ML17145A306

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Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report
ML17145A306
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/27/2017
From: Lane N
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
17-144
Download: ML17145A306 (83)


Text

{{#Wiki_filter:VIRGINIA ELECTRIC AND P OWER C OMPANY RICHMOND, VIRGINIA 23261 April 27, 2017 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No. 17-144 NAPS/JHL Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2, enclosed is the 2016 Annual Radiological Environmental Operating Report. The Radiological Environmental Operating Report provides the details associated with the Radiological Environmental Monitoring Program. If you have any questions or require additional information, please contact Mr. Donald R. Taylor at (540) 894-2100. Very truly yours, ~L~!,\\ Site Vice President Enclosure Commitments made in this letter: None

cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Serial No. 17-144 NAPS Annual Radiological Environmental Operating Report Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRG Senior Resident Inspector North Anna Power Station

r Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2016 to December 31, 2016 Prepared by Dominion, North Anna Power Station

Prepared by: Reviewed by: Approved by: Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2016 to December 31, 2016 Bradley T. Pleasants, Jr. Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Barbara J. Thompson Superintendent Health Physics Technical Services Dominion North Anna Power Station 2

Table of Contents

1. EXECUTIVE

SUMMARY

............................................................................................................... 4

2. PROGRAM DESCRIPTION............................................................................................................ 6 2.1 Introduction............................................................................................................................. 6 2.2 Sampling and Analysis Program............................................................................................. 7
3. ANALYTICAL RESULTS............................................................................................................. 21 3.1 Summary of Results.............................................................................................................. 21 3.2 Analytical Results of2016 REMP Samples......................................................................... 31
4. DISCUSSION OF RESULTS......................................................................................................... 59 4.1 Gamma Exposure Rate......................................................................................................... 59 4.2 Airborne Gross Beta.............................................................................................................. 60 4.3 Airborne Radioiodine........................................................................................................... 62 4.4 Air Particulate Gamma......................................................................................................... 62 4.5 Air Particulate Strontium...................................................................................................... 62 4.6 Soil........................................................................................................................................ 62
4. 7 Precipitation.......................................................................................................................... 62 4.8 Cow Milk.............................................................................................................................. 63 4.9 Food Products and Vegetation.............................................................................................. 63 4.10 Well Water.......................................................................................................................... 63 4.11 RiverWater......................................................................................................................... 63 4.12 Surface Water...................................................................................................................... 64 4.13 Bottom Sediment................................................................................................................ 65 4.14 Shoreline Soil...................................................................................................................... 66 4.15 Fish...................................................................................................................................... 66
5. PROGRAM EXCEPTIONS........................................................................................................... 67 REFERENCES.................................................................................................................................... 68' APPENDICES..................................................................................................................................... 69 APPENDIX A: LAND USE CENSUS........................................................................................... 70 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS............................... 73 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2016 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specificat'ion 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2. Radioactivity levels from January 1 through December 31, 2016, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to confirm that radiological effluent releases are As Low As 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 (NAPS) 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. Control samples are collected from areas that are beyond the measurable influence of North Anna Power Station (NAPS) 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 (NAPS), can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration. Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline." Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident, Fukushima Daiichi or natural variation. Mirion Technologies provided thermoluminescent dosimetry (TLD) services and Teledyne Brown Engineering Environmental Services 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, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. The 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. Analytical 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 2016 airborne results were similar to previous years. Fallout or natural radioactivity levels remained at levels consistent with past years' results. Water and aquatic exposure pathway samples include precipitation, surface, river and well water, silt and shoreline sediments, and fish. The average tritium activity in surface water for 2016 was 4270 pCi/liter. No other plant related isotopes were reported in any surface or river water. River water collected from the North 4

Anna River, 5.8 miles downstream of the site had an average tritium level of 3930 pCi/liter. No plant related isotopes were detected in quarterly precipitation samples. Silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background. No plant related isotope was identified in any sample. Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels. No plant related isotope was detected in the indicator or control locations in shoreline soil. No plant related isotope was detected in fish samples from either Lake Anna or the control location, Lake Orange. So il samples, which are collected every three years from twelve stations, were collected in 2016. Cs-137 was identified in 6 of 11 indicator samples. For the indicator stations the average was 362 pCi/Kg. During the preoperational phase Cs-13 7 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout. No other plant related isotope was identified in soil samples during 2016. The terrestrial exposure pathway includes milk and food/vegetation products. No plant related radioisotope was detected in any milk samples. Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data. No plant related isotope was detected in any vegetation sample. Low levels of Cs-13 7 have been detected intermittently in past years. The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years. During 2016, as in previous years, operation of the No1th Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2016 was 0.77 millirem. For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural background sources in the environment provide approximately 50% of radiation exposure to man, while medical uses provide approximately 48%. By comparison, 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. 5

2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2016 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).

The North Anna Power Station of Virginia Electric and Power Company (Dominion) 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 has a gross electrical output of 1029 megawatts electric (MWe). Unit l 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 1998. 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 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 the North Anna Power Station Offsite Dose Calculation Manual (ODCM). North Anna Power Station is responsible for collecting the various indicator and control environmental samples. Mirion Technologies is utilized for processing the TLDs. Teledyne Brown Engineering Environmental Services (TBE) is utilized 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. The pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation. Occasionally samples of environmental media 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 North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 1 OCFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable". This report documents the results of the Radiological Environmental Monitoring Program for 2016 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. 6

~ 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 2016 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 TBE for North Anna Power Station during the year 2016. 7

TABLE 2-1 orth Anna Power Station - 2016 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental NAPS Sewage Treatment Plant 01 0.20 NE 42° Quarterly & Annually Thermo I u mi nescent Fredericks Hall 02 5.30 SSW 203° Quarterly & Annually Dosimetry (TLD) Mineral, Va 03

7. 10 WSW 243° Quarterly & Annually Wares Crossroads 04 5.10 WNW 287° Quarterly & Annually Route 752 05 4.20 NNE 20° Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N

11 ° Quarterly & Annually Levy, VA 06 4.70 ESE 115° Quarterly & Annually Bumpass, VA 07 7.30 SSE 167° Quarterly & Annually End of Route 685 21 1.00 WNW 301° Quarterly & Annually Route 700 22 1.00 WSW 242° Quarterly & Annually "Aspen Hills" 23 0.93 SSE 158° Quarterly & Annually Orange, VA 24 22.00 NW 325° Quarterly & Annually Control Bearing Cooling Tower N-1133 0.06 N 10° Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 11 ° Quarterly Parking Lot "C" (on-site) NNE-3/35 0.24 NNE 32° Quarterly Good Hope Church NNE-4/36 3.77 NNE 25° Quarterly Parking Lot "B" NE-5/37 0.20 NE 42° Quarterly Lake Anna Marina (Bogg's Dr) NE-6/38 1.46 NE 34° Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 74° Quarterly Route 689 ENE-8/40 2.43 ENE 65° Quarterly Near Training Facility E-9/41 0.30 E 91 ° Quarterly "Morning Glory Hill" E-10/42 2.85 E 93° Quarterly Island Dike ESE-11 /43 0.12 ESE 103° Quarterly Route 622 ESE-12/44 4.70 ESE 115° Quarterly DVP Biology Lab SE-13/45 0.64 SE 138° Quarterly Route 70 I (Dam Entrance) SE-14/46 5.88 SE 137° Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 158° Quarterly Elk Creek SSE-16/48 2.33 SSE 165° Quarterly NAPS Access Rd. S-17/49 0.36 s 173° Quarterly 8

TABLE 2-1 North Anna Power Station-2016 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 s 178° Quarterly Thermoluminescent NAPS Access Rd. SSW-19/51 0.24 SSW 197° Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 205° Quarterly 500kv Tower SW-21 /53 0.60 SW 218° Quarterly Route 700 SW-22/54 3.96 SW 232° Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 237° Quarterly Route 700 (Exclusion Boundary) WSW-24/56 1.00 WSW 242° Quarterly South Gate Switchyard W-25/57 0.32 w 279° Quarterly Route 685 W-26/58 1.55 w 274° Quarterly End of Route 685 WNW-27/59 1.00 WNW 301° Quarterly Route 685 WNW-28/60 l.40 WNW 303° Quarterly North Gate - Laydown Area NW-29/61 0.52 NW 321° Quarterly Lake Anna Campground NW-30/62 2.54 NW 319° Quarterly

  1. I /#2 Intake NNW-31 /63 0.07 NNW 349° Quarterly Route 208 NNW-32/64 2.21 NNW 344° Quarterly Bumpass Post Office C-1/2 7.30 SSE 167° Quarterly Orange, VA C-3/4 22.00 NW 325° Quarterly Control Mineral, VA C-516 7.10 WSW 243° Quarterly Louisa, VA C-7/8 11.54 WSW 257° Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 42° Weekly and Radioiodine Biology Lab OJA 0.64 SE 138° Weekly Mineral, VA 03
7. 10 WSW 243° Weekly Wares Crossroads 04 5.10 WNW 287° Weekly Route 752 05 4.20 NNE 20° Weekly Sturgeon's Creek Marina 05A 2.04 N

11 ° Weekly Levy, VA 06 4.70 ESE 115° Weekly Bumpass, VA 07 7.30 SSE 167° Weekly 9

TABLE 2-1 North Anna Power Station-2016 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Airborne Particulate End of Route 685 21 1.00 WNW 301 ° Weekly and Radioiodine Route 700 22 1.00 WSW 242° Weekly "Aspen Hills" 23 0.93 SSE 158° Weekly Orange, VA 24 22.00 NW 325° Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 148° Monthly (Second Cooling Lagoon) Lake Anna (upstream) 09A 12.90 WNW 295° Monthly Control (Route 669 Bridge) River Water North Anna River (downstream) 11 5.80 SE 128° Monthly Ground Water Biology Lab OJA 0.64 SE 138° Quarterly (Well Water) Precipitation Biology Lab OJA 0.64 SE 138° Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon) Lake Anna (upstream) 09A 12.90 WNW 295° Semi-Annually Control (Route 669 Bridge) North Anna River (downstream) 11 5.80 SE 128° Semi-Annually Shoreline Soil Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon) Soil APS Sewage Treatment Plant 01 0.20 NE 42° Once/3 years Fredericks Hall 02 5.30 SSW 203° Once/3 years Mineral, VA 03 7.10 WSW 243° Once/3 years Wares Crossroads 04 5.10 WNW 287° Once/3 years 10

TABLE 2-1 North Anna Power Station - 2016 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 20° Once/3 years Sturgeon's Creek Marina 05A 2.04 N 11° Once/3 years Levy, VA 06 4.70 ESE 115° Once/3 years Bumpass, VA 07 7.30 SSE 167° Once/3 years End of Route 685 21 1.00 WNW 301 ° Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 242° Once/3 years "Aspen Hills" 23 0.93 SSE 158° Once/3 years Orange, VA 24 22.00 NW 325° Once/3 years Control Milk Lakeside Dairy 12A 7.50 NW 310° Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon) Lake Orange 25 16.5 NW 312° Semi-Annually Control Food Products (Vegetation) Stagecoach Road 14B 1.22 NNE 40° Monthly if available or at harvest Route 614 15 1.37 SE 133° Monthly if available or at harvest Route 629/522 16 12.60 NW 314° Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 158° Monthly if available or at harvest "Historic Lane" 26 1.15 s 172 ° Monthly if available or at harvest 11

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY Thermoluminescent Dosimetry (TLD) (84 TLDs) Quarterly (12 TLDs) Annually Airborne Radioiodine Weekly Airborne Particulate Weekly Surface Water River Water Quarterly (a) 2"d Quarter Composite Monthly Quarterly( a) 2"d Quarter Composite Monthly ANALYSIS Gamma Dose Gamma Dose 1-131 Gross Beta Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 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 I-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 LLD REPORT UNITS 2 mR+/-2mR mR/std. Month 2 mR+/-2mR mR/std. Month 0.07 pCi/m3 0.01 pCi/m3 0.05 0.06 (b) (b) l(c) 15 30 15 15 30 30 15 15 18 60 15 2000 (b) (b) l (c) 15 30 15 15 30 30 15 15 18 60 pCi/m3 pCi/m3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L

  • LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the 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 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives. 12

SAMPLE MEDIA River Water Ground Water (Well Water) Aquatic Sediment Precipitation Shoreline Soil TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQUENCY ANALYSIS LLD La-140 15 Quarterly( a) Tritium (H-3) 2000 2nd Quarter Sr-89 (b) Composite Sr-90 (b) Quarterly Gamma Isotopic Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-1 31 IO(c) Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly( a) Tritium (H-3) 2000 2nd Quarter Sr-89 (b) Sr-90 (b) Semi-Annually Gamma Isotopic Cs-134 150 Cs-137 180 Annually Sr-89 (b) Sr-90 (b) Monthly Gross Beta 4 Semi-Annual Gamma Isotopic Composite Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 (d) Cs-134 15 Cs-137 18 Ba-140 (d) La-140 (d) Semi-Annually Gamma Isotopic Cs-134 150 Cs-1 37 180 REPQB.I llNITS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/kg (dry)

  • LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the 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 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no,LLD is applied for these nuclides due to their short half-lives. 13

SAMPLE MEDIA Soil Milk Fish Food Products (Broadleaf Vegetation) TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQ!.!EN!.:;Y A~ALYSIS LLD Annually Sr-89 (b) Sr-90 (b) Once per 3 years Gamma Isotopic Cs-134 150 Cs-137 180 Sr-89 (b) Sr-90 (b) Monthly 1-131 1 Monthly Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (b) Sr-90 (b) Semi-Annually Gamma Isotopic Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Monthly, if Gamma Isotopic available, or Cs-134 60 at harvest Cs-137 80 1-131 60 REPQRT !.!NITS pCi/kg (dry) pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/kg (wet) pCi/kg (wet)

  • LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the 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 pCi/liter (d) LLD applied are those for water samples. However, since thjs is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives. 14

Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Designation Identification (a) 01,NE-5/37 IA OlA,SE-13/45 2 (a) 02,SSW-20/52 3 (a) 03,C-516 4 (a) 04 5 (a) 05 SA (a) OSA,N-2134 6 (a) 06,ESE-12/44 7 (a) 07, C-112 8 08-Water, Fish, Sediment, Shoreline Soil 9A 09A-Water sample, Sediment 11 11-River Water, Sediment 12A 12A-Milk 14B 14B-Vegetation 15 15-Vegetation 16 16-Vegetation 21 (a) 21,WNW-27/59 22 (a) 22,WSW-24/56 23 (a) 23-SSE-15/47,Vegetation 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

  • 15 Map Environmental Station Designation Identification 7/8 C-7/8 1/33 N-1/33 31163 NNW-31163 29/61 NW-29/61 3/35 NNE-3/35 7/39 ENE-7/39 9/41 E-9/41 11/43 ESE-11143 17/49 S-17/49 19/51 SSW-19/51 21/53 SW-21/53 23/55 WSW-23/55 25/57 W-25/57 16/48 SSE-16/48 14/46 SE-14/46 22154 SW-22/54 26/58 W-26/58 28/60 WNW-28/60 32/64 NNW-32/64 8/40 ENE-8/40 4/36 NNE-4/36 10/42 E-10/42

Legend -ixed Environmental Mo

  • oring Sfati<:>

D Locatrons Scale - 3.'8 inch = 235 ft. Figure 1. North Anna Site Radiological Monitoring Locations SSW 16

~NNE -~ -'**rwi*******ftft 17 ~~ ii TSYLVANIA l North Anna Environmental Map Fixed Environmental Sampling Location e TLD Sampling 9 oarden Residents Meat Animals . w CB328DE

18 LA North Anna Environmental Map e Fixed Environmental Sampling Location e TLD Sampling 9 Garden Residents e Meat Animals Original C 1991 by ADC or Alexandria, tne., 6440 Genernl Green Wtty, Alexandria, VA 22312. USED llVITH PERMISSION. No other reprodUdion may be made without the written permission of ADC. C83282E

North Anna Environmental Map 41 Fixed Environmental Sampling Location e TLD Sampling 9 Garden Residents Meat Animals Orlgin~l IJll 199'1 by AOC Of Alexandria lne.. 6440 Geril!l'31 Grllen Wey, Alexandria, VA UJH. USED V\\\\TH PERMISSION. No CU!cr reprOduetion may M made wilhout he wrtlen 041mission ct AOC. 19

e Fixed Environmental Sampling location e TLD Sampling 9 Garden Residents L..---- - M--ea_t_A_n_im_a_is __________________ ~I ~ }W ~~~ Oriigiruil C 1001 ~ADC ol Alexondrio,, Inc_. *6440 Gener:al Green 'W'".;y. / Alex:indrio. VA 22:312. USED WITH PERMISSIOO. No oth"' reproduction / ".._,'-/ l' ~ be ode wiihoul 1he writ:en perm-3ion o4 ADC. 20 I C83281E

3. ANALYTICALRESULTS 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 ODCM. For radioanalytic analyses, the values listed in the columns indicated as "Mean/Range" include any results above the Minimum Detectable Concentration, MDC. Results are considered true positives when the measured value exceeds both the MDC and the 2E error. For TLDs the mean and range include all values.

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 Summary Table because of the basic limitation of data summaries. 21

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia-2016 Docket No. 50-338/339 Page 1 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD<1> Mean Reported Sampled (Unit) Total (pCi/unit) Range Name Distance Mean Mean Measure-Type No. Direction Range Range men ts Direct Radiation Gamma 256 2 4.1 (2561256) 29161 0.52 mi. 7.0 (818) 3.2 (16/16)* 0 (mR/std. Month) Dose (1.0-8.1) NW (6.0-8.1) (1.9-4.3) (Sector TLDs) Direct Radiation Gamma 32 2 2.4 (16116) C-1 12 7.30 mi. 2.9 (818) 3.2 (16116)* 0 (1.9-4.3) (mR/std. Month) Dose (1.1-4.6) SSE (2.1-4.6) (Pre-operational TLDs) Direct Radiation Gamma 40 2 5.2 (40140) EPSP-0.37 mi. 7.7 (818) 3.2 (16/16)* 0 (mR/std. Month) Dose (2.7-9.1) 09110 ENE (6.6-9. 1) (1.9-4.3) (Emergency Sector TLDs) Direct Radiation Gamma 48 2 3.2 (44144) 23 0.93 mi. 4.8 ( 414) 3.2(414) 0 (mR/std. month) Dose (0.8-6.0) SSE (4.3-6.0) (l.9-4.3) (Environmental TLDs) Direct Radiation Gamma 12 2 2.8 ( 11111) OJ 0.20mi. 4.7 ( Il l) 2.5(111) 0 (mR/std. Month) Dose (1.7-4.7) NE (4.7) (2.5) (Annual TLDs) Airborne Gross 676 0.01 13.3 (6241624) 04

5. 10 mi.

14.3 (52152) 15.3 (52152) 0 Particulates Beta ( 4.09-33.9) WNW (7.27-33.9) (8.74-29.6) ( I E-03 pCilm3) Air Iodine l-131 676 0.07 (01624) NIA NIA. NIA (0152) 0 (pCilm3) Airborne Gamma 52 Particulates (I E-03 pCilm3) Be-7 52 128 (48148) 05 4.20mi. 144 (414) 152 (414) 0 (11 3-152) NNE (125-168) (1 14-206) Cs-134 52 0.05 (0148) NIA NIA NIA (014) 0 (I) rnR/std month for TLDs

  • C-3/4, -7 /8 used as control locations 22

Medium or Pathway Sampled (Unit) Airborne Particulates (I E-03 pCilm3) Soil* (pCilKg) (dry) Precipitation (pCi/liter) Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMAR Y North Anna Nuclear Power Station, Louisa County, Virginia-2016 Docket No. 50-338/339 Page 2 of 9 All Indicator Indicator Location Control Analysis Locations with Hi2hest Mean Location LLD Total (pCi/unit) Mean Name Distance Mean Mean Type No. Ran2e Direction Ran2e Ran2e Cs-137 52 0.06 (0148) NIA NIA NIA (014) Sr-89 13 (0/12) NIA NIA NIA (011) Sr-90 13 (0112) NIA NIA NIA (011) Triennial Gamma 12 K-40 12 12970 (1lll1) 23 0.93mi 32400 ( 111) 30600 (I l l) (4600-32400) SSE (32400) (30600) Cs-134 12 150 (0111 ) NIA NIA NIA (Oil) Cs-137 12 180 362 (6111) 06 4.70mi 646 (I l l) (Oil) (177-646) ESE (646) Ra-226 12 3809 (71l 1) 22 1.00mi 5510 (I l l) (011) (2400-5510) WSW (5510) Th-228 12 1644 ( I I ll I ) 22 l.OOmi 3650 (1 11) 209 (I l l) (487-3650) WSW (3650) (209) Th-232 12 1773(9111 ) 05A 2.04mi 3460 (I l l) (0/1) (5 15-3460) N (3460) Sr-89 12 (Oil I) NIA NIA NIA (Oil) Sr-90 12 (Oil I) NIA NIA NIA (Oi i) Monthly Gross 12 4 3.54 (10/12) OJA 0.64 mi. 3.54 (10112) NIA Beta ( 1.93-6.83) SE ( 1.93-6.83) H-3 4 2000 (014) NIA NIA NIA NIA Semiannual 2 Gamma Be-7 2 51 ( 112) OlA 0.64 mi 51 (1/2) NIA (51) SE (51) Mn-54 2 15 (012) NIA NIA NIA NIA Fe-59 2 30 (012) NIA NIA NIA NIA Co-58 2 15 (012) NIA NIA NIA NIA

  • Soil Samples required triennially. Samples were obtained in 2016.

23 Non-routine Reported Measure-men ts 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Medium or Pathway Sampled (Unit) Precipitation (pCi/liter) Docket No. 50-338/339 Page 3of9 All Indicator Indicator Location Analvsis Locations with Highest Mean LLD Total (pCi/un Mean Name Distance Mean Type No. it) Range Direction Range Co-60 2 15 (012) NIA NIA NIA Zn-65 2 30 (012) NIA NIA NIA Zr-95 2 30 (012) NIA NIA NIA Nb-95 2 15 (012) NIA NIA NIA 1-131 2 10 (012) NIA NIA NIA Cs-134 2 15 (012) NIA NIA NIA Cs-137 2 18 (012) NIA NIA NIA Ba-140 2 (012) NIA NIA NIA La-140 2 (012) NIA NIA NIA Th-228 2 5.30 (112) OIA 0.64mi 5.30 (l/2) (5.30) SE (5.30) 24 Control Non-Location routine Reported Mean Measure-Range men ts NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0 NIA 0

jiP Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Docket No. 50-338/339 Page 4 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit) Mean Name Distance Mean Mean Measure-(Unit) Tvoe No. Ran2e Direction Range Range men ts Milk Gamma 12 (pCilliter) K-40 12 1370 (1 2/12) 12A 7.50 mi. 1370 (1 2112) NIA 0 ( 1220-1460) NW (1220-1460) I-I 3 1 12 (0112) NIA NIA. NIA NIA 0 Cs-I 37 12 18 (0112) NIA NIA NIA NIA 0 Ba-140 12 60 (0112) NIA NIA NIA NIA 0 La-140 12 15 (0/12) NIA NIA NIA NIA 0 Sr-89 4 (014) NIA NIA NIA NIA 0 (Quarterly) Sr-90 4 (014) NIA NIA NIA NIA 0 (Quarterly) 25

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Docket No. 50-338/339 Page 5of9 All Indicator Indicator Location Control Non-Medium or Analvsis Locations 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 men ts Food Gamma 40 Vegetation (pCilkg) (wet) Be-7 40 1650 (32132) 15 1.37mi 2 110 (818) 1490 (818) 0 (473-4480) SE (866-3160) (I 060-2380) K-40 40 5380 (32132) 148 l.22mi 5560 (818) 4820 (818) 0 (3050-7410) NNE (4360-7410) (3460-8360) 1-131 40 60 (0132) NIA NIA NIA (018) 0 Cs-134 40 60 (0132) NIA NIA NIA (018) 0 Cs-137 40 80 (0132) NIA NIA NIA (018) 0 Ground Tritium 4 2000 (014) NIA NIA NIA NIA 0 Well Water (pCilliter) Gamma 4 Mn-54 4 15 (014) NIA NIA NIA NIA 0 Fe-59 4 30 (014) NIA NIA NIA NIA 0 Co-58 4 15 (014) NIA NIA NIA NIA 0 Co-60 4 15 (014) NIA NIA NIA NIA 0 Zn-65 4 30 (014) NIA NIA NIA NIA 0 Zr-95 4 30 (014) NIA NIA NIA NIA 0 Nb-95 4 15 (014) NIA NIA NIA NIA 0 I-131 4 10 (014) NIA NIA NIA NIA 0 26

Medium or Pathway Sampled (Unit) Ground Well Water (pCilliter) River Water (pCilliter) Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Docket No. 50-338/339 Page 6of9 All Indicator Location Control Non-Analysis Indicator with Highest Mean Location routine Locations Reported LLD Measure-Total (pCi/un Mean Name Distance Mean Mean men ts Type No. it) Range Direction Range Range Cs-134 4 15 (014) NIA NIA NIA NIA 0 Cs-137 4 18 (014) NIA NIA NIA NIA 0 Ba-140 4 60 (014) NIA NIA NIA NIA 0 La-140 4 15 (014) NIA NIA NIA NIA 0 Sr-89 (Oi l) NIA NIA NIA NIA 0 Sr-90 (Oi l) NIA NIA NIA NIA 0 Tritium 4 2000 3930 ( 414) 11 5.80 mi. 3930 (414) (014)* 0 (3340-4230) SE (3340-4230) Gamma 12 Mn-54 12 15 (0/12) NIA NIA NIA (0112)* 0 Fe-59 12 30 (0112) NIA NIA NIA (0112)* 0 Co-58 12 15 (0/12) NIA NIA NIA (0112)* 0 Co-60 12 15 (0/12) NIA NIA NIA (0/12)* 0 Zn-65 12 30 (0/12) NIA NIA NIA (0112)* 0 Zr-95 12 30 (0112) NIA NIA NIA (0112)* 0 Nb-95 12 15 (0112) NIA NIA NIA (0112)* 0 1-131 12 (0112) NIA NIA NIA (0112)* 0 Cs-134 12 15 (0/12) NIA NIA NIA (0112)* 0 Cs-137 12 18 (0112) NIA NIA NIA (0/12)* 0

  • Results of surface water taken at Location 09A used as control value for river water 27

Medium or Pathway Sampled (Unit) River Water (pCi/liter) Surface Water (pCilL) Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORIN G PROGRAM S UMMARY North Anna Nuclear Power Station, Louisa County, Virginia - 201 6 Docket No. 50-338/339 Page 7of9 All Indicator Indicator Location Control Non-Ana lysis Locations with Highest Mean Location routine Reported LLD Measure-Total (pCi/unit) Mean Name Distance Mean Mean men ts Type No. Range Direction Range Ran2e Ba-140 12 60 (0/12) NIA NIA NIA (0112)* 0 La-140 12 15 (0/12) NIA NIA NIA (0112)* 0 Sr-89 (Oi l) NIA NIA NIA (Oil)* 0 Sr-90 (Oi l) NIA NIA NIA (Oi l)* 0 Tritium 8 2000 4270 (414) 08 3.37 mi. 4270 (414) (014) 0 (3580-58 10) SSE (3580-58 10) Gamma 24 Mn-54 24 15 (0/12) NIA NIA NIA (0112) 0 Fe-59 24 30 (0112) NIA NIA NIA (0112) 0 Co-58 24 15 (0/12) NIA NIA NIA (0112) 0 Co-60 24 15 (0/12) NIA NIA NIA (0112) 0 Zn-65 24 30 (0/12) NIA NIA NIA (0112) 0 Zr-95 24 30 (0112) NIA NIA NIA (0112) 0 Nb-95 24 30 (0/12) NIA NIA NIA (0112) 0 1-131 24 (0112) NIA NIA NIA (0/12) 0 Cs-134 24 15 (0112) NIA NIA NIA (0112) 0 Cs-137 24 18 (0112) NIA NIA NIA (0112) 0 Ba-1 40 24 60 (0112) NIA NIA NIA (0112) 0 La-140 24 15 (0112) NIA NIA NIA (0112) 0

  • Results of surface water taken at Location 09A used as control value for river water 28

) Medium or Pathway Sampled (Unit) Surface Water (pCill iter) Sediment Silt (pCi/kg) Shoreline Soil (pCi/kg) (dry) Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMAR Y North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Docket No. 50-338/339 Page 8 of 9 All Indicator Indicator Location Control Non-Analysis Locations with Highest Mean Location routine Reported LLD Measure-Total (pCi/unit) Mean Name Distance Mean Mean men ts Type No. Range Direction Range Range Sr-89 (011) NIA NIA NIA (0/1) 0 Sr-90 (0/1) NIA NIA NIA (Oi i) 0 Gamma 6 K-40 6 9700 (414) 11 5.80 mi. 17900 (212) 23100(212) 0 ( 1280-2 1800) SE (14000-(22500-23600) 2 1800) Cs-134 6 150 (014) NIA NIA NIA (012) 0 Cs-1 37 6 180 (014) NIA NIA. NIA (012) 0 Ra-226 6 1220 (414) 11 5.80 mi. 2 130(112) 2520 (212) 0 (764-2 130) SE (2 130) (2270-2760) Th-228 6 350 (414) 11 5.80 mi. 602.5 (212) 861 (212) 0 (81.7-779) SE (426-779) (769-953) Th-232 6 512.5 (214) 11 5.80 mi. 512.5 (212) 718 (212) 0 (500-525) SE (500-525) (59 1-845) (Annually) Sr-89 3 (012) NIA NIA NIA (0/1) 0 Sr-90 (012) NIA NIA NIA (0/1) 0 Gamma 2 K-40 2 806 (212) 08 3.37 mi. 806 (212) NIA 0 (532-1080) SSE (532-1080) Cs-1 34 2 150 (012) NIA N'A (012) NIA 0 Cs-1 37 2 180 (012) NIA N'A (012) NIA 0 Ra-226 2 (012) NIA NIA (012) NIA 0 29

} Medium or Pathway Sampled (Unit) Shoreline Soil (pCi/kg) (dry) Fish Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMAR Y North Anna Nuclear Power Station, Louisa County, Virginia-2016 Docket No. 50-338/339 Page 9 of 9 All Indicator Indicator Location Control Non-Analysis Locations with Highest Mean Location routine Reported LLD Measure-Total (pCi/unit) Mean Name Distance Mean Mean men ts Type No. Range Direction Ran2e Ran2e Th-228 2 (012) 08 NIA NIA NIA 0 Th-232 2 (012) NIA NIA NIA NIA 0 (Annually) Sr-89 (Oil) NIA N'A NIA NIA 0 Sr-90 (Oi l) NIA N'A NIA NIA 0 Gamma 8 (pCi/kg) (wet) K-40 8 1750(414) 8 3.37 mi. 1750(414) 1620 (414) 0 (1520-2000) SSE ( 1520-2000) (1400-2140) Mn-54 8 130 (014) NIA N'A NIA (014) 0 Fe-59 8 260 (014) NIA N'A NIA (014) 0 Co-58 8 130 (014) NIA N'A NIA (014) 0 Co-60 8 130 (014) NIA N'A NIA (014) 0 Zn-65 8 260 (014) NIA N'A NIA (014) 0 Cs-134 8 130 (014) NIA N'A NIA (014) 0 Cs-137 8 150 (014) NIA N'A NIA (014) 0 30

3.2 Analytical Results of 2016 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 (2cr) 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 true positives when the measured value exceeds both the MDC and the 21: error. Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data 1* For clarity of this report only detectable results are presented. TBE'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 AnnaODCM. Data are given according to sample type as indicated below.

1.

Gamma Exposure Rate

2.

Air Particulates, Gross Beta Radioactivity

3.

Air Particulates, Weeklyl-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 1 Analytical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984). 31

TABLE 3-2 DIRECT RADIATIONMEASURMENTS-SECTOR QUARTERLY TLD RESULTS Page mRJStd. Month (30.4 days)+/- 2 Sigma 1 of4 First Quarter Second Quarter TmdQuarter F ow1h Quarter Quarterly* Station 12/29120 15 3 912016 612812016 912812016 Average 312912016 612812016 912812016 12127 0 16 +I-2 s.d N-1 5.2 4.4 4.4 4.8 4.6 +!- 0.9 N-33 4.8 4.1 4.1 5.2 N-2 2.6 1.8 2.6 3.0 2.6 +/- L1 N-34 2.6 L9 2.7 3.4 NNE-3 6.6 5.7 5.8 7.5 6.5 +!- u NNE-35 7.6 6.0 6.1 6.7 NNE-4 4.1 33 3.6 3.7 3.8 +/- L1 NNE36 3.8 3.0 3.7 4.9 NE-5 3.9 3.7 4.2 43 3.9 +/- u NE-37 3.9 3.2 2.9 53 NE-6 2.6 2.7 2.9 4.6 3.2 +!- L7 NE-38 3.2 2.6 2.7 4.5 ENE-7 4-5 43 5.2 6.1 5.4 +!- u ENE-39 5.8 6.1 4.9 5.9 ENE-8 2.8 2.5 2.6 2.5 2.8 +!- 0.8 ENE-40 3.2 2.9 2.4 3.5 E-9 5.0 4.7 4.2 5.6 5.0 +!- 0.9 E-41 5.4 5.1 4.6 5.2 E-10 4.8 3.0 3.0 3.9 3.6 +!- 1.4 E-42 3.6 2.9 33 43 ESE-11 3.7 4.5 3.5 5.0 3.9 +!- 1.2 ESE-43 3;6 33 3.5 4.1 ESE-12 4.9 4.5 3.4 5.0 4.4 +!- 1.2 ESE-44 4.2 4.5 3.8 5.1 SE-13 5.1 3.7 3.8 3.7 4.0 +!- 1.9 SE-45 4.5 3.l 2.7 5.4 SE-14 6.8 7.1 5.9 7J 6.9 +I-1.2 SE-46 7J 7.2 6.2 7.9 SSE-15 4.4 3.9 4.6 4.9 4.5 +!- 0.9 SSE-47 5.4 4.2 4.2 4.6 SSE-16 2.4 3.2 L7 3.0 25 +!- LO SSE-48 23 23 2.1 2.7

  • Average of collocated TLD s.

32

TABLEJ..2 DIRECTRi\\DLl\\TION Aff.ASURMENfS-SECTOR QU.'\\RTERLY UDRESULTS Page mR/Std. Month (30.4 days)+/- 2 Sigma 2 of4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly* Station 12 9 015 3 912016 6 8/2016 9 8/2016 A\\1lrage 3 9, 016 6 8 016 9128/2016 1212 712016 -2 s.d. S-17 5.4 3.4 3.1 4.7 4J +/- 2.1 S-49 5.6 2.9 4.4 4.7 S-18 1.7 2.0 L3 1.8 1.7 +/- 0.6 S-50 1.9 l.8 1.1 1.7 SSW-19 6.4 6.8 63 5.9 6.1 +/- 0.9 SS"\\ -51 5J 5.8 6.0 5.9 SS"\\ -20 2.1 2.4 2.1 3J 2.2 +I-0.8 SS"\\ -52 1.9 2.0 2.0 2.2 SW-21 4.8 4.5 3.7 5.1 4.6 +I-0.9 SW-53 4.6 4.7 4.2 5.0 SW-22 4.6 4.4 3.6 5.1 4.1 +/- 1.2 SW-54 3.7 3.8 3.4 4.2 "\\ SW-23 4.9 3.5 32 5.2 4.3 +/- 1.9 "\\ SW-55 3.6 4.8 3.7 5.8 WSW-24 4.7 3.4 3.9 5.0 4.2 +/- l.l "\\ SW-56 4.5 4.5 3.8 3.8 W-25 6.8 7.6 5.7 6.8 6.8 +I-1.4 W-57 7.1 7.0 5.8 7.6 W-26 2.6 2.5 2.6 33 2.7 +!- 0.5 W-58 2.5 2.8 2.7 2.9 WNW-27 2.4 2.8 2.8 3.8 32 +I-1.3 WNW-59 3.7 2.8 2.8 4.2 wm -2& 3.0 2.2 4.7 3.9 3.4 +/- 2.0 \\VNW-60 3.4 1.9 4.5 3.4 NW-29 6.7 6.6 6.0 7.1 7.0 +I-1.4 NW-61 7.8 73 6.5 8.1 NW-30 1.6 1.8 1.0 1.9 L7 +/- 0.9 NW-62 1.8 lJ 1.4 2.4 NN\\V-3 1 32 2.8 3.1 33 3.1 +/- 0.7 NN\\V-63 32 2.4 33 3.5 NN"\\ -3 2 2.8 2.6 32 3.7 3J +/- 1.1 NN"\\ -64 33 3.1 2_9 4.4

Me.an 4.1 +/-

1.5

  • Average of collocated 11.Ds.

33

TABLE 3-2 DIRECTRADIATIONMEASJRMENTS-SECTOR QUARTERLY IlDRESULTS Page mR/Std. Month (30.4 days)+/- 2 !igma 3 of 4 First Quarter Second Quarter Third Quarter Fwrth Quarter Quarterly* Sia lion 12129 015 3 9/2016 6 &/2016 9/2&/2016 Average 3 9/2016 612 2016 912 2016 2712016 - 2 s.d. C-1 2.6 2.3 3.1 3.4 2.9 +I-l.6 C-2 2.4 2.l 2.7 4.6 C-3** 2.8 L9 3.l 3.5 2.9 +I-1.2 C-4** 3.0 2.0 2.9 3.6 C-5 l.7 u l.7 3.0 1.9 +I-1.2 C-6 2.0 L5 2.0 2.5 C-7** 3.6 2J 3.4 3.& 3.5 +/. l.2 C-8** 3.8 3J 3.4 4.3 2.4 +I-l.7 3.2 +/- 1J EPSA-01*** 4.5 4.0 5.4 5.3 4.6 +I-l.l EPSA-02*** 4.6 4_0 4.3 4.& EPSF..03*** 5.0 3.4 3.7 3.8 4.0 +I-l.6 EPSF..04*** 3.4 4.6 3.0 5.2 EPSR-05*** 5.3 5.0 5.6 7.2 5.9 +/- l.7 EPSR..06*** 6.9 6.4 4.9 5.5 EPSJ-07*** 4.1 3.6 2.7 4.7 3.9 +I-13 EPSJ..O&*** 4.1 4.0 3.6 4.6 EPSP-09*** 7.5 &.l 6.6 8.4 7.7 +!- l.7 EPSP-10*** 8.2 7.2 6.7 9.1 Mean 5.2 +!- 3.2

  • Average of collocated TI..Ds.
    • Control S tat:ion
      • Emergen~y Plan TI..Ds.

34

TABLE 3-2 DIRECTRADIATIONAfEASURMENfS- !!ECTOR QUARTERLY UDRE&JLTS Page mR/Std. Month (30.4 d.ays) +/- 2 Sigma 4 of4 First Quarter Second Quarter Third Quarter Fourth Quartet Qmrterly Station 1 29/2015 3 9/2016 6128/2016 9 8/2016 Average Annual 1LD 3129 016 6 8/2016 9/2&12016 12127/2016 +!- 2 s.d. STA-01 3.5 3.2 3.l 5.3 3.& +/. 2J 4.7 STA-02 L7 2.7 2.1 23 2.2 +I- 0.8 1.9 STA-03 2.l 1.7 2.1 2.4 2.1 +I- 0.6 L7 STA-04 2.5 2.1 2.6 2.7 2.5 +I- 0.5 1.7 STA-05 2.4 2.4 2.1 2.6 2.4 +I- 0.4 2.6 STA-05A 2.5 2.5 3.8 2.5 2.8 +I-lJ 2.2 STA-06 4.8 4.6 3.9 52 4.6 +I-l.1 4.l STA-07 33 0.8 2.5 3.2 2.5 +I-2.3 2.4 STA-21 2.5 2.9 2.7 3.6 2.9 +I-1.0 2.2 STA-22 4.5 4.6 4.0 4_9 4.5 +I- 0.7 3.4 STA-23 4.7 43 43 6.l 4.9 +I-1.7 4.l STA-24* 2.9 1.9 3.2 2.9 2.7 +I- 0.6 2.5 Man - Indicator Locations 3.2 +l-12 2.8 +I-2.1 '*Conlrol 35

P!rii>d & J!!ifi,g 01.-05/16 01.t12t115 01119.tlo Olf.l9.t16 fil.tl6 '2.tl0/16 0'211 i'.1115 01a.3.t115 03.-0'2*16 03-0!tll6 13f15Jli5 13.(1:3,1115 13.@.tl6 .05.*115 04.113.*115

  • 00.1115

.Ql5.1115 15!.!4.116 05.13 llllli !i.-07,1115 OM 4.t16 O!i.1.21.'16 015'28116 ll>iE..01 .J!3E+OO 19.>E+Ol 9.37E-+<OO 145E+Ol l llil..01

9. f!:l:E-+<00 9.93E-+<OO l OlE-+-01 U EE+-Ol!

14!lE+-Ol 1 15E+Ol 1 13E+Ol 105E+01 1~+01 l IOE+Ol Hi3B+Ol E.'.BE+OO 16'!E-t-Ol l ©E+Ol Ull!E+Ol l 79B+Ol 5l!E-+OO LOOE+-01 121E+Ol 13~+01 Statioo 01 + + +. + + + +,. +, + +.. +l + + + + + +.~ +,. + +.. +., + + + +, +. 23 fE+OO L'.XlE+-01 2~-+<00 U!8E+0] 2.9;E+00 1.34B+Ol llEE.;(() LllE+Ol 29.fE+OO L34E+-Ol lliE+OO B.Bffi+-00 Sa.rim 02 Ta.bl!3-3 Air Partial!al! Gfo*~ :&!Ill Radioactivity nll"' teilm'l St! lion Stttim I oo I oi 1.448.;(() 1.1 i'E+-01 +/- 1.428+00 lU7E+OO +, H iiE-+<00 *6..92:E+OO +!- 2:.53E+oo 16.9lE+OO +, lilliiE-+<00 15 3E-+-Ol +.I-1.74E+OO 1.19E+Ol +, 1.42E-+<OO LOEE+-01 +t-23 EE-+00 LC9E+-Ol +,

2:.9CE+OO l.22E-+

E-+<X> 1..3 lE++Dl +t-1.1%:+00 UOE+Ol + I S~ioo 1 19E+OO Ll2E+o1 +. 1.43E-+OO Ui'E<-01 +. 3.BE+OO L51E+-Ol +, 2.34B+OO 1.G7E+Ol + 2.90E+OO L41E+-Ol +, 1.21E+-OO 1.lPE+-01... 1.3EE-KXI 1!..4DE+-OO +.<- l32E-+{XI &50E+OO +t-23%:+00 9.~00 +I-2..42E+oo 9.75E+oo +,. 294E+OO L l3E+-OI +.r-3.03E+OO Ll.2E+Ol +t-3"03E+OO 1.14&01 +1-3.09E!-00 U OE+-Ol +. 221E+OO 9.. ffl'E+OO +.1-l.2CE+OO 9..34E+OO +t-1.1 iE+OO La:!Bl-01 +.I-221E+oo l.03B+-Ol +, 3.I<!E!+OO
9. i4E+OO
+I-lliE+ID 9.17E+OO +t-29iE+oo U lE+-01 +,t. 3.07&00 U 4E+-Ol + 2E.CE+OO Ll~Ol +I-1.71E+OO 957E+l>ll +t-2:.53E+OO L:2&E+ol +.I-2.73BIOO l.12E+Ol + 1Jl<!E+OO U lE+iXl +!- 2 1 iE+OO L1 iE+-01 +!- 2428-!00 9.90E+-OO + li~+<Xl 9.(b~OO +.1-2:.53E-+<X> &9PE+oo +!- 1.#'E+OO L05E+Ol + 1.*ISlE.;(() !!.. 7*:+00 +.I-1.52E+OO 555E+-OB +t-1.3~;.()(I U 4B+Ol +, 1.4'.lE+OO Ul3B+OI +.I-H!E-+00 1 1.~-+-0 l +!- 1.41lE.;OB L14Bl-01 +" '.U fE+OO U 3E+Ol +.I-1.5iE+OO L*DOE+Ol +t-2 73E+OO U lB+Ol +. l.~+00 L5.3E+01 +I-292E+OO lo67B+-Ol +t-li'!lB-+00 L29B+ID +.. 1.4i!E+OO
  • 15.2l!E+OO
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~ & ;llin;g 01.GSJllS l.tl2tl.IS 01119.1115 01.QP/16 02filtl.6 02/lo.tJ.6 02.tl 7116 02.'23.tJ.IS 03.>02/16 03Al81115 031151115 03.'231115 03.'29.1115 04.-0S.tl.6 041131115 04/lM!i 04/161115 05,03!115 06'2&116 Tab1e3-4 Airborne Iodine I-131 [to-3 pCi/m3] page l of 'Statim 'S t=tim SI! tioll Stotim St=tion S llllicn S t=tim I 01 I 01 I Q3 I 04 I ffi I 00 I UT I l..l2E-t-Ol 1.lUB+Ol 1.l!tE+-01 2-&SE+-01 1 l!SE+Ol 142E+Ol 2 41.E+-Ol LOOE<!-01 2 64E+Ol 2 7iE-+-Ol 2 64E~ l 164EHll 7.M+OO 206.E+-Ol 15 i.E+Ol 4.0.l!E+Ol 4.01.E+Ol 4.14E+-Ol 4.~+1()1 3.2DE+Ol 3.10E+Ol 3.4fE-+-Ol 3.45E+Ol 3.5<E+Ol U3E+-Ol l47EHll 3.35EH>l 333E+-01 LICE+<lll .1J!3E+Ol 2J!2E+Ol 2.&3E+Ol l l!3E+Ol 3.!l:E+Ol 3.B1E--Ol l.93E-+-01 455E+Ol 4.3~+01 4.45E+ol 4.32Bl-01 195B+-01 l96Bt-Ol 4.92£.;(() l.11E-+-Ol 1.1~+01 U5E+-Ol L 13E+Ol U OE!-01 l.IOE+Ol 4,!SiE-t-01 4J1SiE-t-Ol 4.~+ol LIUE+-01 4.*Di'E+<ll .159E+-01 3.59Et-01 4.21E+Ol 4.11E+Ol 4.21E+ol 4.21£--01 IS. lllEt-()1 IS. i&E+-01 3..SOE+-01 UfE+Ol 3.44E+Ol 3.3iE+ol 3.43E+Ol 3..40E+-01 l!!OE+Ol 3.BlE+-01 23 lE+Ol l.19E+Ol 23(£+-01 2.30Ef-Ol 130E+Ol .1l7E+Ol 1.l 7E+Ol IA5lE+Ol L6lE+Ol l.61E+Ol USlE+Ol L~+Ol L~+Ol L90E-'-Ol 151E-+<01 JJ!AE-+-01 3.i l!E+Ol 3.78E-l-O] 11!3Ei--Ol 4.4EE+Ol 4.4e:E-l-Ol 153E-+-Ol 2J!5E+Ol 2.92E+-Ol 2.94Ef-Ol l~l 3.9.lE!-01 3.92E+-Ol 4.35E-t-Ol 4.42E+Ol 45 lE+Dl 4.45E+Ol iS.lOE!-01 15.~l 6.07E+-Ol 1.46!:'+'01 3.45E+Ol 3.45E+Ol 3..50:&.<ll 145.E+Ol 1 *64:&01 3,64E+Ol 4.2iE-+-Ol 4.0lE-+-01 4,15JE+01 UllE+Ol 7_,fiJE-liX) 35 !!E-l-Ol 2 6!E-+ID 2.35E+Ol 2-SlE+Ol 5Jl54ETOO 4.44E+Ol 4.0lE+Ol 4.63E+-Ol U lE+-01 l.911E+Ol 35 8E+Ol ,6_4iE+Ol 6.25E+Ol 6.44E+Ol U lE+Ol 4.43E+Ol 4.00E+Ol 4J63E+Ol U lE+Ol l.9ffi+Ol U~+Ol 15.4iE+Ol
  • 6.2'iE+Ol
  • 6.4fE+Ol l.2tE+01 40 4.37E+Ol 4.0lE+Ol l..94E--Ol UOE+-01 l.96E+Ol 35 8E+-Ol 65 3E+0]
  • l!U9E.;-01 6.44E+-Ol l.19E+Ol 4.~B-01 i OOE+Ol 4.63E+Ol 7.0lE+OO L915El-Ol 3.5~1 6.47E+m 6.25
  • 6.44:
L30E., 4.Qi.E+Ol i OOE+Ol L4PE+Ol 103E+Ol 231&.-0l
  • 6.llE!-01
  • 6. 76.E+--01 i 65E+Ol i97E+Ol L41E+-Ol 4.95E!-Ol 5.00E+Ol l.49E+Ol 2.03E+-Ol
'lJlE+Ol i5-81E+Ol 6.76E+Ol 5.65E+Ol 5..97E'-Ol L42B-Ol Period
01. 9.<16 01.@. IS O"lh IS O"l/10. IS 6
5 IS 04.l'.2iS.116 05~3 Ci 05.,i].()116 IS 6 6 IS OM!!. 6 Sb tfo11 21 242E+ol lOiE+-01 120E+ol 134E+ol 4.55E+Ol 1 91E+Ol lllE+ol 3.AllE+Ol Q. ilIB+Ol 1 - E+Ol 2 17E+Ol 1915E+Ol 4.48E+ol 193E"'°l
  • 6. 1.SE"'°l lmE+Ol 4.93E-+-Ol 5.0lE+-01 l fi"'°l 203E-+-Ol 230E+ol 6.00E-+-01 Q. i'IIB+Ol 5.67E+ol
5. !lQE-+-01 U PE+ol
  • "' Control Station Stman 22 2.42Et--01 2.CISE.;.fil 3.XIE+Cl 3.34E+Cl 3JllE.;.fil 3.91E+Ol LUE
~ 3.<15lE+Ol ,15.. 7l!E+-Ol
3. 75E 1 2.li'E+Ol 9.04E+OO 4.48Er01 3.9.lE: 1
6. ~01 HiS.E+Ol l.'.l5E+fil LEi'E+Ol L'WE+Ol 2ffiE+Ol 230E+Ol
6. 00E+ 1
6. 'ilSE!-01 5.6i'E+Ol 5.@E+()l U9E+Ol Table3-4 Airbome Iodine I-131
[ 10-3 pCih:n 3] Stnca 23 2SOE+Cl 207& 1 l51E+01 3..iPE+Ol 137E+()l 2 71E+Cl l21E+Cl 2 i3E+-C1 4.19E+Ol 106E+()l 241E+Cl 1 67E+Ol
4. lOE+- l 3..J5E+Ol
6., E*Ol 191E-Ol
4. ll!E+Ol 4.1!1EHll 200E+Ol 194E+Ol 3..- E+Ol i38E+Ol
  • 6.02E+Ol 5.~
H lE 2 99E 1 4 1 Station 24"* 2.4m+Ol 253E+Ol H~+o l U3E+ol 331E+Ol 2,,ISQE+-01 l..21E+Ol 2748+01 4.191>-+-0l 2.95E+Ol 241E+Ol lJl5iE-+-Ol 4.~+0 1 3.1tE+ol 6..9JE.;-01 4.15E+ol 4J <tE+Ol 4.E2E+Ol 2.0IE+Ol 1..948+01 3_ 3E;-01 B iE+Ol 6.0lE+Ol 5.Z'E+Ol l.S3E+Ol llllE-+-01 Station OlA 252E+-01: 2528+01 351E-+-Ol 3Jt.JE+Ol BiE+Ol 2illE+Ol U iE+Cl 2i3E+Ol 4.l'!lE-+-01 3.0EE+Ol 2-41E-+-Ol L6iE+ol 4.13E+Ol 3.2JE+Ol 2a<E+Ol 4.0tE+ol 4.0JE+Ol 4.91!8-+-0l 2.0IE-+-01 1..948+01 3.74B+Dl 5.3 BE+Ol 6.l'!lE-t-01 5.HE+Ol .2.ElE-t-01 3.028-+-0l Stman 05A ~01 2.S3E+Ol 3Al!E+ 1 3.6l!E+ 1 3.3i'E+Ol
l. i3E+Ol l. ~01
l. i3E+Ol 4.19E+Ol 2.99E+Ol l.41E+Ol L6i'E+Ol 4.lOE+Ol 3.25E+Ol 6.83E+Ol HlE+-01 4.BE+Ol 4.lnE+-01 201E+-Ol L93E--Ol
3. i4E 1
>-JEE+Ol 6.mE+Ol 5.1iE+Ol 2!0.E+Ol 94:e+-01 page 2 of 4
R!rii:d
~.g 07.IOi/16 Oi'.112116 0711~ 1 6 071161liS 0&.'02fl6 (lg.@116 O&ili'.116 OW2416 O&l.30!16 '05'16 Oll!14116 0~1 6 12&116 10"04116 10'11116 10'lg'l6 10'1il16 lll!Wl l5 115 M21 Table3-4 Airborne Iodine I-131 [to*3pCilm3) page 3 of 4 Statm Statim 'Stalim Staticn Station Station Statioo I 01 L m I 03 I ~ I 0:> I os I UT I i 1DE+Ol B 2E-t-Ol 2 l&E-+-Ol L63B-+-Ol 4-23E+Ol 7..07E+OO L'.:\\4E+-01
2. 15E-+-01
.3..26B-+-Ol 491E-!-01 9.39E+OO L 71E+Ol H lOE+Ol .3..96E+-01 4-19E-!-Ol L21E+Ol i 52E-<-Ol L45E+-Ol 2 33E-+-01 L57E+-01 423E+Ol Ll2E+-Ol 9-BISB+OO .3..96E+Ol Ui'E+Ol l.51E+Ol 5.8DE+-Ol S34E+-01 5.04E+-Ol U5E+ol US4E+-01 Llt3E+-Ol 3.17E+-Ol 5_1.15E+-Ol 6..2*6E'+Ol 4..91Ei-Ol 239E+Ol 4.os:E+-01 4.51E+Ol 3..PPE;-01 4.!0E+-01 1.S5E+Ol 5.42E+-Ol 3.3/E!-01 J.56E+Ol H2E+-01 4..23E+-01 l.66E+Ol 236E+-Ol 3..94E'-01 3J4E-'-01 +, .3..35E+Ol
  • 6.13E+-Ol 5.34E+-Gl 5Jl7E+Ol
3. 1!3E+Ol 4.23E+-01 L.1!3E+-01 3.F7E+Ol 5.15Bl-01
,IS_l)Bt-01 4.91E+<ll l.35E+<ll l.1!3E+Ol
5. l!SE+Ol 3.32:E+01 3.55E+-Ol
3. 71E+-01 4.!IB+-01 l.,67E+-()1 l.36E+-01 3.~E+Ol 3.22E!-Ol
+, 3J5E+-Ol 5..92H+Ol 5J4E+Ol 5.04E+Ol U5E+Ol 4..23E+Ol L83E+Ol 3.l iE-+-01 5-l EE+Ol 6.14!-+-01 4..91E+Ol 2..3iE+Ol 4.0iE+Ol 4.4!iE+Ol 4.05E+Ol 4J!$E+Ol 1.83E+Ol 553E+Ol 3..2.""8-+-01 355E+Ol 3.nE+Ol 4..24!+01 2'61E+Ol 2..3*tE:+Ol l.61E+Ol 3J<E+Ol +!- 336&.-01 42 4.liE+-01 5.1 'iE+Ol 5.G<IE+Ol U 5E+Ol 4..23E+Ol U.3E+Ol 3.l iE+Ol H fE+Ol 6.2!tE+Ol 4J6iE+Ol 23-tE+Ol 4.0EE+Ol < 4.52E+Ol 4.13E+Ol 4..&3E+Ol < l.S5E+Ol < 451E+ol < 3JiE+ol lSl!E+Ol < 3.72E+Ol 4.43E+Ol < l.61E+Ol 231E+Ol 3..94E+ol 3JIE+Ol 3J5E+-Ol +. 4..2fE+ol 5.l 'iE-+-01 5.BlE+-01 5.HE+-01 4J!1E+Ol 2..45E+Ol 3.0IE+Ol 4..93E+Ol 5.71lE+OI 4.6iE+Ol 3J.3E+Ol 5.UE+Ol 4.1.3E+Ol 4.l lE.;-01 4.HE+-01 l.41E.;-01 4.5"1E+Ol 3.B4E+-OI l.Bm+Ol 3JlE+Ol 4.43E.;-01 l.51E+Ol 1.24!+01 3.l lE+Ol 3.4fE+Ol 4.11E+Ol 4.14E+Ol 5.l 'i'E-t-01 5J!IE+Ol 5.lOE+Ol 4.82E+Ol l.45E+Ol 3.00E+-01 4..93E'-Ol 5.7lE+-01 4.67E+Ol 3J3E+-01 5.lOE+-01 4..23E+Ol 4.llE-'-01 4.l 4E+<ll l.41E+Ol 4.53B+-01 3.&4E+Ol l.S&E+-01 3Jl E+-01 4.43E+-Ol l.52:E+Ol 1.24E-+Ol 3.llE+-01 3.44E+Ol 4..20E+-Ol Period B:ufui.g Ol!.<>21115 Ol!.OP/115 Ol!.1171115 Ol!.1141115 Ol!.13M 15 09.06fl6 09.1141115 09ll M 6 09.Ql!.116 10.-04.116 10.llltliS 1M 9J1.15 Ul.l.l51115 Il.02'1115 llll 5116 lli22Jl6 111.291115 12071115 12114.116 12'20116 12Q7116 MB.l\\N Table3-4 Airborne Iodine I-131 [10-3 pCi/m3] Sbfian Sfatian Sb.tim Station Statian Sb.lion I .2l I 22 I 23 I 24'** I OlA I QSA I 4.3CE+Ol
6. llE-+-01 i 9i'E+Ol
6. lllE+-01 2-41!E+Ol
  • 6-08E+Ol i 17E+-Ol i l!4E+Ol i O'iE+Ol 4..!!:IB+(IJ.
2 46E+-01 3.00E+-01 4.93E+-Ol i 77E+-01 4.0iE+-01 BOE+-01 i lOE+-01 4.23E+-01 4.llE+-01 4.13E+Ol
lSOE+-01 4.64E+-01 1 79FH-01
l lfiE+-01 1 31E+-Ol 4.-0E+Ol 2 52E+Ol 2 24E+Ol 3.llE+Ol 3.40E+Ol
+I-4.21E+ol lOOE+-01 i9iE-+-01 i GiE+-01 4.l!:l:E-+01 2 46E-t-Ol 3.00E-t-01 4.93E+-01 i 77E+-01 L23E+-01 3.31E+-01 i C9E+-Ol 4.22E+-Ol 154E+ol 4.b""E+ol 2 43E-t-Ol i&SE+-01 17PB+Ol lli'E+Ol 131E-'-Ol L93E+-Ol 252E+ol 224E+Ol < lllE+Ol 138E+Ol 4.21E+Ol 4.47E-t-Ol H 2E+Ol 4.93E+Ol 4.I7E+Ol 2~+01 2 l!OE-t-01 14/E-+-01 4.91E+Ol 117E+Ol lOOE+ol i51E-t-Ol 4.*filE-t-01 l 55E+-01 1 1!9E+ol l )l)E+ol 1315E+Dl 2,l!fill+-01 1 03E+Ol 135E+ol H lE+-01 231E+Ol 291E+Dl 4.17E+ol 163E+Ol +I-l f!ra+-01
    • Control Station 43
4. 4llE+-Ol i62E+Ol 4.!XE+-01
4. l l!E+Ol l OIE+-01 2 7~+0]
14EE+Ol
4. &llE+-01 11 iE+-01 l 7EE+ol i53E+<ll 4.*62E+<ll
< l53E+Ol l&llE+Ol lll!E.;-01 i91E.;-01 2*6iE-i-Ol 102E+<ll l35E+Ol 4.5g£.;-01 131E+fil
l92E+Ol:
4.HE+-01 153E+Ol H llE+Ol Imica1D! Lca*ti.cns M'21 4.4iE+-Ol 5.4SE+Ol 4..93E+-01 4.liE+Ol 29EE+o1 2JNE +-Ol 3-4SE+m 4..93E.;-Ol 3-liE+ol 3.9JE+-Ol 55IE+Ol 4JIS4E+01 U iE+Ol 3.ZIEt-01 3..2'.lE+Ol 5.75E+-01 2'61E-+-01 3.0E+-01 3.35E+Ol 4J6IE+Ol 231E+ol 291E+-01 4.liE+-01 3.6iE+-Ol 33"-E+ol 4.49E+-Ol 5..59E+Ol 4..93E+-Ol 4.l 7E4-0l 3.0IE+ol 2.79E+-Ol 3.4BE+-Ol 4.&8E+Ol 3.17E+Ol 3.&3Bl-Ol 55 2E+Ol 4,62E+Ol 3..54E+Ol 3.B9E+Ol 3.10E+Ol 5.76E+Ol 2.68E+Ol 3.02:E-+-Ol 3.35B-Ol 4.151E+Ol 231E+<ll 292Bt-Ol 4.14E+-Ol 35 8E+Ol 3.68E4-0l +I-35 3E+<ll page 4 of s-.pLm_g Location B!-i 01 l.3E+<a2 +J-ll<E-l-01 OlA U!!Et-02 2.i EE+Ol 0"2 LOOE+<n..
  • 14!!E-t-Ol 03 U3Et-02 255E-t'Ol
}_19E+{Yl +!-
2. EE+Ol 05 UlE;-02:
402Elt-01 05A U llB!-00: + 2.4mt-Ol IS l.22B+ID: lll!E+Ol 07 IU!9E+ill + .3.l'.lE+Ol 21 LO'lE+ol + 35SE+Ol 22 9.61E+ol +. 25iE+Ol 23 8.46E+-Ol +. L9iE+Ol 24"" U 4E+Q2 2.4(£+-0l Sowpli.ll_g Locaticn B!-i 01 L42E+02 25EE-+<Ol OlA l.52E-+Ol +. 2.i <E+-01 02 U lE-+-02: + 291E+-Ol 03 ]. 7lE+-O:l: +!- lOIE+Ol 04 1.42El-02 + 26$1-0l 05 l.50E+<n +. 23!;E+Ol OSA l.49E+-Ot.2 2.IStE--01 IS Lm"E+m + 2 fE+.01 0 LiBE-n<ll +!- lOEE-+-01 21 l.50E-n<ll +. 2.4EE-+-Ol 22 L42E+m +~ 2.21E. 1 23 L4iEt-02 2.nE+-01 24.... '.l:.a5Et-02 +!- 1 tE+ol
  • ll.D id!!!irtifii!d in th! OD CM
    • CM.i!rol Station Table3-5 Airborne Particulate Gamma Spectra
[10 ~ pCilm>) C!-134" Q...13.. LliSE-+<00 < !1..468-0l U OE+OO < l.01-E+oo +J-IU3B-Ol < 8.15B-01 U IB-+<00 < l..>7Et00 L66E-+<OO < l.22B+OO 19i'B!"OO < L56E+OO 9.17E-Ol < Ll7E+OO L42E+OO < UEE+OO +. 9.32EOl < !.:26E+OO 1.26E+OO < L49E+<O L23E-+<OO < LC6E+oo LltSE+-00 < LOSE+(() L40E-+<OO < 9.@B-01 Cs-134* Cs-13
  • L23E+OO
< 8. 5B-Ol Ll9E+OO < L20E+OO l-26E+<OO < UOEtOO l.16B+OO < IJIEtOO 8...@B-01 < UlE+OO LllE+OO <.S3B-Ol L~ < 32B-Ol L29E+OO < UOE+OO 1.50E-+<OO < Ul!E;.00 Ll9E+OO < LCPE+<Xl l.GiE+OO < L02E+<Xl Ll3E+OO < UllE+OO l.33E+OO < LHIB+OO 44 Sr-&9 < 5.*6BE+<Xl < R 3E+OO < 5.71E+-OO < SZE+OO < 4..21!E+()() < 4.R3E+<XI < &J4E-+iXl < 15.. e oo < 4.65E!(() < 4.738+00 < 4. J!E+(X) < S.4~ < 4.R!E+OO Sr-90 < L93E-!OO < illE-!00 < 2R<E-+OO < 24g:;;;oo < 203Ei00 < 24:iE < 3.1~-!00 &l!E+OO < 255E+OO < L92E-+00 < LlnE+OO < 26!1E+OO < 21SfE-tOO page l of2 Quarter i Quarter2 l Table3-5 Airborne Particulate page Gamma Spectra 2 of2 [lO~ pC - m;l Sznpli.nr; Quarte.r 3 Locatim Be-Q..134* CB-131" 01 L22E-+{ll H2E+-Ol Ul!E+<O L2tE+OO CHA Ll iE+OO: + 1 TIE+-01 Ll.9E+OO 9'6$-01 02 Ll3E+oo: +!- lftE+Ol 939&-01 U tE-+00 03 l.54E!+-<12 HiE+-01 U EE+OO l42E+OO 04 l..liE+02 ~(.. 245E+-01 U 6E+OO .. OfE-01 05 l.6f!e;<l2 +!- ll!'iE+Ol U 6E+OO Li l!E-+00 0 5A 15.SE-+<D: 3.42E+Ol l..13E-+OO l5'iE.;00 06 Ll4E+c!2 '24!E+Ol l.53E-+OO USE..00 07 U 3E+oo 1 448+0} l.JSE+OO DllE+OO 21 LO'EE-+<00 15'iE+Ol 9.llSB-01 LOIE+OO 22 l.l<E+m 1348+01 L44Et00 U3Ei00 23 UiE+oo +,l. 1 4tE+Ol l.58Et<OO U5E+OO 24++ U i3E+<l2 +.I-HiE+ol Ll.5Er00 l31lE-tOO MBAN SznpHnr; ME.AN Quarte.r4 Loclltioo Be-Q..134* Q..131" Be-01 l-1$-02 +.I-lC<E+Ol 8..95E-01
9. m-01 l32E-f02
+/- 235E+Ol OlA L0(!&.-02 19:IB+ol Ui3E+OO lli:E-+00 U3B-!Cl +/- 1.~ 02 UID-02 +!- 29.!E+Ol L73E+OO l 71E-+OO 11:~-!01 +/- 1.14E+Ol 03 U~+oo llllE+Ol < 1.00E+OO l65E.;()() 145E-!-02 +/- 2.97Bl-Ol 04 l.Ol!E-+fil 22lE+Ol Ll8E+OO L24E.;00 124E-!-02 +/- 2.53E+Ol 05 l.15E+-02 +!- 1415+-0l 1.58E+OO LlfE-!-00 144E.;ol +/- 1.94E+Ol 05A L22E+-O'l +f-llllE+Ol 1.11:&.<Xl 14<Ei00 134E+O'l +/- 2@E+ol 06 1.048+01 +!- 12IB+Ol L47E+OO 144Ei00 12fE+()'l +/- 275E+Ol 07 L04E-l-02 19iE+Ol 1..26BKX> - lE-01 12fE-!-02 +l-2.Jl55E+Ol 21 L05E+<l2 +.I-2ll!E+01 1.34EKX> 11<E+OO ll~.;ol +/-
1. i&-01 22 9~1 10.iE+Ol l.95El'OO l 4E;00 lHE.;-02
+!- 1.1!lEl-01 23 lZE+al +!- 121E+Ol l.!l9E+OO l JE+OO L24E.;ol +!- 2a>E+Ol 24-l..lSE+al 2'.lm+Ol l.JSE+-00 U>;J!;OO 1528+()'2 +!- '2'.. /EEf-01 Jiitean cf All In.data locatim: l'.lm+al + 211E.;Gl " LID Idal1ified in ODCM
    • Coo!rol Station 45
Samp.le ~ I 9-89 Date Acivity Core 2 Sigma 7/12116 0 7/12116-02 7112116 ()3 7/12116 04 7112116* ()5 7112116 C5A 7112116 06 7/12116 ()7 7112/16 21 7112/16 22 7112116 23 7112116 2~ Sample station I C5-137 Date Acivity Core 2Sgma 7112116 ()1 7112116 02 4.59E+C2 +I-7112116 03 1.78E+o2 +I-7112116 04 1.77E+o2 +I-7112116 05
4. 4~E-*'02
+I-7112116 05A 7112116 06 6.<<!E+-02 +!- 7112116 07 7/12116 21 7112116 22 7112116 23 26!3E+-02 +I-7112116 2~ ~mol Statio I MOC Acivity Core 6.749<12 .5.38E+02 7.20902 6.5 58!-02 6.SOE+02 5.4SE+02 5.348+02 4.928t02 7.62E+02 6.42E+02 6.24E+02 3.96E+02 I MDC Acivity Core S.S:3Ei<l1 3.89E+o3 1.52Et112 1.08&02 9.70E+01 250E+o3 1.249-02 9.94E+01* 5.0SE-+03 1.408!-02 1.319'02
3. 4~+03 1.52&02 3.S2E+o3 1.13B-02 5.51E+o3 7.41E+01 24CE+o3 S.29E+01 Table 3-6 Sofl
![pOi/ lcg) S-9J 2Sjgma Ra-2213 2Sjgma -+I- +I- +I- -+!- +I- +I- +I-MOC 3.:368-01 2.00E!-01 4.06.E+01: 2.448<01 2.92E+<l1 2.70E+01 2.488-01 2.228-01 3.46E+01 3.028-01 4.1'0E+01* 2.25E+01 MOC 3.77E+03 3.21 E+03 1.71E+03 2.43E+03 2.10E+03 2.24E+03 2.518!-03 2.818!-03 2.27E+03 2..55E+03 1.57E+03 1.82E+03 46 I ~ I Acivity Co.re 2 Sigma MOC 1.60E'4-04 +/- 217Et<l3 S.73E+C3 +/- 221E+03 6.04E-+i03 +I-1.24E+03 4.00E-+03 +/- 1.29E+03 1.10E'4-04 +I-1.93Ef(l3 1.41E+<04 +/- 1.S8Ef(l3 1.0SE"l-04 +I-1.56903 1.:22E+C4 +I-1.63.8+03 1.08E-+ill4 +I-220903 1.00E+04 +I-232903 3.24E+<04 +/- 26281()3 3.0ee+o4 +/- 24381()3 I Th-228 I Acivity Cone 2 Sigma MOC 9.:24E+C2 +I-1.55Bt-02 5.0.3E+C2 +/- 205E+02 6.30E+-02 +I-1.24Et<J2 6.4e8-02 +I-280Etill2 4.S7E+C2 +I-1.44E't02 3.:3eE+03 +l-205.Etill2 7.91E+C2 +I-2108!-02 257E+o3 +/- 2088!-02 290E+-03 +I-3.03E+(]2 3.6~+()3 +/- 246E+o2 1.62E+o3 +I- ,..54'6t02 209E+o2 +I-1:.236t02 Cs-134 Acivity Cone 2Sigma ~232 Acivity Co.re 2Sigma S.S2E+02
  • +I-5.1~
-ti-7.31 E+o2 Tl-3.4<f!E+03 c+f-9.0.0E+02 +f-24eE+o3 -+I-249E+03 +I-
3. 11E+03
+I-1.41E+03 c+f-page 1 of 1 MOC 6.91E+01 S.91.E+01 7.94E+01 8.88E+O 7.45E-+(11 8.75E+Cl1 1.-42E+C2 9.35E+01 1.039<02 9.23E+<l 9.1'8E+01 7.61E+0*1 MOC 2.88E+02 7.998'-02 3.00E+0.2 5.31E+02 3.10E+0:2 3..559<0:2 1.!99E+02 2.778-02 4.418-02 4.04E+02 2.009-02 4.04902 Table3-7 Precipitation Gross Bet!. [pCitL] page t.of2 S<ampl:il!g D~ Gross Beu I H-3 I Ra i.!iall ( UI:h!s)
01..... 7l16 U SE+oo 9.164E+o2 192 O"~l *6
3. 4f:+OO
. OE+oo S.S5E+o2 3.46 03/29.11*6 269E+oo 1.00E+oo 9.47E+o2 2.89 04/26.116
  • 6.21E+o0 111.E+oo 9.47E+o2 l.26 05/31116
.97H OO 1.<>>E+oo 9.25E+o2 S.42 06/2&116 U7E+oo S34E+o2 551 0 ~6116 4JOE+oo O.OOE+oo O.OOE+oo 4.60 0 30.116 4.9SE+oo O.OOE+oo O.OOE+oo 535 09128.116 L93E+oo O.OOE+oo O.OOE+oo 4J4 10/25116 L90E+oo O.OOE+oo O.OOE+oo 4.69 1129116 6.&3E+oo O.OOE+oo O.OOE+oo l.75 1212 116 6.17E+oo O.OOE+oo O.OOE+oo 292 Man 4.0U:+oo 4.47E-01 4.59E+o2 To!al 47.5 47 Table 3-7 Precipitation p.l~i! Gamma Spectra
2of2
[pCi/L] SBi:;lill:g I l<<alioo ~ !.{fi.54 ~~ Co-5& Co-@ OL>\\ 0628116 5.lllE-+-01 ~- 3.548-!-0l l6iE+<O L44Bl-O] 3..95E.;oo l.4!E+OO 12.z IS 2.448-!fil -'i'IB-01 ,('iEE!+f.O l71!E+OO .l!J.B-0] I Zn-a> Zr-9.> Nt>95 I C~l!34 I Q-I37 OU 6'281ll5 3..£2E..00 7.se<O 4.54E+OO L4JE+OO B lE+OO 12 !'Hi l.EE+OO 3.4JEtoOO 10'18+00 ~71E01 .008-01 I Ih-141> La-1411 I I-m I Th-228 I ii.A 6WJ.6 1.l tE+!l3
i. liE+<<t 15JE+04
)J(lE.;oo +. 3.61E+oo l lf.nt!IS 9.i5E-t-02 191El+OO: ILOIE+04 l.3 1E.;.()() ME.irn San~g l<<ali!M! Bo!-~ ~54* ~j9" Co-5&"' Co-6'.l" A Zn-IS5* Zr-95* N1>95* Cs-L'.l4* Cs-13
  • OU Ba-140"'
U.t411* I-131* Th-12.& I OL>\\ 5.31E+OO .;.,'-i&IE+OO
  • Nl m ~..,,~lw;;..l\\11 r~;JJ! t; W!!I!! <l.l!l>\\
48 Table3-8
Milk pa,g~
Gamma Spectra & Strontium l ofl [pCi/L] S!!!llpli!!g Station 12A Dal! K-40 Sf"-119 ~-90 I-13 1
  • Cs-134*
C~l3
  • Bl-140*
Ll-140" 01119116 l.40E+03 +. 6.73E+Ol '[*) {*] 8.14E+Ol < 2J4E,i.()0
2. lE+OO l.23E+Ol
< 3.61E.;-OO 02 l 116 l J3E-+-03 +, l.49E+o2 [a) [a] . 2E--Ol 5Jl52E'l-OO .69B+OO 3D7E-+-O l < 8. 5E-+-OO 03115 116 l.27E-+-03 +,L l.69E+02 O.OOE.;-00 O.OOE+OO 4.53E--Ol 8.1 3E.;-OO 8.915E+Oll 3.20E+O l < l.49E+O l 04120116 l.22E+03 +, 2D7E+02 [a) 1*) 4.16E--Ol . 9E+OO l.07E+Ol 4.&lE-.O t < 8.6SE+OO 0511 116 l.40E+03 +,<!. I J3E+02 fa] (*] 4.00E--01 5.76E-r<OO 6.ZOE+OO
2. 3E+O l
< 9.29E+OO 015.1211115 l.46E+03 +.~ 2J9E...-OZ 4.415E...OO l.09E...00 .22E-Ol 557E.;-00
  • l5.60B-+OO
< 3.42E+O l < 1J4E+Ol 0 ! l 9 t ]6 l.46E+03 +.<- l :l5!ra...-OZ 1[11) ,[;11] 3.19E--Ol .20E.;i-OO 6.53E-+OO 2.49E+O l < 550E+OO 08!1 /]6 l.43E-+-03 + l.63E+02 {11) {a) 5.33E-Ol J5E+OO 8.llE+OO 2.6 1E+O t J8E+OO OP/ZO.fl6 1J2E-+-03 +,L l.7.&E+02 4.31E+o0 tJ.SE-!!00
6. 73E-Ol
+I-9SE+OO l.l4E-+Ol 4.63E+0] < 1D6E-+Ol 1 l.9f!.15 l.44E-+-03 + 119E+02 .[a) l*J. 5.61E-Ol 4.24E+OO 5.35E+OO 2.44E+Ol
6. 9E+OO 11115!]6 t39E-+()3
+J!. 2.06E+(t2 (:1) {*] 8.49E-Ol .70E+OO
8. lE+OO 3.l OlHOI B.84B+OO 1212lO!l6 13 5E-ril3
+,t. 1.83B+02 4.35E"!OO l.49E+OO 6.B'iE-01 .46E+OO 8.53B-+-OO 3J66E-+-O I < 85 1E-+OO St1. Me11111 13 7E.,f()3 +,L l.65E"'l-02 "U.O identifiY i.lll ODCM 49 Table3-9 Food and Vegetation Gamma Spectra page [pCitkg) l of2 Sa~Li:ng San-.,Pling Lcm rtioo &!-7 K-40 I-131
  • Cs-134*
C&-137" 13 6 l.45E+03 +I-
l. ilE-+02 554E-t03
< 3. '9E'!O l < l.96E+Ol <.... OlE+Ol 14B l.44E-+-03 +I-3. 6E-+02 i.41E-T!l3 +.I-Al3E-+(!fl < l.IOE-1{)1 < 333E+Ol < 3.BlE-+-01 9.20E-+02 +I-3.07E-l-02 5.89E-il[)3 - 1 l 6E-fi0'2 < 5.4 E'+O l < 3.:2'.2E+Ol < 3.43E-+-01 01/12 115 2.1 E-+(13 +I-4.1ll!E-l-02 5J4E.;03 156E-+02 < 2.1!5E-i01 < 3.69E-+-Ol < 3.. 1!5E+Ol Ol!I09116 J OE.;-02 +l-435E-+02 457E.;{13 +.I-l!.91E+o2 < 2:20E-i!O] < 4.45E+Ol < 4.Jl!E+Ol 09.114,'16
4. 3E-+02 +l-237E-+(!f2 659E-I03..,._ 92E-+0'.2
< 2. U -IO l < 3.44E-l-Ol < 3.66E-+-Ol l 11/16 l.61E-+03 +l-3.16E ' 2
4. SE.o;OJ
+.'- 5.67E+O... < l.SOE-!-0 1 < 2.2..'E+Ol .55E-+-01 11110. 6 119E"l-02 +l-2. SE-+O'l 4J6E.;03 +*.- 3.i4E+Ol < 2J5E40 1 < 2.41E+Ol < 2.62E+Ol
Mean l ME..t-03 +!-
3.11 E'I02 556E..03 6.46E"l-0'2 +!- +!- +.I-Sa~Liftg Sampli1!ig Loc:atm D*t~ K-40 I-Bl* Cs-134" C&-13
  • 15 04.113 6 8i66E-+<ltl
+l-l.54E-+<02 6!69B-!03 +.I, - 3.48E+Ol < 3.6JE-i01 < l.55E-o-Ol < l.64E+Ol 05tl0116 2SlE+oJ +/- H 9E-+I02 6.70E-f03 - 654E+Ol < lJSE.;O l < 3.28E-o-Ol < 3.65E+Ol 015.>'14 6 9ME-+itl +I-2.04E-+<02 .15E-!-03 5.07E+Ol < 4.62E-<i-O] < 2.05E+Ol < 2.36E+Ol 0 112 6 2.03E-f-03 - 4.64E+02 5.02E-i<l3 JlE+O.... < 2JBE-!O l < 3.4lE+Ol < 3.l2E+Ol (lrlt.1@116 l.07E-f-03 +.I-43SE-+(!f2 4.0lE"ll{IJ - 6. 9E+O.- < 2.91!E-!O l < 4.23ET01 < 3.IWE+Ol
114 6 3.1°6E+()3 +'- 3.62E-+O'l 2.94E-i<l3.- 519E"'l-O:..
< 21 5E-!O l < 2.94E+Ol < 3. E-+-01 1 11 6 316E-+-03 +I-4. 2E+Ct2 5.28E'I03 *- 6.40E+Ol < U l E-IO l < 2.76E+Ol < 3.41E+Ol llfl0/16 3.16E..t-03 +/- U lE'4-02 5,Bl!E-!03 +.'.- 3.65E.,;,(t2 < 2.19E-i01 < l.Tira+ol < U4E+Ol Mean 211E+03 +I-324E4i00: 5.46E-!03 +.'- 5.55E4-02 +!- +t- +.I-5'11JJ>lmg Sa.mp ling Lot1tioo Datt Bt-K-40 I-131" Cs-134" C&-137* M.. 111E+03 +I-2.0l!E+02 599E-'1{13..,._ 3.61E+-02 < 3.2'.2E-!-O l < l.1!4E+Ol < l.87E-+Ol l.40E+o3 +!- 2.95B-+02 3.S2E-!-03 +.I-5J~ISET02 < lJSE-IO l < JJlE-+-01 < 3.61SE+Ol l.66E+03 +I-1.99E+02 8J6E-i03 +.I-4'6JE+02 < 3J E-!() I < L l!E+Ol < l.90B+Ol l.JOE+03 +I-3.45E.+02 3.46E-!03 - 5.1!5E+o2 < 2.95E4-0 l < 2.ltiE+Ol < 3.14E-+-Ol l.20B+03 +I-5.60E.+02 3.76E-li03 +.I-BJSE-702 < l.1!6E4-0 l < 4.51E.;-Ol < -.14E+Ol l.06E+03 +l-3..SlE-+02 4.72E.;{13 +.I-6.l l!E'!Cl < l.99E-!O l < 3.02E+Ol < 2_91E+<ll 2 Jl!E'!-03 +/- 3.9"...B+ol 3S7E'IQ3 +.I-5.44E'!Cl < l.4BE"'9 1 < 2. 5E+Ol < 2.iOE+<ll l.40E+o3 +I-U 5E+ol 4.90E.o;03.- 4.25E-+Ol < l57E-T01 < 2.33B+Ol < 2.4]E+Ol l.49E-+<03 +!- 3.17E-!02 4.l!l:E-ii03 +.I-5.53E+02 +I- +I-
  • LID i.62mifi~ in ODCM
.... Comm! Stltioo 50 'Samlp~ S2m-;p'lil!lg Locatm Dae<! I Be-1 I K-40 23 04113116 l.55R-ilill:l +,<. 235R;tfil 697E+m ~ 05'110/16 I. iiE-i-03 +,I-J.5e:+m 511E+ID +.<- OD/14.t16 l..24ET03 +,<.
l. B4E-+-02 710Bi03
~ 071121115 BfE.;-OJ +..:... 3.. 9iE-+<<! 439H'+m 0&@/16 Lm-+m +.'- 3.9fE-+O'l 4.ni:;+-03 +.<- 09114/l !S 6.71E-il-O? +,l. 271E+m 593!!'+03 +,:. lM ltl lS 4.4!!E+m +I-4.83E+m 3.05E*m ~ ll110/l iS
5. i~-il-0?
+$- L91JE+a:l 554B:l-03 +,:. ~~n l.81E+03 +,<. J.14E-+02 52:9B'I03 +.<. Simp,lil!; S'arrllJ'ling Locm:icm D.V-I Be-7 I K-40 26 04113116 6.53E..;<<l +,I-1.71£-i& 5.6:2:B+IOO 051l0/11S l.OJE-ilill:l +I-25!E-+02 511ETm ~ 06.114/16 5.33E+02 +I-274E+m 6.00~ +..<- 07112111)
1. 7!!ET03
+i-2~-+-02 7.00:&!03 -+.'- 0!1.119/16
1. 741!:.;.(E
+.<:.. 5.Sl!E-i& 4.7JE+ffi -+.'- 09.114.lliS l.66H-TID +l-J.OlE-+'02 5.46"Bil<IB ~ 10/l l/liS 21!!lE-TID +,"- 4.91E.;.(l? 3.OOl!ifiOO +.!- H llOtllS .UJE+m +l-2.0IJB,;;(12 J.81ETm ~ i\\tin l.43Eil-03 +I-3.1.1!8+02 5.20H+IOO Indica!Dr locations l.65E+03 +J!. 3.liE+G:!: 53RB'+ffi .. LID :id!!m:ifi~ :in ODCM Table3-9 Food and Vegetation Gamma Spectra [pCilkg] I I-13 1" 531E""°2 6.20E.;;02 3.&0E'l!{)2 6.l2E""°2 6.i"iE,+02 6911E"'6l 625E""62 457B"'6l 5.15E~ + _,:. I I-131+ 3 !ISllE'!O"l 5.77B""62 752E.;!(t2 5.2JE'l!{)2 U 3E-i!03 5.47E-i!Ol 6.111E-i!02: 3.i9E..+02 '6.12E+ll2 +I-597E.;G2 + J!. 51 I Cs-134" 4.49E'!Ol l.&8E'l-Oll 4!11E'!Ol 2.SlE.;(11 2.4DE"ll01 252E+ol L83E'I01 2.70Eil01 +l-I Cs-134.. 332E'l()l U OE-l-01 495E.,;01 J.OlE-i!Ol 1.87E-10l 3.BlE..01 1.00E-i!Ol 2.49E-+01 +I- + J!. I Cs-137" 23JE..;i] 321E-ii01 l.7:8E.;(ll 326E-401 398E-l01 J.08E-!01 332E-!Ol 2.05E...01 +. I C&-137" L88E...Ol J.lOE.,+01 2.61E..01 230E'IO] 5.&fil!-T.0] J.06E-i0] J.44E'!Ol Ll!4E-!Ol +.~ +.I.. 2.46E'11(1l J.64E'!Ol lJ!PE.;ol 3.45E-+0] 3.56B"llOl 3.17B"'IO] 3.4PE.,+0] 2.UE-i!O] 2.0:i-"E-i!Ol 3.liSE"\\IG] J.OOE-!01 2.A54E.,;ol 'iS.9.lE...01 J.:25E'!Ol 3.41SE-+0] 2..23E+!I] I I page 2of2 Siall'...plilllg Da~ 0312'!1116 015!2&116 @!2&116 12/27116 M!!a Sillmpli:f:lg Dat'.!! 03129116 0512&/16 0012&11,15 l21Z71l6 M~an H-3 Sr-&9 1.915E+03 [* ) l.04E-+-03 9.23E'l-02 I*I 8.J5E-+0"2 [a) Zc-95 I Nb-:95 7.67E400
6. 78E'li!IO 8.32E-il-OO
'!U5E.;-OO l[a) St-&'9,9 0 lllllll1}-s!S p!!lfo:lm!!don th! ~rood quarta-sa.1T,PI!!. TabJe3-10 Vlell Water Gamma Spectra. Strontium. and Tritium [pCi>'LJ I Sr-90 I Mt-54 I Fe-59 (*) 3.7iE+OO 8.46E+oo 3.4 iE+oo 5.92.E-Ol 4..95E+OO 6.23E-+OO {*) 5.44E+oo l.06E-+ill {a) 4.34E-l-OO !U7E-l-OO I I-131 I Cs-134 I Cs-137 4.77E+oo 6.46E--OI 4.71E-i-OO 4.44E+OO 4.61E-+OO 5.57E-Ol 5.32E"IOO 499E+OO 6J9E+oo 8..26E--Ol 5.20E+OO 5.03E+OO 5.HlE+OO 7.74E-Ol 5.JBE-!-00 490E+oo 52 page 1 of l Staticm OL4. I Co-5& Co~OO I Zn-65 4J5E+OO 4.72E-+OO 8.37E-+00 25 0E+OO 4.68E+oo 7.94E+OO 5.48E+OO 5.54E+oo l.OiE+Ol 5.1 2E+OO 4.JBE-+00 l.09E+Ol I Ba-140 I La-140 2.00E.;-Ol 6.1?15E-+OO 3.OlE-+01 9.J5E+oo 2.65E.;-01 l.OOE+-01 .2.l 7E-!-Ol 6.73E+oo Table*3-11 River Water page GammaSpectra, Strontium, and Tritium 1 of 1 fpOJL] Safr1Jling station 11 oa:e H-:3 Sr-89 Sr-00 Mn-54* Fe-59"
  • Cl>-58" C C>6l" zrres*
1.1 1112116 fa] ll!JJ UOE+<JO 1.11E+<J1 4 ~t8f't-O O 5.8'E+<JO 1..011E+<J1 02!1Ei/16 a] ll!JJ 3.!UE+<IO &.70E+o:J J..8,(IE+<JO (.28£+<10 .11E+o:J (JJ.f1.(f1 6 4.16'f+(J3 +f-1.11Ei!!l3 ll!JJ 5.95E't-OO 1.1fif+(l1 5.10E+<l0 .06E+<JO 1.11E+<J1 (J.(,f12/'1 6 fa] ll!JJ 1.nE.+<iCJ J.361:+00 1.65E't-OO 1.72E+<JO J Af.EtOO OS16!16 131 lllJ (.. 24e+<JO 1..0.C:.E+(J1 5..07E+<l 5.Z6E+<JO 9.1 (.E+o:J 06.f13J16
  • 4.23E+<J3
+,!- 8..(7Ei02
  • U3E+o:J 7A7E--01
.(..6(E+<JO &.5BE+o:J 4..03E-+<ll0 .U:4E+<l0 1..0SE+Q1 07f11t16 3] lllJ U iO'E+<JO 1..0.C:.E+-01 U4E+<JO U5E+QO 11.ME+oo Ol!.*15116 (a] lllJ
  • (.::9E+<JO 9.7 1E+o:J 4.23E+<JCJ 5.S!Jf'+(l(J 9.a;;lE +o:J 09.f12f1 6 3.J.C.E+QJ
+,f-7.SB!E+.'.12 ll!JJ U 3E+<IO &.J 1E-t!OO 4.19E+<IO .(.f.Eif +(J(J 7.fi6f'+oo 10f1(1,116 fa] ll!JJ
3. 1JE.+QO 6.98E+oa 3.22E-+-OO 3.21E+<IO 6.19E+o:J 11114116 131 ll!JJ U 6E'i-OO
&.66f'+o:l U2E+<JO (.73E+<JO 1..07E+<J1 12ft2f16 3.97JE+(J3 +,!- 7.91Ei02 lllJ .(..52E-t<JO 9.98E+o:J 5.51E.+-00 4.64E+<JO 1.00E+Q1 11.ei'iN 3.93E+<J3 +t-lt&(IEfl!l2 +,<- +.<* +.<- +/'.- +,t.. +.r-Saf"lllling oa:e ' b-S6* Zr-9" l-13t* Cs-1:34* 0;-137" Ba.-140* 1...a.-1.40* 01112'1{1
  • < 9.oseoo
5. 45E+OO
< 6.3...'iE..()1 4.638-00 ,5_,54E-.!OO 278E!{)1 < 5.42900* (12)'16'16 < 7.:00E+OO < 4.10E-'I{)() < 5.4!lE..01 < 3.9fi&OO 4.e8E+OO < 207801 < 6.4EBOO 03114116 1.1'28-01 < 6.64E+O!l' < 3."?JE-01. 5.18E+OO 6.10E-.!OO 2.35&01. 5.08900 04112'16 < :3.02900
1. 70E-il00 5.07E..()1 1.57E+OO 1.71E;()!)
< 8.63800 2.648t00 05'13'16 < 8.7UE+OO
5. t2.E;{K) 5.10E-01 4.51900 4.1:.2E +OO 2.4~1
< 8.3281-00 0013116 < 8.20900 < 5.68E +OO < 7,34E..()1 < :3.96E+OO < 4.:3.EE-i!OO < 214B01 < 5.90900 0711'1'116 .., 8.178 -00 < 4.92E +OO < 3.99E..()1 < 4.048-00 < 4.81E-100* < 2 51E!{)1 < 8.8181-00 OS/15'16 7.938-00 < 4.83E +OO 5.49E..01 < 3.39E+OO < 5.ffSE-+00 < 220E!{)1 5.9281-00 09'12'16 < 7.01E!-OO 4.61E-t00 < 524E..()1 < :3.SEE+OO < :3.82E..,i{)() 2.41Bli!l < 8.80900 10*'1tll16 <.5. 7!l81-001
3.22E401)>
3 ;~.01: 3.07B-00 < :3.42E-t00 1i.6SE!{)1 5.828t-Oll '11/ 14116 8.00B-001 6.3fE +OO < 4 34E..()1 < 4.038-00 5.12E+OD 2.1~1. < 6.938-00 12'12'16 1.038i01 < 5.87E40IJ < 4.00E--01 5.t 2E+OO <.5.a.e800 212801 8.298-00 MEAN ~'* +I-41- +I- +/.. +f..
  • LLD id'entifia:I i OOOM
[ Ti i1iumanalyses on ua1sly ccmpcs ite. (bl Sr-S9'SO ?frlCJ"med amually on2"' arter ccmpcs ite sample. 53 r I ~ i; ~ Q rt: ~ ~ 0 ~ ~ ~ a 0
r....
~ 0 Q Q: ~ ~ ~ 0 f ~ e* t;: ~ ~ F' ~ ~
  • t It
~ !-! !:;;... ~ ;; i; ~ ~ It ~... ~ ;:; - ~ ~ t ,t; F' rt' B ,t; ~ t...
..
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8.
~ c t: ~ I;., iil ~ t4 j;j ~ ~ il; ~ ~ + ~
t + ~~ + :E
+ ~~ t :E E ~ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ ~ ~
E I!! ~ ~ !: e "' "'... p. i"
~ ~ r:; ~ ~ ~ M fl1 ~ ~ ~ m ~ til ~ iii 15 l:l § 8 8 8 8 8 8 8 8 8 8 3 s s s s s s i ~ fj ~ 1 3 t -~ ~ t :!!: :2 ~ ~~ ~ ~~ ~~~... /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ .ti /\\ ~ ~ ,.. e: ~ ... i ~ ~ r* ~ l>' I:. fl ~ ~ r::i l"1 ~ J* I'! I'! 8 8 8 8 8 s 8 8 8 8 8 3 8 /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\
  • t :!!: ~~ :2: 'il' :2:
/\\ :2: 'il' ~~ ::i!: (:;) ~ p..J i,..,.. p.,.....,..,.. ~ ~ ~ ~ iii ! ~ la ~ ~ ~ ~
a
~ ~ b g b g
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~ ~ tr.I 'O (/l 0 lo ~ .~ ~~ ~ n B ;- J! r.n /\\ /\\ *,t /\\ /\\ {\\ /\\ /\\ /\\ /\\ /\\ /\\ 0 ~ /\\ /\\ {\\ /\\ /\\ /\\ /\\ /\\ /\\ {\\ /\\ /\\,,. ~ g ~ 'f (JI ~ ~ If
  • t
~ fl! ~ ~ 8 c "' ~ ~...... c t* !",.. c. ~ ~,.. i" c c... c ~ :-" ~ ~ er. - ~ !.1 ~ 1-.o .~ ~ i ~ ~ ~ ~ ~ ~ fl1 Iii @ ~ Iii t;I ~ tll ~ tJ ~ ~ ~ ;;; t;J ~ t t i!; t t 3 il; t ii; i!; ;!; il; t ii; <!; ;!; 3 0 0 0 0 0 0 0 0 0 0.. 0 0 0 0 0 0 0 0.. 0 0 1-3
i.
j CT. + /\\ {\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ {\\ /\\ + /\\ /\\ /\\ {\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ /\\ c 9 0 fj ~ ~ ~ ~ ~ t: t: l:. t* b... t: t:
I"' e,,. ig,, r:;
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  • ~
Table3-13 Sediment Silt Gamma Spectra, and Strontium [pCilK:g] p!ge Sam~ ld l Oat! Sr..&9 Sr-'00 K-4!l CS-134* Cs-13 ~ I 4121. 16 Stali.m 08 . a] a) 1..ll!E+03 42BE+02 3.048+-0l 288E+ol Stalim.A.. [a) (a) 2.lSE-i-04 U S3E+<E 5.l!E-+01
  • Q 13E+ol Stalim ll
{a) [a) l.4<E+o4 1.]gE-!-03 5.6EE+Dl .84B+ol Ra-226 I Tl!-2:28 I T!i-232 I ,154E-fC2 6.71E+a2 Ll1E+02 +.I-4.45E+ol LSE+<l'.2 'Stalim.A..
1. t!E+<l.3
+!- 9.iOE-+-02 '~ l.05B+a2 &45E-+<()l U IB+<l'.2 Sta1im 11 l..29E+03 4..2!6E+fil l.13E+Ol iliE-+-02 l ~-+-01
  • Sam~>!
Tu<<! Sr-&9 Sr-90 K-40 c-..134* Cs-13~ 1M l!12<l1*6 Stalim OS U E+-02 3..3/E+-01 Li'2E+03 +!- 4.&E+-0'2 4.C2E+<ll 130E+<ll 'Stalim ~~.. 201E+-02 .15IB+ol 1.3 t!E-i-04 +!- L44E-!-03 8.J3B+Ol Ql3E+<ll Stalim 11 L83E+OO: 1 71E-+-01 2.lEE-i-04 +, l..25B+-03 6.3<JE+ol i 96B+-Ol Ra-226 I Th-2:28 I T!i-'lli I . 3E+o2 + S... i!i3E+02 &.l 7E+Ol +f-6.15E+ol LOOE+ol lliE+0.3 +. &.51ETOO 5 3E+-02 +l-USE -+<00 i91E+02 +!- l~+<l'.2 2.13E-+03 +.<- &.l!6E+m 7.79E+Ol l.32E+02 iOOE+-02 +!- USE-+-02 MEAN Sr~
Sr-00 I
C.s-134* Cs-13~ uni:: am +!- +. 8,84E+G2 + Catlrd +.I- +, 1.54E-!-03 + Ra-2215 I Th-2:28 Th-232 !mkalD! l..2:2E+<l3 8.93E+-Ol 3.50B+02 &.7EE-+Ol i 13E+02 +. l42E+02 Cattrd 1.52E+03 +f..
9. E+02 8.61&0'2 U SE-+-0'.2
.l s:E-+-02 + l 75E-t-Ol
  • IlD icE!lif'ed i110DCl.{
.. Cattrol Sia1ion 1[a] s~-89/90 ama'i:y;.e; p!lfamed anruall;: 56 Sllmpl!! Date Sr-&9 4121 16 Sbltic OB [a) Slfi!.ipl!! Oat~ Sr-&9 ]OiH /20] 6 Static OB 2D2E+02 S~-&9 +I-
  • LID i.demtifiM ill ODCM (a) s,.-. 89!90 :amtym p!fi<<imd 2!ll!IU!lly.
Table3-14 Shoreline Soil Gamma Spectra,.and Strontium [pCiJKg] &-90 K-40 (a] 53lE-+0"2 +'.- 4.00E-+02 R.'11-226 8.49E+-02 S!"-90 K-40 4.26E-+Ol 1.0811:-t-03 +.~ 6.31E+02 R.'11-226 9.88E+OZ MEAN Sr-90 K-40 +J.. .S.06E+o2 +I-5.?6E-t-02 R.'11-226 +**.- 57 page 1 of ] C~B4" c~u 1* 3.4&E-l-Ol 3.i'6E,i01 Th-228 Th-2J2 6.79E+Ol l.IUE'I02 C~l34" C~l3 7 *
4. 5E-l-Ol 4.90E-<!Ol Th-228 Th-232 91155E+o]
2.0JE-'!02 C~l34" Cs-13 * +.11.. Th-228 Th-232 +!- Sampfuig Dat!! 1SY16 .0'1~16 b:npl.ing Dat!! 1~16 10'1~'16 b:npl.ing Daf!! 04!1~ 16 10'1~16 Sampl.ing Daf!! I I I K-40 U2E+o3 +I-5.SSIH-02 1.74E+o3 +I-535E-l-Ol K-40 t 44E+o3 +!- 2.89E+o'l U1E+o3 +I-6.1SE+o'l K40 200E+o3 +I'- 6.43E-l-Ol l.75E+o3 +I-8.C6E+02 K40 04! 1~16 H4E+o3 +,L 8.03E+02 10'1~1*6 l..4CE+o3 +I-8.17E-l-02 Mam L75&0.3 +I-6.45B+-02 Imiakir L75B-l-03 +I-6.43BT-02 Cccfrcl L62Et03 +I-6.4IBT-O'l
  • UD idenfified in OOCiv1
    • Controls b:fioo.
[~JNon-bctfumdwelling species Ofgamefish. [.'b] Botmm dv:eD.ing $pecl!!!I of iah. I I I Table3-15 Fish Gamma Spectra [pCi1Kg} Mn-54* I Fe-59* I C<>-58* 4.42E+ol < 1.248+02 < 5S7Bf-Ol 3.48E+ol < S..59E+ol < 296E-:-01 l\\iJn-54* I Fe-59* I C<>-58* 2.laE-i-01 < 5.0t'iEi-01 < 2.41Bi-Ol 4.49E+ol < 7.23E+Ol < 4.82E+Ol Mn-54* I Fe-59* I C<>-58* 4.97.E:+ol < 1.04E+o2 < 453B+Ol 5.19E+ol < l.OSBl-02 < 6J C!Et-01 Mn-54* I Fe-59* I C<>-58* 5.42E+ol < L29B+-02 < 5.65El-Ol 6.76Ei-Ol l.448+02 < 7.49ET01 58 page l of 1 F1'3h [~] Stafion OS I Co-©* I Zn-65* I c~-134* I C!!-l37* < 53U!:+ol 92.2E.;-01 5.6JE+ol 5..tS5E+Ol 3.93E+o1 7 j'JE.;-01 3.95E+ol < 4.148-l-Ol Sb.fion 25** I Co-©* I Zn-65* I Cs-134* I Cs-137* < 2<bl!+ol 4.7SE-t01 < 200E+ol 2!2E+Ol < 3.77E+ol U <E-+02 < 4.74E+ol 6.HB-l-01 cafith lDl SbfionOS I Co-©* I Zn-65* I C:1-l34* I C!i-137* < 4.84E+ol 6.07E.;-Ol 3.84E+ol < 5.6SE+Ol < 3.63E+ol 659E.;-01 5.S(E+ol < 537&-0l Sta:lion 25** I Co-@* I Zn-65* I Cs-134* I C!i-137* < 4.9'7E+ol 9.7U!:.;-Ol < 4"66E+ol 5..5SE+Ol 733E+ol L73E-+02 7.laE+Ol 7.S9E+O DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2016 and tabulated in Section 3, are discussed below. Except for TLDs, Teledyne Brown Engineering analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the TBE 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 environmental samples are performed. The results of the Inter laboratory Comparison Programs are provided in Appendix B. The predominant radioactivity detected throughout 2016 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, Th-228 and Th-232 were detected in numerous samples. Th-228 & Th-232 results were variable and are generally at levels higher than plant related radionuclides. The following is a discussion and summary of the results of the environmental measurements taken during the 2016 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, fa llout 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 the 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 CaS04: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 9.0 8.0 7.0 6.0 5.0 4.0 3.0 2.0 1.0 Sector TLD's 0.0 00 0 N 00 0 N 00 0 N 00 0 00 00 a;> 9 9 0 0 0 .-1 .-1 .-1 .-1 .-1 N I C: C: C: C: C: I I I I I C: ~ c c c c c c c c c c ~ ~ ~ ~ ~ I'll I'll I'll I'll I'll I'll I'll I'll I'll I'll ~ Figure 4-1 TLD (mrem/Standard Month) 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 these 32 sector TLD locations (two badges at each location) was 4.1 mR/standard month with a range of 1.0 to 8.1 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61. This value was 7.0 mR/standard month. This location is on site on the north gate of the construction side laydown area. Quarterly and annual TLDs are also located at twelve environmental air sampling stations. For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3.2 mR/standard month with a range of 0.8 to 6.0 mR/standard month. The average annual reading for these locations was 2.8 mR/standard month with a range from 1.7 to 4.7 mR/standard month. The control location showed a quarterly average of 3.2 mR/standard month with a range of 1.9 to 4.3 mR/standard month. Its annual reading was 2.5 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.2 mR/standard month with EPSP-9/10 having the highest quarterly average of 7.7 mR/standard month. Eight other TLDs, designated C-1 thru C-8, which were pre-operational controls, were collected quarterly from four locations. Stations C-3/4 and C-7 /8 are designated controls. These had a quarterly average of 3.2 mR/ standard month, while Station C-1/2 and C-5/6 had a quarterly average of 2.4 mR/standard month with a range of 1.1 to 4.6 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month. 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. The drop indicated in 2009 may be a function of a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this is in fact the case. 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 60 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 of0.005 pCi/m3 to a high of0.75 pCi/m3. 0.12 0.1 E 0.08
i 0.06
(.) 0 0.04
a.
0.02 0 2.SOE-02 2.00E-02 l.SOE-02 l.OOE-02 5.00E-03 0.00E+OO co Ol C> N <<) ~ l[) CD,._ co Ol C> ~ N <<) ~ l[) CD,._ co Ol C> N <<) co co Ol Ol Ol Ol Ol Ol Ol Ol Ol C> C> C> C> C> C> C> C> C> C> ~ ~ ~ C:: C:: C:: C:: C:: C:: I C:: I I I C:: I I I I I C:: I I C:: I I C:: I C:: c c c c c c c c c c c c c c ro ro (1) ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro ro -- c ontrol Sta. 24 -- Indicator Average Pre-Op -- Required LLD Figure 4-2 Historical Gross Beta in Air Particulates NNrnrnrnrnrnrnrnqqqqqqqq~~~~~~~~~~~~~~~~ MMMMMMMMMMMMMMMMMMMMMMMMMMrlMMMMMM I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I U~~~~§~U6~~~§3~6~~~~3~U~;~~§~U~~~ oo~22 ~ ~0z~2~~~~zo~~2~~00~22~~0z~2 -+-Control Indicator Figure 4-3 2016 Gross Beta in Air Particulates (pCi!m 3) 61 ~ l[) ~ ~ C:: C:: ro ro 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. 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 and the effect of the Fukushima Daiichi event. 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 spectroscopy. 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. The results of these analyses indicate the lack of station effects on the environment. 4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations. There has been no detection of these fission products at any of the indicator or control stations in recent years. 4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2016. Cs-137 was identified in 6 of 11 indicator samples. The average for indicator stations was 362 pCi/Kg. No plant related isotopes were identified in the sample from the control station. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout. No other plant related isotopes were identified in Soil samples during 2016.
4. 7 Precipitation A sample of rain water was collected monthly at on-site station OlA and analyzed for gross beta activity and H-3. The results are presented in Table 3-7. Twelve precipitation samples were obtained in 2016. Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements. No plant related isotopes were reported in any precipitation water sample at the indicator location.
Naturally occurring gamma emitting radioisotopes were detected. No positive H-3 result was reported. 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 cannot be made to the 2016 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. 62 4.8 CowMilk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. 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. No sample indicated positive results. Gamma spectroscopy did not detect the presence of any isotopes related to the operation of North Anna. In years past, Cs-137 has been detected sporadically. These occurrences were attributed to residual global fallout from past atmospheric weapons testing. Naturally occurring K-40 was detected in all samples. Once each quarter a sample from the collection station is analyzed for strontium-89 and strontium-90. Neither Sr-89 nor Sr-90 was 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 gaseous 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 Food/vegetation samples were collected from five locations and analyzed by gamma spectroscopy. The results of the analyses are presented in Table 3-9. Low levels of Cs-137, attributable to fallout, have been seen periodically in vegetation samples. As expected, naturally occurring potassium-40 and cosmogenic beryllium-7 were detected in most samples, and thorium-228 and other natural products, including Bi-214, were detected in some samples. No plant related isotopes were identified in any Vegetation sample during 2016.
4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, 1-131, and gamma emitters. The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period. 4.11 River Water Samples of water from the North Anna River were collected monthly. The analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy. The monthly samples are composited quarterly and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90 in accordance with program requirements. There has been no detection of these fission products at any of the indicator or control stations in recent years. 63 No gamma emitting radioisotopes were positively identified in any of the samples. There was no measured activity of strontium-89 or strontium-90. Tritium was measured in all four samples with an average annual concentration of 3930 pCi/liter and a range of 3340 to 4230 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. River Water 4500 4000 3500 .... 3000 ~ 1--~~~~~~~-t-~~-.,..,.-~+--41>--~-t--~-1-~~~~~~-"11,._-trl-~-+ 3000 u Cl. 2500 2000 1500 1000 l/\\ ID r-- 00 C1l 0 ri N C't\\ '¢ l/\\ 00 00 00 00 00 en en en en en en c c c c. c c c c c c c cu cu cu cu cu cu cu cu cu cu cu ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4.12 Surface Water ID r-- 00 en 0 ri N C't\\ '¢ l/\\ ID r-- 00 C1l 0 en C1l en en 0 0 0 0 0 0 0 0 0 0 ri c c c c c c c c c c c c c.. c c cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Figure 4-4 Tritimn in River water ri N C't\\ '¢ ri ri ri ri c c c c cu cu cu cu ~ ~ ~ ~ l/\\ ri c cu ~ ID ri c cu ~ 2500 ~Tritium Required LLD 1000 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 spectroscopy and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90. There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12. No non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the samples. No tritium was detected at the control location. The average level of tritium activity at the indicator station was 4270 pCi/liter with a range of 3580 to 5810 pCi/liter. Levels of tritium have increased 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. 64 10000 M~r*/Wi~~ I u . I v 1 (\\/ 1000 I /J -- Tritium ...J t;100
a.
Required LLD --+- Average Pre-op 10 1 r-- en lO r-- 0 N 'o:t <D co lO r-- en N 'o:t <D co 0 r-- r-- co co ~ ~ en en al en en 0 0 0 0 0 N
t.
0.. >,;,. I 0.. > I .!. t. bi t; u u c: c: ro ro ro Cl) Cl) ro Cl) 0 Cl) Q. Cl) 0 ro ro
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2:
0 0 LL
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(f) z LL <( (f) z
2:
<( 0 Figure 4.5 Tritium in Surface Water 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 spectroscopy. The October samples were analyzed for strontium-89 and strontium-90. The results are presented in Table 3-13. No plant related isotopes were detected in 2016. 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 also analyzed by gamma spectroscopy. Figure 4-6 shows the historical trend of Cs-137 in sediments. Neither Strontium-89 nor Strontium-90 was detected in any samples of aquatic sediment/silt in 2016. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests. A number of naturally occurring radioisotopes were detected in these samples at background levels. 65 ~~~~~~m~~~~~~~~go~~s~~b~~~~~~~~~~~~ LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL rororororororororororororororororororororororororororororororororororo 22222222222222222222222222222222222 Figure 4-6 Cs-137 in Sediment/Silt 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. Samples of shoreline soil were collected in April and October from indicator station 08. The samples were analyzed by gamma spectroscopy. The October 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. No plant related isotopes were detected in any indicator samples analyzed. Strontium-90 is often 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. 4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2016 and analyzed by gamma spectroscopy. 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. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected. Cs-137 was measured in pre-operational environmental fish samples. 66
5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2016-North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14B,15,16,23,26 Vegetation 01/12/16 Seasonal unavailability 14B,15,16,23, 26 Vegetation 02/10/16 Seasonal unavailability l 4B, 15, 16,23,26 Vegetation 03/08/16 Seasonal unavailability 14B,15,16,23, 26 Vegetation 12/13/16 Seasonal unavailability There was one exception to the Interlaboratory Comparison Program (ICP) for 2016. A QA/QC sample for gross beta analyses for Air Filter (AP) geometry was not provided to Teledyne Brown Engineering, Inc. (TBE) for analysis in the second half of 2016. The provider, Mixed Analyte Performance Evaluation Program (MAPEP), did not supply TBE the required sample media due to funding issues. TBE did not request a QA/QC sample from addidional contracted providers. Eckert & Ziegler Analytics, Inc. will provide the QA/QC sample for AP geometry until MAPEP puts the geometry back into production. This issue is documented in TBE NCR 17-5.
67 REFERENCES References Dominion, North Anna Power Station Technical Specifications, Units 1 and 2. Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications. Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual". Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010, "Radiological Environmental Monitoring Program". Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities". United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October, 1977. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. NUREG 04 72, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992. NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984. 68 APPENDICES 69 APPENDIX A: LAND USE CENSUS Year2016 70 r January 1 to December 31, 201 6 Direction Distance (miles) Nearest Site Boundary N 0.9 NNE 0.9 NE 0.8 ENE 0.8 E 0.8 ESE 0.9 SE 0.9 SSE 0.9 s 0.9 SSW 1 SW 1.1 WSW 1.1 w 1.1 WNW 1 NW 1 NNW 0.9 LAND USE CENSUS North Anna Power Station Louisa County, Virginia Nearest Nearest Resident Garden(> 50m2) 1.3 1.56 0.9 1.22 0.9 1.6 2.37 2.4 1.3 2.04 1.7 1.7 1.4 1.54 1.0 1.0 1.03 1.14 1.27 1.33 1.65 1.65 1.62 2.22 1.5 1.93 1.1 2.67 1.0 1.28 1.0 2.54 71 Nearest Nearest Nearest Meat Milch Milch Animal Cow Goat 2.9 NONE NONE 3.1 NONE NONE 1.6 NONE NONE 2.49 NONE NONE 3.5 NONE NONE NONE NONE NONE 1.4 NONE NONE 1.6 NONE NONE 2.0 NONE NONE 2.0 NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE 4.98 NONE NONE NONE NONE NONE 2.3 NONE NONE 2015 to 2016 Land Use Census Changes 2015 2016 Nearest Direction Distance Distance Resident ENE 2.37 2.37* Site Boundary NONE Garden N 1.76 1.56 ESE 1.7 1.7 w 1.93 1.93* NW 1.96 1.28 NNW 1.22 2.54 Meat Animal ENE 2.65 2.49 w 4.40 NONE Milch Cow NONE Milch Goat NONE
  • Change in physical address only. Distance remains the same as previous.
72 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR 2016 INTRODUCTION This appendix covers the Jntercomparison Program of the Teledyne Brown Engineering - Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). TBE uses QA/QC samples provided by Eckert & Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) and Environmental Resource Associates, (ERA) to monitor the quality of analytical processing associated with the REMP. The suite of samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides. This includes: For the TBE laboratory, 156 out of 160 analyses performed met the specified acceptance criteria. Four analyses (Milk - Sr-90, Vegetation Sr-90, and Water-H-3 samples) did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program. One sample is no longer being analyzed by TBE through MAPEP: Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities. I. Teledyne Brown Engineering's MAPEP February 2016 air particulate cross check samples is now being provided to TBE by Analytics. MAPEP's policy is to evaluate as failed non reported nuclides that were reported in the previous study. Since the Sr-90 was reported in the previous MAPEP study but not in this study MAPEP evaluated the Sr-90 as failed. NCR 16-14 The MAPEP February 2016 Sr-90 in vegetation was evaluated as failing a false positive test. In reviewing the data that was reported vs the data in UMS, it was found that the error was incorrectly reported as 0.023 rather than the correct value of 0.230. If the value had been reported with the correct activity and uncertainty of 0.301 +/- 0.230, MAPEP would have evaluated the result as acceptable. CR 16-14

2.

Teledyne Brown Engineering's Analytics' March 2016 milk Sr-90 result of 15 +/-.125 pCi/L was higher than the known value of 11.4 pCi/L with a ratio of 1.31. The upper ratio of 1.30 (acceptable with warning) was exceeded. After an extensive review of the data it is believed the technician did not rinse the filtering apparatus properly and some cross contamination from one of the internal laboratory spike samples may have been transferred to the analytics sample. We feel the issue is specific to the March 2016 Analytics sample. NCR 16-26

3.

Teledyne Brown Engineering's ERA December 2016 sample for H-3 in water was evaluated as failing. A result of 918 pCi/L was reported incorrectly due to a data entry issue. If the correct value of 9180 had been reporied, ERA would have evaluated the result as acceptable. NCR 16-34 73

4.

Teledyne Brown Engineering's Analytics' December 2016 milk Sr-90 sample result of 14.7 +/-.26 pCi/L was higher than the known value of 10 pCi/L with a ratio of 1.47. The upper ratio of 1.30 (acceptable with warning) was exceeded. The technician entered the wrong aliquot into the LIMS system. To achieve a lower error term we use a larger aliquot of l.2L (Normally we use.6L for client samples). NCR 16-35 74

tr Eckert & Ziegler Anafytfcs HIO SMbOlnl lndllllrill IM!. Atlt~ GA IOIU. UM RESULTS OF RADIOCHEMISTRY SAM.PLE ANALYSIS CROSSCHECK PROGRAM lST QUARTER 2016 (Ref. Date 19 FEB 16) REVISED ~. ~ ,.; '-'r,, L. Tkavadze;.N~c1e-Sr Metr0iog1st - VALUE microCi/cc ANALYTICS VALUE microCilcc RATIO RESOLUTION COMPARISON A31518 LIQUID Tritium -6.79E-04 7.40E-04 0.92 12.5 AGREEMENT A3l519* FILTER Sr-89 Sr-90 2.04E-03 l.OSE-04 2.46E-03 2.68E-04 0.8.1 0.78 17 12.S AGREEMENT AGREEMENT

  • microCi 75

~ m Eckert & Ziegler 1\\na1';tics l i &O Sa.:iboard ll'ciUJh'lai e<vt!. A.tlar.n, GA 30Sla, USi\\ T;? I~ 40ol*i!SH6i7 foic: 404-352-2837 RESULTS OP RADlOCHElVUSTRY SAMPLE A3203S FILTER A32034 J'ILTER ANALYSIS 8~9 Sr-:90 CROSS CHECJ(.PROGRAM 3.RD Q ARTER 2016 (Ref. Date 12 AUG.l6) t . ~ H o. i lG L. Tkav~ltb;<'., Nuclea r Mctrnlogist RATIO VALUE micro Ci ANALYTICS VALVE mic:roCI RESOLUl'lON COMPARISON l.83E-03 2.64E-04 3.67E-03 2.76E--03 0.96 0.94 1.33 17 12.5 AGREEMENT AGREEMENT ........... "'****"'****"**"lrlr**.... ****************************"********'**""********"'****'***"'****************** 76

AN1AL YTICS ENVIRONMENT AL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF3) laen ca hon Reported Known Raho (c) Month/Year Number Matrix Nuclide Units Value {a) Value {bl TB El Analytics March 2016 E11 476 Milk Sr-89 pCifL 97 86.7 Sr-90 pCifL

  • 15 11.4 E11 477 Milk 1-1 31 pCifL 85.9 82.2 Ce-141 pCifL 106 98.4 Cr-51 pCifL 255 243 Cs-134 pCifL 134 130 Cs-137 pCifL 174 161 Co-58 pCifL 123 117 M1-54 pCifL 141 117 Fe-59 pCifL 152 131 Zn-65 pCifL 193 179 C0-80 pCifL 259 244 E1 1184 AP Ce-141 pCi 69 81.1 Cr-51 pCi 242 201 Cs-1 34 pCi 98.1 107.0 Cs-1 37 pCi 136 133 C0-58 pCi 91.9 97 rk!-54 pCi 98.6 96.2 Fe-59 pCi 98.8 108 Zn-65 pCi 131 147 C0-80 pCi 209 2{)1 E1 1478 Charcoal 1-131 pCi 85.3 88.3 E111 85 Water Fe-55 pCifL 1800 1666 June 2016 E 11 537 Milk Sr-89 pCifL 94.4 94.4 Sr-90 pCifL 13.4 15.4 E11 538 Milk 1-131 pCifL 96.8 94.5 Ce-141 pCifL 129 139 Cr-51 pCifL 240 276 Cs-1 34 pCifL 157 174 Cs-1 37 pCifL 117 120 C0-58 pCifL 131 142 rvtl-54 pCifL 128 125 Fe-59 pCifL 132 122 Zn-65 pCifL 235 235 C0-80 pCifL 169 173

{a) Ta"'ffyne Brown Engineering reporfad rewlf. {b) The Ana!yrics known value is equal to 100% of Ifie parameter present irt /he standani a:; determined.by gravimetric and.lw \\iOlumeln*c measurements mao'e during :standard preparat>on. (c} Ra fro of Teledyne Brown Engineerirr-9 lo Anafytic:s re-:sulf:s. (d) Anarytic:; evafuaifon based on rBE internal OC A'm~ : A= Acoepfable, r;:ported re-:sufl faJ.!s within ra.r.'o lim~ of 0.~1. 20. W-Acceptab/;:o with aming., report~ resm~ fc,/,*s wi!h.'n 0. 70--0.80 or 1.20-1.30. N = N-0.r Acoept<tbfe, r;:ported r~u!i fa~ oufaj rJ.? rhe ratio lim.frs of < 0. 0 and > 1. 30. (2) NCR 6-26 was initiated 77 1.12 1.32 1.05 1.08 1.05 1.03 1.08 1.05 121 1.16 1.08 1.06 0.85 120 0.92 1.02 0.95 1.02 0.91 0.89 1.04 0.97 1.08 1.00 0.87 1.02 0:93 0.87 0.90 0.98 0.92 1-02 1.08 1.00 0:98 Evaluation !d) A N(2) A A A A A A w A A A A w A A A A A A A A A A A A A A A A A A A A A

ANALYTICS ENVIHONMENT AL RAIJIOACTIVlTY CROSS CHECK PROGRAM TELEDYN E BROWN ENGINEERING ENVIRONMENTAL SERVICES [PAGE 2' OF 3) ldenuncahon Reported known Raiio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d) June 2016 E11539 Charcoal 1-1 31 pCi 86.1 89.4 E11540 AP Ce-141 pCi 105 99.8 Cr-51 pCi 216 198.0 Cs-134 pCi 113 125 Cs-137 pCi 94.5 86.'6 Co-58 pCi 101 102 rvti-54 pCi 88.8 90.2 Fe-59 pCi 82 87.5 Zn-65 pCi 174 169 Co-60 pCi 143 124 E11185 Water Fe-55 pCi/l 1'64 186 September 2016 E 116-09 Milk Sr-89 pCifL 90 90.9 Sr-90 pCi/l 13.3 13.7 Milk 1-131 pCi/L 80.4 71.9 Ce-141 pCifl 8 1.3 93 Cr-51 pCifL 198 236 Cs-134 pCifL 122 135 Cs-137 pCifL 11 9 119 Co-58 pCifL 92.2 97.4 Ml-54 pCifL 156 152 Fe-59 pCifL 97.5 90.6 Zn-65 pCifl 189 179 Co-60 pCifL 131 135 E11 511 Charcoal 1-131 pCi 52.4 599 E11612 AP Ce-141 pCi 67.5 63.6 Cr-51 pCi 192 161.0 Cs-134 pCi 91.4 92.6 Cs-137 pCi 93_9 80.8 Co-58 pCi 66 66.4 Ml-54 pCi 104 104 Fe-59 pCi 60.5 61.8 Zn-65 pCi 140 122 Co-60 pCi 11 9 91.9 (a) Tekdyne Brown Engineffing reported result. (b) Tlt.e AnaJylics known value.':s equal to 100% of the parameter present in lhe :standard a:s de-.'"errnined by gravimetric am!* volumelric measurements made durittg :standard prepa.ratfun. (c) Ratio of Teledyrte Brown Eng ine~g to Analytic:s re:su!!:s. (d) An.aJytic:s evaluation based on TBE intemat QC lfmit:s: A= Aet:.eptable, reported rew!l faJ1s with.in raf1'o limits of 0.80-1.20. W-Acceptable wiih 'lfilm.'rtg, repolfed re-sifo~ f;;/ls within 0.7().().60 or 1.20-1.30. N =* N<JI Aet:.epf:abre, re-po.rl!Ni re.5ulf f~ outside tft.e. ratio tirnirs of < 0. 70 and > 1. 30. 78 0.96 A 1.05 A 1.09 A 0.90 A 1.09 A 0.99 A 0.98 A 0.94 A 1.03 A 1.15 A 0.88 A 0.99 A 0:97 A 1.12 A 0.87 A 0.84 A 0.90 A 1.00 A 0.95. A 1.03 A 1.08 A 1.06 A 0.97 A 0..87 A 1.06 A 1.19 A 0.99 A 1.16 A 0:99 A 1.00 A 0.98 A 1.15 A 1.29 w

ANALYTIC S ENVlRO NMENTAL RAD OACTIVITY C RO SS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONM ENTAL SERVI CES (PAG E 3 OF 31 Reported Known Ratio (c) Mont '!'ear Mawix u Ude nits Value (a) Val'ue (b) TBEJAnafytics Ev uation (d) Septe l>er 2 6 E1 513 Wa:er e-pCi. 1990 Hl70 1.19 A E 1 514 Soil Ce-141 pCLlg 0.153 0.175 .87 A Cr-5 pCi/g 0.482 0.441

1. 9 A

Cs-34 pCi.lg 0.27 0.254 1.05 A Cs-37 pCi/g 0.313 0_2gg 1.05 A Co-!>B pCi/g

0. 177 0.182

.97 A n -54 pCi/g 0.340 0.285 1.19 A e-pCilg 0.. 206 0.17 1.2 w Z.n-1}.5 pCilg 0.3SB 0.335 1.16 A Co-00 pCitg 0.284 0.2 2 1.13 A Dec-em l>er - 6 E l 59'9 Milk Sr-S9 pCitL 95 7.2 1.28 w Sr-90 pCi/L 4.7 1.47 (3} E l 17 Milk 1-13 pCil L 97.5 97.4 1.00 A Ce-141 pCL'L 136 143 9"

J A

Cr-5 pCi!L 247 280 .88 A Cs-34 pCrtL 1e.t1 178 .92 A C:s-37 pCL<L 12 126 .95 A Co-B pCilL 139 146 .95 A Mn-54 pCilL 126 129 0.98 A e-5tl pCilL 1 125 0.9 A Zrl-6r5 pCi!L 237 244 .97 A Co-00 pCi!L 168 179 .94 A E l 7 1 Ch;mxlal 1-13 pCi 9.e gs .9 A E l 70'~ AP Ce-141 pCi 91.7 97.7 A Cr-5 pCi 2

92.

A Cs-34 pCi 122 122 A Cs-37 pCi 93.Q 86.4 1.09 A Co-58 pCi 92 100 .Q2 A Mn-54 pCi 93.7 88..5

1. 6 A

Fe-5tl pC i 84.9 8.4 1.00 A 2.n-65 pCi 176 167

1. 5 A

Co-00 pCj 1fi1 122 1.24 w E l 7 3 I/ ater e-50 pCifL 2 G 1800 1.2 w E l 730 AP .:.r-81;> pC i 79.7 92 0.86 A Sr-90 pC i 0 2.5 0.80 A fa) ( ~ 11? p~r;;, ete.r p.!':rl! 1 r1~ e.sr ~Cl3rel.;..s ll'ere

  • n:<1 oy g.ra eir.'C
t.'Or 110 m Jw; s0<.s.llrE11r.~.~** m;;tre O\\:m'Jg sr.aoo.:rd' p1eparat>Jn_

(CJ (:1) Y:s:.: ;:,=.A.(;(:Ep!'C'.O e, repClii'.Ed **. :s:

  • ra. s

-.rlllrl raril:l I

s: at O.BtJ-1.20.

11-AccP..p.rC'b: w.tll ;i.*am1'1"9', r.epcrted tesu.t ra

  • wtm.11 o. c-a.M 01.

1.30 N = Net Accoeptab., r.!!pcrrea 1?:s:* a.'IS c.11!"'.Jt\\? e ra l:J IT\\'n'l.s Cl!"' o. o and,. ua. 13 NCR 16-3'5 *A"a6 Ir : teo 79

r"" DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MA PEP) TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1OF 1) Iden ca hon Reported kno111n MonthJY.ear Number Media Nuclide* Units Value (a) Value {b) March 2016 16-MaW34 Water Am-241 Bq/L 0.008 Ni-63 Bq/L 12.4 12.3 Pu-238 Bq/L 1.4900 1..2440 Pu-239/240 Bq/L 0.729 0.641 16-MaS34 Soil Ni-63 Bq/kg 1140 1250.0 Sr-90 Bq/kg 8.15 16-RdF34 AP U-2341233 Bqlsample 0.1620 0.1650 U-238 Sqls3mple 0.163 0.172 16-GrF34 AP Gr~A Sqlsample 0_608 1-2{) Gr-8 Sq/sample 08060 0_79 16-RdV34 Vegetation Cs-134 Sq/sample rn.10 10.62 Cs-1 37 Sq/sample 6.0 5_62 Co-57 Sq/sample 13.3000 11.8 Co-£0 Sq/sample 0_013 tvtl-54 Sq/sample 0.0150 Sr-90 Sq/sample 0.301 Zn~5 Sq/sample 10.500 9.6 Sep ernller 2016 16-MaW35 Water Am-241 Bq/L 0_626 0.814 Ni-63 Bq/L 12.4 17.2 Pu-238 Bq/L 1.23 1-13 Pu-239/240 Bq/L 0.0318 0.013 16-MaS35 Soil Ni-63 Bqlkg 724 990 Sr-90 Bq/kg 747 894 16-RdF35 AP U-234/233 Sq/sample 0.160 0.15 U-238 Sq/sample 0.157 0.156 16-RdV35 Veget3tion CS-134 Sq/sample 1 03 CS-137 Sq/s3mple 5.54 5.54 Co-57 Sq/sample 7.38 6_81 Co-£0 Sq/sample 4.81 4_86 tvti-54 Sqlsample 7.4 7.27 Sr-90 Sq/sample 0.774 0_8{) Zn~5 Sq/sample 5.46 5.4 (1) Fakle positive tesi. (a) Tekdyrre Brow Engine-ering reported rew!t. (b) The MAPEP known value i5 equal to 1W-' of rhe pa ra.~~-=< Pfi?Senl in rhe standard as etemiirred by gravimerric and/or 'Oillmeln'c measuremen~ made duting stana'ard pr?paraoon. (c) DOEl MAPEP evaluafion: A=acceptable, W=acoeplabi'e w'i!ti warning, ~/=not acoeptabre. {4)NCR 1&-14 was - ~~';; fed 80 Acceptance Ran<Je { 1) 8.6-16.0 0.871-1 _617 0.449-0.833 875-1625 { 1) 0.116-0.215 0.120-0.224 0.36-2.04 0.40-1.19 7.43-13.81 3.93-7.31 8.3-15.3 ( 1) { 1) (1) 6.7-12.5 .570-1058 12.0-22.4 0.79-1.47 { 1) 693-1287 626-1 162 0.105-0.195 0.109-0.203 { 1) 3.88-7.20 4.77-8.85 3.40-6.32 5.09-9.45 0.56-1.04 3.78-7.02 Evalua -Oil {c) A A A A A A A A A A A A A A A N(4) A w A w A A A A A A A A A A A A

r - -~ ' ERA ENVIRONMENT AL RADIOACTIVITY CROSS CHEOK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES {PAGE t OF 1) Iden tlcahon Reported Known Wlonth!Year Number ~1edi a Nuclide Units Value (a) Value {b) May2016 RAD-105 Water Sr-89 pCifl 48.9 48.2 Sr-90 pCifL 25.0 28.5 Ba-133 pCifL 53.1 58.8 Cs-134 pCill 40.9 43.3 Cs-137 pCi/l 84.8 78.4 Co-60 pCi/l 1{)8 102 Zn--65 pCill 226 214 Gr-A pCi/l 38.9 62.7 Gr-B pCill 41.9 39.2 1-131 pCill 24.1 26.6 U-at pCi/l 4.68 4.64 H-3 pCill 7720 7840 vember 2016 RAD-107 Water Sr-89 pCifL 43.0 43.3 Sr-90 pCi/l 30.0 33.6 Ba-1 33 pCifl 47.8 54.9 Cs-134 pCi/l 72.9 81.8 Cs-137 pCi/l 189 210 Co-60 pCi/l 58.4 64.5 Zn-65 pCi/l 243 245 Gr-A pCi/l 372 68.4 Gr-8 pCi/l 35.1 33.9 1-131 pCill 23.5 26.3 u a pCi/l 492 51.2 H-3 pCi/l 918

  • 9820 MRAD-25 AP Gr-A pCi/Fil er 56.8 71.2 (a) Tefedyn.p Bro1~'1l Engineeri g reported resulf.

(b) Th.P ERA known va!ue is.PQlfallo 100% of the paramet..r present in the stand;;ni a-.s detem

  • ed by gravimetric aru!lor olumetric measurements mao'e dlfrirtg standard preparation.

Acceptance Limits 37.8 - 55.6 20.7 - 33.1 48.7 - 64.9 34.6 -47.6 70.6 - 88.9 91.8 - 114 193 - 251 32.9 - 77.8 26.0 - 46.7 22.1 - 31.3 3.39-5.68 6790- 8620 33.4-50.5 24.6-38.8 45.4-60.7 67.G-90.0 189-233 58.0-73.4 220-287 35.9-84.5 22.1-41.6 21.9-31.() 41.6-56.9 8540-10800 23.9-11 1 (c) ERA evaluation: A =acoept:able. Reported rewJt faffs within h-P W;;m

  • g Um.~s. NA =n~ ~epta l:; 'e. Repone<J re:st11~ f;;Ns out:;ide of the Control Um.il.s. C.E=cl:ieclc for Em>I. Reporl-ed resuJf fa)J:; with* the Control Um.ts ;;ml oufside of the 'laming Umit.

(5) NCR 6-34 was. initia ed 81 Evalua

  • oo (c}

A A A A A A A A A A A A A A A A A A A A A A A N(5) A}}