Text

2002 Annual Effluent Operating Report
	ML031400490
Person / Time
Site:	Ginna
Issue date:	05/15/2003
From:	; Rochester Gas & Electric Corp
To:	; Office of Nuclear Reactor Regulation
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ML031400497	List: ML031400484; ML031400490; ML031400495;
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-R.E. Ginna Nuclear Plant Rochester Gas and Electric, -

Docket No. 50-244

o 31

.3 2002 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

'1 LIST OF TABLES -

Table 1A Gaseous Effluents - Summation of all Releases Table 2A Liquid Effluents - Summation of all Releases Table 1B 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

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, 2002 through December 31, 2002.

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 RegulatorV 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.

1

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.

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 ,uCi/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

2.2.2 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 iCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.

2.3 Release Rate Limits Based on Average Nuclide Enerqy. 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 2002 average beta/gamma energy of the radionuclide mixture in fission and activation gases released from Ginna Station is available for review upon request.

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: 1.87 E+02

2. Total time period for batch releases: 4.45 E+04 min

3. Maximum time period for a batch release: 3.87 E+03 min

4. Average time period for batch releases: . 2.38 E+02 min

5. Minimum time period for a batch release: 7.00 E+00 min

6. Average blowdown (LPM) during periods of effluent release I into the discharge canal. 320*

Continuous overboard blowdown from steam generators began 8/26102.

3

2.5.2 Gaseous

1. Number of batch releases: 3.1 E+01

2. Total time period for batch releases: 4.14 E+04 min

3. Maximum time period for a batch release: 3.04 E+04 min

4. Average time period for batch releases: 1.34 E+03 min

5. Minimum time period for a batch release: 6.00 E+01 min 2.6 Abnormal Releases The Containment equipment hatch was open between 3/19/02 and 4/11/02 for refueling outage activities. A non-routine batch release permit was generated in accordance with the requirements of section 2.5 of the ODCM, and the calculated conservative doses to the public were included in the applicable monthly release reports.

A small defect was detected in a section of the plant vent ductwork in September 2002. The defect was repaired in December 2002. Air samples were taken continuously during the period that the defect was open, and no radioactivity was detected. A conservative assessment of the potential air flow out of the defect represented an insignificant fraction of vent flow, and would have had a conservative effect on the calculated doses to the public from plant vent releases, so no adjustment to plant vent release calculations were made.

3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and 1B. 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.

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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 The a-posteriori Lower Limit of Detection (LLD), reported on gamma spectroscopy analysis as Minimum Detectable Activity (MDA), was not met on the following eight occasions of liquid batch releases in 2002. Actions have been taken to reduce depletion of the liquid waste processing resin. The a-priori LLD, as defined in the ODCM, was met for all liquid batch releases in 2002.

"A" Monitor Tank release #2002045, 3/15102.

Depletion 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 #2002078, 4/5/02.

Depletion 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 #2002079, 4/6102.

Depletion 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 #2002080, 4/7/02.

Depletion of the liquid waste treatment demineralizer resin led to higher activity in the counted sample. Cs-137, Fe-59, Cs-134, Ce-141, and Zn-65 did not meet LLD's.

"A" Monitor Tank release #2002084, 4/11/02.

Depletion of the liquid waste treatment demineralizer resin led to higher activity in the counted sample. Cs-137, Fe-59, Cs-134, Ce-141, and Zn-65 did not meet LLD's.

"A" Monitor Tank release #2002137, 7/18/02.

Depletion of the liquid waste treatment demineralizer resin led to higher activity in the counted sample. Cs-137, Fe-59, Cs-134, Ce-141, 1-131, and Zn-65 did not meet LLD's.

"A" Monitor Tank release #2002143, 7/31/02.

Depletion of the liquid waste treatment demineralizer resin led to higher activity in the counted sample. Cs-137, Fe-59, Cs-134, Ce-141, 1-131, and Zn-65 did not meet LLD's.

"A" Monitor Tank release #2002152, 8/14/02.

Interference from Ag-1 1Om led to Cs-1 37 LLD not being met.

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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 these personnel, the noble gas exposure and uptake pathways for 2002 are evaluated using maximum meteorological dispersion and deposition parameters on-site in order to assess dose to members of the public on-site.

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 at the site boundary, and the maximum direct radiation measurements at 600 meters SSE, the following are the dose summaries to the hypothetical maximally exposed individual member of the public.

7.9 mrem total body (7.9 mrem direct radiation plus 1.9E-2 mrem all other pathways).

1.24E-2 mrem thyroid (maximum organ dose).

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

Using the maximum gaseous effluent and liquid effluent exposure and uptake pathways on-site in the vicinity of the National Guard outpost, and the maximum direct radiation measurements nearest the outpost, the following are the dose summaries to the hypothetical maximally exposed member of the public on-site.

3.6 mrem total body (3.6 mrem direct radiation plus 1.9E-2 mrem all other pathways) 1.24E-2 mrem thyroid (maximum organ dose).

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8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2002 is not included with this report, but can be made available at the R. E. Ginna Nuclear Station.

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 revised January 24, 2002 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 17.

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-14A, Plant Vent Accident Range Radiation Monitor, was out of service from 3/17/02 through 4/16/02 for repair following a-failure of source check channels 3 and 6.

RM-14A, Plant Vent Accident Range Radiation Monitor, was out of service from 10/01/02 through 10/09/02 due to failure of channel 9.

RM-12A, Containment Vent Accident Range Radiation Monitor was out of service from 3/22/02 through 4/19/02 due to noise spikes on channel 2.

RI 0-B, Plant Vent Iodine Monitor, was out of service from 10/2/02 through 12/31/02 for modification of sarnple line.

R-13, Plant Vent Particulate Monitor, was out of service from 10/2/02 through 12/31/02 for modification of sample line.

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14.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS None.

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ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES January - June :2002 Unit Quer Qu a rter Est. Total A. Fission & activation gases 1st 2nd Error, %

1. Total release Ci 1.12E+01 7.95E+00 1.50E+01

2. Average release rate for period uCi/sec 1.45E+00 1.01 E+00

3. Percent of technical specification limit % 2.30E-04 1.60E-04 B. lodines

1. Total iodine-131 Ci l 2.33E-05 3.04E-05 1.50E+01

2. Average release rate for period uCi/sec 2.99E-06 3.87E-06

3. Percent of technical specification limit % 6.57E-03 8.50E-03 C. Particulates

1. Particulates with half-lives > 8days Ci 1.67E-06 2.OOE+01

2. Average release rate for period uCi/sec 2.15E-07

3. Percent of technical specification limit _ 1.62E-05

4. Gross alpha radioactivity Ci D. Tritium

1. Total release Ci 1.11E+01 1.25E+01 9.20E+O0

2. Average release rate for period uCi/sec 1.41E+00 1.59E+0O

3. Percent of technical specification limit 1.66E-04 1.87E-04 _ _

Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2002 Unit Quarter Quarter Est. Total A. Fission & activation gases 3rd 4th Error, %

1. Total release Ci 7.59E+00 5.14E+00 1.50E+01

2. Average release rate for period uCi/sec 9.55E-01 6.47E-01

3. Percent of technical specification limit 1.52E-04 1.03E-04 B. lodines

1. Total iodine-131 Ci 1.30E-05 8.62E-06 1.50E+01

2. Average release rate for period uCi/sec 1.64E-06 1.08E-06

3. Percent of technical specification limit % 3.59E-03 2.38E-03 C. Particulates

1. Particulates with half-lives > 8days Ci 2.OOE+01

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 l 2.37E+01 6.47E+00 9.20E+00

2. Average release rate for period uCi/sec 2.98E+00 8.14E-01

3. Percent of technical specification limit % 3.51 E-04 9.58E-05 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 I Unit Quarter l Quarter Quarter Quarter 1st 2nd 1st 2nd

1. Fission gases argon-41 Ci 1.83E-01 3.18E-02 krypton-85 Ci krypton-85m Ci 2.20E-03 krypton-87 Ci krypton-88 Ci xenon-131 m Ci 1.20E-02 xenon-133 Ci 7.29E+00 5.72E+00 1.61 E+00 1.76E-01 xenon-133m Ci 1.12E-02 2.69E-02 xenon-135 Ci 2.05E+00 2.01 E+00 6.55E-02 3.53E-03 xenon-135m Ci xenon-138 Ci others (specify) Ci ci ci ITotal for period Ci 9.35E+00 7.73E+00 1.90E+00 2.11E0

2. odines iodine-1 31 Ci 2.31 E-05 3.04E-05 1.96E-07 1.78E-08 iodine-132 Ci 1.86E-03 6.43E-07 2.75E-08 iodine-133 Ci 9.26E-06 1.26E-05 4.22E-08 Total for period Ci 1.89E-03 4.30E-05 8.81 E-07 4.53E-08

3. Particulates strontium-89 Ci 1.68E-06 strontium-90 Ci cesium-134 Ci cesium-1 37 Ci.

niobium-95 Ci cobalt-58 Ci cobalt-60 -Ci Total for period Ci 1.68E-06 unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES Continuous Mode Batch Mode Nuclides released l Unit Quarter Quarter Quarter Quarter 3rd rdhr4 j 4th

1. Fission gases argon-41 Ci 4.69E-02 2.99E-02 krypton-85 Ci krypton-85m Ci 1.45E-04 krypton-87 Ci . -

krypton-88 Ci xenon-131m Ci 8.77E-04 xenon-133 Ci 4.73E+00 3.14E+00 4.37E-01 3.97E-01 xenon-133m Ci 11.37E-03 2.99E-03 xenon-I 35 Ci 2.36E+00 1.57E+00 7.70E-03 9.22E-03 xenon-I 35m Ci l xenon-1 38 Ci others (specify) Ci

~~~~~~~~~ci Total for period Ci 7.09E+00 4.71 E+00 4.94E-O1 4.39E-01

2. lodines iodine-131 Ci i.30E-05 8.62E-06 iodine-133 Ci 1.48E-05 9.80E-06 iodine-1 35 Ci Total for period Ci 2.78E-05 1.84E-05

3. Particulates strontium-89 Ci

strontium-90 Ci cesium-134 Ci cesium-1 37 Ci .

niobium-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 2002 Unit Quarter Quarter Est.Total A. Fission and activation products 1st 2nd Error, %

1. Total release (not including tritium, gases, alpha) Ci 7.02E-04 2.40E-04 9.90E+00

2. Average diluted concentration during period uCi/mi 5.74E-12 1.45E-12

3. Percent of applicable limit 3.30E-05 9.72E-05 B. Tritium

1. Total release Ci 1.43E+02 3.10E+01 9.20E+00

2. Average diluted concentration I during period uCi/ml 1.17E-06 2.24E-07

3. Percent of applicable limit 5.85E+00 1.12E+00 C. Dissolved and entrained gases

1. Total release Ci 2.89E-03 1.82E-04 9.90E+00

2. Average diluted concentration during period uCi/mI 2.37E-11 1.32E-12

3. Percent of applicable limit % 1.19E-05 6.60E-07 D. Gross alpha radioactivity

1. Total release Ci E. Vol. of waste released nprior to dilution) Liters 3.20E+07 2.87E+07 F. Vol. of dilution water used durn eriod Liters 1.22 E+1 1 1.38 E+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 2002 Unit Quarter Quarter Est.Total A. Fission and activation products 3rd 4th Error, %

1. Total release (not including tritium, gases, alpha) Ci 1.17E-02 7.34E-06 9.90E+00

2. Average diluted concentration during period uCi/ml 6.84E-11 4.64E-14

3. Percent of applicable limit % 7.28E-05 2.32E-08 B. Tritium

1. Total release Ci 2.11 E+O1 4.63E+01 9.20E+00

2. Average diluted concentration during period uCi/ml 1.24E-07 2.92E-07

3. Percent of applicable limit % 6.20E-01 1.46E+00 C. Dissolved and entrained gases

1. Total release Ci l _ T

2. Average diluted concentration during period uCi/mi

3. Percent of applicable limit _

D. Gross alpha radioactivity

1. Total release Ci 1.35E-05 2.OOE+01 E. Vol. of waste released (prior to dilution) Liters 5.52E+07 6.80E+07 F. Vol. of dilution water used during period Liters 1.71 E+1 I 1.58E+1 1 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 3.63E-04 manganese-54 Ci iron-55 Ci 3.61 E-04 2.30E-04 iron-59 Ci cobalt-58 Ci 1.01E-04 5.16E-03 cobalt-60 Ci 8.97E-05 5.21 E-04 zinc-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci 6.07E-07 1.66E-05 molybdenum-99 Ci silver-11Om Ci 2.51 E-05 8.08E-05 antimony-1 22 Ci antimony-1 24 Ci antimony-125 Ci 1.25E-04 iodine-131 Ci iodine-133 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci 3.22E-06 barium/lanthanum-140 Ci cerium-141 Ci Te-1 23m Ci Sn-113 Ci Co-57 Ci 1.39E-05 Total for period (above) l Ci 7.02E-04 l6.38E-03 M

unidentified Ci _

lxenon-133 l Ci l l l 2.67E-03 1.82E-04 l lxenon-135 I Ci I I I 2.18E-04 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 4.81 E-04 manganese-54 Ci 1.OOE-04 iron-55 Ci _ 1.50E-03 iron-59 Ci cobalt-58 Ci _ 5.15E-03 7.34E-06 cobalt-60 Ci 2.09E-03 zinc-65 Ci strontium-89 Ci strontium-90 Ci niobium-95 Ci 3.89E-04 molybdenum-99 Ci silver-11Om Ci 1.38E-03 antimony-122 Ci antimony-1 24 Ci antimony-125 Ci 1.93E-04 iodine-131 Ci iodine-133 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-1 37 Ci barium/lanthanum-140 Ci cerium-141 Ci Sn-113 Ci Zr-95 Ci 2.16E-04 Co-57 6.36E-05 Total for period (above) Ci 1.16E-02 7.34E-06 unidentified Ci Ixenon-133 l Ci i lxenon-135 Ci I 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, 2002 - December 31, 2002 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL - (Not irradiated fuel)

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

3

a. Spent resins, filter sludges, m 7.38 7.0 E+00 evaporator bottoms, etc. Ci 312 1.4 E+01

b. Dry compressible waste, m3 11.81 7.0 E+00 contaminated equip, etc. Ci 3.43 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 % 22.35 Co-58 % 18.7 l Ni-63 % 39 Fe-55 % 37.3 %

Cs-1 34 % 2.44 Cr-51 % 4.5 %

Cs-1 37 % 7.24 Co-60 % 16.9 %

Co-60 % 13.2 Ni-63 % 14.23 %

Fe-55 % 12.25 Mn-54 % 0.88 %

Mn-54 % 1.3 Zr-95 % 0.79 %

Ce-144 % 0.72 Ce-144 % 0.49 %

% Nb-95 % 0.95 %

% Cs-137 % 0.38 %

% H-3 % 1.71 %

Total 98.5 II Total l 96.8 I Total _ _ l

3. Solid Waste Disposition l 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 B. IRRADIATED FUEL SHIPMENTS (Disposition)

[ Number of Shipments Mode of Transportation Ji L Destination L *NoneI

I L I r_ L :_

___ __ Table_ 4A Radiation Dose to Maximum Individual Receptor From Gaseous Releases First Quarter 2002 (Units In rem)

_________.'Aill~h7 - ^Aii -4AAdut2l>3 f2'A:TenS.<* i'Child i.¢ Infant:;t T. Body Skin lTHYRD THYRD THYRD THYRD N 1.OE-06 1.38E-06 NNE 8.79E-07 1.11 E-06 ______ __

NE 8.OOE-07 1.08E-06 ____

ENE 9.58E-07 1.45E-06 _ _

E 1.07E-06 1.72E-07 1.51 E-06 1.53E-06 1.37E-06 8.19E-07 ESE 7.68E-07 9.89E-07 5.05E-07 5.13E-07 4.59E-07 2.73E-07 SE 1.08E-06 1.25E-06 3.80E-07 3.94E-07 3.52E-07 2.09E-07 SSE 1.30E-06 1.67E-06 7.51 E-07 7.63E-07 6.83E-07 4.06E-07 S 1.43E-06 1.81 E-06 8.79E-07 8.93E-07 7.99E-07 4.76E-07 SSW 1.21 E-06 1.39E-06 4.17E-07 4.23E-07 3.78E-07 2.24E-07 SW 1.21 E-06 1.41 E-06 4.63E-07 4.71 E-07 4.20E-07 2.50E-07 WSW 5.92E-07 8.12E-07 5.01 E-07 5.10E-07 4.56E-07 2.71 E-07 W 6.23E-07 9.13E-07 6.68E-07 6.80E-07 6.08E-07 3.63E-07 WNW 8.83E-07 1.19E-06 6.94E-07 7.06E-07 6.31 E-07 3.76E-07 NW 7.22E-07 1.08E-06 NNW 8.22E-07 1.15E-06 __. ___

MAX. 1.43E-06 1.81 E-06 1.51 E-06 1.53E-06 1.37E-06 8.19E-07 Note: Meteorological sectors without thyroid dose entries are entirely over Lake Ontario

I Table 4A __ __ ___

Radiation Dose to Maximum Individual Receptor From Gaseous Releases

______________ Second Quarter 2002 (Units In rem)-----,

__Ii.^.';______*: ' A/IFit HAdult'^ [ . t>Teen

':- I Chi id Infan T. Body Skin THYRD THYRD THYRD THYRD N 2.80E-07 4.19E-07 ___ __ ____

NNE 2.79E-07 4.29E-07 _ _ _

NE 4.38E-07 6.87E-07 ENE 4.12E-07 6.38E-07 _ , ____

E 3.60E-07 5.53E-07 6.92E-07 7.02E-07 6.24E-07 3.24E-07 ESE 3.38E-07 5.1 OE-07 6.25E-07 6.34E-07 5.63E-07 3.32E-07 SE 2.97E-07 3.60E-07 3.49E-07 3.54E-07 3.15E-07 1.85E-07 SSE 2.83E-07 3.77E-07 4.OOE-07 4.05E-07 3.60E-07 2.13E-07 S 2.75E-07 3.27E-07 2.92E-07 2.96E-07 2.63E-07 1.55E-07 SSW 2.52E-07 2.63E-07 1.79E-07 1.81 E-07 1.61 E-07 9.48E-08 SW 3.07E-07 3.01 E-07 1.71 E-07 1.73E-07 1.54E-07 9.04E-08 WSW 2.28E-07 3.56E-07 4.58E-07 4.64E-07 4.12E-07 2.43E-07 W 2.86E-07 4.89E-07 6.76E-07 6.85E-07 6.09E-07 3.59E-07 WNW 4.43E-07 7.59E-07 1.05E-06 1.06E-06 9.44E-07 5.57E-07 NW 4.28E-07 7.48E-07 NNW 4.33E-07 7.41 E-07 _

MAX. 4.43E-07 7.59E-07 11.05E-06 .06E-06 9.44E-07 5.57E-07 Note: Meteorological sectors without thyroid dose are entirely over Lake Ontario

____I_ L___ L _L_ ______

-__ ______________ Table 4A _-_ _ _ _ _

Radiation Dose to Maximum Individual Receptor From Gaseous Releases

_______ __ Third Quarter 2002 _____

_____ (Units In rem) __

Al(X9j AIl. 'fi- Ad Teen-. Hild, ; n itl.

T. Body Skin THYRD THYRD THYRD THYRD N 5.57E-07 9.03E-07 NNE 3.68E-07 5.24E-07 ________ _

NE 4.62E-07 6.25E-07 ENE 4.57E-07 6.93E-07 E 3.73E-07 5.08E-07 9.12E-07 9.21 E-07 8.14E-07 4.72E-07 ESE 3.53E-07 4.77E-07 8.40E-07 8.48E-07 7.99E-07 4.35E-07 SE 4.08E-07 5.84E-07 1.17E-06 1.18E-06 1.05E-06 6.08E-07 __

SSE 4.06E-07 5.80E-07 1.17E-06 1.18E-60 1.04E-06 6.04E-07 S 3.18E-07 4.46E-07 8.57E-07 8.65E-07 7.64E-07 4.44E-07 _

SSW 2.47E-07 3.05E-07 4.06E-07 4.1OE-07 3.62E-07 2.1OE-07 SW 4.OOE-07 5.30E-07 8.86E-07 8.95E-07 7.90E-07 4.59E-07 WSW 4.40E-07 7.24E-07 1.86E-06 1.88E-06 1.66E-06 9.64E-07 W 4.30E-07 7.05E-07 1.81 E-06 1.82E-06 1.61 E-06 9.36E-07 _ __ _

WNW 5.22E-07 8.59E-07 2.18E-06 2.20E-06 1.94E-06 1.13E-06 NW 7.25E-07 1.23E-06 _ _ ________

NNW 5.26E-07 8.72E-07 MAX. 7.25E-07 1.23E-06 2.18E-06 2.20E-06 1.94E-06 1.13E-06 Note:_Meteorological_sectors_without_thyroid_dose_are_enti __ ___ Ontario Note:_Meteorolog ical_sectors wit hout_thyroid_do se_are_entirely_over_Lake_Ontario _____ _____

I

__ 1 __ .1 __.____.__

Table 4A Radiation Dose to Maximum Individual Receptor From Gaseous Releases Fourth Quarter 2002 __

(Units In rem)

__ :AV! I____ ____ ~ Te Cid ~Ki~

____'KA~l T. Body Skin THYRD THYRD THYRD THYRD N 2.59E-07 3.87E-07 __ _ __ __ __

NNE 2.32E-07 3.36E-07 ____

NE 3.29E-07 5.06E-07 ENE 2.36E-07 3.48E-07 ___ _

E 2.28E-07 3.36E-07 2.46E-07 2.48E-07 2.20E-07 1.29E-07 ESE 2.95E-07 4.26E-07 2.86E-07 2.89E-07 2.56E-07 1.50E-07 SE 2.76E-07 3.78E-07 1.98E-07 2.OOE-07 1.77E-07 1.03E-07 SSE 2.92E-07 3.96E-07 1.96E-07 1.98E-07 1.75E-07 1.02E-07 S 2.84E-07 3.75E-07 1.53E-07 1.54E-07 1.37E-07 7.96E-08 SSW 3.13E-07 4.17E-07 1.84E-07 1.86E-07 1.65E-07 8.67E-08 SW 2.95E-07 3.90E-07 1.67E-07 1.68E-07 1.49E-07 8.67E-08 WSW 3.12E-07 5.08E-07 5.02E-07 5.08E-07 4.51 E-07 2.64E-07 W 2.88E-07 4.69E-07 4.62E-07 4.67E-07 4.14E-07 2.42E-07 WNW 2.74E-07 4.07E-07 3.07E-07 3.1OE-07 2.75E-07 1.61 E-07 NW 2.63E-07 4.20E-07 NNW 2.41 E-07 3.84E-07 MAX. 3.29E-07 5.08E-07 5.02E-07 5.08E-07 4.51 E-07 2.64E-07 Note: Meteorological sectors without thyroid dose entries are entirely over Lake Ontario

?7 I .

a V Page 4B Radiation Dose To Maximum Individual Receptor From Liquid Release 2002 (Units in rem)

TAdult lTeen Child Infant FirSt Quarter T. Body 1.24E-06 8.80E-07 1.66E-06 1.61 E-06 Bone 3.11 E-10 3.19E-10 5.50E-10 1.84E-10 Thyroid 1.24E-06 8.80E-07 1.66E-06 1.61 E-06 Second Quarter T. Body 2.27E-07 1.61E-07 3.02E-07l 2.92E-07 Bone 1.19E-09 1.26E-09 1.69E-09 1.51 E-10 Thyroid 2.27E-07 1.61 E-07 3.02E-07 2.92E-07 Third Quarter T. Body 1.26E-07 8.95E-08 1.68E-07 1.62E-07 Bone 1.02E-09 1.04E-09 1.74E-09 5.60E-1 0 Thyroid 1.26E-07 8.95E-08 1.68E-07 1.62E-07 Fourth Quarter T. Body 2.69E-07 1.90E-07 3.58E-07 3.48E-07 Bone <1.OE-10 <1.OE-10 <1.OE-10 <1.OE-10 Thyroid 2.69E-07 1.90E-07 3.58E-07 3.48E-07

IC'- - J;i 2002 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT R.E. Ginna Nuclear Plant 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 62

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 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-In 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 TABLESIFIGURES (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 6-1 C 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 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

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 2002 results were consistent with data for the past five years and exhibited no adverse trends.

The analytical results from the 2002 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 2002, 1185 samples were collected for analysis by gross beta counting and/or gamma spectroscopy. These included 932 air samples, 60 water samples, 18 fish samples, 5 sediment samples, 9 vegetation samples, 47 milk samples, and 156 thermoluminescent dosimeter measurements. During 2002 there were two deviations from the sampling schedule for air samples. The minimum number of samples required in ODCM Table 5-1 were collected for all pathways.

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

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

Table 1-1 -3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY SAMPLED TYPE AND TOTAL NUMBER OF INDICATOR LOCATIONS CONTROL LOCATION UNIT OF MEASUREMENT ANALYSES LLD MEAN () RANGE MEAN (1) RANGE NAME, DISTANCE MEAN (1) RANGE AND DIRECTION AIR: Particulate (pCI/Ms) Gross Beta 624 0.003 0.017 (468/468) Onsite Location #13 0.019 (52/52) 0.016 (156/156) 0.006-0.032 194 690M 0.011 - 0.030 0.007 - 0.034 (pCi/M3) Gamma Scan 48 (2) < LLD N/A N/A <LLD 3

Iodine (pCi/M ) Gamma Scan 260 0.006 - < LLD N/A N/A < LLD 0.057 DIRECT RADIATION: TLD Gamma 156 5.0 12.5 (120/120) Onsite Location #7 17.7 (4/4) 11.2 (36/36)

(mrem/quarter) 10.1 - 18.0 257 220M 17.4- 18.0 10.0- 13.4 WATER: Dnking Gross Beta 12 0.2 2.35 (12/12) OWD 2.35 N/A (pCi/Liter) 1.13 - 3.81 70 1200M 1.13 - 3.81 Gamma Scan 12 (2) Ra-226 89 (11/12) OWD Ra-226 89 (11/12) N/A 34 -130 70 1200M 34 - 130 Tritium 12 (2) <LLD N/A N/A N/A Iodine 12 0.58* < LLD N/A N/A N/A WATER: Surface Gross Beta 48 0.2 2.06 (12/12) Deer Creek 3.62 (12/12) 2.14 (12/12)

(pCi/Liter) 0.82 - 2.94 105 260M 1.51 - 5.75 0.76 - 3.09 Gamma Scan 48 (2) Ra-226 100 (10/12) Circ-out Ra-226 100 (10/12) Ra-226 95 (12/12) 60 - 120 15 130M 60-120 41 - 165 Tritium 48 (2) <LLD N/A N/A N/A.

Iodine 48 0.56* < LLD N/A N/A < LLD MILK: Iodine 58 0.46* < LLD N/A N/A < LLD (pCI/Liter)

Gamma Scan 58 (2) < LLD N/A N/A < LLD FISH: Gamma Scan 17 (2) Ra-226 487 (8/9) Indicator Fish Ra-226 487 (8/9) Ra-226 198 (4/4)

(pCI/Kg) 262 - 776 015 130M 262 - 776 122 - 391 VEGETATION: Gamma Scan 9 (2) Ra-226 355 (5/5) Indicator Vegetation Ra-226 355 (5/5) Ra-226 135 (3/4)

(pCi/Kg) 99.7 - 691 99.7 - 691 65 - 204 SEDIMENT: Gamma Scan 5 (2) Ra-226 703 (2/3) Indicator Sediment Ra-226 703 (2/3) Ra-226 975 (2/2)

(pCI/Kg) 682 - 724 682 - 724 950 - 1000

) Mean ana raige uaseu on uetecraDie measurements only. rrartion OT etectawle measurements at speciTiea ocations in parentneses.

(2) Table of LLD values attached for gamma scan and tritfum rr

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. 0

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

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

Following are the requirements from the ODCM:

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

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

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

3

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

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

Interlaboratorv Comparison ProQram 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.

4

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 lodine-131.

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

b. Particulate 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.)

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

ischarge)

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

Intake)

c. Shoreline 1 Control (Russell Station) emi-annnually Gamma Isotopic analysis of each sample Sediment I 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 .

5

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

4. INGESTION

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

indicator*

(June thru October) 1 control t least once per 31 days Gamma isotopic and 1-131 analysis of each sample.

I Indicator (November thru May)

b. Fish 4 control wice during fishing season including at amma isotopic analysis on edible portions of each sample.

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

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

c. Food Products indicator (On site) o of the following:

1. apples

2. cherries

3. Other crops grown on site by contract farmer 1 control t time of harvest. One sample of: Gamma isotopic analysis on edible portion of sample.

1 indicator 1. broad leaf vegetation*

(On site garden or nearest offsite 2. other vegetable garden within 5 miles in the highest D/Q meterological sector)

'leaves from 3 different plant species mposited See Land Use Census, page 50 6

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

Gross Beta 4(a) 1 x 10-2 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 15(b) 1-131 1 7 x 10- 1 60 Cs-134 15(1.0)(a), I x 10Z 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

.I i Table 2-2 Page2of2 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

I I I

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

2 1 87 320 #2 87 320

3 1 110 420 #3 110 420

4 1 140 250 #4 140 250

5 1 185 160 #5 185 160

6 1 232 225 #6 232 225

7 1 257 220 #7 257 220

8 C 258 19200 #8 258 19200

9 I 235 11400 #9 235 11400

10 C 185 13100 #10 185 13100

11 1 123 11500 #11 123 11500

12 C 93 25100 # 12 93 25100

13 1 194 690 # 13 292 230 Water Sample Locations Direction Distance # 14 292 770 Russell Station C 270 25600 # 15 272 850.

Ontario Water District I 70 2200 # 16 242 900 Circ Water Intake S 0 420 # 17 208 500 Circ Water Discharge I 15 130 #18 193 650 Deer Creek S 105 260 # 19 177 400

20 165 680

21 145 600

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

Map 2-1 Onsite Sample Locations Key Giinas Sttion Structures _

(10)

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

Onsite samples detailed on nap 2-1.

(1 1)

CO-e-

Map 2-3 Water Sample and Milk Farm Locations Location of water samples, milk farns and TLDs *.

Onsite samples and samples in close proximity to Ginna Station are detailed on maps 2-1 and 2-2.

(12) C03

3.0 DATA

SUMMARY

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

+/- 1 standard deviation.

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

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

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

13

3.2 Air Samples Radioactive particles in air are collected by drawing approximately one SCFM through a two inch diameter particulate filter. The volume of air sampled is measured by a dry gas meter and corrected for the pressure drop across the filter. The filters are changed weekly and allowed to decay for three days prior to counting to eliminate most of the natural radioactivity such as the short half-life decay pro,ducts 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 16 miles from the site that serve as control stations.

Based on weekly comparisons, there was no statistical difference between the Control and Indicator radioactive particulate concentrations. The averages for the control samples were 0.016 pCi/m 3, and the averages for the indicators were 0.018 pCi/m3 for the period of January to December, 2002. Maximum weekly concentrations for each station were less than 0.038 pCi/m 3 . These values include a worst-case evaluation of the two environmental air sample gas meters which failed as-found testing on 5/23/02 and 8/14/02. The failed as-found flows were 108% and 127%,

respectively, at Stations 3 and 13. 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 3-4 A to D, and indicate only the naturally occurring radioisotopes, Be-7 and K-40.

14

I 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 2002 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.

15

Rochester Gas aind Electric Table 3-IA On-Site Air Particulate Samplers Gross Beta Results n pCi(m3 Collection Station Station Station Station Station Station Station Date #2 () #3 () #4 () #5 () #6 () #7 () #13 A () Average 7-Jan 0.021 +/- 0.004 0.019 +/- 0.004 0.022 +/- 0.004 0.019 +/- 0.005 0.022 +/- 0.005 0.026 +/- 0.005 0.023 +/- 0.006 0.022 14-Jan 0.0 17 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.004 0.018 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.005 0.018 21-Jan 0.016 + 0.003 0.018 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.004 0.017 +/- 0.003 0.017 +/- 0.003 0.022 +/- 0.004 0.018 28-Jan 0.023. +/- 0.003 0.019 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.004 0.022 +/- 0.004 0.020 +/- 0.004 0.026 +/- 0.005 0.022 4-Feb 0.014 + 0.003 0.018 +/- 0.003 0.020 +/- 0.003 0.021 +/- 0.004 0.020 +/- 0.004 0.017 +/- 0.003 0.023 +/- 0.005 0.019 11-Feb 0.021 +/- 0.003 0.030 + 0.004 0.023 +/- 0.003 0.021 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.004 0.030 +/- 0.005 0.025 18-Feb 0.013 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.003 0.016 +/- 0.004 0.014 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.005 0.015 25-Feb 0.0 18 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.004 0.012 +/- 0.003 0.014 +/- 0.003 0.027 +/- 0.005 0.017 4-Mar 0.017 + 0.003 0.015 +/- 0.003 0.032 +/- 0.006 0.017 +/- 0.004 0.017 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.019 11-Mar 0.024 +/- 0.003 0.027 +/- 0.004 0.022 +/- 0.003 0.026 +/- 0.004 0.019 +/- 0.003 0.025 +/- 0.004 0.027 +/- 0.004 0.024 18-Mar 0.022 +/- 0.003 0.028 +/- 0.004 0.021 +/- 0.003 0.020 +/- 0.004 0.021 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.003 0.023 25-Mar 0.013 + 0.003 0.021 + 0.004 0.016 +/- 0.003 0.016 +/- 0.004 0.012 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.016 1-Apr 0.014 +/- 0.003 0.021 +/- 0.003 0.016+/- 0.003 0.015 +/- 0.003 0.018 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.003 0.018 8-Apr 0.015 +/-0.003 0.018 +/- 0.004 0.014 +/- 0.003 0.014 +/- 0.004 0.011 +/- 0.003 0.015 +/- 0.004 0.016 +/- 0.003 0.015 15-Apr 0.014 +/-0.003 0.016 +/- 0.003 0.016 +/- 0.003 0.017 +/- 0.004 0.013 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.015 22-Apr 0.019 +0.003 0.024 +/- 0.004 0.020 +/- 0.003 0.019 +/- 0.004 0.017 +/- 0.003 0.019 +/- 0.004 0.020 +/- 0.003 0.020 29-Apr 0.014 +/-0.003 0.020 +/- 0.004 0.015 +/- 0.003 0.013 +/- 0.004 0.017 +/- 0.003 0.015 +/- 0.003 0.018 +/- 0.003 0.016 6-May 0.011 +/-0.002 0.017 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.014 13-May 0.014 +0.003 0.016 +/- 0.003 0.014 +/- 0.003 0.0 15 +/- 0.004 0.017 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.003 0.016 21-May 0.008 +0.002 0.011 +/- 0.003 0.009 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.003 0.011 +/- 0.003 0.009 28-May 0.009 +/-0.002 0.012 +/- 0.003 0.010 +/- 0.002 0.012 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.003 0.013 +/- 0.003 0.0 11 3-Jun 0.014 +0.003 0.012 +/- 0.003 0.015 +/- 0.003 0.013 +/- 0.004 0.010 +/- 0.003 0.016 +/- 0.004 0.017 +/- 0.004 0.014 10O-Jun 0.011 +0.003 0.015 +/- 0.003 0.013 +/- 0.003 0.010 +/- 0.003 0.012 +/- 0.003 0.014 +/- 0.003 0.013 +/- 0.003 0.013 17-Jun 0.007 k0.002 0.011 + 0.003 0.010 +/- 0.003 0.0 11 +/- 0.003 0.007 +/- 0.003 0.010 +/- 0.003 0.013 +/- 0.004 0.010 24-Jun 0.025 +0.003 0.023 +/- 0.004 0.021 +/- 0.004 0.023i +/- 0.004 0.019 +/- 0.003 0.020 +/- 0.004 0.018 +/- 0.003 0.021 1-Jul 0.019 +0.003 0.021 +/- 0.004 0.019 0.003 0.018 +/- 0.004 0.015 +/- 0.003 0.019 +/- 0.004 0.017 +/- 0.003 0.018 Maximum 0.026 +/- 0.004 0.038 +/- 0.004 0.032 +/- 0.006 0.026 +/- 0.005 0.025 +/- 0.005 0.026 +/- 0.005 0.030 +/- 0.006 Average 0.017 0.024 0.017 0.016 0.016 0.017 0.019 Minimum 0.007 +/- 0.002 0.014 +/- 0.003 0.009 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.003 0.011 +/- 0.003 (a) Sample collected for <84 hours in sample period I= Indicator (15)

C = Control

Rochester Gas and Electric Table 3-1 B On-Site Air Particulate Samplers Gross Beta Results in pCilm3 Collection Station Station Station Station Station Station Station Date #2 (I) #3 () #4 () #5 () #6 (I) #7 () #13 A (I) Average 8-Jul 0.019 + 0.003 0.024 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.004 0.021 +/- 0.004 0.020 +/- 0.003 0.024 +/- 0.003 0.022 15-Jul 0.018 + 0.003 0.020 +/- 0.004 0.016 +/- 0.003 0.017 +/- 0.004 0.017 +/- 0.003 0.018 +/- 0.004 0.018 +/- 0.003 0.018 22-Jul 0.021 + 0.003 0.024 +/- 0.004 0.024 +/- 0.004 0.020 +/- 0.004 0.020 +/- 0.003 0.029 +/- 0.005 0.020 +/- 0.003 0.023 30-Jul 0.017 + 0.003 0.018 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.015 +/- 0.003 0.016 +/- 0.003 0.016 5-Aug 0.022 + 0.004 0.025 +/- 0.004 0.019 +/- 0.004 0.019 +/- 0.005 0.020 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.021 12-Aug 0.017 + 0.003 0.019 +/- 0.003 0.014 +/- 0.003 0.013 +/- 0.004 0.013 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.003 0.015 19-Aug 0.026 + 0.004 0.020 +/- 0.004 0.030 + 0.004 0.030 +/- 0.005 0.023 +/- 0.003 0.024 +/- 0.003 0.027 +/- 0.004 0.026 26-Aug 0.013 + 0.003 0.012 +/- 0.003 0.015 + 0.003 0.012 +/- 0.004 0.016 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.014 3-Sep 0.012 + 0.003 0.012 +/- 0.003 0.017 +/- 0.003 0.015 +/- 0.004 0.017 +/- 0.003 0.013 +/- 0.002 0.014 +/- 0.003 0.014 9-Sep 0.021 + 0.004 0.020 +/- 0.004 0.021 +/- 0.004 0.016 +/- 0.005 0.019 +/- 0.003 0.020 +/- 0.003 0.022 +/- 0.004 0.020 16-Sep 0.025 + 0.004 0.023 +/- 0.004 0.022 +/- 0.004 0.015 +/- 0.004 0.026 +/- 0.004 0.020 +/- 0.003 0.023 +/- 0.003 0.022 23-Sep 0.023 + 0.004 0.024 +/- 0.004 0.026 +/- 0.004 0.007 +/- 0.003 0.025 +/- 0.004 0.025 +/- 0.003 0.024 i 0.004 0.022 30-Sep 0.018 +/- 0.003 0.018 +/- 0.004 0.020 +/- 0.004 0.000 +/- 0.003(a) 0.022 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.003 0.019 7-Oct 0.022 +/- 0.004 0.022 +/- 0.004 0.026 +/- 0.004 0.017 +/- 0.005 0.024 +/- 0.004 0.019 +/- 0.003 0.021 +/- 0.003 0.022 14-Oct 0.011 + 0.003 0.010 +/- 0.003 0.013 +/- 0.003 0.013 +/- 0.004 0.016 +/- 0.003 0.009 +/- 0.002 0.012 +/- 0.003 0.012 21 -Oct 0.010 + 0.003 0.012 +/- 0.003 0.011 +/- 0.003 0.011 +/- 0.004 0.012 +/- 0.003 0.009 +/- 0.002 0.013 +/- 0.003 0.011 28-Oct 0.013 +/- 0.003 0.011 +/- 0.003 0.012 +/- 0.003 0.014 +/- 0.004 0.013 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.003 0.013 4-Nov 0.012 +/- 0.003 0.013 +/- 0.003 0.012 +/- 0.003 0.009 +/- 0.008 0.015 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.003 0.013 12-Nov 0.028 + 0.004 0.030 +/- 0.004 0.029 +/- 0.004 0.028 +/- 0.005 0.030 +/- 0.004 0.022 +/- 0.003 0.030 +/- 0.004 0.028 18-Nov 0.016 + 0.003 0.014' +/- 0.004 0.015 +/- 0.004 0.016 +/- 0.005 0.016 +/- 0.003 0.014 +/- 0.003 0.016 +/- 0.003 0.015 25-Nov 0.019 +/- 0.003 0.014 +/- 0.003 0.017 +/- 0.003 0.022 +/- 0.005 0.022 +/- 0.004 0.015 +/- 0.003 0.022 +/- 0.004 0.019 2-Dec 0.016 + 0.003 0.013 +/- 0.003 0.013 +/- 0.003 0.018 +/- 0.005 0.014 +/- 0.003 0.011 +/- 0.003 0.016 +/- 0.003 0.014 9-Dec 0.020 +/- 0.003 0.020 +/- 0.004 0.018 +/- 0.003 0.022 +/- 0.005 0.025 +/- 0.004 0.018 +/- 0.003 0.021 +/- 0.004 0.021 16-Dec 0.019 +/- 0.004 0.019 +/- 0.004 0.019 + 0.004 0.022 +/- 0.005 0.017 +/- 0.003 0.017 +/- 0.003 0.017 +/- 0.004 0.019 23-Dec 0.014 + 0.003 0.014 +/- 0.003 0.014 +/- 0.003 0.019 +/- 0.005 0.015 +/- 0.003 0.013 +/- 0.003 0.019 +/- 0.003 0.015 30-Dec 0.019 + 0.003 0.016 +/- 0.003 0.020 +/- 0.004 0.019 +/- 0.005 0.020 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.003 0.018 Maximum 0.028 +/- 0.004 0.030 +/- 0.004 0.030 +/- 0.004 0.030 +/- 0.008 0.030 +/- 0.004 0.029 +/- 0.005 0.030 +/- 0.004 Average 0.018 0.018 0.018 0.016 0.019 0.017 0.019 Minimum 0.010 +/- 0.003 0.010 0.003 0.011 +/- 0.003 0.000 +/- 0.003 0.012 +/- 0.003 0.009 +/- 0.002 0.012 +/- 0.003 (a) Sample collected for <84 hours in sample period (16)

I = Indicator C = Control

Rochester Gas and Electric Table 3-2A Off-Site Air Particulate Samplers Gross Beta Results In pCi/m3 Collection Station Station Station Station Station Date #8 (C) #9 () #10 (C) #11 (I) #12 (C) Average 7-Jan 0.023 +/- 0.004 0.021 +/- 0.005 0.016 +/- 0.006 0.018 +/- 0.004 0.019 +/- 0.004 0.019 14-Jan 0.015 +/- 0.003 0.018 +/- 0.004 0.019 +/- 0.005 0.020 +/- 0.003 0.015 +/- 0.003 0.017 21 -Jan 0.015 +/- 0.003 0.017 +/- 0.004 0.017 +/- 0.005 0.020 +/- 0.003 0.015 + 0.003 0.017 28-Jan 0.023 +/- 0.003 0.021 +/- 0.004 0.018 +/- 0.005 0.025 +/- 0.003 0.020 +/- 0.003 0.021 4-Feb 0.018 +/- 0.003 0.019 +/- 0.004 0.015 +/- 0.005 0.017 +/- 0.003 0.016 +/- 0.003 0.017 11-Feb 0.023 +/- 0.003 0.024 +/- 0.004 0.027 +/- 0.005 0.024 +/- 0.003 0.024 +/- 0.003 0.024 18-Feb 0.014 +/- 0.003 0.018 +/- 0.004 0.014 +/- 0.005 0.015 +/- 0.003 0.013 + 0.003 0.015 25-Feb 0.015 +/- 0.003 0.015 +/- 0.004 0.012 +/- 0.004 0.016 +/- 0.003 0.014 + 0.003 0.014 4-Mar 0.013 +/- 0.003 0.015 +/- 0.004 0.015 +/- 0.005 0.016 +/- 0.003 0.014 + 0.003 0.015 11-Mar 0.025 +/- 0.006(a) 0.023 +/- 0.004 0.021 +/- 0.005 0.026 +/- 0.004 0.020 +/- 0.003 0.023 18-Mar 0.016 +/- 0.005 0.023 +/- 0.004 0.025 +/- 0.005 0.025 +/- 0.004 0.021 +/- 0.003 0.022 25-Mar 0.015 +/- 0.003 0.017 +/- 0.004 0.011 +/- 0.005 0.016 +/- 0.003 0.015 +/- 0.003 0.015 1-Apr 0.015 +/- 0.003 0.015 +/- 0.004 0.015 +/- 0.004 0.016 +/- 0.003 0.013 +/- 0.003 0.015 8-Apr 0.015 +/- 0.003 0.017 +/- 0.004 0.014 +/- 0.005 0.017 +/- 0.003 0.016 +/- 0.003 0.016 15-Apr 0.015 +/- 0.003 0.015 +/- 0.004 0.012 +/- 0.004 0.014 +/- 0.003 0.013 + 0.003 0.014 22-Apr 0.018 +/- 0.003 0.023 i 0.004 0.018 +/- 0.005 0.021 +/- 0.003 0.017 +/- 0.003 0.019 29-Apr 0.016 +/- 0.003 0.015 +/- 0.004 0.016 +/- 0.005 0.017 +/- 0.003 0.012 +/- 0.003 0.015 6-May 0.013 +/- 0.003 0.014 +/- 0.003 0.010 +/- 0.004 0.011 +/- 0.003 0.011 + 0.002 0.012 13-May 0.014 +/- 0.003 0.013 +/- 0.003 0.013 i 0.008 0.014 +/- 0.003 0.015 +/- 0.003 0.014 21 -May 0.007 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.004 0.008 +/- 0.003 0.008 + 0.002 0.008 28-May 0.009 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.004 0.012 +/- 0.003 0.009 + 0.002 0.010 3-Jun 0.013 +/- 0.003 0.015 +/- 0.005 0.011 +/- 0.005 0.013 +/- 0.004 0.012 +/- 0.003 0.013 10-Jun 0.011 +/- 0.003 0.006 +/- 0.007 0.016 +/- 0.005 0.011 +/- 0.003 0.012 + 0.002 0.011 17-Jun 0.008 +/- 0.002 0.008 +/- 0.002 0.011 +/- 0.004 0.009 +/- 0.003 0.009 +/- 0.003 0.009 24-Jun 0.016 +/- 0.003 0.016 +/- 0.003 0.018 +/- 0.005 0.017 +/- 0.003 0.018 i 0.004 0.017 1-Jul 0.016 +/- 0.003 0.017 +/- 0.003 0.013 +/- 0.004 0.016 +/- 0.003 0.016 +/- 0.004 0.016 Maximum 0.025 0.005 0.024 +/- 0.007 0.027 0.008 0.026 +/- 0.004 0.024 +/- 0.004 Average 0.015 0.016 0.015 0.017 0.015 Minimum 0.007 0.002 0.006 +/- 0.002 0.009 +/- 0.004 0.008 +/- 0.003 0.008 +/- 0.002 (a) Sample collected for <84 hours in sample period I = Indicator C = Control (17)

Rochester Gas and Electric Table 3-2B3 Off-Site Air Particulate Samplers Gross Beta Results in pCiIm3 Collection Station Station Station Station Station Date #8 (C) #9 () #10 (C) #11 () #12 (C) Average 8-Jul 0.023 +/- 0.003 0.021+/- 0.003 0.023 +/- 0.005 0.019 +/- 0.004 0.020 + 0.004 0.021 15-Jul 0.017 +/- 0.003 0.017+/- 0.003 0.018 +/- 0.005 0.016 +/- 0.003 0.016 + 0.003 0.017 22-Jul 0.018 +/- 0.003 0.022+/- 0.003 0.021 +/- 0.005 0.019 +/- 0.004 0.019 +/- 0.004 0.020 30-Jul 0.014 +/- 0.003 0.013+/- 0.003 0.013 +/- 0.005 0.015 +/- 0.003 0.012 +/- 0.003 0.013 5-Aug 0.022 +/- 0.003 0.020+/- 0.003 0.022 +/- 0.005 0.016 +/- 0.004 0.020+ 0.004 0.020 12-Aug 0.014 +/- 0.003 0.013+/- 0.003 0.017 +/- 0.005 0.012 +/- 0.003 0.016 +/- 0.003 0.014 19-Aug 0.025 +/- 0.004 0.021+/- 0.003 0.021 +/- 0.003 0.022 +/- 0.004 0.023 +/- 0.004 0.022 26-Aug 0.014 +/- 0.003 0.014+/- 0.003 0.013 +/- 0.003 0.013 +/- 0.003 0.010 +/- 0.003 0.013 3-Sep 0.013 +/- 0.003 0.012 +/- 0.002 0.013+/- 0.002 0.013 +/- 0.003 0.014+ 0.003 0.013 9-Sep 0.022 +/- 0.004 0.019 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.004 0.019 + 0.004 0.019 16-Sep 0.021 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.004 0.022 +/- 0.004 0.021 23-Sep 0.024 +/- 0.004 0.023+/- 0.003 0.021 + 0.003 0.022 +/- 0.004 0.022 + 0.004 0.022 30-Sep 0.021 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.003 0.020 +/- 0.004 0.022 +/- 0.004 0.021 7-Oct 0.019 +/- 0.003 -0.021 +/- 0.003 0.022 +/- 0.003 0.018 +/- 0.004 0.024 +/- 0.004 0.021 14-Oct 0.013 +/- 0.003 0.010 +/- 0.003 0.012 +/- 0.003 0.009 +/- 0.003 0.011 +/- 0.004 0.011 21-Oct 0.012 +/- 0.003 0.010 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.003 0.010 +/- 0.003 0.011 28-Oct 0.012 +/- 0.003 0.013+/- 0.003 0.012 +/- 0.003 0.011 +/- 0.003 0.015 +/- 0.004 0.013 4-Nov 0.014 +/- 0.003 0.013+/- 0.003 0.013 + 0.003 0.013 +/- 0.003 0.016 +/- 0.004 0.014 12-Nov 0.026 +/- 0.003 0.025+/- 0.003 0.023 +/- 0.003 0.026 +/- 0.004 0.034 + 0.005 0.027 18-Nov 0.013 +/- 0.003 0.016 0.003 0.014 +/- 0.003 0.015 +/- 0.004 0.021 +/- 0.005 0.016 25-Nov 0.015 +/- 0.003 0.016+/- 0.003 0.015 +/- 0.003 0.018 +/- 0.004 0.018 + 0.004 0.016 2-Dec 0.014 +/- 0.003 0.012+/- 0.002 0.013 + 0.002 0.014 +/- 0.003 0.022 +/- 0.004 0.015 9-Dec 0.022 +/- 0.004 0.019+/- 0.003 0.019 +/- 0.003 0.020 +/- 0.004 0.032 +/- 0.006 0.022 16-Dec 0.013 +/- 0.003 0.015+/- 0.003 0.016 +/- 0.003 0.018 +/- 0.004 0.022 +/- 0.005 0.017 23-Dec 0.012 +/- 0.003 0.013+/- 0.003 0.016 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.005 0.014 30-Dec 0.015 +/- 0.003 0.014 0.003 0.013 +/- 0.003 0.013 +/- 0.003 0.023 0.005 0.016 Maximum 0.026 +/- 0.004 0.025 +/- 0.003 0.023 +/- 0.005 0.026 +/- 0.004 0.034 +/- 0.006 Average 0.017 0.017 0.017 0.016 0.019 Minimum 0.012 +/- 0.003 0.010 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.003 0.010 +/- 0.003 (a) Sample collected for <84 hours in sample period I=Indicator C = Control (18)

Rochester Gas and Electric Figure 3-3 Onsite vs Offsite Air Monitors Gross Beta Analysis 2002

.030 - .----.... -- - - - - - - - -- - - -- - - - -. - - - - -- - - - - ....... ..- - - - - - -- ........ ......... - ... ..... .. ... ... ... . ... ..... .. . ... I --

.025 p

C

.020 C 015 U

M e .010 t

e r

.005 . ...

.000 N N N N N N N NNN N N N N N

. o _

co O co o _ 0 0 0 0 0 0R 0 0 0 0X 0) 0O

- - ~ ~~~N C Cm ' L O co r co co C 0)

. N C>4 d _ CD . CN _ N o N c) LO) co W r- co -

co a

0) ) Q _

0) - N Week 1lkOnsite --mOffsite (19)

Rochester Gas and Electric Table 3-4A 13 Week Composite Gamma Isotopic Analysis Results in pCi/m3 First Quarter Station #2 #3 #4 #5 #6 #7 #8 #9 #10 #11 #12 #13 Be-7 0.108+/-0.011 0.079+/-0.012 0.104+/-0.0116 0.089+/-0.0131 0.098+/-0.012 0.113+/-0.015 0.081+/-0.012 0.101+/-0.017 0.098+/-0.018 0.121+/-0.014 0.103+/-0.011 0.014+/-0.018 Cs-I 34 <0.002 <0.001 <0.002 <0.002 <0.002 <0.002 <0.002 <0.003 <0.002 <0.001 <0.001 <0.002 Cs-1 37 <0.001 <0.001 <0.001 <0.001 <0.001 <0.002 <0.001 <0.002 <0.002 <0.001 <0.001 <0.002 Zr-95 <0.003 <0.004 <0.004 <0.004 <0.004 <0.005 <0.004 <0.004 <0.008 <0.004 <0.003 <0.005 Nb-95 <0.003 <0.004 <0.003 <0.005 <0.004 <0.004 <0.004 <0.004 <0.005 <0.001 <0.003 <0.003 Co-58 <0.022 <0.002 <0.003 <0.003 <0.024 <0.002 <0.002 <0.003 <0.003 <0.002 <0.002 <0.001 Mn-54 <0.013 <0.000 <0.001 <0.002 <0.014 <0.002 <0.001 <0.002 <0.003 <0.001 <0.001 <0.002 Ru-I 03 <0.003 <0.002 <0.003 <0.004 <0.003 <0.003 <0.003 <0.004 <0.003 <0.003 <0.002 <0.004 Ru-106 <0.012 <0.017 <0.014 <0.014 <0.016 <0.015 <0.017 <0.018 <0.002 <0.013 <0.009 '0.019 Ce-141 <0.004 <0.003 <0.003 <0.003 <0.004 <0.043 <0.003 <0.004 <0.006 <0.003 <0.002 <0.005 Ce-144 <0.006 <0.004 .<0.006 <0.006 <0.004 <0.007 <0.006 <0.007 <0.008 <0.006 <0.005 <0.008 Fe-59 <0.006 <0.01 1 <0.008 <0.032 <0.026 <0.010 <0.005 <0.012 <0.016 <0.007 <0.006 <0.015 Zn-65 <0.004 <0.001 <0.003 <0.006 <0.028 <0.007 <0.004 <0.007 <0.007 <0.003 <0.002 <0.007 Co-60 <0.000 <0.002 <0.002 <0.003 <0.001 <0.002 <0.001 <0.027 <0.004 <0.001 <0.002 <0.003 K-40 0.035+/-0.007 <0.007 0.023+/-0.006 <0.007 <0.016 <0.006 0.035+/-0.009 <O.OfD <0.010 <0.005 <0.012 <0.037 Ba/La-140 <0.011 <0.019 <0.020 <0.020 <0.016 <0.025 <0.016 <0.027 <0.029 <0.006 <0.016 <0.034 (20)

Rochester Gas and Electric Table 3-4B 13 Week Composite Gamma Isotopic Analysis Results in pCi/m3 Second Quarter Station #2 #3 #4 #5 #6 #7 #8 #9 #10 #11 #12 #13 Be-7 0.124+/-0.013 0.125+/-0.015 0.112+/-0.013 0.13+/-0.018 0.098+/-0.014 0.099+/-0.013 0.11+/-0.012 0.099+/-0.014 0.11+/-0.019 0.13+/-0.016 0.099+/-0.012 0.11+/-0.013 Cs-1 34 <0.001 <0.002 <0.001 <0.002 <0.002 <0.002 <0.001 <0.002 <0.002 <0.002 <0.001 <0.002 Cs-137 <0.001 <0.001 <0.001 <0.002 <0.002 <0.002 <0.001 <0.001 <0.001 <0.001 <0.002 <0.001 Zr-95 <0.004 <0.004 <0.003 <0.005 <0.004 <0.005 <0.004 <0.003 <0.005 <0.005 <0.002 <0.004 Nb-95 <0.003 <0.004 <0.003 <0.006 <0.004 <0.004 <0.001 <0.004 <0.006 <0.003 <0.003 <0.004 Co-58 <0.002 <0.002 <0.001 <0.003 <0.002 <0.002 <0.001 <0.002 <0.004 <0.003 <0.002 <0.002 Mn-54 <0.000 <0.001 <0.002 <0.002 <0.001 <0.001 <0.001 <0.000 <0.003 <0.001 <0.001 <0.001 Ru-103 <0.003 <0.002 <0.003 <0.004 <0.003 <0.002 <0.002 <0.002 <0.006 <0.004 <0.002 <0.002 Ru-1 06 <0.012 <0.016 <0.014 <0.018 <0.021 <0.010 <0.01 1 <0.010 <0.027 <0.011 <0.013 <0.01'!

Ce-141 <0.002 <0.003 <0.003 <0.006 <0.004 <0.003 <0.002 <0.004 <0.005 <0.004 <0.003 <0.003 Ce-144 <0.003 <0.005 .<0.005 <0.008 <0.007 <0.005 <0.005 <0.007 <0.008 <0.006 <0.005 <0.004 Fe-59 <0.009 <0.003 <0.010 <0.013 <0.010 <0.008 <0.008 <0.003 <0.018 <0.003 <0.005 <0.007 Zn-65 <0.001 <0.003 <0.001 <0.005 <0.004 <0.004 <0.001 <0.006 <0.006 <0.003 <0.003 <0.003 Co-60 <0.000 <0.002 <0.000 <0.003 <0.001 <0.002 <0.002 <0.001 <0.003 <0.001 <0.001 <0.001 K-40 <0.005 <0.015 <0.005 0.046+/-0.013 0.044+/-0.008 <0.020 <0.005 <0.016 <0.009 0.042+/-0.011 0.039+/-0.007 <0.015 Ba/La-140 <0.006 <0.008 <0.006 <0.037 <0.021 <0.008 <0.018 <0.032 <0.013 <0.008 <0.018 <0.008 (21)

tI Rochester Gas and Electric Table 3-4C 13 Week Composite Gamma Isotopic Analysis Results in pCi/m3 Third Quarter Station #2 #3 #4 #5 #6 #7 #8 #9 #10 #11 #12 #13 Be-7 0.102+/-0.011 0.120+/-0.010 0.119+/-0.010 0.088+/-0.011 0.12+/-0.010 0.11+/-0.009 0.112+/-0.013 0.114+/-0.011 0.118+/-0.011 0.107+/-0.010 0.114+/-0.010 0.108+/-0.009 Cs-1 34 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.002 <0.001 <0.001 <0.001 <0.001 <0.001 Cs-i 37 <0.001 <0,001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 Zr-95 <0.003 <0.003 <0.002 <0.003 <0.002 <0.002 <0.004 <0.003 <0.003 <0.003 <0.003 <0.003 Nb-95 <0.002 <0.002 <0.002 <0.003 <0.002 <0.002 <0.003 <0.003 <0.002 <0.002 <0.003 <0.002 Co-58 <0.002 <0.001 <0.001 <0.002 <0.001 <0.001 <0.002 <0.001 <0.002 <0.002 <0.002 <0.001 Mn-54 <0.000 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 Ru-1 03 <0.002 <0.002 <0.002 <0.002 <0.002 <0.002 <0.003 <0.002 <0.003 <0.002 <0.002 <0.001 Ru-106 <0.014 <0.013 <0.009 <0.014 <0.010 <0.007 <0.018 <0.010 <0.008 <0.016 <0.010 <0.009 Ce-141 <0.002 <0.002 <0.002 <0.002 <0.002 <0.002 <0.004 <0.002 <0.002 <0.005 <0.002 <0.002 I

Ce-144 <0.004 <0.004 <0.005 <0.005 <0.005 <0.004 <0.006 <0.004 <0.004 <0.002 <0.004 <0.004 Fe-59 <0.007 <0.007 <0.006 <0.007 <0.004 <0.006 <0.007 <0.009 <0.007 <0.008 <0.006 <0.006 Zn-65 <0.003 <0.002 <0.003 <0.003 <0.003 <0.002 <0.003 <0.002 <0.003 <0.003 <0.003 <0.002 Co-60 <0.002 <0.001 <0.001 <0.001 <0.001 <0.001 <0.000 <0.002 <0.001 <0.002 <0.000 <0.001 K-40 <0.004 <0.014 0.019+/-0.006 0.022+/-0.007 0.030+/-0.006 0.031+/-0.006 0.033+/-0.007 <0.004 <0.003 <0.015 <0.017 0.032+/-0.006 Ba/La-140 <0.012 <0.015 <0.009 <0.004 <0.009 <0.009 <0.004 <0.004 <0.003 <0.010 <0.010 <0.019 (22)

Rochester Gas and Electric Table 3-4D 13 Week Composite Gamma Isotopic Analysis Results in pCifm3 Fourth Quarter Station #2 #3 #4 #5 #6 #7 #8 #9 #10 #11 #12 #13 Be-7 0.075+/-0.008 0.077+/-0.009 0.090+/-0.009 0.080+/-0.015 0.089+/-0.009 0.076+/-0.008 0.094+/-0.89 0.077+/-0.088 0.084+/-0.0078 0.078+/-0.010 0.10+/-0.012 0.083+/-0.010 Cs-134 <0.001 <0.001 <0.001 <0.002 <0.001 <0.001 <0.001 <0.010 <0.001 <0.001 <0.001 <0.001 Cs-I 37 <0.001 <0.001 <0.001 <0.002 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 Zr-95 <0.003 <0.003 <0.004 <0.007 <0.002 <0.002 <0.002 <0.001 <0.001 <0.003 <0.005 <0.003 Nb-95 <0.003 <0.003 <0.002 <0.004 <0.002 <0.002 <0.002 <0.003 <0.002 <0.003 <0.004 <0.002 Co-58 <0.001 <0.002 <0.001 <0.002 <0.001 <0.001 <0.001 <0.002 <0.001 <0.002 <0.002 <0.002 Mn-54 <0.001 <0.001 <0.001 <0.002 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 <0.001 Ru-I 03 <0.002 <0.002 <0.002 <0.005 <0.002 <0.001 <0.001 <0.002 <0.002 <0.003 <0.002 <0.002 Ru-106 <0.008 <0.009 <0.009 <0.016 <0.009 <0.008 <0.009 <0.010 <0.008 <0.009 <0.015 <0.007 Ce-141 <0.002 <0.003 <0.002 <0.004 <0.002 <0.002 <0.002 <0.002 <0.002 <0.003 <0.003 <0.003 Ce-144 <0.004 <0.004 <0.003 <0.007 <0.004 <0.004 <0.003 <0.004 <0.003 <0.004 <0.004 <0.004 Fe-59 <0.002 <0.007 <0.004 <0.011 <0.009 <0.005 <0.007 <0.007 <0.005 <0.005 <0.008 <0.008 Zn-65 <0.003 <0.003 <0.002 <0.005 <0.003 <0.003 <0.003 <0.001 <0.002 <0.003 <0.004 <0.004 Co-60 <0.001 <0.001 <0.001 <0.001 <0.000 <0.001 <0.001 <0.001 <0.001 <0.001 <0.002 <0.002 K-40 <0.003 <0.009 0.016+/-0.005 <0.008 <0.003 <0.009 <0.012 <0.016 <0.008 <0.014 <0.015 <0.016 Ba/La-140 <0.020 <0.020 <0.021 <0.032 <0.004 <0.012 <0.013 <0.019 <0.012 <0.016 <0.023 <0.022 (23)

Table 3-5 Charcoal Cartridges Gamma Analysis for Iodine Results in pCi/M3 Collection Station #2 Station #4 Station #7 Station #8 Station #9 Station #11 Date 7-Jan <0.031 <0.017 <0.042 <0.030 <0.042 <0.031 14-Jan <0.013 <0.026 <0.027 <0.023 <0.040 <0.015 21-Jan <0.017 <0.028 <0.032 <0.024 <0.044 <0.023 28-Jan <0.020 <0.029 <0.030 <0.018 <0.051 <0.027 5-Feb <0.017 <0.019 <0.035 <0.013 <0.031 <0.022 11-Feb <0.027 <0.022 <0.039 <0.030 <0.025 <0.016 18-Feb <0.025 <0.030 <0.024 <0.023 <0.026 <0.025 25-Feb <0.030 <0.022 <0.021 <0.024 <0.044 <0.026 4-Mar <0.018 <0.013 <0.032 <0.026 <0.035 <0.027 11-Mar <0.020 <0.035 <0.038 <0.057 <0.037 <0.022 18-Mar <0.023 <0.025 <0.025 <0.043 <0.024 <0.022 25-Mar <0.025 <0.021 <0.025 <0.038 <0.036 <0.026 1-Apr <0.023 <0.016 <0.023 <0.022 <0.020 <0.019 8-Apr <0.022 <0.028 <0.032 <0.025 <0.022 <0.027 15-Apr <0.023 <0.024 <0.020 <0.021 <0.029 <0.019 22-Apr <0.024 <0.024 <0.006 <0.018 <0.032 <0.032 29-Apr <0.034 <0.024 <0.032 <0.020 <0.039 <0.020 6-May <0.029 <0.018 <0.023 <0.020 <0.027 <0.036 13-May <0.018 <0.021 <0.029 <0.021 <0.038 <0.023 20-May <0.024 <0.029 <0.023 <0.022 <0.022 <0.026 28-May <0.024 <0.017 <0.021 <0.017 <0.022 <0.025 3-Jun <0.017 <0.027 <0.028 <0.028 <0.054 <0.033 10-Jun <0.026 <0.022 <0.032 <0.024 <0.057 <0.043 17-Jun <0.017 <0.026 <0.039 <0.036 <0.018 <0.027 24-Jun <0.018 <0.025 <0.035 <0.023 <0.029 <0.033 1-Jul <0.022 <0.029 <0.034 <0.018 <0.022 <0.025 8-Jul <0.024 <0.024 <0.033 <0.033 <0.014 <0.032 15-Jul <0.018 <0.006 <0.029 <0.023 <0.026 <0.034 22-Jul <0.037 <0.019 <0.026 <0.029 <0.029 <0.041 30-Jul <0.017 <0.023 <0.020 <0.027 <0.024 <0.030 5-Aug <0.035 <0.028 <0.020 <0.014 <0.017 <0.027 12-Aug <0.034 <0.015 <0.016 <0.025 <0.023 <0.039 19-Aug <0.035 <0.031 <0.021 <0.027 <0.025 <0.021 26-Aug <0.029 <0.025 <0.013 <0.027 <0.027 <0.034 3-Sep <0.023 <0.027 <0.031 <0.025 <0.013 <0.025 9-Sep <0.028 <0.049 <0.040 <0.031 <0.021 <0.057 16-Sep <0.016 <0.028 <0.023 <0.020 <0.026 <0.028 23-Sep <0.022 <0.023 <0.013 <0.024 .<0.01 9 <0.031 30-Sep <0.018 <0.014 <0.014 <0.015 <0.015 <0.018 7-Oct <0.021 <0.032 <0.020 <0.031 <0.016 <0.035 14-Oct <0.026 <0.017 <0.012 <0.019 <0.017 <0.025 21-Oct <0.021 <0.017 <0.016 <0.021 <0.015 <0.023 28-Oct <0.012 <0.021 <0.015 <0.016 <0.018 <0.023 4-Nov <0.014 <0.023 <0.012 <0.023 <0.023 <0.032 12-Nov <0.013 <0.018 <0.022 <0.021 <0.014 <0.025 18-Nov <0.022 <0.030 <0.016 <0.014 <0.016 <0.035 25-Nov <0.025 <0.022 <0.012 <0.016 <0.013 <0.027 2-Dec <0.01 9 <0.023 <0.014 <0.017 <0.015 <0.020 9-Dec <0.023 <0.020 <0.021 <0.020 <0.024 <0.026 16-Dec <0.019 <0.020 <0.015 <0.019 <0.025 <0.013 23-Dec <0.031 <0.018 <0.016 <0.015 <0.014 <0.036 30-Dec <0.025 <0.028 <0.017 <0.021 <0.019 <0.025 (24)

,I.

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

0.200 M 0.150 e

t e

0.100 r

0.050 0.000 o O) O 0 - N Cn t 11) (0 1- CO 0 ) ° o N Cn t Ue (0 rs ( 0 0) 0° - N C' w Lt) CD 1. CO 0 ) 0o -o N N Years 1968-2002 l-- Onsite Offsite Peaks are indicative of years in which atmospheric testing of nuclear weapons occurred. (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 2002 averages were 2.14 pCi/liter and 2.35 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 2002 averages were 2.16 pCi/liter and 2.06 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 11 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 composite sample. These are listed in Tables 3-9 to 3-14 and are separated by source of sample. No anomalous results were noted.

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

Composites are made from the weekly samples and a portion filtered to remove interferences for analysis by beta scintillation. Tritium data is given in Table 3-15.

Radioiodine analysis All monthly composite water samples are analyzed for lodine-131. The analysis allows the determination of lodine-131 activity of <1pCi/liter. Radioiodine data is given in Table 3-16. Any positive counts and the 1 sigma error are reported. During 2002, no sample results indicated 1-131 activity in excess of the LLD for the analysis.

27

Rochester Gas and Electric Figure 3-7A Environmental Water Samples IGross Beta Analysis for 2002l 5.00 4.50 ......... .... ............. A..I---------------------------------------------------- ----------------------------- I------------------------------....----................. ... . . . .

4.00 ..-- - -- - ... .............................. I. - ---------------------- --- -- -- --- -- -- -- --- -- -- --- -- -- --

.................. -------------- ------------- . .......... .I.......... I.-. -.. ... - . -. . - ..

-P 3.50 - . ..........

-A.-. -I.-. -. -. --A ...- ..-------....-.- ------- --.....--- --.. . . -. . -- ---------- -------------- -----.--- --....................-....--

C 3.00 --

2.50 L

i 2.00-t e

r 1.50- -

1.00 0.50 -

0.00 -

Jan Feb March April May June July Aug Sept Oct Nov Dec Week Number 1- -- OWD -URussell]

(28)

Rochester Gas and Electric Figure 3-713 Annual Trending of Environmental Water Samples IGross Beta Analysisi 14.00 12.00 10.00 p

C 8.00 L

t 6.00 e

r 4.00 2.00 0.00 CN N 4 Years 1968-2002 1- Russell OWDO (29)

Rochester Gas and Electric - -

Table 3-8 Environmental Water Samples Gross Beta Analysis Results in pCi/Liter Month Russell O.W.D. Circ In Circ Out Deer Creek January 3.04 +/- 0.50 2.53 +/- 0.49 2.70 +/- 0.49 2.53 0.49 4.66 +/- 1.17

- February 2.29 +/- 0.62 1.52 +/- 0.58 2.52 +/- 0.62 1.69 0.60 2.76 +/- 0.63 March 2.22 +/- 0.50 3.81 +/- 0.58 1.96 +/- 0.46 2.94 +/- 0.51 2.90 +/- 0.62 April 2.33 +/- 0.52 1.78 +/- 0.50 1.96 +/- 0.50 2.85 +/- 0.53 4.20 +/- 0.60 May 2.48 +/- 0.54 2.47 +/- 0.56 1.78 +/- 0.51 2.23 +/- 0.55 3.60 +/- 0.58 June 2.19 +/- 0.50 3.10 +/- 0.55 1.57 +/- 0.52 0.82 +/- 0.51 1.78 +/- 0.54 July 1.65 +/- 0.48 1.71 +/- 0.47 1.74 +/- 0.47 1.68 +/- 0.45 2.95 +/- 0.62 August 2.15 +/- 0.47 2.72 +/- 0.48 2.41 +/- 0.47 2.77 +/- 0.49 4.15 +/- 1.05 September 2.27 +/- 0.47 1.85 +/- 0.50 2.52 +/- 0.51 1.77 +/- 0.49 1.51 +/- 0.58 October 0.76 +/- 0.51 1.13 +/- 0.54 1.76 +/- 0.55 <1.61 5.75 +/- 0.71 November 2.20 +/- 0.64 3.20 +/- 0.66 2.86 +/- 0.64 1.31 +/- 0.62 5.56 +/- 0.71 December 3.09 +/- 0.56 2.36 +/- 0.54 4.32 +/- 0.59 1.69 +/- 0.51 5.37 +/- 0.66 Maximum 3.09 +/- 0.64 3.81 +/- 0.66 4.32 +/- 0.64 2.94 +/- 0.62 5.75 +/- 1.17 Average 2.14 2.35 2.16 2.06 3.62 Minimum 0.76 +/- 0.47 1.13 +/- 0.47 1.57 +/- 0.46 0.82 +/- 0.45 1.51 +/- 0.54 (30)

Rochester Gas and Electric Table 3-9 Russell Station Water Gamma Isotopic Analyses Results in pCilLiter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 60Co 140Ba 226Ra January < 24 < 29 <2 <2 <5 <3 <2 <2 < 3 < 24 < 6 < 17 <7 < 5 < 2 < 8 74+/-21 February <27 <36 <2 <3 <5 <4 <3 <3 <4 < 33 < 7 < 20 < 9 < 6 < 3 < 10 99+/-28 March <33 <43 <2 <3 <6 <4 <3 <3 <4 < 31 < 8 < 22 < 10 < 7 < 3 < 14 73+/-25 April <27 <37 <3 <3 <6 <4 <3 <2 <4 < 28 < 4 < 19 < 8 < 6 < 3 < 9 41+/-21 May <34 <44 <3 <3 <7 <5 <4 <3 < 5 < 32 < 9 < 25 < 12 < 7 < 4 < 14 141+/-30 June < 25 < 32 <1 <2 <4 <3 <2 <2 <3 < 24 < 6 < 18 <6 <3 < 2 <6 105+/-19 July < 31 < 38 < 3 <3 <6 <4 <3 <3 <4 < 30 < 5 < 22 < 11 - <8 < 3 < 10 122+/-24 August < 25 < 35 <1 <2 <4 <3 <3 <2 < 3 < 22 < 6 < 18 < 7 <3 <2 < 8 101+/-18 September < 31 < 36 < 3 <3 <5 <4 <3 <3 <2 <30 <7 < 22 < 9 <5 < 3 < 8 63+/-24 October < 25 < 39 < 3 <3 <6 <4 <3 <3 <4 < 30 < 6 <18 <10 <7 <3 <_10 115+/-26 November < 19 < 24 < 2 <2 <4 <3 <2 <2 < 3 < 18 < 3 < 13 < 6 <4 < 2 < 6 165+/-17 December < 25 < 31 < 2 <2 <5 <3 <3 <2 <4 < 25 < 6 < 18 <7 <6 <2 < 8 44+/-20 (31)

Rochester Gas and Electric Table 3-10 Ontario Water District Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 6OCo 140Ba 226Ra January < 28 < 33 <2 <3 < 5 <3 <3 <3 <4 < 28 <6 < 21 < 10 <7 <3 <6 34+/-20 February < 27 < 34 <3 <3 <6 <3 <3 <3 <4 < 30 <6 < 21 <9 < 7 <3 <7 68+/-22 March < 35 < 38 <3 <3 <6 <4 <4 <3 5 < 32 <8 < 24 < 10 <8 <3 <10 126+/-30 April < 43 < 48 <4 <4 <9 <6 <5 <4 5 < 44 <8 < 28 < 12 < 11 <6 < 13 63+/-35 May < 25 < 30 <1 <2 <4 <3 <3 <2 3 < 24 <6 < 17 <7 <5 <2 <5 87+/-21 June < 23 < 33 <3 <3 <5 <4 <3 <3 4 < 29 <3 < 18 <7 <6 <3 <8 99+/-22 July < 23 < 30 <3 <3 <5 <3 <3 <3 c 3 < 28 <6 < 18 < 10 <6 <2 <8 110+/-21 August < 29 < 34 <3 <3 <6 <4 <3 <3 4 < 29 < 6 < 19 <9 <7 <3 <8 83+/-25 September < 37 < 44 <4 <4 <5 <5 <4 <4 6 < 43 <7 < 25 < 14 <7 <4 <9 130+/-33 October < 25 < 35 <2 <2 <6 <3 <3 <3 <4 < 24 <4 < 18 < 10 <6 <3 <8 89+/-24 November < 26 < 34 <2 <3 <5 < 3 <3 <3 <4 <31 <7 <22 <9 <6 <3 <6 < 67 December < 27 < 35 <2 <3 <5 <4 <3 <3 4 < 30 <7 < 22 < 10 <6 <3 <9 94+/-26 (32)

Rochester Gas and Electric Table 3-11 Circ-In Water Gamma Isotopic Analyses Results In pCilLiter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 6OCo 14OBa 226Ra January < 33 < 36 <2 < 3 <6 <4 <3 <3 <5 < 29 <7 < 23 < 10 <5 <4 < 143+/-31 February < 36 < 37 < 4 <4 <7 <5 <5 <4 <5 < 36 < 7 < 21 < 12 <9 <5 < 11 56+/-27 March < 23 < 30 <1 < 2 <4 <3 <2 <2 <3 < 24 < 6 < 18 <6 <3 <2 < 7 66+/-23 April < 34 < 41 < 4 <4 <7 <5 <4 <4 <5 < 45 <8 < 26 <9 <9 <4 < 10 <78 May < 35 < 43 < 3 < 3 <7 <4 <3 <3 <5 < 30 < 6 < 25 < 12 <5 <4 < 11 130+/-30 June < 30 < 37 < 3 <3 <6 <4 <3 <3 <4 < 33 < 5 < 24 < 10 <8 <4 <9 77+/-26 July < 21 < 27 <1 <2 <4 <3 <2 <2 <3 < 23 < 5 < 18 <6 < 3 <2 < 5 88+/-18 August < 26 < 36 < 3 < 3 <5 <4 <3 <3 <4 < 23 <4 < 17 <9 < 5 <3 < 8 107+/-22 September < 36 < 42 < 3 < 4 <8 <4 <5 <4 <6 < 41 < 9 < 28 < 13 < 9 <4 < 11 55+/-30 October < 26 < 36 < 3 < 3 <6 <4 <3 <3 <4 < 29 <6 < 20 <8 < 7 < 3 < 7 46+/-22 November < 23 < 28 <1 < 2 <4 <3 <2 <2 <3 < 23 < 5

18 <7 <3 <2 < 6 98+/-19 December < 28 < 34 <3 < 2 <5 <4 <4 <3 <4 < 27 <6 < 18 < 8 <3 < 3 < 9 125+/-25 (33)

Rochester Gas and Electric Table 3-12 Circ-Outlet Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 6SZn 6OCo 14OBa 226Ra January < 24 < 30 <2 < 3 <5 <3 <3 < 2 < 4 < 26 < 3 < 19 <7 < 3 < 3 < 7 116+/-21 February < 26 < 34 < 2 < 3 <5 <4 <3 < 3 < 3 < 31 < 7 < 23 < 8 < 6 < 3 < 91+/-24 March < 25 < 33 < 3 <3 <5 <4 <3 < 3 < 4 < 25 <6 < 17 < 10 < 6 < 3 <9 108+/-23 April < 39 < 45 < 4 <4 <7 <4 <4 < 4 < 5 < 47 < 9 < 28 < 14 < 7 < 4 < 11 80+/-36 May < 24 < 30 < 2 <2 <5 <3 <3 < 2 < 3 < 24 < 5 < 18 < 7 < 3 < 2 <7 120+/-20 June < 22 < 28 <1 < 2 <4 <3 <2 <2 < 3 < 23 < 3 < 17 < 6 < 3 < 2 < 5 100+/-20 July < 30 < 36 < 2 < 3 <6 <4 <4 < 3 < 4 < 33 < 7 < 24 < 10 < 8 < 3 <9 115+/-27 August < 27 < 35 < 3 < 3 <5 <4 <3 < 3 < 4 < 31 < 7 < 21 < 9 < 6 < 3 <9 60+/-22 September < 37 < 47 <4 < 4 <7 <4 <5 < 4 < 6 < 35 < 8 < 29 < 12 < 8 < 4 < 12 <89 October < 27 < 37 <2 < 3 < 5 <4 <3 < 3 < 4 < 31 < 7 < 22 < 8 < 6 < 3 <9 <63 November <.33 < 39 <3 < 4 <8 <5 <4 < 4 < 5 < 37 < 7 < 23 < 12 < 8 < 4 <9 100+/-27 December < 31 < 41 < 3 < 3 <7 <4 <4 <3 <4 < 36 < 7 < 21 < 12 < 8 < 3 < 11 107+/-28 (34)

Rochester Gas and Electric Table 3-13 Deer Creek Water Gamma Isotopic Analyses Results in pCi/Liter Month 7Be 51Cr 134Cs 137Cs 95Zr 95Nb 58Co 54Mn 103Ru 106Ru 141Ce 144Ce 59Fe 65Zn 6OCo 14OBa 226Ra January < 38 < 37 < 3 <5 <8 <5 < 5 <5 < 5 < 51 < 10 < 40 < 13 < 6 < 6 < 5 < 132 February < 31 < 41 < 5 <5 <9 <5 < 5 4 <4 < 42 <7 < 30 < 12 < 11 < 5 < 8 140+/-40 March < 44 < 47 < 4 <5 <9 <5 < 6 < 6 < 6 < 54 < 9 < 43 < 16 < 15 < 6 < 8 < 130 April < 35 < 44 < 4 <5 <8 <6 <4 5 < 5 < 47 < 8 < 32 < 11 < 15 < 5 < 8 < 110 May < 46 < 45 < 6 < 6 < 10 < 5 <5 <5 < 6 < 45 <9 < 43 < 17 < 13 < 7 < 98+/-46 June < 44 < 52 <5 < 6 < 10 < 6 <6 < 6 < 7 < 67 < 10 < 41 < 15 <-13 < 7 < 8 < 135 July < 45 < 47 < 7 < 6 < 11 < 6 < 7 <7 <6 <50 <9 <35 <11 <14 <6 < 11 < 114 August < 55 < 49 <6 < 5 < 10 < 6 < 7 <6 < 8 < 55 < 10 < 50 < 14 < 19 < 6 < 10 < 153 September < 46 < 42 <7 < 5 < 11 <7 < 6 *8 < 6 < 65 < 9 < 33 < 17 < 12 < 8 <9 125+/-50 October < 44 < 48 <5 <5 <9 <5 < 6 < 5 <6 < 54 < 10 < 41 < 15 < 14 <6 < 6 144+/-48 November < 31 < 35 <3 <4 <7 <4 < 3 <3 < 4 < 39 < 7 < 31 < 8 < 5 < 4 < 4 < 94 December <41 < 42 <5 <4 <8 <5 < 5 < 5 <5 < 48 < 8 < 36 < 13 < 11 < 5 <9 60+/-38 (35)

Rochester Gas and Electric--

Table 3-14 2002 Environmental Water Samples Tritium Analysis Results in pCi/Liter Month Russell O.W.D. Circ In Circ Out Deer Creek January <260 <262 <263 <260 <264 February <265 <263 <262 <260 <272 March <264 <262 <260 <263 <270 April <265 <261 <263 <263 <271 May <258 <251 <255 <253 <264 June <234 <233 <234 <235 <260 July <248 <252 <254 <253 <263 August <248 <247 <248 <248 <256 September <251 <253 <250 <254 <262 October <237 <236 <236 <236 <243 November <235 <235 <237 <235 <241 December <256 <259 <258 <258 <258 (36)

v Rochester Gas and Electric Table 3-15 Radioiodine in Water Results in pCi/Liter Month Russell O.W.D. Circ In Circ Out Deer Creek January <0.7 <0.6 <0.5 <0.5 <0.4 February <0.7 <0.6 <0.5 <0.5 <0.4 March <0.8 <0.5 <0.4 <0.4 <0.5 April <0.7 <0.5 <0.4 <0.5 <0.4 May <0.8 <0.5 <0.4 <0.4 <0.5 June <0.8 <0.5 <0.6 <0.6 <0.5 July <0.6 <0.6 <0.5 <0.4 <0.4 August <1.0 <0.5 <0.4 <0.5 <1.0 September <0.9 <1.2 <0.5 <0.7 <0.4 October <0.9 <0.5 <0.5 <0.6 <0.6 November <0.7 <0.5 <0.5 <0.4 <0.4 December <0.7 <0.5 <0.6 <0.5 <0.4 (37)

I jV 3.4 Milk Samples There were three indicator dairy herds located three to five miles from the plant on 1/1/02. The owner of indicator farm C retired early In 2002, and a change to the ODCM will be submitted to reflect this. Milk samples are collected monthly during November through May from one of the indicator farms and biweekly during June through October from each. A control farm sample is taken for each monthly sample and once during each biweekly period. The milk is analyzed for lodine-131 and also analyzed by gamma spectroscopy for major fission products.

All positive counts and the +/-1 sigma error are reported. During 2002, 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 K-40 Cs-134 Cs-137 Ba-140 1-131 FARM C 01/08/02 1270+/-62.8 <4 <8 <5 <0.45 FARM D 01/08/02 1520+/-93.4 <6 <9 <10 <0.45 FARM B 02/12/02 1510+/-65.6 <6 <5 <5 <0.39 FARM D 02/12/02 1540+/-65.3 <5 <5 <7 <0.40 FARM A 03/11(02 1700+/-89.1 <7 <8 <9 <0.57 FARM D 03/12/02 1450+/-63.7 <5 <6 <7 <0.59 FARM B 04109/02 1270+/-79.9 <7 <6 <10 <0.49 FARM D 04/09/02 1460+/-64.3 <4 <5 <7 <0.45 FARM A 05/14/02 1400+/-62 <4 <5 <6 <0.44 FARM D 05/14/02 1420+/-62 <3 <4 <6 <0.46 FARM A 06/11/02 1400+/-75 <6 <5 <8 <0.51 FARM B 06/11/02 1610+/-85 <8 <7 <12 <0.44 FARM D 06/11/02 1610+/-51 <3 <5 <5 <0.45 FARM A 06/25/02 1600+/-67 <7 <5 <6 <0.42 FARM B 06/25/02 1520+/-64 <4 <4 <6 <0.51 FARM D 06/25/02 1660+/-70 <6 <5 <7 <0.52 FARM A 07/09/02 1830+/-74 <6 <5 <8 <0.47 FARM B 07/09/02 1680+/-50 <3 <4 <5 <0.46 FARM D 07/09/02 1500+/-66 <5 <6 <7 <0.55 FARM A 07/23/02 1490+/-65.0 <5 <5 <6 <0.43 FARM B 07/23/02 1640+/-69.3 <5 <5 <7 <0.43 FARM D 07/23/02 1750+/-50.6 <2 <4 <4 <0.42 FARM A 08/06/02 1420+/-95 <7 <9 <11 <0.51 FARM B 08/06/02 1670+/-84 <7 <7 <10 <0.44 FARM D 08/06/02 1720+/-60 <3 <5 <5 <0.43 FARM A 08/20/02 1570+/-96 <7 <7 <8 <0.54 FARM B 08/20/02 1410+/-75 <5 <6 <7 <0.44 FARM D 08/20/02 1560+/-78 <6 <7 <6 <0.47 FARM A 09/04/02 1710+/-52 <3 <4 <4 <0.46 FARM B 09/04/02 1620+/-85 <6 <7 <10 <0.38 FARM D 09/04/02 1510+/-67 <5 <5 <6 <0.39 FARM A 09/17/02 1780+/-74 <6 <6 <10 <0.44 FARM B 09/17/02 1660+/-51 <3 <4 <4 <0.39 FARM D 09/17/02 1640+/-69 <5 <4 <6 <0.40 FARM A 09/30/02 1590+/-83 <6 <6 <10 <0.66 FARM B 09/30/02 1450+/-64 <5 <6 <7 <0.52 FARM D 09/30/02 1510+/-64 <6 <6 <6 <0.57 FARM A 10/15/02 1540+/-84 <8 <5 <9 <0.48 FARM B 10/15/02 1350+/-63 <5 <5 <3 <0.48 FARM D 10/15/02 1530+/-67 <6 <5 <5 <0.42 FARM A 10/29/02 1390+/-79.8 <6 <7 <5 <0.44 FARM B 10/29/02 1560+/-68.2 <5 <6 <6 <0.39 FARM D 10/29/02 1580+/-67 <4 <6 <6 <0.42 FARM B 11/13/02 1770+/-73 <6 <6 <6 <0.38 FARM D 11/13/02 1630+/-50 <5 <4 <3 <0.47 FARM A 12/10/02 1670+/-88 <6 <7 <5 <0.39 FARM D 12/10/02 1370+/-63 <5 <5 <8 <0.42 I

(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 if they are available. There was no statistically significant difference in the activity of the fish 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 3-1 7A, and 3-17B.

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

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

40

Rochester Gas and Electric Table 3-17A Fish Samples Gamma Isotopic Analysis Results in pCi/kgm Wet Description 226Ra 51Cr 131 1 134Cs 137Cs 103Ru 106Ru 141Ce 144Ce Indicator Fish First Half 2002 Carp <448 < 265 < 49 < 30 < 29 < 28 < 350 < 42 < 147 Walley 350+/-186 < 229 < 54 < 26 < 28 < 27 < 276 < 40 < 127 BrownTrout 536+/-164 < 247 < 55 < 25 < 27 <30 <284 <36 < 132 Small Mouth Bass 459+/-198 < 334 < 61 < 34 < 35 < 36 < 329 < 50 < 174 Second Half 2002 Chinook Salmon 262+158 < 184 < 36 < 22 < 24 < 24 < 221 < 28 < 107 Smallmouth Bass 435+/-137 < 160 < 31 < 21 < 20 < 19 < 184 < 27 < 98 Brown Trout 776+/-133 < 153 < 35 < 20 < 20 < 21 <200 < 28 < 95 Rainbow Trout 512+/-157 < 195 < 38 < 20 < 20 < 27 < 224 < 32 < 126 Coho Salmon 567+/-155 < 194 < 41 < 14 < 20 < 21 < 220 < 33 < 123 Background (Control) Fish First Half 2002 Freshwater Drum 226+/-121 < 249 < 126 < 21 < 20 < 28 < 228 < 40 < 100

-Small Mouth Bass 743+/-112 < 162 < 30 < 17 < 17 < 21 < 165 < 25 < 92 White Sucker 684+/-226 < 322 < 112 < 18 < 31 < 34 < 294 < 52 < 168 Rainbow Trout 411+/-229 < 350 < 117 < 19 < 31 < 35 < 334 < 54 < 178 Second Half 2002 Small Mouth Bass 533+/-141 < 254 < 136 < 22 < 20 <28 <207 <36 < 118 Small Mouth Bass 281+/-124 < 172 < 40 < 20 < 19 <20 <208 <26 < 103 Brown Trout 752+/-154 < 199 < 39 < 21 < 16 <22 <209 <27 < 98

-Freshwater Drum 395+/-159 < 214 < 49 < 23 12.8+/-6.71 < 27 <235 <35 < 126 White Sucker 821+/-151 < 183 < 34 < 13 < 21 < 22 <216 < 31 < 119 (41)

Rochester Gas and Electric Table 3-17B Fish Samples Gamma Isotopic Analysis Results in pCi/kgm Wet Description 95Zr 95Nb 58Co 54Mn 59Fe 65Zn 6OCo 40K 14OBa Indicator Fish First Half 2002 Carp < 53 < 34 < 38 < 33 < 103 < 75 < 30 4590+/-295 < 62 Walley < 48 < 32 < 26 < 26 < 78 < 53 < 37 4450+/-275 < 50 BrownTrout < 53 < 32 <26 <27 <81 < 68 < 34 4430+/-275 < 50 Small Mouth Bass < 55 < 36 < 32 <31 <92 < 88 < 38 6060+/-340 < 74 Second Half 2002 Chinook Salmon < 44 < 29 < 24 < 22 < 72 < 57 < 28 4810+/-253 < 38 Smallmouth Bass < 34 < 19 < 18 < 19 < 63 < 45 < 17 4630+/-199 < 31 BrownTrout < 38 < 23 < 20 <22 < 54 < 51 < 19 4770+/-205 < 26 RainbowTrout < 39 < 27 <23 < 21 < 71 < 57 < 26 5590+/-230 < 42 Coho Salmon < 36 < 23 <20 <21 < 53 < 51 < 21 5980+/-199 < 33 Background (Control) Fish First Half 2002 Freshwater Drum < 41 < 29 < 21 < 22 < 77 < 54 < 21 3440+/-183 < 66 Small Mouth Bass < 35 < 23 < 18 < 20 < 60 < 49 < 19 4020+/-183 < 35 White Sucker < 59 < 36 < 29 < 32 <83 < 68 < 27 5450+/-262 < 75 Rainbow Trout < 57 < 36 < 34 < 29 < 86 < 70 < 28 5450+/-270 < 70 Second Half 2002 Small Mouth Bass < 49 < 40 < 26 < 22 <85 < 66 < 30 4370+/-239 < 72 Small Mouth Bass < 33 < 20 < 20 < 19 < 52 < 50 < 20 4333+/-193 < 38 BrownTrout < 36 < 21 < 22 < 21 <58 < 53 < 17 5180+/-214 < 29 Freshwater Drum < 46 < 25 < 25 < 23 <62 < 62 < 23 5370+/-231 < 51 White Sucker < 35 < 21 < 20 < 21 < 47 < 47 < 21 5410+/-186 < 25 (42)

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

Description Collection Date 226Ra 51Cr 131 1 134Cs 137Cs 103 Ru Ru 106 141Ce 144Ce Shoreline Sediment (I) 04/25/02 724+/-250 <288 <49 <33 <30 <33 <333 <50 <203 Shoreline Sediment (C) 04/25/02 950+/-239 <266 <57 <40 <30 <37 <292 <52 <192 Shoreline Sediment (I) 08/05/02 <661 <234 <41 <34 <35 <32 <309 <47 <188 Shoreline Sediment (C) 07/31/02 1000+/-224 <283 <51 <38 <32 <37 <321 <46 <176 Benthic Sediment (I) 09/18/02 682+/-243 <334 <85 <33 <33 <33 <319 <61 <227 95Zr 95Nb 58Co 54Mn 59Fe 65Zn 6OCo 40K 1408a Shoreline Sediment (I) 04/25/02 <57 <40 <28 <32 <64 <44 <26 8250+/-316 <50 Shoreline Sediment (C) 04/25102 <52 <44 <33 <30 <78 <97 <35 8580+/-39 <59 Shoreline Sediment () 08/05/02 <46 <31 <34 <32 <77 <102 <38 9280+/-407 <47 Shoreline Sediment (C) 07/31/02 <63 <39 <34 <30 <86 <90 <41 14000+/-481 <51 Benthic Sediment (I) 09/18/02 <60 <41 <34 <30 <70 <47 <30 10100+/-352 <68 (I) = Indicator (C) = Control (43)

IA ..

3.0 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

Rochester Gas and Electric Table 3-19 Vegetation Samples Gamma Isotopic Analysis Results in pCi/kg (wet)

Collection Description Date Indicator Vegetation 226Ra 51Cr 131 1 - 134Cs 137Cs 103 Ru Ru 106 141Ce 144Ce Red Raspberries 07/11/02 99.7+/-51.3 <78 <19 <7 <8 <9 <80 <12 <41 Lettuce 07/30/02 691+/-152 <164 <26.5 <25 <22 <22 <257 <29 <110 Lettuce 08/20/02 641+/-115 <100 <14 <9 <12 <12 <134 <18 <78 Tomatoes 09/23/02 106+/-41 <39 <6 <5 <5 <5 <50 <7 <27 Apples 09/23/02 237+/-66.8 <71 <12 <11 <9 <10 <100 <9 <46 Background (Control) Vegetation Raspberries 08/05/02 146+/-37.9 <41 <6 <6 <5 <5 <50 <7 <32 Lettuce 09/13/02 391+/-115 <126 <28 <12 <18 <17 <1 91 <23 <86 Tomatoes 10/17/02 122+/-24.8 <32 <6 <2 <4 <3 <35 <6 <24 Apples 10/17/02 134+/-53.1 <60 <11 <7 <7 <7 <73 <10 <40 Indicator Vegetation 95Zr 95Nb 58Co 54Mn 59Fe 65Zn 6OCo 40K 14OBa Red Raspberries 07/11/02 <15 <9 <8 <8 <22 <20 <7 2360+/-79.3 <20 Lettuce 07/30/02 <44 <30 <26 <28 <77 <64 <28 8330+/-297 <33 Lettuce 08/20/02 <21 <12 <12 <12 <32 <28 <12 5180+/-128 <14 Tomatoes 09/23/02 <9 <5 <5 <4 <15 <14 <6 2030+/-58.0 <6 Apples 09/23/02 <19 <11 <10 <10 <28 <22 <11 1370+/-78.7 <14 Background (Control) Vegetation Raspberries 08/05/02 <9 <5 <5 <5 <16 <13 <6 1750+/-56.5 <7 Lettuce 09/13/02 <33 <22 <18 <19 <54 <47 <24 3980+/-183 <31 Tomatoes 10/17/02 <6 <3 <3 <3 <10 <5 <4 2330+/-42.3 <5 Apples 10/17/02 <13 <8 <7 <7 <20 <18 <7 1450+/-65.5 <12 (45)

i.

3.7 External Penetrating Radiation Thermoluminescent dosimeters, (TLD's), with a minimum sensitivity of 5 millirem per 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 2002, on-site exposure ranged between 10.1 - 18.0 mrem/quarter, with an average exposure of 13.5 mrem/quarter and off-site ranged between 10.0 - 13.4 mrem/quarter with an average exposure of 11.9 mrem/quarter.

40 CFR 190 requires that the annual dose equivalent not exceed 25 millirems to the whole body of any member of the public. Using the annual average of control TLD stations as background and the highest site boundary TLD, leads to 7.9 millirem direct radiation dose to the hypothetical 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 2001 and 2002 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

Rochester Gas and Electric ,

Table 3-20 External Penetrating Radiation Thermoluminescent Dosimetry 2002 Units mrem/91 Day Quarter Location Type 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

2 - #7 plus #13 are 2 1 12.6 +/- 3.2 12.6 +/- 3.2 12.4 +/- 3.1 12.4 +/- 3.1 on-site near the line 3 1 13.1 +/- 3.3 12.9 +/- 3.2 13.7 +/- 3.4 13.1 +/- 3.3 of the highestannual 4 1 13.1 +/- 3.3 13.0 +/- 3.3 13.4 +/- 3.4 13.0 +/- 3.3 average ground level 5 1 12.7 +/- 3.2 13.4 +/- 3.4 13.7 +/- 3.5 13.7 +/- 3.5 concentration. 6 1 10.1 +/- 2.5 10.4 +/- 2.6 10.9 +/- 2.7 10.5 +/- 2.6 7 1 18.0 +/- 4.5 17.9 +/- 4.5 17.4 +/- 4.4 17.5 +/- 4.4

8-#12areoffsiteat 8 C 11.6 +/- 2.9 11.9 +/- 3.0 11.7 +/- 3.0 11.4 +/- 3.0 adistanceof8to15miles. 9 1 11.4 +/- 2.9 11.2 +/- 2.8 10.9 +/- 2.8 10.8 +/- 2.7 10 C 10.9 +/- 2.8 10.9 +/- 2.8 10.9 +/- 2.7 11.1 +/- 2.8 11 1 11.7 +/- 2.9 10.9 +/- 2.8 11.5 +/- 2.9 11.3 +/- 2.9 12 C 10.6 +/- 2.7 10.3 +/- 2.6 10.3 +/- 2.6 10.3 +/- 2.6 13 1 13.9 +/- 3.5 14.1 +/- 3.6 14.7 +/- 3.9 14.1 +/- 3.5

14-#16arelocated 14 1 12.4 +/- 3.1 11.5 +/- 2.9 13.0 +/- 3.3 12.9 +/- 3.2 along a line 3000 ft. west 15 1 13.2 +/- 3.3 13.5 +/- 3.4 14.0 +/- 3.5 13.0 +/- 3.3 of the plant. 16 1 12.6 +/- 3.2 12.8 +/- 3.2 13.2 +/- 3.3 12.9 +/- 3.3

17-#21 are located 17 1 12.2 +/- 3.1 11.6 +/- 2.9 12.3 +/- 3.1 11.8 +/- 3.0 along Lake Road. 18 1 13.5 +/- 3.4 14.0 +/- 3.5 14.0 +/- 3.5 13.9 +/- 3.5 19 1 11.8 +/- 3.0 11.7 +/- 3.0 12.7 +/- 3.2 12.3

3.1 20 1 12.1 +/- 3.0 11.9 +/- 3.0 12.7 +/- 3.2 12.5 +/- 3.1 21 1 13.0 +/- 3.3 12.8 +/- 3.2 13.6 +/- 3.4 13.4 +/- 3.4

22-#24arelocated 22 1 11.5 +/- 2.9 12.6 +/- 3.2 12.0 t 3.0 11.6 +/- 2.9 alongtheeastsite 23 1 12.4 +/- 3.1 12.3 +/- 3.1 13.3 +/- 3.3 13.1 +/- 3.3 boundary line. 24 1 12.5 +/- 3.2 12.4 +/- 3.1 13.3 .+/- 3.4 13.1 +/- 3.3

25 - #30 are offsite 25 C 10.8 +/- 2.7 13.4 +/- 3.4 10.9 +/- 2.8 10.8 +/- 2.7 atadistanceof8 26 C 11.1 +/- 2.8 10.7 +/- 2.7 11.0 +/- 2.8 11.1 +/- 2.8 to 15 miles. 27 C 11.7 +/- 2.9 11.6 +/- 2.9 12.4 +/- 3.1 11.8 +/- 3.0 28 C 11.7 +/- 3.0 12.2 +/- 3.1 12.0 +/- 3.0 12.2 +/- 3.1 29 C 11.4 +/- 2.9 10.7 +/- 2.7 11.4 +/- 2.9 11.2 +/- 2.8 30 C 10.3 +/- 2.6 10.0 +/- 2.5 10.3 +/- 2.6 10.3 +/- 2.6

31 - #40 are located 31 1 12.6 +/- 3.2 11.7 +/- 2.9 13.4 +/- 3.4 12.9 +/- 3.3 in an arcata distance 32 1 11.7 +/- 2.9 11.0 +/- 2.8 11.2 +/- 2.8 10.3 +/- 2.6 of 4-5 miles. 33 1 10.9 +/- 2.7 11.1 +/- 2.8 11.1 +/- 2.8 11.4

2.9 34 1 12.1 +/- 3.1 12.5 +/- 3.1 13.1 +/- 3.3 12.6 +/- 3.2 35 1 12.6 +/- 3.2 12.8 +/- 3.2 13.8 +/- 3.5 12.5 +/- 3.2 36 1 11.3 +/- 2.8 10.8 +/- 2.7 11.6 +/- 2.9 11.4 +/- 2.9 37 1 11.0 +/- 2.8 10.1 +/- 2.5 10.4 +/- 2.6 10.3 +/- 2.6 38 1 12.3 +/- 3.1 12.5 +/- 3.2 12.7 +/- 3.2 12.8 +/- 3.2 39 1 12.0 +/- 3.0 11.8 +/- 3.0 12.7 +/- 3.2 12.1 +/- 3.1 40 1 10.2 +/- 2.6 10.8

2.7 10.9 +/- 2.8 10.4 +/- 2.6 (47)

Rochester Gas and Electric Figure 3-21 (48)

S.

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 2002. The land use remains mainly agricultural in nature. There were several new private home developments. The three dairy operations nearest to the plant began the year in operation with 40 to 70 milk cows. Molino Farm ceased commercial operation early in 2002. There are no goats raised for human consumption of milk or meat within the five mile radius. Beef cattle are still raised on 3 farms within 5 miles of the plant as in past years.

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

A copy of the Land Use Census that was completed in September 2002 is attached.

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

5.0 EXTERNAL INFLUENCES During 2002, there were no external influences such as atmospheric weapons testing or accidents at other nuclear facilities which had an impact on the data.

49

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

None Milk animal locations:

No new milk producing animals identified in 2002 Census. I Milk farm formerly at 5230 m SSE is no longer in business as of 3/1/02.

UFSAR change request: Y N x Land Use Census Completed by: 9, Date: __ _3____

Reviewed b Date: l/0 /'d Page 50

Map 24 (51)

CO4-

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. Framatome, ANP, performed tritium analyses during 2002 for JAFEL. 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 ANRC@ 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

i.a 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.lA, 6.1 B, 6.1 C and 6.1 D 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 2002, there were two analysis that were found outside of the LCL and UCL, beta analysis and Cr-51 (Figures 6.1A, QC-3, 6.1C and 6.1C, QC-6). JAFEL was unable to identify systematic error or programmatic deficiency for either analysis.

Beta Non-conformitv A beta water sample was received from Analytics, Inc. and was analyzed in accordance with standard laboratory procedures. The result for beta was determined to be outside the QA Acceptance Criteria.

An evaluation of the beta result was performed. Results were examined with no abnormalities identified. Upon request from Ginna Station, the sample was re-analyzed by JAFEL. The sample result was 283 pCi/L with a known value of 280 pCi/L. With an error resolution of 20, the comparison ratio is 1.01. This is acceptable within the ratio of agreement limits of 0.75 to 1.33. However, the cause of the initial poor analytical results for this sample was not determined. It is suspected that there may have been a loss of sample in the transfer from lab ware to counting planchet.

Confidence in the accurate analysis of beta can be easily demonstrated by other beta analytical results both in the sample results for the 2002 QA program and historical QA results. No corrective actions were implemented as a result of this non-conformity.

Cr-51 Non-conformity A spiked mixed gamma in an air filter 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. Eight of the nine radionuclides were quantified within the acceptable range.

The result for Cr-51 was determined to be outside the QA Acceptance Criteria.

An evaluation of the 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 27.7day 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-51.

The combination of the 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 air filter samples or other environmental media.

Confidence in the accurate analysis of Cr-51 can be easily demonstrated by other Cr-51 analytical results both in the sample results for the 2002 QA program and historical results.

54

A review of historical QA data for 2001 was also performed to determine if this is a recurring systematic error or bias. In 2001, numerous QA samples were analyzed which contained Cr-51. The mean ratio for these samples relative to the Known (reference)

Value is 0.99. There were two Cr-51 non-conformities in the 2001 Crosscheck Program and were determined not to be systematic or programmatic errors. The historic Cr-51 non-conformities were a low percentage of the overall gamma spectroscopy QA program and have determined to be the result of the low sample activity and low gamma yields for Cr-51 in the spiked samples. Analytical methods and system calibrations are not the cause for this non-conformity, based on the accurate results achieved for the analysis of the other eight radionuclides present in the sample. No corrective actions were implemented as a result of this non-conformity.

55

Figure 6A Trend of BindSSiked War SaNmpes 1.50a 1AO0 1.30 1201 A A

0 1.10A*.1

° CL 1.00s 0.80 0.701 0.60C I boba Mrtm Cesl4l Cr561 jC-134 jCs-137 jMn-54jFe-.69 Zn.65CO.60 CO.88j -131 UCL 1.33 .3.33 1.33 . 13 13 . 13 1.3 1.33 1.33 1.3 C-1 1.08 1.11 0.76 0.99 1.02 A QC-2 0.7 1.00 1.03 1.18 0.89 0.94 1.08 1.13 1.03 0.98 97

QC-3 0.66 1.00 1.05 0.95 0.87 0.96 1.08 1.01 os 1.03 098 C4 089 0.85 1.01 0.95 1.00 CC-5 0.94 0.88 1.05 1.07 0.97 oe 1.07 1.06 1.04 0.95 102 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 0.75 56 C05

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~. ..

Figure &1B Tren of Bind Sk Mik Swles 1.50 IAO 1.30 120

-3 1.10 U* A 80 A A

-C A A U 0 0.90 A 0~~~~~~~

0.80 0.70 0.60 0.50 .

-UCL 1.33 1. 3 1.33 1.33 13 .33 13 13 .33 1.33

QC-1 0.97 1.05 0.90 0.94 1.06 1.06 099 96 0.99 A C-2 0.99 1.02 094 0.99 1.00 1.06 10 0.97 0.95 089

QC-3 0.99 0.78 o89 0.96 1.06 1.08 0.95 0.96 1.04 0.90 C 0.95 0.95 QB83 0.2 1.06 1.07 Om9 Q.98 OAS 0.93

- LCL 0.75 0.75 0.75 0.7555 0.75 Q75 0.75 0.75 57

Figure 6.1C Trend of Blind Spiked Filter Sampes 1.50 1.40 1.30 1.20

1.10

A E 0.90 A 0.80 0.70 0.60 beta Ce.141 Cr-61 Cs-134 Cs-137 N-4 F.9 Zn65 Co-6 Co-5 1-131

_ UCL 133 133 1.33 133 133 133 33 1 133 133 1.33

QC-1 0.92 0.99 1.04 0.96 A QC-2 1.04 0.97 0.92 0.89 .99 1.04 1.11 1.02 .98 0.99 0.92

QC-3 1.01 1.00 O.89 0.96 1.00 1.07 0.96 1.13 0.98 1.06

QC4 0.95 1.08 1.11 1.03 1.16 120 129 124 1.05 1.19 1.02 x QC-5 0.90 1.04 1.11 1.00

QC61 0.98 0.66 0.90 0.93 1.02 0.94 1.20 0.99 0.94 LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 58 IcLol

Figure 1D Trerd of Elind SpHod SolWegstation Samples =

1.I U Ifi -L 130-

.I. U 1.10ZU a A 1.10 E A A n A I AS 12 0

CL 1.00z A E

0.

0 Q0.,0 Q0. t 0.70.

0.60 EIRA 0.50 - - - -- -- - -

C-141 Cr-51 Co134 C9137 Mn-54 Zn-65 UCL 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.33

QC-1 1.20 1.16 .96 1.05 1.09 1.07 1.09 0.92 0.87 .

A QC-2 1.11 1 1.09 16 1.15 1.09 1.07 1.06 1.08 LCL 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 D

=

59 "I............ ..._

Figure 6.2A Trend of QC Blind Spiked TLDs 025 0.20 02 015 0

.{ 0.10 0.05

0.00 mrom

- UCL 020 020 020 0.20

QC-1 0.05 A QC-2 __0.04

C-3 _ 0.16

C4 0.03 6.2 INTRALABORATORY BLIND SAMLE COMPARISON A Laboratory's use of in-house quality control spiked samples provides a means for verifying measurement accuracy for analyzing environmental sample media. In 2002, Ginna Station implemented field spiked environmental TLDs by irradiating TLDs with a Cs-137 source to a known dose. The spiked TLDs were placed in the field and processed with each quarter's environmental TLDs. The reported dose was background corrected, using the average of the field control TLDs. The reported dose and delivered dose are used to calculate a perfornance quotient ((reported - delivered)/delivered) for each TLD within the set of spiked TLDs. The performance bias is the average of the performance quotients. The standard deviation of bias is the standard deviation of the performance quotients. For the set of spiked TLDs a performance criteria is calculated by adding the performance bias and standard deviation of the bias. The performance criteria limit was established to be 0.20. Spike performance criteria of less than 0.20 validate the TLD processing at Ginna Station. All blind TLD performance criteria for year 2001 were less than 0.20. Figure 6.2A displays the spike TLD performance criteria.

60

__Ocq

6.3 AUDIT OF CONTRACT LABORATORY Ginna Station Quality Assurance personnel conducted an audit of the ODCM and REMP during the period of January 28, 2002 to March 28, 2002, Audit report AINT-2002-0001-JMT. A strength was identified with the forrriat and function of the Offsite Dose Calculation Manual. Two concerns were identified in the audit with three deficiencies. None of the areas for improvement identified in the report were related to the JAFEL. There were no surveillances performed at the JAFEL in 2002.

Surveillance is required every three years and was performed in 2001 in the following six areas: Control of MT&E, Control of Records/Documents, Control/Adequacy of Sampling and Analysis, Qualification/Training of Personnel, Shipping and Storage of Samples, and Quality Program Controls. The surveillance report indicated that the JAFEL functioned in an acceptable manner and was rated satisfactory with respect to all six areas.

61

I ' 1 7.0 DEVIATIONS FROM SCHEDULE Two items reportable in the Annual Environmental Radiological Operating Report under procedure CHA-RETS-VARIATION were reported as follows:

1. Environmental Air Sample Station (ES) # 8 found off 3/11/02. Trouble card issued for repair. Sample period was 73.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

2. ES #5 found on 10/01/02 with hose barb broken. No sample results for week of 9/23/02 - 9/30/02. Returned to service 10/01/02.

In addition to these deviations, two 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 62

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