Text

Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report for 2010
	ML11123A215
Person / Time
Site:	North Anna
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
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND), VIRGINIA 23261 April 26, 2011 United States Nuclear Regulatory Commission Serial No.11-213 Attention: Document Control Desk NAPS/JHL Washington, D. C. 20555 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

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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

~- ~ V Dominion North Anna Power Station RadiologicalEnvironmentalMonitoringProgram January1, 2010 to December 31, 2010 Preparedby Dominion, North Anna Power Station

r Annual RadiologicalEnvironmental OperatingReport North Anna Power Station January1, 2010 to December 31, 2010 Preparedby:

Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Reviewed by:

MarK C. Lane Supervisor Health Physics Technical Services Dominion North Anna Power Station Approved by:

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 ARY ......................................................................................................... 4

2. PRO GRA M D ESCRIPTION ...................................................................................................... 7 2.1 Introduction ....................................................... 7 2.2 Sam pling and A nalysis Program ......................................................................................... 8

3. AN A LYTICA 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 ESULTS .................................................................................................... 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 Gam m a ................................................................................................... 64 4.5 A ir Particulate Strontium ................................................................................................. 64 4 .6 S o il ........................................................................................................................................ 65 4.7 Precipitation .......................................................................................................................... 65 4.8 Cow Milk .............................................................................................................................. 65 4.9 Food Products and V egetation ........................................................................................ 66 4.10 W ell W ater .......................................................................................................................... 66 4.11 River Water ......................................................................................................................... 66 4.12 Surface W ater ...................................................................................................................... 67 4.13 Bottom Sedim ent ................................................................................................................ 68 4.14 Shoreline Soil ...................................................................................................................... 69 4.15 Fish ...................................................................................................................................... 70

5. PRO GRA M EX CEPTION S ..................................................................................................... 71 REFEREN CES ................................................................................................................. ;.................. 72 A PPEND 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.

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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 andAnalysis 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.

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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 Environmental NAPS Sewage Treatment Plant 01 0.20 NE 420 Quarterly & Annually Thermoluminescent Fredericks Hall 02 5.30 SSW 2030 Quarterly & Annually Dosimetry (TLD) Mineral, Va 03 7.10 WSW 2430 Quarterly & Annually Wares Crossroads 04 5.10 WNW 2870 Quarterly & Annually Route 752 05 4.20 NNE 200 Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N 110 Quarterly & Annually Levy, VA 06 4.70 ESE 1150 Quarterly & Annually Bumpass, VA 07 7.30 SSE 1670 Quarterly & Annually End of Route 685 21 1.00 WNW 3010 Quarterly & Annually Route 700 22 1.00 WSW 2420 Quarterly & Annually "Aspen Hills" 23 0.93 SSE 1580 Quarterly & Annually Orange, VA 24 22.00 NW 3250 Quarterly & Annually Control Bearing Cooling Tower N-1/33 0.06 N 100 Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 110 Quarterly Parking Lot "C" (on-site) NNE-3/35 0.24 NNE 320 Quarterly Good Hope Church NNE-4/36 3.77 NNE 250 Quarterly Parking Lot "B" NE-5/37 0.20 NE 420 Quarterly Lake Anna Marina (Bogg's Dr) NE-6/38 1.46 NE 340 Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 740 Quarterly Route 689 ENE-8/40 2.43 ENE 650 Quarterly Near Training Facility E-9/41 0.30 E 910 Quarterly "Morning Glory Hill" E- 10/42 2.85 E 930 Quarterly Island Dike ESE-11/43 0.12 ESE 1030 Quarterly Route 622 ESE-12/44 4.70 ESE 1150 Quarterly DVP Biology Lab SE-13/45 0.64 SE 1380 Quarterly Route 701 (Dam Entrance) SE-14/46 5.88 SE 1370 Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 1580 Quarterly Elk Creek SSE-16/48 2.33 SSE 1650 Quarterly

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.

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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 NAPS Access Rd. S-17/49 0.47 S 1730 Quarterly Environmental Elk Creek Church S-18/50 1.55 S 1780 Quarterly Thermoluminescent NAPS Access Rd. SSW- 19/51 0.42 SSW 1970 Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 2050 Quarterly 500kv Tower SW-21/53 0.6 SW 2180 Quarterly Route 700 SW-22/54 3.96 SW 2320 Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 2370 Quarterly Route 700 (Exclusion Boundary) WSW-24/56 1.00 WSW 2420 Quarterly South Gate Switchyard W-25/57 0.32 W 2790 Quarterly Route 685 W-26/58 1.55 W 2740 Quarterly End of Route 685 WNW-27/59 1.00 WNW 3010 Quarterly Route 685 WNW-28/60 1.40 WNW 3030 Quarterly North Gate - Construction Side NW-29/61 0.45 NW 3210 Quarterly Laydown Area Lake Anna Campground NW-30/62 2.54 NW 3190 Quarterly

1/#2 Intake NNW-31/63 0.07 NNW 3490 Quarterly Route 208 NNW-32/64 2.21 NNW 3440 Quarterly Bumpass Post Office C-1/2 7.30 SSE 1670 Quarterly Orange, VA C-3/4 22.00 NW 3250 Quarterly Control Mineral, VA C-5/6 7.10 WSW 2430 Quarterly Louisa, VA C-7/8 11.54 WSW 2570 Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 420 Weekly and Radioiodine Biology Lab*** OIA 0.64 SE 1380 Weekly Mineral, VA 03 7.10 WSW 2430 Weekly Wares Crossroads 04 5.10 WNW 2870 Weekly Route 752 05 4.20 NNE 200 Weekly Sturgeon's Creek Marina 05A 2.04 N 110 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.

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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 Levy, VA 06 4.70 ESE 1150 Weekly Bumpass, VA 07 7.30 SSE 1670 Weekly Airborne Particulate End of Route 685 21 1.00 WNW 3010 Weekly and Radioiodine Route 700 22 1.00 WSW 2420 Weekly "Aspen Hills" 23 0.93 SSE 1580 Weekly Orange, VA 24 22.00 NW 3250 Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 1480 Monthly (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 WNW 2950 Monthly Control (Route 669 Bridge)

River Water North Anna River (downstream) 11 5.80 SE 1280 Monthly Ground Water Biology Lab 01A 0.64 SE 1380 Quarterly (Well Water)

Precipitation Biology Lab 01A 0.64 SE 1380 Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 WNW 2950 Semi-Annually Control (Route 669 Bridge)

North Anna River (downstream) 11 5.80 SE 1280 Semi-Annually Shoreline Soil Waste Heat Treatment Facility 08 ** 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Soil NAPS Sewage Treatment Plant 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.

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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 Fredericks Hall 02 5.30 SSW 2030 Once/3 years Mineral, VA 03 7.10 WSW 2430 Once/3 years Wares Crossroads 04 5.10 WNW 2870 Once/3 years Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina 05A 2.04 N 110 Once/3 years Levy, VA 06 4.70 ESE 1150 Once/3 years Bumpass, VA 07 7.30 SSE 1670 Once/3 years End of Route 685 21 1.00 WNW 3010 Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 2420 Once/3 years "Aspen Hills" 23 0.93 SSE 1580 Once/3 years Orange, VA 24 22.00 NW 3250 Once/3 years Control Milk Holladay Dairy (R.C. Goodwin) 12"**** 8.30 NW 3100 Monthly Lakeside Dairy 12A 7.50 NW 3100 Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Lake Orange 25 16.5 NW 3120 Semi-Annually Control Food Products Moody Lane*** 14a 1.70 ESE 1030 Monthly if available or at harvest Vegetation) Route 614 15 1.37 SE 1330 Monthly if available or at harvest Route 629/522 16 12.60 NW 3140 Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 1580 Monthly if available or at harvest "Historic Lane" 26 1.15 S 172 0 Monthly if available or at harvest

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.

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TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS h II ler IuIuniunceII Dosimetry (TLD)

(84 TLDs) Quarterly Gamma Dose 2 mR+2mR mR/std. Month (12 TLDs) Annually Gamma Dose 2 mR+2mR mR/std. Month 3

Airborne Radioiodine Weekly 1-131 0.07 pCi/m 3

Airborne Particulate Weekly Gross Beta 0.01 pCi/mi 3

Quarterly (a) Gamma Isotopic pCi/mi Cs-134 0.05 Cs-137 0.06 3 2nd Quarter Sr-89 (b) pCi/mi Composite Sr-90 (b)

Surface Water Monthly 1-131 1(c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La- 140 15 Quarterly(a) Tritium (H-3) 2000 pCi/L 2nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

River Water Monthly 1-131 1(c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15

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 FREQUENCY ANALYSIS LLD REPORT UNITS River Water Quarterly(a) Tritium (H-3) 2000 pCi/L 2nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

Ground Water Quarterly Gamma Isotopic pCi/L (Well Water) Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 10(c)

Cs-134 15 Cs-137 18 Ba-140 60 La- 140 15 Quarterly(a) Tritium (H-3) 2000 pCi/L 2nd Quarter Sr-89 (b) pCi/L Sr-90 (b)

Aquatic Sediment Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

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 pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

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 ANALYSIS LLD REPORT UNITS Soil Soil Once per 3 years Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

Milk Monthly 1-131 1 pCi/L Monthly Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (b) pCi!L Sr-90 (b)

Fish Semi-Annually Gamma Isotopic pCi/kg (wet)

Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly, if Gamma Isotopic pCi/kg (wet)

(Broadleaf available, or Cs-134 60 Vegetation) at harvest Cs-137 80 1-131 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 Environmental Station Map Environmental Station Designation Identification Designation Identification 1 (a) 01 ,NE-5/37 27 27-Milk 1A O1A,SE-13/45 7/8 C-7/8 2 (a) 02,SSW-20/52 1/33 N-1/33 3 (a) 03,C-5/6 31/63 NNW-31/63 4 (a) 04 29/61 NW-29/61 5 (a) 05 3/35 NNE-3/35 5A (a) 05A,N-2/34 7/39 ENE-7/39 6 (a) 06,ESE- 12/44 9/41 E-9/41 7 (a) 07, C-1/2 11/43 ESE-1 1/43 8 08-Water, Fish, Sediment, 17/49 S-17/49 Shoreline Soil 19/51 SSW-19/51 9A 09A-Water sample, Sediment 21/53 SW-21/53 11 11-River Water, Sediment 23/55 WSW-23/55 12 12-Milk 25/57 W-25/57 12A (e) 12A-Milk 16/48 SSE-16/48 14a (d) 14a-Vegetation 14/46 SE- 14/46 15 15-Vegetation 22/54 SW-22/54 16 16-Vegetation 26/58 W-26/58 21 (a) 21 ,WNW-27/59 28/60 WNW-28/60 22 (a) 22,WSW-24/56 32/64 NNW-32/64 23 (a) 23-SSE-15/47 8/40 ENE-8/40 24 (a)(b) 24,C-3/4 4/36 NNE-4/36 25 (c) 25-Fish 10/42 E- 10/42 26 26-Vegetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.

(b) In Orange (c) In Lake Orange (d) Station 14a replaced 14 in October 2008 (e) Dairy at Station 12 ceased milking in May 2010. 16

Figure 1. North Anna Site Radiological Monitoring Locations 17

18 19 0lrgl a. 22312 7j8OAr~c~"-r SERnSzN 6 hllSwa ieerVf rayeMe Wftmt Wevftfrl perf-har ZrADC.

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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.

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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 Gamma 256 2 5.3(256/256) 19/51(2) 0.42 mi. 27.9(8/8) 3.4(16/16)* 0 (mR/std. Month) Dose (0.9-39.2) SSW (7.8-39.2) (2.3-5.1)

(Sector TLDs)

Direct Radiation Gamma 32 2 2.6(16/16) C-1/2 7.3 mi. 2.9 (8/8) 3.4(16/16)* 0 (mR/std. Month) Dose (1.7-3.7) SSE (2.0-3.7) (2.3-5.1)

(Pre-operational TLDs)

Direct Radiation Gamma 40 2 5.3(40/40) EPSP- 0.37 mi. 7.5(8/8) 3.4(16/16)* 0 (mR/std. Month) Dose (2.9-9.3) 09/10 ENE (5.1-9.3) (2.3-5.1)

(Emergency Sector TLDs)

Direct Radiation Gamma 48 2 3.4(44/44) 23 0.93 mi. 4.9(4/4) 3.3(4/4) 0 (mR/std. month) Dose (1.5-6.4) SSE (4.2-6.2) (2.0-4.9)

(Environmental TLDs)

Direct Radiation Gamma 12 2 3.4(11/11) 01 0.20 mi. 5.1(1/1) 2.6(1/1) 0 (mR/std. Month) Dose (2.2-5.1) NE (5.1) (2.6)

(Annual TLDs)

Airborne Gross 685 0.01 17.0(633/633) 02 5.30 mi. 20.5(52/52) 20.0(52/52) 0 Particulates Beta (4.83- 34.4) SSW (8.55-35.5) (9.55-41.0)

(1E-03 pCi/m 3 )

Air Iodine 1-131 685 0.07 (0/633) N/A N/A N/A (0/52) 0 3

(pCi/m )

Airborne Gamma 52 Particulates (1E-03 pCi/m 3 ) Be-7 52 151(48/48) 05A 2.04 mi. 165(4/4) 160(4/4) 0 (103-226) N (129-226) (117-196)

Cs-134 52 0.05 (0/48) N/A N/A N/A (0/4) 0 (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 Cs-137 52 0.06 (0/48) N/A N/A N/A (0/4) 0 Particulates (1E-03 pCi/m 3 ) Sr-89 13 - (0/12) N/A N/A N/A (0/1) 0 Sr-90 13 - (0/12) N/A N/A N/A (0/1) 0 Soil Triennial (pCi/Kg) (dry) Gamma 24 10800 (22/22) 0.93 23400 (2/2) 4010 (2/2)

K-40 24 23 12 (2130-24000). SSE (22700-24000) (2780-5230) 150 237 (3/22)

(32) 0.93 327 (1/2)

Cs-134 24 23 SSE (0/2) 12 (75.2-327) (327) 24 180 283(18/22) 5.10 567 (2/2) 223 (2/2)

Cs-137 12 (52.7-732) WNW (401- 732) (84.2-362) 2400(17/22) 4150(2/2) 2900(2/2)

Ra-226 24 22 1.00 12 (1260-4630) WSW (3660-4630) (2790-3010) 1130(22/22) 22 1.00 1850(2/2) 1270(2/2)

Th-228 24 12 (451-2330) WSW (1690-2010) (1010-1530) 1080(21/22) 1830(2/2) 1090(2/2)

Th-232 24 22 1.00 12 (387-2090) WSW (1750-1900) (1080-1210)

Sr-89 24 (0/22) N/A N/A N/A (0/2) 12 Sr-90 24 (0/22) N/A N/A N/A (0/2) 12 Monthly Precipitation (pCi/liter) Gross 12 4 5.18(10/12) 01A 0.64 mi. 5.18(10/12) N/A 0 Beta (1.96-23.5) SE (1.96-23.5)

Semiannual 2 Gamma Be-7 2 37.8(1/2) 01A 0.64 mi. 37.8(1/2) N/A 0 (37.8) SE (37.8)

Mn-54 2 15 (0/2) N/A N/A N/A N/A 0 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 N/A N/A 0 Precipitation (pCi/liter)

Co-58 2 15 (0/2) N/A N/A N/A N/A 0 Co-60 2 15 (0/2) N/A N/A N/A N/A 0 Zn-65 2 30 (0/2) N/A N/A N/A N/A 0 Zr-95 2 30 (0/2) N/A N/A N/A N/A 0 Nb-95 2 15 (0/2) N/A N/A N/A N/A 0 1-131 2 (0/2) N/A N/A N/A N/A 0 Cs-134 2 15 (0/2) N/A N/A N/A N/A 0 Cs-137 2 18 (0/2) N/A N/A N/A N/A 0 Ba- 140 2 (0/2) N/A N/A N/A N/A 0 La- 140 2 (0/2) N/A N/A N/A N/A 0 Th-228 2 (0/2) N/A N/A N/A N/A 0 Th-232 2 4.49(1/2) 01A 0.64 mi. 4.49(1/2) N/A 0 (4.49) SE (4.49)

Gamma 12 Milk (pCi/liter)

K-40 12 - 1340(12/12) 12 8.3 mi. 1430(4/4) N/A 0 (1160-1520) NW (1270-1520) 1-131 12 1 (0/12) N/A N/A N/A N/A 0 Cs-134 12 15 (0/12) N/A N/A N/A N/A 0 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 Cs-137 12 18 (0/12) N/A N/A N/A N/A 0 Milk (pCi/liter)

Ba-140 12 60 (0/12) N/A N/A N/A N/A 0 La-140 12 15 (0/12) N/A N/A N/A N/A 0 Sr-89 7 (0/5) N/A N/A N/A N/A (Quarterly)

Sr-90 7 (01/5) N/A N/A N/A N/A 1 (Quarterly)

Food Gamma 30 Vegetation (pCi/kg) (wet) Be-7 30 1260(24/24) 23 varies 1620(5/6) 709(6/6) 0 (382-2810) SSE (731-2810) (317-1260)

K-40 30 4910(24/24) 14a varies 6460(6/6) 5810(6/6) 0 (2080-9560) ESE (4250-9560) (3170-10700) 1-131 30 60 (0/24) N/A N/A N/A (0/6) 0 Cs-134 30 60 (0/24) N/A N/A N/A (0/6) 0 Cs-137 30 80 26.1(1/24) N/A N/A N/A (0/6) 0 Ground Tritium 4 2000 (0/4) 01A 0.64 mi. (0/4) N/A 0 Well Water SE (pCi/liter)

Gamma 4 Mn-54 4 15 (0/4) N/A N/A N/A N/A 0 Fe-59 4 30 (0/4) N/A N/A N/A N/A 0 Co-58 4 15 (0/4) N/A N/A N/A N/A 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 Co-60 4 15 (0/4) N/A N/A N/A N/A Well Water (pCi/liter) Zn-65 4 30 (0/4) N/A N/A N/A N/A Zr-95 4 30 (0/4) N/A N/A N/A N/A Nb-95 4 15 (0/4) N/A N/A N/A N/A 1-131 4 10 (0/4) N/A N/A N/A N/A Cs-134 4 15 (0/4) N/A N/A N/A N/A Cs-137 4 18 (0/4) N/A N/A N/A N/A Ba-140 4 60 (0/4) N/A N/A N/A N/A La- 140 4 15 (0/4) N/A N/A N/A N/A Sr-89 4 (0/1) N/A N/A N/A N/A Sr-90 1 (0/1) N/A N/A N/A N/A River Water Tritium 4 2000 3510(4/4) 11 5.80 mi. 3510(4/4) (0/4)*

(pCi/liter) (2250-4660) SE (2250-4660)

Gamma 12 Mn-54 12 15 (0/12) N/A N/A N/A (0/12)* 0 Fe-59 12 30 (0/12) N/A N/A N/A (0/12)* 0 Co-58 12 15 (0/12) N/A N/A N/A (0/12)* 0 Co-60 12 15 (0/12) N/A N/A N/A (0/12)* 0 Zn-65 12 30 (0/12) N/A N/A N/A (0/12)* 0 Zr-95 12 30 (0/12) N/A N/A N/A (0/12)* 0

Results of surface water taken at Location 09A used as control value for river water 27

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 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 Nb-95 12 15 (0/12) N/A N/A N/A (0/12)* 0 (pCi/liter) 1-131 12 1 (0/12) N/A N/A N/A (0/12)* 0 Cs-134 12 15 (0/12) N/A N/A N/A (0/12)* 0 Cs-137 12 18 (0/12) N/A N/A N/A (0/12)* 0 Ba-140 12 60 (0/12) N/A N/A N/A (0/12)* 0 La-140 12 15 (0/12) N/A N/A N/A (0/12)* 0 Sr-89 1 - (1/0) N/A N/A N/A (1/0)* 0 Sr-90 I - (1/0) N/A N/A N/A (1/0)* 0 Tritium 8 2000 3100(4/4) 08 3.37 mi. 3100(4/4) (0/4) 0 Surface Water (pCi/L) (2340-4060) SSE (2340-4060)

Gamma 24 Mn-54 24 15 (0/12) N/A N/A N/A (0/12)

Fe-59 24 30 (0/12) N/A N/A N/A (0/12)

Co-58 24 15 (0/12) N/A N/A N/A (0/12)

Co-60 24 15 (0/12) N/A N/A N/A (0/12)

Zn-65 24 30 (0/12) N/A N/A N/A (0/12)

Zr-95 24 30 (0/12) N/A N/A N/A (0/12)

Nb-95 24 15 (6.28)(1/12) 08 3.37 mi. (6.28)(1/12) (0/12)

(6.28) SSE (6.28) 1-131 24 1 (0/12) N/A N/A N/A (0/12)

Cs-134 24 15 (0/12) N/A N/A N/A (0/12)

Results of surface water taken at Location 09A used as control value for river water 28

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 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 Cs-137 24 18 (0/12) N/A N/A N/A (0/12) 0 (pCi/liter)

Ba-140 24 60 (0/12) N/A N/A N/A (0/12) 0 La-140 24 15 (0/12) N/A N/A N/A (0/12) 0 Sr-89 1 - (0/1) N/A N/A N/A (0/1) 0 Sr-90 1 - (0/1) N/A N/A N/A (0/1) 0 Sediment Silt Gamma 6 (pCi/kg) K-40 6 12900(4/4) 11 5.80 mi. 16600(2/2) 12100(2/2) 0 (3050- SSE (15300- (11800-12400) 17900) 17900)

Cs-134 6 150 (0/4) N/A N/A (0/2) 176(1/2) 0 (176)

Cs-137 6 180 100(1/4) 08 3.37 mi. 100(1/2) 155(1/2) 0 (100) SSE 100 (155)

Ra-226 6 2130(4/4) 11 5.80 mi. 2280(2/2) 2760(1/2) 0 (1020-2950) SSE (2040-2520) (2760)

Th-228 6 1080(4/4) 11 5.80 mi. 1230 (2/2) 802(2/2) 0 (356-1520) SSE (1190-1270) (672-932)

Th-232 6 1060 (4/4) 11 5.80 mi. 1190(2/2) 713 (2/2) 0 (318-1540) SSE (1150-1230) (586-840)

(Annually)

Sr-89 3 (0/2) N/A N/A N/A (0/1) 0 Sr-90 3 (0/2) N/A N/A N/A (0/1) 0 Shoreline Soil Gamma 2 (pCi/kg) (dry) K-40 2 - 6060(2/2) 08 3.37 mi. 6060(2/2) N/A 0 (2770-9350) 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 Cs-134 2 150 (0/2) N/A NA (0/2) N/A 0 (pCi/kg) (dry)

Cs-137 2 180 N/A N/A NA (0/2) N/A 0 Ra-226 2 1510(2/2) 08 3.37 mi. 1510(2/2) N/A 0 (1350-1670) SSE (1350-1670)

Th-228 2 1070(2/2) 08 3.37 mi. 1070(2/2) N/A 0 (862-1270) SSE (862-1270)

Th-232 2 1000(2/2) 08 3.37 mi. 1000(2/2) N/A 0 (894-1000) SSE (894-1000)

(Annually)

Sr-89 I (0/1) N/A NA N/A N/A 0 Sr-90 1 (0/1) N/A NA N/A N/A 0 Fish Gamma 8 (pCi/kg) (wet)

K-40 8 2220(4/4) 08 3.37 mi. 2220(4/4) 2260(4/4) 0 (2080-2450) SSE (2080-2450) (1610-3050)

Mn-54 8 130 (0/4) N/A NA N/A (0/4) 0 Fe-59 8 260 (0/4) N/A NA N/A (0/4) 0 Co-58 8 130 (0/4) N/A NA N/A (0/4) 0 Co-60 8 130 (0/4) N/A NA N/A (0/4) 0 Zn-65 8 260 (0/4) N/A NA N/A (0/4) 0 Cs-134 8 130 (0/4) N/A NA N/A (0/4) 0 Cs-137 8 150 (0/4) N/A NA N/A (0/4) 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 Page mR/Std. Month (30.4 days) +/- 2 Sigma 1 of 4 First Quarterly*

Quarter Second Quarter Third Quarter Fourth Quarter Station 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.

N-1 6.5 4.4 4.7 5.3 5.0 +/- 2.0 N-33 6.2 3.3 4.8 5.1 N-2 4.1 2.9 3.4 4.4 3.5 +/- 1.2 N-34 3.8 2.9 2.9 3.8 NNE-3 8.3 4.7 6.4 8.2 6.9 +/- 3.3 NNE-35 8.9 4.5 6.5 7.3 NNE-4 5.2 4.0 3.9 6.0 4.0 +/- 2.8 NNE 36 1.7 2.6 3.7 4.8 NE-5 5.2 3.5 5.5 5.9 5.0 +/- 1.7 NE-37 6.1 4.5 4.4 5.2 NE-6 4.3 2.4 3.5 3.8 3.4 +/- 1.5 NE-38 4.1 2.2 3.2 3.7 ENE-7 6.5 4.2 5.1 7.2 5.9 +/- 2.4 ENE-39 6.2 4.5 5.6 7.5 ENE-8 3.7 2.8 3.4 5.3 3.7 +/- 1.8 ENE-40 3.7 2.8 3.3 4.7 E-9 5.2 4.4 5.0 5.9 5.2 +/- 1.2 E-41 5.6 4.5 4.8 6.0 E-1 0 5.0 3.1 4.2 5.9 4.4 +/- 2.0 E-42 5.0 2.9 4.5 4.9 ESE-11 5.2 3.0 4.3 4.8 4.3 +/- 1.7 ESE-43 5.1 3.0 4.1 4.5 ESE-12 5.3 3.1 4.1 5.9 4.6 +/- 2.2 ESE-44 5.4 3.3 4.0 5.8 SE-13 4.8 2.7 3.8 5.5 4.4 +/- 2.3 SE-45 4.6 3.7 3.6 6.3 SE-14 7.3 6.1 5.9 8.1 6.5 +/- 2.1 SE-46 7.1 4.6 6.4 6.8 SSE-15 5.5 3.5 4.5 5.9 4.9 +/- 2.4 SSE-47 5.7 3.1 4.3 6.4 SSE-16 3.3 1.5 2.9 4.0 2.9 +/- 1.8 SSE-48 2.9 1.8 3.0 4.1

Average of collocated TLDs.

32

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS Page mR/Std. Month (30.4 days) +/- 2 Sigma 2 of 4 First Third Fourth Second Quarter Quarter Quarter Quarterly*

Station Quarter 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 +/- ?.3 S-49 8.3 6.8 7.3 9.3 S-18 3.2 1.3 2.3 2.9 2.6 +/- 1.5 S-50 2.7 2.2 2.3 3.9 SSW-19 24.2 14.5 33.7 39.2 27.9 +/- 2, 3.0 SSW-51 39.1 32.3 32.3 7.8 SSW-20 2.9 1.4 2.4 3.0 2.4 +/- 1.6 SSW-52 3.1 1.2 2.0 3.4 SW-21 4.7 4.1 4.5 6.0 4.7 +/- '.9 SW-53 5.5 2.9 4.7 5.1 SW-22 5.1 4.0 4.5 5.5 4.7 +/- .7 SW-54 5.8 3.2 4.6 4.7 WSW-23 5.6 4.1 7.2 6.1 5.8 +/- 2.6 WSW-55 6.5 3.9 5.2 7.4 WSW-24 5.1 3.2 4.5 5.8 4.7 +/- 1.7 WSW-56 5.0 4.2 4.0 5.5 W-25 7.6 5.2 6.7 8.6 7.2 +/- ?.4 W-57 8.3 6.1 6.8 8.2 W-26 4.1 1.6 2.8 3.5 3.1 +/- 1.9 W-58 3.4 2.3 2.6 4.4 WNW-27 3.7 2.7 4.5 3.5 3.7 +/- 1.4 WNW-59 4.2 3.0 3.1 4.6 WNW-28 4.1 2.0 2.9 4.6 3.5 +/- ?.0 WNW-60 4.1 2.5 2.8 4.6 NW-29 7.5 4.4 6.1 7.5 6.4 +/- ?.5 NW-61 6.7 4.7 6.6 7.5 NW-30 2.7 1.0 2.2 3.3 2.2 +/- 1.7 NW-62 2.4 0.9 2.0 2.8 NNW-31 4.5 2.2 3.7 5.1 3.6 +/- 2.0 NNW-63 3.6 2.3 3.1 4.2 NNW-32 4.5 2.7 3.5 5.2 4.0 +/- 2.0 NNW-64 3.5 2.9 3.9 5.5 Mean 5.3 +/- 4.8

Average of collocated TLDs.

33

TABLE 3-2 DIRECT RADIATION MEASURMENTS - PRE-OPERATIONAL LOCATIONS

& EMERGENCY SECTOR Page QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma 3 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Qu arterly*

Statiorn 12/29/2009 03/31/2010 06/30/2010 09/28/2010 Av erage 03/31/2010 06/30/2010 09/28/2010 12/28/2010 +/- 2 s.d.

C-1 3.1 2.0 3.0 3.7 2.9 +/- 1.3 C-2 3.1 2.0 2.7 3.6 C-3"* 3.4 2.6 3.0 4.9 3.4 +/- 1.5 C-4"* 3.5 2.5 3.4 3.5 C-5 2.5 1.7 1.7 3.0 2.3 +/- 1.0 C-6 2.1 2.0 2.1 3.0 C-7"* 3.6 2.6 3.1 3.9 3.4 +/- 1.7 C-8"* 3.6 2.3 3.1 5.1 Mean Indicator 2.6 +/- 0.7 Control** 3.4 +/- 0.8 EPSA-01*** 5.4 4.1 4.8 6.4 5.2 +/- 2.0 EPSA-02*** 5.8 3.9 4.8 6.6 EPSF-03*** 4.7 4.3 4.2 6.4 4.5 +/- 1.9 EPSF-04*** 4.5 2.9 4.1 4.7 EPSR- 5.8 5.0 +/- 1.2 05*** 5.8 4.6 4.6 EPSR-06*** 4.2 4.6 5.5 4.9 EPSJ-07*** 6.0 3.3 3.1 4.7 4.5 +/- 2.4 EPSJ-08*** 5.7 3.0 4.9 5.2 EPSP-09*** 8.2 5.1 6.9 9.3 7.5 +/- 2.7 EPSP-1 0*** 7.6 6.8 7.1 9.0 Mean 5.3 +/- 1.5

Average of collocated TLDs.

- Control Station

- - Emergency Plan TLDs.

34

TABLE 3-2 DIRECT RADIATION MEASURMENTS - ENVIRONMENTAL QUARTERLY TLD RESULTS Page mR/Std. Month (30.4 days) +/- 2 Sigma 4 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Station 12/29/2009 03/31/2010 06/30/2010 09/28/2010 Average Annual TLD 03/31/2010 06/30/2010 09/28/2010 12/28/2010 +/- 2 s.d.

STA-01 5.7 3.9 4.5 6..4 4.7 +1- 1.8 5.1 STA-02 2.2 1.9 2.7 3.0 2.5 +1- 1.0 2.3 STA-03 2.3 1.5 2.0 2.8 2.2 +1- 1.1 2.2 STA-04 2.9 2.6 1.9 3.8 2.8 +1- 1.6 2.3 STA-05 3.3 1.9 3.4 3.6 3.1 +1- 1.6 3.8 STA-05A 3.4 2.0 4.7 4.7 3.7 +1- 2.6 2.9 STA-06 4.2 2.8 4.6 5.8 4.4 +1- 2.5 4.2 STA-07 2.9 2.0 2.6 3.7 2.8 +1- 1.4 3.0 STA-21 2.2 2.0 2.8 4.4 2.9 +1- 2.2 2.6 STA-22 4.2 3.0 4.2 5.4 4.2 +1- 2.0 4.1 STA-23 4.6 4.2 4.4 6.2 4.9 +1- 1.8 4.7 STA-24* 3.1 2.0 3.3 4.9 3.3 +1- 1.2 2.6 Mean - Indicator Locations 3.4 +1- 1.2 3.4 +/- 2.1

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 page Gross Beta Radioactivity 2 of 4

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Ending 22 23 24* 01A 05A I 01/05/10 1.34E+01 2.72E+00 1.65E+01 +/- 2.88E+00 1.36E+01 +/- 2.73E+00 1.75E+01 +/- 2.94E+00 1.20E+01 2.63E+00 1.53E+01 +/- 2.82E+00 01/12/10 1.24E+01 2.58E+00 1.44E+01 +/- 2.70E+00 1.44E+01 +/- 2.70E+00 1.31 E+01 +/- 2.62E+00 8.03E+00 2.32E+00 1.51 E+01 +/- 2.73E+00 01/19/10 1.48E+01 3.32E+00 1.77E+01 +/- 3.45E+00 2.51E+01 +/- 3.75E+00 2.05E+01 +/- 3.56E+00 1.97E+01 3.53E+00 1.96E+01 +I- 3.53E+00 01/28/10 9.44E+00 3.04E+00 1.81E+01 +/- 3.42E+00 1.69E+01 +/- 3.38E+00 1.83E+01 +/- 3.44E+00 1.55E+01 3.31 E+00 1.65E+01 +/- 3.36E+00 02/05/10 1.55E+01 3.26E+00 2.00E+01 +/- 3.46E+00 1.43E+01 +/- 3.20E+00 1.99E+01 +/- 3.46E+00 1.47E+01 3.22E+00 1.48E+01 +/- 3.24E+00 02/09/10 7.92E+00 3.40E+00 1.39E+01 +/- 4.14E+00 1.06E+01 +/- 3.60E+00 1.87E+01 +/- 3.71E+00 1.12E+01 3.67E+00 1.22E+01 +/- 3.44E+00 02/16/10 1.34E+01 3.05E+00 1.53E+01 +/- 3.18E+00 1.46E+01 +/- 3.11E+00 1.32E+01 +/- 3.12E+00 1.29E+01 3.07E+00 1.21E+01 +/- 3.04E+00 02/23/10 9.91 E+00 2.36E+00 1.21E+01 +/- 2.46E+00 1.24E+01 +/- 2.52E+00 1.44E+01 +/- 2.63E+00 1.05E+01 2.36E+00 9.98E+00 +/- 2.37E+00 03/02/10 5.18E+00 2.29E+00 8.71E+00 +/- 2.51 E+00 5.61E+00 +/- 2.31E+00 9.55E+00 +/- 2.50E+00 7.61E+00 2.45E+00 6.76E+00 +/- 2.35E+00 03/09/10 1.47E+01 2.68E+00 1.58E+01 +/- 2.74E+00 1.46E+01 +/- 2.68E+00 1.87E+01 +/- 2.89E+00 1.72E+01 2.82E+00 1.56E+01 +/- 2.73E+00 03/16/10 8.94E+00 3.03E+00 1.10E+01 +/ 3.13E+00 9.01 E+00 +/- 3.03E+00 1.06E+01 +/- 3.11 E+00 6.67E+00 2.94E+00 7.58E+00 +/- 2.96E+00 03/23/10 1.30E+01 3.36E+00 1.70E+01 +/- 3.52E+00 1.48E+01 +/- 3.39E+00 1.67E+01 +/- 3.54E+00 1.76E+01 3.55E+00 1.56E+01 +/- 3.46E+00 03/31/10 1.22E+01 2.47E+00 1.46E+01 +/ 2.57E+00 9.96E+00 +/- 2.37E+00 1.41 E+01 +/- 2.52E+00 1.41E+01 2.59E+00 8.53E+00 +/- 2.24E+00 04/06/10 9.55E+00 3.73E+00 9.95E+00 +- 3.73E+00 1.05E+01 +/- 3.66E+00 1.47E+01 +/- 3.95E+00 1.03E+01 3.73E+00 1.61 E+01 +/- 4.08E+00 04/14/10 1.68E+01 3.00E+00 1.87E+01 +- 3.09E+00 1.71E+01 +/- 3.07E+00 2.10E+01 +/- 3.19E+00 1.78E+01 3.04E+00 1.73E+01 +/- 3.02E+00 04/20/10 1.46E+01 3.10E+00 1.59E+01 +- 3.17E+00 1.35E+01 +/- 3.02E+00 1.80E+01 +/- 3.27E+00 1.55E+01 3.15E+00 1.33E+01 +/- 3.01E+00 04/27/10 1.91E+01 3.29E+00 2.13E+01 +/ 3.39E+00 2.09E+01 +/- 3.39E+00 2.17E+01 +/- 3.42E+00 1.93E+01 3.31 E+00 1.77E+01 +/- 3.25E+00 05/04/10 1.53E+01 3.24E+00 1.57E+01 +/ 3.25E+00 1.65E+01 +/- 3.28E+00 1.32E+01 +/- 3.13E+00 1.61E+01 3.27E+00 1.80E+01 +/- 3.35E+00 05/11/10 1.64E+01 3.15E+00 2.10E+01 +/ 4.97E+00 1.86E+01 +/- 3.25E+00 1.94E+01 +/- 3.28E+00 1.53E+01 3.11E+00 1.61 E+01 +/- 3.13E+00 05/19/10 5.81 E+00 2.04E+00 7.84E+00 +/ 2.24E+00 1.08E+01 +/- 2.33E+00 1.21E+01 +/- 2.46E+00 7.93E+00 2.21 E+00 1.09E+01 +/- 2.34E+00 05/25/10 1.00E+01 3.55E+00 9.39E+00 +/- 3.52E+00 1.11E+01 +/- 3.60E+00 1.21E+01 +/- 3.52E+00 7.56E+00 3.34E+00 1.08E+01 +/- 3.58E+00 06/02/10 1.05E+01 2.86E+00 1.24E+01 +- 3.13E+00 1.17E+01 +/- 2.91 E+00 1.76E+01 +/- 3.17E+00 5.33E+00 2.80E+00 1.30E+01 +/- 2.99E+00 06/08/10 1.45E+01 3.71 E+00 7.18E+00 +- 3.32E+00 1.30E+01 +/- 3.63E+00 1.81E+01 +/- 3.81E+00 1.50E+01 3.71 E+00 1.38E+01 +/- 3.61E+00 06/15/10 1.01 E+01 2.62E+00 1.02E+01 +- 2.63E+00 1.45E+01 +/- 2.85E+00 1.93E+01 +/- 3.11E+00 1.40E+01 2.83E+00 1.07E+01 +/- 2.67E+00 06/22/10 1.33E+01 3.31 E+00 1.33E+01 +/- 3.31E+00 1.04E+01 +/- 3.19E+00 1.17E+01 +/- 3.24E+00 1.02E+01 3.17E+00 1.70E+01 +/- 3.48E+00 06/29/10 2.11E+01 3.61 E+00 1.63E+01 +/ 3.41 E+00 1.50E+01 +/- 3.36E+00 1.92E+01 +/- 3.54E+00 1.85E+01 3.52E+00 1.75E+01 +/- 3.46E+00

Control Station 37

Table 3-3 Air Particulate page Gross Beta Radioactivity 3 of 4

[10-3 pCi/m 3]

Period Ending Station Station 02 Station 03 l

Station 04 I Station 05 I Station 06 Station 07 07/06/10 1.61 E+01 +/- 2.91E+00 1.89E+01 +/- 3.06E+00 1.57E+01 +/- 2.90E+00 1.62E+01 +/- 2.94E+00 1.95E+01 3.10E+00 1.80E+01 +/- 3.02E+00 1.18E+01 +/- 2.71 E+00 07/13/10 2.96E+01 +/- 3.46E+00 3.35E+01 +/- 3.61E+00 2.42E+01 +/- 3.22E+00 2.85E+01 +/- 3.39E+00 3.01E+01 3.46E+00 2.20E+01 +/- 3.10E+00 2.49E+01 +/- 3.24E+00

+/-

07/21/10 2.63E+01 +/- 3.54E+00 2.91 E+01 +/- 3.63E+00 1.36E+01 +/- 3.04E+00 2.07E+01 +/- 3.33E+00 2.OOE+01 3.30E+00 1.75E+01 +/- 3.20E+00 1.46E+01 +/- 3.08E+00 07/27/10 1.62E+01 +/- 3.15E+00 2.51 E+01 +/- 3.61E+00 1.56E+01 +/- 3.14E+00 1.84E+01 +/- 3.29E+00 1.52E+01 3.12E+00 1.73E+01 +/- 3.23E+00 1.61 E+01 +/- 3.17E+00 2.90E+00 +/- +/- 2.92E+00 1.71 E+01 +/- 3.06E+00 08/04/10 1.76E+01 +/- 3.08E+00 2.50E+01 +/- 3.38E+00 1.31 E+01 +/- 1.69E+01 +/- 3.05E+00 1.69E+01 3.05E+00 1.40E+01

+/- 2.41E+01 +/- 3.53E+00 2.18E+01 +/- 3.42E+00 08/12/10 2.37E+01 +/- 3.53E+00 2.93E+01 +/- 3.78E+00 2.OOE+01 +/- 3.32E+00 2.04E+01 +/- 3.34E+00 2.53E+01 3.58E+00 08/18/10 2.23E+01 +/- 3.20E+00 3.06E+01 +/- 3.51 E+00 2.10E+01 +/- 3.13E+00 2.41 E+01 +/- 3.27E+00 2.68E+01 3.38E+00 1.86E+01 +I- 3.04E+00 2.06E+01 +/- 3.12E+00 08/24/10 2.43E+01 +/- 3.69E+00 2.09E+01 +/- 3.62E+00 2.22E+01 +/- 3.56E+00 2.11E+01 +/- 3.50E+00 2.74E+01 3.79E+00 2.61E+01 +/- 3.76E+00 2.15E+01 +/- 3.53E+00 08/31/10 2.35E+01 +/- 3.53E+00 1.93E+01 +/- 3.40E+00 2.05E+01 +/- 3.44E+00 1.92E+01 +/- 3.40E+00 2.38E+01 3.60E+00 2.23E+01 +/- 3.52E+00 2.41E+01 +/- 3.60E+00 09/07/10 2.64E+01 +/- 3.57E+00 2.86E+01 +/- 3.63E+00 2.47E+01 +/- 3.47E+00 2.53E+01 +/- 3.49E+00 3.36E+01 3.83E+00 3.20E+01 +- 3.77E+00 2.67E+01 +/ 3.56E+00 09/14/10 2.55E+01 +/- 3.51 E+00 2.04E+01 +/- 3.31E+00 2.23E+01 +/- 3.41E+00 2.20E+01 +/- 3.40E+00 2.17E+01 3.38E+00 1.62E+01 +/ 3.12E+00 2.OOE+01 +/- 3.30E+00 09/21/10 2.38E+01 +/- 3.56E+00 2.03E+01 +/- 3.38E+00 2.29E+01 +/- 3.59E+00 2.69E+01 +/- 3.72E+00 2.21E+01 3.49E+00 2.20E+01 +/ 3.48E+00 2.55E+01 +/- 3.61 E+00 09/28/10 3.05E+01 +/- 3.54E+00 2.53E+01 +/- 3.34E+00 2.61E+01 +/- 3.27E+00 3.04E+01 +/- 3.48E+00 2.77E+01 3.40E+00 2.41E+01 +/- 3.25E+00 2.35E+01 +/- 3.24E+00

+/-

10/06/10 1.12E+01 +/- 2.60E+00 8.55E+00 +/- 2.46E+00 1.10E+01 +/- 2.66E+00 9.35E+00 +/- 2.55E+00 1.02E+01 2.57E+00 8.81 E+00 +/- 2.50E+00 1.12E+01 +/- 2.61E+00 10/12/10 3.42E+01 +/- 4.42E+00 2.43E+01 +/- 3.99E+00 1.75E+01 +/- 3.70E+00 3.31E+01 +1 4.37E+00 2.79E+01 4.15E+00 2.89E+01 +/- 4.18E+00 2.69E+01 +/- 4.10E+00

+/-

10/19/10 2.12E+01 +/- 3.22E+00 1.31 E+01 +/- 2.83E+00 1.53E+01 +/- 2.93E+00 1.79E+01 +/- 3.06E+00 2.41E+01 3.35E+00 1.70E+01 +/- 3.03E+00 1.32E+01 +/- 2.83E+00 10/26/10 1.80E+01 +/- 3.22E+00 1.79E+01 +/- 3.26E+00 1.83E+01 +/- 3.19E+00 1.65E+01 +/ 3.13E+00 2.43E+01 3.51 E+00 2.01E+01 +/- 3.34E+00 1.74E+01 +/- 3.22E+00 11/02/10 1.51E+01 +/- 3.11E+00 9.87E+00 +/- 2.84E+00 1.26E+01 +/- 2.99E+00 1.30E+01 +/- 3.OOE+00 1.53E+01 3.11E+00 1.47E+01 +/- 3.08E+00 1.18E+01 +/- 2.84E+00 11/09/10 1.27E+01 +/- 3.OOE+00 9.28E+01 +/- 2.83E+00 1.17E+01 +/- 2.94E+00 1.26E+01 +- 2.99E+00 1.38E+01 3.05E+00 8.89E+00 +/- 2.80E+00 7.93E+00 +/- 2.75E+00 11/16/10 1.98E+01 +/- 2.61E+00 1.71E+01 +/- 2.45E+00 1.77E+01 +/- 2.53E+00 2.17E+01 +/ 2.73E+00 2.29E+01 2.78E+00 1.88E+01 +/- 2.56E+00 2.OOE+01 +/- 2.63E+00 11/23/10 2.36E+01 +/- 3.20E+00 2.78E+01 +/- 3.37E+00 2.13E+01 +/- 3.11E+00 2.31 E+01 +/ 3.19E+00 3.09E+01 3.52E+00 2.96E+01 +/- 3.46E+00 3.13E+01 +/- 3.53E+00 11/30/10 1.46E+01 +/- 2.58E+00 1.50E+01 +/- 2.62E+00 2.01E+01 +/- 2.83E+00 1.91E+01 +/- 2.80E+00 1.54E+01 2.62E+00 1.39E+01 +/- 2.55E+00 1.80E+01 +/- 2.78E+00 12/07/10 1.28E+01 +/- 3.03E+00 1.12E+01 +/- 2.96E+00 8.46E+00 +/- 2.82E+00 1.24E+01 +/ 3.02E+00 1.43E+01 3.11E+00 1.21E+01 +/- 3.OOE+00 1.20E+01 +/- 2.99E+00 12/14/10 1.73E+01 +/- 2.86E+00 1.80E+01 +/- 2.89E+00 1.65E+01 +/- 2.81 E+00 1.84E+01 +/ 2.91E+00 2.16E+01 3.07E+00 1.80E+01 +/- 2.89E+00 1.74E+01 +/- 2.86E+00 12/21/10 2.12E+01 +/- 3.44E+00 1.34E+01 +/- 3.03E+00 2.06E+01 +/- 3.41 E+00 2.08E+01 +/- 3.45E+00 2.25E+01 3.48E+00 2.19E+01 +/- 3.45E+00 2.05E+01 +/- 3.36E+00 12/28/10 1.08E+01 +/- 2.48E+00 1.07E+01 +/- 2.50E+00 1.01 E+01 +/- 2.42E+00 1.22E+01 +/- 2.53E+00 1.53E+01 2.73E+00 1.25E+01 +/- 2.59E+00 9.55E+00 +/- 2.43E+00 MEAN 1.77E+01 +/- 3.17E+00 2.05E+01 +/- 3.23E+00 1.59E+01 +/- 3.10E+00 1.70E+01 +/- 3.15E+00 1.82E+01 +/- 3.30E+00 1.60E+01 +/- 3.09E+00 1.63E+01 +/ 3.12E+00 38

Table 3-3 Air Particulate page Gross Beta Radioactivity 4 of 4

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Ending 21I 221 23 23 24*

24*

01A 01A 05A 05A 07/06/10 1.49E+01 +/- 2.86E+00 1.49E+01 +/- 2.86E+00 1.88E+01 +/- 3.06E+00 1.78E+01 +/- 3.02E+00 1.56E+01 +/- 2.90E+00 1.43E+01 +/- 2.84E+00 07/13/10 2.35E+01 +/- 3.19E+00 2.57E+01 +/- 3.29E+00 2.16E+01 +/- 3.10E+00 3.06E+01 +/- 3.49E+00 2.49E+01 +/- 3.25E+00 2.73E+01 +/- 3.35E+00 07/21/10 1.77E+01 +/- 3.20E+00 2.35E+01 +/- 3.42E+00 1.94E+01 +/- 3.27E+00 2.21E+01 +/- 3.38E+00 2.01E+01 +/- 3.31E+00 2.23E+01 +/- 3.39E+00 07/27/10 1.80E+01 +/- 3.25E+00 1.88E+01 +/- 3.30E+00 1.90E+01 +/- 3.31 E+00 2.06E+01 +/- 3.40E+00 1.55E+01 +/- 3.11E+00 1.66E+01 +/- 3.19E+00 08/04/10 1.20E+01 +/- 2.83E+00 1.50E+01 +/- 2.97E+00 1.53E+01 +/- 2.98E+00 2.14E+01 +/- 3.24E+00 1.61E+01 +/- 3.02E+00 1.64E+01 +/- 3.03E+00 08/12/10 2.06E+01 +/- 3.37E+00 2.35E+01 +/- 3.51 E+00 2.50E+01 +/- 3.58E+00 2.33E+01 +/- 3.49E+00 2.40E+01 +/- 3.53E+00 2.24E+01 +/- 3.44E+00 08/18/10 2.21E+01 +/- 3.20E+00 2.45E+01 +/- 3.27E+00 2.34E+01 +/- 3.25E+00 2.66E+01 +/- 3.37E+00 2.05E+01 +/- 3.13E+00 2.10E+01 +/- 3.14E+00 08/24/10 2.15E+01 +/- 3.57E+00 2.42E+01 +/- 3.70E+00 2.18E+01 +/- 3.57E+00 2.59E+01 +/- 3.70E+00 1.87E+01 +/- 3.42E+00 2.62E+01 +/- 3.74E+00 08/31/10 1.97E+01 +/- 3.37E+00 2.29E+01 +/- 3.51E+00 " 2.22E+01 +/- 3.50E+00 2.72E+01 +/- 3.74E+00 1.92E+01 +/- 3.35E+00 2.82E+01 +/- 3.79E+00 09/07/10 2.77E+01 +/- 3.61 E+00 3.OOE+01 +/- 3.70E+00 3.44E+01 +/- 3.87E+00 3.60E+01 +/- 3.91 E+00 2.87E+01 +/- 3.66E+00 3.30E+01 +/- 3.80E+00 09/14/10 1.46E+01 +/- 3.04E+00 2.20E+01 +/- 3.37E+00 1.91E+01 +/- 3.25E+00 2.81 E+01 +/- 3.66E+00 1.99E+01 +/- 3.27E+00 2.08E+01 +/- 3.34E+00 09/21/10 2.66E+01 +/- 3.68E+00 2.44E+01 +/- 3.50E+00 1.38E+01 +/- 3.08E+00 2.91E+01 +/- 3.81E+00 2.35E+01 +/- 3.49E+00 2.62E+01 +/- 3.66E+00 09/28/10 2.55E+01 +/- 3.31E+00 2.55E+01 +/- 3.31E+00 2.15E+01 +/- 3.17E+00 3.27E+01 +/- 3.58E+00 2.07E+01 +/- 3.15E+00 2.74E+01 +/- 3.38E+00 10/06/10 8.85E+00 +/- 2.50E+00 9.44E+00 +/- 2.53E+00 6.46E+00 +/- 2.34E+00 1.25E+01 +/- 2.71 E+00 9.41 E+00 +/- 2.48E+00 1.16E+01 +/- 2.65E+00 10/12/10 2.13E+01 +/- 3.89E+00 3.07E+01 +/- 4.28E+00 3.26E+01 +/- 4.33E+00 3.34E+01 +/- 4.37E+00 3.37E+01 +/- 4.36E+00 3.20E+01 +/- 4.32E+00 10/19/10 2.05E+01 +/- 3.18E+00 2.27E+01 +/- 3.28E+00 1.85E+01 +/- 3.10E+00 2.44E+01 +/- 3.36E+00 1.59E+01 +/- 3.04E+00 1.60E+01 +/- 2.97E+00 10/26/10 2.50E+01 +/- 3.53E+00 1.65E+01 +/- 3.15E+00 2.25E+01 +/- 3.47E+00 1.97E+01 +/- 3.29E+00 2.25E+01 +/- 3.42E+00 1.75E+01 +/- 3.21E+00 11/02/10 1.03E+01 +/- 2.87E+00 1.65E+01 +/- 3.17E+00 1.31E+01 +/- 3.01E+00 1.41E+01 +/- 3.06E+00 1.23E+01 +/- 2.97E+00 1.44E+01 +/- 3.07E+00 11/09/10 1.07E+01 +/- 2.90E+00 7.93E+00 +/- 2.75E+00 1.17E+01 +/- 2.95E+00 1.20E+01 +/- 2.94E+00 1.03E+01 +/- 2.88E+00 1.11E+01 +/- 2.91E+00 11/16/10 1.55E+01 +/- 2.36E+00 2.01E+01 +/- 2.63E+00 2.15E+01 +/- 2.71 E+00 2.42E+01 +/- 2.85E+00 2.42E+01 +/- 2.85E+00 2.47E+01 +/- 2.88E+00 11/23/10 2.14E+01 +/- 3.10E+00 2.42E+01 +/- 3.23E+00 2.31E+01 +/- 3.14E+00 4.10E+01 +/- 3.97E+00 2.11E+01 +/- 3.04E+00 2.38E+01 +/- 3.21 E+00 11/30/10 2.12E+01 +/- 2.93E+00 1.96E+01 +/- 2.84E+00 1.69E+01 +/- 2.74E+00 1.89E+01 +/- 2.79E+00 1.90E+01 +/- 2.86E+00 2.67E+01 +/- 3.19E+00 12/07/10 7.91E+00 +/- 2.79E+00 1.18E+01 +/- 2.99E+00 1.12E+01 +/- 2.95E+00 1.37E+01 +/- 3.08E+00 1.24E+01 +/- 3.02E+00 1.23E+01 +/- 3.01E+00 12/14/10 1.50E+01 +/- 2.74E+00 2.20E+01 +/- 3.09E+00 1.13E+01 +/- 2.53E+00 2.45E+01 +/- 3.20E+00 1.29E+01 +/- 2.62E+00 1.55E+01 +/- 2.76E+00 12/21/10 2.17E+01 +- 3.46E+00 2.28E+01 +/- 3.51 E+00 2.06E+01 +/- 3.34E+00 2.55E+01 +/- 3.64E+00 2.40E+01 +/- 3.56E+00 2.25E+01 +/- 3.49E+00 12/28/10 1.04E+01 +/- 2.45E+00 1.40E+01 +/- 2.66E+00 1.04E+01 +/- 2.50E+00 1.31E+01 +/- 2.58E+00 1.02E+01 +/- 2.45E+00 1.11E+01 +/- 2.49E+00 MEAN 1.54E+01 +/- 3.08E+00 1.75E+01 +/- 3.21E+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 page 1-131 1 of 4

[10-3 pCi/m 3]

Station Station Station Station Period Station S Station 06 Station Endino 01 I 02 03 w04 1205 I 07 -- .

01/05/10 < 3.65E+01 3.70E+01 3.70E+01 < 2.04E+01 3.70E+01 " 3.94E+01 3.94E+01 01/12/10 < 2.66E+01 2.66E+01 2.64E+01 < 2.65E+01 2.99E+01 " 2.99E+01 2.99E+01 01/19/10 < 1.48E+01 2.69E+01 2.70E+01 < 2.69E+01 2.69E+01 < 1.05E+01 2.47E+01 01/28/10 < 1.44E+01 2.62E+01 2.60E+01 < 2.62E+01 2.62E+01 < 3.66E+01 3.66E+01 02/05/10 < 4.98E+00 9.03E+00 9.09E+00 < 9.07E+00 9.07E+00 " 4.59E+00 1.08E+01 02/09/10 < 9.24E+00 5.28E+00 1.04E+01 < 9.37E+00 9.18E+00 < 1.27E+01 1.04E+01 02/16/10 < 4.78E+00 8.73E+00 8.97E+00 < 8.91 E+00 8.86E+00 < 9.68E+00 9.64E+00 02/23/10 < 1.93E+01 1.98E+01 1.11E+01 < 1.98E+01 1.98E+01 < 2.17E+01 2.17E+01 03/02/10 < 7.66E+00 1.78E+01 1.71E+01 < 1.75E+01 1.76E+01 " 9.52E+00 2.24E+01 03/09/10 < 7.28E+00 1.71E+01 1.71E+01 < 1.71E+01 1.71 E+01 " 1.41E+01 1.41E+01 03/16/10 < 1.76E+01 3.01 E+01 2.99E+01 < 3.63E+01 3.OOE+01 < 3.00E+01 3.32E+01 03/23/10 < 2.05E+01 2.04E+01 2.12E+01 < 2.09E+01 < 2.06E+01 < 2.52E+01 2.51E+01 03/31/10 < 2.12E+01 2.13E+01 2.06E+01 < 2.08E+01 0.OOE+00 < 1.89E+01 1.90E+01 04/06/10 < 2.68E+01 2.71E+01 2.69E+01 < 2.77E+01 2.61E+01 < 1.18E+01 2.13E+01 04/14/10 < 2.03E+01 2.03E+01 2.04E+01 < 2.03E+01 4.53E+01 < 1.83E+01 1.01 E+01 04/20/10 < 1.05E+01 2.46E+01 2.45E+01 < 2.46E+01 3.81E+01 " 2.61 E+01 2.61E+01 04/27/10 " 2.50E+01 2.51E+01 2.51E+01 < 2.51E+01 < 1.87E+01 " 1.87E+01 1.87E+01 05/04/10 < 1.18E+01 2.76E+01 2.76E+01 < 2.76E+01 " 2.76E+01 " 2.33E+01 2.33E+01 05/11/10 < 2.58E+00 4.67E+00 4.67E+00 < 4.67E+00 < 4.67E+00 " 6.23E+00 6.23E+00 05/19/10 < 1.32E+01 1.31E+01 1.34E+01 < 1.32E+01 " 1.24E+01 " 1.24E+01 1.24E+01 05/25/10 < 1.07E+01 2.04E+01 1.93E+01 < 1.95E+01 < 2.OOE+01 " 1.89E+01 1.89E+01 06/02/10 " 2.45E+01 4.45E+01 4.47E+01 < 4.49E+01 < 4.49E+01 < 5.26E+01 5.23E+01 06/08/10 " 1.57E+01 2.84E+01 2.82E+01 < 2.82E+01 < 2.82E+01 < 3.54E+01 3.54E+01 06/15/10 " 1.68E+01 1.68E+01 1.69E+01 < 1.69E+01 < 2.42E+01 " 2.42E+01 2.42E+01 06/22/10 " 5.54E+00 1.01E+01 1.01 E+01 < 1.01E+01 < 1.01E+01 < 1.18E+01 1.18E+01 06/29/10 < 2.81E+01 2.79E+01 2.80E+01 < 2.79E+01 < 2.77E+01 < 2.77E+01 2.77E+01 40

Table 3-4 Airborne Iodine page 1-131 2 of 4

[10-3 pCi/m3]

Period Station Station Station Station Station Station S 05A Ending 21 22 23 24* J 2 01A I 01/05/10 < 3.93E+01 < 3.93E+01 < 3.76E+01 < 3.77E+01 < 3.73E+01 < 3.77E+01 01/12/10 " 3.OOE+01 2.40E+01 2.40E+01 2.39E+01 " 2.40E+01 < 1.32E+01 01/19/10 " 2.46E+01 2.47E+01 2.46E+01 2.76E+01 < 2.76E+01 < 2.76E+01 01/28/10 " 3.66E+01 3.65E+01 2.98E+01 2.98E+01 < 2.97E+01 < 2.98E+01 02/05/10 " 1.07E+01 1.07E+01 1.07E+01 2.18E+01 < 2.18E+01 < 2.18E+01 02/09/10 " 1.09E+01 1.26E+01 1.22E+01 1.14E+01 < 2.69E+01 < 1.13E+01 02/16/10 " 9.51 E+00 9.68E+00 9.83E+00 1.02E+01 < 1.OOE+01 < 1.01E+01 02/23/10 " 2.17E+01 2.12E+01 1.08E+01 1.08E+01 < 1.06E+01 < 1.08E+01 03/02/10 < 2.27E+01 2.27E+01 2.26E+01 1.94E+01 < 2.01E+01 " 1.96E+01 03/09/10 " 1.41 E+01 1.41 E+01 1.58E+01 1.58E+01 < 1.58E+01 " 1.58E+01 03/16/10 < 3.33E+01 3.32E+01 3.33E+01 3.63E+01 < 3.66E+01 " 3.63E+01 03/23/10 < 2.54E+01 2.53E+01 1.07E+01 1.10E+01 " 1.09E+01 " 1.09E+01 03/31/10 " 1.91 E+01 1.89E+01 1.48E+01 1.43E+01 " 1.48E+01 " 1.44E+01 04/06/10 < 2.13E+01 2.12E+01 2.25E+01 2.33E+01 < 2.31E+01 < 2.37E+01 04/14/10 " 1.83E+01 1.83E+01 1.11E+01 2.54E+01 < 2.53E+01 < 2.53E+01 04/20/10 < 2.62E+01 2.62E+01 2.50E+01 2.51E+01 < 2.52E+01 < 2.51E+01 04/27/10 " 1.14E+01 1.86E+01 2.16E+01 2.15E+01 < 2.15E+01 < 2.15E+01 05/04/10 < 2.33E+01 2.33E+01 3.42E+01 3.42E+01 < 3.42E+01 < 3.42E+01 05/11/10 < 6.25E+00 1.05E+01 1.21E+01 1.21 E+01 " 1.21E+01 < 1.21E+01 05/19/10 " 1.24E+01 7.1KE+00 1.50E+01 1.55E+01 < 1.53E+01 " 1.51E+01 05/25/10 " 1.90E+01 1.90E+01 2.39E+01 2.29E+01 < 2.32E+01 < 2.38E+01 06/02/10 < 5.22E+01 5.63E+01 5.57E+01 5.59E+01 < 6.01E+01 < 5.61E+01 06/08/10 < 3.61 E+01 3.59E+01 4.85E+01 4.77E+01 < 4.83E+01 < 4.77E+01 06/15/10 < 2.41 E+01 2.36E+01 2.35E+01 7.19E+00 < 2.36E+01 < 2.37E+01 06/22/10 " 1.18E+01 1.18E+01 1.11E+01 1.11E+01 < 1.11E+01 < 1.11E+01 06/29/10 < 2.77E+01 2.49E+01 2.49E+01 2.49E+01 < 2.50E+01 < 1.06E+01 01/05/10 < 3.93E+01 3.93E+01 3.76E+01 3.77E+01 < 3.73E+01 < 3.77E+01

Control Station 41

Table 3-4 Airborne Iodine page 1-131 3 of 4

[10.3 pCi/m 3 ]

Period Station Station Station Station Station Station Station Ending 01 !

02 !

03 1204 !

05 2.E06 J2 07 -I 07/08/09 1.36E+01 < 2.49E+01 " 2.49E+01 " 2.50E+01 " 2.50E+01 " 2.71 E+01 " 2.71E+01 07/13/10 2.26E+01 " 2.26E+01 < 2.26E+01 < 2.25E+01 < 2.44E+01 < 2.44E+01 " 2.45E+01 07/21/10 9.12E+00 " 2.13E+01 < 2.14E+01 < 2.14E+01 < 2.14E+01 < 2.14E+01 < 2.14E+01 07/27/10 8.91 E+00 " 1.07E+01 < 1.94E+01 " 1.95E+01 " 1.95E+01 < 1.95E+01 < 2.49E+01 08/04/10 2.14E+01 " 1.18E+01 < 2.15E+01 < 2.14E+01 " 2.14E+01 < 1129E+01 " 3.03E+01 08/12/10 2.05E+01 < 2.04E+01 < 2.04E+01 < 2.04E+01 " 1.25E+01 < 1.90E+01 " 1.90E+01 08/18/10 9.60E+00 < 9.58E+00 < 9.55E+00 < 9.59E+00 < 9.59E+00 < 3.36E+01 " 3.35E+01 08/24/10 1.99E+01 < 2.06E+01 " 8.36E+00 " 1.96E+01 " 1.96E+01 < 1.43E+01 " 1.42E+01 08/31/10 3.10E+01 < 3.15E+01 " 3.14E+01 " 3.16E+01 < 2.54E+01 " 2.52E+01 < 2.52E+01 09/07/10 3.87E+01 < 3.83E+01 " 3.83E+01 " 2.10E+01 " 3.83E+01 < 1.85E+01 " 4.35E+01 09/14/10 2.99E+01 < 3.02E+01 < 3.04E+01 < 3.04E+01 < 2.35E+01 " 2.35E+01 < 2.35E+01 09/21/10 1.16E+01 < 2.68E+01 < 2.79E+01 < 2.75E+01 < 2.72E+01 < 2.61E+01 < 2.60E+01 09/28/10 3.70E+01 < 3.73E+01 < 3.57E+01 < 3.62E+01 < 1.59E+01 < 1.59E+01 < 2.92E+01 10/06/10 1.82E+01 < 3.28E+01 < 3.40E+01 < 3.36E+01 < 3.32E+01 < 1.87E+01 < 4.34E+01 10/12/10 4.65E+01 " 4.61E+01 < 4.63E+01 < 4.63E+01 < 6.03E+01 < 6.OOE+01 < 6.02E+01 10/19/10 4.24E+01 < 4.25E+01 < 4.24E+01 < 4.24E+01 < 6.08E+01 < 2.60E+01 < 6.10E+01 10/26/10 2.66E+01 " 4.90E+01 < 4.72E+01 < 4.78E+01 < 4.85E+01 < 4.27E+01 < 4.30E+01 11/02/10 5.95E+01 " 5.94E+01 < 5.95E+01 < 5.94E+01 < 5.92E+01 < 5.92E+01 < 3.26E+01 11/09/10 4.16E+01 " 4.16E+01 < 4.13E+01 < 4.15E+01 < 3.22E+01 < 3.22E+01 < 3.22E+01 11/16/10 2.61E+01 " 6.41E+01 < 4.88E+01 < 4.81E+01 < 4.47E+01 < 3.64E+01 < 3.64E+01 11/23/10 6.82E+01 < 6.75E+01 < 6.86E+01 < 6.84E+01 < 6.23E+01 < 6.21 E+01 < 6.20E+01 11/30/10 3.50E+01 < 3.54E+01 < 3.41 E+01 < 3.46E+01 < 1.92E+01 < 3.87E+01 < 3.88E+01 12/07/10 1.17E+01 < 2.14E+01 < 2.14E+01 < 2.14E+01 < 2.14E+01 < 1.78E+01 < 1.78E+01 12/14/10 2.32E+01 < 2.32E+01 < 2.31 E+01 < 2.32E+01 < 2.43E+01 < 2.43E+01 < 2.43E+01 12/21/10 2.64E+01 < 4.68E+01 < 4.79E+01 < 4.85E+01 < 4.77E+01 < 5.40E+01 < 5.34E+01 12/28/10 3.52E+01 < 3.57E+01 < 3.49E+01 < 3.46E+01 < 5.35E+01 < 5.39E+01 < 5.45E+01 42

Table 3-4 Airborne Iodine page 1-131 4 of 4

[10.3 pCi/m 3 ]

Period Station Station S Station 23 Station Station Station Ending I 21 I 22 I 24* I I

01A S 05A I

07/08/09 < 2.70E+01 2.70E+01 < 2.19E+01 < 2.20E+01 2.19E+01 2.20E+01 07/13/10 < 2.46E+01 2.43E+01 " 2.43E+01 < 2.42E+01 2.43E+01 " 1.48E+01 07/21/10 " 2.13E+01 2.13E+01 " 2.66E+01 < 2.67E+01 2.67E+01 " 2.67E+01 07/27/10 < 2.48E+01 2.48E+01 < 2.48E+01 < 1.79E+01 1.77E+01 " 1.79E+01 08/04/10 < 3.03E+01 3.03E+01 < 3.03E+01 " 2.64E+01 2.64E+01 " 2.64E+01 08/12/10 < 1.91 E+01 1.91 E+01 < 2.52E+01 < 2.51E+01 2.52E+01 " 2.51E+01 08/18/10 < 3.37E+01 3.34E+01 < 2.92E+01 " 2.91E+01 2.91E+01 < 2.91 E+01 08/24/10 < 1.44E+01 1.45E+01 " 2.24E+01 < 2.19E+01 2.25E+01 < 2.21 E+01 08/31/10 < 2.48E+01 1.06E+01 < 1.33E+01 < 1.35E+01 1.32E+01 < 1.35E+01 09/07/10 < 4.37E+01 4.37E+01 < 4.34E+01 < 4.30E+01 4.36E+01 < 4.32E+01 09/14/10 < 2.34E+01 1.29E+01 < 2.66E+01 < 5.67E+01 2.65E+01 < 2.68E+01 09/21/10 < 2.62E+01 2.62E+01 < 2.71E+01 " 2.79E+01 2.70E+01 < 2.76E+01 09/28/10 " 2.90E+01 2.89E+01 < 3.02E+01 " 2.92E+01 3.04E+01 < 2.94E+01 10/06/10 " 4.37E+01 4.37E+01 " 4.30E+01 < 1.62E+01 1.57E+01 < 1.61 E+01 10/12/10 < 6.06E+01 5.35E+01 < 5.30E+01 < 5.32E+01 5.29E+01 < 2.93E+01 10/19/10 < 6.07E+01 6.07E+01 " 4.35E+01 < 4.33E+01 4.47E+01 " 4.33E+01 10/26/10 < 4.24E+01 4.24E+01 < 4.88E+01 < 4.76E+01 4.79E+01 < 4.81 E+01 11/02/10 < 5.93E+01 5.93E+01 " 6.90E+01 " 6.90E+01 6.90E+01 < 6.88E+01 11/09/10 < 3.22E+01 3.73E+01 < 3.73E+01 " 3.70E+01 3.74E+01 " 1.59E+01 11/16/10 " 2.OOE+01 3.64E+01 < 3.90E+01 < 3.90E+01 3.89E+01 " 3.90E+01 11/23/10 < 6.25E+01 3.01 E+01 < 4.82E+01 " 5.OOE+01 4.80E+01 " 4.92E+01 11/30/10 " 3.84E+01 3.84E+01 < 3.95E+01 < 3.84E+01 3.97E+01 < 3.88E+01 12/07/10 " 1.78E+01 1.78E+01 < 1.80E+01 < 1.80E+01 1.80E+01 < 1.80E+01 12/14/10 " 2.43E+01 3.19E+01 < 1.36E+01 " 3.19E+01 3.19E+01 < 3.19E+01 12/21/10 < 5.44E+01 5.44E+01 < 4.95E+01 < 5.13E+01 5.10E+01 < 5.08E+01 12/28/10 < 5.35E+01 4.74E+01 < 4.87E+01 < 1.99E+01 4.76E+01 < 4.74E+00

Control Station 43

Table 3-5 Airborne Particulate page Gamma Spectra 1 of 2

[10.3 pCi/m 3 ]

Sampling Quarter 1 Location I Be-7 Cs-1 37** I I 01 1.96E+02 +1- 4.44E+01 " 1.70E+00 < 1.71 E+00 01A 1.35E+02 +/- 3.40E+01 " 1.59E+00 < 1.14E+00 02 1.61 E+02 +/- 4.17E+01 " 1.83E+00 " 1.76E+00 03 1.74E+02 +/- 3.36E+01 " 1.28E+00 < 1.65E+00 04 1.36E+02 +/- 3.13E+01 " 1.32E+00 < 1.38E+00 05 2.07E+02 +/- 4.15E+01 " 1.86E+00 " 1.88E+00 05A 1.56E+02 +/- 3.40E+01 " 1.31 E+00 < 1.13E+00 06 1.03E+02 +/- 3.60E+01 " 1.46E+00 < 1.38E+00 07 1.54E+02 +/- 3.11E+01 " 1.35E+00 < 1.51E+00 21 1.21E+02 +/- 2.84E+01 " 1.27E+00 < 1.26E+00 22 1.82E+02 +/- 3.45E+01 " 1.64E+00 < 1.62E+00 23 1.60E+02 +/- 3.12E+01 " 1.42E+00 " 1.15E+00 24* 1.96E+02 +/- 3.74E+01 " 1.66E+00 < 1.69E+00 Sampling Quarter 2 Location Be-7 Cs-137** Sr-89 Sr-90 I 01 2.01 E+02 +/- 4.43E+01 " 1.94E+00 < 2.20E+00 < 5.75E+00 " 1.88E+00 01A 1.40E+02 +/- 3.85E+01 " 2.19E4+00 < 1.67E+00 " 5.87E+00 " 1.37E+00 02 1.75E+02 +/- 4.22E+01 " 1.83E+00 < 2.07E+00 < 5.62E+00 " 1.70E+00 03 1.71 E+02 +/- 4.21E+01 " 2.12E+00 < 2.OOE+00 < 6.68E+00 " 2.23E+00 04 1.73E+02 +/- 4.63E+01 " 1.77E+00 < 2.03E+00 " 6.57E+00 " 2.66E+00 05 1.74E+02 +/- 4.03E+01 " 1.97E+00 " 1.47E+00 < 7.03E+00 " 2.44E+00 05A 2.26E+02 +/- 4.40E+01 " 1.47E+00 " 2.46E+00 < 7.23E+00 " 2.16E+00 06 1.90E+02 +/- 3.55E+01 " 1.80E+00 " 1.81E+00 < 7.19E+00 " 3.14E+00 07 1.88E+02 +/- 3.29E+01 " 2.20E+00 < 1.81E+00 < 6.67E+00 " 2.43E+00 21 1.61E+02 +/- 4.31E+01 " 2.20E+00 < 1.69E+00 < 5.99E+00 " 1.85E+00 22 1.34E+02 +/- 3.71E+01 " 1.45E+00 < 1.29E+00 < 6.80E+00 " 2.OOE+00 23 1.94E+02 +/- 3.50E+01 " 1.73E+00 < 1.39E+00 < 6.57E+00 " 1.84E+00 24* 1.66E+02 +/- 4.23E+01 " 1.91 E+00 < 1.84E+00 < 5.54E+00 " .7E0 44

Control Station **LLD identified in ODCM Table 3-5 Airborne Particulate page Gamma Spectra 2 of 2

[10-3 pCi/m 3]

Sampling Quarter 3 Location Be-7 Cs-134"* i Cs-137**

I 1.25E+02 +1- 2.99E+01 < 1.69E+00 < 1.46E+00 01 1.29E+02 +1- 2.56E+01 < 1.63E+00 " 1.48E+00 01A 1.58E+02 +/- 3.08E+01 < 1.86E+00 " 1.49E+00 02 1.50E+02 +/- 2.38E+01 < 1.30E+00 " 1.30E+00 03 1.57E+02 +/- 3.06E+01 < 1.45E+00 " 1.46E+00 04 1.45E+02 +/- 3.20E+01 < 1.61E+00 " 1.46E+00 05 1.40E+02 +/- 2.56E+01 < 1.72E+00 " 1.48E+00 05A 1.68E+02 +/- 3.29E+01 < 1.56E+00 " 9.49E-01 06 1.13E+02 +/- 2.84E+01 < 1.46E+00 " 1.38E+00 07 1.35E+02 +/- 3.23E+01 < 1.55E+00 " 1.61 E+00 21 1.25E+02 +/- 2.78E+01 < 1.81 E+00 " 1.58E+00 22 1.39E+02 +/- 2.34E+01 < 1.47E+00 " 1.05E+00 23 1.62E+02 +/- 2.98E+01 < 1.29E+00 " 1.28E+00 24*

MEAN Sampling MEANS Quarter 4 Location Be-7 Cs-1 34** Be-7 I I 01 1.33E+02 +/- 2.68E+01 " 1.43E+00 " 1.20E+00 1.64E+02 +1- 3.64E+01 01A 1.30E+02 +/- 2.41E+01 " 1.19E+00 " 8.22E-01 1.34E+02 3.06E+01 02 1.21E+02 +/- 2.30E+01 " 1.11E+00 " 1.26E+00 1.54E+02 3.44E+01 03 1.20E+02 +1- 2.32E+01 " 1.06E+00 " 1.20E+00 1.54E+02 +1- 3.07E+01 04 1.26E+02 +1- 2.68E+01 " 7.70E-01 " 9.61E-01 1.48E+02 3.38E+01 05 1.27E+02 +/- 2.40E+01 " 1.05E+00 " 9.66E-01 1.63E+02 3.45E+01 05A 1.39E+02 +/- 2.98E+01 " 1.11E+00 " 1.74E+00 1.65E+02 +/ 3.34E+01 06 1.35E+02 +/- 2.83E+01 " 1.43E+00 " 1.33E+00 1.49E+02 3.32E+01 07 1.14E+02 +/- 2.69E+01 " 1.45E+00 " 1.03E+00 1.42E+02 2.98E+01 21 1.15E+02 +/- 2.32E+01 " 1.06E+00 " 1.04E+00 1.33E+02 +/ 3.18E+01 22 1.63E+02 +/- 2.86E+01 " 9.50E-01 " 1.02E+00 1.51E+02 3.20E+01 23 1.34E+02 +/- 2.50E+01 " 1.29E+00 " 1.26E+00 1.57E+02 +/ 2.87E+01 24* 1.17E+02 +/- 2.55E+01 " 6.57E-01 " 5.10E-01 1.60E+02 +/ 3.38E+01 45

Control Station **LLD identified in ODCM Mean of All Indicator Location: 1.51 E+02 +/- 3.24E+01 Table 3-6 Soil page

[pCi/kg] 1 of 3 Sample Stton I Sr-89 Sr-90 I K-40 Cs-134 Date Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Cone 2 Sigma MDC

+/-

7/6/10 01 1.04E+02 5.51 E+01 2.13E+03 1.74E+03 6.33E+01

+/-

7/6/10 02 1.28E+02 7.30E+01 7.98E+03 1.64E+03 4.69E+01

+/-

7/6/10 03 8.91 E+01 3.93E+01 9.11E+03 8.30E+02 7.52E+01 +/- 3.75E+01

+/-

7/6/10 04 1.21E+02 5.91 E+01 3.98E+03 8.42E+02 5.88E+01

+/-

7/6/10 05 9.41E+01 4.85E+01 8.85E+03 1.15E+03 5.45E+01

+/-

7/6/10 05A 9.87E+01 3.67E+01 6.75E+03 1.06E+03 3.09E+02 +/- 5.45E+02

+/-

7/6/10 06 1.18E+02 5.69E+01 1.50E+04 1.48E+03 6.39E+01

+/-

7/6/10 07 8.88E+01 4.97E+01 4.41E+03 1.38E+03 6.04E+01

+/-

7/6/10 21 8.77E+01 3.72E+01 9.89E+03 1.07E+03 4.48E+01

+/-

7/6/10 22 1.15E+02 4.63E+01 1.72E+04 2.02E+03 7.45E+01

+/-

7/6/10 23 1.06E+02 4.31 E+01 2.27E+04 1.73E+03 3.27E+02 +/- 6.95E+01

+/-

7/6/10 24* 1.12E+02 5.63E+01 5.23E+03 9.33E+02 7.10E+01 Sample Station I Cs-i 37 Ra-226 Th-228 Th-232 I l Date Acivity Cone 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC

+/- +/- +/-

7/6/10 01 7.54E+01 2.68E+03 1.53E+03 9.14E+02 1.37E+02 1.09E+03 1.63E+02

+1 +/- +/-

7/6/10 02 1.79E+02 1.09E+02 1.42E+03 6.38E+02 1.24E+02 6.84E+02 1.49E+02

+1 +/- +/-

7/6/10 03 1.18E+02 5.27E+01 3.02E+03 +/- 1.11E+03 1.74E+03 1.31E+02 1.22E+03 1.64E+02

+1 +/- +/-

7/6/10 04 4.01 E+02 7.80E+01 1.95E+03 +/- 1.12E+03 7.47E+02 9.34E+01 5.38E+02 1.58E+02

+- +/- +/-

7/6/10 05 1.91 E+02 7.28E+01 1.81E+03 1.12E+03 1.14E+03 1.14E+02 1.13E+03 1.57E+02

+1 +/- +/-

7/6/10 05A 1.52E+02 4.69E+01 1.77E+03 9.84E+02 1.36E+02

+- +/-

7/6/10 06 4.18E+02 9.62E+01 2.91 E+03 +/- 1.70E+03 9.44E+02 1.79E+02 1.37E+03 +/- 2.24E+02

+1 +/-

7/6/10 07 9.72E+01 8.36E+01 1.96E+03 +/- 1.97E+03 1.02E+03 1.68E+02 1.21E+03 +/- 1.79E+02

+1 +/-

7/6/10 21 5.27E+01 8.09E+01 1.26E+03 +/- 9.25E+02 4.51 E+02 7.71 E+01 4.41 E+02 +/- 1.48E+02

.7/6/10 1.46E+02 +- 6.04E+01 4.63E+03 2.11E+03 2.01 E+03 +/- 1.70E+02 22 1.90E+03 +/- 2.43E+02

+- +/- +/-

7/6/10 23 1.49E+02 6.37E+01 2.28E+03 1.16E+03 1.30E+02 9.30E+02 +/- 2.06E+02

+/-

7/6/10 24* 8.42E+01 +1 5.48E+01 2.79E+03 1.58E+03 1.53E+03 1.23E+02 1.21E+03 2.45E+02

Control Station 46

Table 3-6 Soil page

[pCi/kg] 2 of 3 Sample Station I Sr-89 Sr-90 K-40 Cs-134 Date Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC

+/-

11/9/10 01 7.73E+02 4.44E+01 1.72E+04 1.52E+03 5.75E+01

+/-

11/9/10 02 6.85E+02 4.15E+01 9.51E+03 1.44E+03 6.55E+01

+/-

11/9/10 03 6.15E+02 4.12E+01 3.99E+03 8.09E+02 5.52E+01

+/-

11/9/10 04 6.47E+02 4.31 E+01 9.OOE+03 1.37E+03 6.62E+01

+/-

11/9/10 05 7.72E+02 4.47E+01 1.46E+04 1.55E+03 6.42E+01

+/-

11/9/10 05A 7.04E+02 4.57E+01 8.36E+03 1.15E+03 6.33E+01

+/-

11/9/10 06 6.44E+02 5.25E+01 1.05E+04 1.57E+03 7.21 E +01

+/-

11/9/10 07 5.71 E+02 3.64E+01 5.77E+03 1.24E+03 7.27E+01

+< +/-

11/9/10 21 5.94E+02 3.84E+01 1.17E+04 1.20E+03 6.21 E+01

+< +/-

11/9/10 22 6.59E+02 3.79E+01 1.56E+04 1.66E+03 8.07E+01

+< +1-11/9/10 23 7.10E+02 3.09E+01 2.40E+04 1.54E+03 5.58E+01

+/-

11/9/10 24* 7.53E+02

+<

3.55E+01 2.78E+03 8.94E+02 5.14E+01

+/-

MEANS Indicators 1.08E+04 1.36E+03 2.37E+02 +1 2.37E+02

+< 4.01E+03 +/-

Control 9.14E+02

+<

Ra-226 Th-228 Th-232 Sample Station -I Cs-i 37 I I I Date +< 2 Sigma 2 Sigma Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc MDC Acivity Conc MDC

+< +/- +/-

11/9/10 01 6.65E+01 1.73E+03 1.07E+03 1.06E+03 9.68E+01 8.57E+02 1.73E+02

+< +/- +/-

11/9/10 02 6.20E+02 +/- 1.05E+02 2.37E+03 1.65E+03 4.86E+02 9.87E+01 3.90E+02 1.72E+02

+/- +/- +/-

11/9/10 03 3.76E+02 7.03E+01 2.OOE+03 1.26E+03 6.04E+02 9.76E+01 3.87E+02 1.26E+02

+/- +/- +/-

11/9/10 04 7.32E+02 1.15E+02 1.65E+03 1.19E+03 1.28E+02 9.94E+02 2.62E+02

+/- +/- +/-

11/9/10 05 1.71 E+02 7.72E+01 2.47E+03 1.33E+03 1.27E+03 1.18E+02 1.29E+03 1.70E+02

+/- +/-

11/9/10 05A 7.94E+01 1.66E+03 5.90E+02 1.43E+02 8.19E+02 1.63E+02

+/- +/- +/-

11/9/10 06 1 .67E+02 1.09E+02 2.02E+03 +/- 1.46E+03 2.33E+03 1.67E+02 2.09E+03 2.79E+02 11/9/10 07 4.07E+02 +I- 9.07E+01 2.21E+03 1.75E+03 +/- 1.31E+02 1.19E+03 +/-

1.36E+03 2.56E+02 11/9/10 +/- 1.84E+03 1.36E+03 +/- +/-

21 5.85E+02 8.76E+01 5.90E+02 9.73E+01 4.94E+02 1.38E+02

+/- +/-

11/9/10 22 1.08E+02 3.66E+03 1.76E+03 1.69E+03 1.43E+02 1.75E+03 2.78E+02

+/- +/- +/-

11/9/10 23 1.31 E+02 6.19E+01 2.25E+03 1.14E+03 1.93E+03 1.13E+02 1.93E+03 1.68E+02 11/9/10 24* 3.62E+02 +/- 8.41 E+01 3.01 E+03 1.39E+03 1.01E+03 +/- 9.93E+01 9.68E+02 +/- 1.84E+02 2.83E+02 +/- 8.12E+01 2.40E+03 1.51E+03 1.13E+03 +/- 1.27E+02 1.08E+03 +1-Indicator 1.89E+02 MEANS +/- +/-

Control 2.23E+02 +1- 6.95E+01 2.90E+03 1.49E+03 1.27E+03 1.11E+02 1.09E+03 2.15E+02 47

Control Station Table 3-6 Soil page

[pCi/kg] 3 of 3 Station Mean Sr-89 I Sr-90 I K-40 Cs-134 Station 2 Sigma Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigm a MDC Acivity Conc MDC Acivity Conc 2 Sigma MDC 9.67E+03 +/- 1.63E+03 01 8.75E+03 +/-

02 1.54E+03

+/-

03 6.55E+03 8.20E+02 7.52E+01 +/- 3.75E+01 6.49E+03 +/-

04 1.11E+03 1.17E+04 +/-

05 1.35E+03

+/- +/- 5.45E+02 05A 7.56E+03 1.11E+03 3.09E+02

+/-

06 1.28E+04 1.53E+03

+/-

07 5.09E+03 1.31 E+03 1.08E+04 +/- 1.14E+03 21 1.64E+04 +/- 1.84E+03 22

+/-

23 2.34E+04 1.64E+03 3.27E+02 +/- 6.95E+01

+/-

24* 4.01 E+03 9.14E+02 Cs-137 Ra-226 Th;228 Th-232 Station ! !

2 Sigma l

2 Sigma 2 Sigma Acivity Conc 2 Sigma MDC Acivity Conc MDC Acivity Conc MDC Acivity Conc MDC 2.21 E+03 +/- +/- +/-

01 1.30E+03 9.87E+02 1.17E+02 9.74E+02 1.68E+02 4.OOE+02 +1- 1. 07E+02 2.37E+03 +/- 1.65E+03 5.62E+02 +/- 1.11E+02 +/-

02 5.37E+02 1.61 E+02 2.47E+02 +1- 6. 15E+01 2.51E+03 +/- 1.19E+03 1.17E+03 +/- +/-

03 1.14E+02 8.04E+02 1.45E+02 5.67E+02 +1- 9. 65E+01 1.95E+03 +/- 1.12E+03 9.69E+02 +/- +/-

04 1.11E+02 7.66E+02 2.10E+02 1.81E+02 +1- 7. 50E+01 2.14E+03 +/- 1.23E+03 1.21E+03 +/- 1.16E+02 +/-

05 1.21E+03 1.64E+02 1.52E+02 +1- 4.69E+01 7.87E+02 +/- 1.40E+02 +/-

05A 8.19E+02 1.63E+02 2.93E+02 +1- 1.03E+02 2.47E+03 +/- +/- +/-

06 1.58E+03 1.64E+03 1.73E+02 1.73E+03 .2.52E+02 2.52E+02 +1- 8.72E+01 2.09E+03 +/- +/- +/-

07 1.86E+03 1,.19E+03 1.50E+02 1.20E+03 2.18E+02 3.19E+02 +1- 8.43E+01 1.55E+03 +/- +/- +/-

21 1.14E+03 5.21 E+02 8.72E+01 4.68E+02 1.43E+02 1.46E+02 +1- 6.04E+01 4.15E+03 +/- 1.94E+03 1.85E+03 +/- 1.57E+02 +/-

22 1.83E+03 2.61E+02 1.40E+02 +1- 6.28E+01 2.25E+03 +/- 1.14E+03 1.55E+03 +/- 1.22E+02 +/-

23 1.43E+03 1.87E+02 2.23E+02 +1- 6.95E+01 2.90E+03 +/- 1.49E+03 1.27E+03 +/- 1.11E+02 +/-

24* 1.09E+03 2.15E+02

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

LLD identified in ODCM 49

Table 3-7 Precipitation page Gamma Spectra 2 of 2

[pCi/L]

Sampling Location Be-7 Mn-54 Fe-59 Co-58 Co-60 O]A 06/29/10 3.78E+01 +/- 2.64E+01 < 4.74E-01 < 4.18E+00 1.08E+00 < 4.14E-01 12/28/10 < 4.87E+01 < 1.50E+00 1.45E+01 3.55E+00 < 1.21E+00 Zn-65 I Zr-95 I Nb-95 I Cs-134 I Cs-137 I 01A 06/29/10 < 1.01E+00 < 2.19E+00 < 1.36E+00 < 3.64E-01 < 4.37E-01 12/28/10

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 01A 06/29/10 < 1.11E+03 < 2.78E+02 1.72E+04 1.08E+00 4.49E+00 +/- 2.86E+00 12/28/10 < 2.52E+03 < 8.30E+02 3.22E+04 2.41 E+00 0.OOE+00 MEAN Sampling Location Be-7 Mn-54 Fe-59 Co-58 Co-60 O]A 3.78E+01 +/- 3.76E+01 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-137 I 01A Ba-140 Law140 1-131 I Th-228 I Th-232 I 01A 4.49E+00 +/- 2.86E+00 50

Table 3-8 Milk page Gamma Spectra & Strontium 1 of 1

[pCi/L]

Sampling Station 12 S La-140*

Date K-40 Sr-89 I Sr-90 I 1-i31* 1 Cs-134* !

Cs-137* !

Ba-140* !

01/19/10 1.49E+03 +/- 1.49E+02 [a] [a] < 6.74E-01 < 7.41 E+00 8.OOE+00 4.42E+01 < 9.18E+00 02/16/10 1.45E+03 +/- 1.25E+02 [a] [a] < 6.13E-01 < 1.97E+00 2.24E+00 1.20E+01 < 4.15E+00 03/16/10 1.52E+03 +- 1.50E+02 < 4.37E+00 1.17E+00 < 5.90E-01 < 5.65E+00 < 6.51E+00 3.96E+01 < 1.23E+01 04/20/10 1.27E+03 +/ 1.16E+02 [a] [a] < 7.80E-01 < 4.81 E+00 < 5.26E+00 2.36E+01 " 5.92E+00 Dairy ceased operations in May 2010.

Sta. Mean 1.43E+03 +/- 1.35E+02 Sampling Station 12A S La-140*

Date K-40 Sr-89 I Sr-90 I 1-131* I Cs-i134* Cs-1 37* Ba-140* I 05/19/10 1.30E+03 1.03E+02 [a] [a] < 9.OOE-01 " 4.01E+00 < 4.18E+00 4.76E+01 < 1.31E+01 06/15/10 1.16E+03 1.62E+02 3.28E+00 1.59E+00 < 7.27E-01 < 8.42E+00 - 8.83E+00 4.47E+01 < 1.26E+01 07/21/10 1.26E+03 6.OOE+01 [a] [a] < 6.05E-01 <- 2.55E+00 < 2.86E+00 1.31E+01 < 3.45E+00 08/18/10 1.47E+03 1.31E+02 [a] [a] < 8.35E-01 < 4.85E+00 < 4.41 E+00 3.58E+01 < 8.66E+00 09/21/10 1.22E+03 1.34E+02 2.33E+00 1.06E+00 < 5.51E-01 " 6.26E+00 < 7.43E+00 4.29E+01 < 7.83E+00 10/19/10 1.25E+03 1.43E+02 3.76E+00 8.44E-01 < 8.33E-01 < 5.24E+00 < 6.55E+00 2.59E+01 < 8.61E+00 11/19/10 1.44E+03 1.59E+02 [a] [a] < 7.03E-01 < 5.58E+00 < 5.98E+00 2.74E+01 < 1.03E+01 12/17/09 1.30E+03 1.19E+02 4.96E+00 1.23E+00 < 4.33E-01 < 4.66E+00 < 4.99E+00 3.59E+01 < 1.03E+01 Sta. Mean 1.30E+03 +/- 1.26E+02 Total 1.34E+03 +/-

1.29E+02 Mean

LLD identified in ODCM

[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.

51

Table 3-9 Food and Vegetation Gamma Spectra page

[pCi/kg] 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-* 05/11/10 3.17E+02 1.85E+02 5.59E+03 5.53E+02 4.58E+01 2.06E+01 2.26E+01

- Control 06/08/10 6.64E+02 1.05E+02 1.07E+04 3.56E+02 3.07E+01 1.24E+01 1.35E+01 Station 07/13/10 7.38E+02 2.80E+02 5.28E+03 5.24E+02 4.92E+01 2.87E+01 2.90E+01 08/10/10 5.44E+02 4.56E+02 4.93E+03 7.83E+02 3.19E+01 4.35E+01 4.43E+01 09/14/10 7.33E+02 2.85E+02 3.17E+03 4.99E+02 3.10E+01 2.33E+01 2.35E+01 10/12/10 1.26E+03 5.81E+01 5.20E+03 1.37E+02 3.65E+01 3.33E+00 3.99E+00 Mean 7.09E+02 +/- 1.96E+02 5.81E+03 +/- 4.07E+02 +/- +/- +/-

LLD identified in ODCM 52

Table 3-9 Food and Vegetation page Gamma Spectra 2 of 2

[pCi/kg]

Sampling Sampling Location Date I Be-7 I K-40 I 1-131* I Cs-134* I Cs-1 37*

23 05/11/10 :7.31E+02 +/- 1.85E+02 7.25E+03 3.21 E+02 2.93E+01 2.06E+01 1.99E+01 06/08/10 1.65E+03 +/- 2.15E+02 5.75E+03 3.84E+02 2.82E+01 1.54E+01 1.74E+01 07/13/10 1.24E+03 +/- 2.24E+02 3.64E+03 4.49E+02 5.66E+01 2.43E+01 3.24E+01 08/10/10 2.81 E+03 +/- 5.11E+02 2.92E+03 5.67E+02 2.61E+01 5.79E+01 5.93E+01 09/14/10 2.21 E+02 2.52E+03 3.98E+02 4.20E+01 1.97E+01 2.45E+01 10/12/10 1.69E+03 +/- 9.86E+01 3.75E+03 1.50E+02 3.67E+01 5.78E+00 6.29E+00 Mean 1.62E+03 +/- 2.47E+02 4.31E+03 +/- 3.24E+02 Sampling Sampling Location Date Be-7 K-40 1-131* Cs-134* I Cs-1 37*

26 05/11/10 4.92E+02 2.01 E+02 6.60E+03 6.29E+02 3.49E+01 2.25E+01 2.27E+01 06/08/11 1.46E+03 1.44E+02 4.74E+03 2.67E+02 2.98E+01 1.32E+01 1.49E+01 0713/10 7.55E+02 3.43E+02 5.68E+03 7.30E+02 3.92E+01 3.28E+01 4.08E+01 08/10/10 1.41E+03 5.17E+02 4.24E+03 1.02E+03 3.68E+01 5.89E+01 7.46E+01 09/14/10 3.82E+02 2.26E+02 2.08E+03 3.57E+02 4.01E+01 2.16E+01 2.39E+01 10/12/10 1.69E+03 7.72E+01 2.58E+03 1.19E+02 3.56E+01 5.46E+00 5.80E+00 Mean 1.03E+03 +/- 2.515E+02 4.32E+03 +/- 4.46E+02 +/- +/- +/-

+/- +/- +/-

Indicator locations 1.26E+03 +/- 2.55E+02 4.91 E+03 +/- 3.97E+02

LLD identified in ODCM 53

Table 3-10 Well Water page Gamma Spectra, Strontium, and Tritium 1 of 1

[pCi/L]

Sampling Station 01A Date H-3 Sr-89 Sr-90 Mn-54 I Fe-59 Co-58 I Co-60 Zn-65 03/31/10 6.26E+02 [a] [a] 3.48E+00 6.24E+00 3.73E+00 3.17E+00 6.82E+00 06/29/10 7.12E+02 3.23E+00 6.24E-01 1.81E+00 4.56E+00 2.10E+00 1.98E+00 3.99E+00 09/28/10 1.69E+02 [a] [a] 2.60E+00 5.58E+00 3.06E+00 2.63E+00 5.60E+00 12/28/10 4.02E+02 [a] [a] 2.49E+00 5.84E+00 2.51 E+00 2.53E+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 6.57E+00 3.85E+00 5.69E-01 2.97E+00 3.32E+00 2.22E+01 8.48E+00 06/29/10 3.51 E+00 2.16E+00 6.70E-01 1.86E+00 1.97E+00 1.31 E+00 4.58E+00 09/28/10 5.32E+00 3.17E+00 7.13E-01 2.73E+00 2.79E+00 1.97E+01 6.47E+00 12/28/10 4.91 E+00 2.92E+00 7.19E-01 2.46E+00 2.68E+00 1.72E+01 6.46E+00 Mean

[a] Sr-89/90 analyses performed on the second quarter sample.

54

Table 3-11 River Water page Gamma Spectra, Strontium, and Tritium 1 of 1

[pCi/L]

Sampling Station 11 Date H-3* Sr-89 Sr-90 I Mn-54* Fe-59* I Co-58* I Co-60* I Zn-65*

01/12/10 [a] [b] [b] 3.33E+00 < 9.03E+00 4.14E+00

3.76E+00 7.56E+00 02/15/10 [a] [b] [b] 4.49E+00 < 8.98E+00 3.60E+00

4.39E+00 7.98E+00 03/16/10 4.66E+03 +/- 9.21E+02 [b] [b] 4.33E+00 < 8.49E+00 3.58E+00

3.90E+00 7.34E+00 04/13/10 [a] [b] [b] 1.70E+00 < 4.41 E+00 2.03E+00

1.74E+00 3.54E+00 05/10/10 (a] [b] [b] 2.84E+00 < 6.81 E+00 3.16E+00

2.57E+00 6.14E+00 06/14/10 3.77E+03 +/- 7.44E+02 3.59E+00 6.25E-01 3.78E+00 < 6.83E+00 3.52E+00

3.07E+00 8.57E+00 07/12/10 [a] [b] [b] 4.66E+00 < 1.18E+01 5.01E+00

5.55E+00 9.80E+00 08/16/10 [a] [b] [b] 4.05E+00 < 8.85E+00 4.78E+00

4.30E+00 8.67E+00 09/14/10 3.36E+03 +/- 5.82E+02 [b] [b] 4.20E+00 < 9.05E+00 3.06E+00

4.80E+00 9.14E+00 10/10/10 [a] [b] [b] 1.82E+00 < 3.93E+00 1.90E+00

1.80E+00 3.69E+00 11/16/10 [a] [b] [b] 4.71 E+00 < 8.77E+00 4.14E+00

4.58E+00 7.94E+00 12/13/10 2.25E+03 +/- 7.34E+02 [b] [b] 3.69E+00 < 9.04E+00 4.55E+00 *3.71 E+00 8.96E+00 MEAN 3.51E+03 +/- 7.45E+02 Sampling Date Zr-95* Nb-95* I 1-131* I Cs- 134* Cs-137* Ba-140* La-140*

01/12/10 6.43E+00 4.21 E+00 5.96E-01 3.51 E+00 4.25E+00 2.69E+01 9.74E+00 02/15/10 7.62E+00 5.OOE+00 7.47E-01 4.18E+00 4.86E+00 2.26E+01 6.97E+00 03/16/10 7.11 E+00 4.70E+00 5.77E-01 3.77E+00 3.73E+00 2.14E+01 7.20E+00 04/13/10 3.36E+00 2.07E+00 5.36E-01 1.66E+00 1.75E+00 1.81E+01 5.40E+00 05/10/10 5.38E+00 3.27E+00 6.57E-01 2.72E+00 3.36E+00 2.07E+01 6.38E+00 06/14/10 6.22E+00 4.42E+00 8.34E-01 3.56E+00 3.86E+00 2.73E+01 9.27E+00 07/12/10 6.99E+00 6.43E+00 6.40E-01 5.34E+00 5.72E+00 2.23E+01 7.92E+00 08/16/10 7.38E+00 4.43E+00 9.34E-01 3.43E+00 4.38E+00 2.28E+01 6.60E+00 09/14/10 6.56E+00 5.OOE+00 1.OOE+00 3.07E+00 5.08E+00 2.50E+01 1.42E+01 10/10/10 3.43E+00 2.16E+00 8.74E-01 1.74E+00 1.98E+00 1.22E+01 3.64E+00 11/16/10 7.28E+00 4.72E+00 5.81E-01 4.16E+00 4.25E+00 2.06E+01 5.86E+00 12/13/10 7.83E+00 4.42E+00 5.56E-01 4.99E+00 5.28E+00 2.52E+01 1.01E+01 MEAN

LLD identified in ODCM [a] Tritium analyses on quarterly composite. [b] Sr-89/90 performed annually on 2nd quarter composite sample.

55

Table 3-12 Surface Water page Gamma Spectra, Strontium, Tritium 1 of 2

[pCi/L]

Sampling Station 08 Date H-3*

I Sr-89 b Sr-90 I Mn-54* Fe-59*

I Co-58*

I Co-60" SZn5.5*

01/12/10 [a] [b] [b] < 2.83E+00 " 6.60E+00 < 2.70E+00 < 2.70E+00 " 5.85E+00 02/15/10 [a] [b] [b] < 4.48E+00 < 8.52E+00 < 4.11E+00 < 4.29E+00 < 7.81E+00 03/16/10 3.35E+03 +/- 7.91E+02 [b] [b] < 3.55E+00 " 6.45E+00 < 3.07E+00 < 3.81E+00 < 4.95E+00 04/13/10 [a] [b] [b] < 1.77E+00 " 4.54E+00 < 1.91E+00 < 1.78E+00 < 3.39E+00 05/10/10 [b] [b] < 3.20E+00 < 7.85E+00 < 3.05E+00 < 3.36E+00 < 7.42E+00 06/14/10 2.34E+03 +/- 6.25E+02 < 4.33E+00 < " 8.07E+00 3.25E+00 2.82E+00 6.72E-01 < 2.85E+00 < < < 6.70E+00 07/12/10 [a] [b] [b] < 7.83E+00 < 1.46E+01 < 6.19E+00 < 5.79E+00 < 1.16E+01 08/16/10 [a] [b] [b] < 4.87E+00 < 1.23E+01 < 5.59E+00 < 5.06E+00 < 1.18E+01 09/14/10 4.06E+03 +/- 6.45E+02 [b] [b] < 7.83E+00 < 1.50E+01 < 8.20E+00 < 7.29E+00 < 1.22E+01 10/10/10 [a] [b] [b] < 1.32E+00 < 3.21 E+00 < 1.41E+00 < 1.37E+00 < 2.60E+00 11/16/10 [a] [b] [b] < 3.24E+00 < 7.10E+00 < 2.93E+00 < 3.47E+00 < 7.37E+00 12/13/10 2.65E+03 +/- 7.81E+02 [b) [b] < 4.43E+00 < 1.OOE+01 < 4.73E+00 < 4.22E+00 " 8.52E+00 Mean 3.10E+03 +/- 7.11E+02 Sampling Date Zr-95* Nb-95* 1-131 I Cs-134 I Cs-137 I Ba-140* La-140*

I I I 01/12/10 < 5.11E+00 < 3.30E+00 < 3.96E-01 < 2.63E+00 < 2.96E+00 < 2.05E+01 < 6.02E+00 02/15/10 < 7.37E+00 < 4.44E+00 < 5.68E-01 < 4.30E+00 < 4.59E+00 < 2.24E+01 < 8.06E+00 03/16/10 < 6.38E+00 < 3.11E+00 < 9.31 E-01 < 3.02E+00 < 3.82E+00 < 1.96E+01 < 6.14E+00 04/13/10 < 3.54E+00 < 1.97E+00 < 6.85E-01 < 1.60E+00 < 1.93E+00 < 1.64E+01 < 6.09E+00 05/10/10 < 6.57E+00 6.28E+00 +/- 2.53E+00 < 6.74E-01 < 2.76E+00 < 3.19E+00 < 2.11E+01 < 8.15E+00 06/14/10 < 5.64E+00 < 3.93E+00 < 9.03E-01 < 3.30E+00 < 3.17E+00 < 2.36E+01 < 7.26E+00 07/12/10 < 1.09E+01 < 6.10E+00 < 5.05E-01 < 6.73E+00 < 5.59E+00 < 2.48E+01 < 9.47E+00 08/16/10 < 8.95E+00 < 5.41 E+00 < 9.20E-01 < 4.98E+00 < 5.43E+00 < 2.88E+01 < 1.OOE+01 09/14/10 < 1.66E+01 < 8.35E+00 < 8.15E-01 < 5.69E+00 < 8.76E+00 < 5.37E+01 < 1.22E+01 10/10/10 < 2.42E+00 < 1.54E+00 < 4.67E-01 < 1.24E+00 < 1.42E+00 < 8.88E+00 < 2.93E+00 11/16/10 < 6.17E+00 < 3.75E+00 < 6.66E-01 < 3.64E+00 < 3.67E+00 < 1.95E+01 < 5.58E+00 12/13/10 < 8.05E+00 < 4.43E+00 < 5.34E-01 < 3.63E+00 < 5.03E+00 < 2.33E+01 < 5.54E+00 Mean 6.28E+00 +/- 2.53E+00

LLD identified in

[a] Tritium analyses on quarterly composite.

ODCM [b] Sr-89/90 performed annually on 2nd quarter composite sample.

56

Table 3-12 Surface Water page Gamma Spectra, Strontium, Tritium 2 of 2

[pCi/L]

Sampling Station 09A Date H-3* I Sr-89 I

[b Sr-90 I Mn-54*

3.15E+00 Fe-59*

< 7.56E+00 I <

Co-58" 3.78E+00 I Co-60"

" 4.05E+00 < 7.O0E+00 01/12/10 [a] [b]

[b] [b < 3.99E+00 < 7.66E+00 < 4.58E+00 " 3.21E+00 < 9.22E+00 02/15/10 [a]

[b] [b] < 4.12E+00 < 9.62E+00 < 5.07E+00 " 4.88E+00 < 6.61E+00 03/16/10 < 8.50E+02

[b] < 1.66E+00 < 4.16E+00 < 1.84E+00 " 1.57E+00 < 3.24E+00 04/13/10 [a] [b]

[b] < 3.21 E+00 < 7.63E+00 < 3.33E+00 " 3.50E+00 < 7.05E+00 05/10/10 [a] [b]

< 5.39E-01 < 3.88E+00 < 9.76E+00 < 4.36E+00 " 3.30E+00 < 9.09E+00 06/14/10 8.63E+02 < 3.35E+00

[b] < 5.43E+00 < 1.06E+01 < 4.57E+00 < 3.68E+00 < 9.12E+00 07/12/10 [a] [b]

[b] < 4.70E+00 < 8.83E+00 < 4.63E+00 " 4.89E+00 < 9.47E+00 08/16/10 [a] [b]

< 5.80E+02 [b] [b] < 3.96E+00 < 1.11E+01 < 4.86E+00 " 4.77E+00 < 6.70E+00 09/14/10

[b] < 1.96E+00 < 4.27E+00 < 2.16E+00 < 1.94E+00 " 4.28E+00 10/10/10 [a] [b]

[b] < 4.42E+00 < 9.02E+00 < 3.94E+00 < 4.13E+00 < 9.76E+00 11/16/10 [a] [b]

[b] < 3.53E+00 < 8.76E+00 < 4.04E+00 < 4.43E+00 < 9,44E+00 12/13/10 < 9.88E+02 [bI MEAN Sampling Date J Zr-95* j Nb-95* J 1-131" SCs-134" 0 Cs-137"6+ Ba-140" La-140*

l I

< 3.81E+00 < 4.11E-01 " 3.13E+00 3.46E+00 < 2.45E+01 < 9.28E+00 01/12/10 < 6.26E+00 <

6.01E+00 < 4.51E+00 < 4.38E-01 < 3.48E+00 " 3.88E+00 < 2.23E+01 " 6.26E+00 02/15/10 <

8.65E+00 < 4.42E+00 < 5.47E-01 < 4.OOE+00 < 4.78E+00 < 2.55E+01 < 7.94E+00 03/16/10 <

< 3.31 E+00 < 2.OOE+00 < 3.09E-01 < 1.52E+00 < 1.68E+00 < 1.63E+01 < 5.42E+00 04/13/10

< 5.79E+00 < 3.56E+00 < 7.87E-01 < 2.78E+00 < 3.29E+00 < 2.38E+01 < 8.08E+00 05/10/10 9.17E+00 < 5.01E+00 < 7.88E-01 < 3.80E+00 < 4.31 E+00 < 2.99E+01 < 1.24E+01 06/14/10 <

9.73E+00 < 5.11E+00 < 6.44E-01 < 5.53E+00 " 5.49E+00 < 2.38E+01 < 1.OOE+01 07/12/10 <

< 5.10E+00 < 6.46E-01 < 4.32E+00 < 4.75E+00 " 2.54E+01 < 9.33E+00 08/16110 < 8.95E+00

< 3.77E+00 < 9.43E-01 < 3.24E+00 < 5.OOE+00 < 2.84E+01 < 1.20E+01 09/14/10 < 7.60E+00 3.63E+00 < 2.26E+00 < 4.84E-01 < 1.89E+00 < 2.08E+00 < 1.33E+01 < 4.02E+00 10/10/10 <

7.76E+00 < 4.94E+00 < 7.OOE-01 < 4.02E+00 < 4.69E+00 < 2.34E+01 < 5.48E+00 11/16/10 <

8.16E+00 < 3.75E+00 < 5.90E-01 < 3.77E+00 < 4.36E+00 < 1.94E+01 < 7.73E+00 12/13/10 <

MEAN LLD identified in ODCM [a] Tritium analyses on quarterly composite. [b] Sr-89/90 performed annually on 2 nd quarter composite sample.

57

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

page Sample 1 of 1 Date Sr-89 Sr-90 K-40 Cs-i134* Cs-137*

IDate IrI8I 04/19/2010 Station 08 [a] [a] 3.05E+03 +/- 5.06E+02 < 2.90E+01 1.OOE+02 +/- 2.59E+01 Station 09A** [a] [a] 1.24E+04 +/- 9.34E+02 < 3.78E+01 1.55E+02 +/- 4.55E+01

[a] [a] 1.53E+04 +/- 8.74E+02 < 3.39E+01 < 3.52E+01 Station 11 Ra-226 Th-228 I Th-232 I 04/19/ 2 0 1 0 Station 08 1.02E+03 +/- 5.89E+02 3.56E+02 +/- 4.26E+01 3.18E+02 +/- 6.42E+01 Station 09A** 2.76E+03 +/- 9.48E+02 9.32E+02 +/- 6.22E+01 8.40E+02 +/- 1.27E+02 Station 11 2.52E+03 +/- 7.46E+02 1.19E+03 +/- 6.50E+01 1.15E+03 +/- 1.09E+02 Sample Date Sr-89 Sr-90 K-40 Cs-134* Cs-137*

10/18/2010 Station 08 9.28E+01 < 3168E+01 1.53E+04 +/- 1.39E+03 < 5.32E+01 < 6.41E+01 Station 09A** 1.12E+02 < 4.26E+01 1.18E+04 +/- 1.24E+03 1.76E+02 +/- 6.58E+01 < 8.22E+01 Station 11 9.30E+01 < 3.07E+01 1.79E+04 +/- 1.35E+03 < 5.08E+01 < 5.87E+01 Ra-226 Th-228 Th-232 10/18/2010 Station 08. 2.95E+03 +/- 1.01E+03 1.52E+03 +/- 1.45E+02 1.54E+03 +/- 1.61E+02 Station 09A** < 1.54E+03 6.72E+02 +/- 8.66E+01 5.86E+02 +/- 1.71E+02 Station 11 2.04E+03 +/- 9.08E+02 1.27E+03 +/- 1.03E+02 1.23E+03 +/- 1.59E+02 MEAN Sr-89 Sr-90 K-40 Cs-134* Cs-1 37*

Indicator +/- +/- 1.29E+04 +/- 1.03E+03 +/- 1.OOE+02 +/- 4.60E+01 Control +/- +/- 1.21E+04 +/- 1.09E+03 1.76E+02 +/- 5.18E+01 1.55E+02 +/- 6.39E+01 Ra-226 Th-228 I Th-232 Indicator 2.13E+03 +/- 8.13E+02 1.08E+03 +/- 8.89E+01 1.06E+03 +/- 1.23E+02 Control 2.76E+03 +/- 1.24E+03 8.02E+02 +/- 7.44E+01 7.13E+02 +/- 1.49E+02

LLD identified in ODCM

- 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 6.79E+01 Ra-226 Th-228 Th-232 1.35E+03 +/- 1.11E+03 8.62E+02 +/- 1.02E+02 8.94E+02 +/- 1.94E+02 MEAN Sr-89 Sr-90 K-40 Cs-134 Cs-137

+1-

+/- +/- 6.06E+03 +/- 8.70E+02 +1-

+/- +/-

Ra-226 Th-228 I Th-232 1.51E+03 +/- 9.64E+02 1.07E+03 +/- 8.93E+01 1.OOE+03 +/- 1.54E+02

LLD identified in ODCM

[a] Sr-89/90 analyses performed annually.

59

Table 3-15 Fish page Gamma Spectra 1 of 1

[pCi/Kg]

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 2.20E+03 +/- 5.76E+02 "z 1.72E+01 < 4.12E+01 " 1.92E+01 < 1.81E+01 < 3.27E+01 < 1.36E+01 " 1.77E+01 10/19/10 2.18E+03 +/- 1.04E+03 " 6.87E+01 < 1.76E+02 < 7.65E+01 < 6.95E+01 < 1.28E+02 " 5.93E+01 < 6.45E+01 Mean 2.24E+03 +/- 8.32E+02 Indicator 2.22E+03 +/- 8.37E+02 Control 2.26E+03 +/- 8.27E+02

LLD identified in ODCM

- 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 o00~o1.0 0 0 0 0 00 -

C C C C Ca C Figure 4-1 TLD (mrem/StandardMonth)

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 Iý 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 3 3 .

pCi/m to a high of 0.75 pCi/m 0.12 0.1 E 0.0'8

.~0.06 0.04 0.02 0

D -) 0 (--) -O ) (0 r-- CO C) a -D MN a-

'j" (a

0) O 0) 0) 0)

TO 0) 0So --)

a a a) a 71 a a a) 00

- ) <

- Control Sta-24 - Indicator Average Pre-op - Required LLD Figure4-2 HistoricalGross Beta in Air Particulates 63

3.50E-02 3.OOE-02 --

A 2.50E-02 -

2.00E-02 1.50E-02 1,00E-02 - - -

5.OOE-03 OOOE+O0 o o0 0 C> 0 0 LL IA 0

--

Control Sta-24 Indicator Figure4-3 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 ParticulateGamma 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 ParticulateStrontium 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 Productsand 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)0C)QQQQOOOOOO0

0) 0) V Date

- H-3 in RW Tritium - H-3 in RW Required LLD Figure4-4Tritium 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 10__1Average _ _ _ _

Pre-op 1 Dae Date Figure4.5Tritium 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 loo 0)1000 S100 0- 10 Date Station-8 - Staton-9 Control-Sta-09A

--- Station-11 -Average Pre-Op -Required LLD's Figure4-6 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 (>50m 2) 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.

ERA

> 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 1-131 pCi/L 65.2 74.0 0.88 A Ce-141 pCi/L 241 261 0.92 A Cr-;5 pCi/L 388 361 1.07 A Cs-1 34 pCi/L 157.0 178 0.88 A Cs-1 37 pCi/L 150 158 0.95 A Co-58 pCi/L 143 143 1.00 A Mn-54 pCi/L 202 207 0.98 A Fe-59 pCi/L 146 137 1.07 A Zn-65 pCi/L 247 254 0.97 A Co-60 pCi/L 177 183 0.97 A E6981-396 AP Ce-i 41 pCi 211 185 1.14 A Cr-51 pCi 304 255 1.19 A Cs-134 pCi 142 125 1.14 A Cs-137 pCi 131 111 1.18 A Co-58 pCi 119 101 1.18 A Mn-54 pCi 162 146 1.11 A Fe-59 pCi 110 97 1.14 A Zn-65 pCi 217 179 1.21 W Co-60 pCi 145 129 1.12 A E6980-396 Charcoal 1-131 pCi 80.2 85.6 0.94 E6982-396 Water Fe-55 pCi/L 2490 1970 1.26 June 2010 E7132-396 Milk Sr-89 pCi/L 82.0 93.4 0.88 A Sr-90 pCi/L 15.8 16.7 0.95 A E7133-396 Milk 1-131 pCi/L 83.5 96.9 0.86 A Ce-1 41 pCi/L 107 110 0.97 A Cr-51 pCi/L 325 339 0.96 A Cs-i 34 pCi/L 114.0 126 0.90 A Cs-1 37 pCi/L 144 150 0.96 A Co-58 pCi/L 92.3 101 0.91 A Mn-54 pCi/L 165 169 0.98 A Fe-59 pCi/L 121 119 1.02 A Zn-65 pCi/L 197 206 0.96 A Co-60 pCi/L 190 197 0.96 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 pCi 292 282 1.04 A Cs-1 34 pCi 101 105 0.96 A Cs-1 37 pCi 132 125 1.06 A Co-58 pCi 87.3 84.0 1.04 A Mn-54 pCi 150 140 1.07 A Fe-59 pCi 105 98.6 1.06 A Zn-65 pCi 168 171 0.98 A Co-60 pCi 170 163 1.04 A E7134-396 Charcoal 1-131 pCi 76.4 79.9 0.96 June 2010 E7136-396 Water Fe-55 pCi/L 1710 1880 0.91 September 2010 E7229-396 Milk Sr-89 pCi/L 85.0 92.8 0.92 A Sr-90 pCi/L 12.6 14.7 0.86 A E7230-396 Milk 1-131 pCi/L 80.2 94.1 0.85 A Ce-1 41 pCi/L 130 130 1.00 A Cr-51 pCi/L 235 234 1.00 A Cs-1 34 pCi/L 83.2 93.0 0.89 A Cs-1 37 pCi/L 95.1 94.5 1.01 A Co-58 pCi/L 77.3 73.7 1.05 A Mn-54 pCi/L 121 119 1.02 A Fe-59 pCi/L 96.4 91.1 1.06 A Zn-65 pCi/L 216 204 1.06 A Co-60 pCi/L 172 171 1.01 A E7232-396 AP Ce-141 pCi 122 119 1.03 A Cr-51 pCi 228 214 1.07 A Cs-1 34 pCi 79.9 85.3 0.94 A Cs-1 37 pCi 93.8 86.7 1.08 A Co-58 pCi 71.5 67.6 1.06 A Mn-54 pCi 113 110 1.03 A Fe-59 pCi 73.8 83.6 0.88 A Zn-65 pCi 186 187 0.99 A Co-60 pCi 163 157 1.04 A E7231-396 Charcoal 1-131 pCi/L 62.3 59.9 1.04 E7233-396 Water Fe-55 pCi 1620 1790 0.91 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 Sr-89 pCi/L 92.7 98.0 0.95 A Sr-90 pCi/L 13.5 13.5 1.00 A E7376-396 Milk 1-131 pCi/L 87.9 96.9 0.91 Ce-1 41 pCi/L not provided by Analytics for this study Cr-51 pCi/L 389 456 0.85 A Cs-1 34 pCi/L 137 157 0.87 A Cs-1 37 pCi/L 172 186 0.92 A Co-58 pCi/L 84.3 90.2 0.93 A Mn-54 pCi/L 120 120 1.00 A Fe-59 pCi/L 134 131 1.02 A Zn-65 pCi/L 162 174 0.93 A Co-60 pCi/L 284 301 0.94 A E7378-396 AP Ce-1 41 pCi not provided by Analytics for this study Cr-51 pCi 387 365 1.06 A Cs-1 34 pCi 135 126.0 1.07 A Cs-1 37 pCi 157 149.0 1.05 A Co-58 pCi 73.6 72.3 1.02 A Mn-54 pCi 88.7 96.0 0.92 A Fe-59 pCi 127 105.0 1.21 W Zn-65 pCi 151 139 1.09 A Co-60 pCi 249 241 1.03 A December 2010 E7377-396 Charcoal 1-131 pCi 79.6 84.2 0.95 A E7379-396 Water Fe-55 pCi 1720 1880 0.91 (a) Teledyne Brown Engineeringreportedresult.

(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.

(c) Ratio of Teledyne Brown Engineeringto 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 Bq/L 1.25 1.30 0.091 - 1.69 A Cs-1 34 Bq/L -0.0942 (1) A Cs-1 37 Bq/L 58.5 60.6 42.4 - 78.8 A Co-57 Bq/L 27.2 28.3 19.8 - 36.8 A Co-60 Bq/L 0.0226 (1) A H-3 Bq/L 104 90.8 63.6-118.0 A Mn-54 Bq/L 26.6 26.9 18.8 - 35.0 A Ni-63 Bq/L 61.3 59.9 41.9 - 77.9 A Pu-238 Bq/L 1.94 1.93 1.35-2.51 A Pu-239/240 Bq/L 0.0660 0.009 (2) A Sr-90 Bq/L 0.1029 (1) A Tc-99 BqIL -0.3907 (1) A U-234/233 Bq/L 1.21 1.22 0.85-1.59 A U-238 BqIL 1.27 1.25 0.88 - 1.63 A Zn-65 BqIL 42.0 40.7 28.5 - 52.9 A 10-GrW22 Water Gr-A Bq/L 0.5173 0.676 1.352 A Gr-B Bq/L 3.98 3.09 1.55-4.64 A 10-MaS22 Soil Am-241 Bq/kg 4.90 (1) A Cs-1 34 Bq/kg 665 733 513-953 A Cs-1 37 Bq/kg 800 779 545-1013 A Co-57 Bq/kg 508 522 365-679 A Co-60 Bq/kg 648 622 435-809 A Mn-54 Bq/kg 893 849 594-1104 A Ni-63 Bq/kg 514 477 334-620 A Pu-238 Bq/kg 28.4 24.1 16.9-31.3 A Pu-239/240 Bq/kg 0.2806 (1) A K-40 Bq/kg 597 559 391 -727 A Sr-90 Bq/kg 221 288 202-374 W Tc-99 Bq/kg -3.45 (1) A U-234/233 Bq/kg 68.0 60 42-78 A U-238 Bq/kg 69.2 64 45-83 A Zn-65 Bq/kg -4.97 (1) A 10-RdF22 AP Cs-134 Bq/sample 1.81 2.13 1.49-2.77 A Cs-1 37 Bq/sample 1.70 1.53 1.07-1.99 A Co-57 Bq/sample 0.0056 (1) A Co-60 Bq/sample 2.65 2.473 1.731 -3.215 A Mn-54 Bq/sample 3.70 3.02 2.11 -3.93 W 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 0.0582-Pu-239/240 Bq/sample 0.0757 0.0832 0.1082 A Sr-90 Bq/sample 0.0523 (1) A U-234/233 Bq/sample 0.0732 0.068 0.048 - 0.088 A U-238 Bq/sample 0.0791 0.071 0.050 - 0.092 A Zn-65 Bq/sample -0.0627 (1) A 10-GrF22 AP Gr-A Bq/sample 0.1533 0.0427 0.854 A Gr-B Bq/sample 1.240 1.29 0.65-1.94 A March 2010 10-RdV22 Vegetation Cs-1 34 Bq/sample 4.48 4.39 3.07 - 5.71 A Cs-1 37 Bq/sample 3.43 3.06 2.14-3.98 A Co-57 Bq/sample -0.0117 (1) A Co-60 Bq/sample 3.55 3.27 2.29 - 4.25 A Mn-54 Bq/sample 0.007 (1) A Sr-90 Bq/sample -0.0002 (1) A Zn-65 Bq/sample 8.12 7.10 4.97 - 9.23 A September 2010 10-MaW23 Water Am-241 Bq/L 0.009 (1) A Cs-1 34 Bq/L 27.1 31.4 22.0 - 40.8 A Cs-1 37 Bq/L 41.8 44.2 30.9 - 57.5 A Co-57 Bq/L 33.2 36.0 25.2 - 46.8 A Co-60 Bq/L 26.5 28.3 19.8-36.8 A H-3 Bq/L 500 453.4 317.4 - 589.4 A Mn-54 Bq/L 0.024 (1) A Ni-63 Bq/L 51.6 56.1 39.3 - 72.9 A Pu-238 Bq/L 1.25 1.81 1.27 - 2.35 N (3)

Pu-239/240 Bq/L 0.925 1.350 0.95-1.76 N (3)

Sr-90 Bq/L 8.10 8.3 5.8 - 10.8 A Tc-99 Bq/L 36.4 33.6 23.5 - 43.7 A U-234/233 Bq/L 2.02 2.01 1.41 - 2.61 A U-238 Bq/L 2.01 2.07 1.45-2.69 A Zn-65 Bq/L 30.8 31.0 21.7-40.3 A 10-GrW23 Water Gr-A Bq/L 2.36 1.92 0.58-3.26 A Gr-B Bq/L 6.37 4.39 2.20 - 6.59 A 10-MaS23 Soil Am-241 Bq/kg NR Cs-1 34 Bq/kg 837 940 658-1222 A Cs-1 37 Bq/kg 680 670 469-871 A 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 Bq/kg 350 343 240-446 A Mn-54 Bq/kg 853 820 574-1066 A Ni-63 Bq/kg 938 1058 741 -1375 A Pu-238 Bq/kg NR Pu-239/240 Bq/kg NR K-40 Bq/kg 721 699 489-909 A Sr-90 Bq/kg 2.24 (1) A Tc-99 Bq/kg 297 325 228-423 A U-234/233 Bq/kg NR U-238 Bq/kg NR Zn-65 Bq/kg 287 265 186-345 A 10-RdF23 AP Am-241 Bq/sample 0.125 0.115 0.081 -0.150 A Cs-1 34 Bq/sample 2.31 2.98 2.09 - 3.87 W Cs-1 37 Bq/sample -0.025 (1) A Co-57 Bq/sample 0.0056 3.64 4.08 A Co-60 Bq/sample 2.81 2.92 2.04 - 3.80 A Mn-54 Bq/sample 3.19 3.18 2.23- 4.13 A 0.0342 -

Pu-238 Bq/sample 0.048 0.0489 0.0636 A Pu-239/240 Bq/sample 0.080 0.082 0.057 - 0.107 A September 2010 10-RdF23 AP Sr-90 Bq/sample 1.01 1.01 0.71 -1.31 A U-234/233 Bq/sample 0.123 0.122 0.085 - 0.159 A U-238 Bq/sample 0.111 0.127 0.089 - 0.165 A Zn-65 Bq/sample 0.0310 (1) A 10-GrF23 AP Gr-A Bq/sample 0.004 (1) A Gr-B Bq/sample 0.473 0.50 0.25 - 0.75 A 10-RdV23 Vegetation Cs-1 34 Bq/sample 4.90 4.79 3.35 - 6.23 A Cs-1 37 Bq/sample 6.78 5.88 4.12-7.64 A Co-57 Bq/sample 10.2 8.27 5.79 - 10.75 W Co-60 Bq/sample 0.00 (1) A Mn-54 Bq/sample 7.36 6.287 4.401 - 8.173 A Sr-90 Bq/sample 2.53 2.63 1.84-3.42 A Zn-65 Bq/sample 6.40 5.3900 3.77 - 7.01 A See footnotes on next page.

86

(1) False positive test.

(2) Sensitivity evaluation (3) NCR 11-01 initiated to investigate failure.

(a) Teledyne Brown Engineeringreported result.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.

(C) DOEIMAPEPevaluation: A=acceptable, W=acceptable with warning, N=notacceptable.

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 pCi/L 64.4 60.4 48.6 - 68.2 A Sr-90 pCi/L 37.8 41.3 30.4 - 47.4 A Ba-1 33 pCi/L 66.4 65.9 54.9 - 72.5 A Cs-1 34 pCi/L 66.43 71.6 58.4 - 78.8 A Cs-1 37 pCi/L 137.33 146 131 -163 A Co-60 pCi/L 83.33 84.5 76.0 - 95.3 A Zn-65 pCi/L 177 186 167-219 A Gr-A pCi/L 26.37 32.9 16.9-42.6 A Gr-B pCi/L 28.77 37.5 24.7 - 45.0 A 1-131 pCi/L 26.27 26.4 21.9-31.1 A U-Nat pCi/L 57.19 62.3 50.7 - 69.1 A 10800 -

H-3 pCi/L 12967 12400 13600 MRAD-12 Filter Gr-A pCi/filter 88.1 79.6 41.3-130 November 2010 RAD-83 Water Sr-89 pCi/L 77.8 68.5 55.8 - 76.7 N (1)

Sr-90 pCi/L 39.3 43.0 31.7-49.3 A Ba-1 33 pCi/L 70.3 68.9 57.5 - 75.8 A Cs-1 34 pCi/L 39.9 43.2 34.5 - 47.5 A Cs-1 37 pCi/L 117 123 111-138 A Co-60 pCi/L 53.5 53.4 48.1 -61.3 A Zn-65 pCi/L 11.0 102 91.8-122 N (1)

Gr-A pCi/L 35.1 42.3 21.9 - 53.7 A Gr-B pCi/L 35.5 36.6 24.0 - 44.2 A 1-131 pCi/L 27.9 27.5 22.9 - 32.3 A U-Nat pCi/L 36.8 36.8 29.8 - 41.0 A 11200 -

H-3 pCi/L 13233 12900 14200 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 reportedas 11.0. No action required. NCR 10-09 (a) Teledyne Brown Engineering reportedresult.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.

(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.

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ML11123A215

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