Text

Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report
	ML031270721
Person / Time
Site:	Surry, 07200002
Issue date:	04/29/2003
From:	Blount R; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	-RFPFR, 03-306, SS&L/BAG
	Download: ML031270721 (100)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 29, 2003 United States Nuclear Regulatory Commission Serial No.03-306 Attention: Document Control Desk SS&UBAG 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 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 Radiological Environmental Operating Report for the period of January 1, 2002 through December 31, 2002 which includes environmental monitoring for the Surry ISFSI.

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

Richard H. Blount, Site Vice President Surry Power Station Attachment Commitments made in this letter: None 693l)

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 R. A. Musser NRC Senior Resident Inspector Surry Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23219

ATTACHMENT 2002 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

Surry Power Station 2002 Annual Radiological Environmental Operating Report

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Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2002 to December 31, 2002 Prepared by Dominion Surry Power Station and Dominion Nuclear Connecticut

Annual Radiological Environmental Operating Report Surry Power Station January 1, 2002 to December 31, 2002 Prepared by:

</ IV-J.

. Eakin ervisor Radiological Engineering Dominion Nuclear Connecticut Prepared by:

P. F. Blount Health Physicist Dominion Surry Power Station Reviewed by: 4+~ B.i A.wHiltSS Supervisor Radiological Analysis and Material Control Dominion Surry Power Station Reviewed by:

D. K. Miller Supervisor Health Physics Technical Services Dominion Surry Power Station Approved by: f- ~J~ L-i7 T. F. Steed Manager Radiological Protection Dominion Surry Power Station 2

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

1. EXECUTIVE

SUMMARY

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

2. PROGRAM DESCRIPTION .................................................................... 8 2.1 Introduction .................................................................... 8 2.2 Sampling and Analysis Program .................................................................... 9

3. ANALYTICAL RESULTS .................................................................. 21 3.1 Summary of Results ................................................................... 21 3.2 Analytical Results of 2002 REMP Samples ................................................................... 30

4. DISCUSSION OF RESULTS .................................................................. 57 4.1 Gamma Exposure Rate .................................................................. 57 4.2 Airborne Gross Beta .................................................................. 58 4.3 Airborne Radioiodine .................................................................. 60 4.4 Air Particulate Gamma ................................................................... 60 4.5 Cow Milk ................................................................... 60 4.6 Food Products .................................................................. 61 4.7 Well Water .................................................................. 61 4.8 River Water .................................................................. 61 4.9 Silt .................................................................. 61 4.10 Shoreline Sediment .................................................................. 63 4.11 Fish .................................................................... 63 4.12 Oysters .................................................................... 64 4.13 Clam s ................................................................... 64 4.14 Crabs ................................................................... 64

5. PROGRAM EXCEPTIONS ................................................................... 65

6. CONCLUSIONS ................................................................... 66 REFERENCES .................................................................. 68 APPENDICES ................................................................... 70 APPENDIX A: LAND USE CENSUS ................................................................... 71 APPENDIX B: DOMINION NUCLEAR CONNECTICUT QUALITY ASSURANCE PROGRAM ................................................................... 73 APPENDIX C:

SUMMARY

OF INTERLABORATORY COMPARISONS ............................... 77 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.

4

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2002 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2002, 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.

The 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 is 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 DE&S Environmental Laboratory provides radioanalyses for this program and 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 5

level for certain radionuclides. Licensed nuclear facilities must report the radionuclide activities 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. The 2002 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. The cobalt-60 was detected at the indicator location. 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 2002 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. A ten-year activity trend continues to indicate the slow decrease in Sr-90 activity. Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels. No man-made radioisotopes were detected in food product samples. Consistent with historical data, potassium-40 was detected. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained relatively constant over the years.

During 2002, 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 2002 was 0.0004 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 6

but also demonstrate the adequacy of radioactive effluent control at Surry Power Station.

7

2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2002 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 861 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 (ALARA). 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. ICN Biomedicals is responsible for processing the TLDs. The Framatome ANP DE&S 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-2 103S, Offsite Dose Calculation Manual (Surry).

These concentrations are based upon the annual dose commitment recommended 8

by 10CFR50, Appendix I, to meet the criterion of "As Low as is Reasonably Achievable."

This report documents the results of the Radiological Environmental Monitoring Program for 2002 and satisfies the following objectives of the program:

> 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 andAnalysis Program Table 2-1 summarizes the 2002 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." The Surry 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 DE&S Environmental Laboratory for Surry Power Station during the year 2002.

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 DE&S Environmental Laboratory, located in Westborough, MA, for analysis. The TLDs are shipped to ICN Biomedicals, located in Costa Mesa, CA, for processing.

9

I I I I I I I I I I I I I I I I Table 2-1 SURRY - 2002 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Control (00) Quarterly Onsite (Stored in leadcontaineroutsideprotectedarea)

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 (I 1) 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 10

I I I I Il I I I I I I Il l l l l l Table 2-1 SURRY - 2002 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) 7.10 mi 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 Population Center Newport News (38) 16.50 mi ESE 1220 Quarterly Population Center James River Bridge (39) 14.80 mi SSE 1470 Quarterly Control Location Benn's Church (40) 14.50 mi S 1750 Quarterly Control Location Smithfield (41) 11.50mi 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 (HIR) 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 (HIR) 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 11

I I I I I I I I I I I I I I I I I I I Table 2-1 SURRY - 2002 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Milk Colonial Parkway (CP) 3.70 mi NNW 3370 Monthly Pivarnik (PIV) 17.60 mi NNE 250 Monthly Control Location Epp's (EPPS) 4.80 mi SSW 2010 Monthly Oysters Point of Shoals (POS) 6.40 mi SSE 157° 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 (HIP) 2.40 mi NE 520 Semi-Annually Lawne's Creek (LC) 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 Fann (BROCK'S) 3.80 mi S 1880 Annually (Corn, Peanuts, Slade's Farm (SLADE'S) 2.40 mi S 1770 Annually Soybeans) 12

Table 2-2 (Page of 3)

SURRY - 2002 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2 mR/Std. Month Dosimetry (TLD)

Air Iodine Weekly I-131 0.07 pCi/m3 Air Particulate Weekly Gross Beta 0.01 pCi/m3 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 1-131 10 pCi/L Gamma Isotopic 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 pCi/L I-131 1 Gamma Isotopic 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 located at end of table.

13

Table 2-2 (Cont.)

(Page 2 of 3)

SURRY - 2002 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 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 - 2002 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-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Annually Gamma Isotopic pCi/kg - wet I-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 that the environmental samples should be analyzed to, in accordancewith the Surry Radiological EnvironmentalMonitoringProgram. Actual analysis ofthe samples by the Framatomelaboratory may be lower than those LLD values listed.

(a) Quarterly composites of each location 's weekly airparticulatesamples are analyzedfor gamma emitters.

15

I I I I I I I I I I I I I I I I I I I

[.111 Ifl inI' I i'fl :ti. I [a] [ala j [af;J a a a e rJ CO)

I I I I I I I I I I I I I I I I I I I C83308

I I 1 1 I I I I I I 1 1 I I I I I I I Figure 3. Surry Emergency Plan Map

Air Sampling Stations

Nearest Residents

TLD Sampling

Nearest Milk Animal

Nearest Garden 9 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

I I I I I I I I I I I I I I I I I I I Figure 4. Surry Emergency Plan Map

Air Sampling Stations

Nearest Residents

TLD Sampling

Nearest Milk Animal

Nearest Garden

Aquatic Samples OriginalO 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, CB3310 cO

I I 1 I I I I I I I I I I I I I I I 1 Figure 5. Surry Emergency Plan Map

Air Sampling Stations

Nearest Residents

TLD Sampling

Nearest Milk Animal

Nearest Garden

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.

,- + A ,7,,,,,,;'s,,wt CB3307A Co5

3. ANALYTICAL RESULTS 3.1 Summary ofResults 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.

21

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 1 of 8

_ All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-

[ (Unit) No. _I Range Direction Range Range ments Air lodine 1-131 416 0.07 < LLD N/A < LLD < LLD 0 3

(pCi/m )

Air Gross 416 10 24.6(364/364) ALL 5.1 mi. 26.2(52/52) 24.9(52/52) 0 Particulate Beta (8.9-79.7) WSW (8.9-41.3) (9.946.2)

(1E-3 pCi/m 3)

Gamma 32 Be-7 32 87(28/28) NN 16.5 mi. 98(4/4) 98(4/4) 0 (47-141) ESE (55-120) (55-120)

Cs-134 32 50 < LLD N/A < LLD < LLD 0 Cs-137 32 60 < LLD N/A < LLD < LLD 0 River Gamma 24 Water (pCi/Liter) K-40 24 122(10/12) SD 0.17 mi. 122(10/12) 88(6/12) 0 (59-155) NW (59-155) (36-135)

Th-228 24 < LLD N/A < LLD < LLD 0 1-131 24 10 < LLD N/A < LLD < LLD 0 Mn-54 24 15 < LLD N/A < LLD < LLD 0 Fe-59 24 30 < LLD N/A < LLD < LLD 0 Co-58 24 15 < LLD N/A < LLD < LLD 0 Co-60 24 15 < LLD N/A < LLD < LLD 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.

22

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Sury Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 2 of 8 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments River Gamma 24 Water (pCi/Liter) Zn-65 24 30 < LLD N/A < LLD < LLD 0 Zr-95 24 30 < LLD N/A < LLD < LLD 0 Nb-95 24 15 < LLD N/A < LLD < LLD 0 Cs-134 24 15 < LLD N/A < LLD < LLD 0 Cs-137 24 18 < LLD N/A < LLD < LLD 0 Ba-140 24 60 < LLD N/A < LLD < LLD 0 La-140 24 15 < LLD N/A < LLD < LLD 0 Tritium H-3 8 2000 < LLD N/A < LLD < LLD 0 Well Gamma 8 Water (pCi/Liter) 1-131 8 1 < LLD N/A < LLD N/A 0 Mn-54 8 15 < LLD N/A < LLD N/A 0 Fe-59 8 30 < LLD N/A < LLD N/A 0 Co-58 8 15 < LLD N/A < 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.

23

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 3 of 8 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments Well Gamma 8 Water (pCi/Liter) Co-60 8 15 < LLD N/A < LLD N/A 0 Zn-65 8 30 < LLD N/A < LLD N/A 0 Zr-95 8 30 < LLD N/A < LLD N/A 0 Nb-95 8 15 < LLD N/A < LLD N/A 0 Cs-134 8 15 < LLD N/A < LLD N/A 0 Cs-137 8 18 < LLD N/A < LLD N/A 0 Ba-140 8 60 < LLD N/A < LLD N/A 0 La-140 8 15 < LLD NJA < LLD N/A 0 Tritium H-3 8 2000 < LLD N/A < LLD N/A 0 Silt Gamma 4 (pCi/kg dry)

K-40 4 15785(2/2) CHIC 11.2 mi. 17335(2/2) 17335(2/2) 0 (13770-17800) WNW (17170-17500) (17170-17500)

Th-228 4 975(2/2) CHIC 11.2 mi. 1215(2/2) 1215(2/2) 0 (959-990) WNW (1150-1280) (1150-1280)

Cs-134 4 150 < LLD N/A < LLD < LLD 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

Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 4 of 8 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. I Range Direction Range Range ments Silt Gamma 4 (pCi/kg dry) Cs-137 4 180 286(2/2) SD 1.3 mi. 286(2/2) 224(2/2) 0 (259-313) NNW (259-313) (212-236)

Co-60 4 53(2/2) SD 1.3 mi. 53(2/2) < LLD 0 (38-67) NNW (38-67)

Shoreline Gamma 4 Sediment (pCi/kg dry) K-40 4 7865(2/2) HIR 0.8 mi. 7865(2/2) 1025(2/2) 0 (6780-8950) N (6780-8950) (970-1080)

Th-228 4 127(2/2) CHIC 11.2 mi. 666(2/2) 666(2/2) 0 (116-138) WNW (131-1200) (131-1200)

Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 < LLD N/A < LLD < LLD 0 Milk Gamma 36 (pCi/Liter) K-40 36 1392(24/24) CP 3.7 mi. 1398(12/12) 1324(12/12) 0 (1240-1520) NNW (1240-1520) (1037-1770) 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 Strontium Sr-89 4 < LLD N/A < LLD N/A 0 Sr-90 4 1.95(3/4) CP 3.7 mi. 1.95(3/4) N/A 0 (1.52-2.5) NNW (1.52-2.5)

LLDis the Lower Umit of Detection as defined 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

Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 5 of 8 All Indicator Control Non-Medium or Pathway Sampled Anal sis Type Total LLD*

r Locations Mean Location with Highest Mean Name Distance Mean Location Mean Routine Reported Measure-(Unit) No. Range Direction Range Range ments Milk Gamma 36 (pCi/Liter) Ba-140 36 60 < LLD N/A < LLD < LLD 0 La-140 36 15 < LLD N/A < LLD < LLD Clams Gamma 8 (pCi/kg wet) K-40 8 733(4/6) HIP 2.4 mi. 840(1/2) 620(1/2)

(480-1090) NE Mn-54 8 130 < LLD N/A < LLD < LLD Fe-59 8 260 < LLD N/A < LLD < LLD Co-58 8 130 < LLD N/A < LLD < LLD Co-60 8 130 < LLD N/A < LLD < LLD Zn-65 8 260 < LLD N/A < LLD < LLD Cs-134 8 130 < LLD N/A < LLD < LLD Cs-137 8 150 < LLD N/A < LLD < LLD Oysters Gamma 4 (pCi/kg wet) K-40 4 817(3/4) POS 6.4 mi. 930(2/2) N/A (590-970) SSE (890-970)

Mn-54 4 130 < LLD N/A < LLD N/A a Fe-59 4 260 < LLD N/A < LLD N/A c

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 6 of 8 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments Oysters Gamma 4 (pCi/kg wet) Co-58 4 130 <LLD N/A <LLD N/A 0 Co-60 4 130 <LLD N/A < LLD N/A 0 Zn-65 260 <LLD N/A < LLD N/A 0 Cs-1 34 130 < LLD N/A < LLD N/A 0 Cs-1 37 150 <LLD N/A < LLD N/A 0 Crabs Gamma (pCi/kg wet) K-40 1560(1/1) SD 1.3 mi. 1560(1/1) N/A NNW Mn-54 130 < LLD N/A < LLD N/A Fe-59 260 < LLD N/A < LLD N/A Co-58 130 < LLD N/A < LLD N/A Co-60 130 <LLD N/A <LLD N/A Zn-65 260 < LLD N/A < LLD N/A Cs-1 34 130 < LLD N/A < LLD N/A Cs-137 150 < LLD N/A < LLD N/A

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.

27

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 7 of 8 All Indicator Control Non-Medium or Anal sis Locations Location with ighest Mean Location Routine Pathway Reported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments Fish Gamma (pCi/kg wet) K-40 2413(4/4) SD 1.3 mi. 2413(4/4) N/A (2200-2570) NNW (2200-2570)

Mn-54 130 < LLD N/A < LLD N/A Fe-59 260 < LLD N/A < LLD N/A Co-58 130 < LLD N/A < LLD N/A Co-60 130 <LLD N/A <LLD N/A Zn-65 260 < LLD N/A < LLD N/A Cs-1 34 130 < LLD N/A < LLD N/A Cs-1 37 150 < LLD N/A < LLD N/A Food Gamma Products K-40 8433(313) Brock's 3.8 mi. 8433(3/3) N/A (pCi/kg wet) (3310-15610) Farm S (3310-15610) 1-131 60 <LLD N/A <LLD N/A Cs-1 34 60 < LLD N/A < LLD N/A Cs-137 80 < LLD N/A < LLD N/A

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.

28

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Sury County, Virginia - 2002 Docket No. 5-280-281 Page 8 of 8 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway IReported Sampled Type Total LLD* Mean Name Distance Mean Mean Measure-(Unit) No. Range Direction Range Range ments Direct Gamma 168 2 2.9(156/156) STA-38 16.5 mi. 5.4(4/4) 3.8(12/12) 0 Radiation (0.9-5.9) ESE (4.5-5.9) (1.4-6.6)

TLD (mR/

Std.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.

29

3.2 Analytical Results of 2002 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 2cs error (i.e., the measured value exceeds 3cr).

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 DE&S's 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 I- 131

4. Air Particulates, Quantitative Gamma Spectra

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 handledas recommended by HASL ("Reporting ofAnalytical Results from HASL," letter by Leo B. Higginbotham) and NUREGICR-4007 (Sept. 1984).

30

SURRY 2002 TABLE 3-2 QUARTERLY GAMMA EXPOSURE RATE (MR/STD MONTH +/- 2 SIGMA)

L O C A T I O N S PERIOD 02 03 04 05 06 07 08 09 10 11 12 1Q 4.9 0.5 4.7 0.4 3.4 0.3 3.8 0.7 4.3 0.2 3.3 0.3 3.3 0.3 3.6 0.6 3.4 0.4 3.4 0.5 4.1 0.9 2Q 4.1 0.4 3.1 1.3 2.1 2.5 3.7 0.8 3.4 0.9 2.3 0.4 3.0 0.4 2.5 1.1 1.9 0.2 3.0 0.4 2.4 1.0 3Q 4.8 0.5 4.3 0.6 2.8 1.6 2.4 0.9 3.3 0.9 3.9 1.2 3.2 0.5 2.3 1.5 2.8 0.5 3.3 2.0 2.8 0.4 4Q 5.0 0.5 5.1 0.2 4.1 0.6 4.0 0.4 4.7 0.5 3.6 0.3 3.3 0.3 3.7 0.3 3.3 0.6 3.7 0.4 3.8 0.1 PERIOD 13 14 15 16 17 18 19 20 21 22 23 1Q 3.9 0.8 4.2 1.0 3.1 0.7 3.6 0.4 2.4 0.5 1.8 0.5 2.5 0.5 2.7 0.4 2.3 1.1 1.8 1.3 3.3 1.3 2Q 3.2 0.2 3.7 0.4 2.1 1.5 3.1 0.8 2.3 0.6 1.0 0.9 2.4 0.2 2.1 0.6 2.6 0.6 1.7 1.6 2.6 1.1 3Q 2.6 0.7 3.0 0.7 2.4 0.2 2.3 1.9 2.6 0.6 1.7 0.7 1.6 0.3 1.7 1.5 2.3 1.3 1.0 0.7 2.2 0.8 4Q 4.1 0.3 4.6 0.4 3.5 0.5 3.5 0.5 3.2 0.4 2.2 0.2 2.7 0.2 2.9 0.1 2.8 0.4 2.3 0.7 4.4 0.5 PERIOD 24 25 26 27 28 29 30 31 32 33 34 lQ 2.9 0.5 3.2 0.8 2.7 0.2 2.9 1.4 2.7 0.7 2.6 1.0 2.7 0.5 1.6 1.0 2.8 0.2 2.9 0.2 3.1 0.3 2Q 2.0 0.8 1.8 0.6 1.6 0.3 1.4 0.3 1.7 0.5 0.9 0.2 1.7 1.2 1.7 0.5 1.4 0.1 2.3 1.2 2.3 0.4 3Q 1.9 0.3 2.8 1.0 1.9 0.3 1.4 1.1 1.6 0.4 1.3 2.3 2.3 0.8 1.7 1.1 2.3 1.0 2.1 0.5 2.8 0.8 4Q 3.3 0.3 3.5 0.6 3.1 0.5 2.8 0.8 3.0 0.9 2.6 0.3 2.8 0.4 2.2 0.3 3.1 0.6 2.9 1.2 3.5 0.2 PERIOD 35 36 37 38 39C 40C 41C 42 43 1Q 4.3 0.5 5.0 0.9 3.4 1.2 5.9 0.6 2.7 0.4 3.6 0.5 6.6 1.2 2.9 0.4 2.7 0.4 2Q 2.4 0.3 2.9 1.1 2.7 0.4 5.1 0.4 2.0 1.0 3.1 0.2 5.3 0.6 2.1 0.6 1.7 1.0 3Q 3.1 1.1 2.9 1.7 2.0 2.2 4.5 0.6 1.4 1.0 2.5 0.6 5.3 0.7 2.3 0.6 1.8 0.6 4Q 4.0 0.4 4.5 0.4 2.7 0.9 5.9 0.6 2.9 0.2 3.6 0.3 6.6 0.8 3.0 0.4 3.0 0.5 31

l l I I I I I II I I II I I I I I SURRY 2002 TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (lE-3 PCI/M3)

L O C A T IO N S PERIOD ENDING SS HIR BC ALL CP BASF FE NN-C

(+/-) (+/-) (/ ) (/ ) (3/1)

JAN 09 26.6 3.1 27.4 3.1 28.1 3.1 41.3 3.7 27.4 3.2 29.6 3.1 30.8 3.2 26.3 3.1 JAN 15 23.9 3.0 24.0 3.0 27.2 3.1 32.3 3.2 26.5 3 .1 27.2 3.1 28.3 3.2 27.3 3.1 JAN 22 30.1 3.1 30.5 3.1 28.9 3.1 35.0 3.2 35.4 3.3 35.2 3.2 35.4 3.2 31.1 3.3 JAN 29 14.4 2.8 18.1 2.9 19.6 2.9 20.5 3.0 19.4 3.0 21.4 3.0 22.0 3.0 20.9 3.0 FEB 05 20.6 2.5 25.9 2.7 21.1 2.5 26.0 2.7 24.4 2.7 24.4 2.7 25.4 2.7 23.7 2.7 FEB 12 20.5 2.9 20.9 2.9 22.2 2.9 24.3 2.9 24.2 3.1 22.8 2.9 24.9 3.0 23.9 3.0 FEB 19 18.8 2.6 20.7 2.6 21.4 2.6 25.8 2.7 21.4 2.7 23.8 2.7 22.0 2.7 23.3 2.7 FEB 26 23.3 2.8 25.5 2.5 A 23.0 2.7 29.9 3.0 24.9 2.8 28.1 2.9 24.2 2.8 24.1 2.8 MAR 05 18.6 2.8 22.1 3.4 21.2 2.9 27.1 3.0 24.4 3.0 19.5 2.8 21.8 2.9 25.6 3.1 MAR 12 27.9 2.7 28.9 2.8 30.2 2.8 33.2 2.8 29.1 2.8 30.5 2.8 55.0 12.0 B 27.4 2.8 MAR 20 17.1 2.2 16.4 2.1 19.3 2.2 21.7 2.3 18.0 2.2 18.5 2.2 16.0 2.1 18.9 2.2 MAR 26 26.1 3.8 25.8 3.7 27.2 3.7 33.6 3.9 25.6 3.7 27.8 3.7 29.7 3.9 25.9 3.7 APR 02 17.4 2.4 19.8 2.6 17.6 2.4 24.8 2.6 22.7 2.6 21.7 2.6 18.8 2.5 19.8 2.5 APR 09 20.8 2.4 32.3 6.8 C 20.3 2.4 29.1 2.7 22.6 2.5 21.3 2.4 25.6 2.6 24.2 2.5 APR 16 15.0 2.3 18.3 2.4 16.7 2.4 24.0 2.6 17.3 2.4 14.8 2.3 18.4 2.4 14.2 2.3 APR 23 18.5 2.5 23.3 2.6 21.5 2.6 22.1 2.6 19.0 2.5 18.5 2.5 21.3 2.6 21.5 2.6 APR 30 21.6 2.7 23.3 2.8 21.0 2.7 23. 3 2.7 15.8 2.6 21.1 2.7 22.4 2.8 19.7 2.7 MAY 06 19.2 3.0 20.6 3.1 20.0 3.1 20.6 3.1 20.6 3 .3 21.0 3.1 22.2 3.1 18.0 3.0 MAY 14 17.8 2.3 25.2 2.5 22.4 2.5 28.7 2.7 29.8 2.6 22.2 2.4 23.7 2.5 23.0 2.4 MAY 21 21.0 2.4 22.9 2.5 20.2 2.4 25.3 2.6 22.3 2.5 20.3 2.4 26.1 2.6 19.9 2.4 MAY 29 22.5 2.4 24.9 2.4 21.0 2.3 24.0 2.4 25.9 2.5 22.6 2.3 22.8 2.3 19.0 2.2 JUN 04 18.2 2.5 20.9 2.6 18.9 2.6 22.7 2.7 22.4 2.6 21.4 2.7 24.2 2.8 25.6 2.8 JUN 11 18.6 2.4 32.3 3.7 25.3 2.6 24.3 2.5 31.3 3.7 21.8 2.5 21.5 2.5 25.7 2.6 JUN 18 19.2 2.7 24.0 2.9 26.4 2.9 39.2 4.4 22.3 1.8 23.2 2.8 18.6 2.7 27.1 2.9 JUN 25 31.4 5.8 D 24.8 2.8 24.4 2.8 20.2 2.7 19.9 2.7 17.8 2.6 18.4 2.7 21.3 2.8 32

I I I I I I I II I I I I I I I I SURRY 2002 TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (1E-3 PCI/M3)

L O C A T I O N S PERIOD ENDING SS HIR BC ALL CP BASF FE NN-C

(+/-)

JUL 02 16.3 2.2 19.0 2.3 22.0 2.5 20.6 2.4 18.9 2.3 18.4 2.3 19.1 2.3 20.2 2.4 JUL 09 35.1 3.4 30.7 3.0 42.7 3.7 30.4 3.0 35. 0 3.2 31.4 3.0 33.5 3.3 36.8 3.5 JUL 16 15.1 2.4 15.3 2.4 13.2 2.3 12.2 2.3 16.3 2.4 12.9 2.3 13.8 2.4 13.3 2.3 JUL 23 40.2 3.4 38.7 3.1 39.4 3.7 38.9 3.2 37.1 3.1 39.0 3.2 36.0 3.1 37.5 3.8 JUL 30 21.8 3.1 23.2 3.2 23.1 3.1 21.6 3.1 21.2 3.1 18.6 3.0 22.8 3.1 22.6 3.2 AUG 06 29.9 3.9 32.6 3.9 41.1 4.5 30.4 3.8 31.5 3.9 32.2 3.9 30.4 3.9 35.7 4.0 AUG 13 20.6 2.9 22.2 3.0 25.4 3.1 22.3 3.0 23.8 3.1 19.7 2.5 B 24.7 3.1 24.8 2.9 E AUG 20 24.2 2.5 24.2 2.5 26.4 2.6 24.9 2.5 23.4 2.5 22.3 2.6 22.8 2.6 24.5 2.8 AUG 27 33.4 3.0 79.7 7.0 C 42.7 3.7 33.6 2.8 31.8 2.7 31.6 2.7 31.8 2.8 46.2 3.7 SEP 03 10.1 2.5 10.6 2.5 11.5 2.5 8.9 2.4 9.7 2.4 10.3 2.5 10.0 2.5 9.9 2.5 SEP 10 22.7 2.9 22.0 2.9 25.6 3.0 22.2 2.9 20.9 2.8 18.5 2.8 19.4 2.8 23.4 3.0 SEP 17 24.2 3.3 23.8 3.3 30.8 3.6 24.3 3.3 22.6 3.2 24.5 3.3 27.3 3.4 28.2 3.4 SEP 24 31.7 3.5 31.7 3.5 42.8 4.5 33.8 3.6 29.9 3.4 31.6 3.5 30.0 3.5 34.8 3.7 OCT 01 26.6 3.6 25.7 3.6 29.4 3.7 25.5 3.5 25.3 3.5 24.0 3.5 23.9 3.5 25.4 3.6 OCT 08 36.5 3.6 29.1 3.1 32.0 3.6 28.8 3.0 35.0 3.3 29.5 3.0 31.2 3.2 35.1 3.5 OCT 15 19.5 3.0 21.6 3.0 20.4 3.0 22.6 3.1 18.0 2.9 18.8 3.0 20.0 3.0 20.3 3.0 OCT 22 26.8 3.4 27.8 3.4 32.9 3.7 23.8 3.2 26.3 3.3 23.9 3.2 25.7 3.3 30.7 3.7 OCT 29 26.4 3.2 31.8 3.4 33.8 3.5 31.6 3.4 27.2 3.1 30.1 3.9 27.5 3.2 36.2 3.9 NOV 05 20.4 3.2 26.7 3.3 29.0 3.6 23.9 3.4 22.6 3.1 20.8 3.3 24.3 3.4 25.4 3.5 NOV 12 22.0 3.3 22.7 3.4 25.0 3.4 27.5 3.5 24.6 3.4 22.2 3.3 22.4 3.3 26.2 3.5 NOV 19 19.1 3.2 18.2 3.2 20.4 3.3 18.7 3.2 18.1 3.2 18.0 3.2 20.9 3.3 21.8 3.4 NOV 26 23.3 3.3 22.5 3.3 32.9 3.7 28.5 3.5 23.5 3.3 24.9 3.4 23.3 3.3 22.2 3.8 DEC 02 22.9 3.8 20.8 3.7 26.7 4.0 23.5 3. 8 21.3 3 .7 20.0 3 .7 26.1 3.9 20.8 3.8 DEC 10 30.6 3.4 27.3 3.2 31.6 3.7 29.1 3.3 28.0 3.2 24.7 3 .1 28.3 3.3 27.1 3.3 DEC 17 21.7 2.9 17.9 2.8 23.0 2.9 20.3 2. 8 18.4 2. 8 18.0 2.8 20.8 2.9 17.7 2.8 DEC 23 20.6 3.9 23.9 4.1 25.1 4.1 25.0 4.0 20.0 3. 9 18.9 3 .9 20.8 4.0 21.4 4.0 DEC 31 27.5 3.2 24.7 3.1 32.1 3.5 29.7 3. 2 25.4 3.1 25.5 3 .1 26.9 3.2 27.8 3.3 33

I I I I I I I I I I I I Table 3-3 Footnotes A Sample collected on 2/27/02.

B Sampler malfunction. Sample volume based on sampler timer indication at time of malfunction. See Program Exceptions.

C Sampler malfunction. Sample volume based on sampler timer indication at time of malfunction. LLD met.

D Sampler inoperable at time of sample collection. The sampler timer indicated 0.0 hours0 days 0 hours 0 weeks 0 months of sampler run time.

Typical weekly particulate loading was evident on sample filter. Conservative estimate of 3 days sampler run time was assigned for sample volume determination. LLD met.

E Samples collected on 8/14/02.

34

I I I Il Il Il I I I I I I I I I I SURRY 2002 TABLE 3-4 AIRBORNE IODINE 1-131 (1E-3 PCI/M3)

L O C A T I O N S PERIOD ENDING SS HIR BC ALL CP BASF FE NN-C

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

JAN 09 -18 19 5 17 -21 16 7 18 0 18 4 16 21 14 -4 17 JAN 15 7 15 3 13 -2 14 2 14 -7 15 -3 14 -4 16 -1 14 JAN 22 -1 11 -3 13 -7 12 -12 12 0 12 -5 12 0 11 -4 11 JAN 29 4 13 -3 11 6 12 -12 10 -5 11 -3 11 -2 13 1 11 FEB 05 3 12 2 12 0 12 1 13 3 12 -1 13 0 13 0 12 FEB 12 -17 14 -8 13 2 11 4 13 -3 13 -7 11 4 12 -1 13 FEB 19 0 13 -13 15 2 13 2 11 -7 11 -3 11 -6 11 12 11 FEB 26 -5 19 1 14 A 0 15 -7 19 -8 18 2 15 20 20 2 21 MAR 05 4 17 15 20 4 15 6 20 -1 19 1 17 -3 19 1 17 MAR 12 -3 19 11 21 -5 17 18 18 0 21 19 20 26 22 B 19 20 MAR 20 11 14 4 16 2 15 11 15 -9 15 4 15 -9 14 -6 17 MAR 26 2 15 0 18 0 17 4 17 11 16 2 13 -2 13 -4 11 APR 02 -6 13 11 15 1 12 1 11 -1 11 -8 12 12 12 -5 12 APR 09 11 16 8 41 C -5 16 0 17 -4 20 5 17 0 14 0 13 APR 16 -3 16 14 18 8 18 -7 17 7 19 15 16 0 16 4 17 APR 23 -1 16 -9 17 -6 19 -7 18 -3 15 -12 19 3 16 15 20 APR 30 -14 20 14 19 12 18 -2 16 3 22 -16 17 -10 21 10 21 MAY 0 6 -2 14 -2 13 -5 13 1 12 -3 13 -1 14 -4 12 -5 9 MAY 14 2 12 6 12 0 11 10 12 -3 11 0 10 1 10 -5 10 MAY 21 0 16 -2 18 -2 17 13 17 -6 20 -7 16 0 21 2 15 MAY 29 16 18 -3 16 11 17 11 17 5 15 20 19 -3 17 -3 18 JUN 04 0 11 1 12 -5 14 -15 13 -5 14 -8 17 -15 15 -4 16 JUN 11 1 11 -2 24 4 13 -4 9 15 22 -1 11 -3 13 1 13 JUN 18 -3 18 -6 16 1 18 9 31 -7 18 7 16 6 14 0 17 JUN 25 -10 17 D 5 16 -4 15 -10 18 -8 21 12 16 -14 15 -4 17 35

I i I I I I I I I I I I I I I SURRY 2002 TABLE 3-4 AIRBORNE IODINE 1-131 (1E-3 PCI/M3)

L O C A T I O N S PERIOD ENDING SS HIR BC ALL CP BASF FE NN-C

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

JUL 02 4 23 -9 18 -1 26 12 19 14 24 -12 27 -22 18 -13 16 JUL 09 -4 13 -2 14 -18 17 -11 15 2 15 -3 14 -3 15 0 15 JUL 16 -10 9 -1 11 1 13 4 13 1 10 2 11 -3 8 7 11 JUL 23 -7 13 0 11 1 13 -8 10 1 12 -6 14 4 12 8 18 JUL 30 5 10 -7 15 -7 13 6 16 13 16 7 13 -13 14 0 18 AUG 06 2 10 -8 14 0 14 2 13 -2 15 -20 26 -2 17 -2 14 AUG 13 9 11 0 10 -3 12 13 13 -8 16 -6 12 E 9 15 7 13 E AUG 20 6 13 3 11 4 13 -10 11 -4 13 -5 14 11 12 0 11 AUG 27 12 15 -5 19 C -5 18 -9 14 11 14 1 12 7 15 3 16 SEP 03 6 19 10 18 -10 13 8 21 6 17 -4 19 -8 16 2 16 SEP 10 2 9 -4 9 -6 11 -4 11 4 9 -1 9 2 9 -4 10 SEP 17 -2 14 2 10 -4 11 2 11 1 13 9 12 2 10 5 11 SEP 24 -20 18 2 21 -6 23 2 16 1 12 -2 17 0 18 5 17 OCT 01 9 10 0 9 10 9 -1 14 0 11 1 11 -4 12 -14 13 OCT 08 -17 20 -2 16 -3 15 9 14 -4 18 -1 15 0 15 -4 11 OCT 15 -3 8 4 9 5 11 6 11 -10 10 -5 12 0 12 -1 9 OCT 22 -5 22 -5 21 5 21 -1 24 -9 21 -19 20 -3 23 -1 21 OCT 29 9 21 -11 15 -9 12 8 21 -3 17 -12 28 -7 22 -1 25 NOV 05 2 10 3 9 -3 10 2 9 -7 9 -10 12 -2 11 2 14 NOV 12 -6 8 -4 7 -4 7 0 8 -1 9 -7 8 0 8 2 8 NOV 19 -6 15 9 14 6 14 -13 15 -3 15 8 16 11 14 2 12 NOV 26 13 24 2 20 -2 20 9 19 -1 13 1 11 -5 13 11 14 DEC 02 6 16 0 16 -1 14 5 16 -6 20 19 20 0 18 -16 18 DEC 10 13 17 3 9 3 22 8 18 10 20 -5 16 3 18 -5 17 DEC 17 -6 18 0 16 6 18 0 21 6 18 0 18 6 16 -6 14 DEC 23 -1 15 8 13 -7 13 -4 13 -8 13 -3 15 4 14 8 14 DEC 31 -11 13 0 11 -1 13 -3 17 8 18 2 23 -4 21 -9 21 36

I I I IlI I I I II I I I I I I I Table 3-4 Footnotes A Sample collected on 2/27/02.

B Sampler malfunction. Sample volume based on sampler timer indication at time of malfunction. Sample was analyzed with an extended count time to meet the required LLD.

C Sampler malfunction. Sample volume based on sampler timer indication at time of malfunction. LLD met.

D Sampler inoperable at time of sample collection. The sampler timer indicated 0.0 hours0 days 0 hours 0 weeks 0 months of sampler run time.

Typical weekly particulate loading was evident on sample filter. Conservative estimate of 3 days sampler run time was assigned for sample volume determination. LLD met.

E Samples collected on 8/14/02.

37

f I I I I I I I I I I I I I I I I I SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 1 (1E-3 PCI/M3)

LOCATION BE-7 K-40 CO-60 ZR-95 NB-95 RU-103

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

SS 119 45 -3.6 7.2 0.14 0.58 0.8 2.7 1.1 4.1 1.6 3.3 HIR 97 37 1.5 7.8 0.32 0.79 -0.6 3.0 -5.7 6.0 0.0 4.3 BC 81 36 5.4 7.9 0.51 0.82 0.1 1.6 -1.7 4.1 2.1 2.5 ALL 81 42 3.5 8.7 0.32 0.45 -1.1 1.5 2.1 5.1 0.0 2.6 CP 91 37 14.0 11.0 -0.32 0.65 -1.7 3.5 -4.0 4.9 -2.5 3.9 BASF 70 42 9.0 10.0 0.51 0.82 0.7 2.0 2.9 5.8 1.0 1.5 FE 72 36 9.0 10.0 -0.02 0.83 1.3 1.9 -2.7 3.1 1.2 3.3 NN-C 120 36 8.5 7.9 -0.24 0.59 -0.4 2.6 3.3 5.5 -0.4 2.5 LOCATION RU-106 CS-134 CS-137 BA-140 CE-141 TH-228

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

SS 0.7 5.0 -0.49 0.60 -0.27 0.56 170 250 -0.3 4.7 0.3 2.4 HIR 1.9 4.6 -0.61 0.92 -0.09 0.49 100 140 -3.4 7.1 -0.5 2.5 BC 4.4 6.9 -0.44 0.57 0.08 0.36 50 190 -0.2 4.4 -1.4 2.0 ALL 2.9 4.7 0.03 0.71 -0.17 0.58 0 0 -0.8 5.2 0.3 2.4 CP 0.0 6.0 -0.36 0.70 0.28 0.68 - 110 210 -1.5 6.4 -1.0 2.9 BASF 2.6 5.5 0.03 0.49 -0.16 0.57 -50 110 -3.7 3.7 1.1 2.0 FE 1.8 5.7 0.05 0.86 -0.05 0.58 0 230 -2.1 5.0 0.8 1.6 NN-C 1.4 6.7 -0.57 0.49 0.42 0.44 60 210 4.5 6.0 -1.2 1.9 38

I I I I I I I I I IlI I I I I I SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 2 (1E-3 PCI/M3)

LOCATION BE-7 K-40 CO-60 ZR-95 NB-95 RU-103

( -)

Ss 120 36 5.4 8.2 0.16 0.67 -0.8 3.1 0.1 3.7 0.3 2.9 HIR 70 30 13.0 11.0 -0.28 0.55 0.8 1.9 0.7 3.4 0.3 2.7 BC 136 36 10.0 10.0 -0.15 0.46 0.1 1.1 0.9 3.7 0.3 2.1 ALL 141 31 7.1 7.1 0.15 0.44 0.2 1.9 0.2 3.2 1.8 2.4 CP 114 35 0.2 5.1 -0.06 0.65 0.8 2.0 1.8 3.9 -1.7 2.6 BASF 109 34 2.1 8.8 -0.03 0.53 -0.3 1.4 1.5 3.6 -0.3 2.1 FE 119 32 -0.3 5.1 -0.04 0.44 -0.4 1.8 -1.8 2.8 -1.0 1.8 NN-C 112 33 10.0 11.0 0.16 0.64 0.4 2.4 2.3 3.9 -0.3 3.3 LOCATION RU-106 CS-134 CS-137 BA-140 CE-141 TH-228

(+/-)

SS 3.8 5.0 -0.22 0.45 0.46 0.61 -4 89 0.0 5.0 1.7 2.3 HIR -1.5 5.0 -0.11 0.47 -0.66 0.60 38 83 -0.8 4.1 0.9 2.5 BC -4.2 6.1 -0.49 0.41 0.26 0.58 -70 100 1.7 3.5 -0.2 2.2 ALL -2.2 3.5 0.05 0.45 -0.06 0.44 46 68 0.3 3.6 1.3 1.8 CP 0.7 6.5 0.08 0.40 -0.07 0.54 -30 100 -1.1 4.6 2.6 2.3 BASF -0.5 4.8 0.29 0.46 0.44 0.57 23 47 -0.8 4.0 -0.2 2.8 FE -2.6 4.9 -0.05 0.31 -0.04 0.35 15 69 0.5 3.2 -0.6 1.6 NN-C 4.4 6.5 0.36 0.64 0.07 0.57 62 72 1.8 4.5 -2.9 2.5 39

I I I I I lI l lI lIIIIIIIII l l l SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 3 (1E-3 PCI/M3)

LOCATION BE-7 K-40 CO-60 ZR-95 NB-95 RU-103 (4/-)

SS 65 17 -0.2 5.3 -0.35 0.55 0.1 1.3 0.3 1.3 -0.6 0.8 HIR 47 20 6.6 9.5 0.22 0.65 1.0 1.4 -1.2 1.6 0.0 1.3 BC 54 21 -2.9 8.1 0.10 0.62 -1.1 1.4 -1.3 2.2 1.1 1.4 ALL 64 17 0.7 7.2 -0.03 0.52 -0.7 1.6 -0.8 1.7 0.6 1.0 CP 57 19 2.5 6.8 -0.34 0.84 0.5 1.7 0.1 1.4 0.0 1.2 BASF 80 21 3.0 8.5 0.14 0.55 0.3 2.0 -0.6 1.9 1.8 1.4 FE 50 18 0.5 4.9 0.48 0.62 0.2 2.0 -0.4 1.6 0.4 1.3 NN-C 55 20 -3.1 5.7 -0.32 0.69 -1.1 1.4 -1.1 1.1 -0.6 1.2 LOCATION RU-106 CS-134 CS-137 BA-140 CE-141 TH-228 (4/-) (4/-)

(4/-)

SS 2.3 4.5 0.10 0.37 -0.09 0.54 -3 11 0.4 1.4 -1.2 1.7 HIR -2.0 4.1 0.12 0.35 -0.06 0.43 -8 23 0.3 1.9 -1.9 1.7 BC -0.7 5.5 -0.16 0.49 -0.24 0.54 -8 17 -1.4 1.8 0.5 1.9 ALL 0.1 5.2 -0.06 0.41 -0.39 0.43 12 14 0.4 1.6 0.5 2.2 CP -2.9 4.4 -0.14 0.53 0.03 0.52 0 11 -0.6 1.5 1.1 2.0 BASF 0.7 5.2 -0.37 0.63 -0.07 0.56 7 10 0.1 2.6 -0.9 1.6 FE 2.0 4.1 -0.08 0.32 -0.14 0.51 -8 11 -1.1 1.9 1.8 2.2 NN-C 0.4 4.5 0.27 0.65 0.24 0.39 8 17 -0.3 1.8 2.6 2.6 40

I I I I I I l l Il Il I I I I I I l SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 4 (1E-3 PCI/M3)

LOCATION BE-7 K-40 CO-60 ZR-95 NB-95 RU-103

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

SS 75 15 4.8 5.1 0.12 0.33 0.2 1.1 -1.1 1.5 -0.2 1.1 HIR 89 19 2.3 5.3 0.21 0.50 0.0 1.3 1.4 2.3 -0.5 1.6 BC 108 20 7.8 7.4 -0.22 0.54 0.1 1.2 0.6 1.7 -0.7 1.2 ALL 85 19 -3.0 3.7 0.21 0.42 0.5 1.2 0.3 1.1 -0.4 1.3 CP 86 15 3.0 5.0 -0.05 0.35 -0.8 1.2 -0.4 1.3 0.0 1.1 BASF 79 21 1.9 6.7 0.09 0.54 0.5 1.5 0.3 1.8 0.0 1.9 FE 75 19 -1.2 5.5 0.17 0.51 -1.0 1.2 0.4 1.6 0.2 1.1 NN-C 106 23 0.3 7.9 0.30 0.49 -0.5 1.9 -0.1 1.9 0.0 1.4 LOCATION RU-106 CS-134 CS-137 BA-140 CE-141 TH-228 3 ) (+1-) (+1/-) (+/-) (+/-)

SS -0.2 3.9 -0.15 0.41 0.20 0.36 -15 16 -0.5 1.6 -0.7 1.3 HIR 1.9 3.9 -0.25 0.44 -0.36 0.43 7 23 0.5 2.6 0.1 1.7 BC -1.9 3.6 -0.08 0.30 -0.07 0.41 5 21 0.7 1.8 -0.2 1.6 ALL -2.3 3.5 0.06 0.43 0.24 0.32 1S 22 -1.3 1.5 -0.5 1.3 CP -3.7 3.6 -0 .11 0.27 -0.19 0.31 -15 19 -0.4 1.4 -0.5 1.1 BASF -0.5 3.6 0.36 0.63 0.26 0.46 -7 29 -2.0 2.8 -0.5 1.7 FE -1.0 3.5 -0.37 0.36 -0.20 0.28 -6 26 -0.3 1.7 0.5 1.4 NN-C 0.1 4.1 -0.04 0.38 -0.17 0.38 12 39 1.1 2.0 -0.6 1.3 41

I I I I I I I I I I I IlI I Ii SURRY 2002 TABLE 3-6 COW MILK (PCI/L)

COLLECTION LOCATION DATE K-4C SR-89 SR-90 I-131 CS-134 CS-137 BA-140 LA-140 I

( / ) ( / )

CP 01/09/02 1340 110 0.16 0.24 1.9 2.7 1.8 2.4 0.6 3.3 0.7 3.8 02/05/02 1520 110 0.01 0.08 0.3 2.9 -0.6 2.5 1.8 2.3 2.1 2.6 03/05/02 1400 98 -6.4 6.6 2.5 1.1 -0.06 0.08 1.8 2.5 -2.1 2.5 -2.0 4.9 -2.3 5.6 04/17/02 1420 120 0.21 0.26 2.9 3.6 -2.7 3.2 -1.7 5.6 -2.0 6.4 05/15/02 1510 140 -0.02 0.07 3.8 3.5 0.2 3.6 0.5 5.7 0.6 6.5 06/18/02 1450 100 -6.7 5.1 1.5 0.7 0.70 0.78 0.6 2.8 2.1 2.9 2.4 3.7 2.7 4.2 07/02/02 1300 110 0.35 0.49 1.1 3.4 -2.6 3.1 -3.1 5.6 -3.5 6.5 08/06/02 1240 110 0.11 0.33 -0.3 3.3 2.2 3.1 -5.3 5.6 -6.0 6.5 09/03/02 1390 110 -4.2 4.0 1.1 1.0 0.73 0.72 0.6 3.3 1.5 3.0 0.6 4.3 0.7 4.9 10/01/02 1400 100 0.17 0.52 -1.8 2.7 -2.1 2.8 -2.6 4.2 -3.0 4.9 11/12/02 1450 110 0.02 0.28 -1.3 3.1 0.3 3.1 1.5 5.1 1.8 5.9 12/02/02 1350 110 6.3 5.6 1.8 0.9 0.04 0.30 -2.4 2.9 -0.7 3.1 1.7 4.3 2.0 5.0 EPPS 01/22/02 1430 130 0.05 0.12 -1.1 3.3 -1.5 3.1 3.9 4.4 4.5 5 .0 02/26/02 1370 150 0.07 0.14 0.5 3.6 3.2 4.1 2.0 5.1 2.3 5. 9 03/26/02 1452 96 0.04 0.23 -2.6 2.5 -0.1 2.6 -0.8 3.8 -0.9 4.4 04/23/02 1420 110 0.03 0.09 0.5 2.8 1.5 3.0 -3.6 5.3 -4.2 6.1 05/29/02 1450 100 -0.08 0.03 -0.9 2.8 -0.1 2.6 -1.2 3.7 -1.4 4.2 06/18/02 1340 110 0.28 0.52 -2.2 3.2 -0.9 3.1 -2.4 4.8 -2.8 5.5 07/23/02 1480 100 0.08 0.21 1.2 2.9 -1.4 3.1 -0.5 4.1 -0.5 4.8 08/20/02 1280 120 0.14 0.53 2.5 3.6 1.6 3.4 -0.4 4.8 -0.4 5.5 09/24/02 1430 110 0.22 0.52 2.6 2.3 0.1 2.6 3.0 3.1 3.4 3.6 10/22/02 1322 83 0.27 0.53 0.2 2.3 0.6 2.4 0.7 3.9 0.9 4.5 11/26/02 1372 80 0.39 0.49 -0.2 2.0 -0.3 2.2 0.7 3.1 0.8 3.6 12/17/02 1300 120 0.22 0.43 1.9 3.3 -0.3 3.2 -0.8 4.2 -0.9 4.8 STRONTIUM ANALYSES FOR CP MILK SAMPLES REQUESTED BY THE COMMONWEALTH OF VIRGINIA 42

SURRY 2002 TABLE 3-6 COW MILK (PCI/L)

COLLECTION LOCATION DATE K-40 SR-89 SR-90 1-131 CS-134 CS-137 BA-140 LA-140

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

PIV-C 01/22/02 1190 140 0.00 0.12 1.3 3.6 -1.2 3.1 0.6 4.5 0.7 5.2 02/26/02 1170 120 -0.03 0.08 1.8 3.2 0.8 3.1 1.9 5.2 2.1 6.0 03/26/02 1037 87 0.08 0.13 0.7 2.8 0.7 2.7 0.7 4.8 0.8 5.6 04/23/02 1770 120 0.04 0.09 -0.5 2.9 0.5 3.2 -1.5 3.3 -1.7 3.8 05/23/02 1410 120 0.00 0.17 -0.2 2.7 0.8 3.1 -2.8 5.3 -3.3 6.1 06/18/02 1290 130 0.27 0.50 -1.3 3.4 -1.4 3.9 0.0 5.1 0.0 5.9 07/23/02 1332 92 0.11 0.25 -2.8 2.7 0.1 2.3 -0.7 3.3 -0.8 3.8 08/20/02 1285 94 0.27 0.53 -1.6 2.6 0.5 2.8 -3.6 4.2 -4.1 4.8 09/24/02 1310 140 -0.06 0.48 1.0 3.4 0.7 3.7 0.0 5.0 0.0 5.7 10/15/02 1320 110 0.37 0.59 1.2 3.0 -1.0 3.0 -4.6 5.0 -5.3 5.7 11/19/02 1320 120 0.18 0.41 3.9 3.0 0.3 3.3 -1.8 4.0 -2.1 4.5 12/17/02 1457 99 0.24 0.45 2.1 3.0 -0.5 2.7 2.1 3.5 2.4 4.1 43

I I I I I I I I I I I I I I I I i SURRY 2002 TABLE 3-7 FOOD PRODUCTS (PCI/KG WET WT.)

COLLECTION LOCATION DATE TYPE BE-7 K-40 CR-51 MN-54 CO-58 FE-59 BROCK'S 11/19/02 PEANUTS 36 47 6380 320 13 52 -4.8 6.0 -2.1 5.9 -5 14 11/19/02 CORN -35 57 3310 250 -2 63 -6.3 7.3 14.0 12.0 1 16 12/18/02 SOYBEANS 9 31 15610 270 -2 35 -2.1 4.3 -2.5 4.3 8 14 COLLECTION LOCATION DATE TYPE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106 BROCK'S 11/19/02 PEANUTS 2.4 8.0 24 36 -1.0 10.0 -2.0 10.0 -2.4 5.7 -28 58 11/19/02 CORN 8.5 9.0 54 41 -9.0 10.0 9.0 13.0 -1.3 6.5 -29 62 12/18/02 SOYBEANS 0.3 7.6 0 12 -1.7 7.5 0.1 4.9 -2.0 3.9 16 34 COLLECTION LOCATION DATE TYPE SB-125 I-131 CS-134 CS-137 BA-140 LA-140 BROCK'S 11/19/02 PEANUTS 8.0 17.0 1.7 7.4 1.3 6.6 -2.6 7.3 1.9 5.8 2.2 6.7 11/19/02 CORN -9.0 20.0 -1.1 8.8 -0.4 7.2 1.0 13.0 -3.2 7.0 -3.7 8.1 12/18/02 SOYBEANS -3.5 8.3 -5.0 12.0 1.6 4.2 2.3 4.0 2.0 5.6 2.3 6.4 COLLECTION LOCATION DATE TYPE CE-141 CE-144 TH-228 BROCK'S 11/19/02 PEANUTS -4.3 8.5 -4 34 7 24 11/19/02 CORN 5.0 11.0 59 45 8 27 12/18/02 SOYBEANS 2.8 5.5 1 16 17 16 44

I I I I I I I I I I I I I II l SURRY 2002 TABLE 3-8 WELL WATER (PCI/L)

COLLECTION LOCATION DATE K-40 CR-51 MN-54 CO-58 FE-59 CO-60

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

HIR 03/26/02 8.0 36.0 -3.0 22.0 0.6 2.6 0.7 2.3 0.6 6.5 -0.3 2.4 06/18/02 2.0 18.0 15.0 18.0 -0.3 1.5 -0.5 1.5 -2.1 4.4 -0.1 1.3 09/24/02 -26.0 31.0 9.0 27.0 -2.3 2.6 -1.2 2.3 -1.0 5.2 0.4 2.5 12/02/02 -1.0 41.0 -4.0 30.0 -2.0 2.7 0.3 2.9 -5.1 6.2 1.7 3.1 SS 03/26/02 7.0 35.0 4.0 23.0 -0.5 2.2 -0.3 2.1 2.0 5.3 1.0 2.3 06/18/02 20.0 29.0 -9.0 23.0 -0.2 2.3 -0.1 2.1 3.7 5.0 -1.2 2.2 09/24/02 -22.0 28.0 1.0 23.0 1.5 2.0 -1.1 2.0 -0.4 4.4 0.7 2.6 12/02/02 2.0 38.0 9.0 30.0 0 .0 3.0 0.2 3.2 3.2 7.1 1.2 3.6 COLLECTION LOCATION DATE ZN-65 ZR-95 NB-95 RU-103 RU-106 1-131 HIR 03/26/02 -3.7 5.3 0.0 4.2 -0.3 2.6 -0.6 2.7 -2.0 21.0 0.01 0.26 06/18/02 -3.0 3.5 -1.0 2.7 0.4 1.8 -2.2 1.9 11.0 15.0 0.30 0.53 09/24/02 5.0 10.0 -2.1 4.3 2.5 2.8 -1.3 2.9 -6.0 23.0 -0.06 0.31 12/02/02 -1.9 6.6 -0.3 4.9 -2.6 2.8 -0.6 3.1 3.0 25.0 0.59 0.61 SS 03/26/02 -3.4 4.6 2.8 3.8 1.4 2.5 -1.1 2.4 -1.0 20.0 0.00 0.24 06/18/02 -6.1 5.1 -0.3 3.6 -2.9 2.8 -3.9 2.4 -14.0 19.0 -0.05 0.29 09/24/02 3.8 9.1 0.3 3.3 1.6 2.3 -1.7 2.5 5.0 19.0 0.21 0.41 12/02/02 -4.0 17.0 -1.4 4.2 -0.2 3.7 -1.7 3.4 -2.0 26.0 0.38 0.56 45

I I l I I I I lI lI l l I I I I I I SURRY 2002 TABLE 3-8 WELL WATER (PCI/L)

COLLECTION LOCATION DATE CS-134 CS-137 BA-140 LA-140 H-3

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

HIR 03/26/02 1.2 2.2 1.7 2.5 -2.6 4.5 -3.0 5.1 -140 730 06/18/02 1.8 1.5 -0.6 1.5 -0.5 3.2 -0.6 3.7 -90 740 09/24/02 1.7 2.6 -0.9 2.7 -1.5 4.5 -1.7 5.2 -500 1000 12/02/02 -0.8 2.8 3.0 3.5 0.6 5.2 0.7 6.0 400 900 SS 03/26/02 -0.5 2.3 0.4 2.3 -3.1 3.6 -3.6 4.2 -40 760 06/18/02 0.0 1.7 1.9 2.1 2.0 4.9 2.3 5.6 0 760 09/24/02 -1.8 1.9 -1.8 2.2 -0.8 3.6 -0.9 4.1 600 1100 12/02/02 3.3 3.9 -2.0 5.9 3.8 5.6 4.3 6.4 780 920 46

l I I I I IIIIIIIIIIII l l l l l l SURRY 2002 TABLE 3-9 RIVER WATER (PCI/L)

COLLECTION LOCATION DATE K-40 CR-51 MN-54 CO-58 FE-59 CO-60

(+/-)

SD 01/29/02 154 42 -7 20 0.2 1.7 -0.8 1.7 3.7 5.6 0.1 1.8 02/26/02 106 53 -13 29 -1.4 2.4 2.3 2.5 0.0 6.6 -0.3 2.7 03/26/02 150 51 11 22 0.0 2.1 0.9 1.9 -6.8 6.5 -1.2 2.7 04/30/02 61 31 -10 19 0.8 1.9 -0.8 1.7 -2.5 4.1 1.7 1.7 05/29/02 59 27 -7 17 0.4 1.5 -1.2 1.5 -1.1 4.1 1.1 1.6 06/18/02 147 33 2 16 -0.9 1.5 -0.2 1.7 1.1 3.5 0.2 1.6 07/30/02 145 42 -13 21 -0.1 1.8 -1.5 2.0 2.3 4.7 1.3 2.1 08/20/02 145 39 0 18 -0.7 1.5 -0.8 1.6 -0.8 4.9 -0.3 1.8 09/24/02 155 49 4 25 0.7 2.7 -2.9 2.5 1.9 4.8 0.7 2.6 10/22/02 94 23 -5 12 0.4 1.1 -0.4 1.1 0.3 2.3 -0.8 1.0 11/26/02 39 30 2 17 -1.7 1.9 -0.1 1.6 0.3 3.7 0.3 1.7 12/23/02 42 29 1 17 0.4 1.7 -0.6 1.8 -1.3 3.8 0.3 1.8 SW-C 01/29/02 68 52 23 27 -0.8 2.4 1.9 2.6 4.4 7.2 2.5 2.9 02/26/02 59 45 10 25 3.2 2.5 0.0 2.4 -3.8 8.3 0.9 2.8 03/26/02 31 30 -4 16 -0.9 1.5 0.1 1.6 -1.7 5.1 -0.3 1.8 04/30/02 34 26 3 19 0.6 1.8 1.8 2.0 -1.2 4.2 -0.1 1.7 05/29/02 36 24 4 16 0.8 1.4 -0.2 1.5 -4.0 4.2 0.2 1.3 06/18/02 76 28 -1 16 0.1 1.3 0.5 1.2 -0.8 3.0 -0.7 1.4 07/30/02 91 38 -12 21 -0.1 1.9 -0.4 2.0 -0.6 6.3 1.7 2.1 08/20/02 83 32 -1 15 -0.5 1.3 1.0 1.6 0.1 4.2 0.1 1.6 09/24/02 104 51 9 24 0.4 2.5 0.8 2.6 0.0 5.1 -0.4 2.8 10/22/02 135 25 10 11 -0.6 1.1 -0.4 1.1 -0.3 2.3 0.7 1.2 11/26/02 16 33 -3 21 0.2 2.2 0.0 2.1 2.1 4.4 -0.2 2.0 12/23/02 -17 21 6 16 -1.0 1.5 -0.9 1.5 -1.5 3.4 1.6 1.6 47

I I I I I I I I lIIIIIIIII l l l l l SURRY 2002 TABLE 3-9 RIVER WATER (PCI/L)

COLLECTION LOCATION DATE ZN-65 ZR-95 NB-1-95 RU-103 RU-106 1-131 SD 01/29/02 0.7 4.7 3.2 3.3 1.1 1.8 -1.7 2.3 -35 17 -0.1 0.3 02/26/02 -4.6 5.3 5.1 4.4 1.7 2.8 1.5 3.0 -3 21 0.2 1.5 03/26/02 1.7 5.7 -1.4 3.8 1.2 2.2 -1.3 2.2 -5 20 -0.4 4.0 04/30/02 -1.8 3.5 -1.0 2.7 -1.3 2.3 -1.6 2.0 4 16 2.9 5.8 05/29/02 -4.0 3.2 2.4 2.5 0.8 1.6 -0.7 1.6 -2 14 -1.7 4.6 06/18/02 -3.9 3.5 -0.3 2.6 -0.2 1.7 -1.8 1.8 1 14 -0.5 5.0 07/30/02 -0.4 9.8 -1.3 3.1 -1.6 2.2 -1.2 2.1 -7 20 -0.5 3.9 08/20/02 -4.4 4.1 0.8 3.1 -1.8 1.5 0.6 1.8 6 16 -0.2 3.8 09/24/02 -9.6 9.7 -0.2 3.7 -1.1 2.9 -0.1 2.9 -12 21 -0.3 4.7 10/22/02 -1.5 2.3 -0.8 2.0 -0.6 1.3 -2.1 1.3 4 9 1.0 3.0 11/26/02 5.3 6.7 0.9 2.9 0.9 1.8 -1.8 1.9 -4 17 1.9 3.5 12/23/02 1.2 6.4 0.2 2.5 0.1 1.9 -0.9 2.0 -7 16 -2.1 3.2 SW-C 01/29/02 -7.4 5.7 1.1 4.7 -2.4 3.1 -4.1 3.1 -3 22 0.0 0.4 02/26/02 -1.6 5.9 -1.6 4.6 1.2 2.7 -2.3 3.0 0 23 2.8 3.3 03/26/02 -0.3 3.8 2.0 2.7 -0.2 1.9 -1.4 1.9 -10 18 -1.8 3.3 04/30/02 -4.7 4.3 1.7 2.9 0.7 2.0 -1.6 2.3 -5 17 2.6 5.8 05/29/02 -1.4 3.4 0.4 2.4 0.0 1.7 -1.3 1.8 0 14 2.4 4.4 06/18/02 -2.8 3.1 0.1 2.6 0.5 1.7 -0.7 1.6 -3 13 -5.7 4.6 07/30/02 0.3 4.0 0.6 3.5 -1.3 2.3 -1.4 2.3 -7 18 -0.6 4.1 08/20/02 -0.8 3.0 -1.0 2.5 -2.1 1.7 -0.4 1.7 -6 14 2.4 3.6 09/24/02 -0.5 6.5 0.8 3.9 -0.8 2.8 -2.2 2.6 -2 22 4.4 5.1 10/22/02 -0.4 2.4 1.2 1.7 -0.2 1.2 -1.8 1.2 -2 9 0.7 3.0 11/26/02 0 .9 8.2 0.2 3.4 0.4 2.3 -0.5 2.3 8 18 -2.9 4.0 12/23/02 2.7 7.3 -0.3 2.8 0.3 3.0 -0.4 1.8 -7 17 0.6 3.3 48

I I I I I I I I I I I I I I I I l I I SURRY 2002 TABLE 3-9 RIVER WATER (PCI/L)

COLLECTION LOCATION DATE CS-134 CS- 137 BA-140 LA- 140 H-3

( / )-

SD 01/29/02 1.3 1.6 -0.6 1.8 -2.0 2.7 -2.3 3.1 02/26/02 -1.0 2.6 -2.0 2.4 -0.6 5.6 -0.7 6.4 03/26/02 -0.8 2.6 -0.5 2.4 0.4 4.1 0.5 4.7 40 830 04/30/02 0.3 1.7 0.2 1.7 4.7 3.8 5.4 4.4 05/29/02 0.9 1.5 -0.4 1.5 0.2 3.1 0.3 3.6 06/18/02 0.0 1.6 -0.7 1.5 -1.2 2.9 -1.3 3.3 -1200 1100 07/30/02 1.8 1.8 -1.3 2.1 -0.5 3.3 -0.6 3.8 08/20/02 0.3 1.7 0.2 1.8 0.3 2.7 0.3 3.1 09/24/02 0.3 2.3 -3.7 2.4 -2.0 4.2 -2.3 4.9 0 830 10/22/02 0.2 1.2 -0.5 1.0 -0.8 2.2 -0.9 2.6 11/26/02 1.2 1.6 -0.4 1.7 -0.5 2.5 -0.6 2.9 12/23/02 1.0 1.9 -0.9 1.8 -0.2 2.5 -0.3 2.9 120 900 Sw-C 01/29/02 -2.2 2.9 -1.3 2.8 -0.5 4.7 -0.6 5.4 02/26/02 0.4 2.8 0.8 2.7 0.7 6.2 0.8 7.2 03/26/02 0.3 1.9 -0.7 1.9 -1.1 2.6 -1.3 3.0 280 780 04/30/02 0.5 2.0 0.1 1.7 0.6 4.2 0.7 4.9 05/29/02 1.0 1.7 0.2 1.5 -0.4 2.8 -0.5 3.2 06/18/02 -0.2 1.4 0.5 1.4 1.1 2.8 1.3 3.3 -700 1100 07/30/02 1.7 2.1 0.3 2.4 -0.9 3.7 -1.0 4.2 08/20/02 -1.3 1.5 -0.5 1.6 0.3 2.4 0.3 2.7 09/24/02 -1.1 2.7 -0.5 2.8 -1.5 4.6 -1.7 5.3 300 840 10/22/02 0.1 1.0 -0.7 1.1 0.1 2.5 0.1 2.8 11/26/02 -1.1 2.2 0.8 2.2 -1.5 2.5 -1.8 2.9 12/23/02 -0.4 1.6 -0.6 1.6 -1.6 2.4 -1.8 2.8 290 930 49

I I I I I I I I I I I I I I SURRY 2002 TABLE 3-10 SILT (PCI/KG DRY WT.)

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

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

CHIC-C 03/14/02 640 440 17170 980 -60 410 6 30 -20 32 50 100 09/17/02 -170 370 17500 1000 -30 490 -22 30 9 36 -62 91 SD 03/14/02 -30 210 13770 660 130 330 14 18 -7 21 26 72 09/17/02 470 480 17800 1100 -390 570 1 32 22 44 -30 110 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106

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

CHIC-C 03/14/02 36 36 A 40 130 -15 58 -10 70 -7 37 -10 250 09/17/02 18 30 80 140 -14 70 1 76 -12 41 -20 290 SD 03/14/02 38 17 -15 86 22 43 -38 33 -18 29 60 160 09/17/02 67 32 -30 160 0 71 -81 98 -39 49 -10 290 COLLECTION LOCATION DATE AG-lOM 1-131 CS-134 CS-137 SB-125 TH-228

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

CHIC-C 03/14/02 7 39 -60 270 -9 28 236 47 57 71 1280 110 09/17/02 -27 37 380 490 10 41 212 46 42 74 1150 110 SD 03/14/02 23 23 90 300 54 71 259 36 0 50 959 75 09/17/02 -12 47 -140 530 -42 34 313 57 7 90 990 140 A: CO-60 WAS REANALYZED DUE TO A FALSE PEAK IDENTIFIED IN THE ORIGINAL ANALYSIS 50

IlI I I I I I I I II I I II I I SURRY 2002 TABLE 3-11 SHORELINE SEDIMENT (PCI/KG DRY WT.)

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

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

CHIC-C 02/26/02 150 190 1080 360 -90 240 -15 19 16 21 7 62 09/03/02 40 340 970 450 -240 430 9 34 -25 33 43 82 HIR 02/27/02 140 130 8950 820 -110 140 -4 16 4 14 -9 60 09/03/02 5 75 6780 490 56 99 6 9 -9 9 36 34 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106 CHIC-C 02/26/02 0 18 39 79 -6 36 -29 30 6 22 0 200 09/03/02 -3 24 -110 130 36 61 -5 45 18 41 90 290 HIR 02/27/02 9 18 84 79 29 28 2 18 -2 15 -10 120 09/03/02 -8 11 -19 49 -14 15 -4 10 6 10 -11 82 COLLECTION LOCATION DATE AG-IOM I-131 CS-134 CS-137 SB-125 TH-228

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

CHIC-C 02/26/02 -2 22 -70 110 -41 79 -17 21 46 54 131 57 09/03/02 -17 42 -60 110 4 31 -5 35 51 93 1200 140 HIR 02/27/02 -2 21 -36 63 3 14 3 15 -7 35 116 59 09/03/02 0 12 41 30 6 7 12 13 -4 21 138 39 51

I I Il Il Il I I I I I I I I I I l SURRY 2002 TABLE 3-12 FISH (PCI/KG ET WT.)

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

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

SD 04/03/02 CATFISH 80 250 2200 550 70 350 -20 22 -4 29 17 74 04/03/02 PERCH 220 300 2570 770 300 470 12 27 14 31 -60 110 10/30/02 CATFISH 170 300 2460 820 -40 660 0 35 -35 41 30 110 10/09/02 PERCH -360 480 2420 710 190 850 3 30 -38 39 -10 130 COLLECTION LOCATION DATE TYPE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106 SD 04/03/02 CATFISH -15 22 -32 53 4 41 19 39 -11 31 30 200 04/03/02 PERCH 12 31 -25 73 -25 74 9 51 0 41 140 300 10/30/02 CATFISH -10 40 9 63 10 69 -33 62 54 47 210 310 10/09/02 PERCH -10 29 -20 67 60 73 29 80 -5 65 -60 260 COLLECTION LOCATION DATE TYPE AG-110M 1-131 CS-134 CS-137 SB-125 TH-228 SD 04/03/02 CATFISH 5 28 0 240 14 24 -9 24 43 61 -29 87 04/03/02 PERCH -42 42 230 370 29 28 5 29 31 71 30 130 10/30/02 CATFISH 0 50 -200 1100 19 33 -22 34 -6 75 -40 110 10/09/02 PERCH -38 36 1600 5500 -9 29 13 26 -4 57 90 110 52

I I I I I I I lI l lIIIIIIIII l l l SURRY 2002 TABLE 3-13 OYSTERS (PCI/KG WET WT.)

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

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

MP 03/14/02 80 200 540 530 20 250 -10 22 -5 26 -33 81 09/17/02 -130 180 590 280 -210 270 -7 15 -14 18 -28 43 POS 03/14/02 0 260 970 520 -10 350 24 20 -9 26 87 87 09/17/02 -100 170 890 280 0 290 -5 14 -11 18 6 42 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106

(+/ -)

MP 03/14/02 1 27 -54 71 -4 41 -19 28 0 26 110 210 09/17/02 -10 15 -4 35 36 43 -17 32 -21 26 0 120 POS 03/14/02 14 19 -43 65 35 52 14 33 5 32 0 230 09/17/02 2 14 -34 37 -7 31 -8 30 12 23 -40 130 COLLECTION LOCATION DATE AG-lOM 1-131 CS-134 CS-137 SB-125 TH-228 NP 03/14/02 31 29 -30 120 14 23 9 21 -5 43 -16 96 09/17/02 -1 20 -300 490 5 16 3 15 20 41 -75 53 POS 03/14/02 -12 34 10 140 3 29 18 24 -5 57 -1 93 09/17/02 1 22 -530 440 5 14 4 13 -20 37 -21 49 53

SURRY 2002 TABLE 3-14 CLAMS (PCI/KG WET WT.)

COLLECTION LOCATION DATE BE-7 K-40 CR-51 mN-54 Co-58 FE-59

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

CHIC-C 03/14/02 -80 150 200 380 -40 230 -10 22 13 20 44 69 09/17/02 50 220 620 300 -20 320 4 20 -25 23 22 45 HIP 03/14/02 60 230 430 370 -60 240 -16 19 8 21 46 72 09/17/02 -10 190 840 290 -100 270 4 15 10 19 53 56 LC 03/14/02 -100 130 480 260 -30 170 -3 12 -3 16 2 51 09/17/02 -40 220 1090 380 50 370 -9 20 -14 23 -32 50 SD 03/14/02 -120 150 130 300 10 240 -3 16 18 19 7 62 09/17/02 40 190 520 320 110 310 -3 19 4 23 6 53 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106 CHIC-C 03/14/02 -10 23 -67 53 -5 38 10 27 18 22 10 200 09/17/02 -18 26 -5 36 -6 40 -25 31 5 24 -30 160 HIP 03/14/02 -4 34 0 44 0 39 -6 31 -5 22 90 170 09/17/02 5 14 8 41 20 32 2 30 -7 26 90 160 LC 03/14/02 5 17 -43 36 4 33 1 19 8 21 -40 170 09/17/02 -19 18 -21 47 33 41 -4 36 -11 28 150 170 SD 03/14/02 -7 15 27 50 4 29 0 25 -9 20 -50 190 09/17/02 8 16 -8 32 4 31 -16 33 -11 24 -70 160 54

I l I I l [I I I IlI l I lI I I I I SURRY 2002 TABLE 3-14 CLAMS (PCI/KQ WET WT.)

COLLECTION LOCATION DATE AG-110M 1-131 CS-134 CS-137 SB-125 TH-228

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

CHIC-C 03/14/02 -19 31 50 120 -5 23 17 20 14 45 13 76 09/17/02 -8 20 -110 570 14 18 19 16 -4 42 5 67 HIP 03/14/02 -20 31 70 120 -4 25 -9 24 -20 51 -43 87 09/17/02 20 19 -200 500 14 17 -6 16 -8 35 -15 52 LC 03/14/02 23 23 -53 88 -8 14 0 17 -28 44 18 53 09/17/02 -21 30 -120 500 -10 15 -18 18 10 39 -2 69 SD 03/14/02 7 24 10 100 4 16 -8 17 3 46 68 68 09/17/02 4 22 -130 560 4 15 -1 19 23 36 -27 61 55

SURRY 2002 TABLE 3-15 CRABS (PCI/KG WET WT.)

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

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

SD 06/07/02 -110 210 1560 600 -150 450 -3 20 -8 30 10 120 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 RU-103 RU-106

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

SD 06/07/02 -27 23 -16 70 -13 56 -11 53 -21 41 30 170 COLLECTION LOCATION DATE AG-llOM 1-131 CS-134 CS-137 SB-125 TH-228

( ) ( 9) ( ) ( ) ( 7) ( 1)

SD 06/07/02 4 35 240 990 4 25 19 23 5 57 -20 100 56

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2002 and tabulated in Section 3, are discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Framatome ANP DE&S 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 2002 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.

The following is a discussion and summary of the results of the environmental measurements taken during the 2002 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.

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 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.

57

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

'E 5 '1 A \.- 11 I

.8 4- - \i \

E 2-1--

O - 1 1 I '

W)~

't c r- cc 0N o -

0N CON ON ON~ ON ON1 0) 0 0 ON) ON1 ON ON ON ON 0 0 0

- - - - - - ('1~~~~~~~~~~~~~~~~~~~c Cl cl I - Site Boundary 5 Mile -- Avg Controll 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 gross beta activity at levels similar to that seen over the last decade. 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.

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).

58 cc)

Figure 4-2: GROSS BETA INAIR PARTICULATES FOR 2002 0.050 0.045 A 0.040

.9~~~

0.035 II A IE 0.030 jA .AA I z \I\ I -IfV\. A A t

j. 0.025 0.020 I w IK ..-

X4

'r-A *i

- -X ?. I .. I I 1

.1 -

o X w F

0.015 v l 4 "I V.

A % -- v lllllllllll+lll : - A 0.010 Q) cm I N I IS t I EQ tD t- t- CO T-O Or Or ~

o,~O O5 ~ OI OE O O 0 O O - _ _

I *P Avg Infficator -.. .. Avg Control

A Indicator ... --- AX Control Figure 4-3: GROSS BETA IN AIR PARTICULATES 10 YEAR TREND 1.0E+00 (a) 1.OE-01 I .OE-02 M-9 1 '

0.~~~~~

.0E 03 A.v..........

.......................... t Require .. .Av

.C. .

In

" a 0 0 V9 co

@ e C9 4N lAvg Indicator _ Avg Control Avg-Pre Op Required LLDsl (a) Chemobyl 59 COI -

4.3 AirborneRadioiodine 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 no positive activity 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.

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 confirm 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 2002.

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 three of the four composites analyzed. The average yearly Sr-90 measured at the indicator location was 1.95 pCi/L. The long-term activity trend for Sr-90 continues to slowly decrease. It should be noted that Sr-90 is not 60

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 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 Food Products Three samples were collected and analyzed by gamma spectroscopy. The results 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 other gamma emitters were 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 61

presented in Table 3-10 and trending graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.

Cobalt-60 was detected in both indicator samples collected in 2002. The average level observed from the station discharge at 53 pCi/kg is station related and is comparable to levels detected in past years. Cobalt-60 was detected in 2001 with an average activity of 46.5 pCi/kg. In 1999, cobalt-60 was detected with an 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 concentrations as high as 800 pCi/kg (dry weight). In 2002, cesium-137 was detected with an average indicator location concentration of 286 pCi/kg and an average control location concentration of 224 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 4-4: COBALT-60 IN SILT 1.OE+04 1OE+03 A l.OE+02

.OE+O1 L.OE+OO ON Cl r- \~~~'O r-vO 00 r-oo 0

oN 00 C9 00 N

'T 00 ON

~.O 00 ON 00 00 oN 0D oall Cl4 O1 ON

'I ON ON NO 00 0 C o o CD C 1- C-ot oo - k m -oo- Discharge

_ _ es ~es Control - Chickahominy -- Station Dischargel Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDL.

Station Discharge was < MDL activity 1996 through 1998.

62 C* j

Figure 4-5: CESIUM-137 IN SILT 1.OE+04 X l.OE+03 0..O I , l l I- , , I , ,

1LOE+02 I . ~~~~~~~~~~~~~~~~

II . . I I ~~~~~~~~~~~~. I I I .

Cl4 'I 1.O 00 0 Cl4 Il sO 00 0 't 'o 00 F b r- t- 00 00 as

-f ON -z ON ON-r ON

-E ON 00 O~

00 ON 00 O\

ol O

O\

_ O O\

OC al ON o C o

+ Control - Chickahominy & Station Discharge

- Avg-Pre-Op - Required LLD 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.

63

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. Only naturally occurring potassium-40 activity at levels comparable to past years was detected.

4.14 Crabs A crab sample was collected in June from the station discharge canal and analyzed by gamma spectroscopy. The results of this analysis are presented in Table 3-15. Other than naturally occurring potassium-40, no other gamma emitting radioisotope was detected in this sample. This is consistent with pre-operational data and data collected during the past ten years.

64

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2002 - Surry Date of Location Description Sampling Reason(s) for Loss/Exception FE Air Part. 03/12/02 Air sampler malfunction. Sample volume was Gross Beta insufficient to meet the gross beta LLD with the standard sample count time. Prior to sampler malfunction, sufficient activity was deposited on the filter to determine a gross beta activity.

Because a quantifiable activity was determined, a reanalysis with an extended count time was not performed to meet the LLD.

65

6. CONCLUSIONS The results of the 2002 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. A new type of TLD was placed in the field in 2001. The ambient dose trend has reduced from that of the previously used TLD. This trend will continue to be monitored and evaluated.

Airborne Exposure Pathway - Air particulate gross beta concentrations at all of the indicator locations for 2002 trend well with the control location.

The gross beta concentrations also indicate a steady trend over the past decade. Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected.

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 concentration of strontium-90 in this year's analysis was 1.95 pCi/L.

Strontium-90 is not a part of station effluents, but rather, a product of nuclear weapons testing fallout. The long-term activity trend continues to decrease.

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 2002.

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.

River Water - All river water samples were analyzed for gamma emitting radioisotopes. Naturally occurring potassium-40 was detected in many of the samples. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2002.

66

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 Biota

1. 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.

2. Oysters and Clams - Naturally occurring potassium-40 was detected in three of the four oyster samples and in five of the eight clam samples. A review of the previous ten years indicates the potassium-40 in clams and oysters is at average environmental levels. There were no other gamma emitting radioisotopes detected in any of the samples. This trend is consistent with pre-operational data.

3. Crabs - Naturally occurring potassium-40 was detected in the crab sample. No other gamma emitting radioisotopes were detected.

67

REFERENCES 68

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.

69

APPENDICES 70

APPENDIX A: LAND USE CENSUS Year 2002 71

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January 1 to December 31, 2002 Page 1 of 1 l lI Nearest Nearest l Nearest Nearest I Sectorl Direction I Resident I Garden** I Cow I Goat N 4.12 @30° (a) (a) (a)

NNE 1.90 2 340 1.90 @ 340 (a) (a)

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

ENE (a) 4.91 @ 56° (a) (a)

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

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

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

SSE 4.75 @ 1520 5.00 @ 1600 (a) (a)

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

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

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

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

W 3.15 @ 260° 4.14 @2690 (a) (a)

WNW 4.79 @ 2810 (a) (a) (a)

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

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

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

- Area greater than 50 m2 and contains broadleafvegetation.

(a) None 72

APPENDIX B: DOMINION NUCLEAR CONNECTICUT QUALITY ASSURANCE PROGRAM YEAR 2002 73

INTRODUCTION Dominion Nuclear Connecticut (DNC) maintains an independent non-required quality assurance (QA) program as part of the radiological environmental monitoring program (REMP). The QA program consists of contractor appraisals and quality control samples.

DNC QA PROGRAM The DNC 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 DNC Radiological Engineering Instructions RAB B-3, 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 QA Program is not the only QA Program that monitors REMP radioanalysis performance. Other programs include:

1. Contractor lab's internal QA program. In addition to the DNC 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.

3. Contractor lab's participation in the National Institute of Standards and Technology (NIST) 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). 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 samples.

74

RESULTS OF DNC QA PROGRAM FOR CONTRACTOR RADIOANALYSES Criteria for passing QA sample analysis is that the result be within 20% of the known spike except in the case of strontium-89 or strontium-90 spikes in milk which have to be within 30% of the known spike. To allow more tolerance for lower activity spikes, an alternate criterion is used. If the two sigma error range of the analyzed result includes the known spike value, the result passes.

The DNC QA Program indicated that the contractor lab's environmental radiological analysis program was adequate in 2002. Results are shown on Table B-2. Of 97 analysis results on QA samples, 77 passed criteria, for a 79% 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.

75

TABLE B-1 QUALITY CONTROL SAMPLES o~~~~~~~i AAE~~~~~~~~~~~~~~~~~

~~~~~~~ . i4 ES.

~~~~~~OO~~~~~~~~~N~~~~~~~ANAr~~

l ,

fNp5ote,l ii'i'l'35I Milk - Strontium 3 (Note 2) 12 Milk- Iodine 4 36 Milk - Gamma (Note 3) 36 Water- Gamna 58 24 Water - Tritium 4 32 Oysters - Gamma 5 60 Vegetation/Aquatic Flora/Sediment - Gamma 0 2079 Air Particulate - Gross Beta 4 832

- Iodine 4 416

- Gamma 15 740

1. All samples are spikes except fish/invertebrate that are duplicate oyster samples from the Millstone quarry.

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

3. Gamma in water QA spikes are treated as milk surrogates.

TABLE B-2 RESTTTS OlF 9009 OfLIATY CONTROT SAMPTF ANAT.YSES Milk - Strontium 3 0 Milk - Iodine 4 0 Water - Gamma 49 9 Water - Tritium 4 0 Oysters - Gamma 5 0 Air Particulate Gross Beta 2 2 Iodine 1 3 Gamma 9 6 TOTALS Samples: 77 Samples: 20*

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

76

APPENDIX C:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2002 77

INTRODUCTION This appendix includes the Interlaboratory Comparison Program (ICP) of the Framatome ANP DE&S Environmental Laboratory. Framatome uses independently prepared QA/QC samples to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP). The suite of 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. The suite was modified to more closely to match the media mix presently being processed by Framatome. The Framatome ANP DE&S Environmental Laboratory's Interlaboratory Comparison Program for environmental sample analyses consists of samples from the following three sources:

1. Environmental Crosscheck Program administered by Analytics, Inc.,

2. Environmental Resource Associates (ERA) Proficiency Test (PT) Program, and

3. Department of Energy (DOE) Quality Assessment Program (QAP).

All samples required by the ODCM for Surry Power Station were included in the ICP for the year 2002. Of the 151 analyses, only one analysis did not meet the acceptance criteria. Results are presented in tables and trending graphs on the following pages. Trending graphs are provided when there were two or more data points to plot.

78

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 1 OF 4) 1st Quarter Identification Reported Known 2002 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E3096-186 Milk 1-131 LL pCi/L 99 90 1.09 A Ce-141 pCi/L 32 29 1.10 A Cr-51 pCi/L 262 241 1.09 A Cs-134 pCi/L 103 110 0.94 A Cs-137 pCi/L 248 240 1.03 A Mn-54 pCilL 224 202 1.11 A Fe-59 pCi/L 112 104 1.08 A Zn-65 pCi/L 215 199 1.08 A Co-60 pCi/L 144 142 1.01 A E3027-162 Milk 1-131 pCi/L 87.9 92 0.96 A 1-131LL pCi/L 93 92 1.01 A Ce-141 pCi/L 317.8 326 0.98 A Cr-51 pCi/L 277 267 1.04 A Cs-134 pCi/L 119 122 0.98 A Cs-137 pCiIL 271.2 266 1.02 A Mn-54 pCi/L 231.2 224 1.03 A Fe-59 pCi/L 123.6 116 1.07 A Zn-65 pCi/L 225.9 221 1.02 A Co-60 pCi/L 152.9 158 0.97 A E3028-162 Milk Sr-89 pCi 79.9 83 0.96 A Sr-90 pCi 24.7 27 0.93 A E3023-162 Water Gr-Beta pCi/L 310.3 313 0.99 A E3024-162 Water 1-131 pCi/L 54.5 61 0.90 A 1-131LL pCi/L 63.4 61 1.04 A Ce-141 pCi/L 239.4 242 0.99 A Cr-51 pCi/L 175.7 198 0.89 A Cs-1 34 pCi/L 87.8 91 0.97 A Cs-137 pCi/L 197.7 197 1.01 A Mn-54 pCi/L 168.5 166 1.02 A Fe-59 pCi/L 87.6 86 1.02 A Zn-65 pCi/L 157.2 164 0.96 A Co-60 pCi/L 114.6 117 0.98 A E3026-162 Filter Gr-Beta pCi 149 136 1.1 A E3097-186 Charcoal 1-131 pCi 74 77 0.96 A E3098-186 Charcoal 1-131 pCi 65 69 0.94 A E3099-186 Charcoal 1-131 pCi 91 87 1.05 A Footnotes are on page 4 of 4.

79

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 2 OF 4) 2nd Quarter Identification Reported Known 2002 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E3153-162 Milk 1-131 pCi/L 88 87 1.01 A 1-1 31 LL pCi/L 85 87 0.98 A Ce-141 pCi/L 86 90 0.96 A Cr-51 pCi/L 230 235 0.98 A Cs-1 34 pCi/L 121 120 1.01 A Cs-1 37 pCi/L 89 91 0.98 A Co-58 pCi/L 100 100 1.00 A Mn-54 pCi/L 97 95 1.02 A Fe-59 pCi/L 83 81 1.02 A Zn-65 pCi/L 179 180 0.99 A Co-60 pCi/L 127 125 1.02 A E3148-162 Water H-3 pCi/L 6970 6970 1.00 A E3149-162 Water Sr-89 pCi/L 42 64 0.66 U (1)

Water Sr-90 pCi/L 36 39 0.92 A E3150-162 Filter Gr-Beta pCi (2) (2) (2) (2)

E3151-162 Filter Ce-141 pCi 59 61 0.97 A Cr-51 pCi 165 160 1.03 A Cs-1 34 pCi 77 82 0.94 A Cs-1 37 pCi 64 62 1.03 A Co-58 pCi 68 68 1.00 A Mn-54 pCi 69 65 1.06 A Fe-59 pCi 62 55 1.13 A Zn-65 pCi 131 122 1.07 A Co-60 pCi 82 85 0.96 A E3151-162 Filter Sr-90 pCi 41 48 0.85 A

- (1) Sample was not analyzed in a timely manner due to high volume of client samples.

(2) Filter damaged during sample preparation.

80

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 3 OF 4) 3rd Quarter Identification Reported Known 2002 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E3292-162 Milk 1-131 pCi/L 79 80 0.99 A 1-131 LL pCi/L 77 80 0.96 A Ce-141 pCi/L 156 160 0.98 A Cr-51 pCi/L 231 227 1.02 A Cs-134 pCi/L 128 132 0.97 A Cs-137 pCi/L 122 127 0.96 A Co-58 pCi/L 95 97 0.98 A Mn-54 pCi/L 151 152 0.99 A Fe-59 pCi/L 94 89 1.06 A Zn-65 pCi/L 180 187 0.96 A Co-60 pCi/L 142 149 0.95 A E3293-162 Milk Sr-89 pCi 84 92 0.91 A Sr-90 pCi 36 39 0.92 A E3288-162 Water Gr-Beta pCi/L 204 239 0.85 A E3289-162 Water 1-131 pCi/L 68 79 0.86 A 1-131 LL pCi/L 77 79 0.97 A Ce-141 pCi/L 209 214 0.98 A Cr-51 pCi/L 289 304 0.95 A Cs-134 pCi/L 169 176 0.96 A Cs-137 pCi/L 167 169 0.99 A Co-58 pCi/L 129 130 0.99 A Mn-54 pCi/L 206 204 1.01 A Fe-59 pCi/L 118 119 0.99 A Zn-65 pCi/L 251 251 1.00 A Co-60 pCi/L 187 199 1.04 A E3291-162 Filter Gr-Beta pCi 144 155 0.93 A 81

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 4 OF 4) 4th Quarter Identification Reported Known 2002 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E3466-162 Milk 1-131 pCi/L 81 86 0.94 A 1-131 LL pCi/L 89 86 1.03 A Ce-141 pCi/L 103 111 0.93 A Cr-51 pCi/L 334 346 0.97 A Cs-134 pCi/L 98 99 0.99 A Cs-137 pCi/L 220 220 1.00 A Co-58 pCi/L 134 139 0.96 A Mn-54 pCi/L 142 142 1.00 A Fe-59 pCi/L 74 72 1.03 A Zn-65 pCi/L 177 178 0.99 A Co-60 pCi/L 162 164 0.99 A E3461-162 Water H-3 pCi 5450 5987 0.91 A E3462-162 Water Sr-89 pCi 72 79 0.91 A Sr-90 pCi 16 16 1.00 A E3463-162 Filter Gr-Beta pCi 147 150 0.98 A E3464-162 Filter Ce-141 pCi 59 59 1.00 A Cr-51 pCi 184 184 1.00 A Cs-134 pCi 51 53 0.96 A Cs-137 pCi 125 117 1.07 A Co-58 pCi 75 74 1.01 A Mn-54 pCi 83 75 1.11 A Fe-59 pCi 43 38 1.13 A Zn-65 pCi 103 95 1.08 A Co-60 pCi 84 87 0.97 A E3465-162 Filter Sr-90 pCi 61 60 1.02 A (a) Framatome reported result.

(b) The Analytics standard.

(c) Ratio of Framatome to Analytics results.

(d) Analytics evaluation: A= Acceptable. W= Acceptable with waming. U= Unacceptable.

82

QAP/DOE-EML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 1 OF 1)

Identification Reported Known Ratio (c)

Month/Year Number Media Nuclide Units Value (a) Value (b) FRM/EML Evaluation (d)

January - QAP 56 Water Co-60 Bq/L 350.300 347.330 1.009 A June 2002 Cs-1 37 Bq/L 55.300 56.067 0.986 A Sr-90 Bq/L 6.260 7.579 0.826 A H-3 Bq/L 309.000 283.700 1.089 A Gr-Beta Bq/L 951.000 1030.000 0.923 A Filter Co-60 Bq 29.700 30.520 0.973 A Cs-1 37 Bq 28.400 28.230 1.006 A Mn-54 Bq 38.700 38.530 1.004 A Sr-90 Bq 4.100 4.832 0.849 A Gr-Beta Bq 1.174 1.300 0.903 A July - QAP 57 Water Co-60 Bq/L 257.200 268.570 0.957 A December 2002 Cs-1 34 Bq/L 60.700 60.200 1.008 A Cs-I 37 Bq/L 79.700 81.430 0.979 A Sr-90 Bq/L 7.770 8.690 0.894 A H-3 Bq/L 252.100 227.300 1.109 A Gr-Beta Bq/L 808.700 900.000 0.899 A Filter Co-60 Bq 23.195 23.000 1.008 A Cs-1 37 Bq 33.400 32.500 1.028 A Mn-54 Bq 51.680 52.200 0.990 A Sr-90 Bq 4.820 5.561 0.867 A Gr-Beta Bq 0.785 0.871 0.901 A (a) Framatome reported result.

(b) The DOEIEML standard.

(c) Ratio of Framatome to DOE/EML results.

(d) DOEIEML evaluation: A=acceptable, W=acceptable with waming, N=not acceptable.

83

PTIERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 1 OF 1)

Identification Reported Known ERA Control Month/Year Number Media Nuclide Units Value (a) Value (b) Limits (c) Evaluation (d)

January - 12030105 Water Gr-Beta pCi/L 16.9 16.3 7.6 - 25.0 A June 2002 RAD-49 Water Gr-Beta pCi/L 174 189 140 - 238 A Co-60 pCi/L 39.5 39.1 30.4 - 47.8 A Cs-134 pCi/L 17.1 17.1 8.44 - 25.8 A Cs-137 pCi/L 53.6 52.1 43.4 - 60.8 A 1-131 LL pCi/L 19.5 14.7 11.2- 18.2 NA (1)

H-3 pCi/L 17100 17400 14400 - 20400 A Sr-89 pCi/L 31.1 31.7 23.0 - 40.4 A Sr-90 pCi/L 28.6 28.3 19.6 - 37.0 A July - RAD-50 Water Gr-Beta pCi/L 23.1 21.9 13.2 - 30.6 A December 2002 Ba-1 33 pCi/L 74.9 80 66.4 - 93.6 A Co-60 pCi/L 24.5 23.3 14.6 - 32.0 A Cs-1 34 pCi/L 73 71.7 63.0 - 80.4 A Cs-1 37 pCi/L 228 214 195 - 233 CE (2)

Zn-65 pCi/L 95.6 95.7 79.4 - 112 A Sr-89 pCi/L 26.3 29 20.3 - 37.7 A Sr-90 pCi/L 33.3 36.4 27.7 - 45.1 A RAD-51 Water H-3 pCi/L 10100 10200 8440 - 12000 A 1-1 31 LL pCi/L 6.83 6.76 3.30 - 10.2 A

- (1) Equipment problem with iodine probe. Probe replaced and re-analysis result was acceptable at 14.5 pCi/L.

(2) A review of the sample documentation, Proficiency Test participant data and instrument calibration data was perfonmed. No problems were noted with any sample or calibration documentation.

(a) Framatome reported result.

(b) The ERA standard.

(c) Range of acceptable results.

(d) ERA evaluation: A=acceptable. Reported result falls within the Waming Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for enor. Reported result falls within the Control Limits and outside of the Waming Limits.

84

1-131 IN MILK 120 -

100 80 a P 60-cL 40-20 -

0- I 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l FRM L Analytics Ce-141 IN MILK 400 -

300 S-

> 200-cS u 100 0 a 0

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l*FRM Analytics Cr-51 IN MILK 360 340 U 320 L. -

,I 300 3 280 I t 260 240 a_ _ _

200 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l* FRM

nalytics 85 CA(

Cs-134 IN MILK 200 -

- 180 -

s 160-

3 140 -

Q 120 w 1/1/02 4/202 7/2V02 10/1/02 1/1/03 I* FRM Analytics Cs-137 IN MILK 300 -

250 1 we 200-J 150-100 w 50 0 l I 1/1/02 4/2/02 7/202 10/1/02 1/1/03

FRM Analytics Mn-54 IN MILK 300

- 250-2 200 i i-ri 150 *a CL 100 50l 1/1/02 4/202 712/02 10/1/02 1/1/03 l FRM

Analytics 86

("l \

Fe-59 IN MILK

> 100 50 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM

Analytics Zn-65 IN MILK 300 275 -

250 -

225 i L-

,> 2001 L) 175- 0 9 l 150 -

125 -

100 I 1/1/02 412/02 7/2/02 10/1/02 1/1/03

FRM

Analytics l Co-60 IN MILK 200 180 -

L.

, 160-J3 I L) 140 120 100 1/1/02 4/2/02 7/2/02 10/l/02 1/l/03

FRM m Analytics 87

Sr-90 IN MILK 60-40 X. T 20 -

0- I l 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM Analytics Co-58 in Milk 150

- 130 -

j 110k t 90

0-i 70 50 l l 1/1/02 4/2/02 7/02 10/1/02 1/1/03 l*FRM Anaytics Sr-89 in Milk 150 130 cj 110

0. 90 70 50 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 I+ FRM Analytics 88 cv?

Ce-141 IN FILTERS 100 80

,_ 60 is 0 CL40 20 1/1/02 4/2/02 7/2102 10/1/02 1/1/03

FRM

Analytics l Cr-51 IN FILTERS 200 180

._ 160 A

' 140 120 100 1/1/02 4/2/02 7/2/02 10/l/02 1/1/03 I* FRM

Analytics Cs-134 IN FILTERS 100 80

,_ 60

) 1 40 20 0

1/1/02 4/2/02 7/2102 10/1/02 1/1/03 l FRM

Analytics 89 C A) r

GROSS BETA IN FILTERS 200 180 160 L140iI 120 100 l 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM

Analyticsl 1-131 IN CHARCOAL CARTRIDGE 100 --

80 l a

I 60 ,

Cf 40-20-0 I 1/1/02 4/202 7/2/02 10/1/02 1/1/03

FRM

Analytics 90

Cs-137 IN FILTERS 200 -

160 -

._120 -

CL 80-40 -

0 l 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM

Analytics Mn-54 IN FILTERS 100 80 60: '

0.

40 20 0

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l*FRM Analyticsl Fe-59 IN FILTERS 100 80

,_ 60-

'. 40 A 20 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM

Analytics 91

Zn-65 IN FILTERS 200 160 120 a 80 40 0

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM

Analytics Co-60 IN FILTERS 100 80 I g 60 0 CL40-20 0

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l- FRM

Analyticsl Co-58 IN FILTERS 100 80 a

60 40 20 0 I 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l FRM

Analytics 92 c.ri

H-3 IN WATER 7500 7000 L-g 6500

-j c3 6000 1/11/02 4/2102 7/2102 10/1/02 1 1 0.

5500 I I~~~~~~~~~~~

5000 1/1 1/02 4/2/02 7/2102 10/1/02 1/1/03 l* FRM Analytics Sr89 IN WATER 1.OE+02 8.0E+01 L.

,S 6.OE+01 -

0 4.OE+01 a.

2.OE+01 O.OE+00 1/1/02 4/2102 7/2/02 10/1/02 1/1/03 l* FRM

Analytics Sr-90 IN WATER 1.OE+02 8.OE+01 -

L..

._ 6.OE+01-o3 4.OE+01

0. 9 2.OE+01 O.OE+00 I 1/1/02 4/2/02 7/2/02 10/1/02 /1/03 l FRM

Analytics 93 cil i

Ba-133 IN WATER 100 80

. 6 S C 40 20 0- I 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM *ERA Co-60 IN WATER 100 80 I-

) 60 U3 40 m 20 a 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l*FRM ERAI Cs-134 IN WATER 100 -

80 -

I- a

S 60 i 40-0.

20 -

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM ERA 94 C

Cs-137 IN WATER 300 250 -

& 200 J 150-50 00 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 I*FRM ERA]

Zn-65 IN WATER 200-160-N-

2 120 C. 80 -

0.

40 -

0 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l*FRM ERA Sr-89 IN WATER 100 80 -

I-

0

-J C) 40 20 0 -I 1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l*FRM ERA 95 cZ°

Sr-90 IN WATER 100 80 S 60 O 40 20 0 -

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM ERA 1-131 IN WATER 50 40 -

I-2 30-( 20-0.~~~

10 10 - I 0~~~~~~~~~~

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03

FRM ERA GROSS BETA IN WATER 200 160 L-

,2 120 Q 80 40 0

1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l*FRM ERA 96

(--71

ML031270721

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