ML011240370

Independent Spent Fuel Storage Installation Annual Radiological Environmental Operating Report

ML011240370
Person / Time
Site:	North Anna
Issue date:	04/27/2001
From:	Heacock D Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, -RFPFR, 01-243
Download: ML011240370 (115)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 April 27, 2001 United States Nuclear Regulatory Commission Serial No.01-243 Attention: Document Control Desk NAPS: MPW Washington, D.C. 20555 Docket Nos. 50-338 50-339 72-16 License Nos. NPF-4 NPF-7 SNM-2507 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS I & 2 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 Ann Independent Spent Fuel Storage Installation Technical Specification 5.5.2b, require the submittal of an Annual Radiological Environmental Operating Report. Accordingly, enclosed is the Radiological Environmental Operating Report for the reporting period of January 1, 2000 through December 31, 2001. The report is not complete due to the vendor, Teledyne Brown Engineering, relocating their laboratory from New Jersey to Tennessee. Information not provided in this report includes:

1) 3 rd and 4 th quarter gamma analyses of air particulate composites

2) Second half tritium results in precipitation

3) 09/20/00 tritium results in precipitation

4) 3 rd and 4 th quarter tritium results in river water

5) 08/07/00 Sr-89/90 results in sediment/silt

6) Sr-89/90 results for 3rd and 4th quarter milk composites

7) Ground water tritium graph

8) Surface water tritium graph The 2000 Annual Radiological Environmental Operating Report will be updated following receipt of final analyses from the vendor.

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:

1. The 2000 Annual Radiological Environmental Operating Report will be updated following receipt of final analyses from the vendor.

cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION Radiological Environmental Monitoring Program January 1, 2000 to December 31, 2000 Prepared by DOMINION VIRGINIA POWER and TELEDYNE BROWN ENVIRONMENTAL SERVICES

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2000 to December 31, 2000 Prepared by:

f James B. Breeden Siupe.rvisor Radiological Analysis and Materia 1 Control Reviewed by Erich W. DreySF Supervisor Health Physics Technical Services Approved by:

w- *an H. Stafford Manager Radiological Protection 2

Table of Contents Section Title Page Pre fa c e ................................................................................................................................... 6 Executive Sum m ary ....................................................................................................... 7 I. Introduction ....................................................................................................... 9 II. Sam pling and Analysis Program ........................................................................ 12 III. Program Exceptions ............................................................................................. 28 IV . Sum mary and D iscussion of 2000 Analytical Results ........................................ 31 A. A irborne Exposure Pathway ..................................................................... 32

1. Air Iodine/A ir Particulates ............................................................... 32

2. Precipitation ...................................................................................... 34

3. Soil ................................................................................................... 34 B. W aterborne Exposure Pathw ay ................................................................. 34

1. Ground/W ell W ater ........................................................................... 34

2. River W ater ...................................................................................... 35

3. W ell W ater ........................................................................................ 35 C. Aquatic Exposure Pathw ay ........................................................................ 35

1. Sedim ent/Silt .................................................................................... 35

2. Shoreline Soil .................................................................................... 36 D. Ingestion Exposure Pathway ...................................................................... 40

1. Milk ................................................................................................. 40

2. Fish .................................................................................................... 40

3. Food/Vegetation ............................................................................... 40 E. D irect Radiation Exposure Pathway .......................................................... 41

1. TLD Dosim eters ............................................................................... 41 V. Conclusion .............................................................................................................. 43 3

Table of Contents (Cont)

Section Title Page VI. R eferen ces ............................................................................................................... 47 VII. Appendices ........................................................................................................ 49 Appendix A - Radiological Environm ental M onitoring ..................................... 50 Program Annual Summary Tables - 2000 Appendix B - Data Tables ................................................................................. 57 Appendix C - Land Use Census -2000 .............................................................. 81 Appendix D - Synopsis of Analytical Procedures .............................................. 85 Appendix E - Interlaboratory Comparison Program .......................................... 97 List of Trending Graphs

1. Gross Beta in Air Particulates ............................................................................. 33

2. Tritium in River W ater ........................................................................................ 33

3. Tritium in W ell W ater ........................................................................................ 37

4. Cobalt-58 in Sediment Silt .................................................................................. 37

5. Cobalt-60 in Sediment Silt .................................................................................. 38

6. Cesium-134 in Sediment Silt ............................................................................ 38

7. Cesium-137 in Sediment Silt ............................................................................. 39

8. Cobalt-58 in Fish ................................................................................................. 39

9. Cobalt-60 in Fish ............................................................................................... 42

10. Environm ental Radiation-TLDs ........................................................................ 42 4

List of Tables Table Page

1. Radiological Sampling Station Distance and Direction fro m U n it I .............................................................................................................. 14

2. North Anna Power Station Sample Analysis Program ....................................... 25

3. REMP Exceptions for Scheduled Sampling and Analysis during 2000 ............ 29 Appendix B Tables B-1 Iodine- 131 Concentrations in Filtered Air ........................ . 58 B-2 Concentrations of Gross Beta in Air Particulates .................... ...... 60 B-3 Gamma Emitter and Strontium Concentrations in Air Particulates ........ ...... 64 B-4 Gross Beta, Tritium and Gamma Emitter Concentrations in Precipitation .... ...... 67 B-5 Gamma Emitter and Strontium Concentrations in Soil ................ ...... 68 B-6 Gamma Emitter, Strontium and Tritium Concentrations in Ground/Well Water ...... 69 B-7 Gamma Emitter, Strontium and Tritium Concentrations in River Water ..... ...... 69 B-8 Gamma Emitter, Strontium and Tritium Concentrations in Surface Water ... ...... 70 B-9 Gamma Emitter and Strontium Concentrations in Sediment Silt .......... ...... 71 B-10 Gamma Emitter and Strontium Concentrations in Shoreline Soil ......... ...... 72 B-1I Gamma Emitter and Strontium Concentrations in Milk ................ ...... 73 B- 12 Gamma Emitter Concentrations in Fish .......................... ...... 75 B-13 Gamma Emitter Concentrations in Food/Vegetation ................. ...... 76 B-14 Direct Radiation Measurements - Quarterly & Annual TLD Results ....... ...... 78 B-15 Direct Radiation Measurements - Sector Quarterly TLD Results ......... ...... 79 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 2000 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2000 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 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 Chernobyl accident, or natural variation.

Teledyne Brown Engineering 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 as a percent of the reporting level.

Analytical results are divided into five categories based on exposure pathways: Airborne, waterborne, aquatic, ingestion, and direct radiation. Each of these pathways is described below:

• The airborne exposure pathway includes airborne iodine, airborne particulate, precipitation, and soil samples. The overall 2000 airborne results were very similar to previous years and to 7

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 2000.

" The waterborne exposure pathways 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 2000 was 3000 pCi/liter which was 10% of the reporting level for a water sample. The 1999 tritium level was 3975 pCi/liter. The preoperational level was 150 pCi/liter and has risen since 1997, though it has remained relatively consistent since 1986. Naturally occurring potassium-40 was measured in one of twenty-four samples at 39.8 pCi/liter. 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 3100 pCi/liter. The average tritium level in 1999 was 3350 pCi/liter.

Naturally occurring potassium-40 was measure in three out of twelve samples at an average concentration of 454 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 one of two samples at 167 pCi/kg (dry).

" The ingestion exposure pathway includes milk, fish, and food/vegetation samples. Iodine-131 was not detected in any 2000 milk samples. Although cesium- 137 has been detected in the past, it was not detected in 2000 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 2000 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator repairs and better liquid waste processing, however, 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.

During 2000, 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 2000 would be approximately 0.38 millirem. For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes 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.

8

I. INTRODUCTION 9

DOMINION VIRGINIA POWER COMPANY NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM I. INTRODUCTION The operational radiological environmental monitoring program conducted for 2000 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, 2000 through December 31, 2000 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 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. These 10

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 2000 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.

11

II. SAMPLING AND ANALYSIS PROGRAM 12

SAMPLING AND ANALYSIS PROGRAM A. Sampling Program

1. Table I summarizes the sampling program for environmental monitoring stations for North Anna Power Station during 2000. The relative location of these stations is shown.

2. For routine TLD measurements, two dosimeters made of CaSO 4 :Dy in a teflon card 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 located in Knoxville, TN.

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

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TABLE 1 (Page 1 of4)

NORTH ANNA POWER STATION - 2000 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental NAPS Sewage 01 0.20 NE 420 Quarterly Thermoluminescent Treatment Plant & Annually Dosimetry (TLD) Fredericks Hall 02 5.30 SSW 225° Quarterly

& Annually Mineral, Va 03 7.10 WSW 2430 Quarterly

& Annually Wares Crossroads 04 5.10 WNW 2870 Quarterly

& Annually Route 752 05 4.20 NNE 200 Quarterly

& Annually Sturgeon's Creek 05A 3.20 N 110 Quarterly Marina & Annually Levy, VA 06 4.70 ESE 1150 Quarterly

& Annually Bumpass, VA 07 7.30 SSE 1670 Quarterly

& Annually End of Route 685 21 1.00 WNW 3010 Quarterly

& Annually Route 700 22 1.00 WSW 2420 Quarterly

& Annually "Aspen Hills" 23 0.93 SSE 1580 Quarterly

& Annually Orange, VA 24 22.00 NW 3250 Quarterly Control

& Annually Bearing Cooling N-1/33 0.06 N 100 Quarterly Tower Sturgeon's Creek N-2/34 3.20 N 110 Quarterly Marina Parking Lot "C" NNE-3/35 0.24 NNE 320 Quarterly (on-site)

Good Hope Church NNE-4/36 4.96 NNE 250 Quarterly Parking Lot "B" NE-5/37 0.20 NE 420 Quarterly Lake Anna Marina NE-6/38 1.46 NE 340 Quarterly 0.36 ENE 740 Quarterly Weather Tower Fence ENE-7/39 Route 689 ENE-8/40 2.43 ENE 650 Quarterly Near Training E-9/41 0.30 E 910 Quarterly Facility 14

TABLE I (Page 2 of 4)

NORTH ANNA POWER STATION - 2000 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental "Morning Glory Hill" E-10/42 2.85 E 930 Quarterly Thermoluminescent Island Dike ESE- 11/43 0.12 ESE 1030 Quarterly Dosimetry (TLD) Route 622 ESE- 12/44 4.70 ESE 1150 Quarterly DVP Biology Lab SE-13/45 0.75 SE 1380 Quarterly Route 701 SE-14/46 5.88 SE 1370 Quarterly (Dam Entrance)

"Aspen Hills" SSE-15/47 0.93 SSE 1580 Quarterly Elk Creek SSE-16/48 2.33 SSE 1650 Quarterly NAPS Access Rd. S-17/49 0.47 S 1730 Quarterly Elk Creek Church S-18/50 1.55 S 1780 Quarterly NAPS Access Rd. SSW-19/51 0.42 SSW 1970 Quarterly Route 618 SSW-20/52 5.30 SSW 2050 Quarterly 500kv Tower SW-21/53 0.6 SW 2180 Quarterly Route 700 SW-22/54 4.36 SW 2320 Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 2370 Quarterly Route 700 WSW-24/56 1.00 WSW 2420 Quarterly (Exclusion Boundary)

South Gate Switchyard W-25/57 0.32 W 2790 Quarterly Route 685 W-26/58 1.55 W 2740 Quarterly End of Route 685 WNW-27/59 1.00 WNW 3010 Quarterly Route 685 *,NW-28/60 1.40 WNW 3030 Quarterly North Gate NW-29/61 0.45 NW 3210 Quarterly Construction Side Laydown Area Lake Anna NW-30/62 2.54 NW 3 190 Quarterly Campground

1. I/#2 Intake NNW-3 1/63 0.07 NNW 3490 Quarterly NNW 3440 Quarterly Route 208 NNW-32/64 3.43 Bumpass Post Office C-1/2 7.30 SSE 1670 Quarterly Control Orange, VA C-3/4 22.00 NW 3250 Quarterly Control Mineral, VA C-5/6 7.10 WSW 2430 Quarterly Control Louisa, VA C-7/8 11.54 WSW 2570 Quarterly Control 15

TABLE I (Page 3 of 4)

NORTH ANNA POWER STATION - 2000 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Airborne Particulate NAPS Sewage 01 0.20 NE 420 Weekly and Radioiodine Treatment Plant Fredericks Hall 02 5.30 SSW 2050 Weekly Mineral, VA 03 7.10 WSW 2430 Weekly Wares Crossroads 04 5.10 WNW 2870 Weekly Route 752 05 4.20 NNE 200 Weekly Sturgeon's Creek Marina 05A 3.20 N 110 Weekly Levy, VA 06 4.70 ESE 1150 Weekly Bumpass, VA 07 7.30 SSE 1670 Weekly End of Route 685 21 1.00 WNW 3010 Weekly Route 700 22 1.00 WSW 2420 Weekly "Aspen Hills" 23 0.93 SSE 1580 Weekly Orange, VA 24 22.00 NW 3250 Weekly Control Surface Water Waste Heat 08 1.10 SSE 1480 Monthly Treatment Facility (Second Cooling Lagoon)

• Lake Anna (upstream) 09 2.20 NW 3200 Monthly Control (Route 208 Bridge)

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

River Water North Anna River 11 5.80 SE 1280 Monthly (downstream)

Ground Water Biology Lab O0A 0.75 SE 1380 Quarterly (Well Water)

Precipitation Biology Lab OIA 0.75 SE 1380 Monthly Aquatic Sediment Waste Heat 08 1.10 SSE 1480 Semi-Annually Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 WNW 3200 Semi-Annually Control (Route 669 Bridge)

North Anna River 11 5.80 SSE 1280 Semi-Annually (Downstream)

Shoreline Soil Waste Heat 08** 1.10 SSE 1480 Semi-Annually Treatment Facility (Second Cooling Lagoon) 16

• 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.

TABLE I (Page 4 of 4)

NORTH AN-NA POWER STATION - 2000 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Soil NAPS Sewage 01 0.20 NE 42' Once/3 years Treatment Plant Fredericks Hall 02 5.30 SSW 2050 Once/3 years Mineral, VA 03 7.10 WSW 2430 Once/3 years Wares Crossroads 04 5.10 WN W 287° Once/3 years Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek 05A 3.20 N I IC Once/3 years Marina Levy, VA 06 4.70 ESE Once!3 years Bumpass, VA 07 7.30 SSE 1670 Once/3 years End of Route 685 21 1.00 WN1W 3010 Once/3 years Route 700 22 1.00 WSW 2420 Once/3 years (Exclusion Boundary)

"Aspen Hills" 23 0.93 SSE 1580 Once/3 years Orange, VA 24 22.00 NW 3250 Once/3 years Control Milk Holladay Dairy 12 8.30 NW 3100 Monthly (R.C. Goodwin)

Terrell's Dairy 13 5.60 SSW 2050 Monthly (Fredericks Hall)

Fish Waste Heat 08 1.10 SSE 1480 Semi-Annually Treatment Facility (Second Cooling Lagoon)

Lake Orange 25 16.5 NW 3120 Semi-Annually Control Food Products Route 713 14 1.20 NE 430 Monthly if available (Broadleaf or at harvest .I Vegetation) Route 614 15 1.37 SE 1330 Monthly if available or at harvest Route 629/522 16 12.60 NW 3140 Monthly if available or at harvest Control End of Route 685 21 1.00 WNW 3010 Monthly if available or at harvest Aspen Hills 23 0.93 SSE 1580 Monthly if available or at harvest 17

Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Map Environmental Designation Identification Designation Station 1 (a) 01 ,NE-5/37 7/8 C-7/8 1A O1A,SE-13/45 1/33 N-1/33 2 (a) 02,SSW-20/52 31/63 NNW-31/63 3 (a) 03,C-5/16 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) o5 7/39 ENE-7/39 5A (a) 05A,N-2/34 9/41 E-9/41 6 (a) o6,ESE- 12/44 11/43 ESE-1 1/43 7 (a) 07,C-1 &2 17/49 S-17/49 8 08-Water, Fish Sediment 19/51 SSW-19/51 Shoreline Soil (d) 9 09 21/53 SW-21/53 9A 09A-Water sample, sediment 23/55 WSW-23/55 11 11-River Water, Sediment 25/57 W-25/57 12 12-Milk 16/48 SSE-16/48 13 13-Milk 18/50 S-18/50 14 14-Vegetation, NE-6/38 14/46 SE- 14/46 15 Vegetation 22/54 SW-22/54 16 Vegetation 26/58 W-26/58 21 (a) 21 ,WNW-27/59 28/60 WNW-28/60 22 (a) 22,WSW-24/56 32/64 NNW-32/64 23 (a) 23-SSE-15/47 8/40 ENE-8/40 24 (a)(b) 24,C-3&4 4/36 NNE-40/36 25 (c) 25-Fish 10/42 E- 10/42 18 (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.

Figure 1. North Anna Site Radiological Monitoring Locations I

0 1 q

0 S 0 North Anna Environmental Map 0 Fixed Environmental Sampling Location

• TLD Sampling SGarden Residents

• Meat Animals Original © 1991 by ADC of Aiexandria, Inc. 6440 General Green Way.

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

0] 0 North Anna Environmental Map

• Fixed Environmental Sampling Location

• TLD Sampling

• Garden

• Residents

• Meat Animals Orignal © 199 1 by ADC of Alexandria Incd, 6440 Geeral Green Way, Alexandria VA 22312 USED WITH PERMISSION No oiher reproduction may be made withoift ihe written permission of ADC (7

9

S 0 North Anna Environmental Map

• Fixed Environmental Sampling Location

• TLD Sampling

• Garden

• Residents

• Meat Animals Original 1991 by ADC of Alexandria Inc, 6440 Gonerad Green Wai Alexandria, VA22312 USED WITH PERMISSION No other reproduction may be made wdhhut the wdrttxe permission of AIO

B. Analysis Program Table 2 summarizes the analysis program conducted by Teledyne Brown Engineering for North Anna Power Station during 2000. 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.

24

TABLE 2 (Page 1 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mR+/-2mR mR/std. month Dosimetry (TLD)

(84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mR+2mR mR/std. month Airborne Weekly 1-131 0.07 pCi/m3 Radioiodine Airborne Weekly Gross Beta 0.01 pCi/m3 Particulate Quarterly (a) Gamma Isotopic pCi/m3 Cs- 134 0.05 Cs-137 0.06 2nd Quarter Sr-89 (c) pCi/m3 Composite Sr-90 (c)

Surface Water Monthly 1-131 1(b) pCi/I Gamma Isotopic pCi/I Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba- 140 60 La-140 15 Quarterly (a) Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 (c) pCi/I Composite Sr-90 (c) 25 LLD's 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 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 LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

TABLE 2 (Page 2 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORTUNITS River Water Monthly 1-131 1(b) pCi/I Gamma Isotopic pCi/I Mn-54 15 Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs- 134 15 Cs- 137 18 Ba- 140 60 La- 140 15 Quarterly (a) Tritium (H-3) 2000 pCi/1 2nd Quarter Sr-89 (c) pCi/I Composite Sr-90 (c)

Ground Water Quarterly Gamma Isotopic pCi/I (Well Water) Mn-54 15 Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 1(b)

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

Sr-90 (c)

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

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

Sr-90 (c)

Precipitation Monthly Gross Beta pCi/I Semi-Annual Gamma Isotopic pCi/I Composite 26 LLD's 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 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 LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

TABLE 2 (Page 3 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Soil Semi-Annual Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (a)

Sr-90 (a)

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

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

Sr-90 (a)

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

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

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

(Broadleaf available or Vegetation) at harvest Cs- 134 60 Cs-137 80 1-131 60 pCi/kg (wet) 27 LLD's 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 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 LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

III. PROGRAM EXCEPTIONS 28

REMP Exceptions For Scheduled Sampling And Analysis During 2000 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception All Stations Vegetation 01/19/00 Seasonal unavailability.

02/16/00 03/15/00 Sta 08 Aquatic Sediment 02/21/00 Possible cross-contamination at lab.

Sta 01, 02, 03, Charcoal Filter 04/26/00 TBE instrument malfunction. Data lost.

04, 05, 05A.

All Stations Vegetation 06/21/00 Low level Iodine not requested or performed.

Sta 24 Charcoal Filter 07/26/00 TBE lost during laboratory move.

Sta 06 Air Particulate 08/23/00 Low value. No particulates on filter.

Sta 24 Charcoal Filter 08/30/00 TBE lost sample.

Sta 14, 15, 16, Vegetation 10/18/00 1-131 LLD not met due to untimely analysis.

22, 23 Sta 08, 09A Surface Water 12/18/00 Ba-140 LLD not met due to untimely analysis.

Sta 11 River Water 12/18/00 Ba-140 LLD not met due to untimely analysis.

Sta O0A Precipitation 12/27/00 Co-58, Fe-59, Zr-95, and Ba- 140 LLDs not met due to untimely analysis.

All Stations Annual Environmental 01/11/01 Removed annual TLD's 6 months early to TLDs reflect true annual dose from June to December with change of vendor.

All Stations Vegetation 01/11/01 Seasonal unavailability.

Seasonal unavailability.

All Stations Vegetation 01/11/01 29

In late September of 1999, Teledyne Brown Engineering announced that the laboratory would move from its 35 year home in Westwood, NJ and relocate to Knoxville, TN. Build out of the new laboratory in Knoxville, began in January of 2000 with a two-phase move from Westwood to Knoxville scheduled for June and September. Unfortunately construction delays prevented the June phase one occupancy forcing the laboratory into a one-phase move, a significant delay in NUPIC approval of the Knoxville facility, and the use of NUPIC approved sub-contract laboratories to analyze REMP samples.

This change resulted in significant delays in analytical turnaround times, in obtaining necessary regulatory compliance approvals, and caused extraordinary difficulties for the laboratory and all of its customers. The most important consequences of this delay was the need to utilize two sub-contractor laboratories, Allegheny Environmental Services in Northbrook, IL and the Duke Engineering Laboratory in Marlborough, MA, to perform REMP analyses between October, 20000 and January, 2001 The Westwood laboratory ceased analytical operations in October and was closed on November 15; the Knoxville laboratory was ready to analyze samples by the middle of December, but was not scheduled for NUPIC audit until the end of January, 2001. During the period October 15 through December 15, 2000, the Knoxville laboratory under went several customer surveillances allowing it to perform some limited customer analyses. The Knoxville laboratory is now in full production, is NUPIC approved, and looks forward to another 35 years of partnership with our nuclear power colleagues.

30

IV.

SUMMARY

AND DISCUSSION OF 2000 ANALYTICAL RESULTS 31

IV. Summary And Discussion of 2000 Analytical Results Data from the radiological analyses of environmental media collected during 2000 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance manual and are explained in the Teledyne Brown Engineering 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's analytical methods meet the Lower Limit of Detection (LLD) requirements give 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 2000 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-one control samples with an average concentration of 0.019 pCi/m 3 and a range of 0.007 to 0.040 pCi/m 3 . The average measurement for the indicator locations was 0.019 pCi/m 3 with a range of 0.006 to 0.070 pCi/m 3 . The results of the gross beta activities are presented in Table B-2. The gross beta activities for 2000 were comparable to levels measured in the 1982-1999 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/m 3 to a high of 0.75 pCi/m 3 .

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 all 23 of the 24 composite samples. The average measurement for the control location was 0.067 pCi/m 3 with a range of 0.066 to 0.067 pCi/m 3 . The indicator locations had an average concentration of 0.061 pCi/m 3 and a range of 0.029 to 0.076 pCi/m 3 . During the preoperational period, beryllium-7 was measured at comparable levels, as would be 32

Trending Graph-i: Gross Beta in Air Particulates 1-t 0.1 0.01 0.001

[-Control Sta-24 UIndicator - Average Pre-op Re.ued LLD'Is Trending Graph 2: Tritium in River Water-Station 11 10000

.................-----. . mm ... -....----..-........................................

• 1000 z

8100 During the preoperational period, tritium was not detected in the samples analyzed.

1I I b \ ", 1)

• htý, P ýIi`, Nc)

Pý Nci91 Nc)I)b N,,iFý )o Nq Fý N4, N41 N,) N,ý Nci N4b N

- Tritium - Required LLD's C J 33

expected. Naturally occurring potassium-40 was not detected in any control samples..

Potassium-40 was detected in two indicator samples with an average concentration of 0.005 pCi/m3 and a range of 0.005 to 0.006 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 01A, on site, 0.75 miles, 138 degrees SE and analyzed for gross beta activity. The results are presented in Table B-4.

The average gross beta activity for 2000 in ten of the twelve samples was 3.9 pCi/liter with a range from 0 to 10 pCi/liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. Beryllium-7 was not detected during the semi-annual composite sample for the first half of 2000. All other gamma emitters were below their detection limits. Tritium was not detected in the semi-annual composite samples. These results were comparable to or lower than those measured in 1986 through 1999. 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 2000 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 are collected every three years. Since they were collected in 1998, they were not collected during 2000.

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 2000. 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 not measured above the detection level. No gamma emitting isotopes were detected during the preoperational period. Tritium was measured in most of the samples during that period with concentrations between 80 and 370 pCi/liter.

34

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 SSE. 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.

Potassium-40 was detected in three of the twelve samples with an average concentration of 148 pCi/liter and a range of 7.7 to 385 pCi/liter 3 . 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 two samples with an average level of 3100 pCi/liter and a range of 1500 to 4700 pCi/liter. This is lower than the average level measured in 1999 of 3350 pCi/liter and a range of 3000 to 3800 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.

No iodine was detected in the 18 samples analyzed. The results are presented in Table B-8.

The samples were also analyzed by gamma ray spectrometry. Naturally occurring potassium-40 was detected in one of the twelve samples with a concentration of 39.8 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 3000 pCi/liter with a range of 1500 to 4500 pCi/liter. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCi/liter. However, during 2000 the results were within the same range as those measured in 1986 through 1999. During the preoperational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter. Tritium was not detected at station 09A.

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. One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in two samples with an average activity of 104 pCi/kg (dry weight) and a range from 38.8 to 205 pCi/kg (dry weight). The highest reading for cesium-137 was obtained from station 8 located 1.10 miles SSE.

Naturally occurring potassium-40 was observed in all five of the six samples with an average activity of 10928 pCi/kg (dry weight) and a range from 3040 to 1470 pCi/kg (dry weight). Naturally occurring, thorium-228 was observed in all six samples with an average 35

concentration of 932 pCi/kg (dry weight) and a range of 846 to 1100 pCi/kg (dry weight).

Radium-226 was measured in four of the six samples with an average concentration of 1420 pCi/kg (dry weight) and a range of 399 to 1870 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium-90. There were no measurable amounts of strontium-89 or strontium-90 in aquatic sediment/silt.

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 Table B- 11. The naturally occurring nuclide potassium-40 was measured in both samples with an average activity of 1345 pCi/kg (dry weight) and a range of 1280 to 1410 pCi/kg (dry weight). Cosmogenic beryllium-7 was not measured during 2000. Thorium-228 was measured in both samples at an average of 251 pCi/kg (dry weight) and a range of 203 to 298 pCi/kg (dry weight). Radium-226 was measured in both samples with a concentration of 464 pCi/kg (dry weight) and a range of 313 to 615 pCi/kg (dry weight). Cesium-137, a fission product, was measured in one sample with a concentration of 167 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 100 pCi/kg (dry weight).

36

I Trending Graph-3: Tritium in Surface Water-Sta 08 10000 t

z 1000 100

• r vr r.... . .

[--Tritium - Required *LLD's -- Average Pre-op Trending Graph-4: Cobalt-58 in Sediment Silt 1000 100 I

0 Q.

10 I

-[s Station-8 ý Station-09 & Control Sta -09A x Station-Il I

37

- I Trending Graph-5: Cobalt-60 in Sediment Silt 1000 t

100 0

z 10 0,

I ~ ~~II I I T T 1 1 1 1 1 1 1 1 1 1 S' l4' I" #4'1V s 4' f1ýZ5 4

-- Station-S -- Station-09 -,-Control-Sta-09 -x< Station-I1 Trending Graph-6: Cesium-134 in Sediment Silt 1000 -

Cu

"'A " A

-I 100 0

10 CL Q

0' I

%'p %b 'b" ýP Sý' Sýý 03 4' 4b So ýl Asý Asý s, 41, ýý 41, 41,

-- Station-8 -Station-09 A---Control-Sta-09 x- Station-Il -U--RequiredLLD'sý 38

1 Trending Graph - 7: Cesium-137 in Sediment Silt 10000 1000 z

I E 100 C-)

10 I 1 Te T r r'e.. . . s ,\ . . . , ,

[- Station-8 -U-Station-9 -*-Control-Sta-09 --- Station-Il - Average Pne-Op 4--ýRequired LLD's Trending Graph - 8:Cesium 134 in Fish S1000]

-' 100 1oC

"%Q)4)434

,ýs '?ý g&ý -4ý ý

-*--' Station 08 Station 09 - Control Sta 25 -x- Required LLD 39 C

D. Ingestion Exposure Pathway

1. Milk The results of the iodine-131 analysis of milk samples are presented in Table B-12.

A sample was collected monthly from two stations. A total of 24 samples were analyzed during 2000. 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-12. A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all samples with an average of 1261 pCi/liter and a range of 1090 to 1410 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 2000. 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 four samples monitored with an average level of 0.97 pCi/liter and a range of 0.75 to 1.2 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-13. Eight samples of fish were collected during 2000. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all samples at an average of 1157 pCi/kg (wet weight) with a range of 1120 to 2380 pCi/kg (wet weight). The fission product cesium-137 was measured in two of the eight samples with an average activity of 42.6 pCi/kg (wet weight) with a range of 34.1 to 51.1 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-five food samples were collected from five locations and analyzed by gamma spectrometry. The results are presented in Table B-14. Naturally occurring potassium-40 was monitored in all 35 samples with an average activity level of 11116 pCi/kg (wet weight) and a range of 7190 to 21300 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in 23 of the 35 samples with an average concentration of 933 pCi/kg (wet weight) and a range of 221 to 3540 pCi/kg (wet weight)..

Cesium-134, a fission product, was not detected at levels above LLD during 2000.

Cesium-137 has been detected in some samples at low-levels in previous years and was detected in two samples at an average concentration of 98.8 pCi/kg (wet weight). Cesium-40

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 I1. 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 5.5 mR/standard month with a range of 4.3 to 7.1 mR/standard month. This is comparable to the preoperational range. Station, No. 1, had an average reading of 8.2 mR/standard month with a range of 7.5 to 8.7 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 6.9 mR/standard month with a range of 3.9 to 11.1 mR/standard month. The eight control TLDs, collected quarterly from four locations, showed an average reading of 5.9 mR/standard month with a range of 3.9 to 7.9 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.

41

1 Trend Graph 9: Cs-137 In Fish 10000.0 0

0 1000.0 z

C 100.0 Fr ~ ellzo

.4 10.0 U

0-1.0 4 # ,I &Q*.....

-- Sta 08 - Sta 09 m Sta 25 ----- Average Pre op --- Required LLD Trending Graph 10: North Anna TLDs 10.0 S 9.01 8.0 7.0 o5.0 t 4.0 II 3.0 S2.0 S

rrr --

- Environmental TLD - Sector TLD - Average Pre-op C 4 42

V. CONCLUSIONS 43

V. Conclusions The results of the 2000 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 2000 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 Chernobyl 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 2000. Iodine-131 was not detected in the charcoal filters analyzed during 2000.

A precipitation sample was collected monthly during 2000 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 not observed above the LLD during this reporting period in 1998.

During the preoperational period the average tritium activity was 165 pCi/liter.

Waterborne Exposure Pathway No man-made or natural isotopes were monitored in the surface water of Lake Anna except tritium. The average tritium activity during 2000 at the waste heat treatment facility was 3000 pCi/liter which is 13.2% of the reporting level for a water sample. In 1999 the tritium level was 3975 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 3100 pCi/liter. The average tritium in 1999 had been 2600 pCi/liter.

Naturally occurring potassium-40 wad measured in 3 out of 12 samples at an average concentration of 148 pCi/liter. No other gamma emitters were detected.

Ground water from the environmental well on site contained no gamma emitters. There were also no detection of tritium in ground/well water during 2000.

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 isotope was present. Cesium-I137 was detected in two samples at the indicator location and in one 44

sample at the control location. During the preoperational period, cesium-137 was measured in samples of aquatic sediment. 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 both samples at an average level of 167 pCi/kg.

Cesium-137 was not detected during 1999.

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 2000.

Strontium-90 was measured in all four 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 2000 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 1999. 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 2000 of cesium-137 was 1.6% of the reporting level.

One vegetation sample contained cesium-137 at a level of 186 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.

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 45

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 10CFR50, 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 2000.

46

VI. REFERENCES 47

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-2103, "Offsite Dose Calculation Manual".

3. Title 10 Code of Federal Regulation, Part 50 (10CFR50), "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 10CFR50, 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)"

48

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

TABLES - 2000 49

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page I of 7 All Indicator Control Non Medium or Analysis Locations Location with Highest Mean Location routine Pathway LD* Reported Sampled Total Mean Name Distance Mean Mean Measure (Unit) Type No. Range Direction Range Range ments Air Iodine 1-131 624 0.04 (0/561)(a,b) N/A N/A (0/49)(a,b) 0 (pCi/m 3)

Airborne Gross 624 5 18.7(560-572)(a) 23 0.93 mi 20.0(52/52) 19.4(51/52)(a) 0 Particulates Beta (6.0-70) SSE (7.6-70) (7.1-41)

(1E-03 pCi/m 3 )

Gamma 24 Be-7 24 10 61.0(21/22) 24 22.0 mi 66.7(2/2) 66.7(2/2) 0 (29.2-75.6) NW (66.0-67.4) (66.0-67.4)

K-40 24 10 5.43(2/22) 07 7.30 mi 5.91(1/2) (0/4) 0 (4.95-5.91) SSE Sr-89 12 3 (0/10) N/A N/A (0/2) 0 Sr-90 12 0.4 (0/10) N/A N/A (0/2) 0 Ground Gamma 4 Well Water K-40 4 60 (0/4) N/A N/A (0/0) 0 (pCi/liter)

Tritium 3 2000 (0/3) N/A N/A (0/0) 0 Sr-89 1 3 (0/1) N/A N/A (0/0) 0 Sr-90 1 0.4 (0/1) N/A N/A (0/0) 0 50 LLD is the Lower Limit of Detection as defined and requiredin USNRC Branch Technical Positionon an Acceptable Radiological EnvironmentalMonitoring Program,Revision 1, November 1979.

a) Sample was lost.

b) Samples not analyzed c) No precipitationfor October.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 2 of 7 All Indicator Control Non Medium or Analysis Locations Location with Highest Mean Location routine Pathway LD* Reported Sampled Total Mean Name Distance Mean Mean Measure (Unit) Type No. Range Direction Range Range ments River Gamma 12 Water (pCi/liter) K-40 12 200 148(3/12) 11 5.8mi 148(3/12) (0/0) 0 (7.7-385) SSE (7.7-385)

Tritium 2 2000 3100(2/2) 11 5.8 mi. 3100(2/2) (0/0) 0 (1500-4700) SSE (1500-4700)

Sr-89 1 3 (0/1) N/A N/A (0/0) 0 Sr-90 1 0.4 (0/1) N/A N/A (0/0) 0 Precipitation Monthly (pCi/liter)

Gross 12 4 3.89(10/12) 01A 0.2 mi. 3.89(10/12) (0/0) 0 Beta (0-10) NE (0-10)

Gamma 2 (0/2) (0/0)

(Semi-Annually Tritium 1 2000 (0/1) N/A N/A (0/0) 0 Surface 1-131 24 0.5 (0/12) N/A N/A (0/12) 0 Water (pCi/liter)

Regular Gamma 24 Monthlies K-40 24 200 39.8(1/12) 08 1.0 mi 39.8(1/12) (0/12) 0 SSE Tritium 4 2000 3000(2/2) 08 1.10mi 3000(2/2) (0/2) 0 (1500-4500) SSE (1500-4500) 51 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program,Revision 1, November 1979.

a) Sample was lost.

b) Samples not analyzed c) No precipitationfor October.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 3 of 7 Surface Sr-89 1 (0/1) N/A N/A (0/1) 0 Water (pCi/liter)

Regular Sr-90 I (0/1) N/A N/A (0/1) 0 Monthlies Surface Gamma NA Water (pCi/liter) K-40 NA State Splits Tritium NA Sediment Gamma 6 Silt (pCi/kg Be-7 6 (0/4) NA NA 227(1/2) 0 (dry)) (227)

K-40 6 200 10460(4/4) 11 5.8mi 13800(2/2) 12800(1/2) 0 (3040-14700) SSE (12900-14700) (12800)

Cs-137 6 194 132(2/4) 08A 1.10mi 205(1/2) 1720(1/2) 0 (58.8-205) SSE (205) (1720)

Ra-226 6 100 1320(3/4) 08 1.10 mi 1870(1/2) 1720(1/2) 0 (399-1870) SSE (1870) (1720)

Th-228 6 30 975(2/4) 08 1.10mi. 1100(1/2) 846(1/2) 0 (849-1100) SSE (1100) (846)

Sr-89 3 4.0 (0/0) N/A N/A (0/0) 0 (Annually)

Sr-90 3 0.8 (0/0) N/A N/A (0/0) 0 (Annually) 52 LLD is the Lower Limit of Detection as defined and requiredin USNRC Branch Technical Positionon an Acceptable Radiological EnvironmentalMonitoring Program,Revision 1, November 1979.

a) Sample was lost.

b) Samples not analyzed c) No precipitationfor October.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 4 of 7 Soil Gamma 0 (pCi/kg (dry)) Be-7 0 K-40 0 Cs-134 0 100 Cs-137 0 180 Ra-226 0 100 Th-228 0 30 Sr-89 0 200 (Annually)

Sr-90 0 40 (Annually)

Soil samples are collected every three years. Since they were collected in 1998, they were not collected during 2000.

53 LLD is the Lower Limit of Defection as defined and requiredin USNRC Branch Technical Positionon an Acceptable Radiological Environmental Monitoring Program,Revision 1, November 1979.

a) Sample was lost.

b) Samples not analyzed.

c) No precipitation for October.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 5 of 7 Shoreline Gamma 2 Soil (pCi/kg Be-7 2 (0/2) N/A N/A (0/0) 0 (dry))

K-40 2 200 1345(2/2) 8 1.10mi 1345(2/2) (0/0) 0 (1280-1410) SSE (1280-1410)

Cs-137 2 40 167(1/2) 8 1.10mi 167(1/2) (0/0) 0 (167) SSE (167)

Ra-226 2 100 464(2/2) 8 1.10mi 464(2/2) (0/0) 0 (313-615) SSE (313-615)

Th-228 2 30 251(2/2) 8 1.10mi 251(2/2) (0/0) 0 (203-298) SSE (203-298)

Sr-89 1 4.0 (0/1) N/A N/A (0/0) 0 (Annually)

Sr-90 1 0.8 100(1/1) 8 1.10mi 100(1/1) (0/0) 0 (Annually) (100) SSE (100)

Milk 1-131 24 0.5 (0/24) N/A N/A (0/0) 0 (pCi/liter)

Gamma 24 K-40 24 100 1336(23/24) 12 8.3 mi. 1394(11/12) (0/0) 0 (1010-1590) NW (1220-1590)

Sr-89 4 5 (0/4) N/A N/A (0/0) 0 (Quarterly)

Sr-90 4 0.8 0.97(4/4) 12 8.3 mi 0.98(2/2) (0/0) 0 (Quarterly) (0.75-1.2) NW (0.75-1.2) 54 LLD is the Lower Limit of Detection as defined and requiredin USNRC Branch Technical Position on an Acceptable Radiological Environmental MonitoringProgram,Revision 1, November 1979.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 6 of 7 Fish Gamma 8 pCi/kg (wet) K-40 8 200 1157(4/4) 08 1.10mi 1157(4/4) 1860(4/4) 0 (1120-1730) SSE (1120-1730) (1120-2380)

Cs-137 8 40 42.6(2/4) 08 1.10mi. 42.6(2/4) (0/4) 0 (34.1-51.1) SSE (34.1-51.1)

Food Gamma 35 Vegetation Dose (pCi/kg Be-7 35 1064(18/28) 21 1.00 mi 1236(4/7) 614(5/7) 0 (wet)) (221-3540) WNW (506-2210) (351-972)

K-40 35 10796(27/28) 23 0.93 mi 12723(7/7) 12350(7/7) 0 (5390-21300) SSE (7270-21300) (9750-17100)

Cs-137 35 80 186(1/28) 15 1.20 mi 186(1/7) 11.2(1/7) 0 NE Th-228 35 (0/28) (0/7) (0/7) 0 55 LLD is the Lower Limit of Detection as defined andrequired in USNRC Branch Technical Position on an Acceptable Radiological EnvironmentalMonitoring Program,Revision 1, November 19 79.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 7 of 7 Direct Gamma 48 0.2 6.24(44/44) 01 0.2 mi. NE 8.20(4/4) 5.8(4/4) 0 Radiation Dose (4.1-8.77) (7.5-8.7) (5.0-6.4)

(mR/std. month)

(Regular TLDs)

Direct Gamma 12 0.2 5.47(11/11) 01 0.2 mi. NE 7.1(2/12) 5.3(1/1) 0 Radiation Dose (4.3-7.1) 23 0.93 mi. SSE (7.1) (5.3)

(mR/std. Month)

(Annual TLDs)

Direct Gamma 288 0.2 6.89(256/256) 17/49 0.22 mi.S 9.9(8/8) 5.86(32/32) 0 Radiation Dose (4.9-11.1) (8.4-11.1) (3.9-7.9)

(mR/std. Month)

(Sector TLDs) 56 LLD is the Lower Limit of Detection as defined andrequired in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program,Revision 1, November 19 79.

APPENDIX B DATA TABLES 57

TABLE B-i: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 2000 pCi/m 3 +/- 2 Sigma Page 1 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JANUARY 12/29-01/06 <.007 <.007 <.007 <.007 <.005 <.01 <.01 <.01 <.01 <.007 <.006 <.005 01/06-01/12 <.009 <.009 <.009 <.009 <.006 <.008 <.009 <.008 <.008 <.006 <.01 <.01 01/12-01/19 <.008 <.008 <.008 <.008 <.006 <.008 <.008 <.008 <.008 < .006 <.01 <.01 01/19-01/27 <.01 <.01 <.01 <.01 <.009 <.01 <.01 <.01 <.01 <.008 <.02 < .02 01/27-02/02 <.02 <.02 <.02 <.02 <.009 <.009 <.009 <.009 <.01 < .01 <.01 <.01 FEBRUARY 02/02-02/09 <.01 <.01 <.01 <.01 <.008 <.007 <.007 <.007 <.007 <.006 <.01 <.01 02/09-02/16 <.008 <.008 <.008 <.008 <.005 <.01 <.01 <.01 <.01 <.008 <.01 <.01 02/16-02/23 <.008 <.008 <.008 <.008 <.006 <.008 <.008 <.008 <.008 <.005 <.01 <.01 02/23-03101 <.008 <.008 <.008 <.008 <.005 <.01 <.01 <.01 <.01 <.008 <.01 <.01 MARCH 03/01-03/08 <.008 < .008 < .009 <.008 < .006 <.008 <.008 <.009 <.008 <.006 < .01 <.01 03/08-03/15 <.007 < .008 < .007 <.006 < .008 <.01 <.01 <.01 <.01 <.008 <.009 <.006 03/15-03/22 <.008 < .007 < .007 <.007 < .005 <.01 <.01 <.01 <.01 <.008 <.01 <.007 03/22-03/29 <.009 < .009 < .009 <.009 < .007 <.009 <.009 <.009 <.009 <.006 <.01 <.01 APRIL 03/29-04/05 <.008 < .008 < .008 <.008 < .005 <.01 <.01 <.01 <.01 <.009 <.007 <.006 04/05-04/12 <.008 < .008 < .008 <.008 < .006 <.01 <.01 <.01 <.01 <.008 <.01 <.01 04/12-04/19 <.009 <.009 < .008 <.009 < .007 <.008 <.008 <.008 <.007 <.006 <.01 <.01 04/19-04/26 (a) (a) (a) (a) (a) <.008 <.008 <.008 <.008 <.006 <.02 <.02 04/26-05/03 <.009 < 009 < 009 < .009 < .007 <.009 <.009 <.009 <.009 <.006 <.02 <.02 MAY 05/03-05/10 <.007 <.007 <.007 <.007 <.005 <.007 <.007 <.008 <.007 <.004 <.006 <.01 05/10-05/17 <.009 <.009 <.009 <.009 <.006 <.02 <.02 <.02 <.02 <.01 <.005 <.007 05/17-05/23 <.01 <.01 <.01 <.008 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 05/23-05/31 <.009 <.009 <.009 <.009 <.006 <.01 <.01 <.01 <.01 <.008 <.01 <.01 JUNE 05/31-06/07 <.009 <.009 <.009 <.009 <.007 <.009 <.009 <.009 <.009 <.006 <.01 <.01 06/07-06/14 <.007 <.008 <.007 <.007 <.005 <.01 <.01 <.01 <.01 <.008 <.01 <.01 06/14-06/21 <.009 <.009 <.009 <.009 <.006 <.01 <.01 <.01 < .01 <.009 <.009 <.007 06/21-06/28 <.01 <.01 <.01 <.01 <.008 <.01 <.01 <.01 <.01 <.007 < .01 <.01 58 (a) The gamma spectral data was transcribed to magnetic tape. Due to a malfunction of this magnetic tape device, the data was irretrievable and the gamma data not reportable.

(b) The sample was not analyzed.

TABLE B-I: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 2000 pCi/m 3 + 2 Sigma Page 2 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JULY 06/28-07/05 <.008 <.008 <.008 <.008 <.006 <.01 <.01 <.01 <.01 <.009 <.01 <.01 07/05-07/12 <.02 <.02 <.02 <.02 <.02 <.01 <.01 <.01 <.01 <.008 <.007 < .006 07/12-07/19 <.009 <.009 <.009 <.009 <.007 <.01 <.01 <.01 <.01 <.009 <.01 <.01 07/19-07/25 <.009 <.01 <.01 <.01 <.007 <.02 <.01 <.01 <.02 <.01 <.01 < (b) 07/25-08/02 <.01 <.01 <.01 <.01 <.01 <.01 < .01 <.01 <.01 <.007 <.02 <.01 AUGUST 08102-08/09 <.011 <.011 <.011 <.01118<.007 <.014 <.014 <.014 <.014 < 0.01 <.009 <.01 08/09-08/16 <.01 <.01 <.01 < .01 <.009 <.02 <.02 <.02 <.02 <.01 <.01 < .009 08/16-08/23 <.02 <.02 <.02 < .02 <.02 <.02 <.02 <.02 <.02 <.01 <.02 < .02 08/23-08/30 <.006 <.006 <.006 < .006 <.006 <.007 <.007 <.007 <.007 <.008 <.01 < (b)

SEPTEMBER 08/30-09/06 <.01 <.01 <.01 <.01 <.01 <.02 <.02 .02 <.02 <.01 <.01 <.01 09/06-09/14 <.01 <.01 <.01 <.01 <.008 <.01 <.01 .01 <.01 <.008 <.01 <.008 09/14-09/20 <.03 <.03 <.03 <.03 <.02 <.02 <.02 .02 <.02 <.01 < .01 <.02 09/20-9/27 <.009 <.008 <.009 <.009 <.006 <.01 <.01 .01 <.01 <.009 <.009 <.009 OCTOBER 09/27-10/04 <.007 <.007 <.007 <.007 <.005 <.008 <.008 <.008 <.008 <.005 <.006 < 005 10/04-10/11 <.008 <.008 <.008 <.008 <.004 <.006 <.006 <.006 <.006 <.004 <.004 <.005 10/11-10/18 <.006 <.006 <.007 <.006 <.004 <.006 <.006 <.006 <.006 <.004 <.003 <.005 10/18-10/25 <.007 <.007 <.008 <.008 <.006 <.009 <.009 <.009 <.009 <.006 <.01 <.005 10/25-11/01 < 004 < 005 <.007 <.007 <.007 <.006 <.004 <.007 <.007 <.007 <.007 <.005 NOVEMBER 11/01-11/08 <.008 < .008 <.008 < .009 < .005 < .008 <.008 < .008 < .008 <.006 <.02 <.01 11/08-11/15 <.01 <.01 <.01 <.01 < .007 <.01 <.01 <.01 <.01 < .007 <.01 <.01 11/15-1122 (b) (b) (b) (b) (b) (b) (b) (b) (b) (b) (b) (b) 11/22-11/29 <.006 < .006 <.006 < .006 < .004 < .006 <.006 < .006 <.006 <.004 <.008 <.008 DECEMBER 11/29-12/6 <.01 <.01 <.01 <.01 <.006 <.01 <.01 <.01 <.01 <.008 <.01 <.01 12/6-12/13 <.004 <.007 <.007 <.007 <.007 <.005 <.006 <.006 <.006 <.006 <.004 <.007 12/13-12119 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.02 <.02 12/19-12/27 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 < .01 59 (a) The gamma spectral data was transcribed to magnetic tape. Due to a malfunction of this magnetic tape device, the data was irretrievable and the gamma data not reportable.

(b) The sample was not analyzed.

TABLE B-2:CONCENTRA TIONS OF GROSS BETA IN AIR PAR TICULA TES North Anna Power Station, Louisa County, Virginia - 2000 1.OE-03 pCi/m 3 +/- 2 Sigma Page 1 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 +/-2s.d.

JANUARY 12/29-01/06 26_+/-_2 25_+/-2 27_+/-2 29_+/-2 20_+/-2 27_+/-2 22_+/-2 29_+/-2 28++/-_2 24+/-2 22_+/-2 26_+/-2 25_+/-6 01/06-01/12 18_+/-2 16_+/-2 19_+/-2 18_+/-2 19_+/-2 19+/-2 18_+/-2 19+/-2 19+/-2 17+/-2 18+/-2 21+/-2 18+/-2 01/12-01/19 10-+/-1 15_+/-2 14_+/-2 16_+/-2 12+/-1 13-+/-2 12_+/-1 15_+/-2 14_+/-2 10+/-1 14-+/-2 14_+/-2 13+/-4 01/19-01/27 21+/-2 21+/-2 25+/-2 26_+/-2 26+/-2 26-+/-2 20-+/-2 21+/-2 27-+/-2 25+/-2 25_+/-2 29_+/-2 24+/-6 01/27-02/02 14_+/-2 17_+/-2 16_+/-2 21+/-2 18_+/-2 19_+/-2 18_+/-2 17_+/-2 19_+/-2 16_+/-2 17_+/-2 17_+/-2 17+/-4 FEBRUARY 02/02-02/09 19_+/-2 20+/-2 20+/-2 23-+/-2 22-+/-2 22+/-2 20_+/-2 24_+/-2 21 +/-2 21 +/--2 20+/-2 24+/-2 21 3 02/09-02/16 21 +/-_2 24+/-2 23-+/-2 26-+/-2 24_+2 23 +/-_2 23 +/--2 27-+/-2 29-+/-2 22-+/-2 25_+/-2 26+/-2 24+/-5 02/16-02/23 16+/-2 17+/-2 17_+/-2 18_+/-2 17+/-2 18+/-2 15+/-2 20-+/-2 21-+/-2 18_+/-2 20_+/-2 17+/-2 18+/-3 02/23-03/01 13-+/-2 14-+/-2 15+2 14_+/-2 14_+/-2 14_+/-2 13+/-2 16_+/-2 15_+/-2 14_+/-2 14+/-2 15-+/-2 14+/-2 MARCH 03/01-03/08 16-+/-2 15_+/-2 18_+/-2 19_+/-2 21_+/-2 18_+/-2 17_+2 22_+/-2 18_+/-2 14_+/-2 19+/-2 19_+/-2 18_+/-5 03/08-03/15 18_+/-2 19_+/-2 17+/-2 20-+/-2 21_+/-2 19_+/-2 17_+/-2 22_+/-2 18+/-2 16_+/-2 18_+/-2 17_+/-2 19_+/-4 03/15-03/22 10+/-2 11_1 10+/-1 10+/-1 10+/-1 12+/-2 10+/-1 11+/-1 13+/-2 9+/-1.4 10+1 11+/-1 11+/-2 03/22-03/29 11_+/-2 12+/-2 10-+/-1 12+/-2 11+2 13_+/-2 10_+/- 13++/-2 12_+/-2 10_+/-1 12_+/-2 11+/-1 11-+/-2 Quarter Avg. 16 +/-10 17 +/- 9 18 +/- 11 19 +/- 11 18 +/- 10 19+/-10 17 +/- 9 20 +/- 11 20 +/- 11 17 +/- 10 18 +/- 9 19 +/- 12 18 +/- 10

+/- 2 s.d.

(a) Sample not analyzed. 60

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2000 1.OE-03 pCi/rn3 +/- 2 Sigma Page 2 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 +/-2s.d.

APRIL 03/29-04/05 14 +/-_2 15 +/-_2 15 +/-_2 15+/-2 15_+/-2 13+/-2 14-+/-2 16-+/-2 14+2 13++/-2 13+/-2 12+/-2 14+/-2 04/05-04/12 16_+/-2 17_+/-2 17+/-2 17-+/-2 14_+/-2 15_+/-2 14_+/-2 16_+/-2 14+/-2 13+/-2 15+/-2 16+/-2 15+/-3 04/12-04/19 8+/- 1 8+/- 1 9+/- 1 9_+/-1 9_+/-1 9+/-1 8+/-1 10-+/-1 10_+/-1 9+/-1 8+/-1 9+/-1 9+/-1 04/19-04/26 7+/- 1 8+/- 1 8+/- 1 7+/-1 7+/-1 8+/-1 7+/-1 9+/-1 7+/-1 6+/-1 8+/-1 7+/-1 7+/-2 04/26-05/03 14 +/- 2 15 +/- 2 15 +/- 2 15_+/-2 13+/-2 15-+/-2 14_+/-2 17_+/-2 15+/-2 13+/-2 14+/-2 15+/-2 15+/-2 MAY 05/03-05/10 21_+/-2 21_+/-2 20_+/-2 20+/-2 19+/-2 20_+/-2 18+/-2 21_+/-2 22+/-2 19+/-2 19-+/-2 21+/-2 20+/-2 05/10-05/17 16-+/-2 17-+/-2 16+/-2 15+/-2 18+/-2 18_+/-2 14_+/-2 21+/-2 18+2 16+/-2 16-+/-2 18-+/-2 17_+/-4 05/17-05/23 15_+/-2 15_+/-2 13_+/-_2 15+/-+2 13_+/-2 14_+2 12+2 10+/-2 12+/-+2 14+/-2 14-+/-2 14-+/-2 13+/-3 05/23-05/31 14-+/-2 14_+/-2 14+/-+2 14_+/-2 14_+/-2 13+1 15+2 13+1 14+2 15-+2 13-+1 12+1 14+2 JUNE 05/31-06/07 11-+/-1 14+/-2 12-+/-1 13+/-2 13-+/-2 14+/-2 12-+/-1 13-+/-2 11-+/-1 13_+/-2 13+/-2 14-+/-2 13++/-2 06/07-06/14 21 +/--2 21 +/--2 23 +/-2 21 +/-2 21 +/--2 24+/-2 18-+/-2 19+_2 21+/-2 21+/-2 20-+/-2 23+/-2 21+/-3 06/14-06/21 10-+/-1 9+/-111++/-1 10+/-+1 10+/-1 11_+/-1 9-+/-1.4 10+1 9_+/-1 10_+/-1 11_+/-1 11_+/-1 10+/-2 06/21-06/28 22 +/- 2 21 +/- 2 20 +/- 2 21 +/- 2 17 +/- 2 21 +/- 2 19+/-2 21_+/-2 17_+/-2 20_+/-2 20+2 20-+/-2 20_+/-3 Quarter Avg. 15 +/- 10 15 +/- 9 15 +/- 9 15 +/-9 14 +/- 8 15 +/- 9 13-+/-8 15+/-9 14_+/-9 14+/-9 14-+/-8 15-+/-9 14-+/-9

+/- 2 s.d.

(a) Sample not analyzed. 61

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES North Anna Nuclear Power Station, Louisa County, Virginia- 2000 1.OE-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 +/-2s.d.

JULY 06/28-07/05 18+/-2 17+/-2 16+/-2 17+/-2 15+2 18+2 17+/-2 16+/-2 16+/-2 17+/-2 15+/-2 15+/-2 16+/-2 19+/-2 18+/-2 16+/-2 18+/-2 16+2 17+/-2 14+/-2 15+/-2 15+/-2 16+/-2 15+2 15+/- 2 16+/-3 07/05-07/12 07/12-07/19 15+/-2 15+/-2 17+/-2 18+/-2 15+2 14+2 14+/-2 16+/-2 14+/-2 13+/-2 15+2 14+/-2 15+/-3 18+/-2 19+/-2 19+/-2 17+/-2 18+/--2 18+/-2 15+/-2 18+/-2 16+/-2 16+/-2 16+/-2 17+/-3 07/19-07/25 18+/-2 07/25-08/02 13 +/- 1 11 +/- 1 14 +/- 1 14 +/- 1 11+/-1 12+/-1 10 +/-1 11 +/- 1 13+/-1 12+/-1 12+/-1 12+/-1 12+/-2 AUGUST 08/02-08/09 22+/-2 22+/-2 23+/-2 23+2 18+/-2 22+/-2 19+/-2 23+/-2 21+/-2 22+/-2 24+/-2 23+/-2 22+/-4 08/09-08/16 19+/-2 18+2 19+/-2 20+/-2 17+/-2 18+/-2 15+/-2 16+/-2 20+/-2 18+/-2 19+/-2 19+/-2 18_+/-_3 08/16-08/23 14 +/- 2 16 +/- 2 18 +/- 2 17 +/- 2 15 +/- 2 16 +/- 2 < 1.0(a) 15 +/- 2 19 +/- 2 17 +/- 2 16 +/- 2 18 +/- 2 16_+/- 3 08/23-08/30 28 +/- 2 25 +/- 2 24 +/- 2 26 +/- 2 23 +/- 2 22 +/- 2 22 +/- 2 23 +/- 2 24 +/- 2 24 +/- 2 23 +/- 2 31 +/- 2 25 +/- 5 SEPTEMBER 08/30-09/06 13 +/- 2 12 +/-2 12 +/-2 13 +/-2 12+/-2 13+/-2 12+/-2 11+/-2 8.6+1.5 13+/-2 14+/-2 12+/-2 12+/-3 17 +/-2 19 +/-2 17 +/-2 17+/-2 19+/-2 15+/-1 18+/-2 17+/-2 19+/-2 18+/-2 18+/-2 18+/-2 09/06-09/14 19 +/- 2 16 +/- 2 13 +/-2 16 +/-2 13 +/-2 14+/-2 14+/-2 13+/-2 13+/-2 14+/-2 15+/-2 16+/-2 13+/-2 14+/-3 09/14-09/20 14 +/- 2 13 +/-2 12 +/-2 13 +/-2 12+/-2 11+/-1 11+/-1 10+/-1 13+/-2 12+/-2 13+/-2 12+/-2 12+/-2 09/20-09/27 Quarter Avg. 18+/- 9 16+/-8 17+/-7 17+/-8 16+/-6 16+/-7 15+/-7 16+/-8 16+/-8 16+/-7 17+/-7 17+/-11 16+/-8

+/-2 s.d.

(a) Sample not analyzed. 62

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PAR TICULA TES North Anna Nuclear Power Station, Louisa County, Virginia- 2000 1.OE-03 pCi/m 3 +/- 2 Sigma Page 4 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 +2s.d.

OCTOBER 09/27-10/04 20 +/- 2 21+/-2 20+/-2 20+/-2 19+/-2 19_+/-2 22 +/- 2 19+/-2 19 +/- 2 20+/- 2 22 +/- 2 19+/-2 20 +/-2 10/04-10/11 22 +/- 2 20+/-2 22 +/- 2 21 +/-2 21+/-2 21+/-2 20+/-2 25 +/-2 18 +/- 2 18+/-2 23 +/- 2 24+/-2 21+/-4 10/11-10/18 39+/-3 38+/-3 41+/-3 38 +/- 3 41 +/- 3 37 +/- 2 36+/-2 34+/-2 34 +/- 2 39+/-2 42 +/- 3 40 +/- 3 38 +/- 5 10/18-10/25 42 +/- 3 39+/-3 41+/-3 42 +/- 3 41+/-3 37+/-2 31+/-2 31+/-2 39+/-3 41+/-3 44 +/- 3 41 +/- 3 39 +/- 8 10/25-11/01 28 +/- 2 27+/-2 27+/-2 27 +/-2 28+2 26 +/- 2 19 +/- 2 21+/-2 26+/-2 25 +/-2 28+/-2 28 +/--2 26 +/- 6 NOVEMBER 11/01-11/08 29_+/-2 25_+/-2 29-+/-2 32 +/- 3 30_+/-2 27 +/- 2 27 +/- 2 26 +/- 2 24 +/- 2 29 +/- 2 70 +/- 5 29 +/- 3 31 +/- 25 11/08-11/15 23+/-2 23-+/-2 23+/-2 25-+/-2 22 +/-_2 25_+/-2 19 +/- 2 20 +/- 2 22+/- 2 20 +/- 2 22 +/- 2 24 +/- 2 22 +/- 4 11/15-11/22 (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) (a) 11/22-11/29 19 +/- 2 20 +/- 2 20_+/-2 21_+/-2 20_+/-2 20_+/-2 18_+/-2 18_+/-2 19_+2 20-+/-2 21-+/-2 21-+/-2 20_+/-2 DECEMBER 11/29-12/06 18 +/- 2 16_+/-2 20 +/- 2 19 +/- 2 18_+/-2 19_+2 17_+/-2 17_+2 18 +/- 2 17_+/-2 19 +/- 2 19_+/-2 18 +/- 3 12/06-12/13 32_+/-2 28_+/-2 33-+/-2 30 +/- 2 27 +/- 2 28_+2 27 +/- 2 27_+2 30_+/-2 27 +/- 2 29 +/- 2 27 +/- 2 29 +/- 4 12/13-12/19 23 +/-_2 23 +/-_2 27+/-2 29+/-2 22 +/- 2 25_+/-2 24 +2 21_+/-2 23 +/-_2 25 +/- 2 28 +/- 2 28_+/-2 25 +/- 5 12/19-12/27 31 +/-_2 28 +/--2 36-+/-2 31 +/- 2 28 +/- 2 30_+/-2 33+2 30+/-2 28_+/-2 30_+/-2 37 +/- 2 31_+/-2 31+/-6 Quarter Avg. 27_+/- 16 26_+/-14 28_+/-16 28 +/- 15 26 +/- 16 26 +/- 12 24 +/- 13 24 +/- 11 25_+/-13 26_+/-16 32_+/-29 28-+/-14 27_+/-16

+/- 2 s.d.

Annual Avg. 19 +/- 14 19 +/- 13 19 +/- 15 20 +/- 14 18 + 14 19 +/- 13 17 +/- 12 18 +/- 12 19 +/- 13 18 +/- 14 20 +/- 21 19 +/- 15 19 +/- 14

+/- 2 s.d.

63 (a) Sample not analyzed.

TABLE B-3: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN AIR PAR TICULA TES North Anna Power Station, Louisa County, Virginia - 2000 1.0 E-03 pCi/m 3 +/- 2 Sigma Page 1 of3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide* 12129-03/29 03129-06/28 STA-01 Sr-89 (a) <4 Sr-90 (a) <0.5 Be-7 58.8 +/- 5.9 68.6 +/- 6.9 63.7 +/- 13.9 K-40 <8 <4 Co-60 <0.3 < 0.3 Ru-103 < 0.4 < 0.4 Cs-1 34 <0.3 < 0.2 Cs-1 37 <0.3 < 0.2 Th-228 < 0.4 < 0.4 STA-02 Sr-89 (a) <4 Sr-90 (a) <0.4 Be-7 61.5 + 6.1 58.9 +/- 5.9 60.2+3.7 K-40 <10 <4 Co-60 < 0.4 <0.2 Ru-103 <0.5 <0.3 Cs-1 34 <0.3 <0.2 Cs-1 37 <0.3 <0.2 Th-228 < 0.4 < 0.4 STA-03 Sr-89 (a) <4 Sr-90 (a) <0.5 Be-7 69.5 +/- 6.9 56.4 +/- 5.6 63.0 + 18.5 K-40 <4 <10 Co-60 < 0.2 <0.3 Ru-103 < 0.4 <0.4 Cs-1 34 <0.3 <0.3 Cs-137 <0.2 <0.3 Th-228 < 0.4 <0.4 STA-04 Sr-89 (a) <2 Sr-90 (a) <0.3 Be-7 64.9 +/- 6.5 61.5 +/- 6.2 63.02 +/- 4.8 K-40 4.95 + 2.14 <5 Co-60 <0.3 <0.3 Ru-103 < 0.4 < 0.4 Cs-134 <0.2 < 0.2 Cs-137 < 0.2 <0.3 Th-228 < 0.4 <0.4 64 All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter samples.

TABLE B-3: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN AIR PAR TICULA TES North Anna Power Station, Louisa County, Virginia - 2000 1.0 E-03 pCi/m 3 +/- 2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average 12129-03/29 03/29-06/28 (a) <6 Sr-90 (a) < 0.8 Be-7 68.5 + 6.9 58.2 +/- 5.8 63.4 + 14.6 K-40 <5 <5 Co-60 <0.3 < 0.2 Ru-103 < 0.4 <0.3 Cs-134 <0.3 <0.2 Cs-137 <0.3 < 0.2 Th-228 < 0.4 <0.3 STA-05A Sr-89 (a) <3 Sr-90 (a) <0.5 Be-7 65.6 + 6.6 51.2 +/- 5.1 58.4 +/- 20.4 K-40 <4 <7 Co-60 < 0.2 <0.2 Ru-103 < 0.4 < 0.4 Cs-134 < 0.2 <0.2 Cs-137 <0.2 <0.2 Th-228 <0.5 <0.3 STA-06 Sr-89 (a) <3 Sr-90 (a) < 0.4 Be-7 57.3 +/- 5.7 29.2 +/-3.7 43.3 + 39.7 K-40 <5 <9 Co-60 <0.3 < 0.4 Ru-103 < 0.4 <0.5 Cs-134 < 0.3 <0.3 Cs-137 < 0.3 < 0.3 Th-228 < 0.4 < 0.4 STA-07 Sr-89 (a) <2 Sr-90 (a) < 0.4 Be-7 74.6 +/- 7.5 56.4 +/-5.6 65.5 + 25.7 K-40 <6 5.91 +/-1.69 Co-60 <0.3 <0.3 Ru-103 <0.4 < 0.4 Cs-134 <0.3 < 0.2 Cs-137 <0.2 < 0.2 Th-228 <0.3 < 0.3 65 All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter samples.

TABLE B-3: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN AIR PAR TICULA TES North Anna Power Station, Louisa County, Virginia - 2000 1.0 E-03 pCi/m3 + 2 Sigma Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide* 12/29-03/29 03/29-06128 STA-21 Sr-89 (a) < 10 Sr-90 (a) < 0.8 Be-7 75.6 +/- 7.6 56.8 +/- 4.17 66.2 +/- 26.6 K-40 <10 <3 Co-60 < 0.4 < 0.2 Ru-103 < 0.6 <0.3 Cs-1 34 < 0.4 < 0.2 Cs-137 < 0.4 < 0.2 Th-228 <0.5 <0.3 STA-22 Sr-89 (a) < 20 Sr-90 (a) <4 Be-7 64.0 +/- 6.4 49.0 +/- 3.92 56.5 + 21.2 K-40 <5 <9 Co-60 <0.3 < 0.3 Ru-103 <0.5 < 0.4 Cs-134 < 0.4 < 0.3 Cs-137 < 0.4 <0.3 Th-228 <0.5 < 0.4 STA-23 Sr-89 (a) <6 Sr-90 (a) < 1 Be-7 74.2+/- 7.4 <2 K-40 <6 <1 Co-60 < 0.3 <0.1 Ru-103 < 0.4 < 0.3 Cs-134 <0.3 < 0.2 Cs-137 <0.3 <0.1 Th-228 <0.5 <0.5 STA-24 Sr-89 (a) (b)

Sr-90 (a) (b)

Be-7 67.4 +/- 6.7 66.0 +/- 4.66 66.7 +/- 2.0 K-40 <8 <8 Co-60 <0.3 <0.3 Ru-103 < 0.4 < 0.4 Cs-134 <0.3 < 0.3 Cs-137 <0.3 <0.3 Th-228 < 0.4 < 0.4

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

66 (a) Strontium-89/90 analyses performed only on second quarter samples.

TABLE B-4: GROSS BETA, TRITIUMAND GAMMA EMITTER* CONCENTRATIONS IN PRECIPITATION Station 01A -- (On Site)

North Anna Power Station, Louisa County, Virginia - 2000 pCi/1 +/- 2 Sigma Page 1 of 1 Collection Dates Gross Beta Rainfall (inches) 12/29/99-01/27/00 5.0 +/- 0.8 2.10 01/27/00-02/23/00 2.2 +/- 0.5 2.15 02/23/00-03/29/00 4.0+/- 0.7 3.67 03/29/00-04/26/00 1.8+/- 0.6 5.45 04/26/00-05/31/00 2.7+/- 0.7 3.71 05/31/00-06/28/00 3.1+/- 0.7 3.17 06/28/00-07/25/00 10.0+/- 1.0 2.35 07/25/00-08/30/00 4.5+/- 1.1 3.74 08/30/00-09/27/00 5.2+/- 0.8 4.6 9/27/00-10/25/00 (a) (a) 10/25/00-11/29/00 <3 1.61 11/29/00-12/27/00 4.3 +/- 1.7 2.13 Average +/- 2 s.d. 3.89 +/- 5.1 SEMI-ANNUAL PRECIPITATION COMPOSITES 12/29/99 - 06/28/00 06/28/00 - 12/27/00 Be-7 = < 10 Be-7 = < 300 H-3 < 200 67 (a) No precipitation for October.

TABLE B-5 CONCENTRATIONS OF GAMMA EMITTERS* IN SOIL North Anna Power Station, Louisa County, Virginia - 2000 pCi/kg +/- 2 Sigma COLL STATION DATES Sr-89 Sr-90 Be-7 K-40 Cs-134 Cs-137 Ra-226 Th-228 Soil samples are collected every three years. Since they were collected in 1998, they were not collected during 2000.

68

TABLE B-6: GAMMA EMITTER* STRONTIUMAND TRITIUM CONCENTRATIONS IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 2000 pCi/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 01A 03/29/00 (a) (a) < 100 < 30 < 50 < 7 (b) <5 <6 06/28/00 <0.9 <0.8 < 100 < 30 < 50 < 10 (b) <9 <6 09/27/00 (a) (a) < 200 < 75 <900000 < 30000 <8 12/28/00 (a) (a) < 100 < 40 < 80 < 40 <50 <7 Average +/- 2 sd.

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

(a) Strontium-89/90 analyses performed only on second quarter sample.

(b) 1-131 results by Gamma. More sensitive method by radiochemistry not requested.

TABLE B- 7: GAMMA EMITTER*, STRONTIUM, TRITIUM, AND IODINE CONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 2000 pCi/i + 2 Sigma Page 1 of I Collection Dates Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-226 Th-228 STATION - 11 01/13/00 (a) (a) 4700 +/- 200 < 30 <60< <0.5 <3 <7 < 50 <5 02/15/00 (a) (a) (b) <30 < 60 <0.2 <3 <5 < 50 <5 03/15/00 (a) (a) (b) < 30 < 50 <0.3 <4 <6 < 70 <6 04/17/00 <4 <0.6 1500 +/- 100 < 30 < 60

• 0.4 <2 < 10

• 40 <4 05/11/00 (a) (a) (b) < 20 52.3 + 13.7 <0.3 <2 <10 < 40 <3 06/15/00 (a) (a) (b) < 30 < 30 < 0.6 <2 <9 < 50 <4 07/12/00 (a) (a) < 40 385 +/- 38 <0.8 <3 <10 < 60 <5 08/15/00 (a) (a) (b) < 30 < 80 <0.4 <3 <9 < 60 <6 09/15/00 (a) (a) (b) < 40 < 80 <0.8 <3 <10 < 60 <5 10/16/00 (a) (a) < 40 < 60 <0.1 <3 < 40 < 100 < 300 11/16/00 (a) (a) (b) < 20 < 40 <1.0 <3 <8 < 80 <10 12/18/00 (a) (a) (b) < 50 7.71 +/- 31.5 < 1.0 <4 < 200 <9 <8 Average +/- 2 sd 3100 +/- 4525 148 + 412 (a) Strontium-89/90 analyses performed only on second quarter sample.

(b) Tritium analysis performed on quarterly composite.

69

TABLE B-8: GAMMA EMITTER*, STRONTIUM AND TRITIUM CONCENTRATIONS IN SURFACE WATER North Anna Power Station, Louisa County, Virginia - 2000 pCi/I + 2 Sigma Page I of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131** Cs-137 Ba-140 Ra-226 Th-228 STAIIUN - 08 01/13 (a*) (a) 4500 +/- 200 < 30 < 50 <0.4 <3 <7 < 70 <6 02/15 (a*) (a) (b) < 30 < 50 <0.2 <3 <5 < 80 <6 03/15 (a*) (a) (b) < 30 < 50 <0.4 <3 <3 < 70 <6 04/17 <4 < 0.6 1500 +/- 100 < 30 < 30 <0.3 <2 <10 < 40 <4 05/11 (a,) (a) (b) <20 < 20 <0.6 <1 <10 < 30 <3 06/15 (a*) (a) (b) < 30 39.8 +/- 21.9 <0.6 <3 <10 <60 <5 07/12 a) (a) < 30 < 30 <0.6 <3 <7 < 70 <6 08/15 (a,) (a) (b) < 30 < 40 <0.4 <3 <8 < 70 <6 09/15 (a (a) (b) < 40 < 80 <0.6 <3 <10 <60 <5 10/16 (a*) (a) < 60 < 100 <0.8 <5 < 60 < 120 < 600 11/16 (a (a) (b) < 30 < 50 <0.8 <3 <10 < 90 <10 12/18 (a (a) (b) < 40 < 50 <0.8 <5 < 100 <6 < 100 Average +/- 2 sd 3000+/-4243 STATION - 09A 01/13 (a) (a) < 200 <20 < 40 <0.3 <3 <6 < 60 <6 02/15 (a) (a) (b) < 20 < 40 <0.2 <3 <5 < 60 <5 03/15 (a) (a) (b) < 30 < 60 <0.3 <4 <5 < 60 <5 04/17 <2 <0.9 < 200 <30 < 30 <0.3 <2 <10 < 50 <4 05/11 (a) (a) (b) <20 < 40 <0.3 <1 <10 < 30 <2 06/15 (a) (a) (b) < 40 < 100 <0.6 <4 <10 < 70 <6 07/12 (a) (a) < 40 < 90 <0.6 <4 <9 < 70 <5 08/15 (a) (a) (b) < 30 < 40 <0.4 <2 <6 <60 <5 09/15 (a) (a) (b) < 40 < 80 <0.7 <3 <10 < 60 <5 10/16 (a) (a) < 40 < 80 <0.9 <4 < 60 < 100 < 300 11/16 (a) (a) (b) < 30 < 50 <1 <3 <10 < 100 < 10 12/18 (a) (a) (b) < 50 < 50 <0.9 <3 < 100 11.4 +/- 2.6 <8 Average +/- 2 sd 70 (a) Strontium-89/90 analyses performed only on second quarter sample.

(b) Tritium analysis performed on quarterly composite.

TABLE B-9: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 2000 pCi/kg + 2 Sigma Page I of 1 STA-08 STA-09A STA-1 1 STA-08 STA-09A STA-1 1 Average Nuclide 02/21 (b) 02121 02/21 08107 08107 08/07 +/- 2 s.d.

Sr-89 (a) (a) (a)

Sr-90 (a) (a) (a)

Be-7 < 1000 < 400 < 300 < 250 227 +/- 119 < 457 K-40 11200 +/- 1100 12800 +/- 1300 12900 +/- 1300 3040 +/- 362 < 405 14700 +/- 950 10900 +/- 9160 Mn-54 < 40 < 30 < 20 < 20 < 30 < 50 Co-58 < 90 < 40 < 30 < 30 < 30 < 50 Co-60 < 40 < 30 < 20 < 30 < 30 < 40 Cs-134 < 50 < 40 < 30 < 20 < 28 < 40 Cs-137 205 +/- 39 114+/- 38 58.8 +/- 15.3 < 30 38.8 +/- 15.9 < 50 104+/- 149 Ra-226 1870 +/- 530 1720 570 1690 +/- 70 399 +/- 28.2 < 80 <110 1420 +/- 1370 Th-228 1100 +/- 110 846 +/- 85 849 +/- 85 < 40 < 50 < 70 932 _ 292 71 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

(b) Europium-I 52 was measured at 2250 +/- 260 pCi/kg.

TABLE B-J0: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 2000 pCi/kg +/- 2 Sigma Page I of I Station-08 Station-08 Average Nuclide 02121100 08107/00 +/- 2 Sigma Sr-89 (a) < 2000 Sr-90 (a) 100 +/- 60 Be-7 < 200 < 330 K-40 1280 +/- 210 1410 +/- 315 1345 +/- 185 Mn-54 <20 < 30.8 Co-58 <20 < 33.0 Co-60 <20 < 42.9 Cs-1 34 < 20 < 32.6 Cs-137 <20 167 + 23.6 Ra-226 615 +/- 256 313 +/- 22.7 464 + 427 Th-228 298 + 32 203 + 21.3 251 +/- 134 72

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

(a) Strontium 89/90 analyses performed annually.

TABLE B-11: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 2000 pCi/1 + 2 Sigma Page 1 of 2 MONTH NUCLIDE STATION-12 STATION-13 JANUARY Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 1360 +/- 140 1420 +/- 140 Cs-137 <4 <5 1-131 <0.3 <0.2 FEBRUARY Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 1580 +/- 160 1250 +/- 120 Cs-137 <4 <5 1-131 <0.3 <0.3 MARCH Sr-89 <3 <2 Sr-90 1.2 +/- 0.3 0.82 +/- 0.25 K-40 1370 +/- 140 1250 +/- 120 Cs-1 37 <4 <4 1-131 <0.3 <0.2 APRIL Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 1220 +/- 120 1400 +/- 140 Cs-1 37 <4 <5 1-131 <0.3 <0.3 MAY Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 1590 +/- 160 1310+ 130 Cs-1 37 <3 <4 1-131 <0.2 <0.3 JUN E Sr-89 <2 <2 Sr-90 0.75 +/- 0.23 1.1 +/- 0.2 K-40 1370 +/- 140 1340+ 130 Cs-137 <4 <3 1-131 <0.5 <0.4 73 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed quarterly.

(b) The gamma library did not contain K-40.

TABLE B-11: GAMMA EMITTER

• AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 2000 pCi/I + 2 Sigma Page 2 of 2 MONTH NUCLIDE STATION-12 STATION-13 JULY Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 1270+/- 130 1260 +/- 130 Cs-1 37 <4 <3 1-131 <0.3 <0.3 AUGUST Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 1420 +/- 84 1310 +/- 93 Cs-1 37 <4 <5 1-131 <0.3 <0.4 SEPTEMBER Sr-89 Sr-90 K-40 1430 +/- 127 1010 +/- 69 Cs-1 37 <6 <4 1-131 <0.6 < 0.4 OCTOBER Sr-89 (a) (a)

Sr-90 (a) (a)

K-40 (b) 1240 +/- 110 Cs-1 37 <4 <2 1-131 <0.6 <0.7 NOVEMBER Sr-89 (a) (a)

SR-90 (a) (a)

K-40 1390 +/- 140 1310+/- 110 Cs-1 37 <5 <2 1-131 <0.6 <0.5 DEC EMBER Sr-89 Sr-90 K-40 1340 +/- 53 1280 +/- 57 Cs-137 <5 <4 1-131 <0.6 <0.9 Aver age Sr-89 2 s.d I. Sr-90 0.98 +/-0.63 0.96 +/- 0.40 K-40 1395 +/- 224 1282 +/- 206 Cs-1 37 1-131 74 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed quarterly.

(b) The gamma library did not contain K-40.

TABLE B-12: GAMMA EMITTER* CONCENTRATIONS IN FISH North Anna Power Station, Louisa County, Virginia - 2000 pCi/kg + 2 Sigma Page 1 of I Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 02/24 08 Fish (a) 1730 +/- 270 < 30 < 30 51.1 +/- 20.6 02/22 25 Fish (a) 1880 +/- 230 <20 <20 <20 02/24 08 Catfish (b) 1630 +/- 210 <20 <20 34.1 +/- 16.8 02/23 25 Catfish (b) 1120 +/- 200 < 30 <20 < 30 08/10 08 Fish (a) 1670 +/- 217 <20 <20 < 20 08/09 25 Fish (a) 2380 +/- 330 <30 < 20 < 30 08/10 08 Catfish (b) 1120 +/- 203 <20 < 20 < 20 08/09 25 Catfish (b) 2060 +/- 306 <38 < 20 < 30 Avg. 08 1157 +/- 1813 42.6 + 24.0

+/- 2 s.d.

25 1860 +/- 1070 75 All gamma emitters other than those listed were <LLD.

(a) Non-bottom dwelling species of gamefish.

(b) Bottom dwelling species of fish.

TABLE B-13: GAMMA EMITTER* CONCENTRATIONS IN FOOD!VEGETA TION North Anna Power Station, Louisa County, Virginia -2000 pCi/kg +/- 2 Sigma Page 1 of 2 Collection Date Be-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATION 14 04/19 1290+/- 130 5930+/- 590 <50 <9 <8 <8 <100 <10 05/17 627 +/- 172 7270 +/- 730 < 30 < 30 < 20 < 20 < 300 < 30 06/21 584 +/- 180 7191 +/- 720 < 100 (a) < 30 < 20 < 20 < 400 < 30 07/25 1270 +/- 200 12300+/- 1200 < 50 < 30 < 30 < 20 < 400 < 30 08/16 2170 +/- 260 10300 +/- 1000 < 60 < 40 < 30 < 30 < 500 < 50 09/20 < 2040 11600 +/- 530 <10 < 590 < 20 < 20 < 550 < 30 10/18(b) < 300 < 200 < 300 < 30 < 20 < 20 < 400 < 90 STATION 15 04/19 983+/- 98 6840+/- 680 <50 <10 <10 <10 <200 <10 05/17 337 +/- 124 7970 +/- 800 < 20 < 20 <10 <10 < 200 < 20 06/21 283 +/- 120 9420 +/- 940 < 400 (a) < 20 <10 <10 < 200 < 20 07/25 933 +/- 107 13300 +/- 570 < 40 < 27 < 19 186 +/- 16.6 < 47 < 30 08/16 3540+/- 540 11100+/- 1100 <50 <80 <60 <60 < 1000 < 100 09/20 < 700 8140+250 <9 < 200 <8 <7 < 100 < 20 10/18(b) < 400 13100 +/- 800 < 300 < 40 < 30 < 20 < 400 < 100 STATION 16 04/19 429+/- 52 10300+/- 1000 <60 <8 <7 <6 <100 <10 05/17 907 +/- 203 11100 +/- 1100 < 20 < 30 < 20 < 20 < 400 < 40 06/21 409 +/- 138 9750 +/- 980 < 90 (a) < 20 < 20 < 20 < 200 < 20 07/25 351 +/-66.7 10600+/-440 <50 < 18 < 13 11.2+/-8.5 <30 <30 08/16 972 + 172 17100 + 1700 < 60 < 20 < 20 < 20 < 300 < 30 09/20 < 3200 12800 +/-600 < 10 < 980 < 40 < 30 < 700 < 60 10/18(b) < 400 14800 +900 < 270 < 40 < 30 < 30 < 500 < 100 STATION 21 04/19 < 200 7360 +/- 740 < 50 < 20 < 10 < 10 < 200 < 20 05/17 506 +/- 101 6910 +/- 690 < 20 < 20 < 10 < 10 < 200 < 20 06/21 < 80 7690 +/-770 <5 < 8 < 10 < 10 < 200 < 20 07/25 1590 +/- 280 13200 +1300 < 40 < 40 < 30 < 30 < 500 < 50 08/16 2210 +/- 220 18600 +/-1900 < 70 < 30 < 30 < 20 < 400 < 40 09/20 < 2850 13400 +570 < 10 < 850 < 40 < 30 < 60 < 40 10/18(b) 637 +/- 232 10800+/- 600 < 400 < 40 < 30 < 20 < 500 < 100 76

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

(a) More sensitive 1-131 method by radiochemistry not requested by customer nor ordered by lab. Specs not met for 1-13 1.

(b) Vegetation samples were not subbed in a timely manner. Some detection levels were not met.

TABLE B-13: GAMMA EMITTER

• CONCENTRA TIONS IN FOOD/VEGETA TION North Anna Power Station, Louisa County, Virginia -2000 pCi/kg + 2 Sigma Page 2 of 2 Collection Date Be-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATION 23 04/19 857 +/- 86 7270 +/- 730 < 50 <10 <8 <8 < 100 <10 05/17 661 +/- 111 7800 +/- 780 < 30 < 20 < 10 < 10 < 200 <20 06/21 221 +/- 93 9420 +/- 940 < 80 (a) <20 <10 < 10 < 200 <20 07/25 < 500 7470 +/- 750 < 50 < 70 < 50 < 50 < 1000 < 90 08/16 < 400 21300 +/- 2100 < 50 < 50 < 30 < 40 < 700 < 60 09/20 < 4400 21300 +/- 830 < 10 < 1300 < 60 < 40 < 800 < 100 10/18(b) 457 +/- 232 14500 +/- 800 < 300 < 40 < 30 < 30 < 500 < 100 Average 966+/-1570 11116+/-8038 98.8+247

+/- 2 s.d.

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

77 (a) More sensitive 1-131 method by radiochemistry not requested by customer nor ordered by lab. Specs not met for 1-131.

(b) Vegetation samples were not subbed in a timely manner. Some detection levels were not met.

TABLE B-14: DIRECT RADIATION MEASUREMENTS -- QUARTERLY AND ANNUAL TLD RESULTS North Anna Power Station, Louisa County, Virginia - 2000 mR/Std. Month (30.4 days) + 2 Sigma Page 1 of 1 Station First Qtr Second Qtr Third Qtr Fourth Qtr Quarterly Annual TLD Number 01/06100 03/29/00 07/05/00 09128/00 Average 03/29/00 07/05/00 09/28/00 01/11101 01 8.7 +/- 0.5 7.5 +/- 0.4 8.1 +/- 0.7 8.5 +/- 0.4 8.2 +/- 1.1 7.1 +/-0.8 02 5.5 +/- 0.2 4.1 +/- 0.2 5.3+/- 0.1 5.3+0.1 5.1 +/- 1.3 4.3 +/- 0.5 03 5.8 +/- 0.5 4.1 +/- 0.3 4.9 +/- 0.2 5.1 +/- 0.2 5.0 +/- 1.4 4.3 +/- 0.3 04 5.2+/-0.6 4.3 +/-0.5 5.0 +/- 0.5 51+/-0.4 4.9 +/- 0.8 4.5+/-0.4 05 6.6 +/- 0.4 5.3+/-0.4 6.6 +/- 0.6 6.7 +/- 0.2 6.3+/-1.3 5.7 +/-0.3 05A 6.0+/- 0.1 4.7 +/- 0.1 5.2 +/- 0.8 5.9 +/- 0.3 5.5+1.2 5.1 +/-0.3 06 7.3 +/- 0.1 6.8+/-0.5 7.9+/-0.8 7.8+/-0.5 7.5+/-1.0 6.3+/-0.7 07 6.3+/-1.2 4.8 +/-0.4 6.0 +/- 0.4 6.2+/-0.3 5.0 +/-0.1 5.8+/-1.4 21 6.6+/-0.9 4.9+/-0.3 5.9 +/- 0.2 6.0 +/-0.3 4.7 +/-0.3 5.9 +/- 1.4 22 6.9 +/- 0.8 6.3 +/- 1.0 7.5+/-0.6 7.3 +/-0.5 7.0+1.1 62+/-0.4 23 7.1 +/- 1.3 6.6 +/- 0.3 8.4+/-1.4 8.4+0.4 7.6 +/- 1.8 7.1+/-0.2 24 6.0+ 0.4 5.0 +/- 0.1 5.8 +/- 0.6 6.4 +/- 0.4 5.8 +/- 1.2 5.3+0.5 Average 6.5 +/- 1.9 5.4 +/- 2.3 6.4+/- 2.6 6.6+2.4 6.2 +/- 2.2 5.5+2.0

+/- 2 s.d.

78

TABLE B-15: DIRECT RADIATION MEASUREMENTS SECTOR - QUARTERL Y TLD RESULTS North Anna Power Station, Louisa County, Virginia - 2000 mR/Std. Month (30.4 days) + 2 Sigma Page ] of 2 Station First Qtr. Second Qtr. Third Qtr. Fourth Qtr. Average Number 01/06-03/29 03/29-07/05 07/05-09/28 09/28-01/11/01 +/- 2 s.d.

N-1 7.6 +/- 0.5 5.9 +/- 0.6 7.2 +/- 0.5 6.7 +/- 0.9 6.9 +/- 1.5 N-2 5.7 +/- 0.3 4.3 +/- 0.8 5.2 +/- 0.5 5.3 + 0.3 5.1 + 1.2 NNE-3 10.1 + 0.6 7.8 +/- 1.2 9.6 +/- 0.5 9.5 + 0.4 9.3 + 2.0 NNE-4 6.8 +/- 0.2 5.3 +/- 1.0 6.7 +/- 0.7 6.5 + 0.3 6.3+ 1.4 NE-5 8.6 +/- 1.0 7.0 +/- 0.4 8.1 +/- 0.3 7.9+0.5 7.9 +/- 1.3 NE-6 6.5 +/- 0.4 5.0 + 0.9 6.2 + 0.6 5.9 +/- 0.5 5.9 + 1.3 ENE-7 7.9 + 0.6 5.9 +/- 0.8 7.3 + 0.2 7.1 +/- 0.4 7.1 +1.7 ENE-8 5.4 +/- 0.4 4.1 +/- 0.2 5.7 + 0.4 5.5 +/- 0.0 5.2 + 1.5 E-9 7.9 +/- 0.4 6.6 +/- 0.4 8.1 + 0.4 7.6 +/- 0.3 7.6+1.3 E-10 6.9 + 0.5 5.5 +/- 0.4 7.1 + 0.7 6.7 +/- 0.3 6.6 + 1.4 ESE-11 7.1 +/- 0.6 5.6 +/- 0.5 6.6 +/- 0.4 6.7+0.5 6.5_+/- 1.3 ESE-12 7.9 + 0.3 6.2 + 0.4 7.5_+ 0.5 7.2 + 0.8 7.2 +1.5 SE-13 7.1 +/- 0.4 5.9 +/- 0.4 6.8_+ 0.1 6.5+/- 0.4 6.6+1.0 SE-14 9.6 +/- 0.2 7.9 +/- 1.3 9.3_+ 0.5 9.0+0.8 9.0 +/- 1.5 SSE-15 8.2 +/- 0.6 6.4 + 0.4 8.1 +/- 0.4 7.4+0.3 7.5 + 1.7 SSE-16 6.5 +/- 0.3 4.7 +/- 0.4 5.9 + 0.2 5.6 +/- 0.4 5.7 +/-1.5 S-17 10.2 +/- 0.2 8.5 +/- 0.7 10.3 0.2 9.8+0.5 9.7+ 1.7 S-18 5.9 +/- 0.3 4.3 +/- 0.3 5.2 0.3 4.7+0.1 5.0 + 1.4 SSW-19 8.8 +/- 0.9 7.8 +/- 0.1 9.3 1.1 8.7 + 0.7 8.7 + 1.2 SSW-20 5.6 +/- 0.7 4.0 +/- 0.5 5.0+ 0.2 4.7 + 0.2 4.8 +/- 1.3 SW-21 6.6 +/- 0.5 5.4+ 0.2 6.7 1.0 5.9+0.5 6.2 +/- 1.2 SW-22 7.3 +/- 0.2 5.8 + 1.0 7.1 + 0.4 6.8+0.4 6.8 +/- 1.3 WSW-23 8.7 +/- 0.3 7.3 + 0.4 8.4+ 0.4 7.6+0.2 8.0 +/-1.3 WSW-24 7.6 + 0.2 6.1 +/- 0.6 7.1 +0.5 6.9 +/- 0.4 6.9 +/- 1.2 W-25 9.6 +/- 0.3 8.0 +/- 1.3 8.8 + 0.4 8.1 +/- 0.4 8.6 +/- 1.5 W-26 6.3 +/- 0.3 4.5 +/- 0.6 5.7+ 0.4 5.5+0.2 5.5 + 1.5 WNW-27 6.1 +/- 0.6 4.8 +/- 0.5 6.0 +/- 0.3 5.6 +/- 0.4 5.6+1.2 WNW-28 6.8 +/- 1.0 4.9 +/- 0.4 6.0 +/- 0.2 5.6 +/- 0.3 5.8 +/- 1.6 NW-29 9.9 +/- 0.6 7.8 +/- 0.3 9.7 + 0.5 8.8 +/- 0.3 9.1 _ 1.9 NW-30 6.1 + 0.4 4.6 +/- 0.3 5.3 +/- 0.3 5.3+0.2 5.3+ 1.2 NNW-31 6.8 +/- 0.2 5.2+ 0.3 6.2 +/- 0.5 60 +/- 0.1 6.1 +/- 1.3 NNW-32 7.6 +/- 0.8 5.3 + 0.4 6.7 +/- 0.3 6.3 +/- 0.7 6.5 +/- 1.9 N-33 8.3 +/- 1.1 6.2 +/- 0.2 7.0 + 0.3 7.2+0.4 7.2+ 1.7 N-34 5.9 +/- 0.6 4.3 +/- 0.5 5.2 + 0.2 5.4 + 0.2 5.2 +/- 1.3 NNE-35 10.6 +/- 0.7 8.0 +/- 0.9 9.4_+/- 0.9 9.7 +/- 0.9 9.4 +/- 2.2 NNE-36 7.5 +/- 0.2 5.8 +/- 0.3 6.9 +/- 0.2 6.7 + 0.3 6.7 + 1.4 NE-37 9.0 +/- 0.5 7.0 + 0.5 8.2 +/- 0.2 7.9 +/- 0.6 8.0 +/- 1.7 NE-38 6.7 +/- 0.4 5.1 +/- 1.2 6.3 + 0.2 6.0 +/- 0.3 6.0_+/- 1.4 79

TABLE B-15: DIRECT RADIATION MEASUREMENTS SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 2000 mR/Std. Month (30.4 days) + 2 Sigma Page 2 of 2 Station First Qtr Second Qtr Third Qtr Fourth Qtr Average Number 01/06-03129 03/29-07105 07105-09128 09/28-01/11/01 +/- 2 S.d.

ENE-39 7.7+ 0.6 6.5 +/- 0.7 7.5 +/- 1.1 7.5 +/- 0.1 7.3 +/- 1.1 ENE-40 5.7+/- 0.3 3.9 +/- 0.3 5.9 + 0.2 5.6 + 0.5 5.3 +/- 1.9 E-41 8.0+/- 0.5 6.5 +/- 0.3 7.9 +/- 0.4 8.0 +/- 0.4 7.6 + 1.5 E-42 7.2+ 0.4 5.8 +/- 0.3 7.0 + 0.1 7.0-+0.6 6.0+/-2.9 ESE-43 7.4+ 0.7 5.5 +/- 0.7 6.7 + 0.9 6.8+0.5 6.6+1.6 ESE-44 7.9+ 0.4 6.1 +/- 1.1 7.7 + 0.3 7.5 +/- 0.3 7.3 +/- 1.6 SE-45 7.7 + 0.2 6.2 +/- 0.3 6.8 +/- 0.5 6.8_+0.3 6.9 +/- 1.2 SE-46 9.4 +/- 0.9 7.5+/- 1.2 9.8 +/- 0.6 9.0+0.4 8.9+2.0 SSE-47 8.6 + 0.7 6.4 0.4 8.3 +/- 0.6 7.5_+0.4 7.7+2.0 SSE-48 6.6 +/- 0.8 5.0+/- 0.4 6.3 +/- 0.9 5.9_+0.4 6.0+1.4 S-49 10.2 +/- 0.3 8.4+/- 1.4 11.1 +0.9 9.8_+0.9 9.9+2.2 S-50 5.4 +/- 0.3 4.2+ 0.3 5.4 + 0.5 4.9 +/- 0.1 5.0+/- 1.1 SSW-51 9.2 +/- 1.4 7.6 +/- 0.5 9.6 +/-0.3 9.3 +0.5 8.9 +/- 1.8 SSW-52 5.8 +/- 0.2 4.0 +/- 0.5 5.5 +/- 0.2 5.0_+0.4 5.1 +1.6 SW-53 7.1 +/- 0.6 5.3 + 0.4 6.8 + 0.7 61+/-0.5 6.3 +/- 1.6 SW-54 7.4 +/- 0.3 6.1 +/- 0.6 7.8 +/- 0.5 7.2_+0.3 7.1 +1.5 WSW-55 8.6+ 0.6 6.9 +/- 0.8 8.6 +/- 0.7 7.8_+0.3 8.0 + 1.6 WSW-56 8.0+/- 1.4 6.4 + 0.5 7.9 + 1.0 7.0 +/-0.2 7.3 +/- 1.5 W-57 9.3+ 0.2 7.6 + 0.5 9.5 +/- 1.2 8.5+0.4 8.7 +/- 1.7 W-58 6.7 +/- 0.6 4.7 + 0.4 5.8 + 0.3 5.2_+0.2 5.6 + 1.7 WNW-59 6.4 + 0.3 5.0 + 0.1 5.5 +/- 0.7 5.6_+0.2 5.6 +/- 1.2 WNW-60 6.9+ 1.2 4.8 + 0.6 6.3 +/- 0.1 5.8_+0.2 6.0 +/- 1.8 NW-61 9.7 +/- 1.1 7.9_+/-0.6 9.2 + 0.4 8.5_+0.7 8.8 + 1.6 NW-62 5.9 +/- 0.4 4.7+ 0.1 5.6 +/- 0.3 5.2 + 0.3 5.4 +/- 1.0 NNW-63 7.0 +/- 0.4 5.3+ 0.3 6.5 + 0.5 6.2_+0.1 6.3+1.4 NNW-64 6.9 +/- 0.6 5.4 + 0.4 6.4 + 0.8 6.3_+0.4 6.3 +/- 1.2 C-1 6.4 +/- 1.1 4.9+ 0.5 6.1 + 0.1 6.2+1.0 5.7 +/- 1.4 C-2 5.9 +/- 0.7 5.1+ 0.3 6.0 +/- 0.1 5.9_+0.1 5.7 +/- 0.8 C-3 6.3 +/- 0.1 5.1+ 0.2 6.0 + 0.2 6.0 + 0.3 5.9+1.0 C-4 6.8 +/- 0.9 5.1+ 0.2 5.9 +/- 0.5 6.0_+0.3 6.0 + 1.4 C-5 5.3 +/- 0.1 3.9 + 0.4 5.1 + 0.5 5.24+0.5 4.9 + 1.3 C-6 5.4 +/- 0.3 4.0 + 0.2 5.3 + 0.5 4.8_+0.2 4.9 + 1.3 C-7 7.4 +/- 0.3 5.7 + 0.5 7.9 +/- 0.5 6.9_+0.4 7.0 _ 1.9 C-8 7.5 + 0.5 5.9 + 0.2 7.7 +/- 0.7 6.9 +/- 0.6 7.0 + 1.6 Average 7.4 + 2.7 5.8 +/- 2.5 7.1 +/- 3.0 6.8+2.7 6.8 +/- 2.7 80

APPENDIX C LAND USE CENSUS - 2000 81

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 2000 August 1 - September 8 Nearest I Nearest Site Milch

• Meat Milch

• Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq. ft.

kM kM kM kM kM kM N 2.4 1.4 3.5 2.4 NNE 1.4 1.4 EE_2.3 2.5 NE 1.5 1.3 2.3 1.5 ENE 3.4 1.3 4.0 3.4 E 2.1 1.3 5.7 2.1 ESE 2.7 1.4 NONE 5.6 SE 2.3 1.4 2.3 2.3 SSE 1.6 1.5 4.5 4.1 S 1.7 1.5 NONE 1.5 I - - -, 4 -- I SSW 4 1.9 I 1.6 4 4 3.1 4.6 SW 5.0 1.7 NONE 5.0 WSW 2.7 1.8 2.7 2.7 W 2.4 1.7 7.1 8.0 WNW 1.8 1.6 6.5 3.5 NW 1.7 1.6 NONE 1.9 NNW 1.6 1.4 3.2 1.9 4 -1 + 1 4

• Note: No milch cow or goats within a 5 mile radius of North Anna Power Station kM = kilometer 82

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 2000 August 1 - September 8 Nearest I Nearest Site Mitch

• Meat Milch

• Veg. Garden Resident Boundary Cow Animal Goat 500 Sq. Ft.

Sector M M M M M M N 1.5 0.9 2.2 1.5 NNE 0.9 0.9 1.5 1.5 NE 0.9 0.8 1.4 0.9

- i - i ENE 2.1 0.8 2.5 2.1 E 1.3 0.8 3.5 1.3 ESE 1.7 0.9 NONE 3.5 SE 1.4 0.9 1.4 1.4 SSE 1.0 0.9 2.8 2.6 S 1.1 0.9 NONE-NONE 1.0 SSW 1.2 1.0 2.0 2.9 SW 3.1 1.1 NONE 3.1 WSW 1.7 1.1 1.7 1.7 W 1.5 1.1 4.4 5.0 WNW 1.1 1.0 4.1 2.2 NW 1.0 1.0 NONE 1.2 NNW 1.0 0.9 2.0 1.2

• Note: No milch cow or goats within a 5 mile radius of North Anna Power Station M = mile I 83

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION COMPARISON OF THE 2000 TO THE 1999 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 South 2.1 kM to 1.5 kM.

b. Sector N 3.2 kM to 2.4 kM

c. Sector ESE 5.3 kM to 5.6 kM

d. Sector SSE 1.6 kM to 4.1 kM V. The following change was observed in the nearest meat animal status as compared to the previous year:

a. Sector South 1.5 miles to deletion of the meat animal.

84

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 85

ANAL YTICAL PROCEDURESSYNOPSIS 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 and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979.

ANALYSIS TITLE Gross Beta Analysis of Samples ........................................................................... 87 Airborne Particulates .......................................................................... 87 W ater ......................................................................................... . . . .88 Analysis of Samples for Tritium (Liquid Scintillation) .............................................. 89 Analysis of Samples for Strontium-89 and 90 ........................................................ 90 T otal W ater .................................................................................. . . 90 M ilk .......................................................................................... . . . 90 Soil and Sedim ent ........................................................................... .90 O rganic Solids ................................................................................. 90 A ir Particulates ............................................................................. 91 Analysis of Samples for Iodine-131 ................................................................. 93 M ilk or W ater ................................................................................. 93 Gamma Spectrometry of Samples ..................................................................... 94 M ilk or W ater ................................................................................. 94 Dried Solids other than Solids and Sediment ............................................. 94 F ish ............................................................................................... 9 4 Soils and Sediments ........................................................................ 94 Charcoal Cartridge (Air Iodine) .................................... 94 Airborne Particulates ..................................................................... 94 Environmental Dosimetry ................................................................................. 96 86

GROSS BETA ANALYSIS OF SAMPLES 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/m 3) - ((S/T) - B/t))/(2.22 V E)

TWO SIGMA ERROR (pCi/m 3) = 2((S/T 2) + (B/t 2 ))" 2/2.22 V E)

LLD (pCi 3) = 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) 87

DETERMINATION OF GROSS BETA ACTIVITY IN WATER 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/l at the 2.83 sigma level), assuming that 1 liter of sample is used and that V2 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.

88

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)/,t) /2/ (2.22 V E)

LLD = 4.66 (Bl/,t) // (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 et counting time for the sample 89

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(N0 3) 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 SrCO 3 from the sample after yttrium 2

separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm aluminum absorber for low level beta counting.

Milk Stable strontium carrier is added to I 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 SrNO 3 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 SrCO 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm 2 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(N0 3 )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 SrCO 3 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 Sr(N0 3) 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 SrCO 3 from the sample after 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.

90

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(N0 3) 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 SrCO 3 from the sample after yttrium separation. This precipitate is counted on a nylon planchette and is covered with 80 mg/cm 2 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/Dt-Bc-BA)/(2.22 V Ys DFsR-89EsR- 89)

TWO SIGMA ERROR Sr-89 2(N/Dt+Bc+BA)/et) /2/(2.22 V YsDFsR-89EsR-89)

LLD Sr-89 4.66(Bc+BA)/ ot)"/2 /(2.22 V YsDFSR-89ESR- 89)

RESULT Sr-90 (N/st-B)/(2.22 V Y1 Y2 DF IF E)

TWO SIGMA ERROR Sr-90 2(N/ot+B) /et) /(2.22 V Y, Y2 DF E IF)

LLD Sr-90 4.66(B/ot) 1/(2.22 V Y, Y2 IF DF E)

Where: N total counts from sample ot 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 0.016(K) + (K) EY/abs)(IGY- 90 )

Ys chemical yield of strontium DFSR-89 decay factor from the mid collection date to the counting date for SR-89 K (Net-Bc)y-9 0 )/Ey-9 0 IFy-90 DFy-9oY 1 )

DFy.90 the decay factor for Y-90 from the "milk" time to the mid count time efficiency of the counter for Y-90 ingrowth factor for Y-90 from scavenge to time to milking time IGy-9 0 = the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 91

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)

Y = 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 92

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/ot-B)/(2.22 V Y DF)

TWO SIGMA ERROR 2((N/et+B) /at)"2 /(2.22 E V Y DF)

LLD = 4.66(B/st)"2 /(2.22 E V Y DF)

Where N = total counts from sample et - 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-0.006 IMs)

Es = efficiency of the counter determined from an 1-13 1 standard mount Ms mass of Phi 2 on the standard mount, mg M = mass of PDI2 on the sample mount, mg 93

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 Ge(Li) detector coupled to a mini computer-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 Ge(Li) detector coupled to a mini computer-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 Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Soil and Sediments Soils and sediments are dried at a low temperature, less than 100IC. 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 Ge(Li) detector coupled to a min-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 Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) 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 Particulate 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 Ge(Li)detector coupled to a min-computer-based data acquisition system which performs pulse height analysis.

A mini-computer software programs defines peaks by certain changes I 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.

94

Calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume of pCi/mass:

RESULT = (s-b)/2.22 T E V F DF)

TWO SIGMA ERROR = 2(S+B)" 2 (2.22 t E V F DF)

LLD = 4.66 (B)1/2(2.22 t E V F DF) where: S Area, in counts, of sample peak and background (region of spectrum of interest.)

B Background area, in counts, under sample peak, determined by a linear Interpolation of the representative backgrounds on peak.

t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)

F = fractional gamma abundance (specific for each emitted gamma)

DF = decay factor from the mid-collection date to the counting date 95

ENVIRONMENTAL DOSIMETRY Teledyne Brown Engineering uses a CaSO 4: Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.

Following the field exposure period TLDs are placed in a Teledyne Brown Engineering Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use.

The transit controls are read in the same manner.

In June of 2000, clients were notified that TBE would no longer a provider of environmental TLD service.

Calculations of results and the two sigma error in net milliRoentgen (mR):

RESULT = D=(Di+D2+D3+D4)/4 TWO SIGMA ERROR = 2(D,-D)2+(D-D)2+D3-D)2+(D4-D)2)/3)"

Where: D1 = the net mR of area 1 of the TLD, and similarly for D2 , D3 , and D 4 D = 11 K/R 1-A 1I = the instrument reading of the field dose in area 1 K = the know exposure by the Cs-137 dose on area 1 RI = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs D the average net mR of all 4 areas of the TLD 96

APPENDIX E INTERLABORATORY COMPARISON PROGRAM 97

INTERLABORATORY COMPARISION PROGRAM The US Environmental Protection Agency (EPA) discontinued their Interlaboratory Comparison Program in December 1998. Since the EPA is no longer involved in the program, there are no "approved" laboratories for Intercomparison Studies; however, Teledyne Brown Engineering participates in the Analytics, Inc. and Environmental Resource Associates (ERA) programs to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability.

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 EPA Program and for Analytics when there were at least two data points to plot.

98

ANALYTICS CROSS CHECK COMPARISON PROGRAM 2000 Teledyne Brown Analytics Sample Date Media Nuclide Engineering Result (a) Result Ratio (b) 03/20/00 Milk 1-131 18 +/- 1 20+/- 1 0.90 Cr-51 381 + 38 387 +/- 19 0.98 Cs-134 132 +/- 13 143 +/- 7 0.92 Cs- 137 128+/- 13 114 + 6 1.12 Co-58 89 +/- 9 79 +/- 4 1.13 Mn-54 195 +/- 20 176 +/- 9 1.11 Fe-59 161 +/- 16 144 +/- 7 1.12 Zn-65 171 +/- 17 165 +/- 8 1.04 CO-60 179 +/- 18 176 +/- 9 1.02 03/20/00 Milk Sr-89 13+/- 3 25+/- 1 0.52(c)

Sr-90 16+/- 1 19+/- 1 0.84 06/19/00 Air Filter Ce- 141 143 + 8 132 +/- 7 1.08 Cr-51 229 + 17 198 +/- 10 1.16 Cs- 134 74 +/- 4 81 +/- 4 0.91 Cs-137 143 +/- 8 115 +/- 6 1.24 Co-58 89 +/- 5 77 +/- 4 1.16 Mn-54 102 +/- 6 84+/- 4 1.21 Fe-59 98 +/- 6 75 +/- 4 1.31 Zn-65 188 +/- 11 139+/- 7 1.35 Co-60 113 +/- 7 104 +/- 5 1.09 06/19/00 Cartridge 1-131 106 +/- 6 88+/- 4 1.20 06/19/00 Air Filter Sr-90 88+/- 5 96+/- 5 0.92 06/19/00 Air Filter Gross Alpha 103 +/- 6 93 +/- 5 1.11 Gross Beta 210+/- 6 193+/- 10 1.09 09/18/00 Milk 1-131 97+/- 10 87 +/- 4 1.11 Ce- 141 83 +/- 8 77 +/- 4 1.08 Cr-51 323 +/- 40 304 +/- 15 1.06 Cs- 134 98 +/- 10 102 5 0.96 Cs-137 117+/- 12 107 +/- 5 1.09 Co-58 64 +/- 6 60 +/- 3 1.07 Mn-54 99 +/- 10 88 + 4 1.13 Fe-59 132 +/- 13 119 +/- 6 1.11 Zn-65 218 +/- 22 196 +/- 10 1.11 Co-60 209 +/- 21 197 +/- 10 1.06 99

ANALYTICS CROSS CHECK COMPARISON PROGRAM 2000 (cont.)

Teledyne Brown Analytics Sample Date Media Nuclide Engineering Result (a) Result Ratio (b) 09/18/00 Milk Sr-89 14+ 1 15++/- 1 0.93 Sr-90 18+ 1 14 +/- 1 1.29 09/18/00 Milk Sr-89 77 + 8 90 +- 5 0.86 Sr-90 58 +/- 1 59++/- 3 0.98 09/18/00 Milk 1-131 83 +/- 8 84 + 4 0.99 Ce- 141 470 +/- 47 460 +/- 23 1.02 Cr-5I 266 + 35 256 + 13 1.04 Cs- 134 150 15 150 8 1.00 Cs-137 155 +/- 15 138 + 7 1.12 Co-58 53 +/- 5 47 + 2 1.12 Mn-54 191 +/- 19 171 9 1.12 Fe-59 115 +/- 12 99 + 5 1.16 Zn-65 237 + 24 208 + 10 1.14 Co-60 133 + 13 125 - 6 1.06 09/18/00 Milk Fe-55 140 + 60 99 + 5 1.41 Sr-89 65 + 7 74 +/- 4 0.88 Sr-90 35 + 1 37++/- 2 0.90 09/18/00 Air Filter Ce-141 90 + 9 110 + 6 0.82 Cr-51 92 + 25 133 +/- 7 0.69 Cs- 134 48 +/- 5 74 +/- 4 0.64 Cs-137 107 +/- 11 126 + 6 0.85 Co58 27+/- 4 34 +/- 2 0.80 Mn-54 42 + 4 52 +/- 3 0.80 Fe-59 24 + 8 31 +/- 2 0.77 Zn-65 65 +/- 9 77 + 4 0.84 Co-60 112++/- 11 142 + 7 0.79 Footnotes:

(a) Teledyne Results - counting error is two standard deviations. Units are pCi/liter for water and milk. For gamma results, if two standard deviations are less than 10%, then a 10% error is reported. Units are total pCi for air particulate filters.

(b) Ratio of Teledyne Brown Engineering to Analytics results.

(c) Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted and was documented in the analyst's training file. Subsequent tests on two milk samples spiked with Sr-89 produced correct results.

100

ERA* STATISTICAL

SUMMARY

PROFICIENCY TESTING (PT) PROGRAM - 2000 ERA Expected Known TBE Dev. Known Control Warning Value Result (b) (c) Limits (d) Limits (e) Performance DATE NUCLIDE (pCi/l)(a) (pCi/I) (pCi/i) (pCi/I) (pCi/I) Evaluation (f) 2/10/00 Gr-A 58.4 83.6 14.6 33.3-83.5 41.5-75.3 NA (g) 2/10/00 Gr-B 16.8 15.4 5.00 38.1-25.5 3.1-22.6 A 2/24/00 U(NAT) 6.07 5.77 3.00 0.870-11.3 2.61-9.53 A 2/24/00 Ra-226 8.26 7.20 1.24 6.11-10.4 6.83-9.69 A 2/24/00 Ra-228 2.25 2.37 0.56 1.28-3.22 1.60-2.90 A 2/24/00 Gr-A 25.4 14.0 6.35 14.5-36.3 18-132.7 NA 2/24/00 Gr-B 42.1 34.0 5.00 33.4-50.8 36.3-47.9 CE 2/25/00 Ba-133 98.2 91.7 9.82 81.5-115 86.9-110 A 2/25/00 Co-60 99.6 101 5.00 90.9-108 93.8-105 A 2/25/00 Cs-134 49.2 48.0 5.00 40.5-57.9 43.3-55.0 A 2/25/00 Cs-137 209 76.3 10.4 191-227 197-221 NA 2/26/00 Sr-89 16.4 15.7 5.00 7.70-25.1 10.6-22.2 A 2/26/00 Sr-90 28.9 29.0 5.00 20.2-37.6 23.1-34.7 A 2/26/00 Co-60 64.4 68.3 5.00 55.7-73.1 58.6-70.2 A 2/26/00 Cs-134 12.3 12.0 5.00 3.60-21.1 6.53-18.1 A 2/26/00 Cs-137 72.2 76.3 5.00 63.5-80.9 66.4-78.0 A 3/01/00 H-3 23800 22300 12380 21100-26500 21000-26500 A 101

ERA* STATISTICAL

SUMMARY

PROFICIENCY TESTING (PT) PROGRAM - 2000 ERA Expected Known TBE Dev. Known Control Warning Value Result (b) (c) Limits (d) Limits (e) Performance DATE NUCLIDE (pCi/l)(a) (pCi/I) (pCi/I) (pCi/I) (pCi/I) Evaluation (f) 5/18/00 Sr-89 22.5 18.3 5.00 13.8-31.2 16.7-28.3 A 5/18/00 Sr-90 9.6 8.33 5.00 0.9-18.3 3.83-15.4 A 5/23/00 1-131 19.9 2.03 3.00 14.7-25.1 16.4-23.4 NA 9/1/00 Ra-226 13.0 9.70 1.15 7.41-18.6 9.25-16.8 A 9/1/00 U (NAT) 63.4 57.0 4.44 52.6-74.2 56.1-70.7 A 9/1/00 Ra-228 2.83 2.99 6.34 2.21-3.77 2.47-3.51 A 9/1/00 Ra-228 13.0 10.0 3.25 7.41-16.8 9.25-16.8 A 9/1/00 Sr-90 26.2 28.6 1.40 17.5-34.9 20.4-32.0 A 9/1/00 Gr-A 7.17 6.90 1.11 DL- 15.9 1.40-12.9 A 9/1/00 Gr-B 87.5 88.8 9.76 70.2-105 76.0-99.0 A 9/1/00 H-3 8320 8740 174 6910-9730 7360-9280 A Footnotes:

• All ERA samples are water.

(a) 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.

(b) Average+ I sigma.

(c) Established per the guidelines contained in the EPA's National Standards for Water Proficiency Testing Criteria Document, December 1998, as applicable.

(d) Established per the guidelines contained in the EPA's National Standards for Water Proficiency Testing Criteria Document, December 1998, as applicable.

(e) Established per the guidelines contained in the EPA's National Standards for Water Proficiency Testing Criteria Document, December 1998, as applicable.

(f) A= Acceptable. Reported Result falls within the Warning 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 Warning Limit.

(g) For Westwood, NJ results outside control limits, an investigation was not instituted. After the relocation to Knoxville, TN, it has been determined that the vast majority of outlying results were caused by analyst error or equipment failure. These possibilities were eliminated by the relocation.

102

1-131 IN MILK 120 100 U

80 a 60 w I 40 20 0 0

Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE

• Analytics Ce-141 IN MILK 800 U

700 600 500 400 +

300 200 100 l a 0

Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE m Analytics Cr-51 IN MILK 1200 1000 B 800 600 400 a a

200 a If 0

Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE mAnalytics

Cs-134 IN MILK 300 U

200 I

100" a 0"

Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01 TBE - Analytics Cs-137 IN MILK 200 4

150 100 a 50 a m J

Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE mAnalytics Mn-54 IN MILK 200 150 p I a

100 a 50 0 m Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE mAnalytics

Fe-59 IN MILK 200 150 I B A

100 U 50 I 0T Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE

• Analytics Zn-65 IN MILK 250 200 B 11 150 U I 100 50 0

Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE m Analytics Co-60 IN MILK 250 200 a I a 150 a 100 0

50 0J Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01

• TBE mAnalytics

Sr-90 IN MILK 50 40 a 30 20 I U 10 0

Jul-98 Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00 Oct-00 Jan-01

• TBE mAnalytics

Ce-141 IN FILTERS 600 U

500 400 300 200 a a 100 0

Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• TBE m Analytics Cr-51 IN FILTERS 900 800

• 700 U 600 500 400 300 200 a a 1000 Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• TBE

• Analytics Cs-134 IN FILTERS 200 150-100 If 50 0

0 Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• TBE

• Analytics

Cs-137 IN FILTERS 450 300 150 a

a 0

Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

. TBE mAnalytics Mn-54 IN FILTERS 160 120 U,

80 a 40 0

Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• • TBE mAnalytics Fe-59 IN FILTERS 200 150 100 B U 50 0

Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• TBE

• Analytics

Zn-65 IN FILTERS 250 200 150 4 0 100 50 0

Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• TBE m Analytics Co-60 IN FILTERS 250 200 a 150 a

100 a 50 Nov-98 Feb-99 May-99 Aug-99 Dec-99 Mar-00 Jun-00

• TBE mAnalytics

GROSS ALPHA IN WATER 90 75 60 45 30 m 15 0B 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00 08/12/00 10/01/00

• TBE *ERA GROSS BETA IN WATER 100 a

80 60 40 20 A 0

07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00 08/12/00 10/01/00 I*TBE mERA U (NAT) IN WATER 80 60 40 20 0T 07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00 08/12/00 10/01/00

• TBE EERA

R226 IN WATER 14 m

12 10 8U 6

4 2

07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00 08/12/00 10/01/00

[

• TBE mERA Ra-228 IN WATER 14 0

12 10 1 8

6 4 0 2 -lL ,

0 07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00 08/12/00 10/01/00

• TBE mERA Co-60 IN WATER 120 100 80 2

60 40 20 0

02/25/00 02/25/00 02/25/00 0)2/25/00 02/25/00 02/26/00 02/26/00 02/24/00 L*TBE mERA

Cs-134 IN WATER 60 50" 9 40 30 20 w

10 02124/00 02/25/00 02/25/00 02/25/00 02/25/00 02/25/00 02/26/00 02/26/00

[*TBE MERA Cs-137 IN WATER 250 0

200 150 100 50 0 - - I..

02/24/00 02/25/00 02/25/00 02/25/00 02/25/00 02/25/00 02/26/00 02/26/00

• TBE mERA H-3 IN WATER 30000 25000 I

20000 15000 10000 91 5000 a 0

07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00

• TBE . ERA

Sr-89 IN WATER 30 25 20 15 10 5

0*

07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00

• TBE mERA Sr-90 IN WATER 50 40-30- m 20 10 0 T 07/09/99 08/28/99 10/17/99 12/06/99 01/25/00 03/15/00 05/04/00 06/23/00 08/12/00 10/01/00

.TBE .ERA