Text

Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report
	ML15105A241
Person / Time
Site:	North Anna
Issue date:	04/10/2015
From:	Gerald Bichof; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	15-177
	Download: ML15105A241 (90)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 10, 2015 United States Nuclear Regulatory Commission Serial No.15-177 Attention: Document Control Desk NAPS/JHL Washington, D. C. 20555 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-417 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSl)

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 5.5.2, enclosed is the 2014 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 S4A5 2-E p'~4s

Serial No.15-177 NAPS Annual Radiological Environmental Operating Report cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station

Dominion North Anna Power Station RadiologicalEnvironmentalMonitoringProgram January1, 2014 to December 31, 2014 Preparedby Dominion, North Anna Power Station

Annual RadiologicalEnvironmental OperatingReport North Anna PowerStation January1, 2014 to December 31, 2014 Preparedby:

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

Aziz A. Malyj Supervisor Health Physics Technical Services Dominion North Anna Power Station

- ~~Robert B. Evans HE heisr Approved by:

Manager Radiological Protect n and Chemistry Dominion North Anna Power Station 2

Table of Contents

1. EX ECU TIV E SU M M A R Y ....................................................................................................... 4

2. PRO GRA M DESCRIPTION ........................................................................................................ 7 2.1 Introduction ............................................................................................................................. 7 2.2 Sampling and Analysis Program ........................................................................................ 8

3. AN A LY TICA L RESU LTS ........................................................................................................ 22 3.1 Sum m ary of Results ........................................................................................................ 22 3.2 A nalytical Results of 2014 REM P Sam ples ................................................................... 32

4. D ISCU SSION 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 ...................................................................................................... 64 4.4 A ir Particulate G am m a ................................................................................................... 64 4.5 A ir Particulate Strontium ................................................................................................. 64 4 .6 So il ........................................................................................................................................ 64 4.7 Precipitation .......................................................................................................................... 64 4.8 Cow M ilk .............................................................................................................................. 65 4.9 Food Products and V egetation ........................................................................................ 65 4.10 W ell W ater .......................................................................................................................... 66 4.11 R iver W ater ......................................................................................................................... 66 4.12 Surface W ater ...................................................................................................................... 67 4.13 Bottom Sedim ent ................................................................................................................ 68 4.14 Shoreline Soil ...................................................................................................................... 69 4 .15 F ish ...................................................................................................................................... 70

5. PRO G RA M EX CEPTIO N S ..................................................................................................... 71 REFEREN CES .................................................................................................................................... 72 A PPEN D ICES ..................................................................................................................................... 73 APPEN D IX A : LAN D U SE CEN SU S ...................................................................................... 74 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS .......................... 77 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2014 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, 2014, 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 2014 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 2014 was 2630 pCi/liter. No other plant related isotopes were reported in any 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 2870 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. No plant related isotope was detected in the indicator or control locations in shoreline soil. No plant related isotope was 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 2014.

The terrestrial exposure pathway includes milk and food/vegetation products. No plant related radioisotope was detected in any milk samples. Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data. No plant related isotope was detected in any vegetation sample. Low levels of Cs- 137 have been detected intermittently in past years.

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The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years.

During 2014, 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 2014 was 0.39 millirem. For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural background sources in the environment provide approximately 50% of radiation exposure to man, while medical uses provide approximately 48%.

By comparison, 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 2014 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).

The North Anna Power Station of Virginia Electric and Power Company (Dominion) 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 has a gross electrical output of 1029 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. The pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact. of station operation.

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

reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2014 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 2014 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 2014.

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TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental NAPS Sewage Treatment Plant 01 0.20 NE 420 Quarterly & Annually Thermoluminescent Fredericks Hall 02 5.30 SSW 2030 Quarterly & Annually Dosimetry (TLD) Mineral, Va 03 7.10 WSW 2430 Quarterly & Annually Wares Crossroads 04 5.10 WNW 2870 Quarterly & Annually Route 752 05 4.20 NNE 200 Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N 110 Quarterly & Annually Levy, VA 06 4.70 ESE 1150 Quarterly & Annually Bumpass, VA 07 7.30 SSE 1670 Quarterly & Annually End of Route 685 21 1.00 WNW 3010 Quarterly & Annually Route 700 22 1.00 WSW 2420 Quarterly & Annually "Aspen Hills" 23 0.93 SSE 1580 Quarterly & Annually Orange, VA 24 22.00 NW 3250 Quarterly & Annually Control Bearing Cooling Tower N-1/33 0.06 N 100 Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 110 Quarterly Parking Lot "C" (on-site) NNE-3/35 0.24 NNE 320 Quarterly Good Hope Church NNE-4/36 3.77 NNE 250 Quarterly Parking Lot "B" NE-5/37 0.20 NE 420 Quarterly Lake Anna Marina (Bogg's Dr) NE-6/38 1.46 NE 340 Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 740 Quarterly Route 689 ENE-8/40 2.43 ENE 650 Quarterly Near Training Facility E-9/41 0.30 E 910 Quarterly "Morning Glory Hill" E-10/42 2.85 E 930 Quarterly Island Dike ESE-l 1/43 0.12 ESE 1030 Quarterly Route 622 ESE-12/44 4.70 ESE 1150 Quarterly DVP Biology Lab SE-13/45 0.64 SE 1380 Quarterly Route 701 (Dam Entrance) SE-14/46 5.88 SE 1370 Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 1580 Quarterly Elk Creek SSE-16/48 2.33 SSE 1650 Quarterly NAPS Access Rd. S-17/49 0.36 S 1730 Quarterly 9

NO.

TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION UNIT DISTANCE AND DIRECTION FROM 2014 UNIT NO. 1 STATION FROM Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 SAMPLING 2-1S Power DIRECTION Station Anna AND North RADIOLOGICAL DISTANCE TABLE 1780 Quarterly Thermoluminescent NAPS Access Rd. SSW-19/51 0.24 SSW 1970 Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 2050 Quarterly 500kv Tower SW-21/53 0.60 SW 2180 Quarterly Route 700 SW-22/54 3.96 SW 2320 Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 2370 Quarterly Route 700 (Exclusion Boundary) WSW-24/56 1.00 WSW 2420 Quarterly South Gate Switchyard W-25/57 0.32 W 2790 Quarterly Route 685 W-26/58 1.55 W 2740 Quarterly End of Route 685 WNW-27/59 1.00 WNW 3010 Quarterly Route 685 WNW-28/60 1.40 WNW 3030 Quarterly North Gate - Laydown Area NW-29/61 0.52 NW 3210 Quarterly Lake Anna Campground NW-30/62 2.54 NW 3190 Quarterly

1/#2 Intake NNW-31/63 0.07 NNW 3490 Quarterly Route 208 NNW-32/64 2.21 NNW 3440 Quarterly Bumpass Post Office C-1/2 7.30 SSE 1670 Quarterly Orange, VA C-3/4 22.00 NW 3250 Quarterly Control Mineral, VA C-5/6 7.10 WSW 2430 Quarterly Louisa, VA C-7/8 11.54 WSW 2570 Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 420 Weekly and Radioiodine Biology Lab O0A 0.64 SE 1380 Weekly Mineral, VA 03 7.10 WSW 2430 Weekly Wares Crossroads 04 5.10 WNW 2870 Weekly Route 752 05 4.20 NNE 200 Weekly Sturgeon's Creek Marina 05A 2.04 N 110 Weekly Levy, VA 06 4.70 ESE 1150 Weekly Bumpass, VA 07 7.30 SSE 1670 Weekly 10

TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 NO. 1 UNIT 2014

-STATION FROM Collection Sample Media Location Station Station SAMPLING Distance Power Direction Degrees Frequency Remarks AND Anna NorthDIRECTION TABLE RADIOLOGICAL DISTANCE Airborne Particulate End of Route 685 21 1.00 WNW 3010 Weekly and Radioiodine Route 700 22 1.00 WSW 2420 Weekly "Aspen Hills" 23 0.93 SSE 1580 Weekly Orange, VA 24 22.00 NW 3250 Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 1480 Monthly (Second Cooling Lagoon)

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

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

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

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

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

Soil NAPS Sewage Treatment Plant 01 0.20 NE 420 Once/3 years Fredericks Hall 02 5.30 SSW 2030 Once/3 years Mineral, VA 03 7.10 WSW 2430 Once/3 years Wares Crossroads 04 5.10 WNW 2870 Once/3 years 11

TABLE 2-1 North Anna Power Station - 2014 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 05A 2.04 N 110 Once/3 years Levy, VA 06 4.70 ESE 1150 Once/3 years Bumpass, VA 07 7.30 SSE 1670 Once/3 years End of Route 685 21 1.00 WNW 3010 Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 2420 Once/3 years "Aspen Hills" 23 0.93 SSE 1580 Once/3 years Orange, VA 24 22.00 NW 3250 Once/3 years Control Milk Lakeside Dairy 12A 7.50 NW 3100 Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)

Lake Orange 25 16.5 NW 3120 Semi-Annually Control Food Products (Vegetation) Stagecoach Road 14B 1.22 NNE 400 Monthly if available or at harvest Route 614 15 1.37 SE 1330 Monthly if available or at harvest Route 629/522 16 12.60 NW 3140 Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 1580 Monthly if available or at harvest "Historic Lane" 26 1.15 S 1720 Monthly if available or at harvest 12

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

(84 TLDs) Quarterly Gamma Dose 2 mR+2mR mR/std. Month (12 TLDs) Annually Gamma Dose 2 mR+2mR mR!std. Month Airborne Radioiodine Weekly 1-131 0.07 pCi/m3 3

Airborne Particulate Weekly Gross Beta 0.01 pCi/m 3

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

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

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

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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TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS La- 140 15 River Water Quarterly(a) Tritium (H-3) 2000 pCi/L 2 nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

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

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

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

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

Sr-90 (b)

Precipitation Monthly Gross Beta 4 pCi/L Semi-Annual Gamma Isotopic pCi/L Composite Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1.-131(d)

Cs-134 15 Cs-137 18 Ba- 14 0 (d)

La- 140(d)

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.

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TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

Soil Once per 3 years Gamma Isotopic pCi/kg (dry)

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

Sr-90 (b)

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

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

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

(Broadleaf available, or Cs-134 60 Vegetation) at harvest Cs-137 80 1-131 60

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

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter (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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Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Map Environmental Station Designation Identification Designation Identification 1 (a) 01,NE-5/37 7/8 C-7/8 IA 01A,SE-13/45 1/33 N-1/33 2 (a) 02,SSW-20/52 31/63 NNW-31/63 3 (a) 03,C-5/6 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) 05 7/39 ENE-7/39 5A (a) 05A,N-2/34 9/41 E-9/41 6 (a) 06,ESE-12/44 11/43 ESE- 11/43 7 (a) 07, C-1/2 17/49 S-17/49 8 08-Water, Fish, Sediment, 19/51 SSW-19/51 Shoreline Soil 21/53 SW-21/53 9A 09A-Water sample, Sediment 23/55 WSW-23/55 1I 11-River Water, Sediment 12A 12A-Milk 25/57 W-25/57 14B 14B-Vegetation 16/48 SSE-"16/48 15 15-Vegetation 14/46 SE- 14/46 16 16-Vegetation 22/54 SW-22/54 21 (a) 21,WNW-27/59 26/58 W-26/58 22 (a) 22,WSW-24/56 28/60 WNW-28/60 23 (a) 23-SSE- I 5/47,Vegetation 32/64 NNW-32/64 24 (a)(b) 24,C-3/4 8/40 ENE-8/40 25 (c) 25-Fish 4/36 NNE-4/36 26 26-Vegetation 10/42 E-10/42 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.

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

ESE D

Legend 174 S SE*13145 I* Fixed Enwmmntal

TLD Monbin- A Locabons boi Scale - WS mnch~

- 235 fL Figure 1. North Anna Site Radiological Monitoring Locations 17

18 North Anna Environmental Map

. Fixed Environmental Sampling Location O TLD Sampling Garden Residents

. Meat Animals Orlginui 191 byADC otlWxnroia. Imc.64O GenealGrwnVfty AkMMiira. VA 22312. USE-D AM~PERMSSION. NO OINK Woroudlon maybe made w11hoqfm wdftkn pennisio of ADC.

C832ME 19

North Anna Environmental Map O Fied Environmental Sampling Location S TLD Sampling

Garden Residents

. Meat Animals OfVWCi ISM byADC ~of Alruiwk.hrc.6440Guw~erGmui Wy.

AkmiwiaWVAM32 USAD NTH PERMISSION NocOhwraupmjebw may be mude wIUhm* ft wkn pa visehan dADO.

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North Anna Environmental Map SFbied Environmental Sampling Location TLD Sampling

Garden Residents O Meat Animals Or~WtgIW19 byADC fAtMmmnfl& Inc. 640G-wN Grfteei Nemdftla.VA2=231.USEDTH PERMSSKON. N~ooterrepdtxhn may be mad. vilout lI* wils pwniwimso oEADC 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.

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 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-Type INo. _ I Direction Range Range . ments Direct Radiation Gamma 256 2 4.0(256/256) 29/61 0.52 mi. 7.1(8/8) 3.15(16/16)* 0 (mR/std. Month) Dose (1.3-8.0) NW (5.6-7.6) (2.6-3.7)

(Sector TLDs)

Direct Radiation Gamma 32 2 2.4(16/16) C-1/2 11.54 2.7(8/8) 3.15(16/16)* 0 mi. (2.6-3.7)

(mR/std. Month) Dose (1.6-3.4) WSW (2.2-3.4)

(Pre-operational TLDs)

Direct Radiation Gamma 40 2 4.9(40/40) EPSP- 0.37 mi. 7.1(8/8) 3.15(16/16)* 0 (mR/std. Month) Dose (3.0-8.2) 09/10 ENE (6.2-8.2) (2.6-3.7)

(Emergency Sector TLDs)

Direct Radiation Gamma 48 2 3.2(44/44) 23 0.93 mi. 5.0(4/4) 2.7(4/4) 0 (mR/std. month) Dose (1.6-5.8) SSE (4.3-5.8) (2.5-3.1)

(Environmental TLDs)

Direct Radiation Gamma 12 2 2.9(11/11) 06 4.70 mi. 4.1(1/1) 2.8(1/1) 0 (mR/std. Month) Dose (2.0-4.1) ESE (4.1) (2.8)

(Annual TLDs)

Airborne Gross 676 0.01 15.4(619/624) 23 0.93 mi. 17.4(52/52) 16.2(52/52) 0 Particulates Beta (6.75-29.8) SSE (10.6-28.5) (10.4-27.2)

(I E-03 pCi/m 3 )

Air Iodine 1-131 676 0.07 (0/624) N/A N/A. N/A N/A 0 3

(pCi/m )

Airborne Gamma 52 Particulates (IE-03 pCi/m 3 ) Be-7 52 116(48/48) 01 0.2 mi. 129(4/4) 131(4/4) 0 (83.9-164) NE (116-135) (119-151)

Cs-134 52 0.05 (0/48) N/A N/A N/A (0/4) 0 (1) mR/std month for TLDs

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 2 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine S ahame(LLD Reported Sampled (Unit) Total (pCi/unit) Mean Name Distance Mean Mean Measure-

---Ptwy--_ Type No. Range Direction Range Range ments Airborne Cs-137 52 0.06 (0/48) N/A N/A N/A (0/4) 0 Particulates (1E-03 pCi/m 3 ) Sr-89 13 (0/12) N/A N/A N/A (0/1) 0 Sr-90 13 (0/12) N/A N/A N/A (0/1) 0 Soil* Triennial (pCi/Kg) (dry) Gamma 12 K-40 12 N/A N/A N/A N/A N/A 0 Cs-134 12 150 N/A N/A N/A N/A N/A 0 Cs-137 12 180 N/A N/A N/A N/A N/A 0 Ra-226 1_ N/A N/A N/A N/A N/A 0 Th-228 12 N/A N/A N/A N/A N/A 0 Th-232 12 N/A N/A N/A N/A N/A 0 Sr-89 1, N/A N/A N/A N/A N/A 0 Sr-90 12 N/A N/A N/A N/A N/A 0 Precipitation Monthly (pCi/liter) Gross 12 4 3.46(10/12) 01A 0.64 mi. 3.46(9/12) N/A 0 Beta (1.64-11.2) SE (1.64-11.2)

H-3 2 2000 (0/2) N/A N/A N/A N/A 0 Semiannual 2 Gamma Be-7 2 - (0/2) 01A N/A N/A N/A 0 Mn-54 2 15 (0/2) N/A N/A N/A N/A 0 Fe-59 2 30 (0/2) N/A N/A N/A N/A 0 Co-58 2 15 (0/2) N/A N/A N/A N/A 0

Soil Samples required triennially. Samples not obtained in 2014..

24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 3 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Tot (pCi/unit) Mean Name Distance Mean Mean Measure-Type al Range Direction Range Range ments No. I I I I _II Precipitation Co-60 2 15 (0/2) N/A N/A N/A N/A 0 (pCi/liter)

Zn-65 2 30 (0/2) N/A N/A N/A N/A 0 Zr-95 30 (0/2) N/A N/A N/A N/A 0 Nb-95 15 (0/2) N/A N/A N/A N/A 0 1-131 10 (0/2) N/A N/A N/A N/A 0 Cs-134 15 (0/2) N/A N/A N/A N/A 0 Cs-137 18 (0/2) N/A N/A N/A N/A 0 Ba-140 (0/2) N/A N/A N/A N/A 0 La- 140 (0/2) N/A N/A N/A N/A 0 Th-228 (0/2) N/A N/A N/A N/A 0 25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 4 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/utit) Mean Name Distance Mean Mean Measure-(Unit) Type No. Range I Direction Range Range ments Gamma 12 Milk (pCi/liter)

K-40 12 - 1340(12/12) 12A 7.50 mi. 1340(12/12) N/A 0 (1210-1460) NW (1210-1460) 1-131 12 1 (0/12) N/A N/A. N/A N/A 0 Cs-137 12 18 (0/12) N/A N/A N/A N/A 0 Ba-140 12 60 (0/12) N/A N/A N/A N/A 0 La-140 12 15 (0/12) N/A N/A N/A N/A 0 Sr-89 4 (0/4) N/A N/A N/A N/A 0 (Quarterly)

Sr-90 4 (0/4) N/A N/A N/A N/A 0 (Quarterly) 26

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 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 Direction Range Range ments Food Gamma 35 Vegetation (pCi/kg) (wet) Be-7 35 1320(24/24) 15 1.37mi 1520(6/6) 1330(6/6) 0 (343-3160) SE (487-3160) (681-2450)

K-40 35 6280(24/24) 14B 1.22mi 7220(6/6) 6110(6/6) 0 (3830-8800) NNE (4910-8300) (5920-8360) 1-131 35 60 (0/24) N/A N/A N/A (0/6) 0 Cs-134 35 60 (0/24) N/A N/A N/A (0/6) 0 Cs-137 35 80 (0/24) N/A N/A N/A (0/6) 0 Ground Tritium 4 2000 (0/4) N/A N/A N/A N/A 0 Well Water (pCi/liter) Gamma Mn-54 15 (0/4) N/A N/A N/A N/A Fe-59 30 (0/4) N/A N/A N/A N/A Co-58 15 (0/4) N/A N/A N/A N/A Co-60 15 (0/4) N/A N/A N/A N/A Zn-65 30 (0/4) N/A N/A N/A N/A Zr-95 30 (0/4) N/A N/A N/A N/A Nb-95 15 (0/4) N/A N/A N/A N/A 1-131 10 (0/4) N/A N/A N/A N/A 27

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 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. I') Range Direction Range Range ments Ground Cs- 134 15 (0/4) N/A N/A N/A N/A 0 Well Water (pCi/liter) Cs-137 18 (0/4) N/A N/A N/A N/A 0 Ba- 140 60 (0/4) N/A N/A N/A N/A 0 La- 140 15 (0/4) N/A N/A N/A N/A 0 Sr-89 (0/1) N/A N/A N/A N/A 0 Sr-90 (0/1) N/A N/A N/A N/A 0 River Water Tritium 2000 2870(4/4) 11 5.80 mi. 2870(4/4) (0/4)* 0 (pCi/liter) (2430-3050) SE (2430-3050)

Gamma Mn-54 15 (0/12) N/A N/A N/A (0/12)* 0 Fe-59 30 (0/12) N/A N/A N/A (0/12)* 0 Co-58 15 (0/12) N/A N/A N/A (0/12)* 0 Co-60 15 (0/12) N/A N/A N/A (0/12)* 0 Zn-65 30 (0/12) N/A N/A N/A (0/12)* 0 Zr-95 12 30 (0/12) N/A N/A N/A (0/12)* 0 Nb-95 12 15 (0/12) N/A N/A N/A (0/12)* 0 1-131 12 1 (0/12) N/A N/A N/A (0/12)* 0 Cs-134 12 15 (0/12) N/A N/A N/A (0/12)* 0 Cs-137 12 18 (0/12) N/A N/A N/A (0/12)* 0

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 - 2014 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 INo. Range Direction Range Range ments River Water Ba- 140 12 60 (0/12) N/A N/A N/A (0/12)* 0 (pCi/liter)

La- 140 12 15 (0/12) N/A N/A N/A (0/12)* 0 1 (0/1) N/A N/A N/A (0/1)*

Sr-89 0 1 (0/1) N/A N/A Sr-90 N/A (0/1)* 0 Tritium 8 2000 2630(3/4) 08 3.37 mi. 2630(4/4) (0/4) 0 Surface Water (pCi/L) (1810-3070) SSE (1810-3070)

Gamma 24 Mn-54 24 15 (0/12) N/A N/A N/A (0/12) 0 Fe-59 24 30 (0/12) N/A N/A N/A (0/12) 0 Co-58 24 15 (0/12) N/A N/A N/A (0/12) 0 Co-60 24 15 (0/12) N/A N/A N/A (0/12) 0 Zn-65 24 30 (0/12) N/A N/A N/A (0/12) 0 Zr-95 24 30 (0/12) N/A N/A N/A (0/12) 0 Nb-95 24 30 (0/12) N/A N/A N/A (0/12) 0 1-131 24 1 (0/12) N/A N/A N/A (0/12) 0 Cs-134 24 15 (0/12) N/A N/A N/A (0/12) 0 Cs-137 24 18 (0/12) N/A N/A N/A (0/12) 0 Ba-140 24 60 (0/12) N/A N/A N/A (0/12) 0 La- 140 24 15 (0/12) N/A N/A N/A (0/12) 0

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 - 2014 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 Direction Range Range ments Surface Water Sr-89 l (0/1) N/A N/A N/A (0/1) 0 (pCi/liter) 1 Sr-90 (0/1) N/A N/A N/A (0/1) 0 Sediment Silt Gamma 6 (pCi/kg) K-40 6 12100 (4/4) 11 5.80 mi. 22550 (2/2) 30800(2/2) 0 SE (18300-(2340-16000) (27800-33800) 26800)

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

Cs-137 6 180 (0/4) N/A N/A. N/A 112(1/2) 0 (112)

Ra-226 6 - 2530(4/4) 11 5.80 mi. 2530(2/2) 1970(1/2) 0 (2370-2690) SE (2370-2690) (1970)

Th-228 6 766(4/4) 11 5.80 mi. 1430(2/2) 764(2/2) 0 (98.5-1840) SE (1020-1840) (448-1080)

Th-232 6 1425 (2/4) 11 5.80 mi. 1425(2/2) 642(2/2) 0 (1120-1730) SE (1120-1730) (414-869)

(Annually)

Sr-89 3 (0/2) N/A N/A N/A (0/1) 0 Sr-90 3 (0/2) N/A N/A N/A (0/1) 0 Shoreline Soil Gamma 2 (pCi/kg) (dry) K-40 2 1028.5(2/2) 08 3.37 mi. 1028.5(2/2) N/A 0 (527-1530) SSE (527-1530)

Cs- 134 2 150 (0/2) N/A NA (0/2) N/A 0 Cs-137 2 180 (0/2) N/A NA (0/2) N/A 0 Ra-226 2 (0/2) N/A N/A (0/2) N/A 0 30

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia- 2014 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.

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

Th-228 2 148(2/2) 08 3.37 mi. 148(2/2) N/A 0 (147-149) SSE (147-149)

Th-232 2 265 (1/2) 08 3.37 mi. 265(1/2) N/A 0 (265) SSE (265)

(Annually)

Sr-89 (0/1) N/A NA N/A N/A 0 1

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

K-40 8 1725(4/4) 8 3.37 mi. 1725(4/4) 1930(4/4) 0 (1400-1960) SSE (1400-1960) (1370-2410)

Mn-54 8 130 (0/4) N/A NA N/A (0/4) 0 Fe-59 8 260 (0/4) N/A NIA N/A (0/4) 0 Co-58 8 130 (0/4) N/A NA N/A (0/4) 0 Co-60 8 130 (0/4) N/A NA N/A (0/4) 0 Zn-65 8 260 (0/4) N/A NA N/A (0/4) 0 Cs-134 8 130 (0/4) N/A NA N/A (0/4) 0 Cs-137 8 150 (0/4) N/A NA N/A (0/4) 0 31

3.2 Analytical Results of 2014 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 (2y) of the net activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered true positives when the measured value exceeds both the MDC and the 2a error.

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

(November 1979, Revision 1) and the North Anna ODCM.

Data are given according to sample type as indicated below.

1. Gamma Exposure Rate

2. Air Particulates, Gross Beta Radioactivity

3. Air Particulates, Weekly 1-131

4. Air Particulates, Quantitative Gamma Spectra

5. Air Particulate Strontium

6. Soil

7. Precipitation

8. Cow Milk

9. Food Products and Vegetation

10. Well Water

11. River Water

12. Surface Water

13. Bottom Sediment/Silt

14. Shoreline Soil

15. Fish 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 RESUL TS Page mR/Std. Month (30.4 days) +/- 2 Sigma 1 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly*

Station 3/26/2014 6/24/2014 9/30/2014 Average 3/26/2014 6/24/2014 9/30/2014 12/30/2014 +/- 2 s.d.

N-1 5.1 4.6 4.5 4.2 4.6 +/- 0.9 N-33 5.0 4.2 3.9 4.9 N-2 3.4 3.0 3.1 2.4 2.9 +/- 0.7 N-34 3.1 2.9 2.5 2.4 NNE-3 6.4 6.1 6.2 7.2 6.6 +/- 1.3 NNE-35 7.6 5.7 6.7 7.2 NNE-4 4.4 3.3 3.7 3.6 3.8 +/- 0.8 NNE 36 3.7 3.8 4.4 3.6 NE-5 4.3 4.1 3.6 4.1 4.4 +/- 1.2 NE-37 5.3 4.4 5.2 3.9 NE-6 3.0 2.8 3.5 3.2 3.0 +/- 0.5 NE-38 2.9 3.1 2.8 2.7 ENE-7 4.9 4.9 5.3 4.3 5.0 +/- 1.0 ENE-39 4.4 5.6 4.7 5.6 ENE-8 2.2 3.0 2.9 2.0 2.4 +/- 0.9 ENE-40 2.0 2.5 2.5 1.8 E-9 4.9 4.6 5.1 5.0 4.7 +/- 0.8 E-41 4.0 4.1 5.0 4.6 E-1 0 4.0 3.9 4.6 4.9 4.3 +/- 0.9 E-42 3.7 4.1 4.6 4.6 ESE-11 3.5 4.0 4.3 3.6 3.6 +/- 1.1 ESE-43 2.9 3.2 4.4 3.1 ESE-12 3.3 4.6 3.7 4.6 4.1 +/- 1.1 ESE-44 4.0 4.8 4.4 3.6 SE-13 3.8 3.8 4.2 4.0 4.1 +/- 0.8 SE-45 4.8 3.7 4.4 3.7 SE-14 5.9 5.2 6.1 6.2 6.0 +/- 1.1 SE-46 6.2 5.5 5.8 7.0 SSE-15 5.3 4.3 4.9 4.3 4.6 +/- 0.8 SSE-47 4.9 4.2 4.9 4.2 SSE-16 2.1 2.5 2.7 2.4 2.5 +/- 0.5 SSE-48 2.2 2.8 2.7 2.3

Average of collocated TLDs.

33

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

Station 12/31/2013 3/26/2014 6/24/2014 9/30/2014 Average 3/26/2014 6/24/2014 9/30/2014 12/30/2014 +/- 2 s.d.

S-17 4.6 4.9 3.5 4.0 4.3 +/- 1.3 S-49 5.4 3.5 4.3 4.3 S-18 1.9 2.1 2.2 2.9 2.1 +/- 0.7 S-50 1.8 2.1 2.1 1.9 SSW-19 5.7 5.6 6.1 5.9 5.9 +/- 1.0 SSW-51 7.0 5.4 6.1 5.6 SSW-20 1.9 1.8 2.4 2.0 2.0 +/- 0.4 SSW-52 1.8 2.1 1.9 1.9 SW-21 6.5 4.6 3.9 4.4 4.5 +/- 1.8 SW-53 4.0 4.7 4.2 3.5 SW-22 3.4 3.8 4.4 3.5 4.0 +/- 1.1 SW-54 4.6 4.3 4.8 3.4 WSW-23 4.5 3.6 4.2 5.0 4.2 +/- 1.1 WSW-55 4.9 4.0 4.1 3.6 WSW-24 3.8 4.4 4.1 3.6 4.1 +/- 0.7 WSW-56 4.4 3.8 4.6 4.3 W-25 6.5 7.2 6.7 7.7 7.0 +/- 0.8 W-57 7.2 7.3 6.8 6.8 W-26 2.2 3.6 2.8 2.5 2.7 +/- 0.9 W-58 2.4 2.5 3.0 2.3 WNW-27 2.7 3.0 3.8 3.2 2.9 +/- 1.1 WNW-59 2.4 3.2 2.2 2.5 WNW-28 3.3 2.4 3.1 2.4 3.0 +/- 0.9 WNW-60 3.5 2.6 3.4 3.0 NW-29 7.3 5.6 7.2 7.6 7.1 +/- 1.4 NW-61 6.7 7.1 7.4 8.0 NW-30 1.6 1.7 1.3 1.6 1.7 +/- 0.6 NW-62 1.7 2.0 2.2 1.4 NNW-31 3.1 2.9 3.0 4.1 3.3 +/- 0.9 NNW-63 3.1 3.6 3.0 3.8 NNW-32 4.1 3.1 3.8 3.8 3.7 +/- 0.7 NNW-64 4.1 3.6 3.8 3.4 Mean 4.0 +/- 1.5

Average of collocated TLDs.

34

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

Station 12/31/2013 3/26/2014 6/24/2014 9/30/2014 Average 3/26/2014 6/24/2014 9/30/2014 12/30/2014 +/- 2 s.d.

C-1 2.4 2.8 3.1 2.4 2.7 +/- 0.9 C-2 3.2 2.3 3.4 2.2 C-3"* 2.7 2.8 3.2 2.6 3.0 +/- 0.7 C-4"* 3.4 2.9 3.5 2.6 C-5 1.7 2.2 2.3 1.7 2.1 +/- 0.9 2

C-6 2.8 1.8 2.6 1.6 C-7"* 3.2 3.2 3.1 3.5 3.3 +/- 0.5 C-8"* 3.7 3.0 3.6 3.0 2.4 +/- 1.1 3.1 +/- 0.7 EPSA-01 *** 4.4 3.9 4.3 4.3 1.2 +/- 0.5 EPSA-02*** 4.0 3.9 4.6 4.0 EPSF-03*** 4.5 3.0 4.1 4.6 3.8 +/- 1.2 EPSF-04*** 4.1 3.3 3.8 3.3 EPSR-05*** 5.7 5.5 5.0 4.9 5.4 +/- 0.9 EPSR-06*** 6.3 5.3 5.6 5.2 EPSJ-07*** 3.7 3.9 4.1 3.3 3.7 +/- 1.0 EPSJ-08*** 4.6 3.3 3.2 3.2 EPSP-09*** 7.3 7.0 7.2 7.9 7 .1 +/- 1.4 EPSP-1 0** 8.2 6.2 6.3 7.0 Mean 4.9 +/- 2.8

Average of collocated TLDs.

- Control Station

- - Emergency Plan TLDs.

35

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS Page mR/Std. Month (30.4 days) +/- 2 Sigma 4 of 4 First Quarter Second Quarter Third Quarter Fourth Quartei Quarterly Station 12/31/2013 3/26/2014 6/24/2014 9/30/2014 Average AnnualTLD 3/26/2014 6/24/2014 9/30/2014 12/30/2014 +/- 2 s.d.

STA-01 3.8 4.2 4.0 4.0 4.0 +/- 0.3 4.0 STA-02 2.1 2.2 2.4 1.6 2.1 +/- 0.7 2.3 STA-03 1.7 2.7 2.5 1.7 2.2 +/- 1.1 2.4 STA-04 2.2 2.8 2.0 2.1 2.3 +/- 0.7 2.0 STA-05 3.3 2.9 3.2 2.2 2.9 +/- 1.0 2.9 STA-05A 2.1 3.4 3.0 3.2 2.9 +/- 1.1 2.2 STA-06 4.1 4.3 4.4 4.3 4.3 +/- 0.3 4.1 STA-07 3.1 2.6 3.2 3.1 3.0 +/- 0.5 2.6 STA-21 2.7 2.7 3.1 2.2 2.7 +/- 0.7 2.5 STA-22 5.0 3.8 4.3 4.4 4.4 +/- 1.0 3.4

+/-

STA-23 5.3 4.5 5.8 4.3 5.0 +/- 1.4 3.8 STA-24* 2.5 2.7 3.1 2.5 2.7 +/- 0.3 2.8 Mean - Indicator Locations 3.2 1.0 2.9 +/- 1.5

Control 36

Table 3-3 Air Particulate page Gross Beta Radioactivity 1 of 4

[10-3 pC i/m3]

Period Station Station Station Station Station Station Station Ending I I I I I 05 I I 07 I 01/08/14 2.27E+01 3.22E+00 1.29E+01 2.36E+00 1.32E+01 2.44E+00 1.55E+01 2.53E+00 1.51E+01 2.49E+00 1.73E+01 2.60E+00 1.40E+01 2.43E+00 01/14/14 2.05E+01 3.46E+00 1.26E+01 3.03E+00 1.64E+01 3.25E+00 1.76E+01 3.30E+00 1.56E+01 3.20E+00 1.58E+01 3.21 E+00 1.93E+01 3.39E+00 01/21/14 1.45E+01 2.78E+00 1.39E+01 2.75E+00 1.47E+01 2.79E+00 1.50E+01 2.81E+00 1.48E+01 2.80E+00 1.96E+01 3.04E+00 1.19E+01 2.64E+00 01/28/14 1.37E+01 2.63E+00 1.49E+01 2.69E+00 1.12E+01 2.48E+00 1.69E+01 2.80E+00 1.58E+01 2.74E+00 1.63E+01 2.77E+00 1.59E+01 2.75E+00 02/04/14 2.15E+01 3.18E+00 1.55E+01 2.88E+00 1.79E+01 3.OOE+00 1.69E+01 2.95E+00 1.91E+01 3.06E+00 1.30E+01 2.75E+00 2.08E+01 3.14E+00 02/11/14 2.50E+01 3.30E+00 2.44E+01 3.28E+00 2.50E+01 3.31 E+00 2.98E+01 3.51E+00 2.61E+01 3.36E+00 2.84E+01 3.45E+00 2.56E+01 3.33E+00 02/18/14 2.01 E+01 3.05E+00 1.63E+01 2.88E+00 2.18E+01 3.12E+00 2.61E+01 3.37E+00 1.85E+01 2.70E+00 2.58E+01 3.32E+00 2.24E+01 3.17E+00 02/26/14 1.31 E+01 2.35E+00 1.16E+01 2.25E+00 1.08E+01 2.22E+00 9.82E+00 2.13E+00 1.36E+01 2.38E+00 1.32E+01 2.35E+00 1.21E+01 2.28E+00 03/05/14 1.36E+01 2.82E+00 2.25E+01 3.25E+00 1.88E+01 3.08E+00 2.71E+01 3.45E+00 1.71E+01 3.OOE+00 2.71 E+01 3.45E+00 2.40E+01 3.32E+00

+/-

03/12/14 1.86E+01 3.08E+00 1.68E+01 2.99E+00 2.25E+01 3.27E+00 1.46E+01 2.87E+00 1.63E+01 2.96E+00 1.92E+01 3.11E+00 03/19/14 1.37E+01 2.74E+00 1.48E+01 2.76E+00 1.59E+01 2.87E+00 1.29E+01 2.68E+00 1.26E+01 2.67E+00 1.31E+01 2.71E+00

+/-

03/26/14 1.36E+01 2.80E+00 1.27E+01 2.69E+00 1.47E+01 2.87E+00 1.51E+01 2.78E+00 1.24E+01 2.67E+00 9.68E+00 2.50E+00 1.28E+01 2.69E+00 04/02/14 1.55E+01 2.80E+00 1.31E+01 2.70E+00 1.09E+01 2.67E+00 1.76E+01 2.97E+00 1.09E+01 2.60E+00 1.43E+01 2.78E+00 1.12E+01 2.60E+00 04/08/14 1.21 E+01 2.88E+00 1.25E+01 2.92E+00 1.09E+01 2.82E+00 1.40E+01 3.01 E+00 1.17E+01 2.87E+00 1.01 E+01 2.77E+00 1.32E+01 2.96E+00 04/16/14 1.37E+01 2.50E+00 1.44E+01 2.53E+00 1.31E+01 2.47E+00 1.52E+01 2.57E+00 1.38E+01 2.50E+00 1.33E+01 2.47E+00 1.22E+01 2.41E+00 04/22/14 1.98E+01 3.23E+00 1.09E+01 2.71 E+00 1.62E+01 3.03E+00 1.65E+01 3.05E+00 1.02E+01 2.67E+00 1.91E+01 3.20E+00 1.95E+01 3.22E+00 I

04/29/14 1.12E+01 2.46E+00 1.19E+01 2.47E+00 1.39E+01 2.56E+00 1.73E+01 2.78E+00 1.48E+01 2.64E+00 1.15E+01 2.45E+00 05/06/14 1.06E+01 2.46E+00 1.09E+01 2.51 E+00 7.65E+00 2.35E+00 9.20E+00 2.42E+00 1.27E+01 2.63E+00 9.00E+00 2.46E+00 1.15E+01 2.55E+00 05/13/14 1.68E+01 2.86E+01 1.89E+01 2.97E+00 1.12E+01 2.55E+00 1.72E+01 2.88E+00 1.24E+01 2.61E+00 2.09E+01 3.07E+00 2.26E+01 3.16E+00 05/21/14 1.35E+01 2.38E+00 1.48E+01 2.45E+00 1.08E+01 2.21E+00 1.76E+01 2.60E+00 1.51E+01 2.46E+00 1.16E+01 2.26E+00 1.66E+01 2.55E+00 05/27/14 1.47E+01 3.06E+00 1.41E+01 3.03E+00 1.25E+01 2.93E+00 1.25E+01 2.93E+00 1.11E+01 2.85E+00 1.36E+01 3.00E+00 1.76E+01 3.23E+00 06/04/14 7.98E+00 2.23E+00 1.01E+01 2.35E+00 8.88E+00 2.28E+00 1.03E+01 2.36E+00 1.02E+01 2.35E+00 8.70E+00 2.27E+00 1.38E+01 2.54E+00 06/10/14 1.30E+01 3.07E+00 9.71 E+00 2.72E+00 1.30E+01 2.93E+00 1.54E+01 3.07E+00 1.17E+01 2.85E+00 1.51E+01 3.05E+00 1.62E+01 3.10E+00 06/18/14 1.52E+01 2.50E+00 1.23E+01 2.36E+00 1.14E+01 2.29E+00 1.54E+01 2.51E+00 1.34E+01 2.40E+00 9.02E+00 2.17E+00 3.01E+00 06/24/14 1.36E+01 2.93E+00 1.18E+01 2.88E+00 1.30E+01 2.93E+00 1.61E+01 3.11E+00 1.54E+01 3.07E+00 1.42E+01 2.99E+00 1.20E+01 2.92E+00 07/01/14 1.49E+01 2.71 E+00 1.09E+01 2.46E+00 1.24E+01 2.53E+00 1.58E+01 2.73E+00 1.85E+01 2.87E+00 1.76E+01 2.83E+00 1.65E+01 2.78E+00

Sample not obtained due to sampler not operating 37

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

[10-3 PC i/m3]

Period Station Station Station Station Station Station Ending II 21 I I

22

+/-

I 23 1 24* I olA I 05A I 01/08/14 1.65E+01 +/- 2.57E+00 1.46E+01 2.48E+00 1.95E+01 +/- 2.69E+00 1.48E+01 +/- 2.51E+00 1.76E+01 +/- 2.58E+00 1.93E+01 +/- 2.71E+00 01/14/14 1.51E+01 +1- 3.18E+00 1.22E+01 3.02E+00 1.66E+01 +/- 3.25E+00 1.44E+01 +/- 3.13E+00 1.53E+01 +/- 3.18E+00 1.74E+01 41- 3.29E+00

+/-

01/21/14 1.41E+01 +/- 2.76E+00 1.22E+01 2.66E+00 1.45E+01 +/- 2.78E+00 1.36E+01 4/- 2.74E+00 9.71E+00 +/- 2.51E+00 1.56E+01 +/- 2.84E+00

+/-

01/28/14 1.50E+01 +/- 2.69E+00 1.98E+01 2.94E+00 1.67E+01 +/- 2.79E+00 1.13E+01 +/- 2.48E+00 1.39E+01 +/- 2.64E+00 1.42E+01 +/- 2.66E+00

+/-

02/04/14 1.56E+01 +/- 2.88E+00 1.75E+01 2.98E+00 1.70E+01 +/- 2.96E+00 1.68E+01 +/- 2.94E+00 2.03E+01 +/- 3.12E+00 1.77E+01 +/- 2.99E+00

+/-

02/11/14 2.24E+01 +/- 3.18E+00 2.21E+01 3.17E+00 2.73E+01 +/- 3.40E+00 2.68E+01 +/- 3.38E+00 2.36E+01 +/- 3.24E+00 2.32E+01 +/- 3.22E+00 02/18/14 1.64E+01 +/- 2.87E+00 2.OOE+01 +/- 3.06E+00 2.44E+01 +/- 3.25E+00 2.24E+01 4/- 3.17E+00 1.84E+01 +/- 2.97E+00 2.06E+01 +/- 3.07E+00 02/26/14 1.17E+01 +/- 2.26E+00 1.43E+01 +/- 2.40E+00 1.25E+01 +/- 2.31EE+00 1.24E+01 +/- 2.31E+00 9.77E+00 +/- 2.15E+00 1.22E+01 +/- 2.30E+00 03/05/14 2.14E+01 +/- 3.20E+00 2.23E+01 +/- 3.24E+00 2.79E+01 +/- 3.48E+00 2.53E+01 +/- 3.37E+00 2.04E+01 +/- 3.15E+00 1.68E+01 +/- 2.98E+00 03/12/14 1.78E+01 +/- 3.04E+00 1.72E+01 +/- 3.01E+00 1.93E+01 +/- 3.11E+00 2.02E+01 +/- 3.15E+00 1.77E+01 +/- 3.03E+00 1.93E+01 +/- 3.11E+00 03/19/14 1.26E+01 +/- 2.67E+00 1.32E+01 +/- 2.70E+00 1.77E+01 +/- 2.95E+00 1.18E+01 +/- 2.63E+00 1.11E+01 +/- 2.58E+00 1.19E+01 +/- 2.62E+00 03/26/14 1.15E+01 +/- 2.59E+00 1.61E+01 2.86E+00 1.80E+01 +/- 2.98E+00 1.55E+01 +/- 2.80E+00 1.49E+01 +/- 2.86E+00 1.34E+01 +/- 2.72E+00

+/-

04/02/14 1.27E+01 +/- 2.71E+00 1.51E+01 2.84E+00 1.46E+01 +/- 2.78E+00 1.63E+01 +/- 2.94E+00 1.52E+01 +/- 2.78E+00 1.10E+01 +/- 2.61 E+00

+/-

04/08/14 1.10E+01 +/- 2.83E+00 1.32E+01 +/-

2.96E+00 1.39E+01 +/- 3.OOE+00 1.21E+01 +/- 2.90E+00 1.30E+01 +/- 2.94E+00 1.35E+01 +/- 2.98E+00 04/16/14 1.39E+01 +/- 2.51E+00 1.40E+01 2.51E+00 1.47E+01 +1- 2.55E+00 1.48E+01 +/- 2.55E+00 1.53E+01 +/- 2.58E+00 1.20E+01 +/- 2.40E+00

+/-

04/22/14 1.40E+01 +/- 2.90E+00 1.67E+01 3.06E+00 2.14E+01 +/- 3.32E+00 1.83E+01 +/- 3.15E+00 2.03E+01 +/- 3.26E+00 1.92E+01 +/- 3.21E+00 04/29/14 1.15E+01 +/- 2.43E+00 1.37E+01 2.56E+00 1.51E+01 +I- 2.68E+00 1.40E+01 +/- 2.55E+00 1.04E+01 +/- 2.41E+00 8.17E+00 +/- 2.21E+00

+/-

05/06/14 6.78E+00 +/- 2.24E+00 9.21E+00 2.44E+00 1.16E+01 +/- 2.58E+00 1.17E+01 +/- 2.61E+00 1.06E+01 +/- 2.46E+00 9.70E+00 +/- 2.46E+00 05/13/14 1.56E+01 +/- 2.80E+00 1.74E+01 2.90E+00 2.40E+01 +/- 3.22E+00 2.09E+01 +/- 3.08E+00 2.04E+01 +/- 3.04E+00 1.59E+01 +/- 2.81 E+00

+/-

05121114 1.49E+01 +/- 2.45E+00 1.58E+01 2.50E+00 1.25E+01 +/- 2.32E+00 1.04E+01 +/- 2.21E+00 1.71E+01 +/- 2.68E+00 1.17E+01 +/- 2.27E+00

+/-

05/27/14 1.57E+01 +/- 3.12E+00 1.52E+01 3.09E+00 1.91E+01 +/- 3.31E+00 1.81E+01 +/- 3.25E+00 1.71E+01 +/- 3.20E+00 1.32E+01 +/- 2.97E+00

+/-

06/04/14 8.49E+00 +1- 2.26E+00 8.88E+00 2.28E+00 1.21E+01 +/- 2.46E+00 1.13E+01 +/- 2.41E+00 1.12E+01 +/- 2.41E+00 6.75E+00 +/- 2.16E+00 06/10/14 9.45E+00 +/- 2.72E+00 1.36E+01 +/- 2.96E+00 1.55E+01 +/- 3.05E+00 1.36E+01 +/- 2.96E+00 1.37E+01 +/- 2.95E+00 1.25E+01 +/- 2.90E+00 06/18/14 1.32E+01 +/- 2.39E+00 1.07E+01 2.25E+00 1.23E+01 +/- 2.35E+00 1.34E+01 +/- 2.40E+00 1.16E+01 +/- 2.31E+00 1.18E+01 +/- 2.31 E+00 06124/14 1.08E+01 +/- 2.79E+00 1.52E+01 3.06E+00 1.45E+01 +/- 3.02E+00 1.90E+01 +/- 3.27E+00 1.60E+01 +/- 3.07E+00 1.65E+01 +/- 3.31 E+00 07/01/14 1.54E+01 +/- 2.70E+00 1.47E+01 2.66E+00 1.62E+01 +/- 2.76E+00 1.78E+01 +/- 2.83E+00 1.73E+01 +/- 2.83E+00 1.34E+01 +/- 2.60E+00

Control Station 38

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

[1O3 pCi/m 3]

Period Ending I Station I

Station 02 I Station 03 I Sa 0

I Station Station 06 I

Sa 0

1.10E+01 +/ 2.41E+00 1.13E+01 +/- 2.43E+00 1.16E+01 +I- 2.52E+00 1.28E+01 +/-

07/09/14 1.36E+01 2.54E+00 2.45E+00 1.29E+01 2.51E+00 1.23E+01 2.48E+00

+/ 3.40E+00 2.31E+01 +/- 3.46E+00 2.64E+01 +/- 3.35E+00 2.28E+01 +/-

07/15/14 2.06E+01 3.34E+00 2.18E+01 3.61E+00 2.10E+01 3.44E+00 2.18E+01 3.40E+00

+/- 2.62E+00 9.91E+00 +/-

07/22/14 8.50E+00 2.36E+00 1.33E+01 +1- 2.65E+00 1.10E+01 +1- 2.51E+00 1.46E+01 +/- 2.72E+00 1.29E+01 2.44E+00 1.27E+01 2.61E+00 2.68E+00 1.21E+01 +/- 2.70E+00 1.74E+01 +I- 2.71E+00 1.55E+01 +/-

07/29/14 1.60E+01 2.90E+00 1.19E+01 +- 3.01E+00 1.23E+01 2.90E+00 1.46E+01 2.83E+00 2.50E+00 1.25E+01 +/- 2.48E+00 1.53E+01 +/-

08/06/14 1.32E+01 2.57E+00 1.29E+01 +- 2.64E+00 1.69E+01 +/- 2.70E+00 1.29E+01 2.50E+00 1.68E+01 2.70E+00 2.66E+00 1.62E+01 +/- 2.62E+00 1.99E+01 +I- 2.69E+00 2.02E+01 +/-

08/14/14 1.84E+01 2.72E+00 1.72E+01 +- 2.78E+00 1.79E+01 2.80E+00 1.53E+01 +/- 2.57E+00 08/19/14 1.67E+01 3.75E+00 1.88E+01 +/- 3.87E+00 1.53E+01 +/- 3.67E+00 2.08E+01 3.98E+00 1.96E+01 +/ 3.92E+00 2.23E+01 4.07E+00 2.11E+01 4.00E+00 08/26/14 1.53E+01 2.76E+00 1.26E+01 +/- 2.61E+00 1.11E+01 +/- 2.52E+00 1.54E+01 2.76E+00 1.38E+01 +- 2.67E+00 1.48E+01 2.73E+00 1.31E+01 2.64E+00 09/02/14 1.55E+01 2.76E+00 1.49E+01 +/ 2.73E+00 1.25E+01 +/- 2.60E+00 1.34E+01 2.65E+00 1.68E+01 +/ 2.83E+00 8.58E+00 2.37E+00 1.56E+01 2.77E+00 09/09/14 1.OOE+01 2.78E+00 1.00E+01 +- 2.74E+00 9.25E+00 +/- 2.66E+00 1.32E+01 +/- 2.90E+00 1.34E+01 +- 2.90E+00 1.16E+01 2.81E+00 9.17E+00 +/- 2.69E+00

+- 2.57E+00 1.05E+01 +/- 2.51E+00 1.20E+01 +/- 2.64E+00 8.20E+00 +/-

09/16/14 9.37E+00 2.44E+00 1.15E+01 +/- 2.60E+00 1.27E+01 2.37E+00 1.03E+01 2.50E+00 3.05E+00 2.15E+01 +/- 3.06E+00 2.62E+01 +/ 2.75E+00 +/-

09/23/14 1.95E+01 2.95E+00 2.13E+01 +/ +/- 3.27E+00 1.54E+01 1.94E+01 2.96E+00 2.72E+00 1.48E+01 +/- 2.78E+00 1.71E+01 +/ 2.78E+00 1.82E+01 +/-

09/30/14 1.11E+01 2.65E+00 1.28E+01 +/ 2.92E+00 1.40E+01 3.00E+00 1.19E+01 +/- 2.67E+00 2.08E+00 1.59E+01 +/- 2.79E+00 2.04E+01 +- 2.99E+00 2.72E+01 +/-

10/07/14 2.14E+01 3.02E+00 5.33E+00 +/ +/- 3.00E+00 2.03E+01 3.31E+00 1.95E+01 +/- 2.94E+00

+/- 2.91E+00 1.71E+01 +I- 2.89E+00 1.91E+01 +/ 3.02E+00 2.32E+01 +/-

10/14/14 1.75E+01 2.84E+00 1.79E+01 2.97E+00 2.01E+01 3.16E+00 1.57E+01 ~1- 2.78E+00 10/21/14 9.43E+00 2.34E+00 9.17E+00 +/ 2.32E+00 1.06E+01 +/- 2.40E+00 8.42E+00 +/- 2.27E+00 1.14E+01 +I- 2.45E+00 1.06E+01 2.41E+00 1.12E+01 +/- 2.45E+00 10/28/14 9.83E+00 2.35E+00 1.15E+01 +/ 2.43E+00 1.28E+01 +/- 2.55E+00 8.99E+00 +/- 2.31E+00 1.52E+01 +/ 2.68E+00 1.51E+01 2.67E+00 1.27E+01 +/- 2.53E+00 11/05/14 2.10E+01 2.93E+00 1.99E+01 +/ 2.87E+00 1.87E+01 +/- 2.80E+00 1.82E+01 +/- 2.78E+00 1.13E+01 +- 2.42E+00 1.78E+01 2.76E+00 1.97E+01 +/- 2.86E+00

+/-

11/12/14 1.46E+01 2.84E+00 1.72E+01 +- 2.98E+00 1.52E+01 +/- 2.88E+00 1.35E+01 +/- 2.79E+00 9.80E+00 I+ 2.59E+00 1.56E+01 2.90E+00 1.54E+01 2.90E+00 11/18/14 1.01E+01 3.10E+00 8.46E+00 +- 2.90E+00 1.39E+01 +/- 3.21E+00 9.46E+00 2.99E+00 7.93E+00 I+ 2.86E+00 6.96E+00 2.80E+00 9.61E+00 +/- 2.97E+00

+/-

11/26/14 2.06E+01 2.78E+00 2.03E+01 +/- 2.79E+00 1.84E+01 +/- 2.64E+00 2.15E+01 2.81E+00 1.63E+01 +- 2.59E+00 1.75E+01 2.65E+00 1.36E+01 +/- 2.46E+00 12/02/14 1.79E+01 3.20E+00 1.52E+01 +/- 3.08E+00 1.66E+01 +/- 3.26E+00 1.78E+01 3.26E+00 1.57E+01 +- 3.13E+00 1.63E+01 3.16E+00 1.29E+01 2.95E+00 12/09/14 2.23E+01 3.05E+00 1.55E+01 +/- 2.71E+00 2.18E+01 +/- 3.03E+00 1.80E+01 +/- 2.84E+00 1.55E+01 +/ 2.71E+00 1.64E+01 2.76E+00 9.83E+00 2.38E+00 12/16/14 1.86E+01 2.96E+00 1.14E+01 +/- 2.57E+00 1.76E+01 +/- 2.90E+00 1.87E+01 +/- 2.96E+00 1.75E+01 +- 2.89E+00 1.38E+01 2.70E+00 1.62E+01 2.83E+00 12/23/14 1.60E+01 2.76E+00 1.44E+01 +/- 2.67E+00 1.49E+01 +/- 2.70E+00 1.94E+01 +/- 2.94E+00 1.36E+01 +/ 2.63E+00 1.53E+01 2.72E+00 1.36E+01 +/- 2.63E+00 12/30/14 1.54E+01 2.81E+00 1.16E+01 +I- 2.63E+00 1.62E+01 +/- 2.89E+00 1.19E+01 +/- 2.65E+00 1.30E+01 +- 2.71E+00 1.34E+01 2.72E+00 1.39E+01 +/- 2.75E+00 MEAN 1.547E+01 +/- 3.35E+00 1.41E+01 +/- 2.74E+00 1.45E+01 +/- 2.77E+00 1.67E+01 +/- 2.88E+00 1.47E+01 +I- 2.77E+00 1.56E+01 +/- 2.82E+00 1.54E+01 +/- 2.82E+00

Sample not obtained due to sampler not operating 39

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

[10 3 pCi/m3 ]

Period Station Station Station Station Station Station Ending U

S 21 S 22 I I 24 I 01A I05A II 07/09/14 1.19E+01 +/- 2.47E+00 1.24E+01 +/- 2.49E+00 1.41E+01 2.57E+00 1.27E+01 +1- 2.51 E+00 I 1.25E+01 2.48E+00 1.17E+01 +1- 2.46E+00 07115/14 2.08E+01 +/- 3.34E+00 1.95E+01 +/- 3.27E+00 2.42E+01 3.53E+00 1.80E+01 +1- 3.19E+00 2.21E+01 3.42E+00 2.08E+01 +1- 3.34E+00 07/22/14 1.04E+01 +/- 2.48E+00 1.42E+01 +/- 2.69E+00 1.12E+01 2.52E+00 1.37E+01 +1- 2.67E+00 1.26E+01 2.60E+00 1.20E+01 2.57E+00 07/29/14 1.62E+01 +/- 2.91E+00 1.39E+01 +/- 2.80E+00 1.81E+01 3.01E+00 1.38E+01 +1- 2.79E+00 1.46E+01 2.83E+00 1.27E+01 4/- 2.77E+00 08/06/14 1.39E+01 +!- 2.55E+00 1.31E+01 +/- 2.51E+00 1.61E+01 2.66E+00 1.19E+01 +1- 2.44E+00 1.52E+01 2.67E+00 1.31E+01 +1- 2.51E+00 08114/14 1.30E+01 +/- 2.45E+00 1.78E+01 +/- 2.69E+00 1.70E+01 2.65E+00 1.51 E+01 +1- 2.56E+00 2.04E+01 2.82E+00 1.46E+01 +1- 2.53E+00 08/19114 1.72E+01 +/- 3.78E+00 1.95E+01 +/- 3.91E+00 1.73E+01 3.79E+00 1.96E+01 3.93E+00 3.26E+01 4.14E+00 1.54E+01 ~1- 3.68E+00 08/26/14 1.26E+01 +/- 2.61 E+00 1.51E+01 +I- 2.74E+00 1.53E+01 2.75E+00 1.11E+01 +1- 2.52E+00 1.53E+01 2.75E+00 1.44E+01 4/- 2.70E+00 09/02/14 1.53E+01 +/- 2.76E+00 1.41E+01 +/- 2.69E+00 1.96E+01 2.97E+00 1.63E+01 +1- 2.81E+00 1.18E+01 2.56E+00 1.31E+01 ~1- 2.64E+00 09/09/14 1.24E+01 +/- 2.83E+00 9.57E+00 +/- 2.68E+00 1.29E+01 2.91E+00 1.11E+01 +1- 2.74E+00 1.19E+01 2.87E+00 8.14E+00 4/- 2.61E+00 09/16/14 1.38E+01 +/- 2.70E+00 1.08E+01 +/- 2.53E+00 1.28E+01 2.63E+00 1.27E+01 +1- 2.64E+00 1.02E+01 2.49E+00 1.97E+01 +1- 3.00E+00 09/23/14 2.50E+01 +/- 3.21E+00 2.11E+01 +I- 3.03E+00 2.85E+01 3.39E+00 2.72E+01 3.32E+00 2.71E+01 3.31E+00 2.41E+01 +1- 3.18E+00 09/30/14 1.32E+01 +/- 2.74E+00 1.47E+01 +/ 2.82E+00 1.48E+01 2.82E+00 1.44E+01 +1- 2.80E+00 1.43E+01 2.82E+00 1.18E+01 2.66E+00 10/07/14 1.65E+01 +I- 2.77E+00 1.73E+01 +- 2.82E+00 2.32E+01 3.12E+00 2.43E+01 +1- 3.18E+00 1.91E+01 2.90E+00 1.47E+01 2.68E+00 10/14/14 1.97E+01 +/- 3.03E+00 1.60E+01 +- 2.83E+00 2.36E+01 3.15E+00 1.72E+01 +1- 2.91 E+00 1.82E+01 2.88E+00 1.81E+01 4/- 2.93E+00 10/21/14 5.91 E+00 +/- 2.10E+00 1.12E+01 +1 2.45E+00 1.30E+01 2.56E+00 1.18E+01 +1- 2.48E+00 2.70E+00 1.06E+01 ~1- 2.40E+00 10/28/14 1.29E+01 +/- 2.55E+0(0 1.32E+01 +- 2.57E+00 1.51E+01 2.67E+00 1.36E+01 +1- 2.59E+00 1.27E+01 ~1- 2.54E+00 11/05/14 2.12E+01 +/- 2.92E+0(0 1.92E+01 +- 2.82E+00 1.85E+01 2.80E+00 1.94E+01 2.83E+00 1.83E+01 2.80E+00 1.57E+01 +1- 2.65E+00 11/12/14 1.89E+01 +/- 3.07E+0(0 1.57E+01 +- 2.91E+00 2.25E+01 3.23E+00 1.73E+01 +1- 2.99E+00 1.76E+01 2.99E+00 1.30E+01 +1- 2.77E+00 11/18/14 1.06E+01 +/- 3.02E+0C0 1.07E+01 +- 3.03E+00 1.23E+01 3.13E+00 1.18E+01 4/- 3.08E+00 7.63E+00 2.95E+00 1.03E+01 +1- 3.01E+00 11/26/14 2.14E+01 +/- 2.82E+000 2.35E+01 +- 2.91E+00 2.51E+01 3.01 E+00 2.36E+01 +1- 2.90E+00 2.02E+01 2.76E+00 2.11E+01 +1- 2.81E+00 12/02/14 1.41E+01 +/- 3.06E+000 1.55E+01 +- 3.14E+00 1.66E+01 3.15E+00 1.80E+01 +1- 3.31E+00 1.11E+01 2.81E+00 1.28E+01 +1- 2.96E+00 12/09/14 1.99E+01 +/- 2.94E+0(0 1.83E+01 +/ 2.86E+00 2.15E+01 3.01E+00 2.38E+01 +1- 3.13E+00 2.25E+01 3.06E+00 1.76E+01 +1- 2.82E+00 12/16/14 1.54E+01 +I- 2.79E+000 1.82E+01 +/- 2.93E+00 1.49E+01 2.77E+00 1.99E+01 +1- 3.02E+00 1.93E+01 2.99E+00 1.43E+01 +1- 2.73E+00 12/23/14 1.57E+01 +/- 2.75E+0(0 1.61E+01 +I- 2.77E+00 1.06E+01 2.46E+00 1.70E+01 +1- 2.81 E+00 1.38E+01 2.64E+00 1.50E+01 +1- 2.71E+00 12/30/14 1.26E+01 +/- 2.70E+0(0 1.22E+01 +/- 2.68E+00 1.46E+01 2.79E+00 1.08E+01 +1- 2.59E+00 8.86E+00 2.46E+00 1.30E+01 ~1- 2.71E+00 MEAN 1.47E+01 +/- 2.77E+00 1.53E+01 +/- 2.81E+00 1.74E+01 +/- 2.91E+00 1.62E+01 +/- 2.86E+00 1.60E+01 +/- 2.84E+00 1.46E+01 +/- 2.77E+00 Mean - All Indicator Locations 1.54E+01 +I- 2.85E+00

Sample not obtained due to sampler not operating. **Control Station 40

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

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Station Ending I

01 C

I 02 C

I 03 U

I 04 C

IA 05 06 C

I 07 I

01/08/14 5.60E+01 4.64E+01 4.80E+01 4.71E+01 3.64E+01 3.61E+01 3.60E+01 C C 01/14/14 <

1.57E+01 4.05E+01 4.06E+01 4.05E+01 4.05E+01 3.17E+01 3.17E+01

< C C C C 01/21/14 3.93E+01 3.93E+01 3.93E+01 3.93E+01 4.24E+01 4.24E+01 4.24E+01 C C C C < C C 01/28/14 1.57E+01 3.72E+01 3.70E+01 3.72E+01 3.72E+01 3.54E+01 3.54E+01 C C 02/04/14 3.92E+01 1.65E+01 3.91E+01 3.92E+01 3.86E+01 3.86E+01 3.86E+01 C C C <

02/11/14 3.01E+01 3.01E+01 3.01E+01 3.01E+01 C 3.26E+01 3.26E+01 3.26E+01 C C C C < C 02/18/14 4.11E+01 4.15E+01 4.09E+01 4.18E+01 3.63E+01 3.65E+01 3.66E+01 C C

< C 02/26/14 1.01E+01 2.59E+01 2.63E+01 2.57E+01 <

2.61E+01 2.56E+01 2.55E+01 C C 03/05/14 C 4.20E+01 C 4.20E+01 C c 4.20E+01 4.20E+01 4.69E+01 4.69E+01 4.69E+01 C

C < C 03/12/14 2.47E+01 2.47E+01 2.47E+01 2.47E+01 3.91E+00 2.53E+01 C C C C C 03/19/14 3.03E+01 2.98E+01 3.05E+01 3.01E+01 2.96E+01 2.97E+01 C C 03/26/14 1.62E+01 4.07E+01 4.20E+01 <

3.96E+01 c 4.05E+01 C 5.07E+01 C 5.07E+01

< C C C 04/02/14 1.08E+01 2.82E+01 2.95E+01 2.87E+01 C 2.85E+01 2.88E+01 2.87E+01

<C C C C

04/08/14 2.26E+01 3.82E+01 3.82E+01 3.82E+01 3.82E+01 4.15E+01 C 4.15E+01 C C < C 04/16/14 3.54E+01 2.10E+01 3.54E+01 3.53E+01 C 3.53E+01 C 3.87E+01 3.87E+01 C <

C C 04/22/14 1.97E+01 5.06E+01 5.04E+01 5.06E+01 5.06E+01 6.42E+01 6.42E+01 C C C C C C 04/29/14 5.70E+01 5.59E+01 2.13E+01 5.57E+01 5.56E+01 5.98E+01 C C C C C C 05/06/14 1.22E+01 3.21E+01 3.28E+01 3.23E+01 C 3.24E+01 2.69E+01 2.68E+01

< C C C C C 05/13/14 2.75E+01 2.75E+01 2.77E+01 1.07E+01 2.76E+01 3.40E+01 3.40E+01 C C C

< C C C 05/21/14 9.93E+00 2.56E+01 2.55E+01 2.55E+01 2.55E+01 2.69E+01 2.69E+01 C C C C C C 05/27/14 3.41E+01 3.41E+01 3.40E+01 3.41E+01 1.13E+01 2.69E+01 2.69E+01 C

C 06/04/14 3.43E+01 3.43E+01 3.43E+01 3.43E+01 3.94E+01 3.94E+01 3.94E+01 C

06/10/14 3.00E+01 2.81E+01 2.82E+01 2.82E+01 3.73E+01 1.56E+01 3.73E+01 06/18/14 1.47E+01 3.51E+01 3.48E+01 3.48E+01 3.48E+01 3.58E+01 4.25E+01 06/24/14 4.14E+01 4.27E+01 4.21E+01 4.22E+01 3.86E+01 3.84E+01 1.66E+01 07/01/14 1.34E+01 3.41E+01 3.39E+01 3.40E+01 3.40E+01 3.18E+01 3.18E+01

Sample not obtained due to sampler not operating 41

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

[10-3 pCi/m 3]

Period Station Station Station Station Station Station Ending 01/08/14 I 21 S

U -I 1.53E+01 22 3.65E+01 I

23 4.06E+01 I 24*

4.19E+01 S 01A C 44.02E+01 S 05A

< 44.13E+01 C

C C C 01/14/14 3.18E+01 3.18E+01 3.33E+01 3.33E+01 3.33E+01 3.33E+01 C

C C 01/21/14 4.24E+01 1.42E+01 3.39E+01 3.40E+01 3.39E+01 3.39E+01 01/28/14 C 3.53E+01 <

3.53E+01 C 4.OOE+01 3.99E+01 < 44.00E+01 < 4 .002E+01 02/04/14 C 3.85E+01 <

4.26E+01 C 1.51E+01 C 4.26E+01 < 44.27E+01 C< 41.27E+01 C

02/11/14 3.26E+01 1.28E+01 3.05E+01 3.05E+01 3.05E+01 3.05E+01 C C C C 02/18/14 3.66E+01 3.83E+01 3.81E+01 1.60E+01 3.81E+01 3.79E+01 C

C 02/26/14 2.56E+01 2.54E+01 2.39E+01 2.39E+01 2.39E+01 C 2.40E+01 C

C C 03/05/14 4.69E+01 3.40E+01 3.40E+01 3.40E+01 1.42E+01 3.40E+01 C

C C 03/12/14 2.53E+01 2.53E+01 2.53E+01 2.57E+01 2.57E+01 C 2.57E+01 03/19/14 2.96E+01 2.48E+01 C 2.48E+01 2.48E+01 2.48E+01 c 1.03E+01 C C 1C <

03/26/14 5.01E+01 5.01E+01 4.47E+01 4.36E+01 4.57E+01 4.46E+01 C C C C 04/02/14 2-91E+01 2.90E+01 2.85E+01 2.95E+01 2.81E+01 2.90E+01 C 1 C C

04/08/14 4.16E+01 C 4.16E+01 3.67E+01 3.70E+01 3.67E+01 3.69E+01 1 C C 1C <

04/16/14 3.87E+01 3.87E+01 3.39E+01 3.38E+01 3.39E+01 3.38E+01 C

C 1 < i 1 C 04/22/14 6.40E+01 6.40E+01 4.84E+01 4.82E+01 4.84E+01 4.84E+01 C C 5.91E+01 5.92E+01 C 6.06E+01 6.38E+01 1 < 6.65E+01 1 < 6.47E+01 04/29114 C C 05/06/14 2.64E+01 2.71E+01 C 3.69E+01 3.73E+01 1 <

3.58E+01 1 < 3.68E+01 C

C 3.88E+01 1 < 3.87E+01 1 < 3.88E+01 05113/14 3.42E+01 3.42E+01 3.87E+01 05/21/14 C 2.68E+01 2.68E+01 <

2.64E+01 2.67E+01 1 < 2.80E+01 2.63E+01 C

05/27/14 C 2.68E+01 2.68E+01 <

3.77E+01 3.77E+01 1 < 3.77E+01 3.77E+01 C

06/04/14 3.93E+01 1.04E+01 2.49E+01 2.48E+01 1 < 2.49E+01 2.49E+01 C

1 06/10/14 3.76E+01 3.73E+01 3.80E+01 3.83E+01 3.89E+01 3.83E+01 1 < C 1

06/18/14 3.53E+01 3.53E+01 2.61E+01 2.59E+01 2.61E+01 2.59E+01 1 < C 1

06/24/14 3.86E+01 3.87E+01 5.38E+01 5.36E+01 5.29E+01 5.36E+01 C ,

1 07/01/14 3.16E+01 3.16E+01 3.05E+01 3.03E+01 3.07E+01 3.03E+01

Control Station 42

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

[10.3 pCi/m3 ]

Period Station Station Station Station Station Station Station Ending I 01 02 I 04 I 06 I II I

II 07/09114 4.87E+01 C 4.89E+01 C 4.90E+01 " 4.90E+01 C 5.57E+01 " 5.55E+01 5.55E+01 07/15/14 2.44E+01 C 6.25E+01I C 6.24E+01 " 6.23E+01 6.23E+01 " 6.63E+01 6.64E+01 07/22/14 C 5.18E+01 5.18E+01I C 5.18E+01 " 5.18E+01 5.16E+01 " 5.16E+01 5.16E+01 07129/14 C 6.01E+01 C 6.01E+01I C 6.02E+01 " 6.13E+01 6.51E+01 " 5.52E+01 5.51E+01 08/06/14 C 2.43E+01 C 2.37E+01I C 2.36E+01 < 2.39E+01 C 2.70E+01 " 2.70E+01 2.70E+01 08/14/14 3.11E+01 C 3.11E+01I C 3.12E+01 " 3.08E+01 C 3.96E+01 " 3.96E+01 3.97E+01 08/19/14 5.43E+01 5.43E+01I C 5.43E+01 " 5.43E+01 6.34E+01 " 3.64E+01 3.64E+01 08/26/14 1.98E+01 5.10E+01I C 5.10E+01 " 5.10E+01 5.10E+01 " 4.91E+01 4.91E+01 09/02/14 C 6.09E+01 C 6.09E+01 6.09E+01 " 6.09E+01 C 6.49E+01 " 6.49E+01 6.49E+01 09/09/14 1.70E+01 4.30E+01I C 4.22E+01 " 4.29E+01 C 4.26E+01 " 3.70E+01 3.71E+00 09/16/14 3.09E+01 C 3.09E+01I C 3.08E+01 " 3.10E+01 C 1.75E+01 " 1.75E+01 1.75E+01

< 6.47E+01 < 6.85E+01 09/23/14 C 2.51E+01 C 6.50E+01 6.50E+01 C 6.49E+01 09/30114 2.10E+01 C 5.35E+01 C 5.25E+01 " 5.30E+01 C 5.35E+01 " 6.44E+01 6.44E+01 10/07114 C 1.88E+01 C 4.89E+01 4.99E+01 " 4.94E+01 C 4.90E+01 " 5.28E+01 5.28E+01 10/14/14 1.58E+01 C 6.30E+00 C 1.65E+01 " 1.62E+01 1.63E+01 " 1.84E+01 1.83E+01 10/21/14 C 9.73E+00 C 2.50E+01I C 2.49E+01 " 2.49E+01 C 2.49E+01 " 2.80E+01 2,80E+01 10/28/14 C 3.21E+01 C 3.21 E+01 C 3.23E+01 " 3.23E+01 3.14E+01 " 3.14E+01 3,14E+01 11/05/14 1.44E+01 C 3.42E+01I C 3.40E+01 " 3.41 E+01 3.41E+01 " 2.73E+01 2.73E+01 11/12/14 2.25E+01 C 2.27E+01I C 8.82E+00 " 2.27E+01 C 2.27E+01 " 1.24E+01 2.96E+01 11/18/14 C 2.69E+01 C 2.57E+01I C 9.96E+00 " 2.60E+01 C 2.57E+01 " 1.22E+01 2,91E+01 11/26/14 C 2.18E+01 C 4.99E+01 C 4.84E+01 " 4.89E+01 C 4.97E+01 " 1.67E+01 4.74E+01 12/02/14 C 2.21E+01 C 5.77E+01 C 6.04E+01 " 5.86E+01 C 5.83E+01 " 2.73E+01 6,48E+01 12/09/14 C 6.87E+00 C 1.96E+01 1.96E+01 " 1.96E+01 1.96E+01 " 1.26E+01 2,44E+01 12/16/14 4.10E+00 1.05E+01 C 1.05E+01 " 1.05E+01 1.05E+01 " 4.43E+00 1,06E+01 12/23/14 C 2.73E+01 2.73E+01 C 2.73E+01 " 1.06E+01 C 2.73E+01 " 6.02E+01 6.02E+01 12/30/14 1.95E+01 C 1.97E+01 C 1.98E+01 " 1.98E+01 C 8.77E+00 " 2.03E+01 2.03E+01 Mean #DtV/0~ +/ 1.67E+01 #D~V/0' +/- 3.32E+0 1 #DIV/0I +/- 3.39E+01 #DIVlO! +1- 3.35E÷0 1 #DIVl0! +/- 3.34E+01 #DIVI0! +1/ 3.52E+01 #DIV/0! +I- 3.51E+01

Sample not obtained due to sampler not operating.

43

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

[10.3 pCi/m 3]

Period Station Station Station Station Station Station Ending 07/09/14 2.34E+01 22

" 5.57E+01 2C 5.83E+01 L24*

" 5.86E+01 I 01A

< 5.83E+01 < 5.86E+01 07/15/14 6.63E+01 " 6.63E+01 539E+01 " 5.36E+01 C 5.39E+01 < 5.35E+01 C

07122/14 5.16E+01 " 2.21 E+01 5.27E+01 " 5.27E+01 5.27E+01 " 5.27E+01 07129/14 C 5.52E+01 " 5.52E+01 5.51E+01 " 5.52E+01 5.51E+01 " 2.36E+01 08/06/14 C 2.69E+01 " 2.67E+01 I.12E+01 " 2.66E+01 C 2.74E+01 " 2.67E+01 08/14/14 3.98E+01 " 3.32E+01 3.31 E+01 " 1.17E+01 C 3.31 E+01 " 3.31E+01 08/19/14 6.33E+01 < 5.38E+01 5.39E+01 " 5.41E+01 2.26E+01 " 5.39E+01 08/26/14 C 4.91E+01 " 4.91E+01 5.05E+01 " 5.05E+01 C 5.05E+01 " 5.05E+01 09/02/14 C 6.49E+01 " 4.52E+01 4.52E+01 " 4.52E+01 1.90E+01 " 4.52E+01 C

09/09/14 3.66E+01 " 3.67E+01 4.72E+01 " 4.56E+01 4.75E+01 " 4.62E+01 09/16/14 1.76E+01 " 3.38E+01 3.37E+01 " 3.39E+01 C 3.38E+01 " 1.42E+01 09/23/14 C 6.82E+01 " 6.83E+01 6.69E+01 " 6.66E+01 6.65E+01 < 6.66E+01

<CE 09/30/14 6.45E+01 " 6.45E+01 6.1 8E+01 " 6.18E+01 <C 6.23E+01 " 6.18E+01 10107/14 C 5.27E+01 " 5.28E+01 5.51 E+01 " 5.52E+01 C 5.47E+01 " 5.52E+01 10/14/14 C 1.86E+01 " 1.86E+01 1.73E+01 " 1.80E+01 C 1.72E+01 " 1.77E+01 10/21/14 2.79E+01 " 2.79E+01 3.01 E+01 " 3.OOE+01 3.01E+01 " 3.OOE+01 C

10/28/14 C 3.15E+01 " 3.73E+01 3.70E+01 " 3.72E+01 " 1.56E+01

<CE C:

11/05/14 2.72E+01 " 2.72E+01 2.64E+01 < 2.62E+01 2.64E+01 " 2.63E+01 C

11/12/14 2.96E+01 < 2.96E+01 C 2.95E+01 " 1.55E+01 2.83E+01 " 2.85E+01 C:

C 11/18/14 2.91 E+01 " 2.91E+01 2.92E+01 1 " 3.39E+01 C

3.55E+01 " 3.41E+01 11/26/14 C 4.68E+01 " 4.68E+01 4.77E+01 1 " 5.09E+01 5.11E+01 " 5.15E+01 1#DV/0!+/-C C 12/02/14 C 6.60E+01 " 6.60E+01 6.43E+01 1 " 4.59E+01 4.40E+01 " 4.50E+01

DV0 /

12/09/14 C 2.44E+01 " 2.44E+01 2.43E+01 1 " 1.57E+01 1.57E+01 " 1.57E+01 12/16/14 C 1.06E+01 " 1.06E+01 1.06E+01 1 " 1.20E+01 1.21E+01 " 1.20E+01 12/23/14 C 6.01E+01 " 6.01E+01 5.11 E+01 1 < 5.10E+01 5.11E+01 " 5.11E+01 12/30/14 C 2.05E+01 " 2.05E+01 2.10E+01 I " 2.12E+01 2.09E+01 C 2.11E+01 MEAN #DIV/0' +/- 3.54E+01 #DIV/0! +/- 3.53E+01 3.26E+01 1 #DIV/0! +/- 3.33E+01 3.29E+01 #DIV/0! +/- 3.30E+01 Indicator Locations Mean #DIV/0! +/- 3.25E+01

Sample not obtained due to sampler not operating. ** Control Station 44

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

[10-3 pCi/m 3]

Sampling Quarter 1 Location I Be-7 I Cs-134*

I SCs-1 37" I I 01 1.32E+02 +1- 3.32E+01 < 1.81E+OC < 1.77E+00 01A 1.28E+02 +1- 2.22E+01 " 1.06E+OC " 1.08E+00 02 1.20E+02 +1- 2.13E+01 " 1.04E+0C " 1.12E+00 03 1.22E+02 +1- 2.OOE+01 < 1.18E+OC " 9.24E-01 04 1.58E+02 +1- 2.50E+01 < 1.27E+0C " 1.21E+00 05 1.19E+02 +1- 2.50E+01 < 1.35E+0C " 1.38E+00 05A 1.12E+02 +1- 1.85E+01 " 1.03E+OC " 9.68E-01 06 1.37E+02 +1- 2.56E+01 " 1.26E+OC " 1.34E+00 07 1.23E+02 +1- 2.38E+01 " 1.27E+OC " 1.01E+00 21 1.11E+02 +1- 2.67E+01 " 1.65E+OC " 1.88E+00 22 1.38E+02 +1- 3.39E+01 " 1.59E+OC " 1.37E+00 23 1.26E+02 +1- 3.27E+01 " 1.96E+0C " 1.81E+00 24 1.51 E+02 +1- 2.67E+01 " 1.96E+OC " 1.78E+00 Sampling Quarter 2 Location Be-7 I Cs-1 34* SCs-137" Sr-89 S Sr-90 01 1.32E+02 +1- 2.21E+01 < 1.06E+OC I < 8.70E-01 < 5.62E+00 < 2.79E+00 01A 1.22E+02 +1- 3.32E+01 < 1.57E+OC I < 1.62E+00 < 7.39E+00 " 1.74E+00 02 1.26E+02 +1- 2.40E+01 < 1.52E+OC I < 1.09E+00 < 5.58E+00 " 2.37E+00 03 1.64E+02 +1- 3.56E+01 < 1.89E+OC I < 1.39E+00 < 8.10E+00 " 3.68E+00 04 1.20E+02 +1- 2.09E+01 < 1.06E+OCI < 1.00E+00 < 6.86E+00 " 4.33E+00 05 1.28E+02 2.87E+01 < 1.32E+OC I < 1.12E+00 < 7.95E+00 " 3.54E+00 05A 1.07E+02 +1- 2.44E+01 " 1.37E+OC I < 1.26E+00 < 9.29E+00 < 2.05E+00 06 1.15E+02 +1- 2.26E+01 " 1.19E+OC < 1.31E+00 " 6.78E+00 " 2.711E+00 07 1.26E+02 +1- 2.11E+01 " 1.07E+OC 0 < 7.29E-01 < 5.34E+00 < 2.43E+00 1.27E+02 +1- 2.81E+01 " 1.60E+OC < 1.58E+00 " 5.47E+00 " 2.89E+00 21 22 1.48E+02 +1- 2.53E+01 " 1.15E+OC < 1.07E+00 < 7.88E+00 < 2.80E+00 23 1.10E+02 +1- 2.71E+01 " 1.11E+OC < 1.09E+00 < 5.73E+00 < 2.53E+00 24* 1.26E+02 +1- 2.23E+01 " 1.13E+OC I < 9.29E-01 < 7.02E+00 < 2.22E+00

LLD identified in the ODCM Control Station 45

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

[10O. pCi/m 3]

Sampling Quarter 3 Location I Be-7

+1- 2.41E+01 Cs-134* I Cs-137*

j 01 1.35E+02 < 1.04E+00 " 9.01 E-01 01A 1.12E+02 +1- 2.46E+01 < 1.08E+00 " 1.09E+00 02 8.50E+01 +1- 1.87E+01 " 1.24E+00 " 9.77E-01 03 1.10E+02 +1- 2.34E+01 < 5.68E-01 " 6.42E-01 04 9.76E+01 +1- 1.83E+01 < 1.01E+00 " 9.73E-01 05 9.50E+01 +1- 2.87E+01 < 1.74E+00 " 1.56E+00 05A 9.79E+01 +1- 2.50E+01 < 1.48E+00 " 1.03E+00 06 1.07E+02 +1- 2.50E+01 < 1.71E+00 " 1.16E+00 07 1.08E+02 +1- 2.61E+01 < 6.87E-01 " 8.22E-01 21 1.12E+02 +1- 2.48E+01 c 1.25E+00 " 1.16E+00 22 1.26E+02 +1- 3.75E+01 " 1.89E+00 " 1.82E+00 23 1.04E+02 +1- 2.44E+01 c 1.21E+00 " 1.24E+00 24* 1.19E+02 +1- 3.31 E+01 " 2.34E+00 " 1.41E+00 MEAN Sampling MEAN Quarter 4 Location Be-7 Cs-134* S CS-1 37- Be-7 01 1.16E+02 +1- 3.02E+01 " 1.33E+00 " 1.31E+00 1.29E+02 .4-I- 2.74E+01 01A 9.61E+01 +1- 3.08E+01 " 1.71E+00 " 1.78E+00 1.15E+02 +1- 2.77E+01 02 8.65E+01 +1- 2.08E+01 " 1.49E+00 c 1.10E+00 1.04E+02 +1- 2.12E+01 03 1.21E+02 +1- 2.78E+01 " 2.00E+00 " 1.62E+00 1.29E+02 4-I- 2.67E+01 04 1.28E+02 +1- 2.60E+01 " 9.88E-01 " 1.06E+00 1.26E+02 -'-I- 2.26E+01 05 1.08E+02 +1- 2.64E+01 " 1.98E+00 " 1.45E+00 1.13E+02 4-I- 2.72E+01 05A 9.19E+01 +1- 2.06E+01 " 1.04E+00 " 8.85E-01 1.02E+02 4-I- 2.21E+01 06 9.17E+01 +1- 2.09E+01 " 1.14E+00 " 8.84E-01 1.13E+02 4-I- 2.35E+01 07 1.02E+02 +1- 2.09E+01 " 1.21E+00 " 1.35E+00 1.15E+02 4-I- 2.30E+01 21 8.39E+01 +1- 2.45E+01 " 1.10E+00 " 1.19E+00 1.08E+02 4-I- 2.60E+01 22 9.71E+01 +1- 2.32E+01 " 1.27E+00 " 9.59E-01 1.27E+02 4-I- 3.00E+01 23 8.95E+01 +1- 2.19E+01 " 1.13E+00 " 9.19E-01 1.07E+02 4-I- 2.65E+01 24** 1.29E+02 +1- 3.24E+01 " 1.67E+00 " 1.79E+00 1.31E+02 4-I- 2.86E+01 Mean of All Indicator Location: 1.16E+02 +1- 2.53E+01

LLD Identified in ODCM

- Control Station 46

Table 3-6 Soil

[pCi/kg]

Triennial Soil Samples Not Required in 2014 47

Table 3-7 Precipitation Gross Beta

[pCi/L] page 1 of 2 Sampling Date Gross Beta I H-3 I I Rainfall (inches) Ij 01/28/14 1.12E+01 1.80E+00 < 7.75E+02 2.99 02/26/14 2.32E+00 1.32E+00 < 8.85E+02 2.64 03/26/14 5.OOE+00 1.23E+00 < 1.09E+03 2.04 04/29/14 1.54E+00 < 1,40E+03 4.58 05/27/14 1.32E+00 < 1.16E+03 6.76 06/24/14 2.01E+00 1.07E+00 < 6.96E+02 6.78 07/29/14 2.44E+00 1.17E+00 < 1.38E+03 3.84 08/26/14 3.09E+00 2.07E+00 < 1.57E+03 2.31 09/30/14 2.42E+00 1.11E+00 < 1.86E+03 0.86 10/28/14 1.64E+00 1.11E+00 < 1.29E+03 3.35 11/26/14 2.40E+00 1.12E+00 < 1.44E+03 2.26 12/30/14 2.05E+00 1.05E+00 < 1.69E+03 3.50 Mean 3.46E+00 1.41E+00 < 1.27E+03 Total 41.91 48

Table 3-7 Precipitation page Gamma Spectra 2 of 2

[pCi/L]

Sampling Location Be-7 I Mn-54 I Fe-59 I ro-58 I Co-60 I 01A 06/24/14 < 3.41E+01 < 7.72E-01 < 1.15E+01 < 2.46E+00 < 8.53E-01 12/30/14 < 4.23E+01 < 1.18E+00 < 9.03E+00 < 2.69E+00 < 1.27E+00 Zn-65 I Zr-95 I Nb-95 I Cs-134 Cs-137 01A 06/24/14 < 2.10E+00 < 4.95E+00 < 2.87E+00 < 6.58E-01 " 7.33E-01 12/30/14 < 2.37E+00 < 5.77E+00 < 3.31E+00 < 9.70E-01 " 1.08E+00 Ba-140 I La-140 I 1-131 I Th-228 01A 06/24/14 " 5.62E+03 < 1.60E+03 < 1.89E+05 < 1.32E+00 12/30/14 " 2.15E+03 < 7.63E+02 < 2.94E+04 < 2.51 E+00 MEAN Sampling Location Be-7 I Mn-54 I Fe-59 Co-58 I Co-60 I OIA I Zn-65 I 7r-g5 I Nb-95 I Cs-1 34 I Cs-1 37 Zn-65 I Zr-95 I Nb-95 I Cs-134 I Cs-137 01A I Ra-140 I La-140 I 1-131 I Th-228 I 01A No mean values. All results were <MDA 49

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

[pCi/L]

Sampling Station 12A Date I K-40 I Sr-89 I Sr-90 I 1-131" I Cs-134- I CsI137* Ba-140° La-140*'

01/21/14 1.33E+03 +/- 1.33E+02 [a] [a] < 7.92E-01 " 4.62E+00 < 5.12E+00 < 4.14E+01 < 1.36E+01 02/18/14 1.41E+03 +/- 1.27E+02 [a] [a] " 8.65E-01 " 4.06E+00 < 5.34E+00 < 2.33E+01 < 7.75E+00 03/19/14 1.39E+03 +/- 7.66E+01 < 3.25E+00 < 8.42E-01 < 9.63E-01 " 1.63E+00 < 2.05E+00 < 1.69E+01 < 5.82E+00 04/16/14 1.39E+03 +/- 1.46E+02 [a] [a] " 7.50E-01 < 5.24E+00 < 6.58E+00 < 2.95E+01 < 9.53E+00 05/21/14 1.37E+03 +/- 1.54E+02 [a] [a] " 1.OOE+00 < 6.13E+00 < 6.42E+00 < 3.63E+01 < 1.21E+01 06/18/14 1.21E+03 +/- 1.64E+02 < 3.31 E+00 < 8.19E-01 " 8.13E-01 " 7.73E+00 < 7.64E+00 < 3.47E+01 < 1.06E+01 07/15/14 1.35E+03 +/- 1.53E+02 [a] [a] < 7.65E-01 " 8.45E+00 < 8.84E+00 < 4.03E+01 < 1.01E+01 08/19/14 1.23E+03 +/- 1.66E+02 [a] [a] < 8.19E-01 " 6.68E+00 < 7.36E+00 < 3.95E+01 < 1.22E+01 09/16/14 1.25E+03 +/- 1.59E+02 < 2.79E+00 < 1.47E+00 < 7.24E-01 " 6.42E+00 < 6.94E+00 < 2.80E+01 < 1.09E+01 10/21/14 1.41 E+03 +/- 4.79E+01 [a] [a] " 8.53E-01 < 2.49E+00 < 2.52E+00 < 2.45E+01 < 6.39E+00 11/12/14 1.26E+03 +/- 1.98E+02 [a] [a] " 9.78E-01 < 7.62E+00 < 7.05E+00 < 3.56E+01 < 8.42E+00 12/16/14 1.46E+03 +/- 1.40E+02 < 3.79E+00 < 1.04E+00 < 9.71 E-01 " 5.09E+00 < 6.65E+00 < 4.64E+01 < 1.37E+01 Sta. Mean 1.34E+03 +/- 1.39E+02

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 page

[pCi/kg] 1 of 2 Sampling Sampling Location Date Be-7 K-40 f-131* Cs-134* Cs-137" 05/13/14 1.17E+03 +/- 2.45E+02 6.74E+03 +/- 5.23E+02 < 3.87E+01 < 2.57E+01 < 2.84E+01 14B 06/10/14 8.34E+02 +/- 2.76E+02 6.44E+03 +/- 5.44E+02 < 5.64E+01 < 2.70E+01 < 2.72E+01 07/09/14 9.57E+02 +/- 3.82E+02 8.36E+03 +/- 1.03E+03 < 2.69E+01 < 4.43E+01 < 4.42E+01 08/14/14 1.19E+03 +/- 4.22E+02 5.92E+03 +/- 8.01E+02 < 4.17E+01 < 3.87E+01 < 3.88E+01 09/10/13 5.64E+02 +/- 2.18E+02 8.30E+03 +/- 5.60E+02 < 2-49E+01 < 2.34E+01 < 2.46E+01 10/14/14 1.42E+03 +/- 1.86E+02 7.56E+03 +/- 4.86E+02 < 2.59E+01 < 1.93E+01 < 2.26E+01 Mean 1.02E+03 +/- 2.88E+02 7.22E+03 +/- 6.57E+02 +/- +/- +/-

Sampling Sampling Location Date Be-7 I K-40 1-131" Cs-134* Cs-137" 15 05/13/14 5.80E+02 +/- 1.21E+02 6.54E+03 +/- 3.45E+02 < 3.99E+01 < 1.29E+01 < 1.44E+01 06/10/14 7.43E+02 +/- 2.44E+02 4.85E+03 +/- 4.93E+02 < 5.26E+01 < 2.24E+01 < 2.39E+01 07/09/14 4-87E+02 +/- 4.31E÷02 6.31E+03 +/- 9.46E+02 < 3.04E+01 < 4.24E+01 < 3.76E+01 08/14/14 2.68E+03 +/- 5.57E+02 7.39E+03 +/- 1.02E+03 < 411E+01 < 2.81E+01 < 3.29E+01 09/10/13 1.47E+03 +/- 4.11E+02 6.74E+03 +/- 9.14E+02 < 2.81E+01 < 4.16E+01 < 4.69E+01 10/14/14 3.16E+03 +/- 2.86E+02 5.08E+03 +/- 5.24E+02 < 2.47E+01 < 2.60E+01 < 2.73E+01 Mean 1.52E+03 +/- 3.42E+02 6.15E+03 +/- 7.07E+02 +/- +/- +/-

Sampling Sampling Location Date Be-7 I K-40 1-131* Cs-134" Cs-137*

16" 05/13/14 1.30E+03 +/- 1.53E+02 7.12E+03 +/- 3.85E+02 < 3.58E+01 < 1.61E+01 < 1.76E+01 06/10/14 < 2.70E+02 5.18E+03 +1- 5.50E+02 < 4.60E+01 < 2.37E+01 < 2.72E+01 07/09/14 7.28E+02 +/- 5.30E+02 2.91E+03 +/- 8.97E+02 < 3.30E+01 < 5.30E+01 < 5.59E+01 08/14/14 1.47E+03 +/- 3.84E+02 6.15E+03 +/- 9.36E+02 < 3.26E+01 < 3.11E+01 < 2.95E+01 09/10/13 6.81E+02 +/- 3.06E+02 1.04E+04 +I- 1.10E+03 < 2.95E+01 < 4.65E+01 < 4.98E+01 10/14/14 2.45E+03 +/- 2.23E+02 9.85E+03 +/- 4.47E+02 < 2.80E+01 < 1.92E+01 < 2.02E+01 Mean 1.33E+03 +/- 3.11E+02 6.94E+03 +/- 7.19E+02 +/- +/- +/-

LLD identified in ODCM

- Control Station 51

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

[pCi/kg]

Sampling Sampling Location Date I Be-7 I K-40 1-131" Cs-134" Cs-137" 23 05113/14 7.69E+02 +/- 2.22E+02 7.86E+03 +/- 5.22E+02 < 4.15E+01 < 2.65E+01 < 2.91E+01 06/10/14 1.26E+03 +/- 3.42E+02 5.27E+03 +/- 6.21E+02 < 3.68E+01 < 3.04E+01 < 3.07E+01 07/09/14 8.85E+02 +/- 4.63E+02 5.43E+03 +/- 9.53E+02 < 4.15E+01 < 5.39E+01 < 5.36E+01 08114/14 1.80E+03 +/- 3.82E+02 3.83E+03 +/- 7.65E+02 < 3.62E+01 < 2.22E+01 < 2.48E+01 09/10/13 2.22E+03 +/- 3.83E+02 8.80E+03 +/- 8.90E+02 < 2.67E+01 < 4.24E+01 < 4.86E+01 10/14/14 1.38E+03 +/- 1.14E+02 5.68E+03 +/- 2.72E+02 < 2.90E+01 < 1.22E+01 < 1.23E+01 Mean 1.39E+03 +/- 3.18E+02 6.15E+03 +/- 6.71E+02 +/- +/- +/-

Sampling Sampling Location Date I Be-7 I K-40 1-131 I Cs-134* Cs-137" 26 05/13/14 3.43E+02 +/- 2.17E+02 7.44E+03 +/- 4.08E+02 < 5.16E+01 " 8.68E+00 " 1.03E+01 06/10/14 4.84E+02 +/- 2.57E+02 4.49E+03 +I- 6.89E+02 < 4.19E+01 " 2.78E+01 < 2.97E+01 07/09114 1.40E+03 +/- 4.52E+02 6.63E+03 +/- 1.08E+03 < 3.80E+01 " 4.26E+01 " 5.46E+01 08/14/14 2.67E+03 +/- 4.91E+02 5.92E+03 +/- 8.99E+02 < 3.59E+01 " 2.62E+01 < 2.87E+01 09/10/13 1.21E+03 +/- 2.64E+02 4.41E+03 +/- 5.20E+02 < 2.57E+01 " 2.76E+01 " 3.OOE+01 10/14/14 1.93E+03 +/- 1.60E+02 4.70E+03 +/- 3.39E+02 < 3.33E+01 " 1.66E+01 < 1.82E+01 Mean 1.34E+03 +/- 3.07E+02 5.60E+03 +/- 6.56E+02 +/- +/- +/-

+/-

Indicator locations 1.32E+03 +/- 3.14E+02 6.28E+03 +/- 6.73E+02

LLD identified in ODCM 52

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

[pCi/L]

Station O0A Sampling N~*

Date H-3 I gr-89 Sr-89 I Sr-90 I Mn-54 I Fe-59 I Co-58 I Co-60 Zn-65 1.1 3E+03 [a] [a] < 4.68E+00 < 8.32E+00 < 4.31E+00 < 4.81E+00 < 7.63E+00 03/26/14 *

< 1.79E+00 < 7.59E-01 < 4.27E+00 < 8.60E+00 < 4.92E+00 < 3.99E+00 < 1.04E+01 06/24/14

6.87E+02

[a] [a] < 2.54E+00 < 4.38E+00 < 2.13E+00 < 1.40E+00 < 5.31E+00 09/30/14

1.85E+03

[a] [a] < 4.34E+00 < 9-74E+00 < 4.41E+00 < 5.86E+00 < 8.60E+00 12/31/14

1.09E+03 Mean Sampling fl'3t* 7r-95 I Nb-95 i1 1-131 iI Cs-134 i1 Cs-137 I Ba-140 I La-140 lm Date Zr-95 I Nb-95 1-131 Cs-1 34

< 4.87E+00 < 6.58E-01 < 3.35E+00 < 4.89E+00 < 3.30E+01 < 1.44E+01 03/26/14 < 9.37E+00

< 5.39E+00 < 5.33E-01 < 7.44E+00 < 5.73E+00 < 2.53E+01 < 5.51E+00 06/24/14 < 9.56E+00

< 2.22E+00 < 6.12E-01 < 2.06E+00 < 2.13E+00 < 1.50E+01 < 4.82E+00 09/30/14 < 3.28E+00

< 4.52E+00 < 7.80E-01 < 5.09E+00 < 5.22E+00 < 2.52E+01 < 8.56E+00 12/31/14 < 8.38E+00 Mean

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

53

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

[pCi/L]

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

I 01/14114 [a] [b] [b) 3.79E+00 < 9.31 E+00 " 3.94E+00 < 3.86E+00 < 8.08E+00 02/11/14 al [b] [b] 3.34E+00 < 8.08E+00 < 3.46E+00 < 3.93E+00 " 7.06E+00 03/12/14 3.OOE+03 +/- 1.23E+03 [b] [b] < 4.40E+00 1.32E+01 " 6.66E+00 < 5.80E+00 " 1.19E+01 04115/14 [a] [b] [b] < 4.25E+00 <1.23E+01 " 4.97E+00 " 5.20E+00 " 1.05E+01 05/12/14 a] [b) [b] < 4.98E+00 S7.05E+00 " 4.33E+00 < 3.63E+00 " 9.17E+00 06/17/14 3.05E+03 +/- 9.35E+02 < 4.29E+00 9.23E-01 < 4.28E+00 " 8.31E+00 " 3.90E+00 " 3.74E+00 7.37E+00 07/15/14 [a] ib] [b] < 4.54E+00 " 9.98E+00 " 5.09E+00 " 5.74E+00 1.10E+01 08/11/14 a] [b] b] < 4.81E+00 " 8.13E+00 3.84E+00 < 4.98E+00 I 8.68E+00 09/16/14 2.99E-03 +/- 1.69E÷03 [b] [b] I 6.45E+00 " 1.20E+01 " 6.60E+00 < 6.19E+00 " 1.15E+01 10/15/14 [a] [b] (b] < 3.03E+00 "8.20E+00 < 3.35E+00 " 3.58E+00 " 6.27E+00 11/12/14 a] [b] [b] < 4.61E+00 " 9.34E+-00 " 4.82E+00 " 4.48E+00 " 8.91E+00 12/16/14 2.43E+03 +/- 1.30E+03 [b] [b] < 3.07E+00 " 7.54E+-00 " 3.OOE+00 " 3.29E+00 " 5.60E+00 MEAN 2.87E+03 +/- 1.29E+03 +/- + +I-Sampling Date I Nb-95* Zr-95 I 1-131" I Cs-134.9+ Cs-137+0 Ba-140* La-140o 01/14/14 7.48E+00 " 4.85E+00 < 7.57E-01 < 3.59E+00 4.01E+00 < 4.69E+01 < 1.46E+01 02/11/14 6.92E+00 < 3.64E+00 < 5.05E-01 " 3.57E+00 S4.03E+00 " 1.97E+01 < 5.31E+00 03/12/14 9.61 E+00 " 7.03E+00 < 6.43E-01 < 5.95E+00 6.61E+00 " 2.52E+01

8.42E+00 04/15/14 8.89E+00 " 5.01E+00 < 6.59E-01 < 4.50E+00

4.82E+00 < 3.29E+01 < 1.40E+01 05/12/14 9.19E+00 < 5.23E+00 < 5.50E-01 " 4.54E+00 5.13E+00 " 2.20E+01 < 6.30E+00 06/17/14 7.37E+00 " 4.18E+00 < 4.73E-01 " 3.86E+00 4.57E+00 < 1.96E+01

5.27E+00 07/15/14 8.74E+00 " 6.07E+00 < 7.68E-01 < 4.68E+00

5.03E+00 < 2.69E+01 < 7.01E+00 08/11/14 8.53E+00 < 3.91E+00 < 5.77E-01 < 4.07E+00

4.05E+00 < 2.35E+01 < 8.29E+00 09/16/14 9.51E+00 < 5.54E+00 < 4.99E-01 " 5.39E+00

5.66E+00 < 3.17E+01 < 1.19E+01 10/15/14 6.26E+00 " 3.19E+00 < 1.25E+00 " 3.17E+00 3.44E+00 < 2.06E+01

6.10E+00 11112/14 8.10E+00 < 4.96E+00 < 4.91E-01 < 4.55E+00 5.03E+00 < 2.03E+01

7.01E+00 12/16/14 6.07E+00 < 3.23E+00 < 3.08E-01 < 2.80E+00

3.18E+00 " 2.05E+01 < 9.84E+00 MEAN +/-

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

1-131 LLD of 1 pCi/L not met on 10/15/14 sample due to delay in sample arriving at laboratory for analysis.

54

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

[pCi/L]

Sampling Station 08 Mn-54*

Date H-3* Sr-89 I Sr-90 Fe-59*

Co-58" Co-60*

01/14/14 [a] [b] [b] 3.77E+00 < 1 09E+01 " 4.91E+00 3.64E+00 " 8.61E+00 02/11/14 1a] [b] [b] " 3.54E+00 < 7.42E+00 " 3.15E+00 5.19E+00 " 7.16E+00 03/12/14 3.07E+03 +1- 1.22E+03 [b) [b] " 4.61 E+00 < 1.12E+01 " 5.35E+00 4.95E+00 " 1.25E+01 04/15/14 [a] [b) [b] < 5.48E+00 < 1.09E+01 " 6.28E+00 5.56E+00 " 1.15E+01 05/12/14 [a] [b] [b] " 2.91E+00 < 6.59E+00 " 3.46E-00 3.63E+00 " 6.27E+00 06/17/14 1.81E-03 -/- 8.15E-02 < 4.67E+00 < 8.48E-01 " 2.91E+00 < 6.02E+00 " 2.66E+00 2.97E+00 < 5.46E+00 07/15/14 [a] [b] [b] " 3.62E+00 < 7.87E+00 " 3.34E+00 4.20E+00 " 7.77E+00 08/11/14 [a] [b] [b] < 3.22E+00 < 5.71E+00 " 2.88E+00 3.77E+00 " 6.19E+00 09/16/14 < 1.89E+03 [b] [b[ 5.26E+00 < 1.14E+01 " 5.70E+00 5.30E+00 < 8.66E+00 10/15/14 [a] [b] [b)

2.90E+00 < 6.88E+00 " 2.81E+00 2.72E+00 " 5.36E+00 11/12/14 [a] [b] [b]

3.21 E+00 I 7.32E+00 " 3.66E+00 2.74E+00 " 6.87E+00 12/16/14 3.OOE+03 +/- 1.35E+03 [b] [b]

2.45E+00 < 5.31E+00 " 2.74E+00 2 14F+00 " 4.20E+00 Mean 2.63E+03 +/- 1.32E+03 +/- +1- +/-

Sampling Date I Zr-95* Nb-95* I 1-131"* I Cs-134" Cs-137" Ba-140* I La-140

-j 01/14/14 8.02E+00 < 5.08E+00 < 6.72E-01 " 3.99E+00 < 4.55E+00 < 4.82E+01 1.47E+01 02/11/14 6.531+00 " 3.27E+00 < 5.32E-01 " 3.70E+00 < 3.60E+00 < 1.79E+01 5.14E+00 03/12/14 9.43E+00 " 6.02E+00 < 6.59E-01 " 5.55E+00 < 5.55E+00 < 2.77E+01 9.45E+00 04/15/14 9.13E+00 S5.51E+00 < 6.62E-01 " 4.90E+00 < 4.85E+00 < 2.95E+01 1.15E+01 05/12/14 5.54E+00 " 3.43E+00 5.68E-01 " 3.21E+00 < 3.35E+00 < 1.58E+01 5.11E+00 06/17/14 5.59E+00 " 3.19E+00 < 4.65E-01 " 2.67E+00 < 2.92E+00 < 1.37E+01 4.96E+00 07/15/14 6.64E+00 " 4.38E+00 < 5.99E-01 " 4.06E+00 < 3.88E+00 < 1.94E+01 </ 5.68E+00 08/11/14 4.49E+00 3.69E+00 < 6.59E-01 " 3.07E+00 < 3.59E+00 < 1.57E+01 4.58E+00 09/16114 1.14E+01 " 5.42E+00 < 4.84E-01 " 4.64E+00 < 5.11E+00 < 2.93E+01 8.24E÷00 10/15/14 5.42E+00 " 2.87E*00 < 6.23E-01 " 2.79E+00 < 2.91 E+00 < 1.79E+01 6.33E+00 11/12/14 5.12E+00 " 3.64E+00 < 5.49E-01 " 3.06E+00 < 3.69E+00 < 1.62E+01 5.53E+00 12/16/14 4.22E+00 " 2.91E+00 < 4.69E-01 " 2.30E+00 < 2.60E+00 < 1.88E+01 4.62E+00 Mean +I- +/-

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

55

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

[pCi/L]

Sampling Station 09A Date H-3" Sr-89 Sr-90 Mn-54. Fe Co-58. Co Zn-65*

01/14/14 [a] [b] [b] < 3.54E+00 < 9.10E+00 < 4.34E+00 < 3.92E+00 < 7.84E+00 02/11/14 [a] [b] [b] < 3.50E+00 < 7.81E+00 < 3.91E+00 < 4.20E+00 < 7.32E+00 03/12/14 < 1.40E+03 [b] [b] < 5.03E+00 < 1.13E+01 < 5.79E+00 < 9.78E+00 < 1.08E+01 04/15/14 [a] [b] [b] < 4.83E+00 < 1.26E+01 < 5.45E+00 < 5.44E+00 < 9.75E+00 05/12/14 [a] [b] [b] < 3.80E+00 < 8.06E+00 < 4.39E+00 < 4-26E+00 < 8.03E+00 06/17/14 < 9.78E+02 < 4.36E+00 < 8.81E-01 < 4.42E+00 < 1.03E+01 < 4.52E+00 < 4.65E+00 < 6.78E+00 07/15/14 [a] [b] [b] < 4.20E+00 < 1.07E+01 < 4.26E+00 < 5.57E+00 < 1.04E+01 08/11/14 [a] [b] [b] < 4.64E+00 < 8.00E+00 < 5.39E+00 < 3.96E+00 < 9.07E+00 09116/14 < 1.89E+03 [b[ [b] < 5.32E+00 < 1.13E+01 < 4.74E+00 < 4.61E+00 < 9.76E+00 10/15/14 [a] [b] [b] < 3.32E+00 < 7.50E+00 < 3.24E+00 < 2.93E+00 < 5.64E+00 11/12/14 [a] [b] [b] < 5.51E+00 < 1.05E+01 < 5.85E+00 < 4.24E+00 < 1.32E+01 12/16/14 < 1.69E+03 [b] [b] < 3.53E+00 < 7.45E+00 < 297E+00 < 3.23E+00 < 6.12E+00 MEAN +/- +/- +/- +/- +/- +/- +/-

Sampling Date Zr-95* Nb-95* 1-131* i s-1_34. Cs-137. Ba-140 I La-140" 01/14/14 < 7.43E+00 < 4.53E+00 < 8.14E-01 < 3.23E+00 < 3.69E+00 < 4.48E+01 < 1.48E+01 02/11/14 < 6.65E+00 < 4.16E+00 < 4.93E-01 < 3.85E+00 < 3.59E+00 < 1.86E+01 < 6.68E+00 03/12/14 < 9.94E+00 < 5.20E+00 < 6.39E-01 < 5.15E+00 < 6.30E+00 < 2.41E+01 < 8.20E+00 04/15/14 < 1-13E+01 < 4.93E+00 < 5.43E-01 < 5.10E+00 < 4.50E+00 < 3.76E+01 < 1.12E+01 05/12/14 < 6.77E+00 < 4.25E+00 < 5.25E-01 < 3.58E+00 < 4.31E+00 < 1.85E+01 < 7.07E+00 06/17/14 < 7.93E+00 < 5.69E+00 < 5.85E-01 < 4.39E+00 < 5.06E+00 < 1.90E+01 < 7.64E+00 07/15/14 < 1.00E+01 < 5.74E+00 < 5.61E-01 < 5.01E+00 < 5.93E+00 < 2.51E+01 < 6.38E+00 08/11/14 < 7.08E+00 < 4.69E+00 < 5.95E-01 < 3.82E+00 < 4.06E+00 < 2.22E+01 < 9.72E+00 09/16/14 < 8.85E+00 < 5.24E+00 < 5.54E-01 < 4.73E+00 < 4.70E+00 < 2.29E+01 < 8.60E+00 10/15/14 < 5.72E+00 < 3.46E+00 < 7.80E-01 < 3.36E+00 < 3.03E+00 < 2.26E+01 < 6.14E+00 11/12/14 < 1.04E+01 < 5.80E+00 < 6.45E-01 < 6.45E+00 < 5.84E+00 < 2.74E+01 < 9.21E+00 12/16/14 < 5.89E+00 < 3.32E+00 < 5.01E-01 < 2.95E+00 < 3.28E+00 < 2.43E+01 < 6.76E+00 MEAN +/- +/- +/- +/- +1- +/- +/-

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

56

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

page Sample 1 of 1 Date I Sr-89 Sr-90 K-40 Cs-134* I Cs-137" 4/15/2014 Station 08 [a] [a] 1.29E+03 +/- 4.78E+02 < 5.04E+01 < 4.69E+01 Station 09A** [a] [a] 2.78E+04 +/- 1.73E+03 < 6.30E+01 < 7.47E+01 Station 11 [a] [a] 1.83E+04 +/- 1.60E+03 < 6.59E+01 < 7.63E+01 Ra-226 I Th-228 I Th-232 I 4/15/2014 Station 08 < 1.10E+03 9.85E+01 +I- 7.55E+01 < 1.98E+02 Station 09A** 1.97E+03 +/- 1.60E+03 1.08E+03 +/- 1.14E+02 8.69E+02 +/- 1.91E+02 Station 11 2.37E+03 +/- 1.40E+03 1.84E+03 +/- 1.22E+02 1.73E+03 +/- 2.01E+02 Sample Date I Sr-89 Sr-90 K-40 I Cs-134 I Cs-137 10/15/2014 Station 08 < 1.80E+02 < 3.06E+01 1.87E+03 +/- 6.23E+02 < 3.31E+01 < 3.42E+01 Station 09A** < 1.87E+02 < 2.86E+01 3.38E+04 +1- 1.86E+03 < 5.OOE+01 < 5.54E+01 Station 11 < 1.87E+02 < 3.55E+01 2.68E+04 +/- 1.49E+03 < 4.85E+01 < 6.13E+01 Ra-226 I Th-228 I Th-232 I 10/15/2014 Station 08 < 9.43E+02 1.05E+02 +/- 5.91E+01 < 1.25E+02 Station 09A** < 9.19E+02 4.48E+02 +/- 6.33E+01 4.14E+02 +/- 1.18E+02 Station 11 2.69E+03 +/- 1.05E+03 102E+03 +/- 8.16E+01 1.12E+03 +/- 1.26E+02 MEAN Sr-89 Sr-90 K-40 Cs- 34* I Cs-137l Indicator +/- +/- 1.21E+04 +/- 1.05E+03 +/- +I-Control +I- +1- 3.08E+04 +/- 1.80E+03 +/- +/-

Ra-226 I Th-228 I Th-232 I Indicator 2.53E+03 +/- 1.13E+03 7.66E+02 +/- 8.46E+01 1.43E+03 +/- 1.63E+02 Control 1.97E+03 +/- 1.60E+03 7.64E+02 +/- 8.87E+01 6.42E+02 +1- 1.55E+02

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 I Sr-90 I K-40 I Cs-134 I Cs-137-4/24/2014 Station 08 [a] [a] 1.53E+03 +/- 5.54E+02 < 4.99E+01 < 5.96E+01 Ra-226 Th-228 Th-232

< 1.20E+03 1.49E+02 +/- 9.63E+01 2.65E+02 +/- 9.05E+01 Sample Date I Sr-89 Sr-90 K-40 Cs-134" I Cs.137 10/15/2014 Station 08 < 1.82E+02 < 3.70E+01 5.27E+02 +/- 5.31 E+02 < 4.80E+01 < 5.45E+01 I Ra-226 I Th-228 I Th-232 I

< 1.26E+03 1.47E+02 +/- 7.41E+01 < 1.98E+02 MEAN I Sr-89 I Sr-90 I K-40 I Cs-134* I Cs-137* I

+/- +/- 1.03E+03 +/- 5.43E+02 +/- +/-

I Ra-226 I Th-228 I Th-232 I

+/- 1.48E+02 +/- 8.52E+01 2.65E+02 +/- 1.44E+02

LLD identified in ODCM

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

58

Table 3-15 Fish page Gamma Spectra 1 of 1

[pCi/Kg]

Fish [a]

Sampling Station 08 Date I K-40 I Mn-54' I Fe-59* I Co-58" I Coo60. I Zn-65* I Cs- 34 I Cs-"137 I 04/16/14 1.96E+03 +/- 1.08E+03 < 9.49E+01 < 2.34E+02 < 8.59E+01 < 8.72E+01 < 1.77E+02 < 8.81E+01 < 9.55E+01 10/16/14 1.96E+03 +/- 8.77E+02 < 8.03E+01 < 1.46E+02 < 8.86E+01 < 8.63E+01 < 1.44E+02 < 6.82E+01 < 8.24E+01 Sampling Station 25*

Date I K-40 Mn I Fe-59 I Co-58 I Co-60 I Zn-65 I Cs-134- I Cs-137 I 04/16/14 2.41E+03 +/- 7.84E+02 < 5.90E+01 < 1.36E+02 < 5.52E+01 < 6.45E+01 < 1.29E+02 < 5.37E+01 < 4.80E+01 10/16/14 1.37E+03 +/- 8.41E+02 < 9.53E+01 < 1.84E+02 < 1.08E+02 < 9.41E+01 < 1.64E+02 < 8.16E+01 < 8.77E+01 catfish [b]

Sampling Station 08 Date I K-40 I Mn-54" I Fe-59 I Co-58" I Coo60. I Zn-65* I Cs-34* I Cs-137 I 04/16/14 1.58E+03 +/- 6.19E+02 < 6.24E+01 < 1.44E+02 < 6.22E+01 < 7.78E+01 < 1.28E+02 < 5.18E+01 < 7.27E+01 10/16/14 1.40E+03 +/- 6.94E+02 < 6.79E+01 < 2.06E+02 < 5.82E+01 < 8.24E+01 < 1.35E+02 < 6.39E+01 < 6.73E+01 Sampling Station 25*

Date I K-40 Mn-54' I Fe I CoO58 Co"60 I Zn-65' I Cs-i 34' Cs-'137 I 04/16/14 1.58E+03 +/- 1.02E+03 < 6.72E+01 < 1.21E+02 " 7.66Ei-01 " 7.13E+01 < 1.05E+02 < 6.32E+01 < 6.61E+01 10/16/14 2.35E+03 +/- 1.27E+03 < 6.61 E+01 < 2.28E+02 " 1.18E+02 " 4.61E+01 < 2.36E+02 < 8.31E+01 < 1.12E+02 Mean 1.73E+03 +/- 8.98E+02 Indicator 1.73E+03 +/- 8.18E+02 Control 1.93E+03 +/- 9.79E+02

LLD identified in ODCM

- Control Station

[a] Non-bottom dwelling species of gamefish.

[b] Bottom dwelling species of fish.

59

DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2014 and tabulated in Section 3, are discussed below. Except for TLDs, Teledyne Brown Engineering 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 2014 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 2014 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 60

dose with the replacement TLDs is lower than that of the previously used TLDs.

This will continue to be monitored.

9.0 8.0 7.0 6.0___

5.0 4.0 -- $-Environmental TLI~s

-USector TLI~s 3.0

-- Avg. Pre-op 2.0 1.0 0.0 ko 0 N 00 0 9C. 9 '9 9 -4 '-I C C C M0 10 10 Figure4-1 TLD (mrem/StandardMonth)

Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. A self assessment of the Offsite Dose Calculation Manual environmental program requirements was conducted during this reporting period. It was identified that outer ring sector TLDs in the SE, SSW and WSW sectors are located at distances greater than the 5 mile distance required by the Offsite Dose Calculation Manual with sector TLDs located at 5.88 miles, 5.3 miles and 7.1 miles respectively. A subsequent evaluation found that these three TLD locations either deviate less than twenty percent from the distance requirement where the sector is mostly covered by water or the TLD is placed at a combined TLD / Air sample location.

It was determined that these locations meet the intent of the environmental program and that having these TLDs at their current locations in no way jeopardizes public health and safety. Therefore, it was concluded that these current TLD locations are acceptable and no TLDs need be relocated.

61

The average level of these 32 sector TLD locations (two badges at each location) was 4.0 mR/standard month with a range of 1.3 to 8.0 mR/standard month.

The highest quarterly average reading for any single location was obtained at location NW-29/61. This value was 7.1 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 1.6 to 5.8 mR/standard month. The average annual reading for these locations was 2.9 mR/standard month with a range from 2.0 to 4.1 mR/standard month. The control location showed a quarterly average of 2.7 mR/standard month with a range of 2.5 to 3.1 mR/standard month. Its annual reading was 2.8 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 7.1 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 3.15, while Station C-1/2 and C-5/6 had a quarterly average of 2.4 mR/standard month with a range of 1.6 to 3.4 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. The drop indicated in 2009 may be a function of a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this is in fact the case. Inner and outer ring monitoring locations c'ontinue 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 .

62

0.12 0.1 E 0.08 0.06 C.

0.04 0.02 0

~~~~ 0n - 0 r0 w- o mNL)C ~N (~) .~

w W w m3 m C u u u u cu C C, 2 8C Cu C Cu CD OC

- Control Sta-24 - Indicator Average Pre-op - Required LLD Figure4-2 HistoricalGross Beta in Air Particulates 2.50E-02 2.OOE-02 1.50E-02 W-

air-1 .OOE-02 5.OOE-03 O.OOE+0O I (N m M .q . 1;r U,

-4 -4r -4 -4

-4 -4 -4 -4 -4 U

m m 1.*

C -4 C C

~2J m 0

Cu 0 Cu

4) 0 0 0 z z

--- Sta 24 Ctri -U-Indicators Figure4-3 2014 GrossBeta in Air Particulates(pCi/m 3) 63

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 ParticulateGamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy.

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

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

4.5 Air ParticulateStrontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations. There has been no detection of 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 not collected in 2014.

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

7. Twelve precipitation samples were obtained in 2014. Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements. No plant related isotopes were reported in any precipitation water sample at the indicator location. Naturally occurring 64

gamma emitting radioisotopes were detected. No positive H-3 result was 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 2014 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 sample indicated positive results. Gamma 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. These 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.

4.9 Food Products and Vegetation Food/vegetation samples were collected from five locations and analyzed by gamma spectroscopy. 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. No 65

plant related isotopes were identified in any Vegetation sample during 2014.

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

These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, 1-131, and gamma emitters. 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 Samples of water from the North Anna River were collected monthly. The analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy. The monthly samples are 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 2870 pCi/liter and a range of 2430 to 3050 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.

66

River Water 4500 4500 4000 4000 3500 3500

_j3000 3000 2500 2 5"-Tritium

--U1Required LLD 2000 2000 1500 1500 1000 1000 Figure4-4 Tritium 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 spectroscopy 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 samples. No tritium was detected at the control location. The average level of tritium activity at the indicator station was 2630 pCi/liter with a range of 1810 to 3070 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.

67

Figure 4.5Tritium in Surface Water 100I0 1000 0Ioo -Required LLD Average Pre-op

-Tritium 10 w~ 3 0 aL 0 ~ ~ L.t~ 2 W2 i.

n 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 spectroscopy. The October samples were analyzed for strontium-89 and strontium-90. The results are presented in Table 3-13.

No plant related isotopes were detected in 2014. The detection of Cs-137 in bottom sediment is historically common with positive indications usually 68

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

Neither Strontium-89 nor Strontium-90 was detected in any samples of aquatic sediment/silt in 2014. 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.

1600 1400 1200

--- Station-8 S1000 -U- Station-9 to 800 Control-Sta-09A Station-11

-Average Pre-Op 400 - Required LLD's 200 0

ýýS@EgRaSDSC-Da-)SsBC30 Figure4-6 Cs-137 in Sediment/Silt 4.14 Shoreline Soil Shoreline soil/ sediment, unlike bottom sediment, may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses.

Samples of shoreline soil were collected in April and October from indicator station 08. The samples were analyzed by gamma spectroscopy. The October sample was analyzed for strontium-89 and strontium-90. The results are presented in Table 3-14.

69

Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities. No plant related isotopes were detected in any 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 2014 and analyzed by gamma spectroscopy. Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately. The results are presented in Table 3-15. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected. Cs- 137 was measured in pre-operational environmental fish samples.

70

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2014 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14B, 15,16,23, Vegetation 01/14/14 Seasonal unavailability 26 14B, 15,16,23, Vegetation 02/11/14 Seasonal unavailability 26 14B, 15,16,23, 26 Vegetation 03/12/14 Seasonal unavailability STA I *AP/Char 03/12/14 Sampler not running/ replaced. Minimum volume not met.

STA I *AP/Char 03/19/14 Sampler not running/ replaced. Minimum Volume not met.

14B,15,16,23, Vegetation 04/08/14 Seasonal unavailability 26 STA 5 *AP/Char 04/29/14 Sampler not running/ replaced. Minimum volume not met.

STA 6 *AP/Char 09/23/14 Sampler not running/ replaced. Minimum volume not met.

AP/Char Sampler not running/ replaced. Minimum STA 0]A 10/28/14 volume not met.

14B,15,16,23, Vegetation 11/12/14 Seasonal unavailability 26 14B, 15,16,23, Vegetation 12/09/14 Seasonal unavailability 26

AP/Char denotes an air particulate and charcoal sampling station.

71

REFERENCES 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 IOCFR50, 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," 27th 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.

72

APPENDICES 73

APPENDIX A: LAND USE CENSUS Year 2014 74

LAND USE CENSUS North Anna Power Station Louisa County, Virginia January I to December 31, 2014 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden (> Meat Milch Milch Boundary 50m2 ) Animal Cow Goat N 0.9 1.3 1.78 2.9 NONE NONE NNE 0.9 0.9 1.22 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.37 2.4 2.65 NONE NONE E 0.8 1.3 2.04 3.5 NONE NONE ESE 0.9 1.7 1.7 NONE NONE NONE SE 0.9 1.4 1.54 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE S 0.9 1.03 1.02 2.0 NONE NONE SSW 1 127 1.33 2.0 NONE NONE SW 1.1 1.65 1.65 NONE NONE NONE WSW 1.1 1.62 2.22 1.62 NONE NONE W 1.1 1.5 1.93 4.4 NONE NONE WNW 1 1.1 2.67 4.98 NONE NONE NW 1 1.0 1.96 NONE NONE NONE NNW 0.9 1.0 1.22 2.3 NONE NONE 75

2013 to 2014 Land Use Census Changes 2013 2014 Nearest Direction Distance Distance Resident NONE Site Boundary NONE Garden WSW 2.36 2.22 WNW 2.59 2.67 Meat Animal NONE Milch Cow NONE Milch Goat NONE 76

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2014 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:

77

E & Z Analytics:

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

Air particulate for gamma emitters once per quarter Charcoal for 1-131 once per quarter ERA Water for tritium, gamma, Iodine-131, Sr-89, Sr-90, gross alpha and beta during the 2nd and 4th quarters.

Water for natural uranium during the 2nd quarter DOE Water and soil for gamma, Iodine-131, U-233/234, U-238, transuranics, tritium, Fe-55, Ni-63, Sr-90 and Tc-99 analyses during the 1st quarter.

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

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

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

78

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

For the TBE laboratory, 163 out of 169 analyses performed met the specified acceptance criteria. Six analyses (Ni-63, K-40 and 1-131 in water, and two Sr-90s and one Gross Alpha in AP samples) did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's MAPEP March 2014 Ni-63 in water result of 32.7 +/- 1.69 Bq/L was overlooked when reporting the data but would have passed the acceptance range of 23.9 - 44.2 Bq/L.

2. Teledyne Brown Engineering's MAPEP March 2014 K-40 in water result of 1.63 +/- 2.49 Bq/L was overlooked when reporting the data but would have passed the false positive test. NCR 14-04

3. Teledyne Brown Engineering's ERA November 2014 1-131 in water result of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, failing below the lower acceptance limit of 16.8. The result was evaluated as failed with a found to known ratio of 0.778. No cause could be found for the slightly low result. All ERA 1-131 evaluations since 2004 have been acceptable. NCR 14-08

4. Teledyne Brown Engineering's MAPEP March 2014 Sr-90 in AP result of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, failing below the lower acceptance limit of 0.83 Bq/sample. The rerun result was still low, but fell within the lower acceptance range of 0.836. The rerun result was statistically the same number as the original result. No cause could be found for the slightly low results. NCR 14-04 79

5. Teledyne Brown Engineering's MAPEP September 2014 Sr-90 in AP result of 0.310 Bq/sample was lower than the known value of 0.703 Bq/sample. The gravimetric yield of 117% was very high (we normally see yields of 60% to 70 %) and could account for the low activity. NCR 14-09

6. Teledyne Brown Engineering's MAPEP September 2014 Gr-Alpha in AP result of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample. The AP sample was counted on the wrong side.

The AP was flipped over and recounted with acceptable results.

NCR 14-09 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.

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

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2014 E10854 Milk Sr-89 pCi/L 95.1 91.7 1.04 A Sr-90 pCi/L 10.9 15.1 0.72 W E10855 Milk 1-131 pCi/L 96.6 98.5 0.98 A Ce-141 pCi/L 112 119 0.94 A Cr-51 pCi/L 449 491 0.91 A Cs-134 pCi/L 186 210 0.89 A Cs-137 pCi/L 250 253 0.99 A Co-58 pCi/L 248 268 0.93 A Mn-54 pCi/L 292 297 0.98 A Fe-59 pCi/L 230 219 1.05 A Zn-65 pCi/L 312 323 0.97 A Co-60 pCi/L 321 337 0.95 A E10857 AP Ce-141 pCi 53.0 53.9 0.98 A Cr-51 pCi 232 223 1.04 A Cs-1 34 pCi 100 95.3 1.05 A Cs-137 pCi 122 115 1.06 A Co-58 pCi 122 121 1.01 A Mn-54 pCi 135 135 1.00 A Fe-59 pCi 111 99.3 1.12 A Zn-65 pCi 140 147 0.95 A Co-60 pCi 187 153 1.22 W E10856 Charcoal 1-131 pCi 74.1 76.4 0.97 A E10858 Water Fe-55 pCi/L 2090 1760 1.19 A June 2014 E10913 Milk Sr-89 pCi/L 85.9 91.3 0.94 A Sr-90 pCi/L 13.8 14.5 0.95 A E10914 Milk 1-131 pCi/L 86.5 90.9 0.95 A Ce-141 pCi/L ill 124 0.90 A Cr-51 pCi/L 255 253 1.01 A Cs-134 pCi/L 147 162 0.91 A Cs-137 pCi/L 123 120 1.03 A Co-58 pCi/L 105 112 0.94 A Mn-54 pCi/L 155 156 0.99 A Fe-59 pCi/L 106 102 1.04 A Zn-65 pCi/L 251 252 1.00 A Co-60 pCi/L 218 224 0.97 A E10916 AP Ce-141 pCi 95.1 92.6 1.03 A Cr-51 pCi 215 190 1.13 A Cs-134 pCi 122 122 1.00 A Cs-137 pCi 95.1 89.8 1.06 A Co-58 pCi 88.7 84.1 1.05 A 81

Mn-54 pCi 115 116 0.99 A Fe-59 pCi 72.6 76.7 0.95 A Zn-65 pCi 193 189 1.02 A Co-60 pCi 179 168 1.07 A E10915 Charcoal 1-131 pCi 85.6 85.2 1.00 A ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Value Month/Year Number Matrix Nuclide Units Value (a) (b) TBE/Analytics Evaluation (d)

June 2014 E10917 Water Fe-55 pCi/L 1680 1810 0.93 A September 2014 E10946 Milk Sr-89 pCi/L 90.7 96.9 0.94 A Sr-90 pCi/L 14.0 16.4 0.85 A E10947 Milk 1-131 pCi/L 92.0 97.6 0.94 A Ce-141 pCi/L 117 126 0.93 A Cr-51 pCi/L 281 288 0.98 A Cs-1 34 pCi/L 141 158 0.89 A Cs-1 37 pCi/L 186 193 0.96 A Co-58 pCi/L 137 143 0.96 A Mn-54 pCi/L 138 142 0.97 A Fe-59 pCi/L 162 158 1.03 A Zn-65 pCi/L 75.2 73.0 1.03 A Co-60 pCi/L 286 297 0.96 A E10949 AP Ce-141 pCi 97.8 82.1 1.19 A Cr-51 pCi 212 188 1.13 A Cs-134 pCi 106 103 1.03 A Cs-137 pCi 131 126 1.04 A Co-58 pCi 85.7 93.0 0.92 A Mn-54 pCi 92.8 92.3 1.01 A Fe-59 pCi 113 103 1.10 A Zn-65 pCi 53.2 47.5 1.12 A Co-60 pCi 202 193 1.05 A E10948 Charcoal 1-131 pCi 83.9 89.8 0.93 A E10950 Water Fe-55 pCi/L 2010 1720 1.17 A E10951 Soil Ce-141 pCi/g 0.208 0.186 1.12 A Cr-51 pCi/g 0.398 0.425 0.94 A Cs-134 pCi/g 0.216 0.233 0.93 A Cs-1 37 pCi/g 0.398 0.365 1.09 A Co-58 pCi/g 0.197 0.211 0.93 A 82

Mn-54 pCi/g 0.242 0.209 1.16 A Fe-59 pCi/g 0.238 0.233 1.02 A Zn-65 pCi/g 0.117 0.108 1.08 A Co-60 pCi/g 0.447 0.438 1.02 A December 2014 E11078 Milk Sr-89 pCi/L 85.7 95.7 0.90 A Sr-90 pCi/L 12.9 15.6 0.83 A El1079 Milk 1-131 pCi/L 85.9 95.1 0.90 A Ce-141 pCi/L 205 219 0.94 A Cr-51 pCi/L 402 406 0.99 A Cs-134 pCi/L 156 164 0.95 A Cs-137 pCi/L 194 198 0.98 A Co-58 pCi/L 122 130 0.94 A Mn-54 pCi/L 220 225 0.98 A Fe-59 pCi/L 183 175 1.05 A Zn-65 pCi/L 287 297 0.97 A Co-60 pCi/L 224 235 0.95 A 83

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 30F 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2014 El1081 AP Ce-141 pCi 96.4 102 0.95 A Cr-51 pCi 171 190 0.90 A Cs-1 34 pCi 73.1 76.9 0.95 A Cs-1 37 pCi 99.0 92.6 1.07 A Co-58 pCi 57.5 60.8 0.95 A Mn-54 pCi 107 105 1.02 A Fe-59 pCi 74.2 81.6 0.91 A Zn-65 pCi 144 139 1.04 A Co-60 pCi 114 110 1.04 A El1080 Charcoal 1-131 pCi 93.5 98.2 0.9'5 A E11082 Water Fe-55 pCi/L 1760 1970 0.8 '9 A (a) Teledyne Brown Engineering reportedresult.

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

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning, reportedresult 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.

84

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)

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

March 2014 14-MaW30 Water Am-241 Bq/L 0.764 0.720 0.504 - 0.936 A Cs-1 34 Bq/L 20.7 23.1 16.2 -30 0 A Cs-137 Bq/L 28.0 28.9 20.2 - 37.6 A Co-57 Bq/L 26.5 27.5 19.3 - 35.8 A Co-60 Bq/L 15.6 16.0 11.2 -20.8 A H-3** Bq/L NR 321 225-417 N (3)

Mn-54 Bq/L 13.5 13.9 9.7 - 18.1 A Ni-63 Bq/L NR 34.0 23.8 - 44.2 N (3)

Pu-238 Bq/L 0.911 0.828 0.580 - 1.076 Pu-239/240 Bq/L 0.751 0.676 0.473 - 0.879 K-40 Bq/L NR (1) N (3)

Sr-90** Bq/L NR 8.51 5,96-11.06 N (3)

U-234/233** Bq/L NR 0.225 0.158 - 0.293 N (3)

U-238** Bq/L NR 1.45 1.02-1.89 N (3)

Zn-65 Bq/L -0.201 (1) A 14-MaS30 Soil Cs-134 Bq/kg 2.02 (1) A Cs-137 Bq/kg 1300 1238 867-1609 A Co-57 Bq/kg 1069 966 676-1256 A Co-60 Bq/kg 1.32 1.22 (2) A Mn-54 Bq/kg 1510 1430 1001 - 1859 A K-40 Bq/kg 669 622 435 - 809 A Sr-90 Bq/kg 4.14 (1) A Zn-65 Bq/kg 763 695 487 - 904 A 14-RdF30 AP Cs-134** Bq/sample NR 1.91 1.34-2.48 N (3)

Cs-1 37** Bq/sample NR 1.76 1.23 - 2.29 N (3)

Co-57** Bq/sample NR (1) N (3)

Co-60** Bq/sample NR 1.39 0.97-1.81 N (3)

Mn-54** Bq/sample NR (1) N (3)

Sr-90 Bq/sample 0.8220 1.18 0.83-1.53 N (3)

Zn-65** Bq/sample NR (1) N (3) 14-GrF30 AP Gr-A Bq/sample 0.606 1.77 0.53-3.01 A Gr-B Bq/sample 0.7507 0.77 0.39-1.16 A 14-RdV30 Vegetation Cs-134 Bq/sample 5.96 6.04 4.23 - 7.85 A Cs-137 Bq/sample 5.06 4.74 3.32 -6.16 A Co-57 Bq/sample 11.8 10.1 7.1 -13.1 A Co-60 Bq/sample 7.34 6.93 4.85 - 9.01 A Mn-54 Bq/sample 8.95 8.62 6.03-11.21 A Sr-90 Bq/sample 1.23 1.46 1.02-1.90 A Zn-65 Bq/sample 8.91 7.86 5.50- 10.22 A 85

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)

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

September 2014 14-MaW31 Water Am-241 Bq/L 0.705 0.88 0.62-1.14 A Cs-134*** Bq/L NR (1) N (4)

Cs-137*** Bq/L NR 18.4 12.9-23.9 N (4)

Co-57*** Bq/L NR 24.7 17.3 - 32.1 N (4)

Co-60*** Bq/L NR 12.4 8.7 - 16.1 N (4)

Mn-54*** Bq/L NR 14.0 9,8-18.2 N (4)

Ni-63 Bq/L 24.07 24.6 17.2 - 32.0 A Pu-238 Bq/L 0.591 0.618 0.433 - 0.803 A Pu-239/240 Bq/L 0.0153 0.0048 (2) A K-40*** Bq/L NR 161 113-209 N (4)

Zn-65*** Bq/L NR 10.9 7.6 - 14.2 N (4)

Cs-14-MaS31 Soil 134*** Bq/kg NR 622 435 - 809 N (4)

Cs-137*** Bq/kg NR (1) N (4)

Co-57*** Bq/kg NR 1116 781 - 1451 N (4)

Co-60*** Bq/kg NR 779 545 - 1013 N (4)

Mn-54*** Bq/kg NR 1009 706 - 1312 N (4)

K-40*** Bq/kg NR 824 577 - 1071 N (4)

Sr-90 Bq/kg 694 858 601-1115 A Zn-65*** Bq/kg NR 541 379 - 703 N (3) 14-RdF31 AP Sr-90 Bq/sample 0.310 0.703 0.492 - 0.914 N (4) 14-GrF31 AP Gr-A Bq/sample 0.153 0.53 0.16 -0.90 N (4)

Gr-B Bq/sample 0.977 1.06 0.53-1.59 A September 2014 14-RdV31 Vegetation Cs-134 Bq/sample 7.31 7.38 5.17-9.59 A Cs-1 37 Bq/sample 8.93 8.14 5.70- 10.58 A Co-57 Bq/sample 10.8 9.2 6.4 - 12.0 A Co-60 Bq/sample 6.31 6.11 4.28 - 7.94 A Mn-54 Bq/sample 7.76 7.10 4.97 - 9.23 A Sr-90 Bq/sample 0.738 0.85 0.60-1.11 A Zn-65 Bq/sample 7.16 6.42 4.49 - 8.35 A 86

The MAPEP cross check isotope list has been reduced due to duplication of effort or analysis not being performed for clients.

- Starting 3Q14, these nuclides will no longer be part of the TBE cross check program due to duplication of effort or analysis not being performed for clients. MAPEP evaluates non-reported analyses as failed if they were reported in the previous series.

- - All future gamma cross check samples for these isotopes will be provided by Analytics.

(1) False positive test.

(2) Sensitivity evaluation (3) Water, Ni-63 overlooked when reporting, but the result of 32.7 +- 1.69 would have passed the acceptance criteria. NCR 14-04 Water, the non-detected K-40 was overlooked when reporting,but would have passed the false positive test. NCR 14-04 AP, Sr-90 rerun was within the low range of the acceptqance criteria. The original and rerun results were statistically the same. No cause could be identified for the slightly low Sr-90 activity. NCR 14-04 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-04 (4) AP, Sr-90 gravimetricyield was very high at 117%. Could indicate larger than normal amounts of calcium in the AP. A second fuming HN0 3 separationwould be required to remove the excess calcium; The Gross Alpha AP was counted on the wrong side. NCR 14-09 AP, Gr-Beta was counted on the wrong side. When flipped over and recounted the results were acceptable. NCR 14-09 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-09 (a) Teledyne Brown Engineeringreportedresult.

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

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

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

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

May 2014 RAD-97 Water Sr-89 pCi/L 38.25 36.7 27.5-43.6 A Sr-90 pCi/L 24.65 26.5 19.2- 30.9 A Ba-133 pCi/L 89.1 87.9 74.0- 96.7 A Cs-1 34 pCi/L 45.55 44.3 35.5-48.7 A Cs-137 pCi/L 91.15 89.1 80.2-101 A Co-60 pCi/L 65.10 64.2 57.8-73.1 A Zn-65 pCi/L 244 235 212-275 A Gr-A pCi/L 45.65 61.0 31.9-75.8 A Gr-B pCi/L 27.95 33.0 21.4-40.7 A 1-131 pCi/L 23.75 25.7 21.3-30.3 A U-Nat pCi/L 9.61 10.2 7.95-11.8 A H-3 pCi/L 8435 8770 7610-9650 A MRAD-20 Filter Gr-A pCi/filter 28.0 46.0 15.4-71.4 A November 2014 RAD-99 Water Sr-89 pCi/L 30.4 31.4 22.8-38.1 A Sr-90 pCi/L 18.6 21.8 15.6-25.7 A Ba-133 pCi/L 46.8 49.1 40.3- 54.5 A Cs-1 34 pCi/L 88.0 89.8 73.7- 98.8 A Cs-1 37 pCi/L 99.0 98.8 88.9-111 A Co-60 pCi/L 92.5 92.1 82.9-104 A Zn-65 pCi/L 325 310 279-362 A Gr-A pCi/L 29.9 37.6 19.4-48.1 A Gr-B pCi/L 27.5 27.4 17.3-35.3 A 1-131 pCi/L 15.8 20.3 16.8-24.4 N (1)

U-Nat pCi/L 5.74 5.80 4.34-6.96 A H-3 pCi/L 6255 6880 5940-7570 A MRAD-21 Filter Gr-A pCi/filter 27.3 36.9 12.4 - 57.3 A (1) The Iodine-131 was evaluated as failed with a ratio of 0. 778. No cause could be found for the slighly low activity. TBE would evaluate this as acceptable with warning. A rerun was not possible due to 1-131 decay. All ERA Iodine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown Engineeringreported result.

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

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

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