Text

Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report for 2008
	ML091250186
Person / Time
Site:	Surry, 07200002, 07200055
Issue date:	04/24/2009
From:	Stanley B; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	09-267
	Download: ML091250186 (75)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 24, 2009 Attention: Document Control Desk Serial No.09-267 U.S. Nuclear Regulatory Commission SS&LITJN RO Washington, D. C. 20555-0001 Docket Nos.

50-280 50-281 72-2 72-55 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen:

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 Technical 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 the Surry Power Station.

Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2008 through December 31, 2008, which includes environmental monitoring for the Surry ISFSI.

If you have any questions or require additional information, please contact Paul Harris at 757-365-2692.

Sincerely, B. L. Stanley Director Station Safety and Licensing Surry Power Station Attachment Commitments made in this letter: None

Serial No.09-267 Docket Nos.: 50-280 50-281 72-2 72-55 copy: US Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center, 23T85 61 Forsyth Street, S.W.

Atlanta, Georgia 30303-8931 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 NRC Senior Resident Inspector Surry Power Station Director Division of Radiological Health 109 Governor Street, Room 730 Richmond, Virginia 23219

Serial No.

Docket Nos.:

09-267 50-280 50-281 72-2 72-55 ATTACHMENT 1 2008 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION VIRGINIA ELECTRIC AND POWER COMPANY

Surry Power Station 2008 Annual Radiological Environmental Operating Report iP" Dominion

Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2008 to December 31, 2008

Annual Radiological Environmental Operating Report Surry Power Station January 1, 2008 to December 31, 2008 Prepared by:

Reviewed by:

P. i.Blount Health Physicist P. R. Harris Supervisor Radiological Analysis B. A. Hilt Supervisor Health Physics Technical Services Approved by:

.3 L. B. Jones Mana Uradiological Protection and Chemistry 2

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

4

1. EXECUTIVE SUM M ARY......................................................................................................

.5

2. PROGRAM DESCRIPTION..........................................................

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

7 2.2 Sampling and Analysis Program.........................................

8

3. ANALYTICAL RESULTS................................................

20 3.1 Sum m ary of Results..............................................................................

......................... 20 3.2 Analytical Results of 2008 REM P Sam ples...................................................................

27

4.

DISCU SSION OF RESULTS....................

...................................................................... 48 4.1 Gam m a Exposure Rate................................................

48 4.2 Airborne Gross Beta........................................................................................................

49 4.3 Airborne Radioiodine....................................................................................................

51 4.4 Air Particulate Gam m a........................................................................................

......... 51 4.5 Cow M ilk..............................................................

............................................................ 51 4.6 Food Products....................................................................................................................

52 4.7 W ell W ater.............................................................................................................................

52 4.8 River W ater.........................................................................................................................

52 4.9 S ilt...;.....................................................................................................................................

5 2 4.10 Shoreline Sedim ent................................................

54 4.11 Fish........................................

...................... 54 4.12 Oysters................................................................................................................................

54 4.13 Clam s................................................................................................................................

55 4.14 Crabs...............................................................................................................................

55

5. PROGRAM EX CEPTION S............................................

I...................... :....................................... 56

6. CON CLU SION S.............................................................................................................................

57 REFEREN CES....................................................................................................................................

59 APPEN DICES.............................................................................................................

I....................... 61 APPEN DIX A : LAN D U SE CEN SU S......................................................................................

62 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS.......................... 64 3

PREFACE This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report, for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281.

4

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2008 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January, 1 through December 31, 2008, in air, water, silt, shoreline sediment, milk, aquatic biota, food products and direct exposure pathways have been analyzed, evaluated and summarized.

The REMP is designed to confirm that radiological effluent releases are As Low As is Reasonably Achievable (ALARA),

no undue environmental effects occur and the health and safety of the public are protected.

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

Radiation and radioactivity in the environment are monitored within a 20-mile radius of the station. Surry Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data.

Two types of samples are obtained. The first type, control samples, is collected from areas that

ýare beyond the measurable influence of Surry Power Station or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than Surry Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained.

These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.

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

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

GEL Laboratories LLC provides radioanalyses for this program and Global Dosimetry Solutions Inc. provides thermoluminescent dosimetry (TLD) services.

Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the United States Nuclear Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible.

The USNRC also mandates a reporting level for 5

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

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

Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates. The 2008 airborne results were similar to previous years. No plant related radioactivity was detected and natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters. Naturally occurring potassium-40 was detected at average environmental levels.

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

Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels. The terrestrial exposure pathway includes milk and food products. Iodine-131 was not detected in any 2008 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-89 and strontium-90 were detected in milk in 2008. The presence of strontium-89 in milk is suspect and attributable to contamination of milk samples at the laboratory.

The presence of strontium-90 is attributable to past atmospheric nuclear weapons testing.

No man-made radionuclides were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk and food products.

The direct exposure pathway measures environmental radiation doses using TLDs. TLD results have remained relatively constant over the years.

During 2008, as in previous years, the operation of Surry Power Station has created no adverse environmental effects or health hazards. The maximum dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2008 was 0.001 millirem.

For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources.

Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%.

These results demonstrate compliance with federal and state regulations and also demonstrate the adequacy of radioactive effluent controls at Surry Power Station.

6

2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2008 Surry Power Station operational Radiological Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 855 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.

The United States Nuclear Regulatory Commission regulations (10CFR50.34a) require that nuclear power plants be designed, constructed and operated to keep levels of radioactive material in effluents to unrestricted areas As Low As is Reasonably Achievable. To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications that address the release of radioactive effluents.

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

As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the station environs is also included in Surry Power Station Technical Specifications.

Dominion personnel are responsible for collecting the various indicator and control environmental samples.

Global Dosimetry Solutions Incorporated is responsible for processing the TLDs.

GEL Laboratories LLC is responsible for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radionuclides. Data collected prior to station operation is used to indicate the degree of natural variation to be expected.

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

Occasionally, samples of environmental media may show the presence of man-made radionuclides.

As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",

(December, 1975) and VPAP-2103S, Offsite Dose Calculation Manual (Surry).

These concentrations are based upon the annual dose commitment recommended 7

by 10CFR50, Appendix I, to meet the criterion of "As Low As is Reasonably Achievable."

This report documents the results of the REMP for 2008 and satisfies the following objectives of the program:

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

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

> To identify changes in radioactivity in the environment.

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

2.2 Sampling and Analysis Program Table 2-1 summarizes the 2008 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." Dominion personnel collect all samples listed in Table 2-1.

Table 2-2 summarizes the analysis program conducted by GEL Laboratories LLC and Global Dosimetry Solutions for Surry Power Station. All samples, with the exception of the TLDs, are shipped to GEL Laboratories LLC, located in Charleston, SC, for analysis.

The TLDs are shipped to Global Dosimetry Solutions, located in Costa Mesa, CA, for processing.

The Surry Radiological Monitoring Locations maps (Figures 1 - 5) denote sample locations for Surry Power Station.

The locations are color coded to designate sample types.

8

Table 2-1 SURRY - 2008 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROMUNITNO. 1 Distance Sample Media Location Environmental Control TLDs West North West Surry Station Discharge North North West North North North East North East East North East East West West South West South West South South West South South South East South East Station Intake Hog Island Reserve Bacon's Castle Route 633 Alliance Surry Route 636 and 637 Scotland Wharf Jamestown Colonial Parkway Route 617 and 618 Kingsmill Williamsburg Kingsmill North Budweiser Water Plant Station (00)

(02)

(03)

(04)

(05)

(06)

(07)

(08)

(09)

(10)

(11)

(12)

(13)

(14)

(15)

(16)

(18)

(19)

(20)

(21)

-(22)

(23)'

(24)

(25)

(26)

(27)

(28)

(29)

(30)

(31)

(32)

(33)

Distance Miles 0.2 0.4 0.2 0.3 0.3 0.3 0.4 0.3 0.1 0.4 0.3 0.3 0.4 0.6 0.9 1.6 2.0 4.5 4.9 5.1 7.7 4.0 5.0 6.3 3.8 4.9 4.6 7.8 5.5 5.8 5.0 Direction Degrees WNW NW NNW N

NNE NE ENE E

W WSW SW SSW S

SSE SE ESE NNE SSW SW WSW WSW W

WNW NW NNW NNW N

N NNE NNE NE 2930 3210 3290 40 280 440 670 890 2710 2520 2280 2010 1820 1570 1350 1150 260 2020 2270 2470 2560 2700 2840 3080 3330 3400 20 00 120 270 460 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Onsite (Stored in a lead shield outside the protected area)

Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Near Resident Apx. 5 mile Apx. 5 mile Apx. 5 mile Population Center Apx. 5 mile Apx. 5 mile Apx. 5 mile Apx. 5 mile Apx. 5 mile Apx. 5 mile Population Center Apx. 5 mile Population Center Apx. 5 mile 9

Table 2-1 SURRY - 2008.

RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Sample Media Location Environmental BASF TLDs Lee Hall Goose Island Fort Eustis Newport News James River Bridge Benn's Church Smithfield Rushmere Route 628 Air Charcoal Surry Station and Particulate Hog Island Reserve Bacon's Castle Alliance Colonial Parkway BASF Fort Eustis Newport News Station (34)

(35)

(36)

(37)

(38)

(39)

(40)

(41)

(42)

(43)

(SS)

(HIR)

(BC)

(ALL)

(CP)

(BASF)

(FE)

(NN)

Miles 5.1 7.1 5.1 4.9 19.3 17.1 17.0 13.4 5.3 5.1 0.3 2.0 4.5 5.1 3.8 5.1 4.9 19.3 Direction ENE ENE E

ESE SE SE SSE SSE SSE S

NNE NNE SSW WSW NNW ENE ESE SE Degrees 700 750 900 1040 1300 1420 1590 1670 1560 1770 180 260 2020 2470 3330 700 1040 1300 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Monthly Monthly Quarterly Quarterly Quarterly Remarks Apx. 5 mile Population Center Apx. 5 mile Apx. 5 mile Population Center Control Location Control Location Control Location Apx. 5 mile Apx. 5 mile Site boundary location with highest D/Q Control Location River Water Surry Station Discharge Scotland Wharf (SD)

(SW)

(SS)

(HIR)

(CS) 0.4 4.9 0.1 2.0 0.3 NW 3230 WNW 2840 Control Location Well Water Surry Station Hog Island Reserve Construction Site SW NNE E

2270 280 870 Onsite Shoreline Sediment Hog Island Reserve Chickahominy River Chickahominy River Surry Station Discharge (HIR) 0.6 (CHIC) 11.2 N

70 Semi-Annually WNW 3010 Semi-Annually Control Location Silt (CHIC)

(SD) 11.2 WNW 3000 Semi-Annually Control Location 1.3 NNW 3410 Semi-Annually 10

Table 2-1 SURRY - 2008 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROMUNITNO. 1 Distance Sample Media Location Milk Colonial Parkway Williams Epps Oysters Point of Shoals Mulberry Point Clams Chickahominy River Surry Station Discharge Hog Island Point Lawne's Creek Jamestown Island Station (CP)

(WMS)

(EPPS)

(POS)

(MP)

(CHIC)

(SD)

(HIP)

(LC)

(I)i Miles 3.7 27.5 4.8 6.4 4.9 112 1.3 2.4 2.4 3.9 Direction NNW S

SSW SSE ESE WNW NNW NE SE NNW Degrees 3360 1750 2000 Collection Frequency Monthly-Monthly Monthly Remarks Control Location 1570 Semi-Annually 1240 Semi-Annually 3000 3410 520 1310 3240 Semi-Annually Control Location Semi-Annually Semi-Annually Semi-Annually Semi-Annually Fish Surry Station Discharge Surry Station Discharge (SD)

(SD) 1.3

-NNW 1.3 NNW 3410 Semi-Annually Crabs 1830 1790.

Annually Annually Annually Crops Brock's Farm (Corn, Peanuts, Slade's Farm Soybeans)

(BROCK) 3.8 (SLADE) 3.2 S

S 11

Table 2-2 (Page 1 of 3)

SURRY - 2008 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2

mR/Std. Month Dosimetry (TLD)

Air Iodine Weekly 1-131 0.07 pCi/m 3 Air Particulate Weekly Gross Beta 0.01 pCi/rn 3 Quarterly (a)

Gamma Isotopic pCi/mr Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium (H-3) 2000 pCi/L Composite of monthly sample Monthly 1-131 10 pCi/L Gamma Isotopic pCiJL Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium (H-3) 2000 pCi/L 1-131 1

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

12

Table 2-2 (Cont.)

(Page 2 of 3)

SURRY - 2008 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA Shoreline Sediment FREQUENCY Semi-Annual ANALYSIS Gamma Isotopic Cs-134 Cs-137 LLD*

REPORT UNITS pCi/kg - dry 150 180 Silt Semi-Annual Monthly Gamma Isotopic Cs-134 Cs-137 150 180 pCi/kg - dry pCi/L Milk 1-131 1

Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 15 18 60 15 NA NA pCi/L pCi/L Quarterly Composite of CP monthly sample Sr-89 Sr-90 Oysters Clams Semi-Annual Semi-Annual Annually Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 130 260 130 130 260 130 150 130 260 1:30 130 260 130 150 130 260 130 130 260 130 150 pCi/kg - wet pCi/kg - wet pCi/kg - wet Crabs Footnotes located at end of table.

13

Table 2-2 (Cont.)

(Page 3 of 3)

SURRY - 2008 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS Fish Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic 1-131 Cs-134 Cs-137

130, 260 130 130 260 130 150 Food Products Annually pCi/kg - wet 60 60 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, are also identified and reported.

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

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

NA None assigned 14

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" WW

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'ESE

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' SE

,/ :*

SAir Sampling Stations SSW SSE

"*TLD Sampling State Environmental Monitoring Sites

i:

State TLD Sites Exclusion Area Boundary

Figure 2. Surry Emergency Plan Map Air Sampling Stations Nearest Residents TLD Sampling Nearest Milk Animal IoL Nearest Garden Aquatic Samples I S N

a v ell*

l

",: may be made without the written permission of ADC.

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Nearest Garden Aquatic Samples Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

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Nearest Milk Animal Nearest Garden Aquatic Samples Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the Surry Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979. A more detailed analysis of the data is given in Section 4.

20

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2008 Docket No. 50-280-281 Page 1 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Hip hest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units)

Type No.

LLD*

Range Name Direction I Range Range Measurements Direct Gamma 164 2

3.8 (152/152)

STA-9 0.3 mi 5.8 (4/4) 4.1 (12/12) 0 Radiation (1.6-7.3)

E (5.0-6.4)

(2.0-6.6)

TLD (mR/

Std Month)

Air Gross 416 10 29.9 (364/364)

BC 4.5 mi 32.5 (52/52) 30.2 (52/52) 0 Particulate Beta

(-0.4 - 71.2)

SSW (5.1 -71.2)

(8.5-66.3)

(IE-3 pCi/m3)

Gamma 32 Be-7 32 133 (28/28)

BC 4.5 mi 158 (4/4) 128 (4/4) 0 (88-192)

SSW (106-192)

(83-146)

Cs-134 32 50

< LLD N/A

< LLD

< LLD 0

Cs-137 32 60

< LLD N/A

< LLD

< LLD 0

Air Iodine 1-131 416 70

< LLD N/A

< LLD

< LLD 0

(1E-3 pCi/m3)

Milk (pCi/Liter)

Strontium 4

Sr-89 Sr-90 4

4 2.78 (2/4)

(1.56 - 4.00) 1.37 (2/4)

(1.10 - 1.64)

CP 3.7 mi 2.78 (2/4) 1 NNW (1.56 - 4.00)

CP 3.7 mi 1.37 (2/4)

NNW (1.10 - 1.64)

N/A N/A 0

0 Gamma 36 K-40 1-131 36 1427 (24/24)

(1350 - 1520) 36 1

< LLD CP 3.7 mi 1437 (12/12) 1347 (12/12)

NNW

'(1350-1520)

(1269-1400)

Cs-134 36 15

< LLD Cs-137 36 18

< LLD Ba-140 36 60

< LLD La-140 36 15

< LLD N/A N/A N/A N/A N/A

< LLD

" LLD

< LLD

" LLD

< LLD

" LLD

< LLD

" LLD 0

0 0

0

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.

21

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surny County, Virginia - 2008 Docket No. 50-280-281 Page 2 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (units)

Type No.

LLD*

Range Name Direction Range Range Measurements Food Gamma 3

Products (pCi/kg wet)

K-40 3

8295 (3/3)

Slade 3.2 mi 14850(1/1)

N/A 0

(2662 - 14850)

S (14850-14850) 1-131 3

60

< LLD N/A

< LLD N/A 0

Cs-134 3

60

< LLD N/A

< LLD N/A 0

Cs-137 3

80

< LLD N/A

< LLD N/A 0

Well H-3 12 2000

< LLD N/A

< LLD N/A 0

Water (pCi/Lter)

Gamma Mn-54 Co-58 Fe-59 Co-60 Zn-65 12 12 12 12 12 12 15 15 30 15 30 15 30 1

15

< LLD

< LLD N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

" LLD

< LLD

,<L.LD

< LLD

< LLD N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Nb-95 Zr-95 1-131 Cs-1 34 12 12 12 12 Cs-137 12 18

< LLD

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.

22

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2008 Docket No. 50-280-281 Page 3 of 6 Medium or Pathway Analysis Sampled Total (Units)

Type No.

LLD*

Well Ba-140 12 60 Water (pCi/Liter)

La-140 12 15 River H-3 8

2000 Water (pCi/Liter)

Gamma 24 K-40 24 Mn-54 24 15 Co-58 24 15 Fe-59 24 30 Co-60 24 15 Zn-65 24 30 Nb-95 24 15 Zr-95 24 30 1-131 24 10 Cs-134 24 15 Cs-137 24 18 Ba-140 24 60 Indicator Locations Mean Range

" LLD

< LLD

< LLD Control Location with Hi9 hest Mean Locations Non-Routine Distance Mean Mean Reported Name Direction Range Range Measurements N/A

< LLD N/A 0

N/A

< LLD N/A 0

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

N/A

< LLD N/A 0

111.7 (9/12)

(47.9-152)

< LLD

" LLD

< LLD

" LLD

< LLD SD N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0.4 mi 111.7 (9112)

NW (47.9-152)

< LLD

" LLD

< LLD

<'LLD

" LLD

< LLD

< LLD 72.4 (3/12)

(65.8 - 75.7)

< LLD

" LLD

< LLD

" LLD

< LLD

< LLD La-140 24 15

< LLD N/A

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.

23

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2008 Docket No. 50-280-281 Page 4 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (units)

Type No.

LLD*

Range Name Direction Range Range Measurements Silt Gamma 4

(pCi/kg dry)

K-40 4

12017 (2/2)

CHIC 11.2 mi 13007 (2/2) 13007 (2/2) 0 (8633-15400)

WNW (6423-19590)

(6423-19590)

Cs-134 4

150

< LLD N/A

< LLD

< LLD 0

Cs-137 4

180 154 (2/2)

CHIC 11.2 mi 167 (2/2) 167 (2/2) 0 (110-198)

WNW (61.3-272)

(61.3-272)

Th-228 4

948 (2/2)

CHIC 11.2 mi 1005 (2/2) 1005(2/2) 0 (566 - 1330)

WNW (483 - 1528)

(483 - 1528)

Shoreline Gamma 4

Sediment (pCi/kg dry)

K-40 4

6604(2/2)

HIR 0.6 mi 6604(2/2) 1877 (2/2) 0 (4785 - 8423)

N (4785 - 8423)

(1732 - 2022)

Cs-134 4

150

< LLD N/A

< LLD

< LLD 0

Cs-137 4

180

< LLD N/A

< LLD

< LLD 0

Th-228 4

323 (1/2)

HIR 0.6 mi 323 (1/2) 129 (1/2) 0 (323-323)

N (323-323)

(129 - 129)

Fish (pCi/kg wet)

Gamma 4

K-40 4

2277 (4/4)

(1764 - 2489)

SD 1.3 mi 2277(4/4)

NNW (1764 - 2489)

Mn-54 Co-58 Fe-59 Co-60 Zn-65 4

130

<LLD 4

130

< LLD 4

260

< LLD 4

130

< LLD 4

260

< LLD N/A N/A N/A N/A N/A

< LLD

" LLD

< LLD

< LLD N/A N/A N/A N/A N/A N/A 0

0 0

0

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.

24

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2008 Docket No..50-280-281 Page 5 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Hig hest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units)

Type No.

LLD*

Range NameI Direction Range Range Measurements Fish Cs-1 34 4

130

< LLD N/A

< LLD N/A 0

(pCi/kg wet)

Cs-1 37 4

150

< LLD N/A

< LLD N/A 0

Oysters Gamma 4

(pCi/kg wet)

K-40 4

697 (4/4)

MP 4.9 mi 763 (2/2)

N/A 0

(413 - 877)

ESE (650 - 877)

Mn-54 4

130

< LLD N/A

< LLD N/A 0

Fe-59 4

260

< LLD N/A

< LLD N/A 0

Co-58 4

130

< LLD N/A

< LLD N/A 0

Co-60 4

130

< LLD N/A

< LLD N/A 0

Zn-65 4

260

< LLD N/A

< LLD N/A 0

Cs-134 4

130

< LLD N/A

< LLD N/A 0

Cs-137 4

150

< LLD N/A

< LLD N/A 0

(pCi/kg weo

%jamma

(

K-40 8

589 (4/6)

(524 - 649)

JI 3.9 mi 641 (1/2) 490 (1/2)

NNW (641 - 641)

(490 -490)

Mn-54 Co-58 Fe-59 Co-60 8

130

< LLD 8

130

< LLD 8

260

< LLD 8

130

< LLD N/A N/A N/A N/A

< LLD

< LLD 0

0 0

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.

25

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2008 Docket No. 50-280-281 Page 6 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Hig hest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units)

Type No.

LLD*

Range Name Direction Range Range Measurements Clams Zn-65 8

260

< LLD N/A

< LLD

< LLD 0

(pCi/kg wet)

Cs-134 8

130

< LLD N/A

< LLD

< LLD 0

Cs-137 8

150

< LLD N/A

< LLD

< LLD 0

Crabs (pCi/kg wet)

Gamma 1

K-40 1

1648(1/1)

(1648 - 1648)

SD 1.3 mi 1648 (1/1)

NNW (1648 - 1648)

Mn-54 1

130

.< LLD Co-58 1

130

< LLD Fe-59 1

260

< LLD Co-60 1

130

< LLD Zn-65 1

260

< LLD Cs-134 1

130

< LLD Cs-137 1

150

< LLD N/A N/A N/A N/A N/A N/A N/A

< LLD

< LLD N/A N/A N/A N/A N/A N/A N/A N/A 0

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.

26

3.2 Analytical Results of 2008 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.

The reported error is two times the standard deviation (2y) of the net activity.

Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2(y error (i.e., the measured value exceeds 3(y).

GEL Laboratories LLC analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the Surry ODCM.

Data are given according to sample type as indicated below.

1.

Gamma Exposure Rate

2.

Air Particulates, Weekly Gross Beta Radioactivity

3.

Air Particulates, Weekly 1-131

4.

Air Particulates, Quarterly Gamma Spectroscopy

5.

Cow Milk

6.

Food Products

7.

Well Water

8.

River Water

9.

Silt

10.

Shoreline Sediment

11.

Fish

12.

Oysters

13.

Clams

14.

Crabs 27

TABLE 3-2: GAMMA EXPOSURE RA TE Surry Power Station, Surry County, Virginia - 2008 mRIStd Month +/- 2 Sigma Page I of I STATION FIRST SECOND THIRD FOURTH AVERAGE NUMBER QUARTER QUARTER QUARTER QUARTER

+/- 2 SIGMA 02 03 04 05 06 07 08 09 10 11 12 13 14 15 16 18 19 20 21 22 23 24 25 2.6 27 28

'29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 5.4 +/- 0.2 5.4 +/- 0.3 4.2 +/- 1.0 4.8 +/- 0.4 5.0 +/- 0.8 5.1 +/- 1.0 4.4 +/- 0.6 6.4 +/- 0.7 4.9 +/- 1.9 4.1 +/- 0.5 3.9 +/- 0.4 4.7 +/- 1.1 4.8 +/- 0.5 5.5 +/- 1.2

4.6 +/- 0.9 2.7 +/- 0.9 3.8 +/- 0.2 3.3 +/- 0.6 3.8 +/- 0.3 2.3 +/- 0.2 3.8 +/- 0.5 3.3 +/- 1.0 4.3 +/- 0.6 5.1 +/- 0.3 3.1 +/- 1.0 3.4 +/- 0.6 2.5 +/- 0.8 2.6 +/- 0.4 2.8 +/- 0.5 3.2 +/- 0.9 3.6 +/- 1.0 3.7 +/- 0.1 5.2 +/- 0.6 5.3 +/- 0.2 3.7 +/- 0.5 7.3 +/- 0.9 3.1 +/- 0.7 4.2 +/- 1.0 6.6 +/- 0.6 4.3 +/- 0.6 3.4 +/- 0.7 3.8 +/- 0.2 3.4 +/- 0.4 4.4 +/- 1.6 3.8 +/- 1.5 4.4 +/- 0.9 3.9 +/- 1.0 3.8 +/- 1.1 5.0 +/- 0.6 3.9 +/- 0.3 2.5 +/- 0.2 3.1 +/- 1.0 3.4 +/- 1.0 3.1 +/- 0.2 3.7 +/- 0.3 2.8 +/- 0.6 1.8 +/- 0.3 2.2 +/- 0.3 2.1 +/- 0.1 3.2 +/- 0.5 1.7 +/- 0.4 3.0 +/- 0.3 2.5 +/- 0.3 2.8 +/- 0.6 3.3 +/- 0.3 2.0 +/- 0.3 2.4 +/- 0.9 2.0 +/- 0.6 2.2 +/- 0.9 1.6 +/- 0.2 2.6 +/- 0.6 3.3 +/- 0.4 3.1 +/- 1.4 3.2 +/- 0.3 3.1 +/- 0.3 2.4 +/- 0.1 4.6 +/- 0.7 2.0,r+/- 0.7 2.9 +/- 0.3 4.9 +/- 1.0 2.7 +/- 0.3 2.5 +/- 0.6 4.4 +/- 0.5 4.4 +/- 0.2 4.3 +/- 0.6 3.8 +/- 0.6 4.4 +/- 0.3 4.3 +/- 0.5 3.8 +/- 0.1 5.3 +/- 0.2 4.5 +/- 1.2 3.6 +/- 1.6 3.7 +/- 0.3 4.0 +/- 0.8 4.6 +/- 2.0 4.5 +/- 0.2 4.3 +/- 1.9 2.5 +/- 0.6 3.2 +/- 1.2 3.3 +/- 1.7 3.7 +/- 1.9 2.0 +/- 0.2 3.7 +/- 0.7 2.6 +/- 0.1 2.8 +/- 0.3 3.8 +/- 0.3 2.7 +/- 0.3 2.9 +/- 0.9 2.5 +/- 0.2 2.5 +/- 0.4 2.1 +/- 0.2 3.0 +/- 0.4 3.1 +/- 0.6 3.0 +/- 0.3 4.0 +/- 0.4 3.8 +/- 0.4 3.3 +/- 0.9 5.2 4+/- 0.5 2.6 +/- 0.1 3.5 +/- 0.5 5.5 +/- 0.6 3.1 +/- 0.2 2.7 +/- 0.7 5.7 +/- 0.3 5.4 +/- 0.3 4.8 +/- 0.4 5.0 +/- 0.4 5.3 +/- 0.9 4.9 +/- 0.2 4.7 +/- 0.3 6.4 +/- 0.2 5.1 +/- 0.2 3.9 +/- 0.8 3.9 +/- 0.7 5.0 +/- 0.5 5.0 +/- 0.5 5.6 +/-,0.6 4.8 +/- 0.3 3.5 +/- 0.1.

3.3 +/- 0.9 3.3 +/- 1.3 3.6 +/- 1.5 2.5 +/- 0.8 4.8 +/- 0.9 3.5 +/- 1.1 3.6 +/- 0.2 4.9 +/- 1.0 3.0 +/- 0.4 3.3 +/- 1.0 2.7 +/- 1.5 3.0 +/- 1.7 2.4 +/- 0.9 3.5 +/- 0.8 4.2 +/- 0.7 3.8 +/- 1.0 4.6 +/- 0.7 5.0 +/- 0.8 31.4 +/- 0.7 6.0 +/- 1.2 3.5 +/- 0.3 3.8 +/- 0.1 6.5 +/- 0.9 3.5 +/- 0.5 2.9 +/- 0.8 4.8 +/- 0.9 4.7 +/- 1.0 4.4 +/- 0.3 4.4 +/- 0.6 4.8 +/- 0.4 4.6 +/- 0.6 4.2 +/- 0.5 5.8 +/- 0.7 4.6 +/- 0.5 3.5 +/- 0.7 3.7 +/- 0.4 4.3 +/- 0.7 4.4 +/- 0.9 4.8 +/- 0.9 4.1 +/- 0.9 2.6 +/- 0.7 3.1 +/- 0.7 3.0 +/- 0.6 3.6 +/- 0.3 2.1 +/- 0.4 3.8 +/- 0.7 3.0 +/- 0.5 3.4 +/- 0.7 4.3 +/- 0.9 2.7 +/- 0.5 3.0 +/- 0.5 2.4 +/- 0.3 2.6 +/- 0.3 2.2 +/- 0.5 3.1 +/- 0.4 3.6 +/- 0.5 3.4 +/- 0.4 4.3 +/- 0.9 4.3 +/- 1.0 3.2 +/- 0.6 5.8 +/- 1.2 2.8 +/- 0.6 3.6 +/- 0.5 5.9 +/- 0.8 3.4 +/- 0.7 2.9 +/- 0.4 28

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2008 1.OE-3 pCi/m3 2 Sigma Page 1 of 2 COLLECTIONI SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C January 08 January 15 January 22 January 29 February 05 February 12 February 19 February 26 45.1 +/-4.5 17.0 + 16.5 41.1 +/-4.6 64.3 + 5.7 42.6 + 4.4 2.7 + 16.0 13.6 + 3.0 22.7 + 3.6 44.6 +/- 4.5 19.1 +/- 16.8 36.0 +/- 4.4 71.2 +/- 6.0 45.5 +/- 4.9 32.4 +/- 13.8 33.7 + 14.0 29.4 + 15.4 36.3 16.2 35.3 64.3 45.7 32.2 31.8 30.6 52.4 +

33.9 +

33.0 +/-

29.5 +/-

35.1 +/-

32.6 +/-

35.4 +/-

21.2 _

5.2 13.6 13.9 15.2 13.3 12.9 12.0 13.0 18.6 +

28.7 +

32.1 +/-

25.1 +/-

29.0 +

24.8 +

38.2 _

22.1 +

3.3 13.3 13.8 15.0 12.7 13.1 11.9 12.8

+/- 4.1

+/- 16.7

+/- 4.3

+/- 5.7

+/- 4.9

+/- 13.6

+ 14.0

+ 15.3

_ 13.3

+ 13.0

+/- 12.2

+ 13.0 49.0 +/- 4.7 17.5 +/- 16.2 34.5 +/- 4.2 55.7 +/- 5.3 43.5 +/- 4.7 32.0 +/- 13.2 31.9 +/- 13.6 17.5 +/- 14.7 23.8 + 12.9 20.1 +/- 12.4 24.8 +/- 11.6 14.9 + 12.6 March 04 March 11 March 18 March 25 40.4 +/-

25.3 +/-

42.9 +/-

29.9 +

13.6 12.9 12.3 13.2 31.3 29.7 42.4 25.1 Qtr. Avg. +/- 2 s.d.

April 01 April 08 April 15 April 22 April 29 May 06 May 13 May 21 May 27 June 03 June 10 June 17 June 24 36.7 +/- 25.7 38.0 +/- 12.2 10.3 +/- 12.6 11.0 +/- 11.5 10.8 +/- 2.5

-0.4 +/- 9.1 6.4 +/- 2.1 28.4 + 3.9 24.9 +/- 12.1 17.5 +/- 15.6 21.0 +/- 15.2 29.5 +/- 15.2 28.0 + 10.4 20.3 +/- 10.3 18.9 _ 21.8 25.0 +/- 21.3 28.1 +/- 11.9 10.9 +/- 12.6 14.8 +/- 11.5 10.2 +/- 2.4 7.1 +/- 9.1 4.9 +/- 1.9 30.5 +/- 4.0 15.7 +/- 11.8 12.7 +/- 15.4 18.2 +/- 15.1 23.7 +/- 15.0

-2.6 +/- 9.7 16.2 +/- 10.2 37.5 +/- 26.6 35.1 +/- 23.8 30.4 +/- 26.5 37.0 +/- 4.1 12.0 +/- 16.8 39.4 + 4.5 61.1 +/- 5.6 46.4 +/- 4.9 24.8 +/- 13.6 28.2 +/- 13.9 29.0 +/- 15.3 32.2 +/- 13.4 27.0 + 12.9 39.3 + 12.3 30.0 + 13.4 33.9 - 24.5 34.1 +/- 12.9 15.7 + 12.8 15.8 +/- 11.8 9.1 +2.4 18.5 +/- 9.5 4.3 +/- 1.9 29.3 +/- 4.0 19.1 +/- 12.0 16.0 +/- 15.6 19.0 + 15.4 23.7 +/- 15.4 18.3 +/- 10.4 0.5 + 10.0 32.9 +/-

22.4 +/-

38.9 +/-

23.2 +

43.6 +/- 4.4 17.0 +/- 16.4 40.6 +/- 4.5 62.8 +/- 5.5 42.3 +/- 4.6 32.8 +/- 13.4 30.5 +/- 13.6 29.2 +/- 14.9 41.2 +/- 4.3 13.3 +/- 16.7 33.5 + 4.2 66.3 +/- 5.8 45.0 +/- 4.8 33.7 +/- 13.5 27.8 +/- 13.9 33.5 + 15.7 13.1 12.5 11.9 12.7 32.9 +/-

27.9 +

37.5 +/-

27.2 +

35.1 +/- 13.2 14.8 +/- 12.8 15.5ý+/- 11.7 5.1 +/- 2.0 18.6 +/- 9.5 6.9 42.5 29.0 18.1 22.6 30.6 29.8 17.9 13.4 12.8 12.1 13.2

+2.1

+4.7

+ 12.2

+ 15.7

+ 15.3

+ 15.4

+ 10.6

+ 10.4 33.4 + 12.1 16.4 + 12.7 13.1 +/- 11.5 4.7 +/- 1.9 22.4 + 9.6 4.6 +/- 1.9 32.2 + 4.1 24.4 _ 12.1 13.7 +/- 15.7 20.8 + 15.5 31.0 + 15.4 21.7 +/- 10.4 14.9 + 10.3 20.3 +/- 11.6 4.9 +/- 12.3 3.4 +/- 11.2 7.2 +/- 2.1 4.4 +/- 8.8

-1.1 +/-.1.0 31.8 +/- 4.1 21.2 +/- 12.1 16.9 +/- 15.8 16.9 +/- 15.4 33.0+/- 15.6 15.6 +/- 10.4 14.1 + 10.5 34.7 + 24.3 33.8 +/- 11.9 14.1 +/- 12.4 10.9 +/- 11.4 18.5 +/- 3.1 22.9 + 9.3 4.9 +/- 1.9 32.3 +/- 4.1 22.6 +/- 11.8 14.0 +/- 15.2 21.7 + 15.0 26.9 +/- 15.0 18.5 +/- 10.1 21.7 +/- 10.2 20.2 - 16.3 35.0 +/- 25.4 30.8 + 11.9 12.6 +/- 12.5 10.5 +/- 11.7 18.4 +/- 3.1 25.6 +/- 9.4 8.5 +/- 2.3 31.8 +/- 4.1 20.7 +/- 11.8 17.7 +/- 15.2 24.9 27.1 15.4 26.7

+/- 15.2

+/- 15.5

+/- 10.4

+ 10.6 Qtr. Avg. +/- 2 s.d.

14.7 +/- 18.4 22.0 +/- 21.8 19.5 +/- 18.9 14.5 +/- 21.2 17.2 +/- 18.3 20.8 +/- 15.3 29

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2008 1.OE-3 pCi/m3 =- 2 Sigma Page 2 of 2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN July 01 July 08 July 15 July 22 July 29 August 05 August 13 August 19 August 26 September 02 September 09 September 16 September 23 September 30 Qtr. Avg. +/- 2 s.d.

October 07 October 14 October 21 October 28 32.3 + 14.4 24.4 +/- 13.6 22.9 +/- 13.8 30.7 + 14.1 35.3 + 13.4 42.7 _ 14.4 27.2 + 11.3 42.6 +/- 12.3 31.6 +/- 12.0 27.6 _ 11.2 38.2 _ 12.7 27.5 + 11.6 33.7 _ 10.8 16.8 + 10.2 31.0 +/- 14.7 49.8 _+ 12.4 42.4 _ 11.8 47.5 _ 11.8 31.3 + 12.5 46.8 + 11.2 37.9 + 10.2 20.8 +/- 9.7 25.8 +/- 11.4 44.8 _ 11.9 43.4 + 10.0 32.3 _ 12.4 38.6 + 12.3 61.9 _ 13.5 40.3 + 21.8 31.6 + 26.2 35.9 + 14.0 22.8 + 13.5 24.7 + 13.7 29.8 + 13.9 33.2 + 13.2 36.9 +/- 14.1 31.4 +/- 11.3 42.1 +/- 12.2 30.0 +/- 11.8 27.0 + 11.1 33.9 +/- 12.5 20.4 + 11.2 29.2 _ 10.6 21.4 _ 10.2 29.9 - 12.5 41.4 _ 12.1 33.7 + 11.5 42.0 + 11.5 22.0 + 12.3 38.4 +/- 10.9 30.1 +/- 9.9 17.4 +/- 9.5 19.8 +/- 11.1 33.6 +/-

22.8 +/-

24.3 +/-

25.9 +/-

38.3 +

48.6 +

34.4 +

44.1 +/-

35.3 +/-

28.3 +/-

39.6 +/-

26.3 +/-

35.2 +/-

23.2 _

14.2 13.7 13.9 14.1 13.6 14.6 11.6 12.4 12.2 11.3 12.9 11.6 10.9 10.4 29.5 +/-

26.0 +/-

26.4 +

31.4 +/-

40.5 +/-

50.8 +/-

43.1 +

45.5 +

36.1 +

30.1 +

41.8 +

24.3 +

34.3 +/-

23.3 +

14.0 13.9 13.9 14.1 13.6 14.7 11.7 12.4 12.0 11.3 13.0 11.5 10.9 10.4 34.5 28.9 28.5 36.2 43.7 46.5 37.9 43.5 30.6 30.6 36.8 28.2 32.2 20.9

+ 16.0

+ 13.8

+ 14.2

+ 14.3

+ 13.9

+ 14.7

+ 11.7

+ 12.6

+ 12.0

+ 11.4

+ 12.7

+ 11.7

+ 11.0

+ 10.4 27.2 16.2 18.4 24.2 24.1 36.8 6.5 35.0 26.4 20.5 28.3 19.0 33.3 18.2

+/- 13.8

+/- 13.6

+/- 14.0

+/- 13.4

+/- 14.5

+/- 11.0

+/- 12.3

+/- 12.0

+/- 11.2

+/- 12.7

+/- 11.4

+ 10.8

+ 10.3 30.3 +/- 13.7 19.4 +/- 13.1 23.2 +/- 13.7 30.1 +/- 13.7 41.8 +/- 13.5 38.5 +/- 14.0 36.7 +/- 11.5 48.9 +/- 12.4 30.0 +/- 11.7 27.8 +/- 11.0 37.5 +/- 12.5 23.6 +/- 11.2 30.8 +/- 10.6 20.5 +/- 10.0 36.1 +/- 14.0 19.0 +/- 13.4 20.2 +/- 13.7 27.4 + 13.9 37.6 + 13.5 39.5 +/-

35.3 +/-

42.6 +/-

27.3 +/-

28.6 +/-

35.4 +/-

18.5 +/-

27.3 +/-

2.1.1 +

14.4 11.4 12.1 11.8 11.2 12.6 11.2 10.4 10.0 32.8 +/- 16.1 34.5 +/- 17.3 34.2 +/- 14.2 23.9 +/- 16.4 31.4 +/- 17.0 29.7 +/- 16.2 42.1 +/-

42.8 +/-

45.3 +/-

27.8 +

12.3 12.0 11.9 12.5 November 03 November 11 November 18 November 25 December 02 December 09 December 16 December 23 December 29 45.9 +/- 11.3 39.2 +/- 10.3 22.6 +/- 9.9 29.6 +/- 11.6 47.5 +

43.3 +/-

49.8 +/-

28.4 +

49.2 +/-

36.2 +/-

21.6 +/-

29.9 +/-

46.2 +

44.8 +

26.7 +

38.2 +/-

62.8 +

12.4 11.8 11.9 12.5 11.3 10.3 9.8 11.5 11.9 10.0 12.4 12.4 13.6 45.1 41.1 46.5 29.6 43.9 31.4 21.5 30.8

+ 12.6

+ 12.0

+ 16.1

+ 12.6

+ 11.3

+ 10.2

+ 9.9

+ 11.7 9.1 36.0 40.7 24.6

+/- 11.8

+/- 11.6

+/- 11.8

_ 12.4 43.6 +/- 12.0 37.5 + 11.5 44.4 +/- 11.5 26.2 + 12.1 29.3 + 10.6 32.8 _ 9.9 19.9 + 9.5 34.3 + 11.4 44.3 +/- 11.1 31.3 +/- 10.1 19.7 +/- 9.7 25.6 +/- 11.3 45.7 +/- 11.8 37.8 +/- 8.8 28.4 +/- 14.0 41.0 + 12.3 50.5 _ 13.3 41.7 _

40.9 +/-

44.4 +

26.0 +/-

44.7 +/-

27.4 +/-

22.7 +

27.4 +/-

43.5 +

34.5 +/-

24.3 _

35.0 +/-

51.1 +

12.0 11.4 11.9 12.3 11.9 9.9 9.8 13.6 11.7 8.8 13.9 12.3 13.1 35.8 +/-

38.5 +/-

28.5 +/-

35.5 +/-

46.2 +

11.6 9.7 12.2 12.2 13.1 40.5 +/-

40.7 +/-

30.2 _

33.3 +

55.3 +

11.9 10.0 12.5 12.3 13.6 47.7 +/- 12.0 42.2 +/- 10.1 26.1 +/- 12.5 43.6 +/- 12.7 61.8 + 13.7 46.9 +/-

35.5 +/-

25.1 +/-

39.7 +

45.4 +

11.6 8.6 13.8 12.1 12.9 Qtr. Avg. +/- 2 s.d.

Ann. Avg. +/- 2 s.d.

33.0 +/- 17.9 25.7 +/- 22.2 38.1 +/- 17.9 32.5 +/- 23.9 40.3 +/- 23.1 32.3 +/- 25.6 39.3 +/- 21.8 33.4 +/- 23.4 29.7 +/- 27.8 26.9 +/- 24.5 35.4 +/- 17.1 30.4 +/- 22.0 35.7 +/- 18.7 30.2 +/- 22.0 30

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2008 1.OE-3 pCi/m3 - 2 Sigma Page 1 of 2 I COLLECTION S

SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C January 08 January 15 January 22 January 29 February 05 February 12 February 19 February 26 March 04 March 11 March 18 March 25 April 01 April 08 April 15 April 22 April 29 May 06 May 13 May 21 May 27 June 03 June 10 June 17 June 24 7.1 +/- 4.2

-0.2 +/- 4.5 2.7 7.1 0.0 +/- 5.3 1.7 + 8.4 0.6 + 5.0

-4.3 + 5.9

-0.9 + 5.0 2.0 + 5.8 0.9 + 5.4 3.6 + 4.5 3.6 +/- 4.5

-1.6 + 5.0 6.0 + 3.9 4.2 +/- 3.9 1.2 _ 5.0 0.4 + 6.0 0.7 + 5.0 1.1 +/- 5.7

-2.0 + 4.6 1.2 + 5.3

-0.6 + 7.0 0.1 +6.9

-2.8 + 6.2

-1.5 + 4.6 2.5 + 4.7 2.8 + 4.8 3.3 + 8.0

-1.2 + 4.1 9.1 +8.8 0.4 + 4.8 1.4 +/- 5.9

-0.4 + 4.2 0.6 + 5.0

-5.2 +/- 6.1 3.0 +/- 7.9 0.4 + 5.2 0.9 + 7.8

-6.5 + 6.0 2.8 + 8.2 0.8 + 3.2

-2.8 +/- 6.5

-1.3 + 5.5

-0.2 +/- 5.8

-1.9 + 4.0 0.8 + 4.6 0.3 +/- 6.2

-2.8 + 4.7 3.7 + 4.7

-2.9 + 4.2 1.3 + 4.4 0.0 + 5.0 1.0+/-8.3

-4.3 + 5.7

-8.7 + 11.5 4.4 + 6.1

-1.2 + 4.1

-1.6 +/- 6.1 4.2 +/- 6.2

-5.7 + 6.0 0.8 +/- 6.9

-1.7 + 5.5 8.2 + 10.4

-0.1 + 3.2 1.1 +/-8.0

-1.8 +/- 4.9 2.8 + 9.0 1.0 +/- 4.7 2.5 +/- 7.8 2.3 +/- 3.8 2.8 +/- 6.8

-0.8 +/- 4.7 3.1 +6.2

-1.6 +/- 5.0 5.6 +/- 4.9 4.1 +/- 6.1 0.7 +/- 4.5 0.3 +/- 3.6

-2.0 +/- 3.7

-1.7 + 4.8

-6.5 + 5.1

-1.4 +/- 7.3 1.0 +/- 3.9 2.6 +/- 4.9 2.9 +/- 6.0

-1.7 +/- 4.8

-4.6 + 5.3 0.5 +/- 4.5

-1.6 +/- 4.8 3.8 + 8.3

-0.6 +/- 5.2.

1.1 +7.7

-0.8 +/- 4.0 1.0 +/- 6.9 1.8 +/- 3.6

-1.1 +/-4.7

-1.3 +/- 7.5 4.7 + 5.8 1.6 +/- 5.2

-0.6 +/- 5.8

-2.9 +/- 3.7 1.0 +/- 6.2 0.0 +/- 4.1

-2.4 +/- 5.3 1.5 + 6.4 5.8 +/- 5.7 8.8 +/- 5.9 6.8 + 7.7

-1.4 +/- 3.7

-2.3 +/- 4.7 9.6 +/- 8.5 2.9 +/- 5.1

-3.8 +/- 8.2 1.2 + 5.2 5.3 +/- 4.8

-3.6 + 5.5

-1.0 +/- 5.2

-2.9 +/- 6.1

-3.8 +/- 3.7

-5.4 +/- 5.8 4.2 + 5.6 0.9 6.1 1.3 +/- 5.5 0.8 + 6.0

-2.1 +/- 4.8

-2.3 +/- 5.3 1.5 +/- 5.4 3.2 + 5.6 1.9 +/- 5.9 2.3 + 5.2

-0.4 +/- 4.9 0.6 +/- 9.3

-1.4 + 5.1

-1.5 +/- 5.9 4.7 +/- 7.3 1.9 +/- 7.9 3.8 +/- 4.7 0.1 +7.9

-0.8 +/- 8.3

-4.6 +/- 5.8

-2.0 +/- 3.6 2.0 +/- 3.7

-3.2 + 5.3 1.1 +/-4.6 0.5 + 5.6 3.1 +5.7 2.4 5.1 8.2 +/- 7.3 1.8 +/- 5.2 3.6 +/- 4.8 2.6 +/- 4.2 4.5 +/- 6.8 2.8 +/- 3.8 3.5 + 11.4 0.2 + 3.6

-2.7 +/- 5.3 0.1 +/-6.6

-1.2 + 6.1 1.4 + 4.2 3.7 +/- 5.7 3.7 +/- 7.3 0.3 +/- 6.6 2.0 +/- 8.5 0.5 +/- 5.0 0.7 + 3.8 5.2 + 4.5 3.1

-1.9

-6.8

-4.2

+/- 7.3

+ 4.5

+/- 7.0

+ 6.4

-1.3 +

5.8 +

1.2 +

4.6 +/-

-1.6 +/-

0.5 +

16.1 +/-

0.1 +/-

-0.3 +/-

0.4 +/-

-3.2 +/-

0.4 +/-

-0.8 +

4.8 4.4 4.6 5.3 5.7 4.9 9.7 3.5 5.5 4.0 6.5 4.3 4.2 8.5 +/- 5.4 1.9 +/- 5.6

-3.7 +/- 5.3

-3.4 + 4.3

-2.8 + 4.3 3.4 0.0

-1.1

-3.4

-0.7 1.6 0.6 3.2

+/-5.1

+/- 4.2

+/- 4.9

+/- 5.5

+/- 4.6

+4.5

+ 4.3

+ 9.8 3.3

-1.1 1.0

-0.2

+/- 4.3

+/- 4.5

+/- 6.4

+7.1 31

TABLE 3-4: IODINE-131 CONCENTRA4TION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2008 1.0E-3 pCi/m3 +/- 2 Sigma Page 2 of 2 COLLECTION SS SAMPLING LOCATIONS I

DATE I

SHIR BC ALL CP BASF FE NN July 01 July 08 July 15 July 22 July 29 August 05 August 13 August 19 August 26 September 02 September 09 September 16 September 23 September 30 October 07 October 14 October 21 October 28 November 03 November 11 November 18 November 25 December 02 December 09 December 16 December 23 December 29

-3.8 + 5.1 3.6 +/- 4.7 4.2 +/- 4.8

-6.4 + 6.2 0.3 +4.1 1.1 +/-4.5 4.5 +/- 6.3

-1.9 + 5.8

-2.2 + 6.5 4.2 + 5.0 2.1 +5.3 0.2 + 5.1 1.9 + 4.2

-1.2 +/- 3.7 1.0 + 4.2

-1.1 +/-5.5 0.7 +/- 6.3 1.3 +/- 4.6

-0.8 + 8.6 1.5 +/- 5.6

-0.6 +/- 5.5

-2.1 + 4.6

-1.5 + 5.0 0.2 +/- 5.5

-1.5 + 4.8 0.9 +/- 6.7

-1.1 +/-6.5 1.4 +/- 5.9 1.0 + 6.4

-1.9 + 4.9

-1.3 +/- 5.4 4.6 + 4.8

-3.1 +/- 4.7 0.4 +/- 4.4 2.1 +/-5.3

-0.4 +/- 4.4

-2.9

-2.5

-0.1

-9.8 0.9-0.1

-3.2

-5.2 6.2

-1.3

-2.8

-3.5

-5.2

-0.1

-4.1

-4.5

-3.2

-0.3

+ 4.7

+ 6.7

+ 5.7

+ 7.2

+ 6.0

+ 4.3

+ 4.6

+5.1

+ 6.4

+ 4.5

+ 6.5

+ 4.5

+ 6.2

+ 5.4

+ 4.7

- 6.4

- 5.5

-1.1 1.7

-4.9

-2.9

-0.4 0.6

-0.8 0.0 1.8

-3.2

-1.3

-2.8

-2.6

+ 5.5

+5.1

+/- 5.4

+ 5.6,

_ 4.4

+ 3.5

+/- 5.2

+/- 6.5

+/- 5.7

+/- 7.6

+/- 5.7

+/- 4.2

+ 5.2

-2.2 + 4.9

-0.9 +/- 4.1 1.0 +/- 4.5 6.4 + 8.1 1.9 +/- 5.4 2.4 +/- 4.4

-2.3 +/- 4.6 0.4 +/- 5.5 0.0 +/- 3.7

-0.6 +/- 7.0

-1.7 +/- 5.4

-5.3 +/- 4.6

-0.4 +/- 5.5 2.3 + 4.2

-2.5 +/- 4.7 1.3 +/- 3.8 3.6 +/- 8.5 2.2 +/- 7.3 1.1 +/-7.8

-1.4 +/- 5.0

-0.4 +/- 5.1 0.5 +/- 7.3

-2.7 +/-

0.2 +/-

-1.6 +/-

0.6 +/-

-5.1 +/-

5.0 +

-4.1 +/-

0.3 +

0.8 +

-6.0 +/- 6.0 11.2 +/- 6.5 3.4 +/- 5.7 0.7 +/- 5.4 3.0 + 4.5 5.6 3.9 5.4 6.3 6.7 5.8 3.6 5.4 6.0

-6.4 +/- 4.3 2.9 +/- 7.7

-3.2 +/- 4.9

-1.6 +/- 7.4 2.3 +/- 4.6

-3.7 +/- 4.8

-4.0 +/- 5.2

-4.1 +/- 5.6

-5.0 +/- 4.8 3:9 +/- 6.0 0.2 +/- 4.8

-4.8 +/- 5.0

-3.6 + 6.5 0.6 +/-4.1 0.0 +/- 5.3 0.5 +/- 4.1 2.0 +/- 7.6

-5.1 +/- 5.5

-2.0 + 9.2 1.8 + 6.4

-0.1 7.2 1.9 +/- 5.4 0.7 +/- 5.2

-1.3 +/- 4.1 1.1 +5.3

-3.6 +/- 6.0 2.1 +5.6

-1.6 +/-

-1.9 +/-

-3.2 +

1.0 +/-

-2.4 +/-

-3.6 +/-

1.7 +/-

-1.7 +/-

4.4 +/-

-1.2 +/-

2.0 +/-

-2.0 +/-

-2.5 +/-

2.5+

-1.2 +/-

0.2 +/-

0.7 +/-

-2.3 +/-

-3.3 +/-

1.7 +

-2.1 +/-

3.1 +/-

-1.4 +/-

-2.0 +/-

3.7 +/-

4.6 +/-

-0.8 +

4.8 4.7 7.8 5.4 4.6 4.0 4.0 5.4 5.3 4.9 3.8 4.5 4.4 4.3 6.0 4.2 6.7 4.4 8.9 4.5-4.9 4.4 6.8 4.3 5.2 4.8 5.0 6.1+/-

-4.7+/-

-1.5+/-

-4.5+/-

1.9 +/-

-0.6 +/-

-0.1 +/-

-3.1 +/-

-0.8 +/-

1.7+/-

0.4+/-

0.5+/-

2.2+/-

-0.1+/-

7.8 5.8 5.9 4.8 5.7 4.3 5.2 7.0 3.7 5.7 3.6 4.2 5.6 5.1 8.3 +/- 9.7 3.3 +/- 4.8 0.1 +/-5.9

-2.6 +/- 4.6

-3.5 +/- 7.9 1.8 +/-6.1 3.2 +/- 4.8 1.7 +/- 3.9

-5.5 +/- 7.2

-0.2 +/- 5.8 1.4 +/- 5.5 0.1 +/-6.5 2.0 +/- 4.9 7.3 +/- 7.4

-1.6 +/- 4.1

-3.8 +/- 6.2 1.6 +/- 5.0

-4.8 +/- 8.3 0.8 +/- 4.9 0.5 +/- 6.3 0.0 +/- 7.5

-3.2 +/- 6.8 2.7 +/- 5.1 4.6 +/- 4.6

-1.6 +/- 5.7 8.3 +/- 6.9 5.1 +/-11.9 1.0 +/- 4.0 3.1 +/-5.6 1.1 +/-5.2 2.6 +/- 4.8 3.5 +/- 4.2

-1.0 +/- 6.1 3.0 +/- 5.5

-6.9 + 6.8

-3.9 +/- 7.2 1.0 +/- 5.2

-3.5 +/- 6.1 2.2 +/- 6.0 3.5 +/- 6.2 0.2 +/-

-2.7 +/-

1.2+/-

4.8 +/-

2.0 +/-

5.0 4.9 4.5 6.5 5.8 32

TABLE 3-5: GAMMA EMITTER CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2008 I.OE-3 pCi/m3 +/- 2 Sigma Page I of I SAMPLING FIRST SECOND THIRD FOURTH AVERAGE LOCATIONS NUCLIDE QUARTER QUARTER QUARTER QUARTER

+/- 2 SIGMA SS Cs-134 Cs-137 Be-7 HIR Cs-1 34 Cs-1 37 Be-7 BC Cs-1 34 Cs-1 37 Be-7 ALL Cs-1 34 Cs-1 37 Be-7 0.09

-0.01 157.0

-0.19

-0.02 110.0 0.07 0.08 158.0

-0.04 0.08 134.0

-0.05

-0.08 104.0

-0.16

-0.13 137.0 0.19

-0.12 136.0 0.14 0.14 146.0

+/- 0.26

+/- 0.03

+/- 20.9

+/- 0.27

+/- 0.23

+/- 17

+/- 0.33

+/- 0.29

+/-,20.0

+/- 0.25

+/- 0.22

+/- 18.1

+/- 0.28

+/- 0.26

+/- 16.3

+/- 0.50

+/- 0.45

+/- 21.3

+/- 0.40

_+0.36

+/- 21.1

+ 0.42

+/- 0.31

_ 24.1 0.20

-0.60 145.4 0.10 0.10 126.6

-0.40 0.20 191.8 0.00 0.20 159.7 0.10 0.10 119.9

-0.30 0.10 147.3

-0.10 0.00 157.6 0.20 0.30 146.4

+/- 0.60

+/- 0.50

+/- 27.7

+/- 0.30

+/- 18.3

+/- 0.40

+/- 0.30

+/- 26.7

+/- 0.30

+/- 20.7

+/- 0.50

+/- 0.20

+/- 19.0

+/- 0.50

+/- 0.30

+/- 28.3

+/- 0.30

+/- 0.20

+/- 20.3

+/- 0.50

+/- 25.0

-0.20

-0.10 165.9 0.00 0.20 135.9 0.10 0.00 174.7

-0.10 0.00 145.2 0.40 0.10 151.3 0.10

-0.20 124.1 0.00 0.10 144.7 0.10 0.20 137.3

+ 0.40

+ 0.30

+ 24

+ 0.30.

+ 0.30

+ 21.7

+ 0.40

+ 0.30

+ 25.0

+ 0.40

+ 0.20

+ 21.7

+ 0.40

+ 0.20

+ 25.4

+ 0.40

+ 0.30

+ 24.3

+ 3.00

+ 0.30

+ 22.7

+ 0.30

+ 21.0

-0.20 0.00 103.2

+/- 0.20

+/- 13.0 0.10 0.10 106.3 0.00

-0.10 103.4 0.00 0.10 108.1

+/- 0.20

+/- 12.2

+/- 0.20

+/- 13.6

+/- 0.20

+/- 0.10

+/- 13.1 0.10 +/- 0.20

-0.10

+/- 0.10 88.0 +/- 11.1 143 +/- 55 115 +/- 42 158 +/- 74 136 +/- 48 CP Cs-1 34 Cs-1 37 Be-7 BASF Cs-134 Cs-137 Be-7 FE Cs-134 Cs-137 Be-7 0.00

+/- 0.20 0.10 +/- 0.10 94.1

+/- 11.9 0.20

+/- 0.20 0.10

+/- 0.20 95.5

+/- 11.4 0.00 +/- 0.20 0.10

+/- 0.10 83.3 +/- 11.3 121 +/- 43 126 +/- 46 133 + 54 NN-C Cs-134 Cs-137 Be-7 128 +/- 61 33

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2008 pCi/Liter :L 2 Sigma Page 1 of 3 COLONIAL NUCLIDE EPPS PARKWAY' WILLIAMS-C JANUARY Cs-134 Cs-1 37 Ba-140 La-1 40 1-131 K-40 FEBRUARY Cs-134 Cs-137 Ba-140 La-i 40 1-131 K-40 0.30

-2.51

-3.54 0.53

-0.10 1410 MARCH Cs-134 Cs-137 Ba-140 La-140 1-131 K-40

Sr-89 Sr-90 APRIL Cs-134 Cs-137 Ba-140 La-140 1-131 K-40

-0.73 0.50

-1.93

-0.26

-0.07 1380 0.72 0.93 0.20 1.81 0.47 1350 0.52

-0.10

-1.72 1.30 0.01 1410 1.55 1.48 6.50 1.81 0.45 151 1.29 1.22 5.52 2.08 0.33 99 1.49 1.38 5.26 3.06 0.82 120 0.49 1.14 1.07 0.61

-0.32 1450

-0.44

-0.73

-2.97 0.45 0.08 1460

-0.40 1.01 0.06 1.50 0.10 1510 0.02 1.10 1.76 0.85 1.84

-1.18 0.32 1480 1.26 1.29 6.11 1.73 0.61 109 1.61 1.30 6.04 2.14 0.44 104 1.39 1.24 4.63 1.51 0.32 106 0.56 0.45 1.47 1.29 6.09 1.89 0.52 129

-0.85 0.73

-0.38

-0.39

-0.12 1269

-0.36 2.05 3.70 0.32

-0.24 1400 0.38 0.13

-0.09

-0.73 0.25 1351 1.52 1.11 4.60 1.30 0.48 93 1.24 1.35 5.64 1.61 0.38 106 1.30 1.29 5.40 1.86 0.43 105 1.18 1.05 5.83 1.29 0.55 93 1.25 1.22 5.40 1.67 0.52 100

-1.12 0.32 1.73

-0.13 0.26 1295 34

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2008 pCi/Liter +/- 2 Sigma Page 2 of 3 COLONIAL W

NUCLIDE EPPS PARKWAY WILLIAMS-C MAY Cs-i 34 Cs-i 37 Ba-140 La-I 40 1-131 K-40 JUNE Cs-134 Cs-137 Ba-i 40 La-140 1-131 K-40 Sr-89 Sr-90 JULY Cs-134 Cs-i 37 Ba-140 La-i 40 1-131 K-40

-0.21 0.31

-1.26

-1.21 0.00 1420 0.48

-0.08

-2.06 0.59 0.14 1410

-1.01 0.04

-0.90 0.72 0.51 1400

-0.01 0.31 2.72 0.01 0.28 1470 1.32 1.62 10.30 1.97 0.40 109 1.61 1.52 6.70 1.66 0.27 121 0.26

-1.61 1.71

-0.32 0.08 1430

-0.67 0.22

-6.57 1.19 0.24 1370 1.56 0.25 0.13 1.77

-7.75 1.16 0.34 1440 2.20

-1.06

-3.21 0.21 0.29 1380 1.70 2.86 7.05 2.24 0.34 104 1.49 1.45 5.77 1.75 0.45 123 0.87 0.38 1.37 1.32 8.59 1.75 0.43 112 2.12 3.98 7.79 2.46 0.25 115

-0.32 1.55 3.44

-0.09 0.48 1318

-0.48

-0.05 0.21

-0.89

-0.11 1380 1.11 1.61 5.22 1.73 0.50 94 1.18 1.22 4.47 1.41 0.22 99 1.33 1.92ý 5.64 1.70 0.29 116 1.35 1.98 4.50 1.37 0.32 98 2.36 2.00 7.20 2.43 0.40 111 1.89 1.77 6.78 2.08 0.32 119

-0.55 0.37 1.56 2.98 0.05 1399 0.91

-1.28 3.41 0.95 0.20 1360 AUGUST Cs-i 34 Cs-i 37 Ba-140 La-140 1-131 K-40 35

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2008 pCi/Liter +/- 2 Sigma Page 3 of 3 N

D ICOLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C SEPTEMBER Cs-1 34 Cs-1 37 Ba-140 La-140 1-131 K-40 Sr-89 Sr-90 OCTOBER Cs-1 34 Cs-1 37 Ba-140 La-1 40 1-131 K-40 NOVEMBER Cs-1 34 Cs-1 37 Ba-1 40 La-140 1-131 K-40 DECEMBER Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 1-131 K-40 Sr-89 Sr-90

-0.67 2.07 0.04 0.55

-0.03 1426

+

_+

+

1.48 2.06 7.50 2.22 0.39 126

-0.16

-2.73

-14.28 0.68 0.06 1483 1.20 2.16 0.78 1.90

-0.10 1481

-0.47 1.11 2.82

-0.82

-0.19 1378

+

2.14 2.90 14.68 2.35 0.38 129 1.59 1.39 5.96 1.69 0.42 112 1.50 1.32 5.32 1.61 0.45 102

-1.13 0.72

-4.86 0.31

-0.20 1360 4.00 1.64 0.02 0.58

-1.15 1.24 0.14 1350

-0.64 0.90 1.90

-2.58 0.14 1490 0.05

-0.73

-1.16

-2.16 0.20 1520

-0.96 0.84 1.42 1.90 7.54 2.22 0.38 106 1.02 A 0.67 A 1.85 2.18 6.43 1.89 0.42 148 1.99 1.38 6.72 2.10 0.57 129 1.58 2.48 6.86 1.89 0.40 134 2.32 0.56 1.12

-0.91 1.17 0.39

-0.02 1352

-0.47 0.64

-7.27

-0.63 0.07 1325 0.25 0.95 6.46 1.13 0.08 1379 0.97

-0.32 3.90

-0.34 0.15 1339 1.53 1.49 7.27 2.12 0.45 116 1.60 2.16 5.30 1.61 0.29 121 1.38 1.14 7.62 1.64 0.42 104 1.72 1.43 8.03 2.56 0.43 122

+

Footnote A - These concentrations were subsequently determined to be the result of sample contamination at the laboratory.

36

TABLE 3-7: GAMMA EMITTER CONCENTRATION IN FOOD PRODUCTS Surry Power Station, Surry County, Virginia - 2008 pCi/kg (wet) +/- 2 Sigma SAMPLING COLLECTION SAMPLE LOCATIONS DATE TYPE BROCK 12/01/2008 Corn FARM 12/01/2008 Peanuts Page 1 of 1 Cs-134

-2.08 +/- 5.32 5.55 +/- 10.09 Cs-137 4.41

- 5.07 1.02 + 7.77 1-131

-2.00 +/- 5.83 1.83 +/- 8.82 K-40 2,662 +

281 7,372 +

711 SLADE FARM 12/01/2008 Soybeans

-1.48 +/- 8.71

-4.79 +/- 6.33 2.46 +/- 7.47 14,850 +/- 1,019 37

TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER Surry Power Station, Surry County, Virginia - 2008 pCi/Liter +/- 2 Sigma Page 1 of 2 SAMPLING COLLECTION LOCATIONS DATE IISOTOPE SS 03/10/2008 06/09/2008 09/08/2008 12/09/2008 03/10/2008 06/09/2008 09/08/2008 12/09/2008 03/10/2008 06/09/2008 09/08/2008 12/09/2008 Ba-140 1.41

+/-

4.84

-0.97

+/-

4.54

-9.32

+/-

7.41 5.01

+/-

6.47 Fe-59

-0.45

+/-

2.61

-0.64

+/-

3.78 1.69

+. 2.59 0.70

+

2.84 Zn-65

-2.77

+/-

2.59

-0.35

+/-

2.82

-1.42

+/-

2.54

-0.59

+/-

3.86 Ba-140 3.25

+/-

4.31 3.74

+/-

3.92 8.73

+/-

6.62

-0.62

+/-

6.42 Fe-59

-0.06

+/-

2.05

-0.44

+/-

1.99 1.87

+/-

2.44 1.75

+/-

2.56 Zn-65 0.85

+/-

2.45

-2.82

+/-

2.05 0.26

+/-

2.19

-2.75

+/-

2.74 0.06

-0.02 0.06

-0.12 3.09 0.42 1.36 0.1.6 Co-58

-0.59

+/-

1.16

-0.41

+/-

1.12

-0.03

+/-

1.21 0.37

+/-

1.23 1-131

_+

2+

_+

2+

Zr-95

) +

.3+

+

_+

0.32 0.27 0.21 0.38 2.20 1.92 2.15 2.36 Co-60

-0.36

+/-

1.31 0.58

+/-

1.34

-0.29

+/-

1.74 0.10

+/-

1.42 La-140

-0.77

+/-

1.73

-1.22

+/-

1.61

-0.79

+/-

2.42 0.69

+/-

2.32 H-3 116.3

+/- 183.1 0.0

+/-

84.4

-104.9

+/- 224.1 127.7

+/- 290.5

, Co-60

-0.04

+/-

1.12 0.12

+/-

0.99 1.38

+/-

1.13 1.10

+/-

1.25 La-140

-1.03

+/-

1.51

-0.85

+/-

1.31 0.69

+/-

2.17

-0.46

+/-

2.46 H-3 88.6

+/-.184.7 23.1

+/-

91.9 127.5

+/- 247.3 89.3

+/- 286.2 Cs-1 34 0.57

+

1.37

-0.04

+/-

1.42

-0.69

+

1.20 0.96

+

1.56 Mn-54

-0.74

+/-

1.23

-0.02

+/-

1.21 0.11

+

1.19

-0.53

+

1.17 2.09 0.40 0.02 1.68 Cs-137 0.91

+/-

1.27 1.73

+

1.55 0.17

+

1.18 0.38

+

1.36 Nb-95

)+

) +

_*+

+/-

1.80 1.17 1.36 1.42 HIR 03/11/2008 06/09/2008 09/08/2008 12/09/2008 03/11/2008 06/09/2008 09/08/2008 12/09/2008 03/11/2008 06/09/2008 09/08/2008 12/09/2008 Co-58 0.28

+/-

0.99

-0.24

+/-

0.95

-0.36

+/-

1.04

-0.22

+/-

1.18 Cs-134 0.64

+/-

1.14

-0.95

+

1.34

-0.08

+/-

1.12 0.13

+

1.43 Mn-54 0.13

+/-

1.00 0.17

+/-

0.99

-0.15

+/-

1.04 0.44

+/-

1.20 Cs-137 0.02

+/-

1.01 0.04

+/-

1.25 0.03

+/-

1.05 0.54

+/-

1.22 0.20 0.26 0.08 0.33

-0.12 0.29 0.89 0.40 1-131

)+

+

S+

t,+

Zr-95 2+

)+

) +

)+

0.27 0.26 0.29 0.37 1.65 1.70 1.76 2.17 1.86 0.74 0.73 1.58 Nb-95

_+

+/-

1.05 1.02 1.50 1.45 38

TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER Surry Power Station, Surry County, Virginia - 2008 pCi/Liter +/- 2 Sigma Page 2 of 2 SAMPLING COLLECTIOND LOCATIONS DATE ISOTOPE CS 03/11/2008 06/09/2008 09/08/2008 12/09/2008 Ba-140 Co-58 2.50

+/-

5.49 0.05

+/-

0.86

-0.61

+/-

4.21

-0.37

+/-

1.06

-4.35 +/-

6.95 0.76

+/-

1.23

-3.58 +/-

7.16 0.75

+/-

1.37 Co-60

-0.22

+/-

1.04 1.40

+/-

1.22 1.10

+

1.23

-0.66

+

1.45 La-1 40

-0.28

+

1.25

-0.16

+/-

1.50

-0.93

+

2.44

-0.07

+

2.24 Cs-134 Cs-137 0.18

+/-

1.07

-0.48

+/-

0.96

-1.26

+/-

1.12

-1.20

+/-

1.16

-0.02

+/-

1.24 0.98

+

1.24

-0.81

+

1.71

-0.06

+/-

1.47 Mn-54 Nb-95

-0.31

+

0.89 0.23

+

1.04

-0.39

+/-

1.06 1.65

+

1.29

-0.11

+

1.14 0.26

+

1.37

-0.21 1.31 1.42

+

1.48 03/11/2008 06/09/2008 09/08/2008 12/09/2008 03/11/2008 06/09/2008 09/08/2008 12/09/2008 Fe-59

-0.68

+/-

0.87

+/-

-1.00

+/-

0.17

+/-

Zn-65 0.45

+

1.06

+

-1.07

+

-2.03

+

1.81 0.23 1.98 0.30 2.52

-0.07 2.83

-0.31 2.13 0.21 2.45 1.01 2.55

-0.73 3.76 1.07 I-!31 Zr-95

-+

0.29 0.28 0.31 0.53 H-3 1.63 238.7 + 193.9 1.77.

23.9

+/-

95.2 2.11 25.1

+/- 236.6 2.32 -253.8 + 256.8 39

TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WA TER Surry Power Station, Surry County, Virginia - 2008 pCi/Liter +/- 2 Sigma Page 1 of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Ba-140 SD 01/08/08 02/19/08 03/10/08 04/15/08 05/21/08 06/17/08 07/15/08 08/19/08 09/08/08 10/21/08 11/11/08 12/09/08

-0.38 0.51

-1.60

-0.42

-0.27 0.64 1.19 1.11 4.10

-2.37

-1.65

-0.29

+

9.87 5.93 6.28 3.88 6.22 4.28 4.67 5.43 6.36 5.32 4.29 4.96 Fe-59 01/08/2008 02/19/2008 03/10/2008 04/15/2008 05/21/2008 06/17/2008 07/15/2008 08/19/2008 09/08/2008 10/21/2008 11/11/2008 12/09/2008 01/08/2008 02/19/2008 03/10/2008 04/15/2008 05/21/2008 06/17/2008 07/15/2008 08/19/2008 09/08/2008 10/21/2008 11/11/2008 12/09/2008 1.37 2.47 1.49 0.11

-3.84

-0.55 0.18 1.79

-0.13 0.41 0.70

-1.15

+

4.60 2.52 2.19 2.69 3.46 2.00 2.39 2.41 2.70 2.14 1.87 2.12 Co-58

-3.24 + 1.26 0.52 + 1.26 1.00 + 1.03 0.30 + 1.11

-0.31

+ 1.04 0.52 _ 1.02 0.43 + 1.10

-0.50 +/- 1.18

-0.43 +/- 1.14

-1.08 +/- 1.00

-0.63 + 0.91 0.64 +/- 1.09 1-131 1.24 +/- 5.52 0.79 + 2.33 0.27 + 1.53

1.17 + 1.39 0.23 +/- 2.37 0.70 + 1.61

-1.32 + 1.56

-0.56 + 1.97 0.02 +/- 2.29 1.09 +/- 1.89

-0.36 +/- 1.68

-0.91 + 1.85 Zr-95 1.43 +/- 2.32 0.40 +/- 2.15 0.36 +/- 1.86

-0.85 + 1.77 0.86 +/- 1.94 0.85 + 1.73

-0.08 +/- 1.95 2.50 + 2.03 2.22 + 2.07

-0.83 + 1.81

-0.05 + 1.58 1.31

+ 1.85 Co-60 1.35 +/- 1.44 0.45 +/- 1.33 0.42 +/- 1.16

-0.44 +/- 1.09 0.86 +/- 1.01 0.83 +/- 1.02 0.48 +/- 1.16 0.49 +/- 1.19

-1.22 +/- 1.74

-0.06 +/- 1.09

-0.69 + 0.94

-0.34 +/- 1.23 La-140 2.36 +/- 6.19

-1.05 +/- 1.99

-0.04 +/- 1.56 0.44 +/- 1.38 0.60 +/- 2.14

-0.33 +/- 1.48 0.12 + 1.62

-0.89 + 1.84

-0.15 + 1.93

-0.60 +/- 1.75

-0.05 + 1.40

-0.04 +/- 1.89 H-3 13.0 +/- 281.8 13.5 +/- 290.5 13.1

+/- 286.6 32.9 +/- 181.4

-0.51 0.04 0.20 0.15

-1.14 0.46

-1.45

-0.31 1.01 1.19 0.59 0.92

+

2.10 1.43 1.22 1.15 1.08 1.04 1.34 1.26 1.34 1.24 1.07 1.35 Cs-134 Mn-54 Nb-95 Cs-1 37 0.41

-0.36

-0.70 0.21

-1.13

-0.51 0.29 1.06 0.84 0.39 0.18 0.23

+

-0.26 0.37

-0.06

-1.86 0.24

-1.00

-0.86 0.10

-1.16

-0.17

-0.30 0.26

+

2.08 1.26 1.00 1.57 1.00 0.93 1.58 1.13 1.14 0.94 0.90 1.03 0.45 1.23 1.26

-0.03 0.46 0.84 1.00 1.47 0.45

-0.49 0.23 0.47 1.32 1.94 1.46 1.07 1.16 1.00 1.25 1.14 1.25 1.08 0.98 1.05

+

1.51 1.37 1.02 1.04 1.15 1.04 1.20 1.21 1.32 1.41 1.26 1.17 Zn-65 0.69

-3.72

-0.70 0.14 0.94

-1.23

-1.15 1.18

-2.64

-1.73

-2.26

-1.20

+

2.67 3.06 2.20 2.08 2.57 2.10 2.81 2.79 2.69 2.16 1.92 2.31 K-40 104.0 +/- 32.1 72.7 +/- 34.4 47.9 +/- 28.3 78.1 +/- 31.7 151.5 124.4 150.8 146.1 130.0

+

+_

+

35.5 36.1 31.7 27.2 29.9 40

TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WA TER Surry Power Station, Surry County, Virginia - 2008 pCi/Liter + 2 Sigma Page 2 of 2 SAMPLING COLLECTION1 LOCATIONS DATE ISOTOPES

. Ba-140 SW-C 01/08/08 02/19/08 03/11/08 04/15/08 05/21/08 06/17/08 07/15/08 08/19/08 09/09/08 10/21/08

.11/11/08 1.69 0.68 0.07 1.67

-0.47 5.83 2.94 1.83

-2.03 1.64

-1.41

+

8.78 5.07 5.63 3.73 5.60 5.11 4.78 4.84 5.11 4.57 4.43 12/09/08 2.33 +/- 4.69 Fe-59 01/08/2008 02/19/2008 03/11/2008 04/15/2008 05/21/2008 06/17/2008 07/15/2008 08/19/2008 09/09/2008 10/21/2008 11/11/2008 12/09/2008 01/08/2008 02/19/2008 03/11/2008 04/15/2008 05/21/2008 06/17/2008 07/15/2008 08/19/2008 09/09/2008 10/21/2008 11/11/2008 12/09/2008 0.60

-0.69 1.32

-0.38 1.21

-2.25 1.09

-1.57 0.27 0.16

-1.10

-0.82

+

2.55 2.44 2.77 2.74 2.22 2.28 2.16 2.26 2.22 2.06 1.75 2.03 Co-58

-0.61

+/- 1.23 0.74 + 1.11 0.53 + 1.34 0.11 + 0.91

-0.14 + 1.00 0.14 +/- 1.02

-0.27 +/- 1.16 0.72 +/- 1.03 0.55 + 1.06

-0.74 0.92 0.46 + 0.81

-0.74 +/- 0.99 1-131 4.72 + 5.83 0.91 +/- 2.10

-0.71 + 1.53

-1.27 + 1.47

-0.18 + 2.60

-0.04 +/- 1.89

-0.16 +/- 1.57 0.53 + 1.82 0.13 +/- 1.93 0.60 _ 1.77

-0.41

+/- 1.61

-0.17 _ 1.74 Zr-95 0.19 +/- 2.12

-1.07 + 1.86

-0.82 + 2.40 0.39 + 1.43 0.49 + 1.93

-0.79 + 1.73 1.27 + 2.06

-0.39 +/- 1.91

-0.38 + 1.98

-0.34 + 1.74 0.10 + 1.67

-1.68 + 1.72 Co-60 0.49 + 1.11 0.31 + 1.14

-0.15 +/- 1.42 0.30 +/- 0.91 0.47 +/- 1.11 0.60 +/- 1.15 0.93 +/- 1.22

-0.84 + 1.80

-0.58 +/- 1.14 0.66 +/- 1.02 0.53 + 0.92 0.72 +/- 1.10 La-140

-4.31 5 5.18 0.07 +/- 1.77 0.15 + 1.88 0.56 + 1.13 0.60 + 2.10

-0.26 + 1.64

-0.63 +/- 1.43 0.21 1.77

-0.26 + 1.94

-0.73 + 1.70

-0.48 +/- 1.44

-0.11

+/- 1.80

-0.10

-0.11 0.17 0.45

-0.10

-0.32 0.57 0.00 0.52 0.67

-0.10 0.58

+

Cs-1 34 Cs-137 Mn-54 Nb-95 1.34 1.21 1.55 0.94 1.15 1.16 1.40 1.12 1.17 1.13 1.00 1.26 1.06 0.41

-1.21 0.18

-0.89 0.48 0.60 0.48 0.46

-0.57

-0.42

-0.19

+

-0.38

-1.07 0.13

-0.39 0.41

-0.06

-0.50

-0.03

-0.60

-0.51 0.25

-0.14

+

1.30 1.80 1.37 0.92 0.97 1.09 1.68 1.11 1.04 0.95 0.83 1.06 0.27 0.80

-1.49 2.15

-0.69 0.32 0.99

-0.03

-0.36 0.19 0.40

-0.14 1.26 1.17 2.24 0.97 1.04 1.17 1.28 1.13 1.11 1.01 0.89 1.09

+

1.45 1.12 1.45 1.77 1.14 1.16 1.23 1.12 1.46 1.07 0.96 1.09 Zn-65 H-3 K-40 65.80 +/- 24.20 0.06

-2.37

-0.88

-2.30

-1.80

-1.14 0.01 1.76

-0.57

-2.50

-0.93 0.56

+

4

+

2.40 2.33 3.02 2.85 2.10 2.91 2.48 2.32 2.16 2.21 1.76 2.21 347.0 +/- 313.1 24.8 + 288.3

-74.7 +/- 278.2

-88.7 _ 163.6 75.60 +/- 25.68 75.73 +/- 28.53 41

TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT Surry Power Station, Surry County, Virginia - 2008 pCi/kg (dry) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTIOND LOCATIONS DATE Cs-I 34 Cs-I 37 Th-228 K-40 SD 03/25/2008 19.6

+/- 17.6 09/08/2008 20.9 +/- 69.2 CHIC-C 03/25/2008 15.9

+/- 12.3 09/08/2008 58.4 +/- 67.5 110 +/- 19 198 +/- 82 61.3 +/- 11.9 272 +/- 102 566 +/- 47.2 1330 +/- 169 8633 +/- 715.7 15400 +/- 2140 483 +/- 40 6423 +/- 545.7 1528 +/- 202 _19590 +/- 2487 42

TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT Surry Power Station, Surry County, Virginia - 2008 pCi/kg (dry) + 2 Sigma SAMPLING COLLECTION1 LOCATIONS DATE Cs-134 HIR 02/19/2008 9.88

+/- 7.80 08/13/2008 20.90 +/- 16.40 Page I of 1 Cs-1 37 0.32 +/- 4.22 2.45 +/- 15.60 Th-228 323 +/- 25.6 K-40 4785 +/- 384 8423 +/- 823 CHIC-C 02/19/2008 7.46

+/- 7.98 1.03 +/- 4.00 08/13/2008 2.02 +/- 15.30 8.03 +/- 13.70 129 +/- 13.7 2022 +/- 194 1732 +/- 367 43

TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH Surry Power Station, Surry County, Virginia - 2008 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTION SAMPLE I LOCATION DATE TYPE ISOTOPE SD 04/23/2008 04/23/2008 10/30/2008, 10/30/2008 04/23/2008 04/23/2008 10/30/2008 10/30/2008 Catfish White Perch Catfish White Perch Catfish White Perch Catfish White Perch K-40 2367

+/- 235 2487

+/- 199 2489 +/- 283 1764 +/- 264 Cs-137 4.43 +/- 2.98 0.48

+/- 3.16

-2.51

+/- 5.74 7.76

+/- 6.73 Co-58

-1.23 +/- 4.15

-3.37 +/- 2.94

-1.64 +/- 6.45

-3.30 +/- 8.44 Fe-59

-7.98 +/- 9.53

-0.28 +/- 8.55 10.9 +/- 19.0

-2.86 +/- 21.1 Co-60 0.05 +/- 3.47 0.64 +/- 3.04

-0.98 +/- 6.64 0.94 +/- 7.41 Mn-54

-1.45 +/- 3.10

-0.27 +/- 2.41 0.46 +/- 5.08

-0.89 +/- 6.15 Cs-134

-1.08

+/- 3.32 0.40 +/- 2.83 10.5 +/- 6.45 2.90 +/- 8.38 Zn-65 8.26 +/- 7.26 0.39 +/- 6.79

-3.50 +/- 14.6

-6.15 +/- 17.2 44

TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Surry Power Station, Surry County, Virginia - 2008 pCi/kg(wet) +/- 2 Sigma Page I of I SAMPLING COLLECTION1 LOCATIONS DATE ISOTOPE POS K-40 03/25/2008 413 +/- 252 09/08/2008 850 +/- 410 Cs-137 03/25/2008 3.05 +/- 12.9 09/08/2008 1.82 +/- 5.71 K-40 03/25/2008 877 +/- 376 09/08/2008 650 +/- 430 Cs-137 03/25/2008

-13.3

+/- 18.9 09/08/2008

-0.86 +/- 7.28 Co-58 1.25 +/- 13.8 0.97 +/- 8.42 Fe-59

-14.8

+/- 22.7 0.89 +/- 21.6 Co-58 16.9 +/- 16.7 2.11

+/- 10.3 Fe-59 19.1

+/- 34.2

-8.83 +/- 21.2 Co-60

-1.36 +/- 13.2

-0.28 +/- 7.29 Mn-54

-5.41

+/- 13.5 0.24 +/- 6.65 Co-60

-12.9

+/- 19.7

-9.35 +/- 8.32 Mn-54

-17.4

+/- 15.9

-0.44 +/- 8.51 Cs-134

-1.91

+/- 15.2

-4.25 +/- 9.08 Zn-65 2.52

+/- 42.5

-13.4

+/- 19.1 Cs-134 10.5 +/- 18.3

-3.9 +/- 6.98 Zn-65

-23.6 +/- 44.1 0.58 +/- 12.0 MP 45

TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Surry Power Station, Surry County, Virginia - 2008 pCi/kg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE K-40 641

+/- 254 JI 03/25/2008 09/08/2008 Cs-137 03/25/2008 2.21

+/- 14.6 09/08/2008 3.55 +/-_5.82 K-40 542

+/- 285 SD 03/25/2008 09/08/2008 Cs-137 03/25/2008

-6.07 +/- 13.9 09/08/2008

-2.92 +/- 9.29 Co-58 4.96 +/- 15.5 1.27 +/- 7.40 Fe-59

-63.7 +/- 43.8 5.95 +/- 16.9 Co-58

-2.47 +/- 12.2

-1.96 +/- 10.2 Fe-59

-4.87 +/- 25.7.

4.90 +/- 22.6 Co-58

-2.77 +/- *18.5

-4.60 +/- 10.5 Fe-59 0.48 +/- 38.4 10.90

+/- 23.9 Co-58

-5.23 +/- 13.4 9.57 +/- 11.6 Fe-59

-1.73

+/- 29.7 15.1

+/- 29.3 Co-60 8.78

+/- 24.5 6.71

+/- 7.01 Mn-54 11.4 +/-+17.3 0.64 +/- 5.87 Co-60 13.00 +/- 14.8 2.31

+/- 9.75 Mn-54 3.92

+/- 11.9 3.72

+/- 8.85 Co-60

-24.1

+/- 31.1

-3.51

+/- 8.43 Mn-54 23.4 +/- 26.2 0.08

+/- 8.48 Co-60

-2.45 +/- 15.6 0.35

+/- 8.96 Mn-54 17.50

+/- 19.3

-3.30

+/- 9.66 Cs-134

-2.92 + 18.9 3.82 + 8.39 Zn-65 8.20 +/- 29.2

-17.3

+14.8 Cs-134

-1.81

+/- 20.7

-10.5 +/- 11.7 Zn-65

-9.98 +/- 26.8 5.50 +/- 16.4 Cs-134 0.15 +/- 19.1 0.41

+/- 8.13 Zn-65

-3.20 + 42.0

-10.5 +/- 21.1 Cs-134

-0.78 +/- 14.0

-0.23 +/- 8.78 Zn-65

-28.8 +/- 30.1 6.29 +/- 20.9 K-40 490 +/- 395 CHIC-C 03/25/2008 09/08/2008 Cs-1 37 03/25/2008

-4.82 +/- 17.7 09/08/2008

-2.73 +/- 7.38 K-40 LC 03/25/2008 649 +/- 286 09/08/2008 524 +/- 201 Cs-1 37 03/25/2008

-1.48

+/- 13.0 09/08/2008

-3.31

+/- 9.17 46

TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS Surry Power Station, Surry County, Virginia - 2008 pCi/kg (wet) +/- 2 Sigma SAMPLING COLLECTIONI LOCATIONS DATE Page 1 of I K-40 SD 06/17/2008 1648 + 365 Cs-137 8.5 +/- 14.8 Co-58

-7.51

+ 19 Fe-59

-23.8 +/- 41 ISOTOPE Co-60

.6 10.8 +/- 15.8 Mn-54

.4

-7.78 +/- 16.1 1

Cs-134

-4.63 + 18.2 Zn-65

-16.1

+/- 36.4 47

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2008 and tabulated in Section 3, are discussed below.

The procedures and specifications followed in the laboratory for these analyses are as required in the GEL Laboratories LLC quality assurance manual and laboratory procedures.

In addition to internal quality control measures performed by the laboratory, it also participates in an Interlaboratory Comparison Program.

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

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

The predominant radioactivity detected throughout 2008 was from external sources, such as fallout from nuclear weapons tests (cesium-137, strontium-90) and naturally occurring radionuclides. Naturally occurring nuclides such as beryllium-7, potassium-40, and thorium-228 were detected in numerous samples.

The following is a discussion and summary of the results of the environmental measurements taken during the 2008 reporting period.

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

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

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

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

The results of the TLD analyses are presented in Table 3-2. Figure 4-1 shows a historical trend of TLD exposure rate measurements, comparing the average of indicator TLDs located near the site boundary and at 5 miles to the average of all control TLD locations.

Control and indicator averages indicate a steady relationship.

Two dosimeters, made of CaF and LiF elements and specifically designed for environmental monitoring, are deployed at each sampling location.

In 26001, these TLDs replaced the previously used CaSO4:Dy in Teflon TLDs. The dose with the replacement TLDs is lower than that of the previously used TLDs as the increased sensitivity of the replacement TLD provides a more representative response to ambient radiation.

48

The eight-year trend since TLD type replacement indicates a minor increase in ambient exposure. Because the trend of the control and indicator locations continue to show the same historical relationship, this demonstrates that the increasing trend is not related to the operation of Surry Power Station. The most recent six-year trend indicates a stable trend. These trends will continue to be monitored.

Figure 4-1: DIRECT RADIATION MEASUREMENT TLD RESULTS 8

7 6

0

'E E 2 0

00 0

0 0

0 C'4 V3

("4 oC Site Boundry 5 Mile -i--

Avg Control ]

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

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

Gross beta activity found during the pre-operational and early operating period of Surry Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide.

In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady.

49

Rgure 4-2: 2008 GROSS BETA IN AIR PARTICULATES 0.070 0.060 0.050 0.040

0. 0.030 0.020 0.010 0.000

- ~ ~

~

ý 0w cl

'D

=

m 00 sl n0 C,

Cl (3, 'n r~-

ý 00C o

Cl C

C-4

(-=,

Cl_

5R Q,

5;?

Q C

Ql C

lC lC M

M

-t

'Zr kn kn

ý0

ý0 r-N-

C-0W000 a, 2

C lC

-Avg Indicator - -- A----

Ave Control Rgure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND 1.OE+00 I.QE-01 0.

&A 14 1%

&Af INV -IMF

-ME WT

-wv_

W I

1.OE-02 I.OE-03

'C, ml

ý W_,

'0 N-00 0'

C, lr-0 N

0 00 0'

0' 0'

0' 0

0' a,

0\\

a, 0'

C C

C Cl C"

Cl I=

Cl Cl C

Avg Indicator

- Avg Control -

Avg-Pre Op Required LLD 50

4.3 Airborne Radioiodine Air is also continuously sampled for radioiodines by passing it through charcoal cartridges.

Once a week the charcoal cartridge samples are collected and analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection.

No positive iodine-131 was detected. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.

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

No man-made radionuclides were identified. These analyses confirm the lack of station effects.

4.5 Cow Milk Analysis of milk samples is generally the. most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint.

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

Analysis results for cow milk are contained in Table 3-6. All results show a lack of detectable iodine-131 above the LLD of 1 pCi/L. Results of gamma spectroscopy indicate no other detectable station related radioactivity in the milk samples. In years past, cesium-137 has been detected sporadically. The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2008.

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.

Sr-90 was detected in the 1st and 3rd quarterly composites at an average concentration of 1.37 pCi/L. The average Sr-90 concentration for the ten year period of 1999 to 2008 is 1.84 pCi/L. Sr-89 was detected in the 2nd and 3rd quarterly composites at an average concentration of 2.78 pCi/L.

A historical review of milk analyses back to 1985 revealed no previous Sr-89 detection. Due'to the unusual detection of Sr-89, the vendor laboratory initiated an independent 51

assessment of the analyses.

The assessment concluded that sample contamination at the laboratory was the only reasonable explanation for the 3rd quarter composite sample results. Although the analytical data is included in this report, Surry Power Station does not have confidence in the positive Sr-89 data in the 2nd and 3rd quarter composite analyses and the positive Sr-90 data in the 3rd quarter composite analysis based on the conclusion -of the independent assessment and the fact that Sr-89 and Sr-90 are not components of the station radiological effluents. The presence of Sr-90 in the environment is rather a product of nuclear weapons testing fallout which has been well documented.

4.6 Food Products Three samples were collected and analyzed by gamma spectroscopy. The results of the analyses are presented in Table 3-7.

As expected, naturally occurring potassium-40 was detected in all samples.

The average concentration is consistent with that observed in previous years. No station relafed radioactivity was detected.

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

No gamma emitting isotopes were detected during the pre-operational period.

4.8 River Water Samples of the James River water are collected monthly and the results are presented in' Table 3-9. All samples are analyzed by gamma spectroscopy. The monthly samples are also composited and analyzed for tritium on a quarterly basis. With the exception of naturally occurring potassium-40 detected in some samples analyzed, no other gamma emitters were detected.

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

52

Samples of silt are collected from two locations, one upstream and one downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10. Trend graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.

Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). Cobalt-60 has not been detected since 2003.

Cesium-137 was detected, as expected, in both the control and indicator samples.

The levels detected indicate a continual decreasing trend seen for over a decade.

The detection of Cs-137 in both the control and indicator samples and decreasing levels indicate that the presence of Cs-137 is the result of accumulation and runoff into the river of residual weapons testing fallout. Its global presence has been well documented. During the pre-operational period, Cs-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5. In 2008, cesium-137 was detected with an average indicator location concentration of 154 pCi/kg and an average control location concentration of 167 pCi/kg. These activities continue to represent fallout from nuclear weapons testing.

Both indicator and control cesium-137 activities trend closely as shown in Figure 4-5.

Figure 4-4: COBALT-60 IN SILT 1.OE+04 1.OE+03 1.OE+02 C.,

1.0E+0 I L.OE+00 C1

'I 0

00 C

4 1-0 00 Ct Cl0 00 C

l 00 N-r-

r 00 00 00 00 00 C'

00C C

C, C

C',

0' F,

C' a' '

CD C

C Fý a F-a, z

-'C1 C4 Cl Cl C

Control - Chickahorniny A

Station Discharge 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 2008.

53

Figure 4-5: CESIUM-1 37 IN SILT L.OE+04 M 1.0E+03--

C.,

1.OE+02 (N

'I

'0 00

=>

N I '

00

'I (Ný 0

00 0

C1 "It 00 tN N-r 00 00 00 00 00 01 C,

C, C,

C' 0

0=

0 Control - Chickahorniny A Station Discharge -

Ave-Pre Op

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

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

The naturally occurring radionuclides potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities.

The activities of these radionuclides indicate a steady trend. There were no radionuclides attributable to the operation of the station found in any shoreline sediment samples.

4.11 Fish The radioactivity measured in fish sampled from the station discharge canal and analyzed by gamma spectroscopy is presented in Table 3-12. These results are the same as those seen over the last decade.

No activity was observed in this media except for naturally occurring potassium-40.

4.12 Oysters Oysters are collected from two different locations.

The results of the oyster analyses are presented in Table 3-13.

54

There were no gamma emitting radionuclides detected in oysters sampled except for naturally occurring potassium-40.

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

4.13 Clams Clams are analyzed from four different locations.

The results of the gamma spectroscopy analyses are presented in Table 3-14.

Like oysters, no station related radioactivity was detected.

Naturally occurring potassium-40 was detected.

4.14 Crabs A crab sample was collected in June from the station discharge canal and analyzed by gamma spectroscopy. The results of the analysis are presented in Table 3-15.

Other than naturally occurring potassium-40, no other gamma emitting radionuclides were detected in the sample. This is consistent with pre-operational data and data collected over the past decade.

55

5. PROGRAM EXCEPTIONS There were two REMP exceptions for scheduled sampling and analysis during 2008.

The 1-131 minimum detectable concentration (MDC) was 1.02 pCi/L in the January Colonial Parkway milk sample. This concentration is greater than the lower limit of detection (LLD) concentration of 1.0 pCi/L. Although an MDC is a posteriori measurement, Surry Power Station requires that this value be less than or equal to the required LLD. This ensures that REMP samples are analyzed to required program elements.

During the March clam sampling campaign, clams were not found at the Hog Island Point sample location. An alternate sampling location, Jamestown Island, was selected and sampled throughout 2008.

56

6. CONCLUSIONS The results of the 2008 Radiological Environmental Monitoring Program for Surry Power Station have been presented in previous sections. This section presents conclusions for each pathway.

Direct Radiation Exposure Pathway - Control and indicator location averages continue to indicate a steady relationship. The dose trend of the new type TLD will continue to be monitored and evaluated.

Airborne Exposure Pathway - Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. Air particulate gross beta concentrations at all of the indicator locations for 2008 trend well with the control location.

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

Strontium-89 was detected in the 2nd and 3rd quarter samples and strontium-90 was detected in 1st and 3rd quarter samples this year. The 2nd and 3rd quarter sample analyses for strontium-89 and strontium-90 are questionable due to probable laboratory contamination issues during sample preparation.

In the 1st quarter, strontium-90 was detected at a concentration of 1.10 pCi/L. Strontium-90 is not a component of station effluents, but rather, a product of nuclear weapons testing fallout.

Food Products - As expected, naturally occurring potassium-40 was detected in all three samples.

In the past, cesium-137 has occasionally been detected in these samples and is attributable to global fallout from past nuclear weapons testing. Cesium-137 was not detected in any of the three samples collected in 2008.

Well Water - Well water samples were analyzed and the analyses indicated that there were no man-made radionuclides present.

This trend is consistent throughout the monitoring period. No radioactivity attributable to the operation of the station was identified.

River Water - All river water samples were analyzed for gamma emitting radionuclides.

Only naturally occurring potassium-40 was detected in twelve of twenty-four samples. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2008.

k 57

Silt - Cesium-137 was detected in both the control and indicator samples.

The presence of Cs-137 is attributable to residual weapons testing fallout; its presence has been well documented. Cobalt-60 has not been detected since 2003.

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

Aquatic Biota

> Fish - As expected, naturally occurring potassium-40 was detected in all four sarrmples. There were no other gamma emitting radionuclides detected in any of the fish samples.

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

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

58

REFERENCES 59

References

1.

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

Draft Rev. 3, March 1982.

2.

United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October 1977.

3.

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

December 1975.

4.

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

5.

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

6.

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

7.

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

8.

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

60

APPENDICES 61

APPENDIX A: LAND USE CENSUS Year 2008 62

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January I to December 31, 2008 Page 1 of I i

Nearest Nearest Nearest Nearest I

Sector Direction Resident Garden*.*

Cow Goat A

N 4.1 @ 100 (a)

(a)

B NNE 1.9 @ 32-1.9 @ 320 (a)

(a)

C NE 4.7 @ 350 4.9 @ 56-(a)

(a)

D ENE (a)

(a)

E E

(a)

F ESE (a)

(a)

G SE (a)

(a)

H SSE 3.1 @ 1490 (a)

(a)

J S

1.7 @ 1810 1.8 @ 1830 (a)

(a)

K SSW 2.3 @ 2120 4.3 @ 193-4.8 @ 2000 (a)

L SW 2.3 @ 2210 3.6 @ 2230 (a)

(a)

M WSW 0.4 @ 2440 3.6 @ 2450 (a)

(a)

N W

3.1 @ 2600 3.4 @ 2600 (a)

(a)

P WNW 4.9 @ 283-(a)

(a)

Q NW 4.6 @ 3210 (a)

(a)

R NNW 3.8 @ 3380 4.4 @ 3340 3.7 @ 336-(a)

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

- Area greater than 50 m2 and contains broadleaf vegetation.

(a) None 63

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2008 64

INTRODUCTION This appendix covers the Interlaboratory Comparison Program (ICP) of GEL Laboratories LLC (GEL).

GEL uses QA/QC samples provided by Analytics, Inc.,

Environmental Resource Associates (ERA) and the Mixed Analyte Performance Evaluation Program (MAPEP) to monitor the quality of analytical processing associated with the REMP. Each provider has a documented Quality Assurance.

program and the capability to prepare Quality Control materials traceable to the National Institute of Standards and Technology (NIST). The providers supply the samples to GEL, and upon receipt, the laboratory performs the analyses in a normal manner. The results are then reported to the provider for evaluation. The suite of QA/QC samples is designed to provide sample media and radionuclide combinations that are offered by the providers and included in the REMP and typically includes:

3 milk for gamma nuclides and low-level iodine-131 analyses, 3 milk for Sr-89 and Sr-90 analyses, 3 water for gamma nuclides, low-level iodine-131, and gross beta analyses, 3 water for tritium, Sr-89, and Sr-90 analyses, 3 cartridge for l-131 analyses,

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

The accuracy of each result reported to Analytics, Inc is measured by the ratio of GEL's result to the known value.

Accuracy for all other results is based on statistically derived acceptance ranges calculated by the providers.

An investigation is undertaken whenever the ratio or reported result fell outside of the acceptance range.

RESULTS The GEL ICP results are included in the following tables for the first through the fourth quarters of 2008. Nine results did not meet the acceptance criteria and are discussed as follows.

- 1st quarter milk - The root cause of the Sr-90 failure was determined to be method inaccuracies when 'Using a small sample volume. The Sr-90 data over the past 2.5 years was evaluated using average relative bias and relative precision statistics as outlined in ANSI N13.30. The average relative bias over this period is 0.0230 which is an excellent average relative bias. The relative precision is within the recommended 0.40 range at 0.2325. This indicates the method is in control.

The normal procedure utilizes 500 - 800 mL of sample for analysis resulting in a lower detection limit and a lower uncertainty when compared to the analysis of the cross check samples normally utilizing 200 mL of sample due to limited sample volume.

65

1st quarter water - The nickel-63 failure was attributed to an unusually low gravimetric yield.

Results back to the year 2000 were reviewed with no other failures for this matrix identified. The carrier was re-standardized and the sample was re-analyzed with acceptable results. No further actions needed.

2nd quarter milk - The Sr-89 result fell below the acceptance criteria. All data were reviewed and no errors are apparent. A batch duplicate was also analyzed with this sample and its results fall within the acceptance criteria. All other quality control criteria were also met. No further investigation will be performed.

2nd quarter water - The root cause of the gamma emitter (Ba-133, Cs-134, Cs-137, Co-60, Zn-65) failures was attributed to an incorrect dilution. The samples are received as concentrates and must be diluted prior to preparation. Per the instructions, the samples should have been diluted to a final volume of 2 liters but were diluted to 4 liters instead. All instructions are now scanned by the Quality Assurance Officer and emailed to the laboratory Group Leader when the samples are logged. The instructions are also stored in a location accessible to all laboratory personnel.

o 4th quarter water - The Cs-137 result fell just above the acceptance criteria. All data was reviewed and no errors were apparent. A batch duplicate was also analyzed with this sample and its results fall within the acceptance criteria. All other quality control criteria were also met. A remedial sample was performed and the results fell within the acceptance range.

2007 Interlaboratory Comparison Data The 2007 Annual Radiological Environmental Operating Report was submitted documenting seven analyses that did not pass the acceptance criteria of the AREVA NP Inc. Environmental Laboratory Analytics Intercomparison Program.

The unsuccessful analyses occurred in the 2nd and 4th quarters.

AREVA NP submitted Condition Reports (CR) 08-02, 08-10 and 08-11 to document the unsuccessful analyses. The CRs have since been closed and are summarized as follows.

CR 08-02 documented the 2nd quarter low biased analyses for cerium-141 in the milk matrix and chromium-51 in the particulate filter matrix. The cause for the cerium-141 low bias was determined to be poor counting statistics due to a delay in sample analysis. The sample decayed through two half-lives before analysis.

Contributing factors included laboratory staff turn-over, sample back log, failure to initially identify the sample'as a quality control sample and analyze appropriately, and failure of laboratory supervision to identify the problem in a 66

reasonable time frame. Corrective actions included laboratory staff retraining and elimination of sample back log.

The cause for the chromium-51 low bias was determined to be a sample geometry issue.

Upon examination, it was discovered that the particulate filter did not completely lay flat in the sample holder. The corrective action taken was to modify the sample holder to ensure the sample laid completely flat. A subsequent filter analysis with the modified holder performed in the 2nd quarter of 2008 passed the Analytics Intercomparison Program criteria.

CR 08-10 documents the 4tf quarter low biased analyses for strontium-89 and strontium-90 in the particulate filter matrix.

The bias was caused by a radiotracer sample volume error that led to an incorrect determination of chemical recovery. A sample volume of 2 mL was used while a sample volume of 1 mL is hard coded in the laboratory data management system. Corrective actions included restricting the radiotracer volume to 1 mL, removing the hard coded 1 mL sample volume from the laboratory data management system, and requiring manual entry of tracer sample volume by the laboratory technician into the laboratory data management system.

CR 08-11 documents the 4th quarter low biased analyses for iron-59, zinc-65 and cobalt-60 in the particulate filter matrix. The same issue and corrective action described above in CR 08-02 apply to CR 08-11.

67

INTERLABORATORY COMPARISON DATA GEL ENVIRONMENTAL LABORATORY QA PROGRAM GEL LABORATORIES LLC (PAGE 1 OF 4) 1st Quarter Reported Known 2008 Date Matrix Nuclide Units Value (a)

Value (b) Evaluation (c) 2/22/2008 Filter Cs-134 Bq 1.97 2.52 A

Cs-137 Bq 2.47 2.70 A

Co-57 Bq 3.30 3.55 A

Co-60 Bq 1.16 1.31 A

Mn-54 Bq

-0.0113 0.00 A

Zn-65 Bq 1.92 2.04 A

3/6/2008 Water Cs-134 Bq/L 0.108 0

A Cs-137 Bq/L 0.0648 0

A Co-57 Bq/L 23.2 22.8 A

Co-60 Bq/L 8.41 8.4 A

Mn-54 Bq/L 483 472 A

Zn-65 Bq/L 17.4 16.3 A

3/12/2008 Am-241 Bq/L 1.27 1.23 A

3/18/2008 Filter Am-241 Bq 0.123 0.158 A

3/20/2008 Milk 1-131 pCi/L 61.8 60 A

Ce-141 pCi/L 255 249 A

Cr-51 pCi/L 331 359 A

Cs-134 pCi/L 107 125 A

Cs-137 pCi/L "151 146 A

Co-58 pCi/L 72.9 70.8 A

Mn-54 pCi/L 98.7 94.2 A

Fe-59 pCi/L 106 102 A

Zn-65 pCi/L 142 137 A

Co-60 pCi/L 240 236 A

Sr-89 pCi/L 96.7 95.8 A

Sr-90 pCi/L 9.32 12.9 U

3/20/2008 Water 1-131 pCi/L 77.3 70.4 A

Ce-141 pCi/L 191.3 198 A

Cr-51 pCi/L 279.2 286 A

Cs-134 pCi/L 96.1 99.7 A

Cs-137 pCi/L 114.8 116 A

Co-58 pCi/L 58.9 56.4 A

Mn-54 pCi/L 80.4 75 A

Fe-59 pCi/L 86.1 81.4 A

Zn-65 pCi/L 110.7 109 A

Co-60 pCi/L 194.8 188 A

Sr-90 Bq/L 12.0 11.4 A

3/20/2008 Cartridge 1-131 pCi 63 60 A

3/22/2008 Filter Gr-Beta Bq 0.321 0.286 A

Gr-Alpha Bq 0.143 0.348 A

3/27/2008 Water Fe-55 Bq/L 46.9 36.5 A

Ni-63 Bq/L 40.3 30.7 U

3/28/2008 Filter Sr-90 Bq 1.48 1.548 A

Footnotes are on page 4 of 4.

68

INTERLABORATORY COMPARISON DATA GEL ENVIRONMENTAL LABORATORY QA PROGRAM GEL LABORATORIES LLC (PAGE 2 OF 4) 2nd Quarter Reported Known 2008 Date Matrix Nuclide Units Value (a)

Value (b) Evaluation (c) 4/15/2008 Water 1-131 pCi/L 28.4 28.7 A

5/8/2008 Water Gr-Beta pCi/L 46.3 51.4 A

Gr-Alpha pCi/L 56.0 50.8 A

Am-241 pCi/L 95 90.9 A

Cs-134 pCi/L 693 751 A

Cs-137 pCi/L 1970 1990 A

Co-60 pCi/L, 1480 1420 A

Mn-54 pCi/L

<9.32 0

A Zn-65 pCi/L 800 694 A

5/9/2008 Water Sr-89 pCi/L 57.8 60.4 A

Sr-90 pCi/L 30.7 39.2 A

5/13/2008 Water Ba-133 pCi/L 17.2 58.3 U

Cs-134 pCi/L 11.2 46.6 U

Cs-137 pCi/L 24.8 102 U

Co-60 pCi/L 20.6 76.6 U

Zn-65 pCi/L 31.8 106 U

Sr-90 pCi/L 517 512 A

5/19/2008 Water H-3 pCi/L 12500 12000 A

6/19/2008 Water 1-131 pCi/L 40.9 45.3 A

Ce-141 pCi/L 222 237 A

Cr-51 pCi/L 212 188 A

Cs-134 pCi/L 100 104 A

Cs-137 pCi/L 169 158 A

Co-58 pCi/L 85.6 84.2 A

Mn-54 pCi/L 193 184 A

Fe-59 pCi/L 129 125.

A Zn-65 pCi/L 194 172 A

Co-60 pCi/L 155 142 A

6/20/2008 Water H-3 pCi/L 25800 25800 A

6/19/2008 Cartridge 1-131 pCi

ý87.5 84.5 A

6/19/2008 Milk 1-131 pCi/L 72.9 71.4 A

Ce-141 pCi/L 166 174 A

Cr-51 pCi/L 151.5 138 A

Cs-134 pCi/L 73.8 76.7 A

Cs-137 pCi/L 122 116 A

Co-58 pCi/L 64.4 61.9 A

Mn-54 pCi/L 153 135 A

Fe-59 pCi/L 92 91.7 A

Zn-65 pCi/L 128

127, A

Co-60 pCi/L 103 104 A

Sr-89 pCi/L 61.14 85 U

Sr-90 pCi/L 11.82 14.5, A

Footnotes are on page,4 of 4.

69

INTERLABORATORY COMPARISON DATA GEL ENVIRONMENTAL LABORATORY QA PROGRAM GEL LABORATORIES LLC (PAGE 3 OF 4) 4th Quarter Reported Known 2008 Date Matrix Nuclide Units Value (a)

Value (b) Evaluation (c)

There were no samples processed in the 3rd quarter 10/15/2008 Water 1-131 pCi/L 29.2 28.1 A

10/22/2008 Water Am-241 Bq/L

-0.0003 0

A Cs-134 Bq/L 18.9 19.5 A

Cs-137 Bq/L 23.0 23.6 A

Co-57 Bq/L 0.01 0

A Co-60 Bq/L 11.4 11.7 A

Mn-54 Bq/L 13.4 13.7 A

Zn-65 Bq/L 17.0 17.1 A

Fe-55 Bq/L 44.8 46.2 A

Ni-63 Bq/L

-0.2 0

A Sr-90 Bq/L 6.40 6.45 A

10/22/2008 Filter Gr-Beta Bq 0.564 0.525 A

Gr-Alpha Bq 0.003 0

A Am-241 Bq

-0.0003 0.0 A

Cs-134 Bq 2.727

2.63 A

Cs-137 Bq 0.024 0.00 A

Co-57 Bq 1.653 1.50 A

Co-60 Bq 0.051 0.00 A

Mn-54 Bq 2.87 2.64 A

Zn-65 Bq 1.063 0.94 A

Sr-90 Bq 1.08 1.12 A

10/30/2008 Milk 1-131' pCi/L 69.1 67.9 A

Ce-141 pCi/L 159 161 A

Cr-51 pCi/L 392 421 A

Cs-134 pCi/L 213 232 A

Cs-137 pCi/L 154 162 A

Co-58 pCi/L 167 179 A

Mn-54 pCi/L 172 166 A

Fe-59 pCi/L 157 144 A

Zn-65 pCi/L 327 319 A

Co-60 pCi/L 227 234 A

Sr-89 pCi/L 63.1 73.9 A

Sr-90 pCi/L 9.25 11 A

10/30/2008 Water 1-131 pCi/L 115 105 A

Ce-141 pCi/L 114 107 A

Cr-51 pCi/L 317 279 A

Cs-134 pCi/L 147 154 A

Cs-137 pCi/L 116 107 A

Co-58 pCi/L

'119 118 A

Mn-54 pCi/L 126 110 A

Fe-59 pCi/L 109 95.6 A

Zn-65 pCi/L 228 211 A

Co-60 pCi/L 155 155 A

10/30/2008 Cartridge 1-131 pCi 93.8 89.1 A

Footnotes are on page 4 of 4.

70 f

INTERLABORATORY COMPARISON DATA GEL ENVIRONMENTAL LABORATORY QA PROGRAM GEL LABORATORIES LLC (PAGE 4 OF 4) 4th Quarter Reported Known 2008 Date Matrix Nuclide Units Value (a)

Value (b)

Evaluation (c) 11/1/2008 Water H-3 pCi/L 2100 2220 A

11/8/2008 Water Sr-89 pCi/L 44.3 48.7 A

Sr-90 pCi/L 32.2 33.6 A

11/11/2008 Water Ba-133 pCi/L 60.7 63.5 A

Cs-134 pCi/L 28.1 25.6 A

Cs-137 pCi/L 31.5 25.6 U

Co-60 pCi/L 46.7 49.1 A

Zn-65 pCi/L 77.2 68.6 A

11/20/2008 Water Ba-133 pCi/L 72.6 73.1 A

Cs-134 pCi/L 72.8 64.9 A

Cs-137 pCi/L 184 176 A

Co-60 pCi/L 87.3 84.4 A

Zn-65 pCi/L 354 327 A

11/21/2008 Water Gr-Beta pCi/L 28.8 38 A

Gr-Alpha pCi/L 17.6 26.9 A

Am-241 pCi/L 174 161 A

Cs-134 pCi/L 1250 1240 A

Cs-137 pCi/L 1270 1270 A

Co-60 pCi/L 1160 1130 A

Mn-54 pCi/L

<9.12 0

A Zn-65 pCi/L 1070 987 A

Sr-90 pCi/L 678 655 A

H-3 pCi/L 27600 28800 A

12/11/2008 Water 1-131 pCi/L 63.7 64.1 A

Ce-141 pCi/L 224 224 A

Cr-51 pCi/L 278 288 A

Cs-134 pCi/L 159 157 A

Cs-137 pCi/L 148 140 A

Co-58.

pCi/L 126 122 A

Mn-54 pCi/L 192 178 A

Fe-59 pCi/L 128 117 A

Zn-65 pCi/L 238 214 A

Co-60 pCi/L 168 156 A

12/11/2008 Milk 1-131 pCi/L 76.6 79.9 A

Ce-141 pCi/L 179 191 A

Cr-51 pCi/L 248 246 A

Cs-134 pCi/L 128 134 A

Cs-137 pCi/L 123 120 A

Co-58 pCi/L 101 104 A

Mn-54 pCi/L 151 152 A

Fe-59 pCi/L 103 100 A

Zn-65 pCi/L 193 183 A

Co-60 pCi/L 139 133 A

Sr-89 pCi/L 85.5 91.9 A

Sr-90 pCi/L 10.9 12.6 A

12/11/2008 Cartridge 1-131 pCi 56.5 53.2 A

(a) GEL reported result.

(b) Reference value.

(c) Evaluation: A= Acceptable. U= Unacceptable.

71

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