Text

Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report
	ML17125A202
Person / Time
Site:	Surry, 07200002, 07200055
Issue date:	04/27/2017
From:	Lawrence D; Virginia Electric & Power Co (VEPCO)
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	17-116
	Download: ML17125A202 (76)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 27, 2017 United States Nuclear Regulatory Commission Serial No.17-116 Attention: Document Control Desk S&L/TSC RO Washington, DC 20555-0001 Docket Nos. 50-280 50-281 72-2 72-55 License Nos. DPR-32 DPR-37 SNM-2501 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry Units 1 and 2 Technicaf Specification 6.6.B.2 requires the submittal of an Annual Radiological Environmental Operating Report (AREOR) for Surry Power Station. Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specification Appendix C, Item 1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2016 through December 31, 2016, which includes environmental monitoring for the Surry ISFSI.

If you have any further questions, please contact Lee Ragland at 757-365-2010.

Douglas C. wrence Director Safety & Licensing Surry Power Station Attachment Commitments made in this letter: None

Serial No.17-116 Docket Nos.: 50-280 50-281 72-2 72-55 cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 NRG Senior Resident Inspector Surry Power Station Director, Virginia Health Department Division of Radiological Health 109 Governor Street, Room 730 Richmond, Virginia 23219

Serial No.17-116 Docket Nos.: 50-280 50-281 72-2 72-55 ATTACHMENT 1 2016 Annual Radiological Environmental Operating Report SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

Surry Power Station 2016 Annual Radiological Environmental Operating Report

Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2016 to December 31, 2016 Annual Radiological Environmental Operating Report

Surry Power Station January 1, 2016 to December 31, 2016 Prepared by: _ _ _/_._f_._$--+--~--T_,_____

P. F. Blount Health Physicist Reviewed by: ------~ __ __,_A_._/_-r-_l o.. __._.,_______

P.R. Harris SuperiZ:?CJT~hfilcfil Scrvic~

Approvedby:~~~~~~~~~~~"""'d"-~~~~~~~~~~~

T. L. Ragland Manager Radiological Protection and Chemistry

Table of Contents PREFACE .............................................................................................................................................. 4

1. EXECUTIVE

SUMMARY

.............................................................................................................. 5

2. PROGRAM DESCRIPTION ............................ .'............................................................................... 7 2.1 Introduction ............................................................................................................................. 7 2.2 Sampling and Analysis Program ............................................................................................. 8

3. ANALYTICAL RESULTS ..................................................... :...................................................... 20 3.1 SummaryofResults .............................................................................................................. 20 3.2 Analytical Results of 2016 REMP Samples ........................................................................ .28

4. DISCUSSION OF RESULTS ..................................................................................................... 49 4.1 Gamma Exposure Rate ......................................................................................................... 49 4.2 Airborne Gross Beta ............................................................................................................. 50 4.3 Airb,eme Radioiodine ............................................................................................................ 51 4.4 Air Particulate Gamma ......................................................................................................... 51 4.5 Cow Milk .............................................................................................................................. 52 4.6 Food Products ....................................................................................................................... 52 4.7 Well Water ............................................................................................................................ 52 4.8 RiverWater ........................................................................................................................... 53 4.9 Silt ......................................................................................................................................... 53 4.10 Shoreline Sediment ............................................................................................................. 55 4.11 Fish ...................................................................................................................................... 55 4.12 Oysters ................................................................................................................................ 56 4.13 Clams .................................................................................................................................. 56 4.14 Crabs ................................................................................................................................... 56

5. PROGRAM EXCEPTIONS ........................................................................................................... 57

6. CONCLUSIONS ............................................................................................................................. 58 REFERENCES .................................................................................................................................... 60 APPENDICES ..................................................................................................................................... 62 APPENDIX A: LAND USE CENSUS ........................................................................................... 63 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS ............................... 65 3

PREFACE This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report, for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281, and the Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications, Appendix C, Item 1.3.1.

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1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2016 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2016, in air, water, silt, shoreline sediment, milk, aquatic biota, food products and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to confirm that radiological effluent releases are As Low As (is) 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 20-mile radius of the station. Surry Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. The first type, control samples, is collec~ed from areas that are beyond the measurable influence of Surry Power Station or any other nuclear facility. These samples represent normal background radiation levels. Background radiation levels 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 control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or natural variation, or other causes such as the Chernobyl and Fukushima Daiichi accidents that released radioactive material to the environment.

Teledyne Brown Engineering, Inc. (TBE) provides radioanalyses for this program and Mirian Technologies provides thermoluminescent dosimetry (TLD) 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 iow that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the United States Nuclear Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The USNRC also mandates a reporting level for radionuclides. Licensed nuclear facilities must report the radionuclide activities in those env!ronmental 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.

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Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates. The 2016 airborne results were similar to previous years. No station related radioactivity was detected and natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters. Naturally occurring radionuclides such as beryllium-7, potassium-40, radium-226, thorium-228 and thorium-232 were detected at average environmental levels. No man-made radionuclides were detected in well water.

This trend is consistent throughout the operational environmental monitoring program. No man-made radionuclides were detected in river water. Silt samples indicated the presence of cesium-137 and naturally occurring radionuclides. The cesium-137 activity was present in the control location and is attributable to global fallout from past nuclear weapons testing and nuclear accidents such as Chernobyl. Shoreline sediment, which may provide a direct exposure pathway, contained no station related radionuclides. Naturally occurring radionuclides potassium, radium and thorium were detected at average environmental levels.

The terrestrial exposure pathway includes milk and food products. lodine-131 was not detected in any 2016 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. No

.man-made radionuclides were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk. Naturally occurring potassium-40 was detected in food products. The direct exposure pathway measures environmental radiation doses using TLDs. TLD results have remained relatively constant over the years.

During 2016, as in previous years, the operation of Surry Power Station has 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 2016 was 0.022 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 sources in the environment provide approximately 50% of radiation exposure to man, while nuclear power contributes less than 0.1 %. These results demonstrate compliance with federal and state regulations and also demonstrate the adequacy of radioactive effluent controls at Surry Power Station.

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2. PROGRAM DESCRIPTION 2.1. Introduction This *report documents the 2016 Surry Power Station operational Radiological Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. 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 is designed with a nominal gross electrical output of 910 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.

The United States Nuclear Regulatory Commission regulations (10CFR50.34a) require that nuclear power plants be designed, constructed and operated to keep levels of radioactive material in effluents to unrestricted areas As Low As (is)

Reasonably Achievable. To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications that address the release of radioactive effluents. In-plant monitoring is used to ensure that these release limits are not exceeded. As a precaution against unexpected or undefined environmental processes, which might allow undue accumulatipn of radioactivity in the environment, a program for monitoring the station environs is also included in Surry Power Station Technical Specifications.

Dominion personnel are responsible for collecting the various indicator and control environmental samples. Mirion Technologies is responsible for processing the 1LDs. Teledyne Brown Engineering is responsible 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 values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioriuclides. Data collected prior to station operation is used to indicate the degree of natural variation to be expected. This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.

Occasionally, samples of environmental media may show the presence of man-made radionuclides. 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 the USNRC Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",

(December, 197~) and VPAP-2103S, Offsite Dose Calculation Manual (Surry).

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."

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Tilis report documents the results of the REMP for 2016 and satisfies the following objectives of the program:

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

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

~ To identify changes in radioactivity in the environment.

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

2.2 Sampling and Analysis Program Table 2-1 summarizes the 2016 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." Dominion personnel collect all samples listed in Table 2-1.

Table 2-2 summarizes the analysis program conducted by Teledyne Brown Engineering and Mirion Technologies for Surry Power Station. All samples, with the exception of the TLDs, are shipped to Teledyne Brown Engineering, located in Knoxville, TN, for analysis. The TLDs are shipped to Mirion Technologies, located in Irvine, CA, for processing.

The Surry RadiOlogical Monitoring Locations maps (Figures 1 - 5) denote sample locations for Surry Power Station. Tue locations are color coded to designate sample types.

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-1 Table 2-1 SURRY-2016 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Pg. 1 of3 Distance Collection Sam~le Media Location Station Miles Direction Degrees Freguenc~ Remarks Environmental Control (00) Quarterly Onsite (Stored in a lead shield outside the protected area)

TLDs West North West (02) 0.2 WNW 293° Quarterly Site Boundary Surry Station Discharge (03) 0.4 NW 321° Quarterly Site Boundary North North West (04) 0.2 NNW 329° Quarterly Site Boundary North (05) 0.3 N 40 Quarterly Site Boundary North North East (06) 0.3 NNE 28° Quarterly Site Boundary North East (07) 0.3 NE 44° Quarterly Site Boundary East North East (08) 0.4 ENE 67° Quarterly Site Boundary East (09) 0.3 E 890 Quarterly Site Boundary West (10) 0.1 w 271° Quarterly Site Boundary West South West (11) 0.4 WSW 252° Quarterly Site Boundary South West (12) 0.3 SW 228° Quarterly Site Boundary South South West (13) 0.3 SSW 201° Quarterly Site Boundary South (14) 0.4 s 182° Quarterly Site Boundary South South East (15) 0.6 SSE 157° Quarterly Site Boundary South East (16) 0.9 SE 135° Quarterly Site Boundary Station Intake (18) 1.6 ESE 115° Quarterly Site Boundary Hog Island Reserve (19) 2.0 NNE 26° Quarterly Near Resident Bacon's Castle (20) 4.5 SSW 202° Quarterly Apx. 5 mile Route 633 (21) 4.9 SW 227° Quarterly Apx. 5 mile Alliance (22) 5.1 WSW 247° Quarterly Apx. 5 mile Surry (23) 7.7 WSW 256° Quarterly Population Center Route 636 and 637 (24) 4.0 w 270° Quarterly Apx. 5 mile Scotland Wharf (25) 5.0 WNW 284° Quarterly Apx. 5 mile Jamestown (26) 6.3 NW 308° Quarterly Apx. 5 mile Colonial Parkway (27) 3.8 NNW 333° Quarterly Apx. 5 mile Route 617 and 618 (28) 4.9 NNW 340° Quarterly Apx. 5 mile K.ingsmill (29) 4.6 N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.8 N oo Quarterly Population Cel}ter Kingsmill North (31) 5.5 NNE 12° Quarterly Apx. 5 mile Budweiser (32) 5.8 NNE 27° Quarterly Population Center Water Plant (33) 5.0 NE 46° Quarterly Apx. 5 mile 9

Table 2-1 SURRY-2016 RADIOWGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Pg. 2 of3 Distance Collection Sampte Media Location Station Miles Direction Degrees Frequency Remarks Environmental BASF (34) 5.1 ENE 70° Quarterly Apx. 5 mile TLDs Lee Hall (35) 7.1 ENE 75° Quarterly Population Center Goose Island (36) 5.1 E 90° Quarterly Apx. 5 mile Fort Eustis (37) 4.9 ESE 104° Quarterly Apx. 5 mile Newport News (38) 19.3 SE 130° Quarterly Population Center James River Bridge (39) 17.l SE 142° Quarterly Control Location Benn's Church (40) 17.0 SSE 159° Quarterly Control Location Smithfield (41) 13.4 SSE 167° Quarterly Control Location Rushmere (42) 5.3 SSE 156° Quarterly Apx. 5 mile Route 628 (43) 5.1 s 177° Quarterly Apx. 5 mile Air Charcoal Suny Station (SS) 0.3 NNE 18° Weel<ly Site boundary location with highest D/Q and Particulate Hog Island Reserve (HIR) 2.0 NNE 26° Weel<ly Bacon's Cas,tle (BC) 4.5 SSW 202° Weel<ly Alliance (ALL) 5.1 WSW 247° Weel<ly Colonial Parkway (CP) 3.8 NNW 333° Weel<ly BASF (BASF) 5.1 ENE 70° Weel<ly Fort Eustis (FE) 4.9 ESE 104° Weel<ly Newport News (NN) 19.3 SE 130° Weel<ly Control Location River Water Suny Station Discharge (SD) 0.4 NW 323° Monthly Scotland Wharf (SW) 4.9 WNW 284° Monthly Control Location Well Water Suny Station (SS) 0.1 SW 227° Quarterly Onsite Hog Island Reserve (HIR) 2.0 NNE 280 Quarterly Construction Site (CS) 0.3 E 87° Quarterly Shoreline Hog Island Reserve (HIR) 0.6 N 70 Semi-Annually Sediment Chickahominy River (CHIC) 11.2 WNW 301° Semi-Annually Control Location Silt Chickahominy River (CHIC) 11.2 WNW 300° Semi-Annually Control Location Suny Station Discharge (SD) 1.3 NNW 341° Semi-Annually 10

Sample Media Location Milk Colonial Parkway W illiaffi'l Lover Retreat Epps Oysters Point of Shoals Mulbeny Point lawne's Creek Clams Chickahorniny River Surry Station Discharge Jamestown Island Fish Surry Station Discharge Crabs Surry Station Discharge Crops Brock's Farm (Corn, Peanuts, Slade's Farm Soybeans) 11

Table 2-2 SURRY-2016 SAMPLE ANALYSIS PROGRAM Pg. 1 of3 SAMPLE MEDIA ~UENCY ANALYSIS LLD* REPORT UNITS Thermolumines cent Quarterly Gamma Dose 2 mR/Std. Month Dosimetry (1LD) 3 Air Iodine Weel<ly I-131 O.Q7 pCi/m Air Particulate Weel<ly Gross Beta 0.01 pCi!m3 3

Quarterly (a) Gamma Isotopic pCi/m Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium(H-3) 2000 pCi/L Composite of monthly sample Monthly I-131 10 pCi/L Gamma Isotopic pCi/L

. Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium(H-3) 2000 pCi/L I-131 1 Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Footnotes located at end of table.

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Table 2-2 SURRY-2016 SAMPLE ANALYSIS PROGRAM Pg. 2 of3 SAMPLE MIDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Sediment Semi-Annually Garrnna Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Silt Semi-Annually Garrnna Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Milk Monthly I-131 pCi/L Garrnna Isotopic pCi/L Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 NA pCi/L Composite ofCP Sr-90 NA monthly sample Oysters Semi-Annually Garrnna 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 Clams Semi-Annually Garrnna 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 Crabs Annually Garrnna 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 Footnotes located at end of table.

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Table 2-2 SURRY-2016 SAMPLE ANALYSIS PROGRAM Pg. 3 of3 SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS 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 Annually Gamma Isotopic pCi/kg -wet I-131 60 Cs-134 60 Cs-137 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that ar are measurable and identifiable, together with the above nuclides, are also identified and reported.

LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. LLDs indicate those concentrations to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than these listed values.

(a) Quarterly composites of each location's weekly air particulate samples are analyzed for gamma emitters.

NA None assigned 14

WSW ESE SW Legend

Air Sampling Stations SSW

TLD Sampling State Environmental Monitoring Sites

State TLD Sites Figure 1. Surry Radiological Monitoring Locations

Figure 2. Surry Emergency Plan Map e Air Sampling Stations e Nearest Residents Gl

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Figure 5. Surry Emergency Plan Map e Air Sampling Stations e Nearest Residents e TLD Sampling e Nearest Milk Animal e Nearest Garden Aquatic Samples Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. US ED WITH PERMISSION. No other reproduction may be made without the written permission of ADC .

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3. ANALYTICAL RESULTS 3.J. Summary ofResults In accordance with the Surry 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", Revision 1, November 1979. A more detailed analysis of the data is given in Section 4.

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TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Vrrginia - 2016 Docket No. 50-280-281 Page 1 of7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled (Units) Type

!Total No. LLD Mean Range IDistance Name Direction I Mean Range Mean Range Reported Measurements Air Gross 416 10 13.9 (363/364) BC 4.5m1 16.2 (52/52) 12.2 (52/52) 0 Particulate Beta (4.74-34.1) SSW (5.1 - 33.1) (5.3. 22.3)

(1E-3 pCilm3)

Gamma 32 Be-7 32 140.6 (28/28) ALL 5.1 mi 160.3 (4/4) 131.8 (4/4) 0 (86.7. 218) WSW (115. 218) (99.0 -163)

K-40 32 15.6 (2/28) CP 3.Bmi 16.3 (1/4) <LLD 0 (14.9. 16.3) NNW (16.3. 16.3)

Cs-134 32 50 <LLD NIA <LLD <LLD 0 Cs-137 32 60 <LLD NIA <LLD <LLD 0 Air Iodine 1-131 416 70 <LLD NIA <LLD <LLD 0

. (1E-3 pCilm3)

Milk Strontium 4 (pCi/Uter)

Sr-89 4 <LLD N/A <LLD <LLD 0 Sr-90 4 1.59 (3/4) CP 3.7*mi 1.59 (3/4) <LLD 0 (1.33. 1.79) NNW (1.33 -1.79)

Gamma 36 K-40 36 1349 (24/24) CP 3.7mi 1355 (12/12) 1562 (11/12) 0 (1080. 1530) NNW (1080. 1530) (1270. 1850) 1-131 36 1 <LLD NIA <LLD <LLD 0 Cs-134 36 15 <LLD N/A <LLD <LLD 0 Cs-137 36 18 <LLD NIA <LLD <LLD 0 Ba-140 36 60 <LLD N/A <LLD <LLD 0 La-140 36 15 <LLD NIA <LLD <LLD 0 21

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2016 Docket No. 50-280-281 Page 2 of7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean . Locations Non-Routine Sampled (Units) Type

!Total No. LLD Mean Range I Distance Name Direction I. Mean Range Mean Range Reported Measurements Food Gamma 3 Products (pCi!kg v.et) K-40 3 11120 (3/3) Slade 3.2mi 22900 (1/1) N/A 0 (4730

22900) s (22900-22900)

Be-7 3 <LLD NIA <LLD N/A 0 Th-228 3 <LLD NIA <LLD N/A 0 1-131 3 60 <LLD NIA <LLD N/A 0 Cs-134 3 60 <LLD NIA <LLD N/A 0 Cs-137 3 80 <LLD NIA <LLD NIA 0 Well H-3 12 2000 <LLD NIA <LLD N/A 0 (pCi/Uter)

Gamma 12 K-40 12 66.8 (1/12) cs 0.3mi ,66.8 (1/12) N/A 0 (66.8

66.8) E (66.8

66.8)

Ra-226 12 113 (1/12) SS 0.1 mi 113 (1/12) N/A 0 (113. 113) E (113-113)

Mn-54 12 15 <LLD NIA <LLD N/A 0 Co-58 12 15 <LLD NIA <LLD N/A 0 Fe-59 12 30 <LLD NIA <LLD N/A 0 Co-60 12 15 <LLD NIA <LLD N/A 0 Zn-65 12 30 <LLD NIA <LLD N/A 0 22

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Suny Power Station, Suny County, Virginia - 2016 Docket No. 50-280-281 Page 3 of7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled (Units) Type

!Total No. LLD Mean Range I Distance Name Direction I Mean Range Mean Range Reported Measurements Well Nb-95 12 15 <LLD NIA <LLD N/A 0 Water (pCi/Liter)

Zr-95 12 30 <LLD NIA <LLD N/A 0 1-131 12 <LLD NIA <LLD N/A 0 Cs-134. 12 15 <LLD NIA <LLD N/A 0 Cs-137 12 18 <LLD NIA <LLD N/A 0 Ba-140 12 60 <LLD NIA <LLD N/A 0 La-140 12 15 <LLD NIA <LLD N/A 0 River H-3 8 2000 <LLD NIA <LLD <LLD 0 (pCi!Uter)

Gamma 24 K-40 24 84.0 (5/12) SD 0.4mi 84.0 (5/12) 67.8 (2/12) 0 (59.3 -112) NW (59.3 -112) (65.2

70.3)

Ra-226 24 253 (1/12) SD 0.4mi 253 (1/12) <LLD 0 (253. 2~3) NW (253. 253)

Th-228 24 <LLD NIA <LLD 9.11 (1/12) 0 (9.11. 9.11)

Mn-54 24 15 <LLD NIA <LLD <LLD 0 Co-58 24 15 <LLD NIA <LLD <LLD 0 Fe-59 24 30 <LLD NIA <LLD <LLD 0 Co-60 24 15 <LLD NIA <LLD <LLD 0 Zn-65 24 30 <LLD NIA <LLD <LLD 0 23

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Vrrginia - 2016 Docket No. 50-280-281 'Page 4 of7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled (Units) Type rota No.

I LLD Mean Range IDistance Name Direction I Mean Range Mean Range Reported Measurements River 1-131 24 10 <LLD N/A <LLD <LLD 0 Water (pCi/Liter)

Cs-134 24 15 <LLD N/A <LLD <LLD 0 Cs-137 24 18 <LLD N/A <LLD <LLD 0 Ba-140 24 60 <LLD N/A <LLD <LLD 0 La-140 24 15 <LLD N/A <LLD <LLD 0 Silt Gamma 4 (pCi/kg dry)

Be-7 4 3170 (1/2) SD 1.3 mi 3170 (1/2) <LLD 0 (3170 - 3170) NNW (3170 - 3170)

K-40 4 15700 (2/2) CHIC 11.2 mi 17200 (2/2) 17200 (2/2) 0 (10000-21400) WNW (15900-18500) (15900-18500)

Cs-134 4 150 <LLD N/A <LLD <LLD 0 Cs-137 4 180 <LLD CHIC 11.2 mi 226 (2/2) 226 (2/2) 0 WNW (219 - 233) ' (219 - 233)

Ra-226 4 2255 (2/2) CHIC 11.2 mi 2620 (2/2) 2620 (2/2) 0 (1910 ~ 2600) WNW (2510 - 2730) (2510 - 2730)

Th-228 4 1209 (2/2) CHIC 11.2 mi 1745 (2/2) 1745 (2/2) 0 (818 - 1600) WNW (1700 - 1790) (1700 -* 1790)

Th-232 4 1088 (2/2) CHIC 11.2 mi 1240 (2/2) 1240 (2/2) 0 (786 - 1390) WNW (1200 - 1280) (1200 - 1280) 24

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Suny Power Station, Suny County, Vrrginia- 2016 Docket No. 50-280-281 Page 5 of7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled !Total Mean I Distance I Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Shoreline K-40 4 5805 (2/2) HIR 0.6mi 5805 (2/2) 1910 (2/2) 0 (pCilkg dry) (3650 - 7960) N (3650 - 7960) (1820 - 2000)

Cs-134 4 150 <LLD N/A <LLD <LLD 0 Cs-137 4 180 <LLD N/A <LLD <LLD 0 Ra-226 4 <LLD CHIC 11.2 mi 1390 (1/2) 1390 (1/2) 0 WNW (1390 - 1390) (1390 - 1390)

Th-228 4 1920 (1/2) HIR 0.6mi 1920 (1/2) 1090 (2/2) 0 (1920 - 1920) N (1920 - 1920) (930 -1250)

Th-232 4 . 1550 (1/2) HIR 0.6mi 1550 (1/2) 1015 (2/2) 0 (1550 -1550) N (1550 - 1550) (790 -1240)

Fish Gamma 4 (pCilkg l'A'lt)

K-40 4 2548 (4/4) SD 1.3 mi 2548 (4/4) NIA 0 (1810 - 3170) NNW (1810 - 3170)

Mn-54 4 130 <LLD N/A <LLD N/A 0 Co-58 4 130 <LLD N/A <LLD NIA 0 Fe-59 4 260 <LLD N/A <LLD N/A 0 Co-60 4 130 <LLD N/A <LLD NIA 0 Zn-65 4 260 <LLD N/A <LLD N/A 0 Cs-134 4 130 <LLD N/A <LLD N/A 0 Cs-137 4 150 <LLD NIA <LLD N/A 0 25

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Vrrginia - 2016 Docket No. 50-280-281 Page 6of7 Medium or Indicator Control Pathway Locations Location with Highest Mean Locations Non-Routine Sampled ean istance ean ean Reported (Units) Type LLD Range Name Direction Range Range Measurements Oysters Gamma 6 (pCi/kg wet)

K-40 6 770 (5/6) POS 6.4mi 844 (2/2) NIA 0 (581

1090) .SSE (597 -1090)

Mn-54 6 130 <LLD N/A <LLD NIA 0 Fe-59 6 260 <LLD NIA <LLD NIA 0 Co-58 6 130 <LLD N/A <LLD NIA 0 Co-60 6 130 <LLD N/A <LLD NIA 0 Zn-65 6 260 <LLD N/A <LLD NIA 0 Cs-134 6 130 <LLD N/A <LLD NIA 0 Cs-137 6 150 <LLD N/A <LLD NIA 0 Clams Gamma .6 (pCi/kg wet)

K-40 6 630 (2/4) JI 3.9mi 712 (1/2) '675 (1/2) 0 (548. 712) NW (712. 712) (675. 675)

Mn-54 6 130 <LLD N/A <LLD <LLD 0 Co-58 6 130 <LLD NIA <LLD <LLD 0 Fe-59. 6 260 <LLD N/A <LLD <LLD 0

. Co-60 6 130 <LLD NIA <LLD <LLD 0 Zn-65 6 260 <LLD NIA <LLD <LLD 0 Cs-134 6 130 <LLD NIA <LLD <LLD 0 Cs-137 6 150 <LLD NIA <LLD <LLD 0 26

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Suny Power Station, Suny County; Vrrgiriia - 2016 Docket No. 50-280-281 Page 7 of7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled !Total Mean I Distance 1

Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Crabs Gamma 1 (pCilkg v,et)

K-40 1180 (1/1) SD 1.3 mi 1180 (1/1) NIA 0 (1180 - 1180) NNW (1180 -1180)

Mn-54 1 130 <LLD N/A <LLD NIA 0 Co-58 1 130 <LLD NIA <LLD NIA 0 Fe-59 1 260 <LLD NIA <LLD NIA 0 Co-60 130 <LLD N/A <LLD NIA 0 Zn-65 260 <LLD N/A <LLD NIA 0 Cs-134 130 <LLD N/A <LLD NIA 0 Cs-137 150 <LLD N/A <LLD NIA 0 27

3.2 Analytical Results of 2016 REMP Samples

- Radiological analyses of environmental media charactetj.stically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The reported error is two times the standard deviation (2cr) of the net activity. Uriless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 2cr uncertainty.

Teledyne Brown Engineering 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 SurryODCM.

Data are given according to sample type as indicated below.

1. Gamma Exposure Rate

2. Air Particulates, Weekly Gross Beta Radioactivity

3. Air Particulates, Weekly 1-131

4. Air Particulates, Quarterly Gamma Spectroscopy

5. Cow Milk

6. Food Products

7. Well Water

8. River Water

9. Silt

10. Shoreline Sediment

11. Fish .

12. Oysters

13. Clams

14. Crabs 28

TABLE 3-2: GAMMA EXPOSURE RATE Surrv Power Station. Surrv Countv. Virginia - 2016 MDD 0 =3xcr0 =3xl.0=3(5) Note: IF MDD 0 < 5 mR, THEN MDD 0 rounded to 5 mR {ANSI N13.37)

MDDA = 3 x O"A = 3 x 2.8 = 8.8 {10) Note: IF MDDA < 10 mR, THEN MDDA rounded to 10 mR {ANSI N13.37)

Moni- Quarterly Normalized Quarterly Quarterly Facility Annual Annual Annual toring Baseline, Monitoring Data, M 0 Dose,* Base- Moni- Facility Loca- Bo (mrem per standard Fo=Mo- Bo Ii ne, BA toring Dose,"

tion Baseline, quarter) (mrem) (mrem) Data, FA=

(mrem) MA MA- BA 1 2 3 4 1 2 3 4 (mrem) (mrem) 2 19.8 19.7 19.4 20.3 18.8 ND ND ND ND 79.7 78.3 ND 3 19.1 19.4 17.9 19.7 19.7 ND ND ND ND 76.1 76.7 ND 4 17.7 17.0 16.4 18.8 18.2 ND ND ND ND 71.0 70.4 ND 5 18.9 18.8 19.7 20.3 19.4 ND ND ND ND 74.7 78.3 ND 6 18.4 17.9 17.3 19.7 19.1 ND ND ND ND . 73.5 74.0 ND 7 18.6 17.9 19.1 18.8 18.8 ND ND ND ND 74.1 74.6 ND 8 16.9 17.0 15.8 17.3 17.6 ND ND ND ND 67.8 67.6 ND 9 23.1 22.8 23.4 23.7 23.1 ND ND ND ND 92.4 92.8 ND 10 18.2 17.6 17.0 19.4 17.6 ND ND ND ND 73.0 71.6 ND 11 16.0 16.7 16.1 16.7 16.1 N.D ND ND ND 63.3 65.5 ND 12 16.6 15.8 16.1 17.0 16.7 ND ND ND ND 66.5 65.5 ND 13 18.5 18.2 17.3 19.1 19.1 ND ND ND ND 73.8 73.7 ND 14 17.8 18.2 15.5 19.4 18.5 ND ND ND ND 70.9 71.6 ND 15 18.4 18.2 16.4 18.5 18.8 ND ND ND ND 74.0 71.9 ND 16 16.9 17.3 15.8 17.3 17.6 ND ND ND ND 67.1 67.9 ND 18 14.3 14.9 13.7 15.2 15.2 ND ND ND ND 56.5 58.8 ND 19 15.4 15.5 14.3 15.8 16.1 ND ND ND ND 61.6 61.6 ND 20

14.3 14.3 13.7 14.6 14.9 ND ND ND ND 57.1 57.3 ND 21 15.0 14.9 14.6 16.1 15.8 ND ND ND ND 59.3 61.3 ND 22 13.0 13.0 12.7 13.3 13.7 ND ND ND ND 52.0 52.8 ND 23 17.8 18.2 16.1 18.2 18.5 ND ND ND ND 71.5 71.0 ND 24 14.7 14.9 15.8 14.9 15.2 ND ND ND ND 58.3 60.7 ND 25 18.1 17.6 20.6 18.2 18.2 ND ND ND ND 71.7 74.6 ND 26 16.8 15.2 15.8 16.4 15.5 ND ND ND ND 68.7 62.8 ND 27 14.6 14.6 13.3 15.8 14.9 ND ND ND ND 58.2 58.5 ND 28 14.1 14.3 13.0 15.2 14.6 ND ND ND ND 56.3 57.0 ND 29 13.1 13.3 12.7 13.3 13.3 ND ND ND ND 52.5 52.8 ND 30 14.4 15.5 14.0 15.5 14.3 ND ND ND ND 57.1 59.2 ND 31 12.2 12.1 11.2 12.1 12.4 ND ND ND ND 49.3 47.9 ND 32 15.2 . 15.2 14.0 15.5 m ND ND ND N/A 61.1 59.5 ND

.33 14.0 14.3 12.1 14.9 14.9 ND ND ND ND 56.2 56.1 ND 34 15.9 15.8 14.3 17.6 16.4 ND ND ND ND 63.3 64.0 ND 35 18.3 18.8 18.5 20.6 19.7 ND ND ND ND 72.0 77.7 ND 36 18.5 18.5 19.1 20.0 18.2 ND ND ND ND 73.1 75.8 ND 37 15.3 15.2 13.7 16.4 15.8 ND ND ND ND 61.4 61.0 ND 38 21.0 20.6 19.7 21.2 20.9 ND ND ND ND 84.3 I 82.5 ND 39 14.8 14.9 14.9 15.5 14.6 ND ND ND ND 58.9 59.8 ND 40 16.1 16.1 16.7 17.6 16.1 ND ND ND ND 63.8 66.4 ND 41 21.7 21.8 20.0 22.4 21.8 ND ND ND ND 87.2 86.1 ND 42 16.2 17.0 15.5 16.7 16.7 ND ND ND ND 64.4 65.8 ND 43 14.3 15.2 13.3 14.6 14.3 ND ND ND ND 57.0 57.3 ND aND =Not detected, where M 0 <(Bo+ MDDo) bND =Not detected, where MA< (BA+ MDDA) d =Damaged TLDs m = MissingTLDs N/A =Missing or Damaged TLD Reading Not Available for Calculation Note: Table formatted in accordance with ANSl/HPS NB.37-2014, Environmental Dosimetry-Criteria for system Design and Implementation.

29

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County; Vrrginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page 1 of2 COLLECTION SAMPLING LOCATIONS DATE. SS HIR BC ALL CP BASF FE NN-C January 05 11.3+/-2.69 11.2+/-2.69 12.8 +/- 2.81 10.7 +/- 2.64 12.8 +/- 2.80 12.5 +/- 2.75 14.7 +/- 2.85 15.5 +/- 2.87 January 12 9.41 +/- 2.56 10.9 +/- 2.64 11.6 +/- 2.71 11.5+/-2.66 10.4 +/- 2.65 9.23 .+/- 2.54 12.9 +/- 2.75 11.1 +/- 2.62 January 19 16.6 +/- 2.81 15.0 +/- 2.72 17.6 +/- 2.93 17.0 +/- 2.83 18.4 +/- 2.95 17.6 +/- 2.85 16.9 +/- 2.79 15.8 +/- 2.72 January 26 13.4 +/- 2.50 14.6 +/- 2.56 13. 7 +/- 2.56 12.4 +/- 2.41 13.4 +/- 2.56 14.0 +/- 2.53 12.9 +/- 2.45 12.0 +/- 2.37 February 02 17.4 +/- 2.96 19.2 +/- 3.06 20.7 +/- 3.17 18.9 +/- 2.99 19.4+/-3.11 . 18.6 +/- 3.01 17.7 +/- 2.95 18.4 +/- 2.99 February 09 11.0+/-2.45 12.5 +/- 2.54 9.48 +/- 2.43 12.2 +/- 2.52 12.9 +/- 2.62 9.45 +/- 2.57 12.3 +/- 2.52 11.5+/-2.46 February 16 14.5 +/- 2.76 12.4 +/- 2.65 14.6 +/- 2.82 13.5 +/- 2.69 12.3 +/- 2.69 14.7 +/- 2.77 12.2 +/- 2.63 13.4 +/- 2.66 February 22 11.1 +/- 2.87 12.3 +/- 2.95 10.5 +/- 2.88 10.5 +/- 2.81 11.9+/-2.98 10.8 +/- 2.85 13.1 +/- 3.00 11.3+/-2.86 March 01 9.08 +/- 2.25 10.9 +/- 2.35 10.5 +/- 2.39 11.2+/-2.38 9.82 +/- 2.34 8.44 +/- 2.20 10.4 +/- 2.35 9.26 +/- 2.24 March 08 12.5 +/- 2.66 15.0 +/- 2.82 13.7 +/- 2.79 13.1 +/- 2.70 14.8 +/- 2.85 15.7 +/- 2.86 14.0 +/- 2.76 13.7 +/- 2.73 March 15 13.8 +/- 2.78 13.1 +/- 2.76 13.0 +/- 2.79 15.1 +/- 2.86 17.1 +/-3.02 16.2 +/- 2.92 14.6 +/- 2.82 11.7+/-2.65 March 22 11.1 +/- 2.49 10.3 +/- 2.43 10.1 +/- 2.46 11.5+/-2.50 12.5 +/- 2.59 11.3 +/- 2.49 13.2 +/- 2.61 10.6 +/- 2.43 March 29 7.96 +/- 2.53 9.69 +/- 2.65 9.24 +/- 2.64 8.35 +/- 2.54 11.4 +/- 2.80 11.3 +/- 2.71 7.58 +/- 2.49 9.14 +/- 2.58 Qtr. Avg. +/-2 s.d. 12.2 +/- 5.7 12.9 +/- 5.2 12.9 +/- 6.7 12.8 +/- 5.7 13.6 +/- 6.0 13.1 +/- 6.6 13.3 +/- 5.2 12.6 +/- 5.4 April 05 9.76 +/- 2.54 9.03 +/- 2.52 12.2 +/- 2.73 11.1 +/-2.62 12.7 +/- 2.77 11.5 +/- 2.64 9.90 +/- 2.54 10.6 +/- 2.58 April 12 11.2 +/- 2.64 12.5 +/- 2.72 12.1 +/- 5.12 13.1 +/- 2.73 13.3 +/- 2.79 13.0 +/- 2.71 13.2 +/- 2. 71 11.6 +/- 2.61 April 19 12.6 +/- 2.61 12.7 +/- 2.63 14.5 +/- 2.77 10.5 +/- 2.49 13.7 +/- 2.74 13.1 +/- 2.68 13.4 +/- 2. 70 11.0+/-2.53 April 25 12.2 +/- 3.00 14.7 +/- 3.16 16.3 +/- 3.29 13.4 +/- 3.07 13.0 +/- 3.09 14.4 +/- 3.12 13.0 +/- 3.04 9.31 +/- 2.81 May 03 11.1 +/-2.35 10.5 +/- 2.32 13.9 +/- 2.55 11.8+/-2.39 12.3 +/- 2.46 13.0 +/- 2.46 10.8 +/- 2.33 13.8 +/- 2.48 May 10 6.16 +/- 2.26 5.49 +/- 2.21 7.54 +/- 2.39 5.17 +/- 2.19 6.93 +/- 2.35 6.25 +/- 2.27 4.74 +/- 2.17 5.33 +/- 2.17 May 17 6.83 +/- 2.22 6.57 +/- 2.19 5.11 +/- 2.12 7.31 +/- 2.24 8.18 +/- 2.33 7.53 +/- 2.25 6.70 +/- 2.19 5.96+/-2.11 May 24 9.10 +/- 2.54 9.63 +/- 2.57 10.6 +/- 2.69 11.1 +/- 2.66 12.6 +/- 2.80 10.7 +/- 2.65 12.2 +/-r 2.72 9.46 +/- 2.54 May 31 14.4 +/- 2.90 14.2 +/- 2.89 16.4 +/- 3.06 :15.1 +/- 2.92 17.5 +/- 3.13 13.5 +/- 2.83 15.5 +/- 2.96 14.0 +/- 2.85 June 07 7.77 +/- 2.34 6.30 +/- 2.23 8.88 +/- 2.43 8.42 +/- 2.35 8.83 +/- 2.43 7.67 +/- 2.29 6.64 +/- 2.21 7.97 +/- 2.29 June 13 15.4 +/- 3.04 12.8 +/- 2.88 19.3 +/- 3.33 18.2 +/- 3.20 17.5 +/- 3.21 16.1 +/- 3.10 16.6 +/- 3.13 13.7 +/- 2.94 June 20 7.66 +/- 2.21 8.67 +/- 2.27 11.7 +/- 2.51 8.51 +/- 2.25 9.65 +/- 2.38 9.37 +/- 2.31 9.76 +/- 2.34 9.86 +/- 2.32 June 28 13.7 +/- 2.59 12.5 +/- 2.52 19.0 +/- 2.91 13.8 +/- 2.58 11.9 +/- 2.53 12.8 +/- 2.53 14.3 +/- 2.61 10.5 +/- 2.39 Qtr. Avg. +/-2 s.d. 10.6 +/- 6.0 10.4 +/- 6.2 12.9 +/- 8.5 11.3 +/- 7.0 12.2 +/- 6.4 11.5 +/- 5.9 11.3 +/- 7.2 10.2 +/- 5.5 30

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Vrrginia - 2016 l.OE-3 pCi/m3 +/- 2 Sigma Page2 of2 COLLECTION SAMPLING LOCATION$

DATE SS HIR BC ALL CP BASF FE NN July 05 10.7 +/- 2.45 11.3 +/- 2.48 17.0 +/- 2.85 12.3 +/- 2.51 13.5 +/- 2.62 12.9 +/- 2.55 10.5 +/- 2.39 14.9 +/- 2.64 July 12 9.23 +/- 2.32 10.3 +/- 2.40 15.6 +/- 2.77 11.1 +/- 2.44 12.8 +/- 2.60 12.3 +/- 2.54 10.3 +/- 2.40 10.8 :!; 2.43 July 19 13.7 +/- 2.84 12.5 +/- 2.79 21.4 +/- 3.31 11.2 +/- 2.70 15.7 +/- 3.09 13.4 +/- 2.93 14.3 +/- 2.87 13.7 +/- 2.83 July 26 20.5 '+/- 3.14 20.9 +/- 3.16 32.4 +/- 3.76 24.2 +/- 3.33 23.2 +/- 3.34 24.4 +/- 3.32 18.9 +/- 3.03 22.3 +/- 3.19 August 02 12.7 +/- 2.46 17.3 +/- 2.74 12.8 +/- 2.51 12.2 +/- 2.43 14.6 +/- 2.64 15.2 +/- 2.63 13.8 +/- 2.52 14.5 +/- 2.56 August 09 13.8 +/- 2.65 12.1 +/- 2.56 20.5 +/- 3.08 13.7 +/- 2.66 16.3 +/- 2.89 13.4 +/- 2.66 12.5 +/- 2.6 11.9 +/- 2.54 August 15 7.20 +/- 2.81 5.75 +/- 2.71 9.51 +/- 3.02 6.53 +/- 2.75 7.62 +/- 2.92 8.03 +/- 2.87 6.86 +/- 2.86 5.77 +/- 2.68 August 22 11.9+/-2.62 9.49 +/- 2.46 12.6 +/- 2.67 9.96 +/- 2.45 12.3 +/- 2.65 11.2+/-2.54 11.6+/-2.56 10.5 +/- 2.47 August 29 9.39 +/- 2.34 12.5 +/- 2.54 17.9 +/- 2.89 11.8 +/- 2.49 13.3 +/- 2.63 13.9 +/- 2.62 13.1 +/- 2.57 12.4 +/- 2.51 September 06 15.5 +/- 2.48 15.3 +/- 2.47 19.4 +/- 2.73 17.4 +/- 2.57 17.0 +/- 2.60 17.7 +/- 2.67 . 16.3 +/- 2.51 15.0 +/- 2.42 September 13 18.8 +/- 2.89 19.6 +/- 2.93 30.4 +/- 3.50 22.6 +/- 3.08 25.7 +/- 3.29 21.0 +/- 3.02 24.7 +/- 3.21 16.9 +/- 2.80 September 20 9.06 +/- 2.45 10.2 +/- 2.53 11.6 +/- 2.65 12.2 +/- 2.63 10.6 +/- 2.58 11.6+/-2.60 8.50 +/- 2.41 10.0 +/- 2.48 September 27 11.0 +/- 2.46 10.6 +/- 2.44 11.7 +/- 2.53 10.5 +/- 2.40 9.55 +/- 2.40 11.7 +/- 2.51 9.84 +/- 2.42 8.27 +/-. 2.27 Qtr. Avg. +/- 2 s.d. 12.6 +/- 7.8 12.9 +/- 8.6 17.9 +/- 14.1 13.5 +/- 10.0 14.8 +/- 10.1 14.4 +/- 8.8 13.2 +/- 9.5 12.8 +/- 8.3 October 04 10.5 +/- 2.39 11.0 +/- 2.42 15.1 +/- 2.72 11.1 +/- 2.41 11.5+/-2.49 12.8 +/- 2.51 7.89 +/- 2.20 9.71 +/- 2.29 October 11 10.8 +/- 2.44 11.5 +/- 2.48 12.2 +/- 2.63 8.52 +/- 2.36 12.0 +/- 2.85 7.05 +/- 2.28 6.25 +/- 2.24 5.71*+/- 2.18 October 18 14.0 +/- 2.82 14.3 +/- 2.83 20.8 +/- 3.18 6.21 +/- 2.26 16.7 +/- 2.96 14.8 +/- 2.80 12.9 +/- 2.71 12.0 +/- 2.63 October 25 10.7 +/- 2.39 17.6 +/- 2.80 20.3 +/- 3.07 15.1 +/- 2.73 15.1 +/- 2.78 17.0 +/- 2.85 14.3 +/- 2.68 11.8 +/- 2.51 Nm.ember 01 16.4 +/- 2.95 20.0 +/- 3.16I 24.5 +/- 3.36 19.2 +/- 3.01 17.8 +/- 3.01 18.4 +/- 2.98 19.0 +/- 3.02 13.0 +/- 2.67 Nm.ember 8 0.30 +/- 1.75 19.6 +/- 2.99 25.4 +/- 3.40 19.0 +/- 3.02 22.0 +/- 3.24 18.5 +/- 3.01 18.4 +/- 3.02 17.1 +/- 2.91 Nm.ember 15 17.4 +/- 3.01 12.7 +/- 2.74 20.0 +/- 3.13 16.4 +/- 2.88 15.7 +/- 2.89 13.1 +/- 2.67 15.7 +/- 2.84 12.3 +/- 2.61 November 22 34.1 +/- 3.76 23.0 +/- 3.27 33.1 +/- 3.79 24.5 +/- 3.35 20.0 +/- 3.18 25.5 +/- 3.40 22.4 +/- 3.26 19.6 +/- 3.10 November 29 25.9 +/- 3.43 16.1 +/-2.95 22.6* +/- 3.35 21.8 +/- 3.26 21.2 +/- 3.25 18.0 +/- 3.04 18.2 +/- 3.07 13.3 +/- 2.76 December 05 21.0 +/- 3.25 16.2 +/- 2.97 23.8 +/- 3.45 19.0 +/- 3.13 15.7 +/- 2.98 18.4 +/- 3.08 17.7 +/- 3:06 15.1 +/- 2.85

December 12 13.4 +/- 2.71 8.45 +/- 2.3.9 11.8+/-2.64 11.3+/-2.58 9.88 +/- 2.51 10.3 +/- 2.52 10.1 +/- 2.51 7.45 +/- 2.32 December 19 20.5 +/- 3.02 12.7 +/- 2.58 21.7 +/- 3.11 16.3 +/- 2.78 14.6 +/- 2.72 18.1 +/- 2.88 15.2 +/- 2.74 16.3 +/- 2.76 December 26 24.4 +/- 3.23 19.2 +/- 2.96 22.1 +/- 3.16 15.8 +/- 2.77 19.7 +/- 3.04 19.3 +/- 2.96 17.7 +/- 2.90 17.4 +/- 2.88 Qtr. Avg. +/- 2 s.d. 18.3 +/- 14.5 15.6 +/- 8.5 21.0 +/- 11.4 15.7 +/- 10.5 16.3 +/- 7.6 16.3 +/- 9.3 15.1 +/- 9.4 13.1 +/- 8.0 Ann. Avg. +/- 2 s.d. 14.2 +/- 12.8 13.5 +/- 9.0 18.5 +/- 13.6 14.2 +/- 10.4 15.0 +/- 9.1 14.6 +/- 9.3 13.6 +/- 9.6 12.5+/-8.1 November 8: SS had <Minimum Detectable Activity 31

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Suny Power Station, Suny County, Vrrginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page 1 of2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C January 05 10.1 +/- 26.2 10.1 +/- 26.4 10.2 +/- 26.6 9.97 +/- 26.0 -10.9 +/- 26.2 -10.7 +/- 25.7 -10.6 +/- 25.4 -10.4 +/- 25.0 January 12 -5.48 +/- 17.5 -5.45 +/- 17.5 -5.52+/-17.7 -5.38 +/- 17.2 -2.32 +/- 23.3 -2.27 +/- 22.8 -2.25 +/- 22.7 -2.2 +/- 22.3 January 19 9.40 +/- 14.1 9.42 +/- 14.1 9.74 +/- 14.6 9.35 +/- 14.0 11.3+/-21.4 11.0+/-20.7 10.9 +/- 20.5 10.7 +/- 20.3 January 26 -1.64 +/- 5.82 -4.22 +/- 14.9 -4.33 +/- 15.3 -4.17 +/- 14.8 -4.36 +/- 15.5 10.9 +/- 20.6 10.7 +/- 20.3 10.5 +/- 19.9 February 02 20.4 +/- 21.1 20.4 +/- 21.1 20.8 +/- 21.5 19.9 +/- 20.6 -10.7 +/- 19.2 -10.4 +/- 18.7 -10.3 +/- 18.5 -10.3 +/- 18.4 February 09 1.22 +/- 34.4 1.22 +/- 34.3 1.27 +/- 3.58 1.21 +/- 34.2 2.98 +/- 35.9 3.24 +/- 39.0 2.87 +/- 34.5 2.84 +/- 34.1 February 16 11.6+/-20.6 11.6+/-20.7 11.9+/-21.1 11.5+/-20.5 -2.60 +/- 18.1 -2.51 +/- 17.5 -2.51 +/- 17.5 -2.45 +/- 17.0 February 22 1.56 +/- 23.4 1.56 +/- 23.4 1.59 +/- 23.9 1.54 +/- 23.1 -1.10+/-27.9 -1.06 +/- 27.0 -1.06 +/- 27.0 -1.05 +/- 26.6 March 01 -6.25 +/- 18.2 -6.25 +/- 18.2 -6.45 +/- 18.8 -6.25 +/- 18.2 16.7 +/- 19.4 16.1 +/- 18.7 16.3 +/- 19.0 15.9 +/- 18.5 March 08 -4.06 +/- 6.14 -10.6 +/- 15.9 -10.8 +/- 16.3 -10.5 +/- 15.8 -3.17 +/- 16.8 -3.09 +/- 16.4 -3.09 +/- 16.4 -3.06 +/- 16.2 March 15 6.04 +/- 15.2 6.10 +/- 15.3 6.20 +/- 15.6 6.03+/-15.1 0.97 +/- 13.5 0.94+/-13.1 0.94+/-13.1 0.94 +/- 13.0 March 22 -6.00 +/- 10.7 -5.97 +/- 10.7 -6.09 +/- 10.9 -5.94 +/- 10.6 -7.35 +/- 10.8 -7.22 +/- 10.6 -7.25 +/- 10.7 -7.13 +/- 10.5 March 29 -22.0 +/- 24.2 -22.1 +/- 24.3 -22.3 +/- 24.5 -21.8 +/- 24.0 6.65 +/- 32.0 6.41 +/- 30.8 6.40 +/- 30.8 6.35 +/- 30.5 April 05 -9.00 +/- 32.4 -9.11 +/- 32.8 -9.17 +/- 33.0 -8.96 +/- 32.3 -5.28 +/- 29.7 -5.11 +/- 28.8 -5.11 +/- 28.8 -5.08 +/- 28.6 April 12 -12.6 +/- 19.4 -12.6 +/- 19.5 -28.3 +/- 43.7 -12.4 +/- 19.1 5.72 +/- 12.9 5.51 +/- 12.4 5.46 +/- 12.3 5.42 +/- 12.2 April 19 -0.36 +/- 27.3 -0.36 +/- 27.6 -0.37 +/- 28 -0.36 +/- 27.4 -13.4 +/- 25.0 -13.1 +/- 24.6 -13.2 +/- 24.6 -12.9 +/- 24.2 April 25 2.24 +/- 10.7 2.25 +/- 10.7 2.29 +/- 10.9 2.23 +/- 10.7 -1.22 +/- 16.3 -1.19 +/- 15.9 -1.19+/-15.9 -1.18 +/- 15.8 May 03 -2.63 +/- 13.6 -2.37 +/- 13.7 -2.41 +/- 13.9 -2.35 +/- 13.6 6.30 +/- 16.2 6.12 +/- 15.8 6.11 +/- 15.7 6.00 +/- 15.5 May 10 -6.16 +/- 11.3 -6.16 +/- 11.3 -6.30 +/- 11.6 -6.12+/-11.2 16.3 +/- 13.6 16.0 +/- 13.3 15.9 +/- 13.3 15.6 +/- 13.0 May 17 2.21 +/- 19.4 2.20 +/- 19.3 2.23 +/- 19.6 2.18 +/- 19.2 -4.09 +/- 19.9 -3.99 +/- 19.4 -3.99 +/- 19.4 -3.88 +/- 18.9 May 24 17.4 +/- 37. 7 17.3 +/- 37.6 17.9 +/- 38.8 15.8 +/- 37.7 16.1 +/- 38.6 15.8+/-37.7 6.65 +/- 14.4 6.48 +/- 15.5 May 31 -19.4 +/- 45.4 -19.4 +/- 45.4 -19.9 +/- 46.5 -19.3 +/- 45.0 -2.89 +/- 38.0 -2. 78 +/- 36.6 -2.81 +/- 36.9 -1.16 +/- 15.2 June 07 -7.91 +/- 21.9 -7.86+/-21.7 -7.94 +/- 22.0 -7.73+/-21.4 4.37 +/- 30.9 4.21 +/- 29.7 4.19 +/- 29.6 4.14 +/- 29.2

June 13 -5.06 +/- 29.6 -5.06 +/- 29.6 -7.04 +/- 43.7 -5.03 +/- 29.4 -5.13 +/- 30.0 -6.86 +/- 42.6 -6.86 +/- 42.6 -6.75 +/- 41.9 June 20 3.36 +/- 20.9 3.36 +/- 20.9 3.43 +/- 21.3 3.32 +/- 20.7 -22.3 +/- 41.7 -21.6 +/- 40.4 -21.5 +/- 40.4 -8.24 +/- 15.4 June 28 9.20 +/- 25.0 9.19 +/- 25.0 9.44 +/- 25.7 9.08 +/- 24.7 1.51 +/- 17.8 1.47+/-17.2 1.46 +/- 17.2 1.45 +/- 17.0 32

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Suny Power Station, Suny County, Vrrginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page2 of2 COLLECTION SAMPLING LOCATIONS DATE , SS HIR BC ALL CP BASF FE NN-C July 05 -25,3 +/- 40.5 -25.2 +/- 40.4 -25.7 +/- 41.2 -24.6 +/- 39.5 -27.0 +/- 34.4 -26.5 +/- 33.7 -26.2 +/- 33.4 -25.9 +/- 33.0 July 12 -11.4 +/- 18.4 -11.5 +/- 18.5 -11.8 +/- 18.9 -11.4 +/- 18.3 -14.0 +/- 22.5 13.7 +/- 22.0 13.6 +/- 21.8 13.5 +/- 21.7 July 19 3.44 +/- 19.3 3.47 +/- 19.5 3.53 +/- 19.8 3.45 +/- 19.4 -29.7 +/- 25.8 -29.2 +/- 25.5 -27.7 +/- 24.1 -27.5 +/- 23.9 July 26 -7,17 +/- 24.9 2.02 +/- 17.0 -7.32 +/- 25.4 -7.14 +/- 24.8 2.06 +/- 17.3 -7.05 +/- 24.5 1.97 +/- 16.6 1.95 +/- 16.4 August 02 -27.8 +/- 29.0 -27.9 +/- 29.1 -28.5 +/- 29.7 -27.9 +/- 29.0 -19.7 +/- 24.3 -19.1 +/- 23.6 -18.9 +/- 23.3 -7.29 +/- 8.99 August 09 8.06 +/- 21.2 8.09 +/- 21.3 8.29 +/- 21.8 8.10 +/- 21.3 0.73 +/- 25.2 0.70 +/- 24.4 0.70 +/- 24.4 0.69 +/- 24.0 August15 -11.3 +/- 41.2 -11.2+/-41.1 -11.5 +/- 42.2 -11.2 +/- 40.8 5.72 +/- 36.7 5.54 +/- 35.6 56.9 +/- 36.6 5.43 +/- 34.9 August 22 -6.27 +/- 16.0 -6.27 +/- 16.0 -6.31 +/- 16.1 -6.11+/-15.5 2.57 +/- 13.0 2.50 +/- 12.7 2.49 +/- 12.6 2.45 +/- 12.4 August 29 0.73 +/- 11.2 0.73 +/- 11.2 0.74 +/- 11.4 0.72 +/- 11.1 4.48 +/- 9.46 4.38 +/- 9.24 4.36 +/- 9.19 4.30 +/- 9.08 September 06* 13.9 +/- 26.1 13.9 +/- 26.1 14.2 +/- 26.6 13.7 +/- 25.7 -4.66 +/- 21.7 -4.73 +/- 22.0 -4.47 +/- 20.8 -4.41 +/- 20.5 September 13 -4.52 +/- 19.4 -4.52 +/- 19.4 -4.64 +/- 19.9 -4.51 +/- 19.4 2.77 +/- 15.9 2.71 +/- 15.5 2.72 +/- 15.5 2.67 +/- 15.3 September 20 -19.3 +/- 18.3 -19.3 +/- 18.3 -19.7 +/- 18.7 -19.1+/-18.1 7.36 +/- 21.0 7.19 +/- 20.5 7.18 +/- 20.5 2.74 +/- 7.82 September 27 -2.01 +/- 15.4 -2.01 +/- 15.4 -2.04 +/- 15.7 -1.97 +/- 15.1 -6.66 +/- 15.0 -6.53 +/- 14. 7 -6.62 +/- 14.9 -6.41 +/- 14.5 October 04 -3.77 +/- 23.5 -3.77 +/- 23.5 -3.87 +/- 24.1 -3.72 +/- 23.2 -2.23 +/- 20.1 -2.14 +/- 19.3 -2.16 +/- 19.5 -0.82 +/- 7.38 October 11 -0.44 +/- 13.4 -0.45 +/- 13.4 -0.48 +/- 14.4 -0.46 +/- 14.0 9.37 +/- 20.1 8.21 +/- 17.6 8.27 +/- 17.7 8.14 +/- 17.4 October 18 2.93 +/- 14.6 2.91 +/- 14.5 2.95 +/- 14.6 2.81 +/- 14.0 -1.26 +/- 14.9 -1.21 +/- 14.4 -1.23 +/- 14.5 -1.20 +/- 14.2 October 25 1.27 +/- 9.94 1.28 +/- 10.0 1.37 +/- 10.7 1.34 +/- 10.4 -1.86 +/- 11.6 -1.82 +/- 11.3 *-1.81 +/- 11.3 -1.77+/-11.0 No\iember 01 19.8 +/- 35.7 19.9 +/- 35.9 19.8 +/- 35.7 19.1 +/- 34.5 -13.0 +/- 34.1 -12.6 +/- 33.1 -12.6 +/- 33.2 -12.5 +/- 32. 7 No\iember 8 -2.14 +/- 21.1 -2.16 +/- 21.3 -2.32 +/- 22.9 -2.25 +/- 22.1 -8.43 +/- 20.0 -8.19 +/- 19.4 -8.23 +/- 19.5 -8.03 +/- 19.1 .

No\iember 15 0.46 +/- 17.2 0.46 +/- 17.2 0.46 +/- 17.2 0.45 +/- 16.7 -12.6 +/- 18.9 -12.1 +/- 18.2 -12.3 +/--18.4 -4.64 +/- 6.97 No\iember 22 -14.4 +/- 25.7 -14.4 +/- .25.6 -14.8 +/- 26.5 -14.4 +/- 25.7 11.0+/-24.2 10.7 +/- 23.6 10.7 +/- 23.7 10.6 +/- 23.4 No\iember 29 5.15 +/- 23.5 5.16 +/- 23.5 5.30 +/- 24.2 5.20 +/- 23.7 9.19 +/- 18.4 9.01 +/- 18.0 9.08 +/- 18.2 8.85 +/- 17.7 December 05 5.58 +/- 22.3 5.58 +/- 22.3 5.71 +/- 22.8 5.55 +/- 22.2 -2.91 +/- 19.6 -2.82 +/- 19.0 -2.84 +/- 19.2 -2.75 +/- 18.6 December 12 -0.42 +/- 9.60 -0.41 +/- 9.51 -0.42 +/- 9.72 -0.42 +/- 9.55 -0.89 +/- 7.72 -0.88 +/- 7.62 -0.88 +/- 7.64 -0.86 +/- 7.51 December 19 1.99+/-10.6 1.97 +/- 10.5 2.01 +/- 10.7 1.97+/-10.5 5.50 +/- 13.3 5.40 +/- 13.1 5.44 +/- 13.2 5.28 +/- 12.8 December 26 -9.99 +/- 13.0 -9.93 +/- 12.9 -10.2 +/- 13.2 -9.86 +/- 12.8 8.05 +/- 14.4 7.79 +/- 13.9 7.85 +/- 14.0 7.81 +/- 13.9 33

TABLE 3-5: GAMMA EMITTER CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page 1of1 SAMPLING FIRST SECOND THIRD FOURTH AVERAGE LOCATIONS NUCLIDE QUARTER QUARTER .QUARTER QUARTER +/- 2 SIGMA SS Cs-134 0.69 +/- 0.72 -0.22 +/- 0.90 0.50. +/- 0.79 0.76 +/- 0.61 Cs-137 0.00 +/- 0.68 -0.79 +/- 0.88 0.46 +/- 0.77 0.28 +/- 0.50 Be-7 124 +/- 22.2 192 +/- 34.2 136 +/- 31.4 133 +/- 23.2 146 +/- 61.8 HIR Cs-134 0.26 +/- 0.65 0.93 +/- 1.03 0.63 +/- 0.87 0.23 +/- 0.64 Cs-137 -0.37 +/- 0.50 0. 79 +/- 0.96 -0.62 +/- 0.62 -0.11 +/- 0.81 Be-7 126 +/- 21.5 134 +/- 35.2 144 +/- 28.4 125 +/- 27.1 132 +/- 17.6 K-40 14.9 +/- 12.8 14.9 +/- 12.8 BC Cs-134 -0.03 +/- 0.77 0.66 +/- 0.86 1.22 +/- 1.33 0.64 +/- 0.82 Cs-137 -0.34 +/- 0.69 -0.16 +/- 0.93 -0.19 +/- 1.24 0.57 +/- 0.65 Be-7 122 +/- 33.5 156 +/- 36.2 132 +/- 36.5 162 +/- 27.0 143 +/- 38.2 ALL Cs-134 0.33 +/- 0.87 0.37 +/- 0. 76 0.00 +/- 0. 72 -0.12 +/- 1.21 Cs-137 -0.16 +/- 0.80 0.00 +/- 0.71 0.13 +/- 0.66 -0.21 +/- 1.10 Be-7 115 +/- 30.3 169 +/- 26.9 218 +/- 33.4 139 +/- 32.7 160 +/- 88.8 CP Cs-134 0.86 +/- 0.80 -0.05 +/- 0.63 0.04 +/- 0.98 0.01 +/- 0.78 Cs-137 -0.51 +/- 0.68 -0.60 +/- 0.61 -0.21 +/- 0.83 -0.03 +/- 0.67 Be-7 112 +/- 24.8 140 +/- 23.3 146 +/- 28.6 142 +/- 26.7 135 +/- 31.1

K-40 16.3 +/- 12.7 16.3 +/- 12.7 BASF Cs-134 0.11 +/- 1.13 0.81 +/- 1.19 1.74 +/- 1.41 0.53 +/- 0.87 Cs-137 -0.30 +/- 1.15 0.99 +/- 1.08 0.08 +/- 1.12 -0.32 +/- 0.77 Be-7 154 +/- 39.1 170 +/- 36.5 142 +/- 37.6 115 +/- 32.7 145 +/- 46.4 FE Cs-134 0.66 +/- 0.92 -0.51 +/- 0. 75 2.01 +/- 0.89 0.45 +/- 1.05 Cs-137 0.88 +/- 0. 79 -0.22 +/- 0.80 0.22 +/- 0. 75 0.43 +/- 0.92 Be-7 146 +/- 30.4 149 +/- 27.6 108 +/- 25.7 86.7 +/- 32.6 122 +/- 60.5 NN-C Cs-134 -0.33 +/- 0.75 1.68 +/- 0.82 -0.35 +/- 0.87 -0.32 +/- 0.74 Cs-137 0.31 +/- 0.80 0.18 +/- 0.69 0.39 +/- 0.67 0.04 +/- 0.61 Be-7 115 +/- 24.8 163 +/- 28.3 150 +/- 30.3 99.0 +/- 20.9 132 +/- 59.6 34

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Suny Power Station, Suny County, Vrrginia - 2016 pCi/Liter +/- 2 Sigma Pagelof3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C JANUARY Cs-134 -9.41 +/- 5.60 -5.36 +/- 6.09 -0.93 +/- 4.68 Cs-137 5.08 +/- 6.12 -1.62 +/- 4.57 5.42 +/- 4.78 Ba-140 16.2 +/- 25.1 13.7 +/- 27.1 -6.81 +/- 20.8 La-140 -1.27 +/- 7.46 2.07 +/- 6.45 -0.67 +/- 6.64 1-131 -0.16 +/- 0.12 -0.13 +/- 0.16 -0.16 +/- 0.12 K-40 1180 +/- 200 1080 +/- 211 1420 +/- 194 FEBRUARY Cs-134 2.03 +/- 4.06 -0.41 +/- 6.18 -1.67 +/- 4.34 Cs-137 -2.10 +/- 5.17 0.71 +/- 6.02 0.53 +/- 4.49 Ba-140 -1.72 +/- 22.8 1.49 +/- 24.5 2.01 +/- 17.9 La-140 -3.08 +/- 5.60 3.97 +/- 8.24 0.16 +/- 5.48 1-131 -0.15 +/- 0.25 0.21 +/- 0.45 -0.12 +/- 0.24 K-40 1400 +/- 202 1200 +/- 199 1420 +/- 191 MARCH Cs-134 -5.63 +/- 4.38 3.35 +/- 4.56 -0.56 +/- 4.28 Cs-137 -3.04 +/- 4.99 3.25 +/- 4.83 1.81 +/- 4.74 Ba-140 -1.38 +/- 19.3 -2.92 +/- 18.3 -3.97 +/- 18.7 La-140 3.24 +/- 5.21 -1.46 +/- 5.64 0.71 +/- 4.73 1-131 -0.19 +/- 0.36 0.08 +/- 0.46 -0.11 +/- 0.28 K-40 1220 +/- 163 1460 +/- 203 1270 +/- 159 Sr-89 3.02 +/- 2.84 Sr-90 0.28 +/- 0.20 APRIL Cs-134 -5.42 +/- 5.42 -2.11 +/- 5.44 Cs-137 4.56 +/- 7.33 -0.41 +/- 6.01 Ba-140 6.38 +/- 23.3 4.67 +/- 24.3 La-140 4.09 +/- 7.58 1.66 +/- 6.61 1-131 0.12 +/- 0.30 0.03 +/- 0.14 K-40 1180 +/- 222 1450 +/- 204 35

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Suny Power Station, Suny County, Vrrginia - 2016 pCi/liter +/- 2 Sigma Page 2 of3 COLONIAL LOVER NUCLIDE EPPS PARKWAY RETREAT-C MAY Cs-134 -5.17 +/- 6.25 0.30 +/- 5.89 -7.60 +/- 5.53 Cs-137 -1.87 +/- 5.36 1.04 +/- 6.25 1.96 +/- 5.00 Ba-140 4.19 +/- 23.5 15.7 +/- 21.4 -19.7 +/- 29.9 La-140 -1;51 +/- 5.20 ' 6.80 +/- 6.96 4.98 +/- 7.06 1-131 -0.14 +/- 0.33 -0.26 +/- 0.34 -0.27 +/- 0.43 K-40 1490 +/- 248 1520 +/- 201 1680 +/- 185 JUNE Cs-134 0.11 +/- 3.97 -2.50 +/- 3.99 -5.42 +/- 3.50 Cs-137 1.10 +/- 4.07 -2.21 +/- 3.39 -0.74 +/- 3.41 Ba-140 9.93 +/- 22.8 6.39 +/- 20.9 4.20 +/- 17.0 La-140 -5.56 +/- 6.15 -5.93 +/- 5.16 3.95 +/- 4.64 1-131 -0.08 +/- 0.35 0.52 +/- 0.46 0.24 +/- 0.34 K-40 1500 +/- 192 1410 +/- 152 1580 +/- 153 Sr-89 4.17 +/- 2.92 Sr-90 1.65 +/- 0.48 JULY Cs-134 -7.61 +/- 5.13 0.54 +/- 5.02 -3.69 +/- 4.10 Cs-137 -4.08 +/- 5.21 0.37 +/- 5.17 0.79 +/- 3.79 Ba-140 6.09 +/- 20.5 13.4 +/- 21.4 3.18 +/- 19.7 La-140 1.76 +/- 5.94 0.81 +/- 6.36 3.99 +/- 5.09 1-131 0.21 +/- 0.22 0.08 +/- 0.25 -0.08 +/- 0.17 K-40 1330 +/- 189 1410 +/- 202 1850 +/- 174 AUGUST Cs-134 -16.3 +/- 6.45 -3.26 +/- 4.28 -9.45 +/- 6.36 Cs-137 -1.55 +/- 6.15 0.57 +/- 4.57 1.81 +/- 6.27 Ba-140 1.06 +/- 26.4 -7.71 +/- 16.8 12.6 +/- 28.4 La-140 2.98 +/- 7.72 1.19 +/- 4.84 -0.88 +/- 6.62 1-131 0.02 +/- 0.42 0.14 +/- 0.57 0.07 +/- 0.45 K-40 1450 +/- 231 1300 +/- 159 1450 +/- 232 36

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Suny Power Station, Suny County, Vrrginia - 2016 pCi/Liter +/- 2 Sigma Page 3 of3 COLONIAL LOVER NUCLIDE EPPS PARKWAY RETREAT-C SEPTEMBER Cs-134 -2.66 +/- 5.42 -3.13 +/- 4.52 1.42 +/- 6.51 Cs-137 -3.58 +/- 5.74 -1.08 +/- 4.72 2.12 +/- 7.09 Ba-140 0.56 +/- 30.2 2.95 +/- 21.9 13.2 +/- 32.6 La-140 -8.14 +/- 9.17 -6.71 +/- 8.05 -3.84 +/- 9.88 1-131 -0.08 +/- 0.22 0.02 +/- 0.36 -0.22 +/- 0.29 K-40 1280 +/- 212 1530 +/- 170 1760 +/- 218 Sr-89 3.43 +/- 2.34 Sr-90 1.79 +/- 0.50 OCTOBER Cs-134 0.43 +/- 8.67 13.9 +/- 7.67 A 18.1 +/- 8.71 A Cs-137 1.86 +/- 5.86 5.69 +/- 5.68 4.68 +/- 7.42 Ba-140 18.9 +/- 26.9 10.1 +/- 24.5 11.1 +/- 28.2 La-140 5.57 +/- 6.45 2.86 +/- 7.98 0.35 +/- 9.01 1-131 0.06 +/- 0.27 0.24 +/- 0.49 0.48 +/- 0.41 K-40 1470 +/- 178 1360 +/- 136 1650 +/- 205 NOVEMBER Cs-134 -0.23 +/- 4.71 -0.18 +/- 6.37 38.2 +/- 7.75A Cs-137 -5.66 +/- 4.76 1.40 +/- 5.25 -1.08 +/- 5.32 Ba-140 12.4 +/- 22.4 -29.0 +/- 27.0 -1.17 +/- 24.7 La-140 7.86 +/- 7.74 -3.34 +/- 7.51 0.33 +/- 5.76 1-131 0.16 +/- 0.39 0.14 +/- 0.49 0.22 +/- 0.39 K-40 1400 +/- 188 1230 +/- 195 1680 +/- 154 DECEMBER Cs-134 -7.82 +/- 6.58 -8.33 +/- 4.95 -4.48 +/- 5.52 Cs-137 2.65 +/- 7.00 2.46 +/- 4.13 2.69 +/- 5.45 Ba-140 3.44 +/- 27.0 8.38 +/- 18.9 2.38 +/- 20.2 La-140 0.98 +/- 4.89 -1.86 +/- 6.93 -5.54 +/- 6.37 1-131 0.08 +/- 0.40 0.12 +/- 0.38 -0.13 +/- 0.40 K-40 1210 +/- 209 1310 +/- 186 1420 +/- 213 Sr-89 1.61 +/- 2.53 Sr-90 1.33 +/- 0.53 A: Compound/analyte not detected. Peak not identified.

37

TABLE 3-7: GAMMA EMITTER CONCENTRATION IN FOOD PRODUCTS Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (wet)+/- 2 Sigma Page 1of1 SAMPLING COLLECTION SAMPLE LOCATIONS DATE TYPE ISOTOPE Cs-134 Cs-137 1-131 K-40 BROCK 11/10/2016 Com 1.33+/-10.1 0.53 +/- 10.9 -3.27 +/- 13.9 4730 +/- 460 FARM Cs-134 Cs-137 1-131 K-40 11/10/2016 Peanuts 3.66 +/- 13.7 3.63 +/- 15.2 0.34 +/- 17.3 5730 +/- 545 Cs-134 Cs-137 1-131 K-40 SLADE 11/10/2016 Soybeans -8.15 +/- 19.7 6.33 +/- 18.6 -3.54 +/- 23.8 22900 +/- 1210 FARM 38

TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER Surry Power Station, Surry County, Virginia - 2016

pCi/Llter+/-2Sigma Page 1 of2 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60 Zn-65 SS 3/1/2016 -0.08 +/- 2.79 2.96 +/- 3.53 2.26 +/- 7.08 -0.38 +/- 3.54 -5.70 +/- 7.02 6/6/2016 3.16 +/- 2.71 -1.56 +/- 2.78 1.05 +/- 5.78 1.26 +/- 2.82 -5.99 +/- 5.59 9/5/2016 -0.73 +/- 3.06 0.52 +/- 3.16 -2.95 +/- 5.87 1.26 +/- 2.68 -1. 71 +/- 7.52 12/5/2016 0.12 +/- 3.QO 0.91 +/- 3.39 -0.99 +/- 5.01 0.68 +/- 3.50 0.06 +/- 7.28 Nb-95 Zr-95 1-131 Cs-134 Cs-137 3/1/2016 -3.66 +/- 3.21 2.87 +/- 5.44 -0.09 +/- 0.25 -3.10 +/- 3.57 -1.31 +/- 3.15 6/6/2016 1.15 +/- 2.75 -4.99 +/- 4.97 0.10 +/- 0.27 -5.90 +/- 2.79 1.15 +/- 2.97 9/5/2016 5.46 +/- 3.70 -0.29 +/- 5.09 -3.73 +/- 5.64 2.01 +/- 3.33 0.39 +/- .3.19 12/5/2016 1.89 +/- 3.38 7.00 +/- 5.62 0.17 +/- 0.42 2.35 +/- 3.29 0.09 +/- 3.02 Ba-140 La-140 H-3 Ra-226 3/1/2016 -2.18 +/- 14.7. -5.09 +/- 5.11 227 +/- 880 6/6/2016 -2.14 +/- 15.7 -3.30 +/- 5.81 108 +/- 533 *113 +/- 106 9/5/2016 -14.3 +/- 16.4 -2.94 +/- 4.84 228 +/- 570 12/5/2016 13.6 +/- 11.1 -2.07 +/- 3.75 404 +/- 531 Mn-54 Co-58 Fe-59 Co-60 Zn-65 HIR 3/1/2016 -0.72 +/- 2.99 1.50 +/- 2.91 1.93 +/- 5.59 -0.96 +/- 2.43 -9.33 +/- 6.71 6/7/2016 -1.15 +/- 2.66 0.57 +/- 2.71 2.82 +/- 6.46 0.24 +/- 2.51 -7.25 +/- 6.16 9/6/2016 0.92 +/- 2.67 1.18 +/- 2.82 4.58 +/- 5.25 -0.45 +/- 2.76 -0.40 +/- 6.13 12/5/2016 -1.61 +/- 3.69 -0.82 +/- 3.97. 0.00 +/- 8.04 2.02 +/- 4.88 -3.55 +/- 8.48 Nb-95 Zr-95 1-131 Cs-134 Cs-137 3/1/2016 -1.38 +/- 3.04 0.30 +/- 5.59 -0.24 +/- 0.27 0.61 +/-. 3.00 -0.36 +/- 3.31 6/7/2016 -0.04 +/- 2.59 -1.52 +/- 4.84 0.08 +/- 0.20 1.29 +/- 2.92 -0.04 +/- 3.00 9/6/2016 0.63 +/- 2.79 0.93 +/- 4.52 -2.87 +/- 4.96 -1.39 +/- 2.80 -2.57 +/- 2.85 12/5/2016 0.98 +/- 4.29 1.37 +/- 6.82 0.38 +/- 0.43 -6.00 +/- 4.93 0.07 +/- 3.93 Ba-140 La-140 H-3 3/1/2016 7.89 +/- 13.4 -1.53 +/- 3.75 813 +/- 944 6/7/2016 9.52 +/- 15.4 -0.13 +/- 4.28 31.9 +/- 526 9/6/2016 -12.7 +/- 13.0 3.01 +/- 4.30 -205 +/- 543 12/5/2016 -6.38 +/- 15.90 -2.81 +/- 5.29 170 +/- 505 39

TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER Surry Power Station, Surry County, Vrrginia - 2016 pCi/Llter +/- 2 Sigma Page2 of2 SAMPLING COLLECTION L,OCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60 Zn-65

_cs 3/1/2016 2.80 +/- 3.71 -1.72 +/- 3.90 -2.19 +/- 6.21 -0.72 +/- 3.75 -4.16 +/- 7.94 6/6/2016 1.48 +/- 2.89 1.39 +/- 2.76 1.98 +/- 6.64 1.23 +/- 2.84 -4.60 +/- 5.83 9/5/2016 1.47 +/- 2.60 2.23 +/- 2.55 1.48 +/- 5.20 -0.37 +/- 2.45 -2.04 +/- 6.04 12/5/2016 -2.58 +/- 3.72 -1.10 +/- 3.90 3.72 +/- 7.13 0.81 +/- 3.55 -12.9 +/- 9.40 Nb-95 Zr-95 1-131 Cs-134 Cs-137 3/1/2016 -1.25 +/- 3.87 -3.47 +/- 6.14 -0.28 +/- 0.23 0.18 +/- 3.56 3.03 +/- 3.53 6/6/2016 0.36 +/- 2.87 2.41 +/- 4.93 0.34 +/- 0.33 0.83 +/- 2.67 1.01 +/- 2.97 9/5/2016 -1.82 +/- 2.89 -5.06 +/- 4.75 2.60 +/- 5.50 2.45 +/- 2.82 -1.10 +/- 2.72 12/5/2016 -3.42 +/- 3.38 0.60 +/- 5.81 0.22 +/- 0.39 1.90 +/- 3.77 0.65 +/- 3.62 Ba-140 La-140 H-3 K-40 3/1/2016 17.8 +/- 16.3 -1.67 +/- 5.52 395 +/- 946 6/6/2016 -0.71 +/- 15.0 -4.09 +/- 5.13 485 +/- 569 66.8 +/- 54.8 9/5/2016 9.16 +/- 13.8 0.03 +/- 4.77 12.4 +/- 557 12/5/2016 -1.56 +/- 15.4 -2.29 +/- 4.97 -117 +/- 498 40

TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WATER Suny Power Station, Suny County, Vrrginia - 2016 pCi/liter +/- 2 Sigma Page 1 of2 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60 Zn-65 SD 1/12/2016 -2.08 +/- 2.81 0.79 +/- 2.71 0.13 +/- 5.70 0.42 +/- 2.81 0.68 +/- 6.15 2/9/2016 ' -0.53 +/- 3.01 -0.54 +/- 2.89 -0.86 +/- 4.78 -0.71 +/- 2.58 -3.51 ,' +/- 6.56 3/1/2016 0.99 +/- 3.89 2.56 +/- 4.71 11.3 +/- 7.83 -3.28 +/- 4.08 -6.43 +/- 9.00 4/11/2016 -1.25 +/- 2.41 3.00 +/- 2.68 -2.22 +/- 4.46 -1.08 +/- 2.26 -12.0 +/- 5.82 5/10/2016' 3.20 +/- 4.36 2.53 +/- 4.39 1.24 +/- 6.15 1.59 +/- 4.34 -10.1 +/- 10.2 6/6/2016 -0.86 +/- 2.22 -0.01 +/- 2.46 0.75 +/- 5.53 0.39 +/- 2.12 -6.63 +/- 5.52 7/4/20t6 2.80 +/- 2.79 -2.78 +/- 3.20 0.84 +/- 6.05 -0.57 +/- 2.57 -4.74 +/- 6.66 8/2/2016 1.23 +/- 2.69 -2.24 +/- 3.21 -2.46 +/- 6.10 0.44 +/- 3.07 2.62 +/- 5.93 9/5/2016 -0.12 +/- 3.47 -0.51 +/- 3.21 3.15 +/- 6.55 -2.62 +/- 3.54 -3.44 +/- 7.00 10/3/2016 -2.13 +/- 4.66 0.01 +/- 4.83 5.79 +/- 8.75 0.92 +/- 4.30 -1.23 +/- 11.3 11/1/2016 0.29 +/- 2.54 -3.07 +/- 3.25 0.00 +/- 0.06 -1.29 +/- 2.60 -3.30 +/- 7.37 12/5/2016 -0.28 +/- 4.37 -1.94 +/- 4.39 -2.29 +/- 8.86 ' -1.72 +/- 5.34 -14.1 +/- 10.8 Nb-95 Zr-95 1-131 Cs-134 Cs-137 1/12/2016 0.80 +/- 2.65 1.57 +/- 4.69 1.34 +/- 4.56 -1.52 +/- 3.39 -1.30 +/- 3.12 2/9/2016 0. t7 +/- 3.38 0.26 +/- 5.44 0.61 +/- 3.82 -5.85 +/- 3.29 -1.90 +/- 3.05 3i1/2016 -2.14 +/- 3.72 1.29 +/- 6.43 -1.45 +/- 5.93 1.79 +/- 4.52 0.97 +/- 4.35 4/11/2016 0.84 +/- 2.69 0.75 +/- 4.65 -1.19 +/- 5.62 1.52 +/- 2.94 -1.16 +/- 3.05 5/10/2016 1.36 +/- 4.56 5.48 +/- 7.85 0.03 +/- 5.67 0.83 +/- 4.68 1.73 +/- 4.74 6/6/2016 0.15 +/- 2.63 -0.21 +/- 4.62 -0.21 +/- 5.32 0.17 +/- 2.49 1.26 +/- 2.64 7/4/2016 -0.97 +/- 3.51 2.34 +/- 6.08 -2.59 +/- 5.50 1. 79 +/- 2.68 -1.06 +/- 3.18 8/2/2016 0.65 +/- 3.35 -0.91 +/- 5.02 3.07 +/- 5.55 3.33 +/- 3.01 0.40 +/- 3.48 9/5/2016 2.61 +/- 3.65 4.01 +/- 6.08 1.19 +/-. 5.80 -0.12 +/- 3.12 -2.02 +/- 3.32 10/3/2016 4.05 +/- 5.51 -7.64 +/- 7.97 0.34 +/- 6.05 -0.07 +/- 5.01 -3.66 +/- 4.96 11/1/2016 -0.12 +/- 3.00 2.01 +/- 5.36 5.99 +/- 5.22 0.42 +/- 3.10 0.76 +/- 2.83 12/5/2016 2.16 +/- 3.59 6.87 +/- 6.50 -5.70 +/- 5.96 -5.64 +/- 4.54 1.68 +/- 4.15 Ba-140 La-140 H-3 K-40 Ra-226 1/12/2016 -5.33 +/- 13.7 0.88 +/- 3.83 74.2 +/- 55.2 2/9/2016 -6.33 +/- 11.5 1.47 +/- 3.57 59.3 +/- 56.8 3/1/2016 10.00 +/- 18.6 2.97 +/- 5.15 55.1 +/- 806 '

4/11/2016 -3.91 +/- 13.9. 0.74 +/- 3.69 5/10/2016 9.56 +/- 20.2 -0.97 +/- 4.76 6/6/2016 -1.58 +/- 14.4 -1.34 +/- 3.91 -330 +/- 542 7/4/2016 6.41 +/- 15.2 -4.05 +/- 4.87 8/2/2016 -4.8 +/- 1.4.4 0.87 ' +/- 4.40 9/5/2016 2.09 +/- 15.60 0.63 +/- 5.18 -351 +/- 521 109 +/- 79.2 253 +/- 125 10/3/2016 0.40 +/- 20.1 1.32 +/- 7.11 112 +/- 99.6 11/1/2016 -6.87 +/- 14.5 -1.72 +/- 3.91 65.6 +/- 47.3

'12/5/2016 4.58 +/- 17.0 0.80 +/- 6.29 360 +/- 564 41

TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WATER Suny Power Station, Suny County, Vrrginia - 2016 pCi/Llter +/- 2 Sigma Page 2 of2 SAMPLING COLLECTION LOCATIONS DATE ISOTOPES Mn-54 Co-58 Fe-59 Co-60 Zn-65 SW-C 1/12/2016 -1.19 +/- 3.84 0.60 +/- 3.15 -0.64 +/- 5.63 1.44 +/- 4.04 -1.82 +/- 7.60 2/9/2016 1.21 +/- 2.69 -2.88 +/- 3.64 1.23 +/- 6.48 0.47 +/- 3.18 -3.94 +/- 7.84 3/1/2016 2.63 +/- 2.96 -0.09 +/- 2.86 -1.05 +/- 5.38 0.14 +/- 3.18 -7.55 +/- 6.82 4/12/2016 1.63 +/- 2.71 -0.08 +/- 3.01 4.10 +/- 6.18 2.10 +/- 3.80 -0.78 +/- 6.69 5/10/2016 -0.51 +/- 3.36 -1.41 +/- 3.25 -2.14 +/- 7.06 2.46 +/- 3.52 -4.84 +/- 7.46 6/7/2016 0.81 +/- 2.46 -0.54 +/- 2.35 -1.06 +/- 4.70 -0.66 +/- 2.22 -2.18 +/- 6.30 7/5/2016 1.60 +/- 3.02 -1.31 +/- 3.46 2.62 +/- 6.65 -3. 73 +/- 2. 77 -1.90 +/- 8.12 8/2/2016 -2.42 +/- 2.67 -3.48 +/- 3.47 0.87 +/- 6. 71 1.03 +/- 3.87 -9.46 +/- 6.64 9/6/2016 -0.50 +/- 2.72 0.04 +/- 2.70 3.57 +/- 5.95 0.98 +/- 2.66 -1.94 +/- 5.61 10/4/2016 -2.39 +/- 5.65 -0.84 +/- 4.79 -12.8 +/- 8.86 -0.67 +/- 5.22 -0.06 +/- 11.3 11/1/2016 -1.33 +/- 3.07 -2.01 +/- 3.39 1.30 +/- 6.42 0.27 +/- 3.13 -7.51 +/- 6.93 12/5/2016 -3.27 +/- 4.91' -4.53 +/- 4.21 1.38 +/- 7.08 1.45 +/- 4.28 -3.63 +/- 10.0 Nb-95 Zr-95 1-131 Cs-134 Cs-137 1/12/2016 0.98 +/- 4.02 -2.21 +/- 6.28 0.64 +/- 5.89 -2.26 +/- 4.65 -0.72 +/- 3.65 2/9/2016 0.73 +/- 3.36 -3.80 +/- 5.38 0.19 +/- 4.69 -5.85 +/- 3.68 0.02 +/- 3.26 3/1/2016 -1.18 +/- 3.22 1.22 +/- 5.82 0.17 +/- 5.35 -5.87 +/- 3.81 0.99 +/- 3.10 4/12/2016 2.29 +/- 2.73 0.31 +/- 4.38 0.72 +/- 4.74 0.22 +/- 3.05 -1.32 +/- 3.21 5/10/2016 2.23 +/- 3.14 3.66 +/- 5.56 -1. 73 +/- 4.45 -2.88 +/- 3.96 -1.93 +/- 3.75 6/7/2016 1.38 +/- 2.51 2.75 +/- 4.34 5.12 +/- 5.50 -2.33 +/- 2.96 0.41 +/- 2.55 7/5/2016 1.23 +/- 3.58 -1.88 +/- 6.03 1.54 +/- 5.10 -0.32 +/- 3.27 0.18 +/- 3.39 8/2/2016 -0.52 +/- 2.98 0.86 +/- 6.59 -0.93 +/- 6.10 -11.9 +/- 4.12 -2.49 +/- 3.43 9/6/2016 -0.23 +/- 2.71 0.96 +/- 4.64 -1.21 +/- 4.82 -6.74 +/- 3.10 -1.32 +/- 2.76 10/4/2016 -7.32 +/- 6.25 -1.03 +/- 8.13 -6.25 +/- 6.48 -3.49 +/- 5.40 0.66 +/- 5.64 11/1/2016 -0.34 +/- 3.61 1.57 +/- 4.52 -1.65 +/- 5.89 -1.30 +/- 3.45 0.34 +/- 3.54 12/5/2016 -0.03 +/- 4.06 -1.09 +/- 7.09 0.88 +/- 5.81 -5.42 +/- 4.62 1.84 +/- 4.25 Ba-140 La-140 H-3 K-40 Th-228 1/12/2016 5.57 +/- 17.1 0.00 +/- 4.11 2/9/2016 -8.39 +/- 13.5 0.79 +/- 5.24 65.2 +/- 53.6 3/1/2016 -6.10 +/- 14.6 2.27 +/- 4.26 -145 +/- 791 4/12/2016 9.96 +/- 14.6 -3.18 +/- 4.49 9.11 +/- 7.46 5/10/2016 -3.64 +/- 13.1 -5.97 +/- 4.36 6/7/2016 1.77 +/- 13.0 2.19 +/- 4.33 -130 +/- 561 7/5/2016 -7.16 +/- 15.4 -2.85 +/- 5.50 8/2/2016 2.92 +/- 15.9 2.09 +/- 5.08 9/6/2016 5.78 +/- 13.2 0.46 +/- 4.43 -229 +/- 528 70.3 +/- 63.5 10/4/2016 6.29 +/- 19.2 1.09 +/- 6.50 11/1/2016 -12.3 +/- 16.6 -0.48 +/- 5.85 12/5/2016 -11.0 +/- 17.4 3.07 +/- 5.90 882 +/- 897 42

TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT Suny Power Station, Suny County, Virginia - 2016 pCi/kg (dry)+/- 2 Sigma Page I of I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Cs-134 Cs-137 K-40 Th-228 Th-232 SD* 3/7/2016 -32.1 +/- 40.9 -8.05 +/- 44.1 10000 +/- 1560 818 +/- 143 786 +/- 194 9/7/2016 83.3 +/- 73.4 8 143 +/- 89.1 8 21400 +/- 2650 1600 +/- 289 1390 +/- 305 Ra-226 Be-7 3/7/2016 1910 +/- 1310 9/7/2016 2600 +/- 2260 3170 +/- 967 Cs-134 Cs-137 K-40 Th-228 Th-232 CHIC*C 3/7/2016 -30.0 +/- 78.2 233 +/- 123 15900 +/- 2640 1700 +/- 228 1280 +/- 347 9/6/2016 353 +/- 77.3 A 219 +/- 83.7 18500 +/- 1700 1790 +/- 206 1200 +/- 279 Ra-226 3/7/2016 2510 +/- 2420 9/6/2016 2730 +/- 2010 A: Compound/analyte not detected. Peak not identified.

B: <LLD 43

TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (dry)+/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Cs-134 Cs-137 K-40 Ra-226 Th-228 HIR 2/2/2016 -20.8 +/- 37.2 -0.68 +/- 30.0 7960 +/- 1240 8/2/2016 362.0 +/- 62.9 A 41.5 +/- 46.8 3650 +/- 963 3010 +/- 1270 A 1920 +/- 171 Th-232 2/2/2016 8/2/2016 1550 +/- 213 Cs-134 Cs-137 K-40 Ra-226 Th-228 CHIC-C 2/2/2016 9.24 +/- 43.4 -12.6 +/- 46.9 2000 +/- 775 1250 +/- 150.0 8/2/2016 -25.5 +/- 31.9 -4.16 +/- 28.8 1820 +/- 512 1390 +/- 1130 930 +/- 88.2 Th-232 2/2/2016 1240 +/- 311 8/2/2016 790 +/- 177 A: Compound/analyte not detected. Peak not identified.

44

TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (wet)+/- 2 Sigma Page 1of1 SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE K-40 Mn-54 Co-58 Fe-59 SD 4/6/2016 Catfish 3170 +/- 1250 26.8 +/- 53.4 -21.6 +/- 44.5 32.9 +/- 85.2 4/6/2016 Game fish 2000 +/- 978 -64.3 +/- 61.3 10.1 +/- 60.0 13.0 +/- 108 10/5/2016 Catfish 1810 +/- 560 -6.02 +/- 24.7 20.0 +/- 21.9 -4.10 +/- 42.3 10/5/2016 Game fish 2850 +/- 1010 -19.7 +/- 48.3 -38.6 +/- 51.7 22.4 +/- 81.1 Co-60 Zn-65 Cs-134 Cs-137 4/6/2016 Catfish 0.90 +/- 55.2 -17.2 +/- 98.6 -15.9 +/- 53.0 23.0 +/- 35.1 4/6/2016 Game fish 4.10 +/- 51.2 -2.31 +/- 111 -45.2 +/- 55.3 16.7 +/- 57.3 10/5/2016 Catfish -3.45 +/- 19.9 -39.8 +/- 56.6 6.97 +/- 25.8 0.03 +/- 26.1 10/5/2016 Game fish 18.5 +/- 46.6 -140 +/- 107, 5.85 +/- 53.6 -17.7 +/- 41.4 45

TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (wet)+/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60

Pos 3/8/2016 30.2 +/- 38.2 -7.12 +/- 56.0 88.6 +/- 114 16.0 +/- 28.6 9/7/2016 16.4 +/- 31.2 -19.8 +/- 31.6 29.2 +/- 60.5 8.68 +/- 24.0 Zn-65 Cs-134 Cs-137 K-40 3/8/2016 -27.1 +/- 95.8 -32.1 +/- 43.2 0.72 +/- 43.9 597 +/- 588 9/7/2016 -26.0 +/- 71.9 18.7 +/- 44.8 21.4 +/- 31.5 1090 +/- 648 Mn-54 Co-58 Fe-59 Co-60 MP 3/8/2016 20.1 +/- 40.1 2.99 +/- 42.0 48.5 +/- 129 -1.82 +/- 36.6 9/8/2016 4.42 +/- 32.4 -7.83 +/- 30.5 -27.6 +/- 69.5 1.06 +/- 24.3 Zn-65 Cs-134 Cs-137 K-40 3/8/2016 -37.8 +/- 83.4 -10.6 +/- 45.0 -26.9 +/- 41.9 9/8/2016 -99.4 +/- 70.5 33.3 +/- 35.5 2.16 +/- 31.0 680 +/- 581 Mn-54 Co-58 Fe-59 Co-60 LC 3/8/2016 -10~9 +/- 30.2 -1.64 +/- 43.9 21.5 +/- 90.7 -3.78 +/- 20.3 9/8/2016 18.1 +/- 29.3 -9.52 +/- 32.3 -57.9 +/- 61.1 6.22 +/- 24.7 Zn-65 Cs-134 Cs-137 K-40 3/8/2016 -66.0 +/- 77.8 3.16 +/- 33.4 9.61 +/- 27.5 581 +/- 447 9/8/2016 4.92 +/- 71.6 52.7 +/- 42.68 -2.57 +/- 31.1 900 +/- 545 B: <LLD 46

TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (wet) +/- 2 Sigma Page 1of1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60 JI 3/8/2016 9.22 +/- 44.2 -33.5 +/- 53.0 -61.1 +/- 155 -10.6 +/- 54.0 9/7/2016 13.2 +/- 30.9 4.13 +/- 30.6 17.7 +/- 69.2 24.4 +/- 28.9 Zn-65 Cs-134 Cs-137 K-40 3/8/2016 -129 +/- 127 -47.1 +/- 53.3 -7.53 +/- 40.8 9/7/2016 -9.94 +/- 80.0 -16.1 +/- 41.3 -4.27 +/- 30.4 712 +/- 625 Mn-54 Co-58 Fe-59. Co-60 SD 3/8/2016 22.5 +/- 39.2 8.54 +/- 54.6 37.4 +/- 109. 18.5 +/- 39.5 9/7/2016 18.1 +/- 31.8 27.5 +/- 35.2 4.84 +/- 61.3 12.0 +/- 33.4 Zn-65 Cs-134 Cs-137 K-40 3/8/2016 -96.6 +/- 114 -13.0 +/- 44.8 19.0 +/- 41.7 9/7/2016 -13.5 +/- 63.0 38.1 +/- 50.6 3.88 +/- 37.1 548 +/- 524 Mn-54 Co-58 Fe-59 Co-60 CHIC-C 3/7/2016 -10.7 +/- 34.7 -32.1 +/- 46.9 -12.9 +/- 90.0 6.79 +/- 34.8 9/6/2016 30.8 +/- 34.5 4.19 +/- 25.9 16.9 +/- 78.2 -9.92 +/- 28.7 Zn-65 Cs-134 Cs-137 K-40 3/7/2016 -77.4 +/- 83.0 -6.25 +/- 34.0 32.6 +/- 33.4 9/6/2016 39.6 +/- 85.3 6.58 +/- 32.5 -23.9 +/- 36.0 675 +/- 551 L_

47

TABLE 3-15: GAMM'A EMITTER CONCENTRATIONS IN CRABS Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (wet)+/- 2 Sigma Page 1of1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE K-40* Mn-54 Co-58 Fe-59 SD 6/7/2016 1180 +/- 762 16.3 +/- 28.0 11.4 +/- 31.8 -5.99 +/- 67.2 Co-60 Zn-65 Cs-134 Cs-137 9.06 +/- 29.5 -12.4 +/- 89.0 3.58 +/- 39.8 13.3 +/- 35.9 48

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2016 and tabulated in Section 3, are discussed below.

The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering quality assurance manuals and laboratory procedures. In addition to internal quality control measures performed by the laboratories, 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 Program are provided in Appendix B.

The predominant radioactivity detected throughout 2016 was from external sources, such as fallout from nuclear weapons tests (cesium-137) and naturally occurring radionuclides. Naturally occurring nuclides such as beryllium-7, potassium-40, raditim-226, thorium-228 and thorium-232 were detected in numerous samples.

The following is a discussion and summary of the results of the environmental measurements taken during the 2016 reporting period.

' 4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TI.D) is an inorganic ciystal used to detect ambient radiation. Two TLDs, made of CaF and LiF elements and specifically designed for environmental monitoring, are deployed at each sampling location ..

TLDs are placed in two concentric rings around the station. The inner ring is located in the vicinity of 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 centers 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 efiluents and direct radiation from the station.

The results of the TLD analyses are presented in Table 3-2. There was no detectable external dose to members of the public from Surry Power Station in 2016. The results of the TLD analysis shown in Table 3.2 comply with Section 7 of ANSI/HPS Nl3.37-2014 in order to ensure accurate environmental results. The long-term integrity of each field monitoring location is accomplished by a thorough, documented evaluation of the location for changes that could impact data quality in accordance with Section 7 .1 of the ANSI Standard. Since off-site processing of TLDs *is used, extraneous dose received prior to and after removal from the field is quantified in compliance with Section 7.2 of the ANSI Standard.

Data analysis for Table 3-2 was performed in accordance with Section 7. 3 of the

. 49

_J

ANSI Standard. This includes normalizing results to a standard 91 day quarterly monitoring period, determination of the baseline background dose for each monitoring location and determination of the smallest facility-related dose that can be detected above the baseline background.

4.2 Airborne Gross Beta Air is continuously sampled by passing it through glass fiber particulate filters.

The filters collect airborne particulate radionuclides. Once a week the samples are collected and analyzed for gross beta activity. Results of the weekly gross beta analyses are presented in Table 3 -3. A review of the results from control and indicator locations continues to show no significant variation in measured activities (see Figure 4 - 1 and 4-2). A slight separation was observed in the fourth quarter between the indicator and control location trend data points. Data from Figure 4-1 and 4-2 indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of Surry Power Station was higher because of nuclear weapons testing. During that time, nearly 7 40 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.

Figure 4-1: 2016 GROSS BETA IN AIR PARTICULATES 0.045 ~----------------------------~

0.040 -------------------------------i

0. 035 -------------------------------i 0.030 -+--------------------------------<

'E 0.025

~ 0.020 T--~--------------t-<r------:r-;:-----::ii;:-tr""'<-=---,*1

0. 0 15 +.-~-:-H--\----=-----:-.,....--+--i\----=-..------T-:m..----t'~,.__--..,.,..---,f-¥f--\.......-!F---i 0.0 I 0 +--'-----=-~f-'~._.~a...l--+--,'ll~~f-6----~i---_.,,.~frf-=------\'llJ-----I 0.005 0.000 in

°'(::!- N \0 - in 00 N \0 0 ("') r- in

°'(::!r- N \0

°'Q (::!

("') r- "<!" 00 N \0 0 Q :::::: (::! :::::: (::! Q (::! Q (::! Q Q :::::: :::::: (::! Q (::! Q Q :::::: ~

N N "<!" "<!" \0 \0 r- r- 00 00

'.::: '.::: ~ ~ ~

°' °'

("') ("') in in I---+--- Avg Indicator __._ AveControll 50

,---~------

Figure 4-2: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND e

(,)

Cl.

c-- 00 0\ 0 0 g0 80 g ~ ~ b ~ ~ ~ - N 0\0\0\0 0\0\0\0 0 0 0 0 0 0 0 0 0 0 N N N N N N N N N N N N N

- Avg Indicator - . - Avg Control - - Avg-Pre Op - - Required LLD 4.3 Airborne Radioiodine Air is also continuously sampled for radioiodines by passing it through charcoal cartridges. Once a week the charcoal cartridge samples are collected and analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection. No positive iodine-131 was detected. 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 Fukushima Daiichi nuclear incident in 2011.

4.4 Air Particulate Gamma The air particulate filters from 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 potassium-40 and beryllium-7, which are produced by cosmic processes. No man-made radionuclides were identified. These analyses confirm no effects from station effluents.

51

4.5 CowMilk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption_ of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be carefully evaluated when trying to determine if there is any station effect.

Results of gamma spectroscopy indicate no detectable station related radioactivity in the milk samples. The results of the analyses are presented in Table 3-6. In years past, cesium-137 had been detected sporadically. The occurrences were .

attributed to residual global fallout from past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2016.

At the request of .the Commonwealth of Virginia, a quarterly composite *sample is prepared from the monthly milk samples from the Colonial Parkway collection station. The composite samples are analyzed for strontium-89 and strontium-90.

No strontium-89 was detected in the four composites analyzed. Strontiuin-90 was detected in three of the composite samples at an average concentration of 1.59 pCi/L. Sr-90 is not a component of the station radiological effluents and is a product of nuclear weapons testing fallout which has been well documented.

4. 6 Food Products Three samples were collected and analyzed by gamma spectroscopy. The results of the analyses are presented in Table 3-7. As expected, naturally occurring potassium-40 was detected in all samples. The average concentration is consistent with that. observed in previous. years. No station related radioactivity was detected.

4.7 Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry Power Station monitors well water quarterly at three indicator locations and analyzes for gamma radiation and for tritium. The results of these analyses are presented in Table 3-8. Consistent .

with past monitoring, no. station related radioactivity was detected. No gamma emitting isotopes were detected during the pre-operational period.

52

4.8 River Water Samples of the James River water are collected monthly and the results are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. The monthly samples are also composited and analyzed for tritium on a quarterly basis. Tritium was not detected and, with the exception of natural products, no other gamma emitters were detected. The naturally occurring radionuclides detected were potassium-40, radium-226 and thorium-228. No station related radioactivity was detected.

4.9 Silt Silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Sampling of this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish.

Samples of silt are collected from two locations, one upstream and one downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10. Naturally occurring beryllium-7, potassium-40, radium-226, thorium-228 and thorium-232 were detected. Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). Cobalt-60 has not been detected since 2003. Trend graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-3 and 4-4.

The concentrations of cesium-137 detected indicate a continual decreasing trend as seen for over two decades. The detection of cesium-137 in both control and indicator samples and decreasing levels indicate that the presence of cesium-137 is the result of accumulation and runoff into the river of residual weapons testing fallout. Its global presence has been well documented. During the pre-operational period, cesium-137 was detected in silt samples with an average concentration as indicated in Figure 4-4. At the control location, cesium-137 was detected with an average concentration of 226 pCi/kg. This is the second consecutive year that cesium-137 was not detected in the indicator location. The cesium-137 concentrations in silt continue to decline and fluctuate around the REMP lower limit of detection (LLD) concentration, which could account for the non-detect. This trend will continue to be closely monitored.

53

Figure 4-3: COBALT-60 IN SILT 1.0E+03

"'C Cl) s

(.)

1.0E+02 c.

1.0E+Ol 0

00 N

00

'<t" 00

\0 00 00 00 0

0\

\0 0\

00 0\

0 0

N 0 g \0 0

00 0

0

...... N

...... \0 0\ 0\ 0\ 0\ 0\ 0\ 0\ 0\ 0 0 0 0 0 0 0 0 N N N N N N N N

- Control - Chickahominy ---+--- Station Discharge LLD Avg Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDC, Minimum Detectable Concentration. Station Discharge was <MDC activity 1996 through 1998 and 2004 through 2016.

54

Figure 4-4: CESIUM-137 IN SILT

~

"ti Cl S l.OE+03 -i+-lr-f-T""""---,...--=-----,,._-2'::::::.m--~~----------------i

(,)

c..

- Control - Chickahominy - Station Discharge - - Ave-Pre Op - - Required LLD 4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans.

Buildup of radionuclides along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. The results are presented in Table 3-11.

The naturally occurring radionuclides potassium-40, radium-226, thorium-228 and thorium-232 were detected at concentrations equivalent to normal background activities. The activities of these radionuclides indicate a steady trend. There were no radionuclides attributable to the operation of the station found in any shoreline sediment samples.

4.11 Fish The radioactivity measured in fish sampled from the station discharge canal and analyzed by gamma spectroscopy is presented in Table 3-12. These results are the same as those seen over the last decade. No activity was observed in this media except for naturally occurring potassium-40.

55

I 4.12 Oysters Oysters were collected from three different locations. The results of the oyster analyses are presented in Table 3-13.

There were no gamma emitting radionuclides detected in oysters sampled except for naturally occurring potassium-40. No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of 'steam generators in 1982 and past improvements made to liquid effluent treatment systems.

4.13 Clams Clams are analyzed from three different locations. The results of the gamma spectroscopy analyses are presented in Table 3-14. Like oysters, no station related radioactivity was detected.

4.14 Crabs A crab sample was collected in June from the station discharge canal and analyzed by gamma spectroscopy. The results of the analysis are presented in Table 3-15. Other than naturally occurring potassium-40, no other gamma emitting radionuclides were detected in the sample. This is consistent with pre-operational data and data collected over the past decade.

56

5. PROGRAM EXCEPTIONS There was one REMP exception for scheduled sampling and analysis during 2016.

Tue control milk sample for the month of April was unavailable because Williams dairy closed its operation. Another control sampling location was successfully identified. The new location is Lover Retreat Dairy and sampling for this location was initiated in May 2016 .

.There was one exception to the Interlaboratory Comparison Program (ICP) for 2016. A gross beta analysis was not performed for the Air Filter (AP) geometry in the second half of 2016. The Department of Energy, under the Mixed Analyte Performance Evaluation Program (MAPEP), has historically provided this sample to Teledyne Brown Engineering, Inc. (TBE). In the second half of 2016, TBE was notified by MAPEP that they were no longer supplying the AP geometry due to MAPEP funding issues. TBE did not request a replacement sample from other ICP sample providers for the balance of 2016. TBE has made arrangements with Eckert & Ziegler Analytics, Inc. to provide the AP geometry going forward.

57

6. CONCLUSIONS Tue results of the 2016 Radiological Environ!£,~,ptai Monitoring Program for Suny Power Station have been presented in previou*s sections. This section presents conclusions for each pathway.

> Direct Radiation Exposure Pathway - There was no detectable external dose to members of the public from Suny Power Station in 2016.

> Airborne Exposure Pathway - Analysis of charcoal cartridge samples for .

radioiodines indicated no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples* identified only naturally occurring beryllium-7 and potassium-40. Air particulate gross beta concentrations at all of the indicator locations for 2016 trend well with the control location. A slight separation between indicator and control location trend data points was observed in the .fourth quarter. Observation of this will continue into 201 7. *

> Milk - Milk samples are an important indicator measuring the effect of radioactive iodine and radionuclides in airborne releases. Cesium-137 and iodine-131 were not detected in any of the thirty-five samples. Naturally occurring potassium-40 was detected at a similar level when compared to the averages of the previous years.

Strontium-90 was detected in three samples at an average concentration of 1.59 pCi/L. Strontium-90 is not a component of station effluents, but rather, a product of nuclear weapons testing fallout.

> Food Products - As expected, naturally .occurring potassium-40 was detected in all three samples. In the past, cesium-137 had occasionally been detected in these samples and is attributable to global fallout from past nuclear weapons testing. Cesium-137 was not detected in any of the three samples collected in 2016.

> Well Water - Well water sample analyses indicated there was no radioactivity attributable to the operation of the station. This trend is consistent throughout the monitoring period.

> River Water - River water samples were analyzed for gamma emitting radionuclides and tritium. Only the naturally occurring gamma* emitting radionuclides potassium-40, radium-226 and thorium-228 were detected.

Tritium was not detected.

> Silt - Cesium-137 was detected in the control sample and not in the indicator sample. The presence of cesium-137 is attributable to residual weapons testing fallout and its presence has been well documented. Cobalt-60 has not been detected since 2003.

58

> Shoreline Sediment - Naturally occurring radionuclides were detected at concentrations equivalent to. normal background activities. There were no radionuclides attributable to the operation of Surry Power Station found in any sample.

Aquatic Biota

> Fish - As expected, naturally_ occurring potassium-4Q-cwas-'detected:

There -

were no other gamma emitting radionuclides detected in any of the fish samples.

> Oysters and Clams - Other than naturally occurring potassium-40, there were no other gamma emitting radionuclides detected in ahy of the oyster or clam samples.

> Crabs - Naturally occurring potassium-40 was detected. No other gamma emitting radionuclides were detected.

59

REFERENCES 60

r------

f/

References *

1. NUREG-0472, "Radiological Effluent Technical Specifications for PWRs",

Draft Rev. 3, March 1982.

2. 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.

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

December 1975.

- 4. United States Nuclear Regulatory Commission Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.

5. Dominion, Station Administrative Procedure, VPAP-2103S, "Offsite Dose Calculation Manual (Surry)".

6. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.

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

8. NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.

9. NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009.

10 ..Position paper on "Implementation of ANSI/HPS Nl3.37-2014 Environmental Dosimetry Criteria at Surry Power Station", November 2016 by John M. Sukosky, CHP.

61

APPENDICES 62

APPENDIX A: LAND USE CENSUS Year 2016

I 63

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January 1 to December 31, 2016 Page 1of1 Nearest Nearest Nearest Nearest Sector Direction Resident Garden** Cow Goat A N 4.1@ 10° (a) (a) (a)

B NNE 1.9 @32° (a) (a) (a) c NE 4.7@35° (a) (a) (a)

D ENE (a) (a) (a) (a)

E E (a) (a) (a) (a)

F ESE (a) (a) (a) (a)

G SE 2.8@ 142° (a) (a) (a)

H SSE 2.7@ 158° 2.7@ 158° (a) (a)

J s l.7@181° 2.0@ 183° (a) (a)

K SSW 1.9@ 192° 1.9@ 192° 4.8@200° (a)

L SW 2.3@221° 4.7@228° (a) (a)

M WSW 0.4@244° 3.6@245° (a) (a)

N w 3.1 @260° 3.4@260° (a) (a) p WNW* 4.9@283° (a) (a) (a)

Q NW 4.6@321° (a) (a) (a)

R NNW 3.8 @338° 4.4@334° 3.7@336° (a)

Locations are listed by miles and degrees heading relative to true north from center of Unit #1 Containment.

- Area greater than 50 m 2 and contains broadleafvegetation.

(a) None 64

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS Year 2016 65

nYTRODUCTION This appendix covers the Interlaboratmy Comparison Program (ICP) of Teledyne Brown Engineering (TBE). TBE use QA/ QC samples provided by Eckert & Ziegler Analytics, Inc., Environmental Resource Associates (ERA) and the Mixed Analyte Performance Evaluation Program (MAPEP) to monitor the quality of analytical processing associated with the REMP. Each provider has a documented Quality Assurance program and the capability to prepare Quality Control materials traceable to the National Institute of Standards and Technology (NIST). The providers supply the samples to TBE, and upon receipt, the laboratories perform the analyses in a normal manner. The results are then reported to the provider for evaluation. The suite of QA/ QC samples is designed to provide sample media and radionuclide combinations that are offered by the providers and included in the REMP and typically includes:

> milk for gamma nuclides and low-level iodine-131 analyses,

> milk for Sr-89 and Sr-90 analyses, *

> water for gamma nuclides, low-level iodine-131, and gross beta analyses,

> water for tritium, Sr-89, and Sr-90 analyses,

> cartridge for I-131 analyses,

> air filter for gamma nuclide, gross beta, and Sr-90 analyses.

The accuracy of each result reported to Eckert & Ziegler Analytics, Inc. is measured by the ratio of the TBE result to the known value. Accuracy for all

. other results is based on statistically derived acceptance ranges calculated by the providers. An investigation is undertaken whenever the ratio or reported result fell outside of the acceptance range.

RESULTS The TBE ICP results are included in the following tables for the first through the fourth quarters of 2016. Some analyses did not meet the acceptance criteria. TBE initiated non-conformance reports (NCRs) to document and address the analyses.

The results of the NCRs are as follows.

1. NCR 16-26, Eckert & Ziegler Analytics milk sample El 1476 failed Sr-90.

The TBE value of 15.0 pCi/L was higher than the known value of 11.4 pCi/L. The resultant ratio was 1. 32 failing above 1:4e high acceptance limit of 1.30. The QA data, yield, and associated raw data of the analysis were reviewed and found to be acceptable. It is believed the laboratory technician did not rinse the filtering apparatus properly and some cross contamination from an internal laboratory spike sample may have been transferred to the Analytics sample. The sequence of filtering samples would have placed the Analytics sample on the same filtering apparatus as the internal laboratory spike sample. Additional training has been given to the laboratory technician on how to properly rinse the filtering apparatus. Additional 66

clarifying language on cleaning filtering apparatus has been added to laboratory procedure TBE-2019 Radiostrontium Ion Exchange.

2. NCR 16-34, ERA water sample RAD-107 failed H-3. The TBE value of 918 pCi/L was lower than the known value of 9,820 pCi/L, failing below the lower acceptance limit of 8,540. The result of 918 pCi/L was incorrectly reported due to a data entry issue. The actual TBE value was 9, 180 pCi/L, and if reported correctly, would have been within the acceptable range of 8,540- 10,800 pCi/L. The data entry error was missed during the review process. TBE will perform additional review of data entry into the ERA database.

3. NCR 16-35, Eckert & Ziegler Analytics milk sample El 1699 failed Sr-90.

The TBE value of 14. 7pCi/L was higher than the known value of 10. The resultant ratio was 1.47, failing above the high acceptance limit of 1.30.

The cause was determined to be an incorrect volume entry in the Laboratory Information Management System. A lower volume of 0.6L, the typical sample volume, was entered instead of the actual l .2L volume used for this sample. If the correct volume of l .2L had been entered, the result would have had an acceptable ratio of 1.22. The laboratory manager will specify the sample aliquot going forward to avoid any future confusion.

67

ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1OF3)

Identification Reported Known Ratio (c)

Month/Year Matrix Nuclide Units Evaluation (d)

Number Value (a) Value (bl TBE/Anal~ics February 2016 A31519(3) AP Sr-89 µCi/cc 2.04 2.46 0.83 A Sr-90 µCi/cc 2.08 2.68 0.78 A March 2016 E11476 Milk Sr-89 pCi/L 97 86.7 1.12 A Sr-90 pCi/L 15 11.4 1.32 N(2)

E11477 Milk 1-131 pCi/L 85.9 82.2 1.05 A Ce-141 pCi/L 106 98.4 1.08 A Cr-51 pCi/L 255 243 1.05 A Cs-134 pCi/L 134 130 1.03 A Cs-137 pCi/L 174 161 1.08 A Co-58 pCi/L 123 117 1.05 A Mn-54 pCi/L 141 117 1.21 w Fe-59 pCi/L 152 131 1.16 A Zn-65 *pCi/L 193 179 1.08 A Co-60 pCi/L 259 244 1.06 A E11184 AP Ce-141 pCi 69 81.1 0.85 A Cr-51 pCi 242 201 1.20 w Cs-134 pCi 98.1 107.0 0.92 A Cs-137 pCi 136 133 1.02 A Co-58 pCi 91.9 97 0.95 A Mn-54 pCi 98.6 96.2 1.02 A Fe-59 pCi 98.8 108 0.91 A Zn-65 pCi 131 147 0.89 A Co-60 pCi 209 201 1.04 A E11478 Charcoal 1-131 pCi 85.3 88.3 0.97 A E11185 Water Fe-55 pCi/L 1800 1666 1.08 A June 2016 E11537 Milk Sr-89 pCi/L 94.4 94.4 1.00 A Sr-90 pCi/L 13.4 15.4 0.87 A E11538 Milk 1-131 pCi/L 96.8 94.5 1.02 A Ce-141 pCi/L 129 139 0.93 A Cr-51 pCi/L 240 276 0.87 A Cs-134 pCi/L 157 174 0.90 A Cs-137 pCi/L 117 120 0.98 A Co-58 pCi/L 131 142 0.92 A Mn-54 pCi/L 128 125 1.02 A Fe-59 pCi/L 132 122 1.08 A Zn-65 pCi/L 235 235 1.00 A Co-60 pCi/L 169 173 0.98 A (a) Teledyne Brown Engineering reported result.

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

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1. 20.

W-Acceptable with warning, reported result falls within 0. 70-0.80or1.20-1.30. N =Not Acceptable, reported result falls outside the ratio limits of< 0. 70 and> 1. 30.

(2) NCR 16-26 was initiated (3) Sample results provided by Eckert & Ziegler are from another utility's cross check program.

68

ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE2 OF3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value(a) Value (b) TB ElAnalytics Evaluation (d)

June 2016 E11540 Filter Ce-141 pCi 105 99.8 1.05 .A Cr-51 pCi 216 198 1.09 A Cs-134 pCi 113 125 0.90 A Cs-137 pCi 94.5 86.6 1.09 A Co-58 pCi 101 102 0.99 A Mn-54 pCi 88.8 90.2 0.98 A Fe-59 . pCi .82.0 87.5 0.94 A Zn-65 pCi 174 169 1.03 A Co-60 pCi 143 124 1.15 A E11539 Charcoal 1-131 pCi 86.1 89.4 0.96 A September 2016 E11609 Milk Sr-89 pCi/L 89.9 90.9 0.99 A Sr-90 pCi/L 13.3 13.7 0.97 A E11610 Milk 1-131 pCi/L 80.4 71.9 1.12 A Ce-141 pCi/L 81.3 93.2 0.87 A Cr-51 pCi/L 198 236 0.84 A Cs-134 pCi/L 122 136 0.90 A Cs-137 pCi/L 119 119 1.00 A Co-58 pCi/L 92.2 97.4 0.95 A Mn-54 pCi/L 156 152 1.03 A Fe-59 pCi/L 97.5 90.6 1.08 A Zn-65 pCi/L 189 179 1.06 A Co-60 pCi/L 131 135 0.97 A E11612 Filter Ce-141 pCi 67.5 63.6 1.06 A Cr-51 pCi 192 161.0 1.19 A Cs-134 pCi 91.4 92.6 0.99 A Cs-137 pCi 93.9 80.8 1.16 . A Co-58 pCi 66.0 66.4 0.99 A Mn-54 pCi 104 104 1.00 A Fe-59 pCi 60.5 61.8 0.98 A Zn-65 pCi 140 122 1.15 A Co-60 pCi 119 91.9 1.29 w E11611 Charcoal 1-131 pCi 52.4 59.9 0.87 A December 2016 E11699 Milk Sr-89 pCi/L 95.2 74.2 1.28 w

-Sr-90 pCi/L 14.7 10 1.47 N (2)

Footnotes are on page 3 of 3.

69

ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE30F3)

Identification Reported Known Ratio (c)

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

December 2016 E11700 Milk 1-131 pCi/L 97.5 97.4 1.00 A Ce-141 pCi/L 136 143 0.95 A Cr-51 pCi/L 247 280 0.88 A Cs-134 pCi/L 164 178 0.92 A Cs-137 pCi/L 120 126 0.95 A Co-58 pCi/L 139 146 0.95 A Mn-54 pCi/L 126 129 0.98 A Fe-59 pCi/L 114 125 0.91 A Zn-65 pCi/L 237 244 0.97 A Co-60 pCi/L 168 178 0.94 A 11702 Filter Ce-141 pCi 91.7 97.7 0.94 A Cr-51 pti. 210 192 1.09 A Cs-134 pCi 122 122 1.00 A Cs-137 pCi 93.9 86.4 1.09 A Co-58 pCi 92.0 100 0.92 A Mn-54 pCi 93.7 88.5 1.06 A Fe-59 pCi 84.9 85.4 0.99 A Zn-65 pCi 176 167 1.05 A Co-60 pCi 151 122 1.24 w E11701 Charcoal 1-131 pCi 95.6 98.0 0.98 A E11730 Filter Sr-89 pCi 79.7 92.0 0.87 A Sr-90 pCi 10.0 12.5 0.80 A N (1) Milk, Sr The failure was due to cross-contamination of laboratory apparatus. NCR 16-26 N (2) Milk, Sr The failure was due to sample volume data entry error. NCR 16-35 (a) Teledyne Brown Engineering reported result.

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

(c) Ratio of Teledyne Brown Engineering to Analytics results.

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

W-Acceptable with warning, reported result falls within 0. 70-0. 80 or 1.20-1.30. N =Not Acceptable, reported result falls outside the ratio limits of< 0.70.and > 1.30.

70

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE1 OF1)

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

March 2016 16-GrF34 Filter Gr-A Sq/sample 0.608 1.20 0.36- 2.04 A Gr-S Sq/sample 0.806 0.79 0.40 -1.19 A (a) Teledyne Brown Engineering reported result.

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

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

71

ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE1OF1)

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

May 2016 RAD-105 Water Sr-89 pCi/L 48.9 48.2 37.8 - 55.6 A Sr-90 pCi/L 25.0 28.5 20.7 - 33.1 A Ba-133 pCi/L 53.1 58.8 48.7- 64.9 A Cs-134 pCi/L 40.9 43.3 34.6 - 47.6 A Cs-137 pCi/L 85 78 70.6 - 88.9 A Co-60 pCi/L 108.0 102.0 91.8- 114 A Zn-65 pCi/L 226 214 193 - 251 A Gr-A pCi/L 38.9 62.7 32.9 - 77.8 A Gr-B pCi/L 41.9 39.2 26.0 - 46.7 A 1-131 pCi/L 24.1 26.6 22.1 - 31.3 A U-Nat pCi/L 4.68 4.64 3.39 - 5.68 A H-3 pCi/L 7720 7840 6790 - 8620 A November 2016 RAD-107 Water Sr-89 pCi/L 43 43.3 33.4- 50.5 A Sr-90 pCi/L 30 33.6 24.6 - 38.8 A Ba-133 pCi/L 47.8 54.9 45.4- 60.7 A Cs-134 pCi/L 72.9 81.8 67.0- 90.0 A Cs-137 pCi/L 189 210 189.- 233 A Co-60 pCi/L 58.4 64.5 58.0- 73.4 A Zn-65 pCi/L 243 245 220 - 287 A Gr-A pCi/L 37.2 68.4 35.9 - 84.5 A Gr-B pCi/L 35.1 33.9 22.1-41.6 A 1-131 pCi/L 23.5 26.3 21.9 - 31.0 A U-Nat pCi/L 49.2 51.2 41.6-56.9 A H-3 pCi/L 918 9820 8540 -10800 N (3)

N (3) Water, H The failure was due to a data entry error. NC~ 16-34 (a) Teledyne Brown Engineering reported result.

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

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

72

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