Text

ISFSI - Annual Radiological Environmental Operating Report
	ML17139B444
Person / Time
Site:	Surry, 07200002, 07200055
Issue date:	04/27/2017
From:	Lawrence D; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	17-116
	Download: ML17139B444 (76)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 27, 2017 United States Nuclear Regulatory Commission Serial No.17-116 Attention: Document Control Desk s&Lrrsc RO Washington, DC 20555-0001 Docket Nos. 50-280 50-281 72-2 72-55 License Nos. DPR-32 DPR-37 SNM-2501 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry Units 1 and 2 Technicaf Specification 6.6.B.2 requires the submittal of an Annual

Radiological Environmental Operating Report (AREOR) for Surry Power Station. Surry

. Independent Spent Fuel Storage Installation (ISFSI) Technical Specification Appendix C, Item 1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period. of January 1, 2016 through December 31, 2016, which includes environmental monitoring for the Surry ISFSI.

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

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

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

Serial No.17-116 Docket Nos.: 50-280 50-281 72-2 72-55 ATTACHMENT 1 2016 Annual Rad~o!ogica! Environmenta~ Operat~ng Report SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

Surry Power Stati.on I

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I I Dominion Surry Power Station I Radiological Environmental Monitoring Program January 1, 2016 to December31,-2016 ----- __.. _ - ---

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I I .Surry Power Station I January 1, 2016 to December 31, 2016 I

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I Prepared by:: _ _ t:_l._?l;-+--~--}-_ _

I P. F. Blount Health-Physicist I Reviewedby: ~~~~~___!_~~a~~-~~lt.~.___!::_L,~L~o..t~~*~~~~~~~~~

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P.R. Harris I

I T. L. Ragland

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Manager Radiological Protection and Chemistry I

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I I Table of Contents I

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

1. EXECUTIVE

SUMMARY

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

3. ANALYTICAL RESULTS ............................................................................................................ 20 I 3.1 Summary ofResults ...................................................................................................... '. ....... 20 3.2 Analytical Results of2016 REMP Samples ..........................................................................28

. 4. DISCUSSION OF RESULTS ..................................................................................................... 49 I 4.1 Gamma Exposure Rate ................................................................................................ , ........ 49 4.2 Airborne Gross Beta ..................................................... :....................................................... 50 4.3 Airborne Radioiodine ............................................................................................................ 51 I 4.4 Air Particulate Gamma ..... :................................................................................................... 51 4.5 Cow Milk ................................................................................... :.......................................... 52 4.6 Food Products .......................................................................................................................

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4.7 Well Water ............................................................................................................................. 52 4.8 RiverWater .............................................................................................. ~ ............................. 53 4.9 Silt ..... ,................................................................................................................................... 53 I 4.10 Shoreline Sediment ............................................................................................................. 55 4.11 Fish ...................................................................................................................................... 55 4.12 Oysters ................................................................................................................................ 56 I 4.13 Clams ...................................................................................................................... ;........... 56 4.14 Crabs ................................................................................................................................... 56

5. PROGRAM EXCEPTIONS ........................................................................................................... 57 I 6. CONCLUSIONS .............................................................................................................................. 58 REFERENCES .................................................................................................................................... 60 APPENDICES ........... :.......................................................................................................................... 62 I APPENDIX A: LAND USE CENSUS ................ :.................................................................... :..... 63 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS ............................... 65 I

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I I PREFACE I 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 2016 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1- -

through December 31, 2016, in air, water, silt, shoreline sediment, milk, aquatic I biota, food products and direct exposure pathways have been analyzed, evaluated and summartzed. 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 radius of the station. Surry Power Station personnel collect a variety of samples I within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. The *first type, control samples, is collected from areas that I are beyond the measurable influence of Surry 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 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 compared to control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or natural variation, or other causes such as the Chernobyl and Fukushima Daiichi accidents that released radioactive material to the environment.

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

Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity I 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 Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be abl,e 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 cti,rborne, aquatic, terrestrial and direct radiation exposure. The_ airborne exposure pathway includes radioactive airborne iodine and particulates. The 2016 airborne results were similar to previous years. No station 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 deteded in well water.

I This trend is consistent throughout the operational environmental monitoring program. No IDaJ:!:-m~g_uadlopuclide~ were__ d~1~~te_d_in riyer water._SilLsamples indicated_fue 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, radium and thorium were detected at average environmental levels.

The terrestrial exposure pathway includes milk and food products. Iodine-131 I was not detected in any 2016 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. No I man-made radionuclides were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk. Naturally I occurring potassium-40 was detected in food products. The direct exposure pathway measures environmental radiation doses using TLDs. TLD results have remained re.latively constant over the years.

I During 2016, as LTI previous years, the operation of Surry Power Station has created no adverse environmental effects or health hazards. The maximum total I body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous. effluents released from the station during 2016 was 0.022 millirem.- For* reference, this dose may be compared to the 620 millirem - --

I average annual exposure--to every person in the Umied States from riatiircil and man-made sources. Natural sources in the environment provide approximately 50% of radiation exposure to man, while nuclear power contributes less than I 0.1 %.. These -results demonstrate compliance with federal and state regulations and also demonstrate the adequacy of radioactive effluent controls at Surry Power Station.

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I I 2. PROGRAM DESCRIPTION I 2.1 Introduction This report documents the 2016 *Surry Power Station operational Radiological I Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located _op. th~~Gravel N_eck peninsula adjacent to~the James Rive;r, approximately _.

25 miles upstream of the Chesapeake Bay. The--site consists -of tWo units, each I with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each ur:i;it is designed I 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, coristructed 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, t4e 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. Mirion Techriologies is responsible for processing the TLDs. Teledyne Brown Engineering is responsible for sample analyses. The I results of the analyses are used to determine if changes *in radioactivity levels may be attributable to station operations. Measured values are compared *with control values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapon~ test fallout and seasonal variations of naturally occu_rring _:rq,QJ._9nuc]jdes. ____I)at(l_ collected prior to station operation is u~ed_j;Q__ _

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 2016 and satisfies the following I objectives of the program:

> To provide measurements of radiation artd of radioactive* materials in those exposure pathways and

for* those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public

- resulting from station operations~- - ------* - -- ---- --- ----- ---

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

> To iden~ 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 2016 sampling program for Surry Power Station. All samples listed _in .Table 2-1 are taken at indicator locations except those labeled I "control." Dominion personnel collect all samples listed .in Table 2-1.

Table 2-2 summarizes the analysis program conducted by Teledyne Brown I Engineering and Mirian 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 Mirian Technologies, located I in Irvine, CA, for processing.*

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

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- - - - - - - - - - - - - - - *- - - - Table 2-1 SURRY-201()

RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Pg. 1 of3 Distance Collection Sam~le Media Location - Station Miles Dir;ection Degrees Freguenc~ Remarks Environmental Control (00) Quf!-rterly Onsite (Stored in a lead shield outside the protected area) 1 TLDs West North West (02) 0.2 WNW 293° Quarterly Site Boundary i~ '

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 S~te Boundary South South West (13) 0.3 SSW 201° Quarterly S~te Boundary South (14) 0.4 s 182° Quarterly s;te 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-20Hi RADIOWGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Pg. 2 of3 Distance Collection S amP!e Media Location Station Miles Direction Degrees Frequencr Remfil-ks Environmental BASF (34) 5.1 ENE 70° Quarterly Apx. 5 mile 1LDs 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 PopuJation Center James River Bridge (39) 17.l SE 142° Quarterly . Control Location Benn's Church (40) 17.0 SSE 159° Quarterly Contl:ol Location Smithfield (41) 13.4 SSE 167°

Quarterly Contl:ol 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° Weel<ly Site boundary location with highest D/Q and Particulate Hog Island Reserve (HIR) 2.0 NNE 26° Weel<ly Bacon's Castle (BC) 4.5 SSW 202° Weel<ly Alliance (AIL) 5.1 WSW 247° Weel<ly

Colonial Parkway (CP) 3.8 NNW 333° Weel<ly BASF (BASF) 5.1 ENE 70° Weel<ly Fort Eustis (FE) 4.9 ESE 104° Weel<ly Newport News (NN) 19.3 SE 130° Weel<ly Control Location River Water Surry Station Dis charge (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 Dis charge (SD) 1.3 NNW 341° Semi-Annually 10

Table 2-1 SURRY-20i6 RADIOLOGICAL SAMPLING STATidNS DISTANCE AND DIRECTION FROM UNIT NO. 1 Pg. 3 of3 Distance Collection S amE!e Media Location Station Miles Direction Degrees Freque:q.cx Remarks Milk Colonial Parkway (CP) 3.7 NNW 336° Monthly Williams (WMS) 27.5 s 175° .Monthly Control Location 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 Mulbeny Point (MP) 4.9 ESE 124° Semi-Annually Lawne's \:reek (LC) 2.4 SE 131° Semi-Annually Clams Chickahominy River (CHIC) 11.2 WNW 300° Semi-Annually Control Location Suny Station Dis charge (SD) 1.3 NNW 341° Semi-Annually Jamestown Island (JI) 3.9 NW 324° Semi-Annually Flsh Suny Station Dis charge (SD) 1.3 NNW 341° Semi-Annually Crabs Suny 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 SURRY-2016 I SAMPIE ANALYSIS PROGRAM Pg. 2of3 SAMPLE MEDIA Fru12UENCY ANALYSIS LLD* REPORT UNITS I Shoreline Sediment Semi-Annually Gannna Isotopic Cs-134 150.

pCi/kg - dry Cs-137 180 I Silt Semi-Annually Gannna Isotopic Cs-134 pCi/kg - dry 150 I Milk Monthly Cs-137 I-131 180 1 pCi/L I Gannna Isotopic Cs-134 15 pCi/L Cs-137* *--**- 18 I Ba-140 La-140 60 15 I Quarterly Composite ofCP Sr-89 Sr-90 NA NA pCi/L monthly sample I Oysters Semi-Annually Gamma Isotopic pCi/kg-wet Mn-54 130 I Fe-59 Co-58 Co-60 260 130 130 I Zn-65 Cs-134 Cs-137 260 130 150 I Clams Semi-Annually Gannna 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 Crabs Annually Gannna Isotopic Mn-54 130 pCi/kg-wet Fe-59 260 I Co-58 Co-60 Zn-65 130 130 260 I Cs-134 Cs-137 130 150 I Footnotes located at end of table.

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I Table 2-2 SURRY-2016 I SAMPLE ANALYSIS PROGRAM Pg. 3 of3 SAMPLE MEDIA FREQUENCY ANALYSIS I.LD* 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 Isotopic I-131 Cs-134 60 60 pCi/kg-wet I

Cs-137 80 I

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I Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that ar are measurable and identifiable, together with the above nuclides, are also identified and reported.

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

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

NA None assigned I

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SW Legend :

Air Sampling Stations '

TLD Sampling State Environmental Monitoring Sites

State TLD Sites Figure 1. Surry Radiological Monitoring Locations

Figure 2. Surry Emergency Plan Map

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Air Sampling Stations TLD Sampling Nearest Garden e

e Nearest Residents Nearest Milk An imal Aquatic Samples

- ":::;***:::::; Original © 1991 by ADC of Alexandria , Inc

6440 General Green Way,

- - t Alexandria, VA22312. USED WITH PERMISSION . No other reproduction t

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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 Al exandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISS ION . 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 ofResults 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 Radiologkcil 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: RAJJIOLOGICA L ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Suny Power Station, Surry County, Virginia- 2016 I Docket No. 50-280-281 Page 1 of7 Medium or I ndicator Control I Pathway Sampled (Units)

Analysis Type

!Total No. LLD L ocations Mean Range Location with Highest Mean Distance Name Direction -* Range--

Mean _

Locations Mean Range Non-Routine Reported Measurements Air Gross 416 10 13. 9 (363/364) ec- -*- 4.5 mi -15:z(52152f-12.2 (52152) 0 I Particulate Beta (1E-3 pCilm3)

(4.74-34.1) SSW (5.1 - 33.1) (5.3 - 22.3)

Gamma 32 I Be-7 32 140.6 (28/28)

(8 6.7 - 218)

ALL 5.1 mi WSW 160.3 (4/4)

(115 - 218) 131.8 (4/4)

(99.0 - 163) 0 I K-40 32 15.6 (2/28)

(1 4.9 - 16.3)

CP 3.8 mi NNW 16.3 (1/4)

(16.3 - 16.3)

<LLD 0 I Cs-134 32 50 <LLD N/A <LLD <LLD 0 Cs-137 32 60 <LLD N/A <LLD < LUJ 0 I -------------------

Air Iodine 1-131 416 70 <LLD N/A <LLD <LLD 0 I (1E-3 pCilm3)

Milk Strontium 4 (pCi/uter)

I Sr-89 4 <LLD N/A <LLD <LLD 0 Sr-90 4 1.59 (3/4) CP

3.7 mi 1.59 (3/4) <LLD 0 I (1 .33 -1.79) NNW (1.33 - 1.79)

Gamma 36 I K-40 36 1349 (24/24)

(1 080 -1530)

.CP 3.7 mi NNW 1355 (12/12) 1562 (11/12)

(1080 - 1530) (1270 - 1850) 0 I 1-131 36 1 <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 Ba-140 36 60 <LLD NIA <LLD <LLD 0 I La-140 36 15 <LLD N/A <LLD <LLD 0 I

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I I TABLE 3-l; RADIOEOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Vrrginia -2016 I Docket No. 50-280-281 Page 2 of7 Medium or Indicator Control I Pathway Sampled (Units)

Analysis Type -

'Total No. LLD Locations Mean Range __

Location with Highest Mean IDistance Name Direction I Mean Range .

Locations Mean -

Non-Routine Reported Range __ ..Measurements I Food Gamma 3 Products

.I (pCi/kg v.et) K-40 3 11120 (3/3)

(4730 - 22900)

Slade 3.2mi s

22900 (1/1)

(22900-22900)

N/A 0 Be-7 3 <LLD NIA <LLD N/A 0 I

Th-228 3 <LLD N/A <LLD NIA 0 I 1-131 3- 60 <LLD N/A <LLD N/A 0 I Cs-134 3 60 <LLD NIA <LLD N/A 0 I Cs-137 3 80 <LLD NIA <LLD N/A 0 I ______..___

Well H-3 12 2000 <LLD NIA <LLD N/A 0 (pCi/Uter)

I Gamma K-40 12 12 66.8 (1/12) cs 0.3mi 66.8 (1/12) NIA 0 (66.8 - 66.8) E (66.8 - 66.8)

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

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

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2016 I Docket No. 50-280-281 Page 3 of7 Medium or Indicator ' Control I - Pathway Sampled (Units)

Analysis Type

'Total No. LLD Locations Mean

- Range Location with Highest Mean IDistance Name Direction I Mean Range- -

Locations Mean Range Non-Routine Reported Measurements

~--

I Well Water Nb-95 12 15 <LLD N/A <LLD N/A 0 (pCi/Uter)

I Zr-95 12 30 <LLD N/A <LLD NIA 0 1-131 - 12 1 <LLD NIA <LLD N/A *-. 0 I

Cs-134 12 15 <LLD NIA <LLD N/A 0 I Cs-137 12 1"8 <LLD N/A <LLD N/A 0 I Ba-140 12 60 <LLD N/A <LLD N/A 0 I La-140 12 15 <LLD NIA <LLD N/A 0 I River (pCi/Uter)

H-3 __ 8 2000______<_LLD NIA <LLD <LLD 0 Gamma 24 I K-40 24 84.0 (5/12)

(59.3 --112)

SD 0.4mi NW 84.0 (5/12)

(59.3- 112) 67.8 (2/12)

(65.2 - 70.3) 0 I Ra-226 24 253 (1/12)

(253 - 253)

SD 0.4mi NW 253 (1/12)

(253 - 253)

<LLD 0 I Th-228 24 <LLD N/A <LLD 9.11 (1/12)

(9.11 - 9.11) 0 Mn-54 24 15 <LLD NIA <LLD <LLD 0 I

I Co-58 24 15 <LLD NIA <LLD <LLD 0 Fe-59 24 30 <LLD NIA <LLD <LLD 0 I Co-60 24 15 <LLD N/A <LLD <LLD 0 I Zn-65 24 30 <LLD. NIA <LLD <LLD 0 I 23

I I TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2016 I Docket No. 50-280-281 Page 4 of7 Medium or Indicator Control I Pathway Sampled (Units)

Analysis

!Total Type---- No. LLD Locations Mean Range Location with Highest ME!an IDistance Name Direction I Mean Range ___

Locations Mean Non-Routine Reported Range ___ Measurements River 1-131 24 10 <LLD N/A <LLD <LLD 0 I Water (pCi/Uter)

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 I La-140- 24 15 <LLD N/A <LLD <LLD 0 I Silt (pCi/kg dry)

Gamma Be-7 4

4 3170 {112) SD 1.3 mi 3170 (1/2) <LLD 0 I K-40 4 (3170 - 3170) 15700 (2/2) CHIC NNW 11.2 mi (3170 - 3170) 17200 (2/2) 17200 (2/2) 0 (10000-21400) WNW (15900-18500) (15900-18500)

I Cs-134 4 150 <LLD NIA <LLD <LLD 0 I Cs-137 4 180 <LLD CHIC 11.2 mi WNW 226 (2/2)

(219 - 233) 226 (2/2)

(219 - 233) 0 I Ra-226 4 2255 (2/2)

(1910 - 2600)

CHIC 11.2 mi WNW 2620 (2/2) 2620 (2/2)

(2510 - 2730) (2510 - 2730) 0 Th-228 4 1209 (2/2) _ CHIC- - 11.2 mi 1745 (2/2)- 1745 (2/2) - - 0 I (818 - 1600) WNW (1700 - 1790) (1700 - 1790)

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

I I

I I 24

I I TAJILE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I Surry Power Station, Surry County, Vrrginia - 2016 Docket No. 50-280-281 Page 5 of7 Medium or Indicator Control I Pathway Sampled (Units)

Analysis Type

!Total No. LLD Locations Mean

~Range Location with Highest Mean Name Distance I IDire.ction Mean

-=..-Range*-=::'_

Locations Mean Range Non-Routine Reported Measureme_nts I Shoreline (pCilkg dry)

K-40 4 5805.(2/2)

(3650 - 7960)

HIR 0.6 mi N

5805 (2/2)

(3650 - 7960) 1910 (2/2)

(1820 - 2000) 0 I Cs-134 4 150 <LLD NIA <LLD <LLD 0 Cs-137 4 180 <LLD NIA <LLD <LLD 0 I

Ra-226 4 <LLD CHIC 11.2 mi 1390 (1/2) 1390 (1/2) 0 I Th-228 4 1920 (112) HIR WNW 0.6 mi (1390 - 1390) 1920 (1/2)

(1390 - 1390) 1090 (2/2) 0 (1920 - 1920) N (1920 - 1920) . (930 -1250)

I Th-232 4 1550 (1/2) HIR 0.6mi 1550 (112) 1015 (2/2) 0 (1-550 - 1550) N (1550 - 1550) (790 -1240)

I Fish (pCilkg v.etJ Gamma 4 K-40 4 2548 (4/4) SD 1.3 mi 2548 (4/4) NIA 0 I (1810 - 3170) NNW (1810 - 3170)

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

I I 25

I I TABLE 3-1: RADIOLOGICAL ENVIR-ONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Vrrginia - 2016 I Docket No. 50-280-281 Page 6 of7 Medium or Indicator Control I Pathway Sampled (Units)

Analysis Type

!Total No. LLD Locations Mean Range Location with Highest Mean IDistance Name Direction I Mean Range Locations Mean Range

Non-Routine Reported Measurements I Oysters (pCi/kg wet)

Gamma K-40 6

6 770 (5/6) POS 6.4mi 844 (212) N/A 0 (581 - 1090) SSE (597 -1090)

I Mn-54 6 130 <LLD N/A <LLD NIA 0 I Fe-59 6 260 <LLD N/A <LLD NIA 0 I Co-58 6 130 <LLD N/A <LLD NIA 0 Co-60 6 130 <LLD N/A <LLD N/A 0 I Zn-65 6 260 <LLD NtA <LLD NIA 0 I Cs-134 6 no <LLD N/A <LLD NIA 0 I Cs-137 6 150 <LLD N/A <LLD NIA 0 I Clams (pCi/kg wet)

Gamma K-40 6

6 630 (214) JI 3.9 mi 712 (1/2) 675 (1/2) 0 (548 - 712) NW (712 - 712) (675 - 675)

I Mn-54 6 130 <LLD N/A <LLD <LLD 0 I Co-58 6 130 <LLD N/A <LLD <LLD 0 I Fe-59 6 260 <LLD NIA <LLD <LLD 0 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 NIA <LLD <LLD 0 I Cs-137 6 150 <LLD N/A <LLD <LLD 0 I 26

I I TABLE 3-1: RADIOLOGICAL ENVIRONA/ENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Vrrginia ~ 2016 I Docket No. 50-280-281 Page 7 of7 Medium or Indicator Control I Pathway Sampled (Units)

Analysis Type

!Total No. LLD Locations Mean

-- Range Location with Highest Mean Name IDirection Distance I Mean

~ Range*

0 Locations Mean Range Non-Routine Reported Measurements I Crabs (pCilkg v.et)

Gamma K-40 1180 (1/1) SD 1.3 mi 1180 (1/1) NIA 0 I Mn-54 130 (1180 -1180)

<LLD NIA NNW (1180-1180)

<LLD NIA 0 I Co-58 130 <LLD N/A <LLD NIA 0 I Fe-59 260 <LLD NIA <LLD NIA 0 I Co-60 130 <LLD NIA <LLD NIA 0 NIA I Zn-65 26.0 < L:LD <LLD NIA 0 Cs-134 130 <LLD NIA <LLD NIA 0 I

Cs-137 150 <LLD NIA <LLD NIA 0 I

I I

I 27

I I 3.Z--Antilytical Results of2016 REMP Samples Radiological analyses of environmental media characteristically approach and frequently I is twobelowtimesthe the fall detection limits of state-of-the-art measurement methods. Tue reported error standard deviation (2cr) of the net activity. Unless otherwise noted, the

I thoverallli errdor (counting, sample sizde, chdemistry, errohrs, etthc.) is estimatded talo be to 5dtimes at *ste . Resu ts are consi ere positive w en 1 e measure v ue excee s cr 2

2 uncertam*1y*- -- - - ------------ -

--- --- ------~

~----

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 Surry ODCM.

I Data are givenGamma 1.

according to sample 1ype as indicated below.

Exposure Rate

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

4.

Air Particulates, Weekly 1-131 Air Particulates, Quarterly Gamma Spectroscopy

5. Cow 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 Surrv Power Station. Surtv Countv. Virginia - 2016 I MDD 0 =3xcr0 =3x1.0=3(5) Note: iF MDDu < 5 mR, THEN MDDu rounded to 5 mR (ANSI N13.37)

MDDA=3XO"A =3x2.8=8.8(10) Note: IFMDDA<lOmR, THEN MDDAroundedto lOmR(ANSI N13.37)

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

Dose,*

FQ'=.MQ- BQ Annual Base-line, BA Annual Moni-toring Annual Facility

,Dose,w tion Baseline, quarter) - -(mrem) (mrem) Data, FA=

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

MA-BA (mrem) i 19.8 19.7 . . 19.4 20.3 18.8 ND ND ND ND 79.7 78.3 ND I 3 4

5 19.1 17.7 18.9 19.4 17.0 18.8 17.9 16.4 19.7 19.7 18.8 20.3 19.7 18.2 19.4 ND ND ND ND ND ND ND ND ND ND ND ND 76.1 71.0 74.7 76.7 70.4 78.3 ND ND ND I 6 7

8 18.4 18.6 16.9 17.9 17.9 17.0 17.3 19.1 15.8 19.7 18.8 17.3 19.1

-18.8 17.6 ND ND ND ND ND ND ND ND No*

ND NID ND 73.5 74.1 67.8 74.0 74.6

~67.6 ND ND ND I*

9 23.1 22.8 23.4 23.7 23.1 ND ND ND ND 92.4 92.8 ND 10 18.2 17.6 17.0 19.4 17.6 ND ND ND ND 73.0 71.6 ND 11 16.0 16.7 16.1 16.7 16.1 ND ND ND ND 63.3 65.5 ND 12 16.o 15.8 16.1 17.0 16.7 ND ND ND ND 66.5 65.5" ND I 13 14 15 18.5-

11. 8 18.4 18.2

.18.2 18.2 17.3 15.5 16.4 19.1 19.4 18.5 19.l 18.5 18.8 ND ND ND ND ND ND ND ND ND ND ND ND 73.8 70.9 74.0 73.7 71.6 71.9 ND ND ND ND I 16 16.9 17.3 15.8 17.3. 17.6 ND ND ND 67.1 67.9 ND 18 14.3 14.9 13.7 .15.2 15.2 ND ND ND ND 56.5 58.8 ND 19 15.4 15.5 14.3 15.8 16.1 ND ND ND ND 61.6 61.6 ND 20 14.3 14.3 13.7 14.6 14.9 ND ND ND ND 57.1 57.3 ND I 21 22 15.0 13.0 14.9 13.0 14.6 12.7 16.1 13.3 15.8 13.7 ND ND ND ND ND ND ND ND 59.3 52.0 61.3 52.8 ND ND 23 17.8 18.2 16.1 18.2 18.5 ND ND ND ND 71.5 71.0 ND I 24 25 26 14.7 18.1 16.8 14.9 17.6 15.2 15.8 20.6 15.8 14.9 18.2 16.4 15.2 18.2 15.5 ND ND ND ND ND ND ND ND ND ND ND ND 58.3 71.7 68.7 60.7 74.6 62.8 ND ND ND 27 14.6 14.6 13.3 15.8 14.9 ND ND ND ND 58.2 58.5 ND I 28 29 14.1 13.1 14.3 13.3 13.0 12.7 15.2 13.3 14.6

. 13.3-ND ND ND ND ND ND.

ND ND 56.3 52.5 57.0 52.8 ND ND 30 14.4 15.5 14.0 15.5 14.3 ND ND ND ND 57.1 59.2 ND I 31 32 12.2 15.2 14.0 12.1 15.2 14.3 11.2 14.0 12.1 12.1 15.5 14.9 12.4 m

14.9 ND ND ND ND ND ND

ND ND ND ND N/A ND 49.3 61.1 56.2 47.9 59.5 56.1 ND ND ND 33 I 34 35 36 15.9 18.3 18.5 15.8 18.8 18.5 14.3 18.5 19.1 17.6 20.6 20.0 16.4 19.7 18.2 ND ND ND ND ND ND ND ND ND ND ND ND 63.3 72.0 73.1 64.0 77.7 75.8 ND ND ND 37 15.3 15.2 13.7 16.4 15.8 ND ND ND ND 61.4 61.0 ND I 38 39 21.0 14.8 20.6 14.9 19.7 14.9 21.2 15.5 20.9 14.6 ND ND ND ND ND-ND ND ND 84.3 58.9 82.5 59.8

.ND ND 40 16.1 16.1 16.7 17.6 16.1 ND ND ND ND 63.8 66.4 ND I 41 42 43 21.7 16.2 14.3 21.8 1io 15.2 20.0 15.5 13.3 22.4 16.7 14.6 21.8 16.7 14.3 ND ND ND ND ND ND ND ND ND ND ND ND 87.2 64.4 57.0 86.1 65.8 57.3 ND ND ND I* *No= Not detected, where MQ < (BQ + MDD 0 )

bND =Not detected, where MA< (BA+ MDDA) d =Damaged TLDs I m = MissingTLDs N/A =Missing or Damaged TLD Reading Not Available for Calculation Note: Table formatted in accordance with ANSl/HPS N13.37-2014, Environmental *oosimetry-Criteria for system Design and Implementation.

I 29

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Suny Nuclear Power Station, Suny County, Virginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page2of2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN July 05 10.7 +/- 2.45 11.3 +/- 2.48 17.0 +/- 2.85 12.3 +/- 2.51 13.5 +/- 2.62 12.9 +/- 2.55 10.5 +/- 2.39 14.9 +/- 2.64 July 12 9.23 +/- 2.32 10.3 +/- 2.40 15.6 +/- 2.77 11.1 +/- 2.44 12.8 +/- 2.60 12.3 +/- 2.54 10.3 +/- 2.40 10.8 +/- 2.43 July 19 13.7 +/- 2.84 12.5 +/- 2.79 21.4 +/- 3.31 11.2 +/- 2.70 15.7 +/- 3.09 13.4 +/- 2.93 14.3 +/- 2.87 13.7 +/- 2.83 July 26 20.5 +/- 3.14 40.9 +/- 3.16 32.4 +/- 3.76 24.2 +/- 3.33 23.2 +/- 3.34 24.4 +/- 3.32 18.9 +/- 3.03 22.3 +/- 3.19 I

I I

I '

August 02 12.7 +/- 2.46 17.3 +/- 2.74 12.8 +/- 2.51 12.2 +/- 2.43 14.6 +/- 2.64 15.2 +/-

. I 2.63 13.8 +/- 2.52 14.5 +/- 2.56 August 09 13.8 +/- 2.65 12.1 +/- 2.56 20.5 +/- 3.08 13.7 +/- 2.66 16.3 +/- 2.89 13.4 +/- 2.66 12.5 +/- 2.6 11.9 +/- 2.54 August 15 7.20 +/- 2.81 5.75 +/- 2.71 9.51 +/- 3.02 6.53 +/- 2.75 7.62 +/- 2.92 8.03 +/- 2.87 6.86 +/- 2.86 5.77 +/- 2.68 August 22 11.9+/-2.62 9.49 +/- 2.46 12.6 +/- 2.67 9.96 +/- 2.45 12.:3 +/- 2.65 11.2+/-2.54 11.6 +/- 2.56 10.5 +/- 2.47 August 29 9.39 +/- 2.34 12.5 +/- 2.54 17.9 +/- 2.89 11.8 +/- 2.49 13.3 +/- 2.63 13.9 +/- 2.62 13.1 +/- 2.57 12.4 +/- 2.51 I

September 06 15.5 +/- 2.48 1'5.3 +/- 2.47 19.4 +/- 2.73 17.4 +/- 2.57 17.0 +/- 2.60 17.7 +/- 2.67 16.3 +/- 2.51 15.0 +/- 2.42 September 13 18.8 +/- 2.89 19.6 +/- 2.93 30.4 +/- 3.50 22.6 +/- 3.08 25.7 +/- 3.29 21.0 +/- 3.02 24.7 +/- 3.21 16.9 +/- 2.80 September 20 9.06 +/- 2.45 10.2 +/- 2.53 11.6 +/- 2.65 12.2 +/- 2.63 10.6 +/- 2.58 11.6+/-2.60 8.50 +/- 2.41 10.0 +/- 2.48 September 27 11.0 +/- 2.46 10.6 +/- 2.44 11.7 +/- 2.53 10.5 +/- 2.40 9.55 +/- 2.40 11.7+/-2.51 9.84 +/- 2.42 8.27 +/- 2.27 Qtr. Avg. +/- 2 s.d. 12.6 +/- 7.8 12.9 +/- 8.6 17.9 +/- 14.1 13.5 +/- 10.0 14.8+/-10.1 14.4 +/- 8.8 13.2 +/- 9.5 12.8 +/- 8.3 October 04 10.5 +/- 2.39 11.0 +/- 2.42 15.1 +/- 2.72 11.1 +/- 2.41 11.5 +/- 2.49 12.8 +/- 2.51 7.89 +/- 2.20 9.71 +/- 2.29 October 11 10.8 +/- 2.44 11.5 +/- 2.48 12.2 +/- 2.63 8.52 :+/-; 2.36 12.0 +/- 2.85 7.05 +/-I 2.28 6.25 +/- 2.24 5.71 +/- 2.18 October 18 14.0 +/- 2.82 14.3 +/- 2.83 20.8 +/-'3.18 6.21 +/- 2.26 16.7 +/- 2.96 14.8 +/- 2.80 12.9 +/- 2.71 12.0 +/- 2.63 October 25 10.7 +/- 2.39 17.6 +/- 2.80 20.3 +/- 3.07 15.1 +/- 2.73 15.1 +/- 2.78 17.0 +/- 2.85 14.3 +/- 2.68 11.8 +/- 2.51 Nm.ember 01 16.4 +/- 2.95 20.0 +/- 3.16 24.5 +/- 3.36 19.2 +/- 3.01 17.8 +/- 3.01 18.4 +/- 2.98 19.0 +/- 3.02 13.0 +/- 2.67 No'vember 8 0.30 +/- 1.75 1.9.6 +/- 2.99 25.4 +/- 3.40 19.0 +/- 3.Ci2 22.0 +/- 3.24 18.5 +/- 3.01 t8.4 +/- 3.02 17.1 +/- 2.91 No'vem ber 15 17.4 +/- 3.01 12.7 +/- 2.74 20.0 +/- 3.13 16.4 +/- 2.88 15.7 +/- 2.89 13.1 +/- 2.67I 15.7 +/- 2.84 12.3 +/- 2.61 No'vember 22 34.1 +/- 3.76 23.0 +/- 3.27 33.1 +/- 3.79 24.5 +/- 3.35 20.0 +/- 3.18 25.5 +/- 3.40 22.4 +/- 3.26 19.6 +/- 3.10 No'vember 29 25.9 +/- 3.43 16.1 +/- 2.95 22.6 +/- 3.35 21.8 +/- 3.26 21.2 +/- 3.25 18.0 +/- 3.04 18.2 +/- 3.07 13.3 +/- 2.76 I

December 05 21.0 +/- 3.25 16.2 +/- 2.97 23.8 +/- 3.45 19.0 +/- 3.13 15.7 +/- 2.98 18.4 +/- 3.08 17.7 +/- 3.06 15.1 +/- 2.85 December 12 13.4 +/- 2.71 8.45 +/- 2.39 11.8 +/- 2.64 11.3 +/- 2.58 9.88 +/- 2.51 10.3 :!! 2.52 10.1 +/-2.51 7.45 +/- 2.32 December 19 20.5 +/- 3.02 12.7 +/- 2.58 21.7 +/- 3.11 16.3 +/- 2.78 14.6 +/- 2.72 18.1 +/- 2.88 15.2 +/- 2.74 16.3 +/- 2.76 December 26 24.4 +/- 3.23 19.2 +/- 2.96 22.1 +/- 3.16 15.8 +/- 2.77 19.7 +/- 3.04 19.3 +/- 2.96 '.17. 7 +/- 2.90 17.4 +/- 2.88 Qtr. Avg. +/- 2 s.d. 18.3 +/- 14.5 15.6 +/- 8.5 21.0 +/- 11.4 15.7 +/- 10.5 16.3 +/- 7.6 16.3 +/- 9.3 15.1 +/- 9.4 13.1 +/- 8.0 Ann. Avg. +/- 2 s.d. 14.2 +/- 12.8 13.5 +/- 9.0 18.5 +/- 13.6 14.2 +/- 10.4 15.0+/-9.1 14.6 +/- 9.3 13.6 +/- 9.6 12.5+/-8.1 No~mber 8: SS had <Minimum Detectable Acti'vity 31

.------------------------------------------------------~----------

TABLE 3-4: IODINE-131 CONCENTRATIONJN FILTERED AIR Surry Power Station, Surry County, Vrrginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page 1 of2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C f 1 January 05 10.1 +/- 26.2 10.1 +/- 26.4 10.2 +/- 26.6 9,97 +/- 26.0 -10.9 +/- 26.2 -10.i +/- 25.7 -10.6 +/- 25.4 -10.4 +/- 25.0 January 12 -5.48 +/- 17.5 -5.45 +/- 17.5 -5.52+/-17.7 -5.38 +/- 17.2 -2.32 +/- 23.3 -2.27 +/-:22.8 -2.25 +/- 22. 7 -2.2 +/- 22.3 January 19 ~.40 +/- 14.1 9.42 +/- 14.1 9.74 +/- 14.6 9.35 +/- 14.0 11.3 +/- 21.4 11.0.+/-i20.7 10.9 +/- 20.5 10.7+/- 20.3 January 26 -1.64 +/- 5.82 -4.22 +/- 14.9. -4.33 +/- 15.3 -4.17 +/- 14.8 -4.36 +/- 15.5 10.9.. +/- I 20.6 1

10.7 +/- 20.3 10.5 +/- 19.9 February 02 20.4 +/- 21.1 20.4 +/- 21.1 20.8 +/- 21.5 19.9 +/- 20.6 -10.7 +/- 19.2 -10.4 +/- 18.7 -10.3 +/- 18.5 -10.3 +/- 18.4 February 09 1.22 +/- 34.4 1.22 +/- 34.3 1.27 +/- 3.58 1.21 +/- 34.2 2.98 +/- 35.9 3.24 +/- 39.0 2.87 +/- 34.5 2.84 +/- 34.1 February 16 11.6+/-20.6 11.6+/-20.7 11.9+/-21.1 11.5+/-20.5 -2.60 +/- 18.1 -2.51 +/- 17.5 -2.51 +/- 1i7.5 -2.45 +/- 17.0 February 22 1.56 +/- 23.4 1;5'6 +/- 23.4 1.59 +/- 23.9 1.54 +/- 23.1 -1.10 +/- 27.9 -1.06 +/- 27.0 -1.06 +/- 27.0 -1.05 +/- 26.6'

I

~ I I *:I I I

March 01 -6.25 +/- 18.2 -6.25 +/- 18.2 -6.45 +/- 18.8 -6.25 +/- 18.2 16. 7 +/- 19.4 16.1 +/- 18.7 16.3 +/- 1.9.0 15.9 +/- 18.5 March 08 -4.06 +/- 6.14 -10.6 +/- 15.9 -10.8 +/- 16.3 -10.5 +/- 15.8 -3.17 +/- 16.8 -3.09 +/- 16.4 -3.09 +/- 16.4 -3.Q6 +/- 16.2 March 15 6.04 +/- 15.2 6.10 +/- 15.3 6.20 +/- 15.6 6.03 +/- 15.1 0.97 +/- 13.~ 0.94 +/- 13.1 0:94 +/- 13.1 0.94 +/- 13.Q March 22 . -6.00+/-10.7 -5.97 +/- 10.7 -6.09 +/- 10.9 -5.94 +/- 10.6 -7.35 +/- 10.8 -7.22 +/- 10.6 -7.25 +/- 10.7 -7.13 +/- 10.5 March 29 -22.0 +/- 24.2 ~22.1 +/- 24.3 -22.3 +/- 24.5 -21.8 +/- 24.0 6.65 +/- 32.0 6.41 +/- 30.8 6.40 +/- 30.8 6.35 +/- 30.5 l

April 05 -9.00 +/- 32.4 -9.111 +/- 32.8 -9.17 +/- 33.0 -8.96 +/- 32.3 -5.28 +/- 29. 7 -5.11 +/- 28.8 -5.11 +/- 28.8 -5.08 +/- 28.6 April 12 -12.6 +/- 19.4 -12.'6 +/- 19.5 -28.3 +/- 43. 7 -12.4 +/- 19.1 5.72 +/- 12.9 5.51 +/- 12.4 5.46 +/- 12.3 5.42 +/- 12.2 April 19 -0.36 +/-- 27.3 -0.36 +/- 27.6 -0.37 +/- 28 -0.36 +/- 27.4 -13.4 +/- 25.0 -13.1 +/- 24.6 -13.2 +/- 24.6 -12.9 +/- 24.2 .

April 25 2.24 +/- 10.7 2.25 +/- 10.7 2.29 +/- 10.9 2.23 +/- 10.7 -1.22 +/- 16.3 -1.19.+/-15.9 -1.19 +/- 15.9 -1.18+/-15.8 May 03 -2.63 +/- 13.6 -2'.37 +/- 13. 7 -2.41 +/- 13.9 -2.35 +/- 13.6 6.30 +/- 16.2 6.12 +/- 15.8 6.11 +/- 15. 7 6.00 +/- 15.5 May 10 -6.16+/-11.3 -6.16 +/- 11.3 -6.30 +/- 11.6 -6.12 +/- 11.2 16.3 +/- 13.6 16.0 +/- 13.3 15.9 +/- 1.3.3 15.6, +/- 13.0 I

May 17 2.21 +/- 19.4 2.20 +/- 19.3 2.23 +/- 19.6 2.18 +/- 19.2 -4.09 +/- 19.9 -3.99 +/-1 19.4 -3.99 +/- 19.4 -3.88, +/- 18.91 I I May 24 17.4 +/- 37.7 17.3 +/- 37.6 17.9 +/- 38.8 15.8 +/- 37.7 16.1 +/- 38.6 15.8 +/-* 37.7 6.65 +/- 14.4 6.48 +/- 15.5 May 31 -19.4 +/- 45.4 -19.4 +/- 45.4 -19.9 +/- 46.5 -19.3 +/- 45.0 -2.89 +/- 38.0 -2.78 +/- 36.6 -2.81 +/- 36.9 -1.16+/-15.2 II I I i June 07 -7.91 +/- 21.9 -7.:86 +/- 21. 7 -7.94 +/- 22.0 -7.73+/-21.4 4.37 +/- 30.9 4.2f +/- 29,7 4.19~ +/- 29~6 4.14 +/- 29.2 June 13 -5.06 +/- 29.6 -5.06 +/- 29.6 -7.04 +/- 43.7 -5.03 +/- 29.4 -5.13 +/- 30.0 -6.86'.+/-,42.6 -6.86 +/- 42.'6 . -6.75 +/- 41.9 June 20 3.36 +/- 20.9 3.36 +/- 20.9 3.43 +/- 21.3 3.32 +/- 20.7 -22.3 +/- 41.7 -21.6 +/- :40.4 -21.5 +/- 40.4 -8.24 +/- 15.4 June 28 9.20 +/- 25.0 9.19 +/- 25.0 9.44 +/- 25.7 9.08 +/- 24.7 1.51 +/- 17.8 1.47+/-17.2 1.46 +/- 17.2 1.45 +/- 17.0 i!

\!

I i ;i

' i 32

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Suny Power Station, Suny County, Vrrginia - 2016 1.0E-3 pCi/m3 +/- 2 Sigma Page2 of2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE, NN-C July 05 -25.3 +/- 40.5 -25.2 +/- 40.4 -25.7 +/- 41.2 -24.6 +/- 39.5 -27.0 +/- 34.4 -26.5 +/- 33.7 -26.2 +/- 33.4 -25.9 +/- 33.0 July 12 -11.4 +/- 18.4 -11.5 +/- 18.5 -11.8 +/- 18.9 -11.4 +/- 18.3 -14.0 +/- 22.5 13.7 +/- 22.0 13.6+/-21.8 13.5+/-21.7 July 19 3.44 +/- 19.3 3.47 +/- 19.5 3.53 +/- 19.8 3.45 +/- "rn.4 -29. 7 +/- 25.8 -29.2 +/- 25.5 -27.7 +/- 24.1 -27.5 +/- 23.9 July 26 -7.17 +/- 24.9 2.02 +/- 17.0 -7.32 "+/- 25.4 -7.14 +/- 24.8 2.06 +/- 17.3 -7.05 +/- 24.5 1.97 +/- 16.6 1.95 +/- 16.4 August 02 -27.8 +/- 29.0 -27.9 +/- 29.1 -28.5 +/- 29.7 -27.9 +/- 29.0 -19.7 +/- 24.3 -19.1 +/- 23.6 -18.9 +/- 23.3 -7.29 +/- 8.99 August 09 8.06 +/- 21.2 8.09 +/- 21.3 8.29 +/- 21.8 8.10 +/- 21.3 0.73 +/- 25.2 *0.70 +/- 24.4 . 0.70 +/- 24.4 0.69 +/- 24.0 August 15 -11.3 +/- 41.2 -11.2+/-41.1 -11.5 +/- 42.2 -11.2 +/- 40.8 5.72 +/- 36.7 5.54 +/- 35.6 56.9 +/- 36.6 5.43 +/- 34.9 August 22 -6.27 +/- 16.0 -6.27 +/- 16.0 -6.31+/-16.1 -6.11+/-15.5 2.57 +/- 13.0 2.50 +/- 12.7 2.49 +/- 12.6 2.45 +/- 12.4 August 29 0.73 +/- 11.2 0.73+/-11.2 0.74 +/- 11.4 0. 72 +/- 11.1 4.48 +/- 9.46 4.38 +/- 9.24 4.36 +/- 9.19 4.30 +/- 9.08 September 06 13.9 +/- 26.1 13.9 +/- 26.1 '14.2 +/- 26.6 13.7 +/- 25.7 -4.66 +/- 21.7 -4.73 +/- 22.Q -4.47 +/- 20.8 -4.41 +/- 20.5 September 13 -4.52 :!;: 19.4 -4.52 +/- 19.4 -4.64 +/- 19.9 -4.51 +/- 19.4 2.77+/-15.9 2.71 +/- 15.5 2. 72 +/- 15.5 2.67 +/- 15.3 September 20 -19.3 +/- 18.3 -19.3 +/- 18.3 -19.7 +/- 18.7 -19.1+/-18.1 7.36 +/- 21.0 7.19+/-20.5 7.18 +/- 20.5 I

2.74 +/- 7.82 September 27 -2.01 +/- 15.4 . -2.01 +/- 15.4 -2.04 +/- 15.7 -1.97 +/- 15.1 -6.66 +/- 15.0 -6.53 +/- 14.7 -6.62 +/- 14.9 -6.41 +/- 14.5

'I October 04 -3.77 +/- 23.5 -3.77 +/- 23.5 -3.87 +/- 24.1 -3.72 +/- 23.2 -2.23 +/- 20.1 -2.14 +/- 19.3 -2.16 +/- 19.5 -0.82 +/- 7.38 October 11 -0.44 +/- 13.4 -0.45 +/- 13.4 -0.48 +/- 14.4 -0.46 I

+/- 14.0 9.37 +/- 20.1 8.21 +/- 17.6 8.27+/-17.7 8.14 +/- 17.4 October 18 2.93 +/- 14.6 2.91 +/- 14.5 2.95 +/- 14.6 2.81 +/- 14.0 -1.26 +/- 14.9 -1.21 +/- 14.4 -1.23 +/- 14.5 -1.20 +/- 14.2 October 25 1.27 +/- 9.94 1.28 +/- 10.0 1.37 +/- 10.7 1.34 +/- 10.4 -1.86+/-11.6 -1.82+/-11.3 -1.81+/-11.3 -1.77+/-11.0 November 01 19.8 +/- 35.7 19.9 +/- 35.9 19.8 +/- 35. 7 19.1 :!; 34.5 -13.0 +/- 34.1 -12.6 +/- 33.1 -12.6 +/- 33.2 -12.5 +/- 32.7 November 8 -2.14 +/- 21.1 -2.16+/-21.3 -2.32 +/- 22.9 -2.25 +/- 22.1 -8.43 +/- 20.0 -8.19 +/- 19.4 -8.23 +/- 19.5 -8.03 +/- 19.1 November 15 0.46 +/- 17.2 0.46 +/- 17.2 0.46 +/- 17.2 0.45 +/- 16.7 -12.6 +/- 18.9 -12.1+/-18.2 -12.3 +/- 18.4 -4.64 +/- 6.97 November 22 -14.4 +/- 25.7 -14.4 +/- 25.6 -14.8 +/- 26.5 -14.4 +/- 25.7 11.0 +/- 24.2 10.7+/-23.6 10.7 +/- 23.7 10.6 +/- 23.4

\

November 29 5.15+/-23.5 5.16 +/- 23.5 5.30 +/- 24.2 5.20 +/- 23.7 9.19 +/- 18.4 9.01 +/- 18.0 9.08 +/- 18.2 8.85+/-17.7 December 05 5.58 +/- 22.3 5.58 +/- 22.3 5.71 +/- 22.8 5.55 +/- 22.2 -2.91 +/- 19.6 -2.82 +/- 19.0 -2.84 +/- 19.2 -2.75 +/- 18.6 December 12 -0.42 +/- 9.60 -0.41 +/- 9.51 -0.42 +/- 9.72 -0.42 +/- 9.55 -0.89 +/- 7. 72 -0.88 +/- 7.62 -0.88 +/- 7.64 -0.86 +/- 7.51 December 19 1.99 +/- 10.6 1.97+/-10.5 2.01 +/- 10.7 1.97+/-10.5 5.50 +/- 13.3 5.40 +/- 13.1 5.44 +/- 1°3.2 5.28 +/- 12.8 December 26 -9.99 +/- 13.0 -9.93 +/- 12.9 -10.2 +/- 13.Z -9.86 +/- 12.8 8.05 +/- 14.4 7.79 +/- 13.9 7.85 +/- 14.0 7.81 +/- 13.9 33

TABLE 3.::s: GAMMA EMITTER CONCENTRAtiolV IN FILTERED AIR I Surry Power Station, Surry County, Vrrginia - 2016 I SAMPLING LOCATIONS 1.0E-3 pCi/m3 +/- 2 Sigma NUCLIDE FIRST QUARTER SECOND QUARTER THIRD QUARTER Page I ofl FOURTH QUARTER AVERAGE

- +/- 2 SIGMA __

I SS Cs-134 Cs-137 0.69 +/- 0.72 0.00 +/- 0.68

-0.22 +/- 0.90

-0.79 +/- 0.88 0.50 +/- 0.79 0.46 +/- 0.77

- 0.76 +/- 0.61 0.28 +/- 0.50 Be-7 124 +/- 22.2 192 +/- 34.2 136 +/- 31.4 1;33 +/- 23.2 146 +/- 61.8 I HIR Cs-134 0.26 +/- 0.65 0.93 +/- 1.03 - 0.63 +/- 0.87 -- 0.23 +/- 0.64 I Cs-137 Be-7 K-40

-0.37 +/- 0.50 126 +/- 21.5 0.79 134 14.9

+/-

0.96 35.2 12.8

-0:62-*+/- 0.62 144 +/- 28.4

-0;11 +/-" 0.81 125 +/- 27.1 132 +/- 17.6 14.9 +/- 12.8 I BC Cs-134 Cs-137

-0.03 +/- 0.77

-0.34 +/- 0.69 0.66 +/- 0.86

-0.16 +/- 0.93 1.22 +/- 1.33

-0.19 +/- 1.24 0.64 +/- 0.82 0.57 +/- 0.65 Be-7 122 +/- 33.5 156 +/- 36.2 132 +/- 36.5 162 +/- 27.0 143 +/- 38.2 I

ALL Cs-134 0.33 +/- 0.87 0.37 +/- 0. 76 0.00 +/- 0. 72 -0.12 +/- 1.21 I Cs-137 Be-7

-0.16 +/- 0.80 115 +/- 30.3 0.00 +/- 0.71 169 +/- 26.9 0.13 +/- 0.66 218 +/- 33.4

-0.21 +/- 1.10 139 +/- 32.7 160 +/- 88.8 I CP Cs-134 Cs-137 0.86 +/- 0.80

-0.51 +/- 0.68

-0.05 +/- 0.63

-0.60 +/- 0.61 0.04

-0.21

+/-

0.98 0.83 0.01 +/- 0.78

-0.03 +/- 0.67 Be-7 112 +/- 24.8 140 +/- 23.3 146 +/- 28.6 142 +/- 26.7 135 +/- 31.1 I K-40 16.3 +/- 12.7 16.3 +/- 12.7 BASF Cs-134 0.11 +/- 1.13 0.81 +/- 1.19 1.74 +/- 1.41 0.53 +/- 0.87 I Cs-137.

Be-7

-0.30 +/- 1.15 154 +/- 39.1 0.99 +/- 1.08 170 +/- 36.5 0.08 +/- 1.12 142 +/- 37.6

-0.32 +/- 0.77 115 +/- 32.7 145 +/- 46.4 I FE Cs-134 Cs-137 0.66 +/- 0.92 0.88 +/- 0.79

-0.51 +/- 0. 75

-0.22 +/- 0.80 2.01 +/- 0.89 0.22 +/-. 0.75 0.45 +/- 1.05 0.43 +/- 0.92 Be-7 146 +/- 30.4 149 +/- 27.6 108 +/- 25.7 86.7 +/- 32.6 122 +/- 60.5 I

NN-C Cs-134 -0.33 +/- 0.75 1.68 +/- 0.82 -0.35 +/- 0.87 -0.32 +/- 0.74 I Cs-137 Be-7 0.31 +/- 0.80 115 +/- 24.8 0.18 +/- 0.69 163 +/- 28.3 0.39 +/- 0.67 150 +/- 30.3 0.04 +/- 0.61 99.0 +/- 20.9 132 +/- 59.6 I

I I 34

I I

I TABLE 3-6: GA.MMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK I Surry Power Station, Surry County, Vugii:im *- 2016 pCi/Llter +/- 2 Sigma Page 1 of3 I NUCLIDE EPPS COLONIAL PARKWAY WILLIAMS-C

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

I JANUARY Cs-134 Cs-137

-9.41 5.08

+/-

5.60 6.12

-5.36

-1.62

+/-

6.09 4.57

-0.93

-5.42

+/-

4.68 4.78 Ba-140 16.2 +/- 25.1 13.7 +/- 27.1 -6.81 +/- 20.8 I La-140 1-131

-1.27

-0.16

+/-

7.46 0.12 2.07

-0.13

+/-

6.45 0.16

-0.67

-0.16

+/-

6.64 0.12 K-40 - - - - 1180 +/- 200 1080 +/- 211 1420 +/- 194 I

FEBRUARY I Cs-134 Cs-137 2.03

-2.10

+/-

4.86 5.17

-0.41 0.71

+/-

6.18 6.02

-1.67 0.53

+/-

4.34 4.49 Ba-140 -1.72 +/- 22.8 1.49 +/- 24.5 2.01 +/- 17.9 I La-140 1-131

-3.08

-0.15

+/-

5.60 0.25 3.97 0.21

+/-

8.24 0.45 0.16

-0, 12

+/-

5.48 0.24 K-40 1400 +/- 202 1200 +/- 199 1420 +/- 191 I MARCH Cs-134 -5.63 +/- 4.38 3.35 +/- 4.56 -0.56 +/- 4.28 I Cs-137 Ba-140 La-140

-3.04

-1.38 3.24

+/-

4.99 19.3 5.21 3.25

.92

-1.46

+/-

4.83 18.3 5.64 1.81

-3.97 0.71

+/-

4.74 18.7 4.73 I 1-131 K-40 Sr-89

-0.19 1220

+/-

0.36 163 0.08 1460 3.02

+/-

0.46 203 2.84

-0.11 1270

+/-

0.28 159 Sr-90 0.28 +/- 0.20 I

APRIL I Cs-134 Cs-137

-5.42 4.56

+/-

5.42 7.33

-2.11

-0.41

+/- 5.44

+/- 6.01 Ba-140 6.38 +/- 23.3 4.67 :t 24.3 I La-140 1-131 4.09 0.12

+/-

7.58 0.30 1.66 0.03

+/-

6.61 0.14 K-40 1180 +/- 222 1450 +/- 204 I

I I

I 35

I I TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK I Suny Power Station, Suny County, Vrrginia - 2016 pCi/Liter +/- 2 Sigma Page2 of3 I NUCLIDE EPPS COLONIAL PARKWAY LOVER RETREAT-C I MAY Cs-134 Cs-137

-5.17

-1.87

+/-

6.25 5.36 .

0.30 1.04

+/-

5.89 6.25

-7.60 1.96

+/-

5.53 5.00 Ba-140 4.19 +/- 23.5 15.7 +/- 21.4 -19.7 +/- 29.9 I La-140 1-131

-1.51

-0.14

+/-

5.20 0.33 6.80

-0.26

+/-

6.96 0.34 4.98

-0.27

+/-

7.06 0.43 K-40 1490 +/- 248 1520 +/- 201 1680 +/- 185 I

JUNE I Cs-134 Cs-137 0.11 1.10

+/-

3.97 4.07

-2.50

-2.2-1

!: 3.99

+/- 3.39

-5.42

--0.74

+/-

3.50 3.41 Ba-140 9.93 +/- 22.8 6.39 +/- 20.9 4.20. +/- 17.0 I La-140 1-131

-5.56

-0.08

+/-

6.15 0.35

-5:93 0.52

+/-

5.16 0.46 3.95 0.24

+/-

4.64 0.34 K-40 1500 +/- 192 1410 +/- 152 1580 +/- 153 I Sr-89 Sr-90 4.17 1.65

+/-

2.92 0.48 I JULY Cs-134 Cs-137

-7.61

-4.08

+/-

5.13 5.21 0.54 0.37

+/-

5.02 5~ 17

-3.69 0.79

+/-

4.10 3.79 I Ba-140 La-140 1-131 6.09 1.76 0.21

+/-

20.5 5.94 0.22 13.4 0.81 0.08

+/-

21.4 6.36 0.25 3.18 3.99

-0.08

+/-

19.7 5.09 o*.11 K-40 1330 +/- 189 1410 +/- 202 1850 +/- 174 I AUGUST Cs-134- -16.3 +/- 6.45 -3.26 +/- 4.28 -9.45 +/- 6.36 I Cs-137 Ba-140

-1.55 1.06

+/-

6.15 26.4 0.57

-7.71

+/-

4.57 16.8 1.81 12.6

+/-

6.27 28.4 La-140 2.98 +/- 7.72 1.19 +/- 4.-84 -0.88 +/- 6.62 I 1-131 K-40 0.02 1450

+/-

0.42 231 0.14 1300

+/-

0.57 159 0.07 1450

+/-

0.45 232 I

I I

I 36

I I

I TABLE 3-6: GA1J1MA Ek!ITTER AND STRONTIUM CONCENTRATIONS IN MILK I Surry Power Station, Surry County, Virginia- 2016 pCi/Liter +/- 2 Sigma Page3of3 I NUCLIDE EPPS COLONIAL PARKWAY LOVER RETREAT-C I SEPTEMBER Cs-134 Cs-137

-2.66

-3.5-8

+/-

5.42 5.74

-3.13

-1.08

+/- 4.52

+/- 4.72 1.42 +/- 6.51 2.12 +/- 7.09 Ba-140 0.56 +/- 30.2 . 2.95 +/- 21.9 13.2 +/- 32.6 I La-140 .

1-131

-8.14

-0.08

+/-

9.17 0.22

-6.71 0.02

+/- 8.05 L0.36

-3.84 +/- 9.88

-0.22 +/- 0.29 K-40 1280 +/- 212 1530 -+/- 170 1760 +/- 218 I Sr-89 Sr-90 3.43 1.79

+/- 2.34

+/- 0.50 .

I OCTOBER Cs-134 0.43 +/- 8.67 13.9 +/- 7.67 A 18.1 +/- 8.71 A Cs-137 1.86 +/- 5.86 5.69 +/- 5.68 4.68 +/- 7.42 I Ba-140 La-140 18.9 +/- 26.9 5.57 +/- 6.45 10.1 2.86

+/-

24.5 7.98 11.1 0.35

+/-

28.2 9.01 1-131 0.06 +/- Oo27 0-.24 +/- 0.49 0.48 +/- 0.41 I K-40 1470_ +/- 178 1360 +/- 136 1650 +/- 205 NOVEMBER I Cs-134 Cs-137_

Ba-140

-0.23

-5.66 12.4

+/-

4.71 4.76 22.4

-0.18 1.40

-29.0

+/- 6.37

+/- _5.25

+/- 27.0 38.2 +/- 7.75A *

-1.08 +/- 5.32

-1.17 +/- 24.7 I La-140 7.86 +/- 7.74 -3.34 +/- 7.51 0.33 +/- 5.76 i

1-131 0.16 +/- 0.39 0.14 +/- 0.49 0.22 +/- 0.39 K-40 1400 +/- 188 1230 +/- 195 1680 +/- 154 I DECEMBER Cs-134 -7.82 +/- 6.58 -8.33 +/- 4.95 -4.48 +/- 5.52 Cs-137-

2.65. +/- 7 .. 00- 2.46 * :t 4.13 - 2.69 +/- 5.45 I Ba-140 La-140 3.44 0.98

+/-

27.0 4.89 8.38

-1.86

+/-

18.9 6.93 2.38

-5.54

+/-

20.2 6.37 1-131 0.08 +/- 0.40 0.12 +/- 0.38 -0.13 +/- 0.40 I K-40 Sr-89 1210 +/- 209 1310 1.61

+/-

186 2.53

'1420 +/- 213 Sr-90 1.33 +/- 0.53 I

A: Compound/analyte not detected. Peak not identified.

I I

I 37

I

I TABLE 3-7: GAMMA EMITTER CONCENTRATION IN FOOD PRODUCTS .

I Suny Power Station, Suny County, Vrrginia-2016 pCi/kg (wet)+/- 2 Sigma Page 1 of I I SAMPLING COLLECTION LOCATIONS DATE SAMPLE TYPE ISOTOPE Cs-134 Cs-137 1-131

K-40 I BROCK FARM 11/10/2016 Com 1.33+/-10.1 0.53 +/- 10.9 -3.27 +/- 13.9 4730 +/- 460 Cs-134 Cs-137 1-131 K-40 .

1* 11/10/2016 Peanuts 3.66 +/- 13.7 3.63 +/- 15.2 0.34 +/- 17.3 5730 +/- 545 I SLADE FARM 11/10/2016 Soybeans Cs-134

-8.15 +/- 19.7 Cs-137 6.33 +/- 18.6 1-131

-3.54 +/- 23.8 K-40 22900 +/- 1210 I

I I

I 38

I I TABLE 3-8: GAMMA EMITTER AND1'RITIUM CONCENTRATIONS IN WELL WATER.

I pCi/liter +/- 2 Sigma Surry Power Station, Surry County, Vrrginia - 20.16 Page 1 of2 SAMPLING COLLECTION I LOCATIONS DATE ISOTOPE Mn-54 ** - Co-58 - ~ Fe-59 Co - Zn-65 I SS '3/1/2016 - *- -0.08 +/- 2.79 6/6/2016 3.H> +/- 2.71 2.96 +/- 3.53

-1.56 +/- 2.78

-_ 2.26 +/- 7.08 1.05 +/- 5.78

-0.38 +/- 3.54 1.26 +/- 2.82

-5. 70 ' +/- 7.02

-5.99 +/- 5.59 9/5/2016 -0.73 +/- 3.06 0.52 +/- 3.16 -2.95 +/- 5.87 1.26 +/- 2.68 -1.71 +/- 7.52 I '12/5/2016 0.12 +/- 3.00 0.91 +/- 3.39 -0.99 +/- 5.01 0.68 +/- 3.50 0.06 +/- 7.28 Nb-95 Zr-95 1-131 Cs-134 Cs-137 I 3/1/2016 6/6/2016 9/5/2016

-3.66 1.15 5.46

+/- 3.21

+/- 2.75

+/- 3.?G 2.87

-4.99

-0.29

+/- 5.44

+/- 4.97

+/- 5.09

-0~09 +/- 0.25 0.10 +/- 0.27

-3.73 +/- 5.64

-3.10

-5.90 2.01

+/- 3.57

+/- 2.79

+/- 3.33

-1.31 1.15 0.39

+/- 3.15

+/- 2.97

+/- 3.19 12/5/2016 1.89 +/- 3.38 7.00 +/- 5.62 0.17 +/- 0.42 2.35 +/- 3.29 0.09 +/- 3.02 I Ba-140 La-140 H-3 Ra-226 3/1/2016 -2.18 +/- 14.7 -5.09 +/- 5.11 227 +/- 880 I 6/6/2016 9/5/2016

.* -2.14

-14.3

t 15.7

+/- 16.4

-3.30

-2.94

+/- 5.81

+/- 4.84 108 228

+/-

533 570 113 +/- 106 12/5/2016 13.6 +/- 11.1 -2.07 +/- 3.75 404 +/- 531 I Mn-54 Co-58 ' Fe-59 Co-60 Zn-65 I HIR 3/1/2016 6/7/2016 9/6/2o1'6

-0. 72

-1.15 0.92

+/- 2.99

+/- 2.66

+/- 2.67 1.50 0.57 1.18

+/- 2.91

+/- 2;71

+/- 2.82 1.93 2.82 4.58

+/- 5.59

+/- 6.46

+/- 5.25

-0.96 0.24

-0.45

+/- 2.43

+/- 2.51

+/- 2.76

-9.33

-7.25

-0.40

+/- 6. 71

+/- 6.16

+/- 6.13 12/5/2016 -1.61 +/- 3.69 -0.82 +/- 3.97 0.00 +/- 8.04 2.02 +/- 4.88 -3.55 +/- 8.48 I Nb-95 Zr-95 . 1-131 Cs-134 Cs-137 3/1/2016 -1.38 +/- 3.04 0.30 +/- 5.59 -0.24 +/- 0.27 0.61 +/- 3.00 -0.36 +/- 3.31 I 6/7/2016 9/6/2016

-0.04 0.63

+/- 2.59

+/-' 2.79

-1.52 0.93

+/- 4.84

+/- 4.52 0.08

-2.87

+/- 0.20

+/- 4.96 1*.29

-1.39

+/- 2.92

+/- 2.80

-0.04

-2.57

+/- 3.00

+/- 2.85 12/5/2016 0.98 +/- 4.29 1.37 +/- 6.82 0.38 +/- 0.43 -6.00 +/- 4.93 0.07 +/- 3.93 I 3/1/2016 7.89 Ba-140

+/- 13.4 -1.53 La-140

+/- 3.75 813 H-3

+/- 944 I 6/7/2016 9/6/2016 12/5/2016 9.52

-12.7

-6.38

+/- 15.4

+/- 13.0

+/- 15.90

-0.13 3.01

-2.81

+/- 4.28

+/- 4.30

+/- 5.29 31.9

' -205 170

+/- 526

+/- 543

+/- 505 I

I I

I 39 I

I I TABLE 3-8: GA.MMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER-I pCi/Llter +/- 2 Sigma Surry Power Station, Surry Omnty, Virginia - 2016 Page2 of2 I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE.

Mn-54 Co-58 . Fe-59 Co-60 Zn-65 I cs 3/1/2016 6/6/2016 2.80 +/- 3.71 1.48 +/- 2.89

-1.72 +/- 3.90 1.39 +/- 2.76

-2.19 +/- 6.21 1.98 +/- 6.64

-0.72 +/- 3.75 1.23 +/- 2.84

-4.16 +/- 7.94

-4.60 +/- 5.83 9/5/2016 1.47 +/- 2.60 2.23 +/- 2.55 1.48 +/- 5.20 -0.37 +/- 2.45- -2.04 +/- 6.04 I 12/5/2016 -2.58 +/- 3.72 -1.10 +/- 3.90 3.72 +/- 7.13 -0.81- .+/- 3.55 -12.9 +/- 9.40 Nb-95 Zr-95 1-131 Cs-134-- CS:13T I 3/1/2016 6/6/2016

-1.25 +/- 3.87 0.36 +/- 2.87

-1:82 +/- 2.89

-3.47 +/- 6.14 2.41 +/- 4.93

-5.06 +/- 4.75

-0.28 +/- 0.23 0.34 +/- 0.33 0.18 +/- 3.56 0.83 +/- 2.67 3.03 +/- 3.53 1.01 +/- 2.97 9/5/2016 2.60 +/- 5.50 2.45 +/- 2.82 -1.10 +/- 2.72 I 12/5/2016 -3.42 +/- 3.38 Ba-140 0.60 +/- 5.81 La-140 0.22 +/- 0.39 H-3 1.90 +/- 3.77 K-40 0.65 +/- 3.62 3/1/2016 17.8 +/- 16.3 -1.67 +/- 5.52 395 +/- 946 I 6/6/2016 9/5/2016

-0.71 +/- 15.0 9.16 +/- 13.8

-4.09 +/- 5:13 0.03 +/- 4.77 485 12.4

+/-

569 557 66.8 +/- 54.8 12/5/2016 -1.56 +/- 15.4 -2.29 +/- 4.97 -117 .+/- 498 I

I I

I 40

I I TABLE 3--9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RWER WATER I pCi/Llter +/- 2 Sigma Surry Power Station, Surry County, Virginia - 2016 Page I of2 I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Mn-54 Co-58 * ** -~ Fe-59 .. Co-60 . Zn-65 I

e**

. SD 1/12/2016 -2.08 +/- 2.81 0.79 +/- 2.71 0.13 +/- 5.70 0.42 +/- 2.81 0.68 +/- 6.15 2/9/2016 -0.53 +/- 3.01 -0.54 +/- 2.89 -0.86 +/- 4.78 -0.71 +/- 2.58 -3.51 +/- 6.56 3/1/2016 0.99 +/- 3.89 2.56 +/- 4.71 11.3 +/- 7.83 -3.28 +/- 4:08 -6.43 +/- 9.00 I 4/1.1/2016 5/10/2016

-1.25 3.20

+/-

2.41 4.36 3.00 +/- 2.68 2.53 +/- 4.39

-2.22 1.24

+/- 4.46

+/- 6.15

-1.08 1.59

+/- 2.26

+/- 4.34

-12.0

-10.1

+/-

5.82 10.2 6/6/2016 -0.86 +/- 2.22 ----0.01 +/- 2.46 0. 75 +/- 5.53 - 0.39 +/- 2.12 -6.63 +/- 5.52 .

I 7/4/2016 8/2/2016 9/5/2016 2.80 1.23

-0.12

+/-

2. 79 2.69 3.47

-2. 78 +/- 3.20

-2.24 +/- 3.21

-0.51 +/- 3.21 0.84

-2.46 3.15

+/- 6.05

+/- 6.10

+/- 6.55

-0.57 0.44

-2.62

+/- 2.57

+/- 3.07

+/- 3.54

-4.74 2.62

-3.44

+/-

6.66 5.93 7.00 I 10/3/2016 11/1/2016 12/5/2016

-2.13 0.29

-0.28

+/-

4.66 2.54 4.37 0.01 +/- 4.83

-3.07 +/- 3.25

-1.94 +/- 4.39

5. 79 0.00

-2.29

+/- 8. 75

+/- 0.00

+/- 8.86 0.92

-1.29

-1.12*

+/- 4.30

+/- 2.60

+/- 5.34

-1.23

-3.30

-14.1

+/-

11.3 7.37 10.8 I 1/12/2016 0.80 Nb-95

+/- 2.65 1.57 Zr-95

+/- 4.69 1.34 1-131

+/- 4.56 Cs-134

-1.52 +/- 3.39 Cs-137

-1.30 +/- 3.12 2/9/2016 0.17 +/- 3.38 0.26 +/- 5.44 0.61 +/- 3.82 -5.85 +/- 3.29 -1.90 +/- 3:05-I 3/1/2016 4/11/2016

-2.14 0.84

+/-

3.72 2.69 1.29*

0.75

+/-

6.43 4.65

-1.45

-1.19

+/-

5.93 5.62 1.79 1.52

+/-

4.52 2.94 0.97

-1.16

+/-

4.35 3..05 5/10/2016 1.36 +/- 4.56 5.48 +/- 7.85 0.03 +/- 5.67 0.83 +/- 4.68 1.73 +/- 4.74

.I 6/6/2016 7/4/2016 0.15

-0.97

+/-

2.63 3.51

-0.21 2.34

+/-

4.62 6.08

-0.21

-2.59

+/-

5.32 5.50 0.17 1.79

+/-

2.49 2.68 1.26

-1.06 0.40

+/- 2.64

+/- 3.18

+/-. 3.48 8/2/2016 0.65 +/- 3.35 -0.91 +/- 5.02 3.07 +/- 5.55 3.33 +/- 3.01 I 9/5/2016 10/3/2016 11/1/2016 2.61 4.05

-0.12

+/-

3.65 5.51 3.00 4.01

-7.64 2.01

+/-

6.08 7.97 1.19 0.34 5.36 . 5.99

+/-

5.80 6.05 5.22

-0.12

-0.07 0.42

+/-

3.12 5.01 3.10

-2.02

-3.66 0.76

+/- 3.32

+/- 4.96

+/- 2.83 12/5/2016 2.16 +/- 3.59 6.87 +/- 6.50 -5.70 +/- 5.96 -5.64 +/- 4.54 1.68 +/- 4.15 I Ba-140 La-140 H-3 K-40 Ra-226 1/12/2016 ~5.33 +/- 13.7 0.88 +/- 3.83 74.2 +/- 55.2 I 2/9/2016 3/1/2016

-6.33 +/- 11.5 10.00 +/- 18.6 1.47 2.97

+/-

3.57 5.15 55.1 +/- 806

. 59.3 +/- 56.8 4/11/2016 -3.91 +/- 13.9 0.74 +/- 3.69 I 5/10/2016 6/6/2016 9.56 +/- 20.2

-1.58 +/- 14.4 -1.34

-0.97 +/-

+/-

4.76 3.91 -330 +/- 542 7/4/2016 6.41 +/- 15.2 -4.05 +/- 4.87 I 8/2/2016 9/5/2016 10/3/2016

-4.8 +/- 14.4 2.09 +/- 15.60 0.63 0.40 +/- 20.1 0.87 1.32

+/-

4.40 5.18 7.11

-351 +/- 521 109 +/- 79.2 112 +/- 99.6 253 +/- 125 I 11/1/2016 12/5/2016

-6.87 +/- 14.5 -1.72 4.58 +/- 17.0 0.80

+/-

3.91 6.29 360 +/- 564 65.6 +/- 47.3 I

I 41

I I TABLE 3:..9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WATER I pCi/Llter+/- 2 Sigma Suny Power Station, Suny County, Vrrgfuia -2016 Page2 of2 I SAMPLING COLLECTION LOCATIONS DATE ISOTOPES Mn-54 Co-58 Fe-59 Co-60 Zn-65 I SW-C 1/12/2016 2/9/2016

-1.19 +/- 3.84 1.21" +/- 2.69 0.60 +/- 3.15

-2.88 +/- 3.64

-0.64 +/- 5.63 1.23 +/- 6.48 1.44 +/- 4.04 0.47 +/- 3.18

-1.82 +/- 7.60

-3.94 +/- 7.84 3/1/2016 2.63 +/- 2.96 -0.09 +/- 2.86 -1.05 +/- 5.38 0.14 +/- 3.18 -7.55 +/- 6.82 I 4/12/2016 5/10/2016 1.63- +/- 2.71

-0.51 +/- 3.36

-0.08 +/- 3.01

-1.41 +/- 3.25 4.10 +/- 6.18

-2.14 +/- 7.06 2.10 +/- 3.80 2.46 +/- 3.52

-0. 78 +/- 6.69

-4.84 +/- 7.46 6!712orn- *0.81 +/- 2.46 -0.54 +/- 2.35 -1.06 +/- 4.70 -0.66 +/- 2.22 -2.18 +/- 6.3o- --

I 7/512016 8/2/2016 9/6/2016 1.60 +/- 3.02

-2.42 +/- 2.67

-1.31 +/- 3.46

-3.48 +/- 3.47

-0.50 +/- 2.72 . 0.04 +/- 2.70 2.62 +/- 6.65

. 0.87 +/- 6.71 3.57 +/- 5.95

-3.73 +/- 2.77 1.03 +/- 3.87 0.98 +/- 2.66

-1.90 +/- 8.12

-9.46 +/- 6.64

-1.94 +/- 5.61 I 10/4/2016 11/1/2016 12/5/2016

-2.39 +/- 5.65

-1.33 +/- 3.07

-3.27 +/- 4.91

-0.84 +/- 4.79

-2.01 +/- 3.39

-4.53 +/- 4.21

-12.8 +/- 8.86 1.30 +/- 6.42 1.38 +/- 7.08

-0.67 +/- 5.22 0.27 +/- 3.13 1.45 +/- *4.28

-0.06 +/- 11.3

-7.51 +/- 6.93

-3.63 +/- 10.0 I 1/12/2016 Nb-95 0.98 +/- 4.02

. Zr-95

-2.21 +/- 6.28 1-131 0.64 +/- 5.89 Cs-134

-2.26 +/- 4.65 Cs-137

-0.72 +/- 3.65 2/9/2016 0. 73 +/- 3.36 -3.80 +/- 5.38 0.19 +/- 4.69 -5.85- +/- 3.68 0.02 +/- 3.26 I 3/1/2016 4/12/2016

-1.18 +/- 3.22 2.29 +/- 2.73 1.22 +/- 5.82 0.31 +/- 4.38 0.17 +/- 5.35 0.72 +/- 4;74

-5.87 +/- 3.81 0.22 +/- 3.05 0.99 +/- .3.10

-1.32 +/- 3.21 5/10/2016 2.23 +/- 3.14 3.66 +/- 5.56 -1.73 +/- 4.45 -2.88 +/- 3.96 -1.93 +/- 3.75 I I 6/7/2016 7/5/2016 8/2/2016 1.38 +/- 2.51 1.23 +/- 3.58

-0.52 +/- 2.98 2.75 +/- 4.34

-1.88 +/- 6.03 0.86 +/- 6.59 5.12 +/- 5.50 1.54 +/- 5.10

-0.93 +/- 6.10.

-2.33 +/- 2.96

-0.32 +/- 3.27

-11.9 +/- 4.12 0.41 +/- 2.55 0.18 +/- 3.39

-2.49 +/- 3.43 I 9/6/2016

. 10/4/2016 11/1/2016

-0.23 +/- 2.71

-7.32 +/-* 6.25

-0.34 +/- 3.61 0.96 +/- 4.64.

-1.03 +/- 8.13 1.57 +/- 4.52

-1.21 +/- 4.82

-6.25 +/- 6.48

-1.65 +/- 5.89

-6.74 +/- 3.10

-3.49 +/- 5.40

-1.30 +/- 3.45

-1.32 +/- 2.76 0.66 +/- 5.64 0.34 +/- 3.54 12/5/2016 -0.03 +/- 4.06 -1.09 +/- 7.09 0.88 +/- 5.81 -5.42 +/- 4.62 1.84 +/- 4.25 I Ba-140 La-140 H-3 K-40 Th-228 --

1/12/2016-----5.57 +/- 17.1 . 0.00 +/--4.11 I 2/9/2016 3/1/2016

-8.39 +/- 13.5

-6.10 +/- 14.6

0. 79 +/- 5.24 2.27 +/- 4.26 -145 +/- 791 65.2 +/- 53.6 4/12/2016 9.96 +/- 14.6 -3.18 +/- 4.49 9.11 +/- 7.46 I 5/10/2016 6/7/2016

-3.64 +/- 13.1 1.77 +/- 13.0

-5.97 +/- 4.36 2.19 +/- 4.33 -130 +/- 561 7/5/2016 -7.16 +/- 15.4 -2.85 +/- 5.50 I 8/2/2016 9/6/2016 10/4/2016 2.92 +/- 15.9

5. 78 +/- 13.2 6.29 +/- 19.2 2.09 +/- 5.08 0.46 +/- 4.43 1.09 +/- 6.50

-229 +/- 528 70.3 +/- 63.5 11/1/2016 -12.3 +/- 16.6 -0.48 +/- 5.85 I 12/5/2016 -11.0 +/- 17.4 3.07 +/- 5.90 882 +/- 897 I

1* 42

I I TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT I pCi/kg (dry)+/- 2 Sigma Surry Power Station, Surry County, Virginia -2016 Pagelofl I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE Cs-134 Cs-137 K-40 Th-228 - Th-232 I SD 3/7/2016 9/7/2016

-32.1 +/- 40.9 83.3 +/- 73.4 B

-8.05 +/- 44.1 10000 +/- 1560 143 +/- 89.1 B 21400 +/- 2650 818 +/- 143 1600 +/- 289 786 +/- 194 1390 +/- 305 I 3/7/2016 9/7/2016-Ra-226 1910 +/- 1310 2600 +/-- 2260 Be-7

.3170 +/- 967 I

I C&-134

-30.0 +/- 78.2 Cs-137 233 +/- 123 K-40 15900 +/- 2640 Th-228 1700 +/- 228 Th-232 CHIC-C 3/7/2016 1280 +/- 347 I 9/6/2016 353 +/- 77.3 A Ra-226 219 +/- 83.7 18500 +/- 1700 1790 +/- 206 1200 +/- 279 3/7/2016 2510 +/- 2420 I 9/6/2016 2730 +/- 2010 A: Compound/analyte not detected. Peak not identified.

I B: <LLD I

I I

I 43

I I TABLE 3-11: GAJV.lMA EMITTER CONCENTRATIONS-IN SHORELINE SEDIMENT I pCi/kg (dry)+/- 2Sigma Surry Power Station, Surry County, Vitgmfa -i016 Page 1 ofl SAMPLING COLLECTION I LOCATIONS DATE ISOTOPE.

Cs-134~~--- Cs-137 K-40

Ra-226 - - Th-228 ~-

I HIR 2/2/2016 8/2/2016

-20.8 +/- 37.2 -0.68 +/- 30.0 362.0 +/- 62.9A 41.5 +/- 46.8 7960 +/- 1240 3650 +/- 963 3010 +/- 1270 A 1920 +/- 171 I 2/2/2016 8/2/2016 Th-232

. 1550 __ +/-__ 213 _ __

I CHIC-C 2/2/2016 Cs-134 9.24 +/- 43.4 Cs-137

-12.6 +/- 46.9 K-40 2000 +/- 775 Ra-226 Th-228 1250 +/- 150.0 8/2/2016 -25.5 +/- 31.9 -4.16 +/- 28.8 1820 +/- 512 1390 +/- 1130 930 +/- 88.2 I 2/2/2016 Th-232 1240 +/- 311 I

8/2/2016 790 +/- 177 A: Compound/analyte not detected. Peak not identified.

I I

I I 44

I I -TABLE 3-12: GAMMA EMITTER CONCENTRA-TION IN FISH I Surry Power Station, Surry County, Vrrginia - 2016 pCi/kg (wet) +/- 2 Sigma Page 1 ofl I SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE I SD 4/6/2016 4/6/2016 Catfish Game fish 3170 2000 K-40

+/-

1250 978 26.8

-64.3 Mn-54

+/- 53.4

-+/- 61.3

-21.6 10.1 Co-58

+/-

44.5 60.0 32.9 13.0 Fe-59

+/-

85.2 108 10/5/2016 Catfish 1810 +/- 560 -6.02 +/- 24.7 20.0 +/- 21.9- -4.10 +/- 42.3 I 10/5/2016 Game fish 2850 +/- 1010 -19.7 +/- 48.3 -38.6 +/- 51.7 22.4 +/- 81.1 Co-60 Zn-65 Cs-134 Cs-137 I 4/6/2016 4/6/2016 Catfish Game fish 0.90 4.10

+/-

55.2 51.2

-17.2

-2.31

+/-

98.6 111

-15.9

-45.2

+/-

53.0 55.3 23.0 16.7

+/-

35.1 57.3 10/5/2016 Catfish -3.45 +/- 19.9 -39.8 +/- 56.6 6.97 +/- 25.8 0.03- +/- 26.1 I 10/5/2016 Game fish 18.5 +/- 46.6 -140 +/- 107 5.85 -+/- 53.6 -17.7 +/- 41.4

~ I I

I I

I 45

I I TABLE 3-13: GA.MU4 EMITTER CONCENTRATIONS IN OYSTERS II Suny Power Station, Suny County, Vrrginia - 2016 pCi/kg (wet)+/- 2 Sigma Page I ofl I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE~

I POS 3/8/2016 9/7/2016 Mn-54 30.2 +/- 38.2 16.4 +/- 31.2 Co-58

-7.12 +/- 56.0

-19.8 +/- 31.6

- Fe-59 88.6 +/- 114 29.2 +/- 60.5 Co-60 16.0 +/- 28.6 8.68 +/- 24.0 I 3/8/2016 Zn-65

-27.1 +/- 95.8 Cs-134

-32.1 +/- 43.2 Cs-137 0.72 +/- 43.9 K-40 597 +/- 588 9/7/2016 -26.0 +/- 71.9 18.7 +/- 44.8 .. *21.4 +/- 31.5 1090 +/- 648 -*

I Mn-54 Co-58 Fe-59 Co-60 MP 3/8/2016 20.1 +/- 40.1 2.99 +/- 42.0 48.5 +/- '129 -1.82 +/- 36.6 I 9/8/2016 4.42 +/- 32.4 -7.83 +/- 30.5 -27;6 +/- 69.5 1.06 +/- 24.3 Zn-65 Cs-134 Cs-137 .K-40 I 3/8/2016 9/8/2016

-37.8 +/- 83.4

-99.4 +/- 70.5

-10.6 +/- 45.0 33.3 +/- 35.5

-26.9 +/- 41.9 2.16 +/- 31.0 680 +/- 581 I LC 3/8/2016 Mn-54

-10.9 +/- 30.2 Co-58

-1.64 +/- 43.9 Fe-59 21.5 +/- 90.7 Co-60

-3.78 +/- 20.3 9/8/2016 18.1 +/- 29.3 -9.52 +/- 32.3 -57.9 +/- 61.1 6.22 +/- 24.7 I 3/8/2016 Zn-65

-66.0 +/- 77.8 Cs-134 3.16 +/- 33.4 Cs-137 9.61 +/- 27.5 K-40 581 +/- 447 4.92 +/- 71.6 . 52.7 +/- 42.6 B -2.57 +/- 31.1 900 +/- 545 I B:<LLD 9/8/2016 I

'I I

I 46

I I TABLE 3~14: GA.MMA EMITTER CONCENTRATIONS IN CLAMS I Surry Power Station, Surry County, Vrrginia- 2016 pCi/kg (wet)+/- 2 Sigma Page 1 of 1 I SAMPLING COLLECTION LOCATIONS - - DATE ISOTOPE I JI 3/8/2016 9/7/2016 Mn-54 9.22 +/- 44.2 13.2 +/- 30.9 Co-58

-33.5 +/- 53.0 4.13 +/- 30.6 Fe-59 --

-61.1 +/- 155 1T.7 +/- 69.2 Co-60

-10.6 +/- 54.0 24.4 +/- 28.9 I 3/8/2016 ---

Zn-65

-129- +/--127 -

Cs-134 Cs-137

-47.1 +/- 53.3 - - -7.53 +/- 40.8 K-~O 9/7/2016 '-9.94 +/- 80.0 -16.1 +/- 41.3 -4.27 +/- 30.4 712 +/- 625 I

Mn-54 Co-58 Fe-59 Co-60 I SD 3/8/2016 9/7/2016 22.5 +/- 39.2 18.1 +/- 31.8 8.54 +/- 54.6 27.5 +/- 35.2 37.4 +/- 109 4.84 +/- 61.3 18.5 +/- 39.5 12.0 .+/- 33.4 I 3/8/2016 Zn-65

-96.6 +/- 114 Cs-134

-13.0 +/- 44.8 Cs-137 19.0 +/- 41.7 K-40 9/7/2016 -13.5 +/- 63.0 38.1 +/- 50.6 3.88 +/- 37.1 548 +/- 524 I

Mn-54 Co-58 Fe-59 Co-60 CHIC-C 3/7/2016 -10.7 +/- 34.7 -32.1 +/- 46.9 -12.9 +/- 90.0 6.79 +/- 34.8 1* 9/6/2016 30.8 +/- 34.5 4.19 +/- 25.9- 16.9 +/- 78.2-* -- -9.92 +/- 28.7 I 3/7/2016 9/6/2016 Zn-65

-77.4 +/- 83.0 39.6 +/- 85.3 Cs-134*

-6.25 +/- 34.0 6.58 +/- 32.5 Cs-137 32.6 +/- 33.4

-23.9 +/- 36.0 K-40 675 +/- 551 I

I I

I I 47

I I TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS I Surry Power Station, Surry County, Vrrginia- 2016 pCi/kg (wet)+/- 2 Sigma Page 1of1 I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE K-40

Mn-54 Co-58 Fe-59 _

I SD 6/7/2016 1180 +/- 762 16.3 +/- 28.0 11.4 +/- 31.8 -5.99 +/- 67.2 I Co-60 9.06 +/- 29.5 Zn-65

-12.4 +/- 89.0 Cs-134 3.58_ +/- 39.8 Cs-137 13.3 +/- 35.9 I

I I

I 1*

I I

I I 48

I I 4. DISCUSSION OF RES UL TS I Data from the radiological analyses of environmental media *collected during 2016 and tabulated in Section 3, are discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the I Teledyne Brown Engineering quality assurance manuals and laboratory procedures.--In--addition to internal-quality-Gontrol 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.

The predominant radioactivity detected throughout 2016 was from external sources, such as fallout from nuclear weapons tests (cesium-13 7) and naturally occurring radionuclides. Naturally occurring nuc:Iides such as beryllium-7, potassium-40, radium-226, thorium-228 and thorium-232 were detected in numerous samples.

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

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

TLDs are placed in two concentric rings around* the station. The inner ring is 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 2016. The results of the TLD analysis shown in Table 3.2 comply with Section 7 of ANSI/HPS Nl3.37-2014 in order to ensure accurate environmental results. The long-term integrity of each field monitoring location is accomplished by a I 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

1 processing of TLDs is used, extraneous dose received prior to and after re:qioval 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 ii ii 49 11_____ _

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

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

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

I Gross beta activity fou nd during the pre-operational and early operating period of Surry Power Station was higher because of nuclear weapons testing. During that time, nearly 7 40 nuclear weapons were tested worldwide. In 1985 weapons I testing ceased, and with the exception of the Chernobyl accident in 198 6 , airborne gross beta results have remained steady.

I I Figure 4-1: 2016 GROSS BETA IN AIR PARTICU LATES I 0.045 0.040

~----------------------------~

- - -- - - -- - - - - - -- - - -- -- - - - - - - ---i 0.035 + - - - - - - - -- -- - -- - - -- - - - -- - - - - - - - - - <

I 0.030 -- - - - - - - - - - - - - - -- - - -- - - - -- - ---i

'E 0.025 I

~ 0.020 ------------------fi>----....,:..;.---~-----~..i O.DI 5 +.-~rl!-'t-----=---~.,....--+--ft-~..----br----1-.r-'l'!----T.._,,_,.r-->t-*.--F---i I 0.010 0.005

+-'-----=--~1-- ....~~-\--,"l---\-;f---:11~---~l---.P~~-----\f---i I 0.000 Q

°'

c:!

N

'° -

--- c:! ---

N N ("')

c:! Q

("')

00 N

c:!

'° Q

0

.,... c:!

("')

.,... Q r-

'° ° Q

r-r-

°'

c:!

r-N 00 c:! °'

'° 00 Q

("')

c:! Q r-

°' °' s s c:! Q 00 N

Q

~

'°

~

0

~

I I---+--- Avg Indicator ---+-- AveControll I

I 50

I I

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

I I

I I r-

°'

00

°' °'

°'

°' °'

°'

0 0

0 N

0 0

N N

0 0

N

('<)

0 0

N

"<t 0

0 N

V) 0 0

N 0

0 N

r-0 0

N 00 0

0 N

g 0

N 0

N N

0 N

~

0 N

~

0 N

I ---- Avg Indicator --.--- Avg Control - Avg-Pre Op - - Required LLD I

4.3 Airborne Radioiodine I Air is also continuously sampled for radioiodines by passing it through charcoal cartridges. Once a week the charcoal cartridge samples are collected and I analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection. No positive iodine-131 was detected. These results are similar to pre-operational data and the results of samples taken prior I to and after the 1986 accident in the Soviet Union at Chernobyl and the Fukushima Daiichi nuclear incident in 2011.

I 4. 4 Air Particulate Gamma I The air particulate filters from the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy. The results are listed in Table 3-5. The results indicate the presence of naturally occurring potassium-40 I and beryllium-7 , which are produced by cosmic processes.

radionuclides were identified. These analyses confirm no effects from station No man-made I effluents.

I I 51

I I 4.5 CowMilk I Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. Tiiis, in combination with L~e I fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint._ _This pathway also shows measurable-*. amounts of nuclear :weapons* testing .-fallout.. Therefore,--this media

I needs to be carefully evaluated when trying to determine if there is any station effect.

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 .c:l~t~cted sporadically. The -occurrences were I attributed to residual global fallout from 'past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2016.

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

I No strontium-89 was detected in the four composites analyzed. Strontium-90 was detected in three of the composite samples at an average concentration of 1* 1.59 pCi/L. Sr-90 is not a component of the station radiological effluents and is a product of nuclear weapons testing fallout which has been well documented.

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

I 4.7 Well Water I Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry Power* Station monitors well I water quarterly at three indicator locations and analyzes for gamma radiatior.t. and for tritium. The results of these analyses are presented in Table 3-8. Consistent with past monitoring, no station related radioactivity was detected. No gamma I emitting isotopes were det~cted during the pre-operational period.

I I

I 52

l I

I 4. 8 River Water I Samples of the James River water are collected monthly and the results are presented in Table 3-9 .. All samples are analyzed by gamma spectroscopy. The monthly samples are also composited and analyzed for tritium on a quarterly I basis. Trttium was not detected and, with the exception of natural products, no other gamma emitters were detected. _The naturally occu~g _radionuclides detected -were-- potassium-40~---,radium-"226-:-and thorium-=-228; No<station related~_:-.:cc I radioactivity was detected.

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 I of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish.

I Samples of silt are collected from two locations, one upstream and one

. downstream of the station. The results of the gamma spectroscopy analyses are I presented in . Table 3-10. Naturally occurring beryllium-7, potassium-40, radium-226, thorium-228 and thoriurrt-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 silt appear in Figures 4-3 and 4-4.

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

I I

I I 53

I I Figure4-3: COBALT-60 IN SILT I

I l.OE+03 I ....>-

"'C Cl 1.0E+02 I .!!:

(3 0.

I 1.0E+Ol I N r--

\0 r--

00 r--

0 N "<!" \0 00 0 N \0 00 0 0

N 0 30 \0 0

00 0

0 N "<!" \0

°' °' °' °' °' °' °' °' °' °' °'

°' °'

00 00 00 00 00 0 0 0 0 0 0 0 0

°' °' °'

I N N N N N N N N N

~ Contro l - Oiic kahominy - Station Discharge LLD Avg I Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDC , Minimum Detectable Concentration. Station Discharge was <MDC activity 1996 through 1998 and 2004 through 2016.

I I

I 54

I I Figure 4-4: CESIUM-137 IN SILT I

I I ,,....>.

~ l. OE+03 -++-1-+--=----.--------.6--'r-::illl-...,..r.-- - - - - - - - - - - - - - - - - - - i I :::.

ua.

I I

I - + - Control - Chickahominy __..._ Station Discharge - Ave- Pre Op - - Required LLD I

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

Buildup of radionuclides along the shoreline may provide a source of direct I 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 the same as those seen over the last decade. No activity was observed in this I media except for naturally occurring potassium-40.

,I I 55

I I

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

There- were riogamm.a:-: emitting- tadionuclides detected in'. oysters sampled". excepc--_, -

for naturally occurring potassium-40. No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is

'I attributable. to the replacement of steam generators in 1982 and past improvements made to liquid effiuent treatment systems ..

4.13 Clams--*----- -. --

I

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

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

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

I I

~---------

I I

I 56

I I 5. PROGRAM EXCEPTIONS I There was one REMP exceptioh for scheduled sampliiig and analysis during 2016.

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

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

I I

I 1* 57

I I 6. CONCLUSIONS I Tue results of the 2016 Radiological Environmental Monitoring Program for Suny 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 2016.

I )> Airborne Exposure Pathway - Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. Quarterly gannna 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 2016 trend well with

the* *control* location. *A slight separation between-:-indicator*-and c6nfrol I location trend data points was observed in the fourth quarter. Observation of this will continue into 201 7.

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 thili:y-five samples. Naturally I occurring potassium-40 'Was detected *at a similar level when compared to the averages of the previous years.

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

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

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

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

Tritium was not detected.

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

58

I I I ~ Shoreline Sediment - Naturally occurring radionuclides were detected at concentrations equivalent to normal background activities. There-were no I radionuclides attributable to the operation of Surry Power ~tation found in

_any sample.

I Aquatic Biota

~ Fisli-:-As expected, --naturally occurring potassium-'-40 was detected. -There:

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

I ~ Oysters and Clams - Other than naturally occurring potassium-40, there*

were no other gamma emitting radionuclides detected in any of the oyster or clam_samples_.__ ___ _ _ _

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

I I

I I 59

I I

REFERENCES - -- -

I I

I

I I .

i I I

I I

I I 60

I I References I 1: NUREG-0472, "Radiological Effluent Technical Specifications for PWRs",

Draft Rev. 3, March 1982.

I

2. United States Nuclear Regulatory Corn.mission, 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 I 10CFR50, Appendix I", October 1977.

1- 3. United States Nuclear Regulatory Corn.mission, Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",

December 1975.

I

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

I 5. Domir..ion, Station Administrative Procedure, VPAP-2103S, "Offsite Dose Calculation Manual (Suny)",

I

6. Virginia Electric apd Power Company, Suny Power Station Technical I Specifications, Units 1 and 2.

7. HASL--300, EnVironrnental 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/RPS Nl3.37-2014 Environmental Dosimetry Criteria at Suny Power Station", November 2016 by John M. Sukosky, CHP.

I I

I 61

I I

I I - -~~::-*:-- ~.~

~ ~- -*

I I

I APPENDICES II I

I I

I 62

I I

! I I

I APPENDIX A: LAND USE CENSUS I

Year 2016 I

I I

I I I

I I

I 63

I I LAND USE CENSUS*

Surry Power Station, Surry County, Virginia I January 1 to December 31, 2016 Page 1of1 I Sector Direction Nearest Resident Nearest Garden**

Nearest Cow Nearest Goat A N 4.1@ 10° (a) (a) (a)

I B NNE l.9@32° (a) (a) (a) c NE 4.7@35° (a) (a) (a)

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

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

I F G

ESE SE (a) 2.8@ 142° (a)

(a)

(a) 11 H J

SSE s

2.7@ 158° l.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 6 (a) (a)

M WSW 0.4@244° 3.6@245° (a) (a)

I N p

w 3.1 @260° 3.4@260° (a) (a)

WNW 4.9@283° (a) (a) (a)

Q NW 4.6@321° (a) L (a) (a)

R NNW 3.8 @338° 4.4@334° 3.7@336° (a)

I I

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

- Area greater than 50 m2 and contains broadleafvegetation, (a) None I

I I 64

I I

I 1-1 I APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS I

Year 2016 I

I

,I i

I I

I 65

I I INTRODUCTION I

. . ~

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

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

-~ milk for Sr-89 and Sr-90 analyses, I ~

~

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 The accuracy of each result reported to Eckert & Ziegler Analytics, Inc. is measured by the ratio of the TBE result to the known value. Accuracy for all other results is based on statistically derived acceptance ranges calculated by the I providers. An investigation is undertaken whenever the ratio or reported result fell outside of the acceptance range.

I RESULTS The TBE ICP results are included in the following tables for the first through the

I fourth quarters of 2016. Some analyses did riot. meet the acceptance criteria. TBE initiated non-conformance reports (NCRs) to document and address the analyses.

The results of the NCRs are as follows.

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

The TBE value of 15.0 pCi/L was higher than the known value of 11.4 I pCi/L. The resultant ratio was 1.32 failing above the high acceptance limit of 1.30. The QA data, yield, and associated raw data of the analysis were

reviewed and found to be acceptable. It is believed the laboratory technician I did not rinse the filtering apparatus .Properly and some cross contamination from an internal laboratory spike sample may have been transferred to the I Analytics sample. The sequence of filtering samples would have placed the Analytics sample on the same filtering apparatus as the internal laboratory spike sample. Additional training has been given to the laboratory I technician on how to properly rinse the filtering apparatus. Additional I 66

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

I 2. NCR_l6-34, ERA water sample RAD-107 failed H-3 .. The TBE value of 918 pCi/L was lower than the known value of 9,820. pCi/L, failing below the lower acceptance limit of 8,540. The result of 918 pCi/Lwas incorrectly I reported due. to a data entry issue. The actual TBE value was 9, 180 pCi/L~

__ and ifreported correctly, wou,ld have been withip. the acceptable range of

~.=c8, 540 =-- 1O;800 pGi/L.=Th:e-:data entry error was -missed-during the review I process. TBE will perform additional review of data entry into the ERA database.

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

I The TBE value of 14. 7pCi/L was higher than the known value of 10. The resultant ratio was 1.47, failing above the high acceptance limit of L30.

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

I I

I, I

I I

I 67

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

I Month/Year Identification Number Matrix Nuclide Units Reported Known Value (a) *Value (b)

Ratio (c)

TB ElAnalytics Evaluation (d)

February 2016 A31519(3) AP Sr-89 µCi/cc 2.04 2.46 0.83 A I March 2016 E11476 Milk Sr-90 Sr-89 sr-90___

µCi/cc pCi/L pcf/L 2.08 97 15 2.68 86.7 11.4 .

0.78 1.12 1.32v~ ~---

A A

N(2)

- -E11477 Milk 131 -,-~~-~. -.. 'pCfiL'-'-- 85.9. -~ **-82.i=-~*=:.. 1.05 "-'"-"

I A

Ce-141 pCi/L 106 98.4 1.08 A Cr-51 pCi/L 255 243 1.05 A Cs-134 pCi/L 134 130 1.03 A I Cs-137 Co-58 Mn-54 pCi/L pCi/L pCi/L 174 123 141 161 117 117 1.08 1.05 1.21 A

A w

. Fe-59 *----

pCi/L ___ _ 152 131

- - 1.16 A I

-n~-*- ~-*--*---T Zn-65 pCi/L 193 179 1.08 A

-Co-60 pCi/L 259 244 1.06 A E11.184 AP Ce-141 pCi 69 81.1 0.85 A I Cr-51 Cs=134 Cs-137 pCi pCi pCi 242 98.1 136 201 107.0 133 1.20 0.92 1.02 w

A A

Co-58 pCi 91.9 97 0.95 A I. Mn-54 Fe-59 pCi pCi 98.6 98.8 96.2 108 1.02 0.91 A

A Zn-65 pCi 131 147 0.89 A I Co-60 pCi 209 201 1.04 A E114.78 Charcoal 1-131 pCi 85.3 88.3 0.97 A I June 2016 E11185 E11537 Water Milk Fe-55 Sr-89 pCi/L pCi/L 1800 94.4 1666 94.4 1.08 1.00 A

A Sr-90 pCi/L* 13.4 15.4 0.87 A I E11538 Milk 1-131 Ce-141 pCi/L pCi/L 96.8 129 94.5 139 1.02 0.93 A

A Cr-51 pCi/L 240 276 0.87 A I Cs-134 Cs-137 Co-58 pCi/L pCi/L pCi/L 157 117 131 174 120 142 0.90 0.98 0.92 A

A A

Mn-54 pCi/L 128 125 1.02 A I Fe-59 Zn-65 pCi/L pCi/L 132 235 122 235.

1.08 1.00 A

A Co-60 . pCi/L 169 173 0.98 A I

I (a) Teledyne Brown Engineering reported result.

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

(c) Ratio of Teledyne Brown EngineeringtoAnalyticsresults.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20.

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

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

I 68

I I ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE20F3)

Identification Reported Known .Ratio (c)

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

June 2016 E11540 Filter Ce-141 pCi .*:, 10Q, " 99.8 1.05 A I Cr-51 Cs-134 Cs-137 pCi pCi pCi 216 113 94.5 198 125 86.6 1.09 0.90 1.09 A

A A

Co-58 pCi 101 102 0.99 A I Mn-54 Fe-59 pCi pCi 88.8 82.0 90.2 87.5 0.98 0.94 A

A Zn-65 pCi 174 169 1.03 A I E11539 Charcoal Co-60 1-131 pCi pCi 143 ...

86.1 124 89A 1.15 0.96 A

A I September 2016 E11609 Milk Sr-89 Sr-90 pCi/L pCi/L 89.9 13.3 90.9 13.7 0.99 0.97 A

A I E11610 Milk 1-131 Ce-141 Cr-51 pCi/L pCi/L pCi/L 80.4 81.3 198 71.9 93.2 236 1.12 0.87 0.84 A

A A

Cs-134 pCi/L 122 136 0.90 A I Cs-137 Co-58 pCi/L pCi/L 119 92.2 119 97.4 1.00 0.95 A

A Mn-54 pCi/L 156 152 1.03 A I Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L 97.5 189 ..

131 90.6 179 135 1.08 1.06 0.97 A

A A

I E11612 Filter Ce-141 Cr-51 pCi pCi 67.5 192 63.6 161.0 1.06 1.19 A

A Cs-134 pCi 91.4 92.6 0.99 A I Cs-137 Co-58 Mn-54 pCi pCi pCi 93.9 66.0 104 80.8 66.4 104 1.16 0.99 1.00 A

A A

Fe-:59 pCi 60.5 61.8 0:98 A I Zn-65 Co-60 pCi pCi 140 119 122 91:9 1.15 1.29 A

w I December 2016 E11611 E11699 Charcoal Milk 1-131 Sr-89 pCi pCi/L 52.4 95.2 59.9 74.2 0.87 1.28 w A

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

I I Footnotes are on page 3 of3; I

I 69

I I ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES I

(PAGE30F3)

Identification Reported Known Ratio (c)

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

I December 2016 E11700 Milk 1-131

pCi/L Ce-141 . . ~c pCi/L 97.5 136 97.4 143 ----

1.00 0.95 A

A I Cr-51 Cs-134 Cs-137 pCi/L pCi/L pCi/L 247 164 12ff 280 178 126 0.88 0.92 0.95 A

A A

Co-58 pCi/L 139 146 0.95 A Mn-54 pCi/l 126 129 0.98 A Fe-59 pCi/L 114 125 0.91 A Zn-65 pCi/L 237 244 0.97 A Co-60 pCi/L 168 178 0.94 A 11.702 Filter Ce-141 pCi 91.7 97.7 0.94 A Cr-51 per 210 192 1.09 A I Cs-134 Cs-137 Co-58 pCi pCi pCi 122 93.9 92:0 122 86.4 100 1.00 1.09 0.92 A

A A

II Mn-54 pCi 93.7 88.5 1.06 A Fe-59 pCi 84.9 85.4 0.99 A Zn-65 pCi 176 167 1.05 A Co-60 pCi 151 122 1.24 w II E11701 Charcoal 1-131 pCi 95.6 98.0 0.98 A E11730 Filter Sr-89 pCi 79.7 92.0 0.87 A II Sr-90 pCi 10.0 12.5 0.80 A II II II II N (1) Milk, Sr The failure was due to cross-contamination of laboratory apparatus. NCR 16-26 n N (2) Milk, Sr The failure was due to sample volume data entry error. NCR 16-35 (a) Teledyne Brown Engineering reported result.

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

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

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of0.80-1.20.

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.

II 70

I I -DO E's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1OF1)

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

I March 2016 16-GrF34 Filter Gr-A Gr-B Sq/sample

.Sq/sample 0.608 0.806 1.20 0.79 0.36- 2.04 0.40-1.19 A

A I

I I

I I (a) Teledyne Brown Engineering reported result.

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

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

I 71

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

I Month/Year Identification Number Media Nuclide Units Reported Known Value (a) Value (b)

Acceptance Limits Evaluation (c)

I

-~r- - --

May 2016 RAD-105 Water Sr-89 pCi/L 48.9 48.2 37.8 -55.6 A Sr-90 ,-. p~i/L 25.0 28.5 20.7 - 33.1 A 8a-133 pCi/L* *53.1- - 58.8 48.7 - 64.9 - . A*

I Cs-134 Cs-137 Co-60 pCi/L pCi/L pCi/L 40.9 85 108.0 43.3 78.

102.0 34.6 -47.6 70.6 - 88.9 91.8-114 A

A A

Zn-65 pCi/L 226 214 193 - 251 A I Gr-A Gr-8 1-131

-pCi/L pCi/L pCi/L 38.9 41.9 24.1 62.7 39.2 26.6 32.9 - 77.8 26.0 -46.7 22.1 -31.3 A

A A

U-Nat pCi/L 4.68 4.64 3.39 - 5.68 A I November 2016 RAD-107 Water H-3 Sr-89 pCi/L pCi/L 7720 43 7840 43.3 6790 - 8620 33.4- 50.5 A

A Sr-90 pCi/L 30 33.6 24.6 - 38.8 I

A 8a-133 pCi/L 47.8 54.9 45.4- 60.7 A Cs-134 pCi/L 72.9 81.8 67.0 - 90.0 A Cs-137 pCi/L 189 210 189 - 233 A I Co-60 Zn-65 Gr-A pCi/L pCi/L pCi/L 58.4 243 37.2 64.5 245

. 68.4 58.0 - 73.4 220 -287 35.9 - 84.5 A

A A

Gr-8 pCi/L 35.1 33.9 22.1 -41.6 A I 1-131 U-Nat H-3 pCi/L pCi/L pCi/L 23.5 49.2 918 26.3 51.2 9820 21.9-31.0 41.6 - 56.9 8540-10800 A

A N (3)

I I

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

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

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

I 72

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