ML041310484

2003 Independent Spent Fuel Storage Installation Annual Radiological Environmental Operating Report

ML041310484
Person / Time
Site:	Surry, 07200002
Issue date:	04/30/2004
From:	Blount R Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
-RFPFR, 04-246
Download: ML041310484 (84)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 2004 United States Nuclear Regulatory Commission Serial No.04-246 Attention: Document Control Desk SS&L/TJN Washington, D. C. 20555-0001 Docket Nos. 50-280 50-281 72-2 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry Units 1 and 2 Technical Specification 6.6.B.2 requires the submittal of an Annual Radiological Environmental Operating Report (AREOR) for Surry Power Station. Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specification Appendix C.1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for the Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2003 through December 31, 2003 which includes environmental monitoring for the Surry ISFSI.

During the review of the 2003 AREOR report, an error was discovered in the previously submitted 2002 AREOR historical trend graph for air particulate gross beta activity. In Figure 4-3 of the 2002 report, only the 2002 gross air particulate control and indicator data were incorrect. The 2002 data has been corrected in the attached 2003 AREOR report.

If you have any questions or require additional information, please contact Beth Hilt at 757-365- 2608.

Very truly yours Richard H. Blount, Site Vice President Surry Power Station Attachment Commitments made in this letter: None

copy: US Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.E., Suite 23T85 Atlanta, Georgia 30303-8931 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Mr. G.J. McCoy NRC Senior Resident Inspector Surry Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23218

Serial No.04-246 Docket Nos.: 50-280 50-281 72-2 ATTACHMENT 2003 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37 INDEPENDENT SPENT FUEL STORAGE INSTALLATION LICENSE NO. SNM-2501 VIRGINIA ELECTRIC AND POWER COMPANY

Surry Power Station 2003 Annual Radiologica I Environmental Operating Report SDominionw

Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2003 to December 31, 2003 Prepared by Dominion Surry Power Station and Dominion Resources Services

Annual Radiological Environmental Operating Report Surry Power Station January 1, 2003 to December 31, 2003 Prepared by:

Dm nW. J. E Sin (3GervsorRadiological Engineering DomiionResources Services Prepared by: A? god P. F. Blount Health Physicist Dominion Surry Power Station Reviewed by: 1&T0A.iPIJ B. A. Hilt Supervisor Radiological Analysis and Material Control Dominion Surry Power Station Reviewed by:

D. K. Miller Supervisor Health Physics Technical Services Do inion Surry Power Station Approved by:

ks B.nes Manager Radiogical Protection Dominion Surry Power Station 2

Table of Contents PREFACE .......................................................... 4

1. EXECUTIVE

SUMMARY

.......................................................... 5

2. PROGRAM DESCRIPTION .......................................................... 7 2.1 Introduction .......................................................... 7 2.2 Sampling and Analysis Program .......................................................... 8

3. ANALYTICAL RESULTS ........................................................ 20 3.1 Summary of Results ........................................................ 20 3.2 Analytical Results of 2003 REMP Samples ........................................................ 27

4. DISCUSSION OF RESULTS ......................................................... 54 4.1 Gamma Exposure Rate ......................................................... 55 4.2 Airborne Gross Beta ......................................................... 56 4.3 Airborne Radioiodine ........................................................ 57 4.4 Air Particulate Gamma ........................................................ 58 4.5 Cow Milk ........................................................ 58 4.6 Food Products ........................................................ 58 4.7 Well Water ........................................................ 59 4.8 River Water ......................................................... 59 4.9 Silt ........................................................ 59 4.10 Shoreline Sediment ........................................................ 61 4.11 Fish ........................................................ 61 4.12 Oysters ......................................................... 62 4.13 Clams ......................................................... 62 4.14 Crabs ......................................................... 62

5. PROGRAM EXCEPTIONS ........................................................ 63

6. CONCLUSIONS ......................................................... 64 REFERENCES ........................................................ 66 APPENDICES ........................................................ 68 APPENDIX A: LAND USE CENSUS ................................................... 69 APPENDIX B: DOMINION NUCLEAR CONNECTICUT QA PROGRAM .. 71 APPENDIX C:

SUMMARY

OF INTERLABORATORY COMPARISONS .. 75 3

PREFACE This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report, for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-28 1.

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1. EXECUTIVE

SUMMARY

TShis document is a detailed report of the 2003 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2003, in air, water, silt, shoreline sediment, milk, aquatic biota, food products and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to confirm that radiological effluent releases are As Low as is Reasonably Achievable (ALARA), no undue environmental effects occur and the health and safety of the public are protected.

TIhe program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.

Radiation and radioactivity in the environment are monitored within a 20-mile radius of the station. Surry Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. The first type, control samples, are collected from areas that are beyond the measurable influence of Surry 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 Surry Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.

Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline." Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident or natural variation.

The Framatome ANP Environmental Laboratory provides radioanalyses for this program and Global Dosimetry Solutions Incorporated (formerly ICN Biomedicals) provides thermoluminescent dosimetry (TLD) services. Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the United States Nuclear Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The USNRC also mandates a reporting level for certain radionuclides. Licensed nuclear facilities must report the radionuclide activities 5

in those environmental samples that are equal to or greater than the specified reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.

Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates. Ihe 2003 airborne results were similar to previous years. No plant related radioactivity was detected and fallout or natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters. Naturally occurring potassium-40 was detected at average environmental levels. No man-made radioisotopes were detected in well water.

This trend is consistent throughout the operational environmental monitoring program. Silt samples indicated the presence of cesium-137 and cobalt-60. The cesium-137 activity was present in the control and indicator locations and is attributable to global fallout from past nuclear weapons testing and nuclear accidents such as Chernobyl. Cobalt-60 was detected at the indicator location, as expected. Cobalt-60 was also unexpectedly identified in the control location in March; however, this anomaly is believed to be due to sample mislabeling (see Section 4.9). There is no reporting level assigned for cobalt-60 and the trend over the past ten to fifteen year period continues to decrease. Shoreline sediment, which may provide a direct exposure pathway, contained no station related radioisotopes. The terrestrial exposure pathway includes milk and food products.

Iodine-131 was not detected in any 2003 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was again detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. No man-made radioisotopes were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk and food products. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TfLDs).

MRD results have remained relatively constant over the years.

During 2003, as in previous years, operation of the Surry Power Station has created no adverse environmental effects or health hazards. The maximum dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2003 was 0.001 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 Surry Power Station.

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2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2003 Surry Power Station operational Radiological Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. 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 855 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.

The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) 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 (LARA). To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications that address the release of radioactive effluents. In-plant monitoring is used to ensure that these 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 station environs is also included in Surry Power Station Technical Specifications.

Dominion personnel are responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions Incorporated is responsible for processing the TLDs. The Framatome ANP Environmental Laboratory is responsible for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes. Data collected prior to station operation is used to indicate the degree of natural variation to be expected. This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.

Occasionally, samples of environmental media show the presence of man-made radioisotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",

(December, 1975) and VPAP-2103S, Offsite Dose Calculation Manual (Surry).

These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low as is Reasonably 7

Achievable."

This report documents the results of the Radiological Environmental Monitoring Program for 2003 and satisfies the following objectives of the program:

9 To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public resulting from station operations.

> To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.

> To Identify changes in radioactivity in the environment.

> To verify that station operations have no detrimental effect on the health and safety of the public.

2.2 Sampling and Analysis Program Table 2-1 sunmmarizes the 2003 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." The Surzy Radiological Monitoring Locations maps (Figures 1 - 5) denote sample locations for Surry Power Station. The locations are color coded to designate sample types. Table 2-2 summarizes the analysis program conducted by Framatome ANP Environmental Laboratory and Global Dosimetry Solutions Incorporated for Surry Power Station during the year 2003.

On June 30, 1998, the Commonwealth of Virginia, Department of Health, discontinued its comparative analysis (state split) program with Surry Power Station. Although the routine splitting of samples with the Commonwealth of Virginia has been discontinued, samples will be split at the request of the state.

Dominion personnel collect all samples listed in Table 2-1. All samples, with the exception of the TLDs, are shipped to Framatome ANP Environmental Laboratory, located in Westborough, MA, for analysis. The T=Ds are shipped to Global Dosimetry Solutions Incorporated, located in Costa Mesa, CA, for processing.

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Table 2-1 SURRY - 2003 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Control (00) - Quarterly Onsite (Stored in lead containeroutside protectedarea)

TLDs West North West (02) 0.17 mi WNW 2920 Quarterly Site Boundary Surry Station Discharge (03) 0.60 mi NW 3090 Quarterly Site Boundary North North West (04) 0.40 mi NNW 3300 Quarterly Site Boundary North (05) 0.29 mi N 3570 Quarterly Site Boundary North North East (06) 0.28 mi NNE 220 Quarterly Site Boundary North East (07) 0.31 mi NE 450 Quarterly Site Boundary East North East (08) 0.43 mi ENE 680 Quarterly Site Boundary East (Exclusion) (09) 0.31mi E 900 Quarterly Onsite West (10) 0.40 mi W 2700 Quarterly Site Boundary West South West (11) 0.45 mi WSW 2500 Quarterly Site Boundary South West (12) 0.30 mi SW 2250 Quarterly Site Boundary South South West (13) 0.43 mi SSW 2030 Quarterly Site Boundary South (14) 0.48 mi S 1800 Quarterly Site Boundary South South East (15) 0.74 mi SSE 1570 Quarterly Site Boundary South East (16) 1.00 mi SE 1350 Quarterly Site Boundary East (17) 0.57 mi E 900 Quarterly Site Boundary Station Intake (18) 1.23 mi ESE 1130 Quarterly Site Boundary Hog Island Reserve (19) 1.94 mi NNE 260 Quarterly Near Resident Bacon's Castle (20) 4.45 mi SSW 2020 Quarterly Apx. 5 mile Route 633 (21) 5.00 mi SW 2240 Quarterly Apx. 5 mile Alliance (22) 5.10mi WSW 2480 Quarterly Apx. 5 mile Surry (23) 8.00 mi WSW 2500 Quarterly Population Center Route 636 and 637 (24) 4.00 mi W 2700 Quarterly Apx. 5 mile Scotland Wharf (25) 5.00 mi WNW 2850 Quarterly Apx. 5 mile Jamestown (26) 6.30 mi NW 3100 Quarterly Apx. 5 mile Colonial Parkway (27) 3.70 mi NNW 3300 Quarterly Apx. 5 mile Route 617 and 618 (28) 4.70 mi NNW 3400 Quarterly Apx. 5 mile Kingsmill (29) 4.80 mi N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.80 mi N 00 Quarterly Population Center Kingsmill North (31) 5.60 mi NNE 140 Quarterly Apx. 5 mile Budweiser (32) 5.70 mi NNE 270 Quarterly Population Center Water Plant (33) 4.80 mi NE 410 Quarterly Apx. 5 mile 9

Table 2-1 SURRY - 2003 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks BASF (34) 5.10 mi ENE 700 Quarterly Apx. 5 mile Lee Hall (35) 7.10mi ENE 730 Quarterly Population Center Goose Island (36) 5.00 mi E 880 Quarterly Apx. 5 mile Fort Eustis (37) 4.80 mi ESE 1070 Quarterly Apx. 5 mile Newport News (38) 16.50 mi ESE 1220 Quarterly Population Center James River Bridge (39) 14.80 mi SSE 1470 Quarterly Control Location Bean's Church (40) 14.50 mi S 1750 Quarterly Control Location Smithfield (41) 11.50 mi S 1760 Quarterly Control Location Rushmere (42) 5.20 mi SSE 1560 Quarterly Apx. 5 mile Route 628 (43) 5.00 mi S 1770 Quarterly Apx. 5 mile Air Charcoal Surry Station (SS) 0.37 mi NNE 150 Weekly Site Boundary (Highest D/Q) and Particulate Hog Island Reserve (MIR) 2.00 mi NNE 260 Weekly Bacon's Castle (BC) 4.50 mi SSW 2020 Weekly Alliance (ALL) 5.10 mi WSW 2480 Weekly Colonial Parkway (CP) 3.70 mi NNW 3300 Weekly BASF (BASF) 5.10 mi ENE 700 Weekly Fort Eustis (FE) 4.80 mi ESE 1070 Weekly Newport News (NN) 16.50 mi ESE 1220 Weekly Control Location River Water Surry Station Discharge (SD) 0.17 mi NW 3250 Monthly Scotland Wharf (SW) 5.00 mi WNW 2850 Monthly Control Location Well Water Surry Station (SS) - - Quarterly Onsite Hog Island Reserve (HR) 2.00 mi NNE 270 Quarterly Shoreline Hog Island Reserve (HIR) 0.80 mi N 50 Semi-Annually Sediment Chickahominy River (CHIC) 11.20 mi WNW 3000 Semi-Annually Control Location Silt Chickahominy River (CHIC) 11.20 mi WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.30 mi NNW 3410 Semi-Annually 10

Table 2-1 SURRY - 2003 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECIION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Milk Colonial Parkway (CP) 3.70 mi NNW 3370 Monthly Pivarnik (PV) 17.60 mi NNE 250 Monthly Control Location (01/03 - 05/03)

Williams (WMS) 27.50 mi S 1820 Monthly Control Location (06/03 - 12/03)

Epp's (EPPS) 4.80 mi SSW 201° Monthly Oysters Point of Shoals (POS) 6.40 mi SSE 1570 Semi-Annually Mulberry Point (MP) 4.90 mi ESE 1240 Semi-Annually Clams Chickahominy River (CHIC) 11.20 mi WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.30 mi NNW 3410 Semi-Annually Hog Island Point MP) 2.40 mi NE 520 Semi-Annually Lawne's Creek C) 2.40 mi SE 1310 Semi-Annually Fish Surry Station Discharge (SD) 1.30 mi NNW 3410 Semi-Annually Crabs Surry Station Discharge (SD) 1.30 mi NNW 3410 Annually Food Products Brock's Farm (BROCK'S) 3.80 mi S 1880 Annually (Corn, Peanuts, Slade's Farm (SLADE'S) 2.40 mi S 1770 Annually Soybeans) 11

Table 2-2 (Page 1 of 3)

SURRY - 2003 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2 mR/Std. Month Dosimetry (TLD)

Air Iodine Weekly 1-131 0.07 pCi/m 3 Air Particulate Weekly Gross Beta 0.01 pCi/r 3 Quarterly (a) Gamma Isotopic pCi/M3 Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium (H-3) 2000 pCi/L Composite of monthly sample Monthly I-131 10 pCiL Gamma Isotopic pCiL Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium (H-3) 2000 pCitL I-131 1 Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Footnotes locatedat end of table.

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Table 2-2 (Cont.)

(Page 2 of 3)

SURRY - 2003 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Silt Semi-Annual Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Milk Monthly I-131 1 pCi/L Gamma Isotopic pCi/L Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Oysters Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Clams Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Crabs Annually Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Footnotes located at end of table.

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Table 2-2 (Cont.)

(Page 3 of 3)

SURRY - 2003 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Fish Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-S58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Annually Gamma Isotopic pCi/kg - wet 1-131 60 Cs-134 60 Cs-137 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, are also Identified and reported.

• LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than these listed values.

(a) Quarterly composite of each location's samples are used for the required analysis.

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SW Legend

• Air Sampling Stations SSW

• TLD Sampling A State Environmental Monitoring Sites

• State TLD Sites

- - - - Exclusion Area Boundary U) 0

Ca CB3308

Figure 3. Surry Emergency Plan Map

• Air Sampling Stations

• Nearest Residents

• TLD Sampling

• Nearest Milk Animal

• Nearest Garden Im Aquatic Samples Original 0 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312, USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

CB3309 (o3

,,P 00 Figure 4. Surry Emergency Plan Map

• Air Sampling Stations

• Nearest Residents

• TLD Sampling

• Nearest Milk Animal

• Nearest Garden IAquatic Samples Original 01991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written pemmission of ADC.

C9331 0 C04

Figure 5. Surry Emergency Plan Map

• Air Sampling Stations

• Nearest Residents

. TLD Sampling

• Nearest Milk Animal

• Nearest Garden I 0 1 Aquatic Samples Original 0 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

, 6" CB3307A

3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the Surry Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented In Table 3-1. A more detailed analysis of the data is given in Section 4.

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Suny Power Station, Surry County, Virginia - 2003 Docket No. 5-280-281 Page 1 of 6 Medium or Indicator Control Pathway Ana sis Locations Location with Hi hest Mean Locations Non-Routine Sampled lTotal Mean Distance Mean Mean Reported (Un) Type INo LLD Range Name I Direction I Range Range Measurements Air Iodine 1-131 415 0.07 < LLD N/A < LLD c LLD 0 (pCWm)

Alr Gross 415 10 20.0(361163) HIR 2.0 ml 21.0(51/52) 20.2(52/52) 0 Particulate Beta (3.2-55.4) NNE (8.9-55.4) (8.248.2)

Gamma 32 Be-7 32 93.5(28128) HIR 2.0 ml 98.3(4/4) 89.5(4/4) 0 (68-119) NNE (88-111) (79-109)

Cs-134 32 50 < LLD N/A < LLD < LLD 0 Cs-137 32 60 < LLD N/A < LLD < LLD 0 River H-3 8 2000 < LLD N/A < LLD c LLD 0 Water (pOci)ter)

Gamma 24 K-40 24 57.0(3112) SD 0.17 ml 57.0(3112) 56.0(1/12) 0 (25-76) NW (25-76) (56-56)

Mn-54 24 15 <LLD N/A < LLD < LLD 0 Co-58 24 15 < LLD NWA < LLD < LLD Fe-59 24 30 < LLD N/A < LLD < LLD Co-60 24 15 < LLD N/A c LLD < LLD Zn-65 24 30 < LLD NWA < LLD < LLD Nb-95 24 15 < LLD N/A < LLD < LLD Zr-95 24 30 < LLD N/A < LLD < LLD 1-131 24 10 < LLD N/A < LLD < LLD

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

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surny County, Virginia - 2003 Docket No. 5-280-281 Page 2 of 6 Medium or indicator Control Pathway Anal sis Locations Location with HIchest Mean Locations Non-Routine Sampled I Totall Mean Distance Mean Mean Reported (Units) Type INo LLD Range Name Direction Range Range Measurements River Cs-134 24 15 < LLD N/A c LLD < LLD 0 Water (pCifier)

Cs-137 24 18 < LLD N/A < LLD < LLD 0 Ba-140 24 60 < LLD N/A < LLD < LLD 0 La-140 24 15 c LLD N/A < LLD < LLD 0 Well H-3 8 2000 < LLD N/A < LLD N/A 0 Water mifter) _ _ . . _ _ _ _ _ _ _ _ _

Gamma 8 Mn-54 8 15 < LLD N/A < LLD N/A Co-58 8 15 < LLD N/A < LLD N/A Fe-59 8 30 < LLD N/A < LLD N/A Co-60 8 15 < LLD N/A < LLD N/A Zn-65 8 30 < LLD N/A < LLD N/A Nb-95 8 15 < LLD N/A < LLD N/A Zr-95 8 30 < LLD N/A < LLD N/A 1-131 8 1 < LLD N/A < LLD N/A Cs-134 8 15 < LLD N/A < LLD N/A Cs-137 8 18 < LLD N/A c LLD N/A Ba-140 8 60 < LLD N/A < LLD NJA 0

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

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2003 Docket No. 5-280-281 Page 3 of 6 Medium or Indicator Control Pathway Anal sls Locations Location with Hi hest Mean Locations Non-Routine Sampled Totall Mean DIstance Mean Mean Reported (Units) Type No ! LLD Range Name Direction Range Range Measurements Well La-140 8 15 < LLD N/A LLD N/A 0 Water (pCiliter)

Slit Gamma 4 (pkgdry)

Be-7 4 2100(1/2) SD 1.3 ml 2100(1/2) c LLD 0 (2100-2100) NNW (2100-2100)

K-40 4 17740(2/2) CHIC 11.2 ml 18550(2/2) 18550(2/2) 0 (17080-18400) WNW (17600-19500) (17600-19500)

Co-60 4 66.5(212) SD 1.3 ml 66.5(212) < LLD 0 (42-91) NNW (42-91)

Cs-134 4 150 < LLD N/A < LLD <LLD 0 Cs-1 37 4 180 290.5(212) SD 1.3 ml 290.5(212) 228.5(212) 0 (288-293) NNW (288-293) (223-234)

Th-228 4 1175(2/2) CHIC 11.2 ml 1380(2/2) 1380(212) 0 (1160-1190) WNW (1310-1450) (1310-1450)

Shoreline Gamma 4 Sediment (pCkg dry) K-40 4 5305(212) HIR 0.8 ml 5305(2/2) 2665(212) 0 (5300-5310) N (5300-5310) (2590-2740)

Cs-134 4 150 < LLD N/A <LLD cLLD 0 Cs-137 4 180 < LLD N/A < LLD < LLD 0 Th-228 4 240.5(212) HIR 0.8 ml 240.5(212) 147.5(212) 0 (132-349) N (132-349) (143-152)

Milk Strontium 4 (pClMit Sr-89 4 < LLD N/A <LLD N/A 0 Sr-9o 4 3.35(214) CP 3.7 ml 3.35(2/4) N/A 0 (2.1-4.6) NNW (2.1-4.6)

Gamma 36 K-40 36 1358.4(24/24) EPPS 4.8 ml 1374.7(12112) 1225.2(12/12) 0 (1247-1490) SSW (1247-1490) (891-1530)

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

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SurIy Power Station, Suny County, Virginia - 2003 Docket No. 5-280-281 Page 4 of 6 Medium or Indicator Control Pathway Anal sis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported nlins) Type No LLD Range Name Direction Range Range Measurements Milk 1-131 36 1 < LLD N/A < LLD < LLD 0 Cs-134 36 15 < LLD N/A < LLD < LLD 0 Cs-137 36 18 < LLD N/A < LLD < LLD 0 Ba-140 36 60 < LLD N/A < LLD < LLD 0 La-140 36 15 < LLD N/A < LLD < LLD 0 Clams Gamma 8 (P0b wet)

Mn-54 8 130 < LLD N/A < LLD < LLD 0 Co-58 8 130 < LLD N/A < LLD <LLD 0 Fe-59 8 260 < LUD N/A <LLD < LLD 0 Co-60 8 130 < LLD N/A < LLD < LLD 0 Zn-65 8 260 < LLD N/A cLLD cLLD 0 Cs-134 8 130 < LLD N/A < LLD < LLD 0 Cs-137 8 150 < LLD N/A < LLD < LLD 0 Oysters Gamma 4 (pC&*g wet)

K-40 4 535(214) MP 4.9 ml 535(2/4) NWA 0 (500-570) ESE (500-570)

Mn-54 4 130 < LLD N/A < LLD N/A 0 Co-58 4 130 < LLD NtA < LLD N/A 0

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

24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Sury Power Station, Surry County, Virginia - 2003 Docket No. 5-280-281 Page 5 of 6 Medium or Indicator Control Pathway Ana yss Locations Location with Hiahest Mean Locations Non-Routine Sampled Total

• Mean Distance Mean Mean Reported T eINoInits LLD Range Name Direction Range Range Measurements Oysters Fe-59 4 260 < LLD NWA < LLD N/A 0 o7a*g wet)

Co-60 4 130 cLLD N/A <LLD N/A 0 Zn-65 4 260 < LLD N/A LLD N/A 0 Cs-134 4 130 c LLD N/A <LLD N/A 0 Cs-1 37 4 150 < LLD N/A <LLD N/A 0 Crabs Gamma 1 (pQ*g wet)

K-40 1 1320(1/1) SD 1.3 ml 1320(1/1) NWA 0 (1320-1320) NNW (1320-1320)

Mn-54 1 130 c LLD N/A <LLD N/A Co-58 1 130 < LLD NWA <LLD N/A Fe-59 1 260 c LLD N/A <LLD N/A Co-60 1 130 <LLD N/A <LLD N/A Zn-65 1 260 <LLD NIA <LLD N/A Cs-134 1 130 < LLD N/A < LLD N/A Cs-137 1 150 c LLD N/A < LLD N/A Fish Gamma 4 (pa*g wet)

K-40 4 2060(414) SD 1.3 ml 2060(414) NIA 0 (1490-2380) NNW (1490-2380)

Mn-54 4 130 <LLD N/A < LLD N/A 0

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

25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Sunry Power Station, Surry County, Virginia - 2003 Docket No. 5-280-281 Page 6 of 6 Fish C0-58 4 130 c LLD N/A < LLD N/A 0 (pCbkg wet)

Fe-59 4 260 < LLD N/A c LLD N/A 0 Co-60 4 130 < LLD N/A < LLD N/A 0 Zn-65 4 260 < LLD N/A < LLD N/A 0 Cs-1 34 4 130 < LLD NWA < LLD NWA 0 Cs-137 4 150 < LLD N/A < LLD N/A 0 Food Gamrma 3 Products 0CMg wet) K-40 3 7006.7(3/3) Slade's 2A ml 12740(111) W/A 0 (2560-12740) S (12740-12740) 1-131 3 60 < LLD N/A < LLD N/A 0 Cs-134 3 60 < LLD N/A < LLD N/A 0 Cs-1 37 3 80 < LLD N/A < LLD N/A 0 Th-228 3 60(1/3) Brock's 3.8 ml 60(113) NA 0 (60-60) S (60-60)

Direct Gamma 168 3.04(156/156) STA-41 11.5 ml 5.88(414) 3.86(12/12) 0 Radiation (o.8-.7) S (5.2-6.6) (1.7-6.6)

TLD (mRI SW Month)

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

26

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

The reported error is two times the standard deviation (2a) of the net activity.

Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 3a).

Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For the purposes of this report all valid data are presented, in order to indicate any background biases. Framatome ANP analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, 'An Acceptable Radiological Environmental Monitoring Program",

(November 1979, Revision 1) and the Surry ODCM.

Data are given according to sample type as indicated below.

1. Gamma Exposure Rate

2. Air Particulates, Gross Beta Radioactivity

3. Air Particulates, Weekly 1-131

4. Air Particulates, Gamma Spectroscopy

5. Cow Milk

6. Food Products

7. Well Water

8. River Water

9. Silt

10. Shoreline Sediment

11. Fish

12. Oysters

13. Clams

14. Crabs I Analytical results are handled as recommended by HASL (,Reporting of Analytical Results from HASL,'

letter by Leo B. Higginbotham) and WJREG/CR-4007 (Sept. 1984).

27

BURRY 2003 TABLE 3-2 QUARTERLY GAMME M[POSURE RATE (PM/BTD MOMNH +/- 2 8IMM)

L O C A T IO N8 PERIOD 02 03 04 05 06 07 08 09 10 11 12 O+M-) (+/-) (+/-) (4/-) (4/-) (O/-) (4/-) (+/-) (e/-) (4/-) (4/-)

1Q 3.8 1.6 3.5 0.6 2.4 0.8 3.3 0.8 3.0 0.9 2.7 1.3 2.1 0.9 3.0 0.7 2.5 1.7 2.6 0.8 2.9 0.8 2Q 4.5 0.4 4.8 1.5 3.6 0.4 4.0 0.3 4.5 0.2 3.3 0.1 3.2 0.3 3.4 0.5 2.8 0.4 3.2 0.5 3.5 0.3 30 4.3 0.6 4.1 0.6 3.7 0.9 3.8 0.5 4.6 0.4 3.4 0.5 3.4 0.5 3.3 0.3 3.2 0.3 3.3 0.4 3.4 0.3 4Q 5.0 0.8 5.4 1.3 3.7 1.0 4.0 0.8 4.7 1.0 4.2 1.1 3.5 0.6 3.9 1.8 3.3 0.9 3.4 0.9 3.9 1.0 13 14 15 16 17 18 19 20 21 22 23

(+/-) (+1-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-)

1Q 2.8 0.7 3.2 0.7 2.3 1.3 2.4 0.9 1.7 0.7 1.2 0.6 1.5 0.7 2.7 0.7 1.8 1.5 1.2 0.5 2.7 0.7 20 4.0 0.3 3.9 0.9 2.9 0.3 3.1 0.4 2.7 0.2 1.8 0.3 2.4 0.2 2.6 0.5 2.6 0.1 2.4 0.3 3.3 0.5 30 3.7 0.3 4.0 0.4 2.3 1.1 3.2 0.4 2.8 0.2 1.9 0.2 2.4 0.4 2.6 0.3 2.5 0.3 2.3 0.2 3.7 0.5 40 4.0 1.0 4.3 1.1 3.3 0.8 3.5 0.9 3.0 1.1 2.0 0.8 2.6 0.5 3.1 0.8 2.9 1.0 2.3 0.7 4.1 1.0 24 25 26 27 28 29 30 31 32 33 34

(+/ ) (O/M (+/ ) (OM (+/) (+/ ) (+/ ) (+/ ) (+/ ) (+/ ) ( +/ )

1Q 2.8 1.4 2.5 0.4 1.8 0.2 1.7 0.6 1.7 0.4 1.8 0.3 2.1 1.2 0.8 0.7 2.0 0.5 2.2 0.6 2.2 0.9 2Q 2.8 0.5 3.0 0.5 2.9 0.2 2.5 0.7 2.7 0.7 2.0 0.1 2.7 0.8 1.8 0.1 2.9 0.3 2.9 0.5 3.1 0.3 30 2.8 0.2 2.8 0.4 2.8 0.5 2.5 0.3 2.4 0.2 2.0 0.3 2.3 0.3 2.0 0.1 3.0 0.5 2.8 0.2 2.7 0.4 4Q 3.9 4.2 3.2 0.9 3.4 1.1 2.4 1.2 2.9 0.6 2.0 0.8 2.8 1.3 1.8 1.0 3.1 1.2 3.0 0.7 3.8 1.3 35 36 37 38 39-C 40-C 41-C 42 43 1Q 2.8 0.5 4.1 1.0 2.0 0.6 5.0 0.6 1.7 0.5 2.8 0.4 5.2 0.9 2.2 1.8 1.9 0.9 20 3.7 0.4 4.4 1.1 2.7 0.3 5.6 0.4 2.6 0.2 3.4 0.2 5.9 0.8 2.5 0.2 2.3 0.3 3Q 3.8 0.7 3.7 0.5 2.5 0.3 5.3 0.4 2.6 0.4 3.2 0.3 5.8 0.4 2.9 0.2 2.6 0.5 4Q 4.2 1.1 4.3 1.1 3.0 0.6 5.7 1.3 2.7 1.0 3.8 0.8 6.6 1.4 3.2 0.8 2.6 0.5 28

BURRY 2003 TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (18-3 PCI/M3)

LOCATION8 PERIOD 7NDSM 8a DC ALL CP BASF FE MN-C (4/ ) (./-) (+/-) (./-) (.1-) (+/-)

JAN 07 17.6 3.0 16.7 3.0 18.0 3.1 18.3 3.1 16.0 3.0 16.1 3.0 15.8 3.0 19.8 3.2 JAN 14 24.6 3.6 20.4 3.4 31.8 3.9 26.6 3.6 22.6 3.5 22.3 3.4 27.3 3.6 23.4 3.6 JAN 21 27.5 3.9 28.0 3.9 36.2 4.2 31.5 4.0 23.5 3.8 27.8 4.0 27.5 4.0 28.7 4.1 JA 28 25.2 3.5 25.1 3.5 28.0 3.6 27.2 3.5 23.6 3.4 25.0 3.4 27.8 3.6 26.0 3.6 FED 04 23.6 3.9 25.5 3.9 24.8 3.9 26.9 3.9 25.2 3.9 25.0 3.9 23.2 3.9 24.8 4.2 FEB 11 20.3 3.4 20.9 3.4 19.5 3.3 25.1 3.5 19.3 3.3 22.7 3.4 23.7 3.5 22.4 3.5 FEB 19 14.5 3.0 16.9 3.1 16.1 3.0 21.3 3.2 15.1 3.1 16.0 3.1 15.1 3.0 17.8 3.3 FEB 25 14.0 3.6 14.1 3.6 11.9 3.5 13.1 3.5 11.3 3.3 14.0 3.5 15.9 3.6 13.7 3.4 MAR 04 20.6 3.5 22.7 3.6 17.2 3.4 19.4 3.5 18.1 3.4 20.2 3.5 18.9 3.5 17.0 3.5 MAR 11 24.5 3.5 26.6 3.5 20.3 3.2 30.6 3.6 24.2 3.4 26.2 3.5 24.6 3.4 22.3 3.4 MAR 18 19.5 3.6 21.4 3.7 20.4 3.6 21.9 3.7 15.7 3.5 23.0 3.8 18.2 3.6 16.1 3.6 MAR 25 11.6 3.2 18.5 3.4 17.7 3.6 21.3 3.7 15.5 3.4 17.0 3.4 15.2 3.4 14.8 3.5 APR 01 9.4 2.3 15.0 2.5 18.6 2.6 19.3 2.6 12.6 2.4 14.2 2.5 17.4 2.6 14.7 2.6 APR 08 12.4 3.1 22.3 3.5 19.3 3.4 20.1 3.4 16.7 3.3 18.4 3.3 16. 1 3.3 14.6 3.3 APR 15 10.7 2.8 11.3 2.8 12.8 2.9 12.4 2.9 9.8 2.8 11.3 2.8 13.1 2.9 9.4 2.8 APR 22 14.6 3.2 20.7 3.1 21.1 3.4 23.3 3.5 18.2 3.3 20.4 3.4 18.1 3.3 19.3 3.5 APR 29 11.6 3.0 17.8 3.8 13.2 3.1 17.0 3.3 14.4 3.2 16.1 3.2 14.2 3.2 17.2 3.4 MAY 06 12.2 3.1 20.5 3.4 22.8 3.9 25.4 3.6 19.4 3.4 19.8 3.4 20.8 3.4 24.0 3.8 MAY 13 17.3 3.2 16.9 3.2 15.1 3.1 18.8 3.3 13.9 3.0 15.0 3.1 14.6 3.1 20.7 3.5 MAY 20 17.6 3.3 19.8 3.4 19.3 3.4 21.1 3.4 18.4 3.3 15.0 3.2 19.9 3.4 17.6 3.2 MAY 27 8.1 3.0 10.9 3.1 11.0 3.1 11.1 3.1 8.8 3.1 10.7 3.1 8.6 3.1 8.2 3.1 JUN 03 8.1 3.0 12.9 3.2 12.7 3.1 12.9 3.2 12.3 3.1 14.5 3.2 13.2 3.2 12.0 3.2 JUN 10 13.5 3.2 15.6 3.3 12.8 3.2 16.7 3.3 13.6 3.2 12.4 3.2 15. 5 3.3 14.0 3.3 JUN 17 14.6 3.2 19.5 3.4 16.6 3.3 18.3 3.4 19.4 3.4 16.9 3.3 15.7 3.4 17.9 3.4 JUN 24 10.2 3.1 11.3 3.1 9.8 3.1 14.4 3.1 9.5 3.0 11.9 3.1 8.6 3.0 11.2 3.2 29

BURRY 2003 TANAL 3-3 AIR PARTICULATZB GROS BETA RADIOACTIVITY (1F-3 PCI/N3)

LOCATIONS 8s HIR ALL CP DBA8 MN-C J0L 01 27.9 3.7 31.1 3.8 26.0 4.1 30.1 3.9 32.7 3.9 25.8 3.7 30.5 3.8 33.3 4.3 JUL 08 16.0 3.1 18.4 3.2 14.9 3.1 17.9 3.2 17.4 3.2 5.7 2.6 17.4 3.2 17.8 3.2 JUL 14 16.4 2.8 16.6 2.8 16.2 2.7 17.8 2.8 14.0 2.7 15.4 2.8 16. 0 2.8 15.8 2.9 JUL 21 16.0 2.5 55.4 7.8 A 17.6 2.6 21.3 2.7 15.1 2.5 17.6 2.6 19.0 2.6 16.6 2.6 JUL 28 12.2 3.1 15.1 3.4 14.8 3.4 15.7 3.3 16.7 3.3 21.0 3.5 21.9 3.5 20.0 3.4 ADU 04 14.4 2.5 14.0 2.4 18.3 5.6 13.7 2.4 19.4 5.7 17.5 4.5 13.3 2.3 15 .1 3.3 AUG 11 11.4 3.3 8.9 3.0 9.2 3.0 10.2 3.1 12.4 3.2 9.7 3.1 11.9 3.1 10.8 3.2 AUG 19 20.9 3.4 17.5 3.0 21.0 3.2 18.3 3.0 22.6 3.2 16.9 3.0 20.6 3.1 27.2 3.5 AUG 26 26.7 3.0 22.9 2.8 24.8 2.9 23.8 2.9 25.4 3.0 43.6 5.6 B 22.9 2.8 25.3 3.0 SEP 02 33.0 3.9 35.2 3.9 28.5 3.7 31.3 3.8 -340.0 700.0 C 28.9 3.7 28.9 3.7 31.8 3.8 SEP 09 16.1 2.5 14.9 2.5 16.5 2.5 15.0 2.5 13.0 4.8 D 15.0 2.5 16.5 2.5 15.7 2.6 SEP 16 12.5 3.3 12.4 3.2 10.3 3.2 13.0 3.3 10. 6 3.2 9.4 3.2 11.2 3.2 8.8 3.2 SEP 23 30.7 5.1 x 50.7 5.5 F 26.8 2.6 3 27.1 5.0 B 22.3 4.9 3 22.2 3.7 3 32.1 5.5 3 27.2 2.6 3 REP 30 19.8 4.4 a F 23.9 2.7 3.2 3.2 a 14.2 5.2 G 23.6 2.8 23.4 2.8 23.4 2.7 OCT 07 21.6 3.6 19.5 3.4 22.4 3.5 24.1 3.5 22.7 3.6 23.2 3.5 25.0 3.6 22.8 3.6 OCT 14 38.3 4.0 38.7 3.9 37.6 3.8 40.9 4.0 43.6 4.1 40.4 4.0 40.3 3.9 38.2 3.9 OCT 21 29.2 3.6 21.9 3.2 28.3 3.4 27.4 3.4 31.0 3.7 25.6 3.4 31.3 3.6 26.6 3.5 OCT 28 18.4 3.3 20.3 3.3 18.9 3.2 19.5 3.3 20.8 3.4 20.7 3.4 19.6 3.3 20.6 3.3 NOV 04 28.6 4.0 20.9 3.5 23.4 3.5 26.1 3.6 27.5 3.7 25.8 3.6 23.3 3.5 24.6 3.8 NOV 11 17.2 3.3 19.6 3.3 15.0 3.1 18.5 3.2 20.8 3.3 18.4 3.3 19.5 3.3 16.6 3.2 NOV 18 27.3 3.7 27.3 3.7 24.5 3.6 25.0 3.6 21.1 3.5 28.1 3.8 28.2 3.8 30.6 3.9 NOV 25 30.9 3.8 26.2 3.7 26.8 3.6 26.7 3.7 29.3 3.8 28.1 3.8 24.3 3.6 26.8 3.7 DEC 02 23.4 3.4 23.9 3.3 24.9 3.4 26.7 3.4 25.1 3.4 24.1 3.4 22.2 3.3 23.5 3.4 DEC 09 16.7 3.0 16.3 3.0 16.1 2.9 18.1 3.0 18.4 3.1 17.8 3.1 16.1 2.9 14.8 3.0 DEC 16 18.0 3.1 15.9 3.0 18.9 3.1 17.3 3.1 19.7 3.2 18. 0 3.2 16.4 3.0 20.9 3.3 DEC 22 14.5 3.7 20.2 3.8 21.3 3.9 27.1 4.1 23.2 4.0 19.1 3.9 21.2 3.8 22.7 4.0 DEC 29 17.8 3.7 15.8 3.5 -. 8 2.8 H 20.9 3.7 17.1 3.6 21.6 3.8 17.3 3.6 22.8 3.9 30

Table 3-3 Footnotes A. Sampler timer malfunction. Particulate filter had normal loading. Sample volume based on conservative timer indication. Sample volume was sufficient to meet required LLD.

B. Sampler not operational at sample change out. 71mer indicated 166.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. Particulate filter had normal loading. Sample volume based on conservative estimate of one-half typical volume. Sample volume was sufficient to meet required LLD.

C. Sampler malfunction due to blown fuse after 0.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of run time. Sample volume Insufficient to meet required LLD.

D. Sampler malfunction due to blown fuse after 75.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of run time. Sample volume was sufficient to meet required LLD.

E. Sampler lost power due to Hurricane Isabel. Sample volume was sufficient to meet required LLD.

F. Sampler not in service due to extended power outage resulting from Hurricane Isabel.

G. Lower than typical sample volume due to Hurricane Isabel power outages. Sample volume was sufficient to meet required LLD.

H. Particulate filter had lighter than normal loading. Sampler operational entire week. Sample volume was sufficient to meet required LLD.

31

SURRY 2003 TABLE 3-4 AIRBORNE IODINE X-131 (1E-3 PCI/M3)

LOCATIONS PERIOD ENDING sIR 88 DC ALL CP BASF FE mN-C

(+1-) (el-) (+1-) (+/-) (.1-) (.1-/) (4l/-) (4l/-)

JAN 07 -6 13 -1 10 -6 11 -1 10 3 10 1 12 1 11 -17 11 JAN 14 -7 15 -3 13 -4 13 2 13 -6 14 -2 16 2 16 -7 17 JJM 21 -8 14 -6 17 13 18 -5 14 -5 16 0 18 -2 14 14 18 JAW 28 -2 17 -5 18 -8 14 -18 15 -12 19 -8 18 0 18 8 19 FEB 04 9 25 12 19 -15 21 6 19 12 23 6 25 6 22 -6 22 FB 11 3 16 -5 16 -6 14 7 16 -6 19 -7 15 -6 19 -8 16 FEB 19 -7 12 -4 13 8 11 -1 12 2 12 6 11 -11 13 -8 13 FB 25 -12 14 3 13 12 17 -2 16 11 16 -15 17 -16 18 -8 18 MR 04 -5 13 -12 13 a 14 -6 12 -4 13 -2 11 -3 12 5 14 MR 11 -4 12 1 11 -5 12 11 13 -5 13 -3 13 2 11 2 12 MAR18 3 9 9 11 11 12 7 12 9 12 -6 12 3 11 6 12 M R25 2 10 -3 13 9 12 -2 13 1 12 5 12 -3 12 1 11 APR 01 3 18 4 13 -13 15 -5 16 4 16 1 20 2 14 -3 23 APR 08 -1 11 -6 11 -2 9 -13 13 0 12 -12 14 1 14 -3 15 APR 15 -1 8 -3 9 1 9 3 9 -2 10 2 9 -3 10 6 8 APR 22 8 13 -5 9 6 10 -4 11 8 10 4 13 -2 8 -8 9 APR 29 -7 12 -8 14 3 13 -7 11 -8 12 -5 12 -5 10 -6 12 MY 06 2 11 -1 10 8 14 -3 12 14 13 -7 12 5 16 2 15 MAY 13 -1 12 6 12 3 11 6 12 -2 12 2 13 6 14 1 12 MAY 20 -3 10 -2 10 -6 10 0 12 1 10 -5 10 1 10 5 9 MAY 27 11 16 -7 16 -9 13 3 17 3 12 0 9 -1 10 5 10 JUN 03 1 9 2 13 2 12 0 11 4 10 -3 13 -15 12 1 12 JUN 10 13 13 1 8 1 8 3 9 4 9 -3 7 5 8 -5 10 JUN 17 5 10 11 13 -4 10 -4 10 -6 12 -8 10 5 11 0 11 JUN 24 -1 14 13 12 7 14 12 11 -5 12 12 13 8 14 0 16 32

BURRY 2003 TABLE 3-4 AIRSORNE IODINE I-131 (1E-3 PCVIM3)

L O C A TI O n 8 PERIOD 8s mm RC ALL CP BA8F FE Mn-C

(.1-) (.1-) (+1-) (4/-) OM1-JUL 01 3 10 -5 9 -2 16 4 12 0 12 -4 11 -7 14 8 14 JUL 08 0 18 -4 11 -2 17 -6 17 4 17 11 14 5 14 -3 12 JUL 14 2 18 4 13 7 10 6 11 6 13 -6 10 1 12 4 11 JUL 21 -2 10 -2 27 5 10 0 a -12 9 -10 10 1 9 0 13 JUL 28 -3 12 -2 14 4 10 a 11 2 9 3 10 3 9 0 10 AUG 04 -4 9 1 9 3 12 -2 10 -1 12 -19 15 -4 9 1 14 AUG 11 -4 11 -4 12 -11 13 2 11 -2 9 2 12 -4 11 -14 12 AUG 19 1 10 11 10 5 10 9 10 -5 11 -1 9 -2 a 1 11 AUG 26 -5 7 0 7 -4 9 -8 9 1 10 -4 15 0 10 -4 10 SEP 02 -5 24 -14 20 6 17 7 21 -632 7895 A 9 20 6 22 5 22 SEP 09 9 12 -6 9 -2 11 9 12 -3 32 R 3 12 1 12 -7 12 SEP 16 -9 10 5 12 -4 13 -7 11 0 13 1 14 0 11 3 10 SEP 23 -11 31 C 31 32 C -3 10 C -23 31 C 4 33 C 8 20C 5 40 D 6 12 C EP 30 -4 19 F 5 -2 12 5 18 F 2 16 F 7 14 -2 14 a 13 OCT 07 -1 15 13 15 7 14 3 14 -3 14 2 16 -7 12 -4 17 OCT 14 -4 14 5 13 -2 12 4 13 9 13 0 15 1 13 2 14 OCT 21 3 16 -6 16 2 14 0 12 -9 16 6 15 -12 15 11 17 OCT 28 4 10 1 10 -1 11 -2 12 3 10 5 11 -5 9 -11 12 NOV 04 10 22 -1 17 -7 14 13 19 -6 20 13 16 2 15 -3 19 nO 11 -2 17 -1 15 -14 17 6 17 7 20 -5 14 -1 14 -1 14 NOV 18 8 14 -2 12 4 12 -4 13 7 15 9 14 -7 13 4 12 NOV 25 33 24 -14 21 13 20 6 21 -6 23 14 21 8 22 8 22 DEC 02 -4 19 5 18 -11 19 5 18 -9 19 -2 18 -13 18 -2 20 DEC 09 -4 19 21 23 0 23 7 20 0 27 10 15 -14 12 -13 13 DEC 16 2 14 4 18 6 15 -4 15 2 16 1 21 -5 16 12 19 DEC 22 4 12 8 13 2 11 1 12 12 11 2 11 8 11 7 9 DEC 29 8 16 -9 17 17 15 14 17 4 15 -4 13 8 14 -4 14 33

Table 3-4 Footnotes A. Sampler malfunction due to blown fuse after 0.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of run time. Sample volume insufficient to meet required LLD.

B. Sampler malfunction due to blown fuse after 75.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of run time. Sample volume was sufficient to meet required LLD.

C. Sampler lost power due to Hurricane Isabel. Sample volume was sufficient to meet required LLD.

D. Sampler lost power due to Hurricane Isabel. Sample volume was insufficient to meet required LLD.

E. Sampler not in service due to extended power outage resulting from Hurricane Isabel.

F. Lower than typical sample volume due to Hurricane Isabel power outages. Sample volume was sufficient to meet required LLD.

34

BURRY 2003 TABLE 3-5 AIR PARTICULATLS GAMMA SPECTRA - QTR 1 (1R-3 PCI/143)

WOCATION DE-7 R-40 CO-60 ZR-95 "3-95 RU-103 (3.-)

as 93 35 -24.0 13.0 -0.70 1.30 0.1 3.8 1.5 4.3 0.7 2.5 RIR ll 38 -14.0 13.0 -0.10 1.20 1.9 2.5 3.2 4.4 1.1 3.1 BC 87 36 -18.0 12.0 -0.80 1.10 1.6 4.1 -0.2 4.2 -2.5 2.9 ALL 89 35 -11.0 17.0 0.30 1.00 0.8 2.9 -0.7 3.3 -1.8 3.4 CP 89 34 -16.0 16. 0 -0.10 1.30 2.8 3.2 2.7 4.2 0.0 2.7 BAS? 112 39 -18.0 16. 0 0.10 1.30 0.8 2.9 2.3 2.9 0.4 2.9 FE 116 38 -20.0 14.0 -0.10 1.30 -1.9 3.2 2.2 3.8 -0.4 3.1 PN-C 79 38 -23.0 14.0 1.00 1.10 -1.9 3.3 -2.2 4.9 -1.1 3.6 RU-l06 CB-134 CS-137 BA-140 Cl-141 TH-228 (4/-)

so 11.1 9.9 0.20 1.10 -1.70 1.70 -10 33 0.1 4.1 4.1 3.5 RIR 1.1 9.1 0.10 1.00 -0.90 1.70 -19 38 -2.2 4.0 -3.9 3.8 DC -4.4 7.7 -0.50 1.00 0.10 1.70 -29 51 2.0 4.5 -0.1 3.8 ALL -5.5 9.1 0.07 0.93 -0.80 1.70 19 61 4.1 4.3 -0.1 2.7 CP -4.4 8.3 -0.24 0.94 1.10 1.90 19 47 0.2 4.7 -0.1 2.0 BABS 0.0 9.4 -0.51 0.72 0.00 1.60 -19 38 -1.4 4.5 0.8 3.6 FE 2.2 7.7 0.80 1.00 0.20 1.80 -29 51 2.1 4.3 1.7 3.5 nw-C -4.6 8.6 0.09 0.85 -1.30 1.70 30 44 -1.9 4.8 2.8 3.4 35

BURRY 2003 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 2 (13-3 PCX/M3)

LOCATION BE-7 R-40 CO-60 ZR-95 IM-95 RU-103 88 73 32 -2.6 7.7 0.45 0.52 0.2 2.4 -1.1 3.2 1.7 2.3 KIR 100 32 -8.1 8.5 0.28 0.63 -0.6 2.3 -1.2 3.2 -0.6 2.0 DC 91 30 -13.5 7.4 -0.87 0.77 0.3 2.7 -2.5 4.2 -0.7 2.6 ALL 107 35 0.3 8.7 -0.08 0.91 -1.0 2.5 1.4 3.4 1.7 3.1 CP 108 41 12.0 16.0 0.00 0.87 -1.5 3.7 -0.4 4.4 -2.5 3.3 naor 89 37 12.0 15.0 0.10 1.50 -0.2 2.8 3.9 3.8 -1.7 3.7 FE 90 35 9.0 15.0 -0.61 0.99 -0.3 3.3 -0.4 4.5 0.0 3.1 MN-C 86 41 7.0 15.0 -0.30 1.40 1.7 5.3 0.8 5.8 1.7 3.7 RU-106 C8-134 CB-137 BA-140 CE-141 TE-228 (4/-)

88 2.9 7.4 -0.07 0.50 -0.05 0.50 12 65 -2.1 5.4 0.1 2.4 HIR -0.8 6.4 -0.03 0.75 0.16 0.89 0 49 3.8 5.2 0.8 1.9 BC 2.2 6.7 0.44 0.84 -0.27 0.60 50 50 -3.9 5.0 -1.1 2.6 ALL -7.3 8.3 0.31 0.79 0.02 0.68 -62 55 1.4 5.1 3.9 2.6 CP -4.5 9.0 -0.38 0.89 0.20 1.70 -16 31 7.0 5.4 -1.7 3.0 DA"? 6.8 9.6 -0.30 1.00 -1.00 1.70 -16 70 2.7 5.7 0.7 3.4 FE 1.1 6.8 -0.40 1.10 -0.20 1.70 0 77 4.9 4.7 0.2 2.7 MN-C -5.8 9.0 -0.10 1.00 0.20 1.70 0 46 -0.5 5.7 -1.2 3.5 36

BURRY 2003 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 3 (1Z-3 PCXIM3)

LOCATION K-40 CO-60 ZR-95 NB-95 RU-103 (4/) M/-) (./ )

88 68 26 8.0 13.0 0.15 0.60 0.9 2.4 2.1 2.3 -0.2 1.5 HMR 94 29 -5.0 10.0 -0.62 0.71 -1.2 3.1 -1.6 2.9 0.6 2.0 BC 109 28 0.0 11.0 -0.24 0.91 -0.7 2.3 0.5 1.9 0.4 1.3 ALL 76 24 3.0 11.0 -0.25 0.94 0.6 2.4 -0.4 2.0 0.0 1.8 CP 83 30 18. 0 17.0 -0.49 0.90 2.0 2.9 -0.2 2.2 1.7 2.3 BASF 108 30 10.0 13.0 -0.21 0.64 1.0 2.6 -0.6 2.5 -0. 5 1.5 86 26 1.0 10.0 -0.30 1.00 0.5 1.7 0.6 2.4 0.2 1.7 NW-C 109 28 4.0 10.0 0.10 0.89 0.9 2.3 -1.2 2.2 0.9 1.7 RU-106 CB-134 CB-137 BA-140 CZ-141 TN-228

( ,-)

B8 3.6 5.8 -0.29 0.72 0.28 0.59 -11 11 0.8 3.0 0.7 2.8 NIR 1.4 7.3 -0.40 1.10 0.00 0.90 15 26 4.7 3.8 -3.5 3.0 BC -3.5 8.8 -0.05 0.70 0.08 0.87 0 7 0.6 2.9 1.4 2.7 ALL -3.2 8.0 0.19 0.73 -0.17 0. 61 -3 5 -0.6 2.8 0.6 1.9 CP 2.0 12.0 0.24 0.92 0.30 1.00 -3 11 -1.5 4.1 -1.3 3.2 DAS? -3.5 8.8 0.45 0.77 0.72 0.74 0 11 2.5 3.3 -1.5 2.5 FE 5.6 7.9 -0.12 0.8s -0.10 0.74 -5 12 -4.9 3.0 1.0 2.5 P -C -0.3 8.4 0.55 0.76 -0.27 0.55 0 10 0.2 2.6 -1.0 2.2 37

BURRY 2003 TAMA. 3-5 AIR PARTICULATES GAMIA SPECTRA - QTR 4 (1Z-3 PCIMU3)

LOCATION DE-7 R-40 CO-60 ZR-95 1B-95 RU-103

(+1-)

as 119 37 0.0 10.0 0.40 1.20 -2.9 3.8 -3.9 5.3 1.3 3.2 FIR 88 33 12.0 14.0 0.04 0.99 -0.5 4.0 -4.1 3.7 -1.3 2.8 DC 83 34 8.0 13.0 0.60 1.20 -0.4 3.7 0.1 4.5 -1.9 2.7 ALL 96 35 -3.0 12.0 -1.30 1.40 0.2 3.0 2.0 2.7 1.6 2.3 CP 84 35 16.0 17.0 -0.52 0.91 1.1 3.6 -2.3 3.0 -2.3 2.9 BASF 71 28 14.0 15.0 1.20 1.50 1.7 3.1 3.3 4.1 -0.3 2.0 FE 99 34 0.0 11.0 0.10 1.30 0.3 2.6 -0.7 2.8 -1.0 2.3 MN-C 84 32 4.0 14.0 -0.90 1.30 0.8 2.5 2.5 3.7 -0.3 2.9 RV-106 CB-134 CB-137 BA-140 CR-li TH-228

_ __ __1 __1 (4/-) (+1-) (4/-) 4/) (4/-)

88 -1.1 8.8 0.10 1.10 0.60 2.00 8 26 1.6 4.0 1.6 4.2 HIR -4.4 8.8 -0.70 1.10 -0.20 1.50 15 21 0.0 4.0 -0.3 2.5 BC -6.5 9.2 0.38 0.90 -1.30 1.50 -22 38 -2.8 3.9 1.6 3.6 ALL -3.3 7.3 0.07 0.92 -0.10 1.60 0 29 1.9 4.3 0.2 3.3 CP -3.0 11.0 -0.60 1.10 -1.00 1.60 45 36 1.0 4.4 -0.3 2.9 BASF -2.2 7.1 0.30 1.40 -0.70 1.70 0 37 -0.1 4.2 0.7 3.7 8.8 7.6 0.40 0.80 -0.50 1.50 -29 46 2.4 4.0 -0.8 3.5 MR-C -5.7 8.8 0.20 1.30 -1.10 1.90 -23 40 2.3 3.9 -3.2 3.3 38

BURRY 2003 TABLE 3-6 COW MILK (PCI/L)

COLLECTION LOCATION DATE K-40 BR-89 BR-90 X-131 C8-134 CS-137 BA-140 LA-140 CP 01/07/03 1410 120 0.04 0.30 -0.3 3.1 1.7 3.3 -1.8 4.2 -2.1 4.9 02/04/03 1360 110 -0.11 0.04 2.5 2.7 1.0 2.9 1.6 4.1 1.9 4.7 03/04/03 1290 140 -7.9 5.3 0.8 1.1 -0.08 0.03 0.5 3.6 -0.6 3.7 1.9 5.9 2.1 6.8 04/01/03 1328 94 0.15 0.31 0.0 2.6 -3.3 2.7 0.0 4.2 0.0 4.8 05/13/03 1273 85 0.11 0.24 0.9 2.4 -0.5 2.2 -0.2 3.3 -0.2 3.8 06/03/03 1370 150 -0.7 6.3 1.4 1.0 0.01 0.29 0.3 4.1 0.2 4.1 -1.4 6.3 -1.6 7.3 07/01/03 1252 93 -0.13 0.05 -1.9 2.8 -0.2 2.6 0.2 3.4 0.3 3.9 08/19/03 1260 69 0.04 0.26 1.0 1.9 -0.1 1.9 0.2 4.5 0.2 5.1 09/02/03 1280 170 -1.1 7.3 2.1 1.0 0.39 0.36 1.5 4.4 3.6 4.8 -1.5 5.5 -1.7 6.4 10/14/03 1396 95 -0.13 0.05 1.1 2.8 -1.9 2.8 -0.7 3.7 -0.8 4.3 11/04/03 1456 97 -0.13 0.22 -1.1 2.5 1.7 2.4 3.9 4.7 4.4 5.4 12/02/03 1430 160 -24.5 7.0 4.6 1.2 -0.14 0.24 1.6 5.5 -3.1 4.1 3.4 6.6 4.0 7.6 EPPS 01/21/03 1490 110 0.11 0.33 0.3 3.2 2.6 2.9 -0.5 5.4 -0.6 6.2 02/19/03 1410 140 0.48 0.51 1.7 3.4 -1.3 3.7 -2.9 4.0 -3.4 4.6 03/25/03 1472 88 0.30 0.43 -0.1 2.2 0.1 2.1 0.5 3.8 0.6 4.4 04/22/03 1430 100 0.02 0.21 -0.9 2.9 0.2 2.4 2.1 4.3 2.4 4.9 05/27/03 1370 130 0.09 0.24 1.3 3.8 -0.2 3.9 -1.1 4.9 -1.2 5.6 06/24/03 1400 160 -0.22 0.07 0.9 4.2 1.1 4.2 0.7 5.6 0.8 6.4 07/28/03 1290 170 0.14 0.25 -2.6 4.2 0.3 4.7 3.9 6.3 4.5 7.3 08/19/03 1247 79 0.04 0.28 0.0 2.2 -1.2 2.0 2.4 5.1 2.7 5.8 09/30/03 1285 95 -0.25 0.25 1.6 2.9 0.3 2.5 0.0 3.5 0.0 4.0 10/28/03 1322 95 0.05 0.37 -0.1 2.7 -0.5 2.4 1.3 3.7 1.5 4.3 11/18/03 1420 100 0.22 0.41 -1.5 2.7 -0.3 2.3 3.0 4.6 3.5 5.3 12/16/03 1360 110 0.01 0.22 -1.2 2.8 2.4 2.8 2.7 5.6 3.1 6.4 STRONTIUM ANALYBEB FOR CP MILK SAMPLES REQUESTED BY TIE COMONNWEM OF VIRGINIA 39

BURRY 2003 TADLZ 3-6 COW MIL (PCI/L)

COLLECTION LOCATION DATE K-40 BR-89 SR-90 X-131 CS-134 CB-137 EA-140 LA-140

(+/-) (+/-) (+/-) (OM-) (+/-) (+/-) (+/-) (+/-

PlV-C 01121103 1270 120 0.09 0.30 -0.2 2.8 -1.7 3.0 0.0 5.0 0.0 5.8 02/19/03 1121 97 0.31 0.39 2.4 2.7 -2.3 2.6 2.5 3.6 2.9 4.1 03/18/03 970 120 -0.01 0.03 1.8 3.5 1.5 3.1 -0.9 5.2 -1.1 6.0 04/15/03 920 100 0.11 0.27 -1.9 3.3 1.3 2.8 -1.4 5.2 -1.6 6.0 05/27/03 891 88 0.37 0.39 -1.1 2.7 2.9 2.6 3.5 5.0 4.0 5.7 vMB-c 06/24/03 1240 130 0.07 0.33 0.2 4.0 0.2 3.9 -2.9 5.6 -3.3 6.4 07/14/03 1378 93 0.05 0.23 -0.1 2.7 0.0 2.6 -2.7 3.8 -3.1 4.4 08/26/03 1360 190 0.15 0.35 3.3 5.7 0.1 4.4 8.9 8.2 10.3 9.4 09/30/03 1350 110 0.00 0.30 -1.3 2.8 -0.1 2.8 0.5 4.7 0.5 5.4 10128/03 1390 120 0.66 0.67 0.6 3.4 -0.4 2.9 -2.0 5.4 -2.3 6.2 11/18/03 1282 88 0.12 0.35 0.8 2.4 -1.0 2.1 -3.1 4.7 -3.6 5.4 12/16/03 1530 100 0.08 0.37 -0.2 2.6 -1.1 2.3 -4.2 4.6 -4.8 5.3 WILLIANS REPLACED PIVARNIK AS CONTROL IR JUNE 40

BURRY 2003 TABLE 3-7 FOOD PRODUCTS (PCI/KG WET NWT.)

COLLECTION LOCATION DATE TYPE BE-7 1-40 CR-51 MN-54 CO-58 F7-59

/-) (4-) (4-) (4/-) /-) (4-)

BROCKI8 10/28/03 CORN -6 50 2560 270 -5 46 3.8 6.8 0.0 5.4 -14 17 10/28/03 PEANUTS 12 59 5720 450 43 61 2.9 7.8 -3.0 8.2 1 27 SLADE'S 12/03/03 SOYBEANS 19 25 12740 220 -13 28 -1.3 3.2 -1.8 3.5 -14 15 CO-60 3N-65 ZR-95 NB-95 RU-103 RU-106 (4/-) (4-) (4-) (4-) (4-) (4-)

BROCK'S 10/28/03 CORN -1.8 6.2 -13 17 3.0 11.0 4.6 6.7 2.7 5.2 28 55 10/28/03 PEANUT8 4.1 8.2 -24 22 0.0 12.0 3.6 8.0 2.3 8.0 -45 81 SLADE'S 12/03/03 SOYBEANS -4.1 4.3 -4 10 -3.1 6.1 -2.2 4.1 -1.7 3.2 -11 28 5B-125 X-131 CS-134 CS-137 3A-140 LA-140 (4/-) (4-) (4-) (4-) (4-) (4-)

BROCK'S 10/28/03 CORN 5.0 14.0 3.2 8.6 -2.2 6.5 3.9 5.7 -1.0 5.9 -1.1 6.7 10/28/03 PEAkUTS 2.0 21.0 -4.0 11.0 4.6 8.9 11.0 11.0 7.1 6.7 8.2 7.7 BLADES 12/03/03 SOYBEANS -5.0 6.9 3.1 9.4 -1.1 3.5 4.1 3.7 1.2 4.9 1.3 5.6 CE-141 CE-144 TH-228 (4-) (4-)

BROCK'S 10/28/03 CORN -4.3 9.0 -20 30 13 23 10/28/03 PEANUTS -2.0 10.0 18 40 60 39 SLADE'S 12/03/03 SOYBEANS -2.3 6.5 2 13 11 16 41

MMRRY 2003 TABLE 3-8 WELL WATER (PCI/L)

COLLECTION LOCATION DATE E-40 CR-51 MN-54 CO-58 FE-59 CO-60 EIR 03/19/03 0.0 23.0 16.0 19.0 0.0 1.8 0.3 1.9 0.6 4.0 0.9 1.7 06/24/03 16.0 31.0 -36.0 23.0 0.4 1.9 -0.8 2.2 3.9 4.6 -0.2 2.1 09/16/03 3.0 23.0 16.0 17.0 0.5 1.6 -0.5 1.5 -1.6 4.0 -0.9 1.9 12/16/03 13.0 27.0 19.0 21.0 2.1 2.2 -0.5 2.3 3.8 5.9 -0.1 2.3 sB 03/19/03 -7.0 22.0 16.0 22.0 -0.3 2.0 0.1 1.9 2.8 4.0 0.5 1.7 06/24/03 -2.0 27.0 5.0 29.0 -0.9 2.6 -3.1 2.6 -0.2 5.5 -0.9 2.0 09/16/03 0.0 33.0 0.0 24.0 0.6 2.2 -3.3 2.5 3.1 7.1 -0.5 2.1 12/16/03 18.0 28.0 15.0 23.0 -0.5 2.0 0.4 1.9 2.3 7.0 -0.9 2.2 ZN-65 ZR-95 N8-95 RU-103 RU-106 1-131 (4/-)

fIR 03/19/03 -3.5 3.4 1.7 3.0 -0.1 2.1 -2.5 2.0 2.0 18.0 -0.01 0.03 06/24/03 -8.9 5.4 1.3 4.2 -0.4 2.6 -3.4 2.6 11.0 21.0 0.01 0.22 09/16/03 -0.6 4.6 2.5 2.7 -0.2 2.0 -0.2 2.1 11.0 15.0 -0.14 0.05 12/16/03 4.5 8.8 2.0 4.4 -1.7 3.1 -0.4 2.6 1.0 19.0 0.22 0.53 8B 03/19/03 0.0 3.8 2.2 2.9 1.1 2.3 -0.2 2.1 9.0 17.0 -0.01 0. 04 06/24/03 4.0 13.0 -2.8 4.8 5.1 4.6 -1.8 2.6 -6.0 24.0 0.22 0.32 09/16/03 0.9 7.0 -0.1 4.6 0.7 2.4 -3.3 2.4 -3.0 22.0 -0.14 0. 05 12/16/03 -3.8 4.1 -0.8 3.9 0.8 2.5 -1. 0 2.2 -16.0 19.0 -0.13 0.39 42

SURRY 2003 TABLE 3-8 WELL WATER (PCI/L)

COLLECTION LOCATION DATE CB-134 CB-137 BA-140 LA-140 E-3

(.1-) (.1-/) (+/-) (+1-/) (.1-)

RIR 03/19/03 -0.3 1.5 -0.3 1.9 0.5 3.4 0.6 3.9 0 850 06/24/03 2.9 2.3 2.3 2.2 -3.6 3.3 -4.1 3.8 -230 790 09/16/03 0.1 1.5 0.7 1.7 2.8 2.7 3.2 3.1 90 810 12/16/03 -0.9 2.2 1.2 2.1 -1.3 5.3 -1.5 6.1 -870 770 88 03/19/03 -0.3 1.9 -0.3 2.0 1.1 3.3 1.3 3.8 140 860 06/24/03 -1.2 2.4 1.1 4.1 1.3 4.6 1.5 5.3 -110 800 09/16/03 2.4 2.4 -1.5 2.3 -1.3 4.6 -1.5 5.3 230 810 12/16/03 0.3 2.2 1.9 2.0 3.7 5.3 4.3 6.1 -200 810 43

SMRRY 2003 TABLE 3-9 RIVER WATNR (PCXIL)

COLLECTION WOCATZON DATZ K-40 CR-51 MN--54 0O-58 FP-59 CD--60 (4/-)

SD 01/21/03 70 34 -8 18 0.4 1.9 0.7 1.8 4.2 3.7 0.3 2.0 02/19/03 76 28 1 13 -1.3 1.4 0.7 1.5 -0.1 3.1 0.7 1.3 03/25/03 3 31 8 20 -1.0 1.8 -0.7 1.7 2.3 4.4 -1.7 2.2 04/29/03 19 42 -24 26 -0.7 2.8 -0.5 2.7 -4.0 5.9 2.3 2.7 05/21/03 -13 32 -5 19 -1.3 2.0 0.2 2.0 3.6 4.4 -0.7 2.8 06/17/03 17 31 -4 19 0.1 2.1 2.0 1.9 2.7 4.3 1.1 2.1 07/14/03 35 33 6 25 -1.8 2.5 -0.6 2.4 -2.4 5.4 0.8 2.4 08/19/03 25 16 -5 11 0.0 0.9 0.2 1.0 -0.7 2.8 -0.9 1.0 09/16/03 20 33 -10 22 -1.4 2.3 0.0 2.2 2.8 6.2 -0.2 2.5 10/21/03 17 39 -8 27 -0.6 2.2 0.6 2.4 2.1 7.5 -0.3 2.7 11/18/03 28 37 6 24 -0.8 2.0 -0.4 1.9 -3.2 7.1 -0.2 2.0 12/09/03 13 28 2 18 -0.1 1.5 1.2 1.7 -1.6 4.8 -0.2 1.8 SW-C 01/21/03 34 34 8 20 -0.3 2.1 -1.3 1.9 -4.9 3.7 0.0 2.0 02/19/03 56 35 1 19 -3.1 2.2 0.3 1.8 0.0 4.1 -0.1 2.1 03/25/03 10 39 10 24 -0.8 2.8 1.6 2.5 7.4 5.5 1.8 3.7 04/29/03 3 40 -15 27 0.7 2.5 0.0 2.4 2.7 5.1 -0.4 2.8 05/21/03 5 24 a 19 0.8 1.6 0.4 1.9 -0.5 3.6 -1.7 2.0 06/17/03 2 26 2 22 2.1 2.0 -1.0 2.1 0.5 4.3 0.7 2.1 07/14/03 24 30 1 24 -0.6 2.2 1.6 2.5 -1.3 5.2 -0.5 2.4 08/19/03 -12 22 4 14 -1.0 1.7 1.1 1.6 -3.1 5.6 0.9 1.9 09/16/03 25 37 9 26 1.3 2.1 -2.0 2.4 -3.2 6.5 0.0 2.4 10/21/03 -4 39 -9 22 0.4 2.7 -0.6 3.2 -1.0 6.1 1.8 2.7 11/18/03 -9 34 -4 19 0.6 2.0 -2.4 2.4 -2.1 5.8 2.3 2.9 12/09/03 1 32 5 16 1.1 1.9 -1.8 1.9 4.5 5.0 -1.3 2.1 44

BURRY 2003 TABLE 3-9 RIVER VMTER (PCX/L)

COLLCMTION LWCATION DATE ZN-65 ZR- .-95 ND-95 RU- 103 RU-106 1-131 OM (e/-)

BD 01/21/03 0.0 8.3 2.0 3.1 0.0 2.0 -1.3 1.8 -17 17 0.0 3.7 02/19/03 1.9 7.3 0.7 2.3 -0.6 1.9 -0.8 1.4 -13 13 -0.4 2.6 03/25/03 -4.2 4.0 -0.2 3.5 0.4 2.3 0.0 2.4 -4 20 -0.4 3.9 04/29/03 -3.2 6.6 0.3 5.2 0.0 3.4 -2.2 3.2 5 25 -4.8 5.1 05/21/03 -1.4 4.7 2.1 4.1 1.0 2.6 -0.9 2.5 -9 21 2.0 4.4 06/17/03 10.8 9.5 -0.8 3.8 0.5 2.3 -1.5 2.4 -5 18 -1.0 3.9 07/14/03 -1.1 6.2 -0.7 4.0 -1.9 2.7 -1.6 2.8 5 19 4.0 4.4 08/19/03 -1.9 2.2 0.0 1.7 0.0 1.2 -0.9 1.7 4 9 -0.5 3.5 09/16/03 -3.0 5.8 4.1 4.0 2.7 2.4 2.1 3.0 19 21 2.3 4.6 10/21/03 -2.5 5.3 -2.1 4.1 2.6 2.4 -1.9 2.8 24 22 3.4 5.2 11/18/03 -3.3 4.5 -1.6 3.5 2.1 2.0 0.3 2.4 -10 21 3.2 4.2 12/09/03 -3.9 3.6 0.3 2.8 0.0 1.8 -2.2 1.9 1 14 -0.2 5.2 ON-C 01/21/03 -4. 0 4.5 -5.4 3.6 -1.0 2.3 -1.1 2.2 -3 17 0.8 4.0 02/19/03 -1.7 4.3 -2.0 3.2 1.8 2.1 -1.9 2.1 7 18 1.2 4.0 03/25/03 5.0 6.6 1.0 3.9 0.9 2.6 -3.5 3.1 1 26 -0.9 4.7 04/29/03 -1.7 5.7 0.5 5.2 0.3 2.6 -3.5 2.7 -9 25 -0.2 5.6 05/21/03 3.3 4.1 -1.5 3.7 -0.5 2.1 -0.4 2.5 1 16 -0.6 4.3 06/17/03 3.2 8.4 1.9 3.5 0.3 2.2 -1.3 2.2 -1 19 2.8 4.4 07/14/03 -7.3 5.9 0.3 3.6 -1.4 2.8 0.4 2.6 16 19 -1.7 4.5 08/19/03 -1. 8 3.4 3.5 2.8 -0.7 2.0 -2.2 1.7 -8 12 -3.6 2.9 09/16/03 5.0 11.0 -0.2 3.9 0.9 4.1 -1.7 2.5 -9 22 -1.6 5.0 10/21/03 -3.5 5.7 -0.9 5.0 -1.2 2.2 -0.2 2.6 -4 22 -1.8 4.1 11/18/03 -0.9 4.5 -1.1 3.8 0.8 2.4 -2.0 2.5 -7 17 -0.7 3.7 12/09/03 -2.8 3.8 -0.4 3.9 1.3 2.2 -2.2 2.2 0 17 1.9 5.3 45

BURRY 2003 TABLE 3-9 RIVUR WMTER (PCX/L)

COLLECTION LOCATION DATE CB-134 CS- 137 DA-140 LA- 140 m-3 ED 01/21/03 1.2 1.9 -0.2 1.9 0.6 3.9 0.7 4.5 02/19/03 -0.5 1.5 0.3 1.5 0.7 2.1 0.8 2.4 03/25/03 -1.2 2.0 1.0 1.9 1.2 3.0 1.4 3.4 570 880 04/29/03 -0.5 2.9 -0.1 2.4 -3.2 4.4 -3.7 5.1 05/21/03 2.8 2.4 0.0 2.6 0.9 4.6 1.0 5.3 06/17/03 0.5 2.1 -0.4 2.0 -0.3 3.0 -0.3 3.5 170 760 07/14/03 -1.3 2.7 1.3 2.4 -0.4 4.7 -0.5 5.5 08/19/03 -0.3 1.0 0.1 1.0 0.4 2.2 0.5 2.5 09/16/03 -0.9 2.6 -0.4 2.0 -0.9 3.3 -1.0 3.8 390 840 10/21/03 -0.9 2.4 1.3 2.6 0.0 4.1 0.0 4.7 11/18/03 0.7 2.4 0.7 1.8 1.8 4.1 2.0 4.8 12/09/03 0.0 1.6 -0.6 1.7 -1.2 3.5 -1.4 4.1 210 590 SW-C 01/21/03 0.1 2.0 -1.8 2.3 -5.3 3.7 -6.1 4.3 02/19/03 -1.1 2.1 -2.0 2.1 0.9 2.7 1.1 3.2 03/25/03 1.3 2.0 -0.6 2.9 0.0 3.7 0.0 4.3 330 860 04/29/03 -1.4 2.9 -1.1 2.5 0.4 4.3 0.5 5.0 05/21/03 -0.9 2.1 -1.4 2.0 -0.3 3.0 -0.4 3.4 06/17/03 -1.3 1.9 -0.3 2.0 0.1 3.5 0.1 4.0 490 800 07/14/03 -0.4 2.3 1.3 2.1 -2.1 4.2 -2.4 4.9 08/19/03 -0.1 1.6 -1.7 1.6 -1.5 3.3 -1.7 3.8 09/16/03 -0.7 2.2 -2.7 2.5 -0.8 3.7 -1.0 4.2 200 800 10/21/03 3.0 2.4 2.1 2.3 2.8 4.0 3.2 4.6 11/18/03 1.4 2.1 1.7 2.0 1.7 4.1 2.0 4.7 12/09/03 -0.5 1.9 -1.0 1.8 -0.4 4.0 -0.5 4.6 200 590 46

BURRY 2003 TABTL 3-10 SILT (PCX/PM DRY WT.)

CoLlECTIoN LOCATION DATE BE-7 K-40 CR-S1 Ma-54 CO-58 13-59

(+W-) (+/-) (+/-) (+1-) (W1-) (+1-)

CHIC-C 03/25/03 430 480 16600 1100 -430 760 40 35 6 42 -110 120 07/17/03 0 420 19500 1100 560 680 19 33 4 43 110 150 09/25/03 -20 400 17600 1200 190 510 14 31 -46 38 -8 91 SD 03/25/03 220 430 15800 1400 -250 720 28 33 -1 44 -130 130 07/17/03 230 520 17080 850 -1100 1200 17 26 7 42 -10 170 09/25/03 2100 540 18400 1300 -570 510 37 37 0 38 20 96 c0-60 ZN-65 ZR-95 NB-95 RU-103 RU-106

( /) ( /) ( /) (W/-) (4/-) (4/-)

CHIC-C 03/25/03 58 28 A 80 160 -12000 12000 7 85 13 68 -50 280 07/17/03 39 32 50 150 -11 82 56 92 24 54 -90 320 09/25/03 18 35 -10 150 -60 150 0 56 16 45 100 300 RD 03/25/03 19 33 70 160 66 82 -67 79 -12 56 110 310 07/17/03 42 21 0 130 41 87 -50 150 -2 75 60 230 09/25/03 91 35 60 160 -7200 7700 -34 58 -2 48 -40 310 AG-110M X-131 CS-134 CS-137 83-125 TH-228

( /) ( /) ( /) ( /) ( /) ( /)

CHIC-C 03/25/03 29 42 -1400 1700 -12 28 280 54 -46 81 950 140 07/17/03 4 43 -400 1100 -23 42 234 48 -26 86 1450 130 09/25/03 7 47 -50 340 17 33 223 56 121 81 1310 150 SD 03/25/03 9 41 -400 1200 42 A1 197 60 22 78 970 140 07/17/03 -5 34 10000 14000 -1 32 288 41 15 72 1160 98 09/25/03 16 47 330 340 -19 36 293 59 -18 91 1190 150 (A) UNEXPECTED POSITIVE C0-60 AT CONTROLy SPLIT 8AMPLE REBUAS 66 +/- 36.

MARCH RESULTS ARE NOT INCLUDED IN TABLE 3-1. (MSM ECTION 4 9 FOR DETAILS) 47

BURRY 2003 TABLE 3-11 SHORZLINE SEDIPMW (PCI/KO DRY WT.)

COLLECTXON LOCATION DATE DE-7 R-40 CR-51 M-54 co-se FE-59

(+-) (4-) (6-) (4-) (4-) (4-)

CHIC-C 02/04/03 100 94 2740 400 -20 120 -8 10 -1 10 -16 22 08/19/03 40 37 2590 160 -4 35 1 4 -2 4 -5 9 NIR 02/04/03 0 110 5300 480 -80 130 -6 10 -11 12 2 29 08/19/03 80 110 5310 420 -110 110 4 11 -2 12 -3 25 CO-60 ZN-65 ZR-95 ND-95 RU-103 RU-106 (4-) (4-) (4.-) (4-) (4-) (4-)

CHIC-C 02/04/03 7 13 67 50 -19 30 8 15 -1 11 -23 84 08/19/03 -3 4 26 21 -18 14 -1 6 0 4 -20 34 HXR 02/04/03 -2 10 -9 27 -11 30 -6 15 -10 12 -10 110 08/19/03 5 11 -60 60 -44 42 3 15 -13 13 -60 110 AG-lOM X-131 CS-134 CS-137 83-125 TH-228 (4-) (4-) (4-) (4-) (4-) (4-)

CRHC-C 02/04/03 -3 16 19 26 -46 49 12 12 -9 29 152 50 08/19/03 -3 5 0 6 -8 8 0 4 -1 10 143 17 FIR 02/04/03 -5 15 38 29 49 38 16 15 -26 33 132 61 08/19/03 -11 15 -7 20 -5 13 12 13 -8 32 349 54 48

SURRY 2003 TABLE 3-12 FISH (PCI/? WNT WT.)

COLLECTION LOCATION DATE TYPE B3-7 K-40 CR-51 MN-54 CO-58 F7-59 (4/) (4/-)

RD 04/29/03 CATFISH -50 260 2380 880 100 300 3 26 1 36 -76 89 04/29/03 WHITE PERCH -30 220 1490 570 50 240 10 24 -18 31 56 63 10/14/03 CATFIHR 80 270 2300 810 300 370 5 24 9 36 69 89 10/14/03 WRITE PERCH -380 250 2070 670 -160 330 3 23 17 37 -30 110 CO-60 ZN-65 ZR-95 RU-103 RU-106 (4/-) (4/-)

SD 04/29/03 CATFISR 28 37 -10 55 0 54 36 39 -11 32 -110 260 04/29/03 WHITE PERCH 3 27 -39 58 22 53 14 26 -14 30 240 230 10/14/03 CATFISH -3 31 -83 72 35 47 -3 51 35 -60 210 10/14/03 WHITE PERCH 32 28 58 60 -19 42 -22 46 11 32 100 240 AG- 1101 1-131 CS-134 C0-137 8B-125 TH-228 (4/-) (4/-) (4/-)

RD 04/29/03 CATFISH -24 44 57 81 15 26 4 30 75 77 -120 140 04/29/03 WRITE PERCH 0 29 -53 67 -5 25 7 26 -10 54 -43 77 10/14/03 CATFISR 5 37 30 200 -26 33 -10 26 45 53 -28 82 10/14/03 WHITE PERCH -28 33 -80 260 -6 28 1 29 0 66 -30 100 49

BURRY 2003 TABLE 3-13 OYOTERS (PCI/KG NET "T.)

COLLECTION LOCATION DATE nz-7 K-40 CR-51 MN-54 CO-58 FE-59 (1) (-) (.1-) (+-) (.) ( )

HP 03/25/03 170 280 570 350 -140 500 -2 17 0 31 -25 64 09/25/03 -70 250 500 330 200 400 0 18 -3 20 12 83 POO 03/25/03 70 260 220 260 460 470 -16 20 0 29 -42 63 09/25/03 -210 240 240 320 60 450 26 26 -18 27 -20 58 CO-60 ZN-65 ZR-95 NB-95 RU-103 Rm-106 W+/) W+/) W+-) W+-) W+/) W-/)

MP 03/25/03 8 18 -4 53 0 48 14 48 14 39 -190 200 09/25/03 8 19 -41 44 19 44 -8 41 -29 37 20 140 Poo 03/25/03 -13 19 17 43 -41 60 17 54 -28 45 70 230 09/25/03 5 16 -11 47 5 49 18 49 -17 35 -140 160 AG-lO0 1-131 CB-134 CS-137 SB-125 T1-228

("4-)

NP 03/25/03 12 29 290 980 2 20 -7 21 -30 45 33 71 09/25/03 9 27 -600 960 -8 21 0 18 10 55 43 65 FOS 03/25/03 -3 31 0 1100 11 23 -6 16 -40 49 22 70 09/25/03 -3 30 -400 1100 7 19 11 17 -21 36 -39 70 50

BURRY 2003 TAALE 3-14 CLRM (PCI/KG WGT W"T.)

COLLECTION LOCATION DATE RE-7 K-40 CR-51 Mn-54 00-58 FE-59

(.1-) (./-) (+1-) X /-) (./-) (O/M)

CHIC-C 03/25/03 -230 300 70 360 -280 540 0 22 3 28 -35 70 09/25/03 -30 300 350 310 140 520 0 21 -17 23 -60 100 RIP 03/25/03 60 290 -50 270 110 410 -2 18 12 36 -38 76 09/25/03 120 280 300 330 350 570 11 23 17 36 -10 110 LC 03/25/03 10 250 190 240 -140 430 -2 17 20 27 -32 59 09/25/03 -10 230 260 290 180 410 -27 19 23 29 109 93 OD 03/25/03 -170 330 160 360 360 540 1 28 -13 35 72 87 09/25/03 -10 240 130 240 -140 430 -2 22 19 29 65 96 CO-60 ZN-65 ZR-95 ND-95 RU-103 RU-106

( /) ( /) ( /) ( /) ( /) (+/)

CHIC-C 03/25/03 10 23 -43 50 33 51 8 47 9 43 -80 260 09/25/03 -9 21 -25 51 -6 47 -53 51 22 40 240 180 HIP 03/25/03 10 29 16 38 25 54 -52 63 31 47 -110 150 09/25/03 -18 20 -80 63 -22 66 -33 48 4 45 70 250 LC 03/25/03 8 23 1 51 15 44 26 37 10 36 -20 210 09/25/03 12 19 -31 47 -14 49 3 37 34 35 130 170 RD 03/25/03 4 22 0 61 -13 38 -7 51 -30 45 150 270 09/25/03 -2 21 -44 54 -29 47 -34 50 -2 37 160 190 51

BURRY 2003 TABLE 3-14 CLM8 (PCIKG WEZT WT.)

COLLECTION LOCATIOS DATE AG-lO1 X-131 CS-134 C8-137 83-125 TH-228

(+/-) (+/-) (OM-) (+/-) (+/-) (+/-)

CHIC-C 03/25/03 -17 33 800 1200 10 22 7 24 -42 59 2 98 09/25/03 29 25 -100 1100 -3 23 -7 21 -4 49 79 82 HIP 03/25/03 -18 24 -620 830 3 25 0 23 5 52 22 80 09/25/03 4 28 400 1200 -3 21 -19 28 -58 55 15 98 LC 03/25/03 -24 25 600 1100 -2 17 -5 21 12 52 39 71 09/25/03 -3 31 -500 1000 10 19 -5 20 9 52 0 59 RD 03/25/03 -15 33 100 1300 8 29 9 25 -12 51 30 110 09/25/03 -8 23 -70 920 0 21 -5 16 4 49 -19 62 52

SUERR 2003 TABLE 3-15 CRABS (PCI/KM WET "T.)

COLLECTION LOCATION DATE BE-7 K-40 CR-51 MN-54 CO-58 FE-59

(.1-) (+1-) (.1-) (+1-) (.1-) (.1-)

oD 07/03/03 110 260 1320 320 -430 590 -4 15 12 25 10 93 CO-60 Zn-65 ZR-95 1B-95 IW-103 RU-106 W+/) W+/) ( /) W+/) ( /) ( /)

SD 07/03/03 8 15 -39 35 -57 54 -54 55 -11 42 40 130 AG-l1O0 X-131 CB-134 CS-137 BB-125 TE-228 1 23) 10 7) - 14) 3 15) -2 3) 2 4)

SD 07/03/03 17 23 1900 7500 -9 14 3 15 -21 3A 2 49 53

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2003 and tabulated in Section 3, are discussed below. TIhe procedures and specifications followed in the laboratory for these analyses are as required in the Framatome ANP Environmental Laboratory quality assurance manual and laboratory procedures. In addition to internal quality control measures performed by the laboratory, it also participates in an Interlaboratory Comparison Program.

Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the Interlaboratory Comparison Program are provided in Appendix C.

The predominant radioactivity detected throughout 2003 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Naturally occurring nuclides such as beryllium-7, potassium-40, and thorium-228 were detected in numerous samples.

Massive power outages resulted from Hurricane Isabel's destructive forces when it struck Virginia on September 18, 2003. The airborne sampling stations, which require electrical power to operate, were out of service for time periods varying from 2 to 12 days. The extended power outages resulted in two deviations from the Radiological Environmental Monitoring Program requirements.

TIhe Hog Island Reserve (HIR) air sampling station was inoperable for the entire sampling period from 9/23/03 through 9/30/03 as a result of physical damage to the sampler and loss of power. Due to this inoperability, the required gross beta, iodine-131 and gamma isotopic analyses were not performed, as there was no sample for this period. The HIR sampling station was returned to service on 9/30/03 following repairs to the sample station and restoration of electrical power. Other than repairs to the sampling station, no other plans to prevent recurrent hurricane damage could be implemented.

The second deviation was a failure to meet the required airborne iodine-131 LLD at the Fort Eustis air sampling station for the sampling period 9/16/03 through 9/23/03. Due to the extended power outage at this location, a smaller than typical sample volume was obtained. Even though the volume was atypically low, the sample was initially analyzed to the required iodine-131 LLD. Later in 2003, industry Operating Experience (OE) identified a need to correct iodine-131 concentrations in continuous air samples based on collection efficiency. Surry researched the issue and determined that a collection efficiency of 95% should be applied to continuous environmental air samples when analyzing for iodine-131.

Correction for collection efficiency was incorporated into the REMP beginning with the October 14, 2003 continuous air samples. Subsequently, the continuous air sample iodine- 131 analysis results from January to October 2003 were corrected 54

for collection efficiency and the data was reviewed. The review confirmed no positive iodine- 131 concentration in the samples. The review also determined that the referenced Fort Eustis air sample analysis did not meet the required iodine-131 LLD when the collection efficiency correction was applied.

The following is a discussion and summary of the results of the environmental measurements taken during the 2003 reporting period.

4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. TLDs are placed in two concentric rings around the station.

The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population centers and nearby residences. Additional TLDs serve as controls. Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.

Figure 4-1: DIRECT RADIATION MEASUREMENT TLD RESULTS 8-s 7-0-6 -

2 3-- &,AI 2

4- W 'A 1f - l 00 ON 0 I Cl CO ONy 0 0 0 0 ON ON 0 0 0 0

- - N Cq N cCl

-+- Site Boundary e 5 Mile - Avg Control The results of the analyses are presented in Table 3-2. Figure 4-1 shows a historical trend of TLD exposure rate measurements, comparing the average of indicator TLDs located near the site boundary and at 5 miles to the average of all 55

control TLD locations. Control and indicator averages indicate a steady relationship. Also apparent in Figure 4-1 is the replacement, in 2001, of the previously used CaSO4:Dy in Teflon TLDs with a new type of TLD comprised of two elements each of CaF and LiF. Two TLDs are deployed at each monitoring location. The difference in response between the two systems is very apparent with the new TLDs reading up to 50% lower. This trend will continue to be monitored.

4.2 Airborne Gross Beta Air is continuously sampled by passing it through glass fiber particulate filters.

The filters collect airborne particulate radionuclides. Once a week the samples are collected and analyzed for gross beta activity. Results of the weekly gross beta analyses are presented in Table 3-3. A review of the results indicates that the 2002 - 2003 average activity is 26% higher than the average activity since 1986.

However, results from control and indicator locations continue to show no significant variation in measured activities (see Figure 4-2). This indicates that any station contribution is not measurable.

Figure 4-2: 2003 GROSS BETA IN AIR PARTICULATES 0.050 -

0.045 -

0.040 0.035 -

,, 0.030 - _ _ _ t 0.010

_ q & &- An oS cb E- 3%

S 0 O X0 et 0 o o 00 0 0 0 0 0o 0 0t 0 0 0 0 04 00 to _ 1~ -

--- Avg Indicator *- ..- Avg Control 56

Gross beta activity found during the pre-operational and early operating period of Surry Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady (see Figure 4-3).

Figure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND 1.0E+00 (a) 1.OE 1.OE-02 . . . .

co X cm co LO

-8>XO co I M0) oM0 CD a) 0n 0 r-a) 0 0_ n 0 a) 0 o o o o

_ _- _ _ _- _ V_ 1'_ _. _

Ir- _ _ Cr1 (J N N

-+- Avg Indicator e Avg Control - Avg-Pre Op - Required LLDI (a) Chernobyl 4.3 Airborne Radioiodine Air is also continuously sampled for radioiodines by passing it through charcoal cartridges. Once a week the charcoal cartridge samples are collected and analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection with the exception of those noted in Section 5, Program Exceptions. No positive iodine-131 was detected. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.

CoD 57

4.4 Air ParticulateGamma The air particulate filters from the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy. The results are listed in Table 3-5. The results indicate the presence of naturally occurring beryllium-7, which is produced by cosmic processes. Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected. No man-made radionuclides were identified. These analyses confirmn the lack of station effects.

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

Analysis results for cow milk are contained in Table 3-6. All results show a lack of detectable iodine-131 above the LLD of 1 pCi/L. Results of gamma spectroscopy indicate no other detectable station related radioactivity in the milk samples. In years past, cesium- 137 has been detected sporadically. The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2003.

At the request of the Commonwealth of Virginia, a quarterly composite sample is prepared from the monthly milk samples from the Colonial Parkway collection station. The composite samples are analyzed for strontium-89 and strontium-90.

Sr-90 was detected in two of the four composites analyzed, at an average concentration of 3.4 pCi/L. Although the average level of Sr-90 is somewhat higher this year than in past years, the historical trend shows activity slowly decreasing over the long-term. The Sr-90 detected is not a part of station effluents but, rather, a product of nuclear weapons testing fallout. This conclusion can be made based upon: examination of effluent release totals showing the lack of any positive indications of Sr-90 in effluents to account for such measurements, the lack of any positive indications of Sr-89 which is chemically similar and generally released in comparable quantities from the station, and the trend of consistent declining levels since the pre-operational period.

4.6 FoodProducts Three samples were collected and analyzed by gamma spectroscopy. The results 58

of the analyses are presented in Table 3-7. As expected, naturally occurring potassium-40 was detected in all samples. The average concentration is consistent with that observed in previous years. No station related radioactivity was detected.

4.7 Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry Power Station monitors well water quarterly at two indicator locations and analyzes for gamma radiation and for tritium. The results of these analyses are presented in Table 3-8. Consistent with past monitoring, no station related radioactivity was detected. No gamma emitting isotopes were detected during the pre-operational period.

4.8 River Water The analysis results for the James River water sampling program are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. These samples are also composited and analyzed for tritium on a quarterly basis. With the exception of naturally occurring potassium-40 observed in some samples analyzed, no other gamma emitters were detected.

4.9 Silt Silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Sampling of this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish.

Samples of silt are collected from two locations, one upstream and one downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10 and trending graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.

Upon examination of sample results for March 25, it was suspected that a mislabeling of the two samples had occurred. Historically, Cobalt-60 is detected in samples obtained from the indicator location (SD). In March, analysis results showed no indication of Co-60 at (SD) but did indicate positive Co-60 detected in the sample from the control location (CHIC). To verify the results, a split of the original (CHIC) sample was delivered to the laboratory for analysis in June. It also showed positive Co-60 at the control location, which is located over 11 miles up-river from the station. Because of the suspicious nature of the results compared to what is normally observed, extra samples were taken in July. July results were consistent with expected observations due to historical trends; positive Co-60 was 59

observed from the indicator location, not the control location. Therefore, the results obtained in March appear to be due to sample mislabeling at the station; confirmed by the split of the same sample, labeled as being from the control location, but also showing positive Co-60 results. No further occurrences of sample mislabeling were noted throughout the year. Results from the March silt samples are not included in the summary of results Table 3-1 nor the trend graph Figure 4-4, due to the suspected mislabeling of the samples.

Figure 4-4: COBALT-60 INSILT L.OE+04 L.OE+03 1.OE+02 L.OE+O1 l.OE+OO N

(4 N

No 00 o

0 00 C'4 00 00

'00

%O 00 00 o (4

es le0 00 l+Control - Chickahominy- Station Discharge l Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDL.

Station Discharge was < MDL activity 1996 through 1998.

Cobalt-60 was detected In the indicator samples collected in 2003. The average level observed from the station discharge at 67 pCi/kg is station related and is comparable to levels detected in past years. Cobalt-60 was detected in 2002 with an average activity of 53 pCi/kg. In 1999, cobalt-60 was also detected with an average activity of 67 pCi/kg.

Cesium-137 was also detected, as usual, in both the control and indicator samples. The levels detected indicate a continual decreasing trend seen for over a decade. The detection of Cs-137 in both the control and indicator samples and decreasing levels indicate that the presence of Cs-137 is the result of accumulation and runoff into the river of residual weapons testing fallout. Its global presence has been well documented. During the pre-operational period, Cs-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5. In 2003, cesium-137 was detected with an average indicator location concentration of 291 pCi/kg and an average control location 60

concentration of 229 pCi/kg. These activities continue to represent fallout from nuclear weapons testing. Both indicator and control cesium-137 activities trend closely as shown in Figure 4-5.

Figure 4-5: CESIUM-137 IN SILT L.OE+04 -

b , &- )

1.OE+03 Ii I I-- Z \ I 1.OE+02 N

ON- EN 00 ram Nl ON (6

00 00 Cr 00 ON 00 ON 1o 00 00 00 (ON ON 0

CON 00 ON ON~

I

- Control - Chickahominy - Station Discharge

-Avg-Pre Op -Required LI])

4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans.

Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. The results are presented in Table 3-1 1.

The naturally occurring radioisotopes potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities. The activities of these radioisotopes indicate a steady trend. There were no radioisotopes attributable to the operation of the station found in any shoreline sediment samples.

4.11 Fish The radioactivity measured in fish sampled from the station discharge canal and analyzed by gamma spectroscopy is presented in Table 3-12. These results are the same as those seen over the last decade. No activity was observed in this media except for naturally occurring potassium-40.

61 I

4.12 Oysters Oysters are collected from two different locations. The results of the oyster analyses are presented in Table 3-13.

There were no gamma emitting radioisotopes detected in oysters sampled except for naturally occurring radionuclides such as potassium-40. No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of steam generators in 1982 and past improvements made to liquid effluent treatment systems.

4.13 Clams Clams are analyzed from four different locations. The results of the gamma spectroscopy analyses are presented in Table 3-14. Like oysters, no station related radioactivity was detected.

4.14 Crabs A crab sample was collected in July from the station discharge canal and analyzed by gamma spectroscopy. The results of the analysis are presented in Table 3-15.

Other than naturally occurring potassium-40, no other gamma emitting radioisotopes were detected in the sample. This is consistent with pre-operational data and data collected over the past decade.

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5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2003 - Surly Date of Location Description Sampling Reason(s) for Loss/Exception CP Airborne; 09/02/03 This continuous air sampler was out of service Gross beta, Air for the sampling period of 08/26/03 through Particulate & 09/02/03. The sampler blew a fuse Air iodine- 131 approximately 30 minutes after being started.

Therefore, the sample volume was insufficient to meet the required analysis LLDs.

FE Airborne; 09/23/03 This continuous air sampler was out of service Air iodine- 131 for a portion of the sampling period 09/16/03 through 09/23/03 due to loss of power caused by Hurricane Isabel. The sample volume obtained was insufficient to meet the Iodine-131 LU).

HIR Airborne; 09/30/03 This continuous air sampler was out of service Gross beta and for the sampling period 09/23/03 through Gamma 09/30/03. The sampler and its housing isotopic, Air structure were damaged by Hurricane Isabel.

Particulate & Additionally, electric power was unavailable to Air iodine- 131 the sampler for an extended period of time.

Therefore, samples were not obtained during this period.

63

6. CONCLUSIONS The results of the 2003 Radiological Environmental Monitoring Program (REMP) for Surry Power Station have been presented in previous sections. This section presents conclusions for each pathway.

> Direct Radiation Exposure Pathway - Control and indicator location averages continue to indicate a steady relationship.

> Airborne Exposure Pathway - Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. Air particulate gross beta concentrations at all of the indicator locations for 2003 trend well with the control location.

The 2002 - 2003 average concentration trend is 26% higher than the average concentration trend from 1987 through 2003. This increase is primarily due to 2002 data. The contract laboratory Interlaboratory Comparison Program data for particulate filter gross beta analyses was closely reviewed and no issues were identified. For the 2002 - 2003 period, the average vendor gross beta analysis was within 1% of the spike sample activity. Gaseous effluent release data was also reviewed and determined not to be a factor as the long term trend of activity released continues to decline. Due to satisfactory vendor performance, good effluent management practices and because the gross beta activity in the control and indicator locations show no significant variation, the increased gross beta trend seen in 2002 is not attributable to the operation of Surry Power Station.

> Milk - Milk samples are an important indicator measuring the effect of radioactive iodine and radioisotopes in airborne releases. Cesium-137 and iodine-131 were not detected in any of the thirty-six samples. Naturally occurring potassium-40 was detected at a similar level when compared to the average of the previous year.

The maximum concentration of strontium-90 in this year's analysis was 4.6 pCi/L. Strontium-90 is not a part of station effluents, but rather, a product of nuclear weapons testing fallout.

> Food Products - As expected, naturally occurring potassium-40 was detected in all three samples. In the past, cesium-137 has occasionally been detected in these samples and is attributable to global fallout from past nuclear weapons testing. Cesium-137 and beryllium-7 were not detected in any of the three samples collected in 2003.

> Well Water - Well water samples were analyzed and the analyses indicated that there were no man-made radioisotopes present. This trend is consistent throughout the monitoring period. No radioactivity attributable to the operation of the station was identified.

64

> River Water - All river water samples were analyzed for gamma emitting radioisotopes. Naturally occurring potassium-40 was detected in several of the samples. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2003.

> Silt - Cesium-137 was detected in both the control and indicator samples.

The presence of Cs-137 is attributable to residual weapons testing fallout; its presence has been well documented. Cobalt-60 was detected in the indicator sample location; however, the long-term trend continues to reflect decreasing activity.

> Shoreline Sediment - Only naturally occurring radioisotopes were detected, at concentrations equivalent to normal background activities. There were no radioisotopes attributable to the operation of Surry Power Station found in any sample.

Aquatic Blota

> Fish - As expected, naturally occurring potassium-40 was detected in all four samples. There were no other gamma emitting radioisotopes detected in any of the fish samples.

> Oysters and Clams - Other than naturally occurring potassium-40 detected in some oysters, there were no other gamma emitting radioisotopes detected in any of the oyster or clam samples.

> Crabs - Naturally occurring potassium-40 was detected in the crab sample.

No other gamma emitting radioisotopes were detected.

65

REFERENCES 66

References

1. NUREG-0472, "Radiological Effluent Technical Specifications for PWRs",

Draft Rev. 3, March 1982.

2. 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.

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

December 1975.

4. United States Nuclear Regulatory Commission Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.

5. Dominion, Station Administrative Procedure, VPAP-2103S, "Offsite Dose Calculation Manual (Surry)".

6. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.

7. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.

8. NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.

67

APPENDICES 68

APPENDIX A: LAND USE CENSUS Year 2003 69

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January I to December 31, 2003 Page 1 of 1 l lI Nearest l Nearest Nearest Nearest

[ Sector Direction l Resident l Garden"* Cow I Goat A N 4.12 @ 80 (a) (a) (a)

B NNE 1.90 @ 340 1.90 @ 340 (a) (a)

C NE 4.60 @ 340 4.91 @ 560 (a) (a)

D ENE (a) 4.91 @ 560 (a) (a)

E E (a) (a) (a) (a)

F ESE (a) (a) (a) (a)

G SE (a) (a) (a) (a)

H SSE 4.44 @ 1600 5.00 @ 1600 (a) (a)

I S 1.69 @ 1820 2.05 @ 1830 (a) (a)

K SSW 1.87 @ 1930 4.26 @ 1950 4.84 @ 2010 (a)

L SW 2.28 @ 2220 3.65 @ 2240 (a) (a)

M WSW 2.82 @ 2430 3.57 @ 2460 (a) (a)

N W 3.15 @ 2600 4.14 @ 2690 (a) (a) p WNW 4.79 @ 2810 (a) (a) (a)

Q NW 4.84 @ 3190 (a) (a) (a)

R NNW 3.73 @ 3390 4.39 @ 3340 3.65 @ 3370 (a)

• Locations are listed by miles anddegrees heading relative to true northfrom center of Unit #1 Containment.

• • Area greaterthan 5O m2 and contains broadleafvegetation.

(a) None 70

APPENDIX B: DOMINION NUCLEAR CONNECTICUT QA PROGRAM YEAR 2003 71

INTRODUCTION Dominion Nuclear Connecticut (DNC) maintains an independent non-required quality assurance (QA) program as part of the radiological environmental monitoring program (REMP). TIhe QA program consists of contractor appraisals and quality control samples. This independent program is applicable to all Dominion nuclear facilities because they share a joint contract with Framatome ANP Environmental Laboratory.

DNC QA PROGRAM The DNC independent QA Program includes spikes of various sample media and duplicate samples. Sample spikes are a check on the accuracy of results of the contractor's radioanalyses. Duplicate samples test the contractor's precision, or reproducibility of results, by comparing analytical results of split samples. The number and type of DNC QA Program quality control samples are defined in Millstone Nuclear Power Station Health Physics Operations Procedure RPM 2.9.13, "Quality Control of Radiological Environmental Monitoring Program Sample Analyses". An investigation is conducted on any result or trend that does not satisfy acceptance criteria.

OTHER QA PROGRAMS The DNC Independent QA Program is not the only QA Program which monitors REMP radioanalysis performance. Other programs include:

1. Contractor lab's internal QA program. In addition to the Millstone quality control samples, the radioanalysis contractor has its own quality control samples.

In total, at least five percent of the contractor's sample analyses include quality control samples.

2. Contractor lab's interlaboratory comparison program with an independent third party, Analytics, Inc. Results of the Analytics intercomparison are contained in Appendix C. Primary contractor participation in an interlaboratory comparison program is required by station Technical Specifications. The Analytics comparison satisfies this requirement.

3. Contractor lab's participation in the National Institute of Standards and Technology (NIST) Measurement Assurance Program P(AP), the Environmental Resource Associates (ERA) Proficiency Test (P1) Program, the Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP). The lab participates in these interlaboratory QA programs because of other clients' needs, not because of nuclear power station environmental sample analyses. However, some of these intercomparison samples are also applicable to nuclear power environmental 72

samples.

RESULTS OF MILLSTONE QA PROGRAM FOR CON ACTOR RADIQANALYSES Criteria for passing QA sample analysis is that the result be within 20%/6 of the known spike except in the case of Sr-89 or Sr-90 spikes in milk which have to be within 300/%of the known spike. To allow more tolerance for lower activity spikes an alternate criterion may be used. If the two sigma error range of the analyzed result includes the known spike value, the result passes.

The Millstone QA Program indicated that the contractor lab's environmental radiological analysis program was adequate in 2003. Results are shown on Table

2. Of 101 individual nuclide analysis results on QA samples, 93 passed the acceptance criteria, a 92% success rate. Sample results, which did not pass criteria, failed because of problems with the spike source or with sample preparation. There were no failures in QA sample results associated with contractor lab analyses. The contractor laboratory is Framatome ANP DE&S Environmental Laboratory.

73

TABLE 1 2003 QUALITY CONTROL SAMPLES ROUTINE ..

S .,AMPL I SPLE SAMPLE (Note 1) ROUTINE M -- TYPE QC SAMPLES SAMPLES NfiLk - Strontium 2 (Note 2) 12 Milk - Iodine 4 36 Milk - Gamma (Note 3) 36 Water - Gamma 12 27 Water - Tritium 4 27 Fish/Invertebrate - Gamma 4 80 Vegetation/Aquatic Flora/Sediment/Soil - Gamma 0 81 Air Particulate -e Gross Beta 5 416

- Iodine 4 416

- Gamma 3 32 FOOTNOTES:

1. All samples are spikes except fishlinvertebrate which are duplicate oyster samples.

2. One sample with Sr-89 and Sr-90 and one sample with Sr-90 only.

3. Gammna in water QA spikes are treated as milk surrogates TABLE 2 RESULTS OF 2003 QUALITY CONTROL SAMPLE ANALYSES I SAMPLE ANALYSES IANALYSES TYPE PASSED FARLED Milk - Strontium* 3 0 Milk - Iodine 4 0 Water - Gamma* 58 4 Water - Tritium 3 1 Oysters - Gamma 4 0 Air Particulate Gross Beta 5 0 Iodine 3 Gamma 13 2 TOTALS Individual Nuclides: 93 Individual Nuclides: 8**

FOOTNOTE:

• Each nuclide was considered as an analysis fbr the strontium and gamma analyses.

• e There were no failures in QA sample results associated with contractor lab analyses. Sample results, which did not pass critera, failed because of problems with the spike source or with sample preparation.

74

APPENDIX C:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2003 75

INTR7ODUC7ION This appendix covers the Intercomparison Program of the Framatome ANP Environmental Laboratory. Framatome uses QA/QC samples provided by Analytics, Inc. to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP). The suite of Analytics QA/QC samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides. It was modified to more closely match the media mix presently being processed by Framatome and includes:

> milk for gamma (10 nuclides) and low-level (LL) iodine-131 analyses once per quarter,

> milk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,

> water for gamma (10 nuclides), low-level (LL) iodine-131, and gross beta analyses during the 1st and 3rd quarters,

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

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

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

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

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

In addition to the Analytics Intercomparison Program, Framatome also participates in other intercomparison programs. These programs are the National Institute of Standards and Technology (NISI) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (PT)

Program, the Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP).

RESULTS Intercomparison program results are evaluated using Framatome's internal bias acceptance criteria as defined below:

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

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

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

> within two sigma of the known value.

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

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

76

FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION I 1 II IRatio Sample Quarterl Sample Reported Known Framatome Number Year , Media Nuclide Units Values Values Analytics Evaluation E3597-162 1sV03 Water Gross Alpha pCiVL 55 61 0.90 Agreement E3597-162 1st03 Water Gross Beta pCi/L 146 186 0.78 Agreement E3598-162 1st/03 Water 1-131 pCi/L 68 70 0.97 Agreement E3598-162 lstV03 Water 1-1 31 LL pCi/L 68 70 0.97 Agreement E3598-162 lst/03 Water Ce-141 pCi/L 163 168 0.97 Agreement E3598-162 1st/03 Water Cr-51 pCi/L 243 238 1.02 Agreement E3598-162 1st/03 Water Cs-134 pCi/L 83 88 0.94 Agreement E3598-162 1st/03 Water Cs-137 pCi/L 188 195 0.96 Agreement E3598-163 lstV03 Water Co-58 pCiIL 44 42 1.05 Agreement E3598-162 lstV03 Water Mn-54 pCiAL 61 63 0.97 Agreement E3598-162 1st/03 Water Fe-59 pCiVL 48 46 1.04 Agreement E3598-162 1stV03 Water Zn-65 pCUL 88 90 0.98 Agreement E3598-162 1sV03 Water Co-60 pCiVL 156 157 0.99 Agreement E3599-162 1st03 Filter Gross Alpha pCi 52 49 1.06 Agreement E3599-162 1st03 Filter Gross Beta pCi 157 148 1.06 Agreement E3600-162 1st/03 Milk 1-131 pCi/L 73 74 0.99 Agreement E3600-162 1st03 Milk 1-1 31 LL pCi/L 73 74 0.99 Agreement E3600-162 1stV03 Milk Ce-141 pCi/L 170 173 0.98 Agreement E3600-162 lstV03 Milk Cr-51 pCi/L 244 246 0.99 Agreement E3600-162 lsV03 Milk Cs-1 34 pCi/L 86 90 0.96 Agreement E3600-162 1stV03 Milk Cs-137 pCi/L 196 200 0.98 Agreement E3600-163 lstV04 Milk Co-58 pCi/L 44 47 0.94 Agreement E3600-162 1st03 Milk Mn-54 pCi/L 61 64 0.95 Agreement E3600-162 1sV03 Milk Fe-59 pCi/L 47 47 1.00 Agreement E3600-162 1st03 Milk Zn-65 pCVL 96 93 1.03 Agreement E3600-162 lsV03 Milk Co-60 pCi/L 162 162 1.00 Agreement E3601-162 1st03 Milk Sr-89 pCiL 121 133 0.91 Agreement E3601 -162 IsVt03 Milk Sr-90 pCi/L 13 12 1.08 Agreement E3608-162 sVt/03 Water Sr-89 pCi/L 104 114 0.91 Agreement E3608-162 1sVt03 Water Sr-90 PCi/L 11 10 1.10 Agreement 77

FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known Framatorne/

Number Year Media Nuclide Units Values Values Analytics Evaluation E3704-162 2nd/03 Water H-3 pCUL 10643 11953 0.89 Agreement E3705-162 2nd/03 Filter Gross Alpha pCiUL 20 21 0.95 Agreement E3705-162 2nd/03 Filter Gross Beta pCUL 116 115 1.01 Agreement E3706-162 2nd/03 Filter Ce-141 pCi/Filter 149 154 0.97 Agreement E3706-162 2nd/03 Filter Cr-51 pCi/Filter 134 130 1.03 Agreement E3706-162 2nd/03 Filter Cs-1 34 pCi/Filter 54 56 0.96 Agreement E3706-162 2ndl03 Filter Cs-137 pCi/Filter 135 125 1.08 Agreement E3706-162 2nd/03 Filter Co-58 pCi/Filter 53 50 1.06 Agreement E3706-162 2nd/03 Filter Mn-54 pCi/Filter 110 101 1.09 Agreement E3706-162 2nd/03 Filter Fe-59 pCVFilter 60 54 1.11 Agreement E3706-162 2nd/03 Filter Zn-65 pCV/Filter 110 99 1.11 Agreement E3706-162 2ndlO3 Filter Co-60 pCi/Filter 71 72 0.99 Agreement E3707-162 2ndlO3 Filter Sr-89 pCi/Filter 78 87 0.90 Agreement E3707-162 2nd/03 Filter Sr-90 pCi/Filter 24 24 1.00 Agreement E3708-162 2nd/03 Milk 1-131 pCUL 109 103 1.06 Agreement E3708-162 2nd/03 Milk 1-131LL pCUL 104 103 1.01 Agreement E3708-162 2nd/03 Milk Ce-141 pCi/L 283 283 1.00 Agreement E3708-162 2nd/03 Milk Cr-51 pCUL 239 239 1.00 Agreement E3708-162 2ndlO3 Milk Cs-134 pCU/L 98 103 0.95 Agreement E3708-162 2nd/03 Milk Cs-1 37 pCU/L 232 230 1.01 Agreement E3708-162 2nd/03 Milk Co-58 pCUL 92 93 0.99 Agreement E3708-162 2nd/03 Milk Mn-54 pCUL 186 186 1.00 Agreement E3708-162 2nd/03 Milk Fe-59 pCU/L 100 99 1.01 Agreement E3708-162 2nd/03 Milk Zn-65 pCI/L 181 181 1.00 Agreement E3708-162 2ndlO3 Milk Co-60 pCI/L 134 132 1.02 Agreement 78

FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM lPERFORMANCE EVALUATION I Ratio Sample Quarterl Sample Reported Known Framatome/

Number Year Media Nuclide Units Values Values Analytics; Evaluation E3866-162 3rd/03 Water Gross Alpha pCi/L 37 36 1.03 Agreement E3866-162 3rd/03 Water Gross Beta pCi/L 264 246 1.07 Agreement E3867-162 3rd/03 Water 1-131 pCi/L 69 76 0.91 Agreement E3867-162 3rd/03 Water 1-131 LL pCi/L 78 76 1.03 Agreement E3867-162 3rd/03 Water Ce-141 pCi/L 78 81 0.96 Agreement E3867-162 3rd/03 Water Cr-51 pCi/L 198 221 0.90 Agreement E3867-162 3rd/03 Water Cs-134 pCi/L 108 113 0.96 Agreement E3867-162 3rd/03 Water Cs-137 pCi/L 85 84 1.01 Agreement E3867-162 3rd/03 Water Co-58 pCi/L 92 94 0.98 Agreement E3867-162 3rd/03 Water Mn-54 pCUL 93 88 1.06 Agreement E3867-162 3rd/03 Water Fe-59 pCUL 74 75 0.99 Agreement E3867-162 3rd/03 Water Zn-65 pCi/L 170 166 1.02 Agreement E3867-162 3rd/03 Water Co-60 pCiVL 118 117 1.01 Agreement E3868-162 3rd/03 Filter Gross Alpha pci 30 28 1.07 Agreement E3868-162 3rd/03 Filter Gross Beta pC! 197 189 1.04 Agreement E3869-162 3rd/03 Milk 1-131 pCi/L 66 74 0.89 Agreement E3869-162 3rd/03 Milk I-1 31 LL pCi/L 74 74 1.00 Agreement E3869-162 3rd/03 Milk Ce-141 pCi/L 90 86 1.05 Agreement E3869-162 3rd/03 Milk Cr-51 pCVL 228 233 0.98 Agreement E3869-162 3rd/03 Milk Cs-134 pCVL 123 119 1.03 Agreement E3869-162 3rd/03 Milk Cs-1 37 pCVL 94 88 1.07 Agreement E3869-162 3rd/03 Milk Co-58 pCVL 99 99 1.00 Agreement E3869-162 3rd/03 Milk Mn-54 pCV/L 101 93 1.09 Agreement E3869-162 3rdJ03 Milk Fe-59 pCVL 84 79 1.06 Agreement E3869-162 3rd/03 Milk Zn-65 pCV/L 178 176 1.01 Agreement E3869-162 3rd/03 Milk Co-60 pCVL 129 123 1.05 Agreement E3870-162 3rd/03 Milk Sr-89 pCi/L 80 100 0.80 Agreement E3870-162 3rd/03 Milk Sr-90 pCV/L 11 14 0.79 Agreement 79

FRAMATOME ANP 2003 ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM lPERFORMANCE EVALUATION PEFRACEAUTO Sample Quarter/ Sample Reported Known Framatomel Number Year Media Nuclide Units Values Values Analytics Evaluation E3937-162 4th/03 Water H-3 pCi/L 2307 2290 1.01 Agreement E3938-162 4th/03 Water Sr-89 pCi/L 99 100 0.99 Agreement E3938-162 4th/03 Water Sr-90 pCi/L 11 10 1.10 Agreement E3939-162 4th/03 Filter Gross Beta pCi 50 43 1.16 Agreement E3940-162 4th/03 Filter Ce-141 pci 110 100 1.10 Agreement E3940-162 4thW03 Filter Cr-51 pC! 171 153 1.12 Agreement E3940-162 4thW03 Filter Cs-134 pC! 75 74 1.01 Agreement E3940-162 4th/03 Filter Cs-137 pC! 75 71 1.06 Agreement E3940-162 4thW03 Filter Co-58 pci 64 61 1.05 Agreement E3940-162 4th/03 Filter Mn-54 pci 103 95 1.08 Agreement E3940-162 4th/03 Filter Fe-59 pci 64 56 1.14 Agreement E3940-162 4thW03 Filter Zn-65 pci 117 108 1.08 Agreement E3940-162 4thW03 Filter Co-60 pci 82 85 0.96 Agreement E3941 -162 4thW03 Filter Sr-90 pci 11 11 1.00 Agreement E3942-162 4th/03 Milk 1-131 pCi/L 84 90 0.93 Agreement E3942-162 4t03 Milk 1-131LL pCi/L 91 90 1.01 Agreement E3942-162 4thW03 Milk Ce-141 pCi/L 191 202 0.95 Agreement E3942-162 4thl03 Milk Cr-51 pCi/L 275 280 0.98 Agreement E3942-162 4thW03 Milk Cs-134 pCi/L 135 135 1.00 Agreement E3942-162 4th/03 Milk Cs-137 pCi/L 126 129 0.98 Agreement E3942-162 4th/03 Milk Co-58 pCi/L 107 111 0.96 Agreement E3942-162 4thW03 Milk Mn-54 pCi/L 173 173 1.00 Agreement E3942-162 4th/03 Milk Fe-59 pCl/L 106 102 1.04 Agreement E3942-162 4th/03 Milk Zn-65 pCVL 203 197 1.03 Agreement E3942-162 4th/03 Milk Co-60 pCVL 148 155 0.95 Agreement 80