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ISFSI, Annual Radiological Environmental Operating Report for 2006
	ML071230069
Person / Time
Site:	North Anna
Issue date:	04/25/2007
From:	Stoddard D G; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	07-0297
	Download: ML071230069 (90)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 25, 2007 United States Nuclear Regulatory Commission Serial No. 07-0297 Attention:

Document Control Desk NAPS/JHL Washington, D. C. 20555 Docket Nos. 50-338/339 72-16 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2b, enclosed is the 2006 Annual Radiological Environmental Operating Report.If you have any questions or require additional information, please contact Page Kemp at (540) 894-2295.Very truly yours, D. G. Stoddard Site Vice President Enclosure Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station/J* C550

0 Dominon*M North Anna Power Station 2006 Annual Radiological Environmental Operating Report Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2006 to December 31, 2006 Prepared by Dominion, North Anna Power Station Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2006 to December 31, 2006 Prepared by: George R. Simmons Supervisor Radiological Analysis Dominion North Anna Power Station Reviewed by: Approved by: ch W. Dreyer Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B. Evans, Jr.Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2 Table of Contents 1. EXECU TIVE SU M M A R Y .......................................................................................................

4 2. PRO G RA M D ESCRIPTIO N ......................................................................................................

7 2.1 Introduction

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

7 2.2 Sam pling and A nalysis Program ........................................................................................

8 3. AN ALY TICAL RESULTS ........................................................................................................

22 3.1 Sum m ary of Results......................................................................................................

22 3.2 A nalytical R esults of 2006 REM P Sam ples ...................................................................

32 4. D ISCU SSIO N O F RESULTS ......................................................................

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

59 4.1 G am m a Exposure R ate ...................................................................................................

59 4.2 A irborne G ross Beta ..............................................................................................................

61 4.3 A irborne R adioiodine

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

62 4.4 Air Particulate Gamma ...........

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

62 4.5 A ir Particulate Strontium

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

62 4.6 Soil ........................................................................................................................................

63 4.7 Precipitation

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

63 4.8 Cow M ilk ..............................................................................................................................

63 4.9 Food Products and V egetation

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

64 4.10 W ell W ater ..........................................................................................................................

64 4.11 R iver W ater .........................................................................................................................

64 4.12 Surface W ater ......................................................................................................................

65 4.13 Bottom Sedim ent .................................................................................................................

66 4.14 Shoreline Soil .......................................................................................................................

67 4.15 Fish .....................................................................................................................................

68 5. PRO G RA M EX CEPTIO N S .....................................................................................................

69 RE FERE N CES ....................................................................................................................................

71 A PPEND ICES .....................................................................................................................................

73 A PPEND IX A : LA ND U SE CEN SU S ......................................................................................

74 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS

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

77 APPENDIX C:

SUMMARY

OF GOUNDWATER PROTECTION ANALYSES ..........

85 3

.1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2006 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2b. Radioactivity levels from January 1 through December 31, 2006, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized.

The REMP is designed to confirm that radiological effluent releases are As Low As is Reasonably Achievable (ALARA), no undue environmental effects occur and the health and safety of the public are protected.

The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.Radiation and radioactivity in the environment is monitored within a 25-mile radius of the station. North Anna Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained.

The first type, control samples, are collected from areas* that are beyond the measurable influence of North Anna Power Station or any other nuclear facility.

These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained.

These samples show how much radiation is contributed to the environment by the station.Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.

Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a"pre-operational baseline." Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident or natural variation.

Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and AREVA Environmental Laboratory provided radioanalytical services.Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy.

Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the.minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for 4

radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible.

The NRC also mandates a reporting level for certain radionuclides.

Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, water, aquatic, terrestrial, and direct radiation exposure.

The airborne exposure pathway includes radioactive airborne iodine and particulates, and precipitation.

The 2006 airborne results were similar to previous years. No plant related radioactivity was detected and fallout or natural radioactivity levels remained at levels consistent with past years' results.Water and aquatic exposure pathway samples include surface, river and well water, silt and shoreline sediments, and fish. No plant related isotopes were detected in Lake Anna surface water except for tritium. The average tritium activity in surface water for 2006 was 3625 pCi/liter.

Naturally occurring potassium-40 was detected at average environmental levels. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3283 pCi/liter.

No plant related radioisotopes were detected in well water. This trend is consistent throughout the environmental operational monitoring program. Both silt samples indicated the presence of naturally occurring thorium-228 at levels consistent with the natural background.

Shoreline sediment, which may provide a direct exposure pathway, indicated the presence of Th-228 also at levels consistent with natural levels. Cs-137 was detected in only one sediment sample at 153 pCi/kg. No Cs-137 was detected in shoreline soil. This Cs-137 level is consistent with historic levels. The terrestrial exposure pathway includes milk and food/vegetation products.

Iodine-131 was not detected in any 2006 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident.

No plant related radioisotopes were detected in any milk samples. A ten-year activity trend continues to indicate the slow decrease in Sr-90 activity.

Naturally occurring potassium-40 was detected at evironmental levels consistent with historical data. Cs-137 was detected in one vegetation sample at 88 pCi/kg. This level is consistent with low levels of Cs- 137 detected intermittently in past years. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs).TLD results have remained essentially constant over the years.During 2006, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum dose calculated for a 5

hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2006 was 0.32 millirem.

For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%. These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.S 6

.2. PROGRAM DESCRIPTION

2.1 Introduction

This report documents the 2006 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).The North Anna Power Station of Dominion Virginia Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia.

The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation.

Each unit was designed with a gross electrical output of 979 megawatts electric (MWe). Unit 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as is reasonably achievable (ALARA). To ensure these criteria are met, the operating license for.North Anna Power Station includes Technical Specifications, which address the release of radioactive effluents.

In-plant monitoring is used to ensure release limits are not exceeded.

As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).North Anna Power Station is responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions is responsible for processing the TLDs. AREVA Environmental Laboratory is responsible for sample analyses.

The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations.

Measured values are compared with control levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes.

Data collected prior to station operation is used to indicate the degree of natural variation to be expected.

This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.

Occasional samples of environment media show the presence of man-made isotopes.

As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and 7 W North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2006 and satisfies the following objectives of the program: To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public resulting from station operations.

To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.To identify changes in radioactivity in the environment.

To verify that station operations have no detrimental effect on the health and safety of the public.O 2.2 Sampling and Analysis Program Table 2-1 summarizes the 2006 sampling program for North Anna Power Station.All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." The North Anna Radiological Monitoring Locations maps denote sample locations for North Anna Power Station. The locations are color coded to designate sample types. Table 2-2 summarizes the analysis program conducted by AREVA Environmental Laboratory for North Anna Power Station during the year 2006.Samples of various subsurface waters were taken as part of the Nuclear Energy Institute, NEI, Ground Water Protection Initiative.

The results of these analyses are included in Appendix C of this report as part of that initiative.

S 8

~TABLO-1 North Anna Power Station -2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental NAPS Sewage Treatment Plant 01 Thermoluminescent Fredericks Hall 02 Dosimetry (TLD) Mineral, Va 03 Wares Crossroads 04 Route 752 05 Sturgeon's Creek Marina 05A Levy, VA 06 Bumpass, VA 07 End of Route 685 21 Route 700 22"Aspen Hills" 23 Orange, VA 24 Bearing Cooling Tower N- 1/33 Sturgeon's Creek Marina N-2/34 Parking Lot "C" (on-site)

NNE-3/35 Good Hope Church NNE-4/36 Parking Lot "B" ' NE-5/37 Lake Anna Marina (Bogg's Dr) NE-6/38 Weather Tower Fence ENE-7/39 Route 689 ENE-8/40 Near Training Facility E-9/41"Morning Glory Hill" E- 10/42 Island Dike ESE-1 1/43 Route 622 ESE- 12/44 DVP Biology Lab SE-13/45 Route 701 (Dam Entrance)

SE- 14/46"Aspen Hills" SSE-15/47 Elk Creek SSE-16/48 NAPS Access Rd. S-17/49* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.47 NE SSW WSW WNW NNE N ESE SSE WNW WSW SSE NW N N NNE NNE NE NE ENE ENE E E ESE ESE SE SE SSE SSE S 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Quarterly

& Annually Quarterly

& Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control 9 TAB*- I North Anna Power Station -2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Environmental Thermoluminescent Dosimetry (TLD)Location Elk Creek Church NAPS Access Rd.Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate -Construction Side Station S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 1.55 0.42 5.30 0.6 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.45 2.54 0.07 2.21 7.30 22.00 7.10 11.54 Direction S SSW SSW SW SW WSW WSW W W WNW WNW NW NW NNW NNW SSE NW WSW WSW Degrees 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Laydown Area Lake Anna Campground

1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA Control Control Control Control Airborne Particulate and Radioiodine NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA 01 02 03 04 05 05A 06 07 0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 NE SSW WSW WNW NNE N ESE SSE 420 2030 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.10

~TABLO-1 North Anna Power Station -2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Sample Media Airborne Particulate and Radioiodine Location End of Route 685 Route 700"Aspen Hills" Orange, VA Station 21 22 23 24 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)Precipitation Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)*Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream)

Biology Lab Biology Lab Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream)

Waste Heat Treatment Facility (Second Cooling Lagoon)NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 3.37 SSE 1480 Monthly 09A 11 01A 01A 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE 1380 Monthly Control 08 3.37 SSE 1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually 5.80 SE 1280 Semi-Annually Control 11 Shoreline Soil Soil 08 **3.37 SSE 1480 Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.11 TAB*-1 North Anna Power Station -2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 0 N Sample Media Soil Location Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)"Aspen Hills" Orange, VA Station 05 05A 06 07 21 22 23 24 Distance 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 Direction NNE N ESE SSE WNW WSW SSE NW Degrees 200 110 1150 1670 3010 2420 1580 3250 Collection Frequency Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Remarks Control Milk Holladay Dairy (R.C. Goodwin)Terrell's Dairy (Fredericks Hall)Anderson's Farm Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Orange Fish Food Products (Broadleaf Vegetation)

Bel Aire Plantation 12 13 27 08 25 14 15 16 23 26 8.30 NW 5.60 SSW 2.49 ENE 3.37 SSE 16.5 NW 3100 Monthly 2050 Monthly 660 Monthly 1480 Semi-Annually 3120 Semi-Annually Control 1.20 NE 430 Monthly if available or at harvest 1.37 SE 1330 Monthly if available or at harvest Route 614 Route 629/522 12.60 NW 0.93 SSE Aspen Hills 3140 Monthly if available or at harvest 1580 Monthly if available or at harvest 172 0 Monthly if available or at harvest Control"Historic Lane" 1.15 S* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.12 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)(84 TLDs)(12 TLDs)Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Gamma Dose Gamma Dose 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month 1-131 Weekly Gross Beta Surface Water Quarterly (a)2 nd Quarter Composite Monthly Quarterly(a) 2 nd Quarter Composite Gamma Isotopic Cs- 134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs- 134 Cs-137 Ba-140 La- 140 Tritium (H-3)Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs- 134 Cs-137 Ba-140 La- 140 0.07 0.01 0.05 0.06 (b)(b)l(c)15 30 15 15 30 30 15 15 18 60 15 2000 (b)(b)1(c)15 30 15 15 30 30 15 15 18 60 15 pCi/mr 3 pCi/mi 3 pCi/mr 3 pCi/m 3 pCi/L pCi/L pCi/L pCi/L River Water Monthly pCi/L pCi/L*LLDs indicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

13 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA River Water FREOUENCY Quarterly(a) 2 nd Quarter Composite ANALYSIS Tritium (H-3)Sr-89 Sr-90 Ground Water (Well Water)Quarterly Quarterly(a) 2 nd Quarter Semi-Annually Aquatic Sediment Annually Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs- 134 Cs-137 Ba-140 La- 140 Tritium (H-3)Sr-89 Sr-90 Gamma Isotopic Cs- 134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs- 134 Cs-137 Ba-140 La- 140 Gamma Isotopic Cs- 134 Cs-137 Sr-89 Sr-90 LLD 2000 (b)(b)15 30 15 15 30 30 15 l(c)15 18 60 15 2000 (b)(b)pCi/L pCi/L pCi/L Precipitation Monthly Semi-Annual Composite REPORT UNITS pCi/L pCi/L 150 180 (b)(b)4 15 30 15 15 30 30 15 1(c)15 18 60 15 pCi/kg (dry)pCi/kg (dry)pCi/L pCi/L Shoreline Soil Semi-Annually 150 180 (b)(b)Annually pCi/kg (dry)pCi/kg (dry)Actual analysis of samples may 0*LLDs indicate those levels to which environmental samples are required to be analyzed.be lower than the listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

14 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY Soil Once per 3 years Milk Monthly Monthly Quarterly Fish Semi-Annually.

ANALYSIS LLD Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs- 134 Cs-137 Ba-140 La- 140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs- 134 Cs-137 Gamma Isotopic Cs- 134 Cs-137 1-131 150 180 (b)(b)1 15 18 60 15 (b)(b)130 260 130 130 260 130 150 REPORT UNITS pCi/kg (dry)pCi/kg (dry)pCi/L pCi/L pCi/kg (wet)Food Products (Broadleaf Vegetation)

Monthly if available or at harvest pCi/kg (wet)60 80 60 0*LLDs indicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

15 Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation 1 1A 2 3 4 5 5A 6 7 8 9A S 11 12 13 14 15 16 21 22 23 24 25 26 (a) 01,NE-5/37 01A,SE-13/45 (a) 02,SSW-20/52 (a) 03,C-5/6 (a) 04 (a) 05 (a) 05A,N-2/34 (a) 06,ESE-12/44 (a) 07,C-1/2 08-Water, Fish Sediment, Shoreline Soil 09A-Water sample, sediment 11-River Water, Sediment 12-Milk 13-Milk 14-Vegetation, NE-6/38 Vegetation Vegetation (a) 21,WNW-27/59 (a) 22,WSW-24/56 (a) 23-SSE-15/47 (a)(b) 24,C-3/4 (c) 25-Fish 26-Vegetation 27 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 Environmental Station 27-Milk C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE- 11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E- 10/42 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.(b) In Orange (c) In Lake Orange 16 0 oaf, 10, ESE Legend*1LD LOCgOM SCOR -WOS kch -235 IL Fgr1. Nort Anna S+/- 1BiteC Radoloica Moiorn Loain 17 0"W~O 1991 tblADC OfA*mmwft ft, 6"D GKO" ~uf Way AIfiAEW. A22312 USED WIThPOR99SOWP~

NCOPWMVCMW~

m-9W 1A ~ ~ ncAC C402M0 18 0 *i Anna Environmental Map.TLD Smln* N~tMResGadent

~~il ' MatAnial 0Norff. ia AnnaA Env~bir ~onmna MapD C632M 19 North Anna Environmental Map.Fixed Environmental Sampling Location O TLD Sampling*Garden Residents Meat Animals 00"0w 1931 OyAD MOANZW&U.

ft., UM4 GWJJ Gr~W4)JýAW~nd& 'A22312.USeD VMtPMA~SSaXft 140 Ieu Ad*M Pbt imio 14lftod wUft pwmnbi0 @IAM.as=20 0 C612=0 21

3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM.A more detailed analysis of the data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries.

22 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 1 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-Type No. ____ Range Direction Range Range ments Air Iodine 1-131 624 0.07 (0/572) N/A N/A N/A (0/52) 0 (pCi/m 3)Airborne Particulates (1E-03 pCi/m 3)Gross Beta 624 0.01 24.9(572/572)

(9.0-55.5) 01 0.20 mi. 29.6(52/52) 25.7(52/52)

NE (12.2-55.5)

(13.4-46.7) 0 Gamma 48 Be-7 48 131.7 (44/44)(40-200)01 0.20 mi. 155.5(4/4) 127(4/4)NE (110-200)

(92-142)Cs-134 48 0.05 Cs-137 48 0.06 Sr-89 12 -Sr-90 12 -Tritium 4 2000 (0/44)(0/44)(0/11)(0/11)(0/4)N/A N/A N/A N/A N/A N/A N/A N/A 01A 0.75 mi.SE N/A N/A N/A N/A N/A (0/4)(0/4)(0/1)(0/1)N/A 0 0 0 0 0 0 Ground Well Water (pCi/liter)

Gamma 4 Mn-54 4 15 (0/4)Fe-59 4 30 (0/4)Co-58 4 15 (0/4)Co-60 4 15 (0/4)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 s 23 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 2 of 9 All Indicator Control Non-Medium or Ana is Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-__Type I No. I Range Direction Range Range ments Ground Well Water (pCi/liter)

River Water (pCi/liter)

Zn-65 4 30 (0/4)Zr-95 4 30 (0/4)Nb-95 4 15 (0/4)1-131 4 10 (0/4)Cs-134 4 15 (0/4)Cs-137 4 18 (0/4)Ba-140 4 60 (0/4)La-140 4 15 (0/4)Sr-89 1 -(0/1)Sr-90 1 -(0/1)Tritium 4 2000 3283(4/4)(2130-4300)

Gamma 12 Mn-54 12 15 (0/12)Fe-59 12 30 (0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 11 5.80 mi. 3283(4/4)SE (2130-4300) 0 N/A N/A N/A N/A N/A N/A N/A N/A 0 0 24 t_TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 3 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-Type I _No. Range Direction Range Range ments River Water (pCi/liter)

Surface Water (pCi/liter)

Co-58 12 15 (0/12)Co-60 12 15 (0/12)Zn-65 12 30 (0/12)Zr-95 12 30 (0/12)Nb-95 12 15 (0/12)1-131 12 1 (0/12)Cs-134 12 15 (0/12)Cs-137 12 18 (0/12)Ba-140 12 60 (0/12)La-140 12 15 (0/12)Sr-89 1 -(0/1)Sr-90 1 -(0/1)Tritium 8 2000 3625(4/4 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4).08 3.37 mi. 3625(4/4)0 (2900-4100)

SSE (2900-4100)

Gamma 24 25 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 4 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-Type I No. Range Direction Range Range ments Surface Water Mn-54 24 15 (pCi/liter)

Fe-59 24 30 Co-58 24 15 Co-60 24 15 Zn-65 24 30 Zr-95 24 30 Nb-95 24 15 1-131 24 1 Cs-134 24 15 Cs-137 24 18 Ba-140 24 60 La-140 24 15 Sr-89 1 -(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/1)(0/1)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/1)N/A N/A N/A N/A N/A N/A 0 0 0 Sr-90 1 (0/1)26 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 5 of 9 All Indicator Control Non-Medium or [ nalsis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pL/unit)

Mean Name Distance Mean Mean Measure-Type o. I [ Range Direction Range Range ments Precipitation (pCi/liter)

Monthly Gross 10 Beta Semiannually Gamma 2 Mn-54 2 Fe-59 2 Co-58 2 Co-60 2 Zn-65 2 Zr-95 2 Nb-95 2 1-131 2 Cs-134 2 Cs-137 2 4 7.1(9/12)(3.3-13.4) 01A 0.75 mi.SE 15 30 15 15 30 30 15 10 15 18 (0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 7.1(9/12)(3.3-13.4)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/0)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Ba-140 2 60 (0/2)N/A N/A N/A 0 27 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 6 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-__Type No. Range I Direction Range Range ments La-140 2 15 (0/2)N/A N/A N/A N/A 0 Precipitation (pCi/liter)

Sediment Silt (pCi/kg) (dry)Gamma 6 K-40 6-12178(4/4)

(3010-16200)11 5.80 mi. 14900(2/2)

SSE (13600-16200)9515(2/2)(7200-11830) 0 Cs-134 6 150 (0/4)N/A N/A N/A (0/2)(0/2)Cs-137 6 180 153(1/4)(153)08 3.37 mi. 153(1/2)SSE (153)Th-228 6 Sr-89 3 (Annually)

Sr-90 3 (Annually) 1208(4/4)(370-1880)

(0/2)(0/2)11 5.80 mi. 1290(2/2) 505(2/2)SSE (1230-1350)

(420-590)0 0 0 0 0 N/A N/A N/A N/A N/A N/A (0/1)(0/1)Soil (pCi/Kg) (dry)Triennial Gamma 12 Soil samples not required in 2006 Cs-134 12 Cs-137 12 Th-228 12 Sr-89 12 Sr-90 12 150 180 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 28 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 7 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-Type No. I Range Direction Range Range ments Shoreline Soil (pCi/kg) (dry)Gamma K-40 Th-228 Cs-134 Cs-137 Sr-89 (Annually)

Sr-90 (Annually)

Gamma K-40 1-131 Cs-134 Cs-137 Ba-140 2 2 2 2 2 1 1 24 24 24 24 24 24 5055(2/2)(2200-7910)

-1210(1/2)(1210)150 (0/2)180 (0/2)(N/A)-(0/1)-(0/1)8 8 N/A N/A N/A N/A 12 N/A N/A N/A N/A 3.37 mi.SSE 3.37 mi.SSE N/A N/A N/A N/A 5055(2/2)(2200-7910) 1210(1/2)(1210)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Milk (pCi/liter) 1 15 18 60 1355(24/24)

(1210-1440)

(0/24)(0/24)(0/24)(0/24)8.3 mi.NW N/A N/A N/A N/A 1357(12/12)

(1230-1430)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 29 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 8 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pah/uwit)

Mean Name Distance Mean Mean Measure-Type No. I Range Direction Range Range ments Milk (pCi/liter)

La-140 24 15 (0/24)N/A N/A N/A N/A 0 Fish (pCi/kg) (wet)Sr-89 (Quarterly)

Sr-90 (Quarterly)

Gamma K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs- 134 Cs-137 (0/8)(0/8)130 260 130 130 260 130 150 1313(4/4)(1010-1460)

(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)N/A N/A 08 N/A N/A N/A N/A N/A N/A N/A N/A N/A 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A N/A N/A 1313(4/4)(1010-1460)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 1773(4/4)(1460-2050)

(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0 30 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2006 Docket No. 50-338/339 Page 9 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (PC/unit)

Mean Name Distance Mean Mean Measure-Type INo. Range Direction Range Range ments Food Vegetation (pCi/kg) (wet)Gamma 20 Be-7 20 K-40 20-2510(23/24)

(550-8030)

-12583(24/24)

(2870-27700) 14 varies 3102(6/6)NE (910-7180) 2758(5/6)(970-6670) 14 varies 3102(6/6) 2758(5/6)NE (910-7180)

(970-6670) 1-131 20 60 (0/24)Cs- 134 20 60 (0/24)Cs-137 20 80 88(1/24)(88)N/A N/A N/A N/A N/A N/A 15 varies 88(1/6)SE (88)26 varies 294(2/6)S (147-440)23 0.93 mi. 5.6(4/4)SSE (5.1-6.1)(0/6)(0/6)(0/6)(0/6)0 0 0 0 0 0 0 Th-228 20 267(4/24)(147-440)Direct Radiation (mR/std. month)(Environmental TLDs)Direct Radiation (mR/std. Month)(Annual TLDs)Direct Radiation (mR/std. Month)(Sector TLDs)Gamma Dose 48 2 3.8(44/44)

(2.3-6.1)3.5(4/4)(3.1-4.6)Gamma 12 Dose 2 3.4(11/11)

(1.9-5.1)23 0.93 mi. 5.1(1/1)SSE (5.1)3.6(1/1)(3.6)0 Gamma 256 Dose 2 5.5(256/256) 19/51"') 0.42 mi.(1.6-38.3)

SSW 27.8(8/8)(16.0-38.3) 3.4(32/32)

(1.9-4.8)0 (1) 19/51 located onsite near ISFSI.31

3.2 Analytical

Results of 2006 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.The data reported in the following tables are strictly counting statistics.

The reported error is two times the standard deviation (2a) of the net activity.

Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2y error (i.e., the measured value exceeds 3cy).Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For the purposes of this report all valid data are presented in order to indicate any background biases. AREVA Environmental Laboratory's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the North Anna ODCM.Data are given according to sample type as indicated below.1. Gamma Exposure Rate 2. Air Particulates, Gross Beta Radioactivity

3. Air Particulates, Weekly 1-131 4. Air Particulates, Quantitative Gamma Spectra 5. Air Particulate Strontium 6. Soil 7. Precipitation

8. Cow Milk 9. Food Products and Vegetation

10. Well Water 11. River Water 12. Surface Water 13. Bottom Sediment/Silt

14. Shoreline Soil 15. Fish Analytical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).32 VTABLE #3-2'DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 1 of 4 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly 01/05/2006 04/06/2006 06/29/2006 09/28/2006 Average 04/06/2006 06/29/2006 09/28/2006 01/05/2007 N-1 5.4 4.0 4.3 4.5 4.6 +/- 1.2 N-33 5.7 5.2 4.4 5.8 5.3 +/- 1.3 N-2 4.0 3.4 3.1 3.7 3.6 +/- 0.8 N-34 3.7 2.7 3.1 4.5 3.5 +/- 1.6 NNE-3 7.3 6.9 5.5 8.8 7.1 +/-2.7 NNE-35 7.1 5.7 7.6 8.6 7.3 2.4 NNE-4 4.9 4.4 4.6 5.4 4.8 _ 0.9 NNE 36 4.5 4.5 4.9 5.4 4.8 +/- 0.9 NE-5 6.2 4.9 4.1 4.6 5.0 1.8 NE-37 5.9 4.8 3.1 6.2 5.0 +/- 2.8 NE-6 3.6 4.0 3.7 4.1 3.9 _ 0.5 NE-38 3.9 2.8 3.4 4.2 3.6 _ 1.2.ENE-7 4.9 4.6 5.6 7.2 5.6 +/- 2.3 ENE-39 5.1 4.1 4.9 6.9 5.3 _ 2.4 ENE-8 4.7 3.4 3.2 3.1 3.6 1.5 ENE-40 3.4 3.3 3.3 4.0 3.5 +/- 0.7 E-9 5.9 4.9 4.4 6.2 5.4 +/- 1.7 E-41 5.9 4.8 5.1 6.0 5.5 +/- 1.2 E-10 6.1 4.7 4.2 4.9 5.0 1.6 E-42 5.0 4.6 5.3 5.6 5.1 +/- 0.9 ESE-1 1 4.4 4.2 4.3 5.0 4.5 +/- 0.7 ESE-43 4.6 4.1 4.2 5.7 4.7 +/- 1.5 ESE-12 6.4 4.7 4.8 5.4 5.3 +/- 1.6 ESE-44 4.6 4.6 4.4 5.6 4.8 +/- 1.1 SE-13 4.9 3.7 4.6 4.9 4.5 +/- 1.1 SE-45 5.4 4.4 4.3 5.7 5.0 +/- 1.4 SE-14 7.8 7.0 6.1 7.4 7.1 +/- 1.5 SE-46 6.7 6.5 6.8 8.0 7.0 +/- 1.4 SSE-1 5 5.7 5.2 5.2 6.5 5.7 +/- 1.2 SSE-47 5.5 5.1 5.3 6.4 5.6 +/- 1.1 SSE-16 4.3 3.4 2.1 3.7 3.4 +/- 1.9 A SSE-48 3.4 3.2 3.0 3.8 3.4 +/- 0.7 33 WTABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mRPStd. Month (30.4 days) +/-2 Sigma Page 2 of 4 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly 01/05/2006 04/06/2006 06/29/2006 09/28/2006 Average 04/06/2006 06/29/2006 09/28/2006 01/05/2007 S-17 8.6 7.1 7.5 8.3 7.9 +/- 1.4 S-49 7.6 7.4, 7.1 8.8 7.7 +/- 1.5 S-18 3.3 2.0 2.4 3.0 2.7 +/- 1.2 S-50 3.4 2.6 2.6 2.9 2.9 +/- 0.8 SSW-19 21.8 36.8 27.9 22.3 27.2 +/- 13.9 SSW-51 21.9 16.0 37.3 38.3 28.4 +/- 22.3 SSW-20 2.8 2.7 2.4 2.4 2.6 +/- 0.4 SSW-52 3.3 2.6 2.4 3.3 2.9 +/- 0.9 SW-21 5.6 3.8 5.0 6.4 5.2 +/- 2.2 SW-53 6.3 4.6 4.4 6.1 5.4 +/- 2.0 SW-22 5.0 4.5 3.9 5.5 4.7 +/- 1.4 SW-54 4.7 4.8 4.6 5.2 4.8 +/- 0.5.WSW-23 5.3 5.7 4.5 5.3 5.2 +/- 1.0 WSW-55 6.0 5.6 5.5 6.9 6.0 +/- 1.3 WSW-24 4.9 4.7 4.7 5.4 4.9 +/- 0.7 WSW-56 5.0 4.6 4.5 5.8 5.0 +/- 1.2 W-25 7.4 6.8 5.7 8.6 7.1 +/- 2.4 W-57 7.3 6.0 6.6 9.2 7.3 +/- 2.8 W-26 3.4 3.2 3.1 3.6 3.3 +/- 0.4 W-58 2.7 2.3 2.3 3.9 2.8 +/- 1.5 WNW-27 3.1 3.3 3.7 3.7 3.5 +/- 0.6 WNW-59 3.3 2.5 3.4 3.5 3.2 +/- 0.9 WNW-28 3.2 3.1 3.2 3.6 3.3 +/- 0.4 WNW-60 3.0 3.3 3.2 3.8 3.3 +/- 0.7 NW-29 7.2 6.6 5.8 7.5 6.8 +/- 1.5 NW-61 6.9 6.1 6.4 7.8 6.8 +/- 1.5 NW-30 2.3 2.4 1.6 2.9 2.3 +/- 1.1 NW-62 2.5 1.8 2.3 3.0 2.4 +/- 1.0 NNW-31 4.4 2.8 2.7 4.3 3.6 +/- 1.9 NNW-63 4.6 2.8 3.8 4.8 4.0 +/- 1.8 NNW-32 4.7 4.1 3.9 4.7 4.4 +/- 0.8 NNW-64 4.0 3.9 4.2 4.8 4.2 +/- 0.8 34 TABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/-2 Sigma Page 3 of 4 Station Name C-1 C-2 C-3 C-4 C-5 C-6 C-7 C-8 First Quarter 01/05/2006 04/06/2006 3.3 3.0 3.6 3.8 2.9 2.2 3.7 4.3 Second Quarter 04/06/2006 06/29/2006 3.1 3.4 3.4 2.6 1.9 2.6 4.0 4.0 Third Quarter 06/29/2006 09/28/2006 3.5 3.1 3.3 3.3 2.4 2.6 3.6 3.7 Fourth Quarter 09/28/2006 01/05/2007 4.1 4.0 3.9 3.9 3.0 3.5 4.8 4.7 Quarterly Average EPSA-01**

5.1 3.8 EPSA-02**

5.6 4.0 EPSF-03**

5.3 4.8 EPSF-04**

5.2 4.3 EPSR-05**

5.2 4.7 EPSR-06**

5.0 4.8 EPSJ-07**

4.1 4.1 EPSJ-08**

4.3 3.2 EPSP-09**

8.5 7.7 EPSP-10**

8.3 7.7** Emergency Plan TLDs. Included for informational purposes only.4.9 4.9 4.6 4.6 5.1 3.8 4.2 3.6 7.4 7.5 6.5 6.4 6.1 5.7 5.8 5.8 4.9 5.1 9.4 9.1 3.5 3.4 3.6 3.4 2.6 2.7 4.0 4.2 5.1 5.2 5.2 5.0 5.2 4.9 4.3 4.1 8.3 8.2 0.9 0.9 0.5 1.2 1.0 1.1 1.1 0.9 2.2 2.0 1.3 1.2 0.9 1.6 0.8 1.7 1.8 1.4 35 TABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/-2 Sigma Page 4 of 4 Station Name STA-01 STA-02 STA-03 STA-04 STA-05 STA-05A STA-06 STA-07 STA-21 STA-22 STA-23 STA-24 First Quarter 01/05/2006 04/06/2006 4.9 2.4 2.6 2.8 3.7 3.6 5.1 3.6 3.3 4.6 5.7 3.2 Second Quarter 04/06/2006 06/29/2006 4.0 2.5 2.3 2.7 3.2 2.4 4.6 3.2 3.1 5.0 5.1 3.2 Third Quarter 06/29/2006 09/28/2006 3.9 3.0 2.5 2.6 3.6 2.6 4.2 3.7 3.2 4.6 5.3 3.1 Fourth Quarter 09/28/2006 01/05/2007 4.1 3.3 3.0 3.0 3.9 4.4 5.1 4.1 3.9 5.3 6.1 4.6 Quarterly Average 4.2 +/- 0.9 2.8 +/- 0.8 2.6 +/- 0.6 2.8 +/- 0.3 3.6 +/- 0.6 3.3 +/- 1.9 4.8 +/- 0.9 3.7 +/- 0.7 3.4 +/- 0.7 4.9 +/- 0.7 5.6 +/- 0.9 3.5 +/- 1.4 3.7 +/- 1.7 AnnualTLD 3.7 2.1 2.0 1.9 3.6 2.6 4.6 3.5 3.3 4.7 5.1 3.6 3.4 +/-2.2 Average +/- 2 s.d.3.8 +/- 2.1 3.4 +/- 2.0 3.5 +/- 1.7 4.2 +/- 1.9 36 0 41 Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi x 1 0 3/m3]Period Ending 01/04/06 01/11/06 01/18/06 01/25/06 02/01/06 02/08/06 02/15/06 02/22/06 03/01/06 03/08/06 03/16/06 03/22/06 03/29/06 04/05/06 04/12/06 04/19/06 04/26/06 05/04/06 05/11/06 05/17/06 05/25/06 05/31/06 06/07/06 06/14/06 06/21/06 06/28/06 Station 01L 20.2 +-4.6 19.1 +-4.4 17.1 +-2.3 14.6 +-4.1 21.8 +-4.3 22.7 +-4.3 25.3 +-4.7 27.0 +-4.8 29.4 +-4.7 25.3 +-4.7 25.3 +-3.9 23.2 +-5.1 12.2 +-4.1 28.4 +-4.5 16.3 +-5.1 29.5 +-5.7 25.9 +-5.9 25.1 +-3.8 24.5 +-5.6 15.1 +-4.5 25.1 +-2.8 35.2 +-7.1 31.6 +-6.2 29.3 +-6.1 31.7 +-5.7 24.9 +-5.4 Station 02~19.0 +/21.6 +/12.8 +-11.4 +/15.4 +/18.6 +-20.2 +/26.2 +/9.7 +/-0.1 +/0.9 +-25.4 +/11.0 +-22.9 +/15.4 +-22.6 +/19.5 +/20.4 +/19.1 +/15.1 +/20.0 +/34.7 +/27.1 +/24.5 +/28.5 +/18.6 +/4.6 4.5 2.2 3.8 3.9 4.2 4.4 4.8 3.6 3.3 2.3 5.3 4.0 4.3 3.9 4.3 4.4 2.9 4.3 3.4 2.1 5.9 4.8 4.7 5.4 4.4 Station 13.3 +/23.9 +/18.9 +/9.0 +/22.5 +/24.3 +/20.2 +/26.4 +/29.4 +/13.0 +/24.3 +/20.4 +/11.0 +/11.3 +/23.3 +/20.8 +/18.5 +/21.4 +/16.7 +/14.2 +/18.3 +/33.0 +/28.1 +/23.3 +/27.2 +/22.5 4.2 4.7 2.4 3.6 4.4 4.4 4.4 4.8 4.7 4.1 3.9 5.0 4.0 3.6 4.3 4.2 4.4 2.9 4.2 3.4 2.1 5.6 4.8 4.6 4.5 4.5 Station 042 22.2 +-4.6 22.0 +- 4.5 18.2 +-2.4 16.3 +-4.1 21.1 +-4.3 24.5 +-4.4 27.2 +-4.8 27.6 +- 4.8 24.5 +-4.5 16.6 +-4.3 22.6 +- 3.9 29.0 +- 5.5 11.1 +- 4.1 25.8 -i- 4.4 16.2 +- 3.9 22.0 +-4.3 18.4 +-4.4 18.5 +-2.8 20.1 +- 4.3 13.1 +- 3.4 17.5 +-2.0 30.7 +- 5.5 25.1 +- 4.7 20.3 +-4.4 17.5 +- 3.9 18.9 +-4.4 Station 25.6 +-4.8 25.0 +-4.7 17.6 +-2.4 17.9 +- 4.2 20.0 +- 4.2 25.8 +- 4.5 20.0 +- 4.5 32.3 +- 5.1 36.2 +- 5.0 21.4 +-4.6 24.1 +-3.9 29.3 +-5.5 13.9 +-4.2 27.7 +-4.5 21.7 +-4.2 20.4 +- 4.2 18.7 +-4.4 19.4 +- 2.9 16.3 +- 4.2 16.1 +- 3.4 17.0 +- 2.0 29.6 +- 5.4 19.9 +-4.4 20.0 +-4.5 20.8 +-4.1 20.7 +-4.3 Station 21.5 +/23.6 +/16.5 +/16.9 +/21.5 +/22.6 +/15.8 +/30.9 +/28.6 +/20.1 +/22.4 +/17.4 +/12.0 +/23.4 +/20.7 +/20.7 +/18.3 +/16.2 +/17.2 +/10.9 +/19.0 +/37.1 +/23.0 +/23.9 +/24.1 +/18.6 +-4.6 4.6 2.4 4.2 4.3 4.3 4.2 5.0 4.7 4.5 3.8 4.8 4.1 4.4 4.1 4.2 4.4 3.7 4.3 4.2 4.8 5.8 4.6 4.7 4.3 4.2 Station 20.9 +/25.4 +/16.2 +/11.7 +/20.8 +/24.3 ,/22.9 +/25.5 +/26.9 +/15.6 +/23.5 +/22.2 +/9.0 +/22.4 +/22.5 +/18.8 +/15.0 +/16.4 +/19.1 +/13.1 +/16.0 +/30.0 +/20.8 +/20.0 +/23.1 +/16.7 +/I 4.5 4.7 2.4 3.8 4.3 4.4 4.6 4.8 4.6 4.3 3.9 5.1 3.9 4.2 4.3 4.1 4.2 2.8 4.3 3.4 2.0 5.5 4.4 4.5 4.2 4.1 37 e Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi x 10-3/m3]0 Period Ending 01/04/06 01/11/06 01/18/06 01/25/06 02/01/06 02/08/06 02/15/06 02/22/06 03/01/06 03/08/06 03/16/06 03/22/06 03/29/06 04/05/06 04/12/06 04/19/06 04/26/06 05/04/06 05/11/06*05/17/06 05/25/06 05/31/06 06/07/06 06/14/06 06/21/06 06/28/06 Station L07 20.3 +-4.6 19.8 +-4.4 13.8 +-2.3 11.2 +-3.8 16.3 +- 4.0 19.4 +- 4.2 19.2 +- 4.3 21.2 +- 4.6 25.4 +-4.6 18.0 +-4.4 19.2 +-3.6 20.3 +-5.0 8.9 +-3.9 18.1 +-4.0 15.3 +-3.8 14.9 +- 3.8 16.3 +- 4.2 16.7 +- 2.8 11.0 +- 3.8 9.8 +A 3.2 14.5 +- 1.9 28.5 +-5.4 13.2 +-4.1 15.3 +-4.2 16.3 +-3.8 14.7 +-4.0 Station 21L 18.9 +-4.5 19.7 +-4.4 31.0 +/-6.8 14.6 ./- 4.0.20.4 +-4.3 16.8 +-4.0 22.8 +-4.6 28.7 +-4.9 29.4 +-4.7 18.5 +-4.4 23.4 +-3.9 24.5 +-5.2 11.2 +-4.1 22.8 +-4.3 21.9 +-4.4 18.5 +-4.1 18.3 +-4.4 15.9 +-2.7 16.5 +-4.1 14.3 +-3.5 14.8 +-2.0 32.1 +-5.6 23.4 +-4.6 16.0 +-4.2 20.5 +-4.1 17.9 +-4.2 Station 20.9 +/21.2 +/15.0 +/15.2 +-19.3 +/21.0 +/22.4 +/29.7 +/32.4 +/21.9 +/24.6 +/22.5 +/15.0 +/25.2 +/25.2 +/20.0 +/14.9 +/22.4 +/13.5 +/14.5 +/17.0 +/37.2 +/20.8 +/19.1 +/24.3 +/Station 4.6 4.5 2.3 4.1 4.2 4.2 4.5 4.9 4.9 4.6 3.9 5.1 4.2 4.4 4.4 4.1 4.2 3.0 3.9 3.5 2.0 5.8 4.4 4.4 4.3 15.9 +/22.6 +/18.9 +/14.9 +/17.4 +/20.2 +/18.2 +-23.4 +/32.3 +/21.1 +/23.5 +/20.2 +/12.3 +/.21.5 +/14.8 +/23.6 +/21.3 +/20.0 +/13.3 +-13.3 +-18.1 +-34.3 +/30.2 +/21.5 +/14.0 +/4.5 4.6 2.4 4.1 4.0 4.1 4.3 4.7 4.9 4.5 3.9 5.0 4.1 4.2 3.8 4.3 4.5ý2.9 4.0 3.3 2.1 5.7 4.9 4.6 3.7 Station 23.2 +- 4.7 20.1 +- 4.4 21.4 +- 2.5 14.3 +- 4.0 20.5 +- 4.3 19.6 +- 4.1 23.7 +- 4.6 31.7 +- 5.1 31.2 +- 4.8 18.5 +- 4.4 27.2 +- 4.1 21.7 +- 5.0 13.4 +- 4.2 23.4 +- 4.3 15.1 +- 3.9 16.0 +- 3.9 17.1 +- 4.3 23.9 +- 3.3 15.4 -+- 4.5 16.0 44- 3.1 18.4 +- 2.1 33.4 +- 5.6 14.7 +- 4.2 17.5 +- 4.3 22.9 +-4.2 I 21.5 +/- 4.3 20.8 +/- 4.4 18.3 +/- 4.2* Station 24 collected on 05/10/06 38 Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi x 10-3/m3]Period Station Station Station Stato Station Station Station Ending 01 02 03 041 05 05A 06 07/05/06 43.2 +-6.7 37.3 +- 5.4 35.5 +-5.3 30.3 +- 5.1 29.7 +- 5.1 33.4 +- 5.2 22.1 +- 4.7 07/12/06 30.5 +- 6.3 23.7 +-4.7 22.5 +- 4.5 24.6 +- 4.6 22.1 +- 4.6 27.1 +- 4.8 22.3 +- 4.5 07/19/06 34.6 +- 6.3 33.2 +-5.1 28.6 +- 4.9 25.4 +- 4.7 28.4 +- 4.9 28.6 +- 4.8 23.5 +- 4.6 07/26/06 19.5 +- 5.8 22.6 +-4.7 21.6 +-4.7 21.8 +- 4.8 22.7 +-4.8 19.0 +- 4.6 12.1 +- 4.2 08/02/06 46.3 +-7.0 37.3 +-5.3 37.7 +-5.3 36.7 +- 5.3 37.1 +- 5.3 36.6 +- 5.3 34.1 +- 5.1 08/09/06 53.2 +- 6.8 37.7 +-5.1 42.4 1-5.3 30.1 +- 4.7 37.7 +- 5.1 39.6 +- 5.1 38.1 +- 5.1 08/16/06 36.5 +-6.1 24.8 +-4.5 27.8 +-4.6 29.5 +- 4.7 20.6 +- 4.3 28.5 +- 4.7 29.2 +- 4.8 08/23/06 30.9 +-6.1 24.3 +- 4.7 30.0 +-5.0 27.3 +- 4.8 22.2 +- 4.6 27.9 +- 4.8 23.4 +- 4.6 08/30/06 47.8 +- 7.1 40.0 +- 5.5 45.6 +- 5.7 39.7 +- 5.5 31.3 +- 5.1 44.5 +- 5.7 41.4 +- 5.5 09/06/06 14.7 +- 5.1 10.8 +- 3.8 7.7 +- 3.6 9.7 +- 3.8 10.5 +- 3.8 11.4 +- 3.9 7.5 +- 3.5 09/13/06 55.5 +- 7.3 32.6 +- 5.2 28.8 +- 4.9 31.2 +- 5.0 37.9 +- 5.3 32.1 +- 5.1 30.6 +- 5.0 09/20/06 23.4 +- 4.5 24.8 +- 4.6 17.0 +- 4.2 26.7 +- 4.7 18.1 +- 4.3 21.0 +- 4.4 15.6 +- 4.2 09/27/06 24.3 +- 4.7 25.8 +- 4.8. 19.7 +- 4.5 26.7 +- 4.9 22.1 +- 4.7 24.7 +- 4.8 18.4 +- 4.5 10/04/06 38.2 +- 5.3 26.7 +- 4.8 23.8 +- 4.6 34.1 +- 5.1 26.6 +- 4.7 23.5 +- 4.6 25.6 +- 4.7 10/11/06 35.7 +- 5.1 26.1 +- 4.6 22.9 +- 4.6 30.3 +- 4.9 26.2 +- 4.7 29.3 +- 4.8 26.5 +- 4.7 10/18/06 37.5 +- 4.9 29.9 +- 4.7 29.2 +- 4.6 38.8 +- 5.0 28.5 +- 4.6 33.2 +- 4.9 38.5 +- 5.1 10/26/06 24.5 +- 4.2 25.0 +- 4.2 20.4 +- 4.0 28.6 +- 4.4 22.1 +- 4.1 22.3 +- 4.1 23.9 +- 4.2 11/01/06 27.1 +- 5.4 29.3 +- 5.5 26.8 +- 5.3 31.6 +- 5.6 30.2 +- 5.5 31.2 +- 5.5 31.2 +- 5.5 11/09/06 32.2 +- 4.4 29.4 +- 4.2 19.7 +- 3.7 22.1 +- 3.9 28.1 +- 4.1 23.9 +- 3.9 27.1 +- 4.1 11/15/06 29.5 +- 5.4 27.4 +- 5.3 29.9 +- 5.5 24.7 +- 5.2 26.6 +- 5.2 27.9 +- 5.3 23.6 +- 5.1 11/21/06 28.8 +- 5.5 27.4 +- 5.4 30.0 +- 5.5 22.4 +- 5.1 25.0 +- 5.3 27.6 +- 5.5 29.6 +- 5.5 11/29/06 34.9 +- 4.8 27.7 +- 4.5 22.4 +- 4.2 32.5 +- 4.7 32.6 +- 4.6 30.6 +- 4.6 32.3 +- 4.6 12/07/06 47.4 _+- 5.3 40.5 +- 5.0 36.2 +- 4.8 42.6 +- 5.1 40.0 +- 5.0 32.5 +- 4.7 45.5 +/.5.2 12/13/06 45.9 +- 6.4 41.4 +- 6.1 46.3 +- 6.4 47.4 +- 6.4 34.3 +- 5.8 39.2 +- 6.0 42.2 +- 6.2 12/20/06 43.5 +- 5.5 43.9 +- 5.4 40.1 +- 5.4 44.4 +- 5.5 39.9 +- 5.3 36.5 +- 5.2 39.5 +- 5.3 12/27/06 29.9 +- 5.1 27.1 +- 5.0 26.0 +- 4.9 26.3 +- 5.0 20.6 +- 4.7 25.3 +- 4.9 28.4 +- 5.0 39 Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi x 10-3/m3]Period Station Station Station Station 24aio 07/05/06 27.2 +- 4.9 30.2 +- 5.1 30.8 +- 5.1 27.1 +- 5.0 33.6 +- 5.3 07/12/06 19.1 -I- 4.4 24.5 +- 4.5 22.9 +- 4.7 18.8 +- 4.4 24.1 +- 4.6 07119/06 23.5 +- 4.6 24.5 +- 4.9 27.9 4.8 25.5 +- 4.7 29.5 1- 4.9 07/26/06 23.9 +- 4.8 19.0 +- 4.6 26.0 +- 4.9 24.0 +- 4.8 20.6 +- 4.7 08/02/06 26.4 +- 4.8 39.7 +- 5.4 35.6 +- 5.2 37.2 +- 5.3 36.9 +- 5.3 08/09/06 30.4 +- 4.7 33.3 +- 4.8 37.6 +- 5.0 37.2 +- 5.1 33.8 +- 4.8 08/16/06 21.7 +- 4.3 28.5 +- 4.7 24.6 +- 4.5 34.1 +- 4.9 31.9 +- 4.8 08/23/06 21.3 +- 4.5 22.6 +- 4.6 28.5 +- 5.0 22.7 +- 4.6 14.0 -I- 4.1 08/30/06 25.8 +- 4.9 41.0 +- 5.5 46.6 +- 5.7 44.8 +- 5.7 46.7 +- 5.8 09/06/06 7.2 +- 3.6 8.8 +- 3.7 10.4 +- 3.8 9.8 +- 3.7 10.4 +- 3.8 09/13/06 32.4 -/- 5.2 30.2 +- 5.0 34.2 +- 5.2 35.6 +- 5.3 40.1 +- 5.4 09/20/06 27.8 +- 4.7 22.6 +- 4.5 20.7 +- 4.4 22.4 +- 4.5 23.3 +- 4.5 09/27/06 24.0 +- 4.8 24.0 +- 4.8 30.4 +- 5.1 22.2 +- 4.7 23.9 +- 4.7 10/04/06 33.6 +- 5.1 30.0 +- 4.9 27.1 +- 4.8 27.2 +- 4.8 27.1 +- 4.7 10/11/06 28.2 +- 4.7 26.6 +- 4.7 26.3 +- 4.7 34.2 +- 4.9 31.9 +- 5.0 10/18/06 37.8 +- 5.1 31.4 +- 4.7 34.8 +- 4.9 32.9 +- 4.9 39.0 +- 5.1 10/26/05 23.8 +- 4.2 20.0 +- 4.0 20.7 +- 4.0 18.5 +- 3.9 23.6 +- 4.2 11/01/06 29.3 +- 5.4 28.2 +- 5.4 27.8 +- 5.4 35.1 +- 5.7 29.1 +- 5.4 11/09/06 29.2 +1- 4.2 26.5 +- 4.1 24.5 +1- 4.0 26.3 +- 4.1 26.0 +1.4.1 11/15/06 27.3 +- 5.3 23.1 +- 5.0 18.9 +- 4.8 26.6 +- 5.2 27.8 +- 5.3 11/21/06 26.6 +- 5.3 18.7 +- 5.0 25.8 +- 5.3 30.9 +- 5.6 27.3 +- 5.4 11/29/06 31.8 +- 4.6 31.5 +- 4.7 30.8 +- 4.6 25.6 +- 4.4 38.6 +- 5.0 12/07/06 6.8 +- 3.4 37.0 +- 4.8 41.4 +- 5.0 40.7 +- 5.0 42.2 +- 5.0 12/13/06 49.5 +- 7.1 35.8 +- 5.9 40.8 +- 6.1 47.2 +- 6.3 39.0 +- 6.0 12/20/06 39.4 +- 5.1 38.9 +- 5.3 40.9 +- 5.4 42.7 +- 5.4 42.9 +- 5.5 12/27/06 26.2 +- 5.0 25.9 +- 4.9 22.6 +- 4.9 28.5 +- 5.1 32.0 +- 5.2 40 Table 3-4 Airborne Iodine I- 131[pCi-x 100 3/m3]Period Station Station Station Station Station Station Station Ending 01 02 03 04 05 05A 06 01/04/06 -2.0 +/- 19.0 -24.0 +/- 21.0 -3.0 +/- 19.0 2.0 +/- 19.0 7.0 +/- 19.0 -2.0 +/- 16.0 12.0 +/- 19.0 01/11/06 0.0 +/- 15.0 9.0 +/- 16.0 2.0 +/- 16.0 -2.0 +/- 17.0 -12.0 +/- 16.0 -11.0 +/- 16.0 16.0 +/- 18.0 01/18/06 7.0 +/- 14.0 1.0 +/- 12.0 1.0 +/- 12.0 -9.0 +/- 15.0 9.0 +/- 16.0 3.0 +/- 11.0 6.0 +/- 13.0 01/25/06 5.0 +/- 15.0 -3.0 +/- 16.0 0.0 +/- 18.0 12.0 +/- 16.0 2.0 +/- 16.0 -2.0 +/- 19.0 0.0 +/- 18.0 02/01/06 -5.0 +/- 18.0 -11.0 +/- 16.0 8.0 +/- 14.0 -17.0 +/- 16.0 11.0 +/- 17.0 22.0 +/- 17.0 -12.0 +/- 18.0 02/08/06 -4.0 +/- 14.0 10.0 +/- 14.0 -11.0 +/- 14.0 3.0 +/- 14.0 6.0 +/- 13.0 -10 +/- 13.0 -6.0 +/- 15.0 02/15/06 10.0 +/- 18.0 -3.0 +/- 18.0 19.0 +/- 17.0 -12.0 +/- 16.0 7.0 +/- 14.0 -8.0 +/- 17.0 -5.0 +/- 16.0 02/22/06 -26.0 +/- 21.0 0.0 +/- 19.0 0.0 +/- 17.0 -7.0 +/- 18.0 11.0 +/- 16.0 -2.0 +/- 14.0 -9.0 +/- 17.0 03/01/06 0.0 +/- 15.0 6.0 +/- 15.0 5.0 +/- 15.0 -8.0 +/- 14.0 -5.0 +/- 13.0 -5.0 +/- 16.0 -5.0 +/- 14.0 03/08/06 0.0 +/- 15.0 8.0 +/- 17.0 5.0 +/- 12.0 -8.0 +/- 16.0 -9.0 +/- 14.0 16.0 +/- 15.0 -11.0 +/- 16.0 03/16/06 11.0 +/- 29.0 10.0 +/- 28.0 7.0 +/- 18.0 13.0 +/- 23.0 10.0 +/- 23.0 -25.0 +/- 23.0 17.0 +/- 24.0 03/22/06 6.0 +/- 13.0 11.0 +/- 12.0 0.0 +/- 14.0 0.0 +/- 16.0 -11.0 +/- 15.0 -10.0 +/- 17.0 3.0 +/- 14.0 03/29/06 -15.0 +/- 15.0 -7.0 +/- 16.0 -3.0 +/- 15.0 -2.0 +/- 13.0 5.0 +/- 14.0 -17.0 +/- 16.0 -7.0 +/- 15.0 04/05/06 5.0 +/- 15.0 1.0 +/- 16.0 0.0 +/- 17.0 18.0 +/- 19.0 8.0 +/- 13.0 7.0 +/- 15.0 3.0 +/- 17.0 04/12/06 13.0 +/- 20.0 -2.0 +/- 11.0 -5.0 +/- 14.0 -5.0 +/- 15.0 -5.0 +/- 15.0 0.0 +/- 13.0 5.0 +/- 13.0 04/19/06 -2.0 +/- 17.0 0.0 +/- 15.0 -3.0 +/- 13.0 11.0 +/- 17.0 2.0 +/- 16.0 -3.0 +/- 13.0 -24.0 +/- 17.0 04/26/06 -8.0 +/- 17.0 1.0 +/- 11.0 -9.0 +/- 12.0 3.0 +/- 15.0 6.0 +/- 11.0 -1.0 +/- 12.0 3.0 +/- 13.0 05/04/06 9.0 +/- 14.0 -8.0 +/- 15.0 -3.0 +/- 10.0 -1.0 +/- 11.0 -1.0 +/- 13.0 -8.0 +/- 16.0 3.0 +/- 11.0 05/11/06 -9.0 +/- 15.0 -10.0 +/- 14.0 3.0 +/- 14.0 0.0 +/- 12.0 9.0 +/- 12.0 0.0 +/- 14.0 0.0 +/- 16.0 05/17/06 2.0 +/- 23.0 -3.0 +/- 18.0 -5.0 +/- 16.0 9.0 +/- 15.0 -2.0 +/- 20.0 -18.0 +/- 23.0 -7.0 +/- 16.0 05/25/06 -9.0 +/- 18.0 -3.0 +/- 13.0 7.0 +/- 16.0 -10.0 +/- 14.0 -7.0 +/- 14.0 -7.0 +/- 20.0 -14.0 +/- 13.0 05/31/06 7.0 +/- 27.0 -14.0 +/- 20.0 2.0 +/- 17.0 -9.0 +/- 18.0 3.0 +/- 17.0 12.0 +/- 17.0 0.0 +/- 20.0 06/07/06 -6.0 +/- 20.0 3.0 +/- 11.0 -8.0 +/- 14.0 -2.0 +/- 15.0 5.0 +/- 15.0 -8.0 +/- 17.0 -5.0 +/-- 14.0 06/14/06 18.0 +/- 20.0 -12.0 +/- 16.0 7.0 +/- 15.0 17.0 +/- 17.0 -3.0 +/- 17.0 -3.0 +/- 18.0 7.0 +/- 20.0 06/21/06 13.0 +/- 22.0 2.0 +/- 21.0 -2.0 +/- 17.0 3.0 +/- 16.0 -5.0 +/- 15.0 -7.0 +/- 17.0 -7.0 +/- 13.0 06/28/06 8.0 +/- 19.0 -8.0 +/- 18.0 17.0 +/- 17.0 6.0 +/- 14.0 -5.0 +/- 14.0 -2.0 +/- 16.0 -2.0 +/- 18.0 41 0 Table 3-4 Airborne Iodine I- 131[pCi x 100 3/m3]Period Ending 01/04/06 01/11/06 01/18/06 01/25/06 02/01/06 02/08/06 02/15/06 02/22/06 03/01/06.03/08/06 03/16/06 03/22/06 03/29/06 04/05/06 04/12/06 04/19/06 04/26/06 05/04/06 05/11/2006*

05/17/06 05/25/06 05/31/06 06/07/06 06/14/06 06/21/06 06/28/06 Station Station 21 Station 22 Station 23 Station 24-2.0-5.0 0.0-2.0 6.0 4.0-10.0 4.0-13.0-12.0 9.0-2.0-14.0 4.0-3.0 6.0-1.0 1.0-2.0 0.0-1.0 9.0-8.0 4.0 3.0 10.0 14.0 12.0 13.0 18.0 15.0 15.0 15.0 15.0 17.0 15.0 26.0 17.0 17.0 16.0 13.0 13.0 14.0 16.0 12.0 18.0 14.0 17.0 16.0 18.0 12.0 17.0-11.0-5.0-4.0 4.0-11.0 4.0-3.0-2.0 3.0 6.0 7.0 11.0-14.0-6.0 2.0-11.0 3.0-7.0-5.0 0.0 4.0 7.0-5.0 7.0 0.0 2.0 16.0 16.0 23.0 15.0 17.0 18.0 18.0 11.0 17.0 18.0 22.0 16.0 15.0 18.0 16.0 13.0 12.0 12.0 18.0 13.0 10.0 18.0 17.0 16.0 18.0 19.0-11.0 5.0-1.0-29.0 8.0 6.0-5.0-8.0-8.0 3.0 0.0 8.0-3.0-24.0-8.0-3.0-10.0-7.0 8.0-5.0 6.0-10.0 6.0-10.0-3.0-2.0 22.0 15.0 14.0 19.0 16.0 15.0 18.0 19.0 15.0 15.0 28.0 18.0 14.0 18.0 17.0 16.0 13.0 12.0 16.0 18.0 16.0 16.0 14.0 14.0 14.0 17.0 7.0-6.0-3.0 5.0 3.0-12.0-3.0-2.0-2.0 0.0 19.0 10.0-1.0 7.0 3.0 3.0 13.0 9.0 8.0 5.0 4.4-4.0 5.0-3.0-9.0 0.0 20.0 13.0 15.0 15.0 15.0 15.0 19.0 16.0 15.0 15.0 27.0 19.0 11.0 18.0 16.0 12.0 13.0 12.0 15.0 18.0 9.6 15.0 12.0 18.0 14.0 17.0-5.0-3.0 6.0-2.0 16.0 3.0 0.0 0.0 14.0 3.0-4.0 7.0-2.0 8.0 0.0 2.0 1.0-2.0 12.0-3.0 14.0 9.0-9.0 7.0 0.0 3.0 17.0 15.0 14.0 18.0 16.0 15.0 18.0 15.0 13.0 15.0 23.0 16.0 13.0 16.0 15.0 12.0 14.0 16.0 17.0 15.0 15.0 18.0 19.0 14.0 14.0 14.0*Station 24 Collected on 05/10/2006 42 Table 3-4 Airborne Iodine 1- 131[pCi x 1 0 3/m3]Period Station Station Station Stato Station Station Station Ending 01 02 03 04 05 05A 06 07/05/06 18.0 +- 17.0 6.0 +- 14.0 -2.0 +- 17.0 -6.0 +- 13.0 -5.0 +- 14.0 0.0 +- 14.0 9.0 +- 15.0 07/12/06 -17.0 +- 17.0 3.0 +- 15.0 5.0 +- 14.0 6.0 +- 15.0 15.0 +- 16.0 -11.0 +- 16.0 -3.0 +- 15.0 07/19/06 5.0 +- 23.0 18.0 +- 17.0 4.0 +- 17.0 5.0 +- 19.0 4.0 +- 19.0 4.0 +- 19.0 -17.0 +- 19.0 07/26/06 -11.0 +- 19.0 12.0 +- 15.0 2.0 +- 17.0 5.0 +- 16.0 -8.0 +- 15.0 -18.0 +- 16.0 8.0 +- 15.0 08/02/06 -2.0 +- 17.0 3.0 +- 14.0 -2.0 +- 11.0 -9.0 +- 17.0 5.0 +- 16.0 -2.0 +- 14.0 -17.0 +- 18.0 08/09/06 18.0 +- 21.0 -3.0 +- 15.0 3.0 +- 15.0 11.0 +- 18.0 -11.0 +- 15.0 -2.0 +- 16.0 -2.0 +- 15.0 08/16/06 13.0 +- 17.0 1.0 +- 15.0 -14.0 +- 16.0 6.0 +- 12.0 3.0 +- 18.0 -3.0 +- 14.0 6.0 +- 12.0 08/23/06 2.0 +- 16.0 7.0 +- 15.0 13.0 +- 14.0 -1.0 +- 10.0 4.0 +- 11.0 6.0 +- 15.0 -13.0 +- 13.0 08/30/06 -8.0 +- 19.0 -9.0 +- 15.0 11.0 +- 14.0 -5.0 +- 15.0 -16.0 +- 16.0 13.0 +- 15.0 6.0 +- 16.0 09/06/06 -13.0 +- 16.0 1.0 +- 12.0 -7.0 +- 15.0 0.0 +- 14.0 -10.0 +- 13.0 0.0 +- 11.0 3.0 +- 13.0 09/13/06 3.0 +- 27.0 -10.0 +- 15.0 -15.0 +- 16.0 6.0 +- 17.0 -8.0 +- 19.0 6.0 +- 18.0 8.0 +- 18.0 09/20/06 3.0 +- 16.0 7.0 +- 16.0 15.0 +- 17.0 -2.0 +- 18.0 3.0 +- 17.0 -8.0 +- 12.0 -27.0 +- 17.0 09/27/06 8.0 +- 14.0 6.0 +- 15.0 5.0 +- 15.0 11.0 +- 17.0 0.0 +- 15.0 -2.0 +- 17.0 -8.0 -/- 15.0 10/04/06 0.0 +- 19.0 13.0 +- 18.0 -8.0 +- 16.0 -7.0O / 20.0 -2.0 +- 15.0 -8.0 +- 15.0 -3.0 +- 20.0 10/11/06 -6.0 +- 18.0 2.0 +- 14.0 0.0 +- 20.0 -24.0 +- 18.0 -2.0 +- 18.0 13.0 +- 21.0 0.0 +- 16.0 10/18/06 6.0 +- 16.0 0.0 +- 17.0 -5.0 +- 18.0 -3.0 +- 16.0 -2.0 +- 17.0 7.0 +- 16.0 -2.0 +- 15.0 10/26/06 12.0 +- 14.0 2.0 +- 12.0 -3.0 +- 16.0 -11.0 +- 15.0 3.0 +- 16.0 5.0 +/- 13.0 -5.0 +- 15.0 11/01/06 -21.0 +- 18.0 3.0 +- 16.0 -18.0 +- 17.0 13.0 +- 17.0 0.0 +- 16.0 0.0 +- 18.0 -16.0 +- 17.0 11/09/06 -3.0 +- 16.0 -17.0 +- 15.0 -1.0 +- 14.0 3.0 +- 17.0 14.0 +- 16.0 5.0 +- 14.0 8.0 +- 12.0 11/15/06 -12.0 +- 20.0 -5.0 +- 13.0 11.0 +- 16.0 5.0 +- 19.0 0.0 +- 14.0 2.0 +- 14.0 9.0 +- 20.0 11/21/06 -9.0 +- 24.0 -14.0 +- 22.0 14.0 +- 25.0 -2.0 +- 21.0 -5.0 +- 20.0 -33.0 +- 26.0 -12.0 +- 21.0 11/29/06 -14.0 +- 13.0 7.0 +- 14.0 -1.0 +- 13.0 -4.0 +- 15.0 11.0 +- 15.0 4.0 +- 15.0 11.0 +- 13.0 12/07/06 -5.0 +- 12.0 -3.0 +- 13.0 3.0 14.0 3.0 +- 13.0 0.0 +- 12.0 4.0 +- 13.0 -3.0 +- 14.0 12/13/06 -9.0 +- 16.0 -12.0 +- 13.0 4.0 +- 18.0 11.0 +- 17.0 -9.0 +- 14.0 14.0 +- 21.0 -11.0 +- 16.0 12/20/06 7.0 +- 17.0 0.0 +- 18.0 16.0 +- 16.0 -2.0 +- 18.0 9.0 +- 18.0 4.0 +- 17.0 9.0 +- 16.0 12/27/06 -2.0 +- 19.0 8.0 +- 18.0 8.0 +- 18.0 6.0 +- 20.0 6.0 +- 17.0 8.0 +- 17.0 -2.0 +- 23.0 43 Table 3-4 Airborne Iodine 1 -131[p~ji x 10-3/m3]Period Station Station Station Station Station 07/05/06 6.0 +- 14.0 0.0 +- 13.0 2.0 +- 14.0 -19.0 +- 14.0 3.0 +- 14.0 07/12/06 -8.0 +- 13.0 -13.0 +- 15.0 -9.0 +- 15.0 6.0 +- 14.0 14.0 +- 15.0 07/19/06 6.0 +- 17.0 -10.0 +- 18.0 -4.0 +- 19.0 11.0 +- 20.0 8.0 +- 18.0 07/26/06 -3.0 +- 18.0 -3.0 +- 19.0 14.0 +- 15.0 -12.0 +- 17.0 2.0 +- 17.0 08/02/06 2.0 +- 12.0 0.0 +- 15.0 -3.0 +- 14.0 -14.0 +- 13.0 3.0 +- 15.0 08/09/06 -9.0 +- 16.0 0.0 +- 14.0 6.0 +- 14.0 5.0 +- 16.0 2.0 +- 16.0 08/16/06 -7.0 +- 15.0 -3.0 +- 16.0 18.0 +- 15.0 7.0 +- 15.0 1.0 +- 15.0 08/23/06 -6.0 +- 12.0 -9.0 +- 11.0 4.0 +- 15.0 -3.0 +- 15.0 1.0 +- 17.0 08/30/06 -8.0 +- 16.0 6.0 +- 18.0 9.0 +- 16.0 -11.0 +- 16.0 -3.0 +- 16.0 09/06/06 -6.0 +- 14.0 0.0 +- 12.0 11.0 +- 13.0 -7.0 +- 12.0 0.0 +- 14.0 09/13/06 8.0 +- 19.0 -12.0 +- 23.0 12.0 +- 19.0 -6.0 +- 19.0 0.0 +- 19.0 09/20/06 -8.0 +- 15.0 -8.0 +- 17.0 10.0 +- 18.0 -2.0 +- 17.0 7.0 +- 20.0 09/27/06 3.0 +- 13.0 3.0 +- 17.0 0.0 +- 13.0 -3.0 +- 17.0 3.0 +- 13.0 10/04/06 14.0 +- 17.0 3.0 +- 17.0 2.0 +- 18.0 0.0 +- 19.0 -21.0 +- 17.0 10/11/06 -17.0 -/ 17.0 -19.0 +- 20.0 11.0 +- 18.0 -2.0 +- 17.0 2.0 +- 17.0 10/18/06 -19.0 +- 18.0 -8.0 +- 17.0 -5.0 +- 16.0 -8.0 +- 16.0 9.0 +- 15.0 10/26/06 0.0 +- 16.0 -6.0 +- 15.0 -2.0 +- 14.0 0.0 +- 15.0 -3.0 +- 15.0 11/01/06 -10.0 +- 18.0 5.0 +- 16.0 -2.0 +- 16.0 7.0 +- 17.0 15.0 +- 18.0 11/09/06 8.0 +- 13.0 -2.0 +- 15.0 -9.0 +- 14.0 6.0 +- 16.0 -2.0 +- 14.0 11/15/06 9.0 +- 15.0 -7.0 +- 16.0 21.0 +- 19.0 7.0 +- 16.0 0.0 +- 16.0 11/21/06 12.0 +- 20.0 0.0 +- 22.0 5.0 +- 23.0 -10.0 +- 18.0 12.0 +- 22.0 11/29/06 -4.0 +- 12.0 -7.0 +- 13.0 -6.0 +- 15.0 12.0 +- 16.0 1.0 +- 17.0 12/07/05 1.0 +- 14.0 8.0 +- 14.0~ 11.0 +- 13.0 3.0 +- 11.0 -4.0 +- 12.0 12/13/06 11.0 +- 21.0 -2.0 +- 17.0 2.0 +- 16.0 -7.0 +- 17.0 -9.0 +- 19.0 12/20/06 6.0 +- 15.0 1.0 +- 18.0 4.0 +- 18.0 -10.0 +- 17.0 -20.0 +- 20.0 12/27/06 0.0 +- 20.0 -6.0 +- 18.0 4.0 +- 22.0 -2.0 +- 17.0 4.0 +- 18.0 44 0 0 Table 3-5 Airborne Particulate Gamma Spectra and Strontium[pCi x1 0-3/m3]Sampling Location 01 02 03 04 05 05A 06 07 21 22 23 24 Quarter 1 S Be-7 125.0 +/- 32.0 56.0 +/- 27.0 123.0 +/- 31.0 127.0 +/- 30.0 139.0 +/- 25.0 96.0 +/- 21.0 76.0 +/- 21.0 83.0 +/- 21.0 96.0 +/- 22.0 109.0 +/- 22.0 113.0 +/- 20.0 92.0 +/- 23.0 S K-40 9.0 +/- 12.0-3.0 +/- 13.0-3.0 +/- 12.0-5.1 +/- 9.7 2.8 +/- 8.2 0.9 +/- 6.9-0.8 +/- 9.2-2.4 +/- 5.6-1.2 +/- 7.1 2.1 +/- 6.5 0.1 +/- 5.1-5.4 +/- 7.5 S Cs- 134 0.0 +/- 1.2-0.1 +/- 0.7 0.2 +/- 0.7 0.2 +/- 0.9 0.3 +/- 0.5 0.5 +/- 0.4-0.1 +/- 0.7-0.1 +/- 0.5-0.1 +/- 0.1 0.2 +/- 0.6 0.3 +/- 0.4-0.3 +/- 0.5 S CS- 134 0.1 +/- 0.8-0.2 +/- 0.5-0.3 +/- 0.5 0.1 +/- 0.7-0.2 +/- 0.6-0.2 +/- 0.7 0.4 +/- 0.8-0.4 +/- 0.5 0.4 +/- 0.8 0.2 +/- 0.6 0.0 +/- 0.1-0.6 +/- 0.7-Cs- 137-0.1 +/- 1.6 0.3 +/- 1.6-0.9 +/- 1.6-0.6 +- 1.7-0.4 +/- 0.4-0.3 +/- 0.6 0.1 +/- 0.6 0.0 +/- 0.5 0.3 +/- 0.4 0.4 +/- 0.4-0.3 +/- 0.3 0.4 +/- 0.6 2Cs-1 37-0.4 +/- 1.0-0.1 +/- 0.6 0.1 +/- 0.7 0.1 +/- 0.1-0.1 +/- 0.8-0.5 +/- 0.7 0.1 +/- 0.7 0.0 +/- 0.3-0.1 +/- 0.7-0.3 +/- 0.6 0.1 +/- 0.7 0.0 +/- 0.7 I I Sampling 1Location I Be-7 01 200.0 +/- 43.0 02 169.0 +/- 32.0 03 153.0 +/- 31.0 04 143.0 +/- 32.0 05 156.0 +/- 32.0 05A 161.0 +/- 35.0 06 144.0 +/- 30.0 07 129.0 +/- 22.0 21 150.0 +/- 31.0 22 147.0 +/- 29.0 23 177.0 +/- 33.0 24 135.0 +/- 30.0 Sr-89/90 sampled in 2nd Qtr.Quarter 2 I K-40-1.0 +/- 11.0-4.5 +/- 6.9 3.8 +/- 8.1 2.7 +/- 9.3-4.4 +/- 6.8-10.0 +/- 10.0-5.9 +/- 4.9-3.5 +/- 5.8-1.4 +/- 8.8-6.9 +/- 7.7 1.4 +/- 9.6 0.0 +/- 11.0 S Sr-89-2.6 +/- 8.9 9.0 +/- 10.0 7.0 +/- 10.0-4.3 +/- 6.4 2.0 +/- 9.1-4.7 +/- 6.8 0.6 +/- 9.5-7.4 +/- 5.6 9.4 +/- 9.6 2.0 +/- 8.3 7.8 +/- 9.8 0.2 +/- 8.1 0 +Sr-90 0.6 +/- 0.8 0.7 +/- 0.8 0.7 +-0.8 0.8 +/- 0.7 0.6 +/- 0.8 0.7 +/- 0.7 0.0 +/- 0.8 0.9 +/- 0.7 0.4 +/- 0.7 0.1 +/- 0.7 0.2 +/- 0.7 1.1 +/- 0.8 I 45 0 0 Table 3-5 Airborne Particulate and Strontium Gamma Spectra[pCi x10 3/m3]0 Sampling Location 01 02 03 04 05 05A 06 07 21 22 23 24 Sampling Location 01 02 03 04 05 05A 06 07 21 22 23 24 Quarter 3 I Be-7 110.0 +/- 25.0*166.0 +/- 27.0 153.0 +/- 27.0 153.0 +/- 28.0 143.0 +/- 25.0 153.0 +/- 26.0 114.0 +/- 24.0 123.0 +/- 24.0 139.0 +/- 24.0 119.0 +/- 24.0 137.0 +/- 25.0 142.0 +/- 26.0 I K-40-5.0 +/--0.9 +/--0.4 +/--0.8 +/-6.7 +/--3.3 +/--3.4 +/-0.1 +/-0.2 +/--4.5 +/-0.1 +/--2.0 +/-7.4 5.8 8.1 6.3 7.9 7.0 6.5 6.1 6.6 5.7 6.1 8.8-CS- 134-0.1 +/- 0.5-0.1 +/- 0.4-0.1 +/- 0.5-0.1 +/- 0.5-0.1 +/- 0.4 0.2 +/- 0.5 0.4 +/- 0.5 0.0 +/- 0.5-0.1 +/- 0.5-0.2 +/- 0.5 0.0 +/- 0.5-0.2 +/- 0.5 I CS-134 0.6 +/- 0.7-0.3 +/- 0.5-0.1 +/- 0.7-0.1 +/- 0.6 0.4 +/- 0.8-0.7 +/- 0.8 0.2 +-0.8 0.3 +-0.6 0.2 +/- 0.7 0.1 +/- 0.7 0.2 +/- 0.7-0.3 +/- 0.9.Cs- 137 0.0 +/- 0.6 I!0.1 +/-0.1 +/--0.3 +/-0.0 +/-0.3 +/-0.0 +/-0.2 +/-0.2 +/--0.1 +/--0.1 +F-0.5 +/-0.5 0.4 0.5 0.4 0.4 0.5 0.6 0.6 0.5 0.5 0.6 Quarter 4 I Be-7 187.0 +/-40.0 +/-179.0 +/-132.0 +/-158.0 +/-127.0 +/-103.0 +/-112.0 +/-123.0 +/-120.0 +/-154.0 +/-139.0 +/-48.0 21.0 43.0 37.0 39.0 37.0 37.0 39.0 35.0 37.0 42.0 37.0 4 +K-40 4.0 +- 10.0-7.0 +/- 10.0 1.6 +/- 5.9-8.7 +/- 8.5-0.7 +/- 8.7 6.0 +/- 11.0-2.2 +/- 7.3 3.4 +/- 9.3-3.2 +/- 9.4-0.6 +/- 9.5-2.1 +/- 8.2-3.0 +/- 11.0' Cs-137-0.2 +-0.6 +-0.0 +-0.2 +-0.2 +--0.5 +-0.0-0.2 0.2 0.6 0.3 +/--0.4 +-0.7 0.6 0.7 0.8 0.5 0.6 0.7 0.5 0.5 0.7 0.7 0.7 46 0 0 Table 3-6 Soil Gamma Spectra and Strontium[pCi/kg]0 I Station I Sr-89 I Sr-90 I Be-7 I K-40 I Cs-134 I Cs-137 I Th-228 I 01 02 03 04 05 05A 06 07 21 22 23 24 Soil Not Collected 2006 47 Table 3-7 Precipitation Gamma Spectra[pCi/L]06/28/2006 Sampling Location Be-7 I K-40 I Cr-51 I Mn-54 I Fe-59 I Co-58 I Co-60 I 01A 2.0 +/- 17.0-13.0 +/- 23.0 Zr-95 6.0 +/- 19.0 Nb-95-0.1 +/- 1.9 0.0 +/- 4.5 0.9 +/- 2.0-0.3+/-2.0 Zn-65 Ru-103 Ru-1 06 S Sb-125 1-131 I 01A 3.3 +/- 4.5 03Cs- 134 0.3 +/- 1.7 0.4 +/- 3.2 15Cs- 137 1.5 +/- 1.6-0.2 +/- 2.4-.Ba- 140-3.2 +- 4.4-3.2 +/- 2.4-7La- 140-3.7 +/- 5.1 0.0 +/- 14.0 2.3 +/- 5.0 0.6 +/- 5.2 j Th-228 6.8 +/- 7.7 I I 01A 12/27/2006 Sampling Location Be-7 I K-40 I Cr-51 Mn-54 Fe-59 Co-58 Co-60 I 01A 10.0 +/- 11.0 11.8 +/- 9.3 Zr-95-14.0 +/- 19.0 Nb-95 0.1 +/- 0.5 Ru-103 0.7 +/- 2.5 Ru-106-0.4 +/- 0.9 Sb-125-0.2 +/- 0.7 1-131 Zn-65 I 01A-1.0 +/- 1.2-.Cs- 134-0.3 +/- 0.6-0.9 +/- 1.5-.Cs- 137-0.2 +/- 0.5 1.3 +/- 1.5-0Ba-140-1 .0 +/- 13.0-1.5 +/- 2.4-.La- 140-2.0 +/- 15.0 1.6 +/- 5.3-1Th-228-1.1 +/- 2.5-0.2 +/- 1.4-51.0 +/- 91.0 I 01A 48 0 Table 3-7 Precipitation Gross Beta[pCi/L]Sampling Date 01/25/06 02/22/05 03/30/05 04/28/05 05/31/06 06/28/06 07/26/06 08/30/06 09/27/05 10/26/06 11/29/06-12/27/06 Gross Beta 4.2 +/- 2.1 13.4 +/- 2.9 No Sample No Sample 3.5 +/- 1.9 4.6 +/- 2.1 1.9 +/- 1.9 11.4 +/- 2.7 4.8 +/- 2.1 5.6 +/- 2.1 3.3 +/- 1.9 13.3 +/- 2.8 I1 Rainfall (inches) j 3.30 2.10 0.25 2.05 3.50 7.99 4.25 2.03 7.90 5.65 7.49 1.48 Total = 47.99" 49 Table 3-8 Milk Gamma Spectra and Strontium r-Date 01/18/06 1360.0 02/15/06 1370.0 03/22/06 1390.0 04/12/06 1320.0 05/11/06 1350.0 06/14/06 1230.0 07/12/06 1400.0 08/16/06 1420.0 09/13/06 1290.0 10/18/06 1415.0 11/15/06 1310.0 12/13/06 1430.0 K-40 160.0 140.0 130.0 140.0 130.0 130.0 130.0 130.0 130.0 91.0 110.0 120.0 Sr-89[a][a]3.0 +/- 2.9[a][a]2.3 +/- 4.2[a][a]0.9 +/- 4.8[a][a]0.3 +/- 3.8 S Sr-90[a][a]-0.8 +/- 0.9[a][a]-1.1 +/- 1.0[a][a]0.4 +/- 1.0[a][a]1.0 +/- 0.9 Sr-90[a][a]-0.8 +/- 1.0[a][a]-0.8 +/- 1.0[a][a]-1.3 +/- 1.1[a][a]0.1 +/- 1.0[pCi/L]S 1-131-0.04 +/- 0.26 0.23 +/- 0.40 0.05 +/- 0.30 0.01 +/- 0.19 0.08 +/- 0.33-0.13 +/- 0.05-0.21 +/- 0.09 0.44 +/- 0.58-0.13 +/- 0.05 0.04 +/- 0.29-0.13 +/- 0.05-0.11 +/- 0.29 0 Cs-134 0.7 +/- 4.2 1.6-4.5-1.0-2.5-1.4-1.9 3.1-1.4 0.8 0.0-0.3 4.3 4.0 3.9 3.9 4.4 3.4 3.9 3.7 2.8 3.4 3.8 i Cs-137 2.2 +/- 3.6 3.7 +/- 3.8-0.8 +/- 3.4 2.1 +/- 4.0 1.3 +/- 3.2-1.4 +/- 3.3 1.5 +/- 2.7-0.3 +/- 3.3-0.8 +/- 3.6-0.5 +/- 2.3 1.2 +/- 3.0 3.1 +/- 3.2 0 +Cs-137 0.3 +-3.5 0.3 +/- 3.7 2.9 +/- 2.9-0.3 +/- 3.4 0.3 +/- 3.8 4.2 +/- 4.8-0.4 +/- 3.9 1.9 +/- 2.6 2.7 +/- 4.2 0.3 +/- 2.5-0.5 +/- 2.1 1.3 +/- 3.6 S Ba- 140 1.2 +/- 5.1-2.4 +/- 4.9-1.0 +/- 4.4-3.0 +/- 4.2 1.8 +/- 5.7-5.1 +/- 5.6-0.5 +/-4.4-4.9 +/- 5.7 0.3 +/- 5.4-5.3 +/- 5.7-0.8 +/- 4.9-3.3 +/- 3.9 S Ba-140 3.0 +/- 4.2-2.2 +/- 5.5-0.8 +/- 4.6-1.0 +/- 4.0-1.5 +/- 6.7 1.7 +/- 6.4 5.3 +/- 7.0 2.3 +/- 3.6-0.7 +/- 6.4-1.2 +/- 6.7 1.1 +/- 4.0-3.8 +/- 4.7 Station 12 1 La- 140 1.3 +/- 5.8 I-2.7 +/--1.1 +/--3.4 +/-2.1 +/--5.8 +/--0.5 +/--5.6 +/-0.4 +/--6.1 +/--0.9 +/--3.8 +/-5.6 5.1 4.9 6.6 6.5 5.0 6.5 6.3 6.6 5.7 4.5 Date 01/18/06 02/15/06 03/22/06 04/12/06 05/11/06 06/14/06 07/12/06 08/16/06 09/13/06 10/18/06 11/15/06 12/13/06 10 +K-40 1390.0 +/-1360.0 +/1320.0 +/-1350.0 +/-1280.0 +/-1400.0 +/-1320.0 +/-1409.0 +/-1210.0 +/-1369.0 +/-1385.0 +/-1440.0 +/-170.0 130.0 110.0 130.0 130.0 180.0 170.0 95.0 160.0 95.0 88.0 Sr-89[a][a]1.6 +/- 4.6[a][a]-2.1 +/- 4.0[a][a]-0.8 +/- 3.9[a][a]L1 1-131 1 0.09 +/- 0.39-0.19 +/- 0.26 0.09 +/- 0.35 0.09 +/- 0.26-0.02 +/- 0.25 0.12 +/- 0.38 0.10 +/- 0.39-0.14 +/- 0.05-0.15 +/- 0.05-0.15 +/- 0.06 0.18 +/- 0.44 0.14 +/- 0.42 Cs-134 1.6 + 4.3-0.9 + 3.8-0.9 + 2.8 0.2 + 3.7 2.5 + 3.9 0.9 +- 4.9 1.0 +- 3.8 1.9 +- 2.6 3.2 +- 4.3 0.9 +- 2.8 0.7 +- 2.5-0.2 +- 4.0 Station 13 S La- 140 3.4 +/- 4.9-2.5 +/- 6.3-0.9 +/- 5.3-1.1 +/- 4.6-1.8 +/- 7.7 2.0 +/- 7.3 6.1 +/- 8.1 2.7 +/- 4.1-0.8 +/- 7.4-1.4 +/- 7.7 1.3 +/- 4.6-4.4 +/- 5.4 I 140.0 3.3 +/- 4.6[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.50 0 Table 3-9 Food and Vegetation Gamma Spectra[pCi/kg]Sampling Sampling Location Date 14 05/17/07 06/21/06 07/19/07 08/23/06 09/20/06 10/27/06 m Be-7 1300.0 +/- 370.0 910.0 +/- 350.0 1990.0 +/- 450.0 1840.0 +/- 510.0 5390.0 +/- 600.0 7180.0 +/- 440.0 I K-40 5610 +/- 850.0 27700 +/- 1100.0 20500 +/- 1200.0 14400 +/- 1000.0 11360 +/- 900.0 16300 +/- 880.0.I 1-131 5.0 +/- 22.0 0.0 +/- 16.0-7.0 +/- 27.0-5.0 +/- 22.0 15.0 +/- 23.0-18.0 +/- 12.0 I Cs-134-17.0 +/- 26.0 10.0 +/- 25.0 34.0 +/- 36.0 41.0 +/- 35.0 17.0 +/- 33.0-8.0 +/- 27.0 I Cs-137 12.0 +/- 22.0 3.0 +/- 24.0 30.0 +/- 35.0 5.0 +/- 35.0 21.0 +/- 29.0 6.0 +/- 18.0 I1 Th-228 55.0 +/- 96.0 10.0 +/- 120.0 90.0 +/- 190.0 100.0 +/- 210.0 50.0 +/- 160.0 140.0 +/- 100.0-1 15 05/17/07 06/21/06 07/19/07 08/23/06 09/20/06 10/27/06 16 05/17/07 06/21/06 07/19/07 08/23/06 09/20/06 10/27/06 Be-7 K-40 1-131 Cs-134 Cs-137 Th-228 920.0 +/- 340.0 10150 +/- 920.0 -11.0 +/- 17.0 5.0 +/- 23.0 -21.0 +/- 24.0 70.0 +/- 110.0 320.0 +/- 260.0 6000 +/- 1000.0 -8.8 +/- 3.9 16.0 +/- 26.0 2.0 +/- 25.0 100.0 +/- 100.0 900.0 +/- 280.0 13600 +/- 830.0 2.0 +/- 15.0 13.0 +/- 27.0 12.0 +/- 26.0 60.0 +/- 130.0 800.0 +/- 260.0 10190 +/- 800.0 9.0 +/- 28.0 7.0 +/- 28.0 38.0 +/- 35.0 170.0 +/- 130.0 3870.0 +/- 510.0 9900 +/- 800.0 9.0 +/- 25.0 2.0 +/- 28.0 40.0 +/- 40.0 120.0 +/- 130.0 3260.0 +/- 390.0 16130 +/- 890.0 -1.0 +/- 22.0 -9.0 +/- 27.0 88.0 +/- 31.0 150.0 +/- 130.0 Be-7 K-40 1-131 Cs-1 34 Cs-137 Th-228 350.0 +/- 270.0 970.0 +/- 450.0 1870.0 +/- 380.0 1570.0 +/- 340.0 2710.0 +/- 500.0 6670.0 +/- 550.0 9010 +/- 860.0 51700 +/- 1600.0 14820 +/- 910.0 12380 +/- 890.0 14700 +/- 1100.0 20700 +/ 1100.0-1.0 +/- 19.0 21.0 +/- 28.0-15.0 +/- 16.0 2.0 +/- 26.0 24.0 +/- 32.0-10.0 +/- 19.0-12.0 +/- 23.0 3.0 +/- 33.0 3.0 +/- 28.0-5.0 +/- 31.0 13.0 +/- 35.0 12.0 +/- 29.0 6.0 +/- 19.0 29.0 +/- 33.0-19.0 +/- 24.0 0.0 +/- 23.0 13.0 +/- 26.0-11.0 +/- 28.0 89.0 +/- 83.0 130.0 +/- 170.0 100.0 +/- 150.0 0.0 +/- 130.0 170.0 +/- 140.0 230.0 +/- 250.0 51 Table 3-9 Food and Vegetation Gamma Spectra[pCi/kg]Sampling Sampling LocationI Date 23 05/17/07 06/21/06 07/19/07 08/23/06 09/20/06 10/27/06 Be-7 1260.0 +/-2030.0 +/-2800.0 +/-550.0 +/-2610.0 +/-8030.0 +/-170.0 390.0 390.0 180.0 440.0 480.0 K-40 9540 +/- 400.0 10830 +/- 910.0 13770 +/- 930.0 11670 +/- 750.0 10350 +/- 820.0 20160 +/- 890.0 I 1-131 3.0 +/- 18.0-10.6 +/- 4.7 3.0 +/- 54.0 22.0 +/- 30.0-1.0 +/- 19.0 4.0 +/- 27.0 I Cs-1 34 1.0 +/- 16.0 28.0 +/- 31.0 35.0 +/- 32.0 29.0 +/- 25.0 41.0 +/- 34.0 19.0 +/- 25.0 I Cs-137 1.0 +/- 11.0 7.0 +/- 27.0 21.0 +/- 28.0 43.0 +/- 31.0 1.0 +/- 29.0 5.0 +/- 21.0 I Th-228 242.0 +/- 42.0 110.0 +/- 120.0 200.0 +/ 210.0 170.0 +/- 120.0 240.0 +/- 110.0 60.0 +/- 100.0-I 26 05/17/07 06/21/06 07/19/07 08/23/06 09/20/06 10/27/06 10 +Be-7 1860.0 +/-710.0 /1930.0 +/-600.0 +/-4320.0 +/-2660.0 +/-300.0 290.0 360.0 360.0 440.0 180.0 S K-40 10980 +/- 790.0 2870 +/- 450.0 16400 1000.0 21170 +/- 990.0 8590 +/- 750.0 3810 +/- 270.0 I 1-131 17.0 +/- 24.0-9.3 +/- 4.1-32.0 +/- 53.0 2.0 +/- 27.0 8.0 +/- 25.0-12.0 +/- 18.0 I Cs-1 34 I 15.0 +/- 21.0 0.0 +/- 18.0 25.0 +/- 33.0 20.0 +/- 30.0-8.0 +/- 29.0-2.0 +/- 9.9 2.0 +/- 19.0 23.0 +/- 18.0 30.0 +/- 27.0 37.0 +/- 30.0-1.0 +/- 21.0 10.3 +/- 8.5 Cs-137 I Th-228 69.0 +/- 93.0 147.0 +/- 67.0 150.0 +/- 160.0 440.0 +/- 110.0 123.0 +/- 99.0 28.0 +/- 39.0 I 52 Table 3-10 Well Water Gamma Spectra, Strontium, and Tritium[pCi/L]Sampling Station 01A Date H-3 Be-7 K-40 Sr-89 Sr-90 1-131 Ba-140 Th-228 03/29/06 -710.0 +/- 910.0 -14.0 +/- 21.0 14.0 +/- 34.0 [a] [a] -3.3 +/- 5.2 0.0 +/- 4.7 1.2 +/- 9.3 06/28/06 -230.0 +/- 880.0 -11.0 +/- 14.0 -9.0 +/- 24.0 1.3 +/- 3.6 -0.2 +/- 1.0 -4.4 +/- 5.2 -1.4 +/- 3.7 3.6 +/- 7.0 09/27/06 -1140.0 +/- 920.0 29.0 +/- 20.0 53.0 +/- 26.0 [a] [a] 3.4 +/- 5.7 1.4 +/- 4.1 2.0 +/- 7.6 12/28/06 -730.0 +/- 870.0 -4.0 +/- 17.0 10.0 +/- 23.0 [a] [a] 1.4 +/- 3.7 -0.4 +/- 2.4 2.1 +/- 6.0[a] Sr-89/90 analyses performed on the second quarter sample.53 Table 3-11 River Water Gamma Spectra, Strontium, and Tritium[pCi/L]Sampling Date 01/13/06 02/16/06 03/14/06 04/13/06 05/15/06 06/15/06 07/13/06 08/14/06 09/14/06 10/16/06 11/13/06 12/15/06 H-3[b][b]4300.0 +/-[b][b]3600.0 +/-[b][b]3100.0 +/-[b][b]2130.0 +/-I Be-7 I K-40-8.0 +/- 20.0 6.0 +/- 11.0-1.0 +/- 21.0-32.0 +/- 36.0 1000.0 -4.0 1.0-6.0 1000.0 7.0-9.0 6.0 1100.0 1.0-0.4 4.0 960.0 2.9 15.0 20.0 17.0 16.0 16.0 18.0 17.0 8.4 16.0 5.5 37.0 +/--1.0 +/-9.0 +/-21.0 +/--7.0 +/-9.0 +/-25.0 +/-1.0 +/--6.0 +/--4.0 +/-29.0 36.0 31.0.30.0 26.0 35.0 24.0 14.0 23.0 13.0 Sr-89 Sr-90[a] [a][a] [a][a] [a][a] [a][a] [a]2.0 +/- 5.3 0.1 +/- 1.0[a] [a][a] [a][a] [a][a] [a][a] [a][a] [a]1-131-0.2 +/- 0.1 0.1 +/- 0.3-0.1 +/- 0.0 0.0 +/- 0:1 0.3 +/- 0.5 0.3 +/- 0.5-0.2 +/- 0.1-0.3 +/- 0.1 0.2 +/- 0.4-0.1 +/- 0.3 0.1 +/- 0.5-0.3 +/- 0.1 I Cs-137-0.3 +/- 1.2-1.1 +/- 2.3 0.8 +/- 1.6-0.5 +/- 3.0 0.4 +/- 2.2-0.3 +/- 2.1 0.4 +/- 2.1 1.7 +/- 2.3-0.8 +/- 1.6 0.3 +/- 1.0 0.3 +/- 1.8-0.2 +/- 0.6 I Ba-140-1.6 +/- 2.7 0.3 +/- 4.1 2.4 +/- 3.2 0.0 +/- 4.4-1.2 +/- 3.9 0.2 +/- 3.2-2.2 +/- 4.2-1.2 +/- 4.0-2.8 +/- 3.1 1.9 +/- 2.4 2.3 +/- 3.7-0.4 +/- 1.6 Station 11 S Th-228-2.6 +/--2.6 +/--1.5 +/-0.3 +/-0.6 +/-5.3 +/-5.4 +/-5.2 +/-0.6 +/-3.8 +/-0.5 +/--0.3 +/-5.1 9.1 8.3 9.6 7.1 8.9 9.0 8.7 6.4 3.8 6.4 3.5[a] Sr-89/90 analyses performed on the second quarter sample.[b] Tritium analyses on quarterly composite.

54 Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium Date 01/13/06 02/16/06 03/14/06 04/13/06 05/15/07 06/15/06 07/13/06 08/14/06 09/14/06 10/16/06 11/13/06 12/15/06 Date 01/13/06 02/16/06 03/14/06 04/13/06 05/15/07 06/15/06 07/13/06 08/14/06 09/14/06 10/16/06 11/13/06 12/15/06 H-3[b][b]3700.0 +/-[b][b]3800.0 +/-[b][b]2900.0 +/-[b][b]4100.0 +/--: H-3[b][b]-660.0 +/-[b][b]-610.0 +/-[b][b]-290.0 +/-[b][b]-350.0 +/-Sr-89 Sr-90[a] [a][a] [a]1000.0 [a] [a][a] [a][a] [a]1000.0 4.2 +/- 5.6 0.0 +/-[a] [a][a] [a]1100.0 [a] [a][a] [a][a] [a]1000.0 [a] [a]Sr-89 Sr-90[a] [a]1.0 S Be-7-1.0 +/-17.0 +/-0.0 +/-20.0 +/--1.0 +/-17.0 +/-11.0 +/--4.0 +/-9.0 +/-11.0 +/-8.0 +/--0.4 +/-14.0 26.0 24.0 28.0 24.0 29.0 24.0 18.0 16.0 15.0 18.0 7.1[pCi/L]S K-40 0.0 +/- 28.0 7.0 +/- 45.0-36.0 +/- 41.0-13.0 +/- 42.0-14.0 +/- 38.0-27.0 +/- 45.0 6.0 +/- 43.0-30.0 +/- 33.0 0.0 +/- 34.0 2.0 +/- 24.0 13.0 +/- 34.0 12.0 +- 11.0 S K-40 9.0 +/- 26.0 16.0 +/- 44.0 12.0 +/- 39.0-3.0 +/- 44.0-42.0 +/- 33.0-3.0 +/- 60.0-34.0 +/- 38.0 14.0 +/- 29.0-10.0 +/- 39.0 17.0 +/- 24.0 13.0 +/- 28.0 15.0 +/- 15.0 0 1-131 0.0 +/- 0.3 0.0 +/- 0.2 0.0 +/- 0.3 0.0 +/- 0.1-0.1 +/- 0.0 0.1 +/- 0.3 0.7 +/- 0.7-0.1 +/- 0.3 0.0 +/- 0.3-0.1 +/- 0.2 0.3 +/- 0.5 0.3 +/- 0.5 S 1-131 0.1 +/- 0.3-0.3 +/- 0.1 0.0 +/- 0.3-0.1 +/- 0.0 0.3 +/- 0.5 0.1 +/- 0.3 0.4 +/- 0.6-0.1 +/- 0.3-0.1 +-0.2-0.1 /-0.3 0.1 +/- 0.4 0.4 +/- 0.5 S Cs-137 0.3 +/- 1.7-0.9 +/- 3.5 1.9 +/- 2.3 0.6 +/- 3.0 0.9 +/- 2.7 3.3 +/- 3.1 3.8 +/- 3.3 0.1 +/- 2.2 0.7 +/- 1.8-0.4 +/- 1.4-0.9 +/- 1.6-0.1 +/- 0.7 Cs-137 0.0 +/- 1.6 0.0 +/- 2.9-0.5 +/- 2.4 0.1 +/- 3.0-1.2 +/- 2.6-1.8 +/- 3.5 1.2 +/- 2.5-2.3 +/- 2.0-1.0 +/- 2.2-0.2 +/- 1.3-1.8 +/- 2.2-0.7 +/- 0.9 I Ba- 140-1.2 +/- 4.5-1.5 +/- 6.1-4.7 +/- 5.8-1.0 +/- 4.5 0.8 +/- 5.2 1.3 +/- 7.0-2.6 +/- 5.9-5.5 +/- 4.8 2.2 +/- 5.0 2.1 +/- 4.6-2.7 +/- 5.0-0.3 +/- 1.7 I Ba-140-0.3 +/- 3.8-4.7 +/- 6.0 1.3 +/- 4.5 3.2 +/- 4.5 1.6 +/- 5.4-1.0 +/- 5.9 0.8 +/- 6.9-1.1 +/- 3.4-1.7 +/- 5.2-1.7 +/- 4.3-1.4 +/- 4.5 2.1 +/- 3.1 Station 08 I Th-228 5.4 +/- 6.8 3.0 +/- 14.0 5.0 +/- 10.0-2.0 +/- 13.0-2.5 +/- 9.8 6.0 +/- 12.0 6.0 +/- 12.0-5.8 +/- 9.4-2.1 +/- 9.1-3.2 +/- 6.1-2.4 +/- 6.5-1.2 +/- 2.8 Station 09A I Th-228-2.9 +/- 6.3 2.0 +/- 11.0 3.0 +/- 12.0 0.0 +/- 12.0-3.0 +/- 10.0-5.0 +/- 14.0 6.0 +/- 11.0 2.0 +/- 11.0-3.8 +/- 8.8 2.7 +/- 6.7 1.0 +/- 8.2-2.1 +/- 4.7 1 Be-7 1.0 +/-860.0 840.0 940.0 870.0[a][a][a][a]-0.1 +/- 4.8[a][a][a][a][a][a][a] -15.0 +/-[a] 5.0 +/-[a] 11.0 +/-[a] 0.0 +/--0.2 +/- 0.9 4.0 +/-[a] -16.0 +/-[a] -11.0 +/-[a] 10.0 +/-[a] -1.0 +/-[a] -8.0 +/-[a] -0.5 +/-15.0 24.0 23.0 26.0 21.0 29.0 21.0 17.0 23.0 13.0 18.0 8.8[a] Sr-89/90 analyses performed on the second quarter sample.[b] Tritium analyses on quarterly composite.

55 Table 3-13 Sediment Silt Gamma Spectra and Strontium[pCi/Kg]Date Sr-89 Sr-90 Be-7 K-40 Mn-54 03/20/2006 Station 08 [a] [a] -760.0 +/- 820.0 15900.0 +/- 2700.0 -15.0 +/- 69.0 Station 09A [a] [a] -60.0 +/- 540.0 7200.0 +/- 1900.0 27.0 +/- 51.0 Station 11 [a] [a] -340.0 +/- 670.0 13600.0 +/- 2500.0 33.0 +/- 71.0 Date Sr-89 Sr-90 Be-7 K-40 Mn-54 10/16/2006 Station 08 -190.0 +/- 140.0 71.0 +/- 98.0 -100.0 +/- 310.0 3010.0 +/- 620.0 -36.0 +/- 32.0 Station 09A -80.0 +/- 130.0 -13.0 +/- 84.0 -270.0 +/- 310.0 11830.0 +/- 990.0 3.0 +/- 28.0 Station 11 130.0 +/- 170.0 -30.0 +/- 110.0 -150.0 +/- 370.0 16200.0 +/- 1200.0 5.0 +/- 35.0 Date Co-58 Co-60 Cs-134 Cs-i 37 Th-228 03/20/2006 Station 08 -43.0 +/- 81.0 -18.0 +/- 75.0 40.0 +/- 73.0 -69.0 +/- 80.0 1880.0 +/- 380.0 Station 09A 5.0 +/- 56.0 8.0 +/- 51.0 -22.0 +/- 50.0 14.0 +/- 63.0 420.0 +/- 200.0 Station 11 -44.0 +/- 83.0 -6.0 +/- 67.0 27.0 +/- 58.0 24.0 +/- 71.0 1350.0 +/- 310.0 Date Co-58 Co-60 Cs-134 0s-137 Th-228 10/16/2006 Station 08 Station 09A Station 11-2.0 +/- 36.0 15.0 +/- 30.0-5.0 +/- 37.0 -23.0 +/- 32.0-23.0 +/- 39.0 0.0 +/- 33.0 26.0 +/- 36.0 49.0 +/- 36.0-15.0 +/- 45.0 153.0 +/- 45.0 42.0 +/- 36.0-13.0 +/- 34.0 370.0 +/- 120.0 590.0 +/- 120.0 1230.0 +/- 140.0[a] Sr-89/90 analyses performed annually.56 Table 3-14 Shoreline Soil Gamma Spectra and Strontium[pCi/Kg]Sample Date Sr-89 I Sr-90 I Be-7 I K-40 I Mn-54 03/20/2006 Station 08 [a] [a] 110.0 +/- 510.0 2200.0 +/- 1000.0 6.0 +/- 51.0 Sample Date Sr-89 Sr-90 Be-7 K-40 Mn-54 10/16/2006 Station 08 190.0 +/- 160.0 -45.0 +/- 93.0 10.0 +/- 380.0 7910.0 +/- 930.0 16.0 +/- 39.0 Sample Date Co-58 Co-60 Cs-1 34 Cs-i 37 Th-228 03/20/2006 Station 08 24.0 +/- 53.0 -24.0 +/- 59.0 10.0 +/- 45.0 49.0 +/- 46.0 +Sample Date Co-58 Co-60 Cs-134 Cs-137 Th-228 10/16/2006 Station 08 -16.0 +/- 40.0[a] Sr-89/90 analyses performed annually.2.0 +/- 32.0-24.0 +/- 47.0-14.0 +/- 36.0 1210.0 +/- 150.0 57 Table 3-15 Fish Gamma Spectra[pCi/Kg]Sampling Date K-40 Fish [a]Station 08 Cs-137 I Mn-54 I Fe-59 I Co-58 1 Co-60 I Zn-65 I Cs-134 I 03/20/06 1360.0 +/- 830.0 0.0 +/- 25.0 27.0 +/- 54.0 12.0 +/- 21.0 24.0 +/- 37.0 -3.0 +/- 94.0 3.0 +/- 29.0 6.0 +/- 32.0 10/17/06 1010.0 +/- 400.0 -3.0 +/- 20.0 4.0 +/- 44.0 0.0 +/- 20.0 -5.0 +/- 18.0 -19.0 +/- 42.0 0.0 +/- 20.0 -2.0 +/- 19.0 Fish [a]Sampling Station 25 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-i37 03/20/06 1710.0 +/- 800.0 12.0 +/- 30.0 39.0 +/- 70.0 -15.0 +/- 33.0 -25.0 +/- 31.0 12.0 +/- 65.0 3.0 +/- 25.0 -22.0 +/- 26.0 10/18/06 2050.0 +/- 410.0 0.0 +/- 16.0 25.0 +/- 34.0 9.0 +/- 16.0 10.0 +/- 15.0 -27.0 +/- 34.0 0.0 +/- 17.0 2.0 +/- 16.0 Catfish [b]Sampling Station 08 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 cs-i 34 Cs-137 03/20/06 1460.0 +/- 650.0 13.0 +/- 23.0 11.0 +/- 70.0 7.0 +/- 30.0 11.0 +/- 26.0 30.0 +/- 54.0 -11.0 +/- 31.0 9.0 +/- 33.0 10/17/06 1420.0 +/- 400.0 -9.0 +/- 17.0 -3.0 +/- 46.0 -10.0 +/- 21.0 6.0 +/- 15.0 -9.0 +/- 37.0 3.0 +/- 18.0 3.0 +/- 18.0 Catfish [b]Sampling Station 25 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-i 34 Cs-137 03/20/06 1870.0 +/- 680.0 10/18/06 1460.0 +/- 250.0 9.0 +/- 22.0 -15.0 +/- 63.0 6.0 +/- 10.0 -15.0 +/- 23.0 3.0 +/- 28.0 8.0 +/- 10.0 0.0 +/- 32.0 2.0 +/- 10.0-22.0 +/- 56.0 9.0 +/- 23.0 6.0 +/- 19.0 3.0 +/- 11.0-1.0 +/- 29.0-1.0 +/- 10.0[a] Non-bottom dwelling species of gamefish.[b] Bottom dwelling species of fish.58

.4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2006 and tabulated in Section 3, are discussed below. Except for TLDs, AREVA Environmental Laboratory analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the AREVA Environmental Laboratory quality assurance manuals and laboratory procedures.

In addition to internal quality control measurements performed by each laboratory, they also participate in an Interlaboratory Comparison Program.Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed.

The results of the Interlaboratory Comparison Programs are provided in Appendix B.The predominant radioactivity detected throughout 2006 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.

Naturally occurring nuclides such as Be-7, K-40, and Th-228 were detected in numerous samples. Th-228 results were variable and are generally at levels higher than plant related radionuclides.

The following is a discussion and summary of the results of the environmental

.measurements taken during the 2006 reporting period.4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation.

TLDs are placed in two concentric rings around the station.The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population areas and nearby residences.

Additional TLDs serve as controls.

Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.The results of the analyses are presented in Table 3-2. Figure 4-1 shows a historical trend of TLD exposure rate measurements.

Control and indicator averages indicate a steady relationship.

Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location.

These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs. This will continue to be monitored.

59 Figure 4-1: Environmental Radiation

-TLDs 10.0--- Environmental-TL-- --- -t -- ------Ave.-Pre-op.

--0 0 1.0'.0 00 O 0 It W) ýO '- ' 0 C , N 0 -C C ? .00 00 00 C0 ON ý O 9N ON 1 ON I'l O 7N O N O*Environmental TLDs -a-Sector TLI~s - Ave. Pre-op.]Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location.

The average level of the 32 locations (two badges at each location) was 5.5 mR/standard month with a range of 1.6 to 38.3 mR/standard month. The highest quarterly average reading and highest single quarter average for any single location were obtained at location SSW-19/51.

These values were 27.8 mR/standard month and 32.6* mR/standard month, respectively.

This location is on site directly across the access road from the Independent Spent Fuel Storage Facility.

The higher values can thus be attributed to the spent fuel stored in the ISFSI. Quarterly and annual TLDs are also located at each of the twelve environmental air sampling stations.For the eleven locations within 10 miles of the station the average quarterly reading was 3.8 mR/standard month with a range of 2.3 to 6.1 mR/standard month. The average annual reading for these locations was 3.4 mR/standard month with a range of from 1.9 to 5.1 mR/standard month. The control location showed a quarterly average of 3.5 mR/standard month with a range of 3.1 to 4.6 mR/standard month. Its annual reading was 3.6 mR/standard month. Eight other TLDs, designated C- 1 thru C-8, were collected quarterly from four locations and showed an average reading of 3.4 mR/standard month with a range of 1.9 to 4.8 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.60

4.2 Airborne

Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged.

Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide.

In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.Figure 4-2: Gross Beta in Air Particulates 0.1 0.010.001 i -- -I I I 1986 1993 1999 2006---*--Control Sta-24 -Indicator

Average Pre-op --*- Required LLD]61 0 4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine.

Once a week the samples are collected and analyzed.

The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection with no positive activity detected.

These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.

4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectrometry.

The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes.

Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected.

No other positive results were seen. These analyses indicate the lack of station effects.4 4.5 Air Particulate Strontium 62 Strontium-89 and 90 analyses were performed on the second quarter composites of air particulate filters from all twelve monitoring stations.

The results are listed in Table 3-5. There was no detection of these fission products at any of the indicator or control stations.4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2004 and therefore not collected in 2006.4.7 Precipitation A sample of rain water was collected monthly at on-site station 01A and analyzed for gross beta activity.

The results are presented in Table 3-7. Ten precipitation samples were obtained with no samples available for two months due to drought.Nine of the ten precipitation samples showed positive results in 2006. The average annual gross beta activity was 7.1 pCi/liter with a range from 3.3 to 13.4 pCi/liter.

Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. No positive indications of gamma emitting radioisotopes were observed in the semi-annual composite samples for 2006.During the pre-operational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison can not be made to the 2006 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter.

4.8 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment.

This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint.

This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any plant effect.Analysis results for cow milk are contained in Table 3-8. All results show no detectable I- 131 above the LLD of 1 pCi/1. Results of gamma ray spectroscopy indicate no detectable plant related radioactivity in the milk samples. In years* past, Cs-137 has been detected sporadically.

The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Cs- 137 was not detected at a level above the LLD in 2006.63 w Once each quarter a sample from each of the two collection stations is analyzed for strontium-89 and strontium-90.

Neither Sr-89 not Sr-90 were detected.

Sr-90 has been observed in the past. Pre-operational levels of 2.2 to 5.4 pCi/liter were measured for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents.

Its detection is the product of nuclear weapons testing fallout. This conclusion can be made based upon the fact that Sr-89 and Sr-90 have not been detected in effluents released from the station in many years, and the trend of consistent declining levels since the pre-operational period.4.9 Food Products and Vegetation Twenty-four food/vegetation samples were collected from five locations and analyzed by gamma spectrometry.

The results of the analyses are presented in Table 3-9. Cs-137 was detected at 88 pCi/kg in one sample, as has occurred intermittently in previous years. As expected, naturally occurring potassium-40 was detected in all samples, cosmogenic beryllium-7 was detected in most samples, and thorium-228 was detected in some samples.4.10 Well Water Water was sampled quarterly from the on site well at the metrology laboratory.

These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed for strontium-89 and strontium-90.

The results of these analyses are presented in Table 3-10. Consistent with past monitoring, no plant related radioactivity was detected.

No gamma emitting isotopes were detected during the pre-operational period.4.11 River Water A sample of water from the North Anna River was collected monthly, the analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy.

The monthly samples were composited quarterly and analyzed for tritium, the second quarter samples were additionally analyzed for strontium-89 and strontium-90.

No gamma emitting radioisotopes were detected in any of the samples. There was no measured activity of strontium-89 or strontium-90.

Tritium was measured in all four samples with an average annual concentration of 3283 pCi/liter and a range of 2130 to 4300 pCi/liter.

These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were 64 collected during the pre-operational period.Figure 4-4: Tritium in River Water 10000 0 z 1 10()(I) II1 I00 ..00 OW M ....W 00 O ...00 00 00 00 00 O7N ON ON ON ON ON O, ON ON ON 8 0 0 0 0 ON ON ONý ON ON ON ON1 ON O11 OI C\0 ' ON ON ý ON CN 0 0 0 00 0---- ------- -------'4e C4 (N-4--Tritium

--A --Required LLD 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma ray spectrometry and for iodine- 131 by radiochemical separation.

A quarterly composite from each station was prepared and analyzed for tritium, and the second quarter samples were additionally analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-12.Neither gamma emitting radioisotopes nor iodine were detected in any of the samples. The average level of tritium activity at the indicator station was 3625 pCi/liter with a range of 2900 to 4100 pCi/liter.

Levels of tritium have been increasing since 1978 when the average level was below 300 pCi/liter.

Levels measured at the indicator location (Station 8) are comparable to those measured since 1986, see Figure 4-5. During the pre-operational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter.

65 Figure 4-5: Tritium in Surface Water 10000 Z 1000 S 100 r,-00o~o~r-r-oo~ I CO CO CO CO-~ ~C-Ni M~ 'I k \ r- 00 C) CD -Ni M r T V 0 r- WoO C\ 0 Mi "T V- \C C? 0? C O O C O CO ?C ? O? CO, CO 91 9\ CO C CO CO CO1 ICO CO C? C? O C I Tritium --N --Required LLD --A -Average Pre-op !4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectrometry.

The October samples were analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-13. Figure 4-6 shows the historical trend of Cs- 137 in sediments.

66 Figure 4-6: Cesium-137 in Sediment Silt 0 z~10000 1000"l 100 10 A A& A~XXjX~)O(~

h~XX~k\A 00 00 r-00 I I I I I I 00 Q 00 00 0 00 Z0 00 00 0 00l 0 00 00i 0 0 0 0 05--- Station-8

-Station-9

Control-Sta-09A-x- Station-11

Average Pre-Op --* Required LID's* Cesium-137 was detected in the one sediment sample in 2006 at a level of 153 pCi/kg. This level is consistent with the historical trend. The detection of Cs- 137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout;its global presence has been well documented.

During the pre-operational period sediment samples were analyzed by gamma ray spectroscopy.

There was no measurable amount of strontium-89 or 90 in aquatic sediment/silt.

A number of naturally occunring radioisotopes were detected in these samples at background levels.4.14 Shoreline Soil Shoreline soil/sediment, unlike bottom sediment, may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. A sample of shoreline sediment was collected in March and October from indicator station 08. The samples were analyzed by gamma ray spectrometry.

The September sample was analyzed for strontium-89 and strontium-90.

The results* are presented in Table 3-14.Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities.

The activities of these radioisotopes indicate a 67 steady trend. Cesium- 137 was not detected in 2006, but has been detected intermittently in the past. No Strontium was detected.

Strontium-90 is normally detected in this media, however as discussed previously, the presence of Sr-90 and Cs- 137 is attributed to accumulation of residual global fallout from past atmospheric weapons testing.4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2006 and analyzed by gamma spectroscopy.

Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately.

The results are presented in Table 3-15. Except for naturally occurring K-40, no other nuclide was observed in this media in 2006. Only Cs-137 was measured in pre-operational environmental fish samples.68 0 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2006 -North Anna Location Description Date of Sampling Reason(s) for Loss/Exception Sta. 21 Sta. 27 Sta. 14-16, 23, 26 Sta. 27 Sta. 14-16, 23, 26 Sta. 14-16, 23, 26 Sta. 27 Sta. O0A Sta. 27 Sta. 14-16, 23, 26 Sta. O0A Sta. 05A Sta. 27 Sta. 05A Sta. 05A Sta. 24 Sta. 27 Sta. 02 Sta. 27 Sta. 27 Sta. 27 Sta. 01 Sta. 14-16, 23, 24 Air Iodine and Particulate Milk Vegetation Milk Vegetation Vegetation Milk Precipitation Milk Vegetation Precipitation Air Particulate and Iodine Milk Air Particulate and Iodine Air Particulate and Iodine Air Particulate and Iodine Milk Air Iodine and Particulate Milk Milk Milk Air Particulate and Iodine 01/18/06 01/18/06 01/25/06 02/15/06 02/22/06 03/16/06 03/22/06 03/29/06 04/12/06 04/19/06 04/26/06 05/04/06 05/11/06 05/17/06 05/25/06 06/07/06 06/14/06 06/21/06 07/12/06 08/16/06 09/13/06 09/28/06 10/10/06 Low Volume -pump stopped. LLD achieved.Milk animal no longer present Seasonal Unavailability.

Milk animal no longer present.Seasonal Unavailability.

Seasonal Unavailability.

Milk animal no longer present.No sample, lack of precipitation Milk animal no longer present..Seasonal Unavailability.

Insufficient volume, lack of precipitation.

Low Volume -GFIC tripped & reset. LLD achieved.Milk animal no longer present.Low Volume -GFIC tripped & reset. LLD achieved.Low Volume -GFIC tripped & reset. LLD achieved.Motor running no flow indicated.

LLD achieved.Milk animal no longer present.Low Volume -power loss. LLD achieved.Milk animal no longer present.Milk animal no longer present.Milk animal no longer present.Air sampler failed calibration.

Notified vendor of corrected volume. All values recalculated and LLDs were achieved.Seasonal Unavailability.

0 69 Location Description Date of Sampling Reason(s) for Loss/Exception Sta. 27 Milk 10/24/06 Milk animal no longer present Sta. 27 Milk 11/21/06 Milk animal no longer present Sta. 14-16, 23, Vegetation 11/22/06 Seasonal Unavailability.

26 Sta. 27 Milk 12/19/06 Milk animal no longer present Sta. 14-16, 23, Vegetation 12/20/06 Seasonal Unavailability.

26 Station O0A Precipitation 12/27/06 LLD not met for 1-131 and La-140 due to delay in vendor analysis (CR-07-07 submitted by vendor)REMP Exceptions for 2005 -North Anna Several typographical errors were identified in the 2005 North Anna REMP following distribution." Table 3-3 Gross Beta Air Particulate:

.03/16/2005 Station 05 the value should be 17.8 vice 17.6 08/17/05 Station 21 the error should be + 4.6 vice + 4.4 08/24/05 Station 21 the error should be + 4.7 vice + 4.3" Table 3-4 Airborne Iodine: 09/14/05 Station 24 the error should be + 32 vice + 3.2* Table 3-5 Airborne Particulate Gamma Spectra and Strontium:

2 nd Quarter Station 01 the Sr-90 value should be 3.4 vice 0.3 2 nd Quarter Station 24 the Sr-89 error should be + 9.4 vice + 2.4 3rd Quarter Station 01 the Cs-137 error should be + 0.75 vice + 0.7" Table 3-7 Precipitation Gamma Spectra: 06/28/05 Station O0A 1-131 value should be -5.4 + 4.0 vice -0.9 + 2.5 06/28/05 Station 01A Cs-134 value should be 0.2 vice -0.2" Table 3-8 Milk 09/14/2005 Station 13 Sr-89 value should be -0.9 vice 0.9* Table 3-11 River Water Gamma Spectra, Strontium, and Tritium 01/13/05 Station 11 Cs-137 value should be 0.1 vice -0.1* Table 3-12 Surface Water Gamma Spectra, Strontium, and Tritium Station 08 sample date should be 01/13/05 vice 01/19/05 Station 09A sample should be 01/13/05 vice 01/19/05* Table 3-14 Shoreline Soil Gamma Spectra and Strontium 10/19/05 Station 08 Sr-89 value should be -10 + 360 vice blank Sr-90 value should be 80 + 150 vice 41 + 98 70 REFERENCES 71 References

1. Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.2. Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications.

3. Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".4. Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010, "Radiological Environmental Monitoring Program".5. Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities".

6. United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1OCFR50, Appendix I", October, 1977.7. United States Nuclear Regulatory Commission, Regulatory Guide 4.8"Environmental Technical Specifications for Nuclear Power Plants", December 1975.8. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.9. NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.10. '"Technical Specifications for North Anna Independent Spent Fuel Storage Installation (ISFSI)".11. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.12. NUREG/CR-4007, "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.S 72 0 APPENDICES 73 0 APPENDIX A: LAND USE CENSUS Year 2006 74 LAND USE CENSUS North Anna Power Station North Anna County, Virginia January I to December 31, 2006 Direction Distance (miles)Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch 1Boundary

(> 50m 2) Animal Cow Goat N 0.9 1.5 1.8 None None None NNE 0.9 0.9 3.4 1.5 None None NE 0.8 0.9 0.9 1.5 None None ENE 0.8 2.1 2.1 2.5 None None E 0.8 1.3 1.3 3.5 None None ESE 0.9 1.7 1.7 None None None SE 0.9 1.4 1.4 1.5 None None SSE 0.9 1.0 1.0 2.8 None None S 0.9 1.1 1.2 2.8 None None SSW 1.0 1.4 1.4 1.9 None None SW 1.1 1.7 3.9 None None None WSW 1.1 1.6 2.7 1.6 None None W 1.1 1.5 2.0 None None None WNW 1.0 1.1 1.7 3.9 None None NW 1.0 1.0 1.1 None None None NNW 0.9 1.0 1.1 None None None 0 75 2005 to 2006 Land Use Census Changes 2005 2006 Nearest Direction Distance Distance Site Boundary None Resident SW 3.1 1.7 Garden N 1.5 1.8 NNE 1.4 3.4 SSW None 1.4 SW 3.1 3.9 WSW 1.6 2.7 W 1.5 2.0 WNW 2.5 1.7 Meat Animal None Milch Cow None Milch Goat ENE 2.5 None 76 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2006 S 77 INTRODUCTION This appendix covers the Intercomparison Program of the AREVA ANP Environmental Laboratory as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). Framatome uses QA/QC samples provided by Analytics, Inc to monitor the quality of analytical processing associated with the REMP. The suite of Analytics QA/QC samples are designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides.

It was modified to more closely match the media mix presently being processed by Framatome and includes:> milk for gamma (10 nuclides) and low-level (LL) Iodine- 131 analyses once per quarter,> milk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,> water for gamma (10 nuclides) and low-level (LL) Iodine- 131 analyses during the 1st and 3rd quarters,> water for Sr-89 and Sr-90 analyses during the 4th quarter,> water tritium analysis during the 2nd and 4th quarters,> air filter for gamma (9 nuclides) analyses during the 2nd quarter, and> air filter for gross beta analysis during the 1 st and 3rd quarters.* In addition to the Analytics Intercomparison Program, AREVA ANP also participates in other intercomparsion programs which include radionuclides and media similar to those required by the REMP. These programs are the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (PT)Program, the Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP).RESULTS Intercomparison program results are evaluated using AREVA ANP's internal bias acceptance criterion.

The criterion is defined as within 25% of the known strontium value for samples containing both Sr-89 and Sr-90 and within 15% of the known value for other radionuclides, or within two sigma of the known value.Any sample analysis result that does not pass the criteria is investigated by AREVA ANP.Analytics Intercomparison Program results are included on pages 79 through 82 for the first quarter of 2006 through the third quarter of 2006. A total of 95 analysis results were obtained with 93 passing acceptance criteria, a 97.9%success rate. 2 result in the Analytics program were not in agreement.

Condition* Reports 06-08 and 06-16 were generated.

No cause was identified in the 06-08, but the based on the fact that the instrument calibration was verified and subsequent samples were in agreement, the cause must be attributed to sample 78 subsequent samples were in agreement, the cause must be attributed to sample preparation, since no other cause could be identified.

CR 06-16 was re-eluted and acceptable results were obtained.

However, the CR is still open pending finalization of actions to be taken to enhance the scintillation vial background process. In the DOE program received 6 results received a warning, and 6 results were not in agreement.

Condition Reports 06-19, 06-20, and 06-21 were generated.

Additional samples have been ordered for the DOE disagreements and warnings.

These CR's are still open, as results are currently not available.

In addition to the above, the third quarter Sr-89/-90 in milk was delayed until the fourth quarter. Results from the fourth quarter analyses are not yet available.

The results of the any open corrective actions will be reported in the 2007 report.79 Ratio Sample Quarter! Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation E4884-162 sV2,006 Water Gross Alpha pCiIL 38.7 38.1 1.02 Agreement E4884-162 Ist!2006 Water Gross Beta pCiLL 265 262 1-01 Agreement E4885-162 Ist;2006 Water 1-131LL pCiVL 65.6 67.4 0.98 Aqreement E4885-162 1st12006 Water 1-131 pCiIL 6B.3 67T4 098 Agreement E4885-162 1st1,2006 Water Ce-141 pCifL 83.0 86.8 0.98 Agreement E4885-162 Ist/2006 Water Cr-51 pCi/L 217 234 0.93 Agreement E48854-62 IsJ2006 Water Cs-134 pCiiL 91:9 101 0.91 Agreement E4885-162 lst12006 Water Cs-137 pCi/L 73.3 74.3 099 Agreement E4885 t 1-162 Ist2006 Water Co-58 pCiL 84.7 87.5 0.97 Agreement E4685-162 lstL2006 Water Mn-54 pCifL 74.7 78,1. 0.96 Agreement E4885-162 10t12006 Water Fe-59 oCifL 73.2 724 1.01 Agreement E48685-162 lst2006 Water Zn-65 pCiIL 1467 148 0&99 Agreement E4885-162 1sti20N6 Water Co-60 pCitL 102.5 107 0,.98 Agreement E488;-162 1s02006 Water Sr-89 pCilL 82.0 99.4 0.82 Agreement E4889-1:62 Iet!2006 Water Sr-90 pCiL T0.2 10.8 0,94 Agreement E4887-162 10t!2006 Charcoal 1-131 pCi 84.3 84.8 0.99 Agreement E488W,-162 1stf2006 Filter Gross Alpha pCi 13,5 14.2 0.95 Agreement E4888-162 Ist'2006 Filter Gross Beta pCi 104.5 97.3 1.07 Agreement:

E4889-162 Istf2006 Milk 1-131LL pCilL 81.6 78.0 1.05 Agreement E4889-162 s1t2006 Milk 1-131 1 pCifL 77.4 78.8 0.98 Agreement E4889-162 IstI2006 Milk Ce-141 pCiiL 101 104 0.97 Agreement E4889-162 IsVJ2006 Milk Cr-51 pCifL 277 280 0..99 Agreement E4889-162 ItsY2006 Milk Cs-134 pCi!L 113,8 121 0.94 Agreement E4889-I62 tst12006 MVilk Cs-137 pCirL 86.7 88.8 0.98 Agreement E4889-162 ist12006 Milk Co-58 pCifL 100 105 0.95 Agreement E4889-4 62 Isct2006 Milk Mn-54 pCifL 94.6 93.3 1.01 Agreement E4889-462 tstP2006 Milk Fe-59 PCi!L 90.7 86.6 1-05 Agreement E4889-162 IsYt2006 Milk Zn-65 pCiL 172.2 176 0.98 Agreement E4889-162 1st/2006 Milk Co-60 pCi!L 125-0 128 0.98 Agreement E4899-162 Ist!2006 Milk Sr-89 pCi!L 79.7 99.2 0HO Agreement E4890-162 Istr2006 Milk Sr-90 pCiVL -t0.6 10.8 0I Agreement 80 v Ratio Sample Quarter! Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation E5013-162 2nd,120t6 WYater H-3 pCVIL 583f) 6000 3.97 Agreement E5014-162 2ndt2006 Filer Gross Alpha Pei 31.8 36.6 0,87 Aqreement ES0t4-162 2nd12006 Filter Grose Beta pci 103.8 96.8 1 07 Agreement ES015-162 2nd,2006 Filter Ce-141 pCVL 91.6 92.8 0919 Agreement E"15S-162 2ndW2006 Filter Cr-51 pCI1L 131.7 131 1.01 Aclreement E5015-162 2ndt2006 Filter Cs-134 pCWL 60.5 63.9 095 Agreement E5D15-162 2nd!2006 Filter Cs-137 pCifL 62.9 59.3 1707 Agreement E5015-162 2nd,2006 Filter Co-58 pCiL 52.0 50.6 1.03 Agreement E5015-162 2ndW2006 Filter NIn-54 pCi. 74.5 73.9 1.01 Agreement EH,15-162 2nd,2006 Fi eer Fe-59 pCVL 46.4 47.3 .98 Agreement E0t15-162 2nd,2006 Fi ter Zn-65 pCi, 93.4 93.6 1.00 Agreement E"tO5-162 2nd;2006 Filer Co-60 pCiL 63.0 65.0 0.97 Agreement E5015-162 2nd,&2006 Filter Sr-89 pCi,'L 146.6 163 0.90 Agreement ES016-162 2ndt2006 Filter Sr-go pCiiL 7.01 12.3 0.57 Non-Aareement E5017-162 2nd12006 1-131LL pCilL 67.0 63.2 1.06 Agreement E5017-162 2ndL2:006 Milk 1-131 pCiL 62.0 63.2 0.9B6 Agreement E5017-162 2ndf2006 Milk Ce-141 pCifL 180,8 184 0.9 .Agreement E5017-162 2ndf2006 Milk Cr-51 pCifL 24&0 259 0.96 Agreement E5017-162 2nd:2006 Milk. Cs-134 pCifL 120.1 127 0.95 Agreement E5017-162 2nd!2006 Milk Cs-137 p CiL '117.3 117 1.00 Agreement E5017-162 2nd12006 Milk Co-58 pCitL 97.3 100 0.97 Agreement E5O017-162 2ndl2006 Milk Mn-54 pCi/L 150.5 146 1.03 Agreement E5017-162 2nd,12006 Milk Fe-59 pCi,'L 95.4 93.6 1.02 Agreement E5017-162 2ndt2006 Milk. Zn-65 pCi!L 18.3.9 185 0.99 Agreement E5017-162 2nd,2:006 Milk Co-60 pCilL 126.2 129 0.98 Agreement 81 Ratio Sample Quarterl Sample Reported Known E-LAB,?Number Year Media Nuclide Units Value Value Analytics Evaluation E5090-462 3rd ,2006 Water Gross Alpha pCiIL 71.5 69.4 1.03 Agreement E5090-362 3rd 12006 Water Gross Beta pCi1L 253 273 0.93 Agreement E5091-162 3rd 12016 Water 1-131LL pCifL 84.4 79.9 1.06 Agreement E5091-162 3rd 12006 Water 1- 31 piL 77.3 79.9 0.97 Agreement E5091-162 3rd 12006 Water Ce-141 pCifL 84.5 88.0 196 Agreement ESD91-162 3rd 2006 Water Cr-5 pCilL 287 288 1.00 Agreement ES091462 3rd 12006 Water Cs-134 pCi!L 85.6 87.0 0.98 Agreement ES091-162 3rd !2006 Water Cs-137 pCifL 174 179 0.97 Agreement E5091-162 3rd 12006 Water Co-58 pCiiL 108 112 0.95 Agreement E5091-162 3rd/2006 Water Mn-54 pCiiL 116 115 1.01 Agreement E5091-'162 3rd !2006 Water Fe-59 pCifL 47.0 44.7 1.05 Agreement E5D91-162 3rd12006 Water Zn-65 pCifL 146 148 0.9 Agreement E51091462 3rd 12006 Water Co-60 pCi/L 130 137 0.95 Agreement E5092-162 3rd 12006 Charcoal 1-131 pCi 88.3 91.1 0.97 Agreemem E5093-I62 3rd 12006 Fl ter Gross Aloha pCi 36.9 37.3 0.9i Agreement E5093-4'2 3rd /20v6 Filter Gross Beta pCi 142 147 0.97 Agreement.

E5094- 62 3rd 12006 Milk 1-131LL Pci'q. 79.9 73.8 1.08 Agreement E5094-162 3rd 12006 Milk 1-131 pCifL 72.5 73.8 0.98 Agreement E509 4-162 3rd 12006 Milk Ce-141 pCifL 85.5 86.0 0.99 Agreernent E5094-162 3rd 12006 Milk Cr-5 pCifL 283 282 1 ,02 Agreement E50914-62 3rd12006 Milk Cs-134 pCifL 84.6 85.0 1.00 Agreement E5094-162 3rd 12006 Milk Cs-137 pCifL 171 175 0.98 Agreement E50944 -162 3rd 12006 Milk Co-58 pCi/L 106 109 0.97 Agreement E5094-162 3rd 12006 Milk Mn-54 peL 112 113 0.99 Agreemem E5004 4-t 62 3rd /2006 Milk Fe-59 pCifL 45.3 43.7 1.04 Agreement E5094-162 3rd !2006 Milk Zn-65 pCilL 146 145 1.01 Agreement E5094-162 3rd 12006 Milk Co-60 pCilL 129 134 0.96 Agreement 82 REPORTED IA5APEP SAMPLE MATRIX) REFERENCE RADIO- MEAN VALUE VALUE ID UNITS DATE NUCLIDE BqfUnits BqlUnits % Bias EVALUATION MAPEP-G,5-RdF1i5J Filter iB2,cgiter)

I-Jul-aO Am-241 O.13: 0. l42 -2.5 Agreement MAPE P-G5-RdFS 7 iteiBr ifiltef) 1-JLul-C8 Cs-13S4 3.21 3. 47 32 Agree ment MAPEP-GS-RdF1F6 Flte erlifillteTl i-Jul-ca Cs-137 2. 31 5 1 .05 1 p.C Agreement MAPEP-35-RdFi,5 (Fo'i ter) Co-57 2.834 2.522 9'8 Agreement MAPE F-35-RdF1,3 Filter B9cf1iter 2-Jul-OS Co-0. 1. 1577 2T APreemen, MAPEP.08-RdFia Filter fBedilfter) 1-JuI-OS Mrv-r-64 2.118 1 R2 10.3 Agreement MAPEP-35-RdF16 Flter lBojiilter) 1ý-Jul-OS Pu-232. C.122 0. 4 18 4.2 Aqetrent MIAPEP-G&-RcFIS Fflter (SBoilfter) 1-JLJ1-OS Pu-239f240 0.0016 +1- O.0G12 False Posiie Test NiA Agreement MAPEP-0S-RoFI, FHier fqffifterl 1-Jul-0S S,-92 G.473 0.52 -23.7 Warni~ng (1)MAPEP-Ce-RdFl16 Filter (8q!*ilter) t-Jul-OS Zn-65 -0.034 +,- 0.344 False Positive Test NA Agreement MNAP EP-08-Ms1S1 Soil jBqikg) I-Jul-OS Am-241 105A7 -&.2 Agreenent tAPEP-.3-M4aS1 Soil (Bqgkg) 1-Jul-OS Cs- 34 5195.7 452.13 3i.8 Acceotable (2), MAPEP-G3-MaS1a Soil (BOg~kg) I-Jul-OS Cs- 137 5,91.3 525.73 31.5 No Ac-cegable (2)88APEP-35-MaS1O Soil (Egqkg) i-Jul-08 Co-.57 P13.2 078.33 3:.0 No: Acceptable (2)PAAPEP-05-MaSld Soil Bq'kg) I -Jul-OS Co-0O 2.53 +1- 1.53 1.-8 NA Agreement -r3)MA PEP-Ge-MaS15 Soil 3q4Pi) 1-Jl1-96 MrV-E4 713.3 594.25 33.5 No. Acceirabie (2)MAEF-06-MaS15 Soil (Boýk4g) I-Ju-OSJ Pu-238 813 82 -1.3 Aqreement MAPEP-OS-MaSIS Soil (1Blka) I-Jjul-OS Pu-232)240 0.46 ÷,4- DA 0.93 NWA Aoreement f3i Soil lBq,'kg) I-Jul-O K-40 7W0 C-4 3n.P No" Acceozable

(,2 MAPEP-OB-MaSi1 Soil (Bq,'kg) -Jul-OS 210 213.51 -2,.7 Agreement MAPEP-C.-MaS1,3 Soil (Bqlkg) I.Jul-GO Zn-0.5 1196.7 L33.51 a2.4 iNo. Acceg.able (2)MAFEP-83 -RdV5 I Ver -.,t c -(nl'sample)

"-Jul-08 Am-24, 0.0352 +f- 0.0C32. False PositiveTest PICA Aglreerment MAPEP-D3-RdV1O.

Vegeat.a (Bqisamp]le) 1-Juý-OS Cs-134 5.747 7,487 -23.2 Warning (4W MAPEFP-1-3-RdVIC.

'eg etatu( sqsample)

I-JuH-S Cs-137 4.303 5,405 -21.7 arning f4)MAPEP-0-5-RdVt B Veegeratin

(&qfsample)

I-Jul-OS Co-57 0.00N3 +1-.0.0 False Positive Test NiA Agreement MAPEP-Ot-RdV ir5 Vegeawrcc (Sqlsample)

I-Jul-0S Co-S 4.317 r5.&03 -25.6 Warning (4)MAFEP- a- Rd !e Vegetatin (Bc/sarrple) 1-Jul-OS Mn-54 F.344 %.351 -24.0 Warning (4)MAPEP-OS-R dV1S V ahe n (-q-sample) -I-Jul-OS Pu-238 G.144 9.151 -4.S Agreemeni MAPEP-05-RdV16 Yeteatrc- (Sq/sample)

I-Jul-0S Pu-239f240 0.30365/-0.0023 False Positive Test N1'A Agreement MAPEP- 3R.Rd" 16 Vegetat co (Bq/sample)

I -JulO8 Sr-90 1.081? 1.u95 -0.5 AgreemenI MAPEP-O -,RdVI(6 Vegpeat:.n (Bq/saprrpte) -Jul-OSJ Zn-rES 4.738 5.984 -20. WVarning (4)MAPEP,-O-MaW 1 6 Wa~er (BSqL) 1-JUl-OS Am-241 2.092 2.31 -&.4 Areement MAPEP-00-NtaWI6 Wa.er(BcYL t i-Jul-OS Cs-134 109.22 112.82 -3.5 Aoreement MAPEP-06-MaWlt Water 1-Jul-OS Cs-1i7 187.44 125.14 -4.4 Agreement TAAPEP-0O-8tAaWS' Water (Bq/'L) 1-JulOS Co-57 203-41 213.3 .-4.5 Agreement M APEP-X,- NaW 15 Waer (SBqL) 1-Jul-OS Co-SO 45.50 47.6 -4.1 Agreement M APEP-06-3AaW 1e Water (BqL) 1-Jul-DO H-3 44.5 428.85 3.'e, Agreement MAPEP-06-MiaW lO Water (30q1L) 1-JuJl-OS Fe-55 IN 1 -a5..4 2.2 Agreement MAPEP-06-PaW 15 Water (S!q'L) 1-Jul-3[5 Mn-54 -3.16 +,,- 0315 False Positive Test N1A Agreememn MAPEP-064-aW Waer (BSqL) I-Jul-OD Il-43 C5 5.3 11'1 -;9.7 Agreement MAPEP-06-MaWN1 Wa er(BqL) 1-Jul-OS Pu-238 1.363 1.39 -I .Agreemeni 1,1 APEP-06-11aW'O 1 Waaer (Bq'L, 1--ul-O Pu-23i240 137H 1."4 -7.3 Agreement MAPEP-0O-05aW

1. W a*er (Bqý!L-) 1-Jul-0S Tc-@Q 27 27t 5 t5 Agreement EMAPEP-06-MaWi0 Waer (BSqL) I -JuI-O I Zn-ff 174.29 17637 -033 Agreement (1)-See CR SBcckup-sam.le recuested ,or re-analysis and (2) -See CR 0-5-20. Backup sample requested for re-analysis and evaluation.

(3) -Sens'tiMiy evaluations i.n agreement as result 4- 2-sigma cross the krown value.(4)- See CR 12. Non-homogeneity of container causing Warnings.

Backup sample requested for re-analysis and re-calibration.

83 Mean Ratio Sample Quarter/ Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation A20050-162 tst/2006 Liquid Fe-55 uCilcc 5.48E-04 5.11 E-04 1.07 Agreement A20051-162 lst/2006 Liquid Sr-89 uCi/cc 3.83E-03 3.98E-03 0.96 Agreement A20051-162 1st2006 Liqufd Sr-90 uCiicc 2 54E-04 3.01E-04 0.84 Non-Agreement (0)A20427-162 2ndI2006 Liqu d Fe-55 uCiicc 3.14E-04 3.00E-04 1.05 Agreement A20428-162 2nd/2006 Liquid Sr-89 uLCicc 4.71E-03 5.20E-03 0.91 Agreement A20428-162 2nd,2006 Liquid Sr-90 uCi/cc 2.51E-04 2.71E-04 0.93 Agreement (1) -CR 06-08 generated Mean ,Ratio Sample Q.uarter/

Sample Reported Known E-LAB, Number Year Media Nuclide Units Value Value Analytics Evaluation A2753.-12 d06 Liquid Fe-55 , 2.27E= 7.-=4 .15 Agreemenm:

A20539-162 3rd/2006 Liquid Sr-89 uCifcc 1.74E-03 1.57E-03 1.11. Agreemenm A20539-162 3rd/2006 Liquid Sr-90 uCifcc 1.57E-04 1.51 E-04 1.04 Agreement A21012-162 4th,f206 Liquid Fe-55 uCiicc 6.80E-04 6.15E-04 1.11 Agreement A21013.-l&2 4th120 06 Liquid Sr-89 uCifcc 3.47E-03 3.6-E-03 0.97 Agreemen It A210C3- l-2 4th,2U06 Liquid Sr-90 uCi'cc 1.83E-04 2.03E-04 0.90 Agreement 84 9, APPENDIX C:

SUMMARY

OF GOUNDWATER PROTECTION ANALYSES YEAR 2006 0 S 85

.INTRODUCTION This appendix covers the ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative.

In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples and soil samples from various locations on the site.The industry groundwater protection initiative was prompted as a result of elevated levels of tritium being detected at an Illinois plant in November 2005. It was determined that these elevated levels of tritium were the result of a spill incident that occurred in 1998. The tritium, which migrated into the groundwater both on and off site, posed negligible health or safety hazard to the public. There were no regulatory requirements for the notification of State/local officials when the release occurred in 1998. In response to this event and several others in the nuclear industry, the Nuclear Energy Institute (NEI)developed an industry groundwater protection initiative to improve the reporting of spills/leaks of radioactive contaminants (including tritium) into groundwater to State/local officials.

In addition, the Nuclear Regulatory Commission has formed a Lessons-Learned Task Force to evaluate the regulatory processes to identify areas of improvement.

RESULTS The results of these samples are displayed in the table on the following page.Though some tritium has been detected in some samples, the levels detected are less than the surface water samples obtained from Lake Anna. The average for positive subsurface water samples was 1113 pCi/L. The values ranged from<166 pCi/L to 2080 pCi/L. In approximately 60% of all samples counted, no tritium was detected above the minimum detectable concentration.

Two samples from the ISFSI were analyzed for Sr-89/-90 and gamma emitters in addition to H-3 and no licensed material was detected above the minrumum detectable concentration.

These results are indicative of lake to ground water communication and not indicative of a leak from a radioactive system.86 Sample Date Sample Media Nuclide Value Units Domestic Water 05/10/06 Water H-3 <166 pCi/L Subsurface Drains 05/10/06 Water H-3 1110. pCi/L ISFSI Well #1 06/22/06 Water H-3 <1300 pCi/L ISFSI Well #1 06/22/06 Water Gamma < MDC pCi/L Emitters ISFSI Well #1 06/22/06 Water Sr-89/-90

<MDC pCi/L ISFSI Well #4 06/22/06 Water H-3 <1300 pCi/L ISFSI Well #4 06/22/06 Water Gamma < MDC pCi/L Emitters ISFSI Well #4 06/22/06 Water Sr-89/-90

<MDC pCi/L U-1 Mat Sump East 06/27/06 Water H-3 <725 pCi/L U-1 Mat Sump South 06/27/06 Water H-3 <725 pCi/L U-2 Mat Sump East 06/27/06 Water H-3 1740 pCi/L U-2 Mat Sump South 06/27/06 Water H-3 <726 pCi/L Discharge Canal 07/11/06 Water H-3 <417 pCi/L Storm Drain U-1 Storm Drain 07/11/06 Water H-3 1120 pCi/L U-2 Storm Drain 07/11/06 Water H-3 <417 pCi/L U-1 Mat Sump East 07/13/06 Water H-3 476 pCi/L U-1 Mat Sump South 07/13/06 Water H-3 1060 pCi/L U-2 Mat Sump East 07/13/06 Water H-3 1210 pCi/L U-2 Mat Sump South 07/13/06 Water H-3 1180 pCi/L Subsurface Drains 07/13/06 Water H-3 689 pCi/L NANIC Well 07/19/06 Water H-3 <465 pCi/L Security Training 07/19/06 Water H-3 <465 pCi/L Well Station 01A Well 07/19/06 Water H-3 <465 pCi/L Manhole #10 08/31/06 Water H-3 1320 pCi/L Manhole #23 09/01/06 Water H-3 560 pCi/L Manhole #1 09/01/06 Water H-3 <471 pCi/L Manhole #30 09/01/06 Water H-3 <471 pCi/L Manhole #31 09/01/06 Water H-3 <471 pCi/L Manhole #33 09/01/06 Water H-3 <471 pCi/L Manhole # 46 09/01/06 Water H-3 <471 pCi/L 0 87 Sample Date Sample Media Nuclide Value Units Manhole # 41 09/01/06 Water H-3 520 pCi/L Manhole # 42 09/01/06 Water H-3 <463 pCi/L Manhole # 47 09/01/06 Water H-3 <463 pCi/L Manhole # 40 09/01/06 Water H-3 <469 pCi/L Soil Sample from U-3 09/03/06 Soil Gamma <MDC giCi/kg or Bq/g Boring Emitters WS-2-ISI-03 09/15/06 Water H-3 <469 pCi/L WS-3-1SI-Q3 09/15/06 Water H-3 <469 pCi/L Service Water Vault 10/17/06 Water H-3 1260 pCi/L Service Water #4 10/17/06 Water H-3 <490 pCi/L Subsurface Drains 11/03/06 Water H-3 <483 pCi/L Discharge Canal 11/09/06 Water H-3 1740 pCi/L Storm Drain Outfall U-1 Storm Drain 11/09/06 Water H-3 <497 pCi/L Outfall U-2 Storm Drain 11/09/06 Water H-3 <497 pCi/L Outfall U-1 Mat Sump East 11/10/06 Water H-3 701 pCi/L U-1 Mat Sump South 11/10/06 Water H-3 697 pCi/L U-2 Mat Sump East 11/11/06 Water H-3 1430 pCi/L U-2 Mat Sump South 11/11/06 Water H-3 764 pCi/L Aux Bldg GW 11/11/06 Water H-3 846 pCi/L Monitoring Well U-2 Valve Pit Ground 11/13/06 Water H-3 1880 pCi/L water U-3 Well #901 11/22/06 Water H-3 <461 pCi/L U-3 Well #945 11/22/06 Water H-3 <461 pCi/L U-3 Well #947 11/22/06 Water H-3 <461 pCi/L U-3 Well #950 11/22/06 Water H-3 <461 pCi/L U-2 Valve Pit Ground 11/30/06 Water H-3 2080 pCi/L water U-1 AFW Tunnel 12/08/06 Water H-3 <477 pCi/L U-3 Well #946 11/22/06 Water H-3 1610 pCi/L U-3 Well #949 11/22/06 Water H-3 <477 pCi/L U-3 Well #951 11/22/06 Water H-3 500 pCi/L 88

@@ Line 2: / Line 2: @@
 | number = ML071230069
 | issue date = 04/25/2007
-| title = North Anna Units 1 & 2, ISFSI, Annual Radiological Environmental Operating Report for 2006
+| title = ISFSI, Annual Radiological Environmental Operating Report for 2006
 | author name = Stoddard D G
 | author affiliation = Virginia Electric &amp; Power Co (VEPCO)

ML071230069: Difference between revisions

Revision as of 11:44, 10 February 2019

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2.1 Introduction

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3.2 Analytical

4.2 Airborne

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ML071230069: Difference between revisions

Revision as of 11:44, 10 February 2019

Text

SUMMARY

SUMMARY

SUMMARY

2.1 Introduction

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

3.2 Analytical

4.2 Airborne

SUMMARY

SUMMARY

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