ML041260191

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Units I & 2 and Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report
ML041260191
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/27/2004
From: Jennifer Davis
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, -RFPFR, 04-213
Download: ML041260191 (83)
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Text

VIRGINIA ELECTRIC AND POWI R COMPANY RICHMOND, VIRGINIA 23261 April 27, 2004 United States Nuclear Regulatory Commission Serial No.04-213 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 I & 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 1,2003 through December 31, 2003. 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 5.5.2b.

If you have any questions or require additional information, please contact us.

Very truly yours,

. M. Davis Site Vice President Enclosure Commitments made in this letter: None 563

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. M.T. Widmann NRC Senior Resident Inspector North Anna Power Station q

North Anna Power Station 2003 Annual Radiological Environmental Operating Report

Dominion North Anna Power Station RadiologicalEnvironmentalMonitoring Program January1, 2003 to December31, 2003 Preparedby Dominion, North Anna Power Station and Dominion Resources Services

A innualRadiologicalEnvironm ental OperatingReport North Anna PowerStation January1, 2003 to December 31, 2003 Preparedbya:

/ /W. J Eakin Supervi o/Radiological Engineering Dominion Resources Services Preparedbya:

James B. Breeden Supervisor Radiological Analysis and Material Control Dominion North Anna Power Station Reviewed bar: a Erich W. Dreyer Supervisor Health Physics Technical Services Dominion North Anna Power Station Approved byr: ~-7~+ A~/ff%

Robert B. Evans, 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 2003 REMP Samples ........................................................ 33
4. DISCUSSION OF RESULTS ........................................................ 59 4.1 Gamma Exposure Rate ......................................................... 59 4.2 Airborne Gross Beta ........................................................ 61 4.3 Airborne Radioiodine ........................................................ 62 4.4 Air Particulate Gamma and Strontium Analyses ........................................................ 62 4.5 Soil ........................................................ 63 4.6 Precipitation ........................................................ 63 4.7 Cow Milk......................................................... 63 4.8 Food Products and Vegetation ........................................................ 64 4.9 Well Water ........................................................ 64 4.10 River Water ........................................................ 64 4.11 Surface Water ........................................................ 65 4.12 Bottom Sediment ........................................................ 66 4.13 Shoreline Soil ........................................................ 67 4.14 Fish.................................................................................................................................68
5. PROGRAM EXCEPTIONS ......................................................... 69 REFERENCES ......................................................... 70 APPENDICES ......................................................... 72 APPENDIX A: LAND USE CENSUS ................................................... 73 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS .. 75 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2003 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, 2003, 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 Incorporated . (formerly ICN Biomedicals) provided thermoluminescent dosimetry (ELD) services and Framatome ANP DE&S 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 4

Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The NRC also mandates a reporting level for certain radionuclides.

Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.

Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, water, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates and precipitation. The 2003 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 2003 was 2000 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 1868 pCi/liter. No plant related radioisotopes were detected in well water. This trend is consistent throughout the environmental operational monitoring program. One Silt sample indicated the presence of cesium- 137 and is attributable to global fallout from past nuclear weapons testing and nuclear accidents such as Chernobyl. Shoreline sediment, which may provide a direct exposure pathway, indicated the presence of Cs-137 also at levels consistent with global fallout levels. The terrestrial exposure pathway includes milk and food/vegetation products. Iodine-131 was not detected in any 2003 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident.

Although normally observed, Strontium-90 was not detected in milk during 2003.

Its historical presence is attributable to past atmospheric nuclear weapons testing. A ten-year activity trend indicates a slow decrease in Sr-90 activity.

Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels. No man-made radioisotopes were detected in vegetation samples. Consistent with historical data, potassium-40 was detected. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). ELD results have remained relatively constant over the years.

During 2003, 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 2003 was 0.14 millirem. For reference, this dose may be compared to the 360 millirem average annual exposure to every 5'

person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%. These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.

6

2. PROGRAM DESCRIPTION' 2.1 Introduction This report documents the 2003 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 Incorporated (formerly ICN Biomedicals) is responsible for processing the TLDs. Framatome ANP DE&S 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 7

commitment recommended by IOCFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2003 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 2003 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 Framatome ANP DE&S Environmental Laboratory for North Anna Power Station during the year 2003.

8

Table 2-1 NORTH ANNA - 2003 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 103 0 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 - 2003 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Mledia Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 S 1780 Quarterly IThermoluminescent 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) WSW-24/56 1.00 WSW 2420 Quarterly South Gate Switchyard W-25157 0.32 W 2790 Quarterly Route 685 W-26158 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

Tabit 2-1 NORTH ANNA - 2003 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 Radioiodiic 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 OA 0.64 SE 1380 Quarterly (Well Water)

Precipitation Biology Lab OA 0.64 SE 1380 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.

11

Tabie 2-1 NORTH ANNA - 2003 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 2030 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 SAMPETs. M41TA 1; FRTlPnTC.WV ANAT. V.Q T 1.Tn 1RlPn1RT TTNTTT.

Thermoluminescent Dosimetry (TLD)

(84 TLDs) Quarterly Gamma Dose 2 mR+2mR mRlstd. Month (12 TLDs) Annually Gamma Dose 2 mR+2mR mR/std. Month Airborne Radioiodine Weekly 1-131 0.07 pCi/m 3 Airborne Particulate Weekly Gross Beta 0.01 pCi/M3 Quarterly (a) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 2nd Quarter Sr-89 (b) pCi/m 3 Composite Sr-90 (b)

Surface Water Monthly I-131 l(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 I-131 l(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

  • 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.

13

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDTA FROT TENCY ANALY.STS T.T 1) PERPORT I NIT. x,.x---s....

,At.,

,^ w River Water Quarterly(a) Tritium (H-3) 2000 pCi/L 2 nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

Ground Water Quarterly Gamma Isotopic pCiIL (Well Water) Mn-54 15 Fe-59 30 Co-58 15 Co 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 l(c)

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

14

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE, MFED1A FREOQUENCY ANALYVSTI Gre TI,

REPORT

}- t- I TNTT.

Soil Once per 3 years Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Sr-89 (b) pCilkg (dry)

Sr-90 (b)

Alilk Monthly I-131 1 pCiIL Monthly Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (b) pCiAL Sr-90 (b)

Fish Semi-Annually Ganmma 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 1-131 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 lA 01A,SE-13/45 1/33 N-1/33 2 (a) 02,SSW-20/52 31/63 NNW-31/63 3 (a) 03,C-5/16 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 SSV-19/51 Shoreline Soil (d) 21/53 SW-21/53 9A 09A-Water sample, sediment 23/55 WSW-23/55 11 11-River Water, Sedimcnt 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-40/36 25 (c) 25-Fish 10/42 E-10/42 26 (e) 26-Vegetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil. -

(b) In Orange (c) In Lake Orange (d) Station 09 changed to 08 effective August 1996.

(e) Vegetation changed to Station 26 effective Oct 2001 16

(a CB3280C North Anna Environmental Map

  • Fixed Environmental Sampling Location
  • TLD Sampling Garden Residents 0 Meat Animals Original 01991 by ADC of Alexandria, Inc.. 6440 General Green Way.

Atexandria, VA22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

CB32820

I

\ L -AI- \(m7' North Anna Environmental Map

  • Fixed Environmental Sampling Location
  • TLD Sampling Q Garden Residents OriginalO 1991 byADC of Atexandria, Inc., 6440 General Green Way.

Alexandria, VA 22312. USED WITH PERMISSION. No other reproduetion may be made without the written permission of ADC.

CB32S3C

North Anna Environmental Map

  • Fixed Environmental Sampling Location
  • TLD Sampling A 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 D

i 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.

22

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 1 of 10 Air Iodine 1-131 636 0.07 (0/583) N/A N/A (0/53) 0 (pCi/m 3 )

Airborne Gross 636 0.01 23.1(583/583) 05 4.20 mi. 25.2(53/53) 23.2(53/53) 0 Particulates Beta (4.3-43.9) NNE (7.6-40.3) (7.8-36.8)

(IE-03 pCi/m 3)

Gamma 48 Be-7 48 0.1(43/44) 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 (014) 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 Well 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

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program. Revision 1. November 1979.

Table 3-1 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 2 of 10 All Indicator Control Non-Medium or Anal sis Locations Location with Iighest Mean Location routine Pathway l LLD* Reported Sampled Total Mean Namne 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 (014) 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 - (0/1) N/A N/A N/A Sr-90 - (0/1) N/A N/A N/A River Tritium 2000 1868(4/4) 11 5.80 mi. 1868(4/4) N/A Water (800-3560) SE (800-3560)

(pCiAiter)

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program. Revision 1.November 1979. 24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 3 of 10 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) 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 (0112) N/A N/A N/A 0 Zn-65 12 30 (0/12) N/A N/A N/A 0 Zr-95 12 30 (0/12) N/A N/A N/A 0 Nb-95 12 15 (0/12) N/A N/A N/A 0 I-131 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 1 - (0/1) N/A N/A N/A

  • LLD is the Lower Lirnit of Detection as defined and required in USNRC Branch Technical Position on an Accepuble Radiological Environmental Monitoring Program. Revision 1,November 1979.

25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 4 of 10 All Indicator Control Non-Medium or Analysis Locations Location with Iighest Mean Location routin Pathway LLD* .Report(

Sampled l Total Mean Name Distance Mean Mean Mleasur (Unit) Type No. Range Direction Range Range ments River V rater Sr-90 1 - (0/1) N/A N/A N/A 0 (1pCilliter)

S urface Tritium 8 2000 2000(4/4) 08 1.10 mi. 2000(4/4) (0/4) 0 VVater (940-3630) SSE (940-3630) -

(1pCi/liter)

Gamma 24 Mn-54 24 15 (0/12) N/A N/A (0/12) 0 Fe-59 24 30 (0/12) N/A N/A (0/12) 0 Co-58 24 15 (0/12) N/A N/A (0/12) 0 Co-60 24 15 (0/12) N/A N/A (0/12) 0 Zn-65 24 30 (0/12) N/A N/A (0/12) 0 Zr-95 24 30 (0/12) N/A N/A (0/12) 0 Nb-95 24 15 (0/12) ' N/A N/A (0/12) 0 1-131 24 1 (0/12) N/A N/A- (0/12) 0 Cs-134 24 15 (0/12) N/A N/A (0/12) 0 Cs-137 24 18 (0/12) N/A N/A (0/12) 0

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 26

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page S of 10 All Indicator Control Non-Medium or Analysis Locations Location with highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Ty No. Range Direction Range Range ments 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 Sr-90 I - (0O1) N/A N/A (0/1) 0 Precipitation Monthly (pCi/liter) Gross 12 4 7.61(9/12) O1A 0.75 mi. 7.61 N/A Beta (3.1-15.4) SE (3.1-15.4)

Semiannually Gamma 2 Mn-54 2 15 (0/2) N/A N/A N/A 0 Fe-59 2 30 (0/2) N/A N/A N/A 0 Co-58 2 15 (0/2) N/A 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

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 27

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 6 of 10 T All Indicator Control Non-Medium or Anal sis - Locations - Location with Iighest Mean Location routine Pathway LLD* M N D Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) T No. l Range Direction Range Range ments J Precipitation Zr-95 30 (0/2) N/A N/A N/A 0 (pCi/liter)

Nb-95 15 (0/2) NIA N/A N/A 0 I-131 10 (0/2) N/A N/A N/A 0 Cs-134 15 (0/2) N/A N/A NIA 0 Cs-137 18 (0/2) N/A N/A NIA 0 Ba-140 60 (0/2) N/A N/A NIA 0 La-140 15 (0/2) N/A N/A N/A 0 Sediment Gamma Silt (pCi/kg K-40 - 14080(4/4) . 11 5.80 mi. 17015(2/2) 10750(2/2) 0 (dry) (5590-17510) SSE (16520-17510) (10480-11020)

Cs-134 150 (0/4) N/A N/A (0/2) 0 Cs-137 180 133(1/4) 11 5.80 mi. 133(1/2) (0/2) 0 SSE -

Th-228 - 1412(4/4) 08 1.10 mi. 1454(2/2) 567(2/2) 0 (837-2070) SE (837-2070) (360-774)

Sr-89 - (0/2) N/A N/A (0/1)

(Annually)

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program. Revision 1.November 1979. 28

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 7 of 10 Sediment Sr-90 3 - (0/2) N/A N/A (0/1) 0 Silt (Annually) -

(pCi/kg)

(dry)

Soil Triennial (pCi/Kg) Gamma 0 (dry)

Cs-134 0 150 Cs-137 0 180 Sr-89 0 -

Sr-90 0 -

Soil samples are collected every three years. Since they were collected in 2001, they were not collected during 2003.

Shoreline Gamma 2 Soil (pCi/kg) K-40 2 - 2320(2/2) 8 1.10mi. 2320(2/2) N/A 0 (dry) (2280-2360) SSE (2280-2360)

Th-228 2 262(2/2) 8 1.10 mi. 262(2/2) N/A 0 (239-284) SSE (239-284)

Cs-134 2 150 (0/2) N/A N/A N/A 0 Cs-137 2 180 216(2/2) 8 1.10 mi. 216(2/2) N/A 0 (199-233) SSE (199-233)

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

Sr-90 I - (0/1) N/A N/A N/A 0 (Annually)

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmnental Monitoring Program. Revision 1, November 1979. 29

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 8 of 10

. All Indicator Control Non-Medium or Analysis Locations Location with Iighest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) No. Range J Direction Range Range ments Milk Gamma 24 (pCi/liter)

K-40 24 - 1361(24/24) 12 8.3 mi. 1399(12/12) N/A 0 (1196-1530) NW (1320-1530) 1-131 24 1 (0/24) NIA N/A NIA 0 Cs-134 24 15 (0/24) N/A N/A NIA 0 Cs-137 24 18 (0/24) NIA 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 - (0/8) N/A N/A N/A 0 (Quarterly)

Fish Gamma 8 (pCi/kg)

(wet) K-40 8 - 1560(4/4) 08 1.10 mi. 1560(4/4) 1567(3/4) 0 (1210-1900) SSE (1210-1900) (1420-1730)

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

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program. Revision 1, November 1979. 30

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 9 of 10 All Indicator Control Non-Medium or Analysis Locations Location with Iighest Mean Location routin6 Pathway LLD* Reported Sampled Total Mean Distance Mean Mean ReName Measure-(Unit) V e No. _ Range Direction Range Range l ments Fish Co-60 8 130 (014) N/A N/A (0/4) 0 (pCi/kg)

(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 (0/4) N/A N/A (0/4) 0 Food Gamma 25 Vegetation (pCi/kg Be-7 25 -. 2210(19/20) 14 varies 3160(5/5) 936(5/5) 0 (wet)) (470-8260) NE (740-6680) (470-1420)

K-40 25 - 14833(20/20) 14 varies 16436(5/5) 12140(5/5) 0 (8540-32300) NE (9750-32300) (5530-26100)

I-131 25 60 (0/24) N/A N/A (0/5) 0 Cs-134 25 60 (0/24) N/A N/A (0/5) 0 Cs-137 25 80 96(5/20) 23 varies 165(1/5) 104(1/5) 0 (53-165) SSE -

Th-228 - 280(7/20) 15 varies. 360(1/5) 224(1/5) 0 (190-437) SE (282-437)

Direct Gamma 48 2 3.4(44/44) 01 0.20 mi. 5.0(4/4) 2.9(4/4) 0 Radiation Dose (1.0-5.6) NE (4.4-5.6) (2.5-3.4)

(mRlstd. month)

(Environmental TLDs)

  • LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program. Revision 1, November 1979. 31

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2003 Docket No. 50-338/339 Page 10 of 10 All Indicator Control Non-Medium or Anal sis Locations Location with fizhest Mean Location routine Pathway LL*Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) T e No. ___ RaneI____ Direction Range Ranee j ments Direct Gamma 12 2 3.0(11/11) 01 0.2 mi. 5.1(1/1) 3.0(1/1) 0 Radiation Dose (1.6-5.4) NE (mR/std. Month)

(Annual TLDs)

Direct Gamma 288 2 4.4(256/256) 19/51 0.42 mi. 14.4(8/8) 3.0(32/32) 0 Radiation Dose (1.1-19.3) SSW (10.2-19.3) (2.04.0)

(mR/std. Month)

(Sector TLDs)

  • LLD is the Lower Lirnit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 32

3.2 Analytical Results of 2003 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.

The data reported in the following tables are strictly counting statistics. The reported error is two times the standard deviation (2a) of the net activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 3a).

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. Framatome ANP DE&S's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the North Anna ODCM.

Data are given according to sample type as indicated below.

1. Gamma Exposure Rate
2. Air Particulates, Gross Beta Radioactivity
3. Air Particulates, Weekly 1-131
4. Air Particulates, Quantitative Gamma Spectra and Strontium
5. Soil*
6. Precipitation
7. Cow Milk
8. Food Products and Vegetation
9. Well Water
10. River Water
11. Surface Water
12. Bottom Sediment/Silt
13. Shoreline Soil
14. Fish
  • Soil sampling is performed once per three years, therefore no table is included this year. Next sample will be collected 2004.

'Analytical results are handled as recommended by HASL ("Reporting of Analytical Resultsfrom IIASL, " letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).

33

TABLE 3-2 Direct Radiation Measurements - Sector Quarterly TLD Results mR/Std. Month (30.4 days) +/- 2 Sigma Page 1of 3 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Station Name 1/9/2003 4/2003 7/812003 10/2003 Average 4/3/2003 7/812003 10/8/2003 117/2004 C-G 2.8 3.0 3.2 3.1 3.0 0.4 C-2 2.6 3.0 2.9 3.3 3.0 0.5 C-3 2.9 3.3 3.2 3.7 3.3 +/- 0.7 C-4 3.0 3.2 2.2 3.5 3.0 1.1 C-5 2.0 2.5 23 2.4 2.3 +/-0.4 C-6 2.1 2.5 2.4 2.1 2.3 f 0.5 G-7 3.1 3.8 3.9 4.0 3.7 +/- 0.8 C-8 3.2 3.7 32 3.5 3.4 +/-0.5 E-10 4.0 3.0 42 42 3.9 +/-1 2 E-41 4.5 4.8 4.5 5.3 4.8+/-0.7 E-42 3.7 4.3 42 4.5 4.2 +/-0.7 E-9 4.6 4.9 4.8 5.3 4.9 +/-0.6 ENE-39 4.4 4.8 4.4 4.8 4.6 +/-0.5 ENE-40 2.8 3.0 2.9 3.4 3.0 +/-0.5 ENE-7 4.6 4.9 4.4 4.3 4.6 +/- 0.5 ENE-8 2.9 3.1 32 3.1 3.1 +/-0.2 EPSA-01 4.6 4.6 4.9 4.6 4.7 +/- 0.3 EPSA-02 4.8 4.7 4.7 4.9 4.8 +/-0.2 EPSF-03 4.0 4.4 4.3 5.6 4.6 +/-1.4 EPSF-04 4.4 4.4 4.1 4.9 4.5+/-0.7 EPSJ-07 2.8 3.1 2.4 3.4 2.9+/-0.8 EPSJ-08 3.3 3.1 3.5 32 3.3 +/-0.4 EPSP-09 6.9 7.2 7.1 7.8 7.3 +/- 0.8 EPSP-10 7.3 7.2 7.2 8.0 7.4 +/-0.8 EPSR-05 5.6 5.0 4.7 4.9 5.0 +/-0.8 EPSR-06 5.2 5.2 3.6 4.9 4.7 +/-1.5 ESE-11 4.1 4.4 4.6 4.4 4.4 +/-0.4 ESE-12 4.0 4.1 2.8 4.0 3.7+/-1 2 ESE-43 3.9 4.1 4.0 2.9 3.7 +/-1.1 ESE-44 4.1 4.1 4.1 4.5 4.2+/-0.4 N-1 5.0 4.9 4.4 4.5 4.7 +/-0.6 N-2 2.8 3.6 32 3.3 32 +/-0.6 N-33 4.8 5.0 4.1 4.6 4.6 +/-0.7 N-34 2.6 3.1 3.2 3.2 3.0 +/-0.6 NE-37 5.6 5.9 4.3 4.8 5.1 +/-1.5 NE-38 3.2 3.6 3.0 3.5 3.3 +/-0.5 NE-5 4.4 4.3 32 4.5 4.1 +/-1 2 NE-6 3.1 3.4 2.1 4.0 3.1 +/- 1.6 NNE 36 3.6 4.0 3.5 3.8 3.7 +/-0.4 NNE-3 7.0 5.1 6.0 6.5 62 +/-1.7 NNE-35 7.0 6.5 5.9 6.4 6.4t+/-0.9 NNE-4 3.4 4.1 3.7 4.2 3.9 +/-0.7 34

TABLE 3-2 Direct Radiation Measurements - Sector Quarterly TLD Results mR/Std. Month (30.4 days) +/-2 Sigma Page 2 of 3 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Station Name 1/912003 4/3/2003 7/8/2003 10/8/2003 Average 4/12003 7/8/2003 10/8/2003 1(7/2004 NNW-31 3.6 3.7 3.0 3.5 3.5*+/-0.6 NNW-32 3.0 3.8 3.5 4.1 3.6t 0.9 NNW-63 4.4 3.8 3.2 3.4 3.7 +/-1.0 NNW-64 3.0 4.1 3.4 3.5 3.5 +/- 0.9 NW-29 6.6 5.7 5.6 5.8 5.9 +/-0.9 NW-30 2.4 2.8 2.4 2.6 2.5t+/-0.5 NW-61 5.6 5.6 5.9 5.6 5.7+/-0.3 NW-62 2.6 2.8 1.6 3.0 2.5 +/-1.3 S-17 6.9 7.3 6.5 7.0 6.9 +/-0.6 S-18 2.8 2.8 1.1 3.1 2.5+/-1.8 S-49 7.2 6.4 7.1 6.9 6.9 +/-0.7 S-50 2.3 2.5 2.2 1.7 2.2+/-0.6 SE-13 4.1 3.8 3.8 3.8 3.9 +/-0.3 SE-14 6.5 6.8 4.5 7.0 6.2t+/-2.3 SE-45 3.9 4.2 3.9 4.1 4.0 +/- 0.3 SE-46 6.7 6.7 6.0 6.3 6.4:t 0.7 SSE-15 4.7 4.8 5.1 4.9 4.9 +/-0.3 SSE-16 2.9 3.2 2.3 3.2 2.9 +/- 0.8 SSE-47 4.9 4.6 4.8 4.9 4.8 +/-0.3 SSE-48 3.3 3.1 3.1 3.6 3.3 +/-0.4 SSW-19 12.5 13.1 18.0 13.4 142t +/-5.1 SSW-20 2.1 2.8 2.2 2.1 2.3 +/-0.6 SSW-51 14.7 13.9 10.2 19.3 14.5 : 7.5 SSW-52 2.0 32 2.2 2.6 2.5+/-1.1 SW-21 4.0 3.5 3.5 3.4 3.6t+/-0.6 SW-22 4.4 4.1 3.0 4.3 3.9 +/- 1.3 SW-53 4.0 3.2 3.4 4.3 .3.7+/-1.0 SW-54 3.9 4.4 4.1 5.3 4.4 +/-1.2 W-25 5.5 5.9 6.8 6.5 6.2: 1.1 W-26 2.8 2.8 2.3 2.3 2.5 +/- 0.6 W-57 5.3 6.0 5.8 6.1 5.8 +/- 0.6 W-58 2.5 2.8 2.4 2.6 2.6t+/-0.3 WNW-27 2.9 3.5 3.2 2.3 3.0 +/-1.1 WNW-28 2.6 3.7 2.1 3.0 2.9 +/-1.4 WNW-59 2.8 3.1 3.0 3.1 3.0 +/-0.3 WNW-60 2.9 2.9 3.1 2.6 2.9 +/- 0.4 WSW-23 5.3 5.8 5.2 5.2 5.4t+/-0.6 WSW-24 5.1 4.4 4.5 5.0 4.7+/-0.7 WSW-55 4.9 5.6 5.1 5.3 5.2 +/- 0.6 WSW-56 3.8 5.1 4.8 4.2 4.5+/-fi12 Average t 2 s.d. 4.0+/- 3.6 4.2 +/-3.4 3.9 +/- 4.4 42 +/- 3.8 4.1 +/-3.7 35

TABLE 3-2 Direct Radiation Measurements - Quarterly and Annual TLD mR/Std. Month (30.4 days) + 2 Sigma Page 3 of 3 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Annual TLD Station Name 1/9/2003 4/3/2003 7/8/2003 108/82003 Average 4/3/2003 7/8/2003 10/8/2003 1/7/2004 STA-01 5.4 5.6 4.7 4.5 5.1 +/-1.1 3.9 STA-02 2.2 2.3 1.6 2.6 2.2 +/- 0.9 1.5 STA-03 2.1 2.2 1.0 1.9 1.8+/- 1.1 2.1 STA-04 2.3 2.6 1.5 2.6 2.3 +/- 1.0 2.0 STA-0S 3.1 3.4 3.2 3.7 3.4 +/- 0.5 3.1 STA-05A 3.1 3.2 3.0 3.4 3.2 +/- 0.3 2.6 STA-06 3.8 4.0 4.1 4.2 4.0 +/- 0.3 4.2 STA-07 2.7 3.1 3.1 3.0 3.0 +/- 0.4 2.9 STA-21 3.0 2.3 3.1 3.0 2.8 +/- 0.7 2.9 STA-22 4.2 4.5 4.2 4.5 4.4 +/- 0.3 4.2 STA-23 4.8 5.0 4.7 5.2 4.9 +/- 0.4 4.5 STA-24 3.1 3.4 2.8 2.5 3.0 +/- 0.8 2.7 Average +/-2 s.d. 3.3+/- 2.1 3.5 +/-2.2 3.1 +/-t 2.5 3.4 +/-2.0 3.3 +/-2.1 3.1 +/- 1.9 36

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCVm3 ] x 10 pg. 1 of 4 Period Station Station Station Station Station Station Station Endino I 01 I ,

02 03 1 04 1 05 I 05A I 06

_I I

01/01/03 43.9 +/- 4.1 39.7 +- 3.9 36.5 +4- 3.9 34.2 +I- 3.7 40.3 +4- 3.9 36.6 +/- 3.8 37.8 +4- 3.9 01/08/03 14.5 +4- 3.0 13.5 +4- 3.0 11.8 +4- 2.8 16.5 +1- 3.1 14.9 4- 3.0 14.5 +/- 3.0 13.2 +/- 2.9 01/15/03 27.1 +1- 3.3 27.8 +4- 3.3 22.7 +4- 3.1 24.8 +/- 3.2 24.2 4- 3.1 29.3 4- 3.3 27.0 +- 3.2 01/22/03 37.2 4- 3.8 36.0 +4- 3.8 36.8 +4- 3.8 37.7 +/- 3.8 36.6 +4- 3.8 36.0 4- 3.7 37.5 +4- 3.8 01/29/03 27.0 41 3.3 24.1 +4- 3.2 22.0 41-3.1 26.1 4- 3.3 26.0 4- 3.2 24.3 +/ 3.2 26.0 +4- 3.2 02/05/03 30.8 4- 3.6 28.2 +- 3.5 28.5 +4- 3.5 31.5 +/- 3.6 31.0 4- 3.6 30.9 4/- 3.6 29.7 +4- 3.6 02/12/03 26.7 41- 3.5 34.3 +4- 3.8 30.6 4- 3.6 34.8 +1- 3.8 27.4 4- 3.5 28.1 +/- 3.6 31.3 4- 3.7 02/19103 15.2 4- 2.7 17.3 4- 2.8 15.5 4- 2.7 19.7 +/- 4.9 15.8 4- 2.7 14.8 +/- 2.7 16.5 4- 2.8 02/26/03 20.8 4- 3.4 21.3 4- 3.3 19.8 4- 3.4 21.3 +/ 3.4 19.0 4- 3.3 19.0 +/- 3.3 18.2 +4- 3.3 03/05/03 20.5 4- 3.1 26.4 4- 3.3 26.1 +4- 3.3 24.7 +/ 3.3 20.8 4- 3.1 24.4 +I- 3.2 25.7 +4- 3.2 03/12/03 31.2 4- 3.6 26.4 4- 3.5 27.4 4- 3.5 34.1 +/- 3.7 30.6 4- 3.6 24.3 4- 3.4 27.8 41-3.5 03/19/03 24.3 4- 3.2 27.7 41 3.4 27.0 4- 3.3 30.9 +1 3.5 31.2 4/ 3.5 27.2 4- 3.3 27.3 +- 3.4 03/26/03 19.0 +4- 3.2 18.4 41- 3.2 18.9 4- 3.2 19.5 +/- 3.2 22.4 +4- 3.3 21.0 +/- 3.3 21.0 +4- 3.3 04/02/03 19.1 41 3.2 15.9 +- 3.1 19.9 +4- 3.2 22.5 +- 3.3 20.8 +- 3.2 17.6 +/- 3.1 22.4 +- 3.3 04/09/03 14.9 4- 2.8 18.2 +4- 3.0 18.2 4- 3.0 19.6 4- 3.0 19.5 4- 3.1 18.2 +/ 3.0 18.9 +4- 3.0 04/17/03 24.1 4- 3.0 23.4 +1- 2.9 22.2 4- 2.8 25.9 4- 3.0 26.0 4- 3.0 24.6 4/- 2.9 22.8 +4- 2.9 04/23/03 15.8 4- 2.7 11.6 4- 2.6 15.9 4- 2.7 17.1 +/- 2.8 18.8 4- 2.8 11.6 +/- 2.6 14.0 +4- 2.7 05/01/03 25.7 4- 3.0 23.7 4- 2.9 22.2 4- 2.9 23.2 +/- 2.9 25.0 4/ 3.0 24.0 +/- 2.9 20.9 +4- 2.8 05/07/03 19.2 4- 3.2 19.4 41 3.2 22.2 4- 3.3 20.6 +/- 3.4 19.9 4- 3.2 20.4 +/- 3.2 17.1 +- 3.1 05/14103 17.9 4- 3.0 16.0 +4- 2.9 14.9 4- 2.9 16.6 +/- 3.0 18.1 4- 3.0 17.3 +- 3.0 15.7 +- 2.9 05/21/03 17.2 4- 3.0 17.4 4- 3.0 17.2 +4 3.0 18.7 +/ 3.1 17.6 4- 3.0 18.3 +/- 3.0 17.5 +- 3.0 05/28/03 8.1 4- 2.2 7.2 4- 2.1 7.1 +- 3.1 4.3 +/ 2.0 7.6 4- 2.2 5.3 4- 2.1 7.5 +- 2.2 06/04/03 15.7 +- 3.0 16.5 +- 3.0 15.7 +- 3.0 18.9 +/- 3.1 20.0 4- 3.1 14.4 +/- 2.9 17.4 +4- 3.0 06/11/03 17.9 +4- 3.4 18.3 +4- 3.4 16.7 +4- 3.3 18.9 +/- 3.4 13.7 4- 3.2 16.3 4- 3.3 15.8 4- 3.3 06/18/03 20.4 +- 4.3 15.9 +- 2.4 17.4 +- 2.4 17.7 +/ 2.5 20.7 +- 2.6 20.2 +/- 2.6 13.8 4- 2.3 06/25/03 19.0 +/- 3.4 17.0 +4- 3.3 19.1 +4- 3.4 23.0 +/ 3.6 21.8 +4- 3.5 17.9 +/- 3.4 17.1 4- 3.3 37

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m3] x 10-3 pg. 2 of 4 Period Station Station Station Station Station Ending 07 .121 I. 22 23 24 I mum 01/01/03 36.5 +4- 3.8 17.1 +4- 3.1 38.1 +/- 3.9 38.9 +/- 3.9 33.7 +4- 3.4 01/08/03 13.0 +- 3.0 6.1 4/- 2.6 14.4 4/- 3.0 12.9 4- 2.9 17.4 +4- 3.5 01/15/03 27.7 4- 3.3 12.7 +- 2.7 28.9 +- 3.3 26.3 +/- 3.2 24.6 4- 3.2 01/22/03 34.4 41 3.7 17.2 +/- 3.1 33.0 +/- 3.6 33.1 +/- 3.7 32.5 4- 3.7 01/29/03 21.5 +/ 3.1 10.9 +- 2.6 24.8 +4- 3.2 20.7 +/ 3.0 25.0 4- 3.2 02/05/03 26.9 41 3.5 18.0.4- 3.2 30.5 4- 3.6 28.7 +4- 3.6 31.5 4- 3.6 02/12103 28.3 4- 3.6 31.7 4- 3.7 33.6 4- 3.8 27.7 +/ 3.6 32.0 +4- 3.7 02/19/03 17.3 4- 2.8 19.7 4- 2.8 16.0 4- 2.7 16.6 +1- 2.7 17.3 +- 2.7 02/26/03 19.2 4- 3.3 20.0 4- 3.4 20.0 4- 3.4 16.4 4- 3.2 17.5 +4- 3.3 03/05/03 24.3 41- 3.2 24.9 4- 3.2 21.6 +- 3.1 26.5 +/ 3.3 18.2 +- 3.0 03/12/03 28.1 4- 3.5 26.9 4- 3.5 27.2 41- 3.5 30.9 +1 3.6 28.0 +- 3.5 03/19/03 26.2 4- 3.3 23.5 4- 3.2 29.7 4- 3.4 27.3 +1- 3.3 27.7 41- 3.3 03/26/03 17.1 4- 3.1 14.9 4- 3.0 19.8 4- 3.2 16.7 +4- 3.1 18.3 4- 3.2 04/02/03 20.1 4- 3.2 20.1 4- 3.2 16.9 +4- 3.1 20.4 4- 3.2 17.3 4- 3.1 04/09103 16.0 +4- 2.9 17.0 4- 3.0 20.1 +4- 3.1 16.6 4- 2.9 17.4 4- 3.0 04/17/03 21.4 +4- 2.8 21.7 4- 2.8 13.1 41- 2.5 24.7 4- 2.9 22.2 4- 2.8 04/23/03 14.1 4- 2.7 16.3 4- 2.7 16.6 +- 2.7 12.8 +/- 2.6 15.0 4- 2.6 05/01/03 22.0 4- 2.9 19.2 4- 2.7 15.8 +- 2.6 20.8 +/- 2.8 24.9 4- 3.0 05/07/03 17.0 4- 3.1 19.8 4- 3.2 18.2 +4- 3.2 18.3 +/- 3.2 19.2 4- 3.2 05/14/03 15.7 4- 2.9 14.3 +4- 2.9 17.2 +4- 3.0 17.8 +/- 3.0 14.8 4- 2.9 05/21/03 15.3 +4- 2.9 17.6 +- 3.0 15.5 +- 2.9 16.0 +/- 3.0 15.3 4- 2.9 05/28/03 7.1 +/- 2.1 5.7 4- 2.1 8.9 +- 2.2 7.8 +/ 2.1 7.8 +4- 2.2 06/04/03 17.1 +4- 3.0 17.1 4- 3.0 15.0 +4- 2.9 18.8 +/- 3.1 17.5 +/- 3.1 06/11/03 19.6 +/- 3.4 16.8 +/- 3.3 15.5 +4- 3.3 20.3 +/- 3.4 17.7 4- 3.4 06/18/03 17.5 +4- 2.5 15.2 4- 2.3 17.7 +4- 2.5 17.1 +/- 2.5 13.7 4- 2.3 06/25/03 16.2 +/- 3.3 19.3 4- 3.5 17.2 +4- 3.3 21.2 +/ 3.4 21.8 4/ 3.5 38

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m31 X 10-3 pg. 3 of 4 Period Station Station Station Station Station Station Station Ending I 01 I 02 03 1 04 I 05 1 05A I .06 I 07/02/03 33.3 +4- 3.5 27.8 4- 3.4 27.1 +- 3.4 32.7 4- 3.6 30.8 +- 3.5 31.3 4- 3.5 26.5 +- 3.4 07/09/03 17.3 4- 3.4 19.3 4- 3.2 20.1 4- 3.2 24.3 +l 3.3 23.4 4- 3.3 21.2 4- 3.2 19.7 +4- 3.2 07/16/03 16.8 +t- 3.4 18.2 4- 2.5 16.2 4- 2.5 17.4 +/- 2.5 20.4 4- 2.6 21.4 +1 2.6 19.0 +4- 2.5 07/23/03 31.8 4- 3.6 26.0 4- 3.4 29.4 +t- 3.5 31.0 4- 3.6 36.2 4- 3.7 29.2 +1 3.5 25.0 +4- 3.4 07/30/03 24.5 41 4.1 19.0 4- 3.2 21.4 +4- 3.3 24.7 +l 3.4 29.5 4- 3.5 24.5 +1- 3.4 18.3 +- 3.1 08/06/03 16.7 +4- 3.0 15.2 4t 2.9 20.1 4- 3.1 18.4 +1- 3.1 20.9 4- 3.2 16.3 +1- 3.0 14.8 +4- 2.9 08/13/03 17.1 +- 3.1 18.0 +- 3.1 18.3 4- 3.1 23.9 +1- 3.3 22.5 4- 3.3 20.0 4/- 3.2 19.4 +4- 3.1 08/20/03 24.1 +4- 2.6 27.7 +4- 2.7 28.3 4- 2.7 30.2 +1 2.8 36.3 4- 3.0 35.1 4- 5.1 26.9 4- 2.7 08/27103 30.5 +4- 3.5 32.9 +- 3.7 28.3 +- 3.5 37.2 +1- 3.8 38.4 4+- 3.8 29.3 +1- 3.5 30.4 4- 3.6 09/03103 31.2 +- 3.6 26.1 4t 3.4 27.3 4. 3.5 29.5 +t- 3.5 35.3 +- 3.7 27.2 +1- 3.4 30.3 +- 3.5 09/10/03 30.0 +4 70.0 17.8 4- 2.3 17.0 4- 2.3 18.7 4- 2.3 18.8 +4- 2.3 17.7 +1- 2.3 19.1 +/- 2.3 09/17/03 17.1 4- 3.2 19.4 4- 3.2 15.8 4- 3.1 16.3 4- 3.2 21.1 +- 3.3 13.7 +1 3.0 13.0 +- 3.0 09/24/03 26.1 4- 3.5 29.6 4- 3.2 27.4 4- 4.1 31.1 +1 4.0 30.0 4- 11.0 28.2 +1 2.8 31.6 4- 3.2 10/01/03 28.6 4- 3.5 24.1 +4- 3.4 29.1 4- 3.5 29.3 +1 3.7 26.3 4- 4.5 26.7 +1- 3.6 26.5 4- 3.6 10/08/03 28.9 +4- 2.7 26.2 +- 2.5 25.3 +- 2.5 30.5 +1- 2.7 32.2 +/- 2.7 15.1 +1- 6.1 28.1 4- 2.6 10/15/03 34.8 41 3.7 31.5 +- 3.6 36.6 +- 3.8 42.9 +1- 4.0 40.3 4- 3.9 34.1 +1- 3.7 36.6 4- 3.8 10/22103 35.6 4- 3.6 35.3 +- 3.7 31.2 +4- 3.5 38.2 +1- 3.7 37.7 4- 3.7 32.6 +1 3.6 37.3 +l 3.7 10/29/03 19.5 4- 3.2 17.8 +4- 3.1 14.3 +4- 3.0 17.2 +- 3.1 16.1 4- 3.6 14.2 4- 3.0 17.2 +- 3.1 11/05/03 31.9 +- 3.6 26.9 +- 3.5 29.4 +4- 3.5 33.3 +- 3.7 26.6 4t 3.4 29.8 4- 3.5 36.8 4- 3.7 11/13/03 25.0 +- 3.1 25.5 +4- 3.1 20.4 +4- 3.0 25.1 4- 3.1 25.4 4- 3.1 25.0 +1- 3.1 26.7 +- 3.2 11/19/03 27.4 +4- 2.9 28.5 +- 2.9 27.8 +4- 2.9 30.9 4- 3.0 29.9 +4- 3.0 29.0 +4- 2.9 31.8 +4- 3.0 11/25/03 23.6 +4- 3.5 23.4 +4-.3.5 27.2 +- 3.6 23.3 +1- 3.5 27.2 +4- 3.6 25.4 +1- 3.5 29.7 +4- 3.7 12/03/03 25.8 +- 3.2 25.8 +- 3.2 24.8 +4- 3.2 26.6 +1- 3.2 24.5 4- 3.2 26.4 +1- 3.2 26.1 +- 3.2 12/10/03 15.1 +4- 3.2 11.5 +4- 4.1 14.4 +4- 3.1 17.7 +1- 3.3 17.3 +4- 3.3 17.1 4- 3.2 16.0 +4- 3.2 12t17/03 19.2 +4- 2.9 17.8 +4- 2.9 16.9 4- 2.9 22.0 +t 3.1 16.0 +- 2.8 18.2 +/ 2.9 19.7 +4- 3.1 12/23103 28.0 +- 3.9 25.9 4- 3.8 24.8 +- 4.0 27.9 +1- 3.9 30.8 +- 4.1 24.2 4- 3.9 27.4 +- 4.0 12/30/03 21.0 +4- 3.1 23.5 41 3.2 22.0 +- 3.1 22.5 +/- 3.1 23.5 +4- 3.2 22.8 +/- 3.1 22.5 +4- 3.1 39

Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi/m3] x 10-3 pg. 4 of 4 Period tation Station Station Station Station Ending 07 I 21 22 m

23 24 Ij 07/02103 29.1 4. 3.5 28.0 4/ 3.5 25.3 +1- 3.4 25.9 4- 3.4 31.4 +/ 3.6 07/09/03 21.4 +/ 3.3 17.1 +/- 3.1 17.1 +4- 3.1 22.6 4- 3.3 22.5 +1- 3.3 07/16/03 17.2 +/- 2.5 17.0 +/- 2.5 18.3 +/- 2.5 17.6 +/- 2.5 18.4 +/- 2.5 07/23/03 29.0 4* 3.5 25.4 +/- 3.4 25.8 4- 3.4 33.2 +/- 3.6 28.9 +4- 3.5 07/30/03 18.3 +1- 3.1 22.0 +/ 3.3 24.1 4/- 3.3 24.7 +l 3.4 21.8 +/- 3.3 08/06/03 16.1 +/- 3.0 17.6 4/- 3.0 18.1 +4- 3.1 20.0 +/ 3.1 15.7 +/ 3.0 08/13/03 16.7 +/- 3.1 19.3 4 3.2 17.5 +/- 3.1 21.4 +/ 3.2 22.0 4- 3.2 08/20/03 28.8 +1- 2.8 28.9 +4 2.8 27.9 4- 2.7 30.9 +- 2.8 27.8 4- 2.8 08/27/03 I 32.2 +1 3.6 29.3 4 3.5 25.5 +1- 3.4 33.4 +1- 3.7 34.8 4- 3.7 09/03/03 26.1 +1 3.4 28.7 4- 3.5 28.7 +4- 3.6 29.0 +/- 3.5 23.9 +/- 3.3 09/10/03 16.6 +- 2.3 14.9 +4- 2.2 16.4 +/- 2.3 17.4 +4- 2.3 16.2 +/- 2.2 09/17/03 14.4 +4- 3.1 15.6 +/- 3.1 15.9 4- 3.1 15.9 +- 3.1 17.9 +4- 3.2 09/24/03 30.0 41- 3.2 31.8 +/- 3.4 12.0 4- 2.3 34.8 +1- 3.6 28.4 4- 2.8 10/01/03 26.1 +/- 3.5 25.9 +1- 3.5 28.6 +1- 3.5 27.4 +/- 3.5 29.2 4- 3.6 10/08/03 26.9 +1- 2.6 22.6 4/- 2.4 23.4 +1- 2.5 26.9 4/- 2.6 27.2 +/- 2.6 10/15/03 36.3 +4- 3.8 35.3 4- 3.8 29.8 4- 3.6 40.2 +/- 3.9 34.5 +4- 3.8 10/22103 36.5 +/- 3.7 30.1 4/ 3.5 33.0 4- 3.6 35.1 +/- 3.7 33.6 +/- 3.6 10/29/03 17.3 +/- 3.0. 17.0 +/- 3.1 15.4 +/- 3.0 17.4 +/- 3.1 17.3 +4- 3.1 11/05/03 33.4 +4- 3.7 30.0 4- 3.5 32.6 4- 3.6 33.4 +/- 3.6 36.8 4- 3.7 11/13/03 25.7 +/- 3.1 18.5 4- 2.9 21.3 +/ 3.0 23.2 +/- 3.0 25.4 +/ 3.1 11/19/03 15.9 4/ 6.0 27.8 4- 2.9 26.4 +1- 2.8 31.1 +/ 3.0 28.4 +4- 2.9 11/25/03 22.2 4- 3.4 28.5 +1- 3.6 20.3 +/- 3.3 23.8 +/- 3.5 22.9 4- 3.4 12/03/03 23.4 +/ 3.1 25.3 +1- 3.2 22.9 +- 3.1 29.0 +/ 3.3 25.6 +/ 3.2 12/10/03 15.5 +1 3.2 14.9 +/- 3.2 15.6 +/- 3.2 18.8 +/- 3.3 15.9 +/- 3.2 12/17/03 19.9 +/- 3.0 19.3 +/- 3.0 20.3 4- 3.0 20.7 +/- 3.0 19.7 +/ 2.9 12/23/03 26.4 +1 3.9 28.7 4/- 4.0 26.6 +1- 3.9 24.8 +1- 3.8 30.8 4- 4.1 12/30/03 22.3 4/- 3.1 19.6 +/- 3.0 21.0 +/- 3.1 24.9 +/- 3.2 22.9 +/- 3.1 40

Table 3-4 Airborne Iodine I- 131

[pCVm3] X 103 pg. 1 of 4 Period Station Station Station Station Station Station Station Ending 01 I 02 I 03 I 04 I 05 I 05A 06 I

01101/03 -17.0 +1- 15.0 9.0 +4- 16.0 11.0 4- 15.0 -2.0 +1- 12.0 -6.0 4/- 15.0 -5.0 +/- 15.0 -7.0 4- 14.0 01108103 9.0 4- 11.0 0.0 4- 16.0 1.0 4- 13.0 4.0 +/ 13.0 -7.0 +/- 15.0 -6.0 4- 13.0 -8.0 4- 13.0 01/15/03 0.0 +4- 13.0 -6.0 4- 13.0 1.0 4- 15.0 6.0 I-15.0 -1.0 +- 14.0 1.0 +4- 14.0 -4.0 4- 13.0 01/22103 -3.0 +1- 16.0 4.0 4- 17.0 -1.0 +4- 16.0 12.0 +- 18.0 5.0 4- 16.0 10.0 4- 14.0 -14.0 4- 18.0 01/29/03 -4.0 4- 17.0 -2.0 4- 16.0 5.0 4- 14.0 0.0 +/- 14.0 -8.0 4- 21.0 -10.0 4- 18.0 -10.0 4- 19.0 02105103 7.0 +/- 12.0 2.0 +4- 13.0 1.0 4- 11.0 4.0 +- 11.0 -9.0 +- 12.0 -14.0 +- 13.0 0.0 4- 11.0 02/12/03 4.0 4- 11.0 -4.0 4- 12.0 4.0 4- 12.0 -3.0 4- 12.0 0.0 +- 14.0 2.0 +/- 13.0 -7.0 +4- 12.0 02/19/03 -15.0 4- 13.0 7.0 4- 17.0 7.0 4- 16.0 36.0 4- 30.0 -1.0 +4- 16.0 11.0 +/- 16.0 -1.0 +- 18.0 02/26/03 7.0 4- 16.0 2.0 4- 16.0 4.0 +- 16.0 -1.0 4- 14.0 5.0 4- 16.0 2.0 4- 16.0 0.0 4/- 15.0 03105/03 7.0 +4- 14.0 2.0 4- 13.0 1.0 4- 12.0 -5.0 +/ 13.0 0.0 4- 11.0 -7.0 4-/ 12.0 1.0 4- 13.0 03/12103 3.0 +/- 12.0 -2.0 4- 12.0 11.0 4- 12.0 -5.0 +/- 11.0 -4.0 4/- 12.0 5.0 4- 12.0 5.0 4/- 11.0 03/19/03 -4.0 +- 11.0 -5.0 4- 11.0 -4.0 4- 10.0 4.0 +/ 13.0 -4.0 +4- 14.0 1.0 4- 14.0 4.0 +/- 14.0 03/26103 -4.0 - 11.0 -5.0 4- 12.0 7.0 4- 11.0 3.0 +/ 14.0 -7.0 4- 13.0 -7.0 +1-:12.0 -8.0 4+- 15.0 04102/03 10.0 4- 13.0 11.0 +4- 12.0 -4.0 4- 12.0 -4.0 +/- 12.0 -2.0 4- 14.0 -1.0 4- 14.0 -3.0 4- 12.0 04/09/03 -2.0 4- 11.0 1.0 4- 10.0 2.9 4- 9.8 -4.7 4- 9.4 6.0 4- 12.0 -6.7 +1- 9.9 -3.0 4- 13.0 04/17/03 -1.0 4/ 10.0 -13.1 4- 9.3 -3.0 +- 12.0 -5.0 4- 10.0 10.0 +/- 10.0 -4.0 +- 10.0 -14.0 4- 11.0 04/23/03 10.0 4- 15.0 7.0 4- 14.0 1.0 4- 11.0 -8.0 +/- 13.0 1.0 4- 12.0 -3.0 +- 12.0 -5.0 +- 13.0 05/01/03 2.0 4- 11.0 7.0 4- 10.0 -8.0 4- 11.0 -7.0 +/- 11.0 0.0 4- 11.0 0.0 +/- 12.0 -2.0 4- 10.0 05/07/03 -9.0 +/ 16.0 -4.0 4- 17.0 -24.0 4- 14.0 -3.0 4- 19.0 2.0 4- 17.0 0.0 +/ 16.0 *-3.0 -/ 17.0 05/14/03 7.0 4- 14.0 0.0 4- 14.0 -5.0 4- 13.0 -6.0 +/- 19.0 -6.0 4- 13.0 4.0 +/- 13.0 -6.0 4- 11.0 05/21/03 -11.0 4- 15.0 2.0 +4- 12.0 -4.0 +- 13.0 6.0 +/ 17.0 2.0 +- 15.0 18.0 +/- 15.0 0.0 +/- 17.0 05/28103 0.0 4- 11.0 2.0 4- 11.0 0.0 4- 11.0 -8.0 +/- 11.0 -1.0 +/- 13.0 -4.0 +/- 12.0 12.0 +/- 14.0 06/04/11 -10.0 4- 11.0 6.0 4- 13.0 9.0 4- 12.0 -2.0 +/- 13.0 10.0 +- 12.0 -9.0 4- 12.0 4.0 4/- 10.0 06/11/03 -2.0 4- 12.0 6.0 +- 12.0 2.0 4- 12.0 -3.0 +/- 13.0 -2.0 +4- 12.0 4.0 4- 14.0 -3.0 +/- 13.0 06/18/03 -10.0 +4- 17.0 -4.0 +- 12.0 -1.0 +- 12.0 4.0 +/- 14.0 10.0 +- 13.0 -2.0 4- 12.0 1.0 4- 12.0 06/25/03 0.9 +1- 9.3 5.0 +4- 10.0 -3.5 +- 9.6 4.0 +/- 13.0 -4.0 +4- 16.0 4.0 +/- 15.0 3.0 +/- 14.0 41

Table 3-4 Airborne Iodine I - 131

[pCi/m3] x 10-3 pg. 2 of 4 Period Station Station Station Station Station Endina I 07 1 21. I 22 I 23 I 24 I 01/01/03 -6.0 4+ 15.0 -10.0 +- 14.0 1.0 +4 12.0 0.0 4- 13.0 -4.0 +- 12.0 01/08/03 -15.0 4- 12.0 -3.0 +- 14.0 2.0 +4- 11.0 3.0 +/- 12.0 -1.0 +- 13.0 01/15/03 -5.0 4- 15.0 -7.0 4- 15.0 -7.0 4- 12.0 -1.0 +- 12.0 -3.0 4- 16.0 01/22/03 -11.0 +4- 15.0 9.0 +4 14.0 5.0 +4- 15.0 15.0 4- 17.0 5.0 4- 16.0 01/29/03 .6.0 4- 18.0 11.0 +- 16.0 2.0 +- 16.0 -3.0 4- 19.0 11.0 +- 16.0 02/05103 -7.0 +/- 12.0 -1.0 +4- 12.0 8.0 +4 10.0 -10.0 4- 11.0 4.0 +4- 12.0 02/12t03 -4.0 +t 13.0 -11.0 4- 13.0 -2.0 +- 13.0 0.0 +/- 12.0 4.0 +- 13.0 02/19/03 -16.0 +t- 20.0 -14.0 +4- 18.0 -14.0 +- 18.0 -6.0 4- 17.0 -16.0 4- 17.0 02/26/03 -2.0 +4- 16.0 7.0 4- 16.0 2.0 4t 19.0 -14.0 4- 17.0 -10.0 4- 16.0 03/05/03 11.0 +4- 15.0 -5.0 t 12.0 .2.0 4- 14.0 -5.0 +/ 12.0 6.0 +4- 14.0 03/12/03 4.0 +4- 13.0 6.0 +4 11.0 6.0 4t 12.0 0.0 +/ 10.0 0.0 +- 11.0 03/19103 -7.0 4t- 12.0 2.0 + 14.0 11.0 4- 13.0 1.0 +/ 13.0 -4.0 +4- 14.0 03/26t03 3.0 4- 15.0 -5.0 4- 13.0 -5.0 4- 15.0 -10.0 4- 14.0 3.0 +4- 13.0 04/02/03 5.0 4- 12.0 -5.0 +4- 11.0 -4.0 +4- 12.0 -4.0 4- 13.0 1.0 +4- 14.0 04/09/03 0.0 4- 11.0 4.0 +4- 11.0 -6.0 4- 11.0 3.0 +/ 13.0 3.0 +4- 11.0 04/17/03 4.5 4- 9.5 -4.0 4- 11.0 1.0 4- 11.0 5.0 4- 12.0 6.0 +4- 13.0 04/23t03 0.0 4- 14.0 -3.0 4- 13.0 5.0 4- 14.0 -15.0 +/ 13.0 -4.0 4+- 14.0 05/01/03 10.0 4- 11.0 -5.0 4- 13.0 -1.0 4- 12.0 -2.0 +- 10.0 -1.0 4- 11.0 05/07/03 -3.0 +4- 15.0 -19.0 +4- 16.0 20.0 +- 18.0 -17.0 +/- 17.0 -1.0 4- 17.0 05/14/03 13.0 +4- 15.0 1.0 +4- 14.0 12.0 4- 14.0 14.0 4- 15.0 -4.0 +4- 14.0 O5/21/03 -5.0 4. 17.0 -3.0 +- 14.0 -2.0 4- 13.0 7.0 +/- 20.0 8.0 4- 17.0 05/28/03 -3.0 +- 11.0 14.0 4- 11.0 4.0 +4- 11.0 2.0 +/- 11.0 -2.0 4- 10.0 06/04111 -2.0 +4- 12.0 9.0 4- 12.0 -4.0 4- 11.0 5.0 +/ 12.0 14.0 4- 12.0 06/11103 -5.0 +4- 11.0 4.0 4- 11.0 9.0 4- 15.0 5.0 +- 14.0 -7.0 +4- 13.0 06/18/03 -2.0 +4- 15.0 0.0 4/ 14.0 7.0 4- 13.0 7.0 +/ 14.0 2.0 +4- 14.0 06/25/03 11.0 +4- 13.0 8.0 +4- 13.0 5.0 +- 14.0 -5.0 4- 14.0 -14.0 +4- 14.0 42

Table 3-4 Airborne Iodine I - 131

[pCi/m 3 J X 10 3 pg. 3 of 4 Period Station Station Station Station Station Station Station Ending 01 l 02 03 04 05 05A 06 07/02/03 -5.0 11.0 .5.'0 4- 11.0 3.0 +4- 1.3.0 2.0 +/- 12.0 1.0 4- 11.0 12.0 +/- 12.0 8.3 4- 8.3 07/09/03 .1.1 8.8 -4.(0 4- 11.0 5.0 +/- 11.0 -5.0 +/- 12.0 8.0 4- 10.0 -5.0 +/- 12.0 -2.0 4- 12.0 07/16/03 -12.0 23.0 -2.(0 4- 20.0 6.0 +/- 20.0 0.0 +/- 15.0 -15.0 4- 18.0 7.0 +/ 19.0 -13.0 4- 14.0 .

07/23/03 13.0 12.0 -7.(0 4- 14.0 8.0 4- 14.0 -5.0 +/ 13.0 -3.0 +/- 14.0 -4.0 +/- 13.0 11.0 4- 15.0 07/30/03 -3.0 16.0 4.(0 +- 14.0 0.0 +- 13.0 0.0 +/- 14.0 -4.0 4/- 15.0 -2.0 +/ 13.0 6.0 +/- 13.0 08/06/03 4.0 12.0 -2.() 4- 12.0 -6.0 +4- 14.0 10.0 +- 11.0 10.0 4-/ 1 2.0 1.0 +/- 12.0 7.0 4/- 14.0 08/13/03 -2.0 12.0 -12.(0 +4- 12.0 4.0 +4- 12.0 -2.0 4- 12.0 3.0 4- 13.0 1.0 4- 13.0 -2.0 +/- 14.0 4I-08/20103 14.0 11.0 12.(2 4- 14.0 -6.0 4- 13.0 -6.0 4- 13.0 3.0 4- 10.0 -14.0 4- 27.0 3.0 +4- 13.0 4I-08/27/03 9.0 .15.0 -20.(0 +4- 17.0 0.0 +4- 16.0 2.0 +/- 15.0 0.0 4- 1 6.0 2.0 +/- 15.0 4.0 +- 15.0 4I-09/03103 7.0 17.0 0.( +/- 14.0 -11.0 +/- 18.0 4.0 +- 17.0 -7.0 + 2'1.0 0.0 +- 16.0 -9.0 +/- 23.0 4.-

09/10/03 -160.0 660.0 -5.(0 4/ 11.0 3.0 +4 1.5.0 5.0 +/ 15.0 7.0 4- 14.0 7.0 4- 14.0 5.0 4/- 13.0 4I 09/17/03 7.0 17.0 -12.( +/- 15.0 -8.0 +- 1.5.0 -17.0 +- 16.0 -2.0 4- 16.0 10.0 +/ 17.0 -6.0 4- 17.0 09/24/03 *4.0 21.0 5.( +/- 16.0 -7.0 +4- 19.0 -13.0 +/- 20.0 3.0 4- 17.0 1.0 4- 12.0 -5.0 4- 15.0 10/01/03 0.0 4I 15.0 9.(0 +/- 14.0 8.0 +/- 1.4.0 12.0 +- 16.0 11.0 4- 2'1.0 3.0 4- 19.0 -8.0 4- 15.0 10/08/03 *2.0 15.0 8.(0 4- 15.0 8.0 +/- 15.0 0.0 +- 13.0 5.0 4- 12.0 7.0 4- 19.0 -9.0 4+- 1 4.0 4I 10/15/03 -11.0 14.0 *6.(2 +- 11.0 -6.0 +- 15.0 5.0 +/ 13.0 7.0 4- 13.0 0.0 +/ 13.0 -7.0 4- 15.0 4I 10/22/03 2.0 16.0 -6.(0 4- 15.0 -11.0 4- 16.0 10.0 +/- 16.0 0.0 4- 15.0 3.0 +/- 13.0 5.0 4- 17.0 10/29/03 3.0 4I 12.0 -2.(2 4- 11.0 9.0 4- 14.0 -11.0 4- 17.0 -8.0 4/- 220.0 -2.0 +/ 13.0 -6.0 4- 15.0 11/05/03 6.0 13.0 -9.(0 4- 15.0 5.0 4- 16.0 6.0 +/- 14.0 0.0 +4- 15.0 -14.0 +/- 15.0 -20.0 4/- 14.0 11/13/03 *6.0 16.0 0.(2 +- 12.0 3.0 4- 14.0 -1.0 +/ 15.0 -13.0 4+- 13.0 -1.0 +/- 12.0 -4.0 4- 14.0 11/19/03 14.0 14.0 .3.'2 +- 12.0 1.0 4- 11.0 -8.0 +/ 14.0 4.0 4+- 14.0 -6.0 +/- 14.0 0.0 4- 10.0 11/25/03 14.0 20.0 1.12 +/- 16.0 6.0 +- 18.0 13.0 +- 22.0 14.0 +/- 18.0 10.0 +/- 15.0 -3.0 4- 20.0 12/03103 0.0 17.0 -1.( +/- 16.0 -1.0 +/- 16.0 7.0 +/ 15.0 -7.0 4- 15.0 1.0 +/ 15.0 -6.0 4- 14.0 12/10/03 I 4.0 17.0 4.(0 +/ 25.0 -13.0 +- 19.0 -10.0 +/ 18.0 15.0 4- 17.0 -9.0 +/- 15.0 5.0 +- 1I6.0 12/17/03 7.0 15.0 +/- 15.0 1.0 +/- 16.0 -4.0 +/- 14.0 11.0 4- 1 2.0 12.0 4- 13.0 -6.0 +/- 13.0 12/23/03 33.0 35.0 20.( +/- 28.0 3.0 +4- 38.0 0.0 +/- 34.0 30.0 4- 37.0 -10.0 4- 28.0 -11.0 4+- 3 3.0 12/30/03 10.0 20.0 -2.( +/- 21.0 -16.0 +4- 20.0 -2.0 +/- 16.0 4.0 4- 221.0 -10.0 4- 19.0 10.0 +/- 2 1.0 43

Table 3-4 Airborne Iodine I - 131

[pCi/m3] x 10-3 pg. 4 of 4 Period Station Station Station Station Station Ending 07 I. 21 22 23 24 I

m 07/02103 -1.0 +/- 13.0 -13.0 +1- 12.0 3.0 +/- 11.0 -3.0 +/- 12.0 -11.0 4/ 13.0 07/09/03 3.0 +/- 12.0 -4.0 +1- 11.0 -3.0 +/- 11.0 -2.0 +/- 13.0 .8.0 +1- 11.0 07/16/03 2.0 +/. 15.0 8.0 +1- 13.0 16.0 +/- 15.0 6.0 +l 16.0 -7.0 +1- 13.0 07/23/03 2.0 +/ 13.0 7.0 +1- 13.0 -11.0 +1- 13.0 -12.0 +l 15.0 7.0 +1- 15.0 07/30/03 7.9 41- 8.5 -8.0 11.0 11.4 +1 9.6 3.1 +/- 7 .8 0.0 +1 10.0 08/06/03 -10.0 +/- 14.0 -4.0 +1- 13.0 -16.0 +1 14.0 6.0 +/- 13.0 14.0 13.0 I/-

08/13/03 -1.0 4/- 13.0 1.0 +1- 14.0 -12.0 +1- 12.0 -1.0 +/- 13.0 1.0 4/- 12.0 08/20/03 11.0 +/- 15.0 -3.0 +1-14.0 -3.0 4/- 14.0 -11.0, +1 13.0 3.0 +1- 11.0 08/27/03 -3.0 +/- 23.0 1.0 19.0 5.0 +1- 20.0 0.0 + 16.0 I- 2.0 +/- 17.0 09/03/03 -18.0 +/ 17.0 -2.0 19.0 -5.0 +1- 17.0 9.0 +/- 2.1.0 -9.0 +1- 22.0

+1-09/10iO3 -1.0 4/- 14.0 * -8.0 14.0 -2.0 4/- 13.0 0.0 +1- 15.0 10.0 +/- 13.0

+1-09/17/03 -4.0 +/- 14.0 -2.0 17.0 0.0 +1 20.0 .8.0 +/- 14.0 .4.0 +1- 17.0

+1-09/24/03 14.0 +/ 17.0 11.0 16.0 6.0 +1- 11.0 -1.0 +1 16.0 10.0 +1 13.0

+1-10/01/03 5.0 +/- 14.0 .10.0 16.0 0.0 +/- 15.0 -11.0 + 14.0 I- 8.0 4/- 15.0 10/08103 3.0 +/- 11.0 -3.0 16.0 -3.0 +/- 15.0 10.0 +/- 15.0 -10.0 +/- 14.0

+1-10/15/03 -8.0 4/ 13.0 0.0 13.0 -9.0 +/- 15.0 -18.0 +/ 13.0 4.0 4/- 14.0

+1-10/22/03 -13.0 +/- 14.0 10.0 14.0 -10.0 +4- 15.0 -18.0 +/ 15.0 -3.0 4/- 16.0 10/29/03 .11.0 +/ 14.0 0.0 18.0 -14.0 +1/ 17.0 -11.0 +1- 13.0 3.0 +1 13.0 11/05/03 13.0 +/- 17.0 2.0 13.0 6.0 +1- 14.0 3.0 4/- 11.0 6.0 +- 15.0 11/13/03 -9.0 +/- 14.0 -7.0 13.0 0.0 +/ 13.0 -4.0 4I- 15.0 0.0 +1- 14.0 11/19/03 -6.0 +/- 16.0 -4.0 12.0 10.0 4/- 11.0 1.0 +/ 15.0 -1.0 4/- 12.0

+1-11/25/03 9.0 +/ 19.0 14.0 20.0 16.0 +/ 19.0 0.0 +1 18.0 3.0 +/- 17.0 12/03/03 3.0 4/- 14.0 -1.0 14.0 6.0 4/- 13.0 -4.0 +/- 14.0 -1.0 +/- 15.0 12/10/03 9.0 +/- 14.0 12.0 +1- 20.0 -4.0 +/ 17.0 14.0 +/- 18.0 -12.0 +/- 16.0 Ie 12/17/03 -2.0 +/ 15.0 2.0 4/ 14.0 -1.0 +/- 13.0 -9.0 +/- 16.0 -6.0 +1/ 14.0 12/23/03 16.0 +/- 37.0 0.0 4/ 24.0 -17.0 4/ 32.0 30.0 4/- 333.0 0.0 +1- 303.0 12/30/03 0.0 +/- 26.0 14.0 17.0 -14.0 +1- 20.0 -10.0 +/- 226.0 -10.0 +/- 2!4.0 44

Table 3-5 Airborne Particulate First Quarter Gamma Spectra and Strontium

[pCi/me] X 10'3 Sampling Location l Be-7 l K-40 l Cs-134 l Cs-137' Sr-89 l Sr-90 01 109.0 4- 32.0 -17.0 +4- 13.0 -0.6 4- 0.9 -1.8 +- 1.4 [a] [a]

02 86.0 4/ 30.0 -25.0 +4- 9.1 -0.4 +/- 0.3 0.0 +/- 1.4 [a] [a]

03 74.0 +4- 29.0 .20.0 +- 11.0 -0.5 4- 0.9 -0.4 +4- 1.6 [a] [a]

04 77.0 +4- 29.0 -18.0 4- 13.0 0.0 4- 1.1 0.0 +/- 1.7 [a] [a]

05 101.0 +4- 30.0 -18.0 4- 12.0 -0.1 4- 0.9 0.4 +4 1.4 [a] [a]

05A 108.0 4- 34.0 -20.0 4- 11.0 -0.1 4- 0.9 -1.2 4- 1.4 [a] [a]

06 111.0 4- 30.0 -20.0 4+- 11.0 0.0 4- 0.7 0.4 4- 1.6 [a] [a]

07 128.0 4- 34.0 -25.0 +/- 11.0 -0.1 +4- 1.0 0.1 4- 1.5 [a] [a]

21 95.0 4- 33.0 -25.0 +- 9.1 -0.4 +/- 0.6 0.8 4- 1.6 [a] [a]

22 115.0 4- 29.0 -20.0 +4- 9.4 -0.5 4- 0.9 -0.4 +- 1.4 [a] [a]

23 76.0 4- 34.0 -19.0 +- 13.0 0.0 4- 0.8 0.8 4- 1.6 [a] [a]

24 88.0 4- 30.0 -25.0 .4- 11.0 0.5 4- 0.8 0.4 4- 1.9 [a] [a]

Second Quarter Gamma Spectra and Strontium

[pCi/m 31 X 103 Sampling Location l Be-7 l K-40 Cs-134 l Cs-137 l Sr-89 Sr-90 01 104.0 4- 33.0 -2.0 +4- 11.0 0.0 +- 0.6 -0.1 4- 0.7 1.3 +/- 9.3 0.6 +/- 1.5 02 100.0 4- 33.0 -5.2 +4- 8.7 -0.2 4- 0.6 -0.3 4- 0.5 -4.0 +l 11.0 0.2 +- 1.9 03 121.0 4- 33.0 0.1 +/- 8.0 0.4 4/- 0.5 -0.2 4- 0.6 1.6 +I- 9.2 -0.5 +4- 1.3 04 115.0 4- 32.0 0.1 +/- 8.1 -0.4 +- 0.8 0.0 4- 0.8 -4.9 +1- 8.3 -4.0 4- 1.4 05 112.0 4- 32.0 4.3 +/- 8.6 0.2 4- 0.7 0.0 4- 0.6 -9.6 +/ 6.5 0.1 4- 1.3 05A 131.0 +- 32.0 1.0 +- 10.0 0.2 4- 0.8 0.0 4- 0.8 -5.2 4- 6.7 0.1 4- 1.2 06 95.0 +- 30.0 1.4 +- 7.6 -0.1 4- 0.7 -0.7 41- 0.7 -2.7 +1- 6.8 0.1 4- 1.1 07 95.0 4- 30.0 -2.6 +4- 7.9 0.6 4- 0.8 0.5 +- 0.7 -6.6 +l 6.8 -0.5 4- 1.2 21 118.0 4- 32.0 10.0 +- 10.0 0.7 +4- 0.6 0.1 +4- 0.6 -2.7 +1- 8.2 0.8 +- 1.4 22 82.0 +- 30.0 -1.0 +4- 9.3 0.2 +4- 0.7 0.7 4- 0.8 -5.8 +/- 6.9 0.0 +- 1.2 23 94.0 4- 34.0 -9.5 +- 7.2 0.4 4- 0.7 0.2 4- 0.5 -5.9 +/ 6.3 0.1 +- 1.1 24 117.0 4- 31.0 -8.4 +4- 5.5 0.0 4- 0.6 0.0 4- 0.8 -4.9 +/- 8.3 0.2 +4- 1.5

[a] Sr-89/90 analysis performed on the second quarter composite 45

Table 3-5 Airborne Particulate Third Quarter Gamma Spectra and Strontium

[pCi/M 3 ] X 103 Sampling Location I Be-7 I K-40 I

Cs-134 I Cs-137*

I Sr-89 I Sr-90

_I I

01 69.0 22.0 3.0 +- 10.0 0.4 +/- 0.7 -0.3 /- 0.7 [a] [a]

02 67.0 22.0 -0.5 4- 7.0 -0.3 +4-0.5 -0.2 +/ 0.7 la] [a]

03 88.0 23.0 -6.3 4. 5.6 0.0 +/- 0.7 -0.4 +/- 0.7 [a] [a]

04 82.0 4I- 24.0 4.0 +/- 9.6 0.2 4 0.6 0.4 +/- 0.6 1a] [a]

05 105.0 4I- 26.0 3.3 +4. 8.5 0.2 +/ 0.7 0.4 +/- 0.7 la] [a]

05A 82.0 26.0 -0.1 4+-9.9 -0.2 +/- 0.6 -0.3 +/- 0.6 [a] [a]

4I-06 53.0 21.0 5.0 +4 12.0 0.6 +/- 0.6 0.4 +/- 0.7 [a] [a]

07 100.0 4I- 29.0 0.0 +4- 15.0 0.6 +/- 1.0 -0.2 +4 1.6 [a] [a]

21 78.0 28.0 -6.0 +/- 15.0 0.1 4- 0.8 -0.6 +/- 1.8 [a] [a]

22 89.0 26.0 4.0 +/ 9.5 0.0 4- 0.9 1.3 4/- 1.8 la] [a]

23 116.0 32.0 4.0 4- 12.0 0.2 +/- 1.0 0.6 4. 1.8 [a] [a]

24 90.0 28.0 -8.0 +/- 11.0 0.9 4J- 0.7 -0.6 41- 1.7 [a] [a]

Fourth Quarter Gamma Spectra and Strontium

[pCi/M 3 ] X 10i 3 Sampling Location Be-7 1 K-40 I Cs-134' I Cs-137' I Sr-89 I Sr290 l-l 01 80.0 4J- 26.0 2.0 10.0 0.2 4/- 0.6 -0.6 4/ 0.9 [a] I [a]

02 79.0 4- 27.0 -4.9 4I- 6.9 -0.1 4- 0.7 0.1 +/- 0.8 [a] [a]

03 65.0 4- 27.0 -0.7 4I- 7.3 0.0 +4- 0.7 -0.1 +/- 0.8 la] [a]

04 87.0 4. 31.0 0.6 4.- 6.9 -0.6 +/- 0.6 -0.4 +/- 0.6 [a] * [a]

05 78.0 4/ 27.0 -6.5 4.- 4.8 0.0 +/- 0.6 0.2 +/- 0.7 [a] [a]

05A 87.0 +1 31.0 -3.3 9.8 0.0 48- 0.8 0.1 41- 0.7 [a] [a]

4.-

06 96.0 +4- 30.0 -6.0 8.2 0.0 +/- 0.8 0.2 +4- 0.5 [a] [a]

4.-

07 74.0 +4- 27.0 -2.0 10.0 0.1 4- 0.7 -0.8 +/- 0.8 [a] [a]

21 105.0 +- 29.0 3.0 11.0 -0.2 +/- 0.7 -0.5 +/- 0.7 [a] [a]

22 64.0 +- 25.0 6.5 9.8 0.1 +4- 0.8 0.2 +/- 0.5 [a] [a]

23 100.0 +- 28.0 1.1 9.3 0.3 4/- 0.7 0.0 +4- 0.5 [a] [a]

24 76.0 4- 27.0 -3.2 8.3 0.3 +/- 0.7 -0.3 +- 0.7 [a] [a]

[a] Sr-89/90 analysis performed on the second quarter composite 46

Table 3-6 Soil sampling is performed once per three years, therefore no table is included this year.

Next sample will be collected in 2004 47

Table 3-7 Precipitation Gamma Spectra

[pCVLI pg. 1 of 2 06/25/2003 Sampling Location I Be-7 II K-40 I Cr-51 I Mn-54 l Fe-59 I Co-58 l Co-60 I 01A 16.0 +/- 15.0 1.0 +/- 28.0 -10.0 +/- 14.0 -1.9 +/- 1.7 -1.8 +/- 3.4 1.0 +/- 1.8 -0.2 +/-

MMMMMW 1.8 I Zn-65 L Zr-95 I Nb-95 I Ru-1 03 l Ru-106 I Sb-125 1 1-131 I O0A -0.8 +/- 3.6 -1.5 +/- 3.7 1.2 +4- 2.0 -0.1 +/- 1.9 3.0 +/- 14.0 -3.8 +/- 4.6 -1.4 +/- 4.0 L Cs-134 *I Cs-137 I Ba-140 , I

OA 0.7 +/- 1.8 1.1 +/- 1.5 0.0 +/- 3.4 0.0 +/- 3.9 4.9 +4- 6.0 12/30/2004 Sampling Location l Be-7 l K-40 I Cr-51 I Mn-54 I Fe-59 I Co-58 l Co-60 `--

OIA -5.0 +/- 21.0 22.0 +/- 34.0 15.0 +/- 25.0 0.2 +/- 2.4 0.9 +1- 8.2 -1.4 +/- 2.3 -1.5 +4- 2.6 OA L Zn-65 I Zr-95 I Nb-95 I Ru-103 I Ru-106 I Sb-1 25 I 1-131 I

5.0 +/- 9.3 -0.7 +/- 4.2 -0.3 +/- 2.4 -1.5 +/- 2.6 -3.0 41- 23.0 3.8 +/- 6.6 -1.3 +/- 5.1 L Cs-1 34 I Cs-137 I Ba-140 I La-140 I Th-228 I

==

OA -1.9 +/- 2.4 -0.5 +4- 2.7 -0.9 +/- 3.4 -1.1 +/- 4.0 -5.5 +1- 9.4

Table 3-7 Precipitation Gross Beta rpci/L]

pg. 2 of 2 Sampling Date I Gross Beta I l Rainfall (inches) I 01/29/03 13.3 +/- 2.2 1.99 02/26/03 15.4 +- 2.9 4.60 03/26/03 4.8 4- 1.4 3.95 05/01/03 4.6 4/ 2.0 5.83 05/28/03 1.6 4- 1.5 7.14 06/25/03 3.3 4- 1.9 6.80 07/30/03 3.5 +4- 1.9 5.88 08/27/03 15.2 +4- 2.9 1.03 09/24/03 0.4 4- 1.6 9.97 10/29/03 5.3 4- 2.1 2.95 11/25/03 3.1 +/- 1.9 4.28 12/31/03 0.3 4- 1.6 6.26 mean 5.9 +4- 2.0

' LLD identified in ODCM 49

Table 3-8 Milk Gamma Spectra

[pCi/L]

Sampling Station 12 Date 01/22/03 I K-40 1360.0 +/- 120.0 I Sr-89 I Sr-90 0.15 1-131'

+/- 0.26 L Cs-134-3.7 +- 3.1 N

_ I Cs-i 37_

-0.9 +/- 3.3 I Ba-1 40'

-0.8 +/- 5.9

. La-1 40'

-1.0 +/- 6.8 I

[a] [a]

02/19/03 1350.0 +/- 120.0 la] [a] -0.06i +/- 0.02 1.6 +/- 3.4 -1.9 +/- 3.3 1.8 +/- 4.6 2.1 +/- 5.3 03/19/03 1358.0 +/- 96.0 -41.0 +/- 12.0 0.8 +/- 2.3 -0.022 +/- 0.07 .0.1 +/- 3.0 0.0 +/- 2.4 3.1 +/- 4.9 3.5 +/- 5.6 04/23/03 1400.0 +/- 100.0 [a] [a] -0.12 +/- 0.04 40.4 +/- 2.7 -0.2 +/- 2.6 -0.5 +- 5.6 -0.6 +/- 6:4 05/21103 1420.0 +/- 140.0 [a] [a] 0.30I +/- 0.35 -3.6 +/- 3.9 0.8 +/- 3.4 3.8 +/- 6.1 4.3 +/- 7.0 06/25/03 1380.0 +/- 120.0 -4.2 +/- 4.4 0.0 +/- 1.1 -0.08 3 +/- 0.21 1.2 +/- 3.4 1.0 +/- 2.8 0.7 +/- 5.0 0.8 +/- 5.8 07/23/03 1320.0 +/- 140.0 [a] [a] -0.06; +/- 0.02 1.9 +/- 4.1 -0.6 +/- 3.6 1.8 +/- 6.7 2.1 +/- 7.7 08/27/03 1480.0 +/- 120.0 [a] [a] 0.201 +/- - 0.S4 0.5 +/- 3.0 4.2 +/- 3.1 -3.9 +/- 4.7 -4.5 +/- 5.4 09/24/03 1380.0 +/- 120.0 2.0 +/- 4.3

  • 0.4 4+- 1.0 0.12 3 +/. 0.49 1.4 +/- 3.4 -3.2 +/- 3.1 0.3 +- 4.3 0.4 +/- 5.0 10/28/03 1320.0 +/- 110.0 ((a] l[a]. 0.17 I +/- 0.43 -0.9 +/- 3.1 1.3 +/- 2.5 -2.7 +/- 4.0 -3.1 +4- 4.6

.11/25/03 1530.0 +/- 120.0 [a] [a] 0.26; +/- 0.56 -0.8 +/- 3.8 -3.7 +4- 3.3 3.5 +- 7.1 4.0 +/t 8.2 12/17/03 1500.0 +/- 99.0 3.5 +l- 5.0 1.0 +/- 1.0 0.12 +/- 0.31 -1.1 +/- 2.9 -0.7 +/- 2.5 2.1 +/- 5.8 2.5 +/- 6.7 Sampling Station 13 Date 01/22/03 I

1260.0 K-40

+/- 120.0 I Sr-89 I Sr-90 I 1-131' 0.13 3 +l 40.24 I Cs-134 0.4 +/- 3.0 I

-2.4 Cs-137'

+/- 3.0 I

2..4 Ba-140*

+/- 4.5 l La-140' 2.7 +/- 5.2 I

[a] [a]

02/19/03 1339.0 +/- 87.0 [a] [a] -0.06; + I43.02 0.0 +/- 2.2 -3.4 +/- 2.3 -0,.2 +/- 3.1 -0.2 +/- 3.6-03/19/03 1330.0 +/- 96.0 -15.0 +/- 13.0 0.0 +/- 2.2 0.25; +l I3.36 -0.8 +/- 2.8 1.4 +/- 2.4 -1..2 +I- 4.7 -1.4 +/- 5.4 04/23/03 1196.0 +/- 86.0 [a] [a] 0.42I + 4 I3.43 -1.5 +/- 2.7 0.0 +/- 2.1 -1..3 +/- 5.1 -1.5 +/- 5.9 05/21/03 1340.0 +/- 130.0 [a] [a] 0.00 I +l/ I3.17 1.4 +/- 3.7 -1.0 +/- 3.5 -4.,.3 +/- 6.1 -4.9 +/- 7.0 06/25/03 .1290.0 +/- 100.0 -0.7 +/- 5.2 1.5 +/- 1.8 0.13 3 +/- 0.30 1.0 +/- 2.7 -1.6 +/- 2.8 -1..4 +I- 3.9 -1.6 +/ 4.5 07/23/03 1480.0 +/- 140.0 [a] [a] -0.083 +/- I3.03 0.2 +/- 3.7 0.2 +/- 3.8 0..4 +/- 6.0 0.5 +/- 6.9 08/27/03 1360.0 +/- 110.0 [a] [a] 0.01 I+/- 3.19 -0.1 +/- 2.7 -0.6 +/- 3.0 0..4 +/- 5.0 0.5 +/ 5.7 09/24/03 1370.0 +/- 110.0 -1.3 +/- 5.2 0.0 +/- 1.0 -0.21 +/- I3.45 -2.9 +/- 3.4 2.9 +/- 3.1 0..0 +/- 4.1 0.0 +/ 4.7 10/28/03 1274.0 +/- 99.0 [a] [a] 0.12 4+l 43.40 3.7 +/- 2.8 -0.2 +/- 2.7 -4,.1 +/ 4.9 -4.7 +/- 5.6 11/25/03 1410.0 +/- 140.0 [a] [a] 0.19 I +l I0.57 1.8 +/- 4.0 -0.4 +/- 4.3 3,.4 +/- 7.3 3.9 +I- 8.4 12/17/03 1210.0 +/- 140.0 3.4 +/- 6.1 1.1 +/- 1.1 -0.10 I +l I0.04 -3.7 +/- 4.7 -0.3 +/- 4.6 4,.8 +l- 7.5 5.5 +I- 8.6

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

50

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

pg. 1 of 2 Sampling Sampling Location 14 Date 05/21/03 I

Be-7 1590.0 4I- 560.0 l

12300.0 K-40

+/- 1400.0 1 54.0 1-131'

+/- 49.0 I

28.0 Cs-134'

+/- 36.0 1

5.0 Cs-137'

+/- 31.0

-Ir 80.0 Th-228

+/- 140.0 06/18/03 3310.0 400.0 14700.0 +/- 960.0 39.0 +/- 42.0 30.0 +/- 25.0 5.0 +/- 26.0 160.0 +/- 130.0 07/16/03 3480.0 4/- 450.0 13130.0 +/- 850.0 13.0 +/- 29.0 -1.0 +/- 26.0 10.0 +/- 23.0 109.0 +/- 86.0 08/20/03 740.0 240.0 9750.0 4- 680.0 -2.0 +/- 21.0 4.00 +/- 20.00 3.0 +/- 16.0 -3.0 +/- 87.0 09/17/03 6680.0 4I- 580.0 32300.0 +- 1200.0 14.0 +/- 28.0 29.00 +/- 33.00 75.0 +4- 37.0 290.0 +/- 120.0 I-x +/- y x +1- y x +/- y x +/- y x +/- y x +- y Be-7 l K-40 11-131* Cs-134 l Cs-137 l Th-228 15 05/21/03 1080.0 +/- 450.0 11900.0 +/- 1200.0 15.0 +/- 30.0 6.0 +/- 33.0 0.0 +/- 28.0 80.0 +4- 160.0 06/18/03 680.0 +/- 300.0 16900.0 +/- 960.0 45.0 +/- 45.0 33.0 +/- 28.0 55.0 +- 34.0 437.0 4- 91.0 07/16/03 570.0 +/- 350.0 9940.0 +/- 860.0 -8.4 +/- 3.7 5.0 +4- 28.0 0.0 +- 26.0 50.0 4- 130.0 08/20/03 1510.0 +/- 320.0 8540.0 +4- 700.0 -8.0 +/- 18.0 9.00 +/- 22.00 -7.0 +/- 19.0 18.0 +- 97.0 09/17/03 6070.0 4- 500.0 31400.0 4- 1300.0 0.0 +/- 28.0 31.00 +/- 29.00 53.0 +/- 33.0 282.0 +/- 98.0 x 4 y x y x +/- y x 4- y x +/-y' x +1- y Be-7 l K-40 11-131 l Cs-134 l Cs-137 l Th-228 16 05/21/03 1240.0 +1- 520.0 10600.0 +/- 1400.0 4 6.0I +/- 25.0 18.0 4+- 33.0 -19.0 +/- 32.0 -10.0 +/- 150.0 06/18/03 1280.0 4- 250.0 5530.0 I +/- 490.0 16.0 +/- 32.0 2.0 4/- 20.0 13.0 +/- 18.0 -12.0 +/- 87.0 07/16/03 920.0 4- 290.0 8520.0 i +/- 820.0 21.0 +/- 35.0 32.0 4/- 22.0 -10.0 +/- 20.0 98.0 4/- 87.0 08/20/03 1290.0 41- 350.0 9950.0 i +/- 720.0 7.0i +/- 27.0 9.00 4+- 23.00 -14.0 +/- 20.0 95.0 +/- 77.0 09/17/03 7120.0 +1- 440.0 26100.0 4

+/- 1000.0 18.0i +/- 30.0 27.00 4- 24.00 104.0 +/- 28.0 224.0 +/- 84.0

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

pg. 2 of 2 Sampling Sampling Location Date Be-7 I IK-40 M I 1-131* Cs-134- I Cs-137' I Th-228 23 05/21/03 470..0 +4- 360.0 13700.0 1400.0 .6.0 ) +/- 116.0 11.0 +/- 30.0 30.0 +/- 30.0 30.0 +/ 120.0 06/18/03 1070..0 +/- 200.0 8920.0 560.0 5.0I +/- "2.5 5.0 +- 16.0 5.0 +/- 17.0 21.0 4/- 71.0

+/-

07/16/03 860..0 +/1 280.0 12020.0 810.0 23.0I +/- v35.0 12.0 +/- 22.0 3.0 +/- 19.0 100.0 +/- 100.0 4.l 08/20/03 1420,.0 +I- 660.0 15100.0 -+/1400.0 3.0I +/- "22.0 37.00 +/- 37.00 40.0 +/- 36.0 290.0 +/- 120.0 09/17/03 8260..0 +/- 520.0 25560.0 950.0 0.0I +/- :27.0 8.00 +/ 26.00 165.0 +/- 32.0 190.0 4- 120.0 x +/- y x +I- y I . x +1- y x +1- y x +4- y L IBe-7 420.0,I I K.40 I 1 1131* Cs-134- I Cs-13 I Th-228 26 05/21/03 - 860.0 12400.0 +/- 1200.0 1.0 +/- I19.0 26.0 4+ 33.0 -11.0 +/- 3!5.0 100.0 +/- 170.0 06/18/03 1140.0 4-+ 180.0 10220.0 4.- 510.0 30.0 +/-: 38.0 23.0 +/- 21.0 2.0 +/- 1:3.0 44.0 4/- 68.0 07/16/03 830.0 250.0 9280.0 +/ 670.0 26.0 +/- 31.0 13.0 +/- 19.0 -2.0 +/- 1i1.0 96.0 +/- 87.0

)4+-

08/20/03 1680.0 510.0 8800.0 4. 1100.0 -3.0 +4- <24.0 13.00 +/- 32.00 -20.0 +/- 3:2.0 240.0 4- 130.0 4.+

09/17/03 6780.0 540.0 19800.0 +/- 1000.0 3.0 +/- 23.0 30.00 +/- 29.00 134.0 +/- 313.0 228.0 +/ 98.0

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

[pCVL]

Sampling Station 01 A Date 03/26/03 I

0 20.0 H-3

+/- 910.0 I Be-7

-2.0 +/- 22.0 I

-8.0 K-40 25.0 I Sr-89 (a]

I Sr-90 I l-131P 1.2 +/- 4.6 I

-1.7 Ba-140

+- 3.7 I

0.9 Th-228

+/- 8.9 I

[a]

06/25/03 -400.0 +/- 790.0 -14.0 +/- 24.0 -7.0 34.0 0.5 +/- 2.6 0.9 +1- 1.0 -1.5 +/- 5.4 0.0 +- 4.6 4.7 +/- 8.8 09/24/03 -70.0 +/- 860.0 10.0 +/- 20.0 15.0 +1- 38.0 [a] [a] -2.5 +/- 3.8 -3.3 +/- 3.8 -7.5 +t- 9.0 12/30/03 -80.0 +/- 830.0 1.0 +/- 16.0 -8.0 18.0 [a] [a] 2.8 +/- 5.5 0.3 +/- 3.4 1.5 +t- 5.4

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

53

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

[pC!/L]

Sampling Station 11 ninf. I I

HA I Ra.7 I ic-An I Sr-A 89 I Sr.-9on I .1 31 I Cs-137

.I Ba-140 I Th-228 I b 2.0 [a]

01/15/03 +/- 23.0 -8.0 +/- 36.0 [a] 0.2 +/- 0.4 -2.2 4/- 3.4 0.7 +/- 5.3 0.0 +/- 13.0 02/13/03 b 9.0 4- 23.0 -21.0 +/- 38.0 la] [a] 0.2 +/- 0.3 -1.7 +t- 3.5 0.0 +/- 6.1 5.6 +/- 9.3 03/13/03 3560.0 +/- 970.0 -12.0 +/- 15.0 2.0 +/- 25.0 [a] [a] 0.2 +/- 0.3 0.3 +/- 1.6 -1.1 +/- 3.6 4.2 +1- 5.7 04/15/03 b 7.0 +/- 28.0 -41.0 +/- 39.0 [a] [a] 0.1 +/- 0.2 3.2 +/- 3.2 -0.8 +/- 6.0 1.0 +/; 14.0 05/1503 b 1.0 +/. 17.0 4.0 +/- 26.0 [a] [a) 0.2 +/- 0.5 -1.0 +/- 1.9 1.5 4/- 4.4 3.4 +/-. 7.7 06/1203 1720.0 +/- 870.0 -6.0 '+/- 19.0 -8.0 +/- 22.0 -0.6 +/- 4.0 0.0 +/- 0.8 0.2 +/- 0.4 -2.5 +1- 2.2 25 +4- 4.6 6.0 4+/- 9.0 07/10/03 b .1.0 +/- 16.0 16.0 +/- 23.0 [a] la) 0.4 +/- 0.4 -1.0 +/- 1.5 -26 4/- 3.2 3.2 +/- 5.6 08/13103 b 7.0 +/- 26.0 29.0 +/- 43.0 [a] [a] 0.0 +/- 0.3 1.6 +/- 2.7 -2.7 +/- 4.4 -5.1 +/- 9.4 09/12/03 1390.0 +/- 870.0 -5.0 +/- 16.0 2.0 +/- 18.0 [a) [a] 0.3 /- 0.6 -1.5 +/- 1.7 2.5 +/- 3.4 Z4 +1/ 5.8 10/16/03 b 6.0 +/- 17.0 ' 6.0 +/- 26.0 [a] [al -0.2 +/- 0.2 -1.4 +/ 1.8 -0.6 +/- 4.0 3.2 +1- 7.3 11/17/03 b 12.0 +/- 17.0 9.0 +/- 28.0 (a) (a] 0.1 +/- 0.5 -9.0 4/- 1.9 -0.6 +/- 2.8 3.5 +1- 6.5 12/16103 . 800.0 +/- 460.0 - 2.0 +/- 11.0 15.0 +/- 19.0 la] [a] . -0.1 +/- 0.4 -0.1 +/- 1.1 -3.0 +/- 4.8 7.5 +/- 3.7

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

(b]Tritium analyses on quarterly composite.

54

Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium fpCVLJ Sampling Station 08 Date I H-3 I Sr-89 I Sr-90 I Ba-7 I K-40 I-131- -

Cs-137 l

- Ba-140 I

Th-228

. . _ JI 01/1503 +/- [a] [a] 2.00 +/- 15.00 .14.00 +/- 26.00 0.09 +/- 0.29 -2.20 +/- 2.30 -2.30 +/- 3.10 2.90 +/- 8.20 02/13/03 [b] (a] [a] -25.00 +/- 21.00 22.00 +/- 34.00 0.02 +/- 0.20 0.60 +/- 2.60 -0.60 +/- 4.10 3.70 +/- 14.00 03/13/03 3630.0 +/- 930.0 [a] la] -5.00 +/- 18.00 -3.00 +/- 25.00 -0.01 +/- 0.05 -1.00 +/- 1.60 -1.20 +/- 3.20 7.50 +1/ 6.30 04/15603 lb] [a] [a] .16.00 +/- 18.00 -7.0 +/- 32.0 0.0 +/- 0.4 0.5 +/- 2.7 -1.4 +/ 3.5 3.0 +1- 9.3 0511503 lb] [a] [a] 7.00 +/- 16.00 -2.0 +/- 23.0 -0.1 +/- 0.2 0.1 +/- 1.8 -2.2 +/- 3.5 -2.5 +1- 6.8 06/12/03 2010.0 +/- 930.0 2.1 +/- 5.3 -0.2 +/- 1.1 13.00 +/ 18.00 -13.0 +/- 26.0 0.1 +/- 0.3 1.0 +/- 2.0 2.6 +/- 3.9 -1.8 +1 .-.7.6 07/10103 lb] [a] [a] -4.00 +/- 15.00 -13.0 +/- 21.0 -0.1 +/- 0.0 -0.2 +/- 1.5 -1.1 +/- 3.2 .1.5 4- 6.3 08/13/03 lb] la] [a] 13.00 +/- 17.00 -2.0 +/- 35.0 0.7 +/- 0.7 0.2 +/- 2.5 3.6 +/- 6.0 1.7 +1- 9.6 09/12103 1420.0 +/- 870.0 [a) [a] -5.00 +/- 13.00 -4.0 +/- 21.0 0.0 +/- 0.5 -0.6 +/- 1.4 -1.7 +/- 3.3 -0.2 +1- 5.3 10/16/03 lb] (a] [a) 21.00 +/- 24.00 0.0 +/- 34.0. 0.0 +/- 0.2 0.7 +/- 2.9 0.8 +/- 6.1 .1.0 +/- 11.0 11/17/03 [b] Ia] la] *6.00 +/- 21.00 24.0 +/- 33.0 0.3 +/- 0.5 -0.5 +/- 2.1 -2.2 +1- 4.8 4.3 +/- 7.6 12116/03 940.0 +/- 460.0 la] la] 11.00 +/- 15.00 -9.0 +/- 19.0 0.1 +/- 0.5 -1.6 +/- 1.4 -1.3 +/- 6.7 3.1 +1- 5.4 Sampling Station 09A Date l H3 . I Sr8A9 I 'SRr90 I Be-7 1 K-40 I 1-131' .I Cs-137 I Ba-140 I *---

Th-228 01/15103 [b] [a] [a] 5.00 +/- 23.00 26.00 +/- 35.00 -0.01 +/- 0.24 -0.50 +/- 2.60 4.40 +/- 5.70 4.00 +/- 11.00 -

02/13/03 [b] [a] [a] -7.00 +/- 22.00 2.00 +/- 36.00 -0.09 +/- 0.03 0.50 +4- 2.70 -2.30 +/- 5.60 6.00 +/- 10.00 03/13/03 240.0 +/- 84.0 [a] [a] 2.00 +/- 15.00 10.00 +/- 26.00 0.20i +/- 0.29 0.30 +/- 1.60 -1.50 +/- 2.80 -0.50 +/- 6.60 04/15103 [YI [a] [a] 15.00 +/- 21.00 -2.6 +/- 34.0 0.0 +/-

/ 0.3 -1.4 +/- 2.4 3.1 +/- 5.1 -3.0 +/- 10.0 05/15O3 [b] [a] [a] -1.00 +/- 17.00 14.0 +/- 30.0 0.1 +/- 0.6 -0.9 +/- 1.7 -2.3 +/- 4.3 7.2 +/- 7.4 06/12103 -580.0 +/- 840.0 -9.8 +/- 4.4 0.2 +/- 1.1 7.00 +/- 23.00 2.0 +/- 25.0 0.22 +/- 0.4 1.8 +/- 2.2 3.4 +1- 4.7 1.0 +/-- 8.2 07/10/03 lb] (a] (a] -1.00 +/- 16.00 0.0 +/- 23.0 0.22 +/- 0.3 -0.8 +/- 1.6 0.5 +/- 3.3 -1.7 +-- 6.5 08/13/03 lYb [a] [a] -3.00 +/- 20.00 -15.0 +/- 35.0 0.4 *4+/- 0.5 0.0 +/- 2.6 1.2 +/- 4.4 -2.1 +/- 8.9 09/12/03 -230.0 +/- 810.0 (a] [a] -6.00 +/- 12.00 20.0 4/- 17.0 0.0 i +/- 0.4 -0.4 +/- 1.4 -0.2 +/- 3.0 3.3 +1- 7.3 10/16103 [Yb [a] [a] 3.00 +/- 23.00 -15.0 +/- 35.0 -0.1 +/- 0.2 -0.7 +/- 2.2 2.8 +/- 4.0 3.3 +/- 9.1 11/17/03 [b] [a] la] -2.00 +/- 24.00 27.0 +/- 35.0 0.31 +/- 0.3 -0.8 +/- 2.9 -1.6 +1- 4.7 -6.0 +/- 11.0 12/16/03 -220.0 +/- 820.0 [a] (a]. -9.00 +/- 15.00 8.0 +/- 21.0 0.77 +/- 0.7 -0.8 +/- 1.3 -4.7 +/. 6.1 1.3 +1- 6.4

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

[b] Tritium analyses on quarterly composite.

55

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

Sample Date Sr-89 I Sr-go l . Be-7 I K-40 I Mn-54 I 02/2012003 Station 08 [a] [a] -210.0 +/- 310.0 16700.0 +1- 1000.0 20.0 +/- 31.0 Station 09A [a] [a] 140.0 4- 220.0 11020.0 +/- 800.0 -23.0 4/- 22.0 Station 11 [a] [a] -20.0 +- 210.0 16520.0 +/- 780.0 17.0 +/- 22.0 09/08/2003 Station 08 100.0 +/- 110.0 41.0 +- 86.0 90.0 +4- 190.0 5590.0 +- 570.0 11.0 +- 20.0 Station 09A 100.0 4/- 130.0 31.0 +4- 95.0 30.0 +/- 160.0 10480.0 +- 560.0 -4.0 4+- 13.0 Station 11 100.0 +/- 150.0 30.0 +/- 110.0 10.0 +- 17.0 17510.0 +/- 700.0 -4.0 4+- 17.0 Sample Date Co-58 0Co-60 I Cs-134* 1 Cs- 137-I Th-228

_ _I I

02/20/2003 Station 08 -35.0 +/- 30.0 -3.0 +4- 25.0 2.0 +/- 46.0 -10.0 +4- 30.0 2070.0 +4- 140.0 Station 09A -25.0 +- 23.0 -4.0 +/- 21.0 -15.0 +/- 19.0 36.0 +/- 35.0 774.0 +/- 95.0 Station 11 3.0 +/- 23.0 10.0 +/- 22.0 3.0 +/- 76.0 133.0 +/- 34.0 1672.0 +/- 97.0 09/08/2003 Station 08 -5.0 +4- 17.0 20.0 +/- 19.0 -68.0 +/- 74.0 1.0 +/- 22.0 837.0 +4- 80.0 Station 09A -22.0 +/- 15.0 3.0 +4- 13.0 51.0 +4- 52.0 3.0 +/- 14.0 360.0 +/- 56.0 Station 11 -7.0 +- 19.0 9.0 +/- 16.0 4.0 +/- 16.0 0.0 +/- 17.0 1069.0 +/- 73.0

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

56

Table 3-14 Shoreline Soil Gamma Spectra, and Strontium

[pC!/Kg]

Sample Date I Sr-89 1 Sr-90 1 Be-7 I K-40 L Mn-54 ld 02/20/2003 Station 08 la) [a] 80.0 +- 220.0 2360.0 +/- 520.0 -20.0 +4- 18.0 Sample Date 09/08/2003 Station 08 130.0 +/- 130.0 35.0 +/- 92.0 250.0 +/4 220.0 2280.0 +/- 330.0 -8.0 +/- 15.0 Sample Datel Co-58 I I Co-60 I Cs- 134 I Cs-137* I Th-228 I 02/20/2003 Station 08 11.0 +/- 21.0 7.0 +/- 21.0 -3.0 +/- 24.0 199.0 +/- 46.0 239.0 +/- 91.0 Sample Date 09/08/2003 Station 08 -1.0 +/- 14.0 3.0 +4- 13.0 -18.0 4- 58.0 233.0 +/- 31.0 284.0 4/- 60.0

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

57

Table 3-15 Fish Gamma Spectra

[pCUKg]

Fish [a]

Samnlina Station 08 Date I K-40 l Mn-54 l Fe-59* l Co-58 l Co-60 l Zn Cs-134 l Cs-137*

03/04/03 1710.0 +/- 560.0 -5.0 4- 24.0 62.0 +4- 53.0 0.0 +l 28.0 -3.0 4/- 23.0 -7.0 +- 53.0 9.0 +- 26.0 37.0 +4- 30.0 09/10/03 1900.0 4- 670.0 23.0 4/ 26.0 -20.0 +4- 100.0 -4.0 +t- 28.0 -4.0 +4- 23.0 15.0 +4- 67.0 9.0 +/1 30.0 13.0 +/- 29.0 Fish [a]

Sampling Station 25 Date l K-40 l Mn Fe Co-58 l Co-60 l Zn-65 l Cs-134 l Cs-137*

03/05/03 1540.0 +- 710.0 3.0 +- 25.0 -50.0 +4- 67.0 10.0 +/- 24.0 9.0 +4- 31.0 18.0 4- 69.0 11.0 +/- 30.0 -28.0 4+ 36.0 09/10/03 1430.0 +- 550.0 0.0 +- 20.0 10.0 +4- 100.0 24.0 +/- 27.0 7.0 4- 25.0' -29.0 4- 63.0 -5.0 +1 28.0 5.0 4- 20.0 Catfish [b]

Sampling Station 08 Date l K-40 l Mn-54' Fe-59 l Co-58' l Co-60' Zn-65 l Cs134- Cs-137

  • 03/04/03 1210.0 +4- 450.0 9.0 4- 26.0 -32.0 4- 55.0 -12.0 +/ 25.0 -6.0 +4- 26.0 -24.0 +- 53.0 0.0 +/- 22.0 17.0 +- 24.0 09/10/03 1420.0 4- 560.0 8.0 4- 25.0 42.0 +- 99.0 2.0 +/- 35.0 5.0 +/- 27.0 -21.0 +4- 65.0 9.0 +/- 24.0 -6.0 +4- 28.0 Catfish [b]

Sampling Station 25 Date l K-40 l Mn-54 l Fe-59 l Co-58' l Co-60' Zn-65* l Cs-134 l Cs-137 03/05/03 1730.0 +- 720.0 -7.0 +4- 32.0 -47.0 +4- 62.0 3.0 +/- 27.0 -8.0 +4- 31.0 17.0 +4- 64.0 11.0 +/- 41.0 -1.0 +4- 29.0 09/10/03 970.0 +- 720.0 20.0 +4- 22.0 20.0 41- 120.0 1.0 +/- 40.0 -14.0 +/- 31.0 11.0 +4- 48.0 1.0 +/- 31.0 29.0 +- 29.0

'LLD identified in ODCM

[a] Non-bottom dwelling species of gamefish.

{b} Bottom dwelling species of fish.

58

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2003 and tabulated in Section 3, are discussed below. Except for TLDs, Framatome ANP DE&S Environmental Laboratory analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the Framatome ANP DE&S Environmental Laboratory quality assurance manuals and laboratory procedures. In addition to internal quality control measurements performed by each laboratory, they also participate in an Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the Interlaboratory Comparison Programs are provided in Appendix B.

The predominant radioactivity detected* throughout 2003 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 2003 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 TLDs serve as controls. Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.

The results of the analyses are presented in Table 3-2. Figure 4-1 shows a historical trend of TLD exposure rate measurements. Control and indicator averages indicate a steady relationship. Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location. These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs. The dose trend with the replacement TLDs is lower than that of the previously used TLDs.

59

Figure 4-1: Environmental Radiation - TLDs

' 10.0

'.o r-. 00 o7% 0 - en~f %O r-. co ON 0) r en CO CO C CO O\ O C O C\ C~0 Q C~\ ;1 Q1 0 0 CI 00 C C C C CC C C C CZ r-Cu g

CZ rC CZ g C- g i:

Cu Cu Cu C Cu Cu C CZ Cu CZ CZ I Kj C 0

5

-- Environmental TLDs -A-Sector TLDs - 4-Avg. 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 4.4 mR/standard month with a range of 1.1 to 19.3 mR/standard month. The highest quarterly average reading and highest single quarter average for any single location were obtained at location SSW-19/51. These values were 14.2 mR/standard month and 14.5 mR/standard month, respectively. This location is on site directly across the access road from the Independent Spent Fuel Storage Facility inside the Owner Controlled area. 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 3.4 mR/standard month with a range of 1.0 to 5.6 mR/standard month. The average annual reading for these locations was 3.0 mR/standard month with a range of from 1.6 to 5.4 mR/standard month. The control location showed a quarterly average of 2.9 mR/standard month with a range of 2.5 to 3.4 mR/standard month. Its annual reading was 3.0 mR/standard month. Eight other TLDs, designated C-I thru C-8 were collected quarterly from four locations and showed an average reading of 3.0 mR/standard month with a range of 2.0 to 4.0 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

60

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the 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 CI 9 0.01 ........................... ,,,

0.001 - . I I , . I I I I I I I I I I I I I I I I I I I I I I I I I I I 1986 1988 1990 1992 1994 1996 1998 2000 2002

  • Control Sta Indicator - Average Pre-op .. - Required LLD 61

Figure 4-3 NORTH ANNA AIR PARTICULATE [ Indicator pCUm 3 2003 Gross Beta Radioactivity l'. A ..^ Controll 0.040

_ N N Lu (o r-uco X co 0 0 0 V- N C. e C)

CD 0 0 0 0 0 0 a C 0 0 0 0s _

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. TIhese 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 ParticulateGamnia and Stronitium Analyses 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.

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 62

indicator or control stations.

4.5 Soil Per the sampling frequency defined in the North Anna ODCM, soil samples are collected every three years. Results are normally reported in Table 3-6. The last sampling period for soil was 2001.

4.6 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. Nine of twelve precipitation samples showed positive results in 2003. The average annual gross beta activity was 7.6 pCi/liter with a range from 3.1 to 15.4 pCi/liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes. No positive indications of gamma emitting radioisotopes were observed in the semi-annual composite samples for 2003. These results are comparable to those measured since 1986. 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 2003 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. The tritium activity ranged from 100 to 330 pCi/liter.

4.7 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any plant effect.

Analysis results for cow milk are contained in Table 3-8. All results show 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 2003.

Once each quarter a sample from each of the two collection stations is analyzed for strontium-89 and strontium-90. No positive indications of either Sr-89 or Sr-90 were observed. 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 63

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. TMis 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.

4.8 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, no other gamma emitters were detected. Although not detected in 2002, cesium-137 was detected in six of the twenty-five 2003 samples collected. 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.

4.9 Well Water Ground water was sampled quarterly from the on site well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed for strontium-89 and strontium-90. The results of these analyses are presented in Table 3-10. Consistent with past monitoring, no plant related radioactivity was detected. No gamma emitting isotopes were detected during the pre-operational period.

4.10 River Water A sample of water from the North Anna River was collected monthly, the analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy. The monthly samples were composited quarterly and analyzed for tritium, the third quarter samples were additionally analyzed for strontium-89 and strontium-90. No gamma emitting radioisotopes were detected in any of the 64

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 1868 pCi/liter and a range of 800 to 3560 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 44: Thitium in River Water 0

1000 ....

mr 5 r- 00 OnO-_ r- 00 c0 o-00 00 00 00 00 cad c. 0 0 l

  • Tritium - - Required LU) 4.11 Sitrface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma ray spectrometry and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium, and the 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 2000 pCi/liter with a range of 940 to 3630 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. One control station showed a positive indication of tritium at 240 pCi/liter. During the pre-operational period tritium was measured in several 65

samples with concentrations between 90 and 250 pCi/liter.

4.12 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.

Sediment samples were collected during February and September from each of three locations and were analyzed by gamma spectrometry. The September 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.

Cesium-137 was detected in one indicator sample at 133 pCi/kg dry weight. 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 66

spectroscopy. Cesium-137 was measured in most of the samples with concentrations between 33 and 1210 pCi/kg (dry weight).

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.

4.13 Shoreline Soil Shoreline soil/sediment, unlike bottom sediment, may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. A sample of shoreline sediment was collected in February and September from indicator station 08. The samples were analyzed by gamma ray spectrometry. The September sample was analyzed for strontium-89 and strontium-90. The results are presented in Table 3-14.

Naturally occurring radioisotopes were -detected at concentrations equivalent to normal background activities. The activities of these radioisotopes indicate a 67

steady trend. Cesium-i37 was measured in both samples collected with an average concentration of 216 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.

4.14 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2003 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. These results are the same as previously seen. No activity, except for naturally occurring K-40, was observed in this media in 2003. Only Cs-137 was measured in pre-operational environmental fish samples.

68

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. 04 Air Iodine and 02119/03 Low volume due to sampler malfunction.

Particulate Sta. 14-16, 23, Vegetation March Seasonal Unavailability 26 Sta. 14-16, 23, Vegetation April Seasonal Unavailability 26 Sta.01 Air Iodine and 06/18/03 Low volume due to breaker trip.

Particulate Sta. 01 Air Iodine and 07/16/03 Low volume due to breaker trip Particulate Sta. OSA Air Iodine and 08/20/03 Low volume due to sampler malfunction.

Particulate Sta. 01 Air Iodine and 09/10/03 Low volume due to breaker trip.

Particulate Sta. 01, 02, 03, Air Iodine and 09/24/03 Low volume due to power failure related to hurricane 04, 05, 06, 07, Particulate Isabel.

21,23 Sta. 05 Air Iodine and 10/01/03 Low volume due to power disturbance.

Particulate Sta. 14-16, 23, Vegetation October Seasonal Unavailability 26 Sta. 05A Air Iodine and 10/03103 Low volume due to breaker trip.

Particulate Sta. 14-16, 23, Vegetation November Seasonal Unavailability 26 Sta. 07 Air Iodine and 11/19/03 Low volume due to breaker trip Particulate Sta. 14-16, 23, Vegetation December Seasonal Unavailability 26 Sta. 02 Air Iodine and 12/10/03 Low volume due to blown fuse.

Particulate 69

REFERENCES 70

e! ;'.;Y 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.

71

APPENDICES 72

APPENDIX A: LAND USE CENSUS Year 2003 73

LAND USE CENSUS North Anna Power Station North Anna County, Virginia JanuaryI to December31, 2003 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Animal Milldng Milking Boundary (> 50 mn) Cow

  • Goat
  • N 0.9 1.5 1.8 2.2 NNE 0.9 0.9 1.6 1.5 NE 0.8 0.9 0.9 1.4 ENE 0.8 2.1 2.1 2.5 E 0.8 1.3 1.3 3.5 ESE 0.9 1.7 1.7 None SE 0.9 1.4 1.4 1.4 SSE 0.9 1.0 1.3 2.8 S 0.9 1.1 1.2 None SSW 1.0 1.2 None 2.0 SW 1.1 3.1 None None .

WSW 1.1 1.7 2.0 1.7 W 1.1 1.5 1.9 None WNW 1.0 1.1 2.5 4.1 NW' 1.0 1.0 1.4 None NNNNW 0.9 1.0 2.2 2.0

  • No milking cow or milking goat within 5.0 miles of North Anna Power Station 2002 to 2003 Land Use Census Changes 2002 2003 Nearest Direction Distance Distance Site Boundary No Changes Resident No Changes Garden ESE 3.5 mi 1.7 mi SSW 1.6 mi None WNW

_ 2.8 mi 2.5 mi Meat Animal No Changes Milking Cow No Changes Milking Goat No Changes 74

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2003 75

INTRODUCTION This appendix covers the 'Intercomparison Program of the Framatome ANP Environmental Laboratory. 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), low-level (LL) iodine-131, and gross beta analyses during the 1st and 3rd quarters,

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

> water tritium analysis during the 2nd and 4th quarters,

> air filter for gamma (9 nuclides) analyses during the 2nd and 4th quarters,

> air filter for gross beta analysis during the 1st, 3rd and 4th quarters,

> filter for Sr-90 analysis during the 2nd and 4th quarters.

In addition to the Analytics Intercomparison Program, Framatome also participates in other intercomparison programs which include radionuclides and media similar to those required by the Millstone program. These programs are the National Institute of Standards and Technology (NIS'1 Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (Vi 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 Framatome's internal bias acceptance criteria as defined below:

'> within 25% of the known for gross beta in water,

> within 25% of the known for samples containing both Sr-89 and Sr-90,

> within 15% of the known value for other radionuclides, or

> within two sigma of the known value.

Framatome investigates any sample analysis result that does not pass these criteria.

Analytics Intercomparison Program results are included on the pages that follow for the first quarter through the fourth quarter of 2003. A total of 102 analysis results were obtained with 102 passing acceptance criteria,-a 100% success rate.

76

I FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION

- ;!E f z', ;, . iRatio;-,,,,,;,,,.

Reported. Knownr Framatome/

Values Values Analytics I Evaluation E3597-162 1stV03 Water Gross Alpha pCi/L 55 61 0.90 Agreement E3597-162 1st/03 Water Gross Beta pCiVL 146 186 0.78 Agreement E3598-162 1stV03 Water 1-131 pCVL 68 70 0.97 Agreement E3598-162 1st/03 Water I-1 31 LL pCi/L 68 70 0.97 Agreement E3598-162 1st/03 Water Ce-141 pCi/L 163 168 0.97 Agreement E3598-162 1st/03 Water Cr-51 pCi/L 243 238 1.02 Agreement E3598-162 1st/03 Water Cs-1 34 pCi/L 83 88 0.94 Agreement E3598-162 1st/03 Water Cs-137 pCi/L 188 195 0.96 Agreement E3598-163 1st03 Water Co-58 pCi/L 44 42 1.05 Agreement E3598-162 1st03 Water Mn-54 pCVL 61 63 0.97 Agreement E3598-162 1st/03 Water Fe-59 48 46 1.04 Agreement

.pCV'L E3598-162 1st/03 Water Zn-65 pCi/L 88 90 0.98 Agreement E3598-162 1st/03 Water Co-60 IpCI/L 156 157 0.99 Agreement E3599-162 I st/03 Filter Gross Alpha pCi 52 49 1.06 Agreement E3599-162 1st/03 Filter Gross Beta pCi 157 148 1.06 Agreement E3600-162 1st/03 Milk 1-131 pCi/L 73 74 0.99 Agreement E3600-162 1sV03 Milk I-131 LL pCi/L 73 74 0.99 Agreement E3600-162 1st/03 Milk Ce-141 - pCi/L 170 173 0.98 Agreement E3600-162 1st/03 Milk Cr-51 pCi/L 244 246 0.99 Agreement E3600-162 1st/03 Milk Cs-134, pCi/L 86 90 0.96 Agreement E3600-162 1st/03 Milk Cs-1 37 pCi/L 196 200 0.98 Agreement E3600-163 1st/04 Milk Co-58 pCi/L 44 47 0.94 Agreement E3600-162 1st/03 Milk Mn-54 pCi/L 61 64 0.95 Agreement E3600-162 1st/03 Milk Fe-59 pCi/L 47 47 1.00 Agreement E3600-162 1st/03 Milk Zn-65 I pCi/L 96 93 1.03 Agreement E3600-162 1st/03 Milk Co-60 pCi/L 162 162 1.00 Agreement E3601 -162 1st/03 Milk Sr-89 pCi/L 121 133 0.91 Agreement E3601-162 1st/03 Milk Sr-90 pCi/L 13 12 1.08 Agreement E3608-162 1st/03 Water Sr-89  ; pCi/L 104 114 0.91 Agreement E3608-162 1st/03 Water Sr-90 pCi/L 11 10 1.10 Agreement 77

I FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION

.;
;.,.Ratio Sample ' uarter - Same - Reported K: Framatome ' -

--Number Year' Media ,' Nucid e' ,,'Units Values': Values .:1Evaluatin' Analytics E3704-162 2nd/03 Water H-3 pCi/L 10643 11953 0.89 Agreement E3705-162 2nd103 Filter Gross Alpha pCi/L 20 21 0.95 Agreement E3705-162 2nd/03 Filter Gross Beta pCVL 116 115 1.01 Agreement E3706-162 2nd/03 Filter Ce-141 pCi/Filter 149 154 0.97 Agreement E3706-162 2nd/03 Filter Cr-51 pCi/Filter 134 130 1.03 Agreement E3706-162 2nd/03 Filter Cs-134 pCi/Filter 54 56 0.96 Agreement E3706-162 2nd/03 Filter Cs-1 37 pCi/Filter 135 125. 1.08 Agreement E3706-162 2nd/03 Filter Co-58 pCi/Filter 53 50 1.06 Agreement E3706-162 2nd/03 Filter Mn-54 pCi/Filter 110 101 1.09 Agreement E3706-162 2nd/03 Filter Fe-59 pCi/Filter 60 54 1.11 Agreement E3706-162 2nd/03 Filter Zn-65 pCU/Filter 110 99 1.11 Agreement E3706-162 2nd/03 Filter Co-60 pCi/Filter 71 72 0.99 Agreement E3707-162 2nd/03 Filter Sr-89 pCi/Filter 78 87 0.90 Agreement E3707-162 2nd/03 Filter Sr-90 pCi/Filter 24 24 1.00 Agreement E3708-162 2nd/03 Milk 1-131 pCi/L 109 103 1.06 Agreement E3708-162 2nd/03 Milk 1-131LL pCi/L 104 103 1.01 Agreement E3708-162 2nd/03 Milk Ce-141 pCi/L 283 283 1.00 Agreement E3708-162 2nd/03 Milk Cr-51 pCi/L 239 239 1.00 Agreement E3708-162 2nd/03 Milk Cs-1 34 pCi/L 98 103 0.95 Agreement E3708-162 2nd/03 Milk Cs-1 37 pCU/L 232 230 1.01 Agreement E3708-162 2nd/03 Milk Co-58 pCU/L 92 93 0.99 Agreement E3708-162 2nd/03 Milk Mn-54 pCi/L 186 186 1.00 Agreement E3708-162 2nd/03 Milk Fe-59 pCUL 100 99 1.01 Agreement E3708-162 2nd/03 Milk Zn-65 pCi/L 181 181 1.00 Agreement E3708-162 2nd/03 Milk Co-60 pCUL 134 132 1.02 Agreement 78

FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION

'Sa'mple.' ': S Sampl p' "'at. Reported f . -'

Number' '

-Year 'Media' Nuclide Units Values Values ^ 'Analtics -',.;Evaluation E3866-162 3rd/03 Water Gross Alpha pCi/L 37 36 1.03 Agreement E3866-162 3rdl03 Water Gross Beta pCVL 264 246 1.07 Agreement E3867-162 3rd/03 Water 1-131 pCUL 69 76 0.91 Agreement E3867-162 3rd/03 Water 1-131LL pCiUL 78 76 1.03 Agreement E3867-162 3rd/03 Water Ce-141 pCiUL 78 81 0.96 Agreement E3867-162 3rd/03 Water Cr-51 pCiUL 198 221 0.90 Agreement E3867-162 3rd/03 Water Cs-1 34 pCVL 108 113. 0.96 Agreement E3867-162 3rd/03 Water Cs-137 pCiUL 85 84 1.01 Agreement E3867-162 3rd/03 Water Co-58 pCUL 92 94 0.98 Agreement E3867-162 3rdc03 Water Mn-54 pCi/L 93 88 1.06 Agreement E3867-162 3rd/03 Water Fe-59 pCi/L 74 75 0.99 Agreement E3867-162 3rd/03 Water Zn-65 pCi/L 170 166 1.02 Agreement E3867-162 3rd/03 Water Co-60 pCiUL 118 117 1.01 Agreement

.E3868-162 3rd/03 Filter Gross Alpha pCi 30 28 1.07 Agreement E3868-162 3rd/03 Filter Gross Beta pCi 197 189 1.04 Agreement E3869-162 3rd/03 Milk 1-131 pCi/L 66 74 0.89 Agreement E3869-162 3rd/03 Milk 1-131 LL pCUL 74 74 1.00 Agreement E3869-162 3rd/03 Milk Ce-141 pCi/L 90 86 1.05 Agreement E3869-162 3rd/03 Milk Cr-51 pCiUL 228 233 0.98 Agreement E3869-162 3rd/03 Milk Cs-134 pCiUL 123 119 1.03 Agreement E3869-162 3rd/03 Milk Cs-1 37 pCUL 94 88 1.07 Agreement E3869-162 3rdc03 Milk Co-58 pCUL 99 99 1.00 Agreement E3869-162 3rd/03 Milk Mn-54 pCVL 101 93 1.09 Agreement E3869-162 3rd/03 Milk Fe-59 pCUL 84 79 1.06 Agreement E3869-162 3rd/03 Milk Zn-65 pCUL 178 176 1.01 Agreement E3869-162 3rd/03 Milk Co-60 pCi/L 129 123 1.05 Agreement E3870-162 3rd103 Milk Sr-89 pCi/L 80 100 0.80 Agreement E3870-162 3rd/03 Milk Sr-90 pCi/L 11 14 0.79 Agreement 79

FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION

  • R atio l.,, .,. .... . .- :~

Sample -,Quarter/ Sample 'F'^matome! Relerted.;', w'

Number Year Media Nuclide Units Valus - Values' 'Analytics ,,Evaluation E3937-162 4th/03 Water H-3 pCUL 2307 2290 1.01 Agreement E3938-162 4th/03 Water Sr-89 pCUL 99 100 0.99 Agreement E3938-162 4th/03 Water Sr-90 pCVL 11 10 1.10 Agreement E3939-162 4th/03 'Filter Gross Beta pCi 50 43 1.16 Agreement E3940-162 4th/03 Filter Ce-141 pCi 110 100 1.10 Agreement E3940-162 4th/03 Filter Cr-51 pCi 171 153 1.12 Agreement E3940-162 4th/03 Filter Cs-134 pCi 75 74 1.01 Agreement E3940-162 4th/03 Filter Cs-1 37 pCi 75 71 1.06 Agreement E3940-162 4th/03 Filter Co-58 pCi 64 61 1.05 Agreement E3940-162 4th/03 Filter Mn-54 pCi 103 95 1.08 Agreement E3940-162 4th/03 Filter Fe-59 pCi 64 56 1.14 Agreement E3940-162 4th/03 Filter Zn-65 pCi 117 108 1.08 Agreement

_3940-162 4th/03 Filter Co-60 pCi 82 85 0.96 Agreement E3941 -162 4th/03 Filter Sr-90 pCi 11 11 1.00 Agreement E3942-162 4th/03 Milk 1-131 pCi/L 84 90 0.93 Agreement E3942-162 4th/03 Milk .1-131LL pCUL 91 90 1.01 Agreement E3942-162 4th/03 Milk Ce-1 41 pCiUL 191 202 0.95 Agreement E3942-162 4th/03 Milk Cr-51 pCi/L 275 280 0.98 Agreement E3942-162 4th/03 Milk Cs-i 34 pCVL 135 135 1.00 Agreement E3942-162 4th/03 Milk Cs-137 pCi/L 126 129 0.98 Agreement E3942-162 4th/03 Milk Co-58 pCi/L 107 ili 0.96 Agreement E3942-162 4th/03 Milk Mn-54 pCUL 173 173 1.00 Agreement E3942-162 4th/03 Milk Fe-59 pCi/L 106 102 1.04 Agreement E3942-162 4th/03 Milk Zn-65 pCi/L 203 197 1.03 Agreement E3942-162 4th/03 Milk Co-60 pCi/L 148 155 0.95 Agreement 80

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