Text

Virginia Electric and Power Company North Anna Power Station Units 1 and 2 Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report
	ML003710637
Person / Time
Site:	North Anna ; (NPF-004, NPF-007, SNM-2507)
Issue date:	04/28/2000
From:	Matthews W; Virginia Electric & Power Co (VEPCO)
To:	; NRC/OCIO/IMD/RMB
References
	+sunsi/sispmjr=200603, -RFPFR
	Download: ML003710637 (157)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 2000 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.

NAPS/JHL Docket Nos.

License Nos.00-222 50-338 50-339 72-16 NPF-4 NPF-7 SNM-2507 Gentlemen:

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

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT North Anna Units 1 and 2 Technical Specifications 6.9.1.8 require the submittal of an Annual Radiological Environmental Operating Report. Accordingly, enclosed is the Annual Radiological Environmental Operating Report for North Anna Units 1 and 2 and North Anna Independent Spent Fuel Storage Installation for the reporting period of January 1, 1999 through December 31, 1999.

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

Very truly yours, W. R. Matthews 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

North Anna Power Station 1999 Annual Radiological Environmental Operating Report 0

VIRGINIA POWER

VIRGINIA ELECTRIC AND POWER COMPANY NOR TH ANNA POWER STATION Radiological Environmental Monitoring Program January 1, 1999 to December 31, 1999 Prepared by VIRGINIA ELECTRIC AND POWER COMPANY and TELEDYNE BROWN ENGINEERING I

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 1999 to December 31, 1999 Prepared by:

Reviewed bj Approved bj "I James B. Breeden, Supervisor Radiological Analysis and Material Control Erich W. 3ryer Supervisor Health Physics Technical Services Alandent aff ord Superintendent Radiological Protection 2

V-*

)

Table Of Contents Section Title Page Preface........................................................................................................................

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

7 Introduction..............................................................................................................

10 II.

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

........... 13 IIl.

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

30 IV.

Summary and Discussion Of 1999 Analytical Results.......................................

32 A.

Airborne Exposure Pathw ay........................................................................

33

1.

A ir Iodine/Particulates........................................................................

33

2.

Precipitation...........................................................................................

35

3.

Soil.....................................................................................................

36 B.

W aterborne Exposure Pathw ay..................................................................

36

1.

Ground/W ell W ater...........................................................................

36

2.

River W ater.......................................................................................

36

3.

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

37 C.

Aquatic Exposure Pathw ay.........................................................................

37

1.

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

37

2.

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

41 D.

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

41

1.

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

41

2.

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

42

3.

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

42 E.

D irect Radiation Exposure Pathw ay...........................................................

44

1.

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

44 V.

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

45 3

Table Of Contents (Continued)

Section Title Page VI.

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

49 VII.

Appendices............. ;............................................................................................ 51 Appendix A - Radiological Environmental M onitoring.................................... 51 Program Annual Summary Tables - 1999 Appendix B - Data Tables...................................................................................

58 Appendix C - Land Use Census - 1999..............................................................

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

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

98 List of Trending Graphs

1.

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

34

2.

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

34

3.

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

38

4.

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

38

5.

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

39

6.

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

39

7.

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

40

8.

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

40

9.

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

43

10.

Environmental Radiation - TLDs.......................................................................

43 4

List of Tables Table Page

1.

Radiological Sampling Station Distance and Direction from U nit 1..........................................................................................................

15

2.

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

27

3.

REMP Exceptions for Scheduled Sampling and A nalysis D uring 1999..........................................................................................

31 Appendix B Tables B-i Iodine-13 1 Concentration in Filtered Air..........................................................

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

61 B-3 Gamma Emitter, Strontium 89, and Strontium 90 Concentrations in Air Particulates.....................................................................

65 B-4 Gamma Emitter and Tritium Concentration in Precipitation..............................

68 B-5 Gamma Emitter Concentration in Soil..............................................................

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

70 B-7 Gamma Emitter, Strontium, and Tritium Concentrations in R iver W ater.............................................................................................................

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

71 B-9 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water State-Split Samples................................................................

72 B-10 Gamma Emitter Concentrations in Sediment Silt..............................................

73 B-1I Gamma Emitter Concentrations in Shoreline Soil............................................

73 B-12 Gamma Emitter Concentrations in Milk............................................................

74 B-13 Gamma Emitter Concentrations in Fish............................................................

76 B-14 Gamma Emitter Concentrations in Food/Vegetation.........................................

77 B-15 Direct Radiation Measurements Quarterly Annual TLD Results.........................................................................

79 B-16 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 1999 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 1999 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 pathway chains.

Radiation and radioactivity in the environment is constantly monitored within a 25 mile radius of the station. Virginia Electric and Power Company (VEPCO) also collects samples within this 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 operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline."

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

Teledyne Brown Engineering provides sample analyses for various radioisotopes as appropriate for each sample media. Participation in an interlaboratory comparison program provides an independent check of sample measurement precision and accuracy.

Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLD). This 7

ensures that analyses are as accurate as possible. Samples with extremely low levels of radiation which cannot be detected are therefore reported as being below the LLD.

The NRC also mandates a "reporting level." Licensed nuclear facilities must report any releases equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.

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

" The airborne exposure pathway includes airborne iodine, airborne particulate, precipitation, and soil samples. The overall 1999 airborne results were very similar to previous years and to preoperational levels. No increase was noted and there were no detections of fission products or other man-made isotopes in the airborne particulate media during 1999.

The waterborne exposure pathway includes ground/well water, river water, and surface water samples. No man-made or natural isotopes were detected in Lake Anna surface water except for tritium. The average tritium activity in 1999 was 13.4% of the NRC reporting level. This has essentially remained unchanged from 1995 levels.

The aquatic exposure pathway includes sediment/silt and shoreline samples. North Anna sediment contained some cesium-137.

During the preoperational period, cesium-137 was detected.

Sediment contamination, however, does not provide a direct dose pathway to man.

In shoreline soil, which may provide a direct dose pathway, no cesium-137 was detected.

The ingestion exposure pathway includes milk, fish, and food/vegetation samples.

Iodine-131 was not detected in any 1999 milk samples. Although cesium-137 has been detected in the past, it was not detected in 1999 milk samples. Strontium-90 vXas detected at levels comparable to 1998, and lower than preoperational years. Both strontium-90 and cesium-137 are attributable to atmospheric nuclear weapons testing in the past. Naturally occurring potassium-40 was detected at normal environmental levels.

Fish samples during 1999 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). TLD results have remained essentially the same since the preoperational period in 1977.

8

During 1999, as in previous years, operation of the North Anna Nuclear Power Station created no adverse environmental 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 1999 would be approximately 0.58 millirem. For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1%. These results demonstrate not only compliance with federal and state regulations, but also demonstrate the adequacy of radioactive effluent control at the North Anna Nuclear Power Station.

9

I. INTRODUCTION 10

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL OPERA TING PROGRAM L

INTRODUCTION The operational radiological environmental monitoring program conducted for 1999 for the North Anna Power Station is provided in this report. The results of measurements and analyses of data obtained from samples collected from January 1, 1999 through December 31, 1999 are summarized.

A. The North Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles south West 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 is 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.

Virginia Electric and Power Company is responsible for collecting the various indicator and control environmental samples.

Teledyne Brown Engineering is responsible for sample analysis and submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with control levels, which vary with time due to such 11

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 environmental 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 con centrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".

E.

This report documents the results of the Radiological Environmental Monitoring Program for 1999 and satisfies the following objectives of the program:

1.

Provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.

2.

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

3.

Identifies radioactivity changes in the environment.

4.

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

12

II. SAMPLING AND ANALYSIS PROGRAM 13

I.

SAMPLING AND ANALYSIS PROGRAM A.

Sampling Program

1.

Table 1 summarizes the sampling program for North Anna Power Station during 1999. Figure 1 indicates the locations of the environmental monitoring stations.

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, Virginia Electric and Power Company (VEPCO) splits samples with the Commonwealth of Virginia.* All samples listed in Table 1 are shipped to Teledyne Brown Engineering located in Westwood, New Jersey.

4.

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

Routine splitting of samples with the Commonwealth of Virginia has been discontinued.

Samples are only split if requested by the Commonwealth of Virginia.

14

(

Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks C

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 Quarterly

& Annually 2250 Quarterly

& Annually 2430 Quarterly

& Annually 2870 Quarterly

& Annually 200 Quarterly

& Annually 110 Quarterly

& Annually 1150 Quarterly

& Annually 1670 Quarterly

& Annually 3010 Quarterly

& Annually 2420 Quarterly

& Annually 1580 Quarterly

& Annually 3250 Quarterly

& Annually 100 Quarterly 110 Quarterly 320 250 420 340 740 650 910 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly K

TABLE 1 (Page 1 of 5)

North Anna Power Station - 1999 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Control

C

(

Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental Thermoluminescent Dosimetry (TLD)

"Morning Glory Hill" Island Dike Route 622 VEPCO 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

(

TABLE 1 (Page 2 of 5)

North Anna Power Station - 1999 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I E-10/42 ESE-11/43 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 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 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 2.54 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 3190 3490 3440 1.670 3250 2430 2570 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control Control Control Control

K TABLE 1 (Page 3 of 5)

North Anna Power Station - 1999 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 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 Surface Water River Water Ground Water (Well Water)

Precipitation Aquatic Sediment In October 1991 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 01 02 03 04 05 05A 06 07 21 22 0.20 5.30 7.10 5.10 4.20 3.20 4.70 7.30 1.00 1.00 23 24 08 09 0.93 22.00 1.10 2.20 12.90 09A 11 OIA O0A 5.80 0.75 0.75 Waste Heat 08 1.10 Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 (Route 669 Bridge)

Nrthn A

aR'vr

.11 the Surface.Wa er Sam-leocaton at station 09 was moved to 09.

fdownstreama as NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW SSE NW WNW SE SE SE SSE WNW SSE 420 Weekly 2050 2430 2870 200 110 1150 1670 3010 2420 1580 3250 1480 3200 2950 1280 1380 1380 1480 3200 1280 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Monthly Monthly Monthly Monthly Quarterly Monthly Semi-Annually Semi-Annually Semi-Annually

/

Control Control Control Control

(

TABLE 1 (Page 4 of 5)

North Anna Power Station - 1999 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Waste Heat Treatment Facility (Second Cooling Lagoon)

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 Route 713 Route 614 08

01 02 03 04 05 05A 06 07 21 22 23 24 12 13 08 25 14 15 1.10 0.20 5.30 7.10 5.10 4.20 3.20 4.70 7.30 1.00 1.00 0.93 22.00 8.30 5.60 1.10 16.5 1.20 1.37 SSE NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW NW SSW SSE NW NE SE 148" Semi-Annually 420 Once/3 years 2050 2430 2870 200 110 1150 1670 3010 2420 1580 3250 3100 2050 148" 3120 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 Once/3 years Once/3 years Monthly Monthly Semi-Annually Semi-Annually Control Control 430 Monthly if available or at harvest 133" Monthly if available or at harvest Shoreline soil was changed from station 09 to 08 effective with the August 96 sample.

(

Shoreline Soil Soil Milk Fish Food Products (Broadleaf Vegetation)

C TABLE 1 (Page 5 of 5)

North Anna Power Station - 1999 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I

. Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Food Products (Broadleaf Vegetation)

Route 629/522 End of Route 685 Aspen Hills 16 21 23 12.60 1.00 0.93 NW WNW SSE 3140 3010 1580 Monthly if available Control or at harvest Monthly if available or at harvest Monthly if available or at harvest

(

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

(a)

(a) 1 1A 2

3 4

5 5A 6

7 8

01,NE-5/37 o1A,SE-13/45 02,SSW-20/52 03,C-5/16 04 5

05A,N-2/34 6,ESE-12/44 07,C-1&2 8-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,WNN-27/59 22,WSW-24/56 23-SSE-15/47 24,C-3&4 25-Fish Indicates air sample station, annual and quarterly TLD, Triennial soil In Orange In Lake Orange Station 09 changed to 08 effective with the August 96 sample.

20 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/93 17/49 19/51 21/53 23/55 25/57 16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 C-7&8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-40/36 E-10/42 9

9A 11 12 13 14 15 16 21 22 23 24 25 (a)

(b)

(c)

(d)

(a)

(a)(b)

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Analysis Program

1.

Table 2 summarizes the analysis program conducted by Teledyne Brown Engineering for North Anna Power Station during 1999.

26

TABLE2 (Page 1 of 3)

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 Annually Weekly Weekly Quarterly (a)

Annually (2nd Quarter Composite)

Monthly Quarterly (a) 2nd Quarterly Composite Gamma Dose 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 2mR+/-2mR 0.07 0.01 0.05 0.06 (c)

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

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

(a)

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

(b)

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

(c)

There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

27

TABLE 2 (Page 2 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM

,qA MPT.FE MF1MA FREOUENCY ANALYSIS LLD*

REPORT UNITS River Water Ground Water (Well Water)

Monthly Quarterly (a) 2nd Quarter Sample Quarterly (a) 2nd Quarter Composite Quarterly (a) 2nd Quarter Composite Semi-Annually Annually Aquatic Sediment 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 l(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) pCi/i pCi/1 pCi/1 pCi/i pCi/1 pCi/1 pCi/kg (dry) pCi/kg (dry)

Precipitation Monthly Gross Beta pCi/l Semi-Annual Gamma Isotopic pCi/1 Composite LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.

(a)

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

(b)

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

(c)

There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

28 SAMPLE MEDIA FREQUENCY ANALYSIS

TABLE 2 (Page 3 of 3)

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

REPORT UNITS Shoreline Soil Semi-Annual Annually Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 pCi/kg (dry) 150 180 (a)

(a)

Once per 3 yrs.

Monthly Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 150 180 (a)

(a) 1 pCi/kg (dry) pCi/kg (dry) pCi/l Monthly Quarterly Fish Food Products (Broadleaf Vegetation)

Semi-Annual Monthly if available or at harvest 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 15 18 60 15 (a)

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

This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

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

(a)

There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

29 Soil Milk

III. PROGRAM EXCEPTIONS 30

Appendix B REMP Exceptions For Scheduled Sampling And Analysis During 1999 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception All stations Sta-03 Sta-01A Air Iodine/

Air Particulates Air Iodine Precipitation 04/01-04/08 07/21-07/28 01/27-02/24 Samples were collected but lost by carrier.

Not received at the lab.

Positive result detected and confirmed by three gamma scans on different detectors. Result was slightly above lab detection limit. Result for this station for Air Particulates was in normal limits.

Sample was collected but lost by carrier.

Not received at the lab. Insufficient volume for back-up.

31

IV.

SUMMARY

AND DISCUSSION OF 1999 ANALYTICAL RESULTS 32

IV.

Summary and Discussion of 1999 Analytical Results Data from the radiological analyses of environmental media collected during 1999 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance Manual and are explained in the Teledyne Brown Engineering Analytical Procedures.

A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed.

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

Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of counting to time of collection.

Teledyne Brown Engineering's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, Radiological Monitoring Acceptable Program (November 1979, Revision 1) and the ODCM.

The following is a discussion and summary of the results of the environmental measurements taken during the 1999 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 except for one measurement from Station 03 at 0.03 pCi/m 3. For air particulates, gross beta activity was observed in all 51 control samples with an average concentration of 0.0 18 pCi/m 3 and a range of 0.011 to 0.034 pCi/m3. The average measurement for the indicator locations was 0.018 pCi/m3 with a range of 0.010 to 0.036 pCi/m 3.

The results of the gross beta activities are presented in Table B-2. The gross beta activities for 1999 were comparable to levels 33

TRENDING GRAPH-I: GROSS BETA IN AIR PARTICULATES 1987 1989 1990 1991 1992 1994 1995 1996 1997 1999 Control-Sta-24 Indicator Average Pre op

- 4 Required LLD's TRENDING GRAPH 2: TRITIUM IN RIVER WATER-STATION 11 I

ý L

I

[

t I

I 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 During the preoperational period, tritium was not detected in the samples analyzed.

Tritium Required LLD's 34

,Ct C

C Co tL 0.001 "

1986 10000 z

C C

1000 100 1o0

.C

==

4

measured in the 1982-1998 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing performed in other countries. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.

Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in all 48 composite samples. The average measurement for the control location was 0.084 pCi/m 3 with a range of 0.072 to 0.102 pCi/m 3. The indicator locations had an average concentration of 0.080 pCi/m 3 and a range of 0.055 to 0.119 pCi/m 3. During the preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Naturally occurring potassium-40 was not detected in any control samples.

Potassium-40 was detected in nine indicator samples with an average concentration of 0.004 pCi/m3 and a range of 0.003 to 0.007 pCi/m 3. 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 eleven indicator stations nor at the control station.

2.

Precipitation A sample of rainwater was collected monthly at station OIA, on site, 0.75 miles, 138 degrees SE and analyzed for gross beta activity. The February sample was not received at the lab. The results are presented in Table B-4. The average gross beta activity for 1999 in the 11 samples was 3.0 pCi/liter with a range from 1.4 to 6.5 pCi/liter. Semi annual composites were prepared and analyzed for gamma emitting isotopes and tritium.

Beryllium-7 was not detected during the semi-annual composite sample for the first half of 1999. 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 1998. During the preoperational period gross beta activity in rain water was expressed in pCi per square meter of the collector surface, 35

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 from twelve stations. They were collected and analyzed in 1998, therefore will not be collected during 1999.

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 1999. The second quarter sample was analyzed for strontium-89 and strontium-90. There were no detections of these isotopes above the detection level.

Tritium was also not measured above the detection level. No gamma emitting isotopes were detected during the preoperational period.

Tritium was measured in most of the samples during that period with concentrations between 80 and 370 pCi/liter.

2.

River Water A sample of water from the North Anna River was collected monthly at station 11, 5.8 miles downstream from the discharge lagoon, 128 degrees SSE. The results are presented in Table B-7.

The samples were analyzed by gamma spectroscopy monthly.

The samples were analyzed for tritium quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.

Potassium-40 was not detected during 1999 and all other gamma emitters were below the detection level. No detections of strontium-89 or strontium-90 occurred. Tritium was measured in all four samples with an average level of 3350 pCi/liter and a range of 3000 to 3800 pCi/liter. This is higher than the average level measured in 1998 of 2433 pCi/liter and a range of 1900 to 3000 pCi/liter. No river water samples were collected during the preoperational period.

36

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. No gamma emitters were above their detection level at either sampling station.

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 3975 pCi/liter with a range of 3300 to 4900 pCi/liter. Tritium was not detected at station 09A.

The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCi/liter. However, during 1999 the results were within the same range as those measured in 1986 through 1998.

During the preoperational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter..

C.

Aquatic Exposure Pathway

1.

Sediment/Silt Sediment samples were collected during February and August from each of three locations and were analyzed by gamma spectrometry. The results are presented in Table B-10.

One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in one sample with an activity of 142 pCi/kg (dry weight). The reading for cesium-137 was obtained from station 09A located 2.20 miles NW.

Naturally occurring potassium-40 was observed in all six samples with an average activity of 14750 pCi/kg (dry weight) and a range from 10700 to 20800 pCi/kg (dry weight).

Radium-226 was measured in five of the six samples with an average concentration of 1940 pCi/kg (dry weight) and a range of 1530 to 2410 pCi/kg (dry weight).

Also naturally occurring, thorium-228 was observed in all six samples with an average concentration of 1225 pCi/kg (dry weight) and a range of 593 to 1890 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89 or strontium-90 in aquatic sediment/silt.

37

TRENDING GRAPH - 3: TRITIUM IN SURFACE WATER - STA 08 1/77 V/79 1/81 1/83 1/85 1/87 1/89 1/91 1193 1/95 1/97 1/99 Tritium

-0 Required LLD's Average Pre-op TRENDING GRAPH -4: COBALT-58 IN SEDIMENT SILT 03/85 03/86 04/87 03/88 04/89 03/90 03/91 03/92 03/93 10/93 08/94 8/95 8/96 8/97 8/98 8/99 Dunng the preoperational period, cobalt-58 was not detected in the samples analyzed.

-Station-8 -

Station-0 Control Sta-09A Station-1I 38 10000 C

1000

,c 0

z 100 C*

C t 0 23

$=

TRENDING GRAPH -5: COBALT-60 IN SEDIMENT SILT 1000 I00 10 ii 0II86 I

I I

0190 I

I I

9I 08/8I 089 I

I I

0 8

I 9

03185 03/86 03187 03/88 04/89 03/90 03191 03/92 03/93 10193 08/94 08/95 08/96 08/97 08/98 8/99 During the preoperational period, cobaft-60 was not detected in the samples analyzed.

-U--

Station-8 - Station-09 Control-Sta-OSA Station-I1 TRENDING GRAPH - 6: CESIUM-134 IN SEDIMENT SILT 1000 1 0o 10-i I

i I

i i

i I

i 03/85 03/86 03/87 03/88 04/89 03/90 03/91 03/92 03/93 10/93 08/94 08/95 08/96 08/97 8/98 8/99 During the preoperational period, cesium-134 was not detected in the samples analyzed.

Station-8 Station-09 Control-Sta-09A Station-1l1 Required LLD's C-4-

39 C

-Z z

C" C

C 0

-o

TRENDING GRAPH - 7: CESIUM-137 IN SEDIMENT SILT 10O0 10 4/80 4/83 4/85 10/86 8/87 3/88 12/88 8/89 10/90 4/92 10/93 03/95 08/96 02/98 8/99

-U1--

Station-08 -

Station-09 Control-Sta-25 - Required LLD's TRENDING GRAPH - 8: CESIUM-134 IN FISH 4/80 4/83 4/85 10/86 8/87 3/88 12f88 8/89 10/90 4/92 10/93 03/95 08/96 02/98 During the preoperational period, cesium-134 was not detected in the samples analyzed.

Station 25 replaced station 09.

Station-08 Station-09 Control-Sta-25 Required LLD's 40 IC m

2 -C 0

a VX vA I

O-c t

0 aIo

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

Cesium-137 was measured in most of the samples with concentrations between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight). Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were measured at background levels.

2.

Shoreline Soil A sample of shoreline sediment was collected in February and August from station 08.

The samples were analyzed by gamma ray spectrometry. The results are presented in Table B-11. The naturally occurring nuclide potassium-40 was detected in both samples with an average activity of 1583 pCi/kg (dry weight) and a range of 895to 2270 pCi/kg (dry weight). Cosmogenic beryllium-7 was not detected during 1999. Thorium-228 was detected in both samples at an average of 341 pCi/kg (dry weight) and a range of 289 to 392 pCi/kg (dry weight). Radium-226 was detected in one sample with a concentration of 692 pCi/kg (dry weight). Cesium-137, a fission product, was not detected during 1999.

The August sample was analyzed for strontium. There was no detection of strontium-89 in shoreline soil. Strontium-90 was measured in the one sample with a concentration of 2300 pCi/kg (dry weight).

D.

Ingestion Exposure Pathway

1.

Milk The results of the iodine-131 analysis of milk samples are presented in Table B-12. A sample was collected monthly from two stations. A total of 24 samples were analyzed during 1999. There were no measurements of iodine-131 above the detection limits. The milk samples were also analyzed by gamma ray spectroscopy and the results are also presented in Table B-12. A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all samples with an average of 1291 pCi/liter and a range of 1100 to 1470 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 1999. All other gamma emitters were below their detection levels.

41

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 all eight samples monitored with an average level of 1.28 pCi/liter and a range of 0.96 to 2.4 pCi/liter.

This is similar to activities determined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/liter.

2.

Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-13. Eight samples of fish were collected during during 1999. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all samples at an average of 1289 pCi/kg (wet weight) with a range of 1000 to 1800 pCi/kg (wet weight). The fission product cesium-137 was measured in four samples an average activity of 37.8 pCi/kg (wet weight) and a range of 30.0 to 48.7 pCi/kg (wet weight). During the preoperational period cesium-137 was measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weight). All other gamma emitters were below their detection levels.

3.

Food/Vegetation Thirty-five food samples were collected from five locations and analyzed by gamma spectrometry. The results are presented in Table B-14. Naturally occurring potassium-40 was monitored in all samples with an average activity level of 21833pCi/kg (wet weight) and a range of 8270 to 36500 pCi/kg (wet weight).

Cosmogenic beryllium-7 was detected in all samples with an average concentration of 2952 pCi/kg (wet weight) and a range of 447 to 9910 pCi/kg (wet weight).

The terrestrial nuclide thorium-228 was detected in thirteen samples with an average activity of 170 pCi/kg (wet weight) and a range of 20.7 to 710 pCi/kg (wet weight).

Cesium-134, a fission product, was not detected at levels above LLD during 1999.

Cesium-137 was detected in five samples at an average activity of 40.1 pCi/kg (wet weight) and a range of 22.4 to 57.6 pCi/kg (wet weight). Cesium-137 has been detected in some samples at low-levels in previous years. Cesium-137 was measured in broadleaf 42

TRENDING GRAPH -9: CESIUM-137 IN FISH 10C

'U C

C 4

C t 0 z C-)

a 5/80 5/83 4/85 8/86 7/87 4/88 12/88 10189 10190 10191 4/93 8/94 03/96 08/97 02/99 Station 25 replaced station 09.

Station-08 ---

Station-09 Station-25 -A Average Pre-op 4

0 Required LLD TRENDING GRAPH - 10: ENVIRONMENTAL RADIATON - TILD's 10 1/86 1/87 1/88 1/89 1/90 1/91 1/92 1/93 1194 1195 1/96 1/97 1/98 1/99 Environmental TLD's Sector TLD's

-A Average Pre-op 43

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-15. Individual measurements of external radiation levels in the environs of the North Anna site had an average dose of 5.7 mRlstandard month with a range of 3.6 to 8.2 mR/standard month. This is comparable to the preoperational range. The control station, No. 24, had an average reading of 5.4 mR/standard month with a range of 4.6 to 6.1 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

16.

The average level of the 32 locations (two badges at each location) was 6.2 mR/standard month with a range of 3.6 to 9.5 mR/standard month. The eight control TLDs, collected quarterly from four locations, showed an average reading of 5.2 mR/standard month with a range of 3.4 to 7.1 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.

44

V. CONCLUSIONS 45

V. Conclusions The results of the 1999 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 1999 followed the gross beta concentrations at the control location.

The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1987 which was influenced by the Chernobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/CuM, due to occasional atmospheric nuclear weapons tests. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There were no detections above the LLD for fission products nor other man-made isotopes in the particulate media during 1999.

Iodine-131 was not detected in the charcoal filters during 1999 except for one measurement at Station 03, 7.1 miles, 243 WSW during the last week of July with a marginally positive result of 0.026 pCi/CuM.

A precipitation sample was collected monthly during 1999 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 1999. During the preoperational period the average tritium activity was 165 pCi/liter.

Waterborne Exposure Pathway No man-made or natural isotopes were monitored in the surface water of Lake Anna except tritium. The average tritium activity during 1999 at the waste heat treatment facility was 3975 pCi/liter, which is 13.2% of the reporting level for a water sample. In 1998 the tritium level was 2675 pCi/liter. The preoperational level was 150 pCi/liter and has risen since 1977, though it has remained relatively consistent since 1986.

46

The Commonwealth of Virginia discontinued the state sampling program in the third quarter of 1998.

River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3350 pCi/liter. The average tritium in 1998 had been 2600 pCi/liter.

No gamma emitters were detected.

Ground water from the environmental well on site contained no gamma emitters. There were also no detections of tritium in ground/well water during 1999.

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 one sample at the control location. During the preoperational period, cesium-137 was measured in samples of aquatic sediment. Sediment contamination does not provide a direct dose pathway to man.

The samples of shoreline soil monitored downstream of the site contained no measurement of cesium-134. Cesium-137 was also not detected during 1999. Cesium-137 was measured during 1998 at an average of 276 pCi/kg.

Ingestion Pathway Iodine-131 was not detected in any of the twenty-four milk samples using the radiochemical separation method.

Although cesium-137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there were no detections during 1999. Strontium-90 was measured in all eight 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 1999 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 1998.

Only cesium-137 was measured in preoperational environmental fish samples.

Due to primary and secondary steam generator 47

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 1999 of cesium-137 was 1.9% of the reporting level.

One vegetation sample for the control station contained cesium-137 at a level of 50.5 pCi/kg. There were also four samples for the indicator stations that measured cesium-137 at an average level of 37.6 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.

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 1999.

48

VI. REFERENCES 49

VI.

References

1.

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

2.

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

3.

Title 10 Code of Federal Regulation, Part 50 (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," Draft Rev. 3, March 1982.

50

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

TABLES - 1999 51

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1999 Docket No. 50-338/339 Air Iodine (pCVm3) 1-131 612 0.04 0.026(1/561)

Airborne Gross Particulates Beta (1 E-03 pCi/m 3) 612 5

18.0(561/561)

(9.8-36)

Gamma 48 Be-7 48 10 79.9(44/44)

(54.9-119)

K-40 48 10 4.99(9/44)

(3.4-7.4)

Sr-89 12 3

(0/11)

Sr-90 12 0.4 (0/11) 05 4.2 mi.

NNE 03 7.1 mi.

WSW N/A N/A 86.2(4/4) 84.2(4/4)

(62.8-117)

(71.7-102) 6.63(2/4)

(5.85-7.4)

N/A N/A (0/4)

(0/1)

Gamma 4

K-40 4

60 (0/4)

Tritium 4

2000 (0/4)

Sr-89 1

3 (0/1)

Sr-90 1

0.4 (0/1)

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

(0/0)

(0/0) 0 0

0 0

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

52 Page 1 of 6 All Indicator Control Non Medium or Anaysis Locations Locationwith ighestMean Location routine Pathway LocD*

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

Type No.

Range Direction Range Range ments 03 7.1 mi WSW 22 1.0 mi.

WSW (0/51) 0.026(1/51) 19.1(51/51)

(11-32) 1 17.8(51/51)

(11-34) 0 0

0 0

0 Ground Well Water (pCi/liter)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1999 Docket No. 50-338/339 Page 2 of 6 Gamma 12 K-40 12 200 (0/12)

Tritium 4

2000 3350(4/4)

(3000-3800)

Sr-89 1

3 (0/1)

Sr-90 1

0.4 (0/1)

N/A 11 5.8 mi.

SE N/A N/A N/A 3350(4/4)

(3000-3800)

N/A N/A Precipitation Monthly (pCi/liter)

Gross Beta Surface Water (pCi/liter)

Regular Monthlies 11 4

2.99(11/11)

(1.4-6.5)

Gamma 2

(Semi-Annually)

Tritium 2

2000 (0/2) 1-131 24 0.5 (0/12)

Gamma 24 K-40 24 200 (0/12)

Tritium 8

2000 3975(4/4)

(3300-4900) 01A 0.75mi.

2.99(11/11)

SE (1.4-6.5)

N/A N/A N/A N/A 08 1.10 mi SSE N/A N/A N/A N/A 3975(4/4)

(3300-4900)

(0/0)

(0/12)

-(0/4)

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.

53 All Indicator Control Non Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD*

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

Type No.

Range Direction Range Range ments River Water (pCi/liter)

(0/0)

(0/0) 0 0

0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1999 Docket No. 50-338/339 Page 3 of 6 Sr-89 1

Sr-90 (0/1)

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

(0/1) 0 0

Gamma 6

Be-7 K-40 6

(0/4) 6 200 16225(4/4)

(13200-20800)

Cs-1 37 6

194 (0/4)

Ra-226 6

100 1963(4/4)

(1530-2410)

NA 08 1.1 mi SSE 09A 12.9 mi.

WNW 08 1.1 mi.

SSE 18650(2/2)

(16500-20800) 142(1/2) 1970(2/2)

(1530-2410)

Th-228 6

30 1429(4/4) 08 1.1 mi.

1810(2/2)

(966-1890)

SSE (1730-1890)

Sr-89 (Annually)

Sr-90 (Annually) 3 4.0 (0/2) 3 0.8 5200(2/2)

(4600-5800)

N/A 11 5.8 mi.

SSE N/A 5800(1/2)

(0/2) 11800(2/2)

(10700-12900) 142(1/2) 1850(1/2) 817(2/2)

(593-1040)

(0/1) 4800(1/1)

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.

54 All Indicator Control Non Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD*

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

Type No.,

Range Direction Range Range ments Surface Water (pCi/liter)

Regular Monthlies Sediment Silt (pCi/kg (dry))

0 0

0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1999 Docket No. 50-338/339 Page 4 of 6 Gamma 2

Be-7 K-40 2

(0/2) 2 200 1583(2/2)

(895-2270)

Cs-1 37 2

40 (0/2)

Ra-226 2

100 692(1/2)

Th-228 2

30 341(2/2)

(289-392)SSE Sr-89 1

4.0 (0/1)

(Annually)

Sr-90 (Annually) 1 0.8 2300(1/1) 1-131 24 0.5 (0/24)

Gamma 24 K-40 24 100 1291(24/24)

(1110-1470)

Sr-89 (Quarterly) 12 8.3 mi.

NW 8

5 N/A Sr-90 8

0.8 1.28(8/8)

(Quarterly)

(0.96-2.4) 12 8.3 mi.

NW 1332(12/12)

(1160-1470)

N/A 1.45(4/4)

(0.99-2.4)

(0/0) 0 0

0 (0/0)

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

55 All Indicator Control Non Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD*

I*eported Sampled Total Mean Name Distance Mean Mean Ileasure (Unit)

Type No.

Range Direction Range Range ments Shoreline Soil (pCi/kg (dry))

N/A 8 1.1 mi.

SSE N/A 8 1.1 mi.

SSE 8 1.1 mi.

N/A N/A N/A N/A 1583(2/2)

(895-2270)

N/A 692(1/2) 341(2/2)

(289-392)

N/A 2300(1/1)

N/A (0/0)

(010)

(0/0)

(0/0) 0 0

0 0

Milk (pCi/liter)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1999 Docket No. 50-338/339 Page 5 of 6 Gamma 8

K-40 8

200 1303(4/4)

(1020-1800) 08 1.1 mi.

SSE Cs-137 8

40 37.8(4/4) 08 1.1 mi.

(30.0-48.7)

SSE 1303(4/4)

(1020-1800) 37.8(4/4)

(30.0-48.7) 1275(4/4)

(1000-1560)

(0/4)

Gamma 35 Dose Be-7 K-40 35 35 3089(28/28)

(447-9910)

- 21153(28/28)

(8270-36500)

Cs-1 37 35 80 37.6(4/28)

(22.4-57.6)

Ra-226 35 Th-228 35 506(8/28)

(225--965) 180(12/28)

(20.7-710) 21 1.0 mi.

WNW 16 12.6 mi.

NW 16 12.6 mi.

NW 14 1.2 mi.

NE 14 1.2 mi.

NE 3923(7/7)

(828-9910) 24557(6/6)

(18600-30900) 50.5(1/6) 203(2/6)

(129-276) 203(2/6)

(129-276) 2406(7/7)

(761-5960) 0 24557(7/7) 0 (18600-30900) 50.5(1/7) 0 416(1/7) 0 58.4(1/7) 0 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

56 All Indicator Control Non Medium or Anal sis Locations Location with Highest Mean Location rou t ine Pathway LLD*

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

Type INo.

Range Direction Range Range

,ments Fish pCi/kg (wet)

Food Vegetation (pCi/kg (wet))

0 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1999 Docket No. 50-338/339 Page 6 of 6 Direct Gamma Radiation Dose (mR/std. month)

(Regular TLDs)

Direct Gamma Radiation Dose (mR/std. Month)

(Annual TLDs) 48 0.2 5.69(44/44)

(3.6-8.2) 12 0.2 6.66(11/11)

(4.5-12.7)

Direct Gamma 288 0.2 Radiation Dose (mR/std. Month)

(Sector TLDs) 6.23(256/256)

(3.6-9.5) 01 0.2 mi. NE 7.63(4/4)

(6.7-8.2) 23 0.93 mi. SSE 9.1(1/1) 17/49 0.47 mi. S 9.08(8/8)

(8.7-9.4)

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.

57 All Indicator Control Non Medium or Anal sis Locations Locationwith ighestMean Location routine Pathway LLD*

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

Type No.

Range Direction Range Range ments 5.38(4/4)

(4.6-6.1) 6.3(1/1) 5.19(32/32)

(3.4-7.1) 0 0

0

APPENDIX B DATA TABLES 58

TABLE B-1: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 1999 pCi/m 3 +/- 2 Sigma Page 1 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JANUARY 12/30-01/07 01/07-01/13 01/13-01/20 01/20-01/27 01/27-02/03 FEBRUARY 02/03-02/10 02/10-02/17 02/17-02/24 02/24-03/04 MARCH 03/04-03/11 03/11-03/17 03/17-03/24 03/24-03/31 APRIL

<.007

<.01

<.008

<.006

<.009

<.02

<.008

<.005

<.008

<.007

<.01 04/01-04/08 (b) 04/08-04/14

<.03(c) 04/14-04/21

<.008 04/21-04/28

<.008

<.007

<.01

<.007

<.009

<.007

<.008

<.007

<.005

<.009

<.008

<.007

<.01

<.008

<.007

<.01

<.007

<.006

<.009

<.007

<.008

<.007

<.005

<.009

<.008

<.006

<.01

<.008

<.009

<.007

<.006

<.01

<.007

<.009

<.007

<.008

<.007

<.005

<.009

<.008

<.007

<.01

<.008

<.006

<.005

<.007

<.005

<.007

<.005

<.004

<.007

<.006

<.008

<.007

<.006

<.007

<.009(a) <.007

<.01

<.009

<.01

<.008

<.006

<.009

<.007

<.008

<.009

<.01

<.007

<.008

<.01

<.009

<.01

<.008

<.006

<.009

<.007

<.008

<.009

<.01

<.007

<.008

<.01

<.009

<.01

<.008

<.007

<.009

<.008

<.007

<.008

<.009

<.01

<.007

<.008 MAY 04/28-05/05 05/05-05/12 05/12-05/19 05/19-05/26 05/26-06/02

<.008

<.007

<.008

<.007

<.008

<.007

<.009

<.008

<.007

<.008

<.01

<.005

<.006

<.01

<.007

<.008

<.01

<.007

<.008

<.01

<.007

<.008 JUNE 06/02-06/09 06/09-06/16 06/16-06/23 06/23-06/30

<.007

<.006

<.007

<.009

<.007

<.006

<.007

<.009

<.007

<.006

<.007

<.009

<.007

<.006

<.007

<.009

<.005

<.007

<.01

<.01 (a)

Volume lower due to sampler malfunction.

[b)

Samples for the week of 04/01-04/08 collected, but lost by carrier.

59

<.007

<.01

<.009

<.01

<.008

<.007

<.009

<.008

<.006

<.008

<.009

<.01

<.008

<.005

<.007

<.009

<.007

<.006

<.008

<.005

<.006

<.005

<.006

<.009

<.005

<.01

<.02

<.005

<.01

<.009

<.01

<.007

<.009

<.01

<.007

<.01

<.006

<.01

<.007

<.01

<.02

<.008

<.01

<.009

<.01

<.007

<.01

<.007

<.009

<.01

<.007

<.008

<.01

<.007

<.008

<.01

<.008

<.009

<.005

<.01

<.008

<.007

<.008

<.01

<.009

<.01

<.005

<.006

<.009

<.01

<.008

<.009

TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 1999 Page 2 of 2 pCi/m 3 +/-2 Sigma Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JULY 06/30-07/07 07/07-07/14 07/14-07/21 07/21-07/28

<.008

<.03

<.007

<.02

<.008

<.03

<.008

<.01

<.008

<.03

<.007

<.008

.03+/-.005 (a)<.01

<.005

<.008

<.005

<.01

<.009

<.008

<.01

<.007

<.005

<.01

<.008 AUGUST 07/28-08/04 08/04-08/11 08/11-08/18 08/18-08/25 08/25-09/01 SEPTEMBER 09/01-09/08 09/08-09/15 09/15-09/22 09/22-09/29 OCTOBER 09/29-10/05 10/05-10/13 10/13-10/20 10/20-10/27 10/27-11/04 NOVEMBER 11/04-11/09 11/09-11/17 11/17-11/24 11/24-12/01 DECEMBER 12/01-12/08 12/08-12/15 12/15-12/22 12/22-12/29

<.007

<.009

<.007

<.008

<.009

<.01

<.006

<.01

<.02

<.01

<.007

<.008

<.009

<.01

<.008

<.009

<.007

<.008

<.009

<.01

<.009

<.007

<.01

<.007

<.008

<.009

<.01

<.008

<.009

<.007

<.008

<.009

<.01

<.006

<.01

<.007

<.008

<.009

<.01

<.008

<.009

<.007

<.008

<.009

<.01

<.009

<.006

<.01

<.007

<.008

<.009

<.01

<.005

<.006

<.005

<.006

<.007

<.008

<.006

<.004

<.008

<.007

<.04 (b)

<.008

<.005

<.006

<.009

<.01

<.009

<.01

<.02

<.01

<.008

<.01

<.009

<.02

<.007

<.01

<.008

<.01

<.009

<.01

<.02

<.01

<.007

<.01

<.009

<.02

<.007

<.01

<.009

<.01

<.009

<.01

<.007

<.01

<.009

<.02

<.007

<.01

<.008

<.01

<.009

<.01

<.007

<.01

<.009

<.02

<.007

<.01

<.008

<.01

<.008

<.009

<.008

<.009

<.006

<.007

<.009

<.007

<.005

<.008

<.006

<.01

<.005

<.007

<.006

<.008

<.007 (a)

Result confirmed by 3 counts on different detectors.

(b)

Low sample volume due to sampler not running; volume estimated.

60

<.005

<.01

<.007

<.01

<.008

<.01

<.008

<.01

<.007

<.01

<.007

<.005

<.006

<.01

<.006

<.005

<.01

<.008

<.01

<.007

<.01

<.008

<.006

<.01

<.009

<.007

<.01

<.007

<.01

(

TABLE B-2 (Page 1 of 4)

NORTH ANNA - 1999 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 1.OE-03 pCi/m3 +/- 2 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24

+/- 2 s.d.

12/30-01/07 17 +/- 2 15.+/- 1 01/07-01/13 24+/- 2 18-+/- 2 01/13-01/20 15 +/- 2 12 +/- 2 01/20-01/27 14 +/- 2 12_+/- 1 01/27-02/03 17 +/- 2 15 +/- 2 17+/- 2 16+/- 1 14+/- 1 20+/- 2 20+/- 2 21 +/- 2 12_+/- 2 15+/- 2 13+/- 2 13+/- 2 11 +/- 1 10+/- 1 17_+/-2 18-+/-2 17+/-2 16+/- 2 13- +/-2(a) 22+/- 2 22-+/- 2 13+/- 2 14+/- 2 11+/-1 13+/-2 17+/- 2 18+/- 2 FEBRUARY 02/03-02/10 17+/-4 15 +/- 2 01 02/10-02/17 13+/- 1 13 +/- 2 02/17-02/24 17 +/- 2 17+/- 2 02/24-03/04 15 +/- 1 12 +/- 1 14+/- 2 17+/-2 14+/- 2 14+/- 2 14+/- 2 14_+/- 2 15_+/- 2 18+/- 2 18-+/- 2 13+/- 1 15+/- 1 13+/- 1 15+/- 2 16-+/- 2 15+/- 2 16+/- 2 17+/- 2 18-+/- 2 12+/- 1 14+/- 1 MARCH 03/04-03/11 15+/- 2 15+/- 2 03/11-03/17 11 +/- 2 11 +/- 2 03/17-03/24 14 +/- 2 11 +/- 1 03/24-03/31 15 +/- 2 13 +/- 1 Quarter Avg.

16 +/- 6 14 +/- 4

+/- 2 s.d.

15_+/-_2 16+/-2 14-+/-2 9.8 +/- 1.5 10+/-t 1 9.9 +/- 1.5 12 +/- 2 14 +/- 2 15 +/- 2 15+/- 2 15-+/- 2 14+/- 2 14+/- 5 15+/- 6 14+/- 6 14 2

12+/- 2 11+/-2 11+/-2 13+/- 2 14 2

14+/- 2 15 2

15+/- 6 15 6

12+/- 2 12+/- 2 14+/- 2 15 +/- 2 14-+/- 4 12+/- 2 17 2

12+/-t 2 11 1

13+/- 2 15 2

16+/- 2 15 2

15+/- 5 15 5

12_+/- 2 13 +/- 2 15 +/- 2 14 +/- 2 14-+/- 2 12++/- 2 14_+/- 2 17+/- 2 15.t 6 15+/- 5 (a) Volume lower due to sampler malfunction.

(

C JANUARY 16-+/- 1 19+/- 2 13+/- 2 12+/- 2 16+/- 2 16+/- 2 20 +/- 2 13 +/- 2 13+/- 2 18-+/- 2 16+/- 1 21 +/- 2 13+/- 2 13_+/- 2 17+/- 2 16+/- 2 23 +/- 2 14+/- 2 13+/-2 16+/- 2 16+/- 2 22++/- 2 13-+/-2 12+/- 2 17+/-t 2 16+/-t 2 21-+/- 3 13+/-2 12 2

17.1: 2 15_+/- 2 14+/- 2 17 +/- 2 12-+/- 1 15+/- 2 15t 2 15_+/- 2 13 1

17+/-- 2 14-+/- 2 17 +/- 2 15++/- 1 16+/- 2 16_+/- 2 17-+/- 2 14.+/- I 17+/- 2 15-+/-2 15 +/- 2 15-+/- 1 16_+/- 2 14+/- 2 17+/- 2 14-+/- 2 14+/- 3 11+/- 2 14+/- 3 15+/-2 15+/- 5

(

TABLE B-2 (Page 2 of 4)

NORTH ANNA - 1999 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 1.OE-03 pCi/m3 +/- 2 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24

+/- 2 s.d.

APRIL 04/01-04/08 (b) 04/08-04/14 04/14-04/21 04/21-04/28 12+/- 2 12+/- 1 17_+/- 2 13 +/- 2 114+/-1 14++/-2 14-+ 2 13_+/- 1 19+/- 2 15 +/- 2 13+/- 1 14+/- 2 16+/- 2 13+/- 1 19+/- 2 15 +/- 2 12+/- 1 15 +/- 2 15 +/- 2 13-+/- 1 16_+/- 2 17_+/- 2 13+/- 1 17-+/- 2 14+/- 2 14+/- 2 23 +/- 2 15 +/- 2 14_+/- 2 18 +/- 2 16-+/- 6 13_+/- 2 17+/- 5 17+/- 2 11+/- 1 17+ 2 9.9 +/- 1.4 13+/- 2 12+/- 2 15 +/- 2 20_+/- 2 18_+/-2 14-+/- 2 13-+/-2 14+/- 2 12+/- 1 14-+/- 2 12 +/- 2 13_+/-_2 20 +/- 2 18_+/-2 15 +/- 2 14-+/- 2 17 +/- 2 11-+/-1 15 +/- 2 12+/- 2 15 +/- 2 19+/-2 17 +/- 2 14_+/- 2 12+/- 1 14_+/- 2 14+/- 6 15 +/-5 14+/- 4 11+/- 1 16+/-2 13 +/- 2 14_+/- 2 22+/- 2 22 +/- 2 15 +/- 2 14+/- 2 17 +/- 2 10-t 16+/-

11+/-

16+/-

20 +/-

1 2

2 20 +/- 2 14+/- 2 12+/-2 13 +/- 2 16+/- 7 15-t 7 10+/- 1 14+/- 2 10-+/- 1 15 +/- 2 23 +/- 2 20+/- 2 14+/- 2 13+/- 2 15 +/- 2 15 +/- 7 11 +/-

15 11+/-

14+/-

20+/-

1 2

2 20 +/- 2 12-+/- 1 12_+/- 2 14-+/- 2 11 +/-

15+/-

11+/-

14+/-

22+/-

1 2

2 19_+/- 2 14+/- 2 13 +/- 2 18_+/-2 11+/- 1 16+/- 2 13_+/- 2 14+/- 2 19+/- 2 19-+/- 2 14_+/- 2 13 +/- 2 16+/- 2 11+/- 1 15+/- 2 11+/- 1 14+/- 2 20+/- 2 17_+/-_2 14_+/- 2 12-+/- 2 17 +/- 2 14+/- 6 15+/- 7 16+/- 7 15+/- 6 (a) Samples for the week of 04/01-04/08 collected, but lost by carrier.

(b) Low sample volume.

(

24 +/- 5(c) 14-+/- 2 17_+/-2 MAY 9.8 +/-

13+/-

11+/-

12+/-

20+/-

1.3 2

1 2 2 04/28-05/05 05/05-05/12 05/12-05/19 05/19-05/26 05/26-06/02 JUNE 06/02-06/09 06/09-06/16 06/16-06/23 06/23-06/30 Quarter Avg.

+/- 2 s.d.

10+/- 1 13 +/- 2 13 +/- 2 16+/-2 21 t 2 21 +/- 2 16-+/- 2 13_+/-2 12 +/- 2 16 +/- 8 17 +/- 2 12_+/- 1 11+/-1 15+/- 2 14+/- 6 11_+/-1 15_+/-2 12+/- 2 14-+/- 2 21 +/- 2 19-+/- 3 14-+/- 2 13_+/-2 15 +/- 4 15 +/- 6

(

TABLE B-2 (Page 3 of 4)

NORTH ANNA - 1999 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 1.OE-03 pCi/m 3 +/- 2 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 t 2 s.d.

JULY 06/30-07/07 23 +/- 2 19 +/- 2 07/07-07/14 17 +/- 2 16 +/- 2 07/14-07/21 25 +/- 2 20:+/- 2 07/21-07/28 24 +/- 2 18 +/- 2 22-+/-2 23+/-2 21+/-2 16+/-2 17+/-2 17+/-2 20+/- 2 22+/- 2 22+/- 2 21+/-2 19+/-2 20+/-2 25+/- 2 19-+/- 2 17+/- 2 14_+/- 2 24+/- 2 20+/- 2 22+/- 2 22+/- 2 24+/- 2 14+/- 2 23+t 2 21:+/- 2 20+/- 2 25+/- 2 24+/- 2 22+/- 2 13+/-2 16+/-2 15+/-2 16+/-2 20+/- 2 26+/- 2 22+/- 2 24+/- 2 21+/- 2 24+/- 2 23+/- 2 21 +/- 2 AUGUST on 07/28-08/04 25 +/- 2 19+/- 2 C,

08/04-08/11 29 +/- 2 22 +/- 2 08/11-08/18 30+/- 2 26+/- 2 08/18-08/25 23 +/- 2 19 +/- 2 08/25-09/01 23 +/- 2 19 +/- 2 20+/- 2 23+/- 2 19+/- 2 24+/- 2 24-+/- 2 23+/- 2 27-+/-2 31-+/--2 30-+/-2 20+/-2 21+/-2 20+/-2 17+/- 2 18+/- 2 18+/- 2 25+/- 2 19+/- 2 26+/- 2 22+/- 2 32+/- 2 27+/-2 22+/- 2 19+/- 2 21+/- 2 20+/- 2 22:t 2 26+/- 2 26+/- 2 20+/- 2 21 +/- 2 20+/- 2 25+/- 2 22+/- 2 18+/- 2 22+/- 2 25+/- 2 24+/- 2 23+/- 2 26+/- 2 27+/- 2 30+/- 2 26+/- 2 18+/-2 23+/-2 21+/-2 18+/-2 16+/- 2 20+/- 2 18+/- 2 16+/- 2 SEPTEMBER 09/01-09/08 17 +/- 2 15 +/- 2 09/08-09/15 19 +/- 2 24 +/- 2 09/15-09/22 12 +/- 2 15 +/- 2 09/22-09/29 17 +/- 2 23 +/- 2 Quarter Avg.

22 +/- 10 20 +/- 7

+/- 2 s.d.

18 +/-2 17-+/- 2 17-+/- 2 23+/-2 28-+/-2 26+/-2 16+/-2 16+/-2 15+/-2 22+/- 2 24+/- 2 25-+ 2 20+/- 6 22+/- 9 21+/- 8 21+/-2 18+/-2 27+/- 2 24+/- 2 21+/-2 18+/-2 25+/- 2 22-+/- 2 24 +/-7 20+/- 6 17 +/- 2 29 +/- 2 16-+/--2 26+/- 2 22+/- 9 13+/- 2 20+/- 2 17+/- 2 18+/- 2 25+/- 2 29+/- 2 27-+/- 2 25+/-t 2 15+/- 2 19-+/- 2 15+/- 2 14-+/- 2 23+/- 2 28-+/- 2 22+/- 2 18+/- 2 19-+/- 8 24+/- 8 22-+/- 9 20+/- 8 22+/- 4 16+/- 3 22 +/- 4 21 +/- 4 21 +/- 5 24+/- 4 28-+/- 4 20+/- 3 19+/-4 17 +/- 4 26-+/- 6 16+/- 5 23 +/- 6 21 +/- 8

(

TABLE B-2 (Page 4 of 4)

NORTH ANNA - 1999 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 1.OE-03 pCi/m3 +/-2 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24

+ 2 s.d.

OCTOBER 09/29-10/05 13 +/- 2 10/05-10/13 17 +/- 2 10/13-10/20 12+/- 2 10/20-10/27 18+/- 2 10/27-11/04 31 +/- 2 15 +/- 2 17+/- 2 16+/- 2 17+/- 2 28 +/- 2 17 +/- 2 20+/- 2 14+/- 2 20 +/- 2 25 +/- 2 22+/- 2 19-+/- 2 20+/- 2 20++/- 2 18+ +/-2 16-+/- 2 18+/- 2 18+/- 2 31+/-2 32-+/-2 21 +/- 2 19+/- 2 22+/- 2 22+/- 2 18+/- 2 16+/- 2 18+/- 2 20++/- 2 31++/-2 27-+/-2 20+/- 2 22+/- 2 17+/- 2 18+/-2 33 +/- 2 15 +/- 2 18-+/- 2 16+/- 2 19+/- 2 28 +/- 2 19+/- 2 20+/- 2 19+/- 2 20+/- 2 21 +/- 2 16+/- 2 20+/- 2 15+/- 2 15-+/- 2 19+/- 2 19+/- 2 18+/- 2 32+/- 2 29+/- 2 29-+/- 2 NOVEMBER oh 11/04-11/09 27+/- 3 24+/- 2 11/09-11/17 34 +/- 2 29 +/- 2 11/17-11/24 13+/- 2 9.8+/- 1.4 11/24-12/01 17+/- 2 15-+/- 2 29-+/- 3 33 +/- 2 12+/- 1 19+/- 2 25 +/- 2 26 +/- 7 (a) 32 +/- 3 28 +/- 3 32+/- 2 29+/- 2 36+/- 2 28+/- 2 14+/-2 11 +/-1 13+/-2 11 1

21+/- 2 14+/- 2 14+/- 2 17 2

32-+/- 3 36+/- 2 14-+/- 2 18-+/- 2 25 +/- 2 30-+/- 2 11+/- 1 18-+/-2 30+/- 3 29+/- 3 24-+/- 2 32+/- 2 32+/- 2 34++/- 2 12+/- 1 12+/- 2 14+/- 2 19+/-2 17-+/-2 21+/-2 DECEMBER 12/01-12/08 20+/- 2 19+/- 2 12/08-12/15 21 +/- 2 18 +/- 2 12/15-12/22 17 +/- 2 16 +/- 2 12/22-12/29 21 +/- 2 18 +/- 2 Quarter Avg.

20 +/- 14 19 +/- 11

+/- 2 s.d.

Annual Avg.

18 +/- 11 16 +/- 9

+/- 2 s.d.

19+/- 2 20 +/- 2 18_+/- 2 19+/- 2 22+/- 2 20-+/- 2 22+/- 2 20+/- 2 20+/- 2 17++/- 2 22+/- 2 18-+/- 2 19+/- 2 20-+/- 2 21 +/- 2 18 +/- 2 18+/- 2 19-+/- 2 17+/- 2 19-+/- 2 20+/- 11 22+/- 10 20 +/- 12 22+/- 14 20 +/- 10 17+/- 10 19 +/- 10 17 +/- 10 19 +/- 12 18 +/- 9 21 +/- 2 21 +/- 2 14+/- 2 19+/- 2 19+/- 2 22-+/- 2 20-+/- 2 19+/- 2 21-+/-2 20+/-2 23-+/-2 21 +/- 2 23+/- 2 22+/- 2 18+ +/-2 19+/- 2 20+/- 2 19+/- 2 19+/- 2 19-+/- 2 22 +/- 14 20 +/- 10 22 +/- 12 21 +/- 12 21 +/- 11 18 +/- 12 17 +/- 9 19 +/- 11 18 +/- 10 18 +/- 9 20-+/- 3 21 +/- 3 18++/-4 19-+/- 3 21 +/- 12 18 +/- 10 (a)

Low sample volume due to sampler not running; volume estimated.

18+/- 5 20+/- 4 16+/- 2 19+/- 2 30+/- 5 28 +/- 6 32+/- 5 12-+/- 3 18++/-5

TABLE B-3: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 1999 1.0 E-03 pCi/m 3 -- 2 Sigma Page 1 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/30-03/31 03/31-06130 06/30-09/29 09/29-12/29 STA-01 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-i 34 Cs-1 37 Th-228 STA-02 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-134 Cs-i 37 Th-228 STA-03 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-1 34 Cs-i 37 Th-228 STA-04 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-1 34 Cs-i 37 Th-228 (a)

(a) 68.4 +/- 6.8

<7

< 0.2

< 0.4

< 0.2

< 0.3

< 0.4 (a)

(a) 63.4 +/- 6.3

<9

< 0.3

< 0.4

< 0.3

< 0.3 (a)

(a) 78.0 +/- 7.8

<5

< 0.2

< 0.4

< 0.2

< 0.5 (a)

(a) 74.8 +/- 7.5

<5

< 0.2

< 0.3

< 0.2

< 0.3

<2

< 0.2 99.8 +/- 10

<6

< 0.4

< 0.3

< 0.5

<2

< 0.3 96.3 +/- 9.6

<5

< 0.3

< 0.4

< 0.3

< 0.5

<2

< 0.3 90.1 +/- 9 5.85 +/- 2.43

<0.3

< 0.4

< 0.3

<0.4

<3

< 0.4 92.6 +/- 9.3

<10

< 0.3

<0.5

< 0.3

< 0.4 (a)

(a) 83.1 +/- 8.3

<5

< 0.3

< 0.5

< 0.3

< 0.5 (a)

(a) 78.4 +/- 7.8

<4

< 0.3

< 0.5

< 0.2

< 0.3

< 0.4 (a)

(a) 72.3 +/- 7.2 7.40 +/- 2.33

<0.3

< 0.5

< 0.3

< 0.3 (a)

(a) 74.9 +/- 7.5

<10

< 0.3

< 0.5

< 0.3

< 0.4 (a)

(a) 70.7 +/- 7.1

<4

< 0.3

< 0.2

< 0.4 (a)

(a) 54.9 +/- 5.5 4.56 +/- 1.65

< 0.2

< 0.3

< 0.2

< 0.3 (a)

(a) 74.6 +/- 7.5

<4

<0.3

< 0.3

< 0.2

< 0.4 (a)

(a) 66.6 +/- 6.7

<4

< 0.3

< 0.2

< 0.4 80.5 +/- 28.8 73.3 +/- 36.4 4.56 +/- 1.65 78.8 +/- 15.8 6.63 +/- 2.19 77.2 +/- 21.9 All gamma emitters other than those listed were <LLD.

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

65

TABLE B-3: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 1999 1.0 E-03 pCi/m 3 +/- 2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/30-03/31 03/31-06/30 06/30-09/29 09129-12/29 STA-05 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-1 34 Cs-i 37 Th-228 STA-05A Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-103 Cs-1 34 Cs-1 37 Th-228 STA-06 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-i 34 Cs-137 Th-228 STA-07 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-1 34 Cs-i 37 Th-228

<2

< 0.3 117+/- 12 4.89 +/- 2.04

< 0.3

< 0.4

< 0.2

< 0.3

< 0.5

<2

< 0.3 107+/- 11

<6

< 0.2

< 0.3

<0.2

< 0.3

< 0.4

<2

<0.2 107+/- 11 6.46 +/- 2.82

< 0.3

< 0.5

< 0.3

< 0.5 (a)

(a) 86.7 +/- 8.7

<4

< 0.3

< 0.4

<0.2

< 0.2

< 0.5 (a)

(a) 68.4 +/- 6.8

<4

<0.2

< 0.3

< 0.2

< 0.3

< 0.4 (a)

(a) 78.5 +/- 7.8

<4

<0.2

<0.3

< 0.2

< 0.4 (a)

(a) 66.4 +/- 6.6

<7

< 0.2

< 0.3

< 0.2

< 0.3 (a)

(a) 78.3 +/- 7.8

<3

< 0.3

< 0.4

<0.2

< 0.2

< 0.4 (a)

(a) 88.0 +/- 8.8

<6

< 0.2

< 0.3

< 0.2

< 0.3 (a

(a) 82.0 +/- 8.2 3.99 +/- 1.68

< 0.2

< 0.4

< 0.2

< 0.4 (a)

(a) 79.5 +/- 7.9

<4

< 0.2

< 0.3

< 0.2

< 0.4 (a)

(a) 62.8 +/- 6.3 3.77 +/- 1.59

< 0.3

< 0.2

< 0.3 1.35 +/- 0.32 (a)

(a) 64.7 +/- 6.5

<5

< 0.2

< 0.3

< 0.2

< 0.3 (a)

(a) 63.3 +/- 6.3

<10

< 0.3

< 0.4

< 0.3

< 0.5 (a)

(a) 77.1 +/- 7.7

<5

< 0.3

< 0.4

< 0.3

< 0.5 86.2 +/- 45.6 4.33 +/- 1.58 1.35 +/- 0.32 82.0 +/- 39.1 82.7 +/- 36.2 5.23 _ 3.49 82.0 +/- 32.7 All gamma emitters other than those listed were <LLD.

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

66

<2

< 0.3 105+/- 11

<5

<0.2

< 0.4

< 0.2

< 0.5

TABLE B-3: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 1999 1.0 E-03 pCi/m 3 _+ 2 Sigma Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/30-03/31 03/31-06/30 06/30-09/29 09/29-12/29 STA-21 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-i 34 Cs-1 37 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-1 37 Th-228 STA-24 Sr-89 Sr-90 Be-7 K-40 Co-60 Ru-1 03 Cs-134 Cs-1 37 Th-228 (a)

(a) 56.5 t 5.7

<4

< 0.3

< 0.4

< 0.2

< 0.3

<0.4 (a)

(a) 58.9

5.9

<5

< 0.2

< 0.3

< 0.2

< 0.3 (a)

(a) 74.6 +/-- 7.5

<3

<0.2

< 0.3

<0.2

< 0.3

< 0.3 (a)

(a) 72.9 +/- 7.3

<10

<0.3

< 0.5

< 0.3

< 0.5

<1

< 0.2 89.1 +/- 8.9

<8

< 0.3

< 0.4

<0.3

< 0.4

<2

< 0.3 94.6 +/- 9.5

<10

< 0.3

< 0.4

< 0.3

< 0.4

<3

< 0.4 119 +/- 12 4.52 +/- 2.15

<0.2

<0.3

< 0.3

< 0.4

<1

<0.2 102 +/- 10

<6

< 0.3

<0.2

< 0.4 (a)

(a) 74.2 +/- 7.4

<4

< 0.2

< 0.4

< 0.2

<0.4 (a)

(a) 88.6 +/- 8.9

<5

< 0.2

< 0.4

<0.2

< 0.2

< 0.3 (a

(a) 72.3 +/- 7.2

<10

<0.3

<0.6

<0.3

< 0.3

< 0.5 (a)

(a) 90.0 + 9.0

<4

< 0.2

< 0.4

< 0.2

<0.4 (a)

(a) 66.6 +/- 6.7

<6

< 0.2

< 0.3

< 0.2

< 0.3

< 0.5 (a)

(a) 76.1 +/- 7.6

<4

< 0.2

< 0.3

< 0.2

< 0.4 (a)

(a) 72.5 +/- 7.3 3.44 +/- 1.52

< 0.2

< 0.3

< 0.2

< 0.3 (a)

(a) 71.7 +/- 7.2

<4

< 0.2

< 0.3

< 0.2

< 0.4 71.6 +/- 27.5 79.6 t 31.6 84.6 +/- 45.9 3.98 +/- 1.53 84.2 t 29.1 All gamma emitters other than those listed were <LLD.

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

67

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

CONCENTRATIONS IN PRECIPITATION Station 01A -- (On Site)

North Anna Power Station, Louisa County, Virginia - 1999 pCi/I +/-2 Sigma Page 1 of 1 Collection Dates Gross Beta Rainfall (inches) 12/30/98-01/27/99 01/27/99-02/24/99 02/24/99-03/31/99 03/31/99-04/28/99 04/28/99-05/26/99 05/26/99-06/30/99 06/30/99-07/28/99 07/28/99-08/25/99 08/25/99-09/29/99 09/29/99-10/27/99 10/27/99-11/24/99 11/24/99-12/29/99 Average +/-2 s.d.

(a) Sample not received.

SEMI-ANNUAL PRECIPITATION COMPOSITES 12/30/98-06/24199 06130/99-12/29/99 i

Be-7 = < 30 H3

< 200 Be-7 = < 30 H3 = < 200 All gamma emitters other than those listed were <LLD.

68 2.6:+/- 0.6 (a) 2.8 +/- 0.8 6.5 +/- 0.9 3.5 +/- 0.7 1.8 +/- 0.6 3.4 +/- 0.7 5.3 +/- 0.8 2.1 +/- 0.6 1.6 +/- 0.6 1.4 +/- 0.7 1.9 +/- 0.6 3.0 +/- 3.2 4.40 4.85 1.36 1.27 1.34 1.55 1.48 8.11 4.77 0.82 3.39

TABLE B-5 NORTH ANNA - 1999 CONCENTRATIONS OF GAMMA EMITTERS* IN SOIL 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 will not be collected during 1999.

(

TABLE B-6: GAMMA EMITTER*, STRONTIUM AND TRITIUM CONCENTRATIONS IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 1999 pCi/I t 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 Ba-140 Th-228 STATION 01A 03/31/99 (a)

(a)

< 200

< 30

< 50

< 0.4

< 4

<6 06/30/99

< 3.0

< 0.3

< 200

< 40

< 50

< 0.3

<7

< 7 09/29/99 (a)

(a)

< 300

< 30

< 50

< 8 (b)

< 6

< 6 12/29/99 (a)

(a)

< 200

< 40

< 90

<10

< 8

< 6 Average +/-2 sd.

All gamma emitters other than those listed were <LLD.

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

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

TABLE B-7: GAMMA EMITTER*, STRONTIUM AND TRITIUM CONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1999 pCi/I +/-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 - 11 01/13/99 (a)

(a) 3000 +/- 200

< 30

< 50

< 0.3

< 4

< 6

< 60

< 5 02/11/99 (a)

(a)

(b)

< 30

< 100

< 0.4

< 4

< 7

< 70

< 6 03/15/99 (a)

(a)

(b)

< 30

< 90

< 0.3

< 4

< 5

< 70

< 6 04/12/99 < 4.0

< 0.3 3000 +/- 200

< 30

< 40

< 0.2

< 3

< 4

< 70

< 6 05/17/99 (a)

(a)

(b)

< 30

< 60

< 0.3

< 3

< 6

< 60

< 6 06/14/99 (a)

(a)

(b)

< 30

< 60

< 0.3

< 3

< 6

< 80

< 7 07/09/99 (a)

(a) 3800 +/- 300

< 30

< 90

< 0.7

< 4

< 7

< 70

< 6 08/16/99 (a)

(a)

(b)

< 40

< 50

< 20 (c)

< 4

<10

< 70

< 6 09/13/99 (a)

(a)

(b)

< 30

< 50

< 0.3

< 3

<10

< 60

< 6 10/15/99 (a)

(a) 3600 +/- 200

< 40

< 60

< 20 (c)

< 4

<10

< 90

< 8 11/12/99 (a)

(a)

(b)

< 50

< 100

< 20 (c)

< 4

<10

< 80

< 7 12/13/99 (a)

(a)

(b)

< 30

< 50

< 10 (c)

< 4

< 7

< 70

< 6 Average +/- 2 sd 3350 +/- 825 (a) Sr-89/90 analyses performed only on second quarter samples.

(b) Tritium analysis performed on quarterly composite.

(c) 1-131 results by gamma. More sensitive results by radiochemistry not requested nor performed by vendor.

70

TABLE B-8: GAMMA EMITTER*, STRONTIUM AND TRITIUM CONCENTRATIONS IN SURFACE WATER North Anna Power Station, Louisa County, Virginia - 1999 pCi/Il +/- 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)

(a) 3300 +/-200 < 30

< 50

< 0.4

<4

<7

< 70

<6 02/11 (a)

(a)

(b)

< 30

< 50

< 0.4

<3

<6

< 80

<7 03/15 (a)

(a)

(b)

< 30

< 50

< 0.3

<3

<5

< 80

<6 04/12

< 8.0

< 0.6 3500 +/-200 < 30

< 50

< 0.3

< 3

< 7

< 80

< 6 05/17 (a)

(a)

(b)

< 30

< 50

< 0.4

< 3

< 4

< 70

< 6 06/14 (a)

(a)

(b)

< 20

< 40

< 0.4

< 3

< 4

< 60

< 5 07/09 (a)

(a) 4900 +/-300

< 30

< 50

< 0.6

< 3

< 7

< 90

< 7 08/16 (a)

(a)

(b)

< 30

< 50

< 20 (c)

< 3

<10

< 70

< 6 09/13 (a)

(a)

(b)

< 30

< 80

< 0.4

< 3

< 6

< 60

< 5 10/15 (a)

(a) 4200 +/-200

< 30

< 50

< 20 (c)

< 4

<10

< 70

< 6 11/12 (a)

(a)

(b)

<30

<50

<20 (c)

<3

<10

<70

<<7 12/13 (a)

(a)

(b)

< 40

< 60

< 10 (c)

< 4

< 9

< 90

< 7 Average +/-2 sd 3975 +/- 1455 STATION - 09A 01/13 (a)

(a)

< 200

< 30

< 60

< 0.3

< 4

< 7

< 60

< 5 02/11 (a)

(a)

(b)

< 30

< 40

< 0.4

< 3

< 6

< 70

< 6 03/15 (a)

(a)

(b)

< 30

< 40

< 0.3

< 3

< 4

< 70

< 6 04/12

< 4.0

< 0.3

< 200

< 30

< 50

< 0.2

< 4

< 6

< 80

< 7 05/17 (a)

(a)

(b)

< 30

< 90

< 0.4

< 4

< 6

< 70

< 6 06/14 (a)

(a)

(b)

< 40

<100

< 0.3

< 5

< 7

< 80

< 7 07/09 (a)

(a)

< 300

< 30

< 50

< 0.6

<3

<5

< 70

<6 08/16 (a)

(a)

(b)

< 30

< 70

< 20 (c)

<3

<10

< 60

< 6 09/13 (a)

(a)

(b)

< 30

< 50

< 0.4

<3

<7

< 70

<6 10/15 (a)

(a)

< 200

< 40

< 60

< 20 (c)

<4

<10

< 70

<7 11/12 (a)

(a)

(b)

< 40

< 90

< 20 (c)

<4

<10

< 70

< 6 12/13 (a)

(a)

(b)

< 30

< 40

< 10 (c)

<3

< 6

< 80

<6 All gamma emitters other than those listed were <LLD.

1-131 by radiochemistry (a) Analysis performed only with second quarter.

(b) Tritium analysis performed on quarterly composite.

(c) 1-131 results by gamma. More sensitive method by radiochemistry not requested nor performed by vendor.

71

TABLE B-9: GAMMA EMITTER* AND TRITIUM CONCENTRATIONS IN SURFACE WATER State-Split Samples North Anna Power Station, Louisa County, Virginia - 1999 pCi/I +/- 2 Sigma Page 1 of 1 Collection Dates H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-226 Th-228 State sampling was discontinued in the third quarter 1998.

72

TABLE B-10: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 1999 pCi/kg +/- 2 Sigma Page 1 of 1 STA-08 STA-09A STA-1 1 STA-08 STA-09A STA-1 1 Average Nuclide 02/11 02/11 02/11 08/16 08/16 08/16

+/- 2 s.d.

Sr-89 (a)

(a)

< 2000

< 2000 Sr-90 (a)

(a)

(a) 4600 _ 600 4800 +/- 600 5800 +/- 600 5067 +/- 1286 Be-7

< 200

< 300

< 200

< 400

< 300

< 300 K-40 20800_+/- 2100 10700+/- 1100 14400+/-t 1400 16500+/- 1600 12900+/- 1300 13200+/- 1300 14750+/-t 7044 Mn-54

< 30

< 20

< 40

< 30

< 30 Co-58

< 30

< 20

< 40

< 30

< 30 Co-60

< 30

< 40

< 20

< 40

< 30

< 30 Cs-134

< 30

< 40

< 40 Cs-137

< 30

< 40

< 30

< 40 142 +/- 34

< 30 142 +/- 34 Ra-226 2410 +/- 440

< 700 1930 +/- 360 1530 +/-t 630 1850 +/- 460 1980 +/- 420 1940 +/- 632 Th-228 1890_+/- 190 593_+/- 61 1130+/- 110 1730+/- 170 1040_+/- 100 966_+/- 97 1225+/- 983 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

TABLE B-11: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 1999 pCi/kg +/-2 Sigma Page 1 of 1 Station-08 Station-08 Average Nuclide 02111/99 08/16/99

+/- 2 Sigma (a)

(a)

< 300 895 +/- 251

< 30

< 20

< 30

< 600

< 2000 2300+/- 500

< 200 2270 +/- 230

<10

< 20

< 20 692 +/- 236 2300:+/- 500 1583:+/- 1945 692 +/- 236 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

73 Sr-89 Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-1 37 Ra-226

TABLE B-12: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 1999 pCi/I +/- 2 Sigma Page 1 of 2 MONTH NUCLIDE STATION-12 STATION-13 JANUARY FEBRUARY Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-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 MARCH APRIL MAY JUNE (a)

(a) 1300 +/- 130

<4

<0.2 (a)

(a) 1450 +/- 140

<3

<0.3

<4 0.99 +/- 0.25 1330 +/- 130

<4

<0.2 (a)

(a) 1470 +/- 150

<3

<0.3 (a)

(a) 1370 +/- 140

<4

<0.2

<7 2.4+/- 0.5 1360 +/- 140

<3

<0.4 (a)

(a) 1110+/- 110

<4

< 0.2 (a)

(a) 1310 +/- 130

<4

< 0.3

<6 1.3 +/- 0.4 1350 +/- 140

<4

< 0.3 (a)

(a) 1240 +/- 120

<4

< 0.2 (a)

(a) 1160+/- 120

<4

< 0.3

<4 0.96 +/- 0.27 1300 +/- 130

<4

< 0.2 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.

74

TABLE B-12: GAMMA EMITTER* AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 1999 pCi/I +/- 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-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 (a)

(a) 1250 +/- 120

<4

< 0.2 (a)

(a) 1370 +/- 140

<4

< 0.2

<3 1.3 +/- 0.3 1210 +/- 120

<4

< 0.3 (a)

(a) 1390 +/- 140

<4

< 0.3 (a)

(a) 1160+/- 120

<4

<0.3

<4 1.1 +/- 0.3 1320 +/- 130

<4

< 0.2 1.45 +/- 1.3 1332 +/- 183 (a)

(a) 1400 +/- 140

<3

<0.3 (a)

(a) 1180 +/- 120

<4

<0.2

<4 1.1+/- 0.3 1120+/- 110

<5

<0.2 (a)

(a) 1240 +/- 120

<4

<0.3 (a)

(a) 1270 +/- 130

<3

<0.3

<3 1.1+/-0.2 1330 +/- 130

<4

<0.3 1.12+/- 0.28 1251 +/- 186 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.

75

TABLE B-13: GAMMA EMITTER* CONCENTRATIONS IN FISH North Anna Power Station, Louisa County, Virginia - 1999 pCilkg +/- 2 Sigma Page 1 of I I 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) 1800 +/- 210 1430 +/- 150 1360 +/- 160 1110 +/- 110 1020 +/- 160 1560 +/- 170 1030 +/- 130 1000 +/- 140 1289 +/- 593

<10

< 20

<10

< 20

<10

< 20

<10

< 20 48.7 +/- 14.4

<10 42.0 +/- 12.3

<10 30.5 +/- 12.8

<10 30.0 +/- 12.2

< 20 37.8 +/- 18.3 All gamma emitters other than those listed were <LLD.

(a) Non-bottom dwelling species of gamefish.

(b)

Bottom dwelling species of fish.

76 08 25 08 25 08 25 08 25 02/09 02/09 02/09 02/09 08/18 08/16 08/18 08/16 Avg.

+/- 2 s.d.

TABLE B-14: GAMMA EMITTER* CONCENTRATIONS IN FOOD/VEGETATION North Anna Power Station, Louisa County, Virginia - 1999 pCi/kg t 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 04/21 2400+/-+ 240 19200:+/- 1900

< 30

< 20

< 20 22.4+/- 10.9 548 +/- 176 276 +/- 28 05/19 469 +/- 195 26300:+/- 2600

< 40

< 30

< 400

< 40 06/16 722 +/- 170 19900 +/- 2000

< 40

< 30

< 20 27.4 +/- 14.6

< 400

< 40 07/21 447 +/- 121 21300 +/- 2100

< 40

< 20

<10

< 300

< 20 08/18 609 +/- 78 27200 +/- 2700

< 20

<10

< 200

<10 09/22 9100 +/- 910 19000 +/- 1900

< 50

< 40

< 40 57.6:+/- 26.1

< 700 129:+/- 31 10/20 582 128 15100+/- 1500

< 20

< 300

< 30 STATION 15 04/21 2860+/- 290 21500 +/- 2200

< 30

< 20

< 20 323 +/- 170

< 20 05/19 1100:+/- 210 31700 +/- 3200

< 30

< 400

< 50 06/16 956:+/- 181 19300 +/- 1900

< 40

< 20

< 400

< 40 07/21 2450:+/- 250 31600:+/- 3200

< 30

< 400

< 40 08/18 568 +/- 78 18500:+/- 1900

< 20

<10

< 200 20.7:+/- 11.3 09/22 6980 +/- 700 14200+/- 1400

< 50

< 40

< 700

< 60 10/20 4080 410 17800 1800

< 20

< 20 384 +/- 202 121 21 STATION 16 04/21 3280+/- 330 26600+/- 2700

< 30

<10

< 200 58.4 +/-10.9 05/19 1310+/- 250 30900+/- 3100

<40

<30

<600

<50 06/16 948+/- 192 23800 +/- 2400

< 40

< 30

< 30 50.5 +/- 20.4

< 500

< 40 07/21 761 +/- 176 21000+/- 2100

<20

<30

<20

<400

<30 08/18 1340+/- 160 29400 +/- 2900

< 20

< 20 416 +/- 242

< 30 09/22 5960+/- 600 21600:+/- 2200

< 50

< 30

< 500

< 50 10/20 3240 320 18600 +/- 1900

< 30

< 20

<10

< 200

< 20

All gamma emitters other than those listed were <LLD.

77

TABLE B-14: GAMMA EMITTER* CONCENTRATIONS IN FOOD/VEGETATION North Anna Power Station, Louisa County, Virginia - 1999 pCi/kg +/-2 Sigma Page 2 of 2 Collection Date Be-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATION 21 14700 +/-

28500 +/-

20600 +/-

34500 +/-

28600 +/-

10700 +/-

1500 2800 2100 3400 2900 1100 11100+/- 1100

< 30

< 40

< 20

< 60

< 30

<10

< 60

< 30

< 20

< 40

< 20

<10

< 50

< 30

< 20

< 40

< 20

<10

< 50 42.8 +/- 20.5

< 20

< 40

< 20

< 200

< 700

< 500 450 +/- 238

< 300

< 600 648 +/- 255 90.3 +/- 14.7

< 70

< 50 146 +/- 18 58.7 +/- 16.7 246 - 47 64.0 21.9 15200:+/-

36500 +/-

8270 +/-

18500 +/-

30000 +/-

17700 +/-

1500 3700 830 1900 3000 1800 14800 +/- 1500

< 40

< 30

< 50

< 40

< 20

< 50

< 40

<10

< 70

< 40

< 30

< 20

< 30

< 20

<10

< 60

< 30

< 20

< 30

< 20

<10

< 50

< 30

< 20

< 30

< 20 225 +/- 123

< 800

< 600

< 500

< 300 965 +/- 357 1090 +/-200 40.1 +/- 29.9 561 +/- 585 78 04/21 05/19 06/16 07/21 08/18 09/22 10/20 2260 +/-

1260 +/-

828 +/-

2650 +/-

2530 +/-

9910 +/-

8020 +/-

230 360 220 260 250 990 800 STATION 23 04/21 05/19 06/16 07/21 08/18 09/22 10/20 1940 +/-

1650 +/-

3360+/-

5820 +/-

1420 +/-

7190 +/-

4330 +/-

190 390 340 580 150 720 430 73.9+/- 12.7

< 80

< 50

< 30 218 +/- 37 710+/- 71 170 +/- 360 Average 2952 +/- 5273 21833 +/- 14163 2 s.d.

All gamma emitters other than those listed were <LLD.

TABLE B-15: DIRECT RADIATION MEASUREMENTS -- QUARTERLY AND ANNUAL TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1999 mR/Std. Month (30.4 days) t 2 Sigma Page 1 of 1 Station First Qtr Second Qtr Third Qtr Fourth Qtr Quarterly Annual TLD Number 01113/99 03/31/99 06/30/99 10/05/99 Average 07/01/98 03/31/99 06/30/99 10/05/99 01/06/00 06/30/99 01 8.2 + 0.1 8.1 t 0.9 7.5:+/- 1.1 6.7 +/- 1.1 7.6 +/- 1.4 8.2 +/-0.5 02 4.6 +/- 0.4 4.6 +/- 0.3' 4.3 +/- 0.1 3.9 +/- 0.3 4.4 +/- 0.7 5.0 +/-0.7 03 4.5+/- 0.3 4.7 +/- 0.4 4.2 +/- 0.2 3.6 +/- 0.2 4.3 +/- 1.0 4.9 +/-0.9 04 4.8+/- 0.2 5.1 +/- 0.4 4.3 +/- 0.1 3.7 +/- 0.5 4.5 +/- 1.2 5.0 +/-0.3 05 5.6 +/- 0.7 6.3 +/- 0.4 5.6 +/- 0.2 5.3 +/- 0.1 5.7 +/- 0.8 6.6 +/-0.7 05A 5.4+/- 0.3 5.3 +/- 0.4 5.1 +/- 0.2 4.6 +/- 0.2 5.1 +/- 0.7 5.4 +/-1.0 06 6.8:+/- 0.6 7.3 +/- 1.1 6.6 +/- 0.3 6.5 +/- 0.7 6.8 +/- 0.7 7.8 +/-1.1 07 5.6 +/- 0.2 5.7 +/- 0.5 5.0 +/- 0.2 4.7 +/- 0.4 5.3 +/- 1.0 5.8 +/-0.3 21 5.5 +/- 0.3 5.7 +/- 0.7 5.0 +/- 0.1 4.6 +/- 0.3 5.2 +/- 1.0 5.7 +/-0.7 22 6.9 +/- 0.2 7.4 +/- 0.8 6.1 +/- 0.7 6.0 +/- 0.6 6.6 +/- 1.3 7.5 +/-1.2 23 7.6 +/- 0.1 7.7 +/- 1.0 6.9 +/- 0.2 6.7 +/- 0.2 7.2 +/- 1.0 7.7 +/-0.4 24 6.1 +/- 0.2 5.6 +/- 0.2 5.2 +/- 0.1 4.6 +/- 0.2 5.4 +/- 1.3 6.2 +/-0.9 Average 6.0 +/- 2.4 6.1 +/- 2.4 5.5 t 2.2 5.1 +/- 2.3 5.7 +/- 2.4 6.3 -+/- 2.4 2 s.d.

79

TABLE B-16: DIRECT RADIATION MEASUREMENTS SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1999 mR/Std. Month (30.4 days) t 2 Sigma Page 1 of 2 Station First Qtr.

Second Qtr.

Third Qtr.

Fourth Qtr.

Average Number 01/07-04/02 03/31-06/30 06/30-10/05 10/05-01/06

+/- 2 s.d.

N-1 N-2 NNE-3 NNE-4 NE-5 NE-6 ENE-7 ENE-8 E-9 E-1 0 ESE-11 ESE-12 SE-1 3 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 6.8+/- 0.4 5.2 +/- 0.1 9.5 +/- 0.5 6.2 +/- 0.4 7.8+/- 0.1 5.6+/- 0.2 7.0 +/- 0.3 4.6 +/- 0.1 7.2 +/- 0.4 6.2 +/- 0.3 6.1 +/- 0.3 6.7 +/- 0.2 6.3 +/- 0.6 8.7+/- 0.3 7.3:+/- 0.3 5.2 +/- 0.5 8.8 +/- 0.4 4.4 +/- 0.5 8.0 +/- 0.5 4.4+/- 0.1 5.5 +/- 0.3 6.3 +/- 0.5 7.7 +/- 0.4 6.2 +/- 0.3 8.2+/- 1.1 5.3 +/- 0.5 5.1 +/- 0.3 5.4 +/- 0.3 8.4+/- 0.2 4.7 +/- 0.1 5.8 +/- 0.2 6.2 +/- 0.3 6.5 +/- 0.3 5.0 +/- 0.3 9.2 +/- 0.3 6.1 +/- 0.1 7.9 +/- 0.5 5.7 +/- 0.3 6.3 +/- 0.4 4.7+/- 0.3 8.8 +/- 0.9 5.9 +/- 0.3 7.8+/- 0.1 5.5 +/- 0.5 6.8 +/- 0.5 4.2 +/-0.3 7.1 +/-0.7 6.1 +/-0.3 6.2+/- 0.4 6.7 +/-0.2 6.0 +/-0.9 8.1 +/-1.0 6.8 +/-0.4 5.3 +/-0.7 9.4 +/-0.4 4.1 +/-0.6 7.7 +/-0.8 4.1 +/-0.5 5.5 +/- 0.4 6.2 +/- 0.5 7.3 +/- 0.6 6.4+/- 0.5 7.7 +/- 0.6 4.9 +/- 0.3 4.6 +/- 0.4 4.9 +/- 0.3 8.0+/- 1.0 4.2 +/- 0.3 5.4+/- 0.2 5.8 +/- 0.4 5.9 +/- 0.2 4.6 +/- 0.4 8.5 +/-0.4 5.7 +/-0.7 7.3+/- 0.6 5.3 +/-0.6 6.1 +/-0.4 4.8 +/-0.4 9.0 +/-0.9 5.7 +/-0.5 7.2 +/-0.5 5.3 +/-0.4 6.5 +/-0.2 4.0 +/-0.1 6.7 +/-1.1 5.8 +/-0.4 5.8 +/- 0.4 6.7 +/- 0.2 6.2 +/- 0.1 7.6 +/- 2.0 6.9 +/-0.3 4.8 +/-0.2 8.9 +/-0.4 4.1 +/-0.2 7.5+/-1.1 4.1 +/-0.1 5.5 +/-0.3 6.2 +/- 0.4 7.5 +/- 0.1 6.2 +/- 0.3 7.8 +/- 0.4 4.9 +/-0.1 5.0 +/- 0.3 4.9 +/- 0.2 8.2 +/- 0.2 4.6 +/- 0.2 5.2 +/-0.2 5.5 +/-0.4 6.2 +/- 0.3 4.7 +/- 0.2 8.5 +/- 0.4 6.0 +/- 0.2 7.2 +/- 0.4 5.4 +/- 0.3 5.8 +/- 0.4 4.3 +/- 0.6 8.1 +/-1.0 5.5 +/- 0.1 5.8 +/- 2.8 5.3 +/- 0.8 6.3 +/- 0.3 3.6 +/- 0.4 6.4 +/- 0.1 5.6 +/- 0.5 5.5 +/- 0.3 6.5 +/- 0.4 6.1 +/-0.7 8.0 +/- 0.7 6.4 +/- 0.2 5.0 +/- 0.1 8.9 +/- 0.2 3.9 +/- 0.3 8.2 +/- 0.5 3.7 +/- 0.0 4.8 +/- 0.9 6.3 +/- 0.3 6.8 +/- 0.7 6.2 +/- 0.3 8.1 +/- 1.2 4.3 +/- 0.2 4.4 +/- 0.5 4.6 +/- 0.7 7.8 +/- 0.3 4.0 +/- 0.3 5.0 +/- 0.6 5.1 +/-0.3 5.9 +/- 0.1 4.3 +/- 0.4 8.4 +/- 0.4 5.3 +/- 0.2 7.0 +/- 0.4 4.9 +/- 0.4 6.3 +/- 0.8 4.8 +/- 0.7 8.9+/-1.2 5.8 +/- 0.6 7.2+/-1.9 5.4 +/- 0.3 6.7 +/- 0.6 4.1 +/-0.8 6.9 +/- 0.7 5.9 +/- 0.6 5.9 +/- 0.6 6.7 +/- 0.2 6.2 +/- 0.3 8.1 +/-0.9 6.9 +/- 0.7 5.1 +/-0.4 9.0 +/- 0.5 4.1 +/-0.4 7.9 +/- 0.6 4.1 +/-0.6 5.3 +/- 0.7 6.3 +/- 0.1 7.3+/-0.8 6.3 +/- 0.2 8.0 +/- 0.5 4.9 +/- 0.8 4.8 +/- 0.7 5.0 +/- 0.7 8.1 +/-0.5 4.4 +/- 0.7 5.4 +/- 0.7 5.7 +/- 0.9 6.1 +/-0.6 4.7 +/- 0.6 8.7 +/- 0.7 5.8 +/- 0.7 7.4 +/- 0.8 5.3 +/- 0.7 80

TABLE B-16: DIRECT RADIATION MEASUREMENTS SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1999 mRPStd. Month (30.4 days) -t 2 Sigma Page 2 of 2 Station First Qtr Second Qtr Third Qtr Fourth Qtr Average Number 01/13-03/31 03/31-06/30 06/30-10/05 10/05-01106

+/- 2 S.d.

ENE-39 ENE-40 E-41 E-42 ESE-43 ESE-44 SE-45 SE-46 SSE-47 SSE-48 S-49 S-50 SSW-51 SSW-52 SW-53 SW-54 WSW-55 WSW-56 W-57 W-58 WNW-59 WNW-60 NW-61 NW-62 NNW-63 NNW-64 C-1 C-2 C-3 C-4 C-5 C-6 C-7 C-8 Average 6.9 +

5.0 +/-

7.1 +/-

6.3 +/-

6.8 +/-

6.9 +/-

9.2 +/-

7.1 +/-

5.5 +/-

9.3 +/-

4.5 +/-

8.4 +/-

4.6 +/-

6.0 +/-

7.1 +/-

8.4 +/-

6.8 +/-

9.1 +/-

5.5 +/-

5.3 +/-

5.6 +/-

8.6 +/-

5.0 +/-

6.1 +/-

6.4 +/-

5.6 +/-

5.7 +/-

5.4 +/-

4.7 +/-

6.6 +/-

0.3 0.1 0.2 0.4 0.3 0.3 0.3 0.0 0.3 0.1 0.6 0.1 0.4 0.4 0.3 0.3 0.3 0.1 0.1 0.2 0.4 0.2 0.4 0.1 0.1 0.2 0.3 0.3 0.1 0.3 0.3 0.2 0.3 0.4 6.5 +/- 2.7 6.5 +/- 0.8 4.7+/- 0.0 7.1 +/- 0.5 6.2 +/- 0.2 6.0 +/- 0.6 7.0+/- 0.4 6.3 +/- 0.7 8.6+/- 1.0 7.3 +/- 0.7 5.0+/- 0.6 9.4+/- 0.4 4.3 +/- 0.4 8.2+/- 0.4 4.2 +/- 0.6 6.1+

1.1 7.1 +/- 0.2 8.2+/- 1.0 6.8 +/- 0.7 9.0 +/- 0.5 5.2+ 0.5 5.5+/- 1.3 5.8 +/- 0.4 9.3+/- 1.3 5.1+0.5 5.5 +/- 0.6 6.3 +/- 0.8 5.6 +/- 0.9 5.6+/- 1.1 5.7+/- 1.0 5.7 +/- 0.6 4.6 +/- 0.6 5.1+

1.4 6.7+/- 1.1 7.1 +/- 0.9 6.3 +/- 2.8 6.9 +/- 0.4 4.1 +/-0.2 7.1 +/-0.2 6.3 +/- 0.4 5.9 +/- 0.3 6.6 +/- 0.3 6.4 +/- 0.3 8.4 +/- 0.2 6.9 +/- 0.3 5.1 +/-0.1 9.2 +/-0.4 4.1 +/-0.3 8.3 +/-0.5 4.2 +/-0.2 5.4 +/-0.4 6.3 +/-0.2 7.5 +/-0.2 6.3 +/-0.6 8.1 +/-0.4 4.9 +/-0.1 4.8 +/-0.2 4.9 +/-0.3 8.1 +/-0.4 4.3 +/-0.3 5.4 +/-0.2 5.8 +/-0.3 4.8 +/-0.2 4.9 +/-0.1 5.1 +/-0.4 4.9 +/-0.2 4.0 +/-0.3 4.0 +/-0.2 5.9 +/-0.2 6.1 +/-0.2 6.0 +/- 2.8 6.4 +/- 0.4 4.0 +/- 0.4 6.8+/-0.4 5.4 +/- 0.4 5.3 +/- 0.7 6.5+/- 1.2 5.8 +/- 0.2 8.6 +/- 0.9 6.6 +/- 0.4 4.8 +/- 0.3 8.7+/-1.3 3.8 +/- 0.1 7.7+/-1.3 3.7 +/- 0.1 4.6 +/- 0.7 6.2 +/- 0.4 6.9 +/- 0.5 6.1 +/-0.5 7.9 +/- 0.5 4.2 +/- 0.2 4.4 +/- 0.3 5.0 +/- 0.5 7.4 +/- 0.3 4.0 +/- 0.4 5.1 +/-0.2 4.9 +/- 0.7 4.4 +/- 0.2 4.5 +/- 0.7 4.1 +/-0.5 4.5 +/- 0.1 3.4 +/- 0.7 3.4 +/- 0.2 5.3 +/- 0.9 5.8+/-1.3 5.7 +/- 2.9 6.7 +/- 0.5 4.5+/-1.0 7.0 +/- 0.3 6.1 +/-0.9 5.9 +/- 0.8 6.7 +/- 0.4 6.4 +/- 0.9 8.7 +/- 0.7 7.0+/- 0.6 5.1 +/-0.6 9.2 +/- 0.6 4.2 +/- 0.6 8.2 +/- 0.6 4.2 +/- 0.7 5.5+/-1.4 6.7+/-1.0 7.8 +/-1.4 6.5 +/- 0.7 8.5+/-1.2 5.0+/-1.1 5.0+/-1.0 5.3 +/- 0.9 8.4+/-1.6 4.6 +/- 1.1 5.5 +/- 0.8 5.9+/-1.4 5.1 +/-1.2 5.2+/-1.1 5.2+/-1.5 5.1 +/- 1.1 4.2 +/-1.2 4.3+/-1.5 6.1 +/-1.3 6.4+/-1.1 6.1 +/-2.8 81

APPENDIX C LAND USE CENSUS - 1999 82

VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 1999 July (1-31)

Nearest Nearest Site Milch

Meat Milch

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

KM KM KM KM KM KM N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 2.4 1.4 1.5 3.4 2.1 2.7 2.3 1.6 1.7 1.9 5.0 2.7 2.4 1.8 1.7 1.6 1.4 1.4 1.3 1.3 1.3 1.4 1.4 1.5 1.5 1.6 1.7 1.8 1.7 1.6 1.6 1.4 3.5 2.3 2.3 4.0 5.7 NONE 2.3 4.5 2.4 3.1 NONE 2.7 7.1 6.5 NONE 3.2

Note:

No milch cow or goats within a five mile radius of North Anna Power Station KM = Kilometer 83 3.2 2.5 1.5 3.4 2.1 5.3 2.3 1.6 2.1 4.6 5.0 2.7 8.0 4.2 1.9 1.9

VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 1999 July (1-31)

Nearest Sector Resident M

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 1.5 0.9 0.9 2.1 1.3 1.7 1.4 1.0 1.1 1.2 3.1 1.7 1.5 1.1 1.0 1.0 Nearest Site Boundary M

0.9 0.9 0.8 0.8 0.8 0.9 0.9 0.9 0.9 1.0 1.1 1.1 1.1 1.0 1.0 0.9 Milch

Cow M

Meat Milch

Veg. Garden Animal Goat 500 Sq Ft.

M M

M 2.2 1.5 1.4 2.5 3.5 NONE 1.4 2.8 1.5 2.0 NONE 1.7 4.4 4.1 NONE 2.0 2.0 1.5 0.9 2.1 1.3 3.3 1.4 1.0 1.3 2.9 3.1 1.7 5.0 2.6 1.2 1.2

Note:

No milch cow or goats within a five mile radius of North Anna Power Station M = Mile 84 M

M

VIRGINIA POWER NORTH ANNA POWER STATION COMPARISON OF THE 1999 TO 1998 LAND USE CENSUS I.

No changes were observed in the nearest resident status.

II.

No changes were observed in the nearest site boundary distances.

inI.

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.

SectorSSW 4.8 kM to 4.6 kM V. No change was observed in the nearest milk cow/goat status.

VI.

The following change was observed to the nearest meat animal status as compared to the previous year.

a.

ESE Sector 7.7 kM to None 85

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 86

ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Brown Engineering 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 Total W ater......................................................................................................................

91 M ilk..................................................................................................................................

91 Soil and Sediment.....................................................................................................

91 Organic Solids.................................................................................................................

92 Air Particulates................................................................................................................

92 Analysis of Samples for Iodine-131........................................................................................

94 M ilk or W ater..................................................................................................................

94 Gam m a Spectrometry of Samples...........................................................................................

95 M ilk and W ater................................................................................................................

95 Dried Solids other than Soils and Sedim ent................................................................

95 Fish..................................................................................................................................

95 Soils and Sedim ents..........................................

......................................................... 95 Charcoal Cartridges (Air Iodine)................................................................................

95 Airborne Particulates.................................................................................................

95 Environmental Dosimetry....................................................................................................

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 results, the two sigma error and the lower limit of detection (LLD):

RESULT (pCi/m 3)

=

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

TWO SIGMA ERROR (pCi/m3 )

=

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

LLD (pCi/m 3 )

=

4.66 (B1/2)/(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 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 counting 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 gram of sample residue is mounted on the planchette. These figures are based upon a 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

ANALYSIS OF*SAMPLES FOR TRITIUM (Liquid Scintillation)

Water Ten milliliters 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 results, the two sigma error and the lower limit detection (LLD) in pCi/I:

RESULT

=

(N-B)/(2.22 V E)

TWO SIGMA ERROR LLD where:

N B

2.22

=

2((N + B)/ot)1/2/ (2.22 V E)

=

4.66 (B/ot) 1/2/(2.22 V E )

=

the gross cpm of the sample

=

the background of the detector in cpm

=

conversion factor changing dpm to pCi V

=

volume of the sample in ml E

efficiency of the detector t

=

counting time for the sample 90

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(N0 3)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 yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

Milk Stable strontium carrier is added to I liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN03 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 SrC03 from the sample after yttrium separation.

This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric 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 activity is determined by precipitating SrC03 from the sample after yttrium separation. This 91

precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

Organic Solids A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N03 ) 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 SrC0 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

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 SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 mg/cm2 aluminum absorber for low level beta counting.

Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass:

RESULT Sr-89

= (N/Dt-Bc-BA)/(2.22 V YS DFSR-89 ESR-89)

TWO SIGMA ERROR Sr-89

= 2((NIDt+Bc+BA)/It) 1/ 2/(2.22-V YS DFSR-89 ESR-89)

LLD Sr-89

= 4.66((BC+BA)Iot)l12/(2.22 V YS DFSR89 ESRS89)

RESULT Sr-90

= (N/°t - B)/(2.22 V Y1 Y2 DF IF E)

TWO SIGMA ERROR Sr-90

= 2((N/-t+B)/ot)l1 2/(2.22 V Y1 Y2 DF E IF))

92

= 4.66(B/ot) 1/2/(2.22 V Y 1 Y2 IF DF E)

WHERE:

N

=

total counts from sample (counts) o=

counting time for sample (min)

BC

=

background rate of counter (cpm) using absorber configuration 2.22

=

dpm/pCi V

=

volume or weight of sample analyzed BA

=

background addition from Sr-90 and ingrowth of Y-90 BA

=

0.016 (K) + (K) Ey/abs) (IGy_90)

YS

=

chemical yield of strontium DF SR-89

=

decay factor from the mid collection date to the counting date for SR-89 ESR-89

=

efficiency of the counter for SR-89 with the 80 mg/cm.sq.

aluminum absorber K

=

(Nt - Bc)y 9 0/(Ey.90 IFy_90 DFy_9 0 Y1 )

DFy_9 0 )

=

the decay factor for Y-90 from the "milk" time to the mid count time Ey90=

efficiency of the counter for Y-90 IFy_9 0

=

ingrowth factor for Y-90 from scavenge time to milking time IGy90

=

the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 0.016

=

the efficiency of measuring SR-90 through a No. 6 absorber EY/abs

=

the efficiency of counting Y-90 through a No. 6 absorber B

=

background rate of counter (cpm)

Y=

chemical yield of yttrium Y2=

chemical yield of strontium DF

=

decay factor of yttrium from the radiochemical milking time to the mid count time E

=

efficiency of the counter for Y-90 IF

=

ingrowth factor for Y-90 from scavenge time to the radio chemical milking time 93 LLD Sr-90

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

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

RESULT

=

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

TWO SIGMA ERROR

=

2((N/-t+B)/°t)1/2/(2.22 E V Y DF)

LLD

=

= 4.66(BI-t)1t2/(2.22 E V Y DF) where:

N

=

total counts from sample (counts) ot

=

counting time for sample (min)

B

=

background rate of counter (cpm) 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 Pdl 2 on the standard mount, mg M

=

mass of PDI2 on 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 Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

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

Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

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

Charcoal Cartridges (Air Iodine)

Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) 95

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

A mini-computer 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.

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

RESULT TWO SIGMA ERROR LLD where:

either side of the

=

(S-B)/(2.22 t E V F DF)

=

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

=

4.66(B)1/2/(2.22 t E V F DF)

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 uses a CaS04 :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 the TLDs are placed in a Teledyne Brown Engineering Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner.

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

RESULT

=

D = (Dl+D2+D3+D4 )/4 TWO SIGMA ERROR

=

2((D1-D)2+(D2-D)2+(D3-D)2+(D4-D)2)/3)l/2 WHERE:

D

=

the net mR of area 1 of the TLD, and similarly for D2, D3, and D4 D1

=

1 K/R 1 - A 1

=

the instrument reading of the field dose in area I K

=

the known exposure by the Cs-137 source R

=

the instrument reading due to the Cs-137 dose on area I 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

INTERLABORATORY COMPARISON PROGRAM The US Environmental Protection Agency (EPA) discontinued their Interlaboratory Comparison Program in December 1998.

Since the EPA is no longer involved in the program, there are no "approved" laboratories for Intercomparison Studies; however, Teledyne Brown Engineering participates in the Analytics, Inc. and Environmental Resource Associates (ERA) programs to the fullest extent possible. That is we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability.

The National Institute of Standards and Technology (NIST) is the approval authority for laboratory providers participating in Intercomparison Study Programs; however, at this time, there are no approved laboratories for environmental and/or radiochemical isotope analyses.

The EPA Interlaboratory Comparison and Analytics tables for 1997 and 1998 have been included with this report since there were investigations still in progress when the REMP report for 1998 was submitted to the NRC.

Trending graphs are provided in this section for the EPA Program and for Analytics when there were at least two data points to plot.

99

VEPCO - NORTH ANNA EPA INTERLABORATORY COMPARISON Environmental PROGRAM 1997 Collection Teledyne Brown Date Media Nuclide EPA Result(a)

Engineering Result(b)

Deviation(c) 01/17/97 01/31/97 Water Water 02/07/97 Water Sr-89 Sr-90 Gross Alpha Gross Beta 1-131 02/14/97 Water Ra-226 Ra-228 03/07/97 04/15/97 06/06/97 Water Water Water H-3 Gr-Beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 Gr-Alpha Ra-226 Ra-228 Co-60 Zn-65 Cs-134 Cs-137 Ba-133 06/13/97 Water Ra-226 Ra-228 06/18/97 Water Gr-Alpha Gr-Beta 07/11/97 Water 08/08/97 Water 09/12/97 Water 09/19/97 Water Sr-89 Sr-90 H-3 Ra-226 Ra-228 1-131 12.0 +/-

5.0 25.0 +/-

5.0 5.2 +/-

5.0 14.7 +/-

5.0 86.0 +/-

9.0 5.9 +/-

0.9 8.2 +/-

2.1 7900.0 +/-

790.0 102.1 +/-

24.0 +/-

13.0 +/-

21.0 +/-

31.0 +/-

22.0 +/-

48.0 +/-

13.0 +/-

3.1 +/-

18.0 +/-

100.0 +/-

22.0 +/-

49.0 +/-

25.0 +/-

15.3 5.0 5.0 5.0 5.0 5.0 12.0 2.0 0.8 5.0 10.0 5.0 5.0 5.0 3.0 +/-

0.5 3.1 +/-

0.8 3.1 +/-

5.0 15.1 +/-

5.0 44.0 +/-

5.0 16.0 +/-

5.0 11010 +/-

1101.0 20.0 +/-

3.0 8.0 +/-

2.0 10.0 +/-

6.0 10.00+/-

1.00 25.00 +/-

1.00 8.10 +/-

0.89 15.00 +/-

1.00 106.00 +/-

4.36 5.27 +/-

0.23 8.40 +/-

0.30 7366.67 +/- 378.59 103.33 +/-

23.00 +/-

12.67 +/-

22.67 +/-

28.67 +/-

24.67 +/-

54.67 +/-

13.00 +/-

4.87 +/-

19.00 +/-

99.33 +/-

18.67 +/-

48.67 +/-

22.33 +/-

5.77 1.00 1.15 0.58 0.58 1.53 1.53 1.00 0.12 0.00 1.15 1.15 0.58 2.52 3.43 +/-

0.49 3.43 +/-

0.23 2.93 +/-

0.25 14.00 +/-

1.00 38.33 +/-

1.53 25.00 +/-

0.00 12000.00 +/-

0.00 20.00 +/-

1.73 7.40 +/-

0.17 11.00 +/-

0.00 99a

-0.69 0.00 1.00 0.10 3.85 (d)

-1.22 0.16

-1.17 0.14

-0.35

-0.12 0.58

-0.81 0.92 0.96 0.00 3.82 0.35

-0.12

-1.15

-0.12

-0.92 1.50 0.72

-0.06 0.38

-1.96 3.12 1.56 0.00

-0.52 0.29 (e)

(f)

VEPCO - NORTH ANNA EPA INTERLABORATORY COMPARISON PROGRAM 1997 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result(a)

Engineering Result(b)

Deviation(c) 10/21/97 Water Gr-Beta 143.4 +/-

21.5 136.67 +/-

5.77

-0.54 Sr-89 36.0 +/-

5.0 36.00 +/-

1.00 0.00 Sr-90 22.0 +/-

5.0 21.67 +/-

2.08

-0.12 Co-60 10.0 +/-

5.0 10.67 +/-

0.58 0.23 Cs-134 41.0 +/-

5.0 41.33 +/-

0.58 0.12 Cs-137 34.0 +/-

5.0 36.00 +/-

1.00 0.69 Gr-Alpha 49.9 +/-

12.5 45.67 +/-

1.15

-0.59 Ra-226 5.0 +/-

0.8 5.90 +/-

0.10 1.95 Ra-228 5.0 +/-

1.3 4.27 +/-

0.12

-0.98 10/31/97 Water Gr-Alpha 14.7 +/-

5.0 19.67 +/-

1.53 1.72 Gr-Beta 48.9 +/-

5.0 50.67 +/-

3.51 0.61 11/07/97 Water Co-60 27.0 +/-

5.0 25.00 +/-

1.00

-0.69 Zn-65 75.0 +/-

8.0 71.00 +/-

3.61

-0.87 Cs-134 10.0 +/-

5.0 10.67 +/-

0.58 0.23 Cs-137 74.0 +/-

5.0 76.00 +/-

1.00 0.69 Ba-133 99.0 +/-

10.0 78.67 +/-

0.58

-3.52 (g)

Footnotes:

(a)

EPA Results-Expected laboratory precision (1 sigma). Units are pCi/liter for water and milk except K is in mg/liter. Units are total pCi for air particulate filters.

(b)

Teledyne Results - Average +/- one sigma. Units are pCi/liter for water and milk except K is in mg/liter. Units are total pCi for air particulate filters.

(c)

Normalized deviation from the known.

(d)

Erroneously high reading of the stable iodine content by ion specific electrode occurred, causing an erroneously low chemical yield. If the electrode reading is ignored, the average I 131 result becomes 90 pCi/l, in good agreement with the given value. An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulfide. We will investigate suspiciously high electrode readings by performing a gravimetric yield on the sample without the addition of iodide carrier or the 1-131 content of active samples can also be verified by performing a gamma spectral analysis.

(e)

An investigation discovered a low chemical yield on one sample and the loss of another during analysis. In the future we will repeat analyses of samples with yields less than 85%.

(f)

Error apparently caused by insufficient training. The strontium separation chemistry was performed on 7/22/97 by a summer employee. Initial results for the three samples did not agree well, so all were remilked by a senior analyst. This was insufficient to correct the problem. In-house QC samples showed satisfactory results at this time. Additional in-house analyses performed after retraining have been acceptable.

(g)

No apparent cause for the discrepancy could be identified.

Equipment calibrations and efficiencies for this analysis were within expected normal ranges.

99b

VEPCO NORTH ANNA EPA INTERLABORATORY COMPARISON PROGRAM 1998 Environmental VCollection Date Media Nuclide EPA Result(a)

Teledyne Brown Engineering Result(b)

Normal Dev.

Known(c) 01/16/98 Water 01/30/98 Water 02/06/98 Water 02/13/98 Water 03/13/98 Water 04/21/98 Water 06/05/98 Water 06/12/98 Water 07/17/98 Water 07/24/98 Water Sr-89 Sr-90 Gr-Alpha Gr-Beta 1-131 Ra-226 Ra-228 H-3 Gr-Alpha Ra-226 Ra-228 Gr-Beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 Co-60 Zn-65 Cs-134 Cs-137 Ba-133 Ra-226 Ra-228 Sr-89 Sr-90 Gr-Alpha Gr-Beta 08/07/98 Water H-3 09/11/98 Water 1-131 09/18/98 Water Ra-226 Ra-228 10/20/98 Water Gr-Beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 8.0 +/-

5.0 32.0 +/-

5.0 30.5 +/-

7.6 3.9 +/-

5.0 104.9 +/-

10.5 16.0 +/-

2.4 33.3 +/-

8.3 2155.0 +/-

348.0 54.4 +/-

15.0 +/-

9.3 +/-

94.7 +/-

6.0 +/-

18.0 +/-

50.0 +/-

22.0 +/-

10.0 +/-

12.0 +/-

104.0 +/-

31.0 +/-

35.0 +/-

40.0 +/-

13.6 2.3 2.3 10.0 5.0 5.0 5.0 5.0 5.0 5.0 10.0 5.0 5.0 5.0 4.9+/-

0.7 2.1+/-

0.5 21.0+/-

5.0 7.0+/-

5.0 7.2+/-

5.0 12.8 +/-

5.0 17996.0 +/- 1800.0 6.1+/-

2.0 1.7+/-

0.3 5.7+/-

1.4 94.0 +/-

19.0 +/-

8.0 +/-

21.0 +/-

6.0 +/-

50.0 +/-

10.0 5.0 5.0 5.0 5.0 5.0 5.00 +/-

1.73 31.67 +/-

0.58 33.00 +/-

2.65 5.60 +/-

0.90 110.00 +/-

0.00 14.67 +/-

0.58 32.00 +/-

2.00 1833.33 +/-

57.74 50.00 +/-

15.00 +/-

8.50 +/-

102.00 +/-

4.67 +/-

21.67 +/-

52.33 +/-

21.00 +/-

11.67 +/-

13.00 +/-

111.67 +/-

32.33 +/-

37.67 +/-

35.00 +/-

1.73 0.00 0.20 6.56 1.15 1.15 1.53 1.00 0.58 1.00 2.52 0.58 2.08 2.65 4.47 +/-

0.85 1.93 +/-

0.21 21.00 +/-

1.00 6.33 +/-

0.58 5.43 +/-

0.64 14.67 +/-

2.08 16000.00 +/-

0.00 5.93 +/-

0.55 1.53 +/-

0.46 6.70 +/-

0.35 74.67 +/-

18.33 +/-

8.33 +/-

22.33 +/-

6.67 +/-

56.33 +/-

7.64 1.53 1.15 1.15 0.58 3.79 100

-1.04

-0.12 0.57 0.59 0.84

-0.96

-0.27

-1.60

-0.56 0.00

-0.60 1.26

-0.46 1.27 0.81

-0.35

.0.58 0.35 1.33 0.46 0.92

-1.73

-1.07

-0.58 0.00

-0.23

-0.61 0.65

-1.92

-0.14

-0.96 1.24

-3.35

-0.23 0.12 0.46 0.23 2.19 (d)

(e)

St

VEPCO NORTH ANNA EPA INTERLABORATORY COMPARISON PROGRAM 1998 Environmental

-ollection Teledyne Brown Normal Dev.

Date Media Nuclide EPA Result(a)

Engineering Result(b)

Known(c) 10/20/98 Water Gr-Alpha 30.1 +/-

7.5 21.67 +/-

2.31

-1.95 Ra-226 4.5 +/-

0.7 4.67 +/-

0.25 0.41 Ra-228 1.5 +/-

0.4 1.9 +/-

0.20 1.73 11/06/98 Water Co-60 38.0 +/-

5.0 39.67 +/-

2.52 0.58 Zn-65 131.0 +/-

13.0 140.67 +/-

10.97 1.29 Cs-134 105.0 +/-

5.0 103.00 +/-

2.00

-0.69 Cs-137 111.0 +/-

6.0 115.33 +/-

1.53 1.25 Ba-133 56.0 +/-

6.0 46.33 +/-

2.52

-2.79 (f)

Footnotes:

(a)

EPA Results-Expected laboratory precision (1 sigma). Units are pCi/liter for water and milk except K is in mg/liter. Units are total pCi for air particulate filters.

(b)

Teledyne Results - Average +/- one sigma. Units are pCi/ liter for water and milk except K is in mg/liter. Units are total pCi for air particulate filters.

(c)

Normalized deviation from the known.

(d)

The special EPA instructions concerning multiple evaporation with concentrated nitric acid (to purge chlorides derived from HC1 preservative) were omitted by oversight. The chlorides cause greater self absorption and lead to lower results.

Two additional aliquots using two evaporations with concentrated nitric acid were analyzed. The results, when corrected for decay of Gr-Beta, were 87 and 83 pCi/liter which compare favorably with the EPA result.

(e)

Weekly efficiency checks for the sample collect date (10/20/98) counted in December 1998, indicate that detectors were in compliance during that period of time. All detectors are calibrated using NIST traceable mixed gamma standards containing Cs137.

The Branching Intensity value used in the calculation by the EPA is not available for cross-reference checks.

(f)

The results of the EPA Interlaboratory Comparison Program, sample collect date 11/06/98, indicate a low bias for the Ba-133 result.

Weekly efficiency counts for our detectors were found to be in compliance during that period of time. One possible cause for the low bias may be the Branching Intensity value used in the calculation.

The EPA does not supply their values used to calculate activity.

If the Brookhaven or RadDecay Data Tables are used to supply the B.I. and Half-Life, the calculated results will fall within the acceptable range:

TBEES (Atomic Data and Nuclear Data Tables Vol 13 Nos 2-3 1974)

Branching Intensity Half-Life Calculated Activity TBEES 0.670 10.9 years 46.33 Brookhaven Tables 0.6205 10.52 years 50.04 RadDecay Tables 0.605 10.5 years 51.31 101

VEPCO - NORTH ANNA ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a)

Result Ratio (b)

E0975-396 TI#41238 03/20/97 Milk 1-131 Ce-141 Cr-5 1 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 CO-60 18 +/-

L.T. 1.

381 +/-

132 +/-

128 +/-

89 +/-

195 +/-

161 +/-

171 +/-

179 +/-

1 38 13 13 9

20 16 17 18 20 +/-

232 +/-

387 +

143 +/-

114 +/-6 79 +/-4 176 +/-9 144 +/-7 165 +/-8 176 +/-9 1

12 19 7

1.12 1.13 1.11 1.12 1.04 1.02 0.90 0.98 0.92 E0976-396 TI #41239 03/20/97 Milk Sr-89 Sr-90 13+/-

3 16+/-

1 (c) 25 +/-1 0.52 19 +/-1 0.84 E1092-396 TI #49899-901 06/19/97 Air Filter Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 EI093-396 TI #49902-04 06/19/97 Cartridge E1094-396 Air Filter TI #49893-95 06/19/97 E1095-396 Air Filter TI #49896-98 06/19/97 1-131 Sr-90 Gross Alpha Gross Beta 106 +/-

6 88 +/-

5 103 +/-

6 210 +/-

6 E1204-396 TI#57520 09/18/97 143 +/-

229 +/-

74 +/-

143 +/-

89 +/-

102 +/-

98 +/-

188 +/-

113 +/-

8 17 4

8 5

6 6

11 7

132 +/-7 198 +/-10 81 +/-4 115 +/-6 77 +/-4 84 +/-4 75 +/-4 139 +/-7 104 +/-5 1.08 1.16 0.91 1.24 1.16 1.21 1.31 1.35 1.09 88 +/-

4 96+/-

5 1.20 0.92 Milk

.93 +/-

5 193 +/-

10 1.11 1.09 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 97 +/-

83 +/-

323 +/-

98 +/-

117 +/-

64 +/-

99 +/-

132 +/-

218 +/-

209 +/-

10 8

40 10 12 6

10 13 22 21 87 +/-

77 +/-

304 +/-

102 +/-

107 +/-

60 +/-

88 +/-

119 +/-

196 +/-

197 +/-

4 4 15 5

5 3

4 6

10 10 1.11 1.08 1.06 0.96 1.09 1.07 1.13 1.11 1.11 1.06 101a

ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a)

Result Ratio (b)

E1203-396 TI#57517 09/18/97 Milk Sr-89 Sr-90 14+/-

1 18+/-

1 15+/-

1 14 +/-

1 0.93 1.29 Footnotes:

(a)

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

(b)

Ratio of Teledyne Brown Engineering to Analytics results.

(c)

Caused by incorrect rinsing of the strontium extraction column.

Additional training was conducted on 9/5/97 and was documented in the analyst's training file. Subsequent tests on two milk samples spiked with Sr-89 produced good results.

Ce-141 was identified by gamma spectrometry system (232 +/- 23 pCi/l) for the 3/20/97 milk sample, but was not reported to Analytics.

101b

ANALYTICS CROSS CHECK COMPARISON PROGRAM 1998 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a)

Result Ratio (b)

E1346-396 TI #71657 03/12/98 E1460-396 TI#78921 06/11/98 E1630-396 TI #94881 12/14/98 Milk Milk Milk E1631-396 Filter TI#94882 12/14/98 E1632-396 TI#94883 12/14/98 E1633-396 TI#94884 12/14/98 Water Water 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 CO-60 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 CO-60 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 CO-60 Sr-89 Sr-90 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 CO-60 H-3 Am-241 Pu-239 87 +/-

66 +/-

220 +/-

85 +/-

180 +/-

130+/-

110 +/-

160 +/-

82 +/-

68 +/-

94 +/-

97+/-

101 +/-

79+/-

112+/-

58+/-

143 +/-

157 +/-

65 +/-

647 +/-

900 +/-

200 +/-

177 +/-

136 +/-

156 +/-

132 +/-

169 +/-

20 +/-

16+/-

566 +/-

800 +/-

147 +/-

158 +/-

122 +/-

134 +/-

129 +/-

134 +/-

9 7

30 9

20 10 10 20 8

7 9

31 10 8

11 9

14 16 1

65 90 20 18 14 16 14 17 2

1 57 80 15 16 12 13 13 13 5500 +/-

200 8.3+/-

1.5 9.8+/-

1.8 82 +/-

70 +/-

201 +/-

84 +/-

161 +/-

133 +/-

95 +/-

142 +/-

85 +/-

67 +/-

99++/-

132 +/-

95 +/-

70 +/-

106 +/-

45 +/-

122 +/-

143 +/-

71 +/-

746 +/-

979 +/-

220 +/-

183 +/-

142 +/-

148 +/-

140 +/-

178 +/-

69 +/-

41 +/-

524 +/-

687 +/-

154 +/-

128 +/-

100 +/-

104 +/-

98 +/-

125 +/-

4 4

10 4

8 7

5 7

4 3

5 7

5 4

5 2

6 7

4 37 49 11 9

7 7

7 9

3 2

26 49 8

6 5

5 5

6 5980 +/- 299 7.9 +/-

0.4 8.9 +/-

0.4 102 1.06 0.94 1.09 1.01 1.12 0.98 1.16 1.13 0.96 1.01 0.95 0.73 1.06 1.13 1.06 1.29 1.17 1.10 0.92 0.87 0.92 0.91 0.97 0.96 1.05 0.94 0.95 0.29 0.39 1.08 1.16 0.95 1.23 1.22 1.29 1.32 1.07 0.92 1.05 1.10 (c)

(c)

Footnotes:

(a)

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

(b)

Ratio of Teledyne Brown Engineering to Analytics results. Acceptance criteria are based on USNRC acceptance criteria described in USNRC Procedure 84750 dated March 15, 1994.

(c)

The original and repeat analysis data sheets for Sr-89 and Sr-90 have been reconstructed from information in the laboratory notebook and the counter printouts. This sample was originally analyzed in January 1999 (login IA004) and produced unacceptable radlostrontium results. The analysis was repeated in April 1999 using a smaller aliquot of 500 ml because 1000 ml was no longer available. The repeat analysis produced good results:

Result Analytics value ratio Sr-89 74+-8 69+-3 1.07 Sr-90 37+- 1 41+- 2 0.90 A problem such as sample identity is suspected for the first analysis.

103

VEPCO - NORTH ANNA ANALYTICS CROSS CHECK COMPARISON PROGRAM 1999 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a)

Result(b)

Ratio (c)

E1823-396 Water TI#09576 06/24/99 E1824-396 Water TI#09577 06/24/99 E1825-396 Water TI#09578 06/24/99 E1826-396 Filter TI#09579 06/24/99 E1827-396 Soil TI#09580 06/24/99 Footnotes:

Sr-89 Sr-90 Gr-A Gr-B 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 Co-60 60 +/-

5 35 +/-

2 160 +/-

10 300 +/-

10 77 +/-

139 +/-

162 +/-

86 +/-

167 +/-

77+/-

40 +/-

113 +/-

179 +/-

169 +/-

241 +/-

105 +/-

211 +/-

96 +/-

55 +/-

144 +/-

214 +/-

0.274 +/-

0.374 +/-

0.200 +/-

0.450 +/-

0.153 +/-

0.118.+/-

0.206 +/-

0.351 +/-

13 14 42 9

17 8

9 12 18 17 24 10 21 10 8

14 21 0.027 0.103 0.020 0.045 0.015 0.022 0.021 0.035 (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. Units are pCi/gram for Soil, which has been added to the program for 1999.

(b)

Analytics Result - Average +/- 3 sigma 104 69 +/-

3 46 +/-

2 98 +/-

5 290+/- 15 0.87 0.76 1.63 (d) 1.03 1.13 1.04 0.94 0.93 1.11 1.13 1.05 1.15 1.05 1.04 1.16 0.95 1.16 1.17 1.20 1.22 1.04 1.02 1.08 1.09 1.05 1.13 1.53 (e) 1.05 1.02 68 +/-

134 +/-

172 +/-

92 +/-

151 +/-

68 +/-

38 +/-

98 +/-

171 +/-

162 +/-

208 +/-

111 +/-

182 +/-

82 +/-

46 +/-

118 +/-

206 +/-

0.269 +/-

0.345 +/-

0.184 +/-

0.429 +/-

0.136 +/-

0.077 +/-

0.196 +/-

0.343 +/-

3 7 9

5 8

3 2

5 9

8 10 6

9 4

2 6

10 0.013 0.017 0.009 0.021 0.007 0.004 0.010 0.017

(c)

Ratio of Teledyne Brown Engineering to Analytics results. Acceptance criteria are based on USNRC acceptance criteria described in USNRC Procedure 84750 dated March 15, 1994.

(d)

A high Gross Alpha result was obtained because the calculation was mistakenly performed using Th-230 counting efficiency. If our normal Am-241 calibration were used, we would have reported 110 +- 10 pCi/L, which is an acceptable value.

(e)

Random or coincidental summing caused the problem. Two other energy lines can sum a peak on the same energy band causing more counts to be thrown in.

The key line was changed and the resulting value was 0.079, which is in agreement with Analytics.

105

VEPCO - NORTH ANNA ERA STATISTICAL

SUMMARY

PROFICIENCY TESTING (PT) PROGRAM - 1999 SAMPLE TYPE: WATER ERA Expected Known TBE Dev.

Control Value Result (b)

Known (c)

Limits (d)

Warning Limits (e)

I--/'*-*

/1\\

Performance TI #s DATE NUCLIDE (pCi/l)(a)

(pCi/I)

(pUI/I)

(ptI-/I) kI(pLI)

Evaluatuon it) 11811-11813 8/23/99 U(NAT) 12.4 13.0 3.00 7.20-17.6 8.94-15.9 A

11811-11813 8/20/99 Ra-226 7.21 7.37 1.08 5.34-9.08 5.96-8.46 A

11811-11813 8/23/99 Ra-228 4.51 7.17 1.13 2.57-6.45 3.21-5.81 NA (g) 11808-11810 8/24/99 Sr-89 26.6 25.0 5.00 17.9-35.3 20.8-32.4 A

11808-11810 8/24/99 Sr-90 40.2 39.7 5.00 31.5-48.9 34.4-46.0 A

13058-13060 9/15/99 Gr-A 48.6 30.3 12.2 27.7-69.5 34.6-62.6 CE (h) 13061-13063 9/14/99 Gr-B 20.0 22.0 5.00 11.3-28.7 14.2-25.8 A

14425-14427 9/01/99 H-3 6130 5530 613 5090-7170 5420-6840 A

Footnotes:

(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 Limits.

(g)

A calculation error was made by not correcting for Ra-226 content. If this correction is made, an average result of 5.7 pCi/l is obtained which is in the acceptance region.

(h)

The low value is attributed to greater self-absorption characteristics of the sample matrix compared to those of the calibration matrix. This source of bias is often observed in gross alpha measurements, nevertheless, the average result is within the control region (but also in the warning region).

(

Interlaboratory Comparison Program 1997-1998 -1999 ADDENDUM

1.

Analysis of milk samples for Potassium (K) in the Interlaboratory Comparison Program (ICP) (1997-1999).

The Offsite Dose Calculation Manual lists the analyses to be performed for the Interlaboratory Comparison Program. The requirement for Milk - "K" cannot be met.

The EPA deleted the analysis of Milk samples from the Cross-Check program in 1996. Teledyne Brown Engineering Environmental Services (TBEES) contracted with Analytics, Inc., to provide milk samples spiked with Sr-89/90, I 131, and other gamma emitters.

Although the results reported to Analytics included K-40, this radionuclide was not evaluated by Analytics.

Subsequent analyses of Analytics milk samples were not evaluated for K-40 also. Analytics has indicated that the accuracy of the potassium measurement cannot be determined with a sufficiently high degree of integrity to permit its' use as a proficiency test radionuclide.

2.

Analysis of milk samples for Strontium (Sr) 89 and 90 (1998).

The VEPCO contract requires TBE to perform interlaboratory crosschecks of these analyses.

TBE presumed, erroneously, that we were meeting the requirements of the contract.

3.

Analysis of air filter samples for Strontium 90, Gross Beta (1998 - 1999).

The VEPCO contract requires TBEES to perform interlaboratory crosschecks of these analyses.

TBEES erroneously presumed they were meeting the requirements of the contract

4.

Analysis for Milk 131, Gamma, Strontium 89 and 90 (1999).

The VEPCO contract requires TBE to perform interlaboratory crosschecks of these analyses.

TBEES erroneously presumed they were meeting the requirements of the contract

5.

Methodology and results of the LCP - Analytics (vendor) not in TBEES QC Manual.

This requires documentation revision. This issue will be addressed in the year 2000 with the entire implementation of the National Environmental Laboratory Accreditation Program (NELAP). Revisions of controlled documentation will be distributed to the appropriate control officers at the power plant stations as outlined in the contract.

6.

Trend Data of Cross-Check Program (ICP) (1997-1999)

Graphs of data have been updated in the report. Data in which there is only one data point have not been graphed, since there are no trends apparent to the upper and lower control limits. Therefore, one-point data information has no real value.

107

7.

Corrective Actions to prevent non-compliance of the Interlaboratory Comparison Program (1999).

The remaining requirements for Water and Air Filters were supported by TBEES' Vendor Interlaboratory Comparison Program. Analyses of Air Filters for Sr-90 and Gross Beta analyses were not performed in the 1999 Analytics studies.

TBEES ordered ICP studies based on workload for the entire laboratory operations and did not take into account the specific contract requirements for VEPCO. Corrective actions include the following:

"* The VEPCO contract with TBEES was revised to include the specific media and analysis requirements for the ICP.

"* TBEES' 2000 Performance Testing (PT) Programs will meet the VEPCO contract requirements. Vendor (Analytics and Environmental Resource Associates) contracts have been revised and implemented for the year 2000.

"* The potassium analysis requirement for milk was eliminated from the ICP since it is a primordial element and not associated with nuclear power plant effluents.

"* An ICP checklist has been included in the North Anna Power Station procedure for generating the Radiological Environmental Operating Report (REOR). This checklist ensures all ICP elements are assessed prior to submitting the REOR to the NRC.

"* The requirement to maintain the methodology and results of the ICP in a QC manual has been eliminated as it is not a requirement of Branch Technical Position, November

1979, Revision 1, An Acceptable Radiological Environmental Monitoring Program.

"* VEPCO will perform an audit of TBEES in the year 2000.

108

APPENDIX E INTERLABORATORY COMPARISON PROGRAM 109

EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICULATES (pg. 1 of 1)

U1 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996

[13 TI+/-3 Sigma 0

EPA+/-3SIgma The US EPA discontinued air particulate filter samples in 1996.

I-

z.

I-(

(

tii tt It4i U I!4 0o 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 I0 TI+/-3Sigma o

EPA++/-3Sigma The US EPA discontinued air particulate filter samples in 1996.

EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg. 1 of 1) 1 R(

I An 140-I--.

Z.

0 I.-

tiI 120 100 80 60 40 20-4 It 14 0

l

Ii 80 70 60 50 40 30 20 10 0 I 1 8I 19I 1982 1983 1984 I

I I

I 1985 1986 1987 1988 1989 199 1

1 1

1989 1990 1991 1992 1993 1994 a

Tl+3Sigma, o

EPA+/-3Sigma The US EPA discontinued air particulate filter samples in 1996.

ii I-,

0.

I-I'

-eA 1981 1

1995 1996 I

I EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES (pg. 1 of 1)

_O1'3

(

EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg. 1 of 1) 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1o TI+3 Sigma o

EPA +/-S3Sigma The US EPA discontinued air particulate filter samples in 1996.

(

c3 I.-

(

EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK (pg. 1 of 1) 100 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996

ý o Tl+/-_3Sigma 0

EPA+/-3 Sigma The US EPA discontinued milk samples in 1996.

(

I-.

I 0

(

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg. 1 of 1) 80 60 40 20" 0

1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992. 1993 1994 1995 1996 F

T, T+/-+3Sigma o

EPA+/-3 Sigma The US EPA discontinued milk samples In 1996.

0, I.

0.

(

EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg. 1 of 1) 2600 2400 2200 2000 1800 T

1600 1400 1200 1000 800 600 1981 1982 1983 1984 1985 1986 198.7 1988 1989 1990 1991 1992 1993 1994 1995 1996 r

Tl+/-3Sigma o

EPA+/-3Sigma The US EPA discontinued milk samples in 1996.

(

EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg. I of 1) 160 140 120' 100 80 o

440 I20 0

0

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996

[

Tl+/-3 Sigma 0

EPA+/-3 Sigma The US EPA discontinued milk samples in 1996.

C EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK (pg. 1 of 1) 20 O lI I

.I 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 I a TI+/-3Sigma o

EPA+/-3 Sigma The US EPA discontinued milk samples in 1996.

100.

80' 60 00.

4-,

Z 5-40

K EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER (pg. 1 of 1) 3 U, CL 1986 1989 1992 1995 2r Tl+/-+3Sigma o

EPA+/-3Sigma

(

180 160 140 120 100 80 60 40 20 0

-20 L 1983 1998

EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 60 20 a3

-201 1986 1988 1990 1992 1994 1996 50r T++/-3 Sigma o

EPA+/-3 Sigma

(

K, 260 220 180 140 I

o a.

100 1998 2000

(

EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 1 of 2) 220 200 180 160 140 120 100 80 60 40 20 0

-20 1981 I

p 03 Tl:+/-S3sigma 0

EPA+/-3sigma C

CL I--.

1 1

1982 1983 1984 1985 1986

(

EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 1988 1990 I

I

I 1994 1992 r,

TI+/-3Sigma o

EPA+/-3Sigma

(

30000 20000 1-I--'

0*

4 C.

10000 F

'JI 1984 M

13 0v 4

1986 Ila 1996 2000 1998

(

EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 1 of 2) 1982 1983 1984 1985 1 13 TI+3sigma o

EPA++/-3 sigma i

(

5000 4000 3000

0) 4-t C--,

2000 1000 0

-1000 1981

C C

EPA CROSS CHECK PROGRAM IODINE IN WATER (pg. 1 of 1) 200 180 160 140 120 100 80 60 40 20 0

-201 1980 1

1982 1984 I o TI+/-3Sigma o

EPA+/-3Sigma I

I I

4 1*

13 m I Ii II 1986 1988 1990 1992 1994 1996 1998 2000 tE

(

EPA CROSS CHECK. PROGRAM COBALT-60 IN WATER.(pg. 2 of 2) 120 100 80 60 T

L3 40

-20 1988 1990 1992 1994 1996 1998 2000 1-0 T++/-3Sigma o

EPA +/-:3Sigma

(

EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg 1 of 2) 1982 1983 1984 1985 1986 1987 1988

+/-

Tl+3sigma o

EPA+/-3 sigma

(

100 80 60 Z_

6 0.

I.-

40 20° 0

-20 1981

(

EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 2 of 2) 2000 1990 1992 1994 1996 1998 m TI++/-3 Sigma 0

EPA+/-3Sigma

(

140 120 100 80 I-DO I

C.)

60 40 201 0

-20 1988

t,

(

EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 1 of 2) 1982 1983 1984.

1985 1986 1987 1988 1 1 TI+/-3sigma 0

EPA+/-3sigma I 100 80 60 1..

0 0

40 OD 20 0

-201 1981

(

EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 2 of 2) 2000 1990 1992 1994 1996 1998 I m T+/-_3 Sigma o

EPA+/-3Sigma I

(

140 120 100 80 a,,

Z-4 CL.

60 40 20 0

-20 1988

(

EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 1 of 2)

I I

p I

1985 1986 1984 TI T+/-

+/-3 sigma o

EPA +/-3 sigma

(

80 60

(

40 I-, a) 0 Z.

CL

.,0 20 0

-',

I 1981 1982 1983

)87 I

1986 1985

(

EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2 of 2) 100 80 I-60 40 20 0

-20 1 198

it 7

I I

1986 i

1988 1990 1992 1994 1996 1998 2000 tw TIT +/- 3 Sigma 0

EPA +/- 3 Sigma I iI--,t (A)

I-'

U 34

(

EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 1 of 2) 1982 1983 1984 STI +/- 3 sigma 0

EPA +/-3 sigma

(

100 80 60

(

(-.3 C-.-

a 02.

40 20 0

-20 L 1981 1985

(

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER (pg. 1 of 1) 80 60 40 20 I-0 I II I1E

+/-q

I P1' T

I I

a 1984 1986 1988 1990 T++/-3Sigma 0

EPA+/-3 Sigma C,-,

C.A) 0 4

U 0.

A L

1980 1982 1992 1994 1996 1998 2000

(

E T

r

/

(

/

09/18/97 03/12/98 1

06/11/98 1

12/14/98

[

Teledyne Result Analytics Result ANALYTICS INTERLABORATORY COMPARISON PROGRAM IODINE-131 IN MILK' 240 200 160 4:-

120 I

C.)

'.4

'.4 U

5 0U a

80 40 0

0 03/20/97

(

1000 800 600 03/20/97 09/18/97 03/12/98 06/11/98 12/14/98 (a) Teledyne result was Less Than 1 pCiliter I

Teledyne Result Analytics Result ANALYTICS INTERLABORA, ORY COMPARISON PROGRAM CERIUM-141 IN MILK (a)

I II

(

1

G) 4 I-.

C..,

0

C.)

a.

400 200 0

(

ANALYTICS INTERLABORATORY COMPARISON PROGRAM CHROMIUM-51 IN MILK 1200 1000 800 600 09/18/97 03/12/98 06/11/98 12/14/98

[

Teledyne Resulti Analytics Result K

C S

U I

I 0

U I

I I

I.

(A) 0

C, a.

400 200 0

03/20/97

K K

ANALYTICS INTERLABORATORY COMPARISON PROGRAM CESIUM-134 IN MILK 240 l0 200 160 S120 Z

CL 80.

40 C.,I U

0.

03/20/97 09/18/97 03/12/98 06/11/98 12/14/98

[

Teledyne Result Analytics Result

(

240 200 160

-t 03/12/98 Teledyne Result Analytics Result ANALYTICS INTERLABORA iORRY COMPARISON PROGRAM CESIUM-137 IN MILK U

S wU p[

(

120 0

CL I

oD C.

80 40 0

03/20/97 1

09/18/97 06/11/98 12/14/98

(

03/20/97 09/18/97 03/12/98 06/11/98 12/14/98 Teledyne Result Analytics Result ANALYTICS INTERLABORA ifORY COMPARISON PROGRAM MANGANESE-54 IN MILK 240 200 160 3

U) 4 CA)

(0

(*)

a.

120 80 40 0

C 240 200 160 03/12/98 Teledyne Result Analytics Result ANALYTICS INTERLABORA, ORY COMPARISON PROGRAM IRON-59 IN MILK U

0 U

U 0

I

.5 p

(

120

4)

CD o

C a,.

80 40 0

03/20/97 09/18/97 06/1 1/98 12/14/98

C 240 200 160 09/18/97 03/i12/98 06/11/98 12/14/98 Teledyne Result Analytics Result ANALYTICS INTERLABORATORY COMPARISON PROGRAM ZINC-65 IN MILK U

0 U

S U

0 U

C 120 1

0 4

C.,

0.

i..

4ý:

80 40 0 *1 03/20/97 I

i

ANALYTICS INTERLABORA i'ORY COMPARISON PROGRAM C

COBALT-60 IN MILK.

240 200 160 0

120 0

80 40 l0!'

03/20/97 09/18/97 03/12/98 06/11/98 12/14/98 Teledyne Result Analytics Result

/

(

12/14/98 6/24/99 N

Teledyne Result Analytics Result ANALYTICS INTERLABORATORY COMPARISON PROGRAM CERIUM-141 IN AIR FILTERS

(

.o 0

I,--

(

ANALYTICS INTERLABORATORY COMPARISON PROGRAM CHROMIUM-51 IN AIR FILTERS 1000 800 9

600 "0

400 200 0

12/14/98 6/24/99 Teledyne Result 0

Analytics Result

(

ANALYTICS INTERLABORATORY COMPARISON PROGRAM CESIUM-134 IN AIR FILTERS 240 200 160 120 Sa 80 40 0

12/14/98 6/24/99 N

Teledyne Result Analytics Result

(

240 200 160 120 80 40 0

12/14/98 6/24/99 0

Teledyne Result Analytics Result ANALYTICS INTERLABORATORY COMPARISON PROGRAM CESIUM-137 IN AIR FILTERS

'-3 C.,

(

ANALYTICS INTERLABORATORY COMPARISON PROGRAM MANGANESE-54 IN AIR FILTERS 240 200 160 120 80 40 0

12/14/98 6/24/99 E

Teledyne Result Analytics Result

(

R1

(

ANALYTICS INTERLABORATORY COMPARISON PROGRAM IRON-59 IN AIR FILTERS tu 20 0

80 40-12/14/98 6/24/99 0

Teledyne Result 0

.Analytics Result

(

240 "pi(

If )

I

(

1

,o oo.

ANALYTICS INTERLABORATORY COMPARISON PROGRAM ZINC-65 IN AIR FILTERS 240 200

160, S120 80 40 0

12/14/98 6/24/99

.0 Teledyne Result Analytics Result

(

Z-

/

ANALYTICS INTERLABORATORY COMPARISON PROGRAM COBALT-60 IN AIR FILTERS 240 200O 160 120 U,T 0

80 40 0

12/14/98 6/24/99 0

Teledyne Result Analytics Result

Person / Time
ML003710637
Site:	North Anna (NPF-004, NPF-007, SNM-2507)
Issue date:	04/28/2000
From:	Matthews W Virginia Electric & Power Co (VEPCO)
To:	NRC/OCIO/IMD/RMB
References
+sunsi/sispmjr=200603, -RFPFR
Download: ML003710637 (157)
v • d • e

ML003710637

Text

SUMMARY

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SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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