ML061230649

Radiological Environmental Operating Report

ML061230649
Person / Time
Site:	Maine Yankee
Issue date:	12/31/2005
From:	Maine Yankee Atomic Power Co
To:	Document Control Desk, NRC/FSME
References
Download: ML061230649 (79)

Text

Maine Yankee RELIABLE ELECTRICITY FOR MAINE SINCE 1972 2005 cdgumingVTyvcov

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2005 MAINE YANKEE ATOMIC POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DOCKET NO. 50-309 LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY AREVA Doc. # 47-9001395-A

EXECUTIVE

SUMMARY

This report is prepared to cover the Radiological Environmental Monitoring Program (REMP) activities during 2005 which were associated with the final site remediation and decommissioning of the former Maine Yankee Nuclear Power Plant. In early October, 2005, the NRC notified Maine Yankee that they had accepted that the former power plant site had been successfully decommissioned in accordance with NRC procedures. As a result, the NRC amended Maine Yankee's license reducing the land under license from approximately 179 acres (former plant proper) to the 12 acre Independent Spent Fuel Storage Installation. The Offsite Dose Calculation Manual (ODCM) was amended (Change 31, Reference 8) at the end of the site decommissioning activities to reflect that only the direct radiation from the Independent Spent Fuel Storage Installation (ISFSI) remains as a potential source of radiation in the environment.

During this time period (first half of 2005), the REMP was conducted to assess the levels of radiation or radioactivity in the Maine Yankee environment which had the potential of being impacted by decommissioning activities. Eighty-one samples were collected from January through August, 2005, with 741 radionuclide or exposure rate analyses being performed on them. From January through August, samples collected as part of this program included demolition air particulate, estuary water, fish, mussels, crabs, and lobsters. Sample collections also included direct radiation measurements at 16 on-site location associated with the ISFSI, and 2 off-site control locations, using continuously recording TLD's.

Low levels of radioactivity from naturally-occurring fallout sources were detected. Many samples had measurable concentrations of K-40. This is one of the most common of the naturally-occurring radionuclides. None of the samples indicated radioactivity resulting from emissions from Maine Yankee site. Consequently, there was judged to be no offsite environmental or health impact from the activities performed in 2005 for the decommissioning of Maine Yankee.

In August, 2005, there was one change made to the ODCM that affected several functions of the Radiological Environmental Monitoring Program. As part of change number 31 to the ODCM, environmental media associated with liquid effluents (i.e., surface water, fish and invertebrates), and on-site air particulate monitoring of demolition activities, were eliminated from the program since potential for both liquid effluents and airborne particulates were removed with the completion of site remediation.

In the fourth quarter of 1999, TLDs were placed within about 340 meters of the Independent Spent Fuel Storage Installation (ISFSI) in each of the 16 major compass directions. This was done to establish a baseline measurement before the transfer of radioactive materials to the storage pad. The first storage canister was placed on the ISFSI in December, 2001, with the last canister transferred to the ISFSI in February, 2004. The ISFSI TLD's located adjacent to the plant's site boundary did not show any significant change in exposure rate during the first half of 2005 over the baseline measurements. The ISFSI TLDs will remain in-place monitoring the ISFSI during its operating life.

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TABLE OF CONTENTS

1.0 INTRODUCTION

................................................................. 1 2.0 NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY ................................ 2 2.1 NATURALLY OCCURRING BACKGROUND ADIOACnVITY ................................................................ 2 2.2 MAN-MADE BACKGROUND RADIOACIVITY ................................................................ 3 3.0 GENERAL PLANT AND SITE INFORMATION ................................................................. 4 4.0 PROGRAM DESIGN ................................................................ 5 4.1 MONITORING ZONES ................................................................ 6 4.2 PATHWAYS MONITORED ................................................................ 6

4.3 DESCRIPTION

S OF MONITORING PROGRAMS ................................................................ 7 4.3.1 Air Sampling (AP Demo) ........................................... 7 4.3.2 Estuary Water Sampling (WE)........................................... 7 4.3.3 Ground Water Sampling (WG) ........................................... 7 4.3.4 Sediment Sampling (SE) ............................................ 8 4.3.5 Marine Algae Sampling (AL) ............................................ 8 4.3.6 Milk Sampling (TM) ........................................... 8 4.3.7 Fish (FH) and InvertebrateSampling (CA, HA, MU, and MA) ........................................... 8 4.3.8 Mixed Vegetation Sampling (TF)........................................... 8 4.3.9 TLD Monitoring (TL) ........................................... 8 5.0 RADIOLOGICAL DATA

SUMMARY

TABLES . 20 6.0 ANALYSIS OF ENVIRONMENTAL RESULTS . 29 6.1 SAMPLING PROGRAM DEVIATIONS . 29 6.2 COMPARISON OF ACHIEVED LLDs WITH REQUIREMENTS . 30 6.3 COMPARISON OF RESULTS AGAINST REPORTING LEVELS . 30 6.4 DATA ANALYSIS BY MEDIA TYPE . 32 6.4.1 Airborne Pathways.32 6.4.2 Waterborne Pathways . 32 6.4.3 Ingestion Pathways . 33 6.4.4 Direct Radiation Pathway(TL) . 33 7.0 QUALITY ASSURANCE PROGRAM . 40 8.0 LAND USE CENSUS .45

9.0 REFERENCES

.48 APPENDIX A.. A-I iii

LIST OF TABLES Table Title Page 4.1 Radiological Environmental Surveillance Program. 9 4.2 Radiological Environmental Monitoring Locations (Non-TLD) in 2005 .11 4.3 Radiological Environmental Monitoring Locations (TLD) in 2005 .13 4.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements 15 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 16 5.1 Radiological Environmental Program Summary .22 5.2 Environmental TLD Summary .27 5.3 2005 Environmental ISFSI and Control TLD Measurements .28 7.1 FANPEL Results in the Intralaboratory Process Control Program .42 7.2 FANPEL Results in the Analytics Inc. Cross Check Program .43 7.3 Summary of Blind Duplicate Samples.44 8.1 2005 Land Use Census Locations .47 iv

LIST OF FIGURES Figure Title Pape 4.1 Radiological Environmental Sampling Locations Within 1 Kilometer of Maine Yankee .17 4.2 Radiological Environmental Sampling Locations Outside 1 Kilometer of Maine Yankee .18 4.3 Direct Radiation Monitoring Locations Outside 1 Kilometer of Maine Yankee ............................................. ................. 19 6.1 H-3 in Estuary Water .............................................................. 35 6.2 Exposure at TLDs TL-I-01 through TL-I-04 and Avg. of Control TLDs ................. 36 6.3 Exposure at TLDs TL-I-05 through TL-I-08 and Avg. of Control TLDs ................. 37 6.4 Exposure at TLDs TL-I-09 through TL-I-12 and Avg. of Control TLDs ................. 38 6.5 Exposure at TLDs TL-I-13 through TL-I-17 and Avg. of Control TLDs................. 39 v

1.0 INTRODUCTION

This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Maine Yankee Atomic Power Company in the vicinity of the Maine Yankee Nuclear Power Station in Wiscasset, Maine, during the calendar year 2005. It is submitted annually in compliance with Appendix C, item 1, of the Offsite Dose Calculation Manual (ODCM). The remainder of this report is organized as follows:

Section 2: Provides an introduction to the background radioactivity and radiation that is detected in the Maine Yankee environs.

Section 3: Provides a brief description of the Maine Yankee site and its environs.

Section 4: Provides a description of the overall REMP design. Included is a summary of the ODCM requirements for REMP sampling, tables listing routine sampling and TLD monitoring locations with compass sectors and distances from the plant, and maps showing the location of each of the sampling and TLD monitoring locations. Tables listing Lower Limit of Detection requirements and Reporting Levels are also included.

Section 5: Consists of the summarized data as required by the ODCM, in the format specified by the NRC Branch Technical Position on Environmental Monitoring (Reference 1). Also included are complete environmental TLD data. Included in this data is the exposure-rate monitoring results for the ISFSI area.

Section 6: Provides the results of the 2005 monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year is analyzed.

Section 7: Provides an overview of the Quality Assurance programs used at the Framatome ANP Environmental Laboratory (FANPEL). The results of the Laboratory participation in an Interlaboratory Comparison Program required by ODCM section 2.4 are also given.

Section 8: Summarizes the requirements and the results of the 2005 annual Land Use Census.

Section 9: References Appendix A: A listing of radiological laboratory analyses of environmental media for 2005.

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2.0 NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY Radiation or radioactivity potentially detected in the Maine Yankee environment can be grouped into three categories. The first is "naturally-occurring" radiation and radioactivity. The second is "man-made" radioactivity from sources other than the Maine Yankee site. The third potential source of radioactivity is due to emissions from the former Maine Yankee plant site due to activities associated with area remediation and decommissioning. For the purposes of the Maine Yankee REMP, the first two categories are classified as "background" radiation, and are the subject of discussion in this section of the report. The third category is the one that the REMP is designed to detect and evaluate.

2.1 Naturally Occurring Background Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate categories: "primordial radioactivity,"

"cosmogenic radioactivity" and "cosmic radiation." "Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth. Included in this category are the radionuclides that these elements have decayed into. A few of the more important radionuclides in this category are Uranium-238 (U-238),

Thorium-232 (Th-232), Rubidium-87 (Rb-87), Potassium40 (K40), Radium-226 (Ra-226), and Radon-222 (Rn-222). Uranium-238 and Thorium-232 are readily detected in soil and rock, whether through direct field measurements or through laboratory analysis of samples. Radium-226 in the earth can find its way from the soil into ground water, and is often detectable there. Radon-222 is one of the components of natural background in air, and its daughter products are detectable on air sampling filters. Potassium-40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2).

The second category of naturally-occurring radiation and radioactivity is "cosmogenic radioactivity." This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radionuclides in this category are Carbon-14 (C-14), Hydrogen-3 (H-3 or Tritium), Sodium-22 (Na-22), and Beryllium-7 (Be-7). Beryllium-7 is the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).

The third category of naturally-occurring radiation and radioactivity is "cosmic radiation." This 2

consists of high energy atomic or sub-atomic particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's atmosphere. The primary radiation comes mostly from outside of our solar system, and to a lesser degree from the sun. We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation. Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of air for protection. This "direct radiation" can be detected in the field with various instruments, including thermoluminescent dosimeters (TLD's).

2.2 Man-Made Background Radioactivity The second source of "background" radioactivity in the Maine Yankee environment is from "man-made" sources not related to the power plant site. The most recent contributor to this category was the fallout from the Chernobyl accident in April of 1986, which was detected in the Maine Yankee environment and other parts of the world. A much greater contributor to this category, however, has been fallout from atmospheric nuclear weapons tests. Tests were conducted from 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962. (A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.) Atmospheric testing was conducted by the People's Republic of China as recently as October 1980. Much of the fallout detected today is due to this testing and the previous large scale test(Reference 3).

The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout from the troposphere (Reference 4). Most of this fallout has decayed into stable elements, but the residual radioactivity is still detectable at low levels in environmental samples worldwide. The two predominant radionuclides are Cesium-137 (Cs-137) and Strontium-90 (Sr-90). They are found in soil and in vegetation, and since cows and goats graze large areas of vegetation, these radionuclides can also be detected in the milk.

Other potential "man-made" sources of environmental "background" radioactivity include other nuclear power plants, coal-fired power plants, national defense installations, hospitals, research laboratories and industry. These collectively are insignificant on a global scale when compared to the sources discussed above (natural and fallout).

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3.0 GENERAL PLANT AND SITE INFORMATION The Maine Yankee Nuclear Power Station site is located in the town of Wiscasset, Lincoln County, Maine, approximately six miles northeast of Bath, Maine. The site vicinity is rural and lightly populated.

The plant site is located on Bailey Point, a peninsula bounded to the east by the Back River and to the west by a shallow inlet known as Bailey Cove, both of which are part of the Montsweag Bay-Sheepscot River Estuary. (See the maps in Figures 4.1 to 4.4) Bailey point is an elongated bedrock ridge with flat or gently rolling topography rising to an average elevation of about 25 feet above sea level (Reference 5).

The single 900 megawatt PWR (Pressurized Water Reactor) unit at Maine Yankee began commercial operation in 1972. The Radiological Environmental Monitoring Program (REMP) began pre-operational measurements in 1970, two years prior to commercial operation. The REMP has been in continuous operation since that date.

Maine Yankee shut down in December 1996. In August 1997 the decision was made to permanently cease power production after 24 years of operation. The plant has since been in the process of decommissioning, which involves the disassembly and removal of the plant components and structures. In 2005, this decommissioning process was completed. This process took place in strict conformance with USNRC regulations. Oversight also continued from the State of Maine.

The radiological environmental monitoring program for Maine Yankee continued to operate during 2005 for those exposures pathways that had a potential to be impacted by the remaining site remediation activities associated with the final stage of site decommissioning.

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4.0 PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee Nuclear Power Station was designed with the following specific objectives in mind. These objectives continued in force, as appropriate, throughout decommissioning activities at the Maine Yankee site.

• To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the decommissioning operations at the station and the storage of spent nuclear fuel.

• To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.

• To verify the adequacy and proper functioning of station effluent controls and monitoring systems.

• To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.

The program was initiated in 1970, approximately two years before the plant began commercial operation in 1972. It has been in operation continuously since that time, with improvements made periodically over those years.

Prior to January 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were stated in the Radiological Effluent Technical Specifications (RETS). In January 1992, the REMP specifications were relocated from the RETS and placed in the Offsite Dose Calculation Manual (ODCM) pursuant to NRC Generic Letter 89-01 (Reference 6).

The REMP is a requirement of the ODCM. The detailed sampling requirements of the REMP are given in Table 2.3 of ODCM Section 2.4. This table is summarized in this report as Table 4.1.

The required sampling locations are identified in Section 5 of the ODCM. The locations monitored in 2005 are shown on Tables 4.2 and 4.3, as well as Figures 4.1 through 4.4 of this report. The environmental sampling and TLD locations were determined using a differential Global Positioning System (GPS), with a typical accuracy of less than 5 meters. The reference point chosen for direction and distance was the former plant Primary Vent Stack (PVS). The ISFSI TLD's were positioned at a distance from the concrete storage pad using the centerline of the pad as a reference point.

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4.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the site to levels found in areas not influenced by site activities during the final stages of remediation and decomissioning. The first area is called Zone 1, and its monitoring locations are called "indicators." The second area is called Zone 2, and its monitoring locations are called "controls." The distinction between the two zones, depending on the type of sample or sample pathway, is based on one or more of several factors, such as site meteorological history, meteorological dispersion calculations, relative direction from the plant, river flow, and distance.

Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to plant releases and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.

4.2 Pathways Monitored During the first half of 2005, four pathway categories were monitored by the REMP. They were direct radiation, airborne, waterborne, and ingestion pathways. Each of these four categories is monitored by the collection of one or more sample media, which are listed below, and are described in more detail in this section:

Airborne Pathway

• Demolition Particulate Sampling Waterborne Pathways

• Estuary Water Sampling Ingestion Pathways

• Fish and Invertebrate Sampling Direct Radiation Pathway

• TLD Monitoring 6

4.3 Descriptions of Monitoring Programs 4.3.1 Air Sampling (AP Demo)

Continuous offsite air samplers were not operated in 2005 due to the elimination of any significant release sourcesat the plant site. Continuous air sampling (AP) was terminated in July, 2004 according to change #29 of the ODCM. (Reference 7)

During 2005, on-site demolition particulate air sampling was conducted as part of the program. The purpose was to monitor airborne activity levels surrounding plant structures that were being demolished or land rememdiation locations that were part of the decommissioning process. The number and location of sampling points is dependent on the number of demolition or remediations jobs being performed. Collection frequency is at least once weekly, or as required by dust loading.

The filters were held for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at the Framatome ANP Environmental Laboratory (FANPEL) before being analyzed for gross-beta radioactivity. The filters were composited by location at the laboratory for a quarterly gamma spectroscopy analysis. Should any individual filter gross beta result exceed the annual average of the normal REMP control locations, that individual filter was required to be analyzed for gamma isotopic analysis.

4.3.2 Estuary Water Sampling (WE)

Weekly grab samples are collected from the boat dock on the Back River, near the site's discharge point. In addition, a weekly grab sample is collected at the control location in the Kennebec River.

All estuary water samples are preserved with HCl to prevent the plate out of radionuclides on the container walls. These weekly grab samples are composited for a monthly sample analysis at the Framatome-ANP Environmental Laboratory. Each monthly composite sample is analyzed for gamma-emitting radionuclides. These monthly samples are then composited by location at the FANPEL for a quarterly H-3 analysis.

4.3.3 Ground Water Sampling (WG)

Due to the hydraulic gradient at the Maine Yankee site, whereby the ground water flow is southward down the peninsula and toward the water on the east and west sides, ground water sampling is not required at the Maine Yankee site, pursuant to ODCM Table 2.3. Nevertheless, grab samples were previously collected quarterly from one on-site location and one control location and analyzed for gamma-emitting radionuclides. These samples were eliminated in 2003 due to the home and well at the indicator station being abandoned. No ground water samples were taken in 2005.

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4.3.4 Sediment Sampling (SE)

Sediment sampling was eliminated by ODCM change #29. No sediment samples were collected in 2005.

4.3.5 Marine Algae Sampling (AL)

Sampling of this media is not required by ODCM Table 2.3 and no samples were collected during the calendar year 2005.

4.3.6 Milk Sampling (TM)

Milk sampling was eliminated following the second 2004 sample collection according to Change

1. 29 of the MY ODCM. No milk samples were taken in 2005.

4.3.7 Fish (FH) and Invertebrate Sampling (CA, CR, HA, MU)

Samples of commercially important fish and invertebrates are collected two times seasonally at two locations (near the site's discharge, and at a control location on the Sheepscot River). Typical sample species collected (as available) include fish (F1H), crabs (CA) or rock crab (CR), lobsters (HA) and mollusks (blue mussels [MU]). Samples are separated by species and are then frozen and delivered to the FANPEL, where the edible portions are analyzed for gamma-emitting radionuclides.

4.3.8 Mixed Vegetation Sampling (TF)

No vegetation samples were collected in 2005. Change #29 to the ODCM discontinued vegetation sampling as a substitiute for milk collections which also removed from the ODCM by Change #29.

These program reduction were made after the potential for any significant site sources affecting these media pathways had been eliminated.

4.3.9 TLD Monitoring (TL)

Direct gamma radiation exposure was continuously monitored with the use of thermoluminescent dosimeters (TLD's). TLD's were placed (starting the fourth quarter of 1999) on-site within about 340 meters of the Independent Spent Fuel Storage Installation (ISFSI) in each of the 16 major compass directions. The ISFSI is located approximately 450 meters NE of the former location of the containment dome. The ISFSI TLD's are classified as TL-I-# in Table 5.3.

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I I I r , I I -- C r F r I F- r TABLE 4.1 Radiological Environmental Surveillance Program (as required during First Half 2005 by ODCM Table 2.3 and Table 5.1)

0 0: '  ; .___________________X __ Colle ction  ; 0

__;'______________....0 Ad Is 0  : I:0E; : A ntalysis' Exposure Pathway andtor Number of 'Routine Anlysis  ; Analysis Sample Media Sample Locations :Samplng C ollection T;pe Frequency Mod Frequency,

1. Direct Radiation (TLDs) (1) Total Locations: 18 Continuous Quarterly Gamma dose Each TLD

2. Airborne (2)

Demolition Particulate Dependent T Continuous Continuous Gross beta Each sample operationTT of sampler with sample Gamma Isotopic Quarterly Composite' collection as required by dust loading but at least once weekly.

3. Waterbome (3)

Estuary Water Total Locations: 2 Weekly grab sample Monthly Gamma Isotopic Each Sample for a monthly Tritium (H-3) Quarterly Composite composite sample"

• IForfl the ndicatorstaton 54 sL~tablaaiminle ~fth on the tide~ cv3lef when shall be coA~lW~Ulecte direto I5 off~lUI rive 5Wis w from heUfl n UStoW5 IUIWU of discharVe the~ coSlletSion niJU T

The number and location of sampling points is dependent on the activities performed. Air samplers are placed in or within close proximity of buildings undergoing demolition activities to provide reasonable assessment of the airborne activity that may be generated.

TT Continuous operation during periods when a building is no longer tied into existing ventilation systems, has large permanent openings to the environment, and is subject to active demolition activities.

Analyze for gross beta at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Perform gamma isotopic analysis on any filter indicating activity greater than 5 times the yearly mean of the control samples (I) ODCM Change #29 eliminated all inner ring TLD's (except for controls) from the program.

(2) Continuous air samples were eliminated in July 2004 per ODCM Change #29.

(3) Sediment sampling was discontinued per ODCM Change #29.

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IIIr I I( r I r I Ir I [ U TABLE 4.1 (Continued)

Radiological Environmental Surveillance Program (as required during First Half 2005 by ODCM Table 2.3 and Table 5.1) z 0 t:  : 0 0_

_ _ _ _ _ _.; Collection _____________0 ; - :Q '; - 8 ' 00 A nalysi $s Exposure Pathway andor .- Nominal Number of Routine Nominal - Analysis Analysis Sample Media Sample L'otons Sampling Coleetin Tye Frequency MW ode~ Frequency __ _ _ _ _ _ _ _ __ _ _ _ _ _ _

4. Ingestion (4)

b. Fish and Invertebrates Total Locations: 2 Grab Semiannually Gamma Isotopic on edible Each sample (commercially or recreationally (or seasonal if portions important species) appropriate)

(4) Milk sampling was performed until July 2004 when collections were discontinued per ODCM Change #29. Vegetation sampling was also removed from the ODCM by Change # 29. Vegetation samples were not required per the ODCM if milk was sampled.

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TABLE 4.2 Radiological Environmental Monitoring Locations (non-TLD)

During First Half 2005 Distance Direction Station From Plant From Exposure Pathway Code Station Description Zones (km) Plant

1. Airborne

a. Demolition AP Demo- N/A Various Various Particulateb xx

2. Waterborne

a. Surface Water WE-14 Boat Dock 1 0.5 NE (Grab Sample)

WE-20 Kennebec River 2 9.5 WSW (Grab Sample)

3. Ingestion

a. Fish & FH-l lc Long Ledge Area 1 0.9 S Invertebrates MU-1I CA/CR-1 1 HA-1I FH-24 Sheepscot River 2 11.1 S MU-24 CAICR-24 HA-24 11

TABLE 4.2 (Continued)

Radiological Environmental Monitoring Locations (non-TLD)

During First Half 2005 1I = Indicator Stations; 2 = Control Stations b The number and location of Demolition sampling points is dependent on the activities performed. Air samplers are placed in or within close proximity of buildings undergoing demolition activities to provide reasonable assessment of

- the airborne activity may be generated

¢ FH = Fish, MU = Mussels, CA = Crabs, CR= Rock Crab, HA = Lobsters (1) Continuous air sampling was eliminated in July 2004 per ODCM Change #29 (2) Milk sampling was eliminated per ODCM change #29. Sampling was discontinued following collection of the June 2004 samples.

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TABLE 4.3 Radiological Environmental Monitoring Locations ( Off-site TLD)

In 2005 Distance From Plant Direction Station Code Station Description Zone* (kmi) From Plant TL-36 Boothbay Harbor Fire Station 2 12.2 SSE TL-37 Dresden Substation 2 20.1 N

• 2 = Control TLD Note: Per ODCM Change #29 off-site TLD's were eliminated (other than controls) as of July 2004.

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TABLE 4.3 (Continued)

Radiological Environmental Monitoring Locations (On-site TLD) in 2005 Direction From ISFSI TLDs Centerline of ISFSI*

TL-I-OI Spent Fuel Storage N TL-1-02 Spent Fuel Storage NNE TL-1-03 Spent Fuel Storage NE TL-1-04 Spent Fuel Storage ENE TL-1-05 Spent Fuel Storage E TL-1-06 Spent Fuel Storage ESE TL-I-07 Spent Fuel Storage SE TL-I-08 Spent Fuel Storage SSE TL-I-09 Spent Fuel Storage S TL-I-10 Spent Fuel Storage SSW TL-I-II Spent Fuel Storage SW TL-I-12 Spent Fuel Storage WSW TL-I-13 Spent Fuel Storage W TL-I-14 Spent Fuel Storage WNW TL-I-15 Spent Fuel Storage NW TL-I-1 6 Spent Fuel Storage NNW

• ISFSI TLD locations are on site within 340 meters of the spent fuel storage facility.

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TABLE 4.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements Airborne Particulate i Fish*&

Analysis Water or vertebrates IGasn

___________. (pCi/rn 3 )(pCi/kgwet)

Gross-Beta 4 0.01 H-3 2000*

Mn-54 15 130 Co-58,60 15 130 Zr-Nb-95 15 Cs-134 15 0.05 130 Cs-137 18 0.06 150 Ba-La-140 15

• If no drinking water pathway exists, a value of 3000 pCi/l may be used.

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TABLE 4.5 Reporting Levels for Radioactivity Concentrations In Environmental Samples Particulates Fish &

Analysis Water orGases Invertebrates

Ci/mn 3 ). (pCi/kg wet)

H-3 20,000 Mn-54 1000 30,000 Co-58 1000 30,000 Co-60 300 10,000 Zr-Nb-95 400 b Cs-134 30 10 1000 Cs-137 50 20 2000 Ba-La-140b 200

' If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

bParent only.

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Ficure 4.1 Environmental Radiological Sampling Locations (within 1 KM) 17 AU-DI

Figure 4.2 Environmental Radiological Sampling Locations (outside 1 KM) 4" _" PftQ _~fift 3.0 C"Vop im. CWp NW CPO a TOM. me.

18 t- 0 n

Figure 4.3 Direct Radiation Monitoring Locations (outside 1 KM) 19 b

5.0 RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples, which were collected during the first half of 2005. These results, shown in Table 5.1, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide.

The units for each media type are also given.

The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 2004, and the number of measurements (if any) which exceeded the Reporting Levels found in Table 2.5 of the ODCM. Measurements exceeding the Reporting Levels are classified as "Non-Routine" measurements. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides that have detection capability requirements as specified in the ODCM Table 2.4. The absence of a value in this column indicates that no LLD is specified in the ODCM for that radionuclide in that media. The target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. Occasionally, the required LLD is not met. This is usually due to malfunctions in sampling equipment, or lack of sufficient sample media (i.e., low sample volume. Such cases, if any, are addressed in Section 6.2.

For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations: (1) the indicator or Zone 1 stations, which are within the range of influence of the site and which could conceivably be affected by remediation and decommissioning activities on-site; (2) the station within Zone 1 or Zone 2 which had the highest mean concentration during the first half of 2005 for that radionuclide; and (3) the control or Zone 2 stations, which are beyond the influence of the site operations. Environmental TLD or direct radiation monitoring stations are grouped into either an Inner Ring, an Outer Ring, or Control category.

In each of these columns, for each radionuclide, the following statistical values are given:

• The mean value of all concentrations, including negative values and values considered "not detectable".

• The lowest and highest concentration.

• The number of detectable measurements divided by the total number of measurements.

For example, (4/20) would indicate that 4 of the 20 samples collected in 2005, for that 20

sample type and that radionuclide, contained detectable radioactivity.

A sample is considered to yield a "detectable measurement" when the concentration exceeds three times its associated standard deviation. The standard deviation on each measurement represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure.

The radionuclides reported in this section represent those that: 1) had an LLD requirement in Table 2.4 of the ODCM, or a Reporting Level listed in Table 2.5, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of specific interest for any other reason. The radionuclides routinely analyzed and reported by the FANPEL for a gamma spectroscopy analysis are: Ac-Th-228, Ag-108m, Ag-l OInm, Ba-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131, K-40, La-140, Mn-54, Nb-95, Ru-103, Ru-106, Sb-124, Sb-125, Se-75, Zn-65 and Zr-95. In no case did a radionuclide not shown in Table 5.1 appear as a "detectable measurement" during 2005.

The complete listing of quarterly TLD data is provided in Table 5.3.

21

Table 5.1 Radiological Environmental Program Summary Maine Yankee, Wiscasset, ME (2005)

MEDIUM: Demolition Air Particulates (AP) UNITS: PCiIcubic meter Indicator Stations Station With Highest Mean Control Stations Radionuclides- Mean Station Mean Mean (No. Analyses) Required Range Range Range (Non-Routine-) LLD (No. Detected,") (No. Detected-) (No. Detected--)

GR-B (25) 0.01 1.7z -2 68 2.9E -2 SO DATA (0) ( 5.3 - 29.9)E -3 ( 2.8 - 3.0)E -2 (25/ 25) (2/ 2)

Be-T (6) -e.3z -' 73 6.2E -2 NO DATA (0) ( -1.3 - 0.6)1 -1 (0/ 6) (0/ 1)

K-40 (6) 4.5E -2 22 1.9E -1 NO DATA (0) ( -2.2 - 19.0)Z -2 (0/ 6) (O/ 1)

Mn-54 (6) -7.68 -4 22 4.0z -3 NO DATA (0) ( -4.4 - 4.0)1 -3 (0/ 6) (0/ 1)

Co-58 (6) -3.41 -3 67 2.1Z -2 NO DATA (0) ( -3.1 - 2.1)K -2 (0/ 6) (0/ 1)

Co-60 (6) 6.7E -4 57 5.1z -3 NO DATA (0) ( -5.3 - 5.1)1 -3 (0/ 6) (0/ 1)

Cs-134 (6) 0.05 1.81 -4 22 6.8z -3 NO DATA (0) C -9.8 - 6.8)1 -3 (0/ 6) (0/ 1)

Cs-137 (6) 0.06 4.8Z -3 67 1.4Z -2 NO DATA (0) ( -1.7 - 14.0)Z -3 (0/ 6) (O/ 1)

Th-232 (6) -7.9E -3 22 2.0Z -2 NO DATA (0) ( -4.6 - 2.0)1 -2 (0/ 6) (0/ 1)

Footnotes to Table 5.1:

• The radionuclides reported in this table are those that: t) had an LLD requirement in ODCM Table 2.4, or a Reporting Level in ODCM Table 2.5. or 2) had a positive measurement of radioactivtty, whether it was naturally occuring or man-made; or 3) were of specific interest for any other reason.

• -Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 2.5.

- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown In parentheses.

22

Table 5.1 Radiological Environmental Program Summary Maine Yankee, Wiscasset, ME (2005)

MEDIUM: Lobster (HA) & Rock Crabs (CR) UNrTS:vClikg Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range (Non-Routine*) LLD (No. Detected-) (No. Detected*-) (No. Detected-)

Be-7 (4) 5.3X 1 24 8.22 1 NO DATA (0) ( 1.8 - 12.9)Z 1 ( 3.4 - 12.9)X 1 (O/ 4) (O/ 2)

K-40 (4) 1.7E 3 24 2.03 3 NO DATA (0) ( 1.4 - 2.1)E 3 ( 1.8 - 2.1)3 3 (4/ 4) (2/ 2)

Mn-54 (4) 130 8.0K -1 11 4.43 0 NO DATA (0) ( -7.4 - 6.0)E 0 ( 2.8 - 6.0)E 0 (O/ 4) (0/ 2)

Co-58 (4) 130 4.6Z 0 11 8.13 0 NO DATA (0) -1.6 - 13.6)E 0 ( 2.5 - 13.6)Z 0 (0/ 4) (0/ 2)

Fe-59 (4) 260 1.O 0 24 1.33 1 NO DATAA (0) -2.3 - 1.9)E 1 ( 7.0 - 19.0)3 0 (0/ 4) (0/ 2)

Co-60 (4) 130 -6.0Z -1 24 2.33 0 NO DA~TA (0) -7.0 - 3.0)E 0 ( 1.6 - 3.0)E 0 (0/ 4) (0/ 2)

Zn-65 (4) 260 -1.7Z 1 11 -7.03 0 NO DATA (0) -3.6 - -0.7)3 1 ( -7.0 - -7.0)Z 0 (O/ 4) (0/ 2)

Cs-1134 (4) 130 3.9Z 0 24 5.03 0 NO DATA (0) -2.6 - 12.6)3 0 ( -2.6 - 12.6)1 0 (O/ 4) (0/ 2)

Cs-137 (4) 150 5.53 -1 11 5.13 0 NO DATA (0) -7.1 - 10.2)E 0 ( 0.0 - 1.0)E 1 (0/ 4) (0/ 2)

Th-232 (4) O.O 0 11 1.13 1 NO DATA (0) -2.1 - 1.1)3 1 ( 1.0 - 1.1)3 1 (O/ 4) (0/ 2)

Footnotes to Table 5.1:

• The radionudides reported In this table are those that: 1) had an LLD requirement In ODCM Table 2.4, or a Reporting Level In ODCM Table 2.5, or 2) had a positive measurement of radioactivity, whether it was naturally occuring or man-made; or 3) were of specific interest for any other reason.

-Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 2.5.

• - The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown in parentheses.

23

Table 5.1 Radiological Environmental Program Summary Maine Yankee, Wiscasset, ME (2005)

MEDIUM: Fish (FH) UNITS: vCI/kq Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Station Mean Mean (No. Analyses) Required Range Range Range (Non-Routine-) LLD (No. Detected-) (No. Detected-*) (No. Detected-)

Be-7 (2) -7.13 1 24 3.3Z 1 3.3E 1 (0)

(0/ 1) (O/ 1) (Of 1)

K-40 (2) 2.1E 3 24 2.2z 3 2.2E 3 (0)

(2/1 / 1)(if 1)

Mn-54 (2) 130 O.O 0 24 6.3Z 0 6.33 0 (0)

(Of 1) (Of 1) (Of 1)

Co-58 (2) 130 O.O 0 24 1.9Z 0 1.93 0 (0)

(Of 1) (Of 1) (Of 1)

Fe-59 (2) 260 2.03 1 11 2.03 1 6.03 0 (0)

(O 1) (Of 1) (O0 1)

Co40 (2) 130 6.43 0 11 6.43 0 -1.3Z 0 (0)

(O 1) (O 1) (of 1)

Zn-ES (2) 260 -9.OE 0 11 -9.O3 0 -1.63 1 (0)

(O 1) (O 1) (O 1)

Cs-134 (2) 130 -7.3E 0 24 7.83 0 7.8E 0 (0)

(O 1) (Of 1) (o/ 1)

Cs-137 (2) 150 7.23 0 11 7.23 0 7.03 0 (0)

(Of 1) (O/ 1) (Of 1)

Footnotes to Table 5.1:

• The radionuclides reported In this table are those that: 1) had an LLD requirement In ODCM Table 2.4, or a Reporting Level in ODCM Table 2.5, or 2) had a positive measurement of radioactivity, whether it was naturally occuring or man-made; or 3) were of specific interest for any other reason.

"Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 2.5.

The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.

24

Table 5.1 Radiological Environmental Program Summary Maine Yankee, Wiscasset, ME (2005)

MEDIUM: Mussel (MU) UNITS: oCi/kq Indicator Stations Station With Highest Mean Control Stations Radionuclides* Mean Station Mean Mean (No. Analyses) Required Range Range Range (Non-Routine-) LLD (No. Detected-) (No. Detected-) (No. Detected-^)

Be-7 (2) -4.5Z 1 24 1.2E 2 1.21 2 (0)

(0/ 1) (0/ 1) (0/ 1)

K-40 (2) 1. OE 3 24 1.2E 3 1.21 3 (0) 0)(1/ 1) (1/ 1)(1/ 1)

Mn-54 (2) 130 2.71 0 24 1.1E 1 1.11 1 (0)

(0/ 1) (O/ 1) (0/ 1)

Co-58 (2) 130 1.31 1 11 1.31 1 8.11 0 (0)

(0/ 1) (0/ 1) (0/ 1)

Fe-59 (2) 260 3.21 1 11 3.2Z 1 -2.3E 1 (0)

(0/ 1) (0/ 1) (0/ 1)

Co-S0 (2) 130 1.51 0 24 1.91 1 1.91 1 (0) 0)(O/ 1) (0/ 1) (0/ 1)

Zn-65 (2) 260 -3.0E 0 11 -3.0E 0 -7.0Z 0 (0)

(0/ 1) (Of11{1)

Cs-134 (2) 130 -2.01 0 24 8.11 0 8.1Z 0 (0)

(0 0/ 1) (0/ 1) (Ox/ 1)

Cs-137 (2) 150 -1.91 0 24 0.O1 0 O.O 0 (0)

(0/ 1) (0/ 1) (0/ 1)

Footnotes to Table 5.1:

• The radionudides reported in this table are those that: 1) had an LLD requirement In ODCM Table 2.4. or a Reporting Level In ODCM Table 2.5. or 2) had a positive measurement of radioactivity whether it was naturally occuring or man-made; or 3) were of specific Interest for any other reason.

"Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 2.5.

- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown in parentheses.

25

Table 5.1 Radiological Environmental Program Summary Maine Yankee, Wiscasset, ME (2005)

MEDIUM: EstuaryWater (WE) UNiTS: DCi/kq Indicator Stations Station With Highest Mean Control Stations Radionuclides- Mean Station Mean Mean (No. Analyses) Required Range Range Range (Non-Routine-) LLD (No. Detected-) (No. Detected-) (No. Detected--)

H-3 (4) 3000 -8.5E 1 14 -8.53 1 -6.5Z 2 (0) -1.1 - -0.6)Z 2 (-1.1 - -0.6)E 2 (-7.0 - -6.0)3 2 (0/ 2) (0/ 2) (0/ 2)

K-40 (12) 1.9Z 2 14 1.93 2 1.43 1 (0) 1.3 - 2.3)Z 2 (1.3 - 2.3)E 2 1.0 - 43.2)E 0 (6/ 6) (6/ 6) (2/ 6)

Mn-54 (12) 15 -2.8e -2 20 6.7E -2 6.7Z -2 (0) -5.0 - 6.0)Z -1 ( -1.1 - 1.1)3 0 -1.1 -1.1) 0 (0/ 6) (0/ 6) (0/ 6)

Co-58 (12) 15 9.0Z -1 14 9.03 -1 -1.9Z -1 (0) (-6.4 - 28.0)Z -1 (-6.4 - 28.0)z -1 -1.2 -0.6)Z 0 (0/ 6) (0/ 6) (0/ 6)

Fe-59 (12) 30 -1.63 0 20 -7.7E -1 -7.73 -1 (0) -5.5 - 2.7)Z 0 (-5.7 - 2.9)3 0 -5.7 - 2.9)E 0 (0/ 6) (0/ 6) (0/ 6)

Co-60 (12) 15 4.OZ -2 20 6.4Z -1 6.4Z -1 (0) -4.1 - 16.0)E -1 (-4.8 - 42.0)E -1 -4.8 - 42.0)Z -1 (0/ 6) (0/ 6) (0/ 6)

Zn-65 (12) 30 -8.1E -1 20 -3.1Z -1 -3.1Z -1 (0) -1.7 - 0.3)Z 0 ( -1.3 - 1.1)E 0 -1.3- 1.1) 0 (0/ 6) (0/ 6) (0/ 6) zi-95 (12) 15 -1.7Z -3 20 9.0Z -1 9.0Z -1 (0) -1.6 - 2.7)Z 0 (-7.1 - 52.0)3 -1 (-7.1 -52.0)Z -1 (0/ 6) (0/ 6) (0/ 6)

Cs-134 (12) 15 -2.6E -1 20 7.2E -1 7.2E -1 (0) -1.1 - 1.3)3 0 (2.1 - 20.0)3 -1 2.1 - 20.0)3 -1 (0/ 6) (0/ 6) (0/ 6)

Cs-1137 (12) 18 1.33 -1 20 4.53 -1 4.5E -1 (0) -9.1 - 13.0)Z -1 (-9.0 - 100.0)3 -2 -9.0 - 100.0)Z 2 (0/ 6) (0/ 6) (0/ 6)

Ba-i40 (12) 15 -2.1Z 1 14 -2.1Z 1 -4.3Z 1 (0) -6.3 - -0.2)Z 1 (-6.3 - -0.2)Z 1 -2.6 - 0.3)Z 2 (0/ 6) (0/ 6) (0/ 6)

Footnotes to Table 5.1:

• The radionudides reported in this table are those that: 1) had an LLD requirement in ODCM Table 2.4 or a Reporing Level in ODCM Table 2.5, or 2) had a positive measurement of radioactivity whether It was naturally occuring or man-made; or 3) were of specific interest for any other reason.

"Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 2.5.

• -- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.

26

TABLE 5.2 ENVIRONMENTAL TLD DATA

SUMMARY

MAINE YANKEE, WISCASSET, ME (JANUARY - JUNE 2005)

(plRhr)

ISFSI TLDs STATION WITH HIGHEST MEAN CONTROL TLDs 0******** ** *** ** ******* ******************************* ******************

MEAN t S.D. MEAN +/- S.D. MEAN

• S.D.

RANGE STA. RANGE RANGE (NO. MEASUREMENTS)* NO. (NO. MEASUREMENTS)* (NO. MEASUREMENTS)*

9.2 +/- 1.5 TL-I-1 1 13.0 +/- 0.5 9.0 +/- 1.2 6.9 - 13.3 12.6 13.3 7.8 - 10.0 32 2 4

• Each "measurement is based on quarterly readings.

NOTE: S.D. = standard deviation.

27

TABLE 5.3 2005 Environmental ISFSI and Control TLD Measurements (Micro-R per hour)

Semi-Annual Sta. Direction From Ist Quarter 2nd Quarter Ave.

No. Centerline of ISFSI Exp. Exp.

TiLl-01 N 8.6 8.4 8.5 TL-1-02 NNE 8.6 7.7 8.2 TL-1-03 NE 9.2 8.7 9.0 T[A1-04 ENE 8.6 8.0 8.3 TL-I-05 E 8.6 6.9 7.8 TL-I-06 ESE 10.0 12.3 11.2 TL-I-07 SE 8.1 8.7 8.4 TL,1-08 SSE 9.4 8.7 9.1 TLA1-09 S 11.1 11.6 11.4 TL-1-10 SSW 8.3 8.0 8.2 TL-1-1 I SW 13.3 12.6 13.0 TL-1-12 WSW 8.1 8.4 8.3 TL-1-13 W 7.8 9.4 8.6 TL--14 WNW 9.7 9.1 9.4 TL-1-15 NW 8.9 9.8 9.4 TL-1-16 NNW 8.3 10.5 9.4 TL-36 Boothbay Harbor 8.1 10.0 9.1 71-37 Dresden Substation 7.8 10.0 8.9 28

6.0 ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Sampling Program Deviations Table 2.3 of the Offsite Dose Calculation Manual (ODCM) allows for deviations in the REMP sampling schedule "if specimens are unobtainable due to hazardous conditions, to seasonal unavailability or to malfunction of sampling equipment." Such deviations do not compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for any radiological environmental monitoring program. The deviations during 2005 to the end of the plant decommissioning are as follows:

• At the completion of the decommissioning process (June of 2005 marks the end of liquid discharges from the Maine Yankee site), a final set of estuary water samples were submitted for analysis for the month of June, and an ODCM change was submitted to eliminate this requirement. However, this change was not processed in a timely manner and the requirement remained in the ODCM beyond the departure date of qualified REMP personnel.

• Fish and invertebrate samples are required to be collected in season, or semiannual if not seasonal. Typically, these are collected semiannually in the months of June and again in September. However, due to an injury to Maine Yankee's licensed commercial fisherman, the collection of these samples could not be completed until August for the first sample period.

In addition, Table 2.3, Section la of the ODCM required the change out of the demolition air particulate samples at least weekly. In some cases, these samples were in continuous operation for more than a 1 week period (see below):

• AS-5, and AS-73 were in operation from 1/13/05-1127105

• AS-5, AS-57, and AS-73 were in operation from 2127/05- 3/13/05

• AS-5, AS-57 and AS-73 were in operation from 3/13/05- 4/10/05 Although the collection period for these samples are longer than what is specified by the ODCM, it should be noted that the ODCM only required these samples for the active demolition of buildings that were no longer tied to existing ventilation systems and had large permanent openings to the environment. In the year 2004, all buildings within the restricted area were demolished and the remaining work activities for 2005 were soil remediation and waste disposal. Technically, these 29

samples were not required by the ODCM but were collected as a good practice due to the creation of dust during this work.

6.2 Comparison of Achieved LLDs with Requirements Table 2.4 of the ODCM gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. (This table is duplicated in Table 4.4 of this report.) Occasionally an LLD is not achievable due to a situation such as a low sample volume caused by sampling equipment malfunction. In such a case, ODCM Appendix C, Section 1 requires a discussion of the situation.

At the FANPEL, the target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. Expressed differently, the typical sensitivities achieved for each analysis are at least 2.5 to 3 times greater than that required by the Maine Yankee ODCM.

For each analysis having an LLD requirement in ODCM Table 2.4, the a posteriori(after the fact)

LLD, or Minimum Detectable Concentration (MDC) calculated for that analysis was compared with the required LLD. During the collection period covered by this report in 2005 (to completion of plant site decommissioning), approximately 300 analyses had an LLD requirement listed in Table 2.4. There were twelve instances where the sample analysis failed to meet the required LLD. Six instances occurred with gross beta analyses for Demolition Particulate Samples due to relatively low air volumes collected (small sample size) during the sampling times associated demolition activities. Six other instances of missed detection sensitivity occurred with Surface Water (Estuary) samples (three sets of two sample locations) where the analysis for Ba- 140 (gamma isotopic analysis) was not achieved due to long decay time (half life for Ba-140 equals 12.75 days) from sample collection to sample receipt at the analysis laboratory. Appendix A lists the results of all environmental sample analyses for 2005 to the end of plant decommissioning. Each of the occurrences of an analysis not meeting its specific required detection sensitivity is marked in the right hand column with a (+) and the actual MDC achieved for each analysis. For Ba-140, the ODCM indicates that the LLD in water samples is 15 pCi/kg. Due to the number of years since Maine Yankee permanently shutdown, it is not credible that any plant related Ba-140 could still remain.

6.3 Comparison of Results against Reporting Levels Section 2.4.3.3 of the ODCM requires the notification of the NRC (via the Annual Radioactive Effluent Release Report) whenever a Reporting Level in ODCM Table 2.5 is exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. It should be noted that environmental concentrations are averaged over 30

calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to site effluents. During this period, no Reporting Levels were exceeded.

31

6.4 Data Analysis by Media Type The 2005 REMP data for each media type is discussed below. Whenever a specific measurement result is presented, it is given as the concentration plus or minus one standard deviation. This standard deviation represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. A sample is considered to yield a "detectable measurement" when the concentration exceeds three times its associated standard deviation. With respect to data plots, it should be noted that all values for a given graph are plotted, whether or not they are considered statistically significant (detectable).

6.4.1 Airborne Pathways 6.4.1.2 Demolition Air Particulates (AP Demo)

As required by ODCM Table 2.3 (Table 4.1 of this report), when a building is undergoing demolition activities, a continuous particulate air sample is collected weekly onsite in the vicinity of the work and analyzed for gross beta radioactivity. This information is considered a supplement to the standard off- site monitoring program and provides information on site area airborne particulates associated with demolition of plant structures due to their close proximity to any potential sources. At a minimum, a composite of the filters from each location collected during the quarter is then analyzed for gamma isotopic radioactivity. In addition, individual filters are required to be analyzed for gamma constituents if gross beta activity is greater than five times the yearly mean of the control station samples. During the conduct of the REMP in 2005, a total of six locations were monitored and the results of the sampling program are provided in Table 5.1. The data is presented in the same format as for the routine REMP air samples discussed above. During the 2005 collection period, none of these sites indicated positive gamma isotopic radioactivity results for particular isotopes.

6.4.2 Waterborne Pathways 6.4.2.1 Estuary Water (WE)

Grab samples of estuary water were collected weekly at the boat dock, (WE-14), in the Back River near the plant discharge. These samples were composited monthly and sent to the FANPEL for analysis. Grab samples were also collected at the control location (WE-20). Table 5.1 shows that naturally-occurring K-40 was detected in samples collected at both WE-14 and WE-20. This is 32

typical at these two locations. The monthly samples were again composited by FANPEL each quarter, by station, for tritium (H-3) analyses. Table 5.1 shows that neither the WE-14 nor the control location samples contained detectable tritium. Figure 6.1 provides a historical trend plot for quarterly composite H-3 concentrations at WE-12 and WE-14. All concentrations are plotted regardless of whether they are considered "detectable" or "not detectable". Those concentrations determined to be positive as defined in Section 5 are indicated with a solid black symbol. A plot for WE-20 is also indicated. As shown in Figure 6. 1, no detectable tritium in estuary waters was found during 2005. For previous years, all detectable tritium concentrations were well below the Reporting Level for tritium in non-drinking water of 30,000 pCi/L.

6.4.3 Ingestion Pathways 6.4.3.1 Fish (FH) & Invertebrates (CR, HA, MU)

Up to the time of completion of the plant site decommissioning, samples of fish (FH) and invertebrates (lobster (HA), rock crab (CR) and blue mussel (MU)) were collected from locations -

11 and -24 in 2005. The edible portions of each of these biota were analyzed for gamma-emitting radionuclides. As expected in biological matter, naturally occurring K-40 was detected in all fish and invertebrate samples. No plant site related radionuclides were detected.

6A.4 Direct Radiation Pathway (TL)

The TLD's are collected on a calendar quarter basis for readout. At the mid-year change-out in the TLD program, direct radiation was continuously measured at 18 locations surrounding the Maine Yankee ISFS1. In 2000, TLD locations surrounding the Independent Spent Fuel Storage Installation (ISFSI) were selected for inclusion in the site's measurement program to collect base line data near the ISFSI before the transfer of radioactive materials to the facility. Figures 6.2 through 6.5 indicate exposure trends prior to, during and following placement of spent fuel and waste material canisters on the storage pad.

As can be seen in Figures 6.2 to 6.5, there is a distinct annual cycle at both indicator and control locations. The lowest point of the cycle occurs during the winter months. This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another. Two off-site locations provide background exposure trend data for the area to assist in the assessment of ISFSI radiation in the local area above background.

33

Figures 6.2 through 6.5 illustrate the exposure rate history for the on-site environmental TLD's located within 1,100 feet surrounding the ISFSI in each of the sixteen major compass directions.

The data record begins before any radioactive material was placed in the facility, through the fourteen month transfer period of storage canisters to the ISFSI, and following completion of all transfers in early 2004. Most of the TLD locations indicate little or no significant change in exposure rate from the pre-operational period to the current period in 2005. However, three locations, TL-I-6, TL-I-9 and TL-I-1 1, do appear to reflect an increase from the pre-operational conditions. Both TL-I-6 (ESE, within 550 feet of ISFSI pad center) and TL-I-9 (South, within 500 feet of pad center) are on-site and border a water boundary to the ISFSI site area, the Back River.

Location TL-I-1 1 is the closest environmental TLD to the storage pad in any of the sixteen sectors and records the highest exposure rate response of any of the environmental set. It is situated in the SW sector, approximately 375 feet from the center of the ISFSI. None of the three locations are near a site property line which could be occupied by members of the public. The closest on-site TLD locations to the site property line are TL-I-3 and TL-I-4, each about 1000 feet away from the ISFSI in the NE and ENE sectors, respectively. Neither of these locations show any change in exposure rate from the pre-operational period through to the full ISFSI configuration in 2004 and through the second quarter of 2005.

34

FIGURE 6.1 H-3 IN ESTUARY WATER 2900 - 2900 2500 - 2500 2100 - 2100 1700 1700 o 1300 1300 go900 900 500 j\j500 100lo

-300 -300

-700 -700 1989 1991 1993 1995 1997 1999 2001 2003 2005

-- WE- 12 Plant Outfall x WE-20 Kennebec River

- -*-- WE- 12 Positive Concentrations

- WE-14 Boat Dock WE-1 4 Positive Concentration 35 (7 7t-C

FIGURE 6.2 EXPOSURE AT ISFSI TLDS TL-I TL-I-04 25 25 12/27/01 First 2/19/04 Last Fuel Fuel Canister Canister Placed on Placed on ISFSI ISFSI 20 20 14 15 15 E10 10 5 5 0 . . . . . . 0.

2000 2001 2002 2003 2004 2005 Retrieval Date

-- TL-I-01 TL-1-02

- TL-1-03 x TL-1-04 x Average of Control TLDs 36 C-C

FIGURE 6.3 EXPOSURE AT ISFSI TLDS TL-I TL-I-08 30 30 25 25 20 20 0)

_4 oN S 15 15 10 10 5 5 0 0 2000 2001 2002 2003 2004 2005 Retrieval Date

-0E-- TL-1-05

- TL-1-06 TL-I-07 X TL-1-08 X Average of Control TLDs 37

FIGURE 6.4 EXPOSURE AT ISFSI TLDS TL-I TL-I-12 35 35 2/19/04 Last Fuel Canister 12/2/01 irstPlaced on ISFSI 30 Fuel Canister P 30 25 25 20 20 1 15 10 10 5 5 2000 2001 2002 2003 2004 2005 Retrieval Date TL-I-09 TL-I- 0

- TL-1-1 I X TL-I-12

-x- Average of Control TLDs 38

FIGURE 6.5 EXPOSURE AT ISFSI TLDS TL-I TL-I-17 35 35 30 12/27/01 First 2/19/04 Last Fuel 30 Fuel Canister Canister Placed on ISFSI Placed on:

25 25 20 20

&15 15 10 10 5 5 0 . . . . . . . . 0 2000 2001 2002 2003 2004 2005 Retrieval Date TL-1-13

--- TL-1-14

- TL-1-15 x TL-1-16

- TL-1-17 X Average of Control TLDs 39

7.0 QUALITY ASSURANCE PROGRAM The quality assurance program at the AREVA Framatome ANP Environmental Laboratory (FANPEL) is designed to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, measurement and reporting of data, as well as the record keeping of the final results. Quality control, as part of the quality assurance program, provides a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements.

The FANPEL employs a comprehensive quality assurance program designed to monitor the quality of analytical processing to ensure reliable environmental monitoring data. The program includes the use of controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits by external groups, a laboratory quality control program, and a staff training program. Monitoring programs include the Intralaboratory Quality Control Program administered by the Laboratory QA Officer (used in conjunction with the National Institute of Standards and Technology Measurement Assurance Program, NIST MAP) and a third party cross check program administered by Analytics, Inc. Together these programs are targeted to supply QC/QA sources at 5% of the client sample analysis load. In addition a blind duplicate program is conducted through client environmental monitoring programs.

This summary reports all intralaboratory and third party results received by FANPEL on or before June 30, 2005.

7.1 Intralaboratory Quality Control Program The FANPEL QA Officer administers an extensive intralaboratory quality control program in which process check samples are submitted for analysis. These samples are "spiked" with a known amount of radioactive material and are routinely submitted in triplicate to evaluate the bias and precision of a measurement process. Table 7.1 provides the summary of the process check results for January to June 2005. Of the 275 analyses, 100% passed the bias criteria and 100% of the 45 results evaluated for precision were acceptable. The FANPEL internal acceptance criteria are summarized at the end of Table 7. 1.

40

7.2 Third Party Cross Check Program The FANPEL participates in a third party cross check program managed by Analytics Inc. to satisfy the requirement of the Environmental Technical Specification/ODCM. The FANPEL Analytics program was originally used to augment the EPA Intercomparison Program that it now replaces. The current program is designed to be comparable to the pre-1996 EPA PE Program in terms of the number of samples, matrices and nuclides. The results for the Vst quarter 2005 through the 2ud quarter 2005 are summarized in Table 7.2. Each sample is normally analyzed in triplicate and the results are evaluated against the internal acceptance criteria described in the FANPEL Manual 100-Laboratory Quality Assurance Plan. This acceptance protocol is used for all interlaboratory programs with no pre-set acceptance criteria.

When results fall outside of the acceptance criteria, an investigation is initiated to determine the cause of the problem and if appropriate, corrective measures are taken. The FANPEL internal acceptance criteria are summarized at the end of Table 7.1.

7.3 Blind Duplicate Program Under the Blind Duplicate Quality Assurance Program, samples are split from homogeneous environmental media by the client and sent to the FANPEL for analysis. They are "blind" in that the identification of the matching sample is not identified to the Laboratory.

Participating clients submitted a total of 9 paired samples in 2005. The measurements evaluated include twenty-six gamma emitting radionuclides, H-3, Sr-89/90, and gross beta.

All measurements are evaluated, whether the results are statistically positive or not, and whether the net concentration is positive or negative.

The samples submitted as part of this program are listed in Table 7.3. For the 2005 mid-year program, 99.8% (486/487) of the measurements met the FANPEL internal acceptance criteria.

41

Table 7.1 INTRA-LABORATORY ENVIRONMENTAL PROCESS CONTROL RESULTS BY FRAMATOME ANP ENVIRONMENTAL LABORATORY ACCEPTANCE CRITERIA, MEDIA, AND MEASUREMENT CATEGORIES JANUARY-JUNE 2005 Bias Criteria (1) Precision Criteria (2), (3) 11 2 3 4 11 2 3 4 I. Air Particulate iBeta 124 S 0 0 0 0 Gamma -

II. Air Charcoal Gamma-Quantitative 2 2 0 0 Gamma - Screening 55 11 3 0 l.i Milk Gamma - I Iodine (L - _

Sr-O 4 1 0 0 1 5 0 0 0 O

Sr-50 5 0 0 0 1 5 O 0 0 IV. SollUSed.

Am-241 - - [ -I [ -

Gamma 1 r Pu-239

. Water An-241 2 0 8 0 2 0 8 0 C-14 2 3 3 0 0 0 8 0 Fe-65 1 3 3 0 0 0 4 0 Gross Aipha 8 3 7 0 0 0 6 0 Gross Beta 6 15 1 0 6 0 0 0 Gamma 3 5 0 0 0 0 8 0 Iodine (LL4 - - - - - - -

Ni-63 3 1 2 0 0 0 4 0 Pu-238 1 5 0 0 0 0 6 0 Pu-241 0 5 3 0 0 0 8 0 Sr-90 2 0 4 0 0 0 6 0 Tritium 11 8 0 0 15 2 2 0 Tc-99 4 1 2 0 0 0 8 0 TotalNumber 233 6S 36 0 33 2 68 0 In Range:

Percentage of 69.1 20.2 10.7 0.0 32.0 1.9 66.0 0.0 Total Processed:

Sum of Analyses: 337 103 (1) Percent Bias by Deviation Categoryas noted in Table 1, Footnote (1)

(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)

(3) Most Precision data generated from non-positive client samples for specilic contractual evaluation Total may not equal 100 due to rounding 42

Table 7.2 FRAMATOME ANP ENVIRONMENTAL LABORATORY ANALYTICS RADIOCHEMISTRY CROSS-CHECK PERFORMANCE EVALUATION

_ Mean Ratio Sample Quarterl Sample l Reported Known E-LABI l Number Year Media Nuclide Units Value Value Analyics Evaluation Al lti=-1b2 r iquid LrU 12zt4U4

- =CC 0l1 Agreement A17777-162 1sU12005 Liquid Sr-89 uCiucc 1.62E-03 1.63E-03 0.99 Agreement A17777-162 isi2005 Liquid Sr-90 uCicc 1.84E-04 2.06E-04 0.89 Agreement A18125 162 2ndr2UO6 Liquid Fe-6 uCilcc 1.38E-3 A18126-162 2nd/20O5 Liquid Sr-89 uCilcc 1.04E-03 A18126-162 2ndr2005 Liquid Sr-90 uCu/cc 9-14E44

- Results subnitted to Analytcs, pending final report issuance.

43

Table 7.3

SUMMARY

OF BLIND DUPLICATE SAMPLES January - June 2005 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Ground Water 1 Surface Water 6 Algae 1 Mussels 1 TOTAL 9 44

8.0 LAND USE CENSUS 8.1 REQUIREMENTS FOR LAND USE CENSUS As required by section 2.4.4 of the Maine Yankee Offsite Dose Calculation Manual (Change 31, Reference 8), a Land Use Census was conducted for the areas surrounding the Maine Yankee Atomic Power Station site in 2005. The Land Use Census is required at least once per 12 months between the dates of June 1 st and October ISt.

8.2 BACKGROUND

The Maine Yankee "plant" has been fully demolished, and the decommissioning of the Non-Independent Spent Fuel Storage Facility (ISFSI) lands have passed a final status survey for unrestricted use. The remaining structures on the Maine Yankee site are the Security Operations Building for the Independent Spent Fuel Storage Installation and the Vertical Concrete Casks' (VCC's), which store's the stations spent nuclear fuel. The design of the Universal MPC System (UMS) storage canisters are approved by the Nuclear Regulatory Commission and are considered to be leak tight as defined in ANSI N14.5-1997. The leakage analysis for normal, off normal, and accident conditions as described in Chapter 7 of NUREG-1536 and Interim Staff Guidance are unnecessary. Consequently, based on the leak tight configuration, there is no release of radioactive material during ISFSI operations or accident conditions. Therefore, the Maine Yankee ODCM has been revised to remove the environmental sampling and analysis sections relating to effluent releases.

8.3 LAND USE CENSUS Historically, the Land Use Census required the identification of the nearest resident, garden and nearest milk animal. These analyses were appropriate due to the past potential for gaseous effluent releases from the Maine Yankee site. However, due to completion of the Maine Yankee decommissioning and the leak tight UMS canister design for the Maine Yankee ISFSI, the nearest garden and milk section of the Land Use Census is no longer necessary. Therefore, the only remaining section applicable to the Maine Yankee site is the identification of the nearest resident for external dose calculations for compliance with dose limitations and dose calculations from direct radiation from accident conditions.

As a result of this assessment, no new residences were identified in 2005 which were different from the 2004 Land Use Census as documented in Table 8.1. Although, an entity named "Point East" has intentions of developing the land that was purchased from Maine Yankee that is located just North of Old Ferry Road. As development in this area progresses, future Land Use Census for the nearest resident may result in revisions to Table 8.1. However, since current environmental TLD's are located within the Maine Yankee site boundary, it is not 45

expected that additional monitoring locations will be required, unless the site boundary is reduced and the public use of the current Maine Yankee land changes.

Basis: Compliance with direct radiationdose limitationsis demonstratedby TLD measurements stationedat the perimeterof the site boundary. As specified by section 2.4.4 of the ODCM, the addition of new sampling locations is limited to those location'sthat yield a dose commitment at least twice the dose commitment at any location currentlybeing sampled.

The area of development is currently beyond the areas currently assessed for direct radiation by means of environmental TLD measurements.

46

TABLE 8.1 2005 LAND USE CENSUS LOCATIONS SECTOR NEAREST NEAREST NEAREST MILK RESIDENCE+ GARDEN ANIMAL km (miles) km (miles) km (miles)

N 1.26 (0.78) .

NNE 2.23 (1.38) 2.40(1.49) 2.65 (1.7) (Cows)

NE 1.27(0.79) 1.47(0.91)

ENE 0.92 (0.57) 1.25 (0.78)

E 0.90 (0.56) 0.90 (0.56)

ESE 0.70 (0.43)

SE 0.70(0.43) 0.90 (0.56)

SSE 0.90 (0.56) 0.90 (0.56)

S 1.70 (1.06) 1.70 (1.06)

• SSW 3.00(1.86) 5.0 (3.11)

• SW 1.50 (0.93) 4.0 (2.48)

• WSW 0.96 (0.60) 1.94 (1.20) 1.88 (1.2) (Cows)

W 0.81 (0.50) 2.71 (1.68)

• WNW 1.90 (1.18) *

• NW 1.93 (1.20) 1.93 (1.20)

NNW 1.06 (0.66) 1.18 (0.73)

• No location was identified within 5 miles of the site.

No new location identified different from location in 2004.

47

9.0 REFERENCES

1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

2. NCRP Report No. 94, Exposure of the Population in the United States and Canada from NaturalBackgroundRadiation, National Council on Radiation Protection and Measurements, 1987.

3. Ionizing Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.

4. Kathren, Ronald L., Radioactivityand the Environment - Sources, Distribution, and Surveillance, Harwood Academic Publishers, New York, 1984.

5. Maine Yankee FinalSafety Analysis Report.

6. NRC Generic Letter 89-01,

Subject:

Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Dated January31, 1989.

7. Maine Yankee Offsite Dose Calculation Manual (ODCM), Change #29, dated July 21, 2004, Maine Yankee Atomic Power Company.

8. Maine Yankee Offsite Dose Calculation Manual (ODCM), Change #31, dated August 31, 2005, Maine Yankee Atomic Power Company.

48

Appendix A MY Radiological Environmental Monitoring Program Summary of 2005 Data A-i

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3 ) (pCi/lm) (pCi/m3)

AP DEMO L9305-02 4/10/2005 AcTh-228 -1.60E-03 2.90E-03 1.30E-02 AP DEMO L9305-02 4/10/2005 Ag-108m -6.90E-04 6.90E-04 3.0013-03 AP DEMO L9305-02 4/10/2005 Ag-Il10m 8.OOE-04 1.60E-03 6. 1OE-03 AP DEMO L9305-02 4/10/2005 Ba-140 2. 1OE-01 1.90E-01 6.50E-01 AP DEMO L9305-02 4/10/2005 Be-7 5.60E-02 3.40E-02 1.IOE3-01 AP DEMO L9305-02 4/10/2005 Ce-141 -3. 1OE-03 7.90E-03 3.0013-02 AP DEMO L9305-02 4/10/2005 Ce-144 -3.40E-03 5.20E-03 2.OOE-02 AP DEMO L9305-02 4t10/2005 Co-57 -9. 10E-04 5.40E-04 2.30E-03 AP DEMO L9305-02 4/10/2005 Co-58 -1.50E-03 3.10E-03 I1.30E-02 AP DEMO L9305-02 4/10/2005 Co-60 -1.00E-04 1.20E-03 5.10OE-03 AP DEMO L9305-02 4110/2005 Cr-51 7.50E-02 6.50E-02 2.20E-01 AP DEMO L9305-02 4/1012005 Cs-134 -2.00E-04 1.20E-03 4.90E-03 AP DEMO L9305-02 4/10/2005 Cs-137 -1.70E-03 1.80E-03 7.0013-03 AP DEMO L9305-02 4/1012005 Fe-59 3.10E-03 8.30E-03 3.40E-02 AP DEMO L9305-02 4/10/2005 1-131 -5.00E-01 1.20E+00 5.10OE+00 AP DEMO L9305-02 4/10/2005 K-40 3.1OE-02 1.70E-02 5.30E-02 AP DEMO L9305-02 4/1012005 La-140 2.40E-01 2.10E-01 7.50E-01 AP DEMO L9305-02 4/1012005 Mn-54 -6.00E-04 1.50E-03 6.20E-03 AP DEMO L9305-02 4/1012005 Nb-95 -5.50E-03 7.10E-03 3.10OE-02 AP DEMO L9305-02 4/10/2005 Ru-103 -5.90E-03 5.20E-03 2.20E-02 AP DEMO L9305-02 4/10/2005 Ru-106 0.00E+00 9.20E-03 3.80E-02 AP DEMO L9305-02 4/10/2005 Sb-124 -4.50E-03 8.40E-03 4.OOE-02 AP DEMO L9305-02 4/10/2005 Sb-125 2.20E-03 2.50E-03 8.80E-03 AP DEMO L9305-02 4/10/2005 Se-75 -1.70E-03 1.80E-03 7.20E-03 AP DEMO L9305-02 4/10/2005 Zn-65 I .90E-03 2.70E-03 1.00E-02 AP DEMO L9305-02 4/10/2005 Zr-95 -I.1OE-03 5.20E-03 2.20E-02 AP DEMO L921 5-03 1/27/2005 GROSS BETA 5.30E-03 I .20E-03 3.80E-03

• AP DEMO L9215-06 2/5/2005 GROSS BETA 2.63E-02 2.10E-03 5.40E-03 AP DEMO L9216-03 2/12/2005 GROSS BETA 2.21E-02 2.80E-03 8.0013-03 AP DEMO L9216-06 2/19/2005 GROSS BETA 8.00E-03 2.30E-03 7.20E-03 AP DEMO L9217-03 2/2712005 GROSS BETA 1.35E-02 2.20E-03 6.30E-03 AP DEMO L9217-06 3/13/2005 GROSS BETA I .73E-02 I .40E-03 3.60E-03 AP DEMO L921 8-03 4/10/2005 GROSS BETA 9.00E-03 1.30E-03 3.50E-03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-2

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/rn 3) (pCi/M )

3 (pci/m )

3 AP DEMO 22 L9305-01 1/1312005 Acrh-228 2.OOE-02 2.60E-02 9.60E-02 AP DEMO 22 L9305-01 1/13/2005 Ag-108m 4.90E-03 5.80E-03 2.10OE-02 AP DEMO 22 L9305-01 1/13/2005 Ag-110in -1.IOE-02 1.I OE-02 5.60E-02 AP DEMO 22 L9305-01 1/13/2005 Ba-140 5.30E+01 4.70E+01 I1.70E+02 AP DEMO 22 L9305-01 1/13/2005 Be-7 0.OOE+00 4.30E-01 I1.70E+00 AP DEMO 22 L9305-01 1/13/2005 Ce-141 -1.00E-02 I1.90E-01 7.OOE-01 AP DEMO 22 L9305-01 1/13/2005 Ce-144 2.OOE-02 3.90E-02 I1.40E-01 AP DEMO 22 L9305-01 1/13/2005 Co-57 4.OOE-04 4.60E-03 I1.70E-02 AP DEMO 22 L9305-01 1/13/2005 Co-58 -9.OOE-03 4.00E-02 I1.60E-01 AP DEMO 22 L9305-01 1/13/2005 Co-60 5.OOE-03 1.20E-02 4.50E-02 AP DEMO 22 L9305-01 1/13/2005 Cr-51 3.10E+00 1.90E+O0 6.OOE+00 AP DEMO 22 L9305-01 1/13/2005 Cs-134 6.80E-03 8.I OE-03 3.00E-02 AP DEMO 22 L9305-01 1/13/2005 Cs-137 8.OOE-03 I1.40E-02 5.1 OE-02 AP DEMO 22 L9305-01 1/13/2005 Fe-59 I .OE-01 I1.50E-01 5.80E-O1 AP DEMO 22 L9305-01 1/13/2005 1-131 2.00E+02 4.OOE.03 1.60E+04 AP DEMO 22 L9305-01 1/13/2005 K-40 1.90E-01 L.IOE-01 3.40E-01 AP DEMO 22 L9305-01 1/13/2005 La-140 6.20E.01 5.40E+01 I1.90E+02 AP DEMO 22 L9305-01 1/13/2005 Mn-54 4.OOE-03 8.20E-03 3.20E-02 AP DEMO 22 L9305-01 1/13/2005 Nb-95 -3.20E-01 1.90E-01 8.40E-01 AP DEMO 22 L9305-01 1/13/2005 Ru-103 -4.60E-02 9.20E-02 3.90E-01 APDEMO 22 L9305-01 1/13/2005 Ru-106 -2. 10E-02 7.60E-02 3.20E-01 AP DEMO 22 L9305-01 1/13/2005 Sb-124 -1.OOE-02 I1.20E-01 5.50E-01 AP DEMO 22 L9305-01 1/13/2005 Sb-125 -2.50E-02 2.OOE-02 8.60E-02 AP DEMO 22 L9305-01 1/13/2005 Se-75 -3.70E-02 1.90E-02 7.80E-02 AP DEMO 22 L9305-01 1/13/2005 Zn-65 1.60E-02 2.OOE-02 7.50E-02 AP DEMO 22 L9305-01 1/13/2005 Zr-95 6.50E-02 6.70E-02 2.40E-01 AP DEMO 22 L8784-01 1/6/2005 GROSS BETA 2.06E-02 2.40E-03 6.80E-03 1.'78E-02 3.60E-03 L IOE-02 * +

AP DEMO 22 L8785-01 1/13/2005 GROSS BETA AP DEMO 57 L9305-03 4/10/2005 AcTn-228 -1.36E-02 7.60E-03 3.90E-02 AP DEMO 57 L9305-03 4/10/2005 Ag-108m -2.1IOE-03 2.1lO-03 8.80E-03 AP DEMO 57 L9305-03 4/10/2005 Ag-I 10m -4.OOE-03 4.50E-03 2.OOE-02 AP DEMO 57 L9305-03 4/10/2005 Ba-140 0.OOE+00 6.00E-01 2.40E+00 AP DEMO 57 L9305-03 4/10/2005 Be-7 -4.30E-02 6.60E-02 2.70E-01

• Radioactivity detected insample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-3

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/rn3) 3 (pCi/m )

3 (pCi/M )

AP DEMO 57 L9305-03 4/10/2005 Ce-141 -2.301E-02 1.80E-02 7.00E-02 APDEMO 57 L9305-03 4/10/2005 Ce-14 2.0013-03 1.IOE-02 4.1OE-02 AP DEMO 57 L9305-03 4/10/2005 Co-57 -3.30E-03 1.50E-03 6.20E-03 AP DEMO 57 L9305-03 4/10/2005 Co-58 -4.OOE-04 3.80E-03 1.80E-02 AP DEMO 57 L9305-03 4/1012005 Co-60 5.10E-03 3.70E-03 1.20E-02 AP DEMO 57 L9305-03 4/10/2005 Cr-51 I1.50E-01 1.70E-01 5.80E-01 AP DEMO 57 L9305-03 4/10/2005 Cs-134 -4.OOE-04 2.50E-03 1.1OE-02 AP DEMO 57 L9305-03 4/10/2005 Cs-137 4.3013-03 4.90E-03 1.70E-02 AP DEMO 57 L9305-03 4/10/2005 Fe-59 0.OOE3+00 2.10E-02 8.80E-02 AP DEMO 57 L9305-03 4/1012005 1-131 3.10E+O0 3.40E+00 1.20E+01 AP DEMO 57 L9305-03 4/10/2005 K-40 -1.00E-02 3.50E-02 1.501E-01 AP DEMO 57 L9305-03 4/10/2005 La-140 0.00E+O00 6.90E-01 2.80E+00 AP DEMO 57 L9305-03 4/10/2005 Mn-54 -2.60E-03 3.00E-03 1.30E-02 AP DEMO 57 L9305-03 4110/2005 Nb-95 -3.OOE-03 1.50E-02 6.30E-02 AP DEMO 57 L9305-03 4/10/2005 Ru-103 8.00E-03 1.40E-02 5.20E-02 APDEMO 57 L9305-03 4/10/2005 Ru-106 6.001E-03 2.50E-02 9.50E-02 AP DEMO 57 L9305-03 4/10/2005 Sb-124 6.00E3-03 2.30E-02 9.50E-02 AP DEMO 57 L9305-03 4/10/2005 Sb-125 6.70E3-03 5.80E-03 2.00E-02 AP DEMO 57 L9305-03 4/10/2005 Se-75 6.80E-03 4.30E-03 1.40E-02 AP DEMO 57 L9305-03 4/10/2005 Zn-65 6.90E-03 7.70E-03 2.80E-02 AP DEMO 57 L9305-03 4/10/2005 Zr-95 1.50E-02 1.30E-02 4.30E-02 2.62E-02 * +

AP DEMO 57 L9215-01 1/27/2005 GROSS BETA 3.90E-03 1.1OE-02 AP DEMO 57 L9217-01 2/27/2005 GROSS BETA I1.45E-02 3.30E-03 1.00E-02 AP DEMO 57 L9217-04 3/13/2005 GROSS BETA I1.64E-02 2.1OE-03 5.80E-03 AP DEMO 57 L9218-01 4/10/2005 GROSS BETA 9.60E-03 1.90E-03 5.60E-03 AP DEMO 67 L9305-04 2/19/2005 AcTh-228 -4.60E-02 2. 1OE-02 1.1OE-01 AP DEMO 67 L9305-04 2/19/2005 Ag-108m 4. IOE-03 5.1OE-03 1.80E-02 AP DEMO 67 L9305-04 2/19/2005 Ag-I 1Omn 1.1II E-02 8.90E-03 3.00E-02 AP DEMO 67 L9305-04 2119/2005 Ba-140 -2.40E-g00 5.30E+00 2.50E+01 AP DEMO 67 L9305-04 2/19/2005 Be-7 5.OOE-02 2.50E-01 9.30E-01 AP DEMO 67 L9305-04 2119/2005 Ce-141 -2.07E-01 8.30E-02 3.50E-01 AP DEMO 67 L9305-04 2/19/2005 Ce-144 6.601E-02 2.90E-02 8.90E-02 AP DEMO 67 L9305-04 2/19/2005 Co-57 -6.90E-03 4.00E-03 1.60E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-4

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/n 3 ) (pCi/n 3 ) (pCi/m 3 )

AP DEMO 67 L9305-04 2/19/2005 Co-58 2.101E-02 I1.60E-02 5.60E-02 AP DEMO 67 L9305-04 2/19/2005 Co-60 -3.00E-03 5.20E-03 2.70E-02 AP DEMO 67 L9305-04 2/19/2005 Cr-51 -1.21E+00 8.60E-01 3.60E+00 AP DEMO 67 L9305-04 2/19/2005 Cs-134 -9.80E-03 5.70E-03 3.OOE-02 AP DEMO 67 L9305-04 2/19/2005 Cs-137 1.40E-02 I1.30E-02 4A40E-02 AP DEMO 67 L9305-04 2/19/2005 Fe-59 5.40E-02 8.50E-02 3.20E-01 AP DEMO 67 L9305-04 2/19/2005 1-131 1.00E+01 1.60E+02 6.50E+02 AP DEMO 67 L9305-04 2/19/2005 K-40 7.90E-02 9.60E-02 3.50E-01 AP DEMO 67 L9305-04 2/19/2005 La-140 -2.70E+00 6.10E+00 2.90E401 APDEMO 67 L9305-04 2/19/2005 Mn-54 -2.90E-03 7.30E-03 3.IOE-02 AP DEMO 67 L9305-04 2/19/2005 Nb-95 -1.32E-01 7.OOE-02 3.30E-01 AP DEMO 67 L9305-04 2t19/2005 Ru-103 -6.40E-02 5.OOE-02 2.20E-01 AP DEMO 67 L9305-04 2/19/2005 Ru-106 -1.70E-02 7.60E-02 3.OOE-01 AP DEMO 67 L9305-04 2/19/2005 Sb-124 -5.00E-03 5.80E-02 2.70E-01 AP DEMO 67 L9305-04 2/19/2005 Sb-125 -1.70E-02 I1.70E-02 7.10OE-02 AP DEMO 67 L9305-04 2/19/2005 Se-75 -5.00E-03 1.20E-02 4.80E-02 AP DEMO 67 L9305-04 2119/2005 Zn-65 -6.00E-03 I1.40E-02 6.60E-02 AP DEMO 67 L9305-04 2/19/2005 Zr-95 I .OOE-03 4.40E-02 1.70E-01 3.OOE-03 9. 10E-03

• AP DEMO 67 L9215-05 2/5/2005 GROSS BETA 1.43E-02 AP DEMO 67 L9216-01 2/12/2005 GROSS BETA 1.34E-02 3.80E-03 I1.20E-02 +

AP DEMO 67 L9216-04 2/19/2005 GROSS BETA 2.25E-02 3.90E-03 1.20E-02 AP DEMO 68 L9305-05 1/13/2005 AcTh-228 -3.00E-03 1.40E-02 6.30E-02 AP DEMO 68 L9305-05 1/13/2005 Ag-108m -6. 1OE-03 3.80E-03 1.70E-02 AP DEMO 68 L9305-05 1/13/2005 Ag-110m 7.70E-03 9.70E-03 3.60E-02 AP DEMO 68 L9305-05 1/13/2005 Ba-140 -1.30E+0I 3.40E+01 I1.50E+02 AP DEMO 68 L9305-05 1/13/2005 Be-7 -1.30E-01 3.00E-0l I1.20E+00 AP DEMO 68 L9305-05 1/13/2005 Ce-141 3.00E-02 I1.30E-01 4.80E-01 AP DEMO 68 L9305-05 1/13/2005 Ce-144 2.80E-02 2.7013-02 9.40E-02 AP DEMO 68 L9305-05 1/13/2005 Co-57 I .IOE-03 3.OOE-03 1.IOE-02 APDEMO 68 L9305-05 1/13/2005 Co-58 -3.10E-02 2.OOE-02 I .00E-01 AP DEMO 68 L9305-05 1/13/2005 Co-60 -5.30E-03 6. 1OE-03 2.90E-02 AP DEMO 68 L9305-05 1/13/2005 Cr-51 2. 1E+00 1.70E+00 5.60E+00 AP DEMO 68 L9305-05 1/13/2005 Cs-134 4.60E-03 6.40E-03 2.40E-02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-5

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3 ) (pCi/m3) (pCi/n 3)

AP DEMO 68 L9305-05 1/13/2005 Cs-137 2.90E-03 9.00E-03 3.30E-02 AP DEMO 68 L9305-05 1/13/2005 Fe-59 -1.14E-01 8.50E-02 4.60E-01 AP DEMO 68 L9305-05 1/13/2005 1-131 1.40E+03 3.70E+03 1.40E+04 AP DEMO 68 L9305-05 1/13/2005 K-40 -2.20E-02 6.80E-02 2.90E-01 AP DEMO 68 L9305-05 1/13/2005 La-140 -1.50E+01 3.90E+01 I1.80E.02 AP DEMO 68 L9305-05 1/13/2005 Mn-54 -4.40E-03 6.80E-03 3.OOE-02 AP DEMO 68 L9305-05 1/13/2005 Nb-95 7.00E-02 1.20E-01 4.60E-01 AP DEMO 68 L9305-05 1/13/2005 Ru-103 1.60E-02 8.50E-02 3.20E-01 AP DEMO 68 L9305-05 1/13/2005 Ru-106 9.00E-02 6.00E-02 2.OOE-01 AP DEMO 68 L9305-05 1113/2005 Sb-124 -1.49E-01 7.40E-02 4.30E-01 AP DEMO 68 L9305-05 1/13/2005 Sb-125 9.00E-03 1.40E-02 5.10OE-02 AP DEMO 68 L9305-05 1/13/2005 Se-75 -5.00E-03 1.20E-02 4.70E-02 AP DEMO 68 L9305-05 1/13/2005 Zn-65 1.IOE-02 1.60E-02 6. 1OE-02 AP DEMO 68 L9305-05 1/13/2005 Zr-95 -1.IOE-02 5.20E-02 2. 10E-01 2.99E-02 2.30E-03 5.70E-03

• AP DEMO 68 L8784-.02 1/6/2005 GROSS BET'A 2.80E-02 2.40E-03 6.10E-03

• AP DEMO 68 L8785-02 1/13/2005 GROSS BETA AP DEMO 73 L9305-06 4/10/2005 AcTh-228 -2.90E-03 3.30E-03 I1.30E3-02 AP DEMO 73 L9305-06 4/10/2005 Ag-108m 1.90E-04 5.40E-04 2.OOE-03 AP DEMO 73 L9305-06 4/10/2005 Ag-110m -2.60E-03 1.60E-03 6.70E-03 AP DEMO 73 L9305-06 4/10/2005 Ba-140 -2.70E-01 1.60E-O1 8.00E-01 AP DEMO 73 L9305-06 4/10/2005 Be-7 6.20E-02 2.80E-02 8.60E-02 APDEMO 73 L9305-06 4/10/2005 Ce-141 7.OOE-03 8.40E-03 2.90E-02 AP DEMO 73 L9305-06 4/10/2005 Ce-144 -1.90E-03 3.90E-03 I AO0E-02 AP DEMO 73 L9305-06 4/10/2005 Co-57 -1.60E-04 5.70E-04 2.0013-03 AP DEMO 73 L9305-06 4/10/2005 Co-58 2.00E-04 1.80E-03 7.20E-03 AP DEMO 73 L9305-06 4/10/2005 Co-60 2.30E-03 1.20E-03 3.70E-03 AP DEMO 73 L9305-06 4/10/2005 Cr-51 5.70E-02 7.50E-02 2.60E-01 AP DEMO 73 L9305-06 4/10/2005 Cs-134 5.00E-05 7.50E-04 2.90E-03 AP DEMO 73 L9305-06 4/10/2005 Cs-137 1.24E-03 9.50E-04 3.20E-03 AP DEMO 73 L9305-06 4/10/2005 Fe-59 3.60E-03 7.70E-03 2.90E-02 AP DEMO 73 L9305-06 4/10/2005 1-131 1.20E+00 2.20E+00 7.90E+00 AP DEMO 73 L9305-06 4/10/2005 K-40 5.OOE-03 1.lOE-02 4.OOE-02 APDEMO 73 L9305-06 4/10/2005 La-140 -3. IOE-01 1.80E-01 9.2013-01

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

• Minimum Detectable Concentration > Lower Limit of Detection Requirement A-6

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/M3 ) (pCi/m3 ) (pCi/m3 )

AP DEMO 73 L9305-06 4/10/2005 Mn-54 1.80E-03 1.1OE-03 3.40E-03 AP DEMO 73 L9305-06 4/10/2005 Nb-95 -1.16E-02 5.70E-03 2.60E-02 AP DEMO 73 L9305-06 4/1012005 Ru-103 -5.80E-03 3.80E-03 1.60E-02 AP DEMO 73 L9305-06 4110/2005 Ru-106 -2.29E-02 9.40E-03 4.00E-02 AP DEMO 73 L9305-06 4110/2005 Sb-124 1.00E-02 6.00E-03 1.90E-02 AP DEMO 73 L9305-06 4/10/2005 Sb- 125 -3.00E-03 2. 1OE-03 8.30E-03 AP DEMO 73 L9305-06 4/10/2005 Se-75 1.20E-03 1.60E-03 5.60E-03 AP DEMO 73 L9305-06 4/1012005 Zn-65 2.60E-03 1.50E-03 4.80E-03 AP DEMO 73 L9305-06 4/10/2005 Z7-95 I.20E-03 3.80E-03 1.40E-02 AP DEMO 73 L9215-02 1/2712005 GROSS BETA 1.5lE-02 2.10E-03 6.20E-03

• AP DEMO 73 L9215-04 215/2005 GROSS BETA 1.37E-02 3.00E-03 9.10E-03

• AP DEMO 73 L9216-02 2/12/2005 GROSS BETA 1.74E-02 3.80E-03 1.20E-02 *

+

AP DEMO 73 L9216-05 2119/2005 GROSSBETA 2.12E-02 3.90E-03 1.20E-02

• AP DEMO 73 L9217-02 212712005 GROSS BETA 1.82E-02 3.40E-03 1.OOE-02

• AP DEMO 73 L9217-05 3/1312005 GROSSBETA 1.31E-02 2.00E-03 5.80E-03

• AP DEMO 73 L921 8-02 4/1012005 GROSS BETA 1.30E-02 2.00E-03 5.60E-03 *

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-7

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

CR 11 L9720-01 8/10/2005 AcTh-228 1.10E+01 3.00E+01 1.IOE+02 CR 11 L9720-01 8/10/2005 Ag-108m -9.OOE-01 5.50E+00 2.10E+01 CR 11 L9720-01 8/10/2005 Ag-l lOmn 3.20E+00 9.70E+00 3.60E+01 CR 11 L9720-01 8/10/2005 Ba-140 1.07E+01 9.40E+00 3.302+01 CR 11 L9720-01 8/10/2005 Be-7 1.80E+01 4.80E+01 1.80E+02 CR 11 L9720-01 8/10/2005 Ce-141 l.50E+00 8.90E+00 3.102+01 CR 11 L9720-01 8/10/2005 Ce-144 -6.00E+01 2.50E+01 1.00+02 CR 11 L9720-01 8/10/2005 Co-57 l.OOE-01 3.30E+00 1.20E+01 CR II L9720-01 8/10/2005 Co-58 2.50E+00 7.OOE+00 2.60E+01 CR I1 L9720-01 8/10/2005 Co-60 O.OOE+00 8.60E+00 3.40E+01 CR 11 L9720-01 8/10/2005 Cr-51 -7.30E+01 5.20E+01 2.10E+02 CR 11 L9720-01 8/10/2005 Cs-134 6.40E+00 9.40E+00 3.302+01 CR II L9720-01 8/10/2005 Cs-137 O.OOE+00 6.90E+00 2.602+01 CR 11 L9720-01 8/10/2005 Fe-59 -2.30E+01 2.30E+01 9.90E+01 CR 11 L9720-01 8/10/2005 1-131 2.10E+01 1.20E+01 3.70E+01 8/10/2005 1.42E+03 2.00E+02 3.90E+02

• CR 11 L9720-01 K-40 CR 11 L9720-01 8/10/2005 La-140 1.20E+01 1.IOE1+OI 3.80E+01 CR 11 L9720-01 811012005 Mn-54 6.00E+00 5.90E+00 2.10E+01 CR 11 L9720-01 8/1012005 Nb-95 -4.40E+00 7.702+00 3.102+01 CR 11 L9720-01 8/1012005 Ru-103 2.30E+00 6.50E+00 2.40E+01 CR 11 L9720-01 8/10/2005 Ru-106 -1.1OE+01 5.90E+01 2.30E+02 CR 11 L9720-01 8/10/2005 Sb-124 -6.00E+00 1.80E+01 7.90E+01 CR 11 L9720-01 811012005 Sb-125 -1.302+01 1.80E+01 6.80E+01 CR 11 L9720-01 8/102005 Se-75 -5.30E+00 7.OOE+00 2.70E+01 CR 11 L9720-01 8/10/2005 Zn-65 -7.00E+00 1.40E+0O 5.90E+01 CR 11 L9720-01 8/10/2005 Zr-95 -2.11OE+01 1.60E+01 6.50E+01 CR 24 L9720-02 8110/2005 AcTh-228 O.OOE+00 3.00E+01 1.lIOE+02 CR 24 L9720-02 8/10/2005 Ag-108m O.OOE+00 7.20E+00 2.60E+01 CR 24 L9720-02 8/1012005 Ag-I lOIm -2.00E+00 1.302+01 4.90E+01 CR 24 L9720-02 8/10/2005 Ba-140 8.00E+00 1.20E+01 4.50E+01 CR 24 L9720-02 8/10/2005 Be-7 1.29E+02 6.702+01 2.10E+02 CR 24 L9720-02 8/10/2005 Ce-141 -1.30E+01 1.1OE+01 4.00E+01 CR 24 L9720-02 8/10/2005 Ce-144 -3.00E+00 3.80E+01 1.302+02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-8

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

CR 24 L9720-02 8/1012005 Co-57 3.00O1+00 5.OOE+00 1.70E+01 CR 24 L9720-02 8/10/2005 Co-58 -1.60E+00 8.10E+00 3.20E+01 CR 24 L9720-02 8/10/2005 Co-60 3.OOE+00 1.20E+01 4.50E.01 CR 24 L9720-02 8/10/2005 Cr-51 6.601E+01 7.OOE+01 2.40E+02 CR 24 L9720-02 8/10/2005 Cs-134 -2.60E+00 9.601E+00 3.70E-e.01 CR 24 L9720-02 8/1012005 Cs-137 -7.101E+00 9.00E+O00 3.501E+01 CR 24 L9720-02 8/10/2005 Fe-59 7.001E+00 2.501E+01 9.501E+01 CR 24 L9720-02 8/10/2005 I-131 4.001E+00 I1.30E3+01 4.70E-,01 CR 24 L9720-02 8/10/2005 K-40 1.84E3+03 2.401E+02 4.50E+02

• CR 24 L9720-02 8110/2005 La-140 9.OOE+00 1.40E+01 5.20E+01 CR 24 L9720-02 8/10/2005 Mn-54 -7.40E+00 7.7013O00 3.201E+01 CR 24 L9720-02 8/10/2005 Nb-95 1.141+01 9.303+O00 3.10OE.O1 CR 24 L9720-02 8/10/2005 Ru-103 5.003+O00 8.101E+00 2.901E+01 CR 24 L9720-02 8/10/2005 Ru-106 -1 .26E+02 7.701E+01 3.201E+02 CR 24 L9720-02 8/10/2005 Sb-124 I1.901E+01 2. 10E-,01 7.601E+01 CR 24 L9720-02 8/10/2005 Sb-125 1.201E+01 2.10E+01 7.40E+01 CR 24 L9720-02 8/10/2005 Se-75 6.001E+00 7.80E+00 2.70E+01 CR 24 L9720-02 8/10/2005 Zn-65 -1 .60E+01 1.80E+01 7.50E+01 CR 24 L9720-02 8/10/2005 Zr-95 6.0011+00 1.IOE+01 4.OOE+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit or Detection Requirement A-9

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

FH 11 L9721-01 8/10/2005 AcIh-228 -1.40E+01 2.30E+01 8.90E+O1 FH 11 L9721-01 8/10/2005 Ag-108m 6.00E-01 5.OOE+00 1.80E+01 FH 11 L9721-01 8/10/2005 Ag-llOm 2.70E+00 8.30E+00 3.OOE+01 FH 11 L9721-01 8/10/2005 Ba-140 4.10E+00 8.30E+00 3.10E+0I FH 11 L9721-01 8/10/2005 Be-7 -7.10E+01 5. 1OE+01 2.00E+02 FH 11 L9721-01 8/10/2005 Ce-141 -1.80E+01 9.50E+00 3.50E+0I FH II L9721-01 8/10/2005 Ce-144 6.10E+01 3.60E+01 1.20E+02 FH II L9721-01 8/10/2005 Co-57 3.OOE+00 4.1OE+00 1.40E3+01 FH 11 L9721-01 8/10/2005 Co-58 O.OOE+00 6.00E-+00 2.20E+0I FH 11 L9721-01 8/10/2005 Co-60 6.40E+00 7.10E-+00 2.50E+0I FH 11 L9721-01 8/10/2005 Cr-51 -2.80E+01 5.50E+01 2.00E+02 FH II L9721-01 8/10/2005 Cs-i134 -7.30E1+00 7.60E+00 2.90E+01 FH 11 L9721-01 8/10/2005 Cs-137 7.20E+00 7.00E+00 2.40E+O1 FH 11 L9721-01 8/10/2005 Fe-59 2.00E+01 2.1OE+01 7.30E+01 FH 11 L9721-01 8/10/2005 1-131 4.00E+00 1.IOE+0I 4.00E+01 FH 11 L9721-01 8/10/2005 K-40 2.08E+03 1.90E+02 3.50E+02 FH 11 L9721-01 8/10/2005 La-140 4.70E+00 9.50E+00 3.60E+0I FH II L9721-01 8/10/2005 Mn-54 0.OOE+00 5.30E+00 2.OOE+I01 FH 11 L9721-01 8/10t2005 Nb-95 1.40E+01 7.80E+00 2.50E+01 FH 11 L9721-01 8/10/2005 Ru-103 -9.OOE-01 6.40E+00 2.30E+01 FH 11 L9721-01 8/10/2005 Ru-106 4.20E+01 5.90E+01 2.OOE+02 FH 11 L9721-01 8/10/2005 Sb-124 2.80E+01 1.40E+01 4.10E+01 FH 11 L9721-01 8/10t2005 Sb-125 -1.40E+01 1.50E+01 5.80E+01 FH 11 L9721-01 8/10/2005 Se-75 3.50E+00 8.20E+00 2.80E+01 FH II L9721-01 8/10/2005 Zn-65 -9.00E+00 1.70E+01 6.30E+01 FH 11 L9721-01 8/10/2005 Zr-95 3.00E+00 1.30E+01 4.50E+01 FH 24 L9721-02 8/10/2005 AcTh-228 -2.50E1+01 2.20E+01 8.90E+01 FH 24 L9721-02 8/10/2005 Ag-108m -3.00E-01 5.50E+00 2.00E+01 FH 24 L9721-02 8/10t2005 Ag-blOm -3.90E+00 9.1OE+00 3.40E+O1 FH 24 L9721-02 8/10/2005 Ba-140 -7.80E+00 8.20E+00 3.50E+01 FH 24 L9721-02 8/10/2005 Be-? 3.30E+01 4.80E+01 1.70E+02 FH 24 L9721-02 8/10/2005 Ce-141 1.40E+00 9.40E+00 3.30E+0I FH 24 L9721-02 8/1012005 Ce-14 3.70E+01 3.50E+01 1.20E+02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-10

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

FH 24 L9721-02 811012005 Co-57 3.00E3-01 4.10OE+00 1.50E+01 FH 24 L9721-02 8/10/2005 Co-58 1.90E1i-00 6.90E+00 2.501E+01 FH 24 L9721-02 8/10/2005 Co-60 -1.30E+00 6.401E+00 2.40E+01 FH 24 L9721-02 8/1012005 Cr-51 -2.301E+01 6.30E3+01 2.30E.02 FH 24 L9721-02 8/1012005 Cs-134 7.80E-i-00 6.501E+00 2.2013.01 FH 24 L9721 -02 8/10/2005 Cs-137 7.OOE-,00 6.70E3+00 2.3013+01 FH 24 L9721-02 8/10/2005 Fe-59 6.OOE+00 1.9013+01 6.801E+01 FH 24 L9721-02 8/10/2005 1-131 -4,00E+00 I1.30E+01 4.60E1i-01 2.20E+03 1.90E3+02 3.20E+02

• FH 24 L9721-02 8/10/2005 K-40 FH 24 L9721-02 8/10/2005 La-140 -8.90E+00 9.40E3+00 4.10E+01 FH 24 L9721-02 8/10/2005 Mn-54 6,30E+00 7.001E+00 2.40E1,-01

- FH 24 L9721-02 8/10/2005 Nb-95 6.80E+00 6.601E+00 2.301E+01 FH 24 L9721-02 8/10/2005 Ru-103 7.10O3+00 5.50E+00 1.80E+01 FH 24 L9721-02 8/10/2005 Ru-106 6.601E+01 6.30E-i01 2.10OE.02 FH 24 L9721-02 8/10/2005 Sb-124 -2.0013+00 1.IOE+01 4.60E3+01 FH 24 L9721-02 8/10/2005 Sb-125 1.40E3+01 1.701E+01 5.901E+01 FH 24 L9721-02 8/10/2005 Se-75 -4.001E+00 6.90E+00 2.5013+01 FH 24 L9721-02 8/1012005 Zn-65 -1 .60E.01 1.60E+01 6.30E1e-01 FH 24 L9721-02 8/1012005 Zr-95 2.40E+01 1.IOE+01 3.40E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > ILower Limit of Detection Requirement A-1l

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

HA 11 L97 19-01 8/10/2005 AcTh-228 1.00E+01 2.20E+01 7.80E+01 HA II L9719-01 8/10/2005 Ag-108m -6.90E+00 5.60E+00 2.102+01 HA 11 L9719-01 8/10/2005 Ag-i lOin 6.70E+00 8.90E+00 3.102+01 HA 11 L9719-01 8/10/2005 Ba-140 -6.20E+00 8.60E+00 3.60E+01 HA 11 L9719-01 8/10/2005 Be-7 3.20E+0I 4.902+01 1.70E+02 HA 11 L9719-01 8/10/2005 Ce- 141 6.20E+00 9.20E+00 3.102+01 HA 11 L9719-01 8/10/2005 Ce-144 6.00E+00 3.30E+01 1.10+02 HA 11 L9719-01 8/10/2005 Co-57 7.90E+00 4.103E+00 1.30E+01 HA 11 L9719-01 8/10/2005 Co-58 1.362+01 6.30E+00 1.902+01 HA 11 L9719-01 8/10/2005 Co-60 -7.00E+00 6.60E+00 2.70E+01 HA II L9719-01 8/10/2005 Cr-51 -6.20E+01 5.50+01 2.10E+02 HA 11 L9719-01 8/10/2005 Cs-134 -1.00O+00 6.90E+00 2.60E+01 HA 11 L9719-01 8/10/2005 Cs-137 1.022+01 5.90E+O0 1.90E+01 HA 11 L9719-01 8/10/2005 Fe-59 1.00E+00 1.50+01 5.80E+01 HA 11 L9719-01 8/1102005 1-131 5.OOE+00 1.101E+01 4.00E+01 HA 11 L9719-01 8/10/2005 K-40 1.49E+03 1.80E+02 3.90E+02 HA 11 L9719-01 8/10/2005 La-140 -7.20E+00 9.80E+00 4.20E+01 HA 11 L9719-01 8/10/2005 Mn-54 2.80E3+00 5.90E+00 2.102+01 HA 11 L9719-01 8/10/2005 Nb-95 5.90E+00 7.70E+00 2.702+01 HA 11 L9719-01 8/10/2005 Ru-103 -2.30E+00 6.00E+00 2.20E+01 HA 11 L9719-01 8/10/2005 Ru-106 -1.40E+0I 6.40E+01 2.302+02 HA 11 L9719-01 8/1012005 Sb-124 3.00E+00 l.00E+01 4.102+01 HA 11 L9719-01 8/10/2005 Sb-125 0.00E+00 1.70E+01 6.202+01 HA 11 L9719-01 8/102005 Se-75 -1.112+01 8.00E+00 3.002+01 HA 11 L9719-01 8/1012005 Zn-65 -7.00E+00 1.40E+01 5.302+01 HA 11 L9719-01 8/102005 Zr-95 -5.00E+00 9.60E+00 3.702+01 HA 24 L9719-02 8/10/2005 Aclh-228 -2.10E+01 2.20E+01 8.60E+01 HA 24 L9719-02 8/10/2005 Ag-108m -5.80E+00 5.20E+00 2.00E+01 HA 24 L9719-02 8/10/2005 Ag-l lOm 2.60E+00 7.50E+00 2.70E+01 HA 24 L9719-02 8/10/2005 Ba-140 0.00E+00 1.10E+01 4.00E+01 HA 24 L9719-02 8/10/2005 Be-7 3.40E+01 5.302+01 1.80E+02 HA 24 L9719-02 8/10/2005 Ce-141 -6.20E+00 9.50E+00 3.402+01 HA 24 L9719-02 8/10/2005 Ce-144 -4.70E+01 3.20E+01 1.202+02

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-12

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

HA 24 'L9719-02 8/10/2005 Co-57 1.70E+00 4.50E+00 I .50E+01 HA 24 L9719-02 8/10/2005 Co-58 3.70E+00 6.00E1+00 2.1 OE+01 HA 24 L9719-02 8/10/2005 Co-60 1.60E+00 5.70E+00 2.101E+01 HA 24 L9719-02 8/10/2005 Cr-51 -1.70E+01 5.90E+01 2.10E+02 HA 24 L9719-02 8/1012005 Cs-134 1.26E+01 7.30E+00 2.40E+01 HA 24 L9719-02 8/10/2005 Cs-137 -9.00E-01 7.20E+00 2.60E+01 HA 24 L9719-02 8/10t2005 Fe-59 1.90E+01 I .70E+01 5.70E+01 HA 24 L9719-02 8/10/2005 1-131 -1.00E+01 1.30E+01 4.70E+01 HA 24 L9719-02 8/1012005 K-40 2.13E+03 1.80E+02 2.70E+02

• HA 24 L9719-02 8/1012005 La-140 0.00E+00 1.20E+01 4.60E+01 HA 24 L9719-02 8/10/2005 Mn-54 1.80E+00 6.10E+O0 2.20E+01 HA 24 L9719-02 8/10/2005 Nb-95 7.70E+00 6.80E+00 2.30E+01 HA 24 L9719-02 8/10/2005 Ru-103 -5.00E-01 5.80E+00 2.10E+01 HA 24 L9719-02 8/10/2005 Ru-106 2.90E+01 5.90E+01 2.1 OE+02 HA 24 L9719-02 8/10/2005 Sb-124 -5.00E+00 1.00E+01 4.60E+01 HA 24 L9719-02 8/10/2005 Sb-125 -1.90E+01 1.60E+I01 6.00E+01 HA 24 L9719-02 8/1012005 Se-75 -1.30E3+00 6.80E3+00 2.40E+01 HA 24 L9719-02 8110/2005 Zn-65 -3.60E+01 1.50E+01 6.30E+01 HA 24 L9719-02 8/10/2005 Zr-95 2.OOE+00 1.1OE+01 4.00E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-13

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

MU 11 L9722-01 8/10/2005 AcTh-228 3.30E+01 3.50E+01 1.20E+02 MU 11 L9722-01 8/10/2005 Ag-108m -1.70E+00 5.90E+00 2.20E+01 MU 11 L9722-01 8/10/2005 Ag-llOm 6.00E+00 1.1OE+01 4.00E+0I MU 11 L9722-01 8/10/2005 Ba-140 -3.00E+OO 1.10E+0I 4.70E+OI MU 11 L9722-01 8/10/2005 Be-7 -4.50E+01 6.40E+01 2.50E+02 MU 11 L9722-01 8/10/2005 Ce-141 3.OOE+00 1.10E+01 3.80E+O1 MU 11 L9722-01 8/10/2005 Ce-144 -6.00E+00 4.00E+01 1.40E+02 MU 11 L9722-01 8/10/2005 Co-57 -5.90E+00 4.60E+00 1.70E+01 MU 11 L9722-01 8/10/2005 Co-58 1.30E+01 7.10E+00 2.20E+I01 MU 11 L9722-01 8/1012005 Co-60 1.50E+00 8.1OE+00 3.10E+01 MU 11 L9722-01 8/10/2005 Cr-51 6.20E+01 7.20E+01 2.50E+02 MU 11 L9722-01 8/1012005 Cs-134 -2.00E+00 6.60E+00 2.70E+01 MU 11 L9722-01 8/1012005 Cs-137 -1.90E+00 7.70E+00 2.90E+0I MU 11 L9722-01 8/10/2005 Fe-59 3.20E+01 2.10E+01 7.OOE+01 MU 11 L9722-01 8/10/2005 1-131 7.00E+00 1.40E+01 5.10E+01 MU 11 L9722-01 8/10/2005 K-40 1.OIE+03 1.90E+02 4.60E+02 MU 11 L9722-01 8/10/2005 La-140 -4.00E+00 1.30E+01 5.40E+01 MU 11 L9722-01 8/10/2005 Mn-54 2.70E+00 7.00E+00 2.60E+O1 MU 11 L9722-01 8/10/2005 Nb-95 8.90E+00 7.90E+00 2.70E+01 MU 11 L9722-01 8110/2005 Ru-103 2.30E1+00 7.70E1+00 2.80E+01 MU 11 L9722-01 8/1012005 Ru-106 -6.60E+01 6.90E+01 2.70E1+02 MU 11 L9722-01 8/1012005 Sb-124 2.10E+01 1.70E+01 5.60E+01 MU 11 L9722-01 8/10/2005 Sb-125 -3.00E+00 1.80E+01 6.80E+01 MU 11 L9722-01 8/10/2005 Se-75 4.60E+00 9.20E+00 3.20E+01 MU 11 L9722-01 8/10/2005 Zn-65 -3.00E-+00 1.90E+01 7.10E+01 MU 11 L9722-01 8/10/2005 Zr-95 2.00E+01 1.20E+01 3.70E+01 MU 24 L9722-02 8/10/2005 AcTh-228 -2.20E+01 2.60E+01 1.lOE+02 MU 24 L9722-02 8/10/2005 Ag-108m 4.30E+00 5.50E+00 1.90E+01 MU 24 L9722-02 8/10/2005 Ag-I lOm 1.30E+00 9.60E1+00 3.70E+01 MU 24 L9722-02 8/10/2005 Ba-140 0.00E+00 1.50E+01 5.90E+0I MU 24 L9722-02 8/10/2005 Be-7 1.18E+02 6.30E+01 2.00E+02 MU 24 L9722-02 8/1012005 Ce-141 -1.90E+00 8.30E+00 3.00E+01 MU 24 L9722-02 8/10/2005 Ce-144 9.00E+00 2.50E+01 8.90E+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-14

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

MU 24 L9722-02 8/10/2005 Co-57 5.00E-01 3.30E+00 1.20E+01 MU 24 L9722-02 8/10/2005 CO-58 8.10E+00 7.90E3+00 2.70E+01 MU 24 L9722-02 8110/2005 Co60 1.88E+0I 8.80E+00 2.60E+01 MU 24 L9722-02 8/10/2005 Cr-51 -5.70E+01 4.90E+01 2.00E+02 MU 24 L9722-02 8/10/2005 Cs-134 8.10OE+O0 6.60E+O0 2.20E+01 MU 24 L9722-02 8/10/2005 Cs-137 0.OOE+O0 6.40E+00 2.50E+01 MU 24 L9722-02 8/10/2005 Fe-59 -2.30E+01 2.40E+01 l .OOE+02 MU 24 L9722-02 8/10/2005 1-131 -1.08E+01 9.90E3+00 4.10E+01 MU 24 L9722-02 8/10/2005 K-40 1.18E+03 1.90E+02 4.20E+02

• MU 24 L9722-02 8/10/2005 La-140 0.00E+O0 1.70E+01 6.80E+01 MU 24 L9722-02 8/10/2005 Mn-54 1.06E+01 7.70E+00 2.60E+01 MU 24 L9722-02 8/10/2005 Nb-95 -3.00E-01 8.80E+00 3.30E+01 MU 24 L9722-02 8110/2005 Ru-103 5.70E3+00 6.80E+00 2.40E+01 MU 24 L9722-02 8/10/2005 Ru-106 5.50E+01 5.50E+O1 1.90E+02 MU 24 L9722-02 8/10/2005 Sb-124 3.50E+01 2.20E+01 7.10 E+01 MU 24 L9722-02 8/10/2005 Sb-125 5.00E3+00 1.90E+01 6.80E+01 MU 24 L9722-02 8/10/2005 Se-75 1.36E3+01 7.60E+00 2.50E+O1 MU 24 L9722-02 8/10/2005 Zn-65 -7.00E+O0 2.00E+01 7.90E+01 MU 24 L9722-02 8/10/2005 Zr-95 0.00E+O0 1.30E3+01 5.10OE+01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit or Detection Requirement A-15

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCilL) (pCK/L)

WE 14 L9201-01 1/25/2005 AcTh-228 -7.00E-01 1.80E+00 6.00E+00 WE 14 L9201-01 1/25/2005 Ag-108m 3.101E-01 2.80E-01 9.40E-01 WE 14 L9201-01 1125/2005 Ag-110n 0.00E+00 5.80E-01 2.00E+O0 WE 14 L9201-01 1/25/2005 Ba-140 -6.30E+01 7.40E+01 2.60E+02 +

WE 14 L9201-01 1/25/2005 Be-7 3.50E+00 9.40E+00 3.20E+01 WE 14 L9201-01 1/25/2005 Ce-141 -1.70E+00 5.80E+00 l.90E+01 WE 14 L9201-01 1/25/2005 Ce-144 -4.30E+00 2.90E+00 9.80E+00 WE 14 L9201-01 1/25/2005 Co-57 -4.20E-01 3.80E-01 1.30E+00 WE 14 L9201-01 1/25/2005 Co-58 1.22E+00 8.30E-01 2.80E+00 WE 14 L9201-01 1/25/2005 Co-60 -2.10E-01 3.70E-01 1.30E+OO WE 14 L9201-01 1/25/2005 Cr-51 2.20E+01 3.30E+01 1.l10E+02 WE 14 L9201-01 1/25/2005 Cs-134 -8.60E-01 4.20E-01 1.50E+00 WE 14 L9201-01 1/25/2005 Cs-137 4.10E-01 3.20E-01 1.lOE+00 WE 14 L9201-01 1/25/2005 Fe-59 -3.80E+00 3.90E+00 1.40E+01 WE 14 L9201-01 1/25/2005 1-131 4.00E+02 1.80E+03 6.101E+03 WE 14 L9201-01 1/25/2005 K-40 2.31E+02 9.00E+3O0 I.90E+01

• WE 14 L9201-01 1/25/2005 LA-140 -7.20E+01 8.50E+01 3.00E+02 WE 14 L9201-01 1/25/2005 Mn-54 -3.80E-01 4.00E-01 1.40E+00 WE 14 L9201-01 1/25/2005 Nb-95 2.50E+00 2.60E+0O 8.80E+00 WE 14 L9201-01 1/25/2005 Ru-103 -6.60E+00 2.101E+00 7.40E+0O WE 14 L9201-01 1/25/2005 Ru-106 6.00E-01 3.80E+00 1.30E+01 WE 14 L9201-01 1/25/2005 Sb-124 -3.00E+00 2.20E+00 8.00E+00 WE 14 L9201-01 1/25/2005 Sb-125 1.19E+00 9.20E-01 3.00E+00 WE 14 L9201-01 1/25/2005 Se-75 -1.03E+OO 7.90E-01 2.70E+00 WE 14 L9201-01 1/25/2005 Zn-65 -9.60E-01 9.70E-01 3.40E+O0 WE 14 L9201 -01 1/25/2005 7Z-95 2.70E+00 1.60E+00 5.30E+O0 WE 14 L9203-01 2123/2005 AcTh-228 -1.40E+00 1.20E+O00 4.30E+00 WE 14 L9203-01 2/23/2005 Ag-108m -1.SOE-01 3.00E-01 1.00E+00 WE 14 L9203-01 2/23/2005 Ag-l lOm -6.00E-02 5.40E-01 l.90E+O00 WE 14 L9203-01 2/23/2005 Ba-140 -2.80E+01 1.40E3+01 5.30E+01 +

WE 14 L9203-01 2/23/2005 Be-7 -2.90E+00 6.30E+00 2.20E+01 WE 14 L9203-01 2/23/2005 Cc-141 2.20E+O0 3.00E+00 1.00E+01 WE 14 L9203-01 2/23/2005 Ce-144 -1.IOE+00 2.70E+00 9.20E+00

• Radioactivity detected in sample (ie., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-16

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (pCi/L)

WE L9203-01 2123/2005 Co-57 1.20E-01 3.50E-01 I1.2013+00 WE L9203-01 2/23/2005 Co-58 6.40E-01 6.50E-01 2.2013+00 WE L9203-01 2/23/2005 Co-60 -4.10O3-01 3.60E-01 I1.30E+00 WE L9203-01 2/23/2005 Cr-51 I1.20E+01 1.6013+01 5.3012+01 WE L9203-01 2123/2005 Cs-134 I1.801E-01 3.80E-01 I1.30E+00 WE L9203-01 2/23/2005 Cs-137 -3.0013-02 3.2013-01 1.IO13,00 WE L9203-01 2/23/2oo5 Fe-59 -1.3013.00 2.40E+00 8.30E-,00 WE L9203-01 2123/2005 1-131 -9.0013.01 1.40E+02 4.80E+02 2.2913.02 9.10]3+00 1.9013+01

• WE L9203-01 2123/2005 K-40 WE L9203-01 2123/2005 La-140 -3.30E+01 1.70E3+01 6.10O3+01 WE L9203-01 2/23/2005 Mn-54 -2.7013-01 3.8013-01 I1.30E+00 WE L9203-01 2123/2005 Nb-95 7.0013-01 I1.701E+00 5.70E+00 WE L9203-01 2123/2005 Ru-103 -2.10O3+00 I1.20E+00 4.30E.00 WE L9203-01 2/23/2005 Ru-106 -3.40E+00 3.50E+O0 1.2013+01 WE L9203-01 2/23/2005 Sb-124 -1.601E+00 I.5013+00 5.50E.+00 WE L9203-01 2/23/2005 Sb-125 1.I 11+00 9.50E-01 3.2013+00 WE L9203-01 2/23/2005 Se-75 -9.30E-01 6.90E-01 2.40E+00 WE L9203-01 2/23/2005 Zn-65 -1.41E+00 8.80E-01 3.2013+00 WE L9203-01 2/23/2005 Zr-95 6.OOE-01 1.2013+00 4.2013+00 WE L9204-01 3/31/2005 AcTh-228 3.6013i00 2.7013+00 9.1013+00 WE L9204-01 3/31/2005 Ag-lOSm -5.30E-01 4.40E-01 1.6013+00 WE L9204-01 3/31/2005 Ag- lOmn -1.1OE-01 7.60E-01 2.70E+00 WE L9204-01 3/31/2005 Ba-140 -4.30E+00 3.30E-g-00 1.30E+01 WE L9204-01 3/31/2005 Be-7 -1.14E+01 6.10OE+00 2.20E+01 WE L9204-01 3/31/2005 Ce-141 -1.0013-01 1.30E+00 4.50E+00 WE L9204-01 3/31/2005 Ce-144 -1.OOE3-01 3.201E+00 1.IE0130 WE L9204-01 3/31/2005 Co-57 -5.80E-01 4.10O3-01 I1.4013+00 WE L9204-01 3/31/2005 Co-58 I.0013+00 6.60E3-01 2.20E3+00 WE L9204-01 3/31/2005 Co-60 -4.1013-01 5.8013-01 2.1013+00 WE L9204-01 3/31/2005 Cr-51 -4.30E+00 9.2013+00 3.2013+01 WE L9204-01 3131/2005 Cs-134 -7.OOE-01 5.3013-01 1.90E+00 WE L9204-01 3131/2005 Cs-137 -9.10E-01 5.60E-01 2.OOE+00 WE L9204-01 3131/2005 Fe-59 -2.20E3+00 2.40E2+00 8.70E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-17

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (pCi/L)

WE 14 L9204-01 3/31/2005 1-131 -4.80E+00 9.70E+00 3.40E+01 WE 14 L9204-01 3/31/2005 K-40 2.13E+02 1.40E+01 3.00E+01 WE 14 L9204-01 3/31/2005 La-w40 -4.90E+00 3.80E+00 1.40E+01 WE 14 L9204-01 3/31/2005 Mn-54 -5.00E-01 5.30E-01 1.90E+00 WE 14 L9204-01 3/31/2005 Nb-95 7.00E-01 1.00E+00 3.50E+00 WE 14 L9204-01 3/31/2005 Ru-103 -2.90E-01 8.40E-01 2.90E+00 WE 14 L9204-01 3/31/2005 Ru-106 -4.30E+00 5.00E+00 1.80E+01 WE 14 L9204-01 3/31/2005 Sb-124 -1.70E+00 1.90E+00 7.20E1+00 WE 14 L9204-O1 3/31/2005 Sb-125 -8.00E-01 1.40E+00 4.80E+00 WE 14 L9204-01 3/31/2005 Se-75 2.40E-01 6.80E-01 2.30E+00 WE 14 L9204-01 3131/2005 Zn-65 -1.20E1+00 1.30E1+00 4.80E+00 WE 14 L9204-01 3/31/2005 Zr-95 -1.60E+00 1.30E+00 4.70E+00 WE 14 L9508-01 5/26/2005 AcTh-228 -2.00E+00 1.60E+00 5.60E+00 WE 14 L9508-01 5/26/2005 Ag-108m -5.00E-02 2.90E-01 1.OOE+00 WE 14 L9508-01 5/6/2005 Ag-I1m 1.10E-01 4.90E-01 1.70E+00 WE 14 L9508-01 5/26n/5 Ba-140 -3.00E+00 3.10E+00 1.1OE+01 WE 14 L9508-01 5/2612005 Be-7 3.20E+00 4.60E+00 1.50E+01 WE 14 L9508-01 5/26/2005 Ce-141 1.00E-01 1.30E+00 4.30E+00 WE 14 L9508-01 5/26/2005 Ce-i44 -7.00E-01 2.50E+00 8.50E+00 WE 14 L9508-01 5/26/2005 Co-57 1.10E-01 3.40E-01 1.1OE+00 WE 14 L9508-01 5/26/2005 Co-58 -6.40E-01 4.60E-01 1.60E+00 WE 14 L9508-01 5/26/2005 Co-60 -4.10E-01 3.60E-01 1.30E+00 WE 14 L9508-01 5/26/2005 Cr-SI 4.00E+00 7.80E+00 2.60E+01 WE 14 L9508-01 5/26/2005 Cs-134 -1.07E+00 4.00E-01 1.SOEg+00 WE 14 L9508-01 5/26/2005 Cs-137 -8.00E-02 3.40E-01 1.20E+00 WE 14 L9508-01 5/26/2005 Fe-59 4.00E-01 1.60E+00 5.40E+00 WE 14 L9508-01 5/26/2005 1-131 -9.00E+00 1.20E+01 4.30E+01 WE 14 L9508-01 5/26/2005 K-40 1.65E+02 8.40E1+00 1.901E+01 WE 14 L9508-01 526/2005 la-140 -3.40E+00 3.60E+00 1.30E+01 WE 14 L9508-01 5/26/2005 Mn-54 -1.10E-01 3.50E-01 1.20E+00 WE 14 L9508-01 5/26/2005 Nb-95s.LE+00 7.80E-01 2.60E+00 WE 14 L9508-01 5/26/2005 Ru-103 5.00E-01 1.10E+00 3.70E+00 WE 14 L9508-01 5/26/2005 Ru-106 -4.90E+00 3.40E+00 1.20E+01

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-18

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (pCiL)

WE 14 L9508-01 5/26/2005 Sb-124 -1.30E+00 I.IOE+00 4.00E+00 WE 14 L9508-01 5/26/2005 Sb-125 -4.80E-01 9.30E-01 3.20E+00 WE 14 L9508-01 5/26/2005 Se-75 1.57E+00 5.60E-01 1.80E+00 WE 14 L9508-01 5/26/2005 Zn-65 2.80E-01 8.50E-01 2.90E+3O0 WE 14 L9508-01 5/2612005 Zr-95 -5.70E-01 8.90E-01 3.10E+00 WE 14 L9509-01 6/29/2005 Aclh-228 4.10E+00 7.00E+00 2.50E+01 WE 14 L9509-01 6/29/2005 Ag-108m 1.90E+00 1.50E+00 5.IOE+00 WE 14 L9509-01 6/29/2005 Ag-lilm -1.30E+00 2.70E+00 I.OOE+01 WE 14 L9509-01 6/29/2005 Ba-140 -2.40E+00 3.50E+00 1.SOE+01 WE 14 L9509-01 6/29/2005 Be-7 1.20E+01 1.SOE+01 5.40E+01 WE 14 L9509-01 6/29/2005 Ce-141 1.OOE+00 3.20E+00 1.IOE+01 WE 14 -L9509-01 6/29/2005 Ce-144 1.70E+01 I.IOE+01 3.70E+01 WE 14 L9509-01 6/29/2005 Co-57 -2.30E+00 1.40E+00 5.40E+00 WE 14 L9509-01 6/29/2005 Co-58 2.80E+00 2.00E+00 6.80E+O0 WE 14 L9509-01 6/29/2005 Co-60 1.60E+00 2.10E+00 7.30E+00 WE 14 L9509-01 6/29/2005 Cr-5I -4.OOE+00 1.90E+01 7.00E+O1 WE 14 L9509-01 6/29/2005 Cs-134 1.30E+00 2.20E+00 7.70E3+00 WE 14 L9509-01 6/29/2005 Cs-137 1.30E+00 2.00E+00 7.10E+00 WE 14 L9509-01 6/29/2005 Fe-59 -5.50E+00 6.30E+00 2.50E+01 WE 14 L9509-01 6/29/2005 1-131 -5.00E-01 4.90E+00 1.80E+01 WE 14 L9509-01 6/29/2005 K-40 1.95E+02 4.20E+01 1.20E+02 WE 14 L9509-01 6/29/2005 La-140 -2.80E+00 4.00E+00 1.70E+01 WE 14 L9509-01 6/29/2005 Mn-54 6.00E-01 1.90E+00 7.00E+00 WE 14 L9509-01 6/29/2005 Nb-95 2.80E+00 2.50E+00 8.50E+00 WE 14 L9509-01 6/29/2005 Ru-103 8.00E-01 2.30E+00 8.IOE+00 WE 14 L9509-01 6/29/2005 Ru-106 -1.60E+01 2.00E+01 7.40E+01 WE 14 L9509-01 6/29/2005 Sb-124 -1.IOE+00 4.40E+00 1.80E+01 WE 14 L9509-01 6/29/2005 Sb-125 5.30E+00 4.90E+00 1.70E+01 WE 14 L9509-01 6/29/2005 Se-75 1.30E1+00 2.50E+00 8.60E+00 WE 14 L9509-01 6/29/2005 Zn-65 -1.70E+00 3.50E+00 1.40E+01 WE 14 L9509-01 6/29/2005 Zr-95 -1.60E+00 3.40E+00 1.30E+01 WE 14 L9510-01 4/27/2005 AcTh-228 1.98E+00 7.60E-01 3.OOE+00 WE 14 L9510-01 4/27/2005 Ag-108m 3.00E-02 1.80E-01 6.10E-01

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-19

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (KUiL) (pci/L) (pCi/L)

WE 14 L9510-01 4/27/2005 Ag-l lim -4.9013-01 3.50E-01 I1.201E+00 WE 14 L9510-01 4/27/2005 Ba-140 -2.601E+01 I1.2013+01 4.20E2+01 +.

WE 14 L9510-01 4/27/2005 Be-7 3.801E+00 6.60E3+00 2.2013+01 WE 14 L9510-01 4/27/2005 Ce-141 6.0013-01 2.7013+00 9.0013+00 WE 14 L9510-01 4/27/2005 Ce-144 2.60E3+00 I1.60E3+00 5.2013+00 WE 14 L9510-01 4/27/2005 Co-57 3.0013-01 2.101E-01 6.8013-01 WE 14 L9510-01 4/27/2005 Co-58 4.0013-01 3.701E-01 I1.2013+00 WE 14 L9510-01 4/27/2005 Co60 8.0013-02 2.3013-01 7.90E3-01 WE 14 L9510-01 4/27/2005 Cr-51 3.00E3+00 I.001E+01 3.5013+01 WE 14 L9510-01 4/27/2005 Cs-134 -4.0013-01 2.4013-01 8.30E3-01 WE 14 L9510-01 4/27/2005 Cs-137 I .00E3-01 2.2013-01 7.40E3-01 WE 14 L9510-01 4/27/2005 Fe-59 2.70E3+00 I1.70E+O00 5.701E+00 WE 14 L95 10-01 4/27/2005 1-131 -7.0013+01 1.IOE+02 3.6013+02 WE 14 L9510-01 4/27/2005 K-40 1.33E3+02 5.601E+00 1.5013+01 WE 14 L9510-01 4/27/2005 La-140 -3.001E+01 I1.4013+01 4.901E+01 WE 14 L9510-01 4/27/2005 Mn-S4 4.90E3-01 2.50E3-01 8.OOE-01 WE 14 L9510-01 4/27/2005 Nb-95 -4.601E-01 S. IOE013 2.701E+00 WE 14 L9510-01 4127/2005 Ru-103 -2.42E+O0 7.0013-01 2.50E3+00 WE 14 L9510-01 4127/2005 Ru-106 -2.1013+00 2.3013+00 7.8013+00 WE 14 L9510-01 4/27/2005 Sb-124 -4.00E3-01 1.IO1+00 3.70E3+00 WE 14 L9510-01 4/27/2005 Sb-125 -1.6313+00 5.90E-01 2.0013+00 WE 14 L9510-01 4/27/2005 Se-75 3.30E3-01 4.101E-01 I1.401E+00 WE 14 L9510-01 4/27/2005 Zn-65 I1.30E3-01 5.3013-01 1.801E+00 WE 14 L9510-01 4/27/2005 Zr-95 4.601E-01 7.20E-01 2.40E+O00 WE 14 L9586-01 3/31/2005 H-3 -1.1 OE+02 3.80E3+02 I1.30E3+03 WE 14 L9587-01 6/29/2005 H-3 -6.OOE+01 3.701E+02 I1.20E.+03 WE 20 L9201-02 1/25/2005 AcTh-228 2.001E-01 1.501E+00 5.101E+00 WE 20 L9201-02 1/25/2005 Ag-108m 6.001E-02 2.80E3-01 9.60E3-01 WE 20 L9201-02 1/25/2005 Ag- lOin 3.50E3-01 5.2013-01 I1.7013+00 WE 20 L9201-02 1/25/2005 Ba-140 2.701E+01 7.3013+01 2.5013+02 +

WE 20 L9201 -02 1/252005 Be-7 3.701E+00 9.10OE+00 3.101E.01 WE 20 L9201-02 1/25/2005 Ce-141 7.601E+00 4.10OE.00 1.40E3+01 WE 20 L9201-02 1/25/2005 Ce-144 -4.40E+00 2.80E+00 9.60E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-20

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE KUCL) (pCVL) (pCi/L)

WE 20 L9201-02 1/25/2005 Co-57 3.001E-02 3.701E-01 I1.2013t00 WE 20 L9201-02 1/25/2005 Co-58 -2.801E-01 7.30E3-01 2.5013+00 WE 20 L9201-02 1/25/2005 Co60 -2.00E3-02 3.301E-01 1.2013+00 WE 20 L9201-02 1/25/2005 Cr-SI -6.001E+01 3.20E3+01 1.AOE+02 WE 20 L9201-02 1/25/2005 Cs-134 4.20E3-01 3.601E-01 1.20E1,-00 WE 20 L9201-02 1/25/2005 Cs-137 -9.001-02 3.3013-01 I AOE3+00 WE 20 L9201-02 1/25/2005 Fe-59 -5.70E+00 3.601E+00 1.301+01 WE 20 L9201-02 1125/2005 1-131 8.00E3+02 I1.80E3+03 6.10OE+03 L9201-02 4.32E4.01

• WE 20 1125/2005 K-40 6.101E+00 1I801E+01 WE 20 L9201-02 1/25/2005 La-140 3.101E+01 8.301E+01 2.901E+02 WE 20 L9201-02 1/25/2005 Mn-54 3.40E3-01 3.80E-01 1.3013t00 WE 20 L9201-02 1/25/2005 Nb-95 1.80E-,.00 2.101-t00 7.00E.+00 WE 20 L9201-02 1/25/2005 Ru-103 -5.30E+00 2.60E3+00 9.101E+00 WE 20 L9201-02 1/25/2005 Ru-106 4.3013.00 3.40E3+00 LIOE1+01 WE 20 L9201-02 1/25/2005 Sb-124 -9.001E-01 2.301E+00 800OE+00 WE 20 L9201-02 1/25/2005 Sb-125 2.001E-01 I. 1OE+00 3.701-e00 WE 20 L9201 -02 1/25/2005 Se-75 -7.60E-01 7.101-01 2.401E+00 WE 20 L9201-02 1/25/2005 Zn-65 -9.50E-01 8.90E3-01 3.201E+00 WE 20 L9201-02 1/25/2005 Zr-95 -4.001E-01 I1.501E+00 5.101E+00 WE 20 L9203-02 2123/2005 Aclb-228 -7.00E3-01 1.501E.00 5.001E+00 WE 20 L9203-02 2/23/2005 Ag-108m -1.301E-01 3.001E-01 1.001E+00 WE 20 L9203-02 2/23/2005 Ag-IlOm -8.901E-01 4.80E3-01 1I70E-tOO WE 20 L9203-02 2/23/2005 Ba-140 -3.10E1u01 1.601E+01 5.801E+0I +

WE 20 L9203-02 2/23/2005 Be-7 -3.801E+00 6.30E+O00 2.20E1t-01 WE 20 L9203-02 2/23/2005 Ce-141 1.901E+00 2.3013t00 7.70E+O0 WE 20 L9203-02 2/23/2005 Ce-144 2.20E-,.00 2.7013-00 8.90E3+00 WE 20 L9203-02 2/23/2005 Co-57 2.301E-01 3.501E-01 1.20E3+00 WE 20 L9203-02 2/23/2005 CO-58 -2.401E-01 5.801E-01 2.001E+00 WE 20 L9203-02 2/23/2005 Co-60 -3.80E-01 3.401E-01 1.201E+00 WE 20 L9203-02 2/23/2005 Cr-SI -2.60E-e01 1.601E+01 5.401E.01 WE 20 L9203-02 2/23/2005 Cs-134 2.10E-01 3.401E-01 1.20E+O00 WE 20 L9203-02 2/23/2005 Cs-137 6.401E-01 3.30E3-01 1I101E+00 WE 20 L9203-02 2/23/2005 Fe-59 2.501E+00 2.201E+00 7.5013t00

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-21

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (pCi/L)

WE 20 L9203-02 2/23/2005 1-131 -1.70E+02 1.40E+02 4.80E+02 WE 20 L9203-02 2/23/2005 K-40 1.83E+01 5.70E+00 1.80E+01 WE 20 L9203-02 2/23/2005 La-wo -3.60E+01 1.80E+01 6.70E+01 WE 20 L9203-02 2/23/2005 Mn-54 3.10E-01 3.40E-01 1.20E+O0 WE 20 L9203-02 2/23/2005 Nb-95 1.60E+00 1.lOE+00 3.80E+O0 WE 20 L9203-02 2/23/2005 Ru-103 -3.20E+00 1.50E+00 5.40E+00 WE 20 L9203-02 2/23/2005 Ru-106 1.90E+00 3.20E+O0 1.OE+01 WE 20 L9203-02 2/23/2005 Sb-124 -1.00E-01 1.60E+00 5.40E+00 WE 20 L9203-02 2/23/2005 Sb-125 -I.1OE+00 l.lOE+00 3.80E+O0 WE 20 L9203-02 2/23/2005 Se-75 -1.60E-01 6.10E-01 2.00E+00 WE 20 L9203-02 2/23/2005 Zn-65 -3.00E-01 8.30E-01 2.90E3+00 WE 20 L9203-02 2123/2005 Zr-95 6.00E-01 1.00E+00 3.60E+00 WE 20 L9204-02 3/31/2005 Aclh-228 -9.00E-01 2.30E+00 8.00E+O0 WE 20 L9204-02 3/31/2005 Ag-108m -4.60E-01 4.10E-01 1.40E+00 WE 20 L9204-02 3/31/2005 Ag-i iOm 4.50E-01 7.20E-01 2.50E+00 WE 20 L9204-02 3/31/2005 Ba-140 -1.90E+00 3.30E+00 1.20E+01 WE 20 L9204-02 3/31/2005 Be-7 -8.20E+00 5.50E+00 2.00E3+01 WE 20 L9204-02 3/31/2005 Ce-141 -1.IOE+00 1.40E1+00 4.80E+00 WE 20 L9204-02 3/31/2005 Ce-144 O.OOE+00 3.00E+00 1.00E+01 WE 20 L9204-02 3/31/2005 Co-57 5.30E-01 3.80E-01 1.30E+00 WE 20 L9204-02 3/31/2005 Co-58 3.30E-01 6.30E-01 2.101E+00 WE 20 L9204-02 3/31/2005 Co-60 4.70E-01 5.90E-01 2.00E3+00 WE 20 L9204-02 3/31/2005 Cr-SI 1.00E+01 7.60E+00 2.50E+01 WE 20 L9204-02 3/31/2005 Cs-134 5.80E-01 5.60E-01 1.90E+00 WE 20 L9204-02 3/31/200s Cs-137 5.90E-01 4.70E-01 1.60E+00 WE 20 L9204-02 3/31/2005 Fe-59 -3.50E+00 2.00E+00 7.60E+00 WE 20 L9204-02 3/31/2005 1-131 -4.90E+00 7.80E+00 2.70E+01 WE 20 L9204-02 3/31/2005 K-40 1.43E+01 9.00E+00 2.90E+01 WE 20 L9204-02 3/31/2005 La-140 -2.20E+00 3.80E+00 1.40E+01 WE 20 L9204-02 3/31/2005 Mn-54 1.1I E+00 5.30E-01 1.70E+00 WE 20 L9204-02 3/31/2005 Nb-95 2.80E-01 9.20E-01 3.10E+00 WE 20 L9204-02 3/31/2005 Ru-103 -1.60E+00 l.00E+00 3.80E+00 WE 20 L9204-02 3/31/2005 Ru-106 3.00E-01 3.70E+00 1.30E+01

• Radioactivity detected In sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-22

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCz/L) (pCi/L)

WE L9204-02 3/31/2005 Sb-124 2.00E3+00 1.801+00 6.003+O00 WE L9204-02 3/31/2005 Sb-125 -1 .00E-01 1.3013+00 4.3013+00 WE L9204-02 3/31/2005 Se-75 -6.2013-01 6.10O3-01 2.1013+00 WE L9204-02 3/31/2005 ZnS65 -1 .3013+00 1. IOE+00 4.101E+00 WE L9204-02 3/31/2005 Zr-95 3.OOE-01 I1.2013+00 4.00E+00 WE L9508-02 5/26/2005 Aclh-228 4.00E3-01 1.60E+00 5.20E3+00 WE L9508-02 5/26/2005 Ag-108m -1.901E-01 2.90E-01 1.0013+00 WE L9508-02 5/26/2005 Ag-I lOm -6.801E-01 4.6013-01 1.60E-,00 WE L9508-02 5/26/20o5 Ba-140 3.7013+00 3.4013+00 1. IOE+01 WE L9508-02 5126/2005 Be-7 2.7013+00 4.501E+00 1.501E+01 WE L9508-02 5/26/2005 Ce-141 2.301E+00 1.301E+00 4.30E+O0 WE L9508-02 5/26/2oo5 Ce-144 -1 .OOE+00 2.5013+00 8.50E+00 WE L9508-02 5/2612005 Co-57 -1.301E-01 3.3013-01 1. l13+00 WE L9508-02 5/26/2005 Co-58 -3.7013-01 4.5013-01 1.601E.00 WE L9508-02 5/26/2005 Co60 2.0013-02 3.301E-01 I. I1E+00 WE L9508-02 5/26/2005 Cr-SI 4.2013+00 7.9013+00 2.60E1,.01 WE L9508-02 5/26/2005 Cs-134 6.801E-01 3.401E-01 1.IO1E+00 WE L9508-02 512612005 Cs-137 -8.001E-02 3.20E-01 I.1O1E+00 WE L9508-02 5/26/2005 Fe-59 2.9013+00 1.501E+00 5.0013+00 WE L9508-02 5/2612005 1-131 5.OOE-,00 1.2013+01 4.1013+01 WE L9508-02 5/26/2005 K-40 2.7013+00 5.40E3+00 1.80E3+01 WE L9508-02 5/26/2005 La-140 4.2013+00 3.901-i-00 1.3013+01 WE L9508-02 5/26/2005 Mn-54 I.001E-01 3.401E-01 1.2013+00 WE L9508-02 5/26/2005 Nb-95 6.2013-01 6.8013-01 2.3013400 WE L9508-02 5/26/2005 Ru-103 -2.0313+00 9.40E-01 3.301E+00 WE L9508-02 5/26/2005 Ru-106 -3.0013-01 3.1013+00 I.IOE+01 WE L9508-02 5/26/2005 Sb-124 2.0013-01 I1.2013.00 4.2013+00 WE L9508-02 5/262005 Sb-125 -9.0013-01 I. IOE+00 3.8013+00 WE L9508-02 5/26/2005 Se-75 -2.80E-01 5.0013-0I 1.701E+00 WE L9508-02 5/26/O205 Zn-65 -8.0013-01 7.2013-01 2.6013+00 WE L9508-02 5/26/2005 Zr-95 -7.1011-01 7.9013-01 2.80E+O0 WE L9509-02 6129/2005 AcTh-228 1.5013+00 6.901E+00 2.50O3+01 WE L9509-02 6/29/2005 Ag-108m 1. IE+O00 I1.3013+00 4.501E+00

• Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-23

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (PCi/L) (pCi/L) (pCi/L)

WE 20 L9509-02 6/29/2005 Ag-I t1rn 1.20E3+00 2.401E+00 8.50E+00 WE 20 L9509-02 6/29/2005 Ba-140 3.7013+00 3.70E+00 1.30E+01 WE 20 L9509-02 6/29/2005 Be-7 -1.3013+01 I1.50E+01 5.60E+01 WE 20 L9509-02 6/29/2005 Ce-141 -4.7013+00 2.6013+00 9.50E3+00 WE 20 L9509-02 6/29/2005 Ce-144 4.30E+00 8.70E+00 3.OOE+01 WE 20 L9509-02 6/29/2005 Co-57 5.OOE-01 1.IOE+00 3.80E3+00 WE 20 L9509-02 6/29/2005 Co-SS 6.OOE-01 I1.50E+00 5.40E2+00 WE 20 L9509-02 6/29/2005 Co-60 4.20E+00 2.10OE+00 6.50E3+00 WE 20 L9509-02 6/29/2005 Cr-51 -4.OOE+00 1.40E+01 5.10O3+01 WE 20 L9509-02 6/29/2005 Cs-134 2.OOE+00 I1.80E+00 6.OOE-i00 WE 20 L9509-02 6/29/2005 Cs-137 1.OOE+00 I1.601E+00 5.60E3+00 WE 20 L9509-02 6/29/2005 Fe-59 2.70E+00 5.30E.+00 1.90E.+01 WE 20 L9509-02 6/29/2005 1-13 1 2.30E+00 4.10O3.00 I1.40E+01 WE 20 L9509-02 6/29/2005 K-40 1.00E+00 2.70E+01 9.70E3+01 WE 20 L9509-02 6/29/2005 La- 140 4.301E+00 4.20E3+00 I1.50E+.01 WE 20 L9509-02 6/29/2005 Mn-54 -1. IOE+00 1.8013+00 6.90E+00 WE 20 L9509-02 6/29/2005 Nb-95 -6.0013-01 2.3013+00 8.40E+00 WE 20 L9509-02 6/29/2005 Ru-103 -1.50E.00 1.90E+00 7.10O3+00 WE 20 L9509-02 6/29/2005 Ru-106 -I1.40E+01 I1.40E3+01 5.30E3+01 WE 20 L9509-02 6/29/2005 Sb-124 9.601E+00 5.101E-i00 1.60E+01 WE 20 L9509-02 6/29/2005 Sb-125 3.30E+00 4.OOE+00 I1.40E+01 WE 20 L9509-02 6/29/2005 Se-75 -5.0013-01 1.70E+00 6.10OE+00 WE 20 L9509-02 6/29/2005 Zn65 1.IOE+00 4.OOE+00 1.4013+01 WE 20 L9509-02 6/29/2005 Z1-95 4.OOE-01 2.80E-,00 I .00E-,.01 WE 20 L9510-02 4/27/2005 Ac'M-228 2.60E+00 I1.80E3+00 6.I1OE+00 WE 20 L9510-02 4/27/2005 Ag-108m 1.00E2-02 4.90E3-01 1.70E3+00 WE 20 L9510-02 4/27/2005 Ag-I l0in -8.OOE-02 8.1013-01 2.90E3+00 WE 20 L9510-02 4/27/2005 Ba-140 -2.60E+02 9.0013+01 3.7013+02 +

WE 20 L9510-02 4/27/2005 Be-7 3.00E3+00 I1.40E3+01 4.80E3+01 WE 20 L9510-02 4/27/2005 Ce- 14 1 3. I OE+00 6.50E3+00 2.20E+01 WE 20 L9510-02 4/27/2005 Ce-144 -4.60E+00 4.8013i.00 1.70E+01 WE 20 L9510-02 4/27/2005 Co-57 4.8013-01 6.OOE-01 2.OOE+00 WE 20 L9510-02 4/27/2005 Co-58 -1.201E+00 1.30E+00 4.601E+00

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-24

Maine Yankee Radiological Environmental Monitoring Program Summary of 2005 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pUiL) (pCi/L) (pCitL)

WE 20 L9510-02 4127/2005 Co-60 -4.80E-01 5.6012-01 2.10E+00 WE 20 L9510-02 4/27/2005 Cr-51 6.201E+01 4.801E+01 1.60E+02 WE 20 L9510-02 4/27/2005 Cs-134 4.201E-01 5.90E-01 2.00E+00 WE 20 L9510-02 4/27/2005 Cs- 137 6.30E3-01 5.501E-01 1.80E+00 WE 20 L9510-02 4/27/2005 Fe-59 -3.501E+00 5.60E3+00 2.10E+01 WE 20 L9510-02 4/27/2005 1-13 1 -1.80E+03 2.00E3+03 7.10E+03 WE 20 L9510-02 4/27/2005 K-40 I1.6013+00 8.30E3+00 2.90E+01 WE 20 L9510-02 4/27/2005 La- 140 -3.0013+02 I.OOE+02 4.30E+02 WE 20 L9510-02 4/27/2005 Mn-54 '-3.60E-01 6.30E-01 2.30E+00 WE 20 L9510-02 4/27/2005 Nb-95 1.801E+00 3.00E+i00 1.001E+01 WE 20 L9510-02 4/27/2005 Ru-103 -5.50E.+00 3.701E+00 1.40E+01 WE 20 L9510-02 4/27/2005 Ru-106 -3.40E+00 5.601E+00 2.COE+01 WE 20 L9510-02 4/27/2005 Sb-124 -6.1013+00 3.40E+00 1.30E+01 WE 20 L9510-02 4/27/2005 Sb-125 -2.9013+00 1.701E+00 6.20E+00 WE 20 L9510-02 4/27/2005 Se-75 -7.001E-01 1. IOE+00 4.00E+00 WE 20 L9510-02 4/27/2005 Zn-65 4.00E3-01 I1.30E3+00 4.60E+00 WE 20 L9510-02 4/27/2005 Zr-95 5.201E+00 2.201E+00 7.10E+O00 WE 20 L9586-02 3/31/2005 H-3 -6.00E.+02 3.80E3+02 1.30E+03 WE 20 L9587-02 6129/2005 H-3 -7.001E+02 3.701E+02 1.30E+03

• Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement A-25