ML051180266

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Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report for 2004
ML051180266
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/20/2005
From: Jennifer Davis
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, 05-234
Download: ML051180266 (85)


Text

VIRGINIA ELECTRIC AND POVEIR COMPANY RIChMOND, VIRGINIA 23261 April 20, 2005 United States Nuclear Regulatory Commission Serial No.05-234 Attention: Document Control Desk NAPS/JRP Washington, D. C. 20555 Docket Nos. 50-338 50-339 72-16 License Nos. NPF-4 NPF-7 SNM-2507 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 & 2 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the Annual Radiological Environmental Operating Report for the reporting period of January 1, 2004 through December 31, 2004. This report is provided pursuant to North Anna Units 1 and 2, Technical Specifications 5.6.2, and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c.

If you have any questions or require additional information, please contact Page Kemp at (540) 894-2295.

Very truly 1.Davis Vice President Enclosure

,  ;"s Commitments made in this letter: None e-'-'-,

cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., 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

Dominion North Anna PowerStation RadiologicalEnvironmentalMonitoring Program January1, 2004 to December 31, 2004 Preparedby Dominion, North Anna Power Station

Annual RadiologicalEnvironmental OperatingReport North Anna Power Station January 1, 2004 to December 31, 2004 Preparedby:

James B. Breeden Supervisor Radiological Analysis Dominion North Anna Power Station Reviewed by:

Erich W. Dreyer Supervisor Health Physics Technical Services Dominion North Anna Power Station Approved by:

Robert B. EvnMs, Jr.

Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2

Table of Contents

1. EXECUTIVE

SUMMARY

......................................................... 4

2. PROGRAM DESCRIPTION ......................................................... 7 2.1 Introduction ......................................................... 7 2.2 Sampling and Analysis Program ......................................................... 8
3. ANALYTICAL RESULTS ........................................................ 22 3.1 Summary of Results ........................................................ 22 3.2 Analytical Results of 2004 REMP Samples ........................................................ 33
4. DISCUSSION OF RESULTS ........................................................ . 60 4.1 Gamma Exposure Rate ........................................................ 60 4.2 Airborne Gross Beta ........................................................ 62 4.3 Airborne Radioiodine ........................................................ 63 4.4 Air Particulate Gamma ........................................................ 63 4.5 Air Particulate Strontium ........................................................ 64 4.6 Soil ........................................................ 64 4.7 Precipitation ........................................................ 64 4.8 Cow Milk ........................................................ 64 4.9 Food Products and Vegetation ........................................................ 65 4.10 Well Water ......................................................... 65 4.11 River Water ......................................................... 66 4.12 Surface Water ......................................................... 66 4.13 Bottom Sediment ........................................................ . 67 4.14 Shoreline Soil ......................................................... 68 4.15 Fish ......................................................... 69
5. PROGRAM EXCEPTIONS ........................................................ 70 REFERENCES ........................................................ 71 APPENDICES ........................................................ 73 APPENDIX A: LAND USE CENSUS ........................................................ 74 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS .............................. 77 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2004 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, 2004, 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 radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as 4

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. TIhe.airborne exposure pathway includes radioactive airborne iodine and particulates and precipitation. The 2004 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 year's 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 2004 was 2423 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 2287 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. The terrestrial exposure pathway includes milk and food/vegetation products. Iodine-131 was not detected in any 2004 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was detected in one milk sample and this activity is attributable to past atmospheric nuclear weapons testing. A ten-year activity trend continues to indicate the slow decrease in Sr-90 activity.

Naturally occurring potassium-40 was detected at average environmental levels.

Cs-137 was detected in one of 25 vegetation samples at an activity of 35 pCi/kg.

Consistent with historical data, potassium-40 was detected. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). 'l) results have remained essentially constant over the years.

During 2004, 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 hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2004 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 5

-- - l only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.

6

2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2004 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 North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As 7

Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2004 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.

2.2 Sampling and Analysis Program Table 2-1 summarizes the 2004 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 2004.

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Table 2-1 NORTH ANNA - 2004 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 0.20 NE 420 Quarterly & Annually Thermoluminescent Fredericks Hall 02 5.30 SSW 2030 Quarterly & Annually Dosimetry (TLD) Mineral, Va 03 7.10 WSW 2430 Quarterly & Annually Wares Crossroads 04 5.10 WNW 2870 Quarterly & Annually Route 752 05 4.20 NNE 200 Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N 110 Quarterly & Annually Levy, VA 06 4.70 ESE 1150 Quarterly & Annually Bumpass, VA 07 7.30 SSE 1670 Quarterly & Annually End of Route 685 21 1.00 WNW 3010 Quarterly & Annually Route 700 22 1.00 WSW 2420 Quarterly & Annually "Aspen Hills" 23 0.93 SSE 1580 Quarterly & Annually Orange, VA 24 22.00 NW 3250 Quarterly & Annually Control Bearing Cooling Tower N-1/33 0.06 N 100 Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 110 Quarterly Parking Lot "C" (on-site) NNE-3/35 0.24 NNE 320 Quarterly Good Hope Church NNE-4/36 3.77 NNE 250 Quarterly Parking Lot "B" NE-5/37 0.20 NE 420 Quarterly Lake Anna Marina (Bogg's Drive) NE-6/38 1.46 NE 340 Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 740 Quarterly Route 689 ENE-8/40 2.43 ENE 650 Quarterly Near Training Facility E-9/41 0.30 E 910 Quarterly "Morning Glory Hill" E-10/42 2.85 E 930 Quarterly Island Dike ESE-1 1/43 0.12 ESE 1030 Quarterly Route 622 ESE-12/44 4.70 ESE 1150 Quarterly DVP Biology Lab SE-13/45 0.64 SE 1380 Quarterly Route 701 (Dam Entrance) SE-14/46 5.88 SE 1370 Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 1580 Quarterly Elk Creek SSE-16/48 2.33 SSE 1650 Quarterly NAPS Access Rd. S-17/49 0.47 S 1730 Quarterly 9

Table 2-1 NORTH ANNA - 2004 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 S 1780 Quarterly Thermoluminescent NAPS Access Rd. SSW-19/51 0.42 SSW 1970 Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 2050 Quarterly 500kv Tower SW-21/53 0.6 SW 2180 Quarterly Route 700 SW-22/54 3.96 SW 2320 Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 2370 Quarterly Route 700 (Exclusion Boundary) WSWV-24/56 1.00 WSW 2420 Quarterly South Gate Switchyard W-25/57 0.32 W 2790 Quarterly Route 685 W-26/58 1.55 W 2740 Quarterly End of Route 685 WNW-27/59 1.00 WNW 3010 Quarterly Route 685 WNW-28/60 1.40 WNW 3030 Quarterly North Gate - Construction Side NW-29/61 0.45 NW 3210 Quarterly Laydown Area Lake Anna Campground NW-30/62 2.54 NW 3190 Quarterly

  1. 1/#2 Intake NNW-31/63 0.07 NNW 3490 Quarterly Route 208 NNW-32/64 2.21 NNW 3440 Quarterly Bumpass Post Office C-1/2 7.30 SSE 1670 Quarterly Control Orange, VA C-3/4 22.00 NW 3250 Quarterly Control Mineral, VA C-5/6 7.10 WSW 2430 Quarterly Control Louisa, VA C-7/8 11.54 WSW 2570 Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 420 Weekly and Radioiodine Fredericks Hall 02 5.30 SSW 2030 Weekly Mineral, VA 03 7.10 WSW 2430 Weekly Wares Crossroads 04 5.10 WNW 2870 Weekly Route 752 05 4.20 NNE 200 Weekly Sturgeon's Creek Marina 05A 2.04 N 110 Weekly Levy, VA 06 4.70 ESE 1150 Weekly Bumpass, VA 07 7.30 SSE 1670 Weekly 10

Table 2-1 NORTH ANNA - 2004 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Airborne Particulate End of Route 685 21 1.00 WNW 3010 Weekly and Radioiodine Route 700 22 1.00 WSW 2420 Weekly "Aspen Hills" 23 0.93 SSE 1580 Weekly Orange, VA 24 22.00 NW 3250 Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 1480 Monthly (Second Cooling Lagoon)

  • Lake Anna (upstream) 09A 12.90 WNW 2950 Monthly Control (Route 669 Bridge)

River Water North Anna River (downstream) 11 5.80 SE 1280 Monthly Ground Water Biology Lab 01A 0.64 SE 1380 Quarterly (Well Water)

Precipitation Biology Lab OA 0.64 SE 1386 Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 WNW 2950 Semi-Annually Control (Route 669 Bridge)

North Anna River (Downstream) 11 5.80 SE 1280 Semi-Annually Shoreline Soil Waste Heat Treatment Facility 08 ** 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Soil NAPS Sewage Treatment Plant 01 0.20 NE 420 Once/3 years Fredericks Hall 02 5.30 SSW 2030 Once/3 years Mineral, VA 03 7.10 WSW 2430 Once/3 years, Wares Crossroads 04 5.10 WNW 2870 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.

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I Table 2-1 NORTH ANNA - 2004 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina 05A 2.04 N 110 Once/3 years Levy, VA 06 4.70 ESE 1150 Once/3 years Bumpass, VA 07 7.30 SSE 1670 Once/3 years End of Route 685 21 1.00 WNW 3010 Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 2420 Once/3 years "Aspen Hills" 23 0.93 SSE 1580 Once/3 years Orange, VA 24 22.00 NW 3250 Once/3 years Control Milk Holladay Dairy (R.C. Goodwin) 12 8.30 NW 3100 Monthly Terrell's Dairy (Fredericks Hall) 13 5.60 SSW 2050 Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Lake Orange 25 16.5 NW 3120 Semi-Annually Control Food Products Bel Aire Plantation 14 1.20 NE 430 Monthly if available (Broadleaf or at harvest Vegetation)

Route 614 15 1.37 SE 1330 Monthly if available or at harvest Route 629/522 16 12.60 NW 3140 Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 1580 Monthly if available or at harvest "Historic Lane" 26 1.15 S 172 0 Monthly if available or at harvest 12

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM

!RAMPVEF MEBTA FREOUFNCY ANATLYSIST VTJ) REPORT UNITS Thermoluminescent Dosimetry (TLD)

(84 TLDs) Quarterly Gamma Dose 2 mR+2mR mR/std. Month (12 TLDs) Annually Gamma Dose 2 mR+2mR mR/std. Month 3

Airborne Radioiodine Weekly I-131 0.07 pCi/M Airborne Particulate Weekly Gross Beta 0.01 pCi/M3 Quarterly (a) Gamma Isotopic pCam 3 Cs-134 0.05 Cs-137 0.06 2 nd Quarter Sr-89 (b) pCi/m3 Composite Sr-90 (b)

Surface Water Monthly 1-131 1(c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly(a) Tritium (H-3) 2000 pCi/L 2 nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

River Water Monthly 1-131 1(c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15

  • LDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the these listed values.

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89190 (c) LLD for non-drinking water is 10 pCi/liter.

13

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM IAMPLEU ME.1TA 1?ROTTJFNCVY ANALYSVTR1S I In REPORT TITS River Water Quarterly(a) Tritium (H-3) 2000 pCi/L 2"d Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

Ground Water Quarterly Gamma Isotopic pCi/L

('Well Water) Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1(c)

Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly(a) Tritium (H-3) 2000 pCi/L 2 nd Quarter Sr-89 (b) pCi/L Sr-90 (b)

Aquatic Sediment Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

Precipitation Monthly Gross Beta 4 pCiIL Semi-Annual Gamma Isotopic pCi/L Composite Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 1(c)

Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

  • LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the these 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

.RAMPT.F MXFTA FTR )JTTFENVCVY ANAT.VFRTY ii,, REPnRT ITN1TR Soil Once per 3 years Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

Milk Monthly 1-131 1 pCi/L Monthly Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (b) pCi/L Sr-90 (b)

Fish Semi-Annually Gamma Isotopic pCi/kg (wet)

Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet)

(Broadleaf Vegetation) available or Cs-134 60 at harvest Cs-137 80 I-131 60

  • LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the these 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 Environmental Station Map Environmental Designation Identification Designation Station 1 (a) 01,NE-5/37 7/8 C-7/8 1A 01A,SE-13/45 1/33 N-1/33 2 (a) 02,SSW-20/52 31/63 NNW-31/63 3 (a) 03,C-5/6 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) 05 7/39 ENE-7/39 SA (a) 05A,N-2/34 9/41 E-9/41 6 (a) 06,ESE-12/44 11/43 ESE-1 1/43 7 (a) 07,C-1/2 17/49 S-17/49 8 08-Water, Fish Sediment, 19/51 SSW-19/51 Shoreline Soil 21/53 SW-21/53 9A 09A-Water sample, sediment 23/55 WSW-23/55 11 11-River Water, Sediment 25/57 W-25/57 12 12-Milk 16/48 SSE-16/48 13 13-Milk 18/50 S-18/50 14 14-Vegetation, NE-6/38 14/46 SE-14/46 15 Vegetation 22/54 SW-22/54 16 Vegetation 26/58 W-26/58 21 (a) 21,WNW-27/59 28/60 WNW-28/60 22 (a) 22,WSW-24/56 32/64 NNW-32/64 23 (a) 23-SSE-15/47 8/40 ENE-8/40 24 (a)(b) 24,C-3/4 4/36 NNE-4/36 25 (c) 25-Fish 10/42 E-10/42 26 26-Vegetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.

(b) In Orange (c) In Lake Orange 16

w I col

North Anna Environmental Map Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

CB3283D

CB3280C C- 0 3

North Anna Environmental Map

  • Fixed Environmental Sampling Location
  • Garden Residents
  • Meat Animals Original 0 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

CB3281 0

North Anna Environmental Map

  • Fixed Environmental Sampling Location
  • TLD Sampling i Garden Residents Original 0 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

CB3282E co0

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.

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.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 1 of 10 Medium or Analysis All Indicator Locations Location with Ilighest Mean 1 Location Control Non-routine Pathway LLD* M N Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Tv e No. Range Direction Range Range ments Air Iodine 1-131 624 0.07 (0/572) N/A N/A (0/52) 0 (pCi/m3 )

Airborne Gross 624 0.01 23.1(572/572) 04 5.10mi. 23.1(52152) 22.7(52/52) 0 Particulates Beta (2.643.9) WNW (7.6-41.7) (5.1-40.9)

(1E-03 pCi/m3)

Gamma 48 Be-7 48 - 0.1(44/44) 07 7.30 mi. 0.1(4/4) 0.3(4/4) 0 (0.0-0.9) SSE (0.1-0.13) (0. 1-0.9)

Cs-134 48 0.05 (0/44) N/A N/A (0/4) 0 Cs-137 48 0.06 (0/44) N/A N/A (0/4) 0 Sr-89 12 - (0/1 1) N/A N/A (0/1) 0 Sr-90 12 - (0/1 1) N/A N/A (0/1) 0 Ground Tritium 4 2000 (0/4) N/A N/A N/A 0 WVell Water (pCi/liter) Gamma 4 Mn-54 4 15 (0/4) N/A N/A N/A 0 Fe-59 4 30 (0/4) N/A N/A N/A 0 Co-58 4 15 (0/4) N/A N/A N/A 0 23

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 2 of 10 All Indicator Control Non-Medium or Anal sis Locations Location with highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure.

(Unit) Type No. Range _ Direction Range Range ments Ground Co-60 15 (0/4) N/A N/A N/A Well

.Water (pCi/liter) Zn-65 30 (0/4) N/A N/A N/A Zr-95 30 (0/4) N/A N/A N/A Nb-95 15 (0/4) N/A N/A N/A I-131 10 (0/4) N/A N/A N/A Cs-134 15 (0/4) N/A N/A N/A Cs-137 18 (0/4) N/A N/A N/A Ba-140 60 (0/4) N/A N/A N/A La-140 15 (0/4) N/A N/A N/A Sr-89 1 - (0/1) N/A N/A N/A 0 Sr-90 1 (0/1) N/A N/A N/A 0 River Tritium 4 2000 2288(4/4) 11 5.80 mi. 2288(4/4) N/A 0 Water (1180-3090) SE (1180-3090)

(pCi/liter) 24

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 3 of 10 All Indicator 1 Control Non-Medium or Anal sis Locations Location with Iighest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Nleasure-(Unit) Tvpe No. Range Direction Range Range ments River Gamma 12 Water (pCi/liter) Mn-54 12 15 (0/12) N/A N/A N/A 0 Fe-59 12 30 (0/12) N/A N/A N/A 0 Co-58 12 15 (0/12) N/A N/A N/A 0 Co-60 12 15 (0/12) N/A N/A N/A 0 Zn-65 12 30 (0/12) N/A N/A N/A 0 Zr-95 12 30 (0112) N/A N/A N/A 0 Nb-95 12 15 (0/12) N/A N/A N/A 0

-9131 12 1 (0/12) N/A N/A N/A 0 Cs-134 12 15 (0/12) N/A N/A N/A 0 Cs-137 12 18 (0/12) N/A N/A N/A 0 Ba-140 12 60 (0/12) N/A N/A N/A 0 La-140 12 15 (0/12) N/A N/A N/A 0 Sr-89 I - (0/1) N/A N/A N/A 0 25

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 4 of 10 T All Indicator Control Non-Medium or Analvsis Locations Location with 1ighest Mean Location routine Pathway TtLLD* M Reported Sampled Total Mean Name Distanceiean Mean Measure-( Tvpe INo. Range IDirection RangeI Range I ments River Water Sr-90 I - (0/1) NIA N/A N/A 0 (pCi/liter)

Surface Tritium 8 2000 2423(4/4) 08 3.37 mi. 2423(4/4) (0/4) 0 Water (1280-2980) SSE (1280-2980)

(pCi/liter)

Gamma 24 Mn-54 24 15 (0/12) N/A N/A (0/12)

Fe-59 24 30 (0/12) N/A N/A (0/12)

Co-58 24 15 (0/12) N/A N/A (0/12)

Co-60 24 15 (0/12) N/A N/A (0/12)

Zn-65 24 30 (0/12) N/A N/A (0/12)

Zr-95 24 30 (0/12) N/A N/A (0/12)

Nb-95 24 15 (0/12) N/A NIA (0/12) 1-131 24 1 (0/12) N/A NIA (0/12)

Cs-134 24 15 (0/12) N/A NIA (0/12)

Cs-137 24 18 (0/12) N/A N/A (0/12) 26

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 5 of 10 All Indicator Control Non-Medium or Anal sis Locations Location with Iighest Mean Location routine Pathway LLD* M Reported Sampled Total Mean Name Distanc Mean Mean Measure-(Unit) Ty No. _ J Range Direction Range Range iments Surface Ba-140 24 60 (0/12) N/A N/A (0/12) 0 Water (pCi/liter)

La-140 24 15 (0/12) N/A N/A (0/12) 0 Sr-89 I - (0/1) N/A N/A (0/1) 0 1

Sr-90 - (0/1) N/A N/A (0/1) 0 Precipitation Monthly (pCi/liter) Gross 12 4 6.43(11/12) O1A 0.75 mi. 6.43 N/A Beta (0.0-15.0) SE (0.0-15.0)

Semiannually Gamma 2 Mn-54 2 15 (0/2) N/A N/A N/A 0 Fe-59 2 30 (0/2) NIA N/A N/A 0 Co-58 2 15 (0/2) NIA N/A N/A 0 Co-60 2 15 (0/2) N/A N/A N/A 0 Zn-65 2 30 (0/2) N/A N/A N/A 0 27

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 6 of 10

- All Indicator Control Non-Medium or Analsis Locations Location with } ighest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distreto Mane Mean Measuret (Unit) Tye No. Range Direction Range Range ments:

Precipitation Zr-95 2 30 (0/2) N/A N/A N/A 0 (pCi/liter)

Nb-95 2 15 (0/2) N/A N/A N/A 0 1-131 2 .10 (0/2) N/A N/A N/A 0 Cs-134 2 15 (0/2) N/A N/A NIA 0 Cs-137 2 18 (0/2) N/A N/A N/A 0 Ba-140 2 60 (0/2) N/A N/A N/A 0 La-140 2 15 (0/2) N/A N/A N/A 0 Sediment Gamma 6 Silt (pCi/kg K-40 6 - 10903(4/4) 11 5.80 mi. 12100(2/2) 11560(2/2) 0 (dry) (12200-16000) SSE (10500-13200) (10920-12200)

Cs-134 6 150 (014) N/A N/A (0/2) 0 Cs-137 6 180 (0/4) N/A N/A (0/2) 0 Th-228 6 - 910(4/4) 08 3.37 mi. 1060(2/2) 648(2/2) 0 (511-1610) SE (511-1610) (377-920)

Sr-89 3 - (0/2) N/A N/A (0/1) 0 (Annually) 28

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Dock-et No. 50-338/339 Page 7 of 10 l All Indicator Control Non-Medium or Anal sis Locations Location with highest Mean Location routine Pathway l l LLD* M Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Ti No. j Range 'Direction Range Range ments Sediment Sr-90 3 (0/2) N/A N/A (0/1) 0 Silt (Annually)

(pCi/kg)

(dry)

Soil Triennial (pCi/Kg) Gamma 12 (dry)

Cs-134 11 150 (0/11) N/A N/A. (0/1) 0 Cs-137 11 180 285(5/11) 3 7.10 mi. 430 360(1/1) 0 (191-430) W'SW Th-228 11 1351(11/11) 7 7.30 mi 2240 1090(1/1)

(540-2240) SSE Sr-89 11 - (0/1 1) N/A N/A (0/1)

Sr-90 11 - (0/11) N/A N/A (0/1)

Shoreline Gamma 2 Soil (pCi/kg) K-40 2 - 2540(2/2) 8 3.37 mi. 2540(2/2) N/A 0 (dry) (2110-2980) SSE (2110-2908)

Th-228 2 - 336(212) 8 3.37 mi. 336(2/2) N/A 0 (334-339) SSE (334-339)

Cs-134 2 150 (0/2) N/A N/A. N/A 0 Cs-137 2 180 199(2/2) 8 3.37 mi. 199(2/2) N/A 0 (162-236) SSE (162-336)

Sr-89 1 - (0/1) N/A N/A N/A 0 (Annually)

Sr-90 1 - (0/1) N/A N/A NIA 0 29

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 8 of 10 All Indicator Control Non-Medium or Analvsis Locations Location with llighest Mean Location routine Pathway - LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) No. Range _ Direction Range Range ments Milk Gamma 24 (pCi/liter)

K-40 24 - 1353(24t24) 12 8.3 mi. 1353(12/12) N/A 0 (1180-1530) NW (1180-1530) 1-131 24 1 (0/24) N/A N/A N/A 0 Cs-134 24 15 (0/24) N/A N/A N/A 0 Cs-137 24 18 (0/24) N/A N/A N/A 0 Ba-140 24 60 (0/24) N/A N/A N/A 0 La-140 24 15 (0/24) N/A N/A N/A 0 Sr-89 8 - (0/8) N/A N/A N/A 0 (Quarterly)

Sr-90 8 - 2.8(1/8) N/A N/A N/A (Quarterly)

Fish Gamma 8 (pCi/}kg)

(wet) K-40 8 1597(4/4) 08 3.37 mi. 1597(4/4) 1457(4/4) 0 (1230-1820) SSE (1230-1820) (1370-1420)

Mn-54 8 130 (0/4) N/A N/A (0/4) 0 Fe-59 8 260 (0/4) N/A N/A (0/4) 0 Co-58 8 130 (0/4) N/A N/A (0/4) 0 30

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 9 of 10 All Indicator Control Non-Medium or Analysis Locations Location with lighest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Tye No. Range I Direction Range - Range ments Fish Co-60 8 130 (014) N/A N/A (0/4) 0 (pCitkg)

(wet)

Zn-65 8 260 (0/4) N/A N/A (0/4) 0 Cs-134 8 130 (0/4) N/A N/A (0/4) 0 Cs-137 8 150 26.3(1/4) 8 3.37 mi. 26.3(1/4) (0/4) 0 Food Gamma 25 Vegetation (pCi/k-g Be-7 25 - 1386(19/25) 23 varies 1286(5/5) 1473(3/5) 0 (wet)) (440-2880) SSE (1010-2880) (1310-1740)

K-40 25 - 13428(25/25) 15 varies 13948(5/5) 11084(5/5) 0 (8900-19400) SE (12800-15010) (9000-14700)

I-131 25 60 (0124) N/A N/A (0/5) 0 Cs-134 25 60 (0124) N/A N/A (0/5) 0 Cs-137 25 80 35(1/25) 15 varies 35(1/5) (0/5) 0 SE -

Th-228 - 292(3/25) 16 varies. 410(1/5) 410(1/5) 0 (197410) NW Direct Gamma 48 2 3.6(44/44) 23 0.93 mi. 5.3(4/4) 3.5(4/4) 0 Radiation Dose - (1.7-6.7) SSE (4.6-6.7) (2.6-4.2)

(mR/std. month)

(Environmental TLDs)

Direct Gamma 12 2 1.56(11/11) 23 0.93 mi. 2.20(1/1) 1.57(1/1) 0 Radiation Dose (1.16-2.20) SSE -

31

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2004 Docket No. 50-338/339 Page 10 of 10 All Indicator Control Non-Medium or Anal-sis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(IUnit) Range _No. Range

_Direction - _Range ments Direct Gamma 253 2 5.3(253/256) 19/51(') 0.42 ni. 27.0(8/8) 3.2(32/32) 0 Radiation Dose (2.6-30) SSW (15.7-39.7) (2.0-4.9)

(mRlstd. Month)

(Sector TLDs)

(1) 19/51 located onsite.

32

3.2 Analytical Results of 2004 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 (2o) 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 2a error (i.e., the measured value exceeds 36).

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 I-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 Resultsfrom HASL,"

letter by Leo B. Higginbotham) and NUREG/CR4007 (Sept. 1984).

33

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mRtStd. Month (30.4 days) . 2 Sigma Page 1 of 3 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly 117/2004 4/13/2004 7/1/2004 10/5/2004 Average 4113/2004 7/1/2004 10/5/2004 1/5/2005 N-1 4.9 5.4 5.0 5.9 5.3 +/- 0.9 N-33 5.0 5.4 4.9 5.3 5.2 +/- 0.5 N-2 3.3 4.0 3.2 4.3 3.7t1.1 N-34 3.2 3.7 3.2 4.5 3.7 +/-1.2 NNE-3 8.1 7.3 6.6 8.2 7.5:t1.5 NNE-35 7.0 7.0 6.7 8.5 7.3 +/-1.6 NNE-4 4.7 4.9 4.4 5.0 4.7 +/-0.5 NNE36 4.7 3.4 4.3 5.0 4.4t+/-1.4 NE-5 4.5 4.3 4.0 5.5 4.6+/- 1.4 NE-37 5.3 5.2 3.4 5.8 4.9t+/-2.1 NE-6 4.0 2.9 3.3 4.4 3.6 +/-1.3 NE-38 3.9 3.9 3.4 5.0 4.1 +/-1.4 ENE-7 4.6 4.2 4.8 5.5 4.8 +/-1.1 ENE-39 4.5 4.8 4.5 6.1 5.0+/-1.5 ENE-8 4.0 3.7 3.4 4.1 3.8 +/- 0.7 ENE-40 3.0 3.8 3.4 3.9 3.5:t 0.8 E-9 5.2 5.1 5.0 6.4 5.4 +/- 1.3 E-41 4.9 4.8 4.9 6.0 52+/- 1.1 E-10 4.3 4.8 5.0 5.2 4.8 +/-0.8 E-42 4.4 5.0 4.5 5.8 4.9:t 1.3 ESE-1 1 4.5 3.8 4.5 5.2 4.5 +/- 1.1 ESE-43 4.2 4.7 4.0 5.0 4.5 +/-0.9 ESE-12 5.4 5.8 4.6 6.1 5.5 +/-1.3 ESE-44 4.3 4.7 4.2 5.4 4.6+/-1.1 SE-13 5.7 4.5 3.9 5.4 4.9 +/-1.7 SE-45 4.0 4.6 4.2 6.4 4.8 +/- 2.2 SE-14 6.8 6.9 6.4 7.3 6.8 +/-0.8 SE-46 6.3 6.7 6.4 6.5 +/-0.3 SSE-15 5.1 4.5 5.0 5.6 5.1 +/-0.8 SSE-47 4.8 5.6 4.9 5.9 5.3 +/-1.1 SSE-16 3.1 3.8 3.3 4.4 3.6 +/- 1.1 SSE-48 3.0 3.8 3.0 4.1 3.5+/-t 1

  • - Refer to Section 1ii,REMP Exceptions for Scheduled Sampling and Analysis During 2004 34

TABLE #3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 2 of 3 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly 1/7/2004 4/13/2004 7/1/2004 10/5/2004 Average 4/13/2004 7/1/2004 10/5t2004 1/5/2005 S-17 7.9 7.1 7.0 8.7 7.7+/-: 1.6 S-49 7.4 7.9 7.0 8.1 7.6+/-1.0 S-18 2.2 2.8 2.7 3.6 2.8+/-12 S-50 2.4 3.0 2.4 3.6 2.8+/-12 SSW-19 36A 28.1 15.7 39.7 30.0 +/- 21.4 SSW-51 31.6 30.4 16.1 18.0 24.0t+/-16.2 SSW-20 2.4 3.0 2.4 3.5 2.8*+/-1.0 SSW-52 2.3 2.8 2.4 3.8 2.8+/-1.4 SW-21 4.2 4.1 4.1 5.0 4.3 +/-0.9 SW-53 3.9 3.8 3.9 4.1 3.9 +/-0.3 SW-22 4.7 4.8 4.4 4.6 +/- 0.4 SW-54 4.3 4.7 4.4 4.5 +/-0.4 WSW-23 5.3 6.0 5.1 5.8 5.5 +/- 0.9 WSW-55 5.7 6.1 4.6 6.1 5.6 +/- 1.4 WSW-24 4.1 5.0 4.5 5.4 4.8t +/-1.1 WSW-56 3.8 4.5 5.0 5.0 4.6 +/- 1.2 W-25 6.4 6.6 5.0 7.5 6.4 +/-2.1 W-57 6.6 6.8 6.3 7.1 6.7t+/-0.7 W-26 2.4 3.5 3.9 3.9 3.4 +/- 1.4 W-58 3.1 2.1 3.0 3.3 2.9 +/-1.0 WNW-27 3.4 4.1 3.3 4.3. 3.8 +/- 1.0 WNW-59 2.9 3.7 3.4 3.7 3.4 +/-0.7 WNW-28 2.9 4.2 2.6 3.8 3.4 +/-1.5 WNW-60 3.0 3.5 2.8 3.4 3.2 +/-0.7 NW-29 5.7 6.5 5.8 72 6.3 +/- 1.4 NW-61 5.8 6.3 5.8 6.9 6.2 +/-1.1 NW-30 2.4 2.1 2.5 3.6 2.6+/-1.3 NW-62 2.4 2.6 2.6 3.5 2.8+/-1.0 NNW-31 3.4 3.8 3.6 5.1 4.0 +/-1.5 NNW-63 3.8 3.5 3.6 4.5 3.9 +/- 0.9 NNW-32 3.6 4.2 4.2 4.8 4.2 +/- 1.0 NNW-64 3.6 2.7 3.6 4.9 3.7 +/- 1.8

'- Refer to *Section il, REMP Exceptions for Scheduled Sampling and Analysis During 2004 35

TABLE #3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mRIStd. Month (30.4 days) +/- 2 Sigma Page 3 of 3 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly 1/7/2004 4/13/2004 7/112004 10/05/2004 Average 4/13/2004 711/2004 10/5/2004 110512005 C-1 3.0 3.1 3.3 3.9 3.3+/- 0.8 C-2 3.0 2.8 3.4 4.3 3.4 +/-1.3 C-3 3.2 2.9 3.3 4.2 3.4+/- 1.1 C-4 3.4 3.0 3.4 4.5 3.6 +/-1.2 C-5 2.2 2.0 2.3 4.9 2.9 +/- 2.8 C-6 2.6 2.5 2.3 3.0 2.6 +/-0.6 C-7 3.0 2.7 3.4 3.8 3.2+/-0.9 C-8 3.3 3.0 2.9 3.9 3.3 +/-0.9 EPSA-01*' 5.1 5.0 4.6 5.7 5.1 +/- 0.9 EPSA-02" 5.0 4.7 4.5 5.9 5.0+/- 1.2 EPSF 4.5 4.7 4.5 5.7 4.8 +/- 1.2 EPSF 4.3 3.9 5.1 6.3 4.9+/- 2.2 EPSR05-* 4.9 5.2 5.2 5.7 5.3+/- 0.7 EPSR 4.9 4.3 4.6 6.1 5.0 +/- 1.6 EPSJ 3.5 3.3 3.9 5.2 4.0 +/- 1.7 EPSJ 3.6 3.4 3.8 5.2 4.0 +/- 1.6 EPSP-09" 6.1 7.4 8.3 7.3+/- 2.3 EPSP 8.5 6.4 7.4 8.9 7.8 +/- 2.3 Average +/- 2 s.d. 5.1 +/- 10.3 5.1 +/-t8.7 4.4t

+/-4.6 5.9 +/- 9.3 5.1 +/- 7.9

'- Refer to Section l1l,REMP Exceptions for Scheduled Sampling and Analysis During 2004

TABLE 3-2 DIRECT RADIATION MEASURMENTS QUARTERLYAND ANNUAL TLD mR/Std. Month (30.4 days)

  • 2 Sigma Page 4 of 4 First Quarter Second Quarter *Third Quarter Fourth Quarter Quarterly Annual TLD Station Name 117/2004 4/13/2004 7/112004 10/5/2004 Average 4/13/2004 7/1/2004 10W5/2004 1/5/2005 STA-01 5.0 3.8 4.7 6.0 4.9 +/- 1.8 1.74 STA-02 2.1 1.8 2.5 3.4 2.5+/- 1.4 1.21 STA-03 1.9 2.7 2.3 2.9 2.4 +/-0.8 126 STA-04 2.1 1.7 2.1 3.6 2.4* 1.7 1.07 STA-05 3.1 2.6 3.8 4.0 3.4 +/- 1.2 1.59 STA-05A 3.1 2.6 3.3 4.4 3.4t+/-1.5 1.35 STA-06 4.5 4.6 4.2 5.3 4.6 +/- 0.9 1.95 STA-07 2.9 3.2 22 3.9 3.1 +/-1.5 1.53 STA-21 2.8 3.5 32 4.1 3.4t+/-1.1 1.48 STA-22 4.4 5.3 4.6 5.0 4.8t+/-0.8 1.83 STA-23 5.1 5.0 4.6 6.7 5.3 +/-1.8 2.20 STA-24 3.9 2.6 3.4 4.2 3.5 +/- 1.4 1.57 Average +/- 2 s.d. 3.4 +/-2.3 3.3 +/-2.4 3.4 : 2.0 4.5 +/-22 3.6 +/- 2.1 1.57+/-0.65 37

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m3 x 10-3]

Period Station Station Station Station Station Station Station Ending 01 -02 03 04 05 23.4 +/- 3.1 l

24.9 05A

+/- 3.1 06 23.1 +/- 3.1 I1 01/07/04 21.5 +/- 3.0 21.5 +/- 3.0 23.5 +/- 3.1 22.0 +/- 3.0 01/14/04 39.1 +/- 3.8 35.4 +I- 3.7 43.9 +I- 4.5 41.7 +/- 3.9 41.2 +I- 3.9 36.1 +I- 3.7 36.6 +I- 3.7 01/21/04 20.3 +/- 3.3 14.7 +/- 3.1 23.3 +I- 3.4 18.8 +/- 3.3 20.2 +I- 3.3 19.1 +/- 3.2 19.3 +I- 3.3 01/28/04 23.4 +I- 3.4 23.1 +I- 3.3 25.5 +I- 3.5 26.1 +/- 3.4 28.0 +I- 3.5 22.9 +/- 3.4 25.0 +I- 3.4 02/04/04 29.0 +/- 3.7 27.3 +I- 3.7 31.5 +/- 3.8 29.6 +I- 3.8 32.4 +I- 3.9 26.7 +I- 3.7 30.6 +I- 3.8 02/11/04 18.3 +/- 2.9 22.5 +I- 3.0 17.9 +/- 2.8 22.2 +/- 3.0 15.8 +I- 2.7 22.7 +I- 3.0 19.3 +I- 2.9 02/18/04 18.5 +/- 3.3 26.5 +I- 3.4 22.2 +I- 3.3 30.9 +/- 3.6 28.7 +I- 3.5 23.8 +I- 3.4 30.1 +I- 3.6 02/25/04 23.0 +/- 3.5 21.0 +I- 3.3 26.6 +I- 3.5 23.7 +I- 3.3 26.7 +I- 3.4 17.2 +I- 3.1 24.1 +I- 3.4 03/03/04 24.0 +/- 3.1 25.6 +I- 3.2 21.8 +/- 3.1 22.9 +I- 3.1 22.0 +I- 3.1 20.5 +I- 3.0 21.9 +I- 3.0 03/10/04 21.0 +/- 3.0 17.8 +I- 2.8 20.1 +/- 3.0 24.2 +I- 3.2 20.4 +I- 3.0 16.0 +I- 2.8 19.3 +I- 2.9 03/17/04 12.5 +t- 3.6 16.2 +I- 3.8 13.5 +/- 3.7 21.2 +I- 4.1 14.3 +I- 4.4 12.4 +I- 3.6 18.9 +I- 4.0 03/24/04 14.8 +I- 3.7 16.2 +1- 3.9 19.6 +/- 4.1 17.8 +I- 4.0 15.5 +I- 3.8 16.5 +I- 3.9 20.6 +I- 4.2 03/31/04 18.8 +/- 4.5 19.0 +I- 4.5 13.4 +/- 4.5 18.2 +I- 4.4 19.7 +I- 4.5 18.3 +1- 4.4 22.2 +I- 4.6 04/06/04 9.6 +I- 3.2 5.8 +I- 3.0 6.0 +/- 3.1 7.6 +I- 3.2 7.5 +I- 3.2 6.2 +I- 3.2 9.1 +I- 3.3 04/14/04 15.8 +I- 3.8 17.9 +I- 3.9 15.5 +/- 3.8 21.3 +I- 4.1 17.5 +I- 3.9 17.4 +I- 3.9 16.5 +I- 3.8 04/21/04 34.1 +I- 3.7 19.7 +I- 3.2 26.4 +I- 3.5 24.7 +I- 3.4 26.3 +I- 3.5 19.3 +I- 3.3 23.6 +I- 3.4 04/28/04 20.7 +I- 4.4 29.0 +I- 4.8 29.1 +/- 4.8 21.9 +I- 4.5 22.5 +I- 4.5 24.3 +I- 4.6 28.9 +I- 4.8 05/05/04 20.1 +I- 4.6 18.5 +I- 2.5 20.6 +/- 2.5 19.5 +I- 2.5 20.4 +I- 2.5 19.9 +I- 2.5 19.1 +/- 2.5 05/12/04 24.7 +I- 4.6 25.5 +I- 4.6 30.8 +/- 4.9 28.1 +I- 4.8 34.3 +I- 5.1 23.0 +I- 4.6 25.2 +I- 4.7 05/19/04 33.6 +/- 5.1 27.1 +I- 4.9 33.8 +/- 5.1 34.6 +I- 5.2 36.5 +I- 5.2 36.5 +I- 5.2 30.7 +I- 5.0 05/26/04 17.1 +/- 4.3 15.3 +I- 4.2 18.2 +/- 4.4 14.8 +I- 4.2 21.0 +/- 4.6 18.8 +I- 4.4 20.7 +I- 4.5 06/02/04 14.3 +/- 4.2 16.4 +I- 4.3 19.7 +/- 4.5 14.1 +I- 4.2 21.1 +/- 4.6 12.5 +I- 4.1 12.6 +I- 4.1 06/09/04 12.8 +/- 4.3 13.4 +I- 4.4 15.1 +/- 4.4 16.1 +/- 4.4 20.1 +I- 4.7 15.6 +I- 4.5 17.0 +I- 4.5 06/16/04 23.5 +I- 4.3 24.0 +I- 4.3 20.6 +/- 4.1 21.6 +/- 4.1 26.8 +1- 4.4 21.4 +I- 4.1 21.9 +I- 4.2 06/23/04 12.0 +/- 3.8 11.6 +I- 3.8 11.5 +/- 3.7 15.4 +/- 4.0 12.5 +I- 3.8 13.9 +I- 3.9 11.1 +I- 3.7 06/30/04 32.8 +I- 5.7 26.2 +I- 5.2 30.7 +/- 5.4 29.0 +/- 5.3 27.2 +I- 5.3 25.2 +I- 5.1 25.5 +I- 5.1 38

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m3 x 10-3]

Period Station Station Station Station Station Ending 1 07 l 21 l 22 1 23 1 24 I 07/07/04 22.3 +/- 3.0 23.5

+/-

3.2 24.4 +/- 3.1 24.9 +/- 3.1 26.5 +I- 3.2 0 07/14/04 33.3 +/- 3.6 38.7 +/- 3.8 37.5 +/- 3.7 40.9 +/- 3.8 40.9 +/- 3.8 07/28/04 20.0 +/- 3.3 16.8 +/- 3.2 24.7 +/- 3.4 21.7 +/- 3.4 24.6 +I- 3.5 07/28/04 21.5 +/- 3.3 26.1 +/- 3.4 23.5 +/- 3.4 23.8 +I- 3.4 26.7 +I- 3.5 08/04/04 25.7 +/- 3.7 30.3 +/- 3.8 34.3 +/- 3.9 28.8 +I- 3.6 28.4 +I- 3.7 08/11/04 17.4 +/- 2.8 22.9 +/- 3.1 24.3 +/- 3.1 22.7 +/- 3.1 21.2 +/- 3.0 08/18/04 22.7 +/- 3.4 24.4 +/- 3.4 22.8 +/- 3.3 24.1 +/- 3.3 21.6 +/- 3.3 08/25/04 21.3 +/- 3.3 28.2 +/- 3.5 22.4 +I- 3.4 26.0 +/- 3.5 22.6 +I- 3.3 09/01/04 19.2 +/- 3.0 23.2 +/- 3.1 22.5 +/- 3.1 19.8 +/- 3.0 20.3 +/- 3.0 09/08/04 22.4 +/- 3.0 20.3 +/- 3.0 20.3 +/- 3.0 20.0 +/- 2.9 22.0 +/- 3.1 09/15/04 16.2 +/- 3.8 15.2 +/- 3.8 17.0 +/- 3.9 10.7 +/- 3.5 15.4 +/- 3.8 09/22/04 19.0 +/- 4.1 15.8 +/- 3.8 17.7 +/- 4.0 16.5 +/- 3.9 18.9 +/- 4.0 09/29/04 19.6 +/- 4.5 20.0 +/- 4.6 22.5 +I- 4.7 22.9 +1- 4.8 22.0 +/- 4.7 10/05/04 4.9 +/- 3.1 7.5 +/- 3.2 5.8 +/- 3.1 8.1 +/- 3.1 5.1 +/- 3.1 10/13/04 14.3 +/- 3.7 13.1 +/* 3.7 18.5 +/- 3.9 5.7 +I- 3.2 11.4 +/- 3.6 10/20/04 28.1 +/- 3.6 19.6 +/- 3.2 27.8 +I- 3.5 23.8 +I- 3.4 28.8 +I- 3.6 10/27/04 27.6 +/- 4.7 22.8 +/* 4.5 24.7 +I- 4.6 27.8 +I- 4.7 31.5 +/- 4.9 11/03/04 17.0 +/- 2.5 18.6 +/- 2.5 17.9 +/- 2.5 20.1 +/- 2.5 22.3 +I- 2.6 11/10/04 24.6 +/- 4.6 19.3 +/- 4.4 28.9 +I- 4.8 35.1 +/- 5.1 25.5 +I- 4.7 11/18/04 32.0 +/- 5.0 32.5 +/- 5.0 29.9 +I- 4.9 30.0 +/- 5.0 30.0 +/- 4.9 11/25/04 19.9 +/- 4.5 15.9 +/- 4.3 18.9 +/- 4.5 18.5 +/- 4.4 12.2 +1- 4.1 12/01/04 16.4 +/- 4.3 11.8 +/- 4.1 15.2 +/- 4.3 12.0 +/- 4.1 21.3 +/- 4.6 12/08/04 14.8 +/- 4.4 12.7 +/- 4.3 15.3 +/- 4.5 18.1 +/- 4.6 13.7 +/- 4.3 12/15/04 20.6 +/- 4.1 21.3 +/- 4.1 21.1 +/- 4.1 20.0 +/- 4.0 20.5 +/- 4.1 12/22/04 11.0 +/- 3.8 8.8 +/- 3.6 11.2 +/- 3.7 14.6 +/- 4.0 13.0 +/- 3.9 12/29/04 24.8 +/- 5.1 22.1 +/- 5.0 32.9 +I- 5.5 23.3 +/- 5.0 26.9 +I- 5.2 39

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m3 x 10-3]

Period Station Station Station Station Station Station Station Ending_

07/07/04 24.1 01

+/- 3.8 20.4 02

+/- 3.7 03 21.5 +/- 3.8 24.6 04

+I- 3.9 21.6 05

+/- 3.7 05A 20.3 +/- 3.6 21.1 06

+/- 3.7 I

07/14/04 24.6 +I- 4.8 22.5 +I- 4.5 23.6 +I- 4.6 23.2 +I- 4.5 23.3 +I- 4.5 23.1 +I- 4.5 16.8 +/- 4.2 07/21/04 20.6 +/- 4.4 21.2 +I- 4.5 24.9 +/- 4.7 24.7 +I- 4.7 22.7 +I- 4.6 24.0 +I- 4.7 17.1 +/- 4.3 07/28/04 18.7 +/. 4.4 20.3 +I- 4.2 16.4 +I- 4.0 19.8 +I- 4.2 16.8 +I- 4.0 18.8 +I- 4.1 18.4 +/- 4.1 08/04/04 15.0 +I 4.3 10.7 +I- 4.1 9.1 +I- 4.0 11.1 +1- 4.1 14.2 +I- 4.2 11.5 +I- 4.1 15.2 +I- 4.3 08/11/04 33.1 +I 4.8 24.2 +I- 4.2 21.9 +I- 4.1 20.3 +I- 4.0 25.0 +I- 4.3 24.4 +I- 4.2 28.3 +I- 4.4, 08/18/04 24.2 +I- 4.7 20.5 +I- 4.5 23.1 +I- 4.6 21.3 +I- 4.5 27.8 +I- 4.8 18.4 +I- 4.4 21.1 +I- 4.5 08/25/04 37.3 +I- 5.1 27.9 +I- 4.9 35.7 +I- 5.2 34.7 +I 5.1 31.9 +I- 5.0 32.9 +I- 5.0 29.2 +/- 4.8 09/01/04 25.8 +I- 4.5 19.4 +I- 4.1 25.9 +- 4.5 22.2 +I- 4.3 25.6 +I- 4.5 22.4 +I- 4.3 21.6 +/- 4.3 09/08/04 25.3 +I- 4.2 22.3 +I- 4.0 26.5 +I- 4.3 23.7 +I- 4.1 18.1 +I- 3.8 23.3 +I- 4.1 22.2 +/- 4.1 09/15/04 18.3 +I- 4.4 17.6 +I- 4.4 17.3 +/- 4.4 16.4 +I- 4.3 9.6 +I- 3.9 17.6 +I- 4.4 16.2 +- 4.3 09/22/24 11.5 +I- 4.1 10.8 +I- 4.1 7.2 +I- 3.9 2.6 +I- 2.3 6.2 +I. 3.9 13.3 +I- 4.2 13.0 +I- 4.2 09/29/04 32.4 +I- 5.1 31.9 +I- 5.1 31.1 +/- 5.1 33.5 +I 5.2 31.9 +I- 5.1 30.1 +- 5.0 28.7 +I- 5.0 10/05/04 33.2 +I- 5.1 26.8 +I- 4.7 33.9 +/- 5.1 34.9 +I. 5.2 29.9 +I- 4.9 27.5 +I- 4.8 29.4 +I- 4.9 10/13/04 -1.0 +1- 16.0 26.6 +- 4.1 27.2 +I- 4.2 29.5 +I- 4.3 24.6 +I- 4.0 12.9 +/- 5.2 28.7 +I- 4.2 10/20/04 34.4 +I- 6.1 22.5 +I- 4.6 26.2 +I- 4.7 24.2 +I- 4.6 16.5 +I- 4.2 24.8 +I- 4.6 26.2 +I- 4.7 10/27/04 12.6 +I- 4.2 13.1 +I- 4.1 11.8 +I- 4.1 14.9 +I- 4.3 10.9 +- 4.1 11.4 +/- 4.1 9.6 +/- 4.0 11/03/04 34.6 +I- 5.1 26.9 +I- 4.8 35.9 +I- 5.2 32.9 +I- 5.0 26.6 +I- 4.8 26.9 +I- 4.8 30.7 +/- 4.9 11/10/04 26.1 +I- 4.9 21.0 +I- 4.8 20.2 +I- 4.7 24.0 +I- 4.9 20.3 +I- 4.7 19.2 +I- 4.6 19.3 +/- 4.6 11/18/04 27.1 +I- 4.1 16.5 +I- 3.5 27.4 +I- 4.1 25.0 +I- 4.0 19.9 +I- 3.7 24.7 +I- 4.0 15.0 +I- 3.4 11/24/04 34.2 +I 5.5 26.4 +I- 5.1 27.7 +I- 5.2 35.7 +I- 5.5 22.4 +I- 4.8 30.0 +- 5.3 26.2 +I- 5.1 12/01/04 16.6 +/- 3.9 10.6 +I- 3.6 11.8 +I- 3.7 15.6 +I- 3.9 8.1 +I- 3.5 12.1 +I- 3.7 8.3 +I- 3.5 12/08/04 29.7 +I- 4.7 30.6 +I- 4.7 24.3 +I- 4.4 29.6 +I- 4.7 23.6 +I- 4.4 28.4 +I- 4.6 28.2 +I- 4.6 12/15/04 15.0 +I- 3.8 11.2 +I- 3.6 19.1 +I- 4.1 18.2 +I- 4.0 15.9 +I- 3.9 15.2 +I- 3.9 15.2 +I- 3.9 12/22/04 27.0 +I- 4.7 24.8 +I- 4.6 27.6 +I- 4.7 23.3 +I- 4.5 21.8 +I- 4.4 21.9 +I- 4.4 24.0 +I- 4.5 12/29/04 26.2 +I- 4.9 23.2 +I- 4.7 23.9 +I- 4.8 27.4 +I 4.9 19.5 +I- 4.6 24.9 +I- 4.8 23.1 +I- 4.7 40

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m3 x 10-3]

Period Ending 07/14/04 07/21/04 I

Station 07 22.4 +/-

28.2 +I-4.5 4.9 26.0 26.1 Station 21

+/- 4.6

+/- 4.7 Station 22 19.5 +- 4.3 25.6 +I- 4.7 21.8 20.6 Station 23

+/-

+I-4.4 4.5 23.5 27.7 Station 24

+I-

+I-4.6 4.8 I

07/28/04 18.9 +/- 4.1 18.8 +/- 4.1 14.0 +/- 3.9 18.6 +/- 4.1 16.2 +- 4.0 08/04/04 8.6 +I- 3.9 9.8 +/- 4.0 12.6 +/- 4.2 13.3 +/- 4.2 16.6 +/- 4.4 07/07/04 17.6 +/- 3.5 25.8 +/- 4.0 23.2 +I- 3.8 17.9 +/- 3.5 18.0 +/- 3.5 08/11/04 25.9 +I- 4.3 24.8 +I- 4.3 19.9 +/- 4.0 27.2 +I- 4.4 28.2 +I- 4.4 08/18/04 22.6 +I- 4.5 21.0 +/- 5.2 21.8 +/- 4.5 22.0 +/- 4.5 22.9 +I- 4.6 08/25/04 33.3 +/- 5.0 37.9 +I- 5.2 38.3 +I- 5.2 34.3 +I- 5.1 33.1 +/- 5.0 09/01/04 24.4 +I- 4.4 25.4 +I- 4.5 25.4 +I- 4.5 24.7 +I- 4.4 22.6 +I- 4.3 09/08/04 19.1 +/- 3.9 22.4 +/- 4.1 23.7 +I- 4.2 22.5 +I- 4.1 25.5 +I- 4.3 09/15/04 13.3 +/- 4.2 14.2 +/- 4.2 16.5 +/- 4.3 13.0 +/- 4.2 16.9 +/- 4.4 09/22/24 8.3 +/- 4.0 13.6 +/- 4.3 6.6 +I- 3.9 11.4 +/- 4.1 12.8 +/- 4.2 09/29/04 28.1 +/- 4.9 29.4 +/- 5.0 32.5 +I- 5.1 28.7 +I- 5.0 30.9 +/- 5.0 10/05/04 28.4 +I- 4.8 34.6 +I- 5.2 32.4 +I- 5.1 31.1 +/- 4.9 32.5 +/- 5.0 10/13/04 23.5 +/- 4.0 27.9 +I- 4.2 22.8 +- 3.9 25.0 +/- 4.1 29.6 +I- 4.3 10/20/04 24.6 +I- 4.6 28.8 +I- 4.8 21.7 +I- 4.5 22.7 +I- 4.6 24.0 +/- 4.6 10/27/04 10.9 +/- 4.1 13.5 +/- 4.2 10.1 +I- 4.0 9.0 +/- 3.9 11.5 +/- 4.1 11/03/04 26.2 +I- 4.7 32.5 +/- 5.0 26.9 +I- 4.8 33.3 +I- 5.1 30.5 +/- 4.9 11/10/04 22.9 +I- 4.9 22.6 +I- 4.8 24.0 +- 4.8 22.1 +/- 4.9 25.2 +/- 4.9 11/18/04 22.0 +- 3.8 25.2 +/- 4.0 22.1 +I- 3.9 22.4 +I- 3.8 23.7 +/- 4.0 11/24/04 28.9 +I- 5.2 29.4 +I- 5.2 30.6 +I- 5.3 28.0 +/- 5.2 29.9 +I- 5.2 12/01/04 8.3 +I- 3.5 16.2 +/- 4.0 10.5 +I- 3.6 12.6 +/- 3.7 13.1 +/- 3.8 12/08/04 23.5 +I- 4.3 28.3 +I- 4.6 29.9 +I- 4.7 27.4 +I- 4.6 28.5 +I- 4.6 12/15/04 7.9 +I- 3.4 18.5 +/- 4.1 15.4 +- 3.9 10.1 +/- 3.5 15.6 +/- 3.9 12/22/04 17.1 +/- 4.2 25.5 +I- 4.6 23.5 +I- 4.5 18.9 +/- 4.3 24.5 +/- 4.6 12/29/04 22.3 +I- 4.7 20.3 +/- 4.6 22.7 +I- 4.7 25.4 +I- 4.9 24.7 +/- 4.8 41

Table 3-4 Airborne Iodine I- 131

[pCi/m3 x 10-3]

Period Ending_

01/07/04 6.0 Station 01

+/- 16.0 -5.0 Station 02

+/- 14.0 8.0 Station 03

+/-

15.0 13.0 Station 04

+/- 16.0 8.0 Station 05

+/- 16.0

-2.0 Station 05A

+/- 14.0 -5.0 Station 06

+/-

I 16.0 01/14/04 -3.0 +/- 15.0 18.0 +/- 16.0 -3.0 +/- 13.0 5.0 +/- 16.0 -2.0 +/- 15.0 5.0 +/- 16.0 -8.0 +/- 18.0 01/21/04 -10.0 +/ 21.0 -9.0 +/- 20.0 4.0 +/- 24.0 -21.0 +/- 22.0 2.0 +/- 22.0 5.0 +/- 19.0 -16.0 +/- 19.0 01/28/04 -2.0 +/ 20.0 6.0 +/- 26.0 0.0 +/- 24.0 -2.0 +- 22.0 6.0 +/- 20.0 0.0 +/- 23.0 6.0 +/- 23.0 02/04/04 3.0 + 15.0 -18.0 +/- 17.0 -2.0 +/- 16.0 11.0 +/- 14.0 3.0 +/- 14.0 -8.0 +/- 17.0 0.0 +/- 17.0 02/11/04 3.0 +/- 21.0 12.0 +/- 19.0 -5.0 +/- 18.0 7.0 +/- 20.0 0.0 +/- 17.0 -9.0 +/- 19.0 -2.0 +/- 18.0 02/18/04 -9.0 +/- 16.0 -7.0 +/- 15.0 -1.0 +/- 15.0 -10.0 +/- 13.0 -1.0 +/- 14.0 6.0 +/- 14.0 -4.0 +/- 15.0 02/25/04 2.0 +/- 17.0 -2.0 +/- 16.0 3.0 +/- 13.0 0.0 +/- 13.0 2.0 +/- 13.0 2.0 +/- 16.0 5.0 +I- 16.0 03/03/04 -8.0 +/- 15.0 -3.0 +/- 14.0 -8.0 +/- 15.0 -5.0 +/- 14.0 -2.0 +/- 15.0 8.0 +/- 17.0 16.0 +/- 16.0 03/10/04 2.0 +- 17.0 3.0 +/- 21.0 -12.0 +/- 18.0 16.0 +/- 17.0 -12.0 +/- 17.0 12.0 +/- 16.0 -2.0 +/- 16.0 03/17/04 -2.0 +/- 14.0 -3.0 +/- 15.0 2.0 +/- 15.0 2.0 +/- 13.0 -19.0 +/- 29.0 -2.0 +I- 15.0 -8.0 +/- 15.0 03/24/04 2.0 +/- 14.0 -12.0 +/- 18.0 -3.0 +/- 17.0 12.0 +/- 17.0 10.0 +/- 15.0 -2.0 +/- 15.0 13.0 +/- 15.0 03/31/04 -3.0 +/- 12.0 2.0 +/- 17.0 -14.0 +/- 13.0 -5.0 I- 13.0 -10.0 +/- 19.0 -6.0 +I- 15.0 -2.0 +/- 16.0 04/06/04 -7.0 +/- 13.0 4.0 +/- 15.0 0.0 +/- 14.0 -3.0 +/- 12.0 -2.0 +/- 15.0 -8.0 +1- 14.0 -2.0 +/- 15.0 04/14/04 6.0 +/- 14.0 -1.0 +/- 12.0 -1.0 +/- 15.0 -4.0 +/- 15.0 1.0 +/- 15.0 6.0 +/- 12.0 12.0 +/ 13.0 04/21/04 -11.0 +/- 13.0 5.0 +/- 15.0 -22.0 +/- 16.0 2.0 +/- 16.0 -11.0 +- 16.0 -2.0 +/- 13.0 3.0 +/- 14.0 04/28/04 5.0 +/- 17.0 -5.0 +/- 16.0 0.0 +/- 14.0 -11.0 +/- 17.0 10.0 +/- 15.0 3.0 +/- 16.0 -6.0 +/- 17.0 05/05/04 11.0 +/- 20.0 -7.0 +/- 13.0 11.0 +/- 13.0 -1.0 +/- 12.0 -1.0 +/- 13.0 3.0 +/- 14.0 -1.0 15.0' 05/12/04 -25.0 +/- 15.0 2.0 +/- 14.0 3.0 +/- 15.0 5.0 +/- 16.0 17.0 +/- 17.0 18.0 +/- 17.0 -10.0 +/ 15.0 05/19/04 -1 9.0 +/ 17.0 -3.0 +/- 17.0 -13.0 +/- 15.0 -6.0 +/- 16.0 -3.0 +/- 16.0 -8.0 +I- 14.0 -5.0 +/- 17.0 05/26/04 -6.0 +/- 17.0 11.0 +/- 16.0 13.0 +/- 18.0 19.0 +/- 17.0 6.0 +/- 21.0 -19.0 +/- 20.0 -19.0 +/- 21.0 06/02/04 7.0 +/- 20.0 -15.0 +/- 20.0 4.0 +/- 21.0 -4.0 +/- 20.0 -2.0 +/- 19.0 -20.0 +/- 18.0 -2.0 +/- 20.0 06/09/04 -5.0 +/- 18.0 -5.0 +/- 16.0 -2.0 +/- 18.0 -5.0 +/- 17.0 2.0 +/- 15.0 -19.0 +/- 20.0 -5.0 +/- 14.0 06/16/04 10.0 +/- 17.0 3.0 +/- 16.0 0.0 +/- 16.0 5.0 +/- 18.0 -16.0 +/- 19.0 -2.1 +/- 8.1 18.0 +/- 18.0 06/23/04 -16.0 +/- 20.0 -12.0 +/- 22.0 16.0 +/- 21.0 -12.0 +/- 17.0 16.0 +/- 23.0 -10.0 +/ 21.0 -10.0 +/- 19.0 06/30/04 8.0 +/- 19.0 0.0 +/- 18.0 10.0 +/- 20.0 0.0 +/- 17.0 -8.0 +/- 21.0 8.0 +/- 22.0 -12.0 +/- 18.0 42

Table 3-4 Airborne Iodine I - 131

[pCi/m3 x 10-3]

Period Ending 01/07/04 I

-6.0 Station 07

+/- 11.0 -14.0 Station 21

+1- 17.0 I

-9.0 Station 22 23.0 I

-4.C Station

+/-

23 26.0 -5.0 Station 24

+/-

I 24.0 01/14/04 10.0 +/- 15.0 3.0 +1- 14.0 -5.0 16.0 6.C +-/- 13.0 10.0 +/- 18.0 01/21/04 -7.0 +/- 21.0 -9.0 +1- 20.0 5.0 +1- 21.0 2.C +/- 20.0 -11.0 +/- 18.0 01/28/04 10.0 +/- 22.0 -16.0 +1- 21.0 -8.0 20.0 14.CI +/- 21.0 0.0 +/- 21.0

+1-02/04/04 11.0 +/- 17.0 10.0 +1- 14.0 -5.0 16.0 -3.CI +/- 17.0 -2.0 +I- 18.0 02/11/04 0.0 +/- 18.0 0.0 +1- 18.0 4.0 +1- 16.0 4.C +/- 20.0 -5.0 +/- 23.0 02/18/04 4.0 +/- 17.0 7.0 +1- 14.0 -3.0 +1- 14.0 7.CI +/- 15.0 15.0 +/- 15.0 02/25/04 0.0 +/- 16.0 -2.0 +1- 11.0 2.0 +1- 16.0 5.CI +/- 15.0 -8.0 +/- 14.0 03/03/04 -8.0 +/- 17.0 0.0 +1- 17.0 0.0 +1- 17.0 2.CI +/- 18.0 -5.0 +1- 14.0 03/10/04 -2.0 +/- 17.0 -2.0 +1- 17.0 7.0 +1- 19.0 -2.CI +I- 16.0 9.0 +/- 18.0 03/17/04 2.0 +/- 15.0 -8.0 +1- 17.0 5.0 12.0 -8.CI +/- 14.0 2.0 +/- 17.0

+1-03/24/04 -2.0 +1- 16.0 -6.0 +1- 17.0 8.0 14.0 7.CI +1- 15.0 2.0 +/- 16.0

+1-03/31/04 -8.0 +1- 15.0 -10.0 +1- 18.0 11.0 16.0 0.0I +/- 15.0 2.0 +/- 16.0

+1-04/06/04 -2.0 +/- 17.0 0.0 +1- 14.0 I 9.0 14.0 -3.CI +/- 14.0 -6.0 +/- 16.0

+1-04/14/04 6.0 +/- 14.0 -6.0 +l 13.0 -7.0 14.0 10. +/- 11.0 -6.0 +/- 15.0

+1-04/21/04 -11.0 +/- 17.0 -2.0 +1- 16.0 -5.0 19.0 -1 1.cI +/- 12.0 15.0 +/- 19.0 04/28/04 2.0 +/- 14.0 0.0 +1- 20.0 3.0 16.0 -10.cI +/- 16.0 -3.0 +/- 15.0 05/05/04 -5.0 +/. 12.0 0.0 +1- 13.0 -3.0 11.0 10.cI +/- 13.0 4.0 +/- 15.0

+1-

.05/12/04 2.0 +/- 17.0 8.0 +1- 16.0 5.0 16.0 -3.C I +/- 18.0 -13.0 +/- 16.0

+1-05/19/04 -6.0 +/- 13.0 -5.0 +1- 11.0 -10.0 17.0 -5.C I +/- 15.0 -8.0 +/- 14.0

+1-05/26/04 2.0 +/- 20.0 2.0 +1- 16.0 -10.0 20.0 -11.cI +/- 20.0 4.0 +/- 19.0 06/02/04 -7.0 +/- 23.0 -7.0 +1- 17.0 7.0 21.0 -21.C I +/- 19.0 4.0 +/- 22.0 06/09/04 0.0 +/- 16.0 -10.0 +1- 18.0 10.0 18.0 8.CI +/- 18.0 -6.0 +/- 15.0 06/16/04 6.0 +/- 16.0 -10.0 +1- 15.0 13.0 17.0 -11.CI +/- 20.0 -3.0 +/ 16.0 06/23/04 -6.0 +1- 19.0 0.0 +1- 24.0 0.0 18.0 4.CI +/- 19.0 -6.0 +/- 19.0 06/30/04 -18.0 +/- 20.0 0.0 +1- 16.0 12.0 23.0 -8.CI +/- 21.0 2.0 +/- 21.0 43

Table 3-4 Airborne Iodine I- 131

[pCi/m3 x 10-3]

Period Ending 07/07/04 20.0 Station 01

+/- 17.0 3.0 Station 02

+/- 20.0 3.0 Station 03

+/- 16.0 -5.0 Station 04

+/- 19.0 -11.0 Station 05

+/- 18.0 -3.0 Station 05A

+/- 17.0

-3.0 Station 06

+/- 17.0 I

07/21/04 8.0 +/- 21.0 6.0 +/- 25.0 8.0 +/- 19.0 -8.0 +I- 18.0 -8.0 +I- 17.0 -14.0 +I- 22.0 27.0 +/- 24.0 07/21/04 15.0 +1- 17.0 -12.0 +/- 20.0 9.0 +/- 22.0 -8.0 +I- 21.0 6.0 +I- 20.0 4.0 +I- 21.0 -10.0 +/- 22.0 07/28/04 -11.0 +/- 19.0 10.0 +/- 17.0 2.0 +/- 13.0 -8.0 +I- 16.0 14.0 +I- 16.0 17.0 +/- 17.0 -14.0 +I- 19.0 08/04/04 11.0 +1- 15.0 0.0 +1- 18.0 0.0 +/- 16.0 -8.0 +I- 17.0 3.0 +I- 16.0 0.0 +I- 18.0 3.0 +/- 19.0 08/11/04 3.0 +1- 14.0 -5.0 +/- 20.0 -12.0 +I- 19.0 13.0 +I- 15.0 -4.0 +I- 14.0 -3.0 + 19.0 I- -7.0 +/- 18.0 08/18/04 7.0 +1- 19.0 -11.0 +/- 16.0 -7.0 +I- 18.0 -8.0 +I- 19.0 1.0 +I- 18.0 -7.0 +1- 19.0 8.0 +/- 19.0 08/25/04 13.0 +/- 15.0 -3.0 +/- 17.0 18.0 +I- 17.0 -9.0 +1- 17.0 8.0 +I- 17.0 7.0 +/- 16.0 7.0 +/- 16.0 09/01/04 -19.0 +/- 20.0 13.0 +1- 21.0 -4.0 +I- 18.0 15.0 +I- 25.0 4.0 +I- 18.0 -6.0 +I- 23.0 15.0 +/- 23.0 09/08/04 1.0 +/- 15.0 2.0 +/- 16.0 5.0 +I- 17.0 5.0 +I- 16.0 -4.0 +I- 16.0 2.0 +1- 22.0 3.0 +/- 14.0 09/15/04 -6.0 +/- 16.0 1.0 +I- 12.0 13.0 +I- 15.0 -9.0 +1- 15.0 6.0 +- 16.0 -6.0 +I- 15.0 -13.0 +/- 16.0 09/22/04 14.0 +/- 16.0 -6.0 +/- 16.0 3.0 +I- 18.0 -3.0 +I- 16.0 -5.0 +I- 16.0 -5.0 +/- 17.0 19.0 +/- 17.0 09/29/04 -7.0 +/- 14.0 -3.0 +1- 11.0 4.0 +I- 14.0 -1.0 +1- 16.0 1.0 +I- 13.0 3.0 +/- 11.0 -13.0 +/- 14.0 10/05/04 -2.0 +/- 20.0 11.0 +/- 20.0 -11.0 +1- 16.0 6.0 +I- 18.0 7.0 +I- 20.0 2.0 +/- 16.0 9.0 +/- 20.0 10/13/04 0.0 +/- 25.0 -3.0 +/- 14.0 12.0 +I- 13.0 5.0 +I- 14.0 3.0 +I- 15.0 9.0 +- 10.0 1.0 +/- 13.0 10/20/04 -2.0 +/- 29.0 -10.0 +/- 16.0 8.0 +I- 16.0 -6.0 +I- 16.0 0.0 +1- 18.0 2.0 +/- 15.0 0.0 +/- 15.0 10/27/04 -6.0 +/- 15.0 -4.0 +/- 16.0 6.0 +/- 15.0 6.0 +/- 15.0 -8.0 +I- 17.0 8.0 +I- 15.0 6.0 +/- 14.0 11/03/04 15.0 +/- 17.0 8.0 +/- 17.0 -15.0 +/- 17.0 -3.0 +/- 14.0 -6.0 +I- 17.0 -5.0 +/- 15.0 -3.0 +/- 18.0 11/10/04 6.0 +/- 21.0 6.0 +/- 23.0 -4.0 +/- 21.0 2.0 +I- 21.0 9.0 +1- 21.0 4.0 +I- 22.0 -17.0 +/- 25.0 11/18/04 1.0 +/- 14.0 11.0 +/- 12.0 8.0 +/- 14.0 7.0 +I- 16.0 6.0 +I- 12.0 6.0 +I- 15.0 -4.0 +/- 18.0 11/24/04 -2.0 +/- 23.0 -8.0 +/- 30.0 -8.0 +I- 21.0 0.0 +1- 21.0 10.0 +I- 22.0 2.0 +1- 22.0 -12.0 +/- 27.0 12/01/04 -4.0 +/- 17.0 6.0 +/- 14.0 0.0 +1- 15.0 6.0 +I- 16.0 -9.0 +/- 15.0 -1.0 +/- 14.0 -10.0 +/- 15.0 12/08/04 17.0 +/- 28.0 5.0 +/- 30.0 0.0 +1- 25.0 0.0 +1- 28.0 -2.0 +/- 30.0 -26.0 4- 27.0 23.0 +/- 27.0 12/15/04 -2.0 +/- 17.0 6.0 +I- 16.0 -11.0 +/- 14.0 8.0 +I- 19.0 8.0 +/- 14.0 6.0 +/- 17.0 -6.0 +- 16.0 12/22/04 -12.0 +6- 24.0 9.0 +/- 26.0 6.0 +/- 22.0 16.0 +/- 24.0 25.0 +/- 24.0 0.0 +/- 32.0 3.0 +/- 19.0 12/29/04 7.5 +/- 8.3 6.0 +/- 11.0 -6.0 +/- 10.0 -6.0 +I- 12.0 2.9 +1- 9.6 -11.0 +/- 12.0 -5.0 +/- 10.0 44

Table 3-4 Airborne Iodine I- 131

[pCi/m3 x 10-3]

Period Ending 07/07/04 I

-6.0 Station 07 17.0 I

-2.0 Station 21

+/- 16.0 I

-6.0 Station 22

+1- 18.0 I

-6.0 Station

  • 23

+/- 18.0

_24

-6.0 Station

+/- 15.0 I

07/21/04 4.0 17.0 -2.0 +/- 19.0 -4.0 +l 16.0 -4.0 +/- 19.0 -19.0 +1- 22.0 07/21/04 2.0 18.0 6.0 +/. 20.0 2.0 +1- 20.0 10.0 +I- 23.0 0.0 +1- 14.0 07128/04 12.0 17.0 5.0 +/- 15.0 10.0 +1- 19.0 3.0 +I- 18.0 14.0 +/- 19.0 08/04/04 6.0 16.0 5.0 +/- 16.0 5.0 +l 15.0 6.0 +I- 19.0 -5.0 +I- 14.0

+1-08/11/04 2.0 16.0 9.0 +/- 17.0 12.0 +1- 16.0 2.0 +/- 19.0 7.0 +- 15.0 08/18/04 -1.0 16.0 -10.0 +/- 23.0 5.0 +1- 18.0 -5.0 +/- 16.0 17.0 +I- 21.0

+1-08/25/04 -3.0 17.0 2.0 +/- 19.0 6.0 +1- 16.0 -2.0 +/- 17.0 -9.0 +- 19.0 09/01/04 -4.0 19.0 -23.0 +/- 25.0 10.0 +1- 23.0 -2.0 +/- 21.0 -19.0 +/- 23.0 09/08/04 -1.0 17.0 2.0 +/- 15.0 0.0 +1- 15.0 -6.0 +/- 13.0 5.0 +/- 14.0 09/15/04 7.0 16.0 6.0 +I- 14.0 3.0 +1- 16.0 -3.0 +/- 16.0 -10.0 +/- 16.0 09/22/04 8.0 15.0 -3.0 +/- 15.0 5.0 +1- 19.0 2.0 +/- 16.0 -3.0 +/ 16.0 09/29/04 -1.0 15.0 1.0 +I- 13.0 4.0 +1- 14.0 7.0 +/- 16.0 6.0 +/- 14.0 10/05/04 0.0 19.0 -13.0 +I- 17.0 0.0 +1- 19.0 -9.0 +/- 18.0 -6.0 +/- 20.0

+/.

10/13/04 5.0 15.0 1.0 +I- 13.0 -4.0 +l 13.0 3.0 +/- 13.0 10.0 +/- 13.0 10/20/04 -2.0 15.0 -5.0 +I- 16.0 15.0 +1- 17.0 -2.0 +/- 17.0 -21.0 +/- 17.0 10/27/04 2.0 15.0 -5.0 +I- 17.0 -9.0 +l 16.0 -5.0 +/- 15.0 6.0 +I- 17.0 11/03/04 9.0 13.0 14.0 +I- 18.0 -2.0 +1- 16.0 16.0 +/- 17.0 -6.0 +I- 16.0 11/10/04 -9.0 23.0 4.0 +I- 21.0 -11.0 +l 20.0 2.0 +/- 21.0 7.0 +I- 20.0 11/18/04 -7.0 15.0 -1.0 +I- 17.0 8.0 +1- 16.0 3.0 +/. 16.0 -14.0 +/- 17.0 11/24/04 -2.0 21.0 2.0 +I- 29.0 -14.0 +l 25.0 6.0 +/- 24.0 -2.0 +/- 24.0 12/01/04 4.0 13.0 7.0 +/- 14.0 -9.0 +l 15.0 -4.0 +/- 15.0 9.0 +- 14.0 12/08/04 -11.0 28.0 8.0 +/- 30.0 10.0 +1- 31.0 -2.0 +I- 30.0 2.0 +/- 28.0 12/15/04 -19.0 19.0 -11.0 +/- 16.0 13.0 +l 17.0 -5.0 +I- 18.0 2.0 +/. 19.0 12/22/04 8.0 23.0 24.0 +/- 20.0 -6.0 +l 23.0 22.0 +I- 24.0 0.0 +/- 25.0 12/29/04 -6.0 +/- 12.0 10.0 +/- 13.0 -5.0 +/- 13.0 3.4 +/- 9.8 -10.0 +/- 11.0 45

Table 3-5 Airborne Particulate Gamma Spectra and Strontium

[pCi/m3 x1 0-3]

Sampling Quarter I l1-ocation I Be-7 I K-40 I Cs-13 I Cs-137 01 96.0 +/- 34.0 -36.4 +/- 8.2 -0.9 +/- 1.2 -0.6 +/- 1.5 02 79.0 +/- 32.0 -26.0 +/- 12.0 0.0 +/- 1.2 0.2 +/- 1.8 03 84.0 +/- 34.0 -19.0 +/- 11.0 0.3 +/- 1.1 -0.2 +/- 1.6 04 109.0 +/- 34.0 -43.1 +/- 9.5 -0.1 +/- 1.0 0.3 +/- 1.7 05 80.0 +/- 34.0 -32.0 +/- 15.0 0.2 +/- 1.1 0.5 +/- 1.7 05A 92.0 +/- 33.0 -27.0 +/- 12.0 0.0 +/- 1.0 -0.2 +/- 1.6 06 112.0 +/- 38.0 -29.0 +/- 11.0 0.5 +/- 1.8 1.2 +/- 1.8 07 102.0 +/- 33.0 -27.0 +/- 12.0 -0.4 +/- 1.2 0.8 +/- 1.8 21 63.0 +/- 33.0 -20.0 +/- 17.0 0.3 +/- 1.0 -1.8 +/- 1.6 22 108.0 +/- 33.0 -26.0 +/- 11.0 0.0 +/- 1.1 -1.2 +/- 1.4 23 94.0 +/- 37.0 -25.0 +/- 12.0 0.2 +/- 0.9 1.2 +/- 1.8 24 105.0 +/- 36.0 -11.0 +/- 16.0 -0.1 +/- 0.9 -0.9 +/- 1.4 Sampling Quarter 2 ILocation 01 I Be-7 125.0 +/- 34.0

- K-40

-0.3 +/- 12.0 I Cs-13 0.8 +/- 1.1 Il Cs-137

-0.4 +/- 1.7 I Sr-89 2.0 +/- 13.0 I

-0.8 Sr-90

+/- 1.7 I

02 136.0 +/- 35.0 -0.5 +/- 11.0 0.1 +/- 0.8 -1.1 +/- 1.7 -2.1 +/- 8.4 0.3 +/- 1.2 03 162.0 +/- 37.0 1.0 +/- 15.0 0.2 +/- 0.9 -0.1 +/- 1.6 -2.7 +/- 8.0 -0.1 +/- 1.1 04 143.0 +/- 35.0 -1.0 +/- 14.0 0.3 +/- 1.1 -0.2 +/- 1.7 2.2 +/- 9.7 0.3 +/- 1.3 05 141.0 +/- 23.0 0.0 +/- 5.6 -0.1 +/- 0.5 -0.1 +/- 0.5 3.3 +/- 9.0 0.4 +/- 1.2 05A 129.0 +/- 34.0 -2.8 +/- 7.5 -0.7 +/- 0.9 0.0 +/- 1.6 -2.0 +/- 1.1 0.1 +/- 1.5 06 130.0 +/- 33.0 -4.6 +/- 8.8 0.3 +/- 0.8 -0.4 +/- 0.7 -4.0 +/- 1.1 0.9 +/- 1.7 07 114.0 +/- 29.0 -4.8 +/- 7.9 -0.4 +/- 0.5 0.5 +/- 0.6 5.0 +/- 12.0 0.3 +/- 1.5 21 109.0 +/- 27.0 2.1 +/- 8.6 -0.1 +/- 0.9 0.1 +/- 0.8 -6.4 +1- 7.7 0.5 +/- 1.2 22 121.0 +/- 29.0 0.7 +/- 8.1 -0.2 +/- 0.7 -0.4 +/- 0.8 1.7 +/- 9.8 1.2 +/- 1.4 23 108.0 +/- 21.0 1.6 +/- 6.8 -0.2 +/- 0.5 0.5 +/- 0.5 -1.0 +/- 13.0 0.4 +/- 1.8 24 99.0 +/- 27.0 -10.2 +/- 7.7 0.1 +/- 0.7 -0.2 +/- 0.6 -4.0 +/- 10.0 1.0 +/- 1.6 Sr-89/90 sampled In2nd Qtr.

46

Table 3-5 Airborne Particulate and Strontium Gamma Spectra

[pCi/m3 x1 0-3]

Sampling Quarter 3 CS-137 l1-ocation l Be-7 l K-40 CS-1 3

+/- +/-

I 01 109.0 +/- 31.0 -0.6 +/- 9.0 -0.1 1.5 -0.5 1.5 02 84.0 +1- 29.0 1.0 +/- 10.0 0.2 +/- 0.9 0.4 +/- 1.6 03 124.0 +/- 30.0 -7.0 +/- 11.0 1.1 +/- 1.0 -0.5 +/- 1.4 04 87.0 +/- 28.0 -12.8 +/- 9.0 0.1 +/- 0.6 0.4 +/- 1.6 05 110.0 +/- 16.0 3.0 +/- 5.3 -0.1 +/- 0.4 -0.2 +/- 0.4 05A 102.0 +/- 30.0 -5.7 +1- 8.9 0.1 +/- 0.5 1.0 +/- 1.5 06 100.0 +/- 31.0 -2.0 +/- 10.0 -0.5 +/- 0.9 0.0 +/- 1.5 07 89.0 +/- 30.0 8.0 +/- 13.0 0.1 +/- 0.6 -0.9 +/- 1.5 21 120.0 +/- 32.0 1.0 +/- 12.0 0.3 +/- 1.0 -0.6 +/- 1.4 22 124.0 +/- 32.0 -4.0 +/- 12.0 0.4 +/- 0.7 -0.7 +1- 1.5 23 108.0 +/- 29.0 5.0 +/- 14.0 -0.5 +/- 0.9 -0.6 +/- 1.5 24 130.0 +/- 32.0 5.0 +/- 13.0 -0.3 +/- 1.0 -0.9 +/- 1.5 Sampling Quarter 4 l Be-7 . K-40 Cs-13 Cs-137 01 142.0 +/- 37.0 2.2 +1- 8.9 0.3 +/- 0.7 0.1 +/- 0.6 02 90.0 +/- 28.0 4.7 +1- 8.5 0.4 +/- 0.7 -0.1 +/- 0.7 03 930.0 +/- 30.0 -7.3 +1- 8.6 -0.2 +/- 0.6 -0.1 +/- 0.7 04 92.0 +1- 28.0 0.5 +/- 7.0 0.1 +/- 0.7 0.3 +/- 0.8 05 82.0 +/- 31.0 -0.5 +/- 9.2 -0.6 +/- 0.7 0.1 +/- 0.5 05A 109.0 +/- 31.0 4.0 +/- 10.0 0.6 +/- 0.8 0.2 +/- 0.6 06 80.0 +/- 28.0 5.0 +/- 10.0 0.0 +/- 0.5 -0.1 +/- 0.4 07 75.0 +/- 27.0 5.0 +/- 11.0 -0.3 +1- 6.3 -0.1 +/- 0.6 21 106.0 +/- 33.0 -3.4 +1- 8.3 -0.4 +/- 0.7 -0.2 +/- 0.5 22 79.0 +/- 28.0 0.7 +/- 8.8 -0.7 +/- 6.8 0.4 +/- 0.7 23 94.0 +/- 30.0 6.3 +1- 9.8 -0.3 +/- 0.6 0.1 +/- 0.7 24 124.0 +/- 32.0 1.7 +/- 6.5 0.1 +/- 0.6 0.0 +/- 0.8 47

Table 3-6 Soil Gamma Spectra and Strontium

[pCi/kg]

collection date: 07/14/04 l Station I Sr-89 l Be-7 I K-40 I Cs-134 I Cs-137 I Th-228 I 01 180 +/- 170 -20 +/- 130 100 +/- 210 18600 +/- 980 1 +/- 22 -1 +/- 27 1300 +/- 100 02 120 +/- 190 60 +/- 150 170 +/- 270 7270 +/- 970 18 +/- 25 48 +/- 41 540 +/- 120 03 0 +1- 190 180 +/- 150 -180 +/- 390 5500 +/- 1100 36 +1- 56 430 +/- 84 570 +/- 170 04 20 +/- 200 130 +/- 160 230 +/- 210 4800 +/- 510 -11 +/- 76 242 +/- 37 621 +/- 83 05 90 +/- 180 60 +/- 140 450 +/- 390 14700 +/- 910 -6 +/- 24 191 +/- 43 1300 +/- 110 05A -110 +/- 190 160 +/- 150 530 +/- 430 10860 +/- 750 -31 +/- 83 27 +/- 27 1038 +/- 93 06 -30 +/- 210 40 +/- 150 160 +/- 350 9500 +/- 1000 19 +/- 37 313 +/- 71 2140 +/- 170 07 70 +/- 190 30 +/- 130 330 +/- 380 5400 +/- 1000 16 +/- 42 17 +/- 47 2240 +/- 210 21 70 +/- 170 240 +/- 160 990 +/- 470 13900 +/- 1200 -11 +/- 31 46 +1- 46 2120 +/- 180 22 10 +/- 210 110 +/- 150 -80 +/- 420 19300 +/- 1800 10 +/- 43 85 +/- 71 1080 +/- 220 23 -70 +/- 240 110 +/- 170 60 +/- 410 26400 +/- 1900 -13 +/- 37 246 +1- 72 1910 +/- 200 24 40 +/- 200 60 +/- 140 450 +/- 430 4600 +/- 1000 -5 +/- 44 360 +/- 94 1090 +/- 200 48

Table 3-7 Precipitation Gamma Spectra

[pCi/L] .

06/29/2004 Sampling Location I Be-7 Cr-51 l Mn-54 I Fe-59 Co-58 I Co-60 l K-40 I 1 l 01A 11.0 +/- 19.0 -12.0 +/- 23.0 1.0 +/- 21.0 -1.5 +/- 1.8 -0.1 +/- 4.3 -0.7 +/- 1.9 0.8 +/- 1.7 I Zn-65 I Zr-95 I Nb-95 I Ru-103 I Ru-106 I Sb-125 l 1-131 I 01A -3.0 +/- 5.9 2.2 +/- 3.2 0.6 +/- 2.0 0.8 +/- 2.3 22.0 +/- 17.0 0.0 +/- 4.9 0.9 +/- 5.4 01A 0 Cs-134 0.6 +/- 1.9 0 Cs-137 0.6 +/- 1.8 1 Ba-140 1.2 +/- 3.7 1 La-140 1.4 +/- 4.3 3 Th-228 3.3 +/- 6.2 I

12/29/2004 Sampling Location I Be-7 I K-40 I Cr-51 I Mn-54 I Fe-59 Il Co-58 I Co-60 I 01A 11.7 +/- 9.9 -2.0 +/- 11.0 4.0 +/- 12.0 -0.3 +/- 0.6 0.5 +/- 2.5 -0.5 +/- 0.8 -0.2 +/- 0.6 I Zn-65 I Zr-95 I Nb-95 I Ru-103 I Ru-106 I Sb-125 I 1-131 I 01A 0.7 +/- 1.9 0.2 +/- 1.5 0.0 +/- 1.1 -0.6 +/- 1.6 2.0 +/- 5.9 0.4 +/- 1.8 -3.0 +/- 11.0 I Cs-134 l Cs-137 I Ba-140 l La-140 I Th-228 I OA 0.3 +/- 0.7 -0.6 +/- 0.7 -2.4 +/- 3.9 -2.8 +/- 4.5 2.7 +/- 2.9 49

Table 3-7 Precipitation Gross Beta

[pci/L]

Sampling Date j Gross Beta l Rainfall (inches) 01/28/04 15.0 +/ 3.0 0.72 02/25/04 5.2 +1- 2.1 2.49 03/31/04 6.1 +/- 2.3 2.13 04/28/04 6.5 +/- 2.2 3.85 05/26/04 4.1 +/ 2.1 2.46 06/29/04 4.6 +/- 2.5 5.43 07/28/04 5.5 +1- 2.2 5.98 09/01/04 4.9 +/ 2.2 4.23 09/29/04 3.9 +/ 2.0 5.79 10/27/04 9.8 +/- 2.6 1.71 11/24/04 1.9 +/ 1.7 3.89 12/29/04 5.1 +/- 2.0 3.23 Total =41.91" 50

Table 3-8 Milk Gamma Spectra and Strontium

[pCi/L]

Station 12 Date Sr-89

[ I Sr-90 1-131 Cs-137 lBa-140 l La140 01/21/04 1410.0 +I- 120.0 [a] [a] -0.75 +I- 0.28 0.0 +/- :3.2 -1.4 +/ 2.9 3.2 +I- 4.1 3.6 4- 4.7 02/11/04 1320.0 +I- 130.0 [a] [a] -0.05 +/- 0.25 2.7 +4- ' 3.8 -2.0 +- 3.7 -2.6 4- 6.4 -3.0 4- 7.4 03/24104 1470.0 +I- 170.0 -3.7 +/- 4.5 0.0 +/- 0.9 0.24 +/- 0.50 -2.8 +4- j4.5 -0.7 +/- 4.0 6.3 +l 7.4 7.2 4- 8.5 04/14/04 1370.0 +I- 120.0 [a] [a] -0.12 +/- 0.04 3.4 +/1-. 3.8 0.6 +/- 2.9 -2.6 4- 5.3 -3.0 +/- 6.1 05/19/04 1430.0 +I- 110.0 [a] [a] -0.05 +I- 0.02 2.2 +/- ,2.9 1.2 +/ 2.6 1.3 +/- 5.7 1.5 4/- 6.6 06/23/04 1338.0 +I- 97.0 -1.1 +I- 3.8 -0.2 +/- 0.9 -0.15 +/- 0.27 -0.7 +/- ,2.8 -1.9 +/- 2.6 0.3 +/- 4.9 0.4 +/- 5.6 07/21/04 1310.0 +l 120.0 [a] [a] -0.07 +/- 0.03 1.5 +/- 3.3 0.5 +/ 3.0 -1.8 +/- 6.0 -2.1 +/- 6.9 08/25/04 1210.0 +/- 140.0 [a] [a] 0.09 4- 0.24 1.6 +/- 44.1 -1.4 4- 4.0 -1.1 4- 5.1 -1.2 4- 5.8 09/15/04 1254.0 +1- 87.0 0.8 +/- 0.8 0.1 +/- 0.6 0.32 +/ 0.41 2.7 +I-. 3.8 -1.0 +/- 3.3 -3.0 +/- 6.4 -3.4 4- 7.3 10/21/04 1410.0 4- 150.0 [a] [a] -0.06 +/- 0.02 -0.9 +/- 44.0 -1.7 4/ 4.2 2.5 4- 6.6 2.9 4- 7.5 11/18/04 1530.0 +I- 110.0 [a] [a] 0.15 +/ 0.39 0.9 +/- 3.1 1.6 4- 3.4 3.2 4- 6.0 3.7 +/- 6.9 12/15/04 1530.0 +/- 170.0 1.0 +/- 3.7 -0.4 +/- 1.2 -0.03 4- 0.22 0.0 +/- 44.7 1.1 4- 4.7 -0.7 4- 6.3 -0.8 4- 7.2 Station 13 Date l K-40 Sr-89 l Sr-90 1-131 I Cs-134 Cs-137 lBa-140 lLa-140 01/21/04 1330.0 +/ 130.0 [a] [a] 1.30 +l 2.90 1.8 +/- 3.9 -0.8 +/- 3.2 -3.6 +I- 5.1 -4.1 4- 5.9 02/11/04 1300.0 +/ 130.0 [a] [a] -1.23 +/- 0.51 -2.0 +/- 3.7 -0.5 4- 3.5 -3.4 +l 5.7 -3.9 +I- 6.5 03/24/04 1440.0 +l- 110.0 1.7 +/- 5.4 2.8 +I- 1.1 0.19 +/- 0.48 2.6 +/- 3.6 1.4 +/- 3.0 0.0 +/- 5.4 0.0 +/- 6.3 04/14/04 1360.0 +/- 110.0 [a] [a] -0.12 +- 0.05 -0.4 +I- 3.1 0.0 +/- 2.8 0.6 +/ 3.8 0.7 +/- 4.3 05/19/04 1360.0 4- 130.0 [a] [a] 0.11 4- 0.33 0.0 +I- 4.0 1.9 +- 3.6 3.6 4- 6.5 4.2 +I- 7.5 06/23/04 1460.0 +/- 110.0 -4.2 +4- 4.3 -0.3 +/- 1.0 0.06 4- 0.42 1.3 +/- 3.4 0.8 4- 2.7 -2.5 +/- 6.7 -2.8 4- 7.7 07/21/04 1400.0 +/ 140.0 [a] [a] 0.11 +- 0.36 2.9 +/- 3.8 1.7 +/- 3.6 1.9 +/ 7.0 2.2 +/- 8.1 08/25/04 1330.0 +I- 6.1 [a] [a] -0.07 +/- 0.03 5.2 +/- 4.2 -0.2 +/- 4.0 -1.6 +/- 5.3 -1.8 +/ 6.1 09/15/04 1284.0 4- 93.0 0.5 +/- 0.9 -0.1 +4- 0.7 -0.03 +/- 0.26 -3.5 +/- .5.1 2.5 +l 3.8 1.9 4- 7.3 2.2 +l 8.4 10/21/04 1180.0 +l 160.0 [a] [a] 0.12 +/ 0.37 -1.7 +/- 4.7 0.0 +/ 4.5 -2.2 +/- 6.0 -2.5 +I- 6.9 11/18/04 1310.0 +1- 120.0 [a] [a] 0.13 +/- 0.37 1.2 +/- 3.4 1.1 +4- 3.0 0.5 +/ 5.6 0.5 +/- 6.5 12/15/04 1150.0 +/- 150.0 -0.7 +/- 4.0 -0.7 +/- 11.0 -0.14 +/- 0.05 1.0 +/- 3.6 2.2 +- 4.3 6.3 +I- 5.7 7.2 +I- 6.5

[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.

51

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

Sampling Sampling ILU%..-#:-CAlIUIII In nota Be-7 LJCL I K-40l 1-131 I Cs-134 I Cs-137 I Th-228 I

- - l 14 05/12/04 440.0 +/- 240.0 10200 +/- 1300.0 1.0 +/- 22.0 7.0 +/- 27.0 5.0 +/- 21.0 -11.0 +/- 86.0 06/17/04. 1060.0 +/- 500.0 18300 +/- 1100.0 15.0 +/- 30.0 24.0 +/- 33.0 30.0 +/- 37.0 110.0 +/- 170.0 07/14/04 650.0 +/- 340.0 13900 +/- 1100.0 -3.0 +/- 31.0 9.0 +/- 30.0 3.0 +/- 25.0 190.0 +/- 130.0 08/18/04 800.0 +/- 330.0 11600 +/- 1100.0 -6.0 +/- 18.0 -6.00 +/- 32.00 26.0 +/- 23.0 -50.0 +/- 100.0 09/22/04 2440.0 +/- 420.0 19400 +/- 1100.0 14.0 +/- 34.0 3.00 +/- 30.00 3.0 +/- 24.0 130.0 +/- 130.0 I BL-7 I K-40 l 1-131 I Cs-134 I Cs-137 I Th-228 Il 15 05/12/04 320.0 +/- 270.0 12800 +/- 1400.0 35.0 +/- 33.0 3.0 +/- 29.0 -3.0 +/- 20.0 100.0 +/- 100.0 06/17/04 2280.0 +/- 450.0 13030 +/- 840.0 30.0 +/- 35.0 28.0 +/- 32.0 -2.0 +/- 28.0 270.0 +/- 110.0 07/14/04 620.0 +/- 240.0 15010 +/- 830.0 12.0 +/- 30.0 -28.0 +/- 22.0 35.0 +/- 23.0 110.0 +/- 110.0 08/18/04 810.0 +/- 180.0 14450 +/- 750.0 6.0 +/- 24.0 11.0 +/- 18.0 7.0 +/- 15.0 78.0 +/- 83.0 09/22/04 970.0 +/- 260.0 14450 +/- 700.0 12.0 +/- 33.0 0.0 +/- 20.0 6.0 +/- 18.0 -30.0 +/- 81.0 I Be-7 K-40 1 1-131 I Cs-134 l Cs-137 I Th-228 I 16 05/12/04 320.0 +/- 240.0 11100 +/- 1400.0 10.0 +/- 25.0 17.0 +/- 22.0 0.0 +/- 23.0 30.0 +/- 110.0 06/17/04 280.0 +/- 260.0 9000 +/- 1000.0 38.0 +/- 38.0 18.0 +/- 22.0 12.0 +/- 17.0 -18.0 +/- 81.0 07/14/04 1370.0 +/- 360.0 14700 +/- 1200.0 -6.0 +/- 23.0 2.0 +/- 32.0 12.0 +/- 26.0 410.0 +/- 130.0 08/18/04 1310.0 +/- 390.0 10420 +/- 930.0 -1.0 +/- 20.0 2.0 +/- 27.0 20.0 +/- 24.0 80.0 +/- 120.0 09/22/04 1740.0 +/- 590.0 10200 +/- 1300.0 9.0 +/- 21.0 -10.0 +/- 29.0 -6.0 +/- 33.0 190.0 +/- 140.0 52

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

Sampling Sampling Location Date Be-7 l K-40 23 05/12/04 570.0 +/- 380.0 11900 +/- 1200.0 L 25.0 1-131

+/- 32.0 I

-9.0 Cs-134

+/- 30.0 I 4.0 Cs-137

+/- 33.0 I 10.0 Th-228

+/- 120.0 I

06/17/04 150.0 +/- 210.0 8900 +1- 1100.0 23.0 +/- 85.0 10.0 +/- 25.0 2.0 +1- 16.0 70.0 +1- 88.0 07/14/04 1010.0 +/- 380.0 13600 +/- 1200.0 3.0 +/- 30.0 8.0 +/- 30.0 35.0 +/- 34.0 94.0 +/- 87.0 08/18/04 2880.0 +1- 280.0 18950 +1- 770.0 -5.0 +/- 16.0 -1.0 +/- 21.0 7.0 +/- 18.0 197.0 +/- 67.0 09/22/04 2540.0 +/- 480.0 17000 +/- 1200.0 -8.0 +/- 29.0 20.0 +/- 33.0 9.0 +/- 27.0 80.0 +/- 140.0 26 I Be-7 05/12104 740.0 +/- 340.0 I K-40 11300 +/- 1100.0 1 1-131 18.0 +/- 32.0 I

-6.0 Cs-134

+/- 27.0 I

9.0 Cs-137

+/- 27.0 I

25.0 Th-228

+I- 97.0 i

06/17/04 130.0 +/- 180.0 8590 +/- 950.0 -5.0 +1- 31.0 5.0 +I- 20.0 9.0 +I- 13.0 15.0 +1- 59.0 07/14/04 1070.0 +/- 350.0 13600 +1- 1300.0 -2.0 +I- 21.0 -10.0 +I- 32.0 17.0 +I- 25.0 180.0 +/- 150.0 08/18/04 680.0 +/- 240.0 24050 +1- 800.0 25.0 +I- 32.0 -6.0 +I- 25.0 11.0 +I- 20.0 62.0 +I- 82.0 09/22104 1900.0 +/- 390.0 12500 +/- 1000.0 8.0 +I- 28.0 5.0 +I- 29.0 0.0 +I- 24.0 10.0 +1- 110.0 53

Table 3-10 Well Water Gamma Spectra, Strontium, and Tritium

[pCi/L]

Sampling Station 01A Date H-3 Be-7 K-40 l Sr-89 Sr-90 l 1.131 l Ba-140 l Th-228 03/31/04 -240.0 +1- 640.0 11.0 +/- 18.0 16.0. +- 31.0 [a] [a] -1.8 +1- 5.5 0.9 +1- 4.0 3.0 +1- 12.0 06/29/04 -280.0 +1- 950.0 -12.0 +/- 22.0 -8.0 +/- 37.0 -1.5 +/- 4.1 1.0 +/- 1.0 -1.5 +/- 4.1 2.7 +/- 3.5 -8.0 +/- 10.0 09/29/04 370.0 +/- 680.0 1.0 +/- 15.0 12.0 +/- 24.0 [a] [a] -2.7 +/- 4.9 1.8 +/- 3.9 -2.1 +/- 7.0 12/29/04 330.0 +/- 870.0 -9.0 +/- 15.0 20.0 +/- 26.0 [a] [a] -1.9 +/- 4.8 -2.1 +/- 3.2 0.9 +/- 6.7

[a] Sr-89/90 analyses performed on the second quarter sample.

54

Table 3-11 River Water Gamma Spectra, Strontium, and Tritium

[pCiVLI Sampling Station 11 Date I H-3 l B-7 I K-40 I Sr-89 I Sr-90 I 1-131 I Cs-137 l Ba-140 .I Th-228 01/14/04 b -14.0 +/- 26.0 31.0 +/- 47.0 [a] [a] 0.3 +/- 0.6 1.0 +/- 2.7 5.1 +/- 7.5 0.6 +/- 9.1 02/16/04 b -11.0 +/- 17.0 -1.0 +/- 25.0 [a] [a] 0.2 +/- 0.4 0.0 +/- 1.7 1.8 +/- 3.1 -3.3 +/- 7.0 03/17/04 1180.0 +/- 680.0 -4.0 +/- 18.0 21.0 +/- 21.0 [a] [a] -0.1 +/- 0.1 0.8 +/- 1.9 -0.1 +/- 3.9 -3.4 +/- 5.7 04/15/04 b -8.0 +/- 15.0 25.0 +/- 22.0 [a] [a] 0.2 +/- 0.5 -0.2 +/- 1.3 -0.4 +/- 5.1 -0.4 +/- 5.5 05/17/04 b -3.0 +/- 21.0 -29.0 +/- 29.0 [a] [a] 0.7 +/- 0.7 0.7 +/- 2.5 -0.5 +/- 4.7 0.0 +/- 10.0 06/14/04 2600.0 +/- 1200.0 -9.0 +/- 38.0 79.0 +/- 57.0 1.1 +/- 5.2 -0.5 +/- 1.1 0.0 +/- 0.4 -0.6 +/- 3.8 2.3 +/- 6.4 -9.0 +/- 14.0 07/14/04 b 5.0 +/- 23.0 -4.0 +/- 32.0 [a] [a] 0.0 +/- 0.3 -0.9 +/- 2.8 -2.0 +/- 5.9 3.0 +/- 11.0 08/16/04 b 7.0 +/- 26.0 -3.0 +/- 28.0 [a] [a] 0.1 +/- 0.3 1.1 +/- 3.0 0.7 +/- 4.4 2.9 +/- 8.9 09/13/04 2280.0 +/- 810.0 -9.0 +/- 17.0 24.0 +/- 28.0 [a] [a] -0.2 +/- 0.2 0.0 +/- 1.8 2.5 +/- 5.6 4.2 +/- 8.9 10/13/04 b 5.0 +/- 18.0 6.0 +/- 27.0 [a] [a] 0.0 +/- 0.3 0.5 +/- 1.9 2.0 +/- 4.6 -9.6 +/- 7.1 11/12/04 b -0.7 +/- 4.9 7.0 +/- 9.3 [a] [a] -0.1 +/- 0.4 -0.5 +/- 0.5 -1.2 +/- 1.1 0.7 +/- 2.7 12/14/04 3090.0 +/- 800.0 3.0 +/- 21.0 -1.0 +/- 33.0 [a] [a] -0.1 +/- 0.0 1.6 +/- 2.4 2.9 +/- 4.9 1.0 +/- 10.0

[a] Sr-89/90 analyses performed on the second quarter sample.

[b] Tritium analyses on quarterly composite.

55

Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium fpciILJ Station 08 Date Sr-89 Sr-90 1131 Cs-137 lBa-140 lTh-228 01/14/04 [b] [a] [a] 3.0 +I- 21.0 10.0 +1- 39.0 0.3 +I- 0.5 1.7 +/ 2.4 0.7 +I- 5.9 -11.2 +l- 9.9 02/16/04 [b] [a] [a] -3.0 +I- 19.0 -3.0 +I- 24.0 0.0 +l 0.2 -1.4 +/- 1.8 0.6 +l- 2.9 -0.3 +l 6.8 03/17/04 1280.0 +/- 680.0 [a] [a] 7.0 +I- 19.0 -4.0 +/- 24.0 0.0 +/ 0.2 -0.9 +/ 1.8 -0.4 +I- 4.1 -0.9 +l 6.2 04/15/04 [b] [a] [a] 13.00 +/- 14.00 -20.0 +I- 21.0 -0.1 +I- 0.3 -0.1 +/- 1.4 -0.3 +1- 4.7 -0.4 +I- 4.7 05/17/04 [b] [a] [a] 2.00 +I- 26.00 -32.0 +l 38.0 0.1 +/- 0.4 -0.5 +I- 2.9 2.5 +I- 6.4 -11.0 +I- 13.0 06/14/04 2700.0 +/- 1300.0 0.0 +/- 5.1 -0.4 +/- 1.1 12.00 +I- 27.00 17.0 +I- 38.0 -0.2 +/- 0.4 2.0 +I- 3.6 -0.8 +I- 6.1 -5.0 +I- 12.0 07/14/04 [b] [a] [a] 12.00 +I- 22.00 -25.0 +I- 38.0 0.2 +/- 0.5 -0.6 +I- 3.0 0.9 +/- 6.2 5.0 +/ 11.0 08/16/04 [b] [a] [a] 0.00 +/- 16.00 18.0 +I- 41.0 0.2 +/- 0.4 0.0 +/-' 2.7 -0.6 +I- 4.8 6.0 4/- 11.0 09/13/04 2980.0 +/- 850.0 [a] [a] 14.00 +I- 19.00 -3.0 +I- 28.0 0.0 +/- 0.3 0.8 +/- 1.7 2.8 +l 5.8 -2.9 +I- 7.2 10/13/04 [b] [a] [a] 13.00 +I- 22.00 7.0 +/ 36.0 -0.1 +/- 0.3 -1.3 +I- 2.5 -3.9 +I- 5.6 3.0 +l- 11.0 11/12104 [b] [a] [a] 0.10 +1- 5.30 3.0 +I- 10.0 -0.3 +/- 0.3 0.3 +l 0.5 1.2 +1 1.1 -1.2 +I- 2.9 12114/04 2730.0 +/- 780.0 [a] [a] -3.00 +I- 21.00 -16.0 +l- 26.0 -0.1 +/- 0.0 0.6 +/ 2.4 -3.9 +/ 4.0 6.6 +l 9.6 Station 09A Date l Sr-89 l Sr-90 1-131 Cs-137 l Ba-140 lTh-228 01/14/04 [b] [a] [a] 7.0 22.0 28.0 +- 34.0 0.1 +/- 0.3 0.0 +1- 2.3 0.5 +/- 5.2 -1.0 +/- 11.0 02/16104 [b] [a] [a] -4.0 +/ 25.0 1.0 +/- 36.0 0.3 +/ 0.4 0.0 +I- 3.1 3.0 +/- 4.6 1.0 +1- 11.0 03/17/04 110.0 +/- 620.0 [a] [a] -7.0 +/- 18.0 5.0 +I- 27.0 -0.1 +/- 0.2 -0.3 +I- 1.9 -3.0 +/- 3.2 -0.7 +I- 7.6 04/15/04 [b] [a] [a] -10.00 +1- 18.00 -9.0 +1 28.0 -0.2 +I- 0.4 -0.1 +1- 1.9 -0.5 +/- 5.6 0.9 +/- 7.6 05/17/04 [b] [a] [a] -17.00 +I- 24.00 10.0 +/- 37.0 0.1 +/- 0.4 -1.5 +/- 2.6 -3.4 +- 3.9 13.0 +l 11.0 06/14/04 -500.0 +/- 1100.0 -1.8 +/- 4.7 0.0 +/- 1.0 12.00 +I- 32.00 -8.0 +/- 53.0 -0.3 +/- 0.3 -0.8 +I- 4.2 2.3 +I- 5.6 13.0 +l 17.0 07/14/04 [b] [a] [a] -8.00 +I- 30.00 -11.0 +/- 40.0 0.5 +1- 0.7 2.5 +I- 2.6 2.3 +I- 5.7 -3.1 +I- 8.5 08/16/04 [bY [a] [a] 4.00 +I- 24.00 -35.0 +/- 42.0 -0.1 +/- 0.3 -1.2 +I- 3.1 0.8 +I- 6.6 -2.0 +I- 11.0 09/13/04 -580.0 +/- 700.0 [a] [a] 9.00 +1- 18.00 -13.0 +/- 27.0 0.0 +/ 0.2 0.7 +/ 1.9 0.3 +I- 5.4 3.5 +l 7.7 10/13/04 [b] [a] [a] 4.00 +I- 25.00 31.0 +/- 36.0 0.4 +/- 0.5 1.2 +I- 2.6 2.8 +1- 6.2 -5.0 +l 11.0 11/12104 [b] [a] [a] 2.50 +l 4.80 10.0 +1- 10.0 -0.5 +/- 0.3 -0.1 +/- 0.5 0.2 +I- 1.0 3.1 +I- 3.0 12/14/04 -350.0 +/- 640.0 [a] [a] -7.00 +I- 22.00 5.0 +I- 35.0 -0.1 +/- 0.0 0.5 +/- 2.6 -1.8 +l 5.2 5.0 +I- 11.0

[a] Sr-89/90 analyses performed on the second quarter sample.

[b] Tritium analyses on quarterly composite.

56

Table 3-13 Sediment Silt Gamma Spectra and Strontium

[pCi/Kg]

Date l Sr-89 Sr-90 Be-7 K-40 Mn-54 03/24/2004 Station 08 [a] [a] -20.0 +/- 200.0 2100.0 +/- 420.0 14.0 +/ 19.0 Station 09A [a] [a] -60.0 +/- 210.0 10920.0 +/- 780.0 15.0 +/- 20.0 Station 11 la] [a] -210.0 +/- 400.0 13700.0 +/ 1400.0 29.0 +/- 43.0 Date l Sr-89 Sr-90 Be-7 K-40 Mn-54 10/25/2004 Station 08 *260.0 +/- 190.0 140.0 +/- 110.0 180.0 +/- 320.0 16000.0 +/- 1400.0 .29.0 +/- 40.0 Station 09A -140.0 +/I 230.0 0.0 +/- 130.0 50.0 +/ 240.0 12200.0 +- 1100.0 -10.0 +/- 27.0 Station 11 -60.0 +/- 260.0 10.0 +/- 140.0 120.0 +/ 290.0 10500.0 +/- 1200.0 -6.0 +/ 31.0 Date l Co-58 Co-60 Cs-134 Cs-137 Th-228 03/24/2004 Station 08 *4.0 +/- 20.0 9.0 4/ 16.0 -12.0 +/- 72.0 15.0 +/- 19.0 511.0 +/- 82.0 Station 09A 1.0 +/- 23.0 -4.0 +- 19.0 43.0 +/- 76.0 -4.0 +/- 23.0 377.0 +/- 87.0 Station 11 -21.0 +/- 39.0 -38.0 +/- 39.0 -13.0 +/- 38.0 37.0 +/- 43.0 1020.0 +- 180.0 Date Co-58 l Co-60 Cs-134 Cs-137 Th-228 10/25/2004 Station 08 -21.0 +/- 42.0 -15.0 +/- 43.0 29.0 +/- 32.0 -16.0 +/- 30.0 1610.0 +/- 160.0 Station 09A -15.0 +/- 27.0 21.0 +/- 30.0 -2.0 +/- 24.0 34.0 +/- 28.0 990.0 +/- 110.0 Station 11 -1.0 +/- 31.0 -8.0 +/- 34.0 17.0 +/- 32.0 56.0 +/- 41.0 500.0 +/- 140.0

[a] Sr-89/90 analyses performed annually.

57

Table 3-14 Shoreline Soil Gamma Spectra and Strontium

[pCi/Kg]

Sample Date I Sr-89 I Sr-90 l Be-7 I K-40 l Mn-54 03/16/2004 Station 08 [a] [a] -90.0 +/- 280.0 2110.0 +/- 470.0 13.0 +/- 18.0 Sample Date Sr-89 Sr-90 Be-7 K-40 Mn-54 10/25/2004 Station 08 -40.0 +/- 160.0 41.0 +/- 98.0 280.0 +/- 200.0 2980.0 +/- 550.0 -4.0 +/- 21.0 Sample Date Co-58 Co-60 Cs-134 Cs-137 Th-228 03/16/2004 Station 08 2.0 +/- 24.0 7.0 +/- 16.0 236.0 +/- 43.0 236.0 +/- 43.0 339.0 +/- 91.0 Sample Date Co-58 Co-60 Cs-134 Cs-1 37 Th-228 10/25/2004 Station 08 13.0 +/- 18.0 -4.0 +/- 18.0 162.0 +/- 41.0 162.0 +/- 41.0 334.0 +/- 87.0

[a] Sr-89/90 analyses performed annually.

58

Table 3-15 Fish Gamma Spectra

[pCi/Kg]

Fish [a]

Sampling Station 08 Date l K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 04/17/04 1820.0 +/- 170.0 5.2 +/- 6.8 -11.0 +/- 27.0 0.5 +/- 7.6 1.5 +/- 6.7 -20.0 +/- 16.0 -1.9 +/- 6.3 26.3 +/- 8.9 10/26/04 1690.0 +/- 720.0 0.0 +/- 30.0 -21.0 +/- 74.0 8.0 +1- 17.0 28.0 +1- 25.0 -11.0 +/- 59.0 -46.0 +/- 37.0 18.0 +/- 25.0 Fish [a]

Sampling Station 25 Date l K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 04/17/04 1670.0 +/- 170.0 1.6 4/- 6.7 0.1 +/- 28.0 -5.9 +/- 7.9 6.0 +/- 6.6 4.0 +/- 15.0 -6.5 +/ 6.2 8.4 +/- 7.1 09/29/04 1370.0 +/- 470.0 0.0 +/- 18.0 24.0 +/ 96.0 -26.0 +/- 23.0 3.0 +/ 17.0 -39.0 +/- 42.0 24.0 +/- 23.0 2.0 4/- 20.0 Catfish [b]

Sampling Station 08 Date l K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 l Cs-137 04/17/04 1650.0 +1- 180.0 2.1 +/- 6.3 4.0 +/- 31.0 3.5 +/- 7.8 -4.4 +/- 7.5 -10.0 +/ 16.0 3.2 +/ 7.2 9.5 + 8.7 10/26/04 1230.0 +/- 630.0 -4.0 +/- 31.0 28.0 +/- 61.0 13.0 +/- 21.0 15.0 +/- 24.0 -9.0 +/- 56.0 3.0 +/- 27.0 21.0 +/ 33.0 Catfish [b]

Sampling Station 25 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 l Cs-137 04/17/04 1420.0 +/- 150.0 1.9 +/- 5.8 -16.0 +/- 24.0 2.1 +/- 7.4 0.6 +/- 6.4 -12.0 +/- 14.0 1.4 +/- 6.5 2.2 +/- 6.3 09/29/04 1370.0 +/- 540.0 -2.0 +/- 22.0 -7.0 +/- 74.0 0.0 +/- 22.0 -3.0 +/- 26.0 -22.0 +/- 63.0 28.0 +/- 24.0 6.0 +/- 21.0

[a] Non-bottom dwelling species of gamefish.

{b) Bottom dwelling species of fish.

59

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2004 and tabulated in Section 3, are discussed below. Except for TLDs, AREVA Environmental Laboratory analyzed all samples throughout the year. Ihe 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 C.

The predominant radioactivity detected throughout 2004 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 2004 reporting period.

4.1 Gamma Exposure Rate A thermoluminescent dosimeter (ILD) 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 ILDs 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 'LD 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 ILDs replaced the previously used CaSO4:Dy in Teflon ILDs. The dose with the replacement ILDs is lower than that of the previously used TLDs. This will continue to be monitored.

60

Figure 4-1: Environmental Radiation - TLDs 0.0 IL-cM E 1.0 .. . . . .. . . . . ........................................... 11 1111 1,11 1111 r- 00 ON 0 - ' t kn mO L- 00 O E - C CO CO CO CO 9O C: ., e CO CO C' Cs C C C I

  • Environmental TLDs A Sector TLDs -U- 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 5.3 mR/standard month with a range of 2.6 to 30.0 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 30.0 mR/standard month and 34.0 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 3.7 mR/standard month with a range of 2.4 to 5.3 mR/standard month. The average annual reading for these locations was 1.57 mR/standard month with a range of from 1.07 to 2.20 mR/standard month. The control location showed a quarterly average of 3.5 mR/standard month with a range of 2.6 to 4.2 mR/standard month. Its annual reading was 1.57 mR/standard month. Eight other TLDs, designated C- 1 thru C-8, were collected quarterly from four locations and showed an average reading of 3.2 mR/standard month with a range of 2.0 to 4.9 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

61 CO)&

61 COC

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the results, shown in a historical plot in Figure 4-2, indicates gross beta activity at levels similar to that seen over the last decade. 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 z

0 .0 1 - - - - - ... . . .. . . .... ...-

. - - -.S...

S.....

.z.

0.001 . ,,,

. , .I,,,,,,,

1986 1988 1990 1992 1994 1996 1998 2000 2002 2004

  • Control Sta-24 *- Indicator A Average Pre-op - Required LLD 62 Co0

Figure 4-3 NORTH ANNA AIR PARTICULATE 4 Indicatorl pCVm 3 2004 Gross Beta Radioactivity *-. A-. Controll 0.055 0.050 0.045 0.040 - A 0 035 -

n.0n - a 1 0.025 I .AA A'- if A .? tI\. IV. AA f'

0.020 0.015 zAN11 ." 1W 0.010 0.005 Ii I. I IA I I I I I I. I . . . . . . . . . .

m a0 -0

_~ °4 oi ;a a- C C 0 0 BJ C I o a a g- '-j g

Ss ~~ '

~ - .

o g a I I le_

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.

63 63 oc

4.5 Air ParticulateStrontium 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 July and analyzed by gamma ray spectroscopy. The results are presented in Table 3-6. Naturally occurring potassium-40 was detected in all eleven indicator stations with an average concentration of 12385 pCi/kg (dry) and a range of 4600 to 26400 pCi/kg (dry). The control location had a measurement of 4600 pCi/kg (dry). Thorium-228 was detected in eleven indicator stations with an average activity of 1351 pCi/kg (dry) and a range of 540 to 2240 pCi/kg (dry). The control station had a concentration of 1090 pCi/kg (dry). The fission product cesium-137 was detected in five of the eleven indicator stations with an average activity of 284 pCi/kg (dry) and a range of 191 to 430 pCi/kg (dry).The control location had a concentration of 360 pCi/kg (dry). The cesium-137 is attributable to past atmospheric nuclear weapons testing.

The twelve soil samples were also analyzed for strontium-89 and strontium-90.

Neither strontium-89 or strontium-90 were detected in any of the samples.

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. Eleven of twelve precipitation samples showed positive results in 2004. The average annual gross beta activity was 6.1 pCi/liter with a range from 3.9 to 15.0 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 2004. 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 2004 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 64

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 a lack of detectable I-131 above the LLD of 1 pCi/l. 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 2004.

Once each quarter a sample from each of the two collection stations is analyzed for strontium-89 and strontium-90. Positive indication of Sr-89 was not detected. One positive indication of Sr-90 was detected in the 1st quarter milk sample collected from station 13 at 2.80 pCi/liter. 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 Productsand Vegetation Twenty-five food samples were collected from five locations and analyzed by gamma spectrometry. The results of the analyses are presented in Table 3-9. 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. Other than cesium-137 observed in one analysis, no other gamma emitters were detected. The levels detected are consistent with those observed in food product or vegetation samples collected in previous years and the presence of cesium-137 is attributed to residual global fallout from past atmospheric weapons testing.

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 65

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 3-1 1. All monthly samples are analyzed by gamma spectroscopy. The monthly samples were composited quarterly and analyzed for tritium, the third 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 2288 pCi/liter and a range of 1180 to 3090 pCi/liter. These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were collected during the pre-operational period.

10000- Figure 4-4: Tritium in River Water z

C.

C S

v a5 1000 mn i I i

\o I

N

, I I 00 O8

.~1 C 0

I 0

i I M

I I t

I I m

I I v

I I r

, I 00

, I I I 0

I I I I 04 I I n

, I I I

00 00 00 00 00 O0 ON ON ON 0 O CON ON ON ON 0 0 O O 0 o cl all of Cay ON ON ON ON ON ON O. ON Os ON 0 0 0 D 0

-- - - - - - - -. . . l 04 0.

- Tritium - - -- -- Required LLD]

4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator 66 C00

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 third quarter samples were additionally analyzed for strontium-89 and strontium-90. The results are presented in Table 3-12.

No gamma emitting radioisotopes nor iodine were detected in any of the samples. The average level of tritium activity at the indicator station was 2423 pCi/liter with a range of 1280 to 2980 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.

Figure 4-5: Tritium in Surface Water 10000-t Z 1000-100 D o o't CC C

$? C

°° °° X ° ° ° C° C° C° C> C° Ci Co C Cs C0 0 c0CC c c X C CTC C CC Ci C- C C C C X C C C X C eC X C , IsCC tY -

--* Tritium --- in-- RequiredLLD-4--AveragePre-opl 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 67 C f'(

67 cr

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.

Figure 4-6: Cesium-137 in Sediment Silt 10000

-t0 1000 100 0.

10 1

'WN 00

~ 0 00 00 00 CN 00 O\ O N

~WO \o O

00 N

ON O

- (N en ON cn ON eCn ON 0 M 00 ri 00 rI 00 cN o - 0) 0 0 0 0 0 0

- Station -8 Station-9

  • Control-Sta-09A

-X-Statio n-l1 + Average Pre-Op -- Required LLD's There was no Cesium-137 detected in any of the sediment samples in 2004. 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 occurring 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 68 e..

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 steady trend. Cesium-137 was measured in both samples collected with an average concentration of 199 pCi/kg (dry weight). 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 2004 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. In one sample, Sta.#08, game species, Cs-137 was observed with a concentration of 26.3 pCi/kg. Except for naturally occurring K-40, no other nuclide was observed in this media in 2004. Only Cs-137 was measured in pre-operational environmental fish samples.

69

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2003 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception Sta. 14-16, 23, Vegetation January Seasonal Unavailability 26 Sta. 14-16, 23, Vegetation February Seasonal Unavailability 26 Sta. 01 Air Iodine and 02/18/04 Low volume due to sampler malfunction.

Particulate Sta. 14-16, 23, Vegetation March Seasonal Unavailability 26 Sta. 05 Air Iodine and 03/17/04 Low volume due to sampler malfunction.

Particulate Sta. 14-16, 23, Vegetation April Seasonal Unavailability 26 Sta. 01 Air Iodine and 05/05/04 Low volume due to breaker trip.

Particulate Sta. 05 Air Iodine and 07/15/04 Motor locked up - end of run.

Particulate AREVA 1-131 Lab 08/03/04 (vendor) Contamination Sta. 01 Air Iodine and 10/13/04 Low volume due to breaker trip.

Particulate Sta. 14-16, 23, Vegetation October Seasonal Unavailability 26 Sta. 05A Air Iodine and 10/13/04 Low volume due to breaker trip.

Particulate Sta.01 Air Iodine and 10/20/04 Low volume due to breaker trip.

Particulate Sta. 14-16, 23, Vegetation November Seasonal Unavailability 26 Sta. 14-16, 23, Vegetation December Seasonal Unavailability 26 TLD TLD 1V Quarter Vendor lost TLD EPSP- 9 TLD TLD 4'h Quarter Power Pole replaced - no notification 22/54 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 10CFR50, 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.

72

APPENDICES 73

APPENDIX A: LAND USE CENSUS Year 2004 74

LAND USE CENSUS North Anna Power Station North Anna County, Virginia JanuaryI to December31, 2004 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch Boundary (> 50m2 ) Animal Cow Goat N 0.9 1.5 1.5 None None None NNE 0.9 0.9 1.3 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 2.5 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 1.1 2.8 None None SSW 1.0 1.4 None 1.9 None None SW 1.1 3.1 3.1 None None None WSW 1.1 1.6 1.6 1.6 None None i 1.1 1.5 1.5 None None None WNW 1.0 1.1 2.5 3.9 None None NW101.0 1.3 None None None NNW 0.9 1.0 1.1 None None None I

75

2003 to 2004 Land Use Census Changes 2003 2004 Nearest Direction Distance Distance Site Boundary No Change ;

Resident WvSW 1.7 mi 1.6 mi (2)

SSW 1.2 mi 1.4 mi (2)

Garden N 1.8 mi 1.5 mi (1)

NNE 1.6 mi 1.3 mi (2)

SSE 1.3 mi 1.0 mi (2)

S 1.2 mi 1.1 mi(1)

SW None 3.1 mi (1)

WSW 2.0 mi 1.6 mi (2)

W 1.9 mi 1.5 mi(1)

NW 1.4 mi 1.3 mi(2)

NNW 2.2 mi 1.1 mi(1)

Meat Animal N 2.2 mi None (1)

NE 1.4 mi 1.5 mi (2)

S None 2.8 mi(1)

WSW 1.7 mi 1.6 mi(2)

WNW 4.1 mi 3.9 mi(2)

NNW 2.0 mi None (1)

Milch Cow No Changes Milch Goat ENE None 2.5 mi (1)

(1) - Actual census location changes.

(2) - Mileage changes due to methodology change in measurements.

76

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2004 77

INTRODUCTION This appendix covers the Intercomparison Program of the AREVA ANP Environmental Laboratory as required by technical specifications for each unit.

Framatome uses QA/QC samples provided by Analytics, Inc to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (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, S> 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 1st 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 Millstone program. These programs are the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (P1l 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 which does not pass the criteria is investigated by AREVA ANP.

Analytics Intercomparison Program results are included on pages 79 through 81 for the first quarter of 2004 through the third quarter of 2004. A total of 113 analysis results were obtained with 111 initially passing acceptance criteria, a 98.2% success rate. During analysis of the second quarter Sr-89/90 filter analyses, problems were encountered in filter dissolution. The analyses were 78

performed during the third quarter and were in agreement.

79

RAATOAE ANP,2004EN OMENTLAOAOR ~- 'E

~>QŽ1!j~PERF RMANCE EVALUATION 7' Ratio Sample Quarter/ Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation E4057-162 1st/04 Water Gross Alpha pCUL 72.3 74.5 0.97 Acceptable E4057-162 1st/04 Water Gross Beta pCVL 285.7 301 0.95 Acceptable E4058-162 1st/04 Water 1-131 pCVL 94 90.2 1.04 Acceptable E4058-162 1st/04 Water 1-131LL pCVL 88.7 90.2 0.98 Acceptable E4058-162 1st/04 Water Ce-141 pCVL 87.5 85 1.03 Acceptable E4058-162 1stJ04 Water Cr-51 pCVL 335 326 1.03 Acceptable E4058-162 1stJ04 Water Cs-134 pCVL 86 89.7 0.96 Acceptable E4058-162 1stJO4 Water Cs-137 pCVL 185.6 185 1.00 Acceptable E4058-162 1st/o4 Water Co-58 pCVL 113.2 112 1.01 Acceptable E4058-162 1stJ04 Water Mn-54 pCUL 112.3 114 0.99 Acceptable E4058-162 1st/04 Water Fe-59 pCUL 60.8 56.7 1.07 Acceptable E4058-162 1st/04 Water Zn-65 pCVL 149.1 143 1.04 Acceptable E4058-162 1st/04 Water Co-60 pCI/L 151.4 153 0.99 Acceptable E4059-162 1stIO4 Water Sr-89 pCi 107.7 123 0.88 Acceptable E4059-162 lst/04 Water Sr-90 pCi 14.85 14.5 1.02 Acceptable E4060-162 1stJ04 Filter Gross Alpha pCi/L 48.09 58.9 0.82 Acceptable E4060-162 1st/04 Filter Gross Beta pCVL 231.1 218 1.06 Acceptable E4061-162 1st/04 Milk 1-131 pCVL 77.73 77.7 1.00 Acceptable E4061-162 1stJO4 Milk 1-131 LL pCi/L 83.6 77.7 1.08 Acceptable E4061-162 1st/04 Milk Ce-141 pCi/L 92 85.2 1.08 Acceptable E4061-162 1stJ04 Milk Cr-51 pCUL 314 327 0.96 Acceptable E4061-162 1st/04 Milk Cs-134 pCi/L 88.7 90 0.99 Acceptable E4061 -162 1stJ04 Milk Cs-137 pCi/L 188.6 185 1.02 Acceptable E4061-162 1st/04 Milk Co-58 pCi/L 115 112 1.03 Acceptable E4061-162 1st/04 Milk Mn-54 pCi/L 114.7 114 1.01 Acceptable E4061-162 1st/04 Milk Fe-59 pCiVL 59.7 56.8 1.05 Acceptable E4061-162 lstJ04 Milk Zn-65 pCi/L 145.5 143 1.02 Acceptable E4061-162 1stJ4 Milk Co60 pCVL 154.8 153 1.01 Acceptable E4062-162 1st/4 Milk Sr-89 pCi 86.2 103 0.84 Acceptable E4062-162 1st/04 Milk Sr-90 pCi 12.7 12.1 1.05 Acceptable 80

>* s;;  ;-- t*.-eFRAM ATOMEANP 2004 ENVIRONMENTAL'LABORATORY i IP '2;r 'X > ANALY TICS ENVIRONMEITALICROS CHECK PROGRAM E RFRA ma

.<.; - ? . ,j Ratio Sample Quarter/ Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation E4182-162 2nd/04 Water H-3 pCi/L 11680 11900 0.98 Agreement E4183-162 2nd/04 Filter Gross Alpha pCi 46.8 48.8 0.96 Agreement E4183-162 2nd/04 Filter Gross Beta pCi 156 160 0.98 Agreement E4184A-162 2nd/04 Filter Ce-141 pCi 86 88.3 0.97 Agreement E4184A-1 62 2nd/04 Filter Cr-51 pCi 127 128 0.99 Agreement E4184A-1 62 2nd/04 Filter Cs-134 pCi 54 56.9 0.94 Agreement E4184A-1 62 2nd'04 Filter Cs-137 pCi 90 87.8 1.03 Agreement E4184A-1 62 2nd/04 Filter Co-58 pCi 27 26 1.03 Agreement E41 84A-162 2nd/04 Filter Mn-54 pCi 42 39.7 1.06 Agreement E41 84A-1 62 2nd/04 Filter Fe-59 pCi 27 25.1 1.09 Agreement E4184A-162 2nd/04 Filter Zn-65 pCi 62 56 1.11 Agreement E4184A-1 62 2nd/04 Filter Co-60 pCi 92 96.8 0.95 Agreement E4185-162 2nd/04 Filter Sr-89 pCi (1)

E4185-162 2nd/04 Filter Sr-90 pCi (1)

E4186-162 2nd/04 Milk 1-131 pCVL 55 58.2 0.95 Agreement E4186-162 2nd/04 Milk 1-131 LL pCi/L 59 58.2 1.01 Agreement E4186-162 2nd/04 Milk Ce-141 pCi/L 165 157 1.06 Agreement E4186-162 2nd/04 Milk Cr-51 pCi/L 241 228 1.06 Agreement E4186-162 2ndl04 Milk Cs-134 pCi/L 99 101 0.98 Agreement E4186-162 2nd/04 Milk Cs-137 put. 157 156 1.01 Agreement E4186-162 2nd/04 Milk Co-58 pCi/L 46 46.2 1.00 Agreement E4186-162 2ndl04 Milk Mn-54 pCUL 73 70.5 1.04 Agreement E4186-162 2nd/04 Milk Fe-59 pCi/L 48 44.5 1.08 Agreement E4186-162 2nd/04 Milk Zn-65 pC0UL 100 99.3 1.01 Agreement E4186-162 2nd/04 Milk Co-60 pC0/L 175 172 1.02 Agreement MAPEP May-04 Filter Sr-90 pci 20.3 22.4 0.91 Agreement (2)

RdFe2 (1) - Problems encountered In filter dissolution, filter re-ordere. See 3uarer rsults.

(2) - Replacement filter for first half 2004 from DOE MAPEP 81

,,-I,>5x-o, ,,FRAMATOME ANP 2004.ENVIRONMENTAL LABORATORY . vand '

t>-HS,,n, --a

.'AiNALYTCS RADIOLOGICAL'ENVIRONMENTALGCROSS-CHECK 2 '  :- t..'

i kit<j n PERFORMANCE' VALUiAT~ON I;'* X .^yi A ,,

Ratio Sample Ouarter/ Sample _ Reported Known E-LAB/

Number Year Media Nuclide Units Value Value Analytics Evaluation E4269-162 3rd12004 Water Gross Alpha pCiL 41.3 42.7 0.97 Agreement E4269-1 62 3rd/2004 Water Gross Beta pCvL 214 225 0.95 Agreement E4270-162 3rd12004 Water 1-131 LL pCUL 67.8 70.8 0.96 Agreement E4270-162 3rd/2004 Water 1-131 pCML 70.5 70.8 1.00 Agreement E4270-162 3rd_2004 Water Ce-141 PM 258 250 1.03 Agreement E4270-162 3rd/2004 Water Cr-51 pCVL 230 223 1.03 Agreement E4270-162 3rd/2004 Water Cs-134 pCi/L 93.4 96.4 0.97 Agreement E4270-162 3rdI2004 Water Cs-137 pCiUL 217 215 1.01 Agreement E4270-162 3rdl2004 Water Co-58 pCVL 93.4 94.6 0.99 Agreement E4270-162 3rd/2004 Water Mn-54 pCUL 181 181 1.00 Agreement E4270-162 3rd/2004 Water Fe-59 pCUL 95.2 91.6 1.04 Agreement E4270-162 3rd/2004 Water Zn-65 pCVL 180 178 1.01 Agreement E4270-162 3rd/2004 Water Co-60 pCUL 126 125 1.01 Agreement E4271-162 3rd/2004 Filter Gross Alpha pCi 38.3 36.8 1.04 Agreement E4271 -162 3rd/2004 Filter Gross Beta pCi 191 194 0.98 Agreement E4272-162 3rd/2004 Milk -131 L pOV_ 79.4 83.5 0.95 Agreement E4272-162 3rd/2004 Milk 1-131 pCU/L 81.1 83.5 0.97 Agreement E4272-162 3rd12004 Milk Ce-141 pCUL 240 235 1.02 Agreement E4272-162 3rd/2004 Milk Cr-14 pCUL 214 210 1.02 Agreement E4272-162 3rd/2004 Milk Cs-134 pCiUL 89.5 90.6 0.99 Agreement E4272-162 3rd/2004 Milk Cs-137 pCi/L 204 202 1.01 Agreement E4272-162 3rd/2004 Milk Co-58 pCUL 90.9 89 1.02 Agreement E4272-162 3rd/2004 Milk Mn-54 pCUL 173 171 1.01 Agreement E4272-162 3rd/2004 Milk Fe-59 pCi/L 91.3 86.1 1.06 Agreement E4272-162 3rd/2004 Milk Zn-65 pCUL 169 167 1.01 Agreement E4272-162 3rd/2004 Milk Co-60 pCUL 116 118 0.98 Agreement E4273-162 3rd/2004 Milk Sr-89 pCi/L 99.2 102 0.97 Agreement E4273-162 3rd/2004 Milk Sr-90 pCi/L 23.4 24.5 0.96 Agreement E4340-162 3rdl2004 Filter Sr-89 pCUL 151 152 1.00 Agreement E4340-162 3rd/2004- Filter Sr-90 pCUL 53.5 58.8 0.91 Agreement

- Replacement filter for lost 2nd quarter filter.

82

rFRAMATOME ANP 2004 ENVIRONMENTAL LABORATORY .~-- . -,;

. .N C AOLOGlCAUEN iRONMENTAL7CROSS-CHECK-,-.- - . . .*

Ratio Sample Quarter/ Sample Reported Known E-LAB/

Number Year Media Nuclide Units Value Value Analytics Evaluation E4380-1 62 4th/2004 Water H-3 pCl/L 8327 8060 1.03 Agreement E4381-162 4th/2004 Fdter Sr-89 pCi 87.7 92.3 0.95 Agreement E4381-162 4thl2004 Filter Sr-90 pCI 8.78 10.6 0.83 Agreement E4382-1 62 4th/2004 Filter Gross Alpha pCi 24.9 29.5 0.84 Agreement E4382-162 4th/2004 Filter Gross Beta pCi 223 204 1.09 Agreement E4383-162 4th/2004 Filter Ce-141 pCi 75.6 80.3 0.94 Agreement E4383-162 4th/2004 Filter Cr-51 pCI 201 189 1.06 Agreement E4383-162 4th/2004 Filter Cs-134 pCi 82.4 84.7 0.97 Agreement E4383-162 4th/2004 Filter Cs-137 pCi 68.8 62.9 1.09 Agreement E4383-162 4th/2004 Filter Co-58 pCi 75.3 72.9 1.03 Agreement E4383-162 4th/2004 Filter Mn-54 pCi 76.3 67.7 1.13 Agreement E4383-162 4th/2004 Filter Fe-59 pCi 69.8 60.5 1.15 Agreement E4383-162 4th/2004 Filter Zn-65 pCi 109 97.7 1.12 Agreement E4383-162 4th/2004 Filter Co-60 pCi 85.1 87.1 0.98 Agreement E4384-162 4th/2004 Milk I-131LL pCVL 64.2 66.7 0.96 Agreement E4384-162 4th/2004 Milk 1-131 pCi/L 69.0 66.7 1.03 Agreement E4384-162 4th/2004 Milk Ce-141 pCiVL 154 155 0.99 Agreement E4384-162 4th/2004 Milk Cr-51 pCVL 385 379 1.02 Agreement E4384-162 4th/2004 Milk Cs-134 pCVL 167 170 0.98 Agreement E4384-162 4th/2004 Milk Cs-137 pCUL 132 126 1.05 Agreement E4384-162 4th/2004 Milk Co-58 pCi/L 147 146 1.01 Agreement E4384-162 4th/2004 Milk Mn-.4 pCi/L 144 136 1.06 Agreement E4384-162 4th/2004 Milk Fe-59 pCVL 129 121 1.07 Agreement E4384-162 4th/2004 Milk Zn-65 pCI/L 197 196 1.01 Agreement E4383-162 4th/2004 Milk Co-60 pCi/L 177 175 1.01 Agreement E4412-162 4th/2004 Water Sr-89 pCi/L 90.9 98.1 0.93 Agreement E4412-162 4th/2004 Water Sr-90 pCVL 9.33 11.3 0.83 Agreement 83