ML070790247

Yankee, Annual Radiological Environmental Operating Report for 2006

ML070790247
Person / Time
Site:	Yankee Rowe
Issue date:	03/14/2007
From:	Gerard van Noordennen Yankee Atomic Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BYR 2007-026
Download: ML070790247 (78)

Text

YA NKEE ATOMIC EL EC TRIC COMPAN Y Telephone (413) 424-5261 r 49 Yankee Road, Rowe, Massachusetts 01367 Y9ANKEE iyo E)March 14, 2007 BYR 2007-026 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-001

Reference:

License No. DPR-3 (Docket No. 50-29)

Subject:

2006 Annual Radiological Environmental Operating Report Yankee Atomic Electric Company (YAEC) herewith submits the 2006 Annual Radiological Environmental Operating Report. This document includes a summary of the findings of the Radiological Environmental Monitoring Program conducted by YAEC in the vicinity of the Rowe site. This information is submitted in accordance with the Quality Assurance Program (formerly referred to as the Yankee Decommissioning Quality Assurance Program).

Should you have any questions regarding this submittal, please contact me at (860)267-3938.

Sincerely, Gerry van Noordennen Regulatory Affairs Manager

Enclosure:

cc: S. Collins, NRC Region I Administrator J. Hickman, NRC Project Manager L. Kaufman, NRC Region 1, Deconmmissioning Branch R. Walker, Director, Radiation Control Program, MA DPH A/A-I S3C)I

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (ARE OR)

YANKEE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1, 2006 - DECEMBER 31, 2006 DOCKET NO. 50-29 LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY Rowe, Massachusetts

Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2006 TABLE OF CONTENTS 1.0 EXECUTIVE

SUMMARY

............................................................................................. 1

2.0 INTRODUCTION

...................................................................................................... 1.

2.1 General Site Information .............................................................................................. 1..

2.2 Program Design.......................................................................................................... 2 2.3 Monitoring Zones........................................................................................................ 3 2.4 Pathways Monitored..................................................................................................... 3 2.5 Descriptions of Monitoring Programs ................................................................................. 4 2.5.1IRiver Water Sampling.............................................................................................. 4 2.5.2 Ground Water Sampling ........................................................................................... 4 2.5.3 Sediment Sampling................................................................................................. 4 2.5.4 Fish Sampling...................................................................................................... 5 2.5.5 TLD Monitoring.................................................................................................... 4 3.0 RADIOLOGICAL DATA

SUMMARY

TABLES .................................................................. 19 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS .................................................................. 29 4.1 Sampling Program Deviations ................................................................................... 29 4.2 Comparison of Achieved LLDs with Requirements............................................................ 29 4.3 Results Compared Against Reporting Levels................................................................... 29 4.4 Data Analysis by Media Type.................................................................................... 29 4.4.1 River Water............................................................................................... 29 4.4.2 Ground Water............................................................................................. 30 4.4.3 Sediment.................................................................................................. 32 4.4.4 Fish ........................................................................................................ 34 4.4.5 Direct Radiation.......................................................................................... 35 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS.............................................................. 39

6.0 REFERENCES

......................................................................................................... 40 APPENDIX A - LAND USE CENSUS............................................................................. A-1 APPENDIX B - QUALITY ASSURANCE PROGRAM

SUMMARY

......................................... B-1 APPENDIX C -

SUMMARY

OF REMP DATA.................................................................. C-1 ii

Yankee Nuclear Power Station Yanke Ncler Radiological PwerStaionAnnual Envirornmental Operating Report 2006 1.0 EXECUTIVE

SUMMARY

The radiological environmental monitoring program for the Yankee Atomic Electric Company's Rowe site (YR) continued for the period January through December 2006, in compliance with the Yankee Quality Assurance Program (YQAP), Appendix D, and the Off-Site Dose Calculation Manual (ODCM). This annual report was prepared by the Yankee Atomic Electric Company (YAEC). YAEC and Normandeau Associates performed sample collection and field preparation activities during 2006. Gamma exposure rate measurements and laboratory analyses were performed by the AREVA Environmental Laboratory (E-LAB).

Thermoluminescent dosimeters (TLDs) were used to measure direct gammna exposure in the vicinity of the site and as far away as 22.2 kilometers. Radiochemiical and radiological analyses of samples were performed to detect the presence of any site-related radioactivity. Samples collected include air-particulate filters, river water, well water, storm drain water, bottom and shoreline sediment, and fish.

In evaluating the results of those analyses it is necessary to consider the variability of natural and man-made sources of radioactivity, distribution in the environment and uptake in environmental media. This variability is dependent on many factors including, past spatial variability of radioactive fallout from nuclear weapons tests and on-going redistribution of the fallout, contribution from cosmically produced radioactivity, ground water dynamics and soil characteristics. Any one of these factors could cause significant variations in measured levels of radioactivity. Therefore, these factors need to be considered in order to properly explain any variations in radiation detected and to distinguish between natural and station related radioactivity.

Yankee Nuclear Power Station (YNPS) was permanently shutdown in 1991. Activities at the site are now focused on fuel storage. By the end of 2006, decommissioning of the site was complete. The radiological monitoring through this REMP was substantially reduced to only include direct radiation by the end of 2006.

The predominant radioactivity detected by the monitoring program during 2006 was that from non-station sources, which includes fallout from past nuclear weapons tests and naturally occurring radionuclides. As has been typical of previous years, site-related radioactivity was observed in some of the monitoring samples. The specific observations of possible site effects included Cesium-137 in bottom sediment near the former plant discharge point and tritium in ground water. Air particulate analysis results collected in 2006 demonstrated that no site-related airborne particulate activity was present in samples collected beyond the site boundary or at the ISFSI.

2.0 INTRODUCTION

2.1 GENERAL SITE INFORMATION The Yankee Atomic Electric Company's Rowe (YR) site is located on over 1800 acres in a predominantly rural area of northwestemn Massachusetts, three-quarters of a mile south of the Vermont border. The site resides in the town of Rowe, Massachusetts, approximately 9 air miles east-northeast of North Adams, Massachusetts.

The surrounding area is heavily forested and lightly populated. Hills bounding the river valley rise 500 to 1000 feet above the site, reaching elevations of2l100 feet.

The Deerfield River is used extensively for hydroelectric power generation both upstream and downstream of YR. The Sherman Dam, immediately adjacent to the site, operates as a hydroelectric generating station.

Sherman Pond, the impoundment behind this damr, had been used as a source of cooling water for the former power plant.

1

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 The former nuclear power plant was voluntarily shut down on October 1, 1991 after 31 years of operation. The site was involved in the process of decommissioning over the years which involved the disassembly and removal of the plant components and structures and was completed in 2006. This process took place in strict conformance with USNRC regulations. Oversight of the site closure process will also continue from the U.S.

Environmental Protection Agency, the Massachusetts Department of Environmental Protection, and Massachusetts Department of Public Health.

2.2 PROGRAM DESIGN The Radiological Environmental Monitoring Program for the site was designed with specific objectives in mind. These were:

" To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by YR activities.

• To provide assurance to regulatory agencies and the public that the enviromnmental impact from YR is known and within anticipated limits.

" To verify the adequacy and proper functioning of site 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.

These objectives have continued to be in force, to varying degrees, throughout the completion of decommissioning activities at the YR site. Due to the completion of deconmiissioning of the site most of the objectives have a much more limited degree of importance than in the past.

The Radiological Environmental Monitoring Program was initiated in 1958, approximately two years before the plant began operation in 1960. It has been in operation continuously since that time, with improvements made periodically over those years. The program continued without modification following the shutdown of the plant in 1991 and was reduced in scope beginning in 1997, primarily to reflect the absence of short-lived radionuclides in various pathways resulting from the plant shutdown (no source of production) and the individual radionuclides short half-life (long decay time since the shutdown). Now that the decommissioning process has been completed, the Radiological Environmental Monitoring Program (REMP) has been reduced to eliminate all enviromnmental media and program elements, with the exception of direct radiation.

The program was designed to meet the intent of NRC Regulatory Guide 4. 1, Programsfor Monitoring Radioactivity in the Environs of Nuclear Power Plants; NRC Regulatory Guide 4.8, Environmental Technical Specificationsfor NuclearPower Plants; the NRC Branch Technical Position of November 1979 entitled, An Acceptable RadiologicalEnvironmentalMonitoringProgram; and NRC NUREG-0472, RadiologicalEffluent Technical Spec (ficationsfor PWR 's.

The environmental TLD program was designed and tested around NRC Regulatory Guide 4.13, Performance, Testing and ProceduralSpecificationsfor Thermoluminescence Dosimetry: EnvironmentalApplications. The quality assurance program was designed around the guidance given in NRC Regulatory Guide 4.15, Quality Assurancefor RadiologicalMonitoring Programs (Normal Operations)- Effluent Streams and the Environment.

2

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 The monitoring requirements of the KEMP are given in Section 2 of the ODCM and in Table 2-1 of this report.

The identification of the required sampling locations is given in Section 2 of the ODCM and in Tables 2-2 and 2-3 of this report. The sampling and monitoring locations are shown graphically on the maps in Figures 2-1 through 2-6.

2.3 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 the site activities. The first area locations are called "indicators" and the second area locations are called "controls." The distinction between the two areas, 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 site, river flow, and distance. Analysis of survey data from the two areas aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity and radiation due to site-related activities and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.

2.4 PATHWAYS MONITORED For all or part of 2006, three pathway categories were monitored by the KEMP. They are waterbomne, ingestion and direct radiation pathways. Each of these three categories is monitored by the collection of one or more sample media, which are listed as follows, and are described in more detail in this section:

" Waterbomne Pathways (Eliminated during 2006)

" River Water Sampling Section 2.5.1

" Ground Water Sampling Section 2.5.2

" Sediment Sampling Section 2.5.3

• Ingestion Pathways 0 Fish Sampling (Eliminated during 2006) Section 2.5.4

" Direct Radiation Pathway 0 TLD Monitoring Section 2.5.5 3

Yankee Nuclear Power Station Radiological Yanke NulearPowe Environmental Operating Report 2006 StaionAnnual

2.5 DESCRIPTION

S OF MONITORING PROGRAMS Sample types and frequency of analysis are given in Table 2-1. The sample locations are listed in Table 2-2 and Table 2-3 and shown in Figures 2-i to 2-7. ODCM lower limits of detection (LLDs) and required reporting levels are listed in Tables 2-4 and 2-5. The program as described here includes both required samples as specified in the Off-Site Dose Calculation Manual (ODCM) and any extra samples. Following is a detailed description of the sampling program for 2006:

2.5.1 River Water Sampling (Eliminated during 2006, Rev. 20 to the ODCM)

An automatic composite sampler is located at one downstream sampling location. The sampler is controlled by a timer that collects an aliquot of river water at least every two hours over a period of one month. In addition, river water grab samples are collected monthly at Sherman Pond, near the plant site, and at one upstream location (control). All river water samples are preserved with.HCL and NaHS0 3 or HN0 3 at the laboratory to prevent the plate-out of potentially present radionuclides on the container wall over time. Each sample is analyzed for gross-beta and gamma-emitting radionuclides. The monthly samples are composited quarterly by location and sent to the E-LAB for a tritium analysis. The monthly samples are also analyzed monthly beyond the minimum requirements of the ODCM.

2.5.2 Ground Water Sampling (Eliminated during 2006, Rev. 20 to the ODCM)

Grab samples are collected monthly from two on-site locations (potable water well at WG- 11 and Sherman Spring, WG-12). The ODCM requires samples to be collected semni-annually. Each sample is required by the ODCM to be analyzed for gamma-em-itting radionuclides and tritium. Samples are also analyzed for gross beta activity, which is beyond ODCM requirements. Gross beta analyses are performed to gather additional data that may help to provide early detection of site-related activity.

2.5.3 Sediment Sampling (Eliminated during 2006, Rev. 20 to the ODCM)

Shoreline sediment cores are collected annually from two locations, downstream and upstream of the site. At these locations, six two-inch inner diameter plastic coring tubes are driven into the sediment at least six inches deep. The cores are carefully extracted and kept in an upright position and sent to the E-LAB. At the E-LAB, the samples are analyzed for gamma-emitting radionuclides.

2.5.4 Fish Sampling (Eliminated during 2006, Rev. 20 to the ODCM)

Fish samples are collected annually at two locations (upstream of the site and in Sherman Pond). The species typically collected are yellow perch, smelt, pickerel, trout, bullheads or suckers. However, the makeup of any individual catch could be dominated by a single species available at the time. No attempt is made to differentiate sample analysis by fish species, such as those who primarily feed on the bottom and are closer to any radioactivity deposited in bottom sediments, from those species that feed higher in the water colunmn. The limiting factor in fish sampling program is the availability of sufficient sample volume needed for analysis, making the differentiation of species typically impractical. The fish samples are frozen and delivered to the environmental laboratory where the edible portions are analyzed for gamma-em-itting radionuclides.

4

Yankee Nuclear Power Station Yanke NulearPowe Radiological Environmental Operating Report 2006 StaionAnnual 2.5.5 TLD Monitoring Direct ganmma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801AS1 and UD-814ASI calcium sulfate dosimeters are used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic-screened container. This container is attached to an object such as a tree, fence or pole. TLDs are posted at 7 locations (6 indicator and 1 control location) which are required by Revision 20 to the ODCM. This number was reduced from the required numbers in the ODCM, Revision 19. All the TLDs are read out semi-annually.

5

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 TABLE 2-1 Radiological Environmental Monitoring Program (Sample Types, Collection Frequency, Analysis Requirements)

(As required by ODCM Section 2)

Collection Analysis Exposure Pathway And/or Number of Routine Collection Analysis Analysis Sample Media Sample Locations Sampling Frequency Type Frequency Mode

1. Direct Radiation (TLDs) 6 Continuous Semi-annually Gamma Dose Each TLD (changed to 6 during 2006) 2.Waterborne (a)

a. Surface Water 1 Composite at two Semi-annually Gross Beta Each Sample hour intervals- Gamma Isotopic Each Sample Downstream Tritium (11-3) Quarterly Composite 1 Grab -Upstream Semni-annually

b. Ground Water 2 Grab Semni-annually Gamma Isotopic Each Sample Tritium (H-3) Each Sample

c. Shoreline Sediment 2 Grab Annually Gamma Isotopic Each Sample

3. Ingestion (a)

a. Fish 2 Grab Annually Gamma Isotopic on edible Each sample portions

• Does not include other locations and those TLDs.

(a) Requirements for these locations were discontinued as part of Revision 20 to the ODCM during 2006.

6

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 TABLE 2-2 Radiological Environmental Monitoring Locations (non-TLD) in 2006 Yankee Rowe Station Distance Exposure Station From Site Direction Pathway Code Station Description Type (a) (km)n

1. Waterborne (b)

a. Surface WR-1 1 Bear Swamp Lower I 6.3 Down-river WR-21 Harriman Reservoir C 10.1 Up -river

b. Ground WG-l 1 Site Potable On-site WG-12 Sherman Spring 0.2 NW

c. Sediment SE-11 No. 4 Station 36.2 Down-river SE-21 Harriman Reservoir C 10.1 Up -river

2. Ingestion (b)

a. Fish FH- 11 Sherman Pond 1 1.5 Near Discharge FH-21 Harriman Reservoir C 10.1 Up -river (a)I=Indicator Station or C=Control Station

()Discontinued in 2006 as part of Revision 20 to the ODCM.

7

Yankee Nuclear Power Station Yanke NclerRadiological PwerStaionAnnual Enviromnmental Operating Report 2006 TABLE 2-3 Radiological Environmental Monitoring Locations (TLD) in 2006 Yankee Rowe Station Distance From Site Direction Station Code Station Description Type (a) (m() From Site GM- 1d) YAEC Visitors' Center (Furlon House) 1 0.8 SW GM2() Observation Stand 1 0.5 NW GM-6 (b) Readsboro Road Barrer 1 1.3 N GM-1 3 (d) Restricted Area Fence F 0.08 WSW GM-14 (d) Restricted Area Fence F 0.11 WANW GM-15 (b) Restricted Area Fence F 0.08 NNW GM-16 (b Restricted Area Fence F 0.13 NNE GM-1 7 (b) Restricted Area Fence F 0.14 ENE GM-18(d) Restricted Area Fence F 0.14 ESE GM- 19(d) Restricted Area Fence F 0.16 SE GM-20(d) Restricted Area Fence F 0.16 SSE GM- 2 1l(b) Restricted Area Fence F 0.11 SSW GM-22 (d) Heartwell-ville, VT C 12.6 NNW GM-27 (b Number 9 Road C 7.6 ENE GM-29 (d) Route 8A 0 8.2 ESE (a)

I = Indicator TLD; C = Control TLD; 0 = Outer Ring TLD; F = Industrial Area TLD, IF=ISFSI TLD.

(b)

These TLI~s are part of the REMP.

(c)

GM station distances and direction are from the former plant stack.

(d)

Requirements for these locations were discontinued as part of Revision 20 to the ODCM during 2006.

(e)

IF station distances and direction from ISFSI pad.

8

Yankee Nuclear Power Station Yanke Ncler Radiological PwerStaionAnnual Enviromnmental Operating Report 2006 TABLE 2-3 (Continued)

Radiological Environmental Monitoring Locations (TLD) in 2006 Yankee Rowe Station Distance From Direction Station Code Station Description Type (a) Site/ISFSI From j (kin) j Site/1SFSI GM-31 (d) Legate Hill Road 0 7 .6 (c) SSE GM-40 (d) Readsboro, Road 1 0 .5 (c) w IF- 1(d) ISFSI Security Fence IF 0.02 (e)WN IF-2 (d) Observation Stand IF 0.56 (e) NW IF-3 (d) ISFSI Security Fence IF 0.02 (e) N IF-4 (d) ISFSI Security Fence IF 0.03 (e) NE IF-5 (d) ISFSI Security Fence IF 0.05 (e) E IF-6 (d) ISFSI Security Fence IF 0.02 (e) SE IF-7 (d) ISFSI Security Fence IF 0.02 (e)

IF-8 (d) ISFSI Security Fence IF 0.04 (e) S IF-9 (d) Restricted Area Fence IF 0.05 (e) SE IF-10 (d) Restricted Area Fence IF 0.05 (e) SSE IF-i 1 (d) Restricted Area Fence IF 0. 14 (e) S IF-12 (d) Restricted Area Fence IF 0.21 ()N IF-18 (d) YNPS CW Intake IF 0.24 ()NNW IF-19 (d) ISFSI Security Fence Admin. Building IF 0. 17 e)w IF-20 (d) ISFSI Security Fence Gatehouse IF 0.24 ()WNW IF-40 (d) Readsboro, Road IF 0.70 (e)WN (a)

I = Indicator TLD; C = Control TLD; 0 = Outer Ring TLD; F =Industrial Area TLD, IF=ISFSI TLD.

(b)

These TLI~s are part of the REMP.

(C)

GM station distances and direction are from the former plant stack.

(d)

Requirements for these locations were discontinued as part of Revision 20 to the ODCM during 2006.

(e)

IF station distances and direction from ISFSI pad.

9

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 TABLE 2-4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements from ODCM Table 4.3 (a)

Analysis Water (Pci/l)

Fish (pCi/kg)

(wet)

{Sedime I

(pCi/kg -dry)

Gross-Beta 4 H-3 2000 Co-58, 60 15 130 Cs-134 15 130 150 Cs-137 18 150 180 (a) Revision 20 of the ODCM eliminated further consideration of these release pathways due to the elimination of the liquid effluent potential.

10

Yankee Nuclear Power Station Yanke NclerRadiological Enviromnmental Operating Report 2006 PwerStaionAnnual TABLE 2-5 Reporting Levels for Radioactivity Concentrations In Environmental Samples from ODCM Table 4 .2(b)

Fish Analysis Water (pCi/kg)

(pC j/I)(a)

H-3 30000 Mn-54 1000 30000 Co-58 1000 30000 Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 Cs-134 30 1000 Cs-137 50 2000 (a) Reporting Level for non-drinking water pathways.

(b) Revision 20 of the ODCM eliminated further consideration of these release pathways due to the elimination of the liquid effluent potential.

11

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 2-1 Radiological Environmental Sampling Locations Within 1 Mile of Yankee Rowe Station (See Table 2-2 for Final 2006 REMP Sample Location(s) 12

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 2-2 Radiological Environmental Sampling Locations Within 12 Miles of Yankee Rowe Station (See Table 2-2 for Final 2006 REMP Sample Locations) 13

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 2-3 Radiological Environmental Sampling Locations Outside 12 Miles of Yankee Rowe Station (See Table 2-2 for Final 2006 REMP Sample Locations) 14

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 2-4 Environmental TLD Monitoring Locations Within 1 Mile of Yankee Rowe Station (See Table 2-3 for Final 2006 REMP Sample Locations) 15

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 2-5 Environmental TLD Monitoring Locations Within 12 Miles of Yankee Rowe Station (See Table 2-3 for Final 2006 REMP Sample Locations) 16

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 2-6 Environmental TLD Monitoring Locations Outside of 12 Miles from Yankee Rowe Station (See Table 2-3 for Final 2006 REMP Sample Loctions) 17

Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2006 Figure 2-7 Environmental TLD Monitoring Locations For the ISFSI Facility at the Yankee Rowe Station (See Table 2-3 for Final 2006 REMP Sample Locations)

P5 OR1 I

18

Yankee Nuclear Power Station Yanke NulearPowe Radiological Environmental Operating Report 2006 StaionAnnual 3.0 RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples that were collected during 2006. These results, shown in Table 3- 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 for the pathways described in Section 2.3. A comparison of indicator stations versus control stations is presented. Table 3-2 provides the same information for TLD direct radiation measurements.

The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 2006, and the number of measurements which exceeded the Reporting Levels found in Table 4.2 Revision 19 of the YR ODCM. The latter are classified as 'Non-routine" results. The second column lists the required Lower Lin-it of Detection (LLD) for those radionuclides, as specified in the ODCM. The absence of a value in this columnm 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, which result in low sample volume. Such cases are addressed in Section 4.2 of this report.

For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations: (1) the indicator stations, which are within the range of influence of the site and which could conceivably be affected by site activities; (2) the station which had the highest mean concentration during 2006 for that radionuclide; and (3) the control stations, which are beyond the influence of the site. Direct radiation monitoring stations (using TLDs) are grouped into Indicator and Control stations.

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

• the mean value of all concentrations including negative values and values that are not considered "detectable",

• the lowest and highest concentration, and

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

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 a Reporting Level listed in Table 4.2 of the ODCM (Revision 19) or, a LLD requirement in Table 4.3 of the ODCM, (Revision 19 or 20) 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 that are routinely analyzed and reported by the E-LAB in a gamma spectroscopy analysis includes: Ac-Th-228, Ag-1 08m,4Ag-I lOin, Ba-140, Be-7, Ce-14 1, Ce-144, Co-57, Co-58, Co-60, Cr-5 1, Cs-134, Cs-137, Fe-59, 1-131, 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 during 2006 did a radionuclide not shown in Table 3-1 appear as a "detectable measurement".

Data from direct radiation measurements made by TLDs are provided in Table 3-2 in a format essentially the same as above. The complete listing of TLD data is provided in Table 3-3. Table 3-4 contains a list of TLDs placed to monitor the Yankee ISFSI site. Locations of these, including two located offisite, are shown in Figures 2-4 and 2-7.

19

Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2006 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2006)

MEDIUM: Air Particulates (AP) UNITS: DCi/cubic 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 (6) 0.01 1.8E -2 11 1.8E -2 NO DATA (0) C1.6 - 2.2)E -2 (1.6 - 2.2)E -2 (61 6) (61 6)

Be-7 (1) 8.4E -2 11 8.4E -2 NO DATA (0)

(1/ 1) (1/ 1)

K-40 (1) -8.OE -3 11 -8.OE -3 NO DATA (0)

(0/ 1) (0/ 1)

Co-58 (1) -4.OE -5 11 -4.OE -5 NO DATA (0)

(0/ 1) (0/ 1)

Co-60 (1) 3.1E -4 11 3.1E -4 NO DATA (0)

(0/ 1) (0/ 1)

Cs-1 34 (1) 0.05 -2.5E -4 11 -2.5E -4 NO DATA (0)

(0/ 1) (0/ 1)

Cs-1 37 (1) 0.06 -1.3E -4 ii -1.3E -4 NO DATA (0)

(0/ 1) (0/ 1)

Th-232 (1) 7.2E -4 11 7.2E -4 NO DATA (0)

(0/ 1) (0/ 1)

• The only radionucl ides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other radionuclides that were analyzed.

Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 4.2 (Rev. 19).

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

20

Yankee Nuclear Power Station Yanke NclerRadiological PwerStaionAnnual Enviromnmental Operating Report 2006 Table 3-1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2006)

MEDIUM: Fish (FH1 UNITS: pCilkg 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-*

K-40 (2) 3.3E 3 3.3E 3 1.8E 3 (0)

(1/ 1) U1/ 1) (1/ 1)

Mn-54 (2) 130 0.0E 0 0.OE 0 -3.2E 0 (0)

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

Co-58 (2) 130 3.013 0 21 7.OE 0 7.OGE 0 (0)

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

Fe-59 (2) 1.3E 1 1.3E 1 -7.OE 0 (0)

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

Co-60 (2) 130 -1.OE 1 21 6. OE 0 6. OE 0 (0)

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

Zn-65 (2) 260 -2.4E 1 21 -1.6E 1 -1.6E 1 (0)

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

Cs-i 34 (2) 130 1.3E 0 11 1.3E 0 -3.1E 1 (0)

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

Cs-I 37 (2) 150 5.5E 1 11 5.5E 1 4.5E 1 (0)

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

• The only radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other radionuclides that were analyzed.

• • Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 4.2 (Rev. 19).

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

21

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Table 3-1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2006)

MEDIUM: Sediment (SE) UNITS: pCi/ka dry 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 (6) -1.5E 2 21 -1.1E 2 -1.1E 2 (0) -5.9 - 2.1)E 2 -2.8 - -0.1)E 2 -2.8 - -0.1)E 2 (0/ 3) (0/ 3) (0/ 3)

K-40 (6) 2.OE 4 11 2.OE 4 1.6E 4 (0) (1.7 - 2.1)E 4 (1.7 - 2.1)E 4 1.4 - 1.8)E 4 (3/ 3) (3/ 3) (3/ 3)

Co-58 (6) -3.7E 0 21 9.313 0 9.3E 0 (0) -3.7 - 4.2)E 1 -9.0 - 23.0)E 0 -9.0 - 23.0)E 0 (0/ 3) (0/ 3) (0/ 3)

Co-60 (6) 2.6E 1 I1 2.6E 1 -2.7E 0 (0) 1.0 - 42.0)E 0 (1.0 - 42.0)E 0 -3.5 - 1.8)E 1 (0/ 3) (0/ 3) (0/ 3)

Cs-I 34 (6) 150 1.15 1 11 1.1E 1 5.05 0 (0) -7.0 - 30.0)E 0 -7.0 - 30.0)E 0 (0.0 - 8.0)E 0 (0/ 3) (0/ 3) (0/ 3)

Cs-I 37 (6) 180 1.45 2 21 3.7E 2 3.7E 2 (0) 1.1 - 1.7)E 2 (3.4 - 4.0)E 2 3.4 - 4.0)E 2 (2/ 3) (3/ 3) (3/ 3)

Th-232 (6) 9.75 2 11 9.7E 2 8.3E 2 (0) 8.6 - 11.6)E 2 (8.6 - 11.6)E 2 7.1 - 9.5)E 2 (3/ 3) (3/ 3) (3/ 3)

• The only radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other radionuclides that were analyzed.

Non-Routine refers to those radionuclides that exceeded the Reporting Levels in 00CM Table 4.2 (Rev. 19).

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

22

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnualEnvironmental Operating Report 2006 Table 3-1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2006)

MEDIUM: Ground Water (WG) UNITS: oCi/liter 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 (13) 4 4. OE 0 12 4.3E 0 NO DATA (0) C2.3 - 6.5)E 0 (3.1 - 6.5)E 0 (9/ 13) (7/ 8)

H-3 (12) 2000 2. 1E 3 12 3 .2E 3 NO DATA (0) -7.0 - 471.0)E 1 (1.3 - 4.7)E 3 (8/ 12) (8/ 8)

Mn-54 (13) 15 -6.5E -1 12 -1.OE -1 NO DATA (0) -2.8 - 1.7)E 0 -2.4 - 1.7)E 0 (0/ 13) (0/ 8)

Co-58 (13) 15 -1.1E 0 12 -3.2E -1 NO DATA (0) -5.8 - 3.6)E 0 -3.7 - 3.6)E 0 (0/ 13) (0/ 8)

Fe-59 (13) -4.2E -1 12 -2.5E -1 NO DATA (0) -4.3 - 5.7)E 0 -4.3 - 5.7)E 0 (0/ 13) (0/ 8)

Co-60 (13) 15 4.8E -1 12 8.6E -1 NO DATA (0) -2.8 - 4.1)E 0 -2.8 - 4.1)E 0 (0/ 13) (0/ 8)

Zn-65 (13) 30 -2.9E 0 12 -2.7E 0 NO DATA (0) -1.0 - 0.5)E 1 -1.0 - 0.4)E 1 (0/ 13) (0/ 8)

Zr-95 (13) 15 -2.4E -1 12 4.8E -1 NO DATA (0) -5.6 - 7.8)E 0 -5.6 - 7.8)E 0 (0/ 13) (0/ 8) 1-131 (13) 2.4E 0 11 3.1E 0 NO DATA (0) -7.0 - 22.0)E 0 -7.0 - 17.0)E 0 (0/ 13) (0/ 5)

Cs-I 34 (13) 15 1.2E -1 11 2.8E -1 NO DATA (0) -3.6 - 3.4)E 0 -2.3 - 1.4)E 0 (0/ 13) (0/ 5)

Cs-1 37 (13) 18 -1.2E 0 12 -1.2E 0 NO DATA (0) -3.6 - 1.3)E 0 -3.6 - 1.3)E 0 (0/ 13) (0/ 8)

Ba-140 (13) -1.8E 0 11 -1.OE 0 NO DATA (0) -9.5 - 0.5)E 0 -1.6 - -0.5)E 0 (0/ 13) (0/ 5)

• The only radionucl ides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other radionuclides that were analyzed.

Non-Routine refers to those radionucl ides that exceeded the Reporting Levels in 00CM Table 4.2 (Rev. 19).

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

23

Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2006 Table 3-1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2006)

MEDIUM: River Water (WR) UNITS: pCi/liter 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 (21) 1.6E 0 31 1.9E 0 1. 58 0 (0) 5.9 - 38.0)E -1 1.5 - 2.3)E 0 -3.1 - 27.8)E -1 (1/ 12) (0/ 3) (1/ 9)

H1-3 (18) 2000 -4.2E 2 21 -2.7E 2 -2.7E 2 (0) -1.0 - 0.4)E 3 -9.6 - 1.0)E 2 -9.6 - 1.0)E 2 (0/ 11) (0/ 7) (0/ 7)

Mn-54 (21) 15 -7.7E -1 21 8.4E -1 8.48 -1 (0) -3.4 - 3.3)E 0 -1.7 - 2.5)E 0 -1.7 - 2.5)E 0 (0/ 12) (0/ 9) (0/ 9)

Co-58 (21) 15 -2.8E -1 31 4.78 -1 -1.8E 0 (0) -3.1 - 2.8)E 0 -1.3 - 2.8)E 0 -4.0 - 0.4)8 0 (0/ 12) (0/ 3) (0/ 9)

Fe-59 (21) -1.8E -1 31 2.3E 0 1.3E 0 (0) C-5.3 - 6.6)8 0 -3.3 - 6.6)E 0 -5.3 - 8.2)E 0 (0/ 12) (0/ 3) (0/ 9)

Co-60 (21) 15 -5.18 -1 21 4.78 -1 4.7E -1 (0) -4.1 - 2.7)E 0 -1.4 - 1.6)E 0 -1.4 - 1.6)E 0 (0/ 12) (0/ 9) (0/ 9)

Zn-65 (21) 30 -1.8E 0 11 -1.08 0 -4.78 0 (0) -8.9 - 4.1)E 0 -8.9 - 4.1)E 0 -1.3 - 0.1)E 1 (0/ 12) (0/ 9) (0/ 9)

Zr-95 (21) 15 -3.4E -1 21 1.7E 0 1.7E 0 (0) -5.8 - 3.1)E 0 -2.4 - 6.1)E 0 -2.4 - 6.1)E 0 (0/ 12) (0/ 9) (0/ 9) 1-131 (21) 3.38 -2 11 6.08 -1 -9.OE -1 (0) -1.3 - 0.6)E 1 -1.3 - 0.6)E 1 -1.5 - 0.5)E 1 (0/ 12) (0/ 9) (0/ 9)

Cs-1 34 (21) 15 -1.08 -1 11-3.3E -2 -3.38 -2 (0) -3.1 - 3.9)E 0 -3.1 - 3.9)E 0 -1.8 - 1.9)8 0 (0/ 12) (0/ 9) (0/ 9)

Cs-137 (21) 18 4.5E -1 11 4.7E -1 -3.4E -1 (0) -2.7 - 3.4)E 0 -2.7 - 3.4)E 0 -2.5 - 2.0)E 0 (0/ 12) (0/ 9) (0/ 9)

Ba-140 (21) 2.1E 0 11 2.7E 0 -2.68 0 (0) -3.3 - 13.6)8 0 -3.3 - 13.6)E 0 -1.5 - 1.5)8 1 (0/ 12) (0/ 9) (0/ 9)

• The only radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other radionuclides that were analyzed.

Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 4.2 (Rev. 19).

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

24

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Tabie 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2006)

MEDIUM: Storm Drain Water (WW) UNITS: pCilliter Indicator Stations Station With Highest Mean Control Stations Radionuclides* Mean Station Mean Mean (No. Anaiyses) Required Range Range Range Non-Routine** LLD No. Detected-* No. Detected-* No. Detected-*

GR-B (7) 4 4 .3E 0 52 4.3E 0 NO DATA (0) (2.0 - 6.8)E 0 2.0 - 6.8)E 0 (5/ 7) (5/ 7)

H-3 (7) 2000 1.6E 2 52 1.6E 2 NO DATA (0) -3.0 - 5.0)E 2 -3.0 - 5.0)E 2 (1/ 7) (1/ 7)

Mn-54 (7) 15 -1.3E 0 52 -1.3E 0 NO DATA (0) -3.9 - 2.3)E 0 -3.9 - 2.3)E 0 (0/ 7) (0/ 7)

Co-58 (7) 1s -1.2E 0 52 -1.2E 0 NO DATA (0) -3.1 - 1.5)E 0 -3.1 - 1.5)E 0 (0/ 7) (0/ 7)

Fe-59 (7) -5.OE -1 52 -5.OE -1 NO DATA (0) -4.1 - 2.9)E 0 -4.1 - 2.9)E 0 (0/ 7) (0/ 7)

Co-60 (7) 15 -1.1E -1 52 -1.1E -1 NO DATA (0) -2.9 - 2.1)E 0 -2.9 - 2.1)E 0 (0/ 7) (0/ 7)

Zn-65 (7) 30 -1.9E 0 52 -1.9E 0 NO DATA (0) -9.7 - 11.3)E 0 -9.7 3)E 0 (0/ 7) (0/ 7)

Zr-95 (7) 15 4.4E -1 52 4.4E -1 NO DATA (0) -4.1 - 4.2)E 0 -4.1 - 4.2)E 0 (0/ 7) (0/ 7) 1-131 (7) 1.4E 0 52 1.4E 0 NO DATA (0) -2.2 - 5.3)E 0 -2.2 - 5.3)E 0 (0/ 7) (0/ 7)

Cs-I 34 (7) 15 4.6E -1 52 4.6E -1 NO DATA (0) -4.8 - 3.6)E 0 -4.8 - 3.6)E 0 (0/ 7) (0/ 7)

Cs-1 37 (7) 18 -2.7E -1 52 -2.7E -1 NO DATA (0) -3.8 - 1.8)E 0 -3.8 - 1.8)E 0 (0/ 7) (0/ 7)

Ba-140 (7) 2.7E -1 52 2.7E -1 NO DATA (0) -2.7 - 3.5)E 0 -2.7 - 3.5)E 0 (0/ 7) (0/ 7)

• The only radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other radionuclides that were analyzed.

• • Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 4.2 (Rev. 19).

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

25

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 TABLE 3-2 ENVIRONMENTAL TLD DATA

SUMMARY

(JANUARY - DECEMBER 2006)

IiR/hr INDICATOR TLDs OUTER RING TLDs FENCELINE TLDs** CONTROL TLDs MEAN MEAN MEAN MEAN RANGE RANGE RANGE RANGE (NO. MEASUREMENTS)* (NO. MEASUREMENTS')* (NO. MEASUREMENTS)* (NO. MEASUREMENTS)I*

7.4 + 0.6 5.8 + 0.3 14.4 +/- 0.7 6.8 0.4 6.9 - 8.3 5.0 - 6.7 7.8 - 39.6 6.3 7.4 (8) (4) (4)

OFFSITE STATION WITH HIGHEST MEAN MEAN STA. RANGE NO. (NO. MEASUREMENTS)*

GM-01 7.7 + 0.3 7.10 - 8.27 2

• Each 'measurement" is based on readings from five TLD elements. Measurement units are pRlhr.

• • Not part of REMP (TLD locations are inside the site boundary). Increased exposure rates are due to fuel placement on the ISFSI which began in the 2nd half of 2002. Fuel and GTCC placement was completed in June 2003.

26

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 TABLE 3-3 2006 ENVIRONMENTAL TLD MEASUREMENTS*

(Micro-R per hour)

Annual 1st Halfyr. 2nd Half yr Average Sta.

No. Description Expos. +/-SD*** Expos. +/-SD*** Expos.

GM01 YR Visitors Center 7.10 0.28 8.27 0.40 7.7 GM02 Observation Stand 6.93 0.70 6.88 0.47 6.9 GM06 Readlsboro Rd. Barrier 7.20 0.52 7.66 0.35 7.4 GM13 Indust. Area Fence"* 9.54 0.39 9.77 0.43 9.7 GM14 Indust. Area Fence-* 7.82 0.32 8.38 0.34 8.1 GM15 Indust. Area Fence"* 8.00 0.40 9.08 0.36 8.5 GM16 Indust. Area Fence-* 7.88 0.39 8.12 0.41 8.0 GM17 Indust. Area Fence"* 8.07 0.36 7.94 0.36 8.0 GM18 Indust. Area Fence-* 39.59 1.58 36.54 2.59 38.1 GM19 Indust. Area Fence-* 29.38 1.50 26.94 1.37 28.2 GM20 Indust. Area Fence"* 12.68 0.51 12.66 0.50 12.7 GM21 Indust. Area Fence-* 7.93 0.66 8.01 0.43 8.0 GM22 Heartwellville, VT 7.24 0.31 7.37 0.40 7.3 GM27 No.9 Road 6.30 0.51 6.26 0.33 6.3 GM29 Route 8A 5.11 0.34 5.01 0.27 5.1 GM31 Legate Road 6.71 0.33 6.54 0.31 6.6 GM40O Readlsboro Rd 7.95 1.78 7.36 0.34 7.7

• Each "measurement" is based on readings from five TLD elements.

• • Not part of the REMP. Increased exposure rates inside the site boundary are due to fuel placement on the ISFS1 which began in the 2nd half of 2002. Fuel and GTCC placement was completed in June 2003.

SID: Standard Deviation 27

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 TABLE 3-4 2006 ISFSI TLD MEASUREMENTS*

(Micro-R per hour)

Annual 1st 6 months 2nd 6 months Average Sta.

No. Description Expos. +/-SD*** Expos. +/-SD*** Expos.

IF-1 ISFS1 Security Fence** 316.75 15.39 293.44 14.48 305.1 1IF-2 Observation Stand** 6.67 0.39 6.84 0.33 6.8 iF-3 ISFS1 Security Fence** 377.33 26.10 360.47 13.61 368.9 IF-4 ISF51 Security Fence"* 123.07 5.49 114.23 7.30 118.6 1F-5 ISF51 Security Fence- 235.68 9.91 215.48 10.71 225.6 1IF-6 ISF51 Security Fence" 318.38 20.57 283.82 11.48 301.1 1IF-7 ISFS1 Security Fence** 157.37 5.50 142.89 7.84 150.1 1IF-8 ISFS1 Security Fence** 23.75 1.44 24.96 1.08 24.4 1IF-9 Restricted Area 43.62 1.40 41.09 1.82 42.4 Fence**

IF-10 Restricted Area 20.77 0.74 18.44 0.81 19.6 Fence**

IF-1i Restricted Area 10.47 0.47 10.08 0.48 10.3 Fence-*

IF-12 Restricted Area 8.33 0.45 8.16 0.38 8.2 Fence-*

IF-18 YNPS CW Intake-* (a) 7.99 0.34 8.69 0.48 8.3 IF-19 ISF51 Security Fence 8.65 0.49 10.08 0.41 9.4 Admin. Building-*

IF-20 ISF51 Security Fence 8.14 0.37 8.71 0.36 8.4 Gatehouse**

IF-40 Readsboro Road"* 7.00 0.27 7.35 0.43 7.2

• Each "measurement" is based on readings from five TLD elements.

• • Not part of the REMP. Increased exposure rates inside the site boundary are due to fuel placement on the ISF51 which began in the 2nd half of 2002. Fuel and GTCC placement was completed in June 2003.

SID: Standard Deviation.

(a) Note: In 2004, IF-18 was relocated about 60 feet closer to the storage pad. This was necessary when the Screen Well House, upon which the TLD had been mounted, was demolished as part of site decommissioning activities.

28

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS 4.1 SAMPLING PROGRAM DEVIATIONS The ODCM allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment." Deviations noted in the REMvP during 2006, included the following:

In February on 2/8 and 2/21 the composite sampler at station WR- I11 was found with the hose not in the sampling container. Subsequently, the problem was corrected and a grab sample was taken.

4.2 COMPARISON OF ACHIEVED LLDS WITH REQUIREMENTS Table 4.3 of the ODCM (Revision 19) gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. On occasion, an LLD is not achieved due to situations such as a low sample volume caused by sampling equipment malfunction. In such a case, the ODCM requires a discussion of the situation in the Annual Radiological Environmental Operating Report. At the E-LAB, 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 better than that required by the YR ODCM.

For each analysis having an LLD requirement in ODCM Table 4.3, the a posteriori or after the fact LLD (or minimum detectable concentration - MDC) calculated for that analysis was compared with the required a priori LLD. Of the 2006 analyses performed with a specified LLD requirement, no sample failed to meet the requirements of Table 4.3 of the ODCM for mninimum level of detection.

4.3 RESULTS COMPARED AGAINST REPORTING LEVELS The ODCM (Revision 19) required written notification to the NRC within 30 days whenever a Reporting Level in ODCM Table 4.2 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 calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to site effluents (none during 2006). During 2006, no Reporting Levels were exceeded.

4.4 DATA ANALYSIS BY MEDIA TYPE The 2006 REMP data for each media type are discussed below. These are arranged in the same order as in Table 3-1 and are further categorized by pathway. Graphical plots of monitoring data are also shown in Figures 4-1 to 4-9. All values are plotted, whether they are "detectable" or "non-detectable."

4.4.1 River Water (Not required in Revision 20 of the ODCM Issued in Octobert 2006)

(See Figure 4-1)

Aliquots of river water were automatically collected every two hours from the Deerfield River downstream from the site (WR-l 11at Bear Swamp Lower Reservoir). These composited samples were collected periodically and sent to the environmental laboratory for gamma, tritium, and gross beta analyses. Monthly grab samples were also collected at the 29

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Harriman Reservoir control location and at Sherman Pond near the discharge area (WR-2 1 and -3 1, respectively).

Table 3-1 shows that gross-beta measurements were positive in five of the twenty-one samples collected from indicator locations, and two of twelve samples from the control site. This result is consistent with past measurement history in the water. No detectable levels of site-related radioactivity were found in any of the 2006 river water samples by tritium or gamma spectroscopy analyses.

The historical concentrations of gross beta activity at the indicator and control locations have not been significantly different, as shown in Figure 4-1, except during the last half of 1992, 1998-1999, and in 2002 when the levels at WR- 11were slightly elevated relative to the control, but no tritium or site related gamma emitter was detected in any sample set for these years of elevated gross beta activity; The gross beta activity was attributed to naturally-occurring radioactivity as discussed in the earlier Annual Radiological Environmental Operating Reports. For 2006, the control station gross beta results and the indicator station values are generally in close agreement, suggesting no significant difference between the control location and indicator samples in 2006.

30

Yankee Nuclear Power Station Yanke NulearPowe Radiological Environmental Operating Report 2006 StaionAnnual Figure 4-1 Gross-Beta Measurements of River Water (Semi-Annual Averages) 4 3

2 0~ 4i i- - i i i 4i i 4 4 i4 4 i 4 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 4.4.2 Ground Water (Not Required in Revision 20 of the ODCM issued in October 2006)

(See Figure 4-2)

Periodic ground water samples were collected from two on-site locations during 2006, the site potable water well (WG-

11) and Sherman Spring (WG-12). Table 3-1 shows that gross-beta measurements were positive in most of the samples, an outcome typical for ground water samples. This is due to naturally-occurring radionuclides in the water.

Tritium was detected in the samples from WG- 12 (Sherman Spring) during 2006. Concentrations are elevated above the range of values for the past 9 years during which a very low or non-detectable concentration of tritium had been observed (Figure 4-2). The detected increases are attributed to disturbance of the aquifer associated with source removal during decommissioning and increased infiltration due to removal of structures, pavement and storm water drainage systems. Peak tritium concentration remained well below ODCM reporting levels. Water from Sherman Spring flows into the Deerfield River. Neither the Deerfield River nor Sherman Spring is used for drinking water. No tritium was detected in any of the samples from the on-site potable water well (WG- 11). No gamma-emitting radionuclides were detected in any of the ground water samples from either WG- 11or WG- 12.

31

Yankee Nuclear Power Station Yanke NclerRadiological7Environmental PwerStaionAnnual Operating Report 2006 Figure 4-2 Tritium in Ground Water Station WG-12, Sherman Spring 6200 5200 4200 3200 U

2200 1200 200

-800 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 4.4.3 Sediment (Not Required in Revision 20 of the ODCM issued in October 2006)

(See Figures 4-3, 4-4, & 4-5)

Periodic semiannual sediment core samples were collected from two locations during 2006. Indicator station SE-li1 is located downstream about 24 river miles at No. 4 Dam in Charlemont, MA. Control station SE-21 is located upstream (control) at Harriman Reservoir. Each sample is segmented by depth (0-5, 5-10, 10-15 cm) and analyzed for gamma-emitting radionuclides. As would be expected, naturally-occurring K-40 and Th-232 were detected in all of the samples. In addition to those naturally-occurring radionuclides, Cs- 137 was also detected in three locations. These results are consistent with what has, been measured in previous years. Presence of Cs- 13 7 at Station SE-li1 and SE-21 is attributed to nuclear weapons testing fallout as the far downstream location and the upstream control location indicate similar levels of Cs-137. Stations SE-IlI and SE-21 are taken from the shoreline. Figure 4-3 shows the consistent range in Cs-137 levels over the last nine years in the down stream (24 mniles) sampling location.

32

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 FIGURE 4-3 CESIUM-137 IN SHORELINE SEDIMENT STATION SE-11 400.00 350.00 300.00 250.00 S200.00 S150.00

~.100.00 50.00 0.00

-50.00

-100.00 Month/Year 100-5cm N5-10cm EII-15 cm I Results for sediment samples from the upstream control location (SE-2 1) (Figure 4-4) are bounded by levels previously reported at that location for recent years. At both the indicator and the control location, the character of the sediment is highly dependent on the specific location sampled, and it also can depend on the water ley'el in Harriman Reservoir or on the Deerfield River shoreline at the time of sampling. The diverse character of the sediment at either location, and the fact that Cs-137 tends to bind more to finer-grained sediment containing organic matter than to sandy and rocky sediment, as well as the dynamic nature of their fluvial environments, leads to a wide range of Cs-137 concentrations, as shown in Figures 4-3 and 4.4.

33

Yankee Nuclear Power Station Yanke Ncler Radiological PwerStaionAnnual Enrvironmental Operating Report 2006 FIGURE 4-4 CESIUM-137 IN SHORELINE SEDIMENT STATION SE-21 1100 900 700 I- 500 300 100

-100 Zp p Month/Year

ý00-5 cm E5-10 cm El10-15 cm I 4.4.4 Fish (Not required in Revision 20 of the ODCM issued in October 2006)

(See Figure 4-6)

Periodic samples of fish were collected from two locations during 2006, FH- 11, an indicator station in Sherman Pond, and FH-2 1, a control station in Harriman Reservoir. The edible portions of each of these samples were analyzed for gamma-emitting radionuclides. As expected in aquatic animals, naturally-occurring K-40 was detected in all samples from both locations. No site-related gamma emitting radionuclides were detected in 2006 fish samples. The average 2006 Cs-137 concentrations shown in Figure 4-6 include the results of counting statistics on sample measurements, even when the analysis counts did not exceed the criteria for a "positive" (detectable) determination. The wide variation in relative Cs-137 activity illustrated in Figure 4-6 over past years is suspected to be due to the different species of fish and their specific eating habits. Fish that are bottom feeders tend to accumulate more of the Cs- 137. activity from aquatic sediment than fish that feed higher in the water column. The makeup of any individual catch (fish sample) could be dominated by a single species available at the time, and no attempt is made to differentiate sample analysis by fish species, such as those who primarily feed on the bottom versus those species that feed higher in the water colunmn.

34

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 FIGURE 4-6 CESmUM-137 IN FISH ANNUAL AVERAGE CONCENTRATIONS 60 50 40 30 20 10 0

1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Year MFH-1 1 Sherman Pond 0 FH-21 Harriman Reservoir (control) 4.4.5 Direct Radiation (Revised in October 2006 with the issuance of Revision 20 of the ODCM)

(See Figures 4-7, 4-8 & 4-9)

Direct radiation was continuously measured at 33 locations surrounding Yankee Rowe site in 2006 with the use of thermoluminescent dosimeters (TLDs). These were collected periodically during the year for readout at the E-LAB.

As shown in Figure 4-7, 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 and frozen ground cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another.

35

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 Figure 4-7 Exposure Rate at Indicator, Outer Ring and Control TLI~s 15 15 10 10 4-5 5 0 1, 1. . . .. . . . . . ' 10 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Based on the data in Table 3-2 and 3-3 and illustrated in Figure 4-7, it is evident that the mean exposure rates for the Indicator and Control categories were not significantly different in 2006. This indicates that there was no significant overall increase in direct radiation exposure rates above background in the site vicinity beyond the industrial area of the site.

As shown in Figure 4-8, the levels at offsite locations in 2006 are consistent with or bounded by levels in previous years.

36

Yankee Nuclear PM0er Station Yanke NclerRadiological Po~erStaionAnnual Environmental Operating Report 2006 Figure 4-8 Exposure Rate at Indicator TLI~s 15 10 4!

5 o 4--

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Results from the Fence line TLDs are shown in Figure 4-9 and summarized in Tables 3-2 and 3-3. These TLDs are located on the fence surrounding the inner restricted area within the Yankee Rowe site property bounds, and are influenced by the ISFSI. Specifically, the elevated exposure rates at TLD locations GM- 18, -19, and -20 since 2002 are due to fuel and GTCC transfer activities to the ISFSI, completed during 2003, and storage of spent fuel at the ISFSI and other decommissioning activities that move and temporarily disturb the earth at various locations across the site.

37

Yankee Nuclear Power Station Yanke Ncler Radiological Enviromnmental Operating Report 2006 PwerStaionAnnual Figure 4-9 Exposure Rate at Fenceline TLDs 40 --- G 13RsrceAraFne-DG 14RsrceAraFne40 35 GM- 15 Restricted Are a Fence X GM-16 Restricted Area Fence GM-17 Restricted Area Fence ---GM-16 Restricted Area Fence 30 - -GM-19 Restricted Area Fence -- GM-20 Restricted Area Fence Area Fence 25- U1-GM-21 Restricted S20 -20 10 15 0 0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 38

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS The purpose of this section is to evaluate off-site dose consequences (dose equivalent commitments) associated with detectable site related radioactivity in environmental media. The method utilizes Regulatory Guide 1.109 (Reference 2)

ODCM models and actual measurements of the concentrations of radioactivity in various environmental media (e.g., air, sediment, ground water) to compute the dose consequences resulting from the inhalation or ingestion of such material.

These evaluations can be used to provide assurance that the station's radioactive liquid and airborne effluent dose models are unlikely to underestimate actual impacts.

The standards for the maximum dose to an individual of the general public taken from 40 CFRl 90, is 25 mRem to the whole body, 75 mRem. to the thyroid, and 25 mRemn to any other organ. The dose commitment to be calculated in this section is also compared to the ALARA dose objectives of 10OCFR50 Appendix I for liquid effluents of 3 mreml1year total body and 10 mrem/yr to any organ. These standards are a fraction of the USA background radiation of 300 mRemn per year given in NCRP 94 (Reference 3).

During 2006 there were no instances of site-related radioactivity observed in environmental media which have a direct human consumption or exposure pathway associated with it. Low levels of tritium in Sherman Spring water samples were detected, but this is a non-drinking water source.

In 2006 the potential dose for the postulated ingestion of 2 liters/day of Sherman Spring water, with an average concentration of 2,711 pCi/liter tritium (observed 2006 average value of all positive measurements), would be a small fraction of the ALARA dose objectives if Sherman Spring was used as a drinking water supply.

Since the REMP for 2006 did not indicate site related radioactivity in off-site media associated directly with human ingestion, there is no indication that the site's effluent dose models are not affectively estimating the dose impact to members of the public.

39

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006

6.0 REFERENCES

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

2. Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I, Rev. 1, October, 1977.

3. Exposure of the Population in the United States and Canadafrom NaturalBackground Radiation. NCRP Report No.

94. National Council on Radiation Protection and Measurements, Bethesda, Maryland, 1994.

40

Yankee Nuclear Power Station Yanke NulearPowe Radiological StaionAnnual Environmental Operating Report 2006 APPENDIX A - LAND USE CENSUS Due to the elimination of any significant airborne term on the YR site, the ODCM was amended in 2005 which removed the requirement to conduct an annual Land Use Census. As such, no Land Use Census was performed in 2006.

A-1

APPENDIX B - QUALITY ASSURANCE PROGRAM

SUMMARY

B-1

Yankee Nuclear Power Station QUALITY ASSURANCE PROGRAM The quality assurance program at the AREVA NP Environmental Laboratory (B-LAB) 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 programi, provides a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements.

The B-LAB 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 intemnal audits, audits by extemnal 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 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 the B-LAB on or before December 3 1, 2006.

Intralaboratory Quality Control Program The B-LAB 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. Additionally, numerous samples of various matrices are periodically re-analyzed as part of the internal duplicate analysis program. Table B. 1 provides the summary of the process check and duplicate results for January to December 2006. Of the 351 analyses evaluated for bias, 99. 1%passed the acceptance criteria and 99. 1% of the 222 results evaluated for precision were acceptable. The B-LAB intemnal acceptance criteria are summarized at the end of Table B.l1.

Third Party Cross Check Program The B-LAB participates in a third party cross check program managed by Analytics Inc. to satisfy the requirement of the Environmental Technical Specification/ODCM. The B-LAB 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 PB Program in terms of the number of samples, matrices and nuclides. The results for the 4h quarter 2005 through the 3 rd quarter 2006 are summarized in Table B.2. The 4h"quarter 2006 sample results are not included in this report as the final results have not been received from the reporting laboratory. This data will be provided in the Quality Assurance Program summary for the subsequent year. Each sample is normally analyzed in triplicate and the results are evaluated against the internal acceptance criteria described in the B-LAB 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 B-LAB intemnal acceptance criteria are summarized at the end of Table B.l1.

B-2

Yankee Nuclear Power Station Blind Duplicate Program Under the Blind Duplicate Quality Assurance Program, samples are split from homogeneous environmental media by the client and sent to the E-LAB 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 23 paired samples in 2006. The measurements evaluated include twenty-six gamma emitting radionuclides, H-3, 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 B.3. For the 2006 program, 99.0% (479/484) of the measurements met the E-LAB internal acceptance criteria.

Environmental TLD Quality Assurance Program Performnance documentation of the routine processing of the Panasonic enviromnmental TLDs (thermoluminescent dosimeter) program at the B-LAB is provided by the dosimetry quality assurance testing program. This program includes independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, sets of six dosimeters are irradiated to ANSI specified testing criteria and submitted for processing as "unknowns." The bias and precision of TLD processing is measured against this standard and is used to indicate trends and changes in performnance. Instrumentation checks, although routinely performed and representing between 5-10% of the TLDs processed, are not presented in this report because they do not represent a true process check sample since the exposures are known to the processor.

Ninety performance tests were conducted in 2006 by the B-LAB and the third party tester. These tests were made on fifteen separate sets of six dosimeters. All of the fifteen TLD test sets passed the mean bias criteria of +/-20.1%. Of the ninety individual measurements, 100% of the dosimeter evaluations met the B-LAB Internal Acceptance Criteria for bias (+/-20.1%) and precision (+/-12.8%). Third Party QC results are summarized below.

Percentage of Individual Analyses that passed E-LAB Internal Criteria Dosimeter Type Number  % Passed Bias Criteria  % Passed Precision Tested Criteria Panasonic Environmental 90 100 100 Summary of Third Party Testing Dosimeter Type Exposure Period ANSI Category  % (Bias +/- SD)

Panasonic Environmental SH112006 11, high energy 7.5 +/- 2.4 ItSH/2006 II, high energy 4.0 +/- 1.0

• American National Standards Institute (ANSI) Performance Statistic as referenced in the Dosimetry Services Semii-Annual QA Status Report.

Note: Results are expressed as the delivered exposure for environmental TLD. ANSI HPS N 13.29-1995 (Draft) Category 11, High energy photons (Cs-137 or Co-60).

B-3

Yankee Nuclear Power Station Conclusion Based on review of the results of the AREVA NP Environmental Laboratory quality assurance program, the quality of the data generated has been verified.

B-4

Yankee Nuclear Power Station TABLE B.1 E-LAB RESULTS IN THE INTRALABORATORY PROCESS CONTROL PROGRAM January - December 2006 Media Bias:Critei(4PeiinCira(2 Anlysis, 1 2 3 4 1 2 34

1. Air Charcoal Gamma-Quantitative 34 11 5 2 0 0 0 0 Gamma-Screening 6 11 1 0 0 0 0 0

11. Air Filter Beta 231 17 0 0 0 0 0 0 111. Milk Gamma 0 0 0 0 14 2 24 0 I-131(LL) 3 0 0 0 3 0 0 0 IV. Soil/Sediment Gamma 0 0 0 0 16 6 16 0 V. Vegetation/Food Gamma 0 0 0 0 16 16 46 2 VI. Water Gross Alpha 0 4 4 1 0 0 2 0 GrossBeta 14 0 1 0 2 4 2 0 Gamma 0 0 0 0 4 2 26 0 I-131(LL) 1 1 1 0 1 2 0 0 Sr-90 0 1 2 0 0 2 0 0 Tritium 0 0 0 0 6 0 8 0 Total Number in Range 289 45 14 3 62 34 124 2 Pe rcentage of Total 82.3 12.8 4.0 0.9 27.9 15.3 55.9 0.9 Processed Sum of Analyses 351 222 (1) Percent Bias Criteria by Bias Category (2) Percent Precision Criteria by Precision Category Bias Category 1 > 0% and < = 5% Precision Category 1 > 0% and < = 5%

Bias Category =2 >5% and <= 10% Precision Category =2 > 5% and < = 10%

Bias Category =3 > 10%and <= 15%, or Precision Category = 3 > 10% and < = 15 %, or within 2 sigma of known within 2 sigma of mean Gross alpha/beta water, Sr 89/90 > 10% and <= 25% Precision Category = 4 Outside Criteria Transuranics > 10% and <= 20%

Bias Category =4 Outside Criteria B-5

Yankee Nuclear Power Station TABLE B.2 E-LAB RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2005 - Quarter 3, 2006 t155)oz 1 4U1/zUO0 vvater M-51j( IJzU1 .U4 Agreement E4837-162 4th/2005 Water Sr-89 80.3 91.4 0.88 Agreement E4837-162 4tti/2005 Water Sr-9O 7.18 7.4 0.97 Agreement E4838-162 4th/2005 Filter Gross Alpha 22.3 25.0 0.89 Agreement E4838-162 4th/2005 Filter Gross Beta 146 136 1.07 Agreement E4839-162 4th/2005 Filter Ce-141 122 131 0.93 Agreement E4839-162 4th/2005 Filter Cr-5I 113 113 1.00 Agreement E4839-162 4th/2005 Filter Cs-134 48.0 51.0 0.94 Agreement E4839-162 4th/2005 Filter Cs-137 ill ill 1.00 Agreement E4839-162 4th/2005 Filter Co-58 44.2 45.2 0.98 Agreement E4839-162 4th/2005 Filter Mn-54 93.5 88.9 1.05 Agreement E4839-162 4th/2005 Filter Fe-59 44.6 48.1 0.93 Agreement E4839-162 4th/2005 Filter Zn-65 95.8 89.9 1.07 Agreement E4839-162 4th/2005 Filter 0o-60 59.1 64.6 0.91 Agreement E4840-162 4th/2005 Filter Sr-89 103 121 0.85 Agreement E4840-162 4th/2005 I Filter Sr-SO 9.05 9.70 0.93 Agreement E4841-162 4th/2005 Milk 1-131LL 72.4 74.6 0.97 Agreement E4841-162 4th/2005 Milk 1-131 74.1 74.6 0.99 Agreement E4841-162 4th/2005 Milk Ce- 141 217 224 0.97 Agreement E4841-162 4th/2005 Milk Cr-51 190 193 0.98 Agreement E4841-162 4th/2005 Milk Cs-134 86.4 87.3 0.99 Agreement E4841-162 4th/2005 Milk Cs-137 187 189 0.99 Agreement E4841-162 4th/2005 Milk Co-58 78.7 77.5 1.02 Agreement E4841-162 4th/2005 Milk Mn-54 153 152 1.01 Agreement E4841-162 4th/2005 Milk Fe-59 87.8 82.4 1.07 Agreement E4841-162 4th/2005 Milk Zn-65 148 154 0.96 Agreement IE4841-162 I 4th/2005 I Milk Co-60 106 ill 0.95 1 Agreement E4879-162 I 4th/2005 ICharcoal 1-131 68.4 72.0 0.95 Agreement

• pCi/Liter (Filters in pCi)

B-6

Yankee Nuclear Power Station TABLE B.2 (cont'd)

E-LAB RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2005 - Quarter 3, 2006 E4884-1 62 1st/2006 Water Gross Alpha 38.7 38.1 1.02 Agreement E4884-162 1st/2006 Water Gross Beta 265 262 1.01 Aareement E4884-162 Ist/2006 Water I11L6. 7409 gemn E4885-162 1lst/2006 Water 1-131L 66.3 67.4 0.98 Agreement E4885-162 1st12006 Water Ce-141 83.0 86.8 0.96 Agreement E4885-162 Ist/2006 Water Cr-5i 217 234 0.93 Agreement E4885-162 I st12006 Water Cs-134 91.9 101 0.91 Agreement E4885-162 1st12006 Water Cs-i 37 73.3 74.3 0.99 Agreement E4885-162 1lst/2006 Water Co-58 84.7 87.5 0.97 Agreement E4885-162 1st/2006 Water Mn-54 74.7 78.1 0.96 Agreement E4885-162 1st/2006 Water Fe-59 73.2 72.4 1.01 Agreement E4885-162 1st/2006 Water Zn-65 146.7 148 0.99 Agreement E4885-162 I st12006 Water Co-60 102.5 107 0.96 Agreement E4886-162 I1st12006 Water Sr-89 82.0 99.4 0.82 Agreement E4886-162 Ist/2006 Water Sr-90 10.2 10.8 0.94 Agreement E4887-162 1st/2006 Charcoal 1-131 84.3 84.8 0.99 Agreement E4888-162 1st12006 Filter Gross Alpha 13.5 14.2 0.95 Agreement E4888-162 1st/2006 Filter Gross Beta 104.5 97.3 1.07 Agreement E4889-162 Ist/2006 Milk 1-131LL 81.8 78.0 1.05 Agreement E4889-162 1st/2006 Milk 1-131 77.4 78.8 0.98 Agreement E4889-162 1st/2006 Milk Ce-141 101 104 0.97 Agreement E4889-162 Ist/2006 Milk Cr-51 277 280 0.99 Agreement E4889-162 1st/2006 Milk Cs-134 113.8 121 0.94 Agreement E4889-162 1st12006 Milk Cs-137 86.7 88.8 0.98 Agreement E4889-162 I1st/2006 Milk Co-58 100 105 0.95 Agreement E4889-162 1lst/2006 Milk Mn-54 94.6 93.3 1.01 Agreement E4889-162 1st/2006 Milk Fe-59 90.7 86.6 1.05 Agreement E4889-162 1st12006 Milk Zn-65 172.2 176 0.98 Agreement E48916 st20 Ml 0-6120 128 1 0.98 1 Agreement E4890-162 lst/2006 Milk Sr-89 79.7 99.2 0.80 Agreement E4890-162 1st12006 Milk Sr-90 10.6 10.8 0.98 Agreement

• pCi/Liter (Filters in pCi)

B-7

Yankee Nuclear Power Station TABLE B.2 (cont'd)

E-LAB RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2005 - Quarter 3, 2006 E5014J-162 2nd/2006 Fwlter Gross Alpha 31.8 366.87 Agreemnent E5014-162 2nd12006 Filter Gross Betha 310.8 96.8 1.07 Agreement E5015-162 2nd/2006 Filter Ce-141 91.6 92.8 0.99 Agreement E5015-162 2nd12006 Filter Cr-5I 131.7 131 1.01 Agreement E5015-162 2nd/2006 Filter Cs-134 60.5 63.9 0.95 Agreement E5015-162 2nd12006 Filter Cs-137 62.9 59.3 1.06 Agreement E5015-162 2nd12006 Filter Co-58 52.0 50.6 1.03 Agreement E5015-162 2nd/2006 Filter Mn-54 74.5 73.9 1.01 Agreement E5015-162 2nd/2006 Filter Fe-59 46.4 47.3 0.98 Agreement E5015-162 2nd/2006 Filter Zn-65 93.4 93.6 1.00 Agreement E5015-162 2nd12006 Filter Co-60 63.0 65.0 0.97 Agreement E5016-162 2nd/2006 Filter Sr-89 146.6 163 0.90 Agreement E5016-162 2nd/2006 Filter Sr-90 7.01 12.3 0.57 Non-Agreement E5017-162 2nd/2006 Milk 1-13ILL 67.0 63.2 1.06 Agreement E5017-162 2nd/2006 Milk 1-131 62.0 63.2 0.98 Agreement E5017-162 2nd/2006 Milk Ce-141 180.8 184 0.98 Agreement E5017-162 2nd/2006 Milk Cr-51 248.0 259 0.96 Agreement E5017-162 2nd/2006 Milk Cs-134 120.1 127 0.95 Agreement E5017-162 2nd/2006 Milk Cs-137 117.3 117 1.00 Agreement E5017-162 2nd/2006 Milk Co-58 97.3 100 0.97 Agreement E5017-162 2nd/2006 Milk Mn-54 150.5 146 1.03 Agreement E5017-162 2nd/2006 Milk Fe-59 95.4 93.6 1.02 Agreement E5017-162 2nd/2006 Milk Zn-65 183.9 185 0.99 Agreement E5017-162 I 2nd/2006 I Milk I 0C-60 1 126.2 1 129 1 0.98 1 Agreement

• pCi/Liter (Filters in pCi)

• • Sr-90 on AP sample was re-analyzed with acceptable results. Analytical blank and background frequencies are being evaluated.

B-8

Yankee Nuclear Power Station TABLE B.2 (cont'd)

E-LAB RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2005 - Quarter 3, 2006 E:5090-162 3rd I200ti Water U.ross Alpha 71.5 69.4 1.03 Agreement E5090-1 62 3rd /2006 Water Gross Beta 253 273 0.93 Agreement E5091-162 3rd /2006 Water 1-131LL 84.4 79.9 1.06 Agreement E5091-162 3rd /2006 Water 1-131 77.3 79.9 0.97 Agreement E5091-162 3rd /2006 Water Ce- 141 84.5 88.0 0.96 Agreement E5091-162 3rd /2006 Water Cr-5i 287 288 1.00 Agreement E5091-162 3rd /2006 Water Cs-I 34 85.6 87.0 0.98 Agreement E5091-162 3rd /2006 Water Cs-I 37 174 179 0.97 Agreement E5091-162 3rd /2006 Water Co-58 108 112 0.96 Agreement E5091-162 3rd /2006 Water Mn-54 116 115 1.01 Agreement E5091-162 3rd /2006 Water Fe-59 47.0 44.7 1.05 Agreement E5091-162 3rd /2006 Water Zn-65 146 148 0.99 Agreement E5091-162 3rd /2006 1 Water Co-60 130 137 0.95 Agreement E5092-162 3rd /2006 Charcoal 1-131 88.3 91.1 0.97 Agreement E5093-162 3rd /2006 Filter Gross Alpha 36.9 37.3 0.99 Agreement E5093-162 3rd /2006 Filter Gross Beta 142 147 0.97 Agreement E5094-162 3rd /2006 Milk 1-131 LL 79.9 73.8 1.08 Agreement E5094-162 3rd /2006 Milk 1-131 72.5 73.8 0.98 Agreement E5094-162 3rd /2006 Milk Ce-141 85.5 86.0 0.99 Agreement E5094-162 3rd /2006 Milk Cr-5i 288 282 1.02 Agreement E5094-162 3rd /2006 Milk Cs-134 84.8 85.0 1.00 Agreement E5094-162 3rd /2006 Milk Cs-137 171 175 0.98 Agreement E5094-162 3rd /2006 Milk Co-58 106 109 0.97 Agreement E5094-162 3rd /2006 Milk Mn-54 112 113 0.99 Agreement E5094-162 3rd /2006 Milk Fe-59 45.3 43.7 1.04 Agreement E5094-162 3rd /2006 Milk Zn-65 146 145 1.01 Agreement E5094-162 I 3rd /2006 1 Milk Co-60 1 129 1 134 1 0.96 1 Agreement

• pCilLiter (Filters in pCi)

B-9

Yankee Nuclear Power Station TABLE B.3

SUMMARY

OF BLIND DUPLICATE SAMPLES January - December 2006 TYPE OF SAMPLE NUMBER OF PAIRED 7ý-j SAMPLES SUBMITTED Water 17 Algae3 Mussels3 TOTAL 23 B- 10

Yankee Nuclear Power Station APPENDIX C -

SUMMARY

OF 2006 REMP DATA C-1

Yankee Nuclear Power Station Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (pCi/m3) (pCi/m3) (pCi/m3)

AP 11 L10398-01 1/11/2006 AcTh-228 3. 1OE-03 4.40E-03 1.60E-02 AP 11 L10398-01 1/11/2006 Be-7 7.70E-02 1.30E-02 2.80E-02 AP 11 L10398-01 1/11/2006 Co-58 2.1OE-03 9.40E-04 2.50E-03 AP 11 L10398-01 1/11/2006 Co-60 -9.OOE-04 1.OOE-03 4.90E-03 AP 11 LI10398-01 1/11/2006 Cs-134 4.50E-04 8.40E-04 3 .30E-03 AP 11 L10398-01 1/11/2006 Cs-137 -3.70E-04 6.OOE-04 2.90E-03 AP 11 L10398-01 1/11/2006 GROSS BETA 1.81 E-02 1.1OE-03 1 .9ME-03 AP 11 L10398-01 1/11/2006 K-40 6.OOE-03 1.20E-02 4.90E-02 AP 11 L10450-01 1/25/2006 AcTh-228 1.60E-03 2.90E-03 1.1OE-02 AP 11 L10450-01 1/25/2006 Be-7 7.90E-02 1.40E-02 3.20E-02 NP 11 Li10450-01 1/25/2006 Co-58 -1.60E-04 8.30E-04 3.70E-03 NP 11 L10450-01 1/25/2006 Co-60 1.62E-03 9.90E-04 3.OOE-03 NP 11 L10450-01 1/25/2006 Cs-134 4.OOE-04 1.20E-03 4.60E-03 NP 11 L10450-01 1/25/2006 Cs-137 -1 .57E-03 8.30E-04 4. 1OE-03 AP 11 Li10450-01 1/25/2006 GROSS BETA I1.76E-02 9.90E-04 1.70E-03 AP 11 L10450-01 1/25/2006 K-40 7.OOE-03 1 .20E-02 4.70E-02 NP 11 L1051i1-01 2/8/2006 AcTh-228 -1 .30E-03 2.90E-03 1.30E-02 AP 11 L1051i1-01 2/8/2006 Be-7 3.70E-02 1.1OE-02 2.80E-02 NP 11 L1051 1-01 2/8/2006 Co-58 6.70E-04 8.50E-04 3 .20E-03 NP 11 LIO0511-01 2/8/2006 Co-60 0.OOE+00 8.50E-04 3.70E-03 NP 11 biO051 -01 2/8/2006 Cs-134 -1 .50E-03 1.1IOE-03 4.80E-03 NP 11 L1051l1-01 2/8/2006 Cs-137 -4.50E-04 7.OOE-04 3. 1OE-03 NP 11 L1051 1-01 2/8/2006 GROSS BETA 1.56E-02 9.80E-04 1 .90E-03 NP 11 L1051 1-01 2/8/2006 K-40 4.OOE-03 1.1OE-02 4.60E-02 NP 11 L10546-01 2/21/2006 AcTh-228 4.60E-03 4.OOE-03 1.40E-02 NP 11 1,10546-01 2/21/2006 Be-7 9.50E-02 1.80E-02 4.60E-02 NP 11 LI10546-01 2/21/2006 Co-58 -1.80E-04 5.90E-04 2.90E-03 NP 11 L10546-01 2/21/2006 Co-60 5 .90E-04 8.60E-04 3.30E-03 NP 11 L10546-01 2/21/2006 Cs-134 -3. 1OE-04 8.80E-04 3.80E-03 NP 11 L10546-01 2/21/2006 Cs-137 -6.70E-04 7. 80E-04 3.50E-03 NP 11 L10546-01 2/21/2006 GROSS BETA 2. 16E-02 1.20E-03 2.20E-03 AP 11 L10546-01 2/21/2006 K-40 I .OOE-03 I1.30E-02 5.20E-02 NP 11 L10596-01 3/8/2006 AcTh-228 -7.0013-04 2.50E-03 1.I1OE-02 NP 11 L10596-01 3/8/2006 Be-7 9.50E-02 I1.40E-02 2.90E-02 NP 11 L10596-01 3/8/2006 Co-58 1.50E-04 6.90E-04 2.80E-03 NP 11 L10596-01 3/8/2006 Co-60 1.40E-03 1.OOE-03 3 .40E-03 NP 11 L10596-01 3/8/2006 Cs-134 -1.33 E-03 8.30E-04 4.OOE-03 NP 11 L1 0596-0 1 3/8/2006 Cs-137 0.OOE+00 7.60E-04 3.OOE-03

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (pCi/m.3) (pCi/m3) (pCi/m3)

• AP L10596-01 3/8/2006 GROSS BETA 1.89E-02 9.90E-04 1 .70E-03 AP L10596-01 3/8/2006 K-40 -1.OOE-04 9.50E-03 4.OOE-02 AP Li10645-01 3/22/2006 AcTh-228 -1 .O13-03 2.90E-03 1 .30E-02

• AP L10645-01 3/22/2006 Be-7 5.50E-02 1.20E-02 2.80E-02 AP L10645 -01 3/22/2006 Co-58 -4.0013-04 6.60E-04 3.20E-03 AP L10645-01 3/22/2006 Co-60 -1.0513-03 7.80E-04 4.20E-03 AP LI10645-01 3/22/2006 Cs-134 6.OOE-04 1.10E-03 3.90E-03 AP Li10645-01 3/22/2006 Cs-137 0.OOE+00 7. 1lOE-04 2.90E-03

• AP L10645-01 3/22/2006 GROSS BETA 1.68E-02 1.0OE-03 1.80E-03 AP L10645-01 3/22/2006 K-40 -1.4013-02 I1.2013-02 5.70E-02 AP L10742-01 3/22/2006 AcTh-228 7.20E-04 7.70E-04 2.80E-03 AP L10742-01 3/22/2006 Ag-i l0i -6.30E-04 4.OOE-04 1.90E-03 AP L10742-01 3/22/2006 Ba-i40 -2.10OE-03 4.20E-03 2.30E-02

• AP Li10742-01 3/22/2006 Be-7 8.3913-02 9.80E-03 1.70E-02 AP L10742-01 3/22/2006 Ce-i41 -3 .OOE-05 5.6013-04 2.2013-03 AP L10742-01 3/22/2006 Ce-144 -5.OOE-05 6.80E-04 2.6013-03 NP L10742-01 3/22/2006 Co-57 0.OOE+00 9.OOE-05 3.40E-04 AP L10742-01 3/22/2006 Co-58 -4.OOE-05 2.90E-04 1.30E-03 AP L10742-01 3/22/2006 Co-60 3.10OE-04 1.80E-04 2.80E-04 AP L10742-01 3/22/2006 Cs-i34 -2.50E-04 2.30E-04 1.l1OE-03 NP L10742-01 3/22/2006 Cs-137 -1 .30E-04 1.60E-04 7.90E-04 AP Li10742-01 3/22/2006 Fe-59 1.3713-03 7.9013-04 I1.20E-03 AP Li10742-01 3/22/2006 1-i131 -1 .05E-02 9.60E-03 4.50E-02 AP L10742-01 3/22/2006 K-40 -8.OOE-03 3.20E-03 1.813-02 AP L10742-01 3/22/2006 La-140 -2.40E-03 4.80E-03 2.60E-02 AP L10742-01 3/22/2006 Mn-54 -l.1013-04 i1.60E-04 8.30E-04 AP L 10742-01 3/22/2006 Nb-95 -6.70E-04 6.30E-04 3. 1OE-03 AP L10742-01 3/22/2006 Ru-103 2.90E-04 3.60E-04 1.40E-03 NP Li10742-01 3/22/2006 Ru-i06 0.OOE+00 1.90E-03 8.OOE-03 NP L10742-01 3/22/2006 Sb-124 1.28E-03 9.OOE-04 1.70E-03 AP L10742-01 3/22/2006 Zn-65 -2.30E-04 3.90E-04 2. 1iOE-03 AP L10742-01 3/22/2006 Zr-95 4.OOE-04 6.20E-04 2.40E-03

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONG STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (pCi/m3) (p~i/m3) (pCi/m3)

AP-DAP Li103 98-02 1/11/2006 AcTh-228 2.60E-03 4. 10E-03 1.50E-02 AP-DAP L10398-02 1/11/2006 Be-7 2.3013-02 1.1OE-02 3.30E-02 AP-DAP L10398-02 1/11/2006 Co-58 -3.20E-04 8.5013-04 3.80E-03 AP-DAP L10398-02 1/11i/2006 Co-60 1.OOE-04 1.40E-03 5.60E-03 AP-DAP Li10398-02 1/11/2006 Cs-134 1.4913-03 8.70E-04 2.60E-03 AP-DAP L10398-02 1/11/2006 Cs-i37 -3.0013-05 9.30E-04 3.80E-03 AP-DAP L10398-02 1/11/2006 K-40 2.1013-02 1.80E-02 6. 1OE-02 AP-DAP Li1045 0-02 1/24/2006 AcTh-228 2.10OE-03 3.90E-03 1.5013-02 AP-DAP L1 045 0-02 1/24/2006 Be-7 3.40E-02 1.40E-02 4.20E-02 AP-DAP L10450-02 1/24/2006 Co-58 2.OOE-04 1.20E-03 4.90E-03 AP-DAP LI1045 0-02 1/24/2006 Co-60 -1 .08E-03 7.70E-04 5.OOE-03 AP-DAP Li1045 0-02 1/24/2006 Cs-134 -2.OOE-04 1.1OE-03 5.OOE-03 AP-DAP Li1045 0-02 1/24/2006 Cs-137 -2.1013-03 9.90E-04 5.30E-03 AP-DAP L10450-02 1/24/2006 K-40 -9.OOE-03 1.20E-02 6.30E-02 AP-DAP L10511-02 2/7/2006 AcThi-228 1 OOE-03 3.30E-03 1.40E-02 AP-DAP L10511-02 2/7/2006 Be-7 2.70E-02 1.O0-02 2.90E-02 AP-DAP L10511-02 2/7/2006 Co-58 -2.70E-04 5.60E-04 3. 1OE-03 AP-DAP L10511-02 2/7/2006 Co-60 -6.OOE-04 1.1OE-03 5.20E-03 AP-DAP L1051 1-02 2/7/2006 Cs-134 -6.OOE-04 1.20E-03 5. 1OE-03 AP-DAP L1051 1-02 2/7/2006 Cs-137 3 .OOE-04 1.l1OE-03 4.20E-03 AP-DAP L10511-02 2/7/2006 K-40 -8.OOB-03 1.LOE-02 5.50E-02 AP-DAP Li105 46-02 2/21/2006 AcTh-228 1.OOE-03 3.70E-03 1.5013-02 AP-DAP Li105 46-02 2/21/2006 Be-7 6.70E-02 1.70E-02 4.60E-02 AP-DAP L10546-02 2/21/2006 Co-58 2.OOE-04 1.1OE-03 4.50E-03 AP-DAP L10546-02 2/21/2006 Co-60 3.OOE-04 1.20E-03 5.1OE-03 AP-DAP L1 05 46-02 2/21/2006 Cs-134 3.OOE-04 1.OOE-03 4.1 OE-03 AP-DAP L10546-02 2/21/2006 Cs-137 - 1.14E-03 9.50E-04 4.40E-03 AP-DAP L10546-02 2/21/2006 K-40 2.30E-02 1.50E-02 4.70E-02 AP-DAP L10596-02 3/7/2006 AcTh-228 -1 .70E-03 1.60E-03 1.OOE-02 AP-DAP Li105 96-02 3/7/2006 Be-7 4.50E-02 1.1OE-02 2.70E-02 AP-DAP L10596-02 3/7/2006 Co-58 -2.OOE-04 1.OOE-03 4.30E-03 AP-DAP Li105 96-02 3/7/2006 Co-60 2.10OE-03 1.20E-03 3.90E-03 AP-DAP Li10596-02 3/7/2006 Cs-134 8.70E-04 9.10O-04 3.30E-03 AP-DAP Li105 96-02 3 /7/2006 Cs-137 1.07E-03 8.40E-04 2.9013-03 AP-DAP L10596-02 3/7/2006 K-40 2.OOE-03 1.4013-02 5.90E-02 AP-DAP LI10645-02 3/21/2006 AcTh-228 -7.90E-03 3.80E-03 1 .90E-02 AP-DAP L10645-02 3/21/2006 Be-7 iLlE-Ol 1.80E-02 3.80E-02 AP-DAP Li10645-02 3/21/2006 Co-58 3.OOE-04 1.1OE-03 4.50E-03

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (p~i/m3) (pCi/m3) (pCi/m3)

AP-DAP 2 L10645-02 3/21/2006 Co-60 2.l1OE-03 1.20E-03 3.40E-03 AP-DAP 2 L10645-02 3/21/2006 Cs-134 -9.70E-04 9.60E-04 4.6013-03 AP-DAP 2 L10645-02 3/21/2006 Cs-137 -4.OOE-03 1.30E-03 6.30E-03 AP-DAP 2 L10645-02 3/21/2006 K-40 -4.OOE-03 1.70E-02 7.20E-02

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

FH L10993-01 6/5/2006 Ag-I11Cm -2.80E+01 2.20E+01 I .OOE+/-02 FH L10993-01 6/5/2006 Ba-140 -3.40E+01 3.40E+01 1.80E+02 FH LI10993-01 6/5/2006 Be-7 2.40E+02 1.50E+02 4.90E+02 PH L10993-01 6/5/2006 Ce- 141 -2.60E+0 1 2.30E+01 9.40E+01 PH L10993-01 6/5/2006 Ce-144 -1 .20E+01 8.20E+01 3 .OOE+02 PH L10993-01 6/5/2006 Co-57 4.30E+00 8.2013+00 3.OOE+0I PH L10993-01 6/5/2006 Co-58 3.OOE+00 1.40E+01 5.90E+01 PH Li10993-01 6/5/2006 Co-60 -1.OOE+01 1.90E+01 8.50E+01 PH L10993-01 6/5/2006 Cs-134 1.30E+00 9.801E+00 4.50E+0 1 FH L10993-01 6/5/2006 Cs-137 5.50E+01 2. 1OE+O I 5.90E+O I PH L10993-01 615/2006 Fe-59 1.30E+01 4.70E+01 1.80E+02 21 PH L10993-01 6/5/2006 1-131 -6.90E+01 5.90E+01 2.50E+02 21 PH L10993-01 6/5/2006 K-40 3.29E+03 5.50E+02 1.1OE+03 21 PH L10593-01 6/5/2006 La-140 -3.90E+01 3.9013+01 2. 1iOE+02 21 PH L10993-01 6/5/2006 Mn-54 0.OO13+/-00 2.OOE+0 I 7.90E+01 211 PH L10993-01 6/5/2006 Nb-95 2.50E+01 2.OOE+Oi 6.60E+01 21 PH L10993-01 6/5/2006 Ru-103 9.0013+00 1.30E+01 4.801E+01 21 PH LI10993-01 6/5/2006 Ru-106 -2.OOE+02 1.50E+02 6.60E+02 21 FH L10993-01 6/5/2006 Sb- 124 0.OOE+00 2.80E3+01 1.50E+02 21 PH L10993-01 6/5/2006 Zn-65 -2.40E+0 1 2.90E+01 I1.40E+02 21 PH L10993-01 6/5/2006 Zr-95 -2.OOE+01 2.50E+01 I1.20E+02 21 PH LI10993-02 6/5/2006 Ag-ib0m 5.OOE+00 1.80E+01 7.10E+01 21 FH L10993-02 6/5/2006 Ba-140 4.10E+01 3.60E3+0 1 1.30E+02 211 FH Li10993-02 6/5/2006 Be-7 3.OOE+01 1.3013+02 4.70E+02 211 PH LI 0993-02 6/5/2006 Ce- 141 2.80E+01 1.90E+01 6.4013+0 1 21 PH Li10993-02 6/5/2006 Ce-144 -1.05E+02 6.001E+01 2.50E+02 211 PH Li10993 -02 6/5/2006 Co-57 9.70E+00 8.80E+00 3.OOE+Oi PH Li10993-02 6/5/2006 Co-58 7.OOE+00 1.30E+01 5. 1OE+O I FH L10993-02 6/5/2006 Co-60 6.OOE+00 1.2013+01 4.60E+01 PH 21 L10993-02 6/5/2006 Cs-134 -3.10OE+01 1.1OE+01 6.10E+01 PH Li10993 -02 6/5/2006 Cs-137 4.5013+01 2.1OE+01I 6.50E+01 PH LI10993-02 6/5/2006 Fe-59 -7.OOE+00 3.20E+01I 1.30E+02 FH Li10993-02 6/5/2006 1-131 2.40E+01I 5.OOE+01 I1.80E+02 PH Li10993-02 6/5/2006 K-40 1.82E+03 3.30E+02 6.90E+02 PH Li10993-02 6/5/2006 L~a-140 4.70E+01 4.1OE+O I I1.40E+02 FH Li10993-02 6/512006 Mn-54 -3.20E+00 8.60E+00 3.90E+01 PH L10993-02 6/5/2006 Nb-95 -3.20E+01 1.50E+01 7.20E+01 PH Li10993 -02 6/5/2006 Ru-103 -1 .90E+01 1.40E+01 6.OOE+01

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-6

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIIDE (pCi/kg) (pCilkg) (pCi/kg)

FH 21 L10993-02 6/5/2006 Ru-106 3.OOE+01 1.20E+02 4.4013+02 FH 21 L10993-02 6/5/2006 Sb-124 3.90E+01 2.30E+0 1 3.50E+01 FH 21 L10993-02 6/5/2006 Zn-65 -1.60E+01 3.3013+01 1.40E+02 FH 21 L10993-02 6/5/2006 Zr-95 4.40E+0 I 2.70E+01 8.80E+01

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END~ CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCilkg) (pCi/kg)

SEl Li10992-01 5/2/2006 AcTh-228 1.16E+03 1.30E+02 4.50E+02 SEl L10992-01 5/2/2006 Be-7 -5.90E+02 5.1OE+02 2.OOE+03 SE 1 L10992-01 5/2/2006 Co-58 -3.70E+01 4.70E+01 I1.90E+02 SE 1 L10992-01 5/2/2006 Co-60 1.OOE+00 2.70E+01 1.1OE+02 SEl L10992-01 5/2/2006 Cs-134 1.1OE+0lI 2.40E+01 8.50E+01 SEI L10992-01 5/2/2006 Cs-137 1.11 E+02 4.30E+01 I1.30E+02 SEI L10992-01 5/2/2006 K-40 2.13E+04 1.20E+03 1 .20E+03 SE2 Li10992-02 5/2/2006 Aclh-228 9.OOE+02 1.30E+02 4.40E+02 SE2 L10992-02 5/2/2006 Be-7 -7.OOE+01 4.80E+02 1.80E+03 SE2 L10992-02 5/2/2006 Co-58 -1.60E+01 4.40E+0 1 1.70E+02 SE2 L10992-02 5/2/2006 Co-60 3.40E+01 2.70E+0 1 9.OOE+01 211 SE2 Li10992-02 5/2/2006 Cs-134 -7.OOE+00 2.40E+01 9.30E+01 21 SE2 Li10992-02 5/2/2006 Cs-137 1.32E+02 4.OOE+01 1.20E+02 21 SE2 L10992-02 5/2/2006 K-40 2.09E+04 1.20E+03 7.60E+02 211 SE3 L10992-03 5/2/2006 AcTh-228 8.60E+02 1.1OE+02 3.30E+02 21 SE3 Li10992-03 5/2/2006 Be-7 2.1OE+02 4.60E+02 1.60E+03 21 SE3 Li10992-03 5/2/2006 Co-58 4.20E+01 4.70E+0 1 1.60E+02 21 SE3 L10992-03 5/2/2006 Co-60 4.20E+'0 1 2.50E+01 7.90E+01 21 SE3 L10992-03 5/2/2006 Cs-134 3.OOE+01 3.20E+01 1.OOE+02 21 SE3 Li10992-03 5/2/2006 Cs-137 1.70E+02 4.OOE+01 1.1OE+02 21 SE3 L10992-03 5/2/2006 K-40 1.66E+04 1 .OOE+/-03 7.50E+02 21 SE 1 Li 1458-01 9/21/2006 AcTh-228 8.33E+02 6.60E+01 1.90E+02 21 SEI LI 1458-01 9/21/2006 Be-7 -1.OOE+01 1.70E+02 6.OOE+02 211 SE 1 Li 1458-01 9/21/2006 Co-58 2.30E+01 1.60E+01 5.40E+01 21 SEl Li 1458-0 1 9/21/2006 Co-60 9.OOE+00 1.80E+01 6.20E+0 1 211 SEl Li 1458-01 9/21/2006 Cs-137 3.38E-i02 3.10E+01 7.20E+01 21 SE 1 Li 1458-01 9/21/2006 K-40 1.80E+04 6.80E+02 5.70E+02 SE2 Li 1458-02 9/21/2006 AcTh-228 9.49E+02 5.80E+01 2.OOE+02 SE2 L 11458-02 9/21/2006 Be-7 -2.80E+02 1.50E+02 5.50E+02 SE2 Li 1458-02 9/21/2006 Co-58 -9.OOE+00 1.60E+01 5.90E+01 SE2 L 11458-02 9/21/2006 Co-60 -3.50E+01 1.60E+01 6.70E+01 SE2 Li 1458-02 9/21/2006 Cs-134 7.OOE+00 1.IOE+01 3.80E+01 SE2 Li 1458-02 9/21/2006 Cs-137 3.99E+02 3.OOE+01 6.20E+0 1 5E2 Li 1458-02 9/21/2006 K-40 1 .70E+04 6.40E+02 5.30E+02 SE3 Li 1458-03 9/21/2006 AcTh-228 7.06E+02 5.70E+01 2. 1OE+02 SE3 L 1145 8-03 9/21/2006 Be-7 -5.OOE+01 1.30E+02 4.80E+02 SE3 Li 1458-03 9/21/2006 Co-58 1.40E+01 I1.40E+01 4.80E+01

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONG STD.DEV. ýMfC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)

SE3 21 L11458-03 9/21/2006 Co-60 1.80E+01 1.40E+01 4.80E+01 SE3 21 L11458-03 9/21/2006 Cs-134 0.OOE+00 1.2013+01 4.20E+01 SE3 21 L11458-03 9/21/2006 Cs-137 3.67E+02 3.OOE+01 6.90E+01 SE3 21 L11458-03 9/21/2006 K-40 1.3913+04 5.80E+02 5.80E+02*

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-9

Yankee Nuclear Power Station Radiological Environmrental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (p~i/L) (pCi/L) (pCi[L)

WG 11 LI 045 1-04 1/25/2006 Ba-140 -9.OOE-Oi 2.70E+00 1.OOE+01 WG 11 L10451-04 1/25/2006 Co-58 -9.OOE-01 1.90E+00 6.90E+00 WG 11 Ll10451-04 1/25/2006 Co-60 2.OOE-0 1 2. 1OE+00 7.80E+00 WG 11 L10451-04 1/25/2006 Cs-134 -2.30E+00 2.OOE+00 7.80E+00 WG ii L10451-04 1/25/2006 Cs-137 -2.80E+00 1.90E+00 7.20E+00 WG Ii L1045 1-04 1/25/2006 Fe-59 -1 .40E+00 3.60E+00 1.40E+01 WG 11 L10451-04 1/25/2006 GROSS BETA 2.7013+00 1.O13+00 3.OOE+00 WG 11 L10451-04 1/25/2006 H-3 1.60E+02 1.OOE+02 3 .OOE+02 WG ii L1045 1-04 1/25/2006 1-131 6.90E+00 3.70E+00 1.20E+01 WG 11 L10451-04 1/25/2006 Mn-54 -2.80E+00 1.90E+00 7.20E+00 WG II L10451-04 1/25/2006 Zni-65 4.90E+00 6.4013+00 2.10OE+01 WG 11 L10451-04 1/25/2006 Zr-95 -2.30E+00 3.60E+00 1 .30E+01 WG 11 L10539-04 2/21/2006 Ba-140 -1 .60E+00 4.20E+00 1.60E+/-01 WG 11 L10539-04 2/21/2006 Co-58 -3.60E+00 1.90E+00 7.90E+00 WG 11 Li10539-04 2/21/2006 Co-60 -1.80E+00 2.1iOE+00 8.30E+00 WG 11 Li10539-04 2/21/2006 Cs-134 1.30E+00 1.90E+/-00 6.60E+00 WG 11 Li105 39-04 2/21/2006 Cs-137 1 OQE-Ol 1.60E+'00 5.90E+00 WG ii Li10539-04 2/21/2006 Fe-59 -1 .30E+00 3.90E+00 1.50E+01

• WG 11 Li10539-04 2/21/2006 GROSS BETA 3.50E+00 1.OOE+00 3.OOE+00 WG ii Li10539-04 2/21/2006 H-3 -7.OOE+0 1 I.OOE+02 3. 1OE+02 WG 11 L10539-04 2/21/2006 1-131 -7.OOE+00 5.1OE+00 1.9013+01 11 L10539-04 2/21/2006 Mn-54 -2. 60E+00 1.80E+00 7.20E+00 WG ii L10539-04 2/21/2006 Zn-65 -5.60E+00 4.OOE+00 I1.60E+/-01 WG 11 L10539-04 2/21/2006 Zr-95 2.20E+00 3.40E+00 1.20E+01 WG 11 L10664-04 3/28/2006 Ba-140 -9.OOE-Oi 2.40E+00 9.30E+00 WG 11 LI10664-04 3/28/2006 Co-58 -5.80E+00 2.OOE+00 8.20E+00 WG 11 L10664-04 3/28/2006 Co-60 6.OOE-01 2.OOE+00 7.30E+00 WG 11 L10664-04 3/28/2006 Cs-134 1.40E+00 2.OOE+00 7. 1OE+00 WG Ii L10664-04 3/28/2006 Cs-137 -2.OOE+00 1.80E+00 6.90E+00 WG 11 L10664-04 3/28/2006 Fe-59 2.30E+00 4.30E+00 1.50E+01 WG

• 11 L10664-04 3/28/2006 GROSS BETA 5 .90E+00 1.20E+00 3.OOE+00 WG 11 L1 0664-04 3/28/2006 H-3 5.60E+01 8.80E+01 2.80E+02 WG 11 L10664-04 3/28/2006 1-131 3.OOE-Oi 3 .20E+00 1. 1OE+0 I WG 11 L10664-04 3/28/2006 Mn-54 -1 .30E+00 I1.90E+00 7.20E+00 WG 11 Li10664-04 3/28/2006 Zn-65 -3.90E+/-00 8.50E+00 3.OOE+01 WG 11 L10664-04 3/28/2006 Zr-95 -5.OOE+00 3 .70E+00 1.40E+01 WG 11 L 11207-03 7/6/2006 Ba-140 -1 .20E+00 6.90E+/-00 2.60E+01 WG 11 Li 1207-03 7/6/2006 Co-58 1.50E+00 1.60E+00 5.70E+00

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-1 0

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END) CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (pCi/L) (pCi/L) (p~i/L)

WG 11I L 11207-03 7/6/2006 Co-60 -1.70E+00 1.60E+00 6.30E+00 WG I1I Li 1207-03 7/6/2006 Cs-134 -4.00E-01 1.60E+00 5.80E+00 WG I1I LI 1207-03 7/6/2006 Cs-137 -1.80E+00 1.30E+00 4.90E+00 WG I11 L 11207-03 7/6/2006 Fe-59 -3.OOE+00 5.OOE+00 I1.9013+01 WG II L 11207-03 7/6/2006 GROSS BETA 2.30E+00 1.OO13+00 3.20E+00 WG II L 11207-03 7/6/2006 1-131 1.70E+01 1.20E+01 1.90E+01 WG I1I L 11207-03 7/6/2006 Mn-54 -9.OOE-01 1.70E+00 6.2013+00 WG I1I L 11207-03 7/6/2006 Zn-65 -5.80E+00 3.60E+00 1.40E+01 WG 11I L 11207-03 7/6/2006 Zr-95 -3.OOE-01 3.60E+/-00 1.30E+01 WG I1I L 11324-03 8/28/2006 Ba-140 -5.OOE-01 3.30E+00 1.20E+01 WG 11I LI 1324-03 8/28/2006 Co-58 -2.70E+00 1.40E+00 5.90E+00 WG II Ll 1324-03 8/28/2006 Co-60 2.I1OE+00 1.70E+00 5.80E+00 WG 11I Li 1324-03 8/28/2006 Cs-134 1.40E+00 1.70E+00 5.80E+00 WG I1I L1 1324-03 8/28/2006 Cs-137 6.OOE-01 1.60E+00 5.70E+00 WG II Li 1324-03 8/28/2006 Fe-59 0.OOE+00 3.20E+00 1.20E+01 WG I1I L 11324-03 8/28/2006 GROSS BETA 2.85E+00 9.8013-0 1 2.9013+00 WG I11 Li 1324-03 8/28/2006 H-3 8.OOE+01 1.2013+02 3.80E+02 WG 11I L1 1324-03 8/28/2006 1-131 -1.90E+400 3.50E+00 1.30E+01 WG I11 Li 1324-03 8/28/2006 Mn-54 0.00E+00 1.50E+00 5.6013+00 WG 11I L 11324-03 8/28/2006 Zn-65 -6.1013+00 3.30E+00 1.40E+01 WG 11I L1 1324-03 8/28/2006 Zr-95 -1.50E+00 3. 1OE+00 1.1OE+01 WG 12 L10451-05 1/25/2006 Ba-140 -2.60E+00 2.80E+00 1.2013+01 WG 12 L10451-05 1/25/2006 Co-58 -1.20E+00 1.90E+00 7.20E+00 WG 12 L10451-05 1/25/2006 Co-60 4. 1OE+00 1.90E+00 5.60E+00 WG 12 L10451-05 1/25/2006 Cs-134 -6.OOE-01 2.20E+00 8.20E+00 WG 12 L10451-05 1/25/2006 Cs-137 -5.00E-01 1.80E+00 6.9013+00 WG 12 L10451-05 1/25/2006 Fe-59 9.OOE-01 4. 1OE+00 1.50E+01 WG 12 L10451-05 1/25/2006 GROSS BETA 4.OOE+00 1.L101+00 3.2013+00 WG 12 L10451-05 1/25/2006 H-3 4.7 1E+03 1.20E+02 3. 1OE+02 WG 12 L10451-05 1/25/2006 1-131 1.90E+00 3.4013+00 1.20E+01 WG 12 L10451-05 1/25/2006 Mn-54 9.00E-01 1.90E+00 6.80E+00 WG 12 L10451-05 1/25/2006 Zn-65 -6.90E+00 4.70E+00 1.90E+01 WG 12 L 10451-05 1/25/2006 Zr-95 7.80E+/-00 3.60E+00 I.IOE+01 WG 12 L10539-05 2/21/2006 Ba-140 -7.00E-01 4.40E+00 1.70E+01 WG 12 L10539-05 2/21/2006 Co-58 -2.40E+00 1.90E+00 7.60E+00 WG 12 L10539-05 2/21/2006 Co-60 1.80E+00 2.10E+00 7.40E+00 WG 12 L10539-05 2/21/2006 Cs-134 -2.40E+00 2. 1OE+00 8.40E+00 WG 12 L10539-05 2/21/2006 Cs-137 1.30E+00 2. 1OE+/-00 7.30E+00

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-11

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END) CONG STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (PUiL)

WG 12 L10539-05 2/21/2006 Fe-59 -3.OOE+00 5.40E+00 2.OOE+0l WG 12 L10539-05 2/21/2006 GROSS BETA 5.30E+00 1.20E+00 3.50E+00*

WG 12 L10539-05 2/21/2006 H-3 4.65E+03 1.20E+02 3.L1OE+02*

WG 12 L10539-05 2/21/2006 1-131 -3.20E+00 5.00E+00 1.80E+01 WG 12 L10539-05 2/21/2006 Mn-54 -4.0013-01 2.OOE+00 7.40E+00 WG 12 L10539-05 2/21/2006 Zn-65 7.00E-01 3.90E+00 1.40E+01 WG 12 L10539-05 2/21/2006 Zr-95 -5.60E+00 3.5013+00 1.40E+01 WG 12 L10664-05 3/28/2006 Ba-140 -4.OOE-01 3.l101+00 1.20E+01 WG 12 L 10664-05 3/28/2006 Co-58 0.OOE+00 2.OOE+00 7.20E+00 WG 12 L10664-05 3/28/2006 Co-60 0.OOE+/-00 1.80E+00 6.90E+00 WG 12 L10664-05 3/28/2006 Cs-134 2.40E+00 2.50E+00 8.70E+00 WG 12 L10664-05 3/28/2006 Cs-137 -2.60E+00 1.90E+00 7.40E+00 WG 12 L10664-05 3/28/2006 Fe-59 2.70E+00 4.I1OE+00 1.50E+01 WG 12 L10664-05 3/28/2006 GROSS BETA 6.50E+00 1.20E+00 3.OOE+00*

WG 12 L10664-05 3/28/2006 H-3 4.35E+03 1.1OE+02 2.80E+02*

WG 12 L10664-05 3/28/2006 1-131 -7.OOE-01 3.OOE+00 l.IOE+01 WG 12 L10664-05 3/28/2006 Mn-54 -2.OOE-01 1.80E+00 6.70E+00 WG 12 L10664-05 3/28/2006 Zn-65 1.40E+00 3.60E+00 1.30E+01 WG 12 L10664-05 3/28/2006 Zr-95 -3.OOE-01 3.60E+00 1.30E+01 WG 12 L10792-03 4/25/2006 Ba-140 0.OOE+00 2.40E+00 9.20E+00 WG 12 L10792-03 4/25/2006 Co-58 7.OOE-01 1.50E+00 5.50E+00 WG 12 L10792-03 4/25/2006 Co-60 2.50E+00 1.80E+00 5.90E+00 WG 12 L10792-03 4/25/2006 Cs-134 -5.OOE-01 1.70E+00 6.30E+00 WG 12 L10792-03 4/25/2006 Cs-137 -4.OOE-01 1.70E+00 6.20E+00 WG 12 L10792-03 4/25/2006 Fe-59 5.70E+00 3.50E+00 1.l1OE+0lI WG 12 L10792-03 4/25/2006 GROSS BETA 3.I1OE+00 l.OOE+00 3.OOE+00*

WG 12 L10792-03 4/25/2006 H-3 3.86E+03 1.1OE+02 2.80E+02*

WG 12 L10792-03 4/25/2006 1-131 -1.80E+00 2.70E+00 9.8013+00 WG 12 L10792-03 4/25/2006 Mn-54 -4.OOE-01 1.70E+00 6.20E+00 WG 12 L10792-03 4/25/2006 Zn-65 -4.10E+00 3.60E+00 1.40E+01 WG 12 L10792-03 4/25/2006 Zr-95 -1.90E+00 3.I1OE+00 1.20E+01 WG 12 L10917-03 5/23/2006 Ba-140 -2.20E+00 3.30E+00 1.30E+01 WG 12 L10917-03 5/23/2006 Co-58 9.OOE-01 1.70E+00 6. 1OE+00 WG 12 L10917-03 5/23/2006 Co-60 2.60E+00 2.OOE+00 6.70E+00 WG 12 L10917-03 5/23/2006 Cs-134 3.40E+00 1.80E+00 5.80E+00 WG 12 L10917-03 5/23/2006 Cs-137 -2.80E+00 1.90E+00 7.30E+00 WG 12 L10917-03 5/23/2006 Fe-59 -2.90E+00 4.OOE+00 1.50E+01

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Surmmary of 2006 Data SAMPLE END CONG STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (Pci/L)

WG 12 L10917-03 5/23/2006 GROSS BETA 3.80E+00 1.I1OE+00 3.OOE+00*

WG 12 L10917-03 5/23/2006 H-3 2.76E+03 1.40E+02 3.60E+02*

WG12 L10917-03 5/23/2006 1-131 1.30E+00 2.90E+00 1.OOE+01 WG 12 L10917-03 5/23/2006 Mn-54 1.70E+00 1.60E+00 5.60E+00 WG 12 L10917-03 5/23/2006 Zn-65 -2.40E+00 4.l1OE+00 1.60E+01 WG 12 L10917-03 5/23/2006 Zr-95 4.OOE-01 3.OOE+00 1.10E+01 WG 12 LI 1207-04 7/6/2006 Ba-140 -9.5013+00 8.80E+00 3.70E+01 WG 12 LI 1207-04 7/6/2006 Co-58 -3.70E+00 2.40E+00 9.6013+00 WG 12 Li 11207-04 7/6/2006 Co-60 -1.30E+00 2.30E+00 8.60E+00 WG 12 Ll 1207-04 7/6/2006 Cs-134 2.4013+00 2.20E+00 7.3013+00 WG 12 Li 1207-04 7/6/2006 Cs-137 -7.OOE-0i 1.90E+00 7.0013+00 WG 12 L 11207-04 7/6/2006 Fe-59 -4.30E+/-00 5.20E+00 2.OOE+0l WG 12 Ll 1207-04 7/6/2006 GROSS BETA 3.50E+00 1.I1OE+00 3.1OE+00*

WG 12 Li 11207-04 7/6/2006 H-3 1.89E+03 1.20E+02 3.40E+02*

WG 12 L 11207-04 7/6/2006 1-131 2.20E+01 1.60E+01 5.50E+01 WG 12 Li 1207-04 7/6/2006 Mn-54 1.20E+00 2.40E+00 8.50E+00 WG 12 Li 1207-04 7/6/2006 Zn-65 -1.O1E+/-01 4.70E+00 2.OOE+01 WG 12 Li 11207-04 7/6/2006 Zr-95 9.OOE-01 4.OOE+00 1.40E+01 WG12 Li 1224-03 8/1/2006 Ba-140 -2.90E+00 3.90E+00 1.60E+01 WG 12 L 11224-03 8/1/2006 Co-58 3.60E+/-00 1.90E+00 5.90E+00 WG 12 Li 1224-03 8/1/2006 Co-60 -2.80E+00 2.30E+00 9.50E+00 WG 12 L11224-03 8/1/2006 Cs-134 -3.60E+00 2.60E+00 i.OOE+01 WG 12 Li 11224-03 8/1/2006 Cs-137 0.OOE+00 2.OOE+00 7.50E+00 WG 12 L 11224-03 8/1/2006 Fe-59 -2.50E+00 3.70E+00 1.50E+01 WG 12 LI 1224-03 8/1/2006 GROSS BETA 4.70E+00 l.OOE+00 2.80E+00*

WG 12 Li11224-03 8/1/2006 H-3 1.69E+03 1.20E+02 3.40E+02*

WG 12 LI 1224-03 8/1/2006 1-131 -1.OOE-01 3.50E+00 1.30E+01 WG 12 LI 1224-03 8/1/2006 Mn-54 -1.20E+/-00 1.90E+00 7.60E+00 WG 12 L 11224-03 8/1/2006 Zn-65 4. 1OE+00 5.OOE+00 1.80E+01 WG 12 LI 11224-03 8/1/2006 Zr-95 2.50E+00 3.80E+00 1.40E+01 WG 12 Li 11324-04 8/28/2006 Ba-140 5.OOB-Ol 2.70E+00 9.90E+00 WG 12 Li 11324-04 8/28/2006 Co-58 -5.OOB-Ol 1.40E+00 5.30E+00 WG 12 Li 11324-04 8/28/2006 Co-60 0.OOE+00 1.80E+00 6.60E+00 WG 12 Lil1324-04 8/28/2006 Cs-134 -9.OOE-01 1.50E+00 5.80E+00 WG 12 Li 11324-04 8/28/2006 Cs-137 -3.60E+00 1.70E+00 6.50E+00 WG 12 Li 11324-04 8/28/2006 Fe-59 1.40E+00 3.50E+00 1.20E+01

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END GONG STD.DEV. MDC TYPE STATION LSN DATE NJCLIDE (pCiIL) (pCi/L) (PCifL)

WG 12 Li 1324-04 8/28/2006 GROSS BETA 3.30E+00 I.1OE+00 3.30E+00 WG 12 LI 1324-04 8/28/2006 H-3 1.32E+03 1.30E+02 3.80E+02 WG 12 Li 1324-04 8/28/2006 1-131 -3.20E+00 3.30E+00 1.20E+01 WG 12 Li 1324-04 8/28/2006 Mn-54 -2.40E+00 1.80E+00 6.70E+00 WG 12 L 11324-04 8/28/2006 Zn-65 -4.20E+00 3.1IOE+00 1.20E+01 WG 12 L 11324-04 8/28/2006 Zr-95 0.OOE+00 2.80E+00 1.OOE+01

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-i14

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIIDE (p~i/L) (pCi/L) (pCi/L)

WR 11 L10451-01 1/25/2006 Ba-140 0.OO13+00 4.20E+00 1.60E+01 WR 11 L10451-01 1/25/2006 Co-58 1.30E+00 1.80E+00 6.60E+00 WR 11 Li10451-01 1/25/2006 Co-60 -4. 1OE+00 2.6013+00 1.1OE+01 WR 11 L10451-01 1/25/2006 Cs-134 -1 .50E+00 2.30E+00 9.20E+00 WvR 11 L10451-01 1/25/2006 Cs-137 -3.OOE-01 2.50OE+i00 9.2013+00 WR 11 L10451-01 1/25/2006 Fe-59 2.OOE+00 4.60E+00 1.70E+01 WVR 11 L10451-01 1/25/2006 GROSS BETA 1.3 1E+00 8.50E-01 2.80E+00 WR 11 L10451-01 1/25/2006 H-3 1.1OE+02 4.50E+02 1.40E+03 W~R 11 L1045 1-01 1/25/2006 1-131 3 .OOE+00 4.30E+00 1.50E+01 WvR 11 L10451-01 1/25/2006 Mn-54 3.3013+00 2.50E+00 8.20E+00 WR 11 L10451-01 1/25/2006 Zn-65 3.L1OE+00 5.40E+00 2.OOE+0 1 WR 11 L10451-01 1/25/2006 Zr-95 -5.80E+00 3. 1OE+00 I1.40E+01 WVR 11 L10539-01 2/21/2006 Ba-140 6.20E+00 4.6013+00 1.60E+01 WR 11 L10539-01 2/21/2006 Co-58 -l .OOE-01 2. 1OE+00 7.9013+00 WIR 11 L10539-01 2/21/2006 Co-60 -1 .90E+00 2.OOE+00 8.50E+00 WVR 11 L10539-01 2/21/2006 Cs-134 -3. 10E+00 2.OOE+00 8.40E+00 WR 11 L10539-01 2/21/2006 Cs-137 1.80E+00 2.OOE+00 6.90E+/-00 WR 11 L10539-01 2/21/2006 Fe-59 -5.30E+00 4.70E+00 1.90E+01I WVR 11 L10539-01 2/21/2006 GROSS BETA 1.81 E+00 8.90E-01 2.90E+00 WR 11 L10539-01 2/21/2006 H-3 -1 .OOE+03 4.50E+02 1.40E+03 WVR 11 L10539-01 2/21/2006 1-131 3.70E+00 5.90E+00 2.OOE+0 1 WR 11 L10539-01 2/21/2006 Mn-54 3.OOE-01 2.30E+00 8.30E+00 WR 11 L10539-01 2/21/2006. Zn-65 -8.OOE-01 5 .OOE+00 1.90E+01 WR 11 L10539-01 2/21/2006 Zr-95 2.30E+00 3.90E+00 1.40E+01 WvR 11 L10664-01 3/28/2006 Ba-140 4.30E+00 3.20E+00 1.1OE+01 W~R 11 L10664-01 3/28/2006 Co-58 -3.1013+00 1.8013+00 7.40E+00 WvR 11 L10664-01 3/28/2006 Co-60 1.20E+00 2.6013+00 9.30E+00 WR 11 L10664-01 3/28/2006 Cs-134 -1 .50E+00 2.OOE+00 7.70E+00 WR 11 L10664-0 1 3/28/2006 Cs-137 1.4013+00 2.OOE+/-00 6.90E+00 WR 11 L10664-01 3/28/2006 Fe-59 -7.OOE-01 3.90E+00 1.50E+01 WR 11 L 10664-01 3/28/2006 GROSS BETA 7.10E-01 8.10E-01 2.80E+/-00 WR 11 LI10664-01 3/28/2006 H-3 -3.10E+02 4.60E+02 1.40E+03 WR 11 L10664-01 3/28/2006 1-131 6.40E+00 3. 1OE+00 I .OOE+/-01 WVR 11 L10664-01 3/28/2006 Mn-54 5.OOB-Ol 2.OOE+00 7.OOE+00 WR 11 L10664-01 3/28/2006 Zn-65 4,1 OE+/-00 4. 80E+00 I1.60E+01 WR 11 L10664-01 3/28/2006 Zr-95 2. 1OE+00 3.30E+00 1.20E+01 WR 11 L10752-01 3/28/2006 H-3 -7.30E+02 4.30E+02 1.30E+03 WR 11 L10792-01 4/25/2006 Ba- 140 1.40E+00 3 .40E+00 1.30E+01

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

+/- Minimum Detectable Concentration > Lower Limit of Detection Requirement C-15

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCiJL) (pCi/L)

WIR I11 L10792-01 4/25/2006 Co-58 -4.OOE-01 2.l1OE+00 8. 1OE+00 WR I1I L10792-01 4/25/2006 Co-60 2.70E+00 2.OOE+00 6.70E+00 WVR I11 L10792-01 4/25/2006 Cs-134 3.90E+00 2.30E+00 7.40E+00 WvR I1I L10792-01 4/25/2006 Cs-137 -2.70E+00 2.00E+00 8. 1OE+00 WR 11I L10792-01 4/25/2006 Fe-59 -4.60E+00 4.10E+00 1.70E+01 WR II L10792-01 4/25/2006 GROSS BETA 3.80E+00 1.OOE+00 3.OOE+00 WvR II L10792-01 4/25/2006 1-131 2.40E+00 3.i1OE+00 1.10E+01 WVR I11 L10792-01 4/25/2006 Mn-54 -1.40E+00 2.OOE+00 7.80E+00 WvR I11 Li10792-01 4/25/2006 Zn-65 3.20E+00 4.50E+00 1.60E+01 WvR I11 L10792-01 4/25/2006 Zr-95 6.OOE-01 4. 1OE+00 1.50E+01 WR II L10917-01 5/23/2006 Ba-140 4.OOE-01 2.OOE+00 7.60E+00 WR I1I Li10917-01 5/23/2006 Co-58 1.20E+00 1.30E+00 4.60E+00 WR I1I L10917-01 5/23/2006 Co-60 8.OOE-01 1.70E+00 6.I1OE+00 WR 11 L10917-01 5/23/2006 Cs-134 -i.OOE+00 1.50E+00 5.80E+00 WvR I1I L10917-01 5/23/2006 Cs-137 6.OOE-01 1.60E+00 5.80E+00 WR I1I L10917-01 5/23/2006 Fe-59 -1.30E+00 3.OOE+00 1.I1OE+/-01I WR I1I L10917-01 5/23/2006 GROSS BETA 1.38E+00 8.90E-01 2.90E+00 WvR I1I L10917-01 5/23/2006 1-131 3.90E+00 2.40E+00 8.OOE+00 WIR I11 L10917-01 5/23/2006 Mn-54 -1.10E+00 1.60E+00 6.OOE+00 WR I1I L10917-01 5/23/2006 Zn-65 -1.80E+00 3.30E+00 1.20E+/-01 WR 11I L10917-01 5/23/2006 Zr-95 -4.1OE+00 2.50E+/-00 9.80E+00 WR I1I Li 1207-01 7/6/2006 Ba-140 1.36E+01 7.60E+00 2.40E+01 WvR 11 Li 1207-01 7/6/2006 Co-58 -1.30E+00 1.80E+00 6.70E+00 WvR I11 L 11207-0 1 7/6/2006 Co-60 8.OOE-01 1.80E+00 6.20E+00 WR I1I L1 1207-01 7/6/2006 Cs-134 2.OOE-01 1.70E+00 5.90E+00 WVR 11 L1 1207-01 7/6/2006 Cs-137 1.70E+00 1.60E+00 5.30E+00 WVR I11 L 11207-01 7/6/2006 Fe-59 3.30E+00 4.40E+00 1.50E+01 WR I1I Li 1207-0 1 7/6/2006 GROSS BETA 1.34E+00 8.30E-01 2.70E+00 WIR 11 L1 1207-01 7/6/2006 1-131 -1.30E+01 1.20E+01 4.50E+01 W~R I11 L 11207-01 7/6/2006 Mn-54 -3.40E+00 1.60E+00 6.20E+00 WR I1I L 11207-01 7/6/2006 Zn-65 4.OOE-01 3.40E+00 1.20E+01 WIR I11 Li 1207-01 7/6/2006 Zr-95 -2.90E+00 3.60E+00 1.30E+01 WR I1I L 11210-01 7/6/2006 H-3 -1.04E+03 4.70E+02 1.50E+03 WVR 11 L 11224-01 8/1/2006 Ba-140 0.OOE+00 3.60E+00 1.40E+01 WVR I11 L 11224-01 8/1/2006 Co-58 -2.80E+00 2. 1OE+00 8.60E+00 WR II Li 1224-01 8/1/2006 Co-60 2.20E+00 2.40E+00 8.30E+00 WVR 11 L 11224-01 8/1/2006 Cs-134 3.20E+/-00 2.40E+00 8. 1OE+00 W;R 11 L11224-01 8/1/2006 Cs-137 3.40E+00 1.80E+00 5.80E+00

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-1 6

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (pCi/L) (PUiL) (pCi/L)

WR Li 11224-01 8/1/2006 Fe-59 1.70E+00 4.0013+00 1.5013+01 WR Li 11224-01 8/1/2006 GROSS BETA 9.80E-01 8.70E-01 2.80E+00 WR LI 11224-01 8/1/2006 1-131 -1 .20E+00 3.4013+00 1.30E+01 WR LI 11224-01 8/1/2006 Mn-54 1.80E+00 1.80E+00 6.40E+00 WR L 11224-01 8/1/2006 Zn-65 -7.70E+/-00 4.70E+00 2.0013+01 WNR Li 11224-01 8/1/2006 Zr-95 -3.40E+00 3.6013+00 1.40E+01 W~R L 11324-01 8/28/2006 Ba-140 -3.30E+00 2.70E+00 1.2013+01 WR Li 11324-01 8/28/2006 Co-58 -3.0013-01 2.OOE+00 7.30E+00 WR L 11324-01 8/28/2006 Co-60 -1 .30E+00 1.9013+00 7.30E+00 WR L 11324-01 8/28/2006 Cs-134 3.OOE-01 1.90E+.00 6.8013+00 WVR L 11324-01 8/28/2006 Cs-137 -1.50E+00 1.70E+00 6.50E+00 WR L 11324-01 8/28/2006 Fe-59 -1 .60E+00 4. 1OE+00 1.50E+01 WR L 11324-01 8/28/2006 GROSS BETA 5.90E-01 8.3013-01 2.90E+00 WR L 11324-01 8/28/2006 1-131 -2.80E+/-00 3 .50E+00 1.30E+01 WVR L 11324-01 8/28/2006 Mn-54 -1 .20E+00 1 .80E+00 6.90E+00 WR L 11324-01 8/28/2006 Zn-65 -8.90E+00 4.OOE+00 1.70E+01 WR Li 11324-01 8/28/2006 Zr-95 3. 1OE+00 2.90E+00 1.OOE+01 W~R Li 1563-01 8/28/2006 H-3 3.50E+02 4.70E+02 1.40E+03 WR L 11567-01 10/10/2006 Ba-140 1.50E+00 6.OOE+00 2.10E+01 WR L 11567-01 10/10/2006 Co-58 7.OOE-01 1.3013+00 4.6013+00 WR Li 1567-01 10/10/2006 Co-60 -1.30E+00 1.101+00 4.20E+00 WR LI 1567-01 10/10/2006 Cs-134 -8.OOE-01 1.20E+00 4.40E+00 WR L 11567-01 10/10/2006 Cs-137 -2.OOE-01 1.OOE+00 3.70E+00 WR L 11567-01 10/10/2006 Fe-59 -2.50OE+00 3.50E+00 1.3013+01 WR LI 1567-01 10/10/2006 H-3 -3.70E+02 4.60E+02 1.4013+03 WR Li 1567-01 10/10/2006 1-131 3.OOE+00 1.80E+01 6.20E+0 1 WR Li11567-01 10/10/2006 Mn-54 -2.90E+00 1.1013+00 4.3013+00 WR Li 1567-01 .10/10/2006 Zn-65 -9.OOE-0 I 2.60E+00 9. 1OE+00 WR Li 1567-01 10/10/2006 Zr-95 2.20E+00 2.40E+00 8.20E+00 WR Li 1638-01 10/10/2006 GROSS BETA 1.87E+00 9. 10E-0 1 2.90E+00 WR L1045 1-02 1/25/2006 Ba- 140 -3 .60E+00 2.60E+00 1.20E+01 WVR L10451-02 1/25/2006 Co-58 -1.90E+00 1 .70E+00 6.90E+00 WR L10451-02 1/25/2006 Co-60 3.OOE-01 1.60E+00 6.20E+00 WR L10451-02 1/25/2006 Cs-134 -1 .20E+00 2.1OE+00 8.OOE+00 WR L10451-02 1/25/2006 Cs-137 4.OOE-01 I1.70E+00 6.20E+00 W~R L10451-02 1/25/2006 Fe-59 3.OOE+00 3.70E+00 1.30E+01 WR L10451-02 1/25/2006 GROSS BETA 2.59E+00 9.90E-01 3.OOB+00 WR L10451-02 1/25/2006 H-3 5.OOE+01 4.5013+02 1.40E+03

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END) CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCiIL) (PCifL) (pCi/L)

WR 21 L10451-02 1/25/2006 1-131 9.OOE-01 2.70E+00 9.50E+00 WIR 21 L10451-02 1/25/2006 Mn-54 2.00E-01 1.70E+00 6.20E+00 WR 21 L10451-02 1/25/2006 Zn-65 -5.50E+00 4.20E+00 1.70E+01 WVR 21 L10451-02 1/25/2006 Zr-95 1.60E+00 3.OOE+00 1.1OE+01 WR 21 L10539-02 2/21/2006 Ba-140 -5.50E+00 3.9013+00 1.70E+01 WR 21 L10539-02 2/21/2006 Co-58 -4.OOE+00 2.20E+00 8.90E+00 AIR 21 L10539-02 2/21/2006 Co-60 1.60E+00 2.40E+00 8.40E+00 WR 21 L10539-02 2/21/2006 Cs-134 -3.OOE-01 2.40E+00 8.70E+00 WR 21 L10539-02 2/21/2006 Cs-137 -2.50E+00 2.30E+00 9.OOE+00 W'R 21 L10539-02 2/21/2006 Fc-59 3.20E+00 5. 1OE+00 1.80E+01 WR 21 L10539-02 2/21/2006 GROSS BETA 1.05E+00 8.80E-01 3.OOE+00 WR 21 L10539-02 2/21/2006 H-3 -9.60E+02 4.50E+02 1.40E+03 WR 21 L10539-02 2/21/2006 1-131 2.70E+00 6.I1OE+00 2.10E+01 WR 21 L10539-02 2/21/2006 Mn-54 -1.50E+00 2.OOE+00 7.70E+00 WR 21 L10539-02 2/21/2006 Zn-65 -1.32E+01 4.40E+00 2.OOE+01 WR 21 L10539-02 2/21/2006 Zr-95 2.90E+00 3.90E+00 1.40E+01 WR 21 L10664-02 3/28/2006 Ba-140 -3.90E+00 3.60E+00 1.50E+01 WR 21 L10664-02 3/28/2006 Co-58 -1.I1OE+00 2.30E+00 8.80E+00 WvR 21 L10664-02 3/28/2006 Co-60 4.OOE-01 2. 1OE+00 8.OOE+00 WR 21 L10664-02 3/28/2006 Cs-134 1.20E+00 2.60E+00 9.20E+00 WYR 21 L10664-02 3/28/2006 Cs-137 -6.OOE-01 1.80E+00 7.1OE+00 WvR 21 L10664-02 3/28/2006 Fe-59 8.20E+00 4.20E+00 1.30E+01 WvR 21 L10664-02 3/28/2006 GROSS BETA 1.57E+00 8.60E-01I 2.70E+00 WR 21 L10664-02 3/28/2006 H-3 -8.60E+02 4.50E+/-02 1.40E+03 WvR 21 L10664-02 3/28/2006 1-131 2.60E+00 3.OOE+00 1.OOE+01 WvR 21 L10664-02 3/28/2006 Mn-54 2.40E+i00 2.30E+00 8.OOE+/-00 WvR 21 L10664-02 3/28/2006 Zn-65 -1.70E+00 3.40E+00 1.40E+01 WvR 21 L10664-02 3/28/2006 Zr-95 7.OOE-01 3.80E+00 1.40E+01 WR 21 L10752-02 3/28/2006 H-3 -1.OOE+/-01 4.4013+02 1.30E+03 WvR 21 L10792-02 4/25/2006 Ba-140 1.30E+00 2.80E+00 1.LOE+01 WR 21 L10792-02 4/25/2006 Co-58 -1.OOE+00 2.10E+00 8.20E+00 WVR 21 L10792-02 4/25/2006 Co-60 1.60E+00 2.20E+00 7.8013+00 WR 21 L10792-02 4/25/2006 Cs-134 -1.80E+00 2.30E+00 9.I1OE+00 WR 21 L10792-02 4/25/2006 Cs-137 1.90E+00 1.80E+00 6.20E+00 WvR 21 L10792-02 4/25/2006 Fe-59 -3.20E+00 3.20E+00 1.40E+01 WvR 21 L10792-02 4/25/2006 GROSS BETA 2.3 1E+00 8.80E-01I 2.70E+00 WVR 21 L10792-02 4/25/2006 1-131 -3.60E+00 3.OOE+00 1.20E+01 V'KR 21 L10792-02 4/25/2006 Mn-54 1.OOE+00 1.80E+00 6.50E+00

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

+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-1 8

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCiIL) (pCi/L) (pCi/L)

WR 21 L10792-02 4/25/2006 Zn-65 1.OOE+00 4.70E+00 1.70E+01 WR 21 L10792-02 4/25/2006 Zr-95 5.70E+00 3.I10E+00 l.OO13+01 WvR 21 L10917-02 5/23/2006 Ba-140 -1.1OE+00 2.60E+00 1.1OE+01I WvR 21 L10917-02 5/23/2006 Co-58 4.0013-01 1.80E+00 6.50E+00 WR 21 L10917-02 5/23/2006 Co-60 6.OOE-01 2.OOE+00 7.30E+00 WR 21 L10917-02 5/23/2006 Cs-134 -7.OOE-0i 1.90E+00 7.0013+00 WR 21 L10917-02 5/23/2006 Cs-137 -1.80E+00 1.60E+00 6.i1OE+00 WVR 21 L10917-02 5/23/2006 Fe-59 -6.0013-01 3.6013+00 1.40E+01 WR 21 L10917-02 5/23/2006 GROSS BETA 2.78E+00 9.10E-01 2.60E+00*

WAR 21 L10917-02 5/23/2006 1-131 2.20E+00 2.40E+00 8.20E3+00 WVR 21 L10917-02 5/23/2006 Mn-54 2.5013+00 1.60E+00 5.40E+00 WIR 21 L10917-02 5/23/2006 Zn-65 -4.90E+00 3.70E+00 1.50E+01 WvR 21 L10917-02 5/23/2006 Zr-95 6.10E+00 2.90E+00 9.30E+00 WvR 21 L1 1207-02 7/6/2006 Ba-140 1.48E+01 7.20E+00 2.20E+01 WR 21 LI 11207-02 7/6/2006 Co-58 -2.60E+00 1.60E+00 6.60E+00 WvR 21 Li 11207-02 7/6/2006 Co-60 -1.40E+00 1.70E+00 6.60E+00 WR 21 LI 1207-02 7/6/2006 Cs-134 1.90E+00 1.70E+00 5.60E+00 W~R 21 LI 11207-02 7/6/2006 Cs-137 -1.50E+00 1.80E+00 6.5013+00 WR 21 LI 11207-02 7/6/2006 Fe-59 2.50E+00 4.40E+00 1.6013+01 WR 21 Li 11207-02 7/6/2006 GROSS BETA -3.10E-01 7.80E-01 2.90E+00 WvR 21 L1 1207-02 7/6/2006 1-131 -6.OOE+00 1.40E+01 5.OOE+01 WR 21 Li 11207-02 7/6/2006 Mn-54 1.50E+00 1.60E+00 5.6013+00 WIR 21 LI 1207-02 7/6/2006 Zn-65 -5.0013-0 1 3.60E+00 1.30E+01 WvR 21 LI 11207-02 7/6/2006 Zr-95 2.80E+00 3.1013+00 1.LO13+01 WR 21 LI 11210-02 7/6/2006 H-3 -2.50E+02 4.80E+02 1.50E+03 WR 21 Li 11224-02 8/1/2006 Ba-140 -8.60E+00 3.90E+00 1.80E+01 WR 21 Li 11224-02 8/1/2006 Co-58 -2.60E3+00 1.7013+00 7.50E3+00 WR 21 Li 11224-02 8/1/2006 Co-60 1.30E+00 2.2013+00 7.90E+00 WR 21 Li 1224-02 8/1/2006 Cs-134 1.80E+00 2.OOE+00 7.OOE+00 WR 21 Li 1224-02 8/1/2006 Cs-137 -2.40E+/-00 2.50E+00 9.40E+00 WvR 21 LI 1224-02 8/1/2006 Fe-59 4.20E+00 4.i1OE+00 1.40E+01 WR 21 Li 11224-02 8/1/2006 GROSS BETA 1.90E+00 8.50E-01 2.70E+00 WR 21 LI 11224-02 8/1/2006 1-131 5.001E+00 4.OOE+00 1.30E+01 WVR 21 LI 11224-02 8/1/2006 Mn-54 1.40E+00 1.90E+00 6.70E+00 WVR 21 Li 1224-02 8/1/2006 Zn-65 -9.40E+00 5.2013+00 2.2013+01 WR 21 L11224-02 8/1/2006 Zr-95 -2.10E+00 3. 1OE+00 1.20E+01 WvR 21 LI 11324-02 8/28/2006 Ba-140 -2. 1OE+00 2.80E+00 1.1OE+01 WR 21 Li 1324-02 8/28/2006 Co-58 -3.50E+00 1.8013+00 7.40E+00

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCiIL) (pCi/L)

WR 21 LI 11324-02 8/28/2006 Co-60 2.OOE-01 1.90E+00 6.90E+00 WR 21 LI 11324-02 8/28/2006 Cs-134 -2.OOE-01 1.90E+00 6.90E+00 WR 21 LI 1324-02 8/28/2006 Cs-137 1.40E+00 1.60E+00 5.40E+00 WvR 21 LI 1324-02 8/28/2006 Fe-59 -5.30E+00 3.50E+00 1.40E+01 WR 21 LI 1324-02 8/28/2006 GROSS BETA 5.70E-01 8.OOE-OI 2.70E+00 AIR 21 LI11324-02 8/28/2006 1-131 3. 1OE+00 3.50E+00 1.20E+01 WR 21 Li 1324-02 8/28/2006 Mn-54 1.80E+00 1.80E+00 6.20E+00 WR 21 L 11324-02 8/28/2006 Zn-65 -2.40E+00 3.50E+00 1.40E+01 WVR 21 Li 1324-02 8/28/2006 Zr-95 -4.OOE-01 3.50E+00 1.3013+01 WvR 21 L1 1563-02 8/28/2006 H-3 6.OOE+01 4.80E+02 1.40E+03 WR 21 L1 1567-02 10/10/2006 Ba-140 -1.45E+01 6.OOE+00 2.40E+01I W;R 21 LI 1567-02 10/10/2006 Co-58 -3.OOE-01 1.20E+00 4.30E+00 WR 21 Li 1567-02 10/10/2006 Co-60 -4.OGB-Ol 1.20E+00 4.20E+00 WR 21 L11567-02 10/10/2006 Cs-134 -1.OO13+00 1.1OE+00 4. 1OE+00 WR 21 LI 1567-02 10/10/2006 Cs-137 2.01E+00 9.30E-01 3.OOE+00 WR 21 L1 1567-02 10/10/2006 Fe-59 -5.OOE-01 3.20E+00 1.IOE+01 WR 21 LI 11567-02 10/10/2006 GROSS BETA 1.20E+/-00 8.40E-01 2.80E+00 WR 21 L1 1567-02 10/10/2006 H-3 1.OOE+02 4.80E+02 1.40E+63 WVR 21 L1 1567-02 10/10/2006 1-131 -1.5OE+01 1.60E+01 5.70E+01 WR 21 Ll 1567-02 10/10/2006 Mn-54 -1.70E+00 1.1013+00 4.OOE+00 W~R 21 Li 1567-02 10/10/2006 Zn-65 -5.90E+00 2.60E+00 9.70E+00 WVR 21 LI 1567-02 10/10/2006 Zr-95 -2.40E+00 2.20E+00 8. 1OE+00 WR 31 L10451-03 1/25/2006 Ba-140 -2.30E+/-00 3.20E+00 1.30E+01 AIR 31 L10451-03 1/25/2006 Co-58 -1.30E+00 1.70E+00 6.5013+00 WR 31 L10451-03 1/25/2006 Co-60 -3.70E+00 2.50E+00 9.70E+00 W~R 31 L10451-03 1/25/2006 Cs-134 3.20E+00 2.OOE+00 6.50E+00 WvR 31 L10451-03 1/25/2006 Cs-137 -1.40E+00 1.70E+00 6.50E+00 WVR 31 L10451-03 1/25/2006 Fe-59 3.60E+00 3.50E+00 1.20E+01 WVR 31 L10451-03 1/25/2006 GROSS BETA 1.51E+00 9.30E-01 3.OOE+00 WR 31 L10451-03 1/25/2006 H-3 -3.60E+02 4.40E+02 1.40E+03 WR 31 L10451-03 1/25/2006 1-131 0.OOE+/-00 3.001+00 1.IOE+01 WR 31 L10451-03 1/25/2006 Mn-54 -2.OOE+00 1.50E+00 6.OOE+00 WYR 31 L10451-03 1/25/2006 Zn-65 -5.50E+00 4.30E+00 1.70E+01 WvR 31 L10451-03 1/25/2006 Zr-95 3. 1OE+00 3.OOE+00 1.OOE+01 WR 31 L10539-03 2/21/2006 Ba-140 1.60E+00 4.20E+00 1.50E+01 WR 31 L10539-03 2/21/2006 Co-58 2.80E+00 2.OOE+00 6.80E+00 WvR 31 L10539-03 2/21/2006 Co-60 -2.20E+00 1.70E+00 7. 1OE+00 WVR 31 L10539-03 2/21/2006 Cs-134 -2.40E+00 1.90E+00 7.50E-I00

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONG STD.DEV. MDC TYPE STATION LSN DATE NUJCLIDE (p~i/L) (p~i/L) (pCi/L)

WVR 31 L10539-03 2/21/2006 CS-137 1.30E+00 1.70E+00 6.OOE+00 WR 31 L10539-03 2/21/2006 Fe-59 6.60E+00 3.9013+00 1.30E+01 WR 31 L10539-03 2/21/2006 GROSS BETA 1.95E+00 8.50E-01 2.7013+00 WNR 31 L10539-03 2/21/2006 H-3 -3.60E+02 4.60E+02 1.40E+03 WR 31 L10539-03 2/21/2006 1-131 -1.50E+00 4.50E+00 1.60E+01 WVR 31 L10539-03 2/21/2006 Mn-54 -2.OOE+00 1.80E+00 6.90E+00 WR 31 L10539-03 2/21/2006 Zn-65 -1.20E+00 3.80E+00 1.5013+01 WvR 31 L10539-03 2/21/2006 Zr-95 2.OOE+/-00 3.80E+00 1.30E+01 WR 31 L10664-03 3/28/2006 Ba-140 1.50E+00 3.l1OE+00 1.2013+01 W~R 31 L10664-03 3/28/2006 Co-58 -1.OO13-01 2.OOE+00 7.60E+00 WvR 31 L10664-03 3/28/2006 Co-60 7.OOE-01 2.40E+00 8.90E+00 WR 31 L10664-03 3/28/2006 Cs-134 -1.70E+00 2.50E+00 9.70E+00 W~R 31 L10664-03 3/28/2006 Cs-137 1.30E+00 2.1013+00 7.30E+00 WR 31 L10664-03 3/28/2006 Fe-59 -3.30E+00 4.30E+00 1.70E+01 WVR 31 L10664-03 3/28/2006 GROSS BETA 2.27E+00 9.60E-01 3.OOE+00 WR 31 L10664-03 3/28/2006 H-3 -3.90E+02 4.50E+02 1.40E+03 WR 31 L10664-03 3/28/2006 1-131 -3.50E+00 3.40E+00 1.30E+01 WVR 31 L10664-03 3/28/2006 Mn-54 -1.1OE+00 1.80E+00 .7.20E+00 WVR 31 L10664-03 3/28/2006 Zn-65 -5. 1OE+00 5.20E+00 2.1013+01 WvR 31 L10664-03 3/28/2006 Zr-95 -3.30E+00 3.50E+00 1.40E+01 WvR 31 L10752-03 3/28/2006 H-3 -5.50E+02 4.40E+02 1.40E+03

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONG STD.DEV. MDC TYPE STATION LSN DATE NJCLIDE (pCi/L) (pCi/L) (pCi/L)

WW 52 L10451-07 1/25/2006 Ba-140 8.OOE-01 2.80E+00 1.1013+0 1 ww 52 L10451-07 1/25/2006 Co-58 -1.80E+00 1.90E+00 7.50E+00 ww 52 L10451-07 1/25/2006 Co-60 2. 1OE+00 1.70E+00 5.60E+00 Vww 52 L10451-07 1/25/2006 Cs-134 3.60E+00 2.30E+00 7.60E+00 ww 52 L10451-07 1/25/2006 Cs-137 -3.80E+00 2.40E+00 9.40E+00 WW 52 L10451-07 1/25/2006 Fe-59 1.50E+00 3.0013+00 1.I101+0 1 Vww 52 L10451-07 1/25/2006 GROSS BETA 3.70E+00 1.I101+00 3.30E+00 52 L10451-07 1/25/2006 H-3 1.50E+02 4.6013+02 1.40E+03 ww 52 L10451-07 1/25/2006 1-131 -2.20E+00 3.90E+00 I1.40E+01 52 L10451-07 1/25/2006 Mn-54 -3.OOE-01 1.90E+00 7.20E+00 52 L10451-07 1/25/2006 Zn-65 -4.50E+00 4.50E+00 1 .80E+01 52 L10451-07 1/25/2006 Zr-95 -4. 1OE+00 3.50E+00 1.40E+01 WW 52 Li10539-06 2/21/2006 Ba- 140 -2.OOE-0 1 3.80E+00 1.50E+01 Vww 52 L10539-06 2/21/2006 Co-58 -2.80E+00 2.2013+00 8.80E+00 ww 52 L10539-06 2/21/2006 Co-60 -1 .20E+00 2.20E+00 8.50E+00 WW 52 L10539-06 2/21/2006 Cs-134 3.30E+00 2.40E+00 7.80E+00 ww 52 L10539-06 2/21/2006 Cs-137 1.60E+00 1.90E+00 6.50E+00 Vww 52 L10539-06 2/21/2006 Fe-59 8.0013-01 4.70E+00 1.70E+01 ww 52 L10539-06 2/21/2006 GROSS BETA 3.20E+00 I .OOE+00 3 .OOE+00 ww 52 Li105 39-06 2/21/2006 H-3 2.OOE+02 1.1OE+02 3. 1OE+02

~ww 52 L10539-06 2/21/2006 1-131 5.30E+00 5 .90E+00 2.OOE+01 ww 52 L10539-06 2/21/2006 Mn-54 -3.90E+00 2.10E+00 8.5013+00 WW 52 L10539-06 2/21/2006 Zn-65 -8.30E+00 4.20E+00 1.80E+01 ww 52 LI10539-06 2/21/2006 Zr-95 4.20E+00 3.60E+00 1.20E+01 Vww 52 Li10664-06 3/28/2006 Ba- 140 -2.30E+00 2. 80E+00 1.20E+01 ww 52 L10664-06 3/28/2006 Co-58 1.50E+00 2.20E+00 7.70E+00 Vww 52 L10664-06 3/28/2006 Co-60 8.OOE-01 2.30E+00 8.6013+00 Vww 52 L10664-06 3/28/2006 Cs-134 -4.80E+00 2.80E+00 1.1OE+01I ww 52 LI10664-06 3/28/2006 Cs-137 -3.OOE-01 2.50E+00 9.30E+00 ww 52 Li10664-06 3/28/2006 Fe-59 4.OOE-01 4.60E+00 1.70E+01 ww 52 L10664-06 3/28/2006 GROSS BETA 2.84E+00 9.60E-01 2.90E+00 ww 52 L10664-06 3/28/2006 H-3 5.03E+02 9.OOE+01 2.70E+02 ww 52 Li10664-06 3/28/2006 1-131 1.30E+00 3.9013+00 1 .40E+01 WW 52 Li10664-06 3/28/2006 Mn-54 -1 .40E+00 2. 1IOE+00 8.40E+00 ww 52 L10664-06 3/28/2006 Zn-65 -9.70E+00 6.0013+00 2.40E+01 Vww 52 Li10664-06 3/28/2006 Zr-95 1.90E+00 3 .90E+00 1.40E+01 Vww 52 L10792-04 4/25/2006 Ba-140 3.40E+i00 2.60E+00 8.60E+00 52 L10792-04 4/25/2006 Co-58 -1 .OOE+00 1.90E+00 6.90E+00

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONG STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/L) (pCi/L) (pCi/L)

WW 52 L10792-04 4/25/2006 Co-60 9.OOE-01 1.50E+00 5.40E+00 WW 52 L10792-04 4/25/2006 Cs-134 -3.60E+00 1.90E+00 7.60E+00 WW 52 L10792-04 4/25/2006 Cs-137 -5.OOE-01 1.70E+00 6.30E+00 WW 52 L10792-04 4/25/2006 Fe-59 2.90E+00 3.20E+00 1.101+01I WW 52 L10792-04 4/25/2006 GROSS BETA 5.40E1+00 1.20E1+00 3. 1011+00*

WW 52 L10792-04 4/25/2006 11-3 -3.OOE+02 4.50E1+02 1.30E1+03 WVW 52 L10792-04 4/25/2006 1-131 -7.0013-01 2.80E+00 l.OOE+01 WW 52 L10792-04 4/25/2006 Mn-54 -3.60E1+00 1.80E1+00 7. 1011+00 WW 52 L10792-04 4/25/2006 Zn-65 1.1311+0 1 7.20E1+00 2.40E1+01 WW 52 L10792-04 4/25/2006 Zr-95 -7.0011-01 3.20E1+00 1.20E+01 WW 52 L10917-04 5/23/2006 Ba-140 -6.OOE-0l 2.70E1+00 1.10E1+01 WW 52 L 10917-04 5/23/2006 Co-58 -9.OOE-01 1.90E1+/-00 7.20E+00 WW 52 L10917-04 5/23/2006 Co-60 -2.90E+00 1.70E1+00 7.6011+00 WW 52 L10917-04 5/23/2006 Cs-134 1.60E1+00 2.1013+00 7.20E1+00 WW 52 L10917-04 5/23/2006 Cs-137 -5.OOE-01 1.80E1+00 6.80E1+00 WW 52 L10917-04 5/23/2006 Fe-59 -4. 1011+00 3.60E1+00 1.50E+01 WW 52 L 10917-04 5/23/2006 GROSS BETA 2.02E1+/-00 8.90E-01 2.80E1+00 WW 52 L10917-04 5/23/2006 11-3 2.OOE+01 2.80E+02 8.50E+02 WW 52 L10917-04 5/23/2006 1-131 9.0013-01 2.70E+00 9.60E1+00 W'WA 52 L10917-04 5/23/2006 Mn-54 2.30E1+00 1.90E+00 6.40E1+00 WW 52 L10917-04 5/23/2006 Zn-65 -7.OOE-01 4.30E+00 1.60E1+01 WVW 52 L10917-04 5/23/2006 Zr-95 3.OOE-01 3.40E1+00 1.30E1+01 WW 52 L1 1224-06 8/1/2006 Ba-140 -2.70E1+00 3.l1OE+00 1.40E+01 WW 52 Li 1224-06 8/1/2006 Co-58 -3. 1013+00 1.90E+00 7.70E1+00 WVW 52 Li 1224-06 8/1/2006 Co-60 1.0011-01 2.30E1+00 8.5011+00 WW 52 L 11224-06 8/1/2006 Cs-134 3.20E+00 1.80E1+00 5.90E1+00 WW 52 Li 11224-06 8/1/2006 Cs-137 1.80E1+00 1.80E+00 6.20E+00 WW 52 L 11224-06 8/1/2006 Fe-59 -3.0011+00 3.80E1+00 1.50E1+01 WVW 52 LI 1224-06 8/1/2006 GROSS BETA 6.80E1+00 1.20E+00 2.90E1+00*

WW 52 Li11224-06 8/1/2006 11-3 2.30E1+02 4.70E+02 1.50E+03 WW 52 L 11224-06 8/1/2006 1-131 2.30E+00 4.70E+00 1.60E1+01 WVW 52 LI 1224-06 8/1/2006 Mn-54 -9.OOE-01 1.90E+/-00 7. 1OE+00 W\V 52 LI 1224-06 8/1/2006 Zn-65 7.OOE-01 4.4013+00 1.60E+01 WW 52 Li 11224-06 8/1/2006 Zr-95 -2.20E+00 3.50E+00 1.3011+01 WVW 52 LI 1324-06 8/28/2006 Ba-140 3.50E+00 2.0011+00 6.5011+00 WW 52 L 113 24-06 8/28/2006 Co-58 -1.OOE-01 1.1OE+00 3.7011+00 WW 52 Li 1324-06 8/28/2006 Co-60 -5.4011-01 9.4011-01 3.40E1+00 W~W 52 L 113 24-06 8/28/2006 Cs-134 -1.OOE-01 1.1011+00 3.90E1+00

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

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

Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2006 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCiIL) (pCi/L) (pCi/L) ww 52 L 11324-06 8/28/2006 Cs-137 -1.80E-01 9.20E-01 3.30E+00 WW 52 Ll11324-06 8/28/2006 Fe-59 -2.OOE+00 2.20E+00 8.l1OE+00 ww 52 Li11324-06 8/28/2006 GROSS BETA 5.80E+00 1.1OE+00 2.80E+00*

ww 52 LI 11324-06 8/28/2006 H-3 3.20E+02 4.0013+02 1.20E+03 ww 52 Li 11324-06 8/28/2006 1-131 3.OOE+00 3.OOE+00 1.OOE+01 ww 52 Ll 11324-06 8/28/2006 Mn-54 -1 .24E+00 9.20E-01 3.40E+00 WW 52 LI11324-06 8/28/2006 Zn-65 -1 .90E+00 2. 1OE+00 7.50E+00 WW 52 LI 11324-06 8/28/2006 Zr-95 3.70E+00 1.90E+00 6.30OE+00

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

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