ML091270309: Difference between revisions
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(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)08 N/A N/A N/A N/A N/A N/A N/A 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A 1500(2/4)(1490-1510) | (0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)08 N/A N/A N/A N/A N/A N/A N/A 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A 1500(2/4)(1490-1510) | ||
N/A N/A N/A N/A N/A N/A (0/4)1480(2/4)(1380-1580) | N/A N/A N/A N/A N/A N/A (0/4)1480(2/4)(1380-1580) | ||
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0*0 0 0 0 0.0 31 3.2 Analytical Results of 2008 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.The data reported in the following tables are strictly counting statistics. | (0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0*0 0 0 0 0.0 31 | ||
===3.2 Analytical=== | |||
Results of 2008 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.The data reported in the following tables are strictly counting statistics. | |||
The reported error is two times the standard deviation (2a) of the net activity. | The reported error is two times the standard deviation (2a) of the net activity. | ||
Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 3y).Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For clarity of this report only detectable results are presented. | Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 3y).Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For clarity of this report only detectable results are presented. | ||
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For the twelve locations within 10 miles of the station the average quarterly reading was 3.3 mR/standard month with a range of 1.6 to 5.8 mR/standard month. The average annual reading for these locations was 3.2 mR/standard month with a range of from 1.9 to 4.8 mR/standard month. The control location showed a quarterly average of 2.9 mR/standard month with a range of 2.0 to 4.2 mR/standard month. Its annual reading was 2.9 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.1 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.3 mR/standard month. Eight other TLDs, designated C-I thru C-8, which were pre-operational controls, were collected quarterly from four locations. | For the twelve locations within 10 miles of the station the average quarterly reading was 3.3 mR/standard month with a range of 1.6 to 5.8 mR/standard month. The average annual reading for these locations was 3.2 mR/standard month with a range of from 1.9 to 4.8 mR/standard month. The control location showed a quarterly average of 2.9 mR/standard month with a range of 2.0 to 4.2 mR/standard month. Its annual reading was 2.9 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.1 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.3 mR/standard month. Eight other TLDs, designated C-I thru C-8, which were pre-operational controls, were collected quarterly from four locations. | ||
Stations C-3/4 and C-7/8 are designated controls. | Stations C-3/4 and C-7/8 are designated controls. | ||
These had a quarterly average of 3.3, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.6 to 4.8 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.61 4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. | These had a quarterly average of 3.3, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.6 to 4.8 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.61 | ||
===4.2 Airborne=== | |||
Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. | |||
Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable. | Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable. | ||
Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide. | Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide. | ||
Revision as of 13:42, 14 October 2018
| ML091270309 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/27/2009 |
| From: | Simmons G R Dominion, Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 09-226 | |
| Download: ML091270309 (87) | |
Text
Dominion North Anna Power Station Annual Radiological Environmental Operating Report January 1, 2008 to December 31, 2008 Prepared by Dominion, North Anna Power Station Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2008 to December 31, 2008 Prepared by: Reviewed by: Approved by:.George R. Simmons Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Erich W. Dreyer Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert A vans, Jr.Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2 Table of Contents 1. EXECUTIVE
SUMMARY
..............................................................................
4 2. PROGRAM DESCRIPTION
............................................................................
7 2.1 In trodu ction ..............................
...........................................................
7 2.2 Sampling and Analysis Program ............................................................
8 3. ANALYTICAL RESULTS ...............................................................................
22 3.1 Summary of Results.............'.................................
22 3.2 Analytical Results of 2008 REMP Samples .........................................
32 4. DISCUSSION OF RESULTS ...........................................................................
60 4.1 Gamma Exposure Rate .........................................................................
60 4.2 Airborne Gross Beta ...........................................................................
62 4.3 Airborne Radioiodine
..........................................................................
63 4.4 Air Particulate Gamma .......................................................................
63 4.5 Air Particulate Strontium
...................................................................
63 4.6 Soil ..........................................................
64 4 .7 Precipitation
...............................................
.......................................
64 4 .8 C ow M ilk ...... I ....................................................................................
64 4.9 Food Products and Vegetation
....................................
65 4.10 W ell W ater .......................................................................................
65 4.11 River Water ..................................................
65 4.12 Surface W ater ..................................................................................
66 4.13 Bottom Sediment ............................................................................
67 4.14 Shoreline Soil ..................................................................................
68 4 .15 F ish ..........................................................................................
...... 6 9 5. PROGRAM EXCEPTIONS
...........................................................................
70 RE FE RE N C E S ................................................................................................
7 1 A P PE N D IC E S .....................................................................................................
73 APPENDIX A: LAND USE CENSUS ..............................................................
74 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS
................
77 3
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2008 North Anna Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2b. Radioactivity levels from January 1 through December 31,-2008, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, "and direct exposure pathways have been analyzed, evaluated and summarized.
The REMP is designed to 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 25-mile radius of the station. North Anna 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, is collected from areas that are beyond the measurable influence of North Anna Power Station or any other nuclear facility.
These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can 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 Chemobyl accident or natural variation.
Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and GEL Laboratories, LLC provided radioanalytical 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 Nuclear Regulatory Commission (NRC) requires that equipment used for 4 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 NRC also mandates a reporting 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, water, aquatic, terrestrial, and direct radiation exposure.
The airborne exposure pathway includes radioactive airborne iodine, particulates, and precipitation.
The 2008 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.Water and aquatic exposure pathway samples include surface, river and well water, silt and shoreline sediments, and fish. No plant related isotopes were detected in Lake Anna surface water except for tritium. The average tritium activity in surface water for 2008 was 3580 pCi/liter.
River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3660 pCi/liter.
No plant related isotopes were detected in well water.This trend is consistent throughout the environmental operational monitoring program. Both silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background.
Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels. No plant related isotopes were detected in shoreline soil. Cs-137 was detected in one indicator sample and one sample from the control location of sediment silt. Cs- 137 was detected in the indicator location at a level of 21.2 pCi/kg and at the control location sediment sample at 120 pCi/kg. This Cs-137 level is consistent with historic levels. The terrestrial exposure pathway includes milk and food/vegetation products.
Iodine-131 was not detected in any 2008 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident.
No plant related radioisotopes were detected in any milk or vegetation samples. Naturally occurring beryllium-7, potassium-40 and thorium 228 were detected at environmental levels consistent with historical data.. Low levels of Cs-137 have been detected intermittently in past years. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years.The vendor failed to perform sets of analyses as requested by North Anna in accordance with program requirements.
The samples were disposed of by the 5 vendor before the analyses could be performed.
These analyses were:* Gamma spectrometry on the 1st half-year composite of precipitation from Station 01A* Sr-89/90 analyses on the 2nd quarter composite of air particulate patches from Stations 01-07 and 21-24 1* Sr-89/90 analyses on the 2nd quarter composite of river water samples from Station 11." Sr-89/90 analyses on the 2nd quarter composite of surface water samples from Stations 08 and 09A.Due to these and other issues associated with this vendor, beginning January 2009, a new vendor will be used for performance of environmental analyses.During 2008, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) 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 2008 was 0.38 millirem.
For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%. These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.6
- 2. PROGRAM DESCRIPTION
2.1 Introduction
This report documents the 2008 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).The North Anna Power Station of Dominion Virginia Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia.
The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation.
Each unit was designed with a gross electrical output of 979 megawatts electric (MWe). Unit 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as is reasonably achievable (ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications, which address the release of radioactive effluents.
In-plant monitoring is used to ensure release limits are not exceeded.
As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).North Anna Power Station is responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions is responsible for processing the TLDs. GEL Laboratories, LLC 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.
Occasional samples of environment media show the presence of man-made isotopes.
As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and 7
- 9 North Anna's 'ODCM. These concentrations are based upon the annual dose commitment recommended by 1OCFR50, 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 2008 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 2008 sampling program for North Anna Power Station.All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." The North Anna Radiological Monitoring Locations maps denote sample locations for North Anna Power Station. The locations are color coded to designate sample types. Table 2-2 summarizes the analysis program conducted by GEL Laboratories, LLC for North Anna Power Station during the year 2008.8 TABLE 2-1 North Anna Power Station -2008 RADIOLOGICAL SAMPLTNG STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Environmental Thermoluminescent Dosimetry (TLD)Location NAPS Sewage Treatment Plant Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700"Aspen Hills" Orange, VA Bearing Cooling Tower Sturgeon's Creek Marina Parking Lot "C" (on-site)Good Hope Church Parking Lot "B" Lake Anna Marina (Bogg's Dr)Weather Tower Fence Route 689 Near Training Facility"Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)"Aspen Hills" Elk Creek NAPS Access Rd.Station Distance Direction Degrees Frequency Remarks 01 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-11/43 ESE-12/44 SE-13/45 SE-14/46 SSE-16/48 S-17/49 0.20 5.30 7.10 5:10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.47 NE SSW WSW WNW NNE N ESE SSE WNW WSW SSE NW N N NNE NNE NE NE ENE ENE E E ESE ESE SE SE SSE SSE S 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.*** Air Sample Station at 01A was added in October 2007.**** Station at 14a was added in October 2008 and Station 14 was deleted.9 TABLE 2-1 North Anna Power Station -2008 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Environmental Thermoluminescent Dosimetry (TLD)Location Elk Creek Church NAPS Access Rd.Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate -Construction Side Laydown Area Lake Anna Campground
- 1/#2-Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NAPS Sewage Treatment Plant Biology Lab***Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA Station S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55-WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 1.55 0.42 5.30 0.6 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.45 2.54 0.07 2.21 37.30 22.00 7.10 11.54 Direction S SSW SSW SW SW WSW WSW W W WNW WNW NW NW NNW NNW SSE NW WSW WSW TABLE 2.1 North Anna Power Station -2008 RADIOLOGICAL SAMPLING STATION -.DISTANCE AND DIRECTION FROM UNIT NO. 1 Degrees 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control Control Airborne Particulate and Radioiodine 01 01A 03 04 05 05A 06 07 0.20 0.64 7.10 5.10 4.20 2.04 4.70 7.30 NE SE WSW WNW NNE N ESE SSE 420 1380 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.* Air Sample Station at 01A was added in October 2007.**** Station at 14a was added in October 2008 and Station 14 was deleted.10 TABLE 2-1 North Anna Power Station -2008 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Airborne Particulate-and Radioiodine Location End of Route 685 Route 700"Aspen Hills" Orange, VA Station 21 22 23 24 TABLE 2-1 North Anna Power Station -2008 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)Precipitation Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)*Lake Anna (upstream).(Route 669 Bridge)North Anna River (downstream)
Biology Lab Biology Lab Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream)
Waste Heat Treatment Facility (Second Cooling Lagoon)NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 3.37 SSE 148" Monthly 09A 11 01A 01A 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE 1380 Monthly Control 08 3.37 SSE 148" Semi-Annually 09A 12.90 WNW 295" Semi-Annually 5.80 SE 128" Semi-Annually Control 11 Shoreline Soil Soil 08 **3.37 SSE 148" Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 42" 203" 243" 2870 Once/3 years Once/3 years Once/3 years Once/3 years* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.* Air Sample Station at 01 A was added in October 2007.**** Station at 14a was added in October 2008 and Station 14 was deleted.11 TABLE 2-1 North Anna Power Station -2008 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 , Once/3 years Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)'Aspen Hills" Orange, VA Holladay Dairy (R.C. Goodwin)Terrell's Dairy (Fredericks Hall)Anderson's Farm Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Orange 05A 06 07 21 22 23 24 2.04 4.70 7.30 1.00 1.00 0.93 22.00 N ESE SSE WNW WSW SSE NW 110 1150 1670 3010 2420 1580 3250 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Control Milk 12 13 27 08 25 8.30 NW 5.60 SSW 2.49 ENE 3.37 SSE 3100 2050 660 Monthly Monthly Monthly Fish 1480 Semi-Annually 3120 Semi-Annually 16.5 NW Control Food Products Vegetation)
Bel Aire Plantation Moody Lane****14 14a 1.20 NE 1.70 ESE 430 Monthly if available or at harvest 1030 Monthly if available or at harvest Route 614 Route 629/522 15 16 23 1.37 SE 1330 Monthly if available or at harvest 12.60 NW 3140 Monthly if available or at harvest 1580 Monthly if available or at harvest Control Aspen Hills 0.93 SSE* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.*** Air Sample Station at 01A was added in October 2007.* Station at 14a was added in October 2008 and Station 14 was deleted.12 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)(84 TLDs)(12 TLDs)Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Weekly Gamma Dose Gamma Dose 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month 1-131 Gross Beta Surface Water Quarterly (a)2 nd Quarter Composite Monthly Quarterly(a) 2nd Quarter Composite Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 0.07 0.01 0.05 0.06 (b)(b)1(c)15 30 15 15 30 30 15 15 18 60 15 2000 (b)(b)1(c)15 30 15 15 30 30 15 15 18 60 15 pCi/m 3 pCi/m 3 pCi/m 3 pCi/mr 3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L River Water Monthly*LLDs indicate those levels to which environmental samples are required to be analyzed.
Actual analysis of samples may be lower than the listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.
13 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA River Water I FREQUENCY Quarterly(a) 2 nd Quarter Composite ANALYSIS Tritium (H-3)Sr-89 Sr-90 Ground Water (Well Water)Quarterly Quarterly(a) 2nd Quarter Semi-Annually Aquatic Sediment Annually Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 LLD 2000 (b)(b)15 30 15 15 30 30 15 1(c)15 18 60 15 2000 (b)(b)REPORT UNITS pCi/L pCi/L Precipitation Monthly Semi-Annual
'Composite pCi/L pCi/L pCi/L 150 180 (b)(b)4 15 30 15 15 30 30 15 1(c)15 18 60 15 pCi/kg (dry)pCi/kg (dry)pCi/L pCi/L Shoreline Soil Semi-Annually 150 180 (b)(b)pCi/kg (dry)pCi/kg (dry)Annually*LLDs indicate those levels to which environmental samples are required to be analyzed.be lower than the listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are norequired LLDs for Sr-89/90 (c). LLD for non-drinking water is 10 pCi/liter.
14 Actual analysis of samples may A" TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM q A MIPT IP A .'. A ipppn'rnTpNiFV Soil Soil Once per 3 years Milk Monthly Monthly Quarterly ANALYSIS Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137-Ba-140 La-140 Sr-,89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 150 180 (b)(b)1 15 18 60 15 (b)(b)LLD REPORT UNITS pCi/kg (dry)pCi/kg (dry)pCi/L pCi/L Fish Semi-Annually pCi/kg (wet)130 260 130 130 260 130 150 pCi/kg (wet)60 80 60 Food Products (Broadleaf Vegetation)
Monthly, if available, or at harvest*LLDs indicate those levels to which environmental samples are required to be analyzed.
Actual. analysis of samples may be lower than the listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.
15 A Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation Environmental Station Identification 1 (a) 01,NE-5/37 IA O1A,SE-13/45 2 (a) 02,SSW-20/52 3 (a) 03,C-5/6 4 (a) 04 5 (a) 05 5A (a) 05A,N-2/34 6 (a) 06,ESE-12/44 7 (a) 07,C- 1/2 8 08-Water, Fish Sediment, Shoreline Soil 9A 09A-Water sample, sediment 11 11 -River Water, Sediment 12 12-Milk 13 13-Milk 14 (d) 14-Vegetation, NE-6/38 14a (d) 14a-Vegetation 15 15-Vegetation 16 16-Vegetation 21 (a) 21,WNW-27/59 22 (a) 22,WSW-24/56 23 (a) 23-SSE-15/47 24 (a)(b) 24,C-3/4 25 (c) 25-Fish 26 26-Vegetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.(b) In Orange (c) In Lake Orange (d) Station 14a replaced 14 in October 2008 16 27 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 27-Milk C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE- 14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E- 10/42 1/43 WSWE Legend 114 S 34 Fod EnvOm~nmavf Mom~oawng Staton* LD Locaums Figure 1. North Anne Site Radlo"Ical Monftring Locations 17 NOTM Anna Lnv'ironnmentai map*Fixed ErvircrintrnaI Sarnoing Locaiiotr* Th Samptpi*Garden Residents Meal kimrals c~~1~~uiaý Gu utaF44: ~srmuI mow ~k Auc.¶~iuv a A l2 U6CA VA1H PCIMPSSW#4 Kzdtnr-W :ajoa_prt~nmg wfu iýU 11-v wilki puwnubrn otA3 CU213C 18 North Anna Environmental Map Fixed Envrnrmenla Sarrwpling Locaion-LD Sarnping Residents Meat Animals AivcuuIv, W*775I2 L=E3 MZC9UM G 4 Wlb rvWW:U 19 ILMDO lassiNG WSW ii',,,\z I.- % .L r North Anna Environmental Map Fixed Envwnrurta Sunplirn Locatcn* TLD S&ing Garden Resbents Meat Animas tat;vta *C1291 bhA rncdkuwtw h: 14G] riGl Mdi=tu VA:3i 2 LSC D, 1 M M 13 I ON di w i'mlidur i~bs m** gl~v~wuxt Mtnpn awADC.~.. ~~cunau 20
, %4-1 WNW , MONflOVIA ti North Anna Environmental Map* Fixed Environmental Sampling Location* TLD Sampling O Garden Residents* Meat Animals 11 F Cr~g~na CO 1 991 by A0C a# A~xdan8 Ia. i 6440 General Green' Way, AlexgNanf1 Vh% 22312. LSED Wf17 PERMI~SSION.
NJo eth reproduc~on ruv be Trrae *Vmtra the W~r"te peWMWn WADC.CB32110 21
- 3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM.For radioanalytic analyses, the values listed in the columns indicated as"Mean/Range" include any results above the Minimum Detectable Activity.Results are considered positive when the measured value exceeds 1.5 times the listed 2y error (i.e., the measured value exceeds 3y). For TLDs the mean and range include all values.A more detailed analysis of the data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries.
22 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 1 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine.Pathway I LLD(') I Reported Sampled (Unit) Total (pCi/unit)
Mean Name Distance Mean Mean Measure-Type No. _ ' Range Direction Range Range ments Direct Radiation (mR/std. Month)(Sector TLDs)Direct Radiation (mR/std. Month)(Pre-operational TLDs)Direct Radiation (mR/std. Month)(Emergency Sector TLDs)Direct Radiation (mR/std. month)(Environmental TLDs)Direct Radiation (mR/std. Month)(Annual TLDs)Airborne Particulates (1E-03 pCi/m 3)Gamnna Dose Gamma Dose 256 2 5.2(256/256)
(1.1-46.9) 2 2.6(16/16)
(1.6-4.0)19/51(2) 0.42 mi.SSW 34.0(8/8)(9.0-46.9) 3.3(16/16)*
(2.0-4.8)3.3(16/16)*
(2.0-4.8)0 32 C-1/2 7.3 mi. 3.1(16/16)
SSE (2.5-4.0)0 Gamma Dose 40 2 5.1(40/40)
EPSP- 0.37 mi. 7.3(8/8)(2.5-8.9) 09/10 ENE (5.5-8.9)3.3(16/16)*
(2.0-4.8)0 Gamma Dose Gamma Dose Gross Beta 48 12 2 3.3(44/44)
(1.6-5.8)2 3.2(11/11)
(1.9-4.8)23 0.93 mi. 4.7(4/4)SSE (3.6-5.8)23 0.93 mi. 4.8(1/1)SSE (4.8)01 0.20 mi. 35.2(52/52)
NE (7.63-72.0) 2.9(4/4)(2.0-4.2)2.9(1/1)(2.9)32.2(52/52)
(10.9-64.6) 0 0 0 676 0.01 33.2(624/624)
(6.77- 72.4)Air Iodine (pCi/m 3)1-131 675 0.07 6.95(1/623)
(6.95)04 5.1 mi.WNW 6.95(1/52)
(6.95)(0/52)0 Airborne Particulates.
(1E-03 pCi/m 3)Gamma 52 Be-7 52 165(48/48) 07 7.3 mi. 175(4/4)169(4/4)(105-253)SSE (121-253)
(118-254),1*1 Cs-134 52 0.05 Cs-137 52 0.06 (0/48)(0/48)N/A N/A N/A N/A (0/4)(0/4)N/A N/A (1) mR/std month for TLDs , (2) 19/51 located onsite near ISFSI.* Results of C-3/4 and C-7/8 used as control location 23 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 2 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) I Type INo. 1 -I Range I Directioni Range Range ments Airborne Particulates (1E-03 pCi/m3)Soil (pCi/Kg) (dry)Sr-89 Sr-90 0 0 (0/0)(0/0)N/A N/A N/A N/A N/A N/A (0/0)(0/0)0 0 Triennial Gamma Be-7 K-40 Cs-134 Cs-137 Th-228 Sr-89 Sr-90 N/A N/A N/A N/A N/A N/A N/A N/A 150 180 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 Precipitation (pCi/liter)
Monthly Gross Beta Semiannual Gamma Mn-54 Fe-59 Co-58 Co-60 12 4 50.8(7/12)
(2.25-316) 01A 0.64 mi. 50.8(7/12)
SE (2.25-316)
N/A 0 15 30 15 15 (0/1).(0/1)(0/1)(0/1)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 24 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 3 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)
Mean Name Distance Mean Mean Measure-Type No. Range Direction Range Range ments Precipitation (pCi/liter)
Zn-65 1 30 (0/1)Zr-95 1 30 (0/1)Nb-95 1 15 (0/1)1-131 1 10 (0/1)Cs-134 1. 15 (0/1)Cs-.137 1 18 (0/1)Ba-140 1 60 (0/1)La-140 1 15 (0/1)N/A N/A N/A N/A N/A N/A N/A N/A N4/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 N/A N/A N/A N/A N/A 0 0 0 0 Milk (pCi/liter)
Gamma 24 K-40 24 1390(24/24)
(1260-1550) 12 8.3 mi. 1410(12/12)
NW (1320-1510) 1-131 24 1 (0/24)Cs-134 24 15 (0/24)Cs-137 24 18 (0/24)Ba-140 24 60 (0/24).La-140 24 15 (0/24)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 Sr-89 (Quarterly) 8 (0/8)25 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 4 of 9 All Indicator Control Non-Medium or Anal sis Locations 4 Location with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range .Direction Range Range ments Milk (pCi/liter)
Sr-90 8 (Quarterly)
Gamma 31 (0/8)N/A N/A N/A N/A 0 Food Vegetation (pCi/kg) (wet)Be-7 31 K-40 31 1110(25/25)
(412-2200) 3910(25/25)
(3320-17600) 14a varies 2090(1/1)ESE (2090)15 varies 5040(6/6)SE (3520-7410) 749(6/6)(344-1250) 4810(6/6)(3720-6600) 1-131 31 60 (0/25)Cs-134 31 60 (0/25)Cs-137 31 80 (0/25)N/A N/A*N/A N/A N/A N/A 01A 0.64 mi.SE N/A N/A N/A (0/4)(0/6)(0/6)(0/6)N/A 0 0 0 0 0 Ground Well Water (pCi/liter)
Tritium 4 2000 (0/4)Gamma 4 Mn-54 4 15 (0/4)Fe-59 4 30 (0/4)Co-58 4 15 (0/4)Co-60 4 15 (0/4)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 N/A N/A N/A N/A 26 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 5 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine SaPathway LLD Reported Sampled (Unit) Total (pCi/unit)
Mean Name Distance Mean Mean Measure-Type No. Range Direction Range Range ments Ground Well Water (pCi/liter)
Zn-65 4 30 (0/4)Zr-95 4 30 (0/4)Nb-95 4 15 (0/4)1-131 4 1 (0/4)Cs-134 4 15 (0/4).Cs-137 4 18 (0/4)Ba-140 4 60 (0/4)La-140 4 15 (0/4)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/Am N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0..0 0 0 0 0 0 Sr-89 1 Sr-90 1 (0/1)(0/1)River Water (pCi/liter)
Tritium 4 2000 3660(4/4)(2850-4100) 11 5.80 mi. 3660(4/4)SE (2850-4100)
(0/4)*0 Gamma 12 Mn-54 12 15 (0/12)Fe-59 12 30 (0/12)N/A N/A N/A N/A N/A N/A (0/12)*(0/12)*0 0*Results of surface water taken at Location 09A used as control value for river water.27 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 6 of 9 All Control Non-Medium or Analysis Indicator Location with Highest Mean Location routine Locations Pathway LLD Reported Sampled (Unit) Total (pCi/unit Mean Name Distance.
Mean Mean Measure-IType No. I I Range Direction Range Range ments River Water (pCi/liter)
Co-58 12 Co-60 12 Zn-65 12 Zr-95 12 Nb-95 12 1-131 12 Cs-134 12 Cs-137 12 Ba-140 12 La-140 12 Sr-89 0 Sr-90 0 15 (0/12)15 (0/12)30 (0/12)30 (0/12)15 (0/12)1 (0/12)15 (0/12)18 (0/12)60 (0/12)15 (0/12)-(0/0)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/0)*(0/0)*-(0/0) N/A N/A 0*Results of surface water taken at Location 09A used as control value for river water.28 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 7 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routin Pathway LLD Report(Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measur (Unit) Typ No. Range Direction Range Range ments Tritium 8 2000 3580(4/4) 08 3.37 mi. 3580(4/4)
(0/4) 0 Surface Water (2730-4140)
SSE (2730-4140)(pCi/liter)
Gamma 24 Mn-54 24 15 (0/12) N/A N/A N/A (0/12) 0 Fe-59 24 30 (0/12) N/A N/A N/A (0/i2) 0 Co-58 24 15 (0/12) N/A N/A N/A (0/12) 0 Co-60 24 15 (0/12) N/A N/A N/A (0/12) 0 Zn-65 24 30 (0/12) N/A N/A N/A (0/12) 0 Zr-95 24 30 (0/12) N/A N/A N/A (0/12) 0 Nb-95 24 15 (0/12) N/A N/A N/A (0/12) 0 1-131 24 1 (0/12) N/A N/A N/A (0/12) 0 Cs-134 24 15 (0/12) N/A N/A N/A (0/12) 0 Cs-137 24 18 (0/12) N/A N/A N/A (0/12) 0 Ba-140 24 60 (0/12) N/A N/A N/A (0/12) 0 29 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia 2008 Docket No. 50-338/339 Page 8 of 9 All Indicator Control Non-, Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Surface Water (pCi/liter)
La-140 24 15 (0/12)Sr-89 0 Sr-90 0 Gamma 6 K-40 6 (0/0)(0/0)N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)(0/0)(0/0)0 0 0 Sediment Silt (pCi/kg) (dry)10300(4/4)
(4690-18100) 11 5.80 mi. 14700(2/2) 10500(2/2) 0 SSE (11200-18100)(8100-12800)
Cs-134 6 150 (0/4)Cs-137 6 180 21.2(1/4)21.2 N/A N/A (0/2)11 5.80 mi. 21.2(1/2)SSE (21.2)(0/2)120(1/2)(120)(0/1)(0/1)0 0 0 0 Sr-89 (Annually)
Sr-90 (Annually) 3 (0/2)(0/2)N/A N/A N/A N/A N/A N/A 3 Shoreline Soil (pCi/kg) (dry)Gamma 2 K-40 2 -Cs-134 2 150, 2990(2/2)(2240-3730)
(0/2)08 3.37 mi. 2990(2/2)SSE (2240-3730)
N/A N/A N/A N/A (0/2)(0/2)N/A N/A N/A 0 0 0 Cs-137 2 180 N/A 30 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2008 Docket No. 50-338/339 Page 9 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)
Mean Name Distance Mean Mean Measure-_Type_ _ No. I Range jDirection Range Range ments Shoreline Soil (pCi/kg) (dry)Fish (pCi/kg) (wet)Sr-89 (Annually)
Sr-90 (Annually)
Gamma K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 (0/1)(0/1)N/A N/A N/A N/A N/A N/A N/A N/A 0 0 130 260.130 130 260 130 150 1500(2/4)(1490-1510)
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)08 N/A N/A N/A N/A N/A N/A N/A 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A 1500(2/4)(1490-1510)
N/A N/A N/A N/A N/A N/A (0/4)1480(2/4)(1380-1580)
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0*0 0 0 0 0.0 31
3.2 Analytical
Results of 2008 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.The data reported in the following tables are strictly counting statistics.
The reported error is two times the standard deviation (2a) of the net activity.
Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 3y).Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For clarity of this report only detectable results are presented.
GEL Laboratories, LLC'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 North Anna ODCM.Data are given according to sample type as indicated below.1. Gamma Exposure Rate 2. Air Particulates, Gross Beta Radioactivity
- 3. Air Particulates, Weekly 1- 131 4. Air Particulates, Quantitative Gamma Spectra 5. Air Particulate Strontium 6. Soil 7. Precipitation
- 8. Cow Milk 9. Food Products and Vegetation
- 10. Well Water 11. River Water 12. Surface Water 13. Bottom Sediment/Silt
- 14. Shoreline Soil 15. Fish'Analytical results are handled as recommended by HASL ("Reporting ofAnalytical Results from HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).32 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Station 12/28/2007 04/01/2008 06/27/2008 10/01/2008 04/01/2008 06/26/2008 09/30/2008 12/31/2008 N-1 4.4 3.6 3.3 4.5 4 N-33 5.7 4.3 3.3 4.0 N-2 4.5 2.2 2.5 2.9 3 N-34 3.8 3.4 2.1 3.8 NNE-3 8.5 6.3 6.1 7.7 7 NNE-35 7.2 5.3 6.8 8.4 NNE-4 4.2 4.1 3.7 3.8 4 NNE 36 5.2 4.2 3.3 3.9 NE-5 6.0 3.5 2.9 4.3 4 NE-37 5.0 3.5 2.3 4.4 NE-6 3.6 2.9 2.1 3.1 3 NE-38 4.6 3.4 2.5 3.4 ENE-7 6.8 5.6 4.5 5.7 5 ENE-39 7.0 4.3 4.3 5.8 ENE-8 3.6 3.5 3.0 2.5 3 ENE-40 4.3 2.5 2.6 2.8 E-9 6.5 6.1 4.3 4.5 5 E-41 6.2 4.7 4.0 4.5 E-10 6.4 4.5 3.7 5.0 4 E-42 5.5 5.4 3.5 4.8 ESE-11 5.5 3.1 2.9 4.1 4 ESE-43 5.6 4.6 4.3 3.6 ESE-12 5.2 4.3 3.1 3.9 4 ESE-44 5.0 4.2 3.6 4.6 SE-13 5.2 4.1 3.3 4.2 4 SE-45 5.8 3.6 3.6 4.0 SE-14 6.3 6.2 5.7 6.3 6 SE-46 7.7 6.3 5.5 6.6 SSE-15 5.9 4.9 3.5 4.7 4 SSE-47 5.3 4.5 3.8 5.0 SSE-16 4.3 2.0 2.2 3.0 2 SSE-48 3.8 2.8 2.1 2.6 Page 1 of 4 Quarterly*
Average+/- 2 s.d..1 +/- 1.6.2 +/- 1.7.0 +/- 2.3.1 +s/- 1.1.0 +/- 2.4.2 +/- 1.5.5 +/- 2.1.1 +/- 1.3.1 +/- 2.0.9 +/- 1.9.2 +/- 2.0.2 +/- 1.4.2 +/- 1.7.3 +/- 1.3.7 +/- 1.6.9 +/- 1.7*Average of collocated TLDs.33 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quartei Third Quarter Fourth Quarter Quarterly*
Station 12/28/2007 04/01/2008 06/27/2008 10/01/2008 Average 04/01/2008 06/26/2008 09/30/2008 12/31/2008
+/- 2 s.d.Page 2 of 4 S-17 S-49 S-18 S-50 SSW-1 9 SSW-51 SSW-20 SSW-52 SW-21 SW-53 SW-22 SW-54 WSW-23 WSW-55 WSW-24 WSW-56 W-25 W-57 W-26 W-58 WNW-27 WNW-59 WNW-28 WNW-60 NW-29 NW-61 NW-30 NW-62 NNW-31 NNW-63 NNW-32 NNW-64 9.0 7.8 3.9 3.3 21.0 46.9 3.6 3.4 5.7 5.8 5.4 5.4 6.2 6.8 5.1 5.3 7.9 8.3 4.0 4.0 42 4.1 3.6 3.8 7.2 7.5 2.4 3.2 4.6 4.3 3.6 4.2 7.5 7.8 1..9 1.7 39.3 38.7 2.4 2.6 4.5 4.3 4.2 4.2 5.7 4.1 4.4'4.1 7.2 5.3 2.1 2.4 3.3 3.1 2.2 2.1 6.3 6.4 2.3 2.1 3.4 2.5 3.3 2.5 7.0 7.7 1.1 1.6 39.4 37.1 1.6 1.5 3.6 3.6 3.4 3.2 5.8 4.6 3.6 3.2 5.6 6.2 2.9 1.9 2.8 2.3 2.5 1.8 5.3 5.6 1.8 0.6 2.6 2.6 3.0 2.7 7.6 7.2 3.3 2.2 9.2 40.0 2.4 2.2 4.6 4.5 3.8 4.0 5.7 5.4 4.1 4.1 6.6 6.4 3.4 2.7 2.7 3.3 2.9 2.7 6.1 6.1 1.7 2.5 3.5 3.6 3.3 3.2 7.7 +/- 1.2 2.4 +/- 2.0 34.0 +/- 24.8 2.5 +/- 1.5 4.6 +/- 1.6 4.2 +/- 1.6 5.5 +/- 1.7 4.2 +/- 1.4 6.7 +/- 2.1 2.9 +/- 1.6 3.2 +/- 1.3 2.7 +/- 1.4 6.3 +/- 1.5 2.1 +/- 1.5 3.4 +/- 1.6 3.2 +/- 1.1 5.2 +/- 5.8 Mean*Average of collocated TLDs.34 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS mRIStd. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Station 12/28/2007 04/01/2008 06/27/2008 10/01/2008 04/01/2008 06/26/2008 09/30/2008 12/31/2008 Page 3 of 4 C-1 C-2 C-3"*C-4"*C-5 C-6 C-7"*C-8"*4.0 3.8 4.1 3.4 2.9 2.3 4.8 4.3 3.2 3.0 3.1 3.1 2.4 1.6 3.6 3.7 3.5 3.5 4.8 4.8 5.7 4.4 4.9 4.6 7.6 7.9 2.5 2.5 2.5 2.0 1.8 1.7 2.3 2.9 3.5 3.9 3.8 3.9 4.3 3.8 4.0 2.5 5.8 5.5 2.7 3.1 3.3 3.0 2.2 2.0 3.4 3.4 Mean Indicator Control**4.8 4.9 4.2 4.4 4.1 4.7 3.9 3.8 7.3 7.6 Quarterly*
Average+/- 2 s.d.3.1 +/- 1.1 3.1 +/- 1.2 2.1 +/- 0.9 3.6 +/- 1.5 2.6 +/- 0.7 3.3 +/- 0.7 4.6 +/- 2.6 4.7 +/- 1.6 4.8 +/- 1.6 4.2 +/- 1.7 7.3 +/- 2.2 5.1 +/- 1.5 EPSA-Ol**EPSA-02***
EPSF-03***
EPSF-04***
EPSRO-5***
EPSR-06***
EPSJ-07***
EPSJ-08***
EPSP-09***
EPSP-1 0**6.7 6.3 5.8 6.0 6.2 5.0 4.8 5.0 7.7 8.9 Mean*Average of collocated TLDs.** Control Station*** Emergency Plan TLDs.35 4 0 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 4 of 4 First Quarter Station 12/28/2007 04/01/2008 STA-01 4.4 STA-02 3.3 STA-03 3.1 STA-04 3.4 STA-05 4.3 STA-05A 4.1 STA-06 5.0 STA-07 3.5 STA-21 3.5 STA-22 4.2 STA-23 5.8 Second Quarter 04/01/2008 06/26/2008 5.0 2.2 2.3 3.5 3.1 2.1 4.4 3.2 3.3 4.1 4.9 Third Quarter Fourth Quarter 06/27/2008 10/01/2008 09/30/2008 12/31/2008 3.9 4.2 1.6 2.4 1.8 1.9 1.6 1.9 2.4 3.1 1.9 2.8 3.1 4.1 2.7 2.5 2.4 3.0 3.5 3.8 3.6 4.5 Quarterly Average+/- 2 s.d., 4.4 +/-2.4 +/-2.3 +/-2.6 +/-3.2 +/-2.7 +/-4.2 +/-3.0 +/-3.1 +/-3.9 +/-4.7 +/-AnnualTLD 0.9 1.4 1.2 2.0 1.6 2.0 1.6 0.9 1.0 0.6 1.8 4.5 1.9.1.9 2.3 3.0 2.9 3.7 2.7 3.0 4.3 4.8 Mean 3.3 +/- 1.0 2.9 +/- 0.9 3.2 +/- 2.0 2.9 STA-24**Control 4.2 2.6 2.0 2.8 36 Table 3-3 Air Particulate Gross Beta Radioactivity
[10-3 pCi/m 3]-A page 1 of 4 Period Ending 01/02/08 01/09/08 01/16/08 01/23/08 01/30/08 02/05/08 02/13/08 02/20/08 02/27/08 03/04/08 03/11/08 03/18/08 03/25/08 04/01/08 04/08/08 04/15/08 04/22/08 04/29/08 05/06/08 05/13/08 05/20/08 05/27/08 06/04/08 06/10/08 06/18/08 06/25/08 07/01/08 Station I 01 Station 01A Station Station Station I 6.23E+01 +/- 5.34E+00 3.53E+01 5.67E+01 +/- 5.10E+00 3.79E+01 2.74E+01 +/- 1.15E+01 3.02E+01 2.60E+01 +/- 1.50E+01 3.15E+01 7.20E+01 +/- 1.42E+01 5.89E+01 3.76E+01 +/- 1.79E+01 2.23E+01 4.17E+01 +/- 1.00E+01 2.94E+01 3.34E+01 +/- 1.39E+01 2.80E+01 3.55E+01 +/- 1.54E+01 2.76E+01 3.42E+01 +/- 1.56E+01 3.20E+01 2.60E+01 +/- 1.31E+01 2.36E+01 3.74E+01 +/- 1.28E+01 4.27E+01 2.17E+01 +/- 1.36E+01 1.77E+01 4.29E+01 +/- 4.53E+00 3.93E+01 1.85E+01 +/- 1.27E+01 1.55E+01 1.47E+01 +/- 1.16E+01 1.63E+01 7.63E+00 +/- 7.35E+00 9.01E+00 1.81E+01 +/- 7.39E+00 2.11E+01 5.33E+01 +/- 5.05E+00 3.99E+01 1.37E+01 +/- 1.40E+01 2.27E+01 2.20E+01 +/- 1.38E+01 1.96E+01 2.94E+01 +/- 9.64E+00 1.85E+01 2.92E+01 +/- 1.26E+01 1.93E+01 3.62E+01 +/- 1.63E+01 2.75E+01 3.23E+01 +/- 3.78E+00 3.06E+01 3.19E+01 +/- 1.29E+01 2.60E+01 4.20E+00 4.28E+00 1.15E+01 1.50E+01 1.42E+01 1.77E+01 9.78E+00 1.39E+01 1.51E+01 1.56E+01 1.31E+01 1.27E+01 1.36E+01 4.36E+00 1.24E+01 1.20E+01 7.39E+00 7.43E+00 4.42E+00 1.41E+01 1.38E+01 9.38E+00 1.25E+01 1.61E+01 3.69E+00 1.28E+01 4.98E+01 4.85E+01 3.46E+01 3.28E+01 5.89E+01 3.22E+01 4.16E+01 3.22E+01 3.53E+01 2.76E+01 2.76E+01 3.94E+01 2.29E+01 3.12E+01 1.72E+01 1.56E+01 1.28E+01 9.50E+00 4.68E+01 1.92E+01 2.16E+01'2.70E+01 2.71E+01 2.74E+01 3.96E+01 2.50E+01 4.94E+00 4.78E+00 1.15E+01 1.50E+01 1.40E+01 1.75E+01 1.01E+01 1.40E+01 1.51E+01 1.35E+01 1.39E+01 1.26E+01 1.38E+01 3.93E+00 1.32E+01 1.17E+01 7.33E+00 7.10E+00 4.75E+00 1.36E+01 1.31E+01 9.58E+00 1.28E+01 1.66E+01 4.05E+00 1.28E+01 5.43E+01 4.16E+01 3.59E+01 2.89E+01 6.01E+01 2.76E+01 3.84E+01 3.32E+01 3.15E+01 2.66E+01 2.43E+01 3.74E+01 2.22E+01 3.57E+01 2.18E+01 1.67E+01 1.21E+01 1.39E+01 4.60E+01 2.23E+01 2.47E+01 2.53E+01 2.32E+01 3.65E+01 3.43E+01 2.65E+01 I 5.05E+00 4.73E+01 4.48E+00 4.08E+01 1.16E+01 3.69E+01 1.50E+01 2.83E+01 1.40E+01 6.43E+01 1.78E+01 3.41E+01 9.95E+00 3.09E+01 1.40E+01 2.67E+01 1.53E+01 2.80E+01 1.55E+01 3.02E+01 1.30E+01 2.11E+01 1.27E+01 4.18E+01 1.36E+01 2.29E+01 4.17E+00 4.23E+01 1.27E+01 1.89E+01 1.18E+01 1.75E+01 7.40E+00 2.37E+01 7.24E+00 1.41E+01 4.71E+00 4.93E+01 1.26E+01 2.90E+01 1.38E+01 2.26E+01 9.54E+00 2.61E+01 1.23E+01 3.23E+01 1.68E+01 3.34E+01 3.86E+00 3.07E+01 1.30E+01 2.55E+01 I 4.83E+00 5.62E+01 4.39E+00 4.22E+01 1.18E+01 2.96E+01 1.50E+01 2.28E+01 1.42E+01 5.58E+01 1.78E+01 3.10E+01 9.79E+00 3.27E+01 1.39E+01 2.99E+01 1.51E+01 3.10E+01 1.58E+01 3.71E+01 1.33E+01 2.54E+01 1.28E+01 3.96E+01 1.36E+01 2.63E+01 4.47E+00 3.72E+01 1.31E+01 1.28E+01 1.18E+01 1.57E+01 7.71 E+00 3.44E+01 7.17E+00 1.34E+01 4.84E+00 4.95E+01 1.35E+01 1.92E+01 1.33E+01 2.47E+01 9.66E+00 3.03E+01 1.26E+01 3.37E+01 1.67E+01 3.29E+01 4.24E+00 3.58E+01 1.30E+01 2.43E+01 S 0+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-r)Station I0 05A 5.17E+00 3.83E+01 +/-4.50E+00 4.02E+01 +/-1.15E+01 3.24E+01 +/-1.49E+01 2.30E+01 +/-1.40E+01 5.54E+01 +/-1.76E+01 3.42E+01 +/-9.85E+00 3.43E+01 +/-1.40E+01 2.73E+01 +/-1.51E+01 2.50E+01 +/-1.57E+01 3.17E+01 +/-1.30E+01 2.57E+01 +/-1.27E+01 2.77E+01 +/-1.38E+01 2.78E+01 +/-4.25E+00 3.24E+01 +/-1.28E+01 1.65E+01 +/-1.21E+01 1.41E+01 +/-7.83E+00 3.50E+01 +/-7.21E+00 2.02E+01 +/-4.87E+00 4.79E+01 +/-1.34E+01 2.17E+01 +/-1.35E+01 2.09E+01 +/-9.62E+00 2.60E+01 +/-1.28E+01 3.27E+01 +/-1.69E+01 3.24E+01 +/-3.92E+00 3.86E+01 +/-1.28E+01 2.36E+01 +/-4.38E+00 4.41E+00 1.16E+01 1.49E+01 1.41E+01 1.77E+01 9.87E+00 1.40E+01 1.49E+01 1.56E+01 1.30E+01 1.25E+01 1.38E+01 4.00E+00 1.28E+01 1.20E+01 7.85E+00 7.40E+00 4.80E+00 1.34E+01 1.34E+01 9.53E+00 1.28E+01 1.69E+01 4.06E+00 1.28E+01 Sample lost by carrier during delivery to vendor for analysis.37 Table 3-3 Air Particulate Gross Beta Radioactivity
[10-3 pCi/m 3]page 2 of 4 Period Ending 01/02/08 01/09/08 01/16/08 01/23/08 01/30/08 02/05/08 02/13/08 02/20/08 02/27/08 03/04/08 03/11/08 03/18/08 03/25/08 04/01/08 04/08/08 04/15/08 04/22/08 04/29/08 05/06/08 05/13/08 05/20/08 05/27/08 06/04/08 06/10/08 06/18/08 06/25/08 07/01/08 I Station 06 Station 07 Station 21 Station 22 5.23E+01 +/-4.18E+01 +/-2.68E+01 +/-2.71E+01 +/-6.27E+01 +/-3.96E+01 +/-3.96E+01 +/-2.99E+01 +/-3.29E+01 +/-3.59E+01 +/-2.37E+01 +/-3.21E+01 +/-2.37E+01 +/-4.57E+01 +/-1.63E+01 +/-1.37E+01 +/-3.39E+01 +/-6.77E+00 +/-4.57E+01 +/-3.27E+01 +/-2.89E+01 +/-2.58E+01 +/-3.32E+01 +/-3.75E+01 +/-3.89E+01 +/-2.84E+01 +/-5.03E+00 4.48E+00 1.15E+01 1.49E+01 1.42E+01 1.77E+01 1.00E+01 1.40E+01 1.51 E+01 1.56E+01 1.30E+01 1.25E+01 1.38E+01 4.62E+00 1.28E+01 1.21 E+01 7.79E+00 1.03E+01 4.69E+00 1.36E+01 1.35E+01 9.54E+00 1.30E+01 1.65E+01 4.06E+00 1.28E+01 5.32E+01 +/-4.09E+01 +/-3.27E+01 +/-2.65E+01 +/-5.86E+01 +/-3.06E+01 +/-3.69E+01 +/-2.47E+01 +/-3.10E+01 +/-3.33E+01 +/-2.10E+01 +/-3.96E+01 +/-2.08E+01 +/-3.83E+01 +/-1.58E+01 +/-1.35E+01 +/-2.25E+01 +/-1.28E+01 +/-4.56E+01 +/-2.28E+01 +/-2.452+01 +/-2.76E+01 +/-2.40E+01 +/-3.62E+01 +/-4.09E+01 +/-3.48E+01 +/-5.07E+00 4.44E+00 1.15E+01 1.49E+01 1.40E+01 1.75E+01 9.97E+00 1.39E+01 1.50E+01 1.56E+01 1.31E+01 1.27E+01 1.37E+01 4.28E+00 1.28E+01 1.21E+01 7.48E+00 1.04E+01 4.69E+00 1.34E+01 1.34E+01 9.59E+00 1.27E+01 1.63E+01 4.26E+00 1.29E+01 5.02E+01 +/-3.99E+01 +/-1.98E+01 +/-2.76E+01 +/-5.85E+01 +/-3.08E+01 +/-3.68E+01 +/-3.58E+01 +/-2.89E+01 +/-3.04E+01 +/-2.39E+01 +/-3:53E+01 +/-2.18E+01 +/-3.77E+01 +/-1.71E+01 +/-1.17E+01 +/-1.23E+01 +/-1.39E+01 +/7 4.12E+01 +/-2.21E+01 +/-3.01E+01 +/-2.37E+01 +/-2.41E+01 +/-2.49E+01 *+/-3.25E+01 +/-2.04E+01 +/-4.90E+00 4.38E+00 1.13E+01 1.50E+01 1.40E+01 1.78E+01 1.OOE+01 1.40E+01 1.52E+01 1.56E+01 1.31E+01 1.26E+01 1.36E+01 4.27E+00 1.28E+01 1.16E+01 7.44E+00 1.02E+01 4.42E+00 1.32E+01 9.80E+00 9.50E+00 1.25E+01 1.58E+01 3.77E+00 1.27E+01 4.68E+01 +/-4.04E+01 +/-3.29E+01 +/-3.99E+01 +/-6.10E+01 +/-3.34E+01 +/-3.30E+01 +/-3.61E+01 +/-3.67E+01 +/-3.52E+01 +/-3.20E+01 +/-4.20E+01 +/-2.56E+01 +/-3.70E+01 +/-2.23E+01 +/-1.99E+01 +/-1.52E+01 +/-9.962+00 +/-5.17E+01 +/-1.95E+01 +/-2.53E+01 +/-2.33E+01 +/-2.45E+01 +/-3.28E+01 +/-3.25E+01 +/-2.63E+01 +/-4.75E+00 4.40E+00 1.16E+01 1.52E+01 1.43E+01 1.78E+01 9.84E+00 1.40E+01 1.54E+01 1.56E+01 1.32E+01 1.27E+01 1.36E+01 4.25E+00 1.29E+01 1.17E+01 7.53E+00 1.03E+01 4.96E+00 1.31E+01 9.70E+00 9.50E+00 1.25E+01 1.59E+01 3.78E+00 1.28E+01 5.29E+0 3.25E+0 2.99E+0 3.04E+0 5.53E+0 3.70E+1 3.65E+0 3.24E+0 2.89E+(2.96E+1 2.72E+0 3.78E+0 2.66E+0 4.12E+(1.29E+0 1.29E+0 2.27E+0 1.15E+(4.62E+0 2.36E+(2.96E+(2.93E+0 3.06E+0 3.25E+0 3.67E+0 3.49E+0 Station Station 23 24*01 +/- 4.95E+00 4.89E+01 +/-01 +/- 4.01E+00 3.82E+01 +/-01 +/- 1.16E+01 2.95E+01 +/-01 +/- 1.50E+01 2.85E+01 +/-01 +/- 1.39E+01 5.53E+01 +/-01 +/- 1.73E+01 2.68E+01 +/-01 +/- 1.02E+01 3.50E+01 +/-01 +/- 1.40E+01 2.83E+01 +/-01 +/- 1.49E+01 3.02E+01 +/-01 +/- 1.56E+01 2.37E+01 +/-01 +/- 1.31E+01 2.14E+01 +/-01 +/- 1.26E+01 3.06E+01 +/-01 +/- 1.38E+01 2.02E+01 +/-01 +/- 4.41E+00 3.90E+01 +/-01 +/- 1.28E+01 1.41E+01 +/-01 +/- 1.19E+01 1.37E+01 +/-01 +/- 7.58E+00 2.56E+01 +/-01 +/- 1.04E+01 1.78E+01 +/-01 +/- 4.72E+00 4.27E+01 +/-01 +/- 1.34E+01 2.32E+01 +/-01 +/- 9.53E+00 3.55E+01 +/-01 +/- 9.65E+00 2.41E+01 +/-01 +/- 1.29E+01 2.77E+01 +/-01 +/- 1.58E+01 3.30E+01 +/-01 +/- 3.95E+00 3.73E+01 +/-01 +/- 1.29E+01 2.66E+01 +/-I 4.88E+00 4.27E+00 1.17E+01 1.50E+01 1.40E+01 1.78E+01 9.79E+00 1.40E+01 1.52E+01 1.55E+01 1.30E+01 1.26E+01 1.35E+01 4.32E+00 1.28E+01 1.19E+01 7.67E+00 1.05E+01 4.56E+00 1.34E+01 9.71 E+00 9.51E+00 1.25E+01 1.62E+01 3.99E+00 1.28E+01 Sample lost during delivery by carrier.* Control Station 38 Table 3-3 Air Particulate Gross Beta Radioactivity
[10.3 pCi/m 3]page 3 of 4 Period Ending 07/08/08 07/16/08 07/23/08 07/30/08 08/05/08 08/12/08 08/19/08 08/26/08 09/02/08 09/09/08 09/16/08 09/23/08 09/30/08 1 0/07/08 10/14/08 10/22/08 10128/08 11/04/08 11/12/08 11/18/08 11/26/08 12/02/08 12/09/08 12/17/08 12/23/08 12/30/08 2.45E+01 3.23E+01 4.59E+01 4.20E+01 3.82E+01 3.68E+01 4.23E+01 3.17E+01 3.37E+01 3.37E+01 3.01E+01 4.64E+01 2.56E+01 4.89E+01 4.74E+01 3.48E+01 2.45E+01 5.28E+01 4.38E+01 2.31 E+01 1.92E+01 3.73E+01 4.13E+01 2.82E+01 4.90E+01 5.42E+01 01+/-+/-+/-+1-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-Station Station Station Station Station I olA I 02 I 03 I 04 I 1.39E+01 2.79E+01 +/- 1.39E+01 2.05E+01 +/- 1.39E+01 2.26E+01 +/- 1.39E+01 2.34E+01 +/- 1.39E+01 2.85E+01 1.09E+01 3.56E+01 +/- 1.10E+01 3.42E+01 +/- 1.12E+01 2.77E+01 +/- 1.11E+01 3.00E+01 +/- 1.11E+01 4.00E+01 1.39E+01 5.10E+01 +/- 1.39E+01 3.83E+01 +/- 1.33E+01 4.58E+01 +/- 1.34E+01 3.41E+01 +/- 1.34E+01 4.54E+01 1.31E+01 4.69E+01 +/- 1.32E+01 4.19E+01 +/- 1.35E+01 3.61E+01 +/- 1.35E+01 4.26E+01 +/- 1.34E+01 5.08E+01 1.63E+01 4.51E+01 +/- 1.62E+01 3.91E+01 +/- 1.57E+01 4.00E+01 +/- 1.57E+01 3.20E+01 +/- 1.56E+01 4.58E+01 1.30E201 4.47E+01 +/- 1.28E+01 3.21E+01 +/- 1.32E+01 4.03E+01 +/- 1.28E+01 3.21E+01 +/- 1.29E+01 4.09E+01 1.13E+01 5.64E+01 +/- 1.19E+01 4.92E+01 +/- 1.12E+01 4.09E+01 +/- 1.15E+01 4.48E+01 +/- 1.14E+01 5.48E+01 9.34E+00 3.97E+01 +/- 9.53E+00 3.73E+01 +/- 9.53E+00 3.95E+01 +/- 9.50E+00 2.90E+01 +/- 9.29E+00 3.59E+01 8.80E+00 6.83E+01 +/- 1.86E+01 2.80E+01 +/- 8.89E+00 3.18E+01 +/- 8.72E+00 3.37E+01 +/- 8.78E+00 2.90E+01 1.30E+01 3.29E+01 +/- 1.30E+01 3.44E+01 +/- 1.30E+01 3.37E+01 +/-1.23E+01 2.05E+01 +/- 1.20E+01 2.22E+01 +/- 1.21E+01 3.08E+01 +/-1.05E+01 4.11E+01 +/- 1.02E+01 2.06E+01 +/- 1.01E+01 3.23E+01 +/-1.11E+01 1.51E+01 +/- 1.14E+01 2.44E+01 +/- 1.10E+01 2.80E+01 +I-1.28E+01 4.38E+01 +/- 1.24E+01 2.62E+01 +/- 1.25E+01 3.19E+01 +/-1.16E+01 5.09E+01 +/- 1.19E+01 4.71E+01 +/- 1.19E+01 4.55E+01 +/-1.10E+01 4.09E+01 +/- 1.11E+01 3.82E+01 +/- 1.09E+01 3.94E+01 +/-1.54E+01 1.51E+01 +/- 1.53E+01 2.23E+01 +/- 1.57E+01 1.74E+01 +/-8.02E+00 5.19E+01 +/- 7.99E+00 4.66E+01 +/- 7.25E+00 4.69E+01 +/-7.84E+00 3.93E+01 +/- 7.82E+00 4.22E+01 +/- 8.11E+00 3.59E+01 +/-1.26E+01 1.71E+01 +/- 1.24E+01 1.81E+01 +/- 1.19E+01 2.31E+01 ÷/-1.02E+01 1.51E+01 +/- 9.93E+00 1.63E+01 +/- 1.01E+01 1.66E+01 ÷/-1.21E+01 3.10E+01 +/- 1.24E+01 2.94E+01 +/- 1.23E+01 2.71E+01 ÷/-1.11E+01 3.01E+01 +/- 1.10E+01 4.16E+01 +/- 1.13E+01 3.41E+01 +/-1.30E+01 3.62E+01 +/- 1.30E+01 4.74E+01 1.22E+01 2.38E+01 +/- 1.21E+01 2.02E+01 1.03E+01 3.88E+01 +/- 1.05E+01 3.79E+01 1.11E+01 1.77E+01 +/- 1.09E+01 2.37E+01 1.26E+01 4.26E+01 +/- 1.29E+01 4.67E+01 1.19E+01 3.84E+01 +/- 1.18E+01 4.42E+01 1.09E+01 3.84E+01 +/- 1.08E+01 4.16E+01 1.54E+01 2.10E+01 +/- 1.54E+01 1.56E+01 7.90E+00 5.38E+01 +/- 8.08E+00 7.24E+01 7.86E+00 3.40E+01 +/- 7.77E+00 4.57E+01 1.22E+01 1.82E+01 +/- 1.22E+01 2.25E+01 1.02E+01 1.86E+01 +/- 1.02E+01 1.69E+01 1.18E+01 3.93E+01 +/- 1.21E+01 3.28E+01 1.15E+01 4.05E+01 +/- 1.15E+01 4.23E+01 Station 1.39E+01 2.95E+01+/- 1.14E+01 1.51E+01+/- 1.35E+01 5.12E+01+/- 1.36E+01 3.50E+01+/- 1.58E+01 4.05E+01+/- 1.31E+01 3.87E+01+/- 1.15E+01 4.41E+01+/- 9.41E+00 3.03E+01+/- 8.65E+00 3.16E+01+/- 1.32E+01 3.37E+01+/- 1.21E+01 2.70E+01+/- 1.04E+01 3.94E+01+I- 1.10E+01 2.59E+01+/- 1.28E+01 3.54E+01+/- 1.18E+01 4.73E+01+/- 1.08E+01 3.41E+01+/- 1.54E+01 1.98E+01+/- 8.53E+00 5.66E+01+/- 8.12E+00 3.96E+01+/- 1.21E+01 1.90E+01+/- 1.02E+01 1.13E+01+/- 1.22E+01 4.74E+01+/- 1.13E+01 2.81E+01+/- 8.73E+00 2.65E+01+/- 1.11E+01 4.60E+01+/- 8.88E+00 4.92E+01+/- 11.4 32.4 Station 05A+/- 1.39E+01+/- 1.10E+01+/- 1.36E+01+/- 1.33E+01+/- 1.57E+01+/- 1.31 E+01+/- 1.13E+01+/- 9.31E+00+/- 8.76E+00+/- 1.30E+01+/- 1.22E+01+/- 1.04E+01+/- 1.10E+01+/- 1.27E+01+/- 1.19E+01+/- 1.08E+01+/- 1.55E+01+/- 8.11E+00+/- 7.96E+00+/- 1.21E+01+/- 1.01E+01+/- 1.24E+01+/- 1.11E+01+/- 8.90E+00+/- 1.13E+01+/- 8.82E+00+/- 11.4 I 8.90E+00 2.16E+01 +/- 8.52E+00 2.73E+01 +/- 8.62E+00 3.38E+01 +/- 8.75E+00 3.10E+01 +/- 8.87E+00 2.30E+01 1.13E+01 4.08E+01 +/- 1.14E+01 4.93E+01 +/- 1.14E+01 2.97E+01 +/- 1.10E+01 4.95E+01 +/- 1.13E+01 4.05E+01 9.08E+00 6.22E+01 +/- 9.31E+00 5.83E+01 +/- 8.96E+00 5.89E+01 +/- 9.12E+00 4.14E+01 +/- 8.64E+00 5.05E+01 Annual Mean 35.2 +/- 11.4 32.8 +/- 11.5 32.5 +/- 11.3 32.5 +/- 11.3 32.8 +/- 11.4 35.0 39 Table 3-3 Air Particulate page Gross Beta Radioactivity 4 of 4[10-3 pCi/mr Period Station Station Station Station Station Station Ending I 06 07 21 22 23 24.07108/08 3.38E+01 +/- 1.40E+01 2.51E+01 +/- 1.40E+01 2.59E+01 +/- 1.37E+01 2.47E+01 +/- 1.36E+01 3.14E+01 +/- 1.41E+01 2.76E+01 +/- 1.39E+01 07/16/08 2.75E+01 +/- 1.13E+01 3.33E+01 +/- 1.12E+01 2.67E+01 +/- 1.10E+01 3.53E+01 +I- 1.13E+01 3.57E+01 +/- 1.12E+01 2.60E+01 +/- 1.11E+01 07/23/08 5.02E+01 +/- 1.35E+01 4.97E+01 +/- 1.35E+01 4.70E+01 +/- 1.38E+01 5.03E+01 +/- 1.39E+01 5.27E+01 +/- 1.36E+01 3.81E+01 +/- 1.33E+01 07/30/08 3.41E+01 +/- 1.33E+01 4.12E+01 +/- 1.34E+01 4.08E+01 +/- 1.31E+01 4.75E+01 +/- 1.32E+01 4.12E+01 +/- 1.35E+01 3.09E+01 +/- 1.33E+01 08/05/08 4,94E+01 +/- 1.59E+01 3.40E+01 +/- 1.56E+01 3.57E+01 +/- 1.60E+01 4.43E+01 +/- 1.62E+01 4.76E+01 +/- 1.58E+01 3.41E+01 +/- 1.56E+01 08/12/08 3.80E+01 +/- 1.31E+01 2.99E+01 +/- 1.30E+01 3.32E+01 +/- 1.27E+01 4.10E+01 +/- 1.28E+01 4.27E+01 +/- 1.34E+01 3.70E+01 +/- 1.29E+01 08/19/08 4.89E+01 +/- 1.13E+01 4.64E+01 +/- 1.12E+01 4.64E+01 +/- 1.16E+01 4.43E+01 +/- 1.16E+01 6.07E+01 +/- 1.14E+01 2.99E+01 +/- 1.11E+01 08/26/08 4.52E+01 +/- 9.61E+00 2.13E+01 +/- 9.16E+00 2.67E+01 +/- 9.23E+00 3.98E+01 +/- 9.56E+00 2.75E+01 +/- 9.26E+00 3.03E+01 +/- 9.30E+00 09/02/08 2.54E+01 +/- 8.62E+00 2.94E+01 +/- 8.64E+00 2.74E+01 +/- 8.60E+00 3.05E+01 +/- 8.62E+00 3.40E+01 +/- 8.77E+00 2.48E+01 +/- 8.52E+00 09/09/08 3.60E+01 +/- 1.30E+01 3.23E+01 +/- 1.29E+01 3.61E+01 +/- 1.29E+01 4.89E+01 +/- 1.32E+01 2.95E+01 +/- 1.29E+01 3.31E+01 +/- 1.30E+01 09/16/08 2.59E+01 +/- 1.22E+01 2.53E+01 +/- 1.22E+01 1.72E+01 +/- 1.22E+01 2.50E+01 +/- 1.21E+01 2.64E+01 +/- 1.22E+01 2.69E+01 +/- 1.21E+01 09/23/08 2.84E+01 +/- 1.02E+01 3.87E+01 +/- 1.04E+01 3.64E+01 +/- 1.04E+01 3.41E+01 +/- 1.04E+01 2.98E+01 +/- 1.02E+01 3.91E+01 +/- 1.06E+01 09/30/08 2.35E+01 +/- 1.10E+01 1.80E+01 +/- 1.09E+01 2.45E+01 +/- 1,11E+01 2.39E+01 +/- 1.10E+01 1.57E+01 +/- 1.09E+01 2.89E+01 +/- 1.11E+01 10/07/08 4.95E+01 +/- 1.29E+01 4.20E+01 +/- 1.28E+01 4.28E+01 +/- 1.27E+01 3.54E+01 +/- 1.26E+01 3.96E+01 +/- 1.28E+01 4.29E+01 +/- 1.27E+01 10/14/08 5.46E+01 +/- 1.20E+01 4.86E+01 +/- 1.19E+01 3.83E+01 +/- 1.15E+01 4.58E+01 +/- 1.16E+01 5.10E+01 +/- 1.19E+01 5.17E+01 +/- 1.19E+01 10/22/08 3.42E+01 +/- 1.07E+01 4.11E+01 +/- 1.08E+01 3.04E+01 +/- 1.09E+01 3.92E+01 +/- 1.11E+01 4.15E+01 +/- 1.08E+01 3.64E+01 +/- 1.07E+01 10/28/08 1.84E+01 +/- 1.56E+01 1.72E+01 +/- 1.56E+01 1.82E+01 +/- 1.54E+01 1.61E+01 +/- 1.53E+01 2.07E+01 +/- 1.56E+01 1.91E+01 +/- 1.54E+01 11/04/08 3.73E+01 +/- 7.64E+00 6.13E+01 +/- 8.21E+00 4.04E+01 +/- 7.72E+00 5.01E+01 +/- 7.97E+00 5.28E+01 +/- 7.97E+00 5.45E+01 +/- 8.02E+00 11/12/08 3.78E+01 +/- 7.95E+00 3.38E+01 +/- 7.91E+00 4.03E+01 +/- 7.88E+00 4.60E+01 +/- 7.99E+00 2.67E+01 +/- 7.67E+00 3.83E+01 +/- 7.88E+00 11/18/08 1.54E+01 +/- 1.20E+01 1.82E+01 +/- 1.20E+01 2.07E+01 +/- 1.24E+01 1.47E+01 +/- 1.23E+01 2.12E+01 +/- 1.23E+01 2.14E+01 +/- 1.22E+01 11/26/08 2.51E+01 +/- 1.02E+01 1.34E+01 +/- 1.01E+01 7.94E+00 +/- 1.01E+01 1.57E+01 +/- 1.01E+01 1.02E+01 +/- 1.01E+01 1.09E+01 +/- 1.01E+01 12/02/08 4.56E+01 +/- 1.26E+01 4.84E+01 +/- 1.26E+01 4.86E+01 +/- 1.24E+01 5.54E+01 +/- 1.26E+01 4.64E+01 +/- 1.24E+01 3.95E+01 +/- 1.22E+01 12/09/08 3.60E+01 +/- 1.12E+01 2.66E+01 +/- 1.11E+01 3.89E+01 +/- 1.12E+01 2.53E+01 +/- 1.10E+01 3.36E+01 +/- 1.13E+01 3.11E+01 +/- 1.13E+01 12/17/08 2.20E+01 +/- 9.91E+00 3.46E+01 +/- 8.87E+00 1.79E+01 +/- 8.66E+00 3.09E+01 +/- 8.92E+00 3.82E+01 +/- 8.73E+00 3.58E+01 +/- 8.78E+00 12/23/08 .3.43E+01
+/- 1.10E+01 4.13E+01 +/- 1.12E+01 4.07E+01 +/- 1.12E+01 3.87E+01 +/- 1.11E+01 3.95E+01 +/- 1.12E+01 4.42E+01 +/- 1.13E+01 12/30/08 4.88E+01 +/- 8.76E+00 4.63E+01 +/- 8.70E+00 4.62E+01 +/- 8.79E+00 6.24E+01 +/- 9.14E+00 4.44E+01 +/- 8.72E+00 6.46E+01 +/- 9.14E+00 Annual 34.2 +/- 11.5 32.8 +/- 11.4 30.9 +/- 11.3 34.6 +/- 11.4 33.9 +/- 11.3 32.2 +/- 11.3 Mean Indicator 33.2 +/- 11.4 Mean* Control Station 40 Table 3-4 Airborne Iodine 1-131[10.3 pCi/m 3]page 1 of 4 Period Ending 01/02/08 01/09/08 01/16/08 01/23/08 01/30/08 02/05/08 02/13/08 02/20/08 02/27/08 03/04/08 03/11/08 03/18/08 03/25/08 04/01/08 04/08/08 04/15/08 04/22/08 04/29/08 No 05/06/08 05/13/08 05/20/08 05/27/08 06/04/08 06/10/08 06/18/08 06/25/08 07/01/08 Station 01" 1.19E+01" 1.21E+01" 1.32E+01" 1.05E+01" 1.27E+01" 8.74E+00" 8.92E+00< 9.45E+00" 9.61E+00" 9.81E+00" 1.57E+01" 9.05E+00< 8.68E+00< 1.25E+01< 9.68E+00< 8.73E+00< 1.11E+01 charcoal in sampler." 7.87E+00" 7.84E+00" 1.76E+01" 7.18E+00" 7.26E+00" 1.03E+01" 8.03E+00" 1.12E+01 Station S 01A< 1.18E+01< 9.60E+00*< 1.56E+01< 1.13E+01< 1.26E+01< 1.15E+01" 7.28E+00" 9.43E+00< 9.33E+00< 8.83E+00< 1.60E+01< 8.20E+00< 7.24E+00< 9.81 E+00< 8.01 E+00< 8.79E+00< 1.09E+01< 1.05E+01< 1.03E+01< 8.94E+00< 1.25E+01< 7.85E+00< 4.75E+00< 1.06E+01< 8.44E+00< 1.15E+01 Station 02< 8.13E+00< 1.01E+01< 1.41E+01< 8.29E+00< 7.81E+00< 1.16E+01< 1.18E+01< 9.83E+00< 8.26E+00< 1.02E+01< 1.12E+01< 6.79E+00" 8.03E+00< 1.07E+01< 9.10E+00< .1.26E+01< 8.79E+00< 9.76E+00< 1.07E+01" 7.49E+00< 1.51E+01< 6.51 E+00" 1.23E+01< 9.99E+00< 1.00E+01< 1.11E+01 Station Station 03I 04< 9.80E+00 < 1.41E+01" 1.OOE+01 < 7.95E+00< 1.55E+01 < 1.52E+01< 9.28E+00 < 1.11E+01< 1.16E+01 < 1.54E+01< 1.11E+01 < 9.51E+00< 1.14E+01 < 7.43E+00< 8.48E+00 < 6.94E+00" 7.39E+00 < 1.57E+01< 1.06E+01 < 1.60E+01" 1.30E+01 < 1.11E+01" 8.97E+00 < 8.00E+00" 8.71E+00 < 7.37E+00" 1.31E+01 < 9.76E+00< 9.72E+00 < 5.87E+00" 7.78E+00 < 8.50E+00< 1.10E+01 < 1.18E+01< 9.33E+00 < 8.97E+00< 8.71E+00 < 1.05E+01< 6.45E+00 < 1.61E+01< 1.41E+01 < 1.34E+01< 7.52E+00 < 9.47E+00< 7.14E+00 < 7.67E+00< 6.56E+00 6.95E+00 +/- 6.95E+00< 8.66E+00 < 1.82E+01< 1.09E+01 < 1.26E+01 Station 05< 9.40E+00< 7.34E+00< 1.78E+01< 1.10E+01< 1.37E+01< 1.33E+01< 1.23E+01< 7.04E+00< 1.19E+01< 1.18E+01< 1.11E+01< 3.75E+00< 5.48E+00< 1.21E+01" 8.30E+00" 5.83E+00" 1.07E+01< 6.74E+00" 1.08E+01< 9.94E+00< 1.25E+01< 6.12E+00< 8.07E+00< 4.93E+00< 8.94E+00< 9.60E+00 Station 05A< 1.07E+01" 1.31E+01" 2.07E+01" 1.33E+01< 8.82E+00< 9.25E+00< 9.93E+00< 1.03E+01< 1.40E+01< 1.i0E+01< 1.37E+01< 8.82E+00" 8.16E+00< 1.54E+01" 1.28E+01" 1.29E+01" 1.14E+01" 9.48E+00< 7.97E+00< 1.06E+01< 1.37E+01< 7.43E+00< 7.79E+00< 1.37E+01< 1.48E+01< 8.78E+00 J Sample lost during delivery by carrier.41 Table 3-4 Airborne Iodine 1-131[10-3 pCi/m 3]page 2 of 4 Period Ending 01/02/08 01/09/08 01/16/08 01/23/08 01/30/08 02/05/08 02/13/08 02/20/08 02/27/08 03/04/08 03/11/08 03/18/08 03/25/08 04101/08 04/08/08 04/15/08 04/22/08 04/29/08 05/06/08 05/13/08 05/20/08 05/27/08 06104/08 06/10/08 06/18/08 06/25/08 07/01/08 I-Station 06<C C<<C<<C<C<C C"C C C C C C C C C C C C C C 7.89E+00 1.04E+01 1.84E+01 8.07E+00 1.16E+01 7.18E+00 7.76E+00 1.60E+01 1.01E+01 1.52E+01 8.51 E+00 1.02E+01 7.09E+00 8.79E+00 1.07E+01 1.23E+01 6.90E+00 1.10E+01 7.90E+00 8.05E+00 1.54E+01 9.17E+00 6.OOE+00 1.17E+01 8.15E+00 1.08E+01 Station 07" 1.02E+01" 1.06E+01" 1.48E+01" 1.11E+01" 1.20E+01" 1.03E+01" 1.02E+01" 1.02E+01" 1.03E+01" 1.01E+01" 1.17E+01" 9.04E+00" 1.08E+01" 1.33E+01" 7.37E+00" 1.14E+01" 9.48E+00" 7.13E+00" 1.10E+01" 7.45E+00" 1.49E+01" 6.21 E+00" 6.67E+00" 1.15E+01" 1.36E+01" 1.09E+01 Station S I 21 I< 1.24E+01< 1.10E+01< 1.67E+01< 9.39E+00< 6.53E+00< 1.31E+01< 7.71 E+00< 1.49E+01< 8.36E+00< 1.54E+01< 9.13E+00 0 < 1.37E+01< 8.61 E+00< 6.32E+00 0 < 1.15E+01< 7.08E+00 0 < 7.63E+00 0 < 9.98E+00< 9.52E+00 0 < 8.80E+00< 1.63E+01 0 < 8.49E+00 0 < 8.38E+00< 6.87E+00< 1.18E+01< 9.08E+00 Sample lost during delivery by carrier.tation 22" 1.26E+01" 9.60E+00" 1.89E+01" 6.63E+00" 9.17E+00" 8.96E+00" 9.89E+00" 1.33E+01" 1.04E+01"C 1.08E+01" 1.75E+01" 1.14E+01" 7.16E+00" 9.85E+00" 8.30E+00" 1.10E+01" 9.39E+00" 1.07E+01" 1.41 E+01" 6.81 E+00" 1.67E+01" 1.23E+01" 5.79E+00" 1.15E+01" 1.02E+01" 1.22E+01 Station 23" 1.11E+01" 7.96E+00" 1.70E+01" 1.10E+01< 1.49E+01" 1.03E+01" 8.70E+00" 8.47E+00" 9.03E+00" 1.59E+01" 1.36E+01" 8.52E+00" 8.44E+00" 9.63E+00" 1.24E+01" 8.61 E+00" 1.28E+01" 9.52E+00" 1.25E+01" 1.04E+01" 1.37E+01" 9.46E+00" 1.04E+01" 6.57E+00" 9.69E+00" 1.18E+01 Station 24*" 9.16E+00" 1.10E+01" 2.03E+01" 1.18E+01" 1.18E+01" 1.OOE+01" 1.30E+01" 1.21E+01" 1.08E+01" 1.23E+01" 1.11E+01" 7.70E+00< -6.70E+00" 1.00E+01" 1.15E+01" 8.05E+00" 9.05E+00" 1.27E+01" 8.08E+00" 6.92E+00" 1.24E+01" 6.91 E+00" 5.98E+00" 1.09E+01" 1.17E+01" 1.24E+01 I* Control Station 42 Table 3-4 Airborne Iodine 1-131[10-3 pCi/m 3]page 3bf 4 Period Ending 07/08/08 07/16/08 07/23/08 07/30/08 08/05/08 08/12/08 08/19/08 08/26/08 09/02/08 09/09/08 09/16/08 09/23/08 09/30/08 10/07/08 10/14/08 10/22/08 10/28/08 11/04/08 11/12/08 11/18/08 11/26/08 12/02/08 12/09/08 12/17/08 12/23/08 12/30/08 Station 8.19E+00 9.01 E+00 1.28E+01 7.55E+00 1.61E+01 9.13E+00 8.56E+00 1.04E+01 1.35E+01 1.05E+01 1.11E+01 7.99E+00 9.17E+00 1.OOE+01 1.28E+01 9.80E+00 1.27E+01 8.67E+00 8.70E+00 8.62E+00 1.68E+01 1.08E+01 1.04E+01 7.11E+00 1.70E+01 7.80E+00 Station S 01A< 7.01 E+00" 1.06E+01" 1.08E+01" 6.27E+00" 1.41E+01" 7.53E+00" 1.12E+01" 1.19E+01" 1.82E+01" 1.21E+01< 9.51 E+00" 8.36E+00< 8.07E+00" 7.85E+00" 1.16E+01" 1.27E+01" 8.36E+00" 1.13E+01" 1.12E+01" 1.OOE+01" 9.27E+00" 1.34E+01-1.27E+01< 5.74E+00< 1.57E+01< 1.22E+01 Station I 0 02<<<<<<<S<<< 9< 9< 9< 8< 2< 7 7.35E+00 8.13E+00 8.42E+00 8.12E+00 1.13E+01 1.30E+01 8.97E+00 1.06E+01 1.12E+01 1.03E+01 7.97E+00 7.53E+00 7.93E+00 7.27E+00 1.06E+01 8.92E+00 1.20E+01 1.24E+01 1.29E+01 9.67E+00 7.99E+00 9.45E+00 9.97E+00 8.10E+00 2.02E+01 7.85E+00 Station 03<<C C n 7.56E+00 8.59E+00 1.13E+01 6.81 E+00 1.30E+01 7.07E+00 1.14E+01 1.06E+01 1.86E+01 1.21 E+01 9.19E+00 8.84E+00 8.82E+00 7.18E+00 1.24E+01 1.06E+01 1.09E+01 1.30E+01 9.47E+00 1.18E+01 1.53E+01 1.46E+01 8.34E+00 8.54E+00 2.11E+01 1.11E+01 Station 04" 1.26E+01" 6.66E+00" 1.56E+01" 9.44E+00" 1.75E+01" 1.04E+01< 9.94E+00" 9.75E+00" 9.69E+00" 9.26E+00" 9.76E+00" 7.29E+00" 8.46E+00" 6.80E+00" 9.73E+00" 7.77E+00" 1.20E+01" 1.32E+01" 9.16E+00" 1.25E+01< 1.1 7E+01" 9.13E+00" 8.88E+00" 6.49E+00" 1.70E+01" 8.96E+00 6.95 +/- 6.95 Station S1.14E+01" 7.43E+00" 1.12E+01" 7.63E+00" 1.33E+01" 8.13E+00" 7.46E+00" 1.11E+01" 1.87E+01" 9.98E+00" 8.86E+00" 8.93E+00" 1.19E+01" 7.58E+00" 1.15E+01" 1.02E+01" 1.21 E+01" 7.73E+00" 8.10E+00" 8.75E+00" 1.12E+01" 9.40E+00" 8.10E+00" 8.15E+00" 1.52E+01" 1.29E+01 Station S 05A< 9< 9<< 9< 1< 9< 8<<<< 8<<<.<<< 9< 9<3<3<9.83E+00 9.10E+00 1.11E+01 9.30E+00 1.02E+01 9.94E+00 8.53E+00 1.24E+01 1.61E+01 7.75E+00 9.20E+00 1.OOE+01 8.31E+00 7.70E+00 8.13E+00 7.79E+00 1.OOE+01 1.54E+01 1.02E+01 1.30E+01 1.08E+01 9.66E+00 9.88E+00 6.76E+00 2.20E+01.73E+00 Annual Mean 43 Table 3-4 Airborne Iodine 1-131[10-3 pCi/m 3]page 4 of 4 Period Endinq Station 06 I 07/08/08 07/16/08 07/23/08 07130/08 08/05/08 08/12/08 08/19/08 08/26/08 09/02/08 09/09/08 09/16/08 09/23/08 09/30/08 10/07/08 10/14/08 10/22/08 10/28/08 11/04/08 11/12/08 11/18/08 11/26/08 12/02/08 12/09/08 12/17/08 12/23/08 12/30/08 Annual Mean Indicator Mean< 7.64E+00< 1.38E+01" 1.09E+01" 6.99E+00" 1.34E+01" 9.88E+00" 7.95E+00" 1.05E+01< 1.21E+01" 8.10E+00" 8.90E+00" 8.44E+00" 9.12E+00" 9.71E+00" 1.14E+01" 7.61E+00" 1.35E+01" 8.37E+00" 7.78E+00" 1.17E+01" 9.80E+00" 9.75E+00" 1.08E+01< '6.56E+00" 1.70E+01" 1.09E+01 Station 07< 9< 1< 9<<< 9<<<< 9< 1< 6< 9<<< 9< 1< 8<<<< 8< 1< 8.81E+00 1.29E+01 9.63E+00 7.38E+01 1.69E+01 1.04E+01 9.34E+00 1.55E+01 1.68E+01 1.00E+01.81E+00 1.01E+01 6.38E+00 9.29E+00 8.92E+00.25E+01 9.94E+00 1.35E+01 8.69E+00 7.01E+00 1.57E+01 1.24E+01 1.29E+01 8.33E+00 1.71E+01 1.86E+00 Station< 8.13E+00< 1.28E+01 0 < 1.07E+01 0 < 6.96E+00< 1.52E+01< 9.65E+00< 1.08E+01< 1.17E+01< 1.23E+01< 6.20E+00< 8.31E+00< 1.01E+01< 1.13E+01< 8.86E+00< 9.70E+00< 7.92E+00< 1.37E+01< 1.24E+01< 8.85E+00< 8.89E+00< 1.29E+01< 1.00E+01< 1.04E+01< 7.18E+00< 1.74E+01< 1.12E+01 Station 22<<<<<<<<<<<<<<<.< .7.33E+00 8.89E+00 8.75E+00 7.00E+00 1.18E+01 1.07E+01 7.61E+00 1.20E+01 1.77E+01 1.06E+01 1.27E+01 8.89E+00 8.52E+00 1.05E+01 9.60E+00 1.08E+01 1.02E+01 1.44E+01 1.01E+01 9.85E+00 1.14E+01 9.99E+00 8.96E+00 5.84E+00 1.89E+01 6.71E+00 Station 23 Station I 24*I 7.93E+00 9.58E+00 7.28E+00 6.49E+00 1.24E+01 9.12E+00 7.83E+00 1.10E+01 1.13E+01 7.92E+00 8.74E+00 7.47E+00 7.45E+00 7.65E+00 8.75E+00 1.04E+01 1.32E+01 1.31E+01 1.06E+01 8.77E+00 1.14E+01 1.20E+01 1.11E+01 8.08E+00 1.24E+01 1.28E+01 1.15E+01 1.10E+01 9.04E+00 7.46E+00 1.24E+01 9.84E+00 7.96E+00 9.49E+00 1.48E+01 7.56E+00 8.52E+00 1.02E+01 6.69E+00 8.94E+00 1.04E+01 8.69E+00 1.35E+01 1.31E+01 9.00E+00 1.12E+01 9.33E+00 9.53E+00 9.00E+00 6.21E+00 1.84E+01 8.49E+00 6.95 +/- 6.95* Control Station 44 Table 3-5 Airborne Particulate Gamma Spectra[pCi/m 3] x 10-3 page 1 of 2 Sampling Location Quarter 1 I Be-7 I Cs-134* I Cs-137' I I I 01 01A 02 03 04 05 05A 06 07 21 22 23 24 2.37E+02 2.21E+02 2.19E+02 2.41E+02 2.24E+02 2.45E+02 2.46E+02 2.19E+02 2.53E+02 2.42E+02 2.16E+02 2.31E+02 2.54E+02+/-+/-+1-+1-+1-+1-+1-+1-+/-+/-+/-+/-+/-3.51E+01 3.11E+01 3.58E+01 3.40E+01 3.27E+01 3.24E+01 4.15E+01 3.08E+01 3.61E+01 3.41E+01 3.45E+01 3.17E+01 3.47E+01 C C 3.96E-01 3.73E-01 7.32E-01 6.06E-01 5.24E-01 3.08E-01 7.04E-01 4.58E-01 6.52E-01 5.62E-01 4.93E-01 4.25E-01 4.54E-01 C C C C C C 4.51E-01 3.21E-01 5.69E-01 4.82E-01 4.06E-01 3.93E-01 5.20E-01 3.21E-01 4.13E-01 3.60E-01 6.73E-01 3.39E-01 4.76E-01 Sampling Location Quarter 2 I Be-7 I Cs-134* .Cs-1 37* Sr-89 I Sr-90 I 01 01A 02 03 04 05 05A 06 07 21 22 23 24 1.47E+02 1.47E+02 1.52E+02 1.74E+02 1.70E+02 1.49E+02 1.44E+02 2.01E+02 1.68E+02 1.50E+02 1.48E+02 1.69E+02 1.56E+02+1-+1-+1-+1-+1-+1-+1-+1-~1*1-+1-+1-+1-2-36E+01 2.19E+01 2.27E+01 2.34E+01 2.36E+01 2.5 1E+01 2.20E+01 2.42E+01 2.23E+01 2.68E+01 2.20E+01 2.61 E+01 2.30E+01 C C C C 4.86E-01 5.32E-01 3.78E-01 2.81E-01 4.81 E-01 8.70E-01 4.57E-01 4.45E-01 4.08E-01 6.86E-01 6.11 E-01 5.80E-01 5.62E-01 C C C C C 5.31E-01 4.50E-01 4.33E-01 2.96E-01 4.69E-01 7.21E-01 3.84E-01 3.96E-01 4.32E-01 3.92E-01 4.56E-01 4.87E-01 4.54E-01 45 Table 3-5 Airborne Particulate Gamma Spectra[10-3 pCi/m 3]page 2 of 2 Sampling Location Quarter 3 I 01 01A 02 03 04 05 05A 06 07 21 22 23 24 1.49E+02 1.61E+02 1.37E+02 1.54E+02 1.39E+02 1.88E+02 1.28E+02 1.48E+02 1.58E+02 1.39E+02 1.55E+02 1.51E+02 1.48E+02 Be-7 I Cs-134"+/- 2.27E+01 < 5.22E-01+/- 2.45E+01 < 5.29E-01+/- 2.35E+01 < 6.55E-01+1- 2.99E+01 < 9.66E-01+/- 2.33E+01 < 6.50E-01+/- 2.71E+01 < 6.54E-01+/- 2.04E+01 < 5.58E-01+/- 2.34E+01 < 4.34E-01+1- 2.36E+01 < 6.66E-01+/- 2.20E+01 < 4.95E-01+1- 2.32E+01 < 3.66E-01+/- 2.40E+01 < 6.36E-01+1- 2.51E+01 < 8.11E-01 I Cs-137"< 4.20E-01< 3.56E-01" 4.66E-01" 7.45E-01" 4.16E-01" 5.08E-01" 4.63E-01" 4.81E-01" 3.88E-01+ 4.35E-01" 4.91E-01" 4.02E-01" 6.94E-01 I I I Sampling Location Quarter 4 I B -01 01A 02 03 05 05A 06 07 21 22 23 24*1.38E+02 1.07E+02 1.30E+02 1.05E+02 1.26E+02 1.17E+02 1.12E+02 1.14E+02 1.21E+02 1.07E+02 1.18E+02 1.19E+02 1.18E+02+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-2.02E+0 1.81E+0 1.95E+0 1.71E+0 1.80E+0 1.96E+0 1.72E+0 1.87E+0 1.81E+0 1.88E+0 1.66E+0 1.85E+0 1.94E+0 I Cs-134"" 1 < T.00E-01 I < 5.21E-01 1 < 6.21E-01 I < 5.28E-01 1 < 5.33E-01 1 < 7.43E-01 1 < 4.53E-01 1 < 5.08E-01 1 < 3.85E-01 1 < 7.37E-01 1 < 3.46E-01 1 < 5.17E-01 1 < 5.88E-01 I Cs-137"< 4.85E-01" 3.40E-01" 2.93E-01" 3,87E-01" 3.55E-01" 4.62E-01" 3.63E-01" 3.92E-01" 3.09E-01" 4.69E-01" 3.72E-01" 5.23E-01" 4.16E-01 Be-7 Mean 1.68E+02 +/- 2.54E+01 1.59E+02 +/- 2.39E+01 1.60E+02 +1- 2.54E+01 1.69E+02 +/- 2.61E+01 1.65E+02 +/- 2.44E+01 1.75E+02 +/- 2.61E+01 1.58E+02 +/- 2.53E+01 1.71E+02 +/- 2.43E+01 1.75E+02 +/- 2.50E+01 1.60E+02 +/- 2.54E+01 1.59E+02 +1- 2.41E+01 1.68E+02 +/- 2.51E+01 1.69E+02 +1- 2.56E+01 I Indicator 1.65E+02 +/- 6.13E+00*Control Station 46 Table 3-6 Soil[pCi/kg]SrB- I K-40 I Cs-i 34 page 1 of 1 S=an I i .....I Cý-l 37' I AcTh-228 I 01 02 03 04 05S 05A 06 07 21 22 23 24*Soil samples collected triennially.
Last collected 2007. Next samples due 2010.Annual Mean Indicator Mean*Control Station 47 Table 3-7 Precipitation Gross Beta[pCi/L]page 1 of 2 Sampling Date 01/30/08 1.70E+01 02/27/08 2.25E+00 03/25/08 04/29/08 3.16E+02 05/27/08 06/25/08 4.57E+00 07/30/08 4.69E+00 08/28/08 09/30/08 10/28/08 4.31E+00 11/26/08 12/30/08 6.78E+00 Mean 5.08E+01* LLD identified in ODCM Gross Beta+/-1.96E+00 9.30E-01 1.11E+00 7.94E+01 3.46E+00 2.36E+00 8.52E-01 2.30E+00 2.25E+00 2.48E+00 3.48E+00 2.23E+00 8.57E+00 I Rainfall (inches)* 2.41 1.65 3.28 5.85 5.55 4.54 3.69 1.30 7.22 0.94 2.17 5.46 44.06 I Total 48 Table 3-7 Precipitation Gamma Spectra[pCi/L]page 2 of 2 Sampling Location I Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 01A +/-/Nb-95 Cs-134 Cs-137 Ba-140 La-140 " 01 A +/- +1- +/- +/- +/- +/-12/30/2008 Sampling Location n Mn-54 I Fe-59 I Co-58 I Co-60 I Zn-65 Zr-95 01A 2.01E+00 < 4.53E+00 2.03E+00 < 2.49E+00 3.84E+00 3.41E+00 01A Mean I Nb-95 I Cs-I 34 Cs-i 37 Ba-i 40 I La-i 40 I I<2.36E+00<2.53E+00<2.25E+00<9.99E+00 La-140 3.87E+0049 Table 3-8 Milk Gamma Spectra[pCi/L Sampling Station 12 Date K-40 Sr-89 Sr-90 I -131 I Cs-134 I Cs-137 I Ba-140 I La-140I 01117108 1.44E+03 +-- 1.10E+02 [a) [a) < 9.07E-01 + 3.34E+00 < 2.84E+00 < 140E+01 < 3.90E+00 02/13/08 1.41E+03 +I- 1.21E+02 [a] [a] < 6.98E-01 + 2.40E+00 < 2.30E+00 < 9.21E+00 + 2.93E+00 03/11108 1.35E+03 +I- 9.84E+01 + 5.97E-01 < 6.34E-01 < 7.25E-01 < 2.10E+00 < 2.02E+00 < 9.43E+00 < 2.60E+00 04/15109 1.32E+03 +I- 1.16E+02 [a] [a] < 6.48E-01 C 2.67E+00 < 2.44E+00 < 1.17E+01 < 2.83E+00 05/13/08 1.45E+03 +I- 1.02E+02 [a] [a] + 4.48E-01 < 1.99E+00 < 1.85E+00 < 8.57E+00 < 2.85E+00 06/10/08 1.33E+03 +/- 1,00E+02 < 3.69E-01 < 3.16E-01 + 7.34E-01 < 2.69E+00 < 2.49E+00 < 1.22E+01 < 4.06E+00 07/16108 1.37E+03 +I- 1.22E+02 [a] [a] 5 5.46E-01 < 2.48E+00 < 2.41E+00 < 1.05E+01 + 3.38E+00 08/12/08 1.47E+03 +I- 1.29E+02 [a[ [a) + 5.90E-01 < 3.42E+00 < 3.34E+00 < 1.49E+01 < 4+79E+00 09/16/08 1.40E+03 +/- 1.21E+02 < 4.22E-01 < 4.88E-01 c 8.36E-01 < 2.76E+00 -C 2.52E+00 < 1.48E+01 < 4.19E+00 10114108 1.38E+03 +/- 1.04E+02 [a] [a] < 7.32E-01 + 2.89E+00 + 2.42E+00 < 1.29E+01 < 4.19E+00 11/12/08 1.43E+03 +I- 1.30E+02 [a] [a] + 8.65E-01 + 3.02E+00 < 2.56E+00 < 1.24E+01 < 3.43E+00 12/09/08 1.51E+03 +/- 1.15E+02 + 1.02E+00 < 1.20E+00 < 6.59E-01 < 2.42E+00 < 2.20E+00 < 1.01E+01 < 3.66E+00 Mean 1.41E+03 +/- 1.14E+02 Sampling Station 13 Date I K-40 I Sr-89 Sr-O I 1-131 I Cs-134 I Cs-13" I 8a-140 I La-140o page 1 of 1 01/17/08 02/13/08 03/11/08 04/1 5108 05/13/08 06110/08 07/16108 08612/08 09/16/08 10/14/08 11/12/08 12/09/08 1.34E+03 +/-1.26E+03 +-1.46E+03 +/-1.46E+03 +/-1.47E+03 +/-1.29E+03 +/-1.39E+03 +/-1.32E+03 +/-1.31E+03 +/-1.33E+03 +1-1.26E+03 +1-1.55E+03 +1-9.66E+01 1.38E+02 1.310E+02 1.08E+02 1.03E+02 9.06E+01 1.05E+02 1.11E+02 1.10E+02 1.22E+02 9.50E+01 1.26E+02[a][a]6.82E-01[a][a]2 4.15E-01[a][a]< 2.46E-01[a][a]< 7.486-01[a][a]< 5.24E-01[a][a]< 4.80E-01[a][a]< 9.60E-01[a][a]< 1.06E+00 9.81E-01 8.42E-01 8.74E-01 7.95E-01 4.65E-01 1.07E+00 6.29E-01 7.05E-01 8.80E-01 7.68E-01 7.93E-01 5.89E-01< 2.38E+00< 2.62E+00< 3.14E+00< 2.98E+00< 1.98E+00< 2.OOE+00< 2.89E+00< 3.29E+00< 2.40E+00" 3.23E+00" 2.75E+00+ 3.65E+00 2.27E+00 2.57E+00 2.99E+00 2.88E+00 1.730+00 1.86E+00 2.59E+00 2.89E+00 2.17E+00 2.97E+00 2.21E+00 3.14E+00" 9.62E+900" 9.96E+00" 1.38E+01" 1.26E+01" 8.01E+00 9.67E+00 C 1.11E+01< 1.35E+01< 1.400+01< 1.68E+01< 1.10E+01< 4.91 E+00<3.24E+00* 3.12E+00* 4.55E+00* 3.81 E+00+ 2.54E+00< 3.10E+00< 3.61E+00+ 4.39E+00+ 3.99E+00* 5.50E+00* 3.38E+00* 4.91 E+00 Mean 1.37E+03 +1- 1.11E+02[ndicator 1.39E+03 +/ 1.13E+02 Mean LLD denSfiled in ODCM[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.50 Table 3-9 Food and Vegetation Gamma Spectra[pCi/kg]page 1 of 2 Sampling Sampling Location Date I Be-7 I K-40 -131!. Cs-134" I s-137" 14 05/20/08 9.81E+02 +I- 1.28E+02 3.36E+03 +I- 3.16E+02 < 1.62E+01 < 9.53E+00 < 8.87E+00 06/17/08 6.30E+02 +I- 1.28E+02 2.85E+03 +I- 3.19E+02 < 2.24E+01 < 1.44E+01 < 1.32E+01 07/23/08 2.20E+03 +I- 2.28E+02 2.91E+03 +/- 3.76E+02 < 2.28E+01 < 1.62E+01 < 1.37E+01 08119/08 9.13E+02 +/- 1.31E+02 4.02E+03 +/- 4.12E+02 < 1.95E+01 < 1.64E+01 < 1.44E+01 09/23/08 7.37E+02 +/- 1.30E+02 3.85E+03 +/- 3.90E+02 < 1.85E+01 < 1.91E+01 < 1.49E+01 10122108 2.06E+03 +/- 1.97E+02 4.27E+03 +/- 3.55E+02 < 5.32E+01 < 1.37E+01 < 1.06E+01 Mean 1.25E+03 +/- 1.57E+02 3.54E+03 +/- 3.61E+02 Sampling Sampling Location Date I Be-7 I K-40 I -131 I Cs-134 I Cs-137 14a 10/22108 2.09E+03 +/- 2.32E+02 3.37E+03 +/- 3.86E+02 < 7.59E+01 < 1.76E+01 < 1.41E+01 Mean 2.09E+03 +/- 2.32E+02 3.37E+03 +/- 3.86E+02 Sampling Sampling Location Date Be-7 I K-40 1-131" Cs-134" Cs-137" 15 05/20/08 1.18E+03 +/- 1.30E+02 3.52E+03 +/- 3.27E+02 < 1.84E+01 < 1.04E+01 < 1.05E+01 06/17/08 6.46E+02 +/- 1.44E+02 6.85E+03 +/- 5.62E+02 < 2.20E+01 < 1.11E+01 < 1.24E+01 07/23/08 1.30E+03 +/- 1.63E+02 3.87E+03 +/- 3.96E+02 < 2.11E+01 < 1.65E+01 < 1.38E+01 08/19/08 1.11E+03 +/- 1.80E+02 4.48E+03 +/- 4.72E+02 <. 2.16E+01 < 1.82E+01 < 1.59E+01 09/23/08 6.74E+02 +/- 1.31E+02 7.41E+03 +/- 6.20E+02 < 2.06E+01 < 1.97E+01 < 1.58E+01 10/22/08 7.02E+02 +/- 1.05E+02 4.09E+03 +/- 3.51E+02 < 4.81E+01 < 1.27E+01 < 9.37E+00 Mean 9.35E+02 +/- 1.42E+02 5.04E+03 +/- 4.55E+02 Sampling Sampling Location Date Be-7 I K-40 1-131 I Cs-134 Cs-137" 16" 05/20108 6.27E+02 +/- 9.09E+01 4.31E+03 +/- 3.58E+02 < 1.65E+01 < 8.57E+00 < 7.54E+00 06/17/08 07/23/08 08/19/08 09/23/08 10/22/08 6.11E+02 7.23E+02 9.41 E+02 3.44E+02 1.25E+03+/-+1-+1."+/-+/-1.14E+02 9.93E+01 1.29E+02 9.14E+01 1.33E+02 4.33E+03 3.72E+03 4.77E+03 6.60E+03 5.11E+03+/-+/-+/-+i-+i-4.84E+02 3.25E+02 4.14E+02 5.18E+02 3.81E+02 2.43E+01 1.56E+01 1.92E+01 1.48E+01 4.50E+01" 1.64E+01< 1.19E+01" 1.49E+01" 1.36E+01" 1.13E+01" 1.36E+01" 1.11E+01" 1.42E+01" 1.16E+01" 9.37E+00 Mean. 7.49E+02 +/- 1.10E+02 4.81E+03 +/- 4.13E+02 LLD identified in ODCM** Control Station.51 Table 3-9 Food and Vegetation Gamma Spectra-[pCi/kg]page 2 of 2 Sampling Sampling Location Date I Be-7 K-40 f-131' Cs-1"34* Cs-I"3" 23 05/20/08 4.42E+02 +/- 1.33E+02 3.78E+03 +/- 3.54E+02 < 2.28E+01 < 1.51E+01 < 1.32E+01 06/17/08 6.70E+02 +I- 1.37E+02 2.94E+03 +/- 3.66E+02 < 2.54E+01 < 2.09E+01 < 1.60E+01 07/23/08 -1.46E+03 +/- 1.90E+02 2.91E+03 +/- 3.75E+02 < 2.51E+01 < 2.28E+01 < 1.67E+01 08119108 1.80E+03 +/- 2.23E+02 4.50E+03 +/- 4.73E+02 < 2.48E+01 < 2.68E+01 < 1.84E+01 09/23/08 7.44E+02 +/- 1.41E+02 5.76E+03 +1- 4.97E+02 < 1.62E+01 < 1.81E+01 < 1.21E+01 10122108 1.42E+03 +/- 1.35E+02 3.091+03 +1- 2.66E+02 < 4.58E+01 < 1.46E+01 < 9.59E+00 Mean 1.09E+03 +/- 1.60E+02 3.83E+03 +I- 3.89E+02 Sampling Sampling Location Date I Be-7 K-40 1-131" Cs-134" Cs-137i 26 05/20/08 1.07E+03 +/- 1.44E+02 3.34E+03 +/- 3.14E+02 < 2.35E+01 < 1.15E+01 < 1.09E+01 06/17/08 8.76E+02 +/- 1.87E+02 07/23/08 1.45E+03 1/- i.99E+02 08/19/08 1.31E+03 +/- 2.27E+02 09/23/08 9.81E+02 +/- i.17E+02 10/22/08 4.12E+02 +/- 9.64E+01 Mean 1.02E+03 +/- 1.62E+02 Mean Indicator 1.11E+03 +/- 1.58E+02 Control 7.49E+02 +/- 1.10E+02 3.14E+03 +/- 3.78E+02 3.08E+03 +/- 3.82E+02 4.96E+03 +/- 6.00E+02 2.88E+03 +/- 2.94E+02 2.07E+03 +/- 2.28E+02 3.25E+03 +/- 3.66E+02 3.89E+03 +/- 3.92E+02 4.81E+03 +/- 4.13E+02" 2.76E+01" 2.55E+01" 3.02E+01" 1.28E+01" 5.50E+01" 2.25E+01" 1.79E+01" 2.50E+01" 1.28E+01 1.31E+01" 2.00E+01< 1.75E+01" 2.07E+01" 1.02E+01< 1.05E+01* LLD identified in ODCM 52 Table 3-10 Well Water Gamma Spectra, Strontium, and Tritium[pCi/L]page 1 of 1 L Sampling Date I 03/25/08 06/25/08 09/29/08 12/30/08 H-3 S 3.13E+02" 4.55E+02" 4.75E+02" 4.26E+02 Mn-54" 2.07E+0(< 1.43E+0(< 2.43E+0(< 2.82E+O(I Fe-59 0 < 4.13E+0() < 3.22E+O(0 < 4.82E+0(0 < 6.20E+0(I Co-58 0 < 2.12E+0(0 < 1.58E+0(< 2.43E+O(< 2.77E+0(I Co-60 0 < 2.OOE+O() < 1.43E+OC) < 2.66E+OC) < 2.94E+OC Zn-65< 4.30E+00< 3.29E+.00< 5.1811+00< 5.91 E+00 Sr-89 I[a]< 1.36E+00[a][a]Station 01A I Sr-90 I[a]< 9.87E-01[a][a]Mean Sampling Date 03/25/08 06/25/08 09/29/08 12/30/08 Zr-95" 3.64E+00" 2.74E+00< 4.32E+00< 5.08E+00" 2.39E+0(" 1 .82E+0(" 3.25E+0(" 3.35E+0(I 1-131< 7.08E-01< 8.78E-01< 7.35E-01) < 7.35E-01 Cs-134" 2.21E+00" 1 69E+00" 2.87E+00" 3.53E+00 Cs-137 I Ba-140" 2.18E+00 < 9.74E+00" 1.52E+00 < 9.93E+00" 2.68E+00 < 1 .29E+01" 3.05E+00 < 1 .43E+01 La-140* 3.71 E+00< 3.51 E+00< 4.31 E+00* 5.16E+00 I Mean[a] Sr-89/90 analyses performed on the second quarter sample.53 Table 3-11 River Water Gamma Spectra, Strontium, and Tritium[pCi/L]Station 11 H-3 Mn-54 Fe-59 I Co-58 I Co-60 I Zn-65 Sr-89 Sr-90 page 1 of 1 Sampling Date I 01114108 02/14/08 03/11/08 04/15/08 05/13/08 06/11/08 07/15/08 08/12/08 09/16/08 10/14/08 11/12/08 12/16/08[a][a]3.89E+03 +/- 5.06E+02[a][a]2.85E+03 +/- 4.42E+02[a][a]3.81E+03 +/- 2.91E+02[a][a]4.10E+03 +/- 5.39E+02 1.52E+00 1.86E+00 1.75E+00 1.81E+00 1.99E+00 1.74E+00 1.64E+00 1.71E+00 1.95E+00 1.24E+00 1.61 E+00 1.35E+00 3.32E+00 3.68E+00 3.57E+00 3.49E+00 4.07E+00 3.65E+00 3.36E+00 3.53E+00 4-65E+00 2.76E+00 3.43E+00 2.97E+00 1.57E+00 1.57E+00 1.75E+00 1.60E+00 1.99E+00 1.81E+00 1.84E+00 1.71E+00 2.03E+00 1.28E+00 1.63E+00 1.26E+00 1.62E+00 2.16E+00 1.93E+00 2.02E+00ý2.23E+00 2.06E+00 1.72E+00 2.14E+00 2.11E+00 1.27E+00 1.62E+00 1.39E+00 3.13E+00 3.72E+00 3.54E+00 3.42E+00 4.04E+00 3.55E+00 3.31E+00 3.43E+00 4.21E+00 2.74E+00 3.50E+00 2.85E+00 Mean 3.66E+03 +/- 4.45E+02 Sampling Date Zr-95 I 01/14/08 02/14/08 03/11/08 04/15/08 05/13/08 06/11/08 07/15/08 08/12/08 09/16/08 10/14/08 11/12/08 12/16/08 2.75E+00 3.17E+00 3.22E+00 2.87E+00 3.43E+00 3.04E+00 3.13E+00 2.95E+00 3.47E+00 2.30E+00 2.93E+00 2.37E+00 Nb-95" 1.70E+00" 2.11E+00" 2.01E+00" 1.85E+00< 2.09E+00" 1.84E+00< 1.97E+00" 1.75E+00" 2.45E+00" 1.58E+00" 1.72E+00" 1.60E+00 1-131 I 9.67E-01 9.08E-01 9.09E-01 9.26E-01 5.09E-01 7.81E-01 4.53E-01 6.17E-01 4.84E-01 8.06E-01 6.98E-01 4.64E-01 Cs-1 34< 1.62E+00" 2.11E+00" 1.97E+00" 1.75E+00" 2.38E+00" 1.91E+00" 1.97E+00" 1.80E+00" 2.16E+00" 1.55E+00" 1.76E+00" 1.69E+00 I Cs-137< 1.66E+00" 1.78E+00" 1.85E+00" 1.86E+00" 2.22E+00" 1.82E+00" 1.99E+00" 2.09E+00" 2.20E+00" 1.38E+00< 1.61E+00" 1.47E+00 I Ba-140" 8.03E+00" 8.02E+00" 8.82E+00< 8.86E+00" 7.73E+00" 8.80E+00" 8,57E+00" 8.45E+00" 1.26E+01" 7.90E+00" 7.90E+00" 7.77E+00 I La-140" 2.45E+00" 2.59E+00" 3.38E+00" 3.42E+00" 2.79E+00" 2.89E+00" 2.84E+00" 2.72E+00" 4.69E+00" 2.41 E+00" 3.05E+00" 2.85E+00 I Mean* LLD identified in ODCM[a] Tritium analyses on quarterly composite.
54 ilýTable 3-12 Surface Water Gamma Spectra, Strontium, Tritium[pCi/L]page 1 of 2 Sampling Date 01/14/08 02/14/08 03/11/08 04/15/08 05/13/08 06/11/08 07/15/08 08/12/08 09/16/08 10/14/08 11/12/08 12/16108 H-3*[a]3.58E+03 +/- 4.95E+02[a][a]2.73+E03 +/- 4.32E+02[a][a]3.888+03 +- 2.028+02[a][a]4.14E+03 +/- 5.52E+02 Mean 3.581+03 +/- 4.44E+02 Mn-54*I Nb-95-1.52E+00 2.03E+00 1.79E+00 1.775÷00 1.62E+00 1.79E+00 1.71E+00 2.00E+00 1.99E+00 1.63E+00 1.57E+00 1.27E+00 Fý59*3.73E+00 4.23E+00 3+65E+00 3.48E+00 3.26E+00 4.02E+00 3.25E+00 4.10E+00 4.65E+00 3.52E+00 3.08E+00 2.78E+00 CO-58*1.69E+00 2,05E+00 1.81E÷00 1.69E+00 1.43E+00 1.71E+00 1.73E+00 2.02E+00 2.07E+00 1.64E+00 1.55E+00 1.41E+00 Co-60*1.79E+00 2.14E+00 1.96E+00 1.72E+00 1.62E+00 2.02E+00 1.76E+00 2.17E+00 2.10E+00 1.80E+00 1.69E8+00 1.39E+00 Zn-65*3.355+00 4.04E+00 3.375+00 3.25E+00 3.361+00 3.99E+00 3.24E+00 3.91E+00 4.62E+00 3.13E+00 3.05E+00 2.70E+00 Sr-89[a][a][a][a][a][a][a][a][a][a][a]Station 08 Sr-90[a][a][a][a][a][a][a][a][a][a][a][a]Sampling Datea 01114/08 02/14/08 03/11/08 04/15/08 05/13/08 06/11/08 07/15/08 08/12/08 09/16/08 10114/08 11/12/08 12/16/08 Zr-85*2.77E+00 3.39E+00 3.11E+00 3.04E+00 2.79E+00 3.24E+00 2.70E+00 3.37E+00 3.92E+00 2.83E+00 2.82E+00 2.35E+00 1.875+00 2.10E+00 1.92E+00 2.03E+00 1.70E+00 1.85E+00 1.86E+00 2.15E+00 2.40E+00 1.78E+00 1.93E+00 1.54E+00 1,05E+00 7.63E-01 8.861-01 5.18E-01 4.45E-01 5,63E-01 6.815-01 4.46E-01 4.601-0g1 7.98E-01 7.40E-01 9.47E-01 Cs-134*1.86E+00 2.03E+00 1.89E+00 1.83E+00 1.78E+00 1.98E+00 1.86E+00 2.04E+00 2.33E+00 1.84E+00 2.08E+00 1.70E+00 Cs-137" 1< 1< 1< 1< 1< 1< 1< 2< 2< 2< 1< 1.75E+00.09E+00.79E+00 1.748+00 1.67E+00 1.805+00.74E+00 2.18E+00.27E+00 2.17E+00.61E+00.33E+00 Ba-140<<<<<<<<8.71E+00 8.71E+00 8,22E+00 8.19E+00 6.58E+00 8.89E+00 7.81E+00 9.11E+00 1.28E+01 9.52E+00 7.97E+00 7.59E+00 La-140*I 3.27E+00 2.94E+00 2.82E+00 2.84E+00 2.08E+00 3.155+00 2.37E+00 3.291+00 4.13E+00 3.82E+00 2.94E+00 2.79E+00 Mean* LLD identified in ODCM[a] Tritium analyses on quarterly composite.
55 Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium[pCi/L]a page 2 of 2 Sampling Date 01/14/08 02/14/08 03/11/08 04/15/08 05/13/08 06/11/08 07/15/08 08/12/08 09/16/08 10/14/08 11/12/08 12/16/08 Station 09A**Sr-90 H-3* I Mn-54*[a] < 1.29&+00[a] < 1.67E+00< 4.82E+02 < 1.50E+00[a) < 1.66E+00[a] < < 1.40E+00< 4.59E+02 < 2.31E+00[a] < 1.82E+00[a] < 2.03E+00< 8.61E+01 < 1.84E+00[a] < 1.45E+00[a] < 1.81E+00< 2.82E+02 < 1.47E+00 S Fe-59*" 2.77E+00" 3.38E+00" 3.12E+00" 3.57E+00" 2.72E+00" 4.86E+00" 3.97E+00" 4.14E+00" 3.88E+00" 3.07E+00" 3.93E+00" 3.15E+00 Co-58*<<<<<< 2< 1< 2< 2 1.20E+00 1.71E+00 1.45E+00 1.71 E+0 1.45E+00 2.40E+00 1.83E+00 2.00E+00 2.09E+00 1.54E+00 1.68E+00 1.50E+00 0 <~0 <~0 <~0 <~0 <~0 <~0 <~1.31 E+00 1.75E+00 1.69E+00 1.88E+00 1.77E+00 2.736+00 1.99E+00 2.26E+00 2.14E+00 1.55E+00 1.85E+00 1.53E+00 Zn-65*" 2.55E+00" 3.44E+00" 3.34E+00" 3.34E+00" 3.07E+00" 5.08E+00" 3.67E+00" 4.23E+00" 3.66E+00" 3.15E+00" 3.44E+00" 3.09E+00 Sr-89 I v Mean Sampling Date I 01/14/08 02/14/08 03/11/08 04/15/08 05/13/08 06/11108 07/15/08 08/12/08 09/16/08 10/14/08 11/12/08 12/16/08 Mean Zr-95* Nb-95*"'2.11E+00
< 1.32E+00" 2.83E+00 < 1.59E+00" 2.80E+00 < 1.69E+00" 3.12E+00 < 1.95E+00" 2.54E+00 < 1.45E+00" 4.59E+00 < 2.65E+00< 3.08E+00 < 2.19E+00" 3.37E+00 < 2.25E+00" 3.71E+00 < 2.16E+00" 2.62E+00 < 1.43E+00" 3.18E+00 < 1.88E+00" 2.60E+00 < 1.69E+00 7.42E-01 9.12E-01 9.20E-01 7.52E-01 3.18E-01 5.35E-01 6.10E-01 4.70E-01 6.98E-01 7.87E-01 5.02E-01 6.01E-01 Cs°134"" 1.39E+00" 1.96E+00< 1.59E+00< 1.83E+00< 1.68E+00" 2.73E+00" 2.28E+00" 2.22E+00" 2.08E+00" 1.85E+00" 2.12E+00" 1.82E+00 7Cs-137"" 1.28E+00" 1.82E+00" 1.53E+00< 1.74E+00" 1.49E+00" 2.58E+00" 2.14E+00" 2.17E+00" 1.94E+00" 1.45E+00" 2.03E+00" 1.54E+00 Ba-140*" 6.33E+00" 7.17E+00" 7.46E+00" 9.18E+00" 6.02E+00" 1.19E+01" 8.36E+00" 9.58E+00" 1.13E+01" 8.59E+00" 9.16E+00" 8.49E+00 S La-140*" 2.45E+00" 2.47E+00" 2.30E+00" 3.01E+00" .2.22E+00" 4.06E+00" 3.32E+00" 3.26E+00" 3.82E+00" 3.19E+00" 3.11E+00" 2.50E+00 I+/- 3.12E+00+/- 1.38E+00 LLD identified in ODCM** Control Location[a] Tritium analyses on quarterly composite.
56 Table 3-13 Sediment Silt Gamma Spectra, and Strontium[pCi/Kg]page 1 of 1 Sample Date I Sr-89 Sr-90 I K-40 I Cs-134 I Cs-137" 03/11/2008 Station 08 [a] [a] 7.22E+03 +/- 7.39E+02 < 2.83E+01 < 1.97E+01 Station 09A** [a] [a] 8.11E+03 +/- 7.40E+02 < 1.98E+01 < 2.00E+01 Station 11 [a] [a] 1.12E+04 +/- 8.46E+02 < 2.60E+01 2.12E+01 +/- 1.54E+01 Sample Date I Sr-89 I Sr-90 K-40 Cs-134 I Cs-137*10/20/2008 Station 08 < 3.16E+02 < 9.11E+02 4.69E+03 +/- 9.53E+02 < 9.63E+01 < 5.72E+01 Station09A**
< 3.93E+02 < 7.12E+02 1.28E+04 +/- 2.01E+03 < 1.28E+02 1.20E+02 +/- 6.34E+01 Station 11 < 3.70E+02 < -1.13E+03 1.81E+04 +/- 2.35E+03 < 1.10E+02 < 6.97E+01 Mean I Sr-89 Sr-90 I K-40 I Cs-134 I Cs-137*Station 08 +/- +/- 5.96E+03 +/_ 8.46E+02 +/- +/-Station 09A**Station 11+/-+/-+/-.+/-1.05E+04+/
1.47E+04+/
1.38E+03 1.60E+03+/-+/-1.20E+02 +-6.34E+01 2.12E+01 +- 1.54E+01 2.12+01+1-1.54E+01 Indicator N Mean 1.03E+04 +/- 1.22E+03 LLD identified in ODCM Control Station[a] Sr-89/90 analyses performed annually.57 Table 3-14 Shoreline Soil Gamma Spectra, and Strontium[pCi/Kg]page 1 of 1 Sample Date 03/11/2008 Station 08 Sample Date 10/20/2008 Station 08 Sr-89 I Sr-90 I K-40 I Cs-1 34 I -Cs-1137 I[a][a]2.24E+03 +/- 3.35E+02< 2.45E+01< 1.97E+01< 3.29E+02< 6.72E+02 3.73E+03 +/- 9.38E+02< 8.72E+01< 7.58E+01 Mean 2.99E+03 +/- 6.37E+02* LLD identified in ODCM[a] Sr-89/90 analyses performed annually.58 g'Table 3-15 Fish Gamma Spectra[pCi/Kg]page 1 of 1 r Fish [a]Sampling Station 08 Date I K-40 I Mn-54" Fe-So' I Co-88. I Co-O. I Zn-oS" I Cs-134' Cs-137" 03/12/08 < 4.58E+01 < 1.38E+02 < 5.89E-01 < 5.99E+01 < 1.11E+02 < 6.30+001 < 5.05E+01 10/21/08 1.49E+03 +/- 2.14E+02 < 1.23E+01 < 4.08E+01 < 1.68E+01 < 1.17E+01 < 2.82E+01 < 1.62E+01 < 1.43E+01+/- 5.05E+01 Fish [a]Sampling Station 25**Date I K-40 I Mn-54' I Fe-Sg' I Co-8O' I Co-SO' I Zn-oS' I Cs-134" Cs-137'03/12/08 < 8.15E+01 < 2.37E+02 < 9.78E+01 < 8.80E+01 < 1.89E+02 < 8.95E+01 < 8.43E+01 10/22/08 1.58E+03 +/- 2.22E1+02
< 1.02E+01 < 3.08E+01 < 1.20E+01 < 1.15E+01
- 2.17E+01 < 1.12E+01 < 1.03E+01 Catfish [b]Sampling Station 08 Date I K-40 I Mn-54' Fe-S9' I Co-S8O Co-S0 I Zn-os I Cs-1 34' Cs-137" 03/12/08 < 4.41E+01 < 1.02E+02 < 4.73E+01 < 4.32E+01 < 6.57E+01 < 4.86E+01 < 4.34E+01 10/29/08 1.51E+03 +/- 2.11E+02 < 1.OOE+01 < 3.21E+01 < 1.23E+01 < 1.19E+01 < 2.01E+01 < 1.41E+01 < 1.55E+01 Catfish [b]Sampling Station 25**Date I K-40 I Mn-4 Fe-SO I Co-SO Co-S0' I Zn-0S Ce-13"4 Cs-137'03/18/08 10/22/08 Mean Indicator Control" 5.74E+01" 1.26E+01" 1.24E+02" 3.96E+01" 5.54E+01" 1.41E+01" 5.30E+01" 1.41E+01" 1.14E+02" 3.07E+01" 5.58E+01" 1.31E+01" 5.08E+01" 1.19E+01 1.38E+03 +/- 2.11E+02 1.50E+03 +/- 2.13E+02 1.48E+03 +/- 2.17E+02'LLD identified in ODCM"Control Station[a] Non-bottom dwelling species of gamefish.[b] Bottom dwelling species of fish.59
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2008 and tabulated in Section 3, are discussed below. Except for TLDs, GEL analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the GEL quality assurance manuals and laboratory procedures.
In addition to internal quality control measurements performed by each laboratory, they also participate 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 Programs are provided in Appendix B.The predominant radioactivity detected throughout 2008 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.
Naturally occurring nuclides, such as Be-7, K-40, and Th-228 were detected in numerous samples. Th-228 results were variable and are generally at levels higher than plant related radionuclides.
The following is a discussion and summary of the results of the environmental measurements taken during the 2008 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 areas 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 the historical trend of TLD exposure rate measurements.
Control and indicator averages indicate a steady relationship.
Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location.
These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs. This will continue to be monitored.
60 Figure 4-1: Environmental Radiation
-TLDs.- 10.0 0 V EU E 1.0~CO f-0 opOPC?C, C, -S0 N M "T LO (0 1, M M 0 -N M It O (0 1, W Enmronmental TLDs -Sector ThDs Av. Pre-op Linear (A\. Pre-op)Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location.
The average level of the 32 locations (two badges at each location) was 5.2 mR/standard month with a range of 1.1 to 46.9 mR/standard month. The highest quarterly average reading for any single location was obtained at location SSW-19/51.
This value was 34.0 mR/standard month. This location is on site directly across the access road from the Independent Spent Fuel Storage Facility.
The higher values can thus be attributed to the spent fuel stored in the ISFSI. Quarterly and annual TLDs are also located at each of the twelve environmental air sampling stations.
For the twelve locations within 10 miles of the station the average quarterly reading was 3.3 mR/standard month with a range of 1.6 to 5.8 mR/standard month. The average annual reading for these locations was 3.2 mR/standard month with a range of from 1.9 to 4.8 mR/standard month. The control location showed a quarterly average of 2.9 mR/standard month with a range of 2.0 to 4.2 mR/standard month. Its annual reading was 2.9 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.1 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.3 mR/standard month. Eight other TLDs, designated C-I thru C-8, which were pre-operational controls, were collected quarterly from four locations.
Stations C-3/4 and C-7/8 are designated controls.
These had a quarterly average of 3.3, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.6 to 4.8 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.61
4.2 Airborne
Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged.
Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.
Gross beta activity found during the pre-operational and early operating period of North Anna 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. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.One set of samples, taken 07/01/08, were lost by the carrier during delivery to the vendor.Figure 4-2: Gross Beta in Air Particulates E 0.12 0.1 0.08 0.06 0.04 0.02 0 I I co ou Cu M' C- -" co ( q t"- CD C C Cý C C C C cu CU Cu co CU CU CU CU-Control Sta-24 Aerage Pre-op Co 00 Co-0 0 M Cn C Cu Cu u C cc ca co M, c c C C-02 C C cu CU-, -7)r- 00 c C Cu- Cu" Indicator-Required LLD 62 Figure 4-3: Air Particulate 2008 Gross Beta Radioactivity 5.OOE-02 E 4.OOE-02 ......5 3.OOE-02 2.OOE-02 " ..1.00E-02 O.OOE+00 CO CO CO CO CO CO CO CO C Co S M L >1 C -5 0) CL >coo" LL < < 0 Z Date-Control Sta-24 -Indicator 4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine.
Once a week the samples are collected and analyzed.
The results of the analyses are presented in Table 3-4. One result was above the minimum detectable activity however, none of the results are considered true positives.
An investigation showed no releases of iodine 1- 131 in gaseous effluents during these periods. 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 that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectrometry.
The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes.
Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected.
No other positive results were seen. These analyses indicate the lack of station effects on the environment.
4.5 Air Particulate Strontium Strontium-89 and 90 analyses were not performed on the second quarter composites of air particulate filters from all monitoring stations as required.
The request was made to the vendor for performance of these analyses, however, the vendor failed to perform them. The samples were discarded by the vendor before 63 the analyses could be performed.
There has been no detection of these fission products at any of the indicator or control stations in recent years.4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2007 and thus were not collected in 2008.4.7 Precipitation A sample of rain water was collected monthly at on-site station 0 lA and analyzed for gross beta activity.
The results are presented in Table 3-7. Twelve (12)precipitation samples were obtained in 2008. Seven (7) of the twelve precipitation samples showed detectable results in 2008. The average annual gross beta activity was 50.8 pCi/liter with a range from 2.25 to 316 pCi/liter.
The 316 pCi/L was considered an anomalous result. The vendor verified the calculations re-analyzed the sample and the same result was obtained.
No unusual gaseous effluents were reported during 'the month of the anomalous result. Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements.
However, the vendor failed to perform the analysis a's requested for the first half-of the year. The samples were discarded by the vendor before the analyses could be performed.
No positive indications of plant related gamma emitting radioisotopes were observed in the 2nd semi-annual composite sample for 2008. During the pre-operational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison can not be made to the 2008 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made.This tritium activity ranged from 100 to 330 pCi/liter.
4.8 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 a critical pathway 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 is any plant effect.Analysis results for cow milk are contained in Table 3-8. All results show no 64 detectable 1-131 above the LLD of 1 pCi/I. Results of gamma ray spectroscopy did not detect the presence of any plant related isotopes.
In years past, Cs- 137 has been detected sporadically.
The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Naturally occurring K-40 was detected in all samples.Once each quarter a sample from each of the two collection stations is analyzed for-strontium-89 and strontium-90.
Neither Sr-89 nor Sr-90 was detected.
Sr-90 has been observed in the past. Pre-operational levels of 2.2 to 5.4 pCi/liter were measured for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents.
Its detection is the product of nuclear weapons testing fallout. This conclusion can be made based upon the fact that Sr-89 and Sr-90 have not been detected in gaseous effluents released from the station in many years, and the trend of consistent declining levels since the pre-operational period.4.9 Food Products and Vegetation Food/vegetation samples were collected from five locations and analyzed by gamma spectrometry.
The results of the analyses are presented in Table 3-9. No plant related isotopes were detected in any samples. As expected, naturally occurring potassium-40 and, cosmogenic beryllium-7 were detected in all samples, and thorium-228 and other natural products, including Bi-214, were detected in some samples.4.10 Well Water Water was sampled quarterly from the on site well at the metrology laboratory.
These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed for strontium-89 and strontium-90.
The results of these analyses are presented in Table 3-10. No plant related isotopes were detected.No gamma emitting isotopes were detected during the pre-operational period.4.11 River Water A sample of water from:the North Anna River was collected monthly. The analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy.
The monthly samples were composited quarterly and analyzed for tritium. Additionally, the second quarter samples were requested to be analyzed for strontium-89 and strontium-90 in accordance with program requirements.
However, the vendor failed to perform them. The samples were discarded by the 65 vendor before the analyses could be performed.
There has been no detection of these fission products at any of the indicator or control stations in recent years.No gamma emitting radioisotopes were detected in any of the samples. There was no measured activity of strontium-89 or strontium-90.
Tritium was measured in all four samples with an average annual concentration of 3660 pCi/liter and a range of 2850 to 4100 pCi/liter.
These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were collected during the pre-operational period.Figure 4-4: Tritium in River Water 8000 .7000 6000 5000 4000 3000 2000 1000 O0 (0 -M0 O0 C) N M 0T 0 (030 0 0 00 0 0 0 0 Date H-3 in RW Tritium -H-3 in RW Required LLD 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma ray spectrometry and for iodine- 131 by radiochemical separation.
A quarterly composite from each station was prepared and analyzed for tritium. Additionally, the second quarter samples were requested to be analyzed for strontium-89 and strontium-90 in accordance with program requirements.
However, the vendor failed to perform them. The samples were discarded by the vendor before the analyses could be performed.
There has been no detection of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.Neither gamma emitting radioisotopes nor iodine were detected in any of the samples. No tritium was detected at the control location.
The average level of 66 tritium activity at the indicator station was 3580 pCi/liter with a range of 2730 to 4140 pCi/liter.
Levels of tritium have increased since 1978 when the average level was below 300 pCi/liter.
Levels measured at the indicator location (Station 8) are comparable to those measured since 1986, see Figure 4-5. During the pre-operational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter.
Figure 4-5: Tritium in Surface Water 10000 1000 C.)03.-.-Tritium 100Required LLD Average Pre-op 100 r-m. r-N McO o r 0)0)0)0)0)0)0)0)0)0)00000000 cc cc ccccc cc c cc ccc c cc ccccc cc cc Date 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectrometry.
The October samples were analyzed for strontium-89 and strontium-90.
The results are presented in Table 3-13. Figure 4-6 shows the historical trend of Cs- 137 in sediments.
In 2008, one (1)of 21.2 pCi/kg.pCi/kg from the sediment sample from an indicator location showed Cs-137 level This should be compared to one (1) sample at a level of 120 control location in 2008. The detection of Cs- 137 in bottom 67 sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs- 137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented.
During the pre-operational period sediment samples were also analyzed by gamma ray spectroscopy.
There was no measurable amount of strontium-89 or 90 in aquatic sediment/silt.
A number of naturally occurring radioisotopes were detected in these samples at background levels.Figure 4-6: Cs-I 37 in Sediment Silt.o, 100 .C. 10 -0 c r- W M C;; N M q ) (0 ý W M00)0 ,N C) LO to I- M Date-. Station-8
-- Station-9 Control-Sta-09A
--- Station-1i1
-Average Pre-Op -Required LLD's 4.14 Shoreline Soil Shoreline soil/sediment, unlike bottom sediment, 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.Samples of shoreline soil were collected in March and October from indicator station 08. The samples were analyzed by gamma ray spectrometry.
The October sample was analyzed for strontium-89 and strontium-90.
The results are presented in Table 3-14.Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities.
No plant related isotopes were detected in the two samples analyzed.
Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs- 137 is attributed to 68 I ýaccumulation of residual global fallout from past atmospheric weapons testing.4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2008 and analyzed by gamma spectroscopy.
Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately.
The results are presented in Table 3-15. Naturally occurring K-40 was detected in half the samples. No plant related isotopes were detected.
Cs-137 was measured in pre-operational environmental fish samples., 69
- 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2008 -North Anna Location Description Date of Sampling Reason(s) for Loss/Exception Sta. 14-16, 23, 26 Sta. 01A Sta. 14-16, 23, 26 Sta. 08 Sta. 14-16, 23, 26 Sta. 14-16, 23, 26 Sta. 01 Sta. 22 Sta. 04 Sta0l-07, 21-24 Sta. O0A Sta 08, 9A, 11 Sta. 01-07, 21-24.Sta. 14a-16, 23,24 Sta. 14a-16, 23, 24 Sta. 06 Sta. 13 Vegetation Air Particulate And Iodine Vegetation Surface water Vegetation Vegetation Iodine Air Particulate and Iodine Air Particulate and Iodine Air Particulate Sr-89/90 Precipitation Gamma Spec.Surface/River Water (Sr-89/90)
Air Iodine and Particulate Vegetation Vegetation Air Particulate and Iodine Milk 01/16/08 02/05/08 02/13/08 02/20/08 03/18/08 04/22/08 04/29/08 06/18/08 06/18/08 04/01/08 -06/25/08 01/01/08 -06/25/08 04/15/08 -06/11/08 07/01/08 11/18/08 12/17/08 12/17/08 12/23/08 Pump not running. LLD achieved Seasonal Unavailability.
LLD not met for 1- 131.Seasonal Unavailability.
Seasonal Unavailability.
Seasonal Unavailability.
No charcoal in sampler.Timer malfunction volume estimated.
LLD achieved.GFCI breaker tripped. LLD achieved.Vendor failed to perform analyses as requested.
Sample disposed of.Vendor failed to perform analyses as requested.
Sample disposed of by vendor.Vendor failed to perform analyses as requested.
Sample disposed of by vendor Samples lost by carrier during deliver to vendor for analysis.Seasonal Unavailability.
Seasonal Unavailability.
Sampler malfunction, blown fuse. LLD achieved.LLD not achieved for Ba-140.70 REFERENCES 71 References
- 1. Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.2. Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications.
- 3. Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".4. Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010, "Radiological Environmental Monitoring Program".5. Title 10 Code of Federal Regulation, Part 50 (1OCFR50), "Domestic Licensing of Production and Utilization Facilities".
- 6. 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 1OCFR50, Appendix I", October, 1977.7. United States Nuclear Regulatory Commission, Regulatory Guide 4.8"Environmental Technical Specifications for Nuclear Power Plants", December 1975.8. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.9. NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.10. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.11. NUREG/CR-4007, "Lower Limit of Detection:
Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.72 APPENDICES 73 APPENDIX A: LAND USE CENSUS Year 2008 74 LAND USE CENSUS North Anna Power Station North Anna County, Virginia January I to December 31, 2008 Direction Distance (miles)Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch Boundary (> 50m 2) Animal Cow Goat N 0.9 1.5 2.7 None None None NNE 0.9 0.9 3.1 1.5 None None NE 0.8 0.9 1.6 1.5 None None ENE 0.8 2.1 2.4 2.5 None None E 0.8 1.3 1.3 3.5 None None ESE 0.9 1.7 1.7 None None None SE 0.9 1.4 1.4 1.5 None None SSE 0.9 1.0 1.0 2.8 None None S 0.9 1.1 1.0 2.8 None None SSW 1.0 1.4 3.8 1.9 None None SW 1.1 1.7 3.1 None None None WSW 1.1 1.6 1.6 1.6 None None W 1.1 1.5 3.3 None None None WNW 1.0 1.1 3.1 3.9 None None NW 1:0 1.0 None None None None NNW 0.9 1.0 1.1 None None None 75 2007 to 2008 Land Use Census Changes 2007 2008 Nearest Direction Distance Distance Site Boundary None Resident None Garden N 1.8 2.7 NE 0.9 1.6 ENE 2.1 2.4 SSW 1.4 3;8 W 1.5 3.3 WNW 2.6 3.1 NW 1.6 None Meat Animal None Milch Cow None Milch Goat None 76 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS YEAR 2008 77 INTRODUCTION This appendix covers the Intercomparison Program of the GEL Laboratories, LLC Environmental Laboratory as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). GEL uses QA/QC samples provided by Eckert & Zeigler Analytics, Inc, Environmental Resource Associates, (ERA) and Mixed Analyte Performance Evaluation Program (MAPEP), to monitor the quality of analytical processing associated with the REMP. The suite of samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides.
This includes: milk for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses once per quarter,> milk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,> water for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses during the 1st and 3rd quarters,> water for Sr-89 and Sr-90 analyses during the 4th quarter,> water tritium analysis during the 2nd and 4th quarters,> air filter for gamma (9 nuclides) analyses during the 2nd quarter, and> air filter for gross beta analysis during the 1st and 3rd quarters.RESULTS Interlaboratory comparison program results are evaluated using GEL's criterion.
Any sample analysis result that does not pass the criteria is investigated by GEL.A summary of GEL's results is provided in the tables below for the required sample matrix types and isotopic distribution.
Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result;analytical date; the known values supplied by the providers; pass or fail criteria.GEL analyzed 17 samples for 85 parameters in 2008. All results except twelve met the acceptance criteria and are discussed below.* The 2nd quarter Sr-89 in milk result fell below the acceptance criteria.
All data were reviewed and no errors are apparent.
A batch duplicate was also analyzed with this sample and its results fell within the acceptance criteria.
All other quality control criteria were also met. No further investigation will be performed.
- The cause of the Sr-90 failure in the 1st quarter was determined to be method inaccuracies when using a small sample volume. The Sr-90 data over the past 2.5 78 0 years was evaluated using average relative bias and relative precision statistics as outlined in ANSI N13.30. The average relative bias over this period is 0.0230 which is an excellent average relative bias. The relative precision is within the recommended 0.40 range at 0.2325. This indicates the method is in control. The normal procedure utilizes 500 -800 mL of sample for analysis resulting in a lower detection limit and a lower uncertainty when compared to the analysis of the cross check samples normally utilizing 200 mL of sample due to limited sample volume* The cause of the Gamma Emitter (Ba-133, Cs-134, Cs-137, Co-60, Zn-65)failures were attributed to an incorrect dilution.
The samples are received as concentrates and must be diluted prior to preparation.
Per the instructions, the samples should have been diluted to a final volume of 2 liters but were diluted to 4 liters instead. All instructions are now scanned by the Quality Assurance Officer and emailed to the laboratory Group Leader when the samples are logged. The instructions are also stored in a location accessible to all laboratory personnel.
- The Cs- 137 result fell just above the acceptance criteria.
All data were reviewed and no errors were apparent.
A batch duplicate was also analyzed with this sample and its results fell within the acceptance criteria.
All other quality control criteria were also met. A remedial sample was performed and the results fell within the acceptance range.P The *cause of the Americium-241 and Cesium- 134 failures is thought to be matrix interference and the potential for volatilization.
Two containers (100g and 10g) of this sample were received and logged for all parameters.
All results were reported from the 100g. The Quality Assurance Officer (QAO) was later informed by the group leader that the gamma results should have been reported from the 1 Og container due to matrix interference and the potential for volatilization of some of the compounds.
- The Nickel-63 failure was attributed an unusually low gravimetric yield. A review of data back to the year 2000 indicated there had been no other failures.
The sample was re-analyzed and acceptable results, 34.4 Bq/L, which is within 12% of the reference value, were obtained.* The cause of the Fe-55 failure was determined to be interference from Co-60, The Standard Operating Procedure (SOP) has been modified to include additional rinses and added Cobalt carrier to help eliminate Cobalt as an interferent.
The sample was also reanalyzed after the SOP modification and acceptable results were obtained.79 v 0, Analysis or Analysis Date GEL Vaue Known Value Pass/Fail Radionucide_
Iodine Analysis of a Cartridge (pCi/L)1-131 03/20/2008
- 63. 60 Pass 06/19/2008 87.5 84.5 Pass 10/30/2008 93.80 89.1 Pass 12/11/2008 56.50 53.2 Pass Sr-89/90 Analysis in Milk (pCi/L)Sr-89 03/20/2008 96.7 95.8 Pass 06/19/2008 61.14 85 Fail 10/30/2008 63.10 73.9 Pass 12/11/2008 85.50 91.9 Pass Sr-90 03/20/2008 9.32 12.9 Fail 06/19/2008 11.82 14.5 Pass 10/30/2008 9.25 11 Pass 12/11/2008 10.90 12.6 Pass Gamma Analysis in Milk (pCi/L)1-131 03/20/2008 61.8 60 Pass 06/19/2008 72.9 71.4 Pass 10/30/2008 69.1 67.9 Pass 12/11/2008 76.6 79.9 Pass Ce-141 03/20/2008 255 249 Pass 06/19/2008 166 174 Pass 10/30/2008 159 161 Pass 12/11/2008 179 191 Pass Cr-51 03/20/2008 331 359 Pass 06/19/2008 151.5 138 Pass 10/30/2008 392 421 Pass 12/11/2008 248 246 Pass Cs-134 03/20/2008 107 125 Pass 06/19/2008 73.8 76.7 Pass 10/30/2008 213 232 Pass 12/11/2008 128 134 Pass Cs-137 03/20/2008 151 146 Pass 06/19/2008 122 116 Pass 10/30/2008 154 162 Pass 12/11/2008 123 120 Pass Co-58 03/20/2008 72.9 70.8 Pass 06/19/2008 64.4 61.9 Pass 10/30/2008 167 179 Pass 12/11/2008 101 104 Pass 80 11 -Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionucide Gamma Anal sis in Milk (pCi/L) (continued)
Mn-54 03/20/2008 96.7 94.2 Pass 06/19/2008 153.0 135 Pass 10/30/2008 172.00 166 Pass 12/11/2008 151 152 Pass Fe-59 03/20/2008 106 102 Pass 06/19/2008 92 91.7 Pass 10/30/2008 157 144 Pass 12/11/2008 103 100 Pass Zn-65 03/20/2008 142 137 Pass 06/19/2008 128 127 Pass 10/30/2008 327 319 Pass 12/11/2008 193 183 Pass Co-60 03/20/2008 240 236 Pass 06/19/2008 103 104 Pass 10/30/2008 227 234 Pass 12/11/2008 139 133 Pass Gross Alpha/Beta in Air Filters (Bq/sample)
Gross Alpha 03/22/2008 0.143 0.348 Pass 10/22/2008 0.003 0 Pass Gross beta 03/22/2008 0.321 0.286 Pass 10/22/2008 0.564 0.525 Pass Gross Alpha/Beta in Water (pCi/L)Gross Alpha 05/08/2008 56.0 50.8 Pass 11/21/2008 17.6 26.9 Pass Gross beta 05/08/2008 46.3 51.4 Pass 11/21/2008 28.8 38 Pass Gamma Analysis in Water (pCi/L)1-131 03/20/2008 77.3 70.4 Pass 06/19/2008 40.9 45.3 Pass 10/30/2008 115 105 Pass 12/11/2008 63.7 64.1 Pass Ce-141 03/20/2008 191.3 198 Pass 06/19/2008 222.0 237 Pass 10/30/2008 114 107 Pass 12/11/2008 224 224 Pass Cr-51 03/20/2008 279.2 286 Pass 06/19/2008 212.0 188 Pass 10/30/2008 317 279 Pass 81 Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionuclide
[Gamma Analysis in Water (pCi/L) (continued)
Cr-51 (cont) 12/11/2008 278 288 Pass Cs- 134 03/20/2008 96.1 99.7 Pass 06/19/2008 100.0 104 Pass 10/30/2008 147 154 Pass 12/11/2008 159 157 Pass Cs- 137 03/20/2008 114.8 116 Pass 06/19/2008 169.0 158 Pass 10/30/2008 116 107 Pass 12/11/2008 148 140 Pass Co-58 03/20/2008 58.9 56.4 Pass 06/19/2008 85.6 84.2 Pass 10/30/2008 119 118 Pass 12/1112008 126 122 Pass Mn-54 03/20/2008 80.4 75 Pass 06/19/2008 193.0 184 Pass 10/30/2008 126 110 Pass 12/11/2008 192 178 Pass Fe-59 03/20/2008 86.1 81.4 Pass 06/19/2008 129 125 Pass 10/30/2008 109 95.6 Pass 12/11/2008 128 117 Pass Zn-65 03/20/2008 110.7 109 Pass 06/19/2008 194.0 172 Pass 10/30/2008 228 211 Pass 12/11/2008 238 214 Pass Co-60 03/20/2008 194.8 188 Pass 06/19/2008 155.0 142 Pass 10/30/2008 155 155 Pass 12/11/2008 168 156 Pass Sr-89/90 Analysis in water (pCi/L)Sr-89 05/09/2008 57.8 60.4 Pass 11/08/2008 44.3 48.7 Pass Sr-90 05/09/2008 30.7 39.2 Pass 11/08/2008 32.2 33.6 Pass Gamma Emitters in Water (pCi/L)Ba-133 05/13/2008 17.2 58.3 Fail 11/11/2008 60.7 63.5 Pass 11/20/2008 72.6 73.1 Pass 82 Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionucide Gamma Analysis in Water (continued)
Cs-134 05/13/2008 11.2 46.6 Fail 11/11/2008 28.1 25.6 Pass 11/20/2008 72.8 64.9 Pass Cs-137 05/13/2008 24.8 102 Fail 11/11/2008 31.5 25.6 Fail 11/20/2008 184 176 Pass Co-60 05/13/2008 20.6 76.6 Fail 11/11/2008 46.7 49.1 Pass 11/20/2008 87.3 84.4 Pass Zn-65 05/13/2008 31.8 106 Fail 11/11/2008 77.2 68.6 Pass 11/20/2008 354.0 327 Pass 1-131 Analysis in Water (pCi/L)1-131 04/15/2008 28.4 28.7 Pass 10/15/2008 29.2 28.1 Pass Tritium in Water (pCi/L Tritium 05/19/2008 12500 12000 Pass 11/01/2008 2100 2220 Pass Soil Radionucides (pCi/kg)Ac-228 05/16/08 1230 1180 Pass 11/21/08 1000 1320 Pass Am-241 05/16/08 1190 1230 Pass 11/21/08 1070 1050 Pass Bi-212 05/16/08 1224 1360 Pass 11/21/08 721 1540 Pass Bi-214 05/16/08 1990 1790 Pass 11/21/08 852 851 Pass Cs-134 05/16/08 5350 5640 Pass 11/21/08 3570 3470 Pass Cs-137 05/16/08 5850 6010 Pass 11/21/08 5320 5390 Pass Co-60 05/16/08 5090 5130 Pass 11/21/08 6140 6040 Pass Pb-212 05/16/08 1221 1080 Pass 11/21/08 1130 1520 Pass Pb-214 05/16/08 2200 2020 Pass 83 Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionuclide Soil Radionuclides (pCi/kg) (continued)
Pb-214 11/21/08 912 948 Pass Mn-54 05/16/08 <52.0 0 Pass 11/21/08 <37.2 0 Pass K-40 05/16/08 9990 11000 Pass 11/21/08 10700 11100 Pass Th-234 05/16/08 1310 2030 Pass 11/21/08 2550 2030 Pass Zn-65 05/16/08 2770 2660 Pass 11/21/08 2680 2450 Pass Sr-90 05/13/08 4420 5360 Pass 11/21/08 2640 2710 Pass Water Radionuclides (pCi/L)Am-241 05/08/2008 95 90.9 Pass 11/21/2008 174 161 Pass Cs- 134 05/08/2008 693 751.0 Pass 11/21/2008 1250 1240.0 Pass Cs-137 05/08/2008 1970 1990 Pass 11/21/2008 1270 1270 Pass Co-60 05/08/2008 1480 1420 Pass 11/21/2008 1160 1130 Pass ,Mn-54 05/08/2008
<9.32 0 Pass_ _11/21/2008
<9_112 0 Pass Zn-65 05/08/2008 800 694 Pass 1/21/2008 1070 987 Pass Sr-90 05/13/2008 517 512 Pass 11/21/2008 678 655 Pass Water Tritium (pCi/L)Tritium 06/20/2008 25800 25800 Pass 11/21/2008 27600 28800 Pass Radiological in Soil (Bq/kg)Am-241 03/12/2008 121 127.2 Pass 10/22/2008 65.88 69.1 Pass Cs- 134 02/02/2008 719 854.0 Pass 10/22/2008 585 581 Pass Cs- 137 02/02/2008 522 545 Pass 10/22/2008 3.5 2.8 Pass 84 Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionucide Radiological in Soil (Bq/kg) (continued)
Co-57 02/02/2008 380 421 Pass 10/22/2008 333.7 333 Pass Co-60 02/02/2008 2.67 2.9 Pass 10/22/2008 149 145 Pass Mn-54 02/02/2008 570 570 Pass 10/22/2008 440.7 415 Pass K-40 02/02/2008 586 571 Pass 10/22/2008 628 570 Pass Zn-65 02/02/2008
-0.426 0 Pass 10/22/2008
-0.67 0 Pass Fe-55 03/28/2008 615 390 Fail 10/22/2008 709.8 676 Pass Ni-63 03/28/2008 639 640 Pass 10/22/2008 763 760 Pass Sr-90 03/27/2008 473 493 Pass 10/22/2008 0.5 0 Pass Radiological in Water (Bq/kg)Am-241 03/12/2008 1.27 1.23 Pass 10/22/2008
-0.0003 0 Pass Cs-134 03/06/2008 0.108 0 Pass 10/22/2008 18.9 19.5 Pass Cs-137 03/06/2008 0.0648 0 Pass 10/22/2008 23.0 23.6 Pass Co-57 03/06/2008 23.2 22.8 Pass 10/22/2008 0.01 0 Pass Co-60 03/06/2008 8.41 8.4 Pass 10/22/2008 11.4 11.7 Pass Mn-54 03/06/2008 483 472 Pass 10/22/2008 13.4 13.7 Pass Zn-65 03/06/2008 17.4 16.3 Pass 10/22/2008 17.0 17.1 Pass Fe-55 03/27/2008 46.9 36.5 Pass 10/22/2008 44.8 46.2 Pass Ni-63 03/27/2008 40.3 30.7 Fail 10/22/2008
-0.2 0 Pass 85 Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionuclide Radiological in Water (Bq/kg) (continued)
Sr-90 03/20/2008 12.0 11.4 Pass 10/22/2008 6.40 6.45 Pass Radiological in Air Filter (Bq/sample)
- Am-241 03/18/2008 0.123 0.158 Pass 10/22/2008
-0.0003 0.0 Pass Cs-134 02/22/2008 1.97 2.52 Pass 10/22/2008 2.727 2.63 Pass Cs- 137 02/22/2008 2.47 2.70 Pass 10/22/2008 0.024 0.00 Pass Co-57 02/22/2008
- 3.30 3.55 Pass 10/22/2008 1.653 1.50 Pass Co-60 02/22/2008 1.16 1.31 Pass 10/22/2008 0.051 0.00 Pass Mn-54 02/22/2008
-0.0113 0.00 Pass 10/22/2008 2.870 2.64 Pass Zn-65 02/22/2008 1.92 2.04 Pass 10/22/2008 1.063 0.94 Pass Sr-90 03/28/2008 1.48 1.548 Pass_____ 10/22/2008 1.080 1.12 Pass Radiological in Vegetation (Bq/sample)
Am-241 03/22/2008 0.121 0.240 Fail 10/22/2008 0.257 0.3 Pass Cs- 134 03/22/2008 4.09 6.28 Fail 10/22/2008 5.47 5.50 Pass Cs- 137 03/22/2008 2.49 3.41 Pass 10/22/2008 0.073 0.00 Pass Co-57 03/22/2008 6.94 6.89 Pass.10/22/2008 6.813 7.10 Pass Co-60 03/22/2008 2.87 2.77 Pass 10/22/2008 4.703 4.70 Pass Mn-54 03/22/2008 5.16 4.74 Pass 10/22/2008 5.737 5.80 Pass Zn-65 03/22/2008
-0.205 0.00 Pass 10/22/2008 7.617 6.90 Pass Sr-90 03/22/2008 1.11 1.273 1 Pass 86
ýtl # 0'" Analysis or Analysis Date GEL Value Known Value Pass/Fail Radionuclide Radiological in Vegetation (Bq/sample) (continued)
Sr-90 10/22/2008 1.713 1.9 Pass AREVA NP Environmental Laboratory Condition Report Status Although AREVA NP Environmental Laboratory was not used by North Anna in 2008 for any environmental analyses, it was used in 2007 and 4 condition reports were still open at the time of the 2007 report. The status of each is summarized below. Any item that is still open will be included in the 2009 Radiological Environmental Operating Report, if North Anna uses AREVA for environmental analyses in 2009.CR-08-01, written due to 3rd quarter 2007 Analytics cross check filters failing the bias criteria for gross alpha, is still open. No error was found in the paperwork.
A recalibration of the instrument using a new source showed a 3.3% change in instrument efficiency.
CR-08-02, written due to 2nd quarter 2007 Analytics cross check filters failing bias criteria for Cr-51 and a failure of Ce-141 bias criteria in milk, has been closed. The failure was determined to be "bubbling" of the filter in the petri dish.The filters were too large for the petri dish. The petri dish was resized and the 2008 2nd quarter sample was counted successfully.
The Ce-141 failure in the milk sample was attributed to delay in counting causing poor statistics.
CR-08-10, written due to failure of the 4th quarter 2007 Analytics environmental cross check filters failing the bias criteria for Sr-89/90, is closed. The root cause was determined to be erroneous data entry for tracer weight. This caused the chemical recovery to be calculated incorrectly CR 11, written due to failure of the Analytics 4th quarter 2007 environmental cross check filters failing the bias criteria for Fe-59, Zn-65 and Co-60, is closed.The failure was determined to be "bubbling" of the filter in the petri dish. The filters were too large for the petri dish. The petri dish was resized and the 2008 2nd quarter sample was counted successfully.87