ML051260123

Independent Spent Fuel Storage Installation Annual Radiological Environmental Operating Report

ML051260123
Person / Time
Site:	Surry, 07200002
Issue date:	04/27/2005
From:	Jernigan D Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200604, 05-228
Download: ML051260123 (81)

Text

VIRGINIA ELECTRIC AND PO\\EOR COMPANY RICIhMOND, VIRGINIA 23261 April 27, 2005 United States Nuclear Regulatory Commission Serial No.05-228 Attention: Document Control Desk SS&L/TJN Washington, D. C. 20555-0001 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, 2004 through December 31, 2004 which includes environmental monitoring for the Surry ISFSI.

If you h any questions or require additional information, please contact Paul Harris at 757 6 2692.

V rytr y4yours, Donald E. Jernigan Site Vice President Surry Power Station Attachment Commitments made in this letter: None

• ARCS 3

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. N. P. Garrett NRC Senior Resident Inspector Surry Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23218

Serial No.05-228 Docket Nos.: 50-280 50-281 72-2 ATTACHMENT 2004 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 oer tat on

a. - sa - - - -

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Radiological 2004 Annual 200,4 Annual Radiological Environmental Operating Report M Domiinionf

Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2004 to December 31, 2004

Annual Radiological Environmental Operating Report Surry Power Station January 1, 2004 to December 31, 2004 Prepared by: A'. P. F. Blount Health Physicist Reviewed by: P.,?. /4 ,

P. R. Harris Supervisor Radiological Analysis Reviewed by: b 1Suk D. K. Miller Supervisor H alth Physics Technical Services Approved by:

a(n .B. Jones Man gadiological Protection 2

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

1. EXECUTIVE

SUMMARY

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

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

3. ANALYTICAL RESULTS ........................................................... . 20 3.1 Summary of Results ........................................................... 20 3.2 Analytical Results of 2004 REMP Samples ........................................................... 27

4. DISCUSSION OF RESULTS ........................................................... 51 4.1 Gamma Exposure Rate ........................................................... 52 4.2 Airborne Gross Beta ........................................................... 53 4.3 Airborne Radioiodine ........................................................... 55 4.4 Air Particulate Gamma ........................................................... 55 4.5 Cow Milk ........................................................... 55 4.6 Food Products ........................................................... 56 4.7 Well Water ........................................................... 56 4.8 River Water ........................................................... 56 4.9 Silt........................................................... 56 4.10 Shoreline Sediment ........................................................... 58 4.11 Fish ........................................................... 58 4.12 Oysters ........................................................... 58 4.13 Clams ........................................................... 59 4.14 Crabs ........................................................... 59

5. PROGRAM EXCEPTIONS ........................................................... . 60

6. CONCLUSIONS ............................................................ 61 REFERENCES ............................................................ 63 APPENDICES ............................................................ 65 APPENDIX A: LAND USE CENSUS ........................................................... 66 APPENDIX B: DOMINION NUCLEAR CONNECTICUT QA PROGRAM .. 68 APPENDIX C:

SUMMARY

OF INTERLABORATORY COMPARISONS .. 72 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 2004 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2004, 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 both current 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 Framatome ANP Environmental Laboratory provides radioanalyses for this program and Global Dosimetry Solutions Incorporated 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 certain radionuclides.

Licensed nuclear facilities must report the radionuclide activities in those 5

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 2004 airborne results were similar to previous years. No plant related radioactivity was detected and fallout or 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 radioisotopes were detected in well water.

This trend is consistent throughout the operational environmental monitoring program. 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. Cobalt-60, which has been detected in silt in the past, was not detected in 2004. There is no reporting level assigned for cobalt-60 and the trend over the past ten to fifteen year period continues to decrease. Shoreline sediment, which may provide a direct exposure pathway, contained no station related radioisotopes. 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 2004 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 radioisotopes 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 by use of thermoluminescent dosimeters (ThDs). T'D results have remained relatively constant over the years.

During 2004, as in previous years, operation of the 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 2004 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 not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at Surry Power Station.

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2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2004 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 (USNRC) 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 (ALARA). 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 Framatome ANP 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 levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes. 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 radioisotopes. 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 Radiological Environmental Monitoring Program for 2004 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 2004 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 Framatome ANP Environmental Laboratory and Global Dosimetry Solutions Incorporated for Surry Power Station during the year 2004.

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 Framatome ANP Environmental Laboratory, located in Westborough, MA, for analysis. The ThDs are shipped to Global Dosimetry Solutions Incorporated, located in Costa Mesa, CA, for processing.

8

I I I I I I I I I I I I Table 2-1 SURRY - 2004 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Control (00) Quarterly Onsite (Stored in lead container autside proterted area)

TLDs West North West (02) 0.2 mi WNW 2930 Quarterly Site Boundary Surry Station Discharge (03) 0.4 mi NW 3210 Quarterly Site Boundary North North West (04) 0.4 mi NNW 3290 Quarterly Site Boundary North (05) 0.3 mi N 3570 Quarterly Site Boundary North North East (06) 0.3 mi NNE 280 Quarterly Site Boundary North East (07) 0.4 mi NE 360 Quarterly Site Boundary East North East (08) 0.5 mi ENE 580 Quarterly Site Boundary East (Exclusion) (09) 0.4 mi ESE 1020 Quarterly Onsite West (10) 0.4 mi WSW 2570 Quarterly Site Boundary West South West (I 1) 0.3 mi WSW 2400 Quarterly Site Boundary South West (12) 0.3 mi SSW 2080 Quarterly Site Boundary South South West (13) 0.4 mi S 1820 Quarterly Site Boundary South (14) 0.5 mi SSE 1680 Quarterly Site Boundary South South East (15) 0.9 mi SE 1430 Quarterly Site Boundary South East (16) 1.1 mi SE 1300 Quarterly Site Boundary East (17) 0.8 mi E 800 Quarterly Site Boundary Station Intake (18) 1.6 mi ESE 1150 Quarterly Site Boundary hlog Island Reserve (19) 2.0 mi NNE 260 Quarterly Near Resident Bacon's Castle (20) 4.5 mi SSW 2020 Quarterly Apx. 5 mile Route 633 (21) 4.9 mi SW 2270 Quarterly Apx. 5 mile Alliance (22) 5.1 mi WSW 2470 Quarterly Apx. 5 mile Surry (23) 7.7 mi WSW 2560 Quarterly Population Center Route 636 and 637 (24) 4.0 mi W 2700 Quarterly Apx. 5 mile Scotland Wharf (25) 5.0 mi WNW 2840 Quarterly Apx. 5 mile Jamestown (26) 6.3 mi NW 3080 Quarterly Apx. 5 mile Colonial Parkway (27) 3.8 mi NNW 3330 Quarterly Apx. 5 mile Route 617 and 618 (28) 4.9 mi NNW 3400 Quarterly Apx. 5 mile Kingsmill (29) 4.6 mi N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.8 mi N 00 Quarterly Population Center Kingsmill North (31) 5.5 mi NNE 120 Quarterly Apx. 5 mile Budweiser (32) 5.8 mi NNE 270 Quarterly Population Center Water Plant (33) 4.8 mi NE 460 Quarterly Apx. 5 mile 9

I I I I I I I I I I I I I I I I I I I Table 2-1 SURRY - 2004 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Collection Sample M~ledia Location Station Distance Direction D)egrees Frequency Remarks 1BASF (34) 5.1 mi ENE 700 Quarterly Apx. 5 mile Lee llall (35) 7.1 mi ENE 750 Quarterly Population Center Goose Island (36) 5.1 mi E 900 Quarterly Apx. 5 mile Fort Eustis (37) 4.9 mi ESE 1040 Quarterly Apx. 5 mile Newport News (38) 19.3 mi SE 1300 Quarterly Population Center James River Bridge (39) 17.1 mi SE 1420 Quarterly Control Location Benn's Church (40) 17.0 mi SSE 1590 Quarterly Control Location Smithfield (41) 13.4 mi SSE 1670 Quarterly Control Location Rushmere (42) 5.3 mi SSE 1560 Quarterly Apx. 5 mile Route 628 (43) 5.1 mi S 1770 Quarterly Apx. 5 mile Air Charcoal Surry Station (SS) 0.3 mi NNE 180 Weekly Site Boundary (Highest D/Q) and Particulate Hog Island Reserve (HIR) 2.0 mi NNE 260 Weekly Bacon's Castle (BC) 4.5 mi SSW 2020 Weekly Alliance (ALL) 5.1 mi WSW 2470 Weekly Colonial Parkway (CP) 3.8 mi NNW 3330 Weekly BASE (BASF) 5.1 mi ENE 700 Weekly Fort Eustis (FE) 4.9 mi ESE 1040 Weekly Newvport News (NN) 19.3 mi SE 13Q0 Weekly Control Location River WVater Surry Station Discharge (SD) 0.4 mi NW 3230 Monthly Scotland Wharf (SW) 4.9 mi WNW 2840 Monthly Control Location Well Water Surry Station (SS) 0.1 mi SW 2270 Quarterly Onsite llog Island Reserve (IHR) 2.0 mi NNE 280 Quarterly Shoreline Hog Island Reserve (HIR) 2.0 mi NNE 300 Semi-Annually Sediment Chickahominy River (CHIC) 11.2 mi WNW 3010 Semi-Annually Control Location Silt Chickahominy River (ClIIIC) 11.2 mi WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.30 mi NNW 3410 Semi-Annually 10

I II I I I I I I I I Table 2-1 SURRY - 2004 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Collection Sample Mledia Location Station D)istance Direction Degrees Frequency Remarks Milk Colonial Parkway (CP) 3.7 mi NNW 3360 Monthly Williams (WMS) 27.5 mi S 1750 Monthly Control Location Epp's (EPPS) 4.8 mi SSW 2000 Monthly Control Location Oysters Point of Shoals (POS) 6.4 mi SSE 1570 Semi-Annually Mulberry Point (MP) 4.9 mi ESE 124° Semi-Annually Clams Chickahominy River (CHIC) 11.2 mi WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 mi NNW 3410 Semi-Annually Ilog Island Point (IHP) 2.4 mi NE 520 Semi-Annually Lawne's Creek (LC) 2.4 mi SE 1310 Semi-Annually Fish Surry Station Discharge (SD) 1.3 mi NNW 3410 Semi-Annually Crabs Surry Station Discharge (SD) 1.3 mi NNW 3410 Annually Food Products Brock's Farm (BROCK'S) 3.8 mi S 1830 Annually (Corn, Peanuts, Slade's Farm (SLADE'S) 3.2 mi S 1790 Annually Soybeans) 11

Table 2-2 (Page I of 3)

SURRY - 2004 SAMPLE ANALYSIS PROGRAM SAMPLE MIEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2 mRlStd. Month Dosimetry (TLD)

Air Iodine Weekly 1-131 0.07 pCi/m3 Air Particulate Weekly Gross Beta 0.01 pCi/m3 Quarterly (a) Gamma Isotopic pCi/m 3 Cs- 134 0.05 Cs- 137 0.06 River Water Quarterly Tritium (11-3) 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 WYell WVater Quarterly Tritium (11-3) 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 Frogip tex locate'd at end !ftalble.

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Table 2-2(Cont.)

(Page 2 of 3)

SURRY - 2004 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Scdiment Semi-Annual Gamma Isotopic pCi/kg - dry Cs- 134 150 Cs- 137 180 Silt Semi-Annual Gamma Isotopic pCi/k}g - 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-54 130 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 Fo{otno*tes Iocatdt It(iend .,J tale'.

13

Tab)lC 2-2 (Cont.)

SURRY - 2004 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 F(ooId Products 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.

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

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

14

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ICO) 1W

--- lll...l--.""- , - 1.11,l.,--.--,,--1-11,1111---,. 11---.---11---.----.----- -,

......-- .....1-11,1111.1-11-11-..",""-"'I 111-1-1

(:u I

- - - - -m- - - - - - -- - - - - - -

-- - - -=- - - - - - - - - - - - - -

Figure 3. Surry Emergency Plan Map

• Air Sampling Stations

• Nearest Residents O TLD Sampling

• Nearest Milk Animal z

• Nearest Garden Aquatic Samples wC0S 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.

CDIŽ;

-- - - - -M- - - - - - -M- -- - - -

Figure 4. Surry Emergency Plan Map

• Air Sampling Stations

• Nearest Residents

• TLD Sampling

• Nearest Milk Animal 0

0 w3

• Nearest Garden Crop Samples 0

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- - - -=- - - -

Figure 5. Surry Emergency Plan Map

• Air Sampling Stations

• Nearest Residents

• TLD Sampling

• Nearest MilkAnimal

• 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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3. ANALYTICAL RESULTS 3.1 Stinunary 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. 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 - 2004 Docket No. 50-280-281 Page I of 6 I

+

Indicator Control Locations Location with Highest Mean Locations Non-Routine Mean Distance Mean Mean Reported Range Name I Direction Range Range Measurements Air Iodine 1-131 416 0.07 < LLD N/A < LLD < LLD 0 (pci/m 3 )

Air Gross 416 10 20.6 (363/364) CP 3.8 mi 21.8 (52/52) 21.6(52/52) 0 Particulate Beta (6.2 - 41.4) NNW (8.6 - 41.4) (8.1 - 38.7)

(pC/rM 3'1E+3)

Gamma 32 Be-7 32 115 (28/28) ALL 5.1 mi 129 (4/4) 110 (4/4) 0 (74 - 159) WSW (97-159) (88 -128)

Cs-134 32 50 < LLD N/A < LLD < LLD 0 Cs-137 32 60 < LLD N/A < LLD < LLD 0 River H-3 8 2000 < LLD N/A < LLD < LLD 0 Water (pCi/Liter)

Gamma 24 K-40 24 61.0 (2112) SD 0.4 mi 61.0 (2112) < LLD 0 (60 - 62) NW (60 - 62)

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

• 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 PROGRA M SUAMAR Y Surry Power Station, Surry County, Virginia - 2004 Docket No. 50-2S0-281 Page 2 of 6 Medium or Indicatoir Control Pathway Analysis Location s Location with Highest Mean Locations I Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) . Type I No. I LLD Range Name Direction Range Range Measurements River Cs-134 24 15 < LLD N/A < LLD < LLD 0 Water (pCULiter)

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 Well H-3 8 2000 < LLD N/A < LLD N/A 0 Water (pC~iter) 8.

Gamma 8 Mn-54 8 15 < LLD N/A < LLD N/A Co-58 8 15 < LLD N/A < LLD N/A Fe-59 8 30 < LLD N/A < LLD N/A Co-60 8 15 < LLD N/A < LLD N/A Zn-65 8 30 < LLD N/A < LLD N/A Nb-95 8 15 < LLD N/A < LLD N/A Zr-95 8 30 < LLD N/A < LLD N/A 1-131 8 1 < LLD N/A < LLD N/A Cs-1 34 8 15 < LLD N/A < LLD N/A Cs-1 37 8 18 < LLD N/A < LLD N/A Ba-140 8 60 < 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 Emironmental Monitoring Program, Revision 1. November 1979.

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Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2004 Docket No. 50-280-281 Page 3 of 6 I

+

Indicator Control Locations Location with Highest Mean Locations Non-Routine Mean Distance Mean Mean Reported Range Name I Direction I Range Range Measurements Well La-1 40 8 15 < LLD N/A < LLD N/A 0 Water (pCilter)

Silt Gamma 4 (pCi4g dry)

Be-7 4 2730 (1/2) SD 1.3 mi 2730 (1/2) < LLD 0 (2730 - 2730) NNW (2730 - 2730)

K-40 4 17600 (2/2) CHIC 11.2 mi 17800 (2/2) 17800 (2/2) 0 (15000-20200) WNW (15500-20100) (15500-20100)

Cs-1 34 4 150 < LLD N/A < LLD < LLD 0 Cs-1 37 4 180 242 (2/2) SD 1.3 mi 242 (212) 184 (2/2) 0 (220 - 264) NNW (220 - 264) (149 - 219)

Th-228 4 1255 (212) CHIC 11.2 mi 1295 (2/2) 1295 (2/2) 0 (1180 - 1330) WNW (1130-1460) (1130-1460)

Shoreline Gamma 4 Sediment (pCiQg dry) K-40 4 6155 (2/2) HIR 2.0 mi 6155 (2/2) 4670 (212) 0 (5590 - 6720) NNE (5590 - 6720) (4060- 5280)

Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 < LLD N/A < LLD < LLD 0 Th-228 4 127 (2/2) CHIC 11.2 mi 613 (2/2) 613 (2/2) 0 (120 - 133) WNW (159 - 1067) (159 - 1067)

Milk Strontium 4 (pCi'Llter)

Sr-89 4 < LLD N/A < LLD N/A 0 Sr-90 4 2.8 (214) CP 3.7 mi 2.8 (214) N/A 0 (2.4 - 3.3) NNW (2.4 - 3.3)

Gamma 36 K-40 36 1400 (24/24) CP 3.7 mi 1452 (12112) 1342 (12112) 0 (1220 - 1520) NNW (1380-1520) (1251 -1410)

• 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 - 2004 Docket No. 50-280-281 Page 4 of 6 Medium or Indicator Control Pathway Analvsis 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 Milk 1-131 36 1 < LLD N/A < LLD < LLD 0 (pCi/Liter)

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 Clams Gamma 8 (pCiAg wet)

K-40 8 387 (3/6) HIP 2.4 mi 480 (1/2) < LLD 0 (320 - 480) NE (480 - 480)

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 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 Oysters Gamma 4 (pCilkg wet)

K-40 4 425 (2/4) MP 4.9 mi 450 (1/2) N/A 0 (400 - 450) ESE (450 - 450)

Mn-54 4 130 < 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 Emironmental Monitoring Program. Revision 1. November 1979.

24

Table 3-1 RADIOLOGICAL ENVIRONAMENTAL MONITORING PROGRAM SUMAIARY Surry Power Station, Surry County, Virginia - 2004 Docket No. 50-280-281 Page 5 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 I No. LLD Range Name I Direction Range Range Measurements Oysters Fe-59 4 260 < LLD N/A < LLD N/A 0 (pCikg wet)

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- 134 130 < LLD N/A < LLD N/A 0 Cs- 137 150 < LLD N/A < LLD N/A 0 Crabs Gamma (pCi9kg wet)

K-40 1510(1/1) SD 1.3 mi 1510 (1/1) N/A 0 (1510-1510) NNW (1510 -1510)

Mn-54 130 < LLD N/A < LLD N/A 0 Co-58 130 < LLD N/A < LLD N/A 0 Fe-59 260 < LLD N/A < LLD N/A 0 Co-60 130 < LLD N/A < LLD N/A 0 Zn-65 260 < LLD N/A < LLD N/A 0 Cs- 134 1 130 < LLD N/A < LLD N/A 0 Cs-1 37 1 150 < 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.

25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Surry Power Station, Surry County, Virginia - 2004 Docket No. 50-280-281 Page 6 of 6 Medium or Indicator Control Pathway Analys s Locations Location with Hig est Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name I Direction Range Range Measurements Fish Gamma 4 (pCilg wet)

K-40 4 1460 (4/4) SD 1.3 mi 1460 (4/4) N/A 0 (1300 - 1700) NNW (1300- 1700)

Mn-54 4 130 < LLD N/A < LLD N/A Co-58 4 130 < LLD N/A < LLD N/A Fe-59 4 260 < LLD N/A < LLD N/A Co-60 4 130 < LLD N/A < LLD N/A Zn-65 4 260 < LLD N/A < LLD N/A Cs- 134 4 130 < LLD N/A < LLD N/A Cs- 137 4 150 < LLD N/A < LLD N/A Food Gamma 3

- Products (pCilg wet) K-40 3 6993 (3/3) Slade's 3.2 mi 13410 (1/1) N/A 0 (2310 - 13410) S (13410-13410) 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 Direct Gamma 168 2 3.4 (156/156) STA-41 13.4 mi 6.15 (4/4) 4.2 (12/12) 0 Radiation (1.7 - 6.6) SSE (5.5 - 6.8) (2.2 - 6.8)

TLD (mRI S.td Month)

' 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 2004 REAIP 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 othenvise 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 2o error (i.e., the measured value exceeds 3a).

Framatome ANP 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 I-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 EXIPOSURE RA7E Surry Nuclear Power Station, Surry County, Virginia - 2004 mRlStd Month +/- 2 Sigma Page I of I l NUMBER QUARTER QUARTER QUARTER QUARTER +/- 2 SIGMA 02 5.1 +/-0.7 4.5 +/- 0.3 4.5 +/- 0.7 5.3 +/- 0.5 4.9 +/- 0.4 03 5.2 + 0.6 5.2 +/- 2.3 4.6 +/- 0.5 5.0 +/- 0.2 5.0 +/- 0.3 04 4.1 +/-0.5 3.3 +/- 0.2 3.9 +/- 0.4 3.8 +/- 0.3 3.8 +/- 0.3 05 4.4 +/- 0.3 3.6 +/- 0.7 3.8 +/- 0.5 4.6 +/- 1.3 4.1 +/- 0.5 06 4.7 + 0.5 4.3 +/- 0.8 4.4 +/- 0.6 5.2 +/- 0.5 4.7 +/- 0.4 07 3.8 +/- 0.5 3.2 +/- 0.6 3.6 +/- 0.4 3.9 +/- 0.3 3.6 +/- 0.3 08 3.3 +/- 0.7 2.7 +/- 0.8 3.2 +/- 0.3 3.5 +/- 0.3 3.2 +/- 0.3 09 4.1 +/- 0.6 3.1 +/- 0.5 3.4 +/- 0.5 3.8 +/- 0.7 3.6 +/- 0.4 10 3.3 +/- 0.6 2.7 +/- 0.2 3.3 +/- 0.9 3.5 +/- 0.3 3.2 +/- 0.3 11 3.6 + 0.7 3.0 +/- 0.7 3.2 +/- 0.3 3.9 +/- 0.7 3.4 +/- 0.4 12 4.1 +/- 0.4 3.0 +/- 0.7 3.3 +/- 0.6 4.0 +/- 0.5 3.6 +/- 0.5 13 4.3 +/- 0.6 3.3 +/- 1.1 3.8 +/- 0.6 4.4 +/- 0.4 4.0 +/- 0.5 14 4.5 +/- 0.7 3.8 +/- 0.3 4.6 +/- 1.1 4.2 +/- 0.8 4.3 +/- 0.4 15 3.4 +/- 0.9 2.4 +/- 0.6 3.1 +0.9 3.2 +/- 0.5 3.0 +/- 0.4 16 4.0 +/- 1.0 3.0 +/- 0.5 3.2 +/- 0.8 3.6 +/- 0.2 3.5 +/- 0.4 17 3.0 +/- 0.6 2.4 +/- 0.5 2.8 +/- 0.3 3.2 +/- 0.3 2.9 +/- 0.3 18 2.3 + 0.7 1.9 +/- 0.2 2.3 +/- 0.4 2.7 +/- 0.8 2.3 + 0.3 19 2.8 + 0.3 2.4 +/- 0.3 1.8 +/- 0.5 2.7 +/- 0.2 2.4 +/- 0.4 20 3.2 +/- 0.6 2.3 +/- 0.6 2.8 +/- 0.6 3.0 +/- 0.7 2.8 +/- 0.4 21 3.3 +/- 0.4 2.5 +/- 0.4 2.7 +/- 1.6 3.7 +/- 1.1 3.1 i 0.6 22 2.7 +/- 0.5 1.8 +/- 0.1 2.3 +/- 0.7 2.9 +/- 1.6 2.4 i 0.5 23 4.4 +/- 1.0 3.5 +/- 0.5 3.8 +/- 0.3 4.1 +/- 0.2 4.0 +/- 0.4 24 3.4 +/- 0.5 2.4 +/- 1.1 2.6 +/- 0.3 3.4 +/- 0.1 3.0 _ 0.5 25 3.5 +/- 0.5 2.5 +/- 1.3 3.3 +/- 0.5 3.8 +/- 0.5 3.3 i 0.6 26 3.9 +/- 0.6 3.1 +/- 0.6 3.0 +/- 0.3 3.6 +/- 0.6 3.4 i 0.4 27 2.7 +/- 0.3 2.4 +/- 0.3 2.7 +/- 0.5 2.7 +/- 0.4 2.6 + 0.2 28 3.0 +/- 0.5 2.1 +/- 0.5 2.7 +/- 0.5 2.6 +/- 1.5 2.6 i 0.4 29 2.4 +/- 0.4 2.0 +/- 0.6 2.1 +/- 0.3 2.4 +/- 0.5 2.2 _ 0.2 30 3.0 +/- 0.4 2.0 +/- 1.1 2.7 +/- 0.6 3.3 +/- 1.1 2.8 i 0.6 31 2.3 +/- 0.5 1.7 +/- 0.3 2.1 +/- 0.5 2.6 +/- 0.7 2.2 +/- 0.4 32 3.4 +/- 0.6 2.1 +/- 0.5 3.0 +/- 0.6 3.1 +/- 0.3 2.9 +/- 0.6 33 3.2 +/- 0.1 2.9 +/- 0.1 3.1 +/- 0.7 3.6 +/- 0.4 3.2 +/- 0.3 34 3.6 +/- 0.7 2.8 +/- 0.4 3.2 +/- 0.5 3.7 +/- 0.3 3.3 i 0.4 35 4.6 +/- 0.6 3.5 +/- 0.4 3.8 +/- 0.4 4.4 +/- 0.4 4.1 +/-0.5 36 4.8 +/- 0.7 3.5 +/- 0.5 3.8 +/- 0.5 5.3 +/- 1.0 4.4 +/- 0.8 37 3.7 +/- 0.2 2.6 +/- 0.3 2.9 +/- 0.6 3.9 +/- 1.2 3.3 i 0.6 38 6.6 +/- 0.3 5.5 +/- 0.6 5.4 +/- 0.4 5.9 +/- 0.3 5.9 +/- 0.5 39 3.4 +/- 0.5 2.6 +/- 0.6 2.2 +/- 0.8 3.1 +/- 0.2 2.8 +/- 0.5 40 4.0 +/- 0.2 3.5 +/- 0.2 3.4 +/- 0.3 3.8 +/- 0.6 3.7 +/- 0.3 41 6.8 +/- 0.5 5.5 +/- 0.3 5.7 +/- 0.7 6.6 +/- 0.4 6.2 +/- 0.6 42 3.4 +/- 0.2 2.5 +/- 0.3 3.0 +/- 0.6 3.4 +/- 0.3 3.1 +/- 0.4 43 3.1 +/- 0.2 2.6 +/- 0.6 2.9 +/- 0.8 3.1 +/- 0.5 2.9 +/- 0.2 28

I I . I I I I I  ! I I I I I I TAIBLE 3-3: GROSS BETA CONCENTRA TION IN FILTE RED A IR Surry Nuclear Plower Station, Surry County. Virginia - 2004 pCi/mfl

• I.()O+3 t 2 Sigmna Pam I of 2 COLLECTION I SAMPLING LOCATIONS DATE I SS HIR BC ALL CP BASF FE NN-C January 06 21.7 +/- 3.5 21.7 +/- 3.3 24.0 +/- 3.4 21.7 +/- 3.4 23.2 +/- 3.4 22.8 +/- 3.5 21.8 +/- 3.3 24.2 +/- 3.5 January 13 29.6 +/- 4.0 34.9 + 4.1 32.0 +/- 4.0 33.4 +/- 4.0 34.0 +/- 4.2 34.0 +/- 4.1 25.7 +/- 3.8 30.4 +/- 4.0 January 20 27.1 +/- 3.8 27.2 +/- 3.7 28.3 +/- 3.8 28.0 +/- 3.8 29.4 +/- 3.8 25.6 +/- 3.8 26.3 +/- 3.7 27.7 +/- 3.9 January 27 21.5 +/- 3.5 22.4 +/- 3.2 (a) 22.7 +/- 3.6 24.9 +/- 3.6 27.4 +/- 3.7 24.1 +/- 3.6 20.1 +/- 3.5 28.8 +/- 3.9 February 03 24.0 + 3.6 25.4 +/- 4.0 25.6 +/- 3.5 29.5 +/- 3.7 26.4 +/- 3.6 27.4 +/- 3.6 25.5 +/- 3.5 29.9 +/- 3.7 February 10 21.7 + 3.5 18.4 +/- 3.3 19.6 +/- 3.4 17.3 +/- 3.3 18.9 +/- 3.4 19.4 +/- 3.4 15.1 +/- 3.2 23.4 +/- 3.6 February 17 26.7 + 3.4 23.7 +/- 3.2 30.1 +/- 3.5 27.2 + 3.3 30.3 +/- 3.5 27.2 +/- 3.5 24.7 +/- 3.3 30.3 +/- 3.8 February 24 22.2 +/- 3.6 22.0 +/- 3.5 23.9 +/- 3.7 24.7 +/- 3.8 24.3 +/- 3.7 23.0 +/- 3.7 27.3 +/- 3.8 27.1 +/- 3.9 March 02 21.0 + 3.3 23.1 +/- 3.4 22.9 +/- 3.4 20.1 +/- 3.2 22.5 +/- 3.3 20.5 +/- 3.3 21.2 -- 3.3 28.1 +/- 3.6 March 09 20.8 +/- 3.1 23.6 +/- 3.2 22.6 +/- 3.1 23.6 +/- 3.2 22.1 +/- 3.1 23.0 +/- 3.2 23.3 +/- 3.2 23.2 +/- 3.2 March 16 19.9 +/- 4.5 19.7 +/- 4.4 19.3 +/- 4.4 21.0 +/- 4.5 20.6 +/- 4.5 19.9 +/- 4.5 20.0 +/- 4.4 19.1 +/- 4.4 March 23 11.2 +/- 4.1 12.2 +/- 4.1 13.1 +/- 4.0 15.6 +/- 4.2 14.7 +/- 4.2 10.4 +/- 4.0 14.9 +/- 4.3 16.5 +/- 4.5 March 30 22.2 + 4.7 20.6 +/- 4.5 21.5 +/- 4.7 19.8 +/- 4.6 27.7 +/- 5.0 13.7 +/- 4.2 19.8 +/- 4.4 22.3 +/- 4.7 Qtr. Avg. +/- 2 s.d. 22.3 +/- 8.8 22.7 +/- 10.4 23.5 +/- 9.8 23.6 +/- 10.1 24.7 +/- 10.4 22.4 +/- 12.0 22.0 +/- 8.0 25.5 +/- 8.9 April 06 8.8 _ 3.7 6.2 +/- 3.5 10.0 +/- 3.7 10.6 +/- 3.7 12.4 +/- 3.9 8.6 +/- 3.6 6.8 +/- 3.5 11.9 +/- 3.9 April 12 22.5 +/- 4.0 19.4 +/- 3.8 24.0 +/- 4.6 24.8 +/- 4.6 20.7 + 3.8 27.5 +/- 4.5 18.1 +/- 3.7 26.4 +/- 4.5 April 20 15.3 + 4.1 16.9 _ 4.1 21.8 +/- 4.5 20.1 +/- 4.2 21.2 +/- 4.4 17.7 +/- 4.2 22.9 +/- 4.5 19.4 +/- 4.5 April 27 29.0 +/- 5.2 27.0 + 5.1 27.9 +/- 5.1 22.6 +/- 4.9 25.2 +/- 5.0 24.0 +/- 4.9 23.3 +/- 4.9 30.4 +/- 5.3 May 04 14.4 +/- 4.4 14.3 _ 4.3 14.1 +/- 4.3 14.1 +/- 4.3 15.6 +/- 4.4 15.9 +/- 4.5 13.9 - 4.3 20.5 +/- 4.7 May 11 22.1 +/- 4.9 24.1 +/- 4.9 33.4 +/- 5.7 28.9 +/- 5.2 26.8 +/- 5.0 23.1 +/- 5.0 23.9 +/- 4.9 29.1 +/- 5.4 May 18 33.4 +/- 5.3 30.5 +/- 5.1 33.6 +/- 5.3 35.7 +/- 5.4 41.4 +/- 5.7 32.5 +/- 5.4 34.9 +/- 5.4 38.7 +/- 5.8 May 25 18.3 +/- 4.7 26.4 +/- 5.1 26.4 +/- 5.1 21.9 +/- 4.9 16.8 +/- 4.7 15.1 +/- 4.6 16.1 +/- 4.6 24.3 +/- 5.2 June 01 18.9 +/- 4.8 14.0 +/- 4.5 17.0 +/- 4.7 16.6 +/- 4.7 20.5 +/- 4.9 19.3 +/- 4.8 20.7 + 4.8 21.2 +/-5.0 June 08 11.2 +/- 4.1 11.0 +/- 4.0 13.1 +/- 4.2 13.5 +/- 4.2 13.5 +/- 4.2 14.7 +/- 4.3 15.7 -- 4.3 15.0 +/- 4.3 June 15 20.9 +/- 4.7 21.2 +/- 4.7 19.1 +/- 4.6 20.8 +/- 4.8 22.9 +/- 4.9 23.4 +/- 5.0 19.7 +/- 4.7 22.5 +/- 4.9 June 22 15.6 +/- 4.4 10.8 +/- 4.1 13.0 +/- 4.2 15.6 +/- 4.4 14.0 +/- 4.3 11.9 +/- 4.2 11.4 +/- 4.2 13.7 +/- 4.4 June 29 19.2 +/- 4.6 18.5 +/- 4.5 19.0 +/- 4.6 21.6 +/- 4.7 21.7 +/- 4.7 17.9 +/- 4.5 20.3 + 4.6 19.7 +/- 4.6 Qtr. Avg. +/- 2 s.d. 19.2 +/- 13.5 18.5 +/- 14.4 21.0 + 15.5 20.5 +/- 13.6 21.0 +/- 15.3 19.4 +/- 13.2 19.1 +/- 13.8 22.5 +/- 14.8 29

I I I I I I I i I I I I I TABLE 3-3: GROSS BETA CONCENTRA TION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2004 3

pCi/in

• 1.01,E+3 +/- 2 SigniI Pagc 2 of 2 COLLECTION l SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN July 06 17.1 +/- 4.6 18.2 +/- 4.7 16.6 +/- 4.6 20.6 +/- 4.7 22.8 -- 4.9 16.2 +/- 4.6 17.6 +/- 4.7 21.0 +/- 4.8 July 13 19.0 +/- 4.6 18.4 +/- 4.6 22.7 +/- 5.2 19.6 +/- 4.6 19.8 - 4.6 19.1 +/- 4.6 17.4 +/- 4.5 19.7 +/- 4.6 July 20 19.2 +/- 4.3 18.3 +/- 4.2 18.5 +/- 4.3 26.6 +/- 4.7 19.8 + 4.3 19.8 +/- 4.4 17.9 +/- 4.3 19.9 +/- 4.5 July 27 23.1 +/- 4.9 20.6 +/- 4.8 19.9 +/- 4.8 21.5 +/- 4.8 26.5 +/- 5.1 19.5 +/- 4.7 25.8 +/- 5.0 19.6 +/- 4.6 August 02 8.8 +/- 4.4 11.6 +/- 4.5 < 6.6 14.2 +/- 4.7 8.9 +/- 4.3 8.9 +/- 4.3 10.7 +/- 4.4 8.9 +/- 4.4 August 09 14.9 +/- 4.6 21.2 +/- 4.8 17.8 +/- 4.6 19.3 +/- 4.6 18.9 +/- 4.6 19.8 +/- 4.7 17.2 +/- 4.5 19.9 +/- 4.9 (b)

August 17 14.0 +/- 2.9 17.6 +/- 3.1 14.6 +/- 3.0 17.4 +/- 3.0 15.6 +/- 3.0 16.5 +/- 3.1 17.4 +/-k 3.1 9.0 +/- 4.3 (b)

August 23 21.9 +/- 5.2 22.1 +/- 5.2 20.6 +/- 5.1 29.0 +/- 5.7 24.6 +/- 5.4 25.8 +/- 5.4 23.4 + 5.2 24.3 +/- 5.3 August 30 20.5 +/- 4.8 27.1 +/- 5.1 24.9 +/- 5.0 23.0 +/- 4.9 25.6 +/-b 5.1 27.2 +/- 5.1 23.2 +/- 4.9 22.6 +/- 4.9 September 07 19.6 +/-i 4.2 18.7 +/- 4.1 17.7 +/- 4.1 20.9 +/- 4.2 22.4 +/- 4.3 19.6 +/- 4.1 20.0 +/- 4.3 19.8 +/- 4.2 September 14 13.8 +/-k 4.4 12.0 +/- 4.3 12.3 +/- 4.3 14.1 +/- 4.4 14.6 +/- 4.4 15.7 +/- 4.5 14.4 +/- 4.4 10.2 +/- 4.2 September 21 6.9 +/-fi 4.3 9.8 +/- 4.5 7.2 +/- 4.3 8.7 +/- 4.4 8.6 +/- 4.4 7.1 +/- 4.3 7.3 +/- 4.4 8.1 +/- 4.4 September 28 20.0 +/- 4.5 22.3 +/- 4.6 21.0 +/- 4.5 21.7 +/- 4.6 24.6 +/- 4.7 24.4 +/- 4.7 21.3 +/- 4.7 (c) 23.8 +/- 4.7 Qtr. Avg. + 2 s.d. 16.8 +/- 9.8 18.3 +/- 9.6 17.8 + 9.6 19.7 + 10.7 19.4 + 12.0 18.4 +/- 11.7 18.0 + 10.2 17.4 +/- 12.1 October 05 15.9 +/- 4.4 19.6 +/- 4.5 18.4 + 4.5 24.0 +/- 4.8 23.7 +/- 4.8 23.1 +/- 4.8 21.7 + 4.7 22.6 +/- 5.5 October 12 18.3 +/- 4.8 14.5 +/- 4.7 21.9 + 5.0 24.5 +/- 5.1 22.6 +/- 5.0 23.5 +/- 5.0 20.3 +/- 4.9 17.3 +/- 4.9 (d)

October 19 24.5 +/- 4.6 26.1 +/- 4.7 21.1 +/- 4.4 23.4 +/- 4.5 28.4 +/- 4.8 23.9 +/- 4.6 24.7 +/- 4.6 23.8 + 4.7 October 25 12.0 +/- 4.7 10.1 +/- 4.5 10.5 +/- 4.5 10.2 +/- 4.4 8.8 +/- 4.4 11.8 +/- 4.6 11.5 +/- 4.6 9.2 +/- 4.6 November 02 25.1 +/- 4.5 (e) 23.8 +/- 4.4 (e) 27.5 +/- 4.6 (e) 32.4 +/- 4.9 (e) 31.2 +/- 4.7 31.1 +/- 4.6 26.6 +/- 4.6 (e) 29.2 +/- 4.7 (e)

November 09 20.3 +/- 4.4 19.8 +/- 4.3 18.6 +/- 4.2 19.6 +/- 4.4 24.1 +/- 4.7 22.5 +/- 4.6 22.7 +/- 4.6 20.5 +/- 4.6 November 16 20.2 +/- 4.9 18.2 +/- 4.7 16.3 +/- 4.4 22.9 +/- 4.8 20.2 _ 4.6 23.0 +/- 4.6 20.5 +/- 4.5 19.5 +/- 4.5 November 23 27.1 +/- 5.1 23.6 +/- 5.0 27.6 +/- 5.2 32.1 +/- 5.4 31.7 +/- 5.2 32.4 +/-ti 5.3 27.3 +/- 4.9 32.4 +/-fi 5.5 November 30 12.9 +/- 4.5 11.0 +/- 4.3 10.1 +/- 4.2 14.6 +/- 4.5 12.7 +/- 4.3 13.4 +/- 4.3 11.5 +/- 4.2 14.5 + 4.5 December 07 29.7 +/- 5.5 28.9 +/- 5.4 24.4 +/- 5.2 29.2 +/- 5.4 26.6 + 5.4 30.8 +/- 5.6 30.1 +/- 5.5 24.8 +/- 5.4 December 14 14.5 +/- 4.7 20.7 +/- 5.0 14.9 +/- 4.7 19.0 +/- 4.8 15.5 +/- 4.7 19.6 +/- 4.9 16.4 +/- 4.8 17.4 +/- 4.8 December 21 24.7 +/- 4.7 24.7 +/- 4.6 19.8 +/- 4.4 24.0 +/- 4.7 21.9 +/- 4.5 23.2 +/- 4.6 26.7 +/- 4.8 21.8 +/- 4.6 December 28 22.0 +/- 4.9 18.5 +/- 4.8 19.1 +/- 4.6 23.1 +/- 4.9 21.8 +/- 4.9 21.4 +/- 4.8 21.7 +/- 4.8 18.0 +/- 4.7 Qtr. Avg. +/- 2 s.d. 20.6 +/- 11.2 20.0 +/- 11.3 19.2 +/- 11.0 23.0 + 12.6 22.2 +/- 13.6 23.1 +/- 12.2 21.7 +/- 11.6 20.8 +/- 12.1 Ann. Avg. 2 s.d. 19.7 +/- 11.4 19.9 +/- 11.8 20.4 + 12.2 21.7 +/- 11.9 21.8 +/- 13.1 20.8 + 12.6 20.2 +/- 11.3 21.6 +/- 13.2 30

i I l I I I I I I I i I I I I I Table 3-3 Footnotes (a) Sample collected 1/28/05.

(b) Sampler not operational at sample change out. Sampler located within a substation. Maintenance was performed that required loss of power to sampler. Sample volume based on timer indication, 162.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for week of 08/02 - 08/08 and 117.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for week of 08/08 - 08/15. Sample volumes sufficient to meet required LLD.

(c) Sampler had high vacuum at sample change out, 8.0 inches FIg versus 2.5 typical average vacuum.

Particulate filter had higher than normal loading due construction activity in area of sampler. Sample volume was sufficient to meet required LLD.

(d) Sampler had high vacuum at sample change out, 7.5 inches Hg versus 2.5 typical average vacuum.

Particulate filter had higher than normal loading due construction activity in area of sampler. Sample volume was sufficient to meet required LLD.

(e) Samplers had high vacuum at sample change out, ranging from 6.0 to 10.0 inches Hg versus 2.5 typical average vacuum. Particulate filters had higher than normal loading due construction activities in the area of the SS, FE and NN samplers. Particulate filters had higher than normal loading due farming activities in the area of the HIR, BC and ALL samplers. Sample volumes were sufficient to meet required LLD.

31

I I I  ! I I I I i I  ! I I TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2004 pC/ni&* 1.OE+3

• 2 Sigma Palie I of 2 COLLECTION I SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C I January 06 <50 <44 <46 <44 <45 <53 <48 <57 January 13 <30 <29 <35 <32 <39 <26 <27 <24 January 20 <35 <32 <34 <33 <37 <37 <34 <31 January 27 <29 <24 (a) <25 <29 <29 <28 <29 <29 February 03 <29 <27 <25 <30 <23 <27 <25 <31 February 10 <20 <27 <22 <21 <23 <25 <20 <24 February 17 <38 <30 <33 <27 <37 <31 <25 <25 February 24 <28 <27 <32 <28 <28 <32 <26 <28 March 02 <24 <22 <26 <16 <16 <25 <19 <24 March 09 <24 <21 <23 <17 <21 <20 <19 <19 March 16 <21 <18 <25 <17 <20 <24 <23 <22 March 23 <28 <34 <37 <37 <29 <35 <40 <30 March 30 <19 <20 <20 <21 <24 <24 <22 <21 April 06 <26 <25 <29 <27 <25 <22 <23 <27 April 12 <24 <25 <37 <39 <28 <38 <28 <37 April 20 <25 <24 <19 <18 <24 <26 <18 <20 April 27 <30 <29 <22 <21 <36 <21 <26 <22 May 04 <28 <26 <28 <25 <21 <24 <22 <23 May11 <26 <24 <21 <22 <23 <25 <27 <29 May18 <22 <23 <32 <25 <29 <23 <20 <27 May25 <34 <32 <24 <31 <30 <31 <28 <28 June 01 <26 <26 <28 <24 <28 <26 <30 <26 June 08 <26 <24 <24 <23 <24 <29 <22 <26 June 15 <33 <31 <27 <28 <24 <22 <33 <31 June 22 <31 <25 <28 <24 <33 <30 <31 <26 June 29 <35 <40 <36 <31 <29 <39 <39 <38 32

I i I I i I I I i ' I I i I TABLE 3-4: IODINE-131 CONCENTRATION IN FILTLERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2004 j)CUnfl

• 1.OE+3 +/- 2 Sigma Page 2 of 2 COLLECTION SAMPLING LOCATIONS I DATE SS HIR BC ALL CP BASF FE NN July 06 <40 <45 <44 <38 <45 <47 <41 <43 July 13 <31 <30 <33 <28 <30 <26 <33 <27 July 20 <32 <25 <22 <19 <22 <22 <29 <30 July 27 <24 <28 <24 <19 <26 <20 <19 <24 August 02 <28 <22 <22 <21 <22 <21 <26 <25 August 09 <37 <36 <28 <28 <34 <31 <40 <33 (b)

August 17 <38 <38 <30 <35 <36 <32 <33 <48 (b)

August 23 <29 <26 <31 <26 <26 <24 <29 <26 August 30 <27 <29 <29 <28 <26 <24 <29 <33 September 07 <27 <25 <19 <21 <26 <23 <23 <21 September 14 <30 <31 <29 <28 <29 <27 <24 <23 September 21 <23 <33 <26 <30 <23 <35 <34 <39 September 28 <21 <22 <24 <27 <24 <24 <24 (c) <23 October 05 <23 <26 <25 <24 <21 <29 <23 <28 October 12 <31 <46 <39 <37 <42 <33 <34 <34 (d)

October 19 <37 <37 <41 <39 <43 <37 <44 <37 October 25 <32 <31 <22 <25 <29 <24 <29 <25 November 02 <29 (e) <27 (e) <34 (e) <28 (e) <25 <20 <29 (e) <26 (e)

November 09 <25 <25 <25 <26 <27 <24 <25 <27 November 16 <29 <35 <29 <25 <26 <23 <30 <24 November 23 <37 <35 <42 <39 <47 <37 <37 <45 November 30 <27 <24 <24 <26 <23 <25 <24 <19 December 07 <21 <24 <24 <26 <25 <24 <24 <25 December 14 <16 <17 <18 <20 <21 <18 <23 <22 December 21 <28 <25 <25 <23 <22 <28 <29 <25 December 28 <34 <34 <22 <26 <25 <30 <25 <22 33

I i I I I I I I Table 3-4 Footnotes (a) Sample collected on 1/28/05.

(b) Sampler not operational at sample change out. Sampler located within a substation. Maintenance was performed that required loss of power to sampler. Sample volume based on timer indication, 162.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for week of 08/02 - 08/08 and 1 17.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for week of 08/08 - 08/15. Sample volumes sufficient to meet required LLD.

(c) Sampler had high vacuum at sample change out, 8.0 inches I-Ig versus 2.5 typical average vacuum.

Particulate filter had higher than normal loading due construction activity in area of sampler. Sample volume was sufficient to meet required LLD.

(d) Sampler had high vacuum at sample change out, 7.5 inches Hg versus 2.5 typical average vacuum.

Particulate filter had higher than normal loading due construction activity in area of sampler. Sample volume wvas sufficient to meet required LLD.

(e) Samplers had high vacuum at sample change out, ranging from 6.0 to 10.0 inches Hg versus 2.5 typical average vacuum. Particulate filters had higher than normal loading due construction activities in the area of the SS, FE and NN samplers. Particulate filters had higher than normal loading due farming activities in the area of the I-hR, BC and ALL samplers. Sample volumes were sufficient to meet required LLD.

34

TABLE 3-5: GAMMA E'MITTER CONCENTRAT7ION IN FILTE'RE,'D AIR Surry Nuclear Power Station, Surry County. Virginia - 2004 pCi/rn 3

• 1.OE+W +/- 2 Sigma Page I of I SAMPLING FIRST SECOND THIRD FOURTH AVERAGE I LOCATIONS NUCLIDE I QUARTER QUARTER QUARTER QUARTER +/- 2 SIGMA Ss Cs-1 34 <1.7 <2.0 <2.2 <2.5 Cs-1 37 <3.5 <1.7 <3.3 <2.9 Be-7 96 + 39 122 +/- 30 113 +/- 38 74 +/- 33 101 +/-21 HIR Cs-1 34 <1.6 <1.6 <2.3 <1.9 Cs-1 37 <2.6 <1.6 <3.2 <3.0 Be-7 110 +/- 35 111 +/- 27 118 +/- 35 119 +/- 36 115 +/-5 BC Cs-1 34 <2.3 <1.5 <1.9 <1.9 Cs-1 37 <3.0 <1.6 <3.0 <2.9 Be-7 144 +/- 38 131 +/- 30 99 +/- 33 90 +/- 35 116 +/- 26 ALL Cs-1 34 <1.7 <1.2 <2.2 <2.0 Cs-1 37 <3.2 <1.6 <3.0 <2.9 Be-7 136 +/- 38 159 +/- 32 97 +/- 34 125 +/- 36 129 +/- 26 CP Cs-134 <2.3 <1.9 <2.3 <2.2 Cs-1 37 <3.2 <3.1 <3.0 <3.5 Be-7 122 +/- 39 139 +/- 34 104 +/- 35 115 + 37 120 +/- 15 BASF Cs-1 34 <2.2 <2.0 <2.2 <1.7 Cs-137 <3.1 <3.4 <2.8 <3.2 Be-7 100 +/- 38 137 +/- 34 96 +/- 33 98 +/- 38 108 +/- 20 FE Cs-1 34 <2.5 <2.4 <2.2 <2.5 Cs-1 37 <3.0 <3.0 <3.1 <3.0 Be-7 113 +/- 37 151 +/- 35 105 +/- 33 106 + 33 119 +/-22 NN-C Cs-134 <1.9 <1.5 <1.5 <1.7 Cs-137 <3.3 <3.1 <3.3 <3.3 Be-7 128 +/- 38 125 +/- 34 88 +/- 37 99 +/- 35 110 +/- 20 35

TABLE 3-6: GAAMAMA EAMITTER AND STRONTIUM CONCENTRATIONS IAN MILK Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/Liter +/- 2 Sigma Page I of 3 COLONIAL NUCLIDE I EPPS PARKWAY WILLIAMS-C JANUARY Cs-1 34 <6 <10 <7 Cs-1 37 <5 <8 <6 Ba-1 40 <9 <12 <7 La-1 40 <10 <14 <8 1-131 <1 <1 <1 K-40 1290 +/- 110 1500 +/- 150 1270 +/- 110 FEBRUARY Cs-1 34 <9 <7 <5 Cs-137 <8 <6 <5 Ba-1 40 <12 <10 <8 La-1 40 <14 <11 <9 1-131 <1 <1 <1 K-40 1370 +/- 150 1510 +/- 120 1342 +/- 87 MARCH Cs-134 <8 <6 <7 Cs-1 37 <7 <6 <6 Ba-1 40 <10 <8 <12 La-140 <11 <9 <14 1-131 <1 <1 <1 K-40 1360 +/- 140 1470 +/- 110 1410 +/- 140 Sr-89 <9 Sr-90 3.3 +/- 1.1 APRIL Cs-1 34 <8 <6 <6 Cs-1 37 <8 <6 <6 Ba-140 <12 <10 <7 La-140 <13 <11 <8 1-131 <1 <1 <1 K-40 1350 +/- 140 1520 +/- 120 1310 +/- 110 36

TABLE 3-6: GAMMA EMITTER CONCE,'NTRATION IN MILK Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/Liter + 2 Sigma Page 2 of 3 COLONIAL NUCLIDE I EPPS PARKWAY WILLIAMS-C MAY Cs-1 34 <5 <6 <6 Cs-1 37 <5 <6 <6 Ba-1 40 <11 <10 <8 La-140 <12 <11 <9 1-131 <1 <1 <1 K-40 1346 +/- 97 1430 +/- 110 1400 +/- 110 JUNE Cs-134 <6 <5 <5 Cs-137 <6 <4 <5 Ba-140 <11 <9 <10 La-140 <12 <10 <11 1-131 <1 <1 <1 K-40 1220 +/- 120 1435 +/- 87 1365 +/- 96 Sr-89 <10 Sr-90 <2 JULY Cs-1 34 <9 <6 <6 Cs-137 <9 <6 <5 Ba-140 <11 <8 <8 La-140 <13 <9 <9 1-131 <1 <7 (a) <1 K-40 1440 +/- 160 1410 +/- 110 1390 +/- 110 AUGUST Cs-134 <7 <6 <7 Cs-137 <6 <5 <6 Ba-140 <9 <10 <10 La-140 <10 <12 <11 1-131 <1 <1 <1 K-40 1300 +/- 120 1380 +/- 98 1400 +/- 120 37

TABLE 3-6: GAMIA EAMITTER CONCE'N7TRATION INAILK Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/Liter +/- 2 Sigma Page 3 of 3 l lCOLONIAL I NUCLIDE I EPPS PARKWAY WILLIAMS-C SEPTEMBER Cs-1 34 <7 <4 <7 Cs-1 37 <8 <3 <7 Ba-1 40 <12 <6 <10 La-140 <14 <7 <12 1-131 <1 <1 <1 K-40 1470 +/- 140 1444 +/- 71 1370 +/- 130 Sr-89 <9 Sr-90 <2 OCTOBER Cs-134 <7 <7 <5 Cs-137 <8 <6 <5 Ba-140 <12 <8 <10 La-1 40 <14 <9 <11 1-131 <1 <1 <1 K-40 1370 +/- 140 1420 +/- 140 1251 +/- 94 NOVEMBER Cs-134 <7 <10 <8 Cs-137 <7 <7 <6 Ba-140 <11 <12 <9 La-140 <12 <14 <10 1-131 <1 <1 <1 K-40 1340 +/- 130 1450 +/- 160 1260 +/- 120 DECEMBER Cs-1 34 <7 <8 <9 Cs-137 <7 <7 <7 Ba-140 <12 <10 <11 La-140 <14 <11 <13 1-131 <1 <1 <1 K-40 1350 +/- 140 1460 +/- 150 1340 +/- 140 Sr-89 <8 Sr-90 2.4 +/- 0.8 38

Table 3-6 Footnotes (a) LLD of 1 pCi/Liter for iodine-131 not met. Sample was cross-contaminated at laboratory. After resolution of cross-contamination issues, sample reanalysis could not meet LLD due to excessive decay time from sample date.

39

TABLE 3-7: GAMMIA EAITTER CONCFANTRATION IN FOOD PRODUCTS Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/kg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTION SAMPLE ILOCATIONS DATE TYPE I Cs-1 34 Cs-1 37 1-131 K-40 BROCKS 11/04/04 Corn <24 <20 <47 2310 +/- 380 FARM 11/04/04 Peanuts <16 <17 <43 5260 +/- 350 SLADES 12/14/04 Soybeans <18 <17 <50 13410 +/- 600 FARM 40

7'ABLE 3-8: GAiM1MA EMITTER AND TRITJUM CONCEN7TRATIONS IN WELL WATER Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/Liter +/- 2 Sigma Page I of I SAMPLING COLLECTION ILOCATIONS DATE ISOTOPE Ba-140 Co-58 Co-60 Cs-1 34 Cs-137 Ss 03/17/04 <7 <4 <4 <4 <4 06/22/04 <12 <8 <7 <7 <6 09/21/04 <10 <5 <4 <5 <5 12/21/04 <12 <4 <6 <5 <5 Fe-59 1-131 La-140 Mn-54 Nb-95 03/17/04 <10 <1 <8 <4 <5 06/22/04 <15 <1 <14 <5 <6 09/21/04 <16 <1 <11 <4 <5 12/21/04 <14 <1 <14 <4 <6 Zn-65 Zr-95 H-3 03/17/04 <9 <6 <1300 06/22/04 <15 <9 <1400 09/21/04 <9 <9 <1400 12/21/04 <10 <9 <1000 Ba-140 Co-58 Co-60 Cs-134 Cs-137 HIR 03/17/04 <6 <4 <4 <4 <4 06/22/04 <12 <6 <6 <7 <4 09/21/04 <12 <6 <7 <6 <6 12/21/04 <11 <5 <6 <5 <4 Fe-59 1-131 La-140 Mn-54 Nb-95 03/17/04 <11 <1 <7 <4 <4 06/22/04 <13 <1 <14 <5 <8 09/21/04 <18 <1 <14 <5 <7 12/21/04 <16 <1 <12 <6 <7 Zn-65 Zr-95 H-3 03/17/04 <8 <6 <1300 06/22/04 <11 <10 <1400 09/21/04 <11 <8 <1400 12/21/04 <11 <9 <1000 41

7ABLE 3-9: GAlMMA EMT17'7ERAND TRITIUM CONCI'N7'1A7'IONSINRIVER WATER Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/l.iter + 2 Sigmna Pagc I of 2 SAMPLING COLLECTIONl l LOCATIONS DATE . ISOTOPE Ba-140 Co-58 Co-60 Cs-134 Cs-1 37 SD 01/28/04 <9 <4 <7 <6 <4 02/24/04 <7 <4 <6 <5 <5 03/30/04 <8 <5 <5 <5 <6 04/27/04 <10 <5 <6 <5 <5 05/25/04 <9 <4 <5 <5 <5 06/29/04 <10 <6 <6 <6 <6 07/27/04 <8 <4 <4 <4 <4 08/23/04 <7 <5 <5 <4 <5 09/28/04 <8 <4 <4 <4 <4 10/25/04 <8 <4 <5 <6 <5 11/23/04 <12 <6 <7 <6 <6 12/21/04 <4 <2 <2 <2 <2 Fe-59 1-131 La-140 Mn-54 Nb-95 01/28/04 <16 <6 <10 <4 <5 02/24/04 <13 <8 <8 <5 <4 03/30/04 <11 <10 <9 <4 <5 04/27/04 <19 <10 <11 <5 <6 05/25/04 <10 <10 <10 <4 <5 06/29/04 <15 <10 <11 <6 <5 07/27/04 <9 <9 <9 <4 <5 08/23/04 <12 <10 <8 <4 <5 09/28/04 <10 <14 (a) <9 <4 <6 10/25/04 <16 <10 <10 <5 <5 11/23/04 <19 <7 <14 <6 <8 12/21/04 <4 <7 <4 <2 <2 Zn-65 Zr-95 H-3 K-40 01/28/04 <10 <9 <66 02/24/04 <10 <7 <64 03/30/04 <10 <9 <1000 <68 04/27/04 <12 <9 <66 05/25/04 <10 <6 60 +/- 40 06/29/04 <11 <9 <1800 <77 07/27/04 <10 <7 62 +/- 31 08/23/04 <9 <7 <56 09/28/04 <10 <7 <1200 <48 10/25/04 <10 <8 <64 11/23/04 <11 <10 <86 12/21/04 <3 <3 <1000 <19 42

TABLE 3-9: GAMA1A EMITTER AND TRITIUM CONCENTRATIONS IN Rll'VER WIATER Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/liter +/- 2 Sigma Page 2 of 2 SAMPLING COLLECTIONl l LOCATIONS DATE l ISOTOPES Ba-1 40 Co-58 Co-60 Cs-134 Cs-137 SW-C 01/28/04 <8 <5 <6 <5 <5 02/24/04 <9 <6 <8 <5 <6 03/30/04 <9 <5 <6 <5 <7 04/27/04 <8 <6 <6 <5 <4 05/25/04 <7 <4 <5 <4 <4 06/29/04 <7 <6 <5 <7 <6 07/27/04 <6 <4 <4 <4 <4 08/23/04 <8 <5 <3 <4 <5 09/28/04 <9 <4 <4 <5 <4 10/25/04 <8 <3 <4 <4 <4 11/23/04 <12 <6 <7 <6 <5 12/21/04 <8 <3 <3 <3 <3 Fe-59 1-131 La-140 Mn-54 Nb-95 01/28/04 <10 <7 <10 <4 <6 02/24/04 <16 <9 <10 <5 <7 03/30/04 <13 <10 <10 <5 <5 04/27/04 <11 <10 <9 <5 <6 05/25/04 <11 <10 <8 <3 <5 06/29104 <11 <10 <9 <6 <7 07/27/04 <8 <10 <6 <3 <4 08/23/04 <10 <10 <9 <4 <5 09/28/04 <8 <14 (a) <10 <5 <6 10/25/04 <11 <8 <9 <4 <4 11/23/04 <16 <10 <14 <6 <6 12/21/04 <10 <8 <9 <3 <4 Zn-65 Zr-95 H-3 K-40 01/28/04 <8 <9 <67 02/24/04 <15 <8 <82 03/30/04 <11 <10 <1000 <51 04/27/04 <11 <7 <70 05/25/04 <9 <6 <45 06/29/04 <20 <9 <1800 <59 07/27/04 <8 <6 <49 08/23/04 <15 <7 <51 09/28/04 <11 <8 <1200 <51 10/25/04 <8 <6 <49 11/23/04 <10 <7 <68 12/21/04 <7 <6 <1000 <35 43

Table 3-9 Footnotes (a) LLD of 10 pCi/Liter for iodine-131 not met. A higher than required LLD was erroneously entered into the laboratory's information management system (LIMS). Upon error discovery, the sample could not be reanalyzed to meet the LLD due to excessive decay time from sample date.

44

TABLE 3-10: GAAMMA EMITTER CONCENTRATIONS IN SILT Surry Nuclear Pow-er Station, Surry County, \irginia - 2004 pCilkg (dry) +/- 2 Sigma Page I of I SAMPLING COLLECTION LOCATIONS DATE I Be-7 K-40 Th-228 Cs-134 Cs-137 SD 03/30/04 <580 15000 +/- 1300 1180 +/- 140 <52 220 +/- 59 09/20/04 2730 + 500 20200 +/- 1200 1330 +/- 130 <59 264 +/- 55 CHIC-C 03/30/04 <390 15500 + 1100 1130 +/- 110 <44 149 +/- 45 09/20/04 <620 20100 + 1100 1460 +/- 140 <53 219 +/- 51 45

TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/kg (dry) +/- 2 Sigma Page I of I SAMPLING COLLECTION ILOCATIONS DATE I Be-7 K-40 Th-228 Cs-134 Cs-137 HIR 02/03/04 <230 6720 k 610 133 + 60 <22 <26 08/02/04 <220 5590

• 540 120 t 56 <27 <29 CHIC-C 02/03/04 <270 4060 +/- 570 1067 + 96 <63 <38 08/02/04 <220 5280 +/- 570 159 + 63 <22 <22 46

TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/kg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE K-40 Co-58 Co-60 Cs-1 34 SD 04/12/04 Catfish 1700 +/- 240 <21 <16 <15 04/12/04 White Perch 1300 +/- 200 <17 <16 <18 11/01/04 Catfish 1430 +/- 240 <20 <18 <18 11/05/04 White Perch 1410 +/- 280 <22 <21 <19 Cs-137 Fe-59 Mn-54 Zn-65 04/12/04 Catfish <18 <68 <16 <40 04/12/04 White Perch <15 <51 <15 <37 11/01/04 Catfish <16 <53 <18 <49 11/05/04 White Perch <21 <77 <18 <58 47

TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Surry Nuclear Power Station, Surry County, Virginia - 2004 pCilkg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTIONl LOCATIONS DATE ISOTOPE K-40 Co-58 Co-60 Cs-134 POS 03/30/04 400 +/- 240 <29 <20 <23 09/20/04 <620 <39 <42 <25 Cs-1 37 Fe-59 Mn-54 Zn-65 03/30/04 <19 <91 <26 <67 09/20/04 <27 <140 <36 <84 K-40 Co-58 Co-60 Cs-134 MP 03/30/04 450

• 180 <21 <17 <18 09/20/04 <440 <31 <40 <31 Cs-1 37 Fe-59 Mn-54 Zn-65 03/30/04 <18 <68 <16 <37 09/20/04 <32 <140 <33 <94 48

TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Surry Nuclear Power Station, Surry County, Virginia - 2004 pCi/lkg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTIONl l LOCATIONS DATE ISOTOPE K-40 Co-58 Co-60 Cs-134 HIP 03/30/04 480 +/- 190 <21 <18 <21 09/20/04 <370 <25 <22 <24 Cs-137 Fe-59 Mn-54 Zn-65 03/30/04 <17 <67 <18 <40 09/20/04 <23 <83 <26 <64 K-40 Co-58 Co-60 Cs-134 SD 03/30/04 320 +/- 180 <22 <22 <23 09/20/04 360

• 230 <25 <28 <25 Cs-137 Fe-59 Mn-54 Zn-65 03/30/04 <17 <64 <16 <49 09/20/04 <28 <98 <31 <72 K-40 Co-58 Co-60 Cs-134 CHIC-C 03/30/04 <300 <23 <20 <17 09/20/04 <500 <35 <37 <29 Cs-137 Fe-59 Mn-54 Zn-65 03/30/04 <22 <78 <17 <47 09/20/04 <35 <110 <25 <78 K-40 Co-58 Co-60 Cs-134 LC 03/30/04 <290 <21 <17 <18 09/20/04 <390 <39 <29 <35 Cs-137 Fe-59 Mn-54 Zn-65 03/30/04 <19 <70 <20 <47 09/20/04 <33 <120 <35 <83 49

TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS Surry Nuclear Power Station, Surry County, Virginia -2004 pCiL/kg (wet) t 2 Sigma Page I of I SAMPLING COLLECTIONi LOCATIONS DATE ISOTOPE K-40 Co-58 Co-60 Cs-134 SD 06/16/04 1510 + 390 <29 <33 <30 Cs-137 Fe-59 Mn-54 Zn-65

<23 <97 <29 <54 50

4. DISCUSSION OF RESULTS L Data from the radiological analyses of environmental media collected during 2004 and tabulated in Section 3, are discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the L Framatome ANP 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 C.

lThe predominant radioactivity detected throughout 2004 was from external sources, L such as fallout from nuclear weapons tests (cesium-137) and naturally occurring radionuclides. Naturally occurring nuclides such as beryllium-7, potassium-40, and thorium-228 were detected in numerous samples.

Two deviations from the Radiological Environmental Monitoring Program requirements occurred in 2004. The deviating events were samples not being analyzed to the required iodine-131 LLD. One milk sample and two James River water samples were not analyzed to the required LLD.

L The July milk sample from the Colonial Parkway sampling station was cross-contaminated at the vendor laboratory. The laboratory equipment used in the iodine-131 analytical process became contaminated during the handling of the carrier verification samples that contain iodine-131. The milk sample was reprocessed after the laboratory concluded its investigation of the contamination event. The required LLD could not be achieved on the reanalysis due to the decay time from the sample date. As part of the laboratory corrective action plan, the laboratory staff was retrained on the safe handling of radioactive materials.

The second deviation was a failure to meet the required iodine-131 LLD for the September James River water samples from the Scotland Wharf and Surry L Discharge sampling stations. This deviation was caused by an incorrect entry of the iodine-131 LLD for non-drinking water samples in the vendor laboratory's information management system (LIMS). LIMS contains client specific data such as sample types, isotopes to analyze for, LLDs to achieve for each isotope per sample type, etc. In early October 2004, Dominion Millstone Power Station requested the laboratory to change the iodine-131 LLD for non-drinking water samples from 10 pCi/L to 15 pCi/L. Dominion Millstone's required iodine-131 LLD for this sample type is 15 pCi/L, while the required LLD for Dominion Surry is 10 pCi/L. The LIMS administrator at the laboratory misunderstood Dominion Millstone's request and changed the iodine-131 LLD for all Dominion nuclear stations. This error resulted in four river water samples not being analyzed to 10 51

I pCi/L for iodine-131. Two of the four samples, November and December Surry I Discharge, were reanalyzed to meet the iodine- 131 LLD.

mentioned September samples could not be reanalyzed to meet the iodine-131 The previously LLD due to excessive decay time. As part of the laboratory corrective action plan, I the iodine-131 LLD was reset to 10 pCi/L for Dominion Surry and the laboratory QA Manager also verified the reset. Additionally, laboratory procedures that direct LIMS file updates with client specific data have been revised to include review and independent verification of the changes made.

The following is a discussion and summary of the results of the environmental measurements taken during the 2004 reporting period.

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

lThe inner ring is located in the vicinity of the site boundary, and the outer ring is located at approximately five miles from the station. ILDs are also placed in special interest areas, such as population centers and nearby residences.

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

Figure 4-1: DIRECT RADIATION MEASURBEENT I TLD RESULTS

• 68 7

33

• E2-e00 0 0> 0r 0f 00 0

- Site Boundry 5 Mile Avg Control

• 52

- C (?CO

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. Also apparent in Figure 4-1 is the replacement, in 2001, of the previously used CaSO4:Dy in Teflon TLDs with a new type of TLD comprised of two elements each of CaF and LiF. Two TLDs are deployed at each monitoring location. The difference in response between the two systems is very apparent with the new TLDs reading up to 50% lower. The response trend has been monitored and it has been determined that one of the control locations (Smithfield, TLD location #41) may not represent a true control. The bias from the Smithfield control was not apparent prior to 2001 when the CaSO4:Dy TLDs were in use. The Smithfield TLD location is under evaluation and revisions to the REMP will be initiated for 2005 as appropriate.

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 i collected and analyzed for gross beta activity. Results of the weekly gross beta analyses are presented in Table 3-3. A review of the results indicates that the 2002 - 2004 average activity is 22% higher than the average activity since 1986.

The five year and ten year trends are 12% and 4% higher, respectively, than the average activity since 1986. However, results from control and indicator locations continue to show no significant variation in measured activities (see Figure 4-2 and 4-3). This indicates that any station contribution is not measurable. In addition, Surry Power Station changed analytical laboratories for REMP samples analyses in 2002.

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.

53

Rgure 4-2:2004 GROSS BETA IN AIR PARTICULATES 0.045 0.040 -

0.035 -

0.030 - & A 0.025 0.020 0.010 0.0 1o5 i *S! 311 1 t1 1 1,1 0.000

- o e~ cF c^ . t X Lf> £o 0 V 0t M 00 -- N

-__-4 _Avg In d S o : ---_ Av Coto Avg Indicator .. -- .. TyeControl]l Figure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND l.OE+00 (a)

I.OE-01 1.OE-02 r 1.OE-03 . . . . . . .. .. . . .

-I C r N0 00 ON 0 - l Cm r . 0 C 0 - C 00 00 00 00 00 00 ON 0\ 0s O 0oN Oa CN ON C 'i 0 0 0-c' o C: c'z ' c o c' c' c'Co' C' ' C' 0' ' I 0 0 0 l-4-Avg lndicator -+-Avg Control- Avg-Pre Op - Required LLD (a) Chernobyl 54 Co7

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.

L 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. 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 L needs to be evaluated very carefully when trying to determine if there are any station effects.

L 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 with the exception of that noted in Section 5, Program Exceptions. 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 2004.

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 two of the four composites analyzed, at an average concentration of 2.07 pCi/L. The average Sr-90 concentration for the ten year 55

L period of 1995 to 2004 is 1.92 pCi/L. The Sr-90 detected is not a part of station effluents but, rather, a product of nuclear weapons testing fallout. This LL conclusion can be made based upon (1) the lack of any positive indications of Sr-90 in effluents to account for such measurements, (2) the lack of any positive indications of Sr-89 in effluents (Sr-89 is chemically similar and would generally L be released in comparable quantities from the station), and (3) the trend of consistent declining levels since the pre-operational period.

L 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 L The analysis results for the James River water sampling program are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. These samples are also composited and analyzed for tritium on a quarterly basis. With the exception

- of naturally occurring potassium-40 observed in some samples analyzed, no other gamma emitters were detected. As noted in Section 5, Program Exceptions, two river water samples were not analyzed to the required LLD for iodine-131.

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 L 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 56

downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10 and trending 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). In 2004, no cobalt-60 was detected.

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

Cs-137 was detected with an average indicator location concentration of 242 pCi/kg and an average control location concentration of 184 pCi/kg. The concentrations indicate a continual decreasing trend as seen for over a decade.

The detection of Cs-137, at comparable and decreasing concentrations in both the control and indicator samples, indicates that its presence is the result of accumulation and runoff into the river of residual Cs-137 from weapons testing fallout. Its global presence has been well documented in national and international scientific reports. During the pre-operational period, Cs-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5.

Figure 4-4: COBALT-60 IN SILT L.OE+04 L.OE+03 i L.OE+02

0. 1L ILOE+01 L.OE+OO Cq t 0 00 0 es Cl 0 to 00 0 es 't C- t- r- o 00 0 t'- 00 00 00 00 00 Oh 0Z a, 0' C0 0 A oZ or oE at oF 0o oF on oE Oa a, 0\ 0 o0' 0 0

0 0

- _ _ _ _ - _ _ _-_ esl I Control Chickahominy

- A Station Discharr, Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were less than minimum detectable activity (MDA). Station Discharge was <MDA activity 1996 through 1998 and 2004.

57 Co?

Figure 4-5: CESIUM-1 37 IN SILT L.OE+04 l gIOE+03 AL A I

LOE+02 N N- N- 00 00 00 00 00 0, C, Ch ON ,

a, ON a, 0 0 a, a, 0 s0 0 l Control - Chickahominy Station Discharge .- Ave-Pre Op -Required LLD I

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

Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational results are presented in Table 3-11. uses. The The naturally occurring radioisotopes potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities. The activities of these radioisotopes indicate a steady trend.

radioisotopes attributable to the operation of the station There were no 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 l

• 58 co09 U

analyses are presented in Table 3-13.

lThere were no gamma emitting radioisotopes detected in oysters sampled except for naturally occurring radionuclides such as 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.

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 radioisotopes were detected in the sample. This is consistent with pre-operational data and data collected over the past decade.

59

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2004 - Surry Date of Location Description Sampling Reason(s) for Loss/Exception CP Milk; 07/06/04 Sample was not analyzed to the required LLD Iodine- 131 for iodine-131. The first sample aliquot was LLD cross-contaminated at the vendor lab. Too much time elapsed (decay) prior to the second sample aliquot analysis to meet the required LLD.

SD, River Water; September 2004 Analyses failed to meet the iodine-131 LLD of SW Iodine-131 10 pCi/L. Analytical laboratory LLD of record was 15 pC/L vice 10 pCi/L. Reanalysis of sample could not meet LLD due to excessive decay.

60

6. CONCLUSIONS The results of the 2004 Radiological Environmental Monitoring Program (REMP) 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.

> 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 2004 trend well with the control location.

The 2002 - 2004 average concentration trend is 22% higher than the average concentration trend from 1987 through 2004. The contract laboratory Interlaboratory Comparison Program data for particulate filter gross beta analyses was closely reviewed and no issues were identified. For the 2002 - 2004 period, the average vendor gross beta analysis was within 1.5% of the spike sample activity. Gaseous effluent release data was also reviewed and determined not to be a factor as the long term trend of activity released continues to decline. Due to satisfactory vendor performance, good effluent management practices and because the gross beta activity in the control and indicator locations show no significant variation, the increased gross beta trend seen in 2002 - 2004 is not attributable to the operation of Surry Power Station and may be more related to the change in analytical laboratories beginning in 2002.

> Milk - Milk samples are an important indicator measuring the effect of radioactive iodine and radioisotopes 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.

The maximum concentration of strontium-90 in this year's analysis was 3.3 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 2004.

> Well Water - Well water samples were analyzed and the analyses indicated that there were no man-made radioisotopes present. This trend is consistent throughout the monitoring period. No radioactivity attributable 61

to the operation of the station was identified.

River Water - All river water samples were analyzed for gamma emitting radioisotopes. Naturally occurring potassium-40 was detected in two samples. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2004.

> 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 was not detected in 2004.

> Shoreline Sediment - Only naturally occurring radioisotopes were detected, at concentrations equivalent to normal background activities. There were no radioisotopes 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 radioisotopes detected in any of the fish samples.

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

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

62

REFERENCES 63

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.

64

APPENDICES 65

APPENDIX A: LAND USE CENSUS Year 2004 66

LAND USE CENSUS*

Surry Power Station, Surry County, Virginia January 1 to December 31, 2004 Page I of 1 Nearest Nearest Nearest Nearest I Sectorl Direction I Resident I Garden** I Cow I Goat N 4.06 @ 100 (a) (a) (a)

NNE 1.90 @ 340 1.90 @ 340 (a) (a)

NE 4.60 @ 340 4.91 @ 560 (a) (a)

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

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

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

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

SSE 4.44 @ 1600 (a) (a) (a)

S 1.69 @ 1820 1.80 @ 1830 (a) (a)

SSW 2.34 @ 2120 4.26 @ 1950 4.84 @ 2000 (a)

SW 2.28 @ 2220 3.65 @ 2240 (a) (a)

WSW 0.41 @ 2440 3.57 @ 2460 (a) (a)

W 3.15 @ 2600 3.44 @ 2600 (a) (a)

WNW 4.90 @2830 (a) (a) (a)

NW 4.84 @ 3190 (a) (a) (a)

NNW 3.73 @ 3390 4.39 @ 3340 3.65 @ 3360 (a)

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

• • Area greaterthan 5O m2 and contains broadleafvegetation.

(a) None located within afive mile radius of Unit #1 Containment.

67

APPENDIX B: DOMINION NUCLEAR CONNECTICUT QA PROGRAM YEAR 2004 68

INTRODUCTION LL Dominion Nuclear Connecticut (DNC) maintains an independent non-required quality assurance (QA) program as part of the radiological environmental monitoring program (REMP). The QA program consists of contractor appraisals and quality control samples. This independent program is applicable to all L Dominion nuclear facilities because they share a joint contract with Framatome ANP Environmental Laboratory.

- DNC QA PROGRAM L The DNC independent QA Program includes spikes of various sample media and duplicate samples. Sample spikes are a check on the accuracy of results of the contractor's radioanalyses. Duplicate samples test the contractor's precision, or L reproducibility of results, by comparing analytical results of split samples. The number and type of DNC QA Program quality control samples are defined in LL Millstone Nuclear Power Station Health Physics Operations Procedure RPM 2.9.13, "Quality Control of Radiological Environmental Monitoring Program Sample Analyses". An investigation is conducted on any result or trend that does not satisfy acceptance criteria.

OTHER gA PROGRAMS L IThe DNC Independent QA Program is not the only QA Program which monitors REMP radioanalysis performance. Other programs include:

1. Contractor lab's internal QA program. In addition to the Millstone quality control samples, the radioanalysis contractor has its own quality control samples.

In total, at least five percent of the contractor's sample analyses include quality control samples.

2. Contractor lab's interlaboratory comparison program with an independent third party, Analytics, Inc. Results of the Analytics intercomparison are contained LL in Appendix C. Primary contractor participation in an interlaboratory comparison program is required by station Technical Specifications. The Analytics comparison satisfies this requirement.

L 3. Contractor lab's participation in the National Institute of Standards and Technology (NISl11 Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (P1 Program, the Department of L Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP). The lab participates in these interlaboratory QA programs because of other clients' needs, not because of nuclear power station environmental sample analyses. However, some of these intercomparison samples are also applicable to nuclear power environmental 69

samples.

L RESULTS OF MIaLSTONE gA PROGRAM FOR CONTRACTOR RADIOAIALYSES Criteria for passing QA sample analysis is that the result be within 20% of the l known spike except in the case of Sr-89 or Sr-90 spikes in milk which have to be within 30% of the known spike. To allow more tolerance for lower activity spikes an alternate criterion may be used. If the two sigma error range of the analyzed L result includes the known spike value, the result passes.

LThe Millstone QA Program indicated that the contractor lab's environmental radiological analysis program was adequate in 2004. Results are shown on Table

2. Of 104 individual nuclide analysis results on QA samples, 79 passed the acceptance criteria, a 76% success rate. TWenty-four sample results failed because of problems with the spike source or with sample preparation. There was one sample result failure associated with the contractor lab analyses.

L A self-assessment identified the adverse trend in failures of spiked sample analyses. A review of the spiking and sample preparation process identified a low bias, consistent with low sample results, when the low range on the adjustable L micropipette was used. Procedure revisions for pipette use were made and the results from December 2004 spike samples significantly improved.

L The analysis in disagreement is from a duplicate oyster sample. Silver-1 lOm was measured at 4.15E-02 pCi/kg in one sample and -3.OE-03 pCi/kg in the duplicate sample. No action was required from the vendor laboratory as this was a

' duplicate sample, rather than a spike sample, and because the 4.15E-02 pCi/kg concentration compared favorably to the recent historical trend for silver- 1 1Om.

70

TABLE 1 2004 QUALITY CONTROL SAMPLES SAMPLE N.ot"') ROUTIE:

t.-.-.,1/21 TYPE.r .QC-SAMPLES AM ESt Milk -Strontium 2 (Note 2) 12 Milk - Iodine 2 -30 Milk - Gamma (Note 3) -30 Water - Gamma 12 28 Water - Tritium 4 28 Fish/Invertebrate - Gamma 4 80 Vegetation/Aquatic Flora/Sediment/Soil - Gamma 0 81 Air Particulate - Gross Beta 6 416

- Iodine 2 416

- Gamma 4 32 FOOTNOTES:

1. All samples are spikes except fishrinvertebrate which are duplicate oyster samples.

2. One sample with Sr-89 and Sr-90 and one sample with Sr-90 only.

3. Gamma in water QA spikes are treated as milk surrogates.

TABLE 2 RESULTS OF 2004 QUALITY CONTROL SAMPLE ANALYSES

'SAMPLE

-.- ', e -ANALYSES ' Xi .::.ANALYSES.'

-P-A--o"EDt FAILED k

Milk - Strontium* 3 0 Milk- Iodine 2 0 Water - Gamma* 46 18 Water - Tritium 2 2 Oysters - Gamma 3 1 Air Particulate - Gross Beta 6 0

- Iodine 2 0

- Gamma 15 4 Individual Nuclides:

TOTALS Individual Nuclides: 79 25**

FOOTNOTE:

• Each nuclide was considered as an analysis for the strontium and gamma analyses.

• • There was one failure in QA sample results associated with the contractor lab analyses. Other sample failures were due to problems with the spike source or with sample preparation.

71

APPENDIX C:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2004 72

InTRODUCTION LL This appendix covers the Intercomparison Program of the Framatome ANP Environmental Laboratory. Framatome 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 L nucides. It was modified to more closely match the media mix presently being processed by Framatome and includes:

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

> filter for Sr-90 analysis during the 2nd, 3rd and 4th quarters.

In addition to the Analytics Intercomparison Program, Framatome also participates in other intercomparison programs. These programs are the National Institute of Standards and Technology (NIS'll 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 Framatome's internal bias acceptance criteria as defined below:

> within 25% of the known for gross beta in water, L ~> within 25% of the known for samples containing both Sr-89 and Sr-90,

> within 15% of the known value for other radionuclides, or L> within two sigma of the known value.

Framatome investigates any sample analysis result that does not pass these criteria.

Analytics Intercomparison Program results are included on the pages that follow for the first quarter through the fourth quarter of 2004. A total of 103 analysis

- results were obtained with 103 passing acceptance criteria, a 100% success rate.

L 1 73

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 1 OF 4) 1st Quarter Identification Reported Known 2004 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E4061-162 Milk 1-131 LL pCi/L 83.6 77.7 1.08 A 1-131 pCi/L 77.73 77.7 1.00 A Ce-1 41 pCi/L 92 85.2 1.08 A Cr-51 pCi/L 314 327 0.96 A Cs-1 34 pCi/L 88.7 90 0.99 A Cs-1 37 pCi/L 188.6 185 1.02 A Co-58 pCi/L 115 112 1.03 A Mn-54 pCi/L 114.7 114 1.01 A Fe-59 pCi/L 59.7 56.8 1.05 A Zn-65 pCi/L 145.5 143 1.02 A Co-60 pCi/L 154.8 153 1.01 A E4062-162 Milk Sr-89 pCi 86.2 103 0.84 A Sr-90 pCi 12.7 12.1 1.05 A E4057-162 Water Gr-Beta pCi/L 285.7 301 0.95 A E4058-162 Water 1-131 pCi/L 94 90.2 1.04 A 1-131 LL pCi/L 88.7 90.2 0.98 A Ce-141 pCi/L 87.5 85 1.03 A Cr-51 pCi/L 335 326 1.03 A Cs-1 34 pCi/L 86 89.7 0.96 A Cs-1 37 pCi/L 185.6 185 1.00 A Co-58 pCi/L 113.2 112 1.01 A Mn-54 pCi/L 112.3 114 0.99 A Fe-59 pCi/L 60.8 56.7 1.07 A Zn-65 pCi/L 149.1 143 1.04 A Co-60 pCi/L 151.4 153 0.99 A E4059-162 Water Sr-89 pci 107.7 123 0.88 A Sr-90 pCi 14.85 14.5 1.02 A E4060-162 Filter Gr-Beta pCi 231.1 218 1.06 A Footnotes are on page 4 of 4.

74

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 2 OF 4) 2nd Quarter Identification Reported Known 2004 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E4186-162 Milk 1-131 pCi/L 55 58.2 0.95 A I-1 31 LL pCi/L 59 58.2 1.01 A Ce-1 41 pCi/L 165 157 1.05 A Cr-51 pCi/L 241 228 1.06 A Cs-1 34 pCi/L 99 101 0.98 A Cs-1 37 pCi/L 157 156 1.01 A Co-58 pCi/L 46 46.2 1.00 A Mn-54 pCi/L 73 70.5 1.04 A Fe-59 pCi/L 48 44.5 1.08 A Zn-65 pCi/L 100 99.3 1.01 A Co-60 pCi/L 175 172 1.02 A E4182-162 Water H-3 pCi/L 11680 11900 0.98 A E4183-162 Filter Gr-Beta pCi 156 160 0.98 A E4184A-1 62 Filter Ce-141 pCi 86 88.3 0.97 A Cr-51 pCi 127 128 0.99 A Cs-1 34 pCi 54 56.9 0.95 A Cs-1 37 pCi 90 87.8 1.03 A Co-58 pCi 27 26 1.04 A Mn-54 pCi 42 39.7 1.06 A Fe-59 pCi 27 25.1 1.08 A Zn-65 pCi 62 56 1.11 A Co-60 PC! 92 96.8 0.95 A MAPEP-04-RdF12

• Filter Sr-90 pCi 20.3 22.4 0.91 A

• Filter from DOE Mixed Analyte Performance Evaluation Program (MEPAP), May 2004.

Footnotesare on page 4 of 4.

75

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 3 OF 4) 3rd Quarter Identification Reported Known 2004 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E4272-162 Milk 1-1 31 LL pCUL 79.4 83.5 0.95 A 1-131 pCiUL 81.1 83.5 0.97 A Ce-1 41 pCUL 240 235 1.02 A Cr-51 pCiUL 214 210 1.02 A Cs-134 pCitL 89.5 90.6 0.99 A Cs-1 37 pCi/L 204 202 1.01 A Co-58 pCi/L 90.9 89 1.02 A Mn-54 pCi/L 173 171 1.01 A Fe-59 pCi/L 91.3 86.1 1.06 A Zn-65 pCi/L 169 167 1.01 A Co-60 pCUL 116 118 0.98 A E4273-162 Milk Sr-89 pci 99.2 102 0.97 A Sr-90 pci 23.4 24.5 0.96 A E4269-162 Water Gr-Beta pCi/L 214 225 0.95 A E4270-162 Water 1-131 pCi/L 70.5 70.8 1.00 A 1-1 31 LL pCi/L 67.8 70.8 0.96 A Ce-1 41 pCi/L 258 250 1.03 A Cr-51 pCi/L 230 223 1.03 A Cs-1 34 pCi/L 93.4 96.4 0.97 A Cs-1 37 pCi/L 217 215 1.01 A Co-58 pCi/L 93.4 94.6 0.99 A Mn-54 pCi/L 181 181 1.00 A Fe-59 pCi/L 95.2 91.6 1.04 A Zn-65 pCi/L 180 178 1.01 A Co-60 pCi/L 126 125 1.01 A E4271 -162 Filter Gr-Beta pCi 191 194 0.98 A E4340-162 Filter Sr-89 pci 151 152 0.99 A Filter Sr-90 pci 53.5 58.8 0.91 A Footnotes are on page 4 of 4.

76

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY QA PROGRAM FRAMATOME ANP DE&S ENVIRONMENTAL LABORATORY (PAGE 4 OF 4) 4th Quarter Identification Reported Known 2004 Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d)

E4384-162 Milk 1-131 pCi/L 69 66.7 1.03 A 1-131 LL pCi/L 64.2 66.7 0.96 A Ce-1 41 pCi/L 154 155 0.99 A Cr-51 pCi/L 385 379 1.02 A Cs-134 pCi/L 167 170 0.98 A Cs-137 pCi/L 132 126 1.05 A Co-58 pCi/L 147 146 1.01 A Mn-54 pCi/L 144 136 1.06 A L Fe-59 Zn-65 pCi/L pCi/L 129 197 121 196 1.07 1.01 A

A Co-60 pCi/L 177 175 1.01 A E4380-162 Water H-3 pCi 8327 8060 1.03 A E4412-162 Water Sr-89 pCi 90.9 98.1 0.93 A Sr-90 pCi 9.33 11.3 0.83 A E4382-162 Filter Gr-Beta pCi 223 204 1.09 A E4383-162 Filter Ce-141 pCi 75.6 80.3 0.94 A Cr-51 pCi 201 189 1.06 A Cs-1 34 pCi 82.4 84.7 0.97 A Cs-137 pCi 68.8 62.9 1.09 A Co-58 pCi 75.3 72.9 1.03 A Mn-54 pCi 76.3 67.7 1.13 A Fe-59 pCi 69.8 60.5 1.15 A Zn-65 pCi 109 97.7 1.12 A Co-60 pCi 85.1 87.1 0.98 A L E4381-162 Filter Sr-89 pCi 87.7 92.3 0.95 A Sr-90 pCi 8.78 10.6 0.83 A (a) Framatorne reported result.

(b) The Analytics standard.

L (c) Ratio of Framatome to Analytics results.

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

77