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Radiological Environmental Monitoring Program January 1, 2017 to December 31, 2017
	ML18128A264
Person / Time
Site:	North Anna
Issue date:	12/31/2017
From:	; Virginia Electric & Power Co (VEPCO)
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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ML18128A283	List: ML18128A263; ML18128A264;
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Dominion Energy North Anna Power Station Radiological Environmental Monitoring Program January 1, 201 7 to December 31, 201 7 Prepared by Dominion Energy, North Anna Power Station

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2017 to December 31, 201 7 Prepared by:

Bradley T. Pleasants, Jr.

Supervisor Radiological Analysis and Instrumentation Dominion Energy North Anna Power Station Reviewed by:

Barbara J. Thompson Superintendent Health Physics Technical Services Dominion Energy North Anna Power Station Approved by:

C George R. Simmons Manager Radiological Protection and Chemistry Dominion Energy North Anna Power Station 2

Table of Contents

1. EXECUTIVE

SUMMARY

.............. ... ........ ........... ........ ....... ... ..... .... ..... ... ... ... ........ ....... .... ... ........... .4

2. PROGRAM DESCRIPTION ............................................................................................................ 6 2.1 Introduction .... ................ ..... ...................... .... ........... ........ ..... ......... .. .... .. ......... ........ .... .... ........ 6 2.2 Sampling and Analysis Program ....... .... .... ......................... ..... .... .. ..... ... ... ..... .... .. ...... ........... ... 7

3. ANALYTICAL RESULTS ....... ....... ......... ... ............ ............. ...... ..... .... .. ... ... ... ... .... .. ....................... 21 3.1 Summary of Results ................... ....... ...... ..... ............ ...... .... ........ ... .. .... ............ ......... .... ...... ... 21 3.2 Analytical Results of 2017 REMP Samples ........... ....... .. ... .. ..... ... ... ... ... ..... ... ... .... ..... ... .... .... 29

4. DISCUSSION OF RESULTS ........ ..... ...... ...... ........ ...... ......... ..... ........ ............ ..... ....... .. ...... ..... ........ 57 4.1 Gamma Exposure Rate ........... ............... ... ............. ..... ...... ..... ..... ......... ..... .............. .............. 57 4.2 Airborne Gross Beta.. ..... ....................................... ....... .... ...... ... .... ... ..... ......... .. .............. ........ 58 4.3 Airborne Radioiodine ..... .............. .... ...... ............... ........ ......... .... ............................................ 60 4.4 Air Particulate Gamma .......... ..... .... ............................................................. ... ........... ........ ... 60 4.5 Air Particulate Strontium .. .. ... ..... ........ ................ .......... ... ....... ... ... .. ... ... ........... ...... .............. .60 4.6 Soil ........................................ ....... ...... .......... .... .......................................................... ........... 60 4.7 Precipitation .... ...... ....... ..... ... .... ... ........ ........ ........ ...... ..... ... ...... ... ... ... ... .... ... ... .... ..... ... ...... ...... 60 4.8 Cow Milk ...................... ....... .. .... ........ ................ ....... .... ...... ..... ... .. ........ ... ... ...... ..... ............... 60 4.9 Food Products and Vegetation .... ............... ..... ........... ........ ..... .............................................. 61 4.10 Well Water ........... ..... .. ....... ......... ........ ...... ..... ... ....... ... ..... ...... ........................ ....... .... .. ........ 61 4.11 RiverWater ..... ..... ...... ..... ... .... .......... .................... .... .... .. ... ..... ...... ... ... ... ..... .. ... ...... ...... ........ 61 4.12 Surface Water ... ..... ................. .... ............ .. ...... .... ....... ........ ..... ...................................... ....... .62 4.13 Bottom Sediment ........... .... ... .... ..... ..... ...... ........ ....... .... .. ......... .. .. ... ... ... ... ............................ 63 4.14 Shoreline Soil ........................ ......... .... ........ ...... .... .... .. .... ..... .. ... ... ... ............ ..... ... .... ..... ....... .64 4.15 Fish ......... ... .... .... ................................................................................ .. .... ......... .... ....... ........64

5. PROGRAM EXCEPTIONS ... ........ .... ........... ...... .. .. .... ...... ... ..... ........ .. ... ... ... .. ...... .... .... .................. 65 REFERENCES ......................................................... ...................... .......... ............... .... .. .... .. ........ .... .... 66 APPENDICES ..................................... ..... ..... .... .... ........ .... .. .... .. ..... ..... ..................... ........................... 67 APPENDIX A: LAND USE CENSUS ..... ...... ....... ...... ....... ...... ... ....... ... .. .. .... ........................ ........ .68 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS ............................... 71 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2017 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, 2017, 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 are monitored within a 25-mile radius of the station. North Anna Power Station (NAPS) personnel collect a variety of samples within this area. A number of sampling locations for 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 (NAPS) or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station (NAPS), can be compared to the environment surrounding the station. Indicator samples are the second sample type 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.

Mirion Technologies 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. Because of this, the Nuclear Regulatory Commission (NRC) requires equipment used for radiological environmental monitoring 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 2017 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 2017 was 5243 pCi/liter. No other plant related isotopes were reported in any surface or river water. River water collected from the North 4

Anna River, 5.8 miles downstream of the site had an average tritium level of 4570 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 2017 .

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 due to weapons testing, Chernobyl, and Fukushima.

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

During 2017, 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 2017 was 0.628 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 2017 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).

The North Anna Power Station of Virginia Electric and Power Company (Dominion Energy) 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. Mirian Technologies 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 reporting level concentrations listed in 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 2017 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.

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~ 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 2017 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 2017.

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TABLE 2-1 North Anna Power Station - 2017 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental NAPS Sewage Treatment Plant 01 0.20 NE 42° Quarterly & Annually Dosimetry (TLD) Fredericks Hall 02 5.30 SSW 203 ° Quarterly & Annually Mineral, Va 03 7.10 WSW 243 ° Quarterly & Annually Wares Crossroads 04 5.10 WNW 287° Quarterly & Annually Route 752 05 4.20 NNE 20° Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N 11 ° Quarterly & Annually Levy, VA 06 4.70 ESE 115° Quarterly & Annually Bumpass, VA 07 7.30 SSE 167° Quarterly & Annually End of Route 685 21 1.00 WNW 301 ° Quarterly & Annually Route 700 22 1.00 WSW 242° Quarterly & Annually "Aspen Hills" 23 0.93 SSE 158° Quarterly & Annually Orange, VA 24 22.00 NW 325° Quarterly & Annually Control Bearing Cooling Tower N-1 /33 0.06 N 10° Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 11 ° Quarterly Parking Lot "C" (on-site) NNE-3/35 0.24 NNE 32° Quarterly Good Hope Church NNE-4/36 3.77 NNE 25 ° Quarterly Parking Lot "B" NE-5/37 0.20 NE 42° Quarterly Lake Anna Marina (Bogg 's Dr) NE-6/38 1.46 NE 34° Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 74° Quarterly Route 689 ENE-8/40 2.43 ENE 65 ° Quarterly Near Training Facility E-9/41 0.30 E 91 ° Quarterly "Morning Glory Hill" E- 10/42 2.85 E 93 ° Quarterly Island Dike ESE-11/43 0.12 ESE 103° Quarterly Route 622 ESE-12/44 4.70 ESE 115° Quarterly DVP Biology Lab SE-13/45 0.64 SE 1380 Quarterly Route 70 1 (Dam Entrance) SE-14/46 5.88 SE 137° Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 158° Quarterly Elk Creek SSE- 16/48 2.33 SSE 165° Quarterly NAPS Access Rd. S-1 7/49 0.36 s 173° Quarterly 8

TABLE 2-1 North Anna Power Station- 2017 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 s 178° Quarterly Thermoluminescent NAPS Access Rd. SSW-19/51 0.24 SSW 197° Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 205 ° Quarterly 500kv Tower SW-21 /53 0.60 SW 218° Quarterly Route 700 SW-22/54 3.96 SW 232° Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 237 ° Quarterly Route 700 (Exclusion Boundary) WSW-24/56 1.00 WSW 242° Quarterly South Gate Switchyard W-25/57 0.32 w 279° Quarterly Route 685 W-26/58 1.55 w 274° Quarterly End of Route 685 WNW-27/59 1.00 WNW 30 1° Quarterly Route 685 WNW-28/60 1.40 WNW 303° Quarterly North Gate - Laydown Area NW-29/61 0.52 NW 321 ° Quarterly Lake Anna Campground NW-30/62 2.54 NW 319° Quarterly

1/#2 Intake NNW-31/63 0.07 NNW 349° Quarterly Route 208 NNW-32/64 2.21 NNW 344° Quarterly Bumpass Post Office C-1 /2 7.30 SSE 167° Quarterly Orange, VA C-3/4 22.00 NW 325° Quarterly Control Mineral, VA C-5/6 7.10 WSW 243 ° Quarterly Louisa, VA C-7/8 11.54 WSW 257° Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 42 ° Weekly and Radioiodine Biology Lab OlA 0.64 SE 1380 Weekly Fredericks Hall 02 5.30 SSW 203 ° Weekly Mineral, VA 03 7.10 WSW 243 ° Weekly Wares Crossroads 04 5.10 WNW 287° Weekly Route 752 05 4.20 NNE 20° Weekly Sturgeon's Creek Marina 05A 2.04 N 11 ° Weekly Levy, VA 06 4.70 ESE 115° Weekly Bumpass, VA 07 7.30 SSE 167° Weekly 9

TABLE 2-1 North Anna Power Station- 2017 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO . 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Airborne Particulate End of Route 685 21 1.00 WNW 301 ° Weekly and Radioiodine Route 700 22 1.00 WSW 242° Weekly "Aspen Hill s" 23 0.93 SSE 158° Weekly Orange, VA 24 22.00 NW 325° Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 148° Monthly (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 WNW 295 ° Monthly Control (Route 669 Bridge)

River Water North Anna River (downstream) 11 5.80 SE 128° Monthly Ground Water Biology Lab 01A 0.64 SE 138° Quarterly (Well Water)

Precipitation Biology Lab 01A 0.64 SE 138° Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon)

Lake Anna (upstream) 09A 12.90 WNW 295 ° Semi-Annually Control (Route 669 Bridge)

North Anna River (downstream) 11 5.80 SE 128° Semi-Annually Shoreline Soil Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon)

Soil NAPS Sewage Treatment Plant 01 0.20 NE 42° Once/3 years Fredericks Hall 02 5.3 0 SSW 203 ° Once/3 years Mineral, VA 03 7.10 WSW 243 ° Once/3 years Wares Crossroads 04 5.10 WNW 287° Once/3 years 10

TABLE 2-1 North Anna Power Station- 2017 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 20° Once/3 years Sturgeon's Creek Marina 05A 2.04 N 11 ° Once/3 years Levy, VA 06 4.70 ESE 115° Once/3 years Bumpass, VA 07 7.30 SSE 167° Once/3 years End of Route 685 21 1.00 WNW 301 ° Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 242° Once/3 years "Aspen Hills" 23 0.93 SSE 158° Once/3 years Orange, VA 24 22.00 NW 325° Once/3 years Control Milk Lakeside Dairy 12A 7.50 NW 310° Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon)

Lake Orange 25 16.5 NW 312° Semi-Annually Control Food Products (Vegetation) Stagecoach Road l4B 1.22 NNE 40° Monthly if available or at harvest Route 614 15 1.37 SE 133° Monthly if available or at harvest Route 629/522 16 12.60 NW 314° Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 158° Monthly if available or at harvest "Historic Lane" 26 1.15 s 172 ° Monthly if available or at harvest 11

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQ!.IEN~Y ANALYSIS LLD REPORT !.!NITS Thermoluminescent Dosimetry (TLD)

(84 TLDs) Quarterly Gamma Dose 2 mR+/-2mR rnR/std. Month (12 TLDs) Annually Gamma Dose 2mR+/-2mR rnR/std. Month Airborne Radioiodine Weekly 1-131 0.07 pCi/m3 Airborne Particulate Weekly Gross Beta 0.01 pCi/m 3 Quarterly (a) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs- 137 0.06 2"d Quarter Sr-89 (b) pCi/m 3 Composite Sr-90 (b)

Surface Water Monthly 1-1 31 l(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-13 7 18 Ba-140 60 La-140 15 Quarterly( a) Tritium (H-3) 2000 pCi/L 2nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

River Water Monthly 1-131 l(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-13 7 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 thi s is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

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

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

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

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

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

Sr-90 (b)

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

Cs-134 15 Cs-137 18 Ba-140 (d)

La-140 (d)

Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180

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

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

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TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA :EREQUEN~X ANALXSIS LLD B.EfQRI UNIIS Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

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

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

Sr-90 (b)

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

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

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

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

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

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

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

(b) 1n Orange (c) ln Lake Orange 15

SSW Legend

- Frxed Environmental Mo

ring Slation TLD Locations Scale - 318 inch =235 ft Figure 1. North Anna Site Radiological Monitoring Locations 16

~ ~ TSYLVAIIA l North Anna Environmental Map

Fixed Environmental Sampling Location

TLD Sampling

. Garden Residents

Meat Animals

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North Anna Environmental Map e Fixed Environmental Sampling Location e TLD Sampling 4t Garden Residents e Meat Animals Original c 1991 by AOC d Alexandria, Inc.* 6440 Genernl Green~.

I Alexandria, VA 22312, USED WITH PERMISSION. No other reproduction may be made without the written permission of AOC.

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19 WNW e Fixed Environmental Sampling Location e TLD Sampling 4t Garden Residents e Meat Anima 1s 1 Origin:il O 1091 by AOC of Alex:mclii:i. Inc., 6440 Gener:il Green W<>y.

Alex:mdri:i. VA22312 . U SED WITH PEAM ISSlctl. No other reproduction m:,y be rn:ide wilhout 1he written permission Di ADC.

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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 2E 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 summanes.

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RADIOLOGICAL EN VIRONMENTAL MONITORIN G PROGRAM S UMMA R Y Page 1 of 7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

NORlli ANNA NUCLEAR POWER STATION, LOUISA COUN"TY, VIRGINIA 20 17 Docket No. 50-338/339 2017 Mediooia- lncfca!Dr Contra Non-R ~

Palhway Ana!y5is Toca! LLD' Locanons Locatfon with Hi Mean locafions Reported Sampled Type Mean Distance Mean Measuremen Ums Number Din!clion Direct Radiation Gamma 2M 2 4.1 (2ffi'255) 25157 0.32mi. 0 (mR.grJ. Month) Dose (0.8-9.0) w

{Sector TLD:;)

Cl'4 -718 ~ far control locations Dil"Kt Radiation Gamma 31 2 2.7 (1C!/lll) C-1/2 7.30 mi. 3.l {E',"8) 3.2{1!1115)' 0 (mR.grJ. Ablfh) Doff (1.7-4.1 ) SSE (2.2-4.1) (1.7-.S.1)

{Pre-oper.,SoraJ 1W.sJ

C3/4, -718 ~ fwooolml locations Direct Radiation Gamma 40 2 5.1 {40/40) EPSP 0.37 mi. 72 {SSJ 3.2 {1!\1'15)' 0

{mR.grJ_Month) Doff (2.1~.1) OPJ10 ENE (5.9-9.1) (1.7 -,5.1)

(Errie,gen;y Secmr Tl.D:i)

C3l4, -718 ~ fw control locations Dir-Kt Radiation Gamma 48 2 3.2 {44144) STA-23 O.Q3mi. 4.8 {4s-tl 2.Q{4.t4) 0 (mR.gd. Abllh) Doff (1.2~.11 S.."E 13.J~.1) (1.6-4.1)

(EnvironmeffaJ 1W.s}

Direct Radiation Gamma 12 2 3.0 (11111 ) STA-23 0.113 mi. 4.5 (1!1)> 3.1 (trt ) 0 (mR.grJ. AllnlhJ Doff (1.3-4.5) SSE {4.5) (3.1)

(Amua/ TLD:;J Air Particublle GR-8 676 ,0.0 1 13.6 (6241624) *02 5 .30 ML 15J {52,'fQ} 4..5 (52152) 0 (fe"" pC.ihn (3.6-2U} SSW (7-27.3) (6..5-23.8)

GAMMA 52 l!E.-7 52 133.5 (48148) 02 5.30 mi. m.3 (414) 134.2 (4i'4) 0 (87.J...201 .7) SSW (147.A-201.J) (1112-148.7) 0 Cs-134 52 0.0 (0/48) NIA NIA 'A (Qi4) 0 C-s-137 !52 o.oe. {OJ48) NIA N!A rA (014) 0

!:c-89 13 {OJ12) NIA N!A (A (Qi1) 0 9--GO 13 (0/12) NIA NIA (A (Qi1) 0 Air Iodine 1-131 676 0.07 (0/62A) NIA NrA NrA (0!52) 0 (1e"" pCim',

Soil* GAMMA 0 (pCilgdry) K.J!,ll 0 WA NIA rA rA 111,'A 0 CS-134 0 150 WA NIA NIA 'A 111,'A 0 CS-137 0 180 N!A NIA rA NrA N!A 0 FG-226 0 NIA NIA NIA NIA NIA 0 Th-228 0 NIA NIA NIA WA NIA 0

' Soi Sa"l)les required triennially. Samples rd obtained in 2017

' mR/sld monlh for TLDs 22

RADIOLOGICAL ENVIRONMENTAL MONITORIN G PROGRAM S UMMAR Y Page 2 of7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

NORTli ANNA NUCLEAR POWER STATION, LOUISA COUNTY. VIRGIJIIIA20 17 Docket No. 50-338l33920 17 Me<riurn or lncicator Control Non-Routine Pathway Analysis Total LLD' Locaiions Localion wilh Hi Locations Reported Sampled T~ Mean Disbnoe ~ Measurement Unils l'llrnber Direction Soil" (cont'd) Th-232 0 NIA Ni'A NrA 0 (pCitg dr:I)

Sr-89 D l'&'A NIA NrA NrA NtA 0 Sr-W D WA Ni'A NrA NIA NIA 0

' S o l ~ ~rad lrienni:alll . Samples not obtained in 2017 p~ GR~ 12 4 5.3{12112) 0 1A 0.64mL 5..3 (12/12) NIA D (pa1ifl'r) (1.7-18.2) SE {1.7-1&2)

H-3 12 2000 {0/1 2) -NIA N'A N'A NIA D GAMMA 2 Be-7 2 (OQ) Ni'A N'A NrA. NtA D Mn-54 2 15 (OQ) ,N,'A NfA NIA NIA D Fe-59 2 30 (0/2) NIA NfA NrA NIA D Co-58 2 15 (0/2) ,N,'A NIA NIA l'&'A D Co-60 2 15 {0/2} 1Ni'A NfA NIA NIA D Zn-65 2 30 (0/2} 1Ni'A N!A NIA NtA 0 Z,..g§ 2 30 (Q/2) NIA NfA NfA NtA D Nt,.,1!5 2 15 (Q/2} *Ni'A NrA. NIA NtA 0 1-13 1 2 10 (OQ) N!'A NIA NrA NIA 0 Cs-134 2 15 (0/2} Ni'A NfA NIA NlA 0 Css137 2 18 (0/2) Ni'A N!A NIA NIA 0 Ba-140 2 (0/2) NIA Ni;&. NIA NIA 0 23

RADIOLOGICAL ENVIRONMEN TAL MONITORIN G PROGRAM S UMMARY Page 3 of 7 RADIO LOGICAt E NVIRONMENT.Ill. MONITORING 'PROGMM $t1MMARY NORTH AK.NA NUCL:EAR POIVER STATION, LOUlii/\ COUNTY, VIRGI NIA. 2017 DOOlel Na. Sil),,JJE\13351 2017 Pwle<IIJmor tllliCa!Or control NOO-ROO!I Pattrway Anal)'516 T'lltll LlO' Locaftm& Locatlonwr.n eil ,M ean LccaDom; Repor1E,111 T)'pe Ncm!JE !Mean i1 >>;1ance Mean Mean Meaiisemeru Ran } Numller oo-ecllon

[contd) La-14 11 2 (Ql7) Ni,\ N'A NIA NIA 0 Th-228 2 {012) NJ:A. N'A NIA NIA ll 1111111 GAMMA 12 (l>Cl!llhll')

K-40 12 1250 112112) 121\ 7 .Elllml. 1250 (1 2112} NIA ,[1 1102D-1457) NIV (1020.1451) 1-131 12 t IIN121 Nl,\ N'A NIA NIA ,o C:.-134 12 16 jltl121 Ni,\ N'A NIA NIA ,D C:.-1J7 12 us jM21 NlA N'A NIA NIA 0 Ba,-140 12 61) jM21 llliA. N.'A NIA N!A 0 La-140 12 15 jlN121 Ni,\ N'A NIA NIA 1D SR-S, 4 (Ol'4) Nl,\ N.'A NIA NIA ,o

( q u ~)

Sfts,O 4 (Ql4} NiA N'A NIA N!A D

( qullllleey) food & V1911ta11on GAMMA JS

[IICL'!lwell BE-7 35 1570 (Zi'1'2BI 26 1.15ml 1758 (717 ) 1fi4.D(7fl l ,o (3n~OO] $ ['QW200) (U7-2nD]

K-40 35 5945 j25,'2BI 15 1-:nm1. 6523 (717) 5526 (717 ) ,o 1301C,-108501 $E f-4415-1042.'0I ('53t~IM1}

1-131 35 60 1um1 NiA N'A NIA (Ql7) ,o C:.-1~ 35 60 N.i'.A N'A NIA IQl7) ,[1 1um1 C:.-137 JS 80 1om1 NiA N'A N/A (Ql7) ,o Ra-226 35 871 13.'28) UB 1..22 ml. 9 16 ( 1fl) (Ql7} 0 (l!W1C] NNE 1'1'1 Al:>-226 35 2.0 (E.'28 ) 26 u sml. JS7 (217) 158 ( 1.171 0 (70-521} s [2-'2-4531 (158)

Th-228 JS 64 (6128) 23 ..93ml 95 (I ll} 88 (317) 0 (4~5) SSE ('5) (73-120)

Th-232 35 90 (t /26) 26 1. 15ml. 90 (1128) (Ql7) 0 (SO} $ ('O}

Grollnll w.11waler H-3 4 2000 (Ol4) Nl,\ N'A NIA NIA ,o (pCHle!J GAMMA 4 Ml1*S4 4 15 (014) Nl,\ N'A N/A NIA D f f'-59 4 JD (0/4} Nl,\ N'A NIA NIA D 24

RADIOL OGICA L EN VIRONMEN TA L M ONITORIN G PROGRAM S UMMAR Y Page 4 of 7 RADIOLOGICA.t ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

HORTH ANNA NUCLE,6.R POWER STATION, LOUISA COUNTY, VlRGJNIA 2017 DDClel No. 50-336,1339 2017 Medl.Jm or r i ~r C4nlrol Noo-Roottn,e Patnway Arlaly$15 T01al LlD' l ocaflans Loca!llln wllll H.lfle s l Mean LooaU11i11S Reported sampled O'a1.t mce (IJJl~l Gro und w.11water (conta)

T)'j>e Co-58 NumlJEI 4 --

1-5 Mean (Ranae\

(014)

Nlllnl>erl

NIA OO"EctlOII

NIA I Me.ill

[Ftanae1 NIA Meaill ffl:anael

NIA Mea5Ul'E'me111 0-

{}l'CHntJ Co-50 4 15 (0/4} NIA ~'A NIA IIIIA ,Q Zll-65, 4 JO (014) NIA ~'A N1A NIA ,o 2Hl5 4 JO (0/4} NIA ~'A NIA 1'1/A ,o Nb-95 4 15 {014) NIA NIA NfA NIA ,I )

H J1 4 tD (0/4) Nl'A ~'A NIA NIA ,o C&-134! 4 15 {0/4) Nl'A ~ 'A NfA NIA 0 C&-137 4 t6 {0/4) NIA ~'A NIA Ni'A Ba.-140 4 all (0/4) NIA ri'A NIA NfA 0 La-t4D ,4 ts (0/4) NIA ~ 'A N!A NIA 0 Sr-89 1 {0/1) NIA ~'A NIA Ni'A D Sr-9D 1 {0/1) NIA WA NIA NIA RIWr Waiar H-3 ,4 2100,n, 457D (41'4) 1t s..w,m1. 457D (41'4) (1114)" 0

/)l'CHntJ (3S8~0} SE (~1>-64.211)

GAIIIIA 12 Mll-54 12 ts (0/121 NIA NIA lil1A (lll't2}" ,o f,~ 591 12 JO (0/12) NIA ~ 'A NfA (lll't2}" 0 Ce>-58 12 15 (0/12) NIA l'i'A NIA (0112}," ,o Co-60 12 15 (0/121 i'i!A WA NIA (0112 )," ,o

Reil& Cf 5tafaee walB!aUn ill lacaUon o~ u&ed a,,oaml valu:e lbr r:.-erwaier 25

RADI OLOGICAL ENVIRONMENTAL M ONITORING PROGRAM

SUMMARY

Page 5 of 7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SlJMMARY ORTH ANNA NUCL'EAR POWER STATION, LOUISA COUNTY, VIR.GINIA 2017 Doctet No. 50-33Et339 2il17 Medl:Jmor rna:cator CGnlrOI Non-RooDne P'atl!Way A/laiy515 LLD' LocatlXl& ocailonwlih, Reported T)'pe Me or.51ance Mear;urement Ran Nwnller O!l'l!cikXl

<IJ Zn-65 12 JO (0/121 NIA Nr.A 0 Zr-95 12 JO (DJ121 NIA Nr.A NIA (0/12)," D Nt>-95 12 15 (0/121 NIA WA NIA (0/1 2}" D J-131 12 (DJ121 NIA Nr.A NIA (0/1 2)" ,o C&-134 12 15 (DJ121 NIA Nr.A NIA (0/1 2)" 0 C&-13,7 12 16 (0/121 NiA WA NIA (0/1 2)" *D 6ir140 12 60 (0/121 NIA f'!(A H/A (D/12)" *D u-1,0 12 15 (111121 NIA WA NIA (0/1 2)" *D Sr-fl 9 {on) NiA Nt;A NIA (011)" 0 S r-9D {on) NIA N'A NIA (011)" *D Surface wat.r H~ ~. 2000 52A3 (414) e 3.37ml. 5243 (41'4) (~) D

<PC*mi:i (37'0-7130) SSE (3l'SO-l130]1 GAIRIA 24

S4 24 15 1111121 NIA N'lt. NIA 4111121 0 F~59 24 JO (0/121 NIA Nt;A NIA IDl121 *D CO-SB 24 15 (111121 NIA Nt;A H/A (111121 *D Co,60 24 15 (111121 MA WA NIA (111121 *D Zn-65, 24 JO (111121 NIA WA NIA (111121 D Zr'-95 24 JO 1111121 NIA Nt;A NIA (111121 D

" RM ,Cf (laf,ace waier tale at. IOc3llon D!?A u5ed a, con!rot value lbr uwaier 26

RADIOLOGICA L EN VIRONMENTAL MONITORIN G PROGRAM S UMMAR Y Page 6 of 7 RADIOLOGICAL ENVIRONMENTAL MOOITORING PROO_RAM

SUMMARY

HOffi"H AN.NA NUCLEAR PO\VER STATION, LOOISA COUNTY, VIRGINIA 20 17 Doct:el No. 50-JJe-1339 :Nl17 MedlJmor ricrcator Conlrol NOO-RDUlln.e Pathway Maiy51$ Tola! LlD' ux:atDns Loca1Jonwllll e,1M.e an Localloos Repolied Type Nlmbe Meilll O!l&tmce Ran Nt.mllle r Oltectlon Nl>-95 24 JD f0/121 NIA N'A 1-131 24 t f0/12) NIA N'A NIA f0/12) *D C&-134 24 15 f0/12) NIA N'A NIA f0/121 ,o C&-137 24 16 f0/12) NIA N'A NIA (01121 ,o Ba-140 24 6D 1on21 NIA N'A NIA (0/121 0 l ,H4D 24 ts (0/121 NIA N'A NIA (0/121 Sr-89 2 (On) NIA N'A NIA (Of1) I)

Sr'9D 2 (On) NIA N'A NIA (Of1} 0 sectlmantHt GAMMA 6 OJCl'lg ,131)')

K-40* 6, 1 t e.2J (414} n 5.Wrnl. 22255 (2.02 } 26320 (2/2) D (980-23510) SE !21021).23.510) (21030~1C10)

C&-134 6 150 {"Ol4} NIA N'A NIA f0/2) ,o C&-137 6 180 {"Ol4]1 NIA N'A NIA f0/2) ,c Ra-226 6 (OU) NIA N'A NIA 2209 (2/2) ,c (12'3-315"}

lb-226 6, ,U!I, (.cJ41 n Saf.il ml. 726,(212) 855(2'2) 0 fSII~, S£ [~,HIU) [71W5:3) lb-232 6 722 (2>41 u 5,f.il,rnl. 722 (2l'4) 665(2'2) ,c (S5C-e5'J SE [~HS,) (544-715)

!;r-89 J (Ca} NIA N'A NIA (Of1) ,o sr.go J (O!Z} NIA N'A NIA (Of1) ,o 27

RADI OL OGICA L EN VIRONMENTAL M ONITORIN G PROGRAM S UMMA R Y Page 7 of7 AADIOW-GICAl. ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

HORTH AK~ NUCLEAR: POWER STATION, LOUISA COUNTY, VIRGINIA 2017 Doctel No.. ro-3361339 .2G17 Medi.Im or lllll'C.1!0r Control Nan-Rootlne

?alrrway Analy&lli TDtll LlD' locat:oo& LocatJon wllh Hldlle&I M_u n LocaUoo& R.eporte,d Mean Meilll Meiill Sample!!

IU'1115l Sholllln8 Sol l);>e GAMMA Num.llel 2

(R.anlJl!l Ntmlllerl m&tance Oll"eC1lon I (RanDl!l (Ranoi!'I

~a&WemEilll (pCl'kg Illy)

K-40 2 1144 (212) Oil 3.37ml 1144 (2l2) NIA D

('"8-12'1) SSE [9'8-12S1)

C&-134! 2 150 ,[0.12) Ni,\ N.~ NIA N!A D C&-137 2 1110 ,[0.12) NIA N.~ NIA NIA ,o lle-7 2 397 (tt2:1 Oil 3a37 ml. Jf11 ( 1.1'21 N.rA 0 (3971 SSE IS371 Ra-22Jfi 2 (012) NIA N.~ NIA NIA ill ll:l-22E/ 2 (Ql'l} Nii\ N.~ NIA N!'A 0 ll:1-232 2 {012) NIA N.'A "'1(A NIA 0 SHl9 1 ,[GIi) NIA 111.'A NIA NIA 0

!I')

Sr~D 1 (Qrl) NIA N.~ NIA N!'A 0 ti')

fleb - obi.,- G.iUIIIA g (jlCL'!J wet)

K...uJ1 a, 1S(l1 (4~) Oil 3-37 ml. 1931 (41'41) 2162 (41\ll) 0 (1331-2:la.&) SSE {1331-220,&) (12lls-3DS2}

Mn-54 8, 130 (0/.&) NIA N.'A NIA IOU) ,I)

F e-531 g 250 (OJ,&) NIA N.'A NIA (OU], ,11 Co-<58 8 130 (0/.&) NIA N.~ NIA (QI.&) ,11 Co-liO 8, 130 (Q/.&) Ni,\ 111.'A NIA (OI.&) 0 Zr.-65 8, 250 (OJ.&) NIA N.'A NIA (OU) 0 C&-1341 a. 130 {0/,&) Ni,\ NrA N/A (OU} 0 C&-137 8, 150 (0/.&} NIA NrA NIA fOl4) D 28

3.2 Analytical Results of 2017 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 (2<J) 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 2E error.

Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data 1. 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 AnnaODCM.

Data are given according to sample type as indicated below.

1. Gamma Exposure Rate

2. Air Particulates, Gross Beta Radioactivity

3. Air Particulates, Weekly I-131

4. Air Particulates, Quantitative Gamma Spectra

5. Air Particulate Strontium

6. Soil

7. Precipitation

8. Cow Milk

9. Food Products and Vegetation

10. Well Water 11 . River Water

12. Surface Water

13. Bottom Sediment/Silt

14. Shoreline Soil

15. Fish 1

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

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

29

TAB LE J.2 QUARTERLY GAMMA EXPOSURE RA TE (mRIStd. Mo th) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter 12127/ 2016- 3/29/2017 6/28/ 20 17 9/27/2017 Quarterly Average*

Station 3129/2017

- - --- *- -- - - - -* - -6/28/2017

9/Z//20 17

12/26.12017 _ _ (.w-1 2 S.D. --,

N-1 5.0 4.3 3.3 5.8 4.7 (.w-) 1.8 N-33 5.0 4.0 4 .2 5.9 N-.2 2.7 2.1 2.1 4.3 2.9 (.w-) 1.0 N-34 4.0 2.1 1.9 4.0 NNE-3 6.8 6.1 5.8 7.4 62 (.w-) 1.9 NNE-35 6.2 5.4 4.4 7. 1 NNE-4 4.9 3.0 3.3 4.3 4.0 (.w-) 2.2 NNE-36 4.3 2.7 3.7 6.0 NE-5 6. 1 4.2 3.3 4.9 4 .2 (.w-) 2.0 NE-37 4.8 3.9 3.0 3.7 NE-6 3.7 3.5 2.3 4.4 3.3 (+/-) 1.7 NE-38 3.5 3.2 1.8 4. 1 ENE-7 5.9 4.3 4 .4 6.1 5.7 (+/-) 2.2 E E-39 6.4 5.2 5.4 7.7 E E-8 2.6 2.1 1. 1 3.4 2.4 (+/-) 1.6 E E-40 2.8 (1) 1.7 3.1 E-9 6.4 4.6 4 .0 4.9 4.8 (+/-} 2.0 E-41 4.9 3.8 3.5 5.9 E-10 4.3 3.2 .2.5 5.4 4.0 (+/-) 1.0 E-42 4.7 3.3 3.3 5.1 ESE-11 4.1 3.2 3.3 4.9 3.9 (+/-) 1.9 ESE-43 5.0 3.4 2.4 4.6 ESE-12 4.9 4.5 3.3 5.8 4.5 (+/-) 1.6 ESE-44 4.3 4.4 3.5 4.9 SE-13 3.9 3.8 3 .2 4.6 3.9 (+/-) 12 SE-45 4.0 3.2 3.7 4.9 SE-14 6.7 5.2 4.5 6.6 6. 1 (+/-) 2.1 SE-46 6..S 5.9 5.2 7 .7 SSE-15 5.0 3.6 4.3 5.8 4.5 (+/-) 2.1 SSE-47 4.3 3.7 3. 1 6.0 SSE-16 2.7 2.1 1.6 3.1 2.5 (+/-) 1.8 SSE-48 2.7 2.0 1.5 4. 1 S-17 5.1 4.6

3.5 6.6 4.5 (+/-) 2.4 S-49 5.1 3.3 3.0 5.1 (1) no not co lected.

Average of collocated TLDs 30

TAB LE 3-2 QUARTERLY GAMMA EXPOSURE RAT E (mRIStd. Monlh) +/- 2 Sigma Rrst Quarter Second Quarter Third Quarter Fourth Quarter 12/27/2016- 3m*2017 6128/2017 9/27/2017 Quarterly Average*

Station 3/29/2017 S-18___ - --Tg-- - -6/28/20

- - -- 17

-- 9/27/2017

12/26/20 17

--2.:;- - -

__ (+I-) 2 S.D. __ ,

2.1 1.5 1.9 (+/-) 0 .5 S-50 2.2 1.6 0.9 2.1 SSW-19 6.1 5.6 5.2 5.1 5.7 (+/-) 1.6 SSW-5 1 6.0 5.2 4.8 7.3 SSW-20 2.5 1.6 1.6 2.2 1.9 (+/-) 1.1 SSW-52 2.3 1.4 1.1 2.5 SW-21 4.3 3.7 3.1 4.6 4.0 (+/- ) 0.7 SW-53 4.2 4.0 2.9 4.9 SW-22 4.4 3.9 3.9 5.4 4.3 (+/-) 1.5 SW-54 4.6 3.3 3.5 5.1 WSW-23 4.2 3.4 4.2 5.1 4.4 (-#-) 1.8 WSW-55 5.3 3.2 3.8 5.7 WSW-24 4.0 4.0 3.0 4.9 3.9 (+/-) 1.3 WSW-56 4.5 3.3 32 4.1 W-25 9.0 5.9 4.9 7.2 6.9 (+I-) 2.4 W-57 7 .0 6.7 6.8 7 .8 W-26 3.5 2.3 2.1 62 3.0 (+/-) 2.9 W-58 2.6 28 1.5 3.3 WW/-27 3.2 27 3.6 3.8 3.3 (+/-) 1.7 WW/-59 4.5 26 1.9 4.0 WW/-28 29 1.8 2.3 4.3 2.8 (-#-) 2.1 WW/-60 3.9 1.9 1.7 3.9 W/-29 8.2 5.4 6.5 6.0 6.6 (-#-) 1.1 W/-61 6.8 6.9 5.1 7.6 W/-30 3.1 1.6 0.9 2.4 1.9 (+/- ) 1.8 W/-62 21 1.3 0.8 2.9 NNW-31 3.6 3.5 2.1 4.6 3.5 (+/-) 1.8 NNW-63 3.4 4. 1 2.1 4.2 NNW-32 4.9 2.9 3.2 3.9 3.6 (+I-) 20 NNW-64 3.8 2.7 2.3 4.9 Mean 4.1 (..J-) 1.0

Average of collocated TLDs 31

TABLE 3-2 QUARTERLY GAMMA EXPOSURE RATE (mR/Std. Month) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter 12/27/2016- 3129{20 17 6128/2017 9/27/2017 Quarterly Average*

Slation

--4:o___

3/29/20 17 6/2812017

9/27/2017

*--3.2 12/26120___

17 (+I-) 2 S.D.

C-1 2.2 2.6 3.1 (+/* ) 1.4 '

C-2 3.0 3.0 2.3 4.1 C-3.. 3.3 2.5 1.8 3.8 2.7 (+/* ) 1.8 c-4** 3.0 1.9 1.7 3.9 C-5 2.1 1.7 1.8 2.5 2.2 (+/-) 1.0 C-6 3.1 1.7 2.0 2.7 c-r** (1) 3.1 2.1 4.0 3.7 (+/-) 2.1 c-8** 5.1 4.2 2.8 4.5 Indicator Mean 2.6 (+/-) 0 .6 Control Mean 3.2 (+/-) 0 .5 EPSA-01-* 4.6 3.8 3.8 5.9 4.5 (+/-) 1.0 EPSA-02... 5.1 3.3 3.9 5.7 EPSF-03... 4.2 7.3 2.3 5.8 4.5 (..!-) 32 EPSF-04... 4.4 4.0 2.7 5.0 EPSR-05*** 5.7 4.7 3.5 7.4 5.4 (.+I-) 2.8 EPSR-06*** 5.8 4.8 4.0 7.1 EPSJ-or* 4.6 4.6 2.5 3.2 3.8 (..!-) 1.1 EPSJ-08-* 4.7 3.3 2.1 5.1 EPSP-09-* 7 .2 5.9 6 .3 7.8 7.2 (+/-) 2.4 EPSP-10-* 9.1 6.7 6.1 8.6 Mean 5.1 (+/-) 2.0 (I) TLD not collected

Average of oo located TLDs .

.. Control Location

-*Emergency Plan TLDs.

32

TABLE 3-2 QUARTERLY GAMMA EXPOSURE RATE (mRIStd. Month) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Q uarter 12/'ll/ 2016-- 3/29/2017 6/28/2017 9/27/2017 Quarterly Average* Annual Station 3/29/20 17 6/28/2017 9/27/ 2017 12/26/2017 (+/-) 2S.O. TLO STA-01 4.8 3.7 2.5 5.5

--4.1 (+/-)_2.6__

3.3 STA-02 2. 1 2. 1 1.8 23 2.1 (+/*) 0.4 1.6 STA-03 23 1.5 1.6 28 2.1 (+/-) 1.2 1.3 STA-04 26 1.8 1.2 3.7 2.3 (+/-) 2.2 2.5 STA-05 3.3 2.5 1.7 3.9 2.9 (+/-} 1.9 3.1 STA-05A 25 2.6 1.7 3.3 2.5 (+/-) 1.3 2.6 STA-06 4.4 4.7 3.5 5.3 4.5 (+/-) 1.5 3.9 STA-07 3.2 3.0 2.8 3.6 3.2 (+/-} 0.7 3.1 STA-21 3.4 2.7 2.1 3.8 3.0 (+/-) 1.5 3.1 STA -22 4.1 4.3 3.2 4.1 3.9 (+/*} 1.0 3.7 STA -23 5.2 3.7 4.1 6. 1 4.8 (+/-) 2.2 4.5 STA-24** 3.5 2.5 1.6 4.1 2.9 (+/-) 22 3.1 Mean lncicator Locations 32 (+/-} 1.4 3.0 (+/-) 1.9

Average ol collocated TLOs.

- Control 33

TABLE 3-3 AIR PARTICULATES GROSS BETA RAD IOACTIVITY (10-3 pCi/m3 )

LOCATIONS PERIOD ENDI NG

- - - -(+/~ 01 ,_____ __ _ - - --- --

02 , 03

04

- ,____05( +/-) __, 06

- - - - (+/-) -* ------- 07

- 21

(+/-) (+/-) (+/-) (+/-) (+/-)

01/04/17 11.20 2.190 11.20 2210 10.70 2.240 12.60 2.310 9.520 2.130 8.640 2.060 10.80 2_1 90 10.60 2.200 01/11/17 11.20 2.460 13.80 2.620 14.50 2.660 12.90 2.570 12_90 2.570 7_530 2.240 1220 2-520 10_40 2.420 01/17/17 12_50 2.880 11.80 2.830 11.50 2.810 15.50 3.050 11 .50 2_810 11-00 2.780 10.60 2.750 12.60 2.880 01/24/17 8 .510 2-320 7_020 2_220 7 ..500 2_250 7-330 2.240 9.590 2.390 7.950 2.280 9200 2-370 7.030 2.220 01/31/17 ,8..340 2_330 11.60 2.530 9.290 2-380 10.20 2.440 10.10 2.440 9.750 2.410 8.930 2.360 8_690 2.340 02/07/17 17.20 2_890 20.70 3.070 18.60 2960 15_30 2_790 18.90 2_980 17.40 2_900 16.10 2.830 14.00 2.720 02/14/17 17.70 2_830 19_80 3.060 1820 2.780 19-60 2_890 15.20 2_650 15.70 2_590 18.30 2_840 15.70 2.670 02/22/17 13.50 2-300 14.40 2.370 14.60 2.430 13.70 2.350 11.90 2_240 14.20 2.370 14.00 2_350 12.40 2280 02/28/17 '9 .430 2.730 14.80 3.030 12.80 2.820 11 .20 2.780 13.50 2.930 12.70 2.890 10.90 2.790 14.10 2_940 03/07/17 14.30 2.620 18.00 2.830 14.50 2.710 16.30 2.770 16.90 2_800 15.00 2.690 16.30 2.750 14.70 2.710 03/15/17 11.20 2.250 15.20 2.480 14.10 2.420 12.20 2.310 12.40 2.320 12.80 2.340 14.40 2.430 13.10 2.360 03/21/17 14.70 3.030 1820 3.230 12.80 2.930 14.30 3.010 10.30 2.770 11 .60 2.850 16.80 3.150 13.60 2.980 03/29/ 17 16.50 2.710 20_20 2.900 20.30 2.910 17.50 2.790 < 2.840 16.80 2.740 15.70 2.680 18.10 2810 04/04/17 7.090 2.560 8-560 2.640 8.820 2.640 6.440 2.480 8 .260 2.620 6.410 2.490 7210 2.550 6.780 2.500 04/11/17 9.950 2.330 11.50 2.400 12.20 2.380 13.60 2.530 12_10 2.440 10.70 2. 360 10.40 2-330 12.20 2.420 04/19/17 14.50 2.410 16.10 2.520 17.60 2.630 14.60 2.480 13.90 2.410 13_00 2.360 14.80 2.460 13.90 2.420 04/25/17 9.250 2.650 9.600 2.660 7.910 2.590 6.230 2.420 7.720 2.560 4.890 2.330 7.240 2.510 5.620 2.400 05/03/17 11.90 2.230 10_90 2.200 11.20 2.160 10.60 2.380 9.030 2_070 9.910 2.130 9.940 2.130 9-220 2.070 05/09/17 10.00 2.830 7.370 2.580 9.410 2.720 8.760 2.670 5.990 2.480 6.330 2.510 7.560 2.600 6.260 2.510 05/16/17 11.60 2.580 12_00 2.610 10.40 2.510 7.010 2.290 9.360 2.450 9.820 2.480 11 .80 2.590 11 .20 2.550 05/23/17 15.70 2.830 17_80 2.940 18.50 3.020 15.50 2.850 12.50 2.640 14.40 2.750 13.40 2.700 11.90 2.610 05130/17 7.690 2.330 10.90 2.540 9.570 2.430 3_570 2.040 7.390 2.330 9.120 2.430 11 .50 2.570 8_320 2.370 06/06/17 15.00 2-790 17.90 2.970 15.00 2.810 14.10 2.770 11.00 2.600 16.10 2.870 16.90 2.910 14.20 2780 06/13/17 13.10 2.530 13.60 2.520 16.20 2.750 11 .70 2.440 16.10 2.680 14.90 2.610 13.70 2_540 9.510 2.310 06/20/17 15.00 2690 15.40 2.710 18.10 2.870 12.00 2.510 9.110 2.320 14.50 2.660 12.90 2.570 9-150 2.330 06/28/17 13.50 2.490 16.70 2650 12.60 2-350 16.90 2.620 13.50 2.450 10.30 2280 14.80 2_530 14.50 2.500 34

TABLE 3-3 AIR PARTICULATES GROSS BETA RAD IOACTIVITY (10-J pCi/m))

LOCATIONS PERIOD 03 04 05 END ING

01

- - - -(+/-) 1-- - --

02

(+/-)

- -- 06--(+{-)--* --- -- 07

(+/-)

,- -- 21

(+{-)

07!05117 12.40 2.930 16.70 3210 15.80 3.180 16.10 3.1 90 12.60 3.020 12.30 3.010 14.70 3.120 13.30 3.040 07/11117 14.10 2.890 12:90 2 .780 15.10 3.010 13.60 2.860 10.00 2.620 13.60 2.830 14.30 2.870 12.70 2.810 07118/17 16.10 2.890 23.50 3260 14.70 2.810 22.60 3210 16.40 2.890 20.40 3.110 20.20 3.100 18.10 2.990 07/25117 15.10 2.730 20.10 2 .990 21.00 3.030 18.70 2.920 17.90 2.880 17.40 2.850 21.40 3.050 19.20 2.950 08!02117 9.680 2.190 12.20 2.340 1290 2.380 8.000 2.090 9.960 2.210 11 .90 2.320 10.30 2.240 9.780 2.690 08/08/17 11.40 2.690 14.20 2.870 13.70 2.840 13.20 2.810 14.50 2.890 10.90 2.670 12.70 2.780 11.70 2.720 08/1 5/17 13.10 2.630 16.90 2 .830 12.30 2590 14.20 2.680 11.10 2.510 15.10 2.730 14.40 2.690 15.60 2.770 08/22117 20.30 3.070 25.00 3.310 19.50 3.020 20.80 3.100 16.80 2.890 20.70 3.090 20.60 3.090 18.40 2.970 08/30/ 17 9.11 0 2.070 14.60 2 .390 8.860 2.060 12.40 2260 8.980 2.060 11.90 2240 12.90 2.290 13.40 2.320 09/05117 17.30 3.210 12.80 2.950 15.50 3.110 12.30 2.920 13.40 2.990 15.80 3.130 16.50 3.170 15.90 3.140 09/12117 11.00 2.420 11 .00 2.420 10.70 2.400 10.10 2.360 7.130 2170 12.90 2.530 9.020 2300 11 .10 2.430 09/19/17 14.10 2.620 15.00 2 .670 15.20 2.690 17.90 2.840 11.00 2.430 1420 2.630 14.90 2.670 14.00 2.620 09/27117 17.60 2.510 22.50 2 .750 14.90 2.370 20.20 2.650 13.90 2.330 14.60 2.360 14.50 2.350 18.70 2.580 10104/ 17 14 .00 2.530 13.60 2.490 14.10 2.510 14.40 2.530 12.30 2.400 11 .90 2.380 14.20 2.520 14.90 2.560 10110/ 17 10.90 2.570 11.20 2.590 13.80 2.790 7.960 2.400 9.580 2.490 11.90 2.640 11.20 2.590 13.80 2.790 10/17117 8.960 2.160 10.50 2 .310 7.480 2.010 5.880 1.930 7.550 2.080 8.440 2.150 7.560 2.090 7.760 2.070 10/24/17 22.20 3.170 25.20 3 .260 28.50 3.510 28.80 3.470 22.70 3.160 24.40 3240 23.10 3.170 27.30 3.390 10/31117 9.170 2.290 11.60 2 .570 11.10 2.540 10.60 2.380 8.800 2.270 11 .70 2.450 8.290 2.230 8.730 2.260 11/08/17 15.00 2.420 16.70 2.530 13.80 2.320 14.80 2.410 14.50 2.400 15.00 2.430 15.90 2.470 17.50 2.540 11/15/1 7 16.30 2.780 22.10 3.060 20.00 3.020 16.80 2 .800 13.80 2.620 14.90 2.720 17.90 2.840 19.40 2.950 11/21/17 17.80 3.230 22.10 3.450 18.00 3.240 22.50 3.470 18.50 3.260 14.00 3.010 18.40 3.250 18.80 3280 11 /28/17 19 .00 2.840 18.30 2.950 16.50 2.610 16.00 2.680 1520 2650 17.30 2.770 15.20 2.660 20.90 2.930 12105/17 23.10 3.380 27.30 3.500 26.40 3.460 27.50 3.510 22.10 3.260 22.20 3.260 25.40 3.410 22.10 3.260 12113/17 17.40 2.620 16.60 2.590 17.30 2.690 15.20 2. 550 14.40 2.520 15.60 2.560 14.10 2.480 15.40 2.560 12119/ 17 11.00 2.710 18.50 3.160 18.60 3.170 18.40 3.150 17.80 3.140 13.90 2.890 18.30 3.140 12.60 2.820 12/26/17 16.10 2.840 1820 2 .920 17.60 2.800 15.00 2.700 17.90 2.870 10.30 2.460 13.60 2.660 13.90 2.640 Mean 13.52 2.638 15.66 2.759 14.62 2.698 14.11 2.666 12.70 2.590 13.17 2.615 13. 96 2.658 13.51 2.642 35

TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (10-3 pCi/m 3)

LOCATIONS PERIOD ENDING

- - - 22 -- -- 23 24*

01A ,________05A ,

(+/-) (+/ -) (+/-) - (+/-) (+/-)

0 1/04/17 6.900 1.970 10.90 2.190 11.90 2280 8.940 2.060 10.00 2.160 0 1/11/ 17 8.600 2.310 12.90 2 ..560 15.10 2.690 9.750 2 .370 15 .20 2.700 0 1/17/17 8 .810 2.640 11.30 2.80~ 14.30 2.980 10.30 2 .740 14.90 3.020 0 1/24/17 7.340 2.240 8.970 2 .350 9.920 2.420 6.780 2200 9 .360 2.380 0 1/31 /17 6 .980 2.230 9.010 2 .370 7 .650 2280 7.670 2280 9.600 2.400 02/07/17 11.80 2.590 20.20 3.040 14.20 2.720 11 .50 2.570 14.70 2.750 02/14/17 15.00 2.630 19.20 2.900 18.50 2.810 17.80 2 .830 19.50 2.880 02/22/17 '9 .990 2.140 14.90 2 .390 11 .80 2.260 8-410 2 .010 14.10 2.370 02/28/1 7 '9 .690 2.670 12.50 2 .900 12.90 2.850 7.690 2.600 9 .900 2.710 03/07/ 17 10.40 2.440 18.00 2.840 15.60 2.760 10.50 2.400 17.80 2.850 0311 5/1 7 10.60 2.2 10 14.90 2.460 13.50 2.380 11 .60 2.270 13..30 2.370 03/2.1/1 7 11.50 2.860 15.70 3.090 14.10 3.010 13.70 2.970 13.90 2.990 03/29/17 11.00 2.470 19.90 2 .880 21 .00 2.940 14.40 2.610 18.10 2.810 04/04/1 7 4 .580 2.340 8.220 2.630 11.80 2.830 5.380 2.430 11.10 2.790 04/1 1/1 7 8.700 2.200 13.20 2520 12.60 2.430 13.60 2.550 7 .650 2.150 04/1 9/1 7 11.10 2.270 16.20 2.5 10 14.80 2.480 14.30 2 .400 14.50 2.440 04/25/17 4.4 10 2.310 7.090 2.500 7.980 2.570 6.910 2.490 6 .430 2.470 05/03/17 7.220 1.940 10.10 2150 13.40 2.300 9.800 2.140 11 .10 2.190 05/09/ 17 6 .870 2.550 7.820 2.610 6 .470 2.650 6.690 2.540 6 .590 2.530 05./1 6/17 8 .160 2.360 9.420 2.450 10.40 2.510 10.60 2.520 10.40 2.510 05/23/17 12.40 2.640 18.00 2.950 14.00 2.740 11 .60 2.590 14 .90 2.780 05/30/1 7 7.920 2.340 10.90 2.530 1120 2.560 9.940 2.480 10.90 2.540 06/06/ 17 10.60 2. 570 17.00 2.920 18.10 2.980 14.00 2.760 14.30 2 .770 06/13/1 7 15.50 2.670 15.00 2.600 12.50 2.510 10.40 2 .320 11.20 2.410 06/20/17 12.40 2.540 17.80 2.850 14.30 2.650 14.30 2.650 13.00 2.570 06/28/1 7 8 .520 2.160 13.60 2.490 15.80 2.540 12.80 2.450 14.90 2.530 "Control Station 36

TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (10-3 p Ci/m 3 )

LOCATIONS PERIOD ENDING 22

(+/-)

23

(+/-)

- --24* --(+/-)-- 01A

(+/-)

05A

(+/-)

0 7/05/17 11-60 2.950 12.30 2.990 15.80 3.180 10.90 2 .920 14.20 3.100 07/1 1/17 13.60 2.870 15.50 2.930 14.40 2.930 9.450 2.540 15.60 2.970 07/1 8/17 13.20 2.720 12.90 2.710 18.20 2.990 12.10 2.660 22.80 3.220 07fl.5/17 14.30 2.690 19.60 2 .960 13.90 2.660 15.10 2 .730 20.90 3.030 08/02/17 8 .000 2.090 13.00 2.390 12.30 2.350 9 .680 2.190 12 .00 2.330 08/08/1 7 7.780 2.460 13.50 2.820 9.240 2.560 8.950 2.530 12.50 2.770 08/15/17 6.050 2.200 13.00 2 .620 14.50 2.710 10.90 2 .500 12.30 2.570 08/22/17 13.90 2.710 2320 3.2 10 18.80 2.980 15.50 2 .820 20.00 3.060 08/30/17 10.90 2.180 12.10 2.250 13.40 2.320 10.80 2.170 15.50 2.430 09/05/17 11 .90 2.890 18.50 3.280 17.70 3.230 14.00 3.020 12.00 2.900 0 9/12/17 7.480 2.200 10.20 2.370 12.70 2.520 10.10 2.360 10.40 2.380 09/19/17 7.170 2.170 17.20 2.800 17.60 2.820 11.80 2 .480 18.30 2.860 09/27/17 20.40 2.670 17.60 2.520 22.40 2.750 14.60 2 .350 21.00 2.690 10/04/17 16.10 2.620 14.20 2.530 13.40 2.470 9.790 2.260 13.40 2.470 10/10/17 12.40 2.700 10.20 2.530 12.40 2.690 10.40 2.540 11.50 2.620 10/17/17 10.20 2.250 6.800 2.060 10.60 2.240 7.850 2140 9 .620 2.220 10/24/17 20.00 3.040 25.90 3.280 23.80 3.270 22.00 3.080 22.30 3.150 10131/17 9.910 2.340 9.250 2 .300 8.360 2.240 9.990 2 .340 7.470 2.180 11/08/17 13.10 2.310 11.70 2 .260 12.90 2290 13.50 2.370 15.20 2.430 11115/17 12.80 2.580 17.70 2.820 17.80 2.850 13.90 2.600 12.80 2.560 11/21/17 16 .60 3.160 15.50 3.100 18.60 3.270 13.10 2.960 16.10 3 .130 11/2.8 /17 15.80 2.660 17.80 2.820 17.00 2.670 11 .90 2.490 17.50 2.770 12/05/17 24.30 3.370 25.10 3.400 22. 10 3.260 19.40 3.130 25.10 3 .400 12/13117 14.40 2.510 18.20 2. 660 17.10 2.660 16.40 2 .570 14.20 3.370

12119/17 17.20 3.090 16.90 3.060 18.80 3.190 16.50 3.040 12.70 2.820 12/26/17 14.00 2.620 17.30 2.900 14.60 2.690 15.40 2 .800 12.60 2.580 Mean 11-35 2.507 14.57 2 .693 14.47 2.691 11.80 2 .535 13 .95 2.675 Mean all indicatior location 13.58 2.640

Control Station 37

TABLE 3-4 AIRBORNE IODINE (10-3 pCilm 3}

LOCATIONS PERIOD ENDING 04 07 21

- --- -----01 ----* 02

~ 03

-- ----~-~ *~-------- 05

-------- 06 01/04117 < 24-36 < 24.70 < 25.51 < 25.00 < 21.12 < 2 1.03 < 20.'96 < 21 .22 01/1 1117 < 12.08 < 28.89 < 28.89 < 28.89 < 28.89 < 22.21 < 22.21 < 22.21 01 /17117 < 11.72 < 27.83 < 27.83 < 27.89 < 27.89 < 30.43 < 30.43 < 30.43 01/24/17 < 12.83 < 30.53 < 30.59 < 30.53 < 30.53 < 26.90 < 26.90 < 26.95 01/31/17 < 9.597 < 27.21 < 27.17 < 2721 < 27.21 < 26.38 < 26.38 < 18.50 02/07/1 7 < 29.04 < 11.28 < 29.04 < 29.04 < 29.04 < 32.36 < 32.36 < 32.36 02/14117 < 12.66 < 34.58 < 31 .19 < 31 .79 < 31.9 1 < 48.36 < 48.53 < 47.85 02/22/17 < 14.68 < 26.89 < 27.77 < 27.22 < 27.14 < 26.50 < 26.38 < 26.78 02/28117 < 12.55 < 29.48 < 28.24 < 29.0 0 < 29.11 < 29.93 < 30.05 < 29.44 03/07117 < 26.08 < 11.11 < 27.34 < 26.72 < 26.62 < 18.78 < 18 .72 < 19.18 03/15117 < 11.75 < 28 .01 < 27.97 < 28.01 < 28.01 < 12..24 < 31 .5 1 < 31,46 03/21117 < 12.12 < 28.91 < 29.03 < 28.91 < 28.91 < 37.06 < 37.06 < 37.21 03/29117 < 12.06 < 34.39 < 34.55 < 34.66 < 34.50 < 3208 < 32.08 < 32.23 04/04117 < 17.48 < 33.63 < 33.29 < 3329 < 33.49 < 35.68 < 35.68 < 35.32 04/ 11/17 < 10.20 < 23.98 < 23.08 < 23 .94 < 23.98 < 19.84 < 19.77 < 19.49 04/1'9/17 < 12 .7*9 < 23.56 < 24.04 < 24.07 < 23.60 < 26.17 < 26.13 < 26.4 1 04/25/17 < 12.42 < 29.36 < 30.09 < 29.25 < 29.72 < 24 .40 < 24.54 < 24.59 05/03/17 < 11 .47 < 27.66 < 26.66 < 3125 < 27.40 < 25.41 < 25.49 < 25.14 05/09/17 < 11.44 < 2628 < 26.39 < 2628 < 26.28 < 24 .61 < 24.66 < 24.66 05/16117 < 16.56 < 39.48 < 39.54 < 39.54 < 39.61 < 24 .70 < 24.65 < 24.61 05/23117 < 14 .57 < 37.51 < 38.24 < 38.04 < 37.44 < 38.65 < 38.65 < 38.65 05/30117 < 33.07 < 33.19 < 32.61 < 33.07 < 34.00 < 33.70 < 33.70 < 33.64 06106/17 < 14.77 < 35.71 < 35.65 < 35.77 < 35.84 < 13.37 < 13.37 < 13.40 06/1 3117 < 27.34 < 26.92 < 28.03 < 27.30 < 24.79 < 24.66 < 24.62 < 25.01 06/20/17 < 13.82 < 32.96 < 33.01 < 32.90 < 32.90 < 29.41 < 29.41 < 29.46 06/28/17 < 31.57 < 31.32 < 12.62 < 30.65 < 30.80 < 36.1 4 < 36.25 < 35.86 38

TABLE 3-4 AIRBORNE IODINE (10-3 pCi/m3}

LOCATIONS PERIOD ENDING

- - -- 01

02

03

* *--- - -- ,- --05-- --

06 , 07

21 07/05117 < 18.16 < 44.66 < 44.89 < 44.89 < 44.89 < 30.81 < 30.76 < 30.60 07/11/17 < 38.18 < 37.49 < 39.23 < 38.10 < 28.86 < 28.68 < 28.63 < 29.16 07/18/17 < 16.62 < 32.18 < 32.13 < 32.07 < 32.07 < 29.37 < 29.37 < 29.32 07/25/17 < 21.91 < 9.24 < 21.91 < 21.91 < 21 .91 < 21 .10 < 21 .10 < 21.10 08/02/17 < 29.58 < 29.62 < 29.62 < 29.62 < 24.39 < 24.39 < 24.39 < 31.87 08/08/17 < 9.763 < 27.74 < 27.79 < 27.85 < 27.79 < 30.71 < 30.71 < 30.77 08/15/17 < 12.90 < 23.33 < 23.41 < 23.29 < 23.29 < 23.42 < 23.42 < 23.46 08/22/17 < 28.44 < 28.44 < 28.29 < 28.44 < 25.83 < 25.83 < 25.83 < 25.70 08/'30/17 < 18.71 < 33.96 < 34.01 < 33.96 < 33.96 < 40.99 < 40.99 < 41.05 09/05117 < 24.78 < 29.57 < 29.57 < 29.57 < 29.57 < 44.55 < 44.55 < 44.55 09/12/17 < 14.38 < 34.10 < 34.10 < 34.16 < 34.16 < 24.73 < 24.73 < 24.73 09/19/17 < 11.36 < 27.09 < 27.09 < 27.04 < 27.04 < 25.90 < 25.90 < 25.90 09flJ/17 < 12.60 < 30.22 < 30.26 < 30.36 < 30.31 < 23.39 < 23.39 < 23.46 10/04/17 < 13.28 < 31.45 < 31.28 < 31.23 < 31.34 < 2.8.31 < 28.36 < 28.21 10/10/17 < 10.45 < 24.79 < 25.14 < 25.20 < 24.89 < 25.86 < 25.80 < 26.17 10/17/17 < 19.26 < 47.15 < 44.60 < 45.60 < 46.41 < 36.45 < 36.58 < 35.75 10/24/17 < 9.99 < 23.23 < 24.33 < 23.68 < 23.52 < 20.50 < 20.43 < 20.68 1001/17 < 11.44 < 29.15 < 29.26 < 27.27 < 27.27 < 21.84 < 21.84 < 21.84 11/08/17 < 31.16 < 31 .60 < 30.56 < 31.21 < 29.02 < 29.11 < 29.02 < 28.80 11/15117 < 13.89 < 32.65 < 33.82 < 33.11 < 32.99 < 22.49 < 22.02 < 22.33 11/21/17 < 50.82 < 50.82 < 50.92 < 50.82 < 38.40 < 38.40 < 38.40 < 38.48 11/28/17 < 30.33 < 32.85 < 15.83 < 30.38 < 30.54 < 39.40 < 39.54 < 38.86 12/05/17 < 16.22 < 18.81 < 18.78 < 18.78 < 18.78 < 28.22 < 28.22 < 28.27 12/13/17 < 39.40 < 39.76 < 41 .19 < 40.37 < 22.37 < 22.03 < 21 .96 < 2216 12/19/17 < 11.86 < 28.29 < 28.46 < 28.29 < 28.58 < 36.59 < 36.59 < 36.82 12/26/17 < 16.25 < 28.93 < 27.80 < 28.33 < 28.57 < 37.01 < 37.14 < 36.49 39

TABLE 3-4 AIRBORNE IODINE (10-3 pCi/m3 )

LOCATIONS PERIOD END ING 22 23 24* 01A 05A

--- -------* --* - ---- -~ --------~ *~--- ----- *--------

01104/17 < 25_56 < 25.13 < 25-75 < 10.50 < 25.44 OU1 1/17 < 22-21 < 3238 < 32.50 < 32.38 '< 32.50 01/17/17 < 30.49 < 28.05 < 27.93 < 28.05 < 27.99 01/24/17 < 26.95 < 28.12 < 28.17 < 28.12 < 28.12 01/31/17 < 26.33 < 21 .10 < 21 .07 < 21.10 < 21 .10 02107/17 < 32.36 < 25.33 < 25.33 < 25.33 < 25.33 02114/17 < 47.85 < 29.42 < 28.61 < 29.58 < 28.96 02122/17 < 26.78 < 25.16 < 25.90 < 25.1 2 < 25.58 02128/17 < 29.44 < 28.38 < 27.41 < 28.56 < 27.97 03/07/17 < 19.01 < 26.95 < 27.62 < 26.68 < 27.23 03/15/17 < 31.46 < 31 .5 1 < 30.46 < 30.51 < 30.51 03/21/17 < 37.21 < 29.46 < 29.58 < 29.46 < 29.46 03/29/17 < 32.83 < 37.32 < 37.49 < 3721 < 37.49 04/04/17 < 35.32 < 2225 < 21 .97 < 22.34 < 22_02 04/11/17 < 19.49 < 22.04 < 21 .36 < 22.1 6 < 21 .96 04/19/17 < 26.41 < 32.91 < 33.83 < 32.77 < 33.32 04/25/17 < 24.59 < 28.1 4 < 2826 < 15.50 < 28.31 05!03/17 < 25.14 < 26.36 < 25.64 < 26.53 < 26.00 05/09/17 < 24.66 < 26.04 < 27.69 < 10.92 < 25.99 05/16/17 < 24 .61 < 38.37 < 38.37 < 38.30 < 38.43 05/23/17 < 38.65 < 45.37 < 45.45 < 45.30 < 45.22 05/30/17 < 40.00 < 15.51 < 40.07 < 40.00 < 40.00 06/06/1 7 < 13.40 < 30.64 < 30.64 < 30.64 < 30.58 06/1 3/17 < 28.51 < 27.88 < 28.71 < 9.764 < 28.31 06/20/17 < 29.46 < 31.64 < 31 .69 < 31.64 < 31 _58 06/28/17 < 35_86 < 28.80 < 27.85 < 28.98 < 28.32 "Control Station 40

TABLE 3-4 AIRBORNE IODINE (10-3 pCi/m3)

LOCATIONS PBRIOD ENDING 22 ___,. 23

- *- ------t 24*

* 01A

-------- 05A 1-------

07/05/17 < 30.60 < 38.06 < 38.33 < 38.00 < 38.33 07/11/17 < 27.16 < 26.45 < 27.33 < 10.19 < 26.94 07/18/17 < 29.32 < 27-72 < 27.67 < 21.n < 27.62 07/25/17 < 21.10 < 22.87 < 22.87 < 22.87 < 22.87 08102/17 < 31.08 < 31.08 < 31.08 < 13.09 < 31.08 08/08/17 < 30.77 < 35.44 < 35.59 < 35.44 < 35.59 08/15/17 < 23.46 < 29.12 < 29.17 < 29.17 < 29.02 08/22/17 < 24.78 < 24.91 < 10.39 < 24.91 < 24.91 08/30/17 < 41.05 < 35.48 < 35.53 < 35.48 < 35.48 09/05/17 < 44.55 < 44.19 < 44.19 < 44.19 < 44.19 09/12/17 < 24.73 < 28.18 < 28.18 < 28.18 < 28.23 09/19/17 < 25.90 < 27.24 < 27.24 < 27.24 < 27.19 00/27/17 < 23.50 < 33.66 < 33.76 < 33.51 < 33.86 10/04/17 < 28.16 < 28.15 < 28.00 < 28.30 < 28.00 10/10/17 < 26.17 < 15.94 < 31.31 < 30.86 < 30.99 10/17/17 < 35.81 < 43.31 < 17.39 < 43.62 < 42.24 10/24/17 < 20.68 < 31.41 < 3270 < 13.08 < 32.02 10/31/17 < 21.84 < 23.54 < 9.93 < 23.54 < 23.54 11/08/17 < 33.63 < 34.36 < 11.82 < 34.46 < 33.89 11/15/17 < 22.37 < 33.08 < 33.60 < 32.91 < 33.54 11/21/17 < 51.64 < 51.54 < 51.64 < 21.73 < 51.54 11/28/17 < 38.86 < 35.72 < 33.85 < 35.91 < 35.10 12/05/17 < 2827 < 21.49 < 21.45 < 21.49 < 21.45 12/13/17 < 30.84 < 3028 < 31.08 < 12.71 < 46.55 12/19/17 < 36.82 < 20.15 < 20.28 < 20.15 < 20.15 12/26/17 < 35.99 < 41.07 < 39.85 < 41.07 < 39.85

COntrol station 41

Virginia Electric and Power Company Annual Radiological Environmental Operating Report 20 17 North Anna Power Station TABLE3-5 A IR PARTICULATES 3 3

( 1CT pCifm )

GAMMA SPECTRA- OT A 1 (12/27/ 16 - 03/29/ 17)

LOCATION Be-7 Cs-134 Cs-137

----- - (+/-)

01 158.40 21.370 < 1.2360 < 0.8425 02 186.50 29.500 < 1.2970 < 1. 1070 03 155.00 22.730 < l .3130 < 1.39 10 04 191.60 32.nO < 1.6180 < 1.8940 05 118.80 24.220 < 0 .9345 < 0.9647 06 141.50 23.420 < 1.1070 < 1.1840 07 162.50 29.820 < 1.9420 < 1.8680 21 137.30 24.250 < 1.1670 < 1.0670 22 137.70 29.260 < 1.7540 < 1.5900 23 171 .40 25.780 < 1.8210 < 1.3020 24* 148.70 20.1 30 < 0 .8365 < 0.9037 01A 120.90 19 .670 < 1.1 490 < 1.4380 05A 182.50 31.710 < 2.1500 < 1.6650 GAMMA SPECT RA AND STRONTIUM 89190- QTR 2 (03/29/1 7 - 06/28/17)

LOCAT IO N Be-7 Cs- 134 Cs-137 Sr-89 Sr-90

(+/- )

01 151.40 20.400 < 1.0630 < 1.0270 < 5.1600 < 2.1 400 02 201.70 28. 140 < 1.4790 < 1.0590 < 5.1000 < 1.9000 03 138.80 24.030 < 1.4090 < 1.0490 < 4.3400 < 1.6700 04 113.50 33.050 < .2.11 40 < 1.9580 < 5.4500 < 2.4100 05 133.20 22.520 < 1.0200 < 0.9860 < 4.4000 < 2.0900 06 122.70 23.000 < 1.3120 < 1.3260 < 6.0900 < 1.5400 07 154.40 31. 120 < 1.8390 < 1.5560 < 4.4900 < 2.1 900 21 99.390 20. 110 < 1.1820 < 1.1880 < 4.6600 < 1.8300 22 135.00 26.300 < 1.6140 < 1.3490 < 4.5000 < 1.7300 23 148.80 23.880 < 1.8020 < 1.3760 < 5.0300 < 1.8100 24* 143.10 21.400 < 1.0860 < 1.0420 < 5.8600 < 2.6700 01A 109.30 22.060 < l .4300 < 1.0490 < 6.1400 < 3.0600 05A 143.00 31.620 < 1.5790 < 1.5330 < 7.5600 < 3.2100

Control Location 42

Virginia Electric and Power Company Annual Radiological Environmental Operating Report 20 17 North Anna Power Station TABLE3-5 A IR PARTICULATES (1 0'l pCi/m3)

GAMMA SPECTRA- QTR 3 (06/28/17 - 09127/ 17)

LOCATION Be-7 Cs- 134 Cs-137

(+/-)

01 135.70 27.160 < 1.3 150 < 1.0970 02 147.40 25.520 < 1.3no < 1.1060 03 134.70 34.850 < 1.9230 < 1.1600 04 127.00 26.470 < 0.7902 < 1.0570 05 119.40 29.220 < 1.4200 < 1.1950 06 110.30 19.920 < 1.0760 < 0.9354 07 120.90 22980 < 1.2300 < 0.9514 21 116.30 25.460 < 1.3490 < 1.1300 22 92.090 23.310 < 1.3280 < 1.2200 23 128.60 30.960 < .2.2580 < 1.7500 24* 133.60 33.900 < 2.11 20 < 1.7400 01A 111.20 23.160 < 0.7727 < 1.1640 05A 130.40 26.290 < 1.1680 < 1.0910 GAMMA SPECTRA- QTR 4 (09/27117 - 12/26/17 )

Annual Mean LOCAT ION Be-7 Cs- 134 Cs-137 Be-7

,------ -- -- ------(+/-)

--------* --------- ---------- (+/-) -

01 143.30 24.830 < 0.893 1 < 1.3150 147.20 23.440 02 165.50 34.230 < 2.4370 < 1.9270 175.28 29.348 03 130.10 23.410 < 1.4820 < 0.68 18 139.65 26.255 04 91.210 27.300 < 1.4500 < 0.8767 140.78 29.898 05 94.800 28.410 < 1.9380 < 2.2480 116.55 26.093 06 87.300 28.200 < 1.3060 < 1.3880 115.45 23.635 07 100.00 18.400 < 1.6380 < 1.3540 134.45 25.580 21 106.30 18 .800 < 1.0 150 < 0.9359 114.82 22.155 22 116.40 28 .980 < 0.9847 < 1.2890 120.30 26.963 23 106.00 32.300 < 2. 1810 < 1.3990 132.05 28.230

.24* 111 .20 32.870 < 1.7 170 < 1.6070 134.15 27.075 01A 111.10 20.970 < 1.0940 < 1.1690 113.13 21 .465 05A 111.40 26.040 < 1.4720 < 1.4470 141.83 28.915 Mean of All indicator Locations 133.50 26.007

Contro Locatio 43

TAB!£ 3-6 Soil (pCi/kg dry wt)

COLLECTION LOCATION DATE Sr-89 K-40 Cs134 Cs-137 Ra-226

---~-----

(+/-)

--- Sr-90

-- (+/-)

- -- (+/-) (+/-) (+/-) (+/-)

01 02 03 04 05 06 07 Soil sampled on Triennial basis. Not required in 2017 21 22 23 24*

01A 05A COLLECTION LOCATION DATE Th-228 Th-232

(+/-)

----~--- (+/-)

01 02 03 04 05 06 07 21 22 23 24" 01A 05A 44

TABLE 3-7 Precipitation (pCin_}

ll.OCATION 01 A OOLLECTION DATE Gr-8 H-3 RainFall (inches)

- - - - -(+l-f-01/31117 1.8 1.1 < 1010 3,.30 02/28117 18.2 4.9 < 890 0.33 03129117 2.3 1.1 < 948 2.52 04125117 3.9 1.3 < 811 3 .72 05130117 1.7 1.0 < 735 4 .13 06/28117 15.1 2.0 < 832 1.20 07125117 4.8 1.4 < 808 280 08130117 4.1 1.3 < 702 7 .31 09/27117 3.3 1.3 < 776 2~06 10131117 2.1 1.0 < 1080 3.09 11128117 2.1 1.2 < 1010 1_77 12126117 3.7 1.2 < 1140 0 .6'1 Mean 5.3 1.5 l';otal 33.44 45

TABLE 3-7 Precipitation (pCi/L)

LOCATION 01A COUECTION DATE Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 06/28/17 < 21 .29 < 0.716 < 5.340 < 1.468 < 0.568 < 1.443 < 2.800 12126117 < 25.50 < 0.855 < 6.467 < 1.891 < 0.767 < 1.790 < 3.3B5 Mean COUECTION DATE Nb-'95 Os-134 Cs-137 Ba-140 La-140 1-131 Th-228 06/28/17 < 1.839 < 0.619 < 0.5 12 < 740.2 < 263.0 < 7469 < 1.671 12126/17 < 2.099 < 0.821 < 0.824 < 1136 < 334.3 < H810 < 1.364 Mean 46

TABLE 3-8 MILK (pCi/1..)

COLLECTION LOCATION DATE K-40

(+/-) '

Sr-89

--- Sr-90 1-131"" , Cs-134" ,

- -Cs-137"

-- - - - - Ba-140" La-140*

12A 01/17/17 1020 192 (a) (a) < 0.807 < 8.726 < 1023 < 4 1.66 < 10.43 02/22/17 1428 172 (a) (a) < 0.635 < 9.402 < 9.595 < 37.65 < 8.528 03/21/17 1425 170 < 4.0 < 1.8 < 0.891 < 9.811 < 10.12 < 51.16 < 12.53 04/19117 1026 198 (a) (a) < 0.672 < 9.747 < 11 .06 < 32.65 < 9 ..352 05/16/17 1204 115 (a) (a) < 0214 < 7.459 < 7.432 < 32.05 < 6.872 06/20/17 1384 211 < 3.5 < 1.7 < 0.800 < 11.43 < 9.553 < 4223 < 10.09 07/18117 1368 162 (a) (a ) < 0.517 < 7.458 < 6.629 < 21.23 < 6.715 08/15117 1369 199 (a) (a) < 0.607 < 9.431 < 8.650 < 32.92 < 12.54 09119/17 1395 174 < 3.3 < 1.2 < 0.585 < 8.418 < 9.048 < 4 1.10 < 9.242 10/17/17 1457 158 (a) (a) < 0.641 < 6.201 < 7.041 < 26.76 < 9.668 11/21/17 1244 171 (a) (a) < 0.706 < 11 .65 < 10.28 < 51.87 < 12.30 12119/17 1154 161 < 1.8 < 0.7 < 0.530 < 10.07 < 9.159 < 38.21 < 10.17 Mean 1290 174

LLD Identified ii ODCM (a) Sr-89190 analysis performed on the last monthly sample of each quarter 47

Virginia Electric and Power Company Annual Radiological Environmental Operating Report 2017 North Anna P*ower station TAB L.E 3-9 Food and Veg81alion (pCilkg wet wt.)

LO CATION 149 OOLLECTIO N DATE 88-7 K-40 1- 13 1" Cs-134.. Cs-137'" Ra-226 Ac;.228 Th-228

-* --- (+I- )

-* (-.;r:f~ ------- ---- ---- *- ---t~-:r- (+I-) (+/-)

04/11/17 7 17. 1 183.7 5763 492.3 < 9.700 < 24.33 < 25.22 < 548.2 < 72.92 < 44.21 0&00'17 1304 300.7 4449 566.B < 14.60 < 29.79 < 31.60 915.7 778.1 < 103.4 7 1.48 51.9g 06113 17 376.7 287.4 4050 652.3 < 22.50 < 42.52 < 40.2 1 < 836.6 < 167.3 < 58.00 07/ 11/17 892.7 231 . 1 6056 500.9 < 39.30 < 29.07 < 27.'ll < 5B4.2 < 108.3 < 49.1 8 08i'OBl17 1347 351.1 3605 585.9 < 32.40 < 48.11 < 36.19 < 858.7 < 1275 < 6 1.96 09112' 17 933.8 295. 1 4180 533.1 < 28.90 < 3 1.13 < 30.27 < 645. 1 114.3 92.95 < 49.02 10110 '17 2784 33&.9 9236 700.2 < 9.640 < 39.39 < 34.27 < 688.7 < 112.9 < 63.43 Moan 1194 284.0 5334 578.2 915.7 778. 1 11 4.3 92.95 7 1.48 5 1.99 LOCATilON 15 OOLLECTION DATE 88-7 K-40 1-13 1" Cs-134 Cs-137.. Ac-228 T~228

(+t- )

-* (~::y- - -* ---- - ---- *---------

04/11/17 2832 209.1 7557 426.9 < 14.80 < 21.21 < 20.27 70.17 60.92 < 3 1.92 05101)'17 1296 '267.7 6 150 573.6 < 18.40 < 32.4 B < 30.10 < 100.6 < 53.84 06113,'17 574.3 336.1 5027 S80.9 < 28.20 < 36.67 < 34.02 333.9 169. 1 6 1.1 3 54.92 0711 1.117 1527 256.3 6424 609. 1 < 3 1.50 < 35.03 < 30.23 < 124.0 < 43.19 08108,'17 854.8 336.5 560 1 800.4 < 25. 10 < 47.37 < 37.75 526.8 200.2 < 6 1.97 09112'17 1571 335.8 4485 594,0 < 45.30 < 30.89 < 30.44 < 12 1.5 < 51.22 1Cll10' 17 2536 441 .9 10420 792.9 < 11.80 < 42.92 < 3B.73 < 169.8 < 75.8B Moan 1599 311 .9 6523 625.8 310.3 144.4 6 1.13 54.92 LOCATION 16" OOLLECTION 88-7 Cs-137 ..

DATE

- -- -*- - -, --- (+I- )

K-40

(~~f- - 13 1"

---- - Cs- 134

-*--- Ac-22B

,- ------- - T~ 228 04111/17 2723 213.6 6109 423.0 < 13.80 < 19.38 < 16 .1 2 < 6B..4 1 73.07 .26.24 0&00' 17 1225 22B..7 5B13 588.5 < 19.30 < 24.67 < 24.47 < 85.75 < 45.94 06/13" 17 668. 0 '266.9 4869 738.4 < 3 1.50 < 43.26 < 40.'ll < 159.3 < 59.84 07/ 11/17 647.3 343. 1 4717 997.0 < 37.70 < 55.72 < 58.45 < 233.0 < 75.62 08,'0S,'17 113 1 345.3 4536 670.8 < 'll.00 < 3B.96 < 31 .62 < 142.2 120.3 64,24 09112'17 2 199 297.2 5299 563.8 < 25.00 < 33.06 < 31.13 < 134. 1 < 57.t7 10/ 10'17 2890 300.1 8041 752.6 < 16.50 < 45.67 < 37.'Jl 15B. 1 132.3 71.96 65.25 Mean 1640 297.8 5626 676.3 15B. 1 132.3 88.44 51.91

control S tation 48

Virginia Electric and PaNer Company Annual Radio1og*ca1 Environmental Operating Report 2017 North Anna PaNer station TABLE 3-9 Food and Vggelatlon (pCi/J(g Wilt wt. )

LOCATION23 COLLECTION

OAT:E 04/ 11/ 17 BG-7

(+/.)

2122 346.6 8267 K-40 i.,_,--*

73 1.4 1-131"

< 7.080 Cs-134"

<34. 12 Cs-137"'

< 30.71 Ra-226 833.8 629.0 Th-228 95.09 51.27 05/00'17 1!130 345.S 7066 720.1 < 18.40 <39. 12 < 37.24 < 670.3 < 55.35 06113117 528.2 279.9 6673 678.2 < 25.90 < 38.44 < 36.10 < 786.8 < 70.36 0'7/ 11117 < 470.7 3506 6402 < 35.40 < 53.95 < 52.49 < 1134 < 88.79 08/0Q,'17 1917 410.5 3016 648.5 < 44.1 0 <46.21 < 46.75 < 852.6 < 83.38 OQ.112117 23Z3 362.4 5676 607.8 < 30.40 < 34.95 < 32.79 < 700.7 < 55.85 1Ql 10'17 1717 278.0 99~ 558.1 < 42.20 < 36.69 < 37.40 < 920.6 < 68.46 Maa.n 1756 3372 6314 654.9 833.8 629.0 96.08 51.27 LOCATION26 COLLECTION

- -OAT:E

--- - BG-7 K-40

- 131"'

_ _g~~ Cs- 137"' Ra-226 _______

Ac-228 ____. Th-228

- ------* Th-232

(+/- ) (...q 04/1 1/ 17 1726 206.5 4338 454. < 12.60 < 24.00 < 23.22 < 463.9 < n.14 5423 30.96 89.62 69.49 05l 09f17 1412 401.l 4958 715.0 < 15.00 < 35.42 < 4 1.83 < 1064 < 174.0 < 67.55 < 173.6 00/13117 008.5 286-3 4592 633.9 < 22.30 < 40.00 < 35.53 < 678..0 261.8 171.8 59.88 39.78 < 223.4 0'7111/17 1767 254..3 4414 460.6 < 31.20 < 31.41 < 26.44 862.1 553.6 452.5 112.9 40.00 36.61 < 163.1 00/08/17 3200 512.9 3670 699.8 < 'll.70 < 51.66 < 48.12 < 1068 < 186.0 < 92.83 < 185.8 09.1 12/17 2272 368.4 6439 681.0 < 15.10 < 29.92 < 28.97 < 532.0 < 144.8 < 59.6Q < 144.4 10110'17 1021 389.6 0850 966.1 < !l.240 <44. 11 < 45.43 < 813. 1 < 173.3 < 64.56 < 172.9 Maan 1758 345.6 5609 658.6 862.1 553.6 357.2 142.4 51..37 35.78 89.62 69.4!1 Al ln<ficalor Mean 1570 319.0 5945 629.4 870.5 653,6 293.2 135.1 63.63 44.26 89.62 69.4!1

" LlD identi ad in ODCM 49

TABLE 3-10 WELL WATER (pCi/1..)

COLLECT1JON LOCATION DATE H-3 Sr-89 Sr-90 Mn-54

- - - - - -, ----- ------- ------- *----- - -* *------* - - Fe-59 Co-58 Co-60

~ - - Zn.SS 01A 03/29/17 < 977 (a) (a) < 0.74 < 2.44 < 1.01 < 0.61 < 1.55 06/28/17 < 824 < 3.32 < 0.626 < 3.39 < 10.7 < 5.24 < 5.43 < 9.58 09/27/17 < 736 ,(a) (a) < 4 .05 < 10.6 < 4.1 1 < 6.01 < 9.19 12126/17 < 1130 ,(a) (a) < 4.76 < 10.7 < 5.08 < 5.40 < 11.0 Mean COLLECTION LOCATION DATE Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 01A 03129/17 < 1.67 < 1.09 < 4.08 < 0.79 < 0.70 < 38.4 < 13.4 06/28/17 < 9.06 < 5.74 < 9.81 < 5.24 < 5.05 < 24.3 < 8.80 09/27/17 < 8.40 < 5.39 < 9.87 < 5.50 < 5.08 < 29.8 < 7.83 12126/17 < 8.87 < 6. 73 < 9.84 < 5.64 < 4.98 < 28.5 < 10.1 Mean (a) Sr-89/9D analyses performed ,on ffle second qu:uter sample.

50

TABLE 3-11 River Water (pCi/L)

LOCATI ON 11 COW ECTIO H-3 S r-90 Fe-59* Co-60*

DATE

(+/-)

""'1-54*

Sr-89---~ *- -- - -- - --*-- -- *-- ---* *- -- ---- --- Co-58*

* *-- -- ---- Zn-65*

01117/17 (a) (b) (b) < 7. .242 < 14.68 < 7.006 < 6.270 < 13.35 02/14/17 (a ) (b) (b) < 4.586 < 9.015 < 3.389 < 4.421 < 10.38 03/15/17 3580 779.0 (b) (b) < 4.589 < 10.57 < 5.067 < 5.046 < 1327 04/1 0/17 (3) (b) (b) < 4.547 < 9.242 < 5.045 < 4.750 < 9.738 05/15/17 (a) (b) (b) < 4.967 < 10.57 < 5.230 < 5.603 < 9.445 06/12/17 4370 791.0 < 4.470 < 0.545 < 6.294 < 10.85 < 5.722 < 4.474 < 12.02 07/1 1/17 (3) (b) (b) < 6.396 < 10.36 < 6.764 < 9.074 < 11.10 08/08/1 7 (3) (b) (b) < 6.798 < 12. .74 < 5.770 < 6.597 < 12.19 09/1 1/17 4910 780.0 (b) (b) < 2.621 < 6.1 22 < 2.928 < 2.627 < 5.295 ff0/17/1 7 (3) (b) (b) < 5.207 < 8.693 < 5.263 < 5.764 < 10.41 H/1 311 7 (a) (b) (b) < 4 .063 < 12.00 < 4.845 < 6.872 < 14.70 12/13/1 7 5420 966.0 (b) (b) < 1.465 < 3.103 < 1.486 < 1.488 < 2.995 Mean 4570 829.0 Nb-95* Zr-95* 1-131* Cs-134* Cs-137" Ba -140* La-140*

--------~ *- - --- -- - -----------, ,- - - - -- - ---------* *- --- - ---

01/17/17 < 6.926 < 12.41 < 0.563 < 7.003 < 6.692 < 26.19 < 9.227 02/14/17 < 5.418 < 7.363 < 0.529 < 4.589 < 4.907 < 24.63 < 5.608 03/1 5/17 < 5270 < 8.966 < 0.733 < 5.483 < 4.746 < 23.70 < 6.806 04/10/17 < 5.102 < 8.876 < 0.5 12 < 5.348 < 5.394 < 25.80 < 6.578 05/15/17 < 4.696 < 10.45 < 0.5 12 < 5.937 < 4.665 < 23.04 < 7.957 06/1 2/17 < 6.522 < 1122 < 0.637 < 7.876 < 4.515 < 24.18 < 8.325 07/11/17 < 6.748 < 13.88 < 0.509 < 7.122 < 6.729 < 31.30 < 10.71 08/08/1 7 < 5.519 < 9.442 < 0.977 < 7226 < 6.098 < 30.42 < 7.452 09/11/17 < 3.089 < 5.094 < 0.226 < 2.985 < 2.796 < 18.84 < 7.005 0/17/17 < 4.875 < 9.701 < 0.475 < 4 .214 < 5.531 < 28.71 < 7.341 11/13/17 < 7 .685 < 12.11 < 0.623 < 8.008 < 7.603 < 21.21 < 11.62 12/13/17 < 1.616 < 2.559 < 0.490 < 1.596 < 1.466 < 10.20 < 3.134 Mean

LLD identified in ODCM (a) Tritium analyses on quarterly composite (b} S r-89/90 perfonned on 2nd quarter compos ite s a mple.

51

TABLE 3-12 Surface Water (pCi/L)

LOCATI ON 08 COLLECTIO DATE H-3 Sr-89 sr~oo Mn-54* Fe-59* Co-58" Co-60" Zn-65°

------ --------- (+(-)

~ *--- - - - -- -----------* *- -- - - - - ---------* *-------- - --- - - - -

01/17/17 (3) (b) (b) < 6.532 < 12.72 < 6.567 < 6.232 < 14.02 02/14/17 (a) (b) (b) < 3.581 < 7.883 < 4.162 < 4.092 < 8.606 03/15/1 7 4390 815.0 (b) (b) < 4.527 < 11.75 < 6.365 < 5.177 < 10.70 04/10/1 7 (3) (b) (b) < 4.618 < 9.977 < 4.716 < 4.244 < 10.1 0 05/15/1 7 (a) (b) (b) < 3.956 < 10.11 < 5.064 < 5.796 < 10.64 06/1 2/17 3760 758.0 < 3.940 < 0.407 < 6.432 < 11.64 < 6.158 < 4.845 < 13.69 0711 1/17 (a) (b) (b) < 7.233 < 14.32 < 7.674 < 8.276 < 16.44 08/08/1 7 (3) (b) (b) < 3.952 < 9.488 < 4.571 < 5.010 < 10.06 09/11/17 5690 827.0 (b) (b) < 2.655 < 6.236 < 2.745 < 2.570 < 5.556 10/17/17 (a) (b) (b) < 4.459 < 9296 < 5.055 < 4.575 < 8.176 11/13/17 (a) (b) (b) < 5.959 < 13.59 < 6.087 < 3.797 < 14 .48 12/13/1 7 7130 1030 (b) (b) < 1.136 < 2.708 < 1.270 < 1.187 < 2.289 Mean 5243 857.5 1-131° Cs-134*

Nb-95*°

Zr-95°

~ *-------- -----------* *- -Cs-13P Ba-140"

- - - - - ---------, *-- -La-140" 01/17/17 < 6.471 < 12.94 < 0.491 < 6.341 < 6.062 < 20.75 < 13.93 02/14/17 < 3.955 < 7.046 < 0.597 < 4.077 < 4.366 < 20.92 < 7.084 03/15/1 7 < 6.159 < 11.01 < 0.483 < 6.525 < 5.465 < 23.78 < 9.221 04/10/17 < 5.008 < 8.116 < 0.401 < 5.304 < 5.474 < 19.97 < 6.700 05/15117 < 4 .671 < 6.997 < 0.790 < 4.766 < 5 ..551 < 22.59 < 7.774 06/12/17 < 7 212 < 9.879 < 0.606 < 6.849 < 6.428 < 28.53 < 9.680 07/11/17 < 7.038 < 13.18 < 0.389 < 9.197 < 7.755 < 29.62 < 12.48 08/08/1 7 < 5.575 < 7.705 < 0.653 < 4 .655 < 4.960 < 23.19 < 8.551 09/11/17 < 3.140 < 4.970 < 0.220 < 2.781 < 2.967 < 20.79 < 5.552 10/17/17 < 5.344 < 9.328 < 0.407 < 6.136 < 5.401 < 25.51 < 9.201 11/13/17 < 6.703 < 9.516 < 0.648 < 8.162 < 7.641 < 28.22 < 9.751 12/13/1 7 < 1278 < 2.260 < 0.532 < 1.288 < 1202 < 8.825 < 2.659 Mean

.. LLD identified in OOCM

{a} Tritium analyses on quarterly -composite (b) Sr-89/90 pertonned on 2nd quarter composite sample.

52

TABLE 3-12 Surface Water (pCi/L)

LOCATION 09N" COLLECTI O DATE H-3 Sr-89 sr~oo Mn-54* Fe-59" Co-58* Co-60* Zn-65*

------ ------- -- --------~ *- ------ - ------ -- ---* *- - - - --- --- - - - ---* *-------- -------~

01/17/1 7 (a ) (b) (b) < 6.284 < 16.37 < 7.943 < 6.337 < 12.55 02/14/17 (a ) (b) (b) < 3.255 < 6.445 < 3.497 < 3.628 < 7.486 03115/17 < 935 (b) (b) < 5.451 < 13.07 < 5.842 < 5.892 < 10.77 04/10/1 7 (a) (b) (b) < 5.140 < 8.948 < 4.724 < 5.477 < 7.728 05/1 5117 (a) (b) (b) < 4.430 < 10.50 < 4.623 < 5.046 < 11.45 06112/17 < 860 < 4.53 < 0.618 < 6.471 < 13.86 < 6.721 < 7.936 < 12.84 07/11/1 7 (a) (b) (b) < 6.201 < 15.30 < 7.836 < 8.190 < 17.56 08/08/1 7 (a) (b) (b) < 4.628 < 8.544 < 4.274 < 4.624 < 8.973 0911 1/1 7 < 814 (b) (b) < 2.339 < 6299 < 2.812 < 2.548 < 4.904 10117/1 7 (3) (b) (b) < 4.662 < 10.89 < 4.616 < 5.420 < 10.1 9 11113/17 (3) (b) (b) < 4.811 < 10.57 < 5.389 < 5.530 < 12.36 12/13/17 < 1170 (b) (b) < 1.368 < 3.310 < 1.451 < 1.426 < 2.909 Mean Zf..95* 1-131*

Nl>-95*

--------~ ,- - - - --- - ----Cs-134"

- --- ---, ,- -Cs-137"

Ba-140"

- ---* ,-- -l a-140" 01117/17 < 7.469 < 1027 < 0.523 < 7.130 < 6.640 < 30.15 < 7.913 02/1 4/17 < 4.219 < 6.890 < 0.515 < 4 .144 < 4.152 < 19.36 < 5.413 03115117 < 6.773 < 10.81 < 0.888 < 6.716 < 5.581 < 30.01 < 9.375 04110/17 < 4.944 < 8.H6 < 0.373 < 5.223 < 5.042 < 20.39 < 6.427 05115/17 < 4.924 < 8.505 < 0.513 < 5.628 < 5.188 < 25.61 < 8.385 0611 2/17 < 6.716 < 10.65 < 0.769 < 7.863 < 8.628 < 28.90 < 7.837 07111/17 < 8.183 < 13.13 < 0.443 < 9.076 < 7.6 13 < 31 .39 < 10.68 08/08/17 < 5.156 < 8.342 < 0.939 < 5.452 < 3.879 < 23.10 < 7.702 09/1 1/17 < 2.866 < 4.793 < 0.220 < 3.135 < 2.599 < 19.43 < 5.482 10117/17 < 4.945 < 7.913 < 0.406 < 4.819 < 5.178 < 21 .81 < 9.673 11113/17 < 5.383 < 9.463 < 0.522 < 5.250 < 5.377 < 21.98 < 6.522 12/13/17 < 1.461 < 2.650 < 0.517 < 1.528 < 1.533 < 10.16 < 3.222 Mean

" LLD identified in ODCM

""Control location (a) Tritium analyses on quarte rly composite (b) S r-89/90 performed on 2nd quarter composite sample.

53

TABLE 3-13 Sediment Silt (pCi/kg dry Wt)

COLLECTION LOCATION DATE Sr-89 Sr-90

------ ------ --------- *------- *--- -K-40

-*(+/-}

- ---* Cs-134 Cs-137

Ra-226

(+/-}

08 04/20/ 17 (a) (a} 980.0 459.3 < 47.12 < 46 .64 < 962.1 09A* 04/20/ 17 (a) (a) 31610 1671 < 65.89 < 53 .07 1263 1163 11 04/20/ 17 (a) (a) 21020 1559 < 72.48 < 54.94 < 984.4 08 10/25/17 < 297.0 < 44.10 1783 811.5 < 80.60 < 7526 < 1763 09A* 10/ 17/17 < 319.0 < 34.10 21030 1697 < 83.50 < 72.18 3154 1128 11 10/25/1 7 < 266.0 < 43.90 23510 1809 < 75.75 < 72.41 < 1179 Indicator Mean 11823 11 60 Control Mean 26320 1684 2209 1146 COL LECTION LOCATION DATE

*----- - -Th-228

Th-232

,- - - - (+/-)-

(+/-)

08 04/20/ 17 88 .03 73.00 < 198 09A* 04/20/ 17 717.8 79.09 544 .3 149.9 11 04/20/17 583.7 73.50 555.5 163.5 08 10/25/ 17 21 1.8 131.4 < 363.9 09N 10/ 17/ 17 992.7 111.4 785.4 184.9 11 10/25/ 17 868.3 100.7 889.0 176.3 Indicator Mean 438.0 '94.65 722.3 169.9 Control Mean 855.3 '9 5.25 664 :9 167.4 (a) Sr-89/90 analyses preformed annually.

Conlrol location, Background location 54

Virginia Electric and Po.var Company Annual Radiological Environmental Operating Report 20 17 North Anna Po.ver Station TABLE3-14 Shoreline Soil (pCilkg dry wt)

LOCATIONS COLLECTION LOCATION DATE Sr-89 Sr-90 K-40 Cs- 134 Cs-137 Ra-226

* -------* --------~ ~-------~-- (#-) --------- *--- -- - ----- --------~

08 04/20/17 {a) (a) 997.8 598.6 < 42.75 < 41.45 < 1027 08 10/25/17 < 283.0 < 31.40 1291 682.4 < 64.56 < 35.57 < 1021 Mean 1144 640.5 COLLECTION LOCATION

*-

DATE

--* - -- Th-228

-- -- -~ ~-- -Th-232

--- -~ -- Be-7

(#-)

08 04/20/17 <n.42 < 1872 < 480.9 08 10/25/17 < 90,56 < 313.0 397.0 376.4 Mean 397.0 376.4

LLD identified on ODCM (a} Sr-sg,rgo analyses pertormed annually.

55

TABLE 3-15 Fish (pCiAcg wet wt)

COLLECTION LOCATIO ,_!_F~h T!'.P!_ - -DATE K-40 Mn-54* Fe-59,. Co-58*

---* * - - - -(+/-) _, - - - -*- *- - - ----- ~------ *- - Co-60*

Zn-65"'

08 (a) 04/ 19117 2204 569.6 < 36.73 < 78.34 < 39.97 < 29.03 < 81 .07 (b) 04/19117 1587 635.1 < 45.26 < 121 .7 < 57.92 < 67.06 < 101 .5 (a) 10/25117 1677 663.5 < 48.88 < 103.1 < 60.90 < 51 .37 < 101 .4 (b) 10/25117 1331 543.1 < 35.97 < 135.0 < 45.31 < 50.78 < 111.2 25" (a) 04/19117 1293 1129 < 70.68 < 184.1 < 77.74 < 49.99 < 166.1 (b) 04/19117 1904 649.7 < 62.11 < 144A < 67.55 < 54.86 < 131.2 (a) 10/18117 2359 870.6 < 52.35 < 119.1 < 61 .36 < 46.93 < 121 .8 (b) 11/01 /17 3092 1004 < 62.97 < 180.8 < 52.83 < 5120 < 159.5 Mean 1931 758 Indicator Mean 1700 603 COntrol Mean 2162 913 COLLECTION LOCATIO DATE Cs-134* Cs-137*

08 (a) 04/19117 < 36.55 < 46.23 (b) 04/19117 < 60.74 < 55.83 (a) 10/25117 < 67.00 < 58.91 (b) 10/25117 < 5264 < 48.95 (a) 04/19117 < 79.08 < 61 .03 (b) 04/ 19117 < 67.16 < 57.44 (a) 10/18117 < 63.49 < 53.31 (b) 11/01 /17 < 67.90 < 60.50 Mean Indicator Mean COntrol Mean

LLD identified il ODCM u ,eontrol stalioo (a) Non-bottom dwelling species of gamefish.

(b) Bottom dwelrng species of fish.

56

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2017 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 2017 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 fo llowing is a discussion and summary of the results of the environmental measurements taken during the 2017 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 CaS04:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs.

This will continue to be monitored.

57

0.0 ..,.

~

C.RI 00 00 C.RI 0

O'l C

I N

O'l C

I O'l C.

§l C

I

~

C.RI ~C N

9 C

0 C

I 8

C I

~I C

0 C

I N

C I I C

I.D C

I 00 C

I 0

N C

I

-, -, ~ ~ ~ RI

-, -, ~ RI

-, ~ ~ ~ ~ ~ ~ RI

-, RI

-, RI Figure 4-1 TLD (mrem/Standard Month)

Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The average level of these 32 sector TLD locations (two badges at each location) was 4.1 rnR/standard month with a range of 0.8 to 9.0 rnR/standard month. The highest quarterly average reading for any single location was obtained at location W-25/57. This value was 6.9 rnR/standard month. This location is on site on the south gate of the switchyard. 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 rnR/standard month with a range of 1.2 to 6.1 rnR/standard month. The average annual reading for these locations was 3.0 rnR/standard month with a range from 1.3 to 4.5 rnR/standard month. The control location showed a quarterly average of 2.9 rnR/standard month with a range of 1.6 to 4.1 rnR/standard month. Its annual reading was 3.1 rnR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.1 rnR/standard month with EPSP-9/10 having the highest quarterly average of 7.2 rnR/standard month. Eight other TLDs, designated C-1 thru C-8, which were pre-operational controls, were collected quarterly from four locations. Stations C-3/4 and C-7/8 are designated controls. These had a quarterly average of 3.2 rnR/ standard month, while Station C-1/2 and C-5/6 had a quarterly average of 2.7 rnR/standard month with a range of 1.7 to 4.1 rnR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 rnR/standard month.

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

Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.

58

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/m3 to a high of 0.75 pCi/m3.

0.1 2 0.1 E 0.08

j u 0.06

(.) 0.04 C.

0.02 0 (X) 0) 0 N C') 'O' ID <D ,..._ (X) 0) 0 N C') 'O' ID <D ,..._

0)

~

C I

0) c

~

t~ 9C

~

9C

~

t t~

~

9C

~

t~ 0

~

c t

~

9C

~

t t t t

~ ~ ~ ~ ~

C I

t t

~ .!13

~

C I

- Control Sta . 24 - - Indicator Average Pre-Op - - Required LLD Fi ure 4-2 Historical Gross Beta in Air Particulates 2.SOE-02 2.00E-02 1.SOE-02 1.00E-02 5.00E-03

-+- Control - Indicator Figure 4-3 2017 Gross Beta in Air Particulates (pCilm 3) 59

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 2017 .

4. 7 Precipitation A sample of rain water was collected monthly at on-site station OlA and analyzed for gross beta activity and H-3. The results are presented in Table 3-7. Twelve precipitation samples were obtained in 2016. Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements. No plant related isotopes were reported in any precipitation water sample at the indicator location. Naturally occurring gamma emitting radioisotopes were not 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 2017 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 CowMilk Analysis of milk samples is generally the most sensitive indicator of fission product existence m 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 60

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 Ra-226 and Ac-228, were detected in some samples. No plant related isotopes were identified in any vegetation sample during 2017.

4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, I-131, and gamma emitters. The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period.

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

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 4570 pCi/liter and a range of 3580 to 5420 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.

61

River Water 5000 4500 4500 4000 4000 3500 3500 3000 ~ titium 2500 - -Required LLD 2000 1500 1500 1000 1<000 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 5243 pCi/liter with a range of 3760 to 7130 pCi/liter.

62

10000 M ~ ~V} J i 1l *a

- I ,

1000 I -

l t\t I

..J

,J 5100 - - Tritium Q.

Requ ired LLD

~ Average Pre-op 10 1 ,... ....co ,... .... ,...

I';-

C)

!2

...l.

1/)

co co C) 0 N C) ~

...l.

tD C) co C) 0

('")

0 1/)

0 I

0 C) 0 .... ....'<I".!. .... ....co N

I tD 0

~

C .!.

Cll

l...: :, ..!.

(.) 0 .6 ;l... ::, 6. ;:I. .6 .!.

0.

C

6. ;:I. C Cll C:

Cl

, u Cll

--, Cll --, Cl) Cl) Cll --, Cl) 0 Cl) Cl) 0 Cll

E ::E 0 Cl u. ::E (/) z u. c( --, (/) z ::E c( 0 Figure 4.5 Tritium in Surface Water 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.

Sediment samples were collected during April 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 2017. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented.

During the pre-operational period sediment samples were also analyzed by gamma spectroscopy. Figure 4-6 shows the historical trend of Cs-13 7 in sediments.

Neither Strontium-89 nor Strontium-90 was detected in any samples of aquatic sediment/silt in 201 7. 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.

63

1600 1400 1200 -+- Sta. 08

~

( .)

1000

a. 800

--- sta. 09 Control Sta.

600 09A

-*""- Sta. 11 400 200 0

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

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

Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities. No plant related isotopes were detected in any indicator samples analyzed. Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is attributed to accumulation of residual global fallout from past atmospheric weapons testing.

4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2017 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.

64

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2017 - North Anna Location Description Date of Sampling Reason( s) for Loss/Exception 14B,15,16,23,26 Vegetation 01/11/17 Seasonal unavailability 14B,15,16,23, 26 Vegetation 02/14/17 Seasonal unavailability 14B,15,16,23,26 Vegetation 03/15/17 Seasonal unavailability C-7 TLD 03/29/17 Lost TLD ENE-40 TLD 06/28/17 TLD Lost ( Power Pole Damaged )

OlA Precipitation 07/ 17/17 February 2017 precipitation sample volume was insufficient for semiannual composite 14B,15,16,23,26 Vegetation 11/15/ 17 Seasonal unavailability 14B,15,16,23,26 Vegetation 12/ 13/17 Seasonal unavailability Station #2 was omitted from Table 2-1 under Air Particulate and Radioiodine sampling stations in 2007 through 2016 Annual Radiological Environmental Operating Reports.

This omission was documented in North Anna Condition Report CR1075273.

65

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 (1 OCFR50), "Domestic Licensing of Production and Utilization Facilities" .

United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I",

October, 1977.

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

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

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

HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 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.

66

APPENDICES 67

APPENDIX A: LAND USE CENSUS Year 2017 68

LAND USE CENSUS North Anna Power Station Louisa County, Virginia January 1 to December 31, 2017 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site R esident Garden(> Meat Milch Milch Boundary 50m 2) A nimal Cow Goat N 0.9 1.3 2.75 2.9 NONE N ONE NNE 0.9 0.9 3.21 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.37 2.4 2.49 NONE NONE E 0.8 1.3 1.75 3.5 N ONE NONE ESE 0.9 1.7 1.7 NONE NONE NONE SE 0.9 1.4 1.4 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE s 0.9 1.03 1.14 2.0 NONE NONE SSW 1 1.27 2.37 2.0 NONE NONE SW 1.1 1.65 1.65 NONE NONE N ONE WSW 1.1 1.62 2.22 NONE NONE NONE w 1.1 1.5 1.93 NONE NONE NONE WNW 1 1.1 2.67 4.98 NONE NONE NW 1 1.0 1.09 NONE NONE NONE NNW 0.9 1.0 1.33 2.3 NONE NONE 69

2016 to 2017 Land Use Census Changes 2016 2017 Nearest Direction Distance Distance Resident NONE Site Boundary NONE Garden N 1.56 2.75 NNE 1.22 3.21 E 2.01 1.75 SE 1.54 1.40 SSW 1.33 2.37 NW 1.28 1.09 NNW 2.54 1.33 Meat Animal NONE Milch Cow NONE Milch Goat NONE 70

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR2017 ANALYTICAL SERVICES QUALITY CONTROL SYNOPSIS A. Interlaboratory Cross-Check Program During this reporting period, 25 nuclides associated with six media types (Air Filter, Charcoal [Air Iodine] , Milk, Soil, Vegetation and Water) were analyzed. Samples were obtained from Analytics, the Department of Energy's (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) and Environmental Resource Associates (ERA). Media types representative of client analyses performed during this reporting period were selected. The results are presented in Attachment A.

1. Analytics Environmental Cross Check Program Fifteen nuclides in milk, air particulate, air iodine (charcoal) and water samples were evaluated for four sets of cross-checks during March - December, 2017. All of the environmental analyses performed were reported as within the acceptable/acceptable with warning criteria except for one Cr-51 in soil sample.

NCR 17-16 was initiated to address the in-house Cr-51 failure and a Corrective Action was issued. All raw data and associated QC data were reviewed and fell within acceptance limits.

2. DOE's MAPEP Quality Assessment Program Thirteen nuclides in water, air particulate, soil, and vegetation samples were evaluated in March - December, 2017. All of the environmental analyses performed were reported as within the acceptable/acceptable with warning criteria except for one U-238 in air particulate sample.

NCR 17-15 was initiated to address the in-house U-238 failure and a Corrective Action was issued. All raw data and associated QC data were reviewed and fell within acceptance limits.

3. ERA Environmental Cross Check Program Twelve nuclides were evaluated in air particulate and water samples during March - December, 2017. All analyses performed were within the acceptable criteria except for Zn-65, Sr-89 and Sr-90 in water samples (one each).

NCR 17-09 was initiated to address the in-house Zn-65 and Sr-89 failures. Corrective Actions for each nuclide were issued. All raw data and associated QC data were reviewed and fell within acceptance limits.

NCR 17-19 was initiated to address the in-house Sr-90 failure and a Corrective Action was issued. All raw data and associated QC data were reviewed and fell within acceptance limits.

71

Analytics Environmental !Radioactivity Cross Check Program Teled~ Brown Enatneertny Environmental Services T BE ldentificartion Known Ratio of iTEE to Monlh/Yea.r Matrix Nucl ide Units Reported Evalualion I)))

Number Val ue 4*J Analytics Result Value March 2017 E118 11 M ilk Sr-8Q 1pCi/L. 87 97.7 0,89 A Sr..QO 1>Ci/L 12.4 16.2 0.77 w E118 12 Milk Ce- 14 tt pC i,11... 135 tt45 O.Q3 A Co-!PB pCi/L 153 150 1.02 A Co-60 pCill... 182 tt 83 1.00 A Or-5 1 pCi/L 258 2QO 0.89 A Cs-tt 34 pCi/L 104 120 0,87 A Cs-137 pCL'I.. 142 tt40 1.02 A Fe-6Q pCi/L. 135 12Q ,.oo, A 1-13 1 pCi/L. Q2 .6, ll7.Q O.Q5 A Mn-64 pCi/L. 173 Ul4 LO!i A Zn-Cl5 pCi/L. 208 1QQ 1.04 A E1 1813 Chia.rcoal 1-13 1 pCi Q2 g3_g O.Q8 A E1~8 t 4 AP Ce- 14 1 pCi IXI.Q 10 1 O.Q9 A Cc-!PB pCi 95 .4 104 O.Q2 A Co-60 pCi 140 127 1.10, A Or-5 1 pCi 2 11 20 1 1.05 A Cs-134 pCi 82..1 83.2 O.Q9 A Cs-137 pCi 92. 8 97.0 O.Q6 A Fe-6Q pCi 107 89.3 1.2,0, A n-54 pCi 106 U 4 O.Q*3 A Zn-Cl5 pCi 137 138 O.Q9 A E1 18 16 Soil Ce-14 1 pCLfg 0.258 0.25'0 1.03 A Co-!PB ,pCi/g 0.241 0.258 O.Q:3 A Co-50 pCi.rg 0.3 12 0.315 O.Q9 A Or"5 1 pCL'g 0.43Q 0.500 o.a0 A Cs-134 pCi.fg 0.176 0.207 0.:8,5, A Cs-137 pCL'g 0.304 0.317 O.Q6, A Fe-6{1 pCi,fg 0.2 10 0.222 O.Q,5, A Mn-54 pCilg 0.2'92 0.283 1.03 A Zn..J65 pCil g O.l53 0 .344 1.03 A E11815 Wats Fe-55 pCi,'I.. 1600 tt 8QO 0115 A (a} The Anafylics !mown !t'alve is equal to 100% of the p..ramete< prNenl .in*the :itandar.d a:i d<<ermined b_y grnimelric andlor volmietric mea:i'lft'l1loMt5 made dl.mng mndaro' preparation

-fbJ Analylic.s evaluation ~ .ed' on TBE infernal QC lmlli$:

A = Acceptable - teported tHutt fa.11:s with.in .rai'o fm~ of 0. 80-1.20

= Acceptable with wam.ing- repo.rted 11!.sul't falf:i 11tifhin C.7(1..0.80 or 1.2(1..1.30 N = Nol Acceptable - reported re:,;Ul'I fa>>.s outside lhe ratio f,imit:i of< ,O. 70 .nd > 1.30 72

Analytics Environmental RadioactMty Cross Oheck Program Te'leclyne Brown Engineering Environmental Services BE ldenti ation Known Rat io of TB E to, Monlhl'Yea r Matrix uclide Units Reported Evaluation ~}

umber Val ue 1" 1 .Analytics Resul Value J une 2Dl7 E1 844 .. *1 Sr -SQ pCill. 81.3 g2.6 D.,88 A S r-QO pC ill. 12.1 13.5 Dago, A E 11846 t. il Ce-141 pCi.ll 142 tt 5 1 o _g4 A Co-58 pCill. 147 155 o_g5, A Co-60 pCill. 185 1Q1 o _g7 A C r-5 1 pCill. 32 1 3 15 1.02 A Cs-134 pCi,'l 168 188 D.SQ, A Cs-137 pCill. 148 150 _gg, A Fe-5Q pCill. 11 6 115 .0 1 A l - tt 3 1 pCi,'l 102 93.6 .OQ1 A IMn-54 pCill. 168 172 [UIB A Zn..e5 pCi.tl 1'!5 204 CHl6, A E 11847 Charcoal 1- tt 3 1 pCi 87 .9 84.,B .04 A E 1 84 5 AP S r-SQ pCi 70.8 79.1 a.go A Sr-QO pCi 9.10 1.5 D.7~ w E 11848 AP C.e-141 pCi 11 2 11 6 o.g6, A Co-58 pCi 11 Q 11Q 1.0D A Co-60 pCi 17 1 146 1.17 .A Cr-5 1 pCi 270 24 1 U 2 A Cs-134 pCi 152 144 1.05, A Cs-tt37 pCi 11 4 115 o _g9 A Fe-5Q pCi 94 .tt S8.3 1.07 A n-54 pCi 13Q 132 l.0 6, A zn..e5 pCi 14 1 156 _go, A E 1 849 Water Fe-55 pCi/1. tt 840 18QO o_g7 A ul y2 17 E 1 QD l AP GR-A pCi ~ ,. 1 44.2 1.13 A GR-B pCi 2 18 233 o_g3 A (a) The AN.fylj'c:s lmOlllll Rl'ue .i:s equal to 100% of the piNii111efer pre:ienJ in the :.fandimJ a5 dederminecl by grav.i metnc .and,,br vat.ume!ric measure.men :. illifde during :standard prep.ration (b) An1mly!ic:s evaoViiOOII ba.$ed on TBE intemal QC lim.n::

A = Accept.ble-,:epoded .re:suft tall:; within ral\io limits of O.SO-t..20

'V = Acceptable 111o'ith warning - reported re:suJt fat/:; within 0.70-0.80 or 1.20-1.30 fl = Not Acceptable -reported reslilt faN:. oufaide the ratio Jimib of < 0.70 and> 1.30 73 I

Analytics Environmental Radioactiviity Cross Check Program Te1ed;t!le Brown Eni,ineerini Environmental Services T BE Identifica tion Known Ratio o f Tl8E to Monthl'Year Matrix uclide Units Reporte-d Evalua tio n ~}

Number Val ue *} Analytics Resul Va e Septem ber 2017 E11Q14 Mil Sr.SQ pCill. 8:4 .3 82.7 1.0'2 A S r-QIJ tpCi.11... 12.6 12.1 1.04 A E 11Q15 .. "lk Ce-141 pCi,11... oo.Q 87.0 1.08 A Co-58 pCi,11... 11 5 117 O.QB. A Co-60 pCi/L 265 262 1.0 1 A Or-5 1 pCiil. 273 217 1.26, w Cs-134 pCi,'L 186 20 1 O.Q:3, A Cs-137 pCiil. 175 172 1.02 A Fe-6Q pCi,iL 137 125 1.0Q1 .A 1-13 pCi,11... 78.0 71.0* 1.10 A M -54 pCi,I L 128 123 1.04 A Zn-65 pCi,11... 206 18 4 U2 A E11Q16 Charcoal 1-13 1 pCi 7 1.Q 64.4 .1 2 A E 11Ql7 AP Ce-141 pCi l!iD.1 86.3 .Q:3 A Co-58 pCi 110 1 6 .Q5 A Co-6D pCi 277 260 t .07 A Or-51 pCi 275 2 5 .2B w Cs-134 pCi 1Q2 mg [lQ6 A Cs-137 pCi Ul5 HO O.Q7 A F>e-6Q pCi 122 124 O.QB A Mn-64 pCi 120 122 O.QQ1 A Zn-65 pCi 175 183 D.Q6 A E 11Q18 Water Fe-65 tpCi,'L 1fl31li 1630 1.00 A E 11QUI Soil Ce-141 pCitg .13'6, lll. 142 Ill.QB, A Co-58 pCi.g 0.17Q 0.1Q*1 O.Q4 A Co-61li pCitg [1_41[15, [J..42'9 O.Q4 A

[I)

C r-51 pCi.g 0.230 D.355 0.65, Cs-134 pCi.fg 0.272 0.32;8, 0.83 A Cs-13-7 pCi.g .33'6 0.356* O.Q4 A Fe-6Q pCi.rg 0.2 10 0.2D5 1.02 A Mn-64 pCi!g 0.2 10 D..201 1.05 A Zn-65 pCitg 0.301 D.3-0*1 1.001 A (aJ The, Anitlylics known value is equal to 1'*00%-of fire parame er p,ie:renf .in*,fhe standard as de.~ed by gravimetric and/or vol'omemc mHSllil'menfs made during standard prepara5on, (bJ Analy!ics evaluaffon based on 1BE inlemal QC lim.~

A = Acceptable, - reported .re5uft fa/1:r within rafio lim.r.; of 0. S0-1.20 W = Acceptab~ with waming - reported result tali:. w,*!hin 0. 70-().80 << 1.20-1.30 N = Nol Acceptable - reported .result falls otrl:iide lhe ra-rio limits of < 0.70 and > 1. 30 (1)' See NCR 17-16 74

Analytics Environmental Radioactivtty Cross Olileck Program Telecl~ Brown Enitneenn11 Environmental Services T BE Iden tification Known Ratio of fflE to Monlh/Yea r J.\atrix Nuclide Units Reported Evaluatio n ~>

Number Value ta} A n alytics R esu lt Value Decem ber 20 17 E 12054 Mill S r-SQ pC iil. 92.1 92.3 1.0D A Sr ..QIJ pCi/L 1.S.3 16.9 1.0Q A E 12055 J.l ilk Ce-141 pCi,'L 97.8 98.3 D.9Q A Co-58 pCill 92.3 89.9 1.03 A Co-60 pCi/L 176 173 1.02 A o r~5 1 pCilL 226 242 0.93 A Cs-134 pCilL 11 8 125 0.95 A Cs-137 pCill. 148 14 1 1.05 A Fe<iQ pC ilL 123 11 3 1.08 A 1-13 1 pCi,ll. 66 .0 57.8 U4 A Mn~ pCi,'1.. 173 16 1 1.oB A Zn-tl5 pCi,ll. 233 2 11 1.10 A E 12056 Chiarcoal 1-13 1 pCi 48 .1 4Hi 1.01 A E 1W57A AP Ce- 14 1 pCi Hl8 111 0.97 A Co-58 pCi S;Q.5 102 D.,88 .A Co-6D pCi 223 U.:16 t.14 A C r-5 1 pCi 311 274 1.13 A Cs-13-4 pCi 14 1 142 LOD A Cs-137 pCi 162 161) 1.0 1 A Fe<iQ pCi 12 1 12Q 0J94 A Mn-64 pCi 177 182 D.97 A Zn-tl5 pCi 203 23Q 0.85 A E 12058 Wa:ter Fe-65 pCi,ll. 1Q70 17 40 1.1 3 A E 12059 AP Sr.SQ pCi 71.2 87.4 D.8 1 A Sr-QCJ pCi 12.9 16.0 o.:e 1 A (a) The-Analytics lrnOl!in ..awe is equal tr;, foo,i;. of i!ne pa.ramete.rp=en! in lhe standard as determined by gravimetric .and/or volumetric me-a.suremenf.s made during standard preparaorm (b} AnaJytics wa.valion based on TBE iinfemaf QC #imh:

A "' Acceptable - repoded r-e;suil! fals withm t.5o #im.~ of 0.80-t ..20

"' Acceptable with wanung- reported result faffs i.t\ilhn 0.70-0.80 or 1.20-1.30 W "'No! Acceptable - reporled reslll't ta>>s omskfe the ratio 1,inits of< ,o. 70 and > 1.30 75

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering Environmental Services TBE lde111fification K nown Acceptance Monthl'Yea r Matrix uclide Units Repo rted Eval uation Umbi! r Val1L1e 1 Ran ge Val ue February 2017 n ~MaS36 Soil i-63 Bqlkg -5!i,12 (1) A Sr-QD Bqlkg !57 1 624 4.37 - 8 11 A 17-MaW36 Water Am-24 1 Bqi1- 0.693 0 .846 0.592 - tt . 100 A 1-63 Bq/l.. 13.4 12. 2 8 .5- tt 5.ll A IPiu-238 Bq/l.. (!_7217 0 .703 0.4*Q2 - Ocll 14 A P,u-2391240 Bq/L O.ll277 O.Q34 D.654 - tt.2 14 A 17--RdlF36 AP U-234/233 B q1sa:m,p1e O.OQH 0 .1 04 0.073 - 0. 135 A U-238 Bqfsam;p1e o.m>>e1 0 .1 07 0.075 -0. 131} A 17-RdV:36 Veg;eta

n C:s,-134 Bqfsa:m,ple tl.44 dQ5 4 .87 ,-9.0 4 A C:s,-137 Bqfsa:m,pl e 4.6 4.60 322-5,Q8 A Co-57 Bqfsa:m,ple -0.0 ~ {1) A Co-60 Bqlsa:m,ple 8.52 8.75 6,.1 3 - H.38 A Mn -~ Bqfsa.m,ple 3.30 3.28 2 .30-4.26 A Sr-00 Bqfsa:m,ple 1.3 tt.75 tt 23 - 2.28 w Zn-6<5, Sq/sample 5.45 5._3g 3 .77- 7.0 A Augu st2017 17-. ~a,S31 Soil J-63 Bq,'kg U 30 122,0 854 - 1586 A Sr-ltD Bq,'kg 2Q6 281} 202-376 A 17-MaW37 Water Am-24 1 B c;IL 0.838 0 .8Q2 0*.624 - 1. 16 A j.ifl,3, B(ill -OJJQ6, (1 )' A Pu-238 Bqll. o.~2 .603 0.422 - 0.784 A Plu-23{1.!2 40 Bqi'L 0.863 0 .78 1 0.547 - tt .0 15 A 17-RdlF37 AP U-234/233 Bqfsam;ple 0. 103 0 .084 D.05Q - 0 . 10Q w U-238 Bqfsam,ple 0. 115 0 .087 D. 61 - 0. 11 3 17-RldV37 Veg;-eta

n C:s,-134 B (ilsam ple 2.34 232 1.62 -3..02 A C:s,-137 B11r-sam,ple. 0.05 (1) A Co-67 Bqlsarnp1e 3.32 2.8 2.0 -3. 6 A Co-60 Bqfsam,p1e 2.0Q 2.07 tt .45-2.6Q A Mn-~ Bqfsam,p1e 2. QD 2.62 tt .83-3.4 1 A Sr-91J B11rsam,ple U 1 L 23 o.se - tt.eo A Zn-6,5 Bqlsa:m ple 6 .07 5.37 3 .76-6.Q8 A (a) The UAPEP knDil'll r 1ue .is equal to 100% of the parameter pra:sent ii ftle .mndarr/ az de erm.ned by 91!iill\ffle.fric and4lr'l>'Olume:fm:

m-lll!WDffll'.:i m.,de during .z .ndard pre,,aration (b) DOEIMAPEP e.*:a1ttadim:

A =Acceptab,le - reparfed ,re.su,\t fa.lb, w.ithin ratio ~ of 0.80-1 .20 W =Acceptable with ~*a.ming

r:eported !Mul'tfa/1.s wifh.ill ,0.7,0-0.SOor 1.20-1.30 N = Urn Acceptable - IV!floded re:su Iii/Is ou.!side the raw fim.'ts of < o.70 and > 1.30 (1) Fal:;,e po:;mve te~t (2) See NCR tt7- 15, 76

ERA Environmental Radioactiv,it y Cross Check Program Teledyne Brown Engineerin g Environmenta Services Tl3!E dentri1icafion !Known Acceptance )

tenth/Year JMa1rix uclicfe U n&!s Repcried ) Evaluation N umber Va e Limits Value arch 20 17 RAD-26 AP GR-A pCilsample 7iL3 85.5 28.6- 133 A ApJil 2017 RAD-10Q Waler Ba-133 pCill 4Q.2 4Q.7 40,8-55.1 A C-s-134 pCill 83.2 QD.1 74_0-QQ.1 A Cs- 137 pCill 2!02 206 185 - 228 A Co-60 pCii'l 5,1.2 54.7 *49.2-62.7 A

[ti Zn-65 pCii'l 3g.3 53.8 47.2-65.Q GR-A pCill 53.6* 75.0 3Q_5 - Q2_3 A GR-B pCii'l 42.7 38.5 25.5-46.0 A IJI.Nat pCill 50.U 55.6 45, 2-6 1.7 A H-3 pCii'l 7090 6850 5920 - 7540 A

[ti Sr~BQ pCii'l '40.7 66--2 53.8- 74.3 Sr-QO pCill 26,Q 26.7 1R3 - 3 U A 1- 13,1 pCii'l 26.7 2Q.Q 24.Q- 34.Q A Sep ember2.0 17 MRAD-27 AP GR-A pCil'sample 41!LQ* 50.1 16,. 8 - n .a A AP GR-B pCil'sample 58.0* 6 .8 3Q. 1 - Q0.1 A Oc!Dber 2017 RAD--11 1 Waier Ba..-133 pCii'l 71 .3, 73.7 6 L 7 - 8 1.1 A Cs.-134 pCill 43.0* 53.0 428 - 58.3 A Cs.-137 pCii'l 48.2 52.'I 47.6-6,1.1 A C o-6,()1 pCii'l 6,t o, 6Q.5 62..6 - 78.Q A Zn-65 pCii'l 335 348 313 - 406 A GR-A pCii'l 32..5, 35.6 18-3-45.8 A GR-B pCii'l 24,3, 25.fl 16, 0 - 33.6, A U-Nat pCii'l 36.6* 37.0 30.0 - 40.Q A H-3 pCi/L 6'Zl 6250 5300 - 6880 A 1- 3,1 pCii'l 21fl.4 24.2 20i. 1 -28.7 A

1ember 2 17 t1 3 170 Waler Sr~BQ pCii'l 57.1 50.0 39.4-57.5 A C2)

Sr-QO pCfu'l 27.1 4 1.8 30.8 - 48.0 a} The ERA b>D1m '1ih'ue is equal ro 100% of the ~fe<rpr,e2r1t .in ~e ~dam' a.s defemnilEd by 91-v.inekic a~w vDll~

mea.suremems made dumg .standard prepara6on.

b} ERA evahatioo:

A = ~-Reported value fall's 1tt'i!hn the A~nce limz N = tJat Acceptable

Reported *va/m> fal,.s our.fide of the Alcceplance Llinil'.s 1(1) See NCR 17--08 1(2), See NCR 17- 1Q 77

ML18128A264

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