.001 <.005 <.002 <.001 <.003 <.003 <.003 <.003 <.013 <.001 <.001 <.017 <.002 <.003

9 0.101+/-0.012 0.042+/-0.008 <.002 <.008 <.002 <.001 <.003 <.004 <.003 <.003 <.015 <.002 <.001 <.004 <.004 <.007

10 0.093+/-0.011 <.004 <.002 <.002 <.002 <.001 <.001 <.004 <.004 <.002 <.012 <.001 <.001 <.025 <.003 <.004

11 0.119+/-0.011 <.011 <.001 <.005 <.001 <.001 <.002 <.002 <.002 <.001 <.009 <.001 <.001 <.016 <.002 <.003

12 0.095+/-0.009 0.031+/-0.006 <.001 <.007 <.002 <.001 <.002 <.003 <.002 <.002 <.010 <.001 <.001 <.011 <.003 <.004

13 0.097+/-0.012 0.051+/-0.008 <.002 <.009 <.003 <.002 <.004 <.005 <.003 <.003 <.017 <.002 <.001 <.017 <.004 <.007 (22)

Rochester Gas and Electric 12 Week Composite 13 Week Composite Gamma Isotopic Analysis Result in pCi/m3 Fourth Qtr Station 7Be 40K 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce

2 0.086+/-0.013 <.006 <.002 <.008 <.002 <.002 <.003 <.005 <.004 <.003 <.018 <.002 <.001 <.017 <.004 <.007

3 0.089+/-0.011 0.049+/-0.009 <.001 <.008 <.002 <.002 <.003 <.004 <.002 <.003 <.016 <.002 <.001 <.018 <.004 <.005

4 0.097+/-0.011 <.005 <.001 <.006 <.002 <.001 <.002 <.003 <.003 <.002 <.008 <.002 <.001 <.005 <.003 <.006

5 0.072+/-0.011 <.021 <.002 <.010 <.003 <.002 <.004 <.003 <.004 <.003 <.012 <.001 <.001 <.023 <.004 <.007

6 0.083+/-0.012 <.020 <.002 <.013 <.002 <.001 <.001 <.004 <.003 <.002 <.016 <.001 <.001 <.017 <.003 <.006

7 0.070+/-0.011 0.041+/-0.009 <.001 <.011 <.003 <.002 <.005 <.006 <.004 <.004 <.020 <.002 <.013 <.013 <.005 <.007

8 0.070+/-0.010 <.013 <.002 <.006 <.002 <.001 <.004 <.003 <.003 <.003 <.012 <.002 <.001 <.013 <.002 <.005

9 0.077+/-0.013 <.017 <.002 <.003 <.003 <.001 <.001 <.004 <.003 <.004 <.020 <.002 <.001 <.021 <.004 <.004

10 0.060+/-0.021 <.041 <.004 <.023 <.007 <.006 <.011 <.012 <.009 <.007 <.041 <.005 <.003 <.010 <.009 <.016

11 0.084+/-0.011 <.005 <.001 <.007 <.001 <.001 <.004 <.004 <.003 <.002 <.012 <.002 <.001 <.025 <.003 <.006

12 0.079+/-0.001 0.031+/-0.007 <.001 <.006 <.003 <.001 <.004 <.003 <.003 <.003 <.014 <.002 <.001 <.010 <.003 <.005

13 0.086+/-0.015 <.022 <.002 <.004 <.003 <.002 <.005 <.005 <.005 <.004 <.026 <.003 <.002 <.026 <.004 <.007 (23)

M"AY-24-2002 11: 00 RGE NOG ADM GI NNA 716 771 3943 P.02/02 Taole 3-5 Charcoal Cartridges Gamma Analysis for Iodine Results in pCi/m3 Collection Sta. #2 Sta. #4 Sta. #7 Sta. #8 Sta- #9 Sta. #11 Date

<.015 <.037 <.017 <.009 <.020 <.010 8-Jan

<.017 <.016 <.012 <.018 <.011 16-Jan <.021

<.016 <.012 <.014 <.020 <.011 22-Jan <.019

<.017 <.013 <.010 <.032 <.015 29-Jan <.027

<.021 <.01s <.009 <.014 <.015 <.010 S-Feb

<.023 <.011 <.017 <.017 <013 12-Feb <.026

<.022 <.016 :c.013 <.015 <.016 <.010 2D-Feb

<.020 <.011 <.013 <.029 <.014 26-Feb <.020

<.018 <.013 <.015 <.019 <.013 5-Mar <.020

<.022 <.013 <.015 <.016 <.020 <.015 12-Mar 19-Mar <.031 <.014 <.012 <.017 <.024 <.009

<.029 C.018 <.020 <.014 <.025 <.013 26-Mar 2-Apr <.038 <.020 <.013 <.019 <.017 <.013 9-Apr <.032 <.023 <.023 <.019 <.026 <.013 16-Apr <.030 <.015 <.014 <.017 <.019 <.008 23-Apr <.044 <.027 <.035 <.030 <.037 <.021 30-Apr <.028 <.028 <.020 <.019 <.054 <.016 7-May <.042 <.043 <.026 <.034 <.043 <.032 14-May <.035 <.035 <.029 <.042 c.028 <,025 21-May <.041 <.022 <.017 <.028 <.037 <.032 29-May <.018 <.013 <.012 <.012 <.016 <1011 4-Jun <.061 <.023 <.028 <.020 <.042 <.024 11-Jun <.044 <.033 <.023 <.027 <.036 <.017 18-Jun <.028 <.026 <,024 <.025 <.023 <.021 25-Jun <.054 <.022 <.024 <.030 <.031 <.020 2-Jul <.042 <.016 <.020 <.014 <.039 <.024 9-Jul <.053 <.021 <.028 <.021 <.029 <.027 16-Jul <.051 <.034 <.029 <.026 <.031 <.024 23-Jul <.026 <.020 <.026 <,021 <.040 <.014 30-Jul <.030 <.028 <.033 <.016 <.034 <.028 6-Aug <.020 <.025 <.019 <.015 c.026 <.023 13-Aug <.028 <.022 - <.017 <.021 <.027 <.022 20-Aug -. 006 <.023 <.006 <,014 <.023 <.019 27-Aug <.030 <.014 <.017 <.029 <.006 <.021 4-Sep <.015 <.063 <.027 <.024 <.023 <.02B 10-Sep <.026 <.023 <,031 <.020 <.021 <.028 17.Sep <.017 <.027 <'.046 <M023 <.027 <.021 24-Sep <.024 <.029 <.027 <.020 <.031 <.020 1-Oct <,027 <.038 <.022 <.016 <.028 <.039 9-Oct <.023 <.024 <.016 <.025 <.034 <.019 16-Oct <.033 ',030 <.034 <.027 <.008 <.037 23-0cw <.024 <.043 <.023 <.013 <.006 <,022 29-Oct C.041 <.032 <.032 <.034 <.030 <.025 5-Nov <.034 <.025 <.030 <.021 <.032 <.028 12-Nov <.027 4.017 <.022 <.028 <.032 <.035 19-Nov <.024 <.023 <,020 <.017 <.028 <.023 26-Nov <.033 <.036 <.025 <.021 <.024 <.022 3-Dec <.062 <.023 <.028 <.022 <.032 <.015 10-Dec <.021 <.023 <.027 <.021 <.037 <.032 17-Dec <.021 <.020 <.025 <.024 <.032 <.021 26-Dec <.015 <.018 <.021 <.017 <.017 <.019 2-Jan <.036 <.031 <,049 <.024 <.025. <.040 (24)

TOTAL P.02

I I I I I I [ [

Rochester Gas and Electric Figure 3-6 Annual Trending of Air Activity IGross Beta Analysisl 0.350 0.300 p 0.250 c 0.200 u

M 0.150 e

t e

0.100 r

0.050 0.000 0)0N0)0 0qt )00 )0)

W M0)0 W 0 C) -N N-M N-Nt-N- -N-N-N-CD ND MD LO D (DC r- WD C 00C (N C11 Years 1968 - 2001

--- Onsite ---- Offsite]

Peaks are indicative of atmospheric nuclear weapon detonations (25)

3.3 Water Samples Water samples are collected on a schedule specified in the ODCM, from locations surrounding the plant to assess if there 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) 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 2001 averages were 2.17 pCi/liter and 2.51 pCi/liter for the upstream and downstream samples respectively. Gamma isotopic analysis of the monthly composite samples showed no significant difference in activity between the upstream and downstream samples.

A graphical comparison of upstream vs downstream gross beta analysis results is given in Table 3-7A. Peaks up to 10 pCi/liter can occur when the lake is stirred up by wind and the weekly sample includes large quantities of suspended silt. A trend plot, Table 3-7 B, showing the annual average activity measured during the years since 1968 is included to show the data during the years the R.E. Ginna Nuclear Power Plant has been in operation. The peaks correspond to the years when atmospheric testing of nuclear weapons occurred.

Weekly samples are taken from the plant circulating water intake (Circ In) and discharge canal (Circ Out), and composited monthly. The 2001 averages were 2.25 pCi/liter and 2.51 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 +

2 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.

26

Isotopic Analysis Gamma isotopic analysis is performed on each monthly sample and on each monthly composite of weekly samples. 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 distilled to remove interferences for analysis by beta scintillation. Tritium data is given in Table 3-15.

Radioiodine analysis All monthly composite water samples are analyzed for Iodine-131. The analysis allows the determination of Iodine-131 activity of <lpCi/liter. Radioiodine data is given in Table 3-16. Any positive counts and the 1 sigma error are reported. During 2001, no sample results indicated 1-131 activity in excess of the LLD for the analysis. One control sample, September composite from Russell failed to meet the required LLD of 1.0 pCi/liter. Actual calculated LLD was 1.49 pCi/liter.

27

Rochester Gas and Electric Figure 3-7A Environmental Water Samples Gross Beta Analysis for 2001 5.00 4.50 4.00 P 3.50 C

i 3.00

/

2.50 L

i 2.00 t

e r 1.50 1.00 0.50 0.00 I I I I I Jan Feb March April May June July Aug Sept Oct Nov Dec Week Number

--- OWD --.- Russell (28)

Rochester Gas and Electric Figure 3-7B Annual Trending of Envrionmental Water Samples Gross Beta Analysis 14.00 12.00 10.00 P

C i 8.00 L

t 6.00 e

r 4.00 2.00 0.00 Oc CO CO o0)0 N-- N- Co N-.

N-- N-- - N-IC (0 N- N-N- co w-r- p )0 oo N-- CO

- C4 CO CO

C,) CO If CO (

CO N-. CO CO co CO c)0)0))0 N CC o- )0)00)00)0 o 0 ,o 0404 Years 1968 - 2001

- Russell OWD (29)

Rochester Gas and Electric Table 3-8 Environmental Water Samples Gross Beta Analysis Results in pCi / I Month Russell O.W.D. Circ In Circ Out Deer Creek January 1.86 +/- 0.44 2.72 0.48 1.84 0.44 2.52 +/- 0.46 2.85 +/- 0.60 February 2.12 +/- 0.50 2.41 0.50 1.55 0.45 2.57 +/- 0.48 3.45 +/- 0.57 March 2.25 +/- 0.49 2.62 0.50 2.68 0.50 3.64 +/- 0.53 3.79 +/- 0.60 April 2.15 +/- 0.47 2.46 0.47 2.30 0.47 2.82 +/- 0.49 3.12 +/- 0.48 May 1.54 +/- 0.48 0.86 0.45 1.96 0.49 0.98 +/- 0.46 3.82 +/- 0.56 June 2.12 +/- 0.44 2.72 0.47 2.24 0.45 2.34 +/- 0.45 5.14 +/- 0.60 July 1.44 +/- 0.43 2.13 0.44 1.15 0.34 2.61 +/- 0.47 5.64 +/- 0.65 August 1.91 +/- 0.53 2.13 0.53 1.82 0.53 2.14 +/- 0.53 4.64 +/- 0.66 September 2.21 +/- 0.47 3.10 0.45 2.16 0.40 3.17 +/- 0.45 3.93 +/- 0.53 October 2.37 +/- 0.44 3.29 0.51 2.63 0.47 3.33 +/- 0.51 4.10 +/- 0.70 November 2.58 +/- 0.55 3.26 0.56 3.12 0.56 2.59 +/- 0.55 1.36 +/- 1.02 December 3.43 +/- 0.93 2.40 +/- 0.89 3.52 +/- 0.90 1.45 +/- 0.89 4.95 +/- 1.22 Maximum 3.43 +/- 0.93 3.29 +/- 0.51 3.52 +/- 0.90 3.64 +/- 0.53 5.64 +/- 0.65 Average 2.17 2.51 2.25 2.51 3.90 Minimum 1.44 +/- 0.43 0.86 +/- 0.45 1.15 +/- 0.34 0.98 +/- 0.46 1.36 +/- 1.02 (30)

Rochester Gas and Electric Table 3-9 Russell Station Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zr195Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Jan <29 <38 <3 <8 <3 <3 <7 <5 <4 <4 <26 <3 <3 <12 <7 <19 <57 Feb <23 <26 <2 <5 <3 <3 <5 <5 <3 <3 <23 <2 <2 <6 <5 <15 36+/-14 March <39 <55 <4 <10 <5 <5 <9 <8 <6 <6 <44 <2 <4 <11 <11 <35 <95 April <42 <41 <4 <10 <5 <4 <10 <9 <5 <6 <48 <4 <4 <10 <9 <29 77+/-31 May <25 <28 <2 <6 <3 <3 <5 <5 <3 <3 <23 <2 <2 <8 <5 <16 61+/-18 June <31 <32 <3 <8 <3 <4 <6 <6 <4 <4 <28 <3 <3 <9 <6 <19 96+/-23 July <20 <28 <2 <5 <2 <2 <5 <5 <3 <3 <21 <2 <2 <9 <5 <14 95+/-19 Aug <21 <29 <2 <9 <2 <2 <4 <5 <3 <2 <21 <2 <2 <11 <5 <14 48+/-15 Sept <37 <47 <3 <11 <4 <3 <4 <7 <5 <5 <33 <2 <3 <14 <10 <28 105+/-37 Oct <24 <29 <2 <8 <3 <2 <5 <5 <3 <4 <24 <1 <2 <9 <6 <16 63+/-13 Nov <25 <30 <2 <8 <3 <2 <3 <5 <4 <3 <25 <1 <2 <7 <7 <20 100+/-21 Dec <17 <22 <1 <5 <2 <2 <2 <3 <2 <2 <1

<18 <2 <5 <5 <14 87+/-16 (31)

(IIIIII I I I Rochester Gas and Electric Table 3-10 Ontario Water District Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Z r 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Jan <27 <33 <2 <7 <3 <3 <6 <5 <4 <3 <29 <3 <3 <7 <3 <19 102+/-23 Feb <37 <48 <4 <9 <5 <5 <10 <8 <6 <5 <43 <2 <4 <11 <9 <31 100+/-36 March <45 <47 <4 <9 <5 <4 <10 <8 <6 <6 <45 <4 <4 <14 <6 <30 176+/-35 April <40 <44 <4 <10 <5 <5 <11 <8 <6 <6 <51 <4 <4 <12 <8 <28 <83 May <30 <34 <3 <7 <3 <3 <6 <6 <4 <4 <31 <3 <3 <8 <6 <20 64+/-23 June <43 <47 <4 <9 <5 <4 <11 <8 <5 <6 <47 <4 <5 <10 <8 <28 82+/-38 July <37 <43 <3 <11 <5 <4 <8 <8 <5 <6 <48 <4 <4 <10 <8 <28 56+/-32 Aug <42 <53 <4 <18 <5 <4 <10 <9 <7 <7 <45 <4

<3 <13 <10 <30 <100 Sept <39 <39 <3 <10 <3 <3 <8 <7 <5 <5 <34 <2 <3 <10 <7 <27 92+/-32 Oct <31 <46 <4 <11 <4 <4 <9 <7 <5 <5 <35 <4 <9

<4 <7 <26 70+/-27 Nov <30 <40 <3 <11 <3 <3 <8 <6 <4 <4 <29 <3 <3 <11 <8 <23 102+/-25 Dec <22 <28 <2 <8 <3 <2 <5 <4 <3 <3 <25 <1 <2 <7 <4 <15 97+/-20 (32)

Rochester Gas and Electric Table 3-11 Circ-ln Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 54Mn 59Fe 5 8Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Jan <21 <29 <5 <3 <2 <5 <4 <3 <3 <25 <1 <2 <6 <6 <18 58+/-23 Feb <23 <29 <5 <3 <2 <6 <5 <3 <3 <2

<23 <2 <5 <4 <19 116+/-21 March <38 <43 <11 <4 <4 <9 <8 <5 <6 <37 <4 <4 <13 <8 <23 <79 April <25 <30 <7 <3 <3 <6 <6 <4 <4 <27 <3 <2 <7 <6 <18 144+/-23 May <37 <45 <11 <4 <4 <9 <7 <5 <6 <39 <4 <4 <7 <8 <26 84+/-29 June <46 <56 <11 <6 <5 <13 <9 <6 <7 <46 <5

<5 <14 <10 <32 66+/-41 July <35 <43 <10 <5 <4 <8 <7 <5 <5 <2

<33 <4 <10 <7 <21 67+/-30 Aug <43 <56 <15 <5 <5 <8 <10 <7 <7 <5

<43 <4 <14 <10 <31 95+/-34 Sept <36 <5 <14 <4 <4 <10 <8 <5 <5 <36 <4

<2 <9 <9 <25 42+/-26 Oct <32 <38 <10 <3 <3 <4 <6 <4 <4 <3

<36 <2 <6 <8 <28 91+/-27 Nov <24 <34 <9 <3 <3 <6 <5 <4 <4 <29 <3 <3 <7 <6 <18 136+/-22 Dec <17 <24 <6 <2 <2 <4 <4 <3 <3 <20 <2 <2 <7 <3 <13 103+/-16 (33)

Rochester Gas and Electric Table 3-12 Circ. Outlet Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Jan <22 <28 <2 <5 <3 <2 <3 <4 <3 <3 <23 <1 <2 <5 <6 <19 96+/-22 Feb <42 <39 <4 <11 <4 <4 <10 <8 <4 <6 <37 <4 <4 <11 <8 <25 <73 March <35 <46 <4 <12 <5 <4 <10 <9 <7 <5 <40 <3 <4 <14 <9 <30 <96 April <37 <41 <4 <8 <4 <4 <9 <7 <5 <5 <42 <2 <3 <8 <8 <27 80+/-31 May <25 <32 <3 <7 <3 <3 <5 <6 <4 <4 <30 <2 <2 <8 <6 <17 145+/-22 June <35 <42 <3 <8 <4 <3 <4 <7 <5 <5 <39 <2 <3 <9 <8 <27 97+/-29 July <43 <47 <4 <10 <5 <5 <12 <8 <5 <6 <44 <3 <4 <11 <10 <30 79+/-33 Aug <43 <57 <4 <13 <5 <4 <9 <7 <5 <6 <41 <3 <4 <11 <10 <31 <92 Sept <36 <39 <3 <13 <4 <3 <8 <8 <5 <5 <39 <3 <3 <9 <5 <23 120+/-31 Oct <43 <48 <4 <15 <5 <4 <10 <9 <6 <5 <41 <3 <4 <13 <10 <31 101+/-35 Nov <33 <45 <3 <10 <4 <3 <8 <7 <5 <4 <35 <2 <3 <14 <8 <21 113+/-21 Dec <19 <25 <2 <6 <2 <2 <4 <4 <3 <3 <21 <2 <2 <7 <5 <16 63+/-18 (34)

Rochester Gas and Electric Table 3-13 Deer Creek Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb 103Ru 106Ru 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Jan <28 <29 <4 <9 <4 <5 <6 <7 <4 <4 <42 <3 <5 <6 <6 <27 113+/-33 Feb <19 <18 <2 <4 <2 <2 <5 <4 <2 <2 <20 <3

<2 <3 <33 <15 51+/-18 March <33 <32 <4 <9 <4 <4 <9 <7 <4 <4 <37 <4 <4 <6 <6 <26 62+/-30 April <37 <37 <4 <8 <5 <5 <11 <9 <5 <6 <48 <3 <6 <7 <7 <30 <113 May <77 <73 <9 <18 <10 <10 <21 <12 <8 <9 <90 <8 <8 <13 <13 <54 <19 June <51 <59 <6 <11 <5 <5 <15 <10 <6 <7 <49 <5 <5 <11 <8 <38 136+/-39 July <38 <37 <5 <10 <4 <5 <10 <9 <5 <5 <40 <4

<5 <7 <7 <30 <96 Aug <40 <41 <5 <14 <4 <5 <13 <10 <6 <5 <44 <5

<3 <7 <7 <25 <97 Sept <52 <50 <6 <18 <6 <5 <19 <10 <7 <6 <66 <6 <7 <10 <10 <38 <142 Oct <54 <48 <6 <14 <5 <7 <13 <10 <6 <7 <53 <6

<5 <7 <9 <39 <131 Nov <43 <50 <6 <17 <6 <6 <14 <9 <6 <6 <60 <6 <8

<5 <6 <36 72+/-42 Dec <39 <47 <7 <13 <5 <6 <16 <11 <6 <6 <49 <5 <5 <7 <10 <37 105+/-46 (35)

II [ I I I I Rochester Gas and Electric Table 3-14 Environmental Water Samples Tritium Analysis Results in pCi/L Month of Ruissell O.W.D. Circ In Circ Out Deer Creek January <267 <268 <268 < 267 <275 February <271 <273 <277 < 275 <294 March <273 <268 <271 < 270 <276 April <282 <286 <285 < ?84 <296 May <291 <287 <291 < 291 <308 June <273 <278 <277 < 278 <287 July <241 <240 <239 < 240 <252 August <258 <260 <260 <2259 <271 September <260 <256 <253 <2254 <267 October <265 <267 <270 <2 72 <276 November <251 <254 <255 <2250 <262 December <256 <259 <258 <2 58 <258 (36)

Rochester Gas and Electric Table 3-15 Iodine in Water Results in pCi/L Month of Russell O.W.D. Circ. In Circ. Out Deer Creek January <.88 <.39 <.45 <.44 <.46 February <.64 <.60 <.54 <.43 <.41 March <.81 <.60 <.47 <.47 <.56 April <.96 <.55 <.74 <.63 <.73 May <.65 <.58 <.58 <.71 <.97 June <.99 <.84 <.75 <.63 <.77 July <.96 <.63 <.58 <.62 <.70 August <.99 <.40 <.47 <.57 <.74 September <1.2 (a) <.57 <.50 <.42 <.58 October <.98 <.63 <.49 <.60 <.54 November <.72 <.43 <.50 <.97 <.45 December <.44 <.48 <.57 <.53 <.54 (37)

3.4 Milk Samples There are three indicator dairy herds located three to five miles from the plant. Milk samples are collected monthly during November through May from one of the three 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 Iodine-1 31 and also analyzed by gamma spectroscopy for major fission products.

All positive counts and the +/-1 sigma error are reported. During 2001, no samples indicated 1-131 activity that exceeded the LLD for the analysis.

Table 3-17 is a listing of all samples collected during 2001 with analytical results.

38

Rochester Gas and Electric Table 3-16 Milk Results in pCi/Liter Farm Date 1-131 Cs-134 Cs-1 37 Ba-1 40 K-40 FARM C 1/9/01 <.45 <5 <5 <7 1540+/-68 FARM D 1/9/01 <.42 <5 <6 <6 1540+/-66 FARM B 2/13/01 <.41 <5 <6 <6 1530+/-68 FARM D 2/13/01 <.51 <4 <4 <4 1440+/-58 FARM A 3/13/01 <.36 <3 <4 <4 1700+/-52 FARM D 3/13/01 <.50 <7 <7 <9 1760+/-76 FARM C 4/10/01 <.49 <5 <5 <5 1450+/-67 FARM D 4/10/01 <.33 <6 <7 <9 1640+/-98 FARM B 5/15/01 <.51 <7 <6 <10 1380+/-82 FARM D 5/15/01 <.67 <9 <8 <8 1470+/-97 FARM A 6/12/01 <.47 <7 <6 <7 3050+/-121 FARM B 6/12/01 <.59 <6 <8 <11 1480+/-95 FARM C 6/12/01 <.53 <12 <10 <12 1510+/-101 FARM D 6/12101 <.70 <4 <6 <6 1900+/-78 FARM A 6/26/01 <.52 <8 <7 <8 1360+/-77 FARM B 6/26/01 <.51 <9 <8 <11 1700+/-90 FARM C 6/26/01 <.58 <6 <6 <9 1380+/-80 FARM D 6/26/01 <.72 <10 <8 <12 1800+/-93 FARM A 7/10/01 <.47 <6 <5 <7 1430+/-71 FARM B 7/10/01 <.56 <8 <7 <7 1550+/-82 FARM C 7/10/01 <.79 <7 <6 <6 1420+/-76 FARM D 7/10/01 <.67 <9 <9 <8 1870+/-94 FARM A 7/24/01 <.47 <5 <5 <7 1450+/-71 FARM B 7/24/01 <.64 <6 <7 <8 1690+/-88 FARM C 7/24/01 <.61 <6 <7 <8 1460+/-79 FARM D 7/24/01 <.55 <9 <8 <6 1800+/-92 FARM A 8/7/01 <.57 <5 <6 <6 1560+/-74 FARM B 8/7/01 <.56 <7 <8 <9 1560+/-84 FARM C 8/7/01 <.70 <7 <6 <8 1380+/-77 FARM D 8/7/01 <.66 <7 <6 <7 1600+/-81 FARM A 9/5/01 <.39 <6 <6 <6 1420+/-70 FARM B 9/5/01 <.45 <7 <7 <7 1680+/-84 FARM C 9/5/01 <.45 <6 <6 <6 1530+/-59 FARM D 9/5/01 <.53 <5 <6 <7 1310+/-68 FARM A 9/18/01 <.42 <6 <5 <7 1460+/-71 FARM B 9/18/01 <.49 <8 <6 <8 1530+/-82 FARM C 9/18/01 <.59 <9 <6 <9 1500+/-83 FARM D 9/18/01 <.55 <7 <7 <12 1460+/-79 FARM A 10/2/01 <.53 <5 <5 <5 1410+/-63 FARM B 10/2/01 <.69 <6 <6 <5 1550+/-66 FARM C 10/2/01 <.58 <3 <4 <4 1450+/-46 FARM D 10/2101 <.73 <3 <4 <5 1490+/-48 FARM A 10/16/01 <.40 <6 <6 <6 1360+/-69 FARM B 10/16/01 <.47 <6 <6 <9 1570+/-79 FARM C 10/16/01 <.55 <7 <7 <12 1730+/-87 FARM D 10/16/01 <.60 <3 <6 <6 1710+/-62 FARM A 10/30/01 <.51 <7 <6 <6 1400+/-77 FARM B 10/30/01 <.51 <6 <6 <7 1410+/-75 FARM C 10/30/01 <.57 <7 <6 <8 1320+/-77 FARM D 10/30/01 <.64 <3 <6 <5 1780+/-63 FARM A 10/16/01 <.40 <6 <6 <6 1360+/-69 FARM B 10/16/01 <.47 <6 <6 <9 1570+/-79 FARM C 10/16/01 <.55 <7 <7 <12 1730+/-87 FARM D 10/16/01 <.60 <3 <6 <6 1710+/-62 FARM B 11/13/01 <.39 <4 <6 <9 1470+/-71 FARM D 11/12/01 <.54 <4 <5 <8 1280+/-75 FARM A 12/11/01 <.44 <3 <5 <6 2430+/-49 (39)

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 ifthey 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. G. & E. biologists and 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, 3-17B.

Samples of shoreline sediment are taken upstream (Russell Station) and downstream (OWD) of Ginna Station.

Results of the gamma isotopic analysis are included in Table 3-18.

40

I fI I I I Rochester Gas and Electric Table 3-17A Fish Samples Gamma Isotopic Analysis Results in pCi/kgm Wet Description 40K 51Cr 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb Indicator Fish First Half 2001 Brown Trout 5090+/-317 <270 <35 <61 <36 <27 <77 <46 <37 Rainbow Trout 6510+/-374 <312 <36 <99 <37 <49 <103 <71 <40 Freshwater Drum 6700+/-348 <400 <42 <101 <42 <39 <72 <73 <47 Smallmouth Bass 4260+/-267 <266 <29 <72 <30 <37 <83 <48 <36 Second Half 2001 Walleye 5490+/-318 <257 <27 <90 <27 <29 <66 <58 <31 White Sucker 4960+/-293 <242 <31 <101 <29 <36 <72 <48 <33 Yellow Perch 6010+/-291 <325 <33 <110 <36 <29 <78 <59 <37 Freshwater Drum 4220+/-298 <243 <31 <87 <42 <38 <63 <58 <36 Background Fish First Half 2001 Lake Trout 3730+/-194 <176 <23 <42 <21 <24 <56 <42 <22 White Sucker 5890+/-26 <237 <26 <64 <27 <34 <71 <47 <30 Freshwater Drum 3830+/-25 <255 <24 <72 <25 <29 <60 <49 <32 Smallmouth Bass 3720+/-258 <213 <25 <69 <34 <28 <70 <50 <31 Second Half 2001 Brown Trout 4350+/-350 <237 <34 <108 <37 <46 <106 <72 <44 Carp 4170+/-336 <303 <36 <90 <33 <39 <87 <47 <47 Chinook Salmon 4640+/-343 <307 <36 <109 <33 <44 <79 <55 <46 Rainbow Trout 4340+/-348 <298 <25 <118 <40 <44 <77 <56 <40 (41 )

t ( f F I I I I I I I I Rochester Gas and Electric Table 3-17B Fish Samples Gamma Isotopic Analysis Results in pCi/kgm Wet Description 103 Ru Ru 106 1311 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Indicator Fish First Half 2001 Brown Trout <31 <293 <48 <30 <32 <56 <39 <151 733+/-204 Rainbow Trout <36 <418 <59 <37 <39 <68 <50 <201 <692 Freshwater Drum <49 <458 <64 <27 <42 <52 <68 <255 996+/-312 Smallmouth Bass <29 <333 <65 <28 <28 <76 <36 <140 <520 Second Half 2001 Walleye <32 <318 <58 <24 <24 <61 <39 <121 945+/-195 White Sucker <29 <326 <58 <26 <26 <52 <38 <134 550+/-1:93 Yellow Perch <40 <361 <69 <22 <31 <56 <50 <200 669+/-266 Freshwater Drum <36 <333 <52 <29 55+/-11 <45 <37 <141 578+/-188 Background Fish First Half 2001 Lake Trout <22 <228 <40 <23 <21 <31 <26 <109 386+/-144 White Sucker <25 <272 <48 <28 <27 <43 <36 <138 405+/-154 Freshwater Drum <30 <260 <96 <26 <27 <94 <41 <134 32+/-17*

Smallmouth Bass <30 <266 <46 <30 <27 <49 <35 <118 <39 Second Half 2001 Brown Trout <37 <398 <65 <38 <36 <70 <47 <174 324+/-194 Carp <41 <422 <78 <34 <35 <82 <57 <191 <727 Chinook Salmon <37 <369 <80 <36 <26 <63 <47 <168 <530 Rainbow Trout <39 <368 <68 <27 <38 <64 <45 <163 835+/-226

statistical outlier from historical data (42)

IfI f I I I I f I f Rochester Gas and Electric Table 3-18 Lake Samples Gamma Isotopic Analysis Results in pCi/kgm Wet Description 40K Cr 51 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb OWD SHORE. 16500+/-504 <317 <35 <90 <38 <43 <59 <67 <49 SHORELINE SED. 11600+/-460 <367 <39 <117 <42 <39 <63 <75 <52 Description 103Ru 106Ru 1311 134Cs 137Cs 140Ba 141 Ce 144Ce 226Ra OWD SHORE. <37 <332 <87 <38 <34 <68 <57 <195 1000+/-286 SHORELINE SED. <46 <327 <205 <42 <41 <143 <68 <195 877+/-253 (43)

3.6 Veqetation Samples Crops are grown on the plant property in a location with a higher D/Q than the location of the maximally exposed individual 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.

44

I f f Rochester Gas and Electric Table 3-19 Vegetation Samples Gamma Isotopic Analysis Results in pCi/kgm Wet Description 40K Cr 51 54Mn 59Fe 58Co 60Co 65Zn 95Zr 95Nb Indicator Vegetation Lettuce 6420+/-243 <111 <18 <44 <17 <19 <41 <34 <19 Cherry 1630+/-46 <29 <4 <9 <4 <5 <10 <7 <4 Tomato 4840+/-124 <67 <9 <26 <10 <8 <23 <16 <10 Corn 2590+/-125 <79 <11 <33 <11 <13 <28 <18 <12 Apples 1800+/-79 <68 <9 <25 <9 <11 <20 <15 <8 Background Vegetation Cherry 1960+/-56 <37 <4 <12 <5 <6 <8

<11 <5 Lettuce 2450+/-136 <88 <13 <30 <14 <14 <33 <22 <12 Tomato 2270+/-104 <70 <29 <10 <12 <24 <20 <11 Corn 3060+/-123 <78 <10 <30 <11 <11 <25 <18 <10 103 Ru Ru 106 1311 134Cs 137Cs 140Ba 141Ce 144Ce 226Ra Indicator Vegetation Lettuce <17 <184 <15 <19 <15 <19 <19 <73 276+/-99 Cherry <4 <40 <5 <4 <4 <6 <5 <20 94+/-30 Tomato <9 <100 <10 <9 <8 <11 <11 <47 506+/-65 Corn <11 <117 <19 <12 <11 <16 <13 <48 141+/-62 Apples <9 <93 <9 <7 <9 <10 <14 <51 307+/-69 Background Vegetation Cherry <4 <45 <6 <5 <5 <7 <5 <21 65+/-29 Lettuce <13 <117 <18 <14 <12 <17 <15 <54 136+/-84 Tomato <8 <93 <14 <9 <9 <13 <13 <50 <166 Corn <9 <98 <15 <9 <9 <11 <12 <50 204+/-58 (45)

3.7 External Penetrating 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 2001, on-site exposure ranged between 10.4 -20.3 mrem/quarter, with an average exposure of 13.1 mrem/quarter and off-site ranged between 9.6 - 14.7 mrem/quarter with an average exposure of 11.4 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 TLD station in the vicinity of the National Guard outpost as the maximum dose to members of the public, leads to 4.8 millirem direct radiation dose to the maximally exposed member of the public.

Table 3-21 gives TLD readings for each quarter.

A trend chart with a comparison of data for each location for the years of 2000 and 2001 is included, Table 3-21. The data plotted is the average quarterly dose measured. TLD location #7 is elevated due to its proximity to radioactive equipment storage areas 46

( I I {

Rochester Gas and Electric Table 3-20 External Penetrating Radiation Thermoluminescent Dosimetry 2001 Units mrem/91 Day Quarter Location Type 1st Quarter 2nd Quarter 4th Quarter

2 - #7 plus #13 are 2 IYR 11.6 + 2.9 3rd Quarter 12.1 +/- 3.1 12.9 +/- 3.3 12.4 +/- 3.1 on-site near the line 3 12.0 +/- 3.0 12.7 +/- 3.2 14.5 +/- 3.7 13.4 +/- 3.4 of the highest annual 4 12.8 +/- 3.2 12.0 +/- 3.0 14.1 +/- 3.5 13.2 +/- 3.3 average ground level 5 13.6 +/- 3.4 12.6 +/- 3.2 15.1 +/- 3.8 13.1 +/- 3.3 concentration. 6 13.1 +/- 3.3 10.4 +/- 2.6 11.3 +/- 2.9 11.1 +/- 2.8 7 C 18.1 +/- 4.6 17.7 +/- 4.5 20.3 +/- 5,1 18.8 +/- 4.7

8 - #12 are offsite at 8 11.3 +/- 2.8 I 11.3 +/- 2.9 12.8 +/- 3.2 11.9 +/- 3.0 a distance of 8 to 15 miles. 9 10.7 +/- 2.7 10.5 C +/- 2.6 11.8 +/- 3.0 11.2 +/- 2.8 10 I 10.4 +/- 2.6 11.1 +/- 2.8 11.5 +/- 2.9 11.0 +/- 2.8 11 C 10.9 +/- 2,7 10.7 +/- 2.7 11.8 +/- 3.0 11.5 +/- 2.9 12 9.7 +/- 2.4 9.6 +/- 2.4 10.6 +/- 2.7 10.6 +/- 2.7 13 12.6 +/- 3.2 13.4 +/- 3.4 15.4 +/- 3.9 14.8 +/- 3.7

14 - #16 are located 14 11.6 +/- 2.9 11.4 +/- 2.9 13.6 +/- 3.4 11.9 +/- 3.0 along a line 3000 ft. west 15 11.9 +/- 3.0 13.1 +/- 3.3 14.7 +/- 3.7 13.8 +/- 3.5 of the plant. 16 12.1 +/- 3.0 12.0 +/- 3.0 14.3 + 3.6 13.1 +/- 3.3

17 - #21 are located 17 11.3 +/- 2.8 11.4 +/- 2.9 13.0 + 3.3 12.0 +/- 3.0 along Lake Road. 18 12.4 +/- 3.1 12.7 +/- 3.2 14.6 +/- 3.7 14.1 +/- 3.5 19 10.9 +/- 2.8 12.0 +/- 3.0 13.4 +/- 3.4 12.5 +/- 3.1 20 11.7 +/- 2.9 12.2 +/- 3.1 13.1 +/- 3.3 12.8 +/- 3.2 21 12.5 +/- 3.2 12.3 +/- 3.1 14.6 +/- 3.7 13.3 +/- 3.3

22 - #24 are located 22 11.2 +/- 2.8 11.2 +/- 2.8 12.3 +/- 3.1 11.7 +/- 2.9 along the east site 23 11.4 +/- 2.9 12.3 +/- 3.1 14.4 +/- 3.6 13.6 +/- 3.4 boundary line. 24 12.0 +/- 3.0 12.0 +/- 3.0 C 13.8 +/- 3.5 13.0 +/- 3.3

25 - #30 are offsite 25 10.5 +/- 2.7 10.6 C +/- 2.7 11.2 +/- 2.8 11.0 +/- 2.8 at a distance of 8 26 10.4 +/- 2.6 10.3 +/- 2.6 C 10.9 +/- 2.8 11.5 +/- 2.9 to 15 miles. 27 C 10.6 +/- 2.7 11.4 +/- 2.9 C 12.7 +/- 3.2 11.9 +/- 3.0 28 C 11.0 +/- 2.8 11.7 +/- 2.9 12.6 +/- 3.2 12.6 +/- 3.2 29 10.4 +/- 2.6 11.1 +/- 2.8 11.8 +/- 3.0 11.7 +/- 2.9 30 10.3 +/- 2.6 9.4 +/- 2.4 10.2 +/- 2.6 10.1 +/- 2.6

31 - #40 are located 31 12.2 +/- 3.1 12.3 +/- 3.1 14.4 +/- 3.6 12.9 +/- 3.3 in an arc at a distance 32 10.4 +/- 2.6 11.0 +/- 2.8 11.6 +/- 2.9 11.1 +/- 2.8 of 4 - 5 miles. 33 9.6 +/- 2.4 10.7 +/- 2.7 11.5 +/- 2.9 11.1 +/- 2.8 34 11.6 +/- 2.9 12.6 +/- 3.2 13.7 +/- 3.4 13.3 +/- 3.3 35 11.4 +/- 2.9 12.2 +/- 3.1 14.2 +/- 3.6 12.9 +/- 3.3 36 10.3 +/- 2.6 11.0 +/- 2.8 12.5 +/- 3.1 11.5 +/- 2.9 37 10.2 +/- 2.6 10.2 +/- 2.6 11.1 +/- 2.8 10.9 +/- 2.8 38 11.4 +/- 2.9 11.9 +/- 3.0 13.2 +/- 3.3 12.7 +/- 3.2 39 10.8 +/- 2.7 11.9 +/- 3.0 12.8 +/- 3.2 12.3 +/- 3.1 40 9.8 +/- 2.5 10.0 +/- 2.5 11.2 +/- 2.8 10.8 +/- 2.7 (47)

Rochester Gas and Electric Figure 3-21 External PenetrationDosimetry Radiation

=Thermoluminescent 20.0 18.0 16.0 A

V E 14.0 m 12.0 R

e 10.0 m

/ 8.0 Q 6 .0 T

R 4.0 2.0 0.0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 TLD Location Number

-- 2001 -- 2000 (48)

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 2001. The land use remains mainly agricultural in nature. There were several new private home developments. The three dairy operations nearest to the plant continued in operation with 40 to 70 milk cows. 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 2001 is attached.

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

5.0 EXTERNAL INFLUENCES During 2001, there were no external influences such as atmospheric weapons testing or accidents at other nuclear facilities which had an impact on the data reported.

49

Attachment I Land Use Census Sector Distance to Nearest Distance to Nearest Distance to Milk Residence Garden Producing Animals E 1260 meter N/A N/A ESE 1050 meter N/A N/A SE 610 meter N/A 8270 meter SSE 660 meter N/A 5230 meter S 1560 meter N/A N/A SSW 760 meter N/A N/A SW 660 meter N/A 4680 meter WSW 1350 meter N/A N/A W 1160 meter N/A N/A Changes from previous year:

None Milk animal locations:

No new milk producing animals identified in 2001 Land Use Census UFSAR change request: Y N X Land Use Census Completed Date:____

Reviewed Date:

50

Cý-04 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. JAFEL reports their comparison results to Ginna Station.

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 = Laboratory Analysis Reference Value 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.

52

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.

53

6.2 ANALYTICS SAMPLE NON-CONFORMITIES For 2001, two nuclides fell outside of the LCL and UCL, Cr-51 (Figures 6.1A, QC-2, 6.1C, QC-2 and 6.1D, QC-1) and Zn-65 (Figure 6.1D, QC-1). JAFEL was unable to identify systematic error or programmatic deficiency for either isotope.

Cr-51 Non-conformities A spiked mixed gamma in soil sample was received from Analytics, Inc. and 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. Seven of the nine radionuclides were quantified within the acceptable range. The results for Cr-51 and Zn-65 were determined to be outside the QA Acceptance Criteria.

An evaluation ofthe Cr-51 result was performed. The spectrum and peak search results were examined with no abnormalities identified. Cr-51 decays by electron capture with a 27.7 day half-life and a gamma ray energy of 320 Kev with a yield of 9.8%. No secondary gamma energies are produced in the Cr-51 decay scheme. This low gamma energy yield and short half-life will result in very low net counts for samples containing environmental levels of Cr-5 1. The average net count rate of the six analyses was less than one count per minute. The counting error for the six analyses was high and ranged from 26%

to 62%. The sample matrix of soil has a relatively high density, which would have a high self-absorption factor for the low energy gamma associated with Cr-51.

The combination ofthe following; low sample activity and resulting very small net count rate, short half life, low gamma energy, small gamma yield and high sample density, resulted in an inaccurate sample result. The wide range of the associated counting errors demonstrates the low confidence level in the reported results. The poor analytical results for this sample is not routine and does not indicate a programmatic deficiency in the analysis of Cr-51 in soil samples or other environmental media.

Additional non-conformities shown for Cr-51 analysis would also be due to the same factors: low sample activity, very low net count rate, short half-life, low gamma energy and small gamma yield. All these variables can result in a poorly defined spectrum peak 54

Confidence in the accurate analysis of Cr-51 can be easily demonstrated by other Cr-51 analytical results both in the aggregate sample results for the 2001 QA program and historical QA results. A review of historical QA data for 2000 was also performed to determine if this is a recurring systematic error or bias.

In 2000, numerous QA samples were analyzed which contained Cr-5 1. The mean ratio for these samples relative to the Known (reference) Value is 0.93. There was one Cr-51 nonconformity in the 2000 Crosscheck Program. The current and historical data demonstrate that there is no systematic error or significant bias for the analysis of Cr-51 in environmental samples. However, JAFEL is investigating additional options for improvement to Cr-51 analysis.

Zn-65 Non-conformity The Zn-65 result for sample E-2677-05 were also evaluated to be outside the Acceptance Criteria with a ratio of 0.73. A review of the peak search and raw spectrum shows that there was a possible interference peak with a centroid of 1120 Key.

In soil samples, Ra-226 is a naturally occurring radionuclide, which produces a secondary peak at 1120 Kev. When the 1115 Kev (Zn-65) peak is manually defined and the interfering 1120 Kev was eliminated, the calculated result for Zn-65 is 0.358+/-0.078 pCi/kg, which has an acceptable reference ratio of 0.97.

In most cases, the computer algorithm can differentiate the two adjacent peaks and correct for interferences from overlapping (doublet) peaks. In this particular sample spectrum, there was a low number of total counts in the 1110, to 1130 Key area of the spectrum. The computer did not identify the counts in the 1120 Kev area as a second peak due to the low activity and subsequent poor peak shape.

By not identifying the peak at 1120 Key the software did not resolve this section of the spectrum as a double peak.

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 non-conformities.

In 2001, eleven spiked samples were analyzed which contained certified concentrations of Zn-65 and other radionuclides. The mean ratio for all eleven Zn-65 results was 1.02 and the ratio for the four soil samples was 0.99. Both of these mean ratio values and the eleven individual ratio values for Zn-65 are excellent indicators that the routine measurement of Zn-65 in environmental media is very accurate.

These results demonstrate that there is no systematic error or bias for the analysis ofZn-65 in soil or other environmental sample media. No corrective action was implemented as a result of this non-conformity.

55

Rgure 6.1ATrend of Bind Spiked Water Samples 1.550 1.440~

1.330 30 1 0v 0 1.2 0

10 1.1001 1.0 11111

t r A - 2 i 0 - -

0 0.9go on LU A

0O, 0.70 0.60 A

0.50 beta tritium Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 IF-59 Zn-65 Co-6I CO-58 1-131

- ULL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 o OC-1 1.02 1.01 1.03 0.93 0.91 0.93 1.09 1.07 1.08 1.01 0.98 0.94 A

F 0-2 0.94 1.02 1.06 0.63 0.83 1.01 1.09 1.15 1.11 1.00 1.05

Or-3 0.90 0.88 0.96 0.99 0.96 0.97 0.97 1.07 1.02 1.03 1.02 0.93 LCL 0.75 0.75 0.75 015 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 Figure 6.lBTrend of Blind Spiked Milk Samples 1.50 0 1.30 0

9 1.10 0

0.90 I a a i I1 'A'A E

- ap -w 0.70 0.50 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 Co-60 Co-58 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 1.01 0.79 0.83 0.97 1.04 1.01 1.07 0.96 1.05 1.04

Q0-2 1.00 0.80 0.92 1.03 1.04 1.11 1.00 1.05 1.00 0.93

OC-3 0.95 0.95 0.95 0.96 1.03 1.05 1.03 0.99 1.02 0.91

QC.4 0.96 0.93 0.91 0.94 0.97 1.05 1.07 0.95 1.07 0.85

- LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 56

-fl Figure 6.lCTrend of Blind Spiked Fiter Samples 1.50 1.40 1.30 0 1.20 1.10 0

1.00 -K ix - )-A T 0.90 M_ z_ ;________

E 0 X-X Aa 0.80 AX 0.70 0.60 0.50 beta Ce-141 Cr-5I Cs-I34 Cs-137 Mn.54 Fe-59 Zn-65 Co-58 Co-60 1-131

UCL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33

0C-1 0.98 0.90 0.95 0.91 0.87 1.06 1.00 1.10 0.99 0.97 1.02 A QC-2 1.02 0.88 0.71 0.81 0.82 0.94 0.97 1.01 0.86 1.05 0.94

QC-3 1.12 0.98 0.99 0.88 0.96 1.05 1.14 1.16 1.00 1.02 0.99

0C-4 1.02 0.97 0.80 0.91 0.96 1.03 1.00 1.04 0.95 0.96 1.03

QC-5 0.90 0.92 0.90 0.88 0.89 1.03 1.07 0.96 0.90 0.93

0C-6 0.85 0.96 1.03 0.94

QC-7 1.03 0.97 1.04 0.95

-LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 57

Figure 6.lDTrend of Blind Spiked SoilNegetation Sam pies 1.50 1.40 1.30 0 1.20 1.10 A A 1.00o A S0.90 o 0.80 0.70.

0.60 0.50 Ce-141 Cr-5I C Cs-134 C Cs-137 M Mn-54 -

Fe-59 I Zn-65 ICO-CO

- 60

_UCL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 M 0C-1 1.09 1.38 0.96 0.94 1.19 0.96 0.73 1.06 0.97 A C0-2 1.07 0.85 1.01 1.03 1.08 1.16 0.94 1.09 1.08 LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 C0o7 58

Figure 6.2A Trend of QC Blind Spiked TLDs 0.25 0.20 0.10 0..10 0.05 Alp 0.00

_m nirern remi UCL 0.20 0.20 0.20 0.20

Qc-1 0.04

QC-2 0.03

QC-3 0.05

QC-4 0.07 6.2 INTRALABORATORY BLIND SAMPLE COMPARISON A Laboratory's use of in-house quality control blind samples provides a means for verifying measurement accuracy of analyzing environmental sample media. Ginma Station maintains a procedure for blind spiked environmental TLDs. A set of environmental TLDs are irradiated to a known dose by the Dosimetry Supervisor to create the spiked blind TLDs which are processed with field environmental TLDs. The reported dose and delivered dose are used to calculate a performance quotient ((reported - delivered)/delivered) for each TLD within the set of blind TLDs. The performance bias is the average of the blind TLDs performance quotients. The standard deviation of bias is the standard deviation of the blind TLDs performance quotients.

For the set of blind 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. Blind TLDs with performance criteria of less than 0.20 validate the TLD processing at Ginna Station.

All blind TLD performance criteria for year 2001 were less than 0.20. Figure 6.2A displays the blind TLD performance criteria.

59

6.3 AUDIT OF CONTRACT LABORATORY Ginna Station Quality Assurance personnel conducted a surveillance at JAFEL in the following six areas: Control of M&TE, Control of Records/Documents, Control/Adequacy of Sampling and Analysis, Handling, Shipping and Storage of Samples, Qualification/Training of Personnel, and Quality Programs Controls. Surveillance Report SQUA-2001-0002-AZP indicates the laboratory has functioned in an acceptable manner and was rated satisfactory with respect to all six criteria.

60

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

1. Environmental Air Sample Station (ES) # 4 found off 1/8/01. Reset breaker.

Sample period was 65.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

2. ES #5 found off 1/8/01. Reset breaker. Sample period was 64.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

3. ES #6 found 4/17/01 with breaker tripped. Sample period was 70.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

4. ES #2 found off 6/4/01. Reset breaker. Sample period was 69.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

5. ES #4 found off. Reset breaker. Sample period was 25.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

6. ES #2 found off. Reset breaker. Sample period was 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months .

7. Circ out autosampler found in standby 12/3/01. No sample collected 11/26/01 12/3/01.

8. Russell Station September liquid composite (control) did not meet required LLD for 1-131, due to late receipt of sample.

9. On 3/2/01, TLD #6 was noted to be missing. It was replaced with a spare TLD that had been stored in the security guardhouse between TLD location #6 and the reactor plant.

In addition to these deviations, four environmental air sampler flow meters failed as found criteria at annual preventive maintenance. Although the failures appeared to have occurred during the test procedures, average air radioactivity and conclusions derived from air radioactivity applied the as found flow rate to the entire sample periods. See section 3.2 61

2001 Annual Effluent Operating Report R.E. Ginna Nuclear Plant Rochester Gas and Electric Docket No. 50-244

2001 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244

TABLE OF CONTENTS 1.0 Introduction 2.0 Supplemental Information 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Release Rate Limits 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0 Summary of Gaseous Radioactive Effluents 4.0 Summary of Liquid Radioactive Effluents 5.0 Solid Waste 6.0 Lower Limit of Detection 7.0 Radiological Impact 8.0 Meteorological Data 9.0 Land Use Census Changes 10.0 Changes to the Offsite Dose Calculation Manual 11.0 Changes to the Process Control Program 12.0 Major Changes to Radwaste Treatment Systems 13.0 Inoperable Monitors 14.0 Changes to Previous Annual Effluent Operating Reports

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases Table 2A Liquid Effluents - Summation of all Releases Table 1 B Gaseous Effluents - Continuous and Batch Releases Table 2B Liquid Effluents - Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments Table 4A Radiation Dose to Nearest Individual Receptor from Gaseous Releases Table 4B Radiation Dose to Nearest Individual Receptor from Liquid Releases Table 5 52 Week Totals for Noble Gases and 1-131

1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is for the Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant and is submitted in accordance with the requirements of Technical Specification Section 5.6.3. The report covers the period from January 1, 2001 through December 31, 2001.

This report includes a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R. E. Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM).

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM limits applicable to the release of radioactive material in liquid and gaseous effluents are:

2.1.1 Fission and Activation Gases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate which would yield < 500 mrem/yr to the total body and < 3000 mrem/yr to the skin if allowed to continue for a full year.

The air dose, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to the following:

(I) During any calendar quarter to < 5 mrad for gamma radiation and to

< 10 mrad for beta radiation.

(ii) During any calendar year to < 10 mrad for gamma radiation and to

< 20 mrad for beta radiation.

2.1.2 Radioiodine, Tritium and Particulates The instantaneous dose rate, as calculated in the ODCM, due to radioactive materials released in gaseous effluents from the site as radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days shall be limited to a release rate which would yield

< 1500 mrem/yr to any organ if allowed to continue for a full year.

1

The dose to an individual, as calculated in the ODCM, from radioiodine, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:

(i) During any calendar quarter to < 7.5 mrem to any organ.

(ii) During any calendar year to < 15 mrem to any organ.

2.1.3 Liquid Effluents The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20. For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2 E-4 /Ci/ml.

The dose or dose commitment to an individual as calculated in the ODCM from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

(i) During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and (ii) During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

2.2 Maximum Permissible Concentrations (MPC) 2.2.1 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary.

2.2.2 For liquid effluents, ten times the effluent concentration values specified in 10CFR20, Appendix B, Table II, column 2, are used to calculate release rates and permissible concentrations at the unrestricted area boundary as permitted by Technical Specification 5.5.4.b. A value of 2E-04 uCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.

2.3 Release Rate Limits Based on Averaqe Nuclide Energy The release rate limits for fission and activation gases from the R. E. Ginna Nuclear Station are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable. However, the 2001 average beta/gamma energy of the radionuclide mixture in fission and activation gases released from Ginna Station is available for review upon request.

2

2.4 Measurements and Approximations of Total Radioactivity Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concentration of gaseous and liquid effluents.

Composite samples were analyzed for Sr-89, Sr-90 and Fe-55 by a contract lab oratory. Tritium and alpha analysis were performed using liquid scintillation and gas flow proportional counting respectively.

The total radioactivity in effluent releases was determined from the measured concentration of each radionuclide present and the total volume of effluents released.

2.5 Batch Releases 2.5.1 Liquid

1. Number of batch releases: 1.56 E+02

2. Total time period for batch releases: 5.13 E+04 min

3. Maximum time period for a batch release: 6.38 E+03 min

4. Average time period for batch releases: 3.29 E+02 min

5. Minimum time period for a batch release: 1.30 E+01 min

6. Average blowdown (LPM) during periods of effluent release into the discharge canal. None 2.5.2 Gaseous

1. Number of batch releases: 3.9 E+01

2. Total time period for batch releases: 9.53 E+04 min

3. Maximum time period for a batch release: 2.47 E+02 min

4. Average time period for batch releases: 1.48 E+02 min

5. Minimum time period for a batch release: 5.00 E+01 min 2.6 Abnormal Releases There were no abnormal or unplanned releases in 2001.

3

3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and lB. Plant vent and Containment Vent releases are modeled as mixed mode and Air Ejector is modeled as ground level release.

4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.

5.0 SOLID WASTE The quantities of radioactive material released in shipments of solid waste transported from the site during the reporting period are summarized in table 3.

Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type. The majority of Dry Active Waste is processed utilizing an off-site processor who reduces the volume and then sends the waste for burial.

6.0 LOWER LIMIT OF DETECTION Required Lower Limit of Detection, (LLD), as defined in the ODCM, was not met on the following five occasions of liquid batch releases in 2001.

"A" Monitor Tank release #2001012, 1/22/01.

Degradation of the liquid waste treatment demineralizer resin led to higher activity in the counted sample. Cs-137, Fe-59, and Zn-65 did not meet LLD's.

"A" monitor Tank release #2001016, 1/29/01.

Interference from Ag-i 1Om resulted in elevated LLD for Cs-1 37.

"A" Monitor Tank release #2001023, 2/14/01.

Interference from Ag-i 1Om resulted in elevated LLD for Cs-1 37.

"A: Monitor Tank release #2001053, 5/7/01.

Interference from Ag-i 1Om resulted in elevated LLD for Cs-1 37.

"A" Monitor Tank release #2001066, 6/15/01.

Interference from Ag-11 Om resulted in elevated LLD for Cs-1 37.

4

7.0 RADIOLOGICAL IMPACT An assessment of doses to the maximally exposed individual from gaseous and liquid effluents was performed for locations representing the maximum calculated dose in occupied sectors. Meteorological sectors from WNW through ENE are entirely over Lake Ontario. In all cases, doses were well below Technical Specification limits as defined in the ODCM. Doses were assessed based upon actual meteorological conditions considering the noble gas exposure, inhalation, ground plane and ingestion pathways. The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cow's milk and meat pathways. The results of this assessment are presented in Tables 4A and 4B.

Since the events of September 11, 2001, Ginna Station Security has been augmented by full-time presence of the New York State Police and the New York National Guard. These personnel have posts within the site boundary. For this reason, the noble gas exposure and uptake pathways for 2001 are calculated using maximum meteorological dispersion and deposition parameters on-site rather than off-site. This change from the site boundary meteorological conditions results in slightly higher calculated doses to the maximally exposed individual member of the public than in 2000, despite better overall fuel performance.

7.1 Total Dose 40CFR190 limits the total dose to members of the public due to radiation and radioactivity from uranium fuel cycle sources to:

<25 mrem total body or any organ and;

<75 mrem thyroid for a calendar year.

Using the maximum gaseous effluent and liquid effluent exposure and uptake pathways, and the direct radiation measurements onsite in the vicinity of the National Guard outpost, yield the following dose summaries to the "hypothetical maximally exposed individual member of the public".

4.8 mrem total body (4.8 mrem direct radiation plus 1.4E-2 mrem all other pathways) 2.32E-2 mrem thyroid (maximum organ dose).

These doses effectively bound the maximum site boundary doses to a real member of the public.

8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2001 is not included with this report, but can be made available at the R. E. Ginna Nuclear Station.

5

9.0 LAND USE CENSUS CHANGES There were no changes in critical receptor location for dose calculations during the reporting period. There were no large changes in land use within 5 miles of the plant.

Additional new homes were built at a rate similar to past years.

10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The ODCM was rewritten to the guidance of NUREG-1301 and moved from an administrative procedure into Technical Specifications Supporting Documentation, effective January 22, 2001. See attached ODCM, Revision 15.

The ODCM was revised July 19, 2001, to correct transcriptional errors, clarify instructions, and include explanatory notes. No major changes were made to requirements or to methodology used in calculation of offsite dose. See attached ODCM, Revision 16.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the reporting period.

12.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.

13.0 INOPERABLE MONITORS

"* RM-15A, Air Ejector Accident Range Gas Monitor, inoperable from 1/23/01 through 2/19/01. Cause of inoperability was electronic failures in channels 6 and

9. Corrected by repair and calibration to affected channels.

"* RM-14A, Plant Vent Accident Range Gas Monitor, inoperable from 3/19/01 through 4/19/01. A Special Report was sent to the Commission on 5/2/01 describing the cause of the inoperability for greater than 30 days.

"* R-31, "A" Main Steam Line Monitor, inoperable from 3/21/01 through 3/29/01 for PPCS software testing and troubleshooting.

"* R-32, "B" Main Steam Line Monitor, inoperable from 3/21/01 through 3/29/01 for PPCS software testing and troubleshooting.

"* RM-15A, Air Ejector Accident Range Gas Monitor, inoperable from 3/21/01 through 3/29/01 for PPCS software testing and troubleshooting.

"* R-1 8, Liquid Waste Disposal Monitor, inoperable from 5/7/01 through 6/15/01 due to flow meter failure. Repair delayed due to back-ordered parts. There were no releases via this pathway during this period of inoperability.

6

"* RM-15A, Air Ejector Accident Range Monitor inoperable from 7/9/01 through 7/17/01 due to primary-to-secondary leakage monitoring modification (Plant Change Request 99-008), including flow gauge replacement.

"* RM-14A, Plant Vent Accident Range Gas Monitor, inoperable from 10/8/01 through 10/16/01 for calibration and repair.

14.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS The following are corrections to discrepancies in the Ginna Station 2000 Annual Effluent Operating Report.

RM-1 5A was listed as inoperable on five occasions in 2000, although only four date periods were listed. The fifth period of inoperability for RM-1 5A was 4/17/00 through 5/15/00.

R-31, "A" Main Steam Line Monitor was inoperable from 1/24/00 through 2/2/00.

R-32, "B" Main Steam Line Monitor was inoperable from 3/24/00 through 3/31/00.

52 Week Running Totals for 2000 table had incorrect 1-131 data for the 1999 column. See corrected table following the 52 Week Running Totals for 2001.

7

ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES January - June 2001 Unit Quarter Quarter Est. Total A. Fission & activation gases 1st 2nd Error, %

1. Total release Ci 9.91 E+00 7.82E+00 1.50E+01

2. Average release rate for period uCi/sec 1.27E+00 9.95E-01

3. Percent of technical specification limit % 2.02E-04 1.58E-04 B. Iodines

1. Total iodine-131 Ci 1.21 E-05 1.22E-05 1.50E+01

2. Average release rate for period uCi/sec 1.54E-06 1.55E-06

3. Percent of technical specification limit % 3.38E-03 3.41 E-03 C. Particulates

1. Particulates with half-lives > 8days Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit %

4. Gross alpha radioactivity Ci D. Tritium

1. Total release Ci 5.89E+00 7.60E+00 9.20E+00

,2. Average release rate for period uCi/sec 7.49E-01 9.67E-01

13. Percent of technical specification limit % 8.81 E-05 1.14E-04 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2001 Unit Quarter Quarter Est. Total A. Fission & activation gases 3rd 4th Error, %

1. Total release Ci 8.76E+00 8.48E+00 1.50E+01

2. Average release rate for period uCi/sec 1 .10E+00 1.07E+00

3. Percent of technical specification limit % 1.75E-04 1.69E-04 B. lodines

1. Total iodine-131 Ci 1.24E-05 1.24E-05 1.50E+01

2. Average release rate for period uCi/sec 1.56E-06 1.56E-06

3. Percent of technical specification limit % 3.43E-03 3.43E-03 C. Particulates

1. Particulates with half-lives > 8days Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit %

4. Gross alpha radioactivity Ci D. Tritium

1. Total release Ci 1.20E+01 6.92E+00 9.20E+01

2. Average release rate for period uCi/sec 1.51 E+00 8.71 E-01

3. Percent of technical specification limit % 1.78E-04 1.02E-04 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES Continuous Mode Batch Mode Nuclides released Unit Quarter I Quarter Quarter Quarter 1st 2nd 1st 2nd

1. Fission gases argon-41 Ci 3.62E-02 5.07E-02 krypton-85 Ci 6.72E-01 4.34E-02 krypton-85m Ci 5.82E-05 2.03E-04 krypton-87 Ci krypton-88 Ci xenon-131m Ci 4.94E-03 2.91E-03 xenon-133 Ci 5.47E+00 4.45E+00 1.18E+00 1.03E+O0 xenon-133m Ci 1.07E-02 8.14E-03 xenon-135 Ci 2.52E+00 2.22E+00 1.64E-02 1.68E-02 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci Ci Ci Total for period Ci 7.99E+00 6.67E+00 1.92E+00 1.15E+00

2. lodines iodine-131 Ci 1.21 E-05 1.22E-05 iodine-133 Ci 1.33E-05 1.37E-05 iodine-135 Ci Total for period Ci 2.54E-05 2.59E-05

3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci Nb-95 Ci cobalt-58 Ci cobalt-60 Ci Total for period Ci unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter j Quarter Quarter 3rd 4th 3rd 4th

1. Fission gases argon-41 Ci 4.83E-02 5.03E-02 krypton-85 Ci 3.48E-02 krypton-85m Ci 3.64E-04 5.16E-04 krypton-87 Ci krypton-88 Ci xenon-131m Ci 5.11E-03 4.51E-03 xenon-133 Ci 4.50E+00 4.50E+00 1.87E+00 1.63E+00 xenon-133m Ci 1.97E-02 1.61E-02 xenon-135 Ci 2.25E+00 2.25E+00 3.42E-02 3.1OE-02 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci Ci Ci Total for period Ci 6.75E+00 6.75E+00 2.01 E+00 1.73E+00

2. lodines iodine-131 Ci 1.24E-05 1.24E-05 iodine-133 Ci 1.41E-05 1.41E-05 iodine-135 Ci Total for period Ci 2.65E-05 2.65E-05

3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci Nb-95 Ci cobalt-58 Ci cobalt-60 Ci Total for period Ci unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January - June 2001 Unit Quarter Quarter Est.Total A. Fission and activation products 1st 2nd Error, %

1. Total release (not including tritium, gases, alpha) Ci 6.61 E-04 2.40E-04 9.90E+00

2. Average diluted concentration during period uCi/ml 5.69E-12 1.45E-12

3. Percent of applicable limit % 5.57E-07 1.42E-07 B. Tritium

1. Total release Ci 2.33E+01 2.22E+01 9.20E+00

2. Average diluted concentration during period uCi/ml 2.01 E-07 4.23E-07

3. Percent of applicable limit % 6.70E-03 1.41 E-02 C. Dissolved and entrained gases

1. Total release Ci 9.90E+00

2. Average diluted concentration during period uCi/mr

3. Percent of applicable limit %

D. Gross alpha radioactivity

1. Total release Ci N/A N/A E. Vol. of waste released (prior to dilution) Liters 2.82E+07 3.02E+07 F. Vol. of dilution water used during period Liters 1.16E+11 1.65E+1 1 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2001 Unit Quarter Quarter Est.Total A. Fission and activation products 3rd 4th Error, %

1. Total release (not including tritium, gases, alpha) Ci 2.12E-05 5.OOE-05 9.90E+00

2. Average diluted concentration during period uCi/ml 1.24E-13 2.97E-13

3. Percent of applicable limit % 1.71 E-07 4.09E-07 B. Tritium

1. Total release Ci 8.56E+01 7.07E+01 9.20E+00

2. Average diluted concentration during period uCi/ml 5.01 E-07 4.20E-07

3. Percent of applicable limit % 1.67E-02 1.40E-02 C. Dissolved and entrained gases

1. Total release Ci 6.97E-05 9.20E+00

2. Average diluted concentration during period uCi/ml 5.01E-07

3. Percent of applicable limit % 2.51 E-01 D. Gross alpha radioactivity

1. Total release Ci N/A N/A E. Vol. of waste released (prior to dilution) Liters 3.14E+07 3.09E+07 F. Vol. of dilution water used during period Liters 1.71 E+1 1 1.68E+11 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd chromium-51 Ci manganese-54 Ci iron-55 Ci 2.58E-04 iron-59 Ci cobalt-58 Ci 1.22E-04 4.86E-05 cobalt-60 Ci 6.42E-05 6.14E-05 zinc-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci 1.83E-05 4.20E-06 molybdenum-99 Ci silver-110m Ci 1.98E-04 1.25E-04 antimony-122 Ci antimony-124 Ci antimony-125 Ci iodine-131 Ci iodine-133 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci 6.27E-07 barium/lanthanum-140 Ci cerium-141 Ci Te-123m Ci Ru-103 Ci Ci ITotal for period (above) Ci 6.61E-04 2.40E-04 unidentified Ci xenon-133 Ci xenon-135 Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th chromium-51 Ci manganese-54 Ci iron-55 Ci iron-59 Ci cobalt-58 Ci cobalt-60 Ci zinc-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci molybdenum-99 Ci silver-i 1Om Ci antimony-122 Ci antimony-124 Ci antimony-125 Ci 2.12E-05 5.OOE-05 iodine-131 Ci iodine-133 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci barium/lanthanum-140 Ci cerium-141 Ci Ru-106 Ci Ru-103 Ci Total for period (above) Ci 2.12E-05 5.OOE-05 unidentified Ci xenon-133 I Ci 6.97E-05 xenon-135 Ci Note: Isotope for which no value is given were not identified in applicable releases.

Table 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 2001 - December 31, 2001 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL - (Not irradiated fuel)

1. Type of waste Unit 12 month period Est. total Error %

a. Spent resins, filter sludges, m 17.41 7.0 E+00 evaporator bottoms, etc. Ci 327.29 1.4 E+01

b. Dry compressible waste, m3 15.7 7.0 E+00 contaminated equip, etc. Ci 11.3 1.4 E+01

c. Irradiated components, control m3 N/A N/A rods, etc. Ci N/A N/A

d. Other: m3 N/A N/A Ci N/A N/A 2.Estimate of major nuclide composition (by type of waste)

a. b. d.

Co-58 % 16.47 Co-58 % 17.02 %

Ni-63 % 29.35 Fe-55 % 37.35 %

Cs-134 % 11.91 Cr-51 % 3.46 %

Cs-1 37 % 18.93 Co-60 % 23.9 %

Co-60 % 10.52 Ni-63 % 11.18 %

Fe-55 % 9.39 Mn-54 % 1.83 %

Mn-54 % 1.34 Zr-95 % 1.29 %

Ce-144 % 0.73 Ce-144 % 1.02 %

% Nb-95 % 1.6 %

%X Sb-125 % 0.23 %

Total 98.64% Total 98.5% Total

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2 Sole use truck Oak Ridge, TN 2 Sole use truck Barnwell, SC 1 Sole use truck Irwin, TN 2 Sole use truck Kingston, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None

Table 4A Radiation Dose to Maximum Individual Receptor First Quarter 2001 (Units In rem)

All All Adult Teen Child Infant T. Body Skin THYRD THYRD THYRD THYRD N 1.82E-06 3.52E-06 NNE 2.38E-06 4.61E-06 NE 2.01E-06 3.91 E-06 ENE 1.48E-06 2.78E-06 E 1.35E-06 2.62E-06 1.41 E-06 1.36E-06 1.22E-06 7.20E-07 ESE 1.73E-06 3.35E-06 1.90E-06 2.09E-06 2.77E-06 3.67E-07 SE 2.85E-06 5.53E-06 2.86E-06 2.90E-06 2.58E-06 1.50E-06 SSE 3.54E-06 6.86E-06 3.60E-06 3.60E-06 3.20E-06 1.90E-06 S 3.34E-06 6.47E-06 3.93E-06 4.50E-06 6.97E-06 1.78E-06 SSW 3.13E-06 6.06E-06 3.14E-06 3.51E-06 5.43E-06 1.67E-06 SW 3.11E-06 6.02E-06 3.12E-06 3.16E-06 2.81E-06 1.66E-06 WSW 1.10E-06 2.12E-06 1.10E-06 1.10E-06 9.90E-07 5.80E-07 W 9.95E-07 1.93E-06 1.OOE-06 1.OOE-06 9.OOE-07 5.30E-07 WNW 1.82E-07 3.54E-06 NW 1.41 E-06 2.73E-06 NNW 1.48E-06 2.86E-06 MAX. 3.54E-06 6.86E-06 3.93E-06 4.50E-06 I 6.97E-06 I 1.90E-061 Note: Meteorological sectors without dose entries are entirely over Lake Ontario.

Table 4A Radiation Dose to Maximum Individual Receptor Second Quarter 2001 (Units In rem)

All All Adult Teen Child Infant T. Body Skin THYRD THYRD THYRD THYRD N 1.68E-06 2.88E-06 NNE 1.92E-06 3.29E-06 NE 1.90E-06 3.25E-06 ENE 1.57E-06 2.70E-06 E 2.OOE-06 3.42E-06 2.90E-06 2.94E-06 2.60E-06 1.50E-06 ESE 2.31E-06 3.96E-06 3.80E-06 4.16E-06 5.52E-06 7.25E-07 SE 2.41E-06 4.13E-06 3.50E-06 3.50E-06 3.14E-06 1.85E-06 SSE 2.92E-06 5.02E-06 4.25E-06 4.30E-06 3.82E-06 2.24E-06 S 2.56E-06 4.39E-06 3.72E-06 3.80E-06 3.34E-06 1.96E-06 SSW 2.64E-06 4.53E-06 3.84E-06 3.89E-06 3.45E-06 2.03E-06 SW 3.18E-06 5.46E-06 4.63E-06 4.68E-06 4.16E-06 2.44E-06 WSW 9.08E-07 1.56E-06 1.32E-06 1.34E-06 1.19E-06 6.97E-07 W 7.03E-07 1.21 E-06 1.02E-06 1.04E-06 9.19E-07 5.40E-07 WNW 1.29E-06 2.21E-06 NW 1.13E-06 1.94E-06 NNW 1.27E-06 2.18E-06 MAX. 3.18E-06 I 5.46E-06 4.63E-06 I 4.68E-06 5.52E-06 2.44E-06 Note: Meteorological sectors without dose entries are entirely over Lake Ontario.

Table 4A Radiation Dose to Maximum Individual Receptor Third Quarter 2001 (Units In rem)

All All Adult Teen Child Infant T. Body Skin THYRD THYRD THYRD THYRD N 1.13E-06 2.00E-06 NNE 1.90E-06 3.36E-06 NE 2.50E-06 4.43E-06 ENE 1.46E-06 2.59E-06 E 1.66E-06 2.94E-06 3.58E-06 3.62E-06 3.21E-06 1.87E-06 ESE 1.80E-06 3.19E-06 4.35E-06 4.77E-06 6.33E-06 8.19E-07 SE 2.38E-06 4.22E-06 5.14E-06 5.19E-06 4.60E-06 2.69E-06 SSE 2.15E-06 3.82E-06 4.65E-06 4.70E-06 4.16E-06 2.43E-06 S 1.56E-06 2.77E-06 3.37E-06 3.40E-06 3.01E-06 1.76E-06 SSW 1.75E-06 3.10E-06 3.77E-06 3.81E-06 3.38E-06 1.97E-06 SW 2.94E-06 5.22E-06 6.35E-06 6.42E-06 5.69E-06 3.32E-06 WSW 8.76E-07 1.55E-06 1.89E-06 1.91 E-06 1.69E-06 9.88E-07 W 6.02E-07 1.07E-06 1.30E-06 1.31 E-06 1.16E-06 6.79E-07 WNW 1.10E-06 i .95E-06 NW 9.20E-07 1.63E-06 NNW 1.01 E-06 1.80E-06 MAX. 2.94E-06 5.22E-06 6.35E-06 6.42E-06 6.33E-06 3.32E-06 Note: Meteorological sectors without dose entries are entirely over Lake Ontario.

Table 4A Radiation Dose to Maximum Individual Receptor Fourth Quarter 2001 (Units In rem)

All All Adult Teen Child Infant T. Body Skin THYRD THYRD THYRD THYRD N 2.06E-06 3.57E-06 NNE 3.04E-06 5.29E-06 NE 3.16E-06 5.50E-06 ENE 1.81E-06 3.14E-06 E 1.56E-06 2.71E-06 1.97E-06 2.OOE-06 1.78E-06 1.04E-06 ESE 2.01E-06 3.49E-06_ 2.81 E-06 3.08E-06 4.09E-06 5.39E-07 SE 2.70E-06 4.69E-06 3.42E-06 3.46E-06 3.07E-06 1.81 E-06 SSE 3.38E-06 5.88E-06 4.28E-06 4.34E-06 3.85E-06 2.27E-06 S 3.19E-06 5.54E-06 4.04E-06 4.09E-06 3.63E-06 2.14E-06 SSW 2.70E-06 4.69E-06 3.41E-06 3.46E-06 3.07E-06 1.81 E-06 SW 2.98E-06 5.18E-06 3.78E-06 3.82E-06 3.40E-06 2.OOE-06 WSW 8.51E-07 1.48E-06 1.08E-06 1.09E-06 9.70E-07 5.71E-07 W 8.21E-07 1.43E-06 1.04E-06 1.05E-06 9.35E-07 5.50E-07 WNW 1.91E-06 3.32E-06 NW 1.54E-06 2.67E-06 NNW 1.49E-06 2.59E-06 MAX. 3.38E-06 5.88E-06 4.28E-06 4.34E-06 4.09E-06 2.27E-06 Note: Meteorological sectors without dose entries are entirely over Lake Ontario.

Table 4B Radiation Dose To Maximum Individual Receptor From Liquid Release

" 2001 (Units in rem)

Adult Teen Child Infant First Quarter T. Body 1.90E-07 1.34E-07 2.56E-07 2.52E-07 Bone 3.33E-09 3.48E-09 4.55E-09 1.33E-10 Thyroid 1.90E-07 1.34E-07 2.56E-07 2.52E-07 Second Quarter T. Body 1.28E-07 9.OOE-08 1.73E-07 1.70E-07 Bone 3.18E-09 3.41E-09 4.28E-09 1.12E-11 Thyroid 1.28E-07 9.OOE-08 1.72E-07 1.70E-07 Third Quarter T. Body 4.84E-07 3.41 E-07 6.55E-07 6.40E-07 Bone <1.OE-1O <1.OE-1O <1.OE-1O <1.OE-1O Thyroid 4.84E-07 3.41 E-07 6.55E-07 6.40E-07 Fourth Quarter T. Body 4.06E-07 2.86E-07 5.50E-07 5.40E-07 Bone <1.OE-10 <1.OE-1O <1.OE-1I <1.OE-1O Thyroid 4.06E-07 2.86E-07 5.50E-07 5.40E-07

ROCHESTER GAS AND ELECTRIC

[52 ] WEEK RUNNING TOTALS FOR: 2001 MONTH NOBLE GAS NOBLE GAS [52 ] WEEK 1-131 1-131 [52] WEEK OF 2000 2001 NOBLE GAS 2000 2001 1-131 CURIES CURIES RUNNING uCi uCi RUNNING

______TOTAL Ci. TOTAL uCi LAST YEARS TOTAL 369.23 LAST YEARS TOTAL 308.33 JANUARY 9.62 2.95 301.65 4.50 4.17 368.89 FEBUARY 12.70 3.03 291.98 12.10 3.26 360.05 MARCH 21.60 3.95 274.33 22.80 4.17 341.42 APRIL 15.80 2.62 261.15 10.20 4.03 335.25 MAY 26.20 2.60 237.55 25.70 4.17 313.72 JUNE 23.40 2.61 216.76 14.20 4.03 303.55 JULY 66.90 3.04 152.90 8.15 4.17 299.57 AUGUST 24.30 3.05 131.65 19.50 4.17 284.24 SEPTEMBER 87.90 2.68 46.43 95.70 4.03 192.57 OCTOBER 13.80 2.76 35.39 144.00 4.20 52.77 NOVEMBER 2.54 2.92 35.77 6.44 4.06 50.39 DECEMBER 3.56 2.82 35.03 5.93 4.18 48.64 YEARLY 308.32 35.03 369.22[ 48.641 TOTALS CURIES CURIES uCi uCI I NOTE: The 52 week running total is not to exceed 25,000 curies for noble gases.

ROCHESTER GAS AND ELECTRIC

[52 ] WEEK RUNNING TOTALS FOR: 2000 MONTH NOBLE GAS NOBLE GAS [52] WEEK 1-131 1-131 [52 ] WEEK OF 1999 2000 NOBLE GAS 1999 2000 1-131 CURIES CURIES RUNNING uCi uCi RUNNING

_____TOTAL Ci. _ ____TOTAL uCi LAST YEARS TOTAL 122.31 TOTAL LAST YEARS TOTAL 186.51 ____ ____

JANUARY 2.12 9.62 129.80 3.81 4.50 187.19 FEBUARY 1.90 12.70 140.60 3.42 12.10 195.87 MARCH 2.45 21.60 159.75 9.15 22.80 209.52 APRIL 1.63 15.80 173.92 3.75 10.20 215.97 MAY 10.50 26.20 189.62 5.57 25.70 236.10 JUNE 30.00 23.40 183.02 48.50 14.20 201.80 JULY 12.40 66.90 237.52 24.60 8.15 185.35 AUGUST 9.36 24.30 252.46 14.30 19.50 190.55 SEPTEMBER 23.90 87.80 316.36 10.50 95.70 275.75 OCTOBER 12.80 13.80 317.36 16.60 144.00 403.15 NOVEMBER 2.54 2.54 317.36 32.30 6.44 377.29 DECEMBER 12.70 3.56 308.22 14.00 5.93 369.22 YEARLY 122.301 308.221 186.50 369.221 TOTALS CURIES CURIES uCi uCI NOTE: The 52 week running total is not to exceed 25,000 curies for noble gases.

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