Text

Independent Spent Fuel Storage Installation, 2009 Annual Radiological Environmental Operating Report
	ML101260475
Person / Time
Site:	North Anna
Issue date:	04/26/2010
From:	Lane N; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	10-250
	Download: ML101260475 (86)
	v • d • e

I

~.

.~

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 26, 2010 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.

NAPS/JHL 10-250 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 2009 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 Page Kemp at (540) 894-2295.

Very truly yours, N. Larry Lane Site Vice President Enclosure Commitments made in this letter: None JTjýt 5

I.

r Serial No.10-250 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

i Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2009 to December 31, 2009 Prepared by Dominion, North Anna Power Station

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2009 to December 31, 2009 Prepared by:

Reviewed by:

Approved by:

C- '

eorge R. Simmons Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Erich W. Dreyer Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B. Evans, Jr.

Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2

Table of Contents

1. EXECUTIVE SUM M ARY........................................................................................................

4

2. PROGRAM DESCRIPTION......................................................................................................

7 2.1 Introduction.............................................................................................................................

7 2.2 Sam pling and Analysis Program........................................................................................

8

3. ANALYTICAL RESULTS................................................

22 3.1 Sum m ary of Results..............................................................................................................

22 3.2 Analytical Results of 2009 REM P Sam ples...................................................................

31

4. DISCU SSION OF RESULTS....................................................................................................

59 4.1 Gam m a Exposure Rate...................................................................................................

59 4.2 Airborne Gross Beta..............................................................................................................

61 4.3 Airborne Radioiodine......................................................................................................

62 4.4 Air Particulate Gam m a.................................

62 4.5 Air Particulate Strontium.................................................................................................

63 4.6 S o il........................................................................................................................................

6 3 4.7 Precipitation..........................................................................................................................

63 4.8 Cow M ilk...............................................................................................................................

63 4.9 Food Products and Vegetation........................................................................................

64 4.10 W ell W ater..........................................................................................................................

64 4.11 River W ater.........................................................................................................................

64 4.12 Surface Water.................

65 4.13 Bottom Sedim ent................................................................................................................

66 4.14 Shoreline Soil......................................................................................................................

67 4.1 5 F ish......................................................................................................................................

6 8

5. PROGRAM EX CEPTION S.....................................................................................................

69 REFEREN CES....................................................................................................................................

71 APPENDICES.....................................................................................................................................

72 APPENDIX A: LAND USE CENSUS........................................

74 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS.......................... 76 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2009 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, 2009, 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 2009 airborne results were similar to previous years. Cs-134 was reported in two samples. In neither sample is the result considered a true positive. The reported Cs-134 was not identified by the peak search software, but the forced activity calculation of the software reported a result greater than both the MDC and the 2-T error. This is not considered a true positive result. 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 2009 was 3260 pCi/liter.

Two plant related isotopes were reported above the Minimum Detectable Concentration in surface water. These were Co-60, detected in one sample and Ba-140 activity reported in another sample from the indicator location. Neither is considered to be a true positive.

The Co-60 was detected at a concentration of 0.838 pCi/L with a 2-T error of 108%.

Ba-140 was reported at a concentration of 9.09 pCi/L. As described previously, it was not identified by the peak search software, but the forced activity calculation of the software reported a result greater than both the MDC and the 2-T error. Nb-95 was reported at a concentration of 1.88 pCi/L in one sample from the control location. However, this is not considered a true positive, since it was a forced activity calculation as described above, and the peak was not identified. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3810 pCi/liter. No plant related isotopes were reported in river water. Well water samples did not indicate the presence of plant related isotopes.

This trend is consistent throughout the environmental operational monitoring program.

Both silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background.

One silt sample indicated the presence of Sr-90 at a specific activity of 92.5 pCi/kg. This level is slightly lower than levels of Sr-90 seen periodically during the pre-operational program, about 110 pCi/kg. This indicates the source is likely fallout from past bomb tests and not related to plant operations. No Sr-89/90 was detected in liquid effluents from 5

the plant. Shoreline soil, which may provide a directzexposure 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.

The terrestrial exposure pathway includes milk and food/vegetation products. Iodine-131 was not detected in any 2009 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. Cs-137 was reported in one vegetation sample at the control location as a result of the software's forced activity calculation at 8.84 pCi/kg, which was greater than both the MDC and the 2-a error. This is not considered a true positive. One sample from an indicator location detected Cs-137 at a level of 26.1 pCi/kg. No other plant related isotopes were detected in any other 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 2009, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards.

The maximum dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2009 was 0.29 millirem. For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%. These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.

6

2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2009 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 meetthe criterion of "As Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2009 and satisfies the following objectives of the program:

> To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public resulting from station operations.

> To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.

> To identify changes in radioactivity in the environment.

> To verify that station operations have no detrimental effect on the health and safety of the public.

2.2 Sampling and Analysis Program Table 2-1 summarizes the 2009 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 2009.

8

TABLE 2-1 North Anna Power Station - 2009 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Environmental Thermoluminescent Dosimetry (TLD)

Location NAPS Sewage Treatment Plant Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA Bearing Cooling Tower Sturgeon's Creek Marina Parking Lot "C" (on-site)

Good Hope Church Parking Lot "B" Lake Anna Marina (Bogg's Dr)

Weather Tower Fence Route 689 Near Training Facility "Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)

"'Aspen Hills" Elk Creek Station Distance Direction Degrees Frequency Remarks 01 0.20 NE 420 Quarterly & Annually 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-11/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW N

N NNE NNE NE NE ENE ENE E

E ESE ESE SE SE SSE SSE 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control

In October 1991 the Surface Water Sample location at station 09 was moved to 09A.

- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.

Air Sample Station at 01A was added in October 2007.

- - - Station at 14a was added in October 2008 and Station 14 was deleted.

- - - - The dairy at Station 13 sold its dairy herd and ceased milking operations in September 2009.

9

TABLE 2-1 North Anna Power Station - 2009 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Environmental Thermoluminescent Dosimetry (TLD)

Location NAPS Access Rd.

Elk Creek Church NAPS Access Rd.

Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)

South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate - Construction Side Laydown Area Lake Anna Campground

1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NAPS Sewage Treatment Plant Biology Lab***

Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Station S-17/49 S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 0.47 1.55 0.42 5.30 0.6 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.45 2.54 0.07 2.21 7.30 22.00 7.10 11.54 Direction S

S SSW SSW SW SW WSW WSW W

W WNW WNW NW NW NNW NNW SSE NW WSW WSW Degrees 1730 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control Control Airborne Particulate.

and Radioiodine 01 O0A 03 04 05 05A 0.20 0.64 7.10 5.10 4.20 2.04 NE SE WSW WNW NNE N

420 1380 2430 2870 200 110 Weekly Weekly Weekly Weekly Weekly Weekly

In October 1991 the Surface Water Sample location at station 09 was moved to 09A.

- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.

Air Sample Station at 01A was added in October 2007.

- - - Station at 14a was added in October 2008 and Station 14 was deleted.

- - - - The dairy at Station 13 sold its dairy herd and ceased milking operations in September 2009.

10

TABLE 2-1 North Anna Power Station - 2009 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Samule Media Airborne Particulate and Radioiodine Location Levy, VA Bumpass, VA End of Route 685 Route 700 "Aspen Hills" Orange, VA Station 06 07 21 22 23 24 TABLE North Anna Power Station - 2009 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance 4.70 7.30 1.00 1.00 0.93 22.00 Direction ESE SSE WNW WSW SSE NW Degrees 1150 1670 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)

Precipitation Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

Biology Lab Biology Lab Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

Waste Heat Treatment Facility (Second Cooling Lagoon)

NAPS Sewage Treatment Plant 08 3.37 SSE 1480 Monthly 09A 11 01A 01A 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE 1380 Monthly Control 08 3.37 SSE 1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually 5.80 SE 1280 Semi-Annually Control 11 Shoreline Soil Soil 08 **

3.37 SSE 1480 Semi-Annually 01 0.20 NE 420 Once/3 years

In October 1991 the Surface Water Sample location at station 09 was moved to 09A.

- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.

Air Sample Station at 01A was added in October 2007.

- - - Station at 14a was added in October 2008 and Station 14 was deleted.

- - - - The dairy at Station 13 sold its dairy herd and ceased milking operations in September 2009.

11

TABLE 2-1 North Anna Power Station - 2009 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Fredericks Hall Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)

"Aspen Hills" Orange, VA Holladay Dairy (R.C. Goodwin)

Terrell's Dairy (Fredericks Hall)

Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Orange 02 03 04 05 05A 06 07 21 22 23 24 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Control Milk 12 13"*****

8.30 NW 3100 Monthly 5.60 SSW 2050 Monthly Fish 08 25 3.37 SSE 1480 Semi-Annually 3120 Semi-Annually 16.5 NW Control Food Products Vegetation)

Moody Lane***

Route 614 Route 629/522 Aspen Hills "Historic Lane" 14a 15 16 23 26 1.70 1.37 12.60 0.93 1.15 ESE SE NW SSE S

1030 1330 3140 1580 Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Control 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 13 sold its dairy herd and ceased milking operations in September 2009.

12

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)

(84 TLDs)

(12 TLDs)

Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Weekly Gamma Dose Gamma Dose 2 mR+2mR mRlstd. Month 2 mR+2mR mR/std. Month 1-131 Gross Beta Surface Water Quarterly (a) 2 d Quarter Composite Monthly Quarterly(a) 2nd Quarter Composite Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-31 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)

Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 0.07 0.01 0.05 0.06 (b)

(b) 1(c) 15 30 15 15 30 30 15 15 18 60 15 2000 (b)

(b) 1(c) 15 30 15 15 30 30 15 15 18 60 15 pCi/m 3

pCi/m3 pCi/m3 pCi/mr 3

pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L River Water Monthly

LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

13

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA River Water FREQUENCY Quarterly(a) 2nd Quarter Composite ANALYSIS Tritium (H-3)

Sr-89 Sr-90 Ground Water (Well Water)

Quarterly Quarterly(a) 2 d Quarter Semi-Annually Aquatic Sediment Annually Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)

Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 LLD 2000 (b)

(b) 15 30 15 15 30 30 15 10(c) 15 18 60 15 2000 (b)

(b) 150 180 (b)

(b)

REPORT UNITS pCi/L pCi/L pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/L Precipitation Monthly Semi-Annual Composite 4

15 30 15 15 30 30 15 10(c)

.15 18 60 15 pCi/L pCi/L Shoreline Soil Semi-Annually 150 180 (b)

(b) pCi/kg (dry) pCi/kg (dry)

Annually

LLDs indicate those levels to which environmental samples are required to be analyzed.

be lower than the listed values.

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

14 Actual analysis of samples may

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA Soil FREQUENCY Once per 3 years ANAIVSIS 1111D Milk Monthly Monthly Quarterly Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 150 180 (b)

(b) 1 15 18 60 15 (b)

(b)

REPORT UNITS pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L Fish Semi-Annually Monthly, if available, or at harvest pCi/kg (wet) 130 260 130 130 260 130 150 Food Products (Broadleaf Vegetation) pCi/kg (wet) 60 80 60

LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

15

Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map' Designation Environmental Station Identification 1

IA 2

3 4

5 5A 6

7 8

9A 11 12 13 14a 15 16 21 22 23 24 25 26 (a)

(a)

(a) 01,NE-5/37 O1A,SE-13/45 02,SSW-20/52 03,C-5/6 04 05 05A,N-2/34 06,ESE-12/44 07, C-1/2 08-Water, Fish, Sediment, Shoreline Soil 09A-Water sample, Sediment 11-River Water, Sediment 12-Milk 13-Milk 14a-Vegetation 15-Vegetation 16-Vegetation 21,WNW-27/59 22,WSW-24/56 23-SSE-15/47 24,C-3/4 25-Fish 27 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 14/46 22/54 26/58' 28/60 32/64 8/40 4/36 10/42 27-Milk C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E-10/42 (e)

(d)

(a)

(a)(b)

(c) 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 13 ceased milking in September 2009.

16

Figr

.I Not Ann Site 17

.VA.;I North Anna Environmental Map Fixed Environmental Sampling Location TLD Sampling Garden Residents Meat Animals p

3

ýk~SNELL

4.. te......na CB3280C 18

0- Mir-)

I ut*rraus

~AVI$&

E LU vi1 414

/

COF North Anna Environmental Map Fixed Environmental Sampling Location TLD Sampling Garden Residents Meat Animals S

CB3282E 19

/.

WSW n-1 North Anna Environmental Map Fixed Environmental Sampling Location TLD Sampling Garden Residents Meat Animals Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION, No other reproduction may be made without the written permission of ADC.

CB3283D 20

North Anna Environmental Map Fixed Environmental Sampling Location O

TLD Sampling Garden Residents Meat Animals Original ©1991 byADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

CB3281 D 21

3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM.

For radioanalytic analyses, the values listed in the columns indicated as "Mean/Range" include any results above the Minimum Detectable Concentration, MDC.

Results are considered true positives when the measured value exceeds both the MDC and the 2y error. For TLDs the mean and range include all values.

A more detailed analysis of the data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries.

22

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009 Docket No. 50-338/339 Page 1 of 7 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..

I Direction Range Range ments Direct Radiation (mR/std. Month)

(Sector TLDs)

Direct Radiation (mR/std. Month)

(Pre-operational TLDs)

Direct Radiation (mR/std. Month)

(Emergency Sector TLDs)

Direct Radiation (mR/std. month)

(Environmental TLDs)

Direct Radiation (mR/std. Month)

(Annual TLDs)

Airborne Particulates (lE-03 pCi/m3 )

Gamma Dose Gamma Dose 256 2

5.0(256/256)

(0.2-54.5) 2 2.6(16/16)

(1.2-4.3) 19/51(2) 0.42 mi.

SSW 31.5(8/8)

(10.0-54.5) 3.2(16/16)*

(2.5-4.2) 3.2(16/16)*

(2.5-4.2) 0 32 C-1/2 7.3 mi.

3.1 (8/8)

SSE (2.3-4.3) 0 Gamma Dose 40 2

5.1(40/40)

EPSP-0.37 mi.

7.6(8/8)

(2.8-8.3) 09/10 ENE (6.7-8.3) 3.2(16/16)*

(2.5-4.2) 0 Gamma Dose 48 2

3.4(44/44)

(1.5-6.1) 23 0.93 mi.

4.9(4/4)

SSE (4.1-6.1) 3.0(4/4)

(2.8-3.4) 0 Gamma Dose Gross Beta 12 2

2.9(11/11)

(1.9-4.7) 06 4.70 mi.

4.7(1/1)

ESE (4.7) 2.6(1/1)

(2.6) 0 676 0.01 15.9(623/624)

(5.80- 32.9) 02 5.30 mi.

SSW 17.2(52/52)

(9.34-31.1) 16.5(52/52)

(7.65-36.3) 0 Air Iodine (pCi/m3) 1-131 676 0.07 (0/624)

N/A N/A N/A (0/52) 0 Airborne Particulates (1E-03 pCi/m3)

Gamma 52 Be-7 52 152(45/48)

(101-267) 22 1.00 mi.

179(2/4) 152(4/4)

WSW (114-267)

(139-171) 0 0

Cs-134 52 0.05 2.59(2/48)

(1.83-3.34)

(1) mR/std month for TLDs (2) 19/51 located onsite near ISFSI.

C-3/4, -7/8 used as control locations 07 7.30 mi.

3.34(1/4)

SSE (3.34)

(0/4) 23

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009 Docket No. 50-338/339 Page 2 of 7 Indicator Location with Highest Mean II-Distance Direction Mean Range Control Non-Location routine Reported Mean Measure-Range ments Airborne Cs-137 52 0.06 (0/48)

N/A Particulates (1E-03 pCi/m3)

Sr-89 13 (0/12)

N/A N/A N/A N/A N/A N/A (0/4)

(0/1)

(0/1) 0 0

0 Sr-90 13 (0/12)

N/A N/A Soil (pCi/Kg) (dry)

Triennial Gamma Be-7 K-40 Cs-134 Cs-137 Th-228 Sr-89 Sr-90 Monthly Gross Beta Semiannual Gamma Be-7 N/A N/A N/A N/A N/A N/A N/A N/A 150 180 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

0 0

Precipitation (pCi/liter) 12 4

9.11(9/12)

.(1.85-39.9) 01A 0.64 mi.

9.11(9/12)

SE (1.85-39.9)

N/A 0

Mn-54 Fe-59 Co-58 Co-60 2

2 2

2 53.8(2/2)

(53.7-53.9) 15 (0/2) 30 (0/2) 15 (0/2) 15 (0/2) 01A 0.64 mi.

SE N/A N/A N/A N/A N/A N/A N/A N/A 53.8(2/2)

(53.7-53.9)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

0 0

0' 0

24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009 Docket No. 50-338/339 Page 3 of 7 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.IIII Precipitation (pCi/liter)

Zn-65 2

30 (0/2)

Zr-95 2

30 (0/2)

Nb-95 2

15 (0/2) 1-131 2

10 (0/2)

Cs-134 2

15 (0/2)

Cs-137 2

18 (0/2)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

0 0

0 Ba-140 2

60 (0/2)

La-140 2

15 (0/2)

Ac-228 2

Th-228 2

Th-232 2

Gamma 21 K-40 21 12.1(1/2)

(12.1) 4.27(1/2)

(4.27) 4.08(1/2)

(4.08) 01A 0.64 mi.

12.1(1/2)

SE (12.1) 01A 0.64 mi.

4.27(1/2)

SE (4.27) 01A 0.64 mi.

4.08(1/2)

SE (4.08) 12 8.3 mi.

1300(12/12)

NW (1180-1500) 0 0

0 Milk (pCi/liter) 1260(21/21)

(983-1540) 1-131 21 1

(0/21)

Cs-134 21 15 (0/21)

Cs-137 21 18 (0/21)

Ba-140 21 60 (0/21)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

0 0

25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009 Docket No. 50-338/339 Page 4 of 7 I*

Indicator Location Control Non-Indicator Location with Highest Mean Control Location with Highest Mean Location routine

.9 9.

Distance Direction Mean Range Mean Range Non-routine Reported Measure-ments Milk La-140 21 15 (0/21)

(pCi/liter)

Sr-89 7

(0/7)

(Quarterly)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

0 Sr-90 (Quarterly)

Gamma Be-7 7

(0/7)

N/A N/A N/A 0

Food Vegetation (pCi/kg) (wet) 35 35 K-40 35 1110(28/28)

(208-2350) 5170(28/28)

(2370-8960)

(0/28)

(0/28) 15 varies SE 14a varies ESE N/A N/A N/A N/A 1420(7/7)

(775-2240) 5840(7/7)

(3860-7720)

N/A N/A 1430(7/7)

(530-3450) 4460(7/7)

(2080-8300)

(0/7)

(0/7) 1-131 Cs-134 35 35 60 60 0

0 0

0 Cs-137 35 80 26.1(1/28) 23 varies SSE Tritium 4

2000 (0/4) 01A 0.64 mi.

SE Ground Well Water (pCi/liter)

Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 4

4 4

4 15 30 15 15 30 (0/4)

(0/4)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 26.1(1/7)

(26.1)

(0/4)

N/A N/A N/A N/A N/A 8.84(1/7)

(8.84)

N/A N/A N/A N/A N/A N/A 0

0 0

26

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009, Docket No. 50-338/339 Page 5 of 7 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 No.

Range Direction Range Range ments Ground Zr-95 4

Well Water (pCi/liter)

Nb-95 4

1-131 4

Cs-134 4

Cs-137 4

Ba-140 4

La-140 4

Sr-89 1

Sr-90 1

River Water Tritium 4

(pCi/liter)

Gamma 12 Mn-54 12 Fe-59 12 Co-58 12 Co-60 12 Zn-65 12 30 (0/4) 15 (0/4) 10 (0/4) 15 (0/4) 18 (0/4) 60 (0/4) 15 (0/4)

(0/1)

(0/1) 2000 3810(4/4)

(2870-5030)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 11 N/A N/A N/A N/A N/A N/A N/A N/A N/A 5.80 mi.

SE N/A N/A N/A, N/A N/A N/A N/A N/A N/A 3810(4/4)

(2870-5030)

N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)*

15 30 15 15 30 (0/12)

(0/12)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)*

(0/12)*

0 0

Zr-95 12 Nb-95 12 1-131 12 30 (0/12)

N/A N/A 15 1

(0/12)

N/A N/A N/A N/A 27

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County; Virginia - 2009 Docket No. 50-338/339 Page 6 of 7 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled (Unit)

Total (pCi/un Mean Name Distance Mean Mean Measure-Type No.

it)

Range Direction Range Range ments River Water (pCillitei)

Cs-134 12 15 (0/12)

N/A Cs-137 12 18 (0/12)

N/A Ba-140 12 60 (0/12)

N/A La-140 12 15 (0/12)

N/A Sr-89 1

(1/0)

N/A Sr-90 1

(1/0)

N/A Tritium 8

2000 3260(4/4) 08 (2600-3860)

N/A N/A N/A N/A N/A N/A 3.37 mi.

SSE N/A N/A N/A N/A N/A N/A 3260(4/4)

(2600-3860)

(0/12)*

(1/0)*

(0/4) 0 0-0 0

0 0

0 Surface Water (pCi/liter)

Gamnia 24 Mn-54 24 15 (0/12)

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

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

N/A N/A Co-60 24 15 0.838 (1/12) 08 3.37 mi.

(0.838)

SSE Zn-65 24 30 (0/12)

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

N/A N/A Nb-95 24 15 (0/12)

N/A N/A N/A N/A N/A 0.838(1/12)

(0.838)

N/A N/A N/A N/A N/A (0/12)

(0/12)

(0/12) 0 0

0 0

(0/12)

(0/12) 1.88(1/12)

(1.88)

(0/12)

(0/12) 0 0

0 0

0 1-131 24 1

Cs-134 24 15 (0/12)

N/A N/A (0/12)

N/A N/A 28

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009 Docket No. 50-338/339 Page 6 of 7 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)

Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range ments Surface Water (pCi/liter)

Cs-137 24 18 (0/12)

Ba-140 24 60 9.09(1/12)

(9.09)

La-140 24 15 (0/12)

N/A N/A 08 3.37 mi.

SSE N/A N/A N/A N/A N/A N/A N/A 9.09(1/12)

(9.09)

N/A N/A N/A (0/12)

(0/12)

(0/12) 0 0

Sr-89 Sr-90 1

(0/1)

(0/1) 0 0

0 Sediment Silt (pCi/kg) (dry)

Gamma 6

K-40 6

18700 (4/4)

(12100 -

32400) 11 5.80 mi.

24500(2/2)

SSE (16500-32400) 12600(2/2)

(11900-13300) 0 Cs-134 6

150 Cs-137 6

180 Ra-226 6

Th-228 6

Th-232 6

(0/4)

N/A N/A N/A N/A (0/2)

(0/2)

(0/4) 2620(3/4)

(1340-4680) 1670(4/4)

(1170-2910) 1670(4/4)

(1170-2910) 88.3(0/1)

(46.5-130) 1720(2/2)

(1230-2210) 11 5.80 mi.

3265(2/2)

SSE (1850-4680) 11 5.80 mi.

2040(2/2) 730(2/2)

SSE (1170-2910)

(661-798) 0 0

0 0

0 11 5.80 mi.

2040(2/2)

SSE (1170-2910) 578(2/2)

(560-595)

Sr-89 (Annually)

Sr-90 (Annually) 3 3

(0/2) 92.5(1/2)

(92.5)

N/A N/A N/A (0/1)

(0/1) 08 3.37 mi.

92.5(1/1)

SSE 92.5 Shoreline Soil (pCi/kg) (dry)

Gamma 2

K-40 2

2700(2/2)

(2560-2700) 08 3.37 mi.

2700(2/2)

SSE (2560-2700)

N/A 0

Results of surface water taken at Location 09A used as control value for river water 29

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2009 Docket No. 50-338/339 Page 7 of 7 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (PCi/unit)

Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range ments Shoreline Soil (pCi/kg) (dry)

(Cs-134 2

150 Cs-137 2

180 (u/2)

N/A N/A N/A NA (0/2)

N/A (0/2)

Ra-226 2

Th-228 2

Th-232 2

1220(2/2)

(1090-1350) 593(2/2)

(571-615) 545(2/2)

(503-586)

(0/1) 08 3.37 mi.

SSE 08 3.37 mi.

SSE N/A NA 1220(2/2)

(1090-1350) 593(2/2)

(571-615) 545(2/2)

(503-586)

N/A N/A N/A N/A N/A N/A N/A N/A N/A U

0 0

Sr-89 (Annually)

Sr-90 (Annually) 1 1

(0/1)

N/A NA Fish (pCi/kg) (wet)

Gamma 8

K-40 8

2370(4/4)

(1630-2240) 08 3.37 mi.

2370(4/4)

SSE (1630-2240) 2030(4/4)

(1730-3410)

Mn-54 8

130 Fe-59 8

260 Co-58 8

130 Co-60 8

130 Zn-65 8

260 Cs-134 8

130 (0/4)

(0/4)

N/A NA N/A NA N/A NA N/A NA N/A NA N/A NA N/A N/A N/A N/A N/A N/A (0/4)

(0/4)

(0/4) 0 0

0 0

0 30

3.2 Analytical Results of 2009 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 Lfinit 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 Resultsfrom HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).

31

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 1 of 4 First Quarter Station 01/01/2009 03/31/2009 N-1 4.1 N-33 2.5 N-2 2.4 N-34 1.2 NNE-3 8.1 NNE-35 5.4 NNE-4 5.1 NNE 36 5.0 NE-5 4.0 NE-37 4.4 NE-6 4.0 NE-38 3.0 ENE-7 5.8 ENE-39 5.2 ENE-8 2.5 ENE-40 2.3 E-9 4.9 E-41 5.5 E-10 3.8 E-42 5.0 ESE-11 4.3 ESE-43 3.4 ESE-12 5.3 ESE-44 4.6 SE-13 3.8 SE-45 5.6 SE-14 6.1 SE-46 5.9 SSE-15 5.7 SSE-47 6.2 SSE-16 3.7 SSE-48 2.4 Second Quarter 03/31/2009 06/30/2009 3.8 3.5 2.3 2.3 5.9 5.6 4.3 4.2 4.1 3.8 3.6 3.1 4.4 4.9 2.5 2.5 3.6 4.6 4.3 3.3 4.1 4.0 4.1 4.2 3.6 3.0 5.2 5.7 3.5 3.2 2.0 1.9 Third Quarter 06/30/2009 09/29/2009 4.3 4.0 3.0 2.6 6.3 5.9 4.0 3.4 4.2 4.5 2.5 3.7 4.7 4.7 2.6 4.1 4.0 6.1 3.7 4.3 3.7 3.9 4.6 4.0 3.7 3.6 7.4 6.3 4.2 4.7 3.9 2.3 Fourth Quarter 09/29/2009 12/29/2009 6.1 5.7 2.6 2.6 7.6 7.5 5.0 4.5 4.9 5.4 3.8 3.9 6.4 5.8 3.9 2.7 5.5 5.1 5.6 5.1 4.8 3.2 5.4 4.7 4.2 4.4 7.5 7.2 5.2 5.0 3.9 3.2 Quarterly*

Average

+/- 2 s.d.

4.3

+/-

2.3 2.4

+-

1.1 6.5

+/-

2.1 4.4

+/-

1.2 4.4

+/-

1.0 3.5

+/-

1.1 5.2

+/-

1.4 2.9

+/-

1.4 4.9

+/-

1.7 4.4

+/-

1.6 3.9

+/-

1.0 4.6

+/-

1.0 4.0

+/-

1.6 6.4

+/-

1.7 4.7

+/-

2.1 2.9

+/-

1.7

Average of collocated TLDs.

32

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

01/01/2009 03/31/2009 06/30/2009 09/29/2009 Average 03/31/2009 06/30/2009 09/29/2009 12/29/2009

+/- 2 s.d.

S-17 6.6 7.1 7.3 8.1 7.4

+/-

S-49 8.4 6.3 7.1 8.0 S-18 2.7 1.6 2.1 2.9 2.2 S-50 2.0 1.5 1.9 2.8 SSW-19 54.5 23.8 21.1 39.0 31.5

+/-

3 SSW-51 48.8 37.0 10.0 17.4 SSW-20 1.8 1.7 2.2 2.9 2.3

+/-

SSW-52 1.8 2.3 2.3 3.2 SW-21 5.3 3.3 4.2 4.7 4.0

+/-

SW-53 3.8 3.9 2.2 4.6 SW-22 5.1 3.7 3.9 5.0 4.5

+/-

SW-54 4.9 4.0 4.2 5.0 WSW-23 5.1 4.4 5.1 6.2 4.7

+/-

WSW-55 4.9 4.3 4.9 2.3 WSW-24 5.0 4.2 3.4 4.7 4.3

+/-

WSW-56 4.9 3.8 3.7 5.0 W-25 6.4 7.0 7.5 8.0 7.2

+/-

W-57 7.7 7.1 6.1 7.5 W-26 2.6 2.1 2.8 3.2 2.7

+/-

W-58 3.5 2.0 2.9 2.5 WNW-27 3.3 3.0 2.8 3.6 2.9

+/-

WNW-59 2.3 2.2 2.8 3.4 WNW-28 3.1, 2.0 2.3 3.3 2.8

+/-

WNW-60 3.0 2.7 2.3 3.7 NW-29 7.0 6.0 5.8 6.5 6.2

+/-

NW-61 7.6 5.4 5.7 5.8 NW-30 0.2 1.3 2.5 2.6 1.8

+/-

NW-62 1.7 2.2 2.0 1.5 NNW-31 1.9 2.6 2.6 4.7 2.9

+/-

NNW-63 2.8 2.6 2.8 3.4 NNW-32 1.7 2.6 4.0 3.1 3.1

+/-

NNW-64 3.0 2.7 3.5 4.2 1.5 1.1 1.6 1.1 1.9 1.2 2.2 1.3 1.3 1.0 1.0 1.2 1.5 1.6 1.7 1.6 Page 2 of 4 Mean 5.0

+/-

5.7

Average of collocated TLDs.

33

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

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

n 01/01/2009 03/31/2009 06/30/2009 09/29/2009 Av 03/31/2009 06/30/2009 09/29/2009 12/29/2009

+/-

Page 3 of 4 Statioi 3rterly*

erage 2 s.d.

C-1 C-2 C-3"*

C-4"*

C-5 C-6 C-7"*

C-8"**

2.6 2.3 2.7 2.5 2.6 1.2 3.1 2.9 2.8 3.5 3.1 2.6 1.5 2.6 2.8 3.1 2.7 2.7 2.6 3.0 1.8 2.1 3.5 3.7 3.5 4.3 3.7 3.5 2.8 1.8 3.8 4.2 Mean Indicator Control**

3.1

+/-

1.3 3.0

+/-

0.9 2.1

+/-

1.2 3.4

+/-

1.0 2.6

+/-

0.8 3.2

+/-

0.5 4.3

+/-

1.0 4.6

+/-

0.8 EPSA-01 ***

EPSA-02***

EPSF-03***

EPSF-04***

EPSR-05***

EPSR-06***

EPSJ-07***

EPSJ-08***

EPSP-09***

EPSP-1 0***

4.2 4.2 4.6 5.3 4.4 4.0 4.8 4.5 7.1 8.3 4.3 3.8 4.2 4.4 4.2 5.3 2.8 3.1 8.0 7.4 4.5 3.9 4.4 4.2 5.1 5.0 4.8 5.2 6.8 6.7 5.4 4.4 4.9 5.1 4.3 4.5

+/-

1.1 3.9 4.7 4.0 8.0 8.1 4.2

+/-

1.7 7.6

+/-

1.3 5.1

+/-

1.4 Mean

Average of collocated TLDs.

- Control Station

- - Emergency Plan TLDs.

34

TABLE 3-2 DIRECT RADIATION MEASURMENTS - ENVIRONMENTAL QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 4 of 4 First Quarter Station 01/01/2009 03/31/2009 STA-01 4.8 STA-02 3.0 STA-03 2.0 STA-04 1.5 STA-05 2.8 STA-05A 3.6 STA-06 4.7 STA-07 3.7 Second Quarter 03/31/2009 06/30/2009 3.7 2.1 1.6 2.1 3.0 2.3 3.2 2.4 Third Quarter 06/30/2009 09/29/2009 4.1 2.9 1.9 2.8 2.8 2.5 4.1 3.0 Fourth Quarter 09/29/2009 12/29/2009 4.9 2.2 1.9 1.7 3.8 3.1 5.2 3.5 Quarterly Average

+/- 2 s.d.

4.4

+/-

1.1 2.6

+/-

0.9 1.9

+/-

0.3 2.0

+/-

1.1 3.1

+/-

1.0 2.9

+/-

1.2 4.3

+/-

1.7 3.2

+/-

1.2 Annual TLD 4.0 1.6 1.8 1.9 2.5 2.4 4.7 3.3 2.5 3.5 4.0 2.6 2.9

+/-

2.1 STA-21 STA-22 STA-23 STA-24*

3.0 5.2 6.1 2.8 3.2 3.9 4.1 2.9 2.5 4.9 4.1 2.8 Mean - Indicator Locations 3.9 5.0 5.3 3.4 3.2

+/-

4.8

+/-

1.2 1.2

\\

4.9

+/-

2.0 3.0

+/-

0.3 3.4

+/-

1.2

Control 35

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3]

page 1 of 4 Period Ending 01/06/09 01/13/09 01/20/09 01/27/09 02/04/09 02/10/09 02/17/09 02/24/09 03/04/09 03/10/09 03/17/09 03/24/09 03/31/09 04/07/09 04/14/09 04/21/09 04/28/09 05/05/09 05/12/09 05/19/09 05/26/09 06/02/09 06/09/09 06/16/09 06/23/09 06/30/09 Station 01 Station 02 Station 03 Station 04 Station 05 Station 06 Station 07 2.23E+01

+/-

3.18E+00 2.01E+01

+/-

3.10E+00 1.51E+01

+/-

2.82E+00 2.05E+01 1.93E+01

+/-

2.99E+00 1.76E+01

+/-

2.95E+00 1.67E+01

+/-

2.83E+00 1.47E+01 2.56E+01

+/-

3.29E+00 2.19E+01

+/-

3.12E+00 2.09E+01

+/-

3.06E+00 2.39E+01 2.56E+01

+/-

3.30E+00 2.21E+01

+/-

3.14E+00 1.86E+01

+/-

2.97E+00 1.74E+01 1.12E+01

+/-

2.33E+00 1.87E+01

+/-

2.72E+00 1.29E+01

+/-

2.43E+00 1.72E+01 2.03E+01

+/-

3.49E+00 2.81E+01

+/-

3.86E+00 2.11E+01

+/-

3.54E+00 2.40E+01 1.64E+01

+/-

2.93E+00 1.76E+01

+/-

2.98E+00 1.32E+01

+/-

2.75E+00 1.50E+01 7.27E+00

+/

2.30E+00 1.98E+01

+/-

3.01 E+00 1.58E+01

+/-

2.81 E+00 1.68E+01 2.10E+01

+/

2.81E+00 1.54E+01

+/-

2.55E+00 1.27E+01

+/-

2.57E+00 1.66E+01 2.21E+01

+/

3.61E+00 2.37E+01

+/-

3.68E+00 1.69E+00 2.19E+01 1.06E+01

+/

2.49E+00 1.39E+01

+/-

2.67E+00 1.54E+01

+/-

2.76E+00 1.27E+01 1.70E+01

+/-

2.71E+00 1.78E+01

+/-

2.75E+00 1.72E+01

+/-

2.72E+00 2.22E+01 1.31E+01

+/-

2.53E+00 1.07E+01

+/-

2.63E+00 1.09E+01

+/-

2.39E+00 7.39E+00 1.16E+01

+/-

2.49E+00 1.40E+01

+/-

2.65E+00 1.07E+01

+/-

2.46E+00 1.50E+01 1.71E+01

+/-

2.77E+00 2.03E+01

+/-

2.92E+00 1.56E+01

+/-

2.68E+00 1.55E+01 1.79E+01

+/-

2.97E+00 1.60E+01

+/-

2.89E+00 1.31E+01

+/-

2.74E+00 9.83E+00 2.53E+01

+/-

3.19E+00 2.04E+01

+/

2.96E+00 2.24E+01

+/-

3.05E+00 1.39E+01 1.40E+01

+/

2.56E+00 1.36E+01

+/-

2.54E+00 8.63E+00

+/-

2.24E+00 1.OOE+01 1.15E+01

+/-

2.42E+00 1.12E+01

+/-

2.40E+00 6.74E+00

+/-

2.09E+01 8.25E+00 1.29E+01

+/

2.55E+00 1.20E+01

+/-

2.54E+00 8.58E+00

+/-

2.39E+00 1.23E+01 1.06E+01

+/

2.51E+00 9.34E+00

+/-

2.40E+00 1.02E+01

+/-

2.41E+00 8.95E+00 9.06E+00

+1-2.51E+00 1.06E+01

+/-

2.60E+00 6.01E+00

+/-

2.32E+00 8.30E+00 1.41E+01

+/-

2.72E+00 1.38E+01

+/-

2.74E+00 1.06E+01

+/-

2.52E+00 1.14E+01 1.14E+01

+/

2.44E+00 1.37E+01

+/-

2.64E+00 1.07E+01

+/-

2.49E+00 1.44E+01 1.16E+01

+/

2.71E+00 1.09E+01

+/-

2.59E+00 9.22E+00

+/-

2.60E+00 1.03E+01 1.30E+01

+/-

2.71E+00 2.66E+01

+/-

3.35E+00 2.49E+01

+/-

3.27E+00 1.01E+01

+/-

3.11E+00

+/-

2.75E+00

+/-

3.23E+00

+/-

2.92E+00

+/-

2.65E+00

+/-

3.67E+00

+/-

2.87E+00

+/-

2.83E+00

+/-

2.60E+00

+/-

3.60E+00

+/-

2.61 E+00

+/-

3.95E+00

+/-

2.16E+00

+/-

2.71 E+00

+/-

2.67E+00

+/-

2.54E+00

+/-

2.62E+00

+/-

2.32E+00

+/-

2.21 E+00

+/-

2.57E+00

+/-

2.37E+00

+/-

2.48E+00

+/-

2.56E+00

+/-

2.68E+00

+/-

2.57E+00

+/-

2.53E+00 1.50E+01

+/-

2.82E+00 1.11E+01

+/-

2.57E+00 1.81E+01

+/-

2.94E+00 2.16E+01

+/-

3.12E+00 1.73E+01

+/-

2.65E+00 2.07E+01

+/-

3.51 E+00 1.27E+01

+/-

2.73E+00 1.56E+01

+/-

2.80E+00 1.87E+01

+/-

2.70E+00 2.26E+01

+/-

3.63E+00 1.28E+01

+/-

2.61E+00 1.98E+01

+/-

2.86E+00 8.25E+00

+/

2.22E+00 1.12E+01

+/

2.49E+00 1.27E+01

+/-

2.57E+00 1.24E+01

+/-

2.69E+00 1.56E+01

+/-

2.71E+00 1.11E+01

+/

2.39E+00 6.56E+00

+/

2.09E+00 9.82E+00

+/

2.44E+00 7.61 E+00

+/

2.28E+00 9.48E+00

+/

2.58E+00 3.07E+01

+/

1.00E+01 1.33E+01

+/

2.63E+00 8.19E+00

+/

2.44E+00 1.30E+01

+-

4.66E+00 2.23E+01 1.35E+01 2.16E+01 2.37E+01 1.50E+01 1.83E+01 1.25E+01 1.60E+01 1.81E+01 2.29E+01 1.41 E+01 1.78E+01 7.51 E+00 1.05E+01 1.31E+01 1.60E+01 1.93E+01 1.11E+01 1.01E+01 1.18E+01 1.00E+01 9.60E+00 7.40E+00 1.20E+01 1.03E+01 1.47E+01

+/-

3.20E+00

+/-

2.72E+00

+/-

3.13E+00

+/-

3.22E+00

+/-

2.54E+00

+/-

3.39E+00

+/

2.72E+00

+/

2.81 E+00

+/-

2.67E+00

+/

3.64E+00

+/

2.69E+00

+/-

2.75E+00

+/-

2.17E+00

+/-

2.44E+00

+/

2.53E+00

+/

2.87E+00

+/-

2.91 E+00

+/

2.39E+00

+/

2.33E+00

+/

2.53E+00

+/

2.43E+00

+/-

2.55E+00

+/-

2.35E+00

+/

2.54E+00

+/-

2.56E+00

+/-

2.78E+00 1.73E+01 1.87E+01 2.00E+01 2.08E+01 1.81E+01 2.22E+01 1.92E+01 1.53E+01 1.44E+01 2.17E+01 1.33E+01 1.64E+01 9.58E+00 1.04E+01 1.66E+01 1.49E+01 1.82E+01 1.15E+01 1.00E+01 1.12E+01 1.20E+01 9.01 E+00 9.94E+00 1.42E+01 1.03E+01 1.41E+01

+/-

2.96E+00

+/-

3.00E+00

+/-

3.02E+00

+/-

3.08E+00

+/-

2.69E+00

+/

3.58E+00

+/-

3.06E+00

+/

2.78E+00

+/

2.49E+00

+/-

3.58E+00

+/

2.64E+00

+/-

2.68E+00

+/-

2.31 E+00

+/-

2.43E+00

+/-

2.72E+00

+/-

2.82E+00

+/-

2.85E+00

+/-

2.41 E+00

+/-

2.32E+00

+/

2.50E+00

+/-

2.55E+00

+/-

2.51 E+00

+/-

2.53E+00

+/-

2.67E+00

+/-

2.56E+00

+/-

2.75E+00 36

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3]

page 2 of 4 Period Ending Station 21 I

Station 22 Station I

23 I

Station 24*

Station 01A Station 05A I

01/06/09 01/13/09 01/20/09 01/27/09 02/04/09 02/10/09 02/17/09 02/24/09 03/04/09 03/10/09 03/17/09 03/24/09 03/31/09 04/07/09 04/14/09 04/21109 04/28/09 05/05/09 05/12/09 05/19/09 05/26/09 06/02/09 06/09/09 06/16/09 06/23/09 06/30/09 1.92E+01 1.29E+01 1.60E+01 2.18E+01 1.63E+01 2.23E+01 1.39E+01 1.11E+01 1.48E+01 1.76E+01 1.06E+01 1.88E+01 1.08E+01 1.02E+01 1.53E+01 1.76E+01 2.42E+01 1.11E+01 9.10E+00 1.10E+01 1.15E+01 8.16E+00 1.06E+01 1.45E+01 1.03E+01 1.15E+01

+/-

3.03E+00 1.83E+01

+/-

2.99E+00 2.05E+01

+/-

3.12E+00 1.85E+01

+/-

2.99E+00 1.58E+01

+/-

2.86E+00 1.85E+01

+/-

3.01E+00

+/-

2.67E+00

+/-

2.83E+00

+/-

3.13E+00

+/-

2.62E+00

+/-

3.59E+00

+/-

2.79E+00

+/-

2.57E+00

+/-

2.51E+00

+/-

3.38E+00

+/-

2.49E+00

+/-

2.80E+00

+/-

2.37E+00

+/

2.42E+00

+/

2.67E+00

+/-

2.96E+00

+/-

3.06E+00

+/

2.39E+00

+I-2.27E+00

+/-

2.45E+00

+/-

2.55E+00

+/-

2.46E+00

+/-

2.55E+00

+/-

2.63E+00

+/-

2.62E+00

+/-

2.62E+00 1.60E+01 2.48E+01 2.51E+01 1.97E+01 2.75E+01 9.26E+00 1.63E+01 1.50E+01 1.49E+01 1.35E+01 2.12E+01 1.30E+01 1.08E+01 1.87E+01 1.60E+01 2.32E+01 8.44E+00 1.04E+01 9.99E+00 1.21E+01 1.04E+01 1.34E+01 1.32E+01 1.30E+01 1.31E+01

+/-

2.83E+00 1.44E+01

+/-

2.78E+00

+/I-3.27E+00 2.14E+01

+/-

3.05E+00

+/-

3.28E+00 2.65E+01

+/-

3.40E+00

+/-

2.76E+00 1.82E+01

+/-

2.71E+00

+/-

3.83E+00 2.58E+01

+/-

3.75E+00

+/-

2.54E+00 1.72E+01

+/-

2.96E+00

+/-

2.82E+00 1.76E+01

+/-

2.95E+00

+/-

2.52E+00 1.54E+01

+/-

2.55E+00

+/-

3.24E+00 2.31E+01

+-

3.65E+00

+/-

2.65E+00 1.39E+01

+/

2.65E+00

+I-2.93E+00 1.64E+01

+-

2.73E+00

+-

2.50E+00 1.12E+01

+-

2.40E+00

+-

2.46E+00 9.11E+00

+/-

2.36E+00

+/

2.85E+00 1.56E+01

+/-

2.68E+00

+/

2.82E+00 1.27E+01

+/

2.70E+00

+/

3.15E+00 1.77E+01

+/-

2.82E+00

+-

2.22E+00 1.28E+01

+/

2.50E+00

+-

2.35E+00 1.06E+01

+/-

2.37E+00

+/

2.39E+00 1.30E+01

+/-

2.58E+00

+/

2.59E+00 1.07E+01

+/-

2.50E+00

+/

2.59E+00 1.02E+01

+/-

2.58E+00

+-

2.68E+00 1.18E+01

+/-

2.63E+00

+-

2.55E+00 1.32E+01

+-

2.56E+00

+/

2.78E+00 9.46E+00

+/-

2.56E+00

+/-

2.70E+00 1.49E+01

+/-

2.80E+00 1.90E+01 1.59E+01 2.47E+01 1.03E+01 2.88E+01 1.69E+01 1.45E+01 1.64E+01 1.75E+01 8.28E+00 1.94E+01 1.03E+01 1.36E+01 1.88E+01 1.29E+01 1.74E+01 1.05E+01 7.65E+00 1.23E+01 1.03E+01 1.14E+01 1.01 E+01 1.35E+01 1.13E+01 1.38E+01

+/-

2.98E+00

+/-

2.81 E+00

+/-

3.26E+00

+/

2.28E+00

+-

3.90E+00

+/-

2.94E+00

+/-

2.74E+00

+/-

2.59E+00

+/-

3.37E+00

+/-

2.53E+00

+/-

2.83E+00

+/-

2.35E+00

+/-

2.64E+00

+/-

2.84E+00

+/-

2.72E+00

+/-

2.80E+00

+/-

2.36E+00

+/-

2.16E+00

+/-

2.52E+00

+/-

2.42E+00

+/-

2.65E+00

+/-

2.48E+00

+/-

2.36E+00

+/-

2.62E+00

+/-

2.73E+00 1.85E+01 2.OOE+01 2.41 E+01 1.14E+01 1.76E+01 1.18E+01 1.74E+01 1.06E+01 1.77E+01 1.56E+01 1.83E+01 8.92E+00 8.55E+00 1.67E+01 1.43E+01 1.73E+01 1.15E+01 1.01E+01 1.OOE+01 1.14E+01 8.33E+00 9.61 E+00 1.35E+01 9.25E+00 1.30E+01

+/-

2.95E+00

+/-

3.01E+00

+/-

3.24E+00

+/-

2.34E+00

+/-

3.50E+00

+/-

2.69E+00

+/-

2.88E+00

+/-

2.29E+00

+/-

3.39E-01

+/-

2.77E+00

+/-

2.78E+00

+/-

2.27E+00

+/-

2.34E+00

+/-

2.75E+00

+/-

2.79E+00

+/-

2.80E+00

+/-

2.42E+00

+/-

2.33E+00

+/-

2.39E+00

+/-

2.55E+00

+/-

2.47E+00

+/-

2.46E+00

+/-

2.56E+00

+/-

2.57E+00

+/-

2.70E+00 1.60E+01 1.48E+01 2.24E+01 1.66E+01 2.30E+01 1.38E+01 1.39E+01 1.55E+01 2.29E+01 1.34E+01 1.81E+01 1.18E+01 1.17E+01 1.44E+01 6.03E+00 1.69E+01 1.OOE+01 9.36E+00 8.94E+00 7.53E+00 8.43E+00 1.36E+01 1.19E+01 8.41 E+00 1.19E+01

+/-

2.84E+00

+/-

2.77E+00

+/-

3.16E+00

+/-

2.62E+00

+/-

3.62E+00

+/-

2.78E+00

+/-

2.71 E+00

+/-

2.54E+00

+/-

3.64E+00

+/-

2.64E+00

+/-

2.77E+00

+/-

2.45E+00

+/-

2.52E+00

+/-

2.65E+00

+/-

2.31 E+00

+/-

2.79E+00

+/-

2.32E+00

+/-

2.28E+00

+/-

2.37E+00

+/-

2.88E+00

+/-

2.52E+00

+/-

2.68E+00

+/-

2.54E+00

+/-

2.45E+00

+/-

2.63E+00

Control Station 37

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

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Station Ending 0I 02I 03I 04 05I 0

I 07 07/08/09 1.33E+01

+/-

2.47E+00 1.31E+01

+/-

2.47E+00 1.22E+01

+/-

2.43E+00 1.07E+01

+/-

2.36E+00 1.12E+01

+/-

2.39E+00 1.06E+01

+/-

2.34E+00 1.25E+01

+/-

2.43E+00 07/14/09 1.09E+01

+/-

3.03E+00 1.17E+01

+/-

3.08E+00 5.80E+00

+/-

2.73E+00 1.26E+01

+/-

3.13E+00 1.17E+01

+/-

3.08E+00 8.14E+00

+/-

2.88E+00 9.22E+00

+/-

2.94E+00 07/21/09 2.32E+01

+/-

3.79E+00 1.75E+01

+/-

3.52E+00 1.58E+01

+/-

3.56E+00 1.79E+01

+/-

3.60E+00 1.80E+01

+/-

3.57E+00 1.32E+01

+/-

3.35E+00 2.02E+01

+/-

3.85E+00 07/28/09 2.16E+01

+/-

3.53E+00 1.97E+01

+/-

3.48E+00 1.33E+01

+/-

3.09E+00 1.92E+01

+/-

3.40E+00 1.76E+01

+/-

3.36E+00 1.45E+01

+b-3.23E+00 2.64E+01

+1-3.95E+00 08/04/09 1.89E+01

+/-

3.55E+00 1.29E+01

+1-3.21E+00 1.29E+01

+/-

3.32E+00 1.47E+01

+1-3.36E+00 1.46E+01

+1-3.29E+00 1.39E+01

+/-

3.26E+00 1.77E+01

+/-

3.42E+00 08/11/09 1.74E+01

+/-

3.46E+00 2.74E+01

+1-3.94E+00 1.63E+01

+/-

3.39E+00 1.92E+01

+1-3.53E+00 2.69E+01

+1-3.91E+00 1.97E+01

+/-

3.63E+00 2.47E+01

+/-

3.84E+00 08/18/09 1.38E+01

+/-

2.93E+00 1.93E+01

+/-

3.20E+00 1.32E+01

+/-

2.89E+00 1.42E+01

+/-

2.95E+00 1.93E+01

+/-

3.20E+00 1.24E+01

+/-

2.86E+00 1.18E+01

+/-

3.17E+00 08/25/09 1.14E+01

+/-

3.35E+00 1.19E+01

+1-3.38E+00 1.03E+01

+/-

3.31E+00 1.34E+01

+/-

3.45E+00 1.11E+01

+1-3.35E+00 1.58E+01

+/-

3.55E+00 1.38E+01

+/-

3.46E+00 09/01/09 2.35E+01

+/-

3.62E+00 2.50E+01

+/-

3.68E+00 1.38E+01

+/-

3.21E+00 1.86E+01

+/-

3.41E+00 2.71E+01

+/-

3.76E+00 2.38E+01

+/-

3.63E+00 2.13E+01

+/-

3.52E+00 09/08/09 2.02E+01

+/-

3.56E+00 1.94E+01

+/-

3.52E+00 1.33E+01

+/-

3.24E+00 1.71 E+01

+/-

3.42E+00 2.14E+01

+/-

3.60E+00 1.96E+01

+/-

3.52E+00 2.29E+01

+/-

3.66E+00 09/15/09 1.39E+01

+/-

3.52E+00 2.07E+01

+/-

3.64E+00 1.02E+01

+/-

3.18E+00 2.03E+01

+/-

3.64E+00 1.40E+01

+/-

3.36E+00 1.95E+01

+/-

3.58E+00 8.16E+00

+/-

3.03E+00 09/22/09 2.51E+01

+/-

3.71E+00 1.82E+01

+/-

3.46E+00 2.01E+01

+/-

3.46E+00 2.04E+01

+/-

3.49E+00 2.18E+01

+/-

3.56E+00 2.09E+01

+/-

3.54E+00 2.26E+01

+/-

3.63E+00 09/29/09 1.63E+01

+/-

.2.96E+00 1.16E+01

+/-

2.71E+00 1.35E+01

+/-

2.86E+00 1.27E+01

+/-

2.78E+00 1.39E+01

+/-

2.83E+00 1.59E+01

+/-

2.94E+00 1.31E+01

+/-

2.78E+00 10/06/09 2.37E+01

+/-

3.56E+00 1.61 E+01

+/-

3.25E+00 1.97E+01

+/-

3.37E+00 2.28E+01

+/-

3.58E+00 2.32E+01

+/-

3.61 E+00 2.05E+01

+/-

3.51 E+00 1.67E+01

+/-

3.28E+00 10/13/09 1.74E+01

+/-

3.07E+00 1.47E+01

+/-

2.93E+00 1.47E+01

+/-

2.93E+00 1.48E+01

+/-

2.94E+00 1.68E+01

+/-

3.04E+00 1.05E+01

+/-

2.72E+00 1.44E+01

+/-

2.92E+00 10/21/09 1.57E+01

+/-

2.95E+00 1.19E+01

+/-

2.77E+00 1.51E+01

+/-

2.93E+00 1.57E+01

+/-

2.95E+00 1.26E+01

+/-

2.80E+00 1.30E+01

+/-

2.82E+00 1.13E+01

+/-

2.74E+00 10/27/09 2.21E+01

+/-

4.21E+00 1.76E+01

+/-

4.03E+00 1.62E+01

+/-

4.05E+00 1.61E+01

+/-

4.01E+00 1.70E+01

+/-

4.03E+00 1.68E+01

+/-

4.01E+00 1.64E+01

+/-

3.99E+00 11/03/09 1.13E+01

+/-

3.08E+00 1.27E+01

+/-

3.16E+00 1.24E+01

+/-

3.08E+00 1.05E+01

+/-

3.03E+00 1.35E+01

+/-

3.18E+00 1.12E+01

+/-

3.08E+00 1.43E+01

+/-

3.21E+00 11/10/09 3.29E+01

+/-

4.17E+00 2.75E+01

+/-

3.84E+00 2.38E+01

+/-

3.69E+00 2.14E+01

+/-

3.59E+00 2.60E+01

+/-

3.77E+00 2.89E+01

+/-

3.88E+00 2.37E+01

+/-

3.69E+00 11/17/09 1.78E+01

+/-

3.70E+00 1.44E+01

+/-

3.56E+00 1.56E+01

+/-

3.60E+00 1.29E+01

+/-

3.51E+00 1.62E+01

+/-

3.64E+00 1.23E+01

+/-

3.48E+00 1.59E+01

+/-

3.62E+00 11/24/09 1.58E+01

+/-

2.71 E+00 1.94E+01

+/-

2.90E+00 1.95E+01

+/-

2.91 E+00 1.53E+01

+/-

2.69E+00 1.89E+01

+/-

2.88E+00 1.83E+01

+/-

2.85E+00 1.78E+01

+/-

2.82E+00 12/01/09 1.61E+01

+/-

2.85E+00 1.62E+01

+/-

2.86E+00 1.34E+01

+/-

2.73E+00 1.54E+01

+/-

2.82E+00 1.61E+01

+/-

3.85E+00 1.28E+01

+/-

2.68E+00 1.32E+01

+/-

2.70E+00 12/08/09 1.70E+01

+/-

3.26E+00 1.38E+01

+/-

3.11E+00 1.50E+01

+/-

3.14E+00 1.78E+01

+/-

3.28E+00 1.93E+01

+/-

3.35E+00 1.65E+01

+/-

3.22E+00 1.46E+01

+/-

3.13E+00 12/15/09 2.01 E+01

+/-

3.06E+00 1.75E+01

+/-

2.93E+00 1.94E+01

+/-

3.03E+00 1.68E+01

+/-

2.91 E+00 1.90E+01

+/-

3.02E+00 1.55E+01

+/-

2.84E+00 1.59E+01

+/-

2.86E+00 12/22/09 2.16E+01

+/-

3.53E+00 2.69E+01

+/-

3.70E+00 1.96E+01

+/-

3.46E+00 2.76E+01

+/-

3.77E+00 2.54E+01

+/-

3.67E+00 2.08E+01

+/-

3.48E+00 2.18E+01

+/-

3.51E+00 12/29/09 1.62E+01

+/-

3.28E+00 1.50E+01

+/-

3.25E+00 1.65E+01

+/-

3.27E+00 1.84E+01

+/-

3.36E+00 1.59E+01

+/-

3.26E+00 1.37E+01

+/-

3.20E+00 1.55E+01

+/-

3.27E+00 MEAN 1.71E+01

+/-

3.07E+00 1.72E+01 4/"

3.08E+00 1.45E+01

+

3.27E+00 1.57E+01

+/-

3.O1E+00 1.62E+01

+/-

3.20E+00 1.53E+01

+/

2.98E+00 1.59E+01

+/-

3.02E+00 38

Table 3-3 Air Particulate Gross Beta Radioactivity

[10.3 pCi/m3]

page 4 of 4 Period Endin*

07/08/09 07/14/09 07/21/09 07/28/09

.08/04/09 08/11/09 08/18/09 08/25/09 09/01/09 09/08/09 09/15/09 09/22/09 09/29/09 10/06/09 10/13/09 10/21/09 10/27/09 11/03/09 11/10/09 11/17/09 11/24/09 12/01/09 12/08/09 12/15/09 12/22/09 12/29/09 MEAN Station 21 1.20E+01 1.05E+01 1.61 E+01 1.67E+01 1.30E+01 2.27E+01 1.52E+01 1.23E+01 1.44E+01 1.99E+01 1.26E+01 2.40E+01 1.07E+01 1.77E+01 1.53E+01 1.53E+01 1.84E+01 8.27E+00 2.58E+01 1.25E+01 1.85E+01 1.22E+01 1.48E+01 1.24E+01 1.77E+01 8.27E+00 Station

+/-

2.41 E+00

+/-

3.02E+00

+/-

3.45E+00

+/-

3.32E+00

+/-

3.21E+00

+/-

3.76E+00

+/-

3.OOE+00

+/-

3.40E+00

+/-

3.22E+00

+/-

3.55E+00

+/-

3.18E+00

+/-

3.74E+00

+/-

2.56E+00

+/-

3.33E+00

+/-

2.96E+00

+/-

2.92E+00

+/-

4.06E+00

+/-

2.94E+00

+/-

3.77E+00

+/

3.48E+00

+/

2.86E+00

+/

2.64E+00

+/

3.16E+00

+/

2.66E+00

+/

3.38E+00

+/-

2.89E+00 1.42E+01 9.06E+00 1.85E+01 2.35E+01 1.47E+01 3.07E+01 1.90E+01 1.41E+01 2.43E+01 1.70E+01 1.98E+01 2.15E+01 1.49E+01 2.16E+01 1.69E+01 1.75E+01 1.78E+01 1.08E+01 3.11E+01 1.38E+01 2.OOE+01 1.46E+01 1.27E+01 1.98E+01 1.93E+01 1.78E+01 22

+/-

4/-

+/-

I Station 23 2.53E+00 2.93E+00 3.55E+00 3.61 E+00 3.29E+00 4.08E+00 3.18E+00 3.47E+00 3.56E+00 3.43E+00 3.48E+00 3.65E+00 2.88E+00 3.49E+00 3.04E+00 3.02E+00 4.03E+00 3.06E+00 3.97E+00 3.54E+00 2.93E+00 2.77E+00 3.05E+00 3.05E+00 3.44E+00 3.33E+00 1.22E+01

+/-

2.42E+00 8.28E+00

+/-

2.88E+00 1.95E+01

+/-

3.59E+00 1.64E+01

+/

3.35E+00 1.51E+01

+/-

3.31E+00 2.56E+01

+/-

3.87E+00 1.41E+01

+/-

2.94E+00 1.36E+01

+/

3.46E+00 2.33E+01

+/-

3.57E+00 1.59E+01

+/-

3.38E+00 1.41E+01

+/-

3.25E+00 1.76E+01

+/-

3.46E+00 1.51 E+01

+/-

2.89E+00 1.89E+01

+/-

3.38E+00 1.37E+01

+/-

2.89E+00 1.60E+01

+/-

2.95E+00 1.92E+01

+/

4.14E+00 1.23E+01

+/-

3.13E+00 3.15E+01

+/

3.99E+00 1.52E+01 4/-

3.59E+00 1.87E+01

+/-

2.87E+00 1.26E+01

+/-

2.67E+00 1.36E+01

+/-

3.10E+00 1.80E+01

+/-

2.95E+00 1.63E+01

+/-

3.25E+00 1.53E+01

+/-

3.29E+00 Station Station 24*I 0A 8.73E+00

+/-

2.24E+00 1.16E+01

+/-

2.39E+00 1.50E+01 9.88E+00

+/-

2.97E+00 1.20E+01

+I-3.10E+00 1.40E+01 1.61E+01

+/-

3.52E+00 1.81E+01

+/

3.52E+00 1.94E+01 2.42E+01

+/-

3.61 E+00 2.20E+01

+/

3.60E+00 3.27E+01 2.09E+01

+/-

3.63E+00 1.68E+01

+/

3.64E+00 2.60E+01 2.50E+01

+/-

3.77E+00 2.58E+01

+/-

3.80E+00 2.71E+01 1.65E+01

+/-

3.06E+00 1.22E+01

+/

2.58E+00 1.99E+01 1.25E+01

+/-

3.42E+00 1.20E+01

+/

3.38E+00 1.83E+01 2.56E+01

+/-

3.70E+00 2.03E+01

+/

3.48E+00 1.80E+01 1.97E+01

+/-

3.52E+00 1.90E+01

+/

3.51E+00 1.94E+01 1.61E+01

+/-

3.45E+00 1.70E+01

+/

3.45E+00 2.02E+01 2.35E+01

+/-

3.58E+00 2.46E+01

+/

3.70E+00 2.41E+01 1.71E+01

+/-

3.00E+00 1.33E+01

+/

2.79E+00 1.31E+01 1.95E+01

+/-

3.42E+00 2.28E+01

+/

3.53E+00 1.77E+01 1.59E+01

+/-

2.99E+00 1.61E+01

+/

3.00E+00 1.47E+01 1.23E+01

+/-

2.79E+00 1.34E+01

+/

2.58E+00 1.53E+01 1.97E+01

+/-

4.14E+00 1.61E+01

+/-

3.96E+00 1.32E+01 8.37E+00

+/-

2.93E+00 9.87E+00

+/

3.01E+00 1.14E+01 3.63E+01

+/-

4.16E+00 2.48E+01

+/

3.73E+00 2.58E+01 1.75E+01

+/-

3.70E+00 1.54E+01

+/

3.60E+00 9.96E+00 1.53E+01

+/

2.69E+00 1.86E+01

+/

2.86E+00 1.83E+01 1.35E+01

+/-

2.72E+00 9.83E+00

+/-

2.51 E+00 1.23E+01 2.18E+01

+/-

3.45E+00 1.28E+01

+/-

3.06E+00 1.73E+01 1.90E+01

+/

3.02E+00 1.49E+01

+/-

2.80E+00 1.89E+01 2.42E+01

+/

3.67E+00 1.83E+01

+/-

3.40E+00 2.16E+01 1.62E+01

+/-

3.23E+00 1.52E+01

+/-

3.22E+00 1.68E+01 1.65E+01

+/-

3.02E+00 1.53E+01

+/-

2.91E+00 1.62E+01 Mean - All Indicator Locations 1.59E+01 Station 05A

+/-

2.58E+00

+/-

3.20E+00

+/-

3.63E+00

+/-

3.97E+00.

+/-

3.76E+00

+/-

3.92E+00

+/-

3.23E+00

+/-

3.56E+00

+/-

3.39E+00

+/-

3.52E+00 1/-

3.63E+00

+/-

3.65E+00

+/-

2.79E+00

+/-

3.37E+00

+/

2.93E+00

+/

2.93E+00

+/-

3.84E+00

+/

3.09E+00

+/

3.76E+00

+/

3.38E+00

+/-

2.85E+00

+/-

2.65E+00

+/-

3.25E+00

+/-

3.01 E+00

+/-

3.53E+00

+/-

3.30E+00

+/

3.02E+00

+/

3.05E+00 I1 1.48E+01

+/-

2.95E+00 1.70E+01

+/-

3.05E+00 1.61 E+01

+/-

3.02E+00

Control Station 39

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m3]

page 1 of 4 Period Ending 01/06/09 01/13/09 01/20/09 01/27/09 02/04/09 02/10/09 02/17/09 02/24/09 03/04/09 03/10/09 03/17/09 03/24/09 03/31/09 04/07/09 04/14/09 04/21/09 04/28/09 05/05/09 05/12/09 05/19/09 05/26/09 06/02/09 06/09/09 06/16/09 06/23/09 06/30/09 Station 01 1.31E+01 2.04E+01 1.28E+01 2.43E+01 9.53E+00 2.08E+01 1.50E+01 1.54E+01 9.77E+00 1.96E+01 1.38E+01 8.69E+00 1.67E+01 2.04E+01 1.58E+01 1.07E+01 3.36E+01 2.58E+01 2.01E+01 2.93E+01 3.42E+01 2.53E+01 1.71E+01 2.63E+01 2.20E+01 2.11E+01 Station 02 I

2.40E+01 3.78E+01 2.32E+01 1.46E+01 1.74E+01 3.77E+01 2.72E+01 1.54E+01 2.29E+01 1.95E+01 2.24E+01 1.60E+01 3.02E+01 4.11 E+01 2.84E+01 1.96E+01 4.23E+01 4.76E+01 3.66E+01 5.46E+01 6.09E+01 6.41 E+01 1.74E+01 2.73E+01 2.12E+01 2.10E+01 Station 03 2.38E+01 3.76E+01 2.32E+01 2.43E+01 1.73E+01 2.84E+01 2.72E+01 1.55E+01 2.52E+01 1.95E+01 2.25E+01 1.60E+01 3.05E+01 4.13E+01 2.85E+01 1.96E+01 4.22E+01 4.70E+01 3.63E+01 5.61 E+01 5.95E+01 5.OOE+01 1.70E+01 2.76E+01 1.23E+01 1.16E+01 I

Station 04 2.40E+01 3.70E+01 I

2.34E+01 2.43E+01 1.74E+01 3.77E+01 2.75E+01 8.38E+00 2.29E+01 1.95E+01 2.24E+01 2.47E+01 3.04E+01 4.13E+01 2.84E+01 1.95E+01 4.25E+01 4.67E+01 3.65E+01 5.47E+01 6.08E+01 5.06E+01 1.70E+01 2.73E+01 2.12E+01 2.09E+01 Station 05 2.38E+01 3.75E+01 2.33E+01 2.43E+01 1.74E+01 3.77E+01 2.72E+01 1.54E+01 2.29E+01 1.20E+01 2.24E+01 1.60E+01 3.03E+01 4.12E+01 2.93E+01 1.95E+01 4.25E+01 4.67E+01 3.65E+01 5.54E+01 6.08E+01 5.14E+01 6.85E+01 1.51E+01 2.12E+01 4.22E+01 I

Station 06 1.61E+01 2.99E+b1 1.71E+01 1.39E+01 1.87E+01 3.77E+01 1.65E+01 1.62E+01 1.23E+01 1.66E+01 2.03E+01 1.43E+01 3.60E+01 2.67E+01 2.24E+01 1.94E+01 2.70E+01 5.09E+01 1.87E+01 4.21E+01 4.88E+01 3.46E+01 8.65E+00

- 2.72E+01 2.10E+01 3.57E+01 Station S

07 2.03E+01 3.76E+01 2.12E+01 2.26E+01 1.87E+01 2.20E+01 3.86E+01 1.62E+01 2.OOE+01 3.30E+01 2.71 E+01 1.91E+01 3.61E+01 4.OOE+01 2.81E+01 1.55E+01 6.34E+01 5.09E+01 3.45E+01 5.28E+01 6.12E+01 3.46E+01 8.76E+00 2.72E+01 2.10E+01 3.57E+01 l

40

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 2 of 4 Period Ending 01/06/09 01/13/09 01/20/09 01/27/09 02/04/09 02/10/09 02/17/09 02/24/09 03/04/09 03/10/09 03/17/09 03/24/09 03/31/09 04/07/09 04/14/09 04/21/09 04/28/09 05/05/09 05/12/09 05/19/09 05/26/09 06/02/09 06/09/09 06/16/09 06/23/09 06/30/09 I

Station 21 2.OOE+01 3.72E+01 2.13E+01 2.26E+01 1.89E+01 3.59E+01 3.86E+01 1.64E+01 2.01E+01 3.30E+01 2.72E+01 1.91E+01 3.59E+01 4.OOE+01 2.82E+01 1.94E+01 6.31E+01 4.06E+01 3.46E+01 5.19E+01 6.21 E+01 3.45E+01 8.69E+00 2.64E+01 2.16E+01 3.57E+01 I

Station 22 2.OOE+01 3.72E+01 2.13E+01 2.26E+01 1.87E+01 3.59E+01 3.88E+01 1.61 E+01 2.01 E+01 3.30E+01 2.72E+01 1.91 E+01 3.59E+01 4.70E+01 2.82E+01 1.88E+01 6.50E+01 5.10E+01 3.46E+01 5.17E+01 6.22E+01 3.45E+01 9.38E+00 1.58E+00 3.36E+01 2.41E+01 I

Station 23 2.03E+01 3.78E+01 2.07E+01 2.32E+01 3.05E+01 3.59E+01 3.86E+01 2.68E+01 2.01E+01 3.30E+01 2.68E+01 1.96E+01 3.27E+01 4.OOE+01 2.82E+01 1.94E+01 6.03E+01 5.10E+01 3.46E+01 5.20E+01 6.21 E+01 3.13E+01 9.53E+00 2.65E+01 3.34E+01 2.41 E+01 I

Station 24*

3.02E+01 6.20E+01 3.27E+01 2.37E+01 3.03E+01 3.60E+01 2.50E+01 2.61E+01 1.99E+01 4.OOE+01 3.61E+01 2.78E+01 3.29E+01 4.99E+01 3.25E+01 2.92E+01 6.44E+01 5.12E+01 3.69E+01 4.72E+01 5.31E+01 5.69E+01 9.31 E+00 3.44E+01 3.26E+01 2.40E+01 Station S

01A 3.01E+01 6.19E+01 3.26E+01 2.37E+01 3.03E+01 4.89E+01 2.52E+01 2.60E+01 2.OOE+01 4.02E+01 3.61 E+01 2.80E+01 3.29E+01 5.02E+01 3.27E+01 2.91E+01 6.43E+01 5.11E+01 3.72E+01 4.72E+01 5.52E+01 5.69E+01 9.36E+00 2.68E+01 1.44E+01 1.33E+01 Station I

05A 3.04E+01 6.27E+01 3.30E+01 2.37E+01 3.04E+01 4.89E+01 2.50E+01 2.61E+01 1.99E+01 4.01E+01 3.60E+01 2.79E+01 3.29E+01 4.97E+01 3.32E+01 2.92E+01 6.48E+01 5.10E+01 3.70E+01 4.87E+01 5.41E+01 5.81E+01 3.97E+00 2.79E+01 3.26E+01 2.41E+01 I

Control Station 41

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 3 of 4 Period Endinl 07/08/09 07/14/09 07/21/09 07/28/09 08/04/09 08/11/09 08/18/09 08/25/09 09/01/09 09/08/09 09/15/09 09/22/09 09/29/09 10/06/09 10/13/09 10/21/09 10/27/09 11/03/09 11/10/09 11/17/09 11/24/09 12/01/09 12/08/09 12/15/09 12/22/09 12/29/09 Station 01 2.44E+01 3.52E+01 5.26E+01 6.43E+01 1.82E+01 1.20E+01 8.68E+00 9.53E+00 1.93E+01 1.36E+01 1.74E+01 4.90E+01 1.55E+01 2.33E+01 1.89E+01 5.31 E+01 6.39E+01 6.20E+01 5.80E+01 1.93E+01 2.81 E+01 5.09E+01 1.53E+01 4.22E+01 6.03E+01 5.36E+01 Station 02 I

2.45E+01 3.52E+01 5.55E+01 6.52E+01 1.77E+01 6.78E+00 1.58E+01 9.57E+00 1.93E+01 1.36E+01 2.96E+01 4.96E+01 1.54E+01 2.35E+01 4.41E+01 5.30E+01 6.41 E+01 3.81E+01 5.54E+01 3.14E+01 1.20E+01 5.09E+01 3.58E+01 3.51E+01 5.91 E+01 5.40E+01 Station 03 2.46E+01 3.52E+01 5.77E+01 6.27E+01 1.11E+01 1.19E+01 1.57E+01 5.25E+00 1.94E+01 1.35E+01 2.96E+01 4.82E+01 8.70E+00 2.31E+01 4.42E+01 5.32E+01 2.80E+01 6.05E+01 5.54E+01 3.14E+01 2.81E+01 2.83E+01 3.54E+01 4.44E+01 6.05E+01 5.31 E+01 Station 04 2.47E+01 3.52E+01 5.68E+01 6.36E+01 1.82E+01 1.20E+01 1.58E+01 9.55E+00 1.93E+01 5.76E+00 2.98E+01 4.84E+01 1.55E+01 1.01E+01 4.42E+01 5.30E+01 6.50E+01 6.15E+01 5.53E+01 3.15E+01 2.81E+01 5.09E+01 3.56E+01 4.45E+01 6.01 E+01 5.31 E+01 I

Station 05 1.36E+01 3.56E+01 5.51 E+01 6.41 E+01 1.77E+01 1.23E+01 1.58E+01 2.38E+01 1.37E+01 5.71E+01 2.97E+01 2.08E+01 1.54E+01 2.39E+01 4.42E+01 6.53E+01 6.43E+01 6.20E+01 4.18E+01 3.15E+01 2.81 E+01 5.09E+01 3.56E+01 3.53E+01 5.48E+01 2.49E+01 I

Station 06 2.29E+01 3.58E+01 5.47E+01 6.43E+01 1.37E+01 1.58E+01 1.42E+01 2.83E+01 2.49E+01 5.71E+01 5.79E+01 4.48E+01 2.59E+01 1.50E+01 3.43E+01 6.53E+01 5.23E+01 5.59E+01 4.18E+01 3.12E+01 2.61 E+01 6.63E+01 2.32E+01 3.53E+01 5.46E+01 2.53E+01 Station S 07 2.29E+01 3.56E+01 3.23E+01 4.16E+01 1.37E+01 1.58E+01 1.42E+01 2.83E+01 2.49E+01 5.71E+01 5.70E+01 4.51E+01 2.57E+01 1.47E+01 3.43E+01 3.60E+01 5.23E+01 5.57E+/-01 4.20E+01 3.11E+01 2.61 E+01 6.63E+01 2.32E+01 3.53E+01 5.44E+01 2.51E+01 l

42

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m3]

page 4 of 4 Period Endin0 07/08/09 Station J

21 2.29E+01 Station 222 2.29E+01 Station

.23 9.74E+00 Station S

24*

1.13E+01 Station 01A 1.12E+01 07/14/09 07/21/09 07/28/09 08/04/09 08/11/09 08/18/09

-08/25/09 09/01/09 09/08/09 09/15/09 09/22/09 09/29/09 10/06/09 10/13/09 10/21/09 10/27/09 11/03/09 11/10/09 11/17/09 11/24/09 12/01/09 12/08/09 12/15/09 12/22/09 12/29/09 3.57E+01 5.42E+01 6.40E+01 1.36E+01 1.59E+01 1.43E+01 2.83E+01 2.49E+01 5.74E+01 5.57E+01 4.61 E+01 2.57E+01 1.47E+01 3.43E+01 6.51E+01 5.21 E+01 2.82E+01 4.19E+01 3.11E+01 2.62E+01 6.62E+01 2.34E+01 3.51 E+01 5.53E+01 2.47E+01 2.53E+01 5.42E+01 6.40E+01 1.36E+01 1.59E+01 1.43E+01 1.20E+01 2.49E+01 1.04E+01 5.55E+01 4.62E+01 2.57E+01 1.47E+01 3.43E+01 6.54E+01 5.20E+01 5.59E+01 2.72E+01 3.11E+01 2.61E+01 6.62E+01 2.34E+01 3.89E+01 6.02E+01 3.46E+01 2.52E+01 6.79E+01 2.65E+01 1.35E+01 1.58E+01 2.67E+01 1.21E+01 2.59E+01 1.04E+01 4.18E+01 6.27E+01 6.48E+01 5.99E+01 6.53E+01 4.14E+01 5.23E+01 5.59E+01 4.93E+01 2.47E+01 2.79E+01 2.82E+01 2.39E+01 3.88E+01 5.87E+01 1.51E+01 2.52E+01 6.97E+01 2.57E+01 1.39E+01 1.53E+01 2.67E+01 5.14E+00 2.59E+01 1.04E+01 4.36E+01 5.98E+01 6.52E+01 6.02E+01 6.51E+01 4.16E+01 5.20E+01 6.13E+01 4.93E+01 2.48E+01 2.79E+01 6.84E+01 2.38E+01 3.90E+01 6.07E+01 3.41 E+01 2.52E+01 6.74E+01 2.66E+01 1.39E+01 1.54E+01 2.68E+01 1.20E+01 2.59E+01 1.04E+01 4.30E+01 6.15E+01 6.47E+01 5.94E+01 6.53E+01 4.16E+01 5.16E+01 6.15E+01 4.94E+01 2.48E+01 2.78E+01 6.83E+01 2.39E+01 3.89E+01 2.57E+01 3.46E+01 Station I105A 1.13E+01 1.39E+01 6.90E+01 2.60E+01 1.35E+01 1.57E+01 2.68E+01 1.20E+01 2.59E+01 1.04E+01 4.37E+01 6.07E+01 6.51E+01 6.08E+01 6.52E+01 4.16E+01 5.19E+01 6.15E+01 4.92E+01 2.48E+01 2.79E+01 6.84E+01 2.38E+01 3.90E+01 5.99E+01 3.47E+01

Control Station 43

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

[103 pCi/rn3]

Sampling Quarter 1 Location I Be-7 I

Cs-134 I

Cs137**

I I

01 1.80E+02

+1-3.79E+01 1.78E+00 1.27E+00 01A 1.31E+02

+/-

2.82E+01 1.15E+00 9.73E-01 02 1.38E+02

+/-

4.45E+01 2.OOE+00 1.85E+00 03 1.55E+02

+/-

3.17E+01 1.73E+00 1.33E+00 04 1.78E+02

+/-

3.81E+01 1.43E+00 1.28E+00 05 1.44E+02

+/-

3.87E+01 2.06E+00 1.92E+00 05A 1.80E+02

+/-

3.12E+01 9.97E-01 1.10E+00 06 1.97E+02

+/-

3.88E+01 1.90E+00 1.69E+00 07 1.66E+02

+/-

3.05E+01 1.35E+00 1.07E+00 21 1.36E+02

+/-

4.53E+01 1.79E+00 1.57E+00 22 1.56E+02

+/-

4.21E+01 1.32E+00 1.22E+00 23 1.73E+02

+/-

4.11E+01 1.40E+00 1.09E+00 24*

1.50E+02

+/-

3.02E+01 1.31E+00 1.08E+00 Sampling Quarter 2 Location I Be-7 I

cs-34**

Cs-137**

I Sr-89 I

Sr-90 01 1.55E+02

+/-

3.53E+01 1.71E+00 1.70E+O0 9.05E+00 3.69E+00 01A 1.50E+02

+/-

3.63E+01 2.13E+00 1.92E+00 6.47E+00 3.99E+00 02 2.OOE+02

+/-

3.92E+01 1.79E+00 1.92E+00 6.07E+00 3.62E+00 03 1.28E+02

+/-

4.09E+01 2.41E+00 1.81E+00 5.97E+00 3.60E+00 04 1.37E+02

+/-

3.38E+01 1.51E+00 2.OOE+00 6.77E+00 3.58E+00 05 1.52E+02

+/-

4.05E+01 1.86E+00 1.43E+00 7.93E+00 5.63E+00 05A 1.04E+02

+/-

2.85E+01 2.OOE+00 1.77E+00 4.87E+00 4.12E+00 06 1.95E+02

+/-

4.24E+01 1.98E+00 1.79E+00 6.10E+00 5.14E+00 07 1.79E+02

+I-3.62E+01 1.90E+00 1.77E+00 5.72E-01 4.26E+00 21 1.44E+02

+/-

4.15E+01 2.08E+00 1.52E+00 5.83E+00 3.89E+00 22 8.92E+02 1.55E+00 1.78E+00 9.95E+00 4.35E-01 23 5.68E+02 1.87E+00 1.46E+00 8.33E+00 3.76E-01 24*

1.49E+02

+/-

4.55E+01 1.70E+00 1.76E+00 5.99E+00 3.76E+00

Control Station ** LLD identified in ODCM 44

Table 3-5 Airborne Particulate Gamma Spectra

[10-3 pCi/m 3]

page 2 of 2 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*

MEAN Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*

Be-7 1.65E+02

+/-

1.89E+02

+/-

1.36E+02

+/-

1.15E+02

+/-

1.70E+02

+/-

1.48E+02

+/-

2.06E+02

+/-

1.37E+02

+/-

1.86E+02

+/-

1.41 E+02

+/-

2.67E+02

+/-

1.71 E+02

+/-

Quarter 3 Cs-134**

3.41E+01 1.83E+00

+/-

1.04E+00 4.40E+01 2.03E+00 3.64E+01 1.56E+00 4.16E+01 2.24E+00 3.34E+01 1.24E+00 3.17E+01 1.56E+00 5.04E+01 2.25E+00 3.99E+01 1.25E+00 3.77E+01 3.34E+00

+/-

1.29E+00 3.30E+01 1.14E+00 1.28E+02 1.70E+00 2.57E+02 1.83E+00 3.17E+01 1.73E+00 S S-137"*E0 1.23E+00 1.61E+00 1.14E+00 1.42E+00 1.33E+00 1.35E+00 1.93E+00 9.31E-01 2.01 E+00 7.19E-01 1.33E+00 1.45E+00 1.26E+00 Be-7 1.54E+02

+/-

3.64E+01 1.17E+02

+/-

3.OOE+01 1.40E+02

+/-

4.42E+01 1.20E+02

+/-

3.35E+01 1.27E+02

+/-

3.71E+01 1.62E+02

+/-

3.69E+01 1.34E+02

+1-2.93E+01 1.25E+02

+/-

3.62E+01 1.05E+02

+/-

3.23E+01 1.01E+02

+/-

3.39E+01 1.14E+02

+/-

4.33E+01 1.22E+02

+/-

3.45E+01 1.39E+02

+/-

3.06E+01 I

2.59E+00

+/-

I.

Cs-134**

2.

7.

1.

2.

1.

2.

17E+00 IjI 7

29E+00 1.31E+00 64E-01 8.70E-01 03E+00 1.73E+00 90E+00 1.11E+00 50E+00 2.22E+00 26E+00 1.91E+00 10E+00 1.03E+00 59E+00 1.95E+00 22E+00 1.92E+00 31E+00 1.96E+00 49E+00 1.83E+00 71E+00 2.01E+00 07E+00 2.03E+00 Mean of All Indicator Location:

1.64E+02 1.47E+02 1.54E+02 1.30E+02 1.53E+02 1.52E+02 1.56E+02 1.64E+02 1.59E+02 1.31 E+02 1.79E+02 1.48E+02 1.52E+02 Be-7

+/-f

+/-

+/-f MEANSI 7.24E+01 1.83E+0(

7.23E+01 7.58E+01 7.92E+01 8.39E+01 9.OOE+01 9.75E+01 1.02E+02 1.07E+02 3.34E+0C 1.15E+02 1.22E+02 7.81 E+01 3.64E+01 Quarter 4 Cs-134*

+f-1.04E+00

+/--

+/-I

+/-f

+f-1.29E+00

+ 1-

+/-f

+4-f

+/-

1.75E+00

Control Station

- LLD identified in ODCM 1.52E+02

+/-

8.71E+01 2.59E+00 45

Table 3-6 Soil

[pCi/kg]

page 1 of 1 Sr-Sr-Be-K-

89 90 7

40 Station Cs-Cs-134*

137*

AcTh-228 01 02 03 04 05 05A 06 07 21 22 23 24*

Annual Mean Indicator Mean Soil samples collected triennially. Last collected 2007. Next samples due 2010.

Control Station 46

Table 3-7 Precipitation Gross Beta

[pCi/L]

page 1 of 2 Sampling Date Gross Beta I

01/27/09 02/24/09 03/31/09 04/28/09 05/26/09 06/30/09 07/28/09 08/25/09 09/29/09 10/27/09 11/24/09 12/29/09 Mean 9.95E+00 3.99E+01 1.30E+01 3.11E+00 5.84E+00 2.58E+00 1.85E+00 3.57E+00 2.21 E+00

+/-

1.79E+00 2.99E+00 1.85E+00 1.18E+00 1.63E+00 1.56E+00 1.34E+00 1.89E+00 1.18E+00 1.43E+00 1.24E+00 1.86E+00 SRainfall inches) 1.82 1.07 3.06 2.60 4.66 7.49 3.03 3.93 2.39 1.81 8.53 7.19 9.11E+00

+/-

1.66E+00 Total 47.58

LLD identified in ODCM 47

Table 3-7 Precipitation Gamma Spectra

[pCi/L]

page 2 of 2 Sampling Location I

Be-7 Mn-54 I

Fe-59 I

Co-58 Co-60 I

Co-60 I

01A 06/30/09 5.39E+01

+,-

12/29/09 5.37E+01

+/-

3.34E+01 2.96E+01 1.05E+00 1.85E+00 7.56E+00 1.36E+01 2.11 E+00 3.75E+00 8.85E-01 1.62E+00 01A 06/30/09 12/29/09 01A 06/30/09 12/29/09 Zn-65 I

Zr-95 I

Nb-95 I

Cs-134 I

Cs-137 I

2.22E+00 4.27E+00 2.56E+00 9.66E-01 8.63E-01 3.91E+00 7.55E+00 4.86E+00 1.56E+00 1.51E+00 Ba-140 I

La-140 I

Ac-228 I

Th-228 I

Th-232 I

8.80E+02 1.59E+03 2.68E+02 5.33E+02 4.08E+00

+/-

3.27E+00 0.OOE+00 1.21E+01

+/-

MEAN 5.42E+00 4.27E+00

+/-

2.20E+00 Sampling Location I

Be-7 Mn-54 I

I I

Fe-59 Co-58 Co-60 01A 5.38E+01

+/

3.15E+01 01A 01A Zn-65 Zr-95 Nb-95 Cs-i34 Cs-137 Ba-140 La-140 Ac-228 I

Th-228 I

Th-232 1.21E+01

+/-

2.71 E+00 4.27E+00

+/-

1.10E+00 4.08E+00

+/-

1.64E+00 48

Table 3-8 Milk Gamma Spectra & Strontium

[pCi/L]

page 1 of 1 Sampling Date 01/20/09 02/17/09 03/17/09 04/21/09 05/19/09 06/16/09 07/22/09 08/18/09 09/15/09 10/21/09 11/17/09 12/17/09 Sta. Mean Sampling Date 01/20/09 02/17/09 03/17/09 04/21/09 05/19/09 06/16/09 07/22/09 08/18/09 09/15/09 I

K-40 1.32E+03

+/-

4.02E+01 1.21E+03

+/-

1.20E+02 1.42E+03

+/-

1.33E+02 1.18E+03

+/-

1.36E+02 1.18E+03

+/-

5.69E+01 1.50E+03

+/-

5.96E+01 1.12E+03

+/-

1.03E+02 1.32E+03

+/-

1.68E+02 1.33E+03

+/-

1.58E+02 1.35E+03

+/-

1.30E+02 1.42E+03

+/-

1.06E+02 1.27E+03

+/-

1.08E+02 1.30E+03

+/-

1.10E+02 Sr-89 I

Sr-90 I

I I

I

[a]

2.07E+00 2.84E+00 3.99E+00 9.46E-01

[a]

1.77E+00 9.45E-01

[a]

4.79E-01

[a]

1.18E+00 Sr-90 1-131*

7.65E-01 6.08E-01 7.32E-01 7.06E-01 7.99E-01 8.62E+00 8.52E-01 4.94E-01 7.48E-01 2.78E-01 7.79E-01 6.94E-01 1-131*

6.11E-01 6.57E-01 7.74E-01 5.34E-01 8.28E-01 6.79E-01 8.67E-01 5.24E-01 9.23E-01 I

Cs-134*

1.45E+00 5.18E+00 4.60E+00 5.41E+00 1.93E+00 1.18E+00 2.63E+00 8.37E+00 5.98Et00 4.73E+00 4.61E+00 4.18E+00 Cs-134*

1.62E+00 4.92E+00 4.89E+00 5.32E+00 1.66E+00 1.67E+00 3.98E+00 6.OOE+00 5.54E+00 I

Cs-137*

1.67E+00 6.23E+00 5.16E+00 6.28E+00 2.31 E+00 1.43E+00 2.86E+00 8.41E+00 6.76E+00 6.27E+00 4.67E+00 4.11E+00 Cs-137*

1.94E+00 5.68E+00 6.09E+00 6.14E+00 1.79E+00 1.80E+00 3.77E+00 7.16E+00 5.92E+00 I

Ba-140*

1.12E+01 3.87E+01 3.60E+01 4.62E+01 2.95E+01 1.46E+01 1.58E+01 5.02E+01 3.01E+01 2.77E+01 3.40E+01 2.09E+01 Ba-140*

1.30E+01 3.30E+01 4.30E+01 3.98E+01 2.47E+02 1.91E+01 2.24E+01 3.39E+01 2.89E+01 Station 12 S La-140*

3.OOE+00 1.29E+01 1.48E+01 1.19E+01 8.76E+00 4.20E+00 4.36E+00 1.47E+01 1.16E+01 7.64E+00 9.71 E+00 4.70E+00 Station 13 oLa-140*

3.82E+00 1.32E+01 9.60E+00 1.45E+01 7.13E+00 5.57E+00 3.42E+00 1.43E+01 8.43E+00 I

1.22E+03 1.25E+03 1.23E+03 1.07E+03 1.22E+03 1.54E+03 9.83E+02 1.25E+03 1.05E+03 K-40 Sr-89 I

I-I-

I

-I 4.80E+01 1.25E+02 1.26E+02 1.47E+02 4.33E+01 5.04E+01 1.24E+02 1.52E+02 1.32E+02 1.05E+02 1.08E+02

[a]

2.14E+00 2.96E+00 4.75E+00

[a]

1.79E+00 1.14E+00 7.62E-01

[b]

Sta. Mean 1.20E+03

+/-

Total Mean 1.26E+03

+/-

LLD identified in ODCM

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

[b] Dairy ceased milking operations 49

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

page 1 of 2 Sampling Sampling Location Date Be-7 K-40 I

1-131" I

Cs-134*

Cs-137*

14A 04/14/09 3.03E+02

+/-

5.92E+01 3.86E+03

+/-

1.73E+02 1.73E+01 4.79E+00 4.92E+00 05/12/09 7.05E+02

+/-

5.56E+01 4.69E+03

+/-

1.10E+02 3.43E+01 3.36E+00 3.92E+00 06/09/09 3.53E+02

+/-

5.35E+01 5.75E+03

+/-

1.52E+02 4.48E+01 4.68E+00 5.51E+00 07/14/09 1.31E+03

+/-

2.33E+02 6.47E+03

+/-

4.57E+02 4.23E+01 1.87E+01 1.99E+01 08/11/09 2.08E+02

+/-

6.30E+01 7.67E+03

+I-2.24E+02 3.55E+01 6.97E+00 7.39E+00 09/08/09 8.66E+02

+/-

2.28E+02 4.70E+03

+/-

4.91 E+02 3.28E+01 1.48E+01 1.57E+01 10/13/09 1.05E+03

+/-

1.21E+02 7.72E+03

+/-

2.86E+02 3.82E+01 1.09E+01 1.16E+01 Mean 6.85E+02

+/-

1.16E+02 5.84E+03

+/-

2.70E+02

+/-

Sampling Sampling Location Date I

Be-7 I

K-40 I

-13I Cs134*

I Cs-37*

15 04/14/09 1.21E+03

+/-

1.49E+02 4.47E+03

+/-

3.15E+02 3.33E+01 9.76E+00 1.16E+01 05/12/09 1.21E+03

+/-

7.20E+01 4.89E+03

+/-

1.30E+02 3.01E+01 3.05E+00 3.47E+00 06/09/09 1.01E+03

+/-

7.93E+01 3.49E+03

+/-

1.68E+02 4.67E+01 5.38E+00 5.94E+00 07/14/09 2.06E+03

+/-

2.08E+02 6.39E+03

+/-

4.48E+02 3.44E+01 1.80E+01 1.98E+01 08/11/09 1.45E+03

+/-

1.80E+02 3.23E+03

+/-

3.48E+02 4.55E+01 9.10E+00 9.90E+00 09/08/09 7.75E+02

+/-

1.41E+02 4.24E+03

+/-

2.53E+02 2.97E+01 1.07E+01 1.04E+01 10/13/09 2.24E+03

+/-

1.74E+02 5.95E+03

+/-

3.06E+02 4.37E+01 1.36E+01 1.47E+01 Mean 1.42E+03

+/-

1.43E+02 4.67E+03

+/-

2.81E+02

+/-

Sampling Sampling Location Date I

Be-7 I

K-40 I

I-I I

ICs-i37*

16**

04/14/09

- Control 05/12/09 Station 06/09/09 07/14/09 08/11/09 09/08/09 10/13/09 Mean

LLD identified in ODCM 5.30E+02 6.37E+02 6.80E+02 2.59E+03 1.40E+03 7.06E+02 3.45E+03 1.43E+03 9.90E+01 6.60E+01 6.95E+01 2.50E+02 1.25E+02 2.95E+02 2.33E+02 1.63E+02 4.25E+03 2.08E+03 3.81E+03 8.30E+03 3.45E+03 3.79E+03 5.53E+03 4.46E+03 2.67E+02 1.15E+02 1.42E+02 4.64E+02 1.99E+02 4.95E+02 3.28E+02 2.87E+02 2.63E+01 2.80E+01 3.68E+01 2.90E+01 4.58E+01 2.92E+01 3.24E+01 7.07E+00 3.OOE+00 4.64E+00 1.56E+01 9.41E+00 1.34E+01 1.42E+01 1.OOE+01 3.43E+00 8.84E+00

+/-

3.24E+00 1.73E+01 1.08E+01 1.84E+01 1.40E+01 8.84E+00

+/-

3.24E+00 50

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

pa 2o Sampling Location Sampling Date I

Be-7 I

K-40 1-131*

I Cs-134*

I Cs-137*

I 23 04/14/09 05/12/09 06/09/09 07/14/09 08/11/09 09/08/09 10/13/09 Mean Sampling Date 3.03E+02 4.08E+02 1.28E+03 2.30E+03 4.06E+02 6.45E+02 2.35E+03

+1-

+1-5.92E+01 5.OOE+01 1.07E+02 2.34E+02 1.06E+02 2.28E+02 1.67E+02 3.86E+03 6.57E+03 6.10E+03 4.15E+03 8.96E+03 3.58E+03 6.07E+03 1.73E+02 1.62E+02 2.25E+02 4.02E+02 3.07E+02 3.65E+02 2.85E+02 1.73E+01 3.40E+01 4.55E+01 3.48E+01 3.58E+01 3.13E+01 3.09E+01 4.79E+00 4.90E+00 5.64E+00 1.69E+01 9.15E+00 1.37E+01 1.31E+01 2.61E+01

+/-

4.92E+00 5.89E+00 6.87E+00 1.42E+01 1.05E+01 1.42E+01 1.40E+01 1.10E+03

+/-

1.36E+02 5.61E+03

+/-

2.74E+02

+/-

2.61E+01

+/-

1.42E+01 Sampling Location Be-7 K-40 1-131*

Cs-134*

I Cs-137*

26 04/14/09 05/12/09 06/09/09 07/14/09 08/13/09 09/08/09 10/13/09 4.58E+02 9.33E+02 7.70E+02 1.62E+03 9.15E+02 6.02E+02 3.15E+02 7.35E+01 6.12E+01 9.62E+01 2.37E+02 1.19E+02 1.40E+02 7.93E+01 4.64E+03 4.71 E+03 4.84E+03 4.82E+03 5.60E+03 2.37E+03 6.55E+03 1.97E+02 1.23E+02 2.OOE+02 4.12E+02 2.35E+03 2.41 E+02 2.25E+02 1.97E+01 3.OOE+01 4.04E+01 3.78E+01 3.33E+01 4.08E+01 4.20E+01 5.72E+00 3.47E+00 8.20E+00 1.66E+01 8.86E+00 1.03E+01 7.41E+00 6.37E+00 3.98E+00 8.73E+00 1.70E+01 1.03E+01 1.16E+01 7.68E+00 Mean 8.02E+02

+/-

1.15E+02 4.79E+03

+/-

5.35E+02 1.11E+03

+/-

1.33E+02 5.17E+03

+/-

3.41E+02

+/-

Indicator locations 2.61E+01

+/-

1.42E+01

LLD identified in ODCM 51

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

[pCi/L]

page 1 of 1 Sampling Date H-3 Sr-89 I

Sr-90 Mn-54 Fe-59 Co-58 I

Station 01A I Zn-65 I

Co-60 03/31/09 06/30/09 09/29/09 12/29/09 1.93E+02 7.50E+00 9.15E+02 5.46E+02

[a]

8.17E-01

[a]

8.21E-01

[a]

7.81E-01 1.09E+00 1.46E+00 2.43E+00 1.85E+00 2.56E+00 3.30E+00 5.85E+00 8.94E-01 1.17E+00 1.67E+00 2.33E+00 8.04E-01 1.12E+00 1.58E+00 2.53E+00 1.99E+00 2.16E+00 3.07E+00 5.65E+00 Mean Sampling Date Zr-95 Nb-95 1-131 I

Cs-134 I

Cs-137 1

Ba-140-I La-140 I

03/31/09 06/30/09 09/29/09 12/29/09 1.55E+00 2.07E+00 3.13E+00 4_80E+00 8.73E-01 1.28E+00 1.91E+00 3.25E+00 1.79E+00 3.42E+00 9.OOE+00 9.33E+00 7.81E-01 1.02E+00 1.48E+00 2.66E+00 8.28E-01 1.18E+00 1.64E+00 2.65E+00 4.68E+00 7.67E+00 1.56E+01 1.97E+01 1.28E+00 2.39E+00 4.34E+00 6.65E+00 Mean

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

52

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

[pCi/L]

page 1 of 1 Sampling Date Sr-89 I

H-3*

Sr-90 I

Mn-54*

Fe-59*

I Co-58*

I Station 11 Co-60*

I Zn-65*

01/13/09 02/17/09 03/17/09 04/14/09 05/12/09 06/16/09 07/13/09 08/11/09 09/14/09 10/13/09 11/17/09 12/17/09 MEAN Sampling Date

[a]

5.03E+03

+/-

[a]

3.76E+03

+/-

[a]

2.87E+03

+/-

[a]

3.59E+03

+/-

3.81 E+03

+/-

5.77E+02 8.53E+02 6.86E+02 6.87E+02 7.01E+02

[b]

4.45E+00

[b]

7.18E-01 4.13E+00 5.04E+00 5.24E+00 1.04E+00 7.58E-01 1.25E+00 3.82E+00 2.46E+00 4.10E+00 4.63E+00 2.57E+00 3.OOE+00 7.97E+00 9.10E+00 1.31E+01 2.12E+00 2.03E+00 3.39E+00 1.17E+01 5.08E+00 1.19E+01 1.13E+01 5.92E+00 7.22E+00 Cs-137*

4.32E+00 5.11E+00 5.63E+00 9.03E-01 9.08E-01 1.47E+00 4.30E+00 2.78E+00 4.82E+00 5.28E+00 3.06E+00 3.80E+00 3.67E+00 4.56E+00 4.39E+00 1.44E+00 7.47E-01 1.26E+00 4.15E+00 2.06E+00 4.05E+00 6.77E+00 2.40E+00 3.25E+00 8.11E+00 9.54E+00 9.76E+00 2.20E+00 1.53E+00 2.55E+00 9.27E+00 4.29E+00 7.10E+00 9.70E+00 5.93E+00 6.53E+00 Zr-95*

Nb-95*

I 1-131*

I Cs-134*

Ba-140*

I La-140*

I 01/13/09 02/17/09 03/17/09 04/14/09 05/12/09 06/16/09 07/13/09 08/11/09 09/14/09 10/13/09 11/17/09 12/17/09 MEAN

LLD identified in ODCM 6.82E+00 8.22E+00 1.04E+01 1.75E+00 1.61 E+00 2.84E+00 9.68E+00 4.OOE+00 8.07E+00 9.71 E+00 5.43E+00 6.03E+00 4.64E+00 5.86E+00 6.53E+00 1.01E+00 9.92E-01 1.55E+00 5.04E+00 2.04E+00 4.99E+00 4.97E+00 3.01 E+00 3.54E+00 6.58E-01 5.54E-01 7.60E-01 9.44E-01 6.26E-01 5.75E-01 6.86E-01 4.74E-01 7.09E-01

'4.37E-01 6.07E-01 5.17E-01 3.84E+00 4.75E+00 4.40E+00 9.25E-01 7.76E-01 1.20E+00 3.18E+00 2.15E+00 5.03E+00 4.85E+00 2.61E+00 2.98E+00 3.53E+00 5.17E+00 5.49E+00 1.19E+00 8.OOE-01 1.29E+00 4.18E+00 2.57E+00 4.60E+00 4.44E+00 3.12E+00 3.25E+00 2.48E+01 2.66E+01 4.41E+01 6.86E+00 1.11E+01 1.57E+01 4.02E+01 1.53E+01 2.14E+01 2.36E+01 2.13E+01 2.27E+01 8.OOE+00 1.07E+01 1.05E+01 2.41 E+00 3.03E+00 5.OOE+00 1.15E+01 5.61E+00 8.21 E+00 7.60E+00 6.39E+00 6.43E+00

[a] Tritium analyses on quarterly composite.

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

53

Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium

[pCi/L]

page 1 of 2 Sampling Date H-3*

01/13/09

[a]

02/17/09

[a]

03/17/09 3.22E+03

+/-

3.72E+02 04/14/09

[a]

05/12/09 06/16/09 3.86E+03

+/-

8.66E+02 07/13/09

[a]

08/11/09

[a]

09/14/09 2.60E+03

+/-

6.70E+02 10/13/09

[a]

11/17/09

[a]

12/15/09 3.37E+03

+/-

6.66E+02 Mean 3.26E+03

+/-

6.44E+02 2Sr-89L

[b]

3.93E+00

[b]

[b)

[b]

Sr-90 I

Mn-54*

[b]

3.84E+00

[b]

6.35E+00

[b]

4.OOE+00

[b]

1.34E+00

[b]

6.28E-01 7.68E-01 6.34E-01

[b]

4.93E+00

[b]

2.06E+00

[b]

6.08E+00

[b]

4.08E+00

[b]

1.88E+00

[b]

2.93E+00 Fe-59*

8.68E+00 1.01E+01 1.10E+01 2.98E+00 1.30E+00 1.56E+00 8.97E+00 5.87E+00 1.31 E+01 9.75E+00 4.30E+00 5.49E+00 Station 08 Co-58" Co-60" Zn-65*

4.34E+00 3.85E+00 7.09E+00 6.89E+00 5.43E+00 1.08E+01 4.83E+00 5.29E+00 9.95E+00 1.41 E+00 1.34E+00 2.61 E+00 6.71E-01 5.38E-01 1.10E+00 7.63E-01 8.38E-01

+/-

9.03E-01 1.27E+00 5.31 E+00 3.59E+00 8.72E+00 2.38E+00 2.77E+00 4.91 E+00 7.20E+00 6.23E+00 1.09E+01 4.66E+00 4.48E+00 9.44E+00 1.95E+00 1.83E+00 3.93E+00 2.93E+00 3.06E+00 6.56E+00 8.38E-01

+/-

9.03E-01 Sampling Date 01/13/09 02/17/09 03/17/09 04/14/09 05/12/09 06/16/09 Zr-95*

Nb-95*

I 1-131*

Cs-134*

Cs-137*

Ba-140*

La-140" I

6.77E+00 1.05E+01 8.81 E+00 2.59E+00 1.21E+00 1.27E+00 8.75E+00 3.85E+00 8.68E+00 7.36E+00 3.31E+00 5.20E+00 4.10E+00 6.96E+00 4.96E+00 1.51E+00 7.01E-01 7.62E-01 4.34E+00 2.76E+00 6.81E+00 4.38E+00 2.13E+00 2.60E+00 7.10E-01 5.63E-01 7.91E-01 9.85E-01 5.99E-01 6.10E-01 7.09E-01 5.09E-01 6.74E-01 4.57E-01 6.30E-01 7.42E-01 3.52E+00 5.99E+00 4.45E+00 1.32E+00 6.13E-01 6.05E-01 4.20E+00 2.28E+00 5.49E+00 3.63E+00 1.78E+00 3.08E+00 3.99E+00 2.29E+01 6.08E+00 3.84E+01 4.06E+00 3.64E+01 1.43E+00 9.45E+00 6.11E-01 9.09E+00

+/-

4.70E+00 7.13E-01 8.04E+00 8.26E+00 1.11E+01 1.OOE+01 2.80E+00 1.79E+00 2.51 E+00 1.24E+01 6.90E+00 1.30E+01 6.75E+00 4.24E+00 6.68E+00 07/13/09 08/11/09 09/14/09 10/13/09 11/17/09 12/15/09 Mean

LLD identified in ODCM 5.19E+00 2.34E+00 6.99E+00 4.90E+00 1.91E+00 3.31 E+00 3.34E+01 2.04E+01 2.78E+01 2.15E+01 1.42E+01 1.80E+01 9.09E+00

+/-

4.70E+00

[a] Tritium analyses on quarterly composite.

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

54

Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium

[pCi/L]

page 2 of 2 Sampling Date 01/13/09 02/1709 03/17/09 04/14/09 05/12/09 06/16/09 07/13/09 08/11/09 09/14/09 10/13/09 11/17/09 12/15/09 MEAN H-3*

I

[a]

[a)

[a]

Sr-89

[

[b]

4.50E+00 Sr-90 I

1.94E+02 5.86E+02 8.71 E+02 7.25E+02-6.22E-01 Mn-54*

3.89E+00 4.68E+00 5.67E+00 1.74E+00 1.34E+00 9.04E-01 3.76E+00 2.78E+00 6.29E+00 4.24E+00 2.63E+00 1.94E+00

[b]

(b]

[b]

Fe-59*

9.65E+00 1.13E+01 1.07E+01 4.62E+00 3.54E+00 2.32E+00 8.89E+00 4.17E+00 1.11E+01 8.35E+00 6.03E+00 6.50E+00 Cs-137*

4.83E+00 5.IOE+00 5.63E+00 1.91E+00 1.36E+00 9.OOE-01 3.34E+00 2.13E+00 6.36E+00 4.75E+00 2.71 E+00 2.42E+00 Co-58*

4.38E+00 5.60E+00 5.51 E+00 2.04E+00 1.54E+00 1.04E+00 3.85E+00 2.61E+00 5.53E+00 4.57E+00 2.90E+00 3.31E+00 Ba-140*

2.73E+01 3.50E+01 4.71E+01 1.26E+01 1.75E+01 1.14E+01 3.54E+01 1.86E+01 3.23E+01 2.03E+01 2.03E+01 2.06E+01 I

Station 09A Co-60*

Zn-65*

4.91 E+00 7.55E+00 4.97E+00 9.86E+00 5.03E+00 1.04E+01 1.95E+00 3.41 E+00 1.28E+00 2.59E+00 8.95E-01 1.80E+00 2.96E+00 7.04E+00 1.37E+00 4.35E+00 6.70E+00 1.12E+01 4.80E+00 7.57E+00 2.86E+00 5.34E+00 2.82E+00 5.24E+00 Sampling Date 01/13/09 02/1709 03/17/09 04/14/09 05/12/09 06/16/09 07/13/09 08/11/09 09/14/09 10/13/09 11/17/09 12/15/09 Zr-95*

I 7.86E+00 9.75E+00 1.11E+01 3.44E+00 2.74E+00 1.89E+00 6.54E+00 4.06E+00 9.81 E+00 8.52E+00 5.02E+00 3.74E+00 Nb-95*

4.28E+00 5.68E+00 6.89E+00 2.01 E+00 1.88E+00

+/-

9.67E-01 1.12E+00 5.07E+00 2.75E+00 5.35E+00 4.28E+00 2.95E+00 1.79E+00 I

1-131*

5.60E-01 6.15E-01 8.62E-01 9.71 E-01 6.19E-01 6.12E-01 7.26E-01 4.97E-01 6.50E-01 4.49E-01 6.44E-01 4.99E-01 I

Cs-134" 4.43E+00 5.66E+00 5.46E+00 1.67E+00 1.25E+00 8.27E-01 3.46E+00 2.39E+00 5.41E+00 4.66E+00 2.68E+00 2.38E+00 I

I I

La-140*

9.14E+00 6.53E+00 1.13E+01 3.57E+00 5.63E+00 3.41 E+00 1.32E+01 5.59E+00 1.03E+01 5.77E+00 7.36E+00 4.09E+00 MEAN LLD identified in ODCM

[a] Tritium analyses on quarterly composite.

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

55

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

page 1 of 1 Sample Date I

Sr-89 Sr-90 K-40 Cs-134*

Cs-137*

04/07/2009 Station 08 Station 09A**

Station 11

[a]

1.21E+04

+/-

9.79E+02 1.33E+04

+/-

1.24E+03 3.24E+04

+/-

1.69E+03 Ra-226 5.03E+01 4.88E+01 4.82E+01 1.30E+02

+/-

6.28E+01 5.72E+01 6.72E+01 Th-228 I

Th-232 04/07/2009 Station 08 Station 09A**

Station 11 Sample Date 1.34E+03

+/-

9.96E+02 1.26E+03

+/-

8.70E+01 1.21E+03

+/-

1.39E+02 2.21E+03

+/-

1.25E+03 7.98E+02

+/-

8.31E+01 5.95E+02

+/-

1.43E+02 4.68E+03

+/-

1.26E+03 2.91E+03

+/-

1.36E+02 2.91E+03

+/-

1.99E+02 Sr-89 Sr-90 K-40 I

Cs-134*

Cs-137*

10/12/2009 Station 08 Station 09A**

Station 11 10/12/2009 I

Station 08 Station 09A**

Station 11 8.36E+01 9.25E+01

+/-

2.17E+01 1.36E+04

+/-

1.50E+03 7.74E+01 2.96E+01 1.19E+04

+/-

9.27E+02 8.22E+01 4.46E+01 1.65E+04

+/-

1.28E+03 Ra-226 7.82E+01 9.18E+01 3.62E+01 4.65E+01

+/-

2.75E+01 5.12E+01 5.35E+01 Th-228 I

Th-232 1.88E+03 1.34E+03

+/-

1.28E+02 1.37E+03

+/-

2.15E+02 1.23E+03

+/-

7.15E+02 6.61E+02

+/-

6.01E+01 5.60E+02

+/-

1.15E+02 1.85E+03

+/-

1.04E+03 1.17E+03

+/-

8.54E+01 1.17E+03

+/-

1.21E+02 MEAN Sr-89 Sr-90 K-40 Cs-1 34*

Cs-137*

Indicator Control

+/-

9.25E+01

+/-

2.17E+01 1.87E+04

+/-

1.36E+03 1.26E+04

+/-

1.08E+03 Ra-226 8.83E+01

+/-

4.52E+01 Th-232 Th-228 Indicator Control

LLD identified in ODCM 2.62E+03

+/-

1.29E+03 1.67E+03

+/-

1.09E+02 1.67E+03

+/-

1.69E+02 1.72E+03

+/-

9.83E+02 7.30E+02

+/-

7.16E+01 5.78E+02

+/-

1.29E+02

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

- Control Station 56

Table 3-14 Shoreline Soil Gamma Spectra, and Strontium

[pCi/Kg] -

page 1 of 1 C

Sample I

Date Sr-89 Sr-90 K-40 I

Cs-134 I

Cs-137 04/07/2009 Station 08

[a]

2.56E+03

+/_ 5.50E+02 4.14E+01 5.01 E+01 I

Ra-226 Th-228 I

Th-232 I

1.09E+03 1.02E+03 5.71E+02 7.18E+01 5.03E+02 1.12E+02 Sample Date Sr-89 Sr-90 K-40 Cs-134 Cs-1 37 10/12/2009 Station 08 8.65E+01 3.21E+01 2.70E+03 4.97E+02

+/-

4.39E+01 4.68E+01 Ra-226 Th-228 Th-232 1.35E+03 5.50E+02

+/-

MEAN K-40 6.15E+02 8.56E+01 5.86E+02 1.22E+02

+/-+-

Sr-89 Sr-90 I

Cs-134 Cs-1 37 I.

IE 0I I.4I+I

+/-

2.3 3

+/-

52E0 Ra-226

+/-

I Th-228 Th-232 1.22E+03

+/-

7.85E+02 5.93E+02

+/-

7.87E+01 5.45E+02

+/-

1.17E+02

LLD identified in ODCM

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

57

Table 3-15 Fish Gamma Spectra

[pCi/Kg]

page 1 of 1 Fish [a]

Sampling Station 08 Date I

K-40 I

Mn-54*

I Fe-59*

I Co_58*

t Co-60 I

Zn-65*

I Cs.134*

I Cs-37 04/08/09 3.41E+03

+/-

8.10E+02 4.78E+01 1.29E+02 5.56E+01 3.97E+01 9.47E+01 4.25E+01 4.94E+01 10/21/09 1.73E+03

+/-

7.42E+02 5.73E+01 1.42E+02 8.OOE+01 5.27E+01 1.36E+02 6.14E+01 6.24E+01 Sampling Station 25**

Date I

K-40 I

Mn-54*

I F e-59*

I Co58*

I Co-60*

I Zn-65*

I Cs134*

I Cs-37*

04/08/09 2.44E+03

+/-

4.99E+02 3.41E+01 6.23E+01 3.71E+01 4.26E+01 6.52E+01 2.88E+01 3.08E+01 10/13/09 2.24E+03,

+/-

8.12E+02 7.56E+01 1.98E+02 9.48E+01 6.59E+01 1.53E+02 6.14E+01 6.70E+01 catfish [b]

Sampling Station 08 Date I

K-40 I

Mn-54.

I Fe-59*

I Co58*

I Co-60 I

Zn-65*

I Cs134*

I Cs-37*

04/08/09 2.27E+03

+/-

7.44E+01 4.71E+01 1.11E+02 4.83E+01 5.38E+01 9.35E+01 4.06E+01 5.33E+01 10/21/09 2.07E+03

+/-

7.10E+02 4.75E+01 1.35E+02 5.71E+01 4.31E+01 1.07E+02 4.55E+01 5.31E+01 Sampling Station 25**

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*

04/08/09 1.82E+03

+/-

5.61E+02 10/13/09 1.63E+03

+/-

6.50E+02 3.39E+01 8.34E+01 4.82E+01 1.18E+02 3.86E+01 5.03E+01 3.17E+01 4.06E+01 5.48E+01 9.66E+01 3.62E+01 3.93E+01 4.43E+01 4.44E+01 Mean 2.20E+03

+'/-

6.07E+02 Indicator 2.37E+03

+/-

5.84E+02 Control 2.03E+03

+/-

6.31E+02

LLD identified in ODCM

- Control Station.

[a] Non-bottom dwelling species of gamefish.

[b] Bottom dwelling species of fish. '

58

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2009 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 TBEW 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 2009 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Naturally occurring nuclides such as Be-7, K-40, and Th-228 were detected in numerous samples. Th-228 results were variable and are generally at levels higher than plant related radionuclides.

The following is a discussion and summary of the results of the environmental measurements taken during the 2009 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.

,59

9.0 8.0 7.0 6.0 5.0

-- *-Environmental TLDs 4.0

-U-Sector TLDs 3.0 Avg. Pre-up 2.0 1.0 0.0

,a 00 10 00

-W0 00 0

OP i

OP

ý T

TT C

C C?

CC Figure 4-1 TLD (mrem/Standard Month)

Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The average level of the 32 locations (two badges at each location) was 5.0 mR/standard month with a range of 0.2 to 54.5 mR/standard month. The highest quarterly average reading for any single location was obtained at location SSW-19/51. This value was 31.5 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 3.4 mR/standard month with a range of 1.5 to 6.1 mR/standard month. The average annual reading for these locations was 2.9 mR/standard month with a range of from 1.6 to 4.7 mR/standard month. The control location showed a quarterly average of 3.0 mR/standard month with a range of 2.8 to 3.4 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 5.1 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.6 mR/standard month. Eight other TLDs, designated C-I thru C-8, which were pre-operational controls, were collected quarterly from four locations. Stations C-3/4 and C-7/8 are designated controls. These had a quarterly average of 3.2, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.2 to 4.3 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

60

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 2009 may be a function a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this in fact the case. Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3).

This indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.

0.12 0.1 E 0.08 0.06 004 0.02 00 M

C 1-t Lf)

(0 o

0

)

0')

0'-)

0')

0)

0) 0-)

00 0)

CL CD C) 0 MV (V

(V (V

(V U')

C)

<0 r-00 0) 0C C)

CD 0C V

(V V

(V Control Sta-24 Indicator Average Pre-op Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 61

2.50E-02 2.OOE-02 1.50E-02 1.0OE-02 5.0OE-03 O.OOE+O0 00 00 M

M*

al*

)

0 75 00 00 2

-0 Control Sta-24 -U-Indicator Figure 4-3 2009 Gross Beta in Air Particulates (pCi/m3) 4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine.

Once a week the samples are collected and analyzed. The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.

4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectrometry.

The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes.

Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected. Cs-134 was reported in two samples. However, it was not identified by the peak search software, but the forced activity calculation of the software reported a result greater than both the MDC and the 2-Y error. This is not considered a true positive result. The results of these analyses indicate the lack of station effects on the environment.

62

4.5 Air Particulate Strontiurn 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 these fission products at any of the indicator or control stations in recent years.

4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2007 and thus were not collected in 2009.

4. 7 Precipitation A sample of rain water was collected monthly at on-site station 0 IA and analyzed for gross beta activity. The results are presented in Table 3-7.

12 precipitation samples, were obtained in 2009.

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 2009.

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 2009 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 snamples" 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 detectable 1-131 above the LLD of 1 pCi/1. 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.

63

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 measure.d for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents.

Its detection is the product of nuclear weapons testing fallout. This conclusion can be made based upon the fact that Sr-89 and Sr-90 have not been detected in gaseous effluents released from the station in many years, and the trend of consistent declining levels since the pre-operational period.

4.9 Food Products and Vegetation Food/vegetation samples, were -collected from five locations and analyzed by gamma spectrometry. The results of the analyses are presented in Table 3-9. One sample from an indicator location detected Cs-137 at a level of 26.1 pCi/kg. Low levels of Cs-137, attributable to fallout, has been seen periodically in vegetation samples. Cs-137 was also reported in one vegetation sample at the control location as a result of the software's forced activity calculation at 8.84 pCi/kg, which was greater than both the MDC and the 2-cy error. This is not considered a true positive.

As expected, naturally occurring potassium-40 and, cosmogenic beryllium-7 were detected in all samples, and thorium-228 and other natural products, including Bi-214, were detected in some samples.

4.10 Well Water Water was sampled quarterly from the 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.

Nogarma ermitting 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 recent years.

No gamma emitting radioisotopes were detected in any of the samples. There 64

was no measured activity of strontium-89 or strontium-90.

Tritium was measured in all four samples with an average annual concentration of 3810 pCi/liter and a range of 2870 to 5030 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 sJ 5000 C) 4000 CL 3000 2000 1000 00 0

Date H-3 in RW Tritium

-H-3 in RW Required LLD I'- CO 03 r-0 0

0 0

0 C001C0,I Figure 4-4Tritium in River water 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma ray spectrometry and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90.

There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.

Co-60 was identified in one sample from the indicator location at a level of 0.838 pCi/L. However, this was less than the 2-sigma value and is not considered a true positive.

Ba-140 was reported in one sample at the indicator location.

However, this was due to a forced activity calculation.

The nuclide was not identified during the peak search and is not considered a true positive. Similarly, Nb-95 was identified at the control location, but this was due to a forced activity 65

calculation and is not considered a true positive.

No other gamma emitting radioisotopes, including iodine were detected in any of the samples. No tritium was detected at the control location.

The average level of tritium activity at the indicator station was 3260 pCi/liter with a range of 2600 to 3860 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 Tritium 1000 4 Required LLD Average Pre-op 100 Figure 4. 5Tritium in Surface Water 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station.

Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.

Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectrometry. The October samples were analyzed for strontium-89 and strontium-90. The results are presented in Table 3-

13. Figure 4-6 shows the historical trend of Cs-137 in sediments.

In 2009, two (2) sediment samples from the control location showed Cs-137 at an average level of 88.3 pCi/kg. No Cs-137 was detected at the indicator location in 2009. 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 66

ray spectroscopy.

Strontium-90 was detected in one (1) indicator sample of aquatic sediment/silt at a specific activity of 92.5 pCi/kg. This has also occurred 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.

0.

10000 1000 100 10 1

Date S Station-8 Station-11 Station-9 Control-Sta-09A

-Average Pre-Op

-Required LLD's Figure 4-6 Cs-13 7 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 March and October from indicator station 08. The samples were analyzed by gamma ray spectrometry. The October sample was analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-14.

Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities. No plant related isotopes were detected in the two samples analyzed.

Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is attributed to accumulation of residual global fallout from past atmospheric weapons testing.

67

4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2009 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.

68

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2009 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14A, 15, 16 Vegetation 01-13-09 Seasonal Unavailability 23, 26 14A, 15, 16 Vegetation 02-10-09 Seasonal Unavailability 23, 26 14A, 15, 16 Vegetation 03-10-09 Seasonal Unavailability 23, 26 03 Air Particulate 03-27-09 Patch not centered, volume collected on patch unknown 05 Air Particulate 06-09-09 Breaker trip during storm. 11.2 hr run time Charcoal 05 Air Particulate 06-30-09 Breaker trip during storm. 84 hr run time Charcoal 13 Milk 10-21-09 Sold cows. No longer milking.

14A, 15, 16 Vegetation 11-10-09 Seasonal Unavailability 23, 26 13 Milk 11-17-09 Sold cows. No longer milking.

14A, 15, 16 Vegetation 12-08-09 Seasonal Unavailability 23, 26 13 Milk 12-15-09 Sold cows. No longer milking.

69

REFERENCES 70

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.

71

APPENDICES 72

APPENDIX A: LAND USE CENSUS Year 2009 73

LAND USE CENSUS North Anna Power Station North Anna County, Virginia January I to December 31, 2009 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch 150m2 Animal Cow Goat N

0.9 1.5 1.9 None None None NNE 0.9 0.9 3.1 1.5 None None NE 0.8 0.9 1.6 1.5 None None ENE 0.8 2.2 2.4 2.5 None None E

0.8 1.3 2.0 3.5 None None ESE 0.9 1.7 1.7 None None None SE 0.9 1.4 1.4 1.5 None None SSE 0.9 1.0 1.0 2.8 None None S

0.9 1.0 1.0 2.8 None None SSW 1

1.3 3.7 1.9 None None SW 1.1, 1.7 3.0 None None None WSW 1.1 1.6 None 1.6 None None W

1.1 1.5 1.8 None None None WNW 1

1.1 2.6 3.9 None None NW 1

1.0 None None None None NNW 0.9 1.0 2.2 None None None 74

0 2008 to 2009 Land Use Census Changes 2008 2009 Nearest Direction Distance Distance Site Boundary None Resident None Garden N

2.7 1.9 E

1.3 2.0 SSW 3.8 3.7 W

3.3 1.8 WNW 3.1 2.6 Meat Animal None Milch Cow None Milch Goat None 75

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2009 76

S..

0 INTRODUCTION 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 1 st 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 4th quarters.

> Water for natural uranium during the 2nd quarter RESULTS 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 09-09: Ni-63 failed high on MAPEP sample. Ni-63 value in soil was biased high due to recovery method. TBE does not currently perform Ni-63 in soil analyses. No action required

.NCR 09-10: Fe-55 in water failed high on MAPEP sample. Concentration in sample near detection limit.

Added Fe-55 to analytics cross check samples.

77

NCR 09-11:

Pu-238, 239/240 in water failed low on MAPEP sample.

Performance of Eichrom resin did not perform as previous lots. If another lot of resin is not usable, samples will be directly plated.

eNCR 09-12: Pu-238, 239/240 in air filter failed low on MAPEP sample.

Performance of Eichrom resin did not perform as previous lots. If another lot of resin is not usable, samples will be directly plated.

NCR 09-13:

Co-57 in vegetation failed high on MAPEP sample.

Due to geometry limitations, only 63.4% of sample could be used.

Non-homogeneity of sample resulted in failure. In future, a minimum of 72%

of sample will be utilized.

'NCR 09-14: Sr-89 in water on ERA sample failed high. Y-90 in-growth was not accounted for in sample. Recalculation assuming Y-90 in-growth was performed and results were in agreement.

Y-90 in-growth assessment question added to calculation spreadsheet.

NCR 09-23: Zn-65 on air particulate patch on Analytics failed high. Count was performed on another detector and was successful. Removed detector that failed from service for this geometry until it could be re-calibrated.

A summary of TBE's results is provided in the tables below for the required sample matrix types and isotopic distribution. Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result; analytical date; the known values supplied by the providers; pass or fail criteria.

78

A 9

1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2009 E6533-396 Milk Sr-89 pCi/L 102 97.7 1.04 A

Sr-90 pCi/L 14.9 15.6 0.96 A

E6534-396 Milk 1-131 pCi/L 66.7 79.3 0.84 A

Ce-141 pCi/L 87.5 94.9 0.92 A

Cr-51 pCi/L 275 305 0.90 A

Cs-134 pCi/L 82.0 93.7 0.88 A

Cs-137 pCi/L 111 111 1.00 A

Co-58 pCi/L 114 119 0.96 A

Mn-54 pCi/L 136 128 1.06 A

Fe-59 pCi/L 112 99.9 1.12 A

Zn-65 pCi/L 160 156 1.03 A

Co-60 pCi/L 142 142 1.00 A

2 E6536-396 AP Ce-141 pCi 120 115 1.04 A

Cr-51 pCi 385 371 1.04 A

Cs-134 pCi 113 114 0.99 A

Cs-137 pCi 149 135 1.10 A

Co-58 pCi 153 145 1.06 A

Mn-54 pCi 155 155 1.00 A

Fe-59 pCi 118 121 0.98 A

Zn-65 pCi 195 189 1.03 A

Co-60 pCi 190 173.

1.10 A

E6535-396 Charcoal 1-131 pCi 82.8 79.4 1.04 A

June 2009 E6742-396 Milk Sr-89 pCi/L 107 112 0.96 A

Sr-90 pCi/L 19.0 16.7 1.14 A

E6743-396 Milk 1-131 pCi/L 98.1 102.0 0.96 A

Ce-141 pCi/L 260 284 0.92 A

Cr-51 pCi/L 389 400 0.97 A

Cs-134 pCi/L 144.0 166 0.87 A

Cs-137 pCi/L 185 192 0.96 A

Co-58 pCi/L 86.9 91.9 0.95 A

Mn-54 pCi/L 133 137 0.97 A

Fe-59 pCi/L 126 122 1.03 A

Zn-65 pCi/L 173 175 0.99 A

Co-60 pCi/L 298 312 0.96 A

E6745-396 AP Ce-141 pCi 186 163 1.14 A

Cr-51 pCi 262 231 1.13 A

Cs-134 pCi 101 95 1.06 A

Cs-137 pCi 135 111 1.22 W

Co-58 pCi 61 53 1.16 A

Mn-54 pCi 83.1 79 1.05 A

Fe-59 pCi 84 70 1.19 A

Zn-65 pCi 137 101 1.36 N (1)

Co-60 pCi 202 180 1.12 A

E6744-396 Charcoal 1-131 pCi 92.2 95.8 0.96 A

79

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

June 2009 E6745-396 Water Fe-55 pCi 1780 1790 0.99 A

September 2009 E6897-396 Milk Sr-89 pCi/L 113 107 1.06 A

Sr-90 pCi/L 17.4 18.8 0.93 A

E6898-396 Milk 1-131 pCi/L 89.2 98.6 0.90 A

Ce-141 pCi/L 249 275 0.91 A

Cr-51 pCi/L 213 221 0.96 A

Cs-134 pCi/L 104.0 123 0.85 A

Cs-137 pCi/L 172 185 0.93 A

Co-58 pCi/L 96.3 99.4 0.97 A

Mn-54 pCi/L 201 206 0.98 A

Fe-59 pCi/L 154 147 1.05 A

Zn-65 pCi/L 213 204 1.04 A

Co-60 pCi/L 154 160 0.96 A

E6900-396 AP Ce-141 pCi 181 161 1.12 A

Cr-51 pCi 145 130 1.12 A

Cs-134 pCi 71.8 72 0.99 A

Cs-137 pCi 115 109 1.06 A

Co-58 pCi 62 58 1.06 A

Mn-54 pCi 129 121 1.07 A

Fe-59 pCi 97 98 0.98 A

Zn-65 pCi 110 120 0.92 A

Co-60 pCi 98.7 94.1 1.05 A

E6899-396 Charcoal 1-131 pCi 89.5 92.3 0.97 A

E6901-396 Water Fe-55 pCi 1980 1980 1.00 A

December 2009 E6946-396 Milk Sr-89 pCi/L 131 131 1.00 A

Sr-90 pCi/L 19.3 17.9 1.08 A

E6947-396 Milk 1-131 pCi/L 79.2 87.3 0.91 A

Ce-141 pCi/L 193 202 0.96 A

Cr-51 pCi/L 512 548 0.93 A

Cs-134 pCi/L 222 253 0.88 A

Cs-137 pCi/L 163 179 0.91 A

Co-58 pCi/L 200 211 0.95 A

Mn-54 pCi/L 178 178 1.00 A

Fe-59 pCi/L 176 178 0.99 A

Zn-65 pCi/L 326 345 0.94 A

Co-60 pCi/L 240 256 0.94 A

E6949-396 AP Ce-141 pCi 103 103 1.00 A

Cr-51 pCi 290 280 1.04 A

Cs-134 pCi 116 129 0.90 A

Cs-137 pCi 93.4 91.5 1.02 A

Co-58 pCi ill 108 1.03 A

Mn-54 pCi 81.0 90.8 0.89 A

Fe-59 pCi 106 90.8 1.17 A

Zn-65 pCi 155 176 0.88 A

Co-60 pCi 135 131 1.03 A

80

,k ;f 4 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2009 E6948-396 E6950-396 Charcoal 1-131 pCi 93.3 93.9 2500 0.99 0.74 A

W Water Fe-55 pCi 1860 (1) NCR 09-23 was initiated to investigate the failure.

(a) Teledyne Brown Engineering reported result.

(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) Ratio of Teledyne Brown Engineering to A nalytics 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 result falls outside the ratio limits of < 0. 70,and> 1.30.

81

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

March 2009 09-MaW20 Water Am-241 Cs-1 34 Cs-1 37 Co-57 Co-60 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-234/233 U-238 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 09-GrW20 09-MaS20 09-RdF20 09-GrF20 Water Gr-A Gr-B Soil Am-241 Cs-134 Cs-137 Co-57 Co-60 Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90 Tc-99 U-234/233 U-238 Zn-65 AP Am-241 Cs-134 Cs-137 Co-57 Co-60 Mn-54 Pu-238 Pu-239/240 Sr-90 U-234/233 J-238 2n-65 AP Gr-A Gr-B Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample NR 18.8 0.0601 17.0 16.1 69.92 332 13.8 50.7 0.349 0.244 6.88 12.5 2.61 2.71 13.2 0.529 1.87 27.17 433 649

-0.120 3.91 339 241 NR NR 644 245 133 158.7 164.8 272 NR 2.77 1.41 1.24 1.33 2.42 0.0965 0.084 0.713 0.187 0.183 1.30 22.5 18.9 17.21 48.20 330.9 14.7 53.50 1.18 0.853 7.21 14.46 2.77 2.88 13.6 0.635 1.27 38.3 467 605 4.113 307 514.9 570.

257 171 149 155 242 2.93 1.52 1.30 1.22 2.2709 0.1763 0.157 0.64 0.198 0.21 1.36 0.348 0.279 18.5-29.3 (1) 13.2-24.6 12.05 - 22.37 33.7 - 62.7 231.6 - 430.2 10.26 - 19.06 37.45 - 69.55 0.83-1.53 0.597 - 1.109 5.05-9.37 10.12 - 18.80 1.94-3.60 2.02 - 3.74 9.5-17.7

>0.0 - 1.270 0.64-1.91 26.8 - 49.8 327 - 607 424 - 787 (1)

(4) 215 - 399 360.4 - 669.4 399 - 741 180- 334 120-222 104-194 109-202 169-315 2.05 - 3.81 1.06-1.98 0.91 -1.69 0.85-1.59 1.5898 - 2.9522 0.1234 - 0.2292 0.110 - 0.204 0.448 - 0.832 0.139 - 0.257 0.15-0.27 0.95 - 1.77

>0.0 - 0.696 0.140 - 0.419 A

A A

A N (2)

A A

A N (3)

N (3)

A.

A A

W A

A A

N (5)

A A

W A

A A

A N (6)

N (6)

A A

Bq/sample 0.188 Bq/sample 0.313 82

4' DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

March 2009 09-RdV20 Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 3.48 1.15 3.12

-0.0105 2.98 64.1 1.09 1.73 3.40 2.38 - 4.42 0.93 0.65-1.21 2.36 1.65-3.07 (1) 2.3 1.61 - 2.99 (8) 1.260 0.882 - 1.638 1.3540 0.948 - 1.760 A

W N (7)

A W

(1) False positive test.

(2) Fe-55 activity is too close to our detection limit. Fe-55 in water will be done quarterly through Analytics from now on. NCR 09-10 (3) Resin problem caused failure. NCR 09-1,1 (4) Sensativity evaluation.

(5) Abnormally high concentration of native nickle in soil caused high recovery resulting in low activity. NCR 09-09 (6) Resin problem caused failure. NCR 09-12 (7) Homogeniety problem. MAPEP requires using entire sample but due to geometry limitations we can only use part of the sample. NCR 09-13 (8) Not evaluated by MAPEP.

(a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100%! of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) DOEIMAPEP evaluation: A=acceptable, W=-acceptable with warning, N=not acceptable.

83

4.

4%

W TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a)

Value (b)

Control Limits Evaluation (c)

April 2009 RAD 77 Water Sr-89 pCi/L 57.4 48.3 37.8-55.7 N (1)

Sr-90 pCi/L 30.6 31.4 22.9 - 36.4 A

Ba-133 pCi/L 55.2 52.7 43.4-58.3 A

Cs-134 pCi/L 65.8 72.9 59.5-80.2 A

Cs-137 pCi/L 157 168 151 -187 A

Co-60 pCi/L 86.4 88.9 80.0- 100 A

Zn-65 pCi/L 85.5 84.4 76.0- 101 A

Gr-A pCi/L 47.7 54.2 28.3 - 67.7 A

Gr-B pCi/L 45.2 43.5 29.1 - 50.8 A

1-131 pCi/L 25.2 26.1 21.7-30.8 A

U-Nat pCi/L 24.0 25.7 20.6 - 28.8 A

H-3 pCi/L 19733 20300 17800 - 22300 A

October 2009 RAD 79 Water Sr-89 pCi/L 64.75 62.2 50.2 - 70.1 A

Sr-90 pCi/L 30.30 30.7 22.4 - 35.6 A

Ba-133 pCi/L 97.9 92.9 78.3 - 102 A

Cs-134 pCi/L 76.8 79.4 65.0 - 87.3 A

Cs-137 pCi/L 59.9 54.6 49.1 - 62.9 A

Co-60 pCi/L 121 117 105-131 A

Zn-65 pCi/L 115 99.5 89.6-119 A

Gr-A pCi/L 19.6 23.2 11.6-31.1 A

Gr-B pCi/L 28.5 26.0 16.2 - 33.9 A

1-131 pCi/L 22.1 22.2 18.4-26.5 A

H-3 pCi/L 16133 16400 14300 - 18000 A

(1) Calculation did not allow for Y-90 ingrowth on the Sr-89 mount. NCR 09-14 (a) [Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

84

ML101260475

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search