ML11123A215
| ML11123A215 | |
| Person / Time | |
|---|---|
| Site: | North Anna  (NPF-004, NPF-007, SNM-2507) |
| Issue date: | 04/26/2011 |
| From: | Lane N Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 11-213 | |
| Download: ML11123A215 (90) | |
Text
i.- ý- *-
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND), VIRGINIA 23261 April 26, 2011 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.
NAPS/JHL 11-213 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2b, enclosed is the 2010 Annual Radiological Environmental Operating Report.
The.
Radiological Environmental Operating Report provides the details associated with the Radiological Environmental Monitoring Program.
If you have any questions or require additional information, please contact D. R. Taylor at (540) 894-2616.
Very truly yours, N. LariIane Site Vice President Enclosure Commitments made in this letter: None
'4-
V Serial No.11-213 NAPS Annual Radiological Environmental Operating Report cc:
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station
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V Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2010 to December 31, 2010 Prepared by Dominion, North Anna Power Station
r Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2010 to December 31, 2010 Prepared by:
Reviewed by:
Approved by:
Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station MarK C. Lane Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B.
vans, Jr.
Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2
Table of Contents
- 1. EX ECU TIV E SU M M A RY.........................................................................................................
4
- 2. PRO G RA M D ESCRIPTION......................................................................................................
7 2.1 Introduction 7
2.2 Sam pling and A nalysis Program.........................................................................................
8
- 3. A N A LY TICA L RESU LTS........................................................................................................
22 3.1 Sum m ary of Results........................................................................................................
22 3.2 A nalytical R esults of 2010 REM P Sam ples...................................................................
31
- 4. D ISCU SSION O F R ESU LTS....................................................................................................
61 4.1 G am m a Exposure Rate...................................................................................................
61 4.2 A irborne G ross Beta..............................................................................................................
63 4.3 A irborne Radioiodine.......................................................................................................
64 4.4 A ir Particulate G am m a...................................................................................................
64 4.5 A ir Particulate Strontium.................................................................................................
64 4.6 S o il........................................................................................................................................
6 5 4.7 Precipitation..........................................................................................................................
65 4.8 Cow M ilk..............................................................................................................................
65 4.9 Food Products and V egetation........................................................................................
66 4.10 W ell W ater..........................................................................................................................
66 4.11 River W ater.........................................................................................................................
66 4.12 Surface W ater......................................................................................................................
67 4.13 Bottom Sedim ent................................................................................................................
68 4.14 Shoreline Soil......................................................................................................................
69 4.15 Fish......................................................................................................................................
70
- 5. PRO G RA M EX CEPTION S.....................................................................................................
71 REFEREN CES.................................................................................................................
- .................. 72 A PPEN D ICES......................................................................................................................................
74 A PPEN D IX A : LA N D U SE CEN SU S......................................................................................
75 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS.......................... 78 3
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2010 North Anna Nuclear 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, 2010, 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.
Control samples are 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 Chernobyl accident or natural variation.
Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and Teledyne Brown Engineering Environmental Services 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 4
equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The 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 and particulates, and precipitation. The 2010 airborne results were similar to previous years.
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. The average tritium activity in surface water for 2010 was 3100 pCi/liter. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3510 pCi/liter.
Nb-95 was reported in one surface water sample at the indicator location. However, the peak was not identified, but forced activity concentration calculation exceeded MDC and the 2 sigma error.
This is considered a false positive.
No plant related isotopes were reported in any other surface or river water. Well water samples did not indicate the presence of plant related isotopes.
No plant related isotopes were detected in precipitation samples. This trend is consistent throughout the environmental operational monitoring program.
Silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background.
Cs-137 was detected in two samples in the first half of the year. These samples were from one indicator and one control location. The levels were 100 and 155 pCi/kg respectively. This has occurred in the past and is attributed to fallout.
This is likely in this instance also as the control location value is larger than the sample location value. During the second half of the year, Cs-134 was detected in one sample location, the control location, at 176 pCi/kg.
However, this is considered a false positive as its'peak was not detected during the analysis, but its forced activity concentration exceeded MDC and the 2 sigma error.
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. Soil samples, which are collected every three years from twelve stations, were collected in 2010. Cs-137 was identified in several samples. For the indicator stations the average was 283 pCi/Kg while for the control station the average was 223 pCi/Kg.
During the preoperational phase Cs-137 was routinely detected and was 5
V attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout.
Cs-134 was detected in three samples, but these are considered false positives since the peak was not identified during the analysis, but the force activity calculation resulted in an activity concentration that exceeded the 2a value and the MDC.
No other plant related isotopes were detected. Naturally occurring nuclides such as Be-7, K-40, Ra-226, Th-228, Th-232 and others were detected.
The terrestrial exposure pathway includes milk and food/vegetation products.
Iodine-131 was not detected in any 2010 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 samples. Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data.
No plant related isotopes were detected in any vegetation samples.
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.
During 2010, 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 total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2010 was 0.45 millirem. For reference, this dose may be compared to the 625 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 2010 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. Teledyne Brown Engineering Environmental Services (TBE) 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 7
reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM.
These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".
This report documents the results of the Radiological Environmental Monitoring Program for 2010 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 2010 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 TBE for North Anna Power Station during the year 2010.
8
TABLE 2-1 North Anna Power Station - 2010 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 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 Station 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-15/47 SSE-16/48 Distance 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 Direction NE SSW WSW WNW NNE N
N NNE NNE NE NE ENE ENE E
E ESE ESE SE SE SSE SSE Degrees 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 Collection Frequency 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 Remarks 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 01 A was added in October 2007.
- Station at 14a was added in October 2008 and Station 14 was deleted.
- The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.
9
TABLE 2-1 North Anna Power Station - 2010 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Environmental Thermoluminescent Dosimetry (TLD)
Location NAPS Access Rd.
Elk Creek Church NAPS Access Rd.
Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)
South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate - Construction Side Laydown Area Lake Anna Campground
- 1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NAPS Sewage Treatment Plant Biology Lab***
Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Station S-17/49 S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 0.47 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 7.30 22.00 7.10 11.54 Direction S
W WNW WNW NW NW NNW NNW SSE NW WSW WSW Degrees 1730 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 Quarterly Remarks Control Control Airborne Particulate and Radioiodine 01 OIA 03 04 05 05A 0.20 0.64 7.10 5.10 4.20 2.04 NE SE WSW WNW NNE N
420 1380 2430 2870 200 110 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 01 A was added in October 2007.
- Station at 14a was added in October 2008 and Station 14 was deleted.
- The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.
10
TABLE 2-1 North Anna Power Station - 2010 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Airborne Particulate and Radioiodine Location Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA Station 06 07 21 22 23 24 Distance 4.70 7.30 1.00 1.00 0.93 22.00 Direction ESE SSE WNW WSW SSE NW Degrees 1150 1670 3010 2420 1580 3250 Collection Frequency Weekly Weekly 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 08 3.37 SSE 1480 Monthly 09A 11 01A 01A 12.90 WNW 2950 Monthly Control 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE 1380 Monthly 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 08 3.37 SSE 1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually 5.80 SE 1280 Semi-Annually Control 11 Shoreline Soil Soil 08 **
3.37 SSE 1480 Semi-Annually 01 0.20 NE 420 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 01A was added in October 2007.
- Station at 14a was added in October 2008 and Station 14 was deleted.
- The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.
11
TABLE 2-1 North Anna Power Station - 2010 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Fredericks Hall Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)
"Aspen Hills" Orange, VA Holladay Dairy (R.C. Goodwin)
Lakeside Dairy Waste Heat Treatment Facility (Second Cooling Lagoon)
Lake Orange 02 03 04 05 05A 06 07 21 22 23 24 12"****
12A 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 SSW WSW WNW NNE N
ESE SSE WNW WSW SSE NW 2030 2430 2870 200 110 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 Once/3 years Once/3 years Once/3 years Once/3 years Control Milk 8.30 NW 7.50 NW 3.37 SSE 16.5 NW 3100 Monthly 3100 Monthly 1480 Semi-Annually 3120 Semi-Annually Fish 08 25 Control Food Products Vegetation)
Moody Lane***
Route 614 Route 629/522 Aspen Hills "Historic Lane" 14a 15 16 23 26 1.70 1.37 12.60 0.93 1.15 ESE SE NW SSE S
1030 1330 3140 1580 172 0 Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest 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 01 A was added in October 2007.
- Station at 14a was added in October 2008 and Station 14 was deleted.
- The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.
12
TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS II h
ler IuIuniunceII Dosimetry (TLD)
(84 TLDs)
(12 TLDs)
Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Gamma Dose Gamma Dose 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month 1-131 Weekly Gross Beta Surface Water Quarterly (a) 2nd 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/mi 3
pCi/mi 3
pCi/mi 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 FREQUENCY Quarterly(a) 2nd Quarter Composite ANALYSIS Tritium (H-3)
(b)
REPORT UNITS pCi/L pCi/L Ground Water (Well Water)
Quarterly 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 15 30 15 15 30 30 15 10(c) 15 18 60 15 2000 (b)
(b) pCi/L pCi/L pCi/L Quarterly(a) 2nd Quarter Semi-Annually Aquatic Sediment 150 180 (b)
(b) pCi/kg (dry) pCi/kg (dry)
Annually Precipitation Monthly Gross Beta 4
pCi/L Semi-Annual Gamma Isotopic pCi/L Composite Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-13 1(')
Cs-134 15 Cs-137 18 Ba-140tl)
La-140)'
(1) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides.
Shoreline Soil Semi-Annually Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 150 180 (b)
(b) pCi/kg (dry) pCi/kg (dry)
Annually
- 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.
14
TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM
~A MPINM MM flA FRF'TIT'FNCV 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) 130 260 130 130 260 130 150 LLD REPORT UNITS pCi/kg (dry) pCi/kg (dry) pCi/L pCi!L Fish Semi-Annually Monthly, if available, or at harvest pCi/kg (wet)
Food Products (Broadleaf Vegetation) pCi/kg (wet) 60 80 60
- 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
(
Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation Environmental Station Identification 1
1A 2
3 4
5 5A 6
7 8
9A 11 12 12A 14a 15 16 21 22 23 24 25 26 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a) 01,NE-5/37 O1A,SE-13/45 02,SSW-20/52 03,C-5/6 04 05 05A,N-2/34 06,ESE-12/44 07, C-1/2 08-Water, Fish, Sediment, Shoreline Soil 09A-Water sample, Sediment 11-River Water, Sediment 12-Milk 12A-Milk 14a-Vegetation 15-Vegetation 16-Vegetation 21,WNW-27/59 22,WSW-24/56 23-SSE-15/47 24,C-3/4 25-Fish 26-Vegetation 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 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-1 1/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 (e)
(d)
(a)
(a)
(a)
(a)(b)
(c)
E-10/42 (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 (e) Dairy at Station 12 ceased milking in May 2010.
16
Figure 1. North Anna Site Radiological Monitoring Locations 17
18
19
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22312 7j8OAr~c~"-r SERnSzN 6
hllSwa ieerVf raye Me Wftmt Wevftfrl perf-har ZrADC.
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ý ADC ct.knwumta rc. 644 3 GnrhI G!E' Way, w
w AkmIn1& VA 22312 USEfl V4 -ERMGS8
.,J oPL rerrwM~tif
- ybe mane wtft.tte arfltenper-,ss3orrACf C.
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 Concentration, MDC.
Results are considered true positives when the measured value exceeds both the MDC and the 2y error. 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 - 2010 Docket No. 50-338/339 Page 1 of 8 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD"'
Mean Reported Sampled (Unit)
Total (PCi/unit)
Range Name Distance Mean Mean Measure-Type No.
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/m3)
Gamma Dose Gamma Dose 256 2
5.3(256/256)
(0.9-39.2) 2 2.6(16/16)
(1.7-3.7) 19/51(2) 0.42 mi.
SSW 27.9(8/8)
(7.8-39.2) 3.4(16/16)*
(2.3-5.1) 3.4(16/16)*
(2.3-5.1) 0 32 C-1/2 7.3 mi.
2.9 (8/8)
SSE (2.0-3.7) 0 Gamma Dose 40 2
5.3(40/40)
EPSP-0.37 mi.
7.5(8/8)
(2.9-9.3) 09/10 ENE (5.1-9.3) 3.4(16/16)*
(2.3-5.1) 0 Gamma Dose Gamma Dose Gross Beta 48 12 2
3.4(44/44)
(1.5-6.4) 2 3.4(11/11)
(2.2-5.1) 23 0.93 mi.
4.9(4/4)
SSE (4.2-6.2) 01 0.20 mi.
5.1(1/1)
NE (5.1) 3.3(4/4)
(2.0-4.9) 2.6(1/1)
(2.6) 0 0
0 685 0.01 17.0(633/633)
(4.83-34.4) 02 5.30 mi.
SSW 20.5(52/52) 20.0(52/52)
(8.55-35.5)
(9.55-41.0)
Air Iodine (pCi/m 3) 1-131 685 0.07 (0/633)
N/A N/A N/A (0/52) 0 Airborne Particulates (1E-03 pCi/m3 )
Gamma 52 Be-7 52 151(48/48) 05A 2.04 mi.
165(4/4) 160(4/4)
(103-226)
N (129-226)
(117-196) 0 0
Cs-134 52 0.05 (0/48)
N/A N/A N/A (0/4)
(1) mR/std month for TLDs (2) 19/51 located onsite near ISFSI.
- C-3/4, -7/8 used as control locations 23
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2010 Docket No. 50-338/339 Page 2 of 8 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)
(pCi/unit)
Mean Name Distance Mean Mean Measure-Type No.
Range Direction Range Range ments Airborne Particulates (1E-03 pCi/m3)
Cs-137 52 0.06 (0/48)
Sr-89 13 Sr-90 13 (0/12)
(0/12)
N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)
(0/1) 0 0
Soil (pCi/Kg) (dry)
Triennial Gamma K-40 (0/1) 4010 (2/2)
(2780-5230) 24 24 10800 (22/22)
(2130-24000).
23 0.93 23400 (2/2)
SSE (22700-24000) 237 (3/22)
Cs-134 24 150 (32)
(75.2-327)
Cs-137 24 180 283(18/22)
(52.7-732) 0.93 23 SSE 327 (1/2)
(327)
(0/2) 5.10 567 (2/2) 223 (2/2)
WNW (401-732)
(84.2-362) 0 12 12 12 12 12 12 12 12 Ra-226 24 Th-228 24 Th-232 24 Sr-89 24 2400(17/22)
(1260-4630) 1130(22/22)
(451-2330) 1080(21/22)
(387-2090)
(0/22) 22 1.00 4150(2/2)
WSW (3660-4630) 1.00 1850(2/2) 22 WSW (1690-2010) 22 1.00 1830(2/2)
WSW (1750-1900) 2900(2/2)
(2790-3010) 1270(2/2)
(1010-1530) 1090(2/2)
(1080-1210)
(0/2)
N/A N/A N/A N/A N/A N/A Precipitation (pCi/liter)
Sr-90 Monthly Gross Beta Semiannual Gamma Be-7 24 (0/22)
(0/2)
N/A 12 4
5.18(10/12)
(1.96-23.5) 2 01A 0.64 mi.
5.18(10/12)
SE (1.96-23.5) 01A 0.64 mi.
37.8(1/2)
SE (37.8) 0 2
37.8(1/2)
(37.8)
N/A N/A 0
0 Mn-54 2
15 (0/2)
N/A N/A N/A 24
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2010 Docket No. 50-338/339 Page 3 of 8 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)
Tot (PCi/unit)
Mean Name Distance Mean Mean Measure-Type al Range Direction Range Range ments No. I I
I II Fe-59 2
30 (0/2)
N/A N/A Precipitation (pCi/liter)
Co-58 Co-60 2
2 15 15 (0/2)
(0/2)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Zn-65 2
30 (0/2)
Zr-95 2
30 (0/2)
Nb-95 2
15 (0/2)
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 1-131 Cs-134 Cs-137 Ba-140 La-140 Th-228 Th-232 Gamma 2
2 2
2 2
2 2
15 18 (0/2)
(0/2)
(0/2)
(0/2)
(0/2)
(0/2) 4.49(1/2)
(4.49)
N/A N/A N/A N/A N/A N/A 01A N/A N/A N/A N/A N/A N/A 0.64 mi.
SE N/A N/A N/A N/A N/A N/A 4.49(1/2)
(4.49) 0 0
0 0
0 0
0 0
0 12 Milk (pCi/liter)
K-40 12 1340(12/12)
(1160-1520) 1-131 12 1
(0/12)
Cs-134 12 15 (0/12) 12 8.3 mi.
NW N/A N/A N/A N/A 1430(4/4)
(1270-1520)
N/A N/A N/A N/A 0
0 0
N/A 25
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2010 Docket No. 50-338/339 Page 4 of 8 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCiunit)
Mean Name Distance Mean Mean Measure-(Unit)
Tye No.,
Range Direction Range Range ments Milk (pCi/liter)
Cs-137 12 18 (0/12)
Ba-140 12 60 (0/12)
La-140 12 15 (0/12)
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
Sr-89 7
(Quarterly)
(0/5)
(01/5) 1 Sr-90 (Quarterly) 7 Food Vegetation (pCi/kg) (wet)
Gamma 30 Be-7 30 K-40 30 1260(24/24)
(382-2810) 4910(24/24)
(2080-9560) 23 varies 1620(5/6)
SSE (731-2810) 14a varies 6460(6/6)
ESE (4250-9560) 709(6/6)
(317-1260) 5810(6/6)
(3170-10700) 0 0
0 0
0 1-131 30 60 (0/24)
Cs-134 30 60 (0/24)
N/A N/A N/A N/A N/A N/A N/A (0/4)
(0/6)
(0/6)
(0/6)
N/A Cs-137 30 80 26.1(1/24)
N/A N/A Ground Well Water (pCi/liter)
Tritium 4
2000 (0/4) 01A 0.64 mi.
SE 0
Gamma 4
Mn-54 4
15 (0/4)
Fe-59 4
30 (0/4)
Co-58 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
26
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2010 Docket No. 50-338/339 Page 5 of 8 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)
Total (pCi/unit)
Mean Name Distance Mean Mean Measure-Type INo. I Range IDirection Range Range ments Ground Well Water (pCi/liter)
Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 4
4 4
4 4
4 4
4 4
4 1
4 12 12 12 12 12 12 15 (0/4) 30 (0/4) 30 (0/4) 15 (0/4) 10 (0/4) 15 (0/4) 18 (0/4) 60 (0/4) 15 (0/4)
(0/1)
(0/1) 2000 3510(4/4)
(2250-4660)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 11 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 5.80 mi.
SE N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 3510(4/4)
(2250-4660)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)*
(0/12)*
(0/12)*
(0/12)*
(0/12)*
(0/12)*
(0/12)*
River Water (pCi/liter) 15 30 15 15 30 (0/12)
(0/12)
(0/12)
(0/12)
(0/12)
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 Zr-95 12 30 (0/12)
N/A N/A
- 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 - 2010 Docket No. 50-338/339 Page 6 of 8 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled Total (pCi/un Mean Name Distance Mean Mean Measure-(Unit)
Type NO.
it)
Range Direction Range Range ments River Water (pCi/liter)
Surface Water (pCi/L)
Nb-95 12 15 1-131 12 1
Cs-134 12 15 Cs-137 12 18 Ba-140 12 60 La-140 12 15 Sr-89 1
Sr-90 I
Tritium 8
2000 (0/12)
N/A (0/12)
N/A (0/12)
N/A (0/12)
N/A (0/12)
N/A (0/12)
N/A (1/0)
N/A (1/0)
N/A 3100(4/4) 08 (2340-4060)
N/A 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 N/A 3100(4/4)
(2340-4060)
(0/12)*
(0/12)*
(0/12)*
(0/12)*
(0/12)*
(0/12)*
(1/0)*
(1/0)*
(0/4) 0 0
0 0
0 0
0 0
0 Gamma 24 Mn-54 24 15 (0/12)
N/A N/A N/A Fe-59 24 30 (0/12)
N/A N/A N/A Co-58 24 15 (0/12)
N/A N/A N/A Co-60 24 15 (0/12)
N/A N/A N/A Zn-65 24 30 (0/12)
N/A N/A N/A Zr-95 24 30 (0/12)
N/A N/A N/A Nb-95 24 15 (6.28)(1/12) 08 3.37 mi.
(6.28)(1/12)
(6.28)
SSE (6.28) 1-131 24 1
(0/12)
N/A N/A N/A Cs-134 24 15 (0/12)
N/A N/A N/A
- Results of surface water taken at Location 09A used as control value for river water (0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12) 28
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2010 Docket No. 50-338/339 Page 7 of 8 All Indicator Indicator Location Control Non-Medium or Analysis Locations 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)
Cs-137 24 18 (0/12)
Ba-140 24 60 (0/12)
La-140 24 15 (0/12)
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)
(0/1)
(0/1) 0 0
Sr-89 Sr-90 1
1 (0/1)
(0/1) 0 0
0 Sediment Silt (pCi/kg)
Gamma 6
K-40 6
Cs-134 6
150 12900(4/4)
(3050-17900)
(0/4)
Cs-137 6
180 100(1/4)
(100) 11 5.80 mi.
16600(2/2)
SSE (15300-17900)
N/A N/A (0/2) 08 3.37 mi.
100(1/2)
SSE 100 11 5.80 mi.
2280(2/2)
SSE (2040-2520) 11 5.80 mi.
1230 (2/2)
SSE (1190-1270) 11 5.80 mi.
1190(2/2)
SSE (1150-1230) 12100(2/2)
(11800-12400) 176(1/2)
(176) 155(1/2)
(155)
Ra-226 6
2130(4/4)
(1020-2950)
Th-228 6
1080(4/4)
(356-1520) 2760(1/2)
(2760) 802(2/2)
(672-932) 713 (2/2)
(586-840)
(0/1) 0 0
0 0
0 0
0 Th-232 6
1060 (4/4)
(318-1540)
(0/2)
(Annually)
Sr-89 3
N/A N/A N/A N/A N/A N/A Sr-90 3
(0/2)
(0/1)
N/A 0
0 Shoreline Soil (pCi/kg) (dry)
Gamma 2
K-40 2
6060(2/2)
(2770-9350) 08 3.37 mi.
6060(2/2)
SSE (2770-9350) 29
Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2010 Docket No. 50-338/339 Page 8 of 8 All Indicator Indicator Location Control Non-Medium or Analysis Locations 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 Shoreline Soil (pCi/kg) (dry)
Cs-134 2
150 Cs-137 2
180 (0/2)
N/A Ra-226 2
Th-228 2
1510(2/2)
(1350-1670) 1070(2/2)
(862-1270) 1000(2/2)
(894-1000)
N/A NA N/A NA 08 3.37 mi.
SSE 08 3.37 mi.
SSE 08 3.37 mi.
SSE N/A NA N/A NA (0/2)
(0/2) 1510(2/2)
(1350-1670) 1070(2/2)
(862-1270) 1000(2/2)
(894-1000)
N/A N/A N/A N/A N/A N/A N/A N/A 0
0 0
0 0
0 0
Th-232 2
(Annually)
Sr-89 I
(0/1)
(0/1)
Fish (pCi/kg) (wet)
Sr-90 1
Gamma 8
K-40 8
N/A 2220(4/4)
(2080-2450) 08 3.37 mi.
2220(4/4) 2260(4/4)
SSE (2080-2450)
(1610-3050)
Mn-54 8
130 Fe-59 8
260 Co-58 8
130 Co-60 8
130 Zn-65 8
260 Cs-134 8
130 Cs-137 8
150 (0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
N/A NA N/A NA N/A NA N/A NA N/A NA N/A NA N/A NA N/A N/A N/A N/A N/A N/A N/A (0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4) 0 0
0 0
0 0
0 0
30
3.2 Analytical Results of 2010 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 true positives when the measured value exceeds both the MDC and the 2(y error.
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.
TBE'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).
31
TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 1 of 4 First Station Quarter 12/29/2009 03/31/2010 N-1 N-33 N-2 N-34 NNE-3 NNE-35 NNE-4 NNE 36 NE-5 NE-37 NE-6 NE-38 ENE-7 ENE-39 ENE-8 ENE-40 E-9 E-41 E-1 0 E-42 ESE-11 ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 6.5 6.2 4.1 3.8 8.3 8.9 5.2 1.7 5.2 6.1 4.3 4.1 6.5 6.2 3.7 3.7 5.2 5.6 5.0 5.0 5.2 5.1 5.3 5.4 4.8 4.6 7.3 7.1 5.5 5.7 3.3 2.9 Second Quarter 03/31/2010 06/30/2010 4.4 3.3 2.9 2.9 4.7 4.5 4.0 2.6 3.5 4.5 2.4 2.2 4.2 4.5 2.8 2.8 4.4 4.5 3.1 2.9 3.0 3.0 3.1 3.3 2.7 3.7 6.1 4.6 3.5 3.1 1.5 1.8 Third Quarter 06/30/2010 09/28/2010 4.7 4.8 3.4 2.9 6.4 6.5 3.9 3.7 5.5 4.4 3.5 3.2 5.1 5.6 3.4 3.3 5.0 4.8 4.2 4.5 4.3 4.1 4.1 4.0 3.8 3.6 5.9 6.4 4.5 4.3 2.9 3.0 Fourth Quarter 09/28/2010 12/28/2010 5.3 5.1 4.4 3.8 8.2 7.3 6.0 4.8 5.9 5.2 3.8 3.7 7.2 7.5 5.3 4.7 5.9 6.0 5.9 4.9 4.8 4.5 5.9 5.8 5.5 6.3 8.1 6.8 5.9 6.4 4.0 4.1 Quarterly*
Average
+/- 2 s.d.
5.0
+/-
2.0 3.5
+/-
1.2 6.9
+/-
3.3 4.0
+/-
2.8 5.0
+/-
1.7 3.4
+/-
1.5 5.9
+/-
2.4 3.7
+/-
1.8 5.2
+/-
1.2 4.4
+/-
2.0 4.3
+/-
1.7 4.6
+/-
2.2 4.4
+/-
2.3 6.5
+/-
2.1 4.9
+/-
2.4 2.9
+/-
1.8
- Average of collocated TLDs.
32
TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Third Fourth Station Quarter Second Quarter Quarter Quarter Quarterly*
12/29/2009 03/31/2010 06/30/2010 09/28/2010 Average 03/31/2010 06/30/2010 09/28/2010 12/28/2010
+/- 2 s.d.
S-17 8.5 5.8 7.2 8.4 7.7
+/-
S-49 8.3 6.8 7.3 9.3 S-18 3.2 1.3 2.3 2.9 2.6
+/-
S-50 2.7 2.2 2.3 3.9 SSW-19 24.2 14.5 33.7 39.2 27.9
+/- 2, SSW-51 39.1 32.3 32.3 7.8 SSW-20 2.9 1.4 2.4 3.0 2.4
+/-
SSW-52 3.1 1.2 2.0 3.4 SW-21 4.7 4.1 4.5 6.0 4.7
+/-
SW-53 5.5 2.9 4.7 5.1 SW-22 5.1 4.0 4.5 5.5 4.7
+/-
SW-54 5.8 3.2 4.6 4.7 WSW-23 5.6 4.1 7.2 6.1 5.8
+/-
WSW-55 6.5 3.9 5.2 7.4 WSW-24 5.1 3.2 4.5 5.8 4.7
+/-
WSW-56 5.0 4.2 4.0 5.5 W-25 7.6 5.2 6.7 8.6 7.2
+/-
W-57 8.3 6.1 6.8 8.2 W-26 4.1 1.6 2.8 3.5 3.1
+/-
W-58 3.4 2.3 2.6 4.4 WNW-27 3.7 2.7 4.5 3.5 3.7
+/-
WNW-59 4.2 3.0 3.1 4.6 WNW-28 4.1 2.0 2.9 4.6 3.5
+/-
WNW-60 4.1 2.5 2.8 4.6 NW-29 7.5 4.4 6.1 7.5 6.4
+/-
NW-61 6.7 4.7 6.6 7.5 NW-30 2.7 1.0 2.2 3.3 2.2
+/-
NW-62 2.4 0.9 2.0 2.8 NNW-31 4.5 2.2 3.7 5.1 3.6
+/-
NNW-63 3.6 2.3 3.1 4.2 NNW-32 4.5 2.7 3.5 5.2 4.0
+/-
NNW-64 3.5 2.9 3.9 5.5 Page 2 of 4
?.3 1.5 3.0 1.6
'.9
.7 2.6 1.7
?.4 1.9 1.4
?.0
?.5 1.7 2.0 2.0 Mean 5.3
+/-
4.8
- Average of collocated TLDs.
33
TABLE 3-2 DIRECT RADIATION MEASURMENTS - PRE-OPERATIONAL LOCATIONS
& EMERGENCY SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Qu n
12/29/2009 03/31/2010 06/30/2010 09/28/2010 Av 03/31/2010 06/30/2010 09/28/2010 12/28/2010
+/-
Page 3 of 4 Statior arterly*
erage 2 s.d.
C-1 C-2 C-3"*
C-4"*
C-5 C-6 C-7"*
C-8"*
3.1 3.1 3.4 3.5 2.5 2.1 3.6 3.6 2.0 2.0 2.6 2.5 1.7 2.0 2.6 2.3 3.0 2.7 3.0 3.4 1.7 2.1 3.1 3.1 3.7 3.6 4.9 3.5 3.0 3.0 3.9 5.1 Mean Indicator Control**
2.9
+/-
1.3 3.4
+/-
1.5 2.3
+/-
1.0 3.4
+/-
1.7 2.6
+/-
3.4
+/-
0.7 0.8 EPSA-01***
EPSA-02***
EPSF-03***
EPSF-04***
EPSR-05***
EPSR-06***
EPSJ-07***
EPSJ-08***
EPSP-09***
EPSP-1 0***
5.4 5.8 4.7 4.5 5.8 4.2 6.0 5.7 8.2 7.6 4.1 3.9 4.3 2.9 4.6 4.6 3.3 3.0 5.1 6.8 4.8 4.8 4.2 4.1 4.6 5.5 3.1 4.9 6.9 7.1 6.4 6.6 6.4 4.7 5.2
+/-
2.0 4.5
+/-
1.9 5.8 5.0
+/-
1.2 4.9 4.7 5.2 9.3 9.0 4.5
+/-
2.4 7.5
+/-
2.7 5.3
+/-
1.5 Mean
- Average of collocated TLDs.
- Control Station
34
TABLE 3-2 DIRECT RADIATION MEASURMENTS - ENVIRONMENTAL QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 4 of 4 First Quarter Station 12/29/2009 03/31/2010 STA-01 STA-02 STA-03 STA-04 STA-05 STA-05A STA-06 STA-07 STA-21 STA-22 STA-23 STA-24*
5.7 2.2 2.3 2.9 3.3 3.4 4.2 2.9 2.2 4.2 4.6 3.1 Second Quarter 03/31/2010 06/30/2010 3.9 1.9 1.5 2.6 1.9 2.0 2.8 2.0 2.0 3.0 4.2 2.0 Third Quarter 06/30/2010 09/28/2010 4.5 2.7 2.0 1.9 3.4 4.7 4.6 2.6 2.8 4.2 4.4 3.3 Fourth Quarter 09/28/2010 12/28/2010 6..4 3.0 2.8 3.8 3.6 4.7 5.8 3.7 4.4 5.4 6.2 4.9 Quarterly Average
+/- 2 s.d.
4.7 2.5 2.2 2.8 3.1 3.7 4.4 2.8 2.9 4.2 4.9 3.3
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-1.8 1.0 1.1 1.6 1.6 2.6 2.5 1.4 2.2 2.0 1.8 1.2 Annual TLD 5.1 2.3 2.2 2.3 3.8 2.9 4.2 3.0 2.6 4.1 4.7 2.6 3.4
+/-
2.1 Mean - Indicator Locations 3.4
+1-1.2
- Control 35
Table 3-3 Air Particulate page Gross Beta Radioactivity 1 of 4
[10-1 pCi/m 3]
Period Station Station Station Station Station Station Station Ending 01 I
I I
04 I
I 06 I
07 01/05/10 1.22E+01
+/-
2.63E+00 1.74E+01
+/-
2.94E+00 1.35E+01
+/-
2.73E+00 1.56E+01
+/-
2.85E+00 1.58E+01
+/-
2.85E+00 1.62E+01
+/-
2.87E+00 1.58E+01
+/-
2.85E+00 01/12/10 1.60E+01
+/-
2.79E+00 1.55E+01
+/-
2.76E+00 1.36E+01
+/-
2.64E+00 1.76E+01
+/-
2.86E+00 1.48E+01
+/-
2.71E+00 1.60E+01
+/-
2.78E+00 1.20E+01
+/-
2.56E+00 01/19/10 2.27E+01
+/-
3.66E+00 2.55E+01
+/-
3.76E+00 2.41E+01
+/-
3.72E+00 2.18E+01
+/-
3.62E+00 1.97E+01
+/-
3.53E+00 1.55E+01
+/-
3.35E+00 2.06E+01
+/-
3.57E+00 01/28/10 1.73E+01
+/-
3.39E+00 2.19E+01
+/-,
3.60E+00 1.70E+01
+/-
3.37E+00 1.48E+01
+/-
3.29E+00 1.72E+01
+/-
3.40E+00 1.29E+01
+/-
3.20E+00 1.32E+01
+/-
3.22E+00 02/05/10 1.99E+01
+/-
3.45E+00 2.06E+01
+/-
3.48E+00 1.99E+01
+/-
3.47E+00 1.89E+01
+/-
3.42E+00 1.74E+01
+/-
3.35E+00 1.14E+01
+/-
3.08E+00 1.94E+01
+/-
3.45E+00 02/09/10 1.61E+01
+/-
3.63E+00 1.12E+01
+/-
3.53E+00 1.52E+01
+/-
3.94E+00 1.17E+01
+/-
3.48E+00 1.45E+01
+1-3.54E+00 1.01E+01
+/-
3.99E+00 1.39E+01
+/-
3.52E+00 02/16/10 1.35E+01
+/-
3.10E+00 1.99E+01
+/-
3.36E+00 1.03E+01
+/-
2.98E+00 1.19E+01
+/-
3.04E+00 1.45E+01
+1-3.15E+00 1.23E+01
+1-3.04E+00 7.37E+00
+/-
2.78E+00 02/23/10 1.23E+01
+/-
2.46E+00 9.32E+00
+/-
2.33E+00 1.28E+01
+/-
2.57E+00 1.17E+01
+/-
2.47E+00 1.09E+01
+/-
2.42E+00 1.15E+01
+1-2.46E+00 8.95E+00
+/-
2.30E+00 03/02/10 8.O0E+00
+/-
2.48E+00 9.95E+00
+/-
2.58E+00 7.59E+00
+/-
2.35E+00 8.66E+00
+/-
2.46E+00 7.16E+00
+/-
2.38E+00 7.09E+00
+/-
2.38E+00 6.23E+00
+/-
2.34E+00 03/09/10 1.39E+01
+/-
2.46E+00 1.66E+01
+/-
2.78E+00 1.32E+01
+/-
2.60E+00 1.41E+01
+/-
2.64E+00 1.31E+01
+/-
2.59E+00 1.59E+01
+/-
2.74E+00 1.33E+01
+/- 2.60E+00 03/16/10 1.18E+01
+/-
3.19E+00 1.56E+01
+/-
3.34E+00 8.89E+00
+/-
3.01E+00 7.28E+00
+/-
2.94E+00 1.12E+01
+/-
3.13E+00 5.35E+00
+/-
2.48E+00 4.83E+00
+/-
2.82E+00 03/23/10 1.66E+01
+/-
3.49E+00 2.13E+01
+/-
3.65E+00 1.21E+01
+/-
3.38E+00 1.22E+01
+/-
3.34E+00 1.46E+01
+/-
5.66E+00 1.30E+01
+/-
3.34E+00 1.77E+01
+/-
3.53E+00 03/31/10 1.28E+01
+/-
2.49E+00 1.80E+01
+/-
2.75E+00 9.49E+00
+/-
2.26E+00 1.21E+01
+/-
2.42E+00 9.93E+00
+/-
2.33E+00 1.14E+01
+/-
2.41E+00 04/06/10 1.02E+01
+/-
3.72E+00 1.81E+01
+/-
4.10E+00 1.15E+01
+/-
3.79E+00 1.04E+01
+/-
3.83E+00 9.38E+00
+/-
4.46E+00 7.57E+00
+/-
2.51E+00
- 9.03E+00
+/-
3.70E+00 04/14/10 1.74E+01
+/- 3.03E+00 2.04E+01
+/-
3.16E+00 1.46E+01
+/-
2.91E+00 1.46E+01
+/-
2.90E+00 1.13E+01
+/-
5.99E+00 1.80E+01
+/-
3.05E+00 2.10E+01
+/-
3.18E+00 04/20/10 1.54E+01
+/-
3.14E+00 2.04E+01
+/-
3.39E+00 1.68E+01
+/-
3.20E+00 1.60E+01
+/-
3.17E+00 1.56E+01
+/- 4.38E+00 1.41E+01
+/-
3.06E+00 1.54E+01
+/-
3.13E+00 04/27/10 1.85E+01
+/-
3.27E+00 2.65E+01
+/-
3.62E+00 1.64E+01
+/-
3.19E+00 1.41E+01
+/-
3.08E+00 2.11E+01
+/-
3.40E+00 1.83E+01
+/-
3.27E+00 1.58E+01
+/-
3.16E+00 05/04/10 1.72E+01
+/-
3.32E+00 2.20E+01
+/-
3.52E+00 1.52E+01
+/-
3.23E+00 1.84E+01
+/-
3.37E+00 1.61E+01
+/-
3.27E+00 1.40E+01
+/-
3.17E+00 1.56E+01
+/-
3.24E+00 05/11/10 1.69E+01
+1-3.18E+00 2.20E+01
+/-
3.40E+00 1.26E+01
+/-
2.96E+00 1.88E+01
+/-
3.26E+00 1.55E+01
+/-
3.10E+00 1.73E+01
+/-
3.19E+00 2.02E+01
+/-
3.32E+00 05/19/10 9.67E+00
+/-
2.31E+00 1.33E+01
+/-
2.48E+00 8.67E+00
+/-
2.27E+00 9.86E+00
+/-
2.32E+00 1.12E+01
+/-
2.36E+00 9.19E+00
+/-
2.26E+00 9.40E+00
+/-
2.66E+00 05/25/10 8.25E+00
+/-
3.37E+00 1.64E+01
+/-
3.91E+00 9.80E+00
+/-
3.42E+00 1.14E+01
+/-
3.54E+00 1.26E+01
+/-
3.66E+00 1.13E+01
+/-
3.60E+00 9.86E+00
+/-
3.52E+00 06/02/10 1.19E+01
+/-
2.92E+00 1.32E+01
+/-
2.97E+00 8.76E+00
+/-
2.79E+00 1.42E+01
+/-
3.04E+00 1.44E+01
+/-
3.05E+00 1.13E+01
+/-
2.91E+00 1.18E+01
+/-
2.92E+00 06/08/10 1.65E+01
+/-
3.78E+00 1.58E+01
+/-
3.73E+00 1.65E+01
+/-
3.74E+00 1.56E+01
+/-
3.70E+00 1.78E+01
+/-
3.80E+00 1.35E+01
+/-
3.60E+00 1.41E+01
+/-
3.63E+00 06/15/10 1.12E+01
+/-
2.69E+00 1.33E+01
+/-
2.80E+00 1.84E+01
+/-
3.06E+00 1.40E+01
+/-
2.85E+00 1.36E+01
+/-
2.83E+00 1.49E+01
+/-
2.89E+00 1.72E+01
+/-
3.OOE+00 06/22/10 1.61E+01
+/-
3.43E+00 1.28E+01
+/-
3.30E+00 2.10E+01
+/-
3.64E+00 9.54E+00
+/-
3.15E+00 1.47E+01
+/-
3.38E+00 1.26E+01
+/-
3.29E+00 1.63E+01
+/-
3.45E+00 06/29/10 2.14E+01
+/-
3.64E+00 2.25E+01
+/-
3.67E+00 1.70E+01
+/-
3.45E+00 1.76E+01
+/-
3.47E+00 1.70E+01
+/-
3.44E+00 1.35E+01
+/-
3.29E+00 1.94E+01
+/-
3.55E+00 36
Table 3-3 Air Particulate Gross Beta Radioactivity
[10-3 pCi/m 3]
page 2 of 4 Period Ending 01/05/10 01/12/10 01/19/10 01/28/10 02/05/10 02/09/10 02/16/10 02/23/10 03/02/10 03/09/10 03/16/10 03/23/10 03/31/10 04/06/10 04/14/10 04/20/10 04/27/10 05/04/10 05/11/10 05/19/10 05/25/10 06/02/10 06/08/10 06/15/10 06/22/10 06/29/10 Station Station 22 Station 23 Station 24*
Station 01A Station 05A I
1.34E+01 1.24E+01 1.48E+01 9.44E+00 1.55E+01 7.92E+00 1.34E+01 9.91 E+00 5.18E+00 1.47E+01 8.94E+00 1.30E+01 1.22E+01 9.55E+00 1.68E+01 1.46E+01 1.91E+01 1.53E+01 1.64E+01 5.81 E+00 1.00E+01 1.05E+01 1.45E+01 1.01 E+01 1.33E+01 2.11E+01 2.72E+00 2.58E+00 3.32E+00 3.04E+00 3.26E+00 3.40E+00 3.05E+00 2.36E+00 2.29E+00 2.68E+00 3.03E+00 3.36E+00 2.47E+00 3.73E+00 3.00E+00 3.10E+00 3.29E+00 3.24E+00 3.15E+00 2.04E+00 3.55E+00 2.86E+00 3.71 E+00 2.62E+00 3.31 E+00 3.61 E+00 1.65E+01 1.44E+01 1.77E+01 1.81E+01 2.00E+01 1.39E+01 1.53E+01 1.21E+01 8.71E+00 1.58E+01 1.10E+01 1.70E+01 1.46E+01 9.95E+00 1.87E+01 1.59E+01 2.13E+01 1.57E+01 2.10E+01 7.84E+00 9.39E+00 1.24E+01 7.18E+00 1.02E+01 1.33E+01 1.63E+01
+/-
2.88E+00
+/-
2.70E+00
+/-
3.45E+00
+/-
3.42E+00
+/-
3.46E+00
+/-
4.14E+00
+/-
3.18E+00
+/-
2.46E+00
+/-
2.51 E+00
+/-
2.74E+00
+/
3.13E+00
+/-
3.52E+00
+/
2.57E+00
+-
3.73E+00
+-
3.09E+00
+-
3.17E+00
+/
3.39E+00
+/
3.25E+00
+/
4.97E+00
+/
2.24E+00
+/-
3.52E+00
+-
3.13E+00
+-
3.32E+00
+-
2.63E+00
+/-
3.31E+00
+/
3.41 E+00 1.36E+01 1.44E+01 2.51E+01 1.69E+01 1.43E+01 1.06E+01 1.46E+01 1.24E+01 5.61E+00 1.46E+01 9.01 E+00 1.48E+01 9.96E+00 1.05E+01 1.71E+01 1.35E+01 2.09E+01 1.65E+01 1.86E+01 1.08E+01 1.11E+01 1.17E+01 1.30E+01 1.45E+01 1.04E+01 1.50E+01
+/-
2.73E+00
+/-
2.70E+00
+/-
3.75E+00
+/-
3.38E+00
+/-
3.20E+00
+/-
3.60E+00
+/-
3.11E+00
+/-
2.52E+00
+/-
2.31E+00
+/-
2.68E+00
+/-
3.03E+00
+/-
3.39E+00
+/-
2.37E+00
+/-
3.66E+00
+/-
3.07E+00
+/-
3.02E+00
+/-
3.39E+00
+/-
3.28E+00
+/-
3.25E+00
+/-
2.33E+00
+/-
3.60E+00
+/-
2.91 E+00
+/-
3.63E+00
+/-
2.85E+00
+/-
3.19E+00
+/-
3.36E+00 1.75E+01
+/-
2.94E+00 1.31 E+01
+/-
2.62E+00 2.05E+01
+/-
3.56E+00 1.83E+01
+/-
3.44E+00 1.99E+01
+/-
3.46E+00 1.87E+01
+/-
3.71E+00 1.32E+01
+/-
3.12E+00 1.44E+01
+/-
2.63E+00 9.55E+00
+/-
2.50E+00 1.87E+01
+/-
2.89E+00 1.06E+01
+/-
3.11 E+00 1.67E+01
+/-
3.54E+00 1.41 E+01
+/-
2.52E+00 1.47E+01
+/-
3.95E+00 2.10E+01
+/-
3.19E+00 1.80E+01
+/-
3.27E+00 2.17E+01
+/-
3.42E+00 1.32E+01
+/-
3.13E+00 1.94E+01
+/-
3.28E+00 1.21E+01
+/-
2.46E+00 1.21E+01
+/-
3.52E+00 1.76E+01
+/-
3.17E+00 1.81E+01
+/-
3.81E+00 1.93E+01
+/-
3.11E+00 1.17E+01
+/-
3.24E+00 1.92E+01
+/-
3.54E+00 1.20E+01 8.03E+00 1.97E+01 1.55E+01 1.47E+01 1.12E+01 1.29E+01 1.05E+01 7.61E+00 1.72E+01 6.67E+00 1.76E+01 1.41E+01 1.03E+01 1.78E+01 1.55E+01 1.93E+01 1.61E+01 1.53E+01 7.93E+00 7.56E+00 5.33E+00 1.50E+01 1.40E+01 1.02E+01 1.85E+01 2.63E+00 2.32E+00 3.53E+00 3.31 E+00 3.22E+00 3.67E+00 3.07E+00 2.36E+00 2.45E+00 2.82E+00 2.94E+00 3.55E+00 2.59E+00 3.73E+00 3.04E+00 3.15E+00 3.31 E+00 3.27E+00 3.11E+00 2.21 E+00 3.34E+00 2.80E+00 3.71 E+00 2.83E+00 3.17E+00 3.52E+00 1.53E+01
+/-
2.82E+00 1.51 E+01
+/-
2.73E+00 1.96E+01
+I-3.53E+00 1.65E+01
+/-
3.36E+00 1.48E+01
+/-
3.24E+00 1.22E+01
+/-
3.44E+00 1.21E+01
+/-
3.04E+00 9.98E+00
+/-
2.37E+00 6.76E+00
+/-
2.35E+00 1.56E+01
+/-
2.73E+00 7.58E+00
+/-
2.96E+00 1.56E+01
+/-
3.46E+00 8.53E+00
+/-
2.24E+00 1.61 E+01
+/-
4.08E+00 1.73E+01
+/-
3.02E+00 1.33E+01
+/-
3.01E+00 1.77E+01
+/-
3.25E+00 1.80E+01
+/-
3.35E+00 1.61 E+01
+/-
3.13E+00 1.09E+01
+/-
2.34E+00 1.08E+01
+/-
3.58E+00 1.30E+01
+/-
2.99E+00 1.38E+01
+/-
3.61E+00 1.07E+01
+/-
2.67E+00 1.70E+01
+/-
3.48E+00 1.75E+01
+/-
3.46E+00
- Control Station 37
Table 3-3 Air Particulate Gross Beta Radioactivity
[10-3 pCi/m 3]
page 3 of 4 Period Ending 07/06/10 07/13/10 07/21/10 07/27/10 08/04/10 08/12/10 08/18/10 08/24/10 08/31/10 09/07/10 09/14/10 09/21/10 09/28/10 10/06/10 10/12/10 10/19/10 10/26/10 11/02/10 11/09/10 11/16/10 11/23/10 11/30/10 12/07/10 12/14/10 12/21/10 12/28/10 1.61 E+01 2.96E+01 2.63E+01 1.62E+01 1.76E+01 2.37E+01 2.23E+01 2.43E+01 2.35E+01 2.64E+01 2.55E+01 2.38E+01 3.05E+01 1.12E+01 3.42E+01 2.12E+01 1.80E+01 1.51E+01 1.27E+01 1.98E+01 2.36E+01 1.46E+01 1.28E+01 1.73E+01 2.12E+01 1.08E+01 Station
+/-
2.91E+00 1.89E+01
+/-
3.46E+00 3.35E+01
+/-
3.54E+00 2.91 E+01
+/-
3.15E+00 2.51 E+01
+/-
3.08E+00 2.50E+01
+/-
3.53E+00 2.93E+01
+/-
3.20E+00 3.06E+01
+/-
3.69E+00 2.09E+01
+/-
3.53E+00 1.93E+01
+/-
3.57E+00 2.86E+01
+/-
3.51 E+00 2.04E+01
+/-
3.56E+00 2.03E+01
+/-
3.54E+00 2.53E+01
+/-
2.60E+00 8.55E+00
+/-
4.42E+00 2.43E+01
+/-
3.22E+00 1.31 E+01
+/-
3.22E+00 1.79E+01
+/-
3.11E+00 9.87E+00
+/-
3.OOE+00 9.28E+01
+/-
2.61E+00 1.71E+01
+/-
3.20E+00 2.78E+01
+/-
2.58E+00 1.50E+01
+/-
3.03E+00 1.12E+01
+/-
2.86E+00 1.80E+01
+/-
3.44E+00 1.34E+01
+/-
2.48E+00 1.07E+01 Station 02 Station 03 l
+/-
3.06E+00 1.57E+01
+/-
2.90E+00
+/-
3.61E+00 2.42E+01
+/-
3.22E+00
+/-
3.63E+00 1.36E+01
+/-
3.04E+00
+/-
3.61E+00 1.56E+01
+/-
3.14E+00
+/-
3.38E+00 1.31 E+01
+/-
2.90E+00
+/-
3.78E+00 2.OOE+01
+/-
3.32E+00
+/-
3.51 E+00 2.10E+01
+/-
3.13E+00
+/-
3.62E+00 2.22E+01
+/-
3.56E+00
+/-
3.40E+00 2.05E+01
+/-
3.44E+00
+/-
3.63E+00 2.47E+01
+/-
3.47E+00
+/-
3.31E+00 2.23E+01
+/-
3.41E+00
+/-
3.38E+00 2.29E+01
+/-
3.59E+00
+/-
3.34E+00 2.61E+01
+/-
3.27E+00
+/-
2.46E+00 1.10E+01
+/-
2.66E+00
+/-
3.99E+00 1.75E+01
+/-
3.70E+00
+/-
2.83E+00 1.53E+01
+/-
2.93E+00
+/-
3.26E+00 1.83E+01
+/-
3.19E+00
+/-
2.84E+00 1.26E+01
+/-
2.99E+00
+/-
2.83E+00 1.17E+01
+/-
2.94E+00
+/-
2.45E+00 1.77E+01
+/-
2.53E+00
+/-
3.37E+00 2.13E+01
+/-
3.11E+00
+/-
2.62E+00 2.01E+01
+/-
2.83E+00
+/-
2.96E+00 8.46E+00
+/-
2.82E+00
+/-
2.89E+00 1.65E+01
+/-
2.81 E+00
+/-
3.03E+00 2.06E+01
+/-
3.41 E+00
+/-
2.50E+00 1.01 E+01
+/-
2.42E+00
+/-
3.23E+00 1.59E+01
+/-
3.10E+00 Station 04 I
1.62E+01
+/-
2.94E+00 1.95E+01 2.85E+01
+/-
3.39E+00 3.01E+01 2.07E+01
+/-
3.33E+00 2.OOE+01 1.84E+01
+/-
3.29E+00 1.52E+01 1.69E+01
+/-
3.05E+00 1.69E+01 2.04E+01
+/-
3.34E+00 2.53E+01 2.41 E+01
+/-
3.27E+00 2.68E+01 2.11E+01
+/-
3.50E+00 2.74E+01 1.92E+01
+/-
3.40E+00 2.38E+01 2.53E+01
+/-
3.49E+00 3.36E+01 2.20E+01
+/-
3.40E+00 2.17E+01 2.69E+01
+/-
3.72E+00 2.21E+01 3.04E+01
+/-
3.48E+00 2.77E+01 9.35E+00
+/-
2.55E+00 1.02E+01 3.31E+01
+1 4.37E+00 2.79E+01 1.79E+01
+/-
3.06E+00 2.41E+01 1.65E+01
+/
3.13E+00 2.43E+01 1.30E+01
+/-
3.OOE+00 1.53E+01 1.26E+01
+-
2.99E+00 1.38E+01 2.17E+01
+/
2.73E+00 2.29E+01 2.31 E+01
+/
3.19E+00 3.09E+01 1.91E+01
+/-
2.80E+00 1.54E+01 1.24E+01
+/
3.02E+00 1.43E+01 1.84E+01
+/
2.91E+00 2.16E+01 2.08E+01
+/-
3.45E+00 2.25E+01 1.22E+01
+/-
2.53E+00 1.53E+01 1.70E+01
+/-
3.15E+00 1.82E+01 Station 05
+/-
+/-
+/-
+/-
+/-
I 3.10E+00 1.80E+01 3.46E+00 2.20E+01 3.30E+00 1.75E+01 3.12E+00 1.73E+01 3.05E+00 1.40E+01 3.58E+00 2.41E+01 3.38E+00 1.86E+01 3.79E+00 2.61E+01 3.60E+00 2.23E+01 3.83E+00 3.20E+01 3.38E+00 1.62E+01 3.49E+00 2.20E+01 3.40E+00 2.41E+01 2.57E+00 8.81 E+00 4.15E+00 2.89E+01 3.35E+00 1.70E+01 3.51 E+00 2.01E+01 3.11E+00 1.47E+01 3.05E+00 8.89E+00 2.78E+00 1.88E+01 3.52E+00 2.96E+01 2.62E+00 1.39E+01 3.11E+00 1.21E+01 3.07E+00 1.80E+01 3.48E+00 2.19E+01 2.73E+00 1.25E+01 Station 06
+/-
3.02E+00 1.18E+01
+/-
3.10E+00 2.49E+01
+/-
3.20E+00 1.46E+01
+/-
3.23E+00 1.61 E+01
+/-
2.92E+00 1.71 E+01
+/-
3.53E+00 2.18E+01
+I-3.04E+00 2.06E+01
+/-
3.76E+00 2.15E+01
+/-
3.52E+00 2.41E+01
+-
3.77E+00 2.67E+01
+/
3.12E+00 2.OOE+01
+/
3.48E+00 2.55E+01
+/-
3.25E+00 2.35E+01
+/-
2.50E+00 1.12E+01
+/-
4.18E+00 2.69E+01
+/-
3.03E+00 1.32E+01
+/-
3.34E+00 1.74E+01
+/-
3.08E+00 1.18E+01
+/-
2.80E+00 7.93E+00
+/-
2.56E+00 2.OOE+01
+/-
3.46E+00 3.13E+01
+/-
2.55E+00 1.80E+01
+/-
3.OOE+00 1.20E+01
+/-
2.89E+00 1.74E+01
+/-
3.45E+00 2.05E+01
+/-
2.59E+00 9.55E+00 Station 07
+/-
2.71 E+00
+/-
3.24E+00
+/-
3.08E+00
+/-
3.17E+00
+/-
3.06E+00
+/-
3.42E+00
+/-
3.12E+00
+/-
3.53E+00
+/-
3.60E+00
+/
3.56E+00
+/-
3.30E+00
+/-
3.61 E+00
+/-
3.24E+00
+/-
2.61E+00
+/-
4.10E+00
+/-
2.83E+00
+/-
3.22E+00
+/-
2.84E+00
+/-
2.75E+00
+/-
2.63E+00
+/-
3.53E+00
+/-
2.78E+00
+/-
2.99E+00
+/-
2.86E+00
+/-
3.36E+00
+/-
2.43E+00
+/
3.12E+00 MEAN 1.77E+01
+/-
3.17E+00 2.05E+01
+/-
3.30E+00 1.60E+01
+/-
3.09E+00 1.63E+01 38
Table 3-3 Air Particulate Gross Beta Radioactivity
[10-3 pCi/m 3]
page 4 of 4 Period Ending 07/06/10 1.49E+01 07/13/10 2.35E+01 07/21/10 1.77E+01 07/27/10 1.80E+01 08/04/10 1.20E+01 08/12/10 2.06E+01 08/18/10 2.21E+01 08/24/10 2.15E+01 08/31/10 1.97E+01 09/07/10 2.77E+01 09/14/10 1.46E+01 09/21/10 2.66E+01 09/28/10 2.55E+01 10/06/10 8.85E+00 10/12/10 2.13E+01 10/19/10 2.05E+01 10/26/10 2.50E+01 11/02/10 1.03E+01 11/09/10 1.07E+01 11/16/10 1.55E+01 11/23/10 2.14E+01 11/30/10 2.12E+01 12/07/10 7.91E+00 12/14/10 1.50E+01 12/21/10 2.17E+01 12/28/10 1.04E+01 MEAN 1.54E+01 Station Station 21I
+/-
2.86E+00 1.49E+01
+/-
3.19E+00 2.57E+01
+/-
3.20E+00 2.35E+01
+/-
3.25E+00 1.88E+01
+/-
2.83E+00 1.50E+01
+/-
3.37E+00 2.35E+01
+/-
3.20E+00 2.45E+01
+/-
3.57E+00 2.42E+01
+/-
3.37E+00 2.29E+01
+/-
3.61 E+00 3.OOE+01
+/-
3.04E+00 2.20E+01
+/-
3.68E+00 2.44E+01
+/-
3.31E+00 2.55E+01
+/-
2.50E+00 9.44E+00
+/-
3.89E+00 3.07E+01
+/-
3.18E+00 2.27E+01
+/-
3.53E+00 1.65E+01
+/-
2.87E+00 1.65E+01
+/-
2.90E+00 7.93E+00
+/-
2.36E+00 2.01E+01
+/-
3.10E+00 2.42E+01
+/-
2.93E+00 1.96E+01
+/-
2.79E+00 1.18E+01
+/-
2.74E+00 2.20E+01
+-
3.46E+00 2.28E+01
+/-
2.45E+00 1.40E+01
+/-
3.08E+00 1.75E+01 221
+/-
2.86E+00 1.88E+01
+/-
3.29E+00 2.16E+01
+/-
3.42E+00 1.94E+01
+/-
3.30E+00 1.90E+01 Station 23 Station 24*
Station 01A Station 05A 23 24*
01A 05A
+/-
2.97E+00
+/-
3.51 E+00
+/-
3.27E+00
+/-
3.70E+00
+/-
3.51E+00 "
+/-
3.70E+00
+/-
3.37E+00
+/-
3.50E+00
+/-
3.31E+00
+/-
2.53E+00
+/-
4.28E+00
+/-
3.28E+00
+/-
3.15E+00
+/-
3.17E+00
+/-
2.75E+00
+/-
2.63E+00
+/-
3.23E+00
+/-
2.84E+00
+/-
2.99E+00
+/-
3.09E+00
+/-
3.51 E+00
+/-
2.66E+00
+/-
3.21E+00 1.53E+01 2.50E+01 2.34E+01 2.18E+01 2.22E+01 3.44E+01 1.91E+01 1.38E+01 2.15E+01 6.46E+00 3.26E+01 1.85E+01 2.25E+01 1.31E+01 1.17E+01 2.15E+01 2.31E+01 1.69E+01 1.12E+01 1.13E+01 2.06E+01 1.04E+01
+/-
3.06E+00 1.78E+01
+/-
3.02E+00
+/-
3.10E+00 3.06E+01
+/-
3.49E+00
+/-
3.27E+00 2.21E+01
+/-
3.38E+00
+/-
3.31 E+00 2.06E+01
+/-
3.40E+00
+/-
2.98E+00 2.14E+01
+/-
3.24E+00
+/-
3.58E+00 2.33E+01
+/-
3.49E+00
+/-
3.25E+00 2.66E+01
+/-
3.37E+00
+/-
3.57E+00 2.59E+01
+/-
3.70E+00
+/-
3.50E+00 2.72E+01
+/-
3.74E+00
+/-
3.87E+00 3.60E+01
+/-
3.91 E+00
+/-
3.25E+00 2.81 E+01
+/-
3.66E+00
+/-
3.08E+00 2.91E+01
+/-
3.81E+00
+/-
3.17E+00 3.27E+01
+/-
3.58E+00
+/-
2.34E+00 1.25E+01
+/-
2.71 E+00
+/-
4.33E+00 3.34E+01
+/-
4.37E+00
+/-
3.10E+00 2.44E+01
+/-
3.36E+00
+/-
3.47E+00 1.97E+01
+/-
3.29E+00
+/-
3.01E+00 1.41E+01
+/-
3.06E+00
+/-
2.95E+00 1.20E+01
+/-
2.94E+00
+/-
2.71 E+00 2.42E+01
+/-
2.85E+00
+/-
3.14E+00 4.10E+01
+/-
3.97E+00
+/-
2.74E+00 1.89E+01
+/-
2.79E+00
+/-
2.95E+00 1.37E+01
+/-
3.08E+00
+/-
2.53E+00 2.45E+01
+/-
3.20E+00
+/-
3.34E+00 2.55E+01
+/-
3.64E+00
+/-
2.50E+00 1.31E+01
+/-
2.58E+00 2.49E+01 2.01E+01 1.55E+01 1.61E+01 2.40E+01 2.05E+01 1.87E+01 1.92E+01 2.87E+01 1.99E+01 2.35E+01 2.07E+01 9.41 E+00 3.37E+01 1.59E+01 2.25E+01 1.23E+01 1.03E+01 2.42E+01 2.11E+01 1.90E+01 1.24E+01 1.29E+01 2.40E+01 1.02E+01 1.56E+01
+/-
2.90E+00 1.43E+01
+/-
2.84E+00
+/-
3.25E+00 2.73E+01
+/-
3.35E+00
+/-
3.31E+00 2.23E+01
+/-
3.39E+00
+/-
3.11E+00 1.66E+01
+/-
3.19E+00
+/-
3.02E+00 1.64E+01
+/-
3.03E+00
+/-
3.53E+00 2.24E+01
+/-
3.44E+00
+/-
3.13E+00 2.10E+01
+/-
3.14E+00
+/-
3.42E+00 2.62E+01
+/-
3.74E+00
+/-
3.35E+00 2.82E+01
+/-
3.79E+00
+/-
3.66E+00 3.30E+01
+/-
3.80E+00
+/-
3.27E+00 2.08E+01
+/-
3.34E+00
+/-
3.49E+00 2.62E+01
+/-
3.66E+00
+/-
3.15E+00 2.74E+01
+/-
3.38E+00
+/-
2.48E+00 1.16E+01
+/-
2.65E+00
+/-
4.36E+00 3.20E+01
+/-
4.32E+00
+/-
3.04E+00 1.60E+01
+/-
2.97E+00
+/-
3.42E+00 1.75E+01
+/-
3.21E+00
+/-
2.97E+00 1.44E+01
+/-
3.07E+00
+/-
2.88E+00 1.11E+01
+/-
2.91E+00
+/-
2.85E+00 2.47E+01
+/-
2.88E+00
+/-
3.04E+00 2.38E+01
+/-
3.21 E+00
+/-
2.86E+00 2.67E+01
+/-
3.19E+00
+/-
3.02E+00 1.23E+01
+/-
3.01E+00
+/-
2.62E+00 1.55E+01
+/-
2.76E+00
+/-
3.56E+00 2.25E+01
+/-
3.49E+00
+/-
2.45E+00 1.11E+01
+/-
2.49E+00 1.64E+01
+/-
3.12E+00 2.OOE+01
+/-
3.28E+00 1.61E+01
+/-
3.11E+00 1.74E+01
+/-
3.16E+00 Mean - All Indicator Locations 1.70E+01
+/-
3.15E+00
- Control Station 39
Table 3-4 Airborne Iodine 1-131
[10-3 pCi/m 3]
page 1 of 4 Period Endino Station 01 Station I
02 01/05/10 01/12/10 01/19/10 01/28/10 02/05/10 02/09/10 02/16/10 02/23/10 03/02/10 03/09/10 03/16/10 03/23/10 03/31/10 04/06/10 04/14/10 04/20/10 04/27/10 05/04/10 05/11/10 05/19/10 05/25/10 06/02/10 06/08/10 06/15/10 06/22/10 06/29/10 3.65E+01 2.66E+01 1.48E+01 1.44E+01 4.98E+00 9.24E+00 4.78E+00 1.93E+01 7.66E+00 7.28E+00 1.76E+01 2.05E+01 2.12E+01 2.68E+01 2.03E+01 1.05E+01 2.50E+01 1.18E+01 2.58E+00 1.32E+01 1.07E+01 2.45E+01 1.57E+01 1.68E+01 5.54E+00 2.81E+01 3.70E+01 2.66E+01 2.69E+01 2.62E+01 9.03E+00 5.28E+00 8.73E+00 1.98E+01 1.78E+01 1.71E+01 3.01 E+01 2.04E+01 2.13E+01 2.71E+01 2.03E+01 2.46E+01 2.51E+01 2.76E+01 4.67E+00 1.31E+01 2.04E+01 4.45E+01 2.84E+01 1.68E+01 1.01E+01 2.79E+01 Station 03 3.70E+01 2.64E+01 2.70E+01 2.60E+01 9.09E+00 1.04E+01 8.97E+00 1.11E+01 1.71E+01 1.71E+01 2.99E+01 2.12E+01 2.06E+01 2.69E+01 2.04E+01 2.45E+01 2.51E+01 2.76E+01 4.67E+00 1.34E+01 1.93E+01 4.47E+01 2.82E+01 1.69E+01 1.01 E+01 2.80E+01 Station w04 2.04E+01 2.65E+01 2.69E+01 2.62E+01 9.07E+00 9.37E+00 8.91 E+00 1.98E+01 1.75E+01 1.71E+01 3.63E+01 2.09E+01 2.08E+01 2.77E+01 2.03E+01 2.46E+01 2.51E+01 2.76E+01 4.67E+00 1.32E+01 1.95E+01 4.49E+01 2.82E+01 1.69E+01 1.01E+01 2.79E+01 Station 1205 3.70E+01 2.99E+01 2.69E+01 2.62E+01 9.07E+00 9.18E+00 8.86E+00 1.98E+01 1.76E+01 1.71 E+01 3.OOE+01 2.06E+01 0.OOE+00 2.61E+01 4.53E+01 3.81E+01 Station S 06 3.94E+01 2.99E+01 1.05E+01 3.66E+01 4.59E+00 1.27E+01 9.68E+00 2.17E+01 9.52E+00 1.41E+01 3.00E+01 2.52E+01 1.89E+01 1.18E+01 1.83E+01 2.61 E+01 1.87E+01 2.33E+01 6.23E+00 1.24E+01 1.89E+01 5.26E+01 3.54E+01 2.42E+01 1.18E+01 2.77E+01 I
Station 07 3.94E+01 2.99E+01 2.47E+01 3.66E+01 1.08E+01 1.04E+01 9.64E+00 2.17E+01 2.24E+01 1.41E+01 3.32E+01 2.51E+01 1.90E+01 2.13E+01 1.01 E+01 2.61E+01 1.87E+01 2.33E+01 6.23E+00 1.24E+01 1.89E+01 5.23E+01 3.54E+01 2.42E+01 1.18E+01 2.77E+01 1.87E+01 2.76E+01 4.67E+00 1.24E+01 2.OOE+01 4.49E+01 2.82E+01 2.42E+01 1.01E+01 2.77E+01 40
Table 3-4 Airborne Iodine 1-131
[10-3 pCi/m3]
page 2 of 4 Period Ending Station 21 Station 22 Station 23 Station 24*
01/05/10 01/12/10 01/19/10 01/28/10 02/05/10 02/09/10 02/16/10 02/23/10 03/02/10 03/09/10 03/16/10 03/23/10 03/31/10 04/06/10 04/14/10 04/20/10 04/27/10 05/04/10 05/11/10 05/19/10 05/25/10 06/02/10 06/08/10 06/15/10 06/22/10 06/29/10 01/05/10 3.93E+01 3.OOE+01 2.46E+01 3.66E+01 1.07E+01 1.09E+01 9.51 E+00 2.17E+01 2.27E+01 1.41 E+01 3.33E+01 2.54E+01 1.91 E+01 2.13E+01 1.83E+01 2.62E+01 1.14E+01 2.33E+01 6.25E+00 1.24E+01 1.90E+01 5.22E+01 3.61 E+01 2.41 E+01 1.18E+01 2.77E+01 3.93E+01 3.93E+01 3.76E+01 3.77E+01 2.40E+01 2.47E+01 3.65E+01 1.07E+01 1.26E+01 9.68E+00 2.12E+01 2.27E+01 1.41 E+01 3.32E+01 2.53E+01 1.89E+01 2.12E+01 1.83E+01 2.62E+01 1.86E+01 2.33E+01 1.05E+01 7.1KE+00 1.90E+01 5.63E+01 3.59E+01 2.36E+01 1.18E+01 2.49E+01 3.93E+01 2.40E+01 2.46E+01 2.98E+01 1.07E+01 1.22E+01 9.83E+00 1.08E+01 2.26E+01 1.58E+01 3.33E+01 1.07E+01 1.48E+01 2.25E+01 1.11E+01 2.50E+01 2.16E+01 3.42E+01 1.21E+01 1.50E+01 2.39E+01 5.57E+01 4.85E+01 2.35E+01 1.11E+01 2.49E+01 3.76E+01 2.39E+01 2.76E+01 2.98E+01 2.18E+01 1.14E+01 1.02E+01 1.08E+01 1.94E+01 1.58E+01 3.63E+01 1.10E+01 1.43E+01 2.33E+01 2.54E+01 2.51E+01 2.15E+01 3.42E+01 1.21 E+01 1.55E+01 2.29E+01 5.59E+01 4.77E+01 7.19E+00 1.11E+01 2.49E+01 3.77E+01 Station J
2 01A 3.73E+01 2.40E+01 2.76E+01 2.97E+01 2.18E+01 2.69E+01 1.OOE+01 1.06E+01 2.01E+01 1.58E+01 3.66E+01 1.09E+01 1.48E+01 2.31E+01 2.53E+01 2.52E+01 2.15E+01 3.42E+01 1.21E+01 1.53E+01 2.32E+01 6.01E+01 4.83E+01 2.36E+01 1.11E+01 2.50E+01 3.73E+01 Station S
05A 3.77E+01 1.32E+01 2.76E+01 2.98E+01 2.18E+01 1.13E+01 1.01E+01 1.08E+01 1.96E+01 1.58E+01 3.63E+01 1.09E+01 1.44E+01 2.37E+01 2.53E+01 2.51E+01 2.15E+01 3.42E+01 1.21E+01 1.51E+01 2.38E+01 5.61E+01 4.77E+01 2.37E+01 1.11E+01 1.06E+01 3.77E+01 I
- Control Station 41
Table 3-4 Airborne Iodine 1-131
[10.3 pCi/m3]
page 3 of 4 Period Ending 07/08/09 07/13/10 07/21/10 07/27/10 08/04/10 08/12/10 08/18/10 08/24/10 08/31/10 09/07/10 09/14/10 09/21/10 09/28/10 10/06/10 10/12/10 10/19/10 10/26/10 11/02/10 11/09/10 11/16/10 11/23/10 11/30/10 12/07/10 12/14/10 12/21/10 12/28/10 Station 01 1.36E+01 2.26E+01 9.12E+00 8.91 E+00 2.14E+01 2.05E+01 9.60E+00 1.99E+01 3.10E+01 3.87E+01 2.99E+01 1.16E+01 3.70E+01 1.82E+01 4.65E+01 4.24E+01 2.66E+01 5.95E+01 4.16E+01 2.61E+01 6.82E+01 3.50E+01 1.17E+01 2.32E+01 2.64E+01 3.52E+01 Station 02 2.49E+01 2.26E+01 2.13E+01 1.07E+01 1.18E+01 2.04E+01 9.58E+00 2.06E+01 3.15E+01 3.83E+01 3.02E+01 2.68E+01 3.73E+01 3.28E+01 4.61E+01 4.25E+01 4.90E+01 5.94E+01 4.16E+01 6.41E+01 6.75E+01 3.54E+01 2.14E+01 2.32E+01 4.68E+01 3.57E+01 Station 03 2.49E+01 2.26E+01 2.14E+01 1.94E+01 2.15E+01 2.04E+01 9.55E+00 8.36E+00 3.14E+01 3.83E+01 3.04E+01 2.79E+01 3.57E+01 3.40E+01 4.63E+01 4.24E+01 4.72E+01 5.95E+01 4.13E+01 4.88E+01 6.86E+01 3.41 E+01 2.14E+01 2.31 E+01 4.79E+01 3.49E+01 Station 1204 2.50E+01 2.25E+01 2.14E+01 1.95E+01 2.14E+01 2.04E+01 9.59E+00 1.96E+01 3.16E+01 2.10E+01 3.04E+01 2.75E+01 3.62E+01 3.36E+01 4.63E+01 4.24E+01 4.78E+01 5.94E+01 4.15E+01 4.81E+01 6.84E+01 3.46E+01 2.14E+01 2.32E+01 4.85E+01 3.46E+01 Station 05 2.50E+01 2.44E+01 2.14E+01 1.95E+01 2.14E+01 1.25E+01 9.59E+00 1.96E+01 2.54E+01 3.83E+01 2.35E+01 2.72E+01 1.59E+01 3.32E+01 6.03E+01 6.08E+01 4.85E+01 5.92E+01 3.22E+01 4.47E+01 6.23E+01 1.92E+01 2.14E+01 2.43E+01 4.77E+01 5.35E+01 Station 2.E06 2.71 E+01 2.44E+01 2.14E+01 1.95E+01 1129E+01 1.90E+01 3.36E+01 1.43E+01 2.52E+01 1.85E+01 2.35E+01 2.61E+01 1.59E+01 1.87E+01 6.OOE+01 2.60E+01 4.27E+01 5.92E+01 3.22E+01 3.64E+01 6.21 E+01 3.87E+01 1.78E+01 2.43E+01 5.40E+01 5.39E+01 Station J2 07 2.71E+01 2.45E+01 2.14E+01 2.49E+01 3.03E+01 1.90E+01 3.35E+01 1.42E+01 2.52E+01 4.35E+01 2.35E+01 2.60E+01 2.92E+01 4.34E+01 6.02E+01 6.10E+01 4.30E+01 3.26E+01 3.22E+01 3.64E+01 6.20E+01 3.88E+01 1.78E+01 2.43E+01 5.34E+01 5.45E+01
-I 42
Table 3-4 Airborne Iodine 1-131
[10.3 pCi/m 3]
page 4 of 4 Period Ending 07/08/09 07/13/10 07/21/10 07/27/10 08/04/10 08/12/10 08/18/10 08/24/10 08/31/10 09/07/10 09/14/10 09/21/10 09/28/10 10/06/10 10/12/10 10/19/10 10/26/10 11/02/10 11/09/10 11/16/10 11/23/10 11/30/10 12/07/10 12/14/10 12/21/10 12/28/10 I
Station 21 2.70E+01 2.46E+01 2.13E+01 2.48E+01 3.03E+01 1.91 E+01 3.37E+01 1.44E+01 2.48E+01 4.37E+01 2.34E+01 2.62E+01 2.90E+01 4.37E+01 6.06E+01 6.07E+01 4.24E+01 5.93E+01 3.22E+01 2.OOE+01 6.25E+01 3.84E+01 1.78E+01 2.43E+01 5.44E+01 5.35E+01 I
Station 22 2.70E+01 2.43E+01 2.13E+01 2.48E+01 3.03E+01 1.91 E+01 3.34E+01 1.45E+01 1.06E+01 4.37E+01 1.29E+01 2.62E+01 2.89E+01 4.37E+01 5.35E+01 6.07E+01 4.24E+01 5.93E+01 3.73E+01 3.64E+01 3.01 E+01 3.84E+01 1.78E+01 3.19E+01 5.44E+01 4.74E+01 Station S 23 2.19E+01 2.43E+01 2.66E+01 2.48E+01 3.03E+01 2.52E+01 2.92E+01 2.24E+01 1.33E+01 4.34E+01 2.66E+01 2.71E+01 3.02E+01 4.30E+01 5.30E+01 4.35E+01 4.88E+01 6.90E+01 3.73E+01 3.90E+01 4.82E+01 3.95E+01 1.80E+01 1.36E+01 4.95E+01 4.87E+01 I
Station 24*
2.20E+01 2.42E+01 2.67E+01 1.79E+01 2.64E+01 2.51E+01 2.91E+01 2.19E+01 1.35E+01 4.30E+01 5.67E+01 2.79E+01 2.92E+01 1.62E+01 5.32E+01 4.33E+01 4.76E+01 6.90E+01 3.70E+01 3.90E+01 5.OOE+01 3.84E+01 1.80E+01 3.19E+01 5.13E+01 1.99E+01 I
I Station 01A 2.19E+01 2.43E+01 2.67E+01 1.77E+01 2.64E+01 2.52E+01 2.91E+01 2.25E+01 1.32E+01 4.36E+01 2.65E+01 2.70E+01 3.04E+01 1.57E+01 5.29E+01 4.47E+01 4.79E+01 6.90E+01 3.74E+01 3.89E+01 4.80E+01 3.97E+01 1.80E+01 3.19E+01 5.10E+01 4.76E+01 Station S
05A 2.20E+01 1.48E+01 2.67E+01 1.79E+01 2.64E+01 2.51E+01 2.91 E+01 2.21 E+01 1.35E+01 4.32E+01 2.68E+01 2.76E+01 2.94E+01 1.61 E+01 2.93E+01 4.33E+01 4.81 E+01 6.88E+01 1.59E+01 3.90E+01 4.92E+01 3.88E+01 1.80E+01 3.19E+01 5.08E+01 4.74E+00 I
- Control Station 43
Table 3-5 Airborne Particulate Gamma Spectra
[10.3 pCi/m3]
page 1 of 2 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*
I Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*
Be-7 1.96E+02
+1-4.44E+01 1.35E+02
+/-
3.40E+01 1.61 E+02
+/-
4.17E+01 1.74E+02
+/-
3.36E+01 1.36E+02
+/-
3.13E+01 2.07E+02
+/-
4.15E+01 1.56E+02
+/-
3.40E+01 1.03E+02
+/-
3.60E+01 1.54E+02
+/-
3.11E+01 1.21E+02
+/-
2.84E+01 1.82E+02
+/-
3.45E+01 1.60E+02
+/-
3.12E+01 1.96E+02
+/-
3.74E+01 Be-7 2.01 E+02
+/-
4.43E+01 1.40E+02
+/-
3.85E+01 1.75E+02
+/-
4.22E+01 1.71 E+02
+/-
4.21E+01 1.73E+02
+/-
4.63E+01 1.74E+02
+/-
4.03E+01 2.26E+02
+/-
4.40E+01 1.90E+02
+/-
3.55E+01 1.88E+02
+/-
3.29E+01 1.61E+02
+/-
4.31E+01 1.34E+02
+/-
3.71E+01 1.94E+02
+/-
3.50E+01 1.66E+02
+/-
4.23E+01 1.70E+00 1.59E+00 1.83E+00 1.28E+00 1.32E+00 1.86E+00 1.31 E+00 1.46E+00 1.35E+00 1.27E+00 1.64E+00 1.42E+00 1.66E+00 1.94E+00 2.19E4+00 1.83E+00 2.12E+00 1.77E+00 1.97E+00 1.47E+00 1.80E+00 2.20E+00 2.20E+00 1.45E+00 1.73E+00 1.91 E+00 I
Cs-1 37**
1.71 E+00 1.14E+00 1.76E+00 1.65E+00 1.38E+00 1.88E+00 1.13E+00 1.38E+00 1.51E+00 1.26E+00 1.62E+00 1.15E+00 1.69E+00 Cs-137**
2.20E+00 1.67E+00 2.07E+00 2.OOE+00 2.03E+00 1.47E+00 2.46E+00 1.81E+00 1.81E+00 1.69E+00 1.29E+00 1.39E+00 1.84E+00 I
Quarter 1 Quarter 2 I
Sr-89 5.75E+00 5.87E+00 5.62E+00 6.68E+00 6.57E+00 7.03E+00 7.23E+00 7.19E+00 6.67E+00 5.99E+00 6.80E+00 6.57E+00 5.54E+00 Sr-90 1.88E+00 1.37E+00 1.70E+00 2.23E+00 2.66E+00 2.44E+00 2.16E+00 3.14E+00 2.43E+00 1.85E+00 2.OOE+00 1.84E+00
.7E0 44
[10-3 pCi/m 3]
page 2 of 2 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*
MEAN Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*
Be-7 1.25E+02
+1-2.99E+01 1.29E+02
+1-2.56E+01 1.58E+02
+/-
3.08E+01 1.50E+02
+/-
2.38E+01 1.57E+02
+/-
3.06E+01 1.45E+02
+/-
3.20E+01 1.40E+02
+/-
2.56E+01 1.68E+02
+/-
3.29E+01 1.13E+02
+/-
2.84E+01 1.35E+02
+/-
3.23E+01 1.25E+02
+/-
2.78E+01 1.39E+02
+/-
2.34E+01 1.62E+02
+/-
2.98E+01 Be-7 1.33E+02
+/-
2.68E+01 1.30E+02
+/-
2.41E+01 1.21E+02
+/-
2.30E+01 1.20E+02
+1-2.32E+01 1.26E+02
+1-2.68E+01 1.27E+02
+/-
2.40E+01 1.39E+02
+/-
2.98E+01 1.35E+02
+/-
2.83E+01 1.14E+02
+/-
2.69E+01 1.15E+02
+/-
2.32E+01 1.63E+02
+/-
2.86E+01 1.34E+02
+/-
2.50E+01 1.17E+02
+/-
2.55E+01 I
Quarter 3 Cs-134"*
1 1
1 1
1 1
1 1
1 1
1 1
1
.69E+00
.63E+00
.86E+00
.30E+00
.45E+00
.61E+00
.72E+00
.56E+00
.46E+00
.55E+00
.81 E+00
.47E+00
.29E+00 i
Cs-137**
1.46E+00 1.48E+00 1.49E+00 1.30E+00 1.46E+00 1.46E+00 1.48E+00 9.49E-01 1.38E+00 1.61 E+00 1.58E+00 1.05E+00 1.28E+00 1.20E+00 8.22E-01 1.26E+00 1.20E+00 9.61E-01 9.66E-01 1.74E+00 1.33E+00 1.03E+00 1.04E+00 1.02E+00 1.26E+00 5.10E-01 I
Cs-1 34**
1.43E+00 1.19E+00 1.11E+00 1.06E+00 7.70E-01 1.05E+00 1.11E+00 1.43E+00 1.45E+00 1.06E+00 9.50E-01 1.29E+00 6.57E-01 MEANS Be-7 1.64E+02
+1-3.64E+01 1.34E+02 3.06E+01 1.54E+02 3.44E+01 1.54E+02
+1-3.07E+01 1.48E+02 3.38E+01 1.63E+02 3.45E+01 1.65E+02
+/
3.34E+01 1.49E+02 3.32E+01 1.42E+02 2.98E+01 1.33E+02
+/
3.18E+01 1.51E+02 3.20E+01 1.57E+02
+/
2.87E+01 1.60E+02
+/
3.38E+01 Quarter 4 I
45
- Control Station
1.51 E+02
+/-
3.24E+01 Table 3-6 Soil
[pCi/kg]
page 1 of 3 Sample Date 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 Stton I
01 02 03 04 05 05A 06 07 21 22 23 24*
Sr-89 Acivity Conc 2 Sigma Cs-i 37 Acivity Cone 2 Sigma 1.79E+02
+1 1.18E+02
+1 4.01 E+02
+1 1.91 E+02
+-
1.52E+02
+1 4.18E+02
+-
9.72E+01
+1 5.27E+01
+1 1.46E+02
+-
1.49E+02
+-
8.42E+01
+1 MDC 1.04E+02 1.28E+02 8.91 E+01 1.21E+02 9.41E+01 9.87E+01 1.18E+02 8.88E+01 8.77E+01 1.15E+02 1.06E+02 1.12E+02 MDC 7.54E+01 1.09E+02 5.27E+01 7.80E+01 7.28E+01 4.69E+01 9.62E+01 8.36E+01 8.09E+01 6.04E+01 6.37E+01 5.48E+01 Sr-90 Acivity Conc 2 Sigma MDC 5.51 E+01 7.30E+01 3.93E+01 5.91 E+01 4.85E+01 3.67E+01 5.69E+01 4.97E+01 3.72E+01 4.63E+01 4.31 E +01 5.63E+01 Acivity Conc 2.13E+03 7.98E+03 9.11E+03 3.98E+03 8.85E+03 6.75E+03 1.50E+04 4.41E+03 9.89E+03 1.72E+04 2.27E+04 5.23E+03 I
K-40 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.74E+03 1.64E+03 8.30E+02 8.42E+02 1.15E+03 1.06E+03 1.48E+03 1.38E+03 1.07E+03 2.02E+03 1.73E+03 9.33E+02 Cs-134 Acivity Cone 2 Sigma 7.52E+01
+/-
3.09E+02
+/-
3.27E+02
+/-
MDC 6.33E+01 4.69E+01 3.75E+01 5.88E+01 5.45E+01 5.45E+02 6.39E+01 6.04E+01 4.48E+01 7.45E+01 6.95E+01 7.10E+01 MDC 1.63E+02 1.49E+02 1.64E+02 1.58E+02 1.57E+02 2.24E+02 1.79E+02 1.48E+02 2.43E+02 2.06E+02 2.45E+02 Sample Date 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10 7/6/10
.7/6/10 7/6/10 7/6/10
- Control Station Station I
01 02 03 04 05 05A 06 07 21 22 23 24*
Acivity Conc 2.68E+03 3.02E+03 1.95E+03 1.81E+03 2.91 E+03 1.96E+03 1.26E+03 4.63E+03 2.79E+03 Ra-226 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.53E+03 1.42E+03 1.11E+03 1.12E+03 1.12E+03 1.77E+03 1.70E+03 1.97E+03 9.25E+02 2.11E+03 2.28E+03 1.58E+03 Acivity Conc 9.14E+02 6.38E+02 1.74E+03 7.47E+02 1.14E+03 9.84E+02 9.44E+02 1.02E+03 4.51 E+02 2.01 E+03 1.16E+03 1.53E+03 I
Th-228 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.37E+02 1.24E+02 1.31E+02 9.34E+01 1.14E+02 1.36E+02 1.79E+02 1.68E+02 7.71 E+01 1.70E+02 1.30E+02 1.23E+02 Acivity Conc 1.09E+03 6.84E+02 1.22E+03 5.38E+02 1.13E+03 1.37E+03 1.21E+03 4.41 E+02 1.90E+03 9.30E+02 1.21E+03 l
Th-232 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
46
Table 3-6 Sample Date 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 11/9/10 Station I
01 02 03 04 05 05A 06 07 21 22 23 24*
MEANS Indicators Control Sample Station Date 11/9/10 01 11/9/10 02 11/9/10 03 11/9/10 04 11/9/10 05 11/9/10 05A 11/9/10 06 11/9/10 07 11/9/10 21 11/9/10 22 11/9/10 23 11/9/10 24*
MEANS Indicator Control Sr-89 Acivity Conc 2 Sigma Cs-i 37 Acivity Conc 2 Sigma 6.20E+02
+/-
3.76E+02
+/-
7.32E+02
+/-
1.71 E+02
+/-
1.67E+02
+/-
4.07E+02
+I-5.85E+02
+/-
1.31 E+02
+/-
3.62E+02
+/-
2.83E+02
+/-
2.23E+02
+1-MDC 7.73E+02 6.85E+02 6.15E+02 6.47E+02 7.72E+02 7.04E+02 6.44E+02 5.71 E+02 5.94E+02 6.59E+02 7.10E+02 7.53E+02 Acivity Conc Soil
[pCi/kg]
+<
+<
+<
+<
+<
+<
+<
+<
+<
+/-
MDC 4.44E+01 4.15E+01 4.12E+01 4.31 E+01 4.47E+01 4.57E+01 5.25E+01 3.64E+01 3.84E+01 3.79E+01 3.09E+01 3.55E+01 Acivity Conc 1.72E+04 9.51E+03 3.99E+03 9.OOE+03 1.46E+04 8.36E+03 1.05E+04 5.77E+03 1.17E+04 1.56E+04 2.40E+04 2.78E+03 1.08E+04 4.01E+03 K-40 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+1-
+/-
+/-
+/-
Th-228 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.52E+03 1.44E+03 8.09E+02 1.37E+03 1.55E+03 1.15E+03 1.57E+03 1.24E+03 1.20E+03 1.66E+03 1.54E+03 8.94E+02 1.36E+03 9.14E+02 Cs-134 Acivity Conc 2 Sigma 2.37E+02
+1 MDC 5.75E+01 6.55E+01 5.52E+01 6.62E+01 6.42E+01 6.33E+01 7.21 E +01 7.27E+01 6.21 E+01 8.07E+01 5.58E+01 5.14E+01 2.37E+02 page 2 of 3
-I I
I I
MDC 6.65E+01 1.05E+02 7.03E+01 1.15E+02 7.72E+01 7.94E+01 1.09E+02 9.07E+01 8.76E+01 1.08E+02 6.19E+01 8.41 E+01 8.12E+01 6.95E+01 Acivity Conc 1.73E+03 2.37E+03 2.OOE+03 2.47E+03 2.02E+03 2.21E+03 1.84E+03 3.66E+03 2.25E+03 3.01 E+03 2.40E+03 2.90E+03 MDC 1.07E+03 1.65E+03 1.26E+03 1.65E+03 1.33E+03 1.66E+03 1.46E+03 1.75E+03 1.36E+03 1.76E+03 1.14E+03 1.39E+03 1.51E+03 1.49E+03 Acivity Conc 1.06E+03 4.86E+02 6.04E+02 1.19E+03 1.27E+03 5.90E+02 2.33E+03 1.36E+03 5.90E+02 1.69E+03 1.93E+03 1.01E+03 1.13E+03 1.27E+03 MDC 9.68E+01 9.87E+01 9.76E+01 1.28E+02 1.18E+02 1.43E+02 1.67E+02 1.31E+02 9.73E+01 1.43E+02 1.13E+02 9.93E+01 1.27E+02 1.11E+02 Acivity Conc 8.57E+02 3.90E+02 3.87E+02 9.94E+02 1.29E+03 8.19E+02 2.09E+03 1.19E+03 4.94E+02 1.75E+03 1.93E+03 9.68E+02 1.08E+03 1.09E+03 Th-232 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+1-
+/-
MDC 1.73E+02 1.72E+02 1.26E+02 2.62E+02 1.70E+02 1.63E+02 2.79E+02 2.56E+02 1.38E+02 2.78E+02 1.68E+02 1.84E+02 1.89E+02 2.15E+02 47
- Control Station Table 3-6 Soil
[pCi/kg]
Station MeanI page 3 of 3 Station Sr-89 Acivity Conc 2 Sigma I
Sr-90 MDC Acivity Conc 2 Sigm a MDC 01 02 03 04 05 05A 06 07 21 22 23 24*
Acivity Conc 9.67E+03 8.75E+03 6.55E+03 6.49E+03 1.17E+04 7.56E+03 1.28E+04 5.09E+03 1.08E+04 1.64E+04 2.34E+04 4.01 E+03 K-40 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.63E+03 1.54E+03 8.20E+02 1.11E+03 1.35E+03 1.11E+03 1.53E+03 1.31 E+03 1.14E+03 1.84E+03 1.64E+03 9.14E+02 Cs-134 Acivity Conc 2 Sigma MDC 7.52E+01 3.09E+02 3.27E+02
+/-
3.75E+01
+/-
5.45E+02
+/-
6.95E+01 Station 01 02 03 04 05 05A 06 07 21 22 23 24*
Cs-137 Acivity Conc 2 Sigma 4.OOE+02 2.47E+02 5.67E+02 1.81E+02 1.52E+02 2.93E+02 2.52E+02 3.19E+02 1.46E+02 1.40E+02 2.23E+02
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-1.
6.
9.
7.
MDC Acivity Conc 2.21 E+03 07E+02 2.37E+03 15E+01 2.51E+03 65E+01 1.95E+03 50E+01 2.14E+03 4.69E+01 1.03E+02 8.72E+01 8.43E+01 6.04E+01 6.28E+01 6.95E+01 Ra-226 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.30E+03 1.65E+03 1.19E+03 1.12E+03 1.23E+03 1.58E+03 1.86E+03 1.14E+03 1.94E+03 1.14E+03 1.49E+03 Acivity Conc 9.87E+02 5.62E+02 1.17E+03 9.69E+02 1.21E+03 7.87E+02 1.64E+03 1,.19E+03 5.21 E+02 1.85E+03 1.55E+03 1.27E+03 l
Th;228 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.17E+02 1.11E+02 1.14E+02 1.11E+02 1.16E+02 1.40E+02 1.73E+02 1.50E+02 8.72E+01 1.57E+02 1.22E+02 1.11E+02 Acivity Conc 9.74E+02 5.37E+02 8.04E+02 7.66E+02 1.21E+03 8.19E+02 1.73E+03 1.20E+03 4.68E+02 1.83E+03 1.43E+03 1.09E+03 Th-232 2 Sigma
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
MDC 1.68E+02 1.61 E+02 1.45E+02 2.10E+02 1.64E+02 1.63E+02
.2.52E+02 2.18E+02 1.43E+02 2.61E+02 1.87E+02 2.15E+02 2.47E+03 2.09E+03 1.55E+03 4.15E+03 2.25E+03 2.90E+03
- Control Station 48
Table 3-7 Precipitation Gross Beta
[pCi/L]
page 1 of 2 Sampling Date I
Gross Beta I
Rainfall(inches) 01/26/10 2.35E+01
+/-
2.21E+00 2.31 02/23/10 2.20E+00
+/-
1.27E+00 2.37 03/31/10 2.46E+00
+/-
1.26E+00 4.62 04/27/10 2.90E+00
+/-
1.29E+00 1.66 05/25/10 2.77E+00
+/-
1.17E+00 2.09 06/29/10 1.70E+00 3.02 07/27/10 2.OOE+00
+/-
1.26E+00 1.50 08/31/10 6.51 E+00
+/-
1.35E+00 4.47 09/28/10 3.66E+00
+/-
1.30E+00 0.92 10/26/10 1.67E+00 5.51 11/30/10 1.96E+00
+/-
1.11E+00 3.25 12/28/10 3.80E+00
+/-
1.81E+00 1.92 Mean 5.18E+00
+/-
1.45E+00 Total 33.64
Table 3-7 Precipitation Gamma Spectra
[pCi/L]
Fe-59 page 2 of 2 Sampling Location Be-7 Mn-54 Co-58 Co-60 O]A 06/29/10 3.78E+01 12/28/10
+/-
2.64E+01 4.87E+01 4.74E-01 1.50E+00 4.18E+00 1.45E+01 1.08E+00 3.55E+00 4.14E-01 1.21E+00 01A 06/29/10 12/28/10 01A 06/29/10 12/28/10 Sampling Location Zn-65 I
Zr-95 I
Nb-95 I
Cs-134 I
Cs-137 I
1.01E+00 2.19E+00 1.36E+00 3.64E-01 4.37E-01 2.95E+00 6.74E+00 3.96E+00 1.22E+00 1.23E+00 Ba-140 I
La-140 I1-131 I
Th-228 I
Th-232 I
1.11E+03 2.52E+03 2.78E+02 8.30E+02 MEAN Fe-59 1.72E+04 3.22E+04 1.08E+00 2.41 E+00 4.49E+00
+/-
2.86E+00 0.OOE+00 Be-7 Mn-54 Co-58 Co-60 O]A 3.78E+01
+/-
3.76E+01 01A 01A Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-137 I
Ba-140 Law140 1-131 I
Th-228 I
Th-232 I
4.49E+00
+/-
2.86E+00 50
Table 3-8 Milk Gamma Spectra & Strontium
[pCi/L]
page 1 of 1 Sampling Date 01/19/10 02/16/10 03/16/10 04/20/10 1.49E+03 1.45E+03 1.52E+03 1.27E+03 K-40
+/-
1.49E+02
+/-
1.25E+02
+-
1.50E+02
+/
1.16E+02 Sr-89 I
Sr-90 I
1-i31*
1
[a]
[a]
4.37E+00
[a]
[a]
[a]
[a]
6.74E-01 6.13E-01 5.90E-01 7.80E-01 Cs-134*
7.41 E+00 1.97E+00 5.65E+00 4.81 E+00 Cs-137*
8.OOE+00 2.24E+00 6.51E+00 5.26E+00 Ba-140*
4.42E+01 1.20E+01 3.96E+01 2.36E+01 Station 12 S
La-140*
9.18E+00 4.15E+00 1.23E+01 5.92E+00 1.17E+00 Dairy ceased operations in May 2010.
Sta. Mean Sampling Date 05/19/10 06/15/10 07/21/10 08/18/10 09/21/10 10/19/10 11/19/10 12/17/09 1.30E+03 1.16E+03 1.26E+03 1.47E+03 1.22E+03 1.25E+03 1.44E+03 1.30E+03 K-40 Sr-89 I
Sr-90 I
1.03E+02 1.62E+02 6.OOE+01 1.31E+02 1.34E+02 1.43E+02 1.59E+02 1.19E+02 1.26E+02 1.29E+02
[a]
[a]
[a]
[a]
3.28E+00 2.33E+00 3.76E+00 4.96E+00
[a]
[a]
[a]
[a]
1.43E+03
+/-
1.35E+02 1.59E+00 1.06E+00 8.44E-01 1.23E+00 1-131*
9.OOE-01 7.27E-01 6.05E-01 8.35E-01 5.51E-01 8.33E-01 7.03E-01 4.33E-01 I
Cs-i134*
4.01E+00 8.42E+00 2.55E+00 4.85E+00 6.26E+00 5.24E+00 5.58E+00 4.66E+00 Cs-1 37*
4.18E+00 8.83E+00 2.86E+00 4.41 E+00 7.43E+00 6.55E+00 5.98E+00 4.99E+00 Ba-140*
4.76E+01 4.47E+01 1.31E+01 3.58E+01 4.29E+01 2.59E+01 2.74E+01 3.59E+01 Station 12A S
La-140*
1.31E+01 1.26E+01 3.45E+00 8.66E+00 7.83E+00 8.61E+00 1.03E+01 1.03E+01 I
Sta. Mean 1.30E+03 Total 1.34E+03 Mean
+/-
+/-
[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.
51
Table 3-9 Food and Vegetation Gamma Spectra
[pCi/kg]
page 1 of 2 Samplina Sampling Location Date I
Be-7 I
K-40 I
1-131
- Cs-134*
Cs-137*
14A 05/11/10 2.11E+02 7.31E+03
+/-
5.70E+02 3.34E+01 1.83E+01 2.06E+01 06/08/10 3.90E+02
+/-
1.56E+02 4.76E+03
+/-
3.75E+02 3.01E+01 1.47E+01 1.45E+01 07/13/10 1.11E+03
+/-
2.61E+02 4.69E+03
+/-
5.17E+02 3.59E+01 2.65E+01 3.02E+01 08/10/10 7.99E+02 9.56E+03
+/-
1.54E+03 2.57E+01 5.81E+01 6.17E+01 09/14/10 1.13E+03
+/-
5.14E+02 8.18E+03
+/-
9.60E+02 4.78E+01 4.06E+01 4.83E+01 10/12/10 2.71E+03
+/-
1.01E+02 4.25E+03
+/-
1.60E+02 4.05E+01 6.31E+00 6.83E+00 Mean 1.06E+02
+/-
4.70E+01 6.46E+03
+/-
5.89E+02
+/-
+/-
+/-
Sampling Sampling Location Date>
I Be-7 I
K-40 I
-131 I
Cs134*
I Cs-37*
15 05/11/10 2.58E+02 6.50E+03
+/-
6.38E+02 3.33E+01 2.49E+01 2.93E+01 06/08/10 7.18E+02
+/-
1.28E+02 7.66E+03
+/-
2.91E+02 3.13E+01 1.20E+01 1.30E+01 07/13/10 4.76E+02
+/-
2.17E+02 7.05E+03
+/-
6.35E+02 3.72E+01 2.63E+01 3.08E+01 08/10/10 7.56E+02
+/-
5.52E+02 8.39E+03
+/-
1.OOE+03 2.58E+01 4.94E+01 5.61E+01 09/14/10 4.38E+02 5.94E+03
+/-
7.63E+02 5.99E+01 3.98E+01 3.95E+01 10/12/10 1.48E+03
+/-
7.08E+01 4.67E+03
+/-
1.35E+02 2.97E+01 5.34E+00 5.84E+00 Mean 8.58E+02
+/-
2.42E+02 6.70E+03
+/-
4.95E+02
+/-
+/-
+/-
Sampling Sampling Location Date I
Be-7 I
K-40 I
-13I Cs 134*
I Cs-37*
16-*
- Control Station 05/11/10 06/08/10 07/13/10 08/10/10 09/14/10 10/12/10 3.17E+02 6.64E+02 7.38E+02 5.44E+02 7.33E+02 1.26E+03 1.85E+02 1.05E+02 2.80E+02 4.56E+02 2.85E+02 5.81E+01 5.59E+03 1.07E+04 5.28E+03 4.93E+03 3.17E+03 5.20E+03 5.53E+02 3.56E+02 5.24E+02 7.83E+02 4.99E+02 1.37E+02 4.58E+01 3.07E+01 4.92E+01 3.19E+01 3.10E+01 3.65E+01 2.06E+01 1.24E+01 2.87E+01 4.35E+01 2.33E+01 3.33E+00 2.26E+01 1.35E+01 2.90E+01 4.43E+01 2.35E+01 3.99E+00 Mean
+/-
1.96E+02 5.81E+03
+/-
4.07E+02
+/-
+/-
+/-
52
Table 3-9 Food and Vegetation Gamma Spectra page 2 of 2
[pCi/kg]
K-40 Sampling Location Sampling Date I
Be-7 I
I 1-131*
I Cs-134*
I Cs-1 37*
23 05/11/10 06/08/10 07/13/10 08/10/10 09/14/10 10/12/10 Mean Sampling Date
- 7.31E+02
+/-
1.65E+03
+/-
1.24E+03
+/-
2.81 E+03
+/-
1.69E+03
+/-
1.62E+03
+/-
1.85E+02 2.15E+02 2.24E+02 5.11E+02 2.21 E+02 9.86E+01 7.25E+03 5.75E+03 3.64E+03 2.92E+03 2.52E+03 3.75E+03 3.21 E+02 3.84E+02 4.49E+02 5.67E+02 3.98E+02 1.50E+02 2.93E+01 2.82E+01 5.66E+01 2.61E+01 4.20E+01 3.67E+01 2.06E+01 1.54E+01 2.43E+01 5.79E+01 1.97E+01 5.78E+00 1.99E+01 1.74E+01 3.24E+01 5.93E+01 2.45E+01 6.29E+00 2.47E+02 4.31E+03
+/-
3.24E+02 Sampling Location Be-7 K-40 1-131*
Cs-134*
I Cs-1 37*
26 05/11/10 06/08/11 0713/10 08/10/10 09/14/10 10/12/10 4.92E+02 1.46E+03 7.55E+02 1.41E+03 3.82E+02 1.69E+03 2.01 E+02 1.44E+02 3.43E+02 5.17E+02 2.26E+02 7.72E+01 6.60E+03 4.74E+03 5.68E+03 4.24E+03 2.08E+03 2.58E+03 6.29E+02 2.67E+02 7.30E+02 1.02E+03 3.57E+02 1.19E+02 3.49E+01 2.98E+01 3.92E+01 3.68E+01 4.01E+01 3.56E+01 2.25E+01 1.32E+01 3.28E+01 5.89E+01 2.16E+01 5.46E+00 2.27E+01 1.49E+01 4.08E+01 7.46E+01 2.39E+01 5.80E+00 Mean 1.03E+03
+/-
2.515E+02 4.32E+03 1.26E+03
+/-
2.55E+02 4.91 E+03
+/-
4.46E+02
+/-
3.97E+02
+/-
+/-
+/-
+/-
+/-
+/-
Indicator locations
Table 3-10 Well Water Gamma Spectra, Strontium, and Tritium
[pCi/L]
page 1 of 1 Station 01A Zn-65 Sampling Date H-3 Sr-89 Sr-90 Mn-54 I
Fe-59 Co-58 I
Co-60 03/31/10 06/29/10 09/28/10 12/28/10 6.26E+02 7.12E+02 1.69E+02 4.02E+02
[a]
[a]
[a]
3.23E+00
[a]
[a]
[a]
6.24E-01 3.48E+00 1.81E+00 2.60E+00 2.49E+00 6.24E+00 4.56E+00 5.58E+00 5.84E+00 3.73E+00 2.10E+00 3.06E+00 2.51 E+00 3.17E+00 1.98E+00 2.63E+00 2.53E+00 6.82E+00 3.99E+00 5.60E+00 4.41 E+00 Mean Sampling Date Zr-95 Nb-95 1-131 Cs-134 1
Cs-137 I
Ba-140 I
La-140 I
03/31/10 06/29/10 09/28/10 12/28/10 6.57E+00 3.51 E+00 5.32E+00 4.91 E+00 3.85E+00 2.16E+00 3.17E+00 2.92E+00 5.69E-01 6.70E-01 7.13E-01 7.19E-01 2.97E+00 1.86E+00 2.73E+00 2.46E+00 3.32E+00 1.97E+00 2.79E+00 2.68E+00 2.22E+01 1.31 E+00 1.97E+01 1.72E+01 8.48E+00 4.58E+00 6.47E+00 6.46E+00 Mean
[a] Sr-89/90 analyses performed on the second quarter sample.
54
Table 3-11 River Water Gamma Spectra, Strontium, and Tritium
[pCi/L]
page 1 of 1 Sampling Date H-3*
Sr-89 Sr-90 I
Mn-54*
Fe-59*
I Co-58*
I Station 11 Co-60*
I Zn-65*
01/12/10 02/15/10 03/16/10 04/13/10 05/10/10 06/14/10 07/12/10 08/16/10 09/14/10 10/10/10 11/16/10 12/13/10 MEAN Sampling Date
[a]
[a]
4.66E+03
+/-
[a]
(a]
3.77E+03
+/-
[a]
[a]
3.36E+03
+/-
[a]
[a]
2.25E+03
+/-
3.51E+03
+/-
Zr-95*
9.21E+02 7.44E+02 5.82E+02 7.34E+02 7.45E+02
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
3.59E+00
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
6.25E-01 3.33E+00 4.49E+00 4.33E+00 1.70E+00 2.84E+00 3.78E+00 4.66E+00 4.05E+00 4.20E+00 1.82E+00 4.71 E+00 3.69E+00 Cs-134*
9.03E+00 8.98E+00 8.49E+00 4.41 E+00 6.81 E+00 6.83E+00 1.18E+01 8.85E+00 9.05E+00 3.93E+00 8.77E+00 9.04E+00 Cs-137*
4.14E+00 3.60E+00 3.58E+00 2.03E+00 3.16E+00 3.52E+00 5.01E+00 4.78E+00 3.06E+00 1.90E+00 4.14E+00 4.55E+00 Ba-140*
- 3.76E+00
- 4.39E+00
- 3.90E+00
- 1.74E+00
- 2.57E+00
- 3.07E+00
- 5.55E+00
- 4.30E+00
- 4.80E+00
- 1.80E+00
- 4.58E+00
- 3.71 E+00 La-140*
7.56E+00 7.98E+00 7.34E+00 3.54E+00 6.14E+00 8.57E+00 9.80E+00 8.67E+00 9.14E+00 3.69E+00 7.94E+00 8.96E+00 Nb-95*
I 1-131*
I 01/12/10 02/15/10 03/16/10 04/13/10 05/10/10 06/14/10 07/12/10 08/16/10 09/14/10 10/10/10 11/16/10 12/13/10 MEAN
- LLD identified in ODCM 6.43E+00 7.62E+00 7.11 E+00 3.36E+00 5.38E+00 6.22E+00 6.99E+00 7.38E+00 6.56E+00 3.43E+00 7.28E+00 7.83E+00 4.21 E+00 5.OOE+00 4.70E+00 2.07E+00 3.27E+00 4.42E+00 6.43E+00 4.43E+00 5.OOE+00 2.16E+00 4.72E+00 4.42E+00 5.96E-01 7.47E-01 5.77E-01 5.36E-01 6.57E-01 8.34E-01 6.40E-01 9.34E-01 1.OOE+00 8.74E-01 5.81E-01 5.56E-01 3.51 E+00 4.18E+00 3.77E+00 1.66E+00 2.72E+00 3.56E+00 5.34E+00 3.43E+00 3.07E+00 1.74E+00 4.16E+00 4.99E+00 4.25E+00 4.86E+00 3.73E+00 1.75E+00 3.36E+00 3.86E+00 5.72E+00 4.38E+00 5.08E+00 1.98E+00 4.25E+00 5.28E+00 2.69E+01 2.26E+01 2.14E+01 1.81E+01 2.07E+01 2.73E+01 2.23E+01 2.28E+01 2.50E+01 1.22E+01 2.06E+01 2.52E+01 9.74E+00 6.97E+00 7.20E+00 5.40E+00 6.38E+00 9.27E+00 7.92E+00 6.60E+00 1.42E+01 3.64E+00 5.86E+00 1.01E+01
[a] Tritium analyses on quarterly composite.
[b] Sr-89/90 performed annually on 2nd quarter composite sample.
55
Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium
[pCi/L]
page 1 of 2 Sampling Date H-3*
01/12/10
[a]
02/15/10
[a]
03/16/10 3.35E+03
+/-
7.91E+02 04/13/10
[a]
05/10/10 06/14/10 2.34E+03
+/-
6.25E+02 07/12/10
[a]
08/16/10
[a]
09/14/10 4.06E+03
+/-
6.45E+02 10/10/10
[a]
11/16/10
[a]
12/13/10 2.65E+03
+/-
7.81E+02 Mean 3.10E+03
+/-
7.11E+02 I
Sr-89 b
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
4.33E+00
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b]
[b)
[b]
Sr-90 I
Mn-54*
2.83E+00 4.48E+00 3.55E+00 1.77E+00 3.20E+00 Fe-59*
6.60E+00 8.52E+00 6.45E+00 4.54E+00 7.85E+00 8.07E+00 1.46E+01 1.23E+01 1.50E+01 3.21 E+00 I
6.72E-01 2.85E+00 7.83E+00 4.87E+00 7.83E+00 1.32E+00 3.24E+00 7.10E+00 4.43E+00 1.OOE+01 Co-58*
2.70E+00 4.11E+00 3.07E+00 1.91E+00 3.05E+00 3.25E+00 6.19E+00 5.59E+00 8.20E+00 1.41E+00 2.93E+00 4.73E+00 Ba-140*
2.05E+01 2.24E+01 1.96E+01 1.64E+01 2.11E+01 2.36E+01 2.48E+01 2.88E+01 5.37E+01 8.88E+00 1.95E+01 2.33E+01 I
Co-60" 2.70E+00 4.29E+00 3.81E+00 1.78E+00 3.36E+00 2.82E+00 5.79E+00 5.06E+00 7.29E+00 1.37E+00 3.47E+00 4.22E+00 Station 08 SZn5.5*
5.85E+00 7.81E+00 4.95E+00 3.39E+00 7.42E+00 6.70E+00 1.16E+01 1.18E+01 1.22E+01 2.60E+00 7.37E+00 8.52E+00 Sampling Date 01/12/10 02/15/10 03/16/10 04/13/10 05/10/10 06/14/10 07/12/10 08/16/10 09/14/10 10/10/10 11/16/10 12/13/10 Mean
Nb-95*
5.11E+00 3.30E+00 7.37E+00 4.44E+00 6.38E+00 3.11E+00 3.54E+00 1.97E+00 6.57E+00 6.28E+00
+/-
2.53E+00 5.64E+00 3.93E+00 1.09E+01 6.10E+00 8.95E+00 5.41 E+00 1.66E+01 8.35E+00 2.42E+00 1.54E+00 I
1-131 I
Cs-134 I
Cs-137 I
3.96E-01 2.63E+00 2.96E+00 5.68E-01 4.30E+00 4.59E+00 9.31 E-01 3.02E+00 3.82E+00 6.85E-01 1.60E+00 1.93E+00 6.74E-01 2.76E+00 3.19E+00 9.03E-01 3.30E+00 3.17E+00 5.05E-01 6.73E+00 5.59E+00 9.20E-01 4.98E+00 5.43E+00 8.15E-01 5.69E+00 8.76E+00 4.67E-01 1.24E+00 1.42E+00 6.66E-01 3.64E+00 3.67E+00 5.34E-01 3.63E+00 5.03E+00 I
La-140*
6.02E+00 8.06E+00 6.14E+00 6.09E+00 8.15E+00 7.26E+00 9.47E+00 1.OOE+01 1.22E+01 2.93E+00 5.58E+00 5.54E+00 I
6.17E+00 8.05E+00 3.75E+00 4.43E+00 6.28E+00
+/-
2.53E+00
[a] Tritium analyses on quarterly composite.
[b] Sr-89/90 performed annually on 2nd quarter composite sample.
56
Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium
[pCi/L]
page 2 of 2 Sampling Date 01/12/10 02/15/10 03/16/10 04/13/10 05/10/10 06/14/10 07/12/10 08/16/10 09/14/10 10/10/10 11/16/10 12/13/10 MEAN Sampling Date J
01/12/10 02/15/10 03/16/10 04/13/10 05/10/10 06/14/10 07/12/10 08/16110 09/14/10 10/10/10 11/16/10 12/13/10 H-3*
I Sr-89 I
[a]
[b]
[a]
[b]
8.50E+02
[b]
[b
[b Sr-90 I
Mn-54*
3.15E+00 3.99E+00
[a]
[a]
[a]
[a]
[b]
[b]
8.63E+02 3.35E+00
[b]
[b]
[b]
4.12E+00
[b]
1.66E+00
[b]
3.21 E+00 5.39E-01 3.88E+00
[b]
5.43E+00
[b]
4.70E+00
[b]
3.96E+00
[b]
1.96E+00
[b]
4.42E+00
[b]
3.53E+00 Fe-59*
7.56E+00 7.66E+00 9.62E+00 4.16E+00 7.63E+00 9.76E+00 1.06E+01 8.83E+00 1.11E+01 4.27E+00 9.02E+00 8.76E+00 I
Co-58" 3.78E+00 4.58E+00 5.07E+00 1.84E+00 3.33E+00 4.36E+00 4.57E+00 4.63E+00 4.86E+00 2.16E+00 3.94E+00 4.04E+00 I
Co-60" 4.05E+00 3.21E+00 4.88E+00 1.57E+00 3.50E+00 3.30E+00 3.68E+00 4.89E+00 4.77E+00 1.94E+00 4.13E+00 4.43E+00 Station 09A 7.O0E+00 9.22E+00 6.61E+00 3.24E+00 7.05E+00 9.09E+00 9.12E+00 9.47E+00 6.70E+00 4.28E+00 9.76E+00 9,44E+00 5.80E+02
[b]
[a]
[b]
[a]
[b]
9.88E+02
[bI Zr-95*
j Nb-95*
J 1-131" 6.26E+00 3.81E+00 4.11E-01 6.01E+00 4.51E+00 4.38E-01 8.65E+00 4.42E+00 5.47E-01 3.31 E+00 2.OOE+00 3.09E-01 5.79E+00 3.56E+00 7.87E-01 9.17E+00 5.01E+00 7.88E-01 9.73E+00 5.11E+00 6.44E-01 8.95E+00 5.10E+00 6.46E-01 7.60E+00 3.77E+00 9.43E-01 3.63E+00 2.26E+00 4.84E-01 7.76E+00 4.94E+00 7.OOE-01 8.16E+00 3.75E+00 5.90E-01 SCs-134" 0
3.13E+00 3.48E+00 4.OOE+00 1.52E+00 2.78E+00 3.80E+00 5.53E+00 4.32E+00 3.24E+00 1.89E+00 4.02E+00 3.77E+00 Cs-137"6+
3.46E+00 3.88E+00 4.78E+00 1.68E+00 3.29E+00 4.31 E+00 5.49E+00 4.75E+00 5.OOE+00 2.08E+00 4.69E+00 4.36E+00 Ba-140" 2.45E+01 2.23E+01 2.55E+01 1.63E+01 2.38E+01 2.99E+01 2.38E+01 2.54E+01 2.84E+01 1.33E+01 2.34E+01 1.94E+01 l
La-140*
9.28E+00 6.26E+00 7.94E+00 5.42E+00 8.08E+00 1.24E+01 1.OOE+01 9.33E+00 1.20E+01 4.02E+00 5.48E+00 7.73E+00 I
[a] Tritium analyses on quarterly composite.
[b] Sr-89/90 performed annually on 2nd quarter composite sample.
57
Table 3-13 Sediment Silt Gamma Spectra, and Strontium
[pCi/Kg]
Sr-90 page 1 of 1 Sample Date Sr-89 K-40 Cs-i134*
Cs-137*
IDate IrI8I 04/19/2010 Station 08 Station 09A**
Station 11
[a]
[a]
[a]
[a]
[a]
[a]
3.05E+03
+/-
1.24E+04
+/-
1.53E+04
+/-
Ra-226 5.06E+02 9.34E+02 8.74E+02 2.90E+01 3.78E+01 3.39E+01 Th-228 1.OOE+02
+/-
2.59E+01 1.55E+02
+/-
4.55E+01 3.52E+01 Th-232 I
I 04/19/ 2 0 10 Station 08 Station 09A**
Station 11 Sample Date 1.02E+03 2.76E+03 2.52E+03
+/-
+/-
+/-
5.89E+02 9.48E+02 7.46E+02 3.56E+02 9.32E+02 1.19E+03
+/-
4.26E+01
+/-
6.22E+01
+/-
6.50E+01 3.18E+02 8.40E+02 1.15E+03
+/-
+/-
+/-
6.42E+01 1.27E+02 1.09E+02 Sr-89 Sr-90 K-40 Cs-134*
Cs-137*
10/18/2010 Station 08 Station 09A**
Station 11 9.28E+01 1.12E+02 9.30E+01 3168E+01 4.26E+01 3.07E+01 1.53E+04
+/-
1.18E+04
+/-
1.79E+04
+/-
Ra-226 1.39E+03 1.24E+03 1.35E+03 5.32E+01 1.76E+02
+/-
6.58E+01 5.08E+01 Th-228 6.41E+01 8.22E+01 5.87E+01 Th-232 10/18/2010 Station 08.
Station 09A**
Station 11 2.95E+03
+/-
1.01E+03 1.54E+03 2.04E+03
+/-
9.08E+02 MEAN K-40 1.52E+03 6.72E+02 1.27E+03
+/-
+/-
+/-
1.45E+02 8.66E+01 1.03E+02 1.54E+03 5.86E+02 1.23E+03
+/-
1.61E+02
+/-
1.71E+02
+/-
1.59E+02 Sr-89 Sr-90 Cs-134*
Cs-1 37*
Indicator Control
+/-
+/-
+/-
+/-
1.29E+04
+/-
1.21E+04
+/-
Ra-226 1.03E+03
+/-
1.OOE+02
+/-
4.60E+01 1.09E+03 1.76E+02
+/-
5.18E+01 1.55E+02
+/-
6.39E+01 Th-228 I
Th-232 Indicator Control
+/-
2.76E+03
+/-
8.13E+02 1.08E+03
+/-
8.89E+01 1.24E+03 8.02E+02
+/-
7.44E+01 1.06E+03
+/-
1.23E+02 7.13E+02
+/-
1.49E+02
- Control Station
[a] Sr-89/90 analyses performed annually.
58
(
Table 3-14 Shoreline Soil Gamma Spectra, and Strontium
[pCi/Kg]
page 1 of 1 Sample Date I
Sr-89 I
Sr-O0 I
K-40 I
Cs-34 I
Cs-137 04/19/2010
[a 9.35E+03
+/-
8.17E+02 3.44E+01 4.26E+01 Station 08[a Ra-226 ITh-228 ITh-232 1.67E+03
+/-
8.18E+02 1.27E+03
+/-
7.66E+01 1.11E+03
+/-
1.14E+02 Sample Date Sr-89 Sr-90 K-40 Cs-134 Cs-i 37 10/18/2010 Station 08 9.31E+01 3.28E+01 2.77E+03
+/-
9.23E+02 5.94E+01 Th-228 6.79E+01 Th-232 Ra-226 1.35E+03
+/-
MEAN K-40 1.11E+03 8.62E+02
+/-
1.02E+02 8.94E+02
+/-
1.94E+02 Sr-89 Sr-90 Cs-134 Cs-137
+1-
+1-
+/-
+/-
6.06E+03
+/-
8.70E+02
+/-
+/-
Th-232 1.51E+03
+/-
9.64E+02 1.07E+03 8.93E+01 1.OOE+03
+/-
1.54E+02
+/-
[a] Sr-89/90 analyses performed annually.
59
Table 3-15 Fish Gamma Spectra
[pCi/Kg]
page 1 of 1 Fish [a]
Sampling Station 08 Date I
K-40 I
Mn-54*
I Fe-59*
I Co-58*
I Co-60*
I Zn-65*
I Cs-134*
I Cs-137" 04/21/10 2.45E+03
+/-
9.29E+02 5.52E+01 1.72E+02 7.39E+01 6.51E+01 1.21E+02 5.14E+01 6.37E+01 10/21/10 2.13E+03
+/-
9.16E+02 5.53E+01 1.21E+02 7.30E+01 5.90E+01 1.48E+02 6.63E+01 6.50E+01 Sampling Station 25**
Date I
K-40 I
Mn-54*
I Fe-59*
I Co-58*
I Coo60*
I Zn-65*
I Cs134*
I Cs-137*
04/20/10 1.61E+03
+/-
6.43E+02 4.51E+01 1.31E+02 4.33E+01 3.57E+01 9.67E+01 3.60E+01 4.99E+01 10/19/10 3.05E+03
+/-
1.05E+03 7.82E+01 1.58E+02 7.83E+01 8.87E+01 1.47E+02 6.33E+01 8.27E+01 catfish [b]
Sampling Station 08 Date K-40 I
Mn-54*
I Fe-59*
I Co-58 I
Co_60*
I Zn-65*
I Cs134*
I Cs-37*
04/21/10 2.23E+03
+/-
8.82E+02 5.81E+01 1.43E+02 6.65E+01 5.03E+01 1.29E+02 5.14E+01 6.24E+01 10/21/10 2.08E+03
+/-
6.21E+02 5.32E+01 1.13E+02 5.44E+01 4.95E+01 1.11E+02 5.42E+01 5.60E+01 Sampling Station 25**
Date I
K-40 I
Mn-54*
I Fe-59*
I Co-58 I
Coo60*
I Zn65*
Cs134*
I Cs-137*
04/20/10 10/19/10 2.20E+03
+/-
2.18E+03
+/-
2.24E+03
+/-
5.76E+02 1.04E+03 8.32E+02 "z 1.72E+01 6.87E+01 4.12E+01 1.76E+02 1.92E+01 7.65E+01 1.81E+01 6.95E+01 3.27E+01 1.28E+02 1.36E+01 5.93E+01 1.77E+01 6.45E+01 Mean Indicator 2.22E+03
+/-
8.37E+02 Control 2.26E+03
+/-
8.27E+02
- Control Station
[a] Non-bottom dwelling species of gamefish.
[b] Bottom dwelling species of fish.
60
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2010 and tabulated in Section 3, are discussed below. Except for TLDs, TBE analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the TBE 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 2010 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, Th-228 and Th-232 were detected in numerous samples. Th-228 & Th-232 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 2010 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.
61
9.0 8.0 6.0 5.0 5.0 Environmental TLDs 3.0 V
mf
-U-Sector TLDs Avg. Pre-op 2.0 1.0 0.0 or 1.0 o00~o 0
0 0
0 00 C
C C
C Ca C
Figure 4-1 TLD (mrem/Standard Month)
Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The average level of the 32 locations (two badges at each location) was 5.3 mR/standard month with a range of 0.9 to 39.2 mR/standard month. The highest quarterly average reading for any single location was obtained at location SSW-19/51. This value was 27.9 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 eleven indicator locations within 10 miles of the station the average quarterly reading was 3.5 mR/standard month with a range of 1.5 to 6.4 mR/standard month. The average annual reading for these locations was 3.4 mR/standard month with a range of from 2.2 to 5.1 mR/standard month. The control location showed a quarterly average of 3.3 mR/standard month with a range of 2.0 to 4.9 mR/standard month.
Its annual reading was 2.6 mR/standard month.
10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.3 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.5 mR/standard month. Eight other TLDs, designated C-1 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 3.4, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.7 to 3.7 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard 62
t I
ý month.
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. The drop indicated in 2010 may be a function a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this in fact the case.
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.
0.12 0.1 E 0.0'8
.~0.06 0.04 0.02 0
-0
-)
D 0 (--)
-O ) (0 r--
TO O
- 0)
- 0)
- 0)
So
- 0)
- 0) 0 CO
--)
C)
-D MN
'j" a-a a) 71 a
a a
a a
(a a) 00
) <
Control Sta-24 Indicator Average Pre-op Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 63
3.50E-02 3.OOE-02 2.50E-02 A
2.00E-02 1.50E-02 1,00E-02 5.OOE-03 OOOE+O0 o
o0 0
C>
0 0
Control Sta-24 Indicator Figure 4-3 2010 Gross Beta in Air Particulates (pCil/mr) 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. 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. The results of these analyses indicate the lack of station effects on the environment.
4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations. There has been no detection of 64
If 1
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 collected in 2010.
Cs-137 was identified in several samples. For the indicator stations the average was 283 pCi/Kg while for the control station the average was 223 pCi/Kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg.
The average was 645 pCi/kg.
The current levels are also varied significantly by location and date. The decrease in the average and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout.
Cs-134 was detected in three samples, but these are considered false positives since the peak was not identified during the analysis, but the force activity calculation resulted in an activity concentration that exceeded the 2(y value and the MDC.
4.7 Precipitation A sample of rain water was collected monthly at on-site station 01A and analyzed for gross beta activity. The results are presented in Table 3-7.
12 precipitation samples were obtained in 2010.
Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements.
No positive indications of plant related gamma emitting radioisotopes were observed in 2010.
Naturally occurring gamma emitting radioisotopes were detected. 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 cannot be made to the 2010 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 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 65
11 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. Low levels of Cs-137, attributable to fallout, have been seen periodically in vegetation samples.
As expected, naturally occurring potassium-40 and, cosmogenic beryllium-7 were detected in most 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 onsite 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 are analyzed for strontium-89 and strontium-90 in accordance with program requirements. There has been no detection of these fission products at any of the indicator or control stations in 66
I, 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 3510 pCi/liter and a range of 2250 to 4660 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.
8000 7000 6000 5000 o
4000 3000 2000 1000 oo CO oco C
) 0) 0) 0) 0) 0) 0C)QQQQOOOOOO0 V
Date H-3 in RW Tritium H-3 in RW Required LLD Figure 4-4Tritium in River water 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 are analyzed for strontium-89 and strontium-90.
There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.
Nb-95 was reported in one surface water sample at the indicator location.
67
However, the peak was not identified, but forced activity concentration calculation exceeded MDC and the 2 sigma error. No other non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the other samples.
No tritium was detected at the control location. The average level of tritium activity at the indicator station was 3100 pCi/liter with a range of 2340 to 4060 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.
10000 1000 Tritium U
100 Required LLD 1Average Pre-op 10__
1 Dae Date Figure 4. 5Tritium in Surface Water 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.
68
In 2010, one (1) sediment sample from an indicator location showed Cs-137 at 100 pCi/kg. Cs-137 was also detected at 155 pCi/Kg in one (1) sample at the control location in 2010. Cs-134 was detected in one sample location, the control location, at 176 pCi/kg. However, this is considered a false positive as its peak was not detected during the analysis, but its forced activity concentration exceeded MDC and the 2 sigma error. The detection of Cs-137 in bottom 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.
Neither Strontium-89 nor Strontium-90 was detected any samples of aquatic sediment/silt in 2010. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests. A number of naturally occurring radioisotopes were detected in these samples at background levels.
10000 0)1000 S100 loo 0-10 Date Station-8
- Staton-9 Control-Sta-09A Station-11
-Average Pre-Op
-Required LLD's Figure 4-6 Cs-137 in Sediment/Silt 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 April 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.
69
0 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 accumulation 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 2010 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 all samples. No plant related isotopes were detected. Cs-137 was measured in pre-operational environmental fish samples.
70
- 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2010 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14A, 15,16,23, Vegetation 01/12/10 Seasonal unavailability 26 13 Milk 01/19/10 Sold cows. No longer operating as dairy 14A, 15,16,23, Vegetation 02/09/10 Seasonal unavailability 26 13 Milk 02/16/10 Sold cows. No longer operating as dairy 14A, 15,16,23, Vegetation 03/09/10 Seasonal unavailability 26 13 Milk 03/16/10 Sold cows. No longer operating as dairy 05 AP/Charcoal 03/31/10 Lost power to sampler due to breaker failure. No sample collected 14A,15,16,23, Vegetation 04/13/10 Seasonal unavailability 26 13 Milk 04/20/10 Sold cows. No longer operating as dairy 14A,15,16,23, Vegetation 11/09/10 Seasonal unavailability 26 14A,15,16,23, Vegetation 12/14/10 Seasonal unavailability 26 71
REFERENCES 72
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 (10CFR50), "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 10CFR50, 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.
"Technical Specifications for North Anna Independent Spent Fuel Storage Installation (ISFSI)".
- 11.
HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.
- 12.
NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.
73
0 p
APPENDICES 74
APPENDIX A: LAND USE CENSUS Year 2010 75
LAND USE CENSUS North Anna Power Station North Anna County, Virginia January 1 to December 31, 2010 Direction Distance (miles)
Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch I Boundary
(>50m2)
Animal Cow Goat N
0.9 1.3 1.9 2.9 NONE NONE NNE 0.9 0.9 1.7 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.2 2.4 2.7 NONE NONE E
0.8 1.3 2.0 3.5 NONE NONE ESE 0.9 1.7 1.7 4.9 NONE NONE SE 0.9 1.4 1.5 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE S
0.9 1.0 1.0 2.0 NONE NONE SSW 1
1.3 3.1 2.0 NONE NONE SW 1.1 1.7 3.0 NONE NONE NONE WSW 1.1 1.6 2.4 1.6 NONE NONE W
1.1 1.5 1.5 4.4 NONE NONE WNW 1
1.1 2.6 5.0 NONE NONE NW 1
1.0 2.0 NONE NONE NONE NNW 0.9 1.0 2.2 NONE NONE NONE 76
2009 to 2010 Land Use Census Changes 2009 2010 Nearest Direction Distance Distance Site Boundary NONE Resident N
1.5 1.3 Garden NNE 3.1 1.7 SE 1.0 1.5 SSW 3.7 3.1 WSW NONE 2.4 W
1.8 1.5 NW NONE 2.0 Meat Animal N
NONE 2.9 NNE 1.5 3.1 NE 1.5 1.6 ENE 2.5 2.7 ESE NONE 4.9 SE 1.5 1.4 SSE 2.8 1.6 S
2.8 2.0 SSW 1.9 2.0 W
NONE 4.4 WNW 3.9 5.0 Milch Cow NONE Milch Goat NONE 77
APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS YEAR 2010 78
InfRODUCTION This appendix covers the Intercomparison Program of the Teledyne Brown Engineering - Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP).
TBE uses QA/QC samples provided by Eckert & Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) and Environmental Resource Associates, (ERA) 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:
E & Z Analytics:
> Milk for gamma emitters, Iodine-131, Fe-55, Sr-89 and Sr-90 analyses once per quarter.
> Air particulate for gamma emitters once per quarter
> Charcoal for 1-131 once per quarter DOE
> Water and soil for gamma, Iodine-131, U-233/234, U-238, transuranics, tritium, Fe-55, Ni-63, Sr-90 and Tc-99 analyses during the 1st quarter.
> Water for gross alpha and beta during the 1st and 3rd quarters
> Air particulates and vegetation for gamma, Iodine-131, U-233/234, U-238, transuranics, Sr-90 analyses during the 1st and 3rd quarters
> Air filter for gross alpha and beta analyses during the 1st and 3rd quarters.
> Water for tritium, gamma, Iodine-131, Sr-89, Sr-90, gross alpha and beta during the 2nd and 4t quarters.
> Water for natural uranium during the 2nd quarter RESULTSI Interlaboratory comparison program results are evaluated using TBE#'s criterion.
Any sample analysis result that does not pass the criteria is investigated by TBE.
The following Nonconformance Reports were generated and corrective actions taken as a result of this program.
NCR 10 Failure of Zn-65 in water was not a failure, but due to a typographical error in reporting the data. Corrective action is data will be reviewed more carefully.
Sr-89 result was evaluated as a failure based on the acceptance range of 55.8-76.7. The TBE to ERA ratio was 1.14 based on the known value of 68.5. Since the result is within 20% of the known, this is not considered a 79
failure by TBE. No corrective action necessary.
NCR 11-01 Failed MAPEP Series 23 water Pu-238 and Pu-239/240. At the time of this report this item is still under investigation.
The results of the investigation and corrective action will be included in next year's report.
A summary of TBE's results is provided in the tables on the following pages 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.
80
- 4.
- e.
0 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Evaluation Value Month/Year Number Matrix Nuclide Units Value (a)
(b)
TBE/Analytics (d)
March 2010 E6978-396 Milk Sr-89 pCi/L 89.3 92.8 0.96 A
Sr-90 pCi/L 13.8 12.7 1.09 A
E6979-396 Milk E6981-396 AP 1-131 Ce-141 Cr-;5 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-i 41 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 65.2 241 388 157.0 150 143 202 146 247 177 211 304 142 131 119 162 110 217 145 74.0 261 361 178 158 143 207 137 254 183 185 255 125 111 101 146 97 179 129 0.88 0.92 1.07 0.88 0.95 1.00 0.98 1.07 0.97 0.97 1.14 1.19 1.14 1.18 1.18 1.11 1.14 1.21 1.12 0.94 1.26 0.88 0.95 0.86 0.97 0.96 0.90 0.96 0.91 0.98 1.02 0.96 0.96 A
A A
A A
A A
A A
A A
A A
A A
A A
W A
E6980-396 Charcoal 1-131 June 2010 E6982-396 Water E7132-396 Milk E7133-396 Milk Fe-55 Sr-89 Sr-90 1-131 Ce-1 41 Cr-51 Cs-i 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 80.2 85.6 2490 1970 82.0 93.4 15.8 16.7 83.5 107 325 114.0 144 92.3 165 121 197 190 96.9 110 339 126 150 101 169 119 206 197 A
A A
A A
A A
A A
A A
A 81
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
Evaluation Value Month/Year Number Matrix Nuclide Units Value (a)
(b)
TBE/Analytics (d)
E7135-396 AP Ce-141 DCi 88.4 91.6 0.97 A
Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi 292 101 132 87.3 150 105 168 170 282 105 125 84.0 140 98.6 171 163 1.04 0.96 1.06 1.04 1.07 1.06 0.98 1.04 A
A A
A A
A A
A E7134-396 Charcoal 1-131 pCi 76.4 79.9 June 2010 September 2010 E7136-396 Water E7229-396 Milk E7230-396 Milk E7232-396 AP Fe-55 Sr-89 Sr-90 1-131 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi/L pCi 1710 1880 85.0 92.8 12.6 14.7 80.2 130 235 83.2 95.1 77.3 121 96.4 216 172 122 228 79.9 93.8 71.5 113 73.8 186 163 94.1 130 234 93.0 94.5 73.7 119 91.1 204 171 119 214 85.3 86.7 67.6 110 83.6 187 157 0.96 0.91 0.92 0.86 0.85 1.00 1.00 0.89 1.01 1.05 1.02 1.06 1.06 1.01 1.03 1.07 0.94 1.08 1.06 1.03 0.88 0.99 1.04 1.04 0.91 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
E7231-396 Charcoal 1-131 62.3 59.9 1620 1790 E7233-396 Water Fe-55 82
4 w ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
Evaluation Value Month/Year Number Matrix Nuclide Units Value (a)
(b)
TBE/Analytics (d)
December 2010 E7375-396 Milk E7376-396 Milk Sr-89 Sr-90 1-131 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 92.7 98.0 13.5 13.5 0.95 1.00 A
A 87.9 not provided 389 137 172 84.3 120 134 162 284 96.9 by Analytics 456 157 186 90.2 120 131 174 301 0.91 for this study 0.85 0.87 0.92 0.93 1.00 1.02 0.93 0.94 A
A A
A A
A A
A A
A A
A A
W A
A E7378-396 AP pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi not provided by Analytics for this study 387 135 157 73.6 88.7 127 151 249 365 126.0 149.0 72.3 96.0 105.0 139 241 1.06 1.07 1.05 1.02 0.92 1.21 1.09 1.03 0.95 0.91 December 2010 E7377-396 Charcoal 1-131 79.6 84.2 1720 1880 A
E7379-396 Water Fe-55 (a) Teledyne Brown Engineering reported result.
(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.
W-Acceptable with warning. Reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable. Reported 83
9 result falls outside the ratio limits of < 0. 70 and > 1.30.
DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)
Identification Reported Known Acceptance Evaluation Value Month/Year Number Media Nuclide Units Value (a)
(b)
Range (c)
March 2010 10-MaW22 Water Am-241 Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-234/233 U-238 Zn-65 10-GrW22 Water Gr-A Gr-B Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L BqIL Bq/L BqIL BqIL Bq/L Bq/L Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 1.25
-0.0942 58.5 27.2 0.0226 104 26.6 61.3 1.94 0.0660 0.1029
-0.3907 1.21 1.27 42.0 1.30 0.091 - 1.69 (1) 60.6 42.4 - 78.8 28.3 19.8 - 36.8 (1) 90.8 63.6-118.0 26.9 18.8 - 35.0 59.9 41.9 - 77.9 1.93 1.35-2.51 0.009 (2)
(1)
(1) 1.22 0.85-1.59 1.25 0.88 - 1.63 40.7 28.5 - 52.9 0.5173 0.676 3.98 3.09 1.352 1.55-4.64 10-MaS22 Soil Am-241 Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90 Tc-99 U-234/233 U-238 Zn-65 4.90 665 800 508 648 893 514 28.4 0.2806 597 221
-3.45 68.0 69.2
-4.97 1.81 1.70 0.0056 2.65 3.70 (1) 733 513-953 779 545-1013 522 365-679 622 435-809 849 594-1104 477 334-620 24.1 16.9-31.3 (1) 559 391 -727 288 202-374 (1) 60 42-78 64 45-83 (1) 2.13 1.49-2.77 1.53 1.07-1.99 (1) 2.473 1.731 -3.215 3.02 2.11 -3.93 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
W A
A A
A A
A A
A W
10-RdF22 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 84
k...
DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)
Identification Reported Known Acceptance Evaluation Value Month/Year Number Media Nuclide Units Value (a)
(b)
Range (c) 10-RdF22 AP Pu-238 Bq/sample 0.0081 0.0010 (2)
A Pu-239/240 Sr-90 U-234/233 U-238 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 0.0757 0.0523 0.0732 0.0791
-0.0627 0.0582-0.0832 0.1082 (1) 0.068 0.048 - 0.088 0.071 0.050 - 0.092 (1) 10-GrF22 AP Gr-A Gr-B Bq/sample 0.1533 0.0427 Bq/sample 1.240 1.29 0.854 0.65-1.94 A
A A
A A
A A
A A
A A
A A
A March 2010 1 0-RdV22 Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 4.48 3.43
-0.0117 3.55 0.007
-0.0002 8.12 4.39 3.07 - 5.71 3.06 2.14-3.98 (1) 3.27 2.29 - 4.25 (1)
(1) 7.10 4.97 - 9.23 September 2010 10-MaW23 Water Am-241 Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-234/233 U-238 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/kg Bq/kg Bq/kg 0.009 27.1 41.8 33.2 26.5 500 0.024 51.6 1.25 0.925 8.10 36.4 2.02 2.01 30.8 31.4 44.2 36.0 28.3 453.4 56.1 1.81 1.350 8.3 33.6 2.01 2.07 31.0 (1) 22.0 - 40.8 30.9 - 57.5 25.2 - 46.8 19.8-36.8 317.4 - 589.4 (1) 39.3 - 72.9 1.27 - 2.35 0.95-1.76 5.8 - 10.8 23.5 - 43.7 1.41 - 2.61 1.45-2.69 21.7-40.3 A
A A
A A
A A
A N (3)
N (3)
A A
A A
A 10-GrW23 Water 10-MaS23 Soil Gr-A Gr-B Am-241 Cs-1 34 Cs-1 37 2.36 6.37 NR 837 680 1.92 0.58-3.26 4.39 2.20 - 6.59 A
A A
A 940 670 658-1222 469-871 85
DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)
Identification Reported Known Acceptance Evaluation Value Month/Year Number Media Nuclide Units Value (a)
(b)
Range (c) 10-MaS23 Soil Co-57 Bq/kg 2.78 (1)
A Co-60 Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90 Tc-99 U-234/233 U-238 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 350 853 938 NR NR 721 2.24 297 NR NR 287 343 820 1058 240-446 574-1066 741 -1375 699 489-909 (1) 325 228-423 265 186-345 10-RdF23 AP Am-241 Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Bq/sample 0.125 0.115 0.081 -0.150 Bq/sample 2.31 2.98 2.09 - 3.87 Bq/sample
-0.025 (1)
Bq/sample 0.0056 3.64 4.08 Bq/sample 2.81 2.92 2.04 - 3.80 Bq/sample 3.19 3.18 2.23-4.13 0.0342 -
Bq/sample 0.048 0.0489 0.0636 Bq/sample 0.080 0.082 0.057 - 0.107 A
A A
A A
A A
A W
A A
A A
A A
A A
A A
A A
A A
W A
A A
A September 2010 10-RdF23 AP Pu-238 Pu-239/240 Sr-90 U-234/233 U-238 Zn-65 Gr-A Gr-B 10-GrF23 AP Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1.01 0.123 0.111 0.0310 0.004 0.473 4.90 6.78 10.2 0.00 7.36 2.53 6.40 1.01 0.122 0.127 0.71 -1.31 0.085 - 0.159 0.089 - 0.165 (1)
(1) 0.50 0.25 - 0.75 10-RdV23 Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 4.79 5.88 8.27 6.287 2.63 5.3900 3.35 - 6.23 4.12-7.64 5.79 - 10.75 (1) 4.401 - 8.173 1.84-3.42 3.77 - 7.01 See footnotes on next page.
86
(1)
(2)
(3)
(a)
(b)
False positive test.
Sensitivity evaluation NCR 11-01 initiated to investigate failure.
Teledyne Brown Engineering reported result.
The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(C) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.
ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Evaluation Value Month/Year Number Media Nuclide Units Value (a)
(b)
Control Limits (c)
May 2010 RAD-81 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 64.4 37.8 66.4 66.43 137.33 83.33 177 26.37 28.77 26.27 57.19 60.4 41.3 65.9 71.6 146 84.5 186 32.9 37.5 26.4 62.3 48.6 - 68.2 30.4 - 47.4 54.9 - 72.5 58.4 - 78.8 131 -163 76.0 - 95.3 167-219 16.9-42.6 24.7 - 45.0 21.9-31.1 50.7 - 69.1 10800 -
13600 A
A A
A A
A A
A A
A A
H-3 12967 12400 MRAD-12 Filter November 2010 RAD-83 Water Gr-A Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat pCi/filter 88.1 79.6 41.3-130 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 77.8 39.3 70.3 39.9 117 53.5 11.0 35.1 35.5 27.9 36.8 68.5 43.0 68.9 43.2 123 53.4 102 42.3 36.6 27.5 36.8 55.8 - 76.7 31.7-49.3 57.5 - 75.8 34.5 - 47.5 111-138 48.1 -61.3 91.8-122 21.9 - 53.7 24.0 - 44.2 22.9 - 32.3 29.8 - 41.0 11200 -
14200 N (1)
A A
A A
A N (1)
A A
A A
H-3 13233 12900 MRAD-13 Filter Gr-A pCi/filter 40.1 52.3 27.1 - 78.7 A
See footnotes on next page.
87
(1) Sr-89 TBE to known ratio of 1.14 fell within acceptable range of +/- 20%. No action required. NCR 10-09 (1) Zn-65 result of 111 was incorrectly reported as 11.0. No action required. NCR 10-09 (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
88