Text

Independent Spent Fuel Storage Installation 2017 Annual Radiological Environmental Operating Report
	ML18130A592
Person / Time
Site:	Surry, 07200002, 07200055
Issue date:	04/30/2018
From:	; Virginia Electric & Power Co (VEPCO)
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	Download: ML18130A592 (77)
	v • d • e

Serial No.18-151 Docket Nos.: 50-280 50-281 72-2 72-55 ATTACHMENT 1 2017 Annual Radiological Environmental Operating Report SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

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I I 2017 Annual Radiological Environmental Operating Report I

I I Surry Power Station I

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I I Dominion Energy Surry Power Station I Radiological Environmental Monitoring Program I January 1, 2017 to December 31, 2017 I

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I I Annual Radiological Environmental Operating Report Surry Power Station I January 1, 2017 to December 31, 2017 I

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Prepared by: - - - - - - ~(}-~~-*__.,.,_tJ,.,.)_ _,.~~"""~"""""-"'---1---'n'/J"---------

iw.Abbott$.1/

2 Health Physicist I

Reviewed by: ~ ..! . ~~::::==--___.-==-----

I - - = - - - - - - -A.-E.-Hairston ------------

Supervisor Radiologicai Analysis I Reviewed by: _ _ _ _ _ ___~~~~-;.=-/~~.:::"--.. .::-_ _______

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I I T. L. Ragland I Manager Radiological Protection and Chemistry I

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Table of Contents I

I PREFACE .............................................................................................................................................. 4

1. EXECUTIVE

SUMMARY

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

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

3. ANALYTICAL RESULTS ............................................................................................................ 20 I 3 .1 Summary of Results .............................................................................................................. 20 3.2 Analytical Results of2017 REMP Samples ......................................................................... 28

4. DISCUSSION OF RESULTS ..................................................................................................... 49 I 4.1 Gamma Exposure Rate ......................................................................................................... 49 4.2 Airborne Grdss Beta ............................................................................................................. 50 4.3 Airborne Radioiodine ............................................................................................................ 52 I 4.4 Air Particulate Gamma ......................................................................................................... 52 4.5 Animal Milk .......................................................................................................................... 52 I 4.6 Food Products ....................................................................................................................... 53 4.7 Well Water ............................................................................................................................ 53 4.8 River Water ........................................................................................................................... 53 I 4.9 Silt ......................................................................................................................................... 54 4.10 Shoreline Sediment ............................................................................................................. 56 4.11 Fish ...................................................................................................................................... 56 I 4.12 Oysters ................................................................................................................................ 56 4.13 Clams .................................................................................................................................. 56 4.14 Crabs ................................................................................................................................... 57 I 5. PROGRAM EXCEPTIONS ........................................................................................................... 58

6. CONCLUSIONS ............................................................................................................................. 59 REFERENCES .................................................................................................................................... 61 I . APPENDICES ..................................................................................................................................... 63 APPENDIX A: LAND USE CENSUS ........................................................................................... 64 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS ............................... 66 I

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I I I PREFACE

,1 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 I Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications, Appendix C, Item 1.3.1.

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I I 1. EXECUTIVE

SUMMARY

I This document is a detailed report of the 201 7 Suny Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from J anuaiy 1 through December 31, 2017, in air, water, silt, shoreline sediment, milk, aquatic I 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 (AI.ARA), no undue I 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.

I Radiation and radioactivity in the environment are monitored within a 20-mile I radius of the station. Suny 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. 1\vo types of I samples are obtained. The first type, control samples, is collected from areas that are beyond the measurable influence of Suny Power Station or any other nuclear facility. These samples represent normal background radiation levels. Background I 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 I samples are taken from areas close to the station where any station contribution will be at the highest concentration.

I 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 I 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 I accidents that released radioactive material to the environment.

Teledyne Brown Engineering, Inc. (TBE) provides radioanalyses for this program I and Mirion Technologies provides thermoluminescent dosimetry (TLD) services.

Participation in an Interlaborato:ry Comparison Program provides an independent I check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of I this, the United States Nuclear Regulato:ry 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 I are as accurate as possible. The USNRC also mandates a reporting level for radionuclides. Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified I reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.

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I I Analytical results are reported for all possible radiation exposure pathways to I man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates. The 2017 airborne results were similar to previous years. No station I 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 I 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.

I 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 I 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, I contained no station related radionuclides. Naturally occurring radionuclides potassium-40, radium-226 thorium-228 and thorium-232 were detected at average environmental levels. The terrestrial exposure pathway includes milk and I food products. Iodine-131 was not detected in any 2017 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident.

I 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 I 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 I the years.

During 201 7, as in previous years, the operation of Surry Power Station has I 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 201 7 was I 0.055 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 I 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 I Station.

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I I 2. PROGRAM DESCRIPTION I 2.1 Introduction I This report documents the 201 7 Surry Power Station operational Radiological Environmental Monitoring Program (REMP) .- Dominion Energy's Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, I 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 I 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.

I The United States Nuclear Regulatory Commission regulations (10CFR50.34a) require that nuclear power plants be designed, constructed and operated to keep I 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 I 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 accumulation of radioactivity I in the environment, a program for monitoring the station environs is also included in Surry Power Station Technical Specifications.

I Dominion personnel are responsible for collecting the various indicator and control environmental samples. Mirian Technologies is responsible for processing I the TLDs. 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 I values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radionuclides. Data collected prior to station operation is used to I 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.

I Occasionally, samples of environmental media may show the presence of man-made radionuclides. As a method of referencing the measured radionuclide I 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",

I (December, 1975) 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 I Achievable."

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This report documents the results of the REMP for 201 7 and satisfies the following I objectives of the program:

~ To provide measurements of radiation and of radioactive materials in those I 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.

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

I ~ To identify changes in radioactivity in the environment.

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

I 2.2 Sampling and Analysis Program I Table 2-1 summarizes the 201 7 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled I "control." Dominion Energy personnel collect all samples listed in Table 2-1.

Table 2-2 summarizes the analysis program conducted by Teledyne Brown I 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 I in Irvine, CA, for processing.

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

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Table 2-1 SURRY-2017 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Pg. 1 of3 Distance Collection Sam~le Media Location Station Miles Direction Degrees Freguenc;y 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 89° 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 Kingsmill (29) 4.6 N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.8 N oo Quarterly Population Center 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 - 2017 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 P . 2 of3 Distance Collection Samele Media Location Station Miles Direction Degrees Freguenc;y 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) 17.1 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 Surry Station (SS) 0.3 NNE 18° Weekly Site boundary location with highest D/Q and Particulate Hog Island Reserve (HIR) 2.0 NNE 26° Weekly Bacon's Castle (BC) 4.5 SSW 202° Weekly Alliance (ALL) 5.1 WSW 247° Weekly Colonial Parkway (CP) 3.8 NNW 333° Weekly BASF (BASF) 5.1 ENE 70° Weekly Fort Eustis (FE) 4.9 ESE 104° Weekly Newport News (NN) 19.3 SE 130° Weekly Control Location River Water Surry Station Discharge (SD) 0.4 NW 323° Monthly Scotland Wharf (SW) 4.9 WNW 284° Monthly Control Location Well Water Surry Station (SS) 0.1 SW 227° Quarterly Onsite Hog Island Reserve (HIR) 2.0 NNE 28° 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 Surry Station Discharge (SD) 1.3 NNW 341° Semi-Annually Surry Station Intake (SI) 1.8 ESE 112° Semi-Annually 10

Table 2-1 SURRY - 2017 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 P . 3 of3 Distance Collection SamEle Media Location Station Miles Direction Degrees Freguencl'. Remarks Milk Colonial Parkway (CP) 3.7 NNW 336° Monthly Lover Retreat (LRD) 30.6 NNW 50 Monthly Control Location Epps (EPPS) 4.8 SSW 200° Monthly Oysters Point of Shoals (POS) 6.4 SSE 157° Semi-Annually Mulberry Point (MP) 4.9 ESE 124° Semi-Annually Swash Hole Island (SHI) 6.8 SE 130° Semi-Annually Clams Chickahominy River (CHIC) 11.2 WNW 300° Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 341 ° Semi-Annually Jamestown Island (JI) 3.9 NW 324° Semi-Annually Fish Surry Station Discharge (SD) 1.3 NNW 341° Semi-Annually Crabs Surry Station Discharge (SD) 1.3 NNW 341° Annually Crops Brock's Farm (BROCK) 3.8 s 183° Annually (Corn, Peanuts, Slade's Farm (SLADE) 3.2 s 179° Annually

/ Soybeans) 11

I Table 2-2 I SURRY -2017 SAMPLE ANALYSIS PROGRAM Pg. 1 of3 I SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS mR/Std.

I Thermoluminescent Dosimetry (TLD)

Quarterly Gamma Dose 2 Month Air Iodine Weekly I-131 0.07 pCi/m3 I Air Particulate Weekly Gross Beta Gamma 0.01 pCi/m3 Quarterly (a) Isotopic pCi/m3 I Cs-134 Cs-137 0.05 0.06 I River Water Quarterly Composite of monthly sample Tritium (H-3) 2000 pCi/L I Monthly 1-131 Gamma 10 pCi/L Isotopic pCi/L I Mn-54 Fe-59 Co-58 15 30 15 Co-60 15 I Zn-65 Zr-95 30 30 Nb-95 15 I Cs-134 Cs-137 Ba-140 15 18 60 La-140 15 I Well Water Quarterly Tritium (H-3) 1-131 2000 1

pCi/L I Gamma Isotopic Mn-54 15 pCi/L Fe-59 30 I Co-58 Co-60 15 15 Zn-65 30 I Zr-95 Nb-95 Cs-134 30 15 15 Cs-137 I Ba-140 La-140 18 60 15 I Footnotes located at end of table.

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I Table 2-2 SURRY-2017 I SAMPLE ANALYSIS PROGRAM Pg. 2 of3 SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS I Shoreline Sediment Semi-Annually Gamma Isotopic Cs-134 Cs-137 150 180 pCi/kg- dry I Silt Semi-Annually Gamma Isotopic Cs-134 150 pCi/kg- dry Cs-137 180 I Milk Monthly 1-131 1 pCi/L I Gamma Isotopic Cs-134 Cs-137 15 18 pCi/L Ba-140 60 I La-140 15 Quarterly Sr-89 NA pCi/L I Composite of CP monthly sample Sr-90 NA I Oysters Semi-Annually Gamma Isotopic Mn-54 Fe-59 130 260 pCi/kg-wet Co-58 130 I Co 60 0

Zn-65 130 260 Cs-134 130 I Clams Semi-Annually Cs-137 Gamma Isotopic 150 pCi/kg-wet Mn-54 130 I Fe-59 Co-58 260 130 Co-60 130 I Zn-65 Cs-134 260 130 Cs-137 150 I Crabs Annually Gamma Isotopic Mn-54 130 pCi/kg-wet Fe-59 260 I Co-58 Co-60 130 130 Zn-65 260 I Cs-134 Cs-137 130 150 I Footnotes located at end of table.

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I Table 2-2 SURRY - 2017 I SAMPLE ANALYSIS PROGRAM P . 3 of3 SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS I Fish Semi-Annually Gamma Isotopic Mn-54 130 pCi/kg - wet Fe-59 260 I Co-58 Co-60 130 130 Zn-65 260 I Cs-134 Cs- 137 130 150 I Food Products Annually Gamma Isotop ic I-131 Cs- 134 60 60 pCi/kg - wet Cs-137 I 80 I

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I ote: This tab le is not a comp lete listing ofnuclides that can be detected and reported. Other peaks that are measurable and identifiab le, together with the above nuclides, are also identified and reported.

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LLD is the Lower Lim it of Detection as defined and required in the USNRC Branch Techn ical Position on an Acceptable Radio logical Environmental Monitoring Program, Revision l , November 1979. LLDs indicate those concentrations to which environmental samples are required to be analyzed. Actual I analysis of samples may be lower than these listed values.

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

A None assigned I

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I Vl WSW ESE SW Legend

Air Sampling Stations TLD Sampling State Environmental Monitoring Sites State TLD Sites I Figure 1. Surry Radiological Monitoring Locations

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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 . USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

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I I 3. ANALYTICAL RESULTS I 3.1 Summary of Results In accordance with the Surry Offsite Dose Calculation Manual (ODCM), a I 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 I Program", Revision 1, November 1979. A more detailed analysis of the data is given in Section 4.

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I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I Medium or Surry Power Station, Surry County, Virginia - 2017 Docket No. 50-280-281 Indicator Page 1 of7 Control I Pathway Sampled (Units)

Analysis Type ITotal No. LLD Locations Mean Range Location with Highest Mean I Distance Name Direction I Mean Range Locations Mean Range Non-Routine Reported Measurements I Direct Radiation TLD (mRI Gamma 164 2 5.6 (150/152)

(4.0 - 8.0)

STA-9 0.3mi E

7.8 (4/4)

(7.3 - 8.0) 6.0 (12/12)

(4.9 - 7.6) 0 Std Month)

I Air Particulate Gross Beta 416 10 13.9 (362/364)

(2.05 - 27.2)

BASF 5.1 mi ENE 15.5 (52/52)

(4.5 -27.2) 12.8 (52/52)

(4.5 - 21.1) 0 (1 E-3 pCilm3) *-----------------------------------------------------------------------------------------------------------------------------------------------------*

I Gamma Be-7 32 32 144.2 (28/28) BASF 5.1 mi 163 (4/4) 134 (4/4) 0 (97.8 - 201) ENE (122 - 201) (122 -150)

I K-40 32 23.7 (1/28)

(23. 7 - 23. 7) 55 0.3mi NNE 23.7 (1/28)

(23.7 - 23.7)

< LLD 0 I Cs-134 32 50 < LLD N/A < LLD < LLD 0 Cs-137 32 < LLD N/A < LLD < LLD 0 I 60 Air Iodine 1-131 416. 70 < LLD N/A < LLD < LLD 0 I (1E-3 pCilm3)

Milk (p Ci/Liter)

Strontium 4 N/A I Sr-89 4 < LLD < LLD < LLD 0 Sr-90 4 1.27 (3/4) CP 3.7mi 1.27 (3/4) < LLD 0 I Gamma 36 (0.97 -1.73) NNW (0.97 - 1.73)

I K-40 36 1361 (24/24)

(1110 -1620)

LR 30.6mi NNW 1610 (12/12)

(1280 -1870) 1610 (12/12)

(1280 -1870) 0 Th-228 36 < LLD N/A < LLD < LLD 0 I 1-131 36 < LLD N/A < LLD < LLD 0 I Cs-134 36 15 < LLD N/A < LLD < LLD 0 I Cs-137 36 18 < LLD N/A < LLD < LLD 0 I Ba-140 36 60 < LLD N/A < LLD < LLD 0 I 21

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2017 I Medium or Docket No. 50-280-281 Indicator Page 2 of7 Control I Pathway Sampled (Units)

Analysis Type ITotal No. LLD Locations Mean Range Location with Highest Mean Name Direction I Distance I Mean Range Locations Mean Range Non-Routine Reported Measurements I Milk (pCi!Liter)

Gamma La-140 36 36 15 < LLD N/A < LLD < LLD 0 I Food Gamma 3 Products I (pCi/kg wet) K-40 3 10453 (3/3)

(4170

21700)

Slade 3.2mi s

21700 (1/1)

(21700-21700)

N/A 0 Be-7 3 < LLD N/A < LLD N/A 0 I Th-228 3 < LLD N/A < LLD N/A 0 I 1-131 3 60 < LLD N/A < LLD N/A 0 I Cs-134 3 60 < LLD N/A < LLD N/A 0 I Cs-137 3 80 < LLD N/A < LLD N/A 0 Well H-3 12 2000 < LLD N/A < LLD N/A 0 I Water (pCi!Liter) *-----------------------------------------------------------------------------------------------------------------------------------------------------*

Gamma 12 I Mn-54 12 15 < LLD N/A < LLD N/A 0 N/A N/A I Co-58 12 15 < LLD < LLD 0 Fe-59 12 30 < LLD N/A < LLD N/A 0 I Co-60 12 15 < LLD N/A < LLD N/A 0 I Zn-65 12 30 < LLD N/A < LLD N/A 0 I K-40 12 84.2 (1/8)

(28.5

84.2)

HIR 2.0mi NNE 84.2 (1/4)

(28.5

84.2)

N/A 0 I

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I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2017 I Medium or Docket No. 50-280-281 Indicator Page 3 of7 Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine I Sampled (Units) Type

'Total No. LLD Mean Range Name Direction I Distance I Mean Range Mean Ran!=le Reported Measurements Well Nb-95 12 15 < LLD N/A < LLD N/A 0 I Water (pCVLiter)

Zr-95 12 30 < LLD N/A < LLD N/A 0 I 1-131 12 < LLD N/A < LLD N/A 0 I Cs-134 12 15 < LLD N/A < LLD N/A 0 I Cs-137 12 18 < LLD N/A < LLD N/A 0 Ba-140 12 60 < LLD N/A < LLD N/A 0 I La-140 12 15 < LLD N/A < LLD N/A 0 I Th-228 12 19.8 (1/12)

(19.8 - 19.8) cs 0.3mi E

19.8 (1/12)

(19.8 -19.8)

N/A 0 I River Water (pCVLiter)

H-3 8 2000 < LLD N/A

< LLD < LLD 0 Gamma 24 I K-40 24 96.6 (7/12)

(69.1 -143)

SW 4.9mi WNW 104.5 (3/12)

(81.0 -142) 104.5 (3/12)

(81.0 - 142) 0 I Ac-228 24 17.4 (1/12)

(17.4 -17.4)

SD 0.4mi NW 17.4 (1/12)

(17.4 - 17.4)

< LLD 0 Ra-226 24 < LLD N/A < LLD < LLD 0 I Th-228 24 < LLD N/A < LLD < LLD 0 I Mn-54 24 15 < LLD N/A < LLD < LLD 0 I Co-58 24 15 < LLD N/A < LLD < LLD 0 Fe-59 24 30 < LLD N/A < LLD < LLD 0 I Co-60 24 15 < LLD N/A < LLD < LLD 0 I Zn-65 24 30 < LLD N/A < LLD < LLD 0 I 23

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2017 I Medium or Docket No. 50-280-281 Indicator Page 4 of7 Control I Pathway Sampled (Units)

Analysis Type ITotal No. LLD Locations Mean Range Location with Highest Mean I Distance Name Direction I Mean Range Locations Mean Range Non-Routine Reported Measurements I River Water (p Ci/Liter)

Nb-95 24 15 < LLD N/A < LLD < LLD 0 Zr-95 24 30 < LLD N/A < LLD < LLD 0 I 1-131 24 10 < LLD N/A < LLD < LLD 0 I Cs-134 24 15 < LLD N/A < LLD < LLD 0 I Cs-137 24 18 < LLD N/A < LLD < LLD 0 I Ba-140 24 60 < LLD N/A < LLD < LLD 0 La-140 24 15 < LLD N/A < LLD < LLD 0 I *------------------------------------------------------------------------------------------------------------------------------------------------------------------------

Silt Gamma 5 (pCi/kg dry}

I Be-7 5 1430 (1/3)

(1430 -1430)

SD 1.3 mi NNW 1430 (1/3)

(1430 -1430)

< LLD 0 K-40 5 16067 (3/3) CHIC 11.2 mi 17100 (2/2) 17100 (2/2) 0 I Cs-134 5 150 (15400-16500)

< LLD N/A WNW (16600-17600) (16600-17600)

< LLD < LLD 0 I Cs-137 5 180 135 (2/3)

(108-162)

SI 1.8 mi ESE 162 (1/1)

(162

162) 170 (2/2)

(132

207) 0 I Ra-226 5 2547 (3/3)

(1940

3130)

SI 1.8 mi ESE 2570 (1/1)

(2570

2570) 3115 (2/2)

(2950

3280) 0 I Th-228 5 1487 (3/3)

(1210 -1790)*

SD 1.3 mi NNW 1625 (2/2)

(1460 -1790) 1435 (2/2)

(1390

1480) 0 Th-232 5 1297 (3/3) SD 1.3mi 1365 (2/2) 1370 (2/2) 0 I (1020 -1710) NNW (1020 -1710) (1310 -1430)

I I

I 24

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2017 I Medium or Docket No. 50-280-281 Indicator Page 5 of7 Control I Pathway Sampled (Units)

Analysis Type ITotal No. LLD Locations Mean Range Location with Highest Mean I Distance Name Direction I Mean Range Locations Mean Range Non-Routine Reported Measurements I Shoreline Sediment (pCi/kg dry)

K-40 4 6190 (2/2)

(5050

7330)

HIR 0.6mi N

6190 (2/2)

(5050

7330) 2645 (2/2)

(1100

4190) 0 Cs-134 4 150 < LLD N/A < LLD < LLD 0 I Cs-137 4 180 < LLD N/A < LLD < LLD 0 I Ra-226 4 1210 (1/2)

(1210

1210)

CHIC 11.2 mi WNW 6150 (1/2)

(6150

6150) 6150 (1/2)

(6150

6150) 0 I Th-228 4 505 (2/2)

(126

884)

CHIC 11.2 mi WNW 2225 (2/2)

(1010

3440) 2225 (2/2)

(1010

3440) 0 Th-232 4 842 (1/2) CHIC 11.2 mi 2161 (2/2) 2161 (2/2) 0 I (842

842) WNW (861 - 3460) (861

3460)

Fish Gamma 4 I (pCilkg wet)

K-40 4 2740 (4/4)

(1980

2335)

SD 1.3mi NNW 2740 (4/4)

(1980

2335)

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

I I

I 25

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2017 I Medium or Docket No. 50-280-281 Indicator Page 6 of7 Control I Pathway Sampled (Units)

Analysis Type ITotal No. LLD Locations Mean Range Location with Highest Mean Name Direction I Distance I Mean Range Locations Mean Range Non-Routine Reported Measurements I Oysters (pCi/kg wet)

Gamma K-40 6

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

K-40 6 859 (2/4)

(735 - 983)

JI 3.9mi NW 859 (2/4)

(735 -983)

< LLD 0 I Mn-54 6 130 < LLD N/A < LLD < LLD 0 Co-58 6 130 < LLD N/A < LLD < LLD 0 I Fe-59 6 260 < LLD N/A < LLD < LLD 0 I Co-60 6 130 < LLD N/A < LLD < LLD 0 I Zn-65 6 260 < LLD N/A < LLD < LLD 0 I Cs-134 6 130 < LLD N/A < LLD < LLD 0 Cs-137 6 150 < LLD N/A < LLD < LLD 0 I

I 26

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2017 I Medium or Docket No. 50-280-281 Indicator Page 7 of7 Control I Pathway Sampled (Units)

Analysis Type ITotal No. LLD Locations Mean Range Location with Highest Mean IDistance Name Direction I Mean Range Locations Mean Range Non-Routine Reported Measurements I Crabs (pCilkg wet)

Gamma K-40 1450 (1/1) SD 1.3 mi 1450 (1/1) N/A 0 (1450 - 1450) NNW (1450 - 1450)

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

I I

I 27

I I 3.2 Analytical Results of 2017 REMP Samples Radiological analyses of environmental media characteristically approach and frequently I 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. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times I that listed.

uncertainty.

Results are considered positive when the measured value exceeds 2cr I 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 I Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the SurryODCM.

I Data are given according to sample type as indicated below.

1. Gamma Exposure Rate

2. Air Particulates, Weekly Gross Beta Radioactivity I 3.

4.

Air Particulates, Weekly I-131 Air Particulates, Quarterly Gamma Spectroscopy

5. Animal Milk I 6.

7.

Food Products Well Water

8. River Water I 9.

10.

Silt Shoreline Sediment

11. Fish I 12.

13.

Oysters Clams

14. Crabs I

I I

I 28

I TABLE 3-2: GAMMA EXPOSURE RATE Surry Power Station, Surry County, Virginia- 2017 I MDDQ:: 3 X O"Q = 3 X 1.0 = 3 (5)

MDDA = 3 x (JA :: 3 X 2.8 = 8.8 (10)

Note: IF MDDQ < 5 mR, THEN MDDQ rounded to 5 mR (ANSI N13.37)

Note: IF MDDA < 10 mR, THEN MDDA rounded to 10 mR (ANSI N13.37)

I Moni-toring Loca-Quarterly Baseline, BQ Normalized Quarterly Monitoring Data, MQ (mrem per standard Quarterly Facility Dose,-

FQ:: MQ- BQ Annual Base-line, BA Annual Moni-toring Annual Facility Dose,-

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

I (mrem) 1 2 3 4 1 2 3 4 MA (mrem)

MA-BA (mrem) 2 19.8 19.7 18.2 V 20.9 ND ND N/A ND 79.4 78.5 ND I 3 4

19.1 17.7 19.7 18.2 18.8 17.3 20.6 19.4 20.3 18.8 ND ND ND ND ND ND ND ND 76.2 71.0 79.5 73.7 ND ND 5 18.9 19.1 17.3 20.6 20.3 ND ND ND ND 75.6 77.4 ND I 6 7

8 18.4 18.6 16.9 17.9 18.5 17.3 16.7 17.9 16.4 19.4 19.7 19.1 20.3 20.0 17.9 ND ND ND ND ND ND ND ND ND ND ND ND 73.6 74.2 67.8 74.3 76.1 70.7 ND ND ND 94.0 ND I 9 10 11 23.1 18.2 16.0 23.7 18.2 16.1 22.1 16.4 15.5 24.3 18.8 17.3 24.0 18.8 17.0 ND ND ND ND ND ND ND ND ND ND ND ND 92.5 72.6 63.8 72.2 65.8 ND ND 12 16.6 16.4 15.2 17.6 17.9 ND ND ND ND 66.2 67.0 ND I 13 14 18.5 17.8 19.4 18.2 17.6 17.0 20.0 19.1 20.0 19.1 ND ND ND ND ND ND ND ND 73.8 71.1 77.0 73.4 ND ND 15 18.4 18.8 17.9 20.0 20.0 ND ND ND ND 73.5 76.7 ND I 16 18 19 16.9 14.3 15.4 17.0 15.2 15.8 16.4 14.9 14.9 18.2 15.8 16.7 17.6 15.8 16.7 ND ND ND ND ND ND ND ND ND ND ND ND 67.3 57.1 61.6 69.2 61.6 64.0 ND ND ND 58.2 ND I 20 21 22 14.3 15.0 13.0 14.6 16.1 13.7 13.3 14.6 12.7 14.9 16.1 14.3 15.5 16.4 14.0 ND ND ND ND ND ND ND ND ND ND ND ND 57.1 59.8 52.2 63.1 54.6 ND ND 23 17.8 18.8 17.9 19.4 19.7 ND ND ND ND 71.4 75.8 ND I 24 25 14.7 18.1 14.9 17.3 14.3 16.7 15.8 18.5 15.8 19.4 ND ND ND ND ND ND ND ND 58.9 72.4 60.7 71.9 ND ND 26 15.6 16.1 14.9 16.4 16.7 ND ND ND ND 62.3 64.0 ND I 27 28 29 14.6 14.1 13.1 15.2 14.6 13.3 14.3 13.7 12.4 15.5 14.9 14.0 15.5 15.2 14.3 ND ND ND ND ND ND ND ND ND ND ND ND 58.3 56.5 52.6 60.4 58.2 54.0 ND ND ND ND ND 58.2 ND I 30 31 32 14.4 12.2 15.2 14.3 12.1 15.2 13.7 12.1 14.0 14.9 m

15.5 15.5 13.3 16.1 ND ND ND ND ND ND N/A ND ND ND 57.6 49.0 60.7 50.2 60.7 ND ND 33 14.0 14.6 14.0 15.8 16.4 ND ND ND ND 56.2 60.7 ND I 34 35 15.9 18.3 16.4 19.7 15.5 17.6 17.6 20.3 17.3 20.6 ND ND ND ND ND ND ND ND 63.5 73.4 66.7 78.3 ND ND 36 18.5 18.8 17.9 19.7 20.3 ND ND ND ND 73.8 76.7 ND I 37 38 39 15.3 21.0 14.8 15.8 21.2 15.5 14.6 18.8 14.9 16.4 20.6 16.1 16.4 21.8 15.8 ND ND ND ND ND ND ND ND ND ND ND ND 61.3 83.9 59.1 63.1 82.5 62.2 ND ND ND 1* 40 41 16.1 21.7 16.4 21.5 15.5 21.2 17.0 23.1 17.0 22.8 ND ND ND ND ND ND ND ND 64.4 86.9 65.8 88.6 ND ND 42 16.2 17.3 16.7 17.3 17.3 ND ND ND ND 64.8 68.6 ND 43 14.3 14.6 13.3 15.5 14.9 ND ND ND ND 57.1 58.2 ND I *No= Not detected, where MQ < (BQ + MDDQ) bND = Not detected, where MA< (BA+ MDDA) d = Damaged TLDs; m = Missing TLDs; v = Vendor reports TLD not received I N/A= Missing or Damaged TLD Reading Not Available for Calculation Note: Table formatted in accordance with ANSI/HPS N13.37-2014, Environmental Dosimetry-Criteria for system Design and Implementation.

I 29

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2017 1.0E-3 pCi/m3 +/- 2 Sigma Page 1 of2 COLLECTION SAMPLING LOCATIONS DATE ss HIR BC ALL CP BASF FE NN-C January 03 13.4 +/- 2.46 9.8 +/- 2.23 10.3 +/- 2.30 8.21 +/- 2.11 9.91 +/- 2.26 7.82 +/- 2.07 9.45 +/- 2.18 13.5 +/- 2.4 January 10 20.5 +/- 3.03 13.5 +/- 2.64 13.5 +/- 2.70 13.1 +/- 2.62 11.9+/-2.62 11.5 +/- 2.54 13.3 +/- 2.68 14.0 +/- 2.7 January 17 15.2 +/- 2.71 13.8 +/- 2.63 16.3 +/- 2.83 11.5 +/- 2.48 11.9 +/- 2.57 11.4 +/- 2.49 9.80 +/- 2.41 11.1 +/- 2.44 January 24 9.41 +/- 2.47 6.66 +/- 2.29 9.60 +/- 2.52 9.68 +/- 2.46 9.18 +/- 2.44 9.23 +/- 2.44 6.54 +/- 2.27 8.80 +/- 2.42 January 31 10.9 +/- 2.55 11.5 +/- 2.57 11.2 +/- 2.51 9.54 +/- 2.36 12.1 +/- 2.52 12.1 +/-2.51 11.3 +/- 2.48 13.1 +/- 2.59 February 07 16.7 +/- 3.04 16.1 +/- 3.02 20.0 +/- 3.27 19.6 +/- 3.18 19.9 +/- 3.20 18.4 +/- 3.08 19.2 +/- 3.15 18.1 +/- 3.06 February 14 19.0 +/- 3.03 19.6 +/- 3.08 19.1 +/- 3.10 . 17.5 +/- 2.95 22.4 +/- 3.21 18.0 +/- 3.68 17.2 +/- 2.99 16.8 +/- 2.95 February 21 12.1 +/- 2.59 12.2 +/- 2.58 12.8 +/- 2.67 11.4+/-2.51 13.3 +/- 2.65 13.8 +/- 2.66 10.3 +/- 2.49 10.4 +/- 2.52 February 28 10.8 +/- 2.40 11.8 +/- 2.46 11.4 +/- 2.49 13.0 +/- 2.54 12.2 +/- 2.50 14.6 +/- 2.62 10.9 +/- 2.43 12.3 +/- 2.51 March 07 11.2 +/- 2.46 11.5 +/- 2.47 11.4 +/- 2.53 11.0 +/- 2.44 12.8 +/- 2.57 13.1 +/- 2.56 13.3 +/- 2.60 11.3+/-2.47 March 13 11.6 +/- 2.85 12.9 +/- 2.93 14.9 +/- 3.11 10.2 +/- 2.75 12.8 +/- 2.93 14.0 +/- 2.99 10.3 +/- 2.80 11.4 +/- 2.85 March 20 10.5 +/- 2.50 12.8 +/- 2.64 13.6 +/- 2.75 9.63 +/- 2.44 14.8 +/- 2.77 16.3 +/- 2.84 12.2 +/- 2.64 13.2 +/- 2.70 March 27 20.9 +/- 3.00 22.0 +/- 3.05 21.5 +/- 3.08 19.0 +/- 2.88 21.1+/-3.01 25.0 +/- 3.20 19.1 +/- 2.92 18.6 +/- 2.87 Qtr. Avg. +/- 2 s.d. 14.0 +/- 8.0 13.4 +/- 8.0 14.3 +/- 7.7 12.6 +/- 7.6 14.2 +/- 8.5 14.3 +/- 8.9 12.5 +/- 7.7 13.3 +/- 5.9 April 04 7.22 +/- 2.09 7.74 +/- 2.11 7.55 +/- 2.12 6.94 +/- 2.04 7.90 +/- 2.10 7.54 +/- 2.05 5.67 +/- 1.95 6.53 +/- 2.01 April 11 12.1 +/- 2.45 10.6 +/- 2.37 2.05 +/- 1.76 11.0 +/- 2.40 11.5 +/- 2.42 12.9 +/- 2.51 11.0 +/- 2.39 12.4 +/- 2.50 April 18 13.8 +/- 2.75 17.0 +/- 2.93 14.8 +/- 2.85 13.8 +/- 2.76 14.7 +/- 2.83 15.7 +/- 2.84 25.1 +/- 3.34 13.5 +/- 2.75 April 25 7.70 +/- 2.17 8.39 +/- 2.22 9.80 +/- 2.35 8.48 +/- 2.23 8.17 +/- 2.21 8.78 +/- 2.22 5.58 +/- 2.02 10.0 +/- 2.34 May02 11.3 +/- 2.67 10.7 +/- 2.63 11.8 +/- 2.75 10.0 +/- 2.58 9.74 +/- 2.57 12.6 +/- 2.68 9.03 +/- 2.51 10.0 +/- 2.55 May09 9.42 +/- 2.32 9.34 +/- 2.30 7.68 +/- 2.23 8.09 +/- 2.23 7.89 +/- 2.22 9.84 +/- 2.36 8.07 +/- 2.29 9.46 +/- 2.33 May 16 9.67 +/- 2.44 9.28 +/- 2.40 9.61 +/- 2.45 9.89 +/- 2.44 10.2 +/- 2.46 10.6 +/- 2.50 8.65 +/- 2.39 7.66 +/- 2.28 May23 16.2 +/- 2.72 15.8 +/- 2.68 16.4 +/- 2.76 12.7 +/- 2.51 15.1 +/- 2.65 16.0 +/- 2.68 12.1 +/- 2.50 13.9 +/- 2.57 May30 10.2 +/- 2.61 12.4 +/- 2.74 11.3 +/- 2.71 9.39 +/- 2.55 11.4 +/- 2.68 12.4 +/- 2.71 10.0 +/- 2.62 11.6 +/- 2.68 June 06 18.2 +/- 3.03 17.8 +/- 2.99 17.6 +/- 3.01 15.4 +/- 2.85 17.6 +/- 2.97 20.9 +/- 3.12 14.6 +/- 2.82 16.2 +/- 2.87 June 12 10.3 +/- 2.84 9.16 +/- 2.75 10.2 +/- 2.86 9.88 +/- 2.80 9.26 +/- 2.78 10.6 +/- 2.85 8.52 +/- 2.77 8.48 +/- 2.74 June 20 15.5 +/- 2.53 17.9 +/- 2.65 12.4 +/- 2.38 14.4 +/- 2.45 17.8 +/- 2.64 19.3 +/- 2.70 14.9 +/- 2.50 13.6 +/- 2.40 June 26 13.3 +/- 2.99 11.8 +/- 2.89 13.0 +/- 3.03 10.9 +/- 2.82 13.0 +/- 2.97 16.3 +/- 3.15 13.1 +/- 3.00 10.4 +/- 2.81 Qtr. Avg. +/- 2 s.d. 11.9 +/- 6.7 12.1 +/- 7.4 11.1 +/- 8.2 10.8 +/- 5.1 11.9 +/- 7.0 13.3 +/- 8.1 11.3 +/- 10.2 11.1 +/- 5.6 30

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2017 1.0E-3 pCi/m3 +/- 2 Sigma Page 2 of2 COLLECTION SAMPLING LOCATIONS DATE ss HIR BC ALL CP BASF FE NN July 03 14.3 +/- 2.67 11.5 +/- 2.49 11.7+/-2.56 10.2 +/- 2.39 13.4 +/- 2.62 13.1 +/- 2.56 10.9 +/- 2.45 9.94 +/- 2.37 July 11 14.8 +/- 2.44 14.4 +/- 2.40 12.0 +/- 2.30 13.6 +/- 2.36 12.3 +/- 2.28 14.7 +/- 2.41 12.5 +/- 2.31 12.6 +/- 2.31 July 18 12.1 +/- 2.83 13.7 +/- 2.92 13.1 +/- 2.94 11.7+/-2.77 16.1 +/- 3.05 19.2 +/- 3.20 14.7 +/- 3.01 10.1 +/- 2.75 July 24 19.0 +/- 3.26 19.5 +/- 3.26 19.4 +/- 3.33 19.3 +/- 3.25 20.5 +/- 3.32 24.1 +/- 3.48 18.1 +/- 3.19 16.5 +/- 3.09 August 01 10.0 +/- 2.19 8.40 +/- 2.07 10.2 +/- 2.24 8.98 +/- 2.10 12.8 +/- 2.34 11.1 +/- 2.21 8.03 +/- 2.03 7.12 +/- 1.97 August 08 10.6 +/- 2.58 12.6 +/- 2.69 11.7+/-2.70 9.28 +/- 2.49 12.5 +/- 2.71 14.9 +/- 2.84 10.5 +/- 2.59 11.8+/-2.70 August 15 14.9 +/- 2.57 12.6 +/- 2.42 14.0 +/- 2.56 10.6 +/- 2.29 13.4 +/- 2.48 14.1 +/- 2.51 9.97 +/- 2.25 11.7 +/- 2.36 August 22 17.1 +/- 2.89 17.3 +/- 2.90 15.5 +/- 2.93 17.7 +/- 2.97 17.0 +/- 2.94 20.6 +/- 3.12 18.6 +/- 3.05 17.3 +/- 2.95 August 29 14.9 +/- 3.00 14.3 +/- 2.95 13.8 +/- 2.92 12.6 +/- 2.78 16.5 +/- 2.99 18.9 +/- 3.10 16.9 +/- 3.04 13.7 +/- 2.84 September 05 13.2 +/- 2.68 10.8 +/- 2.52 12.5 +/- 2.69 10.5 +/- 2.50 15.0 +/- 2.82 15.0 +/- 2.75 15.2 +/- 2.79 14.3 +/- 2.73 September 11 11.9 +/- 2.78 10.7 +/- 2.69 10.4 +/- 2.74 9.23 +/- 2.60 11.5+/-2.74 14.5 +/- 2.96 12.8 +/- 2.89 12.5 +/- 2.86 September 18 15.7 +/- 2.76 13.4 +/- 2.62 14.4 +/- 2.75 12.6 +/- 2.57 15.1 +/- 2.72 17.1 +/- 2.81 16.1 +/- 2.78 12.8 +/- 2.58 September 25 18.4 +/- 2.98 16.0 +/- 2.85 16.8 +/- 2.94 13.9 +/- 2.72 19.4 +/- 3.02 20.2 +/- 3.05 18.4 +/- 2.99 15.6 +/- 2.81 Qtr. Avg. +/- 2 s.d. 14.4 +/- 5.6 13.5 +/- 5.9 13.5 +/- 5.2 12.3 +/- 6.4 15.0 +/- 5.6 16.7 +/- 7.3 14.1 +/- 7.1 12.8 +/- 5.6 October 03 10.8 +/- 2.25 3.68 +/- 1.75 9.83 +/- 2.22 9.88 +/- 2.18 10.3 +/- 2.20 11.9 +/- 2.27 12.1 +/- 2.31 9.25 +/- 2.10 October 10 8.68 +/- 2.37 -1.37 +/- 1.59 E 11.3 +/- 2.59 7.59 +/- 2.29 12.6 +/- 2.61 4.50 +/- 2.09 11.2 +/- 2.56 10.4 +/- 2.49 October 17 7.26 +/- 2.31 2.45 +/- 1.89 A 4.36 +/- 2.16 5.04 +/- 2.14 5.54 +/- 2.19 6.91 +/- 2.28 5.87 +/- 2.24 4.50 +/- 2.13 October 24 25.1 +/- 3.42 19.2 +/- 3.21 19.4 +/- 3.27 18.5 +/- 3.16 21.8 +/- 3.30 27.2 +/- 3.55 22.2 +/- 3.35 18.0 +/- 3.12 October 31 11.3 +/- 2.47 12.6 +/- 2.55 10.9 +/- 2.44 11.5 +/- 2.43 13.6 +/- 2.56 13.5 +/- 2.54 12.5 +/- 2.49 11.6 +/- 2.43 November 07 16.6 +/- 2.83 16.7 +/- 2.84 17.2 +/- 2.91 19.1 +/- 2.95 19.9 +/- 2.98 17.9 +/- 2.85 17.3 +/- 2.85 16.3 +/- 2.76 November 14 12.9 +/- 2.39 12.3 +/- 2.35 12.3 +/- 2.38 12.6 +/- 2.37 12.6 +/- 2.37 14.0 +/- 2.45 16.7 +/- 2.64 11.6 +/- 2.30 November 21 15.6 +/- 2.82 14.5 +/- 2.74 15.5 +/- 2.87 18.5 +/- 2.96 15.9 +/- 2.84 18.0 +/- 2.92 17.2 +/- 2.93 11.9 +/- 2.60 November 28 23.4 +/- 3.14 19.1 +/- 2.92 20.1 +/- 3.02 25.1 +/- 3.23 21.3 +/- 3.02 25.6 +/- 3.22 22.1 +/- 3.10 21.1 +/- 3.03 December 05 21.6 +/- 3.13 24.0 +/- 3.23 23.2 +/- 3.26 24.5 +/- 3.27 25.0 +/- 3.30 23.0 +/- 3.14 20.8 +/- 3.10 16.5 +/- 2.87 December 12 19.2 +/- 2.87 19.1 +/- 2.86 16.8 +/- 2.86 14.6 +/- 2.68 16.8 +/- 2.81 22.7 +/- 3.12 16.9 +/- 2.87 14.8 +/- 2.70 December 19 15.6 +/- 2.81 17.4 +/- 2.88 16.6 +/- 2.84 18.1 +/- 2.86 16.7 +/- 2.78 20.4 +/- 2.95 17.1 +/- 2.82 17.2 +/- 2.82 December 26 16.3 +/- 2.76 22.7+/-3.11 19.1 +/- 3.03 20.9 +/- 3.06 17.5 +/- 2.88 22.4 +/- 3.13 20.5 +/- 3.07 18.1 +/- 2.92 A= <MDC; E = Air sample pump running, but no flow or vac.

Qtr. Avg. +/- 2 s.d. 16.0 +/- 11.4 14.0 +/- 15.9 15.1 +/- 10.3 15.8 +/- 12.5 16.1 +/- 10.5 17.5 +/- 14.0 16.3 +/- 9.6 13.9 +/- 9.1 Ann. Avg. +/- 2 s.d. 14.0 +/- 8.4 13.3 +/- 9.9 13.5 +/- 8.4 12.9 +/- 8.9 14.3 +/- 8.5 15.5 +/- 10.3 13.5 +/- 9.3 12.8 +/- 6.9 31

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2017 1.0E-3 pCi/m3 +/- 2 Sigma Page 1 of2 COLLECTION SAMPLING LOCATIONS DATE 55 HIR BC ALL CP BASF FE NN-C January 03 3.41 +/- 15.4 3.38 +/- 15.3 3.45 +/- 15.6 3.33 +/- 15.1 -6.18 +/- 15.7 -5.93 +/- 15.0 -5.94 +/- 15.1 -5.87 +/- 14.9 January 10 -8.34 +/- 27.2 -8.34 +/- 27.2 -8.58 +/- 28.0 -8.33 +/- 27.2 -7.71 +/- 19.4 -7.47 +/- 18.8 -7.57 +/- 19.0 -7.46 +/- 18.7 January 17 5.73 +/- 16.3 5.73 +/- 16.3 5.89 +/- 16.8 5.68 +/- 16.2 4.01 +/- 13.3 3.90 +/- 12.9 3.94 +/- 13.1 3.81 +/- 12.6 January 24 6.35 +/- 18.8 6.35 +/- 18.7 6.47 +/- 19.1 6.25 +/- 18.5 4.35 +/- 18.8 4.32 +/- 18.7 4.33 +/- 18.7 4.30 +/- 18.6 January 31 17.1 +/- 18.8 16.9 +/- 18.7 16.6 +/- 18.3 16.0 +/- 17.7 2.89 +/- 13.0 2.86 +/- 12.9 2.90 +/- 13.1 2.88 +/- 13.0 February 07 1.12 +/- 16.8 1.13 +/- 16.9 1.15 +/- 17.2 1.12 +/- 16.7 12.9 +/- 15.5 12.6 +/- 15.1 12.7 +/- 15.3 12.4 +/- 15.0 February 14 -3.85 +/- 24.3 -3.89 +/- 24.5 -3.97 +/- 25.1 -3.85 +/- 24.3 5.56 +/- 18.9 7.42 +/- 25.3 5.62 +/- 19.2 5.57 +/- 19.0 February 21 3.58 +/- 24.4 3.56 +/- 24.3 3.65 +/- 24.9 3.49 +/- 23.8 0.48 +/- 15.8 0.47 +/- 15.6 0.48 +/- 15.9 0.49+/-16.1 February 28 -1.23 +/- 17.8 -1.23 +/- 17.7 -1.26 +/- 18.2 -1.22 +/- 17.6 9.04 +/- 16.4 8.91 +/- 16.2 9.06 +/- 16.5 8.96 +/- 16.3 March 07 1.68 +/- 23.0 1.67 +/- 22.9 1.72 +/- 23.6 1.67 +/- 22.8 16.5 +/- 19.8 16.2 +/- 19.4 16.4 +/- 19.7 16.3 +/- 19.6 March 13 1.61 +/- 15.6 1.61 +/- 15.6 1.66 +/- 16.0 1.59 +/- 15.4 1.64 +/- 19.8 1.63 +/- 19.6 1.66 +/- 19.9 1.64+/-19.7 March 20 -5.16 +/- 13.9 -5.16 +/- 13.9 -5.33 +/- 14.3 -5.14 +/- 13.8 0.66 +/- 18.5 0.65 +/- 18.3 0.66 +/- 18.6 0.66 +/- 18.5 March 27 -0.39 +/- 14.2 -0.38 +/- 14.1 -0.40 +/- 14.6 -0.38 +/- 14.1 5.96 +/- 10.4 5.91 +/- 10.3 5.97 +/- 10.4 5.88 +/- 10.2 April 04 -5.65 +/- 18.4 -5.63 +/- 18.3 -5.68 +/- 18.5 -5.51 +/- 17.9 19.2 +/- 16.0 A 7.27 +/- 6.07 A 19.0 +/- 15.8 A 18.9 +/- 15.8 A April 11 2.11 +/- 4.58 5.02 +/- 10.9 5.12 +/- 11.1 5.03 +/- 10.9 2.57 +/- 9.67 2.56 +/- 9.63 2.56 +/- 9.63 2.58 +/- 9.73 April 18 2.17 +/- 10.3 2.17 +/- 10.3 2.20 +/- 10.4 2.16 +/- 10.3 1.67+/-10.6 1.63 +/- 10.4 1.65 +/- 10.5 1.65 +/- 10.5 April 25 -5.11 +/- 13.8 -5.11 +/- 13.8 -5.20 +/- 14.0 -5.11 +/- 13.8 5.96 +/- 14.4 5.85 +/- 14.1 5.95 +/- 14.4 5.95 +/- 14.4 May02 0.02 +/- 18.3 0.02 +/- 18.2 0.02 +/- 18.7 0.02 +/- 18.1 -4.55 +/- 20.8 -4.40 +/- 20.1 -4.47 +/- 20.4 -4.42 +/- 20.2 May09 5.37 +/- 14.9 5.32 +/- 14.8 5.42 +/- 15.1 5.32 +/- 14.8 5.65 +/- 19.2 5.65 +/- 19.2 5.80 +/- 19.7 5.63 +/- 19.1 May 16 3.79 +/- 14.8 3.76 +/- 14.7 3.82 +/- 15.0 3.75 +/- 14.7 -3.48 +/- 13.1 -3.51 +/- 13.2 -3.53 +/- 13.2 -3.43 +/- 12.9 May23 3.28 +/- 9.08 3.25 +/- 8.99 3.33 +/- 9.21 3.26 +/- 9.01 2.86 +/- 9.95 2.81 +/- 9.78 2.89 +/- 10.1 2.82 +/- 9.81 May30 0.46 +/- 15.4 0.46 +/- 15.4 0.47 +/- 15.6 0.46 +/- 15.3 -0.79 +/- 16.0 -0.30 +/- 6.09 -0.80+/-16.1 -0.78 +/- 15.7 June 06 3.04 +/- 8.88 3.00 +/- 8.77 3.05 +/- 8.90 2.99 +/- 8.73 -0.68 +/- 11.2 -0.67 +/- 11.0 -0.29 +/- 4.72 -0.66 +/- 11.0 June 12 -6.09 +/- 12.1 -6.03 +/- 12.0 -6.15 +/- 12.2 -6.03 +/- 12.0 1.92 +/- 7.44 1.89 +/- 7.34 1.94 +/- 7.52 1.90 +/- 7.39 June 20 -0.46 +/- 13.2 -0.46 +/- 13.1 -0.47 +/- 13.4 -0.46 +/- 13.0 -12.8 +/- 14.0 -5.32 +/- 5.82 -0.13 +/- 14.1 -12.7 +/- 13.9 June 26 4.77 +/- 21.6 4.75 +/- 21.5 4.90 +/- 22.2 4.72 +/- 21.4 -8.10 +/- 15.4 -8.02 +/- 15.2 -8.14 +/- 15.5 -8.05 +/- 15.3 A: <MDC 32

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2017 1.0E-3 pCi/m3 +/- 2 Sigma Page 2 of2 COLLECTION SAMPLING LOCATIONS DATE ss HIR BC ALL CP BASF FE NN-C July 03 -5.15 +/- 15.7 -5.10 +/- 15.6 -5.26 +/- 16.0 -5.04 +/- 15.4 -9.20 +/- 21.6 -8.93 +/- 21.0 -9.04 +/- 21.3 -8.95 +/- 21.0 July 11 8.92 +/- 18.7 8.86 +/- 18.6 9.00 +/- 18.9 8.83 +/- 18.5 15.6 +/- 25.0 15.4 +/- 24.7 15.7 +/- 25.1 15.6 +/- 24.9 July 18 0.44 +/- 13.1 0.44 +/- 13.1 0.45 +/- 13.3 0.43 +/- 12.8 -9.61 +/- 14.7 -9.53 +/- 14.6 -9.69 +/- 14.8 -9.66 +/- 14.8 July 24 1.74 +/- 20.7 1.71 +/- 20.4 1.77+/-21.1 1.71 +/- 20.3 -3.36 +/- 16.7 -3.32 +/- 16.5 -3.36 +/- 16.7 -3.34 +/- 16.6 August 01 -5.21 +/- 20.2 -5.17 +/- 20.0 -5.31 +/- 20.6 -5.14 +/- 19.9 3.81 +/- 16.7 3.72 +/- 16.3 3.74 +/- 16.4 3.74 +/- 16.4 August 08 12.5 +/- 13.3 12.5 +/- 13.2 12.8 +/- 13.6 12.4 +/- 13.1 -3.75 +/- 16.9 -3.73 +/- 16.8 -3.72 +/- 16.8 -3.77 +/- 17.0 August 15 -8.20 +/- 15.9 -8.15 +/- 15.8 -8.40 +/- 16.3 -8.14 +/- 15.8 7.10+/-17.5 7.05 +/- 17.3 7.07 +/- 17.4 7.02 +/- 17.3 August 22 -2.51 +/- 14.1 -2.50 +/- 14.1 -2.69 +/- 15.1 -2 ..60 +/- 14.6 -6.69 +/- 13.4 -6.67 +/- 13.4 -6.74 +/- 13.5 -6.62 +/- 13.3 August 29 -14.7 +/- 23.1 -14.5 +/- 22.8 -14.6 +/- 23.0 -14.1 +/- 22.2 -4.62 +/- 17.4 -2.49 +/- 9.39 -4.67 +/- 17.6 -4.57 +/- 17.3 September 05 -6.28 +/- 22.2 -6.25 +/- 22.1 -6.47 +/- 22.9 -6.23 +/- 22.0 2.05 +/- 21.3 1.97 +/- 20.4 2.00 +/- 20.8 1.98 +/- 20.6 September 11 8.21 +/- 19.3 8.14 +/- 19.1 8.41 +/- 19.7 3.41 +/- 7.98 -5.21 +/- 14.9 -5.27 +/- 15.1 -5.33 +/- 15.2 -5.29 +/- 15.1 September 18 5.04 +/- 16.8 4.99 +/- 16.6 5.17 +/- 17.2 4.99 +/- 16.6 -0.34 +/- 13.3 -0.34 +/- 13.2 -0.34 +/- 13.4 -0.34 +/- 13.3 September 25 0.56 +/- 16.4 0.55 +/- 16.4 0.57 +/- 16.8 0.55 +/- 16.2 3.13 +/- 13.2 3.11 +/- 13.1 3.15 +/- 13.3 3.10 +/- 13.1 October 03 6.45 +/- 13.9 6.38 +/- 13.7 E 6.59 +/- 14.2 6.39 +/- 13.7 -10.3+/-11.7 -10.0 +/- 11.3 -10.2 +/- 11.6 -9.96 +/- 11.3 October 10 -12.2 +/- 23.3 -12.2 +/- 23.2 -12.5 +/- 23.9 -12.1 +/- 23.1 -23.1 +/- 20.7 -22.9 +/- 20.5 -23.3 +/- 20.9 -22.9 +/- 20.5 October 17 -1.11 +/- 16.1 -1.05 +/- 15.3 -1.14 +/- 16.5 -1.09+/-15.9 6.75 +/- 9.94 6.72 +/- 9.89 6.83 +/- 10.1 6.76 +/- 9.95 October 24 3.09 +/- 19.0 3.15 +/- 19.4 3.28 +/- 20.2 3.20 +/- 19.7 1.27 +/- 13.6 1.26 +/- 13.6 1.28 +/- 13.7 1.27 +/- 13.6 October 31 -0.18 +/- 12.6 -0.19 +/- 12.6 -0.19+/-12.7 -0.18 +/- 12.3 15.9 +/- 17.0 15.7 +/- 16.8 15.8 +/- 16.9 15.7 +/- 16.8 November 07 10.3 +/- 20.3 10.4 +/- 20.3 10.6 +/- 20.7 10.2 +/- 20.1 1.17 +/- 15.2 1.15 +/- 14.9 1.16 +/- 15.1 1.14 +/- 14.8 November 14 -2.29 +/- 15.9 -2.28 +/- 15.8 -2.32 +/- 16.1 -2.28 +/- 15.8 -3.88 +/- 11.4 -3.86 +/- 11.4 -3.93 +/- 11.6 -3.84 +/- 11.3 November 21 1.00 +/- 14.6 0.99 +/- 14.5 1.02 +/- 15.0 0.99 +/- 14.5 2.84 +/- 11.2 2.80 +/- 11.0 2.86 +/- 11.3 2.80 +/- 11.1 November 28 -12.2 +/- 16.2 -12.2 +/- 16.2 -12.5 +/- 16.6 -12.2 +/- 16.2 8.23 +/- 11.1 8.16 +/- 11.0 8.36 +/- 11.3 8.27 +/- 11.2 December 05 4.73 +/- 16.8 4.68 +/- 16.6 4.82+/-17.1 4.70 +/- 16.7 5.22 +/- 12.4 5.04 +/- 12.0 5.20 +/- 12.4 5.16 +/- 12.3 December 12 14.8 +/- 17.2 14.7 +/- 17.2 15.8 +/- 18.4 15.4 +/- 17.9 1.43 +/- 10.5 1.43 +/- 10.4 1.46 +/- 10.7 1.42 +/- 10.4 December 19 4.62 +/- 14.8 4.54 +/- 14.5 4.57 +/- 14.6 4.42 +/- 14.2 3.04 +/- 10.2 3.00 +/- 10.0 3.06 +/- 10.2 2.55 +/- 8.53 December 26 -3.08 +/- 8.60 -7.32 +/- 20.5 -7.78 +/- 21.8 -7.56 +/- 21.1 20.2 +/- 20.0 A 20.2 +/- 19.9 A 20.5 +/- 20.3 A 20.2 +/- 20.0 A A: <MDC; E: Air sample pump running, but no flow or vac.

33

I I

TABLE 3-5: GAMMA EMITTER CONCENTRATION IN FILTERED AIR I Surry Power Station, Surry County, Virginia - 2017 1.0E-3 pCi/m3 +/- 2 Sigma Page I of I I SAMPLING LOCATIONS NUCLIDE FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER AVERAGE

+/-2SIGMA ss I Cs-134 Cs-137 Be-7

-0.32 +/- 0.85

-0.15 +/- 0.71 200 +/- 29.3

-0.24 +/- 0.65 0.16 +/- 0.52 142 +/- 23.2

-0.62 +/- 1.58

-0.49 +/- 1.34 128 +/- 40.8

-0.35 +/- 0.65 0.06 +/- 0.56 115 +/- 19.9 146 +/- 75.0 K-40 23.7 +/- 21.6 +/- 23.7 21.6 I HIR Cs-134 Cs-137 0.74 +/- 1.01

-0.22 +/- 0.89

-0.14 +/- 0.73

-0.42 +/- 0.70

-0.38 +/- 0.69 0.04 +/- 0.63

-0.87 +/- 0.88

-0.45 +/- 0.62 Be-7 171 +/- 27.1 148 +/- 30.0 127 +/- 23.7 137 +/- 25.7 146 +/- 37.8 I BC Cs-134 Cs-137

-0.74 +/- 0.73 0.09 +/- 0.51 0.44 +/- 1.47

-0.49 +/- 1.06

-0.34 +/- 1.07 0.35 +/- 0.85

-0.24 +/- 1.54 0.22 +/- 1.09 I ALL Be-7 Cs-134 168 +/- 24.4

-0.55 +/- 0.81 157 +/- 36.4

-0.17 +/- 0.97 97.8 +/- 29.2

-0.005 +/- 1.27 132 +/- 31.4

-0.41 +/- 0.83 139 +/- 62.3 Cs-137 1.05 +/- 0.63A 0.19 +/- 0.84 -0.31 +/- 1.06 -0.31 +/- 0.66 I Be-7 181 +/- 30.8 125 +/- 27.1 102 +/- 39.9 136 +/- 24.6 136 +/- 66.4 CP Cs-134 0.41 +/- 0.88 0.44 +/- 1.11 0.11 +/- 0.93 0.01 +/- 1.27 I Cs-137 Be-7 0.28 +/- 0.72 150 +/- 23.8

-0.19 +/- 0.96 143 +/- 35.7

-0.76 +/- 0.81 135 +/- 27.4

-0.03 +/- 1.12 102 +/- 34.7 133 +/- 42.5 I BASF Cs-134 Cs-137 Be-7

-0.65 +/- 1.38

-0.40 +/- 1.27 175 +/- 41.8

-0.36 +/- 0.87

-0.78 +/- 0.85 201 +/- 28.7

-0.41 +/- 0.73 0.03 +/- 0.52 154 +/- 24.5

-0.17 +/- 0.77 0.69 +/- 0.76 122 +/- 21.8 163 +/- 66.8 I FE Cs-134 Cs-137

-0.57 +/- 0.88 0.37 +/- 0.68 0.76 +/- 0.64

-0.18 +/- 0.53 0.59 +/- 0.83 0.11 +/- 0.66 0.00 +/- 0.87 0.78 +/- 0.88 Be-7 159 +/- 27.1 138 +/- 23.3 140 +/- 27.0 153 +/- 24.1 148 +/- 20.3 I

NN-C Cs-134 -0.27 +/- 1.39 -0.39 +/- 0.80 0.25 +/- 0.85 -0.05 +/- 0.63 I Cs-137 Be-7 1.09 +/- 1.11 139 +/- 34.0

-0.65 +/- 0.82 150 +/- 25.9

-0.33 +/- 0.70 122 +/- 24.2

-0.20 +/- 0.61 124 +/- 20.3 134 +/- 26.5 A: <MDC I

I I

I I 34

I I TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK I Surry Power Station, Surry County, Virginia - 2017 pCi/Liter +/- 2 Sigma Page 1 of3 COLONIAL LOVERS I NUCLIDE EPPS PARKWAY RETREAT-C JANUARY I Cs-134 Cs-137 Ba-140

-8.28 2.08 14.1

+/-

6.80 5.98 21.4

-4.44 1.10

-3.48

+/-

3.74 3.88 12.9

-2.01 4.04 0.49

+/-

4.70 5.09 19.9 I La-140 1-131 K-40 1.90

-0.13 1,310

+/-

5.11 0.33 223

-0.86 0.10 1,170

+/-

4.15 0.44 143

-0.49 0.06 1,560

+/-

4.22 0.36 184 I FEBRUARY Cs-134 -7.61 +/- 5.63 3.68 +/- 6.52 -1.76 +/- 6.57 I Cs-137 Ba-140 La-140 2.03

-2.61 2.24

+/-

5.25 17.2 5.98 1.41

-2.96 5.16

+/-

6.48 22.2 7.35 3.15

-1.39

-3.57

+/-

5.54 18.4 4.69 I 1-131 K-40 0.19 1400

+/-

0.28 208 0.43 1280

+/-

0.33A 219

-0.05 1820

+/-

0.23 209 MARCH I Cs-134 Cs-137

. Ba-140 4.10

-2.01

+/-

4.75 5.83 2.69 0.19

+/-

5.02 5.48 1.99

-2.63

+/-

5.55 5.05 20.1 +/- 21.7 -2.66 +/- 18.8 -4.37 +/- 16.7 I La-140 1-131 K-40 3.85

-0.10 1450

+/-

5.92 0.21 210

-0.30 0.10 1280

+/-

5.52 0.32 190 3.36 0.25 1520

+/-

6.42 0.22A 196 Sr-89 1.85 +/- 1.89 I Sr-90 1.12 +/- 0.33 I APRIL Cs-134 Cs-137 2.59

-0.74

+/-

4.73 3.95 1.83 0.81

+/-

5.14 4.15 4.70 3.42

+/-

5.32 5.06 Ba-140 -0.95 +/- 15.8 2.58 +/- 26.2 -9.35 +/- 21.9 I La-140 1-131 1.18 0.04

+/-

5.07 0.09 3.50

-0.36

+/-

6.47 0.32 4.64

-0.01

+/-

7.56 0.19 K-40 1290 +/- 154 1390 +/- 212 1280 +/- 194 I A: <MDC I

I I

I 35

I I TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK I Surry Power Station, Surry County, Virginia - 2017 pCi/Liter +/- 2 Sigma Page 2 of3 I

COLONIAL LOVERS NUCLIDE EPPS PARKWAY RETREAT-C MAY I Cs-134 Cs-137 Ba-140

-1.66

-0.33 13.3

+/-

4.52 4.07 17.2 1.73 3.69 2.89

+/-

4.84 4.34 17.2 2.13

-0.96

-5.74

+/-

4.49 4.61 20.8 I La-140 1-131 K-40

-1.50

-0.34 1360

+/-

6.40 0.46 164 2.27

-0.45 1450

+/-

5.81 0.33 167 0.03

-0.08 1610

+/-

5.31 0.24 195 I JUNE Cs-134 0.00 +/- 4.93 -3.70 +/- 4.53 -6.82 +/- 5.30 I Cs-137 Ba-140 La-140

-0.85 11.4 0.72

+/-

5.53 22.1 6.71

-1.31

-2.18

-1.26

+/-

4.57 17.5 5.05

-0.33

-0.71

-0.95

+/-

5.67 22.2 6.24 I 1-131 K-40 Sr-89 0.47 1510

+/-

0.51 194

-0.04 1510

-5.36

+/-

0.38 166 2.91

-0.08 1680

+/-

0.39 189 Sr-90 1.73 +/- 0.64 I JULY Cs-134 -2.71 +/- 5.03 -0.99 +/- 5.23 -1.15 +/- 5.23 I Cs-137 Ba-140 La-140

-0.90

-9.28

-0.89

+/-

5.20 18.9 6.92 1.82

-1.66 3.17

+/-

5.75 26.5 7.26 2.14 0.89 4.45

+/-

5.31 21.5 7.59 1-131 -0.09 +/- 0.43 0.43 +/- 0.53 -1.01 +/- 0.53 I K-40 1440 +/- 191 1360 +/- 171 1690 +/- 207 AUGUST I Cs-134 Cs-137 Ba-140

-2.09 4.24 25.0

+/-

5.67 4.87 25.9

-0.721

-1.11 5.95

+/-

5.91 5.49 24.5

-1.02 1.52

-1.81

+/-

6.31 5.60 29.6 La-140 -6.10 +/- 9.75 3.88 +/- 8.01 -1.42 +/- 5.90 I 1-131 K-40 0.58 1490

+/-

0.48 A 242 0.00 1410

+/-

0.55 185

-0.14 1500

+/-

0.34 175 I A: <MDC I

I I

I 36

I I TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK I Surry Power Station, Surry County, Virginia - 2017 pCi/Liter +/- 2 Sigma Page 3 of3 COLONIAL LOVERS I NUCLIDE EPPS PARKWAY RETREAT-C SEPTEMBER I Cs-134 Cs-137 Ba-140

-1.16 0.76

-1.48

+/-

4.98 5.31 25.9

-1.84 2.30

-3.29

+/-

4.89 5.02 25.1

-2.14

-1.41

-12.9

+/-

6.17 5.78 29.8

+/-

I La-140 1-131 K-40

-2.92

-0.13 1260

+/-

8.95 0.40 212

-8.56

-0.11 1620

+/-

6.97 0.50 212

-6.23 0.28 1870

+/-

8.53 0.31 204 Sr-89 1.39 +/- 2.53 I Sr-90 0.57 +/- 0.46 A OCTOBER I Cs-134 Cs-137 Ba-140

-1.53 1.27 26.1

+/-

6.08 5.50 20.3A

-1.54 2.16

-14.2

+/-

5.22 4.87 21.0 4.44

-1.01 3.22

+/-

5.66 5.17 21.1

+/-

I La-140 1-131 K-40

-2.11 0.07 1470

+/-

7.38 0.37 188 1.93

-0.05 1350

+/-

5.72 0.38 179

-2.43

-0.09 1580

+/-

5.16 0.45 180 I NOVEMBER Cs-134 1.05 +/- 6.91 5.53 +/- 7.04 5.89 +/- 6.43 Cs-137 3.08 +/- 5.53 0.93 +/- 6.04 2.93 +/- 4.40 I Ba-140 La-140 1-131 13.8

-0.05 0.02

+/-

25.5 6.85 0.34 5.43

-3.84

-0.15

+/-

31.2 6.64 0.24 27.2

-3.49 0.23

+/-

27.2A 8.71 0.64 K-40 1300 +/- 207 1320 +/- 164 1730 +/- 208 I DECEMBER Cs-134 -1.18 +/- 5.45 0.99 +/- 4.34 1.64 +/- 5.92 I Cs-137 Ba-140 La-140

-1.96

-0.21 2.00

+/-

4.70 17.0 5.21 2.24 8.89

-0.67

+/-

3.64 13.8 4.22 9.62 27.9 0.05

+/-

6.12A 21.9A 4.62 1-131 0.08 +/- 0.35 -0.59 +/- 0.46 0.03 +/- 0.33 I K-40 Sr-89 1110 +/- 190 1140 0.77

+/-

157 1.89 1480 +/- 185 Sr-90 0.97 +/- 0.63 I A: <MDC I

I I

I 37

I TABLE 3-7: GAMMA EMITTER CONCENTRATION IN FOOD PRODUCTS I Surry Power Station, Surry County, Virginia - 2017 pCi/kg (wet) +/- 2 Sigma Pa e 1 of 1 I SAMPLING COLLECTION LOCATIONS DATE SAMPLE TYPE ISOTOPE I BROCK FARM 11/16/2017 Corn Cs-134

-14.2 +/- 14.4 Cs-137 1.62 +/- 12.9 1-131

-16.2 +/- 34.7 K-40 4170 +/- 339 Cs-134 Cs-137 1-131 K-40 I 11/16/2017 Peanuts -19.6 +/- 19.6 -3.20 +/- 17.8 -3.58 +/- 32.4 5490 +/- 578 Cs-134 Cs-137 1-131 K-40 I SLADE FARM 12/6/2017 Soybeans 3.82 +/- 24.1 1.88 +/- 23.5 14.8 +/- 21.6 21700 +/- 1340 I

I I

I I 38

I I TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER I pCi/Liter +/- 2 Sigma Surry Power Station, Surry County, Virginia - 2017 Page 1 of2 SAMPLING COLLECTION I LOCATIONS DATE Mn-54 Co-58 ISOTOPE Fe-59 Co-60 Zn-65 ss 3/7/2017 1.31 +/- 3.47 -1.54 +/- 3.28 -6.81 +/- 6.29 -1.30 +/- 3.00 -11.9 +/- 9.09 I 6/20/2017 9/25/2017 12/5/2017 0.98 1.28

-1.30

+/- 3.28

+/- 4.52

+/- 2.48

-2.59

-0.42

-0.91

+/- 3.42

+/- 3.72

+/- 3.17

-0.90

-3.88 0.74

+/- 6.87

+/- 8.85

+/- 7.26

-0.97 0.82

-0.43

+/- 3.87

+/- 4.93

+/- 2.86 8.08

-3.48

-5.40

+/- 9.05

+/- 10.0

+/- 6.51 I 3/7/2017 4.52 Nb-95

+/- 3.61 A -1.01 Zr-95

+/- 5.83 2.17 1-131

+/- 5.54 Cs-134 0.55 +/- 3.59 Cs-137

-1.47 +/- 3.96 6/20/2017 1.79 +/- 3.90 -0.69 +/- 6.84 0.06 +/- 0.44 -1.15 +/- 3.61 4.87 +/- 4.56A I 9/25/2017 12/5/2017 1.60 4.13

+/- 5.20

+/- 3.06 A

-7.56 0.62

+/- 7.98

+/- 5.55 0.07 0.20

+/- 0.31

+/- 0.42 4.62 0.91

+/- 4.27 A

+/- 3.25 0.03

-0.97

+/- 4.43

+/- 3.53 Ba-140 La-140 H-3 Ra-226 I 3/7/2017 6/20/2017 9/25/2017

-2.94

-11.6

-4.84

+/- 15.6

+/- 16.6

+/- 18.1

-2.75

-0.22 0.98

+/- 4.62

+/- 6.26

+/- 6.22 39.4 70.6

-0.76

+/- 541

+/- 437

+/- 535 86.2 1.43

-22.3

+/- 134

+/- 91.5

+/- 110 I 12/5/2017 -2.76 +/- 10.1 0.39 +/- 4.61 155 +/- 675 23.9 +/- 90.6 Mn-54 Co-58 Fe-59 Co-60 Zn-65 I HIR 3/7/2017 6/20/2017 9/25/2017 1.80

-1.34

-1.05

+/- 3.09

+/- 4.21

+/- 3.60

-3.17

-2.80

-0.64

+/- 2.95

+/- 4.08

+/- 3.39 1.88

-1.32 3.04

+/- 6.71

+/- 7.72

+/- 7.34

-0.17 0.18

-0.06

+/- 2.78

+/- 3.98

+/- 2.82

-1.29 2.12

-3.38

+/- 7.30

+/- 7.71

+/- 9.00 12/5/2017 -0.50 +/- 4.12 -0.54 +/- 3.30 -2.08 +/- 8.44 3.01 +/- 4.42 -0.92 +/- 9.54 I 3/7/2017 2.77 Nb-95

+/- 3.82 3.91 Zr-95

+/- 5.82 3.65 1-131

+/- 5.58 Cs-134 0.91 +/- 3.58 Cs-137 0.56 +/- 3.59 6/20/2017 1.62 +/- 4.53 2.04 +/- 7.04 -0.26 +/- 0.41 4.84 +/- 4.56A 2.88 +/- 4.40 I 9/25/2017 12/5/2017 2.59

-2.47

+/- 4.16

+/- 4.43

-0.09

-2.91

+/- 7.33

+/- 6.14 0.18 0.22

+/- 0.27

+/- 0.42

-1.29 4.02

+/- 4.11

+/- 4.60

-1.47

-4.28

+/- 4.46

+/- 4.55 I 3/7/2017 6/20/2017 Ba-140 7.16

-2.69

+/- 14.8

+/- 16.4

-1.05 2.62 La-140

+/- 4.99

+/- 6.58

-133

-21.7 H-3

+/- 533

+/- 428 K-40 47.9 +/- 55.0

-44.0 +/- 58.5 9/25/2017 -4.85 +/- 16.5 -3.29 +/- 5.41 561 +/- 610 84.2 +/- 68.1 I 12/5/2017 A:< MDC 0.45 +/- 15.5 -1.66 +/- 5.05 82.4 +/- 667 28.5 +/- 69.8 I

I I

I I 39

I I TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER I pCi/Liter +/- 2 Si ma Surry Power Station, Surry County, Virginia - 2017 Pa e2 of2 SAMPLING COLLECTION I LOCATIONS DATE Mn-54 Co-58 ISOTOPE Fe-59 Co-60 Zn-65 I TC 3/7/2017 6/20/2017 9/25/2017 2.69 2.39 0.70

+/-

3.48 4.46 3.87

-0.77 0.39

-0.53

+/-

3.07 3.92 3.67

-2.00

-2.68

-6.90

+/-

7.01 8.00 6.76 3.18

-2.88

-2.95

+/-

3.65 4.62 5.17

-17.5 1.59 3.64

+/-

10.1 9.64 8.14 12/5/2017 1.34 +/- 4.14 0.09 +/- 4.07 -4.07 +/- 6.92 1.03 +/- 4.59 -7.73 +/- 10.5 I 3/7/2017 3.05 Nb-95

+/- 3.79 Zr-95

-0.02 +/- 6.10 0.02 1-131

+/- 0.26 Cs-134

-1.88 +/- 4.10 Cs-137

-0.83 +/- 3.85 6/20/2017 5.54 +/- 4.10 A -6.94 +/- 7.56 0.40 +/- 0.49 -2.34 +/- 4.72 -1.36 +/- 4.60 I 9/25/2017 12/5/2017 1.43 2.21

+/-

4.12 3.95

-0.99 +/- 6.77 1.88 +/- 6.94

-0.15

-0.21

+/-

0.33 0.40

-0.96

-3.65

+/-

3.99 4.40

-3.48

-5.34

+/-

3.93 4.46 I 3/7/2017 6/20/2017 Ba-140

-2.52 0.68

+/-

16.6 17.7

-2.25 5.37 La-140

+/-

3.70 5.50 13.1

-59.7 H-3

+/-

539 425 1.72 24.1 K-40

+/-

65.4 63.2 Th-228 9/25/2017 0.02 +/- 16.8 -0.17 +/- *6.16 -23.5 +/- 541 33.9 +/- 75.7 I 12/5/2017 A:< MDC

-14.6 +/- 18.8 -0.62 +/- 5.99 -249 +/- 655 -15.1 +/- 64.3 19.8 +/- 13.3 I

I I

I 40

I I TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WATER I pCi/Liter +/- 2 Sigma Surry Power Station, Surry County, Virginia - 2017 Page 1 of2 SAMPLING COLLECTION I LOCATIONS DATE Mn-54 Co-58 ISOTOPE Fe-59 Co-60 Zn-65 I SD 1/3/2017 2/7/2017 3/7/2017 0.01 1.39

-0.62

+/- 2.54

+/- 2.67

+/- 3.37 0.28

-0.76

-1.51

+/- 2.71

+/- 2.69

+/- 3.62

-0.68

-0.08 2.46

+/- 4.43

+/- 4.39

+/- 6.43 1.36 0.63

-0.25

+/- 2.89

+/- 2.38

+/- 3.09

-3.79

-3.28 2.47

+/- 5.61

+/- 5.44

+/- 7.67 4/18/2017 -1.11 +/- 2.23 -0.30 +/- 2.28 -0.40 +/- 5.09 3.42 +/- 2.45 A -5.76 +/- 6.16 I 5/2/2017 6/12/2017 7/3/2017 0.67 1.22

-0.06

+/- 2.75

+/- 2.86

+/- 2.77

-1.70 0.44

-1.41

+/- 2.42

+/- 2.72

+/- 3.32

-3.22

-2.53

+/- 5.42

+/- 6.32

+/- 6.90

-0.19 3.28 4.36

+/- 2.60

+/- 3.60

+/- 4.07 A

-7.49

-0.67

-13.1

+/- 6.08

+/- 6.26

+/- 9.44 8/1/2017 1.10 +/- 3.24 -3.03 +/- 3.64 1.77 +/- 7.99 3.59 +/- 3.74 0.55 +/- 7.99 I 9/5/2017 10/3/2017 11/7/2017

-2.62

-0.19

-0.21

+/- 3.27

+/- 2.97

+/- 3.36

-1.51 1.12

-2.78

+/- 3.16

+/- 3.41

+/- 3.38 3.33

-0.14 3.38

+/- 7.22

+/- 7.86

+/- 7.05

-1.03 0.62 1.48

+/- 3.46

+/- 3.00

+/- 3.91 3.13

-7.23

-1.89

+/- 5.93

+/- 8.58

+/- 7.61 I 12/5/2017 -0.70 +/- 2.31 Nb-95 0.51 +/- 2.02 Zr-95 3.61 +/- 4.76 1-131 0.82 +/- 2.28 Cs-134

-5.15 +/- 5.16 Cs-137 1/3/2017 -0.11 +/- 2.63 -1.03 +/- 5.07 -0.76 +/- 3.46 0.56 +/- 2.84 -1.16 +/- 2.73 I 2/7/2017 3/7/2017 4/18/2017

-1.09 1.03 3.09

+/- 2.83

+/- 2.88

+/- 2.42A 1.34 5.27

-0.88

+/- 4.34

+/- 5.57

+/- 4.47

-5.68 0.65

-0.33

+/- 4.16

+/- 4.20

+/- 3.00 0.29 +/- 2.50 0.52 +/- 3.73 2.60 +/- 2.76

-0.58

-0.001

-0.95

+/- 2.76

+/- 3.07

+/- 2.84 5/2/2017 0.21 +/- 2.82 -0.10 +/- 4.70 -0.08 +/- 4.26 -4.06 +/- 3.00 -1.48 +/- 2.73 I 6/12/2017 7/3/2017 1.30

-0.84

+/- 2.75

+/- 3.48

-2.95 1.69

+/- 4.29

+/- 6.07 1.13 0.15

+/- 3.35

+/- 4.32 3.03 +/- 3.18 2.24 +/- 3.98 2.55 0.02

+/- 3.09

+/- 3.03 8/1/2017 -1.32 +/- 3.72 -2.36 +/- 6.34 -4.96 +/- 6.19

0.61 +/- 3.91 2.12 +/- 3.78 I 9/5/2017 10/3/2017 11/7/2017 1.77 2.47

-0.66

+/- 3.09

+/- 3.83

+/- 3.85 2.20 3.32

-0.42

+/- 5.19

+/- 6.11

+/- 6.13

-6.20

-5.75

-1.92

+/- 6.67 * -0.21 +/- 3.36

+/- 6.49

+/- 6.14

-0.08 +/- 4.12 0.22 +/- 3.73 0.13 1.03 1.32

+/- 2.68

+/- 3.33

+/- 3.91 12/5/2017 0.16 +/- 2.19 -2.89 +/- 3.31 3.43 +/- 3.53 0.80 +/- 2.26 -1.36 +/- 2.29 I 1/3/2017 Ba-140

-5.33 +/- 11.6 -0.22 La-140

+/- 3.19 H-3 69.1 K-40

+/- 49.5 2/7/2017 -3.23 +/- 10.8 -0.48 +/- 3.83 I 3/7/2017 4/18/2017 6.89 10.30

+/- 13.7

+/- 8.75A 2.63

-0.73

+/- 4.23

+/- 2.92 72.2 +/- 62.8 3/7/2017 -469 +/- 521 I 5/2/2017 6/12/2017 7/3/2017

-1.27

-7.60 2.95

+/-

13.2 10.7 13.8

-2.75 0.63

-2.11

+/-

4.04 4.13 4.98

-135 +/- 529 8/1/2017 -4.57 +/- 18.6 -4.30 +/- 5.77 85.8 +/- 74.4 I 9/5/2017 10/3/2017 11/7/2017

-5.16 9.78 14.4

+/-

16.7 17.8 16.7

-1.27 1.16

-6.41

+/-

2.60 6.41 4.94 5.55 +/- 665 109 97.7 99.2

+/-

68.3 82.9 87.1

-2.16 I

12/5/2017 0.10 +/- 10.2 +/- 3.09 35.9 715 143 +/- 44.5 Ac-228 2/7/2017 17.4 +/- 14.8 I A:< MDC I

I 41

I I TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WATER I pCi/Liter +/- 2 Sigma Surry Power Station, Surry County, Virginia - 2017 Page 2 of2 SAMPLING COLLECTION I LOCATIONS DATE Mn-54 Co-58 ISOTOPES Fe-59 Co-60 Zn-65 SW-C 1/3/2017 3.47 +/- 3.69 -0.85 +/- 3.41 2.35 +/- 7.91 2.80 +/- 3.83 -7.63 +/- 8.82 I 2/7/2017 3/7/2017

-0.48

-3.43

+/-

2.85 4.35

-3.02 0.63

+/-

3.31 5.41 3.45 11.9

+/-

5.97 10.7 A

-0.01

-1.21

+/-

2.40 4.01

-7.29

-15.0

+/-

6.23 12.0 4/18/2017 -1.19 +/- 2.81 -0.36 +/- 2.76 1.01 +/- 4.65 0.01 +/- 2.54 -2.09 +/- 6.81 I 5/2/2017 6/12/2017 7/3/2017

-1.18

-2.01 3.58

+/-

3.15 2.34 3.99 1.66

-1.15

-2.73

+/-

3.21 2.57 4.45

-0.61 3.82

-0.82

+/-

5.95 6.41 7.81

-0.84 1.67 1.32

+/-

2.71 2.33 3.94

-4.82

-6.75

-8.60

+/-

7.74 6.56 9.15 8/1/2017 1.00 +/- 3.21 -0.90 +/- 3.44 2.38 +/- 5.82 -1.16 +/- 2.89 -5.65 +/- 7.86 I 9/5/2017 10/3/2017 11/7/2017 1.00

-3.40

-2.85

+/-

2.17 3.26 3.76

-0.09

-0.49

-0.38

+/-

2.41 3.02 3.34

-0.01 2.86 6.70

+/-

5.01 6.24 7.59 0.70 0.41 3.03

+/-

2.39 3.29 4.42 3.58

-6.34

-7.74

+/-

5.23 5.99 9.21 12/5/2017 -1.48 +/- 2.54 -0.28 +/- 2.54 -2.74 +/- 5.32 3.99 +/- 2.94A -3.44 +/- 5.22 I Nb-95 Zr-95 1-131 Cs-134 Cs-137 1/3/2017 -0.28 +/- 4.14 -2.72 +/- 6.28 2.45 +/- 5.02 -12.6 +/- 4.99 -1.13 +/- 3.29 I 2/7/2017 3/7/2017 4/18/2017 0.97 0.28 2.01

+/-

2.97 4.91 2.99

-2.10

-2.51 3.64

+/-

5.39 8.48 4.90

-0.74 3.47 1.07

+/-

4.95 5.43 3.38

-8.92

-1.09 2.32

+/-

3.47 4.37 3.03

-0.30

-4.29

-0.46

+/-

3.21 4.55 3.25 5/2/2017 -0.84 +/- 3.04 0.44 +/- 4.71 -1.32 +/- 4.39 -0.23 +/- 3.48 -4.21 +/- 3.49 I 6/12/2017 7/3/2017 8/1/2017 0.75 1.07 0.19

+/-

2.27 4.02 3.05 2.46

-1.33

-1.07

+/-

3.93 7.53 5.58

-1.14 0.08

-5.74

+/-

3.03 5.20 6.13 0.06

-0.17 3.59

+/-

2.83 4.59 3.40 A

-3.72 0.54

-3.10

+/-

2.96 4.19 3.51

-1.80 +/- 4.75 0.61 2.36 -0.82 +/- 2.46 I

9/5/2017 0.09 +/- 2.42 +/- 3.77 2.48 +/-

10/3/2017 -0.60 +/- 2.97 -0.12 +/- 5.95 0.23 +/- 5.88 -0.76 +/- 3.25 -2.25 +/- 3.36 11/7/2017 4.44 +/- 4.19A -3.37 +/- 6.47 3.36 +/- 5.74 0.11 +/- 4.01 0.12 +/- 4.25 12/5/2017 -0.18 +/- 2.47 4.12 +/- 4.83 -1.00 +/- 4.14 0.95 +/- 2.76 1.29 +/- 2.78 I 1/3/2017 Ba-140 2.10 +/- 15.6 -0.29 La-140

+/- 5.25 H-3 K-40 2/7/2017 0.69 +/- 13.9 -0.11 +/- 3.54 I 3/7/2017 4/18/2017 3/7/2017 5.12

-4.48

+/-

19.1 10.5 2.37

-1.95

+/- 7.08

+/- 3.70

-474 +/- 525 5/2/2017 -8.37 +/- 12.9 -3.89 +/- 4.07 I 6/12/2017 7/3/2017

-0.25 5.24

+/-

9.79 17.0

-1.42 2.64

+/-

2.68 4.94

-541 +/- 481 8/1/2017 -10.4 +/- 16.6 0.87 +/- 4.85 81.0 +/- 70.4 I 9/5/2017 10/3/2017 11/7/2017

-7.68 3.29 21.4

+/-

12.6 15.2 18.0 A

-4.41 0.84

-2.19

+/-

4.61 4.82 5.48 382 +/- 519 142 +/- 59.7 90.4 +/- 72.2 12/5/2017 7.08 +/- 11.1 -1.13 +/- 3.46 283 720 I A:< MDC I

I I

I 42

I I TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT I pCi/kg (dry)+/- 2 Sigma Surry Power Station, Surry County, Virginia - 2017 Pa e I of I SAMPLING COLLECTION I LOCATIONS DATE Cs-134 Cs-137 ISOTOPE K-40 Th-228 Th-232 SD 3/21/2017 94.7 +/- 56.0 A 61.7 +/- 59.5A 15400 +/- 1700 1790 +/- 142 1710 +/- 207 I 9/7/2017 21.2 +/- 36.9 Ra-226 108 +/- 43.5 Be-7 16500 +/- 863 Zn-65 1460 +/- 120 1020 +/- 111 I 3/21/2017 9/7/2017 3130 +/- 1810 1940 +/- 956 1430 +/- 456 166 +/- 88.7 B I CHIC-C 3/20/2017 9/7/2017 Cs-134 105 +/- 56.0 A 60.1 +/- 43.9 A Cs-137 207 +/- 74.7 132 +/- 55.7 K-40 16600 +/- 1990 17600 +/- 1320 Th-228 1390 +/- 142 1480 +/- 97.1 Th-232 1430 +/- 231 1310 +/- 159 I 3/20/2017 Ra-226 3280 +/- 1520 9/7/2017 2950 +/- 1230 I Cs-134 Cs-137 K-40 Th-228 Th-232 SI I 9/7/2017 25.0 +/- 25.8 Ra-226 162 +/- 35.2 16300 +/- 961 1210 +/- 64.3 1160 +/- 102 I 9/7/2017 2570 +/- 797 A:< MDC I B: Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 2 sigma.

I I

I 43

I I TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT I pCi/kg (dry)+/- 2 Sigma Surry Power Station, Surry County, Virginia - 2017 Page 1 of 1 SAMPLING COLLECTION I LOCATIONS DATE Cs-134 Cs-137 ISOTOPE K-40 Ra-226 Th-228 HIR 2/14/2017 -6.85 +/- 37.4 I 8/1/2017 26.6 +/- 35.3 35.1 +/- 32.4

-7.42 +/- 34.3 7330 +/- 1230 5050 +/- 816 33.2 +/- 598 1210 +/- 920 126 +/- 89.2 884 +/- 85.7 Th-232 I 2/14/2017 8/1/2017 173 +/- 146 842 +/- 132 Cs-134 Cs-137 K-40 Ra-226 Th-228 I CHIC-C 2/14/2017 8/1/2017 92.3 +/- 36.5 211 +/- 64.2 A 19.2 +/- 31.6

-25.0 +/- 40.7 4190 +/- 677 1100 +/- 542 917 +/- 744 6150 +/- 1830 1010 +/- 120 3440 +/- 142 I 2/14/2017 8/1/2017 Th-232 861 +/- 159 3460 +/- 225 Nb-95 90.9 +/- 47.8 A I A: Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 2 sigma.

I I

II I 44

I I TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH I pCi/ (wet) +/- 2 Sigma Surry Power Station, Surry County, Virginia - 2017 Page 1 ofl SAMPLING COLLECTION SAMPLE I LOCATION DATE TYPE ISOTOPE K-40 Mn-54 Co-58 Fe-59 I SD 4/5/2017 4/5/2017 10/10/2017 Catfish Game fish Catfish 1980 2480 2740

+/- 552

+/- 764

+/- 1160 0.04

-13.4

-32.5

+/- 27.4

+/- 24.5

+/- 57.6

-5.76 6.89

-19.5

+/- 26.6

+/- 30.4

+/- 49.7 10.7 19.1 24.0

+/- 63.8

+/- 92.6

+/- 115 10/10/2017 Game fish 2140 +/- 789 21.4 +/- 41.7 5.86 +/- 44.3 -34.6 +/- 85.0 I Co-60 Zn-65 Cs-134 Cs-137 4/5/2017 Catfish -3.56 +/- 19.0 -72.0 +/- 59.1 -8.08 +/- 24.5 -19.9 +/- 24.2 I 4/5/2017 10/10/2017 10/10/2017 Game fish Catfish Game fish 10.4 33.1 16.2

+/- 28.0

+/- 46.7

+/- 41.8

-18.9

-71.5 20.7

+/- 53.2

+/- 121

+/- 99.1

-10.1

-12.7

-65.1

+/- 34.9

+/- 55.8

+/- 45.6 10.3

-16.7 2.93

+/- 29.9

+/- 56.9

+/- 43.8 I

I

'I I

I I

I I 45

I I TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS I Surry Power Station, Surry County, Virginia - 2017 pCi/kg (wet) +/- 2 Sigma Page 1 ofl I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60 I POS 3/21/2017 9/7/2017

-28.8 +/- 26.9 5.57 +/- 27.0

-22.3 +/- 23.2

-10.2 +/- 24.4

-17.7 +/- 48.1 41.2 +/- 58.2 1.09 +/- 22.3

-1.57 +/- 26.6 I 3/21/2017 9/7/2017 Zn-65

-47.2 +/- 61.8 6.94 +/- 65.1 Cs-134 6.05 +/- 27.8 10.4 +/- 23.0 Cs-137

-25.3 +/- 28.5 10.4 +/- 29.8 I MP 3/21/2017 Mn-54

-16.1 +/- 30.8 Co-58 25.4 +/- 35.1 Fe-59

-26.6 +/- 71.1 Co-60 10.5 +/- 35.1 9/7/2017 17.5 +/- 35.8 7.71 +/- 33.5 20.4 +/- 65.4 -36.7 +/- 37.8 I 3/21/2017 Zn-65

-78.6 +/- 81.2 Cs-134 3.73 +/- 35.8 Cs-137 0.01 +/- 36.7 9/7/2017 -59.3 +/- 75.6 -7.81 +/- 37.0 3.73 +/- 37.4 I Mn-54 Co-58 Fe-59 Co-60 LC 3/21/2017 * +/- * +/- * +/- * +/-

I SHI 9/7/2017 3.88 +/- 35.5 Zn-65 23.2 +/- 38.9 Cs-134

-27.2 +/- 77.2 Cs-137 0.73 +/- 26.5 K-40*

I 3/21/2017 9/7/2017

+/-

-51.2 +/- 86.1

+/-

34.8 +/- 45.8

+/-

-15.6 +/- 42.4

+/-

619 +/- 618A

LC samples not collected on 3/21/17 due to lease conflict.

I A: <MDC I

I I

I I 46

I I TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS I Surry Power Station, Surry County, Virginia - 2017 pCi/kg (wet)+/- 2 Sigma Page I ofl I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 Fe-59 Co-60 I JI 3/20/2017 9/7/2017

-20.5 +/- 31.8

-2.19 +/- 47.0 0.75 +/- 29.2 13.7 +/- 42.0 6.73 +/- 57.0 33.9 +/- 91.7

-17.4 +/- 28.3 1.05 +/- 32.5 I 3/20/2017 9/7/2017 Zn-65

-12.0 +/- 62.1 0.75 +/- 87.2 Cs-134 10.4 +/- 30.6 20.6 +/- 42.6 Cs-137

-16.6 +/- 35.3

-18.3 +/- 47.0 K-40 735 +/- 509 983 +/- 763 I Mn-54 Co-58 Fe-59 Co-60 SD 3/21/2017 -6.15 +/- 42.6 0.11 +/- 41.7 -10.7 +/- 82.8 10.4 +/- 36.9 I 9/7/2017 1.93 +/- 30.0 Zn-65

-15.0 +/- 27.2 Cs-134 29.6 +/- 43.1 Cs-137

-3.93 +/- 35.1 I 3/21/2017 9/7/2017

-0.1 +/- 80.8

-63.0 +/- 70.9 48.6 +/- 46.9A 7.44 +/- 30.7 13.1 +/- 43.5

-0.40 +/- 29.9 I CHIC-C 3/20/2017 Mn-54

-2.93 +/- 33.5 Co-58 1.80 +/- 41.9 Fe-59 20.5 +/- 73.3 Co-60

-59.2 +/- 50.3 9/7/2017 25.3 +/- 32.3 1.74 +/- 31.2 -7.78 +/- 74.6 -22.1 +/- 43.7 I 3/20/2017 Zn-65

-11.4 +/- 86.2 Cs-134

-12.2 +/- 45.6 Cs-137 19.6 +/- 48.3 9/7/2017 -48.1 +/- 64.5 6.62 +/- 32.8 -0.14 +/- 29.3 I A: <MDC I

I I

I I 47

I I TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS I Surry Power Station, Surry County, Virginia - 2017 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION I LOCATIONS DATE ISOTOPE K-40 Mn-54 Co-58 Fe-59 I SD 6/15/2017 1450 +/- 853 5.11 +/- 36.0 -0.80 +/- 26.8 17.3 +/- 60.3 I Co-60 13.7 +/- 41.6 Zn-65

-98.1 +/- 74.4 Cs-134

-17.8 +/- 39.1 Cs-137

-22.3 +/- 38.9 I

I I

I I 48

I I 4. DISCUSSION OF RESULTS I Data from the radiological analyses of environmental media collected during 201 7 and tabulated in Section 3, are discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the I 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.

I 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 I are provided in Appendix B.

I The predominant radioactivity detected throughout 201 7 was from external sources, such as fallout from nuclear weapons tests (cesium-137) and naturally occurring radionuclides. Naturally occurring nuclides such as beryllium-7 and potassium-40 I were detected in numerous samples.

The following is a discussion and summary of the results of the environmental measurements taken during the 201 7 reporting period.

4.1 Gamma Exposure Rate I

A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect I ambient radiation. Three 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 I 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 I as controls. Ambient radiation comes from naturally occurring radioisotopes in .

the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.

I 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 I 2017. 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 I

I 49

I I 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 I can be detected above the baseline background.

I Figure 4-1:

DIRECT RAD IAT ION MEASUREMENT TLD RESULTS I 8--.------------------------------------.

7 +-------------------------------------l I .C:r: 6+--- - - - - - - - -- - - - ----.~ ~Pll~~~~*4~~~~~6t

~ 5~---~~----------~~~~~~~~~~~~~~Q I "C

~

C:

,Jg 4'1'r---41--=\--:IIP'----1,r--------,-.,:---4'-- -F-~- ----A~---,~ _,__- - - - - - - - - - - - - - ~

~ 3 I E 2-1-,r.----------------------------------,.---1 Note: In 2013 environmental TLD were changed to Panasonic UD-814 based on industry benchmarking. The field dose with the new TLDs is higher due to greater precision and accuracy of I 0 0

0 c--

the TLD along with an improved method for calculating control dosimeter dose.

00 0

0 0\

0 0

s0 -0 ~

0

~

0 0

~

0

\D 0N

~

0 N N N N N N N N N N I -+- Site Boundry -+- 5 Mile _._ Avg Contro l I

4.2 Airborne Gross Beta I Air is continuous ly sampled by passing through glass fiber particulate filters. The filters collect airborne particulate radionuclides. Once a week the samples are I 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 s ignificant variation in measured I activities (see Figure 4 -2 and 4-3). The December 5, 2017 data point has a notable separation between the indicator and control trend data points. The s ubsequent data points returned to a typical variation. Data from Figures 4-2 and I 4-3 indicate that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of I Surry Power Station was higher because of nuclear weapons t esting. 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 I gross beta results have remained steady.

I I 50

I I

Figure 4-2 :

I 0.045 2017 GROSS BETA IN AIR PARTICULATES I 0.040 0.035 I 10 0.030 0.025

a. 0.020 I 0.0 15 0.010 I 0.005 0.000 t-- t--

'SI" 00 'SI" 00

°' '°0 0 'SI" 00

°' N 0 'SI"

°'

M M lr)

'°~

lr) lr)

I S2 :::::: M N

~

N --- ---

M N

M ~

~

'SI" S2 lr)

N N

--- '°--- '°---

lr)

S2 t--

-+- Avg Indicator

---t-- S2 00 ---

00

~

00

°' °' 0 N

0 S2 ~ S2 N

N

..._ Ave Control I

I Figure 4-3 :

GROSS BETA IN AIR PARTICULATES I l .OE+OO HISTORICAL TREND I

I.OE-OJ I 10 a.

I 1.0E-02 I l .OE-03 00

°' 0 0 0 N

0 M

0

'SI" 0

lr) 0 '°00 t--

0 00 0 °'

0 0 N M 'SI" lr)

'°0 t--

°'

°' °'

°' 0 N

0 N

0 N N 0

N 0

N N N 0

I - Avg Indicator -+- Avg Contro l - A vg-Pre Op - Req uired LLD I

I I 51

I I 4.3 Airborne Radioiodine I Air is also continuously sampled for radioiodines by passing air 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 I 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 I Fukushima Daiichi nuclear incident in 2011.

I 4.4 Air Particulate Gamma The air particulate filters from the weekly gross beta analyses are composited by I 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-?, which are produced by cosmic processes. No man-made I radionuclides were identified. These analyses confirm no effects from station effluents.

I 4. 5 Animal Milk I Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the I fact tha t 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 I needs to be carefully evaluated when determining the effects from station effluents.

I 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 I attributed to residual global fallout from past atmospheric weapons testing.

No positive Cesium-137 activity was detected in 2017.

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

No strontium-89 was detected in the four composites analyzed. Strontium-90 was detected in three of the four composite samples, with an average concentration of 1.27 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.

52

I I 4. 6 Food Products I Three food product samples (corn, peanuts, and soybeans) were collected and analyzed by gamma spectroscopy. The results of the analyses are presented in Tab le 3-7. As expected, naturally occurring potassium-40 was detected in all I samples. The potassium-40 concentration for 201 7 indicates a slight increase when compared to the previous five year average; however, remains consistent with the 2016 concentration. No station related radioactivity was detected.

I I 4. 7 Well Water Well water is not considered to be affected by station operations because there are I 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. With the I exception of natural products, no other gamma emitters were detected. The natu rally occurring radionuclides detected were potassium-40 and thorium-228.

No station related radioactivity was detected. No gamma emitting isotopes were I detected during the pre-operational period.

I 4. 8 River Water Samples of the James River water are collected monthly and the results are I 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 I 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, and actinium-228. No station related radioactivity I was detected.

I I

I I 53

I I 4.9 Silt I 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 I could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish.

I Samples of silt are collected from three locations, one upstream, one downstream of the station and one in the dredge area of the station intake. The station intake was added in the third quarter of 201 7 to provide data for future station intake I dredging operations. The results of the gamma spectroscopy analyses are present ed in Table 3-10. Naturally occurring beryllium-7, potassium-40, radium-226, thorium-228 and thorium-232 were detected. Historically, cobalt-60 I 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 I silt appear in Figures 4-4 and 4-5.

The concentrations of cesium- 137 detected indicate a continual decreasing trend I 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 I 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 4-5.

I In 2017, at the control location, cesium-137 was detected with an average concentration of 1 70 pCi/kg. In the third quarter of 201 7, an additional silt I sampling location was added to the REMP. The new sample location is at the station intake in the dredge channel area. The channel is approximately 150' wide and 1 750' in length. The highest indicator location is the Station Intake at I 162 pCi/kg, which is equivalent to the control location average activity. This location was added to support future station intake channel dredging operations.

I I

I I 54

I I Figure 4-4:

COBALT-60 IN SILT I l.OE+04 I 1.0E+03 I c':'

"O 0)

~ 1.0E+02 I uC.

J.OE+Ol I Note: Station Intake added to REMP, 3rd Qtr 2017 I l .OE+OO N

°'

'-0 r-00 r-0 00 N

00

'St 00

°' °' °' °' °' °' °' °' °'

'-0 00 00 00 0

0, N

°'

00

°'

0 0

0 N

0 0

N N

g; 0

N

'-0 0

0 N

00 0

0 N

0 0

N N

0 N

I

0 N

'-0 0

N I -+- Control - Chickahom iny _..,_ Station Discharge LLD Avg ...,_ Station Intake LLD Avg Chickahominy h a d detectable activity in 1982 and 1984 through 1994. Other years were <MDC, Minimum I Detectable Concentration. Station Discharge was <MDC activity 1996 through 1998 and 2004 through 2017.

Figure 4-5:

I CESIUM -137 IN SILT I

I c':'

J .OE+03 "O

I 0)

~

uC.

l.OE+02 I

I l.OE+Ol 0 N 00

'<:t'-0 00 00

°' °' °' °' °' °' °'

00 000 00 0\

N

°'

'-0

°'

°' °'

00

°'

0 0

0 N

N 0

0 N

'St 0

0 N

'-0 0

0 N

00 0

0 N

0 0

N N

0 N

'St 0

N

'-0 0

N I -+- Control - Chickahom iny _..,_ Station Discharge - Ave-Pre Op - Required LLD - station lntake I

I 55

I I

I 4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans.

I 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.

I The naturally occurring radionuclides potassium-40, radium-226, thorium-228 and thorium-232 were detected at concentrations equivalent to normal I 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.

I 4.11 Fish I 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 I the same as those seen over the last decade. No activity was observed in this media except for naturally occurring potassium-40.

I 4.12 Oysters Oysters were collected from three different locations. The Lawne's Creek oyster I sampling location was replaced with Swash Hole Island in the third quarter of 2017. The results of the oyster analyses are presented in Table 3-13.

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

I 4.13 Clams I Clams are analyzed from three different locations. The results of the gamma spectroscopy analyses are presented in Table 3-14. Other than naturally occurring potassium-40, no station related radioactivity was detected.

I I

I I 56

I I 4.14 Crabs I An annual crab sample was collected 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 I emitting radionuclides related to station effluents were detected in the sample.

This is consistent with pre-operational data and data collected over the past decade.

I I

I 57

I I 5. PROGRAM EXCEPTIONS I There were four exceptions from the REMP sampling schedule in 201 7.

The four exceptions are detailed below:

I 1. Oyster samples were not collected from the Lawne's Creek location during the first half of 201 7 due to the area being under a private lease for shellfish harvesting. Dominion Energy Environmental Biology located a replacement I location that is monitored and stocked by the Virginia Oyster Stock Assessment and Replenishment Archive (VOSARA). The replacement location name is Swash Hole Island. Oyster samples were collected from this I location during the third quarter of 201 7.

2. All three environmental TLDs were missing from location #31 (Kingsmill I North) during collection of the third quarter TLDs.

I 3. All three TLDs from site boundary location #02 (WNW) were collected, packaged and shipped, but not received by the vendor lab. This omission was noted during review of the third quarter vendor supplied TLD results.

I 4. It was noted during the October 10, 2017 collection of environmental air samples, that the Hog Island Reserve (HIR) air sample had very little I discoloration on the patch. This information was forwarded to the vendor and analyzed. Results from the vendor lab indicate the gross beta activity

< MDC, when positive results are typically recorded. The vendor lab was I subsequently contacted and the patch was removed from the quarterly composite group.

I I

I I 58

I I 6. CONCLUSIONS I The results of the 201 7 Radiological Environmental Monitoring Program for Surry Power Station have been presented in previous sections. This section presents conclusions for each pathway.

I }- Direct Radiation Exposure Pathway - There was no detectable external dose to members of the public from Surry Power Station in 2017.

I }- Airborne Exposure Pathway - Radioiodine analysis of charcoal cartridge samples indicated that no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples identified only I naturally occurring beryllium-7 and potassium-40. Air particulate gross beta concentrations at all of the indicator locations for 201 7 trend well with I the control location. The December 5, 2017 data point indicates a separation between the indicator and control trend data points. The subsequent data points returned to a typical variation. The effluent data I was reviewed for the period of interest and concluded the station contribution is not measurable.

I }- 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-six samples. Naturally I 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 I 1.27 pCi/L. Strontium-90 is not a component of station effluents, but rather, a product of nuclear weapons testing fallout.

I }- Food Products - As expected, naturally occurring potassium-40 was detected in all three food product samples. In the past, cesium-137 had occasionally been detected in these samples and is attributable to global I fallout from past nuclear weapons testing. In the 2017 food product analyses, no positive Cesium-137 activity was detected.

I }- 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.

I }- River Water - River water samples were analyzed for gamma emitting radionuclides and tritium. The only gamma emitting radionuclide detected I was naturally occurring potassium-40. No positive Tritium activity was detected.

I I

I 59

I I ~ Silt - In 2017, at the control location, cesium-137 was detected with an average concentration of 170 pCi/kg. In the third quarter of 201 7, an I additional silt sampling location was added to the REMP. The new sample location is at the station intake in the dredge channel area. The channel is approximately 150' wide and 1750' in length. The highest indicator location I is the Station Intake at 162 pCi/kg, which is equivalent to the control location average activity. This location was added to support future station intake channel dredging operations. The presence of cesium-137 is I attributable to residual weapons testing fallout and its presence has been well documented. Cobalt-60 has not been detected since 2003.

I ~ 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 identified I in any sample.

Aquatic Biota I ~ Fish - As expected, naturally occurring potassium-40 was detected. There I were no other positive gamma emitting radionuclides detected in any of the fish samples.

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

I ~ Crabs - Naturally occurring potassium-40 was detected. No other positive gamma emitting radionuclides were detected.

I I

I I 60

I I

I I REFERENCES I

I I

I I 61

I I References I 1. NUREG-04 72, "Radiological Effluent Technical Specifications for PWRs",

Draft Rev. 3, March 1982.

I 2. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, I 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.

I

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

December 1975.

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

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

I 6. Virginia Electric and Power Company, Surry Power Station Technical I 7.

Specifications, Units 1 and 2.

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

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

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

I 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.

I I

I 62

I I

I

.I I

.I

I I

.1 APPENDICES I

I I

I 63

I I

I APPENDIX A: LAND USE CENSUS I

Year 2017 I

I I

I I 64

I I LAND USE CENSUS*

Surry Power Station, Surry County, Virginia I January 1 to December 31, 2017 Page 1 of 1 Nearest Nearest Nearest Nearest I Sector Direction Resident Garden** Cow Goat A N 4.1@ 10° (a) (a) (a)

I B NNE 1.9 @32° (a) (a) (a)

C NE 4.7 @35° (a) (a) (a)

I D E

ENE E

(a)

I F G

ESE SE (a) 2.8@ 142° (a)

(a)

I H J

SSE s

2.7@ 158° 1.7@181° 2.7@ 158° 2.0@ 183° (a)

(a)

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

I L SW 2.3@221° 4.7@228° (a) (a)

M WSW 0.4 @244° 3.6@245° (a) (a)

I N p

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

(a)

I R Q NW NNW 4.6 @321° 3.8 @338° (a) 4.4 @334° (a) 3.7@336° (a)

(a)

I I

I

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

Area greater than 50 m2 and contains broadleaf vegetation.

(a) None I

I I 65

I I

I I APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS I

Year 2017 I

I I

I 66

I I INTRODUCTION I The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc., Environmental Resource I Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set i I acceptance criteria:

A. Analytics Evaluation Criteria

! I Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria.

B. ERA Evaluation Criteria I ERA's evaluation report provides an acceptance range for control and I warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT)

I program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed I percentage limit promulgated under the appropriate regulatory document.

C. DOE Evaluation Criteria I MAPEP's evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

I

Acceptable (flag = "A") - result within +/- 20% of the reference value Acceptable with Warning (flag= "W') - result falls in the+/- 20% to+/-

30% of the reference value I

Not Acceptable (flag = "N") - bias is greater than 30% of the reference value I Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial I nuclear power facilities.

I I

I 67

I I 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 I are offered by the providers and included in the REMP and typically includes:

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

~

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, I ~

~

cartridge for I-131 analyses, air filter for gamma nuclide, gross beta, and Sr-90 analyses.

I RESULTS I For the TBE laboratory, 168 out of 173 analyses performed met the specified acceptance criteria. Five analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action I Program. TBE provided the following narrative.

I 1. ERA April 2017: Two nuclides in water were evaluated as Not Acceptable. (NCR 17-09)

I a. The Zn-65 result of 39.3 pCi/L, exceeded the lower acceptance limit of 47.2. The known value was unusually low for this study. The sample was run in duplicate on two different I detectors. The results of each were 39.3 +/- 18.2 pCi/L (46% error and lower efficiency) and 59.3 +/- 8.23 pCi/L (13.9% error and higher efficiency). The result from the 2nd detector would have I been well within the acceptable range (47.2 - 65.9) and 110.2%

of the known value of 53.8 pCi/L.

I b. The Sr-89 result of 40. 7 pCi/L exceeded the lower acceptance limit of 53.8. All associated QC and recoveries were reviewed and no apparent cause could be determined for the failure. The I prior three cross-check results were from 99 - 115% of the known values and the one that followed this sample (November, 2017) was 114% of the known value.

I 2. DOE MAPEP August 2017: The air particulate U-238 result of 0.115 +/-

0.025 Bq/sample was higher than the known value of 0.087 +/- 0.002 I with a ratio of 1.32, therefore the upper ratio of 1.30 (acceptable with warning) was exceeded. TBE's result with error easily overlaps with I the acceptable range. MAPEP does not evaluate results with any associated error. Also, the spike level for this sample was very low (2.35 pCi) compared to TBE's normal LCS of 6 pCi. TBE considers I this result as passing. (NCR 17-15)

I 68

I I

3. Analytics September 2017: The soil Cr-51 result was evaluated as Not I Acceptable (Ratio ofTBE to known result at 0.65). The reported value was 0.230 +/- 0.144 pCi/g and the known value was 0.355 +/- 0.00592 pCi/ g. The sample was counted overnight for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />; however the I Cr-51 was spiked at a very low level and had a counting error of 65%.

Cr-51 has a 27-day half-life, making low-level quantification even more difficult. The error does not appear to have been taken into I consideration for this result. If it had been evaluated with the error, the highest result would have been 105% of the reference value, which is acceptable. Also, the known value is significantly lower than I TBE's typical MDC for this nuclide in a soil matrix and would typically not be reported to clients (unless* specified). The results of all of the previous cross-checks have been in the acceptable (80 - 120%) range.

I TBE will evaluate further upon completion of the next ICP sample.

(NCR 17-16)

I 4. ERA November 2017: The water Sr-90 sample was evaluated as Not Acceptable. TBE's result of 27.1 pCi/L exceeded the lower acceptance I range (30.8 - 48.0 pCi/L). After reviewing the associated QC data for this sample, it was determined that although the spike recovery for Sr-90 was within our laboratory guidelines (70% -130%), both the I spike result and our ERA result were biased low. The original cross-check sample was completely consumed and we were unable to reanalyze before submitting the result. We (TBE) have modified our I preparation process to avoid this situation for future cross-check samples. We (TBE) also have enhanced LIMS programming to force a LCSD when a workgroup includes cross-check samples (as opposed to I running a DUP). (NCR 17-19)

Toe Inter-Laboratory Comparison Program provides evidence of "in control" I counting systems and methods, and that the laboratories are producing accurate and reliable data.

I I

I I 69

I I Analytics Environmental Radioactivity Cross Check Program Teledlne Brown En!;!ineerin!;! Environmental Services Page 1 of 4 I MonthNear Identification Number Matrix Nuclide Units TBE Reported Known Value (a)

Ratio of TBE to Analytics Result Evaluation (bl Value I March 2017 E11811 Milk Sr-89 Sr-90 pCi/L pCi/L 87 12.4 97.7 16.2 0.89 0.77 A

w I E11812 Milk Ce-141 Co-58 Co-60 pCi/L pCi/L pCi/L 135 153 182 145 150 183 0.93 1.02 1.00 A

A A

I Cr-51 Cs-134 Cs-137 pCi/L pCi/L pCi/L 258 104 142 290 120 140 0.89 0.87 1.02 A

A A

129 A I

Fe-59 pCi/L 135 1.05 1-131 pCi/L 92.6 97.9 0.95 A Mn-54 pCi/L 173 164 1.05 A Zn-65 pCi/L 208 199 1.04 A I E11813 Charcoal 1-131 pCi 92 93.9 0.98 A I E11814 AP Ce-141 Co-58 pCi pCi 99.9 95.4 101 104 0.99 0.92 A

A Co-60 pCi 140 127 1.10 A I Cr-51 Cs-134 Cs-137 pCi pCi pCi 211 82.1 92.8 201 83.2 97.0 1.05 0.99 0.96 A

A A

I Fe-59 Mn-54 Zn-65 pCi pCi pCi 107 106 137 89.3 114 138 1.20 0.93 0.99 A

A A

I E11816 Soil Ce-141 Co-58 pCi/g pCi/g 0.258 0.241 0.250 0.258 1.03 0.93 A

A Co-60 pCi/g 0.312 0.315 0.99 A I Cr-51 Cs-134 pCi/g pCi/g 0.439 0.176 0.500 0.207 0.88 0.85 A

A Cs-137 pCi/g 0.304 0.317 0.96 A I Fe-59 Mn-54 pCi/g pCi/g 0.210 0.292 0.222 0.283 0.95 1.03 A

A Zn-65 pCi/g 0.353 0.344 1.03 A I E11815 Water Fe-55 pCi/L 1600 1890 0.85 A I (a) 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 (b) Analytics evaluation based on TBE internal QC limits:

I 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 I

I 70

I I Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services I Month/Year Identification Matrix Nuclide Page 2 of 4 Units TBE Reported Known Value (a)

Ratio of TBE to Evaluation (b)

Number Analytics Result Value I June 2017 E11844 Milk Sr-89 Sr-90 pCi/L pCi/L 81.3 12.1 92.6 13.5 0.88 0.90 A

A I E11846 Milk Ce-141 Co-58 pCi/L pCi/L 142 147 151 155 0.94 0.95 A

A Co-60 pCi/L 185 191 0.97 A I Cr-51 Cs-134 pCi/L pCi/L 321 168 315 188 1.02 0.89 A

A Cs-137 pCi/L 148 150 0.99 A I Fe-59 1-131 Mn-54 pCi/L pCi/L pCi/L 116 102 168 115 93.6 172 1.01 1.09 0.98 A

A A

I E11847 Charcoal Zn-65 1-131 pCi/L pCi 195 87.9 204 84.8 0.96 1.04 A

A I E11845 AP Sr-89 Sr-90 pCi pCi 70.8 9.10 79.1 11.5 0.90 0.79 A

w I E11848 AP Ce-141 Co-58 pCi pCi 112 119 116 119 0.96 1.00 A

A Co-60 pCi 171 146 1.17 A I Cr-51 Cs-134 pCi pCi 270 152 241 144 1.12 1.05 A

A Cs-137 pCi 114 115 0.99 A I Fe-59 Mn-54 Zn-65 pCi pCi pCi 94.1 139 141 88.3 132 156 1.07 1.06 0.90 A

A A

I E11849 Water Fe-55 pCi/L 1840 1890 0.97 A July 2017 E11901 AP GR-A pCi 50.1 44.2 1.13 A I GR-B pCi 218 233 0.93 A I

I (a) 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 I (b) 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 I =

N Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1.30 I 71

I I Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services I Month/Year Identification Matrix Nuclide Page 3 of4 Units TBE Reported Known Ratio of TBE to Evaluation (bl Number Value (a) Analytics Result Value I September 2017 E11914 Milk Sr-89 Sr-90 pCi/L pCi/L 84.3 12.6 82.7 12.1 1.02 1.04 A

A I E11915 Milk Ce-141 Co-58 pCi/L pCi/L 93.9 115 87.0 117 1.08 0.98 A

A Co-60 pCi/L 265 262 1.01 A I Cr-51 Cs-134 Cs-137 pCi/L pCi/L pCi/L 273 186 175 217 201 172 1.26 0.93 1.02 w

A A

I Fe-59 1-131 Mn-54 pCi/L pCi/L pCi/L 137 78.0 128 125 71.0 123 1.09 1.10 1.04 A

A A

I E11916 Charcoal Zn-65 1-131 pCi/L pCi 206 71.9 184 64.4 1.12 1.12 A

A I E11917 AP Ce-141 Co-58 pCi pCi 80.1 110 86.3 116 0.93 0.95 A

A Co-60 pCi 277 260 1.07 A I Cr-51 Cs-134 pCi pCi 275 192 215 199 1.28 0.96 w

A Cs-137 pCi 165 170 0.97 A I Fe-59 Mn-54 pCi pCi 122 120 124 122 0.98 0.99 A

A Zn-65 pCi 175 183 0.96 A I E11918 Water Fe-55 pCi/L 1630 1630 1.00 A I E11919 Soil Ce-141 Co-58 Co-60 pCi/g pCi/g pCi/g 0.136 0.179 0.405 0.142 0.191 0.429 0.96 0.94 0.94 A

A A

N(1)

I Cr-51 Cs-134 Cs-137 pCi/g pCi/g pCi/g 0.230 0.272 0.336 0.355 0.328 0.356 0.65 0.83 0.94 A

A Fe-59 pCi/g 0.210 0.205 1.02 A I Mn-54 Zn-65 pCi/g pCi/g 0.210 0.301 0.201 0.301 1.05 1.00 A

A I (a) 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 (b) Analytics evaluation based on TBE internal QC limits:

I 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 I (1) See NCR 17-16 I 72

I I Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services I MonthNear Identification Matrix Nuclide Page 4 of4 Units TSE Reported Known Ratio of TSE to Evaluation (bl Number Value (a) Analytics Result Value I December 2017 E12054 Milk Sr-89 Sr-90 pCi/L pCi/L 92.1 18.3 92.3 16.9 1.00 1.09 A

A I E12055 Milk Ce-141 Co-58 pCi/L pCi/L 97.8 92.3 98.3 89.9 0.99 1.03 A

A I Co-60 Cr-51 Cs-134 pCi/L pCi/L pCi/L 176 226 118 173 242 125 1.02 0.93 0.95 A

A A

I Cs-137 Fe-59 1-131 pCi/L pCi/L pCi/L 148 123 66.0 141 113 57.8 1.05 1.08 1.14 A

A A

I Mn-54 Zn-65 pCi/L pCi/L 173 233 161 211 1.08 1.10 A

A I E12056 E12057A Charcoal AP 1-131 Ce-141 pCi pCi 48.1 108 47.5 111 1.01 0.97 A

A I Co-58 Co-60 Cr-51 pCi pCi pCi 89.5 223 311 102 196 274 0.88 1.14 1.13 A

A A

I Cs-134 Cs-137 Fe-59 pCi pCi pCi 141 162 121 142 160 129 1.00 1.01 0.94 A

A A

I Mn-54 Zn-65 pCi pCi 177 203 182 239 0.97 0.85 A

A I E12058 E12059 Water AP Fe-55 Sr-89 pCi/L pCi 1970 71.2 1740 87.4 1.13 0.81 A

A Sr-90 pCi 12.9 16.0 0.81 A I

I I (a) 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 (b) Analytics evaluation based on TBE internal QC limits:

I A W

=Acceptable - reported result falls within ratio limits of 0. 80-1.20

=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 I

I 73

I I DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering Environmental Services Page 1 of 1 I Month/Year Identification Number Matrix Nuclide Units TSE Reported Known Value (a)

Acceptance Range Evaluation (b)

Value I February 2017 17-MaS36 Soil Ni-63 Sr-90 Sq/kg Sq/kg

-5.512 571 624 (1) 437-811 A

A I 17-MaW36 Water Am-241 Ni-63 Sq/L Sq/L 0.693 13.4 0.846 12.2 0.592 - 1.100 8.5 - 15.9 A

A Pu-238 Sq/L 0.7217 0.703 0.492 - 0.914 A I 17-RdF36 AP Pu-239/240 U-234/233 Sq/L Sq/sample 0.9277 0.0911 0.934 0.104 0.654 - 1.214 0.073 - 0.135 A

A U-238 Sq/sample 0.107 0.075 - 0.139 A I

0.0967 17-RdV36 Vegetation Cs-134 Sq/sample 6.44 6.95 4.87 - 9.04 A Cs-137 Sq/sample 4.61 4.60 3.22 - 5.98 A I Co-57 Co-60 Sq/sample Sq/sample

-0.0229 8.52 8.75 (1) 6.13 - 11.38 A

A Mn-54 Sq/sample 3.30 3.28 2.30 - 4.26 A I Sr-90 Zn-65 Sq/sample Sq/sample 1.30 5.45 1.75 5.39 1.23 - 2.28 3.77 - 7.01 w

A I August2017 17-MaS37 Soil Ni-63 Sr-90 Sq/kg Sq/kg 1130 296 1220 289 854 - 1586 202 - 376 A

A 17-MaW37 Water Am-241 Sq/L 0.838 0.892 0.624-1.160 A I Ni-63 Pu-238 Sq/L Sq/L

-0.096 0.572 0.603 (1) 0.422 - 0.784 A

A Pu-239/240 Sq/L 0.863 0.781 0.547-1.015 A I 17-RdF37 AP U-234/233 U-238 Sq/sample Sq/sample 0.103 0.115 0.084 0.087 0.059 - 0.109 0.061 - 0.113 w

N (2J I 17-RdV37 Vegetation Cs-134 Cs-137 Sq/sample Sq/sample 2.34 0.05 2.32 1.62 - 3.02 (1)

A A

Co-57 Sq/sample 3.32 2.8 2.0 - 3.6 A I Co-60 Mn-54 Sq/sample Sq/sample 2.09 2.90 2.07 2.62 1.45 - 2.69 1.83 - 3.41 A

A Sr-90 Sq/sample 1.17 1.23 0.86 - 1.60 A I Zn-65 Sq/sample 6.07 5.37 3.76 - 6.98 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric I

measurements made during standard preparation (b} DOEIMAPEP evaluation:

=

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 I N =Not Acceptable - reported result falls outside the ratio limits of< 0.70 and> 1.30 (1) False positive test (2) See NCR 17-15 I

I 74

I I ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services Page 1 of 1 I Month/Year ldentrification Number Matrix Nuclide Units TBE Reported Known Value(a)

Acceptance Limits Evaluation (bl Value I March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 - 133 A I April 2017 RAD-109 Water Ba-133 Cs-134 Cs-137 pCi/L pCi/L pCi/L 49.2 83.2 202 49.7 90.1 206 40.8 - 55.1 74.0-99.1 185 - 228 A

A A

Co-60 pCi/L 51.2 54.7 49.2 - 62.7 A I Zn-65 GR-A GR-B pCi/L pCi/L pCi/L 39.3 53.6 42.7 53.8 75.0 38.5 47.2 - 65.9 39.5 - 92.3 25.5 -46.0 N (1)

A A

I U-Nat pCi/L 50.1 55.6 45.2-61.7 A H-3 pCi/L 7080 6850 5920 - 7540 A Sr-89 pCi/L 40.7 66.2 53.8 - 74.3 N (1)

Sr-90 pCi/L 26.9 26.7 19.3- 31.1 A I September 2017 MRAD-27 AP 1-131 GR-A pCi/L pCi/sample 26.7 40.9 29.9 50.1 24.9 - 34.9 16.8- 77.8 A

A I October 2017 RAD-111 AP Water GR-B Ba-133 pCi/sample pCi/L 58.0 71.3 61.8 73.7 39.1 -90.1 61.7-81.1 A

A Cs-134 pCi/L 43.0 53.0 42.8 - 58.3 A I Cs-137 Co-60 pCi/L pCi/L 48.2 69.0 52.9 69.5 47.6- 61.1 62.6 - 78.9 A

A Zn-65 pCi/L 335 348 313-406 A I GR-A GR-B pCi/L pCi/L 32.5 24.3 35.6 25.6 18.3 - 45.8 16.0 - 33.6 A

A U-Nat pCi/L 36.6 37.0 30.0 -40.9 A I H-3 1-131 pCi/L pCi/L 6270 26.4 6250 24.2 5390 - 6880 20.1 - 28.7 A

A I November 2017 1113170 Water Sr-89 Sr-90 pCi/L pCi/L 57.1 27.1 50.0 41.8 39.4- 57.5 30.8 -48.0 A

N (2)

I I

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

(b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits I N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 17-09 (2) See NCR 17-19 I

I 75

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