ML021340726

ISFSI - Annual Radiological Environmental Operating Report for January Through December 2001

ML021340726
Person / Time
Site:	North Anna
Issue date:	04/25/2002
From:	Heacock D Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, -RFPFR, 02-288
Download: ML021340726 (128)

Text

{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 April 25, 2002 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No. NAPS/MPW Docket Nos. License Nos. 02-288 50-338 50-339 72-16 NPF-4 NPF-7 SNM-2507 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS I AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT North Anna Units 1 and 2 Technical Specifications 6.9.1.8 and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2.b, require the submittal of an Annual Radiological Environmental Operating Report. Accordingly, enclosed is the Radiological Environmental Operating Report for the reporting period of JanLiary 1, 2001 through December 31, 2001. If you have any questions or require additional information, please contact us. Very truly yours, D. A. Heacock Site Vice President Enclosure Commitments made by this letter: None

cc: U. S. Nuclear Regulatory Commission Region iI Sam Nunn 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. J. Morgan NRC Senior Resident Inspector North Anna Power Station

~0 Do mi n ions T North Anna Power Station 2001 Annual Radiological Environmental Operating Report

DOMINION VIRGINIA POWER NORTH ANNA POWER STA TION Radiological Environmental Monitoring Program January 1, 2001 to December 31, 2001 ANNUAL REPORT Prepared by DOMINION VIRGINIA POWER and TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 1

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2001 to December 31, 2001 Prepared by: Reviewed by Approved by: James B. Breeden Supervisor Radiological Analysis and Material Control Erich W. Dreyer Supervisor Health Physics Technical Services en H. Stafford Manager Radiological Protection 2

Table of Contents Section Title Page Preface.............. 6 Executive Summary.............. 7 I. Introduction .10 II. Sampling and Analysis Program.13 III. Program Exceptions.30 IV. Summary and Discussion of 2001 Analytical Results.32 A. Airborne Exposure Pathway 33

1.

Air Iodine/Air Particulates.33

2.

Precipitation.35

3.

Soil. 35 B. Waterbome Exposure Pathway 36

1.

Ground/Well Water.36

2.

River Water.36

3.

Surface Water.36 C. Aquatic Exposure Pathway 37

1.

Sediment/Silt .37

2.

Shoreline Soil.37 D. Ingestion Exposure Pathway 42

1.

Milk.42

2.

Fish.42

3.

Food/Vegetation.42 E. Direct Radiation Exposure Pathway .43

1.

TLD Dosimeters.43 V. Conclusion.45 3

Table of Contents (Continued) Section Title Page VI. References.......................................... 49 VII. Appendices.......................................... 51 Appendix A - Radiological Environmental Monitoring......................................... 52 Program Annual Summary Tables - 2001 Appendix B - Data Tables.......................................... 60 Appendix C - Land Use Census -2001.......................................... 83 Appendix D - Synopsis of Analytical Procedures.......................................... 87 Appendix E - Interlaboratory Comparison Program.......................................... 99 List of Trending Graphs

1.

Gross Beta in Air Particulates.......................................... 34

2.

Tritium in River Water.......................................... 34

3.

Tritium in Surface Water.......................................... 39

4.

Cobalt-58 in Sediment Silt.......................................... 39

5.

Cobalt-60 in Sediment Silt.......................................... 40

6.

Cesium-134 in Sediment Silt.......................................... 40

7.

Cesium-137 in Sediment Silt.......................................... 41

8.

Cesium-134 in Fish.......................................... 41

9.

Cesium-137 in Fish.......................................... 44

10.

Environmental Radiation-TLDs.......................................... 44 4

Table of Contents (Continued) List of Tables Section Page

1.

Radiological Sampling Station Distance and Direction from Unit 1............................................................ 15

2.

North Anna Power Station Sample Analysis Program........................................... 26

3.

REMP Exceptions for Scheduled Sampling and Analysis during 2001................. 30 Appendix B Tables B-1 Iodine-131 Concentrations in Filtered Air............................................................ 61 B-2 Concentrations of Gross Beta in Air Particulates............................................................ 63 B-3 Gamma Emitter and Strontium Concentrations in Air Particulates.................................... 67 B-4 Gross Beta, Tritium and Gammn a Emitter Concentrations in Precipitation........................ 70 B-5 Concentrations of Gamma Emitter and Strontium in Soil.................................................. 71 B-6 Gamma Emitter, Strontium and Tritium Concentrations in Ground/Well Water............... 72 B-7 Gamma Emitter, Strontium, Tritium, and Iodine Concentrations in River Water.............. 72 B-8 Gamma Emitter, Strontium and Tritium Concentrations in Surface Water........................ 73 B-9 Gamma Emitter and Strontium Concentrations in Sediment Silt....................................... 74 B-10 Gamma Emitter and Strontium Concentrations in Shoreline Soil.75 B-1 Gamma Emitter and Strontium Concentrations in Milk.76 B-12 Gamma Emitter Concentrations in Fish.78 B-13 Gamma Emitter Concentrations in Food/Vegetation.79 B-14 Direct Radiation Measurements - Quarterly & Annual TLD Results.80 B-15 Direct Radiation Measurements - Sector Quarterly TLD Results.81 5

Preface This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 6.9.1.8 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2b. 6

EXECUTIVE

SUMMARY

This document is a detailed report on the 2001 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2001 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 ensure 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 is protected. The program also detects any unexpected environmental processes which could allow radiation accumulations in the environment or food pathways chains. Radiation and radioactivity in the environment is constantly monitored within a 25 mile radius of the station. Dominion Virginia Power (DVP) also collects samples within the area. A number of sampling locations for each medium were 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 Nuclear 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 thus be compared to the environment surrounding the nuclear power station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the plant. Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration. Prior to station operations, 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, other causes such as the Chemobyl accident, or natural variation. Teledyne Brown Engineering Environmental Services provides sample analyses for various radioisotopes as appropriate for each sample media. Participation in an interlaboratory comparison program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLD). This ensures that analyses are as accurate as possible. Samples with extreme low levels of radiation which cannot be detected are therefore reported as being below the LLD. The NRC also mandates a "reporting level." Licensed nuclear facilities must report any releases equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to in percent of reporting level. Analytical results are divided into five categories based on exposure pathways: Airborne, waterbome, aquatic, ingestion, and direct radiation. Each of these pathways is described below: 7

• The airborne exposure pathway includes airborne iodine, airborne particulate, precipitation, and soil samples. The overall 2001 airborne results were very similar to previous years and to preoperational levels. No increase was noted and there was no detection of fission products or other man-made isotopes in the airborne particulate media during 2001.
• The waterborne exposure pathway includes ground/well water, river water, and surface water samples. No man-made isotopes were detected in Lake Anna surface water except for tritium. The average tritium activity in surface water for 2001 was 3825 pCi/liter which was 19.13% of the reporting level for a water sample. The 2000 tritium level was 2850 pCi/liter. The preoperational level was 150 pCi/liter and has risen since 1978, though it has remained relatively consistent since 1986. No other gamma emitters were detected.
• River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3450 pCi/liter. The average tritium level in 2000 was 3025 pCi/liter. Naturally occurring thorium-228 was measured in one out of twelve samples at an average concentration of 5.73 pCi/liter. No other gamma emitters were detected.
• The aquatic exposure pathway includes sediment/silt and shoreline samples. North Anna sediment contained some cesium-137. During the preoperational period, cesium-137 was detected. Sediment contamination, however, does not provide a direct dose pathway to man. In shoreline soil, which may provide a direct dose pathway, cesium-137 was measured in both of the two samples at 177 pCi/kg (dry).

The ingestion exposure pathway includes milk, fish, and food/vegetation samples. Iodine-131 was not detected in any 2001 milk samples. Although cesium-137 has been detected in the past, it was not detected in 2001 milk samples. Strontium-90 was detected at levels lower than 1999, and preoperational years. Both strontium-90 and cesium-137 are attributable to atmospheric nuclear weapons testing in the past. Naturally occurring potasium-40 was detected at normal environmental levels. Fish samples during 2001 contained cesium-137 at a slightly lower activity than preoperational levels. Steam generator repairs and better liquid waste processing have reduced these activity levels from previous years. Vegetation samples were statistically similar to both control and preoperational levels.

• The direct radiation exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). The TLD results have remained essentially the same since the preoperational period in 1977 but have shown a slight decline in 2001 reflecting a change in the TLD design.

During 2001, as in previous years, operation of the North Anna Nuclear Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environment affects or health hazards. The maximum total body dose calculated for a hypothetical individual at the North Anna Power Station site boundary due to liquid and gaseous effluents released from the site during 2001 would be approximately 0.32 millirem. For reference, this dose may be 8

compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes to 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 the North Anna Nuclear Power Station. 9

I. INTRODUCTION 10

DOMINION VIRGINIA POWER COMPANY NORTHANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL OPERA TING PROGRAM I. INTRODUCTION The operational radiological environmental monitoring program conducted for 2001 for the North Anna Power Station is provided in this report. The result of measurement and analyses of data obtained from samples collected from January 1, 2001 through December 31, 2001 are summarized. A. 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. B. 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. Inplant 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). C. Dominion Virginia Power Company is responsible for collecting the various indicator and control environmental samples. Teledyne Brown Engineering Environmental Services is responsible for sample analysis and submitting report of radioanalysis. The results are used to determine if changes in radioactivity levels could be attributed to station operations. Measured values are compared with control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation. D. 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. 11

These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable". E. This report documents the results of the Radiological Environmental Monitoring Program for 2001 and satisfies the following objectives of the program:

1. Provides 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 members of the public resulting from the station operation.

2. Supplements the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.

3. Identifies radioactivity changes in the environment.

4. Verifies that the plant operations have no detrimental effect on the health and safety of the public.

12

II. SAMPLING AND ANALYSIS PROGRAM 13

II. SAMPLING AND ANAL YSIS PROGRAM A. Sampling Program

1. Table 1 summarizes the sampling program for environmental monitoring stations for North Anna Power Station during 2001. The relative location of these stations is shown.

2.

For routine TLD measurements, two dosimeters made of CaF and LiF are deployed at each sampling location. Several TLDs are co-located with NRC and Commonwealth of Virginia direct radiation recording devices.

3.

In addition to the Radiological Environmental Monitoring Program required by North Anna Technical Specifications, samples are split if requested by the Commonwealth of Virginia. Routine splitting of Dominion Virginia Power Company samples with the Commonwealth of Virginia has been discontinued. All samples listed in Table 1 are shipped to Teledyne Brown Engineering Environmental Services located in Knoxville, TN.

4. All samples listed in Table 1 are taken at indicator locations except those labeled "control".

14

Table 1 (Page 1 of 4) NORTH ANNA POWER STATION - 2001 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental Thermoluminescent Dosimetry (TLD) NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads Route 752 01 02 03 0.20 NE 5.30 SSW 7.10 WSW 04 05 Sturgeon's Creek Marina 05A Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA 06 07 21 22 23 24 Bearing Cooling Tower N-1/33 5.10 WNW 4.20 NNE 3.20 N 4.70 ESE 7.30 SSE 1.00 WNW 1.00 WSW 0.93 SSE 22.00 NW 0.06 N 420 Quarterly & Annually 2250 Quarterly & Annually 2430 Quarterly & Annually 2870 Quarterly & Annually 200 Quarterly & Annually 110 Quarterly & Annually 1150 Quarterly & Annually 1670 Quarterly & Annually 3010 Quarterly & Annually 2420 Quarterly & Annually 1580 Quarterly & Annually 3250 Quarterly & Annually 100 Quarterly Sturgeon's Creek Marina N-2/34 3.20 N 110 Quarterly Parking Lot "C" (on-site) Good Hope Church Parking Lot "B" Lake Anna Marina Weather Tower Fence Route 689 Near Training Facility "Morning Glory Hill" Island Dike Route 622 DVP Biology Lab NNE-3/35 0.24 NNE NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-11/43 ESE-12/44 SE-13/45 4.96 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.75 NNE NE NE ENE ENE E E ESE ESE SE 320 Quarterly 250 420 340 740 650 910 930 1030 1150 1380 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 15 Control

Table 1 (Page 2 of 4) NORTH ANNA POWER STATION - 2001 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Mles Direction Degrees Frequency Remarks Environmental Route 701 Thermoluminescent (Dam Entrance) Dosimetry (TLD) "Aspen Hills" Elk Creek NAPS Access Rd. Elk Creek Church NAPS Access Rd. Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary) South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate-Construction Side Laydown Area SE-14/46 SSE-15/47 SSE-16/48 S-17/49 S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23155 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 Lake Anna Campground NW-30/62

1. 1/#2 Intake NNW-31/63 Route 208 NNW-32/64 Bumpass Post Office C-1/2 Orange, VA C-3/4 Mineral, VA C-5/6 Louisa, VA C-7/8 Airborne Particulate NAPS Sewage 01 and Radioiodine Treatment Plant Fredericks Hall 02 Mineral, VA 03 Wares Crossroads 04 Route 752 05 Sturgeon's Creek Marina 05A Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA 06 07 21 22 23 24 5.88 SE 0.93 SSE 2.33 SSE 0.47 S

1.55 S 0.42 SSW 5.30 SSW 0.60 SW 4.36 SW 0.38 WSW 1.00 WSW 0.32 W 1.55 W 1.00 WNW 1.40 WNW 0.45 NW 2.54 NW 0.07 NNW 3.43 NNW 7.30 SSE 22.00 NW 7.10 WSW 11.54 WSW 0.20 NE 5.30 SSW 7.10 WSW 5.10 WNW 4.20 NNE 3.20 N 4.70 ESE 7.30 SSE 1.00 WNW 1.00 WSW 0.93 SSE 22.00 NW 1370 Quarterly 1580 Quarterly 1650 Quarterly 1730 Quarterly 1780 Quarterly 1970 Quarterly 2050 Quarterly 2180 Quarterly 2320 Quarterly 2370 Quarterly 2420 Quarterly 2790 Quarterly 2740 Quarterly 3010 Quarterly 3030 Quarterly 3210 Quarterly 3190 Quarterly 3490 Quarterly 3440 Quarterly 1670 Quarterly 3250 Quarterly 2430 Quarterly 2570 Quarterly 420 Weekly 2050 Weekly 2430 Weekly 2870 Weekly 200 Weekly 110 Weekly 1150 Weekly 1670 Weekly 3010 Weekly 2420 Weekly 1580 Weekly 3250 Weekly 16 Control Control Control Control Control

Table 1 (Page 3 of 4) NORTH ANNA POWER STATION - 2001 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Surface Water Waste Heat Treatment Facility (Second Cooling Lagoon)

• Lake Anna (upstream)

(Route 208 Bridge)

• Lake Anna (upstream)

(Route 669 Bridge) 08 09 09A 1.10 SSE 2.20 NW 12.90 WNW 1480 Monthly 3200 Monthly 2950 Monthly River Water Ground Water (Well Water) Precipitation North Anna River (downstream) Biology Lab Biology Lab 11 5.80 SE 0.75 0IA 0IA SE 0.75 SE 1280 Monthly 1380 Quarterly 138° Monthly Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon) Lake Anna (upstream) (Route 669 Bridge) North Anna River (Downstream) 08 09A 11 1.10 SSE 12.90 WNW 5.80 SSE 1480 Semi-Annually 3200 Semi-Annually Control 1280 Semi-Annually Waste Heat Treatment Facility (Second Cooling Lagoon) 08** 1.10 SSE 1480 Semi-Annually

• 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.

17 Control Control Shoreline Soil

Table 1 (Page 4 of 4) NORTH ANNA POWER STATION - 2001 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary) "Aspen Hills" Orange, VA Holladay Dairy (R.C. Goodwin) Terrell's Dairy (Fredericks Hall) ol 02 03 04 05 05A 06 07 21 22 23 24 12 1 3 0.20 NE 5.30 7.10 5.10 4.20 3.20 4.70 7.30 1.00 1.00 SSW WSW WNW NNE N ESE SSE WNW WSW 0.93 SSE 22.00 NW 8.30 NW 5.60 SSW 420 Once/3 years 2050 2430 2870 200 110 1150 1670 3010 2420 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years 1580 Once/3 years 3250 Once/3 years 3100 Monthly 2050 Monthly Waste Heat Treatment Facility (Second Cooling Lagoon) Lake Orange 08 25 1.10 SSE 16.50 NW 1480 Semi-Annually 3120 Semi-Annually Control Food Products (Broadleaf or at harve Vegetation) Bel Aire Plantation

• Route 614 14 15 1.20 NE 1.37 SE 430 Monthly if available 1330 Monthly if available or at harvest Route 629/522 16 12.60 NW 3140 Monthly if available or at harvest (Control)

End of Route 685 21** 1.00 WNW 301° Monthly if available or at harvest 0.93 SSE 1.15 S 1580 Monthly if available or at harvest 1720 Monthly if available or at harvest

• Food Products station 14 was moved from Route 713 to Bel Aire Plantation during 4th Quarter of2001.
  • Food Products station 26 replaced 21 during 4th Quarter of 2001.

18 Soil Milk Fish Control Aspen Hills Historic Lane 23 26**

Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Map Environmental Station Designation Identification Designation Identification 1 (a) 01,NE-5/37 1A O1A,SE-13/45 2 (a) 02,SSW-20/52 3 (a) 03,C-5/6 4 (a) 04 5 (a) 05 5A (a) 05A,N-2/34 6 (a) 06,ESE-12/44 7 (a) 07,C-1&2 8 08-Water, Fish Sediment Shoreline Soil (d) 9 09 (d) 9A 09A-Water sample, Sediment (d) 11 1 1-River Water, Sediment 12 12-Milk 13 13-Milk 14 14-Vegetation,NE-6/38 15 Vegetation 16 Vegetation 21 (a) 21,WNW-27/59 22 (a) 22,WSW-24/56 23 (a) 23,SSE-15/47 24 (a,b) 24,C-3&4 25 (c) 25-Fish 26 (e) 26-Vegetation 30/62 NW-30/62 (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) Food Products station 26 replaced station 21 during 4th Quarter of 2001. 19 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 10/42

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B. Analysis Program

1.

Table 2 summarizes the analysis program conducted by Teledyne Brown Engineering Environmental Services for North Anna Power Station during 2001. This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are measurable and identifiable, together with the nuclides listed in Table 2, shall also be identified and reported. 25

Table 2 (Page 1 of 4) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Dosimetry (TLD) (84 Routine Station TLDs) 12 Station TLDs Quarterly Annually Gamma Dose Gamma Dose 2mR +/- 2mR 2mR +/- 2mR mR/std. Month mR/std. Month Airborne Radioiodine Airborne Particulate Surface Water Quarterly (a) 2nd Quarter Composite Monthly Quarterly (a) 2nd Quarter Composite Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 I-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3) Sr-89 Sr-90 0.05 0.06 (c) (c) 1(b) 15 30 15 15 30 30 15 15 18 60 15 2000 (c) (c) pCi/m3 pCi/m3 pCi/L pCi/L pCi/L pCi/L

• LLDs indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering Environmental Services may be lower than those listed.

(a) Quarterly Composites of each location's samples are used for the required analysis. (b) LLD for non-drinking water is 10 pCi/liter. (c) There are no required LLDs for strontium-89/90. LLDs are those achieved by Teledyne Brown Engineering Enviromnental Services. 26 Weekly Weekly I-131 Gross Beta 0.07 0.01 pCi/m3 pCi/m3

Table 2 (Page 2 of 4) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS River Water Ground Water (Well Water) Monthly Quarterly (a) 2nd Quarter Composite Quarterly Quarterly 2nd Quarter 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58/Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3) Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58/Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3) Sr-89 Sr-90 Aquatic Sediment Semi-Annually Annually Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90

• LLDs indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering Environmental Services may be lower than those listed.

(a) Quarterly Composites of each location's samples are used for the required analysis. (b) LLD for non-drinking water is 10 pCi/liter. (c) There are no required LLDs for strontium-89/90. LLDs are those achieved by Teledyne Brown Engineering Environmental Services. 27 I (b) 15 30 15 30 30 15 15 18 60 15 2000 (c) (c) 15 30 15 30 30 15 1 (b) 15 18 60 15 2000 (c) (c) pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 150 180 (c) (c) pCi/kg (dry) pCi/kg (dry)

Table 2 (Page 3 of 4) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Monthly Semi-Annual Composite Semi-Annual Annually Once per 3 yrs. Monthly Monthly Quarterly Gross Beta Gamma Isotopic Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Semi-Annual Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 pCi/kg (wet) 130 260 130 130 260 130 150

• LLDs indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering Environmental Services may be lower than those listed.

(a) Quarterly Composites of each location's samples are used for the required analysis. (b) LLD for non-drinking water is 10 pCi/liter. (c) There are no required LLDs for strontium-89/90. LLDs are those achieved by Teledyne Brown Engineering Environmental Precipitation Shoreline Soil 10 10 pCi/L pCi/L Soil Milk pCi/kg (dry) 150 180 (a) (a) pCi/kg (dry) 150 180 (a) (a) Fish 1 15 18 60 15 (a) (a) pCi/L pCi/L pCi/L 28 Services.

Table 2 (Page 4 of 4) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY ANALYSIS LLD* REPORT UNITS Food Products (Broadleaf Vegetation) Monthly if available or at harvest Gamma Isotopic Cs-134 Cs-137 1-131 29 60 80 60 pCi/kg (wet) pCi/kg (wet)

III. PROGRAM EXCEPTIONS 30

REMP Exceptions for Scheduled Sampling And Analysis During 2001 - North Anna Location Description Date of Sample All Stations All Stations All Stations NNE-36, NW-62 Sta 15, 21,23 Sta 15 Qtr Sta 06, ESE-12, ESE-44 Sta 14 Sta 16 Sta 15 All Stations All Station Sta 14, Sta 21, Sta 26 All Stations Vegetation Vegetation Vegetation TLD Vegetation Vegetation TLD 01/17/01 02/21/01 03/21/01 04/05/01 04/19/01 04/19/01 07/12/01 Vegetation 07/19/01 Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation 07/19/01 08/27/01 10/17/01 11/21/01 11/01/01 12/01/01 Reason(s) for Loss/Exception Seasonal unavailability. Seasonal unavailability. Seasonal unavailability. Lost in service. Due to small sample size, the Cs-134 LLD was missed. Due to small sample size, the Cs-137 LLD was missed. Lost in service. Replacement Annual TLD placed in service. Due to small sample size, the Cs-134 and Cs 137 LLDs were missed. Due to small sample size, the Cs-134 LLD was missed. Due to small sample size, the Cs-134 and Cs 137 LLDs were missed. Seasonal unavailability. Season unavailability. Station 14 changed, station 21 deleted, station 26 added. Seasonal unavailability. 31

IV.

SUMMARY

AND DISCUSSION OF 2001 ANALYTICAL RESULTS 32

IV. Summary And Discussion of 2001 Analytical Results Data from the radiological analyses of environmental media collected during 2001 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Environmental Services Quality Assurance manual and are explained in the Teledyne Brown Engineering Environmental Services Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Interlaboratory Comparison program. The results of the Interlaboratory Comparison Program are provided in Appendix E. Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering Environmental Services's analytical methods meet the Lower Limit of Detection (LLD) requirements given in table 2 of the USNRC Branch Technical Position, Radiological Monitoring Acceptable Program (November 1979, Revision 1) and the ODCM. The following is a discussion and summary of the results of the environmental measurements taken during the 2001 reporting period. A. Airborne Exposure Pathway

1.

Air Iodine/Particulates Charcoal cartridges used to collect airborne iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. The results are presented in Table B-1. All results were below the required lower limit of detection. For air particulates, gross beta activity was observed in all fifty-two control samples with an average concentration of 0.020 pCi/m3 and a range of 0.009 to 0.041 pCi/m3. The average measurement for the indicator locations was 0.019 pCi/in3 with a range of 0.007 to 0.047 pCi/m3. The results of the gross beta activities are presented in Table B-2. The gross beta activities for 2001 were comparable to levels measured in the 1982-2001 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing performed in other countries. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m3 to a high of 0.75 pCi/m3. Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in 44 of the 44 composite samples. The average measurement for the control location was 0.081 pCi/m3 with a range of 0.028 to 0.149 pCi/rn3. The indicator locations had an average concentration of 0.086 pCi/m3 and a range of 0.021 to 0.667 33

During the propertional period, tritim was not detected in the sample analyzed. 34 CO,f Trending Graph-1: Gross Beta in Air Particulates I .t0. m0 0.01 .0 A I-4--Control Sta-24 -ifIndiciator --*--Avenge Pro-op - -H - Requied LID mooo-Trending Graph 2: Tritium in River Water-Station 11 t;8 loco z0 8100 10 S Thtium -- - Required LLD

pCi/m3. During the preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Naturally occurring potassium-40 was not detected in any control samples. Potassium-40 was detected in one indicator sample with a concentration of 0.108 pCi/m3. All other gamma emitters were below the detection limits. During the preoperational period gamma ray spectroscopy measured several fission products in numerous air particulate filters. All isotopes were attributed to atmospheric nuclear weapons testing conducted before the preoperational period. Among the isotopes measured were zirconium-95, ruthenium-103, ruthenium-106, cesium-137, cerium-141 and cerium-144. The second quarter composites of air particulate filters from all twelve stations were analyzed for strontium-89 and 90. There was no detection of these fission products at any of the ten indicator stations nor at the control station.

2.

Precipitation A sample of rain water was collected monthly at station OIA, on site, 0.75 miles, 138 degrees SE and analyzed for gross beta activity, tritium, and gamma emitters. The results are presented in Table B-4. The average gross beta activity for 2001 in ten of the twelve samples was 6.5 pCi/liter with a range from 2.9 to 16 pCi/liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. Beryllium-7 was not detected in the semi-annual composite samples for 2001. All other gamma emitters were below their detection limits. Tritium was detected one of the two semi-annual composite samples with a concentration of 170 pCi/liter. These results were comparable to or lower than those measured in 1986 through 2001. During the preoperational 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 2001 period. During the preoperational period, tritium was measured in over half of the few quarterly composites made. The tritium activity ranged from 100 to 330 pCi/liter.

3.

Soil Soil samples, which are collected every three years from twelve stations, were collected in July and analyzed by gamma ray spectroscopy. The results are presented in Table B-5. Naturally occurring potassium-40 was detected in all eleven indicator stations with an average concentration of 13765 pCi/kg (dry) and a range of 6570 to 29400 pCi/kg (dry). The control location had a concentration of 4610 pCi/kg (dry). The terrestrial nuclide radium-226 was measured in seven of the eleven indicator stations, with an average concentration of 1540 pCi/kg (dry) and a range of 538 to 2820 pCi/kg (dry). The control location had a concentration of 1150 pCi/kg (dry). Thorium-228 was detected in all eleven indicator stations with an average activity of 1251 pCi/kg (dry) and a range of 852 to 2260 pCi/kg (dry). The control location had a concentration of 1290 pCi/kg (dry). The fission product cesium-137 was detected in ten of the eleven indicator stations with an average activity of 334 pCi/kg (dry) and a range of 58 to 876 pCi/kg (dry). The control location had a concentration of 527 pCi/kg (dry). The cesium-137 is attributed to past atmospheric nuclear weapons testing. U-235 was also detected in seven of eleven 35

indicator stations with an average activity of 117 pCi/kg (dry) and a range of 82 to 161 pCi/kg (dry). The control location had a concentration of 125 pCi/kg (dry). The twelve soil samples were analyzed for strontium-89 and strontium-90. Strontium-89 was not detected. Strontium-90 was detected in two of eleven indicator stations with an average concentration of 145 pCi/kg (dry) and a range of 130 to 160 pCi/kg (dry). The control location had a concentration of 240 pCi/kg (dry). This was most likely due to fallout from past nuclear weapons testing. B. Waterborne Exposure Pathway

1.

Ground/Well Water Water was sampled quarterly from the on site well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The results are presented in Table B-6. No gamma emitting isotopes were detected during 2001. The second quarter sample was analyzed for strontium-89 and strontium-90. There was no measured activity of these isotopes above the detection level. Tritium was detected in one sample with a concentration of 120 pCi/liter. No gamma emitting isotopes were detected during the preoperational period.

2.

River Water A sample of water from the North Anna River was collected monthly at station 11, 5.8 miles downstream from the discharge lagoon, 128 degrees SE. The results are presented in Table B-7. The samples were analyzed by gamma spectroscopy monthly. The samples were analyzed for tritium quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90. Thorium-228 was detected in one of the twelve samples with a concentration of 6 pCi/liter. All other gamma emitters were below their detection level. There was no measured activity of strontium-89 or strontium-90 above the detection limit. Tritium was measured in all four samples with an average concentration of 3450 pCi/liter and a range of3l00 to 4000 pCi/liter. This is higher than the average level measured in 2000 of 3025 pCi/liter and a range of 1500 to 4700 pCi/liter. No river water samples were collected during the preoperational period.

3.

Surface Water Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon, 1.1 miles, 148 degrees SSE on Lake Anna. Station 09A is located 12.9 miles WNW. The samples were analyzed for iodine-131 by radiochemical separation. One of twelve indicator samples had a concentration of 0.8 pCi/liter. One of twelve control samples had a concentration of 1.4 pCi/liter. The results are presented in Table B-8. The samples were also analyzed by gamma ray spectrometry. Naturally occurring 36

thorium-228 was detected in one of the 12 control samples with a concentration of 7 pCi/liter. All other gamma emitters were below their detection level. A quarterly composite from each station was prepared and analyzed for tritium. The tritium activity at station 08 for the quarterly composites was at an average level of 3825 pCi/liter with a range of 3400 to 4400 pCi/liter. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCi/liter. However, during 2001 the results were within the same range as those measured in 1986 through 2000. During the preoperational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter. C. Aquatic Exposure Pathway

1.

Sediment/Silt Sediment samples were collected during February and August from each of three locations and were analyzed by gamma spectrometry. The results are presented in Table B-9. Two man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in three of the six samples with an average activity of 61 pCi/kg (dry weight) and a range of 15.6 to 136 pCi/kg (dry weight). The highest reading for cesium-137 was obtained from station 09A located 12.90 miles WNW. Naturally occurring potassium-40 was observed in all of the six samples with an average activity of 9087 pCi/kg (dry weight) and a range of 2430 to 14600 pCi/kg (dry weight). Naturally occurring thorium-228 was observed in all six samples with an average concentration of 779 pCi/kg (dry weight) and a range of 282 to 1160 pCi/kg (dry weight). Radium-226 was measured in all six samples with an average concentration of 567 pCi/kg (dry weight) and a range of 163 to 855 pCi/kg (dry weight). U-235 was measurred in the three August samples at an average concentration of 34 pCi/kg (dry weight) and a range of 19.9 to 47.3 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium-90. There was no measurable amount of strontium-89 in aquatic sediment/silt. Strontium-90 was measured in one indicator sample with a concentration of 32 pCi/kg (dry weight). During the preoperational period sediment samples were analyzed by gamma ray spectroscopy. Cesium-137 was measured in most of the samples with concentrations between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight). Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were measured at background levels.

2.

Shoreline Soil A sample of shoreline sediment was collected in February and August from station 08. The samples were analyzed by gamma ray spectrometry. The results are presented in 37

Table B-10. The naturally occurring nuclide potassium-40 was measured in both samples with an average activity of 1820 pCi/kg (dry weight) and a range of 1610 to 2030 pCi/kg (dry weight). Cosmogenic beryllium-7 was not measured during 2001. Thorium-228 was measured in both samples at an average of 329 pCi/kg (dry weight) and a range of 232 to 426 pCi/kg (dry weight). Radium-226 was measured in both samples with a concentration of 407 pCi/kg (dry weight) and a range of 310 to 503 pCi/kg (dry weight). Cesium-137, a fission product, was measured in both samples with a concentration of 177 pCi/kg (dry weight) and a range of 99.9 to 255 pCi/kg (dry weight). The August sample was analyzed for strontium-89 and strontium-90. There was no measured amount of strontium-89. Strontium-90 was measured at a concentration of 48 pCi/kg (dry weight). 38

loo L.d t so -8 -s S'b 'J9 's f0 S 'P o'9

4.

v0, lU* Tdtnm -- -IRapnedLLD-*-Av"e Pop Trending Graph-4: Cobalt-58 in Sediment Silt 1000 z0 10 1---Station-8 U---Station-09 A ContoolSta -0A _Stabon-l During the properatioiia period, oobalt-58 was not detected in the stasples analyzed. 39 co,n Trending Graph-3: Tritium in Surface Water Station 08 10000 S:ib..-_,- z1000

Trending Graph-5: Cobalt-60 in Sediment Silt I 14~` 101 @4~10 ~ 4~10 ~ 4F0 -Station-B -- Station-9 aControl-Sta09 -- Sttattio 1 I During the properational period, cobalt-60 wu not detected in the sanple analyzed. During the properational period, Cesium-134 was not detected in the sarnples analyzed. 40 CO% 1000 A ti( C 4 00 S 10 0 Trending Graph-6: Cesium-134 in Sediment Silt 1000

• c 1000 to lb)St-

-V4 Sta 9° io 9 -~ 9-t -9S Pta 5ion-I1 -U-e L 4-40S4di40rv4 4P Strio-O 4o1-StO D1 StmirFl _RqitredlO

t During the preoperational pedod, resium-134 was not detected in the saamples analyzed. Station 25 replacd station 09. 41 coq Trending Graph - 7: Cesium-137 in Sediment Silt 1 0000 z 1 0 00 W!10

1.

sb\\q7P

1. a

+~-Str4ion-S Stadtio-9 -A--Control-Stt-9 X-Stton-Il -AveragecPr-Op -ReqwredLLD's

D. Ingestion Exposure Pathway

1.

Milk The results of the iodine-13 1 analysis of milk samples are presented in Table B-I1. A sample was collected monthly from two stations. A total of 24 samples were analyzed during 2001. There were no measurements of iodine-131 above the detection limits. The milk samples were also analyzed by gamma ray spectroscopy and the results are also presented in Table B-I1. A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all samples with an average of 1269 pCi/liter and a range of 655 to 1530 pCi/liter. The fission product cesium-137 has been detected sporadically in recent years and the activity has been attributed to global fallout from past atmospheric weapons testing. However, cesium-137 was not detected at levels above LLD in any milk samples during 2001. All other gamma emitters were below their detection levels. A quarterly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontium-89 was not detected at levels above LLD in any of the samples monitored. Strontium-90 was detected in the eight samples monitored with an average level of 1.02 pCi/liter and a range of 0.52 to 1.5 pCi/liter. This is similar to activities determined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/liter.

2.

Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-12. Eight samples of fish were collected during 2001. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all samples at an average of 1653 pCi/kg (wet weight) with a range of 1310 to 2080 pCi/kg (wet weight). The fission product cesium-137 was measured in two of the eight samples with an average activity of 24.5 pCi/kg (wet weight) with a range of 23.5 to 25.5 pCi/kg (wet weight). During the preoperational period cesium-137 was measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weight). All other gamma emitters were below their detection levels.

3.

Food/Vegetation Thirty food samples were collected from five locations and analyzed by gamma spectrometry. The results are presented in Table B-13. Naturally occurring potassium-40 was monitored in all 30 samples with an average activity level of 22480 pCi/kg (wet weight) and a range of 7760 to 37300 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in 28 of the 30 samples with an average concentration of 1828 pCi/kg (wet weight) and a range of 159 to 4950 pCi/kg (wet weight). Cesium-134, a fission product, was not detected at levels above LLD during 2001. Cesium-137 has been detected in some samples at low-levels in previous years and was 42

detected in one sample at a concentration of 47.9 pCi/kg (wet weight). Cesium-137 was measured in broadleaf garden vegetation during the preoperational period with concentrations between 53 and 98 pCi/kg (wet weight). E. Direct Radiation Exposure Pathway

1.

TLD Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table B-14. Individual measurements of external radiation levels in the environs of the North Anna site had an average dose of 3.3 mR/standard month with a range of 1.3 to 6.0 mR/standard month. This is comparable to the preoperational range. Station No. 1, had an average reading of 5.0 mR/standard month with a range of 3.8 to 6.0 mR/standard month. 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 results are presented in Table B-

15. The average level of the 32 locations (two badges at each location) was 4.4 mR/standard month with a range of 0.7 to 17.4 mR/standard month.

The eight control TLDs, collected quarterly from four locations, showed an average reading of 2.9 mR/standard month with a range of 1.1 to 5.5 mR/standard month. During the preoperational period (starting in 1977), when the calculation of the TLD dose included a correction for the in-transit dose, the doses were measured between 4.3 and 8.8 mR/standard month. 43

0.0 1.0 Statio - D8 U-Station - 09 +Statio. - 25 - Avg. Preop - - keqund LLfl Station 25 replaced station 09. Trending Graph-10: Environmental Radiation - TLDs t. 0 ii C E 1.0 l 41 EnvimnmeDal TLDsA_-SetGdrTLDs-{-Ag Pnnp1 44 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~f1 Trending Graph-9: Cesium-137 in Fish 10000.0 aC 100 zt 1DO9.0 sC I.............................. ---................................ I 100.0 1 'ha -7\\

V. CONCLUSIONS 45

V. Conclusions The results of the 2001 Radiological Environmental Monitoring Program for the North Anna Nuclear Power Station and ISFSI have been presented. The following sections discuss each pathway individually followed by a program summary. Airborne Exposure Pathway Air particulate gross beta concentrations of all the indicator locations for 2001 followed the gross beta concentrations at the control location. The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1987 which was influenced by the Chemobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/CuM, due to occasional atmospheric nuclear weapons tests. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There was no detection above the LLD for fission products nor other man-made isotopes in the particulate media during 2001. Iodine-131 was not detected in the charcoal filters analyzed during 2001. A precipitation sample was collected monthly during 2001 and analyzed for gross beta activity. All the gross beta activities were comparable to those measured in previous years. During the preoperational period the average gross beta activity was 0.92 pCi/liter. Semi-annual composites were analyzed for gamma emitting isotopes and tritium. All gamma emitters were below their detection limits. Tritium was detected in one sample at 170 pCi/liter. During the preoperational period the average tritium activity was 165 pCi/liter. Waterborne Exposure Pathway One naturally occurring isotope, potassium-40 and two man-made isotopes were monitored in the surface water of Lake Anna. Iodine-131 was detected in one sample at 0.8 pCi/liter. The average tritium activity during 2001 at the waste heat treatment facility was 3825 pCi/liter, which is 19.13% of the reporting level for a water sample. In 2000 the tritium level was 2850 pCi/liter. The preoperational level was 150 pCi/liter and has risen since 1977, though it has remained relatively consistent since 1986. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3450 pCi/liter. The average tritium in 2000 had been 3025 pCi/liter. Naturally occurring thorium-228 was detected 1 out of 12 samples at a concentration of 6 pCi/liter. No other gamma emitters were detected. Ground water from the environmental well on site contained no gamma emitters. There was no detection of tritium in ground/well water during 2001. Aquatic Pathway Sediment/silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that one man-made 46

isotope was present. Cesium-137 was detected in two samples at the indicator location and in one sample at the control location. During the preoperational period, cesium-137 was measured in samples of aquatic sediment. Strontium-90 was detected in one sample at the indicator location. Sediment contamination does not provide a direct dose pathway to man. The samples of shoreline soil monitored downstream of the site contained no measurement of cesium-134. Cesium-137 was measured in all two samples at a level of 177 pCi/kg. Cesium-137 was detected during 2000 at a level of 167 pCi/kg. Ingestion Pathway Iodine-131 was not detected in any of the twenty-four milk samples using the radiochemical separation method. Although cesium-137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there was no detection during 2001. Strontium-90 was measured in all eight composite milk samples. Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels. Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 2001 showed the presence of one man-made isotope, cesium-137. This isotope was at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1987 through 2000. Only cesium-137 was measured in preoperational environmental fish samples. Due to primary and secondary steam generator problems experienced at North Anna during 1984/1985, a build up in activity levels both in effluents and fish did occur. Repairs to the steam generators and better liquid waste processing have reduced these activity levels in effluents and thus decreased activity levels are now being observed in the fish. The average level of activity during 2001 of cesium-137 was 1.3% of the reporting level. One vegetation sample contained cesium-137 at an average level of 47.9 pCi/kg. Cesium-137 has been measured in the past and in preoperational samples. Direct Exposure Pathway The direct exposure pathway as measured in the environment of the North Anna site by thermoluminescent dosimetry has remained essentially the same since the preoperational period in 1977 at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the internal dose from natural radionuclides. 47

Program Conclusions The results were as expected for normal environmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence. As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in the Offsite Dose Calculation Manual. These concentrations are based upon 25% of the annual dose commitment recommended by 1 OCFR50, Appendix I, to meet the criterion "As Low as is Reasonably Achievable". Based upon the evidence of the environmental monitoring program the station is operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the North Anna Nuclear Power Station during 2001. 48

VI. REFERENCES 49

VI. References

1.

Virginia Electric and Power Company, North Anna Power Station Technical Specifications, Units 1 and 2.

2.

Virginia Electric and Power Company, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".

3.

Title 10 Code of Federal Regulation, Part 50 (1 OCFR50), "Domestic Licensing of Production and Utilization Facilities".

4.

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 I OCFR50, Appendix I", October, 1977.

5.

United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December, 1975.

6.

USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.

7.

NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.

8.

"Technical Specifications for North Anna Independent Spent Fuel Storage Installation (ISFSI)" 50

VII. APPENDICES 51

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

TABLES - 2001 52

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 1 of 7 Air Iodine I-131 624 0.04 (pCi/rn3) -(0/572) N/A N/A -(0/52) Air Particulate (1E 03 pCi/m 3) Gross Beta 624 5 7 (6.6-47) 5A N 3.20 mi. 20.5(52/52) (8.7-47) Gamma 48 Be-7 48 10 86.3(44/44) 5A 3.20 mi. 209(4/4) 80.7(4/4) (21.4-667) N (24.1-667) (27.5-149) K-40 48 10 108(1/44) Sr-89 12 3 -(0/11) Sr-90 12 12 -(0/11) 5A N N/A N/A 3.20 mi. 108(1/44) N/A N/A Gamma 4 K-40 4 60 -(0/4) Tritium 4 2000 120(1/4) Sr-89 1 3 -(0/1) Sr-90 1 0.4 -(0/1) 01A SE N/A N/A 0.75 mi. 120(1/4) N/A N/A 53 f All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. I Range Direction Range Range ments 0 20.3(52/52) (8.8-41) 0 0 Ground Well Water (pCi/liter) -(0/4) -(0/1) -(0/1) 0 0 0 N/A N/A -(0/0) 0 -(0/0) -(0/0) -(0/0) 0 0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 2 of 7 Gamma 12 K-40 12 200 -(0/12) N/A N/A -(0/0) Th-228 12 5.73(1/12) H-3 4 2000 3450(4/4) (3100-4000) Sr-89 1 3 Sr-90 1 0.4 -(0/1) -(0/1) 11 SE 11 SE N/A N/A 5.80 mi. 5.73(1/12) 5.80 mi. 3450(4/4) (3100-4000) N/A N/A 4 6.54(10/12) (2.9-16.0) OIA SE 0.75 rni. 6.54(10/12) (2.9-16.0) Gamma 2 (Semi-Annually) Tritium 2 2000 170(1/2) I-131 24 0.5 0.83(1/12) Gamma 24 K-40 24 200 -(0/12) OIA 0.75 mi. 170(1/2) SE 09A 12.90 mi. 1.40(1/12) WrNW N/A N/A 12.90 mi. 7.0(1/12) 7.0(1/12) 7.0(1/12) -r 1 All Indicator Control Non-Medium or Anal sis Locations Location with Hig hest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments River Water (pCi/liter) 0 -(0/0) Precipitation (pCi/liter) Monthly -(0/0) -(0/0) -(0/0) Gross Beta 12 0 0 0 -(0/2) N/A -(0/0) 0 N/A Surface Water (pCi/liter) Regular Monthlies -(0/0) 0 -(0/0) 1.40(1/12) 0 0 Th-228 24 -(0/12) -(0/12) 09A WNW 0 54

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 3 of 7 Tritium 8 2000 3825(4/4) (3400-4400) Sr-89 1 Sr-90 1 (0/1) (0/1) 08 SSE N/A N/A 1.10 mi. 3825(4/4) (3400-4400) N/A N/A Gamma N/A K-40 N/A Tritium N/A Sediment Silt (pCi/kg (dry)) Gamma 6 K-40 6 200 6353(3/4) (2030-14600) 11 SSE Cs-137 6 194 65.4(2/4) 09A (30.9-99.9 WNW Ra-226 6 100 396(3/4) 09A (163-715) WNW Th-228 6 30 623(3/4) 11 (282-1160) SSE U-235 6 40.9(2/4) (34.4-47.3) 11 SSE 5.80 mi. 14600(1/2) 13200(1/2) 12.90 mi. 136(1/2) 136(1/2) 12.90 mi. 855(1/2) 855(1/2) 5.80mi. 1160(1/2) 1150(1/2) 5.80 mi. 47.3(1/2) 19.9(1/2) 55 All Indicator Control Non-Medium or Analysis Locations Location with Hig hest Mean Location Routine Pathway T L Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) l _No. Range Direction Range Range ments Surface Water (pCi/liter) Regular Monthlies Surface Water (pCi/liter) State Splits -(0/4) (0/1) (0/1) 0 0 0 Be7 6 -(0/4) N/A N/A -(0/2) 0 0 0 0 0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 4 of 7 All Indicator Control Non-Medium or Anal is Locations Location with Hig hest Mean Location Routine Pathway i Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range j Direction Range Range j ments Sediment Silt (pCi/kg (dry)) Soil (pCi/kg (dry)) Sr-89 3 (Annually) Sr-90 3 (Annually) Ganmma 12 Be-7 12 K-40 12 Cs-134 12 Cs-137 12 Ra-226 12 Th-228 12 U-235 12 Sr-89 12 Sr-90 12 4.0 -(0/0) 0.8 32.0(1/2) 100 180 100 30 200 40 -(0/1 1) 13765(11/11) (6570-29400) -(0/1 1) 334(10/11) (58-876) 1540(7/11) (538-2820) 1251(11/11) (852-2260) 117(7/11) (82-158) -(0/1 1) 145(2/11) (130-160) N/A 08 SSE NA 23 SSE NA 05A N 05 NNE 06 ESE 23 SSE NA 24 NW N/A 1.10 nmi. 32.0(1/2) NA 0.93 mi. 29400(1/1) NA 3.20 mi. 876(1/1) 4.20 mi. 2820(1/1) 4.70 mi. 2260(1/1) 0.93 mi. 158(1/1) NA 22.0 rni. 240(1/1) 56 -(0/0) -(0/1) 0 0 -(0/1) 4610(1/1) -(0/1) 527(1/1) 1150(1/1) 1290(1/1) 125(1/1) -(0/1) 240(1/1) 0 0 0 0 0 0 0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 5 of 7 Gamma 2 2 -(0/2) N/A N/A -(0/0) 0 K-40 2 200 1820(2/2) (1610-2030) Cs-137 2 40 177(2/2) (99.9-255) Ra-226 2 100 407(2/2) (310-503) Th-228 2 30 329(2/2) (232-426) Sr-89 1 (Annually) Sr-90 1 (Annually) 4.0 -(0/1) 0.8 48(1/1) 08 SSE 1.10 mi. 1820(2/2) (1610-2030) 08 1.10 mi. 177(2/2) SSE (99.9-255) 08 SSE 08 SSE N/A 08 SSE 1.10 mi. 407(2/2) (310-503) 1.10 mni. 329(2/2) (232-426) N/A 1.10 mi. 48(1/1) -(O/O) -(0/0) -(0/0) (0/0) -(0/0) -(0/0) I-131 24 0.5 -(0/24) Gamma 24 K-40 24 100 1269(24/24) 13 (655-1530) SSW Sr-89 8 5 -(0/8) (Quarterly) SR-90 8 (Quarterly) 0.8 1.02(8/8) (0.52-1.50) N/A 5.60 mi. 1278(12/12) (1070-1530) N/A 13 5.60 mi. 1.04(4/4) SSW (0.52-1.50) 57 A to Indicator Control Non-Medium or AnalA LoainLcoatin with Hig est Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. __I_ Range Direction Range Range ments Shoreline Soil (pCi/kg (dry)) Be-7 0 0 0 0 0 0 Milk (pCi/liter) N/A N/A -(0/0) 0 -(0/0) -(0/0) -(0/0) 0 0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 6 of 7 Fish (pCi/kg (wet)) Gamma 8 K-40 8 200 1525(4/4) (1310-1860) Cs-137 8 40 25.5(1/4) Food Vegetation (pCi/kg (wet)) 25 NW 08 SSE 16.5 mi. 1780(4/4) (1530-2080) 1780(4/4) (1530-2080) 1.10 mi. 25.5(1/4) 23.5(1/4) Ganuna 35 Be-7 30 1981(23/24) (159-4950) 14 NE 1.20 mi. 3039(6/6) 1123(5/6) (306-4950) (197-1520) 22528(24/24) (7760-37300) 14 NE Cs-137 30 80 47.9(1/24) 21 V-WNW 834(4/24) (156-1300) 234(5/24) (57.8-643) 52.0(1/24) 14 NE 21 WNW 23 SSE 1.20 rni. 25000(6/6) 22290(6/6) (11600-33000) (8940-29900) 1.00 mi. 47.9(1/24) -(0/6) 1.20 mi. 1056(2/6) -(0/6) (811-1300) 1.00 rni. 643(1/6) 73.6(2/6) (55.0-92.1) 0.93 MI. 52.0(1/24) -(0/6) Direct Gamma Radiation Dose (mR/std. Month) (Regular TLDs) Direct Gamma Radiation Dose (mR/std. Month) (Annual TLDs) 47 12 0.2 3.29(43/43) (1.3-6.0) 0.2 2.77(11/11) (1.7-4.7) 01 NE 01 NE 0.20 mi. 5.0(4/4) (3.8-6.0) 0.20 mi. 4.7(1/1) 58 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments 0 0 K-40 30 0 Ra-226 30 Th-228 30 I-131 30 0 0 0 2.88(4/4) (1.5-4.2) 2.7(1/1) 0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2001 Docket No. 50-338/339 Page 7 of 7 Direct Gamma 284 0.2 4.43(252/252) SSW-19/51 0.42 mi. Radiation Dose (0.7-17.4) SSW (mR/std. Month) (Sector TLDs) 11.3(8/8) 2.85(32/32) (8.2-17.4) (1.1-5.5) 59 [ 1 J All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway T Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) l No. Range Direction Range Range ments 0

APPENDIX B DATA TABLES 60

TABLE B-1: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 2001 pCi/m 3 +/- 2 Sigma Page 1 of 2 Collection STATIONS I Date 01 02 03 04 05 05A 06 07 21 22 23 24 l JANUARY 12/27 - 01/03 01/03 - 01/10 01/10 - 01/17 01/17 - 01/24 01/24 - 02/01 02/01 - 02/07 02/07 - 02/15 02/15 - 02/22 02/22 - 03/02 03/02 - 03/07 03/07 - 03/14 03/14 - 03/22 03/22 - 03/28 03/28 - 04/04 04/04 - 04/11 04/11 - 04/19 04/19 - 04/25 04/25 - 05/02 05/02 - 05/08 05/08 -05/16 05/16 -05/23 05/23 - 05/30 05/30 - 06/06 06/06 - 06/13 06/13 - 06/20 06/20 - 06/27 < 0.009 < 0.012 < 0.015 < 0.015 < 0.015 < 0.019 < 0.019 < 0.021 < 0.041 < 0.027 < 0.018 < 0.008 < 0.020 < 0.013 < 0.014 < 0.020 < 0.021 < 0.012 < 0.020 < 0.022 < 0.016 < 0.016 < 0.012 < 0.024 < 0.018 < 0.029 < 0.007 < 0.013 < 0.015 < 0.015 < 0.015 < 0.019 < 0.019 < 0.022 < 0.041 < 0.027 < 0.018 < 0.009 < 0.020 < 0.013 < 0.014 < 0.020 < 0.022 < 0.012 < 0.020 < 0.022 < 0.016 < 0.016 < 0.012 < 0.024 < 0.018 < 0.029 < 0.009 < 0.013 < 0.015 < 0.015 < 0.009 < 0.011 < 0.019 < 0.021 < 0.024 < 0.017 < 0.013 < 0.008 < 0.012 < 0.013 < 0.009 < 0.013 < 0.013 < 0.007 < 0.012 < 0.014 < 0.016 < 0.011 < 0.014 < 0.015 < 0.013 < 0.029 < 0.009 < 0.013 < 0.015 < 0.015 < 0.018 < 0.025 < 0.024 < 0.019 < 0.044 < 0.032 < 0.022 < 0.006 < 0.021 < 0.013 < 0.014 < 0.015 < 0.026 < 0.012 < 0.024 < 0.018 < 0.016 < 0.021 < 0.011 < 0.024 < 0.021 < 0.037 < 0.009 < 0.007 < 0.009 < 0.009 < 0.018 < 0.025 < 0.024 < 0.019 < 0.044 < 0.033 < 0.022 < 0.005 < 0.021 < 0.013 < 0.013 < 0.003 < 0.026 < 0.012 < 0.024 < 0.018 < 0.026 < 0.021 < 0.015 < 0.024 < 0.021 < 0.037 < 0.009 < 0.013 < 0.016 < 0.015 < 0.018 < 0.014 < 0.024 < 0.019 < 0.024 < 0.023 < 0.018 < 0.005 < 0.012 < 0.013 < 0.009 < 0.003 < 0.014 < 0.009 < 0.013 < 0.013 < 0.025 < 0.012 < 0.015 < 0.017 < 0.012 < 0.029 < 0.005 < 0.013 < 0.016 < 0.015 < 0.010 < 0.013 < 0.014 < 0.016 < 0.040 < 0.021 < 0.009 < 0.005 < 0.013 < 0.009 < 0.010 < 0.003 < 0.015 < 0.009 < 0.013 < 0.015 < 0.009 < 0.012 < 0.013 < 0.017 < 0.014 < 0.050 < 0.009 < 0.013 < 0.016 < 0.015 < 0.012 < 0.017 < 0.011 < 0.012 < 0.030 < 0.016 < 0.009 < 0.005 < 0.016 < 0.008 < 0.004 < 0.004 < 0.019 < 0.007 < 0.019 < 0.010 < 0.012 < 0.022 < 0.017 < 0.015 < 0.021 < 0.050 < 0.009 < 0.013 < 0.016 < 0.016 < 0.010 < 0.015 < 0.013 < 0.032 < 0.031 < 0.019 < 0.026 < 0.005 < 0.012 < 0.025 < 0.011 < 0.004 < 0.016 < 0.009 < 0.016 < 0.015 < 0.010 < 0.012 < 0.028 < 0.015 < 0.015 < 0.040 < 0.009 < 0.005 < 0.011 < 0.011 < 0.012 < 0.014 < 0.010 < 0.033 < 0.038 < 0.015 < 0.026 < 0.004 < 0.014 < 0.008 < 0.009 < 0.005 < 0.018 < 0.008 < 0.017 < 0.013 < 0.008 < 0.014 < 0.029 < 0.032 < 0.016 < 0.041 < 0.009 < 0.011 < 0.019 < 0.020 < 0.013 < 0.016 < 0.012 < 0.032 < 0.038 < 0.017 < 0.024 < 0.006 < 0.014 < 0.008 < 0.020 < 0.005 < 0.010 < 0.008 < 0.019 < 0.014 < 0.014 < 0.011 < 0.027 < 0.016 < 0.016 < 0.040 < 0.006 < 0.011 < 0.019 < 0.020 < 0.011 < 0.013 < 0.017 < 0.024 < 0.029 < 0.019 < 0.020 < 0.006 < 0.011 < 0.011 < 0.016 < 0.004 < 0.011 < 0.010 < 0.015 < 0.015 < 0.013 < 0.012 < 0.020 < 0.021 < 0.012 < 0.031 61 FEBRUARY MARCH APRIL MAY JUNE

TABLE B-i: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 2001 pCi/m3 +2 Sigma Page 2 of 2 Collection STATIONS I Date 01 02 03 04 05 05A 06 07 21 22 23 24 1 JULY 06/27 - 07/05 07/05 - 07/12 07/12 - 07/19 07/19 - 07/26 07/26 - 08/01 < 0.020 < 0.023 < 0.020 < 0.026 < 0.021 < 0.020 < 0.024 < 0.020 < 0.026 < 0.021 < 0.011 < 0.014 < 0.011 < 0.026 < 0.021 < 0.023 < 0.031 < 0.016 < 0.026 < 0.020 < 0.023 < 0.031 < 0.016 < 0.014 < 0.013 < 0.015 < 0.017 <0.011 < 0.021 < 0.019 < 0.029 < 0.019 < 0.013 < 0.021 < 0.019 < 0.029 < 0.015 < 0.010 < 0.021 < 0.019 < 0.029 < 0.020 < 0.008 < 0.021 < 0.019 < 0.029 < 0.020 < 0.009 < 0.011 < 0.013 < 0.019 < 0.012 < 0.014 < 0.013 < 0.024 < 0.013 < 0.020 < 0.016 < 0.014 < 0.024 AUGUST 08/01 - 08/08 08/08 - 08/15 08/15 - 08/23 08/23 - 08/29 < 0.031 < 0.023 < 0.008 < 0.009 < 0.031 < 0.023 < 0.008 < 0.010 < 0.031 < 0.023 < 0.008 < 0.010 < 0.032 < 0.023 < 0.007 < 0.010 < 0.031 < 0.026 < 0.007 < 0.009 < 0.031 < 0.026 < 0.007 < 0.009 < 0.031 < 0.026 < 0.009 < 0.009 < 0.031 < 0.026 < 0.009 < 0.008 < 0.025 < 0.021 < 0.009 < 0.011 < 0.025 < 0.035 < 0.011 < 0.010 < 0.026 < 0.022 < 0.010 < 0.011 < 0.025 < 0.022 < 0.010 < 0.010 SEPTEMBER 08/29 - 09/05 09/05 - 09/12 09/12 - 09/20 09/20 - 09/26 < 0.011 < 0.016 < 0.015 < 0.017 < 0.011 < 0.016 < 0.015 < 0.016 < 0.011 < 0.016 < 0.015 < 0.016 < 0.011 < 0.014 < 0.015 < 0.016 < 0.009 < 0.014 < 0.009 < 0.016 < 0.009 < 0.014 < 0.010 < 0.016 < 0.009 < 0.012 < 0.010 < 0.016 < 0.009 < 0.012 < 0.008 < 0.016 < 0.012 < 0.012 < 0.010 < 0.014 < 0.012 < 0.013 < 0.010 < 0.014 < 0.012 < 0.013 < 0.009 < 0.014 < 0.012 < 0.013 < 0.010 < 0.014 OCTOBER 09/26 - 10/03 10/03 - 10/10 10/10 - 10/17 10/17 - 10/24 10/24 - 10/31 NOVEMBER 10/31 - 11/07 11/07 - 11/14 X11/14 -11 /21 11/21 - 11/28 DECEMBER 11/28 - 12/05 12/05 - 12/12 12/12 - 12/19 12/19 - 12/27 < 0.006 < 0.016 < 0.016 < 0.024 < 0.017 < 0.018 < 0.021 < 0.023 < 0.028 < 0.040 < 0.018 < 0.026 < 0.045 < 0.006 < 0.015 < 0.016 < 0.025 < 0.014 < 0.018 < 0.023 < 0.023 < 0.028 < 0.040 < 0.019 < 0.026 < 0.013 < 0.006 < 0.015 < 0.016 < 0.024 < 0.010 < 0.018 < 0.021 < 0.025 < 0.028 < 0.040 < 0.019 < 0.025 < 0.013 < 0.006 < 0.015 < 0.016 < 0.024 < 0.023 < 0.018 < 0.021 < 0.023 < 0.028 < 0.040 < 0.015 < 0.026 < 0.013 < 0.004 < 0.016 < 0.016 < 0.019 < 0.023 < 0.022 < 0.015 < 0.023 < 0.021 < 0.038 < 0.019 < 0.020 < 0.030 < 0.009 < 0.016 < 0.016 < 0.019 < 0.023 < 0.017 < 0.018 < 0.024 < 0.021 < 0.038 < 0.011 < 0.020 < 0.030 < 0.010 < 0.016 < 0.014 < 0.019 < 0.023 < 0.022 < 0.018 < 0.023 < 0.021 < 0.038 < 0.016 < 0.020 < 0.030 < 0.012 < 0.015 < 0.014 < 0.019 < 0.012 < 0.022 < 0.020 < 0.022 < 0.021 < 0.038 < 0.016 < 0.020 < 0.030 < 0.011 < 0.021 < 0.014 < 0.024 < 0.016 < 0.022 < 0.018 < 0.030 < 0.022 < 0.032 < 0.016 < 0.027 < 0.036 < 0.012 < 0.021 < 0.011 < 0.023 < 0.016 < 0.014 < 0.013 < 0.027 < 0.022 < 0.043 < 0.016 < 0.027 < 0.036 < 0.011 < 0.011 < 0.011 < 0.024 < 0.016 < 0.024 < 0.029 < 0.028 < 0.022 < 0.033 < 0.009 < 0.028 < 0.036 < 0.009 < 0.010 < 0.011 < 0.023 < 0.016 < 0.024 < 0.032 < 0.030 < 0.022 < 0.032 < 0.014 < 0.027 < 0.036 62

TABLE B-2: CONCENTRATIONS OF GROSS BETA INAIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2001 LOE 03 pCi/r 3 +/- 2 Sigma Page 1 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 +/- 2 s.d. JANUARY 12/27/01 - 01/03/01 01/03/01 - 01/10/01 01/10/01 - 01/17/01 01/17/01 - 01/24/01 01/24/01 - 02/01/01 20+/-2 16+/-2 18+/-2 19+/-2 19+/-2 19+/-2 19+/-2 19+/-2 19+/-2 20+/-2 20+/-2 19+/-2 22+/-2 20+/-2 21 +/-2 FEBRUARY 02/01/01 - 02/07/01 02/07/01 - 02/15/01 02/15/01 - 02/22/01 02/22/01 - 03/02/01 25+/-2 21+/-2 20+/-2 17 +/-2 15 +/-2 16 +/-2 24 +/-2 22 +/-2 25 +/-2 20 +/-2 18 +/-2 21 +/-2 MARCH 03/02/01 - 03/07/01 03/07/01 - 03/14/01 03/14/01 - 03/22/01 03/22/01 - 03/28/01 14 +/-2 15 +/-2 14 +/-2 13+/-2 12+/-2 12+/-2 9 +/- 2 9 +/- 2 8 +/- 1 20 +/-2 18 +/-2 20 +/-2 19 8.9 17 +/-7.5 18 +/-9 20 +/- 10 18 +/- 10 19 +/-9 17 +/-9 18 +/-9 19 +/-8 18 +/-8 19 +/- 10 19 +/-10 18 +/-9 63 21 +/-2 19 +/-2 20 +/- 2 21 +/-2 22 +/- 2 16 +/- 2 15 +/-2 19 +/- 2 21 +/-2 21 +/-2 18 +/-2 19 +/-2 18 +/- 2 21 +/-2 21 +/-2 18 +/- 2 17 +/- 2 17 +/- 2 20 +/- 2 21 +/-2 17 +/- 2 18 +/- 2 17 +/-2 19 +/- 2 19 +/-2 21 +/-2 20 +/- 2 17 +/-2 21 +/-2 22 +/- 2 17 +/- 2 19 +/-2 19 +/- 2 21 +/-2 20 +/- 2 19 +/- 2 19 +/- 2 19 +/-2 22 +/- 2 21 +/-2 18 +/-2 19 +/- 2 19 +/-2 24 +/- 2 20 +/- 2 28 +/- 2 18 +/-2 26 +/- 2 22 +/- 2 18 +/-3 19 +/-3 19 +/- 2 21 +/-3 21 +/-2 26 +/- 2 18 +/- 2 27 +/- 2 22 +/- 2 25 +/-2 18 +/- 2 25 +/-2 21 +/-2 22 +/- 2 17 +/- 2 25 +/- 2 19 +/- 2 24 +/- 2 17 +/- 2 23 +/-2 21 +/-2 25 +/- 2 17 +/- 2 24+/-2 19 +/- 2 23 +/-2 17 +/-2 23 +/- 2 19 +/- 2 26 +/- 2 19 +/-2 26 +/- 2 22 +/- 2 15 +2 14 +/- 2 9 +/- 2 21 +/-2 23 +/- 2 17 +/- 2 26 +/- 2 21 +/-2 Quarter Avg. _2s.d. 15 +/- 2 13 +/-2 8 +/-1 19 +/- 2 24 +/- 5 17 +/- 2 25 +/-3 20 +/- 3 16 +/- 2 12 +/- 2 9 +/-1 18 +/-2 13 +/- 2 12 +/- 2 8 +/- I 18 + 2 15+/- 2 13 +/-2 7 +/- 1 20 +/- 2 15 +2 14 +/- 2 10 +/- 2 21 +/-2 15+/- 2 13 +/-2 8 +/-1 18 +/-2 15+/- 2 14 +/- 2 8 +/-1 19 +/- 2 13 +/- 2 13 +/- 2 9 +/- 2 20 + 2 15+/- 2 13 +/-2 8 +/-1 19 +/-2

I TABLE B-2: CONCENTRATIONS OF GROSS BETA INAIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2001 1.OE-03 pCi/m3 + 2 Sigma Page 2 of 4 COLLECTION AVERAGE I DATE 01 02 03 04 05 05A 06 07 21 22 23 24 +/- 2 s.d. APRIL 03/28/01 -04/04/01 11+/-2 9+/-1 10+/-1 10+/-1 11+/-1 11+/-2 10+/-1 10+/-1 13+/-3 11+/-1 12+/-2 13+/-2 11+/-3 04/04/01-04/11/01 20+/-2 18+/-2 20+/-2 19+/-2 20+/-2 18+/-2 17+/-2 19+/-2 18+/-2 18+/-2 20+/-2 20+/-2 19+/-2 04/11/01 - 04/19/01 16 +/-2 12 +/-2 15 +/-2 14 +/-2 14 +/-2 14 +/-2 14 +/-2 14 +/-2 15 +/-2 14 +/-2 10 +/-2 15 +/-2 14 +/-3 04/19/01 -04/25/01 19+/-2 22+/-2 21+/-2 21+/-2 19+/-2 22+/-2 18+/-2 20+/-2 18+/-2 19+/-2 21+/-2 23+/-2 20+/-3 04/25/01 - 05/02/01 20 +/-2 22 +/-2 21 +/-2 23 +/-2 20 +/-2 22 +/-2 20 +/-2 18 +/-2 19 +/-2 21 +/-2 22 +/-2 20 +/-2 21 +/-3 MAY 05/02/01 - 05/08/01 23 +/-2 24 +/-2 21 +/-2 23 +/-2 26 +/-2 21 +/-2 18 +/-2 21 +/-2 22 +/-2 20 +/-2 23 +/-2 24 +/-2 22 +/-4 05/08/01-05/16/01 19+/-2 19+/-2 18+/-2 16+/-2 15+/-2 22+/-2 17+/-2 17+/-2 17+/-2 19+/-2 19+/-2 20+/-2 18+/-4 05/16/01-05/23/01 9+/-2 7+/-2 10+/-2 9+/-2 9+/-2 12+/-2 8+/-2 8+/-2 7+/-2 9+/-2 8+/-2 9+/-2 9+3 05/23/01 - 05/30/01 15 +/-2 13 +/-2 14 +/-2 15 +/-2 13 +/-2 16 +/-2 15 +/-2 14 +/-2 13 +/-2 13 +/-2 15 +/-2 13 2 14 2 JUNE 05/30/01 -06/06/01 12+/-2 10+/-1 10+/-1 12+/-2 11+/- 2 10+/-1 9+/-1 12+/-2 10+/-1 10+/-1 11+/- 1 11 2 11 2 06/06/01-06/13/01 20+/-2 19+/-2 18+/-2 18+/-2 18+/-2 21+/-2 17+/-2 20+/-2 17+/-2 17+/-2 19+/-2 20+/-2 19+/-3 06/13/01-06/20/01 18+/-2 17+/-2 18+/-2 19+/-2 17+/-2 18+/-2 17+/-2 18+/-2 17+/-2 17+/-2 19+/-2 21+/-2 18+/-2 06/20/01 -06/27/01 19+/-2 17+/-2 18+/-2 18+/-2 18+/-2 20+/-2 18+/-2 18+/-2 15+/-2 19+/-2 18+/-2 17+/-2 18+/-2 QuarterAvg. 17+/-8.2 16+/-11 16+/-9 17+/-9 16+/-9 17+/-9 15+/-8 16+/-8 15+/-8 16+/-8 17+/-10 17+9 16+/-9 +/-2s.d. 64 /

TABLE B-2: CONCENTRATIONS OF GROSS BETA INAIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2001 1.0E-03 pCi/m 3 +/- 2 Sigma Page 3 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 + 2 s.d. JULY 06/27/01 - 07/05/01 07/05/01 - 07/12/01 07/12/01 - 07/19/01 07/19/01 - 07/26/01 07/26/01 - 08/01/01 18+/-2 14 +/- 1 17 +/- 2 17 +/- 2 18+/-2 17+2 23+/-2 19+/-2 18 +/- 2 18+/-2 20 +/- 2 20+/-2 12+/-2 12+/-2 14+/-2 14 +/- 2 11 +/-2 10 +/- 2 11 +/-2 11 +/-2 AUGUST 08/01/01 - 08/08/01 08/08/01 - 08/15/01 08/15/01 - 08/23/01 08/23/01 - 08/29/01 25+/-2 23 +/- 2 24 +/-2 22 +/-2 21 +/-2 26 +/-2 22+/-2 20 +/- 2 26+/-2 27+/-2 23++/- 2 27+/-2 25+/-2 24+/-2 25 +/-2 21+/- 2 25 +/- 2 23+/-2 27+/-2 26+/-2 SEPTEMBER 08/29/01 - 09/05/01 09/05/01 - 09/12/01 09/12/01 - 09/20/01 09/20/01 - 09/26/01 22+/-2 20+/-2 22 +/- 2 22+/-2 18 +/- 2 17 +/-2 20+/-2 18+/-2 26 +/- 2 24 +/- 2 25 +/- 2 25 +/- 2 24 +/- 2 21 +/-2 26 +/- 2 26 +/- 2 20+/-10 18+/-8.7 22+/-10 21+/-10 20+10 21 + 10 19 +/- 10 19 I 8 19 +/- 9 22+/-14 20+/-9 21+/-11 20+10 65 14 +/- 2 18 +/- 2 18 +/- 2 14 +/- 2 11 +/-2 18 +/- 2 19 +/- 2 20 +/- 2 15 +/- 2 11 l 2 15 +/- 2 18 +/- 2 17 +/- 2 12 +/- 2 11+/- 2 16 +/- 2 17 +/- 2 14 +/- 2 13 +/-2 11 +/-2 16 +/- 2 20 +/- 2 17 +/- 2 13 +/- 2 10 +/- 2 16 +/- 2 20 +/- 2 18 +2 13 +/- 2 12 +/- 2 17 +/- 2 20 +/- 2 20 +/- 2 13 +/- 2 11 +/-2 16 +/- 2 21 +/-2 19 +/- 2 14 +/- 2 10 +/- 2 16 +/- 3 19 +/- 3 18 +/- 4 13 +/- 2 11 +/-1 23 +/- 2 24 +/- 2 25 +/- 2 26 +/- 2 22 +/- 2 21 +/-2 22 +/- 2 26 +/- 2 23 +/- 2 21 +/-2 24 +/- 2 23 +/- 2 22 +/- 2 19 +/- 2 24 +/- 2 23 +/- 2 24 +/- 2 39 +/- 3 22 +/- 2 26 +/- 2 23 +/- 2 23 +/- 2 25 +/- 2 24 +/- 2 27 +/- 2 25 +/- 2 24 +/- 2 28 +/- 2 24 +/- 3 24 +/- 10 24 +/- 3 26 +/- 4 20 +/- 2 17 +/- 2 24 +/- 2 25 +/- 2 Quarter Avg. + 2 s.d. 26 +/- 2 19 +/- 2 26 +/- 2 26 +/- 2 22 +/- 2 15 +/- 2 24 +/- 2 25 +/- 2 20 +/- 2 17 +/- 2 22 +/- 2 21 +/-2 21 +/-2 18 +/- 2 22 +/- 2 25 +/- 2 23 + 2 18 + 2 24 +/- 2 25 +/- 2 23 +/- 2 19 +/- 2 24 +/- 2 24 +/- 2 23 +/- 2 19 +/- 2 26 +/- 2 27 +/- 2 22 + 3 18 +/- 3 24 +/- 3 25 +/- 4

TABLE B-2: CONCENTRATIONS OF GROSS BETA INAIR PARTICULA TES North Anna Power Station, Louisa County, Virginia - 2001 1OE-03 pci/m3 + 2 Sigma Page 4 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 +/-2s.d. 19+/-2 19+/-2 17+/-2 25 +/- 2 25+/-2 31+/-2 15+/-2 13+/-2 14+/-2 23+/-2 24+/-2 26+/-2 19+/-2 14+/-2 16+/-2 21+/-2 30 +/- 2 15+/-2 27+/-2 17 +/- 2 19 +/- 2 27 +/- 2 16+/-2 23 +/- 2 16+/-2 19+/-2 31 +/-2 17+/-2 26 +/- 2 16+/-2 18+/-2 25 +/- 2 14 +/- 2 25 +/- 2 16+/-2 17+/-2 26 +/- 2 13 +/-2 24+/-2 16 +/- 2 16 +/- 2 27 +/- 2 14 +/- 2 24 +/- 2 17 +/- 2 18+/-2 29 +/- 2 16+/-2 28 +/- 2 11 +/- 2 18 +/- 2 26 +/- 2 15 +/- 2 24 +/- 2 15+/-2 20 +/- 2 27 +/- 2 17+/-2 26 +/- 2 17+/-2 18 +/- 3 27 +/- 5 15+/-3 25 +/- 3 16 +/- 4 23+/-2 24+/-2 24+/-2 23+/-2 22 +/- 2 23+/-2 41 +/- 3 36+/-3 41+/-3 24+/-2 23+/-2 22+/-2 24+/-2 24 +/- 2 24+/-2 19 +/- 2 20 +/- 2 23+/-2 20+/-2 19+/-2 22+/-2 22+/-4 19+/-2 20+/-2 25 +/- 2 22 +/- 2 36+/-3 23 +/-2 28 +/- 2 23 +/- 2 20 +/- 2 20 +/- 2 25+/-2 24+/-2 21+/-2 24+/-2 40+/-3 47+/-3 22 +/- 2 23+/-2 24 +/- 2 20 +/- 2 17+/-2 19+/-2 27 +/- 2 24+/-2 19+/-2 23 +/- 2 23:+/-12 22+/-11 23+14 24 +/- 11 22 +/- 13 25 + 16 22 +/-13 23 +/-13 22 +/-11 20 +/-11 23 +/-12 24 +/-12 23 +/-12 66 t OCTOBER 09/26 - 10/03 10/03 - 10/10 10/10 - 10/17 10/17 - 10/24 10/24 - 10/31 NOVEMBER 10/31 - 11/07 11/07 - 11/14 11/14 - 11/21 11/21 -11/28 DECEMBER 24 +/- 2 23 +/- 2 39+/-3 22 +/- 2 23+/-2 26 +/- 2 40 +/- 3 22+/-2 11/28 - 12/05 12/05 - 12/12 12/12 - 12/19 12/19 - 12/27 21 +/-2 21+/-2 36+/-3 23 +/- 2 18+/-2 15+/-2 26 +/- 2 17+/-2 23 +/- 2 23 +/- 2 39+/-3 22 +/- 2 23 +/- 2 23 +/- 2 41+/-3 22 +/- 2 23 +/- 4 22 +/- 5 39 +/- 10 22 +/- 3 Quarter Avg. +/- 2 s.d. 26 +/- 2 19 +/- 2 18+/-2 19 +/- 2 24+/-2 23 +/- 2 19+/-2 22 +/- 2 23 +/- 2 21 +/-2 19+/-2 19+/-2 24 +/- 2 20 +/- 2 18+/-2 18+/-2 26 +/- 2 24 +/- 2 19+/-2 21+/-2 28 +/- 2 23 +/- 2 21+/-2 21 +/-2 25 +/- 3 22 +/- 4 19+/-3 20 + 3

TABLE B-3: GAMMA EMITTER

• AND STRONTIUM CONCENTRA TIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2001 1.0 E-03 pCi/m 3 +/- 2 Sigma Page 1 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/27-3/28 03/28-06/27 06/27-09/26 09/26-12/27 STA-01 Sr-89 (a)

< 0.7 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 28.2 +/- 1.9 74.7 +/- 3.9 135 +/- 7.2 62.0 +/- 3.90 75.0 i 89.1 K-40 < 3 < 3 < 3 < 5 Co-60 < 0.2 < 0.2 < 0.2 < 0.3 Ru-103 < 0.2 < 0.3 < 1 < 0.6 Cs-134 < 0.2 < 0.2 < 0.2 < 0.3 Cs-137 <0.2 <0.2 <0.2 <0.3 Th-228 < 0.2 < 0.3 < 1 < 2 STA-02 Sr-89 (a) < 0.7 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 24.3 i 1.8 73.4 +/- 4.3 101 +/- 6.1 62.0 + 3.8 65.2 i 63.6 K-40 < 4 < 5 < 3 < 3 Co-60 < 0.2 < 0.3 < 0.2 < 0.2 Ru-103 < 0.2 < 0.4 < 0.9 < 0.4 Cs-134 < 0.2 < 0.4 < 0.2 < 0.3 Cs-137 < 0.2 < 0.3 < 0.2 < 0.2 Th-228 < 0.3 < 0.4 < 0.2 < 2 STA-03 Sr-89 (a) < 0.8 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 25.8 +/- 1.8 79.3 + 4.5 152 +/- 8.1 62.2 +/- 4.4 79.8 i 106 K-40 < 6 < 5 < 3 < 6 Co-60 < 0.2 < 0.2 < 0.2 < 0.3 Ru-103 < 0.2 < 0.3 < 0.8 < 0.6 Cs-134 < 0.2 < 0.2 < 0.2 < 0.4 Cs-137 < 0.2 < 0.2 < 0.2 < 0.3 Th-228 < 0.2 < 0.3 < 0.2 < 2 STA-04 Sr-89 (a) < 0.9 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 27.9 +/- 1.8 72.1 +/- 3.9 157 + 7.8 65.5 +/- 3.8 80.6 t 109 K-40 <5 <4 <3 <4 Co-60 < 0.3 < 0.2 < 0.1 < 0.2 Ru-103 < 0.2 < 0.2 < 0.5 < 0.3 Cs-134 <0.1 <0.2 <0.1 <0.2 Cs-137 < 0.2 < 0.2 < 0.1 < 0.2 Th-228 < 0.2 < 0.2 < 1 < 1 All gamma emitters other than those listed were <LLD. (a) Strontium-89190 analyses performed only on second quarter samples. 67

TABLE B-3: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2001 1.0 E-03 pCi/m 3& 2 Sigma Page 2of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/27-3/28 03/28-06/27 06/27-09/26 09/26-12/27 STA-05 Sr-89 (a)

< 0.8 (a) (a) Sr-90 (a) < 0.3 (a) (a) Be-7 24.5 +/- 1.8 76.4 +/- 4.3 134 +/- 6.8 65.2 +/- 4.9 75.0 +/- 90.4 K-40 < 4 < 5 < 3 < 5 Co-60 < 0.2 < 0.3 < 0.1 < 0.4 Ru-103 < 0.2 < 0.3 < 0.6 < 0.7 Cs-134 < 0.2 < 0.2 < 0.1 < 0.4 Cs-137 <0.2 <0.2 <0.1 <0.4 Th-228 < 0.2 < 0.3 < 1 < 3 STA-05A Sr-89 (a) < 0.8 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 24.1 +/- 1.9 79.2 +/- 4.7 667 +/- 32.4 64.5 +/- 5.13 209.0 +/- 613 K-40 < 5 < 3 108 +/- 7.6 < 6 108.0 +/- 7.6 Co-60 < 0.2 < 0.4 < 0.5 < 0.4 Ru-103 < 0.2 < 0.6 < 3 < 0.7 Cs-134 < 0.2 < 0.4 < 0.5 < 0.4 Cs-137 < 0.2 < 0.3 < 0.5 < 0.4 Th-228 <0.3 <0.5 <0.8 <3 STA-06 Sr-89 (a) < 0.8 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 21.4 +/- 1.5 68.2 +/- 3.8 131 +/- 6.5 60.3 +/- 5.4 70.2 +/- 90.8 K-40 <4 <2 <2 <8 Co-60 < 0.2 < 0.3 < 0.2 < 0.5 Ru-103 < 0.2 < 0.4 < 0.5 < 0.9 Cs-134 <0.2 <0.2 < 0.1 <0.6 Cs-137 < 0.2 < 0.3 < 0.1 < 0.5 Th-228 < 0.2 < 0.3 < 0.1 < 3 STA-07 Sr-89 (a) < 0.8 (a) (a) Sr-90 (a) < 0.3 (a) (a) Be-7 24.1 +/- 1.8 75.7 +/- 4.2 130 +/- 6.7 64.7 +/- 5.0 73.6 +/- 87 K-40 < 5 < 4 < 3 < 7 Co-60 < 0.3 < 0.2 < 0.1 < 0.5 Ru-103 < 0.3 < 0.2 < 0.6 < 0.9 Cs-134 < 0.2 < 0.2 < 0.1 < 0.5 Cs-137 < 0.2 <0.2 <0.1 <0.4 Th-228 < 0.2 < 0.2 < 0.2 < 3 All gamma emitters other than those listed were LLD. (a) Strontium-89/90 analyses performed only on second quarter samples. 68

TABLE B-3: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2001 1.0 E-03 pCi/m34-2 Sigma Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/27-3/28 03/28-06/27 06/27-09/26 09/26-12/27 STA-21 Sr-89 (a)

< 0.8 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 25.9 +/- 2.0 72.1 +/- 4.1 128 i 6.8 57.6 t 5.1 70.9 +/- 85.4 K-40 <3 <4 <4 <7 Co-60 < 0.3 < 0.2 < 0.1 < 0.5 Ru-103 < 0.4 < 0.3 < 0.7 < 1 Cs-134 < 0.3 < 0.2 < 0.1 < 0.5 Cs-137 <0.3 <0.2 <0.1 <0.4 Th-228 < 0.4 < 0.2 < 1 < 3 STA-22 Sr-89 (a) < 0.9 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 24.6 i 2.0 71.2 +/- 4.0 141 +/- 7.0 55.9 +/- 3.5 73.2 +/- 98.4 K-40 <3 <5 <2 <3 Co-60 < 0.4 < 0.2 < 0.1 < 0.2 Ru-103 < 0.5 < 0.3 < 0.6 < 0.3 Cs-134 < 0.4 < 0.2 < 0.1 < 0.2 Cs-137 < 0.3 < 0.2 < 0.1 < 0.2 Th-228 < 0.6 < 0.4 < 1 < 1 STA-23 Sr-89 (a) < 0.8 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 25.2 +/- 2.5 71.9 +/- 3.9 146 +/- 7.5 66.8 +/- 5.1 77.5 i 100 K-40 <3 <4 <4 <5 Co-60 < 0.3 < 0.3 < 0.2 < 0.3 Ru-103 <0.4 <0.2 <0.7 <0.5 Cs-134 < 0.3 <0.1 < 0.1 <0.2 Cs-137 < 0.3 < 0.2 < 0.1 < 0.3 Th-228 < 0.4 < 0.2 < 0.2 < 2 STA-24 Sr-89 (a) < 0.8 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 27.5 +/- 1.9 79.1 +/- 4.4 149 +/- 7.4 67.0 +/- 5.4 80.7 +/- 101 K-40 < 2 < 4 < 3 < 5 Co-60 < 0.3 < 0.2 < 0.2 < 0.3 Ru-103 <0.4 <0.3 <0.7 <0.5 Cs-134 < 0.3 < 0.2 < 0.2 < 0.3 Cs-137 <0.3 <0.2 <0.1 <0.3 Th-228 <0.4 <0.4 <2 <2 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter samples. 69

TABLE B-4: GROSS BETA, TRITIUMAND GAMMA EMITTER* CONCENTRA TIONS IN PRECIPITA TION Station O0A - (On Site) North Anna Power Station, Louisa County, Virginia - 2001 pCi/L 4 2 Sigma Page 1 of 1 Collection Dates Gross Beta Rainfall (inches) 12/27/00 - 02/01/01 2.9 +/- 1.8 2.71 02/01/01 - 03/02/01 < 4 1.69 03/02/01 - 03/28/01 3.8 +/- 0.7 2.77 03/28/01 - 04/25/01 4.3 +/- 1.5 2.19 04/25/01 - 05/30/01 11.0 + 2.0 4.84 05/30/01 - 06/27/01 8.3 +/- 1.6 3.94 06/27/01 - 07/26/01 16.0 +/- 3.0 0.90 07/26/01 - 08/29/01 4.2 +/- 1.2 4.62 08/29/01 - 09/26/01 4.4 +/- 0.8 1.04 09/26/01 - 10/31/01 <7 0.64 10/31/01 - 11/28/01 6.3 +/- 2.0 0.53 11/28/01 - 12/27/01 4.2 +/- 1.3 2.25 Average + 2 s.d. 6.54 + 8.27 SEMI-ANNUAL PRECIPITA TION COMPOSITES 12/27/00 - 06/27/01 06/27/01 - 12/27/01 Be-7 Be-7 < 80 H-3 < 100 Average 4 2 s.d.

• All gamma emitters other than those listed were <LLD.

70 H-3 < 140 170 +/- 70 170 +/- 70

TABLE B-5: CONCENTRATIONS OF GAMMA EMITTERS

• IN SOIL North Anna Power Station, Louisa Conty, Virginia - 2001 pCi/kg 4+ 2 Sigma Page 1 of 1 COLLECTION STATION DATE Sr-89 Sr-90 Be-7 K-40 Cs-134 Cs-137 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01 07/19/01

< 300 < 300 < 400 < 400 < 300 < 400 < 300 < 400 < 800 < 400 < 300 < 400 < 100 < 100 < 100 < 200 < 100 < 100 160 +/- 90 < 200 < 200 < 100 130 +/- 80 240 +/- 130 < 200 < 200 < 300 < 300 < 300 < 400 < 300 < 300 < 300 < 300 < 500 < 300 21000 +/- 7750 +/- 13700 +/- 6570 +/- 10600 +/- 11000 +/- 10200 +/- 10800 +/- 12800 +/- 17600 +/- 29400 +/- 4610 +/- 730 401 620 381 500 590 480 520 500 690 1070 325 < 20 < 20 < 20 < 20 < 20 < 30 < 20 < 20 < 30 < 50 < 60 < 40 < 20 58 +/- 10 229 +/- 16 681 +/- 31 166 +/- 14 876 +/- 43 213 +/- 16 217 +/- 18 451 +/- 21 210 +/- 19 237 + 22 527 +/- 26 Ra-226 1140+/- 557 < 600 < 700 < 600 2820 +/- 293 2000 +/- 332 1470 +/- 39 < 800 538 +/- 23 1260 +/- 41 1550 +/- 48 1150+/- 39 Average + 2 s.d. 177 +/- 114 13003 +/- 13703 351 + 502 1491 + 1359 1254 +/- 852 118 4 62

• All other gamma emitters were <LLD.

71 01 02 03 04 05 05A 06 07 21 22 23 24 Th-228 1130 +/- 34 1070 +/- 38 1180+ 40 867 +/- 33 1070 +/- 40 859 +/- 39 2260 +/- 68 1140 +/- 44 852 +/- 34 1470 +/- 52 1860 +/- 63 1290 +/- 50 U-235 82 + 30 < 40 128 +/- 16 < 40 161 +/- 18 114+/- 19 89 + 18 < 40 < 30 87+/- 18 158 +/- 31 125 +/- 17

TABLE B-6: GAMMA EMITTER*, STRONTIUM AND TRITIUM CONCENTRATIONS IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 2001 pCi/L 1 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 Ba-140 Th-228 STATION OIA 03/28/01 (a) (a) < 300 < 50 < 90 < 15 < 10 < 10 06/27/01 < 0.9 < 1 < 100 < 50 < 90 < 20 < 10 < 10 09/26/01 (a) (a) < 100 < 35 < 80 < 7 < 7 < 6 01/10/02 (a) (a) 120 +/- 50 < 40 < 90 < 8 < 8 < 40 Average + 2 s.d. 120 + 50 TABLEB-7: GAMMA EMITTER*, STRONTIUMAND TRITIUMCONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 2001 pCi/L + 2 Sigma Page 1 of 1 Collection Date Sr-89 Sr-90 H-3 Be-7 K-40 I-131 Cs-137 Ba-140 Ra-226 Th-228 STATION 11 01/16/01 02/14/01 03/13/01 04/12/01 05/15/01 06/14/01 07/17/01 08/13/01 09/13/01 10/15/01 11/12/01 12/10/01 (a) (a) (a) <4.0 (a) (a) (a) (a) (a) (a) (a) (a) Average +/- 2 s.d. (a) (a) (a) <0.3 (a) (a) (a) (a) (a) (a) (a) (a) 4000 +/- 200 (b) (b) 3400 +/- 100 (b) (b) 3300 +/- 100 (b) (b) 3100 +/- 100 (b) (b) 3450 + 775 < 50 < 70 < 30 < 60 < 30 < 30 < 50 < 40 < 30 < 40 < 40 < 40 < 140 < 100 < 60 < 150 < 70 < 50 < 90 < 90 < 80 < 80 < 70 < 70 < 1 < 0.6 < 0.6 < 0.8 < 0.5 < 0.2 < 0.7 < 0.5 < 0.4 < 0.6 < 0.5 < 0.5 < 6 < 6 < 4 < 6 < 4 < 4 < 6 < 4 < 4 < 4 < 4 < 5 < 40 < 40 < 20 < 20 < 9 < 9 < 10 < 10 < 6 < 9 < 8 < 8 < 10 < 100 < 120 < 160 < 100 < 60 < 100 < 140 < 130 < 140 < 110 < 80 < 8 < 10 < 9 < 10 5.73 +/- 5.5 < 8 < 10 < 6 < 5 < 7 < 6 < 10 5.73 4 5.5 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter sample. 72

TABLEB-8: GAMMA EMITTER*, STRONTIUMAND TRITIUMCONCENTRATIONSIN SURFACE WATER North Anna Power Station, Louisa County, Virginia - 2001 pCi/L 1 2 Sigma Page I of I Collection I Dates Sr-89 Sr-90 H-3 Be-7 K-40 I-131** Cs-137 Ba-140 Ra-226 Th-228 STATION - 08 Average +/- 2 s.d. < 40 <40 < 50 < 40 <40 <30 < 50 < 40 <20 < 50 < 50 < 40 < 70 < 80 < 90 < 80 < 90 < 80 < 80 < 80 < 50 < 130 < 80 <60 < 1 < 0.5 < 0.5 < 0.5 < 0.6 < 0.1 0.83 +/- 0.33 (c) < 0.7 <0.5 < 0.7 < 0.5 < 0.4 <4 <7 < 5 < 5 < 6 < 4 < 6 < 4 < 4 < 5 < 5 < 5 < 30 < 30 < 30 < 20 < 9 < 10 < 10 < 10 < 10 < 10 < 10 < 8.8 < 9 < 10 < 130 < 110 < 120 < 100 < 80 < 150 < 70 < 170 < 90 < 130 < 6 < 9 < 9 < 6 < 9 < 8 < 10 < 10 <4 < 6.8 < 7.8 < 8.2 0.83 + 0.33 STATION - 09A Average +/- 2 s.d. < 40 < 50 < 30 < 40 < 30 < 30 < 60 < 30 < 30 < 30 < 50 < 50 < 80 <90 < 80 < 80 < 60 < 60 < 110 < 80 < 70 < 60 < 70 <70 < 1 <0.5 < 0.7 < 0.6 < 0.5 < 0.2 1.4 +/- 0.5 (c) < 0.5 < 0.4 < 0.5 < 0.4 < 0.5 1.4 I 0.5 <4 <6 < 4 < 4 < 3 <4 < 7 < 3 < 3 < 4 < 5 < 5 < 30 < 30 < 20 < 10 < 8 < 8 < 10 < 8 < 5 < 8 < 10 < 9 < 10 < 110 < 100 < 120 < 70 < 60 < 200 < 120 < 90 < 90 < 80 < 90 < 7 < 10 < 6 7.0 +/- 2.9 < 5 < 4 < 10 < 5 < 5 < 4.9 < 6.1 < 10 7.0 + 2.9 All gamma emitters other than those listed were <LLD.

• • 1-131 by radiochemistry.

(a) Strontium-89/90 analyses performed only on second quarter samples. (b) Tritium analyses performed on quarterly composite. (c) The reported iodine levels detected in station 8 and station 9A on 07/17101 are very close to the MDA and based on no detectable activity prior to nor afterwards, are most likely false positives. 73 01/16 02/14 03/13 04/12 05/15 06/14 07/17 08/13 09/13 10/15 11/12 12/10 (a) (a) (a) < 3 (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) < 0.3 (a) (a) (a) (a) (a) (a) (a) (a) 4400 +/- 200 (b) (b) 3500 +/- 100 (b) (b) 3400 +/- 100 (b) (b) 4000 +/- 100 (b) (b) 3825 +/- 929 01/16 02/14 03/13 04/12 05/15 06/14 07/17 08/13 09/13 10/15 11/12 12/10 (a) (a) (a) < 3 (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) <0.3 (a) (a) (a) (a) (a) (a) (a) (a) < 100 (b) (b) < 100 (b) (b) < 100 (b) (b) < 100 (b) (b)

TABLE B-9: GAMMA EMITTER*AND STRONTIUM CONCENTRATIONS INSEDIMENTSILT North Anna Power Station, Louisa County, Virginia - 2001 pCi/kg + 2 Sigma Page 1 of 1 STA-08 STA-09A STA-1 I STA-08 STA-09A STA-11 Average Nuclide 2/19 2119 2/19 08/06 08/06 08/06 (a) (a) < 270 13200 +/- 650 < 50 < 50 < 50 < 60 136 +/- 32 855 +/- 40 1150 +/- 66 < 330 (a) (a) < 300 14600 +/- 510 < 10 < 30 < 30 < 40 30.9 +/- 7.1 715 +/- 23 1160 +/- 39 < 220 < 100 32.0 +/- 12.0 < 260 6740 +/- 290 < 10 < 20 < 10 < 10 < 10 550 +/- 15 790 +/- 24 34.4 +/- 7.9 < 200 < 50 < 160 7690 +/- 273 < 9 < 20 < 10 < 8 15.6 +/- 4.1 421 +/- 12 310 +/- 12 19.9 +/- 5.8 9860 +/- 697 +/- 983 +/- 47.3 +/- 200 50 290 351 10 30 10 10 20 18 31 10.2 9087 +/- 8930 61 +/- 131 567 +/- 495 779 +/- 796 33.9 +/- 27.4 All gamma emitters other than those listed were <LLD. (a) Strontium 89190 analyses performed annually. 74 Sr-89 Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-1 34 Cs-1 37 Ra-226 Th-228 U-235 (a) (a) < 260 2430 +/- 205 < 30 < 30 < 10 < 30 < 30 163 +/- 19 282 +/- 20 < 170

TABLE B-10: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 2001 pCi/kg +/- 2 Sigma Page I of I Station-08 Station-08 Average Nuclide 02/19/01 08/06101

+/- 2 sigma (a) (a) < 350 2030 +/- 236 < 10 < 40 < 40 < 40 99.9 +/- 11.9 310 +/- 20 426 +/- 31 < 30 48.0 +/- 17.0 < 290 1610 +/- 158 < 10 < 20 < 10 < 10 255 +/- 14 503 +/- 17 232 +/- 13 1820 +/- 594 177 +/- 219 407 +/- 273 329 +/- 274 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed annually. 75 Sr-89 Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-1 37 Ra-226 Th-228

TABLE B-l: GAMMA

• AND STRONTIUM CONCENTRATIONS INMILK North Anna Power Station, Louisa County, Virginia - 2001 pCi/L = 2 Sigma MONTH NUCLIDE STATION-12 STATION-13 I

JANUARY FEBRUARY MARCH APRIL MAY JUNE Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 I-131 (a) (a) 1260 i 88 < 6 < 1 (a) (a) 1360 +/- 75 < 3 < 0.3 < 2 0.71 +/- 0.28 655 +/- 38 < 4 < 0.3 (a) (a) 1340 + 92 < 5 < 0.4 (a) (a) 1260 + 87 < 6 < 0.4 < 2 0.70 + 0.21 1460 +/- 97 < 8 < 0.3 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed on the last monthly sample of each quarter. 76 Page 1 of 2 (a) (a) 1170 +/- 74 < 5 < 1 (a) (a) 1340 +/- 89 < 4 < 0.2 < 2 0.52 +/- 0.22 1270 +/- 82 < 6 < 0.4 (a) (a) 1250 +/- 69 < 3 < 0.5 (a) (a) 1530 +/- 75 < 3 < 0.4 < 2 0.93 +/- 0.22 1070 +/- 74 < 6 < 0.2

TABLE B-1l: GAMMA *AND STRONTIUM CONCENTRATIONS INMILK North Anna Power Station, Louisa County, Virginia - 2001 pCi/L + 2 Sigma Page 2 of 2 IMONTH NUCLIDE STATION-12 STATION-13 I Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 SEPTEMBER OCTOBER Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 1-131 (a) (a) 1310 i 86 < 5 < 0.5 (a) (a) 1310 +/- 61 < 4 < 0.8 < 1 1.4 +/- 0.2 1240 +/- 89 < 6 < 0.4 (a) (a) 1260 +/- 76 < 4 < 0.5 (a) (a) 1360 +/- 88 < 5 < 0.7 (a) (a) 1340 +/- 70 < 5 < 0.8 < 2 1.5 +/- 0.2 1270 +/- 68 < 4 < 0.6 (a) (a) 1160 +/- 74 < 4 < 0.4 Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 1-131 (a) (a) 1300 i 70 < 4 < 0.4 < 3 1.2 +/- 0.3 1360 i 69 < 3 < 0.6 1.0 4 0.71 1260 +/- 400 t All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed on the last monthly sample of each quarter. 77 JU:LY AUGUST NOVEMBER DECEMBER Average 4 2 s.d. (a) (a) 1250 i 73 < 4 < 0.4 < 2 1.2 +/- 0.2 1320 +/- 83 < 5 < 0.7 1.0 4 0.83 1278 +/- 234

TABLE B-12: GAMMA EMITTER

• CONCENTRA TIONS IN FISH North Anna Power Station, Louisa County, Virginia - 2001 pCi/kg 4 2 Sigma Page 1 of 1 Sample Station Type K-40 Co-58 Cs-134 08 Fish(a) 1540 +/- 106

< 9 < 9 25 Fish (a) 1530 +/- 100 < 9 < 8 23 08 Catfish (b) 1860 i 149 < 10 < 10 25 25 Catfish (b) 1700 +/- 106 < 8 < 8 Cs-137 < 10 3.5 i 3.7

.5 i 4.6

< 10 08/09 08/06 08/09 08/07 Average + 2 s.d. 08 Fish (a) 25 Fish (a) 08 Catfish (b) 25 Catfish (b) 08 25 1310 + 241 1810 i 261 1390 +/- 374 2080 +/- 228 <20 <20 <20 <20 <30 <20 <20 < 10 1525 + 486 1780 + 462

• All gamma emitters other than those listed were <LLD.

(a) Non-bottom dwelling species of gamefish. (b) Bottom dwelling species of fish. 78 ICotlection I Date 02/20 02/20 02/20 02/20 < 30 < 20 < 30 < 20 25.5 4 4.6 23.5 + 3.7

TABLE B-13: GAMMA EMITTER

• CONCENTRATIONS IN FOOD AND VEGETATION North Anna Power Station, Louisa County, Virginia - 2001 pCi/kg 4 2 Sigma Page 2 of 2 Collection B

IDate Be-7 K-40 1-13 1 Ru-i103 Cs-134 Cs-137 Ra-226 Th-228 STATION 23 04/19 05/16 06/20 07/19 08/27 09/20 2360 +/- 409 663 +/- 100 549 +/- 101 < 930 1580 +/- 155 1310 i 130 25100 16400 29600 29400 19700 14900 +/- 1090 +/- 620 +/- 1090 +/- 1340 +/- 820 +/- 610 < 60 < 20 < 40 52.0 i 23.0 < 20 < 20 < 80 < 40 < 30 < 80 < 30 < 30 < 70 (a) < 30 < 20 < 50 < 30 < 30 < 70 < 30 < 20 < 60 < 40 < 40 < 110 < 460 < 630 < 1400 < 770 < 750 203 +/- 37.0 < 60 < 30 83.3 +/- 32.0 < 40 < 50 Average 1828 +/- 5758 22480 + 14904 52.0 +/- 23.0 +/- 2 s.d. 47.9 +/- 12.0 834 i 989 All gamma emitters other than those listed were <LLD. (a) Due to small sample size, the LLD was missed. 79 188 +/- 418

TABLE B-14: DIRECTRADIATIONMEASUREMENTS - QUARTERLYAND ANNUAL TLD RESULTS North Anna Power Station, Louisa County, Virginia - 2001 Std. Month (30.4 days) + 2 Sigma Page 1 of 1 Station First Qtr Second Qtr Third Qtr Fourth Qtr Quarterly Annual TLD Number 01/11/01 04/05/01 07/12/01 10/03/01 Average 01/11/01 04/05/01 07/12/01 10/03/01 01/08/01 01/08/02 01 02 03 04 05 05A 06 07 21 22 23 24 Average + 2 s.d. 6.0 2.7 2.4 2.5 3.9 2.9 5.1 3.3 3.8 4.8 5.5 4.2 3.9 +/- 2.4 6.0 2.7 2.6 3.4 2.8 1.7 2.3 2.5 3.5 4.9 3.4 3.2 i 2.5 4.1 1.6 1.7 2.7 3.5 2.4 4.0 2.7 1.7 4.4 3.3 1.5 2.8 +/- 2.1 3.8 2.6 1.3 1.8 4.1 1.7 3.5 3.4 3.0 3.4 5.4 2.4 3.0 +/- 2.3 Refer to Section lIl, "REMP Exceptions for Scheduled Sampling and Analysis During 2001" 80 5.0 i 2.4 2.4 +/- 1.1 2.0 +/- 1.2 2.6 +/- 1.3 3.6 +/- 1.1 2.2 +/- 1.2 4.2 +/- 1.6 2.9 i 1.0 2.7 +/- 1.8 4.0 +/- 1.4 4.8 +/- 2.0 2.9 +/- 2.3 3.3 +/- 2.0 4.7 1.9 1.8 2.2 2.9 2.1 1.7 2.5 2.6 3.6 4.5 2.7 2.8 +/- 2.0

TABLEB-15: DIRECTRADL4TIONMEASUREMENTS-SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 2001 mR/Std. Month (30.4 days) + 2 Sigma Page 1 of 2 Station First Qtr Second Qtr Third Qtr Fourth Qtr Average lNumber 01/11 04/05 04105 07112 07112 10/03 10/03 01108 +/- 2 s.d. N-1 5.0 4.3 4.9 4.6 4.7 +/- 0.6 N-2 3.0 2.8 3.5 2.9 3.0 +/- 0.7 NNE-3 7.5 8.1 6.7 7.0 7.3 +/- 1.2 NNE-4 4.6 4.2 4.1 4.4 4.3 +/- 0.4 NE-5 6.0 5.8 5.9 5.7 5.9 +/- 0.2 NE-6 3.8 4.1 3.7 3.8 3.8 +/- 0.3 ENE-7 4.8 3.1 6.1 4.9 4.7 +/- 2.5 ENE-8 3.1 3.2 2.7 3.2 3.1 +/- 0.5 E-9 5.2 4.6 4.6 5.7 5.0 +/- 1.1 E-10 5.0 4.5 4.5 5.0 4.7 +/- 0.6 ESE-11 4.3 3.1 3.6 4.1 3.8 +/- 1.1 ESE-12 5.2 4.0 4.6 4.6 +/- 1.2 SE-13 4.6 4.5 3.3 4.1 4.1 +/- 1.2 SE-14 7.3 5.4 6.4 6.3 6.4 +/- 1.5 SSE-15 5.0 3.8 5.6 4.8 4.8 +/- 1.5 SSE-16 3.5 4.0 2.6 3.5 3.4 +/- 1.1 S-17 8.2 7.8 6.7 7.2 7.5 +/- 1.3 S-18 2.7 1.7 1.1 2.4 2.0 +/- 1.5 SSW-19 9.1 9.0 8.1 10.1 9.1 +/- 1.6 SSW-20 2.5 2.3 1.7 1.4 2.0 +/- 1.0 SW-21 4.4 3.4 3.4 2.8 3.5 +/- 1.3 SW-22 4.7 4.5 4.0 4.8 4.5 +/- 0.8 WSW-23 5.5 4.3 5.0 3.6 4.6 +/- 1.7 WSW-24 5.0 5.1 5.6 2.7 4.6 +/- 2.5 W-25 6.3 6.1 6.4 4.4 5.8 +/- 1.9 W-26 3.0 2.4 2.1 1.6 2.3 +/- 1.1 WNW-27 3.7 2.2 2.6 2.2 2.7 +/- 1.5 WNW-28 3.4 3.3 3.0 1.9 2.9 +/- 1.3 NW-29 6.9 6.9 5.8 6.5 6.5 +/- 1.0 NW-30 2.9 3.4 0.7 1.5 2.1 +/- 2.5 NNW-31 4.3 4.0 3.0 2.5 3.4 +/- 1.7 NNW-32 4.1 4.2 3.0 2.8 3.5 +/- 1.5 N-33 5.2 5.5 4.2 3.2 4.5 +/- 2.1 N-34 3.5 2.9 2.0 2.6 2.8 +/- 1.2 NNE-35 7.8 7.4 4.6 4.9 6.2 +/- 3.3 NNE-36 3.1 3.9 2.7 3.3 +/- 1.3 NE-37 5.5 6.5 3.5 4.0 4.9 +/- 2.8 NE-38 3.5 4.2 3.2 1.9 3.2 +/- 2.0 ENE-39 5.1 5.0 4.0 3.6 4.4 +/- 1.5 ENE-40 3.3 3.8 2.7 2.1 3.0 +/- 1.5 E-41 5.3 5.4 4.5 4.0 4.8 +/- 1.4 Refer to Section lil, "REMP Exceptions for Scheduled Sampling and Analysis During 2001l 81

TABLE B-15: DIRECT RADL4TION MEASUREMENTS - SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 2001 mR/Std. Month (30.4 days) + 2 Sigma Page 2 of 2 First Qtr Second Qtr 01/11 04/05 04105 07/12 4.7 6.2 4.2 4.7 5.1 4.3 4.8 7.1 7.1 5.2 5.2 3.3 3.4 7.6 7.7 2.8 2.7 9.2 10.5 2.6 2.7 4.5 4.0 4.8 3.5 5.7 5.9 4.7 4.6 6.5 6.0 3.4 3.3 3.5 4.3 3.7 3.6 6.2 6.1 3.0 3.5 3.7 3.3 3.8 3.3 2.2 3.3 3.7 3.5 2.4 3.8 2.3 2.5 2.0 2.5 1.7 4.3 3.1 5.5 3.1 4.8 +/- 3.2 4.5 +/- 3.6 Third Qtr 07/12 10/03 5.0 3.8 4.0 3.6 6.2 5.6 1.8 5.6 1.7 8.2 2.0 3.9 2.9 5.6 4.5 5.9 2.0 3.0 2.6 6.0 2.4 3.7 2.4 1.8 2.7 2.0 1.5 2.1 1.7 3.7 3.4 4.0 +/- 3.4 Fourth Qtr 10/03 01108 3.1 4.2 3.1 4.7 5.2 3.7 3.2 8.1 2.5 17.4 2.7 4.5 4.5 5.0 4.7 6.2 2.9 2.4 3.2 7.0 2.6 3.7 4.0 3.1 2.9 2.2 3.3 2.5 1.1 4.1 4.0 4.2 +/- 4.4 Refer to Section Ill, "REMP Exceptions for Scheduled Sampling and Analysis During 2001" 82 Station Number E-42 ESE-43 ESE-44 SE-45 SE-46 SSE-47 SSE-48 S-49 S-50 SSW-51 SSW-52 SW-53 SW-54 WSW-55 WSW-56 W-57 W-58 WNW-59 WNW-60 NW-61 NW-62 NNW-63 NNW-64 C-1 C-2 C-3 C-4 C-5 C-6 C-7 C-8 Average Average t 2 s.d. 4.8 +/- 2.6 4.2 +/- 0.8 4.1 +/-2.0 4.3 +/- 1.1 6.4 +/- 1.9 4.9 +/- 1.6 2.9 +/- 1.5 7.3 +/- 2.3 2.4 +/- 1.0 11.3 +/- 8.3 2.5 +/- 0.6 4.2 +/- 0.6 3.9 +/- 1.8 5.5 +/- 0.8 4.6 +/- 0.3 6.2 +/- 0.5 2.9 +/- 1.2 3.3 +/- 1.6 3.3 +/- 1.0 6.3 +/- 1.0 2.6 +/- 0.6 3.6 +/- 0.1 3.4 +/- 1.5 2.6 +/- 1.5 3.2 +/- 0.9 2.5 +/- 1.3 2.7 +/- 2.1 2.3 +/- 0.5 1.8 +/- 1.1 3.8 +/- 1.1 4.0 +/- 2.1 4.4 +/- 3.4

APPENDIX C LAND USE CENSUS - 2001 83

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION COMPARISON OF THE 2001 TO TILE 2000 LAND USE CENSUS I. No changes were observed in the nearest resident. II. No changes were observed in the nearest site boundary distances. III. No changes were observed in the nearest milk cow/goat status. IV. The following change was observed in the nearest vegetable garden as compared to the previous year:

a. Sector N 1.5 mi. to 1.8 mi.

b. Sector NNE 1.5 mi. to 1.6 mi.

c. Sector SSE 2.6 mi. to 1.3 mi.

d. Sector S 1.0 mi. to 1.2 mi.

e. Sector SSW 2.9 mi. to 1.6 mi.

f.

Sector WSW 1.7 mi. to 2.0 mi.

g. Sector WNW 2.2 to None

h. Sector NW 1.2 mi. to 1.1 mi.

V. No changes were observed in the nearest meat animal status. 84

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 2001 August 1 - September 8 2.4 1.4 1.5 3.4 2.1 2.7 2.3 1.6 1.7 1.9 5.0 2.7 2.4 1.8 1.7 1.6 1.4 1.4 1.3 1.3 1.3 1.4 1.4 1.5 1.5 3.5 2.9 2.3 2.3 4.0 5.7 NONE 2.3 4.5 NONE 1.6 1.7 1.8 1.7 1.6 1.6 1.4 3.1 NONE 2.7 7.1 6.5 NONE 3.2

• Note: No milch cow or goats within a 5 mile radius of North Anna Power Station km = kilometer 85 N

NNE NE ENE E ESE SE SSE S 2.5 1.5 3.4 2.1 5.6 2.3 2.1 1.9 2.6 5.0 3.2 8.0 NONE 1.8 1.9 SSW SW WSW W WNW NW NNW

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 2001 August 1 - September 8 Nearest Nearest Site Milch* Meat Milch* Resident Boundary Cow Animal Goat M M M M M 1.5 0.9 2.2 0.9 0.9 1.5 0.9 0.8 1.4 2.1 0.8 2.5 1.3 0.8 3.5 1.7 0.9 NONE 1.4 0.9 1.4 1.0 0.9 2.8 1.1 0.9 NONE 1.2 1.0 2.0 3.1 1.1 NONE 1.7 1.1 1.7 1.5 1.1 4.4 1.1 1.0 4.1 1.0 1.0 NONE 1.0 0.9 2.0 Veg. Garden 500 Sq. Ft. M 1.8 1.6 0.9 2.1 1.3 3.5 1.4 1.3 1.2 1.6 3.1 2.0 5.0 NONE 1.1 1.2

• Note: No mitch cow or goats within a 5 mile radius of North Anna Power Station M= mile 86 Sector N

NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 87

ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by Dominion Virginia Power and Teledyne Brown Engineering Environmental Services and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979. ANALYSIS TITLE PAGE Gross Beta Analysis of Samples....................................... 89 Airborne Particulates....................................... 89 Water....................................... 90 Analysis of Samples for Tritium (Liquid Scintillation)....................................... 91 Water....................................... 91 Analysis of Samples for Strontium-89 and 90....................................... 92 Water....................................... 92 Milk....................................... 92 Soil and Sediment....................................... 92 Organic Solids....................................... 92 Air Particulates....................................... 93 Analysis of Samples for Iodine-131....................................... 95 Milk or Water....................................... 95 Gamma Spectrometry of Samples....................................... 96 Milk and Water....................................... 96 Dried Solids other than Solids and Sediment....................................... 96 Fish....................................... 96 Soils and Sediments....................................... 96 Charcoal Cartridge (Air Iodine)....................................... 96 Airborne Particulates....................................... 96 Environmental Dosimetry....................................... 98 88

GROSS BETA ANALYSIS OFSAMPLES Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by the customer, is counted as the blank. Calculations of the result, the two sigma error and the lower limit of detection (LLD): RESULT (pCi/rn3) = ((S/T) - (B/t))/(2.22 V E) TWO SIGMA ERROR (pCi/m3) = 2((S/T2 ) + (B/t2))"/2 /2.22 V E) LLD (pCi3) = 4.66 (B 2)/2.22 V E t) where: S = Gross counts of sample including blank B = Counts of Blank E = Counting Efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 89

DETERMINATION OF GROSS BETA ACTIVITY IN WA TER SAMPLES Introduction The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved. One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through the No. 54 filter paper before evaporation, removing particles greater than 30 microns in size. After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchette which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps. Residue mass is determined by weighing the planchette before and after mounting the sample. The planchette is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective efficiency caused by the residue mass. Detection Capability Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time. The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/I at the 2.83 sigma level), assuming that 1 liter of sample is used and that 1/2 gram of sample residue is mounted on the planchette. These figures are based upon counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38. 90

ANALYSIS OF SAMPLES FOR TRITIUM (Liquid Scintillation) Water Ten millimeters of water are mixed with 10 ml of a liquid scintillation "cocktail" and then the mixture is counted in an automatic liquid scintillator. Calculation of the result, the two sigma error and the lower limit detection (LLD) in pCi/l: RESULT = (N-B)/(2.22 V E) TWO SIGMA ERROR = 2(N + B)/(At) "2 / (2.22 V E) LLD = 4.66 (B/At) 1i/ (2.22 V E) where: N = the gross cpm of the sample B = the background of the detector in cpm 2.22 = conversion factor changing dpm to pCi V = volume of the sample in ml E efficiency of the detector At = counting time for the sample 91

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO3)2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrNO3 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and then re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrCO3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrochloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO3)2 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrCO3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Organic Solids A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as (SrNO3)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrCO3 from the sample after 92

yttrium separation. This precipitate is counted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO3)2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrCO3 from the sample after yttrium separation. This precipitate is counted on a nylon planchette and is covered with 80 mg/cm2 aluminum absorber for low level beta counting. Calculations of the result, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass: RESULT Sr-89 = (N/At-Bc-BA)/(2.22 V Ys DFsr,ggESr-89) TWO SIGMA ERROR Sr-89 = 2(N/At+Bc+BA)/(At)"/ 2/(2.22 V YsDFsr-89Esr-89) LLD Sr-89 = 4.66(Bc+BA)/(At)1 12/(2.22 V YsDFsr-89Esr-89) RESULT Sr-90 = (N/At-B)/(2.22 V Y1 Y2 DF IF E) TWO SIGMA ERROR Sr-90 = 2(N/At+B)/(At)"/2/(2.22 V Yi Y2 DF E IF) LLD Sr-90 = 4.66(BC+BA)/(At) 1/21(2.22 V Y, Y2 IF DF E) Where: N = total counts from sample At = counting time for sample (min) Bc background rate of counter (cpm) using absorber Configuration. 2.22 dpm /pCi V = volume or weight of sample analyzed BA = background addition from Sr-90 and ingrowth of Y-90 Bc 0.01 6(K) +((K) Ey/abs)(IGy_so) Ys = chemical yield of strontium DFsr-89 = decay factor from the mid collection date to the counting date for Sr-89 K = (NAt-Bc)y_ 9 o/(Ey_so IFy-so DFy_9 oYj) DFy-so = the decay factor for Y-90 from the "milk" time to the mid count time Ey-go = efficiency of the counter for Y-90 93

IFygo = ingrowth factor for Y-90 from scavenge to time to milkingtime IGy-go = the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 0.016 = the efficiency of measuring Sr-90 through a No. 6 absorber EY/abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm) Yi = chemical yield of yttrium Y2 = chemical yield of strontium DF = decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency of the counter for Y-90 IF = ingrowth factor for Y-90 from scavenge time to the radiochemical milking time 94

ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode. Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/l: RESULT = (N/At-B)/(2.22 V Y DF) TWO SIGMA ERROR = 2((N/At+B) /At)" 2/(2.22 E V Y DF) LLD = 4.66(B/At)" 2/(2.22 E V Y DF) Where N = total counts from sample At = counting time for sample (min) B background rate of counter 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efficiency of the counter for 1-13 1, corrected for self absorption effects by the formula E = Es(exp-0.0061M)/(exp-0.006lMs) Es = efficiency of the counter determined from an 1-131 standard mount Ms = mass of Pdl2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg 95

GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded high purity germanium (HPGe) detector coupled to a personal computer (PC)-based data acquisition system which performs pulse height analysis. Dried Solids Other Than Soil and Sediments A large quantity of the sample is dried at a low temperature, less than 100°C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis. Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 100 minutes with a shield HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis. Soil and Sediments Soils and sediments are dried at a low temperature, less than 100°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded HPGe detector coupled to a PC-computer-based data acquisition system which performs pulse height and analysis. Charcoal Cartridges (Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a HPGe detector and up to four on the side of the HPGe detector. Each HPGe detector is calibrated for both positions. The detection limit for 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector. Air Particulates The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis. A PC software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. 96

Calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume of pCi/mass: RESULT TWO SIGMA ERROR LLD where: S B t 2.22 E V F DF = (s-b)/(2.22 T E V F DF) 2(S+B)" 2/(2.22 t E V F DF) = 4.66 (B)" 2/(2.22 t E V F DF) = Area, in counts, of sample peak and background (region of spectrum of interest.) = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on peak. = length of time in minutes the sample was counted = dpm/pCi = detector efficiency for energy of interest and geometry of sample = sample aliquot size (liters, cubic meters, kilograms, or grams) fractional gamma abundance (specific for each emitted gamma) = decay factor from the mid-collection date to the counting date 97

ENVIRONMENTAL DOSIMETRY ICN Worldwide Dosimetry Services (ICN) uses a Harshaw/Bicron NE 210 thermoluminescent dosimeter (TLD). The TLD is composed of 2 CaF and 2 LiF sensitive elements. These materials have a high light output, negligible thermally induced fading and, and negligible self-dosing. The energy response curve and all other features satisfy NRC Reg. Guide 4.13. Transit doses are accounted are accounted for by using separate TLD's. A Harshaw/Bicron NE 8800 Automatic TLD Reader processes the TLD's at ICN after each filed exposure. The 8800 reader heats each element by passing hot Nitrogen gas over the sensitive element causing the TLD to emit light. The reader records the light output. The ICN Environmental Algorithm and members of the ICN Technical staff evaluate and investigate any irregularities before reporting to the client. The average and 2-sigma error are calculated for each station in the following manner: N ~~~~~~~~~~~~~~~~2 365.25 ~ = ) (_ Eavg_ ) Emo== 2a = 2-1 =' = 12ADN 2u2N-1 Where: Emon = Element Average/Month Ri = Element Result N = Number of Elements D = Total days in field 98

APPENDIX E INTERLABORATORY COMPARISON PROGRAM 99

INTERLABORA4TOR Y COMPARISIONPROGRAM A review of the 1999 Interlaboratory Comparison Program verified that Teledyne Brown Engineering (TBE) did not perform iodine-131, strontium-89, strontium-90, or gamma analyses on milk samples. TBE presumed, erroneously, that we were meeting client contract requirements. The 2001 Interlaboratory Comparison Program includes all contractually required analyses with the exception of I-131 in water, strontium-89 and strontium-90 in milk as described below. These has been included in the TBE blanket purchase order for Analytics and Environmental Resource Associates (ERA) for the year 2002. The US Environmental Protection Agency (EPA) discontinued their Interlaboratory Comparison Program in December 1998. However, on May 1, 2001, accreditation was granted to Environmental Resource Associates' RadCheM Proficiency Testing Program to complete the process of replacing the USEPA EMSL-LV Nuclear Radiation Assessment Division program. Although TBE Environmental Services participated in the EPA program, there was a lapse in time between the period of the closure of the EPA program and the commencement of the ERA program. We have objective evidence that TBE participates in these commercial ICP programs as well as documentation that we are continuing to do so. For the year 2001 and forward, the determinations in TBE's ICP program are equivalent to or exceed the NRC requirements. This has been verified for all the Nuclear Utility clients. However, in order to ensure this information has been communicated to all the utilities, a copy of this letter is being included in all 2001 annual reports for all utility clients. The U.S. Department of Energy (DOE) Environmental Measurement Laboratory (EML) provides a comprehensive and extensive intercomparison/performance evaluation program. TBE participates in this program twice annually. The program offers an extensive and industry accepted matrix and radionuclide representation. The results supporting our first quarter 2001 strontium-89, strontium-90, and iodine-131 in water was obtained from the EML program based on the receipt schedule of the samples as compared to the start up of the TBE Knoxville laboratory in early 2001. The National Institute of Standards and Technology (NIST) is the approval authority for laboratory providers participating in Intercomparison Study Programs; however, at this time, there are no approved laboratories for environmental and/or radiochemical isotope analyses. Trending graphs are provided in this section for the Analytics, ERA, and DOE/EML Program when there were at least two data points to plot. Exceptions 2001 During 2001, several Interlaboratory Comparison Program (ICP) analyses were not performed as required by the ODCM. This omission was found during the last half of 2001. The omitted analyses occurred during the first half of 2001 while TBE facilities were in transition to the Knoxville, TN facility. The omissions follow.

• Water analysis for iodine-131
• Milk analysis for strontium-89
• Milk analysis for strontium-90 To prevent recurrence, Dominion initiated internal commitment tracking by Radiological Protection Department to verify status and compliance by TBE on a quarterly basis. This tracking identified the above omission. TBE now has blanket purchase orders with Analytics and ERA to eliminate the recurrence of this anomaly.

100

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d) E2584-93 Milk 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Al 4428-55 Water Sr-89 Sr-90 A14429-55 Water Gr-Alpha uCi/mL 2.50E-03 2.95E-03 uCi/mL 2.OOE-04 2.27E-04 uCi/mL 1.70E-04 1.45E-04 A14434-55 Water Fe-55 uCi/mL 2.40E-04 2.53E-04 2707 2708 2709 Charcoal Charcoal Charcoal 1-131 1-131 1-131 pci pci pci 104.5 84.8 99.6 81 72 92 August, 2001 August, 2001 August, 2001 E2755-396 Milk Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-I 34 Cs-1 37 Ce-141 E2757-396 AP Filter Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E2756A-396 Charcoal 1-131 All footnotes for this chart appear on page 3 of 3. 101 March, 2001 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 75 166 433 212 165 81 172 151 314 254 77 162 418 223 176 82 175 146 322 254 May, 2001 0.97 1.03 1.04 0.95 0.94 0.99 0.98 1.03 0.98 1 A A A A A A A A A A June, 2001 0.85 0.88 1.17 0.95 1.29 1.18 1.08 A A A A W A A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pci pci pci pci pci pci pci pci pci pci 131 68 53 134 172 76 141 126 72 79 100 109 140 72 161 51 200 148 87 124 68 50 132 162 86 128 120 76 74 90 125 116 66 134 49 158 128 93 1.06 1.00 1.06 1.02 1.06 0.88 1.10 1.05 0.95 1.07 1.11 0.87 1.21 1.09 1.20 1.04 1.27 1.16 0.94 A A A A A A A A A A A A w A A A W A A

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d) September, 2001 A14734-148 September, 2001 A14735-148 Liquid Sr-89 Total uCi 1.30E-03 Sr-90 Total uCi 1.OOE-04 1.55E-03 1.12E-04 Gas Xe-1 33 Total uCi 0.606 0.585 Kr-85 Total uCi 8.53 8.42 September, 2001 A14736-148 Charcoal 1-131 Total uCi 0.483 0.495 September, 2001 A14737-148 Air Filter Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 September, 2001 A14738-148 Liquid Gr-Alpha Total uCi 5.80E-04 4.67E-04 September, 2001 A14286-148 September, 2001 E2772-396 Liquid Gr-Alpha uCi/cc 1.70E-04 1.45E-04 H-3 uCi/cc 2.92E-03 1.77E-03 Milk 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 September, 2001 E2773-396 Charcoal 1-131 All footnotes for this chart appear on page 3 of 3. pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pci 100 126 349 147 321 190 205 85 246 261 68.6 91 121 366 160 319 177 205 86 254 266 67 102 0.84 0.89 1.04 1.01 A A A A 0.98 A Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi 4.99E-02 1.68E-01 2.47E-02 5.18E-02 4.60E-02 3.96E-02 2.99E-02 5.22E-02 4.71 E-02 5.25E-02 1.85E-01 2.97E-02 5.73E-02 4.75E-02 4.02E-02 2.92E-02 5.12E-02 4.83E-02 0.95 0.91 0.83 0.90 0.97 0.99 1.02 1.02 0.98 A A A A A A A A A 1.24 A 1.17 1.65 1.10 1.04 0.95 0.92 1.01 1.07 1.00 0.99 0.98 0.98 A A A A A A A A A A A A 1.02 A

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d) September, 2001 E2774-396 December, 2001 December, 2001 E2980-396 E-2981 -396 Air Filter Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Milk Sr-89 Sr-90 Fe-55 Milk 1-131 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 December, 2001 E-2983-396 Air Filter Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 December, 2001 E-2982-396 Charcoal 1-131 pci 89 92 0.93 A (a) Teledyne Brown Engineering reported result. (b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to Analytics results. (d) Analytics evaluation: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20. W=Acceptable with waming. Reported result falls within ratio limits of 0. 70-0.79 and 1.21-1.30. 103 1.02 1.03 0.88 1.14 1.08 1.17 1.22 1.25 1.05 0.96 1.27 1.09 A A A A A A w w A A w A pci pci pci pci pci pci pci pci pci pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pci pci pci pci pci pci pci pci pci 118 362 135 350 184 230 100 305 267 75 44 108 50 352 468 173 312 92 148 101 192 322 185 190 74 163 46 80 57 119 165 116 351 153 307 170 197 82 244 255 85 59 99 61 379 497 199 318 90 149 102 206 353 181 237 95 152 43 71 49 99 169 0.82 0.93 0.94 0.87 0.98 1.02 0.99 0.99 0.93 0.93 A A A A A A A A A A 1.02 0.80 0.78 1.07 1.07 1.13 1.16 1.2 0.98 A A w A A A A A A

DOEIEML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1) Identification Reported Known Ratio (c) MonthNear Number Media Nuclide Units Value (a) Value (b) TBE/EML Evaluation (d) March, 2001 March, 2001 May, 2001 June, 2001 June, 2001 QAP 103 Air Filter Mn-54 Co-60 Cs-I 34 Cs-1 37 Gr-Alpha Gr-Beta Sr-90 QAP 103 Water Co-60 Cs-I 37 Gr-Alpha Gr-Beta Sr-90 H-3 QAP 2009 Air Filters Mn-54 Co-57 Co-60 Cs-1 37 Gr-Alpha Gr-Beta Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter QAP 2009 Water Co-60 Bq/L Cs-1 37 Bq/L September, 2001 QAP 0109 September, 2001 QAP 0109 Air Filters Mn-54 Co-60 Cs-1 34 Cs-I 37 Gr-Alpha Gr-Beta Sr-90 Water Co-60 Cs-1 37 Gr-Alpha Gr-Beta Sr-90 H-3 Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L (a) Teledyne Brown Engineerin reported result. (b) The DOE/EML known value is equal to 100% of the parameterpresent in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to DOE/EML results. (d) DOE/EML evaluation: A=acceptable, W=acceptable with waming, N=not acceptable. 104 1.07 1.00 0.92 1.09 0.84 0.88 1.05 1.02 1.04 0.84 0.93 1.04 0.77 1.15 1.05 1.04 1.11 0.98 1.18 1.03 1.03 1.197 1.074 0.981 1.216 1.011 0.94 0.735 A A A A A W A A A A A A W A A A A A A A A A A A W A A W 6.96 19.4 2.59 9.52 3.33 2.26 7.46 100.3 75.8 1600 1200 4.57 61.0 49.5 15.2 8.79 8.26 2.31 1.79 75.7 69.3 97.1 18.8 12.7 20.8 5.42 12.0 2.56 207.3 47.7 1333.0 8533.0 4.76 212.3 6.52 19.44 2.83 8.76 3.97 2.58 7.1 98.2 73 1900 1297 4.4 79.3 43.2 14.5 8.43 7.41 2.35 1.52 73.7 67.0 81.15 17.5 12.95 17.1 5.362 12.77 3.481 209.0 45.133 1150.0 7970.0 3.729 207.0 0.992 1.057 1.159 1.071 1.276 1.026 A A W A W A

ERA* ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1) Identification Reported Known Ratio (c) Month/Year Number Media Nuclide Units Value (a) Value (b) TBE/EML Evaluation (d) February, 2001 September, 2001 August, 2001 September, 2001 August, 2001 Rad-29 Water Co-60 Cs-1 34 Cs-137 Rad-38 Water Ba-133 Co-60 Cs-1 34 Cs-1 37 Zn-65 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L Rad-39 Water Total U pCi/L Ra-226 pCi/L Rad-40 Water Sr-89 Sr-90 pCi/L pCi/L Rad-41 Water Gr-Alpha pCi/L Gr-Beta pCi/L September, 2001 December, 2001 Rad-42 Water H-3 12130109 Water 1-131 pCi/L 2370 pCi/L 3.77 All ERA samples are water. (a) Teledyne Brown Engineering reported result. (b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to ERA results. (d) ERA evaluation: A=acceptable. Reported result falls within the Waming Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Waming Limit. 105 95.5 60.5 48 35.5 47.6 15.5 206 35.4 60.3 14.7 26.4 28.2 15.2 52.0 91.1 59.8 45 36 46.8 15.9 197 36.2 52.9 15.4 31.2 25.9 17.8 53.0 1.05 1.01 1.07 0.99 1.02 0.97 1.05 0.98 1.14 0.95 0.85 1.09 0.85 0.98 A A A A A A A A A A A A A A 2730 4.38 0.87 A 0.86 A

106 1,131 IN MILK 120 100 9 80 a Iu. 60 3 40 240 20 Jan-S8 Ju998 Doe9-Jun99 Dec-99 Jun-00 Dec-00 Jun01 Dec-01

• TSE EAnalics I Ce-141 IN MILK 1000 800 600 400 S

200 8 a 6 ~ ~~~~ Ema Jao98 Ju1-98 De-98 Jun99 De-99 Jun-o De-0 Jun01 Dec-01 l*TBE *Analptcsl

Gs-134 IN MILK O Ja-98 JUt98 Dec98 Jun-99 De-99 Jun-0 Dec,"O Jlnr01 De.-1 I*TBE

• Analytis I

t 107 C 17-300 ISO 75 p II a a Cs-137 IN MILK 350 250 200 zso a V a 100 a a 50 a Ja,v98 .UI-98 Deo-98 .Jiz99 Dec-99 JU140 D00C JwOl Dec-01

• +TBE EAnalCil Mn-S4 IN MILK 240 -

200 160 W U 12D 5 80 a 40 Jan-98 Ju1,98 Dec98 Jun99 De-99 Jur-o Dec-0C Ju-01 Dec-01

• TSE flAnalytiCSl

108 C-v.; Sr-9O IN MILK 60 40 20 a 20 Jul-99 Jn-99 Jul-9 Jan-0 Jul-00 Jannl JUl1 Jan-02

• OTBE EAnalytcsl Zn-65 IN MILK 350 300 U

2505 200; 100 s0 Jan98 Jul-93 De-sB Jun99 De,9 Ju0oo Decc-0 Jun-1 Dengl l*TBE EAMny Is Co-S0 IN MILK 400 350 I-300 4 250 200 150 50I 9O Jdt-98 Dec-98 Jun-O Dec-99 Jun-00 De-00 Jut-1 Dec-1

• TBE EAnalytcsI

Co-58 In Milk 109 C1l' 200 180 3 I60 140 120 INU 60 U 40 20 0 Oct-00 Jan-01 May-01 AugO1 Deo-01

• TBE EAnalytics t

Mamh, 2000 - Inconed rnming of eimbon coiumn resulted in Im esut. 110 Sr-89 IN MILK 100 - so U 40 20 0 De099 Mar-00 Judo Od400 Feb-01 Jugl Sep-01 Jan02 l*TBE EAnalytiCS

500 400 300 200 100 0 Ce-141 IN FILTERS 6D0 U 9 ~~a Dec98 Ju-99 Dec-99 hz-00 De-00 Jun-01 DOeo-JD1-98 hi-98 ITBE rAsialyry sI ill Cr41 IN FILTERS 900 700 600 500 4DO 3000 200 . I a i 100 a - 0II JDn98 JulD'O Dec-98 Ju-99 Drec99 SnDD DD Jun-01 Deo-0

• TBE EAnalytsl Cs-134 IN FILTERS 180 160 U

140 120 - soo 60 49 0 20 D I I I Jan9O8 iJi-Dec-9 JSz.D99 Dec-9 Jun0D Deo-DD An-01 Dec0 l*TBE EAnalytisI

Fe-S9 IN FILTERS .00 SO 60 40 20 00 4 60 40 a I 0 Ja*-Oe se Dee-8 Jim-99 Dec-9 JIA-C0 DJ0 -1 Dec ol I*TE EAnalyicsI 112 Cs-137 IN FILTERS 450 300 150 a a3 Ii a-- 0 Ja-98 JIM-s Dc98 Ju-99 De99 Jun-0 Dee-0C Jun-01 Decr01 I *TBE

• AnalyLcs t

Mn-54 IN FILTERS 180 120 0 40 5 so. 0 ~ Jan-9s Je Dec-O Jun99 Dec-9 Jn-o00 Dec-00 Jun-Cl D01 I *TBE EAnalyksml 2 I

Zn45 IN FILTERS 300 200p 150 50U 0 Ja,-8 Ji98 DecS Ju-99 Dee-99 Jw-00 Dec00 Jumn-U Decl

• TBE EAnalytiCS Co-60 IN FILTERS 300 250 p

200 150-U IO 100 i 50 JanSS8 Jtd-98 Dec-98 Jl-99J Dec-99 Jun0 Dec-00 Ju-l Dec01

• TBE UAnalytics Co-S8 IN FILTERS 2D0 180 140 120 100 120 0

Mar-00 Jun40 Oct4-0 Jan1 Ap-01 Ju141 Nov-01 Feb-02 13TBE EAnalyCS 113

i 114 H-3 IN WATER 1000 100 10 0.1 0.01 Je9 is-9O Dec-s J99 Dec-99 Ju-oo Dec-oO.fo-1 Decoo l*TBE mAnalytics Sr-89 IN WATER 1000 100 9 10 I O.1 0.01 0.001 I Jans JIs Dec-s Ji99 Dec99 Jim-O Dec-00 Ju1-01 DecO1 l*TBE EAnalytics I Sr-90 IN WATER 1000 1oo 10 i 0.1 0.01 0.001 0.0001 M.OM, I Jan-s8 Ju98 Deo-9D Jun-99 De-99 Jun-oo De-00 Jun-l Dee-1 I*TBE AnaIytcsl

GROSS ALPHA IN WATER 115 Clv 1000 10 0.1 a A 0.00001 Ag-99 Feb-00 Aug-00 Jan01 Jul01 De-01 I*TBE EAnoYfisl t

1-131 IN CHARCOAL CARTRIDGE 1000 1 o.1 I I Jan-0 May-40 Aug-0 NWv0-Feb-01 Ju01 Sep-01 Dec01 I*TBE EAnaltosl 116

117 0 2-2 Ba-133 IN WATER 120 100 60 40 n 20 J400 May-O0 Aug-0 Nov-0 Feb-01 Jw-0o Sep-01 Dec01

• TBE
• ERA Co-60 IN WATER 120 100 80 60 40 a

20 O-Oct-99 Jan-w0 May-00 kg-00 Na-OO Feb-01 Jw41 Sep-DI Dec-1

• TBE *ERAl Cs-134 IN WATER 70 6050 40 30 20-10 -

Od-99 Jan-w0 May-40 Aug-00 Nov-O Feb-01 Jw41l Sep-01 Dec-01 r.TBE UERAH

Febmray, 2001-Aj,aly errr or equipment eUre. Zn-SO IN WATER 40 35 30 25 20 JaDem Feb-01 Apr-01 Ju-cl JuFe4l Sep-1 Nov-01 De l-TBE *ERAl [18 Sr-89 IN WATER 35 30U 254 20 1 5 IC Dec-99 May-CO Oct-Go Feb-01 Jte-01 DeeOl

• TBE E ERA]

118 C%Z3 CS-137 IN WATER 250 200 ISO too 50 a O-Oct-s Jan40 May-40 Aug-q0 Nov4-0 Feb-41 Jun-ol Sep41 Dec4l I*TBE

• ERA]

I I-"

• tt A I I

e GROSS ALPHA IN WATER 100 80 a 60 40 20 0I Dec-99 May-o Oct-DO Fe1,01 Jul-0 Dec-0 Febarury, 2001 - AnalWs errr or equipment falieur. 119 Sr-90 IN WATER 40-30 a 20 10 0 Dec-99 May-00 Od400 Feb-1 JuI4l Dec-01 itcE EiAa GROSS BETA IN WATER bO 50 I 40 30 20 a 10 Dec99 May.00 oc-00 Feb-01 Ju1,1 Dec01 I*TBE *ERAl

120 H-3 IN WATER a ¶000 too 10 Jan00 Jul-10 Dec-Oo Jun-41 Deo41 l*TBE *ERAl 1-131 IN WATER S U 4 2 I 0 Jan-00 Ju140 Dec-00 Jun-01 Dec4l

• TSE.

ERAl

Mn-54 IN AIR PARTICULATES 121 100 80 U 60 40 20 a 0 I Feb-01 Jul-01 Dec-01 l*TBE EDOEIEML Co-S0 IN AIR PARTICULATES 30 25 20 15 10 i 5 Feb-01 Jul-01 DeC 01

• TBE EDOE/EMLl Cs-134 IN AIR PARTICULATES 10 8

6 4 2 oI Feb-01 Jul01 Dec-01

• TB8E EDOEBEMLl

Cs-137 IN AIR PARTICULATES 122 CVLI 30 25 20 15 10 0 5 0 Feb-01 Jul-01 Dec1 1 r*TBE EDOE/EMLl GROSS ALPHA IN AIR PARTICULATES 10 8 6 a 4 -U 4 2 Feb-01 Jul01 De-01 r*TBE EDOEIEML GROSS BETA IN AIR PARTICULATES 20 16 12 9 4 U a Feb-01 Ju-01 Dec-01 l*TBE *DOEJEML l

Sr-90 IN AIR PARTICULATES 123 I0 a a 6 4 2 Feb-01 Jul-01 Dec-Cl

• TBE EDOEIEM t

Co-57 IN AIR PARTICULATES 20 16 I 12 8 4 0 Feb-Cl Jul-01 Dec-Cl TBE -- 11-DOESEML

Co-S IN WATER 124 cz9 250 200 a 150 100 a 50 0 Feb-01 Jul-01 De;13

• TE MEOOEIEMLl Cs-137 IN WATER 100 90 80 70 60 50 40 30 20 10 0II Feb-01 Jul-01 DecOl
• GTBE EDOEIEMLl GROSS ALPHA IN WATER 3000 2600 2200 1800 1400 0

1000 I Feb-01 Jul-1 DecO1 F*TBE EDWEIEML1

GROSS BETA IN WATER 125 C30 9000 7000 6000 5000 4000 3000 2000 0 Feb-01 Jul-14 Dec4l

• TBE EDOEIEML l Sr-90 IN WATER 10 9

S 7 6-5. 3 2 1 0* Feb-01 Jul-01 Dec-01 F*TBE EDaEJEML H-3 IN WATER 250 200 p 150 100 50 50 50 I Feb-01 Jul-01 Drc-1

• TE UDOEIEMLl}}