Text

2010 Annual Radiological Environmental Operating Report
	ML11126A183
Person / Time
Site:	Millstone
Issue date:	04/28/2011
From:	Macmanus R; Dominion Nuclear Connecticut
To:	; Document Control Desk, Office of Nuclear Reactor Regulation, NRC/FSME
References
	11-226
	Download: ML11126A183 (143)
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Dominion Nuclear Connecticut, Inc.

Millstone Power Station

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Rope Ferry Road Waterford, CT 06385

'APR 28 2011 U.S. Nuclear Regulatory Commission Serial No. 11-=226 Attention: Document Control Desk MPS Lic/GJC RO Washington, DC 20555 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 1, 2, AND 3 2010 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT This letter transmits the Annual Radiological Environmental Operating Report for the Millstone Power Station, for the period January 2010 through December 2010. This satisfies the provisions of Section 5.7.2 of Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (PDTS), and Sections 6.9.1.6a and 6.9.1.3 of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively.

If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444 4301.

Sincerely, R. K. MacManus Director, Nuclear Station Safety and Licensing

Serial No.11-226 2010 Annual Radiological Environmental Operating Report Page 2 of 4 Attachments: 1 Commitments made in this letter:

1. None.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 S. J. Giebel NRC Project Manager Millstone Unit 1 U.S. Nuclear Regulatory Commission Two White Flint North, Mail Stop T-8 F5 11545 Rockville Pike Rockville, MD 20852-2738 L. A. Kauffman NRC Inspector U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 T. A. Moslak NRC Inspector U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 J. D. Hughey NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-BIA 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.11-226 2010 Annual Radiological Environmental Operating Report Page 3 of 4 (2copies)

Director Bureau of Air Management Monitoring & Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 A. Honnellio Regional Radiation Representative (EPA Region 1, Boston)

U. S. Environmental Protection Agency (Region 1) 5 Post Office Square Suite 100 Boston, MA 02109 G. Allen Jr.

Department of Health and Human Services U. S. Food and Drug Administration 90 Madison St. Room 402 Worcester, MA 01608 R. Stein Chairman Cornncticut Siting Council 10 Franklin Square New Britain, CT 06051 P. Kelley Waterford-East Lyme Shellfish Commission Waterford Town Hall Waterford, CT 06385 J. A. Martinez American Nuclear Insurers 95 Glastonbury Blvd.

Glastonbury, CT 06033 D. Carey Connecticut Department of Agriculture Aquaculture Division P. 0. Box 97 Millford, CT 06460

Serial No.11-226 2010 Annual Radiological.Environmental Operating Report Page 4 of 4 D. Steward First Selectman Town of Waterford Waterford Town Hall Waterford, CT 06385 P. Formica First Selectman Town of-East Lyme PO Box 519 Niantic, CT 06357 D. M. Rose City Manager 181 State Street New London, CT 06320 University Of Connecticut Library Serials Department Storrs, CT 06268

Serial No.11-226 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 ATTACHMENT 1 2010 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Millstone Power Station 2010 Radiological Environmental Operating Report January 1, 2010 - December 31, 2010 Dominion Nuclear Connecticut, Inc.

Unit License Docket 1 DPR-21 50-245 2 DPR-65 50-336 3 NPF-49 50-423 21Dominiow

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT MILLSTONE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2010 MILLSTONE UNIT 1,DOCKET NO. 50-245 MILLSTONE UNIT 2, DOCKET NO. 50-336 MILLSTONE UNIT 3, DOCKET NO. 50-423 By the Dominion Nuclear Connecticut, Inc.

Waterford, Connecticut

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

- TABLE OF CONTENTS -

EXECUTIVE SUM MARY ................................................................................................ i

1. INTRODUCTION ....................................................................................... 1-1 1.1 Overview ........................................................................................... 1-1 1.2 Radiation and Radioactivity .............................................................. 1-1 1.3 Sources of Radiation ........................................................................ 1-2 1.4 Nuclear Reactor Operations ............................................................. 1-3 1.5 Radioactive Effluent Control ............................................................. 1-8 1.6 Radiological Im pact on Hum ans ..................................................... 1-11

2. PROGRAM DESCRIPTION ........................................................................... 2-1 2.1 Sam pling Schedule and Locations ................................................... 2-1 2.2 Sam ples Collected During Report Period ......................................... 2-7

3. RADIOCHEMICAL RESULTS ........................................................................ 3-1 3.1 Sum m ary Table ................................................................................ 3-1 3.2 Data Tables .................................................................................... 3-20

4. DISCUSSION OF RESULTS ......................................................................... 4-1 4.1 Gam m a Exposure Rate (Table 1) .................................................... 4-1 4.2 Air Particulate Gross Beta Radioactivity (Table 2) ........................... 4-3 4.3 Airborne Iodine (Table 3) ................................................................. 4-4 4.4 Air Particulate Gam ma (Table 4A-D) ............................................... 4-4 4.5 Air Particulate Strontium (Table 5) ................................................... 4-4 4.6 Soil (Table 6) ................................................................................... 4-5 4.7 Cow Milk (Table 7) ........................................................................... 4-5 4.8 Goat Milk (Table 8) .......................................................................... 4-5 4.9 Pasture Grass and Feed (Table 9) .................................................. 4-6 4.10 W ell W ater (Table 10) ...................................................................... 4-6 4.11 Meat (Table 11) ............................................................................... 4-7 4.12 Fruits and Vegetables (Table 12) .................................................... 4-7 4.13 Broad Leaf Vegetation (Table 13) .................................................... 4-7 4.14 Seawater (Table 14) ........................................................................ 4-7 4.15 Bottom Sedim ent (Table 15) .......................................................... 4-10 4.16 Aquatic Flora (Table 16) ................................................................ 4-10 4.17 Fish (Tables 17A and 17B) ............................................................ 4-11 4,17.1 Flounder (Table 17A) ....................................................... 4-11 4,17.2 Fish - Other (Table 17B) ................................................... 4-11 4.18 Mussels (Table 18) ........................................................................ 4-11 4.19 Oysters (Table 19) ......................................................................... 4-11 4.20 Clam s (Table 20) ........................................................................... 4-12 4.21 Scallops (Table 21) ........................................................................ 4-12 4.22 Lobsters (Table 22) ........................................................................ 4-12

5. OFFSITE DOSE EQUIVALENT COMMITMENTS ............................................ 5-1

6. DISCUSSION ............................................................................................... 6-1

7. REFERENCES ............................................................................................ 7-1 APPENDIX A - LAND USE CENSUS FOR 2010 ........................................ A-1 APPENDIX B - DNC QA PROGRAM .................................................................... B-1 APPENDIX C -

SUMMARY

OF INTERLABORATORY COMPARISONS .............. C -1 APPENDIX D - 2009 Errata .................................................................................. D-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 EXECUTIVE

SUMMARY

INTRODUCTION This report summarizes the results of the Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Millstone Power Station (MPS) during the period from January 1 to December 31, 2010. This document has been prepared in accordance with the requirements of Millstone Unit 1, Unit 2 and 3 Technical Specifications.

The REMP has been established to monitor the radiation and radioactivity released to the environment as a result of Millstone Station's operation. This program, initiated in April 1967, includes the collection, analysis, and evaluation of radiological data in order to assess the impact of Millstone Station on the environment and on the general public.

SAMPLING AND ANALYSIS The environmental sampling media collected in the vicinity of MPS and at distant locations included air particulate filters, charcoal cartridges, soil, goat milk, pasture grass, hay, well water, broadleaf vegetation, fruits, vegetables, seawater, bottom sediment, aquatic flora, fish, mussels, oysters, clams and lobster.

During 2010, there were 1094 samples collected from the atmospheric, aquatic, and terrestrial environments. In addition, 175 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs).

A small number of inadvertent issues were encountered in 2010 in the collection of environmental samples in accordance with the Millstone Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM). Equipment failures and electrical outages resulted in a small number of instances in which lower than normal sampling volumes were collected at the airborne monitoring stations. However, in all cases sufficient volume was obtained to perform all the appropriate analyses. Therefore, all 416 air particulate and charcoal cartridges were collected and analyzed as required. A full description of all discrepancies encountered with the environmental monitoring program is presented in the Notes for the Data Tables of this report.

There were 1441 analyses performed on the environmental media samples. The AREVA-NP Environmental Laboratory of Westborough, MA, performed these analyses for the first half of 2010. Teledyne Brown Engineering, Inc. of Knoxville, TN performed the analyses for the second half of 2010. Samples were analyzed as required by the Millstone REMODCM.

LAND USE CENSUS The annual land use census in the vicinity of Millstone Station was conducted as required by the Millstone REMODCM between July 15 and December 31, 2010. Although broadleaf sampling may be used in lieu of a garden census, gardens were included in the 2010 census. Only vegetable gardens having an area of more than 500 square feet need to be identified. Due to the difficulty of measuring individual gardens, the nearest garden within each directional sector identified by a drive-by survey is listed in Appendix A. No new dairy animals within 10 miles of the Station were located during the census. Monthly broad leaf sampling was also performed; it may be used in lieu of the garden census.

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 RADIOLOGICAL IMPACT TO THE ENVIRONMENT Most samples collected as part of the Millstone REMP continued to contain detectable amounts of naturally-occurring and man-made radioactive materials. There was no plant related activity detected in any of the terrestrial samples. Offsite ambient radiation measurements using environmental TLDs beyond the site boundary ranged between 55 and 90 milliRoentgens per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for Connecticut.

Monitoring of the aquatic environment in the area of the discharge indicated the presence of the following station related radionuclides: Tritium and silver-I 1Om. These station related nuclides were only found onsite inside the mixing zone of the quarry discharge at levels that were expected from routine plant operation. No plant related activity was detected in any offsite samples. The predominant radioactivity for all samples was from non-plant related sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.

RADIOLOGICAL IMPACT TO THE GENERAL PUBLIC During 2010, radiation doses to the general public as a result of Millstone Station's operation continued to be well below the federal limits and much less than the dose due to other sources of man-made (e.g., X-rays, medical) and naturally-occurring (e.g., cosmic, radon) radiation.

The calculated total body dose to the maximally exposed member of the general public from radioactive effluents and ambient radiation resulting from MPS operations for 2010 was approximately 0.5 mrem for the year. This conservative estimate is well below the Environmental Protection Agency's (EPA) annual dose limit to any member of the general public and is a fraction of a percent of the typical dose received from natural and other sources of man-made radiation.

CONCLUSIONS The 2010 Radiological Environmental Monitoring Program for Millstone Station resulted in the collection and analysis of over a thousand environmental samples and measurements.

The data obtained were used to determine the impact of Millstone Station's operation on the environment and on the general public.

An evaluation of direct radiation measurements, environmental sample analyses, and dose calculations indicates all applicable federal criteria were met. Furthermore, radiation levels and resulting doses from station operation were a small fraction of those attributed to natural and man-made background radiation.

Based on this information, there is no significant radiological impact on the environment or on the general public due to Millstone Station's operation.

ii

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

1. INTRODUCTION This section provides an overview of the Millstone Power Station Radiological Environmental Monitoring Program. It also includes background information to allow a reader to have an informed understanding of radiation and nuclear power operation.

1.1 Overview The Radiological Environmental Monitoring Program for 2010 performed by Dominion Nuclear Connecticut for Millstone Nuclear Power Station (MPS) is discussed in this report.

Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be established to monitor radiation and radioactivity in the environment (Reference 1). This report, published annually per Millstone Station's Technical Specifications (section 5.7.2 for Unit 1, section 6.9.1.6 for Unit 2 and Section 6.9.1.3 for Unit 3), summarizes the results of measurements of radiation and radioactivity in the environment in the vicinity of the Millstone Station and at distant locations during the period January 1 to December 31, 2010.

The Radiological Environmental Monitoring Program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With emphasis on the critical radiation exposure pathways to humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include, but are not limited to: air, soil, goat milk, pasture grass, hay, meat, well water, broadleaf vegetation, fruits, vegetables, seawater, bottom sediment, aquatic flora, fish, mussels, oysters, clams and lobster. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels. The TLDs are processed and the environmental samples are analyzed to measure the very low levels of radiation and radioactivity present in the environment as a result of MPS operation and other natural and man-made sources. These results are reviewed by MPS's radiological staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others for over 30 years.

In order to more fully understand how a nuclear power plant impacts humans and the environment, background information on radiation and radioactivity, natural and man-made sources of radiation, reactor operations, radioactive effluent controls, and radiological impact on humans is provided. It is believed that this information will assist the reader in understanding the radiological impact on the environment and humans from the operation of Millstone Station.

1.2 Radiation and Radioactivity All matter is made of atoms. An atom is the smallest component into which matter can be broken down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particles that is given off from atoms in an excited state (e.g., unstable, radioactive atoms).

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium.

Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are cesium-137 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium-90, and cobalt-60.

Radiation is measured in units of millirem, much like temperature is measured in degrees. A millirem (mrem) is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 600 mrem (References 2, 3, 4, and 5). The per capita dose has increased substantially since the mid 1980's because of the increased usage of medical procedures involving exposure to radiation (see Reference 3).

Radioactivity is measured in Curies. Levels of radioactivity commonly seen in the environment are typically a small fraction of a Curie, therefore radioactivity in the environment is typically measured in picocuries. One picocurie (pCi) is equal to 0.037 disintegrations per second (2.22 disintegrations per minute).

1.3 Sources of Radiation As mentioned previously, naturally occurring radioactivity has always been a part of our environment. Table 1.3 shows the sources and doses of radiation from natural and man-made sources.

Table 1.3 Radiation Sources and Correspondinci Doses (1)

NATURAL MAN-MADE Radiation Dose Radiation Dose Source (millirem/year) Source (m ilirem/year)

Internal, inhalation(2) 228 Medical(3) 300 External, space 33 Consumer(4) 13 Internal, ingestion 29 Industrial, security, (5) 0.3 External, terrestrial 21 Occupational 0.5 Weapons Fallout < 1 Nuclear Power Plants < 1 Approximate Total 311 Approximate Total 314 (1) information from References 3 and 4 (2) from radon and thoron (3) includes CT (147 millirem), nuclear medicine (77 mrem), interventional fluoroscopy (43 mrem) and conventional radiography and fluoroscopy (33 mrem)

(4) primarily from cigarette smoking (4.6 mrem), commercial air travel (3.4 mrem), building materials (3.5 mrem) and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational and research 1-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Cosmic radiation (external, space) from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 30 millirem/year), the ground we walk on (about 20 millirem/year) and the air we breathe (about 230 millirem/year). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil.

Residents at some locations in Colorado, New York, Pennsylvania, New Jersey and even Connecticut have a higher annual dose as a result of higher levels of radon/thoron gases in these areas. In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 310 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is approximately 300 millirem.

Consumer products/uses, such cigarettes, building materials and commercial air travel contribute about 10 millirem/year. Much smaller doses result from weapons fallout (less than 1 millirem/year) and nuclear power plants (less than 1 mrem/year). Typically, the average person in the United States receives approximately 310 millirem per year from man-made sources.

1.4 Nuclear Reactor Operations Millstone Station generates about 2100 megawatts of electricity at full power, which provides approximately one-half of the power consumed in the State of Connecticut. Unit 2 and Unit 3 are pressurized water reactors (Unit 1, which is permanently shutdown, was a boiling water reactor). The nuclear station is located on an approximate 500-acre site about 5 kilometers (three miles) west of New London, CT. Commercial operation of Unit 2 began in December 1975 and Unit 3 in May 1986.

Millstone Station was operational during most of 2010, with the exception of a refueling outage at Unit 3 and mini-outages at each unit. Unit 3 refueling outage was performed between April 1 0 th and May 1 8 th. The resulting monthly capacity factors are presented in Table 1.4.

Nuclear-generated electricity is produced by many of the same techniques used for conventional oil and coal-generated electricity. Both systems use heat to boil water in order to produce steam. The steam turns a turbine, which turns a generator, producing electricity.

In both cases, the steam passes through a condenser where it changes back into water and re-circulates back through the system. The cooling water source for Millstone Station is the Niantic Bay.

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE 1.4 MPS OPERATING CAPACITY FACTOR DURING 2010 (Based on designed electrical rating)

Month Unit 2 Percent Capacity Unit 3 Percent Capacity January 100.1% 82.7%*

February 91.1%* 101.5%

March 98.5% 101.5%

April 100.0% 32.7%**

May 90.9%* 39.1%**

June 99.9% 101.2%

July 99.6% 100.5%

August 99.4% 88.0%*

September 99.5% 100.1%

October 99.6% 101.0%

November 84.6%* 101.3%

December 93.6% 101.3%

Annual Average 96.4% 87.5%

shutdown for mini-outages these months

- shutdown for refueling during these months The key difference between nuclear power and conventional power is the source of heat used to boil the water. Conventional plants burn fossil fuels in a boiler, while nuclear plants use uranium fission in a nuclear reactor.

Inside the reactor, a nuclear reaction called fission takes place. Particles, called neutrons, strike the nucleus of a uranium-235 atom, causing it to split into fragments called radioactive fission products. The splitting of the atoms releases both heat and more neutrons. The newly-released neutrons then collide with and split other uranium atoms, thus making more heat and releasing even more neutrons, and on and on until the uranium fuel is depleted or spent. This process is called a chain reaction. When this chain reaction is self sustaining, the reactor is called "critical."

The operation of a nuclear reactor results in the release of small amounts of radioactivity and low levels of radiation. The radioactivity originates from two major sources, radioactive fission products and radioactive activation products. Radioactive fission products, as illustrated in Figure 1.4-1 (Reference 6), originate from the fissioning of the nuclear fuel.

These fission products get into the reactor coolant from their release by minute amounts of uranium on the outside surfaces of the fuel cladding, by diffusion through the fuel pellets and cladding and, on occasion, through defects or failures in the fuel cladding. These fission products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive fission products on the pipes and equipment emit radiation. Examples of some fission products are krypton-85 (Kr-85),

strontium-90 (Sr-90), iodine-131 (1-131), xenon-133 (Xe-133), and cesium-137 (Cs-137).

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Nuclear Fission Fission is the splitting of atoms (e.g., Uranium-235) by a neutron to release heat and more neutrons, creating a chain reaction. Radiation and fission products are by-products of the process.

_"Rad i.ation Uranium Neutrons R~adiatiion Uranium Uranium Fission Products Figure 1.4-1 Radioactive Fission Product Formation 1-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Radioactive activation products (see Figure 1.4-2), on the other hand, originate from two sources. The first is by neutron bombardment of the hydrogen, oxygen and other gas (helium, argon, nitrogen) molecules in the reactor cooling water. The second is a result of the fact that the internals of any piping system or component are subject to minute yet constant corrosion from the reactor cooling water. These minute metallic particles (for example: nickel, iron, cobalt, or magnesium) are transported through the reactor core into the fuel region, where neutrons may react with the nuclei of these particles, producing radioactive products. So, activation products are nothing more than ordinary naturally-occurring atoms that are made unstable or radioactive by neutron bombardment. These activation products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive activation products on the pipes and equipment emit radiation. Examples of some activation products are manganese-54 (Mn-54), iron-59 (Fe-59), cobalt-60 (Co-60), and zinc-65 (Zn-65).

n-- collision with Stable Radioactive, Neutron Cobalt Nucleus Cobalt Nucleus Figure 1.4-2 Radioactive Activation Product Formation At Millstone Nuclear Power Station there are five independent protective barriers that confine these radioactive materials. These five barriers, which are shown in Figure 1.4-3 (Reference 6), are:

0 fuel pellets; 0 fuel cladding; 0 reactor vessel and associated piping and equipment; 0 primary containment and, 0 secondary containment (enclosure building).

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 SIMPLIFIED DIAGRAM OF A PRESSURIZED WATER REACTOR Pressurized water reactor-a common type of Light Water WAT ER WASTE HEAT TO TI"V FNV~NHMIIT Figure 1.4-3 The ceramic uranium fuel pellets provide the first barrier. Most of the radioactive fission products are either physically trapped or chemically bound between the uranium atoms, where they will remain. However, a few fission products that are volatile or gaseous may diffuse through the fuel pellets into small gaps between the pellets and the fuel cladding.

The second barrier, the fuel cladding, consists of zirconium alloy tubes that confine the fuel pellets. The small gaps between the fuel and the cladding contain the noble gases and volatile iodines that are types of radioactive fission products. This radioactivity can diffuse to a small extent through the fuel cladding into the reactor coolant water.

The third barrier consists of the reactor pressure vessel, steel piping and equipment that confine the reactor cooling water. The reactor pressure vessel, which holds the reactor fuel, is typically a steel tank 40 feet high by 14 feet in diameter with walls about five to nine inches thick. These vessels and associated piping provide containment for radioactivity in the primary coolant and the reactor core. However, during the course of operations and maintenance, small amounts of radioactive fission and activation products can escape through valve leaks or upon breaching of the primary coolant system for maintenance.

The fourth barrier is the primary containment. It is a cylindrical enclosure with approximately five-foot thick steel reinforced concrete walls lined by steel on the inside. Small amounts of radioactivity may be released from primary containment during operation to maintain proper containment pressure and during maintenance and refueling outages.

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 The fifth barrier is the secondary containment or enclosure building. The enclosure building is a steel building that surrounds the primary containment. This barrier is an additional safety feature at Millstone's reactor units to contain radioactivity that may escape from the primary containment. This enclosure building is equipped with a filtered ventilation system that is used when needed to reduce the radioactivity that escapes from the primary containment.

The five barriers confine most of the radioactive fission and activation products. However, small amounts of radioactivity do escape via mechanical failures and maintenance on valves, piping, and equipment associated with the reactor cooling water system. The small amounts of radioactive liquids and gases that do escape the various containment systems are further controlled by the liquid purification and ventilation filtration systems. Also, prior to a release to the environment, control systems exist to collect and purify the radioactive effluents in order to reduce releases to the environment to as low as is reasonably achievable. The control of radioactive effluents at Millstone Station will be discussed in more detail in the next section.

1.5 Radioactive Effluent Control The small amounts of radioactive liquids and gases that might escape the first two barriers are purified in the liquid and gaseous waste treatment systems, then monitored for radioactivity, and released only if the radioactivity levels are below the federal release limits.

Radioactivity released from the liquid effluent system to the environment is limited, controlled, and monitored by a variety of systems and procedures which include:

reactor water cleanup system;

liquid radwaste treatment system;

sampling and analysis of the liquid radwaste tanks; and,

liquid waste effluent discharge radioactivity monitor.

The purpose of the reactor water cleanup system is to continuously purify the reactor cooling water by removing radioactive atoms and non-radioactive impurities that may become activated by neutron bombardment. A portion of the reactor coolant water is diverted from the primary coolant system and is directed through ion exchange resins where radioactive elements, dissolved and suspended in the water, are removed through chemical processes.

The net effect is a substantial reduction of the radioactive material that is present in the primary coolant water and consequently the amount of radioactive material that might escape from the system.

Reactor cooling water that might escape the primary cooling system and other radioactive water sources are collected in floor and equipment drains. These drains direct this radioactive liquid waste to large holdup tanks. The liquid waste collected in the tanks is purified again using the liquid radwaste treatment system, which consists of a filter and ion exchange resins.

Processing of liquid radioactive waste results in large reductions of radioactive liquids discharged into Niantic Bay. Wastes processed through liquid radwaste treatment can be purified and when necessary the processed liquid is re-used in plant systems.

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Prior to release, the radioactivity in the liquid radwaste tank is sampled and analyzed to determine if the level of radioactivity is below the release limits and to quantify the total amount of radioactive liquid effluent that would be released. If the levels are below the federal release limits, the tank is drained to the liquid effluent discharge header.

This liquid waste effluent discharge line is provided with a shielded radioactivity monitor. This detector is connected to a radiation level meter and a recorder in the Control Room. The radiation alarm is set so that the detector will alarm before radioactivity levels exceed the release limits. The liquid effluent discharge header has an isolation valve. If an alarm is received, the liquid effluent discharge valve will automatically close, thereby terminating the release to the Niantic Bay and preventing any liquid radioactivity from being released that may exceed the release limits. An audible alarm notifies the Control Room operator that this has occurred.

Some liquid waste sources, which have a low potential for containing radioactivity, and/or may contain very low levels of contamination, may be discharged directly to the Long Island Sound. One such source of liquid is the turbine building sump. However, periodic representative samples are collected for analysis of radioactivity content to track the amounts of radioactivity being discharged.

Another means for adjusting liquid effluent concentrations to below federal limits is by mixing plant cooling water from the condenser with the liquid effluents in the discharge canal. This larger volume of cooling water further lowers the radioactivity levels to below the release concentration limits.

The preceding discussion illustrates that many controls exist to reduce the radioactive liquid effluents released to the Niantic Bay to as far below the release limits as is reasonably achievable.

Radioactive releases from the radioactive gaseous effluent system to the environment are limited, controlled, and monitored by a variety of systems and procedures which include:

" containment building ventilation system;

" containment building radioactivity monitors;

sampling and analysis of containment building vent and purge effluents;

process gas treatment system;

auxiliary building (and engineered safeguards and fuel building for Unit 3) ventilation system;

stack and vent effluent radioactivity monitors;

sampling and analysis of stack and vent effluents;

process radiation monitors; and

steam jet air ejector (SJAE) monitor The primary sources of gaseous radioactive waste are degassing of the primary coolant, gaseous liquid drains, and gaseous vents. Additional sources of gaseous waste activity include ventilation air released from the auxiliary building and purging and venting of the containment building. The radiation level meter and recorders for the effluent radioactivity monitors are located in the Control Room. The plant process computer aids in tracking the monitor readings. To supplement the information continuously provided by the detector, air samples are taken periodically from the containment, stack and vents. These samples are analyzed to quantify the total amount of tritium and radioactive gaseous and particulate effluents released.

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Gases from the primary coolant are held up in waste gas decay tanks for decay at Unit 2.

Gaseous waste at Unit 3 is purified through a process gas system, consisting of high-efficiency particulate air filters and charcoal adsorber beds. Gases from periodic venting of the Unit 2 containment are released through a similar process system (Enclosure Building Filtration System) while gases from the Unit 3 containment vacuum pumps are released without treatment. If necessary, Unit 3 containment air can be filtered by an internal particulate and charcoal treatment system. Containment purges (purge is the forced ventilation process while containment vents are pressure releases) for Unit 2 are filtered by high-efficiency particulate filters while at Unit 3 these are not normally filtered. If necessary, particulate and charcoal filters can be used for these purges.

The auxiliary building ventilation system provides for ventilation of the auxiliary building and enclosure building (and service building and contiguous areas, waste disposal building, and fuel building for Unit 3, for Unit 2 these are all part of the auxiliary building). Normally, the air from the ventilation of these areas will exhaust through the ventilation vent (which has a particulate filter for Unit 2). If exhaust from these areas reaches a predetermined level, the ventilation flow can be diverted by operator control to a particulate and charcoal filtration system.

Therefore, for both liquid and gaseous releases, radioactive effluent control systems exist to collect and purify the radioactive effluents in order to reduce releases to the environment to as low as is reasonably achievable. The effluents are always monitored, sampled and analyzed to make sure that radioactivity levels are below the release limits. If the release limits are being approached, isolation valves in some of the waste effluent lines will automatically shut to stop the release, or Control Room operators can implement procedures to ensure that federal regulatory limits are always met.

1-10

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 1.6 Radiological Impact on Humans The final step in the effluent control process is the determination of the radiological dose impact to humans and comparison with the federal dose limits to the public. This step is performed in three stages. As mentioned previously, the purpose of continuous radiation monitoring and periodic sampling and analysis is to measure the quantities of radioactivity being released to determine compliance with the radioactivity release limits. This is the first stage for assessing releases to the environment.

The second stage is calculations of the dose impact to the general public from Millstone Station's radioactive effluents are performed. The purpose of these calculations is to periodically assess the doses to the general public resulting from radioactive effluents to ensure that these doses are being maintained as far below the federal dose limits as is reasonably achievable. This is the second stage for assessing releases to the environment.

The types and quantities of radioactive liquid and gaseous effluents released from Millstone Station during each given year are reported to the Nuclear Regulatory Commission annually in the Radiological Effluent Release Report (RERR). Similar to this report, the RERR is submitted annually to the Nuclear Regulatory Commission. Section 5 of this report discusses the detailed dose calculations from the RERR and provides a comparison to REMP dose calculations. The liquid and gaseous effluents were well below the federal release limits and were a small percentage of the MPS REMODCM effluent control limits.

The measurements of the physical and chemical nature of the effluents are used to determine how the radionuclides will interact with the environment and how they can result in radiation exposure to humans. The environmental interaction mechanisms depend upon factors such as the hydrological (water) and meteorological (atmospheric) characteristics in the area. Information on the water flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere.

The most important type of information that is used to evaluate the radiological impact on humans is data on the use of the environment. Information on fish and shellfish consumption, boating usage, beach usage, locations of cows and goats, locations of residences, locations of gardens, drinking water supplies, and other usage information are utilized to estimate the amount of radiation and radioactivity received by the general public.

The radiation exposure pathway to humans is the path radioactivity takes from its release point at Millstone Station to its effect on man. The movement of radioactivity through the environment and its transport to humans is portrayed in Figure 1.6.

1-11

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 EXAMPLES OF MILLSTONE STATION'S RADIATION EXPOSURE PATHWAYS

.. ... ......I...

..I...

LIQUID EFFLUENTS

3. DIRECT RADIATION (STATION),,, 2. AIR /INHALATION

/

4, DIRECT RADIATION

_ (SOIL DEPOSITION) 1. DIRECT RADIATION (AIR SUBMERSION) c/

1. SHORELINE DIRECT RADIATION (FISHING, PICNICING)

DEPOSITION

2. DIRECT RADIATION (IMMERSION IN OCEAN, BOATING, SWIMMING) 6 CONSUMPTION DEPOSITION (MILK AND MEAT)

INGESTION

3. CONSUMPTION V-1, (FISH, SHELLFISH)

Figure 1.6 Radiation Exposure Pathways 1-12

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 There are three major pathways in which liquid effluents affect humans:

external radiation from liquid effluents that deposit and accumulate on the shoreline;

external radiation from immersion in ocean water containing radioactive liquids; and,

internal radiation from consumption of fish and shellfish containing radioactivity absorbed from the liquid effluents.

There are six major ways in which gaseous effluents affect humans:

external radiation from an airborne plume of radioactivity;

internal radiation from inhalation of airborne radioactivity;

external radiation from deposition of radioactive effluents on soil;

ambient (direct) radiation from contained sources at the power plant;

internal radiation from consumption of vegetation containing radioactivity deposited on the vegetation from airborne deposition and absorbed from the soil due to ground deposition of radioactive effluents; and,

internal radiation from consumption of milk and meat containing radioactivity deposited on forage that is eaten by cattle and other livestock.

In addition, ambient (direct) radiation emitted from contained sources of radioactivity at MPS contributes to radiation exposure in the vicinity of the plant. For example, small amounts of ambient radiation result from low-level radioactive waste being processed and stored at the site prior to shipping and disposal. Also, the operation of the ISFSI (Independent Spent Fuel Storage Installation, operation began in 2005) results in very small amounts of direct radiation at the site boundary.

The radiological dose impact on humans is based both on effluent analyses and modeling and on direct measurements of radiation and radioactivity in the environment. When MPS-related radioactivity is detected in samples that represent a plausible exposure pathway, the resulting dose from such exposure is assessed (see Sections 4 and 5). However, the operation of Millstone Power Station results in releases of only small amounts of radioactivity, and, as a result of dilution in the atmosphere and ocean, even the most sensitive radioactivity measurement and analysis techniques cannot usually detect these tiny amounts of radioactivity above thatwhich is naturally present in the environment. Therefore, radiation doses are calculated using radioactive effluent release data and computerized dose calculations that are based on conservative NRC-recommended models that tend to result in over-estimates of the resulting dose. These computerized dose calculations are performed by Dominion Nuclear personnel. These computer codes use the guidelines and methodology set forth by the NRC in Regulatory Guide 1.109 (Reference 7). The dose calculations are documented and described in detail in the Millstone Nuclear Power Station's Radiological Effluent Monitoring and Offsite Dose Calculation Manual (Reference 8), which has been reviewed by the NRC.

It should be emphasized that because of the conservative assumptions made in the computer code calculations, the maximum hypothetical dose to an individual is considerably higher than the dose that would actually be received by a real individual.

After dose calculations are performed, the results are compared to the federal dose limits for the public. The two federal agencies that are charged with the responsibility of protecting the public from radiation and radioactivity are the United States Nuclear Regulatory Commission (NRC) and the United States Environmental Protection Agency (EPA).

1-13

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 The NRC, in 10CFR 20.1301 (Reference 9) limits the levels of radiation to unrestricted areas resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:

less than or equal to 100 mrem per year to the total body.

In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees. Conformance to these guidelines ensures that nuclear power reactor effluents are maintained as far below the legal limits as is reasonably achievable.

The NRC, in 10CFR 50 Appendix I (Reference 10) establishes design objectives for the dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:

less than or equal to 3 mrem per year to the total body; and,

less than or equal to 10 mrem per year to any organ.

The air dose due to release of noble gases in gaseous effluents is restricted to:

less than or equal to 10 mrad per year for gamma radiation; and,

less than or equal to 20 mrad per year for beta radiation.

The dose to a member of the general public from iodine-131, tritium, and all particulate radionuclides with half-lives greater than 8 days in gaseous effluents is limited to:

less than or equal to 15 mrem per year to any organ.

The EPA, in 40CFR190.10 Subpart B (Reference 11), sets forth the environmental standards for the uranium fuel cycle. During normal operation, the annual dose to any member of the public, at or beyond the site boundary, from the entire uranium fuel cycle shall be limited to:

less than or equal to 25 mrem per year to the total body;

less than or equal to 75 mrem per year to the thyroid; and,

less than or equal to 25 mrem per year to any other organ.

The summary of the 2010 radiological impact for Millstone Station and comparison with the EPA dose limits and Appendix I guidelines is presented in Section 5 of this report.

The third stage of assessing releases to the environment is the Radiological Environmental Monitoring Program (REMP). The description and results of the REMP at Millstone Power Station during 2010 is discussed in Sections 2 through 4 of this report.

1-14

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

2. PROGRAM DESCRIPTION 2.1 Samplinq Schedule and Locations The sample locations and the sample types and frequency of analysis are given in Tables 2-1 and 2-2 and Figures 2.1, 2.2 and 2.3. The program as described on Table 2-2 only lists the required samples as specified in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual. However, in order to identify the locations of the extra samples, all locations (both required and extra) are listed in Table 2-1 and shown on the figures.

2-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Table 2-1 Environmental Monitoring Program Sampling Types and Locations Location Direction & Distance Number* Location Name From Release Point** Sample Types 1-1 On-site - Old Millstone Rd. 0.6 Mi, NNW TLD, Air Particulate, Iodine, Vegetation 2-1 On-site - Weather Shack 0.3 Mi, S TLD, Air Particulate, Iodine 3-1 On-site - Bird Sanctuary 0.3 Mi, NE TLD, Air Particulate, Iodine, Soil 4-1 On-site - Albacore Drive 1.0 Mi, N TLD, Air Particulate, Iodine, Soil 5-1 MP3 Discharge 0.1 Mi, SSE TLD 6-1 Quarry Discharge 0.3 Mi, SSE TLD 7-1 Environmental Lab Dock 0.3 Mi, SE TLD 8-1 Environmental Lab 0.3 Mi, SE TLD 9-1 Bay Point Beach 0.4 Mi, W TLD 10-1 Pleasure Beach 1.2 Mi, E TLD, Air Particulate, Iodine, Vegetation 11-1 New London Country Club 1.6 Mi, ENE TLD, Air Particulate, Iodine 12-C Fisher's Island, NY 8.0 Mi, ESE TLD 13-C Mystic, CT 11.5 Mi, ENE TLD 14-C Ledyard, CT 12.0 Mi, NE TLD, Soil 15-C Norwich, CT 14.0 Mi, N TLD, Air Particulate, Iodine 16-C Old Lyme, CT 8.8 Mi, W TLD 17-1 Site Boundary 0.5 Mi, NE Vegetation 21-1 Goat Location #1 2.0 Mi, N Milk 22-1 Goat Location #2 2.7 Mi, NE Milk 24-C Goat Location #4 29.0 Mi, NNW Milk 25-1 Within 10 Miles Within 10 Miles Fruits & Vegetables 26-C Beyond 10 Miles Beyond 10 Miles Fruits & Vegetables 27-1 Niantic 1.7 Mi, WNW TLD, Air Particulate, Iodine 28-1 Two Tree Island 0.8 Mi, SSE Mussels 29-1 West Jordan Cove 0.4 Mi, NNE Clams 29-X West Jordan Cove 0.4 Mi, NNE Bottom Sediment, Fucus 30-1 Niantic Shoals 1.5 Mi, NNW Mussels 31-I Niantic Shoals 1.8 Mi, NW Bottom Sediment, Oysters 31 -X Niantic Shoals 1.8 Mi, NW Scallops 32-1 Vicinity of Discharge < 0.1 Mi Bottom Sediment, Oysters, Lobster, Fish, Seawater 32-X Vicinity of Discharge < 0.1 Mi Fucus 33-1 Seaside Point 1.8 Mi, ESE Bottom Sediment 33-X Seaside Point 1.8 Mi, ESE Fucus 34-1 Thames River Yacht Club 4.0 Mi, ENE Bottom Sediment 34-X Thames River Yacht club 4.0 Mi, ENE Oysters 35-1 Niantic Bay 0.3 Mi, WNW Lobster, Fish 35-X Niantic Bay 0.3 Mi, WNW Bottom Sediment, Clams, Fucus 36-X Black Point 3.0 Mi, WSW Fucus 37-C Giant's Neck 3.5 Mi, WSW Bottom Sediment, Oysters, Seawater 37-X Giant's Neck 3.5 Mi, WSW Lobster 38-1 Waterford Shellfish Bed #1 1.0 Mi, NW Clams 39-X Jordan Cove Bar 0.8 Mi, NE Bottom Sediment. Clams

Key: I - Indicator C - Control X - Extra - sample not required by REMODCM

- The release points are the Site Stack for terrestrial locations and the quarry cut for aquatic locations.

2-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Location Direction & Distance Number* Location Name From Release Point** Sample Types 40-X Quarry Fish 41-1 Myrock Avenue 3.2 Mi, ENE TLD 42-1 Billow Road 2.4 Mi, WSW TLD 43-1 Black Point 2.6 Mi, SW TLD 44-1 Onsite - Schoolhouse 0.1 Mi, NNE TLD 45-1 Onsite Access Road 0.5 Mi, NNW TLD 46-1 Old Lyme - Hillcrest Ave. 4.6 Mi, WSW TLD 47-1 East Lyme - W. Main St. 4.5 Mi, W TLD 48-1 East Lyme - Corey Rd. 3.4 Mi, WNW TLD 49-1 East Lyme - Society Rd. 3.6 Mi, NW TLD 50-1 East Lyme - Manwaring Rd. 2.1 Mi, W TLD 51-I East Lyme - Smith Ave. 1.5 Mi, NW TLD 52-1 Waterford - River Rd. 1.1 Mi, NNW TLD 53-1 Waterford - Gardiners Wood 1.4 Mi, NNE TLD Rd.

55-1 Waterford - Magonk Point 1.8 Mi, ESE TLD 56-1 New London - Mott Ave. 3.7 Mi, E TLD 57-1 New London - Ocean Ave. 3.6 Mi, ENE TLD 59-1 Waterford -Miner Ave. 3.4 Mi, NNE TLD 60-1 Waterford - Parkway South 4.0 Mi, N TLD 61-1 Waterford - Boston Post Rd. 4.3 Mi, NNW TLD 62-1 East Lyme - Columbus Ave. 1.9 Mi, WNW TLD 63-1 Waterford - Jordon Cove Rd. 0.8 Mi, NE TLD 64-1 Waterford - Shore Rd. 1.1 Mi, ENE TLD 65-1 Waterford - Bank St. 3.2 Mi, NE TLD 66-X NAP Parking Lot - Fitness 0.4 Mi, NW TLD Center 67-X Golden Spur 4.7 Mi, NNW Bottom Sediment 69-X Pleasure Beach 0.8 Mi, E Bottom Sediment 71-I 1-MW-XFMR-03 Onsite Well Water 72-1 MW-GPI-1 Onsite Well Water 73-X Site Switchyard Fence 0.3 Mi, N TLD 74-X Ball Field Foul Pole 0.6 Mi, N TLD 75-X Waterford - Windward Way & 0.5 Mi, NE TLD Shotgun 76-X ISFSI-1 Up-gradient of ISFSI Well Water 77-X ISFSI-2A Down-gradient of ISFSI Well Water 78-X ISFSI-3 Down-gradient of ISFSI Well Water 79-1 M3-MW-1 Onsite Well Water 80-1 S1 2-MW-2 Onsite Well Water 80-A S12-MW-1 Onsite Well Water 81-1 S2-MW-1 Onsite Well Water 82-1 MW-GPI-2 Onsite Well Water 83-X MW-GPI-3 Onsite Well Water 84-X MW-GPI-4 Onsite Well Water 85-X MW-GPI-5 Onsite Well Water 86-X MW-GPI-6 Onsite Well Water 88-1 DEP Dock Onsite Oysters 90-C Thames River 4 Mi, E Fucus 91 -X MW-GPI-8 Onsite Well Water 92-X MW-GPI-9 Onsite Well Water 93-X Site Boundary Site Boundary Meat 94-X Site Boundary Site Boundary Meat

Key: I - Indicator C - Control X - Extra - sample not required by the REMODCM

- The release points are the Site Stack for terrestrial locations and the quarry cut for aquatic locations.

2-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Table 2-2 Required Samplinq Frecquencv & Tvpe of Analysis Exposure Pathway No. of Sampling & Collection Type of Analysis andlor Sample Locations Frequency

1. Gamma Dose - 40 a Quarterly Gamma Dose - Quarterly Environmental TLD

2. Airborne Particulate 8 Continuous sampler - weekly Gross Beta - Weekly filter change Gamma Spectrum - Quarterly on composite (by location), and on individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results

3. Airborne Iodine 8 Continuous sampler - weekly 1-131 - Weekly canister change

4. Vegetation 5 One sample near middle and Gamma Isotopic on each sample one near end of growing season

5. Milk 2 Semimonthly when animals Gamma Isotopic and 1-131 on each are on pasture; monthly at sample; Sr-89 and Sr-90 on other times. quarterly composite 5a. Pasture Grass 3 Sample as necessary to Gamma Isotopic and 1-131 on each substitute for unavailable milk sample

6. Sea Water 2 Continuous sampler with a Gamma Isotopic and Tritium on monthly collection at indicator each sample.

location. Quarterly at control location - Composite of 6 weekly grab samples.

6a. Well Water 6 Semiannual Gamma Isotopic and Tritium on each sample

7. Bottom Sediment 5 Semiannual Gamma Isotopic on each sample 7a. Soil 3 Annually Gamma Isotopic on each sample

8. Fin Fish - Flounder 2 Quarterly Gamma Isotopic on each sample and one other type of edible fin fish

9. Mussels 2 Quarterly Gamma Isotopic on each sample (edible portion)

10. Oysters 4 Quarterly Gamma Isotopic on each sample (edible portion)

11. Clams 2 Quarterly Gamma Isotopic on each sample (edible portion)

12. Lobster 2 Quarterly Gamma Isotopic on each sample (edible portion) ka) I wo or more i LUS or I LU witn two or more elements per location.

2-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 p0 3 I

/

2-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 2.2 Millstone Sampling Locations (Within 2 miles)

Li m

I N U

62

-WA F661

=k 2-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 2.3 Millstone Sampling Wells 2-7

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 2.2 Samples Collected During Report Period The following table summarizes the number of samples of each type collected and analyzed during 2010:

Number of Number of Technical Technical Specification Specification Number of Sample Type Required Samples Required Samples Extra Samples Analyzed Analyzed Gamma Exposure 160 159 16 (Environmental TLD)

Air Particulates 416 416 0 Air Iodine 416 416 0 Soil 3 3 0 Goat Milk 38 111 0 Pasture Grass 2 Variable 27 0 Well Water 12 12 51 Meat 0 0 2 Fruit and Vegetables 8 8 3 Broad Leaf Vegetation 6 6 15 Sea Water 16 16 0 Bottom Sediment 10 10 10 Aquatic Flora 0 0 24 Fish 3 16 il 3 Mussels 8 23 0 Oysters 16 16 4 Clams 8 8 8 Lobster 8 8 4 Total All Types 1,141 1,129 140 1 Pasture grass sampled as necessary to substitute for unavailable milk. Hay or grain was substituted when grass was not available.

2 Depends upon availability of goat milk samples 3 Due to sample unavailability, not all required fish and shellfish samples could be obtained (see Notes at end of Section 3 for details) 2-8

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

3. RADIOCHEMICAL RESULTS 3.1 Summary Table In accordance with the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM),Section I.F.1, a summary table of the radiochemical results has been prepared and is presented on the following pages.

The mean and range recorded are based only upon detectable measurements. The parentheses indicate the fraction of the measurements that are considered above the detection limit for each individual analysis.

A more detailed analysis of the data is given in Section 4.0 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries. The data summaries include the extra ("X") samples collected throughout the year. These samples are taken to enhance the monitoring program, or are the results of special studies.

3-1

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled To tal Mean Distance Mean Mean Reported (Units) Type Nun nber LLD Range Number Direction Range Range Measurements Direct Gamma 1 75 - 7.9 (155/155) 8 0.3 mi 11.2(4/4) 8.1 (20/20) 0 Radiation Dose (4.2/11.9) SE (10.8/11.9) (5.9/10.1)

TLD (uR/hr)

Air Iodine 1-131 4 16 70 <LLD - - <LLD 0 (le-3 oCi/m 3)

Air GR-B 4116 10 15.9 (357/364) 10 1.2 mi 16.8 (50/52) 15.8 (51/52) 0 Particulate (5.1/34.7) E (5.9/33) (5.6/28.7)

(le-3 DCi/m3 )

GAMMA 3.2 BE-7 - 115(28/28) 10 1.2 mi 133(4/4) 104(4/4) 0 (67/166) E (96/166) (79/120)

MN-54 - <LLD - - - <LLD 0 CO-58 - <LLD - - - <LLD 0 C0-60 - <LLD - - - <LLD 0 ZN-65 - <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - - <LLD 0 RU-103 - <LLD - - - <LLD 0 RU-106 - <LLD - - - <LLD 0 CS-134 50 <LLD - - - <LLD 0 CS-1 37 60 <LLD - - - <LLD 0 BA-140 - <LLD - - - <LLD 0 CE-141 <LLD - - - <LLD 0 CE-144 <LLD - - - <LLD 0 Soil GAMMA 3 (pCi/gdry) BE-7 <LLD <LLD 0 3-2

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled To tal Mean Distance Mean Mean Reported (Units) Type Nun ber LLD Range Number Direction Range Range Measurements Soil (pCi/g dry) K-40 - 13.9(2/2) 3 0.03 mi 14.4(1/1) 11.7(1/1) 0 (13.3/14.4) NE CR-51 - <LLD - - - <LLD 0 MN-54 - <LLD - - - <LLD 0 CO-58 - <LLD - - - <LLD 0 FE-59 - <LLD - - - <LLD 0 CO-60 - <LLD - - - <LLD 0 ZN-65 - <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - - <LLD 0 RU-1 03 - <LLD - - - <LLD 0 RU-1 06 - <LLD - - - <LLD 0 SB-125 - <LLD - - - <LLD 0 CS-134 0.15 <LLD - - - <LLD 0 CS-137 0.18 0.354 (2/2) 14C 12.0 mi 1.33 (1/1) 1.33 (1/1) 0 (0.300/0.407) NE CE-141 - <LLD <LLD 0 CE-144 <LLD - - <LLD 0 ACTH-228 - 1.43 (2/2) 4 1.0 mi 1.68 (1/1) 0.81 (1/1) 0 (1.17/1.68) N Goat Milk SR-89 10 <LLD - NA 0 (pCi/1)

SR-90 2 <LLD NA 0 3-3

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled To'tal

Mean Distance Mean Mean Reported (Units) Type Nunrber LLD Range Number Direction Range Range Measurements Goat Milk GAMMA I1 (pCO) K-40 - 1373 (8/8) 24C 29.0 mi 1613 (3/3) 1613 (3/3) 0 (1010/1680) NNW (1560/1650) (1560/1650) 1-131 1 <LLD <LLD 0 CS-1 34 15 <LLD - - <LLD 0 CS-1 37 18 8.38 (3/8) 21 2.0 mi 8.38 (3/8) 5.70 (2/3) 0 (5.49/12.4) N (5.49/12.4) (5.30/6.10)

BA-140 70 <LLD - <LLD 0 LA-140 25 <LLD <LLD 0 Pasture GAMMA 27 Grass/Hay 1-131 0.06 <LLD <LLD (pCi/g wet)

BE-7 3.18 (7/11) 21 2.0 mi 3.18 (7/11) 1.95 (11/16)

(0.52/7.32) N (0.52/7.32) (0.36/5.00)

K-40 7.57 (11/11) 24C 29.0 mi 7.82 (16/16) 7.82 (16/16)

(2.17/13.9) NNW (2.89/13.2) (2.89/13.2)

CR-51 <LLD <LLD MN-54 <LLD <LLD CO-58 <LLD <LLD FE-59 <LLD <LLD CO-60 <LLD <LLD ZN-65 <LLD <LLD NB-95 <LLD <LLD ZR-95 <LLD <LLD RU-103 <LLD <LLD RU-106 <LLD <LLD 3-4

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Tottal

Mean Distance Mean Mean Reported (Units) Type Numnber LLD Range Number Direction Range Range Measurements Pasture SB-125 - <LLD <LLD 0 GrasslHay (pCi/gwet)

CS-134 0.06 <LLD - - - <LLD 0 CS-137 0.08 0.052 (2/11) 21 2.0 mi 0.052 (2/11) <LLD 0 (0.047/0.057) N (0.047/0.057)

BA-140 - <LLD - - - <LLD 0 LA-140 - <LLD - - - <LLD 0 CE-141 - <LLD - - - <LLD 0 CE-144 - <LLD - - - <LLD 0 ACTH-228 - <LLD 24C 29.0 mi 0.25 (1/16) 0.25 (1/16) 0 NNW Well Water H-3 63 2000 1660 (1/63) 80 ONSITE 1660 (1/5) NA 0 (pCX)

Sr-89 4 -4 <LLD - NA 0 Sr-90 44 <LLD - NA 0 GAMMA 63 1-131 15 <LLD NA BE-7 - <LLD NA K-40 <LLD NA CR-51 - <LLD NA MN-54 15 <LLD NA CO-58 15 <LLD NA FE-59 30 <LLD NA CO-60 15 <LLD NA 3-5

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total

Mean Distance Mean Mean Reported (Units) Type Number LLD Range Number Direction Range Range Measurements Well Water ZN-65 30 <LLD - - - NA 0 (pC/A)

NB-95 15 <LLD - - - NA 0 ZR-95 30 <LLD - - - NA 0 RU-103 - <LLD - - - NA 0 RU-106 <LLD - - - NA 0 SB-125 - <LLD - - - NA 0 CS-134 15 <LLD - - - NA 0 CS-137 18 <LLD - - - NA 0 BA-140 60 <LLD - - - NA 0 LA-140 15 <LLD - - - NA 0 ACTH-228 - <LLD - - - NA 0 GAMMA 11 Fruits &

Vegetables 1-131 0.06 <LLD <LLD 0 (pCi/g wet)

BE-7 <LLD - -<LLD 0 K-40 2.84 (7/7) 25 within 2.84(7/7) 2.12 (4/4) 0 (0.578/5.47) 10 mi (0.578/5.47) (0.621/3.99)

CR-51 <LLD - - - <LLD 0 MN-54 <LLD S- - <LLD 0 CO-58 <LLD S - - <LLD 0 FE-59 <LLD -

S - <LLD 0 CO-60 <LLD -- - <LLD 0 3-6

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled TOtal Mean Distance Mean Mean Reported (Units) Type Nun nber LLD Range Number Direction Range Range Measurements Fruits & ZN-65 - <LLD - - - <LLD 0 Vegetables (pCi/g wet)

ZR-95 - <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - <LLD 0 RU-1 03 - <LLD - - - <LLD 0 RU-106 - <LLD - - - <LLD 0 SB-125 - <LLD - - - <LLD 0 CS-134 0.06 <LLD - - - <LLD 0 CS-137 0.08 <LLD - - - <LLD 0 BA-140 - <LLD - - - <LLD 0 LA-140 - <LLD - - - <LLD 0 CE-141 - <LLD - - - <LLD 0 CE-144 - <LLD - - - <LLD 0 ACTH-228 - <LLD - - - <LLD 0 Meat - Deer GAMMA (pCi/g wet) 1-131 <LLD NA 0 BE-7 <LLD NA 0 K-40 2.92 (2/2) 94 Site 3.38 (1/1) NA 0 (2.46/3.38) Boundary MN-54 <LLD NA 0 CO-58 <LLD NA 0 3-7

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type Number LLD Range Number Direction Range Range Measurements Meat - Deer FE-59 - <LLD - - - NA 0 (pCi/g wet)

CO-60 - <LLD - - - NA 0 ZN-65 - <LLD - - - NA 0 NB-95 - <LLD - - - NA 0 ZR-95 - <LLD - - - NA 0 RU-1 03 - <LLD - - - NA 0 RU-106 - <LLD - - - NA 0 AG-110M - <LLD - - NA 0 CS-134 - <LLD - - - NA 0 CS-1 37 - 0.275 (2/2) 94 Site 0.356 (1/1) NA 0 (0.194/0.356) Boundary BA-140 - <LLD - - - NA 0 LA-140 - <LLD - - - NA 0 CE-141 - <LLD - - - NA 0 CE-144 - <LLD - - - NA 0 RA-226 - <LLD - - - NA 0 ACTH-228 - <LLD - - - NA 0 GAMMA 21 Broad Leaf Vegetation 1-131 0.06 <LLD NA 0 (pCi/g wet)

BE-7 0.998 (18/21) 1 0.6 mi 1.111 (6/7) NA 0 (0.440/2.55) NNW NE (0.460/1.83)

K-40 3.80 (21/21) 10 1.2 mi 4.15 (7/7) NA 0 (2.55/4.97) E (3.88/4.97) 3-8

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total

Mean Distance Mean Mean Reported (Units) Type I Number LLD Range Number Direction Range Range Measurements Broad Leaf CR-51 - <LLD - - - NA 0 Vegetation (pCi/gwet)

MN-54 - <LLD - - - NA 0 CO-58 <LLD - - - NA 0 FE-59 - <LLD - - - NA 0 CO-60 - <LLD - - - NA 0 ZN-65 - <LLD - - - NA 0 NB-95 - <LLD - - - NA 0 ZR-95 - <LLD - - - NA 0 RU-103 - <LLD - - - NA 0 RU-1 06 - <LLD - - - NA 0 SB-125 - <LLD - - - NA 0 CS-1 34 0.06 <LLD - - - NA 0 CS-137 0.08 0.031 (4/21) 17 0.5 mi 0.035 (3/7) NA 0 (0.020/0.053) NE (0.026/0.053)

BA-140 - <LLD - - - NA 0 LA-140 - <LLD - - - NA 0 CE-141 - <LLD - - - NA 0 CE-144 - <LLD - - - NA 0 ACTH-228 - 0.121 (5/21) 1 0.6 mi 0.172 (1/7) NA 0 (0.083/0.172) NNW H-3 16 2000 642(7/12) 32 < 0.1 mi 642(7/12) <LLD 0 (300/1070) (300/1070) 3-9

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled To tal

Mean Distance Mean Mean Reported (Units) Type Nunrber LLD Range Number Direction Range Range Measurements Sea Water GAMMA 16 (pC0/) 1-131 15 <LLD <LLD 0 BE-7 - <LLD - - <LLD 0 K-40 - 288 (12/12) 32 < 0.1 mi 288 (12/12) 285(4/4) 0 (251/327) (251/327) (243/321)

CR-51 - <LLD - - - <LLD 0 MN-54 15 <LLD - - - <LLD 0 CO-58 15 <LLD - - - <LLD 0 FE-59 30 <LLD - - - <LLD 0 CO-60 15 <LLD - - - <LLD 0 ZN-65 30 <LLD - - - <LLD 0 NB-95 15 <LLD - - - <LLD 0 ZR-95 30 <LLD - - - <LLD 0 RU-103 - <LLD - - - <LLD 0 RU-106 <LLD - - - <LLD 0 SB-125 - <LLD - - - <LLD 0 CS-1 34 15 <LLD - - - <LLD 0 CS-1 37 18 <LLD - - - <LLD 0 BA-140 60 <LLD - - - <LLD 0 LA-140 15 <LLD - - - <LLD 0 ACTH-228 - <LLD - - - <LLD 0 3-10

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Tot tal Mean Distance Mean Mean Reported (Units) Type Numiber LLD Range Number Direction Range Range Measurements Bottom GAMMA 2C0 Sediment 1-131 - <LLD <LLD 0 (pCilgdry)

- <LLD - <LLD0 BE-7 K-40 - 16.3 (18/18) 67 4.7 mi 25.2 (2/2) 15.7 (2/2) 0 (12.0/31.6) NNW (18.8/31.6) (14.0/17.3)

CR-51 - <LLD - - - <LLD 0 MN-54 - <LLD - - - <LLD 0 CO-58 - <LLD - - - <LLD 0 FE-59 - <LLD - - - <LLD 0 CO-60 - <LLD - - - <LLD 0 ZN-65 - <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - - <LLD 0 RU-103 - <LLD - - - <LLD 0 RU-106 - <LLD - - - <LLD 0 AG-110M - <LLD - - - <LLD 0 SB-125 - <LLD - - <LLD 0 CS-134 0.15 <LLD - - <LLD 0 CS-137 0.18 <LLD - - - <LLD 0 ACTH-228 - 0.121 (5/21) 29 0.4 mi 172(1/7) <LLD 0 (0.083/0.172) NNE Flora GAMMA 24 (pCi/g wet) 1-131 <LLD 90C 4.0 mi 0.288 (2/4) 0.288 (2/4) 0 E (0.139/0.436) (0.139/0.436) 3-11

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total

Mean Distance Mean Mean Reported (Units) Type I Number LLD Range Number Direction Range Range Measurements Flora BE-7 - 0.083 (5/20) 29X 0.4 mi 0.097 (1/4) 0.078 (1/4) 0 (pCi/g wet) (0.060/0.104) NNE K-40 - 6.36 (20/20) 32X < 0.1 mi 7.29 (4/4) 6.69 (4/4) 0 (4.12/8.51) (5.60/8.51) (5.80/7.63)

CR-51 - <LLD - - - <LLD 0 MN-54 - <LLD - - - <LLD 0 CO-58 - <LLD - - - <LLD 0 FE-59 - <LLD - - - <LLD 0 CO-60 - <LLD - - - <LLD 0 ZN-65 - <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - - <LLD 0 RU-103 - <LLD - - - <LLD 0 RU-106 - <LLD - - - <LLD 0 AG-110M - <LLD - - - <LLD 0 SB- 25 - <LLD - - - <LLD 0 CS-134 <LLD - - - <LLD 0 CS-1 37 <LLD - - - <LLD 0 ACTH-228 - 0.044 (2/20) 36 3.0 mi 0.048 (1/4) 0.032 (1/4) 0 (0.040/0.048) WSW Fish - GAMMA 5 Flounder 1-131 0.04 <LLD - NA 0 (pCi/g wet)

BE-7 - <LLD NA 0 3-12

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled I Total

Mean Distance Mean Mean Reported (Units) Type I Number LLD Range Number Direction Range Range Measurements Fish - K-40 3.9 (5/5) 35 0.3 mi 3.9 (3/3) NA 0 Flounder (3.7/4.2) WNW (3.7/4.2)

(pCi/g wet)

CR-51 <LLD - - - NA 0 MN-54 0.13 <LLD - - - NA 0 CO-58 0.13 <LLD - - - NA 0 FE-59 0.26 <LLD - - - NA 0 CO-60 0.13 <LLD - - - NA 0 ZN-65 0.26 <LLD - - - NA 0 NB-95 - <LLD - - - NA 0 ZR-95 - <LLD - - - NA 0 RU-103 - <LLD - - - NA 0 RU-106 - <LLD - - - NA 0 AG-110M - <LLD - - - NA 0 SB-125 - <LLD - - - NA 0 CS-134 0.13 <LLD - - - NA 0 CS-137 0.15 <LLD - - - NA 0 ACTH-228 - <LLD - - - NA 0 GAMMA 9 Fish - Other (pCi/g wet) 1-131 0.04 <LLD NA 0 BE-7 - <LLD NA 0 K-40 4.6 (9/9) 32 < 0.1 mi 6.5(3/3) NA 0 (2.9/11.5) (3.5/11.5) 3-13

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator lndic~torlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled To tal Mean Distance Mean Mean Reported (Units) Type Nun nber LLD Range Number Direction Range Range Measurements Fish - Other CR-51 - <LLD - - - NA 0 (pCi/g wet)

MN-54 0.13 <LLD - - - NA 0 CO-58 0.13 <LLD - - - NA 0 FE-59 0.26 <LLD - - - NA 0 CO-60 0.13 <LLD - - - NA 0 ZN-65 0.26 <LLD - - - NA 0 NB-95 - <LLD - - - NA 0 ZR-95 - <LLD - - - NA 0 RU-1 03 - <LLD - - - NA 0 RU-1 06 - <LLD - - - NA 0 AG-110M - <LLD - - - NA 0 SB-125 - <LLD - - - NA 0 CS-134 0.13 <LLD - - - NA 0 CS-137 0.15 <LLD - - - NA 0 ACTH-228 - <LLD - - - NA 0 Mussels GAMMA (pCi/g wet) 1-131 0.1 <LLD NA 0 BE-7 - <LLD NA 0 K-40 2.4 (2/2) 30 1.5 mi 2.4 (2/2) NA 0 (2.2/2.6) NNW (2.2/2.6)

CR-51 <LLD NA 0 3-14

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled I Total Mean Distance Mean Mean Reported (Units) Type I Number LLD Range Number Direction Range Range Measurements Mussels MN-54 0.13 <LLD - - - NA 0 (pCi/g wet)

CO-58 0.13 <LLD - - - NA 0 FE-59 0.26 <LLD - - - NA 0 CO-60 0.13 <LLD - - - NA 0 ZN-65 0.26 <LLD - - - NA 0 NB-95 - <LLD - - - NA 0 ZR-95 - <LLD - - - NA 0 RU-103 - <LLD - - - NA 0 RU-106 - <LLD - - - NA 0 AG-110M - <LLD - - - NA 0 SB-125 - <LLD - - - NA 0 CS-134 0.13 <LLD - - - NA 0 CS-137 0.15 <LLD - - - NA 0 ACTH-228 - <LLD - - - NA 0 Oysters GAMMA 20 (pCl/g wet) 1-131 <LLD <LLD 0 BE-7 <LLD <LLD 0 K-40 2.2 (16/16) 34 4.0 mi 3.1 (4/4) 1.9(4/4) 0 (1.0/6.5) ENE (1.8/6.5) (1.4/2.5)

CR-51 <LLD <LLD 0 MN-54 0.13 <LLD <LLD 0 3-15

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator Indicator/Control Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Tot tal

Mean Distance Mean Mean Reported (Units) Type Numiber LLD Range Number Direction Range Range Measurements Oysters CO-58 0.13 <LLD - - - <LLD 0 (pCi/g wet)

FE-59 0.26 <LLD - - - <LLD 0 CO-60 0.13 <LLD - - - <LLD 0 ZN-65 0.26 <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - - <LLD 0 RU-1 03 - <LLD - - - <LLD 0 RU-106 - <LLD - - - <LLD 0 AG-110M 0.10 (3/16) 32 < 0.1 mi 0.10 (3/4) <LLD 0 (0.063/0.200) (0.063/0.200)

SB-i25 - <LLD - - - <LLD 0 CS-1 34 0.13 <LLD - - - <LLD 0 CS-137 0.15 <LLD - - - <LLD 0 ACTH-228 - <LLD - - - <LLD 0 Clams GAMMA 16 (pCi/gwet) 1-131 <LLD NA 0 BE-7 <LLD NA 0 K-40 2.0 (16/16) 29 0.4 mi 2.4 (4/4) NA 0 (1.5/2.7) NNE (2.1/2.7)

CR-51 <LLD NA 0 MN-54 0.13 <LLD NA 0 CO-58 0.13 <LLD NA 0 3-16

Millstone Station Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total

Mean Distance Mean Mean Reported (Units) Type I Number LLD Range Number Direction Range Range Measurements Clams FE-59 0.26 <LLD - NA 0 (pCi/g wet)

CO-60 0.13 <LLD - NA 0 ZN-65 0.26 <LLD - NA 0 NB-95 - <LLD - NA 0 ZR-95 - <LLD - NA 0 RU-1 03 - <LLD - NA 0 RU-1 06 - <LLD - NA 0 AG-110M - <LLD - NA 0 SB-125 - <LLD - NA 0 CS-134 0.13 <LLD - NA 0 CS-137 0.15 <LLD - NA 0 ACTH-228 - <LLD - NA 0 Lobster GAMMA 12 (pCi/g wet) 1-131 I <LLD <LLD 0 BE-7 <LLD <LLD 0 K-40 2.3 (7/8) 37C 3.5 mi 3.4 (4/4) 3.4 (4/4) 0 (1.5/2.9) WSW (1.7/8.0) (1.7/8.0)

CR-51 - <LLD <LLD 0 MN-54 0.13 <LLD <LLD 0 CO-58 0.13 <LLD <LLD 0 FE-59 0.26 <LLD <LLD 0 3-17

Millstone Station .: Annual Radiological Environmental Operating Report 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Dockets 50-245, 50-336 & 50-423 Medium or Indicator IndicatorlControl Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled To tal

Mean Distance Mean Mean Reported (Units) Type Nun nber LLD Range Number Direction Range Range Measurements Lobster CO-60 0.13 <LLD - - - <LLD 0 (pCi/g wet)

ZN-65 0.26 <LLD - - - <LLD 0 NB-95 - <LLD - - - <LLD 0 ZR-95 - <LLD - - - <LLD 0 RU-1 03 - <LLD - - - <LLD 0 RU-106 - <LLD - - - <LLD 0 AG-110M - <LLD - - - <LLD 0 SB-125 - <LLD - - - <LLD 0 CS-134 0.13 <LLD - - - <LLD 0 CS-137 0.15 <LLD - - - <LLD 0 ACTH-228 - <LLD - - - <LLD 0 3-18

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 NOTES FOR

SUMMARY

TABLE For gamma measurements the Minimum Detectable Level (MDL) - the Lower Limit of Detection (LLD) / 2.33. For all others, MDL = 2 x (the standard deviation of the background). These MDLs are based on the absence of large amounts of interfering activity (excluding naturally occurring radionuclides). Deviations by factors of 3 to 4 can occur.

The LLD at a confidence level of 95% is the smallest concentration of radioactive material in a sample that will be detected with a 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD = 4.66 Sb E

V

2.22

Y

exp (-2At) where, LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per transformation)

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

A is the radioactive decay constant for the particular radionuclide X*t is the elapsed time between sample collection (or end of the sample collection period) and time of counting The LLD is defined as "a priori" (before the fact) limit representing the capability of a measurement system and not an "a posteriori" (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in this report (see Notes for Section 3 or Section 4). As shown in the equation above, for composite samples taken over a period of time, the LLD is decayed to the end of the sample period.

The listed 1-131 LLD for all the vegetation samples is for leafy vegetables.

The 1-131, Ba-1 40 and La-1 40 LLDs for the water samples are from end of sample period.

3-19

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 3.2 Data Tables The data reported in this section are strictly counting statistics. The reported error is two times the standard deviation (2cy) of the net activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed.

Results are considered positive when the measured value exceeds 1.5 times the listed 2Gy error (i.e., the measured value exceeds 3aT). Any errors listed as zero are the artifact that there were no background counts in the area of the peak for these nuclides.

Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data. For the purposes of this report, in order to indicate any background biases, all the valid data are presented. This practice was recommended by Health and Safety Laboratory (HASL) ("Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham), NUREG 0475 and NUREG/CR-4007 (Sept.

1984). In instances where zeros are listed after significant digits, this is an artifact of the computer data-handling program.

Data are given according to sample type as indicated below.

1. Gamma Exposure Rate

2. Air Particulates, Gross Beta Radioactivity

3. Air Particulates, Weekly 1-131

4. Air Particulates, Quantitative Gamma Spectra

5. Air Particulates, Quarterly Strontium*

6. Soil

7. Milk - Dairy Farms*

8. Milk - Goat Farms

9. Pasture Grass

10. Well Water

11. Meat

12. Fruits & Vegetables

13. Broad Leaf Vegetation

14. Seawater

15. Bottom Sediment

16. Aquatic Flora

17. Fin Fish

18. Mussels

19. Oysters

20. Clams

21. Scallops*

22. Lobster (and Crabs)

This type of sampling or analysis was not performed; therefore there is no table for these.

3-20

Millstone Station Radiological Environmental Operating Report 2010 Millton StaionAnnual TABLE 1 QUARTERLY GAMMA EXPOSURE RATE (uRlhr)*

LOCATIONS PERIOD 1- 2 3 4 5 6 7 8 9 10 1Q 7.6 0.3 10.1 0.3 7.5 0.2 7.9 0.2 9.6 0.3 8.1 0.3 5.0 0.2 10.8 0.3 8.6 0.3 10.0 0.6 6.7 0.2 20 8.2 0.3 10.5 0.4 7.6 0.4 7.6 0.4 9.2 0.4 8.3 0.5 4.9 0.4 11.0 0.4 9.1 0.3. 10.7 0.4 6.7 0.3 30 8.2 0.3 9.9 0.2 7.6 0.2 7.9 0.3 9.9 0.3 7.8 0.3 4.2 0.1 11.1 0.3 9.3 0.3 11.0 0.5 7.0 0.2 40 8.5 0.3 10.2 0.4 7.7 0.3 7.9 0.5 9.6 0.4 8.3 0.3 4.9 0.2 11.9 0.4 9.7 0.6 11.5 0.4 7.7 0.3 PERIOD 120 I3C 1 14C 15C 16C 27 41 42 43 44 45

(+1- (;7-)

IQ 7.2 0.2 10.0 0.4 9.0 0.3 7.8 0.4 6.2 0.3 8.4 0.5 6.4 0.2 A 6.6 0.2 7.9 0.2 7.0 0.3 20 7.1 0.4 10.1 0.4 9.3 0.4 8.0 0.4 6.3 0.3 8.5 0.3 6.8 0.3 7.8 0.3 6.8 0.4 8.1 0.3 7.3 0.3 30 6.9 0.2 9.5 0.3 9.0 0.2 7.6 0.3 5.9 0.2 7.8 0.4 6.5 0.2 6.8 0.3 6.7 0.2 8.1 0.2 6.8 0.3 40 7.6 0.3 9.7 0.4 9.7 0.4 8.4 0.3 6.6 0.4 8.6 0.3 7.0 0.3 7.1 0.2 7.0 0.2 8.3 0.3 7.7 0.3 PERIOD 46 47 48 49 50 51 52 53 55 56 57 6.2 0. 7.2 0. 7.3 0.

10 9.1 0.3 7.5 0.2 9.0 0.3 6.7 0.2 7.5 0.2 7.0 0.3 6.4 0.3 7.1 0.2 6.2 0.3 7.2 0.4 7.3 0.3 20 9.4 0.4 7.9 0.3 9.5 0.4 7.1 0.4 8.0 0.3 7.6 0.4 7.2 0.3 6.8 0.3 7.6 0.4 7.6 0.3 30 8.2 0.2 7.5 0.4 9.3 0.2 6.8 0.3 7.6 0.3 6.0 0.2 7.3 0.2 6.8 0.2 7.1 0.2 7.0 0.2 7.2 0.3 4Q 9.3 0.4 8.1 0.3 9.9 0.4 6.9 0.2 8.3 0.5 6.7 0.3 7.5 0.4 7.4 0.3 7.5 0.3 PERIOD 59 60 61 62 63 64 65 66X 73X 74X 75X

(+1-) (+1-)

7.1 0.

10 7.3 0.3 6.5 0.2 7.1 0.3 7.9 0.3 8.5 0.4 7.3 0.4 8.3 0.3 7.2 0.2 9.4 0.4 7.6 0.4 7.1 0.3 20 8.0 0.3 7.0 0.3 7.7 0.3 8.4 0.4 8.9 0.3 7.8 0.3 8.0 0.4 7.1 0.4 9.1 0.4 7.7 0.3 7.1 0.3 30 7.6 0.3 6.7 0.3 7.0 0.2 7.9 0.2 8.2 0.3 7.2 0.2 8.0 0.4 7.0 0.2 8.8 0.2 7.5 0.2 4Q 8.1 0.3 6.9 0.4 7.7 0.5 8.2 0.4 9.0 0.4 7.7 0.4 7.9 0.3 7.3 0.2 9.3 0.5 7.9 0.4 7.1 0.4

READINGS ARE THE AVERAGE OF MULTI CAS04TM PHOSPHOR ELEMENTS WITHIN ONE PANASONIC TLD BADGE ERRORS ARE 1-SIGMA AND INCLUDE COUNTING, TRANSIT, READER AND FADE UNCERTAINTIES 3-21

Millstone Station Radiological Environmental Qeprating Report 2010 Millton StaionAnnual TABLE 2 AIR PARTICULATES GROSS BETA RADIOACTIVITY (pCi/ms)

LOCATIONS PERIOD ENDING --- - -1;7- - - - - --

2 --- - - - - - - - - - - - -- - - - - -- - - - - -- 15C - - -- 27- - - -

01/05/10 0.016 0.004 0.015 0.004 0.013 0.004 0.012 0.004 0.012 0.004 0.015 0.004 0.017 0.004 0.0.16 0.004 01/12/10 0.013 0.004 0.013 0.004 0.013 0.004 0.016 0.004 0.013 0.004 0.013 0.004 0.012 0.004 0.011 0.003 01/19/10 0.027 0.005 0.020 0.004 0.026 0.005 0.029 0.005 0.027 0.004 0.029 0.005 0.024 0.004 0.026 0.004 01/26/10 0.015 0.004 0.017 0.004 0.020 0.004 0.019 0.004 0.021 0.004 0.023 0.004 0.018 0.004 0.018 0.004 02/02/10 0.023 0.004 0.025 0.004 0.023 0.004 0.026 0.004 0.028 0.004 0.023 0.004 0.027 0.004 0.026 0.004 02/09/10 0.017 0.004 0.019 0.004 0.017 0.004 0.017 0.004 0.020 0.004 0.021 0.004 0.020 0.004 0.018 0.004 02/16/10 0.012 0.004 0.017 0.004 0.015 0.004 0.014 0.004 0.016 0.004 0.014 0.004 0.014 0.004 0.012 0.004 02/23/10 0.008 0.004 0.010 0.004 0.008 0.004 0.010 0.004 0.007 0.004 0.009 0.004 0.007 0.004 0.008 0.004 03/02/10 0.006 0.003 0.005 0.004 0.006 0.004 0.007 0.004 0.005 0.004 0.005 0.004 0.005 0.003 0.007 0.004 03/09/10 0.022 0.003 0.022 0.004 0.026 0.005 0.023 0.004 0.025 0.004 0.023 0.004 0.027 0.004 0.025 0.004 03/16/10 0.017 0.003 0.015 0.003 0.015 0.003 0.020 0.004 0.016 0.004 0.016 0.004 0.016 0.003 0.018 0.004 03/23/10 0.028 0.004 0.030 0.005 0.033 0.005 0.030 0.005 0.031 0.005 0.030 0.005 0.029 0.005 0.028 0.005 03/30/10 0.016 0.003 0.023 0.004 0.017 0.004 0.021 0.004 0.021 0.004 0.022 0.004 0.018 0.004 0.023 0.004 04/06/10 0.009 0.003 0.008 0.003 0.007 0.003 0.012 0.004 0.008 0.004 0.012 0.004 0.009 0.003 0.010 0.004 04/13/10 0.021 0.004 0.022 0.004 0.021 0.004 0.021 0.004 0.021 0.004 0.023 0.005 0.022 0.004 0.023 0.005 04/20/10 0.016 0.004 0.017 0.004 0.014 0.004 0.015 0.004 0.017 0.004 0.016 0.004 0.015 0.004 0.015 0.004 04/27/10 0.020 0.004 0.020 0.004 0.017 0.004 0.022 0.004 0.018 0.004 0.022 0.004 0.024 0.005 0.020 0.004 05/04/10 0.020 0.004 0.020 0.004 0.020 0.004 0.025 0.005 0.018 0.005 0.019 0.005 0.021 0.005 0.020 0.005 05/11/10 0.017 0.004 0.016 0.004 0.018 0.004 0.013 0.004 0.014 0.004 0.019 0.004 0.014 0.004 0.017 0.004 05/18/10 0.019 0.004 0.021 0.004 0.019 0.004 0.020 0.004 0.018 0.004 0.021 0.004 0.018 0.004 0.019 0.004 05/25/10 0.014 0.004 0.014 0.004 0.013 0.003 0.011 0.004 0.013 0.004 0.014 0.004 0.015 0.004 0.015 0.004 06/01/10 0.016 0.003 0.015 0.003 0.017 0.003 0.019 0.003 0.018 0.003 0.015 0.003 0.017 0.004 B 0.015 0.003 06/08/10 0.013 0.004 0.014 0.004 0.016 0.004 0.014 0.004 0.017 0.004 0.020 0.004 0.017 0.004 0.015 0.004 06/15/10 0.008 0.003 0.009 0.003 0.010 0.003 0.010 0.004 0.011 0.004 0.012 0.004 0.011 0.003 0.011 0.003 06/22/10 0.017 0.004 0.017 0.004 0.019 0.004 0.020 0.004 0.017 0.004 0.020 0.004 0.016 0.004 0.020 0.004 06/29/10 0.026 0.005 0.016 0.004 0.020 0.004 0.021 0.004 0.022 0.004 0.018 0.004 0.020 0.004 0.016 0.004 SAMPLE DATES MAY VARY BY A FEW DAYS 3-22

Millstone Station Annual Radiological Environmental Oeprating Report 2010 TABLE 2 AIR PARTICULATES GROSS BETA RADIOACTIVITY (pCi/m4 )

LOCATIONS PERIOD ENDING -------- 1 ....... ....... 2. -------- 3 4 10 .. 15C 27

+/- +/- +/- +/- +/- +/- +/- +/-

07/06110 0.010 0.004 0.014 0.004 0.013 0.004 0.014 0.004 0,015 0.004 0.016 0.004 0.016 0.004 0.013 0.004 07/13/10 0.022 0.004 0.019 0.003 0.021 0.003 0.020 0.003 0.022 0.004 0.022 0.003 0.021 0.003 0.021 0.003 07/20/10 0.015 0.004 0.012 0.004 0.015 0.004 0.012 0.003 0.015 0.004 0.016 0.004 0.015 0.004 0.016 0.004 07/27/10 0.012 0.004 0.014 0.004 0.015 0.004 0.012 0.004 0.018 0.004 0.015 0.004 0.014 0.004 0.016 0.004 08/03/10 0.008 0.004 0.009 0.004 0.010 0.004 0.011 0.004 0.014 0.004 0.013 0.004 0.012 0.004 0.014 0.004 08/10/10 0.017 0.005 0.014 0.004 0.016 0.004 0.016 0.004 0.020 0.005 0.018 0.004 0.016 0.004 0.015 0.004 08/17/10 0.015 0.004 0.014 0.004 0.013 0.004 0.016 0.004 0.018 0.004 0.016 0.004 0.016 0.004 0.012 0.004 08/24/10 0.010 0.004 0.014 0.004 0.016 0.004 0.014 0.004 0.017 0.005 0.017 0.004 0.016 0.004 0.016 0.004 08/31/10 0.015 0.004 0.018 0.004 0.018 0.004 0.018 0.004 0.019 0.004 0.019 0.004 0.016 0.004 0.015 0.004 09/07/10 0.032 0.005 0.031 0.005 0.026 0.005 0.030 0.005 0.033 0.005 0.033 0.005 0.025 0.004 0.035 0.005 09/14/10 0.008 0.003 0.010 0.004 0.011 0.004 0.008 0.003 0.013 0.004 0.011 0.004 0.012 0.004 0.012 0.004 09/21/10 0.012 0.004 0.015 0.004 0.015 0.004 0.012 0.004 0.015 0.004 0.018 0.004 0.015 0.004 0.016 0.004 09/28/10 0.016 0.004 0.019 0.004 0.019 0.004 0.020 0.004 0.021 0.005 0.020 0.004 0.020 0.004 0.017 0.004 10/05/10 0.007 0.003 0.008 0.004 0.009 0.004 0.008 0.003 0.007 0.004 0.008 0.004 0.010 0.003 0.007 0.004 10/12/10 0.018 0.004 0.013 0.004 0.013 0.004 0.014 0.004 0.012 0.004 0.015 0.004 0.013 0.006 C 0.013 0.004 10/19/10 0.006 0.003 0.011 0.004 0.010 0.004 0.012 0.004 0.001 0.004 0.008 0.004 0.010 0.004 0.013 0.004 10/26/10 0.014 0.004 0.015 0.004 0.012 0.004 0.010 0.003 0.018 0.004 0.009 0.004 0.008 0.003 0.012 0.004 11/02/10 0.010 0.004 0.009 0.004 0.010 0.004 0.011 0.003 0.009 0.004 0.011 0.004 0.008 0.003 0.009 0.004 11/09/10 0.004 0.003 0.003 0.003 0.005 0.003 0.006 0.003 0.006 0.003 0.006 0.004 0.006 0.003 0.007 0.003 11/16/10 0.013 0.003 0.016 0.003 0.014 0.003 0.015 0.003 0.017 0.003 0.016 0.003 0.014 0.003 0.012 0.003 11/23/10 0.013 0.004 0.018 0.004 0.016 0.004 0.011 0.003 0.016 0.004 0.014 0.004 0.018 0.004 0.014 0.004 11/30/10 0.021 0.004 0.018 0.004 0.019 0.004 0.019 0.004 0.019 0.004 0.018 0.004 0.018 0.004 D 0.022 0.004 12/07/10 0.010 0.003 0.013 0.003 0.010 0.003 0.011 0.003 0.010 0.003 0.010 0.003 0.010 0.003 0.010 0.003 12/14/10 0.010 0.003 0.011 0.003 0.010 0.003 0.009 0.002 0.010 0.003 0.009 0.004 0.012 0.004 0.009 0.004 12/21/10 0.015 0.004 0.017 0.004 0.015 0.004 0.014 0.003 0.018 0.004 0.015 0.003 0.016 0.004 0.017 0.004 12/28/10 0.007 0.003 0.008 0.003 0.007 0.004 0.005 0.003 0.007 0.003 0.007 0.003 0.006 0.003 0.007 0.003 SAMPLE DATES MAY VARY BY A FEW DAYS 3-23

Millstone Station Radiological Environmental Operating Report 2010 Millton StaionAnnual TABLE 3 AIRBORNE IODINE IODINE-I131 (pCi/ms)

LOCATIONS PERIOD ENDING 1 2 3 4 10 11 15C 27

-0.01-004 009).1 .1 0.015 0.050.18 0.0 0.015 -0.017 0.160-00 0.015 000) 0.015 01/05/10

-0.001 0.024 -0.009 0.019 -0.012 0.015 0.005 0.018 -0.000 0.015 -0.017 0.016 0.009 0.015 -0.008 0.015 01/12/10

-0.006 0.015 -0.014 0.017 -0.003 0.018 0.003 0.017 -0.005 0.015 0.002 0.016 -0.003 0.019 -0.0107 0.014 01/19/10

-0.001 0.018 -0.008 0.015 -0.003 0.016 -0.002 0.017 -0.011 0.014 -0.003 0.014 -0.003 0.018 -0.0105 0.015 01/26/10

-0.003 0.013 -0.004 0.014 -0.012 0.015 -0.006 0.010 -0.001 0.010 -0.0016 0.012 0.004 0.0212 -0.005 0.013 02/02/10 02/09/10 0.000 0.010 0.004 0.014 -0.004 0.013 0.007 0.013 -0.010 0.015 0.000 0.020 0.003 0.016 0.012 0.016 02/16/10 -0.001 0.011 -0.006 0.012 0.000 0.018 0.014 0.013 -0.005 0.008 -0.011 0.010 0.006 0.013 -0.007 0.014 02/23/10 0.005 0.018 0.013 0.015 -0.002 0.014 -0.005 0.017 0.007 0.016 -0.02 1 0.023 -0.003 0.017 -0.004 0.014 03/02/10 0.003 0.012 -0.007 0.016 0.002 0.019 0.006 0.019 -0.001 0.015 0.006 0.019 -0.008 0.012 0.002 0.016 03/09/10 -0.003 0.014 -0.007 0.015 0.002 0.016 0.001 0.016 0.017 0.018 0.003 0.015 0.006 0.015 -0.011 0.013 03/16/10 0.010 0.011 -0.006 0.016 0.000 0.014 0.009 0.013 0.004 0.014 -0.007 0.014 0.004 0.013 -0.003 0.013 03/23/10 0.007 0.010 0.003 0.011 0.005 0.013 0.012 0.013 -0.001 0.013 0.001 0.014 -0.002 0.014 -0.005 0.008 03/30/10 0.001 0.012 0.001 0.012 -0.009 0.017 -0.006 0.015 -0.003 0.013 -0.006 0.017 -0.009 0.015 -0.006 0.015 04/06/10 0.013 0.017 0.007 0.014 -0.008 0.017 -0.009 0.019 0.002 0.009 0.005 0.016 -0.002 0.014 0.016 0.014 04/13/10 -0.001 0.014 0.011 0.012 0.020 0.021 0.009 0.017 -0.004 0.014 -0.012 0.014 0.002 0.022 0.005 0.016 04/20/10 -0.001 0.015 -0.007 0.018 0.004 0.014 -0.012 0.014 -0.023 0.016 0.006 0.015 0.003 0.014 0.015 0.021 04/27/10 -0.002 0.018 0.007 0.015 -0.002 0.017 -0.019 0.023 0.007 0.017 0.010 0.013 0.003 0.022 0.003 0.018 05/04/10 -0.010 0.020 0.000 0.022 -0.016 0.021 -0.007 0.02 1 0.022 0.025 -0.007 0.020 0.000 0.029 -0.014 0.025 05/11/10 -0.004 0.018 -0.005 0.012 0.008 0.018 0.007 0.021 0.022 0.017 0.007 0.022 0.006 0.026 -0.002 0.022 05/18/10 -0.008 0.013 0.001 0.015 -0.005 0.010 -0.004 0.016 -0.013 0.015 -0.002 0.010 0.010 0.017 0.000 0.014 05/25/10 0.009 0.015 -0.007 0.013 -0.010 0.018 -0.011 0.021 0.000 0.016 -0.009 0.017 0.003 0.026 0.000 0.014 06/01/10 -0.009 0.029 0.001 0.024 0.006 0.029 0.002 0.029 0.013 0.024 0.000 0.035 0.042 0.030 B 0.000 0.024 06/08/10 -0.011 0.026 0.018 0.021 0.015 0.017 0.037 0.031 -0.007 0.028 -0.020 0.028 0.010 0.022 0.043 0.030 06/15/10 0.005 0.017 -0.018 0.022 0.002 0.016 0.006 0.021 -0.012 0.023 0.004 0.020 0.019 0.016 -0.005 0.022 06/22/10 0.008 0.020 -0.014 0.021 -0.014 0.021 0.012 0.020 0.003 0.022 0.008 0.029 0.013 0.024 0.012 0.02 1 06/29/10 0.011 0.017 -0.008 0.023 0.000 0.018 -0.006 0.023 -0.018 0.022 -0.014 0.032 -0.030 0.033 0.005 0.035 SAMPLE DATES MAY VARY BY A FEW DAYS 3-24

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 3 AIRBORNE IODINE IODINE-131 (pCi/ms)

LOCATIONS PERIOD ENDING 1 2 3 4 10 11 15C 27

(+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+1-)

07/06/10 0.000 0.019 0.000 0.019 0.000 0.018 0.000 0.018 -0.012 0.017 -0.012 0.017 -0.011 0.016 -0.012 0.017 07/13/10 0.015 0.019 0.015 0.019 0.014 0.018 0.014 0.017 0.014 0.028 0.014 0.028 0.013 0.026 0.014 0.028 07/20/10 0.008 0.016 0.008 0.016 0.008 0.015 0.005 0.011 0.017 0.022 0.017 0.021 0.015 0.020 0.017 0.022 07/27/10 -0.006 0.015 -0.006 0.015 -0.006 0.014 -0.005 0.014 0.012 0.019 0.012 0.018 0.011 0.017 0.012 0.018 08/03/10 -0.001 0.036 -0.001 0.035 -0.001 0.034 -0.001 0.032 0.003 0.034 0.002 0.033 0.002 0.030 0.002 0.032 08/10/10 0.003 0.008 0.003 0.008 0.003 0.007 0.003 0.007 -0.001 0.008 -0.001 0.008 -0.001 0.007 -0.001 0.008 08/17/10 0.011 0.014 0.011 0.014 0.010 0.014 0.010 0.013 0.015 0.021 0.014 0.020 0.013 0.018 0.014 0.020 08/24/10 0.007 0.007 0.006 0.007 0.006 0.007 0.006 0.006 -0.006 0.010 -0.006 0.009 -0.005 0.008 -0.006 0.009 08/31/10 0.008 0.013 0.009 0.014 0.009 0.014 0.008 0.012 -0.003 0.019 -0.003 0.018 -0.002 0.016 -0.002 0.018 09/07/10 -0.005 0.007 -0.006 0.008 -0.005 0.008 -0.005 0.007 -0.002 0.011 -0.002 0.011 -0.002 0.010 -0.002 0.010 09/14/10 -0.004 0.015 -0.004 0.015 -0.004 0.016 -0.004 0.015 -0.005 0.027 -0.005 0.025 -0.004 0.023 -0.005 0.024 09/21/10 0.004 0.016 0.004 0.016 0.004 0.017 0.004 0.016 0.005 0.010 0.005 0.010 0.004 0.009 0.004 0.010 09/28/10 -0.010 0.021 -0.003 0.006 -0.003 0.006 -0.003 0.005 0.010 0.008 0.010 0.008 0.009 0.007 0.009 0.008 10/05/10 0.000 0.007 0.000 0.007 0.000 0.008 0.000 0.007 0.016 0.033 0.015 0.031 0.014 0.028 C 0.015 0.030 10/12/10 0.008 0.038 0.008 0.037 0.012 0.037 0.008 0.037 0.012 0.028 0.012 0.027 0.018 0.040 0.012 0.026 10/19/10 -0.010 0.031 -0.010 0.031 -0.011 0.032 -0.010 0.029 -0.022 0.038 -0.020 0.036 -0.018 0.032 -0.019 0.034 10/26/10 -0.011 0.027 -0.010 0.026 -0.011 0.028 -0.010 0.025 -0.027 0.032 -0.029 0.036 -0.026 0.032 -0.028 0.034 11/02/10 -0.027 0.037 -0.027 0.037 -0.028 0.039 -0.025 0.034 -0.032 0.037 -0.034 0.040 -0.031 0.035 -0.033 0.037 11/09/10 -0.026 0.037 -0.026 0.037 -0.027 0.039 -0.024 0.034 -0.017 0.033 -0.019 0.037 -0.016 0.032 -0.018 0.034 11/16/10 -0.031 0.037 -0.030 0.036 -0.033 0.039 -0.028 0.033 -0.007 0.033 -0.007 0.036 -0.007 0.032 -0.007 0.035 11/23/10 0.010 0.027 0.010 0.027 0.011 0.029 0.009 0.025 0.014 0.033 0.015 0.035 0.013 0.031 0.014 0.033 11/30/10 -0.031 0.032 -0.031 0.032 -0.033 0.034 -0.028 0.029 -0.004 0.037 -0.004 0.040 -0.004 0.036 D -0.004 0.037 12/07/10 0.012 0.024 0.011 0.024 0.012 0.026 0.011 0.022 -0.005 0.033 -0.005 0.038 -0.004 0.032 -0.005 0.033 12/14/10 0.003 0.015 0.003 0.014 0.003 0.016 0.003 0.013 0.003 0.021 0.003 0.023 0.003 0.020 0.003 0.021 12/21/10 -0.010 0.025 -0.010 0.024 -0.011 0.027 -0.009 0.023 -0.029 0.039 -0.029 0.040 -0.030 0.041 -0.032 0.044 12/28/10 -0.003 0.013 -0.003 0.013 -0.004 0.014 -0.003 0.012 0.007 0.015 0.008 0.015 0.008 0.016 0.009 0.017 SAMPLE DATES MAY VARY BY A FEW DAYS 3-25

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 4A AIR PARTICULATES GAMMA SPECTRA - QTR 1 (pCi/m3)

ANALYSES LOCATION Be-7 Mn-54 Co-58 Co-60 Zn-65 Nb-95 Zr-95

(+--) (+--) (+--) (+--) (+--) (+T-) -- (-)

1 0.084 0.037 -0.0002 0.0005 0.0014 0.0016 -0.0008 0.0011 -0.0009 0.0017 -0.0006 0.0026 -0.0013 0.0030 2 0.113 0.041 0.0002 0.0016 0.0006 0.0016 -0.0011 0.0013 0.0000 0.0033 0.0010 0.0029 0.0010 0.0029 3 0.067 0.037 0.0000 0.0010 -0.0003 0.0007 0.0008 0.0010 -0.0019 0.0025 -0.0015 0.0024 -0.0012 0.0030 4 0.123 0.043 -0.0002 0.0012 0.0007 0.0025 0.0000 0.0017 0.0000 0.0000 -0.0014 0.0031 -0.0030 0.0039 10 0.096 0.040 -0.0003 0.0005 0.0001 0.0013 0.0000 0.0011 0.0017 0.0024 0.0001 0.0023 -0.0023 0.0027 11 0.090 0.040 -0.0002 0.0007 -0.0003 0.0018 0.0000 0.0008 0.0001 0.0021 0.0003 0.0032 -0.0012 0.0030 15C 0.120 0.040 -0.0010 0.0010 0.0014 0.0016 -0.0004 0.0008 0.0016 0.0022 0.0002 0.0031 -0.0005 0.0035 27 0.101 0.030 0.0009 0.0009 -0.0003 0.0015 -0.0007 0.0009 0.0004 0.0021 -0.0006 0.0022 -0.0017 0.0028 LOCATION Ru-103 Ru-106 Cs-134 Cs-137 Ba-140 Ce-141 Ce-144

(+/-) (+1-) (+/-) (+1-) (+/-) (+/-) (+/-)

1 0.0005 0.0018 -0.010 0.013 0.0003 0.0007 0.0007 0.0008 -0.012 0.023 -0.0008 0.0030 0.0009 0.0041 2 0.0000 0.0022 0.009 0.011 -0.0009 0.0008 0.0000 0.0007 0.000 0.032 -0.0024 0.0033 -0.0019 0.0028 3 0.0005 0.0027 -0.002 0.009 0.0001 0.0008 0.0001 0.0008 -0.001 0.030 -0.0015 0.0032 0.0001 0.0042 4 0.0005 0.0011 -0.001 0.010 -0.0003 0.0008 0.0012 0.0011 -0.013 0.025 -0.0006 0.0029 -0.0020 0.0038 10 -0.0022 0.0031 0.001 0.011 0.0000 0.0008 -0.0004 0.0014 0.034 0.039 -0.0018 0.0030 -0.0019 0.0028 11 -0.0003 0.0028 0.000 0.011 -0.0005 0.0006 -0.0001 0.0010 0.007 0.014 -0.0016 0.0037 -0.0041 0.0037 15C 0.0010 0.0021 -0.008 0.011 0.0002 0.0003 -0.0001 0.0010 0.011 0.022 -0.0002 0.0027 -0.0002 0.0035 27 -0.0005 0.0017 0.006 0.006 -0.0001 0.0005 0.0001 0.0007 -0.011 0.015 0.0000 0.0022 0.0003 0.0023 3-26

TABLE 4B AIR PARTICULATES GAMMA SPECTRA - QTR 2 (pCi/m3)

ANALYSES LOCATION Be-7 Mn-54 Co-58 Co-60 Zn-65(+--) Nb-95 Zr-95

(+1-) (+1-) (-00) (+/-) (*/-)

1 0.108 0.039 0.0003 0.0010 -0.0004 0.0008 -0.0004 0.0008 -0.0003 0.0023 -0.0012 0.0027 0.0016 0.0022 2 0.125 0.040 0.0004 0.0010 -0.0003 0.0021 0.0000 0.0008 0.0004 0.0024 0.0007 0.0021 -0.0006 0.0037 3 0.133 0.041 0.0003 0.0005 0.0001 0.0012 0.0000 0.0000 -0.0020 0.0033 -0.0012 0.0027 -0.0020 0.0023 4 0.089 0.037 0.0006 0.0010 0.0007 0.0017 0.0002 0.0010 0.0016 0.0031 -0.0004 0.0033 -0.0006 0.0037 10 0.166 0.039 -0.0007 0.0007 0.0007 0.0014 -0.0003 0.0005 -0.0008 0.0018 -0.0002 0.0033 -0.0008 0.0029 11 0.141 0.042 0.0008 0.0012 0.0010 0.0015 0.0002 0.0010 -0.0026 0.0030 -0.0015 0.0040 0.0000 0.0024 15C 0.079 0.039 -0.0003 0.0013 0.0000 0.0000 0.0017 0.0017 -0.0005 0.0043 -0.0007 0.0014 -0.0013 0.0038 0.165 0.041 0.0002 0.0011 0,0000 0,0013 -0.0006 0.0009 0.0005 0.0019 -0.0003 0.0031 0.0000 0.0028 27 LOCATION Ru-1 03 Ru-1 06 Cs- 134 Cs-1 37 Ba-140 Ce-141

..................... Ce-144

(+/-) (+/-) (+/-) (+--) (+1-) (,/-)

1 0.0005 0.0021 0.0017 0.0075 -0.0003 0.0008 0.0002 0.0008 0.0090 0.0170 0.0021 0.0028 -0.0020 0.0031 2 0.0009 0.0023 0.0052 0.0095 0.0002 0.0007 0.0005 0.0008 -0.0110 0.0150 -0.0016 0.0032 0.0017 0.0040 3 -0.0005 0.0021 -0.0030 0.0120 0.0001 0.0006 -0.0010 0.0012 0.0080 0.0170 0.0005 0.0026 0.0031 0.0035 4 -0.0003 0.0024 -0.0020 0.0095 0.0005 0.0009 -0.0003 0.0010 -0.0180 0.0320 -0.0017 0.0028 -0.0001 0.0047 10 0.0018 0.0022 0.0004 0.0083 -0.0002 0.0006 -0.0007 0.0009 -0.0020 0.0430 0.0019 0.0027 -0.0003 0.0023 11 0.0001 0.0025 0.0038 0.0087 0.0001 0.0009 0.0003 0.0007 0.0000 0.0290 -0.0005 0.0030 -0.0011 0.0043 15C -0.0005 0.0023 -0.0054 0.0098 -0.0001 0.0006 -0.0001 0.0013 -0.0200 0.0280 0.0006 0.0022 -0.0009 0.0030 27 0.0000 0.0029 0.0010 0.0092 -0.0002 0.0007 0.0008 0.0009 0.0060 0.0110 0.0016 0.0036 -0.0014 0.0042 3-27

TABLE 4C AIR PARTICULATES GAMMA SPECTRA - QTR 3 (pCi/m3)

ANALYSES LOCATION Be-7 Mn-54 Co-58 Co-60 Zn-65 Nb-95 Zr-95

(+/-) (+1-) (+1-) (+1-) (+/-) (+1-) (+1-)

1 0.115 0.039 -0.0001 0.0010 -0.0010 0.0019 -0.0001 0.0011 0.0018 0.0030 0.0003 0.0024 -0.0003 0.0035 2 0.127 0.045 0.0002 0.0020 0.0016 0.0034 -0.0004 0.0018 0.0031 0.0048 -0.0017 0.0038 0.0007 0.0066 3 0.115 0.039 -0.0008 0.0014 -0.0016 0.0025 0.0004 0.0011 0.0007 0.0031 0.0002 0.0024 -0.0018 0.0043 4 0.159 0.045 -0.0012 0.0015 0.0012 0.0026 0.0000 0.0010 0.0012 0.0033 -0.0006 0.0031 -0.0001 0.0050 10 0.159 0.041 0.0002 0.0015 -0.0005 0.0029 -0.0010 0.0011 0.0017 0.0041 -0.0014 0.0025 0.0002 0.0049 11 0.160 0.036 -0.0004 0.0012 -0.0003 0.0022 0.0004 0,0012 0.0001 0.0024 0.0014 0.0028 0.0041 0.0043 15C 0.119 0.038 -0.0003 0.0017 -0.0006 0.0030 0.0004 0.0013 0.0036 0.0043 -0.0007 0.0032 0.0025 0.0052 27 0.095 0.030 -0.0001 0.0016 -0.0009 0.0034 -0.0001 0.0016 0.0005 0.0044 0.0008 0.0027 0.0005 0.0044 LOCATION Ru-103 Ru-106 Cs-134 Cs-137 Ba-140 Ce-141 Ce-144 1 -0.0021 0.0037 0.0076 0.0101 0.0011 0.0012 0.0004 0.0010 -0.0564 0.3240 0.0021 0.0055 0.0026 0.0050 2 0.0010 0.0052 -0.0279 0.0158 0.0023 0.0017 0.0004 0.0015 0.1110 0.4860 0.0027 0.0087 0.0029 0.0071 3 0.0039 0.0041 0.0015 0.0131 0.0012 0.0013 0.0004 0.0010 0.0774 0.4210 -0.0026 0.0068 0.0024 0.0057 4 0.0011 0.0046 -0.0036 0.0097 0.0019 0.0013 0.0005 0.0010 -0.2390 0.3910 0.0020 0.0072 0.0009 0.0056 10 0.0018 0.0046 -0.0023 0.0121 0.0016 0.0013 0.0006 0.0012 0.2670 0.4640 -0.0033 0.0069 0.0018 0.0063 11 -0.0006 0.0034 -0.0055 0.0118 -0.0008 0.0011 0.0012 0.0011 0.4410 0.3950 0.0008 0.0070 0.0019 0.0060 15C -0.0008 0.0054 -0.0057 0.0147 0.0031 0.0016 0.0004 0.0015 -0.2780 0.4000 0.0020 0.0083 -0.0040 0.0061 27 0.0027 0.0061 -0.0119 0.0157 0.0010 0.0018 -0.0002 0.0013 0.5830 0.4840 -0.0073 0.0090 -0.0002 0.0080 3-28

TABLE 4D AIR PARTICULATES GAMMA SPECTRA - QTR 4 (pCi/m3)

ANALYSES LOCATION Be-7 Mn-54 Co-58 Co-60 Zn-65 Nb-95 Zr-95

(+--) (+--) (+1-) -- (- ) -- (- ) (+--) (F--)

1 0.079 0.026 0.0000 0.0010 -0.0008 0.0017 0.0000 0.0010 0.0002 0.0028 0.0018 0.0020 -0.0032 0.0036 2 0.110 0.036 -0.0002 0.0017 -0.0008 0.0025 0.0004 0.0012 -0.0016 0.0027 0.0010 0.0026 -0.0009 0.0046 3 0.109 0.028 0.0001 0.0008 -0.0006 0.0018 -0.0006 0.0012 -0.0013 0.0019 0.0006 0.0017 -0.0009 0.0028 4 0.098 0.032 -0.0003 0.0009 0.0006 0.0018 0.0005 0.0011 -0.0017 0.0025 0.0007 0.0020 0.0012 0.0038 10 0.110 0.031 -0.0009 0.0015 0.0000 0.0025 -0.0003 0.0015 0.0010 0.0040 -0.0020 0.0028 0.0019 0.0048 11 0.096 0.031 -0.0009 0.0012 -0.0007 0.0020 0.0006 0.0014 0.0033 0.0028 0.0013 0.0020 -0.0025 0.0038 15C 0.100 0.025 -0.0003 0.0011 0.0006 0.0017 0.0005 0.0010 -0.0012 0.0023 0.0010 0.0015 -0.0025 0.0033 27 0.085 0.045 0.0007 0.0016 -0.0010 0.0026 -0.0004 0.0011 0.0001 0.0038 -0.0013 0.0031 0.0017 0.0045 LOCATION Ru-103 Ru-106 Cs-134 Cs-137 Ba-140 Ce-141 Ce-144 1 -0.0009 0.0030 -0.0101 0.0088 0.0012 0.0012 -0.0003 0.0008 -0.0420 0.1350 -0.0003 0.0042 -0.0010 0.0048 2 0.0012 0.0038 0.0034 0.0131 0.0008 0.0012 0.0003 0.0014 -0.1020 0.2090 -0.0072 0.0056 -0.0041 0.0063 3 -0.0005 0.0022 0.0010 0.0061 -0.0006 0.0008 0.0005 0.0009 0.0282 0.1610 -0.0003 0.0039 0.0005 0.0041 4 -0.0008 0.0029 -0.0061 0.0083 -0.0005 0.0010 0.0002 0.0010 0.0248 0.1710 -0.0011 0.0050 0.0035 0.0051 10 0.0018 0.0039 -0.0042 0.0129 -0.0007 0.0013 -0.0001 0.0013 -0.0898 0.2380 -0.0022 0.0064 -0.0060 0.0067 11 -0.0016 0.0035 -0.0060 0.0097 0.0003 0.0013 0.0002 0.0010 -0.0184 0.1870 0.0022 0.0053 -0.0007 0.0057 15C 0.0002 0.0027 -0.0013 0.0098 0.0009 0.0011 -0.0002 0.0008 -0.0127 0.1420 -0.0010 0.0044 0.0005 0.0052 27 0.0008 0.0040 0.0033 0.0115 0.0013 0.0013 -0.0007 0.0012 -0.1340 0.1890 0.0003 0.0057 0.0019 0.0066 3-29

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 6 SOIL (pCi/g dry wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+/-) (+/-)

3 06/29/10 0.20 0.53 14.40 1.60 0.29 0.72 0.00 0.04 -0.03 0.06 -0.06 0.15 4 06/29/10 -0.13 0.78 13.30 2.20 -0.67 0.96 -0.01 0.06 0.08 0.07 0.00 0.18 14C 06/30/10 0.80 0.97 11.70 2.30 1.00 1.00 -0.02 0.07 0.03 0.07 0.03 0.14 COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 3 06/29/10 0.00 0.04 -0.15 0.14 -0.03 0.10 0.06 0.11 -0.02 0.07 -0.10 0.37 4 06/29/10 0.01 0.06 -0.29 0.20 -0.05 0.09 0.01 0.13 -0.04 0.10 0.42 0.60 14C 06/30/10 -0.02 0.06 -0.24 0.21 0.00 0.11 0.05 0.16 -0.03 0.09 -0.53 0.58 COLLECTION LOCATION DATE Sb-125 Cs-1 34 Cs-1 37 Ce-141 Ce-144 AcTh-228 T+-/-) (+/-)

3 06/29/10 -0.03 0.11 0.05 0.04 0.41 0.09 0.15 0.13 -0.29 0.26 1.17 0.20 4 06/29/10 -0.08 0.21 0.00 0.06 0.30 0.12 -0.06 0.18 -0.17 0.50 1.68 0.34 14C 06/30/10 -0.05 0.22 0.00 0.05 1.33 0.21 0.03 0.18 0.33 0.49 0.81 0.30 3-30

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 8 GOAT MILK (pCi/I)

COLLECTION LOCATION DATE

Sr-89 Sr-90 K-40 1-131 Cs-134 Cs-137 Ba-140 La-140---

(+1---

-)--- (+/-)

21 05/19/2010 1010 130 -0.09 0.03 -0.9 2.7 -3.8 3.6 -1.6 7.3 -1.6 7.3 21 06/09/2010 1680 180 0.19 0.44 3.3 4.1 7.8 5.5 -0.7 6.8 -0.7 6.8 21 06/23/2010 1480 89 -0.16 0.25 -0.9 1.6 12.4 3.3 6.5 6.4 6.5 6.4 21 07/14/2010 1280 111 0.09 0.55 -2.0 3.0 4.0 4.5 -1.1 13.1 6.4 3.8 21 07/28/2010 1430 55 0.06 0.45 0.8 1.2 5.5 1.5 2.0 10.8 -1.0 3.3 21 08/04/2010 1420 96 -0.30 0.38 -4.9 2.4 8.4 6.7 1.9 17.4 -4.9 3.9 21 08/18/2010 1440 54 0.03 0.43 0.9 1.3 7.3 1.7 10.3 13.1 -0.1 3.6 21 09/08/2010 -1.38 5.14 1.27 0.88 1240 117 -0.26 0.48 -2.6 3.3 5.0 5.5 -1.5 21.1 -1.9 6.5 24C 05/19/2010 1650 170 0.25 0.47 -4.1 3.4 4.4 5.8 -2.2 6.7 -2.2 6.7 24C 06/09/2010 1630 83 -0.12 0.04 0.7 1.7 6.1 2.9 4.3 7.3 4.3 7.3 24C 08/18/2010 A A 1560 53 -0.34 0.48 0.0 1.2 5.3 1.8 1.0 11.9 -2.7 3.3 A: Laboratory QC failed. Not enough sample to perform a rerun.

3-31

Millstone Station Millton StaionAnnual Radiological Environmental Operating Report 2010 TABLE 9 PASTURE GRASS / HAY (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-5i Mn-54 Co-58 Fe-59 Co-60 21 01/13/10 F -0.010 0.130 9.35 0.80 0.02 0.12 -0.004 0.016 0.001 0.017 0.018 0.042 0.006 0.020 21 02/16/10 F 0.070 0.200 9.80 1.10 0.13 0.25 0.002 0.025 0.004 0.029 -0.037 0.068 0.010 0.030 21 03/17/10 F 0.110 0.380 10.30 1.60 -0.06 0.34 0.02 1 0.043 0.009 0.038 0.000 0.100 0.006 0.038 21 04/07/10 E 0.520 0.320 13.90 0.77 -0.18 0.28 -0.003 0.026 0.017 0.030 -0.027 0.067 0.003 0.029 21 04/21/10 1.410 0.380 5.93 0.91 -0.21 0.27 -0.004 0.023 -0.016 0.030 0.018 0.056 0.003 0.033 21 05/05/10 0.930 0.330 5.06 0.85 0.09 0.18 -0.009 0.023 0.002 0.021 0.062 0.063 0.003 0.027 21 09/22/10 7.320 0.229 4.29 0.23 0.03 0.07 -0.002 0.004 -0.003 0.004 0.012 0.010 0.001 0.004 21 10/07/10 5.960 0.407 2.17 0.41 0.01 0.13 -0.004 0.013 -0.007 0.011 -0.040 0.024 0.019 0.013 21 10/21/10 2.630 0.264 6.26 0.48 -0.03 0.10 -0.004 0.010 0.010 0.011 0.012 0.025 0.005 0.014 21 11/18/10 3.500 0.303 6.74 0.46 0.05 0.11 -0.004 0.010 0.001 0.010 -0.001 0.025 -0.005 0.012 21 12/28/10 0.000 0.123 9.43 0.71 0.10 0.13 -0.002 0.014 -0.005 0.015 0.008 0.038 -0.006 0.021 24C 01/13/10 E 1.060 0.320 10.60 0.90 0.02 0.20 -0.032 0.031 0.018 0.029 -0.055 0.073 0.018 0.036 24C 02/16/10 E 0.640 0.350 10.30 0.82 -0.04 0.34 -0.005 0.030 -0.021 0.033 -0.035 0.079 -0.018 0.031 24C 03/17/10 E 0.390 0.320 13.20 0.83 0.09 0.30 -0.001 0.030 -0.013 0.030 0.023 0.071 0.012 0.033 24C 04/07/10 0.960 0.310 4.72 0.69 0.00 0.17 0.009 0.018 -0.015 0.020 0.031 0.048 0.013 0.018 24C 04/21/10 0.360 0.200 6.33 0.66 0.07 0.14 -0.016 0.016 0.007 0.017 0.006 0.042 0.005 0.018 24C 05/05/10 0.300 0.240 5.06 0.99 0.04 0.19 0.023 0.030 -0.007 0.022 0.021 0.072 -0.018 0.030 24C 06/23/10 F 0.090 0.210 11.90 1.10 0.15 0.27 -0.009 0.021 -0.007 0.026 -0.027 0.078 -0.018 0.021 24C 07/14/10 F -0.016 0.124 12.40 0.59 -0.06 0.14 0.000 0.014 -0.009 0.015 -0.016 0.035 0.008 0.015 24C 07/28/10 1.860 0.144 5.75 0.24 -0.01 0.08 0.000 0.006 -0.004 0.006 -0.012 0.014 0.005 0.005 24C 08/04/10 1.340 0.288 5.19 0.43 0.00 0.10 0.006 0.007 -0.004 0.009 -0.005 0.016 -0.002 0.007 24C 09/08/10 0.939 0.130 5.86 0.32 0.02 0.08 0.001 0.006 0.002 0.007 -0.017 0.017 0.003 0.008 24C 09/22/10 1.880 0.091 4.82 0.15 0.02 0.05 0.000 0.003 0.000 0.004 -0.002 0.009 0.000 0.004 24C 10/07/10 3.890 0.398 6.22 0.66 -0.05 0.17 0.009 0.017 -0.002 0.016 0.009 0.036 0.001 0.021 24C 10/21/10 3.550 0.294 2.89 0.33 0.07 0.11 0.001 0.010 -0.010 0.011 -0.005 0.023 -0.007 0.010 24C 11/18/10 5.000 0.299 6.80 0.46 -0.11 0.13 -0.005 0.012 0.001 0.013 -0.008 0.028 0.003 0.015 24C 12/28/10 E 0.139 0.177 13.00 0.81 -0.02 0.16 -0.009 0.015 -0.003 0.015 -0.013 0.034 -0.002 0.017 E - Hay F - Feed 3-32

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 9 PASTURE GRASS / HAY (pCi/g wet wt.)

COLLECTION LOCATION DATE Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125 1-131

(+/-) (+/-) ---- ?;-5) - - -- - - -(+/-)ý- ------ - - ------ ---)T 21 01/13/10 -0.053 0.050 -0.006 0.020 -0.006 0.026 0.016 0.015 0.030 0.170 0.008 0.037 -0.001 0.029 21 02/16/10 -0.101 0.080 -0.004 0.041 0.012 0.048 -0.002 0.027 -0.060 0.220 0.014 0.063 0.051 0.087 21 03/17/10 -0.050 0.110 0.025 0.043 -0.008 0.052 0.024 0.046 0.050 0.300 -0.004 0.079 0.036 0.092 21 04/07/10 -0.102 0.070 0.019 0.037 0.006 0.053 -0.010 0.033 0.000 0.220 0.001 0.068 0.160 0.170 21 04/21/10 -0.042 0.064 0.019 0.034 0.012 0.050 0.017 0.031 0.200 0.260 -0.016 0.069 0.004 0.015 21 05/05/10 -0.008 0.071 -0.013 0.027 -0.014 0.044 0.011 0.023 0.070 0.230 -0.045 0.058 0.006 0.022 21 09/22/10 0.002 0.008 0.000 0.004 -0.005 0.007 -0.003 0.006 0.026 0.033 -0.008 0.012 0.026 0.038 21 10/07/10 0.019 0.027 -0.001 0.012 -0.001 0.021 0.010 0.013 -0.004 0.113 0.004 0.037 0.009 0.024 21 10/21/10 -0.001 0.027 0.001 0.011 0.006 0.020 0.003 0.011 0.006 0.092 -0.005 0.029 0.019 0.026 21 11/18/10 0.002 0.026 -0.006 0.011 0.006 0.020 -0.008 0.011 0.012 0.083 -0.004 0.027 -0.023 0.029 21 12/28/10 -0.068 0.046 0.015 0.017 -0.005 0.025 -0.003 0.015 0.014 0.143 -0.017 0.038 -0.007 0.031 24 01/13/10 0.000 0.110 -0.011 0.031 -0.035 0.049 -0.007 0.027 -0.010 0.270 -0.021 0.069 0.010 0.044 24 02/16/10 -0.091 0.078 -0.005 0.049 -0.041 0.058 0.005 0.039 0.280 0.270 0.012 0.076 0.100 0.140 24 03/17/10 -0.042 0.079 0.017 0.039 -0.005 0.054 0.014 0.035 -0.360 0.250 -0.056 0.075 0.050 0.150 24 04/07/10 0.002 0.049 -0.007 0.017 0.017 0.040 -0.004 0.021 0.100 0.160 0.026 0.047 -0.006 0.003 24 04/21/10 0.007 0.042 -0.004 0.019 -0.008 0.030 -0.001 0.020 -0.020 0.150 -0.020 0.044 0.011 0.020 24 05/05/10 -0.007 0.058 -0.013 0.023 -0.011 0.041 0.030 0.028 0.120 0.270 0.009 0.065 0.008 0.025 24 06/23/10 -0.040 0.064 -0.006 0.039 -0.040 0.045 0.042 0.030 0.000 0.210 -0.025 0.051 0.070 0.300 24 07/14/10 -0.052 0.037 0.006 0.015 -0.001 0.025 -0.007 0.015 0.010 0.135 -0.016 0.038 0.016 0.026 24 07/28/10 -0.004 0.012 -0.005 0.007 0.008 0.011 -0.007 0.008 0.010 0.050 -0.001 0.015 0.004 0.034 24 08/04/10 0.010 0.015 0.002 0.009 -0.013 0.016 0.001 0.010 0.057 0.077 0.006 0.022 0.011 0.036 24 09/08/10 -0.004 0.018 -0.001 0.008 -0.004 0.012 -0.005 0.008 0.002 0.056 0.007 0.017 0.001 0.036 24 09/22/10 -0.001 0.009 -0.002 0.005 -0.002 0.007 0.000 0.005 0.001 0.031 -0.005 0.009 0.006 0.032 24 10/07/10 -0.027 0.045 0.011 0.017 -0.004 0.027 -0.002 0.017 0.009 0.150 0.014 0.050 0.035 0.033 24 10/21/10 -0.017 0.025 0.002 0.010 -0.002 0.020 -0.002 0.010 0.028 0.088 -0.010 0.026 0.015 0.027 24 11/18/10 -0.040 0.031 0.004 0.013 -0.001 0.022 0.017 0.014 -0.028 0.113 -0.002 0.033 -0.005 0.035 24 12/28/10 0.024 0.033 -0.014 0.016 -0.026 0.027 0.004 0.018 -0.003 0.138 0.027 0.044 -0.003 0.035 3-33

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 9 PASTURE GRASS / HAY (pCi/g wet wt.)

COLLECTION LOCATION DATE Cs- 134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 AcTh-228

(+/-) (+/-) (+/-) (+/-) (+/-) (+/-)

21 01/13/10 0.003 0.013 0.008 0.017 0.012 0.023 0.012 0.023 -0.004 0.020 -0.026 0.064 0.021 0.074 21 02/16/10 0.008 0.019 -0.026 0.033 -0.025 0.076 -0.025 0.076 -0.030 0.031 0.080 0.110 -0.010 0.100 21 03/17/10 -0.003 0.022 0.005 0.035 -0.003 0.061 -0.003 0.061 -0.005 0.048 -0.030 0.150 0.070 0.160 21 04/07/10 0.005 0.027 0.013 0.025 -0.080 0.100 -0.080 0.100 0.015 0.038 0.050 0.110 0.090 0.130 21 04/21/10 -0.012 0.020 0.020 0.025 -0.012 0.053 -0.012 0.053 -0.061 0.038 -0.070 0.110 -0.020 0.110 21 05/05/10 -0.007 0.018 0.003 0.025 -0.021 0.059 -0.021 0.059 -0.027 0.028 -0.045 0.086 0.002 0.095 21 09/22/10 -0.001 0.003 0.057 0.013 0.003 0.055 0.008 0.012 0.006 0.011 -0.012 0.030 0.036 0.055 21 10/07/10. 0.006 0.013 0.047 0.025 0.008 0.063 -0.016 0.017 -0.002 0.026 -0.039 0.099 0.034 0.087 21 10/21/10 -0.003 0.011 0.000 0.011 -0.003 0.065 0.009 0.015 -0.012 0.020 -0.086 0.080 0.106 0.046 21 11/18/10 -0.004 0.011 0.007 0.012 0.015 0.062 0.010 0.016 -0.007 0.020 0.041 0.072 0.024 0.083 21 12/28/10 0.001 0.017 -0.003 0.015 -0.025 0.070 -0.001 0.022 0.009 0.022 0.020 0.080 0.011 0.064 24 01/13/10 -0.010 0.023 0.035 0.039 -0.044 0.063 -0.044 0.063 0.004 0.046 0.050 0.110 -0.030 0.160 24 02/16/10 0.011 0.027 0.021 0.030 -0.050 0.110 -0.050 0.110 0.002 0.047 -0.070 0.120 0.080 0.160 24 03/17/10 0.002 0.020 0.001 0.028 -0.051 0.088 -0.051 0.088 -0.065 0.063 0.040 0.110 0.250 0.140 24 04/07/10 -0.003 0.015 -0.009 0.018 -0.002 0.035 -0.002 0.035 -0.008 0.023 0.022 0.069 -0.019 0.065 24 04/21/10 0.009 0.015 0.012 0.016 0.011 0.040 0.011 0.040 -0.006 0.019 -0.028 0.063 0.003 0.059 24 05/05/10 -0.002 0.018 0.012 0.027 -0.029 0.043 -0.029 0.043 0.001 0.031 -0.014 0.087 0.080 0.110 24 06/23/10 0.005 0.015 -0.007 0.023 -0.080 0.130 -0.080 0.130 -0.043 0.041 -0.044 0.082 0.028 0.097 24 07/14/10 -0.014 0.017 -0.003 0.016 0.031 0.068 -0.001 0.018 -0.012 0.026 0.061 0.100 0.016 0.090 24 07/28/10 -0.002 0.006 0.001 0.007 0.032 0.058 -0.012 0.016 0.006 0.013 -0.027 0.040 0.045 0.028 24 08/04/10 0.006 0.008 -0.002 0.008 0.013 0.068 0.000 0.015 -0.008 0.019 -0.012 0.056 0.084 0.107 24 09/08/10 0.004 0.007 -0.003 0.006 0.073 0.066 -0.012 0.015 -0.010 0.014 -0.015 0.047 0.027 0.042 24 09/22/10 -0.003 0.004 0.006 0.004 0.027 0.045 -0.013 0.013 0.006 0.008 0.006 0.022 0.015 0.027 24 10/07/10 0.009 0.017 0.007 0.017 0.062 0.087 0.011 0.028 0.000 0.031 0.073 0.122 -0.032 0.058 24 10/21/10 0.002 0.011 -0.001 0.010 -0.025 0.060 0.006 0.016 -0.006 0.019 0.042 0.068 0.003 0.041 24 11/18/10 0.005 0.014 -0.002 0.013 0.029 0.075 0.001 0.022 -0.008 0.023 0.015 0.079 0.099 0.090 24 12/28/10 -0.002 0.016 0.031 0.018 -0.015 0.095 0.002 0.022 -0.025 0.029 0.007 0.105 -0.015 0.071 3-34

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 10 WELL WATER (pCi/I)

COLLECTION LOCATION DATE H-3 Sr-89 Sr-90 Be-7 K-40 Cr-51 Mn-54 Co-58

(+1-) (+/-) (+/-) (+/-) (+/-) (*/-) (+1-) (+/-)

71 03/16/10 -520 870 -8.4 3.3 1.03 0.92 -12 33 -33 42 21 37 0.2 3.8 -0.7 3.1 71 06/21/10 440 850 -3.2 3.5 0.57 0.99 -2 22 6 48 -19 25 -0.9 2.6 0.8 2.5 71 09/20/10 -164 542 0.3 2.3 0.70 0.97 -1 9 32 22 -9 12 0.2 0.9 0.9 1.1 71 12/22/10 316 457 0 12 21 22 7 16 0.1 1.1 0.2 1.2 72 03/10/10 -230 880 -1.4 2.4 0.30 0.93 -2 30 -16 44 -12 29 1.5 3.8 0.0 3.4 72 03/26/10 -490 870 -1.4 3.1 0.38 0.91 11 32 38 48 11 34 -3.3 3.9 1.6 3.1 72 06/16/10 -310 830 -2.3 2.5 0.06 0.66 13 21 0 44 -15 21 -0.9 2.7 1.7 2.5 72 09/16/10 -174 555 1.9 2.4 0.47 0.97 6 14 -17 24 -12 18 -1.2 1.2 0.9 1.4 72 12/15/10 -443 531 13 30 24 69 -13 28 0.7 3.6 -5.3 3.7 76X 02/26/10 490 870 -2.5 2.6 -0.59 0.66 -3 21 8 34 -16 21 0.0 1.9 1.3 2.2 76X 06/15/10 550 870 -2.9 2.1 -0.14 0.55 15 18 -20 31 2 19 -1.0 2.0 -1.8 2.3 76X 09/13/10 268 679 1.8 1.7 0.17 0.65 -4 12 8 25 -7 16 -0.8 1.2 0.4 1.5 76X 12/07/10 -110 442 -3 31 53 68 -1 35 -0.4 2.9 -1.2 3.3 77X 02/26/10 170 870 -1.2 2.5 -0.14 0.63 14 20 13 44 -6 22 -0.3 2.1 0.7 2.6 77X 06/15/10 -290 820 1.7 2.7 -0.23 0.67 -1 22 -6 40 -2 22 2.4 2.7 1.4 2.6 77X 09/13/10 -346 651 0.1 1.8 0.06 0.67 3 12 41 32 7 15 0.2 1.3 -1.3 1.4 77X 12/07/10 -302 430 -13 25 48 62 3 28 0.7 3.1 -2.8 3.0 78X 02/26/10 380 850 -1.4 2.3 0.06 0.60 5 24 -11 43 -2 24 -2.3 2.4 0.2 2.4 78X 06/15/10 -390 820 -0.3 2.6 -0.69 0.66 7 22 -13 39 13 22 0.1 2.4 -0.5 2.3 78X 09/13/10 273 679 0.3 1.7 -0.09 0.571 3 14 7 27 4 17 -0.3 1.3 -0.8 1.4 78X 12/07/10 137 469 1,; 31 -13 52 -10 38 0.8 3.7 -0.2 4.2 79 03/10/10 -350 870 0.3 2.2 0.20 0.82 -3 28 -31 46 -23 29 1.0 3.5 2.0 3.6 79 06/21/10 490 840 -2.0 3.5 0.07 0.95 4 23 16 46 30 25 2.1 2.5 -0.9 2.8 79 09/15/10 -397 544 -0.7 2.6 0.86 0.85 16 14 45 34 -12 19 0.1 1.4 0.3 1.7 79 12/08/10 222 460 2 27 31 69 -3 32 2.0 3.1 2.7 3.1 80 03/16/10 320 900 -1.5 4.0 0.70 1.00 -7 30 5 53 -1 34 0.9 3.5 0.2 3.9 80 06/21/10 1660 880 -0.1 3.5 -0.07 0.91 -5 26 14 38 2 26 -0.1 2.4 0.7 2.9 80 08/05/10 176 609 -2 12 12 21 -14 17 -0.3 1.2 -0.6 1.3 80 09/20/10 554 599 2.0 2.3 0.93 0.77 3 9 31 26 3 12 -0.3 0.9 0.1 1.1 80 12/15/10 286 560 -16 30 80 65 12 32 -3.1 3.6 -2.8 3.8 80A 08/05/10 841 691 1 11 -5 27 0 13 0.3 1.2 -1.3 1.3 3-35

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 10 WELL WATER (pCi/I)

COLLECTION LOCATION DATE H-3 Sr-89 Sr-90 Be-7 K-40 Cr-51 Mn-54 Co-58

(+/-) (+/-) (+/-) (+1-) (+/-) (+/-) (+/-)

81 03/16/10 250 900 -4.0 3.1 0.31 0.79 4 27 56 51 23 32 1.0 3.3 -0.2 3.9 81 06/21/10 490 840 0.7 4.0 0.20 1.00 -7 22 21 45 9 23 1.4 2.4 1.2 2.8 81 09/20/10 -438 536 0.7 2.6 0.18 0.83 6 6 -92 16 3.8 7.2 -0.1 0.6 0.2 0.7 81 12/22/10 206 215 7 10 24 23 -8.3 13.4 -0.1 1.0 0.9 1.1 82 03/10/10 -120 880 -1.4 2.5 1.16 0.98 -18 28 -15 46 3.0 29.0 0.7 3.1 -2.6 3.1 82 03/26/10 70 880 -1.2 2.9 0.65 0.88 21 27 -3 49 15.0 26.0 -2.6 2.8 0.5 3.3 82 06/16/10 450 870 -2.8 3.6 0.80 1.10 -17 23 0 45 -10.0 23.0 -1.2 2.7 -2.0 2.9 82 08/05/10 786 688 1 14 65 24 -2.0 18.7 0.5 1.2 -1.3 1.4 82 09/15/10 -370 541 2.5 2.6 1.17 0.90 7 10 15 20 -4.6 13.5 -0.6 1.0 -0.2 1.1 82 12/15/10 194 562 -5 34 8 62 7.1 38.6 0.3 3.9 -4.9 4.0 83 03/10/10 -530 860 1.0 2.2 0.45 0.80 0 30 -2 41 -9.0 32.0 1.1 3.7 -1.8 3.0 83 03/26/10 -250 870 -0.6 3.0 0.90 0.92 14 29 38 33 -3.0 30.0 1.5 3.1 -7.4 3.7 83 06/16/10 -110 850 -3.4 2.4 0.00 0.64 4 26 44 40 -24.0 27.0 0.1 2.7 -1.5 2.7 83 09/15/10 -55.4 554 0.4 2.4 0.93 0.73 10 13 76 30 9.9 17.9 -1.5 1.3 0.1 1.4 83 12/08/10 -9.61 452 -24 32 68 60 -0.5 39.2 -2.8 3.5 -3.9 3.7 84 03/10/10 150 880 -0.7 2.2 -0.55 0.81 -5 24 -4 42 -6.0 24.0 1.5 2.5 0.0 2.7 84 06/16/10 180 860 -0.2 2.4 -0.05 0.62 -1 28 -16 46 12.0 27.0 0.4 2.8 2.6 3.2 84 09/20/10 296 571 1.2 2.2 0.20 0.62 6.1 12.0 18 26 -6.8 16.2 -0.6 1.1 0.9 1.3 84 12/08/10 67.7 552 15.7 23.3 1 38 -9.0 30.2 -0.2 2.4 0.8 3.0 85 02/24/10 320 880 -0.7 2.4 1.20 0.84 -11.0 35.0 30 49 6.0 35.0 -2.0 3.8 -4.6 3.4 85 06/24/10 490 840 2.9 3.5 1.02 0.96 7.0 32.0 42 49 1.0 35.0 -1.4 3.3 -0.2 3.2 85 08/05/10 857 701 2.3 15.2 27 36 4.9 19.9 -1.3 1.4 -0.8 1.6 85 09/08/10 83.1 1070 0.9 2.1 1.00 0.858 -11.8 17.5 42 34 -18.8 24.3 -1.2 1.9 -0.2 2.0 85 12/06/10 586 500 13.3 27.7 62 67 -2.9 32.8 -0.7 3.0 -1.4 3.5 86 02/24/10 750 920 -3.7 5.1 0.68 0.76 -4.0 31.0 8 45 17.0 34.0 2.8 3.9 0.0 3.5 86 06/24/10 280 820 -1.4 3.6 0.20 1.00 -15.0 27.0 -34 46 -19.0 30.0 -1.2 3.0 -2.1 3.1 86 09/02/10 309 1080 1.5 2.9 1.18 1.22 3.3 14.6 -46 30 -8.0 18.9 -0.4 1.3 0.5 1.6 86 12/06/10 86.8 460 3.3 21.1 -5 31 -4.8 22.8 -1.0 2.2 -1.3 1.9 91 09/20/10 -274 534 0.7 2.0 0.22 0.85 8.1 9.8 38 27.7 -11.9 13.2 -0.3 0.9 -1.0 1.1 91 12/22/10 248 244 9.3 11.2 21 25.7 2.2 14.8 -0.8 1.0 0.2 1.2 92 09/21/10 -147 560 1.5 2.1 0.27 0.77 5.3 13.0 0 32.6 -8.5 18.1 -1.0 1.2 -0.2 1.4 92 12/15/10 -386 534 34.7 34.8 -28 60.7 9.4 32.8 -0.2 4.0 -0.3 4.3 3-36

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 10 WELL WATER (pCi/I)

COLLECTION LOCATION DATE Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Sb-1 25

(+/-) (+1-) (+1-) (+/-) (+1-) (+1-) (+/-) (+/-)

71 03/16/10 7.8 8.0 -2.8 4.2 -2.8 8.1 1.8 4.7 -0.2 6.4 -1.8 4.5 -14 36 0.0 10.0 71 06/21/10 0.6 6.8 0.2 3.4 -10.2 7.5 0.3 3.4 2.4 4.6 -0.7 2.9 -5 26 -2.1 6.8 71 09/20/10 0.1 2.4 -1.1 0.9 -0.1 2.1 1.2 1.1 1.0 1.8 -1.9 1.4 -2.4 7.9 -0.1 2.6 71 12/22/10 0.2 2.8 0.8 1.1 3.0 2.6 0.0 1.3 0.3 2.3 0.3 1.8 7.1 10.5 -0.3 3.2 72 03/10/10 -17.7 8.9 -1.0 4.4 -0.6 7.5 2.4 4.3 -3.6 6.9 -2.5 4.1 4.0 26.0 8.0 9.6 72 03/26/10 -4.4 7.0 -2.9 3.6 -5.7 6.8 -1.8 3.7 -0.9 5.5 -0.3 4.1 13.0 33.0 4.5 9.3 72 06/16/10 1.1 6.2 2.1 2.8 0.1 7.1 -0.8 3.1 1.5 4.6 -1.1 2.7 9.0 22.0 4.9 6.6 72 09/16/10 -2.4 3.3 0.3 1.3 -2.7 3.2 1.1 1.5 0.4 2.6 -0.9 1.8 1.2 11.7 2.2 3.6 72 12/15/10 0.8 7.6 1.1 4.3 3.6 6.9 2.7 3.9 2.0 6.2 -6.8 3.8 -24.7 30.9 -3.5 9.5 76X 02/26/10 1.9 5.1 1.1 2.4 7.3 9.5 -0.4 2.8 -0.5 4.2 -2.3 2.8 -9.0 21.0 1.0 5.8 76X 06/15/10 3.9 4.6 0.7 2.1 1.6 4.6 -0.2 2.6 0.3 3.6 -1.2 2.4 -15.0 16.0 -0.5 5.4 76X 09/13/10 0.5 3.2 0.3 1.4 1.3 3.0 0.6 1.4 0.3 2.4 -0.2 1.9 -7.8 11.5 -2.5 3.7 76X 12/07/10 -6.0 6.5 1.9 2.9 -6.0 7.5 -0.7 3.5 1.5 5.7 -1.1 3.4 -0.8 30.8 2.6 9.8 77X 02/26/10 0.6 6.3 -2.1 2.9 -2.0 6.8 -1.9 3.3 -0.1 4.4 -2.3 2.8 -4.0 25.0 -0.7 6.3 77X 06/15/10 -3.1 5.8 -0.2 3.0 -4.4 6.1 -1.4 3.0 -2.4 4.8 -1.9 2.6 3.0 23.0 -6.9 6.7 77X 09/13/10 -0.1 3.0 -0.2 1.7 0.5 2.9 -0.3 1.5 -1.2 2.4 -2.5 1.7 -1.8 12.2 -1.4 3.4 77X 12/07/10 0.9 6.6 -1.3 2.8 0.1 6.6 4.2 3.6 -2.0 5.4 1.1 3.3 -11.1 26.4 7.5 8.6 78X 02/26/10 -5.9 6.1 0.0 2.8 3.5 8.3 -1.4 3.0 0.1 5.3 2.5 3.0 -18.0 25.0 3.0 6.8 78X 06/15/10 3.3 5.8 -0.2 2.9 -2.1 6.0 0.3 2.9 1.0 4.6 -2.0 2.9 -7.0 23.0 -1.5 6.3 78X 09/13/10 2.9 3.2 0.2 1.3 -1.3 3.0 0.1 1.5 -0.2 2.6 0.5 1.7 -3.0 11.9 -0.3 3.8 78X 12/07/10 -0.6 7.8 -0.5 3.2 -13.1 8.3 1.4 4.4 -6.4 6.7 -1.3 4.3 9.1 36.1 -1.2 10.4 79 03/10110 4.2 7.7 0.0 3.9 0.5 7.7 3.7 4.0 2.6 6.4 -0.3 4.1 1.0 30.0 4.3 9.9 79 06/21/10 3.3 7.1 0.1 3.3 1.4 5.7 0.9 3.8 -0.8 5.2 -0.2 3.1 4.0 23.0 0.3 6.5 79 09/15/10 1.0 3.3 -0.5 1.6 -0.3 3.0 0.2 1.7 -2.1 2.9 -1.4 1.8 -7.8 12.2 -1.0 3.6 79 12/08110 -3.2 6.4 -1.4 3.1 -7.9 7.8 -1.3 3.0 2.7 5.8 2.3 3.6 17.5 28.5 5.0 8.5 80 03/16/10 2.0 6.1 -2.7 4.2 15.0 12.0 -3.6 4.9 0.8 6.4 -5.1 4.3 23.0 31.0 6.0 10.0 80 06/21/10 2.3 7.0 -0.4 2.8 -3.6 8.3 4.2 3.6 -2.3 5.0 0.4 3.4 -14.0 23.0 4.6 7.4 80 09/20/10 -1.3 2.4 -0.1 0.9 0.0 1.9 -0.7 1.1 0.6 1.8 -1.9 1.3 -1.3 7.8 -0.9 2.5 80 12/15/10 2.2 5.9 3.5 3.5 5.5 6.9 5.0 4.1 -3.7 6.0 -0.9 3.5 4.0 30.4 -0.4 10.4 80 08/05/10 1.8 2.8 0.9 1.1 -6.1 2.8 0.2 1.4 3.1 2.4 -1.9 1.7 3.2 11.1 -2.1 3.5 80A 08/05/10 -0.2 3.0 1.5 1.2 -5.7 2.7 1.0 1.3 3.0 2.3 -1.7 1.5 -5.3 10.4 0.8 2.8 3-37

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 10 WELL WATER (pCi/I)

COLLECTION LOCATION DATE Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 Sb-125

(+/-) (+/-) (+/-) (+1-) (+/-) (+1-) (+/-) (+/-)

81 03/16/10 4.0 7.3 -2.9 3.5 -6.4 7.7 0.2 3.7 3.4 5.2 0.6 3.7 19.0 30.0 -6.5 9.5 81 06/21/10 0.7 6.6 1.7 2.9 -5.0 6.5 0.4 3.2 -1.7 4.9 -1.4 2.8 -15.0 25.0 -1.7 6.5 81 09/20/10 -0.2 1.5 0.2 0.6 -0.3 1.2 -0.2 0.7 -0.6 1.2 -0.4 0.8 2.3 5.4 -0.2 1.6 81 12/22/10 0.004 2.6 -0.4 1.4 -4.1 2.2 0.2 1.2 -1.6 2.0 -1.1 1.7 5.2 9.5 -2.3 2.7 03/10/10 2.7 6.8 -1.0 3.5 15.0 12.0 0.8 4.0 2.2 5.8 0.2 3.6 -2.0 29.0 1.1 9.0 03/26/10 4.2 6.6 -0.2 3.5 4.0 10.0 1.5 6.1 -2.0 5.8 -2.4 3.3 18.0 26.0 -2.7 7.4 06/16/10 -0.8 6.1 0.8 3.0 -1.1 7.6 0.7 3.6 -4.6 4.7 -0.3 3.1 8.0 25.0 2.4 6.6 08/05/10 2.8 2.9 0.5 1.1 1.2 2.7 1.9 1.5 -2.5 2.6 3.0 1.8 7.3 12.0 -2.0 3.7 09/15/10 0.6 2.4 1.2 1.0 -7.1 2.3 1.1 1.3 -0.4 2.0 -0.9 1.6 5.2 9.1 0.5 2.7 12/15/10 -3.4 7.3 -0.8 4.15 6.9 9.5 7.8 4.8 -2.3 6.9 2.4 4.4 26.1 37.0 9.6 12.3 03/10/10 -0.8 6.8 -2.3 3.7 10.0 14.0 1.8 5.6 2.5 5.7 -3.5 3.9 2.0 31.0 1.0 8.6 03/26/10 -4.7 7.9 0.6 3.3 7.0 16.0 1.5 6.2 -0.6 5.9 -1.7 3.8 1.0 27.0 1.1 8.9 06/16/10 -1.0 5.3 -1.7 2.8 11.0 10.0 -2.1 4.8 -0.8 4.3 -4.4 3.3 -10.0 25.0 0.4 7.1 09/15/10 2.4 3.3 -0.5 1.4 -2.6 3.1 0.6 1.6 1.9 2.6 -0.8 1.7 -10.7 11.6 -2.0 3.6 12/08/10 -4.3 7.4 0.2 4.0 0.0 7.8 4.4 4.6 3.8 6.2 0.7 4.4 16.2 31.4 -1.7 11.1 03/10/10 1.5 5.9 1.3 2.4 -6.8 6.1 -0.6 3.4 1.4 5.0 -2.0 3.2 1.0 24.0 -3.0 7.7 06/16/10 1.8 7.4 -1.3 3.7 2.1 6.4 1.7 4.4 3.6 5.8 -4.0 3.6 -25.0 24.0 -1.5 7.7 09/20/10 0.4 3.0 -0.1 1.1 1.0 2.5 0.3 1.6 -0.5 2.3 -0.9 1.9 -3.3 10.0 -0.7 3.3 12/08/10 1.5 5.4 1.4 2.5 -0.8 6.6 1.1 2.9 6.0 4.9 -2.8 2.9 7.2 23.1 -3.4 7.4 02/24/10 2.0 6.8 -1.6 3.3 10.0 17.0 -0.8 6.5 2.5 5.4 -0.1 4.2 17.0 31.0 0.3 9.8 06/24/10 -1.1 7.3 1.9 3.3 7.0 13.0 3.6 6.8 -1.7 5.2 -0.2 4.0 -24.0 32.0 4.1 8.1 08/05/10 0.7 3.3 -0.9 1.4 1.9 3.2 0.3 1.7 -2.7 2.9 -2.3 2.0 -8.9 13.2 1.7 4.1 09/08/10 -3.2 4.0 0.3 1.8 1.8 4.2 4.0 2.7 1.5 3.2 -0.6 2.3 -2.8 18.0 0.9 5.3 12/06/10 -1.0 6.4 0.2 3.0 -6.5 6.8 5.1 3.5 0.3 5.1 -2.2 3.4 -2.6 25.3 7.8 8.5 02/24/10 -3.2 7.3 0.7 3.8 2.5 8.3 1.7 4.1 -0.9 6.3 -0.6 3.8 -12.0 33.0 1.8 9.7 06/24/10 0.4 6.1 0.9 2.6 -3.6 6.6 1.1 3.7 -0.9 5.1 -0.6 3.6 -27.0 25.0 -1.0 8.5 09/02/10 -0.3 3.3 0.4 1.4 0.7 2.5 -0.3 1.5 -2.5 2.7 -0.2 1.9 -8.7 13.4 -0.6 4.2 12/06/10 2.9 4.4 2.6 2.3 -3.0 5.1 0.2 2.6 -1.1 4.3 0.4 2.6 17.7 18.3 1.4 6.5 91 09/21/10 -0.8 2.3 -0.6 0.9 -1.8 1.8 -0.6 1.2 -1.4 2.0 -2.1 1.4 1.5 8.6 0.7 2.8 91 12/15/10 -0.2 2.5 0.6 1.0 0.8 2.4 0.2 1.2 1.1 2.2 -0.3 1.5 1.3 9.6 0.8 2.9 92 09/21/10 -0.3 2.9 -0.1 1.2 4.4 2.7 1.7 1.4 -0.2 2.5 2.6 2.4 -7.6 11.4 2.0 3.6 92 12/15/10 1.4 8.8 0.2 4.4 2.1 7.6 6.0 4.7 -6.3 7.2 -1.5 4.2 26.0 39.0 0.7 10.6 3-38

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 10 WELL WATER (pCi/I)

COLLECTION LOCATION DATE 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 AcTh-228

(+/-) (*/-) (+/-)

71 03/16/10 5.8 8.1 -0.4 3.4 0.0 4.2 -2.5 7.2 -2.5 7.2 0.0 13 71 06/21/10 -0.4 7.3 -1.1 2.3 -1.0 2.7 4.4 8.5 4.4 8.5 -6.0 12 71 09/20/10 1.5 5.4 0.2 1.0 0.3 1.0 0.9 9.3 2.3 3.2 0.7 4.1 71 12/22/10 -1.3 7.4 0.6 1.2 0.4 1.4 7.7 12.2 -0.9 3.6 0.4 5.1 72 03/10/10 1.9 6.3 -0.7 2.6 1.5 3.7 -1.6 7.1 -1.6 7.1 5.0 14.0 72 03/26/10 -5.1 8.0 -0.2 2.7 0.1 3.9 0.0 6.9 0.0 6.9 -3.0 13.0 72 06/16/10 -1.3 5.8 3.3 2.3 0.7 2.7 -1.5 7.9 -1.5 7.9 12.8 9.9 72 09/16/10 -1.8 8.2 0.1 1.4 -0.8 1.6 2.7 13.0 -1.6 4.4 -1.5 5.6 72 12/15/10 2.4 5.0 -0.9 3.7 -1.6 3.8 -10.5 16.0 0.3 4.0 24.1 17.0 76X 02/26/10 -0.2 5.4 -0.6 1.6 0.4 2.1 0.1 4.9 0.1 4.9 -0.1 8.8 76X 06/15/10 -0.3 5.5 1.6 1.8 -1.1 1.8 2.5 5.1 2.5 5.1 -0.5 9.2 76X 09/13/10 0.0 5.1 0.0 1.4 0.3 1.6 6.9 10.1 -1.3 3.2 -2.4 5.5 76X 12/07/10 0.0 6.6 1.6 3.3 -0.7 3.5 -1.9 16.1 1.8 5.3 -1.2 10.9 77X 02/26/10 -2.4 6.0 -1.8 1.9 0.6 2.6 -5.8 7.4 -5.8 7.4 13.0 11.0 77X 06/15/10 2.2 6.3 0.6 2.0 1.5 2.7 -0.9 7.7 -0.9 7.7 0.0 10.0 77X 09/13/10 -0.7 4.7 -0.1 1.4 0.6 1.4 -1.2 10.5 -1.6 3.4 -3.4 5.7 77X 12/07/10 -3.0 5.5 2.5 3.2 -2.2 3.3 5.7 14.8 1.2 5.3 -6.4 10.5 78X 02/26/10 -5.3 7.1 1.0 2.4 -0.7 2.9 -4.5 7.3 -4.5 7.3 13.0 14.0 78X 06/15/10 -0.2 7.6 -0.2 2.2 -2.8 2.7 -4.2 7.2 -4.2 7.2 2.0 12.0 78X 09/13/10 -0.8 5.5 -0.1 1.5 -0.5 1.4 -1.7 10.6 -2.5 3.4 2.9 5.6 78X 12/07/10 -3.9 7.3 2.7 4.3 -0.7 4.4 6.0 17.1 4.6 6.7 -9.6 13.9 79 03/10/10 4.4 6.1 -1.6 2.6 1.5 3.4 -4.0 6.2 -4.0 6.2 -18.0 12.0 79 06/21/10 -3.6 7.4 0.4 2.0 3.7 3.0 4.3 8.6 4.3 8.6 -4.0 12.0 79 09/15/10 -3.6 8.6 -1.1 1.5 0.5 1.5 7.1 14.9 -3.4 4.7 -2.2 6.0 79 12/08/10 2.7 6.1 -0.2 4.1 -1.1 3.4 2.9 15.7 4.4 4.7 4.5 11.9 80 03/16/10 -2.3 7.7 -2.4 3.7 0.4 3.5 -2.9 7.3 -2.9 7.3 3.0 13.0 80 06/21/10 0.9 8.5 2.1 2.3 0.2 2.6 3.6 7.3 3.6 7.3 -4.1 9.7 80 09/20/10 -1.0 5.7 -0.5 0.9 -0.1 0.9 7.4 9.2 -0.7 2.9 2.6 6.6 80 12/15/10 -2.7 5.4 1.1 3.8 0.0 3.5 -1.3 15.7 1.8 5.3 1.9 13.9 80 08/05/10 -5.6 7.4 -7.3 1.4 -0.9 1.4 -5.2 12.8 -0.5 3.9 0.1 5.2 80A 08/05/10 -0.9 6.0 -3.6 1.2 0.8 1.1 12.1 11.4 4.0 4.0 -5.0 7.3 3-39

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 10 WELL WATER (pCi/I)

COLLECTION LOCATION DATE 1-131 Cs-134 Cs-137 Ba-140 La-140 AcTh-228 03/16/10 3.5 7.2 -1.0 2.5 3.3 3.3 0.9 7.2 0.9 7.2 -7.0 13 06/21/10 -0.8 8.4 0.3 2.4 2.2 2.9 5.8 7.3 5.8 7.3 9.0 14 09/20/10 1.8 3.4 -0.17 0.5 -0.6 0.8 1.9 6.1 -1.4 2.1 -3.2 3.6 12/22/10 -0.6 6.0 -0.72 1.1 0.3 1.1 2.7 10.7 -2.0 3.3 1.9 7.5 03/10/10 3.5 6.2 0.2 3.4 -0.5 3.1 -0.7 5.5 -0.7 5.5 -7.0 13.0 03/26/10 -3.3 5.8 -1.7 2.2 -0.3 3.8 -0.5 7.8 -0.5 7.8 10.0 18.0 06/16/10 1.6 7.8 0.0 2.7 -0.8 3.2 2.2 8.0 2.2 8.0 -7.0 12.0 08/05/10 -13.7 8.4 2.01 3.1 0.6 1.3 -1.7 13.6 0.8 3.7 -0.6 5.1 09/15/10 1.1 6.5 -0.27 1.0 -0.2 1.0 7.9 10.1 2.2 3.7 -2.1 5.9 12/15/10 0.4 7.1 0.053 4.8 2.7 4.5 11.3 18.2 -3.1 6.3 -7.8 15.1 03/10/10 -2.4 6.4 1.6 2.5 -4.2 3.9 -0:4 6.2 -0.4 6.2 2.0 13.0 03/26/10 -6.9 7.5 -0.4 2.2 -3.2 3.5 3.0 7.6 3.0 7.6 9.0 12.0 06/16/10 1.3 7.5 0.5 2.3 -1.1 2.7 -2.7 6.4 -2.7 6.4 -1.0 10.0 09/15/10 4.4 8.3 0.324 1.4 0.6 1.3 -3.2 14.0 -2.6 4.6 1.3 9.6 12/08/10 -0.7 7.2 -0.95 4.2 -5.1 4.1 5.6 18.4 2.3 6.0 2.0 14.4 03/10/10 -4.5 4.9 -1.1 2.2 -0.2 2.8 2.4 5.1 2.4 5.1 8.0 11.0 06/16/10 -2.1 7.1 0.4 2.0 -2.6 4.0 6.5 7.2 6.5 7.2 -13.0 12.0 09/20/10 -2.3 7.6 0.693 1.2 0.7 1.2 -6.2 12.4 -3.7 4.1 2.2 5.2 12/08/10 3.4 7.8 -0.42 2.5 1.6 2.8 -6.0 16.4 3.6 4.5 -3.3 10.5 02/24/10 -1.2 7.2 -0.6 3.0 -1.7 3.7 -3.2 6.1 -3.2 6.1 -8.0 13.0 06/24/10 -1.2 8.4 1.1 3.4 -3.3 3.4 3.8 7.2 3.8 7.2 0.0 12.0 08/05/10 4.5 8.3 0.067 1.5 0.0 1.5 -0.2 13.8 -1.1 3.7 3.0 6.2 09/08/10 -1.8 5.6 1.05 2.0 -2.6 2.0 -9.0 12.3 -0.7 4.2 11.5 13.6 12/06/10 3.6 7.7 -0.72 3.4 -1.6 3.2 5.6 18.5 2.2 5.7 6.0 12.1 02/24/10 0.0 6.7 0.3 3.3 2.1 3.7 -0.8 7.0 -0.8 7.0 4.0 13.0 06/24/10 -8.1 7.4 -0.9 2.5 1.8 2.9 -3.0 6.2 -3.0 6.2 0.0 12.0 09/02/10 5.9 7.1 -0.85 1.6 -0.5 1.8 14.7 13.9 -1.7 4.6 -4.4 6.5 12/06/10 1.3 4.9 -0.27 2.6 1.4 2.5 -8.3 11.9 1.3 3.7 7.9 8.1 91 09/20/10 -2.9 5.8 -0.27 1.0 0.9 0.9 -1.1 9.9 -0.7 2.8 -0.5 5.1 12/22/10 -1.0 6.6 0.403 1.2 0.2 1.1 -3.5 11.3 0.3 3.2 3.1 6.3 92 09/21/10 -6.5 7.9 -0.04 1.4 -0.9 1.2 -12.6 13.3 -4.0 4.0 0.5 8.4 12/15/10 2.6 6.1 -3.44 4.3 -2.8 4.2 -5.5 15.3 3.1 6.2 3.6 14.8 3-40

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 11 DEER MEAT (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65

(-/-) (+0-)

93 12/09/2010 0.169 0.181 2.46 0.482 0.014 0.017 -0.013 0.021 0.011 0.047 -0.004 0.019 -0.021 0.038 0.014 -0.005 0.026 -0.008 0.014 -0.009 0.032 94 11/29/2010 -0.109 0.115 3.38 0.378 0.001 0.011 -0.007 COLLECTION LOCATION DATE Nb-95 Zr-95 Ru-103 Ru-106 Ag-110M 1-131 Cs-134

(,/-)(+- (*/-)(*/-)

93 12/09/2010 0.021 0.020 -0.019 0.034 -0.003 0.024 0.073 0.148 -0.003 0.019 0.058 0.170 -0.033 0.019 94 11/29/2010 0.019 0.014 0.006 0.022 0.007 0.014 0.084 0.115 0.001 0.014 -0.001 0.029 0.005 0.015 COLLECTION LOCATION DATE Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 Ra-226 AcTh-228 93 12/09/2010 0.194 0.042 0.187 0.233 0.008 0.068 0.022 0.036 -0.02 0.10 0.13 0.48 0.01 0.06 94 11/29/2010 0.356 0.035 0.015 0.070 0.005 0.023 -0.010 0.020 -0.04 0.07 0.28 0.30 -0.01 0.05 3-41

Millstone Station TABLE 12 Annual Radiological Environmental Operating Report 2010 FRUITS &VEGETABLES (pCi/g wet wt.)

COLLECTION LOCATION DATE TYPE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59 Co-60

(+/-) (+/-) (+/-) (+/-)

25 06/15/10 Lettuce 0.030 0.110 2.130 0.330 -0.110 0.110 -0.009 0.011 0.009 0.011 0.011 0.023 0.005 0.013 25 06/15/10 Strawberries 0.020 0.047 1.120 0.110 0.018 0.057 0.001 0.004 -0.007 0.005 0.001 0.012 0.004 0.005 25 07/13/10 Swiss Chard/Basil 0.147 0.127 5.470 0.482 0.063 0.110 -0.001 0.012 0.000 0.014 -0.008 0.031 -0.001 0.012 25 07/20/10 Bluberries 0.055 0.040 0.578 0.082 0.000 0.021 0.001 0.002 0.003 0.002 0.001 0.005 0.001 0.002 25 08/18/10 Kale 0.113 0.110 5.420 0.446 -0.004 0.112 -0.007 0.011 -0.004 0.012 -0.010 0.029 -0.109 0.012 25 09/08/10 Collard Greens 0.095 0.064 4.080 0.308 -0.036 0.078 0.001 0.006 -0.001 0.007 -0.015 0.014 -0.001 0.006 25 09/09/10 Apples 0.029 0.059 1.110 0.176 0.013 0.073 0.001 0.006 -0.003 0.006 -0.002 0.015 0.007 0.006 26C 06/23/10 Lettuce 0.080 0.150 2.440 0.530 0.110 0.130 0.004 0.015 -0.002 0.018 0.019 0.038 0.006 0.016 26C 06/23/10 Cherries -0.070 0.110 1.430 0.330 -0.110 0.120 -0.004 0.012 0.007 0.013 0.005 0.028 0.001 0.013 26C 07/24/10 Blueberries 0.051 0.030 0.621 0.081 -0.025 0.039 -0.001 0.003 0.002 0.003 -0.002 0.006 -0.001 0.002 26C 08/18/10 Lettuce 0.085 0.108 3.990 0.313 -0.034 0.122 0.007 0.011 0.001 0.011 0.009 0.024 -0.007 0.009 COLLECTION LOCATION DATE TYPE Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125 1-131 25 06/15/10 Lettuce -0.032 0.030 -0.007 0.015 0.005 0.021 0.003 0.012 0.028 0.084 0.008 0.029 0.019 0.034 25 06/15/10 Strawberries -0.003 0.010 0.004 0.006 0.010 0.009 0.001 0.006 -0.032 0.040 -0.013 0.012 0.009 0.028 25 07/13/10 Swiss Chard/Basil -0.012 0.035 0.002 0.012 0.004 0.021 -0.003 0.013 -0.106 0.110 0.020 0.033 0.009 0.022 25 07/20/10 Bluberries -0.001 0.005 -0.001 0.003 0.002 0.004 -0.001 0.002 0.009 0.021 0.000 0.006 0.000 0.004 25 08/18/10 Kale -0.034 0.027 0.006 0.010 0.006 0.019 0.002 0.013 -0.075 0.094 0.016 0.029 0.015 0.031 25 09/08/10 Collard Greens -0.006 0.014 -0.004 0.006 0.001 0.011 0.009 0.007 0.028 0.051 -0.009 0.016 0.002 0.034 25 09/09/10 Apples -0.026 0.013 0.002 0.007 -0.003 0.012 -0.001 0.007 0.012 0.052 -0.014 0.016 -0.004 0.031 26C 06/23/10 Lettuce -0.024 0.046 -0.011 0.015 -0.004 0.024 -0.009 0.015 0.100 0.150 0.009 0.042 0.000 0.025 26C 06/23/10 Cherries 0.004 0.027 0.004 0.016 -0.015 0.025 0.000 0.014 -0.080 0.130 0.024 0.034 0.011 0.019 26C 07/24/10 Blueberries -0.009 0.006 -0.001 0.003 0.001 0.005 -0.003 0.004 -0.004 0.025 -0.005 0.008 0.000 0.020 26C 08/18/10 Lettuce 0.018 0.024 0.002 0.011 -0.005 0.019 0.007 0.013 0.055 0.104 0.028 0.029 -0.003 0.037 3-42

I# It : 15 'In4n IvllilStone Station TABLE 12 PnIuII i'auioUIUyludI -IIVIIUnIIIIwIpILdI JI*JadLy n,**.IJ~ Lu u FRUITS & VEGETABLES (pCi/g wet wt.)

COLLECTION LOCATION DATE TYPE Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 AcTh-228

(+1-) (+1-) (+1-) (+/-) (+/-) (+/-) (+/-)

25 06/15/10 Lettuce 0.002 0.008 0.005 0.012 -0.014 0.028 -0.014 0.028 -0.005 0.015 0.037 0.051 -0.015 0.043 25 06/15/10 Strawberries 0.002 0.004 0.001 0.004 0.003 0.018 0.003 0.018 0.000 0.007 -0.008 0.021 0.002 0.023 25 07/13/10 Swiss Chard/Basil -0.002 0.015 -0.008 0.013 -0.007 0.066 -0.012 0.019 0.009 0.020 0.014 0.081 0.018 0.054 25 07/20/10 Bluberries 0.001 0.002 0.001 0.002 0.004 0.012 0.001 0.004 -0.002 0.004 -0.001 0.015 -0.003 0.010 25 08/18/10 Kale 0.007 0.011 -0.037 0.012 -0.017 0.065 -0.008 0.014 0.008 0.019 -0.014 0.064 -0.007 0.042 25 09/08/10 Collard Greens 0.002 0.005 0.006 0.006 -0.006 0.059 0.002 0.016 0.002 0.015 0.019 0.045 0.019 0.027 25 09/09/10 Apples 0.001 0.006 -0.002 0.006 -0.035 0.056 -0.002 0.015 -0.006 0.012 -0.014 0.037 0.007 0.034 26C 06/23/10 Lettuce -0.003 0.013 -0.009 0.018 0.008 0.029 0.008 0.029 -0.023 0.020 -0.019 0.064 0.010 0.069 26C 06/23/10 Cherries -0.012 0.009 0.001 0.013 -0.002 0.019 -0.002 0.019 -0.013 0.018 -0.041 0.066 0.017 0.051 26C 07/24/10 Blueberries -0.001 0.003 0.002 0.003 -0.011 0.032 0.000 0.007 -0.004 0.007 -0.016 0.021 -0.004 0.012 26C 08/18/10 Lettuce 0.009 0.013 0.007 0.011 -0.002 0.073 0.006 0.019 0.007 0.024 -0.078 0.082 0.003 0.039 3-43

Millstone Station Millton StaionAnnual Radiological Environmental Operating Report, 2010 TABLE 13 BROADLEAF VEGETATION (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59 Co-60 1 04/21/10 0.91 0.27 4.59 0.67 -0.01 0.18 -0.007 0.019 -0.006 0.019 0.018 0.042 -0.004 0.020 1 05/24/10 0.46 0.22 3.56 0.74 0.14 0.19 0.010 0.021 0.003 0.024 -0.009 0.061 0.003 0.030 1 06/08/10 0.44 0.14 3.86 0.32 -0.01 0.12 0.000 0.010 0.006 0.011 0.001 0.027 -0.005 0.011 1 07/13/10 0.83 0.16 3.17 0.35 -0.06 0.09 0.002 0.009 0.000 0.009 0.001 0.020 0.010 0.009 1 08/11/10 1.05 0.16 3.43 0.26 0.01 0.08 0.003 0.006 -0.006 0.007 0.001 0.015 -0.002 0.007 1 09/14/10 1.83 0.12 3.59 0.18 0.00 0.05 0.004 0.004 0.001 0.004 -0.003 0.010 0.001 0.004 1 10/14/10 1.59 0.18 3.02 0.29 0.07 0.10 0.004 0.007 -0.001 0.009 -0.011 0.019 0.008 0.008 10 04/21/10 0.10 0.12 4.97 0.82 -0.06 0.14 -0.013 0.018 0.000 0.020 -0.016 0.044 0.006 0.022 10 05/24/10 0.47 0.41 4.40 1.10 -0.19 0.24 0.006 0.036 -0.018 0.026 -0.020 0.056 0.018 0.033 10 06/08/10 0.14 0.34 4.28 0.82 0.04 0.29 -0.007 0.027 0.022 0.029 0.037 0.073 0.009 0.018 10 07/13/10 0.55 0.15 3.94 0.30 0.04 0.12 0.012 0.011 -0.003 0.012 -0.019 0.023 0.002 0.011 10 08/11/10 0.53 0.10 3.91 0.20 0.04 0.07 0.002 0.006 -0.003 0.007 0.008 0.016 -0.156 0.010 10 09/14/10 1.24 0.12 4.10 0.18 -0.02 0.07 0.002 0.005 0.000 0.006 0.005 0.013 0.001 0.006 10 10/14/10 1.15 0.14 3.88 0.27 0.01 0.09 -0.005 0.008 -0.002 0.008 -0.001 0.019 0.003 0.009 17 04/21/10 0.69 0.29 3.90 0.73 -0.01 0.17 0.006 0.018 0.002 0.020 0.026 0.050 -0.006 0.020 17 05/24/10 0.57 0.25 3.40 0.55 -0.16 0.19 -0.005 0.018 -0.021 0.020 0.004 0.042 0.005 0.024 17 06/08/10 0.44 0.19 3.86 0.43 0.01 0.15 0.005 0.015 0.001 0.016 0.034 0.039 -0.003 0.018 17 07/13/10 0.95 0.16 3.39 0.29 0.02 0.07 .0.000 0.007 -0.002 0.007 -0.0001 0.015 -0.001 0.006 17 08/11/10 0.76 0.10 3.49 0.19 0.02 0.07 -0.003 0.005 -0.003 0.006 0.003 0.014 0.001 0.005 17 09/14/10 2.55 0.15 4.49 0.20 0.06 0.07 0.000 0.005 -0.004 0.005 -0.003 0.012 0.002 0.005 17 10/14/10 1.44 0.17 2.55 0.27 -0.05 0.10 0.003 0.009 0.001 0.009 0.002 0.021 -0.001 0.009 3-44

Millstone Station Annual Radiological Environmental Operating Report, 2010 TABLE 13 BROADLEAF VEGETATION (pCi/g wet wt.)

COLLECTION LOCATION DATE Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125 1-131

(/- (/) (-) -)(A-) (A-) (A-)

1 04/21/10 -0.013 0.049 0.027 0.025 -0.003 0.033 -0.018 0.022 -0.09 0.16 -0.018 0.050 -0.005 0.002 1 05/24/10 -0.011 0.069 -0.012 0.028 -0.024 0.039 0.000 0.023 -0.01 0.19 0.034 0.052 0.027 0.031 1 06/08/10 -0.002 0.024 -0.001 0.016 0.018 0.022 -0.004 0.014 0.03 0.094 -0.008 0.028 0.001 0.023 1 07/13/10 -0.015 0.020 0.003 0.010 -0.005 0.017 -0.001 0.009 0.00 0.09 -0.016 0.025 0.000 0.025 1 08/11/10 -0.001 0.013 -0.003 0.007 0.001 0.012 -0.001 0.008 0.01 0.06 -0.011 0.017 -0.015 0.031 1 09/14/10 0.006 0.009 -0.005 0.004 0.002 0.008 0.003 0.004 0.00 0.03 0.003 0.010 -0.007 0.026 1 10/14/10 0.004 0.017 0.014 0.009 -0.004 0.015 0.002 0.010 0.00 0.07 0.002 0.021 -0.038 0.037 10 04/21/10 0.000 0.061 0.021 0.024 0.006 0.033 0.003 0.018 -0.15 0.18 0.010 0.047 -0.003 0.001 10 05/24/10 -0.036 0.092 -0.001 0.041 0.003 0.059 0.016 0.026 -0.09 0.31 0.012 0.074 -0.004 0.001 10 06/08/10 -0.010 0.064 0.004 0.043 0.000 0.059 0.004 0.033 -0.01 0.24 -0.002 0.063 -0.006 0.015 10 07/13/10 0.024 0.026 -0.009 0.012 0.013 0.020 0.002 0.013 0.01 0.11 -0.011 0.033 -0.001 0.025 10 08/11/10 0.000 0.015 -0.002 0.007 -0.004 0.012 0.008 0.008 -0.03 0.05 0.004 0.017 -0.018 0.026 10 09/14/10 0.003 0.012 0.005 0.006 0.002 0.010 0.000 0.006 -0.01 0.04 -0.009 0.013 -0.004 0.032 10 10/14/10 0.002 0.019 0.006 0.010 0.005 0.015 -0.001 0.010 0.02 0.07 -0.003 0.019 0.017 0.036 17 04/21/10 -0.015 0.046 0.009 0.025 0.002 0.032 -0.005 0.019 -0.17 0.20 -0.010 0.043 -0.003 0.001 17 05/24/10 -0.055 0.048 -0.008 0.029 -0.002 0.043 -0.001 0.021 -0.04 0.17 0.024 0.046 -0.004 0.002 17 06/08/10 -0.008 0.035 0.001 0.022 -0.001 0.029 0.015 0.017 -0.05 0.13 0.001 0.034 -0.006 0.015 17 07/13/10 -0.010 0.017 -0.003 0.008 -0.001 0.013 -0.002 0.008 -0.005 0.07 -0.009 0.020 0.017 0.025 17 08/11/10 -0.006 0.014 0.002 0.007 -0.007 0.011 0.000 0.007 -0.03 0.05 -0.002 0.015 0.000 0.032 17 09/14/10 -0.005 0.012 0.000 0.006 0.005 0.010 -0.007 0.007 0.04 0.04 -0.005 0.014 0.006 0.035 17 10/14/10 0.009 0.022 0.011 0.011 0.010 0.018 0.004 0.011 0.00 0.08 0.000 0.024 -0.019 0.038 3-45

Millstone Station Annual Radiological Environmental Operating Report, 2010 TABLE 13 BROADLEAF VEGETATION (pCi/g wet wt.)

COLLECTION LOCATION DATE Cs-1 34 Cs-1 37 Ba-140 La-140 Ce-141 Ce-144 AcTH-228

(/-) (/-) (/-) (/-) (/-) (/-)

(/-)

04/21/10 -0.008 0.014 0.007 0.017 0.001 0.043 0.001 0.043 -0.004 0.025 -0.048 0.077 0.060 0.081 1 05/24/10 -0.006 0.021 0.014 0.025 -0.006 0.067 -0.006 0.067 0.009 0.027 0.033 0.083 0.070 0.100 1 06/08/10 -0.002 0.010 0.009 0.013 -0.003 0.038 -0.003 0.038 -0.009 0.018 0.026 0.048 0.041 0.056 1 07/13/10 -0.013 0.010 -0.003 0.010 0.024 0.046 0.002 0.013 -0.004 0.015 -0.013 0.058 0.172 0.050 1 08/11/10 -0.001 0.006 -0.004 0.008 0.016 0.063 -0.001 0.015 -0.015 0.017 -0.038 0.050 0.084 0.056 1 09/14/10 0.002 0.004 0.002 0.004 0.012 0.038 -0.001 0.011 -0.009 0.008 0.010 0.023 0.037 0.041 1 10/14/10 0.005 0.009 0.020 0.012 -0.020 0.068 -0.005 0.020 0.004 0.018 -0.022 0.061 0.020 0.031 10 04/21/10 0.005 0.014 0.016 0.022 -0.004 0.048 -0.004 0.048 0.000 0.021 -0.065 0.069 0.068 0.085 10 05/24/10 -0.005 0.019 -0.012 0.029 -0.032 0.078 -0.032 0.078 -0.027 0.037 -0.007 0.096 0.000 0.130 10 06/08/10 -0.009 0.017 0.016 0.023 0.030 0.140 0.030 0.140 0.009 0.043 -0.040 0.100 0.080 0.100 10 07/13/10 0.004 0.012 0.015 0.013 -0.051 0.058 0.015 0.016 0.019 0.024 -0.058 0.095 0.083 0.055 10 10 08/11/10 -0.001 0.006 -0.048 0.009 -0.010 0.058 -0.015 0.016 0.001 0.013 -0.006 0.038 0.024 0.038 10 09/14/10 0.002 0.005 0.005 0.005 0.054 0.054 0.000 0.014 0.007 0.011 -0.0002 0.032 0.051 0.042 10/14/10 -0.005 0.009 0.008 0.009 0.054 0.066 -0.008 0.017 0.010 0.016 0.029 0.051 0.104 0.046 17 04/21/10 -0.011 0.014 -0.006 0.024 -0.064 0.043 -0.064 0.043 0.011 0.022 -0.038 0.068 -0.051 0.086 17 05/24/10 -0.013 0.017 0.000 0.019 0.001 0.046 0.001 0.046 -0.028 0.029 0.036 0.084 0.036 0.078 17 17 06/08/10 0.003 0.011 0.018 0.017 0.032 0.061 0.032 0.061 0.001 0.024 0.007 0.049 0.163 0.075 17 07/13/10 0.000 0.009 0.004 0.008 -0.026 0.038 -0.007 0.009 0.004 0.014 0.036 0.055 0.100 0.066 17 08/11/10 0.003 0.006 0.026 0.010 -0.015 0.052 -0.006 0.015 0.005 0.013 0.001 0.034 0.003 0.041 17 09/14/10 0.002 0.005 0.053 0.010 0.011 0.056 -0.026 0.016 -0.004 0.012 -0.001 0.033 0.090 0.047 10/14/10 -0.003 0.010 0.027 0.014 -0.038 0.075 0.006 0.022 0.017 0.017 -0.005 0.054 0.080 0.071 3-46

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 14 SEA WATER (pCi/I)

COLLECTION LOCATION DATE H-3 Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+1-) (+/-) (+1-) (+1-) (+/-) (+1-) (+1-)

32 G 01/26/10 300 160 2 36 269 80 -41 35 0.0 3.4 -4.8 4.0 -0.1 7.6 G 02/23/10 1070 170 10 25 316 58 -12 28 0.2 2.9 0.6 2.6 -2.4 5.5 03/30/10 330 160 4 25 288 68 -19 27 -3.7 2.8 0.1 3.0 -4.4 7.1 04/27/10 410 160 -10 34 309 79 -9 35 0.0 3.9 0.6 3.4 2.2 7.6 05/25/10 230 160 5 17 278 41 0 18 -0.7 1.9 0.1 2.1 -1.4 4.1 06/29/10 40 150 6 20 256 59 -1 21 1.8 2.5 -1.2 2.4 2.4 6.5 07/29/10 159 181 -6 9 327 40 -10 13 0.4 0.7 -0.1 0.8 -2.1 2.0 08/31/10 59 179 11 11 273 32 1 15 -0.3 1.0 0.7 1.1 0.2 2.7 09/28/10 260 205 -4 25 251 71 17 28 -1.0 2.7 -0.2 2.7 1.9 5.7 10/26/10 664 170 -15 22 266 55 18 25 0.6 2.7 1.4 2.4 3.9 5.4 11/30/10 944 184 -4 23 306 71 -8 25 -2.0 2.4 0.8 2.4 -4.0 5.3 12/28/10 773 169 -13 19 314 53 6 22 -0.9 1.8 -0.3 2.0 -1.6 4.3 37C 02/23/10 10 150 8 22 243 77 14 24 -1.5 2.9 0.2 3.1 8.8 7.6 06/01/10 -20 150 21 27 291 60 11 30 -1.6 2.9 0.9 2.7 -3.6 6.2 08/31/10 -47 101 4 4 283 27 3 4 0.1 0.4 0.2 0.4 -0.2 0.8 11/30/10 78 140 6 14 321 82 5 18 -0.7 1.4 1.4 1.7 0.6 3.5 3-47

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 14 SEA WATER (pCi/I)

COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125

(+1-) (+/-) (+1-) (+1-) (+/-) (+1-) (+1-)

32 12/29/09 2.7 4.4 -6.0 10.0 4.1 4.5 2.3 8.1 -2.3 4.7 2 42 0.0 10.0 01/26/10 0.0 4.7 13.0 17.0 -2.8 4.7 -6.5 6.8 -2.7 4.3 -3 32 0.3 9.5 02/23/10 -0.6 3.1 -1.5 5.5 0.3 2.9 -0.2 4.4 -1.6 3.2 13 24 -0.3 7.5 03/30/10 -0.5 3.7 -6.5 6.8 0.9 3.4 0.3 6.1 -0.9 3.2 -2 25 -3.1 7.0 04/27/10 -1.7 3.9 -2.8 7.2 -1.0 4.1 -1.8 6.4 -3.5 4.5 -13 39 -1.0 9.0 05/25/10 0.9 1.9 -2.4 4.0 -0.7 2.4 -2.4 3.6 -0.6 2.3 -5 16 1.4 4.9 06/29/10 0.2 3.0 -6.5 6.9 -0.5 2.9 1.1 4.4 -2.7 2.7 -18 26 -1.2 6.4 06/29/10 0.0 0.7 1.0 1.5 0.4 0.9 0.3 1.6 0.4 1.2 0 6 2.0 2.2 08/03/10 -0.4 1.0 0.0 2.4 0.7 1.2 1.9 2.0 -0.6 1.4 0 9 -2.7 2.9 09/07/10 0.6 2.9 -3.9 6.5 0.1 2.7 -0.1 4.9 -2.4 3.0 7 23 1.3 7.5 09/28/10 1.5 2.5 -7.9 5.5 2.4 2.8 4.8 4.9 -1.2 2.8 10 23 -1.8 7.1 10/26/10 -0.6 2.8 1.2 6.2 2.2 2.6 0.5 4.4 -1.6 2.9 4 24 0.6 7.5 11/30/10 0.7 1.9 -1.3 4.9 2.8 2.3 0.0 3.4 -1.4 2.4 -8 17 3.2 5.5 37C 02/23/10 1.5 3.7 0.9 7.7 -0.2 3.2 2.9 5.6 -2.4 3.2 -38 29 2.0 7.2 06/01/10 -0.1 2.8 -0.6 5.8 2.2 3.5 -1.3 4.8 -3.6 3.7 -11 29 4.1 7.4 08/31/10 0.3 0.4 -0.1 0.7 0.1 0.4 0.0 0.6 -0.1 0.4 -1 3 -0.3 1.0 11/30/10 -1.5 1.6 2.0 2.7 0.2 2.0 0.8 2.9 -0.8 1.9 -3 15 1.5 5.5 3-48

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 14 SEA WATER (pCi/I)

COLLECTION LOCATION DATE 1-131 Cs-134 Cs-137 Ba-140 La-140 AcTh-228

.. ... (+/-) (,/-) (+.-) (./-) (+.-)

32 01/26/10 -0.3 6.9 2.3 2.7 -2.9 3.5 -0.8 6.5 -0.8 6.5 7.0 15.0 02/23/10 1.0 6.1 -0.3 2.0 1.3 2.9 2.4 4.8 2.4 4.8 -8.0 10.0 03/30/10 0.3 7.0 -0.6 2.3 -1.3 3.9 2.2 8.2 2.2 8.2 13.0 14.0 04/27/10 0.0 7.0 0.7 2.9 -2.4 3.8 2.9 6.7 2.9 6.7 -6.0 15.0 05/25/10 0.3 5.5 1.1 1.6 0.5 1.7 0.0 4.5 0.0 4.5 0.2 8.5 06/29/10 -4.6 5.9 1.0 2.2 -0.4 2.6 -2.9 7.8 -2.9 7.8 5.0 11.0 06/29/10 -2.1 9.1 0.0 0.7 0.0 0.7 2.6 11.1 1.3 3.9 1.2 8.7 08/03/10 -1.6 8.3 -0.5 1.0 -0.8 1.0 -6.6 12.2 -2.7 4.0 2.2 7.5 09/07/10 1.3 5.7 -1.4 2.6 -1.4 3.1 4.4 13.7 -2.8 4.6 -8.7 10.7 09/28/10 6.0 5.1 -2.0 3.0 -1.5 2.6 6.5 14.6 -0.1 4.3 -1.5 10.4 10/26/10 -0.5 4.9 -0.2 2.9 0.6 2.9 -6.2 13.1 2.4 3.2 -8.4 9.3 11/30/10 -2.3 6.3 0.7 2.2 -2.2 1.9 -6.9 13.7 0.9 4.0 6.5 8.5 37C 02/23/10 4.8 6.3 -0.2 2.3 -3.2 3.1 5.1 6.6 5.1 6.6 0.0 13.0 06/01/10 8.3 7.9 -2.0 2.0 0.1 3.1 -1.7 6.0 -1.7 6.0 3.0 11.0 08/31/10 0.3 1.3 -0.3 0.3 0.0 0.4 -0.8 2.8 -0.7 0.9 -8.3 3.4 11/30/10 1.1 3.6 0.4 1.9 1.0 2.1 -0.3 8.9 -0.5 1.7 8.3 10.2 3-49

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 15 BOTTOM SEDIMENT (pCi/g dry wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59 29 04/30/10 -0.20 0.73 18.70 3.20 -0.10 0.73 0.072 0.083 0.036 0.066 0.180 0.180 29 11/30/10 0.04 0.25 14.00 1.14 0.17 0.27 0.029 0.026 0.015 0.028 -0.005 0.063 31 04/19/10 -0.03 0.41 17.10 2.20 0.12 0.52 0.005 0.043 0.011 0.042 0.010 0.130 31 11/03/10 0.05 0.15 17.30 0.81 -0.04 0.15 0.003 0.020 -0.002 0.018 -0.016 0.041 32 04/30/10 -0.20 0.62 13.90 2.00 -0.18 0.67 -0.005 0.055 0.024 0.058 0.040 0.140 32 12/10/10 0.19 0.35 15.90 1.30 -0.40 0.46 -0.003 0.038 -0.027 0.041 -0.086 0.097 33 04/19/10 0.30 0.44 17.10 2.90 0.09 0.44 0.025 0.060 0.013 0.047 -0.110 0.140 33 10/04/10 0.12 0.23 15.10 1.20 -0.08 0.24 0.008 0.026 -0.010 0.027 0.021 0.065 34 04/19/10 0.25 0.36 13.10 2.50 -0.38 0.52 0.029 0.049 -0.019 0.064 0.020 0.140 34 10/04/10 -0.02 0.20 14.00 1.16 0.01 0.23 -0.020 0.024 -0.017 0.025 -0.014 0.064 35X 04/30/10 0.06 0.57 14.70 2.60 0.30 0.77 -0.011 0.069 -0.022 0.073 0.040 0.140 35X 11/30/10 -0.08 0.27 13.50 1.10 -0.07 0.28 0.025 0.030 -0.015 0.031 0.016 0.065 37C 04/19/10 0.18 0.42 17.30 2.20 -0.41 0.47 0.005 0.034 -0.006 0.050 -0.080 0.120 37C 09/15/10 0.13 0.20 14.00 1.15 -0.18 0.21 -0.010 0.023 -0.004 0.026 0.025 0.052 39X 04/30/10 -0.17 0.63 15.40 2.10 -0.22 0.71 0.025 0.051 -0.006 0.061 -0.020 0.130 39X 12/10/10 -0.02 0.20 12.00 0.94 -0.10 0.26 0.020 0.023 0.010 0.024 0.056 0.060 67X 04/19/10 0.00 0.43 18.80 2.20 -0.36 0.47 0.049 0.054 -0.022 0.044 -0.100 0.130 67X 12/15/10 0.02 0.36 31.60 1.84 0.34 0.48 0.014 0.043 -0.016 0.045 0.036 0.124 69X 04/19/10 -0.25 0.41 16.40 2.20 -0.04 0.55 0.021 0.045 -0.006 0.054 -0.072 0.090 69X 11/15/10 0.04 0.24 14.40 1.11 0.16 0.28 0.031 0.026 0.004 0.027 0.042 0.069 3-50

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 15 BOTTOM SEDIMENT (pCi/g dry wt.)

COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106

(+/-) (0/-) (+1-) (/1-) (+.-)

29 04/30/10 -0.090 0.099 0.000 0.200 0.020 0.110 -0.050 0.130 0.108 0.088 0.07 0.58 29 11/30/10 0.015 0.031 -0.047 0.075 0.056 0.033 0.060 0.051 0.027 0.031 0.17 0.23 31 04/19/10 -0.052 0.059 0.000 0.100 -0.006 0.049 0.000 0.078 0.014 0.050 0.25 0.38 31 11/03/10 -0.008 0.021 -0.100 0.047 0.004 0.018 0.025 0.033 -0.013 0.017 -0.02 0.15 32 04/30/10 -0.013 0.063 -0.010 0.260 -0.041 0.094 -0.030 0.120 -0.026 0.080 0.03 0.40 32 12/10/10 0.004 0.040 -0.105 0.098 0.001 0.050 0.004 0.079 -0.047 0.048 0.00 0.31 33 04/19/10 -0.083 0.071 0.020 0.190 -0.052 0.060 0.080 0.130 0.024 0.052 0.22 0.48 33 10/04/10 0.007 0.034 -0.101 0.075 0.009 0.026 -0.032 0.050 0.013 0.026 0.01 0.21 34 04/19/10 -0.018 0.064 0.040 0.150 -0.023 0.066 -0.040 0.100 0.050 0.062 -0.22 0.52 34 10/04/10 -0.012 0.035 -0.022 0.078 0.003 0.025 0.007 0.046 0.007 0.026 0.02 0.23 35X 04/30/10 0.003 0.050 -0.040 0.200 0.063 0.094 0.160 0.120 0.055 0.075 0.44 0.55 35X 11/30/10 0.029 0.032 0.028 0.077 0.053 0.038 -0.017 0.054 0.009 0.032 0.07 0.26 37C 04/19/10 0.020 0.056 -0.014 0.093 -0.075 0.065 -0.020 0.100 0.004 0.063 -0.16 0.28 37C 09/15/10 0.038 0.033 -0.069 0.065 0.025 0.025 -0.012 0.044 -0.011 0.024 0.06 0.22 39X 04/30/10 0.000 0.050 -0.140 0.260 -0.046 0.075 0.080 0.100 -0.031 0.065 0.02 0.48 39X 12/10/10 0.000 0.028 -0.027 0.062 0.000 0.027 0.032 0.043 -0.006 0.026 0.09 0.16 67X 04/19/10 0.006 0.034 -0.220 0.130 0.019 0.058 0.000 0.077 -0.002 0.046 0.02 0.35 67X 12/15/10 0.019 0.050 -0.143 0.110 0.033 0.049 0.023 0.084 0.033 0.049 -0.22 0.37 69X 04/19/10 0.007 0.050 -0.040 0.100 -0.006 0.060 0.072 0.075 -0.003 0.051 0.04 0.46 69X 11/15/10 -0.018 0.033 -0.106 0.071 0.013 0.030 0.072 0.050 -0.014 0.028 0.08 0.23 3-51

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 15 BOTTOM SEDIMENT (pCi/g dry wt.)

COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-134 Cs- 137 AcTh-228

(+/-) (+1-) (+--) (+.-) (00-)

29 04/30/10 0.053 0.099 0.050 0.170 -0.060 0.260 0.008 0.047 0.045 0.093 0.560 0.300 29 11/30/10 -0.013 0.029 0.029 0.071 -0.055 0.059 0.001 0.029 0.033 0.029 0.970 0.258 31 04/19/10 0.007 0.056 0.010 0.120 -0.050 0.170 0.009 0.036 -0.002 0.042 0.290 0.250 31 11/03/10 -0.012 0.017 -0.008 0.045 0.010 0.031 0.003 0.017 0.007 0.018 0.025 0.158 32 04/30/10 -0.015 0.076 -0.010 0.190 -0.180 0.230 0.035 0.042 0.011 0.054 0.830 0.270 32 12/10/10 -0.056 0.036 -0.077 0.088 -0.042 0.293 0.001 0.037 0.009 0.039 1.090 0.307 33 04/19/10 -0.012 0.054 -0.080 0.120 0.000 0.190 -0.006 0.040 -0.006 0.053 0.040 0.250 33 10/04/10 -0.011 0.023 0.012 0.064 0.041 0.056 -0.011 0.029 -0.004 0.026 0.200 0.184 34 04/19/10 0.000 0.070 -0.050 0.140 0.020 0.210 -0.001 0.039 -0.067 0.056 0.100 0.270 34 10/04/10 0.004 0.023 -0.016 0.066 0.000 0.051 0.007 0.027 0.000 0.025 0.108 0.113 35X 04/30/10 0.045 0.090 0.100 0.160 0.160 0.360 0.030 0.051 0.073 0.069 -0.710 0.540 35X 11/30/10 -0.011 0.029 0.041 0.082 0.015 0.062 -0.013 0.031 0.004 0.034 1.020 0.214 37C 04/19/10 0.037 0.044 0.040 0.120 0.090 0.180 0.005 0.040 -0.004 0.039 0.220 0.220 37C 09/15/10 -0.002 0.021 0.068 0.063 0.009 0.043 0.005 0.024 0.024 0.023 0.182 0.150 39X 04/30/10 -0.015 0.069 -0.020 0.180 0.040 0.300 0.101 0.069 0.019 0.056 1.070 0.270 39X 12/10/10 -0.015 0.020 -0.001 0.047 -0.062 0.177 0.001 0.022 0.015 0.023 0.050 0.181 67X 04/19/10 -0.043 0.057 0.030 0.110 -0.060 0.150 0.016 0.037 -0.003 0.040 0.200 0.180 67X 12/15/10 -0.043 0.040 0.051 0.096 -0.031 0.228 0.023 0.038 0.042 0.042 1.140 0.296 69X 04/19/10 0.008 0.063 -0.070 0.120 0.050 0.160 0.014 0.044 -0.032 0.042 0.500 0.430 69X 11/15/10 -0.023 0.026 0.028 0.070 0.010 0.091 -0.015 0.030 -0.001 0.027 0.072 0.211 3-52

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 16 AQUATIC FLORA - FUCUS (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+1-) (+/-)

29 02/22/10 0.070 0.280 4.12 0.90 0.330 0.270 0.018 0.025 -0.016 0.028 0.042 0.073 29 04/21/10 0.270 0.250 5.47 0.97 0.190 0.200 0.010 0.029 0.014 0.026 0.000 0.057 29 08/31/10 0.097 0.042 6.31 0.13 0.023 0.035 -0.001 0.003 0.001 0.003 0.004 0.008 29 11/29/10 0.167 0.125 7.46 0.55 -0.087 0.111 0.001 0.012 -0.007 0.013 -0.006 0.029 32X 02/23/10 0.380 0.260 5.60 1.00 0.250 0.250 0.014 0.032 0.009 0.028 -0.021 0.059 32X 04/20/10 0.160 0.190 7.06 0.79 -0.110 0.180 -0.015 0.023 -0.013 0.020 -0.005 0.053 32X 08/30/10 0.072 0.038 7.98 0.16 0.024 0.029 0.001 0.002 0.001 0.003 0.005 0.007 32X 11/15/10 0.044 0.094 8.51 0.54 0.033 0.099 0.008 0.012 0.002 0.011 0.018 0.035 33X 03/01/10 0.140 0.210 7.10 1.10 0.070 0.190 -0.013 0.027 -0.007 0.028 -0.026 0.075 33X 04/19/10 0.041 0.087 5.60 0.32 0.000 0.086 -0.008 0.009 0.002 0.010 -0.014 0.023 33X 08/18/10 0.060 0.111 6.02 0.44 -0.055 0.109 0.003 0.013 -0.010 0.014 0.003 0.034 33X 11/15/10 0.161 0.097 6.32 0.43 -0.012 0.104 0.003 0.010 0.001 0.011 0.005 0.026 71~

35X 02/22/10 0.060 0.220 5.26 0.96 -0.050 0.200 -0.013 0.028 -0.008 0.026 -0.018 0.066 35X 04/20/10 0.090 0.210 6.49 0.80 0.090 0.190 0.004 0.025 -0.003 0.024 0.046 0.044 35X 08/31/10 0.060 0.034 7.45 0.14 0.014 0.031 0,001 0.003 0.003 0.003 -0.001 0.008 35X 12/10/10 0.104 0.065 6.92 0.26 -0.054 0.064 -0.001 0.005 0.001 0.006 0.001 0.015 36X 02/22/10 -0.090 0.230 5.30 0.96 0.050 0.200 -0.011 0.031 -0.004 0.026 -0.060 0.081 36X 04/21/10 0.240 0.160 5.84 0.76 0.030 0.190 0.014 0.023 0.005 0.023 0.007 0.052 36X 08/31/10 0.081 0.040 5.87 0.14 0.018 0.036 0.001 0.003 0.004 0.003 0.009 0.008 36X 11/30/10 0.040 0.075 6.54 0.40 0.044 0.071 -0.009 0.008 0.001 0.009 -0.007 0.023 90C 03/01/10 0.170 0.270 5.80 1.00 -0.010 0.240 -0.024 0.033 0.010 0.029 0.007 0.074 90C 04/19/10 0.080 0.240 6.20 1.10 -0.030 0.210 0.010 0.026 0.002 0.025 0.038 0.068 90C 08/18/10 0.078 0.025 7.11 0.13 0.012 0.025 -0.002 0.002 0.000 0.003 -0.007 0.007 90C 11/15/10 0.112 0.081 7.63 0.43 -0.002 0.087 0.003 0.009 -0.004 0.010 0.009 0.024 3-53

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 16 AQUATIC FLORA - FUCUS (pCi/g wet wt.)

COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru- 106

(+/-) (+/-) (+.-)

29 02/22/10 0.004 0.033 -0.055 0.070 0.000 0.036 0.079 0.054 0.004 0.032 -0.200 0.270 0.011 0.029 0.004 0.027 -0.040 0.300 29 04/21/10 -0.001 0.027 0.025 0.069 0.034 0.057 29 08/31/10 0.002 0.003 -0.004 0.007 0.001 0.003 0.000 0.006 -0.003 0.003 0.014 0.023 29 11/29/10 -0.012 0.016 0.012 0.030 -0.003 0.015 -0.007 0.023 -0.004 0.013 0.033 0.102 32X 02/23/10 -0.008 0.031 0.040 0.071 0.003 0.037 -0.010 0.054 -0.015 0.032 0.090 0.260 32X 04/20/10 0.017 0.026 0.017 0.057 -0.007 0.024 -0.002 0.036 0.015 0.024 -0.010 0.160 32X 08/30/10 0.000 0.003 0.003 0.006 0.000 0.003 0.003 0.005 -0.001 0.003 -0.008 0.019 32X 11/15/10 -0.002 0.016 0.000 0.031 0.010 0.012 0.011 0.021 0.007 0.012 0.003 0.097 33X 03/01/10 -0.008 0.037 0.049 0.078 -0.024 0.030 -0.004 0.044 -0.006 0.024 -0.100 0.300 33X 04/19/10 -0.002 0.010 -0.027 0.024 0.006 0.011 0.008 0.018 -0.009 0.011 0.033 0.081 33X 08/18/10 -0.008 0.018 0.030 0.035 -0.003 0.014 0.014 0.026 0.005 0.013 0.037 0.106 33X 11/15/10 -0.002 0.014 -0.032 0.027 -0.001 0.011 0.002 0.019 0.000 0.012 -0.036 0.087 35X 02/22/10 -0.027 0.036 0.012 0.070 0.013 0.027 0.012 0.044 -0.006 0.029 -0.140 0.250 35X 04/20/10 -0.013 0.028 0.010 0.051 0.028 0.027 0.065 0.045 -0.004 0.023 -0.140 0.200 35X 08/31/10 0.001 0.003 0.006 0.007 0.001 0.003 0.000 0.005 -0.004 0.003 -0.006 0.022 35X 12/10/10 -0.001 0.006 0.000 0.014 0.002 0.006 0.001 0.010 0.003 0.006 -0.020 0.044 36X 02/22/10 -0.014 0.033 -0.013 0.076 -0.009 0.032 0.015 0.051 0.020 0.027 0.090 0.270 36X 04/21/10 0.011 0.023 -0.046 0.051 -0.003 0.026 0.024 0.042 0.010 0.024 -0.050 0.220 36X 08/31/10 0.001 0.004 -0.011 0.008 0.001 0.003 0.001 0.006 0.000 0.004 -0.007 0.025 36X 11/30/10 0.000 0.013 -0.011 0.023 -0.001 0.009 -0.002 0.015 0.002 0.008 0.025 0.080 90C 03/01/10 0.024 0.032 -0.097 0.076 -0.002 0.035 -0.062 0.061 0.011 0.034 -0.140 0.260 90C 04/19/10 -0.004 0.031 -0.060 0.073 0.009 0.033 0.003 0.043 0.002 0.030 -0.040 0.270 90C 08/18/10 -0.002 0.003 0.001 0.007 0.001 0.003 -0.001 0.004 -0.001 0.003 0.009 0.020 90C 11/15/10 0.000 0.012 -0.005 0.024 0.015 0.010 0.012 0.018 0.002 0.010 0.033 0.080 3-54

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 16 AQUATIC FLORA - FUCUS (pCi/g wet wt.)

COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-1 34 Cs-1 37 AcTh-228

(+/-)

29 02/22/10 -0.015 0.039 0.027 0.078 -0.008 0.062 0.025 0.028 -0.021 0.028 0.140 0.130 29 04/21/10 0.022 0.034 -0.056 0.064 -0.032 0.050 -0.008 0.021 0.010 0.035 0.120 0.130 29 08/31/10 -0.002 0.003 -0.003 0.007 0.007 0.018 0.000 0.003 0.001 0.003 0.016 0.019 29 11/29/10 0.010 0.012 -0.006 0.031 0.013 0.024 -0.002 0.013 -0.001 0.013 0.084 0.054 32X 02/23/10 0.000 0.037 -0.049 0.089 -0.020 0.049 0.016 0.023 -0.010 0.031 0.080 0.110 32X 04/20/10 -0.016 0.029 0.031 0.057 0.036 0.040 0.000 0.015 -0.008 0.021 0.028 0.079 32X 08/30/10 0.006 0.004 -0.004 0.006 0.000 0.016 0.000 0.002 0.003 0.002 0.032 0.025 32X 11/15/10 0.002 0.011 0.009 0.025 -0.027 0.034 -0.005 0.011 -0.003 0.012 0.083 0.065 33X 03/01/10 -0.022 0.034 0.031 0.062 -0.015 0.042 -0.019 0.020 0.006 0.028 0.090 0.120 33X 04/19/10 -0.011 0.013 -0.014 0.025 0.039 0.038 0.003 0.007 -0.003 0.009 0.037 0.048 33X 08/18/10 -0.002 0.012 0.007 0.030 0.026 0.032 -0.006 0.013 0.002 0.013 0.085 0.056 33X 11/15/10 -0.003 0.009 0.014 0.026 -0.002 0.032 -0.010 0.010 0.004 0.011 0.066 0.063 35X 02/22/10 -0.036 0.043 0.004 0.062 0.029 0.053 0.010 0.020 -0.008 0.031 0.060 0.120 35X 04/20/10 -0.011 0.032 -0.025 0.061 0.012 0.042 -0.013 0.020 0.011 0.024 0.016 0.099 35X 08/31/10 -0.001 0.002 0.004 0.006 -0.019 0.016 0.000 0.003 0.002 0.003 0.040 0.020 35X 12/10/10 -0.002 0.005 -0.004 0.012 -0.021 0.034 -0.003 0.005 0.000 0.005 0.047 0.039 36X 02/22/10 0.036 0.038 0.012 0.064 -0.003 0.047 -0.001 0.018 -0.035 0.027 0.060 0.120 36X 04/21/10 -0.020 0.036 0.025 0.068 0.044 0.037 0.014 0.024 -0.001 0.023 0.065 0.089 36X 08/31/10 -0.002 0.003 0.006 0.007 0.006 0.019 -0.002 0.003 0.001 0.003 0.048 0.024 36X 11/30/10 -0.004 0.009 -0.008 0.020 0.008 0.016 0.003 0.009 -0.003 0.009 0.020 0.045 90C 03/01/10 0.000 0.036 -0.030 0.074 -0.054 0.054 -0.013 0.021 0.029 0.030 0.030 0.120 90C 04/19/10 0.000 0.038 0.066 0.064 0.436 0.090 0.007 0.023 -0.007 0.031 -0.010 0.130 90C 08/18/10 -0.001 0.002 0.000 0.006 0.139 0.014 -0.001 0.002 0.002 0.003 0.032 0.019 90C 11/15/10 -0.003 0.008 -0.032 0.021 -0.014 0.029 -0.015 0.008 -0.001 0.009 0.076 0.061 3-55

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 17A FISH - FLOUNDER (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+1-) (+/-) (+/-)

32 H 05/25/10 -0.05 0.16 3.69 0.64 0.07 0.15 0.002 0.013 -0.004 0.016 -0.026 0.043 32 I 08/04/10 -0.10 0.37 3.77 1.10 -0.40 0.40 -0.020 0.037 0.009 0.046 -0.044 0.091 35 H 04/26/10 0.02 0.11 3.91 0.32 0.11 0.13 0.004 0.012 0.008 0.013 -0.026 0.033 35 07/20/10 0.10 0.35 4.18 0.80 -0.18 0.33 -0.004 0.033 0.012 0.038 0.007 0.093 35 10/26/10 -0.09 0.19 3.71 0.75 0.08 0.22 0.006 0.021 -0.002 0.023 0.000 0.046 COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06

(*/-) (+/-) (+/-) (+/-) (*/-) (*/-)

32 05/25/10 -0.015 0.019 -0.041 0.044 0.000 0.020 0.015 0.032 0.000 0.022 -0.01 0.16 32 08/04/10 0.016 0.041 0.033 0.088 -0.001 0.053 -0.021 0.079 -0.040 0.052 -0.01 0.35 35 04/26/10 0.008 0.012 -0.011 0.028 0.008 0.017 -0.005 0.025 -0.012 0.015 -0.04 0.10 35 07/20/10 -0.030 0.041 0.022 0.087 -0.017 0.037 0.079 0.066 -0.004 0.038 0.12 0.33 35 10/26/10 0.001 0.021 -0.041 0.054 -0.013 0.024 -0.014 0.043 0.001 0.026 -0.06 0.19 COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-1 34 Cs-1 37 AcTh-228

(+/-)(+-

32 05/25/10 0.012 0.027 0.012 0.048 -0.010 0.045 -0.005 0.013 0.005 0.018 -0.085 0.076 32 08/04/10 -0.021 0.035 -0.033 0.104 -0.058 0.135 -0.006 0.040 -0.034 0.046 -0.116 0.174 35 04/26/10 0.003 0.017 0.009 0.029 0.073 0.060 0.004 0.011 0.003 0.011 0.034 0.062 35 07/20/10 0.022 0.035 -0.059 0.086 0.015 0.126 -0.030 0.042 -0.017 0.038 -0.020 0.150 35 10/26/10 -0.004 0.021 -0.018 0.054 0.020 0.075 -0.009 0.024 0.003 0.021 -0.020 0.080 3-56

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 17B FISH - OTHER (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+/-) (+/-) (+/-)

32 H 06/22/10 -0.01 0.16 3.54 0.67 0.04 0.14 -0.002 0.018 0.009 0.017 -0.018 0.047 32 08/04/10 0.17 0.24 4.38 0.76 -0.06 0.26 -0.012 0.025 -0.001 0.028 0.068 0.060 32 10/06/10 0.29 0.54 11.50 2.08 -0.04 0.67 0.011 0.066 -0.006 0.060 0.020 0.126 35 H 04/26/10 0.04. 0.10 3.25 0.39 -0.01 0.11 0.008 0.012 -0.007 0.013 0.002 0.032 35 08/23/10 -0.05 0.06 4.74 0.26 0.02 0.08 0.002 0.005 0.007 0.006 0.009 0.015 35 11/18/10 0.04 0.21 3.62 0.68 -0.11 0.24 0.005 0.023 0.009 0.025 -0.012 0.058 40X 02/03/10 0.220 0.240 2.900 1.100 0.130 0.210 -0.036 0.036 -0.029 0.030 -0.024 0.076 40X 05/11/10 0.010 0.130 3.500 0.630 0.020 0.160 0.022 0.019 0.001 0.017 0.018 0.045 40X 09/15/10 -0.003 0.260 4.180 0.841 0.142 0.264 0.000 0.032 0.006 0.032 0.008 0.065 COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06

(+/-) (+/-) (+/-)

32 06/22/10 0.009 0.022 -0.027 0.048 0.016 0.022 0.037 0.038 -0.007 0.017 0.10 0.17 32 08/04/10 -0.247 0.030 0.031 0.072 -0.033 0.031 -0.056 0.049 -0.014 0.032 0.04 0.23 32 10/06/10 0.006 0.059 0.035 0.144 0.000 0.073 -0.044 0.124 -0.021 0.064 -0.12 0.61 35 04/26/10 -0.004 0.014 -0.003 0.024 0.007 0.016 -0.008 0.025 -0.007 0.014 0.00 0.09 35 08/23/10 0.000 0.006 -0.002 0.013 -0.003 0.008 -0.001 0.013 0.007 0.008 -0.03 0.05 35 11/18/10 -0.003 0.028 -0.049 0.053 -0.022 0.027 -0.026 0.051 0.007 0.025 -0.12 0.21 40X 02/03/10 -0.038 0.037 0.000 0.078 0.030 0.042 0.004 0.045 -0.023 0.034 -0.140 0.350 40X 05/11/10 0.000 0.018 0.004 0.043 0.005 0.022 -0.002 0.033 0.001 0.021 0.070 0.170 40X 09/15/10 0.013 0.034 -0.038 0.079 -0.023 0.028 0.010 0.050 0.037 0.031 -0.199 0.304 3-57

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 17B FISH - OTHER (pCi/g wet wt.)

COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-134 Cs-137 AcTh-228

(+/-) (+/-) (+/-) (+/-) (+7-) (+/-)

32 06/22/10 0.017 0.026 0.024 0.042 0.010 0.027 0.000 0.015 -0.014 0.020 0.012 0.780 32 08/04/10 0.003 0.022 0.042 0.067 0.052 0.087 0.020 0.024 -0.101 0.027 0.048 0.109 32 10/06/10 -0.045 0.066 -0.112 0.181 0.149 0.124 -0.069 0.068 -0.005 0.076 -0.194 0.254 35 04/26/10 -0.013 0.016 -0.001 0.028 -0.018 0.042 0.000 0.008 -0.006 0.015 0.040 0.046 35 08/23/10 0.001 0.005 -0.003 0.014 0.028 0.058 -0.005 0.006 0.007 0.006 -0.047 0.035 35 11/18/10 0.003 0.023 -0.005 0.063 -0.002 0.059 -0.058 0.027 0.009 0.025 -0.043 0.092 40X 02/03/10 0.014 0.060 0.000 0.085 -0.019 0.050 0.008 0.025 0.022 0.025 -0.030 0.140 40X 05/11/10 -0.012 0.024 0.000 0.039 -0.010 0.050 0.002 0.012 0.006 0.017 -0.049 0.077 40X 09/15/10 0.022 0.030 0.035 0.087 -0.038 0.049 0.028 0.035 -0.008 0.033 0.006 0.120 3-58

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 18 MUSSELS (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+/-) (+/-) (+/-) (+/-) (+/-) (+/-)

J,K 30 02/12/10 0.23 0.34 2.63 0.98 -0.06 0.30 -0.012 0.035 0.001 0.044 0.060 0.095 30 L 05/17/10 0.09 0.10 2.17 0.25 -0.01 0.11 0.006 0.008 0.005 0.010 -0.003 0.023 COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 30 02/12/10 -0.021 0.044 -0.030 0.100 0.012 0.047 -0.019 0.070 -0.015 0.044 0.180 0.320 30 05/17/10 -0.003 0.008 0.004 0.017 -0.002 0.012 0.010 0.015 -0.001 0.012 -0.011 0.078 COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-134 Cs-137 AcTh-228

(+/-) (+/-) (+/-) (+/-) - (+/-)

30 02/12/10 0.018 0.032 0.044 0.088 -0.048 0.070 -0.017 0.024 0.008 0.036 0.030 0.170 30 05/17/10 0.005 0.013 -0.009 0.023 -0.016 0.054 0.001 0.008 -0.005 0.008 -0.016 0.034 J, K,L Several samples not available due to scarcity of this type of shellfish; see NOTES for more details 3-59

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 19 OYSTERS (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+/-) (+/-) (+/-) (+/-) (*/-) (+/-)

31 03/02/10 0.07 0.20 2.11 0.77 0.03 0.19 -0.007 0.023 -0.009 0.018 -0.018 0.056 31 05/10/10 0.07 0.13 2.05 0.38 -0.09 0.15 0.008 0.014 -0.002 0.015 0.011 0.035 31 08/18/10 0.09 0.12 1.40 0.29 0.02 0.13 -0.003 0.013 0.002 0.015 -0.012 0.028 31 10/08/10 0.07 0.09 1.87 0.41 0.02 0.10 -0.002 0.006 0.003 0.009 -0.006 0.016 32 02/23/10 0.01 0.17 1.91 0.54 0.00 0.20 0.027 0.021 0.011 0.017 -0.013 0.047 32 05/05/10 0.20 0.26 2.35 0.83 -0.01 0.20 -0.003 0.028 -0.003 0.025 0.029 0.057 32 07/19/10 0.01 0.08 2.43 0.46 0.03 0.10 0.000 0.008 -0.001 0.009 -0.017 0.018 32 11/15/10 0.09 0.14 2.10 0.38 0.18 0.16 -0.004 0.014 0.003 0.016 0.009 0.033 34X 03/01/10 0.15 0.19 2.10 0.57 0.03 0.20 0.004 0.019 0.002 0.020 0.001 0.046 34X 05/10/10 -0.03 0.18 1.77 0.55 0.05 0.19 0.010 0.017 0.003 0.027 -0.046 0.047 34X 08/18/10 -0.01 0.07 1.95 0.26 0.03 0.08 -0.001 0.007 0.006 0.008 -0.001 0.016 34X 10/04/10 0.14 0.23 6.47 0.81 0.06 0.27 -0.015 0.031 -0.017 0.025 0.010 0.060 37C 02/22/10 -0.10 0.18 1.39 0.55 0.00 0.18 -0.003 0.028 -0.001 0.019 0.013 0.056 37C 05/11/10 -0.15 0.17 1.59 0.53 -0.04 0.20 -0.013 0.019 -0.016 0.021 -0.075 0.055 37C 08/31/10 0.12 0.10 1.52 0.36 -0.02 0.13 -0.005 0.010 0.012 0.011 -0.018 0.020 37C 11/30/10 -0.01 0.12 2.48 0.41 0.10 0.13 0.011 0.015 -0.008 0.015 -0.016 0.028 88 02/22/10 -0.11 0.20 2.05 0.77 0.07 0.19 -0.013 0.022 -0.010 0.025 -0.009 0.058 88 05/11/10 -0.06 0.14 2.21 0.52 -0.05 0.13 0.002 0.016 0.009 0.017 -0.044 0.051 88 08/25/10 0.04 0.24 1.01 0.57 0.18 0.28 0.005 0.018 0.003 0.025 -0.037 0.067 88 11/15/10 0.03 0.16 1.74 0.43 0.10 0.16 0.007 0.017 -0.003 0.018 -0.016 0.037 3-60

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 19 OYSTERS (pCi/g wet wt.)

COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06

(+/-) (+/-) (+1-) (+1-) (+1-) (+/-)

31 03/02/10 -0.005 0.042 0.036 0.062 0.014 0.026 0.012 0.046 0.023 0.031 0.25 0.26 31 05/10/10 0.003 0.015 -0.003 0.034 -0.018 0.019 -0.002 0.025 0.008 0.016 -0.17 0.12 31 08/18/10 0.003 0.013 0.054 0.035 0.023 0.014 -0.013 0.024 -0.011 0.014 -0.06 0.11 31 10/08/10 0.005 0.008 0.001 0.016 -0.003 0.009 -0.003 0.014 -0.005 0.011 -0.01 0.07 32 02/23/10 -0.009 0.021 -0.077 0.045 0.012 0.025 -0.008 0.029 0.011 0.022 -0.07 0.20 32 05/05/10 -0.003 0.037 0.019 0.067 0.027 0.031 0.023 0.050 0.006 0.029 -0.06 0.26 32 07/19/10 0.001 0.010 0.009 0.018 -0.008 0.009 -0.001 0.016 0.006 0.011 -0.06 0.08 32 11/15/10 -0.008 0.017 -0.008 0.032 0.023 0.018 0.003 0.024 0.000 0.019 -0.04 0.14 34X 03/01/10 -0.006 0.021 0.016 0.049 -0.016 0.023 0.012 0.041 -0.007 0.023 -0.11 0.16 34X 05/10/10 -0.002 0.018 0.019 0.040 0.000 0.026 0.015 0.029 0.009 0.021 -0.10 0.17 34X 08/18/10 0.010 0.008 -0.005 0.017 0.002 0.009 -0.006 0.014 0.000 0.008 -0.05 0.06 34X 10/04/10 0.028 0.031 -0.071 0.066 -0.019 0.028 0.002 0.051 -0.004 0.028 0.02 0.25 37C 02/22/10 0.014 0.029 0.023 0.046 -0.004 0.025 0.020 0.037 -0.008 0.019 -0.03 0.22 37C 05/11/10 -0.009 0.026 -0.011 0.045 -0.024 0.027 0.001 0.042 0.017 0.023 0.10 0.18 37C 08/31/10 0.003 0.010 0.020 0.022 0.003 0.012 -0.005 0.023 -0.008 0.014 0.00 0.09 37C 11/30/10 -0.001 0.016 -0.017 0.035 0.011 0.016 0.010 0.027 0.006 0.015 -0.10 0.12 881 02/22/10 0.016 0.026 0.000 0.035 0.006 0.026 -0.015 0.051 0.000 0.023 0.15 0.26 881 05/11/10 0.000 0.020 -0.005 0.039 0.012 0.018 0.004 0.032 0.009 0.017 -0.03 0.15 881 08/25/10 0.005 0.024 -0.033 0.066 0.040 0.030 -0.005 0.043 -0.004 0.032 0.12 0.22 881 11/15/10 0.010 0.021 -0.029 0.038 0.005 0.019 -0.005 0.033 -0.007 0.019 0.05 0.15 3-61

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 19 OYSTERS (pCi/g wet wt.)

COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-134 Cs-137 AcTh-228

(*/-) (+/-) (+/-) (+/-) (+/-) (+/-)

31 03/02/10 -0.005 0.027 0.007 0.060 0.025 0.042 -0.016 0.018 0.007 0.025 0.050 0.110 31 05/10/10 -0.001 0.023 -0.021 0.041 0.013 0.052 -0.006 0.011 -0.002 0.015 0.002 0.052 31 08/18/10 0.002 0.012 0.002 0.033 -0.003 0.036 0.050 0.015 0.014 0.013 -0.086 0.063 31 10/08/10 -0.011 0.007 -0.016 0.023 -0.001 0.023 -0.008 0.009 0.006 0.009 -0.014 0.034 32 02/23/10 0.063 0.023 0.010 0.066 0.000 0.040 -0.024 0.018 -0.035 0.060 0.015 0.068 32 05/05/10 0.057 0.038 0.007 0.064 0.004 0.051 0.003 0.022 0.050 0.045 0.010 0.120 32 07/19/10 0.200 0.023 -0.006 0.022 0.025 0.055 0.004 0.008 0.001 0.008 0.006 0.102 32 11/15/10 0.101 0.022 0.011 0.043 -0.025 0.056 -0.006 0.016 0.005 0.016 0.030 0.058 34X 03/01/10 -0.006 0.030 -0.010 0.049 -0.040 0.041 -0.009 0.015 0.000 0.022 -0.008 0.075 34X 05/10/10 0.029 0.031 0.032 0.048 0.057 0.055 0.010 0.013 -0.010 0.023 -0.019 0.070 34X 08/18/10 -0.002 0.007 0.012 0.022 0.009 0.023 -0.003 0.008 -0.002 0.007 -0.020 0.037 34X 10/04/10 0.006 0.028 -0.012 0.070 -0.052 0.056 -0.042 0.028 -0.002 0.032 0.005 0.179 37C 02/22/10 0.024 0.031 -0.024 0.065 -0.039 0.040 -0.006 0.014 -0.009 0.019 0.020 0.110 37C 05/11/10 -0.012 0.030 0.004 0.055 0.018 0.052 -0.005 0.014 -0.003 0.024 -0.002 0.065 37C 08/31/10 0.004 0.010 0.009 0.026 -0.015 0.060 -0.003 0.011 0.004 0.012 -0.021 0.043 37C 11/30/10 -0.002 0.013 -0.018 0.036 -0.016 0.030 0.000 0.017 0.000 0.016 -0.049 0.054 881 02/22/10 -0.025 0.038 -0.032 0.073 0.000 0.043 -0.001 0.019 -0.011 0.028 -0.010 0.110 881 05/11/10 -0.002 0.025 -0.014 0.038 0.003 0.042 -0.001 0.012 0.016 0.017 -0.028 0.058 881 08/25/10 0.012 0.026 0.044 0.057 -0.057 0.183 -0.009 0.025 -0.037 0.027 -0.046 0.087 881 11/15/10 0.013 0.016 0.015 0.042 -0.036 0.056 -0.004 0.017 -0.006 0.017 -0.023 0.059 3-62

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 20 CLAMS (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(./-) (+/-) (+1-) (+1-)

29 02/08/10 0.12 0.17 2.49 0.74 -0.15 0.21 0.007 0.026 -0.009 0.022 0.055 0.065 29 06/15/10 0.00 0.14 2.06 0.41 -0.22 0.16 -0.004 0.015 -0.006 0.016 -0.019 0.034 29 07/26/10 0.02 0.08 2.73 0.26 0.05 0.10 0.002 0.008 -0.004 0.009 0.010 0.019 29 11/03/10 -0.03 0.16 2.16 0.50 0.00 0.16 -0.001 0.018 -0.016 0.018 0.010 0.035 35X 03/25/10 0.08 0.13 1.58 0.38 -0.06 0.14 -0.004 0.013 -0.005 0.013 0.026 0.033 35X 06/15/10 0.07 0.15 2.00 0.52 -0.10 0.15 -0.003 0.018 0.006 0.017 0.011 0.035 35X 07/26/10 -0.01 0.08 1.58 0.22 -0.07 0.10 0.000 0.007 0.001 0.009 0.021 0.019 35X 11/03/10 0.03 0.16 1.80 0.47 -0.02 0.17 -0.006 0.017 -0.001 0.019 0.007 0.036 38 03/25/10 -0.05 0.13 2.04 0.51 0.06 0.15 -0.017 0.020 -0.006 0.017 0.008 0.048 38 06/15/10 0.11 0.13 2.52 0.58 -0.06 0.15 -0.011 0.013 0.002 0.021 -0.029 0.047 38 07/26/10 -0.07 0.09 1.98 0.30 0.09 0.12 0.001 0.009 -0.003 0.011 -0.005 0.024 38 11/03/10 0.06 0.13 2.12 0.38 -0.01 0.14 -0.001 0.016 -0.002 0.015 0.013 0.030 39X 02/08/10 0.13 0.14 1.47 0.59 -0.14 0.18 -0.013 0.018 -0.003 0.021 -0.007 0.060 39X 06/17/10 0.08 0.17 1.96 0.58 0.03 0.16 0.004 0.015 -0.003 0.020 -0.037 0.053 39X 09/01/10 0.00 0.07 1.70 0.22 0.03 0.08 0.002 0.007 0.001 0.007 -0.021 0.016 39X 11/29/10 0.08 0.15 2.01 0.48 -0.06 0.17 0.010 0.018 -0.008 0.018 -0.017 0.034 3-63

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 20 CLAMS (pCi/g wet wt.)

COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-106 29 02/08/10 0.010 0.023 -0.051 0.044 0.009 0.028 -0.034 0.044 -0.023 0.026 0.01 0.22 29 06/15/10 0.006 0.015 0.003 0.032 -0.009 0.020 -0.021 0.029 0.006 0.017 -0.06 0.13 29 07/26/10 -0.231 0.014 0.006 0.018 0.000 0.009 -0.008 0.016 -0.004 0.010 0.00 0.07 29 11/03/10 0.005 0.020 -0.013 0.046 0.020 0.024 -0.008 0.030 0.003 0.020 0.13 0.18 35X 03/25/10 0.004 0.013 0.009 0.037 0.012 0.018 0.006 0.024 0.006 0.019 -0.01 0.13 35X 06/15/10 0.007 0.020 -0.010 0.035 0.004 0.020 -0.011 0.033 0.000 0.019 -0.01 0.16 35X 07/26/10 0.000 0.007 0.003 0.017 0.000 0.009 -0.007 0.016 0.003 0.010 -0.01 0.07 35X 11/03/10 -0.016 0.020 -0.063 0.042 0.001 0.019 0.005 0.030 0.008 0.020 0.04 0.19 38 03/25/10 -0.010 0.021 0.028 0.052 -0.010 0.020 -0.004 0.031 -0.011 0.018 0.06 0.17 38 06/15/10 -0.015 0.017 0.000 0.046 -0.008 0.021 -0.005 0.027 -0.008 0.020 0.02 0.14 38 07/26/10 0.014 0.010 -0.002 0.023 -0.008 0.011 0.008 0.019 0.002 0.012 0.03 0.08 38 11/03/10 0.013 0.015 -0.019 0.042 0.016 0.017 -0.009 0.026 0.002 0.015 0.04 0.15 39X 02/08/10 -0.008 0.020 0.034 0.038 -0.009 0.023 0.013 0.034 -0.007 0.023 -0.03 0.19 39X 06/17/10 -0.005 0.020 -0.030 0.043 -0.011 0.028 0.015 0.032 0.014 0.021 -0.03 0.16 39X 09/01/10 -0.002 0.007 -0.006 0.018 0.003 0.007 0.006 0.013 0.003 0.009 -0.03 0.06 39X 11/29/10 0.018 0.020 0.012 0.040 0.014 0.019 0.003 0.032 0.007 0.019 0.12 0.15 3-64

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 20 CLAMS (pCi/g wet wt.)

COLLECTION LOCATION DATE Ag-110M Sb-125 1-13 1 Cs-1 34 Cs- 137 AcTh-228 29 02/08/10 0.017 0.036 0.027 0.061 -0.037 0.064 -0.008 0.017 -0.007 0.025 0.050 0.095 29 06/15/10 0.011 0.019 0.007 0.038 -0.008 0.041 0.000 0.010 0.000 0.014 0.001 0.044 29 07/26/10 0.001 0.007 -0.007 0.019 0.015 0.050 -0.001 0.008 -0.071 0.012 -0.006 0.037 29 11/03/10 0.001 0.017 -0.011 0.052 0.028 0.034 0.003 0.020 -0.008 0.019 -0.011 0.078 35X 03/25/10 -0.022 0.020 -0.023 0.037 -0.009 0.054 0.000 0.012 -0.003 0.015 0.006 0.055 35X 06/15/10 -0.027 0.022 -0.024 0.040 -0.011 0.044 -0.003 0.012 0.004 0.018 0.057 0.067 35X 07/26/10 -0.007 0.008 -0.002 0.020 0.001 0.053 0.000 0.009 0.001 0.008 0.001 0.065 35X 11/03/10 0.014 0.017 0.004 0.048 -0.003 0.033 -0.011 0.021 -0.004 0.019 0.137 0.123 38 03/25/10 0.000 0.024 -0.003 0.039 -0.026 0.044 -0.005 0.011 0.014 0.017 0.027 0.067 38 06/15/10 -0.013 0.028 0.019 0.043 0.029 0.047 0.001 0.012 -0.012 0.022 0.030 0.067 38 07/26/10 0.000 0.009 0.002 0.024 -0.038 0.062 -0.039 0.010 0.001 0.010 -0.019 0.058 38 11/03/10 0.000 0.014 0.016 0.041 -0.025 0.029 -0.001 0.018 -0.006 0.016 0.016 0.064 39X 02/08/10 -0.016 0.019 -0.040 0.059 0.048 0.064 0.003 0.015 0.021 0.028 0.007 0.078 39X 06/17/10 -0.008 0.021 0.000 0.045 -0.004 0.049 0.008 0.013 0.009 0.026 0.127 0.098 39X 09/01/10 0.002 0.007 -0.007 0.018 0.005 0.035 -0.006 0.008 -0.002 0.007 -0.040 0.038 39X 11/29/10 -0.007 0.016 0.009 0.045 0.011 0.037 0.001 0.020 0.002 0.018 -0.032 0.073 3-65

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 22 LOBSTERS (pCi/g wet wt.)

COLLECTION LOCATION DATE Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59

(+1-) (+/-) (+/-) (+1-) (+1-) (+1-)

32 02/03/10 0.03 0.22 2.80 1.00 0.05 0.23 0.018 0.033 0.006 0.040 0.013 0.067 32 05/10/10 0.09 0.17 1.45 0.57 0.19 0.19 -0.004 0.024 -0.006 0.020 -0.030 0.053 32 08/05/10 -0.02 0.08 1.81 0.22 -0.01 0.08 0.007 0.008 -0.003 0.009 -0.005 0.020 32 10/22/10 -0.02 0.06 2.86 0.20 0.00 0.08 0.000 0.007 -0.007 0.008 0.015 0.017 35 02/03/10 0.00 0.23 2.19 0.93 0.02 0.21 -0.014 0.033 -0.002 0.027 0.007 0.064 35 05/10/10 0.01 0.11 2.56 0.43 0.05 0.13 0.009 0.015 0.000 0.016 -0.001 0.031 35 08/05/10 0.00 0.10 2.09 0.29 0.02 0.13 0.007 0.010 -0.001 0.011 -0.016 0.022 35 11/18/10 0.12 0.19 2.64 0.62 -0.14 0.22 0.015 0.022 0.008 0.021 0.003 0.045 37X 02/12/10 -0.05 0.17 1.92 0.62 0.13 0.17 -0.006 0.015 0.010 0.026 0.004 0.046 37X 05/20/10 -0.02 0.11 1.82 0.40 -0.01 0.12 -0.005 0.014 -0.014 0.013 0.008 0.036 37X 09/29/10 -0.05 0.15 8.01 0.71 -0.14 0.16 -0.005 0.025 0.001 0.018 -0.008 0.045 37X 10/12/10 -0.05 0.14 1.65 0.46 -0.14 0.15 0.008 0.016 0.001 0.017 -0.034 0.038 COLLECTION LOCATION DATE Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 32 02/03/10 -0.011 0.043 -0.013 0.078 -0.005 0.037 0.005 0.052 0.000 0.033 -0.08 0.26 32 05/10/10 0.016 0.028 0.000 0.047 0.024 0.028 0.010 0.042 -0.018 0.021 0.05 0.16 32 08/05/10 -0.001 0.010 -0.022 0.020 0.004 0.010 0.011 0.016 0.001 0.010 0.03 0.07 32 10/22/10 0.001 0.007 0.005 0.017 0.013 0.009 0.002 0.014 0.003 0.008 0.07 0.06 35 02/03/10 0.021 0.024 -0.016 0.057 -0.011 0.026 -0.006 0.026 0.004 0.024 -0.08 0.28 35 05/10/10 -0.004 0.013 -0.003 0.034 0.013 0.019 -0.006 0.027 0.004 0.015 0.10 0.13 35 08/05/10 0.010 0.010 -0.015 0.022 -0.004 0.011 0.003 0.018 0.003 0.013 -0.01 0.10 35 11/18/10 -0.005 0.021 -0.058 0.055 0.000 0.023 -0.017 0.034 0.018 0.021 0.04 0.20 37X 02/12/10 -0.008 0.026 0.021 0.067 -0.020 0.024 0.023 0.036 -0.012 0.024 0.06 0.19 37X 05/20/10 -0.010 0.016 -0.003 0.033 0.003 0.018 0.007 0.020 -0.016 0.016 0.03 0.11 37X 09/29/10 0.035 0.021 0.034 0.048 -0.027 0.019 -0.011 0.032 -0.003 0.019 -0.07 0.16 37X 10/12/10 0.013 0.019 -0.069 0.041 -0.002 0.016 -0.010 0.028 -0.009 0.018 -0.05 0.17 3-66

Millstone Station Annual Radiological Environmental Operating Report 2010 TABLE 22 LOBSTERS (pCi/g wet wt.)

COLLECTION LOCATION DATE Ag-110M Sb-125 1-131 Cs-134 Cs-137 AcTh-228

(+/-) (+/-) (+/-) (+/-) (+/-) (+/-)

32 02/03/10 0.018 0.041 0.040 0.089 0.004 0.045 -0.014 0.028 0.009 0.042 -0.020 0.130 32 05/10/10 0.000 0.025 0.045 0.043 0.029 0.056 -0.005 0.014 -0.017 0.023 -0.041 0.083 32 08/05/10 0.000 0.008 0.009 0.022 -0.016 0.024 -0.003 0.009 0.003 0.008 0.031 0.052 32 10/22/10 0.005 0.006 0.006 0.018 0.013 0.036 0.001 0.008 -0.010 0.007 0.014 0.037 35 02/03/10 -0.013 0.046 0.009 0.074 0.027 0.031 -0.001 0.024 -0.010 0.036 0.030 0.110 35 05/10/10 0.012 0.021 -0.035 0.034 -0.019 0.045 0.000 0.010 0.003 0.015 0.014 0.045 35 08/05/10 -0.002 0.011 0.000 0.032 -0.002 0.036 -0.002 0.012 0.002 0.015 0.041 0.077 35 11/18/10 0.010 0.018 -0.053 0.055 0.004 0.054 -0.012 0.023 0.005 0.021 0.051 0.124 37X 02/12/10 -0.012 0.035 -0.005 0.051 -0.006 0.038 -0.007 0.019 0.004 0.024 -0.013 0.068 37X 05/20/10 -0.002 0.019 -0.020 0.026 0.031 0.051 -0.001 0.008 -0.006 0.017 0.042 0.050 37X 09/29/10 -0.006 0.017 -0.013 0.042 0.023 0.058 -0.004 0.018 0.006 0.019 0.001 0.174 37X 10/12/10 0.001 0.014 0.021 0.043 0.004 0.031 0.005 0.020 0.009 0.016 -0.024 0.062 3-67

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 NOTES FOR DATA TABLES Collection Dates for Air Particulates and Iodine are listed as the end date; typically change-out days are on Tuesdays.

A First quarter TLD (location 42) was not recovered after the phone pole it was mounted on was removed. Replaced TLD for second quarter.

Air Particulates had loss of power at Norwich (15) on May 26th. Sampled 10,099 cubic feet of air. Shut down was caused by a blown fuse.

Air Particulates had loss of power at Norwich (15) during sampling week of C October 5 - 12. Sampled 8,218 cubic feet of air. Shut down was caused by a blown fuse.

Air Particulates had loss of power at Norwich (15) on November 24th from 12:45 D to 16:05. Sampled 13,564 cubic feet of air. Shut down was caused by a blown fuse.

E Non-pasture grass samples - hay F Non-pasture grass samples - feed (e.g., grain)

First quarter continuous seawater samples at Vicinity of Discharge (32) had low G volume during the weeks ending January 5th, January 12th, and February 2nd due to freezing/clogging of the intake tubing line, which has since been corrected.

H First quarter flounder plus other fish species at Vicinity of Discharge (32) and Niantic Bay (35) were unavailable due to scarcity during winter season.

I Fourth quarter flounder plus other fish species at Vicinity of Discharge (32) and Niantic Bay (35) were unavailable due to scarcity during winter season.

First quarter mussels at Two Tree Island (28) were unavailable due to not being found intertidally and subtidally using SCUBA.

K Second quarter mussels at Two Tree Island (28) were unavailable due to not being found intertidally and subtidally using SCUBA.

Third and Fourth quarters' mussels at Niantic Shoals (30) and Two Tree Island L (28) were unavailable due to not being found intertidally and subtidally using SCUBA.

3-68

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

4. DISCUSSION OF RESULTS This section summarizes the results of the analyses on the REMP (Radiological Environmental Monitoring Program) samples. DNC has carefully examined the data throughout the year and has presented in this section all cases where station related radioactivity could be detected.

The results are compared with previous environmental surveillance data.

Few impacts of the station operation on the environment were observed. Sub-sections contain a description of each particular media or potential exposure pathway. Naturally occurring nuclides such as Be-7, K-40, and Th-228 were detected in numerous samples. Be-7, which is produced by cosmic processes, was observed predominantly in airborne and vegetation samples. Th-228 results were variable and are generally at levels higher than plant related radionuclides.

Cs-137 and Sr-90 were observed at levels similar to those of past years. The levels of Cs-137 and Sr-90 detected were the result of atmospheric nuclear weapons testing in the 1960's.

4.1 Gamma Exposure Rate (Table 1)

Gamma exposure rate is determined from the integrated exposure measured over a calendar quarter using thermoluminescent dosimeters (TLDs). Prior to 1990, Victoreen CaF 2(Mn) glass bulb glass bulb dosimeters were used for these measurements. In 1990, these were replaced by Harshaw CaF 2(Mn) chips. In 2000, the CaF 2(Mn) TLDs, were replaced with the CaSO 4(Tm) Panasonic model UD-804 ASx TLDs.

The dosimeters are strategically placed at a number of on-site locations, as well as at inner and outer off-site locations. Starting in 2001, the collection of TLDs was changed from monthly to quarterly and additional measurement locations were incorporated into the REMP requirements listed in the REMODCM (Radiological Effluent Monitoring and Offsite Dose Calculation Manual - Reference 8). Three more locations were added in mid-2003 to prepare for monitoring the potential effect of ISFSI (Independent Spent Fuel Storage Installation - Dry Cask Storage). Two Dry Cask Containers were loaded in the first quarter 2005. Three containers were loaded in mid 2006, three in October 2007, three in April 2009, and three in October 2010. None were loaded in 2008. The exposure rate measurements at the three additional TLD locations remain basically unchanged from the background measurements performed prior to any cask loading (six quarter background average mid 2003 - 2004: 9.5 uR/hour at location 73X, 7.6 uR/hour at location 74X and 6.9 uR/hour at location 75X).

Table 1 lists the exposure rate measurements for all 44 monitored locations. Trends similar to those of past years are apparent. These measurements demonstrate the general variations in background radiation between the various on-site and off-site locations and include gamma exposure from all sources of radioactivity. For example, the Weather Shack (location 02), MP3 Discharge (location 05), Environmental Laboratory (location 08), Bay Point Beach (location 09), Pleasure Beach (location 10), Corey Road (location 48), and Site Switchyard Fence (location 73) experience higher exposure rates due to their proximity to granite beds and stonewalls. In addition, the Mystic (location 13C) and Ledyard (location 14C) control locations experience relatively higher background exposure rate than the other control locations at Fisher's Island, Norwich and Old Lyme (locations 12C, 15C and 16C).

4-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 The only appreciable effect seen in the recent TLD data is that attributable to the variation in the background radiation that is consistent with previous years. Figure 4.1-1 shows a historical trend of TLD exposure rate measurements, comparing an annual average of all indicator TLDs, an annual average of all control TLDs, and the annual average of the two most critical indicator locations which are used to represent the two closest site boundary residences in the North-northwest and Northeast directions. Examination of the average measurements since 1990, shows interesting site changes and site characteristics. For example, the average of all indicator locations for the period when Unit 1 was still in operation (through 1995) exhibit the effects of N-16 BWR turbine building sky-shine to immediate areas onsite. As discussed in previous annual reports, the effects of sky-shine at onsite monitoring stations were increased exposure rates as high as 6 uR/hr at certain onsite locations. The elevated exposure rates from sky-shine decreased rapidly with distance to levels indistinguishable from normal background measurements at even the nearest offsite monitoring stations. Also apparent in Figure 4.1-1 is the replacement of the historical Victoreen TLD monitoring system with the Panasonic system in year 2000. The difference in response between the two systems is very apparent, with the new Panasonic TLDs reading 15% to 20% lower. This lower response is consistent for all locations, including both indicator and control locations.

Figure 4.1-1 also relates the difference in critical indicator locations 1 and 3 and the annual average of all indicator TLDs to the annual average of the control TLDs collected and measured during coincident periods throughout the year. As discussed earlier, the exposure measurements of many indicator locations onsite (and two of the control locations) are influenced by natural background exposure differences caused by the many granite out-croppings typical of the local area. Figure 4.1-1 shows the annual average at indicator location 1 is slightly higher in gamma exposure rate than the average control gamma exposure rate. An opposite trend is shown for location 3. These differences are the result of the differences in granite at these locations. Location 3 was moved in the second quarter 2009 to minimize the effect of tree covering for the air sampler also located at this location.

The 2009 and 2010 data for location 3 shows an increase likely attributable to being closer to granite at the new location.

In 2005 and 2006, there was a small increase noted at locations 5 and 8 caused by storage of the Unit 2 replaced reactor head. As expected, this increase exhibited a decreasing trend because of radioactive decay. The head was shipped offsite for disposal in the fourth quarter 2006; the measured levels at these two locations have returned to the background levels measured prior to the head being placed in the storage area. Although not measurable, any resulting site boundary doses are bounded by dose rates from the radwaste storage areas and are discussed in Section 5.

4-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 4.1-1 ulR/hr Annual Gamma Exposure Rate - 20 Year History 10 [ AI] Indicators kLhhiuI..

RAH Controls S Uilndicator Loc 1

==ndicator Loc3 a !

II a, 6 m

0. 01 0 M M 0 0 0 0 0 0 0 0) 0 00 ) ) 0 ) ) 0 0 0 0 0 0 0 0 0, 0 0 4.2 Air Particulate Gross Beta Radioactivity (Table 2)

Air is continuously sampled at seven inner ring (0 to 2 miles) locations and one control location (14 miles N) by passing it through glass fiber particulate filters. These samples are collected weekly and analyzed for gross beta radioactivity. Results are shown on Figure 4.2-1 and Table 2. Gross beta activity remained at levels similar to that seen over the last decade. Inner and control monitoring locations continue to show no significant variation in measured activities (see Figure 4.2-2). This indicates that any station contribution is not measurable.

Figure 4.2-1 Air Particulate Gross Beta Activity pCi/m3 Monthly Averages - 2010 0.035 I ndicatorsol A- Control 0.03 0.025 0.02 N 0.015 ...

0.01 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 4-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 4.2-2 Air Particulate Gross Beta Activity pCi/m3 Monthly Averages - 5 Year Trend 0.035 _

0 Indicators

-- Control 0.03 0.025 0.015 0.01 0 . .0 > 0- 0 0 " 0 0 0 0 US, Z U) -Z Cn Z -, U)C Z - 2 U 4.3 Airborne Iodine (Table 3)

Charcoal cartridges are included at all of the air particulate monitoring stations for the collection of atmospheric iodine. These cartridges are analyzed on a weekly basis for 1-131.

No detectable levels of 1-131 were seen in the 2010 charcoal samples.

4.4 Air Particulate Gamma (Table 4A-D)

The air particulate samples that are utilized for the weekly gross beta analyses are composited quarterly and analyzed for gamma emitting isotopes. The results, as shown in Tables 4A - 4D, indicate the presence of naturally occurring Be-7, which is produced by cosmic radiation. No other positive results are seen. These analyses indicate the lack of station effects.

4.5 Air Particulate Strontium (Table 5)

Prior to 1989 Table 5 was used for listing the data for measurements of Sr-89 and Sr-90 in quarterly composite air particulate filters. The historical data indicated the lack of any detectable station related activity. Since these analyses are not listed in NUREG 1301 (Reference 15), these measurements were discontinued. In the event of widespread station related contamination or other unusual events (such as the 1986 Chernobyl incident), these measurements could be made. Historically, when world events created conditions that caused detectable measurements of these nuclides, there was no difference noted between indicator and control locations. This further confirms that any of the detectable levels for these nuclides were not plant related.

4-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 4.6 Soil (Table 6)

Millstone resumed collection of soil as a required media type in 2001. Prior to 2001, it had not been sampled for over fifteen years. These samples were discontinued due to the fact that, previous sample results never indicated any station related detectable activity.

Similarly, since 2001, no station detectable activity has been seen in these samples. The results of these samples, allows for the determination of baseline activity levels in soil. This is particularly important for Cs-137, since significant levels from past weapons testing fallout remain in the soil. Baseline levels should be useful in the future, when site characterization and decommissioning of the station become the focus during preparations for License termination. This media is collected annually from one control and two indicator locations.

4.7 Cow Milk (Table 7)

Typically, the most sensitive indicator of fission product existence in the terrestrial environment is the radiological analysis of milk samples. Milk is a widely consumed food, therefore it is usually one of the most critical exposure pathways. Since 1996 all dairy (cow) farms close enough to Millstone to be considered an indicator location (i.e. conservatively within 10 miles, reference 15 specifies within 5 miles) have ceased operation. Therefore, the sampling of cow milk has been discontinued until such time dairy activities in the nearby area resume. Each year the Land Use Census is used to identify locations of milk animals that should be included in the monitoring program. It is performed annually and is maintained by observations, door-to-door surveys and consulting with local agriculture authorities. The 2010 census is listed in Appendix A. If a new dairy farm is identified close enough to Millstone to be considered an indicator location, the collection of cow milk will resume.

4.8 Goat Milk (Table 8)

When available, these samples are collected twice per month during grazing season and once per month during the rest of the year. Each sample is analyzed for 1-131 and gamma emitting nuclides. Although not required by the REMODCM, samples from each location are composited quarterly and analyzed for Strontium.

Goat milk samples are typically a more sensitive indicator of fission products in the terrestrial environment than cow milk samples. It should be noted that the uptake of radionuclides in milk is dependent on a number of parameters. These include: metabolism of these animals, feeding habits, farming practices and feed type. Similar to previous years, Cs-1 37 and Sr-90 are observed in goat milk. During past weapons testing periods, samples taken at certain milk locations indicated higher uptake of fallout than others. This was especially apparent in past samples collected in the immediate area around Millstone (see previous Annual Operating Reports). One of these sites, located at 5.2 Mi. NNE of Millstone (previous location 22, sampled from 1994 through 2004), exhibited a trend of showing higher Sr-90 and Cs-1 37 concentrations than at some of the other locations (including ones located closer to Millstone). The Station and regulatory authorities (e.g., see Reference 17) have carefully reviewed past and present data. The presence of the Sr-90 and Cs-137 is the result of residual radioactivity deposited into the environment from the fallout of past nuclear weapons testing. The facts that lead to this conclusion are presented in Section 6.0. These facts include: effluent release totals for these isotopes show insufficient quantities to account for such measurements; Sr-89 and Cs-134 which are chemically similar and generally released in comparable quantities were not detected, and a trend since the early 1960's that shows a consistent declining presence of Cs-137 and Sr-90 in milk from Connecticut.

4-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 The 2010 results indicate no detectable 1-131 in this media. In the 1970's and 1980's low levels of plant related 1-131 were seen in some of these samples. However, for over 20 years, no plant related detectable levels of 1-131 have been seen in goat milk samples. The only other occasions where 1-131 was detected were fallout episodes from the Chinese Weapons Tests of the mid to late 1970's and Chernobyl Accident in 1986.

Goat milk was unavailable at all locations both early and later in the year. Per requirements, pasture grass or feed is collected as a substitute when milk is not available (see 4.9. Pasture Grass and Feed).

4.9 Pasture Grass and Feed (Table 9)

When the routine milk samples are unavailable, samples of pasture grass are required as a replacement. These samples may also be taken to further investigate the levels of radioactivity in milk. During the winter months and early spring, insufficient growth often prohibits sampling of pasture grass. Feed (e.g., hay or grain) is typically sampled whenever pasture grass is not available.

No station effects are noted in these samples. Cosmic produced Be-7 was observed in the majority of the pasture grass samples and many of the hay samples. Due to its relatively short half-life (52 days), it was not detected in the several of the "older" hay samples.

Naturally occurring K-40 was approximately two times higher in hay and feed compared to pasture grass samples. Cs-137 was only observed as positive in only one sample, at a level similar to previous years which have been attributable to residual fallout from weapons testing.

4.10 Well Water (Table 10)

These samples were discontinued in 1985, because no detectable station activity was ever observed in these samples. However, based upon lessons learned at other nuclear plants, including several undergoing decommissioning, sampling was resumed at several locations starting in the fourth quarter 2003. Three additional locations were added in 2005 to monitor potential leakage from the ISFSI. Due to the heightened sensitivity on this potential pathway, three more locations were added in 2006, five more in the summer of 2008 and two more in the Fall of 2010. One of the newer wells, location 86 (GPI 6 - inside the Unit 3 RCA between the Boron and Waste Test Tank berm and the Fuel Building) indicated a positive tritium (H-3) result (2310 +/- 250 pCi/liter) on August 28, 2008. This was the first sample from this new well. The temporary well located nearby also indicated positive levels (see 2008 Annual Radiological Environmental Operating Report and the 2008 Radiological Effluent Report) due to penetrations in the berm and a leaky pressure gauge for one of the Boron Recovery Tanks. The penetrations have been sealed and the pressure gauge repaired. The H-3 levels have since become undetectable at this location.

Location 80 (S12-MW-2) indicated a low level of H-3 (1660 +/- 880) on 6/21/10. Follow-up sampling on 8/5/10 and H-3 analyses of this and nearby wells did not indicate any positive H-

3. Subsequent September and December samples also did not indicate any positive levels of H-3. This and the above positive level were localized and transitory in nature; they were not indicative of any contamination in any drinking water supplies. Consistent with the past data, there were no other incidents of any station activity detected in these samples.

4-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 4.11 Meat (Table 11)

This is a new sample type initiated in December 2010. NRC Regulatory Guide 4.1 was revised (in 2009) to include evaluating the need for sampling and analysis of meat products.

Since deer are abundant in the area near Millstone and the land use census indentified significant consumption in the area, this sample type was added to the REMP. The results indicate expected levels of background. Although Cs-137 was identified, it is related to the types of food deer consume and the weapons testing fallout in these foods. Additional deer meat samples will be taken in 2011 at areas further from the plant to confirm this supposition.

4.12 Fruits and Vegetables (Table 12)

Consistent with past years, this media did not show any station effects. Naturally occurring K-40 was detected in all samples.

4.13 Broad Leaf Vegetation (Table 13)

Consistent with past years, this media did not show any station effects. Most samples had detectable levels of cosmic produced Be-7, at levels consistent with previous years. Similar to deer meat, pasture grass and feed, and milk, periodically these samples have indicated positive levels of Cs-137. Its cause is also the same; fallout from weapons testing has been widespread in terrestrial samples for many years.

This media can be an early and sensitive indicator of releases from the station for both unplanned releases and normal operations. Therefore, to enhance program-monitoring effectiveness, samples of broadleaf vegetation are collected monthly during the growing season, May - October, even though requirements are to collect this media twice a year.

4.14 Seawater (Table 14)

The guidance in Reference 15 specifies one sample upstream (control - beyond significant influence of the discharge) and one sample downstream (indicator - beyond but near the mixing zone) for surface water samples. Historically the downstream sample for Millstone has been located in the vicinity of discharge (location 32 - see Reference 8) which is prior to the mixing zone. This location was chosen since it was readily accessible by power and resistant to cold weather conditions. Operation of an automatic sampler at the indicator location is necessary for providing a representative sample. Although samples obtained at this location actually monitor the undiluted discharge activity, it provides for an excellent check on the radioactive effluent monitoring program. Any dose consequences can be assessed by usage of the appropriate dilution factors. It's not as necessary to have a continuous sampler at the control location due to the historical relative consistency noted in seawater background activity near the Millstone Site.

A technician collects an aliquot from the automatic sampler at Location 32 on a weekly frequency. These samples are composited for monthly analyses. In September 1999, Millstone increased the required analysis frequency for this composite sample to monthly to increase monitoring effectiveness. For the Control Location, Giant's Neck (Location 37C),

six weekly grab samples are obtained for quarterly compositing. In 2003, the LLD for H-3 (tritium) at the indicator location (32) was lowered by approximately a factor of four to further enhance the monitoring effectiveness. This lower LLD was continued through 2010.

4-7

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Naturally occurring K-40 was the only detectable gamma activity seen in several of these samples. Measured plant related levels of H-3 inseawater from the immediate vicinity of discharge (location 32) were observed in 7 of the 12 samples. This is similar to the frequency observed in 2008, more than the positives noted in 2007 and 2009. Although only Unit 3 experienced a refueling outage in the 2 nd quarter of 2010 (tritium releases are typically higher near these outages due to the need for increased liquid processing during these times), higher discharges also occurred in the 4 th quarter of 2010 because of the planned outage for Unit 2. As mentioned above, these samples are taken directly from liquid effluent flow prior to dilution into the Long Island Sound. Dilution studies performed for this discharge have determined that a dilution factor of 3 is appropriate to estimate concentrations immediately outside the quarry within a near-field area.

Tritium builds up in the reactor coolant during each fuel cycle. It is generated during plant operation from fission and neutron reactions. Between 1992 and 2002, H-3 was not typically detected. However, due to the enhanced detection sensitivity, H-3 levels are now often detected at the indicator location. Figure 4.14-1 shows an eighteen-year trend of H-3 releases in the Millstone liquid effluents versus the measured environmental concentrations from the vicinity of discharge location.

Sampling "undiluted discharge water" and analyzing to a "low H-3 LLD" enables a direct comparison of effluent monitoring to environmental monitoring for this exposure pathway.

Figure 4.14-2 (one year trend) and Figure 4.14-3 (five year trend) show this comparison.

This comparison is more accurate than Figure 4.1-1 since it takes into account the dilution flow during each month. Dilution flow can change substantially during plant outages. By plotting the data monthly, the resolution of the comparison is further enhanced. However, there are some slight discrepancies shown in Figure 4.14-2 due to the REMP samples being taken on Tuesdays which may not exactly coincide with the effluent measurement endpoint for the month.

Figure 4.14-1 H-3 Curies Released versus Seawater Concentration 18 Year Trend 1700 1600 isch Curiessd a~rg 1 _____

1500 3-1400

REMP pCi/liter 1300 - -

1200 11 00 I . . . . ........ ...

1000 -

900 700 300 200 100 .. .

M04) 0 O M M M0 M 0 M0 0 00 0 a 04 04 8 0 0 (0 a 0 00 (00) 0) a 4 a4 a 04 0 04 0 04 04a a4 a a4 a a4 a 0 a 04 a 04 a 0 04 a 0 a a4 a a4 a a 4-8

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 4.14-2 Seawater - H-3 Concentration REMP Samples vs. Effluent Measurements - 2010 1400 1200"-- REMP Samples

-Effluent Measurements 1000 200 Jan Feb Mar Apr May Jun Jul Aug Sep Oc t Nov Dec Figure 4.14-3 Seawater H-3 Concentration REMP Samples vs Effluent Measurements - 5 Year Trend 3000 2800 -EM Samples______________

2600 - Effluent Measurements 2400 2200 .... . .

2000 _

1800 1600 -

1400 _

1200O 8200 1000____ -

600 400 200 0 ~ ~~ ~ ~~~~~.. ... ..... N ~ ) 0 ) ) 0 ~ O 0 ) 0 )

(00

-, ~ (0 a) Z -

M 2

(0 0

Z M

, 2) ~

M

- 0 0 Z zd (0

W

(

Zz 0 ( 0 (CO 0

Z 4-9

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 4.15 Bottom Sediment (Table 15)

Typically Cs-137 is detected in samples from Golden Spur (67X). This year both samples did not indicate positive activity. Golden Spur is a fresh water area; levels of Cs-137 in previous years at this location were comparable to those observed in past river water sediments taken from other fresh water areas (e.g., the Connecticut River). Because of the relative distance and direction of the Golden Spur location from the station and comparable levels seen at other more distant river water locations, the historical levels of Cs-137 detected at Golden Spur were from weapons testing fallout. Similarly, in previous years Cs-137 was also detected in the extra samples from Jordon Cove Bar (39X). The levels the past two years have also decreased to below detectable. Prior to the last two years, the previous low levels likely exhibited some effect of the fresh water drainage from Jordan Brook.

Although Co-60 was noted in the previous year samples from Jordan Cove Bar, last year's downward trend continued; both 2010 samples did not indicate any positive Co-60. In any case, bottom sediment is not a significant dose pathway to man, especially at areas not typically used by the public. Analyses of other aquatic media, including seafood, sampled from near these locations (discussions that follow) do not show any detectable Co-60 or Cs-137.

A new sediment location was added in 2006 near the closest public beach (location 69X).

The data for this location has not indicated any plant related activity.

4.16 Aquatic Flora (Table 16)

Although sampling of this media is not required, it provides useful information since it is a very sensitive indicator of radioactivity in the environment. Low levels of activity (e.g., Mn-54, Co-58, Co-60, Zn-65, 1-131 and Ag-110m) have been detected in the past. Since 2000, levels have decreased to undetectable for all nuclides except for 1-131. Positive levels of I-131 were noted in 2004 - 2008. Seaweed has a significant bioaccumulation factor for iodine which makes it an extremely sensitive indicator of iodine in the environment.

Due to the positive 1-131 indications in 2004 and 2005, additional monitoring and studies were conducted in 2006. Extra samples were obtained at Thames River and Rocky Neck to determine if there may have been other sources for these very low levels of 1-131. These extra samples indicated the most likely cause for the 2004 - 2008 positive 1-131 results was the outfall from nearby wastewater (sewage) treatment plants. The usage of 1-131 in medical treatments is becoming more common and it is not unusual for it to be in the wastewater.

The New London Waste Water Treatment Plant is located on the west side of the Thames River near Fort Trumbull. Groton has two wastewater treatment plants, one located across the Thames River (and slightly upstream) from the New London treatment plant and the other near Bluff Point. The highest 1-131 results were in the samples from within the Thames River, which were taken near the outfall from the New London Waste Water Treatment Plant.

Beginning in 2006, a control location in the Thames River (90X) was added to better determine the influence of medical practices on the levels of 1-131 in aquatic flora. This location was the only one with detectable 1-131. There was no other activity detected in the flora samples. Therefore, based upon the above, no Station related radioactivity was detected in aquatic flora since 2000.

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 4.17 Fish (Tables 17A and 17B) 4.17.1 Flounder (Table 17A)

The activity in Flounder is the same as that seen for the past decade. No activity was observed except for the naturally occurring nuclides.

4.17.2 Fish - Other (Table 17B)

The activity in other fish is the same as that seen for the past decade. No activity was observed in this media except for naturally occurring nuclides, including samples taken from within the quarry.

4.18 Mussels (Table 18)

Similar to the last several years, this sampling media showed no station related radioactivity at all locations.

4.19 Oysters (Table 19)

All locations utilize oysters stocked in trays. The oysters used for stocking these trays have been obtained from Ram Island for the last several years. To confirm that the stocked oysters are not initially contaminated, the oysters from Ram Island are also analyzed. The stocked trays are kept at most of the sampling areas to guarantee samples and facilitate sample collection. Historically, native oysters were sampled at the quarry (location 40X),

which was an extra location. Due to safety concerns about diving operations, sampling at location 40X was suspended after obtaining the 2 nd quarter 2007 samples. Similarly, due to other safety concerns, location 32 was moved to a more accessible area in the middle of the quarry. Although it is labeled as vicinity of the discharge, it was previously located at the end of the quarry.

The only station related activity observed in these samples was Ag-i 1Om noted at location

32. This is typical for these samples obtained from this location. Although last year the levels decreased to below the detectable levels, a slight increase in liquid effluents caused all four samples to indicate positive Ag-1 1Om.

For several previous years, high levels of Zn-65 were observed in oysters. This was caused by their high capacity for accumulating zinc. Studies have shown that oysters can accumulate as much as 50 times or more the amount of zinc compared to most other seafood (Wolfe, 1979). A remarkable correlation existed between the Zn-65 concentration measured in the native quarry oysters and the amount of Zn-65 discharged into the environment. However, since the permanent shutdown of Millstone Unit 1 in 1996, the amount of Zn-65 in liquid effluents has decreased significantly. Starting in 2001, no Zn-65 has been detected in either the liquid effluents or in oysters. Figure 4.19-1, shows a historical trend that existed between Zn-65 releases and measured concentrations in quarry oysters.

The decreasing trend in effluent radioactive releases is apparent in both the curies released and the measured concentrations in oysters.

4-11

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 4.19-2 shows the trend of Ag-1 1Om concentration in quarry oysters compared to the liquid effluents discharged. Similar to Zn-65, the correlation between Ag-1 1Om discharged and the Ag-i 1Om concentration measured in the native quarry oysters is apparent. Section 5 provides for a comparison of doses based upon effluent measurements (method 1) to doses based upon environmental measurements (method 2). Per regulatory guidance (reference 7), the bioaccumulation factors for both Zn and Ag were adjusted based upon several years of historical data to account for the higher measured uptakes. These adjustments have typically shown good agreement between the two methods, with method 1 usually being conservative. The 2006 and 2007 data indicate an unusual trend (see Section 5, Table 5-2).

Method 2 (REMP dose assessment) indicates higher doses than method 1 (effluent dose assessment). Due to significant effluent reductions over the last several years, the low resulting doses (less than 0.01 mrem) make this comparison difficult and subject to significant error. Trending of these comparisons is routinely performed and adjustments are made, when appropriate.

The location of the quarry is on-site and not available for public use. No station activity was observed at locations beyond the station discharge area. Therefore, the actual concentration of the nuclides in oysters available for public consumption is much less than the levels found inside the quarry. The near-field dilution factor for liquid discharges from the Millstone quarry discharge is a factor of 3. The dose consequence of the station related radioactivity via this pathway is discussed in Section 5.0.

4.20 Clams (Table 20)

Occasionally this media indicates the presence of station related radioactivity. No station related radioactivity was observed in any of the clam samples taken in 2010.

4.21 Scallops (Table 21)

Scallops are not required by the REMP. However, attempts are made to sample this media to confirm station effects because scallops could be available for public consumption. No scallop samples have been available for several years.

4.22 Lobsters (Table 22)

Like the last several years, no station related radioactivity was detected in this sample media in 2010.

4-12

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 4.19-1 Figure 4.19-1 Zn-65 COMPARISON Curies Curies Discharged vs. Native Oyster Concentration pCi/gram 0.1 100

-- Curies Discharged l

- Oyster Conc.

0.01 10 0.001 1 0.0001 0.1 1E-05 ___ 0.01 1E-06 - -0.001 0N 0 0 0 0 0- 0 aa a a a Quarter Figure 4.19-2 Ag-110m COMPARISON Curies Discharged vs. Native* Oyster Concentration Curies pCi/gram 0.1 -

JYVAA I

0.1

-- i-Curies Discharged

-a-Oyster Conc.

100 0.01 -10 V

0.001 1 0.0001 0.1 I E-05 0,01 IE-06 0.001 0 0 0 0 0 0 0 0 0 0 0) 0 0 0 0 0 0 0 00 0 Quarter

Native oysters until 3Q 2007; because of diver safety issues now the only oysters sampled in the Quarry are stocked in trays similar to what has historically been performed at all the other locations.

4-13

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

5. OFFSITE DOSE EQUIVALENT COMMITMENTS The off-site dose consequences (dose equivalent commitments) of the station's radioactive liquid and airborne effluents have been evaluated using two methods.

The first method utilizes calculations of direct dose from sources onsite and the station's measured radioactive discharges as input parameters into conservative models to simulate the transport mechanism through the environment to man. This results in the calculation of the maximum dose consequences to individuals. The results of these computations have been submitted to the NRC in the Radioactive Effluent Release Report written in accordance with the Radiological Effluent Monitoring and Offsite Site Calculation Manual,Section I.F.2. This method, which is usually conservative (i.e., computes higher doses than that which actually occur), has the advantage of approximating an upper bound to the dose consequences. This is important in those cases where the actual dose consequence cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques.

The second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., fish, shellfish) and then computes the dose consequences resulting from the consumption of these foods.

The results of both methods are compared in Table 5.1 for those pathways where a potential dose consequence exists and a comparison is possible. The doses presented in this table are calculated at the location of maximum effect from the station effluents for that pathway and for the critical age group. For example, the external gamma dose from gaseous effluents is calculated for the site boundary location which is not only the nearest but also has the greatest directional wind frequency and fish and shellfish doses are calculated assuming they are from an area within 500 feet of the station discharge.

Summarizing the data in Table 5.1:

MAXIMUM TOTAL INDIVIDUAL DOSES: WHOLE BODY = 0.52 mrem Bone = 0.80 mrem Thyroid = 0.44 mrem The majority of the whole body dose is due to the calculated dose from the estimated Carbon 14 airborne emissions. Another significant contributor is the conservative determination of dose (=0.19 mrem) to the nearest resident as a result of direct radiation from on-site radioactive waste operation/storage facilities and continuous occupancy. The bone dose is essentially all attributable to the airborne pathway based upon Method 1. The thyroid dose is also based upon conservative assessments using Method 1. Since the maximum dose consequence to an individual is at the location of highest dose consequence, doses will be less for all other locations. The average whole body dose to an individual within 50 miles historically is on the order of 1000 times less than the maximum individual whole body dose.

In order to provide perspective on the doses in Table 5.1, the standards on the allowable maximum dose to an individual of the general public are given in 40CFR1 90 as 25 mrem whole body, 75 mrem thyroid, and 25 mrem to any other organ. These standards are a fraction of the normal background radiation dose of approximately 311 mrem per year and are designed to be inconsequential in regard to public health and safety. Since station related doses are even a smaller fraction of natural background, they have insignificant public health consequences. In fact, the station related doses to the maximum individual are less than 10% of the variation in natural background.

5-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS MILLSTONE POWER STATION 2010 Annual Dose (millirem)

Airborne Effluents

1. External Gamma Dose Max (2) Whole Body 0.0000 0.00025 0.00292 0.0032 NDo)

(gamma air) (8)

2. Whole Body Dose Max (2 ) Whole Body 0.00036 0.177 0.130 0.308 ND (internal and external)

3. Inhalation, vegetables and Max (2 ) Thyroid 0.00036 0.178 0.242 0.421 ND goat milk

4. Inhalation, vegetables and Max( 2 ) Max Organ 0.00044 0.884 0.613 1.50 ND goat milk Direct Dose Nearest Residence Max(2) Whole Body N/A N/A N/A _0. 19(4 <1.8(5,8) 5-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE 5.1 (Cont.)

COMPARISON OF DOSE CALCULATION METHODS MILLSTONE POWER STATION 2010 Annual Dose (millirem)

Max Method 1(1) Method 2(1)

Pathway Individual Organ Unit 1 Unit 2 Unit 3 Station Station (BWR) (PWR) (PWR) Total Liquid Effluents

1. Fish

Adult Whole Body 0.00000013 0.000156 0.000549 0.000705 ND(3)

Teen 0.00000007 0.000125 0.000415 0.000540 Child 0.00000003 0.000112 0.000341 0.000453

Adult Gl(LLl),6) 0.00000000 0.002146 0.001895 0.00404 ND Teen 0.00000000 0.001500 0.001373 0.00287 Child 0.00000000 0.000566 0.000597 0.00116 Adult Liver 0.00000020 0.000211 0.000838 0.00105 ND

Teen 0.00000021 0.000190 0.000803 0.00099 Child 0.00000019 0.000169 0.000721 0.00089

2. Shellfish

Adult Whole Body 0.00000002 0.000078 0.000257 0.000335 0.00001517, Teen 0.00000001 0.000073 0.000239 0.000312 0.000016 Child 0.00000000 0.000081 0.000270 0.000351 0.000017

Adult GI(LLI) 0.00000000 0.006860 0.001254 0.00811 0.0106 Teen 0.00000000 0.004714 0.000903 0.00562 0.00725 Child 0.00000000 0.001691 0.000366 0.00206 0.00258 Adult Liver 0.00000003 0.000155 0.000617 0.00772 0.000026

Teen 0.00000003 0.000155 0.000636 0.00791 0.000026 Child 0.00000003 0.000150 0.000627 0.00777 0.000022 5-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Notes:

1. Except for direct dose, method 1 uses measured station discharges and meteorological data as input parameters to transport-to-man models that conservatively calculate dose to people; method 2 uses actual measured concentrations in environmental media to estimate the dose.

2. Maximum individual - The maximum individual dose is the dose to the most critical age group at the location of maximum concentration of station related activity. The dose to the average individual is much less than the maximum individual dose.

3. ND - Not Detectable - No station related activity could be detected above natural background or above the minimum detectable level (MDL).

4. The dominant source of direct dose from the station is from storage and movement of radioactive waste. Storage of radioactive waste is allowed in several areas onsite.

Operation of the storage facilities is limited by design to ensure that the maximum direct dose at the site boundary from each area does not exceed one millirem. Actual exposure throughout the year was maintained much less than this operational limit. Each facility is monitored onsite by the Radiation Protection Department using TLDs. The exposure measured for each facility TLD was corrected for distance to the nearest site boundary residence. The resultant exposure was conservatively multiplied by 1.5 to account for sky-shine. These maximum estimated doses from each facility were summed for a cumulative site commitment of approximately 0.19 millirem. The whole body dose from airborne effluents was 0.31 and from liquid effluents was 0.0012 (seafood consumption, swimming & boating and shoreline recreation dose total). This results in a total estimated whole body dose to the maximum individual of 0.50 mrem (0.19 + 0.31 + 0.0012).

5. Measured dose was derived from monthly TLD readings. There are two residences that qualify as the closest residence; each has a TLD near enough to use as an estimate to each residence. The one with the highest average dose rate was used to estimate the direct dose to the closest residence. A background dose rate was subtracted. This background was derived from the average of the five control TLD locations. This method is very conservative assuming natural exposure influences, such as granite, are actually plant related exposure. This method provides a bounding high value. The exposure measurements of the select indicator locations are influenced by natural background exposure differences caused by the many granite out-croppings typical of the Millstone area. Historical data has shown that TLD sample locations in the vicinity of granite can be dramatically influenced by natural radioactivity contained within the granite.

6. GI (LLI) - Gastrointestinal Tract - Lower Large Intestine.

7. Based on measured levels in the quarry oysters. A measured near field dilution factor of 3 was used to adjust for the fact that these oysters are on-site and inaccessible to the public. This factor adjusts the measured on-site concentration to that which could occur to a public accessible off-site location after dilution of the effluent by the Long Island Sound. The measured levels in the stocked oysters within the quarry were about one-half the native quarry oysters. For conservatism, it was assumed the maximum individual consumed primarily oysters (activity in clams was much lower than in the oysters).

8. Based upon conservatively assuming no correction for building shielding and occupancy.

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Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

6. DISCUSSION The evaluation of the effects of station operation on the environment requires the careful consideration of many factors. Those factors depend upon the media being affected. They include station release rates, effluent dispersion, occurrence of nuclear weapons tests, seasonal variability of fallout, local environment, and locational variability of fallout.

Additional factors affecting the uptake of radionuclides in milk include soil conditions (mineral content, pH, etc.), quality of fertilization, quality of land management (e.g., irrigation),

pasturing habits of animals, and type of pasturage. Any of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions.

Consider, for example, the problem of deciphering the effect of station releases on the radioactivity measured in milk samples. This is an important issue because this product is widely consumed and several fission products readily concentrate in this media. Some of these fission products, such as 1-131 and Sr-89 are relatively short-lived. Therefore they can result from station effluents, nuclear weapons tests or nuclear incidents (e.g. Chernobyl).

Sr-89's lifetime is longer than 1-1 31's, therefore it will remain around for much longer periods of time. The even longer-lived fission products, Sr-90 and Cs-137, cause more of a concern.

These isotopes are still remaining from the weapons testing era of the 1960's. This results in measurable amounts of Sr-90 and Cs-137 appearing in some milk samples. Distinguishing between this "background" of fallout activity and station effects is of prime interest for a Radiological Environmental Monitoring Program.

In reviewing the historical and present Sr-90 and Cs-137 measured in cow and goat milk in the areas around Millstone station, a casual observer could notice that in some cases the levels of these isotopes are higher at farms closer to the station than at those further away from the station. The station's effluents might at first appear to potentially be responsible.

However, the investigation of the following facts proves this conclusion wrong.

(1) The stations accurately measure many fission products, including Sr-90 and Cs-137 in their releases. Based on these measurements and proven models developed by the Nuclear Regulatory Commission, concentrations in the environment can be calculated.

These calculations (generally conservative, see Section 5.0) show that insufficient quantities of Sr-90 and Cs-137 have been released from the plants to yield the measured concentrations in milk.

(2) Over the many years of station operation, Sr-89 has often been released in comparable quantity to Sr-90. Since they are chemically similar, comparable levels should have been detected in milk if the Sr-90 was station related. No station related Sr-89 has ever been detected in milk samples.

(3) Similar to Sr-89, Cs-1 34 can be used as an indication of station related Cs-1 37. Although not as conclusive as Sr-89, the lack of any measurable Cs-1 34 in any of the milk samples suggests that the Cs-137 is not station related. This is further confirmed by the evaluation of the air particulate data. The only occurrences of detectable Cs-134 in milk resulted from the Chernobyl incident.

(4) Dairy milk sampling in Connecticut began in the 1960's, several years prior to nuclear station operation. The highest levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and 6-2), were measured in the years prior to station operation. Samples taken in the immediate station areas have always shown higher levels of weapons related fallout than samples taken from the Central Connecticut Region (CT Pooled Milk).

Radioactivity levels of fallout related Sr-90 and Cs-1 37 have decreased significantly since the 1964 Nuclear Test Ban Treaty due to decay.

6-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 (5) Local variability of Sr-90 and Cs-137 in milk is common throughout the United States.

Due to the variability in soil conditions, pasturing methods, rainfall, etc., it is the rule rather than the exception. Therefore, it is not surprising that certain farms have higher levels of radioactivity than other farms. In fact, in the past there are some cases where the farms further from the station have higher Sr-90 and Cs-137 values than the farms that are closer to the station.

(6) In the past when a goat farm operated near Millstone (2.0 Mi - ENE), the highest levels of Sr-90 and Cs-1 37 were typically indicated. This same farm also experienced the highest levels of short-lived activity from the 1976 and 1977 Chinese Tests and the 1986 Chernobyl accident. This indicates that for some unknown reason this farm had the ability for higher reconcentration. Special studies performed at this and other farms failed to find any link to the station.

Based on these facts, the observation that the station effluents are responsible is evidently false. The cause must be one or more of the other variables.

Dominion has carefully examined the data throughout the years and has presented in this report all cases where station related radioactivity could be detected. An analysis of the potential exposure to the maximum individual from any station related activity has been performed and shows that in all cases the exposure is insignificant.

The Connecticut Department of Environmental Protection (DEP) performs an independent check on certain environmental program analyses. The results of their analyses are comparable to the results from this program's analyses. These comparisons can be used as a cross-reference to verify measured station activity. DEP performed a comprehensive review of all the historical Millstone data in 2006 (reference 17). It concluded that "the collective sampling in and around Millstone Power Station show expected levels of residual fallout from weapons testing and the Chernobyl event and are unrelated to the operation of the Millstone Power Station."

Figure 6-1 Strontium-90 in Milk pCi/liter 25

-- CT Pooled Milk 20 _ __ Haddam area Milk 15 Millstone area Milk 15 61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 99 Year 6-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Figure 6-2 Cesium-137 in Milk pCi/liter 160 7 140 CT Pooled Milk 120 -- W- Haddam area Milk I -A Millstone area Milk 100 1ý 80 60 40 20 0

61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 99 Year Dairy milk is no longer available in the Millstone area, Haddam Neck no longer collects milk, and CT Pooled milk has not been collected by the State of CT since 1994. Graphs provided to show historical trends.

CY Start-up occurred: July 24,1967 MP2 Start-up occurred: December, 1975 MI1 Start-up occurred: October 26, 1970 MP3 Start-up occurred: April, 1986 6-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010

7. REFERENCES

1) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix A Criteria 64.

2) Donald T. Oakley, "Natural Radiation Exposure in the United States." U. S.

Environmental Protection Agency, ORP/SID 72-1, June 1972.

3) National Council on Radiation Protection and Measurements, Report No. 160, "Ionizing Radiation Exposures of the Population of the United States," March 2009.

4) National Council on Radiation Protection and Measurements, Report No. 94, "Exposure of the Population of the United States and Canada from Natural Background Radiation,"

December 1987.

5) United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instructions Concerning Risks from Occupational Radiation Exposure," Revision 0, July 1981.

6) Millstone Training Brochure.

7) United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

8) Millstone Power Station Radiological Effluent Monitoring and Offsite Dose Calculation Manual, Revision 025-02, December 2006.

9) United States of America, Code of Federal Regulations, Title 10, Part 20.1301.

10) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix I.

11) United States of America, Code of Federal Regulations, Title 40, Part 190.

12) United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Program for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.

13) ICN/TracerLab, "Millstone Nuclear Power Station Pre-operational Environmental Radiation Survey Program, Quarterly Reports," April 1967 to June 1970.

14) International Commission of Radiological Protection, Publication No. 43, "Principles of Monitoring for the Radiation Protection of the Population," May 1984.

15) United States Nuclear Regulatory Commission, NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," April 1991.

16) United States Nuclear Regulatory Commission, Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

17) Reassessment of Millstone Power Station's Environmental Monitoring Data, Connecticut Department of Environmental Protection, Division of Radiation, March 2006.

18) NRC Regulatory Guide 4.1, Radiological Environmental Monitoring for Nuclear Power Plants, Revision 2, June 2009.

7-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 APPENDIX A LAND USE CENSUS FOR 2010 A-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 INTRODUCTION The annual land use census in the vicinity of Millstone Station was conducted as required by the Millstone REMODCM between July 15 and December 31, 2010. Typically the cow milk locations are identified by a review of the annual registration information obtained from the State of Connecticut Department of Agriculture. Gardens are located by a drive-by during the harvest season. Although broadleaf sampling was performed and may be used in lieu of a garden census, gardens were included in the 2010 census. Only vegetable gardens having an area of more than 500 square feet need to be identified. In order to reduce some of the conservatism of the dose modeling, a more detailed census was initiated in 2010 to identify locations of fruits and meats. Due to the difficulty of measuring individual gardens, the nearest garden within each directional sector identified by a drive-by survey is listed.

Goat locations are more difficult to determine, but best efforts are made to consult goat association records, contact previous owners and or drive-bys, if necessary.

RESULTS Tables A-1 through A-3 indicate information from the latest land use census. No new dairy animals within 10 miles of the Station were located during the census. Several changes were identified, these include:

Several locations changed since the distances were more accurately determined

several new dairies were identified in the 10 to 20 mile range (see Table A-i)

" several new gardens were identified

fruit and meat locations were identified These changes indicate that no changes were required in the current sampling locations.

However, due to the interest in obtaining more milk samples, a farm approximately 10.5 miles from the site will be considered for 2011. The dose modeling incorporates the above listed changes.

A-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE A-1 Dairy Cows Within 20 miles of Millstone Point - 2010 Direction Distance (Miles) Location N 15 Norwich N 18 Bozrah N 19 Norwich N 19.5 North Franklin N 19.5 Franklin N 19.5 North Franklin NNE 15 Preston NNE 16 Preston NNE 16 Preston NNE 16.5 Norwich NNE 17.5 Preston NNE 18 Preston NNE 18 Preston NE 13.5 Ledyard NE 13.5 Ledyard NE 14.5 Ledyard NE 14.5 North Stonington NE 14.5 Preston NE 19 North Stonington NE 19 North Stonington ENE 18 North Stonington WNW 10.5 Lyme NW 10.5 Lyme NW 12.5 Salem NW 15 Moodus NNW 12 Salem NNW 19.5 Lebanon NNW 19.5 Lebanon Note: None of these cow farms are used for sampling since all farms are greater than ten miles from plant (NUREG 1301, Reference 15, uses a cutoff distance of 5 miles)

A-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE A-2 Dairy Goats Within 20* miles of Millstone Point- 2010 Direction Distance (Miles) Location (Sample Location)

N 2.1 Waterford (LOCATION 21)**

N 11 Oakdale NE 2.8 Waterford (LOCATION 22)***

ENE 12 Stonington ENE 13 Stonington WNW 18 Haddam NW 17 East Haddam NNW 12 Salem NNW 18 Colchester NNW 21 Colchester NNW 29 Hebron (LOCATION 24)

and beyond for potential control locations

- primarily for cheese, occasionally milk for drinking not milking, raised for meat only, pigs also at this location A-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE A-3 2010 Resident/Garden/Meat Survey Closest Distance Downwind Resident Garden Fruit Meat Source Direction miles meters miles meters miles meters miles meters N 0.97

1,570 0.97

1,550 1.9 2,980 NNE 0.53

850 0.55

890 12 19,750 SB SB NE 0.47

760 0.50

800 12 19,830 SB SB ENE 0.99

1,600 0.96 ** 1,550 9.6 15,510 E 0.90

1,450 0.90 ** 1,450 ESE 1.1

1,700 1.2 1,970 SE N/A N/A N/A N/A N/A N/A N/A N/A SSE N/A N/A N/A N/A N/A N/A N/A N/A S N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A SW 2.3

3,680 2.3* 3,760 WSW 2.0* 3,300 2.3* 3,670 W 1.9" 3,030 1.8" 2,940 11 17,830 1.7

WNW 1.6" 2,540 2,810 5.3 8,450 NW 0.52

840 1.4* 2,210 5.5 8,770 10.4 16,800 NNW 0.51

820 0.76

1,220

distances have been recalculated

- new location for 2010 SB deer (meat) at Site Boundary N/A not applicable (over water sectors)

- no locations found A-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 APPENDIX B DNC QA PROGRAM B-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 INTRODUCTION Dominion Nuclear Connecticut (DNC) maintains an independent non-required quality assurance (QA) program as part of the radiological environmental monitoring program (REMP). The QA program consists of contractor appraisals and quality control samples.

This independent program is applicable to all Dominion nuclear facilities because they share a joint contract with Teledyne Brown Engineering Laboratory.

DNC QA PROGRAM The DNC independent QA Program includes spikes of various sample media and duplicate samples. Sample spikes are a check on the accuracy of results of the contractor's radioanalyses. Duplicate samples test the contractor's precision, or reproducibility of results, by comparing analytical results of split samples. The number and type of DNC QA Program quality control samples are defined in Millstone Nuclear Power Station Procedure REMP 1.4, "Quality Control of Radiological Environmental Monitoring Program." An investigation is conducted on any result or trend that does not satisfy acceptance criteria.

OTHER QA PROGRAMS The DNC Independent QA Program is not the only QA Program which monitors REMP radioanalysis performance. Other programs include:

1. Contractor lab's internal QA program. In addition to the Millstone quality control samples, the radioanalysis contractor has its own quality control samples. In total, at least five percent of the contractor's sample analyses include quality control samples.

2. Contractor lab's interlaboratory comparison program with an independent third party, Eckert & Ziegler Analytics, Inc. Results of the Eckert & Ziegler Analytics intercomparison are contained in Appendix C. Primary contractor participation in an interlaboratory comparison program is required by station Technical Specifications. The Eckert & Ziegler Analytics comparison satisfied this requirement for AREVA-NP.

3. Contractor labs also participate in the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (PT) Program, the Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte performance Evaluation Program (MAPEP). Laboratories typically participate in these interlaboratory QA programs because of other clients' needs, not because of nuclear power station environmental sample analyses. However, several of these intercomparison samples are also applicable to nuclear power environmental samples. Teledyne Brown Engineering's participation in the Eckert & Ziegler Analytics and the other programs listed above satisfy the interlaboratory comparison program as required by station Technical Specifications.

RESULTS OF DNC QA PROGRAM FOR CONTRACTOR RADIOANALYSES Criteria for passing QA sample analysis is that the result be within 20% of the known spike except in the case of Sr-89 or Sr-90 spikes in milk which have to be within 30% of the known spike. To allow more tolerance for lower activity spikes the following alternate criterion may be used: If the two sigma error range of the analyzed result includes the known spike value the result passes.

B-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Opemting Report Millstone Station 2010 Table 1 lists the numbers of QC and routine samples for various sample media for 2009.

The results of the QC samples are shown on Table 2. All of the TLD spike tests satisfied the procedural criteria. Of the 54 individual nuclide analysis results on QA samples, 6 need to be discounted because the tape was removed from the spiked filters, causing a significant loss of activity from the filters. Of the remaining 48 spikes, 44 passed the acceptance criteria, a 91.7% success rate. Of the 2 Sr-90 in milk failures, one was low by 22 % and the other low by 30%. However, both also indicated false positives for Sr-89 and there was a sample control issue. The 2 Cs-137 spikes on air particulate filters were high by 21-23 %

(just outside the acceptance criteria and conservative). Based upon investigation of the results for these spikes, the Millstone QA Program indicated that the contractor lab's environmental radiological analysis program was adequate in 2010.

TABLE 1 2010 QUALITY CONTROL SAMPLES SAMPLE TYPE QC SAMPLES (Note 1) ROUTINE SAMPLES TLD Spike 16 160 Milk - Strontium 2 6 Milk - Iodine 0 -30 Milk - Gamma (Note 2) -30 Pasture Grass/Hay - Gamma (Milk 0 -30 Substitute)

Water - Gamma 6 60 Water - Tritium 4 60 Fish/Invertebrate - Gamma 4 80 Vegetation/Aquatic Flora/Sediment/Soil - 0 74 Gamma Air Particulate - Gross Beta 6 416

- Iodine 0 416

- Gamma 2 32 FOOTNOTES (Table 1):

1. All samples are spikes except fish/invertebrate which are duplicate oyster samples.

2. Gamma in water QA spikes are treated as milk surrogates.

B-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE 2 RESULTS OF 2010 QUALITY CONTROL SAMPLE ANALYSES*

SAMPLE TYPE ANALYSES PASSED ANALYSES FAILED TLD Spike 16 0 Milk - Strontium 0 2 (Note 1)

Milk - Iodine 0 0 (Note 2)

Water - Gamma 30 0 Water - Tritium 4 0 Oysters - Gamma 4 0 Air Particulate - Gross Beta 6 6 (Note 3)

- Iodine 0 0 (Note 2)

- Gamma 10 2 (Note 4)

TOTALS TLDs: 16 TLDs: 0 Individual Nuclides: 54 Individual Nuclides: 10 FOOTNOTES (Table 2):

To provide a more detailed comparison of pass versus failure, each nuclide was considered for the gamma and strontium analyses,

1. One Sr-90 spike low just above the 30% cutoff, however false positives of Sr-89 indentified on both samples and sample control issue also noted - CR generated by vendor to investigate issue.

2. Due to the difficulty of obtaining an 1-131 spike, none of these samples were spiked

3. Results originally low by 20 - 45%; samples typically covered with tape to insure spike is retained on the samples. Teledyne personnel mistakenly removed the tape which resulted in a low bias on the analyses.

4. High by 21 - 23% (just outside the 20% acceptance criteria) - no action necessary.

B-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 APPENDIX C

SUMMARY

OF INTERLABORATORY COMPARISONS C-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 INTRODUCTION This appendix covers the Intercomparison Program of the AREVA-NP Environmental Laboratory and Teledyne Brown Engineering Laboratory as required by technical specifications for each Millstone unit. AREVA-NP uses QA/QC samples provided by Eckert

& Ziegler Analytics to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP). The suite of Eckert & Ziegler Analytics QA/QC samples are designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides. It was modified to more closely match the media mix presently being processed by AREVA-NP and includes:

o milk for gamma (10 nuclides) and low-level (LL) Iodine-1 31 analyses once per quarter

" water for gamma (10 nuclides) and low-level (LL) lodine-131 analyses during the 1st and 3rd quarters

water for Sr-89 and Sr-90 analyses during the 1st and 4th quarters

water tritium analysis during the 2nd and 4th quarters

air filter for gamma (9 nuclides) analyses during the 2nd quarter

" air filter for gross beta analysis during the 1st and 3rd quarters o charcoal filter for 1-131 during the 1st and 3rd quarters

air filter for Sr-89 and Sr-90 analyses during the 2nd and 4th quarters In addition to the Eckert & Ziegler Analytics Intercomparison Program, AREVA-NP also participates in other intercomparison programs which include radionuclides and media similar to those required by the Millstone program. These programs are the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (PT) Program, the Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP).

Teledyne Brown Engineering Laboratory also uses QA/QC samples provided by Eckert &

Ziegler Analytics and the other intercomparison programs listed above. Since Teledyne's participation in the Eckert & Ziegler Analytics is not as intensive as AREVA's, the results from the other programs are reviewed and shown on the following tables.

RESULTS Intercomparison program results are evaluated using each laboratory's internal bias acceptance criterion. The AREVA-NP criterion is defined as within 25% of the known strontium value for samples containing both Sr-89 and Sr-90 and within 15% of the known value for other radionuclides, or within two sigma of the known value. Teledyne Brown's criteria is similar for the Analytics samples but uses a range for the other QC samples. Any sample analysis result which does not pass the criteria is investigated by each laboratory.

AREVA-NP Intercomparison Program results are included on pages C-4 through C-6 for 2010. Since the Fourth Quarter Analytics results are not usually available until mid April, the previous year's results are listed for AREVA-NP. Teledyne Brown Engineering Intercomparison Program results are included on pages C-7 through C-9 for the second half of 2010.

C-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 A total of 110 analysis results were obtained by AREVA-NP with 108 passing the acceptance criteria, a 98% success rate. The low bias for gross alpha on a water sample (E6908-162) and the high Sr-90 on a milk sample (E7012-162) were investigated by AREVA. Gross alpha analyses are not performed on any Millstone REMP samples.

A total of 112 analysis results were obtained by Teledyne Brown Engineering with 100 passing the acceptance criteria, a 89% success rate. Of these 12, 7 were false positives (conservative results) and the remaining 5 were on transuranic analyses (not routine REMP analyses).

CONCLUSION The QC results indicate that both laboratories are providing quality analytical analyses.

C-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 AREVA NP ENVIRONMENTAL LABORATORY ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION RATIO SAMPLE SAMPLE REPORTED KNOWN RAT QUARTER/

NUMBER MEDIA VALUE VALUE ANAL YEAR ANALYTICS 4th/2009 E6908-162 Water Gross Alpha pCi/L 2.14E+02 2.58E+02 0.83 4th/2009 E6908-162 Water Gross Beta pCi/L 2.30E+02 2.30E+02 1.00 4th/2009 E6909-162 Water 1-131LL pCi/L 9.56E+01 9.61E+01 0.99 4th/2009 E6909-162 Water 1-131 pCi/L 9.95E+01 9.61E+01 1.04 4th/2009 E6909-162 Water Ce-141 pCi/L 2.04E+02 2.04E+02 1.00 4th/2009 E6909-162 Water Cr-51 pCi/L 5.85E+02 5.54E+02 1.06 4th/2009 E6909-162 Water Cs-134 pCi/L 2.33E+02 2.55E+02 0.91 4th/2009 E6909-162 Water Cs-137 pCi/L 1.90E+02 1.81E+02 1.05 4th/2009 E6909-162 Water Co-58 pCi/L 2.19E+02 2.13E+02 1.03 4th/2009 E6909-162 Water Mn-54 pCi/L 1.90E+02 1.79E+02 1.06 4th/2009 E6909-162 Water Fe-59 pCi/L 1.94E+02 1.79E+02 1.08 4th/2009 E6909-162 Water Zn-65 pCi/L 3.60E+02 3.48E+02 1.03 4th/2009 E6909-162 Water Co-60 pCi/L 2.58E+02 2.58E+02 1.00 4th/2009 E6910-162 Water Sr-89 pCi/L 9.26E+01 1.11E+02 0.83 4th/2009 E6910-162 Water Sr-90 pCi/L 1.27E+01 1.53E+01 0.83 4th/2009 E6911-162 Water H-3 pCi/L 1.41E+04 1.40E+04 1.01 4th/2009 E6912-162 Charcoal 1-131 pCi 8.73E+01 9.03E+01 0.97 4th/2009 E6913-162 Filter Gross Alpha pCi 1.21E+02 1.29E+02 0.94 4th/2009 E6913-162 Filter Gross Beta pCi 1.27E+02 1.15E+02 1.10 4th/2009 E6914-162 Filter Ce-141 pCi 1.09E+02 1.13E+02 0.97 4th/2009 E6914-162 Filter Cr-51 pCi 3.08E+02 3.05E+02 1.01 4th/2009 E6914-162 Filter Cs-134 pCi 1.35E+02 1.40E+02 0.96 4th/2009 E6914-162 Filter Cs-137 pCi 1.05E+02 9.95E+01 1.05 4th/2009 E6914-162 Filter Co-58 pCi 1.20E+02 1.17E+02 1.02 4th/2009 E6914-162 Filter Mn-54 pCi 9.90E+01 9.87E+01 1.00 4th/2009 E6914-162 Filter Fe-59 pCi 9.65E+01 9.87E+01 0.98 4th/2009 E6914-162 Filter Zn-65 pCi 1.90E+02 1.92E+02 0.99 4th/2009 E6914-162 Filter Co-60 pCi 1.34E+02 1.42E+02 0.94 4th/2009 E6915-162 Milk 1-131LL pCi/L 8.97E+01 8.73E+01 1.03 4th/2009 E6915-162 Milk 1-131 pCi/L 8.75E+01 8.73E+01 1.00 4th/2009 E6915-162 Milk Ce-141 pCi/L 2.09E+02 2.02E+02 1.03 4th/2009 E6915-162 Milk Cr-51 pCi/L 5.56E+02 5.48E+02 1.01 4th/2009 E6915-162 Milk Cs-134 pCi/L 2.35E+02 2.53E+02 0.93 4th/2009 E6915-162 Milk Cs-137 pCi/L 1.91E+02 1.79E+02 1.07 4th/2009 E6915-162 Milk Co-58 pCi/L 2.22E+02 2.11E+02 1.05 4th/2009 E6915-162 Milk Mn-54 pCi/L 1.87E+02 1.78E+02 1.05 4th/2009 E6915-162 Milk Fe-59 pCi/L 1.92E+02 1.78E+02 1.08 4th/2009 E6915-162 Milk Zn-65 pCi/L 3.59E+02 3.45E+02 1.04 4th/2009 E6915-162 Milk Co-60 pCi/L 2.57E+02 2.56E+02 1.01 C-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 AREVA NP ENVIRONMENTAL LABORATORY ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION QUARTER/ SAMPLE SAMPLE NUCLIDE UNITS REPORTED KNOWN RATIO AREVA/

YEAR NUMBER MEDIA VALUE VALUE ANALYTICS lst/2010 E7010-162 Water Gross Alpha pCi/L 154 156 0.99 lst/2010 E7010-162 Water Gross Beta pCi/L 287 293 0.98 lst/2010 E7011-162 Water 1-131LL pCi/L 68.4 72.2 0.95 lst/2010 E7011-162 Water 1-131 pCi/L 73.5 72.2 1.02 Ist/2010 E7011-162 Water Ce-141 pCi/L 248 263 0.94 lst/2010 E7011-162 Water Cr-51 pCi/L 336 364 0.92 lst/2010 E7011-162 Water Cs-134 pCi/L 158 179 0.88 lst/2010 E7011-162 Water Cs-137 pCi/L 156 159 0.98 lst/2010 E7011-162 Water Co-58 pCi/L 136 144 0.94 lst/2010 E7011-162 Water Mn-54 pCi/L 200 209 0.96 lst/2010 E7011-162 Water Fe-59 pCi/L 144 138 1.04 lst/2010 E7011-162 Water Zn-65 pCi/L 255 256 1.00 lst/2010 E7011-162 Water Co-60 pCi/L 177 185 0.96 lst/2010 E7012-162 Water Sr-89 pCi/L 74.5 89.8 0.83 lst/2010 E7012-162 Water Sr-90 pCi/L 20.1 12.3 1.63 lst/2010 E7013-162 Water H-3 pCi/L 11,700 12,000 0.97 lst/2010 E7014-162 Charcoal 1-131 pCi 84.1 85.7 0.98 lst/2010 E7015-162 Filter Gross Alpha pCi 92.9 102 0.91 lst/2010 E7015-162 Filter Gross Beta pCi 218 191 1.14 lst/2010 E7016-162 Milk 1-131LL pCi/L 71.0 74.0 0.96 lst/2010 E7016-162 Milk 1-131 pCi/L 80.6 74.0 1.09 lst/2010 E7016-162 Milk Ce-141 pCi/L 273 261 1.04 lst/2010 E7016-162 Milk Cr-51 pCi/L 368 361 1.02 lst/2010 E7016-162 Milk Cs-134 pCi/L 166 178 0.94 lst/2010 E7016-162 Milk Cs-137 pCi/L 171 158 1.09 lst/2010 E7016-162 Milk Co-58 pCi/L 151 143 1.06 lst/2010 E7016-162 Milk Mn-54 pCi/L 219 207 1.05 lst/2010 E7016-162 Milk Fe-59 pCi/L 155 137 1.13 lst/2010 E7016-162 Milk Zn-65 pCi/L 272 254 1.07 lst/2010 E7016-162 Milk Co-60 pCi/L 187 183 1.02 lst/2010 E7017-162 Milk Sr-89 pCi/L 76.6 92.8 0.83 lst/2010 E7017-162 Milk Sr-90 pCi/L 12.3 12.7 0.97 C-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 AREVA NP ENVIRONMENTAL LABORATORY ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION QUARTER/ SAM PLE SAMPLE REPORTED KNOWN RATIO AREVA/

NUCLIDE UNITS YEAR NUMBER MEDIA VALUE VALUE ANALYTICS 2nd/2010 E7075-162 Water Gross Alpha pCi/L 99.3 102 0.98 2nd/2010 E7075-162 Water Gross Beta pCi/L 294 266 1.10 2nd/2010 E7076-162 Water 1-131LL pCi/L 74.7 78.9 0.95 2nd/2010 E7076-162 Water 1-131 pCi/L 79.5 78.9 1.01 2nd/2010 E7076-162 Water Ce-141 pCi/L 163 161 1.02 2nd/2010 E7076-162 Water Cr-51 pCi/L 505 494 1.02 2nd/2010 E7076-162 Water Cs-134 pCi/L 168 183 0.92 2nd/2010 E7076-162 Water Cs-137 pCi/L 233 218 1.07 2nd/2010 E7076-162 Water Co-58 pCi/L 151 147 1.03 2nd/2010 E7076-162 Water Mn-54 pCi/L 257 246 1.04 2nd/2010 E7076-162 Water Fe-59 pCi/L 185 173 1.07 2nd/2010 E7076-162 Water Zn-65 pCi/L 312 300 1.04 2nd/2010 E7076-162 Water Co-60 pCi/L 289 286 1.01 2nd/2010 E7077-162 Water Sr-89 pCi/L 86.6 100 0.87 2nd/2010 E7077-162 Water Sr-90 pCi/L 18.9 17.9 1.05 2nd/2010 E7078-162 Water H-3 pCi/L 9,160 9,630 0.95 2nd/2010 E7079-162 Charcoal 1-131 pCi 79.6 80.0 1.00 2nd/2010 E7080-162 Filter Gross Alpha pCi 84.3 87.8 0.96 2nd/2010 E7080-162 Filter Gross Beta pCi 233 231 1.01 2nd/2010 E7081-162 Filter Ce-141 pCi 80.3 84.0 0.96 2nd/2010 E7081-162 Filter Cr-51 pCi 257 259 0.99 2nd/2010 E7081-162 Filter Cs-134 pCi 93.7 95.9 0.98 2nd/2010 E7081-162 Filter Cs-137 pCi 123 114 1.07 2nd/2010 E7081-162 Filter Co-58 pCi 78.8 77.1 1.02 2nd/2010 E7081-162 Filter Mn-54 pCi 129 129 1.00 2nd/2010 E7081-162 Filter Fe-59 pCi 91.0 90.5 1.01 2nd/2010 E7081-162 Filter Zn-65 pCi 155 157 0.99 2nd/2010 E7081-162 Filter Co-60 pCi 145 150 0.97 2nd/2010 E7082-162 Milk 1-131LL pCi/L 105.1 96.9 1.08 2nd/2010 E7082-162 Milk 1-131 pCi/L 94.0 96.9 0.97 2nd/2010 E7082-162 Milk Ce-141 pCi/L 105 110 0.95 2nd/2010 E7082-162 Milk Cr-51 pCi/L 333 339 0.98 2nd/2010 E7082-162 Milk Cs-134 pCi/L 114 126 0.90 2nd/2010 E7082-162 Milk Cs-137 pCi/L 150 150 1.00 2nd/2010 E7082-162 Milk Co-58 pCi/L 99.8 101 0.99 2nd/2010 E7082-162 Milk Mn-54 pCi/L 172 169 1.02 2nd/2010 E7082-162 Milk Fe-59 pCi/L 123 119 1.03 2nd/2010 E7082-162 Milk Zn-65 pCi/L 204 206 0.99 2nd/2010 E7082-162 Milk Co-60 pCi/L 196 197 1.00 C-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TELEDYNE BROWN ENGINEERING, INC. ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION SAMPLE SAMPLE REPORTED KNOWN RATIO for QUARTER/ NUCLDE UITSTeledyne/known NUMBER MEDIA VALUE VALUE YEAR or Range 3rd/2010 E7233-396 Water Fe-55 pCi 1620 1790 0.91 3rd/2010 10-MaW23 Water Am-241 Bq/L 0.009 false positive test 3rd/2010 10-MaW23 Water Cs-134 Bq/L 27.1 31.4 22.0 - 40.8 3rd/2010 10-MaW23 Water Cs-137 Bq/L 41.8 44.2 30.9 - 57.5 3rd/2010 10-MaW23 Water Co-57 Bq/L 33.2 36.0 25.2 - 46.8 3rd/2010 10-MaW23 Water Co-60 Bq/L 26.5 28.3 19.8 - 36.8 3rd/2010 10-MaW23 Water H-3 Bq/L 500 453.4 317.4 - 589.4 3rd/2010 10-MaW23 Water Mn-54 Bq/L 0.024 false positive test 3rd/2010 10-MaW23 Water Ni-63 Bq/L 51.6 56.1 39.3 - 72.9 3rd/2010 10-MaW23 Water Pu-238 Bq/L 1.25 1.81 1.27 - 2.35 3rd/2010 10-MaW23 Water Pu-239/240 Bq/L 0.925 1.350 0.95 - 1.76 3rd/2010 10-MaW23 Water Sr-90 Bq/L 8.10 8.3 5.8 - 10.8 3rd/2010 10-MaW23 Water Tc-99 Bq/L 36.4 33.6 23.5 - 43.7 3rd/2010 10-MaW23 Water U-234/233 Bq/L 2.02 2.01 1.41 - 2.61 3rd/2010 10-MaW23 Water U-238 Bq/L 2.01 2.07 1.45 - 2.69 3rd/2010 10-MaW23 Water Zn-65 Bq/L 30.8 31.0 21.7 - 40.3 3rd/2010 10-GrW23 Water Gr-A Bq/L 2.36 1.92 0.58 - 3.26 3rd/2010 10-GrW23 Water Gr-B Bq/L 6.37 4.39 2.20 - 6.59 3rd/2010 E7231-396 Charcoal 1-131 pCi/L 62.3 59.9 1.04 3rd/2010 E7232-396 AP Ce-141 pCi 122 119 1.03 3rd/2010 E7232-396 AP Cr-51 pCi 228 214 1.07 3rd/2010 E7232-396 AP Cs-134 pCi 79.9 85.3 0.94 3rd/2010 E7232-396 AP Cs-137 pCi 93.8 86.7 1.08 3rd/2010 E7232-396 AP Co-58 pCi 71.5 67.6 1.06 3rd/2010 E7232-396 AP Mn-54 pCi 113 110 1.03 3rd/2010 E7232-396 AP Fe-59 pCi 73.8 83.6 0.88 3rd/2010 E7232-396 AP Zn-65 pCi 186 187 0.99 3rd/2010 E7232-396 AP Co-60 pCi 163 157 1.04 3rd/2010 10-RdF23 AP Am-241 Bq/sample 0.125 0.115 0.081 - 0.150 3rd/2010 10-RdF23 AP Cs-134 Bq/sample 2.31 2.98 2.09 - 3.87 3rd/2010 10-RdF23 AP Cs-137 Bq/sample -0.025 false positive test 3rd/2010 10-RdF23 AP Co-57 Bq/sample 0.0056 3.64 4.08 3rd/2010 10-RdF23 AP Co-60 Bq/sample 2.81 2.92 2.04-3.80 3rd/2010 10-RdF23 AP Mn-54 Bq/sample 3.19 3.18 2.23- 4.13 3rd/2010 10-RdF23 AP Pu-238 Bq/sample 0.048 0.0489 0.0342 - 0.0636 3rd/2010 10-RdF23 AP Pu-239/240 Bq/sample 0.080 0.082 0.057 - 0.107 3rd/2010 10-RdF23 AP Sr-90 Bq/sample 1.01 1.01 0.71 - 1.31 3rd/2010 10-RdF23 AP U-234/233 Bq/sample 0.123 0.122 0.085 - 0.159 3rd/2010 10-RdF23 AP U-238 Bq/sample 0.111 0.127 0.089 - 0.165 3rd/2010 10-RdF23 AP Zn-65 Bq/sample 0.0310 false positive test C-7

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TELEDYNE BROWN ENGINEERING, INC. ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION SAMPLE REPORTED KNOWN RATIO for QUARTER/ SAMPLE MEDIA NUCLIDE UNITS VALUE VALUE Teledyne/known YEAR NUMBER or Range 3rd/2010 10-GrF23 AP Gr-A Bq/sample 0.004 false positive test 3rd/2010 10-GrF23 AP Gr-B Bq/sample 0.473 0.50 0.25 - 0.75 3rd/2010 E7229-396 Milk Sr-89 pCi/L 85.0 92.8 0.92 3rd/2010 E7229-396 Milk Sr-90 pCi/L 12.6 14.7 0.86 3rd/2010 E7230-396 Milk 1-131 pCi/L 80.2 94.1 0.85 3rd/2010 E7230-396 Milk Ce-141 pCi/L 130 130 1.00 3rd/2010 E7230-396 Milk Cr-51 pCi/L 235 234 1.00 3rd/2010 E7230-396 Milk Cs-134 pCi/L 83.2 93.0 0.89 3rd/2010 E7230-396 Milk Cs-137 pCi/L 95.1 94.5 1.01 3rd/2010 E7230-396 Milk Co-58 pCi/L 77.3 73.7 1.05 3rd/2010 E7230-396 Milk Mn-54 pCi/L 121 119 1.02 3rd/2010 E7230-396 Milk Fe-59 pCi/L 96.4 91.1 1.06 3rd/2010 E7230-396 Milk Zn-65 pCi/L 216 204 1.06 3rd/2010 E7230-396 Milk Co-60 pCi/L 172 171 1.01 3rd/2010 10-MaS23 Soil Am-241 Bq/kg NCR 11-01 initiated to investigate failure 3rd/2010 10-MaS23 Soil Cs-134 Bq/kg 837 940 658 - 1222 3rd/2010 10-MaS23 Soil Cs-137 Bq/kg 680 670 469 - 871 3rd/2010 10-MaS23 Soil Co-57 Bq/kg 2.78 false positive test 3rd/2010 10-MaS23 Soil Co-60 Bq/kg 350 343 240 - 446 3rd/2010 10-MaS23 Soil Mn-54 Bq/kg 853 820 574 - 1066 3rd/2010 10-MaS23 Soil Ni-63 Bq/kg 938 1058 741 - 1375 3rd/2010 10-MaS23 Soil Pu-238 Bq/kg NCR 11-01 initiated to investigate failure 3rd/2010 10-MaS23 Soil Pu-239/240 Bq/kg NCR 11-01 initiated to investigate failure 3rd/2010 10-MaS23 Soil K-40 Bq/kg 721 699 489 - 909 3rd/2010 10-MaS23 Soil Sr-90 Bq/kg 2.24 false positive test 3rd/2010 10-MaS23 Soil Tc-99 Bq/kg 297 325 228 - 423 3rd/2010 10-MaS23 Soil U-234/233 Bq/kg NCR 11-01 initiated to investigate failure 3rd/2010 10-MaS23 Soil U-238 Bq/kg NCR 11-01 initiated to investigate failure 3rd/2010 10-MaS23 Soil Zn-65 Bq/kg 287 265 186 - 345 3rd/2010 10-RdV23 Vegetation Cs-134 Bq/sample 4.90 4.79 3.35 - 6.23 3rd/2010 10-RdV23 Vegetation Cs-137 Bq/sample 6.78 5.88 4.12 - 7.64 3rd/2010 10-RdV23 Vegetation Co-57 Bq/sample 10.2 8.27 5.79 - 10.75 3rd/2010 10-RdV23 Vegetation Co-60 Bq/sample 0.00 false positive test 3rd/2010 10-RdV23 Vegetation Mn-54 Bq/sample 7.36 6.287 4.401 - 8.173 3rd/2010 10-RdV23 Vegetation Sr-90 Bq/sample 2.53 2.63 1.84 - 3.42 3rd/2010 10-RdV23 Vegetation Zn-65 Bq/sample 6.40 5.3900 3.77 - 7.01 C-8

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TELEDYNE BROWN ENGINEERING, INC. ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION RATIO for SAMPLE SAMPLE REPORTED KNOWN TIOefor QUARTER/

MEDIA VALUE VALUE Rane YEAR NUMBER known or Range 4th/2010 E7375-396 Milk Sr-89 pCi/L 92.7 98.0 0.95 4th/2010 E7375-396 Milk Sr-90 pCi/L 13.5 13.5 1.00 4th/2010 E7376-396 Milk 1-131 pCi/L 87.9 96.9 0.91 4th/2010 E7376-396 Milk Ce-141 pCi/L not provided by Analytics for this study 4th/2010 E7376-396 Milk Cr-51 pCi/L 389 456 0.85 4th/2010 E7376-396 Milk Cs-134 pCi/L 137 157 0.87 4th/2010 E7376-396 Milk Cs-137 pCi/L 172 186 0.92 4th/2010 E7376-396 Milk Co-58 pCi/L 84.3 90.2 0.93 4th/2010 E7376-396 Milk Mn-54 pCi/L 120 120 1.00 4th/2010 E7376-396 Milk Fe-59 pCi/L 134 131 1.02 4th/2010 E7376-396 Milk Zn-65 pCi/L 162 174 0.93 4th/2010 E7376-396 Milk Co-60 pCi/L 284 301 0.94 4th/2010 E7378-396 AP Ce-141 pCi not provided by Analytics for this study 4th/2010 E7378-396 AP Cr-51 pCi 387 365 1.06 4th/2010 E7378-396 AP Cs-134 pCi 135 126.0 1.07 4th/2010 E7378-396 AP Cs-137 pCi 157 149.0 1.05 4th/2010 E7378-396 AP Co-58 pCi 73.6 72.3 1.02 4th/2010 E7378-396 AP Mn-54 pCi 88.7 96.0 0.92 4th/2010 E7378-396 AP Fe-59 pCi 127 105.0 1.21 4th/2010 E7378-396 AP Zn-65 pCi 151 139 1.09 4th/2010 E7378-396 AP Co-60 pCi 249 241 1.03 4th/2010 E7377-396 Charcoal 1-131 pCi 79.6 84.2 0.95 4th/2010 E7379-396 Water Fe-55 pCi 1720 1880 0.91 4th/2010 RAD-83 Water Sr-89 pCi/L 77.8 68.5 55.8 - 76.7 4th/2010 RAD-83 Water Sr-90 pCi/L 39.3 43.0 31.7 - 49.3 4th/2010 RAD-83 Water Ba-133 pCi/L 70.3 68.9 57.5 - 75.8 4th/2010 RAD-83 Water Cs-134 pCi/L 39.9 43.2 34.5 - 47.5 4th/2010 RAD-83 Water Cs-137 pCi/L 117 123 111 - 138 4th/2010 RAD-83 Water Co-60 pCi/L 53.5 53.4 48.1 - 61.3 4th/2010 RAD-83 Water Zn-65 pCi/L 11.0 102 91.8 - 122 4th/2010 RAD-83 Water Gr-A pCi/L 35.1 42.3 21.9 - 53.7 4th/2010 RAD-83 Water Gr-B pCi/L 35.5 36.6 24.0 - 44.2 4th/2010 RAD-83 Water 1-131 pCi/L 27.9 27.5 22.9 - 32.3 4th/2010 RAD-83 Water U-Nat pCi/L 36.8 36.8 29.8 - 41.0 4th/2010 RAD-83 Water H-3 pCi/L 13233 12900 11200 - 14200 4th/2010 MRAD-13 Filter Gr-A pCi/filter 40.1 52.3 27.1 - 78.7 C-9

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 APPENDIX D 2009 Radiological Environmental Operating Report ERRATA D-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 Table 10, Well Water (pCi/L)

Location Collection Isotope Date 71 Ba-140 Be-7 Co-58 Co-60 Cr-51 Cs-134 03/20/09 -1.3 +/- 7.5 3.0 +/- 23.0 -2.0+/- 3.0 0.2+/- 2.7 -9.0 +/- 24.0 -0.8 _+ 2.5

+

06/17/09 0.6 +/- 6.0 26.0+/- 30.0 -2.3+/- 3.3 0.6+/- 3.6 -39.0 +/- 31.0 0.0 2.5

-+

09/21/09 -6.4 +/- 7.2 -6.0 +/- 19.0 -1.2+/- 2.4 -0.4 +/- 2.6 16.0 +/- 23.0 0.7 1.9

-+

12/14/09 -3.2 +/- 4.7 12.0+/- 26.0 -0.4+/- 3.3 -0.8 +/- 3.7 -29.0 +/- 28.0 1.0 2.4 Cs-137 Fe-59 H-3 1-131 K-40 La-140 03/20/09 -0.6 +/- 3.0 2.0+/- 6.6 570 _ 840 0.9+/- 6.1 19.0 +/- 47.0 -1.3 + 7.5

_+

06/17/09 -0.2 +/- 3.7 -0.5 +/- 7.6 40.0 _ 870.0 1.1+/- 7.1 21.0 +/- 49.0 0.6 6.0

+

09/21/09 -0.8 +/- 2.5 0.0+/- 5.3 -410.0+/- 820.0 1.0+/- 7.3 10.0 +/- 37.0 -6.4 7.2

+

12/14/09 -0.9 +/- 3.4 4.4+/- 7.0 -50.0 +/- 890.0 0.7+/- 6.4 -13.0 +/- 55.0 -3.2 4.7 Mn-54 Nb-95 Ru-103 Ru-106 Sb-125 Sr-89 03/20/09 -1.4 +/- 2.7 -0.7 +/- 3.3 -1.7+/- 2.9 10.0+/- 25.0 2.4 +/- 6.7 1.6 + 4.7 06/17/09 0.4 +/- 2.9 0.7+/- 4.2 -0.2+/- 3.8 -21.0 +/- 32.0 -5.0 _ 8.9 -3.8 + 2.2 09/21/09 -1.5 +/- 2.0 -0.1 +/- 2.7 -0.9+/- 2.6 -15.0 +/- 21.0 0.3 +/- 5.5 -3.3 + 2.3 12/14/09 -0.2 +/- 3.4 -2.1 +/- 4.3 0.9 +/- 3.5 -18.0 +/- 27.0 -2.1 + 9.2 -2.1 _+ 2.4 Sr-90 Th-228 Zn-65 Zr-95 03/20/09 -0.4 +/- 1.1 11.0+/- 14.0 0.0 +/- 11.0 1.6+/- 4.5 06/17/09 -0.6 +/- 0.8 -19.0 +/- 14.0 -4.9+/- 9.3 -1.1 +/- 6.3 09/21/09 -0.8 +/- 0.7 12.3 +/- 8.5 0.0 +/- 4.9 -0.9 +/- 4.0 12/14/09 -0.3 +/- 0.7 3.0 +/- 14.0 10.0 +/- 14.0 6.9+/- 6.5 72 Ba-140 Be-7 Co-58 Co-60 Cr-51 Cs-134 03/18/09 -1.8 +/- 5.2 10.0+/- 33.0 4.8 +/- 4.6 -1.5 +/- 5.0 -25.0 +/- 39.0 0.5 _+ 3.7

-0.6+/- 3.1 1.4+/- 3.3 9.0 +/- 30.0 -0.2 _+2.7 06/11/09 6.4 +/- 7.5 20.0+/- 26.0

-4.5 +/- 7.0 -38.0 +/- 36.0 2.0 +/- 4.0 -10.0 +/- 37.0 _+3.7 09/16/09 0.4+/- 3.8 -0.6 1.6 +/- 3.1 -1.0 +/- 24.0 _+3.2 12/14/09 1.4 +/- 7.4 12.0+/- 24.0 0.8+/- 3.6 1.0 Cs-137 Fe-59 H-3 1-131 K-40 La-140 03/18/09 -1.7 +/- 4.2 -2.7 +/- 9.3 1250.0 +/- 860.0 3.9+/- 8.0 -25.0 +/- 52.0 -1.8 +/- 5.2 06/11/09 -0.9 +/- 2.9 -4.9 +/- 7.1 -280.0+/- 860.0 0.0+/- 8.5 2.0 +/- 50.0 6.4 +/- 7.5 09/16/09 1.6 +/- 4.1 -4.5 +/- 7.4 -520.0+/- 840.0 2.6+/- 8.0 -22.0 +/- 55.0 -4.5 +/- 7.0 12/14/09 -1.8 +/- 3.2 -3.3 +/- 7.8 -40.0 +/- 890.0 0.7+/- 4.5 -9.0 +/- 50.0 1.4 +/- 7.4 Mn-54 Nb-95 Ru-103 Ru-106 Sb-125 Sr-89 03/18/09 0.0 +/- 4.1 1.1+/- 5.0 -2.9+/- 4.6 -23.0 +/- 40.0 -7.0 +/- 12.0 0.1 + 3.8

+

06/11/09 1.0 +/- 3.0 0.4+/- 3.9 -1.0+/- 3.7 -16.0 +/- 28.0 1.4 +/- 7.3 1.2 2.6

_+

09/16/09 2.2 +/- 3.3 -1.2 +/- 4.5 -3.2+/- 4.7 -18.0 +/- 33.0 -4.0 +/- 11.0 1.1 2.7

+ 3.3 12/14/09 -2.8 +/- 3.2 2.5 +/- 3.4 -3.7+/- 3.0 -1.0 +/- 30.0 -0.7 +/- 7.7 2.4 Sr-90 Th-228 Zn-65 Zr-95 03/18/09 0.9 +/- 1.0 -16.0 +/- 18.0 -3.0 +/- 11.0 -3.3 +/- 7.5 06/11/09 -0.1 +/- 0.9 -5.0 +/- 12.0 -7.8+/- 7.7 -0.6 +/- 5.8 09/16/09 -0.5 +/- 0.8 17.0+/- 15.0 5.0 +/- 16.0 0.0+/- 6.4 12/14/09 0.0 +/- 0.9 5.0 +/- 13.0 -16.2 +/- 9.5 3.7+/- 4.9 D-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report Millstone Station 2010 TABLE A-1 Dairy Cows Within 20 Miles of Millstone Point - 2009*

Direction Distance Location miles N 14 Preston N 15 Norwich N 20 Norwich NNE 16 Norwich NNE 16 Preston NNE 16 Preston NNE 17 Preston NNE 18 Preston NE 13.5 Ledyard NE 14 Ledyard NE 14.5 Ledyard NE 18 Preston NE 18 North Stonington NE 19 Preston NE 19 North Stonington ENE 17.5 North Stonington ENE 20 North Stonington WNW 10.4 Lyme NW 10.4 Lyme NW 19 East Haddam NNW 12.3 Salem

previous years the data included the number of cows at each location; this is no longer tracked in the census records since 2007 Note: None of these cow farms are used for sampling since all farms are greater than ten miles from plant (NUREG 1301, Reference 15, uses a cutoff distance of 5 miles).

D-3

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