Text

Independent Spent Fuel Storage Installation (ISFSI) - 2011 Annual Radiological Environmental Operating Report
	ML12125A125
Person / Time
Site:	North Anna
Issue date:	04/23/2012
From:	Gerald Bichof; Dominion, Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	12-255
	Download: ML12125A125 (92)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 23, 2012 United States Nuclear Regulatory Commission Ser Attention: Document Control Desk NA Washington, D. C. 20555 Do LicE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 ial No.

PS/JHL 12-255 cket Nos. 50-338/339 72-16 72-56 ense Nos. NPF-4/7 SNM-2507 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 5.5.2c, enclosed is the 2011 Annual Radiological Environmental Operating Report.

The Radiological Environmental Operating Report provides the details associated with the Radiological Environmental Monitoring Program.

If you have any questions or require additional information, please contact D. R. Taylor at (540) 894-2616.

Very truly yours, G. T. Bischof Site Vice President Enclosure Commitments made in this letter: None L13~

Serial No.12-255 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

Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2011 to December 31, 2011 Prepared by Dominion, North Anna Power' Station

Annual Radiological Environmental Operating Report North Anna Power Station, January 1, 2011 to December 31, 2011 Prepared by:

.-Reviewed by:

Approved by:

Leonard E. Oakes Supervisor Radiological Analysis andInstrumentation Dominion North Anna-Power Station oii ge PR-;immons Supervisor:Health Physics Technical Services

-Dominion North Anna-PowerStation

ýRobert B.,vans, Jr.

Manager Radiological Protection and Chemistry Dominion.North Anna-Power-Station 2

Table of Contents

1. EX ECU TIV E SU M M A RY..........................................................................................................

4

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

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

7 2.2 Sam pling and A nalysis Program..............................................................................................

8

3. A N A LY TICA L RESU LTS...........................................................................................

............. 22' 3.1 Summary of Results 22 3.2 A nalytical R esults of 2011 REM P Sam ples.......................................................... I.............. 32

4. D ISCU SSION O F RESU LTS..........................................

..................................... 62 4.1 G am m a Exposure R ate..................................................................................................

. 62 4.2 A irborne G ross Beta......................................

64 4.3 A irborne Radioiodine......................................................................................................

65 4.4 A ir Particulate G am m a...............................................................................

.................... 65 4.5 A ir Particulate Strontium................................................................................................

66 4.6 Soil........................................................................................................................................

66 4.7 Precipitation......................

...... I............................................................................................... 66 4.8 Cow M ilk :.......

...Li............................

.........:.............::............ :67 4.9 Food Products and V egetation......................................................................................

68 4.10 W ell W ater..........................................................................................................................

68 4.11 River W ater..........................................................................................................................

68 4.12 Surface W ater......................................

.............. 69 4.13 Bottom Sedim ent.....................................................................

........................................... 70 4.14 Shoreline Soil......................................................................................................................

71 4.15 Fish......................................................................................................................................

72

5. PRO G RA M EX CEPTION S....................................................................................................

73 REFEREN CES...............................................

I....................................................................................

74 A PPEN D ICES....................................................................................................................................

76 A PPEN D IX A : LA N D U SE CEN SU S......................................................................................

77 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS............... 80 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2011 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, 2011, 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, Fukushima Daiichi 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.

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Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The 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 2011 airborne results were similar to previous years.

Fallout or natural radioactivity levels remained at levels consistent with past years' results.

Water and aquatic exposure pathway samples include precipitation, surface, river and well water, silt and shoreline sediments, and fish. The average tritium activity in surface water for 2011 was 3350 pCi/liter. Nb-95 was reported in one surface water sample at the indicator location. However, the peak was not identified, but forced activity concentration calculation exceeded MDC and the 2 sigma error.

This is considered a false positive. No plant related isotopes were reported in any other surface or river water. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3590 pCi/liter. No plant related isotopeswere detected in quarterly precipitation samples. 1-131 was detected in precipitation samples taken and counted in March and April. These samples are not normally counted for gamma on a monthly basis. Due to the Fukushima Daiichi event, the plant requested that monthly samples be analyzed for gamma emitters in March and April. 1-131 was detected in both samples. The average concentration was 1.83 pCi/L and ranged from 1.10 - 2.55 pCi/L. 1-131 is not normally detected in environmental samples and apparently was not related to operation of North Anna Power Station, but the Fukushima Daiichi incident.

This is discussed in more detail in the appropriate section.

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

No plant related isotope was identified in any sample.

Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels. No plant related isotope was detected in shoreline soil. No plant related isotopes were detected in fish samples from either Lake Anna or the control location, Lake Orange.

Soil samples, which are -collected every three years from twelve stations, were not 5

collected in 2011. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The levels from 2010 also varied significantly by location and date and indicated a decrease from the preoperational levels above. This indicates that the Cs-137 detected in 2010 was most likely due to previous fallout from atomic bomb testing. Naturally occurring nuclides such as Be-7, K-40, Ra-226, Th-228, Th-232 and others were detected in 2010, The terrestrial exposure pathway includes milk and food/vegetation products.

Iodine-131 was detected in one milk sample in April of 2011 at a level of 1.28 pCi/L.

This is most likely a result of the Fukushima Daiichi accident, as previously no 1-131 had been detected in milk prior to or since the 1986 Chernobyl accident.

No plant related radioisotopes were detected in any milk samples.

Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data. No plant related isotopes were detected in any vegetation samples. Low levels of Cs-137 have been detected intermittently in past years. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs).

TLD results have remained essentially constant over the years.

During 2011, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2011 was 0.46 millirem. For reference, this dose may be compared to the 625 millirem average annual exposure to every person in the United States from natural and man-made sources.

Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%.

These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.

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2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2011 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).

The North Anna Power Station of Dominion Virginia Power Company is located on Lake Anna in Mineral,

Virginia, approximately 35 miles southwest of Fredericksburg, Virginia. The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation.

Each unit was designed with a gross electrical output of 979 megawatts electric (MWe).

Unit 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.

The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as is reasonably achievable (ALARA).

To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications, which address the release of radioactive effluents.

In-plant monitoring is used to ensure release limits are not exceeded.

As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).

North Anna Power Station is responsible for collecting the various indicator and control environmental samples.

Global Dosimetry Solutions is responsible for processing the TLDs. Teledyne Brown Engineering Environmental Services (TBE) is responsible for sample analyses.

The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes.

Data collected prior to station operation is used to indicate the degree of natural variation to be expected.

This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.

Occasional samples of environment media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the 7

reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM.

These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2011 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 2011 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 2011.

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TABLE 2-1 North Anna Power Station - 2011 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance.Direction, Degrees Frequency Remarks Environmental Thermoluminescent Dosimetry (TLD)

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 01 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-11/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 0.20 NE 5.30 SSW 7.10 WSW 5.10 WNW 4.20.

NNE 2.04 "N

4.70 ESE 7.30 SSE 1.00 WNW 1.00 WSW 0.93 SSE 22.00 NW 0.06 N

2.04 N

0.24 NNE 3.77 NNE 0.20 NE 1.46 NE 0.36 ENE 2.43 ENE 0.30 E

2.85 E

0.12 ESE 4.70 ESE 0.64 SE 5.88 SE 0.93 SSE 2.33 SSE 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 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 14B was added in October 2011 and Station 14A was deleted.

- - - - The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.

9

TABLE 2-1 North Anna Power Station - 2011 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.

Rourte 613 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)

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

1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA 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 0.36 1.55 0.24 5.30 0.60 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.52 2.54 0.07 2.21 7.30 22.00 7.10 11.54 Direction S

S-SSW-SSW 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 NAPS Sewage Treatment Plant Biology Lab***

Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA 01 O0A.

03 04 05 05A 06 0.20 0.64 7.10 5.10 4.20 2.04 4.70 NE SE WSW WNW NNE N

ESE 420 1380 2430 2870 200 110 1150 Weekly Weekly Weekly Weekly Weekly Weekly Weekly

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

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

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

- - - Station at 14B was added in October 2011 and Station 14A was deleted.

- - - - The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.

10

TABLE 2-1 North Anna Power Station - 2011 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Bumpass, VA 07 7.30 SSE 1670 Weekly Airborne Particulate and Radioiodine End of Route 685 Route 700 "Aspen Hills" Orange, VA 21 22 23 24 08 1.00 WNW 1.00 WSW 0.93 SSE 22.00, NW 3.37 SSE 3010 2420 1580 3250 Weekly Weekly Weekly Weekly Control Surface Water River Water Ground Water (Well Water)

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

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

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

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

Waste Heat Treatment Facility (Second Cooling Lagoon)

NAPS Sewage Treatment Plant Fredericks Hall 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 1480 Monthly 08 3.37 SSE

1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually 5.80 SE 128' Semi-Annually Control 11 Shoreline Soil 08 **

01 02 3.37 SSE 0.20 NE 5.30 SSW 1480.

Semi-Annually 420 Once/3 years 2030 Once/3 years Soil

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 14B was added in October 2011 and Station 14A was deleted.

- - - - The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.

11

TABLE 2-1 North Anna Power Station - 2011 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil 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 Lakeside Dairy Waste Heat Treatment Facility (Second Cooling Lagoon)

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

ESE SSE WNW WSW SSE NW 2430 2870 200 110 115° 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 Control Milk Fish 12A 08 25 14a 14B 15 16 23 26 7.50 NW 3.37 SSE 16.5 NW 3100 Monthly 1480 Semi-Annually 3120 Semi-Annually Control Food Products (Vegetation)

Moody Lane****

Stagecoach Road****

Route 614 Route 629/522 Aspen Hills "Historic Lane" 1.70 1.22 1.37 12.60 0.93 ESE NNE SE NW SSE 1030 400 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 Monthly if available or at harvest Control 1.15 S

172 o 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 01A was added in October 2007.

- - - Station at 14B was added in October 2011 and Station 14A was deleted.

- - - - The dairy at Station 12 sold its dairy herd and ceased milking operations in May 2010.

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

(84 TLDs)

(12 TLDs)

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

Sr-89 Sr-90 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) pCi/mi 3

pCi/m 3

pCi/m3 pCi/n 3 pCi/L pCi/L pCi/L pCi/L River Water Monthly 1-131 1(c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60

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 (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

13

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD' REPORT UNITS River Water Quarterly(a) 2"d Quarter Composite Ground Water (Well Water)

Quarterly Quarterly(a) 2 nd Quarter Semi-Annually La-140 Tritium (H-3)

Sr-89 Sr-90 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(d)

La-14 0 (d) 15 2000 (b)

(b) 15 30 15 15 30 30 15 10(c) 15 i8 60 15 2000 (b)

(b) pCi'L pCi/L pCi/L pCi/L pCi/L Aquatic Sediment 150 180 (b)

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

Annually Precipitation Monthly Sei-mi-Annual Composite (1) 4 15 30 15 15 30 30 15 15 18 pCi/L pCi/L Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180

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 (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

14

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM R AA4PU A4i'D MlA lFl;/F,1FN NV Annually Soil Once per 3 years Milk Monthly Monthly Quarterly ANALYSIS Sr-89 Sr-90 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 LLD (b)

(b) 150 180 (b)

(b) 1 15 18 60 15 (b)

(b)

REPORT UNITS pCi/kg (dry) pCi/kg (dry) pCi/kg (dry) pCi/L

.pCi/L Fish Semi-Annually pCi/kg (wet) 130 260 130 130 260 130 150 Food Products (Broadleaf Vegetation)

Monthly, if available, or at harvest 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:I;or Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

15

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

(a)

IA 2

(a) 3 (a) 4 (a) 5 (a) 5A (a) 6 (a) 7 (a) 8 9A 11 12A (e) 14B (d) 15 16 21 (a) 22 (a) 23 (a) 24 (a)(b 01,NE-5/37 01A,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 12A-Milk 1 4B-Vegetation 15-Vegetation 16-Vegetation 21,WNW-27/59 22,WSW-24/56 23-SSE-15/47 24,C-3/4 25-Fish 26-Vegetation 27 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 27-Milk C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-1 1/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E-10/42 I)

(c) 25 26 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.

(b) In Orange (c) In Lake Orange (d) Station 14B replaced 14A in October 2011 16

WSWE Legend 1913145 OFixed Enwvxunenti MWrOnngSlatofl

RD LOCAboRS Scale - 318 nich = 235 ft.

Figur

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North1 i Anna Site Railoia Moiorn Locations 17

18

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North Anna Environmental Map Fixed Environmental Sampling Location STLD Sampling

Garden Residents Ori&uii 1991 byADC&AtAeymi Inc. 544O Geeaw Gree Way.

Xlw=nkis VA 22312. USED WITH PERMISION. No oliw repkiodclo may be mwade wdhai* to w~iden peimission ofADC.

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 2a 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 - 2011 Docket No. 50-338/339 Page 1 of 9 All Indicator Locations Indicator Location with Highest Mean Control Location 9

I Mean Range Name Distance I Direction Non-routine Reported Measure-ments Mean Range Mean Range I

Direct Radiation (mR/std. Month)

(Sector TLDs)

Direct Radiation (mR/std. Month)

(Pre-operational TLDs)

Direct Radiation (mR/std. Month)

(Emergency Sector TLDs)

Direct Radiation (mR/std. month)

(Environmental TLDs)

Direct Radiation (mR/std. Month)

(Annual TLDs)

Airborne Particulates (1E-03 pCi/m3 )

Gamma 256 Dose 2

4.2(256/256)

(1.5-10.7) 2 2.6(16/16)

(1.6-3.9) 19/51 0.24 mi.

7.1(8/8)

SSW (5.2-10.7) 3.2(16/16)*

(2.3-4.7) 3.2(16/16)*

(2.3-4.7) 0 0

Gamma Dose 32 C-1/2 7.3 mi.

SSE 3.2 (8/8)

(2.2-3.9)

Gamma Dose 40 2

4.8(40/40)

EPSP-0.37 mi.

6.6(8/8)

(1.2-8.9) 09/10 ENE (1.8-8.9) 3.2(16/16)*

(2.3-4.7) 0 Gamma Dose Gamma Dose Gross Beta 48 12 676 2

3.3(44/44)

(1.6-6.0) 2 3.3(11/11)

(2.2-4.7) 0.01 17.4(622/624)

(4.43-42.7) 23 0.93 mi.

4.6(4/4)

SSE (3.4-6.0) 01 0.20 mi.

4.7(1/1)

NE (4.7) 3.3(4/4)

(2.4-4.1) 3.0(1/1)

(3.0) 18.4(52/52)

(5.42-45.1) 0 0

0

.01 0.2 mi.

19.7(50/52)

NE (6.69-42.7)

Air Iodine (pCi/m3) 1-131 676 0.07 89.7(25/624)

(26.8-129) 01 0.2 mi.

129(2/52) 97.9(2/52)

NE (128-129)

(80.8-115) 0 Airborne Particulates (1E-03 pCi/m 3)

Gamma 52 Be-7 52 154(48/48) 05 4.20 mi.

(103-261)

NNE 185(4/4)

(163-220) 143(4/4)

(114-191) 0 Cs-134 52 0.05 (0/48)

N/A N/A N/A (0/4) 0 (1) mR/std month for TLDs

C-3/4, -7/8 used as control locations 23

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 2 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Total (pCiunit)

Mean Name Distance Mean Mean Measure-Type No.

I Range Direction Range Range ments Airborne Particulates (1E-03 pCi/m3)

Cs-137 Sr-89 52 13 0.06 (0/48)

(0/12)

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

(0/1) 0 0

0 Sr-90 13 N/A N/A (0/1)

Soil*

(pCi/Kg) (dry)

Precipitation (pCi/liter)

Triennial Gamma' K-40 Cs-134 Cs-137 Ra-226 Th-228 Th-232 Sr-89 Sr-90 Monthly Gross Beta Semiannual Gamma Be-7 Mn-54 Fe-59 0

0 0

12 2

2 2

2 150 180 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 N/A N/A N/A N/A N/A N/A 4

6.15(8/12)

(1.81-22.1) 01A 0.64 mi.

6.15(8/12)

SE (1.81-22.1) 0 15 30 49.9(1/2)

(49.9)

(0/2)

(0/2) 01A 0.64 mi.

SE N/A N/A N/A N/A N/A N/A 49.9(1/2)

(49.9)

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

0 0

0 Co-58 "

2 15 (0/2)

Soil Samples required triennially.. Last samples were taken 2010. Not required in 2011.

24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 3 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Tot (pCi/unit)

Mean Name Distance Mean Mean Measure-Type al Range Direction Range Range ments No. I I

I Precipitation (pCi/liter)

Co-60 2

Zn-65 2

Zr-95 2

15 (0/2) 30 (0/2) 30 (0/2)

,N/A N/A N/A N/A N/A N/A Nb-95 2

15 (0/2) 1-131 2

(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 0

0 0

0 Cs-134 2

15 (0/2)

Cs-137 Ba-140 La-140 Th-228 Monthly Be-7 2

2 2

2 18 (0/2)

(0/2)

N/A N/A N/A N/A N/A N/A N/A N/A Precipitation*

(pCi/liter)

Mn-54 Fe-59 2

2 15 30 49.9(1/2)

(49.9)

(0/2)

(0/2) 01A 0.64 mi.

SE N/A N/A N/A N/A N/A N/A 49.9(1/2)

(49.9)

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

0 0

0 Co-58 2

15 (0/2)

Monthly samples were analyzed for gamma emitters at the request of the station to determine any effects of the Fukushima event.

25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 4 of 9 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)

Tye No.q Range Direction Range Range ments Co-60 2

15 (0/2)

Precipitation (pCi/liter)

Zn-65 2

30 (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 Zr-95 2

30 (0/2)

Nb-95 2

15 (0/2)

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

0 0

1-131 2

1.83(2/2) 01A 0.64 mi.

1.83(2/2)

(1.10-2.55)

SE (1.10-2.55)

Cs-134 2

15 (0/2)

Cs-137 2

18 (0/2)

Ba-140 2

La-140 2

Th-228 2

(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 0

0 0

Milk (pCi/liter)

Gamma 12 K-40 12 1290(12/12) 12A 7.50 mi.

1290(12/12)

(1100-1450)

NW (1100-1450) 1-131 12,

1 1.28(1/12) 12A 7.50 mi.

1.28(1/12)

(1.28)

Cs-137 12 18 (0/12)

Ba-140 12 60 (0/12)

La-140 12 15 (0/12)

NW N/A N/A N/A N/A (1.28)

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

0 0

N/A N/A 26

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 5 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Total (pCi/unit)

Mean Name Distance Mean Mean Measure-

__Type INo. I Range I

Direction Range Range ments Milk (pCi/liter)

Food Vegetation (pCi/kg) (wet)

Sr-89 (Quarterly)

Sr-90 (Quarterly)

Gamma Be-7 (0/4)

(0/4) 4 30 30 K-40 30 1690(24/24)

(457-3060) 5840(24/24)

(3970-8140)

(0/24)

N/A N/A N/A N/A 26 1.15 S.

15 1.37 SE N/A N/A N/A N/A N/A N/A N/A N/A 1-131 Cs-134 30 30.

60 60 Ground Well Water (pCi/liter)

Cs-137 Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 30 4

4 4

4 80 2000 15 30 15 15 30 30 15 10 (0/24)

(0/4)

(0/4) 8.45(1/4)

(8.45)

(0/4)

N/A N/A 1620(5/6)

(1280-3060) 6660(6/6)

(5150-8140)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 8.45(1/4)

(8.45)

N/A N/A N/A 1610(6/6)

(798-2250) 5060(6/6)

(4200-6910)

(0/6)

(0/6) 0 0

0 0

N/A N/A N/A N/A N/A N/A 01A N/A 27 0

0 N/A N/A N/A N/A N/A N/A 0.64 mi.

SE N/A (0/6)

N/A N/A N/A N/A N/A N/A N/A N/A N/A

Table 3-1 RADIOLOGICAiL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011

[Doc.-et No. 50-338/339 Page 6 of 9 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled Total (pCi/un Mean Name Distance Mean Mean Measure-(Unit)

Type No.

it)

Range Direction Range Range ments Ground Well Water (pCi/liter)

Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Tritium Gamma Mn-54 Fe-59 CO-58 Co-60 Zn-65 4

4 4

41 1

1 4

12 12 12 12 12 12 15 (0/4) 18 (0/4) 60 (0/4) 15 (0/4)

(0/1)

(0/1) 2000 3590(4/4)

(2790-4480)

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 5.80 mi.

SE River Water (pCi/liter) 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 3590(4/4)

(2790-4480)

N/A N/A N/A N/A N/A N/A 10.1(1/12)

(10.1)

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

(0/12)*

0 0

0 Zr-95 i2 30 (0/12)

N/A N/A 0

0 0

0 Nb..95**

1-131 12 12 15 1

10.1(1/12)

(10.1)

(0/12) 11 N/A 5.80 mi.

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

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

N/A N/A

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

- Activity listed is due to forced activity calculation. Nuclide was not identified during analysis. False positive.

28

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 7 of 9 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 IDirection Range Range ments River Water (pCi/liter)

Surface Water (pCi/L)

Ba-140 La-140 Sr-89 Sr-90 Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 12 12 1

1 8

24 24 24 24 24 2000 15 30 15 15 60 15 (0/12)

(0/12)

(1/0)

(1/0) 3350(4/4)

(2270-3930)

(0/12)

N/A N/A N/A 08 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 3.37 mi.

SSE N/A N/A N/A N/A N/A N/A N/A N/A 3350(4/4)

(2270-3930)

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

(0/12)*

(1/0)*

(0/4) 0 0

0 0

0 Zn-65 24 Zr-95 24 Nb-95 24 1-131 24 Cs-134 i24 Cs-137 24 Ba-140 24 30 (0/12) 30 (0/12) 30 (0/12) 1 (0/12) 15 (0/12) 18 (0/12) 60 (0/12)

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

(0/12)

(0/12) 0 0

0 0

La-140 24 15 (0/12)

N/A N/A 29

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 8 of 9 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 INo.

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

Sediment Silt (pCi/kg)

Sr-89 Sr-90 1

(0/1)

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

(0/1)

Gamma 6

K-40 6

16600 (4/4)

(14900-19500)

Cs-134 6

150 (0/4)

Cs-137 6

180 (0/4) 08 3.37 mi.

18200(2/2)

SSE (16900-19500)

N/A N/A N/A 13400(2/2)

(11900-14800)

(0/2)

(176)

(0/2)

N/A N/A.

N/A Ra-226 6

Th-228 6

Th-232 6

2260(3/4)

(2070-2400) 1810(4/4)

(.1090-2980) 1610 (4/4)

(1160-2130)

(0/2) 08 3.37 mi.

2320(1/2)

SSE (2320) 08 3.37 mi.

2460(2/2)

SSE (1940-2980) 08 3.37 mi.

2030(2/2)

SSE (1920-2130) 1560(1/2)

(1560) 730(2/2)

(557-902) 660(2/2)

(587-732)

(0/1) 0 0

0 0

.0 0

0 (Annually)

Sr-89 3

N/A N/A N/A N/A N/A N/A Sr-90 3

(0/2)

Shoreline Soil (pCi/kg) (dry)

Gamma 2

K-40 2

Cs-134 2

150 Cs-137-

-2 180 Ra-226 2

2030(2/2)

(1930-2130)

(0/2)

(0/2) 1780(1/2)

(1780) 08 3.37 mi.

2030(2/2)

SSE (1930-2130)

(0/1)

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

(0/2) 0 0

0 08 3.37 mi.

1780(1/2)

SSE (1780) 30

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2011 Docket No. 50-338/339 Page 9 of 9 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)

Ra-226 2

Th-228 2

Th-232 2

1780(1/2)

(1780) 385(2/2)

(267-502) 433(2/2)

(412-454)

(0/1)

(0/1) 08 3.37 mi.

SSE 08 3.37 mi.

SSE N/A NA N/A NA 1780(1/2)

(1780) 385(2/2)

(267-502) 433(2/2)

(412-454)

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

0 0

(Annually)

Sr-89 Sr-90 Gamma K-40 1

1 8

Fish (pCi/kg) (wet) 2210(4/4)

(1920-2400) 08 3.37 mi.

2210(4/4)

SSE (1920-2400)

Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 130 260 130 130 260 130 150 (0/4)

(0/4)

N/A N/A N/A N/A N/A N/A N/A NA NA NA NA NA NA NA N/A N/A N/A N/A N/A N/A N/A 2730(4/4)

(1680-3630)

(0/4)

(0/4) 0 0

0 0

31

3.2 Analytical Results 0f 2011 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 2a error.

Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data1. For clarity of this report only detectable results are presented. TBE's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the, USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the North Anna ODCM.

Data are given according to sample type as indicated below.

1.

Gamma Exposure Rate

2.

Air Particulates, Gross Beta Radioactivity

3.

Air Particulates, Weekly 1-131

4.

Air Particulates, Quantitative Gamma Spectra

5.

Air Particulate Strontium

6.

Soil

7.

Precipitation

8.

Cow Milk

9.

Food Products and Vegetation

10.

Well Water

11.

River Water

12.

Surface Water

13.

Bottom Sediment/Silt

14.

Shoreline Soil

15.

Fish 1 Analytical results are handled as recommended by HASL ("Reporting ofAnalytical Results from HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).

32

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 1 of 4 First Station Quarter 12/282010 3/29/2011 N-1 N-33 N-2 N-34 NNE-3 NNE-35 NNE-4 NNE 36 NE-5 NE-37 NE-6 NE-38 ENE-7 ENE-39 ENE-8 ENE-40 E-9 E-41 E-1 0 E-42 ESE-1I ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 4.9 4.6 3.0 2.9 6.7 7.1 4.0 4.1 5.7 5.2 3.2 3.7 5.3 5.4 3.3 3.9 4.3 4.7 4.2 4.7 4.1 4.2 4.4 4.8 4.4 4.4 7.3 6.3 5.6 4.5 3.1 2.9 Second Quarter 3/29/2011 6/29/2011 4.0 4.2 2.2 3.7 5.7 5.6 3.1 3.1 4.5 3.9 2.4 2.9 4.0 4.2 2.5 2.1 5.4 4.0 4.3 3.5 3.6 3.4 3.4 3.6 3.4 3.5 5.3 5.1 3.9 3.8 2.1 1.8 Third Quarter 6/29/2011 9/28/2011 3.8 4.1 3.6 2.5 5.5 6.0 3.6 3.5 3.6 4.1 3.2 2.6 4.2 4.2 2.8 2.5 4.3 4.1 3.6 4.5 3.4 3.3 3.5 3.7 3.7 3.5 5.5 5.4 4.0 5.0 2.1 3.1 Fourth Quarter 9/28/2011 12/28/2011 5.9 5.9 4.2 3.8 8.0 7.3 4.7 4.9 4.0 4.2 4.4 4.2 6.3 6.2 4.7 3.4 5.7 5.2 5.2 4.1 5.2 5.0 4.4 5.2 6.0 5.4 7.7 6.8 5.4 5.3 3.7 3.1 Quarterly*

Average

+/- 2 s.d.

4.7

+/-

1.7 3.2

+/-

1.4 6.5

+/-

1.8 3.9

+/-

1.4 4.4

+/-

1.4 3.3

+/-

1.4 5.0

+/-

1.9 3.2

+/-

1.7 4.7

+/-

1.3 4.3

+/-

1.1 4.0

+/-

1.5 4.1

+/-

1.3 4.3

+/-

1.9 6.2

+/-

2.0 4.7

+/-

1.5 2.7

+/-

1.3

Average of collocated TLDs.

33

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

Station 12/282010 3/29/2011 6/29/2011 9/28/2011 Average 3/29/2011

-.6/29/2011 9/28/2011 12/28/2011

+/- 2 s.d.

S-17 6.1 3.6 3.8 6.2 4.9

+/-

2.4 S-49 5.3 4.0 3.9 6.3 S-18 3.1 1.6 1.8 2.4 2.2

+/-

1.1 S-50 2.7 1.6 2.1 2.1 SSW-19 10.4 5.4 5.7 7.4 7.1

+/-

4.5 SSW-51 10.7 5.4 5.2 6.4 SSW-20 3.2 1.9 2.6 2.2 2.3

+/-

1.2 SSW-52 2.4 1.5 1.6 3.0 SW-21 5.7 4.9 5.1 5.3 5.0

+/-

1.1 SW-53 5.2 4.0 4.6 5.4 SW-22 3.8 3.4 3.2 4.5 3.8

+/-

0.9 SW-54 4.2 3.6 3.5 4.3 WSW-23 6.6 4.3 4.2 5.5 5.5

+/-

2.1 WSW-55 6.4 4.6 5.3 6.7 WSW-24 3.9 2.9 3.5 5.2 3.8

+/-

1.6 WSW-56 3.8 3.1 3.4 4.8 W-25 6.9 5.6 7.2 8.1 6.7

+/-

2.0 W-57 7.1 5.7 5.5 7.8 W-26 3.0 2.8 2.5 3.5 3.0

+/-

1.1 W-58 4.0 2.3 2.6 3.2 WNW-27 3.1 2.1 2.5 3.1 2.9

+/-

1.3 WNW-59 3.3 2.3 2.5 4.1 WNW-28 3.0 2.7 2.1 3.0 2.8

+/-

0.8 WNW-60 3.2 2.5 2.4 3.2 NW-29 5.6 5.7 5.9 8.5 6.4

+/-

2.3 NW-61 5.9 5.7 5.7 7.8 NW-30 2.5 1.6 1.6 2.6 2.1

+/-

0.9 NW-62 2.4 1.6 1.8 2.5 NNW-31 3.9 2.7 2.5 4.0 3.2

+/-

1.3 NNW-63 3.8 2.6 2.8 3.2 NNW-32 3.7 2.6 4.0 3.5 3.4

+/-

1.1 NNW-64 3.7 3.1 2.7 4.0 Mean 4.2

+/

1.6

Average of collocated TLDs.

34

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

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

12/282010 3/29/2011 6/29/2011 9/28/2011 Av 3/29/2011 6/29/2011 9/28/2011 12/28/2011

+/-

Page 3 of 4 Statior arterly*

erage 2 s.d.

C-1 C-2 C-3"*

C-4"*

C-5 C-6 C-7"**

C-8"*

3.2 3.9 3.4 3.6 2.3 2.1 3.1 3.4 2.2 2.3 3.5 2.3 1.7 1.6 2.5 3.3 3.6 2.7 2.6 2.7 1.7 2.0 3.0 3.0 3.9 3.9 3.3 3.7 2.7 2.4 3.7 4.7 Mean Indicator Control**

3.2

+/-

1.5 3.1

+/-

1.1 2.1

+/-

0.8 3.3

+/-

1.3 2.6

+/-

3.2

+/-

1.6 1.2 EPSA-01**

EPSA-02***

EPSF-03***

EPSF-04***

EPSR-05***

EPSR-06***

EPSJ-07***

EPSJ-08***

EPSP-09***

EPSP-1 0**

4.9 5.0 4.9 4.8 5.5 5.1 4.9 1.2 1.8 7.7 3.9 3.9 3.8 3.9 3.8 3.9 3.2 3.3 5.9 6.2 4.0 3.9 3.8 4.1 4.5 3.9 3.3 4.5 6.4 7.2 4.9 5.7 5.5 4.5 4.3 5.4 4.1 4.8 8.7 8.9 4.5

+/-

1.4 4.4

+/-

1.2 4.6

+/-

1.4 3.7

+/-

2.4 6.6

+/-

4.5 4.8

+/-

3.1 Mean

Average of collocated TLDs.

- Control Station

- - Emergency Plan TLDs.

35

TABLE 3-2 DIRECT RA-DIATION MEASURMENTS - ENVIRONMENTAL QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 4 of 4 First Quarter Station 12/282010 3/29/201 1 STA-01 5.0 STA-02 STA-03 STA-04 STA-05 STA-05A STA-06 STA-07 STA-21 STA-22 STA-23 STA-24*

2.3 2.9 2.5 3.5 2.8 3.9 3.1 2.9 3.9 6.0 3.2 Second Quarter 3/29/2011 6/29/2011 4.0 1.7 1.6 1.8 2.5 2.5 3.1 2.2 2.3 3.3 3.4 2.4 Third Quarter 6/29/2011 9/28/2011 3.6 2.2 2.2' 2.1 3.2 2.4 3.9 2.6 2.6 4.0 4.6 3.4 Fourth Quarter 9/28/2011 12/28/2011 5.2 2.7 2.8 3.2 4.1 4.0 4.7 4.3 4.0 4.3 4.5 4.1 2.2 2.4 2.4 3.3 2.9 3.9 3.1 0.8 1.2 1.2 1.3 1.5 1.3 1.8 1.5 0.8 2.1 0.7 1.0 2.4 2.2 2.7 3.0 2.6 4.2 3.7 2.5 3.9 4.0 3.0 3.3

+/-

Quarterly Average

+/- 2 s.d.

4.5

+/-

1.5 AnnualTLD 4.7 3.0

+/-

3.9

+/-

4.6

+/-

3.3

+/-

3.3

+/-

Mean - Indicator Locations 1.7

Control 36

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m3]

page 1 of 4 Period Endina Station 01 I

Station 02 Station 03 Station 04 Station 05 Station 06 I

Station 07 I

01/04/11 Oi/:1ilt, 01/18/11 01/25/11 02/01/11 02/08/11 02/15/11 02/23/11 03/01/11 03/08/11 03/15/12 03/22/11 03/29/11 04/06/11 04/13/11 04/20/11 04/27/11 05/03/11 05/11/11 05/18/11 05/24/11 06/01/11 06/08/11 06/14/11 06/21/11 2.53E+01

+/

3.47E+00 1.09L+01

+!

3.24E+00 2.07E+01

+/

3.33E+00 1.86E+01

+/

3.36E+00 2.26E+01

+/

3.33E+00 1.62E+01

+-

3.09E+00 1.55E+01

+-

2.84E+00 1.20E+01

+/-

2.61 E+00 6.69E+00

+/-

2.87E+00 2.84E+00 1.24E+01

+/

2.54E+00 1.09E+01

+-

2.50E+00 3.52E+01

+/

3.41 E+00 3.54E+01

+-

3.70E+00 1.92E+01

+/

3.05E+00 2.12E+01

+/-

2.98E+00 1.30E+01

+-

3.02E+00 1.50E+01

+/-

3.38E+00 1.49E+01

+/-

2.64E+00 1.11E+01

+/-

2.53E+00 1.70E+01

+/o 3.18E+00 2.85E+01

+/-

3.30E+00 2.89E+01

+/-

2.73E+00 2.66E+01

+/-

3.66E+00 2.16E+01

+/-

3.38E+00 2.07E+01 1.94E+01 2.15E+01 1.71E+01 2.24E+01 1.44E+01 9.40E+00 1.11E+01 1.32E+01 1.03E+01 1.18E+01 1.23E+01 3.74E+01 2.19E+01 1.33E+01 1.58E+01 9.48E+00 1.09E+01 1.22E+01 8.40E+00 1.26E+01 1.24E+01 1.84E+01 1.54E+01 1.17E+01

+/

3.29E+00

+/-

3.23E+/-00

+/

3.33E+00

+/

3.33E+00

+/

3.32E+00

+-

3.01 E+00

+/

2.49E+00

+-

2.58E+00

+/

3.23E+00

+/

2.46E+00

+/

2.50E+00

+/

2.55E+00

+-

3.52E+00

+/

3.12E+00

+/

2.74E+00

+-

2.67E+00

+-

2.89E+00

+/

3.17E+00

+1 2.50E+00

+/

2.37E+00

+-

2.93E+00

+-

2.59E+00

+-

2.42E+00

+-

3.16E+00

+-

2.86E+00 2.53E+01

+/-

3.50E+00 2.13E+01

+/-

3.32E+00 1.43E+01

+/-

3.04E+00 1.84E+01

+/-

3.33E+00 1.93E+01

+/-

3.19E+00 1.38E+01

+/-

2.98E+00 1.52E+01

+/-

2.82E+00 8.90E+00

+/-

2.46E+00 1.15E+01

+/-

3.20E+00 1.08E+01

+/-

2.46E+00 9.80E+00

+/-

2.36E+00 6.33E+00

+/-

2.23E+00 1.42E+01

+/-

2.31 E+00 9.67E+00

+/-

2.60E+00 1.39E+01

+/-

2.76E+00 1.64E+01

+/-

2.80E+00 1.08E+01

+/-*

2.89E+00 1.52E+01

+/° 3.41 E+00 1.53E+01

+/

2.65E+00 1.03E+01

+/

2.48E+00 1.42E+01

+-

3.04E+00 2.63E+01

+/

3.21E+00 1.81E+01

+-

2.41E+00 2.11E+01

+-

3.52E+00 1.71E+01

+/

3.07E+00 2.42E+01.

2.53E+01 1.81 E+01 2.29E+01 2.33E+01 1.71 E+01 1.01E+01 1.31E+01 1.46E+01 1.31E+01 1.32E+01 1.62E+01 4.27E+01 2.62E+01 1.28E+01 1.84E+01 1.04E+01 1.15E+01

.1.42E+01 9.15E+00 1.22E+01 1.98E+01 2.OOE+01 2.21E+01 1.48E+01

+/-

3.47E+00

+/-

3.50E+00

+/-

3.23E+00

+/-

3.55E+00

+/-

3.37E+00

+/-

3.13E+00

+/-

2.54E+00

+/-

2.68E+00

+/-

3.34E+00

+/-

2.63E+00

+/-

2.58E+00

+/-

2.80E+00

+/-

3.71 E+00

+/-

3.30E+00

+/-

2.71 E+00

+/-

2.83E+00

+/-

2.91 E+00

+/-

3.19E+00

+/-

2.60E+00

+/-

2.42E+00

+/-

2.91 E+00

+/-

2.94E+00

+/-

2.47E+00

+/-

3.54E+00

+/-

2.99E+00 3.06E+01

+/-

3.70E+00 2.43E+01

+/-

3.45E+00 2.20E+01

+/

3.35E+00 2.43E+01

+/-

3.67E+00 2.09E+01

+-

3.26E+00 2.OOE+01

+/-

3.27E+00 1.58E+01

+/-

2.85E+00 1.35E+01

+-

2.70E+00 1.76E+01

+-

3.46E+00 1.10E+01

+-

2.50E+00 1.58E+01

+-

2.72E+00 1.68E+01

+/

2.83E+00 3.75E+01

+/

3.50E+00 2.89E+01

+/-

3.40E+00 1.85E+01

+/-

3.01 E+00 1.97E+01

+/-

2.88E+00 1.47E+01

+/-

3.14E+00 1.62E+01

+/-

3.44E+00 1.57E+01

+/-

2.67E+00 6.70E+00

+/-

2.27E+00 1.58E+01

+/-

3.11E+00 2.24E+01

+/-

3.05E+00 2.29E+01

+/-

2.56E+00 2.48E+01

+/-

3.64E+00 1.88E+01

+/-

3.20E+00 2.25E+01 2.45E+01 1.73E+01 1.85E+01 2.16E+01 1.47E+01 1.42E+01 1.32E+01 1.31E+01 1.34E+01 1.18E+01 1.29E+01 3.57E+01 2.31E+01 1.82E+01 1.42E+01 8.55E+00 1.25E+01 1.38E+01 6.02E+00 1.21E+01 1.83E+01 1.52E+01 1.83E+01 1.28E+01

+/-

3.36E+00

-/l 3.46E+00"

+/-

3.14E+00

+/-

3.43E+00

+/-

3.29E+00

+/-

3.02E+00

+/-

2.76E+00

+/-

2.68E+00

+/-

3.22E+00

+/-

2.64E+00

+/-

2.50E+00

+/-

2.62E+00

+/-

3.42E+00

+/-

3.17E+00

+/-

2.66E+00

+/-

2.59E+00

+/-

2.83E+00

+/-

3.25E+00

+/-

2.58E+00

+/-

2.22E+00

+/-

2.90E+00

+/-

2.87E+00

+/-

2.33E+00

+/-

3.31 E+00

+/-

2.91 E+00 2A.E+01 "2.e66+01 1.60E+01 2.08E+01 2.05E+01 1.46E+01 1.11E+01 1.20E+01 1.72E+01 1.26E+01 1.30E+01 1.55E+01 4.10E+01 2.27E+01 1.55E+01 1.72E+01 1.29E+01 1.02E+01 1.40E+01 1.OOE+01 1.51 E+01 2.09E+01 1.70E+01 2.21E+01 1.83E+01

.+/-

3.45E+00

'+/-.

3.55E+0O

+/-

3.08E+00

+/-

3.49E+00

+/-

3.24E+00

+/-

3.02E+00

+/-

2.59E+00

+/-

2.62E+00

+/-

3.44E+00

+/-

2.59E+00

+/-

2.57E+00

+/-

2.76E+00

+/-

3.64E+00

+/-

3.15E+00

+/° 2.86E+00

+/-

2.76E+00

+/-

3.05E+00

+/-

3.12E+00

+/-

2.59E+00

+/-

2.47E+00

+/-

3.07E+00

+/-

2.99E+00

+/-

2.38E+00

+/-

3.51 E+00

+/-

3.18E+00 06/29/11 1.70E+01

+/-

2.67E+00 9.34E+00

+/-

2.26E+00 9.93E+00

+/-

2.30E+00 8.74E+00-

+/-

2.23E+00 1.59E+01

+/-

2.61E+00 1.13E+01

+/-

2.37E+00 9.59E+00

+/-

2.27E+00 37

Table 3-3 Air Particulate page Gross Beta Radioactivity 2 of 4

[10"1 pCi/m3]

Period

Station Station Station Station Station Station Ending I21 22 I23 I24*.

01OA I05A 01/04/11 2.04E+01

+/-

3.27E+00 2.33E+01

+/-

3.39E+00 2.26E+01

+/-

3.36E+00 2.26E+01

+/-

3.38E+00 2.55E+01

+/-

3.48E+00 2.44E+01

+/-

3.45E+00 01/11/11 1.92E+01

+/-

3.22E+00 2.57E+01

+/-

3.51E+00 2.62E+01

+/-

3.53E+00 2.78E+01

+/-

3.60E+00 2.42E+01

+/-

3.44E+00 2.16E+01

+/-

.3.33E+00 01/18/11 1.68E+01

+/-

3.14E+00 1.59E+6.1

+I-3.11E+00 1.90E+01

+/-

3.19E+00 2.56E+01

+/-

3.55E+00-

'1.43&E-01

+/-

3.03E+00 2.17E+01 4-/-

3.34E+00 01/25/11 1.94E+01

+/-

3.39E÷00 1.82E+01

+/-

3.34E+00 1.82E+01

+/-

3.40E+00 2.41E+01

+/-

3.58E+00 2.25E+01

+/-

3.53E+00 2.22E+01

+1-3.58E+00 02/01/11 1.76E+01

+/-

3.13E+00 2.23E+01

+/-

3.32E+00 2.53E+01

+/-

3.48E+00 2.47E+01

+/-

3.42E+00 1.65E+01

+/-

3.05E+00 2.01E+01

+1-3.22E+00 02/08/11 1.43E+01

+/-

3.OOE+00 1.56E+01

+I-3.06E+00 1.35E+01

+/-

2.96E+00 1.99E+01

+/-

3.262+00 1.51E+01

+/-

3.04E+00 1.77E+01

+1-3.17E+00 02/15/11 1.26E+01

+/-

2.68E+00 1.30E+01

÷/-

2.70E+00 1.39E+01

+/-

2.75E+00 1.87E+01

+/-

2.99E+00 1.39E+01

+I-2.75E+00 1.75E+01

+/-

2.94E+00 02/23/11 1.13E+01

+/-

2.58E+00 1.33E+01

+/-

2.68E+00 1.21 E+01

+/-

2.63E+00 1.53E+01

+/-

2.78E+00 1.61E+01

+/-

2.81 E+00 1.22E+01

+1-2.63E+00 03/01/11 1.52E+01

+/-

3.34E+00 1.64E+01

+/-

3.40E+00 1.36E+01

+/-

3.26E+00 2.10E+01

+/-

3.63E+00 1.75E+01

+/-

3.46E+00 1.59E+01

+/-

3.37E+00 03/08/11 1.24E+01

+/-

2.582+00 1.29E+01

+/-

2.61E+00 1.11E+01

+/-

2.50E+00 1.45E+01

+/-

2.70E+00 1.29E+01

+/-

2.61 E+00 1.12E+01

+/-

2.51E+00 03/15/12 1.42E+01

+/-

2.66E+00 1.32E+01

+/-

2.58E+00 1.32E+01

+/-

2.58E+00 1.59E+01

+/-

2.73E+00 1.56E+01

+/-

2.72E+00 1.32E+01

+/-

2.58E+00 03/22/11 1.33E+01

+/-

2.64E+00 1.24E+01

+/-

2.59E+00 1.25E+01

+/-

2.59E+00 2.50E+01

+/-

3.24E+00 1.21E+01

+/-

2.57E+00 1.50E+01

+/-

2.73E+00 03/29/11 3.62E+01

+/-

3.44E+00 3.622+01

+/-

3.44E+00 4.01E+01

+/-

3.60E+00 4.51E+01

+/-

3.80E+00 3.83E+01

+/-

3.54E+00 3.672+01

+/-

3.46E+00 04/06/11 2.12E+01

+/-

3.09E+00 2.54E+01

+/-

3.26E+00 2.582+01

+/-

3.32E+00 3.14E+01

+/-

3.50E+00 2.60E+01

+/-

3.28E+00 2.52E+01

+/-

3.26E+00 04/13/11 1.46E+01

+/-

2.81 E+00 1.29E+01

+/-

2.732+00 1.30E+01

+/-

2.73E+00 1.56E+01

+/-

2.86E+00 1.44E+01

+/-

2.80E+00 1.30E+01

+/-

2.73E+00 04/20/11 1.48E+01

+/-

2.65E+00 1.85E+01

+/-

2.85E+00 1.762+01

+/-

2.83E+00 2.27E+01

+/-

3.06E+00 1.81E+01

+/-

2.83E+00 9.76E+00

+/-

2.33E+00 04/27/11 1.28E+01

+/-

3.02E+00 1.122+01

+/-

2.94E+00 9.61E+00

+/-

2.85E+00 1.31E+01

+/-

3.01E+00 1.32E+01

+/,

3.10E+00 1.48E+01

+/-

3.14E+00 05/03/11 8.32E+00 2 +/-

3.02E+00 1.33E+01

+/-

3.30E+00 1.472+01

+/-

3.37E+00 1.46E+01

. +/-

3.38E+00 9.53E+00

+/-

3.09E+00 1.36E+01

+/-

3.30E+00 05/11/11 1.34E+01

+/-

2.57E+00 1.17E+01

+/-

2.48E+00 1.23E+01

+/-

2.51E+00 1.51E+01

+/-

2.65E+00 1.32E+01

+/-

2.56E+00 1.27E+01

+/-

2.53E+00 05/18/11 5.13E+00

+/-

2.16E+00 7.80E+00

+/-

2.34E+00 1.04E+01

+/-

2.50E+00 8.32E+00

+/-

2.37E+00 6.16E+00

+/-

2.23E+00 6.55E+00

+/-

2.26E+00 05/24/11 1.19E+01

+/-

2.89E+00 1.15E+01

+/-

2.86E+00 1.46E+01

+/-

3.04E+00 1.34E+01

+/-

2.99E+00 1.21E+01

+/-

2.90E+00 1.19E+01

+/-

2.89E+00 06/01/11 1.87E+01

+/-

2.89E+00 1.93E+01

+/-

2.92E+00 2.25E+01

+/-

3.06E+00 1.92E+01

+/-

2.91E+00 2.11E+01

+/-

3.00E+00 2.23E+01

+/-

3.05E+00 06/08/11 1.66E+01

+/-

2.37E+00 1.58E+01

+/-

2.35E+00 1.84E+01

+/-

2.43E+00 1.50E+01

+/-

2.32E+00 2.10E+01

+/-

2.512E+00 1.82E+01

+/-

2.42E+00 06/14/11 1.75E+01

+/-

3.24E+00 1.85E+01

+/-

3.28E+00 2.092+01

+/-

3.42E+00 1.86E+01

+/-

3.38E+00 2.21E+01

+/-

3.45E+00 2.24E+01

+/-

3.52E+00 06121/11 1.36E+01

+/-

2.98E+00 1.722+01

+/-

3.16E+00 1.68E+01

+/-

3.13E+00 1.16E+01

+/-

2.81E+00 1.85E+01

+/-

3.23E+00 1.512E+01

+/-

3.02E+00 06/29/11 9.34E+00

+/-

2.26E+00 1.39E+01

+/-

2.51E+00 1.102+01

+/-

2.35E+00 1.25E+01

+/-

2.44E+00 1.17E+01

+/-

2.40E+00 1.24E+01

+/-

2.43E+00

Control Station 38

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3]

page 3 of 4 Period Ending 07/05/11 07/12/11 07/19/11 07/26/11 08/02/11 08/09/11 08/16/11 08/23/11 08/30/11 09/06/11 09/14/11 09/21/11 09/28/11 10/04/11 10/11/11 10/18/11 10/25/11 11/01/11 11/08/11 11/15/11 11/22/11 11/29/11 12/06/11 12/13/11 12/20/11 12/28/11 Station 01 I

Station 02 Station I

03 Station 04 I

Station 05 I

Station 06 Station S07 04 I

05 I

06 07 2.14E+01 2.23E+01 2.08E+01 3.50E+01 3.19E+01 2.93E+01 2.78E+01 2.54E+01 1.94E+01 2.85E+01 2.47E+01 1.64E+01 8.80E+00 1.17E+01 3.48E+01 1.80E+01 1.23E+01 1.48E+01 1.62E+01 1.30E+01 1.01E+01 1.OOE+01 1.58E+01 1.35E+01 2.70E+01 1.28E+01

+/

3.57E+00

+-

3.15E+00

+/

3.01 E+00

+/

3.74E+00

+-

3.55E+00

+-

3.81 E+00

+-

3.51 E+00

+-

3.32E+00

+-

3.34E+00

+-

3.71 E+00

+-

3.05E+00

+-

2.86E+00

+-

2.37E+00

+-

3.17E+00

+-

3.57E+00

+-

2.81 E+00

+-

3.01 E+00

+-

2.87E+00

+/-

2.71 E+00

+/-

2.89E+00

+/-

2.72E+00

+/-

2.62E+00

+/-

2.87E+00

+/-

2.83E+00

+/-

3.39E+00

+/-

2.39E+00 1.37E+01 1:53E+01.

1:28E+01 2.15E+01 2.04E+01 1.76E+01 1.89E+01 1.05E+01 1.18E+01 1.58E+01 1.29E+01 9.71 E+00 4.85E+00 9.48E+00 2.30E+01 2.23E+01 1.86E+01 2.OOE+01 2.13E+01 2.67E+01 1.39E+01 1.43E+01 1.49E+01 1.36E+01 3.26E+01 1.44E+01

+/-

3.19E+00

+/-

2.80E+00

+/-

2.59E+00

+/-

3.16E+00

+/-

3.03E+00

+/-

3.36E+00

+/-

3.12E+00

+/-

2.57E+00

+/-

2.90E+00

+/-

3.71 E+00

+/-

2.48E+00

+I-2.49E+00

+/-

2.10E+00

+/-

3.07E+00

+/-

3.03E+00

+/-

3.04E+00

+/-

3.30E+00

+/-

3.13E+00

+/-

2.97E+00

+/-

3.53E+00

+/-

2.92E+00

+/-

2.85E+00

+/-

2.83E+00

+/

2.83E+00

+/

3.63E+00

+/

2.47E+00 1.65E+01

+/-

3.35E+00.

1.12E+01 1.95E+01

+/-

3.OOE+00 1.86E+01 1.81E+01

+/-

2.87E+00-1.45E+01 2.62E+01

+/-

3.37E+00 2.78E+01

+/-

3.43E+00 2.25E+01

+/-

3.48E+00 2.04E+01

+/-

3.19E+00 1.68E+01

+/-

2.91E+00 1.24E+01

+/-

2.94E+00 2.01E+01

+/-

3.38E+00 1.96E+01

+/-

2.80E+00 1.31 E+01

+/-

2.69E+00 7.55E+00

+/-

2.28E+00 1.38E+01

+/-

3.32E+00 2.72E+01

+/-

3.21 E+00 2.03E+01

+/-

2.96E+00 1.68E+01

+/-

3.22E+00 1.63E+01

+/-

2.95E+00 1.71 E+01

+/-

2.75E+00 1.97E+01

+/-

3.22E+00 1.20E+01

+/-

2.82E+00 1.08E+01

+/-

2.67E+00 1.22E+01

+/-

2.69E+00 1.61 E+01

+/-

2.96E+00 3.24E+01

+/-

3.62E+00 1.30E+01

+/-

2.38E+00 2.20E+01 2.36E+01 1.85E+01 2.07E+01 1.93E+01 1.50E+01 2.29E+01 1.70E+01 1.66E+01 7.64E+00 1.03E+01 2.91E+01 2.10E+01 1.59E+01 2.06E+01 1.78E+01 2.15E+01 1.26E+01 1.25E+01 1.48E+01 1.58E+01 3.36E+01 1.50E+01

+/-

3.05E+00

+/-

2.96E+00

+/-

2.53E+00

+/-

3.18E+00

+/-

3.21 E+00

+/-

3.34E+00

+/-

3.22E+00

+/-

3.04E+00

+/-

3.13E+00

+/-

3.48E+00

+/-

2.69E+00

+/-

2.87E+00

+/-

2.29E+00

+/-

3.11E+00

+/-

3.29E+00

+/-

3.00E+00

+/-

3.18E+00

+/-

3.16E+00

+/

2.79E+00

+/

3.31 E+00

+-

2.85E+00

+-

2.76E+00

+-

2.82E+00

+-

2.94E+00

+/-

3.67E+00

+/-

2.48E+00 1.61E+01

+/

3.20E+00 2.25E+01

+/

3.15E+00 1.33E+01

+/

2.62E+00 2.25E+01

+/

3.20E+00 3.20E+01

+/

3.56E+00 2.15E+01

+/

3.48E+00 2.32E+01

+/

3.32E+00 2.37E+01

+/

3.24E+00 1.46E+01

+/

3.06E+00 2.47E+01

+/

3.56E+00 1.54E+01

+/

2.61 E+00 1.58E+01

+/

2.83E+00 8.01 E+00

+-

2.31 E+00 4.43E+00

+-

2.77E+00 2.34E+01

+/

3.04E+00 2.20E+01

+-

3.04E+00 1.94E+01

+/

3.34E+00 2.08E+01

+/

3.17E+00 2.17E+01

+/

2.99E+00 2.85E+01

+/-

3.61 E+00 1.52E+01

+-

2.98E+00 1.45E+01

+I-2.87E+00 1.73E+01

+/-

2.95E+00 1.93E+01

+/-

3.12E+00 3.76E+01

+/-

3.82E+00 1.66E+01

+/-

2.59E+00 1.02E+01, 1.67E+01 1.39E+01:

2.70E+01 2.26E+01 2.12E+01 1.79E+01 2.05E+01 1.58E+01 2.02E+01 1.69E+01 1.56E+01 5.80E+00 1.02E+01 2.34E+01 2.73E+01 1.67E+01 1.83E+01 1.91E+01 2.33E+01 1.27E+01 1.53E+01 1.52E+01 1.52E+01 3.14E+01 1.56E+01

+/-

2.99E+00

+/-

2.87E+00

+b, 2.65&+00

+/-

3.41E+00

+/-

3.14E+00

+/-

3.48E+00

+/-

3.07E+00

+/-

3.09E+00

+/-

3.12E+00

+/-

3.38E+00

+/-

2.68E+00

+/-

2.82E+00

+/-

2.16E+00

+/-

3.10E+00

+/-

3.04E+00

+/-

3.30E+00

+/-

3.21 E+00

+/-

3.05E+00

+/-

2.86E+00

+/-

3.39E+00

+/-

2.86E+00

+/-

2.90E+00

+/-

2.85E+00

+/-

2.92E+00

+/-

3.57E+00

+/-

2.53E+00 1.43E+01 1.95E+01 1.31E+01 2.30E+01 2.67E+01 2.23E+01 1.89E+01 2.02E+01 1.45E+01 1.73E+01 1.71 E+01 1.23E+01 6.62E+00 1.14E+01 2.54E+01 2.34E+01 1.35E+01 2.01 E+01 1.62E+01 1.90E+01 1.25E+01 1.35E+01 1.26E+01 1.32E+01 2.88E+01 1.32E+01

+/-

3.25E+00

+/-

3.01 E+00

+/

2.60E+00

+/-

3.22E+00

+/

3.33E+00

+/

3.57E+00

+/

3.12E+00

+/

3.08E+00

+/

3.04E+00

+/

3.24E+00

+/

2.70E+00

+-

2.64E+00

+/-

2.22E+00

+/-

3.17E+00

+/-

3.13E+00

+/-

3.11E+00

+/-

3.06E+00

+/-

3.14E+00

+/-

2.71 E+00

+/-

3.20E+00

+/

2.85E+00

+-

2.81E+00

+/

2.71 E+00

+/

2.81 E+00

+/

3.47E+00

+/

2.41E+00 MEAN 1.98E+01

+/-

3.10E+00 1.58E+01

+/-

2.92E+00 1.65E+01

+/-

2.94E+00 1.77E+01

+/-

3.00E+00 1.97E+01

+/-

3.09E+00 1.70E+01

+/-

2.96E+00 1.73E+01

+/-

2.98E+00 39

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

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Endin I 21 I

22 I

I 24*

I AI 07/05/11 1.40E+01

+/-

3.20E+00 1.54E+01

+/-

3.28E+00 1.38E+01

+/-

3.19E+00 1.24E+01

+/-

3.12E+00 1.42E+01

+/-

3.21E+00 1.52E+01

+/-

3.27E+00 07/12/11 1.87E+01

+/-

2.98E+00 2.06E+01

+/-

3.07E+00 1.72E+01

+/-

2.90E+00 1.32E+01

+/-

2.68E+00 2.00E+01

+/-

3.04E+00 1.79E+01

+/-

2.93E+00.

07/19/11 1.56E+01

+/-

2.74E+00 1.51E+01

+/-

2.71E+00 1.81E+01

+/-

2.87E+00 1.65E+01

+/-

2.82E+00 1.59E+01

+/-

2.75E+00 1.44E+01

+/-

2.68E+00 07/26/', 1 2.23E+01.

+/-

3.20E+00 2.56E+01

+/-

3.35E+00 2.80E+01

"+1-3.45E+00

.2.77E+01

"/-

3,43E+00" 2.64E+01

+/-

,3.53E+00 -

2.05E+01

+/-

3.11E+00.

08/02/11 2.31E+01

+/-

3.16E+00 2.71E+01

+I-3.34E+00

. 2.27E+01

+/-

3.15E+00 2.26E+01

+1-3.14E+00 2.18E+01

+/-

3.10E+00 2.82E+01

+/-

3.40E+00 08/09/11 1.45E+01

+/-

3.19E+00 1.77E+01

+/-

3.33E+00 2.03E+01

+/-

3.44E+00 1.99E+01

+/-

3.42E+00 1.98E+01

+/-

3.43E+00 1.76E+01

+/° 3.38E+00 08/16/11 1.60E+01

+I-2.96E+00 1.59E+01

+/-

2.96E+00 1.75E+01

+/-

3.04E+00 1.94E+01

+/-

3.14E+00 2.06E+01

+/-

3.19E+00 1.07E+01

+/-

2.70E+00 08/23/11 1.33E+01

+/-

2.73E+00 1.96E+01

+/-

3.06E+00 1.98E+01

+/-

3.06E+00 1.44E+01

+/-

2.79E+00 2.08E+01

+/-

3.11 E+00 2.07E+01

+/-

3.11E+00 08/30/11 1.11 E+01

+I-2.87E+00 1.04E+01

+I-2.83E+00 1.49E+01

+/-

3.05E+00 1.39E+01

+/-

3.01 E+00 1.03E+01

+/-

2.82E+00 1.62E+01

+/-

3.13E+00 09/06/11 1.69E+01

+/-

3.22E+00 1.90E+01

+/-

3.31 E+00 1.89E+01

+1-3.31 E+00 1.95E+01

+/-

3.32E+00 1.99E+01

+/-

3.35E+00 1.87E+01

+/-

3.30E+00 09/14/11 1.19E+01

+/-

2.43E+00 1.92E+01

+/-

2.80E+00 1.46E+01

+/-

2.57E+00 1.52E+01

+/-

2.61E+00 1.29E+01

+/-

2.49E+00 1.60E+01

+/-

2.64E+00 09/21/11 1.45E+01

+/-

2.76E+00 1.22E+01

+/-

2.63E+00 1.25E+01

+/-

2.65E+00 1.28E+01

+/-

2.67E+00 1.39E+01

+/-

2.72E+00 1.62E+01

+/-

2.85E+00 09/28/11 7.21E+00

+/-

2.26E+00 7.29E+00

+/-

2.27E+00 6.47E+00

+/-

2.21E+00 6.00E+00

+/-

2.17E+00 5.69E+00

+/-

2.17E+00 7.64E+00

+/-

2.29E+00 10/04/11 5.73E+00

+/-

2.84E+00 6.51E+00

+/-

2.89E+00 7.72E+00

+/-

2.96E+00 5.42E+00

+/-

2.84E+00 7.86E+00

+/-

2.96E+00 8.00E+00

+/-

2.98E+00 10/11/11 2.41E+01

+/-

3.09E+00 2.82E+01

+/-

3.28E+00 2.34E+01

+/-

3.06E+00 2.55E+01

+/-

3.13E+00 2.86E+01

+/-

3.30E+00 2.30E+01

+/-

3.01E+00 10/18/11 2.27E+01

+/-

3.05E+00 2.59E+01

+/-

3.21E+00 2.49E+01

+/-

3.17E+00 2.14E+01

+/-

3.02E+00 2.53E+01

+/-

3.18E+00 2.54E+01

+/-

3.21E+00 10/25/11 1.55E+01

+/-

3.15E+00 1.50E+01

+/-

3.13E+00 1.65E+01

+/-

3.20E+00 1.35E+01

+/-

3.07E+00 1.47E+01

+/-

3.12E+00 1.50E+01

+/-

3.13E+00 11/01/11 1.61E+01

+/-

2.94E+00 2.08E+01

+/-

3.178+00 2.12E+01

+/-

3.19E+00 1.90E+01

+/-

3.08E+00 1.82E+01

+/-

3.05E+00 1.85E+01

+/-

3.06E+00 11/08/11 7.45E+00

+/-

2.18E+00 1.87E+01

+/-

2.85E+00 1.758+01

+/-

2.78E+00 1.90E+01

+/-

2.85E+00 2.04E+01

+/-

2.93E+00 1.82E+01

+/-

2.81E+00 11/15/11 1.83E+01

+/-

3.158+00 2.54E+01

+/-

3.47E+00 2.31E+01

+/-

3.37E+00 2.80E+01

+/-

3.59E+00 2.24E+01

+/-

3.34E+00 2.20E+01

+/-

3.33E+02 11/22/11 1.04E+01

+/-

2.74E+00 1.21E+01

+1-2.83E+00 1.03E+01

+/-

2.73E+00 1.05E+01

+/-

2.74E+00 7.75E+00

+/-

2.59E+00 1.05E+01

+/-

2.74E+00 11/29/11 1.23E+01

+/-

2.75E+00 1.13E+01

+1-2.70E+00 1.43E+01

+/-

2.85E+00 1.32E+01

+/-

2.80E+00 1.38E+01

+/-

2.83E+00 1.49E+01

+/-

2.88E+00 12/06/11 1.38E+01

+/-

2.77E+00 1.08E+01

+/-

2.60E+00 1.42E+01

+/-

2.79E+00 1.57E+01

+/-

2.87E+00 1.43E+01

+/-

2.79E+00 1.43E+01

+/-

2.80E+00 12/13/11 1.54E+01

+/-

2.93E+00 1.31E+01

+/-

2.81E+00 1.13E+01

+/-

2.71E+00 1.41E+01

+/-

2.86E+00 1.33E+01

+/-

2.82E+00 1.58E+01

+/-

2.95E+00 12/20/11 2.58E+01

+/-

3.34E+00 3.49E+01

+/-

3.72E+00 2.80E+01

+/-

3.43E+00 3.03E+01

+/-

3.53E+00 3.21E+01

+/-

3.61 E+00 3.20E+01

+/-

3.60E+00 12/28/11 1.31E+01

+/-

2.40E+00 1.41E+01

+/-

2.45E+00 1.54E+01

+/-

2.52E+00 1.40E+01

+/-

2.44E+00 1.29E+01

+/-

2.39E+00 1.41E+01

+/-

2.46E+00 MEAN 1.54E+01

+/-

2.89E+00 1.73E+01

+/-

2.98E+00 1.73E+01

+/-

2.98E+00 1.84E+01

+/-

3.03E+00 1.74E+01

+/-

2.99E+00 1.73E+01

+/-

9.32E+00 Mean - All Indicator Locations 1.74E+01

+/-

3.55E+00

Control Station 40

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m3]

page 1 of 4 Period Endingl 01/04/11 01/11/11 01/18/11 01/25/11 02/01/11 02/08/11 02/15/11 02123/11 03/01/11 03/08/11 03/15/11 03/22/11 03/29/11

04/06/11

04/13/11 04/20/11 04/27/11 05/03/11 05/11/11 05/18/11 05/24/11 06/01/11 06/08/11 06/14/11 06/21/11 06/29/11 Station 01 1.78E+01 3.45E+01 3.03E+01 1.41E+01 1.04E+01 3.26E+01 2.24E+01 1.54E+01 1.60E+01 4.25E+01 1.13E+01 4.48E+01 1.29E+02

+/-

3.26E+01 1.28E+02

+/-

3.25E+01 5.26E+01 3.15E+01 2.93E+01 1.88E+01 4.55E+01 6.30E+01 5.96E+01 6.78E+01 3.02E+01 3.71E+01 3.30E+01 2.26E+01 Station 202 3.28E+01 3.45E+01 A.78E+01 2.60E+01 2.44E+01 3.26E+01 2.23E+01 2.52E+01 2.89E+01 Station

< 03 3.29E+01 1.82E+01 2.05E+01 3.83E+01 1.03E+02

+/-

2.51E+01 4.41 E+01 7.OOE+01

+/-

2.69E+01 2.93E+01 2.54E+01 3.10E+01 5.41E+01 1.88E+01 4.53E+01 6.32E+01 5.96E+01 6.78E+01 3.01E+01 3.80E+01 3.24E+01 2.25E+01 3.46E+01 4.98E+01 2.54E+01 2.44E+01 3.26E+01 2.23E+01 2.52E+01 2.97E+01 4.20E+01 2.03E+01 2.30E+01

+/-

1.79E+01

+/-

2.73E+01 2.51 E+01 3.26E+01 5.27E+01 1.89E+01 4.53E+01 6.28E+01 6.02E+01 6.77E+01 3.01E+01 3.89E+01 3.17E+01 2.25E+01 Station S04 3.32E+01 3.46E+01 5.00E+01 2.57E+01 2.44E+01 3.26E+01 2.24E+01 2.52E+01 2.93E+01 4.24E+01 2:05E+01 4.56E+01 1.22E+02

+/-

2.12E+01 1.05E+02

+/-

2.69E+01 3.12E+01 3.14E+01 5.35E+01 1.88E+01 4.53E+01 6.33E+01 6.OOE+01 6.78E+01 3.01E+01 3.85E+01 3.20E+ 01 2.25E+01 Station S05 3.27E+01 3.52E+01 4.88E+01 2.63E+01 2.44E+01 1.76E+01 2.35E+01 2.52E+01 2.89E+01 4.26E+01 2.05E+01 4.31 E+01 1.16E+02

+/-

3.54E+01 7.14E+01

+/-

3.49E+01 3.21E+01 3.43E+01 5.39E+01 2.16E+01 4.66E+01 6.33E+01 6.74E+01 5.99E+01 3.95E+01 4.49E+01 3.37E+01 3.05E+01

.1 Station 06 3.52E+01 3.52E+01 4.32E+01 2.75E+01 1.70E+01 1.76E+01 2.34E+01 3.02E+01 3.63E+01 3.66E+01 2.60E+01 4.64E+01 9.54E+01

+/-

2.29E+01 9.07E+01

+/-

2.82E+01 2.71 E+01 3.43E+01 4.26E+01 9.21 E+00 4.67E+01 6.32E+01

<c 6.74E+01 5.99E+01 3.96E+01 4.50E+01 3.37E+01 3.05E+01 Station 07 3

3.52E+01 3.52E+01 4.32E+01 2.70E+01 1.70E+01 1.76E+01 2.34E+01 3.02E+01 3.63E+01 3.66E+01 2.60E+01 3.62E+01 1.27E+02

+/-

2.64E+01 6.63E+01

+/-

2.45E+01 3.44E+01 3.43E+01 4.26E+01 2.16E+01 4.67E+01 2.69E+01 6.74E+01 5.99E+01 3.95E+01 4.50E+01 3.37E+01 3.05E+01

Postive iodine results on these dates attributted to Fukushima Daiichi event. See text for more details.

41

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

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Ending I

I 22 I

I I

AI 05A 01/04/11 3.53E+01 3.52E+01 2.83E+01 2.85E+01 2.82E+01 2.83E+01 01/11/11 3.51E+01 3.89E+01 3.89E+01 3.89E+01 3.e9E+01 1.66E+01 01/18/11 4.37E+01 4.38E+01 5.30E+01 5.47E+01 5.44E+01 5.37E+01 01/25/11 2.67E+01 2.67E+01 2.63E+01 2.54E+01 1.39E+01 2.63E+01 02101/11 1.72E+01 1.70E+01 2.09E+01 2.06E+01 2.06E+01 2.06E+01 02/08/11 1.76E+01 3.97E+01 3.97E+01 3.97E+01 3.97E+01 3.97E+01 02/15/11 2.35E+01 1.94E+01 2.59E+01 2.59E+01 2.60E+01 2.60E+01 02/23/11 3.01 E+01 3.01E+01 3.74E+01 3.74E+01 3.73E+01 3.74E+01 03/01/11 3.63E+01 3.64E+01 4.40E+01 4.40E+01 4.40E+01 4.39E+01 03/08/11 3.66E+01 3.66E+01 4.32E+01 4.33E+01 4.33E+01 4.33E+01 03/15/11 2.63E+01 2.61E+01 4.11E+01 4.09E+01 4.11E+01 4.10E+01 03/22/11 3.37E+01 5.13E+01 2.56E+01 4.65E+01 3.83E+01 3.70E+01 03/29/11*

9.58E+01

+/-

3.04E+01 8.72E+01

+/-

2.26E+01 1.04E+02

+/-

2.15E+01 1.15E+02

+/-

3.07E+01 8.08E+01

+/-

2.25E+01 1.23E+02

+/-

3.31E+01 04/06/11*

8.OOE+01

+/-

2.19E+01 1.03E+02

+/-

2.40E+01 6.97E+01

+/-

2.41E+01 8.08E+01

+/-

2.60E+01 7.90E+01

+/-

2.85E+01 9.64E+01

+/-

2.482+01 04/13/11 2.95E+01 2.62E+01 3.45E+01 3.01E+01 2.68E+01*

+/-

2.71E+01 2.78E+01 04/20/11 3.46E+01 4.38E+01 4.44E+01 4.38E+01 4.38E+01 1.84E-201 04/27/11 4.21E+01 4.20E+01 2.09E+01 2.07E+01 2.15E+01 2.11E+01 05/03/11 2.17E+01 2.17E+01 1.87E+01 1.88E+01 1.87E+01 1.87E+01 05/11/11 4.672+01 3.59E+01 3.59E+01 3.59E+01 3.60E+01 1.53E+01 05/18/11 6.32E+01 6.32E+01 5.33E+01 5.33E+01 5.32E+01 5.34E+01 05/24/11 6.73E+01 5.59E+01 5.59E+01 5.62E+01 5.59E+01 5.60E+01 06/01/11 5.99E+01 6.86E+01 6.86E+01 6.86E+01 6.86E+01 6.86E+01 06/08/11 3.96E+01 4.87E+01 4.87E+01 4.86E+01 4.872+01 4.86E+01 06/14/11 1.89E+01 4.41E+01 3.18E+01 3.28E+01 3.14E+01 3.21E+01 06/21/11 3.41E+01 3.22E+01 3.21E+01.

3.11E+01 3.23E+01 1.35E+01 06/29/11 3.05E+01 1.30E+01 1.64E+01 1.65E+01 1.65E+01 1.64E+01

Control Station

- Postive iodine results on these dates attributted to Fukushima Daiichi event. See text for more details.

Result is < 2-s error. Considered to be false positive.

42

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 3 of 4 Period Endingl 07/05/1'.

07/12/ 1 07/19/11 07/26/11 08/02/11 08/09/11 08/16/11 08/23/11 08/30/11 09/06/11 09/14/11 09/21/11 09/28/11 10/04/11 10/11/11 10/18/11 10/25/11 11/01/11 11/08/11 11/15/11 11/22/11 11/29/11 12/06/11 12/13/11 12/20/11 12/28/11 I

Station 01 I

5.61 E+01 7.27E+00 1.73E+01 3.06E+01 1.80E+01 1.58E+01 2.82E+01 2.71E+01 2.23E+01 1.04E+01 1.41 E+01 2.69E+01 5.63E+01 5.24E+01 1.15E+01 4.41E+01 1.70E+01 2.17E+01 1.92E+01 6.23E+00 1.76E+01 2.05E+01 1.05E+01 4.08E+01 1.15E+01 2.33E+01 Station 02 5.66E+01 1.70E+01 4.08E+91 3.05E+01 1.80E+01 1.60E+01 4.63E+01 4.41E+01 3.93E+01 1.91E+01 2.56E+01 1.03E+01 5.60E+01 5.28E+01 Station 03 5.68E+01 1.69E+01 4.08E+01 3.05E+01 1.85E+01 1.54E+01 4.62E+01 4.41E+01 3.95E+01 1.92E+01 2.54E+01 2.70E+01 5.59E+01 2.26E+01 2.04E+01 4.47E+01 3.09E+01 2.17E+01 3.48E+01 6.26E+00 3.19E+01 2.05E+01 1.92E+01 4.07E+01 2.70E+01 2.31E+01 Station 04 I

5.66E+01 1.70E2-01 4.09E+01 3.05E+01 1.83E+01 1.56E+01 4.66E+01 4.42E+01 4.05E+01 1.91 E+01 2.56E+01 2.70E+01 5.60E+01 5.28E+01 St ation 05 I

4.12E+01 1.70E+01 4.09E+01 4.32E+01 1.81E+01 1.20E+01 4.63E+02 4.41E+01 3.96E+01 1.91E+01 2.56E+01 2.70E+01 3.67E+01 5.28E+01 2.05E+01 4.48E+01 3.08E+01 1.17E+01 3.48E+01 6.89E+00 3.20E+01 1.89E+01 1.91E+01 3.85E+01 2.70E+01 3.42E+01 Station 06 4.12E+01 1.28E+01 5.13E+01 4.33E+01 1.71E+01 1.20E+01 3.73E+01 3.31E+01 5.38E+01 2.22E+01 2.72E+01 3.49E+01 3.67E+01 3.78E+01 3.30E+01 2.95E+01 3.90E+01 6.62E+00 3.93E+01 3.73E+00 4.64E+01 1.89E+01 3.14E+01 3.85E+01 2.86E+01 3.42E+01 Station 07 4.17E+0'

1.28E+0" 5.13E+0" 4.33E+0" 1.71E+0" 1.22E+0" 3.73E+0" 3.31E+0' 5.33E+0" 2.21E+O0 2.73E+0" 3.49E+0" 3.68E+0" 3.78E+0' 3.30E+0' 2.95E+0' 3.90E+0' 6.62E+O(

3.93E+0' 6.88E+0(

4.64E+0' 8.05E+0(

3.14E+0' 3.85E+0' 2.86E+0' 3.42E+0' 2.06E+01 4.44E+01 3.08E+01 2.17E+01 3.49E+01 6.26E+00 3.20E+01 2.05E+01 1.91E+01 4.08E+01 2.70E+01 cc 2.32E+01 2.04E+01 1.91E+01 3.08E+01 2.17E+01 3.48E+01 6.28E+00 3.19E+01 2.05E+01 1.91 E+01 4.07E+01 2.70E+01 2.29E+01 Mean 1.29E+02

+/-

3.26E+01 8.65E+01

+/-

2.60E+01 3.67E+01

+/-

2.26E+01 1.14E+02

+/-

2.41E+01 9.37E+01

+/-

3.52E+01 9.31E+01

+/-

2.56E+01 9.67E+01

+/-

2.55E+0 43

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 4 of 4 Period Ending 07/05/11 07/12/11 07/19/11 07/26/11 08/02/11 08/09/11 08/16/11 08/23/11 08/30/11 09/06/11 09/14/11 09/21/11 09/28/11 10/04/11 10/11/11 10/18/11 10/25/11 11/01/11 11/08/11 11/15/11 11/22/11 11/29/11 12/06/11 12/13/11 12/20/11 12/28/11 MEAN I

Station 21 4.12E+01 1.28E+01 5.11E+01 4.34E+02 1.70E+01 1.20E+01 3.72E+01 3.31E+01 5.33E+01 2.20E+01 I

Station 22 I

Station 23 I

I I

4.30E+01 1.28E+01 2.73E+01 3.49E+01 3.68E+01 3.78E+01 3.33E+01 2.92E+01 3.90E+01 6.62E+00 3.94E+01 6.84E+00 4.65E+01 1.89E+01 3.14E+01 1.65E+01 2.86E+01 3.4112+01 8.79E+01

+/-

2.62E+01 5.11E+01 4.54E+01 1.70E+01 1.12E+01 3.72E+01 3.31E+01 5.33E+01 2.20E+01 2.73E+01 3.49E+01 5.11E+00 3.78E+01 3.33E+01 2.92E+01 3.90E+01 6.62E+00 3.94E+01 6.84E+00 4.65E+01 1.89E+01 3.14E+01 3.86E+01 2.86E+01 1.45E+01 2.33E+01 4.30E+01 8.35E+00 3.02E+01 4.53E+01 1.79E+01 1.11E+01 4.06E+01 2.95E+01 4.67E+01 3.31E+01 2.21E+01 1.86E+01 5.10E+00 3.76E+01 3.34E+01 4.29E+01 4.64E+01 2.90E+01 4.48E+01 7.43E+00 3.19E+01 1.34E+01 2.74E+01 3.80E+01 4.63E+01 3.03E+01 2.28E+01 Station 24*

4.30E+01 1.95E+01 3.07E+01 2.49E+01 1.79E+01 1.11E+01 4.07E+01 2.95E+01 4.67E+01 3.30E+01 2.21 E+01 1.86E+01 5.08E+00 3.79E+01 3.29E+01 4.33E+01 4.66E+01 2.90E+01 4.45E+01 7.48E+00 3.19E+01 1.34E+01 2.74E+01 3.79E+01 4.62E+01 3.02E+01 9.79E+01

-+/-

2.84E+01 I

Station O0A 4.29E+01 1.96E+01 3.02E+01 4.83E+02 1.79E+01 4.75E+00 4.05E+01 2.95E+01 4.67E+01 3.31E+01 2.21 E+01 1.86E+01 5.13E+00 3.75E+01 3.35E+01 4.27E+01 4.64E+01 2.90E+01 4.48E+01 7.43E+00 3.19E+01 I

Station 05A 1.83E+01 1.95E+01 3.03E+01 4.52E+01 1.79E+01 4.85E+00 4.07E+01 1.62E+01 4.70E+01 3.32E+01 2.20E+01 1.86E+01 2.81E+00 3.77E+01 3.30E+01 4.33E+01 4.64E+01 2.90E+01 4.46E+01 7.48E+00 3.18E+01 1.34E+01 2.74E+01 3.79E+01 4.62E+01 3.04E+01 1.101+02

+/-

2.90E+01 8.97E+01

÷/-

2.65E+01 I

9.51 E+011

+/

8.69E+01

+/-

1.34E+01 2.74E+01 3.80E+01 4.63E+01 3.04E+01 6.22E+01

+/-

2.60E+01 Indicator Locations Mean 44

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

[10.3 pCi/m 3]

Sampling Quarter 1 Location I

Be-7 I

Cs-34**

Cs137**

I 01 1.31E+02

+/-

2.86E+01 1.76E+00 1.82E+00 01A 1.06E+02

+/-

,2.97E+01 1.32E+00 1.81E+00 02 1.53E+02

+ ÷!

A,35E+01 1.93E+00 1.80E+00 03 1.06E+02

+I-2.64E+01 1.50E+00 1.46E+00 04 1.58E+02

+/-

2.79E+01 1.28E+00 1.81 E+00 05 1.87E+02

+/-

2.98E+01 1.72E+00 1.45E+00 05A 1.41E+02

+/-

3.11E+01 1.56E+00 1.85E+00 06 1.22E+02

+/-

3.16E+01 1.40E+00 1.51 E+00 07 1.70E+02

+/-

3.80E+01 1.69E+00 1.67E+00 21 1.48E+02

+/-

3.36E+01 1.90E+00 2.01E+00 22 1.42E+02

+/-

2.60E+01 1.43E+00 1.65E+00 23 1.55E+02

+/-

3.31E+01 1.66E+00 1.51E+00 24*

1.29E+02

+/-

2.74E+01 1.28E+00 1.32E+00 Sampling Quarter 2 Location I

Be-7 I

Cs-34**

Cs137**

I Sr-89 I

Sr-90 01 2.15E+02

+/-

3.37E+01 1.68E+00 1.87E+00 4.27E+00 1.77E+00 01A 1.88E+02

+/-

3.51E+01 2.22E+00 1.87E+00 3.47E+00 1.74E+00 02 1.61 E+02

+/-

2.97E+01 2.36E+00 1.89E+00 4.40E+00 1.93E+00 03 1.91 E+02

+/-

2.65E+01 1.42E+00 1.29E+00 3.97E+00 1.60E+00 04 1.79E+02

+/-

4.36E+01 2.08E+00 1.98E+00 9.14E+00 2.16E+00 05 2.20E+02

+/-

3.45E+01 2.11E+00 1.88E+00 4.02E+00 2.61E+00 05A 2.61E+02

+/-

3.95E+01 1.97E+00 2.05E+00 3.42E+00 1.97E+00 06 1.59E+02

+/-

2.64E+01 1.33E+00 1.28E+00 4.35E+00 1.69E+00 07 1.68E+02

+1-3.31E+01 2.49E+00 1.99E+00 4.33E+00 2.05E+00 21 1.45E+02

+/-

3.03E+01 1.73E+00 1.62E+00 4.05E+00 1.77E+00 22 2.27E+02

+/-

3.79E+01 1.99E+00 1.92E+00 4.15E+00 2.08E+00 23 1.70E+02

+/-

3.25E+01 1.64E+00 1.55E+00 3.79E+00 1.73E+00 24*

1.91E+02

+/-

2.66E+01 1.52E+00 1.24E+00 3.21E+00 1.56E+00

Control Station ** LLD identified in ODCM 45

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 Be-7 2.OOE+02

+/-

3.94E+01 1.59E+02

+1-2.95E+01 1.15E+02

+1-3.63E+01 i.18E+02

+/-

3.40E+01 1.25E+02

+1-2.41E+01 1.63E+02

+/-

3.43E+01 1.29E+02

+/-

2.78E+01 1.33E+02

+/-

2.39E+01 1.60E+02

+1-3.27E+01 1.03E+02

+/-

3.07E+01 1.33E+02

+/-

3.69E+01 1.20E+02

+/-

2.66E+01 1.37E+02

+/-

4.33E+01 Quarter 3 Cs-134**

1.60E+00 1.23E+00 1.53E+00 1.95E+00 1.37E+00 1.44E+00 1.29E+00 1.19E+00 1.73E+00 1.62E+00 1.90E+00 1.26E+00 2.15E+00 SCs-1.37**

1.20E+00 1.16E+00 1.41 E+00 1.57E+00 1.24E+00 1.26E+00 1.09E+00 9.54E-01 1.40E+00 1.28E+00 1.40E+00 1.52E+00 1.93E+00 Sampling Location Be-7 01 1.22E+02

+/-

3.10E+01 01A 1.59E+02

+/-

2.79E+01 02 1.45E+02

+/-

2.55E+01 03 1.51 E+02

+/-

2.83E+01 04 1.56E+02

+/-

3.23E+01 05 1.70E+02

+/-

2.66E+01 05A 1.33E+02

+/-

3.01E+01 06 1.71 E+02

+/-

2.62E+01 07 1.34E+02

+/-

2.15E+01 21 1.12E+02

+/-

2.39E+01 22 1.50E+02

+/-

2.70E+01 23 1.22E+02

+/-

2.22E+01 24*

1.14E+02

+/-

1.90E+01

Control Station

- LLD identified in ODCM Cs-1 34*

3s71373**I 1.25E+00 1.32E+00 1.55E+00 1.31E+00 9.86E-01 1.08E+00 1.26E+00 1.22E+00 2.04E+00 1.88E+00 1.51E+00 1.55E+00 1.14E+00 1.27E+00 1.32E+00 1.32E+00 1.06E+00 8.OOE-01 1.04E+00 9.98E-01 1.46E+00 1.04E+00 9.37E-01 1.02E+00 1.15E+00 9.07E-01 Mean of All Indicator Location:

Quarter 4 Mean Be-7 1.67E+02

+/-

3.32E+01 1.53E+02

+/-

3.06E+01 1.44E+02

+/-

3.13E+01 1.42E+02

+/-

2.88E+01 1.55E+02

+1-3.20E+01 1.85E+02

+/-

3.13E+01 1.66E+02

+/-

3.21E+01 1.46E+02

+/-

2.70E+01 1.58E+02

+/-

3.13E+01 1.27E+02

+/-

2.96E+01 1.63E+02

+/-

3.20E+01 1.42E+02

+/-

2.86E+01 1.43E+02

+1-2.91E+01 1.54E+02

+/-

3.06E+01

-a 46

Table 3-6 Soil

[pCi/kg]

Soil sampled on triennial basis. Last taken 2010. Not required in 2011 47

Table 3-7 Precipitation Gross Beta

[pCi/L]

page 1 of 3 Sampling

' Date 01/25/11 02/23/11 03/29/11 04/27/11 06/01/11 06/29/11 07/26/11 08/30/11 09/28/11 10/25/11 11/29/11 12/28/11 Mean I

2.21 E+01 6.72E+00 3.OOE+00 5.83E+00 4.48E+00 2.83E+00 2.43E+00 1.81 E+00 6.15E+00 Gross'Beta 2.63E+00 1.74E+00 2.43E+00 1.56E+00 1.72E+00 2.23E+00 1.62E+00 1.19E+00 2.16E+00 2.07E+00 1.42E+00 1.13E+00 1.63E+00 Raiinches)-J 0.78 2.06 5.35 2.60 5.17 4.35 3.20 6.21 6.07 2.76 4.22 6.19 48.96 Total

LLD identified in ODCM 48

Table 3-7 Precipitation Gamma Spectra

[pCi/L]

page 2 of 3 Sampling Location I Be-7 Mn-54 I

Fe-59 I1 Co-58 I

Co-60 I

01A 06/29/11 12/28/11 01A 06/29/11 12/28/11 O0A 06/29/11 12/28/11 3.86E+01 4.99E+01

+/-

2.70E+01 Zn-65 7.48E+01 1.05E+00 I

Zr-95 2.35E+01 7.41 E+00 Nb-95 6.65E+00 1.05E+00 Cs-1 34 2.31 E+00 9.52E-01 Cs-1 37 I

I I

6.74E+00 2.22E+00 Ba-140 1.20E+01 4.38E+00 I

La-140 7.17E+00 2.53E+00 1-131 2.30E+'00 8.99E-01 Th-228 2.60E+00 8.70E-01 I

I 2.70E+03 8.89E+'02 8.45E+02 2.50E+02 2.69E+04 6.05E+03 4.91 E+00 2.78E+00 MEAN Sampling Location I Be-7 I

Mn-54 I

Fe-59 Co-58 I

Co-60 I

01A

+/

4.99E+01

+/-

2.70+01 Zn-65

+/-

Zr-95 I

Nb-95 Cs-1 34 I

Cs-1 37 01A Ba-140

+/_

+/-

+/

I La-1 40 I

1-131 Th-228 I

01A 49

+/-

Precipitation - Monthly*

Gamma Spectra

[pCi/L]

+/--

page 3 of 3 Sampling Location Be-7 I

Mn-54 I

Fe-59 Co-58 I

Co-60 I

01A 03/29/11 04/27/11 01A 03/29/1.1 04/27/11 4.56E-i-0i 6.,95E+01 4.04E+00 5.48E+01 1.03E+01 1.74E+01 4.63E0OQ 7.90E+00 4.01 E+00 5.55E+00 I

Zn-65 Zr-95 I

Nb-95 I

Cs-134 Cs-1 37 I

9.38E+'00 1.35E+-01 7.46E+00 1.35E+01 4.77E+00 8.50E+00 4.39E+00 6.02E+00

< 4.81E+00

< 7.21E+00 I

Ba-140 I

La-140 1-131 I

Th-228 I

01A 03/29/11 04/27/11 Sampling Location 1.96E+01 1.08E+2 5.43E+00 2.67E+01O 2.55E+00 +/-

1.1OE+00 +/-

6.07E-01 4.53E-01 9.48E+00 1.17E+01 MEAN Be-7 Mn-54 Fe-59 I

Co-58 I

Co-60 01A Zn-65

+/-

Cs-134

+/-

Zr-95 Nb-95 Cs-137 OIA

+/-

I Ba-140 I

La-140 1-131 Th-228 01A

+/-

1.83E+00 +/-

5.30E-01

+/-

Monthly samples not normally counted for gamma emitters. Samples counted for gamma emitters due to Fushima Daiichi event. Positve iodine results likely due to Fukushima.

See text for more details 50

Table 3-8 Milk Gamma Spectra & Strontium

[pCilL]

page 1 of 1 Sampling Date I

K-40 I

Sr-89 Sr-90 I

Station 12 1

1-131*

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

Mean 1.45E+03 1.32E+03 1.28E+03 1.32E+03 1.22E+03 1.32E+03 1.24E+03 1.10E+03 1.28E+03 1.36E+03 1.26E+03 1.30E+03 1.43E+03 1.67E+02

.1.23E+02 1.24E+02 1.39E+02 1.24E+02 8.80E+01 1.52E+02 9.87E+01 1.39E+02 1.42E+02 1.47E+02 1.46E+02 1.35E+02 I

[a]

[a]

[a]

4.65E+00

[a]

3.64E+00 1.62E+00 3.12E+00

[a]

1.38E+00 7.27E-01 8.79E-01 7.15E-01 7.67E-01 7.38E-01 7.06E-01 1.28E+00**

+/-

4.85E-01 6.74E-01 8.53E-01 5.54E-01 6.91 E-01 6.15E-01 8.47E-01 6.25E-01 6.90E-01 1.28E+00

+/-

4.85E-01 Cs-134*

6.06E+00 4.OOE+00 9.13E+/--00 6.20E+00 5.48E+00 3.80E+00 5.86E+00 3.88E+00 5.54E+00 6.96E+00 6.22E+00 6.44E+00 Cs-137*

6.89E+00 4.78E+00 7.79E+00 6.03E+00 5.81E+00 3.64E+00 6.12E+00 4.47E+00 6.64E+00 7.25E+00 6.78E+00 6.55E+00 Ba-140*

3.84E+01 2.18E+01 4.25E+01 4.39E+01 4.23E+01 4.33E+01 2.84E+01 1.91E+01 2.78E+01 3.45E+01 3.95E+01 3.65E+01 I

La-140*

9.59E+00 6.54E+00 1.08E+01 1.21E+01 1.03E+01 1.28E+01 1.01E+01 5.35E+00 8.44E+00 1.33E+01 1.27E+01 9.56E+00

+/-

LLD identified in ODCM. [a] Sr-89/90 performed quarterly 51

- Attributed to Fukushima event.

Table 3-9 Food and Vegetation Sampling Lnoc~tian Sampling Dl~te I

Be-7 Location Date I

Be-7 14A °.

05111/11 06/14/11 07/12/11 08/09/11 09/14/11 14B 10/11/11 11/08/11 14A Mean 14B Mean Sampling Sampling Location Date 8.43E+02 1.15E+03 1.44E+03 1.07E+03 2.98E+03 8.61E+02 1.43E+03 1.50E+03 1.15E+03

+1-

+1-2.81E+02 4.70E+02 5.31E+02 2.95E+02 3.86E+02 1.64E+02 3.28E+02 3.93E+02 2.46E+02 5.74E+03 7.15E+03 4.15E+03 5.74E+03 6.08E+03 5.OOE+03 6.95E+03 5.77E+03 5.98E+03 Gamma Spectra

[pCi/kg]

K-40 7.03E+02 1.01E+03 7.67E+02 5.47E+02 6.54E+02 3.36E+02 7.24E+02 7.36E+02

+/

5.30E+02

+/

1-131*

2.84E+01 2.73E+01 2.88E+01 2.51 E+01 3.09E+01 2.82E+01 3.39E+01 I

Cs-134*

3..13E+01 3.53E+01 3.06E+01 2.52E+01 2.79E+01 1.35E+01 2.82E+01 2.92E

+01 4.46E

+01 3.95E

+01 2.76E

+01 2.63E

+01 1.52E

+01 2.83E

+01 I

Cs-137" Ipage 1 of 3 I

Cs13*I l-I-

Cs-134*

Be-7 I

K-40 1-131*

Cs-137" I

15 05/11/11 06/14/11 07/12/11 08/09/11 09/14/11 10/11/11 11/08/11 Mean 7.45E+02 2.12E+03 5.76E+02 4.61 E+02 1.53E+03 4.57E+02 2.34E+03 1.18E+03

+1-

+/-

3.69E+02 5.26E+02 2.01E+02 1.86E+02 3.56E+02 1.58E+02 3.25E+02 3.03E+02 6.45E+03 7.13E+03 8.14E+03 5.15E+03 7.28E+03 6.34E+03 6.1 4E+03 6.66E+03

+1

+1 8.50E+02 9.14E+02 4.17E+02 4.78E+02 7.40E+02' 3.86E+02 5.87E+02 6.25E+02 3.36E+01 2.78E+01 3.08E+01 2.38E+01 2.76E+01 2.59E+01 3.58E+01 3.95E+01 4.33E+01 1.54E+01 2.29E+01 2.51E+01 1.39E+01 2.28E+01 3.65E

+01 4.68E

+01 1.70E

+01 2.39E

+01 2.55E

+01 1.54E

+01 2.92E

+01

+/-

52

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

page 2 of 3 Sampling Location Sampling Date Be-7 K-40 K-40 16"*

05/11/11 Coi rol 06/14/11 Station 07/12/11 08/0911 09/14/11 10/11/11 11/08/11 Mean

LLD identified in ODCM 1.54E+03 1.36E+03 8.97E+02 7.98E+02 2.20E+03 2.25E+03 2.20E+03 1.61E+03

+1-

+/-

+1-

+1-3.75E+02 4.56E+02 2.81E+02 2.71E+02 3.74E+02 1.26E+02 3.01E+02 3.12E+02 4.20E+03 4.47E+03 4.94E+03 4.04E+03 4.67E+03 6.91 E+03 6.20E+03 5.06E+03

+1

+1 7.02E+02 7.20E+02 5.79E+02 4.68E+02 6.25E+02 2.28E+02 6.38E+02 5.66E+02 1-131*

" 3.76E+01 2.55E+01 2.37E+01 4.56E+01 3.06E+01 3.OOE+01 3.65E+01 I

Cs-134*

3.42E+01 i<

3.12E+01 2.98E+01 2.54E+01 2.98E+01 8.94E+00 2.37E+01 I

f.*-1 37*

3.96E

+01 2.95E

+01 3.15E

+01

.2.60E

+01 3.29E

+01 9.58E

+00 2.73E

+01

+/

I

+/-

Sampling Location Sampling Date Be-7 I

K-40 I

1-131*

I Cs-134*

I Cs-137*

I 23 05/11/11 06/14/11 07/12/11 08/09/11 09/14/11 10/11/11 11/08/11 9.56E+02 5.80E+03 9.98E+02 8.24E+02 3.11 E+03 8.95E+02 1.75E+03 3.94E+02 8.03E+02 4.10E+02 2.10E+02 3.90E+02 1.03E+02 3.18E+02 4.80E+03 4.67E+03 7.96E+03 6.78E+03 4.91E+03 5.92E+03 6.29E+03 7.02E+02 9.57E+02, 1.10E+03 5.73E+02 6.18E+02 2.13E+02 6.OOE+02 3.90E+01 3.01E+01 2.76E+01 2.73E+01 3.54E+01 2.71E+01 3.86E+01 3.90E+01 5.58E+01 3.40E+01 2.58E+01 2.52E+01 9.24E+00 2.64E+01 4.17E+0 I1 5.66E+0 4.87E+

1 1

< 2.62E+0 I

1.03E+0 1

2.98E+0 1

Mean 2.05E+03

+/-

3.75E+02 5.90E+03

+/-

6.80E+02

+/-

53

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

page 3 of 3 Cs-137*

Sampling Location Sampling Date6 I

Be-7 K-40 1-131*

I "Cs-1 34*

I 26 05/11/11 06/14/11 07/12/11 08/09/11 09/14/11 10/11/11 11/08/11 Mean 1.39E+03 2.19E+03 2.07E+03 1.28E+03 2.24E+03 3.06E+03 2.77E+03 3.71E+02 6.61E+02 6.52E+02 2.06E+02 3.64E+02 1.43E+02 3.32E+02 5.23E+03 5.98E+03 5.09E+03 5.22E+03 4.42E+03 3.97E+03 4.72E+03 7.34E+02 1.15E+03 9.19E+02 4.88E+02 6.41 E+02 2.09E+02 6.36E+02 3.92E+01 3.37E+01 2.73E+01 2.45E+01 3.60E+01 3.01 E+01 3.84E+01 3.92E+01 5.56E+01 5.34E+01 1.97E+01 2.93E+01 1.04E+01 2.50E+01 3.30E+02 5.98E+01 5.75E+01 2.17E+01 2.98E+01 1.12E+01 3.18E+01 2.14E+03

+/-

3.90E+02 4.95E+03

+/-

6.82E+02 1.69E+03

+/-

3.55E+02 5.84E+03

+/-

6.66E+02

+/-

Indicator locations

LLD identified in ODCM 54

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

[pCi/L]

page 1 of 1 Sampling Date H-3 I

Sr-89 I

Sr-90 I

Mn-54 Fe-59 I

Co-58 I

Station 01A I

Zn-65 Co-60 I

03/29/11 06/29/11 09/28/11 12/28/11 9.98E+02 9.81 E+02 5.28E+02 5.91 E+02

[a]

4.19E+00

[a]

9.84E-01 6.31 E+00 4.68E+00 5.48E+00 4.77E+00 1.19E+01 1.04E+01 1.23E+01 8.10E+00 5.49E+00 5.18E+00 5.96E+00 4.42E+00 5.12E+00 4.25E+00 5.88E+00 4.51 E+00 9.79E+00 1.06E+01 1.32E+01 1.05E+01 Mean Sampling Date I

Zr-95 I

Nb-95 1

1-131 Cs-134 I

Cs-1 37 I

Ba-140 I

La-140 I

03/29/11 06/29/11 09/28/11 12/28/11 9.82E+00 8.81 E+00 9.24E+00 8.66E+00 8.45E+00

+/-

5.76E+00 5.33E+00 4.72E+00 4.39E+00 6.71E-01 8.51E-01 5.90E-01 5.73E-01 4.50E+00 4.89E+00 7.16E+00 4.39E+00 4.87E+00 4.48E+00 6.53E+00 4.68E+00 3.52E+01 3.32E+01 2.77E+01 3.29E+01 9.88E+00 1.18E+01 1.OOE+01 8.20E+00 Mean 8.45E+00

+/-

4.72E+00

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

55

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

[pCi/L]

page 1 of 1 Sampling Date I

Sr-89 I

Sr-90 I

I Fe-5g*

I Co~58*

I Station 11 Co-60" I

Zn-65*

I H-3*

Mn-54*

Date I

Sr-89 I

Sr-90 I

I Fe-59*

I Co-58*

I Co-60*

Zn 01/11/11 02/15/11 03/14/11 04/12/11 05/16/11 06/13/11 07/11/11 08/14/11 09/13/11 10/10/11 11/14/11 12/13/11 MEAN Sampling Date

[a]

3.01E+03

+/-

[a]

2.79E+03

+/-

[a]

4.07E+03

+/-

[a]

4.48E+03

+/-

3.59E+03

+/-

7.29E+02 6.53E+02 7.71 E+02 5.64E+02 6.79E+02

[b]

4.28E+00

[b]

Zr-95*

[b]

.[b]

'[b]

[b]

7.25E-01

[b]

[b]

[b]

1-131*

4.73E+00 3.95E+00 3.57E+00 3.24E+00 3.90E+00 1.09E+00 2.99E+00 3.79E+00 5.71 E+00 4.88E+00 2.79E+00 4.34E+00 9.24E+00 8.62E+00 6.90E+00 7.26E+00 9.56E+00 2.96E+00 6.19E+00 7.90E+00 1.16E+01 1.21E+01 9.79E+00 9.76E+00 4.44E+00 4.09E+00 3.64E+00 4.12E+00 4.43E+00 1.21 E+00 3.47E+00 3.54E+00 6.05E+00 5.40E+00 4.36E+00 4.88E+00 5.15E+00 4.05E+00 3.46E+00 3.58E+00 4.30E+00 1.31E+00 3.74E+00 3.02E+00 6.76E+00 4.57E+00 4.62E+00 4.11E+00 9.32E+00 7.71 E+00 7.24E+00 6.78E+00 8.44E+00 2.27E+00 6.07E+00 6.58E+00 1.35E+01 9.58E+00 7.71 E+00 1.08E+01

+/-

Nb-95*

Cs-134*

I Cs-137*

I Ba-140*

I La-140*

I 01/11/11 1.01 E+01

+/-

02/15/11 03/14/11 04/12/11 05/16/11 06/13/11 07/11/11 08/14/11 09/13/11 10/10/11 11/14/11 12/13/11 MEAN 1.01E+01

+/-

LLD identified in ODCM 3.56E+00 4.14E+00 6.33E+00 6.99E+00 6.78E+00 2.17E+00 6.13E+00 5.98E+00 1.01E+01 9.41 E+00 8.38E+00 8.34E+00 3.56E+00 9.15E+00 7.32E+00 4.04E+00 3.98E+00 3.98E+00 1.42E+00 3.59E+00 4.29E+00 5.80E+00 5.30E+00 3.88E+00 5.79E+00 3.69E-01 2.65E-01 8.36E-01 6.52E-01 6.42E-01 6.80E-01 6.94E-01 7.11E-01 6.99E-01 5.28E-01 7.83E-01 6.42E-01 4.61E+00 3.78E+00 3.47E+00 3.41 E+00 3.56E+00 9.19E-01 2.72E+00 3.49E+00 6.06E+00 5.27E+00 3.94E+00 4.96E+00 5.36E+00 3.86E+00 3.49E+00 3.81E+00 4.59E+00 1.26E+00 3.61 E+00 3.31 E+00 5.80E+00 5.81 E+00 5.15E+00 4.98E+00 2.59E+01 2.20E+01 2.31E+01 2.66E+01 2.59E+01 1.45E+01 2.23E+01 1.92E+01 2.60E+01 2.84E+01 2.70E+01 2.47E+01 9.69E+00 5.75E+00 6.84E+00 8.62E+00 8.13E+00 3.60E+00 7.27E+00 5.80E+00 9.83E+00 8.15E+00 8.48E+00 7.85E+00

+/-

[a] Tritium analyses on quarterly composite.

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

56

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

[pCi/L]

page 1 of 2 Sampling Date H-3*

Sr-89 I

Sr-90 01/11/11

[a]

02/15/11

[a]

03/14/11 3.87E+03

+/-

7.76E+02 04/12/11

[a]

05/16/11 06/13/11 2.27E+03

+/-

6.24E+02 07/11/11

[a]

08/14/11

[a]

09/13/11 3.93E+03

+/-

7.70E+02 10/10/11

[a]

11/14/11

[a]

12/13/11 3.32E+03

+/-

5.30E+02 Mean 3.35E+03

+/-

6.75E+02 Sampling Date 01/11/11 02/15/11 03/14/11 04/12/11 05/16/11 06/13/11 07/11/11 08/14/11 09/13/11

[b]

4.08E+00

[b]

Nb-95*

3.49E+00 4.53E+00 3.34E+00 3.70E+00

. 4.51 E+00 1.38E+00 2.73E+00 4.96E+00 5.39E+00 4.48E+00 5.54E+00 5.81 E+00

[b]

6.02E-01

[b]

3Mn-54*

3.35E+00 3.09E+00

'3.14E+)00 4.08E+00 3.42E+00 1.16E+00 2.20E+00 4.52E+00 4.21 E+00 4.67E+00 5.53E+00 5.33E+00 I

Fe-59*

7.48E+00 9.87E+00 5.67E+00 9.93E+00 8.76E+00 3.31E+00 4.85E+00 1.06E+01 1.25E+01 8.59E+00 1.17E+01 1.18E+01 Cs-137*

3.49E+00 4.04E+00 2.86E+00 3.95E+00 4.03E+00 2.48E+00 5.29E+00 5.29E+00 5.36E+00 I

Co-58*

3.04E+00 4.19E+00 2.82E+00 3.97E+00 4.03E+00 1.07E+00 2.29E+00 3.86E+00 5.24E+00 4.36E+00 5.30E+00 4.36E+00 I

Co-60*

3.18E+0 4.32E+t 3.41E+0 4.08E+0 3.82E+0 1.26E+0 2.95E+0 6.52E+0 5.02E+0 4.94E+0 4.87E+0 5.15E+0

+/-

Station 08 I

Zn-65*

00 6.87E+00 00 8.74E+00 00 6.66E+00 00 8.17E+00 00 7.41 E+00 00 2.38E+00 00 5.27E+00 00 1.08E+01 00 1.17E+01 00 9.59E+00 00 9.50E+00 00 1.05E+01 Zr-95*

6.22E+00 7.27E+00 5.91E+00 6.51 E+00 6.95E+00 2.66E+00 4.67E+00 8.66E+00 8.60E+00 9.46E+00 9.45E+00 7.59E+00 I

I 1-131" 4.20E-01 2.68E+00 7.59E-01 6.85E-01 6.32E-01 7.52E-01 6.66E-01 6.66E-01 7.70E-01 5.90E-01 7.83E-01 6.29E-01 I

Cs-134" 3.36E+00 3.73E+00 3.20E+00 3.43E+00 3.33E+00 1.92E+00 4.76E+00 4.76E+00 4.09E+00 I

I I

Ba-140*

La-I40*

1.52E+01 1.96E+01 2.08E+01 2.75E+01 2.75E+01 1.51E+01 2.40E+01 2.40E+01 2.80E+01 2.54E+01 1.91E+01 2.30E+01 4.75E+00 6.68E+00 7.14E+00 7.87E+00 8.34E+00 5.89E+00 8.OOE+00 8.OOE+00 9.16E+00 1.14E+01 "9.42E+00 7;86E+00 10/10/11 11/14/11 12/13/11 Mean

LLD identified in ODCM 4.49E+00 5.55E+00 5.46E+00 4.79E+00 5.69E+00 5.87E+00

[a] Tritium analyses on quarterly composite.

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

57

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

[pCi/L]

page 2 of 2 Sampling Date H-3*

I Sr-89 I

S;r-g Mn-54*

Fe-59*

I 01/11/11 02/15/11 03/14/'11 04/12/11 05/16/11 06/13/11 07/11/11 08/14/11 09/13/11 10/10/11 11/14/11 12/13/11

[a]

[b]

[a) 8.67E:-02

[a]

8.50E+02

[a]

9.37E+02

[b]

4.21 E+00

[b]

3.51 E+00

[b]

3.41E+00

[bi 3.13E+00

[b]

3.74E+00

[b]

3.69E+00 6.12E-01 1.55E+00

[b]

2.46E+00

[b]

4.41 E+00

[b]

5.16E+00

[b]

5.02E+00

[b]

3.66E+00

[b]

4.59E+00 7.42E+00 8.03E+00 6.62E+00 8.22E+00 8.40E+00 3.41 E+00 4.91 E+00 1.04E+01 1.07E+01 9.92E+00 9.55E+00 1.03E+01 Co-58" 3.71E+00 3.87E+00 3.20E+00 4.44E+00 4.40E+00 1.40E+00 2.24E+00 4.44E+00 5.07E+00 5.08E+00 4.70E+00 5.62E+00 Station 09A Co-60<

Zn365*

3.84E+00 7.67E+00 3.75E+00 7.50E+00 2.87E+00 4.53E+00 3.80E+00 7.10E+00 3.93E+00 8.08E+00 1.25E+00 3.37E+00 2.62E+00 4.57E+00 4.99E+00 8.86E+00 6.08E+00 9.94E+00 5.36E+00 1.07E+01 4.06E+00 7.28E+00 6.69E+00 8.75E+00

[a]

[b]

[a]

6.11E+02

[b]

MEAN

+/-

Sampling Date Zr-95*

Nb-95" 1-131 Cs0134*

01/11/11 7.00E+00 3.98E+00 3.69E-01 3.71E+00 Cs-137" 4

4.05E+00 Ba-140*

2.12E+01 La-140*

6.33E+00 02/15/11 03/14/11 04/12/11 05/16/11 06/13/11 07/11/11 08/14/11 09/13/11 10/10/11 11/14/11 12/13/11 MEAN 6.03E+00 5.02E+00 8.20E+00 5.49E+00 2.80E+00 4.67E+00 9.02E+00 1.01E+01 8.25E+00 8.33E+00 8.46E+00 3.93E+00 5.21 E-01 3.06E+00 7.76E-01 4.49E+00 8.17E-01 4.OOE+00 5.47E-01 1.51E+00 8.13E-01 2.54E+00 7.99E-01 5.39E+00 6.72E-01 5.60E+00 8.71 E-01 4.87E+00 5.24E-01 5.00E+00 7.15E-01 6.26E+00 6.53E-01 3.77E+00 2.56E+00 3.61 E+00 3.83E+00 1.14E+00 2.10E+00 4.50E+00 4.83E+00 4.72E+00 4.58E+00 6.06E+00 3.68E+00 3.01 E+00 4.09E+00 4.58E+00 1.26E+00 2.39E+00 4.78E+00 6.67E+00 4.84E+00 5.49E+00 5.79E+00 1.84E+01 1.90E+01 2.87E+01 2.53E+01 1.58E+01 1.68E+01 2.51E+01 2.77E+01 2.55E+01 2.66E+01 2.94E+01 7.50E+00 4.55E+00 8.25E+00 8.12E+00 5.56E+00 5.61 E+00 8.88E+00 9.07E+00 1.06E+01 8.35E+00 1.16E+01

LLD identified in ODCM

[a] Tritium analyses on quarterly composite.

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

58

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

page 1 of 1 Sample Date 4/18/2011 Station 08-Station 09A**

Station 11 I

Sr-89 I

Sr-90 K-40 I

Cs-134*

I Cs-137*

[a]

1.95E+04 1.19E+04 1.51E+04

+/-

1.46E+03 1.16E+03 1.30E+03 5.17E+01 4.85E+01 4.97E+01 Th-228 5.63E+01 5.19E+01 5.90E+01 Th-232 Ra-226 I

04/18/2011 Station 08 Station 09A**

Station 11 Sample Date 1.39E+03 1.56E+03

+/-

9.57E+02 2.40E+03,

+/-

1.27E+03 2.98E+03 5.57E+02 1.09E+03

+/-

2.30E+02 7.64E+01 1.15E+02 2.13E+03 5.87E+02 1.23E+03

+/-

3.02E+02 1.31E+02 1.67E+02 Sr-89 I

Sr-90 I

K-40 I

Cs-134*

I Cs-137*

10/10/2011 Station 08 Station 09A**

Station 11 8.72E+01 9.32E+01 8.98E+01 3.67E+01 4.92E+01 4.53E+01 1.69E+04 1.48E+04 1.49E+04

+/-

1.78E+03 1.64E+03 1.56E+03 6.59E+01 7.47E+01 6.78E+01 Th-228 Th-232 8.71 E+01 1.04E+02 7.81 E+01 Ra-226 I

I 10/10/2011 Station 08 Station 09A**

Station 11 2.32E+03 2.07E+03 MEAN

+/-

1.56E+03 1.49E+03

+/-

1.85E+03 K-40I 1.94E+03 9.02E+02 1.23E+03

+/-

1.44E+02 1.33E+02 1.33E+02 1.92E+03 7.32E+02 1.16E+03

+/-

2.16E+02

+/-

1.86E+02

+/-

2.05E+02 I

Sr-89 Sr-90 Cs-134*

I Cs-137*

Indicator Control

+/-

1.66E+04 1.34E+04 Ra-226 2.26E+03 1.56E+03

+/-

1.53E+03

+/-

1.40E+03

+/-

Indicator Control

LLD identified in ODCM Th-228

+/-

1.56E+03 1.81 E+03

+/-

9.57E+02 7.30E+02

+/-

I Th-232 1.56E+02 1.61 E+03

+/-

2.23E+02 1.05E+02 6.60E+02

+/-

1.59E+02 I

- Control Station

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

59

Table 3-14 Shoreline Soil Gamma Spectra, and Strontium

[pCi/Kg]

page 1 of 1 Sample Date Sr-89 Sr-90 K-40 Cs-134 I

Cs-137 4/18/2011 Station 08

[a]

1.93E+03

+/-

5.05E+02 3.71E+01 5,27E+01 Ra-226 ITh-228 ITh-232 1.78E+03

+/-

9.45E+02 5.02E+02

+/-

8.10E+01 4.54E+02

+/-

1.25E+02 Sample Date Sr-89 Sr-90 K-40 Cs-134 Cs-1 37 10/10/2011 Station 08 8.71E+01 4.25E+01 2.13E+03

+/-

9.06E+02 8.45E+01 Th-228 1.05E+02 Th-232 Ra-226 I

MEAN K-40 2.03E+03 2.67E+02

+/-

1.52E+02 4.12E+02

+/-

1.61E+02 Sr-89 Sr-90 I

I.

Cs-134 Cs-1 37

+/-

2.03E+03

+/-

7.06E+02

+/-

I Ra-226 I

Th-228 Th-232 I

1.78E+03

+-

9.45E+02 3.85E+02

+/-

1.17E+02 4.33E+02

+/-

1.43E+02

LLD identified in ODCM

[a] Sr-89190 analyses performed annually.

60

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-5*

I Co-60 I

Zn-65*

I Cs-i34.

I Cs-37' I

04/20/11 2.40E+03

+/-

1.04E+03 9.03E+01 2.52E+02 9.63E+01 8.07E+01 1.83E+02 7.98E+01 7.83E+01 10/11/11 2.15E+03

+/-

3.03E+02 2.14E+01 5.08E+01 2.31E+01 2.37E+01 4.33E+01 1.93E+01 2.18E+01 Sampling Station 25**

Date I

K-40 I

Mn-54*

I Fe-59" I

Co-5*

I Coo60*

I Zn-65*

I Cs-i34 I

Cs-i 37*

04/19/11 1.68E+03

+/-

7.51E+02 6.01E+01 2.00E+02 7.75E+01 4.63E+01 1.44E+02 5.50E+01 5.83E+01 10/11/11 3.63E+03

+/-

5.59E+02 2.97E+01 7.03E+01 3.49E+01 3.66E+01 6.05E+01 2.93E+01 3.44E+01 catfish [b]

Sampling Station 08 Date I

K-40 I

Mn-54*

I Fe-59*

I Co-58 I

Co-60o I

Zn-65*

Cs-i34.

I Cs-i-37 I

04/21/11 2.35E+03

+/-

9.28E+02.

6.90E+01 1.98E+02 7.62E+01 6.92E+01 1.47E+02 6.77E+01 7.41E+01 10/12/11 1.92E+03

+/-

1.55E+03 9.98E+01 2.40E+02 1.07E+02 9.81E+01 2.60E+02 1.07E+02 8.89E+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-i34' I

Cs-i 37*

04/19/11 2.44E+03

+/-

7.62E+02 10/19/10 3.15E+03

+/-

9.31E+02 6.45E+01 1.84E+02 6.19E+01 1.85E+02 9.13E+01.

8.28E+01 8.47E+01 7.63E+01 1.51E+02 1.91E+02 7.15E+01 6.21E+01 5.89E+01 8.02E+01 Mean 2.47E+03

+/-

8.53E+02 Indicator 2.21E+03

+/-

9.55E+02 Control 2.73E+03

+/-

7.51E+02

LLD identified in ODCM

- Control Station

[a] Non-bottom dwelling species of gamefish.

[b] Bottom dwelling species of fish.

61

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2011 and tabulated in Section 3, are discussed below. Except for TLDs, TBE analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the TBE quality assurance manuals and laboratory procedures.

In addition to internal quality control measurements performed by each laboratory, they also participate in an Interlaboratory Comparison Program.

Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the Interlaboratory Comparison Programs are provided in Appendix B.

The predominant radioactivity detected throughout 2011 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Naturally occurring nuclides such as Be-7, K-40, Th-228 and Th-232 were detected in numerous samples. Th-228 & Th-232 results were variable and are generally at levels higher than plant related radionuclides.

The following is a discussion and summary of the results of the environmental measurements taken during the 2011 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.

62

9.0 8.0 7.0 6.0 5.0 4.0 3.0 2.0 1.0 fnn

- WON Environmental TLDs

-U-Sector TLDs

--*-Avg. Pre-op

%a 00 0

N~

mr 00 0

N.

-W 00 0

eN SCCCCCC C

a C

a 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 4.2 mR/standard month with a range of 1.6 to 10.7 mR/standard month. The highest quarterly average reading for any single location was obtained at location SSW-19/51. This value was 7.1 mR/standard month. This location was on site directly across the access road from the Independent Spent Fuel Storage Facility for a portion of the first quarter.

It was subsequently relocated due to U-3 construction activities farther from the ISFSI. The higher values in the first quarter can 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 3.3 mR/standard month with a range of 1.6 to 6.0 mR/standard month.

The average annual reading for these locations was 3.3 mR/standard month with a range from 2.2 to 4.7 mR/standard month. The control location showed a quarterly average of 3.3 mR/standard month with a range of 2.4 to 4.1 mR/standard month. Its annual reading was 3.0 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 4.8 mR/standard month with EPSP-9/ 10 having the highest quarterly average of 6.6 mR/standard month. Eight other TLDs, designated C-1 thru C-8, which were pre-operational controls, were collected quarterly from four locations. Stations C-3/4 and C-7/8 are designated controls. These had a quarterly average of 3.2, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.6 to 3.9 63

mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. The drop indicated in 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 0.04 0.02 0

W) M) C (N

1)~

U)>

(0 1-W)

M CO U)

UU)

U)0))

U)

)

U U

(N()-

M

)

(0 U)

C a)))

C)

UC) 18>

Control Sta-24 Indicator Average Pre-op Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 64

3.OOE-02 2.50E-02 2.OOE-02 1.50E-02 1.00E-02 5.OOE-03 O.OOE+O0 o

0.W 0

Z U-Z

--4-Control Sta-24 -U-Indicator Figure 4-3 2011 Gross Beta in Air Particulates (pCi/rm3) 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 and the effect of the Fukushima Daiichi event. During the last week of march and the first week of April positive results were seen on all samples taken.

Each week all results were roughly similar. The indicator locations averaged 89.7 fCi/m 3, while the control location averaged 97.9 fCi/m 3. This indicates the iodine detected was unrelated to plant activities, but instead due to the Fukushima Dalichi event. One sample taken at station 01A the second week of April showed an airborne 1-131 concentration of 26.8 fCi/m3. However, this is considered to be a false positive, since it was less than the 2-a error, though greater than MDA.

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

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

Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected. The results of these analyses indicate the lack of station effects on the 65

environment.

4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations. There has been no detection of 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 2010 and thus were not collected in 2011.

In 2010 Cs-137 was identified in several samples.

For the indicator stations the average was 283 pCi/Kg while for the control station the average was 223 pCi/Kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout.

Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The 2010 levels also varied significantly by location and date and averaged lower than preoperational levels at 283 pCi/Kg.

The decrease in the average and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout.

Cs-134 was detected in three samples in 2010, but these were considered false positives since the peak was not identified during the analysis, but the force activity calculation resulted in an activity concentration that exceeded the 2a value and the MDC.

4.7 Precipitation A sample of rain water was collected monthly at on-site station 01A and analyzed for gross beta activity. The results are presented in Table 3-7.

12 precipitation samples were obtained in 2011.

Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements.

Following the detection of 1-131 in the airborne radioiodine samples in March the plant requested monthly analyses of precipitation samples for March and April.

The samples were positive for 1-131 with an average of 1.83 pCi/L and ranging from 1.10 pCi/L to 2.55 pCi/L. To confirm that this was due to the Fukushima Daiichi event, the plant also analyzed samples taken from several employee residences around the station in a variety of distances, up to 30 miles away, and directions, NW, NE, SW, and SSW of the station. These samples were analyzed on-site and are not included as part in this report, but ranged from 13.6 to 437 pCi/L, with the highest values being obtained from a location about 30 miles from the plant in the NW direction. This confirms the positive results seen were due to 66

the Fukushima Daiichi event.

Thus it can be concluded that no positive indications of plant related gamma emitting radioisotopes were observed in 2011.

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 2011 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter.

4.8 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment.

This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any plant effect.

Analysis results for cow milk are contained in Table 3-8. The sample taken in April was positive for 1-131 at a level of 1.28 pci/L. No other samples indicated positive results. This level is in approximately the same as seen in many locations throughout the United States following the Fukushima Daiichi event. According to the EPA RadNEt Laboratory data milk sample results taken between March 11 and June 30 in the continental US ranged from 0.77 to 8.9 pCi/L. Based on this and the airborne radiodine samples and precipitation sample results, the most likely cause of the positive results is the Fukushima Daiichi event. Results of gamma ray spectroscopy did not detect the presence of any isotopes related to the operation of North Anna. In years past, Cs-137 has been detected sporadically.

The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Naturally occurring K-40 was detected in all samples.

Once each quarter a sample from each of the two collection stations is analyzed for strontium-89 and strontium-90.

Neither Sr-89 nor Sr-90 was detected.

Sr-90 has been observed in the past. Pre-operational levels of 2.2 to 5.4 pCi/liter were measured for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents.

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

67

4.9 Food Products and Vegetation Food/vegetation samples were collected from five locations and analyzed by gamma spectrometry.. *The results of the analyses are presented in Table 3-9. Low levels of Cs-137, attributable to fallout, have been 'seen periodically in vegetation samples.

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

4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory.

These samples were analyzed for gamma radiation and for tritium. The second quarter sample was 'analyzed for strontium-89 and strontium-90. The results of these analyses are presented in Table 3-10. The September sample reported Nb-95 results greater than the 2-a error and MDA. However the peak was identified during the analysis, but. the activity listed is the result of a forced activity calculation, not Nb-95 radioactivity. This is considered a false positive, thus no plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period.

4.11 River Water A sample of water from the North Anna River was collected monthly. The analyses are presented in Table 3-11.

All monthly samples are analyzed by gamma spectroscopy. 'The monthly samples were composited quarterly and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90 in accordance with program requirements. There has been no detection of these fission products at any of the indicator or control stations in recent years.

No gamma emitting radioisotopes were positively identified in any of the samples.

The January sample reported Nb-95 results greater than the 2-a error and MDA.

However the peak was identified during the analysis, but the activity listed is the result of a forced activity calculation, not Nb-95 radioactivity. This is considered a false positive. There was no measured activity of strontium-89 or strontium-90.

Tritium was measured in all four samples with an average annual concentration of 3590 pCi/liter and a range of 2790 to 4480 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.

68

8000 7000 6000

-JW 5000 4000 3000 2000 1000 0

N M0) 0)0 0)

0)

M)00 0

00M IT0 0

0 P- 0 0

0*

0 00 0M 00 0

0000000000 Date -H-3 in RW Tritium

-H-3in RW Required LLD 00 oo

('N 4

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.

No non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the other samples.

No tritium was detected at the control location. The average level of tritium activity at the indicator station was 3350 pCi/liter with a range of 2270 to 3930 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.

69

10000 1000 14 - Tritium O

100 Required LLD Average Pre-op 10 Date Figure 4.5Tritium in Surface Water 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station.

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

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

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

No plant related isotopes were detected in 2011.

The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented. During the pre-operational period sediment samples were also analyzed by gamma ray spectroscopy.

Neither Strontium-89 nor Strontium-90 was detected any samples of aquatic sediment/silt in 2011. Strontium-90 has been detected occasionally in the past at 70

both the indicator and control locations and is attributable to fallout from past bomb tests. A number of naturally occurring radioisotopes were detected in these samples at background levels.

10000 1000 100 C.

10 1 o (V

1--

0 0

MM U)

(0 W

M CD C

0 0

0 00WD 0t (M

(M MV MV M~

0) 0)(

(D (

M MV MV MV CD (V

(

D (V

CV CD (V)

(V

(

V Date

Station-8

--- Station-9 Control-Sta-09A

-x Station-1 1 Average Pre-Op Required LLD's Figure 4-6 Cs-137 in Sediment/Silt 4.14 Shoreline Soil Shoreline soil/sediment, unlike bottom sediment, may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses.

Samples of shoreline soil were collected in April and October from indicator station 08. The samples were analyzed by gamma ray spectrometry. The October sample was analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-14.

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.

71

4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2011 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.

72

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2011 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14A,15,16,23, Vegetation

.01/11/11 Seasonal unavailability 26 14A, 15,16,23, Vegetation 02/08/11 Seasonal unavailability 26 01 AP/Char 03/08/11 Patch was not discolored, hwoevr air sampler indicated normal sample volume 14A, 15,16,23, Vegetation 03/08/11 Seasonal unavailability 26 14A, 15,16,23, Vegetation 04/12/11 Seasonal unavailability 26 01A Well Water 01/25-06/29/11 Gamma Analysis was run on March and April monthly samples during Fukushima Daiichi event. These were not included in semiannual composite.

14B,15,16,23, Vegetation 12/14/11 Seasonal unavailability 26 73

REFERENCES 74

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.

75

APPENDICES 76

APPENDIX A: LAND USE CENSUS Year 2011 77

LAND USE CENSUS North Anna Power Station North Anna County, Virginia January I to December 31, 2011 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch 1Boundary

(>50M2)

Animal Cow Goat N

0.9 1.3 1.7 2.9 NONE NONE NNE 0.9 0.9 1.2 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.2 2.4 2.7 NONE NONE E

0.8 1.3 2.0 3.5 NONE NONE ESE 0.9 1.7 1.7 4.9 NONE NONE SE 0.9 1.4 1.5 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE S

0.9 1.0 1.0 2.0 NONE NONE SSW 1

1.3 3.1 2.0 NONE NONE SW 1.1 1.7 2.6 NONE NONE NONE WSW 1.1 1.6 2.4 1.6 NONE NONE W

1.1 1.5 1.9 4.4 NONE NONE WNW 1

1.1 2.6 5.0 NONE NONE NW 1

1.0 2.0 NONE NONE NONE NNW 0.9 1.0 1.2 2.3 NONE NONE 78

2010 to 2011 Land Use Census Changes 2010 2011 Nearest Direction Distance Distance Site Boundary NONE Resident NONE Garden N

1.9 1.7 NNE 1.7 1.2 SW 3.0 2.6 W

1.5 1.9 NNW 2.2 1.2 NW NONE 2.0 Meat Animal NNW NONE 2.3 Milch Cow NONE Milch Goat NONE 79

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2011 80

ENTRODUCTION 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 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 DOE

> Water and soil for gamma, Iodine-131, U-233/234, U-238, transuranics, tritium, Fe-55, Ni-63, Sr-90 and Tc-99 analyses during the 1st quarter.

Water for gross alpha and beta during the 1st and 3rd quarters.

> Air particulates and vegetation for gamma, Iodine-131, U-233/234, U-238, transuranics, Sr-90 analyses during the 1st and 3rd quarters.

> Air filter for gross alpha and beta analyses during the 1st and 3rd quarters.

RESULTS NCR 11-01 Failed MAPEP Series 23 water Pu-238 and Pu-239/240. At the time of the 2010 report this item was still under investigation, and the results of the investigation and corrective action were to be included in this year's report. The samples were rerun, confirming the original results. The samples were then rerun using a pyrosulfate fusion prep method. The fusion prep method failed due to zero (0%) chemical recovery. Due to limited sample volume, only one sample (L43697-1) was aliquoted for microwave digestion prep. The results fell within the acceptance criteria. Environmental water samples will use microwave digestion as 81

the prep method. Procedure TBE-2001, Alpha Isotopic and Pu-241, has been revised to include the following statement:

For Pu-238 and Pu-239/240 in environmental water samples, prepare samples by microwave digestion. Evaporate the required sample volume down to approximately 10-15 m. Do not take to dryness. Transfer to a digestion vessel.

Then microwave digest as per procedure TBE-3010, Microwave Digestion System Use and Maintenance Interlaboratory comparison program results are evaluated using TBE#'s criterion.

Any sample analysis result that does not pass the criteria is investigated by TBE.

For the primary laboratory, 14 out of 18 analytes met the specified acceptance criteria. Four analytes (one sample each of Cr-51, Sr-89 and Sr-90 and two Gross Alpha samples) did not meet the specified acceptance criteria. Nonconformance Reports were generated and corrective actions taken as a result of this program.

NCR-11-08: ERA Rad85 Gross alpha failed high. Results of investigation showed evaporated samples exceeded EPA solids requirement of 100 mg and beyond the range of the efficiency curve. Corrective action was to coach the technician and to annotate the template with the following statement:

"Solids on the planchet should be less than 0.100 grams for gross alpha..

" NCR 11-11: DOE's MAPEP Gross Alpha AP failed high. Spiked side of AP was incorrectly placed facing down in the planchet. Acceptable results were obtained when the AP was placed in the planchet facing upward and recounted. Technician was coached to place a small dot on filter to indicate which side faces upwards. Sr-90 in soil, air particulate and vegetation were non-reports that were evaluated as failed.

MAPEP evaluated the non-reports as failed due to not reporting a previously reported analyte. No further aqction necessary.

NCR 11-13: Cr-51 failed high on first quarter E &Z Analytics. All results were biased slightly high, - 100 - 115%. Correcitive action was to review 2nd quarter results. These results were acceptable and showed no bias.

NCR 11-16 In-house ERA Crosscheck results for Sr-89 failed high.

The result was within the acceptance criteria for Teledyne Brown Engineeringof

+ 20%. No corrective action necessary A summary of TBE's results is provided in the tables on the following pages for the required sample matrix types and isotopic distribution. Delineated in the table for 82

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.

83

TABLE F-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2011 E7460-396 Milk Sr-89 pCi/L 98.8 Sr-90 pCi/L 15.2 97.4 15.8 1.01 0.96 A

A E7461-396 Milk 1-131 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59, Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 92.9 398 130 232 121 289 201 287 186 243 85.0 168 89.2 171 129 159 132 96.9 0.96 A

not provided by Analytics for this study 298 1.34 N (1) 130 1.00 A

205 1.13 A

113 1.07 A

266 1.09 A

175 1.15 A

261 1.10 A

172 1.08 A

E7463-396 AP Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E7462-396 Charcoal 1-131 not provided by Analytics for this study 215.

1.13 94.2 0.90

148, 1.14 81.8 1.09 192 0.89 126 1.02 189 0.84 124.

1.06 pCi 96.5 June 2011 E7851-3961 Milk E7852-396 Milk Sr-89 pCi/L Sr-90 pCi/L 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 96.7 13.8 110 68.1 186 164 140 141 136 128 263 189 96.3 103 15.6 103.0 79.9 206 190 138 152 138 123 261 195 1.00 0.94 0.88 1.07 0.85 0.90 0.86 1.01 0.93 0.99 1.04 1.01 0.97 A

A A

84

TABLE F-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 3)

Identification Reported Known Ratio (c) -

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

June 2011 E7854-396 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi September 2011 E7853-396 Charcoal E8070-396 Milk E8071-396 Milk E8073-396 AP 1-131 pCi Sr-89 pCi/L Sr-90 pCi/L 1-131 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 49.9 42.9 95.6 110 104 102 83.8 74.0 90.7 81.3 74.5 73.9 62.0 66.1 140 140 119 104 76.2 86.1 102 90.8 13.2 14.7 74.2 89.2 66.9 66.7 249 226 116 128 106 114 95.4 97.5 147 151 53.1 54.8 175 180 150 157 66.6 67.5 263 229 139 130 110 115 108 98.6 152 153 57.5 55.5 190 183 156 159 1.16 0.87 1.02 1.13 1.12 1.01 0.94 1.00 1.14 0.89 1.12 0.90 0.83 1.00 1.10 0.91 0.93 0.98 0.97 0.97 0.97 0.96 0.99 1.15 1.07 0.96 1.10 0.99 1.04 1.04 0.98 0.96 A

A A

A E8072-396 Charcoal 1-131 pCi 77.6 80.6 85

TABLE F-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Value Evaluation Month/Year Number

,Matrix Nuclide Units Value (a)

(b)

TBE/Analytics (d)

December, 2011 E8230-396 Milk Milk E8233-396 AP Sr-89 Sr-90 1-131 Ce-i141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi 93.3 93.1 12.7 15.4 82.5 90.2 not provided 465 566 142 171 185 210 177 221 208 241 164 183 259 291 224 270 1.00 A

0.82 A

0.91 A

by Analytics for this study 0.82 A

0.83 A

0.88 A

0.80 A

0.86 A

0.90 A

0.89 A

0.83 A

not provided by Analytics for this study 344 368 0.93 A

105 111 0.95 A

129 137 0.94 A

145 144 1.01 A

137 157 0.87 A

119 119 1.00 A

145 190 0.76 W

168 176 0.95 A

December 2011 E8232-396 Charcoal 1-131 100 89.5 1.12 A

(1) Sample appears to be biased high. Corrective Action evaluated after the 2nd Quarter Analytics PE sample; no action required. NCR'11-13 (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 (c)

(d) volumetric measurements made during standard preparation.

Ratio of Teledyne Brown Engineering to Analytics results.

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.

86

TABLE F-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 1)

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

(b)

Limits (c)

May 2011 RAD-85 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 pCi/L 59.8 63.2 51.1 - 71.2 pCi/L 42.5 42.5 31.3 - 48.8 pCi/L 73.3 75.3 63.0 - 82.8 pCi/L 64.9 72.9 59.5 - 80.2 pCi/L 74.6 77.0 69.3 - 87.4 pCi/L 87.8 88.8 79.9 - 100 pCi/L 103 98.9 89.0-118 pCi/L 64.1 50.1 26.1 - 62.9 pCi/L 51.8 49.8 33.8 - 56.9 pCi/L 27.4 27.5 22.9 - 32.3 pCi/L 38.5 39.8 32.2 - 44.4 8870-pCi/L 10057 10200 11200 A

A A

N (1)

A A

MRAD-14 Filter Gr-A pCi/filter 79.7 74.3 38.5-112.

A November 2011 RAD-87 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat pCi/L 81.0 69.7 56.9 - 77.9 pCi/L 35.5 41.4 30.2 - 47.2 pCi/L 90.7 96.9 81.8-106 pCi/L 36.6 33.4 26.3 - 36.7 pCi/L 44.7 44.3 39.4 - 51.7 pCi/L 118.7 119 107-133 pCi/L 80.2 76.8 68.9 - 92.5 pCi/L 34.2 53.2 27.8 - 66.6 pCi/L 39.3 45.9 30.9 - 53.1 pCi/L 22.9 27.5 22.9 - 32.3 pCi/L 46.8 48.6 39.4 - 54.0 15200 -

pCi/L 15733 17400 19100 N (2)

A A

A H-3 MRAD-15 Filter Gr-A pCi/filter 44.6 58.4 30.3 -87.8 (1) The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio of 1.16 fell within acceptable range of +/- 20%. No action required. NCR 11-16 (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 A

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.

87

TABLE F-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 2)

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

(b)

Range (c)

March 2011 11 -MaW24 Water 11-GrW24 Water 11 -MaS24 Soil 11-RdF24 AP Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Gr-A Gr-B Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L BqIL Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 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 19.1 29.0 0.139 23.9 265 31.8 94.8 9.64

-0.142 0.767 3.43 612 772 910 500 0.607 569 NR 1497 3.26 2.36 3.30 0.0765 2.84 NR 3.30 21.5 15.1 -28.0 29.4 20.6 - 38.2 (1) 24.6 17.2 - 32.0 243 170-316 31.6 22.1 -41.1 91 64-118 8.72 6.10-11.34 (1) 1.136 0.341 - 1.931 2.96 1.48-4.44 A

A A

680 758 927 482 540 160 1359 3.49 2.28 3.33 2.64 1.36 3.18 476 - 884 531 -985 649 - 1205 337 - 627 (1) 378 - 702 112 - 208 951 -1767 2.44-4.54 1.60-2.96 2.33 - 4.33 (1) 1.85 - 3.43 0.95-1.77 2.23-4.13 A

A A

A N (2)

A A

N (2)

A N (3)

A A

N (2)

A 11-GrF24 AP Gr-A Bq/sample Gr-B Bq/sample 0.101 1.23 11 -RdV24 Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 4.97 0.0356 10.8 4.89 6.42 NR 3.07 0.659 0.198 - 1.120 1.323 0.662 - 1.985 5.50 3.85 - 7.15 (1) 9.94 6.96 - 12.92 4.91 3.44 - 6.38 6.40 4.48 - 8.32 2.46 1.72-3.20 2.99 2.09 - 3.89 88

TABLE F-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 2)

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

Value (b)

Range (c)

September 2011 11 -MaW25 September 2011 11-GrW25 11 -MaS25 Water Water Soil AP Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Gr-A Gr-B Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L BqIL Bq/L Bq/L Bq/L BqcL Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bqlsam pie Bqlsam pie Bqfsam pie Bq/sam pie Bq/sample Bq/sam pie Bq/sample 16.0 0.0043 33.1 26.9 1011 23.2 147 15.8 27.3 19.1 13.4-24.8 (1) 36.6 25.6 - 47.6 29.3 20.5-38.1 1014 710-,1318 25.0 17.5 - 32.5 156 109-203 14.2 9.9-18.5 28.5 20.0 - 37.1 0.894 0.866 0.260 - 1.472 5.87 4.81 2.41 - 7.22

-0.213 1110 1290 731 987 753 276 1870

-0.043 3.09 5.36 3.41 0.067 1.84 5.17 979 1180 644 848 625 320 1560 (1) 685 - 1273 826-1534 451 - 837 594-1102 438 - 813 224-416 1092-2028 A

A A

A W

A A

W September 2011 11-RdF25 (1) 2.60 1.82 - 3.38 5.09 3.56 - 6.62 3.20, 2.24-4.16 (1) 1.67 1.17-2.17 4.11 2.88-5.34 11-GrF25 11-RdV25 AP Gr-A Gr-B Bq/sample 0.0058 Bq/sample

-0.01 (1)

(1)

Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sam pie 0.0081 4.94 0.0639 3.36 5.89 1.31 6.54 4.71 3.38 5.71 1.26 6.39 (1) 3.30.- 6.12 (1) 2,37 - 4.39 4.00 - 7.42 0.88-1.64 4.47 - 8.31 A

A A

Footnotes on next page 89

(1) False positive test.

(2) Evaluated as failed due to not reporting a previously reported analyte. NCR 11-11 (3) The filter for Gross Alpha was counted on the wrong side. Recounted on the correct side resulted in acceptable results. NCR 11-11 (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.

90

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