Revision as of 01:12, 7 May 2019

Text

Independent Spent Fuel Storage Installation, Submittal of Annual Radiological Environmental Operating Report
	ML16117A279
Person / Time
Site:	North Anna
Issue date:	04/20/2016
From:	Bischof G T; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	Download: ML16117A279 (89)
	v • d • e

t . ,. VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 20, 2016 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Serial No.16-110 NAPS/JHL Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2, enclosed is the 2015 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 Robin Klearman at (540) 894-2436.

Very truly yours,

.1 Gerald T.

Site Vice President Enclosure Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE.Suite 1200 Atlanta, Georgia 30303-1257 Serial No.16-110 NAPS Annual Radiological Environmental Operating Report Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2015 to December 31, 2015 Prepared by Dominion, North Anna Power Station Prepared by: Reviewed by: Approved by:

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2015 to December 31, 2015 Jr. Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Aziz A. Maly . Supervisor Health Physics Technical Services Dominion North Anna Power Station Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2 Table of Contents 1. EXECUTIVE

SUMMARY

...............................................................................................................

4 2. PROGRAM DESCRIPTION

............................................................................................................

7 2.1 Introduction

.............................................................................................................................

7 ' 2.2 Sampling and Analysis Program .............................................................................................

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

22 3.1 Summary ofResults

..............................................................................................................

22 3.2 Analytical Results of2015 REMP Samples .........................................................................

32 4. DISCUSSION OF RESULTS .........................................................................................................

60 4.1 Gamma Exposure Rate .........................................................................................................

60 4.2 Airborne Gross Beta ....................................................................................................

.........

62 4.3 Airborne Radioiodine.:

.........................................................................................................

63 -4.4 Air Particulate Gamma .........................................................................................................

63 4.5 Air Particulate Strontium

......................................................................................................

64 4.6 Soil ........................................................................................................................................

64 4.7 Precipitation

..........................................................................................................................

64 4.8 Cow Milk ...............................................................................................

..............................

64 4.9 Food Products and Vegetation

..............................................................................................

65 4.10 Well Water ..........................................................................................................................

65 4.11 River Water .........................................................................................................................

65 4.12 Surface Water ......................................................................................................................

66 4.13 Bottom Sediment ................................................................................................................

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

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

69 5. PROGRAM EXCEPTIONS

...........................................................................................................

70 REFERENCES

....................................................................................................................................

71 APPENDICES

.....................................................................................................................................

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

73 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS

...............................

76. 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2015 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 Spertt Fuel Storage Installation (ISFSI) Technical Specification 5.5.2. Radioactivity levels from January 1 through December *31, 2015, 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 (NAPS) personnel collect a variety of samples within this area. A number of sampling locations for eac:P, 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 (NAPS) 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 (NAPS), can be compared to the environment surrounding the station. Indicator samples are the second sample type obtaineq.

These samples show how much radiation is 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. 4 I' 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 erivironmentai' samples that 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 exposure pathways to man: Th.ese pathways include airborne, water, aquatic, terrestrial, and direct radiation exposure.

The airborne exposure pathway includes radioactive airborne . .iodine and particulates, and precipitation.

The 2015 airborne results were similar to previous years. Fallout or natural radfoactivity levels remained at levels con.sistent with pastyears' 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 2015 was*3450 pCi/liter.

No other plai;itrelated isotopes were reported in any surface or river water. River water collected from the North Anna Ri,ver, 5.8 miles downstream of the site had an average tritium level of 3350 pCi/liter.

No plarit related isotopes were detected in quarterly precipitation samples. Silt samples indicated the presence of naturally occurring potassium-4U 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 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 location, Lake Orange: Soil samples, which are collected every three years from twelve stations, were not collected in 2015. The terrestrial exposure pathway includes milk and food/vegetation products.

No piant related radioisotope was detected in any milk sampl.es.

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. 5 The direct exposure pathway measures environmental radiation doses* by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years. During 2015, 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 2015 was 0.24 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. / 6

\ 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2015 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 prim;* 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 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 2015 and satisfies the following objectives of the program: To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclide's 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 2015 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 2015. 8 TABLE2-1 North Anna Power Station-2015 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 42° Quarterly

& Annually Thermoluminescent Fredericks Hall 02 5.30 SSW 203° Quarterly

& Annually Dosimetry (TLD) Mineral, Va 03 7.10 WSW 243° Quarterly

& Annually Wares Crossroads 04 5.10 WNW 287° Quarterly

& Annually Route 752 05 4.20 NNE 20° Quarterly

& Annually Stlirgeon's Creek Marina 05A 2.04 N 11° Quarterly

& Annually Levy, VA 06 4.70 ESE 115° Quarterly

& Annually Bumpass, VA 07 7.30 SSE 167° Quarterly

& Annually End of Route 685 21 1.00 WNW 301° Quarterly

& Annually Route 700 22 1.00 WSW 242° Quarterly

& Annually "Aspen Hills" 23 0.93 SSE 158° Quarterly

& Annually Orange, VA 24 22.00 NW 325° Quarterly

& Annually Control Bearing Cooling Tower*

N-1/@,3 0.06 N 100 Quarterly Sturgeon's Creek Marina N-2/3,4 2.04 N 110 Quarterly Parking Lot "C'1 NN.l;:*;-$135 0.24 NNE 32° Quarterly Good Hope Chutch NN:Jii:,4/36 3.77 NNE 25° Quarterly Parking Lot "B" * -*

NE-5/37 0.20 NE 42° Quarterly Lake Anna Marina (Bogg's Dr) NE-6/38 1.46 NE 34° Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 74° Quarterly Route 689 ENE-8/40 2.43 ENE 65° Quarterly Near Training Facility E-9/41 Q.30 E 91° Quarterly "Morning Glory Hill" E-10/42 2.85 .E 93° Quarterly Island Dike ESE-11143 0.12 ESE 103° Q\larterly Route 622 ESE-12/44 4.70 ESE 115° Quarterly DVP Biology Lab SE-13/45 0.64 SE 1380 Quarterly Route 701 (Dam Entrance)

SE-14/46 5.88 SE 137° . Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 158° Quarterly Elk Creek SSE-16/48 2.33 SSE 165° Quarterly NAPS Access Rd. S-17/49 0.36 s 173° Quarterly 9

TABLE2-1 North Anna Power Station -2015 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 s 178° Quarterly Thermoluminescent NAPS Access Rd. SSW-19/51 0.24 SSW 197° Quarterly Dosimetry (TLD) Route 618 5.30 SSW 205° Quarterly 500kvTower SW-21/53 0.60 SW 218° Quarterly Route 700 SW-22/54 3.96 SW 232° Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 237° Quarterly Route 700 (Exclusion Boundary)

WSW-24/56 1.00 WSW 242° Quarterly South Gate Switchyard W-25/57 0.32 w 279° Quarterly Route 685 W-26/58 1.55 w 274° Quarterly End of Route 685 WNW-27/59 1.00 WNW 301° Quarterly Route 685 WNW-28/60 1.40 WNW 303° Quarterly North Gate -Laydown Area NW-29/61 0.52 NW 321° Quarterly Lake Anna Campground NW-30/62 2.54 NW 319° Quarterly

1/#2 Intake NNW-31/63 0.07 NNW 349° Quarterly Route 208 NNW-32/64 2.21 NNW 344° Quarterly Bumpass Post Office C-1/2 7.30 SSE 167° Quarterly Orange, VA C-3/4 22.00 NW 325° Quarterly Control Mineral, VA C-516 7.10 WSW 243° Quarterly Louisa, VA C-7/8 11.54 WSW 257° Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 42° Weekly and Radioiodine Biology Lab OlA 0.64 SE 1380 Weekly Mineral, VA 03 7.10 WSW 243° Weekly Wares Crossroads 04 5.10 WNW 287° Weekly Route 752 05 4.20 NNE 20° Weekly Sturgeon's Creek Marina 05A 2.04 N 110 Weekly Levy, VA 06 4.70 ESE 115° Weekly Bumpass, VA 07 7.30 SSE 167° Weekly 10 TABLE2-1 North Anna Power Station-2015 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Airborne Particulate End of Route 685 21 1.00 WNW 301° Weekly and Radioiodine Route 700 22 1.00 WSW 242° Weekly "Aspen Hills" 23 0.93 SSE 158° Weekly Orange, VA 24 22.00 NW 325° Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 148° Monthly (Second Cooling Lagoon) Lake Anna (upstream) 09A 12.90 WNW 295° Monthly Control (Route 669 Bridge) River Water North Anna River (downstream) 11 5.80 SE 128° Monthly Ground Water Biology Lab OIA 0.64 SE 138° Quarterly (Well Water) Precipitation Biology Lab OlA 0.64 SE 138° Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon) Lake Anna (upstream) 09A 12.90 WNW 295° Semi-Annually Control (Route 669 Bridge) North Anna River (downstream) 11 5.80 SE 128° Semi-Annually Shoreline Soil Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon) Soil NAPS Sewage Treatment Plant 01 0.20 NE 42° Once/3 years Fredericks Hall 02 5.30 SSW 203° Once/3 years Mineral, VA 03 7.10 WSW 243° Once/3 years Wares Crossroads 04 5.10 WNW 287° Once/3 years 11 TABLE2-1 North Anna Power Station -2015 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 20° Once/3 years Sturgeon's Creek Marina 05A 2.04 N 110 Once/3 years Levy, VA 06 4.70 ESE 115° Once/3 years Bumpass, VA 07 7.30 SSE 167° Once/3 years End of Route 685 21 1.00 WNW 301° Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 242° Once/3 years "Aspen Hills" 23 0.93 SSE 158° Once/3 years .Orange, VA 24 22.00 NW 325° Once/3 years Control Milk Lakeside Dairy 12A 7.50 NW 310° Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon) Lake Orange 25 16.5 NW 312° Semi-Annually Control Food Products (Vegetation)

Stagecoach Road 14B 1.22 NNE 40° Monthly if available or at harvest

Route 614 15 1.37 SE 133° Monthly if available or at harvest Route 629/522 16 12.60 NW 314° Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 158° Monthly if available or at harvest "Historic Lane" 26 1.15 s 172 ° Monthly if available or at harvest 12 TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS Thermoluminescent Dosimetry (TLD) (84 TLDs) Quarterly Gamma Dose (12 TLDs) Annually Gamma Dose Airborne Radioiodine Weekly 1-131 Airborne Particulate Weekly Gross Beta Surface Water River Water Quarterly (a) 2nd Quarter Composite Monthly Quarterly( a) 2nd Quarter Composite Monthly Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 1 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3) Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 LLD REPORT UNITS 2 mR+/-2mR mR/std. Month 2 mR+/-2mR mR/std. Month 0.07 pCi/m 3 0.01 pCi/m 3 0.05 0.06 (b) (b) l(c) 15 30 15 15 30 30 15 15 18 60 15 2000 (b) (b) l(c) 15 30 15 15 30 30 15 15 18 60 pCi/m 3 pCi/m 3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L *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 I 0 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

13 SAMPLE MED!! River Water Ground Water (Well Water) Aquatic Sediment Precipitation Shoreline Soil TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQUENCY ANALYSIS LLD La-140 15 Quarterly( a) Tritium (H-3) 2000 znd Quarter Sr-89 (b) Composite Sr-90 (b) Quarterly Gamma Isotopic Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 lO(c) Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly( a) Tritium (H-3) 2000 znd Quarter Sr-89 (b) Sr-90 (b) Semi-Annually Gamma Isotopic Cs-134 150 Cs-137 180 Annually Sr-89 (b) Sr-90 (b) Monthly Gross Beta 4 Semi-Annual Gamma Isotopic 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-140 (d) La-140 (d) Semi-Annually Gamma Isotopic Cs-134 150 Cs-137 180 REPORT UNITS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/kg (dry) *LLDs indicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the listed values. (a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 ( c) LLD for non-drinking water is 10 pCi/liter ( d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

14

MEDIA Soil Milk Fish Food Products (Broadleaf Vegetation)

TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQUENCY ANALYSIS LLD Annually Sr-89 (b) Sr-90 (b) Once per 3 years Gamma Isotopic Cs-134 150 Cs-137 180 Sr-89 (b) Sr-90 (b) Monthly I-131 1 Monthly Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (b) Sr-90 (b) Semi-Annually Gamma Isotopic Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Monthly, if Gamma Isotopic available, or Cs-134 60 at harvest Cs-137 80 I-131 60 REPORT UNITS pCi/kg (dry) pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/kg (wet) pCi/kg (wet) *LLDs indicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the listed values. (a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 ( c) LLD for non-drinking water is 10 pCi/liter ( d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

15 Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Designation Identification 1 (a) 01,NE-5/37 lA OlA,SE-13/45 2 (a) 02,SSW-20/52 3 (a) 03,C-516 4 (a) 04 5 (a) 05 SA (a) OSA,N-2/34 6 (a) 06,ESE-12/44 7 (a) 07, C-1/2 8 08-Water, Fish, Sediment, Shoreline Soil 9A 09A-Water sample, Sediment 11 11-River Water, Sediment 12A 12A-Milk 14B 14 B-Vegetation 15 15-Vegetation 16 16-Vegetation 21 (a) 21,WNW-27/59 22 (a) 22,WSW-24/56 23 (a) 23-SSE-15/47,Vegetation 24 (a)(b) 24,C-3/4 25 (c) 25-Fish 26 26-V egetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil. (b) In Orange ( c) In Lake Orange 16 Map Environmental Station Designation Identification 7/8 C-7/8 1/33 N-1/33 31/63 NNW-31/63 29/61 NW-29/61 3/35 NNE-3/35 7/39 ENE-7/39 9/41 E-9/41 11/43 ESE-11143 17/49 S-17/49 19/51 SSW-19/51 21/53 SW-21/53 23/55 WSW-23/55 25/57 W-25/57 16/48 SSE-16/48 14/46 SE-14/46 22/54 SW-22/54 26/58 W-26/58 28/60 WNW-28/60 32/64 NNW-32/64 8/40 ENE-8/40 4/36 NNE-4/36 10/42 E-10/42 Legend Figure 1. North Anna Site Radiological Monitoring Locations SSW 17

"""**-*******-

.. 18 TSYLVAlllA North Anna Environmental Map

Fixed Environmental Sampling Location

TLD Sampling .Garden Residents

Meat Animals Original O 1991 by AfX of Alexandria , I nc .* 6440 General Green \Nat. Alexandria. VA 22312. USED WITH PERM I SS I ON. No other reproduction m

wi1h:;,..._.

written permission of ADC. CB3280C 19 LA

Fixed Environmental Sampling Location

TLD Sampling .Garden Residents

Meat Animals Orig i nal 1991 by AOC o f Alexand ri a , I nc .. 6440 General Green 'Nay , Alexandria, VA 22312. USED WITH PERM I SSION. No other reproduction may be made without the written permission of AOC. C83282 E North Anna Environmental Map

Fixed Environmental Sampling Location

TLD Sampling .Garden Residents

Meat Animals Original C 1991 by AOC of Alexandria , Inc., 6440 General Gre en 'l'Mf , Alexandria , VA 22312. USED WTH PERM ISSIO N. No other reproduction may be made without the written permission of ADC. C832830 20 e Fixed Environmental Sampling Location e TLD Sampling .Garden Residents e Meat Animals 1991 by ADC of Alexandria. Inc., 6440 General Green 'W;r/. Alexandria , VA 22312. USED WITH PERMISSION. No other re produ ction may be made without the written permission of ADC. NNW N 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 2cr error. 'For TLDs the*mean and range include all values. A more detailed analysis of the. data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries.

22 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia-2015 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<1> Mean Reported Sampled (Unit) Total (pCi/unit)

Range Name Distance Mean Mean Measure-Type No. Direction Ran2e Ran2e men ts Direct Radiation Gamma 256 2 4.2(2541256) 29161 0.52 mi. 7.2(818) 3.0(16116)*

0 (mR/std. Month) Dose (1.0-9.8)

NW (6.3-8.4)

(2.4-3.9) (Sector TLDs) Direct Radiation Gamma 32 2 2.6(16116)

C-112 11.54 3.2 (818) 3.0(16116)*

0 mi. (2.4-3.9) (mR/std. Month) Dose (1.3-3.7)

WSW (2.5-3.7) (Pre-operational TLDs) Direct Radiation Gamma 40 2 5.0(40140)

EPSP-0.37 mi. 7.4(818) 3 .0(16116)*

0 (mR/std. Month) Dose (2.8-9.0) 09110 ENE (6.0-9.0)

(2.4-3.9) (Emergency Sector TLDs) Direct Radiation Gamma 48 2 3.3(44144) 23 0.93 mi. 5.1(414) 3.0(414) 0 (mR/std. month) Dose (0.9-6.2)

SSE (4.5-6.2)

(2.0-4.1) (Environmental TLDs) Direct Radiation Gamma 12 2 2.8(11111) 06 4.70 mi. 4.4(1/1) 3.0(1/1) 0 (mR/std. Month) Dose (1.3-4.2)

ESE (4.4) (3.0) (AnnualTLDs)

Airborne Gross 676 0.01 14.4(6221624)

OIA 0.64 mi. 16.5(52152) 15.6(52152) 0 Particulates Beta (3.05-31.7)

SE (4.47-31.7) ( 4.51-28.3) (lE-03 pCifm3) Air Iodine I-131 676 0.07 (01624) NIA NIA. NIA NIA 0 (pCifm3) Airborne Gamma 52 Particulates (lE-03 pCifm3) Be-7 52 117(48148)

OIA 0.64 mi. 142(414) 127.5(414) 0 (61.9-168)

SE (101-159)

(96-157) Cs-134 52 0.05 (0148) NIA NIA NIA (014) 0 (l) mR/std month for TLDs

C-3/4, -7/8 used as control locations 23 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING Pft_OGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2015 . Docket No. 50-338/339 .Page 2of9 All Indicator Indicator Location

Control Medium or Analvsis Locations with Highest Mean Location Pathway LLD ' Sampled (Unit) Total (pCi/unh)

Mean Name Distance Mean Mean Type No. Range Direction Range *Range Airborne Cs-137 52 0.06 (0148) NIA NIA .NIA (014) Particulates (lE-03 pCi/m3) Sr-89 13 (0112) NIA NIA NIA (Oil) Sr-90 13 (0112) NIA NIA NIA (Oil) Soil*

Triennial (pCi/Kg) (dry) Gamma 12 K-40 12 NIA NIA NIA NIA NIA Cs-134 12 150 NIA NIA NIA NIA NIA Cs-137 12 180 NIA NIA NIA NIA NIA Ra-226 12 NIA NIA NIA NIA* NIA Th-228 12 *NIA NIA NIA NIA NIA Th-232 12 NIA NIA.. NIA NIA NIA Sr-89 12 NIA NIA NIA NIA NIA Sr-90 12 NIA NIA NIA NIA NIA Precipitation Monthly (pCi/liter)

Gross 12 4 6.81(10112)

OlA 0.64 mi. 6.81(10112)

NIA Beta (2.29-14.0)

SE (2.29-14.0)

H-3 2 2000 (012) NIA NIA NIA NIA Semiannual 2 Gamma Be-7* 2 (012) . NIA NIA NIA NIA Mn-54 2 15 (012) NIA NIA NIA NIA Fe-59 2* 30 (012) NIA NIA NIA NIA Co-58 2 15 (012) NIA NIA NIA NIA

Soil Samp.les required triennially.

Samples not obtained in 2015. 24 Non-routine Reported Measure-men ts 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia-2015 Medium or Pathway Sampled (Unit) Precipitation (pCilliter)

Docket No. 50-338/339 Page 3of9 All Indicator Indicator Location Analysis Locations with Highest Mean LLD Tot (pCi/unit)

Mean Name Distance Mean Type al Range Direction Range No. Co-60 2 15 (012) NIA NIA NIA Zn-65 2 30 (012) NIA NIA NIA Zr-95 2 30 (012) NIA NIA NIA Nb-95 2 15 (012) NIA NIA NIA 1-131 2 10 (012) NIA NIA NIA Cs-134 2 15 (012) NIA NIA NIA Cs-137 2 18 (012) NIA NIA NIA Ba-140 2 (012) NIA NIA NIA La-140 2 (012) NIA NIA NIA Th-228 2 (1/2) OlA 0.64mi 5.30 (1/2) SE (5.30) 25 Control Non-Location routine Reported Mean Measure-Range men ts NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa*County, Virginia-2015 Docket No. 50-338/339 Page 4 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)

Mean Name Distance Mean Mean Measure-(Unit) Tvpe No. Ran2e Direction Ran2e. Ran2e men ts Milk Gamma 12 (pCi/liter)

K-40 12 1260(12/12) 12A 7.50 mi. 1260(12/12)

NIA 0 (1140-1390)

NW (1140-1390) 1-131 12 1 (0112) NIA NIA. NIA NIA 0 Cs-137 12 18 (0/12) NIA NIA NIA NIA 0 Ba-140 12 60 (0112) NIA NIA NIA NIA 0 La-140 12 15 (0112) NIA NIA NIA NIA 0 Sr-89 4 (014) NIA NIA NIA NIA 0 (Quarterly)

Sr-90 4 (014) NIA NIA NIA NIA 0 (Quarterly) 26 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia-2015 Docket No. 50-338/339 Page 5 of 9 All Indicator Indicator Location Control Non-Medium or Analvsis Locations with Hie:hest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-' Type No. Ranee Direction Rane:e Rane;e men ts Food Gamma 35 Vegetation, (pCi/kg) (wet) Be-7 35 1570(24124) 23 0.93mi 1950(616) 1070(616) 0 (210-5040)

SSE (525-5040)

(475-1550)

K-40 35 6290(24124) 14B 1.22mi 6730(616) 6140(616) 0 (3500-8570)

NNE (4850-7680)

(3130-8910)

I-131 35 60 (0124) NIA NIA NIA (016) 0 Cs-134 35 60 (0124) NIA NIA NIA (016) 0 Cs-137 35 80 (0124) NIA NIA NIA (016) 0 Ground Tritium 4 2000 (014) NIA NIA NIA NIA 0 Well Water (pCi/liter)

Gamma 4 Mn-54 4 15 (0/4) NIA NIA NIA NIA 0 Fe-59 4 30 (014) NIA NIA NIA NIA 0 Co-58 4 15 (014) NIA NIA NIA NIA 0 Co-60 4 15 (014) NIA NIA NIA NIA 0 Zn-65 4 30 (014) NIA NIA NIA NIA 0 Zr-95 4 30 (014) NIA NIA NIA NIA 0 Nb-95 4 15 (014) NIA NIA NIA NIA 0 I-131 4 10 (0/4) NIA NIA NIA NIA 0 27 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2015 Docket No. 50-338/339 Page 6of9 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled Total (pCi/un Mean Name Distance Mean Mean

Measure-(Unit) Type No. . it) Range Direction Range Range men ts Ground Cs-134 4 15 (014) NIA NIA NIA NIA 0 Well Water (pCi/liter)

Cs-137 4 18 (014) NIA NIA NIA NIA 0 Ba-140 4 60 (014) NIA NIA NIA NIA 0 La-140 4 15 (014) NIA NIA NIA NIA 0 Sr-89 1 (Oil) NIA NIA NIA NIA 0 Sr-90 (Oil) NIA NIA NIA NIA 0 River Water Tritium 4 2000 3350(414) 11 5.80 mi. 3350(414)

(014)* 0 (pCi/liter)

(2150-4840)

SE (2150-4840)

Gamma 12 Mn-54 12 15 (0112) NIA NIA NIA (0112)* 0 Fe-59 12 30 (Oll2) NIA NIA NIA (0112)* 0 Co-58 12 15 (0112) NIA NIA NIA (0112)* 0 Co-60 12 15 (Oll2) NIA NIA NIA (0112)* 0 Zn-65 12 30 (0112) NIA NIA NIA (0112)* 0 Zr-95 12 30 (0112) NIA NIA NIA (0112)* 0 Nb-95 12 15 (0112) NIA NIA NIA (0112)* 0 I-131 12 1 (0112) NIA NIA NIA (0112)* 0 Cs-134 12 15 (0112) NIA NIA NIA (0112)* 0 Cs-137 12 18 (0112) NIA NIA NIA (0112)* 0 *Results of surface water taken at Location 09 A used as control value for river water 28

- Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2015 Docket No. 50-338/339 Page 7of9 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. Ranee Direction Ranee Ranee men ts River Water Ba-140 12 60 (0112) NIA NIA NIA (0/12)* 0 (pCi/liter) 12 15 (0112) NIA NIA NIA (0112)* 0 Sr-89 1 (Oil) NIA NIA NIA (Oil)* 0 Sr-90 1 (Oil) NIA NIA NIA (Oil)* 0 Surface Tritium 8 2000 3450(414) 08 3.37 mi. 3450(414)

(014) 0 Water (pCi/L) (2110-6730)

SSE (2110-6730)

Gamma 24 Mn-54 24 15 (0112) NIA NIA NIA (0112) 0 Fe-59 24 30 (0112) NIA NIA NIA (0112) 0 Co-58 24 15 (0112) NIA NIA NIA (0112) 0 Co-60 24 15 (0/12) NIA NIA NIA (0/12) 0 Zn-65 24 30 (0/12) NIA NIA NIA (0112) 0 Zr-95 24 30 (0112) NIA NIA NIA (0112) 0 Nb-95 24 30 (0112) NIA NIA NIA (0112) 0 1-131 24 1 (0112) NIA NIA NIA (0112) 0 Cs-134 24 15 (0112) NIA NIA NIA (0112) . 0 Cs-137 24 18 (0112) NIA NIA NIA (0112) 0 Ba-140 24 60 (0112) . NIA NIA. NIA (0/12) 0 La-140 24 15 (0/12) NIA NIA NIA (0112) i) *Results of surface water taken at Location 09A used as control value for river water 29 Table3-l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia-2015 , Docket No. 50-338/339 Page 8of9 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. Ran2e Direction Range Range men ts Surface Water Sr-89 (Oil) NIA NIA NIA (Oil) 0 (pCi/liter)

Sr-90 1 (0/1) NIA NIA NIA (Oil) 0 Sediment Silt Gamma 6 (pCi/kg) K-40 6 11200 (414) 11 5.80 mi. 21000 (212) 27200(212) 0 " (1210-25600)

SE (16400-(26800-27600) 25600) Cs-134 6 150 (014) NIA NIA NIA (012) 0 Cs-137 6 180 (014) NIA NIA. NIA (012) 0 Ra-226 6 1490(414) 11 5.80 mi. 1490(212) 2090(1/2) 0 (972-2430)

SE (972-2430)

(2090) Th-228 6 422(414) 11 5.80 mi. 708(212) 566(212) 0 (91.1-822)

SE (593-822)

(529-602)

Th-232 6 632 (214) 11 5.80 mi. 632(212) 561(212) 0 (528-736)

SE (528-736) (479-642) (Annually)

Sr-89 3 (012) NIA NIA NIA (Oil) 0 Sr-90 3 (012) NIA NIA NIA (Oil) 0 Shoreline Soil Gamma 2 (pCi/kg) (dry) K-40 2 523(212) 08 3.37 mi. 523(212) NIA 0 (507-539)

SSE (507-539)

Cs-134 2 150 (012) NIA N'A (012) NIA 0 Cs-137 2 180 (012) NIA f A (012) NIA 0 Ra-226 2 (012) NIA NIA (012) NIA 0 30

.. Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia-2015 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/uuit)

Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Ranl!e men ts Shoreline Soil (pCi/kg) (dry) Th-228 2 51.8(112) 08 . 3.37 mi. 51.8(112)

NIA 0 (51.8) SSE (51.8) Th-232 2 (012) NIA NIA NIA NIA 0 (Annually)

Sr-89 (Oil) NIA N'A NIA NIA 0 Sr-90 1 (Oil) NIA N'A NIA NIA 0 Gamma 8 Fish (pCi/kg) (wet) K-40 8 1450(414) 8 3.37 mi. 1450(414) 2100(414) 0 (1200-1660)

SSE (1200-1660) . (1980-2290)

Mn-54 8 130 (014) NIA N'A NIA (014) 0 Fe-59 8 260 . (014) NIA N'A NIA (014) 0 Co-58 8 130. (014) NIA N'A NIA (014) 0 Co-60 8 130 (014) NIA N'A NIA (014) 0 Zn-65 8 260 (014) NIA N'A NIA (014) 0 Cs-134 8 130 (014) NIA N'A NIA (014) 0 Cs-137 8 150 (014) NIA N'A NIA (014) 0 31 3 . .7 Analytical Results of 2015 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 (2cr) 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 whei:i the measured value exceeds both the MDC and the 2cr error. Because of counting statistics, negative values, *zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of datal. 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 I-131 4. Air Particulates, Quantitative Gamma Spectra 5. Air Strontium

6. Soil 7. Precipitation

8. Cow Milk 9. Food Products and Vegetation

10. Well Water 1 l. River Water 12.

Surface Water 13. Bottom Sediment/Silt

14. Shoreline Soil 15. Fish 1 Analytical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984). 32 TABLE 3-2 DIRECT RADIATION IVIEA$URMENTS

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

Station 12/30/2014 3/31/2015 6/30/2015 9/30/2015 Average 3/31/2015 6/30/2015 9/30/2015 12/29/2015

+/-2 s.d. N-1 6.4 5.2 4.7 4.3 5.0 +/-1.7 N-33 5.3 4.0 4.0 5.8 N-2 2.9 2.3 1.9 2.9 2.7 +/-0.8 N-34 3.0 2.9 2.5 3.1 NNE-3 8.4 7.6 6.1 6.5 7.0 +/-1.9 NNE-35 8.1 6.0 6.1 7.0 NNE-4 5.0 4.6 4.3 4.3 4.2 +/-0.9 NNE36 4.3 3.5 3.9 3.9 NE-5 5.2 4.1 3.2 3.4 4.1 +!'-2.1 NE-37 6.1 3.7 3.1 3.6 NE-6 3.5 3.3 3.2 3.4 3.3 +/-0.6 NE-38 3.5 3.8 2.9 2.9 ENE-7 5.5 4.8 4.7 5.2 5.1 +/-1.4 ENE-39 6.5 4.4 4.6 4.7 ENE-8 2.7 2.2 2.5 2.6 2.4 +/-0.5 ENE-40 2.7 2.0 2.5 2.2 E-9 9.8 5.2 4.4 5.6 5.6 +/-3.7 E-41 6.4 3.9 4.7 4.7 E-10 4.4 5.0 3.1 4.2 +/-1.6 E-42 4.2 3.4 4.9 ESE-11 4.2 *5.2 4.1 4.3 4.2 +/-1.5 ESE-43 5.3 4.1 3.5 3.1 ESE-12 4.9 3.9 3.7 4.8 4.5 +/-1.2 ESE-44 5.5 . 4.7 3.9 *4.4 SE-13 5.2 4.9 3.1 3.9 4.1 +/-1.4 SE:-45 4.5 3.9 4.1 3.5 SE-14 7.5. 5.4 5.6 5.6 6.0 +/-1.9 SE-46 7.3 4.8 5.8 5.8 SSE-15 5.6 4.5 4.9 5.8 4.9 +/-1.3 SSE-47 5.6 4.r 4.4 4.5 SSE-16 .3.0 2.4 3.1 2.3 2.8 +/-1.3 . SSE-48 4.1 2.0 2.7 3.1 *Average of collocated TLDs. 33 TABLE 3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS Page mR/Std. Month (30.4 days) +/- 2 Sigma 2 Of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly*

Station 12/30/2014 3/31/2015 6/30/2015 9/30/2015 Average 3/31/2015 6/30/2015 9/30/2015 12/29/2015

+!-2 s.d. S-17 6.2 3.8 4.5 4.7 4.7 +/-1.5 S-49 4.7 4.8 4.0 5.0 S-18 2.4 2.3 1.3 2.4 2.2 +/-0.8 S-50 2.7 2.2 1.9 2.0 SSW-19 6.2 7.0 6.1 5.6 6.4 +/-1.1 SSW-51 6.4 7.3 6.3 5.9 SSW-20 2.5 1.9 2.2 1.8 2.0 +/-0.7 SSW-52 2.4 1.4 2.3 1.8 SW-21 5.6 4.7 3.5 4.2 4.4 +/-1.6 SW-53 5.2 3.4 3.7 4.8 SW-22 5.3 3.6 3.6 3.7 4.0 +/-1.8 SW-54 5.5 3.9 2.9 3.6 WSW-23 4.9 3.9 4.0 5.2 4.4 +/-1.4 WSW-55 5.3 3.6 3.7 4.9 WSW-24 5.1 4.0 3.9 4.3 4.3 +/-1.2 WSW-56 5.2 3.5 3.9 4.2 W-25 7.9 7.7 4.9 6.4 7.1 +/-2.3 W-57 7.6 7.1 6.7 8.7 W-26 3.2 3.0 2.6 2.7 2.7 +/-0.9 W-58 3.2 1.9 2.2 2.9 WNW-27 3.2 3.4 3.4 3.1 3.1 +/-0.5 WNW-59 3.0 2.7 3.1 2.7 WNW-28 3.0 2.4 3.0 3.2 3.0'+/-0.7 WNW-60 3.6 3.0 2.6 3.1 NW-2,9 7.8 6.3 7.2 6.3 7.2 +/-1.6 NW-61 8.4 7.7 6.5 7.7 NW-30 2.8 1.7 2.0 1.7 2.0 +/-1.1 NW-62 2.3 2.4 1.0 1.8 NNW-31 3.9' 2.5 3.3 3.5 3.1 +/-1.2 NNW-63 3.9 2.6 2.3 3.1 NNW-32 4.5 2.6 3.5 3.5 3.7 +/-1.3 4.6 3.8 3.5 3.2 Mean 4.2 +/-1.6 *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 of4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly*

Station 12/30/2014 3/31/2015 6/30/2015 9/30/2015 Average 3/31/2015 6/30/2015 9/30/2015 12/29/2015

+/-2 s.d. C-1 2.8 3.5 3.1 3.0 3.2 +/-0.9 C-2 3.7 2.5 3.1 3.7 C-3** 3.1 2.5 2.4 3.1 3.0 +/-1.0 C-4** . 3.9 2.6 3.1 3.0 C-5 2.4 1.9 1.3 1.8 1.9 +/-1.0 C-6 2.1 2.8 1.6 1.5 C-7** 4.1 3.1 3.6 4.6 4.0 +/-1.4 C-8** 5.2 3.7 3.5 4.5 2.6 +/-1.6 3.5 +/-1.6 EPSA-01***

6.0 3.9 4.1 5.7 4.7 +/-1.9 EPSA-02***

4.8 4.3 3.4 5.4 EPSF-03***

4.2 4.5 2.9 3.4 4.0 +/-1.3 EPSF-04***

4.7 3.8 3.6 4.7 EPSR-05***

6.0 5.3 4.4 5.1 5.4 +/-1.6 EPSR-06***

6.8 5.4 4.5 5.4 EPSJ-07***

4.6 3.5 3.8 3.9 3.7 +/-1.0 EPSJ-08***

3.8 3.8 2.8 3.6 EPSP-09***

6.0 7.6 7.2 7.1 7.4 +/-1.9 EPSP-10***

9.0 6.8 7.3 / 8.4 Mean 5.0 +/-3.1 *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 of4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Station 12/30/2014 3/31/2015 6/30/2015 9/30/2015 Average Annual TLD 3/31/2015 6/30/2015 9/30/2015 12/29/2015

+/-2 s.d. STA-01 5.0 4.1 4.1 3.6 4.2 +/-1.2 4.1 STA-02 2.4 2.3 2.1 2.4 2.3 +/-0.3 1.6 STA-03 2.9 2.6 0.9 2.5 2.2 +/-1.8 1.3 STA-04 2.4 2.0 2.2 2.5 2.3 +/-0.4 1.8 STA-05 4.2 2.5 3.1 2.4 3.1 +/-1.7 2.4 STA-05A 3.1 3.5 1.9 2.8 2.8 +/-1.4 3.0 STA-06 5.3 3.4 3.8 5.0 4.4 +/-1.8 3.5 STA-07 3.9 2.5 2.9 3.7 3.3 +/-1.3 2.4 STA-21 3.6 2.8 2.4 2.7 2.9 +/-1.0 2.2 STA-22 4.7 3.1 4.9 3.7 4.1 +/-1.7 4.2 STA-23 6.2 4.9 4.5 4.6 5.1 +/-1.6 3.9 STA-24* 4.1 2.6 2.0 3.4 3.0 +/-0.9 2.7 Mean -Indicator Locations 3.3 +/-1.1 2.8 +/-2.1 *Control 36 Period Ending 01/06/15 01/13/15 01/20/15 01/28/15 02/03/15 02/10/15 02/18/15 02/24/15 03/04/15 03/10/15 03/17/15 03/24/15 03/31/15 04/08/15 04/14/15 04/21/15 04/28/15 05/06/15 05/12/15 05/19/15 05/26/15 06/02/15 06/09/15 06/16/15 06/23/15 06/30/15 1.52E+01 1.70E+01 Station 01 I +/-2.75E+OO 2.06E+01 +/-2.91 E+OO 1.80E+01 Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3] Station Station 02 I 03 I +/-3.02E+OO 1.91 E+01 +/-2.92E+OO 1.49E+01 +/-2.96E+OO 1.63E+01 +/-2.88E+OO 1.89E+01 Station Station M I I +/-2.71 E+OO 1.95E+01 +/-2.95E+OO 1.88E+01 +/-3.01 E+OO 1.39E+01 +/-2.75E+OO 1.99E+01 Station 06 I +/-2.92E+OO 1.95E+01 +/-3.06E+OO 1.79E+01 Station page 1 of 4 07 I +/-2.96E+OO +/-2.96E+OO 1.44E+01 +/-2.81 E+OO 1.29E+01 +/-2.72E+OO 1.80E+01 +/-2.99E+OO 1.53E+01 +!-2.85E+OO 1.40E+01 +/-2.78E+OO 1.52E+01 +/-2.B4E+OO 1.77E+01 +/-2.97E+OO 1.30E+01 +/-2.34E+OO 9.55E+OO +/-2.14E+OO 1.00E+01 +/-2.17E+OO 1.02E+01 +/-2.18E+OO 7.93E+OO +/-

1.04E+01 +/-2.20E+OO 1.02E+01 +/-2.18E+OO 1.12E+01 +/-2.98E+OO 9.12E+OO +/-2.75E+OO 6.53E+OO +/-2.59E+OO 1.27E+01 +/-3.01E+OO 1.05E+01 +/-2.84E+OO 8.51E+OO +/-2.71E+OO 1.13E+01 +/-2.89E+OO 2.00E+01 +/-2.89E+OO 2.05E+01 +/-2.99E+OO 1.61 E+01 +/-2.75E+OO 1.22E+01 +/-2.51 E+OO 1.96E+01 +/-2.95E+OO 1.81 E+01 +/-2.86E+OO 2.16E+01 +/-3.04E+OO 1.71 E+01 +/-2.72E+OO 1.29E+01 +/-2.50E+OO 1.05E+01 +/-2.40E+OO 9.91 E+OO +/-2.34E+OO 1.26E+01 +/-2.48E+OO 1.42E+01 +/-2.58E+OO 1.46E+01 +/-2.59E+OO 2.59E+01 +/-3.71E+OO 3.47E+01 +/-4.09E+OO 2.62E+01 +/-3.73E+OO 2.71E+01 +/-3.76E+OO 1.45E+01 +/-3.14E+OO 2.69E+01 +/-3.76E+OO 2.70E+01 +/-3.76E+OO 7 .69E+OO +/-2.28E+OO 2.04E+01 +/-2.86E+OO 2.04E+01 +/-2.93E+OO 1.95E+01 +/-2.81 E+OO 1.91 E+01 +/-2.80E+OO 1.46E+01 +/-2.57E+OO 1.76E+01 +/-2.72E+OO 2.14E+01 +/-3.40E+OO 1.26E+01 +/-2.90E+OO 1.80E+01 +/-3.23E+OO 1.68E+01 +/-3.15E+OO 1.87E+01 +/-3.26E+OO 1.64E+01 +/-3.13E+OO 1.25E+01 +/-2.90E+OO 8.52E+OO +/-2.41 E+OO 5.24E+OO +/-2.21 E+OO 1.12E+01 +/-2.54E+OO 1.00E+01 +/-2.50E+OO 6.36E+OO +/-2.26E+OO 1.14E+01 +/-2.57E+OO 1.00E+01 +/-2.50E+OO 1.20E+01 +/-2.80E+OO 1.26E+01 +/-2.58E+OO 1.54E+01 +/-2.77E+OO 1.10E+01 +/-2.49E+OO 1.30E+01 +/-2.62E+OO 1.35E+01 +/-2.64E+OO 8.63E+OO +/-2.34E+OO 9.61E+OO +/-2.31E+OO 8.24E+OO +/-2.24E+OO 1.19E+01 +/-2.47E+OO 1.24E+01 +/-2.51E+OO 7.90E+OO +/-2.23E+OO 1.13E+01 +/-2.43E+OO 1.20E+01 +/-2.48E+OO 1.38E+01 +/-2.42E+OO 1.12E+01 +/-2.26E+OO 1.18E+01 +/-2.32E+OO 1.07E+01 +/-2.22E+OO 1.25E+01 +/-2.33E+OO 9.91 E+OO +/-2.18E+OO 1.08E+01 +/-2.23E+OO 1.03E+01 +/-2.78E+OO 1.03E+01 +/-2.78E+OO 8.72E+OO +/-2.68E+OO 8.72E+OO +/-2.68E+OO 9.83E+OO +/-2.75E+OO 1.01E+01 +/-2.77E+OO 8.12E+OO +/-2.64E+OO 8.55E+OO +/-2.20E+OO 6.93E+OO +/-2.09E+OO 1.14E+01 +/-2.39E+OO 9.44E+OO +/-2.26E+OO 8.41E+OO +/-2.19E+OO 7.96E+OO +/-2.16E+OO 8.63E+OO +/-2.20E+OO 9.0BE+OO +/-2.24E+OO 1.13E+01 +/-2.38E+OO 8.33E+OO +/-2.19E+OO 9.08E+OO +/-2.24E+OO 9.08E+OO +/-2.24E+OO 9.66E+OO +/-2.2BE+OO 1.00E+01 +/-2.30E+OO 1.13E+01 +/-2.33E+OO 1.09E+01 +/-2.30E+OO 1.14E+01 +/-2.33E+OO 1.06E+01 +/-2.29E+OO 7.97E+OO +/-2.12E+OO 1.10E+01 +/-* 2.31 E+OO 1.02E+01 +/-2.26E+OO 1.68E+01 +/-2.86E+01 1.37E+01 +/-2.84E+OO 9.98E+OO +/-2.60E+OO 1.33E+01 +/-2.81 E+OO 1.53E+01 +/-2.93E+OO 1.34E+01 +/-2.82E+OO 1.14E+01 +/-2.70E+OO 1.97E+01 +/-3.04E+OO 1.41 E+01 +/-2.72E+OO 1.53E+01 +/-2.79E+OO 1.17E+01 +/-2.58E+OO 1.40E+01 +/-2.71 E+OO 1.19E+01 +/-2.60E+OO 1.43E+01 +/-2.73E+OO 1.32E+01 +/-2.65E+OO 1.13E+01 +/-2.49E+OO 1.31 E+01 +/-2.59E+OO 1.26E+01 +/-2.58E+OO 1.36E+01 +/-2.62E+OO 1.08E+01 +/-2.46E+OO 1.40E+01 +/-2.65E+OO 1.43E+01 +/-2.71 E+OO 1.13E+01 +/-2.59E+OO 1.37E+01 +/-2.74E+OO 1.23E+01 +/-2.64E+OO 1.15E+01 +/-2.60E+OO 1.05E+01 +/-2.54E+OO B.37E+OO +/-2.41 E+OO 7.71 E+OO +/-2.23E+OO 4.76E+OO +/-2.03E+OO 3.06E+OO +/-1.90E+OO 5.52E+OO +/-2.09E+OO 4.99E+OO +/-2.05E+OO < 3.04E+OO 5.51 E+OO +/-2.08E+OO 1.70E+01 +/-2.81 E+OO 1.11 E+01 +/-2.48E+OO 1.45E+01 +/-2.67E+OO 1.36E+01 +/-2.62E+OO 1.14E+01 +/-2.49E+OO 1.33E+01 +/-2.60E+OO 1.33E+01 +/-2.60E+OO 1.21 E+01 +/-2.44E+OO 1.26E+01 +/-2.47E+OO 1.44E+01 +/-2.58E+OO 9.97E+OO +/-2.31 E+OO 1.00E+01 +/-2.31 E+OO 1.41 E+01 +/-2.56E+OO 8.18E+OO +/-2.19E+OO 1.10E+01 +/-2.68E+OO 5.56E+OO +/-2.38E+OO 8.78E+OO +/-2.57E+OO 1.04E+01 +/-2.66E+OO 1.09E+01 +/-2.69E+OO 1.20E+01 +/-2.75E+OO 3.81 E+OO +/-2.57E+OO 37 Period Ending 01/06/15 01/13/15 01/20/15 01/28/15 02/03/15 02/10/15 02/18/15 02/24/15 03/04/15 03/10/15 03/17/15 03/24/15 03/31/15 04/08/15 04/14/15 04/21/15 04/28/15 05/06/15 05/12/15 05/19/15 05/26/15 06/02/15 06/09/15 06/16/15 06/23/15 06/30/15 Station 21 I 1.04E+01 +/-2.45E+OO 1.88E+01 Station 22 +/-Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3] 2.91 E+OO 1.39E+01 Station 23 +/-2.67E+OO 2.02E+01 Station 24** +/-Station Station 01A I 05A I 2.98E+OO 2.03E+01 +/-3.02E+OO 1.66E+01 +/-2.80E+OO 1.96E+01 +/-3.05E+OO 1.74E+01 +/-2.93E+OO 1.54E+01 +/-2.83E+OO 1.65E+01 +/-2.89E+OO 1.37E+01 +/-2.73E+OO 1.86E+01 +/-2.99E+OO 1.39E+01 +/-2.78E+OO 1.01 E+01 +/-2.57E+OO 1.81 E+01 +/-3.00E+OO 1.42E+01 +/-2.79E+OO 1.64E+01 +/-2.91 E+OO 1.62E+01 +/-2.89E+OO 6.12E+OO +/-1.92E+OO 1.08E+01 +/-2.23E+OO 1.30E+01 +/-2.34E+OO 1.23E+01 +/-2.30E+OO 1.02E+01 +/-2.18E+OO 1.32E+01 +/-3.02E+OO 8.58E+OO +/-2.71 E+OO 1.32E+01 +/-3.00E+OO 1.75E+01 +/-3.25E+OO 1.55E+01 +/-3.22E+OO 9.23E+OO +/-2.78E+OO 1.45E+01 +/-2.66E+OO 1.89E+01 +/-2.90E+OO 2.04E+01 +/-2.98E+OO 2.60E+01 +/-3.25E+OO 2.36E+01 +/-3.07E+OO 1.64E+01 +/-2.76E+OO 1.51 E+01 +/-2.61 E+OO 1.63E+01 +/-2.67E+OO 1.44E+01 +/-2.59E+OO 1.77E+01 +/-2.74E+OO 1.32E+01 +/-2.52E+OO 1.24E+01 +/-2.48E+OO 2.65E+01 +/-3.74E+OO 2.67E+01 +/-3.75E+OO 3.09E+01 +/-3.94E+OO 2.31E+01 +/-3.58E+OO 2.95E+01 +/-3.88E+OO 2.72E+01 +/-3.77E+OO 2.66E+01 +/-3.14E+OO 2.41 E+01 +/-3.03E+OO 2.11 E+01 +/-2.89E+OO 2.55E+01 +/-3.09E+OO 2.31 E+01 +/-2.98E+OO 1.79E+01 +/-2.74E+OO 2.02E+01 +/-3.35E+OO 1.65E+01 +/-3.15E+OO 1.61 E+01 +/-3.1 OE+OO 1.97E+01 +/-3.33E+OO 1.86E+01 +/-3.24E+OO 1.47E+01 +/-3.03E+OO 1.10E+01 +/-2.50E+OO 9.72E+OO +/-2.43E+OO 1.11 E+01 +/-2.58E+OO 1.36E+01 +/-2.69E+OO 1.18E+01 +/-2.60E+OO 1.06E+01 +/-2.51 E+OO 1.59E+01 +/-3.07E+OO 9.26E+OO +/-2.44E+OO 1.42E+01 +/-2.66E+OO 1.47E+01 +/-2.73E+OO 1.21 E+01 +/-2.57E+OO 7.97E+OO +/-2.32E+OO 9.58E+OO +/-2.33E+OO 9.75E+OO +/-2.34E+OO 1.01 E+01 +/-2.36E+OO 1.43E+01 +/-2.61 E+OO 1.57E+01 +/-2.68E+OO 1.1 OE+01 +/-2.42E+OO 9.84E+OO +/-2.18E+OO 3.06E+OO +/-1.72E+OO 8.88E+OO +/-2.12E+OO 1.16E+01 +/-2.28E+OO 9.52E+OO +/-2.17E+OO 1.25E+01.

+/-2.33E+OO 8.55E+OO +/-2.67E+OO 1.02E+01 +/-2.77E+OO 1.22E+01 +/-2.90E+OO 1.00E+01 +/-2.76E+OO 1.20E+01 +/-2.88E+OO 1.02E+01 +/-2.77E+OO 9.84E+OO +/-2.29E+OO 1.14E+01 +/-2.39E+OO 1.00E+01 +/-2.29E+OO 1.04E+01 +/-2.33E+OO 1.09E+01 +/-2.41 E+OO 9.51 E+OO +/-2.26E+OO 1.05E+01 +/-2.33E+OO 9.65E+OO +/-2.27E+OO 1.02E+01 +/-2.31 E+OO 1.12E+01 +/-2.37E+OO 1.17E+01 +/-2.41 E+OO 9.00E+OO +/-2.23E+OO 1.15E+01 +/-2.34E+OO 9.65E+OO +/-2.23E+OO 1.23E+01 +/-2.39E+OO 1.08E+01 +/-2.30E+OO 1.16E+01 +/-2.35E+OO 1.06E+01 +/-2.28E+OO 1.29E+01 +/-2.79E+OO 1.76E+01 +/-3.06E+OO 1.34E+01 +/-2.81 E+OO 1.64E+01 +/-2.99E+OO 1.64E+01 +/-3.16E+OO 1.34E+01 +/-2.82E+OO 1.52E+01 +/-2.78E+OO 1.35E+01 +/-2.69E+OO 1.48E+01 +/-2.76E+OO 1.48E+01 +/-2.76E+OO 1.75E+01 +/-2.98E+OO 1.55E+01 +/-2.79E+OO 1.03E+01 +/-2.42E+OO 1.24E+01 +/-2.55E+OO 1.33E+01 +/-2.60E+OO 1.11E+01 . +/-2.46E+OO 1.72E+01 +/-2.94E+OO 1.23E+01 +/-2.55E+OO 1.15E+01 +/-2.61 E+OO 1.54E+01 +/-2.84E+OO 1.06E+01 +/-2.56E+OO 1.25E+01 +/-2.68E+OO 1.54E+01 +/-2.85E+OO 7.44E+OO +/-2.35E+OO 6.63E+OO +/-2.17E+OO 5.14E+OO +/-2.06E+OO 7.34E+OO +/-2.20E+OO 7.07E+OO +/-2.19E+OO 8.38E+OO +/-2.27E+OO 5.14E+OO +/-2.06E+OO 1.36E+01 +/-2.62E+OO 1.43E+01 +/-2.66E+OO 1.52E+01 +/-2.71 E+OO 1.42E+01 +/-2.65E+OO 1.70E+01 +/-2.81 E+OO 1.17E+01 +/-2.51 E+OO 1.21 E+01 +/-2.44E+OO 1.49E+01 +/-2.60E+OO 1.61 E+01 +/-2.68E+OO 1.32E+01 +/-2.50E+OO 1.54E+01 +/-2.64E+OO 1.18E+01 +/-2.42E+OO 8.87E+OO +/-2.58E+OO 1.10E+01 +/-2.70E+OO 9.48E+OO +/-2.60E+OO 9.83E+OO +/-2.63E+OO 9.26E+OO +/-2.59E+OO 8.61E+OO +/-2.56E+OO

Sample not obtained due to sampler not operating.

- Control Station 38 page 2of4 Period Ending 07/08/15 07/14/15 07/21/15 07/28/15 08/05/15 08/11/15 08/18/15 08/26/15 09/01/15 09/08/15 09/16/15 09/22/15 09/29/15 10/06/15 10/14/15 10/21/15 10/27/15 11/04/15 11/12115 11/18/15 11/24/15 12102/15 12/08/15 12115/15 12122115 12/29/15 MEAN Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3] Station Station Station I I I 1.55E+01 +/-2.45E+OO 1.12E+01 +/-2.21 E+OO 1.44E+01 +/-2.38E+OO 1.43E+01 1.46E+01 +/-3.08E+OO 1.12E+01 +/-2.90E+OO 1.04E+01 +/-2.86E+OO 1.35E+01 Station Station 04 I 05 I +/-2.38E+OO 1.26E+01 +/-2.29E+OO 1.94E+01 +/-3.04E+OO 1.20E+01 +/-2.96E+OO 1.37E+01 Station 06 I +/-2.65E+OO 1.43E+01 +/-3.05E+OO 1.39E+01 Station page 3 of4 07 I +/-2.39E+OO +/-3.06E+OO 1.47E+01 +/-2.56E+OO 1.32E+01 +/-2.46E+OO 1.20E+01 +/-2.39E+OO 1.70E+01 +/-2.67E+OO 1.42E+01 +/-2.52E+OO 1.64E+01 +/-2.65E+OO 1.50E+01 +/-2.56E+OO 1.25E+01 +/-2.49E+OO 1.06E+01 +/-2.38E+OO 1.45E+01 +/-2.60E+OO 1.17E+01 +/-2.45E+OO 1.38E+01 +/-2.57E+OO 1.59E+01 +/-2.69E+OO 1.26E+01 +/-2.50E+OO 1.69E+01 +/-2.54E+OO 1.77E+01 +/-2.58E+OO 1.71E+01 +/-2.55E+OO 1.69E+01 +/-2.54E+OO 2.00E+01 +/-2.69E+OO 1.58E+01 +/-2.48E+OO 2.07E+01 +/-2.72E+OO 1.50E+01 +/-2.99E+OO 1.01E+01 +/-2.70E+OO 1.26E+01 +/-2.85E+OO 1.31E+01 +/-2.89E+OO 1.11 E+01 +/-2.76E+OO 1.40E+01 +/-2.94E+OO 1.43E+01 +/-2.96E+OO 1.34E+01 +/-2.62E+OO 1.61E+01 +/-2.76E+OO 1.54E+01 +/-2.75E+DD 1.33E+01 +/-2.61E+OO 1.34E+01 +/-2.62E+OO 1.59E+01 +/-2.75E+OO 1.57E+01 +/-2.74E+OO 1.46E+01 +/-2.46E+OO 1.53E+01 +/-2.50E+OO 1.13E+01 +/-2.28E+OO 1.79E+01 +/-2.63E+OO 1.35E+01 +/-2.40E+OO 1.69E+01 +/-2.58E+OO 1.70E+01 +/-2.58E+OO 1.68E+01 +/-3.03E+OO 1.47E+01 +/-2.90E+OO 2.1 OE+01 +/-3.26E+OO 1.81 E+01 +/-3.1 OE+OO 1.62E+01 +/" 2.99E+OO 2.42E+01 +/-3.42E+OO 1.63E+01 +/-3.00E+OO 2.71E+01 +/-3.22E+OO 2.30E+01 +/-3.03E+OO 2.71E+01 +/-3.23E+OO 2.32E+01 +/-3.04E+OO 2.48E+01 +/-3.12E+OO 2.75E+01 +/-3.24E+OO 2.79E+01 +/-3.26E+OD 1.58E+01 +/-2.45E+OO 1.35E+01 +/-2.32E+OO 1.06E+01 +/-2.15E+OO 1.24E+01 +/-2.26E+OO 1.31E+01 +/-2.30E+OO 1.70E+01 +/-2.52E+OO 1.36E+01 +/-2.33E+OO 2.03E+01 +/-3.51 E+DO 2.13E+01 +/-3.56E+OO 2.12E+01 +/-3.55E+DD 1.95E+01 +/-3.47E+OO 1.87E+01 +/-3.42E+OO 1.73E+01 +/-3.67E+OO 2.30E+01 +/-3.64E+OO 9.63E+OO +/-2.23E+OO 9.85E+OO +/-2.26E+OO 1.05E+01 +/-2.30E+OO 1.23E+01 +/-2.42E+OO 1.14E+01 +/-2.36E+OO 1.23E+01 +/-2.41E+OO 1.09E+01 +/-2.32E+OO 3.79E+OD +/-2.02E+OO < 2.71E+OO 3.18E+OO +/-1.90E+OO 4.63E+OO +/-2.03E+OD 3.64E+OO +/-1.94E+OO 5.57E+OO +/-2.D9E+OO 3.05E+OO +/-1.90E+OO 1.22E+01 +/-2.43E+OO 1.93E+01 +/-2.83E+OD 1.74E+01 +/-2.75E+OO 1.88E+01 +/-2.79E+OO 1.47E+01 +/-2.61 E+OO 2.02E+01 +/-2.87E+OO 1.75E+01 +/-2.75E+OO 1.73E+01 +/-2.89E+OO 1.56E+01 +/-2.BOE+OO 1.69E+01 +/-2.87E+OO 1.73E+01 +/-2.90E+OO 1.48E+01 +/-2.75E+OO 2.13E+01 +/-3.D9E+OO 2.14E+01 +/-3.10E+OO 2.06E+01 +/-3.55E+OO 2.08E+D1 +/-3.56E+OO 2.11E+01 +/-3.55E+OO 2.69E+01 +/-3.84E+OO .2.49E+01

+/-3.75E+OO 1.57E+01 +/-3.27E+OO 2.28E+01 +/-3.65E+OO 1.26E+01 +/-2.27E+OO 1.93E+01 +/-2.65E+OO 1.45E+01 +/-2.44E+OO 2.04E+01 +/-2.67E+OO 1.81E+01 +/-2.56E+OO 1.53E+01 +/-2.42E+OO 1.62E+01 +/-2.46E+OO 8.74E+OO +/-2.16E+OO 1.13E+01 +/-2.22E+OO 1.18E+01 +/-2.27E+OO 9.23E+OD +/-2.16E+OO 9.46E+OO +/-2.15E+OO 1.D3E+01 +/-2.20E+DO 1.04E+01 +/-2.21E+OO 1.08E+01 +/-2.71E+OO 1.74E+01 +/-3.19E+OO 1.71E+D1 +/-3.20E+OO 1.83E+D1 +/-3.21E+OO 1.82E+01 +/-3.23E+DD 1.98E+01 +/-3.30E+DO 1.96E+01 +/-3.29E+OO 1.24E+01 +/-2.99E+OO 1.31 E+01 +/-3.03E+OD 1.20E+01 +/-2.94E+OO 1.19E+01 +/-2.94E+OO 1.36E+01 +/-3.04E+OO 1.29E+01 +/-3.01 E+OO 1.21 E+01 +/-2.97E+OO 1.25E+01 +/-2.29E+OO 1.32E+01 +/-2.32E+OO 1.30E+01 +/-2.32E+OD 1.24E+01 2.28E+OO 1.30E+01 +/-2.31E+OO 1.41E+01 +/-2.37E+OO 1.39E+01 +/-2.36E+DD 2.41E+01 +/-3.48E+OO 2.23E+01 +/-3.39E+OO 1.93E+01 +/-3.24E+OO 2.77E+01 +/-3.66E+OO 2.82E+01 +/-3.68E+OO 2.15E+01 +/-3.35E+OO 2.43E+01 +/-3.49E+OO 2.58E+01 +/-3.21 E+OO 2.55E+01 +/-3.19E+OO 1.94E+01 +/-2.90E+OO 2.71E+01 +/-3.27E+OO 2.71 E+01 +/-3.27E+OO 2.36E+01 +/-3.11 E+OO 2.53E+01 +/-3.18E+OO 1.13E+01 +/-2.57E+OO 8.06E+OO +/-2.33E+OO 1.31E+01 +/-2.61E+OO 1.08E+01 +/-2.51E+OO 1.19E+01 +/-2.56E+OO 1.02E+01 +/-2.43E+OO 9.BOE+OO +/-2.43E+OO 6.56E+OO +/-2.03E+OO < 2.57E+OO 6.63E+OO +/-2.11 E+OO 4.48E+OO +/-1.93E+OO 6.54E+OO +/-2.1 OE+OO 5.02E+OO +/-1.98E+OO 1.416E+01

+/-3.19E+OO 1.41 E+01 +/-2.68E+OO 1.40E+01 +/-2.67E+OO 1.43E+01 +/-2.68E+OO 1.38E+01 +/-2.66E+OO 1.50E+01 +/-2.7 4E+OO 1.43E+01 +/-2.69E+DO

Sample not obtained due to sampler not operating 39 Period Ending 07/08/15 07/14/15 07/21/15 1.03E+01 9.89E+OO Station Station 21 I 22 I Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pCi/m 3] Station Station Station 23 I 24** I 01A I +/-2.15E+OO 1.29E+01 +/-2.30E+OO 1.09E+01 +/-2.83E+OO 1.22E+01 +/-2.97E+OO 1.32E+01 +/-2.19E+OO 1.36E+01 +/-2.34E+OO 1.81E+01 +/-2.59E+OO 1.42E+01 +/-3.01 E+OO 1.60E+01 +/-3.18E+OO 8.68E+OO +/-2.73E+OO 1.07E+01 Station 05A I +/-2.38E+OO +/-2.88E+OO 1.50E+or +/-2.56E+OO 1.30E+01 +/-2.45Et00 1.19E+01 +/-2.39E+OO 1.40E+01 +/-2.51 E+OO 1.91 E+01 +/-2.BOE+OO 1.23E+01 +/-2.41 E+OO 07/28/15 1.25E+01 +/-2.48E+OO 1.33E+01 +/-2.53E+OO 1.45E+01 +/-2.61 E+OO 1.53E+01 +/-2.64E+OO 1.59E+01 +/-2.69E+OO 1.26E+01 +/-2.50E+OO 08/05/15 1.91 E+01 +/-2.65E+OO 1.60E+01 +/-2.49E+OO 1.68E+01 +/-2.53E+OO 1.82E+01 +/-2.60E+OO 2.25E+01 +/-2.81 E+OO 1.19E+01 +/-2.26E+OO 08/11/15 8.95E+OO +/-2.62E+OO 9.46E+OO +/-2.65E+OO 1.33E+01 +/-2.89E+OO 1.43E+01 +/-2.95E+OO 1.30E+01 +/-2.87E+OO 1.10E+01 +/-2.76E+OO 08/18/15 . 1.50E+01 +/-2.71E+OO 1.08E+01 +/-2.47E+OO 1.82E+01 +/-2.88E+OO 1.76E+01 +/-2.85E+OO 1.58E+01 +/-2.75E+OO 1.62E+01 +/-2.77E+OO 08/26/15 1.61E+01 +/-2.54E+OO 1.59E+01 +/-2.53E+OO 1.58E+01 +/-2.52E+OO 1.35E+01 +/-2.40E+OO 1.96E+01 +/-2.71 E+OO 1.15E+01 +/-2.29E+OO 09/01/15 09/08/15 09/16/15 09/22/15 09/29/15 10/06/15 10/14/15 10/21/15 10/27/15 11/04/15 11/12/15 11/18/15 11/24/15 12/02/15 12/08/15 12/15/15 12/22/15 12/29/15 MEAN 1.83E+01 +/-3.11 E+OO 1.63E+01 +/-3.00E+OO 2.09E+01 +/-3.25E+OO 2.22E+01 +/-3.32E+OO 2.04E+01 +/-3.22E+OO 1.48E+01 +/-2.91 E+OO 2.87E+01 +/-3.32E+OO 2.42E+01 +/-3.11 E+OO 2.38E+01 +/-3.07E+OO 2.64E+01 +/-3.20E+OO 3.17E+01 +/-3.42E+OO 1.78E+01 +/-2.77E+OO 1.50E+01 +/-2.40E+OO 1.13E+01 +/-2.18E+OO 1.46E+01 +/-2.39E+OO 1.53E+01 +/-2.42E+OO 1.76E+01 +/-2.55E+OO 9.86E+OO +/-2.11 E+OO 2.01E+01 +/-3.50E+OO 1.77E+01 +/-3.37E+OO '2.21E+01

+/-3.60E+OO 1.91E+01 +/-3.45E+OO 2.31E+01 +/-3.65E+OO 1.83E+01 +/-3.40E+OO 1.16E+01 +/-2.38E+OO 1.25E+01 +/-2.43E+OO 8.58E+OO +/-2.17E+OO 1.40E+01 +/-2.52E+OO 1.48E+01 +/-2.55E+OO 1.02E+01 +/-2.29E+OO 3.33E+OO +/-1.91 E+OO 3.11 E+OO +/-1.90E+OO < 2.71 E+OO 4.51 E+OO +/-2.00E+OO 4.47E+OO +/-2.07E+OO < 2.70E+OO 1.72E+01 +/-2.74E+OO 1.40E+01 +/-2.62E+OO 1.65E+01 +/-2.69E+OO 2.03E+01 +/-2.88E+OO 2.23E+01 +/-2.91E+OO 2.02E+01 +/-2.88E+OO 1.48E+01 +/-2.76E+OO 1.83E+01 +/-2.96E+OO 1.79E+01 +/-2.92E+OO.

1.73E+01 +/-2.89E+OO 1.43E+01 +/-2.73E+OO 1.22E+01 +/-2.61E+OO 1.98E+01 +/-3.48E+OO 1.94E+01 +/-3.46E+OO 1.79E+01 +/-3.40E+OO 2.18E+01 +/-3.59E+OO 1.90E+01 +/-3.46E+OO 2.75E+01 +/-3.87E+OO 1.80E+01 +/-2.56E+OO 1.60E+01 +/-2.46E+OO 1.74E+01 +/-2.53E+OO 1.86E+01 +/-2.59E+OO 1.97E+01 +/-2.64E+OO 2.32E+01 +/-2.81E+OO 1.15E+01 +/-2.27E+OO 9.69E+OO +/-2.16E+OO 9.90E+OO +/-2.17E+OO 1.17E+01 +/-2.28E+OO 1.06E+01 +/-2.27E+OO 1.01E+01 +/-2.19E+OO 1.94E+01 +/-3.30E+OO 1.55E+01 +/-3.09E+OO 1.63E+01 +/-3.13E+OO 1.90E+01 +/-3.28E+OO 1.65E+01 +/-3.04E+OO 2.00E+01 +/-3.32E+OO 1.33E+01 +/-3.01E+OO 8.94E+OO +/-2.75E+OO 1.23E+01 +/-2.98E+OO 1.14E+01 +/-2.90E+OO 1.17E+01 +/-3.03E+OO 1.39E+01 +/-3.06E+OO 9.76E+OO +/-2.13E+OO 8.00E+OO +/-2.02E+OO 1.45E+01 +/-2.40E+OO 1.47E+01 +/-2.41E+OO 1.52E+01 +/-2.44E+OO 1.37E+01 +/-2.35E+OO 1.80E+01 +/-3.17E+OO 1.39E+01 +/-2.94E+OO 2.51E+01 +/-3.53E+OO 2.13E+01 +/-3.35E+OO 2.83E+01 +/-3.68E+OO 2.64E+01 +/-3.60E+OO 2.12E+01 +/-2.99E+OO 2.06E+01 +/-2.96E+OO 2.57E+01 +/-3.20E+OO 2.83E+01 +/-3.33E+OO 3.12E+01 +/-3.45E+OO 2.90E+01 +/-3.35E+OO 8.66E+OO +/-2.35E+OO 9.1 OE+OO +/-2.38E+OO 1.1 OE+01 +/-2.50E+OO 8.58E+OO +/-2.35E+OO 1.28E+01 +/-2.66E+OO 1.08E+01 +/-2.49E+OO 5.42E+OO +/-2.02E+OO 5.95E+OO +/-2.06E+OO 4.40E+OO +/-1.93E+OO 5.26E+OO +/-2.01E+OO 7.03E+OO +/-2.08E+OO 6.31E+OO +/-2.08E+OO 1.39E+01 +/-2.67E+OO 1.33E+01 +/-2.63E+OO 1.49E+01 +/-2.72E+OO 1.56E+01 +/-2.76E+OO 1.65E+01 +/-2.82E+OO 1.39E+01 +/-2.67E+OO Mean -All Indicator Locations 1.44E+o1 +1-2.73E+oo ** Control Station 40 page 4 of4 Period Ending 01/06/15 01/13/15 01/20/15 01/28/15 02/03/15 02/10/15 02/18/15 02/24/15 03/04/15 03/10/15 03/17/15 03/24/15 03/31/15 04/08/15 04/14/15 04/21/15 04/28/15 05/06/15 05/12/15 05/19/15 05/26/15 06/02/15 06/09/15 06/16/15 06/23/15 06/30/15 Station 01 I < 1.33E+01 < 2.04E+01 < 1.23E+01 < 2.05E+01 < 2.36E+01 < 5.72E+01 < 1.93E+01 < 9.96E+OO <

1.59E+01 < 1.58E+01 < 1.75E+01 < 1.64E+01 < 1.18E+01 < 2.28E+01 < 2.98E+01 < 2.47E+01 < 4.03E+01 < 4.89E+01 < 3.16E+01 < 4.52E+01 < 4.28E+01 < 4.57E+01 < 3.53E+01 < 5.64E+01 < 3.67E+01 < 2.88E+01 Station 02 I < 2.97E+01 < 5.28E+01 < 3.17E+01 < 4.62E+01 < 5.82E+01 < 5.95E+01 < 3.49E+01 < 2.56E+01 < 3.83E+01 < 4.09E+01 < 4.52E+01 < 3.65E+01 < 3.06E+01 < 5.82E+01 < 2.98E+01 < 5.85E+01 < 4.03E+01 < 4.89E+01 < 3.20E+01 < 4.47E+01 < 4.15E+01 < 4.70E+01 < 3.54E+01 < 5.63E+01 < 3.66E+01 < 2.90E+01 Table 3-4 Airborne Iodine 1-131 [10-3 pCi/m 3] Station Station 03 I < 2.94E+01 <

5.28E+01 < 3.18E+01 < 4.61E+01 < 5.85E+01 < 5.93E+01 < 3.57E+01 < 2.57E+01 < 3.97E+01 < 4.10E+01 < 4.44E+01 < 3.72E+01 < 3.06E+01 < 5.93E+01 < 2.98E+01 < 5.87E+01 < 4.02E+01 < 4.88E+01 < 3.20E+01 < 4.48E+01 < 4.14E+01 < 2.60E+01 < 3.55E+01 < 5.62E+01 < 3.66E+01 < 2.90E+01 41 04 I < 2.95E+01 < 5.28E+01 < 3.17E+01 < 4.62E+01 < 5.93E+01 < 5.86E+01 < 3.50E+01 < 2.56E+01 < 3.83E+01 < 4.09E+01 < 4.51E+01 < 3.67E+01 < 3.07E+01 < 5.80E+01 < 2.98E+01 < 5.85E+01 < 4.03E+01 < 4.89E+01 < 3.33E+01 < 3.34E+01 < 4.20E+01 < 4.66E+01 < 3.55E+o1 < 5.63E+01 < 3.66E+01 < 2.90E+01 Station 05 I < 2.95E+01 < 5.82E+01 < 3.17E+01 < 4.62E+01 < 5.82E+01 < 6.24E+01 < 3.50E+01 < 2.56E+01 < 3.83E+01 < 4.09E+01 < 4.48E+01 < 3.69E+01 < 3.07E+01 < 5.80E+01 < 3.45E+01 < 5.85E+01 < 4.70E+01 < 4.07E+01 < 3.33E+01 < 3.34E+01 < 5.58E+01 < 4.70E+01 < 3.29E+01 < 4.32E+01 < 2.02E+01 < 2.67E+01 Station oa I < 1.26E+01 < 5.10E+01 < 2.96E+01 < 1.25E+01 < 6.55E+01 < 6.24E+01 < 4.83E+01 < 4.44E+01 < 4.24E+01 < 4.70E+01 < 4.07E+01 < 3.48E+01 < 2.21E+01 < 6.71E+01 < 3.45E+01 < 5.36E+01 < 4.70E+01 < 4.07E+01 < 3.33E+01 < 3.35E+01 < 5.58E+01 < 5.91E+01 < 3.69E+01 < 4.32E+01 < 4.12E+01 < 2.67E+01 Station page 1 of 4 01 I < 3.58E+01 < 5.10E+01 < 1.24E+01 < 3.55E+01 < 6.55E+01 < 6.24E+01 < 4.81E+01 < 4.44E+01 < 4.24E+01 < 4.70E+01 < 4.09E+01 < 3.47E+01 < 2.21E+01 < 6.72E+01 < 3.45E+01 < 5.36E+01 < 4.70E+01 < 4.07E+01 < 2.29E+01 < 3.43E+01 < 5.58E+01 < 5.91E+01 < 3.29E+01 < 4.32E+01 < 4.12E+01 < 3.09E+01 Period Ending 01/06/15 01/13/15 01/20/15 01/28/15 02103/15 02110/15 02118/15 02124/15 03/04/15 03/10/15 03/17/15 03/24/15 03/31/15 04/08/15 04/14/15 04/21/15 04/28/15 05/06/15 . 05/12115 05/19/15 05/26/15 06/02/15 06/09/15 06/16/15 06/23/15 06/30/15 Station 21 < 3.54E+01 < 5.10E+01 < 2.97E+01. . < 3.55E+01 < 6.59E+01 < 6.22E+01 < 4.79E+01 < 4.45E+01 < 1.77E+01 < 4.71E+01 < 3.97E+01 < 4.02E+01 < 2.22E+01 < 6.71E+01 < 3.45E+01 < 5.38E+01 < 4.69E+01 < 3.71E+01 < 2.29E+01 < 3.43E+01 < 5.55E+01 < 5.94E+01 < 3.29E+01 <. 5.60E+01 < 4.12E+01 < 2.68E+01 Station 22 < 3.54E+01 < 5.10E+01 < 2.97E+01 < 3.57E+01 < 6.53E+01 < 6.98E+01 < 4.79E+01 < 4.45E+01 < 4.23E+01 < 4.71E+01 < 3.97E+01 < 3.57E+01 < 2.22E+01 < 6.71E+01 < 1.63E+01 < 5.38E+01 < 3.48E+01 < 3.71E+01 < 2.29E+01 < 3.43E+01 < 5.84E+01 < 5.94E+01 < 3.74E+01 < 5.60E+01 < 4.12E+01 < 3.02E+01

Sample not obtained due to sampler not operating.

Table 3-4 Airborne Iodine 1-131 [10-3 pCi/m 3] Station 23 < 3.59E+01 < 6.05E+01 < 2.97E+01 < 3.55E+01 < 5.65E+01 < 6.98E+01 < 3.77E+01 < 4.41E+01 < 4.24E+01 < 5.03E+01 < 4.33E+01 < 2.84E+01 < 2.32E+01 < 5.44E+01 < 3.00E+01 < 5.26E+01 < 1.46E+01 < 3.71E+01 < 2.28E+01 < 5.16E+01 < 5.85E+01 < 2.09E+01 < 3.72E+01 < 5.62E+01 < 3.43E+01 < 3.00E+01 ** Control Station 42 Station 24** < 3.50E+01 < 6.07E+01 < 3.61E+01 < 5.51E+01 < 5.67E+01 < 6.99E+01 < 3.74E+01 < 4.41E+01 < 4.99E+01 < 5.07E+01 < 4.27E+01 < 2.90E+01 < 2.33E+01 < 5.44E+01 < 3.00E+01 < 5.28E+01 < .3.48E+01

< 2.69E+01 < 6.49E+01 < 5.16E+01 < 5.82E+01 < 6.74E+01 < 3.73E+01 < 6.16E+01 < 3.42E+01 < 3.01E+01 Station 01A < 3.55E+01 < 6.05E+01 < 3.61E+01 < 5.88E+01 < 6.75E+01 < 3.77E+01 < 4.41 E+01 < 5.00E+01 < 5.03E+01 < 4.28E+01 < 2.87E+01 < 2.31E+01 < 5.48E+01 < 3.00E+01 < 5.45E+01 < 3.48E+01 < 2.70E+01 < 6.82E+01 < 5.31E+01 < 2.42E+01 < 6.78E+01 < 5.03E+01 < 6.18E+01 < 3.43E+01 < 1.33E+01 Station 05A < 3.51E+01 < 6.07E+01 < 3.60E+01 < 5.52E+01 < 5.72E+01 < 3.59E+01 < 3.76E+01 < 4.40E+01 < 5.00E+01 < 5.06E+01 < 4.24E+01 < 2.89E+01 < 2.33E+01 < 5.43E+01 < 3.00E+01 < 5.26E+01 < 3.48E+01 < 2.70E+01 < 6.49E+01 < 5.14E+01 < 5.87E+01 < 6.69E+01 < 5.06E+01 < 6.17E+01 < 3.42E+01 < 3.01E+01 page 2 of4 Period Ending 07/08/15 07/14/15 07/21/15 07/28/15 08/05/15 08/11/15 08/18/15 08/26/15 09/01/15 09/08/15 09/16/15 09/22/15 09/29/15 10/06/15 10/14/15 10/21/15 10/27/15 11/04/15 11/12/15 11/18/15 11/24/15 12/02/15 12108/15 12115/15 12122115 12129/15 Mean Station 01 < 6.66E+OO < 3.94E+01 < 2.81E+01 < 2.67E+01 < 1.00E+01 < 4.61E+01 < 2.50E+01 < 2.65E+01 < 4.70E+01 < 1.56E+01 < 2.46E+01 < 8.67E+OO < 3.42E+01 < 5.39E+01 < 1.81E+01 < 3.23E+01 < 1.57E+01 < 2.47E+01 < 4.34E+01 < 2.74E+01 < 2.59E+01 < 4.96E+01 < 2.18E+01 < 1.45E+01 < 1.99E+01 < 1.66E+01 +/-1.73E+01 Station 02 < 1.71E+01 < 3.97E+01 < 2.80E+01 < 2.67E+01 < 2.58E+01 < 4.64E+01 < 2.50E+01 < 6.28E+01 < 4.70E+01 < 3.73E+01 < 2.46E+01 < 2.23E+01 < 3.44E+01 < 5.19E+01 < 1.86E+01 < 1.25E+01 < 4.02E+01 < 6.01E+01 < 1.72E+01 < 5.57E+01 < 2.59E+01 < 4.96E+01 < 2.19E+01 < 3.46E+01 < 3.51E+01 < 4.44E+01 +/-4.44E+01

Sample not obtained due to sampler not operating.

Table 3-4 Airborne Iodine 1-131 [10-3 pCi/m 3] Station 03 < 1.70E+01 < 3.98E+01 < 2.80E+01 < 2.67E+01 < 2.58E+01 < 4.62E+01 < 2.49E+01 < 6.28E+01 < 4.70E+01 < 3.74E+01 < 2.46E+01 < 2.23E+01 < 3.45E+01 < 5.17E+01 < 1.87E+01 < 3.23E+01 < 3.99E+01 < 6.15E+01 < 4.17E+01 < 5.62E+01 < 2.56E+01 < 4.97E+01 < 2.19E+01 < 3.47E+01 < 3.50E+01 < 4.46E+01 +/-4.50E+01 43 Station 04 < 1.71E+01 < 3.98E+01 < 1.17E+01 < 2.67E+01 < 2.58E+01 < 4.64E+01 < 2.52E+01 < 6.28E+01 < 4.70E+01 < 3.73E+01 < 2.46E+01 < 2.23E+01 < 3.46E+01 < 5.21E+01 < 1.85E+01 < 3.23E+or < 4.00E+01 < 5.90E+01 < 4.26E+01 < 5.48E+01 < 2.57E+01 < 1.87E+01 < 2.19E+01 < 3.46E+01 < 3.55E+01 < 4.42E+01 +/-4.44E+01 Station 05 < 1.71 E+01 < 3.05E+01 < 2.79E+01 < 1.04E+01 < 2.58E+01 < 1.80E+01 < 2.49E+01 < 6.28E+01 < 1.98E+01 < 3.73E+01 < 3.37E+01 < 2.23E+01 < 1.34E+01 < 6.29E+01 < 2.80E+01 < 3.22E+01 < 4.00E+01 < 5.90E+01 < 4.22E+01 < 5.54E+01 < 1.08E+01 < 4.82E+01 < 8.48E+OO < 3.46E+01 < 3.51E+01 < 4.45E+01 +/-4.44E+01 Station 06 < 1.62E+01 < 3.04E+01 < 2.89E+01 < 2.68E+01 < 2.18E+01 < 4.71E+01 < 3.32E+01 < 6.92E+01 < 5.67E+01 < 1.27E+01 < 3.37E+01 < 3.56E+01 < 4.45E+01 < 6.29E+01 < 2.80E+01 < 2.75E+01 < 1.29E+01 < 2.63E+01 < 3.61E+01 < 2.78E+01 < 2.59E+01 < 4.82E+01 < 3.61E+01 < 3.49E+01 < 4.58E+01 +/-4.46E+01 Station 07 < page 3 of4 1.63E+01 < 3.04E+01 <

2.89E+01 < 2.68E+01 < 2.18E+01 < 4.71E+01 < 3.32E+01 < 6.92E+01 < 5.67E+01 < 3.26E+01 < 3.37E+01 < 3.56E+01 < 4.45E+01 < 6.30E+01 < 2.80E+01 < 2.75E+01 < 3.32E+01 < 2.63E+01 < 3.61E+01 < 5.13E+01 < 2.59E+01 < 4.82E+01 < 3.61E+01 < 3.49E+01 < 4.58E+01 < 3.45E+01 +/-4.47E+01 Period Ending 07/08/15 07/14/15 07/21/15 07/28/15 08/05/15 08/11/15 08/18/15 08/26/15 09/01/15 09/08/15 09/16/15 09/22/15 09/29/15 10/06/15 10/14/15 10/21/15 10/27/15 11/04/15 11/12/15 11/18/15 11/24/15 12/02/15 12/08/15 12/15/15 12/22/15 12/29/15 MEAN Station 21 < 1.62E+01 < 3.05E+01 < 2.89E+01 < 2.67E+01 < 2.18E+01 < 4.69E+01 < 3.33E+01 < 6.92E+01 < 2.52E+01 < 3.30E+01 < 3.33E+01 < 3.56E+01 < 4.47E+01 < 6.27E+01 < 2.81E+01 < 2.76E+01 < 3.29E+01 < 2.63E+01 < 3.60E+01 < 5.17E+01 < 2.56E+01 < 4.83E+01 < 3.61E+01 < 3.49E+01 < 4.55E+01 < 3.47E+01 +/-4.47E+01 Station 22 < 1.62E+01 < 1.90E+01 < 2.89E+01 < 2.67E+01 < 2.18E+01 < 4.69E+01 < 3.77E+01 < 6.92E+01 < 5.67E+01 < 3.30E+01 < 3.46E+01 < 3.56E+01 < 1.87E+01 < 4.78E+01 < 2.62E+01 < 2.77E+01 < 3.29E+01 < 2.63E+01 < 3.60E+01 < 5.17E+01 < 2.56E+01 < 1.83E+01 < 3.61E+01 < 3.49E+01 < 4.55E+01 < 3.47E+01 +/-4.47E+01 Table 3-4 Airborne Iodine 1-131 [10-3 pCi/m 3] Station 23 < 1.56E+01 < 3.42E+01 < 2.90E+01 < 3.38E+01 < 2.94E+01 < 5.91 E+01 < 3.77E+01 < 6.43E+01 < 5.67E+01 < 3.26E+01 < 1.36E+01 < 2.72E+01 < 4.44E+01 < 4.80E+01 < 2.55E+01 < 2.89E+01 < 3.33E+01 < 3.24E+01 < 3.03E+01 < 5.17E+01 < 3.17E+01 < 4.34E+01 < 1.51E+01 < 3.59E+01 < 4.08E+01 < 3.62E+01 +/-3.88E+01 ** Control Station 44 Station 24** < 1.55E+01 < 3.44E+01 < 4.90E+01 < 3.37E+01 < 2.94E+01 < 5.92E+01 < 1.58E+01 < 6.43E+01 < 4.21E+01 < 4.38E+01 < 3.49E+01 <

2.72E+01 < 3.78E+01 < 2.00E+01 < 2.56E+01 < 2.89E+01 < 5.15E+01 < 3.24E+01 < 3.04E+01 < 3.78E+01 < 3.13E+01 < 4.36E+01 < 4.00E+01 < 3.59E+01 < 4.05E+01 < 3.65E+01 +/-3.89E+01 Station 01A < 1.56E+01 < 3.41E+01 < 4.92E+01 < 3.38E+01 < 2.94E+01 < 5.91 E+01 < 3.77E+01 < 6.43E+01 < 4.21E+01 < 4.36E+01 < 3.50E+01 < 2.72E+01 < 3.76E+01 < 4.97E+01 < 2.49E+01 < 2.89E+01 < 5.20E+01 < 3.24E+01 < 3.13E+01 < 3.61E+01 < 3.29E+01 < 4.34E+01 < 3.99E+01 < 3.59E+01 < 4.19E+01 < 3.52E+01 +/-3.60E+01 Indicator Locations Mean Station 05A < 1.55E+01 < 3.45E+01 < 4.90E+01 < 3.38E+01 < 2.94E+01 < 5.94E+01 < 3.76E+01 < 6.43E+01 < 4.21E+01 < 4.38E+01 < 3.50E+01 < 2.72E+01 < 3.79E+01 < 4.79E+01 < 9.01E+OO < 2.89E+01 < 5.15E+01 < 3.24E+01 < 3.05E+01 < 3.77E+01 < 3.15E+01 < 4.34E+01 < 4.00E+01 < 3.59E+01 < 4.08E+01 < 3.65E+01 +/-3.8BE+01 +/-4.04E+01 page 4 of4 Table 3-5 Airborne Particulate page Gamma Spectra 1of2 [10*3 pCitm3] Sampling Quarter 1 Location I Be-7 Cs-134* I Cs-137* 01 1.47E+02 +/-3.03E+01 < 1.29E+OO < 7.SOE-01 01A 1.54E+02 +/-5.37E+01 < 2.16E+OO < 2.23E+OO 02 8.75E+01 +/-4.68E+01 < 1.26E+OO < 1.56E+OO 03 8.47E+01 +/-2.85E+01 < 1.61E+OO < 1.41E+OO 04 1.17E+02 +/-2.89E+01 < 1.45E+OO < 1.64E+OO 05 9.27E+01 +/-3.50E+01 < 1.98E+OO < 1.28E+OO 05A 8.49E+01 +/-3.54E+01 < 1.36E+OO < 1.37E+OO 06 1.39E+02 +/-3.52E+01 < 1.44E+OO < 1.29E+OO 07 9.53E+01 +/-3.24E+01 < 1.68E+OO < 1.65E+OO 21 1.04E+02 +/-2.79E+01 < 1.36E+OO < 9.45E-01 22 1.03E+02 +/-3.16E+01 < 1.67E+OO < 1.78E+OO 23 1.49E+02 +/-4.84E+01 < 2.23E+OO < 2.17E+OO 24** 9.60E+01 +/-3.94E+o1 < 1.45E+OO < 1.34E+OO Sampling Quarter 2 Location I Be-7 Cs-134* I Cs-137* Sr-89 I Sr-90 I 01 1.19E+02 +/-2.30E+01 < 1.12E+OO < 9.38E-01 < 5.21E+OO < 2.24E+OO 01A 1.54E+02 +/-2.91E+OO < 1.11E+OO < 9.76E-01 < 4.47E+OO < 2.06E+OO 02 1.15E+02 +/-2.76E+01 < 1.23E+OO < 1.13E+OO < 5.35E+OO < 2.23E+OO 03 1.22E+02 +/-2.63E+01 < 1.51E+OO < 1.07E+OO < 5.06E+OO < 1.87E+OO 04 1.22E+02 +/-4.08E+01 < 2.02E+OO < 1.84E+OO < 5.57E+OO < 2.24E+OO 05 1.28E+02 +/-3.20E+01 < 1.28E+OO < 1:24E+OO < 5.BOE+OO < 1.69E+OO 05A 1.12E+02 +/-2.49E+01 < 1.43E+OO < 1.29E+OO < 6.25E+OO < 2.14E+OO 06 9.58E+01 +/-3.83E+01 < 2.04E+OO < 1.61E+OO < 6.19E+OO < 2.44E+OO 07 9.89E+01 +/-3.08E+01 < 1.36E+OO < 1.13E+OO < 5.49E+OO < 1.87E+OO 21 1.10E+02 +/-2.43E+01 < 1.24E+OO < 8.61E-01 < 5.43E+OO < 2.58E+OO 22 1.17E+02 +/-2.14E+01 < 1.35E+OO < 1.43E+OO < 5.17E+OO < 2.27E+OO 23 1.48E+02 +/-3.26E+01 < 1.32E+OO < 1.31E+OO < 5.06E+OO < 1.72E+OO 24** 1.57E+02 +/-3.13E+01 < 1.36E+OO < 1.38E+OO < 5.30E+OO < 2.54E+OO

LLD identified in the ODCM ** Control Station 45 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24** MEAN Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24** Be-7 1.42E+02 +/-3.18E+01 1.59E+02 +/-3.26E+01 1.19E+02 +/-2.95E+01 1.30E+02 +/-2.69E+01 1.43E+02 +/-4.86E+01 1.68E+02 +/-3.60E+01 1.34E+02 +/-4.23E+01 1.36E+02 +/-4.39E+01 1.36E+02 +/-.3.13E+01 1.33E+02 +/-2.68E+01 1.51E+02 +/-3.27E+01 1.67E+02 +/-3.29E+01 1.55E+02 +/-3.74E+01 Be-7 8.26E+01 +/-2.71 E+01 1.01E+02 +/-1.85E+01 7.40E+01 +/-1.83E+01 9.43E+01 +/-2.51 E+01 6.19E+01 +/-3.71E+01 9.52E+01 +/-2.33E+01 1.03E+02 +/-2.56E+01 1.15E+O? +/-3.35E+01 1.01 E+02 +/-3.26E+01 8.31E+01 +/-2.71E+01 8.13E+01 +/-2.93E+01 1.02E+02 +/-2.31 E+01 1.02E+02 +/-2.80E+01

LLD Identified in ODCM ** Control Station Table 3-5 Airborne Particulate Gamma Spectra [10-3 pCi/m3] Cs-134* < 5.92E-01 < 1.40E+OO < 6.01E-ci1

< 8.64E-01 < 1.41E+OO < 8.85E-01 < 1.73E+OO < 1.06E+OO < 5.42E-01 < 1.35E+OO < 1.14E+OO < 7.01E-01 < 1.14E+OO Cs-134* < 1.76E+OO < 1.22E+OO < 1.01E+OO < 1.01E+OO < 1.96E+OO < 1.47E+OO < 1.10E+OO < 1.91E+OO < 1.45E+OO < 1.23E+OO < 1.80E+OO Cs-137* < 8.30E-01 < 1.01E+OO < 6.15E-01 < 7.77E-01 < 7.19E-01 < 7.16E-01 < 1.33E+OO < 1.16E+OO < 8.03E-01 < 7.60E-01 < 9.63E-01 < 6.11E-01 < 1.32E+OO MEAN Cs-137* Be-7 < 1.69E+OO 1.23E+02 +/-< 9.92E-01 < 9.52E-01 < 9.61E-01 1.42E+02 +/-9.89E+01 +/-1.08E+02 +/-< . 2.04E+OO 1.11 E+02 +/-< 1.17E+OO 1.21E+02 +/-< 1.16E+OO 1.08E+02 +/-< 2.01 E+OO 1.21 E+02 +/-< 1.16E+OO 1.08E+02 +/-< 1.15E+OO 1.08E+02 +/-< 1.52E+OO 1.13E+02 +/-< 1.43E+OO < 1.01 E+OO 1.42E+02 +/-< 1.14E+OO < 1.24E+OO 1.28E+02 +/-Mean of All Indicator Location:

1.17E+02 +/-46 2.81E+01 2.69E+01 3.06E+01 2.67E+01 3.89E+01 3.16E+01 3.21E+01 3.77E+01 3.18E+01 2.65E+01 2.88E+01 3.43E+01 3.40E+01 3.11E+01 page 2 of2 Quarter 3 Quarter 4 Table 3-6 Soil [pCi/kg] Soil sampled on triennial basis. Not required in 2015. 47 page 1 of 1 Table 3-7 Precipitation Gross Beta [pCi/L] page 1 of 2 Sampling Date I Gross Beta I H-3 I Rainfall (inches) I 01/28/15 -1.36E+01 +/-1.89E+OO < 1.56E+03 2.22 02/24/15 3.79E+OO +/-1.31E+OO < 1.79E+03 1.59 03/31/15 9.54E+OO +/-2.03E+OO < 1.30E+03 3.70 04/28/15 < 1.43E+OO < 1.57E+03 3.63 05/26/15 5.64E+OO +/-1.29E+OO < 8.97E+02 1.97 07/01/15 2.29E+OO +/-1.08E+OO < 9.48E+02 5.56 07/28/15 1.40E+01 +/-1.85E+OO < 1.79E+03 2.90 08/26/15 7.76E+OO +/-1.45E+OO < 1.80E+02 2.10 09/29/15 7.04E+OO +/-1.42E+OO < 7.63E+02 2.48 10/27/15 < 1.49E+OO < 9.72E+02 4.93 11/24/15 2.73E+OO +/-1.17E+OO < 1.44E+03 2.87 12/29/15 1.69E+OO +/-9.93E-01 < 9.19E+02 4.94 Mean 6.81E+OO +/-1.38E+OO < 1.18E+03 Total 38.89 48 Table 3-7 Precipitation page Gamma Spectra 2 of2 [pCi/L] Sampling Location Be-7 Mn-54 Fe-59 Co-58 Co-60 01A 07/01/15 < 3.10E+01 < 7.65E-01 < 9.96E+OO < 2.46E+OO < 7.60E-01 12129/15 < 2.24E+01 < 7.51E-01 < 6.80E+OO < 1.50E+OO < 5.84E-01 I Zn-65 Zr-95 Nb-95 I Cs-134 I Cs-137 01A 07/01/15 < 1.78E+OO < 4.64E+OO < 2.62E+OO < 7.18E-01 < 7.63E-01 12/29/15 < 1.43E+OO < 3.66E+OO < 1.83E+OO < 5.95E-01 < 5.80E-01 I Ba-140 La-140 I 1-131 I Th-228 01A 07/01/15 < 4.04E+03 < 1.22E+03 < 9.56E+04 5.30E+OO +/-3.61E+OO 12/29/15 < 1.11E+03 < 3.73E+02 < 1.60E+04 <* 1.67E+OO MEAN Sampling Location Be-7* Mn-54* Fe-59* Co-58* Co-60* 01A Zn-65* Zr-95* Nb-95* Cs-134* Cs-137* 01A Ba-140* La-140* 1-131* Th-228 I 01A 5.30E+OO +/-3.61 E+OO

No mean values. All results were <MDA 49 Table 3-8 Milk page Gamma Spectra & Strontium 1 of 1 [pCi/L] Sampling Station 12A Date K-40 I Sr-89 Sr-90 1-131* Cs-134* I Cs-137* I Ba-140* La-140* I 01/20/15 1.22E+03 +/-1.12E+02 [a] [a] < 9.08E-01 < 4.50E+OO < 5.10E+OO < 2.43E+01 < 7.13E+OO 02/24/15 1.38E+03 +/-1.56E+02 [a] [a] < 3.41E-01 < 6.16E+OO < 8.40E+OO < 3.42E+01 < 8.51E+OO 03/17/15 1.16E+03 +/-1.64E+02 < 3.96E+OO < 9.66E-01 < 7.72E-01 < 7.53E+OO < 9.63E+OO < 3.41 E+01 < 1.04E+01 04/21/15 1.14E+03 +/-1.77E+02 [a] [a] < 9.19E-01 < 8.26E+OO < 9.58E+OO < 3.72E+01 < 1.12E+01 05/19/15 1.28E+03 +/-1.26E+02 [a] [a] < 8.99E-01 < 4.46E+OO < 4.97E+OO < 2.55E+01 < 8.15E+OO 06/16/15 1.39E+03 +/-1.82E+02 < 4.10E+OO < 1.21 E+OO < 8.17E-01 < 7.32E+OO < 7.83E+OO < 4.12E+01 < 1.13E+01 07/21/15 1.32E+03 +/-2.02E+02 [a] [a] < 4.00E-01 '< 7.01E+OO < 6.13E+OO < 3.73E+01 < 1.31E+01 08/18/15 1.27E+03 +/-2.07E+02 [a] [a] < 7.04E-01 < 8.18E+OO < 9.66E+OO < 4.23E+01 < 1.49E+01 09/16/15 1.23E+03 +/-1.79E+02 < 2.25E+OO < 2.68E-01 < 6.97E-01 < 6.70E+OO < 7.28E+OO < 3.59E+01 < 1.33E+01 10/21/15 1.25E+03 +/-1.81E+02 [a] [a] < 3.74E-01 < 8.56E+OO < 7.59E+OO < 3.84E+01 < 1.55E+OO 11/18/15 1.18E+03 +/-1.91E+02 [a] [a] < 6.57E-01 < 7.41E+OO < 9.17E+OO < 3.28E+01 < 7.84E+OO 12/15/15 1.33E+03 +/-1.86E+02 < 2.33E+OO < 1.22E+OO < 8.00E-01 < 6.43E+OO < 8.69E+OO < 3.85E+01 < 1.00E+01 Sta. Mean 1.26E+03 +/-1.72E+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] 1of2 Sampling Sampling Location Date Be-7 K-40 1-131

Cs-134* Cs-137* 05/12/15 3.01E+02 +/-1.20E+02 6.34E+03 +/-3.37E+02 < 1.85E+01 < 1.33E+01 < 1.50E+01 148 06/09/15 1.49E+03 +/-2.95E+02 4.85E+03 +/-5.19E+02 < 2.41E+01 < 2.83E+01 < 2.81 E+01 07/14/15 1.53E+03 +/-4.41E+02 7.43E+03 +/-7.27E+02 < 1.63E+01 < 3.15E+01 < 3.33E+01 08/11/15 1.67E+03 +/-5.61E+02 7.68E+03 +/-9.65E+02 < 3.1QE+01 < 5.46E+01 < 6.44E+01 09/08/15 1.47E+03 +/-5.51E+02 5.51E+03 +/-9.11E+02 < 4.78E+01 < 5.54E+01 < 6.12E+01 10/14/15 1.84E+03 +/-6.12E+02 8.57E+03 +/-1.22E+03 < 1.61 E+01 < 4.92E+01 < 6.15E+01 Mean 1.38E+03 +/-4.30E+02 6.73E+03 +/-7.80E+02 +/-+/-+/-Sampling Sampling Location Date Be-7 K-40 1-131* Cs-134* Cs-137* 15 05/12/15 7.31E+02 +/-1.57E+02 5.54E+03 +/-3.68E+02 < 1.71E+01 < 1.79E+01 < 2.00E+01 06/09/15 7.89E+02 +/-2.59E+02 7.61E+03 +/-6.36E+02 < 2.69E+01 < 2.68E+01 < 2.94E+01 07/14/15 1.46E+03 +/-2.47E+02 5.21E+03 +/-4.84E+02 < 2.14E+01 < 2.38E+01

< 2.63E+01 08/11/15 2.19E+03 +/-5.21E+02 3.50E+03 +/-8.32E+02 < 3.95E+01 < 5.58E+01 < 6.54E+01 09/08/15 < 5.73E+02 6.72E+03 +/-1.03E+03 < 2.97E+01 < 5.24E+01 < 5.12E+01 10/14/15 3.16E+03 +/-5.32E+02 7.79E+03 +/-1.11E+03 < 1.06E+01 < 4.59E+01 < 5.28E+01 Mean 1.67E+03 +/-3.82E+02 6.06E+03 +/-7.43E+02 +/-+/-+/-Sampling Sampling Location Date Be-7 K-40 1-131*. Cs-134* Cs-137* 16** 05/12/15 4.75E+02 +/-1.20E+02 6.40E+03 +/-2.91E+02 < 1.25E+01 < 1.43E+01 < 1.38E+01 06/09/15 8.92E+02 +/-2.25E+02 5.54E+03 +/-5.68E+02 < 2.24E+01 < 2.81E+01

< 3.17E+01 07/14/15 9.69E+02 +/-3.32E+02 5.47E+03 +/-6.87E+02 < 2.01 E+01 < 3.06E+01 < 3.48E+01 08/11/15 1.06E+03 +/-3.91E+02 8.91E+03 +/-1.09E+03 < 3.43E+01 < 3.66E+01 < 4.35E+01 09/08/15 1.46E+03 +/-6.32E+02 3.13E+03 +/-1.06E+03 < 2.72E+01 < 5.84E+01 < 6.46E+01 10/14/15 1.55E+03 +/-6.40E+02 7.36E+03 +/-1.07E+03 < 1.60E+01 < 5.83E+01 < 6.23E+01 Mean 1.07E+03 +/-3.90E+02 6.14E+03 +/-7.94E+02 +/-+/-+/-* LLD identified in ODCM ** Control Station 51 Table 3-9 Food and Vegetation page Gamma Spectra 2 of2 [pCi/kg] Sampling Sampling Location Date Be-7 K-40 1-131* Cs-134* Cs-137* 23 05/12/15 5.25E+02 +/-2.20E+02 6.27E+03

+/-5.11E+02 < 1.55E+01 < 2.21E+01 < 2.39E+01 06/09/15 1.16E+03 +/-2.32E+02 4.88E+03 .+/-5.43E+02 < 3.18E+01 < 2.82E+01 < 2.61E+01 07/14/15 7.16E+02 +/-3.09E+02 5.40E+03 +/-6.31E+02 < 2.11E+01 < 3.15E+01 < 3.14E+01 08/11/15 5.04E+03 +/-6c13E+02 4.11E+03 +/-8.79E+02 < 3.61E+01 < 5.52E+01 < 6.04E+01 09/08/15 < 4.92E+02 7.52E+03 +/-1.04E+03 < 3.42E+01 < 5.85E+01 < 5.77E+01 10/14/15 2.30E+03 +/-4.86E+02 6.55E+03.

+/-1.03E+03 < 1.17E+01 < 5.59E+01 < 5.77E+01 Mean 1.95E+03 +/-3.92E+02 5.79E+03 +/-7.72E+02 +/-+/-+/-Sampling Sampling Location Date Be-7 K-40 1-131* Cs-134* Cs-137* 26 05/12115 2.10E+02 +/-1.29E+02 8.27E+03 +/-3.44E+02 < 1.31E+01 < 1.16E+01 < 1.33E+01 06/09/15 1.35E+03 +/-3.04E+02 7.20E+03 +/-7.33E+02 < 2.59E+01 < 2.65E+01 < 2.81E+01 07/14/15 1.71E+03 +/-3.91E+02 5.06E+03 +/-6.27E+02 < 2.16E+01 < 2.79E+01 < 3.01E+01 08/11/15 2.12E+03 +/-5.29E+02 .6.49E+03

+/-9.14E+02 < 1.67E+01 < 5.42E+01 < 5.53E+01 09/08/15 1.11E+03 +/-5.56E+02 6.54E+03 +/-9.27E+02 < 3.14E+01 < 5.25E+01 < 5.34E+01 10/14/15 1.75E+03 +/-4.39E+02 5.93E+03 +/-9.95E+02 < 1.57E+01 < 4.80E+01 < 5.59E+01 Mean 1.38E+03 +/-3.91E+02 6.58E+03 +/-7.57E+02 +/-+/-+/-Indicator locations 1.57E+03 +/-3.99E+02 6.29E+03 +/-7.63E+02 +/-+/-+/-* LLD identified in ODCM 52 Table 3-10 Well Water page Gamma Spectra, Strontium, and Tritium 1 of 1 [pCi/L] Sampling Station 01A Date H-3 Sr-89 Sr-90 Mn-54 Fe-59 Co-58 Co-60 Zn-65 03/31/15 < 1.29E+03 [a] [a] < 2.66E+OO < 5.59E+OO < 2.90E+OO < 3.43E+OO < 7.19E+OO 07/01/15 < 9.57E+02 < 4.09E+OO < 7.75E-01 < 3.07E+OO < 8.44E+OO < 3.58E+OO < 3.02E+OO < 6.42E+OO 09/29/15 < 7.60E+02 [a] [a] < 4.90E+OO < 1.02E+01 < 5.73E+OO < 3.69E+OO < 1.01E+01 12/29/15 < 9.17E+02 [a] [a] < 5.03E+OO < 1.45E+01 < 4.84E+OO < 6.14E+OO < 1.18E+01 Mean Sampling Date Zr-95 Nb-95 1-131 Cs-134 Cs-137 I Ba-140 La-140 03/31/15 < 5.98E+OO < 2.84E+OO < 6.33E-01 < 2.60E+OO < 3.68E+OO < 1.88E+01 < 6.19E+OO 07/01/15 < 5.85E+OO < 3.68E+OO < 7.58E-01 < 2.98E+OO < 3.42E+OO < 2.19E+01 < 6.02E+OO 09/29/15 < 7.90E+OO < 6.63E+OO < 9.02E-01 < 5.23E+OO < 5.39E+OO < 2.45E+01 < 8.51E+OO 12/29/15 < 1.05E+01 < 7.91E+OO < 4.52.E-01

< 5.59E+OO < 5.74E+OO < 3.16E+01 < 7.79E+OO 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 Sr-89 Sr-90 Mn-54* Fe-59* Co-58* Co-60* Zn-65* 01/13/15 (a] [b] [b] < 4.57E+OO < 8.17E+OO < 5.59E+OO < 4.81E+OO < 9.82E+OO 02/16/15 [a] (b] (b] < 3.59E+OO < 7.75E+OO < 4.71E+OO < 3.44E+OO < 8.58E+OO 03/16/15 4.84E+03 +/-8.09E+02 [b] [b] < 4.76E+OO < 8.88E+OO < 4.15E+OO < 3.40E+OO < 8.97E+OO 04/14/15 [a] [b] [b] < 3.32E+OO < 7.23E+OO < 3.63E+OO < 3.05E+OO < 6.BOE+OO 05/11/15 (a] [b] [b] < 2.26E+OO < 4.87E+OO < 2.45E+OO < 2.11E+OO < 4.29E+OO 06/16/15 3.92E+03 +/-1.49E+03 < 3.54E+OO < 7.39E-01 < 4.45E+OO < 8.91E+OO < 4.40E+OO < 4.14E+OO < 7.27E+OO 07/14/15 [a] [b] [b] < 4.23E+OO < 8.92E+OO < 4.90E+OO < 4.77E+OO < 9.90E+OO 08/10/15 (a] (b] [b] < 4.37E+OO < 1.01E+01 < 4.21E+OO < 4.76E+OO < 9.67E+OO 09/15/15 2.15E+03 +/-7.29E+02 (b] [b] < 5.28E+OO < 8.98E+OO < 5.13E+OO < 3.82E+OO < 9.20E+OO 10/19/15 (a] [b] (b] < 4.21E+OO < 8.76E+OO < 4.30E+OO < 4.07E+OO < 9.60E+OO 11/10/15 (a] [b] [b] < 5.78E+OO < 8.96E+OO < 4.82E+OO < 4.61E+OO < 1.32E+01 12115/15 2.49E+03 +/-7.09E+02 (b] (b] < 1.98E+OO < 5.76E+OO < 2.33E+OO < 2.34E+OO < 4.22E+OO MEAN 3.35E+03 +/-9.34E+02 +/-+/-+/-+/-+/-+/-+/-Sampling Date Nb-95* Zr-95* 1-131

Cs-134* Cs-137*

Ba-140* La-140* 01/13/15 < 9:35E+OO < 4.32E+OO < 4.15E-01 < 4.38E+OO < 5.35E+OO < 2.67E+01 < 1.09E+01 02/16/15 < 6.55E+OO < 4.29E+OO < 2.13E-01 < 3.72E+OO < 4.21E+OO < 2.13E+01 < 5.20E+OO 03/16/15 < 8.90E+OO < 4.23E+OO < 3.52E-01 < 4.50E+OO < 4.41E+OO < 2.04E+01 < 6.41E+OO 04/14/15 < 1 6.52E+OO < 3.68E+OO < 4.33E-01 < 3.02E+OO < 3.81E+OO < 1.99E+01 < 7.08E+OO 05/11/15 < 4.15E+OO < 2.43E+OO < 6.36E-01 < 2.18E+OO < 2.34E+OO < 1.58E+01 < 4.88E+OO 06/16/15 < 7.73E+OO < 4.79E+OO < 4.58E-01 < 3.92E+OO < 4.42E+OO < 2.42E+01 < 9.18E+OO 07/14/15 < 6.71E+OO < 4.84E+OO < 9.73E-01 < 3.96E+OO < 4.63E+OO < 2.19E+01 < 7.93E+OO 08/10/15 < 7.38E+OO < 5.32E+OO < 5.23E-01 < 4.13E+OO < 4.56E+OO < 2.48E+01 < 7.06E+OO 09/15/15 < 9.51E+OO < 6.55E+OO < 5.48E-01 < 4.10E+OO < 6.68E+OO < 2.55E+01 < 5.03E+OO 10/19/15 < 7.32E+OO < 4.21E+OO < 5.03E-01 < 4.59E+OO < 4.72E+OO < 2.32E+01 < 6.96E+OO 11/10/15 < 8.66E+OO < 5.02E+OO < 5.17E-01 < 4.99E+OO < 5.43E+OO < 2.43E+01 < 8.46E+OO 12/15/15 < 4.48E+OO < 2.39E+OO < 9.80E-01 < 2.10E+OO < 2.37E+OO < 1.67E+01 < 5.71E+OO MEAN +/-+/-+/-+/-+/-+/-* LLD identified in ODCM [a] Tritium analyses on quarterly composite.

[b] Sr-89/90 performed annually on t'd quarter composite sample. 54 Sampling Date 01/13/15 02/16/15 03/16/15 04/14/15 05/11/15 06/16/15 07/14/15 08/10/15 09/15/15 10/19/15 11/10/15 12/15/15 Mean Sampling Date 01/13/15 02/16/15 03/16/15 04/14/15 05/11/15 06/16/15 07/14/15 08/10/15 09/15/15 10/19/15 11/10/15 12/15/15 H-3* [a] [a] 6.73E+03 +/-9.03E+02 [a] [a] 2.19E+03 +/-1.33E+03 [a] [a] 2.78E+03 +/-7.66E+02 [a] [a] 2.11 E+03 +/-6.85E+02 3.45E+03 +/-9.21 E+02 Zr-95* < < < 8.58E+OO 8.74E+OO 7.18E+OO < 7.01E+OO < 2.88E+OO < 8.24E+OO < 8.46E+OO < 8.44E+OO < < < < 8.56E+OO 9.32E+OO 9.07E+OO 3.11E+OO Sr-89 [b] [b] [b] [b] [b] < 3.79E+OO [b]

[b] [b] [b] [b] [b] +/-Nb-95* < 6.16E+OO < 4.40E+OO . < 4.25E+OO < 3.65E+OO < 1.82E+OO < 4.42E+OO < 5.76E+OO < 4.69E+OO < 5.49E+OO < 5.38E+OO < 5.29E+OO < 1.69E+OO Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium [pCi/L] [b] [b] [b] [b] [b] Sr-90 < 7.41E-01 [b] [b] [b] [b] [b] [b] +/-1-13.1* < 2.54E-01 < 9.83E+OO < 3.53E-01 < 5.28E-01 < 5.57E-01 < 4.34E-01 < 8.17E-01 < 5.23E-01 < 5.05E-01 < 4.57E-01 < 5.42E-01 < 7.25E-01 Mn-54* < < < < < < < < < < < < +/-5.66E+OO 4.91E+OO 3.67E+OO 3.34E+OO 1.56E+OO 5.46E+OO 4.57E+OO 4.56E+OO 6.07E+OO 5.00E+OO 5.31E+OO 1.51E+OO Cs-134* < < < < < < < < < < < < 5.24E+OO 5.08E+OO 4.03E+OO 3.35E+OO 1.49E+OO 4.74E+OO 4.78E+OO 4.55E+OO 5.60E+OO 4.90E+OO 4.76E+OO 1.55E+OO Fe-59* < 1.25E+01 < 1.08E+01 < 9.34E+OO < 8.00E+OO < 3.78E+OO < 1.14E+01 < 1.01E+01 < 1.04E+01 < 8.34E+OO < 1.08E+01 < 1.00E+01 < 3.47E+OO +/-Cs-137* < 5.29E+OO <

5.06E+OO < 4.40E+OO < 4.26E+OO < 1.55E+OO < 5.05E+OO < 5.36E+OO < 4.83E+OO < 4.40E+OO < 5.05E+OO < 5.62E+OO < 1.63E+OO Co-58* < 5.33E+OO < 4.46E+OO < 3.85E+OO < 3.88E+OO < 1.62E+OO < 5.30E+OO < 4.71E+OO < 4.75E+OO < 5.98E+OO < 4.82E+OO < 5.18E+OO < 1.69E+OO +/-Ba-140* < 2.76E+01 < 3.20E+01 < 1.99E+01 < 2.01E+01 < 1.20E+01 < 2.67E+01 < 2.91E+01 < 2.55E+01 <

2.22E+01 < 2.60E+01 < 2.23E+01 < 1.32E+01 Mean +/-+/-+/-+/-+/-+/-* LLD identified in ODCM [a] Tritium analyses on quarterly composite.

[b] Sr-89/90 performed annually on t* quarter composite sample. 55 Co-60* < 5.48E+OO < 4.84E+OO < 4.06E+OO < 3.25E+OO < 1.46E+OO < 4.60E+OO < 5.86E+OO < 5.22E+OO < 5.27E+OO < 5.21E+OO < 5.12E+OO < 1.52E+OO +/-La-140* < 7.24E+OO < 1.18E+01 < 5.67E+OO < 6.73E+OO < 3.78E+OO < 8.94E+OO < 9.43E+OO < 7.84E+OO < 6.95E+OO < 7.95E+OO < 9.41E+OO < 3.79E+OO +/-page 1of2 Station 08 Zn-65* < 1.10E+01 < 8.72E+OO < 7.44E+OO < 7.86E+OO < 3.10E+OO < 8.45E+OO < 1.03E+01 < 9.68E+OO < 1.09E+01 < 1.02E+01 < 8.13E+OO < 2.95E+OO +/-

Sampling Date 01/13/15 02/16/15 03/16/15 04/14/15 05/11/15 06/16/15 07/14/15 08/10/15 09/15/15 10/19/15 11/10/15 12/15/15 MEAN Sampling Date 01/13/15 02/16/15 03/16/15 04/14/15 05/11/15 06/16/15 07/14/15 08/10/15 09/15/15 10/19/15 11/10/15 12/15/15 MEAN [a] [a] H-3* < 8.09E+02 [a] [a] < 1.81E+03 [a] [a] < 9.73E+02 [a] [a] < 8.86E+02 +/-Zr-95* < 8.26E+OO < 7.BOE+OO < 9.04E+OO < 5.41E+OO < 4.19E+OO < 7.26E+OO < 7.16E+OO < 8.62E+OO < 1.21E+01 < 8.19E+OO < 7.85E+OO < 4.34E+OO +/-* LLD identified in ODCM Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium [pCi/L] Sr-89 [b] [b] [b] [b] [b] < 3.88E+OO [b] [b] [b] [b] [b] [b] +/-Nb-95* < 5.42E+OO < 5.38E+OO < 5.05E+OO < 3.15E+OO < 2.58E+OO < 4.43E+OO < 4.60E+OO < 5.83E+OO < 7.30E+OO < 4.95E+OO < 6.75E+OO < 2.48E+OO +/-Sr-90 [b] [b] [b] [b] [b] < 7.78E-01 [b] [b] [b] [b] [b] [b] +/-1-131* < 2.85E-01 < 2.48E-01 < 3.12E-02 < 5.29E-01 < 5.84E-01 < 4.89E-01 < 9.70E-01 < 6.52E-01 < 4.59E-01 < 5.05E-01 < 4.35E-01 < 7.87E-01 +/-Mn-54* < 4.36E+OO < 4.12E+OO < 5.09E+OO < 2.81E+OO < 2.32E+OO < 4.35E+OO < 4.23E+OO < 4.58E+OO < 5.92E+OO < 4.51E+OO < 4.31E+OO < 2.15E+OO +/-Cs-134* < 4.44E+OO < 4.58E+OO < 5.02E+OO < 2.74E+OO < 1.82E+OO < 4.02E+OO < 4.19E+OO < 4.64E+OO < 6.12E+OO < 4.13E+OO < 5.11E+OO < 2.0BE+OO +/-Fe-59* < 9.00E+OO < 8.70E+OO < 9.00E+OO < 5.52E+OO < 5.04E+OO < 9.58E+OO < 9.10E+OO < 1.12E+01 < 9.23E+OO < 8.41E+OO < 1.34E+01 < 5.49E+OO +/-Cs-137* < 5.02E+OO < 4.75E+OO < 5.13E+OO < 3.11E+OO < 2.12E+OO < 4.94E+OO < 5.08E+OO < 5.22E+OO < 6.41E+OO < 4.87E+OO < 5.23E+OO < 2.36E+OO +/-Co-58* < 4.58E+OO < 4.60E+OO < 4.54E+OO < 3.11E+OO < 2.29E+OO < 4.18E+OO < 4.56E+OO < 4.61E+OO < 5.50E+OO < 4.69E+OO < 5.81E+OO < 2.41E+OO +/-Ba-140* < 2.50E+01 < 2.57E+01 < 2.70E+01 < 1.75E+01 < 1.53E+01 < 2.40E+01 < 2.02E+01 < 2.25E+01 < 3.27E+01 < 2.38E+01 < 2.39E+01 < 1.79E+01 +/-Co-60* < 3.69E+OO < 4.40E+OO < 5.86E+OO < 2.94E+OO < 2.05E+OO < 4.31E+OO < 3.64E+OO < 4.93E+OO .< 8.35E+OO < 4.49E+OO < 6.62E+OO < 2.23E+OO +/-La-140* < 6.35E+OO < 6.84E+OO < 1.05E+01 < 5.42E+OO < 5.00E+OO < 8.47E+OO < 6.77E+OO < 6.82E+OO < 8.91E+OO < 6.42E+OO < 1.20E+01 < 5.71E+OO +/-page 2 of2 Station 09A Zn-65* < 6.79E+OO < 1.04E+01 < 1.03E+01 < 5.32E+OO < 4.65E+OO < 7.26E+OO < 9.60E+OO < 1.17E+01 < 1.15E+01 < 9.24E+OO < 8.06E+OO < 4.35E+OO +/-[a] Tritium analyses on quarterly composite.

[b] Sr-89/90 performed annually on znd quarter composite sample. 56 Sample Date 4/29/2015 Station 08 Station 09A** Station 11 4/29/2015 Station 08 Station 09A** Station 11 Sample Date 10/19/2015 Station 08 Station 09A** Station 11 10/19/2015 Station 08 Station 09A** Station 11 Indicator Control Indicator Control I I

LLD identified in ODCM Sr-89 [a] [a] [a] Sr-89 < 2.52E+02 < 2.19E+02 < 2.65E+02 Sr-89 +(-Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg] page 1 of 1 Sr-90 K-40 Cs-134* Cs-137* .! [a] [a] [a] Sr-90 < 3.59E+01 < 3.03E+01 < 4.35E+01 Sr-90 +/-** Control Station 1.21 E+03 +/-3.91 E+02 2.76E+04 +/-1.31E+03 1.64E+04 +/-1.13E+03 < 3.56E+01 < 4.23E+01 < 3.50E+01 < 2.93E+01 < 4.57E+01 < 4.64E+01 Ra-226 Th-228 I Th-232 I < 7.97E+02 9.11E+01 +/-4.59E+01 < 1.62E+02 1.75E+03 +/-7.98E+02 5.29E+02 +/-6.59E+01 4.79E+02 +/-1.36E+02 < 6.46E+02 5.93E+02 +/-5.63E+01 5.28E+02 +/-1.17E+02 K-40 Cs-134* Cs-137* 1.59E+03 +(-4.50E+02 < 2.43E+01 < 3.57E+01 2.68E+04 +(-1.86E+03 < 5.54E+01 < 7.10E+01 2.56E+04 +(-1.63E+03 < 4.48E+01 < 6.30E+01 Ra-226 I Th-228 I Th-232 9.72E+02 +/-6.75E+02 1.82E+02 +/-4.35E+01 < 1.83E+02 2.43E+03 +/-1.16E+03 6.02E+02 +/-8.19E+01 6.42E+02 +/-1.63E+02 2.00E+03 +/-1.12E+03 8.22E+02 +/-1.02E+02 7.36E+02 +/-1.66E+02 MEAN_ K-40 I Cs-134* Cs-137* 1.12E+04 +/-9.00E+02 +(-+I-2.72E+04 +I-1.59E+03 +(-+(-Ra-226 I Th-228 I Th-232 1.49E+03 +I-8.14E+02 4.22E+o2 +(-6.19E+01 6.32E+02 +(-1.57E+02 2.09E+03 +(-7.98E+02 5.66E+02 +(-7.39E+01 5.61 E+02 +(-1.50E+02 [a] Sr-89/90 analyses performed annually.

57 I I i Sample Date 4/29/2015 Station 08 Sample Date 10/19/2015 Station 08 Sr-89 [a] Sr-89 < Sr-89 +/-* LLD identified in ODCM 2.87E+02 [a] Sr-89/90 analyses performed annually.

Table 3-14 Shoreline Soil Gamma Spectra, and Strontium

[pCi/Kg] Sr-90 K-40 Cs-134* [a] 5.07E+02 +/-3.46E+02 < 2.60E+01 Ra-226 Th-228 < 6.40E+02 5.18E+01 +/-3. 70E+01 Sr-90 K-40 Cs-134* < 2.98E+01 5.39E+02 +/-4.37E+02 < 3.46E+01 Ra-226 Th-228 < 7.80E+02 < 8.62E+01 MEAN Sr-90 K-40 Cs-134* +/-5.23E+02 +/-3.92E+02 +/-Ra-226 Th-228 +/-5.18E+01 +/-6.16E+01 58 r Cs-137* page 1 of 1 < 3.01E+01 Th-232 < 1.21E+02 Cs-137* < 3.73E+01 Th-232 < 1.89E+02 Cs-137* +/-Th-232 +/-1.55E+02 Sampling Date I K-40 I 04/21/15 1.51 E+03 +/-7.33E+02 10/20/15 1.20E+03 +/-7.39E+02 Sampling Date I K-40 I 04/21/15 1.98E+03 +/-9.00E+02 10/20/15 2.07E+03 +/-1.02E+03 Sampling Date K-40 I 04/21/15 10/20/15 Sampling Date 04/21/15 10/20/15 Mean I 1.44E+03 +/-7.81 E+02 1.66E+03 +/-9.26E+02 K-40 2.29E+03 +/-6.23E+02 2.05E+03 +/-7.89E+02 1.45E+03 +/-8.14E+02 Indicator 1.45E+03 +/-7.95E+02 Control 2.1 OE+03 +/-8.33E+02

LLD identified in ODCM ** Control Station I [a] Non-bottom dwelling species of gamefish.

[b] Bottom dwelling species offish. Mn-54* < 4.95E+01 < < 5.05E+01 < Mn-54* < 6.41E+01 < < 9.59E+01 < Mn-54* < 7.41E+01 < < 7.73E+01 < Mn-54* I < 4.41 E+01 < < 5.74E+01 < Table 3-15 Fish Gamma Spectra [pCi/Kg] Fe-59* I Co-58* 1.14E+02 < 4.97E+01 1.29E+02 < 6.62E+01 Fe-59* I Co-58* 1.56E+02 < 5.05E+01 1.48E+02 < 6.96E+01 Fe-59* I Co-58* 1.42E+02 < 7.16E+01 1.89E+02 < 9.16E+01 Fe-59* I Co-58* 1.22E+02 < 5.50E+01 1.83E+02 < 4.91 E+01 59 I Co-60* I Zn-65* < 6.43E+01 < 1.23E+02 < 6.63E+01 < 1.15E+02 I Co-60* I Zn-65* < 6.79E+01 < 1.13E+02 < 6.53E+Ci1

< 1.56E+02 I Co-60* I Zn-65* < 6.43E+01 < 1.53E+02 < 8.87E+01 < 1.34E+02 I Co-60* I Zn-65* < 5.59E+01 < 1.08E+02 < 4.96E+01 < 1.39E+02 I Cs-134* I < 5.75E+01 < 7.39E+01 I Cs-134* I < 6.51 E+01 < 8.23E+01 I Cs-134* I < 6.08E+01 < 4.84E+01 I Cs-134* I < 4.08E+01 < 5.74E+01 page 1 of 1 Fish [a] Station 08 Cs-137* < 5.63E+01 < 4.22E+01 Station 25** Cs-137* < 7.02E+01 < 8.22E+01 catfish [b] Station 08 Cs-137* < 7.94E+01 < 6.35E+01 Station 25** Cs-137* < 4.32E+01 < 5.84E+01 I I I DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2015 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 Compaiison 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 2015 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 2015 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 prese.nted in Table 3-2. Figure 4-1 shows the 1 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 CaS04:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs. This will continue to be monitored.

60 9.0 6.0 -+-Env i ronmental TLD 2.0 +--------------------

Sector TLD 1.0 +--------------------

A P 0 --.-verage re p 0.0 l.O co 0 N '<!' l.O co 0 N '<!' l.O 00 0 N '<!' '° 00 00 00 C7'I C7'I C7'I C7'I C7'I 0 9 0 0 9 .-I .-I .-I .-I .-I I C: C: C: C: C: C: I C: C: C: C: C: C: I c: c: c: c: c: ...., ...., ...., ...., ...., ...., ...., ...., ...., ...., ...., Figure 4-1 TLD (mrem/Standard Month) Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location.

The average level of these 32 sector TLD locations (two badges at each location) was 4.2 mR/standard month with a range of 1.0 to 9.8 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61.

This value was 7.2 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 3.3 mR/standard month with a range of 0.9 t o 6.2 mR/standard month. The average annual reading for these locations was 2.8 mR/ standard month with a range from 1.3 to 4.2 mR/ standard month. The control location showed a quarterly average of 3.0 mR/standard month with a range of 2.5 to 3.1 mR/standard month. Its annual reading was 3.0 mR/ standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.0 mR/standard month with EPSP-9/ 10 having the 61 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 3.0 mR/ standard month, while Station C-1/2 and C-5/6 had a quarterly average of 2.6 mR/standard month with a range of 1.3 to 3.7 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/ standard month. 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 continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide.

In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady. During the preoperational period of July 1, 197 4 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m3 to a high of 0.75 pCi/m3. 0.12 0.1 -E 0.08 ::i 0.06 0 0.04 c.. 0.02 0 00 Ol 00 00 t c ('i] ('i] --, --, tj" L{) <D r--00 c c c c c roromcuro

"""") """') """') """") """") Ol 0 9 c c ('i] ('i] --, --, -Control Sta. 24 Average Pre-Op 9 8 t3 9 9 c c t c c t ('i] ('i] ('i] ('i] ('i] ('i] """") """") """') """') ""'") """') r-00 0 0 t t ('i] ('i] --, --, -Indica t or --Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 62 <:<") '<!" lf) ' ' ' c c c ('i] ('i] ('i] --, --, --,

O.OOE+OO N N rri rri rri rri rri rri ,...; ,...; ,...; ,...; ,...; ,...; ,...; ,...; ' u ' .'.__ >. ' Qo ' ... c c ... u Q) ro ro ro ::J ::J u 0 0 2 2 ...., <! 0 rri o;;j" o;;j" o;;j" o;;j" o;;j" o;;j" o;;j" ,...; ,...; ,...; ,...; ,...; ,...; ,...; ,...;

I a.>

z-.2<!...., V>Z -+-Control St ation -Indicator St ations o;;j" ,...; u Q) 0 lf) lf) ,...; ,...; ..0 ' '--Q) a. LL <! lf) lf) lf) ,...; ,...; ,...; >. ' 6. ro ::J Q) 2 ...., !/) Figure 4-3 2014 Gross Beta in Air Particulates (pCilm 3) 4.3 Airborne Radioiodine lf) lf) <.D ,...; ,...; ,...; ' u ' ... c u Q) ro 0 0 ...., Charcoal cartridges are used to collect airborne radioiodine.

Once a week the samples are collected and analyzed.

The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl and the effect of the Fukushima Daiichi event. 4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma 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.

63 4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations.

There has been no detection of these fission products at any of the indicator or control stations in recent years. 4.6 Soil Soil samples, which are collected every three years from twelve stations, were not collected in 2015. 4. 7 Precipitation A sample of rain water was collected monthly at on-site station 0 lA and anal y zed for gross beta activity and H-3. The results are presented in Table 3-7. Twelve precipitation samples were obtained in 2015. 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 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 2015 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-13 7 has been detected sporadicall

y. These occurrences were attributed to residual global fallout from past atmospheric weapons testing. Naturall y occurring K-40 was detected in all samples. 64 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 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 plant related isotopes were identified in any Vegetation sample during 2015. 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, I-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. 65 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 3350 pCi/liter and a range of 2150 to 4840 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. 4500 4000 3500 ...J 3000 -u Q. 2500 2000 1500 1000 River Water ........ .........

i..-. ......... ......... .......... .........

1-ml-2000 1500 1000 Figure 4-4 Tritium in River water -R e quired LLD 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 occurrmg gamma emitting radioisotopes, including iodine 66 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 3450 pCi/liter with a range of 2110 to 6730 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. Figure 4.5Tritium in Surface Water 10000 1000 ....I t;100 ,__ _____________________ .... ,--Required LLD Q. 10 1 r--a> .... M LO r--0 N "<t" <.D r--r--co co co a> a> a> I .!. >-...!.. t; ..6 >-I c <.> "S c.. ro ro ro Q) Q) ro Q) ...., 2 2 ...., 0 0 u. 2 ...., (/) 4.13 Bottom Sediment co .... M LO r--a> a> 0 0 0 0 0 > I .!. I I > ..0 c c.. 0 Q) c.. Q) 0 z u. ct: ...., (/) z N "<t" .... .... I .!. c ro ro ...., 2 <.D .... I c ...., co .... I O> ct: Average Pre-op -+-Tritium 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 i n bottom sedimen t could i nd i rectly l ead to i ncreasing radioactivity levels in fi sh. 67 Sediment samples were collected during March and October from each of three locations and were anal y zed 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 2015. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented.

During the operational period sediment samples were also analyzed by gamma spectroscop

y. 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 2015. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and i s attributable to fallout from past bomb tests. A number of naturally occurring rad i oisotopes were detected in these samples at background levels. 1600 1400 1200

() 800 a. 600 400 200 0 i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. i..'.. cu ro m ('iJ ID crJ ro ro <"U ('iJ ('iJ ro m C'iJ ('IJ cu C'O ('iJ m cu C'iJ cu cu aJ ('iJ co ('iJ ro ro ro ro m ro 2222222 2 2222222222222222222222222 Figure 4-6 Cs-137 in Sediment/Silt 4.14 Shoreline Soil -+-Sta ti on-8 -station-9 Control-Sta-09A -*-Station-11 S hor e l i ne soil/ sedimen t, unl i ke bottom sediment , ma y pro v ide a dir e ct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of 68 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. 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 2015 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 deteeted.

Cs-137 was measured in pre-operational environmental fish samples. 69

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2015 -North Anna Location 14B,15,16,23, 26 STAOlA 14B,15,16,23, 26 14B,15;16,23, 26 14B,15,16,23, 26 09A E 10/42 Description Vegetation

AP/Char Vegetation Vegetation Vegetation Surface Water Sector TLD's 14B,15,16,23, Vegetation 26 14B,15,16,23, Vegetation 26 STA06 *AP/Char Date of Sampling 01/13/15 01/28/15 02/12/15 03/10/15 04/14/15 06/22/15**

09/29/15 11/12/15 12/08/15 12/29/15 Reason( s) for Loss/Exception Seasonal unavailability Sampler not running/ replaced.

Minimum volume not met. Seasonal unavailability Seasonal unavailability Seasonal unavailability LA-140 LLD of 15 pCi/L not met. LLD. Achieved was 18 pCi/L TLD's missing. 500 kV tower replaced Seasonal unavailability Seasonal unavailability Air sampler was running but not flowing. Minimum volume not met. **Listing is a correction due to omission from 2012 Environmental Report *AP/Char denotes an air particulate and charcoal sampling station. 70 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 10CFR50, Appendix I", October, 1977. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 2?1h Edition, Volume 1, February 1992. NUREG/CR-4007, "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984. 71 \_

.. APPENDICES 72 APPENDIX A: LAND USE CENSUS Year 2015 '( 73 January 1 to December 31, 2015 Direction Distance (miles) Nearest Site Boundarn N 0.9 NNE 0.9 NE 0.8 ENE 0.8 E 0.8 ESE 0.9 SE 0.9 SSE 0.9 s 0.9 SSW 1 SW 1.1 WSW 1.1 w 1.1 WNW 1 NW 1 NNW 0.9 LAND USE CENSUS North Anna Power Station Louisa County, Virginia Nearest Nearest Resident Garden(> 50m2) 1.3 1.76 0.9 1.22 0.9 1.6 2.37 2.4 1.3 2.04 1.7 1.7 1.4 1.54 1.0 1.0* 1.03 1.14 127 1.33 1.65 1.65 1.62 NONE 1.5 1.93 1.1 2.67 1.0 1.96 1.0 1.22 74 Nearest Nearest Nearest Meat Milch Milch Animal Cow Goat 2.9 NONE NONE 3.1 NONE NONE 1.6 NONE NONE 2.65 NONE NONE 3.5 . NONE NONE NONE NONE NONE 1.4 NONE NONE 1.6 NONE NONE 2.0 NONE NONE 2.0 NONE NONE NONE NONE NONE 1.62 NONE NONE 4.4 NONE NONE 4.98 NONE NONE NONE NONE NONE 2.3 NONE NONE

.. _ 2014 to 2015 Land Use Census Changes 2014 2015 Nearest Direction Distance Distance Resident NONE Site Boundary NONE Garden N 1.78 1.76 SSE 1.0 1.0* s 1.02 1.14 WNW 2.67 2.67* Meat Animal WSW 2.22 *NONE Milch Cow NONE Milch Goat NONE *Change in physical address only. Distance remains the same as previous.

75 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR2015 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 Progra!h (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:

76 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 ql1arter Charcoal for I-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 uranium during the 2nd quarter DOE, Water and soil for gamma, Iodine-131, U-233/234, U-238, transuraniCs, tritium, Fe-55, Ni-63, Sr-90 and Tc-99 analyses during the 1st quarter. Water for gross alpha and beta during the 1st and 3rd quarters.

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

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

77 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, 131 out of 139 analyses performed met the specified acceptance criteria.

Eight *analyses (AP -Cr-51, U-234/233*, Gr A, Sr-90; Soil Sr-90; Water -Ni-63 and U natural; Vegetation .s*r-90 samples) did not meet the specified acceptance criteria for" the following reasons: 1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the *known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.20 was exceeded.

The air particulate sample is counted on a shelf (above the detector), which is the ideal geometry for this sample. But due to the fact that Cr-51 has the shortest half-life and the weakest gamma energy of the miXed nudide sample, this geometry produces a larger error for the Cr-51. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1. 19, which would be considered acceptable.

NCR 15-18 2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq.kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the . sample. NCR 15-13 ,. 3.

Teledyne Brown Engineering's MAPEP March 2015 air *particulate U-234/233 result of 0.0211 Bq/sample was higher than the known value of 0.0155 Bq/sample, exceeding the upper acceptance range of 0.0202 Bq/sample.

. Due to the extremely low activity, it was. difficult to quantify the U-:234/233

.. Taking into consideration the uncertainty, the.activity of U-234/233 overlaps with the known value, which is statistically considered the same value. NCR 15-13 4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Bq/ sample was lower . 78

.than the known value of 1.77 Bq/sample, *exceeding the lower acceptance range of 0.53 Bq/ sample. The efficiency used for gross alpha is made from a non-attenuated alpha standard.

The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency.

In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters. NCR

5. Teledyne Brown Engineedng's MAPEP September water Ni-63 result of 11.8 +/- i0.8 Bq/L was higher than the known value of 8.55 Bq/L, .exceeding the upper acceptance range of 11. 12 Bq/ L. The original sample was run with a 10 mL aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 mL produced an acceptable result of 8.81 Bq/L. NCR 15-21 6. Teledyne Brown Engineering's MAPEP September air partiCulate Sr-90 result of 1.48 Bq/ sample was lower than the known value of 2.18 Bq/ sample, exceeding the lower acceptance range of 1.53 Bq/sample.

In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in *. incomplete*

removal of the isotope of interest for the laboratories analyzing the cross checks. We feel this is possibly the case with this sample. NCR 15-21 7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Bq/ sample was lower than the known value of 1.30 Bq/ sample, exceeding the 16wer acceptance range of 0.91 Bq/sample.

In the past, MAPEP has added substances (unusual compounds found in DOE, complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. We feel that this is possibly the case with this sample .. NCR 15-21 8. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L. The technician failed to dilute the original sample, but used the entire 12 mL sample. When recalculated using the 12 mL aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19

79 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; theknown values supplied by the providers; pass or fail criteria.

80

.. Month/Year March 2015

June 2015 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c) Number Matrix Nuclide Units Value (a) Value (b) *TSE/Analytics E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 Sr-90 pCi/L 12.2 17.4 0.70. E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 Ce-141 pCi/L 104 113 0.92 Cr-51 pCi/L 265 276 0.96 Cs-134 pCi/L 138 154 0.90 Cs-137 pCi/L 205 207 0.99 Co-58 pCi/L

178 183 0.97 Mn-54

pCi/L 187 188 0.99 Fe-59 pCi/L 182 177 1.03 Zn-65 pCi/L 345 351 0.98. Co-60 pCi/L 379 405 0.94 E11184 AP

pCi 107 85.0 1.26 Cr-51 pCi 261 224 1.17 Cs-134 pCi 74.6 77.0 0.97 Cs-137 pCi 99.6 102 0.98 Co-58 pCi 99.8 110 0.91 Mn-54 pCi 99.2 96.9 1.02 Fe-59 pCi 109 119 0.92 Zn.-65 pCi 188 183 1.03 Co-60 pCi 200 201 1.00 E11,183

Charcoal 1-131 pCi 82.9 85.4 0.97 E11185 Water Fe-55 pCi/L 1950 1900 1.03 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 Sr-90 pCi/L 14.3 12.7 1.13 E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 Cs-134 pCi/L 165 163 1.01 . Cs-137 pCi/L 143.0 125 1.14 *Co-58 pCi/L, 82.0 I 68.4 1.20 Mn-54 pCi/L 113 101 1.12 Fe-59 pCi/L 184 151 1.22 Zn-65 pCi/L 269 248 1.08 Co-60 pCi/L 208 193 1.08 E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 Cs-134 pCi 139 138 1.01 Cs-137 pCi 111 . 106 1.05 Co-58 pCi 54.0 57.8 0.93 81 *Evaluation (d) A w A A A A A A A A A A w A A A A A A A

A A A A A A w A A A A w A A N (1) A A A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVl.RONMENTAL SERVICES Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d) June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 *Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 *A Cr-51 pCi/L . 499 538 0.93 A Cs-134 pCi/L 208 212 0.98. A Cs-137 pCi/L 270 255 1,06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 .A Fe-59 pCi/L 255 226 1.13 A Zn-65 pCi/L 392 353 1.11 A Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22. w Cs-134. pCi 86.1 84.6 1.02 A Cs-137 pCi 93.0 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 *A Co-60 pCi 146 132 1.11 A E11291* Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 302 0.98 A Fe-59 pCi/kg 248 235 1.06 A 82 Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117' 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 . 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 .A Zn-65 pCi/L 261 248 1.05 A. Co-60 pCi/L 212 213 1.00 A E11357 AP Ce-141 pCi 89.9 84.0 1.07 A Cr-51 pCi 2.15 184 1.17 A Cs-134 pCi 103 105 0.98 A Cs-137 pCi 76.6 74.8 1.02 A Co-58 pCi 76.2 71.9 1.06 A Mn-54 pCi 91.4 94.4 0.97 *A Fe-59 pCi 78.6 70.3 1.12 A Zn-65 pCi 173 162 1.07 A Co-60 pCi 138 139 0.99 A E11422 AP Sr-89 pCi 98.0 96.9 1.01 A Sr-90 pCi 10.0 14.0 0.71 w E11356 Charcoal pCi 74.9 75.2. 1.00 A E11358 Water Fe-55 pCi/L 2.160 1710 1.26 w E11353 Soil Ce-141 .pCi/kg 252 222. 1.14 A Cr-51 pCi/kg 485 485 1.00 A Cs-134 pCi/kg 319 277 1.15 A Cs-137 pCi/kg 292 276 1.06 A Co-58 pCi/kg 193 190 1.02 A Mn-54 pCi/kg 258 250 1.03 A Fe-59 pCi/kg

218 186 1.17 A Zn-65 pCi/kg. 457 429 1.07 A Co-60 pCi/kg 381 368 1.04 A (1) AP Cr-51 -Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable.

NCR 15-18 (a) Teledyne Brown Engineering reported result. (b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to Analytics results. * * (d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.

vii-Acceptable with warning, reported result falls within 0. 70-0. 80 or 1.20-1. 30. N = Not Acceptable, reported result falls outside the ratio limits of< 0. 70 and > 1.30. 83 MonthNear March 2015 September 2015 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Value Number Media Nuclide* Units Value (a) (b) Range 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 -0.850 Ni-63 Sq/L 2.5 (1) Pu-238 Sq/L 0.0204 0.0089 (2) Pu-239/240 Sq/L 0.9 0.8 0.582 -1.082 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314 -582' Sr-90 Sq/kg 286 653 487 -849 15-RdF32 AP Sr-90 Sq/sample

-0.0991 (1) 0.0109 -U-234/233 Sq/sample 0.0211 0.0155 0.0202 U-238 Sq/sample 0.095 0.099 0.069 -0.129 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53 -3.01 Gr-S Sq/sample 0.7580 0.75 0.38 -1.13 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12 -9.52 Cs-137 Sq/sample 11.6 9.18 6.43-11.93 Co-57 Sq/sample

-0.0096 (1) Co-60 Sq/sample 6.53 5.55 3.89 -7.22 Mn-54 Sq/sample 0.0058 (1) Sr-90 Sq/sample 0.999 1.08 0.76 -1.40 Zn-65 Sq/sample

-0.108 (1) 15-MaW33 Water *Am-241 Sq/L 1.012 1.055 0.739 -1.372 Ni-63 Sq/L 11.8 8.55 5.99 -11.12 Pu-238 Sq/L 0.727 0.681 0.477 -0.885 Pu-239/240 Sq/L 0.830 0.900 0.630 -1.170 15-MaS33 Soil

Ni-63 Sq/kg 635 682 477 -887 Sr-90 Sq/kg 429 425 298 -553 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53 -2.83 U-234/233 Sq/sample 0.143 0.143 0.100-0.186 U-238 Sq/sample 0.149 0.148 0.104-0.192 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 Gr-S Sq/sample 1.34 1.56 0.78 -2.34 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 -7.54 Cs-137 Sq/sample 0.0002 (1) 84 Evaluation (c) A A A A A N (3) A N (3) A N (3) A A w A A A A A A N (4) A A A A N (4) A A A A A A

Co-57 Sq/sample 8.01 6.62 4.63 -8.61 Co-60 Sq/sample 4.97 4.56 3.19 -5.93 Mn-54 Sq/sample 8.33 7.68 5.38 -9.98 Sr-90 Sq/sample 0.386 1.30 0.91 -1.69 Zn-65 Sq/sample 6.07 5.46 3.82 -7.10 (1) False positive test. (2) Sensitivity evaluation.

(3) Soil Sr-90 -incomplete digestion of the sample resulted in low results; AP U-2341233

-extremely low activity was difficult to quantify AP Gr-A -the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21. * (a) Teledyne Brown Engineering reported result. (b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (c) DOEIMAPEP evaluation:

A=acceptable, W=acceptable with warning, N=not acceptable.

85 w A A N (4) A

MonthNear May 2015 011/01/2015 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported . Known Acceptance Number Media Nuclide Units Value (a) *Value (b) Limits Water Sr-89 pCi/L 45.2 63.2 51.1-71.2 Sr-90 pCi/L 28.0 41.9 30.8 -48.1 Ba-133 pCi/L 80.6 82.5 63.9 -90.8 Cs-134 pCi/L 71.7 75.7 61.8 -83.3 Cs-137 pCi/L 187 189 170 -210 Co-60 pCi/L 85.7 84.5 76.0 -95.3 Zn-65 pCi/L 197 203 183 -238 Gr-A pCi/L 26.1 42.6 22.1 -54.0 Gr-B pCi/L 28.8 32.9 21.3 -40.6 1-131 pCi/L 23.5 23.8 19.7 -28.3 U-Nat pCi/L 6.19 6.59 4.99 -7.83 H-3 pCi/L 3145 3280 2770 -3620 MRAD-22 Filter Gr-A pCi/filter 28.3 62.2 20.8 -96.6 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 -42.5 Sr-90 pCi/L 29.3 31.1 22.7 -36.1 Ba-133 pCi/L 31.5 32.5 25:9 -36.7 Cs-134 pCi/L 59.65 62.3 50.6 -68.5 Cs-137 pCi/L 156 157 141 -175 Co-60 pCi/L 70.6 71.1 64.0 -80.7 Zn-65 pCi/L 145 126 113-149 Gr-A pCi/L 38.2 51.6 26.9 -64.7 *Gr-B pCi/L 42.0 36.6 24.1 -44.2 1-131 pCl/L 24.8 26.3 21.9 -31.0 U-Nat pCi/L 146.90 56.2 45.7 -62.4 H-3 pCi/L 21100 21300 18700 -23400 MRAD-23 Filter Gr-A pCi/filter Lost during processing 86 Evaluation (c) N (1) N (1) A A A A .A A A A A A A A A A A

A A A A A A N (2) A (1) Yield on the high side of our acceptance range indicates possibility of calcium interference.

NCR 15-09 (2) Technician failed to dilute original sample. If dilulted, the result would have been 57.1, which fell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result. (b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) ERA evaluation:

A=acceptable.

Reported result falls within the Warning Limits. 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. 87 t . ,. VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 20, 2016 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Serial No.16-110 NAPS/JHL Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2, enclosed is the 2015 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 Robin Klearman at (540) 894-2436.

Very truly yours,

.1 Gerald T.

Site Vice President Enclosure Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE.Suite 1200 Atlanta, Georgia 30303-1257 Serial No.16-110 NAPS Annual Radiological Environmental Operating Report Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2015 to December 31, 2015 Prepared by Dominion, North Anna Power Station Prepared by: Reviewed by: Approved by:

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2015 to December 31, 2015 Jr. Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Aziz A. Maly . Supervisor Health Physics Technical Services Dominion North Anna Power Station Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2 Table of Contents 1. EXECUTIVE