ML15105A241

Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report

ML15105A241
Person / Time
Site:	North Anna
Issue date:	04/10/2015
From:	Gerald Bichof Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
15-177
Download: ML15105A241 (90)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 10, 2015 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.

NAPS/JHL 15-177 Docket Nos.

50-338/339 72-16 72-56 License Nos. NPF-417 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

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

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2, enclosed is the 2014 Annual Radiological Environmental Operating Report.

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

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

Very truly yours, Gerald T. Bischof Site Vice President Enclosure Commitments made in this letter: None S4A5 2-E p

'~4s

Serial No.15-177 NAPS Annual Radiological Environmental Operating Report cc:

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station

Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2014 to December 31, 2014 Prepared by Dominion, North Anna Power Station

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2014 to December 31, 2014 Prepared by:

Reviewed by:

Approved by:

Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Aziz A. Malyj Supervisor Health Physics Technical Services Dominion North Anna Power Station

• • ~~Robert B. Evans HE heisr Manager Radiological Protect n and Chemistry Dominion North Anna Power Station 2

Table of Contents

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

4

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

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

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

8

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

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

22 3.2 A nalytical Results of 2014 REM P Sam ples...................................................................

32

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

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

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

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

64 4.4 A ir Particulate G am m a...................................................................................................

64 4.5 A ir Particulate Strontium.................................................................................................

64 4.6 S o il........................................................................................................................................

6 4 4.7 Precipitation..........................................................................................................................

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

65 4.9 Food Products and V egetation........................................................................................

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

66 4.11 R iver W ater.........................................................................................................................

66 4.12 Surface W ater......................................................................................................................

67 4.13 Bottom Sedim ent................................................................................................................

68 4.14 Shoreline Soil......................................................................................................................

69 4.15 F ish......................................................................................................................................

7 0

5. PRO G RA M EX CEPTIO N S.....................................................................................................

71 REFEREN CES....................................................................................................................................

72 A PPEN D ICES.....................................................................................................................................

73 A PPEN D IX A : LAN D U SE CEN SU S......................................................................................

74 APPENDIX B:

SUMMARY

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

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2014 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP).

It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2. Radioactivity levels from January 1 through December 31, 2014, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to confirm that radiological effluent releases are As Low As Reasonably Achievable (ALARA), no undue environmental effects occur and the health and safety of the public are protected.

The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.

Radiation and radioactivity in the environment is monitored within a 25-mile radius of the station.

North Anna Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained.

Control samples are collected from areas that are beyond the measurable influence of North Anna Power Station or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.

Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline."

Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident, Fukushima Daiichi or natural variation.

Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and Teledyne Brown Engineering Environmental Services provided radioanalytical services.

Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy.

Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods.

4

Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The NRC also mandates a reporting level for certain radionuclides.

Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level.

Environmental radiation levels are sometimes referred to as a percent of the reporting level.

Analytical results are reported for all possible radiation exposure pathways to man.

These pathways include airborne, water, aquatic, terrestrial, and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates, and precipitation. The 2014 airborne results were similar to previous years.

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

Water and aquatic exposure pathway samples include precipitation, surface, river and well water, silt and shoreline sediments, and fish. The average tritium activity in surface water for 2014 was 2630 pCi/liter. No other plant related isotopes were reported in any surface or river water. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 2870 pCi/liter.

No plant related isotopes were detected in quarterly precipitation samples. Silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background.

No plant related isotope was identified in any sample.

Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels.

No plant related isotope was detected in the indicator or control locations in shoreline soil. No plant related isotope was detected in fish samples from either Lake Anna or the control location, Lake Orange.

Soil samples, which are collected every three years from twelve stations, were not collected in 2014.

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

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 2014, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2014 was 0.39 millirem. For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural background sources in the environment provide approximately 50% of radiation exposure to man, while medical uses provide approximately 48%.

By comparison, nuclear power contributes less than 0.1%.

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

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2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2014 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).

The North Anna Power Station of Virginia Electric and Power Company (Dominion) is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia. The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit has a gross electrical output of 1029 megawatts electric (MWe). Unit 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980.

An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.

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

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

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

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

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

Global Dosimetry Solutions is utilized for processing the TLDs. Teledyne Brown Engineering Environmental Services (TBE) is utilized for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations.

Measured values are compared with control levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes. Data collected prior to station operation is used to indicate the degree of natural variation to be expected.

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

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

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

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

This report documents the results of the Radiological Environmental Monitoring Program for 2014 and satisfies the following objectives of the program:

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

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

> To identify changes in radioactivity in the environment.

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

2.2 Sampling and Analysis Program Table 2-1 summarizes the 2014 sampling program for North Anna Power Station.

All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." The North Anna Radiological Monitoring Locations maps denote sample locations for North Anna Power Station. The locations are color coded to designate sample types. Table 2-2 summarizes the analysis program conducted by TBE for North Anna Power Station during the year 2014.

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TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Environmental Thermoluminescent Dosimetry (TLD)

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

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

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

"Aspen Hills" Elk Creek NAPS Access Rd.

Station 01 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-l 1/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 Distance 0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.36 Direction NE SSW WSW WNW NNE N

ESE SSE WNW WSW SSE NW N

N NNE NNE NE NE ENE ENE E

E ESE ESE SE SE SSE SSE S

Degrees 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Collection Frequency Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control 9

TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Environmental Thermoluminescent Dosimetry (TLD)

Location Elk Creek Church NAPS Access Rd.

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

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

1. 1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NAPS Sewage Treatment Plant Biology Lab Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA Station S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 1.55 0.24 5.30 0.60 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.52 2.54 0.07 2.21 7.30 22.00 7.10 11.54 TABLE 2-1 North Anna Power Station 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO.

Direction S

SSW SSW SW SW WSW WSW W

W WNW WNW NW NW NNW NNW SSE NW WSW WSW Degrees 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control Control Airborne Particulate and Radioiodine 01 O0A 03 04 05 05A 06 07 0.20 0.64 7.10 5.10 4.20 2.04 4.70 7.30 NE SE WSW WNW NNE N

ESE SSE 420 1380 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly 10

TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Airborne Particulate and Radioiodine Location End of Route 685 Route 700 "Aspen Hills" Orange, VA Station 21 22 23 24 TABLE North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)

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

Lake Anna (upstream)

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

Lake Anna (upstream)

(Route 669 Bridge)

North Anna River (downstream)

Waste Heat Treatment Facility (Second Cooling Lagoon)

NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 3.37 SSE 1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually 5.80 SE 1280 Semi-Annually Control Shoreline Soil Soil 11 08 01 02 03 04 3.37 SSE 1480 Semi-Annually 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years 11

TABLE 2-1 North Anna Power Station - 2014 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)

"Aspen Hills" 05A 06 07 21 22 23 24 2.04 4.70 7.30 1.00 1.00 0.93 22.00 N

ESE SSE WNW WSW SSE NW 110 1150 1670 3010 2420 1580 3250 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Orange, VA Control Milk Fish Lakeside Dairy Waste Heat Treatment Facility (Second Cooling Lagoon)

Lake Orange 12A 7.50 NW 3.37 SSE 16.5 NW 3100 Monthly 1480 Semi-Annually 3120 Semi-Annually 08 25 Control Food Products (Vegetation)

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

400 1330 3140 1580 1720 Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Control 12

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

(84 TLDs)

(12 TLDs)

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

Sr-89 Sr-90 0.07 0.01 0.05 0.06 (b)

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

(b) pCi/m3 pCi/m 3

pCi/m 3

pCi/m 3

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

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

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

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TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS River Water Ground Water (Well Water)

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

Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)

Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1.-131(d)

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

La-140(d)

LLD 15 2000 (b)

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

(b)

REPORT UNITS pCi/L pCi/L pCi/L pCi/L pCi/L Aquatic Sediment 150 180 (b)

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

Annually Precipitation Monthly Semi-Annual Composite 4

pCi/L pCi/L 15 30 15 15 30 30 15 15 18 Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180

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

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c)

LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

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

(b) 150 180 (b)

(b) 1 15 18 60 15 (b)

(b)

REPORT UNITS pCi/kg (dry) pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L Fish pCi/kg (wet) 130 260 130 130 260 130 150 Food Products (Broadleaf Vegetation)

Monthly, if available, or at harvest pCi/kg (wet) 60 80 60

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

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

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

IA 2

3 4

5 5A 6

7 8

(a)

(a)

(a)

(a)

(a)

(a)

(a)

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

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

D ESE Legend 174 S

SE*13145 I* Fixed Enwmmntal Monbin-A boi

• TLD Locabons Scale - WS mnch~

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

18

North Anna Environmental Map Fixed Environmental Sampling Location O

TLD Sampling Garden Residents Meat Animals Orlginui 191 byADC otlWxnroia. Imc. 64O GenealGrwnVfty AkMMiira. VA 22312. USE-D AM~PERMSSION. NO OINK Woroudlon maybe made w11hoq fm wdftkn pennisio of ADC.

C832ME 19

North Anna Environmental Map O Fied Environmental Sampling Location S

TLD Sampling

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

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

20

North Anna Environmental Map SFbied Environmental Sampling Location TLD Sampling Garden Residents O

Meat Animals Or~WtgIW 19 byADC fAtMmmnfl& Inc. 640G-wN Grfteei Nemdftla.VA2=231.USEDTH PERMSSKON. N~o oterrepdtxhn may be mad. vilout lI* wils pwniwimso oEADC 21

3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1.

This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM.

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

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

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

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 1 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD"'

Mean Reported Sampled (Unit)

Total (pCi/unit)

Range Name Distance Mean Mean Measure-Type INo.

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

(Sector TLDs)

Direct Radiation (mR/std. Month)

(Pre-operational TLDs)

Direct Radiation (mR/std. Month)

(Emergency Sector TLDs)

Direct Radiation (mR/std. month)

(Environmental TLDs)

Direct Radiation (mR/std. Month)

(Annual TLDs)

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

Gamma Dose 256 2

4.0(256/256)

(1.3-8.0) 29/61 0.52 mi.

NW 7.1(8/8)

(5.6-7.6) 3.15(16/16)*

(2.6-3.7) 0 Gamma 32 Dose 2

2.4(16/16)

C-1/2 11.54 mi.

(1.6-3.4)

WSW 2.7(8/8) 3.15(16/16)*

(2.6-3.7)

(2.2-3.4) 0 Gamma Dose 40 2

4.9(40/40)

EPSP-0.37 mi.

7.1(8/8)

(3.0-8.2) 09/10 ENE (6.2-8.2) 3.15(16/16)*

(2.6-3.7) 0 Gamma 48 Dose 2

3.2(44/44) 23 0.93 mi.

5.0(4/4) 2.7(4/4)

(2.5-3.1) 0 (1.6-5.8)

SSE (4.3-5.8)

Gamma Dose Gross Beta 12 2

2.9(11/11)

(2.0-4.1) 06 4.70 mi.

4.1(1/1)

ESE (4.1) 2.8(1/1)

(2.8) 0 676 0.01 15.4(619/624)

(6.75-29.8) 23 0.93 mi.

SSE 17.4(52/52)

(10.6-28.5) 16.2(52/52)

(10.4-27.2) 0 Air Iodine (pCi/m 3) 1-131 676 0.07 (0/624)

N/A N/A.

N/A N/A 0

Airborne Particulates (IE-03 pCi/m 3 )

Gamma 52 Be-7 52 116(48/48) 01 0.2 mi.

129(4/4) 131(4/4)

(83.9-164)

NE (116-135)

(119-151) 0 0

Cs-134 52 0.05 (0/48)

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

(1) mR/std month for TLDs

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

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

Total (pCi/unit)

Mean Name Distance Mean Mean Measure-

---Ptwy--_

Type No.

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

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

(0/12)

(0/12)

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

(0/1)

(0/1) 0 0

0 Sr-90 13 Soil*

Triennial (pCi/Kg) (dry)

Gamma 12 K-40 12 Cs-134 12 Cs-137 12 Ra-226 1 _

Th-228 12 Th-232 12 Sr-89 1,

Sr-90 12 Precipitation Monthly (pCi/liter)

Gross 12 Beta H-3 2

Semiannual 2

Gamma Be-7 2

Mn-54 2

Fe-59 2

Co-58 2

• Soil Samples required triennially.

N/A N/A 150 180 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 3.46(9/12)

(1.64-11.2)

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

0 0

0 0

0 0

0 0

0 4

3.46(10/12)

(1.64-11.2) 2000 (0/2) 01A 0.64 mi.

SE N/A N/A (0/2) 15 (0/2) 30 (0/2) 15 (0/2)

Samples not obtained in 2014..

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

0 0

0 24

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 3 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Tot (pCi/unit)

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

I I

_II Precipitation (pCi/liter)

Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Th-228 2

2 15 30 30 15 10 15 18 (0/2)

(0/2)

(0/2)

(0/2)

(0/2)

(0/2)

(0/2)

(0/2)

(0/2)

(0/2)

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

0 0

0 0

0 0

0 0

0 25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 4 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/utit)

Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range I

Direction Range Range ments Milk (pCi/liter)

Gamma 12 K-40 12 1340(12/12) 12A 7.50 mi.

1340(12/12)

(1210-1460)

(0/12)

NW (1210-1460) 1-131 12 1

Cs-137 12 18 (0/12)

Ba-140 12 60 (0/12)

La-140 12 15 (0/12)

N/A N/A.

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

0 0

0 0

0 0

Sr-89 4

(Quarterly)

(0/4)

(0/4)

Sr-90 (Quarterly) 4 26

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 5 of 9 All Indicator Indicator Location Control Non-Medium or Analsis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)

Total (pCi/unit)

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

Gamma Be-7 35 35 K-40 35 1320(24/24)

(343-3160) 6280(24/24)

(3830-8800)

(0/24)

(0/24) 15 1.37mi SE 14B 1.22mi NNE N/A N/A N/A N/A N/A N/A 1520(6/6)

(487-3160) 7220(6/6)

(4910-8300)

N/A N/A 1330(6/6)

(681-2450) 6110(6/6)

(5920-8360)

(0/6)

(0/6) 0 0

0 0

0 1-131 Cs-134 35 35 60 60 Cs-137 35 80 (0/24)

N/A (0/6)

Ground Well Water (pCi/liter)

Tritium 4

2000 Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 15 30 15 15 30 30 15 10 (0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

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

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 6 of 9 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled Total (pCi/un Mean Name Distance Mean Mean Measure-(Unit)

Type No.

I')

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

Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 15 (0/4) 18 (0/4) 60 (0/4) 15 (0/4)

(0/1)

(0/1) 2000 2870(4/4)

(2430-3050)

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

SE N/A N/A N/A N/A N/A N/A 2870(4/4)

(2430-3050)

River Water (pCi/liter) 15 30 15 15 30 (0/12)

(0/12)

(0/12)

(0/12)

(0/12)

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

(0/12)*

(0/12)*

(0/12)*

(0/12)*

(0/12)*

(0/12)*

(0/12)*

(0/12)*

(0/12)*

(0/12)*

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 Zr-95 12 30 (0/12)

N/A N/A Nb-95 1-131 12 12 15 1

(0/12)

(0/12)

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

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

N/A N/A

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 7 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (PCi/unit)

Mean Name Distance Mean Mean Measure-(Unit)

Type INo.

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

Surface Water (pCi/L)

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

1 8

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

(0/1)

(0/1) 2000 2630(3/4)

(1810-3070)

N/A N/A 15 30 15 15 (0/12)

(0/12)

(0/12)

(0/12)

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

SSE N/A N/A N/A N/A N/A N/A N/A 2630(4/4)

(1810-3070)

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

(0/12)*

(0/1)*

(0/1)*

(0/4)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12)

(0/12) 0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 Zn-65 24 30 (0/12)

Zr-95 24 30 (0/12)

Nb-95 24 30 (0/12) 1-131 24 1

(0/12)

Cs-134 24 15 (0/12)

Cs-137 24 18 (0/12)

Ba-140 24 60 (0/12)

La-140 24 15 (0/12)

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

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

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2014 Docket No. 50-338/339 Page 8 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)

Mean Name Distance Mean Mean Measure-(Unit)

Type No.

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

Sediment Silt (pCi/kg)

Sr-89 Sr-90 l

1 (0/1)

(0/1)

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

(0/1) 0 0

Gamma 6

K-40 6

12100 (4/4)

(2340-16000) 11 5.80 mi.

22550 (2/2)

SE (18300-26800)

N/A N/A N/A Cs-134 6

150 (0/4) 30800(2/2)

(27800-33800)

(0/2)

(176) 112(1/2)

(112) 1970(1/2)

(1970)

Cs-137 6

180 Ra-226 6

(0/4) 2530(4/4)

(2370-2690) 766(4/4)

(98.5-1840) 1425 (2/4)

(1120-1730)

N/A N/A.

N/A Th-228 6

Th-232 6

11 5.80 mi.

2530(2/2)

SE (2370-2690) 11 5.80 mi.

1430(2/2)

SE (1020-1840) 11 5.80 mi.

1425(2/2)

SE (1120-1730) 0 0

0 0

0 0

0 764(2/2)

(448-1080) 642(2/2)

(414-869)

(0/1)

(Annually)

Sr-89 3

(0/2)

(0/2)

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

Shoreline Soil (pCi/kg) (dry)

Gamma 2

K-40 2

1028.5(2/2)

(527-1530) 08 3.37 mi.

1028.5(2/2)

SSE (527-1530)

(0/1)

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

0 Cs-134 2

150 (0/2)

Cs-137 2

180 (0/2)

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

NA (0/2) 0 0

0 Ra-226 2

(0/2)

N/A N/A (0/2) 30

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

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

Mean Name Distance Mean Mean Measure-(Unit)

Type No.

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

Th-228 2

Th-232 2

148(2/2)

(147-149) 265 (1/2)

(265)

(0/1)

(0/1) 08 3.37 mi.

SSE 08 3.37 mi.

SSE N/A NA N/A NA 148(2/2)

(147-149) 265(1/2)

(265)

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

0 0

0 (Annually)

Sr-89 Sr-90 1

Fish (pCi/kg) (wet)

Gamma 8

K-40 8

Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 8

8 8

8 8

8 8

130 260 130 130 260 130 150 1725(4/4)

(1400-1960)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4) 8 3.37 mi.

SSE N/A NA N/A NIA N/A NA N/A NA N/A NA N/A NA N/A NA 1725(4/4)

(1400-1960)

N/A N/A N/A N/A N/A N/A N/A 1930(4/4)

(1370-2410)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4)

(0/4) 0 0

0 0

0 0

0 0

31

3.2 Analytical Results of 2014 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.

The data reported in the following tables are strictly counting statistics. The reported error is two times the standard deviation (2y) of the net activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered true positives when the measured value exceeds both the MDC and the 2a error.

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

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

Data are given according to sample type as indicated below.

1.

Gamma Exposure Rate

2.

Air Particulates, Gross Beta Radioactivity

3.

Air Particulates, Weekly 1-131

4.

Air Particulates, Quantitative Gamma Spectra

5.

Air Particulate Strontium

6.

Soil

7.

Precipitation

8.

Cow Milk

9.

Food Products and Vegetation

10.

Well Water

11.

River Water

12.

Surface Water

13.

Bottom Sediment/Silt

14.

Shoreline Soil

15.

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

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

32

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESUL mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Station 3/26/2014 6/24/2014 9/30/2014 3/26/2014 6/24/2014 9/30/2014 12/30/2014 N-1 N-33 N-2 N-34 NNE-3 NNE-35 NNE-4 NNE 36 NE-5 NE-37 NE-6 NE-38 ENE-7 ENE-39 ENE-8 ENE-40 E-9 E-41 E-1 0 E-42 ESE-11 ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 5.1 5.0 3.4 3.1 6.4 7.6 4.4 3.7 4.3 5.3 3.0 2.9 4.9 4.4 2.2 2.0 4.9 4.0 4.0 3.7 3.5 2.9 3.3 4.0 3.8 4.8 5.9 6.2 5.3 4.9 2.1 2.2 4.6 4.2 3.0 2.9 6.1 5.7 3.3 3.8 4.1 4.4 2.8 3.1 4.9 5.6 3.0 2.5 4.6 4.1 3.9 4.1 4.0 3.2 4.6 4.8 3.8 3.7 5.2 5.5 4.3 4.2 2.5 2.8 4.5 3.9 3.1 2.5 6.2 6.7 3.7 4.4 3.6 5.2 3.5 2.8 5.3 4.7 2.9 2.5 5.1 5.0 4.6 4.6 4.3 4.4 3.7 4.4 4.2 4.4 6.1 5.8 4.9 4.9 2.7 2.7 4.2 4.9 2.4 2.4 7.2 7.2 3.6 3.6 4.1 3.9 3.2 2.7 4.3 5.6 2.0 1.8 5.0 4.6 4.9 4.6 3.6 3.1 4.6 3.6 4.0 3.7 6.2 7.0 4.3 4.2 2.4 2.3 TS Quarterly*

Average

+/- 2 s.d.

4.6

+/- 0.9 2.9

+/- 0.7 6.6

+/- 1.3 3.8

+/- 0.8 4.4

+/- 1.2 3.0

+/- 0.5 5.0

+/- 1.0 2.4

+/- 0.9 4.7

+/- 0.8 4.3

+/- 0.9 3.6

+/- 1.1 4.1

+/- 1.1 4.1

+/- 0.8 6.0

+/- 1.1 4.6

+/- 0.8 2.5

+/- 0.5 Page 1 of 4

• Average of collocated TLDs.

33

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULT mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Station 12/31/2013 3/26/2014 6/24/2014 9/30/2014 3/26/2014 6/24/2014 9/30/2014 12/30/2014 S-17 S-49 S-18 S-50 SSW-19 SSW-51 SSW-20 SSW-52 SW-21 SW-53 SW-22 SW-54 WSW-23 WSW-55 WSW-24 WSW-56 W-25 W-57 W-26 W-58 WNW-27 WNW-59 WNW-28 WNW-60 NW-29 NW-61 NW-30 NW-62 NNW-31 NNW-63 NNW-32 NNW-64 4.6 5.4 1.9 1.8 5.7 7.0 1.9 1.8 6.5 4.0 3.4 4.6 4.5 4.9 3.8 4.4 6.5 7.2 2.2 2.4 2.7 2.4 3.3 3.5 7.3 6.7 1.6 1.7 3.1 3.1 4.1 4.1 4.9 3.5 2.1 2.1 5.6 5.4 1.8 2.1 4.6 4.7 3.8 4.3 3.6 4.0 4.4 3.8 7.2 7.3 3.6 2.5 3.0 3.2 2.4 2.6 5.6 7.1 1.7 2.0 2.9 3.6 3.1 3.6 3.5 4.3 2.2 2.1 6.1 6.1 2.4 1.9 3.9 4.2 4.4 4.8 4.2 4.1 4.1 4.6 6.7 6.8 2.8 3.0 3.8 2.2 3.1 3.4 7.2 7.4 1.3 2.2 3.0 3.0 3.8 3.8 4.0 4.3 2.9 1.9 5.9 5.6 2.0 1.9 4.4 3.5 3.5 3.4 5.0 3.6 3.6 4.3 7.7 6.8 2.5 2.3 3.2 2.5 2.4 3.0 7.6 8.0 1.6 1.4 4.1 3.8 3.8 3.4

-S Quarterly*

Average

+/- 2 s.d.

4.3 +/-

1.3 2.1 +/-

0.7 5.9 +/-

1.0 2.0 +/-

0.4 4.5 +/-

1.8 4.0 +/-

1.1 4.2 +/-

1.1 4.1 +/-

0.7 7.0 +/-

0.8 2.7 +/-

0.9 2.9 +/-

1.1 3.0 +/-

0.9 7.1 +/-

1.4 1.7 +/-

0.6 3.3 +/-

0.9 3.7 +/-

0.7 4.0 +/-

1.5 Page 2 of 4 Mean

• Average of collocated TLDs.

34

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Station 12/31/2013 3/26/2014 6/24/2014 9/30/2014 3/26/2014 6/24/2014 9/30/2014 12/30/2014 Page 3 of 4 C-1 C-2 C-3"*

C-4"*

C-5 C-6 C-7"*

C-8"*

2.4 3.2 2.7 3.4 1.7 2.8 3.2 3.7 2.8 2.3 2.8 2.9 2.2 1.8 3.2 3.0 3.9 3.9 3.0 3.3 5.5 5.3 3.9 3.3 7.0 6.2 3.1 3.4 3.2 3.5 2.3 2.6 3.1 3.6 4.3 4.6 4.1 3.8 5.0 5.6 4.1 3.2 7.2 6.3 2.4 2.2 2.6 2.6 1.7 1.6 3.5 3.0 4.3 4.0 4.6 3.3 4.9 5.2 3.3 3.2 7.9 7.0 2

7 Quarterly*

Average

+/- 2 s.d.

2.7

+/-

0.9 3.0

+/-

0.7 2.1

+/-

0.9 3.3

+/-

0.5 2.4

+/-

1.1 3.1

+/-

0.7 1.2

+/-

0.5 3.8

+/-

1.2 5.4

+/-

0.9 3.7

+/-

1.0

.1

+/-

1.4 EPSA-01 ***

EPSA-02***

EPSF-03***

EPSF-04***

EPSR-05***

EPSR-06***

EPSJ-07***

EPSJ-08***

EPSP-09***

EPSP-1 0**

4.4 4.0 4.5 4.1 5.7 6.3 3.7 4.6 7.3 8.2 Mean 4.9

+/- 2.8

• Average of collocated TLDs.

• • Control Station

• • • Emergency Plan TLDs.

35

TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 4 of 4 First Quarter Station 12/31/2013 3/26/2014 STA-01 3.8 STA-02 2.1 STA-03 1.7 STA-04 2.2 STA-05 3.3 STA-05A 2.1 STA-06 4.1 STA-07 3.1 STA-21 2.7 Second Quarter 3/26/2014 6/24/2014 4.2 2.2 2.7 2.8 2.9 3.4 4.3 2.6 2.7 Third Quarter Fourth Quartei 6/24/2014 9/30/2014 9/30/2014 12/30/2014 4.0 4.0 2.4 1.6 2.5 1.7 2.0 2.1 3.2 2.2 3.0 3.2 4.4 4.3 3.2 3.1 3.1 2.2 Quarterly Average

+/- 2 s.d.

4.0

+/-

2.1

+/-

2.2

+/-

2.3

+/-

2.9

+/-

2.9

+/-

4.3

+/-

3.0

+/-

2.7

+/-

AnnualTLD 0.3 0.7 1.1 0.7 1.0 1.1 0.3 0.5 0.7 1.0 1.4 0.3 1.0 4.0 2.3 2.4 2.0 2.9 2.2 4.1 2.6 2.5 3.4 3.8 2.8 2.9 STA-22 STA-23 STA-24*

5.0 5.3 2.5 3.8 4.3 4.5 5.8 2.7 3.1 Mean - Indicator Locations 4.4 4.3 2.5 4.4 5.0 2.7 3.2

+/-

+/-

+/-

+/-

+/-

1.5

• Control 36

Table 3-3 Air Particulate Gross Beta Radioactivity

[10-3 pC i/m3]

page 1 of 4 Period Ending 01/08/14 01/14/14 01/21/14 01/28/14 02/04/14 02/11/14 02/18/14 02/26/14 03/05/14 03/12/14 03/19/14 03/26/14 04/02/14 04/08/14 04/16/14 04/22/14 04/29/14 05/06/14 05/13/14 05/21/14 05/27/14 06/04/14 06/10/14 06/18/14 06/24/14 07/01/14 Station Station Station Station Station Station I

I I

I I

I I

Station 07 I

2.27E+01 2.05E+01 1.45E+01 1.37E+01 2.15E+01 2.50E+01 2.01 E+01 1.31 E+01 1.36E+01 1.36E+01 1.55E+01 1.21 E+01 1.37E+01 1.98E+01 1.12E+01 1.06E+01 1.68E+01 1.35E+01 1.47E+01 7.98E+00 1.30E+01 1.52E+01 1.36E+01 1.49E+01 3.22E+00 3.46E+00 2.78E+00 2.63E+00 3.18E+00 3.30E+00 3.05E+00 2.35E+00 2.82E+00 2.80E+00 2.80E+00 2.88E+00 2.50E+00 3.23E+00 2.46E+00 2.46E+00 2.86E+01 2.38E+00 3.06E+00 2.23E+00 3.07E+00 2.50E+00 2.93E+00 2.71 E+00 1.29E+01 1.26E+01 1.39E+01 1.49E+01 1.55E+01 2.44E+01 1.63E+01 1.16E+01 2.25E+01 1.86E+01 1.37E+01 1.27E+01 1.31E+01 1.25E+01 1.44E+01 1.09E+01 1.19E+01 1.09E+01 1.89E+01 1.48E+01 1.41E+01 1.01E+01 9.71 E+00 1.23E+01 1.18E+01 1.09E+01 2.36E+00 3.03E+00 2.75E+00 2.69E+00 2.88E+00 3.28E+00 2.88E+00 2.25E+00 3.25E+00 3.08E+00 2.74E+00 2.69E+00 2.70E+00 2.92E+00 2.53E+00 2.71 E+00 2.47E+00 2.51 E+00 2.97E+00 2.45E+00 3.03E+00 2.35E+00 2.72E+00 2.36E+00 2.88E+00 1.32E+01 1.64E+01 1.47E+01 1.12E+01 1.79E+01 2.50E+01 2.18E+01 1.08E+01 1.88E+01 1.68E+01 1.48E+01 1.47E+01 1.09E+01 1.09E+01 1.31E+01 1.62E+01 1.39E+01 7.65E+00 1.12E+01 1.08E+01 1.25E+01 8.88E+00 1.30E+01 1.14E+01 1.30E+01 2.44E+00 3.25E+00 2.79E+00 2.48E+00 3.OOE+00 3.31 E+00 3.12E+00 2.22E+00 3.08E+00 2.99E+00 2.76E+00 2.87E+00 2.67E+00 2.82E+00 2.47E+00 3.03E+00 2.56E+00 2.35E+00 2.55E+00 2.21E+00 2.93E+00 2.28E+00 2.93E+00 2.29E+00 2.93E+00 2.53E+00 1.55E+01 1.76E+01 1.50E+01 1.69E+01 1.69E+01 2.98E+01 2.61E+01 9.82E+00 2.71E+01 2.25E+01 1.59E+01 1.51E+01 1.76E+01 1.40E+01 1.52E+01 1.65E+01 1.73E+01 9.20E+00 1.72E+01 1.76E+01 1.25E+01 1.03E+01 1.54E+01 1.54E+01 1.61E+01 1.58E+01 2.53E+00 3.30E+00 2.81E+00 2.80E+00 2.95E+00 3.51E+00 3.37E+00 2.13E+00 3.45E+00 3.27E+00 2.87E+00 2.78E+00 2.97E+00 3.01 E+00 2.57E+00 3.05E+00 2.78E+00 2.42E+00 2.88E+00 2.60E+00 2.93E+00 2.36E+00 3.07E+00 2.51E+00 3.11E+00 2.73E+00 1.51E+01 1.56E+01 1.48E+01 1.58E+01 1.91E+01 2.61E+01 1.85E+01 1.36E+01 1.71E+01 1.46E+01 1.29E+01 1.24E+01 1.09E+01 1.17E+01 1.38E+01 1.02E+01 I

1.27E+01 1.24E+01 1.51E+01 1.11E+01 1.02E+01 1.17E+01 1.34E+01 1.54E+01 1.85E+01 05

+/-

+/-

2.49E+00 3.20E+00 2.80E+00 2.74E+00 3.06E+00 3.36E+00 2.70E+00 2.38E+00 3.OOE+00 2.87E+00 2.68E+00 2.67E+00 2.60E+00 2.87E+00 2.50E+00 2.67E+00 2.63E+00 2.61E+00 2.46E+00 2.85E+00 2.35E+00 2.85E+00 2.40E+00 3.07E+00 2.87E+00 1.73E+01 1.58E+01 1.96E+01 1.63E+01 1.30E+01 2.84E+01 2.58E+01 1.32E+01 2.71 E+01 1.63E+01 1.26E+01 9.68E+00 1.43E+01 1.01 E+01 1.33E+01 1.91E+01 1.48E+01 9.00E+00 2.09E+01 1.16E+01 1.36E+01 8.70E+00 1.51E+01 9.02E+00 1.42E+01 1.76E+01 2.60E+00 3.21 E+00 3.04E+00 2.77E+00 2.75E+00 3.45E+00 3.32E+00 2.35E+00 3.45E+00 2.96E+00 2.67E+00 2.50E+00 2.78E+00 2.77E+00 2.47E+00 3.20E+00 2.64E+00 1.40E+01 1.93E+01 1.19E+01 1.59E+01 2.08E+01 2.56E+01 2.24E+01 1.21E+01 2.40E+01 1.92E+01 1.31E+01 1.28E+01 1.12E+01 1.32E+01 1.22E+01 1.95E+01 1.15E+01 2.43E+00 3.39E+00 2.64E+00 2.75E+00 3.14E+00 3.33E+00 3.17E+00 2.28E+00 3.32E+00 3.11E+00 2.71E+00 2.69E+00 2.60E+00 2.96E+00 2.41E+00 3.22E+00 2.45E+00 2.55E+00 3.16E+00 2.55E+00 3.23E+00 2.54E+00 3.10E+00 3.01E+00 2.92E+00 2.78E+00 2.46E+00 1.15E+01 3.07E+00 2.26E+01 2.26E+00 1.66E+01 3.00E+00 1.76E+01 2.27E+00 1.38E+01 3.05E+00 1.62E+01 2.17E+00 2.99E+00 1.20E+01 2.83E+00 1.65E+01 2.46E+00 1.24E+01

• Sample not obtained due to sampler not operating 37

Table 3-3 Air Particulate Gross Beta Radioactivity

[ 10-3 PC i/m3]

page 2 of 4 Period Station Station Station Station Station Ending I

21 I

I I

01/08/14 01/14/14 01/21/14 01/28/14 02/04/14 02/11/14 02/18/14 02/26/14 03/05/14 03/12/14 03/19/14 03/26/14 04/02/14 04/08/14 04/16/14 04/22/14 04/29/14 05/06/14 05/13/14 05121114 05/27/14 06/04/14 06/10/14 06/18/14 06124/14 07/01/14 1.65E+01

+/-

2.57E+00 1.51E+01

+1-3.18E+00 1.41E+01

+/-

2.76E+00 1.50E+01

+/-

2.69E+00 1.56E+01

+/-

2.88E+00 2.24E+01

+/-

3.18E+00 1.64E+01

+/-

2.87E+00 1.17E+01

+/-

2.26E+00 2.14E+01

+/-

3.20E+00 1.78E+01

+/-

3.04E+00 1.26E+01

+/-

2.67E+00 1.15E+01

+/-

2.59E+00 1.27E+01

+/-

2.71E+00 1.10E+01

+/-

2.83E+00 1.39E+01

+/-

2.51E+00 1.40E+01

+/-

2.90E+00 1.15E+01

+/-

2.43E+00 6.78E+00

+/-

2.24E+00 1.56E+01

+/-

2.80E+00 1.49E+01

+/-

2.45E+00 1.57E+01

+/-

3.12E+00 8.49E+00

+1-2.26E+00 9.45E+00

+/-

2.72E+00 1.32E+01

+/-

2.39E+00 1.08E+01

+/-

2.79E+00 1.54E+01

+/-

2.70E+00 1.46E+01 1.22E+01 1.22E+01 1.98E+01 1.75E+01 2.21E+01 2.OOE+01 1.43E+01 2.23E+01 1.72E+01 1.32E+01 1.61E+01 1.51E+01 1.32E+01 1.40E+01 1.67E+01 1.37E+01 9.21E+00 1.74E+01 1.58E+01 1.52E+01 8.88E+00 1.36E+01 1.07E+01 1.52E+01 1.47E+01 22

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

I 2.48E+00 3.02E+00 2.66E+00 2.94E+00 2.98E+00 3.17E+00 3.06E+00 2.40E+00 3.24E+00 3.01E+00 2.70E+00 2.86E+00 2.84E+00 2.96E+00 2.51E+00 3.06E+00 2.56E+00 2.44E+00 2.90E+00 2.50E+00 3.09E+00 2.28E+00 2.96E+00 2.25E+00 3.06E+00 2.66E+00 1.95E+01 1.66E+01 1.45E+01 1.67E+01 1.70E+01 2.73E+01 2.44E+01 1.25E+01 2.79E+01 1.93E+01 1.77E+01 1.80E+01 1.46E+01 1.39E+01 1.47E+01 2.14E+01 1.51E+01 1.16E+01 2.40E+01 1.25E+01 1.91E+01 1.21E+01 1.55E+01 1.23E+01 1.45E+01 1.62E+01 23 1

+/-

2.69E+00 1.48E+01

+/-

3.25E+00 1.44E+01

+/-

2.78E+00 1.36E+01

+/-

2.79E+00 1.13E+01

+/-

2.96E+00 1.68E+01

+/-

3.40E+00 2.68E+01

+/-

3.25E+00 2.24E+01

+/-

2.31EE+00 1.24E+01

+/-

3.48E+00 2.53E+01

+/-

3.11E+00 2.02E+01

+/-

2.95E+00 1.18E+01

+/-

2.98E+00 1.55E+01

+/-

2.78E+00 1.63E+01

+/-

3.OOE+00 1.21E+01

+1-2.55E+00 1.48E+01

+/-

3.32E+00 1.83E+01

+I-2.68E+00 1.40E+01

+/-

2.58E+00 1.17E+01

+/-

3.22E+00 2.09E+01

+/-

2.32E+00 1.04E+01

+/-

3.31E+00 1.81E+01

+/-

2.46E+00 1.13E+01

+/-

3.05E+00 1.36E+01

+/-

2.35E+00 1.34E+01

+/-

3.02E+00 1.90E+01

+/-

2.76E+00 1.78E+01 24*

I olA I

+/-

2.51E+00 1.76E+01

+/- 2.58E+00 1.93E+01

+/-

3.13E+00 1.53E+01

+/-

3.18E+00 1.74E+01 4/-

2.74E+00 9.71E+00

+/-

2.51E+00 1.56E+01

+/-

2.48E+00 1.39E+01

+/-

2.64E+00 1.42E+01

+/-

2.94E+00 2.03E+01

+/-

3.12E+00 1.77E+01

+/-

3.38E+00 2.36E+01

+/-

3.24E+00 2.32E+01 4/-

3.17E+00 1.84E+01

+/-

2.97E+00 2.06E+01

+/-

2.31E+00 9.77E+00

+/-

2.15E+00 1.22E+01

+/-

3.37E+00 2.04E+01

+/-

3.15E+00 1.68E+01

+/-

3.15E+00 1.77E+01

+/-

3.03E+00 1.93E+01

+/-

2.63E+00 1.11E+01

+/-

2.58E+00 1.19E+01

+/-

2.80E+00 1.49E+01

+/-

2.86E+00 1.34E+01

+/-

2.94E+00 1.52E+01

+/-

2.78E+00 1.10E+01

+/-

2.90E+00 1.30E+01

+/-

2.94E+00 1.35E+01

+/-

2.55E+00 1.53E+01

+/-

2.58E+00 1.20E+01

+/-

3.15E+00 2.03E+01

+/-

3.26E+00 1.92E+01

+/-

2.55E+00 1.04E+01

+/-

2.41E+00 8.17E+00

+/-

2.61E+00 1.06E+01

+/-

2.46E+00 9.70E+00

+/-

3.08E+00 2.04E+01

+/-

3.04E+00 1.59E+01

+/-

2.21E+00 1.71E+01

+/-

2.68E+00 1.17E+01

+/-

3.25E+00 1.71E+01

+/-

3.20E+00 1.32E+01

+/-

2.41E+00 1.12E+01

+/-

2.41E+00 6.75E+00

+/-

2.96E+00 1.37E+01

+/-

2.95E+00 1.25E+01

+/-

2.40E+00 1.16E+01

+/-

2.31E+00 1.18E+01

+/-

3.27E+00 1.60E+01

+/-

3.07E+00 1.65E+01

+/-

2.83E+00 1.73E+01

+/-

2.83E+00 1.34E+01 Station 05A

+/-

2.71E+00 41-3.29E+00

+/-

2.84E+00

+/-

2.66E+00

+/-

2.99E+00

+/-

3.22E+00

+/-

3.07E+00

+/-

2.30E+00

+/-

2.98E+00

+/-

3.11E+00

+/-

2.62E+00

+/-

2.72E+00

+/-

2.61 E+00

+/-

2.98E+00

+/-

2.40E+00

+/-

3.21E+00

+/-

2.21E+00

+/-

2.46E+00

+/-

2.81 E+00

+/-

2.27E+00

+/-

2.97E+00

+/-

2.16E+00

+/-

2.90E+00

+/-

2.31 E+00

+/-

3.31 E+00

+/-

2.60E+00 I

• Control Station 38

Table 3-3 Air Particulate Gross Beta Radioactivity

[1O3 pCi/m 3]

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

Station I

02 Station I

03 I

1.36E+01 2.06E+01 8.50E+00 1.60E+01 1.32E+01 1.84E+01 1.67E+01 1.53E+01 1.55E+01 1.OOE+01 9.37E+00 1.95E+01 1.11E+01 2.14E+01 1.75E+01 9.43E+00 9.83E+00 2.10E+01 1.46E+01 1.01E+01 2.06E+01 1.79E+01 2.23E+01 1.86E+01 1.60E+01 1.54E+01 2.54E+00 3.34E+00 2.36E+00 2.90E+00 2.57E+00 2.72E+00 3.75E+00 2.76E+00 2.76E+00 2.78E+00 2.44E+00 2.95E+00 2.65E+00 3.02E+00 2.84E+00 2.34E+00 2.35E+00 2.93E+00 2.84E+00 3.10E+00 2.78E+00 3.20E+00 3.05E+00 2.96E+00 2.76E+00 2.81E+00 1.10E+01 2.18E+01 1.33E+01 1.19E+01 1.29E+01 1.72E+01 1.88E+01 1.26E+01 1.49E+01 1.00E+01 1.15E+01 2.13E+01 1.28E+01 5.33E+00 1.79E+01 9.17E+00 1.15E+01 1.99E+01 1.72E+01 8.46E+00 2.03E+01 1.52E+01 1.55E+01 1.14E+01 1.44E+01 1.16E+01

+/

2.41E+00 1.13E+01

+/- 2.43E+00 1.16E+01

+/

3.40E+00 2.31E+01

+/- 3.46E+00 2.64E+01

+1-2.65E+00 1.10E+01

+1-2.51E+00 1.46E+01

+-

2.68E+00 1.21E+01

+/- 2.70E+00 1.74E+01

+-

2.50E+00 1.25E+01

+/- 2.48E+00 1.53E+01

+-

2.66E+00 1.62E+01

+/- 2.62E+00 1.99E+01

+/-

3.87E+00 1.53E+01

+/- 3.67E+00 2.08E+01

+/-

2.61E+00 1.11E+01

+/- 2.52E+00 1.54E+01

+/

2.73E+00 1.25E+01

+/- 2.60E+00 1.34E+01

+-

2.74E+00 9.25E+00

+/- 2.66E+00 1.32E+01

+-

2.57E+00 1.05E+01

+/- 2.51E+00 1.20E+01

+/

3.05E+00 2.15E+01

+/-

3.06E+00 2.62E+01

+/

2.72E+00 1.48E+01

+/- 2.78E+00 1.71E+01

+/

2.08E+00 1.59E+01

+/-

2.79E+00 2.04E+01

+/-

2.91E+00 1.71E+01

+I-2.89E+00 1.91E+01

+/

2.32E+00 1.06E+01

+/-

2.40E+00 8.42E+00

+/

2.43E+00 1.28E+01

+/-

2.55E+00 8.99E+00

+/

2.87E+00 1.87E+01

+/-

2.80E+00 1.82E+01

+-

2.98E+00 1.52E+01

+/-

2.88E+00 1.35E+01

+-

2.90E+00 1.39E+01

+/-

3.21E+00 9.46E+00

+/-

2.79E+00 1.84E+01

+/-

2.64E+00 2.15E+01

+/-

3.08E+00 1.66E+01

+/-

3.26E+00 1.78E+01

+/- 2.71E+00 2.18E+01

+/-

3.03E+00 1.80E+01

+/- 2.57E+00 1.76E+01

+/-

2.90E+00 1.87E+01

+/- 2.67E+00 1.49E+01

+/-

2.70E+00 1.94E+01

+I-2.63E+00 1.62E+01

+/- 2.89E+00 1.19E+01 Sa 0

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

I 2.45E+00 1.29E+01 3.61E+00 2.10E+01 2.72E+00 1.29E+01 3.01E+00 1.23E+01 2.64E+00 1.69E+01 2.78E+00 1.79E+01 3.98E+00 1.96E+01 2.76E+00 1.38E+01 2.65E+00 1.68E+01 2.90E+00 1.34E+01 2.60E+00 1.27E+01 3.27E+00 1.54E+01 2.92E+00 1.40E+01 3.00E+00 2.03E+01 2.97E+00 2.01E+01 2.27E+00 1.14E+01 2.31E+00 1.52E+01 2.78E+00 1.13E+01 2.79E+00 9.80E+00 2.99E+00 7.93E+00 2.81E+00 1.63E+01 3.26E+00 1.57E+01 2.84E+00 1.55E+01 2.96E+00 1.75E+01 2.94E+00 1.36E+01 2.65E+00 1.30E+01 Station

+I-2.52E+00 1.28E+01

+/-

3.35E+00 2.28E+01

+/-

2.62E+00 9.91E+00

+I-2.71E+00 1.55E+01

+/-

2.70E+00 1.29E+01

+I-2.69E+00 2.02E+01

+/

3.92E+00 2.23E+01

+-

2.67E+00 1.48E+01

+/

2.83E+00 8.58E+00

+-

2.90E+00 1.16E+01

+/-

2.64E+00 8.20E+00

+/

2.75E+00

+/

2.78E+00 1.82E+01

+-

2.99E+00 2.72E+01

+/

3.02E+00 2.32E+01

+I-2.45E+00 1.06E+01

+/

2.68E+00 1.51E+01

+-

2.42E+00 1.78E+01 I+

2.59E+00 1.56E+01 I+

2.86E+00 6.96E+00

+-

2.59E+00 1.75E+01

+-

3.13E+00 1.63E+01

+/

2.71E+00 1.64E+01

+-

2.89E+00 1.38E+01

+/

2.63E+00 1.53E+01

+-

2.71E+00 1.34E+01 Station 06

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

I 2.51E+00 1.23E+01 3.44E+00 2.18E+01 2.44E+00 1.27E+01 2.90E+00 1.46E+01 2.50E+00 1.68E+01 2.80E+00 1.53E+01 4.07E+00 2.11E+01 2.73E+00 1.31E+01 2.37E+00 1.56E+01 2.81E+00 9.17E+00 2.37E+00 1.03E+01 1.94E+01 3.00E+00 1.19E+01 3.31E+00 1.95E+01 3.16E+00 1.57E+01 2.41E+00 1.12E+01 2.67E+00 1.27E+01 2.76E+00 1.97E+01 2.90E+00 1.54E+01 2.80E+00 9.61E+00 2.65E+00 1.36E+01 3.16E+00 1.29E+01 2.76E+00 9.83E+00 2.70E+00 1.62E+01 2.72E+00 1.36E+01 2.72E+00 1.39E+01 Sa 0

+/-

+/-

+/-

+/-

~1-

+/-

+/-

+/-

+/-

+/-

+/-

+/-

2.48E+00 3.40E+00 2.61E+00 2.83E+00 2.70E+00 2.57E+00 4.00E+00 2.64E+00 2.77E+00 2.69E+00 2.50E+00 2.96E+00 2.67E+00 2.94E+00 2.78E+00 2.45E+00 2.53E+00 2.86E+00 2.90E+00 2.97E+00 2.46E+00 2.95E+00 2.38E+00 2.83E+00 2.63E+00 2.75E+00 MEAN 1.547E+01

+/-

3.35E+00 1.41E+01

+/-

2.74E+00 1.45E+01

+/- 2.77E+00 1.67E+01

+/-

2.88E+00 1.47E+01

+I-2.77E+00 1.56E+01

+/-

2.82E+00 1.54E+01

• Sample not obtained due to sampler not operating

+/-

2.82E+00 39

Table 3-3 Air Particulate Gross Beta Radioactivity

[10 3 pCi/m3]

page 4 of 4 Period Ending 07/09/14 07115/14 07/22/14 07/29/14 08/06/14 08114/14 08/19114 08/26/14 09/02/14 09/09/14 09/16/14 09/23/14 09/30/14 10/07/14 10/14/14 10/21/14 10/28/14 11/05/14 11/12/14 11/18/14 11/26/14 12/02/14 12/09/14 12/16/14 12/23/14 12/30/14 Station Station Station Station U

S 21 1.19E+01

+/-

2.08E+01

+/-

1.04E+01

+/-

1.62E+01

+/-

1.39E+01

+!-

1.30E+01

+/-

1.72E+01

+/-

1.26E+01

+/-

1.53E+01

+/-

1.24E+01

+/-

1.38E+01

+/-

2.50E+01

+/-

1.32E+01

+/-

1.65E+01

+I-1.97E+01

+/-

5.91 E+00

+/-

1.29E+01

+/-

2.12E+01

+/-

1.89E+01

+/-

1.06E+01

+/-

2.14E+01

+/-

1.41E+01

+/-

1.99E+01

+/-

1.54E+01

+I-1.57E+01

+/-

1.26E+01

+/-

2.47E+00 3.34E+00 2.48E+00 2.91E+00 2.55E+00 2.45E+00 3.78E+00 2.61 E+00 2.76E+00 2.83E+00 2.70E+00 3.21E+00 2.74E+00 2.77E+00 3.03E+00 2.10E+00 2.55E+0(

2.92E+0(

3.07E+0(

3.02E+0C 2.82E+00 3.06E+00 2.94E+0(

2.79E+00 2.75E+0(

2.70E+0(

S 22 1.24E+01

+/-

1.95E+01

+/-

1.42E+01

+/-

1.39E+01

+/-

1.31E+01

+/-

1.78E+01

+/-

1.95E+01

+/-

1.51E+01

+I-1.41E+01

+/-

9.57E+00 +/-

1.08E+01

+/-

2.11E+01

+I-1.47E+01

+/

1.73E+01

+-

1.60E+01

+-

1.12E+01

+1 0 1.32E+01

+-

0 1.92E+01

+-

0 1.57E+01

+-

0 1.07E+01

+-

0 2.35E+01

+-

0 1.55E+01

+-

0 1.83E+01

+/

0 1.82E+01

+/-

0 1.61E+01

+I-0 1.22E+01

+/-

I I

2.49E+00 3.27E+00 2.69E+00 2.80E+00 2.51E+00 2.69E+00 3.91E+00 2.74E+00 2.69E+00 2.68E+00 2.53E+00 3.03E+00 2.82E+00 2.82E+00 2.83E+00 2.45E+00 2.57E+00 2.82E+00 2.91E+00 3.03E+00 2.91E+00 3.14E+00 2.86E+00 2.93E+00 2.77E+00 2.68E+00 1.41E+01 2.42E+01 1.12E+01 1.81E+01 1.61E+01 1.70E+01 1.73E+01 1.53E+01 1.96E+01 1.29E+01 1.28E+01 2.85E+01 1.48E+01 2.32E+01 2.36E+01 1.30E+01 1.51E+01 1.85E+01 2.25E+01 1.23E+01 2.51E+01 1.66E+01 2.15E+01 1.49E+01 1.06E+01 1.46E+01 2.57E+00 3.53E+00 2.52E+00 3.01E+00 2.66E+00 2.65E+00 3.79E+00 2.75E+00 2.97E+00 2.91E+00 2.63E+00 3.39E+00 2.82E+00 3.12E+00 3.15E+00 2.56E+00 2.67E+00 2.80E+00 3.23E+00 3.13E+00 3.01 E+00 3.15E+00 3.01E+00 2.77E+00 2.46E+00 2.79E+00 1.27E+01 1.80E+01 1.37E+01 1.38E+01 1.19E+01

1. 51 E+01 1.96E+01 1.11E+01 1.63E+01 1.11E+01 1.27E+01 2.72E+01 1.44E+01 2.43E+01 1.72E+01 1.18E+01 1.36E+01 1.94E+01 1.73E+01 1.18E+01 2.36E+01 1.80E+01 2.38E+01 1.99E+01 1.70E+01 1.08E+01 24

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-4/-

+1-

+1-

+1-

+1-

+1-

+1-I I

I Station 01A Station I05A I

2.51 E+00 3.19E+00 2.67E+00 2.79E+00 2.44E+00 2.56E+00 3.93E+00 2.52E+00 2.81E+00 2.74E+00 2.64E+00 3.32E+00 2.80E+00 3.18E+00 2.91 E+00 2.48E+00 2.59E+00 2.83E+00 2.99E+00 3.08E+00 2.90E+00 3.31E+00 3.13E+00 3.02E+00 2.81 E+00 2.59E+00 1.25E+01 2.21E+01 1.26E+01 1.46E+01 1.52E+01 2.04E+01 3.26E+01 1.53E+01 1.18E+01 1.19E+01 1.02E+01 2.71E+01 1.43E+01 1.91E+01 1.82E+01 1.83E+01 1.76E+01 7.63E+00 2.02E+01 1.11E+01 2.25E+01 1.93E+01 1.38E+01 8.86E+00 2.48E+00 3.42E+00 2.60E+00 2.83E+00 2.67E+00 2.82E+00 4.14E+00 2.75E+00 2.56E+00 2.87E+00 2.49E+00 3.31E+00 2.82E+00 2.90E+00 2.88E+00 2.70E+00 2.80E+00 2.99E+00 2.95E+00 2.76E+00 2.81E+00 3.06E+00 2.99E+00 2.64E+00 2.46E+00 1.17E+01 2.08E+01 1.20E+01 1.27E+01 1.31E+01 1.46E+01 1.54E+01 1.44E+01 1.31E+01 8.14E+00 1.97E+01 2.41E+01 1.18E+01 1.47E+01 1.81E+01 1.06E+01 1.27E+01 1.57E+01 1.30E+01 1.03E+01 2.11E+01 1.28E+01 1.76E+01 1.43E+01 1.50E+01 1.30E+01

+1-

+1-4/-

+1-

+1-

~1-4/-

~1-4/-

+1-

+1-4/-

~1-

~1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

~1-2.46E+00 3.34E+00 2.57E+00 2.77E+00 2.51E+00 2.53E+00 3.68E+00 2.70E+00 2.64E+00 2.61E+00 3.00E+00 3.18E+00 2.66E+00 2.68E+00 2.93E+00 2.40E+00 2.54E+00 2.65E+00 2.77E+00 3.01E+00 2.81E+00 2.96E+00 2.82E+00 2.73E+00 2.71E+00 2.71E+00 MEAN 1.47E+01 +/-

2.77E+00 1.53E+01 +/-

2.81E+00 1.74E+01 +/-

2.91E+00 1.62E+01 +/-

2.86E+00 1.60E+01 +/-

Mean - All Indicator Lo 2.84E+00 1.46E+01 +/-

2.77E+00 cations 1.54E+01 +I-2.85E+00

• Sample not obtained due to sampler not operating.

• • Control Station 40

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 1 of 4 Period Ending 01/08/14 01/14/14 01/21/14 01/28/14 02/04/14 02/11/14 02/18/14 02/26/14 03/05/14 03/12/14 03/19/14 03/26/14 04/02/14 04/08/14 04/16/14 04/22/14 04/29/14 05/06/14 05/13/14 05/21/14 05/27/14 06/04/14 06/10/14 06/18/14 06/24/14 07/01/14 I

Station 01 C

C C

C C

C C

C

<C C

C C

C C

C C

C I

5.60E+01 1.57E+01 3.93E+01 1.57E+01 3.92E+01 3.01E+01 4.11E+01 1.01E+01 4.20E+01 1.62E+01 1.08E+01 2.26E+01 3.54E+01 1.97E+01 5.70E+01 1.22E+01 2.75E+01 9.93E+00 3.41E+01 3.43E+01 3.00E+01 1.47E+01 4.14E+01 1.34E+01 Station 02 C

C C

C C

C C

C C

C C

C C

C C

I 4.64E+01 4.05E+01 3.93E+01 3.72E+01 1.65E+01 3.01E+01 4.15E+01 2.59E+01 4.20E+01 2.47E+01 3.03E+01 4.07E+01 2.82E+01 3.82E+01 2.10E+01 5.06E+01 5.59E+01 3.21E+01 2.75E+01 2.56E+01 3.41E+01 3.43E+01 2.81E+01 3.51E+01 4.27E+01 3.41E+01 Station 03 C

C C

C C

C C

C C

C C

C C

C C

U I

4.80E+01 4.06E+01 3.93E+01 3.70E+01 3.91E+01 3.01E+01 4.09E+01 2.63E+01 4.20E+01 2.47E+01 2.98E+01 4.20E+01 2.95E+01 3.82E+01 3.54E+01 5.04E+01 2.13E+01 3.28E+01 2.77E+01 2.55E+01 3.40E+01 3.43E+01 2.82E+01 3.48E+01 4.21E+01 3.39E+01 Station 04 C

C C

C C

IA 4.71E+01 4.05E+01 3.93E+01 3.72E+01 3.92E+01 3.01E+01 4.18E+01 2.57E+01 4.20E+01 2.47E+01 3.05E+01 3.96E+01 2.87E+01 3.82E+01 3.53E+01 5.06E+01 5.57E+01 3.23E+01 1.07E+01 2.55E+01 3.41E+01 3.43E+01 2.82E+01 3.48E+01 4.22E+01 3.40E+01 Station 05 C

C C

C C

c C

c C

C C

C C

C C

C 3.64E+01 4.05E+01 4.24E+01 3.72E+01 3.86E+01 3.26E+01 3.63E+01 2.61E+01 4.69E+01 2.47E+01 3.01E+01 4.05E+01 2.85E+01 3.82E+01 3.53E+01 5.06E+01 3.24E+01 2.76E+01 2.55E+01 1.13E+01 3.94E+01 3.73E+01 3.48E+01 3.86E+01 3.40E+01 Station 06 C

C C

C C

C C

C C

C C

C C

C C

C I

3.61E+01 3.17E+01 4.24E+01 3.54E+01 3.86E+01 3.26E+01 3.65E+01 2.56E+01 4.69E+01 3.91E+00 2.96E+01 5.07E+01 2.88E+01 4.15E+01 3.87E+01 6.42E+01 5.56E+01 2.69E+01 3.40E+01 2.69E+01 2.69E+01 3.94E+01 1.56E+01 3.58E+01 3.84E+01 3.18E+01 Station 07 C

C C

C C

C C

C C

C C

C C

C C

I 3.60E+01 3.17E+01 4.24E+01 3.54E+01 3.86E+01 3.26E+01 3.66E+01 2.55E+01 4.69E+01 2.53E+01 2.97E+01 5.07E+01 2.87E+01 4.15E+01 3.87E+01 6.42E+01 5.98E+01 2.68E+01 3.40E+01 2.69E+01 2.69E+01 3.94E+01 3.73E+01 4.25E+01 1.66E+01 3.18E+01

• Sample not obtained due to sampler not operating 41

Table 3-4 Airborne Iodine 1-131

[10-3 pCi/m 3]

page 2 of 4 Period Ending 01/08/14 01/14/14 01/21/14 01/28/14 02/04/14 02/11/14 02/18/14 02/26/14 03/05/14 03/12/14 03/19/14 03/26/14 04/02/14 04/08/14 04/16/14 04/22/14 04/29114 05/06/14 05113/14 05/21/14 05/27/14 06/04/14 06/10/14 06/18/14 06/24/14 07/01/14 I

Station 21 S

C C

C C

C C

C C

C C

C C

C C

C U -I 1.53E+01 3.18E+01 4.24E+01 3.53E+01 3.85E+01 3.26E+01 3.66E+01 2.56E+01 4.69E+01 2.53E+01 2.96E+01 5.01E+01 2-91E+01 4.16E+01 3.87E+01 6.40E+01 5.91E+01 2.64E+01 3.42E+01 2.68E+01 2.68E+01 3.93E+01 3.76E+01 3.53E+01 3.86E+01 3.16E+01 Station 22 C

C C

C C

C C

C C

C C

C C

I 3.65E+01 3.18E+01 1.42E+01 3.53E+01 4.26E+01 1.28E+01 3.83E+01 2.54E+01 3.40E+01 2.53E+01 2.48E+01 5.01E+01 2.90E+01 4.16E+01 3.87E+01 6.40E+01 5.92E+01 2.71E+01 3.42E+01 2.68E+01 2.68E+01 1.04E+01 3.73E+01 3.53E+01 3.87E+01 3.16E+01 Station 23 C

C C

C C

C C

C C

C C

C C

C C

C I

4.06E+01 3.33E+01 3.39E+01 4.OOE+01 1.51E+01 3.05E+01 3.81E+01 2.39E+01 3.40E+01 2.53E+01 2.48E+01 4.47E+01 2.85E+01 3.67E+01 3.39E+01 4.84E+01 6.06E+01 3.69E+01 3.87E+01 2.64E+01 3.77E+01 2.49E+01 3.80E+01 2.61E+01 5.38E+01 3.05E+01 24*

C C

C C

Station 4.19E+01 3.33E+01 3.40E+01 3.99E+01 4.26E+01 3.05E+01 1.60E+01 2.39E+01 3.40E+01 2.57E+01 2.48E+01 4.36E+01 2.95E+01 3.70E+01 3.38E+01 4.82E+01 6.38E+01 3.73E+01 3.88E+01 2.67E+01 3.77E+01 2.48E+01 3.83E+01 2.59E+01 5.36E+01 3.03E+01 Station S

01A C

4 4

4 1C 1C 1

i 1

1 1

1 1

1 1

1 4.02E+01 3.33E+01 3.39E+01 4.00E+01 4.27E+01 3.05E+01 3.81E+01 2.39E+01 1.42E+01 2.57E+01 2.48E+01 4.57E+01 2.81E+01 3.67E+01 3.39E+01 4.84E+01 6.65E+01 3.58E+01 3.87E+01 2.80E+01 3.77E+01 2.49E+01 3.89E+01 2.61E+01 5.29E+01 3.07E+01 Station S

05A 4

4 4

C C

C C

C c

C 1

C 1

C 1

C 1

1 1

4.13E+01 3.33E+01 3.39E+01

.002E+01 1.27E+01 3.05E+01 3.79E+01 2.40E+01 3.40E+01 2.57E+01 1.03E+01 4.46E+01 2.90E+01 3.69E+01 3.38E+01 4.84E+01 6.47E+01 3.68E+01 3.88E+01 2.63E+01 3.77E+01 2.49E+01 3.83E+01 2.59E+01 5.36E+01 3.03E+01 1

1 1

1 C

C C

• Control Station 42

Table 3-4 Airborne Iodine 1-131

[10.3 pCi/m3 ]

page 3 of 4 Period Ending 07/09114 07/15/14 07/22/14 07129/14 08/06/14 08/14/14 08/19/14 08/26/14 09/02/14 09/09/14 09/16/14 09/23/14 09/30114 10/07114 10/14/14 10/21/14 10/28/14 11/05/14 11/12/14 11/18/14 11/26/14 12/02/14 12/09/14 12/16/14 12/23/14 12/30/14 Mean Station Station Station I

01 C

C C

C C

C C

C C

C C

C C

1. DtV/0~

+/

4.87E+01 2.44E+01 5.18E+01 6.01E+01 2.43E+01 3.11E+01 5.43E+01 1.98E+01 6.09E+01 1.70E+01 3.09E+01 2.51E+01 2.10E+01 1.88E+01 1.58E+01 9.73E+00 3.21E+01 1.44E+01 2.25E+01 2.69E+01 2.18E+01 2.21E+01 6.87E+00 4.10E+00 2.73E+01 1.95E+01 1.67E+01 02 C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C

1. D~V/0'

+/-

4.89E+01 6.25E+01 5.18E+01 6.01E+01 2.37E+01 3.11E+01 5.43E+01 5.10E+01 6.09E+01 4.30E+01 3.09E+01 6.50E+01 5.35E+01 4.89E+01 6.30E+00 2.50E+01 3.21 E+01 3.42E+01 2.27E+01 2.57E+01 4.99E+01 5.77E+01 1.96E+01 1.05E+01 2.73E+01 1.97E+01 3.32E+0 C

I C

I C

I C

I C

I C

I C

I C

I C

I C

C C

I C

C I

C I

C I

C C

C C

C C

1 #DIV/0I

+/-

I Station 04 4.90E+01 6.24E+01 5.18E+01 6.02E+01 2.36E+01 3.12E+01 5.43E+01 5.10E+01 6.09E+01 4.22E+01 3.08E+01 6.50E+01 5.25E+01 4.99E+01 1.65E+01 2.49E+01 3.23E+01 3.40E+01 8.82E+00 9.96E+00 4.84E+01 6.04E+01 1.96E+01 1.05E+01 2.73E+01 1.98E+01 3.39E+01 4.90E+01 6.23E+01 5.18E+01 6.13E+01 2.39E+01 3.08E+01 5.43E+01 5.10E+01 6.09E+01 4.29E+01 3.10E+01 6.47E+01 5.30E+01 4.94E+01 1.62E+01 2.49E+01 3.23E+01 3.41 E+01 2.27E+01 2.60E+01 4.89E+01 5.86E+01 1.96E+01 1.05E+01 1.06E+01 1.98E+01 3.35E÷0 Station C

C C

C C

C C

C C

C C

C C

C C

C Station Station I

06 I

I II II 5.57E+01 6.23E+01 5.16E+01 6.51E+01 2.70E+01 3.96E+01 6.34E+01 5.10E+01 6.49E+01 4.26E+01 1.75E+01 6.49E+01 5.35E+01 4.90E+01 1.63E+01 2.49E+01 3.14E+01 3.41E+01 2.27E+01 2.57E+01 4.97E+01 5.83E+01 1.96E+01 1.05E+01 2.73E+01 8.77E+00 5.55E+01 6.63E+01 5.16E+01 5.52E+01 2.70E+01 3.96E+01 3.64E+01 4.91E+01 6.49E+01 3.70E+01 1.75E+01 6.44E+01 5.28E+01 1.84E+01 2.80E+01 3.14E+01 2.73E+01 1.24E+01 1.22E+01 1.67E+01 2.73E+01 1.26E+01 4.43E+00 6.02E+01 2.03E+01 3.52E+01 5.55E+01 6.64E+01 5.16E+01 5.51E+01 2.70E+01 3.97E+01 3.64E+01 4.91E+01 6.49E+01 3.71E+00 1.75E+01 6.85E+01 6.44E+01 5.28E+01 1.83E+01 2,80E+01 3,14E+01 2.73E+01 2.96E+01 2,91E+01 4.74E+01 6,48E+01 2,44E+01 1,06E+01 6.02E+01 2.03E+01 3.51E+01

1. DIVlO!

+1 1

1. DIVl0!

+/-

3.34E+01

1. DIVI0!

+1/

1. DIV/0!

+I-

• Sample not obtained due to sampler not operating.

43

Table 3-4 Airborne Iodine 1-131

[10.3 pCi/m 3]

page 4 of 4 Period Ending 07/09/14 07/15/14 07122/14 07129/14 08/06/14 08/14/14 08/19/14 08/26/14 09/02/14 09/09/14 09/16/14 09/23/14 09/30/14 10107/14 10/14/14 10/21/14 10/28/14 11/05/14 11/12/14 11/18/14 11/26/14 12/02/14 12/09/14 12/16/14 12/23/14 12/30/14 MEAN Station C

C C

C C

C C

C C

C C

C C

C

1. DIV/0'

+/-

2.34E+01 6.63E+01 5.16E+01 5.52E+01 2.69E+01 3.98E+01 6.33E+01 4.91E+01 6.49E+01 3.66E+01 1.76E+01 6.82E+01 6.45E+01 5.27E+01 1.86E+01 2.79E+01 3.15E+01 2.72E+01 2.96E+01 2.91 E+01 4.68E+01 6.60E+01 2.44E+01 1.06E+01 6.01E+01 2.05E+01 3.54E+01 Station 22 5.57E+01

" 6.63E+01 2.21 E+01 5.52E+01 2.67E+01 3.32E+01 5.38E+01

" 4.91E+01 4.52E+01 3.67E+01 3.38E+01 6.83E+01 6.45E+01 5.28E+01 1.86E+01 2.79E+01 3.73E+01 2.72E+01 2.96E+01 2.91E+01 4.68E+01 6.60E+01 2.44E+01 1.06E+01 6.01E+01 2.05E+01

1. DIV/0!

+/- 3.53E+01 Station C

2

<CE

<CE C

C 1 #DV/0!+/-C 5.83E+01 539E+01 5.27E+01 5.51E+01 I.12E+01 3.31 E+01 5.39E+01 5.05E+01 4.52E+01 4.72E+01 3.37E+01 6.69E+01 6.1 8E+01 5.51 E+01 1.73E+01 3.01 E+01 3.70E+01 2.64E+01 2.95E+01 2.92E+01 4.77E+01 6.43E+01 2.43E+01 1.06E+01 5.11 E+01 2.10E+01 3.26E+01 Station L24*

5.86E+01 5.36E+01 5.27E+01 5.52E+01 2.66E+01 1.17E+01 5.41E+01 5.05E+01 4.52E+01 4.56E+01 3.39E+01 6.66E+01 6.18E+01 5.52E+01 1.80E+01 3.OOE+01 3.72E+01 2.62E+01 1.55E+01 1

3.39E+01 1

5.09E+01 1

4.59E+01 1

1.57E+01 1

1.20E+01 1

5.10E+01 I

2.12E+01 1

1. DIV/0!

+/- 3.33E+01 Station I

01A 5.83E+01 C

C C

C C

C C

<C C

C C

C:

C C:

C C

1. DV0 /

5.39E+01 5.27E+01 5.51E+01 2.74E+01 3.31 E+01 2.26E+01 5.05E+01 1.90E+01 4.75E+01 3.38E+01 6.65E+01 6.23E+01 5.47E+01 1.72E+01 3.01E+01 2.64E+01 2.83E+01 3.55E+01 5.11E+01 4.40E+01 1.57E+01 1.21E+01 5.11E+01 2.09E+01 3.29E+01 Station 5.86E+01 5.35E+01 5.27E+01 2.36E+01 2.67E+01 3.31E+01 5.39E+01 5.05E+01 4.52E+01 4.62E+01 1.42E+01 6.66E+01 6.18E+01 5.52E+01 1.77E+01 3.OOE+01 1.56E+01 2.63E+01 2.85E+01 3.41E+01 5.15E+01 4.50E+01 1.57E+01 1.20E+01 5.11E+01 C

2.11E+01

1. DIV/0!

+/-

3.30E+01

1. DIV/0!

+/-

3.25E+01 Indicator Locations Mean

• Sample not obtained due to sampler not operating.

• • Control Station 44

Table 3-5 Airborne Particulate Gamma Spectra

[10-3 pCi/m 3]

page 1 of 2 Sampling Location I

Be-7 I

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

1.32E+02 1.28E+02 1.20E+02 1.22E+02 1.58E+02 1.19E+02 1.12E+02 1.37E+02 1.23E+02 1.11E+02 1.38E+02 1.26E+02 1.51 E+02 1.32E+02 1.22E+02 1.26E+02 1.64E+02 1.20E+02 1.28E+02 1.07E+02 1.15E+02 1.26E+02 1.27E+02 1.48E+02 1.10E+02 1.26E+02

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-3.32E+01 2.22E+01 2.13E+01 2.OOE+01 2.50E+01 2.50E+01 1.85E+01 2.56E+01 2.38E+01 2.67E+01 3.39E+01 3.27E+01 2.67E+01 Cs-134*

1.81E+OC 1.06E+OC 1.04E+0C 1.18E+OC 1.27E+0C 1.35E+0C 1.03E+OC 1.26E+OC 1.27E+OC 1.65E+OC 1.59E+OC 1.96E+0C 1.96E+OC Cs-1 34*

1.06E+OC 1.57E+OC 1.52E+OC 1.89E+OC 1.06E+OC 1.32E+OC 1.37E+OC 1.19E+OC 1.07E+OC 1.60E+OC 1.15E+OC 1.11E+OC 1.13E+OC I

SCs-1 37"

< 1.77E+00

" 1.08E+00

" 1.12E+00

" 9.24E-01

" 1.21E+00

" 1.38E+00

" 9.68E-01

" 1.34E+00

" 1.01E+00

" 1.88E+00

" 1.37E+00

" 1.81E+00

" 1.78E+00 I

I Quarter 1 Quarter 2 Be-7

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-I 2.21E+01 3.32E+01 2.40E+01 3.56E+01 2.09E+01 2.87E+01 2.44E+01 2.26E+01 2.11E+01 2.81E+01 2.53E+01 2.71E+01 2.23E+01 SCs-137" I

< 8.70E-01 I

< 1.62E+00 I

< 1.09E+00 I

< 1.39E+00 I

< 1.00E+00 I

< 1.12E+00 I

< 1.26E+00

< 1.31E+00 0

< 7.29E-01

< 1.58E+00

< 1.07E+00

< 1.09E+00 I

< 9.29E-01 Sr-89

< 5.62E+00

< 7.39E+00

< 5.58E+00

< 8.10E+00

< 6.86E+00

< 7.95E+00

< 9.29E+00

" 6.78E+00

< 5.34E+00

" 5.47E+00

< 7.88E+00

< 5.73E+00

< 7.02E+00 S Sr-90

< 2.79E+00

" 1.74E+00

" 2.37E+00

" 3.68E+00

" 4.33E+00

" 3.54E+00

< 2.05E+00

" 2.711E+00

< 2.43E+00

" 2.89E+00

< 2.80E+00

< 2.53E+00

< 2.22E+00

• LLD identified in the ODCM Control Station 45

Table 3-5 Airborne Particulate Gamma Spectra

[10O. pCi/m 3]

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

MEAN I

1.35E+02 1.12E+02 8.50E+01 1.10E+02 9.76E+01 9.50E+01 9.79E+01 1.07E+02 1.08E+02 1.12E+02 1.26E+02 1.04E+02 1.19E+02 Be-7

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-2.41E+01 2.46E+01 1.87E+01 2.34E+01 1.83E+01 2.87E+01 2.50E+01 2.50E+01 2.61E+01 2.48E+01 3.75E+01 2.44E+01 3.31 E+01 Cs-134*

1.04E+00 1.08E+00 1.24E+00 5.68E-01 1.01E+00 1.74E+00 1.48E+00 1.71E+00 6.87E-01 c

1.25E+00 1.89E+00 c

1.21E+00 2.34E+00 I

Cs-137*

9.01 E-01 1.09E+00 9.77E-01 6.42E-01 9.73E-01 1.56E+00 1.03E+00 1.16E+00 8.22E-01 1.16E+00 1.82E+00 1.24E+00 1.41E+00 j

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

1.16E+02 9.61E+01 8.65E+01 1.21E+02 1.28E+02 1.08E+02 9.19E+01 9.17E+01 1.02E+02 8.39E+01 9.71E+01 8.95E+01 1.29E+02 Be-7

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-

+1-3.02E+01 3.08E+01 2.08E+01 2.78E+01 2.60E+01 2.64E+01 2.06E+01 2.09E+01 2.09E+01 2.45E+01 2.32E+01 2.19E+01 3.24E+01 Cs-134*

1.33E+00 1.71E+00 1.49E+00 2.00E+00 9.88E-01 1.98E+00 1.04E+00 1.14E+00 1.21E+00 1.10E+00 1.27E+00 1.13E+00 1.67E+00 S

CS-1 37-1.31E+00 1.78E+00 c

1.10E+00 1.62E+00 1.06E+00 1.45E+00 8.85E-01 8.84E-01 1.35E+00 1.19E+00 9.59E-01 9.19E-01 1.79E+00 Mean of All Indicator Location:

1.29E+02 1.15E+02 1.04E+02 1.29E+02 1.26E+02 1.13E+02 1.02E+02 1.13E+02 1.15E+02 1.08E+02 1.27E+02 1.07E+02 1.31E+02 1.16E+02 MEAN Be-7

.4-I-

+1-

+1-4-I-

-'-I-4-I-4-I-4-I-4-I-4-I-4-I-4-I-4-I-

+1-Quarter 4 2.74E+01 2.77E+01 2.12E+01 2.67E+01 2.26E+01 2.72E+01 2.21E+01 2.35E+01 2.30E+01 2.60E+01 3.00E+01 2.65E+01 2.86E+01 2.53E+01

• LLD Identified in ODCM

• • Control Station 46

Table 3-6 Soil

[pCi/kg]

Triennial Soil Samples Not Required in 2014 47

Table 3-7 Precipitation Gross Beta

[pCi/L]

page 1 of 2 Sampling Date 01/28/14 02/26/14 03/26/14 04/29/14 05/27/14 06/24/14 07/29/14 08/26/14 09/30/14 10/28/14 11/26/14 12/30/14 Mean 1.12E+01 2.32E+00 5.OOE+00 2.01E+00 2.44E+00 3.09E+00 2.42E+00 1.64E+00 2.40E+00 2.05E+00 3.46E+00 Gross Beta I

H-3 I

I 1.80E+00 1.32E+00 1.23E+00 1.54E+00 1.32E+00 1.07E+00 1.17E+00 2.07E+00 1.11E+00 1.11E+00 1.12E+00 1.05E+00 1.41E+00 7.75E+02 8.85E+02 1.09E+03 1,40E+03 1.16E+03 6.96E+02 1.38E+03 1.57E+03 1.86E+03 1.29E+03 1.44E+03 1.69E+03 1.27E+03 Rainfall (inches) 2.99 2.64 2.04 4.58 6.76 6.78 3.84 2.31 0.86 3.35 2.26 3.50 41.91 Ij Total 48

Table 3-7 Precipitation Gamma Spectra

[pCi/L]

page 2 of 2 Sampling Location Be-7 I

Mn-54 I

Fe-59 I

ro-58 I

Co-60 I

01A 06/24/14 12/30/14 3.41E+01 7.72E-01 1.15E+01 2.46E+00 4.23E+01 1.18E+00 9.03E+00 2.69E+00 Zn-65 I

Zr-95 I

Nb-95 I

Cs-134 8.53E-01 1.27E+00 Cs-137 01A 06/24/14 12/30/14 2.10E+00 4.95E+00 2.87E+00 6.58E-01 2.37E+00 5.77E+00 3.31E+00 9.70E-01 Ba-140 I

La-140 I

1-131 I

Th-228 7.33E-01 1.08E+00 01A 06/24/14 12/30/14 5.62E+03 1.60E+03 1.89E+05 1.32E+00 2.15E+03 7.63E+02 2.94E+04 2.51 E+00 Sampling Location MEAN I

Mn-54 I

Fe-59 Be-7 Co-58 I

Co-60 I

OIA I

Zn-65 I

7r-g5 I

Nb-95 I

Cs-1 34 I

Cs-1 37 Zn-65 I

Zr-95 I

Nb-95 I

Cs-134 I

Cs-137 01A 01A I

Ra-140 I

La-140 I

1-131 I

Th-228 I

No mean values. All results were <MDA 49

4 Table 3-8 Milk Gamma Spectra & Strontium

[pCi/L]

page 1 of 1 Sampling Date I

K-40 01/21/14 1.33E+03

+/-

1.33E+02 02/18/14 1.41E+03

+/-

1.27E+02 03/19/14 1.39E+03

+/-

7.66E+01 04/16/14 1.39E+03

+/-

1.46E+02 05/21/14 1.37E+03

+/-

1.54E+02 06/18/14 1.21E+03

+/-

1.64E+02 07/15/14 1.35E+03

+/-

1.53E+02 08/19/14 1.23E+03

+/-

1.66E+02 09/16/14 1.25E+03

+/-

1.59E+02 10/21/14 1.41 E+03

+/-

4.79E+01 11/12/14 1.26E+03

+/-

1.98E+02 12/16/14 1.46E+03

+/-

1.40E+02 Sta. Mean 1.34E+03

+/-

1.39E+02 I

Sr-89 I

Sr-90 I

[a]

[a]

3.25E+00

[a]

[a]

3.31 E+00

[a]

[a]

2.79E+00

[a]

[a]

3.79E+00

[a]

[a]

8.42E-01

[a]

[a]

8.19E-01

[a]

[a]

1.47E+00

[a]

[a]

1.04E+00 1-131" 7.92E-01 8.65E-01 9.63E-01 7.50E-01 1.OOE+00 8.13E-01 7.65E-01 8.19E-01 7.24E-01 8.53E-01 9.78E-01 9.71 E-01 Station 12A I

Cs-134-I CsI137*

Ba-140° La-140* '

" 4.62E+00 5.12E+00 4.14E+01 1.36E+01

" 4.06E+00 5.34E+00 2.33E+01 7.75E+00 1.63E+00 2.05E+00 1.69E+01

< 5.82E+00 5.24E+00 6.58E+00 2.95E+01

< 9.53E+00 6.13E+00 6.42E+00 3.63E+01 1.21E+01 7.73E+00 7.64E+00 3.47E+01 1.06E+01 8.45E+00 8.84E+00 4.03E+01 1.01E+01 6.68E+00 7.36E+00 3.95E+01 1.22E+01 6.42E+00 6.94E+00 2.80E+01 1.09E+01 2.49E+00 2.52E+00 2.45E+01

< 6.39E+00 7.62E+00

< 7.05E+00 3.56E+01

< 8.42E+00 5.09E+00

< 6.65E+00 4.64E+01 1.37E+01

• LLD identified in ODCM

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

50

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

Sampling Sampling Location Date Be-7 K-40 f-131*

Cs-134*

Cs-137" 05/13/14 1.17E+03 +/- 2.45E+02 6.74E+03 +/- 5.23E+02

< 3.87E+01

< 2.57E+01 2.84E+01 14B 06/10/14 8.34E+02

+/- 2.76E+02 6.44E+03

+/- 5.44E+02 5.64E+01

< 2.70E+01

< 2.72E+01 07/09/14 9.57E+02

+/- 3.82E+02 8.36E+03 +/- 1.03E+03 2.69E+01 4.43E+01 4.42E+01 08/14/14 1.19E+03

+/- 4.22E+02 5.92E+03 +/- 8.01E+02 4.17E+01

< 3.87E+01

< 3.88E+01 09/10/13 5.64E+02

+/- 2.18E+02 8.30E+03

+/- 5.60E+02 2-49E+01 2.34E+01 2.46E+01 10/14/14 1.42E+03 +/- 1.86E+02 7.56E+03

+/- 4.86E+02 2.59E+01 1.93E+01 2.26E+01 Mean 1.02E+03

+/-

2.88E+02 7.22E+03

+/-

6.57E+02

+/-

+/-

+/-

Sampling Sampling Location Date Be-7 I

K-40 1-131" Cs-134*

Cs-137" 15 05/13/14 5.80E+02

+/- 1.21E+02 6.54E+03 +/- 3.45E+02 3.99E+01 1.29E+01 1.44E+01 06/10/14 7.43E+02

+/- 2.44E+02 4.85E+03

+/- 4.93E+02 5.26E+01 2.24E+01 2.39E+01 07/09/14 4-87E+02

+/- 4.31E÷02 6.31E+03

+/- 9.46E+02 3.04E+01 4.24E+01 3.76E+01 08/14/14 2.68E+03

+/-

5.57E+02 7.39E+03

+/- 1.02E+03 411E+01 2.81E+01 3.29E+01 09/10/13 1.47E+03 +/- 4.11E+02 6.74E+03

+/- 9.14E+02 2.81E+01 4.16E+01 4.69E+01 10/14/14 3.16E+03

+/- 2.86E+02 5.08E+03

+/- 5.24E+02 2.47E+01 2.60E+01

< 2.73E+01 Mean 1.52E+03

+/-

3.42E+02 6.15E+03

+/-

7.07E+02

+/-

+/-

+/-

Sampling Sampling Location Date Be-7 I

K-40 1-131*

Cs-134" Cs-137*

16" 05/13/14 1.30E+03 +/- 1.53E+02 7.12E+03

+/- 3.85E+02 3.58E+01 1.61E+01 1.76E+01 page 1 of 2 06/10/14 07/09/14 08/14/14 09/10/13 10/14/14 7.28E+02 1.47E+03 6.81E+02 2.45E+03 2.70E+02

+/- 5.30E+02

+/- 3.84E+02

+/- 3.06E+02

+/-

2.23E+02 5.18E+03 2.91E+03 6.15E+03 1.04E+04 9.85E+03

+1-5.50E+02

+/- 8.97E+02

+/- 9.36E+02

+I-1.10E+03

+/- 4.47E+02 4.60E+01 3.30E+01 3.26E+01 2.95E+01 2.80E+01 2.37E+01 5.30E+01 3.11E+01 4.65E+01 1.92E+01 2.72E+01 5.59E+01 2.95E+01 4.98E+01 2.02E+01 Mean

• LLD identified in ODCM

• • Control Station 1.33E+03

+/-

3.11E+02 6.94E+03

+/-

7.19E+02

+/-

+/-

+/-

51

Table 3-9 Food and Vegetation Gamma Spectra

[pCi/kg]

page 2 of 2 Sampling Sampling Location Date I

Be-7 I

K-40 1-131" Cs-134" Cs-137" 23 05113/14 7.69E+02

+/-

2.22E+02 7.86E+03

+/-

5.22E+02 4.15E+01 2.65E+01 2.91E+01 06/10/14 1.26E+03

+/-

3.42E+02 5.27E+03

+/-

6.21E+02 3.68E+01 3.04E+01 3.07E+01 07/09/14 8.85E+02

+/-

4.63E+02 5.43E+03

+/-

9.53E+02 4.15E+01 5.39E+01 5.36E+01 08114/14 1.80E+03

+/-

3.82E+02 3.83E+03

+/-

7.65E+02 3.62E+01 2.22E+01 2.48E+01 09/10/13 2.22E+03

+/-

3.83E+02 8.80E+03

+/-

8.90E+02 2.67E+01 4.24E+01 4.86E+01 10/14/14 1.38E+03

+/-

1.14E+02 5.68E+03

+/-

2.72E+02 2.90E+01 1.22E+01 1.23E+01 Mean 1.39E+03

+/-

3.18E+02 6.15E+03

+/-

6.71E+02

+/-

+/-

+/-

Sampling Sampling Location Date I

Be-7 I

K-40 1-131 I

Cs-134*

Cs-137" 26 05/13/14 06/10/14 07/09114 08/14/14 09/10/13 10/14/14 3.43E+02

+/-

4.84E+02

+/-

1.40E+03

+/-

2.67E+03

+/-

1.21E+03

+/-

1.93E+03

+/-

2.17E+02 2.57E+02 4.52E+02 4.91E+02 2.64E+02 1.60E+02 7.44E+03

+/-

4.08E+02 4.49E+03

+I-6.89E+02 6.63E+03

+/-

1.08E+03 5.92E+03

+/-

8.99E+02 4.41E+03

+/-

5.20E+02 4.70E+03

+/-

3.39E+02

< 5.16E+01

< 4.19E+01

< 3.80E+01

< 3.59E+01

< 2.57E+01

< 3.33E+01

" 8.68E+00

" 2.78E+01 4.26E+01

" 2.62E+01

" 2.76E+01

" 1.66E+01 1.03E+01 2.97E+01 5.46E+01 2.87E+01 3.OOE+01 1.82E+01 Mean 1.34E+03

+/-

3.07E+02 5.60E+03

+/-

6.56E+02

+/-

+/-

+/-

+/-

Indicator locations

• LLD identified in ODCM 1.32E+03

+/-

3.14E+02 6.28E+03

+/-

6.73E+02 52

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

[pCi/L]

I Sr-90 I

Mn-54 I

Fe-59 I

Co-58 I

Co-60 page 1 of 1 Sampling N~*

Station O0A Zn-65 H-3 I

gr-89 Date Sr-89 03/26/14 06/24/14 09/30/14 12/31/14 1.1 3E+03 6.87E+02 1.85E+03 1.09E+03

[a]

[a]

1.79E+00 7.59E-01

[a]

[a]

[a]

[a]

4.68E+00 4.27E+00 2.54E+00 4.34E+00 8.32E+00 4.31E+00 4.81E+00 7.63E+00 8.60E+00 4.92E+00 3.99E+00 1.04E+01 4.38E+00 2.13E+00 1.40E+00 5.31E+00 9-74E+00 4.41E+00 5.86E+00 8.60E+00 Mean Sampling fl'3t*

7r-95 I

Nb-95 i

1-131 i

Cs-134 i

Cs-137 I

Ba-140 I

La-140 l

Date Zr-95 I

Nb-95 1

1-131 I

Cs-1 34 1

m 03/26/14 06/24/14 09/30/14 12/31/14 9.37E+00 9.56E+00 3.28E+00 8.38E+00 4.87E+00 5.39E+00 2.22E+00 4.52E+00 6.58E-01 5.33E-01 6.12E-01 7.80E-01 3.35E+00 7.44E+00 2.06E+00 5.09E+00 4.89E+00 3.30E+01 1.44E+01 5.73E+00 2.53E+01 5.51E+00 2.13E+00 1.50E+01 4.82E+00 5.22E+00 2.52E+01 8.56E+00 Mean

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

53

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

[pCi/L]

page 1 of 1 Sampling Date 01/14114 02/11/14 03/12/14 04115/14 05/12/14 06/17/14 07/15/14 08/11/14 09/16/14 10/15/14 11/12/14 12/16/14 MEAN Sampling Date 3.OOE+03 3.05E+03 2.99E-03 2.43E+03 2.87E+03 H-3 I

Sr-89 I

Sr-90 I

Mn-54"

[a]

[b]

[b) 3.79E+00 al

[b]

[b]

3.34E+00

+/- 1.23E+03

[b]

[b]

4.40E+00

[a]

[b]

[b]

< 4.25E+00 a]

[b)

[b]

4.98E+00

+/- 9.35E+02 4.29E+00 9.23E-01 4.28E+00

[a]

ib]

[b]

4.54E+00 a]

[b]

b]

4.81E+00

+/- 1.69E÷03

[b]

[b]

I 6.45E+00

[a]

[b]

(b]

3.03E+00 a]

[b]

[b]

4.61E+00

+/- 1.30E+03

[b]

[b]

3.07E+00

+/-

1.29E+03

+/-

+

+I-Fe-59*

9.31 E+00 8.08E+00 1.32E+01

<1.23E+01 S7.05E+00 8.31E+00 9.98E+00 8.13E+00 1.20E+01 "8.20E+00 9.34E+-00 7.54E+-00 I

Co-58" 3.94E+00 3.46E+00 6.66E+00 4.97E+00 4.33E+00 3.90E+00 5.09E+00 3.84E+00 6.60E+00 3.35E+00 4.82E+00 3.OOE+00 I

Co-60" 3.86E+00 3.93E+00 5.80E+00 5.20E+00 3.63E+00 3.74E+00 5.74E+00 4.98E+00 6.19E+00 3.58E+00 4.48E+00 3.29E+00 Station 11 Zn-65*

< 8.08E+00 7.06E+00 1.19E+01 1.05E+01

" 9.17E+00 7.37E+00 1.10E+01 I

8.68E+00 1.15E+01

" 6.27E+00 8.91E+00

" 5.60E+00 I

I Nb-95*

01/14/14 02/11/14 03/12/14 04/15/14 05/12/14 06/17/14 07/15/14 08/11/14 09/16/14 10/15/14 11112/14 12/16/14 MEAN 7.48E+00 6.92E+00 9.61 E+00 8.89E+00 9.19E+00 7.37E+00 8.74E+00 8.53E+00 9.51E+00 6.26E+00 8.10E+00 6.07E+00 Zr-95 I

1-131" I

4.85E+00 7.57E-01 3.64E+00 5.05E-01 7.03E+00 6.43E-01 5.01E+00 6.59E-01 5.23E+00 5.50E-01 4.18E+00 4.73E-01 6.07E+00 7.68E-01 3.91E+00 5.77E-01 5.54E+00 4.99E-01 3.19E+00 1.25E+00 4.96E+00 4.91E-01 3.23E+00 3.08E-01 Cs-134.9+

3.59E+00 3.57E+00 5.95E+00 4.50E+00 4.54E+00 3.86E+00 4.68E+00 4.07E+00 5.39E+00 3.17E+00 4.55E+00 2.80E+00 Cs-137+0 4.01E+00 S4.03E+00 6.61E+00

• 4.82E+00 5.13E+00 4.57E+00

• 5.03E+00

• 4.05E+00

• 5.66E+00 3.44E+00 5.03E+00

• 3.18E+00 Ba-140*

4.69E+01 1.97E+01 2.52E+01 3.29E+01 2.20E+01 1.96E+01 2.69E+01 2.35E+01 3.17E+01 2.06E+01 2.03E+01 2.05E+01 La-140o 1.46E+01 5.31E+00 8.42E+00 1.40E+01 6.30E+00 5.27E+00 7.01E+00 8.29E+00 1.19E+01 6.10E+00 7.01E+00 9.84E+00

+/-

• LLD identified in ODCM

[a] Tritium analyses on quarterly composite.

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

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

54

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

[pCi/L]

Sampling Date H-3*

01/14/14

[a]

02/11/14 1a]

03/12/14 3.07E+03

+1-1.22E+03 04/15/14

[a]

05/12/14

[a]

06/17/14 1.81E-03

-/-

8.15E-02 07/15/14

[a]

08/11/14

[a]

09/16/14 1.89E+03 10/15/14

[a]

11/12/14

[a]

12/16/14 3.OOE+03

+/-

1.35E+03 Mean 2.63E+03

+/-

1.32E+03 Sr-89 I

Sr-90

[b]

[b]

[b]

[b]

[b)

[b]

[b)

[b]

[b]

[b]

4.67E+00 8.48E-01

[b]

[b]

[b]

[b]

[b]

[b[

Mn-54*

3.77E+00 3.54E+00 4.61 E+00 5.48E+00 2.91E+00 2.91E+00 3.62E+00 3.22E+00 5.26E+00 2.90E+00 3.21 E+00 2.45E+00

+/-

Fe-59*

1 09E+01 7.42E+00 1.12E+01 1.09E+01 6.59E+00 6.02E+00 7.87E+00 5.71E+00 1.14E+01 6.88E+00 I

7.32E+00 5.31E+00

+1-Co-58" 4.91E+00 3.15E+00 5.35E+00 6.28E+00 3.46E-00 2.66E+00 3.34E+00 2.88E+00 5.70E+00 2.81E+00 3.66E+00 2.74E+00 Co-60*

3.64E+00 5.19E+00 4.95E+00 5.56E+00 3.63E+00 2.97E+00 4.20E+00 3.77E+00 5.30E+00 2.72E+00 2.74E+00 2 14F+00 page 1 of 2 Station 08 8.61E+00 7.16E+00 1.25E+01 1.15E+01 6.27E+00 5.46E+00 7.77E+00 6.19E+00 8.66E+00 5.36E+00 6.87E+00 4.20E+00

+/-

[b]

[b]

[b]

[b)

[b]

[b]

Sampling Date I

01/14/14 02/11/14 03/12/14 04/15/14 05/12/14 06/17/14 07/15/14 08/11/14 09/16114 10/15/14 11/12/14 12/16/14 Mean LLD identified in ODCM Zr-95*

8.02E+00 6.531+00 9.43E+00 9.13E+00 5.54E+00 5.59E+00 6.64E+00 4.49E+00 1.14E+01 5.42E+00 5.12E+00 4.22E+00 Nb-95*

I 1-131"*

I 5.08E+00 6.72E-01 3.27E+00 5.32E-01 6.02E+00 6.59E-01 S5.51E+00 6.62E-01 3.43E+00 5.68E-01 3.19E+00 4.65E-01 4.38E+00 5.99E-01 3.69E+00 6.59E-01 5.42E+00 4.84E-01 2.87E*00 6.23E-01 3.64E+00 5.49E-01 2.91E+00 4.69E-01

+I-

+/-

Cs-134" Cs-137" Ba-140*

3.99E+00 4.55E+00 4.82E+01 3.70E+00 3.60E+00 1.79E+01 5.55E+00 5.55E+00 2.77E+01 4.90E+00 4.85E+00 2.95E+01 3.21E+00 3.35E+00 1.58E+01 2.67E+00 2.92E+00 1.37E+01 4.06E+00 3.88E+00 1.94E+01 3.07E+00 3.59E+00 1.57E+01 4.64E+00 5.11E+00 2.93E+01 2.79E+00 2.91 E+00 1.79E+01 3.06E+00 3.69E+00 1.62E+01 2.30E+00 2.60E+00 1.88E+01

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

I La-140

</

-j 1.47E+01 5.14E+00 9.45E+00 1.15E+01 5.11E+00 4.96E+00 5.68E+00 4.58E+00 8.24E÷00 6.33E+00 5.53E+00 4.62E+00

[a] Tritium analyses on quarterly composite.

55

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

[pCi/L]

Sampling Station 09A Date H-3" Sr-89 Sr-90 Mn-54.

Fe Co-58.

Co Zn-65*

01/14/14

[a]

[b]

[b]

3.54E+00 9.10E+00 4.34E+00 3.92E+00 7.84E+00 02/11/14

[a]

[b]

[b]

3.50E+00 7.81E+00 3.91E+00 4.20E+00 7.32E+00 03/12/14 1.40E+03

[b]

[b]

5.03E+00 1.13E+01 5.79E+00 9.78E+00 1.08E+01 04/15/14

[a]

[b]

[b]

4.83E+00 1.26E+01 5.45E+00 5.44E+00 9.75E+00 05/12/14

[a]

[b]

[b]

3.80E+00 8.06E+00 4.39E+00 4-26E+00 8.03E+00 06/17/14 9.78E+02 4.36E+00 8.81E-01 4.42E+00 1.03E+01 4.52E+00 4.65E+00 6.78E+00 07/15/14

[a]

[b]

[b]

4.20E+00 1.07E+01 4.26E+00 5.57E+00 1.04E+01 08/11/14

[a]

[b]

[b]

4.64E+00 8.00E+00 5.39E+00 3.96E+00 9.07E+00 09116/14 1.89E+03

[b[

[b]

5.32E+00 1.13E+01 4.74E+00 4.61E+00 9.76E+00 10/15/14

[a]

[b]

[b]

3.32E+00 7.50E+00 3.24E+00 2.93E+00 5.64E+00 11/12/14

[a]

[b]

[b]

5.51E+00 1.05E+01 5.85E+00 4.24E+00 1.32E+01 12/16/14 1.69E+03

[b]

[b]

3.53E+00 7.45E+00 297E+00 3.23E+00 6.12E+00 MEAN

+/-

+/-

+/-

+/-

+/-

+/-

+/-

Sampling Date Zr-95*

Nb-95*

1-131*

i s-1_34.

Cs-137.

Ba-140 I

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

+/-

+/-

+/-

+/-

+1-

+/-

+/-

LLOD identified in ODCM

[a] Tritium analyses on quarterly composite.

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

56

Table 3-13 Sediment Silt Gamma Spectra, and Strontium

[pCi/Kg]

page Sample 1 of 1 Date I

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

I Cs-137" 4/15/2014 Station 08

[a]

[a]

1.29E+03

+/- 4.78E+02

< 5.04E+01

< 4.69E+01 Station 09A**

[a]

[a]

2.78E+04

+/-

1.73E+03

< 6.30E+01

< 7.47E+01 Station 11

[a]

[a]

1.83E+04

+/-

1.60E+03

< 6.59E+01

< 7.63E+01 Ra-226 I

Th-228 I

Th-232 I

4/15/2014 Station 08

< 1.10E+03 9.85E+01

+I-7.55E+01

< 1.98E+02 Station 09A**

1.97E+03

+/-

1.60E+03 1.08E+03

+/- 1.14E+02 8.69E+02

+/-

1.91E+02 Station 11 2.37E+03

+/-

1.40E+03 1.84E+03

+/-

1.22E+02 1.73E+03

+/-

2.01E+02 Sample Date I

Sr-89 Sr-90 K-40 I

Cs-134 I

Cs-137 10/15/2014 Station 08

< 1.80E+02

< 3.06E+01 1.87E+03

+/- 6.23E+02

< 3.31E+01

< 3.42E+01 Station 09A**

< 1.87E+02

< 2.86E+01 3.38E+04

+1-1.86E+03

< 5.OOE+01

< 5.54E+01 Station 11

< 1.87E+02

< 3.55E+01 2.68E+04

+/-

1.49E+03

< 4.85E+01

< 6.13E+01 Ra-226 I

Th-228 I

Th-232 I

10/15/2014 Station 08

< 9.43E+02 1.05E+02

+/- 5.91E+01

< 1.25E+02 Station 09A**

< 9.19E+02 4.48E+02

+/- 6.33E+01 4.14E+02

+/-

1.18E+02 Station 11 2.69E+03

+/-

1.05E+03 102E+03

+/-

8.16E+01 1.12E+03

+/- 1.26E+02 MEAN Sr-89 Sr-90 K-40 Cs-34*

I Cs-137l Indicator

+/-

+/-

1.21E+04

+/-

1.05E+03

+/-

+I-Control

+I-

+1-3.08E+04

+/-

1.80E+03

+/-

+/-

Ra-226 I

Th-228 I

Th-232 I

2.53E+03 +/-

1.13E+03 7.66E+02

+/-

8.46E+01 1.43E+03 +/-

1.63E+02 1.97E+03

+/-

1.60E+03 7.64E+02

+/-

8.87E+01 6.42E+02

+1-1.55E+02 Indicator Control

• LLD identified in ODCM

• • Control Station

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

57

Table 3-14 Shoreline Soil Gamma Spectra, and Strontium

[pCi/Kg]

page 1 of 1 Sample Date I

Sr-89 I

Sr-90 I

K-40 I

Cs-134 I

Cs-137-4/24/2014 Station 08

[a]

[a]

1.53E+03

+/-

5.54E+02 4.99E+01 5.96E+01 Ra-226 Th-228 Th-232 1.20E+03 1.49E+02

+/- 9.63E+01 2.65E+02

+/- 9.05E+01 Sample Date I

Sr-89 Sr-90 K-40 Cs-134" I

Cs.137 10/15/2014 Station 08 1.82E+02 3.70E+01 5.27E+02

+/-

5.31 E+02 4.80E+01 5.45E+01 I

Ra-226 I

Th-228 I

Th-232 I

1.26E+03 1.47E+02

+/- 7.41E+01 1.98E+02 I

Sr-89 I

Sr-90 I

MEAN K-40 I

Cs-134*

I Cs-137*

I

+/-

+/-

1.03E+03

+/-

5.43E+02

+/-

+/-

I Ra-226 I

Th-228 I

Th-232 I

+/-

1.48E+02

+/- 8.52E+01 2.65E+02

+/- 1.44E+02

• LLD identified in ODCM

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

58

Table 3-15 Fish Gamma Spectra

[pCi/Kg]

page 1 of 1 Fish [a]

Sampling Station 08 Date I

K-40 I

Mn-54' I

Fe-59*

I Co-58" I

Coo60.

I Zn-65*

I Cs-34 I

Cs-"137 I

04/16/14 1.96E+03

+/-

1.08E+03 9.49E+01

< 2.34E+02 8.59E+01

< 8.72E+01 1.77E+02 8.81E+01 9.55E+01 10/16/14 1.96E+03

+/-

8.77E+02 8.03E+01

< 1.46E+02 8.86E+01

< 8.63E+01 1.44E+02 6.82E+01 8.24E+01 Sampling Station 25*

Date I

K-40 Mn I

Fe-59 I

Co-58 I

Co-60 I

Zn-65 I

Cs-134-I Cs-137 I

04/16/14 2.41E+03

+/-

7.84E+02 5.90E+01

< 1.36E+02 5.52E+01

< 6.45E+01 1.29E+02 5.37E+01 4.80E+01 10/16/14 1.37E+03

+/-

8.41E+02 9.53E+01

< 1.84E+02 1.08E+02

< 9.41E+01 1.64E+02 8.16E+01 8.77E+01 catfish [b]

Sampling Station 08 Date I

K-40 I

Mn-54" I

Fe-59 I

Co-58" I

Coo60.

I Zn-65*

I Cs-34*

I Cs-137 I

04/16/14 1.58E+03

+/-

6.19E+02 6.24E+01

< 1.44E+02 6.22E+01

< 7.78E+01 1.28E+02 5.18E+01 7.27E+01 10/16/14 1.40E+03

+/-

6.94E+02 6.79E+01

< 2.06E+02 5.82E+01

< 8.24E+01 1.35E+02 6.39E+01 6.73E+01 Sampling Station 25*

Date I

K-40 Mn-54' I

Fe I

CoO58 Co"60 I

Zn-65' I

Cs-i 34' Cs-'137 I

04/16/14 10/16/14 1.58E+03

+/-

1.02E+03 2.35E+03

+/-

1.27E+03 6.72E+01 6.61 E+01 1.21E+02

< 2.28E+02 7.66Ei-01

" 1.18E+02

" 7.13E+01

" 4.61E+01 1.05E+02 2.36E+02 6.32E+01 8.31E+01 6.61E+01 1.12E+02 Mean 1.73E+03 +/-

8.98E+02 Indicator 1.73E+03 +/-

8.18E+02 Control 1.93E+03

+/- 9.79E+02

• LLD identified in ODCM

- Control Station

[a] Non-bottom dwelling species of gamefish.

[b] Bottom dwelling species of fish.

59

DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2014 and tabulated in Section 3, are discussed below. Except for TLDs, Teledyne Brown Engineering analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the TBE quality assurance manuals and laboratory procedures.

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

Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed.

The results of the Interlaboratory Comparison Programs are provided in Appendix B.

The predominant radioactivity detected throughout 2014 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Naturally occurring nuclides such as Be-7, K-40, Th-228 and Th-232 were detected in numerous samples. Th-228 & Th-232 results were variable and are generally at levels higher than plant related radionuclides.

The following is a discussion and summary of the results of the environmental measurements taken during the 2014 reporting period.

4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. TLDs are placed in two concentric rings around the station.

The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station.

TLDs are also placed in special interest areas, such as population areas and nearby residences.

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

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

Control and indicator averages indicate a steady relationship. Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location.

These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001. The 60

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

This will continue to be monitored.

9.0 8.0 7.0 6.0___

5.0 4.0

--$-Environmental TLI~s

-USector TLI~s 3.0

-- Avg. Pre-op 2.0 1.0 0.0 ko 0

N 9C.

9

'9 009 C

M0 0-4 C

10

'-I C

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

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

61

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

The highest quarterly average reading for any single location was obtained at location NW-29/61. This value was 7.1 mR/standard month. This location is on site on the north gate of the construction side laydown area. Quarterly and annual TLDs are also located at twelve environmental air sampling stations.

For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3.2 mR/standard month with a range of 1.6 to 5.8 mR/standard month. The average annual reading for these locations was 2.9 mR/standard month with a range from 2.0 to 4.1 mR/standard month. The control location showed a quarterly average of 2.7 mR/standard month with a range of 2.5 to 3.1 mR/standard month.

Its annual reading was 2.8 mR/standard month.

10 emergency sector TLDs, which are all located onsite had a quarterly average of 4.9 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.1 mR/standard month. Eight other TLDs, designated C-1 thru C-8, which were pre-operational controls, were collected quarterly from four locations.

Stations C-3/4 and C-7/8 are designated controls. These had a quarterly average of 3.15, while Station C-1/2 and C-5/6 had a quarterly average of 2.4 mR/standard month with a range of 1.6 to 3.4 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. The drop indicated in 2009 may be a function of a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this is in fact the case. Inner and outer ring monitoring locations c'ontinue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing.

During that time, nearly 740 nuclear weapons were tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady.

During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.

62

E C.

0.12 0.1 0.08 0.06 0.04 0.02 0

~~~~

0n r0 w-mNL)C 0

w w

m m

W 3

C u

u u

u cu C C,

2 8

C Cu C

Cu CD OC o

~N

(~)

.~

Control Sta-24 Indicator Average Pre-op Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 2.50E-02 2.OOE-02 1.50E-02 1.OOE-02 5.OOE-03 O.OOE+0O

• air-W-

I 0

(N

-4 U

~2J 0

-4 C

Cu m

-4 m

m

-4 C

M

-4 0

-4 0z

-4r m

1.*

Cu

-4

.q C

1;r 4)

-4 0z

-4 U,

Sta 24 Ctri

-U-Indicators Figure 4-3 2014 Gross Beta in Air Particulates (pCi/m 3) 63

4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine. Once a week the samples are collected and analyzed. The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl and the effect of the Fukushima Daiichi event.

4.4 Air 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.

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 2014.

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

7.

Twelve precipitation samples were obtained in 2014.

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

gamma emitting radioisotopes were detected.

No positive H-3 result was reported. During the pre-operational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison cannot be made to the 2014 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter.

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

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

Analysis results for cow milk are contained in Table 3-8. No sample indicated positive results.

Gamma spectroscopy did not detect the presence of any isotopes related to the operation of North Anna.

In years past, Cs-137 has been detected sporadically.

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

Once each quarter a sample from the collection station is analyzed for strontium-89 and strontium-90. Neither Sr-89 nor Sr-90 was detected.

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

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

4.9 Food Products and Vegetation Food/vegetation samples were collected from five locations and analyzed by gamma spectroscopy. The results of the analyses are presented in Table 3-9.

Low levels of Cs-137, attributable to fallout, have been seen periodically in vegetation samples.

As expected, naturally occurring potassium-40 and cosmogenic beryllium-7 were detected in most samples, and thorium-228 and other natural products, including Bi-214, were detected in some samples. No 65

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

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

These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, 1-131, and gamma emitters. The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period.

4.11 River Water Samples of water from the North Anna River were collected monthly.

The analyses are presented in Table 3-11.

All monthly samples are analyzed by gamma spectroscopy.

The monthly samples are composited quarterly and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90 in accordance with program requirements.

There has been no detection of these fission products at any of the indicator or control stations in recent years.

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

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

Tritium was measured in all four samples with an average annual concentration of 2870 pCi/liter and a range of 2430 to 3050 pCi/liter. These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were collected during the pre-operational period.

66

River Water 4500 4500 4000 4000 3500 3500

_j3000 3000 2500 2 5"-Tritium

--U1Required LLD 2000 2000 1500 1500 1000 1000 Figure 4-4 Tritium in River water 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma spectroscopy and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium.

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

No non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the samples. No tritium was detected at the control location. The average level of tritium activity at the indicator station was 2630 pCi/liter with a range of 1810 to 3070 pCi/liter.

Levels of tritium have increased since 1978 when the average level was below 300 pCi/liter. Levels measured at the indicator location (Station 8) are comparable to those measured since 1986, see Figure 4-5. During the pre-operational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter.

67

Figure 4.5Tritium in Surface Water 100I0 1000 0Ioo

-Required LLD Average Pre-op

-Tritium 10 3

w~

0 aL 0 ~

~

~

2

i.

2 L.t W

n 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.

Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectroscopy. The October samples were analyzed for strontium-89 and strontium-90. The results are presented in Table 3-13.

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

apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented. During the pre-operational period sediment samples were also analyzed by gamma spectroscopy. Figure 4-6 shows the historical trend of Cs-137 in sediments.

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

Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests.

A number of naturally occurring radioisotopes were detected in these samples at background levels.

1600 1400 1200 Station-8 S1000

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

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

ýýS@EgRaSDSC-Da-)SsBC30 Figure 4-6 Cs-13 7 in Sediment/Silt 4.14 Shoreline Soil Shoreline soil/ sediment, unlike bottom sediment, may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses.

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

The results are presented in Table 3-14.

69

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

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

4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake

Orange, were collected during 2014 and analyzed by gamma spectroscopy. Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately.

The results are presented in Table 3-15. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected. Cs-137 was measured in pre-operational environmental fish samples.

70

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2014 - North Anna Location 14B, 15,16,23, 26 14B, 15,16,23, 26 14B, 15,16,23, 26 STA I STA I 14B,15,16,23, 26 STA 5 STA 6 STA 0]A Description Vegetation Vegetation Vegetation

• AP/Char

• AP/Char Vegetation

• AP/Char

• AP/Char

• AP/Char Date of Sampling 01/14/14 02/11/14 03/12/14 03/12/14 03/19/14 04/08/14 04/29/14 09/23/14 10/28/14 Reason(s) for Loss/Exception Seasonal unavailability Seasonal unavailability Seasonal unavailability Sampler not running/ replaced. Minimum volume not met.

Sampler not running/ replaced. Minimum Volume not met.

Seasonal unavailability Sampler not running/ replaced. Minimum volume not met.

Sampler not running/ replaced. Minimum volume not met.

Sampler not running/ replaced. Minimum volume not met.

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

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

71

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

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

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

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

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

United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with IOCFR50, Appendix I", October, 1977.

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

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

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

HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.

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

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

72

APPENDICES 73

APPENDIX A: LAND USE CENSUS Year 2014 74

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

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden (>

Meat Milch Milch Boundary 50m2)

Animal Cow Goat N

0.9 1.3 1.78 2.9 NONE NONE NNE 0.9 0.9 1.22 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.37 2.4 2.65 NONE NONE E

0.8 1.3 2.04 3.5 NONE NONE ESE 0.9 1.7 1.7 NONE NONE NONE SE 0.9 1.4 1.54 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE S

0.9 1.03 1.02 2.0 NONE NONE SSW 1

127 1.33 2.0 NONE NONE SW 1.1 1.65 1.65 NONE NONE NONE WSW 1.1 1.62 2.22 1.62 NONE NONE W

1.1 1.5 1.93 4.4 NONE NONE WNW 1

1.1 2.67 4.98 NONE NONE NW 1

1.0 1.96 NONE NONE NONE NNW 0.9 1.0 1.22 2.3 NONE NONE 75

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

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2014 INTRODUCTION This appendix covers the Intercomparison Program of the Teledyne Brown Engineering - Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP).

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

77

E & Z Analytics:

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

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

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

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

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

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

78

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

Any sample analysis result that does not pass the criteria is investigated by TBE. Nonconformance Reports were generated and corrective actions taken as a result of this program.

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

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

The AP was flipped over and recounted with acceptable results.

NCR 14-09 A summary of TBE's results is provided in the tables on the following pages for the required sample matrix types and isotopic distribution.

Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result; analytical date; the known values supplied by the providers; pass or fail criteria.

80

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

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

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

W A

A A

A A

A A

A A

A A

A A

A A

A A

A W

A A

A A

A A

A A

A A

A A

A A

A A

A A

A E10856 E10858 Charcoal 1-131 pCi 74.1 Water Fe-55 pCi/L 2090 June 2014 E10913 E10914 E10916 Milk Milk AP Sr-89 pCi/L 85.9 Sr-90 pCi/L 13.8 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi 86.5 ill 255 147 123 105 155 106 251 218 95.1 215 122 95.1 88.7 81

Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi 115 72.6 193 179 116 76.7 189 168 85.2 0.99 0.95 1.02 1.07 1.00 A

A A

A A

E10915 Charcoal 1-131 pCi 85.6 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Value Month/Year Number Matrix Nuclide Units Value (a)

(b)

TBE/Analytics Evaluation (d)

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

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

E10948 E10950 E10951 pCi 83.9 Water Fe-55 pCi/L 2010 Soil Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 pCi/g pCi/g pCi/g pCi/g pCi/g 0.208 0.398 0.216 0.398 0.197 82

Mn-54 pCi/g 0.242 0.209 1.16 A

Fe-59 pCi/g 0.238 0.233 1.02 A

Zn-65 pCi/g 0.117 0.108 1.08 A

Co-60 pCi/g 0.447 0.438 1.02 A

December 2014 E11078 Milk Sr-89 pCi/L 85.7 95.7 0.90 A

Sr-90 pCi/L 12.9 15.6 0.83 A

El1079 Milk 1-131 pCi/L 85.9 95.1 0.90 A

Ce-141 pCi/L 205 219 0.94 A

Cr-51 pCi/L 402 406 0.99 A

Cs-134 pCi/L 156 164 0.95 A

Cs-137 pCi/L 194 198 0.98 A

Co-58 pCi/L 122 130 0.94 A

Mn-54 pCi/L 220 225 0.98 A

Fe-59 pCi/L 183 175 1.05 A

Zn-65 pCi/L 287 297 0.97 A

Co-60 pCi/L 224 235 0.95 A

83

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

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2014 El1081 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi 96.4 171 73.1 99.0 57.5 107 74.2 144 114 102 190 76.9 92.6 60.8 105 81.6 139 110 0.95 0.90 0.95 1.07 0.95 1.02 0.91 1.04 1.04 A

A A

A A

A A

A A

A A

El1080 Charcoal 1-131 pCi 93.5 98.2 0.9 E11082 Water Fe-55 pCi/L 1760 1970 0.8 (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.

W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable, reported result falls outside the ratio limits of < 0. 70 and > 1.30.

'5

'9 84

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)

Identification Reported Known Acceptance Value Month/Year Number Media Nuclide*

Units Value (a)

(b)

Range Evaluation (c)

March 2014 14-MaW30 Water Am-241 Cs-1 34 Cs-137 Co-57 Co-60 H-3**

Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90**

U-234/233**

U-238**

Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 14-MaS30 Soil 14-RdF30 AP 14-GrF30 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Cs-134**

Cs-1 37**

Co-57**

Co-60**

Mn-54**

Sr-90 Zn-65**

Gr-A Gr-B Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 0.764 20.7 28.0 26.5 15.6 NR 13.5 NR 0.911 0.751 NR NR NR NR

-0.201 2.02 1300 1069 1.32 1510 669 4.14 763 NR NR NR NR NR 0.8220 NR 0.606 0.7507 5.96 5.06 11.8 7.34 8.95 1.23 8.91 0.720 23.1 28.9 27.5 16.0 321 13.9 34.0 0.828 0.676 8.51 0.225 1.45 0.504 - 0.936 16.2 -30 0 20.2 - 37.6 19.3 - 35.8 11.2 -20.8 225-417 9.7 - 18.1 23.8 - 44.2 0.580 - 1.076 0.473 - 0.879 (1) 5,96-11.06 0.158 - 0.293 1.02-1.89 (1)

(1) 1238 867-1609 966 676-1256 1.22 (2) 1430 1001 - 1859 622 435 - 809 (1) 695 487 - 904 1.91 1.34-2.48 1.76 1.23 - 2.29 (1) 1.39 0.97-1.81 (1) 1.18 0.83-1.53 (1) 1.77 0.53-3.01 0.77 0.39-1.16 A

A A

A A

N (3)

A N (3)

N (3)

N (3)

N (3)

N (3)

A A

A A

A A

A A

A N (3)

N (3)

N (3)

N (3)

N (3)

N (3)

N (3)

A A

A A

A A

A A

A 14-RdV30 Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 6.04 4.74 10.1 6.93 8.62 1.46 7.86 4.23 - 7.85 3.32 -6.16 7.1 -13.1 4.85 - 9.01 6.03-11.21 1.02-1.90 5.50- 10.22 85

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)

Identification Reported Known Acceptance Evaluation Month/Year Number Media Nuclide*

Units Value (a)

Value (b)

Range (C)

September 2014 14-MaW31 Water Soil Am-241 Cs-134***

Cs-137***

Co-57***

Co-60***

Mn-54***

Ni-63 Pu-238 Pu-239/240 K-40***

Zn-65***

Cs-134***

Cs-137***

Co-57***

Co-60***

Mn-54***

K-40***

Sr-90 Zn-65***

Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 0.705 NR NR NR NR NR 24.07 0.591 0.0153 NR NR NR NR NR NR NR NR 694 NR 0.88 18.4 24.7 12.4 14.0 24.6 0.618 0.0048 161 10.9 622 1116 779 1009 824 858 541 0.62-1.14 (1) 12.9-23.9 17.3 - 32.1 8.7 - 16.1 9,8-18.2 17.2 - 32.0 0.433 - 0.803 (2) 113-209 7.6 - 14.2 435 - 809 (1) 781 - 1451 545 - 1013 706 - 1312 577 - 1071 601-1115 379 - 703 A

N (4)

N (4)

N (4)

N (4)

N (4)

A A

A N (4)

N (4)

N (4)

N (4)

N (4)

N (4)

N (4)

N (4)

A N (3)

N (4)

N (4)

A 14-MaS31 14-RdF31 14-GrF31 AP AP Sr-90 Gr-A Gr-B Bq/sample 0.310 Bq/sample 0.153 Bq/sample 0.977 0.703 0.492 - 0.914 September 2014 14-RdV31 Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 7.31 8.93 10.8 6.31 7.76 0.738 7.16 0.53 1.06 7.38 8.14 9.2 6.11 7.10 0.85 6.42 0.16 -0.90 0.53-1.59 5.17-9.59 5.70- 10.58 6.4 - 12.0 4.28 - 7.94 4.97 - 9.23 0.60-1.11 4.49 - 8.35 A

A A

A A

A A

86

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

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

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

(1) False positive test.

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

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

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

Value (b)

Limits (c)

May 2014 RAD-97 MRAD-20 RAD-99 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 38.25 24.65 89.1 45.55 91.15 65.10 244 45.65 27.95 23.75 9.61 8435 pCi/filter 28.0 36.7 26.5 87.9 44.3 89.1 64.2 235 61.0 33.0 25.7 10.2 8770 46.0 31.4 21.8 49.1 89.8 98.8 92.1 310 37.6 27.4 20.3 5.80 6880 27.5-43.6 19.2-30.9 74.0- 96.7 35.5-48.7 80.2-101 57.8-73.1 212-275 31.9-75.8 21.4-40.7 21.3-30.3 7.95-11.8 7610-9650 15.4-71.4 22.8-38.1 15.6-25.7 40.3-54.5 73.7-98.8 88.9-111 82.9-104 279-362 19.4-48.1 17.3-35.3 16.8-24.4 4.34-6.96 5940-7570 A

A A

A A

A A

A A

A A

A A

November 2014 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 30.4 18.6 46.8 88.0 99.0 92.5 325 29.9 27.5 15.8 5.74 6255 A

A A

A A

A A

A A

N (1)

A A

MRAD-21 pCi/filter 27.3 36.9 12.4 - 57.3 A

(1) The Iodine-131 was evaluated as failed with a ratio of 0. 778. No cause could be found for the slighly low activity. TBE would evaluate this as acceptable with warning. A rerun was not possible due to 1-131 decay. All ERA Iodine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown 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.

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