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Independent Spent Fuel Storage Installation - Transmittal of Annual Radiological Environmental Operating Report for the Period of January 1, 2007 Through December 31, 2007
	ML081210090
Person / Time
Site:	Surry, 07200002, 07200055
Issue date:	04/18/2008
From:	Adams W; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	08-0121, SS&L/TJN R0
	Download: ML081210090 (74)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 18, 2008 Attention: Document Control Desk Serial No. 08-0121 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.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, 2007 through December 31, 2007 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, W. Matt Adams Director Station Safety and Licensing Surry Power Station Attachment Commitments made in this letter: None

Serial No. 08-0121 Docket Nos.: 50-280 50-281 72-2 72-55 copy: US Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 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 Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23218

Serial No. 08-0121 Docket Nos.: 50-280 50-281 72-2 72-55 ATTACHMENT 1 2007 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

- r 71W0 2007 Annual Radiologica I Environmental Operating Report

Dominion

I I

I I Dominion I Surry Power Station*

Radiological Environmental Monitoring Program

l January 1, 2007 to December 31, 2007 I

I I

I

Annual Radiological Environmental Operating Report Surry Power Station January 1, 2007 to December 31, 2007 Prepared by: 1/1/4 P. F. Blount Health Physicist Reviewed by:

P. R. Harris Supervisor Radiological Analysis Reviewed by: Q.K*"& J. A. Keithley Supervisor Health yics Techrnical Services Approved by:

..ý ones Manager Radiological Protection I.2

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

1. EX ECU TIVE SUM MA RY ......... ;............................................... ...................................... .......

5

2. PROGRAM D ESCRIPTION ................................................................................................. 7 2.1 Introduction .................... ................................... 7 2.2 Sam pling and Analysis Program ............

......................................................... 8

3. AN A LYTICAL RESU LTS ..................................................... ................................................ 20 3.1 Sum mary of Results ............................................ ...................................... .. .... 20 3.2 Analytical Results of 2007 REM P Sam ples .......................................... ......................... 27

4. DISCU SSION OF RESU LTS ...................................... ......................................................... 48 4.1 G am m a Exposure Rate .................................................................................................. 48 4.2 Airborne Gross Beta ................................................ 49 4.3 Airborne Radioiodine .................................................................................................... 51 4.4 A ir 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 .................................................... o....................................................... : .............. 52 4 .9 S ilt ............ .................................................... ............................................................... ........... 5 2 4.10 Shoreline Sedim ent ......................................................................................................... 54 4 .1 1 F ish ....................................................................................................................................... 54 4.12 Oysters ........................................................................................................................... 54 4.13 Clam s .............................................................. .................................................................... 55 4.14 Crabs ................................................................................................. ........................ 5555........

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

I 56

6. CON CLU SION S ...................................................................... ............................................... 57 REFEREN CES ............................................................................................................ 59 APPEN DICES ...................................................................... .............................................. ....... 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.

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1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2007 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2007, 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, are collected from areas that are 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.

The AREVA NP Environmental Laboratory 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 5

level for 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 2007 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 2007 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was again detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. ýNo 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 2007, 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 2007 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.

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2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2007 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', 1,973.

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.. The AREVA NP Environmental Laboratory 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).

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These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As is Reasonably Achievable."

This report documents the results of the REMP for 2007 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 andAnalysis Program Table 2-1 summarizes the 2007 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 AREVA NP Environmental Laboratory and Global Dosimetry Solutions for Surry Power Station. All samples, with the exception of the TLDs, are shipped to AREVA NP Environmental Laboratory, located in Westborough, MA, 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.

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Table 2-1 SURRY - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental Control (00) Quarterly Onsite (Stored in lead container outside protrcted area)

TLDs West North West (02) 0.2 WNW 2930 Quarterly Site Boundary Surry Station Discharge (03) 0.4 NW 3210 Quarterly Site Boundary North North West (04) 0.2- NNW 3290 Quarterly Site Boundary North (05) 0.3 N 40 Quarterly Site Boundary North North East (06) 0.3 NNE 280 Quarterly Site Boundary North East (07) 0.3 NE 440 Quarterly Site Boundary East North East (08) 0.4 ENE 670 Quarterly Site Boundary East (09) 0.3 E 890 Quarterly Site Boundary West (10) 0.1 W 2710 Quarterly Site Boundary West South West (11) 0.4 WSW 2520 Quarterly Site Boundary -. -

South West (12) 0.3 SW 2280 Quarterly Site Boundary South South West (13) 0.3 SSW 2010 Quarterly Site Boundary South (14) 0.4 S 1820 Quarterly Site Boundary South South East (15) 0.6 SSE 1570 Quarterly Site Boundary South East (16) 0.9 SE 1350 Quarterly Site Boundary Station Intake (18) 1.6 ESE 1150 Quarterly Site Boundary Hog Island Reserve (19) 2.0 NNE 260 Quarterly Near Resident Bacon's Castle (20) 4.5 SSW 2020 Quarterly Apx. 5 mile Route 633 (21) 4.9 SW 2270 Quarterly Apx. 5 mile Alliance (22) 5.1 WSW 2470 Quarterly Apx. 5 mile Surry (23) 7.7 WSW 2560 Quarterly Population Center Route 636 and 637 (24) 4.0 W 2700 Quarterly Apx. 5 mile Scotland Wharf (25) 5.0 WNW 2840 Quarterly Apx. 5 mile Jamestown (26) 6.3 NW 3080 Quarterly Apx. 5 mile Colonial Parkway (27) 3.8 NNW 3330 Quarterly Apx. 5 mile Route 617 and 618 (28) 4.9 NNW 3400 Quarterly Apx. 5 mile Kingsmill (29) 4.6 N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.8 N 00 Quarterly Population Center Kingsmill North (31) 5.5 NNE 120 Quarterly Apx. 5 mile Budweiser (32) 5.8 NNE 270 Quarterly Population Center Water Plant (33) 5.0 NE 460 Quarterly Apx. 5 mile 9

M -- - M --

M---- M M N M M Table 2-1 SURRY - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental 'BASF (34) 5.1 ENE 700 Quarterly Apx. 5 mile TLDs Lee Hall (35) 7.1 ENE 750 Quarterly Population Center Goose Island (36) 5.1. E 900 Quarterly Apx. 5 mile Fort Eustis (37) 4.9 ESE 1.040 Quarterly Apx. 5 mile Newport News (38) 19.3 SE 1300 Quarterly Population Center James River Bridge (39) 17.1 SE 1420 Quarterly Control Location Benn's Church (40) 17.0 SSE 1590 Quarterly Control Location Smithfield (41) 13.4 SSE 1670 Quarterly Control Location Rushmere (42) 5.3 SSE 1560 Quarterly Apx. 5 mile Route 628 (43) 5.1 S 1770 Quarterly Apx. 5 mile Air Charcoal Surry Station (SS) 0.3 NNE 180 Weekly Site Boundary (Highest D/Q) and Particulate Hog Island Reserve (HIR) 2.0 NNE 260 Weekly Bacon's Castle (BC) 4.5 SSW 2020 Weekly Alliance (ALL) 5.1 WSW 2470 Weekly Colonial Parkway (CP) 3.8 NNW 3330 Weekly BASF (BASF) -5.1 ENE 700 Weekly Fort Eustis (FE) 4.9 ESE 1040 Weekly Newport News (NN) 19.3 SE 1300 Weekly Control Location River Water Surry Station Discharge (SD) 0.4 NW 3230 Monthly Scotland Wharf (SW) 4.9 WNW 2840 Monthly Control Location Well Water Surry Station (SS) 0.1 SW 2270 Quarterly Onsite Training Center (TC) 0.2 NNE 190 Quarterly Onsite Hog Island Reserve (HIR). 2.0 NNE 280 Quarterly Shoreline Hog Island Reserve (HIR) 0.6 N 70, Semi-Annually Sediment Chickahominy River (CHIC) 11.2 WNW 3010 Semi-Annually Control Location Silt Chickahominy River (CHIC) 11.2 WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 341' Semi-Annually 10

Table 2-1 SURRY - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location- Station Miles Direction Degrees Frequency Remarks Milk Colonial Parkway (CP) 3.7 NNW 3360 Monthly Williams (WMS) 27.5 S

1.750 Monthly Control Location Epp's (EPPS) 4.8 SSW 2000 Monthly Oysters Point of Shoals (POS) 6.4 SSE 1570 Semi-Annually Mulberry Point (MP) 4.9 ESE 1240 Semi-Annually Clams Chickahominy River (CHIC) 11.2 WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually Hog Island Point (HIP) 2.4. NE 520 Semi-Annually Lawne's Creek (LC) 2.4 SE 1310 Semi-Annually Fish Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually Crabs Surry Station Discharge (SD) 1.3 NNW 3410 Annually Food Products Brock's Farm (BROCK) 3.8 S 1830 Annually (Corn, Peanuts, Slade's Farm (SLADE) 3.2 S 1790 Annually Soybeans).

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Table 2-2 (Page 1 of3)

SURRY - 2007 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2 mR/Std. Month Dosimetry (TLD) 3 Air Iodine Weekly 1-131 0.07 pCi/mr 3

Air Particulate Weekly Gross Beta 0.01 pCi/m Quarterly (a) Gamma Isotopic pCi/m3 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 pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium (H-3) 2000 pCi/L 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.

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Table 2-2(Cont.)

(Page 2 of 3)

SURRY - 2007 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg - dry Cs-134 .150 Cs-137 180 Silt Semi-Annual Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Milk Monthly 1-131 1 pCi/L Gamma Isotopic pCi/L Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Oysters Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Clams Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 1.30 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Crabs Annually Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 '130 Cs-137 150 Footnotes located at end of table.

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TABLE 2-2 (Cont.)

(Page 3 of 3)

SURRY - 2007 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Fish Semi-Annual Gamma Isotopic pCi/kg - wet Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Crops Annually Gamma Isotopic pCi/kg - wet 1-131 60 Cs-134 60 Cs-137 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, are also identified and reported.

LLDs is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental 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.

14

- m-m-m n-m -n-n-n - n-m-mmm - -

IC)

Li I~.

15 Fiue1 Sur Radioogica

~10)cn0r

n= m-

= = = = = m m

= n m m = = n = m

=-m= M-mmm--=- =-- = = - m Figure 3. Surry Emergency Plan Map Air Sampling Stations 0 Nearest Residents

TLD Sampling 0 Nearest Milk Animal 0

CD Nearest Garden Aquatic Samples zT 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.

m=m-= =---- =--- =- =- = M m _ _

IA f~~~CORNER (61j~

(6

,.m ,.-,.

im i 1ýi, I %EXTON (3

I I l [

Figure 4. Surry Emergency Plan Map Air Sampling Stations 0 Nearest Residents 10

TLD Sampling 0 Nearest Milk Animal

Nearest Garden Crop Samples 0

U=n= M M =-----=---- = - M Figure 5. Surry Emergency Plan Map Air Sampling Stations Nearest Residents

TLD Sampling Nearest Milk Animal

Nearest Garden Aquatic Samples Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA22312. 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.

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TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2007 Docket No. 50-280-281 Page I.of6 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 Direct Gamma 164 2 3.2 (152/152) STA-9 0.3 mi 5.8 (4/4) 3.7 (12/12) 0 Radiation (1.3-6.9) E (4.6 - 69) (1.7- 6.6)

TLD (mR/

Std Month)

Air Gross 424 .10 23.1 (371/371) FE 4.9 mi 24.7 (53/53) 24.2 (53/53) 0 Particulate Beta (0 -48.8) ESE (15.4- 35.6) (11.0 - 39.4)

(1E-3 pCi/m3) --------

Gamma 32 Be-7 32 136 (27/28) NN 19.3 mi 164 (4/4) 164 (4/4) 0 (108- 176) SE (140-202) (140-202)

Cs7134 32 50 < LLD N/A < LLD < LLD 0 Cs-137 32 60 < LLD N/A < LLD < LLD 0 Air Iodine 1-131 424 70. < LLD N/A < LLD <LLD 0 (IE-3 pCi/m3)

Milk Strontium 4

.(pCimLter)

Sr-89 4 < LLD N/A < LLD N/A 0 Sr-90 4 1.9 (1/4). CP 3.7 mi 1.9(1/4) N/A 0 (1.9 -1.9) NNW (1.9-1.9)

Gamma 36 K-40 36 1431 (24/24) CP . 3.7 mi 1463 (12/12) 1288(12/12) 0 (1280 - 1570) NNW (1340-1570) (1210-1400) 1-131 36 1 " LLD N/,A < LLD < LLD 0 Cs-134 36 15 < LLD N/A < LLD " LLD 0 Cs-137 36 18 < LLD N/A " LLD. < LLD 0 Ba-140 36 60 < LLD N/A " LLD < LLD 0 La-140 36 . 15 < LLD N/A < LLD < LLD 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.

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TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2007 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 7723 (3/3) Slade 3.2 mi 15280 (1/1) N/A 0 (2540 - 15280) S (15280-15280) 1-131 3 60 < LLD N/A < LLD N/A .0 Cs-1 34 3 60 <-LLD N/A < LLD N/A 0 Cs-1 37 3 80 < LLD N/A < LLD N/A 0 Well H-3 12 2000 < LLD N/A < LLD N/A 0 Water (pCi/Liter)

Gamma 12 Mn-54 12 15 < LLD N/A <LLD N/A Co-58 12 15 < LLD N/A < LLD, N/A Fe-59 12 30 < LLD N/A < LLD N/A Co-60 12 15 < LLD N/A < LLD N/A Zn-65 12 30 < LLD N/A " LLD NIA Nb-95 12 15 < LLD N/A < LLD N/A Zr-95 12 30 < LLD N/A <LLD N/A 1-131 12 1 < LLD N/A < LLD N/A Cs-134 12 .15 < LLD N/A < LLD N/A Cs-137 12 18 < LLD N/A < 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.

22

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2007 Docket No. 50-280-281 Page 3 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 Well Ba-140 12 60 < LLD N/A < LLD N/A 0 Water (pCi/Liter) La-140 12 15 < LLD N/A < LLD N/A 0 River H-3 8 2000 < LLD N/A < LLD N/A 0 Water (pCi/Liter)

Gamma 24 K-40 24 130 (4/12) SD 0.4 mi 130 (4/12) 113 (1/12) 0 (98-176) NW (98-176) (113-113)

Mn-54 24 15 < LLD N/A < LLD < LLD 0 Co-58 24 15 < LLD N/A < LLD < LLD 0 Fe-59 24 30 < LLD N/A < LLD < LLD 0 Co-60 24 15 < LLD N/A < LLD < LLD 0 Zn-65 24 30 < LLD N/A < LLD < LLD 0 Nb-95 24 15 < LLD N/A < LLD < LLD 0 Zr-95 24 30. < LLD N/A < LLD <LLD 0 1-131 24 10 < LLD N/A < LLD < LLD 0 Cs-134 24 15 < LLD N/A < LLD < LLD 0 Cs-137 24 18 < LLD N/A < LLD < LLD 0 Ba-140 24 60 < LLD N/A < LLD < LLD 0 La-140 24 15 < LLD N/A < LLD < LLD 0

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 - 2007 Docket No. 50-280-281 Page 4 of 6 Medium or Indicator Control Pathway Anal sis 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/kgdry)

K-40 4 17800 (2/2) SD 1.3 mi 17800 (2/2) .17780 (2/2) 0 (17800-17800) NNW (17800-17800) (17560-18000)

Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 252 (2/2) SD 1.3 mi 252 (2/2) .226(2/2) 0 (238 - 266) NNW (238 -266) (196-256)

Th-228 4 1175 (2/2) CHIC 11.2 mi 1375 (2/2) 1375(2/2) 0 (1090 - 1260) WNW (1360 - 1390) (1360 - 1390)

Shoreline Gamma 4 Sediment (pCi/kg dry) K-40 4 4945(2/2) HIR 0.6 mi 4945 (2/2) , 1670 (2/2) 0 (4500 - 5390) N (4500 - 5390) (1330 - 2010).

Cs-1 34 4 150 < LLD N/A < LLD < LLD 0 Cs-137. 4 180 < LLD N/A < LLD < LLD 0 Th-228 4 1731 (1/2) HIR 0.6 mi 1731 (1/2) 1430 (1/2) 0 (1731 - 1731) N (1731 - 1731) (1430 - 1430)

Fish Gamma . 4 (pCi/kg wet)

K-40 4 1898 (4/4) SD 1.3 mi 1898(4/4) N/A 0 (1700 - 2240) NNW (1700 - 2240)

Mn-54 4 130 < LLD N/A < LLD N/A 0 Co-58 4 130 < LLD N/A < LLD N/A 0 Fe-59 4 260 < 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

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 Po*ver Station, Surry County, Virginia - 2007 Docket No. 50-280-281 Page 5 of 6 Medium or Indicator Control Pathway Anal ysis 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 Fish Cs-134 4 130 < LLD N/A < LLD N/A 0 (pCi/kgwet)

Cs-i37 4 150 < LLD N/A <LLD N/A 0 Oysters Gamma 4 (pCi/kg wet)

K-40 4 750 (2/4) POS 6.4 mi 850 (1/2) N/A 0 (650 - 750) SSE (850 - 850)

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 Clams Gamma 8 (pCi/kg wet)

Mn-54 8 130 < LLD N/A < LLD < LLD 0 Co-58 8 130 < LLD N/A < LLD < LLD 0 Fe-59 8 260 <LLD N/A < LLD < LLD 0 Co-60 8 130 < LLD N/A < LLD < LLD 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 - 2007 Docket No. 50-280-281 Page 6 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 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 Gamma 1 (pCi/kg wet)

K-40 1 2150(1/1) SD 1.3 mi 2150(1/1) N/A 0 (2150 - 2150) NNW (2150 - 2150)

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

26

3.2 Analytical Results of 200 7 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 (2a) 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 2cy error (i.e., the measured value exceeds 3(y).

AREVA NP Environmental Laboratory 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 1-13 1

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 Nuclear Power Station, Surry County, Virginia - 2007 mRIStd Month +/- 2 Sigma Page]I of I STATION FIRST SECOND THIRD FOURTH AVERAGE NUMBER QUARTER QUARTER QUARTER' QUARTER +/-2SIGMA 02 5.4 +/-0.6 3.7 +/-0.5 3.1 +/-1.0 5.0 +/-0.5 4.3 +/-1.1 03 4.9 +/-1.5 3.4 +/-0.4 . 3.7 +/-1.2 4.7 +/-1.1 4.2 +/-0.7 04 3.2 +/- 0.3 3.1 +/- 0.4 2.7 +/- 1.2 3.9 +/- 0.4 3.2 +/- 0.5 05 4.4 +/-0.5 3.3 +/-1.3 2.4 +/-0.5 4.2 +/-0.3 3.6 +/-0.9 06 4.8 +/- 0.4 4.3 +/- 0.6 4.0 +/- 1.5 4.8 +/- 0.2 4.5 +/- 0.4 07 4.4'+/- 0.6 3.9 +/- 1.4 3.8 +/- 0.4 4.4 +/- 0.3 4.1 +/- 0.3 08 3.8 +/- 1.2 4.1 +/- 0.5 3.0 +/- 1.4 3.3 +/- 0.3 3.6 +/- 0.5 09 6.9 +/-0.3 5.6 +/-1.7 4.6 +/-1.7 6.2 +/-0.9 5.8 +/-1.0 10 4.0 +/-0.9 3.1 +/-0.4 3.4 +/-1.4 4.4 +/-0.9 3.7 +/-0.6 11 3.3 +/- 0.4 2.6 +/- 0.4 2.2 +/- 0.9 3.3 +/-10.3 2.9 +/- 0.5 12 3..8 +/- 0.3 2.8 +/- 0.4 3.4 +/- 0.4 3.7 +/- 0.4 3.4 +/- 0.5 13 4.7 +/- 0.3 2.8 +/- 0.3 3.3 +/- 0.9 3.7 +/- 1.0 3.6 +/- 0.8 14 4.4 +/- 0.7 3.9 +/- 0.2 3.2 +/- 0.9 4.2 +/- 0.3 3.9 +/- 0.5 15 5.3 +/- 0.6 3.9 +/- 1.2 4.1 +/- 1.4 4.4 +/- 1.2 4.4 +/- 0.6 16 4.3 +/-0.6 2.9 +/-0.5 3.5 +/-0.9 4.0 +/-0.2 3.7 +/-0.6 18 2.1 +/-0.4 2.7 +/-0.4 2.2 +/-0.7 1t9 +/-0.2 2.2 +/-0.3 19 2.8 +/- 1.4 2.3 +/- 0.8 1.7- +/- 0.4 2.5 +/- 1.0 2.3 +/- 0.5 20 3.0 +/- 0.3 2.1 +/- 1.2 1.4 +/- 0.5 2.4,+/- 0.9 2.2 +/- 0.7 21 2.5 +/- 0.3 2.7 +/- 0.6 1.7 +/- 0.7 3.5 +/- 0.2 2.6 +/- 0.7 22 1.8 +/- 0.3 1.4 +/- 0.3 1.5 +/- 1.1 1.7 +/- 0.8 1.6 +/- 0.2 23 4.0 +/- 1.7 2.8 +/- 0.6 3.0 +/- 1.3 3.9 +/- 0.5 3.4 +/- 0.6 24 .3.2 +/-0.4 2.1 +/-0.3 2.4 +/-1.2 3.1 +/-0.2 2.7 +/-0.5 25 3.3 +/- 1.0 2.3 +/-0.5 2.5 +/-0.6 3.1 +/- 0.2 2.8 +/-0.5 26 4.0 +/-0.4 3.4 +/-0.7 2.8 +/-0.3 4.3 +/-0.3 3.6 +/-0.7 27 . 2.5 +/-0.4 2.0 +/-0.3 2.1 +/-1.0 2.6 +/-0.5 2.3 +/-0.3 28 2.7 +/- 1.3 1.6 +/-0.6 2.1 +/- 1.6' 2.9 +/-0.6 2.3 +/-0.6

.29 2.2 +/- 1.3 1.6 +/- 0.3 .1.3 +/- 0.4 2.1 +/- 0.9 .1.8 +/- 0.4 30 .2.2 +/- 0.2 2.0 +/- 0.6. 2.1 +/- 1.3. *2.4 +/- 1.0 2.2 +/- 0.2 31 1.4 +/-0.3 1.3 +/-0.3 1.+/-0.4 1.8 +/-0.8 1.15 +/-0.2 32 3.1. +/- 0.5 2.1 +/- 0.6 2.0 +/- 0.8 2.3 +/- 0.2 2.4 +/- 0.5 33 . 3.6 +/-0.6 2.3 +/-0.3 2.0 +/-1.1 2.9 +/-1.0 2.7 +/-0.7 34 2.7 +/-0.2 2.0 +/-0.4 .1.8 +/-0.4 3.0 +/-1.4 2.4 +/-0.6 35 4.1 +/- 1.2 3.0 +/-0.3 3.0 +/-0.7 4.3 +/-0.5 3.6 +/-0.7 36 4.4 +/- 1.4 3.5 +/- 0.8 3.8 +/- 0.8 4.3 +/- 0.7 4.0 +/- 0.4 37 2.6 +/-0.3 1.9 +/-0.4 1.7 +/-0.4 2.4 +/-0.4 2.2 +/-0.4 38 5.5'+/- 0.3 5.2 +/- 0.6 5.0 +/- 0.3 5.8 +/- 0.5 5.4 +/- 0.4 39 2.5 +/- 0.3 1.7 +/- 0.2 2.0 +/- 0.9 2.9 +/- 0.2 2.3 +/- 0.5 40 3.7 +/- 1.2 2.4 +/- 0.7 3.2 +/- 0.5 3.2 +/- 1.0 3.1 +/- 0.5 41 6.6 +/- 0. 5.3 +/- 0.9 5.1 +/- 0.5 5.6 +/- 1.2 5.7 +/- 0.7 42, 3.8 +/-0.6 2.4 +/-0.3 3.1 +/-0.6 3.5 +/-0.4 3.2 +/-0.6 43 . '3.0 +/-1.2 2.0 +/- 0.2 .2.2 +/- 1.6 2.4 +/- 0.6 2.4 +/- 0.4 28

TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2007 1.OE-3 pCi/m3 - 2 Sigma Page 1 of 2 I COLLECTION S SAMPLING LOCATIONS I I DATE SS HIR BC ALL CP BASF FE NN-C "

January 02 25.4 +/- 4.7 19.9 +/- 4.4 27.9 +/- 4.9 24.1 + 4.7 20.3 +/- 4.4 20.2 + 4.4 23.4 +/- 4.5 18.8 +/- 4.3

+

January 9 20.0 +/- 4.4 12.4 +/- 4.0 23.6 +/- 4.6 13.4 + 4.1 14.0 +/- 4.0 10.6 3.8 16.4 +/- 4.1 11.9 +/- 3.9

+

January 16 18.1 +/- 2.5 16.9 +/- 2.5 0.0 +/- 4.8 17.9 + 2.5 16.6 +/- 2.4 16.2 2.4 16.3 +/- 2.5 15.4 +/- 2.4 January 23 12.4 +/- 4.2 +

15.5 +/- 4.3 20.6 +/- 4.6 18.2 + 4.5 16.9 +/- 4.3 13.9 4.2 19.8 +/- 4.6 15.9 +/- 4.3 January 30 19.5 +/- +

4.5 18.4 +/- 4.4 26.5 +/- 4.9 24.5 + 4.8 27.4 +/- 4.9 23.7 4.8 26.8 +/- 4.9 24.5 +/- 4.9 February 06 26.6 +/- 4.9 24.5 +/- 4.8 29.6 +/- 5.1 33.3 + 5.2 28.5 +/- 5.0 25.8 + 4.9 35.0 +/- 5.4 32.6 +/- 5.3 February 13 21.5 +/- 4.7 23.7 +/- 4.7 21.3 +/- 4.6. 24.1 + 4.7 24.9 +/- 4.8 28.1 + 4.9 26.8 +/- 4.9 26.4 +/- 4.8 February 20 22.9 +/- 5.1 21.3 +/- 5.0 25.3 +/- 5.2 28.0 + 5.3 26.3 +/- 5.2 22.6 + 5.1 29.2 +/- 5.8 27.2 +/- 5.4 February 27 13.5 +/- 4.2 14.5 +/- 4.2 17.2 +/- 4.4 17.5 + 4.4 14.0 +/- 4.2 14.4 + 4.3 19.3 +/- 4.6 20.6 +/- 4.6 March 06 15.0 +/- 4.3 12.7 +/- 4.1 13.1 +/- 4.2 20.1 + 4.5 18.9 +/- 4.5 19.4 + 4.5 20.6 +/- 4.6 19.3 + 4.5 March 13 25.9 +/- 4.7 21.4 +/- 4.4 22.9 +/- 4.5 25.8 + 4.6 24.0 +/- 4.5 21.2 + 4.4 29.1 +/- 4.8 29.7 + 4.8 March 20 22.8 +/- 4.9 16.5 +/- 4.3 22.3 +/- 4.9 21.3 + 4.6 18.2 +/- 4.5 18.3 + 4.7 24.7 +/- 4.8 19.0 + 4.5 March 27 23.1 +/- 5.3 16.9 +/- 4.9 25.1 +/- 5.3 20.6 + 5.0 25.5 +/- 5.3 21.4 + 5.2 24.7 +/- 5.3 20.7 + 5.1 Qtr. Avg. +/- 2 s.d. 20.5 +/- 9.3 18.0 +/- 7.8 21.2 +/- 15.5 22.2 +/- 10.4 21.2 +/- 10.3 19.7 +/- 9.9 24.0 +/- 10.9 21.7 +/- 12.1 April. 02 15.4 +/- 4.9 18.0 +/- 5.0 17.3 +/- 5.0 21.7 + 5.2 20.5 +/- 5.1 18.8 +/- 5.3 18.9 +/- 5.1 23.0 + 5.2 April 10 17.1 +/- 4.0 18.9 +/- 4.0 24.7 +/- 4.4 18.8 + 4.0 18.6 +/- 3.9 19.6 +/- 4.1 22.5 +/- 4.2 18.2 + 3.9 April 17 16.1 +/- 4.8 13.0 +/- 4.6 17.8 +/- 4.8 15.9 + 4.6 19.9 +/- 4.8 15.8 +/- 4.7 18.0 +/- 4.8 16.9 + 4.7 April 24 12.4 +/- 4.5 15.3 +/- 4.6 15.0 +/- 4.7 16.9 + 4.7 18.7 +/- 4.8 15.1 +/- 4.7 19.5 +/- 5.0 13.2 + 4.5 May01 16.4 +/- 4.4 21.4 +/- 4.6 18.5 +/- 4.4 22.3 + 4.5 22.3 +/- 4.5 14.8 +/- 4.2 19.4 +/- 4.5 23.1 + 4.6 May 08 17.4 +/- 4.4 15.9 +/- 4.4 16.1 +/- 4.6 18.2 + 4.6 17.1 +/- 4.5 18.4 +/- 4.7 17.0 +/- 4.6 17.6 + 4.6 May 15 9.2 +/- 4.0 13.5 +/- 4.2 12.5 +/- 4.1 13.5 + 4.1 9.7 +/- 3.9 10.6 + 4.0 15.5 +/- 4.3 11.0 + 4.0 May 22 16.1 +/- 4.3 21.9 +/- 4.5 20.6 +/- 4.5 20.1 + 4.4 20.4 +/- 4.4 16.8 + 4.3 21.2 +/- 4.6 20.8 + 4.5 May 29 21.9 + 4.7 25.5 +/- 4.8 23.2 +/- 4.7 22.8 + 4.7 21.5 +/- 4.6 22.6 + 4.7 27.7 +/- 5.0 24.9 + 4.8 June 05 13.6 + 4.2 21.1 +/- 4.6 18.5 +/- 4.5 .17.5 + 4.4 18.1 +/- 4.4 14.7 + 4.3 15.8 +/- 4.3 22.7 + 4.6 June 12 17.7 + 4.5 18.7 +/- 4.5 20.4 +/- 4.7 20.4 + 4.6 21.0 +/- 4.6 20.2 + 4.6 22.3 +/- 4.8 19.5 + 4.6 June 19 20.3 + 4.7 17.0 +/- 4.5 18.9 +/- 4.7 22.5 + 4.8 17.1 +/- 4.5 16.7 + 4.6 21.5 +/- 4.9 21.6 + 4.8 June 25 16.8 + 4.8 23.3 +/- 5.1 22.6 +/- 5.1 23.3 + 5.1 26.4 +/- 5.2 20.8 +5.1 19.7 +/- 5.0 21.9 + 5.1 Qtr. Avg. +/- 2 s.d. 16.2 +/- 6.5 18.7 +/- 7.6 18.9 +/- 6.8 19.5 +/- 6.1 19.3 +/- 7.6 17.3 +/- 6.4 19.9 +/- 6.5 19.6 +/- 8.2 29

TABLE 3-3: GROSS BETA CONCENTRATION IN FIL TERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2007 1.OE-3 pCi/m3 =2 Sigma Page 2 of 2 COLLECTION S SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN July 03 18.7 + 2.4 21.2 +/- 2.5 20.0 +/- 2.4 23.9 +/- 2.5 48.8 +/- 5.8 19.1 +/- 2.4 20.6 +/- 2.4 20.3 +/- 2.4 July 10 21.3 +/-- 4.6 25.0 +/- 4.8 22.4 +/- 4.7 24.9 +/- 4.8 22.0 +/- 4.6 26.8 +/- 4.9 27.5 +/- 5.0 26.33 4.8 July 17. 19.6 + 4.4 24.3 +/- 4.7 22.6 +/- 4.7 28.1 +/- 4.9 21.1 +/- 4.5 21.6 +*4.7 27.9 +/- 5.0 24.4 +/- 4.8 July 24 13.4 + 4.1 17.6 +/- 4.2 15.8 +/- 4.1 20.7 +/- 4.3 20.2 +/- 4.4 16.0 +/- 4.2 21.2 +/- 4.6 16.8 +/- 4.3 July 31 17.2 + 4.4 15.8 +/- 4.3 21.1 +/- 4.8 19.3 +/- 4.6 18.2 +/- 4.5 19.5 +/- 4.6 21.9 +/- 4.8 14.6 + 4.2 August 07 34.1 + 5.2 33.5 +/- 5.1 32.4 + 5.1 36.5 38:5 +/- 5.3 + 5.0

+ 5.2 29.5 35.4 +/- 5.2 32.1 + 5.1 August 14 25.3 + 4.9 29.1 +/- 5.1 29.4 + 5.1 32.0 + 5.2 28.8 +/--5.0 28.2 + 5.1 25.1 +/- 4.8 28.2 +/- 5.0 August 21 22.9 - 4.8 26.1* +/- 4.9 24.5 -+4.8 25.6 + 4.8 29.0 +/- 5.0 23.4 + 4.8 28.0 +/- 4.9 31.9 +/- 5.2 August28 16.2 + 4.7 15.9 +/- 4.6 16.9 + 4.7 15.9 + 4.6 18.3-+/- 4.6 15.0 + 4.6 18.2 +/- 4.7 19.1 +/- 4.7 September 04 24.5 + 4.9 31.7 +/- 5.2 33.1"+ 5.3 25.3 + 4.9 28.8 +/- 5.0 25.7 + 5.0 28.8 +/- 5.0 33.8 +/- 5.3 September 11 26.2 + 4.8 29.0 +/- 4.9 31.0 + 5.1 30.3 + 5.0 26.3 +/- 4.7 26.7 _ 4.9 30.4 +/- 5:0 31.7 +/- 5.0 September 18 19.9 + 4.8 23.7 +/- 4.9 25.7 + 5.1 25.2 + 4.9 26.3 +/- 5.0 18.8 +/- 4.8 26.4 +/- 5.0 26.0 +/- 5.0 September 25 19.2 + 4.6 17.5 +/- 4.5 19.7 + 4.6 21.2 + 4.7 18.8 +/- 4.5 19.6 +/- 4.7 21.0 +/- 4.7 22.0 + 4.8 Qtr. Avg. +/- 2 s.d. 21.4 +/- 10.6 23.9 +/- 12.0 24.2 +/- 11.5 25.3 +/- 11.1 26.5 +/- 17.7 22.3 +/- 9.5 25.6 +/- 9.6 25.2-+/- 12.6 October 02 24.7 +/- 4.9 24.6 +/- 4.9 29.5 +/- 5.2 29.9 + 5.1 23.2 +/- 4.7 21.9 +/- 4.8 23.9 +/- 4.8 25.3 +/- 4.9 October 09 11.8 +/- 4.2 18.6 +/- 4.6 19.6 +/- 4.6 14.4 + 4.3 17.7 +/- 4.5 12.6 +/- 4.3 16.4 +/- 4.4 19.6 +/- 4.6 October 16 24.3 +/- 5.2 27.7 +/- 5.3 30.6 +/- 5.6 29.6 + 5.5 34.3 +/- 5.6 28.4 +/- 5.5 32.2 +/- 5.5 29.9 +/- 5.5 October 23 324 +/- 5.3 37.3 +/- 5.4 37.9 + 5.5 33.3 + 5.2 34.6 5.3 37.0 +/- 5.5 35.3 +/- 5.3 39.4 +/- 5.5 October 30 15.1 +/- 4.2 13.7 +/- 4.1 16.8 +/- 4.3 15.4 + 4.2 14.4 _ 4.1 14.9 +/- 4.2 15.4.+/- 4.2 19.6 +/- 4.4 November 06 29.7 +/- 5.7 28.2 +/- 5.4 27:9 +/- 5.4 23.7 + 5.2 22.4 +/- 5.1 24.4 +/- 5.3 29.1 +/- 5.4 29.4 +/- 5.4 November 13 30.3 +/- 5.4 27.1 +/- 5.2 32.8 +/- 5.5 22.3 + 4.9 26.9 +/- 5.1 24.0 +/- 5.1 31.4 +/- 5.3 29.7 +/- 5.3 November 20 34.4 +/- 5.6 40.2 +/-+ 5.8 39.2 +/- 5.8 33.2 + 5.4 30.9 +/- 5.3 27.3 +/- 5.3 30.6 +/- 5.4 33.1 +/- 5.5 November 27 26.6 +/- 5.3 25.7 +/- 5.3 28.2 +/- 5.4 29.0 +' 5.3 21.7 +/- 5.0 22.6 +/- 5.2 29.7 +/- 5.4 28.8 +/- 5.3 December 04 33.9 +/- 5.4 28.0 +/- 5.1 31.0 +/- 5.3 28.5 + 5.0 33.5 +/- 5.3 29.0 - 5.1 34.3 +/- 5.3 37.8 +/- 5.5 December 11 36.4 +/- 5:7 36.3 +/- 5.6 38.3 +/- 5.8 32.7 + 5.4 33.0 +/- 5.4 30.0 +/- 5.5 33.1 +/- 5.5 35.5 +/- 5.6 December 18 30.3 +/- 5.4 26.4 +/- 5.2 26.0 +/- 5.2 25.9 + 5.1 28.5 +/- 5.2 25.2 +/- 5.2 28.4 +/- 5.2 29.4 +/- 5.4 December 24 35.4 +/- 6.4 38.2 +/- 6.3 40.0 +/- 6.5 30.5 + 6.0 32.1 +/- 6.1 31.5 +/- 6.1 35.6 +/- 6.2 33.1 +/- 6.1 December 31 39.5 +/- 5.9 33.5 +/- .5.6 39.7 +/- 5.9 26.9 + 5.3 36.0 +/- .5.7 28.1 _ 5.4 31.1 +/- 5.5 29.0,+/- 5.4 Qtr. Avg. 2 s.d. 28.9 +/- 15.8 29.0 +/- 15.1 31.3 +/- 14.7 26.8 +/- 12.0 27.8 +/- 13.7. 25.5 +/- 12.7 29.0 +/- 12.7 30.0 +/- 11.6 Ann. Avg. +/- 2 s.d. 21.9 +/- 14.3 22.5 +/- 14.1 24.0 +/- 15.5 23.5 +/- 11.4 .23.8 +/- 14.5 21.3 +/- 11.5 - 24.7 +/- 12.0 24.2 +/- 13.6 30

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2007 1.OE-3 pCi/m3 + 2 Sigma Page 1 of 2 COLLECTION SAMPLING LOCATIONS DATESS HIR BC ALL CP BASF FE NN-C January 02 <30 <30 <40 <29 <28 <28 <32 <31 January 9 <20 <24 <21 <20 <20 <26 <18 <27 January 16 <32 <28 <40 <33 <26 <33 <30 <31 January 23 <29 <25 <22 <28 <21 <21 <26 <22 January 30 <24 <26 <20 <22 <29 <29 <22 <31 February 06 <33 <28 <37 <31 <33 <31 <37 <36 February 13 <40 <33 <36 <29 <30 <28 <33 <33 February 20 <27 <21 <28 <28 <23 <23 <29 <33 February 27 <19 <27 <18 <23 <22 <24 <23 <22 March 06. <20 <23 <25 <23 <20 <25 <21 <22 March 13 <22 <24 <23 <21 <23 <20 <25 <19 March 20 <35 <17 <31 <25 <33 <35. <24 <22 March 27 <32 <32 <38 <38 <38 <36 <32 <38 April 02 <47 <35 <45 <41 <28 <36 <32 <39 April 10 <18 <21. <24 <20 <24 <22 <24 <19 April 17 <28 <32 <26 <35 <33 <34 <25 <30 April 24 <24 <25 <24 <23 <19 <28 <25 <22 May01 <39 <37 <44 <43 <44 <40 <37 <42 May 08 <21 <18 <27 <27 <24 <25 <26 <28 May 15 <26 <30 <21 <29 <24 <24 <23 <27 May 22 <22 <20 <24 <25 <17 <27 <22 <17 May 29 <27 <35 <35 <37 <32 <32 <39 <37 June 05 <30 <16 <29 <24 <26 <23 <20 <23 June 12 <26 <21 <25 <25 <24 <19 <20 <28 June 19 <23 <17 <27 <18 <17 <32 <24 <29 June 25 <37 <44 <36 <40 <41 <43 <41 <28 31

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2007 1.OE-3 pCi/m3 l 2 Sigma Page 2 of 2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN July 03 <48 <54 <33 <51 <39 <56 <47 <38 July 10 <38 <34 <30 <35 <39 <30 <38 <30 July 17 <31 <35 <33 <32' <30 <26 <39 <37 July 24 <30 <31 <24 <27 <20 <30 <29 <45 July 31 <41 <46 <38 <31 <26 <31 <36 <33 August 07 <32 <31 <30 <27 <25 <34 <36 <33 August 14 <42 <45 <48 <36 <45 <46 <34 <44 August 21 <25 <21 <26 <22 <27 <35 <27 <36 August 28 <30 <28 -<33 <29 <37 <24 <27 <29 September 04 <37 <30 <29 <37 <37 <34 <28 <42 September 11 <33 <43 <40 <28 <28 <30 <43 <32 September 18 <20 <23 <22 <23 <19 <24 <28 <20 September 25 <36 <40 <40 <36 <40 <56 <30 <38 October 02 <22 <22 <24 <22 <31 <27 <29 <25 October 09 <18 <23 <25 <25 <21 <22 <26 <25 October 16 <31 <36 <34 <26 <38 <33 <31 <33 October 23 <26 <24 <29 <23 <27 <27 <29 <26 October 30 <31 <31 <28 <22 <26 <23 <25 <25 November 06 <28 <25 <34 <31 <29 <30 <26 <32 November 13 <27. <24 <26 <34 <32 <22 <26 <30 November 20 <41 <43 <43 <50 <43 <43 <34 <32 November 27 <30 <25 <33 <29 <29 <21 <28 <29 December 04 <32 <34 <32 <33 <37 <43 <30 <36 December 11 <25 <21 <26 <19 <24 <28 .<22 <28 December 18 <41 <39 <49 <49 <39 <48 <42 <40 December 24 <58 <43 <54 <56 <45 <57 <54 <49 December 31 <42 <23 <41 <34 <32 <31 <28 <33 32

TABLE 3-5: GAMMA EMITTER CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2007 1.OE-3 pCi/m3 +/-2 Sigma Page 1 of I SAMPLING FIRST SECOND THIRD FOURTH AVERAGE LOCATIONS NUCLIDE QUARTER QUARTER QUARTER QUARTER +/-2 SIGMA SS. Cs-1 34 <1.5 :<1.7 <1.6 <1.4 Cs-1 37 <1.4 <0.8 <1.2 <1.1 Be-7 120 +/- 29 133 +/- 61 158+/- 34 145 +/- 62 139 +/- 16 HIR Cs-134 <1.5 <2.4. <3.5 Cs-137 <0.8 <1:6 <1.4 <2.6 Be-7 114 +/- 26 124 +/- 58 151 +/- 41 151 +/- 67 135 +19 BC Cs-134 <1.4 <1.7 <1.7 <1.8 Cs-137 <0.8 <0.9 <1.2 <1.4 Be-7 144 +/- 29 ,145 +/- 62 126 2 34. 148 +/- 49 141 +/- 10 ALL

<1.1i <0.4 <1.8 Cs-1 34 <2.3 Cs-137 <0.8 <0.9 <1.9 <2.1 Be-7 120 +/- 26 165. +/- 61 128 +/- 36 130 +/- 43 136 +/- 20 CP Cs-134 <0.7 <1.5 <1.5 <3.5 Cs-137 <0.6 <1.4 <1.0 <0.9 Be-7 136+/- 23 144 +/- 59 117 +/- 32 124 +/- 63 130 +/- 12 BASF Cs-1 34 <0.4 <1.4 <0.8. <2.9 Cs-1 37 <1.4 <0.7' <1.8 <3.3 Be-7 119 +/- 29 137 +/- 56 108 +/- 37 131 +/- 60 124 +/- 13 FE Cs-134 <0.7 <0.9 <0.6 <3.5 Cs-137 <0.9 <0.7 <0.5 <0.9 Be-7 131 +/- 28 176 +/- 50 146 +/- 38 <57 151 23 NN-C Cs-1 34 <1.3 <1.3 <1.6 <4.0 Cs-1 37 <1.0 <0.7 <0.5 <3.8 Be-7 158 +/- 29 202 +/- 64 155 +/- 42 140 +/- 59 164 +/- 27 33

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/Liter +/- 2 Sigma Page 1 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C JANUARY Cs-1 34 <7- <6 <6 Cs-1 37 <6 <5 <6 Ba-140 <9, <8 <10 La-1 40 <10 <19 <12 1-131 <1, <1 K-40 1420 +/- 120 1480 +/- 100 1250 .+/- 120 FEBRUARY Cs-134 <7 <8 <9 Cs-1.37 <7 <8 <8 Ba-140 <14 <12 <12 La-140 <15 <13 <14 1-131 <1 <1 K-40 1420 +/- 130 1340 +/- 150 1220 +/- 140 MARCH Cs-1 34 <8 <9 <9 Cs-1 37 <8 <10 <8 Ba-1 40 <10 <13 <12 La-140 <12 <15 <14 1-131 <1 <1 <1 K-40 1450 +/- 160 .1530 +/- 180 '1210 +/- .150 Sr-89 <9 Sr-90 <2 APRIL Cs-1 34 <10 <9 <7 Cs7137 <9 <7 <7 Ba-140 <13 <12" <14 La- 140 <15 <14 <15

<1 1-131 1<1 <1.

K-40 1400 +/- 170 1490 +/- 150 1310 +/- 130 34

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Nuclear Power Station, Surry County, Virginia - 20071 pCi/Liter +/- 2 Sigma Page 2 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C MAY Cs-1 34 <9 <9 <7 Cs-1 37 <8 <12 <7.

Ba-1 40 <13 <12: <9 La-140 <15 <14 <10 1-131 <1 <1 <1 K-40 1480 + 150 1360 +/- 190 1310 +/- 130 JUNE Cs-134 <10 '<7 <7

<9 <7.

Cs-137 <10 Ba-140 <10' <13 <14 La-140 <12 <15 <15 1-131 <1 <1 <1 K-40 1310 +/- 160 1530 +/- .150 1270 +/- 150 Sr-89 <10 Sr-90 <2 JULY Cs-134 <6 <7 <6 Cs-137 <6 <6 <5 Ba-140 <13 <12 <13 La-1 40 <14 <13 <14 1-131 <1 <1 <1

K-40 1420 +/- 110 1570 +/- 120 1330 +/- 110 AUGUST Cs-134 <12. <12 <9 Cs-137 <10 <9 <9 Ba-140 <7 <12 <12 La-1 40 <8 <14 <13 1-131 <1 <1 <1 K-40' 1440 +/- 190 1490 +/- 170 1270 +/- 150 35

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/Liter +/- 2 Sigma Page 3 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C SEPTEMBER Cs-1 34 <9 <10, <10 Cs-1 37 <8 <8 <8 Ba-1 40 <12 <14 <12 La-140 <14 <15 <14 1-131 <1 <1 <1 K-40 1350 +/- 160, 1490 +/- 160 1400 +/- 180 Sr-89 <9 Sr-90 <2 OCTOBER Cs-1 34 <8 <9 <9 Cs-1 37 <8 <9 <7 Ba-140 <13 <10 <13 La-1 40 <15 <12 <15 1-131 <1 <1 <1 K-40 1350 +/- 130 1470 +/- 160 1360 +/- 150 NOVEMBER Cs-134 <10 <9 <10 Cs-1 37 <10 <10 <9 Ba-140 <14 <14 <16 La-1 40 <15 <14 <15 1-131 <1 <1 <1 K-40 1480 +/- 190 1390 +/- 160 1290 +/- 160 DECEMBER Cs-134 <10 <12 <9 Cs-137 <9 <10 <7 Ba-1 40 <15 <15 <12 La-140 <15 <15 <12 1-131 <1 <1 <1 K-40 1280 +/- 170 1410 +/- 190 1230 +/- 140 Sr-89 <8 Sr-90 1.87 +/- 0.89 36

TABLE 3-7: GAMMA EMITTER CONCENTRA TION IN FOOD PRODUCTS Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION SAMPLE LOCATIONS DATE TYPE Cs-134 Cs-137 1-131 K-40 ,!

BROCK 10/30/2007 Corn <23 <23 <53 2540 +/- 320 FARM 10/30/2007 Peanuts <58 <38 <60 5350 +/- 890 SLADE 11/27/2007 Soybeans <37 <31 <60 15280 +/- 820 FARM 37

TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/Liter +/- 2 Sigma Page 1of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Ba-140 Co-58 Co-60 Cs-134 Cs-137 SS 03/20/2007 <9 <4 <5 <5 <5 06/20/2007 <12 <7 <8 <8 <7 09/11/2007 <11 <8 <7 <8 <7 12/13/2007 <16 <8 <6 <7 <6 Fe-59 1-131 La- 140 Mn-54 Nb-95 03/20/2007 <10 <1 <10 <5 <5 06/20/2007 <13 <1 <14 <6 <9 09/11/2007 <15 <1 <13 <6 <7 12/13/2007 <17 <1 <15 <6 <9 Zn-65 Zr-95 H-3 03/20/2007 <10 <8 <1300 06/20/2007 <18 <14 <530 09/11/2007 <17 <12 <260 12/13/2007 <17 <11 <440 Ba-140 Co-58 Co-60 Cs-134 Cs-137 HIR 03/20/2007 <13 <6 <6 <7 <5 06/20/2007 <13 <7 <7 <7 <8 09/11/2007 <12 <8 <8 <7 <7 12/13/2007 <16 <7 <8 <7 <7 Fe-59 1-131 La- 140 Mn-54 Nb-95 03/20/2007 <14 <1 <15 <5 <8 06/20/2007 <13 <1 <14 <6 <9 09/11/2007 <14 <1 <13 <7. <8 12/13/2007 <15 <1 <15 <6 <8 Zn-65 Zr-95 H-3 03/20/2007 <14 <11 <1300 06/20/2007 <16 <13 <530 09/11/2007 <20 <14 <250 12/13/2007 <16 <12 <450 38

TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WATER Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/Liter + 2 Sigma Page 2 of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Ba-140 Co-58 Co-60 Cs-134 Cs-137 TC / 03/20/2007 <13 <5 <6 <6 <5 06/20/2007 <9 <8 <6 <7 <7 09/11/2007, <14 <7 <7 <8 <6 12/13/2007 <12 <9 <7 <7 .<8 Fe-59 1-131 La-140 Mn-54 Nb-95 03/20/2007 <13 <1 <14 <5 <8 06/20/2007 <15 <1 <11 <6 <8 09/11/2007 <15 <1 <16 <6 12/13/2007 <18 <1 <12 <9 <10 Zn-65 Zr-95 H-3 03/20/2007 ,<14 <12- <1300 06/20/2007 <16 <11 <520.

09/11/2007 <17 <12 <250.

12/13/2007 <18 <16 <450 j

39

TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WATER Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/Liter +/- 2 Sigma Page I of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Ba-140 Co-58 Co-60 Cs-134 Cs-1 37 SD 01/24/2007 <9 <6. <8 <6 <6 02/20/2007 <13 <8 <8 <8 <7 03/27/2007 <19 <5 <6 <6 <5-04/25/2007 <10 <5 <6 <7 <6 05/22/2007 .<9 <5 <5 <5 <6 06/19/2007 <7 <5 <5 <5 <5 07/24/2007 <12 <7 <8 <6 <6 08/29/2007 <13 <8 <7 <7 <6 09/18/2007 <8 <6 <6 <6 <6 10/16/2007 <16 <6 <9 <8 <7 11/20/2007 <7 <4 <4 <5 <4 12/11/2007 <15 <7 <8 <7 <7 Fe-59 1-131 La-140 Mn-54 Nb-95

<10 01/24/2007 <10 <11 <6 <6 02/20/2007 <18 <10 <15 <7 <8 03/27/2007 <13 <10 <10 <6 <6 04/25/2007 <13 <10 <11 <6 <7 05/22/2007 <12 <10 <11 <5 <5 06/19/2007 <10 <10 <8 <5 <5 07/24/2007 <12 <10 <12 <5 <6 08/29/2007 <12 <10 <14 <7 <8 09/18/2007 <13 <10 <9 <6 <7 10/16/2007 <18 <10 <16 <8 <7 11/20/2007 <9 <8 <7 <4 <5 12/11/2007 <16 <10 <15 <6 <6 Zn-65 Zr-95 H-3 K-40 01/24/2007 <15 <10 <89 02/20/2007 <16 <11 <99 03/27/2007 <13 <9 <1650 <71 04/25/2007 <13 <10 <82 05/22/2007 <12 <9 <79 06/19/2007 <9 <8 <1350 <72 07/24/2007 <12 <9 110 +/- 65 08/29/2007 <17 <12 <120 09/18/2007 <13 <11 <1350 135 +/- 59 10/,16/2007 <16 <12 <120 11/20/2007 <12 <7 98 +/- 45 12/11/2007 <27 <12 <1350 176 +/- 65 40

TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WA TER Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/Liter +/- 2 Sigma Page 2 of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPES Ba-140 Co-58 Co-60 Cs-134 Cs-137 SW-C 01/24/2007 <13 <6 <10 <7 <8 02/20/2007 <8 <6 <5 <6 <5 03/27/2007 <9 <6 <6 <6 <6 04/25/2007 <8 <5 <5 <6 <5 05/22/2007 <8 <6 <5 <6 <5 06/19/2007 <11 <6 <6 <6 <5 07/24/2007 <10 <5 <6 <7 .<6 08/29/2007 <1.1 <6 <6 <6 <6

.09/18/2007 <9 <5 <6 <5 <5 10/16/2007 <13 <5 <7 <6 <7 11/20/2007 <6 <4 <5 <4 <4 12/11/2007 <14 <6 <8 <7 <7 Fe-59 1-131 La-140 Mn-54 Nb-95 01/24/2007 <16 <10 <14 <7 <7 02/20/2007 <12 <10 <9 <5 <6 03/27/2007 <11 <10 <10 <6 <7 04/25/2007 <12 <10 <9 <4 <6 05/22/2007 <11 <10 <10 <5 <6 06/19/2007 <12 <10 <13 <6 <5 07/24/2007 <13 <10 <11 <6 <6 08/29/2007 <12 <10 <13 <7 <6 09/18/2007 <10 <9 <10 <5 <6 10/16/2007 <13 <10 <13 <5 <7 11/20/2007 <8 <7 <6 <4 <6 12/11/2007 <15 <9 <14 <6 <8 Zn-65 Zr-95 H-3 K-40 01/24/2007 <15 <10 <85 02/20/2007 <15 <10 <71 03/27/2007 <22 <11 <1650 <72 04/25/2007 <12 <8 <73 05/22/2007 <11 <9 <70 06/19/2007 <11 <9 <1350 <93 07/24/2007 <13 <9 <95 08/29/2007 <12 <9 <83 09/18/2007 <12 <9 <1350 <73 10/16/2007 <14 <12 <100 11/20/2007 <10 <7 113 +/- 42 12/11/2007 <25 <12 <1350 <110 41

TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/kg (dry) d 2 Sigma Page 1 of I SAMPLING COLLECTIONJ LOCATIONS DATE Cs-134 Cs-137 Th-228 K-40 SD 03/22/2007 <61 238 +/- 60 1090 +/- 150 17800 +/- 1200 09/05/2007 <91 266 +/- 83 1260 +/- 250 17800 +/- 1700 CHIC-C 03/22/2007 <75 256 + 46 1390 +/- 130 17560 +/- 990 09/05/2007 <96 196 +/- 80 1360 + 260 18000 +/- 2000 42

TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/kg (dry) d: 2 Sigma Page 1 of I SAMPLING COLLECTION1 LOCATIONS DATE Cs-134 Cs-137 Th-228 K-40 I HIR 02/13/2007 <110 <35 1731 +/- 90 5390 +/- 440 08/28/2007 <40 <32 <150 4500 +/- 590 CHIC-C 02/13/2007 <47 <36 <120 2010 +/- 510 08/28/2007 <54 <44 1430 +/- 100 1330 +/- 340 43

TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE K-40 Co-58 Co-60 Cs-134 SD 04/10/2007 Catfish 1880 +/- 880 <51 <94 <30 04/10/2007 White Perch 1770 +/- 830 <51 <55 <68 11/07/2007 Catfish 2240 +/- 510 <43 <37 <48 10/10/2007 White Perch 1700 +/- 430 <49 <39 <40 Cs-137 Fe-59 Mn-54 Zn-65 04/10/2007 Catfish <78 <151 <68 <171 04/10/2007 White Perch <62 <201 <68 <131 11/07/2007 Catfish <31 <77. <41 <99 10/10/2007 White Perch <31 <98 <34 <82 44

TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Surry Nuclear Power, Station, Surry County, Virginia - 2007 pCilkg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE K-40 Co-58 Co-60 Cs-134 POS 03/22/2007 <452 <41 <35 <40 09/05/2007 850 +/- 410 <30 <40 <27 Cs-1 37 Fe-59 Mn-54 Zn-65 03/22/2007 <37 <84 <45 <111 09/05/2007 <35 <92 <29 <93 K-40 Co-58 Co-60 Cs-134 MP 03/22/2007 <716 <50 <53 <43 09/05/2007 650 +/- 430 <33 <44 <44 Cs-137 Fe-59 Mn-54 Zn-65 03/22/2007 <35 <100 <39 <125 09/05/2007 <44 <115 <49 <125 45

TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Surry Nuclear Power Station, Surry County, Virginia - 2007 SSAMPLtING pCi/kg (wet) +/- 2 Sigma COLLtECTION1 Page I of I LOCATIONS DATE ISOTOPE Co-58 Co-60 Cs-1 34 Cs-137 HIP 03/22/2007 <50 <68 <42 <38 09/05/2007 <48 <45 <41 <52 Fe-59 Mn-54 Zn-65 03/22/2007 <105 <47 <115 09/05/2007 <86 <55 <125 Co-58 Co-60 Cs-134 Cs-137 SD 03/22/2007 <32 <33 <32 <35 09/06/2007 <29 <45 <35 <29 Fe-59 Mn-54 Zn-65 03/22/2007 <115 <38 <115 09/06/2007 <81 <35 <92 Co-58 Co-60 Cs-134 Cs-137 CHIC-C 03/22/2007 <44 <46 <37 <35 09/05/2007 <49 <51 <43 <41 Fe-59 Mn-54 Zn-65 03/22/2007 <61 <35 <90 09/05/2007 <125 <43 <145 Co-58 Co-60 Cs-134 Cs-137 LC 03/22/2007 <47 <43 <40 <57 09/05/2007 <28 <30 <41 <37 Fe-59 Mn-54 Zn-65

.03/22/2007 <96 <39 <90 09/05/2007 <64 <35 <85 46

TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS Surry Nuclear Power Station, Surry County, Virginia - 2007 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE K-40 Co-58 Co-60 Cs-1 34 SD 06/21/2007 2150 + 170 <14 <11 <12 Cs-137 Fe-59 Mn-54 Zn-65

<12 <31 <11 <24 47

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2007 and tabulated in Section 3, are discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the AREVA NP Environmental Laboratory 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 2007 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 2007 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 Ca$ and LiF elements and specifically designed for environmental monitoring, are deployed at each sampling location.

In 2001, 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 seven-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 five-year trend indicates a stable trend. These trends will continue to be monitored.

Figure 4-1: DIRECT RADIATION MEASUREMENT TLD RESULTS 8

7 6-6 05 04 4-3 E 2 0

00 C)0 '

-- Site Boundry -e--5 Mile -- 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 4-2:2007 GROSS BETA IN AIR PARTICULATES 0.045 0.040 0.035 0.030 * '

0.025 A.

" 0.020 ..

0.015 ....

0.010 0.005 0.000 IT 00 C.4 CN, M D C C7 mC - A n4 A l-o SAvg Indicator --- -A-- -AvCotl Rgure 4-3: GROSS BETA INAIR PARTICULATES HISTORICAL TREND I.OE+00 1.OE-01 1 0E-0 3. . . . . . , , , I , , I . . . . . . . . . . . .

00 ON 0 F "l m 'IT tN)0 00 ON1 0 - Cl ) -ItO oo 00 ON ON ON ON

ý ON ON O O N N 0 0 0 0 0 0 O0 0 0 00 0 0 0 AvgIndicator --4-- 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 ParticulateGamma 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 2007.

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 one of the four composites analyzed, at a concentration of 1.87 pCi/L. The average Sr-90 concentration for the ten year period of 1998 to 2007 is 1.89 pCi/L. The Sr-90 detected is not a part of station effluents but, rather, a product of nuclear weapons testing fallout.

51

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

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

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

Samples of silt are collected from two locations, one upstream and one downstream of the station.' The results of the gamma spectroscopy analyses are presented in Table 3-10. 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.

52

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 2007, cesium- 137 was detected with an average indicator location concentration of 252 pCi/kg and an average control location concentration of 226 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 L.0E+02 1.OE+01 I.OE+ 00 . . . . . . . . . . . . .

t-c 00 0- o '*T 00 0 C, , 00 o ei ~- 'C

---N--00 00 00 00 00C0m 0- 0t 0sh0e o o 0 0 o o 0 0 Ci eN (~'4 Cl

-- Control - Chickahomniny -a-Station Discharge Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDL.

Station Discharge was <MDL activity 1996 through 1998 and 2004 through 2007.

53

Fgure 4-5: CESIUM-1 37 INSILT 1.OE+04 m

x 1.OE+03

°)

1.OE+02 C4 I no 00 Ch NC I '0 00 DC C 00 0 R i L 0

Control - Chickahomniny Ai- Station Discharge -Ave-Pre Op -Requie LD 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.

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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 C

Clams are analyzed from four different locations. The results of the gamma spectroscopy arnalyses are presented in Table 3-14. Like oysters, no station related radioactivity was detected. Absent in 2007 was naturally occurring potassium-40. This is most likely due to higher minimum detectable concentrations for potassium-40 in the analyses than in previous years.

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 no REMP exceptions for scheduled sampling and analysis during 2007.

56

6. CONCLUSIONS The results of the 2007 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 2007 trend well with the control location.

SMilk - 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-90 was detected in one of four samples this year at a concentration of 1.87 pCi/L. Strontium-90 is not a part 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 2007.

> 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 five samples. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2007.

> 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.

57

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 samples. 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 2007 62

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January 1 to December 31, 2007 Page 1 of 1 INearest Nearest Nearest Nearest Sector Direction Resident Garden** Cow Goat A N 4.1 @ 100 (a) (a) (a)

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

C NE 4.7 @ 350 4.9 @ 560 (a) (a)

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

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

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

G SE (a) (a) (a) (a)

H SSE 4.4 @ 1630 (a) (a) (a)

J S 1.7 @,1810 1.8 @ 1830 (a) (a)

K SSW 2.3 @212- 4.3 @ 193- 4.8 @ 200- (a)

L SW 2.3 @ 2210 3.6 @ 2230 (a) (a)

M WSW 0.4 @ 2440 3.6 @ 245- (a) (a)

N W 3.1 @ 2600 3.4 @ 260- (a) (a)

P WNW 4.9 @ 283- (a) (a) (a)

Q NW 4.6 @ 321- (a) (a) (a)

R NNW 3.8 @ 3380 4.4 @ 3340 3.7 @ 3360 (a)

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

- Area greater than 50 m2 and containsbroadleafvegetation.

(a) None 63

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2007 64

INTRODUCTION This appendix covers the Intercomparison Program of the AREVA NP Inc.

Environmental Laboratory. AREVA NP uses QA/QC samples provided by Analytics, Inc. to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP). The suite of Analytics QA/QC samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides. It was modified to more closely match the media mix presently being processed by AREVA NP and includes:.

> milk for gamma (10 nuclides) and low-level (LL) iodine-131 analyses once per quarter,

> milk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,

water for gamma (10 nuclides), low-level (LL) iodine- 131, and gross beta analyses during the 1st and 3rd quarters,

> water for Sr-89 and Sr-90 analyses during the 1st and 4th quarters,

> water tritium analysis during the 2nd and 4th quarters,

> air filter for gamma (9 nuclides) analyses during the 2nd and 4th quarters,

> air filter for gross beta analysis during each quarter,

> air filter for Sr-90 analysis during the 2nd and 4th quarters.

In addition to the Analytics Intercomparison Program, AREVA NP also participates in other intercomparison programs. These programs are the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (PT) Program, the' Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP).

RESULTS Intercomparison program results are evaluated using AREVA NP's internal bias acceptance criterion. The criterion is defined as within 25% of the known strontium value for samples containing both Sr-89 and Sr-90 and within 15% of the known value for other radionuclides, or within two sigma of the known value.

AREVA NP investigates any sample analysis 'result that does not pass these criteria.

Analytics Intercomparison Program results are included on the following pages for the' first quarter through the fourth quarter of 2007. A total of 104 analysis results were obtained with 7 not passing the acceptance criteria. 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.

65

CR 08-02 documents the 2nd quarter. low biased. analyses for cerium-141 in the milk matrix and chromium-51 in the particulate filter matrix. The approved corrective actions include reviewing the spectra for possible elevated baseline counts due to interfering radionuclides and adopting measures to assure that samples with short half lives are analyzed more expeditiously. The samples decayed through two half lives before analysis. This CR is not closed.

CR 08-10 documents the 4th quarter low biased analyses for strontium-89 and strontium-90 in, the particulate filter matrix. The approved corrective actions include reviewing the analysis worksheets for potential errors, determining the root cause and implementing appropriate corrective actions. This CR is not closed. A similar low bias analysis for strontium-90 occurred one other time since 2002 when Surry Power Station began using the services of the AREVA NP laboratory. A total of twelve Analytics cross check samples for strontium-90 in this matrix have been analyzed with an average ratio of 0.87. The ratio is 0.95 when excluding the two low biased analyses.

CR 08-11 documents the 4th quarter low biased analyses for iron-59, zinc-65 and cobalt-60 in the particulate filter matrix. The approved corrective actions include reviewing historical performance for the Analytics filter matrix, determining if Analytics has changed the filter preparation method, reviewing filter geometry and recalibrate as needed, and re-analyze the sample. This CR is, not closed.

66

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY QA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 1 OF 4) 1st Quarter Identification Reported Known 2007 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E5243-162 Milk 1-131LL pCi/L 85.1 85.2 1.00 A 1-131 pCi/L 75.4 85.2 0.88 A Ce-141 pCi/L 294 297 0.99 A Cr-51 pCi/L 226 245 0.92 A Cs-1 34 pCi/L 104 112 0.93 A Cs-1 37 pCi/L 228 234 0.97 A Co-58 pCi/L 98.1 98.8 0.99 A Mn-54 pCi/L 184 182 1.01 A Fe-59 pCi/L 109 106 1.03 A Zn-65 pCi/L 1041 1000 1.04 A Co-60 pCi/L 148 152 0.97 A E5244-162 Milk Sr-89 pCi/L 126 137 0.92 A Sr-90 pCi/L 8.85 10 0.88 A E5238-162 Water Gr-Beta pCi/L 104 100 1.04 A E5239-162 Water 1-131LL pCi/L 88.3 89.8 0.98 A 1-131 pCi/L 74.3 89.9 0.83 A Ce-141 pCi/L 257 258 1.00 A Cr-51 pCi/L 218 213 1.02 A Cs-134 pCi/L 93.6 97.1 0.96 A Cs-1 37 pCi/L 197 204 0.97 A Co-58 pCi/L 86.2 85.8 1.00 A Mn-54 pCi/L 155 158 0.98 A Fe-59 pCi/L 87.1 91.7 0.95 A Zn-65 pCi/L 886 869 1.02 A Co-60 pCi/L 131 132 0.99 A E5240-162 Water Sr-89 pCi/L 127 137 0.92 A Sr-90 pCi/L 9.39 9.99 0.94 A E5242-162 Filter Gr-Beta pCi 69.4 61.9 1.12 A Footnotes are on page 4 of 4.

67

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY QA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 2.OF 4) 2nd Quarter Identification Reported Known 2007 Number Matrix Nuclide Units Value (a) Value (b) 'Ratio (c) . Evaluation (d)

E5338-162 Milk 1-131LL pCi/L 73.5 70.1 1.05 A.

1-131 pCi/L 75 70.1 1.07 A Ce-141 pCi/L 168 200 0.84 U Cr-51 pCi/L 447 512 0.87 A Cs-134 pCi/L 223 242 0.92 A Cs-137 pCi/L 165 169 0.98 A Co-58 pCi/L 203 198 1.02 A Mn-54 pCi/L 178 166 1.07 A Fe-59. pCi/L 170 167 1.02 A Zn-65 pCi/L 343 334 1.03 Co-60 pCi/L 238 238 1.00 E5334-162 Water H-3 pCi/L 8520 9040 0.94 A E5335-162 Filter Gr-Beta pCi 127 112 1.13 A E5335-162 Filter Ce-141 pCi 94.1 107 '0.88 A Cr-51 pCi 230 273 0.84 U Cs-134. pCi 114.3 129 0.89 A Cs-137 pCi 86.3 90.1 0.96 A Co-58 pCi 98.4 106 0.93 A Mn-54 pCi 83.3 88.5 0.94 A Fe-59 pCi 79 89 0.89 A Zn-65 pCi 167 178 0.94 A Co-60 pCi 112 127 0.89 A

E5337-162 Filter Sr-89 pCi 71.4 91.2 0.78 A Sr-90 pCi 10.1 12.4 0.82 Footnotes are on page 4 of 4.

68

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY QA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 3 OF 4) 3rd Quarter Identification . Reported Known 2007 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E5434-162 Milk 1-131LL pCi/L 87.2 85.2 1.02 A 1-131 pCi/L 82.9 85.2 0.97 A Ce-141 pCi/L 196 .211 0.93 A Cr-51 pCi/L 282 289 0.97 A Cs-134 pCi/L 141 147 0.96 A Cs-137 pCi/L 126 131 0.96 A Co-58 pCi/L 111.0, 114 0.97 A Mn-54 pCi/L 171 168.0 1.02 A Fe-59 pCi/L 112 :111.0 1.01 A Zn-65 pCi/L 212 202 1.05 A Co-60 pCi/L 145 148 0.98 A E5435-162 Milk Sr-89 pCi/L 89.2 94.9 0.94 A Sr-90 pCi/L 12.9, 13.1 0.98 A E5430-162 Water Gr-Beta pCi/L 218 214 1.02 A E5431-162 Water 1-131LL pCi/L 83.4 80.1 1.04 A 1-131 pCi/L 80.2 80.1 1.00 A Ce-141 pCi/L 176 182 0.97 A Cr-51 pCi/L 228 249 0.92 A Cs-134 pCi/L 111 127 0.87 A Cs-137 pCi/L 1112 112 1.00 A Co-58 pCi/L 94.3 98.1 0.96 A Mn-54 pCi/L 141 144 0.98 A Fe-59 pCi/L 94.8 95.1 1.00 A Zn-65 pCi/L 186 174 1.07 A Co-60 pCi/L' 120 127 0.94 A E5433-162 Filter Gr-Beta pCi 190 196 0.97 A.

'Footnotesare on page 4 of 4.

69

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY QA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 4 OF 4) 4th Quarter Identification Reported Known

2007 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E5533-162 Milk -I131LL pCi/L 59.2 60.8.. 0.97 A 1-131 pCi/L 58.5 60.8 0.96 A Ce-141 pCi/L 136.0 141 0.97 A Cr-51 pCi/L 516.7 512 1.01 A Cs-'134 pCi/L 137.0 .137 1.00 A Cs-137 pCi/L 166.2 166 1.00 A Co-58 pCi/L 166.5 174.01: 0.96 A Mn-54 pCi/L 200.9 190 1.06 A Fe-59 pCi/L 155.0 148.0 . 1.05 A Zn-65 pCi/L 222.9 234 0.95 A Co-60 pCi/L 205.1 211 -0.97 A E5527-162 Water H-3 pCi/L 9003 9020 1.00 A E5528-162 Water Sr-89 pCiiL 87;1- 94.9 0.92 A Sr-90 pCi/L 14.4. 15.4 0.93 A E5530-162 Filter Gr-Beta pCi 166.1 152 1.09 A E5531-162 Filter Ce-141 pCi 84.1 "98.4 0.85 A Cr-51 pCi 311.7 358 0.87 A Cs-1 34 pCi 82.3 96.1 0.86 A Cs-1 37 pCi 108.9 116 1.06 A Co-58 pCi 107.5 122 0.88 A Mn-54 pCi 117.2 133 0.88' A Fe-59 pCi 86.6 104 0.83 U Zn-65 pCi 135.3 164 0.83 U Co-60 pCi 123.1 148- 0.83 U E5532-162 Filter Sr-89 pCi 45.9 102 0.45 U Sr-90 pCi 7.2 16.5 0.44 U (a) AREVA reported result.

(b) The Analytics standard.

(c) Ratio of AREVA to Analytics results.

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

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