Text

R. E. Ginna Nuclear Power Plant - Annual Radioactive Effluent Release and Radiological Environmental Operating Reports
	ML081410051
Person / Time
Site:	Ginna
Issue date:	05/12/2008
From:	John Carlin; Constellation Energy Nuclear Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML081410051 (97)
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John Carlin Site Vice President 0Constellation Energy" Nuclear Generation Group R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.5200 585.771.3943 Fax John.carlin

@constellation.com May 12, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 Annual Radioactive Effluent Release and Radiological Environmental Operating Reports Ladies and Gentlemen:

R. E. Ginna Nuclear Power Plant, LLC is pleased to submit the enclosed Annual Radioactive Effluent Release and Annual Radiological Environmental Operating Reports, prepared in accordance with Technical Specification Section 5.6.3 and Technical Specification 5.6.2, respectively.

Should you have questions regarding the enclosed documents, please contact Tom Harding at (585) 771-3384.

Enclosures:

Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report cc: S. J. Collins, NRC D. V. Pickett, NRC Resident Inspector, NRC 160(q&5 State Emergency Management Office Building #2, First Sublevel State Campus Albany, NY 12226-5000 Attn: Jay Dunkleberger NYS Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Attn: Paul Eddy American Nuclear Insurers 95 Glastonbury, Blvd.Glastonbury, CT 06033 Attn: Thomas Wolff INPO 700 Galleria Parkway Atlanta, GA 30339-5957 2007 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 TABLE OF CONTENTS

1.0 INTRODUCTION

..............................................................................

4 2.0 SUPPLEMENTAL INFORMIATION........................................................

4 2.1I Regulatory Limits..............................................................................

4 22 EfflUent Air and Water Concentrations......................................................

6 2.3 Release Rate Limits ...........................................................................

6 2.4 Measurements and Approx imat ions of Total Radioactivity

...............................

6 2.5 Batch Releases .................................................................................

7 2.6 Abnormal Releases ............................................................................

7 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS............................

8 4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS...............................

8 5.0 SOLID WASTF .................................................................................

8 6.0 LOWER LIMIT OF DETECTION

..........................................................

8 7.0 RADIOLOGICAL IMPACT..................................................................

9 8.0 METEOROLOGICAL DATA...............................................................

10 9.0 LAND USE CENSUS CHANGES...........................................................

10 10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL.................

10 11.0 CHANGES TO THlE PROCESS CONTROL PROGRAM .............................

10 12.0 MAJOR CHANGES TO THE RAD WASTE TREATMENT SYSTEMS ............

10 13.0 INOPERABLE MONITORS ...............................................................

10 t 14.0 GROUNDWATER SAMPLING RESULTS...............................................

10 15.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS....10 2

LIST OF TABLES Table IA Gaseous Effluents

-Summation of all Releases........................................11I Table 2A Liquid Effluents

-Siummation of all Releases...........................................

13 Table 11B Gaseous Effluents

-Continuous and Batch Releases.................................15.

Table 2B Liquid Effluents

-Continuous and Batch Releases ....................................

17 Table 3 Solid Waste and Irradiated Fuel Shipments

......................................

....... 19 Table 4A Radiation Dose to Nearest Individual Receptor from Gaseous Releases ...........

20 Table 4B Radiation Dose to Nearest Individual Receptor from Liquid Releases ............

24 Table 5 Groundwater Sampling Results...........................................................

25 3

1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is for the 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 1L 2007 through December 3 1, 2007.This report includes a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R. E. Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM).2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM limits applicable to the release of radioactive material in liquid and gaseous effluents are: 2.1.1 Fission and Activation Gases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate which would yield < 500 rnrem/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 flowing: (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.

4 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 8 clays 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 rnrem 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 10 CFR 20, as explained in Section I of the ODCM. For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2E-04 uCi/ml.The dose or dose committed 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 < L.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 and .organ.5 2.2 Effluent Air and Water Concentrations 2.2.11 For gaseous effluents, effluent concentration limits are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary, in accordance with Technical Specification 5.5.4.g.2.2.2 For liquid effluents, ten times the effluent concentration values specified in 10 CFR 20, 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 uiCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.

2.3 Release Rate Limits The release rate limits for fission and activation gases from the R. E. Ginna Nuclear Power Plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable.

However the 2007 average beta/gamma energy of the radionuclide mixture in fission and activation gases released from Ginna 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 laboratory.

Tritium and alpha 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.6 2.5 Batch Releases 2.5.1 Liquid 1. Number of batch releases:

1.17 E+02 2. Total time period for batch releases:

1.06 E+06 min 3. Maximum time period for a batch release: 4.47 E+04 min 4. Average time period for batch releases:

9.06 E+03 min 5. Minimum time period for a batch release: 8.00 E+00 min 6. Average blowdown (LPM) during periods of effluent 4.34 E+02 lpm release into the discharge canal: Gaseous 1. Number of batch releases:

4.50 E+0l 2. Total time period for batch releases:

5.30 E+05 min 3. Maximum time period for a batch release: 4.46 E+04 min 4. Average time period for batch releases:

1.18 E+04 min 5. Minimum time period for a batch release: 2.60 E+01 rmin 2.5.2 2.6 Abnormal Releases There were no abnormal or unplanned releases in 2007. Examples of ventilation system deficiencies that could result in small quantities of air exiting controlled areas by pathways other than monitored vent exhaust have been documented by the corrective action process. Sampling did not result in any measured radioactivity.

Gaseous release permit methodology is conservative against small deviations in flow direction, if activity were present.7 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables IA and [B. Plant Vent and Containment Vent releases are modeled as mixed mode and Air Ejector is modeled as ground level release. In 2005, Ginna revised gaseous release procedures to remove the unrealistically conservative step of including sample activity that was less than the Minimum Detectable Activity, MDA, (which is the calculated o posteriori LLD for each sample counted), as if it were actually a measured value. This conservatism had been included in procedures years ago to account for sample purges and valve leakage which have since been demonstrated to be dramatically lower than the conservative estimate.

Any leaks or purges with measurable activity are now included in release permits by integration of Radiation Monitoring System (RMS)data. This change has resulted in lower total reported activity in gaseous effluents for 2007 as compared to years prior to 2005.4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.5.0 SOLID WASTE The quantities of radioactive material released in shipments of solid waste transported from the site during the reporting period are summarized in Table 3.Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type. The majority of Dry Active Waste is processed utilizing an off-site processor who reduces the volume and then sends the waste for burial.6.0 LOWER LIMIT OF DETECTION The required Lower Limit of Detection, (LLD), as defined in the ODCM, was met for all samples used in reporting effluent releases for 2007.All samples also met the a posteriori Minimum Detectable Activity (MDA).8 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 close 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 historical meteorological conditions considering the noble gas exposure, inhalation, ground plane exposure, and ingestion pathways.

The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cow's milk, and cow meat pathways.

Results of this assessment are presented in Tables 4A and 4B. Since September I t, 2001, Ginna Security has been augmented by full-time presence of the New York State Police and the New' York National Guard. These personnel have posts within the site boundary.

For this reason, the exposure and uptake pathways for 2007 are calculated using meteorological dispersion and deposition parameters at onsite posts, as well as at the site boundary.7.1 Total Dose 40 CFR 190 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 exposure and uptake pathways, the maximum liquid pathways, and the direct radiation measurements onsite in the vicinity of the National Guard outpost, yield the following dose summaries to the maximally exposed individual member of the public onsite.2.60E+00 mrem total body (2.60E+00 mrem direct radiation plus 4.8 IE-03 mrem all other pathways).

4.86E-03 mrem GI-LLI (maximum organ dose).Using the maximum exposure and uptake pathways, the maximum liquid pathways, and the direct radiation measurements at the site boundary, yield the following dose summaries to the hypothetical maximally exposed individual member of the public offsite. This dose conservatively bounds any real member of the public.6.00E+00 mrem total body (6.OOE+00 mrem direct radiation plus 4.8 tE-03 .raem all other pathways).

4.86E-03 mrem GI-LLI (maximum organ dose).9 8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2007 is not included with this report, but can be made available at the R. E. Ginna Nuclear Power Plant.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 are being built at consistent rate compared to past years.10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were no changes to the ODCM during the reporting period.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 THE RADWASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.13.0 INOPERABLE MONITORS No gaseous effluent monitors were inoperable for greater than 7 days in 2007.14.0 GROUNDWATER SAMPLING RESULTS No inadvertent releases to groundwater occurred during 2007. Sample results are included in Table 5.15.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS None 10 R. E. Ginna Nuclear Power Plant Table I A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES January -June 2007 Unit Quarter Quarter Est. Total A. Fission & Activation Gases 1_ _ 2'id Error, %I. Total release Ci 1.82E-01 4.32E-01 1.50E+01 2. Average release rate for period uCi/sec 2.34E-02 5.50E-02 3. Percent of Technical Specification limit % 3.71E-05 8,73E-05 B. lodines I. Total iodine-131 Ci 2. Average release rate for period uCi/sec 3. Percent of Technical Specification limit q C. Particulates

1. Particulates with half-lives

> 8 days Ci 2. Average release rate for period .uCi/sec 3. Percent of Technical Specification limit %4. Gross alpha radioactivity Ci D. Tritium I. Total release Ci 7.39E+00 7.47E+00 9.20E+00 2. Average release rate for period juCi/sec 9.50E-01 9.49E-01 3. Percent of Technical Specification limit % 1. 12E-04 1.12E-04 Note: Isotopes for which no value is given were not identified in applicable releases.II R. E. Ginna Nuclear Power Plant Table IA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES July -December 2007 Unit Quarter Quarter Est. Total A. Fission & Activation Gases 3 id 4 ih Error, %1. Total release Ci 2.89E-01 3.03E-0l 1.50E+01 2. Average release rate for period uCi/sec 3.63E-02 3.8 1 E-02 3. Percent of Technical Specification limit ____ 5.76E-05 6.05E-05 B. lodines 1. Total iodine- 131 Ci 2. Average release rate for period uCi/sec 3. Percent of Technical Specification limit %C. Particulates I. Particulates with half-lives

> 8 days Ci 2. Average release rate for period uCi/sec 3. Percent of Technical Specification limit %__4. Gross alpha radioactivity Ci D. Tritium I. Total release Ci 7.29E+00 5.80E+00 9.20E+00 2. Average release rate for period uCi/sec 9.17E-01 7.30E-01 3. Percent of Technical Specification limit % 1.08E-04 8.59E-05 Note: Isotopes for which no value is given were not identified in applicable releases.12 R. E. Ginna Nuclear Power Plant Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES January -June 2007 A. Fission & Activation Products Unit Quarter Quarte Erst. Total Error, % I I. Total release (not including tritium, Ci 5.65E-03 9.24E-03 9.90E+00 gases, alpha)2. Average diluted concentration during uCi/ml 1.30E- I I 1.82E- I I period 3. Percent of applicable limit _ 4.45E- 12 3.80E- 12 B. Tritium 1. Total release Ci 2.73E+01 1.85E+02 9.20E--+00

2. Average diluted concentration during uCi/ml 6.3 1 E-08 3.64E-07 period 3. Percent of applicable limit _ 7__ 3.16E-0I 1.82E+00 C. Dissolved and entrained gases I. Total release Ci 1.37E-04 9.90E+00 2. Average diluted concentration during uCi/mI 2.70E- 13 period .3. Percent of applicable limit .. .._% 1.35E-07 D. Gross alpha radioactivity I. Total release Ci Note: Isotopes for which no value is given were not identified in applicable releases.13 R. E. Ginna Nuclear Power Plant Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES July -December 2007 Unit Quarter Quarter Est. Total A. Fission & Activation Products 3 id 4 Th Error, %I. Total release (not including tritium, Ci 7.02E-03 8.72E-05 9.90E+00 gases, alpha)2. Average diluted concentration during uCi/ml 1.37E- I I 1.78E- 13 period 3. Percent of applicable limit _3.74E- 12 9.38E- 13 B. Tritium 1. Total release Ci 1.63E+02 3.89E+01 9.20E+00 2. Average diluted concentration during uCi/ml 3.19E-07 7.93E-08 period 3. Percent (if applicable limit % .60E+00 3.97E-0t C. Dissolved and entrained gases 1, Total release Ci 3.36E-05 9.90E+00 2. Average diluted concentration during uCi/ml 6.55E- 14 period ....3. Percent of applicable limit % 3.27E-08 D. Gross alpha radioactivity F. Total release Ci E. Volume of waste released (prior to Liters 9.66E+07 I .0IE+08 dilution)F. Volume of dilution water used during Liters 5.12E+1 I 4.91 E+ I1 period Note: Isotopes for which no value is given were not identified in applicable releases.14 R. E. Ginna Nuclear Power Plant TFable lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS

-CONTINUOUS AND BATCH RELEASES January -June 2007 Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides released Unit I lid 1. Fission Gases Argon-41 Ci 7.1OE-02 "6.93E-02 Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon- 131 m Ci 9.84E-04 Xenon- 133 Ci 1. 1 OE-0 I 3.59E-0 I Xenon- 133m Ci 4.33E-04 Xenon- 135 Ci 8.23E-04 2.07E-03 Xenon- 135m Ci Xenon-138 Ci Others (specify)

Ci Xenon- 135 Ci Ci Ci Total for period Ci 0.OOE+00 0.OOE+00 1.82E-01 4.30E-01 2. lodines Iodine-131 Ci Iodine- 132 Ci Iodine- 133 Ci Total for period Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium- 134 Ci Cesium- 137 Ci Niobium-95 Ci Cobalt-58 Ci Cobalt-60 Ci Others (specify)

Ci Total for period Ci 0.OOE+00 0.OOE+00 0OE+00 0.00E+)0 Note: Isotopes for which no value is given were not identified in applicable releases.15 R1. E. Ginna Nuclear Power Plant Table IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS

-CONTINUOUS AND BATCH RELEASES July -December 2007 Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides released Unit 3 1II 411 Y" 4'11 1. Fission Gases Argon-41 Ci 7-20E-02 7.36E-02 Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon- 131 m Ci Xenon-133 Ci 2.15E-0I 2.28E-0I Xenon-133m Ci Xenon- 135 Ci 1.7 1 E-03 1.77E-03 Xenon-135m Ci Xenon-138 Ci Others (specify)

Ci Ci Ci Ci Total for period Ci 0.OOE+00 O.O0E+00 2.89E-0 1 3.03E-0 1 2. lodines Iodine- 131 Ci lodine- 132 Ci Iodine- 133 Ci .... .. ._Total for period Ci 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Niobium-95 Ci Cobalt-58 Ci Cobalt-60 Ci Zirconium-95 Ci Total for period Ci 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Note: Isotopes for which no value is given were not identified in applicable releases.

R. E. Ginna Nuclear Power Plant Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS

-CONTINUOUS AND BATCH RELEASES January -June 2007 Continuous[

Mode Batch MIode Quarter QUarter Quarter Quarter Nuclides released Unit It_ 2 7 d + 2'ld Nuclide Chromium-5 I Ci Manganese-54 Ci Iron-55 Ci Cobalt-57 Ci Cobalt-58 Ci 3.96E-04 3.09E-04 Iron-59 Ci Cobalt-60 Ci 2.64E-05 5.01 E-05 Zinc-65 Ci Stronium-89 Ci Stronium-90 Ci Niobium-95 Ci 6.13E-06 Zirconium-95 Ci Molybdenum-99 Ci Silver- I 10m Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci 1.98E-05 Iodine- 131 Ci Iodine- 132 Ci Tellerium-132 Ci Cesium-134 Ci Iodine- 135 Ci Cesium- 136 Ci Cesium- 137 Ci Barium/Lanthanum-140 Ci Cerium- 141 Ci -Tellerium-123m Ci 4.07E-05 5.74E-05 Tellerium-125m Ci 5.18E-03 8.80E-03 Total for period Ci 0.OOE+00 0.OOE++/-0) 5.65E-03 9.24E-03 Xenon- 133 Ci _[1.37E-04 Xenon- 135 CiI Note: Isotopes for which no value is given were not identified in applicable releases.17 R. E. Ginna Nuclear Power Plant Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS

-CONTINUOUS AND BATCH RELEASES July -December 2007 Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides released Unit 3`d 4t" 3' 41 Nuclide Chrorniuin-5 I Ci Manganese-54 Ci Iron-55 Ci Cobalt-57 Ci Cobalt-58 Ci 9.78E-05 3.57E-05 hron-59 Ci Cobalt-60 Ci 4.88E-05 5.15E-05 Zinc-65 Ci Stronium-89 Ci Stronium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Silver- IlOin Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci Iodine- 131 Ci Iodine- 132 Ci 1.42E-04 Tellerium-132 Ci 1.64E-04 Cesium- 134 Ci Iodine-135 Ci Cesium-136 Ci CesiuIm-137 Ci Barium/Lanthanum-140 Ci Cerium-141 Ci-Tellerium-123m Ci 3.22E-05 Tellerium-125m Ci 6.85E-03 Total for period Ci 0.OOE+00 O.OOE+00 7.03E-03 8.72E-05 Xenon-133 Ci 3.36E-05 Xenon- 135 Ci Note: Isotopes for which no value is given were not identified in applicable releases.18 Table 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 2007 -December 31, 2007 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL -(Not irradiated fuel)1. Type of waste Unit 12 month period Est. total Error %a. Spent resins, filter sludges, m'3 8.42E+01 7.OOE+00 evaporator bottoms, etc. Ci 8.21 E+01 1.40E+01 b. Dry compressible waste, m 3 2.19E+02 7.00E+00 contaminated equip, etc. Ci 2.39E-02 1.40E+01 c. Irradiated components, control m 3 None N/A rods, etc. Ci d. Other: Condensate Cooler m 3 8.72E+00 7.OOE+00 Ci 1.42E-03 1.40E+01 2.Estimate of major nuclide composition (by type of waste)a. b. d. (None)Co-58 % 1.30E-01 Fe-55 % 2.54E+01 Co-60 % 3.66E+01 Ni-63 % 7.12E+01 Co-58 % 1.49E+01 Ni-63 % 5.84E+01 Co-60 % 1.19E+01 Ni-63 % 2.54E+01 Ag-110m % 5.OOE-01 Cs-137 % 3.85E+00 Cr-51 % 2.07E+00 Cs-137 % 2.50E+00 Fe-55 % 1.1OE+01 Co-60 % 2.35E+01 Ce-144 % 2.OOE+00 Sb-125 % 3.90E-01 Zr-95 % 7.90E-01 %Ce-144 % 3.OOE-02 Ag-110m % 1.71E+00 %Mn-54 % 3.50E-01 Cs-137 % 2.02E+00 %Aq-110m % 3.00E-03 Sb-125 % 8.30E-01 %H-3 % I1.50E-01 H-3 % 7.90E-01 I%Total 9.90E+01 Total 9.74E+01 jf Total 1.00E+02 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1.OOE+00 Sole Use Truck Barnwell, SC 4.OOE+00 Sole Use Truck Duratek, TN 2.OOE+00 Sole Use Truck Studsvik, TN 1.OOE+00 Sole Use Truck Toxco, TN IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A B.19 R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor First Quarter 2007 (Units in rem)Al! All Adult Teen Child Infant Noble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta N 1.90E-09 9.51E-10 NNE 1.59E-09 7.97E-10 NE 1.84E-09 9.19E-10 ENE 2.33E-09 1.17E-09 E 4.24E-09 2.12E-09 2.06E-07 2.26E-07 3.1OE-07 1.35E-07 ESE 5.40E-09 2.70E-09 2.63E-07 2.87E-07 3,94E-07 1.72E-07 SE 3.27E-09 1.63E-09 1.59E-07 1.74E-07 2,39E-07 1.04E-07 SSE 1.35E-09 6.73E-10 6.55E-08 7.16E-08 9.84E-08 4.28E-08 S 2.36E-09 1.18E-09 1.15E-07 1.25E-07 1.72E-07 7.49E-08 SSW 2.36E-09 1.18E-09 1.15E-07 1.25E-07 1.72E-07 7.49E-08 SW 2.36E-09 1.18E-09 1.15E-07 1.25E-07 1.72E-07 7.49E-08 WSW 2.51 E-09 1.26E-09 1.22E-07 1.33E-07 1.83E-07 7.99E-08 W 1.60E-09 7.99E-10 7.77E-08 8.49E-08 1.17E-07 5.08E-08 WNW 1.35E-10 6.75E-11 NW 4.42E-10 2.21E-10 NNW 1.38E-09 6.92E-10 IMaximumrn 5'40E-09 2.70E-09 2.626E-07 2.869E-07 3.944E-07 1.718E-07 20 R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor Second Quarter 2007 (Units in rem)All All Adult Teen Child Infant INoble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta N 2.11EE-09 1.66E-09'NNE 1.76E-09 1.39E-09 NE 2.03E-09 1.60E-09 ENE 2.58E-09 2.04E-09 E 4.70E-09 3.70E-09 2.08E-07 2.28E-07 3.14E-07 1.37E-07 ESE 5.98E-09 4.71 E-09 2.65E-07 2.90E-07 3.99E-07 1.74E-07 SE 3.62E-09 2.85E-09 1.60E-07 1.76E-07 2.41E-07 1.05E-07 SSE 1.49E-09 1.17E-09 6.61E-08 7.24E-08 9.96E-08 4.34E-08 S 2.61E-09 2.05E-09 1.16E-07 1.27E-07 1.74E-07 7.60E-08 SSW 2.61 E-09 2.05E-09 1.16E-07 1.27E-07 1.74E-07 7.60E-08 SW 2.61E-09 2.05E-09 1.16E-07 1.27E-07 1.74E-07 7.60E-08 WSW 2.78E-09 2.19E-09 1.23E-07 1.35E-07 1.86E-07 8.1OE-08 W 1.77E-09 1.39E-09 7.84E-08 8.59E-08 1.18E-07 5.15E-08 WNW 1.50E-10 1.18E-10 NW 4.90E-10 3.86E-10 NNW 1.53E-09 1.21 E-09 Maximum 5.98E-09 4.71 E-09 2.65E-07 2.90E-07 3.99E-07 1.74E-07 21 R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor Third Quarter 2007 (Units in rem)All All Adult Teen Child Infant Noble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta N 2.03E-09 1.26E-09 NNE 1.70E-09 1.06E-09 NE 1.96E-09 1.22E-09 ENE 2.49E-09 1.55E-09 E 4.54E-09 2.82E-09 2.03E-07 2.22E-07 3.06E-07 1.34E-07 ESE 5.77E-09 3.59E-09 2.59E-07 2.83E-07 3.89E-07 1.70E-07 SE 3.49E-09 2.17E-09 1.57E-07 1.71 E-07 2.35E-07 1.03E-07 SSE 1.44E-09 8.95E-10 6.46E-08 7.06E-08 9.71 E-08 4.25E-08 S 2,52E-09 1.57E-09 1.13E-07 1.23E-07 1.70E-07 7.43E-08 SSW 2.52E-09 1.57E-09 1.13E-07 1.23E-07 1,70E-07 7.43E-08 SW 2.52E-09 1.57E-09 1.13E-07 1.23E-07 1.70E-07 7.43E-08 WSW 2.68E-09 1.67E-09 1.20E-07 1.32E-07 1.81 E-07 7.92E-08 W 1.71E-09 1.06E-09 7.66E-08 8.37E-08 1,15E-07 5.04E-08 WNW 1.44E-10 8.98E-11 NW 4.73E-10 2.94E-10 NNW 1.48E-09 9.20E-10 Maximum 5.77E-09 3.59E-09 2.59E-07 2.83E-07 3.89E-07 1.70E-07 22 R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor Fourth Quarter 2007 (Units in rem)All All Adult Teen Child Infant Noble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta N 2.09E-09 1.31 E-09 NNE 1.75E-09 1.1OE-09 NE 2.01E-09 1.27E-09 ENE 2.56E-09 1.61E-09 E 4.65E-09 2.93E-09 1.62E-07 1.77E-07 2.43E-07 1.06E-07 ESE 5.92E-09 3.73E-09 2.06E-07 2.26E-07 3.1OE-07 1.35E-07 SE 3.58E-09 2.26E-09 1.25E-07 1.37E-07 1.87E-07 8.16E-08 SSE 1.48E-09 9.30E-10 5.14E-08 5.63E-08 7.72E-08 3.36E-08 S 2.58E-09 1.63E-09 8.98E-08 9.85E-08 1.35E-07 5.88E-08 SSW 2.58E-09 1.63E-09 8.98E-08 9.85E-08 1.35E-07 5.88E-08 SW 2.58E-09 1,63E-09 8,98E-08 9.85E-08 1.35E-07 5.88E-08 WSW 2.75E-09 1.73E-09 9.57E-08 1.05E-07 1.44E-07 6.27E-08 W 1.75E-09 1.10E-09 6.09E-08 6.68E-08 9.16E-08 3.99E-08 WNW 1.48E-10 9.33E-11 NW 4.85E-10 3105E-10 NNW 1.52E-09 9.56E-10 Maximum 5.92E-09 3.73E-09 2.06E-07 *2.26E-07 3.10E-07 1.35E-07 23 R. E. Ginna Nuclear Power Plant Table 4B Radiation Dose to Maximum Individual Receptor From Liquid Release 2007 (Units in rem)Adult Teen I Child Infant First Quarter Total Body 1.86E-07 1.32E-07 2.48E-07 2.40E-07 GI-LLI 2.35E-07 1.70E-07 2.64E-07 2.41E-07 Thyroid 1.88E-07 I1.34E-07 2.51 E-07 2.40E-07 Second Quarter Total Body 1.08E-06 7.65E-07 1.44E-06 1i.40E-06 GI-LLI 1.14E-06 8.10E-07 1.46E-06 1.40E-06 Thyroid 1.08E-06 7.65E-07 1.44E-06 1.40E-06 Third Quarter Total Body 9.55E-07 6.75E-07 1.27E-06 1.23E-06 GI-LLI 1.00E-06 7.10E-07 1.29E-06 1.24E-06 Thyroid 9.55E-07 6.75E-07 1.28E-06 1'.23E-06 Fourth Quarter Total Body 2.37E-07 1.67E-07 3.15E-07 3.06E-07 GI-LLI 2.37E-07 1.67E-07 3.15E-07 3.06E-07[Thyroid 2.37E-07 I1.67E-07 13.15E-07 3.06E-07 24 R. E. Ginna Nuclear Power Plant Groundwater Sampling Results Table 5 LOCATION Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater by Butler Bldg.Groundwater IFFSI work Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Groundwater SE of CSB Pond Pond Pond Pond Pond Pond Pond I DATE SAMPLED , Tritium pCi/L 01/16/07 *02/07/07 *03/29/07 *04/26/07 *05/31/07 *06/26/07 07/31/07 *08/15/07 *09/25/07 *10/28/07 *11/29/07 12/20/07 *08/15/07 01/16/07 02/02/07 *03/29/07 04/26/07 *05/31/07 06/26/07 07/31/07 08/15/07 *09/26/07 10/28/07 11/29/07 12/20/07 01/16/07 *03/29/07 *04/26/07 *05/08/07 *05/31/07 *08/15/07 *10/28/07 *Screen House West 01/16/07 Screen House West 03/29/07 Screen House West 04/26/07 Screen House West 05/31/07 Screen House West 06/26/07 Screen House West 07/31/07 Screen House West 08/15/07 Screen House West 09/25/07 Screen House West 10/28/07 Screen House West 11/29/07* All results are <500 pCi/L unless otherwise shown 25 R. E. Ginna Nuclear Power Plant Groundwater Sampling Results Table 5 continued I LOCATION Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F Storm Drain F lIZE DATE SAMPLED 01/16/07 02/02/07 03/29/07 04/26/07 05/31/07 06/26/07 07/31/07 08/15/07 09/25/07 10/28/07 11/29/07 12/20/07 Tritium pCi/L Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain G Storm Drain H Storm Drain H Storm Drain H Storm Drain H Storm Drain H Storm Drain H Storm Drain H Storm Drain I Storm Drain I Storm Drain I Storm Drain I Storm Drain I Storm Drain I Storm Drain I Storm Drain I Storm Drain I Storm Drain!Storm Drain I 01/16/07 03/29/07 04/26/07 05/31/07 06/26/07 07/31/07 08/15/07 09/25/07 10/28/07 11/29/07 12/20/07 01/16/07 02/02/07 03/29/07 04/26/07 09/26/07 11/29/07 12/20/07 01/16/07 03/29/07 04/26/07 05/31/07 06/26/07 07/31/07 08/15/07 09/25/07 10/28/07 11/29/07 12/20/07* All results are <500 pCi/L unless otherwise shown 26 R. E. Ginna Nuclear Power Plant Groundwater Sampling Results Table 5 continued I LOCATION Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'Groundwater AVT M. 17'I DATE SAMPLED 01/16/07 02/02/07 03/29/07 04/26/07 05/31/07 06/26/07 07/31/07 08/15/07 09/25/07 10/28/07 11/29/07 12/20/07 Tritium pCi/L Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT N.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.Groundwater AVT S.6'6'6'6'6'6'6'6'6'6'6'6'01/16/07 02/02/07 03/29/07 04/26/07 05/31/07 06/26/07 07/31/07 08/15/07 09/25/07 10/28/07 11/29/07 12/20/07 01/16/07 02/02/07 03/29/07 04/26/07 05/31/07 06/26/07 07/31/07 08/15/07 09/25/07 10/28/07 11/29/07 13'13'13'13'13'13'13'13'13'13'13'* All results are <500 pCi/L unless otherwise shown 27 Constellation Energy@Nuclear Generation Group ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT: JANUARY 1, 2007-DECEMBER 31, 2007 MAY 2008 Prepared For: R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519 January 1, 2007 -December 31, 2007 Docket No. 50-244 TABLE OF CONTENTS Page I. S U M M A R Y .................................................................................................................

1 II. R. E. GINNA NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ......................................................

2 II.A. INTRODUCTION

...........................................................................................

2 II.B .P R O G R A M ......................................................................................................

2 II.B .1 O bjectives

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..2 II.B .2 Sam ple C ollection

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2 II.B .3 D ata Interpretation

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3 II.B.4 Program Exceptions

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3 IIC. RESULTS AND DISCUSSIONS

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3 II.C.1 Aquatic Environment

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4 II.C. l.a Surface and Drinking Water .............................................................

4 II.C.l.b Aquatic Organisms

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5 II.C.l.c Shoreline Sediment ..............................................................

5 II.C.2 Atmospheric Environment

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5 II.C.2.a Air Particulate Filters ........................................................................

6 II.C .2.b A ir Iodine ..........................................................................................

.6 II.C.3 Terrestrial Environment........................................................................

6 II.C .3.a V egetation

........................................................................................

6 II.C.3.b Milk ..........................................................

7 II.C .4 D irect R adiation ........................................................................................

7 II.C .5 M onitoring W ells ......................................................................................

8 II.D .C O N C LU SIO N ................................................................................................

8 III. REFERENCES

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13 APPENDIX A REMP SAMPLE LOCATIONS

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14 APPENDIX B REMP ANALYTICAL RESULTS ..........

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23 APPENDIX C QUALITY ASSURANCE PROGRAM...........................................

46 APPENDIX D LAND USE SURVEY.....................................................................

61 i R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 LIST OF FIGURES Figure Title Page A-1 MAP OF NEW YORK STATE AND LAKE ONTARIO SHOWING LOCATION OF THE R. E. GINNA NUCLEAR POWER PLANT ................

19 A-2 ONSITE SAM PLE LOCATIONS

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20 A-3 OFFSITE SAMPLE LOCATIONS (TLDS AND MILK FARMS WITHIN 5 M IL E S ) ... .......................................................................................................

..2 1 A-4 WATER SAMPLE, MILK FARMS AND TLD LOCATIONS

.......................

22 ii R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 LIST OF TABLES Table Title Page 1 SYNOPSIS OF R.E. GINNA NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............

9 2 ANNUAL

SUMMARY

OF RADIOACTIVITY IN THE ENVIRONS OF THE R.E. GINNA NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .........................................

10 A-1 LOCATIONS OF ENVIRONMENTAL SAMPLING STATIONS FOR THE R.E. GINNA NUCLEAR POWER PLANT ....................................................

16 B-1 CONCENTRATION OF TRITIUM, GAMMA EMITTERS AND GROSS BETA IN SURFACE AND DRINKING WATER ...........................................

25 B-2 CONCENTRATION OF GAMMA EMITTERS IN THE FLESH OF EDIBLE F IS H ......................................................................................................................

2 7 B-3 CONCENTRATION OF GAMMA EMITTERS IN SEDIMENT ...................

28 B-4 CONCENTRATION OF IODINE-131 IN FILTERED AIR (CHARCOAL C A R T R ID G E S .................................................................................................

29 B-5 CONCENTRATION OF BETA EMITTERS IN AIR PARTICULATES

-O N SITE SA M PLES ..........................................................................................

31 B-6 CONCENTRATION OF BETA EMITTERS IN AIR PARTICULATES

-O FFSITE SA M PLES ........................................................................................

33 B-7 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATES

....... 35 B-8 CONCENTRATION OF GAMMA EMITTERS IN VEGETATION SA M P L E S .......................................................................................................

..36 B-9 CONCENTRATION OF GAMMA EMITTERS (INCLUDING 1-13 1) IN M IL K .....................................................................................................................

3 7 B-10 TYPICAL MDA RANGES FOR GAMMA SPECTROMETRY

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38 B-11 TYPICAL LLDS FOR GAMMA SPECTROMETRY

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39 B-12 D IRECT RAD IATIO N ....................................................................................

40 B-13 GROUNDWATER MONITORING WELLS .................................................

43 i°, R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 C-1 RESULTS OF PARTICIPATION IN CROSS CHECK PROGRAMS ............

48 C-2 RESULTS OF QUALITY ASSURANCE PROGRAM ....................................

51 C-3 TELEDYNE BROWN ENGINEERING'S TYPICAL MDAS FOR GAMMA SPECTR O M ETR Y ...........................................................................................

60 iv R.E. Ginna Nuclear Power Plant iv R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 I.

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 Cesium-137 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 2007 results were consistent with data for the past five years and exhibited no adverse trends.The analytical results from the 2007 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 2007, 1289 samples were collected for analysis by gross beta counting and/or gamma spectroscopy.

These included 60 water samples, 17 fish samples, 6 sediment samples, 4 cladophera samples, 312 air iodine samples, 672 air particulates samples, 36 milk samples, 26 food products samples, and 156 thermoluminescent dosimeter measurements.

During 2007 there were three deviations from the sampling schedule for air samples, one deviation from the sampling schedule for milk samples, and one deviation from the sampling schedule for surface water samples. In addition a set of samples were delayed in delivery to the laboratory due to a mistake by the shipping vendor. All deviations were documented in the Corrective Action Program. The minimum number of samples required in the ODCM (Ref. 2) was collected for all pathways.Samples were collected by R. E. Ginna Nuclear Power Plant's Chemistry personnel and analyzed by the Constellation Energy Ft. Smallwood Environmental Laboratory.

A summary of the content of the REMP and the results of all the data collected for indicator and control locations are provided in Tables 1 and 2.I R.E. Ginna Nuclear Power Plant I R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 II. R. E. GINNA NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM II.A. INTRODUCTION The R. E. Ginna Nuclear Power Plant (Ginna) is an operating nuclear generating facility consisting of one pressurized water reactor. Unit 1 achieved criticality on September 1969 and commenced commercial operation in July 1970. The location of the plant in relation to local metropolitan areas is depicted in Appendix A, Figure A-1.Results of the monitoring program for the pre-operational and previous operational periods through 2006 have been reported in a series of documents.

Results of the monitoring program for the current operational period are included in this report. The report presents the content of the REMP (Table 1), the sampling locations (Appendix A), the summary of the analytical results (Table 2), a compilation of the analytical data (Appendix B), the results of the Quality Assurance Program (Appendix C), and the results of the Land Use Survey (Appendix D). Interpretation of the data and conclusions are presented in the body of the report.The environmental surveillance data collected during this reporting period were compared with that generated in previous periods whenever possible to evaluate the environmental radiological impact of the R. E. Ginna Nuclear Power Plant.II.B. PROGRAM II.B.1 Objectives The objectives of the REMP for the R.E. Ginna Nuclear Power Plant are: a. Measure and evaluate the effects of plant operation on the environment.

b. Monitor background radiation levels in the environs of the Ginna site.c. Demonstrate compliance with the environmental conditions and requirements of applicable state and federal regulations, including the ODCM and 40 CFR 190.d. Provide information by which the general public can evaluate environmental aspects of the operation of the R.E. Ginna Nuclear Power Plant.II.B.2 Sample Collection The locations of the individual sampling stations are listed in Table A- I and shown in Figures A-2 and A-3. All samples were collected by contractors to, or personnel of Constellation Energy according to Ginna procedures.

2 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 II.B.3 Data Interpretation Many results in environmental monitoring occur at or below the minimum detectable activity (MDA). In this report, all results below the relevant MDA are reported as being"less than" the MDA value. Typical MDA values are listed in Table B-10.II.B.4 Program Exceptions Six items reportable in the Annual Environmental Radiological Operating Report under procedure CHA-RETS-VARIATION were reported as follows: 1. Possible damage to environmental air sample #8 from striking filter housing with paintbrush during painting of sample shed on 5/1/07. Analysis showed no deviation from expected result.2. Circulating Water Outlet water sampler was found out of service on 5/15/07.Compensatory grab samples were taken in accordance with the instructions of the ODCM.3. Particulate filter on environmental air sampler #12 was damaged during annual pump changeout on 6/4/07 and was replaced.4. Milk samples taken on 7/10/07 degraded during shipment due to ineffective preservation.

Samples were retaken 7/16/07.5. Environmental air sampler #11 found off 8/13/07. Reset with no subsequent indications of problem. Sample period was 60.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .6. Milk samples and air samples taken the week of 8/6/07 were lost in shipment by the vendor. Compensatory milk samples were collected and sent 8/14/07. Missing air samples were found by the vendor and resent to the environmental laboratory.

II.C. RESULTS AND DISCUSSIONS All the environmental samples collected during the year were analyzed using Constellation Energy laboratory procedures (Ref. 3). The analytical results for this reporting period are presented in Appendix B and are also summarized in Table 2. For discussion, the analytical results are divided into four categories.

The categories are the Aquatic Environment, the Atmospheric Environment, the Terrestrial Environment, and Direct Radiation.

These categories are further divided into subcategories according to sample type (e.g., Circulating Water, Aquatic Organisms, etc., for the Aquatic Environment).

3 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 II.C.1 Aquatic Environment The aquatic environment surrounding the plant was monitored by analyzing samples of surface and drinking water, aquatic organisms, and shoreline sediment.

These samples were obtained from various sampling locations on Lake Ontario and Deer Creek near the plant.H.C.I.a Surface and Drinking Water Samples are collected weekly from Lake Ontario, upstream (Monroe County Water Authority

-Shoremont) and downstream (Ontario Water District Plant -OWD), composited monthly, and analyzed for gross beta activity (Table B-1). There was no statistically significant difference between the upstream and downstream sample concentrations.

The 2007 averages were 2.00 pCi/liter and 2.28 pCi/liter for the upstream and downstream samples respectively.

Gamma isotopic analysis of the monthly composite samples showed no statistically significant difference in activity between the upstream and downstream samples.Gross beta peaks of up tolO pCi/liter can occur when the lake is stirred up by wind and the weekly sample includes large quantities of suspended silt.Weekly samples are taken from the plant circulating water intake (Circ In) and discharge canal (Circ Out), and composited monthly. The 2007 averages were 2.14 pCi/liter and 2.11 pCi/liter for the intake and discharge canal respectively.

These are essentially the same as the upstream and downstream values as they fall within the + 1 sigma error band and range of the measurement.

Results for all water beta analyses are listed in Table B-1.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.Gamma isotopic analysis including 1-131 is performed on each monthly composite sample. These are listed in Table B-1 and are separated by source of sample. No anomalous results were noted. The analysis allows the determination of Iodine-131 activity of <1 pCi/liter.

Any positive counts and the 1 sigma error are reported.

During 2007, no sample results indicated 1-131 activity.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.

During 2007, no sample results indicated tritium activity.

Tritium data is provided in Table B-1.4 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 ILC.I.b Aquatic Organisms Indicator fish are caught in the vicinity of the R.E. Ginna Nuclear Power Plant 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 traces of radioactivity of the fish caught between the indicator and control locations.

Fish are caught by R. E. Ginna Nuclear Power Plant environmental staff and are analyzed by gamma spectroscopy after being held for periods of less than one week to keep the LLD value for the shorter half-life isotopes realistic.

Detection limits could also be affected by small mass samples, (< 2000 grams), in some species. Gamma isotopic concentrations (pCi/kilogram wet) are provided in Table B-2.II.C.l.c Shoreline Sediment Samples of shoreline sediment are taken upstream (Monroe County Water Authority

-Shoremont) and downstream (Ontario Water District) of R. E. Ginna Nuclear Power Plant.Results of the gamma isotopic analysis for sediment are included in Table B-3, along with benthic sediment and cladophera from Lake Ontario. Positive indication of Iodine-131 was found in cladophera samples taken at Ginna. The corrective action process was used to verify that positive indication of Iodine-131 was also found in cladophera samples taken upstream, outside of the influence of Ginna, and results were verified by the New York State Department of Environmental Conservation.

The apparent cause of this radioactivity in the cladophora is the common nuclear medicine Iodine-131 treatments and subsequent pathway to Lake Ontario via sanitary sewage releases in nearby communities.

Cladophera had been included in the Ginna REMP as a supplemental sample due to its extremely high bioaccumulation factor for iodine.II.C.2 Atmospheric Environment Radioactive particles in air are collected by drawing approximately one SCFM through a two inch diameter particulate filter. The volume of air sampled is measured by a dry gas meter and corrected for the pressure drop across the filter. The filters are changed weekly and allowed to decay for three days prior to counting to eliminate most of the natural radioactivity such as the short half-life decay products of radon. The decay period is used to give a more sensitive measurement of long-lived man-made radioactivity.

5 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 A ring of 6 sampling stations is located on the plant site from 160 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.

See Figure A-2 and Figure A-4.IL C.2.a Air Particulate Filters Based on weekly comparisons, there was no statistical difference between the Control and Indicator radioactive particulate concentrations.

The averages for the control samples were 0.020 pCi/m 3 , and the averages for the indicators were 0.020 pCi/m 3 for the period of January to December 2007. Maximum weekly concentrations for each station were less than 0.034 pCi/m 3.The major airborne species released from the plant are noble gases and tritium. Most of this activity is released in a gaseous form, however, some of the particulate activity is due to short lived noble gas decay products.Tables B-5 is a list of gross beta analysis values for the on-site sample stations.

Table B-6 is 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. One sample indicated a positive result for Cs-137 a factor of 35 times lower than the required limit of detection.

This result is consistent with background levels of this long-lived radionuclide released in historical atmospheric weapons tests.The results of these analyses are listed in Table B-7.II.C.2.b Air Iodine 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 B-4.II.C.3 Terrestrial Environment Crops are grown on the plant property in a location with a highest off-site meteorological deposition parameter, and samples of the produce are collected at harvest time for analysis.

Control samples are purchased from farms greater than ten miles from the plant, (e.g. Gro-Moore Farm Market in Henrietta, New York).II.C.3.a Vegetation There was no indication in the samples of any activity other than naturally occurring radionuclides and trace levels of Cesium-137 consistent with background levels.6 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Gamma isotopic data is given in Table B-8.II. C.3.b Milk There was one indicator dairy herd located within five miles from the plant on 1/1/07.Milk samples are collected monthly during November through May from the indicator farm and biweekly during June through October. A control farm sample is taken for each monthly sample and once during each biweekly period. The milk is analyzed for Iodine-131 and also analyzed by gamma spectroscopy for major fission products.All positive counts and the +/-1 sigma error are reported.

During 2007, no samples indicated Iodine-13 1 activity that exceeded the LLD for the analysis.

One sample from the control farm indicated trace Cesium-137 activity consistent with background levels.Table B-9 is a listing of all samples collected during 2007 with analytical results.II.C.4 Direct Radiation Thermoluminescent dosimeters (TLDs) or Optically Stimulated Luminescent Dosimeters (OSLs) with a sensitivity of 5 millirem/quarter are placed as part of the environmental monitoring program. Thirty-nine TLD/OSL 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/OSL 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 2007 on-site exposure ranged between 9.9 -14.3 mrem/quarter, with an average exposure of 12.5 mrem/quarter and off-site exposure ranged between 9.8 -15.4 mrem/quarter with an average exposure of 11.4 mrem/quarter.

40 CFR 190 requires that the annual dose equivalent not exceed 25 millirem to the whole body of any member of the public. Using the annual average of control TLD/OSL stations as background at 43.7 millirem, and the highest site boundary TLD/OSL annual reading, leads to 6.0 millirem direct radiation dose to the hypothetical maximally exposed member of the public, off-site.Table B-12 gives TLD/OSL readings for each quarter.7 R.E. Ginna Nuclear Power Plant 7 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 II.C.5 Monitoring Wells In accordance with R. E. Ginna Nuclear Power Plant's Chemistry procedures, environmental groundwater monitoring wells are sampled monthly. There are 3 indicator wells, one of which is screened at 3 depths to include groundwater from top of the water table down to bedrock. One well is located upgradient from the reactor containment building and serves as a local control sample point. Additionally, surface water samples from storm drains and the transformer retention pond are sampled monthly when water is present. These samples are analyzed for tritium to a detection limit of 500 pCi/L. In 2007, no radioactivity was detected in any groundwater sample or storm drain sample.Results of the groundwater monitoring well sampling are presented in Table B-13.II.D. CONCLUSION It is concluded that operation of the R. E. Ginna Nuclear Power Plant produced radioactivity and ambient radiation levels significantly below the limits of the ODCM and 40 CFR 190. Additionally, there was no significant buildup of plant-related radionuclides in the environment due to the operations of R. E. Ginna Nuclear Power Plant.8 R.E. Ginna Nuclear Power Plant 8 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table 1 Synopsis of R.E. Ginna Nuclear Power Plant Radiological Environmental Monitoring Program Sample Type Aquatic Environment Drinking Water Surface Water F2 Fish Sediment Cladophera Samolinci FreauencvI Number of Locations Number Collected Analvsis Analysis Frecluencv 1 Number Analyzed MC MC SA SA A 2 3 4 4 3 6 12 12 39 11 24 36 17 6 4 Gamma Gross Beta Tritium Gamma Gross Beta Tritium Gamma Gamma Gamma Gamma Gross Beta Gamma TLD M M M M M M SA SA A 24 24 24 36 36 36 17 6 4 Atmospheric Environment Air Iodine 3 Air Particulates 4 Direct Radiation Ambient Radiation Terrestrial Environment Food Products 5 Milk W W Q 312 624 48 156 W W Q Q A 312 624 48 156 Q A BW (June thru October)M (November thru May)26 22 14 Gamma Gamma Gamma 26 22 14 2 2 BW M 1 W=Weekly, BW=biweekly (15 days), M=Monthly (31 days), Q=Ouarterly (92 days), SA=Semiannual, A=Annual, C= Composite Twice during fishing season including at least four species The collection device contains activated charcoal 4 Beta counting is performed a 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change. Gamma spectroscopy performed on quarterly composite of weekly samples.5 Annually during growing season. Samples include grapes, apples, cabbage, tomatoes, green leafy vegeatables, cucumbers, raspberries, and squash.R.E. Ginna Nuclear Power Plant 9 January 1, 2007 -December 31, 2007 Docket No. 50-244 Table 2 Annual Summary of Radioactivity in the Environs of the Ginna Nuclear Power Plant Location with Type and Total Highest Annual Control Number of Indicator Mean Highest Locations Medium or Pathway Sampled (Unit Analyses Lower Limit of Locations Mean Name/Distance

& Annual Mean Mean of Measurement)

Performed Detection (LLD) (F)/Range 1 Direction 2 (F)/Range 1 (F)/Rangel Aquatic Environment Drinking Water (pCi/L)Gross Beta 24 Cs-1 37 24 0.60 2.30 0.60 2.80 2.28(12/12)

(1.32 -2.73)2.82(1/12) 2.92(36/36)

(0.88 -8.41)4.23 (1/36)Surface Water (pCi/L)Gross Beta 36 Ontario Water District 2.2 km ENE Ontario Water District Station 15 2.2 km ENE Deer Creek Circulating Water Out 0.1 km NNE North Indicator 3 3 2.28(12/12)

(1.32 -2.73)2.82(1/12) 4.51(12/12)

(1.90 -8.41)4.23(1/12) 2.06(12/12)

(1.15 -2.48)3 2.06(12/12)

(1.15 -2.48)3 Fish Cs-137 36 Cs-137 17 Cs-137 5 Cs-137 1 Sediment Shoreline Sediment 17 58 58 43(1/10)0(4/4)0(4/4)43(1/10)0(4/4)0(4/4)3 3 3 Benthic Sediment R.E. Ginna Nuclear Power Plant 10 January 1, 2007 -December 31, 2007 Docket No. 50-244 Table 2 (Continued)

Annual Summary of Radioactivity in the Environs of the Ginna Nuclear Power Plant Location with Type and Total Highest Annual Control Number of Indicator Mean Highest Locations Medium or Pathway Sampled (Unit Analyses Lower Limit of Locations Mean Name/Distance

& Annual Mean Mean of Measurement)

Performed Detection (LLD) (F)/Rangel Direction 2 (F)/RangeI (F)/Range 1 Lake Ontario Cladophera (pCi/kg) 1-131 19 41(3/3) Discharge 53(1/3) 22(1/1)4 Cs-137 4 (22-53)21(1/1)26 Slater Creek 21(1/1)21(1/1)Atmospheric Environment Air Iodine Air Particulates (10-2 pCi/mr 3)1-131 1.9 0(312/312) 3 Gross Beta 624 0.5 0.03 1.94(468/468)

(0.72 -3.55)0.0249(2/28)

(0.0205-0.0292)

Cs-137 28 Substation 13 Station 13 1.4 km SSW Creek Bridge Station 5 0.1 km SSE West Fence Line Station 7 0.22 km WSW 0(312/312) 2.04(52/52)

(0.81 -3.55)0.0292(1/4) 2.02(156/156)

(0.80 -3.55)0.0288(1/20)

Direct Radiation Ambient Radiation (mR/91 days)Dosimeters 156 11.6 (360/360)(9.9-15.4) 13.6(12/12)

(12.9 -14.3)10.9(108/108)

(9.8- 12.3)Terrestrial Environmental Food Products (pCi/kg)Cs-1 37 26 Cs-1 37 36 10.3 2.9 22(1/2)3.5 (1/18)ESE Garden Farm C 22(1/2)Milk 3.5 (1/18)3.5 (1/18)R.E. Ginna Nuclear Power Plant 11 January 1, 2007 -December 31, 2007 Docket No. 50-244 Table 2 (Continued)

Annual Summary of Radioactivity in the Environs of the Ginna Nuclear Power Plant Notes: 1 Mean and range based upon detectable measurements only. Fraction (F) of detectable measurements at specified location is indicated in parentheses 2 From the center point of the containment building 3 There was no detectable activity at the control or indicator location R.E. Ginna Nuclear Power Plant 12 January 1, 2007 -December 31, 2007 Docket No. 50-244 III. REFERENCES (1) R. E. Ginna Nuclear Power Plant, Nos. DPR- 18, Technical Specification 5.6.2; Annual Radiological Environmental Operating Report.(2) Offsite Dose Calculation Manual for the R. E. Ginna Nuclear Power Plant, Revision 20, Effective Date: March 29, 2005.(3) Constellation Energy Laboratory Procedures Manual, General Services Department.

(4) Constellation Energy, "Land Use Survey Around R. E. Ginna Nuclear Power Plant, September 2007." R.E. Ginna Nuclear Power Plant 13 January 1, 2007 -December 31, 2007 Docket No. 50-244 APPENDIX A REMP Sample Locations Summary of Appendix A Content Appendix A contains information concerning the environmental samples which were collected during this operating period. Sample locations and specific information about individual locations for the Ginna are given in Table A-1. Figure A-1 shows the location of the R. E. Ginna Nuclear Power Plant in relation to New York State and Lake Ontario. Figures A-2, A-3, and A-4 show the locations of the power plant sampling sites in relation to the plant site at different degrees of detail.R.E. Ginna Nuclear Power Plant 14 January 1, 2007 -December 31, 2007 Docket No. 50-244 APPENDIX A -REMP SAMPLE LOCATIONS TABLE OF CONTENTS Table Title Page A-1 LOCATIONS OF ENVIRONMENTAL SAMPLING STATIONS FOR THE GINNA NUCLEAR POW ER PLANT ......................................................................................

16 Figure Title Page A-1 MAP OF NEW YORK STATE AND LAKE ONTARIO SHOWING LOCATION OF THE R. E. GINNA NUCLEAR POWER PLANT ........................................................

19 A-2 ONSITE SAM PLE LOCATIONS

.................................................................................

20 A-3 OFFSITE SAMPLE LOCATIONS (TLDS AND MILK FARMS WITHIN 5 MILES) .... 21 A-4 WATER SAMPLE, MILK FARMS AND TLD LOCATIONS

...................................

22 R.E. Ginna Nuclear Power Plant 15 January 1, 2007 -December 31, 2007 Docket No. 50-244 TABLE A-i Locations of Environmental Sampling Stations for the R. E. Ginna Nuclear Plant Station Description Distance Direction Meters Miles Sector________Air Sam lers 2 Manor House Yard 320 0.2 E 3 East Field 420 0.3 ESE 4 Training Center Parking Lot 250 0.2 SE 5 Creek Bridge 160 0.1 SSE 6 Main Parking Lot 225 0.1 SW 7 West Fence Line 220 0.1 WSW 8 Seabreeze 19200 11.9 WSW 9 Webster 11400 7.1 SW 10 Walworth 13100 8.1 S 11 Williamson 11500 7.1 ESE 12 Sodus Point 25100 15.6 E 13 Substation 13 690 0.4 SSW Direct Radiation 2 Onsite-Manor House Yard 320 0.2 E 3 Onsite-In field approximately 200 ft SE of station #2 420 0.3 ESE 4 Onsite-Training Center yard driveway circle 250 0.2 SE 5 Onsite-Between creek and plant entry road 160 0.1 SSE 6 Onsite-SW side of plant parking lot 225 0.1 SW 7 Onsite-utility pole along West plant fence 220 0.1 WSW 8 Topper Drive-Irondequoit, Seabreeze Substation

51 19200 11.9 WSW 9 Phillips Road-Webster, intersection with Highway #104, 11400 7.1 SW Substation

74 10 Atlantic Avenue-Walworth, Substation

230 13100 8.1 S II W. Main Street-Williamson, Substation

207 11500 7.1 ESE 12 12 Seaman Avenue-Sodus Point-Off Lake Road by 25100 15.6 E Sewer district, Substation

209 13 At corner of plant-controlled area fence and dogleg to 230 0.1 WNW West 14 NW corner of field along lake shore 770 0.5 WNW 15 Field access road, west of orchard, approximately 3000' 850 0.5 W West of plant 16 SW Corner of orchard, approximately 3000' West of 900 0.6 WSW plant, approximately 200' North of Lake Road 17 Utility pole in orchard, approximately 75" North of Lake 500 0.3 SSW Road 18 Substation 13A fence, North Side 650 0.4 SSW 19 400 0.2 S On NW corner of house 100' East of plant access road 20 Approximately 150' West of Ontario Center Road and 680 0.4 SSE approximately 170' South of Lake Road R.E. Ginna Nuclear Power Plant 16 January 1, 2007 -December 31, 2007 Docket No. 50-244 Station Description Distance Direction Meters Miles Sector 21 North side of Lake Road, approximately 200' East 600 0.4 SE of Ontario Center Road 22 North side of Lake Road, SE, property corner 810 0.5 SE 23 East property line, midway between Lake Road 680 0.4 ESE and Lake shore 24 Lake shore near NE corner of property 630 0.4 E Substation

73, Klem Road, adjacent to 897 Klein 14350 8.9 WSW Road 26 Service Center, Plank Road, West of 250 14800 9.2 SW Atlantic Avenue at Knollwood Drive utility pole, 14700 9.1 SSW North side of road Substation

193, Marion, behind Stanton Ag. 17700 11.0 SE Service, North Main Street Substation

208, Town Line Road (CR-I 18), 1000 13800 8.6 ESE'North of Route 104 30 District Office, Sodus, on pole, West side of bldg 20500 12.7 ESE 31 Lake Road, pole 20' North of road, 500' East of 7280 4.5 W Salt Road 32 Woodard Road at County Line Road, pole @ 6850 4.2 WSW Northwest comer.33 County Line Road at RR tracks, pole 7950 4.9 SW approximately 100' East along tracks 34 Pole at Route 104, Lincoln Road, SW Corner. 6850 4.2 SSW 35 Transmission Right of Way, North of Clevenger 7600 4.7 SSW Road on pole.36 Substation

205, Route 104, East of Ontario 5650 3.5 S Center Road, North side of fence.37 Rail Road Avenue, pole at 2048 6000 3.7 SSE 38 Fisher Road at RR Tracks, pole East of road 7070 4.4 SE 39 Seeley Road, Pole South side 100' West of 6630 4.1 ESE intersection with Stony Lonesome Road 40 Lake Road at Stoney Lonesome Road, pole at SE 6630 4.1 E corner r r .... .,. F ish ......Lake Ontario Discharge Plume 2200 1.4 ENE Russell Station 25600 15.9 W ,____ _

lon)_-___,____

_ , , .", , , ,, Indicator and background samples of lettuce, apples, tomatoes, and cabbage are collected from gardens grown on company property and purchased from farms >10 miles from the plant.________ " -.,-W ater. "_-____ ,___ ____Shoremont/MCWA 27160 16.9 W Ontario Water District 2200 1.4 ENE Circ Water Intake 420 0.3 N Circ Water Discharge 130 0.1 NNE Deer Creek 260 0.2 ESE R.E. Ginna Nuclear Power Plant 17 January 1, 2007 -December 31, 2007 Docket No. 50-244 Station Description Distance :]Direction Meters Miles Sector SedimentýLake Ontario Discharge Plume 2200 1.4 ENE Russell Station 25600 15.9 W Milk Farm A 8270 5.1 ESE Farm C (Control) 21000 13.0 SE R.E. Ginna Nuclear Power Plant 18 January 1, 2007 -December 31, 2007 Docket No. 50-244 FIGURE A-1 Map of New York State and Lake Ontario Showing Location of R. E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant 19 January 1, 2007 -December 31, 2007 Docket No. 50-244 FIGURE A-2 Onsite Sample Locations R.E. Ginna Nuclear Power Plant 20 January 1, 2007 -December 31, 2007 Docket No. 50-244 FIGURE A-3 Offsite Sample Locations (TLDs and milk farms within 5 miles)R.E. Ginna Nuclear Power Plant 21 January 1, 2007 -December 31, 2007 Docket No. 50-244 FIGURE A-4 Water Sample, Milk Farms and TLD Locations 22 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 APPENDIX B REMP Analytical Results Summary of Appendix B Content Appendix B is a presentation of the analytical results for the R. E. Ginna Nuclear Power Plant radiological environmental monitoring programs.23 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 APPENDIX B TABLE OF CONTENTS -REMP ANALYTICAL RESULTS Table Title Page B-1 CONCENTRATION OF TRITIUM, GAMMA EMITTERS AND GROSS BETA IN SURFACE AND DRINKING WATER ......................................................

25 B-2 CONCENTRATION OF GAMMA EMITTERS IN THE FLESH OF EDIBLE F IS H ...................................................................................................................................

2 7 B-3 CONCENTRATION OF GAMMA EMITTERS IN SEDIMENT.........................

28 B-4 CONCENTRATION OF IODINE-131 IN FILTERED AIR (CHARCOAL C A R T R ID G E S) .................................................................................................................

29 B-5 CONCENTRATION OF BETA EMITTERS IN AIR PARTICULATES

-O N SITE SA M PLE S .....................................................................................................

31 B-6 CONCENTRATION OF BETA EMITTERS IN AIR PARTICULATES

-O FFSITE SA M PLE S ....................................................................................................

33 B-7 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATES

..............

35 B-8 CONCENTRATION OF GAMMA EMITTERS IN VEGETATION SAMPLES ..... 36 B-9 CONCENTRATION OF GAMMA EMITTERS (INCLUDING 1-13 1) IN MILK ..... 37 B-10 TYPICAL MDA RANGES FOR GAMMA SPECTROMETRY

................................

38 B-11 TYPICAL LLDS FOR GAMMA SPECTROMETRY

...............................................

39 B-12 D IRECT RA D IA TIO N .................................................................................................

40 B-13 GROUNDWATER MONITORING WELLS ...............................................................

43 24 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-1 Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2a)Location Sample Date H-3 Gamma Emitters Gross Beta Monroe County Water 01/30/2007

1.15 +/- 0.28 Shoremont (MCWA) 02/26/2007

2.39 +/- 0.55 04/02/2007

2.14 +/- 0.55 04/30/2007

2.31 +/- 0.50 06/04/2007

2.15 +/- 0.52 07/02/2007

2.02 +/- 0.50 07/30/2007

1.94 +/- 0.53 08/28/2007

1.70 +/- 0.50 10/02/2007

1.98 +/- 0.53 10/30/2007

2.44 +/- 0.52 11/27/2007

2.48 +/- 0.54 12/26/2007

1.27 + 0.50 Ontario Water District 01/30/2007

1.32 +/- 0.29 (OWD) 02/26/2007

2.13 +/- 0.54 04/02/2007

2.23 +/- 0.55 04/30/2007

2.60 +/- 0.52 06/04/2007

2.54 +/- 0.54 07/02/2007

2.82+/-1.68 (Cs-137) 2.52 +/- 0.53 07/30/2007

2.24 +/- 0.55 08/28/2007 2.13 +/- 0.53 10/02/2007

1.79 +/- 0.52 10/30/2007 2.73 +/- 0.55 11/27/2007

2.47 +/- 0.53 12/26/2007

2.65 +/- 0.57 Circulating Water Inlet 01/30/2007

0.88 +/- 0.27 (Circ In) 02/26/2007

2.65 +/- 0.57 04/02/2007

2.06 +/- 0.55 04/30/2007

2.63 +/- 0.53 06/04/2007

1.86 +/- 0.49 07/02/2007

1.99 +/- 0.50 07/30/2007

1.18 +/- 0.53 08/28/2007

2.16 +/- 0.53 10/02/2007

1.91 +/- 0.52 10/30/2007

2.50 +/- 0.54 11/27/2007

2.77 +/- 0.56 12/26/2007

3.03 +/- 0.59*All Non-Natural Gamma Emitters, including 1-131, and tritium <MDA.25 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-1 (Continued)

Concentration of Tritium, Gamma Emitters and Gross Beta in Surface and Drinking Water (Results in units of pCi/L +/- 2a)Location Sample Date H-3 Gamma Emitters Gross Beta Circulating Water Outlet (Circ Out)01/30/2007 02/26/2007 04/02/2007 04/30/2007 06/04/2007 07/02/2007 07/30/2007 08/28/2007 10/02/2007 10/30/2007 11/27/2007 12/26/2007 01/16/2007 02/27/2007 03/19/2007 04/23/2007 05/14/2007 06/18/2007 07/16/2007 08/13/2007 09/10/2007 10/16/2007 11/05/2007 12/11/2007 4.23+/-2.42 (Cs-137)1.26 2.80 2.17 3.03 1.95 2.38 1.63 2.03 1.30 2.54 2.43 1.82 1.90 3.61 3.22 3.65 2.88 4.12 8.03 4.81 2.64 6.55 8.41 4.35++++++++_++++++++++++++0.29 0.58 0.55 0.52 0.50 0.52 0.51 0.52 0.50 0.54 0.53 0.53 Deer Creek 0.34 0.75 0.67 0.62 0.63 0.66 0.83 0.79 0.65 0.94 1.26 0.75* All Non-Natural Gamma Emitters, including 1-131, and tritium < MDA.26 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish (Results in units of pCi/kg (wet) +/- 2a)Location Sample Date Fish Type Gamma Emitters North Indicator 1/11/2007 1/17/2007 1/17/2007 1/24/2007 3/07/2007 11/21/2007 11/21/2007 11/28/2007 11/29/2007 Burbot Lake Trout Smallmouth Bass White Sucker Smallmouth Bass Lake Trout White Sucker Brown Trout Smallmouth Bass 43+/-19 (Cs-137)Russel Station (Control)Sandy Creek -Hamlin (Control)5/02/2007 Smallmouth Bass 4/25/2007 6/7/2007 6/7/2007 9/25/2007 9/25/2007 9/25/2007 Rainbow Trout Bowfin Northern Pike Largemouth Bass Chinook Salmon.Northern Pike Greece (Control) 12/13/2006 Lake Trout*All Non-Natural Gamma Emitters <MDA 27 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-3 Concentration of Gamma Emitters in Sediment (Results in units of pCi/kg (wet) +/- 2u)Description Sample Date Gamma Emitters Shoreline Sediment-East (Manor House)-East (Bear Creek)-Greece (Control)Benthic Sediment-North Cladophera

-East (Manor House)-Slater Creek (Control)-Webster Park 6/7/2007 6/14/2007 9/04/2007 6/7/2007 9/04/2007 5/30/2007 8/20/2007 9/5/2007 9/5/2007 9/5/2007 9/5/2007 53+/-15 (1-131 )48+/-24 (1-131 )22+/-9 (1-131 )21 +/-10 (Cs-137)* All Non-Natural Gamma Emitters <MDA 28 R.E. Ginna Nuclear Power Plant 28 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-4 Concentration of Iodine-131 in Filtered Air (Charcoal Cartridges)(Results in units of 10.2 pCi/rn 3+/- 2o)Start Date Stop Date Station#2 (1)Manor House Station#4 (I), Training Center Station#7 (1)West Fence Station ,#8 (C)Seabreeze Station7, Station#9.(l)I #11 (I)Webster Williamson'Yard Parking Lot Line 1/01/2007

'1/08/2007

* * ..* *1/08/2007 1/15/2007

......1/15/2007 1/23/2007 1/23/2007 1/29/2007

......1/29/2007 2/05/2007

......2/05/2007

2/12/2007

- * .....*2/12/2007 2/19/2007

......2/19/2007

2/26/2007

* *I 2/26/2007.

3/05/2007

..- * .3/05/2007 3/12/2007

......F/12/07 3/19/2007 .--..3/19/2007 3/26/2007

......F 3/26/2007, 4/02/2007

..*.. * *4/02/2007 4/09/2007

.... " * *4/09/2007 4/16/2007

......4/16/2007 4/23/2007

..*. .* * ... .4/23/2007 4/30/2007

* *4/30/2007 5/07/2007

......I 5/07/2007

5/14/2007

.-*5/14/2007 5/21/2007

......F 5/21/2007 5/28/2007

* * *.'5/28j2O0,7', `6/04/2007

.....6/04/2007 6/11/2007

.......[-6/11/2007' 6/18/2007

.. .....& .*6/18/2007 6/25/2007

......6/25/2007 7/02/2007

.* * ... -F 1 Control Location*<MDA (1-131)29 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-4 (Continued)

Concentration of Iodine-1 31 in Filtered Air (Charcoal Cartridges)(Results in units of 10-2 pCi/m 3+/- 20)Start Date .StOpDate-Station Station Station StatiOn Station Stationj S S #2 (1) #4 (1) #7 (I) #8(C) #9 (i) #11 (i)Manor Training Center West Seabreeze' Webster Williamson House Fence Yard Parking Lot Line 7/02/2007 7/09/2007

* * * * *7/09/2007 7/16/2007

......7 7/16/2007

. * *. * :7. .7/23/2007 7/30/2007

......7/30/2007 8/06/2007

......8/7/2007 * .8/13/2007 8/20/2007

......8/20/2007 8/27/2007

.......-,*8/27/2007 9/03/2007

.-*9/03/2007 9/10/2007

* ....9/10/2007

<9/17/2007

....* " *9/17/2007 9/24/2007

......F 9/24/2007 61/0'T2007

,6: -77 7: , .......*10/01/2007

'160/08/2007

* .* *10/08/2007 10/15/2007

......10/15/2007 10/22/2007

* * *: *10/23/2007 10/29/2007

*10/29/2007 11/05/2007

......11/05/2007

.11/12/2007

..* ]11/12/2007 11/19/2007

......L 11/19/2007.

1,126/2007

,,* * *, * -* *: 11/26/2007 12/03/2007

......12/03/2007 12/10/2007

......F12/10/2007 12/17?2007

.. * ,.* * *12/17/2007 12/24/2007

......12/24/2007

12/31/2007

......*'F' Control Location,*<MDA (1-131)30 R.E. Ginna Nuclear Power Plant 30 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-5 Concentration of Beta Emitters in Air Particulates

-Onsite Samples (Results in pCi/in 3+/- 2a Uncertainty)

START STOP DATE DATE Station #2 (1)Manor House Yard Station #3 (1)East Field Station #4 (1)Training Center Parking Lot Station #5 (1)Creek Bridge Station #6 (1)Main Parking Lot Station #7 (1)West Fence Line Station #13 (1)Substation 13 01/01/07 01/08/07 01/15/07 01/23/07 01/29/07 02/05/07 02/12/07 02/19/07 02/26/07 03/05/07 03/12/07 03/19/07 03/27/07 04/02/07 04/09/07 04/16/07 04/23/07 04/30/07 05/07/07 05/14/07 05/21/07 05/28/07 06/04/07 06/11/07 06/1 8/07 06/25/07 01/08/07 01/15/07 01/23/07 0 1/29/07 02/05/07 02/12/07 02/19/07 02/26/07 03/05/07 03/12/07 03/19/07 03/26/07 04/02/07 04/09/07 04/16/07 04/23/07 04/30/07 05/07/07 05/14/07 05/21/07 05/28/07 06/04/07 06/11/07 06/18/07 06/25/07 07/02/07 0.0135 +/-0.0140 +/-0.0183 +/-0.0194 +/-0.01 97 +/-0.0161 +/-0.0193 +/-0.01 66 +/-0.0130 +/-0.0211 +/-0.0196 +/-0.0180 +/-0.0161 +/-0.0075 +/-0.0103 +/-0.0169 +/-0.0120 +/-0.0127 +/-0.0198 +/-0.01 60 +/-0.0206 +/-0.0255 +/-0.0123 +/-0.0181 +/-0.0146 +/-0.0192 +/-0.0011 0.0144 0.0010 0.01 52 +/-0.0010 0.01 35 0.0012 0.0195 +/-0.0012 0.0207 +/-0.0011 0.0160 +/-0.0011 0.0188 +/-0.0011 0.0150 0.0010 0.0131 0.0012 0.0220 0.0012 0.0199 +/-0.0010 0.0179 +/-0.0012 0.0162 +/-0.0008 0.0072 +/-0.0009 0.01 08 +/-0.0011 0.0166 +/-0.0010 0.0116 +/-0.0010 0.0123 +/-0.0012 0.01 91 0.0011 0.0177 0.0011 0.0219 +/-0.0014 0.0260 +/-0.0010 0.0115 +/-0.0012 0.0188 +/-0.0011 0.0151 +/-0.0012 0.0191 +/-0.0012 0.0011 0.0009 0.0013 0.0012 0.0011 0.0012 0.0011 0.0010 0.0012 0.0012 0.0011 0.0012 0.0008 0.0010 0.0011 0.0010 0.0010 0.0012 0.0012 0.0012 0.0015 0.0010 0.0012 0.0011 0.0012 0.0144 +/-0.0145 +/-0.0178 +/-0.0199+/-0.0206+/-0.0151+/-0.0194+/-0.0144+/-0.0127 0.0195+/-0.0203+/-0.01 84+/-0.0164+/-0.0076+/-0.0111+/-0.0158+/-0.0114 +/-0.0124 +/-0.0198 +/-0.0165 +/-0.0207 +/-0.0234 +/-0.0118 +/-0.0180 +/-0.0142 +/-0.0207 +/-0.0012 0.0011 0.0011 0.0013 0.0013 0.0011 0.0012 0.0011 0.0010 0.0012 0.0012 0.0011 0.0012 0.0009 0.0010 0.0011 0.0010 0.0011 0.0013 0.0012 0.0012 0.0014 0.0011 0.0013 0.0011 0.0013 0.0153 +/- 0.0014 0.0137 +/- 0.0011 0.0157 +/-0.0158 +/- 0.0013 0.0148 +/- 0.0011 0.0155 +/-0.0209 +/- 0.0013 0.0193 +/- 0.0011 0.0195 +/-0.0217 +/- 0.0015 0.0208 +/- 0.0012 0.0233 +/-0.0233 +/- 0.0015 0.01 94 +/- 0.0012 0.0207 +/-0.0181 +/- 0.0013 0.0138 +/- 0.0010 0.0152 +/-0.0209 +/- 0.0014 0.0171 +/- 0.0011 0.0195 t 0.0177 +/- 0.0013 0.0166 +/- 0.0011 0.0177 t 0.0128 +/- 0.0012 0.0134 +/- 0.0010 0.0131 t 0.0242 +/- 0.0015 0.0211 +/- 0.0011 0.0207 +/-0.0212 +/- 0.0014 0.0199 +/- 0.0013 0.0217+0.0192 +/- 0.0012 0.0189 +/- 0.0011 0.0201+0.0187 +/- 0.0015 0.0155 +/- 0.0011 0.0178+0.0090 +/- 0.0011 0.0082 +/- 0.0008 0.0078+0.0126 +/- 0.0012 0.0098 +/- 0.0009 0.0120+0.0169 +/- 0.0013 0.0163 +/- 0.0011 0.0180+/-0.0127 +/- 0.0012 0.0108 +/- 0.0010 0.0124+0.0125 +/- 0.0012 0.0122 +/- 0.0010 0.0139+0.0157 +/- 0.0011 0.0193 +/- 0.0012 0.0197+0.0164 +/- 0.0011 0.0174 +/- 0.0012 0.0182+0.0195 +/- 0.0011 0.0202 +/- 0.0011 0.0230+/-0.0246 +/- 0.0014 0.0264 +/- 0.0015 0.0298+0.0120 +/- 0.0010 0.0118 +/- 0.0010 0.0142 t 0.0183 +/- 0.0012 0.0168 +/- 0.0012 0.0196 0.0153 +/- 0.0010 0.0144 +/- 0.0010 0.0159+0.0193 +/- 0.0013 0.0189 +/- 0.0012 0.0219+0.0012 0.0011 0.0012 0.0013 0.0013 0.0011 0.0012 0.0012 0.0011 0.0013 0.0013 0.0012 0.0012 0.0009 0.0011 0.0012 0.001 1 0.0012 0.0013 0.0013 0.0012 0.0017 0.0012 0.0014 0.0012 0.0014 0.0145 +/-0.0138 +/-0.0193 +/-0.0186 +/-0.0211+0.0167+0.0198+0.0153+0.0130+/-0.0216+0.0211+0.0157+/-0.0153+0.0081+0.0108+0.0173+0.0101+0.0116+0.0188+0.0171+0.0227+0.0273+0.0130+0.0207+0.0158+0.0227 0.0014 0.0013 0.0014 0.0013 0.0015 0.0013 0.0014 0.0013 0.0012 0.0013 0.0016 0.0012 0,0014 0.0011 0. 0011 0.0014 0.0012 0.0012 0.0014 0.0014 0.0014 0.0018 0.0012 0.0014 0.0013 0.0015 1 st 6-Month Summary Maximum 0.0255 +/- 0.0014 0.0260 +/- 0.0015 0.0234 +/- 0.0014 0.0246 +/- 0.0015 0.0264 +/- 0.0015 0.0298 +/- 0.0017 0.0273 +/- 0.0018 Average 0.0165 0.0165 0.0164 0.0175 0.0164 0.0180 0.0170 Minimum 0.0075 +/- 0.0008 0.0072 +/- 0.0008 0.0076 +/- 0.0009 0.0090 +/- 0.0010 0.0082 +/- 0.0008 0.0078 +/- 0.0009 0.0081 +/- 0.0011 31 31 RE. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-5 (Continued)(Results in pCi/m 3+/- 2a Uncertainty)

START STOP Station #2 (I)DATE DATE Manor House Yard Station #3 (I)East Field Station #4 (I)Training Center Parking Lot Station #5 (I)Creek Bridge Station #6 (I)Main Parking Lot Station #7 (I)West Fence Line Station #13 (I)Substation 13 7/2/2007 7/9/2007 0.0223 _ 0.0013-7/9/2007 7/16/2007 0.0203 +/- 0.0013 7/16/2007 7/23/2007 0.0230 _ 0.0013 7/23/2007 7/30/2007 0.0218 + 0.0014 8/6/2007 8/13/2007 0.0240 + 0.0014 7/30/2007 8/6/2007 0.0263 _ 0.0014 8/13/2007 8/20/2007 0.0116 + 0.0010 8/20/2007 8/27/2007 0.0145 + 0.0011 8/27/2007 9/3/2007 0.0232 _ 0.0012 9/3/2007 9/10/2007 0.0228 +/- 0.0014 9/10/2007 9/17/2007 0.0152 _ 0.0012 9/17/2007 9/24/2007 0.0277 +/- 0.0014 9/24/2007 10/1/2007 0.0195 +/- 0.0013 10/1/2007 10/8/2007 0.0286 +/- 0.0015 10/8/2007 10/15/2007 0.0121 +/- 0.0011 10/15/2007 10/22/2007 0.0296 +/- 0.0015 10/22/2007 10/29/2007 0.0155 +/- 0.0012 10/29/2007 11/5/2007 0.0223 +/- 0.0014 11/5/2007 11/12/2007 0.0187 +/- 0.0012 11/12/2007 11/19/2007 0.0207 +/- 0.0013 11/19/2007 11/26/2007 0.0159 +/- 0.0012 11/26/2007 12/3/2007 0.0245 +/- 0.0013 12/3/2007 12/10/2007 0.0187 +/- 0.0011 12/10/2007 12/17/2007 0.0249 +/- 0.0013 12/17/2007 12/24/2007 0.0278 +/- 0.0014 12/24/2007 12/31/2007 0.0264 +/- 0.0013 0.0227 +/- 0.0013 0.0193 +/- 0.0012 0.0231 +/- 0.0013 0.0223 +/- 0.0013 0.0189 +/- 0.0012 0.0284 +/- 0.0015 0.0110 +/- 0.0010 0.0110 +/- 0.0010 0.0169 +/- 0.0011 0.0191 +/- 0.0014 0.0119 + 0.0011 0.0226 +/- 0.0013 0.0167 +/- 0.0012 0.0231 +/- 0.0014 0.0095 +/- 0.0011 0.0243 +/- 0.0014 0.0145 +/- 0.0012 0.0183 +/- 0.0013 0.0159 +/- 0.0012 0.0164 +/- 0.0011 0.0129 +/- 0.0011 0.0198 +/- 0.0012 0.0157 +/- 0.0010 0.0210 +/- 0.0013 0.0232 +/- 0.0013 0.0228 +/- 0.0013 0.0223 +/- 0.0014 0.0200 +/- 0.0013 0.0210 +/- 0.0013 0.0232 +/- 0.0014 0.0227 +/- 0.0013 0.0264 +/- 0.0015 0.0132 +/- 0.0011 0.0144 +/- 0.0011 0.0216 +/- 0.0012 0.0242 +/- 0.0015 0.0141 +/- 0.0012 0.0263 +/- 0.0014 0.0214 +/- 0.0014 0.0317 +/- 0.0016 0.0111 +/- 0.0011 0.0283 +/- 0.0015 0.0169 +/- 0.0012 0.0244 +/- 0.0014 0.0201 +/- 0.0013 0.0218 +/- 0.0013 0.0167 +/- 0.0012 0.0246 +/- 0.0013 0.0180 +/- 0.0011 0.0254 +/- 0.0014 0.0279 +/- 0.0014 0.0271 +/- 0.0014 0.0227 +/- 0.0013 0.0194 +/- 0.0012 0.0206 +/- 0.0012 0.0230 +/- 0.0013 0.0229 +/- 0.0013 0.0265 +/- 0.0014 0.0128 +/- 0.0010 0.0144 +/- 0.0011 0.0219 +/- 0.0012 0.0231 +/- 0.0014 0.0144 +/- 0.0011 0.0284 +/- 0.0014 0.0198 +/- 0.0012 0.0304 +/- 0.0015 0.0126 +/- 0.0010 0.0315 +/- 0.0015 0.0184 +/- 0.0012 0.0249 +/- 0.0013 0.0200 +/- 0.0012 0.0220 +/- 0.0012 0.0172 +/- 0.0011 0.0242 +/- 0.0012 0.0186 +/- 0.0010 0.0251 +/- 0.0013 0.0269 +/- 0.0013 0.0272 +/- 0.0013 0.0225 +/- 0.0013 0.0230 +/- 0.0014 0.0214 +/- 0.0014 0.0213 +/- 0.0014 0.0252 +/- 0.0014 0.0218 +/- 0.0013 0.0244 +/- 0.0017 0.0236 +/- 0.0016 0.0259 +/- 0.0015 0.0233 +/- 0.0014 0.0273 +/- 0.0016 0.0280 +/- 0.0015 0.0155 +/- 0.0012 0.0128 +/- 0.0011 0.0156 +/- 0.0012 0.0150 +/- 0.0012 0.0225 +/- 0.0013 0.0228 +/- 0.0013 0.0266 +/- 0.0017 0.0264 +/- 0.0016 0.0136 +/- 0.0012 0.0138 +/- 0.0012 0.0298 +/- 0.0016 0.0306 +/- 0.0016 0.0202 +/- 0.0014 0.0195 +/- 0.0014 0.0328 +/- 0.0017 0.0308 +/- 0.0016 0.0118 +/- 0.0012 0.0110 +/- 0.0011 0.0337 +/- 0.0017 0.0316 +/- 0.0016 0.0179 +/- 0.0013 0.0172 +/- 0.0013 0.0236 +/- 0.0015 0.0243 +/- 0.0015 0.0201 +/- 0.0013 0.0204 +/- 0.0013 0.0222 +/- 0.0014 0.0219 +/- 0.0013 0.0165 +/- 0.0027 0.0176 +/- 0.0013 0.0253 +/- 0.0014 0.0256 +/- 0.0014 0.0205 +/- 0.0012 0.0185 +/- 0.0011 0.0264 +/- 0.0015 0.0263 +/- 0.0014 0.0282 +/- 0.0014 0.0295 +/- 0.0014 0.0296 +/- 0.0015 0.0285 +/- 0.0014 0.0234 +/- 0.0015 0.0213 +/- 0.0013 0.0236 +/- 0.0015 0.0245 +/- 0.0017 0.0248 +/- 0.0014 0.0295 +/- 0.0017 0.0159 +/- 0.0014 0.0161 +/- 0.0013 0.0236 +/- 0.0014 0.0270 +/- 0.0017 0.0138 +/- 0.0012 0.0317 +/- 0.0017 0.0229 +/- 0.0015 0.0355 +/- 0.0018 0.0124 +/- 0.0012 0.0352 +/- 0.0018 0.0183 +/- 0.0014 0.0265 +/- 0.0016 0.0208 +/- 0.0014 0.0220 +/- 0.0014 0.0179 +/- 0.0014 0.0273 +/- 0.0015 0.0210 +/- 0.0013 0.0276 +/- 0.0015 0.0329 +/- 0.0016 0.0305 +/- 0.0016_nd 6-Month Summary ,laximum 0.0296 +/- 0.0015 0.0284 +/- 0.0015 0.0317 +/- 0.0016 0.0315 +/- 0.0015 0.0337 +/- 0.0027 0.0316 +/- 0.0016 0.0355 +/- 0.0018 Wverage 0.0215 0.0185 0.0217 0.0219 0.0230 0.0225 0.0241 Ainimum 0.0116 +/- 0.0010 0.0095 +/- 0.0010 0.0111 +/- 0.0011 0.0126 +/- 0.0010 0.0118 +/- 0.0012 0.0110 +/- 0.0011 0.0124 +/- 0.0012 12-Month Summary0.0296 +/- 0.0015 0.0284 +/- 0.0015 0.0317 +/- 0.0016 0.0315 +/- 0.0015 0.0337 +/- 0.0027 0.0316 +/- 0.0017 0.0355 +/- 0.0018 Werage 0.0190 0.0175 0.0191 0.0197 0.0197 0.0202 0.0205 Alinimum 0.0075 +/- 0.0008 0.0072 +/- 0.0008 0.0076 +/- 0.0009 0.0090 +/- 0,0010 0.0082 +/- 0.0008 0.0078 +/- 0.0009 0.0081 +/- 0.0011 32 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-6 Concentration of Beta Emitters in Air Particulates

-Offsite Samples Results in pCi/m 3+ 2sigma Uncertainty START STOP Station #8 ( C)DATE DATE Seabreeze Station #9 (I) Station #10 ( C) Station #11 (I)Webster Walworth Williamson Station #12 ( C)Sodus Point 01/01/07 01/08/07 01/15/07 01/23/07 01/29/07 02/05/07 01/08/07 01/15/07 01/23/07 01/29/07 02/05/07 02/12/07 0.0162 0.0155 0.0183 0.0174 0.0201 0.0172+/-++++-+0.0018 0.0017 0.0017 0.0017 0.0018 0.0018 0.0144 0.0139 0.0167 0.0147 0.0196 0.0153+/-+/-++/-+/-+/-0.0012 0.0011 0.0012 0.0011 0.0013 0.0012 0.0162 0.0139 0.0177 0.0187 0.0206 0.0166+/-+/-++/-+/-+0.0012 0.0011 0.0012 0.0012 0.0012 0.0011 0.0154 0.0139 0.0202 0.0212 0.0191 0.0166+/-++/-+/-+/-+/-0.0020 0.0019 0.0019 0.0023 0.0020 0.0020 0.0154 0.0167 0.0251 0.0225 0.0228 0.0172+/-.4.+/-+/-+/-+/-0.0013 0.0011 0.0014 0.0014 0.0013 0.0012 02/12/07 02/19/07 0.0181 +/- 0.0016 0.0173 +/- 0.0011 0.0184 +/- 0.0011 0.0208 +/- 0.0020 *0.0208 +/- 0.0012 02/19/07 02/26/07 0.0170 +/- 0.0018 0.0143 +/- 0.0012 0.0163 +/- 0.0012 0.0177 +/- 0.0020 0.0175 +/- 0.0012 02/26/07 03/05/07 0.0160 +/- 0.0017 0.0124 +/- 0.0011 0.0125 +/- 0.0010 0.0135 +/- 0.0019 0.0133 +/- 0.0011 03/05/07 03/12/07 0.0230 +/- 0.0019 0.0190 +/- 0.0013 0.0219 +/- 0.0013 0.0217 +/- 0.0020 0.0235 +/- 0.0013 03/12/07 03/19/07 0.0214 +/- 0.0018 0.0191 +/- 0.0013 0.0212 +/- 0.0013 0.0213 t 0.0023 0.0238 +/- 0.0015 03/19/07 03/26/07 0.0199 +/- 0.0016 0.0143 +/- 0.0010 0.0186 +/- 0.0011 0.0172 +/- 0.0018 0.0180 +/- 0.0011 03/27/07 04/02/07 0.0183 +/- 0.0020 0.0163 +/- 0.0013 0.0186 +/- 0.0013 0.0160 +/- 0.0022 0.0164 +/- 0.0013 04/02/07 04/09/07 0.0080 +_ 0.0014 0.0081 +/- 0.0010 0.0081 +/- 0.0009 0.0080 +/- 0.0017 0.0092 +/- 0.0010 04/09/07 04/16/07 04/23/07 04/30/07 05/07/07 05/14/07 05/21/07 05/28/07 06/04/07 06/11/07 06/18/07 06/25/07 04/16/07 04/23/07 04/30/07 05/07/07 05/14/07 05/21/07 05/28/07 06/04/07 06/11/07 06/18/07 06/25/07 07/02/07 0.0128 0.0176 0.0120 0.0145 0.0239 0.0209 0.0238 0.0316 0.0162 0.0198 0.0157 0.0236+++++/-+/-++++++0.0016 0.0017 0.0016 0.0016 0.0020 0.0017 0.0020 0.0024 0.0018 0.0018 0.0017 0.0019 0.0112 0.0163 0.0116 0.0119 0.0213 0.0231 0.0237 0.0289 0.0126 0.0189 0.0153 0.0219+/-+/-+++/-++/-+/-++++/-0.0010 0.0012 0.0011 0.0011 0.0014 0.0014 0.0015 0.0017 0.0012 0.0014 0.0013 0.0014 0.0106 0.0165 0.0117 0.0134 0.0221 0.0231 0.0228 0.0300 0.0139 0.0207 0.0161 0.0214+/-+/-++/-+/-+/-+/-+/-+/-+/-+/-+/-0.0009 0.0011 0.0010 0.0011 0.0013 0.0013 0.0013 0.0016 0.0011 0.0013 0.0012 0.0013 0.0102 0.0172 0.0110 0.0130 0.0219 0.0179 0.0228 0.0302 0.0132 0.0187 0.0150 0.0222+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+0.0017 0.0020 0.0018 0.0019 0.0014 0.0012 0.0012 0.0016 0.0011 0.0013 0.0012 0.0013 0.0103 0.0171 0.0121 0.0145 0.0203 0.0167 0.0204 0.0281 0.0118 0.0202 0.0160 0.0212+/-+/-+/-+/-+/-+/-+/-+/-+/-++/-+/-0.0010 0.0012 0.0011 0.0012 0.0013 0.0012 0.0012 0.0016 0.0018 0.0022 0.0020 0.0021 1 st 6-Month Summary Maximum 0.0316 +/- 0.0024 0.0289 +/- 0.0017 0.0300 +/- 0.0016 0.0302 +/- 0.0023 0.0281 +/- 0.0022 Average 0.0184 0.0166 0.0178 0.0175 0.0181 Minimum 0.0080 +/- 0.0014 0.0081 +/- 0.0010 0.0081 +/- 0.0009 0.0080 +/- 0.0011 0,0092 +/- 0.0010 33 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-6 (Continued)

Concentration of Beta Emitters in Air Particulates

-Offsite Samples (Results in pCi/m 3+/- 2a Uncertainty)

START STOP DATE DATE Station #8 ( C)Seabreeze Station #9 (I)Webster Station #10 ( C)Walworth Station #11 (I)Williamson Station #12 ( C)Sodus Point 7/2/2007 7/9/2007 0.0247 +/- 0.0020 0.0230 +/- 0.0015 0.0233 +/- 0.0014 0.0232 +/- 0.0014 0.0229 +/- 0.0022 7/9/2007 7/16/2007 0.0197 +/- 0.0017 0.0204 +/- 0.0013 0.0226 +/- 0.0013 0.0195 +/- 0.0013 0.0210 +/- 0.0022 7/16/2007 7/23/2007 0.0223 +/- 0,0021 0,0222 + 0.0016 0.0229 +/- 0.0013 0.0219 +/- 0.0012 0.0215 +/- 0.0020 7/23/2007 7/30/2007 0.0262 +/- 0.0021 0.0231 + 0.0015 0.0239 +/- 0.0015 0.0228 +/- 0.0015 0.0237 +/- 0.0025 8/6/2007 8/13/2007 0.0241 +/- 0.0014 0.0238 +/- 0.0015 0.0227 +/- 0.0013 0.0355 +/- 0.0030 0.0227 +/- 0.0020 7/30/2007 8/6/2007 0.0305 +/- 0.0022 0.0272 +/- 0.0016 0.0287 +/- 0.0015 0.0297 +/- 0.0015 0.0293 +/- 0.0024 8/13/2007 8/20/2007 8/20/2007 8/27/2007 8/27/2007 9/3/2007 9/3/2007 9/10/2007 9/10/2007 9/17/2007 9/17/2007 9/24/2007 9/24/2007 10/1/2007 10/1/2007 10/8/2007 10/8/2007 10/15/2007 10/15/2007 10/22/2007 10/22/2007 10/29/2007 10/29/2007 11/5/2007 11/5/2007 11/12/2007 11/12/2007 11/19/2007 11/19/2007 11/26/2007 11/26/2007 12/3/2007 12/3/2007 12/10/2007 12/10/2007 12/17/2007 12/17/2007 12/24/2007 12/24/2007 12/31/2007 0.0146 0.0150 0.0231 0.0237 0.0141 0.0281 0.0205 0.0321 0.0153 0.0336 0.0131 0.0233 0.0190 0.0218 0.0175 0.0232 0.0185 0.0194 0.0237 0.0289 0.0011 0.0011 0.0012 0.0014 0.0011 0.0014 0.0013 0.0015 0.0011 0.0015 0.0012 0.0013 0.0012 0.0012 0.0012 0.0013 0,0011 0.0011 0.0012 0.0014 0.0144 0.0156 0.0231 0.0274 0.0150 0.0303 0.0208 0.0324 0.0176 0.0349 0.0148 0.0239 0.0195 0.0207 0.0161 0.0221 0.0177 0.0227 0.0264 0.0246 0.0012 0.0013 0.0014 0.0017 0.0013 0.0017 0.0015 0.0017 0.0013 0.0018 0.0014 0.0015 0.0014 0.0014 0.0013 0.0014 0.0012 0.0015 0.0014 0.0014 0.0133 0.0153 0.0232 0.0263 0.0146 0.0291 0.0216 0.0302 0.0165 0.0320 0.0144 0.0250 0.0185 0.0225 0.0151 0.0208 0.0215 0.0277 0.0278 0.0292 0.0011 0.0011 0.0013 0.0016 0.0011 0.0015 0.0014 0.0015 0.0011 0.0016 0.0013 0.0014 0.0012 0.0013 0.0012 0.0012 0.0012 0.0015 0.0013 0.0014 0.0133 0.0157 0.0248 0.0269 0.0145 0.0312 0.0230 0.0326 0.0114 0.0331 0.0141 0.0258 0.0198 0.0228 0.0150 0.0243 0.0189 0.0248 0.0292 0.0290 0.0011 0.0011 0.0014 0.0016 0.0011 0.0015 0.0013 0.0017 0.0011 0.0015 0.0012 0.0014 0.0013 0.0013 0.0012 0.0013 0.0011 0.0014 0.0013 0.0014 0.0164 +/- 0.0022 0.0166 +/- 0.0018 0.0244 +/- 0.0022 0.0262 +/- 0.0026 0.0147 +/- 0.0020 0.0304 +/- 0.0025 0.0213 +/- 0.0021 0.0352 +/- 0.0028 0.0097 +/- 0.0020 0.0306 +/- 0.0023 0.0139 +/- 0.0022 0.0262 +/- 0.0024 0.0185 +/- 0.0021 0.0216 +/- 0.0021 0.0154 +/- 0.0021 0.0244 +/- 0.0022 0.0203 +/- 0.0019 0.0254 +/- 0.0023 0.0270 +/- 0.0022 0.0290 +/- 0.0023 2nd 6-Month Summary Maximum 0.0336 +/- 0.0022 0.0349 +/- 0.0018 0.0320 +/- 0.0016 0.0355 +/- 0.0030 0.0352 +/- 0.0028 Average 0.0221 0.0223 0.0226 0.0232 0.0226 Minimum 0.0131 +/- 0.0011 0.0144 + 0.0012 0.0133 +/- 0.0011 0.0114 +/- 0.0011 0.0097 +/- 0.0018 12-Month Summary Maximum 0.0336 +/- 0.0024 0.0349 +/- 0.0018 0.0320 +/- 0.0016 0.0355 +/- 0.0030 0.0352 +/- 0.0028 Average 0.0203 0.0195 0.0202 0.0204 0.0204 Minimum 0.0080 +/- 0.0011 0.0081 +/- 0.0010 0.0081 +/- 0.0009 0.0080 +/- 0.0011 0.0092 +/- 0.0010 34 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-7 Concentration of Gamma Emitters in Air Particulates (Results in units of 10 3 pCi/m 3+/- 20)Location First Quarter Second Quarter Third Fourth Quarter Quarter Station #2 Manor House Yard Station #3 East Field Station #4 Training Center Parking Lot*Station #5 Creek Bridge Cs-1 37 0.292+/-0.187 Station #6 Main Parking Lot Station #7 West Fence Line Station #8 Seabreeze Station #9 Webster Station #10 Walworth Station #11 Williamson Station #12 Sodus Point Station #13 Substation 13* All Non-Natural Gamma Emitters <MDA 35 R.E. Ginna Nuclear Power Plant 35 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-8 Concentration of Gamma Emitters in Vegetation Samples (Results in units of pCi/kg (wet) +/- 20)Location Sample Date Sample Type Gamma Emitters South East Garden 09/19/2007 09/19/2007 Grapes Apples East South East Garden 07/16/2007 07/16/2007 07/30/2007 07/30/2007 09/04/2007 09/04/2007 Raspberries Squash Cucumbers Green Leafy Vegetables Cabbage Tomatoes 22+/-8 (Cs-137)Brockport (Control)Lyndonville (Control)South Southeast Garden 08/11/2007 Green Leafy Vegetables 09/26/2007 Cabbage"k South 08/11/2007 07/24/2007 08/14/2007 09/04/2007 09/04/2007 09/19/2007 09/19/2007 09/19/2007 09/19/2007 09/19/2007 09/19/2007 Raspberries Green Leafy Vegetables

Cucumbers

Cabbage *Tomatoes *Apples *Apples South West West Apples Apples Apples Apples South South West West South West"k Hilton (Control) 08/07/2007 08/07/2007 08/07/2007 09/20/2007 09/20/2007 Tomatoes Squash Cucumbers Grapes Apples* All Non-Natural Gamma Emitters <MDA 36 R.E. Ginna Nuclear Power Plant 36 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-9 Concentration of Gamma Emitters (including 1-131) in Milk (Results in units of pCi/Liter

+/- 2a)Location Sample Date Gamma Emitters FARM A 01/08/07 02/19/07 03/12/07 04/17/07 05/08/07 06/13/07 06/26/07 07/16/07 07/24/07 08/13/07 08/21/07 09/04/07 09/17/07 10/01/07 10/15/07 10/29/07 11/12/07 12/10/07 01/08/07 02/19/07 03/12/07 04/17/07 05/08/07 06/13/07 06/26/07 07/16/07 07/24/07 08/13/07 08/21/07 09/04/07 09/17/07 10/01/07 10/15/07 10/29/07 11/12/07 12/10/07 3.6+/-1.89 (Cs-137)FARM C* All Non-Natural Gamma Emitters <MDA 37 R.E. Ginna Nuclear Power Plant 37 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-10 Typical MDA Ranges for Gamma Spectrometry Selected Nuclides Water pCi/I Fish pCi/Kg Sediment pCi/Kg Particulate Vegetation Milk I 0- 3 pCi/Kg pCi/I H-3 223 -- 779 ..........

Na-22 4-10 27-51 47- 160 0.4-1.0 21-68 6-13 Cr-51 28-77 237-777 353-1380 14-27 143-380 31-61 Mn-54, 4-8 20-39 39 --118 0.5-0.9 1 5-56 5-10 Co-58 4-9 33-50 47-156 0.8-1.6 20-54 5-10 19 7 8-11 '69- J91- 118-:;436 3- 6 45 -144 -1 241 Co-60 4-9 24-47 49-144 0.5-1.0 21-70 5-12 Zn-65. 8-21 53-95 102-365 3-3 45-166 12-25 Nb-95 4-11 39-100 53-222 2-3 23-61 5-9 Zr-95 6-16 47-'94 75-259 1-3 34-102 :8-16 Ru-106 34-71 185-267 319-922 4-6 149-440 37-75 Ag-10mrM"'

3`81- 20"31 37-142 0.4-0.8 652 :4-- 8 Te-129m 42-119 364-1170 538 -2280 19-33 246-674 50-98 F 1-131. 4-29*ý 100-12200 122-1300 161 -827* 21-479 v 4 9***Cs-134 3-7 18-27 33-117 0.4-0.7 14-51 4-8 Cs-137 4-8 21-32 39-125 0.3-0.7 18-57 5-10 Ba-140 6-29 59-2250 103-916 33-87 29-137 6-14 La-146 6-29 59- "2250 103- 916 33-87 29- 137 '6,- 1 Ce-144 18-39 61-80 140-413 1-2 64-195 20-43* The MDA- range for 1-131 measured on a charcoal cartridge is typically 6.3 x 10 3 to 2.3 x 10p The MDA range for 1-131 measured in drinking water is typically 0.5 to 1.1 pCi/L***The MDA range for 1-131 measured in milk is typically 0.6 to 0.9 pCi/L 38 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-11 Typical LLDs for Gamma Spectrometry RvfSeleted: -F at dieV Pe qetatioenn MikýNuclides pCi/I pCi/Kg pCi/Kg 103- pCi/m 3 pCi/Kg pCi/I Na-22 4.1 24 59 3.7 29 6ýr51120 16F 14 3 Mn-54 3.8 20 49 2.8 24 5 36,--81 28- 210 9 5 Fs-59 7.8 45 103 2.8 50 11 FýCo-660 >j74.4~~*4 7-7. 0 >. 2. 2~66 Zn-65 7.9 54 141 7.0 57 12 jN-5< ;42. 60 2A 4 Zr-95 6.5 35 79 5.0 43 8 172 458 25 196 3 Ag-110m 3.6 15 42 2.2 21 4 m 1W~ 7 7 0 551 2 4 1-131 3.2* 13 41 1.9** 19 4*C~ : 3.3 <'17 -4 .20 Q 4 Cs-137 3.9 17 58 2.8 26 5 Ba-.1A9> 0 19- 67 ~ 3.9 3-2 5 La-140 4.8 19 67 3.9 33 5 Ce-1ý44 _7 5819 8.9; .7---81 '20* The LLD for 1-131 measured in drinking water and milk is 0.5 pCi/L**The LLD for 1-131 measured on charcoal filter is 9.4 x 103 pCi/m 3 39 R.E. Ginna Nuclear Power Plant 39 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-1 2 Direct Radiation (Results in Units of mR/90 days + 2a)7 Station Location First Quarter Second Quarter Third Quarter: Fourth Quarter V 2 Onsite-Manor House Yard 12.1 +3.0 11.8 3.0 13.2 3.3 13.0 +/- 3.3 3 Onsite-In field approximately 200 ft 11.9 _ 3.0 11.9 _ 3.0 13.8 + 3.5 13.4 +/- 3.4 SE of station #2 i 4 Onsite-TrainingCenter yard 12.4 3.1 12.4 +/- 3.1 '13.4 3.4 13.4 +/- 3.4 driveway circle 5 Onsite-Between creek and plant 12.9 +/- 3.2 12.7 +/- 3.2 13.9 +/- 3.5 13.7 +/- 3.5 entry road 6 iOnsite-SW sideof plant parking lot 10.1 +/-ý2.6 10.1+/- 2.5 9.9 + 2.5 10.2 ¥ 2.6 7 Onsite-utility pole along West plant 12.9 +/- 3.3 14.3 +/- 3.6 14.0 +/- 3.5 13.0 +/- 3.3 fence-, Topper Drive-lrondequoit, 11.1 +/--2.8 10.8 +/- 2.7 11.5 +/-2.9 11.2 _2.8 Seabreeze Substation

51 , 9 Phillips Road-Webster, intersection 10.5 + 2.6 10.8 +/- 2.7 11.4 +/- 2.9 11.4 +/- 2.9 with Highway #104, Substation

74 101 Atlantic Avenue-Walworth, 10.1 L 2;5 9.8 2.5 10.6 +/- 2.7 10.3 +/- 2.6 Substation

230, 11 W. Main Street-Williamson, 10.5 +/-2.6 10.6 +/- 2.7 10.3 +/-2.6 11.0 +/-2.8 Substation

207 12 Seaman Avenue-Sodus Point-Off 105+/-27 115+/-29 11.6+/- 2.9 1 .13i0--,-Lake Road by.Sewer district, Substation

209.:_13 At corner of plant-controlled area 11.9 _ 3.0 12.2 _ 3.1 13.3 _ 3.3 12.6 _ 3.2 fence and dogleg to West K 14 -:NW corner of field along lake shore 11.1 +/-2.8 11.9+/-3.0 12.9_3.2 12.5 _3.1 ]15 Field access road, west of orchard, 11.8 _ 3.0 12.7 + 3.2 13.4 _ 3.4 13.1 _ 3.3 approximately 3000' West of plant 40 R.E. Ginna Nuclear Power PIaDt January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-12 (Continued)

Direct Radiation (Results in Units of mR/90 days +/- 2a)Station Location "First QuarteK> Secohd'Quarter

-`.Third Quarter'"', -Fourth Quarter 16 SW Corner of orchard, -11.4+/-2.9 12.1 13.0 13.3+/-3.3 12.9+/-3.3 approximately 3000' West of plant,, approximately 200' North of Lake Road ~17 Utility pole in orchard, approximately 11.1 +/-2.8 11.7 2.9 12.4 3.1 12.4 +/- 3.1 75" North of Lake Road 18 Approximately 30' ONorth of NE 10.0 +/- 2.5 10.0 +/-_:2.5 10.3 +/- 2.6 10.4 +/- 2.6 cornerof Substation 13A fence 19 On NW corner of house 100' East of 10.7 +/- 2.7 10.3 _ 2.6 10.5 +/- 2.6 10.7 +/- 2.7 plant access road 20 Approximately~50' West6f Ontario 11'.6 +/- 2.9 11.8 +/- 3.0 12.5 +/- 3.2 12.6 1 3.2 Center Road and approximately 170'.South of Lake Road 21 North side of Lake Road, 10.9 +/- 2.8 11.2 +/- 2.8 12.0 +/- 3.0 12.2 +/- 3.1 approximately 200' East of Ontario Center Road 22 North side ofLake Road, SE, 10.9+/-2.7 11.1 +/-2.8 11.4+/-2.9 10.9.2.8 property owner 23 East property line, midway between 10.8 2.7 12.2 3.1 13.1 +/-3.3 12.9 3.2 Lake Road and Lake shore 4 Lakeshore near oer 7of 1 3.1 0:.12.8+/-3.2 12.9 +/-_3:.3 prope'rty 25' Substation

73, Klem Road, 10.3+/- 2.6 10.4 +/- 2.6 10.7 +/- 2.7 10.7 _ 2.0 adjacent to 897 Klem Road 261 Servie&6ter,.PlankRod,

.0.621.02.8 77,114 -+/-29 11.1 +/-2.7 250 j 27' Atlantic Avenue at Knollwood Drive 10.5 +/- 2.6 11.5 2.9 12.3 +/- 3.1 11.7 3.0 utility pole, North side of road 41 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-12 (Continued)

Direct Radiation (Results in Units of mR/90 days +/- 2a)I 28 1 Substati6'n

i 93, Mario'nibehind Stanton Ag. Service, North Main 10.0 +/- 2.5 11.1`+/-t:2.8 11.2+/-2.8 10.8 +/-'2.7 Street 291 Substation

208, Town Line Road 10.4 +/- 2.6 10.6 2.7 11.2 +/- 2.8 11.0 +/- 2.8 (CR-118), 1000 ' North of Route 104District Office, Sodus,, on/pole, West 11.3 +27T70.72.71.2+/-+2.8 it7+27 side of bldg'31 Lake Road, pole 20' North of road, 11.2 +/- 2.8 12.5 +/- 3.2 13.2 +/- 3.3 12.0 +/- 3.0 500' East of Salt Road 32 Woodard Road at County Line 10.4 +/- 2.6 10.2 2.6 10.8 +/- 2.7 10.8 +/-+2.7 Road, pole 0 BW corner, 33 County Line Road at RR tracks, pole 10.5 +/- 2.6 10.8 +/- 2.7 10.5 +/- 2.6 10.8 +/- 2.7 approximately 100' East along tracks 34 Lincoln Road, pole midway between 12.2 +/- 3.1 12.8 +/- 3.2 13.2 +/- 3.3 13.2 +/- 3.3 Ridge Road and Route 104 35 Transmission Right of Way, North of 11.3 +/- 2.8 12.7 +/- 3.2 13.8 +/- 3.5 15.4 +/- 3.9 Clevenger Road on pole 36 Substation

205, Route 104, East of 10.7 +/- 2.7 10.7 +/- 2.7 11.4 +/- 2.9 11.3 +/-+2.8 Ontario Center Road, North side of fence 37 Rail Road Avenue, pole at 2048 10.1 +/- 2.6 10.4 t 2.6 10.5 +/- 2.7 10.1 +/- 2.5 38 Fisher Road at RR Tracks; pole East 11.5++/-2.9 12.1 +/-3.1 12.5+/-3.1 11.5+/-2.9 of road 39 Seeley Road, Pole South side 100' 11.0 +/- 2.8 12.5 +/- 3.2 12.9 +/- 3.3 11.8 +/- 3.0 West of intersection with Stony Lonesome Road 40 Lake Road at Stoney Lonesome 10.6 +/- 2.7 11.4 + 2.9 10.5 +/- 2.7 11.0 +/- 2.8 Road, pole at SE corner Control Location 42 R.E. Ginna Nuclear Power Plant 42 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-13 Groundwater Monitoring Wells Location Depth to Water (ft)Sample Date Tritium Groundwater AVT M. 17' 3.5 1/16/07 *3.6 2/2/07 *1.8 3/29/07 *3.3 4/26/07 *4.4 5/31/07 *4.4 6/26/07 *4.9 7/31/07 *4.9 8/15/07 *4.9 9/25/07 *(11) 10/28/07 *2.0 11/29/07 *4.9 12/20/07 *Groundwater AVT N. 6' 3.2' 1/16/07 *3.3' 2/2/07 *___ 1.6' 3/29/07 *3.2' 4/26/07 *4.3' 5/31/07 *4.7' (recount 6/26/07 *4.7' 7/31/07 *5.0' 8/15/07 *4.6' 9/25/07 *(1) 10/28/07 *1.6' 11/29/07 *3.9' 12/20/07 *Groundwater AVT S. 13' 3.2' 1/16/07 *3.0' 2/2/07 *1.0' 3/29/07 *3.0' 4/26/07 *4.0' 5/31/07 *--4.3' 6/26/07 *4.4' 7/31/07 *4.9' 8/15/07 *4.6' 9/25/07 *____ _(_I1)10/28/07

1.3' 11/29/07 *5.2' 12/20/07 *43 R.E. Ginna Nuclear Power Plant 43 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-13 (Continued)

Groundwater Monitoring Wells Location Groundwater by Butler Bldq.Depth to Water (ft)7.4'7.7'Sample Date 1/16/07 Tritium 2/7/07 6.4' 3/29/07 *7.0' 4/26/07 *___7.6' 5/31/07 *8.6' 6/26/07 *10.5' 7/31/07 *12.6' 8/15/07 *15.6' 9/25/07 *(1) 10/28/07 *13.6' 11/29/07 *12.8' 12/20/07 *Groundwater SE of CSB 17.1' 1/16/07 *17.4' 2/2/07 *14.2' 3/29/07 *15.8' 4/26/07 *17.6' 5/31/07 *17.9' 6/26/07 *17.4' 7/31/07 *18.4' 8/15/07 *18.3' 9/26/07 *(M) 10/28/07 *16.3' 11/29/07 *16.6' 12/20/07 *Pond 1/16/07 *3/29/07 *4/26/07 *Prior to drain 5/8/07 *5/31/07 *8/15/07 *10/28/07 *Screen House West 6.0' 1/16/07 *___6.0' 3/29/07 *6.2' 4/26/07 *6.4' 5/31/07 *6.2' 6/26/07 *12.3' 7/31/07 *12.7' 8/15/07 *9.7' 9/25/07 *(1) 10/28/07 *12.0' 11/29/07 *44 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table B-13 (Continued)

Groundwater Monitoring Wells Location Depth to Water (ft)Sample Date Tritium Storm Drain F 1/16/07 2/2/07 *3/29/07 *4/26/07 *5/31/07 *6/26/07 *7/31/07 *8/15/07 *9/25/07 *10/28/07 *11/29/07 *12/20/07 *Storm Drain G 1/16/07 *3/29/07 *4/26/07 *5/31/07 *6/26/07 *7/31/07 *8/15/07 *9/25/07 *10/28/07 *11/29/07 *12/20/07 *Storm Drain H 1/16/07 *2/2/07 *3/29/07 *4/26/07 *9/26/07 *11/29/07 *12/20/07 *Storm Drain I 1/16/07 *3/29/07 *4/26/07 *5/31/07 *6/26/07 *7/31/07 *8/15/07 *9/25/07 *10/28/07 *11/29/07 *12/20/07 ** -Analytical results less than MDA (1) -Depth to water information not collected.

45 R.E. Ginna Nuclear Power Plant 45 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 APPENDIX C Quality Assurance Program Summary of Appendix C Content: Appendix C presents a summary of Constellation Energy laboratory's quality assurance program, including the following:

Table C- I compiles the results of the Constellation Energy Laboratory's participation in an intercomparison program with Environmental Resource Associates (ERA), located in Arvada, Colorado and Analytics, Inc. located in Atlanta, Georgia." Table C-2 compiles the results of the Constellation Energy Laboratory's participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee.

Table C-3 lists typical MDAs achieved by Teledyne Brown for Gamma Spectroscopy.

All the Constellation Energy Laboratory's results contained in Table C-1 generally agree with the intercomparison laboratory's results within the range of +/-2 c of each other. In addition, all the sets of intercomparison results in the table are in full agreement when they were further evaluated using the NRC Resolution Test Criteria'.

The uncertainties for the Constellation Energy Laboratory's results and Analytics' results are +/-2(y while the ERA laboratory's uncertainty is based on USEPA guidelines 2.All the results contained in Table C-2 agree within the range of +/-2 T of each other with their respective Constellation Energy Laboratory original, replicate and/or Teledyne Brown Engineering's split laboratory samples, except for the comparisons of five samples involving Cs-137 results: an air filter composite sample from A3 collected 5/15/2007; a soil sample from SFA4 collected 5/31/2007; a shoreline sample from Wbl collected 5/31/2007; a vegetation sample form TbI collected 7/23/2007; and a vegetation sample from SFb3 collected 12/18/2007.

In all five cases low levels of Cs-137 were observed in only one of the results of the comparison set and not observed in the other two. These minor discrepancies, occurring very close to or below the analyses MDA's, are most probably due to counting statistical fluctuations and/or the non-homogeneous nature of the sample-splitting process.Other samples whose nature generally precludes sample splitting are marked "**" in the Split Analysis column.NRC Inspection Manual, Inspection Procedure 84750, March 15, 1994 2 National Standards for Water Proficiency Testing Studies Criteria Document, December 1998 46 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 TABLE OF CONTENTS -ANALYTICAL RESULTS Table Title Page C-1 C-2 C-3 RESULTS OF PARTICIPATION IN CROSS CHECK PROGRAMS ............

48 RESULTS OF QUALITY ASSURANCE PROGRAM ....................................

51 TELEDYNE BROWN ENGINEERING'S TYPICAL MDAS FOR GAMMA SPECTR O M ETRY ...........................................................................................

60 47 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 TABLE C-1 Results of Participation in Cross Check Programs Sample Sample Type Isotope Reported Cross Check Date and Units Observed Laboratory' Lab Results 1 Results 1 1/08/07 Water-pCi/L 3/22/07 Milk-pCi/L 3/22/07 Charcoal Cartridge-pCi 3/22/07 Water-pCi/L 4/09/07 Water-pCi/L 6/14/07 Water-pCi 6/14/07 Water-pCi/L Ba-133 Co-60 Cs-1 34 Cs-137 Zn-65 1-131 Cs-134 Cs-1 37 Ce-141 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Gross p 1-131 Gross p Cs- 134 Cs-1 37 Ce-141 Co-58 Fe-59 Cr-51 Co-60 Mn-54 Zn-65 Cs-137 Zn-65 90+/-10 104+/-9 83+/-7 233+/-15 381+/-33 85+/-29 99+/-13 249+/-28 309+/-28 227+/-109 197+/-27 106+/-22 111+/-30 162+/-17 1075+/-80 80+/-5 99+/-5 19+/-7 147+/-2 172+/-7 138+/-11 145+/-36 171+/-15 145+/-26 489+/-191 202+/-8 144+/-10 283+/-23 112+/-11 194+/-24 91+/-15 101+/-9 89+/-9 231+/-20 350+/-60 85+/-3 112+/-4 234+/-8 297+/-10 245+/-8 182+/-6 100+/-3 106+/-4 152+/-5 1000+/-33 70+/-2 100+/-3 19+/-5 148+/-5 194+/-6 135+/-5 160+/-5 159+/-5 134+/-4 411+/-14 191+/-6 133+/-4 268+/-9 110+/-6 200+/-19'See discussion at the beginning of the Appendix.48 RE. Ginna Nuclear Power Plant 48 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table C-1 (Continued)

Sample Date Sample Type and Units Isotope Observed Reported Laboratory' Results'Cross Check Lab Results'6/14/07 Filter-pCi/filter 7/06/07 Water-pCi/L 7/06/07 Water-pCi/L 9/13/07 Filter-pCi/filter 9/18/07 Filter-pCi/filter 10/06/07 Water-pCi/L 12/06/07 Charcoal See discussion at the beginning of the Appendix Ce-1 41 Cr-51 Cs-1 34 Cs-137 Mn-54 Fe-59 Zn-65 Co-60 Co-58 Ba-1 33 Cs-134 Cs-137 Zn-65 Co-60 Gross 13 Gross 3 Am-241 Cs-1 34 Cs-137 Co-60 Zn-65 1-131 1-131 121+/-24 286+/-130 118+/-6 100+/-8 108+/-9 103+/-29 230+/-22 143+/-8 122+/-14 19+/-7 67+/-6 64+/-9 113+/-15 34+/-5 7.6+/-0.4 82+/-2 31+/-22 859+/-22 916+/-23 562+/-14 1554+/-51 29+/-2 79+/-5 114+/-4 293+/-10 138+/-5 97+/-3 95+/-3 95+/-3 191+/-6 136+/-5 113+/-4 19+/-9 69+/-9 61+/-9 55+/-9 34+/-8 11.5+/-9.0 87+/-1 21+/-8 922+/-208 831+/-269 505+/-126 1290+/-500 29+/-5 74+/-2 49 R.E. Ginna Nuclear Power Plant 49 R.E. Ginna Nuclear Power Plant January 1, 2007 -December 31, 2007 Docket No. 50-244 Table C-1 (Continued)

Results of Participation in Cross Check Programs Reported Sample Sample Type Isotope Laboratory' Cross Check Date and Units Observed Results' Lab Results'12/06/07 Milk-pCi/L 12/06/07 Filter-pCi/filter See discussion at the beginning of the Appendix Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 181+/-17 190+/-16 208+/-16 172+/-19 264+/-30 224+/-13 143+/-7 535+/-60 96+/-6 148+/-10 152+/-12 180+/-12 148+/-14 238+/-30 190+/-10 166+/-6 174+/-6 190+/-6 148+/-5 234+/-8 211+/-8 117+/-4 425+/-14 114+/-4 138+/-5 144+/-5 157+/-6 123+/-4 194+/-6 175+/-6 50 R.E. Ginna Nuclear Power Plant 50 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 Results of Quality Assurance Program Sample Type Sample Type of Original Replicate Split And Location Date Analysis Analysis Analysis Analysis (10.2 pCi/m 3)Air Iodine-Al 2/05/07 1-131 <MDA <MDA **Air Iodine-A2 2/05/07 1-131 <MDA <MDA **Air Iodine-A3 1/08/07 1-131 <MDA <MDA **Air Iodine-A4 1/08/07 1-131 <MDA <MDA **Air Filter -Al 1/08/07 Beta 0.7+/-0.1 0.8+/-0.1 **Air Filter -A2 1/08/07 Beta 1.0+/-0.2 1.0+/-0.2 **Air Filter -A3 1/08/07 Beta 0.7+/-0.1 0.7+/-0.1 **Air Filter -A4 1/08/07 Beta 1.0+/-0.2 1.0+/-0.2 **Air Filter -A5 1/08/07 Beta 0.9+/-0.1 0.9+/-0.1 **Air Filter -SFA1 1/08/07 Beta 0.8+/-0.1 0.9+/-0.1 **Air Filter -SFA2 1/08/07 Beta 1.0+/-0.1 0.9+/-0.1 **Air Filter -SFA3 1/08/07 Beta 1.1+/-0.1 1.1+/-0.1 **Air Filter -SFA4 1/08/07 Beta 1.0+/-0.2 0.9+/-0.1 **Air Filter-Al 2/05/07 Beta 2.5+/-0.2 2.5+/-0.2 **Air Filter-A2 2/05/07 Beta 2.5+/-0.2 2.4+/-0.2 **Air Filter-A3 2/05/07 Beta 2.4+/-0.2 2.3+/-0.2 **Air Filter-A4 2/05/07 Beta 2.7+/-0.3 2.9+/-0.2 **Air Filter-A5 2/05/07 Beta 2.3+/-0.2 2.6+/-0.2 **Air Filter-SFA1 2/05/07 Beta 2.6+/-0.2 2.7+/-0.2 **Air Filter-SFA2 2/05/07 Beta 2.6+/-0.2 2.5+/-0.2 **Air Filter-SFA3 2/05/07 Beta 2.4+/-0.2 2.6+/-0.2 **Air Filter-SFA4 2/05/07 Beta 2.7+/-0.2 2.5+/-0.2 **Bay Water-Wa2 2/28/07 Gamma Air Filter-Al 3/05/07 Beta (pCiL)<MDA <MDA (10.2 pCi/M 3)1.1+/-0.2 1.2+/-0.2**The nature of these samples precluded splitting them with an independent laboratory.

51 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10-2 pCi/m 3) Analysis Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Air Iodine-A3 Air Iodine-A4 Oysters-la3 Bay Water-Wa2 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Air Iodine-Al Air Iodine-A2 3/05/07 3/05/07 3/05/07 3/05/07 3/05/07 3/05/07 3/05/07 3/05/07 3/05/07 3/05/07 3/28/07 4/27/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 4/09/07 Beta Beta Beta Beta Beta Beta Beta Beta 1.4+/-0.2 1.2+/-0.2 1.5+/-0.2 1.0+/-0.1 1.1+/-0.1 1.0+/-0.1 1.1+/-0.1 1.5+/-0.2 1.4+/-0.2 1.1+/-0.2 1.5+/-0.2 1.0+/-0.1 1.1+/-0.1 1.2+/-0.2 1.1+/-0.2 1.4+/-0.2 1-131 1-131 Gamma Cs-137 Beta Beta Beta Beta Beta Beta Beta Beta Beta 1-131 1-131 (10-2 pCi/m 3)<MDA < MDA **< MDA < MDA **(pCi/Kg)<MDA <MDA <MDA (pCi/L)2+/-2 2+/-2 MDA (10-2 pCi/m 3)1.2+/-0.2 1.3+/-0.2 **1.3+/-0.2 1.2+/-0.2 **1.5+/-0.2 1.6+/-0.2 **2.2+/-0.3 2.4+/-0.3 **1.4+/-0.2 1.2+/-0.2 **1.6+/-0.2 1.6+/-0.2 **1.3+/-0.2 1.5+/-0.2 **1.4+/-0.2 1.2+/-0.2 **1.3+/-0.2 1.4+/-0.2 **(10-2 pCi/m 3)<MDA<MDA<MDA<MDA**The nature of these samples precluded splitting them with an independent laboratory.

52 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10.2 pCi/m 3) Analysis Air Filters-Al Air Filters-A2 Air Filters-A3 Air Filters-A4 Air Filters-A5 Air Filters-SFA1 Air Filters-SFA2 Air Filters-SFA3 Air Filters-SFA4 Air Iodine-A3 Air Iodine-A4 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Soil-SFS3 Soil-SFS4 Vegetation-SFb3 Vegetation-SFb4 5/15/07 5/15/07 5/15/07 5/15/07 5/15/07 5/15/07 5/15/07 5/15/07 5/15/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/07/07 5/31/07 5/31/07 5/31/07 5/31/07 Gamma Be-7 Cs-137 Gamma Gamma Gamma Gamma Gamma Gamma 1-131 1-131 Beta Beta Beta Beta Beta Beta Beta Beta Beta Cs-137 Cs-137 Gamma Gamma<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA 2+/-1<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA (10.2 pCi/m 3)<MDA <MDA **<MDA <MDA **(10-2 pCi/m 3)1.5+/-0.2 1.3+/-0.2 **1.2+/-0.1 1.1+/-0.1 **1.4+/-0.2 1.1+/-0.2 **0.9+/-0.2 1.0+/-0.2 **3.1+/-0.3 2.6+/-0.3 **1.3+/-0.2 1.0+/-0.1 **1.2+/-0.1 1.1+/-0.1 **1.0+/-0.1 1.0+/-0.1 **1.1+/-0.1 1.0+/-0.1 **(pCi/Kg)563+/-103 672+/-1013 708+/-99<MDA <MDA 101 +/-32 (pCi/Kg)<MDA<MDA<MDA<MDA<MDA<MDA**The nature of these samples precluded splitting them with an independent laboratory.

53 R.E. Ginna Nuclear Power Plant 53 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10-2 pCi/m 3) Analysis Shoreline-Wbl Air Iodine-SFA2 Air Iodine-SFA3 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 DR05 DR06 DR07 DR08 DR09 DR10 DR11 SFDR14 SFDR15 DR29 DR31 5/31/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/04/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 6/29/07 Gamma<MDA<MDA 336+/-344 1-131 1-131 Beta Beta Beta Beta Beta Beta Beta Beta Beta TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD (10-2 pCi/m 3)<MDA <MDA **<MDA <MDA **(10.2 pCi/m 3)2.0+/-0.2 2.1+/-0.2 **1.8+/-0.2 1.7+/-0.2 **1.8+/-0.2 1.9+/-0.2 **2.0+/-0.2 2.2+/-0.2 **2.0+/-0.2 2.2+/-0.2 **1.7+/-0.2 1.7+/-0.2 **1.8+/-0.2 1.9+/-0.2 **1.7+/-0.2 2.0+/-0.2 **1.9+/-0.2 1.8+/-0.2 **(mR/90 Days)11.15+/-0.97 9.58+/-0.58 11.13+/-0.56 14.01+/-1.23 10.62+/-0.79 9.91+/-0.70 10.68+/-0.45 21.47+/-2.54 20.42+/-3.30 21.49+/-1.87 14.88+/-2.17 11.94+/-1.49 10.06+/-1.32 11.72+/-1.17 14.60+/-0.71 10.94+/-1.58 10.56+/-0.65 10.96+/-1.42 24.08+/-1.47 23.38+/-5.16 14.11+/-1.99 15.26+/-1.32

- The nature of these samples precluded splitting them with an independent laboratory.

54 RE. Ginna Nuclear Power Plant 54 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10-2 pCi/m 3) Analysis Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Air Iodine-A3 Air Iodine-A4 Vegetation-lbl Vegetation-lb3 Vegetation-lb4 Vegetation-lb5 Vegetation-lb6 Vegetation-lb7 Vegetation-lb8 Vegetation-lb9 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/09/07 7/23/07 7/23/07 7/23/07 7/23/07 7/23/07 7/23/07 7/23/07 7/23/07 8/06/07 8/06/07 8/06/07 8/06/07 8/06/07 8/06/07 8/06/07 8/06/07 8/06/07 Beta Beta Beta Beta Beta Beta Beta Beta Beta 1.8+/-0.2 1.3+/-0.2 1.3+/-0.2 1.8+/-0.2 1.7+/-0.2 1.7+/-0.2 1.8+/-0.2 1.8+/-0.2 1.9+/-0.2 2.0+/-0.2 1.2+/-0.2 1.3+/-0.2 2.0+/-0.2 1.7+/-0.2 1.6+/-0.2 1.8+/-0.2 1.8+/-0.2 1.8+/-0.2 1-131 1-131 Cs-137 Gamma Gamma Gamma Gamma Gamma Gamma Gamma Beta Beta Beta Beta Beta Beta Beta Beta Beta (10.2 pCi/m 3)<MDA <MDA **<MDA <MDA **(pCi/kg)<MDA 18+/-11 <MDA<MDA <MDA <MDA<MDA <MDA <MDA<MDA <MDA <MDA<MDA <MDA <MDA<MDA <MDA <MDA<MDA <MDA <MDA<MDA <MDA <MDA (10-2 pCi/m 3)2.8+/-0.3 2.2+/-0.2 2.6+/-0.2 2.0+/-0.2 2.7+/-0.2 2.7+/-0.2 2.8+/-0.2 2.3+/-0.2 2.9+/-0.2 2.7+/-0.3 2.3+/-0.2 2.2+/-0.2 2.1+/-0.2 2.5+/-0.2 2.4+/-0.2 2.6+/-0.2 2.1+/-0.2 2.7+/-0.2****The nature of these samples precluded splitting them with an independent laboratory.

55 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10-2 pCi/m 3) Analysis Air Iodine-Al Air Iodine-A2 Fish-lal Oysters-la3 Bay Water-Wal Vegetation-lb4 Vegetation-lb6 Air Iodine-A3 Air Iodine-A4 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Air Filters-Al Air Filters-A2 Air Filters-A3 8/06/07 8/06/07 8/22/07 8/22/07 8/31/07 8/13/07 8/13/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 9/10/07 10/15/07 10/15/07 10/15/07 1-131 1-131<MDA<MDA<MDA<MDA*'k"k'k" Cs-137 Gamma Gamma Gamma Gamma 1-131 1-131 Beta Beta Beta Beta Beta Beta Beta Beta Beta (pCi/kg)7+/-9 9+/-10 <MDA<MDA <MDA <MDA (pCi/L)<MDA <MDA <MDA (pCi/kg)<MDA <MDA <MDA<MDA <MDA <MDA (10-2 pCi/m 3)<MDA <MDA **<MDA <MDA **(10-2 pCi/m 3)2.7+/-0.3 2.5+/-0.3 **2.0+/-0.2 2.0+/-0.2 **1.9+/-0.2 2.1+/-0.2 **2.0+/-0.2 2.2+/-0.2 **2.2+/-0.3 2.1+/-0.2 **2.3+/-0.3 2.2+/-0.3 **2.4+/-0.3 2.5+/-0.3 **2.2+/-0.2 2.2+/-0.2 **2.1+/-0.2 2.2+/-0.3 **(10-3 pCi/m 3)Gamma Gamma Gamma<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA**The nature of these samples precluded splitting them with an independent laboratory.

56 R.E. Ginna Nuclear Power Plant 56 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10- pCi/m 3) Analysis Air Filters-A4 Air Filters-A5 Air Filters-SFAl Air Filters-SFA2 Air Filters-SFA3 Air Filters-SFA4 Air Iodine-Al Air Iodine-A2 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFAl Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 10/15/07 10/15/07 10/15/07 10/15/07 10/15/07 10/15/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 10/08/07 Gamma Gamma Gamma Gamma Gamma Gamma<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA 1-131 1-131 Beta Beta Beta Beta Beta Beta Beta Beta Beta (10-2 pCi/m 3)<MDA <MDA **<MDA <MDA **(10-2 pCi/m 3)3.1+/-0.3 3.3+/-0.3 **2.0+/-0.2 2.1+/-0.2 **3.3+/-0.3 3.4+/-0.3 **2.1+/-0.2 2.1+/-0.2 **2.2+/-0.2 2.4+/-0.2 **2.3+/-0.2 2.6+/-0.2 **2.5+/-0.2 2.3+/-0.2 **2.3+/-0.2 2.6+/-0.2 **2.3+/-0.2 2.5+/-0.2 **(10-2 pCi/m 3)11/05/07 11/05/07 11/05/07 11/05/07 11/05/07 11/05/07 11/05/07 11/05/07 11/05/07 Beta Beta Beta Beta Beta Beta Beta Beta Beta 1.9+/-0.2 2.0+/-0.2 1.7+/-0.2 2.1+/-0.2 2.3+/-0.2 2.3+/-0.2 2.2+/-0.2 2.4+/-0.2 2.4+/-0.2 2.0+/-0.2 2.0+/-0.2 1.9+/-0.2 2.2+/-0.2 2.2+/-0.2 2.4+/-0.2 2.2+/-0.2 2.4+/-0.2 2.2+/-0.2****The nature of these samples precluded splitting them with an independent laboratory.

57 R.E. Ginna Nuclear Power Plant 57 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (10.2 pCi/m 3) Analysis Air Iodine-A3 Air Iodine-A5 Bay Water-Wa2 Air Filter-Al Air Filter-A2 Air Filter-A3 Air Filter-A4 Air Filter-A5 Air Filter-SFA1 Air Filter-SFA2 Air Filter-SFA3 Air Filter-SFA4 Air Iodine-Al Air Iodine-A2 Soil-SFS2 Soil-SFS3 Vegetation-SFb2 Vegetation-SFb3 11/05/07 11/05/07 11/30/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/10/07 12/18/07 12/18/07 12/18/07 12/18/07 1-131 1-131<MDA<MDA<MDA<MDA Gamma"k'k Beta Beta Beta Beta Beta Beta Beta Beta Beta 1-131 1-131 (pCi/L)<MDA <MDA <MDA (10-2 pCi/m 3)1.9+/-0.2 1.7+/-0.2 **1.5+/-0.2 1.6+/-0.2 **1.7+/-0.2 1.6+/-0.2 **1.8+/-0.2 2.1+/-0.2 **1.9+/-0.2 1.8+/-0.2 **1.7+/-0.2 1.5+/-0.2 **2.0+/-0.2 2.1+/-0.2 **2.0+/-0.2 1.9+/-0.2 **1.9+/-0.2 1.8+/-0.2 **(10-2 pCi/m 3)<MDA <MDA **<MDA <MDA **(pCi/Kg)103+/-39 131+/-46 99+/-71 502+/-91 565+/-91 565+/-91 (pCi/Kg)Cs-1 37 Cs-137 Gamma Cs-137<MDA 27+/-24<MDA<MDA<MDA<MDA**The nature of these samples precluded splitting them with an independent laboratory.

58 RE. Ginna Nuclear Power Plant 58 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-2 (Continued)

Results of Quality Assurance Program Replicate Sample Type Sample Type of Original Analysis Split And Location Date Analysis Analysis (mR/90 Analysis DR05 DR06 DR07 DR08 DR09 DR10 DR11 SFDR14 SFDR15 DR29 DR31 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 01/03/08 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 13.39+/-1.34 11.79+/-1.17 11.02+/-1.06 10.28+/-1.02 11.26+/-1.37 10.15+/-1.22 16.04+/-1.68 15.27+/-0.99 12.29+/-0.45 11.66+/-0.69 11.60+/-1.19 11.09+/-0.81 11.88+/-2.32 11.18+/-1.12 17.90+/-3.71 17.28+/-2.55 20.18+/-3.71 20.83+/-2.71 16.30+/-2.17 15.39+/-1.05 16.91+/-1.74 15.66+/-1.07

- - - - The nature of these samples precluded splitting them with an independent laboratory.

59 R.E. Ginna Nuclear Power Plant 59 R.E. Giana Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 TABLE C-3 Teledyne Brown Engineering's Typical MDAs for Gamma Spectrometry Selected Bay Water Fish Shellfish Sediment Vegetation Particulates Nuclides pCi/I pCi/kg pCi/kg pCi/kg pCi/kg 10-3 pCi/m 3 H-3 175 -- -- -- -- --Na-22 1 8 3 12 6 5 Cr-51 12 105 4 104 50 63 Mn-54 1 9 3 12 5 4 Co-58 1 9 4 9 4 5 Fe-59 3 28 9 24 10 12 Co-60 1 9 4 12 5 6 Zn-65 2 20 8 25 10 9 Nb-95 1 12 7 14 6 9 Zr-95 2 18 8 20 9 9 Ru-106 9 75 30 90 41 40 Ag-110m 1 10 10 10 5 4 Te-129m 16 131 60 162 79 95 1-131 4 65 30 35 22 74 Cs-134 1 8 4 10 5 4 Cs-137 1 9 4 10 5 4 BaLa-140 3 32 15 25 14 36 Ce-144 7 40 16 54 26 18 60 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 APPENDIX D Land Use Survey Summary of Appendix D Content: Appendix D contains the results of a Land Use Survey conducted around R. E. Ginna Nuclear Power Plant during this operating period. A table listing the raw data of this survey and a discussion of the results are included in this appendix.61 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 Land Use Survey Discussion A Land Use Survey was conducted to identify the location of the nearest milk animal, the nearest residence, and the nearest garden greater than 50 square meters in each of the nine sectors within a 5-mile radius of the power plant. A detailed description of the Land Use Survey is given in a separate document (Ref. 4). The position of the nearest residence and garden and animals producing milk for human consumption in each sector is provided in Table D-1.Table D-1 Land Use Survey Distances Sector Distance to Nearest Distance to Nearest Distance to Milk Residence Garden Producing Animals E 1260 m N/A N/A ESE 1050 m Onsite Garden N/A SE 610 m N/A 8270 m SSE 660 m Onsite Supplemental N/A Garden S 1560 m N/A N/A SSW 760 m N/A N/A SW 660 m N/A N/A WSW 1350 m N/A N/A W 1160 m N/A N/A The closest residence is situated in the SE sector (610 meter from the power plant), the nearest garden is in the SSE sector (660 meters), and the nearest milk producing animals was in the SE sector (8,270 meters).Changes from Previous Years: The following land use changes have occurred over the within a 5-mile radius of the power plant: U U U U Development of single family homes continues at a pace consistent with prior years.Interviews with area farmers indicate that the number of acres farmed will continue to decrease.No new agricultural land use was noted.No new food producing facilities were noted.62 R.E. Ginna Nuclear Power Plant 62 R.E. Ginna Nuclear Power Plant January 1, 3007 -December 31, 2007 Docket No. 50-244 Milk Animal Locations:

The milk animal location with a 5-mile radius of the power plant are as follows: " Eaton Farm -- 6747 Salmon Creek Road, Williamson, NY" No new milk producing animals were identified in the 2007 Census.63 R.E. Ginna Nuclear Power Plant 63 R.E. Ginna Nuclear Power Plant

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