Text

Virginia Electric and Power Co., North Anna Power Station Units 1 and 2, Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report
	ML013460416
Person / Time
Site:	North Anna
Issue date:	11/02/2001
From:	Heacock D; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	+sunsi/sispmjr=200603, -RFPFR, 01-243A
	Download: ML013460416 (112)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 2, 2001 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.

NAPS/JHL Docket Nos.

License Nos.

01-243A 50-338 50-339 72-16 NPF-4 NPF-7 SNM-2507 Gentlemen:

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

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Our letter dated April 27, 2001 (Serial No.01-243) provided the 2000 Annual Radiological Environmental Operating Report for North Anna Units 1 and 2 and the North Anna Independent Spent Fuel Storage Installation. The April 2001 submittal indicated that the report was not complete due to the vendor, Teledyne Brown Engineering, relocating their laboratory from New Jersey to Tennessee. We stated that the 2000 Annual Radiological Environmental Operating Report will be updated following receipt of final analyses from the vendor. The purpose of this letter is to provide the updated 2000 Annual Radiological Environmental Operating Report If you have any questions or require additional information, please contact us.

Very truly yours, D. A. Heacock' Site Vice President Enclosure Commitments made by this letter: None

cc:

U. S. Nuclear Regulatory Commission Region II 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 NOR TH ANNA POWER STATION Radiological Environmental Monitoring Program January 1, 2000 to December 31, 2000 Final Report Prepared by DOMINION VIRGINIA POWER and TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SER VICES I

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

Reviewed by Approved by:

James B. Breeden Supervisor Radiological Analysis and Material Control Erich W. Drey r Supervisor Health Physics Technical Services X. o -H. Stafford Manager Radiological Protection 2

Table of Contents Section Title Page Preface...................................................................................................................................

6 Executive Sum m ary......................................................................................................

7 I.

Introduction......................................................................................................

9 II.

Sam pling and Analysis Program........................................................................

12 III.

Program Exceptions............................................................................................

28 IV.

Summary and Discussion of 2000 Analytical Results........................................

31 A.

A irborne Exposure Pathw ay.....................................................................

32

1.

A ir 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.

Surface W ater...................................................................................

35 C.

A quatic Exposure Pathw ay........................................................................

35

1.

Sedim ent/Silt...................................................................................

35

2.

Shoreline Soil...................................................................................

36 D.

Ingestion Exposure Pathw ay......................................................................

40

1.

M ilk...................................................................................................

40

2.

Fish...................................................................................................

40

3.

Food/V egetation...............................................................................

40 E.

Direct Radiation Exposure Pathw ay..........................................................

41

1.

TLD D osim eters...............................................................................

41 V.

Conclusion..............................................................................................................

43 3

Table of Contents (Continued)

Section Title Page VI.

References...............................................................................................................

47 VII.

Appendices..............................................................................................................

49 Appendix A - Radiological Environm ental M onitoring.....................................

50 Program Annual Summary Tables - 2000 Appendix B - Data Tables...................................................................................

58 Appendix C - Land Use Census -2000..............................................................

82 Appendix D - Synopsis of Analytical Procedures..............................................

86 Appendix E - Interlaboratory Comparison Program..........................................

98 List of Trending Graphs

1.

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

33

2.

Tritium in River W ater........................................................................................

33

3.

Tritium in Surface W ater...................................................................................

37

4.

Cobalt-58 in Sedim ent Silt.................................................................................

37

5.

Cobalt-60 in Sedim ent Silt.................................................................................

38

6.

Cesium -134 in Sedim ent Silt..............................................................................

38

7.

Cesium -137 in Sedim ent Silt..............................................................................

39

8.

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

39

9.

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

42

10.

Environm ental Radiation-TLDs..........................................................................

42 4

Table of Contents (Continued)

List of Tables Section Page

1.

Radiological Sampling Station Distance and Direction from 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-13 1 Concentrations in Filtered Air...............................

59 B-2 Concentrations of Gross Beta in Air Particulates..........................

61 B-3 Gamma Emitter and Strontium Concentrations in Air Particulates..............

65 B-4 Gross Beta, Tritium and Gamma Emitter Concentrations in Precipitation..........

68 B-5 Concentrations of Gamma Emitter and Strontium in Soil....................

69 B-6 Gamma Emitter, Strontium and Tritium Concentrations in Ground/Well Water......

70 B-7 Gamma Emitter, Strontium, Tritium, and Iodine Concentrations in River Water.....

70 B-8 Gamma Emitter, Strontium and Tritium Concentrations in Surface Water.........

71 B-9 Gamma Emitter and Strontium Concentrations in Sediment Silt................

72 B-10 Gamma Emitter and Strontium Concentrations in Shoreline Soil...............

73 B-1I Gamma Emitter and Strontium Concentrations in Milk......................

74 B-12 Gamma Emitter Concentrations in Fish.................................

76 B-13 Gamma Emitter Concentrations in Food/Vegetation.......................

77 B-14 Direct Radiation Measurements - Quarterly & Annual TLD Results.............

79 B-15 Direct Radiation Measurements - Sector Quarterly TLD Results...............

80 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 as a "pre-operational baseline."

Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, other causes such as the Chernobyl accident, or natural variation.

Teledyne Brown Engineering Environmental Services provides sample analyses for various radioisotopes as appropriate for each sample media. Participation in an interlaboratory comparison program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLD). This ensures that analyses are as accurate as possible. Samples with extreme low levels of radiation which cannot be detected are therefore reported as being below the LLD. The NRC also mandates a "reporting level." Licensed nuclear facilities must report any releases equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to in percent of reporting level.

Analytical results are divided into five categories based on exposure pathways: Airborne, 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 7

to preoperational levels. No increase was noted and there was no detection of fission products or other man-made isotopes in the airborne particulate media during 2000.

"* The waterborne exposure pathway includes ground/well water, river water, and surface water samples. No man-made isotopes were detected in Lake Anna surface water except for tritium. The average tritium activity in surface water for 2000 was 2850 pCi/liter which was 14.25% 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 1978, 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 3025 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 148 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 and europium-152 was detected.

During the preoperational period, cesium-137 was detected.

The europium-152 was attributed to possible cross-contamination in the laboratory. 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 0.31 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 AnnAi Nuclear Power Station 8

I. INTRODUCTION 9

DOMINION VIRGINIA POWER COMPANY NOR TH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM L

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 Environmental Services is responsible for sample analysis and submitting report of radioanalysis. The results are used to determine if changes in radioactivity levels could be attributed to station operations. Measured values are compared with control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected.

This preoperational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation.

D. Occasional samples of environment media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM.

These 10

concentrations are based upon the annual dose commitment recommended by 1 OCFR50, 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

II. SAMPLING AND ANAL YSIS PROGRAM A.

Sampling Program

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

2.

For routine TLD measurements, two dosimeters made of CaSO4: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 Environmental Services located in Knoxville, TN.

4.

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

13

TABLE 1 (Page 1 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 Environmental Thermoluminescent Dosimetry (TLD)

NAPS Sewage Treatment Plant Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA Bearing Cooling Tower Sturgeon's Creek Marina Parking Lot "C" (on-site)

Good Hope Church Parking Lot "B" Lake Anna Marina Weather Tower Fence Route 689 Near Training Facility 01 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 0.20 5.30 7.10 5.10 4.20 3.20 4.70 7.30 1.00 1.00 0.93 22.00 0.06 3.20 0.24 4.96 0.20 1.46 0.36 2.43 0.30 NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW N

N NNE NNE NE NE ENE ENE E

420 2250 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 Quarterly

& Annually Quarterly

& Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control 14

TABLE 1 (Page 2 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 Environmental Thermoluminescent Dosimetry (TLD)

"Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)

"Aspen Hills" Elk Creek NAPS Access Rd.

Elk Creek Church NAPS Access Rd.

Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)

South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate Construction Side Laydown Area Lake Anna Campground

1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA E-10/42 ESE-1 1/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 2.85 0.12 4.70 0.75 5.88 0.93 2.33 0.47 1.55 0.42 5.30 0.6 4.36 0.38 1.00 0.32 1.55 1.00 1.40 0.45 NW-30/62 2.54 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 0.07 3.43 7.30 22.00 7.10 11.54 E

ESE ESE SE SE SSE SSE S

S SSW SSW SW SW WSW WSW W

W WNW WNW NW NW NNW NNW SSE NW WSW WSW 930 1030 1150 1380 1370 1580 1650 1730 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 3190 Quarterly 3490 3440 1670 3250 2430 2570 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 15 Control Control Control Control

TABLE 1 (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 and Radioiodine Surface Water River Water Ground Water (Well Water)

Precipitation Aquatic Sediment Shoreline Soil NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream)

(Route 208 Bridge)

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

Biology Lab Biology Lab Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (Downstream)

Waste Heat Treatment Facility (Second Cooling Lagoon) 01 0.20 02 03 04 05 05A 06 07 21 22 23 24 5.30 7.10 5.10 4.20 3.20 4.70 7.30 1.00 1.00 0.93 22.00 08 1.10 09 09A NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW SSE 2.20 NW 12.90 WNW 11 5.80 OIA 0.75 OIA 0.75 08 1.10 09A 12.90 11 5.80 08**

1.10 SE SE SE SSE 420 Weekly 2050 2430 2870 200 110 1150 1670 3010 2420 1580 3250 1480 3200 2950 1280 1380 1380 1480 WNW 3200 SSE SSE 1280 1480 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Monthly Monthly Monthly Monthly Quarterly Monthly Control Control Control Semi-Annually Semi-Annually Control Semi-Annually Semi-Annually 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 1 (Page 4 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 NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)

"Aspen Hills" Orange, VA Holladay Dairy (R.C. Goodwin)

Terrell's Dairy (Fredericks Hall)

Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Orange Food Products (Broadleaf or at harvest Vegetation)

Route 713 Route 614 Route 629/522 End of Route 685 Aspen Hills 0.20 5.30 7.10 5.10 4.20 3.20 4.70 7.30 1.00 1.00 Soil "Milk 01 02 03 04 05 05A 06 07 21 22 23 24 12 13 08 25 14 15 16 21 23 0.93 NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW NW SSW SSE NW NE SE NW WNW SSE 420 Once/3 years 2050 2430 2870 200 110 1150 1670 3010 2420 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years 1580 Once/3 years 3250 Once/3 years 3100 Monthly 2050 Monthly 1480 Semi-Annually 3120 Semi-Annually Control Control 430 Monthly if available 1330 Monthly if available or at harvest 3140 Monthly if available or at harvest (Control) 3010

" Monthly if available or at harvest 1580 Monthly if available or at harvest 17 0.93 22.00' 8.30 5.60 1.10 16.5 1.20 1.37 12.60 1.00 Fish

Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Map Environmental Station Designation Identification Designation Identification (a)

(a)

(a) 1 IA 2

3 4

5 5A 6

7 8

9 9A 11 12 13 14 15 16 21 22 23 24 25 01,NE-5/37 O1A,SE-13/45 02,SSW-20/52 03,C-5/16 04 o5 05A,N-2/34 o6,ESE-12/44 07,C-1&2 08-Water, Fish Sediment Shoreline Soil (d) 09 09A-Water sample, sediment 11-River Water, Sediment 12-Milk 13-Milk 14-Vegetation, NE-6/38 Vegetation Vegetation 21,WNW-27/59 22,WSW-24/56 23-SSE-15/47 24,C-3&4 25-Fish 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.

7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-1 1/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-40/36 E-10/42 (a)

(a)

(a)(b)

(c)

---I 00j

cuzl

---I 0

0 C0,3

l CoLf

B.

Analysis Program

1.

Table 2 summarizes the analysis program conducted by Teledyne Brown Engineering Environmental Services 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

TABLE2 (Page 1 of3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS Thermoluminescent Dosimetry (TLD)

(84 Routine Station TLD's) 12 Station TLD's Airborne Radioiodine Airborne Particulate Surface Water Quarterly Gamma Dose Annually Weekly Weekly Quarterly (a) 2nd Quarter Composite Monthly Quarterly (a) 2nd Quarter Composite Gamma Dose 1-131 Gross Beta Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)

Sr-89 Sr-90 2mR+2mR mR/std. month 2mR+2mR mR/std. month 0.07 0.01 0.05 0.06 (c)

(c) 1(b) 15 30 15 15 30 30 15 15 18 60 15 2000 (c)

(c) pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/l pCi/l pCi/l pCi/1 25 LLDs indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering Environmental Services may be lower than those listed.

Quarterly Composites of each location's samples are used for the required analysis.

LLD for non-drinking water is 10 pCi/liter.

There are no required LLDs for strontium-89/90. LLDs are those achieved by Teledyne Brown Engineering Environmental Services.

(a)

(b)

(c)

TABLE2 (Page 2 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS River Water Ground Water (Well Water)

Aquatic Sediment Precipitation Monthly Quarterly (a) 2nd Quarter Composite Quarterly Quarterly 2nd Quarter Semi-Annually Annually Monthly Semi-Annual Composite 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58/Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)

Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58/Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)

Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic 26 LLDs indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering Environmental Services may be lower than those listed.

(a)

Quarterly Composites of each location's samples are used for the required analysis.

(b)

LLD for non-drinking water is 10 pCi/liter.

(c)

There are no required LLDs for strontium-89/90. LLDs are those achieved by Teledyne Brown Engineering Environmental Services.

1(b) 15 30 15 30 30 15 15 18 60 15 2000 (c)

(c) 15 30 15 30 30 15 1(b) 15 18 60 15 2000 (c)

(c) 150 180 (c)

(c) 10 10 pCi/1 pCi/1 pCi/I pCi/1 pCi/l pCi/I pCi/kg (dry) pCi/kg (dry) pCi/I pCi/I

TABLE2 (Page 3 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS Semi-Annual Annually Once per 3 yrs.

Monthly Monthly Quarterly Semi-Annual Monthly if available or at harvest Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 27 LLDs indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering Environmental Services may be lower than those listed.

Quarterly Composites of each location's samples are used for the required analysis.

LLD for non-drinking water is 10 pCi/liter.

There are no required LLDs for strontium-89/90. LLDs are those achieved by Teledyne Brown Engineering Environmental Services.

(a)

(b)

(c)

Shoreline Soil Soil pCi/kg (dry)

Milk 150 180 (a)

(a) 150 180 (a)

(a) 1 Fish Food Products (Broadleaf Vegetation) 15 18 60 15 (a)

(a) 130 260 130 130 260 130 150 pCi/kg (dry) pCi/kg (dry) pCi/1 pCi/1 pCi/1 pCi/kg (wet) pCi/kg (wet) pCi/kg (wet) 60 80 60

III. PROGRAM EXCEPTIONS 28

Location All Stations Sta 08 Sta 0 1, 02, 03, 04, 05.

All Stations Sta 24 Sta 06 Description Vegetation Aquatic Sedimen Charcoal Filter Vegetation Charcoal Filter Air Particulate REMP Exceptions For Scheduled Sampling And Analysis During 2000 - North Anna Date of Sampling Reason(s) for Loss/Exception 01/19/00 Seasonal unavailability.

02/16/00 03/15/00 t

02/21/00 Cross-contamination at lab.

04/26/00 06/21/00 07/26/00 08/23/00 TBE instrument malfunction. Data lost.

Low level Iodine not requested or performed.

TBE lost during laboratory move.

Low value. No particulates on filter.

Sta 24 Sta 12, 13 Sta O0A Sta 14, 15, 16, 22, 23 All Stations Sta 08, 09A Sta 11 Sta OIA All Stations All Stations Charcoal Filter Milk Ground Water Vegetation Air Particulates Surface Water River Water Precipitation Annual Environmental TLDs Vegetation 08/30/00 09/20/00 09/27/00 10/18/00 11/15/00 12/18/00 12/18/00 TBE lost sample.

Sr-89 not analyzed due to untimely analysis.

1-13 1, Co-58, Fe-59, Zr-95 & Ba-140 failed to meet the LLD.

1-131 LLD not met due to untimely analysis.

Sample not received by laboratory.

Ba-140 LLD not met due to untimely analysis.

Co-58, Fe-59, Zr-95, and Ba-140 LLDs not met due to untimely analysis.

Removed annual TLD's 6 months early to reflect true annual dose from June to December with change of vendor.

Seasonal unavailability.

12/27/00 01/11/01 01/11/01 29

In late September of 1999, Teledyne Brown Engineering Environmental Services 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, 2000 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 and is NUPIC approved.

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 Environmental Services Quality Assurance manual and are explained in the Teledyne Brown Engineering Environmental Services Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Interlaboratory Comparison program.

The results of the Interlaboratory Comparison Program are provided in Appendix E.

Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering Environmental Services's analytical methods meet the Lower Limit of Detection (LLD) requirements 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/m3 and a range of 0.007 to 0.041 pCi/mi3. 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/m3.

Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in 47 of the 48 composite samples. The average measurement for the control location was 0.071 pCi/m 3 with a range of 0.066 to 0.080 pCi/m 3.

The indicator locations had an average concentration of 0.064 pCi/m 3 and a range of 0.029 to 0.092 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 I

0.J 0.001 I-- Control Sta-24 U

Indicator -

Average Pre-op - - U -

- Required LLD During the properational period, tritium was not detected in the sample analyzed.

33 t

I 0 a S

Q Trending Graph 2: Tritium in River Water-Station 11 10000

.1000 JO 3

100 10 Q

0'.

Tritium - - Required LL7D

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 O0A, 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 1.8 to 10 pCi/liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. Beryllium-7 was not detected in the semi-annual composite samples for 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 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 SE. The results are presented in Table B-7. The samples were analyzed by gamma spectroscopy monthly. The samples were analyzed for tritium quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.

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/liter3. All other gamma emitters were below their detection level. There was no measured activity of strontium-89 or strontium-90 above the detection limit. Tritium was measured in all four samples with an average level of 3025 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 24 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 24 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 2850 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 detected in one sample at station 09A with an activity of 110 pCi/liter.

C. Aquatic Exposure Pathway

1.

Sediment/Silt Sediment samples were collected during February and August from each of three locations and were analyzed by gamma spectrometry. The results are presented in Table B-9. Two man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in three of the six samples with an average activity of 126 pCi/kg (dry weight) and a range from 58.8 to 205 pCi/kg (dry weight). Europium-152 was detected in one sample at a concentration of 2550 pCi/kg (dry weight), possibly from contamination in the laboratory. The highest reading for cesium-137 was obtained from station 8 located 1.10 miles SSE.

35

Naturally occurring potassium-40 was observed in all of the six samples with an average activity of 10502 pCi/kg (dry weight) and a range from 3040 to 14700 pCi/kg (dry weight).

Naturally occurring, thorium-228 was observed in all six samples with an average concentration of 899 pCi/kg (dry weight) and a range of 474 to 1530 pCi/kg (dry weight).

Radium-226 was measured in all six samples with an average concentration of 1217 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 was no measurable amount of strontium 89 in aquatic sediment/silt. Strontium-90 was measured in the one control sample with a concentration of 290 pCi/kg (dry weight). Strontium-90 was measured in the two indicator samples with an average concentration of 135 pCi/kg (dry weight) and a range of 130-140 pCi/kg (dry weight).

During the preoperational period sediment samples were analyzed by gamma ray spectroscopy.

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

Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight). Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were measured at background levels.

2.

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

10. 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

During the properational period, cobalt-58 was not detected in the samples analyzed.

37 CO-7 Trending Graph-3: Tritium in Surface Water Station 08 10000 4

1000 "10

in-.b z

S4 woSoVP]

IS R

V I

ý S

1I

-- Tritium -

--Required LLD -

Average Nre-op Trending Graph-4: Cobalt-58 in Sediment Silt 1000 t

too-4 S10 U

---Station-S -a-Station-09 --

Control Sta -09A --

Station-I I

During the properational period, cobalt-60 was not detected in the sample analyzed.

During the properational period, Cesium-134 was not detected in the samples analyzed.

38 Trending Graph-5: Cobalt-60 in Sediment Silt 1000 j

t 1001 I

T IIý Station-8 ---

Station-09 -*--

Control-Sta-09 Trending Graph-6: Cesium-134 in Sediment Silt 1000 M 100 0 z 10 U

I t VT VT~VT 1 1 v v

~

vf m

mn -

I T-I F

S T-V V

Station Station-09 -k Control-Sta-09 Station-I Required LLD]

C/k

Trending Graph - 7: Cesium-137 in Sediment Silt S-Station-8 M----- Station-I I Station-9 A Control-Sta-09 --Average Pre-Op

- - Required LLDs TRENDING GRAPH-8: CESIUM-134 IN FISH 1000 100 10 li I I II IIII 5p~~~~~~~

~~~~

0 V

§ pý 9

pI~

0ý pq I

a-Station-'08 Station-09 A Control-Sta - *

- Required LLDs During the preoperational period, cesiunm-134 was not detected in the samnples analyzed.

Station 25 replaced station 09.

39 co0 10000 1000 100 10 t

(-)

S C

C V

0 2

0 +/-

0 0 a

'11ý1 10 llp llp I'#

1\\11ý 4ý lfiý 1ý1 '14, e

'lfý '101 '14, 'lfý se a,\\§,

D. Ingestion Exposure Pathway

1. Milk The results of the iodine-131 analysis of milk samples are presented in Table B-11.

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-11.

A total of 24 samples were analyzed.

Naturally occurring potassium-40 was measured in all samples with an average of 1340 pCi/liter and a range of 1010 to 1590 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 1.09 pCi/liter and a range of 0.67 to 2.6 pCi/liter. This is similar to activities determined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/liter.

2.

Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-12. Eight samples of fish were collected during 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 1699 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-13. Naturally occurring potassium-40 was monitored in 34 of 35 samples with an average activity level of 11116 pCi/kg (wet weight) and a range of 5930 to 21300 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in 23 of the 35 samples with an average concentration of 966 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 98.6 pCi/kg (wet weight). Cesium-137 was 40

measured in broadleaf garden vegetation during the preoperational period with concentrations between 53 and 98 pCi/kg (wet weight).

E. Direct Radiation Exposure Pathway

1.

TLD Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table B-14. Individual measurements of external radiation levels in the environs of the North Anna site had an average dose of 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

Station 25 replaced station 09, TRENDING GRAPH-10: ENVIRONMENTAL RADIATION - TLDs 10.0 R

,C 4

C t

1.0

[* Environmental TL-Ds Sector TLI~s -

-Avg.

=Pre-opl 42 CIO I

TRENDING GRAPH-9: CESIUM-137 IN FISH 10000.0

.=

1000.0 1=

100.0 1.0 --Station - 08 Station -09 Station - 25 4-Avg. Pre-op

- - Required LLD 105

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 Chemobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/CuM, due to occasional atmospheric nuclear weapons tests.

Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There was no detection above the LLD for fission products nor other man-made isotopes in the particulate media during 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 One naturally occurring isotope, potassium-40 and no man-made 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 2850 pCi/liter which is 14.25% 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 3025 pCi/liter. The average tritium in 1999 had been 3350 pCi/liter.

Naturally occurring potassium-40 was 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 was 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-137 was detected in two samples at the indicator location and in one sample at the 44

control location. Europium-152 was detected in one indicator location. The europium-152 activity was attributed to possible cross-contamination in the laboratory. During the preoperational period, cesium-137 was measured in samples of aquatic sediment.

Strontium-90 was detected in two samples at the indicator location and in one sample at the control location. Sediment contamination does not provide a direct dose pathway to man.

The samples of shoreline soil monitored downstream of the site contained no measurement of cesium-134.

Cesium-137 was measured in one of the two samples at a 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 quarterly composite milk samples.

Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels.

Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 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 2.1% of the reporting level.

Two vegetation samples contained cesium-137 at an average level of 98.6 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.

45

Program Conclusions The results were as expected for normal environmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence.

As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in the Offsite Dose Calculation Manual. These concentrations are based upon 25% of the annual dose commitment recommended by 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-2103N, "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

VII. APPENDICES 49

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

TABLES - 2000 50

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 1 of 7 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 Particulates Beta (6.0-70)

SSE 20.0(52/52) 19.4(51/52)(a)

(1E-03 pCi/m 3 )

Gamma 48 Gamma K-40 48 10 63.9(43/44)

(29.2-92.1) 48 10 5.43(2/44)

(4.95-5.91) 12 3

(0/10) 12 0.4 (0/10) 4 4

60 (0/4)

Tritium 4

2000 (0/4) 1 3

(0/1) 1 0.4 (0/1) 24 22.0 mi NW 07 7.30 mi SSE N/A N/A N/A N/A N/A N/A 70.9(4/4)

(66.0-79.7) 5.91(1/4)

(5.91)

N/A N/A N/A N/A N/A N/A 0

70.9(4/4)

(66.0-79.7)

(0/4)

(0/2)

(0/2) 0 0

0 0

0 (0/0)

(0/0)

(0/0) 0 0

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 I, November 1979.

a)

Sample was lost.

b)

Samples not analyzed.

(7.6-70) 0 (7.1-41)

Be-7 K-40 Sr-89 Sr-90 Ground Well Water (pCi/liter)

Sr-89 Sr-90

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 2 of 7 River Gamma 12 Water (pCi/liter)

K-40 12 200 148(3/12) 11 5.8 mi 148(3/12)

(7.7-385)

Tritium 4

2000 3025(4/4)

(1500-4700)

Sr-89 Sr-90 1

3 (0/1) 1 0.4 (0/1)

SSE 11 5.8 mi.

SSE N/A N/A (7.7-385) 3025(4/4)

(1500-4700)

N/A N/A (0/0)

(0/0) 0 0

(0/0) 0 (0/0) 0 Precipitation (pCi/liter)

Monthly Gross 12 4

3.89(10/12)

Beta Gamma 2

(Semi-Annually)

(1.8-10)

(0/2)

Tritium 2

2000 (0/2) 1-131 24 0.5 (0/12) 01A 0.2 mi.

3.89(10/12)

NE (1.8-10)

N/A N/A N/A N/A N/A N/A Gamma 24 K-40 24 200 39.8(1/12)

(39.8)

Tritium 4

2000 2850(2/2)

(1500-4500) 08 1.10 mi 39.8(1/12)

SSE (39.8) 08 1.10 mi 2850(2/2)

SSE (1500-4500) 52 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.

0 (0/0)

(0/0)

Surface Water (pCi/liter)

Regular Monthlies 0

(0/0) 0 0

(0/12)

(0/12) 0 0

(0/2)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 3 of 7 All Indicator Control Non Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure (Unit)

Type No.

Range Direction Range Range ments Sr-89 Sr-90 (0/1)

(0/1)

N/A N/A N/A N/A (0/1)

(0/1) 0 0

Gamma N/A K-40 N/A Tritium N/A Gamma 6

6 (0/4) 6 200 N/A 10460(4/4) 11 5.8 mi (3040-14700)

SSE N/A 13800(2/2)

(12900-14700) 227(1/2)

(227) 0 12800(1/2) 0 (12800)

Cs-137 6

194 132(2/4) 08 1.10 mi (58.8-205)

Ra-226 6

100 Th-228 6

30 Eu-152 6

SSE 1320(3/4) 08 1.10 mi (399-1870)

SSE 975(2/4) 08 1.10 mi.

(849-1100)

SSE 2550(1/4) 08 1.10 mi.

(2550)

SSE 205(1/2)

(205) 1870(1/2)

(1870) 1720(1/2)

(1720) 1720(1/2)

(1720) 1100(1/2) 846(1/2)

(1100)

(846) 2550(1/4)

(0/2)

(2550)

Sr-89 3

4.0 (0/0)

N/A N/A (0/0)

(Annually) 53 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.

Surface Water (pCi/liter)

Regular Monthlies Surface Water (pCi/liter)

State Splits Sediment Silt (pCi/kg (dry))

Be-7 K-40 0

0 0

1 1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 4 of 7 All Indicator Control Non Medium or Analysis Locations Location with Highest Mean Location routine Pathway Reported Sampled Total LLD*

Mean Name Distance Mean Mean Measure (Unit)

Type No.

Range Direction Range Range ments Sediment Sr-90 Silt (pCi/kg (dry))

(Annually) 3 0.8 135(2/2) 09A (130-140) 12.9 mi.

290(1/1) 290(1/1)

WNW (290)

(290)

Gamma 0

Be-7 K-40 0

0 Cs-134 0

100 Cs-137 0

180 Ra-226 0

100 Th-228 0

30 Sr-89 (Annually)

Sr-90 (Annually) 0 200 0

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

54 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.

Soil (pCi/kg (dry))

0

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 Soil (pCi/kg Be-7 (dry))

K-40 Milk (pCi/liter) 2 2

(0/2) 2 200 1345(2/2)

(1280-1410)

Cs-137 2

40 167(1/2)

(167)

Ra-226 2

100 464(2/2)

(313-615)

Th-228 2

30 251(2/2)

(203-298)

Sr-89 1

4.0 (0/1)

(Annually)

Sr-90 1

0.8 100(1/1)

(Annually)

(100) 1-131 24 0.5 (0/24)

Gamma K-40 Sr-89 (Quarterly)

Sr-90 (Quarterly) 24 24 100 1342(24/24)

(1010-1590) 8 5

(0/4) 8 0.8 1.09(8/8)

(0.67-2.6)

N/A 08 1.10mi SSE 08 1.10mi SSE 08 1.10 mi SSE 08 1.10 mi SSE N/A 08 1.10 mi SSE N/A 12 8.3 mi.

NW N/A 12 8.3 mi NW 55 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.

Sample was lost.

Samples not analyzed.

a) b)

0 0

(0/0)

(0/0) 0 N/A 1345(2/2)

(1280-1410) 167(1/2)

(167) 464(2/2)

(313-615) 251(2/2)

(203-298)

N/A 100(1/1)

(100)

N/A 1402(12/12)

(1220-1590)

N/A 1.31(4/4)

(0.65-2.6) 0 0

0 0

(0/0)

(0/0) 0 (0/0)

(0/0)

(0/0) 0 0

0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2000 Docket No. 50-338/339 Page 6 of 7 Fish Gamma 8

(pCi/kg (wet))

K-40 8

200 1699(4/4)

(1120-1730)

Cs-137 8

40 42.6(2/4)

(34.1-51.1)

Gamma 35 Dose Be-7 35 35 1064(18/28)

(221-3540) 10796(27/28)

(5390-21300)

K-40 Cs-137 35 80 186(1/28)

(186)

Th-228 35 08 1.10mi SSE 08 1.10 mi.

SSE 21 1.00 mi WNW 23 0.93 mi SSE 15 1.20 mi NE (0/28) 1860(4/4)

(1120-2380) 42.6(2/4)

(34.1-51.1) 1236(4/7)

(506-2210) 12723(7/7)

(7270-21300) 186(1/7)

(186)

(o/7) 1860(4/4)

(1120-2380)

(0/4) 614(5/7)

(351-972) 12350(7/7)

(9750-17100) 11.2(1/7)

(11.2)

(0/7) 56 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.

Sample was lost.

Samples not analyzed.

a) b)

Food Vegetation (pCi/kg (wet))

0 0

0

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 Radiation Dose (mR/std. month)

(Regular TLDs)

Direct Gamma Radiation Dose (mR/std. Month)

(Annual TLDs)

Direct Gamma Radiation Dose (mR/std. Month)

(Sector TLDs) 48 0.2 6.24(44/44)

(4.1-8.77) 12 0.2 5.47(11/11)

(4.3-7.1) 288 0.2 6.89(256/256)

(4.9-11.1) 01 0.2 mi.

NE 01 0.2 mi.NE 23 0.93 mi. SSE 17/49 0.22 mi.

S 8.20(4/4)

(7.5-8.7) 7.1(2/12)

(7.1) 9.9(8/8)

(8.4-11.1) 5.8(4/4)

(5.0-6.4) 0 0

5.3(1/1)

(5.3) 5.86(32/32) 0 (3.9-7.9) 57 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.

All Control Non Medium or Analysis Indicator Location with Highest Mean Location routine Locations Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure (Unit)

Type No. I_

I_

Range Direction Range Range ments

APPENDIX B DATA TABLES 58

TABLE B-I: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 2000 pCi/m3 +/- 2 Sigma Page 1 of2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JANUARY 12/29-01/06 01/06-01/12 01/12-01/19 01/19-01/27 01/27-02/02 FEBRUARY 02/02-02/09 02/09-02/16 02/16-02/23 02/23-03/01

<.007

<.009

<.008

<.01

<.02

<.01

<.008

<.007

<.009

<.008

<.01

<.02

<.01

<.008

<.007

<.009

<.008

<.01

<.02

<.01

<.008

<.007

<.009

<.008

<.01

<.02

<.01

<.008

<.005

<.006

<.009

<.008

<.005

<.006

<.005

<.01

<.008

<.01

<.009

<.007

<.01

<.008

<.01

<.009

<.008

<.01

<.009

<.007

<.01

<.008

<.01

<.008

<.01

<.009

<.007

<.01

<.008

<.01

<.008

<.01

<.007

<.01

<.008

<.01

<.007

<.006

<.008

<.01

<.006

<.008

<.005

<.008

<.006

<.01

<.02

<.01

<.005

<.01

<.02

<.01

<.01 03/01-03/08 03/08-03/15 03/15-03/22

<.008

<.007

<.008

<.007

<.009

<.007

<.008

<.006

<.007

<.006

<.008

<.005 03/22-03/29

<.009

<.007

<.008

<.01

<.008

<.01

<.009

<.01

<.008

<.01

<.006

<.008

<.01

<.009

<.01

<.006

<.007

<.009

<.006

<.01

<.01 APRIL 03/29-04/05 04/05-04/12 04/12-04/19 04/19-04/26 04/26-05/03

<.008

<.009 (a)

<.009

<.008

<.009 (a)

<.009

<.008

<.008 (a)

<.009

<.008

<.009 (a)

<.009

<.005

<.006

<.007 (a)

<.007

<.01

<.008

<.009

<.01

<.008

<.009

<.01

<.008

<.009

<.01

<.007

<.008

<.009

<.008

<.006

<.007

<.01

<.02

<.006

<.01

<.02

<.02 MAY 05/03-05/10 05/10-05/17 05/17-05/23 05/23-05/31

<.007

<.009

<.01

<.009

<.007

<.009

<.01

<.009

<.007

<.009

<.01

<.009

<.007

<.009

<.008

<.009

<.005

<.006

<.01

<.006

<.007

<.02

<.01

<.007

<.02

<.01

<.008

<.02

<.01

<.007

<.02

<.01

<.004

<.01

<.008

<.006

<.005

<.01

<.007

<.01

<.01 JUNE 05/31-06/07 06107-06/14 06/14-06/21 06/21-06/28 (a)

(b)

<.009

<.007

<.009

<.01

<.009

<.008

<.009

<.01

<.009

<.007

<.009

<.01

<.009

<.007

<.009

<.01

<.007

<.005

<.006

<.008

<.009

<.01

<.009

<.01

<.009

<.01

<.009

<.01

<.006

<.008

<.009

<.007

<.01

<.009

<.01

<.007

<.01 59 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.

The sample was not analyzed.

MARCH

TABLE B-I: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 2000 pCi/m3 +/- 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 07/05-07/12 07/12-07/19 07/19-07/25 07/25-08/02

<.008

<.02

<.009

<.01

<.008

<.02

<.009

<.01

<.008

<.02

<.009

<.01

<.008

<.02

<.009

<.01

<.006

<.02

<.007

<.01

<.02

<.01

<.02

<.01

<.009

<.008

<.009

<.01

<.007

<.01

<.007

<.01

<.02

<.01

<.006

<.01

< (b)

<.01 AUGUST 08/02-08/09 08/09-08/16 08/16-08/23 08/23-08/30 SEPTEMBER 08/30-09/06 09/06-09/14 09/14-09/20 09/20-9/27 OCTOBER 09/27-10/04 10/04-10/11 10/11-10/18 10/18-10/25 10/25-11/01 NOVEMBER 11/01-11/08 11/08-11/15 11/15-1122 11/22-11/29 DECEMBER 11/29-12/6 12/6-12/13 12/13-12/19 12/19-12/27 (a)

(b)

<.011

<.01

<.02

<.006

<.01

<.03

<.009

<.007

<.008

<.006

<.007

<.004

<.008

<.01 (b)

<.006

<.01

<.004

<.02

<.01

<.011

<.01

<.02

<.006

<.01

<.03

<.008

<.007

<.008

<.006

<.007

<.005

<.008

<.01 (b)

<.006

<.01

<.007

<.02

<.01

<.011

<.01

<.02

<.006

<.01

<.03

<.009

<.007

<.008

<.007

<.008

<.007

<.008

<.01 (b)

<.006

<.01

<.007

<.02

<.01

<.011

<.01

<.02

<.006

<.01

<.03

<.009

<.007

<.008

<.006

<.008

<.007

<.009

<.01 (b)

<.006

<.01

<.007

<.02

<.01

<.007

<.009

<.02

<.006

<.01

<.008

<.02

<.006

<.005

<.004

<.006

<.007

<.005

<.007 (b)

<.004

<.006

<.007

<.01

<.014

<.02

<.007

<.02

<.01

<.02

<.01

<.008

<.006

<.009

<.006

<.008

<.01 (b)

<.006

<.01

<.005

<.02

<.01

<.014

<.02

<.007

<.02

<.01

<.02

<.01

<.008

<.006

<.009

<.004

<.008

<.01 (b)

<.006

<.01

<.006

<.02

<.01

<.014

<.02

<.007

<.02

<.01

<.02

<.01

<.008

<.006

<.009

<.007

<.008

<.01 (b)

<.006

<.01

<.006

<.02

<.01

<.014

<.02

<.007

<.02

<.01

<.02

<.01

<.008

<.006

<.009

<.007

<.008

<.01 (b)

<.006

<.01

<.006

<.02

<.01

< 0.01

<.01

<.008

<.01

<.008

<.01

<.009

<.005

<.004

<.006

<.007

<.006

<.007 (b)

<.004

<.008

<.006

<.01

<.009

<.01

<.02

<.01

<.009

<.006

<.004

<.003

<.01

<.007

<.02

<.01 (b)

<.008

<.01

<.004

<.02

<.01

<.009

<.02

< (b)

<.01

<.008

<.02

<.009

< 005

<.005

<.01

<.01 (b)

<.008

<.01

<.007

<.02

<.01 60 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.

The sample was not analyzed.

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2000 1.OE-03 pCi/m3 +/- 2 Sigma Page 1 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24

+/- 2 s.d.

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

=- 2 s.d.

18_+/-2 14_+/-2 18_+/-2 16_+/-2 13_+/-2 9-+/-1 12_+/-2 10_+/-1 61 (a)

Sample not analyzed.

25 +/-6 18_+/-2 13_+/-4 24 +/- 6 17_+/-4 21-+/-3 24 +/- 5 18_+/-3 14_+/-2 19_+/-2 18+/-2 10 +/- 1 12_+/-2 19_+/-2 17_+/-2 11_+1 11_+1 18 +/- 5 19_+/-4 11+/-2 11+/-2 20_+/-11 17_+/-10 18_+/-9 19_+/-12 18_+/-10

//

(

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 2000 1.0E-03 pCi/m 3 +/- 2 Sigma Page 2 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24

+/- 2 s.d.

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

+/- 2 s.d.

14+/-8 15+/-9 13-+/-8 15_+/-9 14+/-9 14+9 14+8 15_+/-9 14_+/-9 62 (a)

Sample not analyzed.

13-+/-2 21-+/-2 10 +/- 1 20 +/- 2 13-+/-2 20 +/- 2 11 +/- 1 20 +/- 2 14-+/-2 23 +/--2 11 +/- 1 20+/-2 13+/-2 21 +/- 3 10-+/-2 20 +/- 3

/

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES North Anna Nuclear Power Station, Louisa County, Virginia-2000 1.OE-03 pCi/mr3 +/- 2 Sigma Page 3 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24

+/- 2 s.d.

JULY 06/28-07/05 18 +/- 2 17 +/- 2 16 +/- 2 07/05-07/12 19 +/- 2 18 +/- 2 16 +/- 2 07/12-07/19 15 +/- 2 15 +/- 2 17 +/- 2 07/19-07/25 18+/-2 18+/-2 19+/-2 07/25-08/02 13 +/- 1 11 +/- 1 14 +/- 1 17+/-2 15+/-2 18+/-2 18+/-2 16+/-2 17+/-2 18+/-2 15+/-2 14+/-2 19+/-2 17+/-2 18+/-2 14+/- 1 11 +/- 1 12+/- 1 17+/-2 16+/-2 16+/-2 17+/-2 15+/-2 15+/-2 16+/-2 14+/-2 15+/-2 15+/-2 16+/-2 15+/-2 15+/-2 16+/-3 14+/-2 16+/-2 14+/-2 13+/-2 15+/-2 14+/-2 15+/-3 18+/-2 15+/-2 18+/-2 16+/-2 16+/-2 16+/-2 17+/-3 10+/-1 11+/-1 13+/-1 12+/-1 12+/-1 12+/-1 12+/-2 AUGUST 08/02-08/09 22 +/- 2 22 +/- 2 08/09-08/16 19+/-2 18+/-2 08/16-08/23 14 +/- 2 16 +/- 2 08/23-08/30 28 +/- 2 25 +/- 2 23 +/-2 19+/-2 18+/-2 24+/-2 23+/-2 18+/-2 20+/-2 17+/-2 17+/-2 15+/-2 26+/--2 23+/-2 22+/-2 19+/-2 23+/-2 18+/-2 15+/-2 16+/--2 16+/-2

<1.0(a) 15+/-2 22+/-2 22+/-2 23+/-2 21 +/-2 22+/-2 20+/-2 18+/-2 19+/-2 17+/-2 24+/-2 24+/-2 24+/-2 23+/-2 19+/-2 19+/-2 16+/-2 18+/-2 23+/-2 31+/-2 SEPTEMBER 08/30-09/06 13 +/- 2 12 +/- 2 09/06-09/14 19 +/- 2 17 +/- 2 09/14-09/20 16 +/- 2 13 +/- 2 09/20-09/27 14 +/- 2 13 +/- 2 Quarter Avg. 18+/- 9 16 +/- 8

+2 s.d.

12+/-2 19+/-2 16+/-2 12+/-2 13+/-2 12+/-2 17+/-2 17+/-2 13+/--2 14+/--2 13+/--2 12+/--2 17+/-7 17+/-8 16+/-6 13+/-2 12+/-2 11+/-2 19+/-2 15+/-1 18+/-2 14+/--2 13+/-2 13+/-2 11 +/- 1 11 +/- 1 10+/-1 16+/-7 15+/-7 16+/-8 9+/-2 13+/--2 17+/-2 19+/-2 14+/-2 15+/-2 13+/--2 12+/--2 16+/-8 16+/-7 14+/--2 12+/--2 18+/-2 18+/-2 16+/-2 13+/-2 13+/-2 12+/--2 17+/-7 17+/-11 63 (a)

Sample not analyzed.

22 +/-4 18+/-3 16+/-3 25 +/- 5 12 +/- 3 18+/-2 14+/-3 12+/-2 16+/-8

TABLE B-2: CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES North Anna Nuclear Power Station, Louisa County, Virginia-2000 1.OE-03 pCi/m3 +/- 2 Sigma Page 4 of 4 COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 2 s.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) 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 12/06-12/13 32 +/- 2 28 +/- 2 12/13-12/19 23 +/-2 23 2

12/19-12/27 31 +/-2 28+/-2 Quarter Avg. 27 +/- 16 26 14

=L 2 s.d.

Annual Avg.

19 +/- 14 19 13

+/--2 s.d.

(a)

Sample not analyzed.

20+/-2 33+/-2 27+/-2 36+/-2 19+/-2 30+/-2 29+/-2 31+/-2 18+2 27 +/- 2 22 +/- 2 28 +/-2 19+/-2 28 +/-2 25 +/-2 30+/-2 17 +/- 2 27+/-2 24+/-2 33_+/-2 17+/-2 27 +/-2 21+2 30+/-2 18+/-2 17+/-2 19+/-2 19+/-2 18+/-3 30+/-2 27+/-2 29+/-2 27+/-2 29+/-4 23+/-2 25+/-2 28+/-2 28+/-2 25+/-5 28+/-2 30+/-2 37+/-2 31+/-2 31+/-6 28+/-16 28+/-15 26+/-16 26+/-12 24+/-13 24+/-11 25+/-13 26+/-16 32+/-29 28+/-14 27+/-16 19+/-15 20+/-14 18+/-14 19+/-13 17+12 18+12 19+/-13 18+/-14 20+/-21 19+/-15 19+/-14 64

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 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide*

12/29-03129 03/29-06128 06/28-09/27 09/27-12127 STA-01 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-1 37 Th-228 STA-02 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-134 Cs-137 Th-228 STA-03 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-137 Th-228 STA-04 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-1 34 Cs-1 37 Th-228 (a)

(a) 58.8 +/- 5.9

<8

<0.3

< 0.4

< 0.3

<0.3

< 0.4 (a)

(a) 61.5 +/- 6.1

<10

< 0.4

<0.5

<0.3

< 0.4 (a)

(a) 69.5 +/- 6.9

<4

< 0.2

< 0.4

< 0.3

<0.2

< 0.4 (a)

(a) 64.9 +/- 6.5 4.95 +/- 2.14

< 0.3

< 0.4

< 0.2

<0.2

< 0.4

<4

<0.5 68.6 +/- 6.9

<4

<0.3

< 0.4

< 0.2

< 0.4

<4

< 0.4 58.9 +/- 5.9

<4

< 0.2

<0.3

< 0.2

< 0.4

<4

<0.5 56.4 +/- 5.6

<10

<0.3

< 0.4

<0.3

< 0.4

<2

<0.3 61.5 +/- 6.2

<5

<0.3

< 0.4

< 0.2

<0.3

< 0.4 (a)

(a) 64.3 +/- 8.56

<5

< 0.2

<5

< 0.2

<0.3 (a)

(a) 61.4 +/- 7.15

<3

<0.3

<4

<0.2

< 0.2

< 0.2 (a)

(a) 66.9 +/- 8.28

<4

<0.2

<5

<0.2

< 0.2

< 0.4 (a)

(a) 69.1 +/- 9.0

<5

< 0.2

<4

< 0.2

< 0.4 (a)

(a) 88.2 + 5.88

<5

<0.1

<2.0

<0.1

< 0.2 (a)

(a) 76.7 +/- 5.08

<3

<0.3

<1

<0.1

< 0.2 (a)

(a) 92.1 +/- 6.18

<4

<0.1

<2

<0.1

< 0.2 (a)

(a) 88.9 +/- 6.45

<4

<0.1

<2

<0.1

< 0.2

< 0.3 70.0 + 25.6 64.6 +/- 16.3 71.2 +/- 30.1 71.1 +/- 24.5 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/m 3 4-2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide*

12/29-03/29 03/29-06/28 06/28-09/27 09/27-12/27 STA-05 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-1 37 Th-228 STA-05A Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-137 Th-228 STA-06 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-137 Th-228 STA-07 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-1 34 Cs-137 Th-228 (a)

(a) 68.5 +/- 6.9

<5

<0.3

< 0.4

<0.3

< 0.4 (a)

(a) 65.6 +/- 6.6

<4

<0.2

< 0.4

< 0.2

<0.5 (a)

(a) 57.3 +/- 5.7

<5

<0.3

< 0.4

<0.3

< 0.4 (a)

(a) 74.6 +/- 7.5

<6

<0.3

< 0.4

<0.3

< 0.2

<0.3

<6

<0.8 58.2 +/- 5.8

<5

<0.2

<0.3

< 0.2

<0.2

<0.3

<3

<0.5 51.2 +/- 5.1

<7

< 0.2

< 0.4

< 0.2

<0.3

<3

< 0.4 29.2 +/-3.7

<9

< 0.4

< 0.5

< 0.3

<0.3

< 0.4

<2

< 0.4 56.4 +/-5.6 5.91 +/-1.69

< 0.3

< 0.4

<0.2

<0.3 (a)

(a) 56.0 +/- 7.16

<3

< 0.2

<4

< 0.2

<0.3 (a)

(a) 70.4 + 11.5

<5

< 0.2

<5

<0.2

< 0.2

<0.3 (a)

(a) 53.1 +/- 7.07

<3

<0.2

<5

<0.3

<0.2

<0.3 (a)

(a) 70.9 +/- 9.07

<4

<0.2

<6

<0.3

<0.2

< 0.4 (a)

(a) 90.1 +/- 5.76

<3

<0.1

<1

<0.1

< 0.2 (a)

(a) 82.2 +7.25

<4

<0.2

<2

<0.2

<0.1

<0.3 (a)

(a) 47.6 +/- 2.95

<3

< 0.2

< 0.8

< 0.2

< 0.2 (a)

(a) 52.1 +/- 3.4

<3

< 0.2

< 0.9

< 0.2

< 0.2 68.2 +/- 31.2 67.4 +/- 25.7 46.8 + 24.8 63.5 +/- 21.9 66 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*

12129-03129 03129-06/28 06/28-09127 09127-12127 STA-21 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-134 Cs-137 Th-228 STA-22 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-1 34 Cs-137 Th-228 STA-23 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-137 Th-228 STA-24 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-1 34 Cs-137 Th-228 (a)

(a) 75.6 +/- 7.6

<10

< 0.4

<0.6

< 0.4

<0.5 (a)

(a) 64.0 +/- 6.4

<5

< 0.3

<0.5

< 0.4

<0.5 (a)

(a) 74.2+/- 7.4

<6

< 0.3

< 0.4

< 0.3

<0.5 (a)

(a) 67.4 +/- 6.7

<8

<0.3

< 0.4

<0.3

< 0.4

<10

<0.8 56.8 +/- 4.17

<3

<0.2

<0.3

<0.2

< 0.2

<0.3

< 20

<4 49.0 +/- 3.92

<9

< 0.3

< 0.4

<0.3

< 0.4

<6

<1

<2

<1

<0.1

<0.3

< 0.2

<0.1

< 0.5

<2

<0.1 66.0 +/- 4.66

<8

< 0.3

< 0.4

< 0.3

<0.3

< 0.4 67 All gamma emitters other than those listed were <LLD.

(a)

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

(a)

(a) 61.0 +/- 8.69

<4

< 0.3

<6

< 0.3

< 0.2

< 0.3 (a)

(a) 58.8 +/- 9.84

<6

<0.3

<8

< 0.4

<0.3

<0.5 (a)

(a) 61.0 +/- 9.02

<5

<0.3

<7

< 0.3

< 0.4 (a)

(a) 79.7 +/- 13.7

<6

< 0.4

<11

<0.5

< 0.4

<0.5 (a)

(a) 37.0 +/- 2.84

<3

< 0.2

<0.9

< 0.2

< 0.2 (a)

(a) 51.9 +/- 3.8

<5

< 0.2

<1

<0.3

< 0.2

<0.3 (a)

(a) 64.6 +/- 4.05

<4

< 0.2

<1

< 0.3

< 0.2 (a)

(a) 70.6 +/- 5.54

<6

< 0.3

<2

<0.3

< 0.4 57.6 + 31.8 55.9 +/- 13.6 66.6 +/- 13.7 70.9 + 12.3

TABLE B-4: GROSS BETA, TRITIUM AND GAMMA EMITTER

CONCENTRATIONS IN PRECIPITA TION Station 01A -- (On Site)

North Anna Power Station, Louisa County, Virginia - 2000 pCi/Il -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 09/27/00-10/25/00 (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.

3.9 +/- 5.1 SEMI-ANNUAL PRECIPITATION COMPOSITES 12129/99 - 06/28100 06128/00 - 12127/00 Be-7 = < 10 H-3 = <200 Be-7 = < 300 H-3 = < 100 All gamma emitters other than those listed were <LLD.

(a)

No precipitation in October.

68

TABLE B-5 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM 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.

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

TABLE B-6: GAMMA EMITTER*, STRONTIUMAND TRITIUM CONCENTRATIONS IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 2000 pCi/I + 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

< 100

< 30

< 100

< 30

< 300

< 200

< 100

< 40

< 50

< 75

< 80

< 7 (b)

< 10 (b)

< 900000 (C)

< 40

<5

<9

< 30000 (c)

< 50

<6

<8

<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.

(c)

Due to delay in analysis, the LLD was missed.

TABLE B-7: GAMMA EMITTER*,- STRONTIUM, TRITIUM, AND IODINE CONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 2000 pCi/1-2 Sigma Page 1 of 1 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 (a)

(a) 4700 +/- 200

< 30

<60

<0.5

<3 (a)

(a)

(b)

< 30

< 60

< 0.2

< 3

<7

<50

<5

<50

<5 (a)

(a)

(b)

< 30

< 50

< 0.3

< 4

< 6

< 70

< 6

<4 (a)

(a)

(a) 0.6 1500+/-100 (a)

(b)

(a)

(b)

(a) 2800 +/-200 (a)

(b)

(a)

(b)

(a)

(a) 3100+/-100 (a)

(a)

< 30

< 20

< 30

< 40

<60

<0.4

<2

<10

<40

<4 52.3 +/- 13.7 < 0.3

< 30

< 0.6 385+/-38

<0.8

<2

<3

<10

<9

<10

< 40

< 50

< 60

<3

<4

<5

< 30

< 80

< 0.4

< 3

< 9

< 60

< 6

< 40

< 80

< 0.8

< 3

< 10

< 60

< 5

< 40

< 60

< 0.1

< 3

< 40

< 100

< 300 (a)

(b)

< 20

< 40

< 1.0

< 3 (a)

(b)

<50 7.71+/-31.5 <1.0

<4

<8

<80

<10

< 200

< 9

< 8 Average +/- 2 sd 3025 +/- 2630 All gamma emitters other than those listed were <LLD.

(a)

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

(b)

Tritium analysis performed on quarterly composite.

70 03/29/00 06/28/00 09/27/00 12/28/00 (a)

<0.9 (a)

(a)

<0.8 (a)

(a) 01/13/00 02/15/00 03/15/00 04/17/00 05/11/00 06/15/00 07/12/00 08/15/00 09/15/00 10/16/00 11/16/00 12/18/00 148 +/- 412

TABLE B-8: GAMMA EMITTER*, STRONTIUMAND TRITIUM CONCENTRATIONS IN SURFACE WATER North Anna Power Station, Louisa County, Virginia - 2000 pCi/l +/- 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131** Cs-137 Ba-140 Ra-226 Th-228 STATION - 08 01/13 (a) 02/15 (a) 03/15 (a) 04/17

< 4 05/11 (a) 06/15 (a) 07/12 (a) 08/15 (a) 09/15 (a) 10/16 (a) 11/16 (a) 12/18 (a)

Average + 2 sd STATION - 09A 01/13 (a) 02/15 (a) 03/15 (a) 04/17

< 2 05/11 (a) 06/15 (a) 07/12 (a) 08/15 (a) 09/15 (a) 10/16 (a) 11/16 12/18 (a)

(a)

<0.6 (a)

(a)

<0.9 (a)

(a)

(a) 4500 +/- 200 (b)

(b) 1500 +/- 100 (b)

(b) 3200 +/- 200 (b)

(b) 2200 +/- 100 (b)

(b) 2850 + 2605

< 200 (b)

(b)

< 200 (b)

(b)

< 300 (b)

(b) 110 +/- 40 (b)

(b)

Average +/- 2 sd All gamma emitters other than those listed were <LLD.

1-131 by radiochemistry.

Strontium 89/90 analyses performed annually.

H-3 analyses performed quarterly.

< 30

<30

< 20

< 30

< 40

< 60

< 30

< 40

<20

< 30

<30

< 20

<40

< 30

< 40

<40

< 30

< 50

< 30

< 20 39.8 +/- 21.9

<30

<40

< 80

< 100

< 50

<40

< 60

< 30

< 40

< 100

< 90

< 40

< 80

< 50

< 0.4

<0.2

< 0.4

<0.3

<0.6

< 0.4

<0.6

<0.8

<0.3

< 0.2

<0.3

<0.6

<0.4

<0.7

<0.9

<1

<0.9

<3

<2

<1

<3

<5

<3

<5

<3

<4

<2

<1

<4

<2

<3

<4

<3

<7

<5

<3

<10

<7

<8

<10

< 60

<10

< 100

<6

<5

<10

<9

<6

<10

< 60

<10

< 100

< 70

< 80

< 70

< 40

< 30

< 60

< 70

< 60

< 120

< 90

<6

< 60

< 50

< 30

< 70

< 60

< 100

< 100 11.4 +/- 2.6

<6

<4

<3

<5

<6

<5

< 600

<10

< 100

<6

<5

<4

<2

<6

<5

< 300

<10

<8 (a)

(b) 71

TABLE B-9: GAMMA EMITTER

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

+/- 2 s.d.

(a)

< 1000 11200+/- 1100

< 40

< 90

< 40

< 50 205 +/- 39 1870 +/- 530 1100+ 110 (a)

(a)

< 400 12800 +/- 1300

< 30

< 40

< 30

< 40 114 +/- 38 1720 +/- 570 846 + 85 (a)

(a)

< 300 12900 +/- 1300

< 20

< 30

< 20

< 30 58.8 +/- 15.3 1690 + 370 849 + 85

< 3000 130 +/- 70

< 250 3040 +/- 362

< 30

< 20

< 30 399 +/- 28.2 596 + 34.2 72 All gamma emitters other than those listed were <LLD.

Strontium 89/90 analyses performed annually.

Europium-152 was measured at 2550 +/- 260 pCi/kg in Station 08 on 02/21/00.

Page 1 of 1 Sr-89 Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-1 37 Ra-226 Th-228

< 2000 290 +/- 60

< 400 8370 +/- 544

< 30

< 40 521 +/- 30 474 +/- 34.1

< 3000 140 +/- 70

< 460 14700 +/- 950

< 50

< 40

< 50 1100 +/- 52 1530 +/- 81 187 +/- 179 10502 +/- 8455 126 +/- 148 1217 +/- 1287 899 +/- 757 (a)

(b)

TABLE B-1O: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 2000 pCi/kg f 2 Sigma Station-08 Station-08 Average Nuclide 02121/00 08/07/00

+/- 2 Sigma (a)

(a)

< 200 1280 +/- 210

< 20

<20

< 20 615 + 256 298 +/- 32 All gamma emitters other than those listed were <LLD.

(a)

Strontium 89/90 analyses performed annually.

Page 1 of I Sr-89 Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-1 34 Cs-1 37 Ra-226 Th-228

< 2000 100 +/- 60

< 330 1410 +/- 315

< 30.8

< 33.0

< 42.9

< 32.6 167 +/- 23.6 313 +/- 22.7 203 + 21.3 1345 +/- 185 464 + 427 251 + 134 73

TABLE B-11: GAMMA EMITTER*AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 2000 pCi/I +/- 2 Sigma Page 1 of 2 MONTH NUCLIDE STATION-12 STATION-13:

JANUARY FEBRUARY MARCH Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 APRIL MAY JUNE (a)

(a) 1360 +/- 140

<4

<0.3 (a)

(a) 1580 +/- 160

<4

<0.3

<3 1.2+/- 0.3 1370 +/- 140

<4

<0.3 (a)

(a) 1220 +/- 120

<4

<0.3 (a)

(a) 1590 +/- 160

<3

<0.2

<2 0.75 +/- 0.23 1370 +/- 140

<4

<0.5 (a)

(a) 1420 +/- 140

<5

< 0.2 (a)

(a) 1250 +/- 120

<5

<0.3

<2 0.82 +/- 0.25 1250 +/- 120

<4

< 0.2 (a)

(a) 1400 + 140

<5

<0.3 (a)

(a) 1310 + 130

<4

<0.3

<2 1.1 +/- 0.2 1340 +/- 130

<3

<0.4 74 (a)

(b)

All gamma emitters other than those listed were <LLD.

Strontium 89/90 analyses performed quarterly.

Due to delay in analysis, Sr-89 was not analyzed.

TABLE B-11: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 2000 pCi/l =L 2 Sigma Page 2 of 2 MONTH NUCLIDE STATION-12 STATION-13 JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Average +

2 s.d.

Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 Sr-89 SR-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-1 37 1-131 (a)

(a) 1270 +/- 130

<4

<0.3 (a)

(a) 1420 +/- 84

<4

<0.3 (b) 2.6 +/- 0.5 1430 +/- 127

<6

<0.6 (a)

(a) 1480 +/- 120

<4

<0.6 (a)

(a) 1390 +/- 140

<5

< 0.6

<8 0.67 +/- 0.25 1340 +/- 53

<5

<0.6 (a)

(a) 1260 +/- 130

<3

<0.3 (a)

(a) 1310 +/- 93

<5

< 0.4 (b) 0.75 +/- 0.20 1010 +/- 69

<4

<0.4 (a)

(a) 1240 +/- 110

<2

<0.7 (a)

(a) 1310 +/- 110

<2

<0.5

<7 0.82 +/- 0.21 1280 +/- 57

<4

<0.9 1.31 +/-1.79 1402 +/- 220 0.87 +/- 0.31 1282 +/- 206 All gamma emitters other than those listed were <LLD.

Strontium 89/90 analyses performed quarterly.

Due to delay in analysis, Sr-89 was not analyzed.

(a)

(b) 75

TABLE B-12: GAMMA EMITTER* CONCENTRATIONS IN FISH North Anna Power Station, Louisa County, Virginia - 2000 pCi/kg +/- 2 Sigma Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 Fish (a)

Fish (a)

Catfish (b)

Fish (a)

Catfish (b)

Catfish (b) 1730 +/-

1880 +/-

1630 +/-

1120 +/-

1670 +/-

2380 +/-

1120 +/-

2060 +/-

270 230 210 200 217 330 203 306

< 30

< 20

< 30

< 20

< 30

< 20

< 38

< 30

< 20

< 20 1537 + 563 1860 +/- 1070 All gamma emitters other than those listed were <LLD.

Non-bottom dwelling species of gamefish.

Bottom dwelling species of fish.

51.1 +/- 20.6

< 20 34.1 +/- 16.8

< 30

< 20

< 30

<20

< 30 42.6 +/- 24.0 76 02/24 02/22 02/24 02/23 08/10 08/09 08/10 08/09 Avg.

+ 2 s.d.

08 25 08 25 08 25 08 25 08 25 (a)

(b)

TABLE B-13: GAMMA EMITTER

CONCENTRATIONS IN FOOD/VEGETATION 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

< 100

<10 05/17 627 +/- 172 7270 +/- 730

< 30

< 20

< 300

< 30 06/21 584+/- 180 7191+/- 720

<100(a)

<30

<20

<400

<30 07/25 1270 +/- 200 12300 +/- 1200

< 50

< 30

< 20

< 400

< 30 08/16 2170 +/- 260 10300 +/- 1000

< 60

<40

< 30

< 500

< 50 09/20

< 2040 11600 +/- 530

< 10

< 590

< 20

< 550

< 30 10/18(b)

< 300

< 200

< 300

< 30

<20

< 20

< 400

< 90 STATION 15 04/19 983 +/- 98 6840 +/- 680

< 50

< 10

< 200

< 10 05/17 337 +/- 124 7970 +/- 800

< 20

< 10

< 200

< 20 06/21 283 +/- 120 9420 +/- 940

< 400 (a)

< 20

< 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

< 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

< 400

< 40 06/21 409 +/- 138 9750 +/- 980

< 90 (a)

< 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

< 300

< 30 09/20

< 3200 12800 +/- 600

< 10

< 980

< 40

< 30

< 700

< 60 10/18(b)

< 400 14800 +/- 900

< 270

< 40

< 30

< 500

< 100 STATION 21 04/19

< 200 7360 +/- 740

< 50

< 20

< 10

< 200

< 20 05/17 506 +/- 101 6910 +/- 690

< 20

< 10

< 200

< 20 06/21

<80 7690+/- 770

<5

<8

<10

<200

<20 07/25 1590 +/- 280 13200 +/- 300

< 40

< 30

< 500

< 50 08/16 2210 +/- 20 18600 +/- 1900

< 70

< 30

< 20

< 400

< 40 09/20

< 2850 13400 +/- 570

< 10

< 850

< 40

< 30

< 620

< 40 10/18(b) 637 +/- 232 10800 +/- 600

< 400

< 40

< 30

< 20

< 500

< 100 77 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 1-131.

(b)

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

TABLE B-13: GAMMA EMITTER

CONCENTRATIONS IN FOOD/VEGETATION North Anna Power Station, Louisa County, Virginia -2000 pCi/kg L 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 05/17 06/21 07/25 08/16 09/20 10/18(b) 857 +/- 86 661 +/- 111 221 +/- 93

< 500

< 400

< 4400 457 +/- 232 Average 966+/-1570

+/- 2 s.d.

7270 +/- 730 7800 +/- 780 9420 +/- 940 7470 +/- 750 21300 +/- 2100 21300 +/- 830 14500 +/- 800 11116+/-8038

< 50

< 30

< 80 (a)

< 50

< 10

< 300

<10

< 20

< 70

< 50

< 1300

< 40

<8

<10

< 50

<30

< 60

< 30

<8

<10

< 50

< 40

< 30

< 100

< 200

< 1000

< 700

< 800

< 500

< 10

< 20

< 90

< 60

< 100

< 100 98.6+/-247 78 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 1-131.

(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 01/06/00 03129/00 07105/00 09128100 Average 03/29/00 07105/00 09128/00 01111101 01 02 03 04 05 05A 06 07 21 22 23 24 Average

+ 2 s.d.

8.7 +/- 0.5 5.5 +/- 0.2 5.8 +/- 0.5 5.2 + 0.6 6.6 +/- 0.4 6.0 +/- 0.1 7.3 +/- 0.1 6.3 +/- 1.2 6.6 + 0.9 6.9 +/- 0.8 7.1 +/- 1.3 6.0 +/- 0.4 6.5 +/- 1.9 7.5 +/- 0.4 4.1 +/-0.2 4.1 +/-0.3 4.3 +/- 0.5 5.3 +/- 0.4 4.7 +/- 0.1 6.8 +/- 0.5 4.8 +/- 0.4 4.9+/- 0.3 6.3+/-1.0 6.6 +/- 0.3 5.0 +/- 0.1 5.4 +/- 2.3 8.1 +/- 0.7 5.3+/- 0.1 4.9 +/- 0.2 5.0 +/- 0.5 6.6 +/- 0.6 5.2 +/- 0.8 7.9 +/- 0.8 6.0 +/- 0.4 5.9 +/- 0.2 7.5 +/- 0.6 8.4+/- 1.4 5.8 +/- 0.6 6.4 +/- 2.6 8.5+/- 0.4 5.3 +/- 0.1 5.1 +/-0.2 5.1 +/-0.4 6.7+/-0.2 5.9 +/- 0.3 7.8+/-0.5 6.2 +/-0.3 6.0 +/- 0.3 7.3 +/- 0.5 8.4 +/- 0.4 6.4 +/- 0.4 6.6 +/- 2.4 8.2 +/- 1.1 5.1 +/- 1.3 5.0 +/- 1.4 4.9 +/- 0.8 6.3+/- 1.3 5.5+/- 1.2 7.5+/- 1.0 5.8+/- 1.4 5.9+/-1.4 7.0+/-1.1 7.6 +/- 1.8 5.8+/-1.2 6.2 +/- 2.2 7.1 +/-0.8 4.3 +/-0.5 4.3 +/- 0.3 4.5 +/- 0.4 5.7 +/- 0.3 5.1 +/-0.3 6.3 +/- 0.7 5.0 +/- 0.1 4.7 +/- 0.3 6.2 +/- 0.4 7.1 +/- 0.2 5.3 +/- 0.5 5.5 +/- 2.0 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 1 of 2 Station Number N-1 N-2 NNE-3 NNE-4 NE-5 NE-6 ENE-7 ENE-8 E-9 E-10 ESE-11 ESE-12 SE-13 SE-14 SSE-15 SSE-16 S-17 S-18 SSW-19 SSW-20 SW-21 SW-22 WSW-23 WSW-24 W-25 W-26 WNW-27 WNW-28 NW-29 NW-30 NNW-31 NNW-32 N-33 N-34 NNE-35 NNE-36 NE-37 NE-38 First Qtr.

Second Qtr.

Third Qtr.

01106-03/29 03129-07105 07105-09128 7.6 +/-

5.7 +/-

10.1 +/-

6.8 +/-

8.6 +/-

6.5 +/-

7.9 +/-

5.4 +/-

7.9 +/-

6.9 +/-

7.1 +

7.9+

7.1 +

9.6 +/-

8.2 +

6.5 +/-

10.2 +

5.9 +

8.8 +

5.6 +

6.6+

7.3 +

8.7 +

7.6 +

9.6 +

6.3 +

6.1 +

6.8 +

9.9 +

6.1 +

6.8 +

7.6 +

8.3 +

5.9 +

10.6 +

7.5 +

9.0 +

6.7 +

0.5 0.3 0.6 0.2 1.0 0.4 0.6 0.4 0.4 0.5 0.6 0.3 0.4 0.2 0.6 0.3 0.2 0.3 0.9 0.7 0.5 0.2 0.3 0.2 0.3 0.3 0.6 1.0 0.6 0.4 0.2 0.8 1.1 0.6 0.7 0.2 0.5 0.4 5.9+

4.3+

7.8+/-

5.3+

7.0+/-

5.0+

5.9+/-

4.1+

6.6+

5.5+

5.6+/-

6.2+

5.9+

7.9+

6.4+/-

4.7+/-

8.5+

4.3+/-

7.8+

4.0 +/-

5.4 +/-

5.8 +/-

7.3 +/-

6.1 +/-

8.0 +

4.5 +/-

4.8 +/-

4.9 +/-

7.8 +/-

4.6 +/-

5.2 +/-

5.3+/-

6.2 +/-

4.3 +

8.0 +/-

5.8 +/-

7.0 +/-

5.1 +/-

0.6 0.8 1.2 1.0 0.4 0.9 0.8 0.2 0.4 0.4 0.5 0.4 0.4 1.3 0.4 0.4 0.7 0.3 0.1 0.5 0.2 1.0 0.4 0.6 1.3 0.6 0.5 0.4 0.3 0.3 0.3 0.4 0.2 0.5 0.9 0.3 0.5 1.2 7.2 +/- 0.5 5.2 +/- 0.5 9.6 +/- 0.5 6.7 +/- 0.7 8.1 +/- 0.3 6.2 +/- 0.6 7.3 +/- 0.2 5.7 +/- 0.4 8.1 +/- 0.4 7.1 +/- 0.7 6.6 +/- 0.4 7.5 +/- 0.5 6.8 +/- 0.1 9.3 +/- 0.5 8.1 +/- 0.4 5.9 +/- 0.2 10.3 +/-0.2 5.2 +/- 0.3 9.3 1.1 5.0 +/- 0.2 6.7 +/- 1.0 7.1 +/-+0.4 8.4 _ 0.4 7.1 +/-0.5 8.8 +/- 0.4 5.7 +/- 0.4 6.0 +/- 0.3 6.0 +/- 0.2 9.7 +/- 0.5 5.3 +/- 0.3 6.2 +/- 0.5 6.7 +/- 0.3 7.0 +/- 0.3 5.2 +/- 0.2 9.4 +/- 0.9 6.9 +/- 0.2 8.2 +/- 0.2 6.3 +/- 0.2 Fourth Qtr.

09128-01/11/01 6.7+/- 0.9 5.3 +/- 0.3 9.5 +/- 0.4 6.5 +/- 0.3 7.9 +/- 0.5 5.9 +/- 0.5 7.1 +/- 0.4 5.5 +/- 0.0 7.6 +/- 0.3 6.7+/- 0.3 6.7_+/-+0.5 7.2_+ 0.8 6.5 +/- 0.4 9.0+/- 0.8 7.4 +/- 0.3 5.6 +/- 0.4 9.8 +/- 0.5 4.7 +/- 0.1 8.7 +/- 0.7 4.7 +/- 0.2 5.9 +/- 0.5 6.8 +/- 0.4 7.6 +/- 0.2 6.9 +/- 0.4 8.1 +/- 0.4 5.5 +/- 0.2 5.6 +/-0.4 5.6 +/- 0.3 8.8 +/- 0.3 5.3+/-0.2 6.0+/-0.1 6.3+/-0.7 7.2 +/- 0.4 5.4 +/- 0.2 9.7+/-0.9 6.7 +/- 0.3 7.9 +/- 0.6 6.0 +/- 0.3 80 Average

+/- 2 s.d.

6.9 +/- 1.5 5.1+1.2 9.3 + 2.0 6.3 +/- 1.4 7.9 +/- 1.3 5.9 +/- 1.3 7.1 +/- 1.7 5.2 +/- 1.5 7.6 +/- 1.3 6.6 +/- 1.4 6.5 +/- 1.3 7.2 +/- 1.5 6.6 + 1.0 9.0 +/- 1.5 7.5 +/- 1.7 5.7 +/- 1.5 9.7 +1.7 5.0 +/-1.4 8.7 +/-1.2 4.8 +/-1.3 6.2 +/- 1.2 6.8 1.3 8.0 1.3 6.9 1.2 8.6 + 1.5 5.5 +/- 1.5 5.6 - 1.2 5.8 +/- 1.6 9.1 + 1.9 5.3 +/- 1.2 6.1 +/- 1.3 6.5 + 1.9 7.2 +/- 1.7 5.2 +/- 1.3 9.4 +/- 2.2 6.7 +/- 1.4 8.0 +/- 1.7 6.0 +/- 1.4

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 01/06-03/29 03/29-07105 07/05-09/28 09/28-01/11101

+/-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 6.1 +/- 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 0-1 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 5.2+/- 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 81

APPENDIX C LAND USE CENSUS - 2000 82

DOMINION VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 2000 August 1 - September 8 Nearest 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 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 SSW 1.9 1.6 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

Note: No milch cow or goats within a 5 mile radius of North Anna Power Station km = kilometer 83

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

Meat Milch

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

Sector 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 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 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 84

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 kmto 1.5 km

b. Sector N 3.2 km to 2.4 krn

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.

85

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 86

ANAL YTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by Dominion Virginia Power and Teledyne Brown Engineering Environmental Services and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979.

ANALYSIS TITLE PAGE Gross Beta Analysis of Samples........................................................................ 88 Airborne Particulates........................................................................... 88 W ater............................................................................................

.. 89 Analysis of Samples for Tritium (Liquid Scintillation).............................................. 90 Analysis of Samples for Strontium-89 and 90..........................................................................

91 W ater.............................................................................................. 9 1 M ilk.........................................................................................

.... 9 1 Soil and Sedim ent............................................................................. 91 O rganic Solids................................................................................

91 A ir P articulates.............................................................................................................

92 Analysis of Samples for Iodine-131..................................................................... 94 M ilk and W ater............................................................................... 94 Gamma Spectrometry of Samples........................................................................ 95 M ilk or W ater.................................................................................... 95 Dried Solids other than Solids and Sediment................................................ 95 F ish...............................................................................................................................

9 5 Soils and Sedim ents................................................................................................

95 Charcoal Cartridge (Air Iodine)..............................................................................

95 A irborne Particulates................................................................................................

95 Environm ental D osim etry................................................................................. 97 87

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/m3)

=

((S/T) - (B/t))/(2.22 V E)

TWO SIGMA ERROR (pCi/m3)

=

2((S/T 2) + (B/t 2))1/2/2.22 V E)

LLD (pCi3)

=

4.66 (B'/ 2)/2.22 V E t) where:

S Gross counts of sample including blank B

=

Counts of Blank E

=

Counting Efficiency T

=

Number of minutes sample was counted t

Number of minutes blank was counted V

Sample aliquot size (cubic meters) 88

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 1/2/2 gram of sample residue is mounted on the planchette. These figures are based upon counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.

The MDL becomes significantly lower as the mount weight decreases because of reduced self absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter.

These values reflect a beta counting efficiency of 0.38.

89

ANAL YSIS 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/i:

RESULT

=

(N-B)/(2.22 V E)

TWO SIGMA ERROR

=

2(N + B)/(At)112/ (2.22 V E)

LLD

=

4.66 (B/At) 12/ (2.22 V E) where:

N

=

the gross cpm of the sample B

=

the background of the detector in cpm 2.22

=

conversion factor changing dpm to pCi V

=

volume of the sample in ml E

=

efficiency of the detector At

=

counting time for the sample 90

ANAL YSIS 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)2 using nitric acid.

A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO 3 from the sample after *¢ttrium 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 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as 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 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/cm2 aluminum absorber for low level beta counting.

Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrochloric acid.

The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(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 (SrNO 3)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating 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.

91

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 SrCO3 from the sample after yttrium separation. This precipitate is counted on a nylon planchette and is covered with 80 mg/cm2 aluminum absorber for low level beta counting.

Calculations of the result, two activity of pCi/volume or pCi/mass:

RESULT Sr-89 TWO SIGMA ERROR Sr-89 LLD Sr-89 RESULT Sr-90 sigma errors and lower limits of detection (LLD) are expressed in (N/At-Bc-BA)/(2.22 V Ys DFsr-8 9Esr8 9) 2(N/At+Bc+BA)/(At) /2/(2.22 V YsDFsr-89Esr-89) 4.66(Bc+BA)/(At)" 2/(2.22 V YsDFsr-sg 9 Esr-89)

(N/At-B)/(2.22 V Y1 Y2 DF IF E)

TWO SIGMA ERROR Sr-90 LLD Sr-90 Where:

N At

=

BC 2.22 V

BA BC

=

Ys DFsr-89 K

=

DFy-90 IGy-90 2(N/At+B)/(At)" 2/(2.22 V Y1 Y2 DF E IF) 4.66(Bc+BA)/(At) "/2/(2.22 V Y1 Y2 IF DF E) total counts from sample counting time for sample (min) background rate of counter (cpm) using absorber Configuration.

dpm /pCi volume or weight of sample analyzed background addition from Sr-90 and ingrowth of Y-90 0.016(K) +((K) EY/abs)(Gy-9o) chemical yield of strontium decay factor from the mid collection date to the counting date for Sr-89 (NAt-Bc)y-9o/(Ey-9o IFy-90 DFy-9oY1) 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 the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 92

the efficiency of measuring Sr-90 through a No. 6 absorber the efficiency of counting Y-90 through a No. 6 absorber background rate of counter (cpm) chemical yield of yttrium chemical yield of strontium decay factor of yttrium from the radiochemical milking time to the mid count time efficiency of the counter for Y-90 ingrowth factor for Y-90 from scavenge time to the radiochemical milking time 93 0.016

=

EY/abs

=

B

=

YI Y2

=

DF

=

E

=

IF

=

ANAL YSIS OF SAMPLES FOR IODINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.

Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/l:

RESULT

=

(N/At-B)/(2.22 V Y DF)

TWO SIGMA ERROR

=

2((N/At+B) /At)" 2/(2.22 E V Y DF)

LLD 4.66(B/At)1 /2/(2.22 E V Y DF)

Where N

=

total counts from sample At

=

counting time for sample (min)

B

=

background rate of counter 2.22 dpm/pCi V

volume or weight of sample analyzed Y

=

chemical yield of the mount or sample counted DF

=

decay factor from the collection to the counting date E

=

efficiency of the counter for 1-131, corrected for self absorption effects by the formula E

Es(exp-0.0061M)/(exp-0.0061 Ms)

Es efficiency of the counter determined from an 1-131 standard mount Ms=

mass of Phi 2 on the standard mount, mg M

=

mass of PDI2on the sample mount, mg 94

GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded high purity germanium (HPGe) detector coupled to a personal computer (PC)-based data acquisition system which performs pulse height analysis.

Dried Solids Other Than Soil and Sediments A large quantity of the sample is dried at a low temperature, less than 100°C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis.

Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 100 minutes with a shield HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis.

Soil and Sediments Soils and sediments are dried at a low temperature, less than 100'C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded HPGe detector coupled to a PC-computer-based data acquisition system which performs pulse height and analysis.

Charcoal Cartridges (Air Iodine)

Charcoal cartridges are counted up to five at a time, with one positioned on the face of a HPGe detector and up to four on the side of the HPGe detector. Each HPGe detector is calibrated for both positions.

The detection limit for 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulates The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis.

A PC software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region.

95

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)11 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 96

ENVIRONMENTAL DOSIMETRY Teledyne Brown Engineering Environmental Services uses a CaSO4: 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 Environmental Services 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 1-D)2+(D-D) 2+D3-D) 2+(D4-D) 2)/3)" 2 Where:

DI the net mR of area 1 of the TLD, and similarly for D2, D3, and D 4 DI

=

IK/Rl -A I1 the instrument reading of the field dose in area 1 K

=

the know exposure by the Cs-137 dose on area 1 R1

=

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 97

APPENDIX E INTERLABORATORY COMPARISON PROGRAM 98

INTERLABORA TORY 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 Environmental Services 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.

Exceptions 2000 During 2000, several Interlaboratory Comparison Program (ICP) analyses were not performed as required by the ODCM. These omissions were identified in the audit EVL# 254T-01. Omitted analyses all occurred during the second half of 2000 while TBE facilities were in transition to the new Knoxville, TN facility and include the following.

"* Water analysis for gamma

"* Water analysis for iodine-131

"* Water analysis for strontium-89

"* Air particulate filters for gross beta

"* Air particulate filters for strontium-90 To prevent recurrence, Dominion has initiated internal commitment tracking by Radiological Protection Department to verify status and compliance by TBE on a quarterly basis. TBE has initiated modifications to management of the ICP. These modifications include the designation of a single point of contact to ensure that all the required samples are ordered, received and reported in a timely fashion. It is apparent, from the 2000 exceptions to the ICP, that after the TBE relocation to the new Knoxville, TN facility, inadequate information was given to new personnel regarding client specific ICP requirements. Newly assigned project managers have been tasked with reviewing their assigned contracts and ODCMs to ensure compliance for the 2001 ICP. TBE is confident that problems with omitted analyses will not be an issue in 2001.

99

ANAL YTICS CROSS CHECK COMPARISON PROGRAM 2000 Teledyne Brown Analytics Sample Date Media Nuclide Engineering Result (a)

Result Ratio (b,d)

Milk Milk 1-131 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Sr-89 Sr-90 18 381 132 128 89 195 161 171 179

+

1 38 13 13 9

20 16 17 18 13 +/-

3 16 +/-

1 03/20/00 03/20/00 06/19/00 Air Filter Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Cartridge 1-131 Air Filter Sr-90 Air Filter Milk Gross Alpha Gross Beta 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60

+

8 17 4

8 5

6 6

11 7

106 +/-

6 88 +/-

5 103 +/-

6 210 +/-

6 97 83 323 98 117 64 99 132 218 209

+

10 8

40 10 12 6

10 13 22 21 20 387 143 114 79 176 144 165 176

+

+/-

+

+/-

+

1 19 7

6 4

9 7

8 9

0.90 0.98 0.92 1.12 1.13 1.11 1.12 1.04 1.02 25 +/-

1 19 -

1 132 198 81 115 77 84 75 139 104

+

0.52(c) 0.84 1.08 1.16 0.91 1.24(e) 1.16 1.21(e) 1.31 (e) 1.35(e) 1.09 7

10 4

6 4

4 4

7 5

88 +/-

4 96 +/-

5 93 +/-

5 193 +/-

10 87 77 304 102 107 60 88 119 196 197

+

+/-

+

1.20 0.92 1.11 1.09 1.11 1.08 1.06 0.96 1.09 1.07 1.13 1.11 1.11 1.06 4

4 15 5

5 3

4 6

10 10 100 143 229 74 143 89 102 98 188 113 06/19/00 06/19/00 06/19/00 09/18/00

ANAL YTICS CROSS CHECK COMPARISON PROGRAM 2000 (cont.)

Teledyne Brown Analytics Sample Date Media Nuclide Engineering Result (a)

Result Ratio (b,d)

Milk Milk Milk Milk Sr-89 Sr-90 Sr-89 Sr-90 09/18/00 09/18/00 09/18/00 09/18/00 09/18/00 Air Filter Ce-141 Cr-51 Cs-134 Cs-137 Co58 Mn-54 Fe-59 Zn-65 Co-60 14 +/-

1 18 1

77 +/-

8 58 +/-

1 83 470 266 150 155 53 191 115 237 133

+

+/-

+

140 +

65

+

35 -

90 92 48 107 27 42 24 65 112

+

+/-

+

15 +/-

1 14 +/-

1 90 +

5 59 +

3 84 460 256 150 138 47 171 99 208 125 8

47 35 15 15 5

19 12 24 13 60 7

1 9

25 5

11 4

4 8

9 11 99 74 37 110 133 74 126 34 52 31 77 142

+/-

+

+/-

+

+/-

+

+/-

+

2I2

+

0.93 1.29 0.86 0.98 0.99 1.02 1.04 1.00 1.12 1.12 1.12 1.16 1.14 1.06 4

23 13 8

7 2

9 5

10 6

5 4

2 1.4 1(e) 0.88 0.90 0.82 0.69(e) 0.64(e) 0.85 0.80 0.80 0.77(e) 0.84 0.79 6

7 4

6 2

3 2

4 7

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 Environmental Services 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.

(d)

Ratio control limits - 0.80-1.20.

(e)

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

These possibilities were eliminated by the relocation.

101 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Fe-55 Sr-89 Sr-90

ERA

STATISTICAL

SUMMARY

PROFICIENCY TESTING (PT) PROGRAM-2000 ERA Known Value (pCi/I)(a) 58.4 16.8 6.07 8.26 2.25 25.4 42.1 98.2 99.6 49.2 209 16.4 28.9 64.4 12.3 72.2 DATE 2/10/00 2/10/00 2/24/00 2/24/00 2/24/00 2/24/00 2/24/00 2/25/00 2/25/00 2/25/00 2/25/00 2/26/00 2/26/00 2/26/00 2/26/00 2/26/00 3/01/00 TBE Result (b)

(pCi/l) 83.6 15.4 5.77 7.20 2.37 14.0 34.0 91.7 101 48.0 76.3 15.7 29.0 68.3 12.0 76.3 19800-27800 Expected Dev. Known (c)

(pCi/I) 14.6 5.00 3.00 1.24 0.56 6.35 5.00 9.82 5.00 5.00 10.4 5.00 5.00 5.00 5.00 5.00 21000-26500 Control Limits (d)

(pCi/l) 33.3-83.5 8.10-25.5 0.870-11.3 6.11-10.4 1.28-3.22 14.5-36.3 33.4-50.8 81.5-115 90.9-108 40.5-57.9 191-227 7.70-25.1 20.2-37.6 55.7-73.1 3.60-21.0 63.5-80.9 A

12380 Warning Limits (e)

(pCi/I) 41.5-75.3 11.0-22.6 2.61-9.53 6.83-9.69 1.60-2.90 18.1-32.7 36.3-47.9 86.9-110 93.8-105 43.3-55.0 197-221 10.6-22.2 23.1-34.7 58.6-70.2 6.53-18.1 66.4-78.0 23800 NUCLIDE Gr-A Gr-B U(NAT)

Ra-226 Ra-228 Gr-A Gr-B Ba-133 Co-60 Cs-134 Cs-137 Sr-89 Sr-90 Co-60 Cs-134 Cs-137 H-3 Performance Evaluation (f)

NA (g)

A A

NA (g)

CE (g)

A A

A NA (g)

A A

A 22300 102

ERA

STATISTICAL

SUMMARY

PROFICIENCY TESTING (PT) PROGRAM - 2000 Expected Dev. Known (c)

(pCi/I) 5.00 5.00 3.00 1.15 4.44 6.34 3.25 1.40 1.11 9.76 Control Limits (d)

(pCi/l) 13.8-31.2 0.9-18.3 14.7-25.1 7.41-18.6 52.6-74.2 2.21-3.77 7.41-18.6 17.5-34.9 1.12-15.9 70.2-105 Warning Limits (e)

(pCi/I) 16.7-28.3 3.83-15.4 16.4-23.4 9.25-16.8 56.1-70.7 2.47-3.51 9.25-16.8 20.4-32.0 1.40-12.9 76.0-99.0 ERA Known Value (pCi/l)(a) 22.5 9.6 19.9 13.0 63.4 2.83 13.0 26.2 7.17 87.5 8320 Performance Evaluation (f)

A A

NA (g)

A A

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+ 1 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.

103 NUCLIDE Sr-89 Sr-90 1-131 Ra-226 U (NAT)

Ra-228 Ra-228 Sr-90 Gr-A Gr-B H-3 DATE 5/18/00 5/18/00 5/23/00 9/1/00 9/1/00 9/1/00 9/1/00 9/1/00 9/1/00 9/1/00 9/1/00 Footnotes:

TBE Result (b)

(pCi/l) 18.3 8.33 2.03 9.70 57.0 2.99 10.0 28.6 6.90 88.8 8740 174 6910-9730 7360-9280

ERA

STATISTICAL SUMMAR Y ENVIRONMENTAL, INC.

PROFICIENCY TESTING (PT) PROGRAM YEAR 2000 Control Limits (pCi/l)

Footnotes are on the last page.

104 DATE Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 ENV Result (b)

(pCi/I)

NUCLIDE Gr-A Gr-B Sr-89 Sr-90 Ra-266 Ra-228 Uranium H-3 Gr-A Gr-B 1-131 Gr-A Ra-226 Ra-228 Co-60 Cs-134 Cs-137 Gr-B Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Ra-226 ERA Known Value (pCi/l)(a) 25.4 42.1 22.5 9.6 8.3 2.3 6.1 23,800 58.4 16.8 19.9 54.0 18.6 3.6 16.9 86.4 123.0 289.0 50.7 32.8 25.5 65.6 13.8 238.0 54.6 3.0 39.3 40.7 17.1 8.1 7.6 5.6 5.4 23,500 83.6 15.4 18.7 52.3 17.5 3.7 19.2 81.0 119.0 276.0 32.3 11.3 22.4 69.9 13.5 232.0 50.9 2.8 14.5-36.3 33.4-50.8 13.8-31.2 0.9-18.3 6.1-10.4 1.3-3.2 0.9-11.3 19,800-27,800 33.3-83.5 8.1-25.5 14.7-25.1 30.8-77.2 13.8-23.4 2.0-5.1 8.2-25.6 77.7-95.1 112.0-134.0 214.0-364.0 42.0-59.4 24.1-41.5 16.8-34.2 56.9-74.3 5.1-22.5 217.0-259.0 45.3-63.9 2.2-3.8 Performance Evaluation (c)

NA (d)

A A

NA (e)

A A

NA (f)

A A

A A (g)

A (g)

A A

ERA

STATISTICAL

SUMMARY

ENVIRONMENTAL, INC.

PROFICIENCY TESTING (PT) PROGRAM YEAR 2000 (cont'd)

ENV Result (b)

Control Limits (pCi/I)

(pCi/l)

Performance DATE Jun, 2000 Jun, 2000 Jul, 2000 Jul, 2000 Aug,2000 Sep, 2000 Sep, 2000 Sep, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 NUCLIDE Ra-228 Uranium Gr-A Gr-B H-3 Ra-226 Ra-228 Uranium 1-131 1-131(g)

Gr-A Ra-226 Ra-228 Uranium Footnotes are on the last page.

105 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Co-60 Cs-134 Cs-137 Gr-B Sr-89 Sr-90 Gr-A Gr-B Ba-133 Co-60 Cs-134 Cs-137 Zn-65 ERA Known Value (pCi/l)(a) 13.0 63.4 7.2 87.5 8320.0 18.9 6.2 11.9 15.9 15.9 74.4 10.5 19.4 44.5 91.1 59.8 45.0 256 41.3 18.0 60.3 25.5 82.2 27.8 76.0 106.0 79.0 10.0 57.0 6.9 88.8 8740.0 17.9 5.7 10.3 16.9 17.1 66.3 10.1 21.2 41.4 93.4 54.8 45.5 209 32.8 16.0 50.3 28.6 78.0 30.8 67.2 109.0 81.5 7.4-18.6 52.6-74.2 0.0-15.9 70.2-105.0 6910.0-9730.0 14.0-23.8 3.5-8.8 6.7-17.1 10.7-21.1 10.7-21.1 42.2-107.0 7.8-13.2 11.0-27.8 36.8-52.2 82.4-99.8 51.1-68.5 36.3-53.7 189-323 32.6-50.0 9.3-26.7 34.4-86.2 16.8-34.2 68.0-96.4 19.1-36.5 67.3-84.7 96.8-115.0 65.3-92.7 Evaluation (c)

A A

NA (h)

A A

ERA

STATISTICAL

SUMMARY

ENVIRONMENTAL, INC.

PROFICIENCY TESTING (PT) PROGRAM YEAR 2000 (cont'd)

All ERA samples are water.

(a) Results are presented as the known values and control limits as provided by ERA.

(b)

Unless otherwise, indicated, the laboratory results are given as the meanfor three determinations.

(c) A = Acceptable. Reported Result falls within the Warning Limits.

NA = Not Acceptable. Reported Result falls outside of the Control Limits.

(d) The analysis was repeated and recalculated with A-241 efficiency: result of reanalysis 28.32 pCi/L. Internal spike program results do not indicate a problem.

(e)

Result of reanalysis: 634 pCi/L. Activity confirmed by gamma spectroscopy: 600 pCi/L

(]) Results were recalculated with Am-241 efficiency; 57.8 pCi/L. Refer to Jan, 2000 Gr-B.

(g) An error was found in calculation. Result of recalculation: Sr-89, 55.5 pCi/L /Sr-90, 30. 7pCi/L. Results of reanalysis:

Sr-89, 47.4 pCi/L / Sr-90, 33.0 pCi/L. Both results are within limits.

(h) The mean value for Cs-134 of all participating laboratories was 70. 7pCi/L. Other gamma emitters are within limits, the counting efficiency is not suspect, Library values were reviewed and found to be correct.

106

DUKE ANAL YTICS CROSS CHECK COMPARISON PROGRAM YEAR 2000 Reported Known Ratio Quarter/

Value Value DUKE/

Year Matrix Nuclide pCi/L (a) pCilL (a)

Analytics Evaluation 1 st/00 Water 1-131 LL 76.63 74 1.04 A

1 st/00 Water 1-131 70 74 0.95 A

1st/00 Water Ce-141 426 427 1.00 A

1st/00 Water Cr-51 205 238 0.86 A

1st/00 Water Cs-134 135 139 0.97 A

1st/00 Water Cs-137 126 128 0.98 A

1st/00 Water Co-58 46 44 1.05 A

1st/00 Water Mn-54 165 159 1.04 A

1st/00 Water Fe-59 94 92 1.02 A

1st/00 Water Zn-65 191 196 0.97 A

1st/00 Water Co-60 117 116 1.01 A

1st/00 Water Gr-A 60 82 0.73 NA (b) 1st/00 Water Gr-B 223 210 1.06 A

1st/00 Water U-234 62 57 1.09 A

1st/00 Water U-235 2.5 2.7 0.93 A

1st/00 Water U-238 64 59 1.08 A

1 st/00 Water Pu-238 80 73 1.10 A

1st/00 Water Pu-239 69 62 1.11 A

1 st/00 Water Ra-226 87 89 0.98 A

1 st/00 Water Ra-228 77 66 1.17 NA (b) 1 st/00 Milk I-131LL 86 84 1.02 A

1 st/00 Milk 1-131 84 84 1.00 A

1st/00 Milk Ce-141 483 460 1.05 A

1st/00 Milk Cr-51 279 256 1.09 A

1st/00 Milk Cs-134 145 150 0.97 A

1st/00 Milk Cs-137 138 138 1.00 A

1st/00 Milk Co-58 43 47 0.91 A

1st/00 Milk Mn-54 166 171 0.97 A

1st/00 Milk Fe-59 103 99 1.04 A

1st/00 Milk Zn-65 197 208 0.95 A

1st/00 Milk Co-60 124 125 0.99 A

1st/00 Milk Sr-89 90 90 1.00 A

1st/00 Milk Sr-90 57 59 0.97 A

Footnotes on last page.

107

DUKE ANAL YTICS CROSS CHECK COMPARISON PROGRAM YEAR 2000 (cont.)

Reported Known Ratio Quarter/

Value Value DUKE/

Year Matrix Nuclide pCilL (a) pCi/L (a)

Analytics Evaluation 2nd/00 Filter Ce-141 75 80 0.94 A

2nd/00 Filter Cr-51 242 243 1.00 A

2nd/00 Filter Cs-134 89 105 0.85 A

2nd/00 Filter Cs-137 230 219 1.05 A

2nd/00 Filter Co-58 119 120 0.99 A

2nd/00 Filter Mn-54 143 136 1.05 A

2nd/00 Filter Fe-59 63 58 1.09 A

2nd/00 Filter Zn-65 182 170 1.07 A

2nd/00 Filter Co-60 159 163 0.98 A

2nd/00 Filter Sr-89 87 109 0.80 A

2nd/00 Filter Sr-90 62 66 0.94 A

2nd/00 Filter Gr-A 25 24 1.04 A

2nd/00 Filter Gr-B 97 93 1.04 A

2nd/00 Water H-3 10627 11400 0.93 A

2nd/00 Milk 1-131LL 81 81 1.00 A

2nd/00 Milk 1-131 86 81 1.06 A

2nd/00 Milk Ce-141 75 69 1.09 A

2nd/00 Milk Cr-51 236 211 1.12 A

2nd/00 Milk Cs-1 34 85 91 0.93 A

2nd/00 Milk Cs-137 199 190 1.05 A

2nd/00 Milk Co-58 98 104 0.94 A

2nd/00 Milk Mn-54 122 118 1.03 A

2nd/00 Milk Fe-59 52 50 1.04 A

2nd/00 Milk Zn-65 136 148 0.92 A

2nd/00 Milk Co-60 151 142 1.06 A

3rd/00 Water 1-131LL 72 75 0.95 A

3rd/00 Water 1-131 79 75 1.05 A

3rd/00 Water Ce-141 192 191 1.00 A

3rd/00 Water Cr-51 219 230 0.95 A

3rd/00 Water Cs-134 121 128 0.95 A

3rd/00 Water Cs-137 225 218 1.03 A

3rd/00 Water Co-58 58 60 0.97 A

3rd/00 Water Mn-54 92 89 1.04 A

Footnotes on last page 108

DUKE ANAL YTICS CROSS CHECK COMPARISON PROGRAM YEAR 2000 (cont.)

Reported Known Ratio Quarter/

Value Value DUKE/

Year Matrix Nuclide pCilL (a) pCi/L (a)

Analytics Evaluation 3rd/00 Water Fe-59 56 54 1.03 A

3rd/00 Water Zn-65 129 134 0.97 A

3rd/00 Water Co-60 247 246 1.01 A

3rd/00 Water Sr-89 90 85 1.06 A

3rd/00 Water Sr-90 52 54 0.97 A

3rd/00 Water Gr-A 55 50 1.10 A

3rd/00 Water Gr-B 228 205 1.11 A

3rd/00 Milk Sr-89 65 74 0.88 A

3rd/00 Milk Sr-90 41 39 1.06 A

3rd/00 Milk 1-131LL 66 58 1.14 A

3rd/00 Milk 1-131 69 58 1.20 NA (c) 3rd/00 Milk Ce-141 176 164 1.07 A

3rd/00 Milk Cr-51 195 198 0.99 A

3rd/00 Milk Cs-134 108 110 0.98 A

3rd/00 Milk Cs-137 193 188 1.02 A

3rd/00 Milk Co-58 50 51 0.99 A

3rd/00 Milk Mn-54 81 77 1.05 A

3rd/00 Milk Fe-59 50 47 1.06 A

3rd/00 Milk Zn-65 117 115 1.02 A

3rd/00 Milk Co-60 212 212 1.00 A

4th/00 Milk 1-131 86 85 1.01 A

4th/00 Milk Ce-141 362 356 1.02 A

4th/00 Milk Cr-51 521 503 1.04 A

4th/00 Milk Cs-1 34 84 85 0.99 A

4th/00 Milk Cs-137 204 199 1.02 A

4th/00 Milk Co-58 79 76 1.04 A

4th/00 Milk Mn-54 162 152 1.06 A

4th/00 Milk Fe-59 93 82 1.13 A

4th/00 Milk Zn-65 148 148 1.00 A

4th/00 Milk Co-60 185 184 1.00 A

4th/00 Filter Sr-89 60 85 0.70 A

4th/00 Filter Sr-90 42 41 1.03 A

4th/00 Filter Gr-A 20 21 0.97 A

4th/00 Filter Gr-B 136 114 1.19 A

4th/00 Water H-3 9657 10082 0.96 A

Footnotes on last page 109

DUKE ANAL YTICS CROSS CHECK COMPARISON PROGRAM YEAR 2000 (cont.)

(a) Results for filters in pCi.

(b) CR 00-26 issued. Gross alpha disagreement: Suspect incomplete rinsing of nuclide from laboratory glassware. Laboratory procedure revised to increase the strength of the acid wash. Ra-228 disagreement: Root cause not determined. Laboratory procedure revised to include new separation techniques obtained from EPA procedures.

(c)

CR 01-07 issued. Disagreement resulted from excessive decay time between sample preparation and analysis.

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