Text

Transmittal of North Anna Units 1 & 2 and Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report for 2005
	ML061210391
Person / Time
Site:	North Anna
Issue date:	04/17/2006
From:	Jennifer Davis; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	06-292
	Download: ML061210391 (86)
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VIRGINIA ELECTRIC AND) POWVER COMPANY RIcnMOND, VIRGINIA 23261 April 17, 2006 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Serial No.NAPS/JRP Docket Nos.06-292 50-338 50-339 72-16 NPF-4 NPF-7 SNM-25r)7 License Nos.Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 & 2 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the Annual Radiological Environmental Operating Report for the January 1, 2005 through December 31, 2005, reporting period. It is provided pursuant to North Anna Units 1 and 2, Technical Specifications 5.6.2, and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c.If you have any questions or require additional information, please contact Page Kernp at (540) 894-2295.Very truly yours, Enclosure Commitments made in this letter: NoneI cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station 0 0 North Anna Power Station 20.05 Annual Radiological Environmental Operating Report Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2005 to December 31, 2005 Prepared by: James B. Breeden Supervisor Radiological Analysis Dominion North Anna Power Station Reviewed by: Approved by: Erich W. Dre er Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B. Evad, Jr.Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2 Table of Contents 1. EXECUTIVE

SUMMARY

...........................................................

4 2. PROGRAM DESCRIPTION

...........................................................

7 2.1 Introduction

...........................................................

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

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

22 3.1 Summary of Results ..........................................................

22 3.2 Analytical Results of 2005 REMP Samples ..........................................................

32 4. DISCUSSION OF RESULTS ..........................................................

59 4.1 Gamma Exposure Rate ..........................................................

59 4.2 Airborne Gross Beta ..........................................................

61 4.3 Airborne Radioiodine

..........................................................

62 4.4 Air Particulate Gamma ..........................................................

62 4.5 Air Particulate Strontium

..........................................................

63 4.65 Soil ..........................................................

63 4.7 Precipitation

..........................................................

63 4.3 Cow Milk ..........................................................

63 4.9 Food Products and Vegetation

..........................................................

64 4.10 Well Water ...........................................................

64 4.11 River Water ..........................................................

64 4.12 Surface Water ...........................................................

65 4.13 Bottom Sediment ..........................................................

.66 4.14 Shoreline Soil ...........................................................

67 4.15 Fish ...........................................................

68 5. PROGRAM EXCEPTIONS

..........................................................

69 REFERENCES

..........................................................

71 APPENDICES

..........................................................

73 APPENDIX A: LAND USE CENSUS ..........................................................

74 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS

..............................

77 3

1. EXECUTIVE

SUMMARY

T'his document is a detailed report of the 2005 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2b. Radioactivity levels from January 1 through December 31, 2005, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized.

The RP&MP 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 is monitored within a 25-mile radius of the station. North Anna 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 North Anna 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 North Anna 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-ciperational 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 Chemnobyl accident or natural variation.

Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and AREVA Environmental Laboratory provided radioanalytical 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, 1he Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified miriimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as 4 possible.

The NRC also mandates a reporting level for certain radionuclides.

Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.Analyical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, water, aquatic, terrestrial, and direct radiation exposure.

The airborne exposure pathway includes radioactive airborne iodine and particulates, and precipitation.

The 2005 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.Water and aquatic exposure pathway samples include surface, river and well water, silt and shoreline sediments, and fish. No plant related isotopes were detected in Lake Anna surface water except for tritium. The average 1ritium activity in surface water for 2005 was 3137 pCi/liter.

Naturally occurring potassium-40 was detected at average environmental levels. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritiurr level of 3170 pCi/liter.

No plant related radioisotopes were detected in well water. This trend is consistent throughout the environmental operational monitoring program. Both silt samples indicated the presence of naturally occurring thorium-228 at levels consistent with the natural background.

Shoreline sediment, which may provide a direct exposure pathway, indicated the presence of Th-228 also at levels consistent with natural levels. Cs-137 was present in sediment at 205 pCi/kg. Cs-137 was likewise present in shoreline soil at 181 pCi/kg. In both cases these Cs-137 levels are consistent with historic levels. TIhe terrestrial exposure pathway includes milk and food/vegetation products.

Iodine-131 was not detected in any 2005 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident.

No plant related radioisotopes were detected in any milk samples. A ten-year activity trend continues to indicate the slow decrease in Sr-90 activity.

Naturally occurring potassium-40 was detected at average environmental levels. Consistent with historical data, potassium-40 was detected.

The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDsI. ThD results have remained essentially constant over the years.During 2005, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) 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 2005 was 0.38 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, 5 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 North Anna Power Station.6

2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2005 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).The North Anna Power Station of Dominion Virginia Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia.

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 was designed with a gross electrical output of 979 megawatts electric (MWe). Unit 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 11998.The United States Nuclear Regulatory Commission (USNRC) regulations 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 North Anna Power Station includes Technical Specifications, which address the release of radioactive effluents.

In-plant monitoring is used to ensure 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 plant environs is also included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).North Anna Power Station is responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions is responsible for processing the TLDs. AREVA 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.

Occasional samples of environment media show the presence of man-made isotopes.

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 and North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As 7 Low As Is Reasonably Achievable".

This report documents the results of the Radiological Environmental Monitoring Program for 2005 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 2005 sampling program for North Anna Power Station.All samples listed in Table 2-1 are taken at indicator locations except those labeled"control." The North Anna Radiological Monitoring Locations maps denote sample locations for North Anna Power Station. The locations are color coded to designate sample types. Table 2-2 summarizes the analysis program conducted by AREVA Environmental Laboratory for North Anna Power Station during the year 2005.8 TABLE 2-1 North Anna Power Station -2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO.1 Sample Media Environmental Thermoltuninescent Dosimetry (TLD)Location Station NAPS Sewage Treatment Plant 01 Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Buumpass, VA End of Route 685 Route 700"Aspen Hills" Orange, VA Bearing Cooling Tower Sturgcon's Crcck Marina Parking Lot "C" (on-site)Good Hope Church Parking Lot "B" Lake Anna Marina (Bogg's Dr)Weather Tower Fence Route 689 Near Training Facility"Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)"Aspen Hills" Elk Creek NAPS Access Rd.02 03 04 05 O5A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-1 1/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 Distance 0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.47 Direction NE SSW WSW WNW NNE N ESE SSE WNW WSW SSE NW N N NNE NNE NE NE ENE ENE E E ESE ESE SE SE SSE SSE S Degrees 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 42°340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Collection Frequency Quarterly

& Annually Quarterly

& Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.9 TABLE 2-1 North Anna Power Station -2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 Thermoluminescent NAPS Access Rd. SSW-19/51 0.42 Dosimetry (TLD) Route 618 SSW-20/52 5.30 500kv Tower SW-21/53 0.6 Route 700 SW-22/54 3.96 NAPS Radio Towver WSW-23/55 0.38 Route 700 (Exclusion Boundary)

WSW-24/56 1.00 South Gate Switchyard W-25/57 0.32 Route 685 W-26/58 1.55 End of Route 685 WNW-27/59 1.00 Route 685 WNW-28/60 1.40 North Gate -Construction Side NW-29/61 0.45 S SSW SSW SW SW WSW WSW W W WNW WNW NW 1780 Quarterly 1970 Quarterly 2050 Quarterly 2180 Quarterly 2320 Quarterly 2370 Quarterly 2420 Quarterly 2790 Quarterly 274° Quarterly 3010 Quarterly 3030 Quarterly 3210 Quarterly Laydown Area Lakc Anna Campground

1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NW-30/62 2.54 NNW-31/63 0.07 NNW-32/64 2.21 C-1/2 7.30 C-3/4 22.00 C-5/6 7.10 C-7/8 11.54 NW NNW NNW SSE NW WSW WSW 3190 Quarterly 3490 Quarterly 3440 Quarterly 1670 Quarterly 3250 Quarterly 2430 Quarterly 2570 Quarterly Control Control Control Control Airborne Particulate NAPS Sewage Treatment Plant 01 and Radioiodine Fredericks Hall 02 Mineral, VA 03 Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Rtimpigc VA 04 05 05A 06 07 0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 NE SSW WSW WNW NNE N ESE SSE 420 Weekly 2030 Weekly 2430 Weekly 2870 Weekly 200 Weekly 110 Weekly 1150 Weekly 1670 Weekly* In October 1991 the Surface Water Sample location at station 09 %vas moved to 09A.** Shoreline soil was changed from station 09 to 08 effective Aith the August 1996 sample.10 TABLE 2-1 North Anna Power Station -2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks A : ----- -T1_ ..rA -.. t o X I fll I TNT I IIlI 0 I .111lA.I A1iruorne rarticuiMUi and Radioiodine End or XUute 6803 Route 700"Aspen Hills" Orange, VA I1 22 23 24 I .iu 1.00 0.93 22.00 WINVY WSW SSE NW JuI -2420 1580 3250 weeaty Weekly Weekly Weekly Control Surface Water River Water Ground Water (Well Water)Precipitation Waste Heat Treatment Facility 08 (Second Cooling Lagoon)*Lake Anna (upstream) 09A (Route 669 Bridge)3.37 SSE 1480 Monthly 12.90 WNW 2950 Monthly Control North Anna River (downstream) 11 5.80 SE 1280 Monthly Biology Lab 01A 0.64 SE 1380 Quarterly Biology Lab 01A 0.64 SE 1380 Monthly Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream) 08 3.37 SSE 1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually Control 11 5.80 SE 1280 Semi-Annually Shoreline Soil Soil Waste Heat Treatment Facility (Second Cooling Lagoon)NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 **3.37 SSE 1480 Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years* In October 1991 the Surface Water Sample location at station 09 was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.11 TABLE 2-1 North Anna Power Station -2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Soil Location 4 Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)"Aspen Hills" Orange, VA Station 05 05A 06 07 21 22 23 24 Distance 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 Direction NNE N ESE SSE WNW WSW SSE NW Degrees 200 110 1150 1670 3010 2420 1580 3250 Collection Frequency Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Remarks Control Milk Holladay Dairy (R.C. Goodwin)Terrell's Dairy (Fredericks Hail)Anderson's Farm 12 13 27 8.30 NW 5.60 SSW 2.49 ENE 3100 2050 660 Monthly Monthly Monthly Fish Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Orange 08 3.37 SSE 1480 Semi-Annually 3120 Semi-Annually 25 16.5 NW Control Food Products (Broadleaf Vegetation)

Bel Aire Plantation 14 1.20 NE 430 Monthly if available or at harvest Route 614 15 1.37 SE 1330 Monthly if available or at harvest Route 629/522 16 12.60 NW 0.93 SSE 3140 Monthly if available or at harvest 1580 Monthly if available or at harvest Control Aspen Hills 23"Historic Lane" 26 1.15 S 1720 Monthly if available or at harvest* In October 1991 the Surface Water Sample location at station 09 Was moved to 09A.** Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.12 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)(84 TLD:;)(12 TLD:;)Quarterly Annually Gamma Dose Gamma Dose 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month Airborne Radioiodine Airborne Particulate Weekly I-131 0.07 0.01 pCi/Mn 3 Weekly Gross Beta Quarterly (a)2 nd Quarter Composite Surface Water Monthly Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 I-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)Sr-89 Sr-90 0.05 0.06 (b)(b)1(c)15 30 15 15 30 30 15 15 18 60 15 2000 (b)(b)pCi/M 3 pCi/rn 3 pCi/L pCi/L pCi/L pCi/L Quarterly(a) 2 nd Quarter Composite River UWater Monthly I-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 1(c)15 30 15 15 30 30 15 15 18 60 15 pCi/L pCi/L*LLDs i adicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the these listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLI) for non-drinking water is 10 pCi/liter.

13 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPElE MEDIA River Water-Quarterly(a) 2 nd Quarter Composite ANALXYST Tritium (H-3)Sr-89 Sr-90 i/A 2000 (b)(b)REPORT UNITS pCi/L pCi/L Ground Water (Well Water)Quarterly Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)Sr-89 Sr-90 15 30 15 15 30 30 15 l(c)15 18 60 15 2000 (b)(b)pCiAL pCiAL pCiAL Quarterly(a) 2 nd Quarter Aquatic Sediment Semi-Annually Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 pCi/kg (dry)150 180 (b)(b)Annually pCi/kg (dry)Precipitation Monthly Semi-Annual Composite Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 4 15 30 15 15 30 30 15 1(c)15 18 60 15 pCi/L pCi/L Shoreline Soil Semi-Annually Gamma Isotopic Cs-134 Cs-137 Sr-89 150 180 (b)pCi/kg (dry)pCi/kg (dry)Annually*LLDs indicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the these listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCifliter.

14 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPJE MEDIA FREOUENCY Soil Milk Once per 3 years Monthly Monthly Quarterly Semi-Annually ANALYSIS Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 150 180 (b)(b)l 15 18 60 15 (b)(b)pCi/kg (dry)pCi/kg (dry)pCiIL pCiIL LL'D REPORT UNITS (b)Fish pCi/kg (wet)130 260 130 130 260 130 150 Food Products (Broadleaf Vegetation)

Monthly if available or at harvest Gamma Isotopic Cs-134 Cs-137 1-131 pCi/kg (wet)60 80 60*LLDs indicate those levels to which environmental samples are required to be analyzed.

Actual analysis of samples may be lower than the these listed values.(a) Quarterly composite of each location's samples are used for the required analysis (b) The:-e are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter.

15 Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation Environmental Station 1 (a) 01,NE-5/37 1A OIA,SE-13/45 2 (a) 02,SSW-20/52 3 (a) 03,C-5/6 4 (a) 04 5 (a) 05 SA (a) 05A,N-2/34 6 (a) 06,ESE-12/44 7 (a) 07,C-1/2 8 08-Water, Fish Sediment, Shoreline Soil 9A 09A-Water sample, sediment 11 11-River Water, Sediment 12 12-Milk 13 13-Milk 14 14-Vegetation, NE-6/38 15 Vegetation 16 Vegetation 21 (a) 21,WNW-27/59 22 (a) 22,WSW-24/56 23 (a) 23-SSE-15/47 24 (a)(b) 24,C-3/4 25 (c) 25-Fish 26 26-Vegetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.(b) In Orange (c) In Lake Orange 16 27 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57 16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 27-Milk C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E-10/42 X L ......co I CB3280C North Anna Environmental Map i Fixed Environmental Sampling Location* TLD Sampling* Garden Residents OriginalO 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.CB3282E C(3 North Anna Environmental Map* Fixed Environmental Sampling Location* TLD Sampling* Garden: Residents* Meat Animals Original 01991 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.CB3283D (05C North Anna Environmental Map* Fixed Environmental Sampling Location* TLD Sampling* Garden Residents* Meat Animals Original X) 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.C03281 D co5

3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the OI)CM.A more detailed analysis of the data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Surmmary Table because of the basic limitation of data summaries.

22 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 1 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-I Type No. I Range Direction Range Range ments Air Iodine (pCi/m 3)1-131 624 0.07 (0/572) N/A N/A N/A (0/52)0 Airborne Particulates (1E-03 pCi/m 3)Gross 624 0.01 22.8(572/572)

Beta (5.1-43.7) 01 0.20 mi.NE 24.5(52/52) 23.1(52/52)

(8.8-39.1)

(6.6-41.4) 0 Gamma 48 Be-7 48 Cs-134 48 0.05 Cs-137 48 0.06 Sr-89 12 -114(44/44)

(85/160)(0/44)(0/44)(0/1 1)23 0.93 125(4/4) 107(4/4)SSE (111-160)

(104-109)0 N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)(0/4)(0/1)0 0 0 Sr-90 12 (0/1 1)N/A N/A N/A (0/1)0 Ground Well Water (pCi/liter)

Tritium 4 2000 (0/4)N/A N/A N/A N/A 0 Gamma 4 Mn-54 4 15 (0/4)Fe-59 4 30 (0/4)Co-58 4 15 (0/4)Co-60 4 15 (0/4)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 23 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 2 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathwvay LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-l Type No. Range Direction Range Range ments Ground Well Water (pCi/liter)

River Water (pCi/liter)

Zn-65 4 30 (0/4)Zr-95 4 30 (0/4)Nb-95 4 15 (0/4)I-131 4 10 (0/4)Cs-134 4 15 (0/4)Cs-137 4 18 (0/4)Ba-140 4 60 (0/4)La-140 4 15 (0/4)Sr-89 1 -(0/1)Sr-90 1 -(0/1)Tritium 4 2000 3170(4/4)(1500-5100)

Gamma 12 Mn-54 12 15 (0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 11 5.80 mi. 3170(4/4)SE (1500-5100)

N/A N/A N/A N/A 0 Fe-59 12 30 (0/12)N/A N/A N/A N/A 0 24 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 3 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled. (Unit) Total (pCiunit)

Mean Name Distance Mean Mean Measure-I 2 Type No. L _ _ Range Direction Range Range ments River Wa.ter (pCi/liter)

Surface Water (pCi/liter)

I I Co-58 12 15 (0/12)Co-60 12 15 (0/12)Zn-65 12 30 (0/12)Zr-95 12 30 (0/12)Nb-95 12 15 (0/12)1-131 12 1 (0/12)Cs-134 12 15 (0/12)Cs-137 12 18 (0/12)Ba-140 12 60 (0/12)La-140 12 15 (0/12)Sr-89 1 -(0/1)Sr-90 I -(0/1)Tritium 8 2000 3137(4/4 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0) 08 3.37 mi. 3137(4/4)(0/4)-__1 (1630-4000)

SSE (1630-4000)

Gamma 24 25 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 4 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled. (Unit) lTotal (pCUunit)

Mean Name Distance Mean Mean Measure-Type L No. Range Direction Range Range I ments Surface Water (pCi/iter)

Mn-54 24 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 24 24 24 24 24 24 24 24 24 24 15 (0/12)30 (0/12)15 (0/12)15 (0/12)30 (0/12)30 (0/12)15 (0/12)1 (0/12)15 (0/12)18 (0/12)60 (0/12)N/A NIA N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)La-140 24 15 (0/12)Sr-89 I (0/1)N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)(0/1)(0/1)0 0 0 Sr-90 1 (0/1)26 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 5 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD _ Reported Samplec (Unit) Total (pci/unit)

Mean Name Distance Mean Mean Measure-Type No. , I Range Direction Range Range _ ments: Precipitation (pCilliter', Monthly Gross 12 Beta Semiannually Gamma 2 Mn-54 2 Fe-59 2 Co-58 2 Co-60 2 Zn-65 2 Zr-95 2 Nb-95 2 I-131 2 Cs-134 2 Cs-137 2 4 5.9(10/12)

(2.3-12.1) 15 (0/2)01A 0.75 mi.SE N/A N/A 30 15 15 30 30 15 10 15 18 (012)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)N/A N/A N/A N/A N/A NIA N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 5.9(10/12)

(2.3-12.1)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/0)0 NIA 0 N/A N/A N/A N/A NIA N/A N/A N/A N/A Ba-140 2 60 (0/2)N/A N/A NIA N/A 0 27 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 6 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCiunit)

Mean Name Distance Mean Mean Measure-__ _ Type No. __ I Range Direction Range Range ments La-140 2 15 (0/2)N/A N/A N/A N/A 0 Precipitation (pCi/liter)

Sediment Silt (pCi/kg) (dry)Gamma 6 K-40 6 14325(4/4) 11 5.80 mi. 17450(2/2) 10620(2/2) 0 (1700-20700)SSE (17200-17500)N/A (10300-19940)Cs-134 6 150 (0/4)N/A N/A (0/2)0 Cs-137 6 180 205(2/4)(87-322)11 5.80 mi. 205(2/2)SSE (87-322)08 3.37 mi. 1220(2/2)SE (430-2010)

Th-228 6 Sr-89 3 (Annually) 1178(4/4)(430-2010)

(0/2)(0/2)600(2/2)(509-690)(0/1)0 0 0 N/A N/A N/A Sr-90 3 (Annually)

(0/2)N/A N/A N/A (0/1)0 Soil (pCi/Kg) Kdry)Triennial Gamma 12 Cs-134 11 Cs-137 11 150 180 N/A N/A N/A Th-228 11 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Sr-89 11 N/A Sr-90 11 N/A 28 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 7 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Samplecl (Unit) Total (pCUunit)

Mean Name Distance Mean Mean Measure-Type No. Range J Direction Range Range ments Shoreline Soil (pCi/kg) (dry)Gamma 2 K-40 2-2455(2/2)(2100-2810) 8 3.37 mi.SSE 2455(2/2)(2100-2810)

N/A 0 Th-228 2-458(2/2)(375-540)8 3.37 mi. 458(2/2)SSE (375-540)N/A 0 Cs-134 2 150 (0/2)N/A N/A N/A N/A 0 Cs-137 2 180 181(1/2)(N/A)8 3.37 mi. 181(1/2)SSE (N/A)N/A 0 Sr-89 (Annually)

Sr-90 (Annually) 1 (0/1)N/A N/A N/A N/A N/A N/A N/A 0 1 (0/1)N/A 0 Gamma 24 Milk (pCi/liter,'

K-40 24-1370(24/24)

(1250-1480) 12 8.3 mi. 1389(12/12)

NW (1250-1453)

N/A 0 I-131 24 1 (0/24)Cs-134 24 15 (0/24)Cs-137 24 18 (0/24)Ba-140 24 60 (0/24)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 N/A 0 N/A 0 N/A 0 29 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 8 of 9 All Indicator Control Non-Medium or Anal sis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled. (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-_ Type No. , I Range Direction Range Range ments Milk (pCi/liter)

La-140 24 15 (0/24)N/A N/A N/A N/A 0 Fish (pCi/kg) (wet)Sr-89 8 (Quarterly)

Sr-90 8 (Quarterly)

Gamma 8 K-40 8 Mn-54 8 Fe-59 8 Co-58 8 Co-60 8 Zn-65 8 Cs-134 8 Cs-137 8 (0/8)(0/8)130 260 130 130 260 130 150 1388(4/4)(1070-1880)

(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)N/A N/A 08 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 3.37 mi. 1388(4/4)SSE (1070-1880)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1743(4/4)(1460-1950)

(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0 30 TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia -2005 Docket No. 50-338/339 Page 9 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location _ routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)

Mean Name Distance Mean Mean Measure-Type No. Range Direction Range Range _ ments Food Vegetation (pCi/kg) (wet)Gamma 20 Be-7 20 1248(16/16)

(350-2720) 23 varies 1273(4/4)SSE (690-2210) 778(4/4)(330-1460' 0 K-40 20 13346(16/16)

(7240-24800) 26 varies 13923(4/4)

S (10200-22100)14550(4/4)

(10200-20900)0 I-131 20 60 (0/24)Cs-134 20 60 (0/24)Cs-137 20 80 (0/25)N/A N/A N/A N/A N/A N/A 26 varies S N/A N/A N/A 560(1/4)(0/5)(0/5)(0/5)235(2/4)(220-250)0 0 0 0 Th-228 20 447(7/16)(223-954)Direct Radiation (mRlstd. month)(Environr.lental TLDs)Gamma Dose 48 2 3.7(44/44)

(1.7-6.4)23 0.93 mi. 5.1(4/4)SSE (4.4-6.2)3.4(4/4)(2.6-4.3)0 Direct Radiation (mRlstd. Month)(Annual TLDs)Gamma 12 Dose 2 3.6(11/11)

(1.7-5.4)23 0.93 mi.SSE 5.4(1/1)3.4(1/1)0 Direct Radiation (mRlstd. Month)(Sector TLDs)Gamma 256 Dose 2 5.2(256/256) 19/51('l 0.42 mi.(2.6-34.8)

SSW 33.5(8/8)(15.5-46.0) 3.3(32/32)

(2.5-3.6)0 (1) 19/5]. located onsite.31 3.2 Analytical Results of 2005 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.The data reported in the following tables are strictly counting statistics.

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

Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 3a).Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For the purposes of this report all valid data are presented in order to indicate any background biases. AREVA Environmental Laboratory's 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 North Anna ODCM.Data are given according to sample type as indicated below.1. Gamma Exposure Rate 2. Air Particulates, Gross Beta Radioactivity

3. Air Particulates, Weekly I-131 4. Air Particulates, Quantitative Gamma Spectra 5. Air Particulate Strontium 6. Soil 7. Precipitation

8. Cow Milk 9. Food Products and Vegetation

10. Well Water 11. River Water 12. Surface Water 13. Bottom Sediment/Silt

14. Shoreline Soil 15. Fish'Analy:ical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL, " letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).32 TABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mRIStd. Month (30.4 days)* 2 Sigma Pige 1 of 4 Station Name First Quarter 1/5/2005 4/6/2005 N-1 N-33 N-2 N-34 NNE-3 NNE-35 NNE-4 NNE36 NE-5 NE-37 NE-6 NE-38 ENE-7 ENE-39 ENE-8 ENE-40 E-9 E-41 E-1 0 E-42 ESE-11 ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 5.0 4.7 3.2 4.1 8.4 7.6 5.6 5.2 4.9 6.4 4.7 4.5 4.8 4.8 4.2 3.2 6.6 6.2 5.9 4.4 4.5 4.2 5.6 4.5 5.5 5.7 8.3 7.4 6.4 6.2 4.8 3.4 Second Quarter 4/6/2005 6/29/2005 3.8 3.9 2.4 3.2 6.9 5.6 4.6 4.4 3.8 3.8 4.0 3.6 4.7 4.8 3.0 2.6 5.0 4.8 4.8 3.8 3.4 3.7 4.8 4.6 4.6 3.6 7.0 7.0 4.8 5.1 2.4 2.5 Third Quarter 6/29/2005 9/28/2005 4.7 4.3 3.1 2.5 4.6 5.8 4.3 3.6 3.3 3.0 3.3 3.7 4.5 2.9 3.3 3.1 4.7 5.0 4.2 4.5 4.4 3.9 4.4 4.5 4.5 4.1 5.5 6.1 4.7 4.5 2.9 2.3 Fourth Quarter 9/28/2005 1/5/2006 5.1 5.8 3.7 3.6 7.3 7.3 5.1 5.0 5.2 5.0 3.9 4.1 5.1 5.1 3.9 3.6 5.9 5.7 4.6 4.9 5.1 4.7 5.5 4.8 5.0 4.8 6.6 6.9 5.5 5.7 3.4 3.7 Quarterly Average 4.6+/- 0.3 4.7+/-1.6 3.1 +/-1.1 3.3+/- 1.3 6.8 3.2 6.6 2.1 4.9+/-1.1 4.5 1.4 4.3 1.8 4.5 +/-2.9 4.0 +/- 1.1 4.0 +/- 0.8 4.8 +/-0.5 4.4 +/- 2.0 3.6 +/- 1.1 3.1 +/- 0.8 5.5 +/- 1.7 5.4 +/- 1.3 4.9 +/- 1.4 4.4 +/- 0.9 4.4 +/- 1.5 4.1 +/- 0.8 5.1 +/- 1.1 4.6 +/- 0.3 4.9 +/- 0.9 4.5 +/- 1.8 6.9 +/- 2.3 6.8 +/- 1.1 5.4 +/- 1.6 5.4 +/- 1.4 3.4 +/- 2.0 3.0 +/- 1.3 33 TABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) t 2 Sigma Page 2 of 4 Station Name S-1 7 S-49 S-18 S-50 SSW-19 SSW-Si SSW-20 SSW-52 SW-21 SW-53 SW-22 SW-54 WSW-2'3 WSW-5'WSW-24 WSW-5i W-25 W-57 W-26 W-58 WNW-27 WNW-59 WNW-28 WNW-60 NW-29 NW-61 NW-30 NW-62 NNW-31 NNW-63 NNW-32 NNW-64 First Quarter 1/5/2005 4/6/2005 9.1 9.1 2.6 2.6 42.1 31.2 2.5 3.4 3.4 5.1 5.6 5.7 6.6 6.6 5.9 4.7 7.3 8.0 2.8 2.7 4.4 4.8 3.4 3.0 7.0 6.8 3.6 3.3 5.6 4.9 5.1 4.2 Second Quarter 4/6/2005 6/29/2005 7.9 7.9 2.6 2.7 15.5 32.9 2.6 2.6 4.1 3.2 4.5 4.8 5.4 5.6 4.8 4.7 6.2 5.2 2.9 3.0 3.3 2.6 2.1 3.4 6.5 6.6 2.3 2.9 2.8 3.9 3.9 3.2 Third Quarter 6/29/2005 9/28/2005 6.8 6.4 2.7 2.6 24.9 39.6 2.3 2.2 4.7 4.0 4.2 4.4 4.8 4.9 4.1 4.0 6.2 6.2 2.9 2.1 3.2 3.2 3.0 2.7 5.9 5.6 1.8 2.6 2.5 3.4 3.8 3.8 Fourth Quarter 9/28/2005 1/5/2006 8.2 7.5 3.1 2.9 46.0 35.5 3.0 2.9 4.8 5.2 5.3 5.0 6.0 5.8 4.9 4.9 6.9 7.0 3.4 3.3 3.7 3.4 3.4 3.5 6.7 6.4 2.8 2.5 4.0 3.7 4.1 4.4 Quarterly Average 8.0:t 1.8 7.7 :t 2.3 2.7:+/- 0.5 2.7 :+/- 0.3 32.1 :+/- 28.7 34.8 t 7.3 2.6:i 0.5 2.8 : 1.0 4.6:t 1.7 4.4 :t 1.9 4.9 :t 1.4 5.0+/- 1.1 5.7 +/- 1.5 5.7 +/- 1.4 4.9 t 1.5 4.6:t 0.8 6.7+/-:t 1.1 6.6+/- 2.3 3.0 :t 0.6 2.8 +/- 1.1 3.6 t 1.1 3.5 +/- 1.8 3.0 +/- 1.3 3.2 +/- 0.8 6.5 t 1.0 6.4 +/- 1.0 2.6 +/- 1.6 2.8 +/-0.7 3.7 +/- 2.8 4.0 +/- 1.3 4.2 t 1.2 3.9 t 1.0 34 TABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days)

2 Sigma Page 3 of 4 Station Name C-1 C-2 C-3 C-4 C-5 C-6 C-7 C-8 EPSA-01 **EPSA-02**EPSF107-*O EPSF-04**EPSR-O!i**

EPSR-06**EPSJ-07**EPSJ-08**EPSP-09**EPSP-10(*'

First Quarter 1/5/2005 4/6/2005 4.0 3.8 3.3 4.3 2.3 3.3 3.0 3.8 5.9 6.1 5.5 5.6 6.3 6.7 4.2 5.4 9.8 9.0 Second Quarter 4/6/2005 6/29/2005 3.5 3.6 2.7 3.6 3.0 2.5 3.0 3.2 4.9 3.9 5.0 4.9 5.2 4.4 4.0 4.4 7.8 7.8 Third Quarter 6/29/2005 9/28/2005 3.5 3.4 3.1 3.3 1.8 2.6 3.5 3.3 4.5 3.6 3.1 4.2 3.3 3.7 2.9 3.6 6.3 6.8 Fourth Quarter 9/28/2005 1/5/2006 3.4 3.2 3.6 3.6 2.7 2.6 3.9 3.9 5.5 5.2 4.6 5.0 5.4 5.6 4.3 4.5 8.4 7.9 Quarterly Average 3.6 -t 0.6 3.5 :: 0.5 3.2 : 0.7 3.7 : 0.9 2.5 : 1.0 2.8 :t 0.7 3.3 :+/- 0.9 3.5 : 0.7 5.2+/-:t 1.2 4.7 :+/- 2.3 4.6 :+/- 2.0 4.9 +/- 1.2 5.1 +/- 2.5 5.1 +/-2.7 3.8 :+/- 1.3 4.5:t 1.5 8.1 +/- 3.1 7.9 : 1.8 Average +/-2 s.d.5.9 +/- 11.1 4.6 +/- 7.8 4.7 +/- 10.0 5.7 +/- 12.4 5.2 a: 10.5'- Refer tc 'Section 111, REMP Exceptions for Scheduled Sampling and Analysis During 2004** EmergEncy Plan TLDs. Included for informational purposes only. Not included in average 35 TABLE #3-2 DIRECT RADIATION MEASURMENTS

-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) i 2 Sigma Pz ge 4 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Annual TLD Station Name 1/5/2005 4/6/2005 6/29/2005 9/28/2005 Average 4/6/2005 6/29/2005 9/28/2005 1/5/2006 STA-01 6.4 3.8 3.1 5.3 4.7 +/- 3.0 4.5 STA-02 3.1 3.1 1.7 2.9 2.4 +/- 1.4 2.5 STA-03 3.0 1.9 2.0 2.5 2.4+/-t 1.0 1.7 STA-04 2.6 2.7 2.6 2.9 2.7 +/- 0.3 1.9 STA-05 4.6 4.3 3.7 3.9 4.1 0.8 3.7 STA-05A 4.3 2.7 2.6 3.4 3.2 +/-1.5 3.3 STA-06 5.4 4.6 4.5 4.9 4.9 +/- 0.9 4.9 STA-07 4.0 3.5 3.2 3.5 3.5 +/- 0.6 3.6 STA-21 3.8 3.3 3.3 3.3 3.4 +/- 0.5 3.7 STA-22 5.2 5.0 4.5 4.7 4.9 +/- 0.6 4.8 STA-23 6.2 4.5 4.4 5.2 5.1 +/- 1.7 5.4 STA-24 4.3 2.6 3.2 3.5 3.4 +/- 1.4 3.4 Average +/- 2 s.d.4.4 +/- 2.4 3.5 +/- 1.9 3.2 +/- 1.8 3.8 +/- 1.9 3.7 +/- 1.9 3.6t i2.3 36 Table 3-3 Air Particulate Grocs Beta Radionctivity

[pCi x 1 0-3/m3]-Period Ending 01/05/05 01/12/05 01/19/05 01/26/05 02102/05 02/09!05 02117/05 02123/05 03/02/05 03109/05 03116/05 03/23/05 03/30/05 04/06/05 04/14/05 04/20/05 04/28105 05/04/05 05/11/05 05/18/05 05/25/05 06102/05 06/08/05 06/15/05 06/22/05 06/29105 29.3 16.5 19.7 29.6 25.3 29.8 21.1 24.1 24.1 23.0 16.6 24.9 11.8 15.9 21.2 25.8 18.1 25.8 21.9 19.1 18.0 14.8 13.4 14.5 14.2 25.2 Station 01+1-+1-+1-+/-+1-+1-+1-+1-+1-+1-+/-+1-+1-+1-+/-+1-+1*+1-+1.+1-5.0 2.2 4.6 5.0 4.8 4.6 4.0 5.3 4.8 4.5 2.9 4.7 3.9 4.3 3.7 5.5 3.9 5.2 3.2 4.3 4.0 3.4 4.2 4.0 4.0 4.6 Station 02 23.1 +/-16.2 +/-19.2 +/-29.1 +/-16.2 +/-26.4 +I-17.3 +/ : 22.6 +I-17.2 +I-21.9 +I.17.4 +1-23.5 +I-11.9 +/-11.9 +/-17.7 +/-20.7 +I-15.3 +I-18.3 +/-23.7 +1 20.9 +I-15.3 +I-19.8 +/-9.4 +I 18.6 +I-13.2 +1-20.5 +I-4.7 2.2 4.6 5.0 4.3 4.4 3.9 5.2 4.5 4.4 2.9 4.6 3.9 4.1 3.6 5.0 3.8 4.8 3.3 4.3 3.8 3.7 3.9 4.3 3.9 4.4 Station 03 36.2 +1-18.7 +/-22.7 +1-29.0 +/-21.1 +/-24.3 +1 22.5 +/-19.7 +1-23.1 +/-27.8 +1-16.4 +/28.0 +1-8.4 +1 14.8 +/-20.8 +1-22.7 +1-19.9 +/-20.3 +/-22.4 +1-18.9 +1 12.8 +1-19.0 +1-12.5 +1 20.4 +1-15.7 +/-24.2 +1-5.3 2.3 4.8 4.9 4.6 4.4 4.1 5.1 4.7 4.7 2.9 4.9 3.7 4.3 3.7 5.2 4.0 4.9 3.3 4.2 3.8 3.6 4.2 4.4 4.0 4.6 Station 04 40.1 +I-19.2 +I-27.2 +I-30.8 +/-23.1 +I 27.8 +I-21.4 +I-26.5 +I-19.6 +I-23.5 +I 19.7 +/-25.0 +I-9.6 +I 17.2 +/23.4 +I 25.1 +I 17.6 +I 22.9 +I 21.8 +I-22.1 +I 15.1 +I 18.8 +/-9.3 +I-18.2 +I-14.2 +I 28.5 +I-Station 5.5 2.3 5.0 5.0 4.6 4.5 4.0 5.4 4.6 4.5 3.0 4.7 3.8 4.4 3.9 5.3 3.9 5.1 3.2 4.4 3.9 3.6 4.0 4.4 4.0 4.8 33.6 +I 15.9 +/-24.4 +I 30.3 +/23.6 +I-25.6 +I-20.2 +I-29.4 +I-19.9 +/-24.0 +I-17.6 +/18.9 +1-11.3 +/-13.7 -21.2 +/-23.0 +/-18.8 +/-18.7 +/18.9 +I 17.1 +I 13.7 +/14.9 +12.7 +/-15.8 +/-16.2 +/-24.8 +I-5.2 2.2 4.8 5.1 4.7 4.4 4.0 5.6 4.6 4.5 2.9 4.4 3.9 4.2 3.7 5.3 4.0 4.8 3.1 4.1 3.8 3.4 4.2 4.2 4.1 4.6 Station 36.8 +I-16.5 +/23.0 +/-30.7 +1 22.2 +I-26.2 +I-17.7 +I 23.3 +I-21.7 +/-22.8 +I-16.9 +/22.3 +I-7.9 +I 9.1 +/-15.3 +/22.6 +I-18.9 +I 23.8 +I-26.1 +I-20.0 +I-11.1 +1 18.9 +/-10.4 +I-20.4 +I-13.7 +/-24.3 +I-5.3 2.2 4.8 5.1 4.6 4.4 3.8 5.3 4.7 4.5 2.9 4.6 3.7 3.9 3.4 5.3 4.0 5.1 4.1 4.2 3.6 3.6 4.0 4.4 3.9 4.6 Station 06 34.1 +I-16.5 +I-23.8 +I-29.3 +I-19.9 +/-27.0 +I-19.9 +/-25.6 +I-18.3 +I 19.1 +1 14.9 +-20.3 +I 10.3 +1 10.2 +/22.1 +I-28.1 +I-17.1 +I-19.1 +I-20.0 +I-26.1 +I 14.1 +I 15.6 +/15.5 +1-18.3 +I 10.6 +1-19.2 +I-5.2 2.2 4.8 5.1 4.5 4.5 3.9 5.4 4.5 4.3 2.8 4.5 3.8 4.0 3.8 5.5 3.9 4.8 3.1 4.6 3.8 3.4 4.3 4.3 3.7 4.3 37 Table 3-3 Air Particulate Gross Beta Radioactivity

[pCi x 1 0-3/m3]-Period Ending 01/05/05 01/12/05 01/19/05 01/26/05 02102/05 02/09/05 02/17/05 02/23/05 03/02/05 03/09/05 03/16/05 03/23/05 03/30/05 04/06/05 04/14/05 04/20/05 04/28/05 05/04/05 05/11/05 05/18/05 05/25/05 06/02/05 06/08/05 06/15/05 06/22/05 06/29/05-Station 32.1 +/-15.1 +/-18.3 +/-23.2 +1-20.6 +1-23.0 +/-16.6 +/-20.7 +/-16.5 +/16.9 +/24.9 +/18.5 +/6.1 +/12.2 +/-17.8 +/26.0 +/-15.4 +/22.2 +1-21.3 +/-18.3 +/13.2 +/13.6 +/10.3 +/16.7 +/14.1 +/20.8 +/-5.1 2.2 4.5 4.8 4.5 4.2 3.8 5.2 4.5 4.2 4.9 4.4 3.6 4.1 3.5 5.4 3.8 5.0 3.2 4.2 3.7 3.3 4.0 4.2 3.9 4.4 Stationl 21 38.3 +1-18.0 +/-21.1 +/-29.5 +1-23.1 +/27.3 +1-22.9 +1-29.4 +-19.3 +/-24.0 +/-16.6 +/-24.6 +1-7.4 +-15.1 +/-17.9 +1-24.2 +1-15.7 +1 18.4 +/-21.4 +/-18.3 +/16.6 +/-18.1 +/14.0 +/19.5 +/12.9 +/24.3 +/5.4 2.3 4.7 5.0 4.7 4.5 4.1 5.5 4.6 4.5 2.9 4.7 3.7 4.3 3.5 5.3 3.8 4.8 3.2 4.2 3.9 3.6 4.3 4.3 3.9 4.6 Station 22 33.1 +/-9.7 +1 23.4 +/23.1 +/16.6 +/-22.6 +/-21.0 +/-25.2 +1-21.9 +1-22.0 +/15.6 +/25.3 +/8.6 +1-11.8 +/-20.7 +/20.2 +/-16.0 +/-20.3 +/20.0 +/-21.0 +/-13.6 +/-14.9 +-17.6 +/17.8 +/13.8 +/27.4 +/Station 5.1 2.0 4.8 4.7 4.3 4.3 4.0 5.4 4.7 4.4 2.9 4.7 3.7 4.1 3.7 5.1 3.8 4.9 3.1 4.4 3.7 3.4 4.5 4.2 3.9 4.7 27.5 +1--2.6 +1-31.4 +1 39.2 +-25.5 +1-33.6 +1-28.0 +1-29.6 +I-20.9 +I-20.8 +/-15.5 +-23.7 +1-8.5 +1-14.1 +/-23.4 +I-26.1 +/13.6 +/15.6 +/-21.1 +/22.8 +1-13.3 +-21.2 +/-13.0 +1 18.5 +/-10.9 +1 27.4 +1.4.9 5.3 5.2 5.4 4.8 4.8 4.3 5.6 4.7 4.3 2.9 4.6 3.8 4.2 3.9 5.3 3.8 4.7 3.1 4.6 3.6 3.7 4.2 4.3 3.8 4.7 Station 24 34.8 +1-15.9 +-22.8 +1-30.4 +1 24.4 +1 25.1 +/-19.6 +/-22.5 +I-22.2 +I-22.0 +/-16.6 +/-21.4 +/-6.6 +I-12.4 +1 19.6 +/-27.1 +/-16.6 +/-17.2 +/-22.1 +/21.7 +/-11.6 +/-17.4 +1 10.9 +1-20.0 +/-14.9 +1 24.2 +1-5.2 2.2 4.7 5.0 4.7 4.4 3.9 5.2 4.7 4.4 2.9 4.6 3.6 4.2 3.6 5.5 3.8 4.7 3.2 4.4 3.6 3.5 4.1 4.3 4.0 4.6 38 Table 3-3 Air Particulate

[pC meeBoin x -d1-^0 3 l/lm f[pCi X 103 3/m3]Period 07/07/05 07/13/05 07/20/05 07/27/05 08/03/05 08/10/05 08/17/05 08/24/05 08/30/25 09/07/05 09/14/05 09/21/05 09/28/05 10/05/05 10/12/05 10/19/05 10/26/05 11/02/05 11/09/05 11/16/05 11/23/05 11/30/05 12/07/05 12/14/05 12/21/05 12/28/05 1 Statio 01 22.2 +I-28.5 +I-16.4 +I-33.3 +-31.3 +-29.5 +I-30.0 +I-33.1 +I-22.9 +I-24.1 +I-35.9 +-34.4 +I-37.5 +/-27.5 +-8.8 +I-21.6 +/-24.8 +I-24.2 +I-39.1 +I-25.9 +I-27.0 +/-22.7 +-27.1 +/-37.7 +I-31.6 +/-34.3 +I-ii 3.8 5.0 3.8 4.7 4.7 4.5 4.6 4.8 4.6 4.0 5.4 5.1 5.3 4.7 3.9 4.7 4.6 4.7 5.2 4.9 4.9 4.3 4.5 5.6 5.2 5.0 Station 02 19.1 +/- 3.6 21.6 +/- 4.7 12.2 +/- 3.5 31.2 +/- 4.6 21.1 +/- 4.2 30.0 +/- 4.6 19.2 +/- 3.9 27.9 +I- 4.5 16.7 +/- 4.2 17.7 +/- 3.6 24.8 +I- 4.9 29.5 +I- 4.8 31.1 +/- 5.0 23.5 +I- 4.5 10.9 +/- 4.0 20.8 +/- 4.6 22.2 +I- 4.6 18.4 +/- 4.4 43.7 +I- 5.4 20.5 +/- 4.7 25.6 +I- 4.8 25.4 +- 4.5 24.8 +/- 4.4 29.6 +I- 5.2 24.5 +/- 5.0 31.1 +- 4.8 I-22.6 24.6 15.9 28.4 25.5 33.3 23.7 25.3 24.: 17.1 31.4 26.f 31.(22.1 6.C 18.'23.21.'41.'18.'12.1 25.'27.1 32.'27.(34.1 Station 03+/- 3.8 21.4+I- 4.8 25.9 9 +/- 3.8 16.8+I- 4.5 25.5+/- 4.3 25.0 3 +/- 4.8 39.2+/- 4.2 24.7 3 +I- 4.4 25.6+/- 4.7 20.2 9 +- 3.6 23.6 4 +/- 5.2 31.8 8 +I- 4.8 29.7 5+/- .9 36.0 1 +/- 4.5 28.5 0 /- 3.7 10.1+/- 4.5 17.5+/- 4.6 23.1 9 +/- 4.5 22.5 9 +/- 5.3 39.9 3 +- 4.6 27.2 9 +I- 4.2 32.2 2 +- 4.4 22.9 9 +- 4.6 29.4 4 +1- 5.3 32.2 0 +/- 5.1 33.6 3 +/- 5.0 33.5 Station 04+1-+1-+1-+1-+1-+1-+1-+1-+1-+1-+1-+1-+1-3.8 4.9 3.8 4.3 4.4 5.1 4.2 4.4 4.4 3.9 5.2 4.9 5.2 4.8 4.0 4.5 4.6 4.6 5.2 5.0 5.1 4.3 4.6 5.4 5.3 5.0 Station 05 22.4 4/-21.5 +/-14.5 +-22.3 +I-24.7 +I-36.2 +/-28.0 +/-30.6 +/-18.6 +/-15.5 +/-32.0 +/-28.4 +I-34.3 +I-18.6 +/-9.5 +I 21.9 +/-24.0 +/-21.9 +/-42.9 +/-24.6 +I-33.0 +/-24.8 +/-33.0 +/-38.3 +I-33.3 +I-35.9 +I-_I 3.8 4.6 3.7 4.1 4.3 4.9 4.4 4.6 4.3 3.4 5.2 4.9 5.1 4.3 3.9 4.7 4.6 4.5 5.3 4.8 5.1 4.4 4.8 5.5 5.4 5.1 Station 05A 20.9 +-24.6 +I-17.8 +/-29.7 +I-23.4 +I-41.8 +/-29.0 +/-22.8 +I-19.9 +-17.5 +/-29.7 +I-30.1 +/-29.3 +I-23.7 +I-7.3 +I-18.7 +/-20.5 +/-22.6 +I-37.7 +/-18.5 +/-26.0 +/-27.6 +/27.1 +/-29.6 +-27.8 +I-27.7 +I-3.8 4.7 3.9 4.6 4.3 5.2 4.5 4.2 4.4 3.6 5.1 4.9 4.9 4.5 3.8 4.5 4.5 4.6 5.1 4.6 4.8 4.5 4.5 5.1 5.2 4.7 21.6 25.2 11.A 29.2 20.6 32.: 26.C 27.: 17.<21.: 26.28.1 32.4 30.1 7.!19.1 22.1 19.1 39.1 26.1 30.(23.'28.1 27.: 32.: 33., Station 06+I- 3.8+I- 4.8+I- 3.5 2+- 4.5+/- 4.1 3 +I- 4.7 D +1- 4.3+I- 4.5 3 +I- 4.2 3 +I- 3.8+I- 4.9 s +I- 4.8 4 +/- 5.1 2 /- 4.8 S +I- 3.8 I +1- 4.5 4 /- 4.6 9 +I- 4.4 2 +I- 5.2 1 +I- 4.9 O +1- 5.0 9 +I- 4.3 6 +I- 4.6 2 +I- 5.1 2 +I- 5.3 7 +I- 5.0 I 39 Table 3-3 Air Particulate

[pCi x 1 0 3/m3]Period Station Station Station Station Station Ending l 07 l 21 l 22 l23 l24l 07/07/05 17.1 +/- 3.5 18.9 +1- 3.7 21.7 +/- 3.8 22.0 +/- 3.8 21.2 +/- 3.8 07/13/05 19.5 +/- 4.5 22.4 +/- 4.6 23.4 +/- 4.7 21.1 +/- 4.6 21.3 +/- 4.5 07/20/05 15.3 +/- 3.8 15.6 +/- 3.7 16.0 +/- 3.8 20.1 +/- 4.0 16.7 +/- 3.8 07/27/05 28.9 +1- 4.5 28.6 +1. 4.5 31.7 +/- 4.7 33.9 +1- 4.7 24.2 +/- 4.3 08/03/05 19.4 +/- 4.1 24.7 +1- 4.3 25.5 +1- 4.3 25.3 +1- 4.4 22.5 +1- 4.2 08/10/05 36.5 +/- 4.9 35.4 +/- 4.8 38.5 +/- 5.0 35.0 +/- 4.8 38.4 +/- 5.0 08/17/05 27.3 +1- 4.4 29.6 +1- 4.4 26.0 +/- 4.3 21.8 +/- 4.1 29.0 +/- 4.4 08/24/05 23.6 +1- 4.3 31.4 +/- 4.3 24.5 +1- 4.3 23.8 +1- 4.3 27.1 +/- 4.5 08/30/25 14.6 +/- 4.1 20.2 +/- 4.4 20.6 +/- 4.5 22.1 +/- 4.6 19.9 +/- 4.4 09/07/05 17.5 +/- 3.6 18.8 +/- 3.6 22.3 +/- 3.9 20.9 +/- 3.8 21.0 +/- 3.8 09/14/05 26.1 +/- 4.9 28.5 +/- 5.1 26.9 +/- 5.0 33.6 +/- 5.2 16.1 +/- 5.7 09/21/05 22.0 +/- 4.5 25.1 +/- 4.7 28.1 +/- 4.8 31.9 +/- 5.0 23.6 +/- 4.7 09/28/05 30.9 +/- 5.0 33.8 +/- 5.1 33.5 +/- 5.1 31.5 +/- 5.1 31.4 +/- 5.0 10/05/05 20.4 +/- 4.3 26.6 +/- 4.7 23.0 +/- 4.5 25.8 +/- 4.6 26.6 +/- 4.7 10/12/05 5.1 +/- 3.6 10.9 +/- 4.0 7.8 +/- 3.8 7.5 +/- 3.8 7.4 +/- 3.8 10/19/05 20.5 +/- 4.6 18.7 +/- 4.5 18.9 +/- 4.5 19.6 +/- 4.5 18.6 +/- 4.5 10/26/05 15.5 +/- 4.2 25.6 +/- 4.7 21.0 +/- 4.5 22.5 +/- 4.6 22.0 +/- 4.5 11/02/05 22.6 +/- 4.6 23.8 +/- 4.7 17.8 +/- 4.3 24.4 +1. 4.7 21.8 +/- 4.6 11/09/05 34.0 +/- 5.0 40.8 +/- 5.3 36.2 +/- 5.1 38.6 +/- 5.2 41.1 +/- 5.3 11/16/05 23.8 +/- 4.8 25.0 +/- 4.9 22.2 +/- 4.9 25.5 +/- 4.9 29.8 +/- 5.0 11/23/05 36.8 +/- 7.3 26.7 +1- 4.8 23.8 +/- 4.7 24.7 +1- 4.7 33.5 +1. 5.2 11/30/05 25.3 +/- 4.4 15.6 +/- 3.9 20.8 +/- 4.2 20.6 +/- 4.2 28.5 +/- 4.6 12107/05 21.3 +/- 4.2 28.4 +/- 4.6 25.6 +/- 4.4 26.7 +/- 4.5 31.0 +/- 4.7 12/14/05 29.5 +/- 5.2 32.1 +/- 5.4 32.9 +/- 5.4 31.1 +/- 5.3 41.4 +/- 5.7 12121/05 24.8 +/- 5.0 29.4 +/- 5.1 21.2 +/- 4.7 29.6 +/- 5.2 28.8 +/- 5.0 12/28/05 28.5 +/- 4.7 31.7 +/- 4.9 29.4 +1- 4.7 28.2 +/- 4.6 40.3 +/- 5.3 40 Table 3-4 Airborne Iodine I -Val1[pCi x 1 0'3/m3]Perdiod Ending 01/05/05 01/12/05 01/19/05 01/26/05 02/02/05 02/09/05 02/17/05 02/23/05 03/02/05 03/09/05 03/16/05 03/23/05 03/30/05 04/06/05 04/14/05 04/20/05 04/28/05 05/04/05 05/11/05 05/18/05 05/25/05 06/02/05 06/08/05 06/15/05 06/22/05 06/29/05 Station 01I 6.0-8.0 3.0 6.0-3.0 0.0 9.0 5.0.11.0 0.0 4.0 2.0 7.0-5.0 0.0-6.0-1.0-12.0.16.0-7.0 9.0 0.0 0.0-2.0-1.0 3.0+1-+I-13.0 13.0 15.0 18.0 14.0 14.0 16.0 16.0 13.0 14.0 17.0 13.0 11.0 14.0 15.0 14.0 12.0 15.0 16.0 16.0 12.0 16.0 17.0 15.0 16.0 14.0 Station 02-1.0 +/-2.0 +/.11.0 +1 12.0 +/6.0 +/-3.0 +/13.0 +/5.0 +1-5.0 +/-17.0 +/-1.0 +/3.0 +1-3.0 +1-5.0 +/5.0 +1 2.0 +/1.0 +/-1.0 +/-8.0 +/4.0 +/-9.0 +/0.0 +1-7.0 +/11.0 +/-1.0 +/14.0 15.0 15.0 24.0 16.0 14.0 14.0 18.0 16.0 16.0 12.0 14.0 14.0 16.0 15.0 15.0 12.0 15.0 16.0 16.0 19.0 13.0 20.0 15.0 14.0-6.0 3.0 0.0-2.0 8.0 11.0 0.0 0.0-3.0-15.0-1.0 O.C 7.C-3.C 12.C 0OC-S.C-6.C-4.C 8.C-11.c 11.(2.(-3.C 13.(Station 03+/.I +/-I +1-I+/.I Station 04 13.0 13.0 11.0 19.0 15.0 16.0 17.0 14.0 13.0 16.0 14.0 13.0 14.0 15.0 13.0 18.0 13.0 16.0 16.0 16.0 15.0 15.0 19.0 16.0 15.0 7.0-15.0 4.0 2.0-2.0-9.0 3.0-10.0-3.0-6.0-1.0 9.0-6.0 14.0 3.0-3.0-4.0-7.0-1.0 11.0 2.0 2.0 12.0 2.0 4.0+1.+1.+1-+1.+1.+1-+1.Station 05 13.0 16.0 14.0 16.0 14.0 16.0 15.0 19.0 16.0 16.0 16.0 17.0 12.0 15.0 17.0 16.0 14.0 17.0 15.0 19.0 14.0 14.0 16.0 10.0 14.0-4.0-5.0-11.0 0.0-5.0 6.0 11.0 12.0 6.0-2.0-1.0-11.0-15.0-3.0 15.0-5.0-5.0 3.0 3.0 13.0-9.0 0.0 0.0-3.0 0.0+1-+1.4/-4-4-4-+1-+1-13.0 14.0 14.0 20.0 15.0 14.0 14.0 17.0 13.0 18.0 15.0 14.0 14.0 16.0 15.0 17.0 14.0 18.0 16.0 15.0 17.0 14.0 19.0 14.0 14.0-3.C 3.C 0.0-8.C 12.C-14.C-1 .C-2.C 2.C-6.C 6.C 8.(7.C 6.(14.(-12.(-2.(Station 05A I 4/-I+/-I+/-I+/-13.0 13.0 14.0 17.0 15.0 15.0 14.0 19.0 16.0 16.0 16.0 12.0 14.0 17.0 12.0 15.0 14.0 15.0 25.0 16.0 18.0 15.0 17.0 15.0 11.0 7.0 9.0-16.0 6.0-5.C 1 1.0 4.0-14.C 8.C 5.C-3.C 0.C-7.C 8.C-2.C-6.(-2.(Station 06+/-I /-I+/-I+/-I +i/-I +/-I+/-I +/-I +/-I +/-I+/-) +/-) +I-I 13.0 1i.0 14.0 17.0 16.0 15.0 17.0 20.0 15.0 17.0 14.0 15.0 15.0 13.0 15.0 15.0 15.0 16.0 16.0 17.0 16.0 12.0 16.0 16.0 15.0-1.5 +/- 7.4 3.0 4/- 13.0 3.0 +/- 13.0-3.0 +/- 12.0 -4.0 4/- 11.0 7.0 +/- 11.0 41 Table 3-4 Airborne Iodine!- 131[pCi x 1 0-3/m3]Period l Station Station Station S tation Station Ending 07 21 1 22 23 I 24 01/05/05 -19.0 +I- 14.0 -3.0 +I- 14.0 9.0 +I- 13.0 2.0 +/- 14.0 -2.0 +I- 12.0 01/12/05 0.0 +I- 12.0 -9.0 +/- 13.0 -6.0 +/- 11.0 20.0 +/- 23.0 -2.0 +1- 15.0 01/19/05 4.0 +/- 15.0 -4.0 +/- 14.0 0.0 +/- 15.0 7.0 +/- 13.0 3.0 +/- 14.0 01/26/05 -4.0 +/- 21.0 0.0 +/- 20.0 -2.0 +/- 19.0 0.0 4/- 19.0 6.0 +/- 19.0 02/02/05 -13.0 +/- 14.0 2.0 +/- 14.0 -2.0 +/- 14.0 6.0 +/- 14.0 3.0 +/- 11.0 02/09/05 6.0 +1- 15.0 14.0 +/- 16.0 -11.0 +/- 13.0 -2.0 +/- 15.0 -8.0 +1- 16.0 02/17/05 3.0 +I- 12.0 -4.0 +I- 14.0 3.0 +I- 13.0 9.0 +I- 16.0 -4.0 +1- 17.0 02/23/05 -16.0 +/- 19.0 5.0 +/- 19.0 12.0 +I- 21.0 -3.0 +I- 19.0 2.0 +/- 21.0 03/02/05 6.0 +I- 16.0 -5.0 +I- 18.0 -5.0 +I- 18.0 0.0 +I- 17.0 -3.0 +I- 14.0 03/09/05 -2.0 +I- 16.0 8.0 +I- 16.0 2.0 +I- 18.0 9.0 +I- 15.0 -9.0 +/- 16.0 03/16/05 2.0 +I- 24.0 -3.0 I- 12.0 4.0 +I- 16.0 -9.0 +I- 16.0 -4.0 +/- 13.0 03/23'05 -11.0 +I- 15.0 -5.0 4/- 16.0 -5.0 4/- 15.0 -5.0 +/- 11.0 -8.0 +/- 16.0 03/30/05 4.0 +I- 13.0 -1.0 +I- 12.0 -16.0 +I- 14.0 0.0 +I- 13.0 1.0 +I- 13.0 04/06/05 5.0 +I- 14.0 -5.0 +I- 14.0 -8.0 +I- 16.0 -15.0 +I- 16.0 3.0 +/- 15.0 04/14105 3.0 +I- 13.0 7.0 +I- 14.0 -10.0 +I- 17.0 5.0 +/- 14.0 -1.0 +/- 15.0 04/20/05 3.0 +/- 17.0 10.0 +/- 17.0 -8.0 +/- 16.0 2.0 +/- 14.0 15.0 +/- 15.0 04/28/05 0.0 +/- 12.0 -5.0 +/- 11.0 7.0 +/- 11.0 -4.0 +/- 18.0 7.0 +/- 11.0 05/04/05 7.0 +/- 14.0 -1.0 +I- 15.0 -9.0 +I- 12.0 5.0 +I- 18.0 1.0 +/- 17.0 05/11/05 2.0 +I- 14.0 2.0 +/- 13.0 1.0 +I- 16.0 3.0 +I- 15.0 0.0 +/- 18.0 05/18/05 7.0 +1- 17.0 5.0 +/- 18.0 3.0 +/- 17.0 -4.0 +/- 20.0 -16.0 +1- 19.0 05/25/05 -20.0 +I- 18.0 0.0 +I- 19.0 9.0 +I- 18.0 2.0 +I- 18.0 -13.0 +I- 17.0 06/02/05 -2.0 +I- 13.0 -5.0 +/- 13.0 -18.0 +I- 16.0 6.0 +I- 13.0 -8.0 +I- 15.0 06/08/05 0.0 +I- 14.0 -2.8 +I- 7.3 7.0 +I- 12.0 -20.0 +I- 19.0 -4.0 +I- 16.0 06115/05 12.0 +I- 15.0 8.0 +/- 12.0 9.0 +/- 16.0 14.0 +/- 14.0 11.0 +/- 15.0 06/22/05 1.0 +/- 13.0 -7.0 +/- 13.0 0.0 +/- 11.0 -1.0 +/- 14.0 7.0 +/- 13.0 06/29/05 4.0 +/- 13.0 -4.0 +/- 13.0 -1.0 +/- 12.0 -4.0 +/- 12.0 -1.0 +/- 10.0 42 Table 3-4 I -131[pCi X 1 0 3/M3]Perriod Endin 07/07/05 07/13/05 07/20/05 07/27/05 08/03/05 08/10/05 08/17/05 08/24/05 08/30/05 09/07/05 09/14/05 09/21/05 09/28/05 10/05/05 10/12105 10/19/05 M10/605 11/02105 11/09/05 11/16/05 11/23/05 11/30/05 12107/05 12114/05 12121/05 12128/05 Station-1.0 0.0-8.0-7.0-8.0-10.0 7.0-9.0-11.0 9.0 3.0 14.0-10.0-3.0 2.0 1.0 5.0 10.0-20.0 4.0-8.0 11.0 6.0 8.0 4.0 0.0+1-+/-+/-+1-+/-13.0 1 8.0 14.0 14.0 14.0 12.0 1 5.0 12.0 17.0 14.0 12.0 16.0 15.0 15.0 16.0 16.0 16.0 17.0 16.0 16.0 13.0 18.0 15.0 18.0 22.0 17.0-3.0-7.0-7.0-2.0 5.0-6.0 0.0-12.0 0.0 12.0 1.0 14.0 5.0-2.0 0.0 9.0-9.0 B.C-B.C-4.0-13.C-5.C 0.0-S.C-2.C 13.C Station 02 I+/-I+/-I+/-I+/-I+/-I +/--I.15.0 13.0 17.0 14.0 16.0 13.0 15.0 18.0 14.0 11.0 13.0 16.0 14.0 14.0 14.0 19.0 15.0 14.0 14.0 16.0 19.0 17.0 17.0 19.0 23.0 6.0 -2.0 +-5.0 +-19.0 +11.0 +--6.0 +/0.0 +--2.0 +--13.0 +-9.0 +-1.0 +/-2.0 +--4.0 +-3.0 +/-5.0 +--7.0 +-14.0 +1 2.0 +--2.0 +--1.0 +--14.0 +--6.0 +--5.0 +--2.0 +-4.0 +-4.0 +/11.0 18.0 16.0 18.0 11.0 11.0 13.0 14.0 15.0 13.0 11.0 15.0 22.0 15.0 17.0 14.0 1 8.0 18.0 14.0 17.0 17.0 19.0 16.0 16.0 23.0 17.0 1.0 0.0 5.0-2.0-9.0 1.0 4.0 3.0-6.0 3.0 0.0 0.0-15.0 9.0 2.0-9.0 M~C 0.0 5.C 1.0-2.C-16.0 3.C 2.C-8.C-4.C Station----------

L-Station 04 4/7 I+/-I+/-I+/-I +/-I +/-I +/-I+/-I+/-13.0 15.0 16.0 16.0 16.0 11.0 15.0 17.0 15.0 14.0 11.0 13.0 15.0 12.0 16.0 13.0 19.0 24.0 15.0 13.0 18.0 17.0 14.0 15.0 22.0 17.0-1 .C-7.C 3.C 19.0 3.C 3.C-1 .C-11 .C-19.C-8.C 0.0 3.0 7.0-7.0-3.0 4.(21.0 13.(-7.0 17.(Station 05 I +/-)+7-+/-I +/-12.0 17.0 16.0 16.0 15.0 15.0 15.0 14.0 16.0 10.0 12.0 15.0 19.0 16.0 17.0 16.0 15.0 14.0 18.0 13.0 19.0 18.0 16.0 14.0 22.0 19.0 Station 05A 0.0 +/-17.0 +-0.0 /0.0 +--2.0 +/3.0 +--7.0 +-6.0 +/0.0 +--1.0 +--1.0 +/3.0 +--5.0 +-2.0 +1 2.0 +/-19.0 +--7.0 +--10.0 +/-6.0 +/-4.0 /5.0 +/3.0 +/13.0 +--3.0 +/-4.0 +/-7.0 +/1 5.0 18.0 15.0 13.0 14.0 12.0 13.0 16.0 20.0 11.0 12.0 12.0 17.0 15.0 14.0 12.0 15.0 14.0 14.0 15.0 16.0 18.0 18.0 16.0 24.0 20.0 0.0 19.0 0.0 9.0 5.0-12.0-12.0-5.0-8.0 3.0-7.0 2.0-3.C 6.0-3.C 7.C 3.C-5.C-3.C-9.C 14.C 0OC-5.C-3.C-2.C-15.(Station 06 I /-I /-I +-I +4-I +/-I +/-I +/-I+/-I 12.0 16.0 18.0 16.0 17.0 14.0 15.0 14.0 15.0 14.0 11.0 16.0 15.0 14.0 16.0 15.0 18.0 15.0 14.0 14.0 14.0 16.0 12.0 17.0 16.0 18.0 43 Table 3-4 Airborne Iodine!- 131[pCi x 1 0-3/m3]Period Station l Station l Station l Station Station Ending 07 21 22 23 24 07/07/05 0.0 15.0 3.0 12.0 -1.0 14.0 6.0 11.0 -4.0 +/- 14.0 07/13/05 -1.0 +/- 11.0 -3.0 +/- 15.0 -7.0 4/- 15.0 0.0 +/- 14.0 -7.0 +/- 14.0 07/20/05 -17.0 +/- 14.0 2.0 +/- 18.0 9.0 +/- 14.0 12.0 +/- 14.0 -3.0 +/- 15.0 07/27/05 0.0 +/- 16.0 15.0 +/- 19.0 9.0 +/- 16.0 -15.0 +/- 15.0 -17.0 +/- 18.0 08/03/05 -3.0 +/- 16.0 10.0 +/- 14.0 12.0 +/- 19.0 -3.0 +/- 16.0 10.0 +/- 15.0 08/10/05 7.0 +/- 14.0 6.0 +/- 11.0 10.0 +/- 12.0 1.0 4/- 11.0 0.0 +/- 15.0 08/17/05 6.0 +/- 14.0 -1.0 +/- 12.0 -4.0 +/- 12.0 6.0 +/- 13.0 0.0 +/- 11.0 08/24/05 0.0 +/- 13.0 16.0 +/- 18.0 -10.0 +/- 14.0 8.0 +/- 15.0 5.0 +/- 15.0 08/30/05 -10.0 +/- 17.0 -6.0 +/- 21.0 -2.0 +/- 18.0 4.0 +/- 14.0 10.0 +/- 17.0 09/07/05 3.0 +/- 13.0 1.0 +/- 13.0 0.0 +/- 13.0 -3.0 +/- 12.0 -3.0 +/- 13.0 09/14/05 3.0 +/- 12.0 -12.0 +/- 12.0 2.0 +/- 12.0 4.0 +/- 12.0 -3.0 +/- 3.2 09/21/05 -8.0 +/- 16.0 0.0 +/- 13.0 10.0 +/- 16.0 -3.0 +/- 17.0 5.0 +/- 17.0 09/28/05 -14.0 +/- 16.0 10.0 +/- 16.0 2.0 +/- 18.0 14.0 +/- 16.0 12.0 +/- 16.0 10/05/05 2.0 +/- 15.0 -5.0 +/- 14.0 -14.0 +/- 15.0 5.0 +/- 13.0 -13.0 +/- 15.0 10/12105 9.0 +/- 16.0 -2.0 +/- 15.0 15.0 +/- 18.0 -3.0 +/- 17.0 5.0 +/- 18.0 10/19/05 9.0 +/- 14.0 -6.0 +/- 16.0 -6.0 +/- 15.0 -1.0 +/- 14.0 -9.0 +- 14.0 10/26/05 4.0 +/- 20.0 -7.0 +/- 16.0 12.0 +/- 14.0 -16.0 +/- 14.0 9.0 +/- 17.0 11/02105 -18.0 +/- 17.0 5.0 +/- 16.0 0.0 +/- 16.0 8.0 +/- 17.0 -7.0 +/- 15.0 11/09/05 0.0 +/- 14.0 -8.0 +/- 16.0 2.0 +1- 15.0 6.0 +/- 13.0 -19.0 +/- 16.0 11/16/05 9.0 +/- 14.0 9.0 +/- 15.0 -6.0 +/- 15.0 7.0 +/- 14.0 0.0 +/- 13.0 11/23/05 4.0 +/- 21.0 9.0 +/- 18.0 -5.0 +/- 14.0 7.0 +/- 18.0 -4.0 +/- 11.0 11/30/05 11.0 +/- 17.0 -8.0 +/- 16.0 0.0 +/- 21.0 10.0 +/- 18.0 2.0 +/- 16.0 12/07/05 0.0 +/- 14.0 14.0 +/- 15.0 5.0 +/- 17.0 -3.0 +/- 12.0 -5.0 +/- 17.0 12/14/05 5.0 +/- 15.0 -2.0 +/- 15.0 0.0 +/- 18.0 -10.0 +/ 15.0 -10.0 +/- 18.0 12121/05 -2.0 +/- 17.0 0.0 +/- 19.0 6.0 +/- 18.0 0.0 +/- 21.0 -4.0 +/- 21.0 12128/05 -7.0 +/- 20.0 15.0 +/- 18.0 -11.0 +/- 21.0 2.0 +/- 19.0 21.0 +/- 22.0 44 Table 3-5 Airborne Particulate G,,vyr Snecrr nd St*rontiu r nm[Ap*i x1 .-LA -[pCi xIO'3/mn3J Sampling ILocation 01 02 03 04 05 05A 06 07 21 22 23 24 Quarter 1-1 Be-7 105.0 +/- 22.0 103.0 +/- 22.0 125.0 +/- 24.0 125.0 +/- 25.0 108.0 +/- 25.0 89.0 +/- 22.0 101.0 +/- 24.0 98.0 +/- 27.0 116.0 +/- 29.0 95.0 +/- 28.0 160.0 +/- 34.0 108.0 +/- 22.0 I K-40-0.4 +/- 7.1-0.4 +/- 5.2-1.4 +/- 4.5-2.7 +/- 7.3 0.6 +/- 7.1 5.3 +1- 8.9 0.8 +/- 5.4 2.3 +/- 8.0-1.3 +/- 6.9 0.4 +/- 9.2 4.4 +1- 7.7-3.1 +/- 3.6 I Cs-134 0.2 +/- 0.6 0.1 +/- 0.4 0.3 +/- 0.6 0.2 +/- 0.8-0.1 +/- 0.6-0.2 +/- 0.7 0.1 +/- 0.5 0.1 +/- 0.4 0.3 +/- 0.7-0.1 +/- 0.7 0.9 +/- 0.9-0.1 +/- 0.5 I Cs-137 0.2 +/- 0.5-0.1 +/- 0.3 0.2 +/- 0.2-0.4 +/- 0.4 0.1 +/- 0.4 0.1 +/- 0.4-0.1 +/- 0.5 0.0 +/- 0.4-0.1 +/- 0.6 0.8 +/- 0.7-0.4 +/- 0.7 0.2 +/- 0.5 I Sampling ILocation I Be-7 01 92.0 +/- 30.0 02 100.0 +/- 27.0 03 117.0 +/- 30.0 04 99.0 +0 -27.0 05 110.0 +/- 29.0 05A 114.0 +/- 31.0 06 110.0 +/- 28.0 07 89.0 +/- 26.0 21 143.0 +/- 31.0 22 93.0 +/- 28.0 23 113.0 +/- 28.0 24 107.0 +/- 30.0 Sr-89/90 sampled in 2nd Qtr.Quarter 2 I K-40-3.0 +/- 10.0-4.5 +1- 7.4 5.3 +/- 9.8 1.1 +/- 8.5-5.7 +1- 7.8-3.2 +/- 8.3 2.5 +/- 8.9-1.5 +/- 9.2-0.5 +/- 7.0 4.0 +/- 10.0 7.0 +/- 10.0 1.2 +/- 9.3-I Cs-134 0.4 +/- 0.7-0.2 +/- 0.8-0.1 +/- 0.7-0.7 +/- 0.7-0.5 +/- 0.6 0.1 +/- 0.8 0.0 +/- 0.5 0.1 +/- 0.7-0.2 +/- 0.7-0.3 +/- 0.6 0.4 +/- 0.5-0.2 +/- 0.4 I CS-137 0.2 +/- 0.5-0.9 +/- 0.8 0.9 +/- 0.7-0.3 +/- 0.6-0.2 +/- 0.7 0.0 +/- 0.7-0.4 +/- 0.6-0.1 +/- 0.5-0.2 +/- 0.7 0.0 +/- 0.8-0.3 +/- 0.6 0.1 +/- 0.7 I Sr-89-3.0 +/--12.9 +/--5.0 +/--5.0 +/-5.0 +/--3.5 +I--2.0 +/--6.0 +/--7.6 +I--7.9 +I-0.0 +/--7.0 +/-11.0 0.8 11.0 8.1 14.0 9.4 10.0 10.0 8.4 9.2 10.0 2.4 I Sr-90 0.3 +/-1.8 +/-1.4 +/-1.6 +/-1.1 +/-1.0 +/-1.4 +/-2.3 +I-2.3 +I-2.3 +I-1.8 +/-1.4 +/--j 0.3 1.7 2.8 1.4 3.0 1.6 2.5 1.9 1.6 1.8 1.7 2.4 45 Table 3-5 Airborne Particulate and Strontium-nn xln 0/ntmr][pCi x1 0-3/m3]SamplinglLocation 01 02 03 04 05 05A 06 07 21 22 23 24 Quarter 3-I Be-7 149.0 +/- 30.0 126.0 +/- 27.0 125.0 +/- 32.0 130.0 +/- 30.0 117.0 +/- 28.0 138.0 +/- 29.0 112.0 +/- 28.0 111.0 +/- 28.0 143.0 +/- 29.0 91.0 +/- 25.0 111.0 +/- 29.0 109.0 +/- 28.0 I K-40 0.8 +/-1.9 +/--3.4 +/-0.6 +/--16.7 +/--0.9 +/--0.9 +/-2.2 +I-12.0 +/--4.9 +I--3.6 +I-7.0 +/-9.3 8.1 8.9 8.5 9.2 7.0 7.0 9.7 12.0 7.4 6.9 12.0 I Cs-134 0.1 +/- 0.7-0.2 +/- 0.6-0.3 +/- 0.9 0.4 +/- 0.5-0.2 +/- 0.6 0.4 +/- 0.6 0.6 +/- 0.7-0.2 +/- 0.7-0.2 +/- 0.9 0.4 +/- 0.6 0.3 +/- 0.9-0.2 +/- 0.6 I CS-137-0.2 +/- 0.7-0.1 +/- 0.8-0.5 +/- 0.8 0.2 +/- 0.6-0.6 +/- 0.7-0.1 +/- 0.7-0.4 +/- 0.7 0.0 +/- 0.6-0.4 +/- 0.8-0.2 +/- 0.7 0.2 +/- 0.7-0.1 +/- 0.6 I___Sampling Lzocation 01 02 03 04 05 05A 06 07 21 22 23 24 Quarter 4-I Be-7 124.0 +/- 30.0 109.0 +/- 31.0 112.0 +/- 31.0 140.0 +/- 34.0 110.0 +/- 30.0 121.0 +/- 31.0 121.0 +/- 31.0 132.0 +/- 34.0 85.0 +/- 29.0 92.0 +/- 28.0 115.0 +/- 32.0 104.0 +/- 32.0-8.1 +1- 7.6 5.0 +/- 10.0 5.7 +/- 9.2 9.7 +1- 8.9 4.4 +/- 9.6 13.0 +/- 11.0 1.6 +1- 8.7 1.2 +/- 5.8 6.8 +/- 8.0-5.6 +/- 4.6 2.0 +1- 10.0 6.0 +/- 10.0-0.1 ++- 0.7 0.0 ++- 0.8-0.5 +/- 0.8 0.1 +1- 0.6-0.2 ++- 0.7-0.3 ++- 0.8-0.1 ++- 0.7-0.5 +1- 0.9 0.4 +/- 0.7 0.3 +/- 0.6-0.2 +/- 0.5-0.4 +/- 0.7 I Cs-137-0.2 +/- 0.7-0.1 +/- 0.7-0.1 +/- 0.7-0.6 +/- 0.6 0.4 +/- 0.6-0.5 +/- 0.7 0.4 +/- 0.6-0.3 +/- 0.6-0.5 +/- 0.6 0.1 +/- 0.6-0.6 +/- 0.7-0.1 +/- 0.6 46 Table 3-6 QniI Gamma Spectra and Strontium[pCi/kg]I Station I Sr-89 I Sr-90 I Be-7 I K-40 I Cs-1 34l Cs-137 I Th-228 I 01 02 03 04 05 05A 06 07 21 22 23 24 Soil Not Collected 2005 47 Table 3-7 Pre initntion Gamma Spectra[pCi/L]06/28/2005 Sampling Location I Be-7 I K-40 I Cr-51 I Mn-54 I Fe-59 I Co-58 I Co-60 l 01A 3.0 +/- 19.0 37.0 +/- 29.0-14.0 +/- 19.0 1.6 +/- 2.4-0.2 +/- 7.5-0.4 +/- 2.6 0.7 +/- 2.7 Zn-65 Zr-95l Nb-95 Ru--103 I Ru-106l Sb-125l 1-131 01A 8.0 +/- 10.0-1.7 +/- 4.5-1.3 +/- 2.9-2.1 +/- 2.6 11.0 +/- 21.0 3.1 +/- 6.3-0.9 +/- 2.5 0 Cs-1 342-0.2 +/- 2.8-0 Cs-137 0.2 +/- 2.0 2 Ba-140 2.2 +/- 4.0 25La-1 40 2.5 +/- 4.6 I Th-228 4.0 +/- 11.0 I 01A 12/28/2005 Sampling Location I Be-7 I K-40l Cr-51l Mn-54 I Fe-59 I Co-58 I Co-60 I 01A 24.0 +/- 10.0-4.0 +/- 11.0 5.0 +/- 13.0-0.4 +/- 0.7 1.1 +/- 2.1 0.6 +/- 1.2 0.6 +/- 0.7 I Zn-65 Zr-95l Nb-95l Ru-1 03 I Ru-1 06 I Sb-125l 1-131 I 01A-0.4 +/- 2.2 0.0 +/- 1.5-0.7 +/- 1.2-1.3 +/- 1.7-5.6 +/- 6.6-1.1 +/- 1.9 0.2 +/- 0.5 I Cs-134 I Cs-137 I Ba-140l La-140 I Th-228 I 01A-0.4 +/- 0.7 0.1 +/- 0.8-0.2 +/- 4.2-0.2 +/- 4.9 1.8 +/- 3.8 48 Tnhl. ';-7 Precipitation Gross Beta[pCi/L]-Sampling Date l01/26/05 02/23/05 03/30/05 04/28/05 Gross Beta 5.2 +/- 2.1 I-12.1 +I- 2.8 3.5 +/- 2.0 11.1 +/- 2.7 I Rainfall (inches)2.91 1.62 4.50 1.59 05/25/05 06/28/05 07/27/05 08/30/05 09/28/05 10/26/05 11/30/05 12/28/05 8.2 +/- 2.3 no sample 2.3 +/- 1.7 3.4 +/- 1.9 no sample 4.6 +/- 2.1 4.7 +1- 2.1 4.2 +/- 2.1 3.69 0.88 4.25 5.04 0.46 7.88 2.94 3.81 Total =39.57 49 Table 3-8 Milk.' a " ' a .r I- _ _,-Date I K-40.01/19/05 02/17/05 03/23/05 04/14/05 05/11/05 06/15/05 07/13/05 08/10/05 09/14/05 10/19/05 11/16/05 12/21/05 Date 01/19/05 02/17/05 03/23/05 04/14/05 05/11/05 06/15/05 07/13/05 08/10/05 09/14/05 10/19/05 11/16/05 12/21/05 1390.0 1290.0 1480.0 1380.0 1410.0 1360.0 1410.0 1370.0 1310.0 1430.0 1440.0 1401.0 110.0 160.0 170.0 140.0 130.0 170.0 110.0 120.0 120.0 140.0 130.0 95.0 I Sr-89 I Sr-90[a] [a][a] [a]-0.2 +/- 4.5 0.4 +/-[a] [a][a] [a]-2.6 +I- 4.4 0.0 +/-[a] [a][a] [a]0.1 +/- 5.6 1.3 +/-[a] [a][a] [a]1.5 +/- 4.2 -0.2 +/-1.0 1.1 1.0 0.9[pCi/L]l-131-0.03 +I- 0.20-0.13 +I- 0.05 0.19 +I- 0.34-0.14 +I- 0.05 0.01 +I- 0.25-0.16 +I- 0.06 0.31 +I- 0.40-0.01 +I- 0.15-0.05 +I- 0.29-0.16 +/- 0.06-0.06 +/- 0.18 0.03 +/- 0.33 1-131 0.21 +/- 0.47-0.12 +I- 0.04-0.06 +I- 0.03-0.11 +I- 0.04 0.01 +I- 0.26-0.17 +I- 0.06 0.02 +I- 0.23-0.06 +I- 0.02-0.17 +I- 0.06 0.07 +/- 0.35-0.05 +/- 0.21 0.30 +/- 0.53 Cs-134-1.0 +/- 2.8-1.9 +1- 4.7 0.3 +/- 4.6-0.7 +/- 4.2 2.8 +I- 3.7 2.6 +I- 4.7 0.3 +/- 3.4-0.2 +I- 3.5 1.6 +I- 3.2 0.8 +/- 3.7 2.1 +/- 3.6 2.6 +I- 2.8 ffCs-134 3.1 +/- 3.3-0.3 +/- 4.2-0.3 +/- 4.0 0.9 +/- 3.8-2.6 +I- 3.8 1.1 +/- 4.3-0.9 +/- 3.7 0.4 +/- 2.4-2.1 +/- 4.8-2.8 +I- 4.6 1.3 +/- 3.2-1.7 +/- 3.0-I Cs-137-0.9 +/- 3.1-1.3 +/- 4.1 3.7 +/- 3.6-2.4 +/- 3.6 0.9 +/- 3.9-2.5 +/- 4.3 0.8 +/- 2.8 1.6 +/- 3.4 1.8 +/- 3.4-1.6 +/- 3.6 1.7 +/- 3.2-0.2 +/- 2.3-lBa-140 1.9 +/- 5.6 2.3 +/- 7.0 2.6 +I- 5.6-1.7 +/- 5.1 0.0 +/- 4.9 2.9 +I- 6.6 2.5 +I- 3.6-1.6 +/- 5.3-1.4 +/- 4.8-1.0 +I- 5.5 1.9 +I- 6.3-2.1 4I- 4.7lBa-140 3.1 +I- 4.8-2.3 4I- 5.8 2.1 +I- 5.1-3.0 +I- 6.1-5.1 +I- 5.3 0.1 +I- 6.4-1.0 +I- 4.4-3.9 +I- 4.7-5.2 +I- 4.6 0.0 +I- 5.9-1.1 +I- 5.2 2.4 +I- 5.1-Station 12_ La-140 l2.2 +/- 6.4 2.6 +/- 8.1 3.0 +/- 6.4-1.9 +I- 5.8 0.0 +/- 5.7 3.3 +/- 7.6 2.9 +/- 4.2-1.8 +/- 6.1-1.6 +/- 5.5-1.1 +/- 6.3 2.2 +/- 7.3-2.4 +I- 5.4 I-l K-40 1250.0 +/- 110.0 1400.0 +I- 160.0 1390.0 +/- 150.0 1360.0 +/- 130.0 1330.0 +/- 130.0 1310.0 +/- 170.0 1400.0 +/- 130.0 1453.0 +/- 90.0 1290.0 +/- 140.0 1250.0 +/- 130.0 1400.0 +/- 120.0 1364.0 +/- 99.0[ Sr-89[a][a]3.0 +/- 5.4[a][a]-1.1 +/- 4.4[a][a]0.9 +/- 5.1[a][a]3.4 +I- 4.6-Sr-90[a][a]1.4 +1-[a][a]-0.9 +/-[a][a]0.0 +/-[a][a]0.2 +/-I 1.0 1.0 Cs-137 2.8 +/- 2.7 3.3 +/- 4.5-1.3 +/- 4.2 0.4 +/- 3.6-0.7 +I- 3.1 3.8 +/- 4.3-2.2 +/- 3.2 0.7 +/- 2.6-1.4 +/- 3.9-1.7 +/- 3.3 3.7 +/- 3.3 0.7 +/- 2.6 Station 13 1f La-140 ___3.6 +/- 5.6-2.6 +/- 6.7 2.4 +I- 5.9-3.5 +/- 7.0-5.9 +/- 6.1 0.2 +/- 7.4 1.0 0.9-1.1-4.4-5.9 0.0-1.3 2.8 4/-+1-+1-+1-+1-+1-5.1 5.4 5.3 6.7 5.9 5.9[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.50 Table 3-9 F o -.9ndr nnrl %/mr-ttntion Gamma Spectra[pCi/kg]Sampling Samplingi Location Date Be-7 14 05/18/05 830.0 +/- 410.0 06/22/05 360.0 +/- 320.0 07/20105 1280.0 +/- 350.0 08/24/25 770.0 +/- 210.0 I K-40 16500 +/- 1100.0 12500 +/- 1300.0 8500 +/- 1000.0 12340 +/- 760.0 L 1-131 2.0 +/- 16.0 4.0 +/- 25.0-8.0 +/- 22.0 2.0 +/- 22.0 I Cs-1 34 I Cs-1 37 I Th-228 I-18.0 +/- 29.0 44.0 +/- 35.0 31.0 +/- 31.0 27.0 +/- 21.0-6.0 +/- 26.0-7.0 +/- 28.0 10.0 +/- 24.0 21.0 +/- 17.0 50.0 +/- 130.0 80.0 +/- 130.0 60.0 +/- 120.0 270.0 +/- 71.0 15 05/18/05 06/22/05 07/20/05 08/24/25 I Be-7 I K-40 l 1-131 l Cs-1 34 l Cs-i 37 l Th-228 l 1710.0 +/- 320.0 24800 +/- 720.0 -10.1 +/- 3.7 2.0 +/- 23.0 17.0 +/- 16.0 355.0 +/- 60.0 480.0 +/- 230.0 11510 +/- 710.0 -14.0 +/- 18.0 9.0 +/- 20.0 12.0 +/- 18.0 145.0 +/- 77.0 1920.0 +/- 290.0 7240 +/- 540.0 10.0 +/- 26.0 13.0 +/- 24.0 2.0 +/- 19.0 110.0 +/- 100.0 2720.0 +/- 260.0 11680 +/- 540.0 -5.0 +/- 19.0 7.0 +/- 22.0 5.0 +/- 16.0 954.0 +/- 65.0l Be-7 K-40 1 -131 l Cs-134 l Cs-137 I Th-228 I 16 05/18/05 1460.0 +/- 520.0 06/22/05 500.0 +/- 290.0 07/20/05 330.0 +/- 330.0 08/24/25 820.0 +/- 400.0 20900 +/- 1200.0 11800 +/- 1300.0 15300 +/- 1100.0 10200 +/- 1300.0 3.0 +/- 22.0 14.0 +/- 31.0-3.0 +/- 21.0-3.0 +/- 18.0 4.0 +/- 28.0 10.0 +/- 33.0 15.0 +/- 27.0 8.0 +/- 28.0 27.0 +/- 31.0-16.0 +/- 24.0 11.0 +/- 23.0 0.0 +/- 25.0 250.0 +/- 140.0 90.0 +/- 140.0 50.0 +/- 100.0 220.0 +/- 110.0 51 Table 3-9 f~rnnl onrl Uncnotntinn Gamma Spectra[pCi/kg]Sampling Samplingl Location Date Be-7 I 23 05/18/05 2210.0 +/- 350.0 06/22105 690.0 +/- 300.0 07/20/05 760.0 +/- 220.0 08/24/25 1430.0 +/- 430.0 K-40 21560 +/- 960.0 7870 +/- 670.0 9950 +/- 730.0 13400 +/- 1200.0 I 1-131-10.7 +/- 4.0-6.0 +/- 22.0 3.0 +/- 28.0 14.0 +/- 24.0 I Cs-1 34 16.0 +/- 26.0 28.0 +/- 23.0 21.0 +/- 19.0 7.0 +/- 34.0 I Cs-137 I 17.0 +/- 19.0-2.0 +/- 20.0 9.0 +/- 16.0-5.0 +/- 26.0 Th-228 625.0 +/- 76.0 80.0 +/- 110.0 223.0 +/- 63.0 190.0 +/- 140.0 I I Be-7 26 05/18/05 1870.0 +/- 650.0 06/22/05 350.0 +/- 290.0 07/20/05 1310.0 +/- 350.0 08/24/25 1270.0 +/- 370.0 I K-40 22100 +/- 1400.0 10800 +/- 1300.0 10200 +/- 1100.0 12590 +/- 920.0l 1-131-3.0 +/- 16.0-14.0 +/- 17.0 23.0 +/- 30.0-7.0 +/- 14.0 I Cs-1 34 I Cs-137 52.0 +/- 38.0 9.0 +/- 32.0 12.0 +/- 30.0 27.0 +/- 28.0 22.0 +/- 36.0-4.0 +/- 25.0 8.0 +/- 24.0-2.0 +/- 23.0 I Th-228 560.0 +/- 140.0-20.0 +/- 100.0 130.0 +/- 130.0 120.0 +/- 120.0 I 52 Table 3-10 Gamma Spectra, Strontium, and Tritium[pCi/L]-Sampling 03/30/05 06/28/05 09/28/05 12/28/05 H-3 I Be-7 I 1 _250.0 +/- 600.0-30.0 +/- 750.0-350.0 +/- 910.0 730.0 +/- 990.0-7.0 +/- 26.0 3.0 +/- 19.0 3.0 +/- 16.0-4.0 +/- 15.0-10.0 37.0-23.0 19.0 K-40 I Sr-89 I Sr-90 l 1-131+/- 42.0 [a] [a] 5.0 +/- 6.0+/- 29.0 3.3 +/- 4.9 0.5 +/- 1.1 -5.4 +/- 4.0+/- 25.0 [a] [a] 1.7 +/- 4.6+/- 31.0 [a] [a] -3.9 +/- 4.8 I Ba-140 3.0 +/- 5.4 2.2 +/- 4.0 1.4 +/- 3.4-2.2 +/- 4.0 Station 01A I Th-228 0.0 +/- 11.0 4.0 +/- 11.0 7.4 +/- 6.1 7.1 +/- 6.0 i[a] Sr-89/90 analyses performed on the second quarter sample.53 Table 3-11 River Water Gamma Spectra, Strontium, and Tritium[pCi/LI-Sampling 01/13/05 02/17/05 03/14/05 04/11/05 05/16/05 06/13/05 07/14/05 08/15/05 09/15/05 10/19/05 11/14/05 12/16/05 H-3[b][b]3050.0 +I-[b][b]1500.0 +/-[b][b]3030.0 +/-[bi[b]5100.0 +/--I Be-7-8.0 +/-1.0 +/-740.0 10.0 +/--10.0 +/--9.0 +/-1100.0 -11.0 +/-8.0 +/-2.1 +1-890.0 0.0 +/--6.0 +/-3.0 +1-1100.0 -5.9 +/-20.0 13.0 11.0 12.0 16.0 19.0 18.0 7.6 14.0 13.0 25.0 6.5l K-40 7.0 +/- 27.0-13.0 +/- 20.0-2.0 +/- 19.0-12.0 +/- 17.0 2.0 +/- 31.0-18.0 +/- 29.0 31.0 +/- 37.0-6.0 +/- 14.0-7.0 +/- 23.0-4.0 +/- 27.0 50.0 +/- 34.0-1.0 +/- 11.0 I Sr-89 l Sr-90 I[a] [a][a] [a][a] [a][a] [a][a] [a]3.0 +/- 5.8 0.6 +/- 0.9[a] [a][a] [a][a] [a][a] Cal[a] [a][a] [a]0.2-0.1 0.2 0.2-0.2 0.1 0.0 0.0 0.1 0.1-0.1 0.0 1-1 31+l-+l-+l-+l-+l-+l-+l-+l-+'l+l-+l-+l-0.4 0.2 0.4 0.4 0.1 0.4 0.2 0.2 0.4 0.3 0.2 0.3-0.1 +/-0.5 +/- 1 0.5 +/- 1 0.3 +/- 1 0.1 +/- 1 0.0 +/- g-0.2 +/- <0.4 +/-0.2 +/- l*0.7 +/- l-2.4 +I- : 0.5 +/- I?.3 1.3 1.2 1.3 1.9 2.1 0.7 1.2 1.6 2.9 0.8 I Ba-140-1.2 +/- 5.1 0.6 +/- 3.2-1.0 +/- 2.2 0.4 +/- 3.1-1.8 +/- 3.6 0.9 +/- 3.8-0.6 +/- 5.2 1.1 +/- 2.6-2.0 +I- 2.9-0.3 +/- 3.4 1.0 +/- 4.7-0.8 +/- 1.7 Station 11_ Th-228 1.5 +/- 9.2 1.8 +/- 5.7 1.9 +/- 5.9 1.1 +/- 4.7-1.6 +/- 8.6 2.5 +I- 7.9 4.0 +/- 10.0 2.8 +/- 4.4-1.2 +/- 7.2 3.0 +/- 7.5 8.0 +/- 13.0-0.4 +/- 3.0-[a] Sr-89/90 analyses performed on the second quarter sample.[bl Tritium analyses on quarterly composite.

54 Table 3-12 Surface Water (GnmmR .S#n~otra; SAtrntitim; Tritiiim Date I H-3 l Sr-89 Sr-90 Be-7 01/19/05 02/17/05 03/14/05 04/11/05 05/16/05 06/13/05 07/14/05 08/15,105 09/15105 10/19/05 11/14/05 12/16/05[b][b]2990.0 +/-[b][b]1630.0 +/-[b][b]3930.0 +/-[b][b]4000.0 +/-[a][a] -3.0 +/- 16.0[a] [a]730.0 [a] [a][a] [a][a] [a]680.0 -0.5 +/- 5.2 0.9 +/- 0.9[a] [a][a] [a]930.0 [a] [a][a] [a][a] [a]1100.0 [a] [a]22.0-13.0 14.0-10.0 12.0 3.0-8.0-29.0 21.00-9.00 10.00 4.+/-+/-+/-+1-+/-+1-+1-+/.+/-+1-17.0 27.0 19.0 21.0 24.0 15.0 16.0 31.0 28.00 27.00 20.00[pci/L]l K-40-18.0 +/- 23.0 7.0 +/- 26.0-3.0 +/- 42.0-17.0 +/- 25.0-23.0 +/- 39.0 40.0 +/- 46.0 45.0 +/- 33.0 9.0 +/- 30.0-13.0 +/- 40.0-13.0 +/- 67.0-9.0 +/- 39.0-5.0 +/- 27.0-L l-131 0.1 +/- 0.3 0.2 +/- 0.4 0.1 +/- 0.4-0.3 +/- 0.3-0.1 +/- 0.0 0.2 +/- 0.5 0.1 +/- 0.3 0.2 +/- 0.4-0.2 +/- 0.1-0.1 +/- 0.0-0.1 +/- 0.2 0.0 +/- 0.4-1.8 +/- 1.8-0.3 +/- 2.0-0.6 +/- 3.1 1.0 +/- 1.8 0.9 +/- 3.0 0.9 +/- 2.6-0.1 +/- 1.7 0.7 +/- 1.7-2.1 +/- 2.9 0.0 +/- 3.2 1.5 +/- 3.3 0.2 +/- 2.2-01-0.1 3.1.3 C 1.(-2., I Cs-137 I Station 08 Ba-140 l Th-228+/- 3.6 0.5 +/- 7.2+I- 3.7 -5.3 +I- 7.3+/- 5.0 -2.6 +1- 9.8+/- 5.7 3.5 +I- 7.5+/- 5.2 12.0 +/- 10.0+/- 5.7 4.0 +/- 12.0+/ 5.0 1.5 +/- 8.2+/- 6.6 -4.0 +/- 5.9 3 +/- 6.6 4.0 +/- 12.0 8 +/- 7.2 0.0 +/. 14.0+/- 5.3 -8.0 +/- 12.0 3 +/- 5.5 2.5 +/- 7.4-01/19/05 02/17/05 03/14/05 04/11/05 05/16/05 06/13/05 07/14/05 08/15/05 09/15/05 10/19/05 11/14/05 12/16/05 H-3[b][b]390.0 +/-[b][b]-420.0 +/-[b][b]-140.0 +/-[b][b]-20.0 +/--l Sr-89 I Sr-90[a] [a][a] [a]610.0 [a] [a][a] [a][a] [a]750.0 4.0 +/- 5.3 0.3 +/- 0.9[a] [a][a] [a]760.0 [a]- [a][a] [a][a] [a]900.0 [a] [a]-12.0 +B--17.0 +/--6.0 +/--13.00 +/-3.00 +/-4.00 +/--9.00 +/--2.00 +/--11.00 +/-1.00 +/1 0.00 +/-4.90 +/-26.0 22.0 24.0 20.0 22.0 25.0 18.0 11.0 22.0 21.0 30.0 8.9l K-40-12.0 +/- 40.0 14.0 +/- 34.0-30.0 +/- 42.0-6.0 +/- 30.0-30.0 +/- 40.0-10.0 +/- 40.0-2.0 +/- 35.0-12.0 +/- 17.0-1.0 +/- 38.0 7.0 +/- 39.0-66.0 +/- 55.0 8.0 +/- 15.0--0 1-131-0.1 +/- 0.2-0.1 +/- 0.2 0.3 +/- 0.4-0.2 +/- 0.2-0.1 +/- 0.0-0.1 +/- 0.3 0.1 +/- 0.3-0.1 +/- 0.0 0.0 +/- 0.2 0.0 +/- 0.2 0.1 +/- 0.2 0.1 +/- 0.4-I Cs-137-1.3 +/- 3.2-0.1 +/- 2.2-0.6 +/- 3.1 0.7 +/- 2.2 0.4 +/- 2.6 2.5 +/- 2.8-0.6 +/- 2.3 0.0 +/- 1.0-1.5 +/- 2.3 0.1 +/- 2.5 1.1 +/- 3.3-0.3 +/- 0.9-I Ba-140 2.4 +/- 6.9 0.0 +/- 5.2-3.1 +/- 5.2 0.0 +/- 5.0-0.7 +/- 5.5-0.2 +/- 5.6-0.9 +/- 5.7-0.6 +/- 3.8-4.2 +/- 5.5-0.8 +/- 5.0 4.0 +/- 6.4 0.8 +/- 2.6-Station 09A I Th-228-4.7 +/- 9.8-1.4 +/- 9.9 0.0 +/- 13.0-3.0 +/- 9.8 6.0 +/- 13.0-3.0 +/- 11.0 10.5 +/- 8.7-1.4 +/- 4.8-2.0 +/- 10.0 2.6 +/- 9.7 5.0 +/- 14.0-0.6 +/- 3.5[a] Sr-89/90 analyses performed on the second quarter sample.[j] Tiatumi arialysses Oil quarteily ed ipc e.55 Table 3-13 Sediment Silt Gnmma Sport> nndi Stron[iKm[pCi/Kg]Date Sr-89 Sr-90 Be-7 K-40 Mn-54 04/11/2005 Station 08 170.0 +/- 180.0 -50.0 +/- 150.0 150.0 +/- 220.0 1700.0 +/- 440.0 -14.0 +/- 22.0 Station 09A -90.0 +/- 150.0 50.0 +/- 120.0 -140.0 +/- 280.0 10300.0 +/- 1100.0 9.0 +/- 28.0 Station 11 -130.0 +/ 170.0 80.0 +/- 140.0 -30.0 +/- 330.0 17700.0 +/- 1400.0 -10.0 +/- 33.0 Date Sr-89 Sr-90 Be-7 K-40 Mn-54 10/19/2005 Station 08 [a] [a] 0.0 +- 270.0 20700.0 +/- 1300.0 15.0 +/- 33.0 Station 09A [a] [a] -50.0 +/- 190.0 10940.0 +/- 880.0 8.0 +/- 21.0 Station 11 [a] [a] 110.0 +/- 200.0 17200.0 +/- 1000.0 -7.0 +/- 28.0 Date Co-58 Co-60 Cs-134 Cs-137 Th-228 04/11/2005 Station 08 -9.0 +/- 21.0 6.0 +/- 16.0 -5.0 +/- 22.0 -11.0 +/- 27.0 430.0 +/- 120.0 Station 09A 0.0 +/- 31.0 -24.0 +/- 31.0 -12.0 +/- 25.0 23.0 +/- 30.0 690.0 +/- 120.0 Station 11 6.0 +/- 36.0 10.0 +/- 38.0 3.0 +/- 32.0 322.0 +/- 61.0 930.0 +/- 140.0 Date Co-58 Co-60 Cs-134 Cs-137 Th-228 10/19/2005 Station 08 Station 09A Station 11-18.0 +/- 32.0-13.0 +/- 22.0-9.0 +/- 26.0-1.0 +/- 31.0-3.0 +/- 24.0 3.0 +/- 26.0 9.0 +/- 26.0 10.0 +/- 20.0-8.0 +/- 21.0-10.0 +/- 31.0 11.0 +/- 26.0 87.0 +/- 37.0 2010.0 +/- 140.0 509.0 +/- 95.0 1340.0 +/- 110.0[a] Sr-89/90 analyses performed annually.56 Table 3-14 Shoreline Soil Gamma Sprctra and Strontium[pCi/Kg]Sample Date l Sr-89 Sr-90 Be-7 K-40 04/11/2005 Station 08 -130.0 +/- 160.0 -40.0 +/- 130.0 0.0 +/- 150.0 2810.0 +/- 360.0 Sample Date l Sr-89 Sr-90 Be-7 K-40 10/19/2005 Station 08 [a] +/- [a] 41.0 +/- 98.0 -60.0 +/- 160.0 2100.0 +/- 410.0 Sample Date l Co-58 Co-60 Cs-1 34 Cs-1137 04/11/2005 Station 08 -10.0 +/- 15.0 5.0 +/- 15.0 1.0 +/- 14.0 181.0 +/- 30.0 Sample Date Co-58 Co-60 Cs-134 Cs-1 37 10/19/2005 4 Station 08 -5.0 +/- 19.0 16.0 +/- 21.0 28.0 +/- 85.0 -16.0 +/- 22.0[a] Sr-89/90 analyses performed annually.I Mn-54 8.0 +I- 13.0l Mn-54-6.0 +/- 16.0 3 Th-228 375.0 +I- 64.0l Th-228 540.0 +/- 84.0 57 Table 3-15 Fish Gamma Qnnntrn[pCi/Kg]Fish [a]Sampling Station 08 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 04/14/05 1070.0 +/- 640.0 7.0 +/- 21.0 70.0 +/- 100.0 18.0 +/- 24.0 -8.0 +/- 29.0 0.0 +/- 58.0 -3.0 +/- 17.0 -1.0 +/- 29.0 10/18/05 1880.0 +/- 580.0 -7.0 +/- 23.0 -14.0 +/- 56.0 -13.0 +/- 26.0 13.0 +/- 24.0 -12.0 +/- 54.0 16.0 +/- 25.0 33.0 +/- 25.0 Fish [a]Sampling Station 25 Date l K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 l Cs-137 04/12/05 1670.0 +/- 460.0 13.0 +/- 15.0 -29.0 +/- 58.0 0.0 +/- 15.0 7.0 +/- 25.0 -22.0 +/- 39.0 -3.0 +/- 18.0 12.0 +/- 15.0 10/18/05 1890.0 +/- 550.0 7.0 +/- 22.0 -55.0 +/- 53.0 11.0 +/- 23.0 5.0 +/- 17.0 -48.0 +/- 55.0 6.0 +/- 28.0 0.0 +/- 17.0 Catfish [b]Sampling Station 08 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 04/13/05 1340.0 +/- 460.0 0.0 +/- 17.0 32.0 +/- 58.0 5.0 +/- 18.0 1.0 +/- 19.0 9.0 +/- 37.0 2.0 +/- 19.0 1.0 +/- 18.0 10/18/05 1260.0 +/- 460.0 -7.0 +/- 19.0 -22.0 +/- 56.0 -11.0 +/- 18.0 -8.0 +/- 22.0 -19.0 +/- 40.0 10.0 +/- 22.0 18.0 +/- 23.0 Catfish [b]Sampling Station 25 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 04/12/05 1460.0 +/- 550.0 10/18/05 1950.0 +/- 530.0-5.0 +/- 22.0 -30.0 +/- 81.0 -21.0 +/- 24.0-2.0 +/- 19.0 -36.0 +/- 55.0 -13.0 +/- 24.0 19.0 +/- 27.0-1.0 +/- 22.0-6.0 +/- 47.0 -16.0 +/- 14.0-22.0 +/- 50.0 -8.0 +/- 18.0 7.0 +/- 25.0 7.0 +/- 19.0[a] Non-bottom dwelling species of gamefish.[b] Bottom dwelling species of fish.58

4. DI'SCUSSION OF RESULTS Data firom the radiological analyses of environmental media collected during 2005 and tabulated in Section 3, are discussed below. Except for TLDs, AREVA Environmental Laboratory analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the AREVA Environmental Laboratory quality assurance manuals and laboratory procedures.

In addition to internal quality control measurements performed by each laboratory, they also participate 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 enviromnental samples are performed.

The results of the Interlaboratory Comparison Prcgrams are provided in Appendix B.The predominant radioactivity detected throughout 2005 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.

Naturally occurring nuclides such as Be-7, K-40, and Th-223 were detected in numerous samples. Th-228 results were variable and are geneially at levels higher than plant related radionuclides.

The following is a discussion and summary of the results of the enviromnental measurements taken during the 2005 reporting period.4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation.

TLDs are placed in two concentric rings around the station.The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population areas and nearby residences.

Additional TLDs serve as controls.

Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.The results of the analyses are presented in Table 3-2. Figure 4-1 shows a historical trend of TLD exposure rate measurements.

Control and indicator averages indicate a steady relationship.

Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location.

These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs. This will continue to be monitored.

59 Figure 4-1: Enviononmntal Radiation

-ThDs 10.0 t z'E 1.0 0 0000 0 O ON O O on ElO ON 00 0 0 O C C CO CO CO CO CO CO CO CO C CO C C C C-BrEnironnental TLDs A Sector TLDs --- e. Pre-opl Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location.

The average level of the 32 locations (two badges at each location) was 5.2 mR/standard month with a range of 2.6 to 34.8 mR/standard month. The highest quarterly average reading and highest single quarter average for any single location were obtained at location SSW-19/51.

These values were 32.1 mR/standard month and 34.8 mR/standard month, respectively.

This location is on site directly across the access road from the Independent Spent Fuel Storage Facility.

The higher values can thus be attributed to the spent fuel stored in the ISFSI. Quarterly and annual TLDs are also located at each of the twelve environmental air sampling stations.For the eleven locations within 10 miles of the station the average quarterly reading was 3.7 mR/standard month with a range of 1.7 to 6.4 mR/standard month. The average annual reading for these locations was 3.6 mR/standard month with a range of from 1.7 to 5.4 mR/standard month. The control location showed a quarterly average of 3.4 mR/standard month with a range of 2.6 to 4.3 mR/standard month. Its annual reading was 3.4 mR/standard month. Eight other TLDs, designated C-1 thru C-8, were collected quarterly from four locations and showed an average reading of 3.3 mR/standard month with a range of 2.5 to 3.7 mR/standard month. During the pre-operational period (starting in 1977)the doses were measured between 4.3 and 8.8 mR/standard month.60 4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged.

Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of North Anna 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. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.Figure 4-2: Gross Beta in Air Particulates

_! 0.1 Z.-3 .01 i ... .. ..... ... .........1 ... .............................

.... --- ...0.001 1986 1991 1996 2000 2005-.- Control Sta-24

Indicator

Average Pre-op -- -, --Required LLD 61 I 0r7 Figure 4-3 NORTH ANNA AIR PARTICULATE 2005 Gross Beta Radioactivity eIndicator

..A --- Control pCVM 3 0.055......... I-- ... .. .. ...Un (0 -OM a 0 '-o No 0 m N _o a o a 0 a 0 co 0 0 mn 0 S.no 5-e 0 co N-0 4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine.

Once a week the 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 with no positive activity detected.

These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.

4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectrometry.

The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes.

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

No other positive results were seen. These analyses indicate the lack of station effects.62 co%

4.5 Ar Particulate Strontium Stronlium-89 and 90 analyses were performed on the second quarter composites of air particulate filters from all twelve monitoring stations.

The results are listed in Table 3-5. There was no detection of these fission products at any of the indicator or control stations.4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2004 and therefore not collected in 2005.4.7 Precipitation A sarnple of rain water was collected monthly at on-site station O1A and analyzed for gross beta activity.

TIhe results are presented in Table 3-7. Ten precipitation samples were obtained with no samples available for two months due to drought.All ten precipitation samples showed positive results in 2005. The average annual gross beta activity was 5.9 pCi/liter with a range from 2.3 to 12.1 pCi/liter.

Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritiura.

No positive indications of gamma emitting radioisotopes were obseived in the semi-annual composite samples for 2005. During the pre-operational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison can not be made to the 2005 period.During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter.

4.8 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 mrdost critical from the plant release viewpoint.

This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any plant effect.Analysis results for cow milk are contained in Table 3-8. All results show no detectable 1-131 above the LLD of 1 pCi/l. Results of gamma ray spectroscopy indicate no detectable plant related radioactivity in the milk samples. In years past, -Cs-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 2005.63 Once each quarter a sample from each of the two collection stations is analyzed for strontium-89 and strontium-90.

Neither Sr-89 not Sr-90 were detected.

Sr-90 has been observed in the past. Pre-operational levels of 2.2 to 5.4 pCi/liter were measured for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents.

Its detection is the product of nuclear weapons testing fallout. This conclusion can be made based upon the fact that Sr-89 and Sr-90 have not been detected in effluents released from the station in many years, and the trend of consistent declining levels since the pre-operational period.4.9 Food Products and Vegetation Twenty food/vegetation samples were collected from five locations and analyzed by gamma spectrometry.

The results of the analyses are presented in Table 3-9. As expected, naturally occurring potassium-40 was detected in all samples, cosmc'genic beryllium-7 was detected in most samples, and thorium-228 was detected in some samples. No other man-made gamma emitters were detected.4.10 Well Water Water was sampled quarterly from the on site well at the metrology laboratory.

These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed for strontium-89 and strontium-90.

The results of these analyses are presented in Table 3-10. Consistent with past monitoring, no plant :related radioactivity was detected.

No gamma emitting isotopes were detected during the pre-operational period.4.11 River Water A sample of water from the North Anna River was collected monthly, the analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy.

The monthly samples were composited quarterly and analyzed for tritiurna, the second quarter samples were additionally analyzed for strontiuim-89 and sirontium-90.

No gamma emitting radioisotopes were detected in any of the samples. There was no measured activity of strontium-89 or strontium-90.

Tritiun was measured in all four samples with an average annual concentration of 3170 pCi/liter and a range of 1500 to 5100 pCi/liter.

These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were collected during the pre-operational period.64 10000 Figure 44: Tritium in River Water C C , C 1000 , III'r ~c 1 00 O\ 0 -(N > w t- 00 o 0-c t o 00 00 00 00 00 er C\ --all Oe Cr C O N 0 ) l*Tritium .. --Required LLD 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma ray spectrometry and for iodine- 131 by radiochemical separation.

A quarterly composite from each station was prepared and analyzed for tritium, and the second quarter samples were additionally analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-12.65 I No gamma emitting radioisotopes nor iodine were detected in any of the samples. The average level of tritium activity at the indicator station was 3137 pCi/liter with a range of 1630 to 4000 pCi/liter.

Levels of tritium have been increasing since 1978 when the average level was below 300 pCi/liter.

Levels measured at the indicator location (Station 8) are comparable to those measured since 1986, see Figure 4-5.During the pre-operational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter.

Figure 4-5: Tritium in Surface Water 10000=..a.---...........

Z 1000 s..100 -a CU 00 CU C? CU O U Ce 0U CU X U C°U CU CU a, C CU C C CU CU* Tritium -- .U-- Required LLD -- Average Pre-op 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectrometry.

The October samples were analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-13. Figure 4-6 shows the historical trend of Cs- 137 in sediments.

66 CIO E --Figure 4-6: Cesiun-137 in Sediment Silt..10000 x 4 1000 A t _t-Xx, XA100 ~"r~I /, 10 1 I I I I I I#1II I I I ~ F ---m. 00 Wo -es \ 00 W o -Cl o -0 0 0 0 0 0 0 -4 Station-8 U Station-9 A Control-Sta-09A-X-Station-11 Average Pre-Op Required LLD's Cesium-137 was detected in the sediment samples in 2005 at an average of 205 pCi/kg. This level is consistent with the historical trend. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout;its global presence has been well documented.

During the pre-operational period sediment samples were analyzed by gamma ray spectroscopy.

There was no measurable amount of strontium-89 or 90 in aquatic sediment/silt.

A number of naturally occurring radioisotopes were detected in these samples at background levels.4.14 Shoreline Soil Shoreline soil/sediment, unlike bottom sediment, 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 uses. A sample of shoreline sediment was collected in March and October from indicator station 08. The samples were analyzed by gamma ray spectrometry.

The September sample was analyzed for strontium-89 and strontium-90.

The results are presented in Table 3-14.Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities.

The activities of these radioisotopes indicate a steady trend. Cesium- 137 was detected in one sample collected with a concentration of 181 pCi/kg (dry weight). No Strontium was detected.

Strontium-90 is normally detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is attributed to accumulation of residual global fallout from past atmospheric weapons testing.67 C11 4.15 Fish Four ,sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2005 and analyzed by gamma spectrciscopy.

Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately.

The results are presented in Table 3-15. Except for naturally occurring K-40, no other nuclide was observed in this media in 2005. Only Cs-137 was measured in pre-operational environmental fish samples.68

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2005 -North Alana Location Description Date of Sampling Reason(s) for Loss/Exception Sta. 23 Sta. 14-16, 23, 26 Sta. 14-16, 23, 26 Sta. 14-16, 23, 26 Sta. 07 Sta. 14-16, 23, 26 Sta. 05A Sta. O1A Sta. 24 Sta. 14-16, 23, 26 Sta. O1A Sta. 14-16, 23, 26 Sta. 14-16, 23, 26 Sta. 27 Sta. 07 Sta. 27 Sta. 14-16,23, 26 Air Iodine and Particulate Vegetation Vegetation Vegetation Air Iodine and Particulate Vegetation Air Iodine and Particulate Precipitation Air Iodine and Particulate Vegetation Precipitation Vegetation Vegetation Milch Air Iodine and Particulate Milch Vegetation 01/12/05 01/26/05 02/23/05 03/16/05 03/16/05 04/20/05 05/11/05 06/29/05 08/14/05 09/21/05 09/28/05 10/05/05 11/15/05 11/16/05 11/23/05 12/21/05 12/21/05 Low Volume -pump stopped. LD achieved.Seasonal Unavailability.

Seasonal Unavailability.

Low Volume -power loss. LLD achieved.Seasonal Unavailability.

Low Volume -breaker tipped. LLD achieved.No Sample -no rain.Low Volume -blown fuse. LLD achieved.No sample -drought.No Sample -no rain.No sample -drought.Seasonal Unavailability.

No sample -animal no longer present.Low Volume -power loss. LLD achieved.Seasonal Unavailability.

Seasonal Unavailability.

69 REMP Exceptions for 2004 -North Anna Several typographical errors were identified in the 2004 North Anna REMP following distribution.

Tatble 3-5, Air Particulate; Gamma Spectra results: The reported value for Be-7 at station 03 of"93 +/-30 pCi/m 3 x 10-3 " appearing on page 47 was incorrectly reported as of "930 +/-30 pCi/m 3 X 1(-3,,* Table 3-3, Air Particulate; Gross Beta results: The reported values for stations 07, 21, 22, 23, and 24 lor the collection periods of 01/14/04 through 06/30/04 appearing on page 39 were incorrectly assigned dates for "periods ending" 07/07/04 through 12/29/04.* Table 3-4, Air Particulate; Iodine results: The reported values for all stations for the collection period ending 07/14/04 appearing on pages 44 and 45 were incorrectly assigned the date 07/21/04.70 IRCEFERENCES 71 References

1. Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.2. Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications.

3. Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".4. Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010, "Radiological Environmental Monitoring Program".5. Title 10 Code of Federal Regulation, Part 50 (lOCFR50), "Domestic Licensing of Production and Utilization Facilities".

6. 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 1OCFR50, Appendix I", October, 1977.7. United States Nuclear Regulatory Commission, Regulatory Guide 4.8"Environmental Technical Specifications for Nuclear Power Plants", December 1975.8. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.9. NUREG 0472, "Radiological Effluent Technical Specifications for I'WRs", Rev. 3, March 1982.10. 'Technical Specifications for North Anna Independent Spent Fuel Storage Installation (ISFSI)".11. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.12. NUREG/CR-4007, "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.72 APPENDICES 73 APPENDIX A: LAND USE CENSUS Year 2005 74 LAND USE CENSUS North Anna Power Station North Anna County, Virginia January I to December 31, 2005 Direction Distance (miles)Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch Boundary (> 50m 2) Animal Cow Goat N 0.9 1.5 1.5 None None None NNE 0.9 0.9 1.4 1.5 None None NE 0.8 0.9 0.9 1.5 None None ENE 0.8 2.1 2.1 2.5 None 2.5 E 0.8 1.3 1.3 3.5 None None ESE 0.9 1.7 1.7 None None None SE 0.9 1.4 1.4 1.5 None None SSE 0.9 1.0 1.0 2.8 None None S 0.9 1.1 1.2 2.8 None None SSW 1.0 1.4 None 1.9 None None SW 1.1 3.1 3.1 None None None WSW 1.1 1.6 1.6 1.6 None None W 1.1 1.5 1.5 None None None WNW 1.0 1.1 2.5 3.9 None None NW 1.0 1.0 1.1 None None None NNW 0.9 1.0 1.1 None None None 75 2004 to 2005 Land Use Census Changes 2004 2005 Nearest Direction Distance Distance Site Boundary None Resident None Garden NW l 1.3 mi I 1.1 mi Meat Animal None Milch Cow None Milch Goat None Xp 76 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2005 77 INVTRODUC7ION This appendix covers the Intercomparison Program of the AREVA ANP Environmental Laboratory as required by technical specifications for each Millstone unit. 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 CQA/QC samples are designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides.

It was modified to more closely match the media mix presently being processed by Framatome and includes: S milk for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses once per quarter,> mrilk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,> water for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses during the 1st and 3rd quarters,> water for Sr-89 and Sr-90 analyses during the 4th quarter,> water tritium analysis during the 2nd and 4th quarters,> air filter for gamma (9 nuclides) analyses during the 2nd quarter, and> air filter for gross beta analysis during the 1st and 3rd quarters.In addition to the Analytics Intercomparison Program, AREVA ANP also participates in other intercomparsion programs which include radionuclides and media similar to those required by the Millstone program. These programs are the National Institute of Standards and Technology (NISI) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (P1)Program, the Department of Energy (DOE) Quality Assessment Program (QAP), and the Mixed Analyte Performance Evaluation Program (MAPEP).RESULTS Intercomparison program results are evaluated using AREVA ANP's internal bias acceptance criterion.

The criterion is defined as within 25% of the known strontium value for samples containing both Sr-89 and Sr-90 and within :15% of the known value for other radionuclides, or within two sigma of the known value.Any sample analysis result that does not pass the criteria is investigated by AREVA ANP.Analytics Intercomparison Program results are included on pages 78 through 82 for the first quarter of 2005 through the fourth quarter of 2005. A total of 104 analysis results were obtained with 103 initially passing acceptance criteria, a 99.00%b success rate. During analysis of water in conjunction with DOE, Ni-63 yielded a 'false negative' result [01/01/2005].

An investigation

[CR 05-14]identified no specific cause: "No apparent cause identified for false negative result.Four samples of lower activities were analyzed concurrently and all passed the acceptance criteria." A review of the CR indicates that sample preparation is the 78 most likely cause since equipment performance is effectively ruled-out.

A review of the CR identified that the direct spike samples are described as being contaminated although the specific contaminant is not identified.

79 FRAMATOME ANP 2005 ENVIRONMENTAL LABORATORY ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Ratio Sample Ouarter/ Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation E4459-162 l st/2005 Water Gross Alpha pCUL 39.9 40.8 0.98 Agreement E4459-162 lst/2005 Water Gross Beta pCIL 279 292 0.96 Agreement E4460-162 1 st/2005 Water 1-131 LL pCIL 66.2 65.9 1 Agreement E4460-162 lst/2005 Water 1-131 pCiUL. 69.3 65.9 1.05 Agreement E4460-162 1 st/2005 Water Ce-141 pCIL 219 221 0.99 Agreement E4460-162 1 st/2005 Water Cr-51 pCi/L 346 322 1.07 Agreement E4460-162

_ st/2005 Water Cs-134 pCVL 130 134 0.97 Agreement E4460-162 1 st/2005 Water Cs-137 pCi/L 127 125 1.01 Agreement E4460-162 1 st/2005 Water Co-58 pCUL 108 111 0.97 Agreement E4460-162 1 st/2005 Water Mn-54 pCUL 160 154 1.04 Agreement E4460-162 1 st2005 Water Fe-59 pCi/L 114 107 1.07 Agreement E4460-162 1 st/2005 Water Zn-65 pCi/L. 192 191 1.01 Agreement E4460-162 lst/2005 Water Co-60 pCIL 138 139 1 Agreement E4461-162 1 st/2005 Water Sr-89 pCiLt 94.6 103 0.92 Agreement E4461-162 1st/2005 Water Sr-90 pCIL/ 15.6 17.2 0.9 Agreement E4462-162 1 st/2005 Filter Gross Alpha pCi 20.8 21.9 0.95 Agreement E4462-162 1 st/2005 Filter Gross Beta pCi 162 157 1.04 Agreement E4463-162 1 st/2005 Milk I-131ILL pCi/L 91.2 92.3 0.99 Agreement E4463-162 1 st/2005 Milk 1-131 pCi/L 95.9 92.3 1.04 Agreement E4463-162 1 st/2005 Milk Ce-141 pCi/L 229 229 1 Agreement E4463-162 ltsV2005 Milk Cr-51 pCIL 334 334 1 Agreement E4463-162 1stV2005 Milk Cs-134 pCi/L 137 139 0.99 Agreement E4463-162 1 st2005 Milk Cs-137 pCIL 133 130 1.03 Agreement E4463-162 1 st/2005 Milk Co-58 pCIL 118 115 1.02 Agreement E4463-162 lst/2005 Milk Mn-54 pCi/L 166 160 1.04 Agreement E4463-162 lst/2005 Milk Fe-59 pCi/L 117 111 1.05 Agreement E4463-162 1 st/2005 Milk Zn-65 pCitL 203 198 1.03 Agreement E4463-162 1 st/2005 Milk Co-60 pCIL 145 144 1.01 Agreement E4464-162 lst/2005 Milk Sr-89 pCi/L 93.8 107 0.88 Agreement E4464-162 1st/2005 Milk Sr-90 pCi/L 16.1 17.9 0.9 Agreement 80 FRAMATOME ANP 2005 ENVIRONMENTAL LABORATORY ANALYTICS.

ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E4599- 162 2nd/2005 Water H-3 pCi/L 9060 9100 1 Agreement E4600-162 2nd/2005 Filter Gross Alpha pCi 31.9 30.9 1.03 Agreement E4600-162 2nd/2005 Filter Gross Beta pCi 125 127 0.99 Agreement E4601-162 2nd/2005 Filter Ce-141 pCVL 59.3 58.9 1.01 Agreement E4601-162 2nd/2005 Filter Cr-51 pCi/L. 207 193 1.07 Agreement E4601-162 2nd/2005 Filter Cs-134 pCi/L 59.1 60.6 0.98 Agreement E4601-162 2nd/2005 Filter Cs-137 pCi/L 131 120 1.09 Agreement E4601-1 62 2nd/2005 Filter Co-58 pCi/L 3.55 3.4 1.04 Agreement E4601 -162 2nd/2005 Filter Mn-54 pCi/L 88.6 79.7 1.11 Agreement E4601-162 2nd/2005 Filter Fe-59 pCi/L 40.1 40.7 0.99 Agreement E4601-162 2nd/2005 Filter Zn-65 pCi/L 112 98.8 1.13 Agreement E4601-162 2nd/2005 Filter Co-60 pCUL 89.4 92.3 0.97 Agreement E4602-162 2nd/2005 Filter Sr-89 pCi/L 90.5 97.5 0.93 Agreement E4602-162 2nd/2005 Filter Sr-90 pCi/L 13 12.6 1.03 Agreement E4603-162 2nd/2005 Milk 1-131 LL pCi/L 85.7 86.9 0.99 Agreement E4603-162 2nd/2005 Milk 1-131 pCi/L 86.8 86.9 1 Agreement E4603-162 2nd/2005 Milk Ce-141 pCi/L 96.3 92.4 1.04 Agreement E4603-162 2nd/2005 Milk Cr-51 pCi/L 295 303 0.98 Agreement E4603-162 2nd/2005 Milk Cs-134 pCi/L 87.7 95 0.92 Agreement E4603-162 2nd/2005 Milk Cs-137 pCi/L 186 189 0.98 Agreement E4603-162 2nd/2005 Milk Co-58 pCUL 5.83 5.3 1.1 Agreement E4603-162 2nd/2005 Milk Mn-54 pCVL 124 125 0.99 Agreement E4603- 162 2nd/2005 Milk Fe-59 pCi/L 67 63.9 1.05 Agreement E4603-162 2nd/2005 Milk Zn-65 pCi/L 149 155 0.96 Agreement E4603-162 2nd/2005 Milk Co-60 pCi/L 138 145 0.96 Agreement 81 FRAMATOME ANP 2005 ENVIRONMENTAL LABORATORY ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample _ Reported Known E-LABI Number Year Media Nuclide Units Value Value Analytics Evaluation E4686-162 3rd/2005 Water Gross Alpha pCUL 42.3 41.6 1.02 Agreement E4686-162 3rd/2005 Water Gross Beta pCi/L 128.5 123 1.05 Agreement E4687-162 3rd/2005 Water 1-131 LL pCi/L 78.3 78.2 1 Agreement E4687-162 3rd/2005 Water 1-131 pCi/L 77.2 78.2 0.99 Agreement E4687- 162 3rd/2005 Water Ce-141 pCi/L 276.4 282 0.98 Agreement E4687 162 3rd/2005 Water Cr-51 pCi/L 353.7 408 0.87 Agreement E4687-162 3rd/2005 Water Cs-134 pCi/L 137.3 148 0.93 Agreement E4687-162 3rd/2005 Water Cs-137 pCi/L 231.1 235 0.98 Agreement E4687-162 3rd/2005 Water Co-58 pCi/L 72.5 77 0.94 Agreement E4687-162 3rd./2005 Water Mn-54 pCi/L 113.2 111 1.02 Agreement E4687-162 3rd/2005 Water Fe-59 pCi/L 74.7 74 1.01 Agreement E4687-162 3rd/2005 Water Zn-65 pCi/L 152.3 149 1.02 Agreement E4687-162 3rd/2005 Water Co-60 pCi/L 192.1 202 0.95 Agreement E4688.162 3rd/2005 Charcoal 1-131 pCi 61 62.7 0.97 Agreement E4689-162 3rd/2005 Filter Gross Alpha pCi 39.3 38 1.04 Agreement E4689-162 3rd/2005 Filter Gross Beta pCi 120.8 112 1.08 Agreement E4690-162 3rd/2005 Milk 1-131 LL pCi/L 99 94.3 1.05 Agreement E4690-162 3rd/2005 Milk 1-131 pCi/L 90 94.3 0.95 Agreement E4690-162 3rd/2005 Milk Ce-141 pCUL 228.5 233 0.98 Agreement E4690-162 3rd/2005 Milk Cr-51 pCi/L 306.3 338 0.91 Agreement E4690-162 3rd/2005 Milk Cs-134 pCi/L 118.3 122 0.97 Agreement E4690-162 3rd/2005 Milk Cs-137 pCi/L 196.5 195 1.01 Agreement E4690-162 3rd/2005 Milk Co-58 pCi/L 64 63.4 1.01 Agreement E4690-162 3rd/2005 Milk Mn-54 pCiVL 94.7 92 1.03 Agreement E4690-162 3rd/2005 Milk Fe-59 pCi/L 63.3 61 1.04 Agreement E4690-162 3rd/2005 Milk Zn-65 pCi/L 121.7 123 0.9 Agreement E4690-162 3rd/2005 Milk Co-60 pCUL 165.2 167 0.99 Agreement E4691-162 3rd/2005 Milk Sr-89 pCi/L 139.6 146 0.96 Agreement E4691-162 3rd/2005 Milk Sr-90 pCUL 10.8 11.5 0.94 Agreement 82 DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP-05-14)

MATRIX/ REFERENCE RADIO- E-LAB MAPEP BIAS JNITS DATE NUCLIDE MEAN VALUE VALUE Evaluation Filter (Bq total) 01-Jul-05 Am-241 0.1359 0.158 -14 Agreement Filter (Bq total) 01-Jul-05 Cs-134 3.828 3.85 -0.6 A.greement Filter (Bq total) 01-Jul-05 Cs-137 3.396 3.23 5.1 Agreement Filter (Bq total) 01-Jul-05 Co-57 6.506 6.2 4.9 Agreement Filter (Bq total) 01-Jul-05 Co-60 2.924 2.85 2.6 Agreement Filter (Bq total) 01-Jul-05 Mn-54 4.55 4.37 4.1 Agreement Filter (Bq total) 01-Jul-05 Pu-238 0.1059 0.0969 9.3 Agreement Filter (Bq total) 01-Jul-05 Pu-239/240 0.096 0.0898 6.9 Agreement Filter (Bq total) 01-Jul-05 Sr-90 2.037 2.25 -9.5 Agreement Filter (Bq total) 01-Jul-05 Zn-65 4.81 4.33 11.1 Agreement Scil (Bq/lkg) 01 -Jul-05 Cs-134 594 568 4.6 Agreement Scil (Bq/kg) 01-Jul-05 Cs-137 468 439 6.6 Agreement Scil (Bq/kg) 01-Jul-05 Co-57 546 524 4.2 Agreement Scil (Bq/kg) 01-Jul-05 Co-60 300 287 4.4 Agreement Scil (Bq/kg) 01-Jul-05 Mn-54 475 439 8.2 Agreement Scil (Bq/kg) 01-Jul-05 K-40 650 604 7.6 Agreement Scil (Bq/kg) 01-Jul-05 Sr-90 663 757 -12.4 Agreement Scil (Bq/lkg) 01-Jul-05 Zn-65 881 823 7 Agreement Vegetation (Bq total) 01-Jul-05 Am-241 0.251 0.23 -10.8 Agreement Vegetation (Bq total) 01-Jul-05 Pu-238 0.00111+/-

0.00054 False Postive Test N/A Agreement Vegetation (Bq total) 01-Jul-05 Pu-239/240 0.1675 0.164 2.1 Agreement Vegetation (Bq total) 01-Jul-05 Sr-90 2.28 2.42 -5.8 Agreement Water (Bq/L) 01-Jul-05 Am-241 1.849 2.23 -17.1 Agreement Water (Bq/L) 01 -Jul-05 Cs-134 160.7 167 -3.8 Agreement Water (Bq/L) 01-Jul-05 Cs-137 306 333 -8.1 Agreement Water (Bq/L) 01-Jul-05 Co-57 257 272 -5.6 Agreement Water (Bq/L) 01-Jul-05 Co-60 248 261 -4.8 Agreement Water (Bq/L) 01-Jul-05 H-3 571 527 8.3 Agreement Water (Bq/L) 01-Jul-05 Fe-55 208 196 6 ;Agreement Water (Bq/L) 01-Jul-05 Mn-54 392 418 -6.3 Agreement Water (Bq/L) 01-Jul-05 Ni-63 93.5 100 -6.5 Atgreement Water (Bq/L) 01-Jul-05 Pu-238 1.659 1.91 -13.1 Agreement Water (Bq/L) 01-Jul-05 Pu-239/240 2.305 2.75 -16.2 Agreement Water (Bq/L) 01-Jul-05 Tc-99 60.8 66.5 -8.6 Agreement Water (Bq/L) 01-Jul-05 Zn-65 326 330 -1.2 Agreement 83 FAMATOME ANP ENVIRONMENTAL LABORATORY ANALYTICS RADIOCHEMISTRY CROSS CHECK PERFORMANCE EVALUATION Mean Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation A1921E -162 2nd/2005 Liquid Fe-55 uCicc 1.38E-03 1.34E-03 1.03 Agreement A1921 E-162 2nd/2005 Liquid Sr-89 uCicc 1.04E-03 1.08E-03 0.96 Agreement A1921E-162 2nd/2005 Liquid Sr-9o uCicc 9.14E-05 9.63E-05 0.95 Agreement A1966E-162 2nd/2005 Liquid Fe-55 uCi/cc 2.44E-04 2.34E-04 1.04 Agreement-A1953E-162 3rd/2005 Liquid Fe-55 uCi/cc 1.23E-04 j 1.17E-04 1.05 Agreement A1954C-162 3rd/2005 Liquid Sr-89 uCicc 3.62E-03 ! 3.71 E-03 0.98 Agreement A1954C-162 3rd/2005 Liquid Sr-90 uCicc 1.99E-04 2.01 E-04 0.99 Agreement A19844 -162 4th/2005 Liquid Fe-55 uCi/cc 1.30E-04 l1.16E-04 1.12 Agreement A19844-162 4th/2005 Liquid Sr-89 uCVcc 3.38E-03 l 3.69E-03 0.92 Agreement A19844-162 4th/2005 Liquid Sr-90 uCicc 1.88E-04 2.06E-04 0.91 Agreement Special Fe-55 sample for CR 05-16 investigation 84

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