Text

Independent Spent Fuel Storage Installation (Isfsi), Submittal of 2012 Annual Radiological Environmental Operating Report
	ML13114A056
Person / Time
Site:	North Anna
Issue date:	04/16/2013
From:	Gerald Bichof; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	13-175
	Download: ML13114A056 (87)
	v • d • e

417i VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 16, 2013 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.

NAPS/JHL 13-175 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. I AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c, enclosed is the 2012 Annual Radiological Environmental Operating Report.

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

If you have any questions or require additional information, please contact Page Kemp at (540) 894-2295.

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

~~jB9~S

Serial No.13-175 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 L

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2012 to December 31, 2012 Prepared by:

Reviewed by:

Approved by:

Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station George R. Simmons Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B. Evansr:

Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2

PD mniin North Anna Power Station 2012 Annual Radiological Environmental Operating Report

.3 Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2012 to December 31, 2012 Prepared by Dominion, North Anna Power Station

I V ~

Table of Contents

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

4

2. PRO G RA M D ESCRIPTION......................................................................................................

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

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

8

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

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

22 3.2 A nalytical Results of 2012 REM P Sam ples...................................................................

32

4. D ISCU SSIO N O F RESU LTS....................................................................................................

60 4.1 G am m a Exposure Rate...................................................................................................

60 4.2 A irborne G ross Beta.........................................................................................................

62 4.3 A irborne Radioiodine......................................................................................................

63 4.4 A ir Particulate G am m a......................................................

63 4.5 A ir Particulate Strontium.................................................................................................

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

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

64 4.8 Cow M ilk..............................................................................................................................

64 4.9 Food Products and V egetation........................................................................................

65 4.10 W ell W ater..........................................................................................................................

65 4.11 River W ater.........................................................................................................................

65 4.12 Surface W ater......................................................................................................................

66 4.13 Bottom Sedim ent................................................................................................................

67 4.14 Shoreline Soil......................................................................................................................

68 4.15 Fish......................................................................................................................................

68

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

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

70 A PPEN D ICES.....................................................................................................................................

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

73 APPENDIX B:

SUMMARY

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

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1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2012 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 5.5.2. Radioactivity levels from January 1 through December 31, 2012, 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 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 2012 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 2012 was 2600 pCi/liter.

Zn-65 was reported in one precipitation 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 3050 pCi/liter.

No plant related isotopes were detected in quarterly precipitation samples. 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. Cs-137 was detected in the control station at a level of 157 pCi/kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. This Cs-137 level is consistent with historic levels. No plant related isotope was detected in the indicator locations 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 collected in 2012.

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j The terrestrial exposure pathway includes milk and food/vegetation products. No plant related radioisotopes were detected in any milk samples.

Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data. Cs-137 was reported in one vegetation sample at the 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.

Therefore, 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 2012, 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 2012 was 0.27 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 2012 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 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 the 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 utilized for processing the TLDs. Teledyne Brown Engineering Environmental Services (TBE) is utilized 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

k 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 2012 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 2012 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 2012.

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TABLE 2-1 North Anna Power Station - 2012 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Sample Media Environmental Thermoluminescent Dosimetry (TLD)

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

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

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

"Aspen Hills" Elk Creek NAPS Access Rd.

Station 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-I 1/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 Distance 0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.36 Direction NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW N

N NN'E NNE NE NE ENE ENE E

E ESE ESE SE SE SSE SSE S

TABLE 2-1 North Anna Power Station

-2012 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO.

1 Degrees 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Collection Frequency Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control

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

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

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

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TABLE 2-1 North Anna Power Station - 2012 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Sample Media Environmental Thermoluminescent Dosimetry (TLD)

Location Elk Creek Church NAPS Access Rd.

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

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

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

Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA Station S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 1.55 0.24 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

SSW SSW SW SW WSW WSW W

W WNW WNW NW NW NNW NNW SSE NW WSW WSW Degrees 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control Control Airborne Particulate and Radioiodine 01 OIA 03 04 05 05A 06 07 0.20 0.64 7.10 5.10 4.20 2.04 4.70 7.30 NE SE WSW WNW NNE N

ESE SSE 420 1380 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly

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

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

- - Air Sample Station at OIA was added in October 2007.

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TABLE 2-1 North Anna Power Station - 2012 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Sample Media Airborne Particulate and Radioiodine Location End of Route 685 Route 700 "Aspen Hills" Orange, VA Station 21 22 23 24 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)

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

Lake Anna (upstream)

(Route 669 Bridge) 08 3.37 SSE 1480 Monthly 09A North Anna River (downstream) 11 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE 1380 Monthly Control Biology Lab Biology Lab 01A 01A Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

Waste Heat Treatment Facility (Second Cooling Lagoon)

NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 3.37 SSE 1480 Semi-Annually 09A 11 12.90 WNW 2950 Semi-Annually 5.80 SE 1280 Semi-Annually Control Shoreline Soil Soil 08 **

3.37 SSE 1480 Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years

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

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

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

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TABLE 2-1 North Anna Power Station - 2012 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)

"Aspen Hills" Orange, VA Lakeside Dairy Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Orange 05A 06 07 21 22 23 24 2.04 4.70 7.30 1.00 1.00 0.93 22.00 N

ESE SSE WNW WSW SSE NW 1150 1670 3010 2420 1580 3250 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Control Milk Fish 12A 08 7.50 NW 3.37 SSE 16.5 NW 3100 Monthly 1480 Semi-Annually 3120 Semi-Annually 25 Control Food Products (Vegetation)

Stagecoach Road Route 614 Route 629/522 Aspen Hills "Historic Lane" 14B 15 16 23 26 1.22 1.37 12.60 0.93 1.15 NNE SE NW SSE S

400 1330 3140 1580 1720 Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Control

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

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

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

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.C TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY 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) 2 "d 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/m 3 pCi/m 3

pCi/m 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.

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1. 17-TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS River Water Quarterly(a) 2nd Quarter Composite Ground Water (Well Water)

Quarterly Quarterly(a) 2"d 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 1-131Vd)

Cs-134 Cs-137 Ba-14 0(d)

La-140(d) 15 2000 (b)

(b) 15 30 15 15 30 30 15 10(c) 15 18 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 Semi-Annual Composite ()

4 pCi/L pCi/L 15 30 15 15 30 30 15 15 18 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 4.ZA XPT F MrbT A 1RRlPnWjVN IW

'V 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 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.

15

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

IA 2

3 4

5 5A 6

7 8

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

(a)

(a) 01,NE-5/37 O1A,SE-13/45 02,SSW-20/52 03,C-5/6 04 05 05A,N-2/34 06,ESE-12/44 07, C-1/2 08-Water, Fish, Sediment, Shoreline Soil 09A-Water sample, Sediment 11-River Water, Sediment 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-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E-10/42 (a)

(a)

(a)(b)

(c)

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

(b) In Orange (c) In Lake Orange 16

ESE L~g~d

5/4 Sc* 1 ci226 W

SE Figure 1. North Anna Site Radiological Monitoring Locations 17

I 18

19

I 20

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 - 2012 Docket No. 50-338/339 Page 1 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD(')

Mean Reported Sampled (Unit)

Total (pCi/unit)

Range Name Distance Mean Mean Measure-Typ I No..

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

(Sector TLDs)

Direct Radiation (mR/std. Month)

(Pre-operational TLDs)

Direct Radiation (mR/std. Month)

(Emergency Sector TLDs)

Direct Radiation (mR/std. month)

(Environmental TLDs)

Direct Radiation (mR/std. Month)

(Annual TLDs)

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

Gamma Dose Gamma Dose 256 2

4.2(256/256)

(1.4-8.6) 2 2.5(16/16)

(1.1-3.7) 29/61 0.52 mi.

7.0(8/8)

NW (5.3-8.5) 3.2(16/16)*

(2.2-3.8) 3.2(16/16)*

(2.2-3.8) 0 32 C-1/2 7.3 mi.

SSE 3.0 (8/8)

(2.0-3.7) 0 Gamma Dose 40 2

4.9(40/40)

EPSP-0.37 mi.

7.2(8/8)

(2.9-8.3) 09/10 ENE (6.1-8.3) 3.2(16/16)*

(2.2-3.8) 0 Gamma Dose 48 2

3.2(44/44)

(2.1-4.5) 06 4.7 mi.

4.5(4/4)

ESE (3.6-4.9) 3.0(4/4)

(2.1-3.8) 0 Gamma Dose Gross Beta 12 2

4.0(11/11)

(3.0-6.1) 01 0.20 mi.

6.1(1/1)

NE (6.1) 3.4(1/1)

(3.4) 0 676 0.01 16.0(623/624)

(3.03-36.8) 05 0.2 mi.

18.4(51/52) 15.5(52/52)

NNE (6.65-36.8)

(6.89-31.9) 0 Air Iodine (pCi/m 3) 1-131 676 0.07 (0/624)

N/A N/A.

N/A N/A 0

Airborne Particulates (IE-03 pCi/m 3)

Gamma 52 Be-7 52 137(48/48) 21 1.0 mi.

208(4/4) 121(4/4)

(80.7-430)

WNW (98.4-430)

(105-147) 0 0

Cs-134 52 0.05 (0/48)

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

(I) 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 - 2012 Docket No. 50-338/339 Page 2 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Total (pCi/unit)

Mean Name Distance Mean Mean Measure-T e

No..

I Range I Direction Range Range ments Airborne Particulates (IE-03 pCi/m 3)

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

(0/12)

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

(0/1)

(0/1) 0 0

0 Sr-90 13 N/A N/A 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 H-3 Semiannual Gamma Be-7 Mn-54 Fe-59 150 180 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 4.02(6/12)

(2.42-7.73)

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 12 4

4.02(6/12)

(2.42-7.73) 2 2000 (0/2) 01A 0.64 mi.

SE N/A N/A 0

0 2

2 2

2 15 30 (0/2)

(0/2)

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

0 0

0 Co-58 2

15 (0/2)

N/A N/A

Soil Samples required triennially. Last samples were taken 2010. Not required in 2012.

24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 Docket No. 50-338/339 Page 3 of 9 All Indicator Indicator Location Control Non-Medium or Analyi 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 I

I I ~No.IIII Co-60 2

15 (0/2)

N/A N/A N/A Precipitation (pCi/liter)

Zn-65 2

30 3.76(1/2)

(3.76) 01A 0.64 mi.

3.76(1/2)

SE (3.76)

Zr-95 2

30 (0/2)

Nb-95 2

15 (0/2) 1-131 2

(0/2)

Cs-134 2

15 (0/2)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 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 Cs-137 2

Ba-140 2

La-140 2

Th-228 2

0 0

0 18 (0/2)

(0/2)

(0/2) 0

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

25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 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)

Tpe No.

Range I

IDirection I Range Range ments Gamma 12 Milk (pCi/liter)

K-40 12 1-131 12 1

1350(12/12)

(1240-1480)

(0/12)

Cs-137 12 18 (0/12)

Ba-140 12 60 (0/12)

La-140 12 15 (0/12) 12A 7.50 mi.

NW 12A N/A.

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1350(12/12)

(1240-1480)

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

0 0

Sr-89 (Quarterly)

Sr-90 (Quarterly) 4 (0/4)

(0/4) 4 26

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 Docket No. 50-338/339 Page 5 of 9 All Indicator Indicator Location Control Non-Medium or Analsis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Total (pCi/unit)

Mean Name Distance Mean Mean Measure-Type No. I Range I Direction Range Range ments Food Vegetation (pCi/kg) (wet)

Gamma Be-7 35 35 K-40 35 1-131 Cs-134 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 35 35 35 4

3 3

3 3

80 2000 60 60 1520(28/28)

(460-4550) 6280(28/28)

(3650-9050)

(0/28)

(0/28) 33.8(1/28)

(33.8)

(0/4)

(0/3)

(0/3) 26 1.15 S

15 1.37 SE N/A N/A N/A N/A 23 0.93 SSE 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 1970(7/7)

(1220-3330) 6980(7/7)

(6000-8580)

N/A N/A 33.8(1/28)

(33.8)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 969(7/7)

(268-2200) 4910(7/7)

(3020-8600)

(0/7)

(0/7) 15 30 15 15 30 30 15 0

0 0

0 (0/7)

N/A N/A N/A N/A N/A N/A N/A N/A N/A 4

10 (0/4)

Missed gamma analysis on 2"d Quarter 2012 Ground water well

- Activity listed is due to forced activity calculation. Nuclide was not identified during analysis. False positive 27

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 Docket 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)

River Water (pCi/liter)

Cs-134 3

15 Cs-137 3

18 Ba-140 3

60 La-140 3

15 Sr-89 I

Sr-90 1

Tritium 4

2000 Gamma 12 Mn-54 12 15 Fe-59 12 30 Co-58 12 15 Co-60 12 15 Zn-65 12 30 Zr-95 12 30 Nb-95 12 15 1-131 12 1

Cs-134 12 15 Cs-137 12 18 (0/3)

(0/3)

(0/1)

(0/1) 3050(4/4)

(2040-4340)

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

SE N/A N/A N/A N/A N/A (0/3)

N/A N/A N/A N/A N/A N/A N/A N/A 3050(4/4)

(2040-4340)

(0/12)

N/A (0/12)

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

(0/12)*

0 0

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

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 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 Direction 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 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 12 12 8

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

(0/12)

(0/1)

(0/1) 2600(4/4)

(2260-2790)

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

SSE N/A N/A N/A N/A 2600(4/4)

(2260-2790)

(0/12)*

(0/1)*

(0/4) 2000 15 30 15 15 0

0 0

(0/12)

N/A N/A N/A N/A N/A N/A N/A N/A 24 30 (0/12) 24 30 (0/12) 24 30 (0/12) 24 1

(0/12) 24 15 (0/12) 24 18 (0/12) 24 60 (0/12) 24 15 (0/12)

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

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 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 No.

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

Sediment Silt (pCi/kg)

Sr-89 Sr-90 1

1 (0/1)

(0/1)

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

(0/1)

Gamma 6

K-40 6

16500 (4/4)

(12400-22100)

Cs-134 6

150 (0/4) 08 3.37 mi.

17300(2/2)

SSE (12400-

.22100)

N/A N/A N/A 12700(2/2)

(12500-12800)

(0/2)

(176) 112(1/2)

(112) 1680(2/2)

(1300-2060)

Cs-137 6

180 (0/4)

N/A N/A.

N/A Ra-226 6

Th-228 6

Th-232 6

3020(4/4)

(2390-4130) 1860(4/4)

(1260-2400) 1700 (4/4)

(1160-2130) 08 3.37 mi.

3260(2/2)

SSE (2390-4130) 08 3.37 mi.

2040(2/2)

SSE (1680-2400) 08 3.37 mi.

1835(2/2)

SSE (1540-2130) 683(2/2)

(623-743) 699(2/2)

(584-813)

(0/1)

(0/1) 0 0

0 0

0 (Annually)

Sr-89 Sr-90 3

(0/2)

N/A N/A N/A N/A N/A N/A 3

Shoreline Soil (pCi/kg) (dry)

Gamma 2

K-40 2

2280(2/2)

(2000-2550) 08 3.37 mi.

2280(2/2)

SSE (2000-2550)

Cs-134 2

150 (0/2)

N/A N

Cs-137 2

180 157(1/2) 08 3.37 mi.

SSE Ra-226 2

1210(1/2) 08 3.37 mi.

(1210)

SSE (0/2) 157(1/2)

(157) 1210(1/2)

(1210)

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

30

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2012 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 IDirectioni Range Range ments Shoreline Soil (pCi/kg) (dry)

Fish (pCi/kg) (wet)

Th-228 2

Th-232 (Annually)

Sr-89 Sr-90 Gamma K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 2

1 8

8 8

574(2/2)

(439-708) 533(2/2)

(399-666)

(0/1)

(0/1) 2320(4/4)

(1930-3030) 130 (0/4) 260 (0/4) 130 (0/4) 130 (0/4) 260 (0/4) 130 (0/4) 150 (0/4) 08 3.37 mi.

SSE 08 3.37 mi.

SSE N/A NA N/A NA 574(2/2)

(439-708) 533(2/2)

(399-666)

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

0 0

0 08 3.37 mi.

SSE N/A NA N/A NA N/A NA N/A NA N/A NA N/A NA N/A NA 2320(4/4)

(1930-3030)

N/A N/A N/A N/A N/A N/A N/A 1740(4/4)

(1190-2560)

(0/4)

(0/4) 0 0

0 0

31

3.2 Analytical Results of 2012 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 2cy error.

Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For clarity of this report only detectable results are presented.

TBE's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program",

(November

1979, Revision 1) and the North Anna ODCM.

Data are given according to sample type as indicated below.

1.

Gamma Exposure Rate

2.

Air Particulates, Gross Beta Radioactivity

3.

Air Particulates, Weekly 1-131

4.

Air Particulates, Quantitative Gamma Spectra

5.

Air Particulate Strontium

6.

Soil

7.

Precipitation

8.

Cow Milk

9.

Food Products and Vegetation

10.

Well Water

11.

River Water

12.

Surface Water

13.

Bottom Sediment/Silt

14.

Shoreline Soil

15.

Fish

'Analytical results are handled as recommended by HASL ("Reporting ofAnalytical Results from HASL, letter by Leo B.

Higginbotham) and NUREG/CR-4007 (Sept. 1984).

32

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Station Page 1 of 4 Quarterly*

Average

+/- 2 s.d.

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-10 E-42 ESE-11 ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 4.7 4.8 3.8 3.7 6.7 6.4 4.7 5.0 4.2 4.3 3.0 3.7 4.9 5.4 3.9 3.3 4.3 5.8 3.8 3.9 4.1 3.9 3.6 4.2 4.0 4.7 7.1 6.1 3.8 4.8 2.2 2.9 3.8 3.7 2.4 1.9 5.2 5.0 3.1 2.6 3.7 4.1 2.2 2.6 4.0 3.8 2.3 2.8 3.3 3.2 4.6 2.9 3.2 3.0 3.1 2.9 3.0 2.8 6.4 5.1 3.9 3.5 2.0 1.8 3.6 4.2 2.9 2.9 6.5 6.8 4.4 4.2 4.6 4.6 2.9 3.1 5.0 4.9 3.0 2.7 4.7 4.9 4.3 4.4 4.0 3.9 5.0 4.4 4.1 4.2 6.4 6.8 4.4 5.0 2.9 2.7 5.6 5.7 4.0 3.5 8.6 8.5 5.0 5.3 5.8 5.4 3.8 4.3 5.2 6.0 3.2 3.3 6.1 4.8 4.9 5.3 4.7 4.9 5.3 5.2 5.0 5.1 7.7 7.6 5.3 5.1 3.5 3.4 4.5

+/- 1.7 3.1

+/- 1.5 6.7

+/- 2.6 4.3

+/- 1.9 4.6

+/- 1.4 3.2

+/- 1.4 4.9

+/- 1.4 3.1

+/- 1.0 4.6

+/- 2.1 4.3

+/- 1.5 4.0

+1-1.3 4.2

+/- 1.9 4.1

+/- 1.7 6.7

+/- 1.7 4.5

+/- 1.4 2.7

+/- 1.3

Average of collocated TLDs.

33

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

Page 2 of 4 Station Average

+/- 2 s.d.

s-17 S-49 S-18 S-50 SSW-19 SSW-51 SSW-20 SSW-52 SW-21 SW-53 SW-22 SW-54 WSW-23 WSW-55 WSW-24 WSW-56 W-25 W-57 W-26 W-58 WNW-27 WNW-59 WNW-28 WNW-60 NW-29 NW-61 NW-30 NW-62 NNW-31 NNW-63 NNW-32 NNW-64 5.0 5.2 2.6 2.1 5.7 6.4 2.3 2.2 4.3 4.9 4.8 4.2 5.2 5.6 3.6 3.5 6.8 6.8 2.5 4.2 2.3 4.0 2.7 2.4 6.7 8.5 1.7 1.7 3.4 3.7 3.2 3.3 3.9 3.7 1.5 1.4 5.3 6.9 1.6 1.5 3.8 5.5 3.7 3.2 4.0 3.8 3.0 2.7 5.5 6.6 2.9 2.3 2.4 2.0 2.0 2.2 5.3 5.4 1.8 1.4 2.2 2.4 2.7 2.6 4.6 5.2 3.0 2.3 6.8 6.0 2.4 2.2 3.9 4.5 4.4 4.3 5.1 3.8 4.3 4.2 6.9 6.5 3.0 2.9 3.0 3.1 2.0 2.1 7.1 6.5 1.9 1.4 2.7 3.1 3.9 4.1 6.4 3.7 2.4 2.8 6.9 7.7 3.0 2.9 5.2 7.6 5.1 4.6 5.8 5.9 4.3 4.6 7.8 7.6 4.3 3.2 3.7 3.6 3.7 3.4 8.2 8.3 2.6 3.0 3.9 4.4 4.4 2.7 4.7 +/-

1.9 2.3 +/-

1.2 6.5 +/-

1.5 2.3 +/-

1.1 5.0 +/-

2.4 4.3 +/-

1.2 4.9 +1-1.8 3.8 +/-

1.4 6.8 +/-

1.4 3.2 +/-

1.5 3.0 +/-

1.5 2.6 +/-

1.3 7.0 +/-

2.5 1.9 +/-

1.1 3.2 +/-

1.5 3.4 +/-

1.4 4.2 +/-

1.6 Mean

Average of collocated TLDs.

34

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Page 3 of 4 Station C-1 C-2 C-3"*

C-4"*

C-5 C-6 C-7"*

C-8"*

3.4 2.9 3.1 2.9 2.0 2.0 3.3 3.7 2.0 3.1 2.2 2.5 1.1 1.2 2.6 3.1 3.6 3.4 3.3 3.6 3.5 3.6 2.9 3.8 6.1 5.9 3.0 2.5 2.8 3.2 2.0 2.6 3.6 3.6 4.5 4.1 3.8 4.4 4.4 4.1 3.5 3.6 6.7 6.8 3.7 3.6 3.7 3.7 2.4 2.6 4.1 3.8 Mean Indicator Control**

5.2 6.1 4.5 5.4 4.9 5.3 5.6 4.9 8.2 8.3 Quarterly*

Average

+/-2 s.d.

3.0

+/- 1.1 3.0

+/- 1.1 2.0

+/- 1.2 3.5

+/- 0.9 2.5

+/-

3.2

+/-

1.5 1.1 EPSA-Ol**

EPSA-02***

EPSF.03~**

EPSF-04***

EPSR-05***

EPSR-06***

EPSJ-07***

EPSJ-08***

EPSP-09***

EPSP-1 0**

4.6 4.5 4.6 5.5 4.3 4.5 3.8 4.5 8.2 7.3 4.5

+/- 1.7 4.4

+/- 1.6 4.3

+/- 1.2 4.1

+/-

1.7 7.2

+1-1.9 4.9

+/- 2.8 Mean

Average of collocated TLDs.

- Control Station

- - Emergency Plan TLDs.

35

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 4 of 4 First Quarter Station 12/282011 3/28/2012 STA-01 4.5 STA-02 2.1 STA-03 2.2 STA-04 2.4 STA-05 3.8 STA-05A 2.9 STA-06 4.6 STA-07 3.0 STA-21 3.4 STA-22 3.6 STA-23 4.0 STA-24*

2.9 Second Quarter Third Quarter Fourth Quartei 3/28/2012 6/26/2012 9/25/2012 6/26/2012 9/25/2012 12/26/2012 3.4 3.8 5.6 1.4 2.2 3.0 1.5 1.9 2.7 1.2 1.9 3.2 2.6 3.2 3.8 2.6 3.4 3.0 3.6 4.7 4.9 2.5 3.3 3.5 2.1 3.2 3.1 2.5 3.2 6.1 3.1 4.4 4.9 2.1 3.1 3.8 Mean - Indicator Locations Quarterly Average

+/- 2 s.d.

4.3

+/-

2.2

+/-

2.1

+/-

2.2

+/-

3.4

+/-

3.0

+/-

4.5

+/-

3.1

+/-

3.0

+/-

3.9

+/-

4.1

+/-

3.0

+/-

3.2

+/-

Annual TLD 1.9 1.3 1.0 1.7 1.1 0.7 1.2 0.9 1.2 3.1 1.5 0.7 1.1 6.1 3.2 3.3 3.1 3.0 3.5 4.8 3.9 3.8 4.4 6.0 3.4 4.1

+/-

2.2

Control 36

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3]

page 1 of 4 Period Ending 01/03/12 01/10/12 01/17/12 01/24/12 01/31112 02/07/12 02/14/12 02/21/12 02/28/12 03/06/12 03/13/12 03/20/12 03/28/12 04/04/12 04/10/12 04/17/12 04/24/12 05/01/12 05/08/12 05/15/12 05/22/12 05/29/12 06/06/12 06/12/12 06/19/12 06/26/12 I

Station 01 Station Station Station Station Station I

l l

1.53E+01 1.26E+01 1.14E+01 1.11E+01 1.27E+01 1.34E+01 1.17E+01 1.42E+01 1.53E+01 1.66E+01 1.50E+01 2.13E+01 8.92E+00 9.37E+00 1.52E+01 1.34E+01 1.38E+01 1.41E+01 9.96E+00 1.34E+01 5.70E+00 7.77E+00 1.06E+01 1.06E+01 1.02E+01 1.14E+01

+/-

3.20E+00 1.60E+01 3.14E+00 2.76E+00 2.62E+00 2.49E+00 2.79E+00 2.51E+00 2.92E+00 2.80E+00 3.00E+00 2.69E+00 3.04E+00 2.21E+00 2.39E+00 3.08E+00 2.70E+00 2.62E+00 3.13E+00 2.60E+00 2.73E+00 2.40E+00 2.29E+00 2.27E+00 2.91E+00 2.43E+00 2.81 E+00 1.61 E+01 1.29E+01 1.27E+01 2.07E+01 1.84E+01 1.47E+01 1.72E+01 1.46E+01 1.93E+01 1.57E+01 1.49E+01 1.04E+01 1.12E+01 1.34E+01 1.18E+01 1.39E+01 1.69E+01 1.12E+01 1.46E+01 9.76E+00 8.81E+00 1.26E+01 1.51E+01 1.01E+01 1.93E+01 02

+/-

I 3.26E+00 3.31 E+00 2.83E+00 2.72E+00 2.92E+00 3.04E+00 2.67E+00 3.07E+00 2.78E+00 3.13E+00 2.72E+00 2.72E+00 2.29E+00 2.51E+00 2.97E+00 2.62E+00 2.62E+00 3.26E+00 2.67E+00 2.81E+00 1.85E+01 1.19E+01 1.14E+01 1.09E+01 1.89E+01 1.31E+01 1.03E+01 1.79E+01 1.48E+01 1.55E+01 1.29E+01 1.74E+01 8.08E+00 8.95E+00 1.18E+01 1.24E+01 1.03E+01 1.28E+01 1.01E+01 1.25E+01 3.41 E+00 3.11E+00 2.75E+00 2.63E+00 2.83E+00 2.78E+00 2.46E+00 3.06E+00 2.76E+00 2.97E+00 2.60E+00 2.86E+00 2.12E+00 2.42E+00 2.88E+00 2.65E+00 2.42E+00 3.07E+00 2.56E+00 2.68E+00 2.53E+00 2.32E+00 2.31 E+00 2.76E+00 2.39E+00 3.04E+00 1.872+01 1.40E+01 1.24E+01 7.45E+00 1.78E+01 1.26E+01 1.41E+01 1.58E+01 1.54E+01 1.79E+01 1.86E+01 2.08E+01 1.08E+01 9.08E+00 1.36E+01 1.15E+01 1.44E+01 1.79E+01 1.10E+01 1.36E+01 7.63E+00 3.43E+00 1.21 E+01 1.21E+01 1.21E+01 1.78E+01 I

04 I

05

+/- 3.44E+00 2.10E+01

+/- 3.51E+00

+/-

3.21E+00 1.31E+01

+/- 3.17E+00

+/- 2.81E+00 1.69E+01

+/- 3.04E+00

+/- 2.41E+00 1.51E+01

+/- 2.85E+00

+/- 2.77E+00 2.30E+01

+/- 3.03E+00

+/- 2.74E+00 1.93E+01

+/- 3.09E+00

+/-

2.67E+00 1.73E+01

+/- 2.82E+00

+/- 2.98E+00 1.72E+01

+/- 3.07E+00

+/- 2.80E+00 1.86E+01

+/- 2.97E+00

+/- 3.06E+00 1.82E+01

+/- 3.08E+00

+/- 2.90E+00 1.61E+01

+/- 2.75E+00

+/-

3.02E+00 2.18E+01

+/- 3.07E+00

+/- 2.29E+00 9.98E+00

+/- 2.26E+00

+/-

2.41E+00 1.15E+01

+/-

2.54E+00

+/- 2.98E+00 1.38E+01

+/- 3.13E+00

+I-2.60E+00 1.69E+01

+/- 3.07E+00

+/- 2.65E+00 1.31E+01

+/- 2.58E+00

+/- 3.31E+00 1.70E+01

+/- 3.26E+00

+/- 2.63E+00 1.31E+01

+/- 2.76E+00

+/- 2.75E+00 1.29E+01

+/- 2.71E+00

+/- 2.52E+00 8.88E+00

+/- 2.59E+00

+/-

1.99E+00 9.32E+00

+/- 2.39E+00

+/- 2.36E+00 1.32E+01

+/- 2.42E+00

+/- 2.99E+00 1.24E+01

+/- 3.00E+00

+/-

2.54E+00 1.05E+01

+/- 2.45E+00

+/- 3.11E+00 1.93E+01

+/- 3.19E+00 I

1.24E+01 1.28E+01 1.06E+01 1.58E+01 1.89E+01 1.28E+01 1.44E+01 1.94E+01 1.49E+01 1.59E+01 1.65E+01 1.04E+01 1.00E+01 1.99E+01 1.57E+01 1.30E+01 1.72E+01 1.15E+01 1.60E+01 8.96E+00 9.32E+00 1.27E+01 1.42E+01 1.10E+01 2.21E+01 3.05E+00 3.16E+00 2.71 E+00 2.88E+00 2.83E+00 2.76E+00 2.67E+00 3.17E+00 2.78E+00 2.96E+00 2.77E+00 2.29E+00 2.45E+00 3.49E+00 2.83E+00 2.58E+00 3.27E+00 2.68E+00 2.88E+00 2.59E+00 2.39E+00 2.39E+00 3.11E+00 2.48E+00 3.33E+00 1.95E+01 1.05E+01 9.51 E+00 1.24E+01 2.16E+01 1.06E+01 1.39E+01 1.46E+01 1.32E+01 4.24E+00 1.53E+01 2.03E+01 1.11E+01 1.16E+01 1.52E+01 1.05E+01 1.14E+01 1.46E+01 1.11E+01 1.50E+01 4.89E+00 7.90E+00 1.11E+01 7.61 E+00 7.53E+00 1.45E+01 3.43E+00 3.05E+00 2.65E+00 2.70E+00 2.97E+00 2.92E+00 2.64E+00 2.94E+00 2.69E+00 1.64E+00 2.76E+00 3.00E+00 2.33E+00 2.54E+00 3.07E+00 2.54E+00 2.48E+00 3.15E+00 2.66E+00 2.83E+00 2.35E+00 2.30E+00 2.30E+00 2.71E+00 2.26E+00 2.96E+00 Station 07 E

2.64E+00 7.79E+00 2.36E+00 8.20E+00 2.38E+00 1.12E+01 3.16E+00 8.51E+00 2.42E+00 9.40E+00 3.18E+00 1.64E+01

Sample not obtained due to sampler not operating 37

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3]

page 2 of 4 Period Ending a

01/03/12 01/10/12 01/17/12 01/24/12 01/31112 02/07/12 02/14/12 02/21/12 02/28/12 03/06/12 03/13/12 03/20/12 03/28/12 04104/12 04/10112 04/17/12 04124/12 05/01/12 05/08/12 05/15/12 05/22/12 05/29/12 06/06/12 06/12/12 06/19/12 06/26/12 U

Station Station 21 I22 1.29E+01

÷/-

3.09E+00 1.43E+01

+/-

1.48E+01

÷/- 3.25E+00 1.12E+01

+/-

1.20E+01

÷/-

2.78E+00 1.03E+01

+/-

1.13E+01

÷/-

2.64E+00 1.21E+01

÷/-

1.82E+01

+/-

2.80E+00 1.87E+01

÷/-

1.69E+01

+/-

2.97E+00 1.74E+01 1/-

1.45E+01 4/-

2.66E+00 1.39E+01

÷/-

1.66E+01

+/-

3.04E+00 1.96E+01

÷/-

1.48E+01 4/-

2.77E+00 1.67E+01

+/-

1.73E+01

+/-

3.04E+00 1.81E+01

+/-

2.86E+00 1.55E+01

+/-

1.99E+01

+/-

2.97E+00 2.03E+01

+/-

1.01E+01

+/-

2.27E+00 9.19E+00

+/-

9.86E+00

+/-

2.43E+00 1.15E+01

+/-

1.33E+01

+/-

2.97E+00 1.36E+01

+/-

1.21E+01

+/-

2.63E+00 1.31E+01 1/-

1.33E+01

+/-

2.59E+00 1.21E+01

+/-

1.21E+01

+/-

3.03E+00 1.44E+01

+/-

1.22E+01

+/-

2.73E+00 1.25E+01

+/-

1.19E+01

+/-

2.65E+00 1.12E+01

+/-

7.32E+00

+/-

2.50E+00 7.02E+00

+/-

8.59E+00

+/-

2.35E+00 1.07E+01

+/-

1.02E+01

+/-

2.25E+00 1.29E+01

+/-

1.05E+01

+/-

2.90E+00 1.26E+01

+/-

1.08E+01

+/-

2.46E+00 8.40E+00

+/-

1.56E+01

+/-

3.OOE+00 1.91E+01

+/-

Station Station I

I 24*

I olA I

Station Station 05A I

I 3.17E+00 3.08E+00 2.70E+00 2.68E+00 2.82E+00 3.OOE+00 2.64E+00 3.18E+00 2.87E+00 2.37E+00 2.72E+00 2.99E+00 2.21 E+00 2.53E+00 2.99E+00 2.69E+00 2.53E+00 3.15E+00 2.73E+00 2.61E+00 2.48E+00 2.48E+00 2.40E+00 3.02E+00 2.32E+00 3.17E+00 1.60E+01 1.71 E+01 1.03E+01 1.66E+01 2.01E+01 1.70E+01 1.71E+01 1.86E+01 1.47E+01 1.57E+01 1.66E+01 2.05E+01 1.11E+01 1.32E+01 1.43E+01 1.36E+01 1.49E+01 1.60E+01 1.26E+01 1.59E+01 6.13E+00 7.62E+00 1.18E+01 1.48E+01 9.21 E+00 1.74E+01 3.26E+00 1.99E+01 3.35E+00 1.16E+01 2.70E+00 1.07E+01 2.92E+00 1.42E+01 2.90E+00 1.52E+01 2.97E+00 1.24E+01 2.81E+00 1.36E+01 3.13E+00 1.64E+01 2.76E+00 1.47E+01 2.96E+00 1.59E+01 2.78E+00 1.51E+01 3.01E+00 1.99E+01 2.32E+00 9.81E+00 2.86E+00 1.24E+01 3.03E+00 1.16E+01 2.72E+00 1.28E+01 2.68E+00 1.06E+01 3.22E+00 1.46E+01 2.74E+00 1.00E+01 2.87E+00 1.16E+01 2.42E+00 6.89E+00 2.29E+00 8.65E+00 2.34E+00 7.54E+00 3.14E+00 1.33E+01 2.37E+00 9.88E+00 3.09E+00 1.60E+01 3.47E+00 1.56E+01

+/-

3.22E+00 1.71E+01

+/

3.31E+00 3.10E+00 1.24E+01

+I-3.13E+00 1.13E+01

+/-

3.08E+00 2.71E+00 1.35E+01

+/-

2.87E+00 1.25E+01

+/-

2.81E+00 2.80E+00 1.27E+01

+/-

2.72E+00 1.16E+01

+/-

2.66E+00 2.63E+00 1.87E+01

+/-

2.82E+00 1.60E+01

+/

2.68E+00 2.73E+00 1.58E+01

+/-

2.91E+00 1.43E+01

+/

2.84E+00 2.62E+00 1.34E+01

+/

2.61E+00 1.35E+01

+/

2.61E+00 3.03E+00 1.77E+01

+/

3.09E+00 1.45E+01

+/-

2.94E+00 2.77E+00 1.51E+01

+/-

2.79E+00 1.29E+01

+/-

2.67E+00 2.97E+00 1.37E+01

+/-

2.86E+00 1.25E+01

+/-

2.79E+00 2.69E+00 1.61E+01

+/- 3.23E+00 1.52E+01

+I-2.70E+00 2.97E+00 1.35E+01

+I-2.64E+00 1.83E+01

+/-

2.90E+00 2.26E+00 8.97E+00

+1-2.21E+00 1.18E+01

+/-

2.36E+00 2.59E+00 9.70E+00

+/-

2.42E+00 1.15E+01

+/-

2.54E+00 2.85E+00 1.42E+01

+/-

3.03E+00 1.27E+01

+/-

2.93E+00 2.68E+00 1.05E+01

+/-

2.54E+00 1.14E+01

+I-2.60E+00 2.44E+00 1.12E+01

+/-

2.47E+00 1.15E+01

+I-2.49E+00 3.15E+00 1.35E+01

+/-

3.10E+00 1.72E+01

+/-

3.27E+00 2.59E+00 8.94E+00

+/

2.54E+00 3.03E+00

+/

1.09E+00 2.64E+00 9.73E+00

÷/

2.52E+00 1.26E+01

+/

2.70E+00 2.47E+00 6.07E+00 4/-

2.42E+00 4.89E+00

+/

2.35E+00 2.35E+00 8.66E+00

+/-

2.35E+00 9.39E+00 4/-

2.40E+00 2.09E+00 1.13E+01

+/

2.31E+00 1.01E+01

+/-

2.24E+00 3.06E+00 8.50E+00

+/-

2.78E+00 1.19E+01

+/

2.97E+00 2.41E+00 9.21E+00

+/-

2.37E+00 1.28E+01

+/-

2.58E+00 3.03E+00 1.33E+01

+/

2.90E+00 1.62E+01

+/-

3.04E+00

Control Station 38

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3]

page 3 of 4 tation 07 Period Ending 07/03/12 07/111/12 07/17/12 07/24/12 07/31112 08/07112 08114112 08/21/12 08/28/12 09/04/12 09/12/12 09119/12 09/25112 10102/12 10/10/12 10/16/12 10/24/12 10/31/12 11/07/12 11/13/12 11/21/12 11/27/12 12/04/12 12/11/12 12/18/12 12/26/12 Station Station Station Station Station Station S

1.60E+01 2.34E+01 1.38E+01 1.12E+01 1.61E+01 1.85E+01 1.41E+01 1.84E+01 2.22E+01 1.61E+01 1.51E+01 1.85E+01 1.72E+01 2.63E+01 1.88E+01 1.96E+01 2.01E+01 1.90E+01 7.95E+00 2.34E+01 2.20E+01 2.46E+01 2.68E+01 1.23E+01 1.99E+01 1.86E+01 01

+1-

+1-I I

2.83E+00 2.93E+00 2.99E+00 2.69E+00 2.76E+00 2.97E+00 3.02E+00 3.03E+00 3.26E+00 2.97E+00 2.49E+00 3.01E+00 3.19E+00 3.25E+00 2.86E+00 3.49E+00 2.76E+00 3.20E+00 2.35E+00 3.57E+00 2.99E+00 3.54E+00 3.40E+00 2.67E+00 3.02E+00 2.84E+00 1.84E+01 2.23E+01 1.44E+01 1.26E+01 1.59E+01 1.88E+01 1.77E+01 1.95E+01 1.81E+01 1.43E+01 1.06E+01 1.02E+01 1.76E+01 2.66E+01 2.22E+01 1.97E+01 2.18E+01 1.66E+01 9.61E+00 2.52E+01 2.55E+01 2.27E+01 2.84E+01 1.13E+01 2.53E+01 1.61E+01 2.96E+00 2.88E+00 3.03E+00 2.77E+00 2.74E+00 3.04E+00 3.13E+00 3.09E+00 3.06E+00 2.89E+00 2.23E+00 2.57E+00 3.21E+00 3.29E+00 3.01E+00 3.51E+00 2.84E+00 3.09E+00 2.45E+00 3.66E+00 3.14E+00 3.43E+00 3.48E+00 2.62E+00 3.28E+00 2.72E+00 1.78E+01 2.24E+01 8.92E+00 1.06E+01 1.41E+01 1.65E+01 1.65E+01 8.89E+00 1.49E+01 1.16E+01 1.38E+01 1.35E+01 1.63E+01 2.44E+01 2.10E+01 2.12E+01 1.55E+01 1.14E+01 5.60E+00 2.51E+01 1.68E+01 2.44E+01 3.00E+01 1.36E+01 2.07E+01 1.88E+01 03

+1-

+1-I 4.58E+00 2.85E+00 2.70E+00 2.70E+00 2.65E+00 2.92E+00 3.03E+00 2.53E+00 2.91 E+00 2.74E+00 2.40E+00 2.81 E+00 3.08E+00 3.19E+00 2.96E+00 3.57E+00 2.53E+00 2.83E+00 2.19E+00 3.66E+00 2.76E+00 3.57E+00 3.50E+00 2.74E+00 3.07E+00 2.83E+00 2.01E+01 2.41E+01 1.15E+01 1.16E+01 1.13E+01 1.73E+01 1.51E+01 1.87E+01 8.88E+00 1.13E+01 1.65E+01 1.17E+01 1.74E+01 2.56E+01 2.10E+01 2.07E+01 2.06E+01 2.09E+01 5.32E+00 2.74E+01 2.17E+01 2.88E+01 2.72E+01 1.60E+01 2.44E+01 2.29E+01 04

+1-

+1-I 3.08E+00 2.94E+00 2.86E+00 2.69E+00 2.54E+00 2.95E+00 2.98E+00 3.05E+00 2.58E+00 2.73E+00 2.55E+00 2.68E+00 3.16E+00 3.25E+00 2.96E+00 3.56E+00 2.78E+00 3.29E+00 2.17E+00 3.76E+00 2.98E+00 3.75E+00 3.41E+00 2.87E+00 3.24E+00 3.02E+00 2.02E+01 2.70E+01 1.47E+01 6.65E+00 1.76E+01 2.01E+01 2.06E+01 2.42E+01 2.25E+01 2.30E+01 1.77E+01 1.66E+01 1.73E+01 2.60E+01 2.14E+01 2.20E+01 2.57E+01 1.58E+01 8.96E+00 2.82E+01 2.32E+01 3.19E+01 3.68E+01 1.75E+01 2.60E+01 2.39E+01 05

+1-

+1-I I

4.27E+00 3.08E+00 3.04E+00 2.40E+00 2.87E+00 3.08E+00 3.26E+00 3.32E+00 3.27E+00 3.31E+00 2.61 E+00 2.93E+00 3.18E+00 3.26E+00 2.98E+00 3.62E+00 3.01E+00 3.06E+00 2.41E+00 3.79E+00 3.04E+00 3.87E+00 3.82E+00 2.94E+00 3.31 E+00 3.06E+00 2.36E+01 2.92E+01 1.46E+01 1.64E+01 1.22E+01 1.92E+01 2.03E+01 2.29E+01 1.85E+01 1.93E+01 1.80E+01 1.83E+01 2.07E+01 2.77E+01 2.23E+01 2.55E+01 2.40E+01 1.92E+01 1.08E+01 2.89E+01 2.54E+01 2.21E+01 3.27E+01 1.43E+01 2.50E+01 2.49E+01 3.33E+00 3.18E+00 3.04E+00 2.92E+00 2.59E+00 3.03E+00 3.26E+00 3.26E+00 3.08E+00 3.13E+00 2.63E+00 3.01E+00 3,36E+00 3.33E+00 3.02E+00 3.78E+00 2.94E+00 3.22E+00 2.51E+00 3.83E+00 3.14E+00 3.40E+00 3.65E+00 2.78E+00 3.27E+00 3.11E+00 1.59E+01 2.13E+01 1.20E+01 1.06E+01 1.50E+01 1.25E+01 1.40E+01 1.08E+01 1.53E+01 1.34E+01 1.23E+01 1.34E+01 1.76E+01 2.47E+01 1.80E+01 1.68E+01 1.87E+01 1.48E+01 9.47E+00 2.34E+01 1.79E+01 2.28E+01 2.07E+01 1.49E+01 2.29E+01 2.01E+01 2.83E+00 2.84E+00 2.89E+00 2.67E+00 2.70E+00 2.71E+00 2.93E+00 2.64E+00 2.92E+00 2.84E+00 2.33E+00 2.75E+00 3.20E+00 3.20E+00 2.83E+00 3.35E+00 2.69E+00 3.00E+00 2.44E+00 3.57E+00 2.81E+00 3.44E+00 3.14E+00 2.81E+00 3.17E+00 2.90E+00 MEAN 1.546E+01

+/-

2.86E+00 1.64E+01

+/-

2.91E+00 1.45E+01

+/- 2.84E+00 1.60E+01

+/-

2.88E+00 1.84E+01

+/-

3.03E+00 1.79E+01

+/-

2.99E+00 1.44E+01

+/-

2.80E+00 39

Table 3-3 Air Particulate Gross Beta Radioactivity

[1 03 pCi/m 3]

page 4 of 4 Period Ending 07/03112 07/11/12 07/17/12 07/24/12 07/31/12 08/07/12 08/14/12 08/21/12 08/28112 09104/12 09/12/12 09/19/12 09/25/12 10/02/12 10/10/12 10/16/12 10/24/12 10/31/12 11/07/12 11/13/12 11/21/12 11/27/12 12/04112 12/11/12 12/18/12 12/26/12 Station Station Station I

I I

I 1.54E+01 2.01E+01 1.25E+01 1.14E+01 1.72E+01 1.71E+01 1.67E+01 1.71 E+01 1.36E+01 1.29E+01 1.62E+01 1.29E+01 1.74E+01 2.53E+01 2.31E+01 2.08E+01 2.20E+01 1.42E+01 1.05E+01 2.39E+01 2.33E+01 2.09E+01 3.21E+01 1.42E+01 2.78E+01 1.70E+01 2.80E+00 2.79E+00 2.92E+00 2.72E+00 2.81E2+00 2.95E+00 3.09E+00 2.96E+00 2.85E+00 2.81 E+00 2.54E+00 2.72E+00 3.20E+00 3.22E+00 3.05E+00 3.55E+01 2.85E+00 2.97E+00 2.50E+00 3.59E+00 3.05E+00 3.35E+00 3.63E+00 2.78E+00 3.39E+00 2.76E+00 2.01E+01 2.46E+01 1.44E+01 1.43E+01 1.70E+01 1.69E+01 1.68E+01 2.16E+01 1.94E+01 1.69E+01 1.70E+01 1.49E+01 1.88E+01 2.83E+01 2.322+01 2.10E+01 1.96E+01 1.93E+01 9.19E+00 2.89E+01 1.43E+01 2.05E+01 2.80E+01 1.75E+01 2.52E+01 2.18E+01 22 I

I Station Station 24*

I OlA 3.052+00 2.98E+00 3.03E+00 2.86E+00 2.80E+00 2.94E+00 3.09E+00 3.18E+00 3.16E+00 3.12E+00 2.58E+00 2.83E+00 3.27E+00 3.36E+00 3.06E+00 3.56E+00 2.74E+00 3.21E+00 2.42E+00 3.83E+00 2.63E+00 3.34E+00 3.46E+00 2.95E+00 3.28E+00 2.98E+00 1.65E+01 2.47E+01 9.07E+00 1.28E+01 1.77E+01 1.83E+01 1.56E+01 1.41E+01 1.58E+01 1.01E+01 1.51E2+01 1.602+01 1.82E+01 2.77E+01 2.112E+01 2.07E+01 2.11E+01 1.49E+01 2.68E+01 2.12E+01 2.39E+01 3.05E+01 1.59E+01 2.14E+01 2.44E+01 3.40E+00 2.99E+00 2.70E+00 2.79E+00 2.84E+00 3.01E+00 3.03E+00 2.81E+00 2.96E+00 2.66E+00 2.48E+00 2.90E+00 3.23E+00 3.33E+00 2.97E+00 3.55E+00 2.81E+00 3.01E+00 7.45E+00 3.73E+00 2.96E+00 3.51E+00 3.56E+00 2.87E+00 3.10E+00 3.09E+00 1.77E+01 2.29E+01 1.24E+01 1.13E+01 1.08E+01 1.86E+01 1.37E+01 1.57E+01 1.54E+01 1.58E+01 1.52E+01 1.39E+01 1.85E+01 2.36E+01 2.01E+01 1.73E+01 1.93E+01 1.63E+01 1.00E+01 2.56E+01 2.23E+01 2.322+01 3.19E+01 1.23E+01 2.48E+01 2.06E+01

+/

2.93E+00

+/

2.91E+00

+/

2.91E+00

+/

2.70E+00

+- 2.47E+00

+-

3.03E+00

+-

2.91E+00

+-

2.90E+00

+/

2.94E+00

+-

2.96E+00

+/

2.48E+00

+1 2.78E+00

+-

3.25E+00

+/

3.15E+00

+- 2.92E+00

+I-3.38E+00

+I-2.73E+00

+/- 3.082+00

+/- 2.462+00

+/- 3.68E+00

+/- 3.00E+00

+/- 3.472+00

+/- 3.62E+00

+/- 2.67E+00

+I-3.26E+00 1.59E+01 2.57E+01 1.532+01 1.39E+01 1.89E+01 1.57E+01 9.43E+00 1.88E+01 1.85E+01 1.43E+01 1.49E+01 1.49E+01 1.572+01 2.57E+01 2.34E+01 1.48E+01 1.82E+01 2.00E+01 8.10E+00 2.32E+01 2.27E+01 2.02E+01 2.79E+01 1.53E+01 2.49E+01 2.83E+00 3.03E+00 3.08E+00 2.83E+00 2.90E+00 2.83E+00 2.87E+00 3.05E+00 3.09E+00 2.88E+00 2.47E+00 2.83E+00 3.11E+00 3.23E+00 3.07E+00 3.25E+00 2.67E+00 3.25E+00 2.36E+00 3.56E+00 3.02E+00 3.32E+00 3.45E+00 2.84E+00 3.26E+00 2.86E+00 Station S

05A 1.54E+01

+/-

2.39E+01

+/-

I 1.28E+01

+/-

1.24E+01

+/-

I 1.30E+01

+/-

I 1.842+01

+1-I 1.59E+01

+-

I 1.93E+01

+-

1.62E+01

+

2 1.63E+01

+1-2 8.10E+00

+/- 2 1.42E+01

+/- 2 1.52E+01

+/-

3 2.29E+01

+1-3 1.70E+01

+1-2 1.80E+01

+-

3 2.24E+01

+-

2 1.80E+01

+

3 2

7.72E+00

+-

2 2.45E+01

+-

3 2.312+01

+-

3 2.15E+01

+-

3 2.58E+01

+-

3 1.37E+01

+-

2 2.46E+01

+-

3 2.052+01

+-

2 I

.81E+00

.95E+00

.93E+00

.73E+00

.63E+00

.00E+00

.04E+00

.09E+00

.97E+00

.99E+00

.08E+00

.80E+00

.07E+00

.11E+00

.78E+00

.42E+00

.86E+00

.16E+00

.33E+00

'.62E+00

.04E+00

.37E+00

.75E+00

.25E+00

.91E+00

+/-

2.922+00 1.90E+01 MEAN 1.58E+01 +/-

3.49E+00 1.66E+01 +/-

2.91E+00 1.67E+01 +/-

3.03E+00 1.55E+01 +/-

2.86E+00 1.53E+01 +/-

2.86E+00 1.512+01 +/-

2.82E+00 Mean - All Indicator Locations 1.61E+01 +/-

2.95E+00

Control Station 40

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 1 of 4 Period Ending 01/03/12 01110/12 01/17112 01/24/12 01/31/12 02/07/12 02/14/12 02/21/12 02/28/12 03/06/12 03/13/12 03/20/12 03/28/12 04/04/12 04110/12 04/17/12 04/24/12 05/01/12 05/08/12 05/15/12 05/22/12 05/29/12 06/06/12 06/12/12 06/19/12 06/26/12 I

Station 01 2.96E+01 4.03E+01 1.72E+01 3.52E+01 2.04E+01 1.80E+01 2.06E+01 2.73E+01 6.40E+00 9.37E+00 7.80E+00 2.42E+01 1.46E+01 2.70E+01 1.38E+01 2.33E+01 1.09E+01 2.44E+01 1.17E+01 2.07E+01 4.OOE+01 4.64E+01 1.55E+01 3.18E+01 1.37E+01 5.65E+01 Station C

0 C

C C

C

?

C 2.97E+0 4.04E+0 3.13E+0 3.52E+0 5.25E+0 1.80E+0 5.27E+01 2.74E+0 1.75E+01 2.41E+0 2.IOE+0 9.39E+0(

3.75E+0 2.71E+01 3.54E+01 2.33E+0 2.95E+0 2.44E+0 3.02E+0 5.37E+0 3.99E+O 4.64E+0 4.20E+0 3.16E+0 3.52E+0 5.61E+0 Station S<03 S<

3 1

4 S<

3 3

S<

5 1<

I 1<

5 S<

2 S<

1 1

2 1

2 0

2 1

3 1<

1 1<

3 1

2 1<

2*

1<

2 1<

5 1

4 1

41 1

3 1

5

.OOE+01

.02E+01

.12E+0

.54E+01

.24E+01

.81E+01

.39E+01

.68E+01

.72E+01

.44E+01

.15E+01

.43E+01 I.68E+01

.08E+01

,54E+01

.33E+

.95E+0

.44E+0

.96E+

.35E+0

.OOE+0

.64E+0 l.20E+0

.15E+0 1.54E+0

~.61E÷0 Station I

04 1

~<

1

~<

1

~<

1 1

~<

3.02E+01 4.04E+01 3.13E+01 5.03E+01 5.24E+01 1.80E+01 5.35E+01 2.71 E+01 1.74E+01 2.41E+01 2.14E+01 2.42E+01 3.71 E+01 2.75E+01 3.54E+01 9.04E+00 2.95E+01 2.44E+01 2.98E+01 5.36E+01 4.OOE+01 4.64E+01 4.20E+01 3.16E+01 3.52E+01 5.62E+01 Station S<

1 I<

1 1

1 S<

I 1

S<

1 1<

1 1

2 S<

2 0<

3 1<

1<

3 1<

.2 1<

2 1<

8 1<

3*

1<

5*

1<

32 1<

4 1<

4

.26E+01

.84E+01 1.13E+01 I.15E+01 t.24E+01 I.61E+01

.29E+01 I.59E+01 I.74E+01

.41 E+01

~.11E+01

~.42E+01 I.75E+01

~.72E+01 I.75E+01 t.54E+01

~.95E+01 1.99E+00 1.01 E+01

.36E+01 I.49E+01 1.01 E+01 I.20E+01 I.75E+01 I.52E+01 I.51E+01 Station C

o C

C 1

C C

4.27E+01 1.84E+01 4.OOE+01 3.15E+01 2.85E+01 1.61E+01 3.74E+01 1.59E+01 2.91E+01 1.40E+01 2.29E+01 2.64E+01 1.70E+01 3.46E+01 1.66E+01 2.89E+01 2.53E+01 2.18E+01 2.20E+01 3.49E+01 4.01E+01 3.10E+01 3.76E+01 2.70E+01 3.52E+01 Station 07 C

C C

C

,C C

C C

U III 4.27E+01 1.84E+01 4.OOE+01 3.15E+01 2.85E+01 1.61E+01 3.74E+01 1.59E+01 2.91E+01 1.40E+01 2.37E+01 2.51 E+01 2.64E+01 1.69E+01 3.23E+01 1.66E+01 2.89E+01 2.53E+01 2.18E+01 5.23E+01 3.49E+01 4.01E+01 3.10E+01 3.76E+01 2.70E+01 3.51E+01

Sample not obtained due to sampler not operating 41

Table 3-4 Airborne Iodine 1-131

[10.3 pCi/m3]

page 2 of 4 Period Ending 01/03/12 01/10/12 01/17/12 0 1/24112 01/31/12 02/07/12 02/14/12 02/21/12 02/28/12 03/06112 03/13/12 03/20/12 03/28/12 04/04/12 04/10/12 04/17/12 04/24/12 05/01/12 05/08/12 05/15/12 05/22/12 05/29/12 06/06/12 06/12/12 06/19112 06/26/12 U

Station S4.29E+01 1.84E+01 4.OOE+01 3.15E+01 2.86E+01 1.61E+01 3.73E+01 1.59E+01 2.91 E+01 1.40E+01 2.29E+01 2.51E+01 2.64E+01 1.69E+01 3.24E+01 1.66E+01 2.89E+01 2.54E+01 2.20E+01 5.21 E+01 3.48E+01 4.02E+01 3.09E+01 1.58E+01 2.70E+01 3.49E+01 I

Station 22 4.29E+01 2.19E+01 4.OOE+01 4.14E+01 2.86E+01 2.16E+01 3.74E+01 2.79E+01 2.91E+01 1.40E+01 2.29E+01 2.51E+01 2.63E+01 1.70E+01 3.24E+01 1.66E+01 2.89E+01 2.54E+01 2.18E+01 5.21E+01 1.71E+01 4.02E+01 3.09E+01 3.76E+01 2.70E+01 1.98E+01 I

Station 23 3.42E+01 9.34E+00 3.52E+01 4.14E+01 3.34E+01 2.16E+01 3.33E+01 2.79E+01 3.58E+01 1.88E+01 2.33E+01 2.51E+01 2.03E+01 2.17E+01 2.66E+01 1.72E+01 1.95E+01 2.68E+01 1.82E+01 5.22E+01 3.16E+01 2.36E+01 3.25E+01 2.51E+01 2.21E+01 4.71 E+01 Station S

24*

3.44E+01 2.19E+01 3.52E+01 1.74E+01 3.33E+01 2.16E+01 3.32E+01 2.79E+01 3.58E+01 1.88E+01 2.33E+01 1.87E+01 2.04E+01 2.17E+01 2.64E+01 1.73E+01 1.95E+01 2.67E+01 1.81E+01 3.32E+01 3.16E+01 2.35E+01 3.24E+01 2.50E+01 2.22E+01 4.72E+01 Station 3.41 E+01 2.19E+01 3.52E+01 4.14E+01 3.34E+01 8.39E+OC 3.32E+01 2.79E+01 3.58E+01 1.88E+01 2.94E+01 1.88E+01 2.04E+01 2.16E+01 2.66E+01 1.72E+01 1.95E+01 2.68E+01 1.82E+01 3.31E+01 3.16E+01 2.36E+01 3.24E+01 2.51E+01 2.21E+01 4.73E+01 Station S

05A 3.41E+01 2.19E+01 3.52E+01 4.15E+01 3.33E+01 2.16E+01 3.32E+01 1.08E+01 3.58E+01 1.88E+01 2.33E+01 1.88E+01 2.04E+01 2.17E+01 2.65E+01 1.73E+01 1.95E+01 2.67E+01 1.81E+01 3.32E+01 3.16E+01 2.35E+01 3.25E+01 2.50E+01 2.22E+01 4.72E+01 I

Control Station 42

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

[10" pCi/m 3]

Period Station Station Station Station Station Station Station Ending 01 02 I

03I I

05 I

I 07 07/03/12 1.73E+01 2.92E+01 5.38E+01 2.96E+01 4.71E+01 4.07E+01 3.86E+01 07/11112 5.73E+01 5.73E+01 5.62E+01 5.67E+01 6.28E+01 6.30E+01 6.30E+01 07/17112 9.02E+00 2.33E+01 2.33E+01 2.32E+01 2.32E+01 3.15E+01 3.15E+01 07/24/12 7.96E+00 2.05E+01 2.09E+01 2.03E+01 2.02E+01 2.32E+01 2.38E+01 07/31/12 1.88E+01 4.84E+01 4.85E+01 4.96E+01 4.94E+01 5.10E+01 4.97E+01 08/07/12 2.02E+01 2.07E+01 2.06E+01 2.06E+01 1.29E+01 1.29E+01 1.31E+01 08/14/12 1.18E+01 2.95E+01 2.89E+01 2.92E+01 2.95E+01 2.90E+01 2.86E+01 08/21/12 2.60E+01 2.62E+01 2.62E+01 2.62E+01 2.16E+01 2.15E+01 2.15E+01 08/28/12 1.69E+01 4.35E+01 4.36E+01 4.35E+01

< 4.35E+01 4.08E+01 4.08E+01 09/04/12 2.05E+01 2.06E+01 2.05E+01 2.06E+01 3.17E+01 3.17E+01 3.17E+01 09/12/12 8.94E+00 1.62E+01 1.61E+01 1.61E+01 1.61E+01 2.18E+01 2.18E+01 09/19/12 1.31E+01 3.55E+01 3.64E+01 3.60E+01 3.57E+01 2.82E+01 2.82E+01 09/25/12 1.66E+01 4.25E+01 4.13E+01 4.18E+01 4.23E+01 5.05E+01 5.05E+01 10/02/12 3.65E+01 1.43E+01 3.68E+01 3.69E+01 3.68E+01 4-82E+01 4.82E+01 10/10/12 9.27E+01 2.39E+01 2.39E+01 2.38E+01 2.38E+01 2.37E+01 2.37E+01 10/16/12 3.07E+01 3.08E+01 1.19E+01 3.08E+01 3.08E+01 2.57E+01 2.57E+01 10/24/12 1.08E+01 1.97E+01 1.97E+01 1.96E+01 1.96E+01 2.25E+01 2.25E+01 10/31/12 2.64E+01 2.64E+01 2.64E+01 1.03E+01 2.64E+01 1.33E+01 3.17E+01 11/07/12 9.88E+00 2.67E+01 2.67E+01 2.67E+01 2,67E+01 2.89E+01 2.89E+01 11/13/12 4.67E+01 4.67E+01 4.68E+01 4.67E+01

< 207E+01 3.77E+01 3.77E+01 11/21/12 1.08E+01 2.77E+01 2.79E+01 2.78E+01 2378E+01 2.71E+01 2.71E+01 11/27/12 4.28E+01 4.25E+01 4.34E+01 4.29E+01 4.48E+01 1.88E+01 4.48E+01 12/04/12 9.04E+00 2.34E+01 2.30E+01 2.32E+01 2.34E+01 1.80E+01 1.80E+01 12/11/12 2.22E+01 2.22E+01 2.22E+01 2.22E+01 2.OOE+01 2.OOE+01 8.39E+00 12/18/12 1.55E+01 1.55E+01 1.55E+01 1.55E+01 1.67E+01 1.67E+01 1.67E+01 12/26/12 1.20E+01 3.06E+01 3.05E+01 3.06E+01 3.06E+01 3.03E+01 3.03E+01 43

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m3]

page 4 of 4 Period Ending 07/03/12 07/11/12 07/17/12 07124/12 07/31/12 08/07/12 08/14/12 08121112 08/28/12 09/04/12 09/12/12 09/19/12 09125112 10/02/12 10/10/12 10/16/12 10/24/12 10/31/12 11/07/12 11/13/12 11/21/12 11/27/12 12/04/12 12/11/12 12/18/12 12/26/12 Station S 21 3

6 3

2 4

1 2

2 4

3 2

2 5

4 2

2 2

3 2

4 1

2 1

3

.85E+01

.31E+01

.15E+01

.39E+01

.97E+01

.31E+01

.89E+01

.14E+01

.10E+01

.16E+01

.18E+01

.81E+01

.06E+01

.81 E+01

.37E+01

.56E+01

.25E+01

.17E+01

.90E+01

.77E+01

.70E+01

.48E+01

.80E+01

.00E+01

.67E+01

.04E+01 Station S 22 1

3.

6.

1 3.

1 2.

1 4.

I 1.

1 2.

1 4.

3.

1 2.

5.

1 4.

1 2.

1 3.

2.

1 3.

1 2.

1 4.

1 1.

1 2.

1 1.

S<

3 86E+01 89E+01 15E+01 37E+01 97E+01 78E+01 89E+01 54E+01 14E+01 76E+01 18E+01 82E+01 05E+01 80E+01 37E+01 56E+01 25E+01 17E+01 90E+01 77E+01 70E+01 50E+01 80E+01 00E+01 05E+01 04E+01 Station 23 2

<2 2

2

<3 1

<2

<2 2

3 1

<2

<2 2

<3

<4

<2

.56E+01

.89E+01 2.88E+01 2.17E+01 3.06E+01

!.77E+01 2.21E+01 2.54E+01 3.12E+01 3.60E+01 1.96E+01 3.78E+01 3.57E+01 2.53E+01 2.10E+01 2.19E+01 3.22E+01 3.17E+01 4.58E+01 5.99E+01 1.96E+01 3.06E+01 2.29E+01 2.02E+01 1.90E+01 2.58E+01 Station S

24*

2

< 6 2

2 3

< 6 2

2 3

3 1

3 3

2 2

< 2 3

2 2

6 1

3 2

2 1

<92

.02E+01

.88E+01

.15E+01

.07E+01

.92E+00

.18E+01

.56E+01

.12E+01

.59E+01

.95E+01

.77E+01

.57E+01

.54E+01

.10E+01

.19E+01

.22E+01

.35E+0

.95E+0

.02E+01

.96E+0

.04E+0

.30E+0

.01E+0

.90E+0

.58E+0 Station S

01A S<

2 6

S<

2 S<

3 0

1 S<

2 S<

1 S<

3 S<

1 S<

3 S<

2 S<

3 1

2 2

S<

5 S<

1 I

3 1

2 1

.01E+01

.89E+01

.88E+01

.15E+01

.05E+01

.73E+01

.37E+01

.06E+01

.11E+01

.59E+01

.96E+01

.76E+01

.60E+01

.52E+01

.10E+01

.18E+01

.22E+01

.35E+01

.96E+01

.99E+01

.96E+01

.06E+01

.29E+01

.02E+01

.90E+01

.59E+01 Station S

05A 2

6 2

2 3

1 2

2 3

1 1

3 3

2 2

2 3

2 2

5 1

3 2

2 1

2 I

.02E+01

.87E+01

.88E+01

.13E+01

.11E+01

.77E+01

.20E+01

.56E+01

.10E+01

.40E+01

.95E+01

.77E+01

.57E+01

.54E+01

.10E+01

.19E+01

.21E+01

.35E+01

.96E+01

.99E+01

.96E+01

.04E+01

.30E+01

.01E+01

.90E+01

'.58E+01 m

v.

=

h

Control Station 44

Table 3-5 Airborne Particulate Gamma Spectra

[10-3 pCi/m 3]

page 1 of 2 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24**

Sampling Location 01 O0A 02 03 04 05 05A 06 07 21 22 23 24*

-IrI 1.16E+02 1.17E+02 1.53E+02 1.25E+02 1.15E+02 1.37E+02 9.95E+01 1.50E+02 1.16E+02 1.57E+02 1.60E+02 1.59E+02 1.13E+02 I

Be-7

+1-

+1-Be-7

+1-

+1-2.16E+01 2.55E+01 2.84E+01 2.77E+01 2.40E+01 3.41E+01 2.04E+01 3.59E+01 2.14E+01 3.45E+01 2.74E+01 2.87E+01 2.82E+01 1.97E+01 2.77E+01 2.24E+01 2.09E+01 3.23E+01 3.65E+01 2.92E+01 2.92E+01 2.89E+01 2.80E+01 2.79E+01 2.76E+01 2.61E+01 CS-1 34" 9.66E-01 1.23E+00 1.45E+00 1.41E+00 1.19E+00 1.40E+00 1.25E+00 2.06E+00 1.13E+00 1.33E+00 1.60E+00 1.40E+00 1.79E+00 1.00E+00 8.92E-01 1.19E+00 8.53E-01 1.41E+00 1.26E+00 1.46E+00 1.27E+00 1.19E+00 1.77E+00 1.10E+00 1.22E+00 1.22E+00 CS-137*

< 9.19E-01

" 1.11E+00

< 9.01E-01

" 1.16E+00

< 1.02E+00

" 1.18E+00

< 1.10E+00

< 1.79E+00

< 8.50E-01

< 1.39E+00

< 1.43E+00

< 1.48E+00

< 1.51E+00 I

I I

I Quarter 1 Quarter 2 1.14E+02 1.45E+02 1.49E+02 1.42E+02 1.64E+02 1.60E+02 1.45E+02 1.84E+02 1.41E+02 1.45E+02 1.61E+02 1.76E+02 1.19E+02 Cs-137"

" 9.19E-01

" 1.08E+00

< 1.05E+00

" 1.01E+00

< 1.45E+00

" 1.26E+00

< 9.13E-01

" 1.02E+00

< 1.23E+00

< 1.36E+00

< 9.24E-01

" 1.11E+00

< 1.14E+00 Sr-89

" 3.69E+00

< 3.83E+00

" 3.83E+00

< 3.97E+00

< 4.00E+00

" 3.84E+00

" 3.73E+00

< 4.05E+00

" 3.87E+00

" 4.00E+00

< 4.91E+00

< 4.51E+00

< 4.37E+00 Sr-90

" 7.39E-01

" 1.13E+00

< 7.65E-01

< 8.61E-01

< 8.68E-01

" 8.93E-01

< 8.08E-01

" 1.10E+00

< 1.17E+00

" 1.11E+00 1.22E+00

< 9.02E-01

< 1.18E+00 I

LLD identified in the ODCM

- Control Station 45

Table 3-5 Airborne Particulate Gamma Spectra

[10-3pCi/m 3]

page 2 of 2 Quarter 3 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24"*

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

I Be-7 1.44E+02

+1-3.35E-01 1.18E+02

+1-4.51E+01 1.49E÷02

/-

3.52E+01 1.33E÷02

+1-4.00E+01 1.37E+02

+/-

3.80E+01 1.64E+02

+/-

3.28E+01 1.50E+02

+/- 3.55E+01 1.40E+02

+/- 4.58E+01 1.27E+02

+/-

3.27E+01 4.30E+02

+/- 1.04E+02 1.41E+02

+/-

2.62E+01 8.07E+01

÷/- 2.38E601 1.47E+02

+/-

3.90E+01 Be-7 8.94E+01

+/-

2.47E+01 9.06E+01

+/- 2.29E801 9.72E+01

+/-

2.58E+01 8.64E+01

+I-2.14E+01 8.90E+01

+/-

2.32E-01 1.21E+02

+/-

3.04E+01 1.07E+02

+I-2.15E+01 1.21E+02

+/-

2.59E+01 1.03E+02

+1-2.38E601 9.84E+01

+I-2.67E+01 1.04E+02

+/- 2.77E+01 1.04E+02

+/-

2.88E+01 1.05E+02

+/-

2.12E+01 CS-134" 1.05E+00 1.24E+00 1.90E+00 1.11E+00 1.71E+00 1.63E+00 1.81E+00 2.26E÷01 1.50E+00 3.88E+00 1.38E+00 1.46E+00 1.95E÷00 S

Cs-137" 1.01E+00 1.07E+00 1.40E+00 9.39E-01 1.20E+00 1.40E+00 1.39E+00 1.60E+00 1.09E+00 3.26E+00 1.20E+00 9.15E-01 1.46E+00 II It I

Cs-134" 1.59E+00 1.40E+00 1.55E+00 1.50E+00 1.70E+00 1.64E+00 1.31E+00 1.46E+00 1.76E+00 1.75E+00 1.54E+00 1.88E+00

+

1.23E+00 I

Cs-137" 1.24E+00 1.18E+00 1.34E+00 1.20E÷00 1.23E+00 1.37E+00 9.85E-01

+

1.49E+00 1.39E+00 1.33E+00 1.14E+00

+

1.64E+00 8.29E-01 MEAN S

Be-7 1.16E+02

+1-1.18E+02

+1-1.37E+02 1.22E+02

+/-

1.26E+02

+1-1.46E+02

+1-1.25E+02

+/-

1.49E+02

+1-1.22E+02

+1-2.08E+02

+1-1.42E+02

+1-1.30E+02

+1-1.21E+02

+/-

Quarter 4 2.49E+01 3.03E+01 2.80E+01 2.75E+01 2.94E+01 3.35E+01 2.67E+01 3.42E+01 2.67E+01 4.83E+01 2.73E+01 2.72E+01 2.86E+01 Mean of All Indicator Location:

1.37E+02

+/.

3.03E+01

LLD Identified in ODCM Control Station 46

Table 3-6 Soil

[pCi/kg]

page 1 of 1 Soil sampled on triennial basis. Last taken 2010. Not required in 2012 47

Table 3-7 Precipitation Gross Beta

[pCi/L]

page 1 of 2 Sampling Date I

Gross Beta 01/31/12 5.20E+00

+/-

1.39E+00 02/28/12 3.48E+00

+/o 1.55E+00 03/28/12 2.27E+00 04/24/12 2.20E+00 05/29/12 2.21E+00 06/26/12 2.13E+00 07/31/12 2.10E+00 08/28/12 2.69E+00

+/-

1.47E+00 09/25/12 2.04E+00 10/31/12 2.61E+00

+/-

1.50E+00 11/27/12 7.73E+00

+/-

1.98E+00 12/26/12 2.42E+00

+/-

1.49E+00 Mean 4.02E+00

+/-

1.56E+00 I

H-3 Rainfall (inches) 1.85 2.11 3.42 1.21 4.71 3.53 4.97 Ij 3.06 2.75 4.56 0.62 1.77 34.56 8.62E+02 7.OOE+02 Total 48

Table 3-7 Precipitation page Gamma Spectra 2 of 2

[pCi/L]

Sampling Location I

Be-7 I

Mn-54 Fe-59 Co-58 I

0o-60 0IA 06/26/12 4.55E+01 1.49E+00 1.24E+01 3.14E+00 1.05E+00 12/26/12 5.97E+01 2.05E+00 1.83E+01 4.48E+00 1.67E+00 I

Zn-65 I

zr-95 I

Nb-95 Cs-134 I

Cs-137 01A 06/26/12 3.76E+00'

+/-

1.73E+00 6.42E+00 3.63E+00 1.14E+00 1.19E+00 12/26/12 4.60E+00 9.32E+00 5.64E+00 1.82E+00 1.81E++00 I

Ba-140 I

L-140 I

1-131 Th-228 I

01A 06/26/12 2.72E+03 7.38E+02 3.89E+04 2.29E+00 12/26/12 2.43E+03 8.54E+02 2.69E+04 3.53E+00

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

49

Table 3-8 Milk Gamma Spectra & Strontium

[pCi/L]

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

1.29E+03 1.27E+03 1.48E+03 1.30E+03 1.36E+03 1.24E+03 1.27E+03 1.39E+03 1.40E+03 1.35E+03 1.42E+03 1.45E+03 1.35E+03 K-40

+1-

1 +1-I Sr-89 I

Sr-90 I

1.70E+02 1.07E+02 1.41 E+02 1.68E+02 1.16E+02 1.28E+02 1.48E+02 1.01 E+02 1.78E+02 1.96E+02 1.37E+02 9.80E+01 1.41 E+02

[a]

1-131*

1.75E+00 2.36E+00 3.08E+00 1.93E+00

[a]

6.53E-01 7.90E-01 1.74E+00 9.68E-01 5.12E-01 4.88E-01 5.67E-01 5.32E-01 7.31 E-01 6.60E-01 5.29E-01 6.73E-01 7.16E-01 6.42E-01 8.51 E-01 8.42E-01 0s-134"

< 4.59E+00 3.99E+00 5.04E+00 5.02E+00

< 4.68E+00 5.22E+00

< 6.55E+00 3.46E+00

" 7.77E+00

< 7.99E+00

" 6.05E+00

" 3.72E+00 Cs-137" 5.48E+00 4.83E+00 5.33E+00 6.05E+00 4.86E+00 5.75E+00 6.51 E+00 3.93E+00 7.51 E+00 9.43E+00 5.49E+00 4.39E+00 I

Ba-140*

2.74E+01 1.99E+01 2.61 E+01 3.01 E+01 2.67E+01 2.47E+01 3.63E+01 2.45E+01 4.02E+01 4.90E+01 3.93E+01 3.22E+01 page 1 of 1 Station 12A

< 6.78E+00 5.98E+00

< 9.20E+00

< 8.76E+00

< 6.25E+00

< 7.65E+00

" 9.98E+00

< 6.17E+00

< 9.60E+00 1.15E+01 1.22E+01

< 9.09E+00

LLD identified in ODCM

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

50

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

Sampling Sampling Location Date I

Be-7 I

K-40 I

-131 I

Cs-134 I

Cs-137 04110/12 4.55E+03 +/- 6.30E+02 7.99E+03 +/-

1.10E+03 1.71E+01 3.32E+01 3.70E+01 14B 05/08/12 5.98E+02

+/- 2.20E+02 5.33E+03

+/- 5.37E+02 3.03E+01 2.45E+01 2.29E+01 06/12/12 7.86E+02

+/- 2.62E+02 6.69E+03 +/- 7.15E+02 2.86E+01 2.87E+01 3.34E+01 07/11/12 1.37E+03 +/- 1.29E+02 9.05E+03

+I-3.18E+02 3.40E+01 1.09E+01 1.31E+01 08/14/12 1.16E+03

+/- 2.11E+02 7.78E+03

+/- 4.85E+02 5.76E+01 1.80E+01 1.82E+01 09/12/12 1.22E+03 +/- 1.59E+02 5.56E+03

+/- 3.77E+02 3.11E+01 1.57E+01 1.69E+01 10/12/12 1.50E+03 +/- 2.09E+02 6.13E+03

+/- 4.70E+02 3.69E+01 2.13E+01 2.18E+01 Mean 1.60E+03 +/-

2.60E+02 6.93E+03

+/-

5.72E+02 Sampling Sampling Location Date Be-I K-40 I

1-131*

I Cs-134*

I Cs-1 37 15 04/10/12 1.31E+03 +/- 2.15E+02 7.63E+03

+/- 5.02E+02 1.88E+01 2.01E+01 2.31E+01 05/08/12 8.49E+02

+/- 2.33E+02 6.53E+03

+/- 5.84E+02 2.37E+01 2.52E+01 2.78E+01 06/12/12 4.60E+02 +I-2.64E+02 6.OOE+03

+/- 8.81E+02 3.89E+01 2.74E+01 2.97E+01 07/11/12 1.12E+03 +/- 1.28E+02 7.04E+03

+/- 3.46E+02 3.56E+01 1.08E+01 1.17E+01 08/14/12 8.26E+02

+/- 1.92E+02 7.OOE+03

+/- 5.07E+02 5.60E+01 1.89E+01 1.79E+01 09/12/12 2.OOE+03

+/- 3.02E+02 6.10E+03

+/- 5.77E+02 3.48E+01 1.60E+01 1.95E+01 10/12/12 1.03E+03 +/- 2.22E+02 8.58E+03

+/- 5.24E+02 3.29E+01 1.93E+01 1.90E+01 Mean 1.09E+03 +/-

2.22E+02 6.98E+03 +/-

5.60E+02 Sampling Sampling Location Date 7

+

Be-7 2 K-40 1 <-13.+1 Cs21 34*

2Cs-137 16-04/10/12 7.96E+02

+/- 2.38Ei-02 8.60E+03

+/- 6.39E+02

< 1.74E+01

< 2.38E+01

< 2.82E+01 page 1 of 2 05/08/12 06/12/12 07/11/12 08/14/12 09/12/12 10/12/12 Mean

LLD identified in ODCM Control Station 2.68E+02 4.76E+02 5.26E+02 1.32E+03 1.20E+03 2.20E+03 9.69E+02

+/-

+1-

+1-1.84E+02 2.23E+02 9.44E+01 2.12E+02 1.76E+02 2.67E+02 1.99E+02 5.14E+03 3.77E+03 3.69E+03 3.86E+03 3.02E+03 6.30E+03 4.91 E+03

+/-

5.44E+02 5.50E+02 1.92E+02 3.89E+02 3.57E+02 5.91 E+02 4.66E+02 2.30E+01 3.46E+01 3.33E+01 4.74E+01 3.07E+01 2.99E+01 2.01E+01 2.35E+01 1.03E+01 1.86E+01 1.62E+01 1.77E+01 2.32E+01 2.32E+01 1.12E+01 1.93E+01 1.77E+01 1.80E+01 51

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

page 2 of 2 Sampling Sampling II II Location Date I

Be-7 I

K-40 1-131" Cs-134" Cs-137" 23 04/10/12 1.17E+03

+/-

3.83E+02 6.70E+03

+/-

6.55E+02 1.67E+01 2.21E+01 2.76E+01 05/08/12 1.08E+03

+/-

3.55E+02 5.02E+03

+/-

9.16E+02 2.31E+01 2.86E+01 2.86E+01 06/12/12 8.OOE+02

+/-

3.42E+02 5.46E+03

+/-

8.45E+02 3.46E+01 3.12E+01 4.04E+01 07/11/12 1.39E+03

+/-

1.47E+02 8.69E+03

+/-

3.20E+02 4.63E+01 1.22E+01 1.38E+01 08/14/12 2.16E+03

+/-

4.18E+02 3.86E+03

+/-

5.89E+02 5.83E+01 2.58E+01 3.38E+1-*

+/-

2.62E+01 09/12/12 1.95E+03

+/-

2.30E+02 5.79E+03

+/-

5.11E+02 2.87E+01 1.99E+01 2.28E+01 10/12/12 1.48E+03

+/-

3.77E+02 8.14E+03

+/-

7.37E+02 2.90E+01 2.75E+01 2.96E+01 Mean 1.43E+03

+/-

3.22E+02 6.24E+03

+/-

6.53E+02

+/-

Sampling Sampling Location Date I

Be-7 I

K-40 1-131*

I Cs-134 Cs-137" 26 04/10/12 05/08/12 06/12/12 07/11/12 08/14/12 09/12/12 10/12/12 1.88E+03

+/-

3.64E+02 1.22E+03

+/-

2.75E+02 1.56E+03

+/-

6.51 E+02 1.87E+03

+/-

2.11E+02 1.81E+03

+/-

2.98E+02 2.15E+03

+/-

2.74E+02 3.33E+03

+/-

3.52E+02 6.32E+03

+/-

7.61 E+02 5.90E+03

+/-

7.14E+02 5.20E+03

+/-

1.29E+03 6.15E+03

+/-

3.66E+02 3.86E+03

+/-

5.38E+02 3.65E+03

+/-

4.17E+02 3.72E+03

+/-

4.64E+02 2.17E+01 2.25E+01 2.74E+01 3.89E+01 5.04E+01 4.12E+01 2.63E+01 3.21E+01 2.78E+01 4.18E+01 1.54E+01 2.98E+01 2.08E+01 2.52E+01 3.63E+01 3.04E+01 4.31E+01 1.66E+01 3.27E+01 2.41E+01 2.86E+01 Mean 1.97E+03

+/-

3.46E+02 4.97E+03

+/-

6.50E+02

+/-

+1-

+/-

Indicator locations 1.52E+03

+/-

2.88E+02 6.28E+03

+/-

6.09E+02

LLD identified in ODCM

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

52

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

[pCi/L]

I Sr-90 I

Mn-54 Fe-59 I

Co-58 I

Co-60 page 1 of 1 Sampling Date H-3 I

Station 01A Zn-65 Sr-89 I

03/28/12 06/28/12 09/25/12 12/26/12 7.24E+02 7.52E+02 8.02E+02 7.07E+02

[a]

2.70E+00 8.09E-01

[a]

4.16E+00 9.69E+00 3.60E+00 4.39E+00 8.04E+00 4.OOE+00 1.04E+01 4.50E+00 4.75E+00 8.07E+00 2.99E+00 6.83E+00 3.92E+00 2.80E+00 6.92E+00 Mean Sampling Date Zr-95 I

Nb-95 I

1-131 I

Cs-134 I

Cs-137 I

Ba-140 I

La-140 I

r--

03/28/12 6.76E+00 06/28/12 09/25/12 7.60E+00 12/26/12 5.70E+00 4.35E+00 3.45E-01 8.70E-01 4.69E+00 8.22E-01 4.26E+00 7.40E-01 3.82E+00 4.04E+00 2.21E+01 8.04E+00 3.83E+00 4.20E+00 3.07E+01 1.13E+01 3.13E+00 3.40E+00 2.47E+01 8.82E+00 Mean

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

Missed gamma analysis on 2 nd Quarter 2012 Ground water well 53

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

[pCi/L]

page 1 of 1 Sampling Date 01/12/12 02/13/12 03/12/12 04/16/12 05/14112 06111112 07/16/12 08/14112 09/10/12 10/15/12 11/14/12 12/12/12 MEAN Sampling Date I

H-3 I

Sr-89 I

Sr-90 I

Mn I

Fe I

Co-58" I

[a]

3.23E+03

+/- 6.20E+02

[a]

2.57E+03

+/- 6.00E+02

[a]

2.04E+03

+/- 6.06E+02

[a]

4.34E+03

+/- 8.OOE+02 3.05E+03

+/-

6.57E+0.

Nb-95*

[b]

3.41E+00

[b]

2 Zr-95 I

[b]

(b]

[b]

(15[

[b) 7.38E-01 fbI

[b]

5.06E+00 3.48E+00 5.59E+00 3.61E+00 3.55E+00 5.63E+00 3.34E+00 2.56E+00 1.78E+00 1.61E+00 3.08E+00 5.20E+00 C

C 1.00E+01 7.42E+00 1.01E+01 1.13E+01 7.75E+00 1.15E+01 7.69E+00 5.40E+00 4.15E+00 3.80E+00 6.26E+00 9.86E+00 C

6.29E+00 3.80E+00 4.14E+00 5.04E+00 4.19E+00 6.14E+00 3.40E+00 2.65E+00 1.97E+00 1.63E+00 2.87E+00 5.12E+00 Co-60"

" 6.12E+00

" 2.78E+00 5.99E+00

" 4.33E+00

" 3.52E+00

" 4.87E+00

" 2.96E+00

" 2.93E+00 1.95E+00 1.71 E+00 3.33E+00 5.22E+00 La-140*

1.37E+01 6.07E+00 7.50E+00 6.05E+00 8.68E+00 7.39E+00 5.81 E+00 3.31E+00 4.65E+00 3.23E+00 4.55E+00 7.28E+00 Station 11 S Z "

1.25E+01 5.71E+00 9.98E+00 8.55E+00 7.47E+00 8.44E+00 7.50E+00 5.67E+00 3.87E+00 3.19E+00 6.65E+00 9.19F+00 I

I I

01/12/12 02/13/12 03/12/12 04/16/12 05/14/12 06/11/12 07/16/12 08/14/12 09/10/12 10/15/12 11/14/12 12/12/12 7.49E+00 3.46E+00 4.49E+00 4.81E+00 3.66E+00 5.52E+00 3.96E+00 3.10E+00 2.17E+00 1.68E+00 3.11E+00 5.69E+00 9.85E+00 6.62E+00 7.21 E+00 8.25E+00 7.23E+00 9.35E+00 6.54E+00 5.29E+00 3.46E+00 2.83E+00 5.27E+00 9.59E+00 1-131" 4.23E-01 4.52E-01 5.36E-01 5.75E-01 3.57E-01 8.94E-01 5.78E-01 6.44E-01 5.75E-01 5.65E-01 6.26E-01 5.19E-01 I

Cs-134" 6.24E+00 2.93E+00 4.30E+00 4.56E+00 3.46E+00 5.36E+00 3.22E+00 2.64E+00 1.76E+00 1.39E+00 2.73E+00 4.82E+00 I

Cs-137"

5.56E+00

< 3.77E+00 4.55E+00

< 5.37E+00

< 3.81E+00

5.65E+00

< 3.70E+00

< 3.04E+00

< 1.92E+00

< 1.68E+00

3.20E+00 5.59E+00 I

Ba-140*

3.75E+01 1.86E+01 2.14E+01 2.45E+01 3.31E+01 2.37E+01 1.95E+01 1.19E+01 1.42E+01 9.40E+00 1.33E+01 2.67E+01 I

I

LLD identified in ODCM

[a] Tritium analyses on quarterly composite.

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

54

Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium page 1 of 2 Sampling Date H-3*

01/12/12

[a]

02/13/12

[a]

03/12/12 2.73E+03

+/-

5.98E+02 04/16/12

[a]

05114/12 06/11/12 2.79E+03

+/- 6.13E+02 07/16/12

[a]

08/14/12

[a]

09/10/12 2.63E+03

+/-

6.35E+02 10115/12

[a]

11/14/12

[a]

12/12/12 2.26E+03

+/-

7.01E+02 Mean 2.60E+03

+/-

6.37E+02 I

Sr-89 Sr-90

[b]

3.78E+00 8.29E-01

[b]

[pCi/L]

Mn-54 Fe-59 6.92E+00 1.13E+01 3.73E+00 9.67E+00 4.49E+00 9.98E+00 6.03E+00 1.54E+01 3.12E+00 8.21E+00 5.84E+00 1.26E+01 3.63E+00 8.27E+00 3.21E+00 6.51E+00 1.91E+00 4.63E+00 1.55E+00 3.16E+00 2.60E+00 S.46E+00 4.31E+00 9.86E+00 CO-58" 6.24E+00 3.83E+00 3.68E+00 6.33E+00 3.11E+00 5.36E+00 4.89E+00 2.59E+00 2.06E+00 1.53E+00 2.33E+00 4.34E+00 Station 08 Co-60" Zn-65*

5.68E+00 9.77E+00 4.77E+00 8.43E+00 4.82E+00 1.08E+01 6.14E+00 1.24E+01 3.14E+00 6.38E+00 4.79E+00 1.35E+01 4.02E+00 8.08E+00 3.64E+00 5.93E+00 1.76E+00 3.59E+00 1.67E+00 3.03E+00 2.56E+00 5.54E+00 5.48E+00 8.07E+00 I

Sampling Date 01/12/12 02/13/12 03/12/12 04/16/12 05/14/12 06/11/12 07/16112 08/14/12 09/10/12 10/15/12 11/14/12 12/12/12 Zr 95" 9.57E+00 7.56E+00 8.77E+00 9.81E+00 6.26E+00 8.67E+00 7.36E+00 5.55E+00 3.56E+00 2.86E+00 3.91E+00 8.69E+00 Nb-95*

1-131" 5.20E+00 3.46E-01 4.82E+00 4.05E-01 5.13E+00 6.06E-01 6.74E+00 5.43E-01 2.97E+00 3.81 E-01 5.82E+00 7.23E-01 4.19E+00 6.07E-01 3.34E+00 6.20E-01 2.21E+00 4.95E-01 1.57E+00 4.73E-01 2.77E+00 6.45E-01 4.80E+00 4.03E-01 Cs-134" Cs-137" Ba-140*

5.09E+00 6.35E+00 2.96E+01 3.66E+00 4.02E+00 2.27E+01 4.37E+00 5.06E+00 2.60E+01 5.71 E+00 5.63E+00 2.83E+01 2.99E+00 2.82E+00 2.68E+01 4.97E+00 5.88E+00 2.51E+01 3.95E+00 4.53E+00 2.09E+01 2.71E+00 3.45E+00 1.21E+01 1.72E+00 1.98E+00 1.41E+01 1.45E+00 1.66E+00 8.71E+00 2.55E+00 2.65E+00 1.10E+01 4.51E+00 5.42E+00 2.44E+01

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

La-140*

1.27E+01 8.12E+00 8.47E+00 1.22E+01 9.15E+00 5.94E+00 8.72E+00 3.95E+00 4.28E+00 3.07E+00 4.43E+00 9.84E+00 I

LLD identified in ODCM

[a] Tritium analyses on quarterly composite.

55

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

[pCi/L]

page 2 of 2 Sampling Date 01/12/12 02/13/12 03/12/12 04116/12 05/14/12 06/11/12 07/16112 08/14/12 09110/12 10/15/12 11/14/12 12/12/12 H-3*

[a]

6.93E+02

[a]

6.91E+02

[a]

7.51E+02

[a]

9.15E+02 Sr-89

[b]

3.87E+00

[b]

[hb

[b]

Station 09A Sr-90 Mn-54 Fe-59 Co-58 I

Co-60

[b]

5.16E+00 1.26E+01 5.33E+00 5.85E+00 1.20E+01

[b]

2.93E+00 6.25E+00 3.18E+00 3.28E+00 6.62E+00

[b]

< 4.91E+00 1.13E+01 4.07E+00 5.16E+00 8.43E+00

[b]

4.69E+00 1.12E+01 4.61E+00 4.83E+00 1.09E+01

[b]

3.82E+00 1.05E+01 4.85E+00 3.95E+00 7.44E+00 9.02E-01 5.73E+00 1.38E+01 5.48E+00 5.18E+00 1.19E+01

[b]

3.96E+00 9.12E+00 5.09E+00 4.48E+00 9.74E+00

[b]

3.39E+00 6.41E+00 2.91E+00 3.35E+00 5.67E+00

[b]

1.46E+00 3.44E+00 1.65E+00 1.40E+00 2.91E+00

[b]

1.41E+00 3.03E+00 1.56E+00 1.41E+00 2.79E+00

[b]

3.18E+00 5.89E+00 3.09E+00 3.27E+00 6.20E+00

[b]

5.46E+00 1.01E+01 4.99E+00 5.83E+00 1.03E+01 Sampling Date Zr-95*

01/12/12 8.75E+00 02/13/12 5.37E+00 03/12/12 8.63E+00 04/16/12 9.30E+00 05/14112 8.19E+00 06/11/12 1.18E+01 07/16112 7.51E+00 08/14112 6.07E+00 09/10/12 2.98E+00 10/15/12 2.60E+00 11/14/12 5.55E+00 12/12/12 9.12E+00 LLD identified in ODCM Nb-95" 6.44E+00 3.72E+00 5.49E+00 5.15E+00 4.76E+00 5.26E+00 4.02E+00 3.58E+00 1.78E+00 1.55E+00 3.60E+00 6.00E+00 I

1-131" 5.61 E-01 3.83E-01 6.14E-01 5.48E-01 3.54E-01 7.65E-01 5.97E-01 7.06E-01 5.69E-01 5.76E-01 6.26E-01 4.78E-01 Cs-134*

Cs-137" Ba-140*

La-140*

3.85E+00 5.48E+00 3.61E+01 1.27E+01 3.10E+00 3.55E+00 1.87E+01 6.05E+00 4.45E+00 5.30E+00 2.43E+01 8.45E+00 5.24E+00 5.54E+00 2.37E+01 8.71E+00 3.92E+00 3.96E+00 3.36E+01 8.35E+00

" 5.15E+00 4.56E+00 3.34E+01 7.77E+00

" 4.01E+00 4.44E+00 2.16E+01 6.72E+00 3.47E+00 3.62E+00 1.49E+01 4.00E+00 1.41E+00 1.58E+00 1.25E+01 3.55E+00 1.46E+00 1.58E+00 8.62E+00 2.55E+00 3.07E+00 3.31 E+00 1.32E+01 4.19E+00 5.03E+00 5.72E+00 2.34E+01 9.20E+00

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

[a] Tritium analyses on quarterly composit 56

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

page Sample 1 of 1 Date Sr-89 Sr-90 I

K-40 Cs-134 Cs-137 I

4/9/2012 Station 08

[a]

2.21E+04

+/-

1.71E+03

< 6.67E+01

< 7.65E+01 Station 09A-

[a]

1.25E+04

+/-

1.22E+03

< 5.80E+01

< 7.29E+01 Station 11

[a]

1.69E+04

+/-

1.34E+03

< 6.20E+01

< 6.98E+01 Ra-226 Th-228 Th-232 I

4/912012 Station 08 4.13E+03

+/-

1.51E+03 2.40E+03

+/- 1.26E+02 2.13E+03

+/- 2.03E+02 Station 09A-2.06E+03

+/- 1.20E+03 6.23E+02

+/- 9.17E+01 5.84E+02

+/-

1.59E+02 Station 11 2.92E+03

+/- 1.40E+03 1.26E+03

+/-

1.05E+02 1.16E+03

+/-

1.64E+02 Sample Date I

Sr-89 Sr-90 K-40 I

Cs134*

I Cs-137 I

10/23/2012 Station 08

< 2.15E+02

< 3.96E+01 1.24E+04

+/- 1.34E+03

< 5.77E+01

< 7.26E+01 Station 09A**

< 1.97E+02

< 3.85E+01 1.28E+04

+/-

1.37E+03

< 6.19E+01 1.12E+02

+/-

8.64E+01 Station 11

< 1.85E+02

< 4.22E+01 1.44E+04

+/-

1.39E+03

< 7.32E+01

< 7.96E+01 Ra-226 I

Th-228 I

Th-232 I

10/23/2012 Station 08 2.39E+03

+/-

1.34E+03 1.68E+03

+/-

1.16E+02 1.54E+03

+/-

1.82E+02 Station 09A-1.30E+03

+/-

1.18E+03 7.43E+02

+/-

1.04E+02 8.13E+02

+/-

1.55E+02 Station 11 2.65E+03

+/-

1.44E+03 2.08E+03

+/-

1.42E+02 1.97E+03

+1-2.07E+02 MEAN Sr-89 Sr-90 K-40 Cs-134 I

Cs-137" Indicator Control 1.65E+04

+/-

1.45E+03 1.27E+04

+/-

1.30E+03 Ra-226 I

Th-228 I

Th-232 3.02E+03 +I-1.39E+03 1.86E+03 +I-1.22E+02 1.70E+03

+/-

1.89E+02 1.68E+03

+/-

1.20E+03 6.83E+02

+/-

9.79E+01 6.99E+02 +/-

1.57E+02 Indicator Control

LLD identified in ODCM

-Control Station

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

57

Table 3-14 Shoreline Soil Gamma Spectra, and Strontium

[pCi/Kg]

page 1 of 1 Sample Date I

Sr-89 Sr-90 I

K-40 I

Cs-134 I

Cs-137" 4/9/2012 Station 08

[a]

2.OOE+03

+/-

8.74E+02 5.64E+01 6.64E+01 I

Ra-226 I

Th-228_

I Th-232 I

1.18E+03 7.08E+02

+/- 1.32E+02 6.66E+02

+/- 2.26E+02 Sample Date I

Sr-89 I

Sr-90 I

K-40 I

Cs-134 I

Cs-137 10/23/2012 Station 08 1.65E+02 4.58E+01 2.55E+03

+/-

5.76E+02 3.36E+01 1.57E+02

+/- 3.83E+01 I

Ra-226 I

Th-228 I

Th-232 I

1.21E+03

+/-

6.73E+02 4.39E+02

+/- 6.56E+01 3.99E+02

+/- 8.88E+01 MEAN I

Sr-89 I

Sr-90 I

K-40 I

Cs-134" I

Cs-137*

I 2.28E+03

+/-

7.25E+02 Ra-226 I

Th-228 I

Th-232 I

1.21E+03

+/-

1.18E+03 5.74E+02

+/- 9.88E+01 5.33E+02

+/- 1.57E+02

LLD identified in ODCM

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

58

Table 3-15 Fish Gamma Spectra

[pCi/Kg]

Sampling Date I

K-40 I

Mn-54 I

Fe-59*

I Co-58 I

Co-60" 04/11/12 1.99E+03

+1-9.45E+02 7.72E+01

< 2.01E+02

< 8.00E+01

< 8.40E+01 10/24/12 2.31E+03

+/- 7.08E+02 5.72E+01

< 1.45E+02 6.OOE+01

< 5.80E+01 Sampling Date i

K-40 i

Mn-54 i

Fe-59" Co-58*

i Co-60 i

04/10/12 1.47E+03

+1-1.18E+03 7.27E+01

< 1.89E+02

< 8.29E+01

< 9.52E+01 10/26/12 1.19E+03

+/- 7.58E+02 6.55E+01

< 1.54E+02

< 6.45E+01

< 7.82E+01 Sampling Date I

K-40 I

Mn-54 I

Fe-59 I

Co-58 I

Co°60*

04/11/12 1.93E+03

+/- 4.35E+02 2.83E+01

< 8.17E+01

< 2.92E+01

< 2.67E+01 10/25/12 3.03E+03

+/-

7.67E+02 5.17E+01

< 1.23E+02

< 4.84E+01

< 5.19E+01 page 1 of 1 Fish [a]

Station 08 Zn-65*

I Cs'134-I Cs-137" j 1.65E+02 7.68E+01

< 8.11E+01 1.34E+02 5.10E+01 5.53E+01 Station 25**

Zn-65 i

Cs-134-i Cs-137-j 1.38E+02

< 6.75E+01

< 8.14E+01 1.28E+02 5.38E+01

< 6.67E+01 catfish [b]

Station 08 Zn-65*

I Cs-134-Cs-137" j 5.37E+01 3.12E+01

< 3.35E+01 1.12E+02 4.91E+01

< 5.01E+01 Sampling Station 25**

Date I

K-40 I

Mn I

Fe-59*

I Co-58 I

Co-o60 I

Zn-65*

I Cs-134 I

Cs-137" J 04/10/12 1.73E+03

+/-

5.26E+02 3.44E+01

< 9.42E+01

< 3,05E+01

< 3.83E+01 6.70E+01 3.11E+01 3.75E+01 10/24/12 2.56E+03

+/-

7.87E+02 5.12E+01

< 1.30E+02 5.59E+01

< 5.60E+01 1.24E+02 5.34E+01

< 6.03E+01 Mean 2.32E+03 +/-

7.63E+02 Indicator 2.32E+03

+/-

7.14E+02 Control 1.74E+03

+/- 8.13E+02

LLD identified in ODCM

- Control Station

[a] Non-bottom dwelling species of gamefish.

[b] Bottom dwelling species of fish.

59

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2012 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 2012 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 2012 reporting period.

4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. TLDs are placed in two concentric rings around the station. The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population areas and nearby residences.

Additional TLDs serve as controls. Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.

The results of the analyses are presented in Table 3-2. Figure 4-1 shows the historical trend of TLD exposure rate measurements.

Control and indicator averages indicate a steady relationship. Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location. These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001.

The dose with the replacement TLDs is lower than that of the previously used TLDs. This will continue to be monitored.

60

!)..1 8.0 7.0..........

6.0 5.0 Environmental TLIs

-U--Sector TLIDs 3

-*--Avg. Pre-op 2.0 1.0 0.0 I

'0D 00 0

f4

1

O 00 0

rJ

'.O 00 0

e~

l 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 1.4 to 8.6 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61. This value was 7.0 mR/standard month. This location is on site on the north gate of the construction side laydown area. Quarterly and annual TLDs are also located at twelve environmental air sampling stations.

For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3.2 mR/standard month with a range of 2.1 to 4.5 mR/standard month. The average annual reading for these locations was 4.0 mR/standard month with a range from 3.0 to 6.1 mR/standard month. The control location showed a quarterly average of 4.5 mR/standard month with a range of 3.6 to 4.9 mR/standard month.

Its annual reading was 6.1 mR/standard month.

10 emergency sector TLDs, which are all located onsite had a quarterly average of 4.9 mR/standard month with EPSP-9/ 10 having the highest quarterly average of 7.2 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 3.0 mR/standard month with a range of 2.0 to 3.7 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

61

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. The drop indicated in 2009 may be a function of 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

M MY M eý M

M l4 919ý 4444 I44444 ý4 4 4 Control Sta-24 Incicator i

Averag Pro-op Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 62

2.50E-02 2.00E-02 1.smF-?

4-1.00E-02 5.OOE-03 +

O.OOE'-+O S.

C Control STA 24 -U-Indicator Figure 4-3 2012 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.

4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectrometry. The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected. The results of these analyses indicate the lack of station effects on the environment.

4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations. There has been no detection of 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 2012.

63

I

?

4.7 Precipitation A sample of rain water was collected monthly at on-site station 0 1A and analyzed for gross beta activity. In November they were also analyzed for H-3. The results are presented in Table 3-7.

12 precipitation samples were obtained in 2012. Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements. Zn-65 was reported in one precipitation 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.

Naturally occurring gamma emitting radioisotopes were detected. No positive H-3 results were reported. 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 2012 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. No samples indicated positive results. 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 the collection station 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.

64

I 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. Cs-137 was reported in one 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.

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. During the second quarter we requested that the vendor analyze for Sr-89, Sr-90, H-3, 1-131, and gamma emitters. The second quarter sample was analyzed for Sr-89, Sr-90, H-3, and Iodine-131; however, it was not analyzed for gamma emitters. This analysis was missed. There was a duplicate analysis run on Sr-89 and Sr-90 so there was no sample remaining for further analysis once we confirmed that the gamma isotopic analysis was missed. The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period.

4.11 River Water A sample of water from the North Anna River was collected monthly. The analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy. The monthly samples were composited quarterly and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90 in accordance with program requirements. There has been no detection of these fission products at any of the indicator or control stations in recent years.

No gamma emitting radioisotopes were positively identified in any of the samples. There was no measured activity of strontium-89 or strontium-90. Tritium was measured in all four samples with an average annual concentration of 3050 pCi/liter and a range of 2040 to 4340 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.

65

8000 7000 6000

_ 5000 (4000 3000 2000 1000 Date

-*-H-31n RWTrItium

-H-31n RWRequired LLD]

Figure 4-4Tritium in River water 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW.

The samples were analyzed by gamma ray spectrometry and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium.

Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90. There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.

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 2600 pCi/liter with a range of 2260 to 2790 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.

66

r V

10000 1000 Trdtlum L

100 Required LLD a--

10 Average Pre-op

=01 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 2012.

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 2012. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests. A number of naturally occurring radioisotopes were detected in these samples at background levels.

67

e 10000 1000 100 10 1

Date Station-8

-a-- Statlon-9 Control-Sta-09A Station-I I

-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. Cs-137 was identified in the control station during October. No plant related isotopes were detected in the two indicator samples analyzed. Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is attributed to accumulation of residual global fallout from past atmospheric weapons testing.

4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2012 and analyzed by gamma spectroscopy. Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately. The results are presented in Table 3-15. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected.

Cs-137 was measured in pre-operational environmental fish samples.

68

I

~

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2012 -- North Anna Location 14B,15,16,23, 26 14B,15,16,23, 26 14B, 15,16,23, 26 STA 6 Description Vegetation Vegetation Vegetation AP/Char Date of Sampling 01/10/12 Reason(s) for Loss/Exception Seasonal unavailability 02/14/12 03/13/12 03/20/12 07//31/12 STA 3,5 AP/Char Seasonal unavailability Seasonal unavailability Sampler not running/ replaced. No sample for this week.

Power lost to samplers due to storm/power outage. Minimum volume not met per procedure.

However, vendor met LLD.

Sampler not running/ replaced. Minimum volume met.

Seasonal unavailability Seasonal unavailability Sample not analyzed by vendor for gamma isotopic STA 23 14B,15,16,2 3,26 14B, 15,16,2 3,26 AP/Char Vegetation Vegetation Well Water 03/20/12 11/13/12 12/11/12 06/26/12 STA 01A 69

REFERENCES 70

References Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.

Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications.

Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".

Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010, "Radiological Environmental Monitoring Program".

Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities".

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 I OCFR50, Appendix I", October, 1977.

United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975.

USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.

NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.

HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 2 7th Edition, Volume 1, February 1992.

NUREG/CR-4007, "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.

71

APPENDICES 72

f I

APPENDIX A: LAND USE CENSUS Year 2012 73

LAND USE CENSUS North Anna Power Station Louisa County, Virginia January 1 to December 31, 2012 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden (>

Meat Milch Milch Boundaryt 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 2.37 2.4 2.7 NONE NONE E

0.8 1.3 2.0 3.5 NONE NONE ESE 0.9 1.7 1.7 NONE NONE NONE SE 0.9 1.4 1.5 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 2.34 2.0 NONE NONE SW 1.1 1.65 1.65 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 74

a,.

2011 to 2012 Land Use Census Changes 2011 2012 Nearest Direction Distance Distance Site Boundary NONE Resident ENE 2.2 2.37 SW 1.7 1.65 Garden SSW 3.1 2.34 SW 2.6 1.65 Meat Animal ESE 4.9 NONE Milch Cow NONE Milch Goat NONE 75

A i APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2012 76

I INTRODUCTION This appendix covers the Intercomparison Program of the Teledyne Brown Engineering -

Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). TBE uses QA/QC samples provided by Eckert

& Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) and Environmental Resource Associates, (ERA) to monitor the quality of analytical processing associated with the REMP. The suite of samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides. This includes:

E & Z Analytics:

Milk for gamma emitters, Iodine-131, Fe-55, Sr-89 and Sr-90 analyses once per quarter.

Air particulate for gamma emitters once per quarter Charcoal for 1-131 once per quarter 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 Ist quarter.

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

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

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

RESULTS Interlaboratory comparison program results are evaluated using TBE's criterion.

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

For the primary laboratory, 14 out of 18 analytes met the specified acceptance criteria. Four analytes (one sample each of Co-60, Sr-89, Sr-90 and Gross Alpha) did not meet the specified acceptance criteria.

Nonconformance Reports were generated and corrective actions taken as a result of this program.

NCR-12-05: ERA Rad89 Gross alpha is slightly biased high for Th-230 on Detector G1.

NCR 12-08: No cause was found for the failed high soil Co-60 sensitivity test or the high 77

Zn-65 in AP, which TBE considers anomaly.

NCR 12-11: Sr-90 in water high due to incorrect aliquot entered in LIMS.

NCR 12-13 The Sr-89 found to known ratio was 1.19, which TBE considers acceptable. It appears the aliquot was entered incorrectly.

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

78

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ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 2012 (PAGE I OF 3)

Table F-1 Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2012 E10066 E10067 E10069 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 101 pCi/L 11.7 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 87.5 247 435 133 156 127 190 179 327 274 167 310 107 109 87.6 133 113 226 185 94.8 13.5 92.5 260 436 149 159 132 195 168 333 279 164 276 94.5 101 83.5 123 106 210 176 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 June 2012 E10068 E10070 E10198 E10199 E10201 E10200 pCi pCi/L 1800 1570 pCi/L 86.1 99.8 pCi/L 9.2 12.7 92.8 94.2 1.07 0.87 0.95 0.95 1.00 0.89 0.98 0.96 0.97 1.07 0.98 0.98 1.02 1.12 1.13 1.08 1.05 1.08 1.07 1.08 1.05 0.99 1.15 0.86 0.72 0.89 0.89 0.98 0.91 0.97 0.97 0.98 1.01 0.97 0.96 0.97 1.00 1.04 1.06 1.01 0.98 1.07 0.99 1.04 1.05 A

A A

A W

A A

A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 88.9 72.8 394 159 206 89.5 129 129 193 342 73.2 367 165 205 84.7 118 125 181 338 99.7 82.2 402 174 212 92.3 132 128 199 355 75.1 366 159 193 84.2 121 117 182 324 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 101 96.6 A

79

I, ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 2012 (PAGE 2 OF 3)

Table F-1 Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

June 2012 E10202 Water Fe-55 September2012 E10296 E10297 E10299 E10298 pCi/L 1890 1580 pCi/L 106 99.6 pCi/L 13.6 16.0 Milk Milk Sr-89 Sr-90 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 pCi pCi pCi pCi pCi pCi pCi pCi pCi 89.8 160 230 101 174 97.2 188 159 195 155 145 219 94.1 140 88.3 173 136 165 133 99.6 164 248 108 174 100 196 152 192 152 135 205 89.4 144 83.0 162 125 159 125 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi 95.5 97.2 pCi/L 1630 1900 1.20 1.06 0.85 0.90 0.98 0.93 0.94 1.00 0.97 0.96 1.05 1.02 1.02 1.07 1.07 1.05 0.97 1.06 1.07 1.09 1.04 1.06 0.98 0.86 1.05 0.82 1.03 1.03 1.07 0.95 0.97 0.96 1.00 1.07 1.02 1.01 1.04 1.10 1.02 0.99 1.01 1.05 0.94 0.92 1.08 A

A A

A E10300 December2012 E10334 E10335 El 0337A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 101 pCi/L 11.3 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 93.1 52.5 373 157 113 94.1 116 124 190 172 51.8 372 165 113 96.5 118 105 166 179 96.6 13.8 90.0 51.0 348 165 117 98.5 116 116 186 170 49.6 338 161 114 95.8 112 112 181 165 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 80

.~

~

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 2012 (PAGE 3 OF 3)

Table F-1 Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2012 E10336 Charcoal 1-131 Water Fe-55 pCi 73.1 72.7 1.01 0.89 A

A E10333 pCi/L 1550 1750 (a)

(b)

(c)

(d)

Teledyne Brown Engineering reported result.

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

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.

81

4.

A.

ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 2012 (PAGE 1 OF 1)

Table F-2 Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Limits Evaluation (c)

May 2012 RAD-89 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 63.4 33.5 89.2 66.5 152 73.3 109 82.4 43.6 25.9 15433 58.5 37.4 82.3 74.2 155 72.9 105 62.9 44.2 27.1 15800 46.9 - 66.3 27.4 -43.1 69.1 -90.5 60.6-81.6 140- 172 65.6 - 82.6 94.5 - 125 33.0 - 78.0 29.6-51.5 22.5-31.9 13800 - 17400 A

A A

N (i)

A A

A MRAD-16 Filter Gr-A pCi/filter 39.5 77.8 26.1-121 A

November, 2012 RAD-91 MRAD-17 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 46.5 16.6 85.2 76.9 177 77.4 209 50.6 59.3 22.9 5020 39.1 20.1 84.8 76.6 183 78.3 204 58.6 39.2 24.8 4890 29.7 -46.1 14.4-23.8 71.3 - 93.3 62.6 - 84.3 165-203 70.5 - 88.5 184 - 240 30.6 - 72.9 26.0 - 46.7 20.6 - 29.4 4190-5380 29.3 - 136 N (2)

A A

A N (2)

A A

A Filter Gr-A pCi/filter 59.6 87.5 (1) Detector G I is slightly biased high for Th-230 based measurements used only for ERA Gross Alpha samples. NCR 12-05 (2) The Sr-89 found to known ratio was 1.19, which TBE considers acceptable. It appears the aliquot was entered incorrectly for the Gross Beta NCR 12-13 (a) Teledyne Brown Engineering reported result.

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

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

82

a r

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.h DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 2012 (PAGE 1 OF 2)

Table F-3 Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

March 2012 12-MaW26 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L

-0.0045 37.5 30.8 22.4 456 31.0 144

-0.0084

-0.369 39.9 32.9 23.72 437 31.8 142 (1) 27.9-51.9 23.0 -42.8 16.60 - 30.84 306-568 22.3-41.3 99-185 (1)

(1)

A A

A 12-GrW26 12-MaS26 12-RdF26 Bq/L 2.06 2.14 0.64 - 3.64 Bq/L 7.48 6.36 3.18 - 9.54 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 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 831 0.145 1270 7.61 634 1690 328 753 2.31 2.15

-0.0701 2.62 4.13 0,0185 4.19 828 1179 1.56 558 1491 392 642 580-1076 (1) 825-1533 (2) 391 -725 1044-1938 274-540 449-835 A

A A

N (3)

A A

A W

W A

N (3) 12-GrF26 12-RdV26 September 2012 12-MaW27 AP Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-1 34 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Bq/sample 0.365 1.2 Bq/sample 2.31 2.4 2.38 1.67 - 3.09 1.79 1.25 -2.33 (1) 2.182 1.527 - 2.837 3.24 2.27 - 4.21 (1) 2.99 2.09 - 3.89 0.4-2.0 1.2-3.6 A

A Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 8.72 0.0424 15.5 6.80 0.0057 2.24 10.5 21.4 17.0 28.7 0.179 387 18.1 139 19.6 27.2 8.43 5.90 - 10.96 (1) 12.0 8.4-15.6 6.05 4.24 - 7.87 (1) 2.11 1.48-2.74 8.90 6.23 - 11.57 23.2 16.2 - 30.2 16.7 11.7-21.7 29.3 20.5 - 38.1 (1) 334 234-434 17.8 12.5 -23.1 134 94-174 12.2 8.5-15.9 25.9 18.1 - 33.7 A

A W

A A

A N (4)

A 12-GrW27 Bq/L 0.966 1.79 Bq/L 10.0 9.1 0.54 - 3.04 4.6-13.7 A

A 83

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

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 2012 (PAGE 2 OF 2)

Table F-3 Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

September 2012 12-MaS27 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 880 1220 1330 552 1000 674 528 665 939 1150 1316 531 920 632 508 606 2.74 191.00 1.728 2.36 1.03 12-RdF27 12-GrF27 12-RdV27 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B 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 2.760 0.0415 2.00 1.78 2.40 0.931

-0.688 657-1221 805-1495 921 -1711 372 - 690 644-1196 442 - 822 356 - 660 424 - 788 1.92-3.56 (1) 1.34 -2.48 1.210 - 2.246 1.65-3.07 0.72-1.34 (1) 0.29 - 1.65 0.96 - 2.88 4.56 - 8.46 3.07 - 5.69 3.96 - 7.36 3.58 - 6.66 2.29 -4.25 (1)

(1)

A A

Bq/sample 0,434 0.97 Bq/sample 1.927 1.92 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 6.28 4.62 6.51 5.32 3.59 0.0012

-0.046 6.51 4.38 5.66 5.12 3.27 (1) False positive test.

(2) Sensitivity evaluation (3) No cause was found for the failed high soil Co-60 sensitivity test or the high Zn-65 in AP, which TBE considers an anomaly. NCR 12-08 (4) Sr-90 in water high due to incorrect aliquot entered in LIMS. 12-11 (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 gravi/metric and/or volumetric measurements made during standard preparation.

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

84

ML13114A056

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