ML031270721
| 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) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 29, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.
SS&UBAG Docket Nos.
License Nos.03-306 50-280 50-281 72-2 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
> Dominionw
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:
Prepared by:
Reviewed by:
Reviewed by:
</
IV-J. Eakin ervisor Radiological Engineering Dominion Nuclear Connecticut P. F. Blount Health Physicist Dominion Surry Power Station 4+~ i w SS B. A. Hilt Supervisor Radiological Analysis and Material Control Dominion Surry Power Station 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 and Analysis 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
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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 TLDs West North West Surry Station Discharge North North West North North North East North East East North East East (Exclusion)
West West South West South West South South West South South South East South East East Station Intake Hog Island Reserve Bacon's Castle Route 633 Alliance Surry Route 636 and 637 Scotland Wharf Jamestown Colonial Parkway Route 617 and 618 Kingsmill Williamsburg Kingsmill North Budweiser Water Plant (00)
(02)
(03)
(04)
(05)
(06)
(07)
(08)
(09)
(10)
(I 1)
(12)
(13)
(14)
(15)
(16)
(17)
(18)
(19)
(20)
(21)
(22)
(23)
(24)
(25)
(26)
(27)
(28)
(29)
(30)
(31)
(32)
(33) 0.17 mi WNW 0.60 mi NW 0.40 mi NNW 0.29 mi N
0.28 mi NNE 0.31 mi NE 0.43 mi ENE 0.31mi E
0.40 mi W
0.45 mi WSW 0.30 mi SW 0.43 mi SSW 0.48 mi S
0.74 mi SSE 1.00 mi SE 0.57 mi E
1.23 mi ESE 1.94 mi NNE 4.45 mi SSW 5.00 mi SW 5.10mi WSW 8.00 mi WSW 4.00 mi W
5.00 mi WNW 6.30 mi NW 3.70 mi NNW 4.70 mi NNW 4.80 mi N
7.80 mi N
5.60 mi NNE 5.70 mi NNE 4.80 mi NE 2920 3090 3300 3570 220 450 680 900 2700 2500 2250 2030 1800 1570 1350 900 1130 260 2020 2240 2480 2500 2700 2850 3100 3300 3400 20 00 140 270 410 Quarterly Onsite (Stored in lead container outside protected area)
Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Onsite Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Near Resident Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Population Center Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Population Center Quarterly Apx. 5 mile Quarterly Population Center Quarterly Apx. 5 mile 10
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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 Lee Hall Goose Island Fort Eustis Newport News James River Bridge Benn's Church Smithfield Rushmere Route 628 Air Charcoal Surry Station and Particulate Hog Island Reserve Bacon's Castle Alliance Colonial Parkway BASF Fort Eustis Newport News (34) 5.10 mi ENE (35) 7.10 mi ENE (36) 5.00 mi E
(37) 4.80 mi ESE (38) 16.50 mi ESE (39) 14.80 mi SSE (40) 14.50 mi S
(41) 11.50mi S
(42) 5.20 mi SSE (43) 5.00 mi S
(SS) 0.37 mi NNE (HIR) 2.00 mi NNE (BC) 4.50 mi SSW (ALL) 5.10 mi WSW (CP) 3.70 mi NNW (BASF) 5.10 mi ENE (FE) 4.80 mi ESE (NN) 16.50 mi ESE 700 Quarterly Apx. 5 mile 730 Quarterly Population Center 880 Quarterly Apx. 5 mile 1070 Quarterly Population Center 1220 Quarterly Population Center 1470 Quarterly Control Location 1750 Quarterly Control Location 1760 Quarterly Control Location 1560 Quarterly Apx. 5 mile 1770 Quarterly Apx. 5 mile 150 Weekly Site Boundary (Highest D/Q) 260 Weekly 2020 Weekly 2480 Weekly 3300 Weekly 700 Weekly 1070 Weekly 1220 Weekly Control Location River Water Surry Station Discharge (SD) 0.17 mi NW Scotland Wharf (SW) 5.00 mi WNW 3250 Monthly 2850 Monthly Control Location Well Water Surry Station Hog Island Reserve Shoreline Hog Island Reserve Sediment Chickahominy River (SS)
(HIR) 2.00 mi NNE (HIR) 0.80 mi N
(CHIC) 11.20 mi WNW Quarterly Onsite 270 Quarterly 50 Semi-Annually 3000 Semi-Annually Control Location Chickahominy River (CHIC) 11.20 mi WNW Surry Station Discharge (SD) 1.30 mi NNW 3000 Semi-Annually Control Location 3410 Semi-Annually 11 Silt
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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 Colonial Parkway Pivarnik Epp's (CP)
(PIV)
(EPPS) 3.70 mi 17.60 mi 4.80 mi NNW NNE SSW 3370 250 2010 Monthly Monthly Monthly Control Location Point of Shoals Mulberry Point (POS)
(MP) 6.40 mi SSE 4.90 mi ESE 157° Semi-Annually 1240 Semi-Annually Chickahominy River Surry Station Discharge Hog Island Point Lawne's Creek (CHIC)
(SD)
(HIP)
(LC) 11.20 mi 1.30 mi 2.40 mi 2.40 mi WNW NNW NE SE 3000 3410 520 1310 Semi-Annually Semi-Annually Semi-Annually Semi-Annually Control Location Surry Station Discharge (SD) 1.30 mi NNW 3410 Semi-Annually Surry Station Discharge (SD) 1.30 mi NNW 3410 Annually Food Products (Corn, Peanuts, Soybeans)
Brock's Fann Slade's Farm (BROCK'S) 3.80 mi (SLADE'S) 2.40 mi S
S 1880 Annually 1770 Annually 12 Milk Oysters Clams Fish Crabs
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 Cs-137 Gamma Isotopic Cs-134 Cs-137 I-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Footnotes located at end of table.
14 Silt 150 180 Milk Semi-Annual Monthly 150 180 pCi/kg - dry pCi/L 1
15 18 60 15 Oysters Clams Semi-Annual Semi-Annual Annually pCi/kg - wet pCi/kg - wet pCi/kg - wet Crabs 130 260 130 130 260 130 150 130 260 130 130 260 130 150 130 260 130 130 260 130 150
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 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 130 260 130 130 260 130 150 Food Products Annually Gamma Isotopic I-131 Cs-134 Cs-137 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 accordance with the Surry Radiological Environmental Monitoring Program. Actual analysis ofthe samples by the Framatome laboratory may be lower than those LLD values listed.
(a) Quarterly composites of each location 's weekly airparticulate samples are analyzedfor gamma emitters.
15 pCi/kg - wet 60 60 80
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I C83308
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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
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I 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 Figure 4. Surry Emergency Plan Map Air Sampling Stations
- Nearest Residents TLD Sampling Nearest Milk Animal Nearest Garden
- Aquatic Samples
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1 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 Figure 5. Surry Emergency Plan Map Air Sampling Stations
- Nearest Residents TLD Sampling Nearest Milk Animal Nearest Garden
- Aquatic Samples
- 3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the Surry Offsite Dose Calculation Manual (ODCM),
a summary table of the analytical results has been prepared and is presented in Table 3-1. A more detailed analysis of the data is given in Section 4.
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 Air lodine 1-131 (pCi/m3) 416 0.07
< LLD Air Gross 416 Particulate Beta (1 E-3 pCi/m 3)
Gamma 32 10 24.6(364/364)
(8.9-79.7)
ALL 5.1 mi.
26.2(52/52)
WSW (8.9-41.3)
Be-7 32 Cs-134 32 Cs-137 32 87(28/28)
(47-141) 50
< LLD 60
< LLD NN 16.5 mi.
98(4/4)
ESE (55-120)
N/A N/A
< LLD
< LLD Gamma 24 24 Th-228 24 122(10/12)
(59-155)
< LLD 1-131 24 10
< LLD Fe-59 24 30
< LLD Co-58 24 15
122(10/12)
NW (59-155)
N/A N/A N/A
< LLD
< LLD
< LLD N/A
< LLD N/A
< LLD N/A
< LLD
- LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
22 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 N/A
< LLD
< LLD 0
24.9(52/52)
(9.946.2) 0 River Water (pCi/Liter) 98(4/4)
(55-120)
< LLD
0 0
88(6/12)
(36-135)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 0
0 0
0 0
0 0
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Sury Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 30
< LLD Page 2 of 8 N/A
< LLD
< LLD 0
Zr-95 24 30
< LLD Nb-95 24 15
< LLD Cs-134 24 15
< LLD Ba-140 24 60
< LLD La-140 24 15
2000
< LLD Gamma 8 1-131 8
1
Fe-59 8
Co-58 8
15
< LLD 30
< LLD 15
< LLD
- LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
23 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 Water (pCi/Liter)
Gamma 24 Zn-65 24 N/A
< LLD N/A N/A N/A
< LLD
< LLD
< LLD
< LLD N/A
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 0
0 0
0 0
0 0
N/A
< LLD Well Water (pCi/Liter)
N/A
< LLD N/A
< LLD N/A N/A 0
< LLD N/A N/A 0
< LLD N/A N/A 0
< LLD N/A 0
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 3 of 8 Gamma 8 Co-60 8
15
< LLD N/A
< LLD N/A 0
Zn-65 8
30
< LLD Zr-95 8
30
< LLD Nb-95 8
15
< LLD Cs-134 8
15
18
< LLD Ba-140 8
60
< LLD La-140 8
15
2000
< LLD 15785(2/2)
(13770-17800)
CHIC 11.2 mi.
17335(2/2) 17335(2/2)
WNW (17170-17500) (17170-17500)
Th-228 4
975(2/2)
(959-990)
Cs-134 4
150
< LLD CHIC 11.2 mi.
1215(2/2)
WNW (1150-1280)
N/A
< LLD 1215(2/2)
(1150-1280)
< LLD LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
24 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 Water (pCi/Liter)
N/A
< LLD N/A N/A 0
< LLD N/A N/A 0
< LLD N/A N/A 0
< LLD N/A N/A 0
< LLD N/A N/A 0
< LLD NJA N/A 0
Silt (pCi/kg dry)
0
< LLD N/A 0
0 0
0
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 4 of 8 Silt Gamma 4 (pCi/kg dry) Cs-137 4
180 286(2/2)
(259-313)
SD 1.3 mi.
286(2/2)
NNW (259-313)
Co-60 4
Shoreline Gamma 4 Sediment (pCi/kg dry) K-40 4
Th-228 4
53(2/2)
(38-67) 7865(2/2)
(6780-8950) 127(2/2)
(116-138)
Cs-134 4
150
180
53(2/2)
NNW (38-67)
HIR 0.8 mi.
7865(2/2)
N (6780-8950)
CHIC 11.2 mi.
666(2/2)
WNW (131-1200)
N/A
< LLD N/A
1398(12/12)
NNW (1240-1520) 1324(12/12)
(1037-1770) 1-131 36 1
< LLD Cs-134 36 Cs-137 36 Strontium Sr-89 4
Sr-90 4
15
< LLD 18
< LLD
< LLD 1.95(3/4)
CP 3.7 mi.
1.95(3/4)
(1.52-2.5)
NNW (1.52-2.5)
- LLD is 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 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 224(2/2)
(212-236) 0
< LLD 1025(2/2)
(970-1080) 666(2/2)
(131-1200)
< LLD
< LLD 0
0 0
0 0
Milk (pCi/Liter)
Gamma 36 K-40 36 1392(24/24)
(1240-1520)
N/A 0
< LLD N/A
< LLD N/A
< LLD
< LLD
< LLD N/A
< LLD N/A 0
0 0
0
< LLD N/A 0
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2002 Docket No. 5-280-281 Page 5 of 8 60
< LLD N/A
< LLD
< LLD 0
La-140 36 Clams Gamma 8 (pCi/kg wet) K-40 8
15
< LLD (480-1090)
Mn-54 8
130
< LLD Fe-59 8
260
< LLD Co-58 8
130
130
< LLD Zn-65 8
260
< LLD Cs-134 8
130
150
< LLD Oysters Gamma 4 (pCi/kg wet) K-40 4
817(3/4)
(590-970)
N/A
< LLD 733(4/6)
HIP 2.4 mi.
840(1/2)
NE N/A N/A N/A
< LLD
< LLD
< LLD N/A
< LLD N/A N/A N/A
< LLD
< LLD POS 6.4 mi.
930(2/2)
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 Milk (pCi/Liter)
All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location Routine Pathway r
Reported Sampled Type Total LLD*
Mean Name Distance Mean Mean Measure-(Unit)
No.
Range Direction Range Range ments Gamma 36 Ba-140 36
< LLD 620(1/2)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD N/A
< LLD
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
<LLD
<LLD
<LLD
< LLD
<LLD 1560(1/1)
< LLD
< LLD
< LLD
<LLD
< LLD
< LLD
< LLD N/A N/A N/A N/A N/A SD N/A N/A N/A N/A N/A N/A N/A
<LLD
< LLD
< LLD
< LLD
< LLD 1.3 mi.
1560(1/1)
NNW
< LLD
< LLD
< LLD
<LLD
< LLD
< LLD
< LLD N/A N/A 0
0 N/A N/A N/A 0
0 0
N/A N/A N/A N/A N/A N/A N/A 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 Oysters (pCi/kg wet)
Crabs (pCi/kg wet)
Gamma 4 Co-58 4
Co-60 4
Zn-65 Cs-1 34 Cs-1 37 Gamma K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-1 34 Cs-137 130 130 260 130 150 130 260 130 130 260 130 150
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 2413(4/4)
(2200-2570) 130
< LLD 260
< LLD 130
< LLD 130
<LLD 260
< LLD 130
< LLD 150
< LLD 8433(313)
(3310-15610) 60
<LLD 60
< LLD 80
< LLD SD N/A N/A N/A N/A N/A N/A N/A Brock's Farm N/A N/A N/A 1.3 mi.
NNW 3.8 mi.
S 2413(4/4)
(2200-2570)
< LLD
< LLD
< LLD
<LLD
< LLD
< LLD
< LLD 8433(3/3)
(3310-15610)
<LLD
< LLD
< LLD
- LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
28 Fish (pCi/kg wet)
Food Products (pCi/kg wet)
Gamma K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-1 34 Cs-1 37 Gamma K-40 1-131 Cs-1 34 Cs-137 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Sury County, Virginia - 2002 Docket No. 5-280-281 Page 8 of 8 Gamma 168 2
2.9(156/156) STA-38 16.5 mi.
(0.9-5.9)
ESE
- 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 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 Radiation TLD (mR/
Std.Month) 5.4(4/4)
(4.5-5.9) 3.8(12/12)
(1.4-6.6) 0
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 handled as 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
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SURRY 2002 TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (lE-3 PCI/M3)
L O C A T I O N S PERIOD ENDING JAN 09 JAN 15 JAN 22 JAN 29 SS 26.6 23.9 30.1 14.4 HIR
(+/-)
3.1 3.0 3.1 2.8 27.4 24.0 30.5 18.1
(+/-)
3.1 3.0 3.1 2.9 BC 28.1 27.2 28.9 19.6 ALL
(/
)
3.1 3.1 3.1 2.9 41.3 32.3 35.0 20.5 CP 3.7 3.2 3.2 3.0 27.4 26.5 35.4 19.4 2.7 21.1 2.9 22.2 2.6 21.4 2.5 A 23.0 2.5 2.9 2.6 2.7 26.0 24.3 25.8 29.9 2.7 24.4 2.9 24.2 2.7 21.4 3.0 24.9 2.7 3.1 2.7 2.8 24.4 22.8 23.8 28.1 2.7 2.9 2.7 2.9 25.4 24.9 22.0 24.2 2.7 23.7 3.0 23.9 2.7 23.3 2.8 24.1 3.0 24.4 2.8 29.1 2.3 18.0 3.9 25.6 2.6 17.6 6.8 C 20.3 2.4 16.7 2.6 21.5 2.8 21.0 3.1 20.0 2.5 22.4 2.5 20.2 2.4 21.0 2.4 2.4 2.4 2.6 2.7 3.1 2.5 2.4 2.3 24.8 29.1 24.0 22.1
- 23. 3 20.6 28.7 25.3 24.0 2.6 2.7 2.6 2.6 2.7 3.1 2.7 2.6 2.4 22.7 22.6 17.3 19.0 15.8 20.6 29.8 22.3 25.9 2.6 2.5 2.4 2.5 2.6 3.3 2.6 2.5 2.5 21.7 21.3 14.8 18.5 21.1 21.0 22.2 20.3 22.6 2.6 2.4 2.3 2.5 2.7 3.1 2.4 2.4 2.3 18.8 25.6 18.4 21.3 22.4 22.2 23.7 26.1 22.8 2.5 19.8 2.6 24.2 2.4 14.2 2.6 21.5 2.8 19.7 3.1 2.5 2.6 2.3 18.0 23.0 19.9 19.0 2.6 18.9 3.7 25.3 2.9 26.4 2.8 24.4 2.6 2.6 2.9 2.8 22.7 24.3 39.2 20.2 2.7 22.4 2.5 31.3 4.4 22.3 2.7 19.9 2.6 3.7 1.8 2.7 21.4 21.8 23.2 17.8 2.7 2.5 2.8 2.6 24.2 21.5 18.6 18.4 2.8 25.6 2.5 25.7 2.7 27.1 2.7 21.3 32 I
I FEB 05 FEB 12 FEB 19 FEB 26 BASF 20.6 20.5 18.8 23.3 2.5 2.9 2.6 2.8 FE 25.9 20.9 20.7 25.5 3.2 3.1 3.3 3.0 NN-C 29.6 27.2 35.2 21.4 3.1 3.1 3.2 3.0 MAR 05 MAR 12 MAR 20 MAR 26 18.6 27.9 17.1 26.1 30.8 28.3 35.4 22.0
(/
)
3.2 3.2 3.2 3.0 2.8 2.7 2.2 3.8 22.1 28.9 16.4 25.8 26.3 27.3 31.1 20.9 (3/1) 3.1 3.1 3.3 3.0 3.4 2.8 2.1 3.7 21.2 30.2 19.3 27.2 2.9 2.8 2.2 3.7 27.1 33.2 21.7 33.6 APR 02 APR 09 APR 16 APR 23 APR 30 MAY 06 MAY 14 MAY 21 MAY 29 3.0 2.8 2.2 3.7 17.4 20.8 15.0 18.5 21.6 19.2 17.8 21.0 22.5 2.7 3.0 2.7 2.8 19.5 30.5 18.5 27.8 2.4 2.4 2.3 2.5 2.7 3.0 2.3 2.4 2.4 2.8 2.8 2.2 3.7 19.8 32.3 18.3 23.3 23.3 20.6 25.2 22.9 24.9 21.8 55.0 16.0 29.7 2.9 12.0 B 2.1 3.9 25.6 27.4 18.9 25.9 3.1 2.8 2.2 3.7 JUN 04 JUN 11 JUN 18 JUN 25 18.2 18.6 19.2 31.4 2.5 2.4 2.7 5.8 D 20.9 32.3 24.0 24.8 2.5 2.5 2.3 2.6 2.7 3.0 2.4 2.4 2.2 2.8 2.6 2.9 2.8
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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 JUL 02 JUL 09 JUL 16 JUL 23 JUL 30 SS 16.3 35.1 15.1 40.2 21.8 2.2 3.4 2.4 3.4 3.1 HIR 19.0 30.7 15.3 38.7 23.2 2.3 3.0 2.4 3.1 3.2 BC 22.0 42.7 13.2 39.4 23.1 ALL
(+/-)
2.5 3.7 2.3 3.7 3.1 20.6 30.4 12.2 38.9 21.6 CP 2.4 3.0 2.3 3.2 3.1 18.9
- 35. 0 16.3 37.1 21.2 2.3 3.2 2.4 3.1 3.1 BASF FE 4.5 3.1 2.6 3.7 30.4 22.3 24.9 33.6 2.5 8.9 3.0 22.2 3.6 24.3 4.5 33.8 3.7 25.5 3.6 28.8 3.0 22.6 3.7 23.8 3.5 31.6 3.6 23.9 3.4 27.5 3.3 18.7 3.7 28.5 3.8 3.0 2.5 2.8 2.4 2.9 3.3 3.6 3.5 3.0 3.1 3.2 3.4 3.4 3.5 3.2 3.5 31.5 23.8 23.4 31.8 9.7 20.9 22.6 29.9 25.3 35.0 18.0 26.3 27.2 22.6 24.6 18.1 23.5 3.9 3.1 2.5 2.7 2.4 2.8 3.2 3.4 3.5 3.3 2.9 3.3 3.1 3.1 3.4 3.2 3.3 32.2 19.7 22.3 31.6 10.3 18.5 24.5 31.6 24.0 29.5 18.8 23.9 30.1 20.8 22.2 18.0 24.9 3.9 30.4 2.5 B 24.7 2.6 22.8 2.7 31.8 2.5 10.0 2.8 19.4 3.3 27.3 3.5 30.0 3.5 23.9 3.0 31.2 3.0 20.0 3.2 25.7 3.9 27.5 3.3 24.3 3.3 22.4 3.2 20.9 3.4 23.3 3.8 20.8 3.4 27.3 2.9 17.9 3.9 23.9 3.2 24.7 3.7 3.2 2.8 4.1 3.1 26.7 31.6 23.0 25.1 32.1 4.0 23.5 3.7 29.1 2.9 20.3 4.1 25.0 3.5 29.7 NN-C 18.4 31.4 12.9 39.0 18.6 2.3 3.0 2.3 3.2 3.0 19.1 33.5 13.8 36.0 22.8 2.3 3.3 2.4 3.1 3.1 20.2 36.8 13.3 37.5 22.6 2.4 3.5 2.3 3.8 3.2 AUG 06 AUG 13 AUG 20 AUG 27 SEP 03 SEP 10 SEP 17 SEP 24 OCT 01 OCT 08 OCT 15 OCT 22 OCT 29 NOV 05 NOV 12 NOV 19 NOV 26 29.9 20.6 24.2 33.4 10.1 22.7 24.2 31.7 26.6 36.5 19.5 26.8 26.4 20.4 22.0 19.1 23.3 3.9 2.9 2.5 3.0 2.5 2.9 3.3 3.5 3.6 3.6 3.0 3.4 3.2 3.2 3.3 3.2 3.3 32.6 22.2 24.2 79.7 10.6 22.0 23.8 31.7 25.7 29.1 21.6 27.8 31.8 26.7 22.7 18.2 22.5 3.9 3.0 2.5 7.0 C 2.5 2.9 3.3 3.5 3.6 3.1 3.0 3.4 3.4 3.3 3.4 3.2 3.3 41.1 25.4 26.4 42.7 11.5 25.6 30.8 42.8 29.4 32.0 20.4 32.9 33.8 29.0 25.0 20.4 32.9 3.9 3.1 2.6 2.8 2.5 2.8 3.4 3.5 3.5 3.2 3.0 3.3 3.2 3.4 3.3 3.3 3.3 35.7 24.8 24.5 46.2 9.9 23.4 28.2 34.8 25.4 35.1 20.3 30.7 36.2 25.4 26.2 21.8 22.2 DEC 02 DEC 10 DEC 17 DEC 23 DEC 31 4.0 2.9 E 2.8 3.7 2.5 3.0 3.4 3.7 3.6 3.5 3.0 3.7 3.9 3.5 3.5 3.4 3.8 22.9 30.6 21.7 20.6 27.5
- 3. 8 3.3
- 2. 8 4.0
- 3. 2 21.3 28.0 18.4 20.0 25.4 3.7 3.2
- 2. 8
- 3. 9 3.1 20.0 24.7 18.0 18.9 25.5 3.7 3.1 2.8 3.9 3.1 26.1 28.3 20.8 20.8 26.9 3.9 3.3 2.9 4.0 3.2 20.8 27.1 17.7 21.4 27.8 3.8 3.3 2.8 4.0 3.3 33
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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 <br />0 hours <br />0 weeks <br />0 months <br /> 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
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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
(+ -)
JAN 09
-18 19 JAN 15 7
15 JAN 22
-1 11 JAN 29 4
13 FEB 05 3
12 FEB 12
-17 14 FEB 19 0
13 FEB 26
-5 19 MAR 05 4
17 MAR 12
15 APR 02
-6 13 APR 09 11 16 APR 16
-3 16 APR 23
-1 16 APR 30
-14 20
(+/-)
(+/-)
5 17
-21 16 3
13
-2 14
-3 13
-7 12
-3 11 6
12 2
12
-8 13
-13 15 1
14 A 0
12 2
11 2
13 0
15 15 20 4
15 11 21
-5 17 4
16 2
15 0
18 0
17 11 15 8
41 C 14 18
-9 17 14 19 1
12
-5 16 8
18
-6 19 12 18 7
2
-12
-12
(+ )
18 14 12 10
(+/ )
0 18
-7 15 0
12
-5 11
(+/ )
4 16
-3 14
-5 12
-3 11 1
13 3
12
-1 13 4
13
-3 13
-7 11 2
11
-7 11
-3 11
-7 19
-8 18 2
15 6
20
-1 19 1
17 18 18 0
21 19 20 11 15
-9 15 4
15 4
17 11 16 2
13 1
11
-1 11
-8 12 0
17
-4 20 5
17
-7 17 7
19 15 16
-7 18
-3 15
-12 19
-2 16 3
22
-16 17
(+ -)
(+/-)
21 14
-4 17
-4 16
-1 14 0
11
-4 11
-2 13 1
11 0
13 0
12 4
12
-1 13
-6 11 12 11 20 20 2
21
-3 19 26 22 B
-9 14
-2 13 1
17 19 20
-6 17
-4 11 12 12
-5 12 0
14 0
13 0
16 4
17 3
16 15 20
-10 21 10 21
-2 13
-5 13 6
12 0
11
-2 18
-2 17
-3 16 11 17 1
12
-3 13
- 1 14 10 12
-3 11 0
10 13 17
-6 20
-7 16 11 17 5
15 20 19 JUN 04 0
11 JUN 11 1
11 JUN 18
-3 18 JUN 25
-10 17 D 1
12
- 5 14
-2 24 4
13
-6 16 1
18 5
16
-4 15
-15 13
-5 14
-8 17
-4 9
15 22
-1 11 9
31
-7 18 7
16
-10 18
-8 21 12 16
-15 15
-4 16
-3 13 1
13 6
14 0
17
-14 15
-4 17 35 CP BASF FE NN-C MAY 0 6 MAY 14 MAY 21 MAY 29
-2 14 2
12 0
16 16 18
-4 12 1
10 0
21
-3 17
-5 9
-5 10 2
15
-3 18
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SURRY 2002 TABLE 3-4 AIRBORNE IODINE 1-131 (1E-3 PCI/M3)
(+/ )
JUL 02 4
23 JUL 09
-4 13 JUL 16
-10 9
JUL 23
-7 13 JUL 30 5
10 HIR
(+/ )
-9 18
-2 14
-1 11 0
11
-7 15 BC
(+/ )
-1 26
-18 17 1
13 1
13
-7 13 L O C A T I O N S ALL 12 19
-11 15 4
13
-8 10 6
16 CP
(+/ )
14 24 2
15 1
10 1
12 13 16 BASF
(+/-)
-12 27
-3 14 2
11
-6 14 7
13 AUG 06 2
10 AUG 13 9
11 AUG 20 6
13 AUG 27 12 15 SEP 03 6
19 SEP 10 2
9 SEP 17
-2 14 SEP 24
-20 18 OCT 01 9
10 OCT 08
-17 20 OCT 15
-3 8
OCT 22
-5 22 OCT 29 9
21 NOV 05 2
10 NOV 12
-6 8
NOV 19
-6 18 DEC 23
-1 15 DEC 31
-11 13
-8 14 0
10 3
11
-5 19 C 10 18
-4 9
2 10 2
21 0
9
-2 16 4
9
-5 21
-11 15 3
9
-4 7
9 14 2
20 0
16 3
9 0
16 8
13 0
11 0
14
-3 12 4
13
-5 18
-10 13
-6 11
-4 11
-6 23 10 9
-3 15 5
11 5
21
-9 12
-3 10
-4 7
6 14
-2 20
-1 14 3
22 6
18
-7 13
-1 13 2
13 13 13
-10 11
-9 14 8
21
-4 11 2
11 2
16
-1 14 9
14 6
11
-1 24 8
21 2
9 0
8
-13 15 9
19 5
16 8
18 0
21
-4 13
-3 17
-2 15
-8 16
-4 13 11 14 6
17 4
9 1
13 1
12 0
11
-4 18
-10 10
-9 21
-3 17
-7 9
-1 9
-3 15
-1 13
-6 20 10 20 6
18
-8 13 8
18
-20 26
-6 12 E
-5 14 1
12
-4 19
-1 9
9 12
-2 17 1
11
-1 15
-5 12
-19 20
-12 28
-10 12
-7 8
8 16 1
11 19 20
-5 16 0
18
-3 15 2
23
-2 17 9
15 11 12 7
15
-8 16 2
9 2
10 0
18
-4 12 0
15 0
12
-3 23
-7 22
-2 11 0
8 11 14
-5 13 0
18 3
18 6
16 4
14
-4 21
-2 14 7
13 E 0
11 3
16 2
16
-4 10 5
11 5
17
-14 13
-4 11
-1 9
-1 21
-1 25 2
14 2
8 2
12 11 14
-16 18
-5 17
-6 14 8
14
(+/ )
-22 18
-3 15
-3 8
4 12
-13 14 NN-C
(+/-)
-13 16 0
15 7
11 8
18 0
18
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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 <br />0 hours <br />0 weeks <br />0 months <br /> 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
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SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 1 (1E-3 PCI/M3)
NB-95
(+/-)
1.1 4.1
-5.7 6.0
-1.7 4.1 2.1 5.1
-4.0 4.9 2.9 5.8
-2.7 3.1 3.3 5.5 CE-141
-0.3
-3.4
-0.2
-0.8
-1.5
-3.7
-2.1 4.5 4.7 7.1 4.4 5.2 6.4 3.7 5.0 6.0 RU-103 1.6 3.3 0.0 4.3 2.1 2.5 0.0 2.6
-2.5 3.9 1.0 1.5 1.2 3.3
-0.4 2.5 TH-228 0.3
-0.5
-1.4 0.3
-1.0 1.1 0.8
-1.2
(+/ )
2.4 2.5 2.0 2.4 2.9 2.0 1.6 1.9 LOCATION BE-7 K-40 CO-60 119 97 81 81 91 70 72 120 ZR-95 45 37 36 42 37 42 36 36
-3.6 1.5 5.4 3.5 14.0 9.0 9.0 8.5
(+/ )
7.2 7.8 7.9 8.7 11.0 10.0 10.0 7.9 0.14 0.32 0.51 0.32
-0.32 0.51
-0.02
-0.24
(+/-)
0.58 0.79 0.82 0.45 0.65 0.82 0.83 0.59 SS HIR BC ALL CP BASF FE NN-C LOCATION SS HIR BC ALL CP BASF FE NN-C 0.8
-0.6 0.1
-1.1
-1.7 0.7 1.3
-0.4 2.7 3.0 1.6 1.5 3.5 2.0 1.9 2.6 RU-106 CS-134 CS-137 BA-140 0.7 1.9 4.4 2.9 0.0 2.6 1.8 1.4 5.0 4.6 6.9 4.7 6.0 5.5 5.7 6.7
-0.49
-0.61
-0.44 0.03
-0.36 0.03 0.05
-0.57
(+/ )
0.60 0.92 0.57 0.71 0.70 0.49 0.86 0.49
-0.27
-0.09 0.08
-0.17 0.28
-0.16
-0.05 0.42
(+/ )
0.56 0.49 0.36 0.58 0.68 0.57 0.58 0.44 170 100 50 0
- 110
-50 0
60
(+/-)
250 140 190 0
210 110 230 210 38
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SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 2 (1E-3 PCI/M3)
BE-7 120 36 70 30 136 36 141 31 114 35 109 34 119 32 112 33 RU-106 3.8
-1.5
-4.2
-2.2 0.7
-0.5
-2.6 4.4
(+/-)
5.0 5.0 6.1 3.5 6.5 4.8 4.9 6.5 K-40 5.4 8.2 13.0 11.0 10.0 10.0 7.1 7.1 0.2 5.1 2.1 8.8
-0.3 5.1 10.0 11.0 CS-134
-0.22 0.45
-0.11 0.47
-0.49 0.41 0.05 0.45 0.08 0.40 0.29 0.46
-0.05 0.31 0.36 0.64 CO-60 0.16 0.67
-0.28 0.55
-0.15 0.46 0.15 0.44
-0.06 0.65
-0.03 0.53
-0.04 0.44 0.16 0.64 CS-137 0.46 0.61
-0.66 0.60 0.26 0.58
-0.06 0.44
-0.07 0.54 0.44 0.57
-0.04 0.35 0.07 0.57 ZR-95
( -)
-0.8 3.1 0.8 1.9 0.1 1.1 0.2 1.9 0.8 2.0
-0.3 1.4
-0.4 1.8 0.4 2.4 BA-140
-4 89 38 83
-70 100 46 68
-30 100 23 47 15 69 62 72 NB-95 0.1 3.7 0.7 3.4 0.9 3.7 0.2 3.2 1.8 3.9 1.5 3.6
-1.8 2.8 2.3 3.9 CE-141 0.0 5.0
-0.8 4.1 1.7 3.5 0.3 3.6
-1.1 4.6
-0.8 4.0 0.5 3.2 1.8 4.5 RU-103 0.3 2.9 0.3 2.7 0.3 2.1 1.8 2.4
-1.7 2.6
-0.3 2.1
-1.0 1.8
-0.3 3.3 TH-228 1.7 2.3 0.9 2.5
-0.2 2.2 1.3 1.8 2.6 2.3
-0.2 2.8
-0.6 1.6
-2.9 2.5 39 LOCATION Ss HIR BC ALL CP BASF FE NN-C LOCATION SS HIR BC ALL CP BASF FE NN-C
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l SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA - QTR 3 (1E-3 PCI/M3)
LOCATION BE-7 (4/-)
SS 65 17 HIR 47 20 BC 54 21 ALL 64 17 CP 57 19 BASF 80 21 FE 50 18 NN-C 55 20 LOCATION SS HIR BC ALL CP BASF FE NN-C RU-106 2.3
-2.0
-0.7 0.1
-2.9 0.7 2.0 0.4 (4/-)
4.5 4.1 5.5 5.2 4.4 5.2 4.1 4.5 K-40
-0.2 5.3 6.6 9.5
-2.9 8.1 0.7 7.2 2.5 6.8 3.0 8.5 0.5 4.9
-3.1 5.7 CS-134 (4/-)
0.10 0.37 0.12 0.35
-0.16 0.49
-0.06 0.41
-0.14 0.53
-0.37 0.63
-0.08 0.32 0.27 0.65 CO-60
-0.35 0.55 0.22 0.65 0.10 0.62
-0.03 0.52
-0.34 0.84 0.14 0.55 0.48 0.62
-0.32 0.69 CS-137
-0.09 0.54
-0.06 0.43
-0.24 0.54
-0.39 0.43 0.03 0.52
-0.07 0.56
-0.14 0.51 0.24 0.39 ZR-95 0.1 1.3 1.0 1.4
-1.1 1.4
-0.7 1.6 0.5 1.7 0.3 2.0 0.2 2.0
-1.1 1.4 BA-140
-3 11
-8 23
-8 17 12 14 0
11 7
10
-8 11 8
17 NB-95 0.3
-1.2
-1.3
-0.8 0.1
-0.6
-0.4
-1.1 1.3 1.6 2.2 1.7 1.4 1.9 1.6 1.1 CE-141 0.4 1.4 0.3 1.9
-1.4 1.8 0.4 1.6
-0.6 1.5 0.1 2.6
-1.1 1.9
-0.3 1.8 RU-103
-0.6 0.8 0.0 1.3 1.1 1.4 0.6 1.0 0.0 1.2 1.8 1.4 0.4 1.3
-0.6 1.2 TH-228 (4/-)
-1.2 1.7
-1.9 1.7 0.5 1.9 0.5 2.2 1.1 2.0
-0.9 1.6 1.8 2.2 2.6 2.6 40
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l SURRY 2002 TABLE 3-5 AIR PARTICULATES GAMMA SPECTRA -
LOCATION BE-7
(+1-)
SS 75 15 HIR 89 19 BC 108 20 ALL 85 19 CP 86 15 BASF 79 21 FE 75 19 NN-C 106 23 LOCATION SS HIR BC ALL CP BASF FE NN-C RU-106
-0.2 1.9
-1.9
-2.3
-3.7
-0.5
-1.0 0.1 3 )
3.9 3.9 3.6 3.5 3.6 3.6 3.5 4.1 K-40 4.8 5.1 2.3 5.3 7.8 7.4
-3.0 3.7 3.0 5.0 1.9 6.7
-1.2 5.5 0.3 7.9 CS-134
-0.15
-0.25
-0.08 0.06
-0.11 0.36
-0.37
-0.04
(+1-)
0.41 0.44 0.30 0.43 0.27 0.63 0.36 0.38 CO-60 0.12 0.33 0.21 0.50
-0.22 0.54 0.21 0.42
-0.05 0.35 0.09 0.54 0.17 0.51 0.30 0.49 CS-137 0.20
-0.36
-0.07 0.24
-0.19 0.26
-0.20
-0.17
(+1/-)
0.36 0.43 0.41 0.32 0.31 0.46 0.28 0.38 ZR-95 0.2 1.1 0.0 1.3 0.1 1.2 0.5 1.2
-0.8 1.2 0.5 1.5
-1.0 1.2
-0.5 1.9 BA-140
-15 7
5 1S
-15
-7
-6 12
(+/-)
16 23 21 22 19 29 26 39 NB-95
(/-
)
-1.1 1.5 1.4 2.3 0.6 1.7 0.3 1.1
-0.4 1.3 0.3 1.8 0.4 1.6
-0.1 1.9 CE-141
-0.5 0.5 0.7
-1.3
-0.4
-2.0
-0.3 1.1 1.6 2.6 1.8 1.5 1.4 2.8 1.7 2.0 41 RU-103
-0.2
-0.5
-0.7
-0.4 0.0 0.0 0.2 0.0
(+/ )
1.1 1.6 1.2 1.3 1.1 1.9 1.1 1.4 TH-228
-0.7 0.1
-0.2
-0.5
-0.5
-0.5 0.5
-0.6
(+/-)
1.3 1.7 1.6 1.3 1.1 1.7 1.4 1.3
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SURRY 2002 TABLE 3-6 COW MILK (PCI/L)
COLLECTION LOCATION DATE CP 01/09/02 02/05/02 03/05/02 04/17/02 05/15/02 06/18/02 07/02/02 08/06/02 09/03/02 10/01/02 11/12/02 12/02/02 EPPS 01/22/02 02/26/02 03/26/02 04/23/02 05/29/02 06/18/02 07/23/02 08/20/02 09/24/02 10/22/02 11/26/02 12/17/02 K-4C 1340 1520 1400 1420 1510 1450 1300 1240 1390 1400 1450 1350 1430 1370 1452 1420 1450 1340 1480 1280 1430 1322 1372 1300 SR-89 SR-90 I-131 CS-134 CS-137 BA-140 LA-140 110 110 98 120 140 100 110 110 110 100 110 110 0.16 0.24 0.01 0.08
-6.4 6.6 2.5 1.1
-0.06 0.08 0.21 0.26
-0.02 0.07
-6.7 5.1 1.5 0.7 0.70 0.78 0.35 0.49 0.11 0.33
-4.2 4.0 1.1 1.0 0.73 0.72 0.17 0.52 0.02 0.28 6.3 5.6 1.8 0.9 0.04 0.30 130 150 96 110 100 110 100 120 110 83 80 120 0.05 0.12 0.07 0.14 0.04 0.23 0.03 0.09
-0.08 0.03 0.28 0.52 0.08 0.21 0.14 0.53 0.22 0.52 0.27 0.53 0.39 0.49 0.22 0.43 1.9 2.7 1.8 0.3 2.9
-0.6 1.8 2.5
-2.1 2.9 3.6
-2.7 3.8 3.5 0.2 0.6 2.8 2.1 1.1 3.4
-2.6
-0.3 3.3 2.2 0.6 3.3 1.5
-1.8 2.7
-2.1
-1.3 3.1 0.3
-2.4 2.9
-0.7
-1.1 3.3
-1.5 0.5 3.6 3.2
-2.6 2.5
-0.1 0.5 2.8 1.5
-0.9 2.8
-0.1
-2.2 3.2
-0.9 1.2 2.9
-1.4 2.5 3.6 1.6 2.6 2.3 0.1 0.2 2.3 0.6
-0.2 2.0
-0.3 1.9 3.3
-0.3 2.4 0.6 3.3 0.7 2.5 1.8 2.3 2.1 2.5
-2.0 4.9
-2.3 3.2
-1.7 5.6
-2.0 3.6 0.5 5.7 0.6 2.9 2.4 3.7 2.7 3.1
-3.1 5.6
-3.5 3.1
-5.3 5.6
-6.0 3.0 0.6 4.3 0.7 2.8
-2.6 4.2
-3.0 3.1 1.5 5.1 1.8 3.1 1.7 4.3 2.0 3.1 3.9 4.4 4.5 4.1 2.0 5.1 2.3 2.6
-0.8 3.8
-0.9 3.0
-3.6 5.3
-4.2 2.6
-1.2 3.7
-1.4 3.1
-2.4 4.8
-2.8 3.1
-0.5 4.1
-0.5 3.4
-0.4 4.8
-0.4 2.6 3.0 3.1 3.4 2.4 0.7 3.9 0.9 2.2 0.7 3.1 0.8 3.2
-0.8 4.2
-0.9 STRONTIUM ANALYSES FOR CP MILK SAMPLES REQUESTED BY THE COMMONWEALTH OF VIRGINIA 42 3.8 2.6 5.6 6.4 6.5 4.2 6.5 6.5 4.9 4.9 5.9 5.0 5.0
- 5. 9 4.4 6.1 4.2 5.5 4.8 5.5 3.6 4.5 3.6 4.8 I
( / )
( / )
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
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i SURRY 2002 TABLE 3-7 FOOD PRODUCTS (PCI/KG WET WT.)
COLLECTION LOCATION DATE BROCK'S 11/19/02 11/19/02 12/18/02 COLLECTION LOCATION DATE BROCK'S 11/19/02 11/19/02 12/18/02 TYPE BE-7 PEANUTS 36 47 CORN
-35 57 SOYBEANS 9
31 TYPE CO-60 PEANUTS 2.4 8.0 CORN 8.5 9.0 SOYBEANS 0.3 7.6 K-40 6380 320 3310 250 15610 270 ZN-65 24 36 54 41 0
12 CR-51 13 52
-2 63
-2 35 ZR-95
-1.0 10.0
-9.0 10.0
-1.7 7.5 MN-54
-4.8 6.0
-6.3 7.3
-2.1 4.3 NB-95
-2.0 10.0 9.0 13.0 0.1 4.9 CO-58
-2.1 5.9 14.0 12.0
-2.5 4.3 RU-103
-2.4 5.7
-1.3 6.5
-2.0 3.9 COLLECTION LOCATION DATE BROCK'S 11/19/02 11/19/02 12/18/02 COLLECTION LOCATION DATE BROCK'S 11/19/02 11/19/02 12/18/02 TYPE SB-125 PEANUTS 8.0 17.0 CORN
-9.0 20.0 SOYBEANS
-3.5 8.3 TYPE CE-141 PEANUTS
-4.3 8.5 CORN 5.0 11.0 SOYBEANS 2.8 5.5 FE-59
-5 14 1
16 8
14 RU-106
-28 58
-29 62 16 34 CS-134 1.3 6.6
-0.4 7.2 1.6 4.2 CS-137
-2.6 7.3 1.0 13.0 2.3 4.0 I-131 1.7 7.4
-1.1 8.8
-5.0 12.0 CE-144
-4 34 59 45 1
16 BA-140 1.9 5.8
-3.2 7.0 2.0 5.6 LA-140 2.2 6.7
-3.7 8.1 2.3 6.4 TH-228 7
24 8
27 17 16 44
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SURRY 2002 TABLE 3-8 WELL WATER (PCI/L)
COLLECTION LOCATION DATE HIR 03/26/02 06/18/02 09/24/02 12/02/02 SS 03/26/02 06/18/02 09/24/02 12/02/02 K-40 8.0 2.0
-26.0
-1.0 7.0 20.0
-22.0 2.0
(+/ )
36.0 18.0 31.0 41.0 35.0 29.0 28.0 38.0 CR-51
( -)
-3.0 22.0 15.0 18.0 9.0 27.0
-4.0 30.0 4.0
-9.0 1.0 9.0 23.0 23.0 23.0 30.0 MN-54
( -)
0.6 2.6
-0.3 1.5
-2.3 2.6
-2.0 2.7
-0.5
-0.2 1.5 0.0 2.2 2.3 2.0 3.0 LOCATION COLLECTION DATE HIR 03/26/02 06/18/02 09/24/02 12/02/02 SS 03/26/02 06/18/02 09/24/02 12/02/02 ZN-65
-3.7
-3.0 5.0
-1.9
-3.4
-6.1 3.8
-4.0 5.3 3.5 10.0 6.6 4.6 5.1 9.1 17.0 ZR-95 0.0 4.2
-1.0 2.7
-2.1 4.3
-0.3 4.9 2.8
-0.3 0.3
-1.4 3.8 3.6 3.3 4.2 NB-95
-0.3 2.6 0.4 1.8 2.5 2.8
-2.6 2.8 1.4
-2.9 1.6
-0.2 2.5 2.8 2.3 3.7 RU-103
-0.6 2.7
-2.2 1.9
-1.3 2.9
-0.6 3.1
-1.1
-3.9
-1.7
-1.7 2.4 2.4 2.5 3.4 RU-106
-2.0 21.0 11.0 15.0
-6.0 23.0 3.0 25.0
-1.0
-14.0 5.0
-2.0 20.0 19.0 19.0 26.0 1-131 0.01 0.26 0.30 0.53
-0.06 0.31 0.59 0.61 0.00
-0.05 0.21 0.38 0.24 0.29 0.41 0.56 45 CO-58 0.7 2.3
-0.5 1.5
-1.2 2.3 0.3 2.9 FE-59
( -)
0.6 6.5
-2.1 4.4
-1.0 5.2
-5.1 6.2 CO-60
-0.3 2.4
-0.1 1.3 0.4 2.5 1.7 3.1
-0.3
-0.1
-1.1 0.2 2.1 2.1 2.0 3.2 2.0 3.7
-0.4 3.2 5.3 5.0 4.4 7.1 1.0
-1.2 0.7 1.2 2.3 2.2 2.6 3.6
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SURRY 2002 TABLE 3-8 WELL WATER (PCI/L)
COLLECTION LOCATION DATE CS-134 CS-137 BA-140 LA-140
(+/-)
(+/-)
(+/-)
(+/ )
HIR 03/26/02 1.2 2.2 1.7 2.5
-2.6 4.5
-3.0 5.1 06/18/02 1.8 1.5
-0.6 1.5
-0.5 3.2
-0.6 3.7 09/24/02 1.7 2.6
-0.9 2.7
-1.5 4.5
-1.7 5.2 12/02/02
-0.8 2.8 3.0 3.5 0.6 5.2 0.7 6.0 SS 03/26/02
-0.5 2.3 06/18/02 0.0 1.7 09/24/02
-1.8 1.9 12/02/02 3.3 3.9 0.4 2.3 1.9 2.1
-1.8 2.2
-2.0 5.9
-3.1 3.6 2.0 4.9
-0.8 3.6 3.8 5.6
-3.6 4.2 2.3 5.6
-0.9 4.1 4.3 6.4 46 H-3
(+/-)
-140 730
-90 740
-500 1000 400 900
-40 760 0
760 600 1100 780 920
l I
I I
I IIIIIIIIIIII l l
l l
l l
SURRY 2002 TABLE 3-9 RIVER WATER (PCI/L)
COLLECTION LOCATION DATE SD 01/29/02 02/26/02 03/26/02 04/30/02 05/29/02 06/18/02 07/30/02 08/20/02 09/24/02 10/22/02 11/26/02 12/23/02 K-40 154 42 106 53 150 51 61 31 59 27 147 33 145 42 145 39 155 49 94 23 39 30 42 29 CR-51 MN-54
(+/-)
-7 20 0.2
-13 29
-1.4 11 22 0.0
-10 19 0.8
-7 17 0.4 2
16
-0.9
-13 21
-0.1 0
18
-0.7 4
25 0.7
-5 12 0.4 2
17
-1.7 1
17 0.4 CO-58 1.7
-0.8 2.4 2.3 2.1 0.9 1.9
-0.8 1.5
-1.2 1.5
-0.2 1.8
-1.5 1.5
-0.8 2.7
-2.9 1.1
-0.4 1.9
-0.1 1.7
-0.6 FE-59 1.7 3.7 2.5 0.0 1.9
-6.8 1.7
-2.5 1.5
-1.1 1.7 1.1 2.0 2.3 1.6
-0.8 2.5 1.9 1.1 0.3 1.6 0.3 1.8
-1.3 CO-60 5.6 0.1 6.6
-0.3 6.5
-1.2 4.1 1.7 4.1 1.1 3.5 0.2 4.7 1.3 4.9
-0.3 4.8 0.7 2.3
-0.8 3.7 0.3 3.8 0.3 SW-C 01/29/02 02/26/02 03/26/02 04/30/02 05/29/02 06/18/02 07/30/02 08/20/02 09/24/02 10/22/02 11/26/02 12/23/02 68 59 31 34 36 76 91 83 104 135 16
-17 52 23 27
-0.8 45 10 25 3.2 30
-4 16
-0.9 26 3
19 0.6 24 4
16 0.8 28
-1 16 0.1 38
-12 21
-0.1 32
-1 15
-0.5 51 9
24 0.4 25 10 11
-0.6 33
-3 21 0.2 21 6
16
-1.0 2.4 1.9 2.5 0.0 1.5 0.1 1.8 1.8 1.4
-0.2 1.3 0.5 1.9
-0.4 1.3 1.0 2.5 0.8 1.1
-0.4 2.2 0.0 1.5
-0.9 2.6 4.4 2.4
-3.8 1.6
-1.7 2.0
-1.2 1.5
-4.0 1.2
-0.8 2.0
-0.6 1.6 0.1 2.6 0.0 1.1
-0.3 2.1 2.1 1.5
-1.5 7.2 2.5 8.3 0.9 5.1
-0.3 4.2
-0.1 4.2 0.2 3.0
-0.7 6.3 1.7 4.2 0.1 5.1
-0.4 2.3 0.7 4.4
-0.2 3.4 1.6 47 1.8 2.7 2.7 1.7 1.6 1.6 2.1 1.8 2.6 1.0 1.7 1.8 2.9 2.8 1.8 1.7 1.3 1.4 2.1 1.6 2.8 1.2 2.0 1.6
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 SD 01/29/02 02/26/02 03/26/02 04/30/02 05/29/02 06/18/02 07/30/02 08/20/02 09/24/02 10/22/02 11/26/02 12/23/02 SW-C 01/29/02 02/26/02 03/26/02 04/30/02 05/29/02 06/18/02 07/30/02 08/20/02 09/24/02 10/22/02 11/26/02 12/23/02 ZN-65 0.7 4.7
-4.6 5.3 1.7 5.7
-1.8 3.5
-4.0 3.2
-3.9 3.5
-0.4 9.8
-4.4 4.1
-9.6 9.7
-1.5 2.3 5.3 6.7 1.2 6.4
-7.4
-1.6
-0.3
-4.7
-1.4
-2.8 0.3
-0.8
-0.5
-0.4 0.9 2.7 ZR-95 NB-3.2 3.3 1.1 5.1 4.4 1.7
-1.4 3.8 1.2
-1.0 2.7
-1.3 2.4 2.5 0.8
-0.3 2.6
-0.2
-1.3 3.1
-1.6 0.8 3.1
-1.8
-0.2 3.7
-1.1
-0.8 2.0
-0.6 0.9 2.9 0.9 0.2 2.5 0.1 5.7 1.1 5.9
-1.6 3.8 2.0 4.3 1.7 3.4 0.4 3.1 0.1 4.0 0.6 3.0
-1.0 6.5 0.8 2.4 1.2 8.2 0.2 7.3
-0.3 4.7
-2.4 4.6 1.2 2.7
-0.2 2.9 0.7 2.4 0.0 2.6 0.5 3.5
-1.3 2.5
-2.1 3.9
-0.8 1.7
-0.2 3.4 0.4 2.8 0.3 1-95 RU-103 1.8
-1.7 2.8 1.5 2.2
-1.3 2.3
-1.6 1.6
-0.7 1.7
-1.8 2.2
-1.2 1.5 0.6 2.9
-0.1 1.3
-2.1 1.8
-1.8 1.9
-0.9 3.1
-4.1 2.7
-2.3 1.9
-1.4 2.0
-1.6 1.7
-1.3 1.7
-0.7 2.3
-1.4 1.7
-0.4 2.8
-2.2 1.2
-1.8 2.3
-0.5 3.0
-0.4 2.3 3.0 2.2 2.0 1.6 1.8 2.1 1.8 2.9 1.3 1.9 2.0 RU-106
-35
-3
-5 4
-2 1
-7 6
-12 4
-4
-7 17 21 20 16 14 14 20 16 21 9
17 16 1-131
-0.1 0.3 0.2 1.5
-0.4 4.0 2.9 5.8
-1.7 4.6
-0.5 5.0
-0.5 3.9
-0.2 3.8
-0.3 4.7 1.0 3.0 1.9 3.5
-2.1 3.2 3.1
-3 22 0.0 3.0 0
23 2.8 1.9
-10 18
-1.8 2.3
-5 17 2.6 1.8 0
14 2.4 1.6
-3 13
-5.7 2.3
-7 18
-0.6 1.7
-6 14 2.4 2.6
-2 22 4.4 1.2
-2 9
0.7 2.3 8
18
-2.9 1.8
-7 17 0.6 0.4 3.3 3.3 5.8 4.4 4.6 4.1 3.6 5.1 3.0 4.0 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 SD 01/29/02 02/26/02 03/26/02 04/30/02 05/29/02 06/18/02 07/30/02 08/20/02 09/24/02 10/22/02 11/26/02 12/23/02 CS-134 CS-1.3 1.6
-0.6
-1.0 2.6
-2.0
-0.8 2.6
-0.5 0.3 1.7 0.2 0.9 1.5
-0.4 0.0 1.6
-0.7 1.8 1.8
-1.3 0.3 1.7 0.2 0.3 2.3
-3.7 0.2 1.2
-0.5 1.2 1.6
-0.4 1.0 1.9
-0.9 137 1.8 2.4 2.4 1.7 1.5 1.5 2.1 1.8 2.4 1.0 1.7 1.8 BA-140 LA-
-2.0 2.7
-2.3
-0.6 5.6
-0.7 0.4 4.1 0.5 4.7 3.8 5.4 0.2 3.1 0.3
-1.2 2.9
-1.3
-0.5 3.3
-0.6 0.3 2.7 0.3
-2.0 4.2
-2.3
-0.8 2.2
-0.9
-0.5 2.5
-0.6
-0.2 2.5
-0.3 140
( / )-
H-3 3.1 6.4 4.7 40 830 4.4 3.6 3.3
-1200 1100 3.8 3.1 4.9 0
830 2.6 2.9 2.9 120 900 Sw-C 01/29/02 02/26/02 03/26/02 04/30/02 05/29/02 06/18/02 07/30/02 08/20/02 09/24/02 10/22/02 11/26/02 12/23/02
-2.2 0.4 0.3 0.5 1.0
-0.2 1.7
-1.3
-1.1 0.1
-1.1
-0.4 2.9
-1.3 2.8 0.8 1.9
-0.7 2.0 0.1 1.7 0.2 1.4 0.5 2.1 0.3 1.5
-0.5 2.7
-0.5 1.0
-0.7 2.2 0.8 1.6
-0.6 2.8
-0.5 2.7 0.7 1.9
-1.1 1.7 0.6 1.5
-0.4 1.4 1.1 2.4
-0.9 1.6 0.3 2.8
-1.5 1.1 0.1 2.2
-1.5 1.6
-1.6 4.7
-0.6 6.2 0.8 2.6
-1.3 4.2 0.7 2.8
-0.5 2.8 1.3 3.7
-1.0 2.4 0.3 4.6
-1.7 2.5 0.1 2.5
-1.8 2.4
-1.8 5.4 7.2 3.0 280 780 4.9 3.2 3.3
-700 1100 4.2 2.7 5.3 300 840 2.8 2.9 2.8 290 930 49
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 09/17/02 470 480 17800 1100 130 330
-390 570 14 18
-7 21 26 72 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 09/17/02
(+ )
(+/-)
36 36 A 40 130 18 30 80 140 SD 03/14/02 09/17/02 38 17
-15 86 67 32
-30 160 22 43
-38 33
-18 29 60 160 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 09/17/02 23 23 90 300
-12 47
-140 530 54 71 259 36 0
50 959 75
-42 34 313 57 7
90 990 140 A: CO-60 WAS REANALYZED DUE TO A FALSE PEAK IDENTIFIED IN THE ORIGINAL ANALYSIS 50
(+/ )
-15 58
-14 70
(+/-)
-10 70 1
76
(+ )
-7 37
-12 41
(+ )
-10 250
-20 290 I
I I
IlI I
I I
I I
I I
I I
I I
I I
I I
I I
SURRY 2002 TABLE 3-11 SHORELINE SEDIMENT (PCI/KG DRY WT.)
COLLECTION LOCATION DATE BE-7 K-40 CR-51 MN-54
( / )
(-
)
(-
)
(-
)
CHIC-C 02/26/02 150 190 1080 360
-90 240
-15 19 09/03/02 40 340 970 450
-240 430 9
34 CO-58 FE-59
(+/-)
(+/-)
16 21 7
62
-25 33 43 82 HIR 02/27/02 09/03/02 140 130 8950 820 5
75 6780 490 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 CHIC-C 02/26/02 0
18 39 79
-6 36
-29 30 09/03/02
-3 24
-110 130 36 61
-5 45 HIR 02/27/02 09/03/02 9
18
-8 11 84 79
-19 49 29 28
-14 15 2
18
-4 10 COLLECTION LOCATION DATE AG-IOM I-131 CS-134 CS-137
(+/ -)
(+1-)
(+/ -)
(+/ -)
CHIC-C 02/26/02
-2 22
-70 110
-41 79
-17 21 09/03/02
-17 42
-60 110 4
31
-5 35 HIR 02/27/02 09/03/02
-2 21 0
12
-36 63 41 30 3
14 6
7 3
15 12 13 RU-103 RU-106 6
22 0
200 18 41 90 290
-2 15
-10 120 6
10
-11 82 SB-125 TH-228 46 54 51 93
-7 35
-4 21
(+ )
131 57 1200 140 116 59 138 39 51
-110 140 56 99
-4 16 6
9 4
14
-9 9
-9 60 36 34
I I
l l
l I
I I
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 SD 04/03/02 04/03/02 10/30/02 10/09/02 COLLECTION LOCATION DATE SD 04/03/02 04/03/02 10/30/02 10/09/02 CATFISH PERCH CATFISH PERCH TYPE CATFISH PERCH CATFISH PERCH
(+/ -)
(+/-)
80 250 2200 550 220 300 2570 770 170 300 2460 820
-360 480 2420 710 CO-60
-15 22 12 31
-10 40
-10 29 ZN-65
-32 53
-25 73 9
63
-20 67
(+/-)
70 350 300 470
-40 660 190 850 ZR-95 4
41
-25 74 10 69 60 73
(+/-)
-20 22 12 27 0
35 3
30 NB-95 19 39 9
51
-33 62 29 80
(+/-)
-4 29 14 31
-35 41
-38 39 RU-103
-11 31 0
41 54 47
-5 65 COLLECTION LOCATION DATE TYPE AG-110M 1-131 CS-134 CS-137 SB-125 SD 04/03/02 04/03/02 10/30/02 10/09/02 CATFISH PERCH CATFISH PERCH 5
28 0
240
-42 42 230 370 0
50
-200 1100
-38 36 1600 5500 14 24 29 28 19 33
-9 29
-9 24 5
29
-22 34 13 26 43 61 31 71
-6 75
-4 57
(+/-)
17 74
-60 110 30 110
-10 130 RU-106 30 200 140 300 210 310
-60 260 TH-228
-29 87 30 130
-40 110 90 110 52 MN-54 CO-58 FE-59
I I
I I
I I
I lI IIIIIIIII l
l 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
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
MP 03/14/02 80 200 540 530 20 250
-10 22
-5 26 09/17/02
-130 180 590 280
-210 270
-7 15
-14 18 POS 03/14/02 0
260 09/17/02
-100 170 970 520 890 280
-10 350 0
290 24 20
-5 14
-9 26
-11 18 COLLECTION LOCATION DATE CO-60 ZN-65 ZR-95 NB-95 RU-103 MP 03/14/02 09/17/02 1
27
-10 15
(+/ -)
-54 71
-4 35
-4 41 36 43
-19 28
-17 32 0
26
-21 26 POS 03/14/02 09/17/02 14 19
-43 65 2
14
-34 37 35 52
-7 31 14 33
-8 30 5
32 12 23 COLLECTION LOCATION DATE AG-lOM 1-131 CS-134 CS-137 SB-125 NP 03/14/02 31 29
-30 120 14 23 9
21
-5 43 09/17/02
-1 20
-300 490 5
16 3
15 20 41 POS 03/14/02 09/17/02
-12 34 10 140 1
22
-530 440 FE-59
-33 81
-28 43 87 87 6
42 RU-106 110 210 0
120 0
230
-40 130 TH-228
-16 96
-75 53 3
29 5
14 18 24 4
13
-5 57
-20 37
-1 93
-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 I
I I
I I
I l
[
l 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 09/17/02 LC 03/14/02 09/17/02
-20 31 70 120
-4 25
-9 24
-20 51
-43 87 20 19
-200 500 14 17
-6 16
-8 35
-15 52 23 23
-53 88
-8 14 0
17
-28 44 18 53
-21 30
-120 500
-10 15
-18 18 10 39
-2 69 SD 03/14/02 09/17/02 7
24 10 100 4
22
-130 560 4
16
-8 17 3
46 68 68 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
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 4-1: DIRECT RADIATION MEASUREMENT TLD RESULTS 8 -
7 -
'E 5 '1 A
\\.-
11 I
.8 4 - -
\\i \\
E 2 -
1--
O 1
1 I
't W) ~
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
Figure 4-2: GROSS BETA IN AIR PARTICULATES FOR 2002 0.050 0.045 0.040 0.035 IE 0.030
- j.
0.025 0.020 0.015 0.010 A Indicator AX Control jA A
.9~~~
II A
.AA I z \\I\\ I
-If V\\. A A t I IK
-X
?.
I
.. I I
.1 w
X 4
'r-A
- i F
1 o
X w
A v
4 "I
V.
v l
A lllllllllll+lll (a) Chemobyl 59 Figure 4-3: GROSS BETA IN AIR PARTICULATES 10 YEAR TREND 1.0E+00 (a) 1.OE-01 0.~~~~~
I.OE-02 M-9 1
.0E 03 A.v..........
...Av
.C t
R equire In a
0 0
V9 co C9 4 N e
lAvg Indicator
_ Avg Control Avg-Pre Op Required LLDsl COI
.. Avg Control I
- P Avg Infficator Q) cm I
I N
IS I
t EQ tD t-t CO T-O o,~ ~
~
OI O
O 0
Or Or O
O5 OE O
O
4.3 Airborne Radioiodine Air is also continuously sampled for radioiodines by passing it through charcoal cartridges.
Once a week the charcoal cartridge samples are collected and analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection with 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 Particulate Gamma 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 Cl
\\~~~'O 00 0
C9
'T ~.O 00 0D Cl4
'I r-r-r-
00 00 00 00 00 all O1 ON ON vO oo oN N
ON ON oN o
ON ON 1-C-ot k
m
-oo-oo Discharge Control - Chickahominy --
Station Dischargel NO 00 0
C o
o CD C
es
~es 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
.O 0.
1LOE+02 Cl4
'I 1.O 00 0
Cl4 Il F
b r-t-
00 00 00 as ON ON ON ON ON O~
-f
-z
-r
-E sO 00 0
' t
'o 00 00 00 ol O\\
O\\
OC ON ON O\\
O O
al
+
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 o
C o
I l
l I-I I
I I
~~~~~~~~~~~~~~~~
I I
I ~~~~~~~~~~~~. I I
I
4.12 Oysters Oysters are collected from two different locations.
The results of the oyster analyses are presented in Table 3-13.
There were no gamma emitting radioisotopes detected in oysters sampled except for naturally occurring radionuclides such as potassium-40.
No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of steam generators in 1982 and past improvements made to liquid effluent treatment systems.
4.13 Clams Clams are analyzed from four different locations.
The results of the gamma spectroscopy analyses are presented in Table 3-14.
Like oysters, no station related radioactivity was detected. 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 Location Description FE Air Part.
Gross Beta Date of Sampling 03/12/02 Reason(s) for Loss/Exception Air sampler malfunction. Sample volume was 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
l I Nearest Nearest l
Nearest Nearest I Sectorl Direction I
Resident I
Garden**
I Cow I
Goat 4.12 @30° 1.90 2 340 4.60 340 (a)
(a)
(a)
(a) 4.75 @ 1520 1.69 @ 1820 1.87 @ 1930 2.28 @ 2220 2.82 @ 2430 3.15 @ 260° 4.79 @ 2810 4.84 @ 3190 3.73 @ 3390 (a) 1.90 @ 340 4.91 @ 560 4.91 @ 56° (a)
(a)
(a) 5.00 @ 1600 2.05 @ 1830 4.26 @ 1950 3.65 @ 2240 3.57 @ 2460 4.14 @ 2690 (a)
(a) 4.39 3340 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a) 4.84 @ 2010 (a)
(a)
(a)
(a)
(a) 3.65 @ 3370 Locations are listed by miles and degrees heading relative to true north from center of Unit #1 Containment.
- Area greater than 50 m2 and contains broadleaf vegetation.
(a) None 72 N
NNE NE ENE E
WNW NW NNW (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
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
- 1. All samples are spikes except fish/invertebrate that are duplicate oyster samples from the Millstone quarry.
- 3. Gamma in water QA spikes are treated as milk surrogates.
TABLE B-2 RESTTTS OlF 9009 OfLIATY CONTROT SAMPTF ANAT.YSES Milk - Strontium Milk - Iodine Water - Gamma Water - Tritium Oysters - Gamma Air Particulate 3
0 4
49 4
0 9
0 5
Gross Beta Iodine Gamma 0
2 1
9 2
3 6
TOTALS Samples: 77 Samples: 20*
76 o~~~~~~~i AAE~~~~~~~~~~~~~~~~~
~~~~~~~
~~~~~~OO~~~~~~~~~N~~~~~~~ANAr~~
ES.
i4 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
- 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.
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.,
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) 1 st 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 1-1 31 LL Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E3148-162 Water H-3 E3149-162 Water Sr-89 Water Sr-90 pCi/L 6970 pCi/L pCi/L E3150-162 Filter Gr-Beta pCi E3151-162 Filter Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E3151-162 Filter Sr-90 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi 6970 42 64 36 39 (2)
(2) 59 165 77 64 68 69 62 131 82 41 61 160 82 62 68 65 55 122 85 48 (1) Sample was not analyzed in a timely manner due to high volume of client samples.
(2) Filter damaged during sample preparation.
80 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 88 85 86 230 121 89 100 97 83 179 127 87 87 90 235 120 91 100 95 81 180 125 1.01 0.98 0.96 0.98 1.01 0.98 1.00 1.02 1.02 0.99 1.02 A
A A
A A
A A
A A
A A
1.00 0.66 0.92 (2) 0.97 1.03 0.94 1.03 1.00 1.06 1.13 1.07 0.96 0.85 A
U (1)
A (2)
A A
A A
A A
A A
A A
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)
QAP 56 Water Co-60 Cs-1 37 Sr-90 H-3 Gr-Beta Filter Co-60 Cs-1 37 Mn-54 Sr-90 Gr-Beta Bq 29.700 Bq 28.400 Bq 38.700 Bq 4.100 Bq 1.174 July -
December 2002 QAP 57 Water Co-60 Cs-1 34 Cs-I 37 Sr-90 H-3 Gr-Beta Filter Co-60 Cs-1 37 Mn-54 Sr-90 Gr-Beta Bq 23.195 Bq 33.400 Bq 51.680 Bq 4.820 Bq 0.785 (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 January -
June 2002 Bq/L Bq/L Bq/L Bq/L Bq/L 350.300 55.300 6.260 309.000 951.000 347.330 56.067 7.579 283.700 1030.000 1.009 0.986 0.826 1.089 0.923 A
A A
A A
30.520 28.230 38.530 4.832 1.300 0.973 1.006 1.004 0.849 0.903 A
A A
A A
Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 257.200 60.700 79.700 7.770 252.100 808.700 268.570 60.200 81.430 8.690 227.300 900.000 0.957 1.008 0.979 0.894 1.109 0.899 A
A A
A A
A 23.000 32.500 52.200 5.561 0.871 1.008 1.028 0.990 0.867 0.901 A
A A
A A
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) 12030105 Water Gr-Beta pCi/L RAD-49 Water Gr-Beta Co-60 Cs-134 Cs-137 1-131 LL H-3 Sr-89 Sr-90 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 16.9 174 39.5 17.1 53.6 19.5 17100 31.1 28.6 16.3 189 39.1 17.1 52.1 14.7 17400 31.7 28.3 7.6 - 25.0 140 - 238 30.4 - 47.8 8.44 - 25.8 43.4 - 60.8 11.2-18.2 14400 - 20400 23.0 - 40.4 19.6 - 37.0 July -
December 2002 RAD-50 Water Gr-Beta Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Sr-89 Sr-90 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 January -
June 2002 A
A A
A A
NA (1)
A A
A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 23.1 74.9 24.5 73 228 95.6 26.3 33.3 21.9 80 23.3 71.7 214 95.7 29 36.4 13.2 - 30.6 66.4 - 93.6 14.6 - 32.0 63.0 - 80.4 195 - 233 79.4 - 112 20.3 - 37.7 27.7 - 45.1 A
A A
A CE (2)
A A
A
1-131 IN MILK 85 CA(
120 -
100 80 a
P 60-cL 40-20 -
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320 L.
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180 -
s 160-
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Q 120 w
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250 1 we 200-J 150-100 w
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250 -
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100 I
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88 Sr-90 IN MILK 60-40 X.
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90 GROSS BETA IN FILTERS 200 180 160 L140iI 120 100 l
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91 Cs-137 IN FILTERS 200 -
160 -
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CL 80-40 0
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Zn-65 IN FILTERS 92 c.ri 200 160 120 a
80 40 0
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g 60 0 CL40-20 0
1/1/02 4/2/02 7/2/02 10/1/02 1/1/03 l - FRM
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60 40 20 0
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95 cZ° Cs-137 IN WATER 300 250 -
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Zn-65 IN WATER 200-160-N-
2 120 C. 80 -
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