Text

Independent Spent Fuel Storage Installation - 2006 Annual Radiological Environmental Operating Report
	ML071230717
Person / Time
Site:	Surry, 07200002
Issue date:	04/30/2007
From:	Jernigan D; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	07-0300
	Download: ML071230717 (76)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 2007 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.

SS&L/TJN 07-0300 Docket Nos.

50-280 50-281 72-2 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, 2006 through December 31, 2006 which includes environmental monitoring for the Surry ISFSI.

If y 2

u ha any questions or require additional information, please contact Paul Harris Donald E-,40igan Site Vice President Surry Power Station Attachment Commitments made in this letter: None I-~3

Serial No. 07-0300 Docket Nos.: 50-280 50-281 72-2 copy: US Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.E., Suite 23T85 Atlanta, Georgia 30303-8931 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Mr. D. C. Arnett NRC Resident Inspector Surry Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23218

Serial No. 07-0300 Docket Nos.: 50-280 50-281 72-2 ATTACHMENT 2006 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37 INDEPENDENT SPENT FUEL STORAGE INSTALLATION LICENSE NO. SNM-2501 VIRGINIA ELECTRIC AND POWER COMPANY

Surry Power Station 2006 Annual Radiological Environmental Operating Report IIWDomin ion

Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2006 to December 31, 2006

Annual Radiological Environmental Operating Report Surry Power Station January 1, 2006 to December 31, 2006 Prepared by:

Reviewed by:

Approved by:

P. F. Blount Health Physicist P. R. Harris Supervisor Radiological Analysis D. K. Miller Supervisor Health Physics Technical Services Manag

'ological Protection 2

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

4

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

5

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

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

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

8

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

20 3.1 Summ ary of Results...........................................................................................................

20 3.2 Analytical Results of 2006 REM P Samples...................................................................

27

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

49 4.1 Gamm a Exposure Rate................................................................................................

50 4.2 Airborne Gross Beta....................................................................................................

51 4.3 Airborne Radioiodine.....................................................................................................

53 4.4 Air Particulate Gamm a................................................................................................... 53 4.5 Cow M ilk.........................................................................................................................

53 4.6 Food Products..................................................................................................................

54 4.7 W ell W ater.......................................................................................................................

54 4.8 River W ater.......................................................................................................................

54 4.9 S ilt....................................................................................................................................

5 4 4.10 Shoreline Sediment.....................................................................................................

56 4.11 Fish.

56 4.12 Oysters..........................................................................................................................

56 4.13 Clams.............................................................................................................................

57 4.14 Crabs..............................................................................................................................

57

5. PROGRAM EXCEPTION S..................................................................................................

58

6. CONCLUSION S........................................................................................................................

59 RE FERE NCES...............................................................................................................................

61 APPEND ICES................................................................................................................................

63 APPEND IX A : LAND U SE CENSU S..................................................................................

64 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS......................... 66 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 2006 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2006, 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 level for radionuclides. Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the 5

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 2006 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. Tritium was detected in one of eight river water samples at 7.4% of the USNRC reporting level, that sample being from the discharge canal. No other 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 2006 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.

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 2006, 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 2006 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 2006 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. 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).

These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As is Reasonably 7

Achievable."

This report documents the results of the REMP for 2006 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 2006 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control."

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. Table 2-2 summarizes the analysis program conducted by AREVA NP Environmental Laboratory and Global Dosimetry Solutions for Surry Power Station during the year 2006.

On June 30, 1998, the Commonwealth of Virginia, Department of Health, discontinued its comparative analysis (state split) program with Surry Power Station. Although the routine splitting of samples with the Commonwealth of Virginia has been discontinued, samples will be split at the request of the state.

Dominion personnel collect all samples listed in Table 2-1. 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.

8

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mm Table 2-1 SURRY - 2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks 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 (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) 0.2 mi WNW 0.4 mi NW 0.2 mi NNW 0.3 mi N

0.3 mi NNE 0.3 mi NE 0.4 mi ENE 0.3 mi E

0.1 mi W

0.4 mi WSW 0.3 mi SW 0.3 mi SSW 0.4 mi S

0.6 mi SSE 0.9 mi SE 1.6 mi ESE 2.0 mi NNE 4.5 mi SSW 4.9 mi SW 5.1 mi WSW 7.7 mi WSW 4.0 mi W

5.0 mi WNW 6.3 mi NW 3.8 mi NNW 4.9 mi NNW 4.6 mi N

7.8 mi N

5.5 mi NNE 5.8 mi NNE 5.0 mi 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 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 On site (Stored in lead container outside 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 - 2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Air Charcoal and Particulate BASF Lee Hall Goose Island Fort Eustis Newport News James River Bridge Benn's Church Smithfield Rushmere Route 628 Surry Station Hog Island Reserve Bacon's Castle Alliance Colonial Parkway BASF Fort Eustis Newport News Surry Station Discharge Scotland Wharf Surry Station Hog Island Reserve Hog Island Reserve Chickahominy River Chickahominy River Surry Station Discharge (34)

(35)

(36)

(37)

(38)

(39)

(40)

(41)

(42)

(43) 5.1 mi 7.1 mi 5.1 mi 4.9 mi 19.3 mi 17.1 mi 17.0 mi 13.4 mi 5.3 mi 5.1 mi 0.3 mi 2.0mi 4.5 mi 5.1 mi 3.8 mi 5.1 mi 4.9 mi 19.3 mi ENE ENE E

ESE SE SE SSE SSE SSE S

NNE NNE SSW WSW NNW ENE ESE SE 700 750 900 1040 1300 1420 1590 1670 1560 1770 180 260 2020 2470 3330 700 1040 1300 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 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 (SS)

(HIR)

(BC)

(ALL)

(CP)

(BASF)

(FE)

(NN)

Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Site Boundary (Highest D/Q)

Control Location River Water Well Water (SD) 0.4 mi NW 3230 Monthly (SW) 4.9 mi WNW 2840 Monthly Control Location Shoreline Sediment Silt (SS) 0.1 mi SW (HIR) 2.0 mi NNE (HMR) 0.6mi N

(CHIC) 11.2 mi WNW (CHIC) 11.2 mi WNW (SD) 1.3 mi NNW 2270 Quarterly 280 Quarterly 70 Semi-Annually 3010 Semi-Annually 300' Semi-Annually 341' Semi-Annually Onsite Control Location Control Location 10

Table 2-1 SURRY - 2006 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Milk Colonial Parkway Williams Epp's (CP)

(WMS)

(EPPS) 3.7 mi NNW 27.5 mi S

4.8 mi SSW 3360 Monthly 1750 Monthly 2000 Monthly Control Location Oysters Point of Shoals Mulberry Point Clams Chickahominy River Surry Station Discharge Hog Island Point Lawne's Creek Fish Surry Station Discharge Crabs Surry Station Discharge Food Products Brock's Farm (Corn, Peanuts, Slade's Farm Soybeans)

(POS) 6.4 mi SSE (MP) 4.9 mi ESE (CHIC)

(SD)

(HIP)

(LC)

(SD)

(SD) 11.2 mi WNW 1.3 mi NNW 2.4 mi NE 2.4 mi SE 1.3 mi NNW 1.3 mi NNW 1570 Semi-Annually 1240 Semi-Annually 3000 Semi-Annually Control Location 3410 Semi-Annually 520 Semi-Annually 1310 Semi-Annually 3410 Semi-Annually 3410 Annually 1830 Annually 1790 Annually (BROCK) 3.8 mi S

(SLADE) 3.2 mi S

11

Table 2-2 (Page 1 of 3)

SURRY - 2006 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/m3 Air Particulate Weekly Gross Beta 0.01 pCi/mr 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.

12

Table 2-2(Cont.)

(Page 2 of 3)

SURRY - 2006 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA Shoreline Sediment FREQUENCY Semi-Annual Silt Semi-Annual Monthly Milk Oysters Clams Semi-Annual Semi-Annual Annually ANALYSIS Gamma Isotopic Cs-134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 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-137 150 180 1

pCi/L 15 18 60 15 LLD*

REPORT UNITS pCi/kg - dry 150 180 130 260 130 130 260 130 150 130 260 130 130 260 130 150 130 260 130 130 260 130 150 pCi/kg - wet pCi/kg - wet pCi/kg - wet pCi/kg - dry pCi/L Crabs Footnotes located at end of table.

13

TABLE 2-2(Cont.)

(Page 3 of 3)

SURRY - 2006 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 Crops 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.

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

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Figure 3. Surry Emergency Plan Map SAir 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, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.

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TLD Sampling Nearest Milk Animal

Nearest Garden Aquatic Samples Original Q 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 - 2006 Docket No. 50-280-281 Page 1 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean I Distance Mean Mean Reported (Unfts)

Type No. LLD*

Range Name [ Direction Range Range Measurements Direct Gamma 164 2

3.5 (152/152)

STA-41 13.4 mi 6.0 (4/4) 4.0 (12112) 0 Radiation (1.8 - 6.6)

SSE (5.5 - 6.5)

(1.8-6.5)

TLD (mR/

Std Month)

Air Gross 413 10 22.3 (358/361)

FE 4.9 mi 23.8 (51/52) 23.1 (52t52) 0 Particulate Beta (7.2 - 44.2)

ESE (10.0 - 44.2)

(8.4-41.5)

(1E -3 pC i/m 3)

Gamma 32 Be-7 32 137 (28/28)

NN 19.3 mi 162 (4/4) 162 (4/4) 0 (91-187)

SE (134-183)

(134-183)

Cs-134 32 50

< LLD N/A

< LLD

< LLD 0

Cs--137 32 60

< LLD N/A

< LLD

< LLD 0

Air Iodine 1-131 413 70

< LLD N/A

< LLD

< LLD 0

(1E-3 pCi/m3)

Milk (pCi/Liter)

Strontium 4

Sr-89 Sr-90 4

4

< LLD N/A

< LLD N/A N/A 0

0 1.7(1/4)

(1.7-1.7)

CP 3.7 mi 1.7(1/4)

NNW (1.7-1.7)

Gamma 36 K-40 1-131 36 36 1

1411 (24/24)

(1260 - 1660)

< LLD CP 3.7 mi 1462 (12/12) 1319 (12/12)

NNW (1370-1600) (1150-1460)

Cs-134 36 15

< LLD Cs-137 36 18

< LLD Ba-1 40 36 60

< LLD La-140 36 15

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

< 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, Surry County, Virginia - 2006 Docket No. 50-280-281 Page 2 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Hi hest Mean Locations Non-Routine Sampled Total Mean I Distance Mean Mean Reported (Unts)

Type I No. LLD*

Range Name Directioni Range Range Measurements Food Products (pCi/kg wet)

Gamma 3

K-40 1-131 3

7617(3/3)

(3340 - 14740)

Slade 3.2 mi 14740 (1/1)

S (14740-14740) 3 60

< LLD

< LLD Cs-134 3

60 N/A N/A N/A

< LLD

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

0 0

0 Cs-137 3

80

< LLD Well Water (pCiter)

H-3 8

2000

< LLD N/A

< LLD N/A 0

Gamma 8

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 8

15

< LLD 8

15

< LLD 8

30

< LLD 8

15

< LLD 8

30

< LLD 8

15

< LLD 8

30

< LLD 8

1

< LLD N/A N/A N/A 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 N/A N/A Cs-134 8

15

< LLD Cs-137 8

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 - 2006 Docket No. 50-280-281 Page 3 of 6 Medium or Pathway Sampled (units)

Well Water (pCiLiter)

River Water (pCiluter)

-AnalysisTotal Type I No. LLD*

Ba-140 8

60 La-140 8

15 H-3 8

2000 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 La-140 24 15 Indicator Control Locations Location with Highest Mean Locations Non-Routine Mean I Distance Mean Mean Reported Range Name I Direction Range Range Measurements

< LLD

< LLD 2210 (1/4)

(2210 - 2210)

N/A N/A SD

< LLD

< LLD 0.4 mi 2210(1/4)

NW (2210 - 2210)

N/A 0

< LLD 0

103 (6/12)

(88-135)

< 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 N/A 0.4 mi 103 (6/12)

NW (88-135)

< LLD

" LLD

< 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.

23

TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2006 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 ITotal Mean Distance I Mean Mean Reported (Units)

Type No. LLD*

Range Name Direction/

Range Range Measurements Silt Gamma 4

(pC/kg dry)

K-40 4

18600 (212)

CHIC 11.2 mi 20550(2/2) 20550(212) 0 (17000-20200)

WNW (19100-22000) (19100-22000)

Cs-134 4

150

< LLD N/A

< LLD

< LLD 0

Cs-137 4

180 224(2/2)

CHIC 11.2 mi 244 (2/2) 244(2/2) 0 (221 -227)

WNW (158-330)

(158-330)

Th-228 4

1195(2/2)

CHIC 11.2 mi 1370(2/2) 1370(2/2) 0 (1140 -1250)

WNW (1220 - 1520) (1220 - 1520)

Shoreline Gamma 4

Sediment (pCi/kg dry)

K-40 4

5430 (2/2)

HIR 0.6 mi 5430(2/2) 3345(2/2) 0 (4230 - 6630)

N (4230 - 6630) (1380 - 5310)

Cs-134 4

150

< LLD N/A

< LLD

< LID 0

Cs-137 4

180

< LLD N/A

< LLD

< LLD 0

Th-228 4

312 (1/2)

HIR 0.6 mi 312 (1/2) 290 (1/2) 0 (312-312)

N (312-312)

(290-290)

Fish (pCi/kg wet)

Gamma 4

K-40 4

2008 (4/4)

(1890 - 2110)

SD 1.3 mi 2008 (4/4)

NNW (1890 - 2110)

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 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 - 2006 Docket No. 50-280-281 Page 5 of 6 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled ITotal Mean Distance Mean Mean Reported (Units)

Type No. LLD*

Range Name Direction Range Range Measurements Fish Cs-134 4

130

< LID N/A

< LLD N/A 0

(pCi*g wet)

Cs-137 4

150

< LLD N/A

< LLD N/A 0

Oysters Gamma 4

(pCbkg wet)

K-40 4

634(4/4)

POS 6.4 mi 642(2/2)

N/A 0

(414-870)

SSE (414-870)

Mn-54 4

130

< LLD N/A

< LLD N/A 0

Fe-59 4

260

< LLD N/A

< LID N/A 0

Co-58 4

130

< LLD N/A

< LLD N/A 0

Co-60 4

130

< LLD N/A

< LID N/A 0

Zn-65 4

260

< LID N/A

< LLD N/A 0

Cs-134 4

130

< LID N/A

< LLD N/A 0

Cs-137 4

150

< LLD N/A

< LLD N/A 0

Clams Gamma 8

(pCikg wet)

K-40 8

517(6/6)

HIP 2.4 mi 535(2/2) 159(1/2) 0 (390-620)

NE (530-540)

(159-159)

Mn-54 8

130

< LLD N/A

< LLD

< LLD 0

Co-58 8

130

< LLD N/A

< LID

<LLD 0

Fe-59 8

260

< 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 - 2006 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 I Direction Range Range Measurements Clams Co-60 8

130

< LLD N/A

< LLD

< LLD 0

(pCilg wet)

Zn-65 8

260

< LLD N/A

< LLD

< LLD 0

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

2150 (1/1)

(2150 - 2150)

SD 1.3 mi 2150(1/1)

NNW (2150 - 2150)

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 2006 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).

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 1-131

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 RATE Surry Nuclear Power Station, Sunry County, Virginia - 2006 niR/Std Month +/- 2 Signim Page 1 of 1 STATION RRS 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 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 5.2 +/- 0.3 5.1 +/- 0.2 3.9 +/- 1.0 4.3 +/- 0.4 4.2 +/-0.6 4.5 +/-0.6 3.8 +/-0.4 6.4 +/-0.5 4.5 +/-1.1 3.2 +/-0.4 3.6.-t 0.5 4.4.-t 0.7 4.2 +/- 0.5 4.8 +/- 0.7 4.4 +/- 1.1 2.4 +/- 1.2 3.2 +/- 1.0 3.2 +/- 0.3 3.4 +/- 0.8 2.2 +/- 0.6 4.2 +/- 0.3 3.4 +/- 0.5 3.1 +/-t0.8 5.0 +/- 1.2 3.2 +/- 0.6 2.9 +/- 0.6 2.8 +/- 0.4 3.5 +/- 0.5 2.5 +/- 0.4 3.4 +/- 0.1 3.5 +/- 0.6 3.7 +/- 0.3.

4.5 +/- 0.6 4.9 +/- 0.4 3.2 +/- 0.7 5.9 +/- 1.0 3.1 +/- 0.4 3.9 +/- 0.2 6.5 +/- 1.4 3.4 +/- 0.4 3.1 +/- 0.4 4.3 +/-0.0 4.1 +/-0.7 3.9 +/-0.6 4.2 +/-1.0 4.3 +/-0.3 4.2 +/-0.8 3.6 +/-0.8 4.8 +/-0.2 3.3 +/- 0.9 3.1 +/- 0.7 3.7 +/- 0.6 4.1 +/- 0.3 3.4 +/- 0.7 4.1 +/- 0.3 3.3 +/- 1.5 2.3 +/- 0.5 2.6 +/- 0.4 2.2 +/- 0.2 2.6 +/- 0.2 1.9 +/- 0.2 3.3 +/- 0.6 2.3 +/- 0.6 2.4 +/- 1.0 3.3 +/- 0.6 2.4 +/- 0.4 2.3 +/- 0.4 2.1 +/- 0.3 1.9 +/- 0.6 2.1 +/- 0.'5 2.2 +/- 0.5 3.2 +/- 0.8 2.8 +/- 1.3 3.7 +/- 0.3 3.5 +/- 0.6 2.4 +/- 0.8 4.4 +/- 1.9 1.8 +/-0.3 2.9 +/-0.6 5.5 +/-1.1 2.8 +/-0.4 2.9 +/-0.7 4.4 +/- 0.4 4.5 +/- 0.9 3.9 +/- 0.3 3.7 +/- 0.3 4.1 +/- 0.3 4.1 +/- 0.3 3.9 +/- 0.7 5.6 +/- 0.2 4.0 +/- 0.5 3.1 +/- 0.2 3.2 +/- 0.2 3.9 +/- 0.2 3.8 +/- 0.7 4.3 +/- 0.4 3.6 +/- 0.3 2.0 +/- 0.5 2.3 +/- 0.6 2.9 +/- 0.2 2.7 +/- 1.2 1.8 +/- 0.7 3.6 +/- 0.2 2.9 +/- 0.2 3.3 +/- 0.9 3.5 +/- 0.7 3.0 +/- 0.4 2.5 +/- 0.3 2.2 +/- 0.1 2.6 +/- 0.5 2.2 +/- 0.4 2.9 +/- 0.4 2.9 +/- 0.1 3.2 +/- 0.5 3.9 +/- 0.3 3.9 +/- 0.4 2.7 +/- 0.9 5.6 +/- 0.7 2.2 +/- 1.0 3.4 +/- 0.2 5.6 +/- 0.3 3.3 +/- 0.8 2.7 +/- 0.3 5.4:+/- 1.2 4.9 +/- 0.3 3.5 +/- 0.7 4.3 +/- 0.2 4.3 +/- 0.4 4.2 +/- 0.3 4.3 +/- 1.2 6.6 +/- 0.6 4.2 +/- 0.6 3.3 +/- 0.3 3.4 +/- 0.8 4.1 _t 0.3 3.7 +/- 0.3 4.8 +/- 0.7 4.2.+/- 0.6 2.6 +/- 0.2 2.4 +/- 0.8 3.1 +/- 0.6 3.2 +/- 0.9 2.1 +/- 0.2 4.2 +/- 0.8 2.8 +/- 1.1 3.5 +/- 0.8 4.4 +/- 0.3 2.7 +/- 0.5 2.8 +/- 0.2 2.4 +/- 0.3 3.0 +/- 0.5 2.0 +/- 0.7 2.9 +/- 1.2 3.3 +/- 0.2 3.1 +/- 0.3 4.5 +/- 0.7 4.5 +/-t 0.2 2.8 +/- 0.4 6.2 +/- 0.5 2.8 +/- 0.5 3.6 +/- 0.4 6.2 +/- 0.4 3.4 +/- 0.4 2.8 +/- 0.9 4.8 +/- 0.6 4.7 +/- 0.4 3.8 +/- 0.2 4.1 +/- 0.3 4.2 +/- 0.1 4.3 +/- 0.2 3.9 +/- 0.3 5.9 +/- 0.8 4.0 +/- 0.5 3.2 +/- 0.1 3.5 +/- 0.2 4.1 +/- 0.2 3.8 +/- 0.3 4.5 +/- 0.4 3.9 +/- 0.5 2.3 +/- 0.3 2.6 +/- 0.4 2.9 +/- 0.5 3.0 +/- 0.4 2.0 +/- 0.2 3.8 +/- 0.4 2.9 +/- 0.5 3.1 +/- 0.5 4.1 +/- 0.8 2.8 +/- 0.3 2.6 +/- 0.3 2.4 +/- 0.3 2.8 +/- 0.7 2.2 +/- 0.2 2.9 +/- 0.5 3.2 +/- 0.3 3.2 +/- 0.4 4.2 +/- 0.4 4.2 +/- 0.6 2.8 +/- 0.3 5.5 +/- 0.8 2.5 +/- 0.6 3.5 +/- 0.4 6.0 +/- 0.5 3.2 +/- 0.3 2.9 +/- 0.2 28

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TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2006 1.OE.3 pCi/m3 +/- 2 Sigma Page 2 of 2 CLLECTION ISAMPLING LOCATIONS DATE Ss HIR BC ALL CP BASF FE NN July 05 July 11 July 18 July 25 August 01 August 08 August 15 August 22' August 29 September 05 September 12 September 19 September 26 Qtr. Avg. +/- 2 s-d.

27.6 15.3 20.9 21.4 31.0 36.2 24.5 26.4 38.4 9.8 23.6 19.8 26.2

4.8

5.0

4.9

4.9

5.4

5.3

4.8

5.2

5.7

3.9

4.7

4.6

+ 5.1 23.7 17.2 15.7 25.2

4.6

+/- 5.1

4.6

+/- 5.1 24.0 +/- 5.1 39.9 +/- 5.4 25.6 +/- 4.9 24.7 +/- 5.1 36.8 +/- 5.6 25.8 +/- 4.7 10.8 +/- 4.7 23.6 +/- 5.1 22.4 +/- 4.9 21.6 +/- 5.0 36.2 +/- 5.2 19.6 +/- 4.5 25.1 +/- 5.1 30.3 +/- 5.3

<5.5 (b) 18.2 +/- 4.5 15.9 +/- 4.1 19.3 +/- 4.8 23.1 +/-

15.1 +/-

22.8 +/-

23.5 +/-

25.6 +/-

39.5 +/-

26.2 +/-

25.1 +/-

38.7 +/-

12.6 +/-

24.2 +/-

21.6 +/-

26.4 +/-

4.5 4.9 4.9 5.0 5.2 5.3 4.9 5.2 5.7 4.1 4.8 4.6 5.2 23.1 16.2 19.4 22.6 24.2 36.7 21.0 23.0 34.2 7.2 21.5 13.7 18.7 4.5 4.9 4.8 4.9 5.1 5.2 4.6 5.1 5.4 3.9 4.6 4.0 4.7 23.3 +/- 4.6 13.5 +/- 4.8 19.0 +/- 4.8 20.6 +/- 4.9 23.0 +/-5.0 35.2 +/-5.1 20.7 +/-4.6 23.7 +/-5.2 32.6 +/-5.4 9.0 +/- 3.7 22.3 +/- 4.7 15.9 +/- 4.1 19.2 +/- 4.7 29.0 +/- 4.8 17.9 +/- 5.0 24.2 +/- 5.0 26.5 +/- 5.1 23.7 +/- 5.0 44.2 +/- 5.5 20.7 +/- 4.6 27.6 +/- 5.2 35.0 +/- 5.5 12.4 +/- 4.1 24.0 +/- 4.8 20.6 +/- 4.4 25.8 +/- 5.0 22.2 12.8 24.0 28.3 32.1 41.5 26.4 26.2 33.0 8.6 22.8 21.7 29.0 4.5 4.8 5.1 5.3 5.5 5.4 5.0 5.2 5.5 3.7 4.8 4.4 5.3 10.1 24.5 17.8 24.6

3.9

4.7

4.4

5.1 24.7 +/- 15.6 October 03 October 10 October 17 October 24 October 31 November 07 November 14 November 21 November 28 December 05 December 12 December 19 December 26 25.1.

22.2 28.8 16.9 20.2

5.1

3.2

4.8

4.7

4.5 29.7 +/- 5.4 18.6 +/- 4.6 24.9 +/- 5.1 16.6 +/- 2.5 24.9 +/- 5.1 28.6 +/- 5.4 39.1 +/- 5.6 19.9 +/- 4.7 24.3 +/- 12.6 22.8 +/- 12.6 23.8 +/- 16.0 24.1 +/- 5.1 (c) 19.8 +/- 5.3 (e) 17.5 +/- 4.8 23.6 +/- 4.7 23.7 +/- 5.2 16.3 +/- 4.5 22.8 +/- 5.0 16.1 +/- 2.5 20.9 +/- 4.9 33.3 +/- 5.6 37.2 +/- 5.6 22.3 +/- 4.8 23.1 +/- 12.8 21.9 :t 12.5 22.4 +/- 13.3 25.0 +/- 15.0 21.7 +/- 15.4 21.4 +/- 14.0 18.7 +/- 4.7 23.5 +/- 3.4 (d) 20.3 +/-4.3 21.6 +/-5.0 18.8 +/-4.6 21.0 +/-4.9 14.5 +/-2.4 26.1 +/-5.2 31.9 +/-5.6 38.0 +/- 5.7 25.6 +/- 5.0 23.6 +/- 13.2 22.2 +/- 11.4 26.2 26.6 27.3 19.9 18.0 30.1 24.3 23.7 19.2 29.0 37.5 40.8 21.7

+

+/-

+

5.2 3.3 4.8 4.9 4.4 5.4 5.0 5.2 2.6 5.3 5.8 5.7 4.7 26.3 24.0 29.4 15.5 18.6 21.3 19.6 17.5 17.3 22.1 34.9 31.6 21.1

5.1

3.2

4.8

4.6

4.3

4.9

4.6

4.7

2.5

4.9

5.6

5.3

4.6 21.6 +/- 4.9 20.8 +/- 3.1 27.6 +/- 4.8 15.1 +/- 4.6 15.9 +/- 4.2 26.3 +/- 5.1 16.1 +/- 4.5 23.7 +/- 5.0 16.3 +/- 2.4 22.3 +/- 4.9 28.1 +/- 5.4 34.4 +/- 5.4

<6.6 (h) 22.4 :t 12.0 21.5 +/-t 11.0 26.6 +/- 5.1 19.1 +/- 3.0 34.6 +/- 5.1 18.5 +/- 4.7 23.4 +/- 4.6 27.3 +/- 5.2 18.7 +/- 4.6 23.6 +/- 5.0

<6.3 (g) 25.4 +/- 5.1 33.8 +/- 5.6 33.6 +/- 5.4 19.5 +/- 4.6 25.3 +/- 12.1 23.8 +/- 12.7 28.4 26.6 32.4 18.9 25.2 24.6 18.7 20.8 16.4 25.4 28.0 34.0 19.4

+

+/-

+

5.2 3.3 5.0 4.8 4.8 25.5 +/- 15.7 25.3 +/- 16.9

5.2

4.6

4.9

2.4

+/-

5.2 5.5 5.5 4.6 Qtr. Avg. +/-2 s.d.

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

26.5 +/- 13.5 22.7 +/- 13.5 23.0

11.9 20.9

11.8 24.5 +/- 10.9 23.1 +/- 12.6 30

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m mm-m m-m TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2006 1.OE-3 pCi/m3 +/- 2 Sigma Page 1 of 2 COLLECTION I SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C January 03 January 10 January 17 January 24 January 31 February 06 February 14 February 21 February 28 March 07 March 14 March 21 March 28 April 04 April 11 April 18 April 25 May 02 May 09 May 16 May 23 May 30 June 06 June 13 June 20 June 27

<27

<32

<30

<28

<47

<22

<32

<36

<28

<26

<27

<29

<25

<24

<30

<32

<21

<25

<26

<24

<28

<26

<17

<33

<26

<28

<27

<40

<31

<29

<30

<25

<30

<29

<34

<28

<24

<23

<24

<22

<23

<21

<24

<33

<20

<28

<26

<34

<25

<30

<24

<30

<27

<38

<28

<29

<25

<24

<31

<26

<45

<32

<27

<21

<34

<24

<21

<27

<24

<29

<20

<24

<23

<39

<25

<36

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<27

<20

<40

<30

<34

<28

<27

<25

<24

<36

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<24

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<34

<19

<21

<24

<23

<30

<31

<21

<25

<40

<22

<30

<26

<28

<42

<27

<35

<38

<25

<28

<26

<34

<26

<29

<30

<28

<21

<23

<28

<20

<24

<28

<31

<35

<27

<29

<31

<23

<29

<41

<33

<36

<40

<25

<29

<25

<27

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<27

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<18

<28

<32 (a)

<25

<28

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<20

<26

<31

<26

<21

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<20

<23

<30

<35

<23

<24

<26

<29

<39

<27

<31

<36

<30

<28

<45

<32

<35

<48

<28

<24

<25

<27

<29

<27

<29

<38

<21

<29

<25

<21

<29

<25

<23

<29

<26 32

TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2006 1.0E-3 pCi/m3 +/- 2 Sigma Page 2 of 2 COLLECTION i SAMPLING LOCATIONS DATE I

SS HIR BC ALL CP BASF FE NN July 05 July 11 July 18 July 25 August 01 August 08 August 15 August 22 August 29 September 05 September 12 September 19 September 26 October 03 October 10 October 17 October 24 October 31 November 07 November 14 November 21 November 28 December 05 December 12 December 19 December 26

<38

<29

<38

<23

<35

<33

<25

<29

<25

<27

<36

<32

<35

<34

<23

<17

<21

<24

<31

<23

<25

<20

<38

<34

<33

<25

<33

<18

<22

<34

<19

<26

<32

<23

<32

<27

<38 (b)

<25 (d)

<31

<26

<34

<32

<28

<37

<18

<29

<26

<23

<26

<39

<26

<36

<42 (c)

(e)

<25

<42

<37

<32

<41

<21

<34

<35

<22

<24

<28

<21

<32

<30

<26

<41

<44

<32

<26

<20

<21

<28

<24

<26

<20

<21

<37

<39

<29

<38

<20

<29

<31

<23

<27

<34

<19

<34

<25

<29

<38

<32

<26

<20

<19

<23

<34

<28

<24

<21

<18

<38

<43

<25

<39

<22

<28

<39

<21

<26

<25

<39

<28

<38

<34

<26

<25

<37

<21

<40

<22

<25

<44

<20

<29

<25

<19

<35

<30

<37

<24

<38

<36

<27

<33

<38

<27

<38

<24

<29

<35

<18.

<29

<28

<19

<31

<37

<40

<28

<35

<28

<18

<24

<26

<31

<33

<24

<29

<21

<43

<20

<23

<29

<26

<20

<24

<34

<22

<26

<35

<23

<31

<17

<22

<39

<23

<29

<24

<33

<26

<23

<41 (g)

<19

<34

<39

<67 (f)

<24

<23

<25

<44 33

Table 3-4 Footnotes (a) Air sampler not operational at sample change out due to blown fuse. Fuse replaced. Sampler had 120.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months run time versus typical run time of 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months . Volume was sufficient to meet required LLD.

(b) Air sampler not operational at sample change out.

Sampler had been submerged due to flooding conditions from a Nor'Easter.

Sample was saturated and not usable for analysis.

Condition Report submitted to document exception to REMP requirements.

(c) Air sampler not operational at sample change out on. Sample volume based on elapsed timer indication of 156.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Volume was sufficient to meet required LLD.

Power pole was snapped due to vehicle accident. Power pole had been temporarily repaired with support brackets. Unable to reinstall sampler on pole due to temporary repair brackets.

(d) Air sampler not operational at sample change out on. Sample volume based on elapsed timer indication of 32.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Volume and count time were sufficient to meet required LLD. The power strip in the sampler housing was defective and replaced.

(e) Air sampler not operational due to inability to reinstall sampler on temporarily repaired power pole. Power pole not replaced due to extended recovery efforts from 10/7/06 Nor'Easter. Condition Report submitted to document exception to REMP requirements.

(f) Air sampler not operational at sample change out due to blown fuse. Fuse replaced. Sampler had 82.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months run time. Volume was sufficient to meet required LLD.

(g) Air sampler not operational at sample change out due to pump failure. Sample volume based on sampler timer indication of 146.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Volume was sufficient to meet required LLD.

34

TABLE 3-5: G4AMMAiFfEMTfER CONCFN1RA4TION IN FILTERED AIR Surry Nuclear Povmer Station, Surry County, Virginia -2006 1.OE3 pG/m3 +/- 2 Signu Page 1 of 1 LATIfSPUNG RST SECOD QTERM FURTUM AV_2 AA%

u=LClONS NUCUE QUARTER QUARTER QUARTER QUARTER

+/- 2 GMA ss Cs-134 Cs-137 Be-7 HIR Cs-134 Cs-137 Be-7 BC Cs-134 Cs-137 Be-7 ALL Cs-134 Cs-137 Be-7

<1.6

<3.1 148 +/- 34

<2.5

<3.4 162 +/- 34

<2.4

<3.2 119 +/- 31

<2.5

<2.9 136 +/- 34

<1.4

<3.1 99_+/-32

<0.6

<0.6 155 +/- 19

<1.8

<3.1 172 +/- 36

<1.6

<3.0 171 +/- 37

<1.3

<1.2 163 +/- 32

<1.5

<1.4 142 +/- 33

<0.9

<1.7 167 +/- 33

<1.5

<1.1 132 +/- 32

<1.6

<1.4 138 +/- 33

<1.7

<0.8 172 +/- 33

<1.8

<1.2 187 +/- 37

<1.2

<1.3 183 +/- 36

<1.6

<1.4 163 +/- 36

<1.5

<1.2 140 +/- 31

<1.4

<1.7 125 +/-32

<1.1

<1.0 138 +/- 26

<1.0

<1.5 122 +/-+25

<1.1

<0.9 115 +/- 27

<1.3

<1.0 163 +/- 29

<1.3

<1.4 160 +/- 27

<1.1

<0.8 112 +/- 28

<1.3

<1.4 102 +/- 37

<1.6

<1.6 158 +/- 48

<1.5

<1.7 114 +/- 41

<1.4

<1.1 91

+/- 36

<1.2

<1.7 93+/-38

<1.1

<1.4 114 +/- 40

<1.5

<1.7 134 +/- 44 147 +/-24 137 +/-25 142 +/-24 130 +/- 11 113 +/-21 134 +/- 36 CP CS-134 CS-137 Be-7 BASF Cs-134 Cs-137 Be-7 FE Cs-134 Cs-137 Be-7 NN-C Cs-134 Cs-137 Be-7 159+/-32 162 +/-21 35

TABLE3-6 GAIMM EMTEAND STRONTIUMCONCENRATIONS INAIJLK Surry Nuclear Power Station, Surry County, Virginia - 2006 p0/Liter +/- 2 Signia Page 1 of 3 NCD

PAKALCO AL NUICUDE EPPS PARKWAY VALWAMS-C JANUARY Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 FEBRUARY Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 MARCH Cs-134 Cs-137 Ba-140 La-i 40 1-131 K-40 Sr-89 Sr-90 APRIL Cs-134 Cs-137 Ba-140 La-140 1-131 K-40

<8

<7

<10

<1 1360 +/- 140

<10

<7

<10

<11

<1 1520 +/- 170

<6

<12

<14

<1 1490 +/- 120

<5

<10

<11

<1 1390 +/- 100

<8

<12

<13

<1 1450 +/- 140

<8

<11

<12

<14

<1 1600 +/- 200

<6

<12

<13

<1 1370 +/- 110

<7

<2

<5

<9

<10

<1 1417 +/- 97

<7

<12

<13

<1 1150 _ 130

<8

<11

<13

<1 1460 +/- 160

<6

<11

<13

<1 1380 +/- 120

<5

<10

<11

<1 1361 +/- 98 36

TABLE 3-6:

M E

AND STRONTIUM CONCENTRATIONS IN MILK Surry Nuclear Power Station, Surry County, Virginia - 2006 p0/Liter +/- 2 Sigim Page 2 of 3 ICOLONIAL NUCUDE EPPS PARKWAY MWIUAMS-C MAY Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 JUNE Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 Sr-89 Sr-90

<7

<8

<13

<15

<1 1340 +/- 130

<7

<6

<11

<12

<1 1330 +/- 130

<8

<6

<9

<1 1430 +/- 140

<10

<8

<7

<8

<1 1560 +/- 170

<9 1.71

+/- 0.99

<8

<7

<12

<13

<1 1450 +/- 150

<8

<10

<12

<1 1380 +/- 140

<8

<7

<11

<12

<1 1310 +/- 140

<4

<6

<7

<1 1333 +/- 74 JULY Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 AUGUST Cs-134 Cs-137 Ba-140 La-140 1-131 K-40

<8

<7

<12

<14

<1 1270 +/- 170

<7

<11

<12

<1 1350 +/- 130

<10

<9

<13

<15

<1 1320 +/- 180

<8

<6

<10

<11

<1 1280 +/- 140 37

TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Nuclear Power Station, Surry County, Virginia - 2006 pCi/Liter +/- 2 Sigma Page 3 of 3 COLONIAL NUCUDE IEPPS PARKWAY WILUAMS-C SEPTEMBER Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 Sr-89 Sr-90 OCTOBER Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 NOVEMBER Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 DECEMBER Cs-134 Cs-137 Ba-140 La-140 1-131 K-40 Sr-89 Sr-90

<7

<6

<8

<9

<1 1270 +/- 140

<8

<7

<9

<10

<1 1260 +/- 130

<5

<9

<10

<1 1430 +/- 110

<6

<5

<10

<12

<1 1322 +/- 94

<5

<9

<10

<1 1460 +/- 110

<8

<2

<8

<10

<12

<1 1490 +/- 150

<6

<10

<11

<1 1440 +/- 120

<6

<4

<8

<10

<1 1493 +/- 87

<9

<2

<7

<6

<8

<10

<1 1310 +/- 120

<7

<11

<13

<1 1300 +/- 130

<6

<5

<11

<13

<1 1320 +/- 110

<4

<8

<10

<1 1299 +/- 79 38

TABLE 3-7: G4MMA FM CONCENTRATIONINFOOD PRODUCTS Surry Nuclear Power Station, Surry County, Virginia - 2006 pC/kg (wet) +/-2 Sigma Page 1 of 1 SAMPLING COLLECliON SAMPLE I S14C_3 LOCATIONS DATE TYPE Cs-134 Cs-i37 1-131 K-40 BROCK 11/07/2006 Corn

<22

<18

<28 3340 +/- 340 FARM 11/16/2006 Peanuts

<46

<44

<53 4770 +/- 860 SLADE 12/05/2006 Soybeans

<28

<29

<36 14740 +/- 790 FARM 39

TABLE 3-8. GAMMA EMITIER AND TRHIUMCONCENTRATIONS IN IELL WATER Sunry Nuclear Power Station, Surry County, Virginia - 2006 p(/Liter_ +/-2 Sigma Page 1 of 1 SAMPUNG COLLECnONI LOCATIONS DATE ISOTOPE SS 03/21/2006 06/20/2006 09/19/2006 12/12/2006 03/21/2006 06/20/2006 09/19/2006 12/12/2006 03/21/2006 06/20/2006 09/19/2006 12/12/2006 Ba-140

<10

<8

<10

<7 Fe-59

<16

<10

<11

<11 Zn-65

<14

<11

<12 Ba-140

<10

<7

<11

<11 Fe-59

<13

<9

<13

<10 Zn-65

<15

<9

<13

<13 CO-58

<8

<5

<6

<5 1-131

<1

<1 Zr-95

<11

<7

<9

<9 CD-58

<7

<4

<7

<6 1-131

<1

<1 Zr-95

<12

<7

<11

<10 Co.O

<7

<5

<6 La-140

<11

<9

<11

<8

--3

<1400-

<1300

<1500

<330 Co-60

<7

<4

<8

<9 La-140

<12

<7

<12

<13 K-'-3

<1400

<1300

<1500

<330 Cs-134

<8

<6

<5

<6 Mn-54

<7

<6

<5

<5 Cs-137

<6

<5

<5 Nb-95

<8

<6

<5

<5 HIR 03/21/2006 06/20/2006 09/19/2006 12/12/2006 03/21/2006 06/20/2006 09/19/2006 12/12/2006 03/21/2006 06/20/2006 09/19/2006 12/12/2006 Cs-134

<7

<5

<7

<7 Mn-54

<7

<4

<6

<6 Cs-137

<7

<5

<6

<6 Nb-95

<8

<5

<7

<7 40

TABLE 3-9:

M EMI17ER AND TRITIUM CONCENTRATIONS IN RIVER WATER Surry Nuclear Power Station, Surry County, Virginia - 2006 pC/Liter_ +/-2 Sigim Page 1 of 2 SAMPiNG COLLECTION LOCATIONS DATE I

ISOTOPE SD 01/24/2006 02/22/2006 03/28/2006 04/2512006 05/16/2006 06/13/2006 07/18/2006

.08/15/2006 09/19/2006 10/17/2006 11/21/2006 12/12/2006 01/24/2006 02/22/2006 03/28/2006 04/25/2006 05/16/2006 06/13/2006 07/18/2006 08/1512006 09/19/2006 10/17/2006 11/21/2006 12/12/2006 01/24/2006 02/22/2006

'03/28/2006 04/25/2006 05/16/2006 06/13/2006 07/18/2006 08/15/2006 09/19/2006 10/17/2006 11/21/2006 12/12/2006 Ba-140

<7

<8

<10

<9

<10

<8

<7

<6

<9

<7 Fe-59

<7

<9

<11

<10

<11

<10

<9

<8

<9

<6

<10

<8 Zn-65

<9

<8

<13

<24

<13

<12

<10

<7

<11

<9 CD-58

<4

<8

<7

<6

<5

<4

<5

<3

<5

<4 1-131

<6

<9

<10

<9

<8

<9

<10

<6 Zr-95

<7

<10

<11

<8

<7

<6

<7

<5

<8

<8 CO0 O

<4

<5

<9

<7

<6

<5

<4

<5

<3

<6

<4 La-140

<8

<9

<12

<10

<11

<10

<9

<8

<7

<10

<8 1-1-3

<1300

<1400 2210 +/- 950 Cs-134

<4

<7

<6

<5

<4

<5

<3

<6

<4 Mn-54

<4

<6

<5

<4

<5

<4

<3

<6

<4 Cs-137

<4

<7

<6

<5

<4

<5

<3

<6

<4 Nb-95

<6

<5

<7

<9

<8

<5

<4

<5

<4

<5

<4 K-40

<66

<59 135 +/- 63 113 +/- 57

<83 93 +/- 51 88 +/-44 96 +/- 39 94+/-38

<40

<78

<25 41

TABLE 3-9: GAMMA EMIATER AND TRITIUM CONCENTRATIONS IN RIVER WATER Surry Nuclear Power Station, Surry County, Virginia - 2006 pCi/Liter +/- 2 Signi Page 2 of 2 SAMPUNG COLLECTION LOCATIONS DATE ISOTOPES Ba-140 Co-58 Co-60 Cs-134 Cs-137 sw-C 01/24/2006

<8

<4

<5

<4 02/22/2006

<8

<4

<5 03/28/2006

<10

<7

<6

<6 04/25/2006

<9

<6

<7

<6 05/16/2006

<8

<5

<6

<5 06/13/2006

<9

<7

<6

<7

<5 07/18/2006

<7

<5

<4 08/15/2006

<8

<4

<5

<4 09/19/2006

<8

<6

<7

<5 10/17/2006

<7

<4

<3 11/21/2006

<7

<4

<5

<4

<5 12/12/2006

<7

<4

<4 Fe-59 1-131 La-140 Mn-54 Nb-95 01/24/2006

<9

<8

<10

<4

<4 02/22/2006

<8

<9

<4

<4 03/28/2006

<13

<9

<12

<6

<8 04/25/2006

<12

<8

<10

<7

<9 05/16/2006

<12

<9

<10

<5

<6 06/13/2006

<10

<9

<10

<6

<8 07/18/2006

<10

<8

<5

<5 08/15/2006

<9

<7

<9

<4

<5 09/19/2006

<12

<10

<9

<5

<6 10/17/2006

<8

<10

<8

<4

<5 11/21/2006

<11

<9

<8

<4

<5 12/12/2006

<8

<7

<8

<4

<4 Zn-65 Zr-95 HI-3 K-40 01/24/2006

<10

<7

<63 02/2212006

<9

<6

<54 03/28/2006

<13

<11

<1300

<94 04/25/2006

<23

<10

<75 05/16/2006

<10

<9

<77.

06/13/2006

<11

<9

<1300

<110 07/18/2006

<13

<7

<62 08/15/2006

<10

<7

<59 09/19/2006

<11

<9

<1400

<73 10/17/2006

<8

<6

<46 11/21/2006

<10

<8

<61 12/12/2006

<8

<7

<1300

<57 42

TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT Surry Nuclear Power Station, Surry County, Virginia - 2006 pi/kg (dry) +/- 2 Sigm Page l of I SAMPUNG COLLECTIONI LOCATIONS DATE Cs-134 Cs-i37 Th-228 K-40 SD 03/30/2006 10/03/2006 CHIC-C 03/30/2006 10/03/2006

<100

<92

<74

<130 221 +/- 84 1250 +/- 240 227 +/- 91 1140 +/- 220 158 +/- 55 1520 +/- 150 330 +/- 100 1220 +/- 240 20200 +/- 1900 17000 +/- 1700 19100 +/- 1300 22000 +/- 2200 43

TABLE 3-11: GAMMA EMITER CONCENTRATIONS IN SHORELINE SEDIMENT Surry Nuclear Power Station, Suny County, Virginia - 2006 pGdkg (dry) +/- 2 Sigi*

SAMPUNG COLLECTION LOCATIONS DATE HIR 02/14/2006 08108/2006 CHIC-C 02114/2006 08/08/2006 Page 1 of 1 Cs-134

<45

<34 Cs-137

<30

<43 Th-228 312 +/- 68

<130 K-40 4230 +/- 550 6630 +/- 930

<30

<40

<23

<60

<97 5310 +/- 500 290 +/- 150 1380 +/- 540 44

TABLE 3-12: GAMMA EMITFER CONCENTRATIONIN FISH Surry Nuclear Power Station, Surry County, Virginia - 2006 pCi/kg (wet) +/- 2 Sigma I

Page I of 1 SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE SD 04/11/2006 04/11/2006 10/05/2006 10/05/2006 04/11/2006 04/11/2006 10/05/2006 10/05/2006 Catfish White Perch Catfish White Perch Catfish White Perch Catfish White Perch K-40 2110 +/- 510 1890 +/- 390 2040 +/- 280 1990 +/- 290 CO-58

<38

<33

<25

<22 Fe-59

<82

<61

<51

<42 CO-60

<38

<30

<19

<21 Mn-54

<42

<30

<20

<19 Cs-134

<39

<27

<19

<18 Zn-65

<87

<62

<48

<48 Cs-137

<31

<29

<19

<20 45

TABLE 3-13: GAMMA EAMITTER CONCENTRATIONS IN OYSTERS Surry Nuclear Power Station, Surry County, Virginia - 2006 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTIONI LOCATIONS DATE I

ISOTOPE POS K-40 03/30/2006 414 +/- 93 10/03/2006 870 +/- 200 03/30/2006 10/03/2006 Cs-137

<8

<18 Co-58

<10

<21 Fe-59

<26

<47 Co-58

<9

<15 Fe-59

<22

<43 CO-60

<10

<18 Mn-54

<9

<19 Co-60

<7

<12 Mn-54

<7

<14 Cs-134

<8

<17 Zn-65

<18

<49 Cs-134

<8

<14 Zn-65

<17

<32 K-40 MP 03/30/2006 472 +/- 80 10/03/2006 780 +/- 160 03/30/2006 10/03/2006 Cs-137

<7

<15 46

TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Surry Nuclear Power Station, Surry County, Virginia - 2006 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION1 LOCATIONS DATE I

ISOTOPE HIP K-40 03/30/2006 530 +/- 150 10/03/2006 540 +/- 230 03/30/2006 10/03/2006 Cs-137

<12

<23 K-40 SD 03/30/2006 620 +/- 120 10/03/2006 390 +/- 130 03/30/2006 10/03/2006 Cs-137

<10

<13 Co-58

<16

<25 Fe-59

<42

<62 Co-58

<12

<13 Fe-59

<29

<30 Co-58

<10

<19 Fe-59

<23

<52 Co-58

<10

<24 Fe-59

<27

<52 Co-60

<14

<34 Mn-54

<13

<22 Co-60

<10

<13 Mn-54

<9

<13 Co-60

<8

<16 Mn-54

<8

<17 Co-60

<9

<21 Mn-54

<9

<21 Cs-1 34

<13

<23 Zn-65

<28

<55 Cs-1 34

<10

<14 Zn-65

<22

<28 Cs-1 34

<8

<19 Zn-65

<19

<43 Cs-1 34

<10

<23 Zn-65

<19

<50 K-40 CHIC-C 03/30/2006 159 +/- 86 10/03/2006

<270 03/30/2006 10/03/2006 Cs-137

<7

<19 K-40 LC 03/30/2006 524 +/- 99 10/03/2006 500 +/- 200 03/30/2006 10/03/2006 Cs-137

<9

<19 47

TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS Surny Nuclear Power Station, Surry County, Virginia - 2006 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION1I LOCATIONS DATE I

ISOTOPE K-40 SD 06/21/2006 2150 +/- 170 Cs-137

<12 Co-58

<14 Fe-59

<31 Co-60

<11 Mn-54

<11 Cs-134

<12 Zn-65

<24 48

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2006 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 2006 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.

On October 7, 2006, 15 inches of rain fell in the vicinity of the Surry Power Station due to a Nor'Easter. This abnormal amount of rain resulted in flooding conditions and extensive power outages.

Two deviations from the Radiological Environmental Monitoring Program requirements occurred because of this storm.

The Hog Island Reserve (HIR) air sampling station was inoperable for the sampling period of 10/03/06 through 10/10/06 as a result of physical damage to the sampler from flooding conditions. In addition, the particulate and charcoal filters were saturated, and therefore, not usable for analyses. Due to this inoperability, the required gross beta, iodine-131 and gamma isotopic analyses were not performed.

The HIR sampling station was returned to service on 10/10/06 following replacement of the air sampler. Other than replacement of the sampling equipment, no other plans to prevent recurrent storm damage could be implemented.

The second deviation was also a failure to perform the required gross beta, iodine-131 and gamma isotopic analyses at the Bacon's Castle (BC) air sampling station for two consecutive sampling periods, 10/10/06 through 10/24/06. A vehicle accident damaged the power pole that the air sampler was attached to. A temporary repair was made to the power pole to restore power. The temporary repair was not suitable for reinstallation of the air sampler to the pole. Due to the extensive regional recovery efforts from the 10/07/06 Nor'Easter, replacement of the power pole, electric lines and transformer was delayed until 10/22/06. The BC air sampler was returned to service on 10/23/06. No other plans to prevent loss of power supply equipment could be implemented.

The following is a discussion and summary of the results of the environmental 49

measurements taken during the 2006 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 sensitive 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. This is due to the increased sensitivity of the replacement TLD that provides a greater response to ambient radiation and improved statistical analysis.

The six-year trend since TLD type replacement indicates a gradual and across the board 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 four-year trend indicates a stable trend. These trends will continue to be monitored.

50

Rgure 4-1: DIRECT RADIATION MEASUREMBE*T TLD RESULTS 8

7 -

C VC4-E2 0

0 S

N Ote Bn N

0 A o Site Boundiry -e5 Mile As-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.

51

Figure 4-2:2006 GROSS BETA IN AIR PARTICULATES 0.045 0.040-0.035 0.030 -AL 0.025 MAI',

.1 li A/\\

g 0 6 0.0 1 5 4

0.010 0.005 0.000 N,-..

I

-- 4---- Avg Indicator.. A-- - Ave Control Figure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TRENID 1.OE+00 1.OE-01 I.OE-02 1.0 E -0 3 I..

ý.

I..

N-00 0\\

0 C'4 m

g f

W 0

N 00 0',

m l

c

~

00 00 00 0

I0d0cato0, 0A 0ý 0g%

CO Rud aCl C

C14 C

-m-Avg Indicator Avg Control -

Avg-Pre Op -

Required LLD i

52

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.

Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected.

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 2006.

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 1.71 pCi/L. The average Sr-90 concentration for the ten year period of 1997 to 2006 is 1.88 pCi/L. The Sr-90 detected is not a part of station effluents but, rather, a product of nuclear weapons testing fallout.

53

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 two 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. Tritium was detected in one of eight samples at 2,210 pCi/liter. This concentration represents 7.4% of the 30,000 pCi/liter NRC reporting level concentration. The tritium was detected at the station discharge canal indicator sample location.

The water in the discharge canal is further diluted by the river water beyond the discharge structure.

No tritium or gamma emitting radionuclides were detected in the control river water samples.

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.

54

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 2006, cesium-137 was detected with an average indicator location concentration of 224 pCi/kg and an average control location concentration of 244 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 1.0E+04 1.OE+03 1.0E+02 1.OE+01 1.0E+00 c.I 00 0

C14

ý 00 0D r4

ý V 00 N

r 00 00 00 00 00 a,,

O O

C, O-O-

O-O\\

o l

O-O\\

Ox

\\o O

S Di O\\

hu OI Control - Chickahominy 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 2006.

55

Rgure 4-5: CESIUM-1 37 IN SILT 1.OE+04 Il.OE+0364 U

L.OE+02 C It t0 00 0

C i

0 00 0

(q

't 0

00 rN r-N-

00 00 00 00 00 cv' a,'

0a, 0

-*---Control

- Chickahomniny -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 56

analyses are presented in Table 3-13.

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

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

4.13 Clams Clams are analyzed from 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.

57

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2006 Location HIR BC Description Airborne; Gross beta, Air Particulate &

Air iodine-131 Airborne; Gross beta, Air Particulate &

Air iodine-131 Date of Sampling 10/10/06 10/17/06, 10/24/06 Reason(s) for Loss/Exception This continuous air sampler was out of service for the sampling period of 10/03/06 through 10/10/06. The sampler was flooded from heavy rains due to a Nor'Easter. The particulate filter and charcoal cartridge samples were saturated and not suitable for radioanalysis.

This continuous air sampler was out of service for two sampling periods, 10/10/06 through 10/24/06. The power pole that the sampler was attached to was destroyed by a vehicle accident. Replacement of the power pole, electric lines and transformer was delayed due to extensive regional recovery efforts from the 10/07/06 Nor'Easter.

58

6. CONCLUSIONS The results of the 2006 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 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 2006 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-90 was detected in one of four samples this year at a concentration of 1.71 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 2006.

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 six samples. Tritium was detected in one of eight samples with a concentration of 2,210 pCi/liter.

This represents 7.4% of the NRC reporting level concentration. Because river water is not used for drinking water or for crop irrigation, there is a reduced dose consequence to the public from this pathway.

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

The presence of Cs-137 is attributable to residual weapons testing fallout; 59

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 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.

60

REFERENCES 61

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.

62

APPENDICES 63

APPENDIX A: LAND USE CENSUS Year 2006 64

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January 1 to December 31, 2006 Page 1 of 1 i

I I

Nearest Nearest Nearest Nearest Sector Direction Resident Garden" I

Cow Goat A

B C

D E

F G

H J

K L

M N

P Q

R N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 4.1 @ 100 1.9 @ 320 4.7 @ 350 (a)

(a)

(a) 4.4 @ 1630 1.7 @ 1810 2.3 @ 2120 2.3 @ 2210 0.4 @ 2440 3.1 @ 2600 4.9 @ 2830 4.6 @ 3210 3.8 @ 3380 (a) 1.9 @ 320 4.9 @ 560 (a)

(a)

(a) 1.8 @ 1830 4.3 @ 1930 3.6 @ 2230 3.6 @ 2450 3.4 @ 2600 (a)

(a) 4.4 @ 3340 (a)

(a)

(a) 4.8 @ 2000 (a)

(a)

(a) 3.7 @ 3360 (a)

(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 65

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2006 66

12VTRODUCTION 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 1 st 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, fiter 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 2006.

A total of 104 analysis results were obtained with 103 passing acceptance criteria, a 99% success rate.

The unsuccessful analysis was Sr-90 in the filter matrix during the 2nd quarter.

AREVA NP submitted Condition Report CR 06-16 to document their investigation of the unsuccessful analysis.

The sample was reprocessed and the result was acceptable, 10.9 pCi and a Ratio of 0.87. AREVA NP also revised the analysis 67

process by increasing the frequency of preparing blanks for background subtraction and extending the Y-90 in-growth phase to improve counting statistics.

68

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY QA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 1 OF 4) 1 st Quarter Identification Reported Known 2006 Number Matrix Nuclide Units Value (a)

Value (b)

Ratio (c)

Evaluation (d)

E4889-162 Milk 1-131LL 1-131 Ce-1 41 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E4890-162 Milk Sr-89 Sr-90 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 81.8 77.4 101 277 113.8 86.7 100 94.6 90.7 172.2 125 pCi/L 79.7 pCi/L 10.6 E4884-162 Water Gr-Beta pCi/L 265 78 78.8 104 280 121 88.8 105 93.3 86.6 176 128 99.2 10.8 262 67.4 67.4 86.8 234 101 74.3 87.5 78.1 72.4 148 107 99.4 10.8 1.05 0.98 0.97 0.99 0.94 0.98 0.95 1.01 1.05 0.98 0.98 0.80 0.98 1.01 0.98 0.98 0.96 0.93 0.91 0.99 0.97 0.96 1.01 0.99 0.96 0.82 0.94 1.07 A

A A

A E4885-162 Water 1-131LL 1-131 Ce-1 41 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E4886-162 Water Sr-89 Sr-90 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 65.8 66.3 83 217 91.9 73.3 84.7 74.7 73.2 146.7 102.5 pCi/L 82 pCi/L 10.2 E4888-162 Filter Gr-Beta pCi 104.5 97.3 Footnotes are on page 4 of 4.

69

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 2006 Number Matrix Nuclide Units Value (a)

Value (b)

Ratio (c)

Evaluation (d)

E5017-162 Milk 1-131LL 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E5013-162 Water H-3 E5014-162 Filter Gr-Beta E5015-162 Filter Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E5016-162 Filter Sr-89 Sr-90 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 67 62 180.8 248 120.1 117.3 97.3 150.5 95.4 183.9 126.2 63.2 63.2 184 259 127 117 100 146 93.6 185 129 pCi/L 5830 6000 pCi 103.8 96.8 1.06 0.98 0.98 0.96 0.95 1.00 0.97 1.03 1.02 0.99 0.98 0.97 1.07 0.99 1.01 0.95 1.06 1.03 1.01 0.98 1.00 0.97 0.90 0.57 A

A A

U pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi 91.6 131.7 60.5 62.9 52 74.5 46.4 93.4 63 146.6 7.0 92.8 131 63.9 59.3 50.6 73.9 47.3 93.6 65 163 12.3 Footnotes are on page 4 of 4.

70

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 2006 Number Matrix Nuclide Units Value (a)

Value (b)

Ratio (c)

Evaluation (d)

E5094-162 Milk 1-131LL pCi/L 79.9 73.8 1.08 A

1-131 pCi/L 72.5 73.8 0.98 A

Ce-141 pCi/L 85.5 86 0.99 A

Cr-51 pCi/L 288 282 1.02 A

Cs-134 pCi/L 84.8 85 1.00 A

Cs-137 pCi/L 171 175 0.98 A

Co-58 pCi/L 106.0 109 0.97 A

Mn-54 pCi/L 112 113.0 0.99 A

Fe-59 pCi/L 45.3 43.7 1.04 A

Zn-65 pCi/L 146 145 1.01 A

Co-60 pCi/L 129 134 0.96 A

E5095-162 Milk Sr-89 pCi/L 84.0 89.2 0.94 A

Sr-90 pCi/L 12.4 12.4 1.00 A

E5090-162 Water Gr-Beta pCi/L 253 273 0.93 A

E5091-162 Water 1-131LL pCi/L 84.4 79.9 1.06 A

1-131 pCi/L 77.3 79.9 0.97 A

Ce-141 pCi/L 84.5 88 0.96 A

Cr-51 pCi/L 287 288 1.00 A

Cs-134 pCi/L 85.6 87 0.98 A

Cs-137 pCi/L 174 179 0.97 A

Co-58 pCi/L 108 112 0.96 A

Mn-54 pCi/L 116 115 1.01 A

Fe-59 pCi/L 47 44.7 1.05 A

Zn-65 pCi/L 146 148 0.99 A

Co-60 pCi/L 130.

137 0.95 A

E5093-162 Filter G r-Beta pCi 142 147 0.97 A

71

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 2006 Number Matrix Nuclide Units Value (a)

Value (b)

Ratio (c)

Evaluation (d)

E5227-162 Milk I-131LL pCi/L 71.0 70.8 1.00 A

1-131 pCi/L 64.8 70.8 0.91 A

Ce-141 pCi/L 277.7 294

.0.94 A

Cr-51 pCi/L 430.7 433 0.99 A

Cs-134 pCi/L 141.4 147 0.96 A

Cs-137 pCi/L 233.9

.237 0.99 A

Co-58 pCi/L 83.1 83.8 0.99 A

Mn-54 pCi/L 110.6 111 1.00 A

Fe-59 pCi/L 82.3 79.7 1.03 A

Zn-65 pCi/L 171.4 164 1.05 A

Co-60 pCi/L 273.1 281 0.97 A

E5222-162 Water H-3 pCi/L 14570 14800 0.98 A

E5223-162 Water Sr-89 pCi/L 68.8 72.6 0.95 A

Sr-90 pCi/L 5.56 5.9 0.94 A

E5224-162 Filter Gr-Beta pCi 209.6 203 1.03 A

E5225-162 Filter Ce-141 pCi 179.0 185 0.97 A

Cr-51 pCi 277.9 273 1.02 A

Cs-134 pCi 89.1 92.7 0.96 A

Cs-137 pCi 158.8 149 1.06 A

Co-58 pCi 54.0 52.8 1.02 A

Mn-54 pCi 71.2 69.8 1.02 A

Fe-59 pCi 51.0 50.2 1.02 A

Zn-65 pCi 104.3 103 1.01 A

Co-60 pCi 166.7 177 0.94 A

E5226-162 Filter Sr-89 pCi 69.5 74.2 0.94 A

Sr-90 pCi 6.46 6.06 1.07 A

(a) AREVA reported result.

(b) The Analytics standard.

(c) Ratio of AREVA to Analytics results.

(d) Analytics evaluation: A= Acceptable. W= Acceptable with warning. U= Unacceptable.

72

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