Text

Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report
	ML17145A306
Person / Time
Site:	North Anna
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)
	v • d • e

{{#Wiki_filter:VIRGINIA ELECTRIC AND P OWER C OMPANY RICHMOND, VIRGINIA 23261 April 27 , 2017 United States Nuclear Regulatory Commission Serial No. 17-144 Attention: Document Control Desk NAPS/JHL Washington , D. C. 20555 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

Serial No. 17-144 NAPS Annual Radiological Environmental Operating Report cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave ., NE Suite 1200 Atlanta , Georgia 30303-1257 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

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

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2016 to December 31, 2016 Prepared by: Bradley T. Pleasants, Jr. Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Reviewed by: Barbara J. Thompson Superintendent Health Physics Technical Services Dominion North Anna Power Station Approved by: 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. DIS CUSSION 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 Nuc lear 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 availab le 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 samp le 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. Fal lout 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 pC i/ liter. No plant related isotopes were detected in quarterly precipitation samp les. Si lt samp les indicated the presence of naturally occurring potassium-40 and thori um and uranium decay daughters at leve ls consistent with the natural background. No plant related isotope was identified in any sampl e. Sho re line soi l, w hi ch may provide a direct exposure pathway, indicated the presence of potassium-40 and thori um 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 fall out. Leve ls 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 a lso 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 fa ll out. No other plant re lated isotope was identified in soi l samp les during 2016. T he terrestria l exposure pathway includes milk and food /vegetation products. No plant related radioisotope was detected in any milk samp les. 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 samp le. 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 remai ned essential ly 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 indi vidua l at the station site boundary due to liquid and gaseous effluents re leased from the station during 2016 was 0.77 millirem. For reference, this dose may be compared to the 620 millirem average annua l 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 federa l 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 commerc ial 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 mo nitoring 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 co llected 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 10CFR50, 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 rad iation 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 radiologica l effluent monitoring program by verifying that radioactive effluents are within allowable limits.

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        ~  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 Iu 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° Quarterl y & 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 2.3 3 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 1.5 5 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 32 1° Quarterly Lake Anna Campground NW-30/62 2.54 NW 319° Quarterly

                      # 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 ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD) (84 TLDs) Quarterly Gamma Dose 2 mR+/-2mR mR/std. Month (12 TLDs) Annually Gamma Dose 2 mR+/-2 mR mR/std . Month Airborne Radioiodine Weekly 1- 13 1 0.07 pCi/m 3 Airborne Particulate Weekly Gross Beta 0.01 pCi/m 3 Quarterly (a) Gamma Isotopic pCi/m3 Cs- 134 0.05 Cs- 137 0.06 2"d Quarter Sr-89 (b) pCi/m3 Composite Sr-90 (b) Surface Water Monthly 1-131 l(c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs- 134 15 Cs- 137 18 Ba-140 60 La-140 15 Quarterly( a) Tritium (H-3) 2000 pCi/L 2"d Quarter Sr-89 (b) pCi/L Composite Sr-90 (b) River Water Monthly I-131 l (c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs- 137 18 Ba-140 60

*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 sampl es are used for the required analysis (b) T here 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 sampl es. However, since this is a semi-ann ual composite no LLD is applied fo r these nuclides due to their short half-lives . 12

TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPQB.I llNITS La-140 15 River Water Quarterly( a) Tritium (H-3) 2000 pCi/L 2nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b) Ground Water Quarterly Gamma Isotopic pCi/L (Well Water) 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 pCi/L 2nd Quarter Sr-89 (b) pCi/L Sr-90 (b) Aquatic Sediment Semi-Annually Gamma Isotopic pCi/kg (dry) Cs-134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry) Sr-90 (b) Precipitation Monthly Gross Beta 4 pCi/L Semi-Annual Gamma Isotopic pCi/L Composite Mn-54 15 Fe-59 30 Co-5 8 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) Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry) Cs-134 150 Cs-1 37 180

*LLDs indicate those levels to whi ch 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 sampl es 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

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

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, si nce 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 Map Environmental Station Designation Identification Designation Identification (a) 01 ,NE-5/37 7/8 C-7/8 IA OlA,SE-13/45 1/33 N-1 /33 2 (a) 02,SSW-20/52 31163 NNW-31163 3 (a) 03 ,C-516 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) 05 7/39 ENE-7/39 SA (a) OSA,N-2134 9/41 E-9/41 6 (a) 06,ESE-12/44 11 /43 ESE-11143 7 (a) 07, C-112 17/49 S-17/49 8 08-Water, Fish, Sediment, 19/51 SSW-19/51 Shoreline Soil 21 /53 SW-21 /53 9A 09A-Water sample, Sediment 23/55 WSW-23/55 11 11-River Water, Sediment 12A 12A-Milk 25/57 W-25/57 14B 14B-Vegetation 16/48 SSE-16/48 15 15-Vegetation 14/46 SE-14/46 16 16-Vegetation 22154 SW-22/54 21 (a) 21 ,WNW-27/59 26/58 W-26/58 22 (a) 22,WSW-24/56 28/60 WNW-28/60 23 (a) 23-SSE-15/47 ,Vegetation 32/64 NNW-32/64 24 (a)(b) 24,C-3/4 8/40 ENE-8/40 25 (c) 25-Fish 4/36 NNE-4/36 26 26-Vegetation 10/42 E-10/42 (a) Indicates air sample stati on, annu al and quarterly TLD, Tri enni al soil. (b) In Orange (c) In Lake O range

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SSW Legend

         *    -ixed Environmental Mo

oring Sfati<:>

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

                          ~~ ii                   TSYLVANIA            l North Anna Environmental Map

Fixed Environmental Sampling Location e TLD Sampling

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9 oarden Residents

Meat Animals

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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 18

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.

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I .,,,,.,,.... 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 Gene r:al G reen 'W'".;y. / Alex:indrio. VA 22:312 . USED WITH PERM ISSIOO. No oth"' reproduction

~ be        ode wiihoul 1he writ:en perm- 3ion o4 ADC.
                                                                               /
                                                                                 ".._,'-/ l' C83281E 20

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 va lues 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 ( 11 111) OJ 0.20mi. 4.7 ( Il l) 2.5(11 1) 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

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 Loca tion Control Non-Medium or Analysis Locations with Hi2hest Mean Location routine Pathway LLD Reported Samp led (Unit) Total (pCi/unit) Mean Name Distance Mean Mean Measure-Type No. Ran2e Direction Ran2e Ran2e men ts Airborne Cs-137 52 0.06 (0148) NIA NIA NIA (014) 0 Particulates (I E-03 pCilm3) Sr-89 13 (0/12) NIA NIA NIA (011) 0 Sr-90 13 (0112) NIA NIA NIA (011) 0 Soil* Triennial (pCil Kg) (dry) Gamma 12 K-40 12 12970 (1lll1) 23 0.93mi 32400 ( 111) 30600 (I l l) 0 (4600-32400) SSE (32400) (30600) Cs- 134 12 150 (0111 ) NIA NIA NIA (Oil) 0 Cs-137 12 180 362 (6111) 06 4.70mi 646 (I l l) (Oil) 0 ( 177-646) ESE (646) Ra-226 12 3809 (71l 1) 22 1.00mi 5510 (I l l) (011) 0 (2400-5510) WSW (5510) Th-228 12 1644 ( I I ll I ) 22 l.OOmi 3650 (1 11) 209 (I l l) 0 (487-3650) WSW (3650) (209) Th-232 12 1773(9111 ) 05A 2.04mi 3460 (I l l) (0/1) 0 (5 15-3460) N (3460) Sr-89 12 (Oil I) NIA NIA NIA (Oil) 0 Sr-90 12 (Oil I) NIA NIA NIA (Oi i) 0 Precipitation Monthly (pCi/liter) Gross 12 4 3.54 (10/12) OJA 0.64 mi . 3.54 (10112) NIA 0 Beta ( 1.93-6.83) SE ( 1.93-6 .83) H-3 4 2000 (014) NIA NIA NIA NIA 0 Semiannual 2 Gamma Be-7 2 51 ( 112) OlA 0.64 mi 51 (1/2) NIA 0 (51) SE (51) Mn-54 2 15 (012) NIA NIA NIA NIA 0 Fe-59 2 30 (012) NIA NIA NIA NIA 0 Co-58 2 15 (012) NIA NIA NIA NIA 0

Soil Samples required triennia lly. Samples were obtained in 2016 .

23

Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Docket No. 50-338/339 Page 3of9 All Indicator Indicator Location Control Non-Medium or Analvsis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/ un Mean Name Distance Mean Mean Measure-Type it) Range Range men ts No. Range Direction Co-60 2 15 (012) NIA NIA NIA NIA 0 Precipitation (pC i/liter) Zn-65 2 30 (012) NIA NIA NIA NIA 0 Zr-95 2 30 (012) NIA NIA NIA NIA 0 Nb-95 2 15 (012) NIA NIA NIA NIA 0 1-131 2 10 (012) NIA NIA NIA NIA 0 Cs-134 2 15 (012) NIA NIA NIA NIA 0 Cs-137 2 18 (012) NIA NIA NIA NIA 0 Ba-140 2 (012) NIA NIA NIA NIA 0 La-140 2 (012) NIA NIA NIA NIA 0 Th-228 2 5.30 (1 12) OIA 0.64mi 5.30 (l/2) NIA 0 (5.30) SE (5.30) 24

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/uni t) Mean Name Distance Mean Mean Measure-(Unit) T voe No. Ran2e Direction Range Range men ts Gamma 12 Milk (pCilliter) 1370 (1 2/12) 12A 7.50 mi. 1370 (1 2112) K-40 12 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

Table 3-1 RADIOL OGICAL ENVIRONMENTAL M ONITORING PROGRAM S UMMAR Y North Anna Nuclear Power Station, Louisa County, Virginia - 2016 Docket No. 50-338/339 Page 6of9 All In d icato r Location Control Non-Med ium or Analysis Indicato r with H ighest Mean Location routine Locations Reported Pathway LLD Measure-Sampled Tota l (pCi/un Mean Name Distance Mea n Mea n men ts (Unit) Type it) Range R a nge No. Ra nge Direction Ground Cs-134 4 15 (014) NIA NIA NIA NIA 0 Well Water (pCilliter) 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 R iver Water Tri tium 4 2000 3930 (414) 11 5.80 mi. 3930 (414) (014)* 0 (pCil liter) (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 va lue for river water 27

Table 3-1 RADIOLOGICAL ENVIRONMENTA L M ONITORIN G PROGRAM S UMMAR Y North Anna Nuclear Power Station, Louisa County, Virginia - 201 6 Docket No. 50-338/339 Page 7of9 All Indicator Indicator Location C ontrol No n-Medium o r Ana lysis Loca tion s w it h Highes t Mean Loca tion rout ine R eported Pa thway LLD Measure-Sa mpled Tota l (pCi/ uni t) Mea n Na me Dista nce Mea n Mea n men ts (U nit) T ype No. Ran ge Direction R a nge R a n2e River W a te r Ba- 140 12 60 (0/12) NIA NIA NIA (0112)* 0 (pCi/liter) 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 Surface Water (pCilL) (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

*Resu lts of surface water taken at Location 09A used as control va lue for river water 28

. ) ' Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S UMMAR Y North Anna Nuclear Power Station, Loui sa County, Virginia - 2016 Docket No. 50-338/339 Page 8 of 9 All Indicator Indicator Location Control Non-Medi um or Analysis Locatio ns with Highest Mea n Location routine Reported Pathway LLD Measure-Sa mpled Total (pCi/unit) Mean Na me Distance Mean Mean men ts (U nit) Type No. Range Direction Range Range Surface Water Sr-89 (011) NIA NIA NIA (0/1) 0 (pCilliter) Sr-90 (0/1) NIA NIA NIA (Oi i ) 0 Sediment Silt Gamma 6 (pCi/kg) K-40 6 9700 (414) 11 5.80 mi . 17900 (212) 23100(212) 0 SE (14000-( 1280-2 1800) (225 00-23600) 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(1 12) 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

                                      .,                                                     NIA Sr-90         -'                  (012)      NIA       NIA                          (0/1)       0 Shoreline Soil     Gamma         2 (pCi/kg) (dry)       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

} ' Table 3-1 RADIOL OGICAL ENVIRONMENTAL M ONITORING PROGRAM S UMMAR Y North Anna Nuclear Power Station, Louisa County, Virginia- 2016 Docket No. 50-338/339 Page 9 of 9 All Indicator Indicator Location Co nt r ol Non-Med ium or Analysis Locations with Highest Mea n Location routine Reported Pathway LLD Measure-Sampled Tota l (pCi/unit) Mean Name Dista nce Mean Mean men ts (U nit) Type No. R ange Directio n Ra n2e Ran2e Shorelin e Soil (pC i/kg) (dry) 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 Fish (pC i/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 DIRE CT RADIATIONMEASU RMENTS- SECTOR QUARTERLY TLD RE SULTS Page mRJStd. Month (30.4 days)+/- 2 Sigma 1 of 4 First Quarter Second Quarter TmdQuarter F ow1h Quarter Quarterly* Stati on 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-3 4 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-3 7 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

Av erage of c ollocated TLD s.

32

TABLEJ..2 DIRECTRi\DLl\TION Aff.ASURMENfS- SECTOR QU.'\RTERLY UDRESULTS Page mR/Std. Month (30.4 days)+/- 2 Sigma 2 of 4 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, 01 6 6 8 016 9128/2016 1212 7120 16 -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"\ -5 1 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-5 7             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. M onth (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 Stat:ion
  - Emergen~y Plan TI..Ds.

34

TABLE 3-2 DIRECTRADIATIONAfEA SURMENfS - !!ECTOR QUARTERLY UDRE &JLTS Page mR/Std. Month (30.4 d.ays) +/- 2 Sigma 4 of4 First Quarter Second Quarter Third Quarter Fourth Qua rtet 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

Ta.bl!3-3 Air Partial!al! pl~ Gfo*~ :&!Ill Radioactivity ld4 nll"' teilm'l P!rii>d & J!!ifi,g Statioo 01 Sa.rim 02 I St! lion oo I Stttim oi I S~ioo I S~iaJ S titirn (11 I

01.-05/16 ll>iE..01 + 23 fE+OO L'.XlE+-01 1.448.;(() 1.1 i'E+-01 +/- 1.428+00 lU7E+OO +, 1 19E+OO Ll2E+o1 +. 1 .3&&oo B.B5E+-OO + l- 214B+OO LICE+ol +t- 23 IIB+OO 01.t12t115 .J!3E+OO + 2~-+<00 U!8E+0] - H iiE-+<00 *6..92:E+OO +!- 2:.53E+oo 6.9lE+OO 1 +, 1.43E-+OO Ui'E<-01 +. 1lr3E+OO 4.19&00 + 2 25&.-00 6.6EE+al +!- 1.42E+OO 01119.tlo 1 9.>E+Ol +. 2.9;E+00 1.34B+Ol - lilliiE-+<00 15 3E-+-Ol +.I- 1.74E+OO 1.19E+Ol +, 3.BE+OO L51E+-Ol +, 2 iSE+OO 1.06E+Ol + 1 03E+OO 15EE+'Ol +I- 2 79E+OO Ol f.l9.t16 9.37E-+<OO + l lEE.;(() L llE+Ol ,,. 1.42E-+<OO LOEE+-01 +t- 23 EE-+00 LC9E+-Ol +, 2.34B+OO 1.G7E+Ol + 236E+-OO L03E+Ol + 233B+OO 9.4iE+OO UBE+OO fil.tl6 1 45E+Ol + 29.fE+OO L34E+-Ol 2:.9CE+OO l.22E-+

E-+<X> 1..3 l E++Dl +t- 1.1%:+00 UOE+Ol + 1.21E+-OO 1.lPE+-01 ... 2 23&00 &ISBB!-00 + l 97E+OO l Ol!E-+-01 +.'- 1.l OE+-00 0'211 i'.1115 9. f!:l:E-+<00 +,. 1.3EE-KXI 1!..4DE+-OO +.<- l32E-+{XI &50E+OO +t- 23%:+00 9. ~00 +I- 2..42E+oo 9.75E+oo +,. .2 42E+-OO U lE+-00 +I- 2 '.b"E+OO I41E+OO +I- U 6E+OO 01a.3.t115 9.93E-+<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 +. 104E+OO Ll lE-+-01 + ,'- 102£+00 l OiE+ol +!- 2..99E+OO 03.-0'2 *16 l OlE-+-01 + 221E+OO 9..ffl'E+OO +.1- l.2CE+OO 9..34E+OO +t- 1.1iE+OO La:!Bl-01 +.I- 221E+oo l.03B+-Ol +, 2 22E+-OO l.06&.-01 +I- 2 14E+OO 1 01E+Ol +!- 1.:2:2E+OO 03-0!tll6 U EE+-Ol! +. 3.I<!E!+OO 9. i4E+OO +I- l liE+ID 9.17E+OO +t- 29iE+oo U l E+-01 +,t. 3.07&00 U 4E+-Ol + 295E+OO 9.96E+OO * .I.. 187E+-OO 1 2<!E!+Ol 3.0IE-+00 13f15Jli5 1 4!lE+-Ol +l 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 + 1 *@&00 1.34&-0l + .'- 1 i i5E+-OO l '.l$E+Ol 1.74E-+OO 13.(1:3,1115 1 15E+Ol + 1Jl<!E+OO U l E+iXl +!- 2 1iE+OO L1 iE+-01 +!- 2428-!00 9.90E+-OO + 2.3 1E+OO U 2E1-0l + 1..SOE+OO U BE+OO +1- 2 25E+OO ll(E+-01 +t- 2 4.3E-+OO 13.@ .tl6 1 13E+Ol + li~+<Xl 9.(b~OO +.1- 2:.53E-+<X> &9PE+oo +!- 1.#'E+OO L05E+Ol + 2 60E+OO 9.ilE+-00 1 + 257& 00 *i5.94E+-00 + 231!&.-0'.l lO>E+ol +t- 265E+OO .05.*115 1 05E+01 + 1.*ISlE.;(() !!.. 7*:+00 +.I- 1.52E+OO 555E+-OB +t- 1.3~;.()(I U 4B+Ol +, 1.75E+OO l..ll!B+-01 + 2 7iE+OO l..21E+-Ol +, 2 72E+OO l ::!SE+-01 'OE+-OO 04.113.*115 1 ~+01 + 1.4'.lE+OO Ul3B+OI +.I- H!E-+00 1 1.~-+-0 l +!- 1.41lE.;OB L14Bl-01 +" 1.43E+OO u i'E-1-0] + 2 40&00 l.llE+Ol +. 2 36E+OO 124E+-01 +i - 1.43B+OO *00.1115 l IOE+Ol + '.U fE+OO U 3E+Ol +.I- 1.5iE+OO L*DOE+Ol +t- 2 73E+OO U lB+Ol +. 25BE+OO U lB+-01 +. 2 7PB+OO LD0&.-01 +. 1. 73E+OO 13~+01 +!- 1.61E+OO .Ql5.1115 Hi3B+Ol + .~ l. ~+00 L5.3E+01 +I- 292E+OO l o67B+-Ol +t- li'!lB-+00 L29B+ID +. 1.74E+OO l S i'E+-01 +. 1 94B;-OO U l!E-+-01 +,. 1. i6BHOO 13 ~-+-01 +!- U3E+OO E.'.BE+OO +,. 1.4i!E+OO *15.2l!E+OO +l - l lliE+OO ,55~ +t- 1.3<1!-+00 7. 71E+OO +. 23 7E+OO 7.19Et-OO +. 234E+-OO U ISE+OO + 230E+OO R.55E+OO +I- 2..43E+OO 1 6'!E-t-Ol + 1.!tiB-+-01 7.31E+OO +.1- 1.1.SE-tOO 7..39B+OO +t- 1.15E-+OO *15.~E+OO + l.H>E+OO 554E-+00 +. 2 02E+-OO 45 1E+-OO + l 94EHXl 6.43E+OO +!- 2.0BE+OO l ©E+Ol +. 234E+OO 9.4i'E+OO +!- 1.N:l+OO !.OOE+OO +.I- U5E+oo 9.0lBt-00 +. 1.26Et00 U l E+Dl + 2 3!l:e+OO L07E+-Ol +, 231Et-OO l HE+OO +!- 1.13E-+OO 15!.!4.116 U ll!E+Ol +., 1.*61E+OO L 14B+Ol +.I- 2'64E+OO l.NE+<ll +!- 1. 71E+OO LOOE+Ol +. 1.5BB+OO LOlE+Ol + 257&00 l.07B+-Ol +. 2.*ffiE+-00 115E+Ol +!- 1.65E+OO 05.13 l lllli l 79B+Ol + l.95E+OO L4i'E+(l] +I- 1. 7iE+oo 1.14E+al +!- 3.1iE+oo l .43E+Ol + 1.75-E+OO I,152E-+<Ol + U5E+OO l..92E+-Ol + 3..0lE+<XI l 74E+-Ol - 1.92:E-+-OO !i.-07,1115 5l!E-+OO + 1.4EE-!iXl B..9l'E+-OO +I- 2.3 EE-t00 L03E-+<Dl +t- 1.4iE+oo L llB+-01 +,. l.53E+oo L07E-+-Ol +, 2~ 6.72E+OO + 2. 23E+OO l l llE+Ol +!- 1 6:2E+OO 1 OM 4.t16 LOOE+-01 + 1.4iE+OO UISB+-OI +!'- U ffl-+<:O l..39E1-0l +!- l:..i'2E+oo 1. ~l + ,. 280E+OO U 4E-+Ol + 2*~ 1-39&01 +. 2 71E+OO 1 54E+ol 1.BOE+OO O!i.1.21.'16 1 21E+Ol +, 155E+OO 9.'.XlB+OO +.I- 2.3 iE-+(() L04E1-0l +!- 1.4SE+oo l.44E+Ol +1 H BE-tOO l .13E-+-Ol + 2 56E+OO l.lOE+Ol +. 1 54B+OO lJl!E:+-01 - 1.<64:e+oo 015'28116 13~+01 +. 2 *1S4E+OO L5.3E+-Ol +!- 2.ISEE+OO L61B+-01 +I- 1.648+00 L46E+Ol +,. 2oi51E+OO L41B+Ol + 159E;<O l..21E+-Ol +, '24BB!-OO 11 ~+01 1.48E+OO 36 Table3-3 Air Particulate page Gross Beta Radioactivity 2 of [ 10-3 pCifm 31 Stafioo Sbticn Statioo Sb!fioo S!afioo Sb!fion 21 22 23 14** Ol A 05A 951E-!OO 2.3!lE+OO . 71E-;OO 2.31lE+OO 58E+oo 26IE+OO lOlE-i-01 + 231E+-OO lt51E+OO +!- 155E+<OO IU lE+oo +.I- 2.SJ:E+oo 6.56E+OO 2 42E+-<X) 8. 2:3E+OO 1.51E+<>O lU3E+OO +/- 1.53E+OO l02E+Ol + 1.t'ilE+OO 15.IB+Ol +.I- 1 'iEE+OO l.64E I +!- 2. &3E+OO 199E+Ol +!- 1 E+OO l tSllE+Ol L!!3E+OO 2.15E+-Ol - 3.o;'E+OO 1 S4E+Ol +. 92E+OO Ul.IB+-01 +.I- 1.34E-+OO 9Ji59E+Gtl +!- *2_ :29E+oo 9..1'1E+OO +l- 227E+4l0 103E+Ol 233E+OO U3E!-Ol +.I- 2.4!:E+OO lo;E+ol + 2.31E+OO 6,2!:E+OO +/- 1 l!lE+OO l.llE+-01 +!- 2. i'6E+oo U lE+OO H lE+OO l *63E+Ol +:~ 3.0fE+oo 1.24~1 +/- 2.&4E+ro 14iE+-Ol +. 9i'E+OO l.l1E+-Ol ._1. 1 llE-'"00 l.OlE+-01 +J- 2. fASE+OO llSE-+-01 113E+OO l 6!E-+-01 2J iE+OD 1.15&-0l 2 l*fE+OO U<E+-01 + 2 22E+OO

5. ,tfB+()() 214E+ro .!!.02:E+OO 2.~ 27E+OO 241E+OO 1 2<E+Ol +. ~+00 l.13E!-Ol - 24iE+ro 105E+Ol + 247Et-OO 5 IE+oo +I- 19.lE+<OO !!.60E+OO 2.87E+OO l E+-01 297E+-OO 12iE+ol +. 3.12E+oo 1.54&-0l +f- 3.1fE+OO 1 4l!E+Ol + 3. 2SE+OO 9.11E-+OO 2. 16E+oo Ul3E+Ol +!- 2 22.E+OO lllE+ol +I- 1 '.27E+-OO U IE-+iXI +. 2.B E+OO L34ErOl +J- 24CE+OO . lEE+OO + 1. l tSE+OO L4!E+Ol 100-E+oo L 6Ei-Ol 2.SSEr<Xl l30E+Ol l IOE+OO U iE+Ol +. l.9;'E+00 U DE+Ol 3.0EE-+<X> 1S2E+Ol +..:. 3. liE+OO 3 Si 6 U1E-t-Ol l i5E+oo 9.67E+OO l.54E B.M+OO +!- 2.SOE;-00 l08E+Ol 2.61E+OD U t5&01 +1- 2 iE+oo 1 22E+o1 +. 2@E+OO 3Q:3. 6 9.1iE+oo 12iE+OO 1.06£:-+-0l l.35E+oo B.i9E+OO +!- 2.24E+OO 11 iE+Ol +.i- 241E+OO l.OSErOl +!- 232 +00 103E+Ol +. 2.34Er00 3.119 6 8..4fE+OO +!- l fi+OO l. E l _QEi-00 L'l.OE+-01 +.t- 2 i'SE+ l OiE+Ol 2.62E+OO l.~1 2 l!E+OO llEE+Ol +, 2. i6E+OO

,0 5 6 1..lEE+Ol 2. i'6E-+OO l.07E 1 2.648-00 142E+ol +!- 2 l!4E+OO ll 5E+-Oli + 27CE+OO UDE;-01 +!- *i . £ -+00 1 2:3E+Ol + B E+OO 04.113.1115 1. iE-+-01 +.f- 2.35E+OO U.6E+Ol +J- l.40E;- 119E+Ol +t- 2.43E+OO 4.65E+OO 1 l!E+OO l.32E+Ol - 2 448-+00 ll.3E+-Ol +, 23!!E+OO .. 6 L53E+Ol 11>"1!+00 U 2E+Ol U SE+-OO li'5E-+-01 +i- H1E+OO 1 048+01 +. 3.13E+OO 200& 01 .- 3.02E+OO 1 ~+01 +. l.4'!!E+O 1 ~m+ro U l!:E+-01 2.!!lE+OO UilE+Ol :lg;"E+OO 1*63E+Ol +. 29iE+OO 1. 56E+-Ol 2:.Sm+OO 163.E+Ol + 296E+OO 6J!2E+OO +J- 1 31E+ro ,6SEH>O +I* 237Et-OO 6SE+OO 130E+OO B.34E+OO 242E+OO . 51E+OO l.42E+OO 4.o;'E+OO + 2 13E+OO 632+00 +.I- 100E+<OO 5.91E+OO +*- l.05E+OO iS.33E+OO +I- 20i'E+OO i98E+oo 2 05E+OO 8..&E 00 - 2..23E+OO i l!E+OO + 2 QiE+OO 8..958+00 2.25E+OO l.OlE+-01 +f* 2. 33E+-OO lOOE-+-01 +.f... B3E+OO 11g;i+01 + 2 448+00 9. i3E+OO +t- B IE+OO B.!!fE+oo + l.'.DE+-00 Ll2E-t-Ol +.I- U lE+OO Ll9E+-Ol 2.67E+-OO Hi6E-+-01 +!- 1 94E+OO US4E+m 1.92E+OO u m:+-01 +t- 1.6IE+<Xl LOfE+Ol +. 1.59E+OO U~+O l +!- 1 99E+OO L7EE+-Ol +!- 2.94E+OO 150E+ol +t- .2 i9&.-00 2 16'+01 3.l 3E+OO UcE * +I- 291!E+00 l iEi-01 + 29:3EHXJ L 3E+-Ol * /. 247E+OO U OE-+-01 2. t'ilE'-00 11 E+.01 151E+OO l 4iE+Ol 3E+OO LJ:2E +I. 1.51!E+00 lliE;-01 + 1.61E+OO Ll.5E+Ol +!- 2.5l!B+OO l.46E+-Ol +!- 2~ 1 26E+Ol +!- 2 t'ilE+OO l E<lE-!-01 +. 295E+OO U 6E+ +!- 2:..64E+OO 145E;-Ol + i5E+OO L14E+Ol +!- 2 51E+OO 9.54E+OO +.t- 2 39E+-OO l2:3E+Ol +!- 2 56E+OO 133E+Ol 2.62E+OO L llErOl - 2~+00 UiE+Ol + 203E+OO 1.048+01 +.I- 135E+OO UlE+-01 +!- 245E+OO Ul2E+Ol +!- 23BE+OO 16t!E+Ol +. +. 37 Table3-3 Air Particulate page Gross Beta Radioacti vity 3 of [l 0-3 pC m3] Si:;.ticti. Stolia'. 01 Llll'E-,-01 1-4."E...00 Ul!E--01 1.3 SE-+<X> U OE-01 +- 154£ -00 l..2tE : 1 +.- 1.51£+00 i .ll E 2-13 £ -CO UlE--01 LHE--01 41E-OO llE:E-01 +- li!E...00 L ;£.+-01 +- 2.37.E..,..f.() LE3E *- .74£ -CO L46E~:n LSE 1 1 '1E.: l 71£ 1 lSE-.<O 1 m:.* 1 +.- 1i3E-CO L52E-.-Ol 14E.""OO 2.11£-01 +- 3. E-00 115E l 1 3£-01 l.9C£ 2 13£-'-0l l li.E.-00 L~-,-01 ~. - L40E: 1. 75£..{X) USE: 1 +- 1.73£ -CO L47£-'-0l 1.5 7£"-0l U 4E.-+<X> U 3E+Ol +. - 1 tCiE.;{X) 1.43£+-01 +.- Lil ... - 71£+{X) 1.15£--01 +.- 1.52£ +<:0 L41E"-Ol +.- l.TiE+-00 Li'.'4E . l .L +oo 1 45£-.-01 +.- +- 165£ +00 13 7£+01 +.- 2~5 £ ' at. li.1 - 9. 72E ' T .- -..34E+<Xl 9.19£+00 +.- 1.30E+oo i35E-+-OO ..-.- L 1E. : 1 +- - 95£+{X) +- +.- l 31E+oo 1 02ET-Ol +.- al; 14.15 Ll7E...Ol 1 71£..;x) L43E+ol +.* 2.fil-00 UlE:+-Ol ll'..59£+00 14()£ +-01 ..... "'l"', - 2 ~1 £-<0 13 lE-!-01 +.- U5£: 1 3.();£"'00 L 72£+-01 - .- 3.00£ -'{.() 11 E l -. 1.13£ 1 +.- +. - 2 i!7£+00 ., 5£: 1 +,- 3.lSE L/5E' ... _ 2-18£.+00 2. 1£...{)l +- 2...01.E..,.,::O L1?6E+ol H 4E.+OO l.04E.-Ol +- 1.93£+00 L55E +-Ol .,.,. +- 2 li!E-'-{X) U8£ 1 +.- 1.85£ +-0:l HAE. . .,..__ 2 :!OE' "'l"' ,- - .- 1.95£ -'-{X) . 31E+-Ol ..... 2. 23£+00 2 ' 1£-01 +.- 1.95£-+<X> l~E+-01 ....- 2 51£+00 l.3$.E+-01 +.- 1.89£ "'00 L33E+-01 ... - 53E..*<X> +.- ~9£-'{.() u 6£+-01 .... - 2.6.5£+00 1..23£--01 2 "tE+OO llA.'1£+00 +, - 2 4()£+{X) 1.17£-+-01 +.- _53£ HiiE+oo +- 73£ -00 LS &01 l.6.5E+oo ~ '"£-,{)l l.9C£

L<;>;>E-+-01 ..... 1 55£ -00 1.7 5£"'-Dl +.- 1.5.5£ -00 2.51£.;{).'.) .,.. 1.f6E-OO iJ OE~ ~ 1£ 7 11£-00 ~'E;.<;() 54£--0:) 5..B:ll'E ... - 255£-<X> 3 .5£-'-00 2.39£ -CO 3 0 8£..{X) 3. 1£ "-00 L SE+-01 3.1<:£+00 U7E+ol 3.23f,+{X) L23£+ol ....- 1.15£--01 +.- 113£+00 UtEi-01 +.- 3.14£+00 1 . 19.15 L4DE+ol * .- 1.39E+OO L41l'E...Ol +.- 2.43£ +'.Xl Ll i E+-01 +.- 2.47£ l.07£+01 +.- 2..SlE+co U4E+ol +.- um 1 +- 133£+00 1.13£-+-0l +.- 2.13£ .;{X) 10.'15.15 9. 92£.+00 ..-.- 2.6::£. ' 1.45£...01 +.- 2.91£ +00 ~ -E * +.- 2.i 3E+OO L4tiE+-Ol +.- 2 5£ : LNE-+-01 185E &.l 7.E.- 00 +,- 154£ +00 1..52£+-0l +/- 2.9'i£.;{X)

11. .115 l :9E. 1 +.- HCE+oo 1.93£+-0l .,. - '.L93E...OO L5 SE +. - l.t:lE : U 8£ . 1 +- H lE l©E+Ol +* 18/E LS2E +.- 2 li!E+OO L4Cf.t-Ol +.- '.l. s;E.;{X) 11.15.lc Ui!E..-01 11£.+<X> l.llE. ....- 2.61£+00 L57E+-O1 2.81£

UtE .... 2 64E+CO UlE+-01 l..11E -52.E.+OO UtE+ol +.- L £ .;{X) 11711 - 2. E 1 - .- 3.4SE-OO ..... 3..51 £ ..-00 2.5 lE - .- 330C 3 . &ilE~ 2 klt:-i-01 1.74£ 141£+00 2.72£1-01 +.- 3. £ .;{X) 11 '29.l .34£"'- l - .- 3..3C£.-OO 337.E."'-~ 11/E *.- +.- 3.4SE+CO 21 E--01 +.- Ul E 2S9£.,..f.() l.90C+ol +.- 3 .<fil.~

U 07.15 UlE+-01 23 3£-00 ..... B4£ +00 Ll IE 1 - .... ~ 2 1£+00 . liE+OO +.* L l E-'-01 +.- 116£+00 l l lE+ol +.- 1.21£ +00 1114.15 L i5E : * .- +- Hi'.lE+OO Llll'E..--01 +.- l.&1E : l 72.E.-i-Ol L74E' +.- HlE...00 131£ . 1 ~. - 135£-+<:0 ll .lS Lfil E' * .- UIE +.- 3. 'E+OO L61E 1 +, - 3.11£+00 Ui.5£+-01 3.ll!E.+CO ll5SE+CO 132£: +.- l £ +00 1.51£+-0l 3.17£+00 u 7.1 234£ ' +.- 135£"-0l +.- 3.16£-00 l "SE 1..53£ : 1 +.'- 3-lE-<X> li17£ : 1 "' .~ L3E +- 195£+<:0 Ul!E. . 1 +. - 2.i!7£-'-{X) UE:iE-+-01 +.- 1.21£.;-0:) U 4E+ol +.- 1.ooE+co 134E. 1 +.- 1.roE+CO 1.43£+01 +- 2.7<:£.;{X) U4E+Ol + .~ 1.6tE-+<X> U4E+Ol +.- 25. E+OO L33E" 1 +r- 255£+00 38 Table3-3 Air Particulate page Gross Beta Ra.di oactivity of [ 10-3 pCi/m3] Station Stztion S talion S tation S tation 22 I 23 I 24** I OlA I O:SA .05116 9. l!l!E+<OO 23i'E+<OO LmE+Ol 243E+OO L31E+Ol 253E+oo B 'iE+Ol +. 263E+oo Ll lE-+-01 + 2.3l:E+<XI L41iE+'6] +. 2.J66E+OO 1 2116 UOE l +/- 244E+oo 9.7iE-'-OO +.1- 231E+oo 9.. i'PE+OO +t- 230E;;OO U<E+Ol + 25<E4<00 LHE +Ol + 23iE...OO L22E+-Ol + 145E+OO 9116 L54E!-Ol +.I- l E;;OO UilE+Ol - 2 ITE+OO L37E+Ol - 2B>E+OO L6EE+Ol + l iE+OO 1.51'.'E+Ol -. lASl!E+OO U9E+Cl + 1 l E+-00 0 . 6.116 L9;E+Ol l90E+(() 1.548+01 Hi!lE+OO 227E+Ol +l- lOiE+OO 2.3 5E+Ol + l I<E+.00 l.55E-+-Ol 21<E+OO L 6E+-Ol + 182E 08.-021115 .9i'El-OO +.i- 240E+OO .64E+oo +.I- 250E-+OO L56E-!-Ol +/- H 4E+oo U EE+Ol ... 3.00E+OO L~+Ol * ~+oo UlE+-01 + 2/0B'-00 0&!09.1115 Ul7E l +.i- 25&E+ro 1.1<E+Ol - lmE+oo l 4:l:E-+-Ol +!- 2 Ti'E+OO LHSE+Ol + .103E+OO L43E+Ol +. 2. EE+OO ].46E+-O] + 2.&0Bl-00 11 6 5_ b"'E!-!00 2 >E-+<E+-01 238:E+OO 8.. 4E+oo + 1 l'iE+OO 9.11E.;-00 2348~ _ IE + 211E+OO u~ . 1 +I- 2 77E-+<E+OO Ll&E-+-01 - 2 71E.;;(XI l .E-+01 + 2115E+OO lS<E+Ol 2.,mi+OO LSOE!-01 + 291E+OO L6i'E l +.I- 296E+oo U3E+Ol - l E+OO lGIB+Ol ll7E+oo 1 fE+iOl +. l 13E+oo l.OOE-+-01 3.1 iE"'-00 l JISIB-01 +. 296E+OO Ll!lSE+-01 +.I- 284E+oo 194E+Ol 2SEE+OO LE3E-!-Ol - +.t- 'l l!2E-!<OO 264E+i01 +. 124E+oo 1-7~+01 + 2.&CE+oo 1Jl59& 0 l +. L9.l:B l +.I- 2 6i'E+OO l ll!E+el - 2 S3E+OO .251SE-+-01 299E+.OO 29fB+i01 +. l l<E-+<O 26>'E+Ol 3.05E+oo 15.JE+o l +. 1-34E+m H4E-+(() U SE+Ol +!- HlE-+O> LSlIB-+-01 l 19E+OO 1.5 t!E+Ol + 2 EE-+<<> l-43E+Ol 2.ilE+OO LlEE+-01 + 253 L@Ef-01 203E+OO U 3E+Ol +!- @E+(X) LG -+-01 251E-+<OO 2.fl!E+Ol + 3. l 2E-+<OO l.91E+Ol +I- 74E-l((I L54E+<Ol + 255E+OO 7.0SE +!- 2 *64E+OO 5.J~2E+OO +!- 256E-HOO a2EE-t<OO +I- lroE-+00 9.l tE-+00 + 2 l!E-+00 6..14E+OD + 2.SiE+OO IS.t53E+OO + 1AS2E+OO 1Ml!ll5 L5i'E+Ol +!- 3...30E+ro L1 fE+-01 "'!- la!:E+oo LSlIB+Ol l.32E-+OO U 4E+i01 + l l EE+OO l.11E+Ol -. 3.HE +OO l..2:3E+-Ol + 3.12.E+OO 1M9.r16 8..lEB-00 +.I- 21 E+ro U l!E+-01 +!- l:2JSE+OO 233E-!-01 +.1- 2l!SE+OO U al:+Ol +. 115E+OO 1-63E+Ol + 252E+OO h53Et-01 +. 251Et00 1M5!11S -i'.lE+-00 - 1 *68E+ro 9,&Q;J;+oo +!- 2 5'E-+iXl L27E-!-01 +.I- .2 ~+00 L14E+Ol +. 2&3E+OO l..2:3E+Ol +/.. &lE+OO L43Ei-Ol +. 293 1Ut21lt5 L 34E+-OJ. HlE-+<<I U '1E+<Dl +!- 26!E+OO L@E+Ol +t- 2 7i'E-+<OO 1-4IE+Ol + 1<1%E+OO L41!E+Ol + 2.64E-l((I L .2E-+-Ol + 1 IIBt-00 11 5 t5 8.. 91Et-00 243E+OO U EE-i-01 - 159E+OO L37E+Ol +!- 2 TIE+OO 1. 7211:-+-0l + l~+oo l.l'iE+Ol + 2.*6fE+OO Ll4E+Ol + :l.>1&00 ll.l.2'.!/16 2.SiE+ l - 1 33E+OO 143E-+-Ol +!- 3.:268+00 129E-+-Ol +.I- lXIE+OO 2.&EE+Ol +. 3.4 iE-+00 263E+Ol .. 3..3 l!E+iXI 2.02E+-01 3.01Et-OO 11.1.29. 6 2.BIE!-01 - 141E-+OO 1.Zl!E-i-01 - 1 07ETOO 2 22E+Ol - 114E+OO 21 lE+Ol +. l ll!E+oo L41!E+Ol 2.ltiE+<<I U 6E+o] +.l* 3.27800 12-07 IS LllE+Ol 222E+OO -4iE+OO +!- 212E+OO L29E-Hlll 132E-+<OO U 'IB+Ol + 13 ffi+OO U IE+Ol +!- 2..33E+OO U 9E+-01 + 2.26E+OO 12114 IS L *~ - 2 77E+OO Ll EE+Ol +!- 24EE+OO 101E+Ol - 295E+.OO LnB+Ol + 1 ~+00 lAEE+Ol +.'- 165E+OO l53Et-0] + 269Et00 12.00!liS u m1. 1 +J- 11!7E+OO 8..91E+OO +l- 215E-+iXl Ll 7E+Ol - 293E.;;(XI Lit!B+Ol + 124E+OO U EE+Ol + l.93E+OO U 6E+-Ot + 3.0'lE+OO 12'2 IS L *61E!-01 2 i9E+OO L~+O l
1- 1 Bl:E-+00 1 E+Ol - 1 l E+OO 111E-+-Ol + 3.0ilE+<Xl L6l:E+Ol + l.&fE+<Xl 145E+Ol + 3.llIBt-00 MEAN 124E+Ol - HOE+oo l..2:3E+Ol + *61IE+OO U!tE+--01 +!- 2'61lE+OO L53E+Ol +!- 2 i6E-+-OO L-4a:i-l-Ol .... '2.i'OE!-00 Ul!E-+-01 . - 261!E+OO Mean -All Indicator Locations U3E+Ol - :2.. CE+OO
** Con1ro1 Station 39 Tab1e3-4 Airborne Iodine page I-131 l of [to-3 pCi/m3] ~ 'Statim 'S t=tim SI! tioll Stotim St=tion S llllicn S t=tim & ;llin;g I 01 I 01 I Q3 I 04 I ffi I 00 I UT I 01.GSJllS < l..l2E-t-Ol < 1.lUB+Ol < 1.l!tE+-01 < 2-&SE+-01 < 1 l!SE+Ol < 142E+Ol < 2 41.E+-Ol l.tl 2tl.IS < LOOE<!-01 < 2 64E+Ol < 2 7iE-+-Ol < 2 64E~ l < 164EHll < 7.M+OO < 206.E+-Ol 01119.1115 < 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 01.QP/16 < 3.4fE-+-Ol < 3.45E+Ol < 3.5<E+Ol < U3E+-Ol < l47EHll < 3.35EH>l < 333E+-01 02filtl.6 < LICE+<lll < .1 J!3E+Ol < 2J!2E+Ol < 2.&3E+Ol < l l!3E+Ol < 3.!l:E+Ol < 3.B1E--Ol 02/lo.tJ.6 < l .93E-+-01 < 455E+Ol < 4.3~+01 < 4.45E+ol < 4.32Bl-01 < 1 95B+-01 < l96Bt-Ol 02.tl 7116 < 4.92£.;(() < l.11E-+-Ol < 1.1~+01 < U5E+-Ol < L 13E+Ol 02/16 < 4.21E+Ol < 4.11E+Ol < 4.21E+ol < 4.21£--01 < IS. lllEt-()1 < IS. i&E+-01 < 3..SOE+-01 03Al81115 < UfE+Ol < 3.44E+Ol < 3.3iE+ol < 3.43E+Ol < 3..40E+-01 < l!!OE+Ol < 3.BlE+-01 031151115 < 23 lE+Ol < l.19E+Ol < 23(£+-01 < 2.30Ef-Ol < 130E+Ol < .1 l7E+Ol < 1.l 7E+Ol 03.'231115 < IA5lE+Ol < L6lE+Ol < l.61E+Ol < USlE+Ol < L~+Ol < L~+Ol < L90E-'-Ol 03.'29.1115 < 151E-+<01 < J J!AE-+-01 < 3.i l!E+Ol < 3.78E-l-O] < 11!3Ei--Ol < 4.4EE+Ol < 4.4e:E-l-Ol 04.-0S.tl.6 < 153E-+-Ol < 2J!5E+Ol < 2.92E+-Ol < 2.94Ef-Ol < l~l < 3.9.lE!-01 < 3.92E+-Ol 041131115 < 4.35E-t-Ol < 4.42E+Ol < 45 lE+Dl < 4.45E+Ol < iS.lOE!-01 < 15.~l < 6.07E+-Ol 04/lM!i < 1.46!:'+'01 < 3.45E+Ol < 3.45E+Ol < 3..50:&.<ll < 145.E+Ol < 1 *64:&01 < 3,64E+Ol 04/161115 < 4.2iE-+-Ol < 4.44E+Ol < 4.43E+Ol < 4.37E+Ol < 4.~B-01 < 4.Qi.E+Ol < 4.95E!-Ol 05,03!115 < 4.0 lE-+-01 < 4.0 lE+Ol < 4.00E+Ol < 4.0lE+Ol < i OOE+Ol < i OOE+Ol < 5.00E+Ol < 4,15JE+01 < 4.63E+-Ol < 4J63E+Ol < l..94E--Ol < 4.63E+Ol < L4PE+Ol < l.49E+Ol < UllE+Ol < U lE+-01 < U lE+Ol < UOE+-01 < 7.0lE+OO < 103E+Ol < 2.03E+-Ol < 7_,fiJE-liX) < l.911E+Ol < l.9ffi+Ol < l.96E+Ol < L915El-Ol < 231&.-0l < 'l JlE+Ol < 35 !!E-l-Ol < 35 8E+Ol < U~+Ol < 35 8E+-Ol < 3.5~1 < *6.llE!-01 < i5-81E+Ol < 2 6!E-+ID < ,6_4iE+Ol < 15.4iE+Ol < 65 3E+0] < 6.47E+m < *6. 76.E+--01 < 6.76E+Ol < 2.35E+Ol < 6.25E+Ol < *6.2'iE+Ol < *l!U9E.;-01 < 6.25 < i 65E+Ol < 5.65E+Ol < 2-SlE+Ol < 6.44E+Ol < *6.4fE+Ol < 6.44E+-Ol < *6.44: < i97E+Ol < 5..97E'-Ol 06'2&116 < 5Jl54ETOO < U lE+Ol < l.2tE+01 < l.19E+Ol < L30E., < L41E+-Ol < L42B-Ol 40 Table3-4 Airbome Iodine page I-131 2 of 4 [ 10-3 pCih:n 3] Period S b tfo11 Stman Stnca Station Station Stman 21 22 23 24"* OlA 05A < 242E+ol < 2.42Et--01 < 2SOE+Cl < 2.4m+Ol < 252E+-01: < ~01 < lOiE+-01 < 2.CISE.;.fil < 207& 1 < 253E+Ol < 2528+01 < 2.S3E+Ol
01. 9.<16 < 120E+ol < 3.XIE+Cl < l51E+01 < H~+o l < 351E-+-Ol < 3Al!E+ 1 01.@ . IS < 134E+ol < 3.34E+Cl < 3..iPE+Ol < U3E+ol < 3Jt.JE+Ol < 3.6l!E+ 1 O"lh IS < 4.55E+Ol < 3JllE.;.fil < 137E+()l < 331E+Ol < BiE+Ol < 3.3i'E+Ol O"l/10. IS < 1 91E+Ol < 3.91E+Ol < 2 71E+Cl < 2,,ISQE+-01 < 2illE+Ol < l. i3E+Ol 6 < lllE+ol < LUE ~ < l21E+Cl < l..21E+Ol -+-0l < 4.l '!lE-+-01 < 4. 19E+Ol
< 1 - E+Ol < 3. 75E 1 < 106E+()l < 2.95E+Ol < 3.0EE+Ol < 2.99E+Ol < 2 17E+Ol < 2. l i'E+Ol < 241E+Cl < 241E+Ol < 2-41E-+-Ol < l.41E+Ol < 1 915E+Ol < 9.04E+OO < 1 67E+Ol < lJl5iE-+-Ol < L6iE+ol < L6i'E+Ol < 4.48E+ol < 4.48Er01 < 4. lOE+- l < 4.~+0 1 < 4.13E+Ol < 4. lOE+Ol < 193E"'°l < 3.9.lE: 1 < 3..J5E+Ol < 3.1tE+ol < 3.2JE+Ol < 3.25E+Ol < *6. 1.SE"'°l < 6. ~01 < 6. , E*Ol < 6..9JE.;-01 < 2a<E+Ol < 6.83E+Ol < lmE+Ol < HiS.E+Ol < 191E-Ol < 4.15E+ol < 4.0tE+ol < HlE+-01 04.l'.2iS.116 < 4.93E-+-Ol < l.'.l5E+fil < 4. ll!E+Ol < 4J <tE+Ol < 4.0JE+Ol < 4. BE+Ol 05~3 Ci < 5.0l E+-01 < LEi'E+Ol < 4.1!1EHll < 4.E2E+Ol < 4.91!8-+-0l < 4. lnE+-01 05.,i].()116 < l fi"'°l < L'WE+Ol < 200E+Ol < 2.0IE+Ol < 2.0IE-+-01 < 201E+-Ol IS < 203E-+-Ol < 2ffiE+Ol < 194E+Ol < 1..948+01 < 1..948+01 < L93E--Ol 6 < 230E+ol < 230E+Ol < 3.. - E+Ol < 3_ 3E;-01 < 3.74B+Dl < 3. i4E 1 6 < 6.00E-+-01 < 6. 00E+ 1 < i38E+Ol -JEE+Ol IS < Q. i'IIB+Ol < 6. 'ilSE!-01 < *6.02E+Ol < 6.0lE+Ol < 6.l'!lE-t-01 < 6.mE+Ol < 5.67E+ol < 5.6i'E+Ol < 5.~ < 5.Z'E+Ol < 5.HE+Ol < 5.1iE+Ol < 5. !lQE-+-01 < 5.@E+()l < H lE < l.S3E+Ol < .2.ElE-t-01 < 2!0.E+Ol OM!!. 6 < U PE+ol < U9E+Ol < 2 99E 1 < l lllE-+-01 < 3.028-+-0l < 94:e+-01 *"' Control Station 41 Table3-4 Airborne Iodine page I-131 3 of 4 [to*3 pCilm 3)
R!rii:d Statm Statim 'Stalim Staticn Station Station Statioo
~.g I 01 L m I 03 I ~ I 0:> I os I UT I 07.IOi/16 < i 1DE+Ol < 5.8DE+-Ol < *6. 13E+-Ol < 5..92H+Ol < 4.liE+-01 < 4..2fE+ol < 4.14E+Ol Oi'.112116 < B 2E-t-Ol < S34E+-01 < 5.34E+-Gl < 5J4E+Ol < 5.1'iE+Ol < 5.l 'iE-+-01 < 5.l 'i'E-t-01 0711~ 1 6 < 2 l &E-+-Ol < 5.04E+-Ol < 5Jl7E+Ol < 5.04E+Ol < 5.G<IE+Ol < 5.BlE+-01 < 5J!IE+Ol 071161liS < L63B-+-Ol < U5E+ol < 3. 1!3E+Ol < U5E+Ol < U 5E+Ol < 5.HE+-01 < 5.lOE+Ol 0&.'02fl 6 < 4-23E+Ol < US4E+-01 < 4.23E+-01 < 4..23E+Ol < 4..23E+Ol < 4J!1E+Ol < 4.82E+Ol (lg.@116 < 7..07E+OO < Llt3E+-Ol < L.1!3E+-01 < L83E+Ol < U .3E+Ol < 2..45E+Ol < l.45E+Ol O&ili'.116 < L'.:\4E+-01 < 3.17E+-Ol < 3.F7E+Ol < 3.l iE-+-01 < 3.l iE+Ol < 3.0IE+Ol < 3.00E+-01 OW2416 < 2. 15E-+-01 < 5_1.15E+-Ol < 5. 15Bl-01 < 5-l EE+Ol < H fE+Ol < 4..93E+Ol < 4..93E'-Ol O&l.30!16 < .3..26B-+-Ol < 6..2*6E'+Ol < ,IS_l)Bt-01 < 6.14!-+-01 < 6.2!tE+Ol < 5.71lE+OI < 5.7lE+-01 '05'16 < 491E-!-01 < 4..91Ei-Ol < 4.91E+<ll < 4..91E+Ol < 4J6iE+Ol < 4.6iE+Ol < 4.67E+Ol Oll!14116 < 9.39E+OO < 239E+Ol < l.35E+<ll < 2..3iE+Ol < 23-tE+Ol < 3J.3E+Ol < 3J3E+-01 0~1 6 < L 71E+Ol < 4.os:E+-01 < < 4.0iE+Ol < 4.0EE+Ol < 5.UE+Ol < 5.lOE+-01 12&116 < H lOE+Ol < 4.51E+Ol < < 4.4!iE+O l < 4.52E+Ol < 4.1.3E+Ol < 4..23E+Ol 10"04116 < .3..96E+-01 < 3..PPE;-01 < < 4.05E+Ol < 4.13E+Ol < 4.l lE.;-01 < 4. l lE-'-01 10'11116 < 4- 19E-!-Ol < 4.!0E+-01 < < 4J!$E+Ol < 4..&3E+Ol < 4.H E+-01 < 4.l 4E+<ll 10'lg'l 6 < L21E+Ol < 1.S5E+Ol < l.1!3E+Ol < 1.83E+Ol < l.S5E+Ol < l.41E.;-01 < l.41E+Ol 10'1il16 < i 52E-<-Ol < 5.42E+-Ol < 5. l!SE+Ol < 553E+Ol < 451E+ol < 4.5"1E+Ol < 4.53B+-01 lll!Wl l5 < L45E+-Ol < 3.3/E!-01 < 3.32:E+01 < 3..2.""8-+-01 < 3JiE+ol < 3.B4E+-OI < 3.&4E+Ol < 2 33E-+-01 < J.56E+Ol < 3.55E+-Ol < 355E+Ol < l Sl!E+Ol < l.Bm+Ol < l.S&E+-01 < L57E+-01 < H2E+-01 < 3. 71E+-01 < 3.nE+Ol < 3.72E+Ol < 3JlE+Ol < 3J l E+-01 115 < 423E+Ol < 4..23E+-01 < 4.!IB+-01 < 4..24!+01 < 4.43E+Ol < 4.43E.;-01 < 4.43E+-Ol < Ll2E+-Ol < l.66E+Ol < l.,67E+-()1 < 2'61E+Ol < l.61E+Ol < l.51E+Ol < l.52:E+Ol < 9- BISB+OO < 236E+-Ol < l.36E+-01 < 2..3*tE:+Ol < 231E+Ol < 1.24!+01 < 1.24E-+Ol < .3..96E+Ol < 3..94E'-01 < 3 .~E+Ol < l .61E+Ol < 3..94E+ol < 3.l lE+Ol < 3.llE+-01 < Ui'E+Ol < 3J4E-'-01 < 3.22E!-Ol < 3J<E+Ol < 3JIE+Ol 3.4fE+Ol < 3.44E+Ol M21 l.51E+Ol +, .3..35E+Ol +, 3J5E+-Ol +!- 336&.-01 3J5E+-Ol +. 4.11E+Ol 4..20E+-Ol 42 Table3-4 Airborne Iodine page I-131 4 of [1 0-3 pCi/m3] Period Sbfian Sfatian Sb.tim Station Statian Sb.lion B:ufui.g I .2l I 22 I 23 I 24'** I Ol A 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 < lOOE+-01 < 4.47E-t-Ol < 4. 4llE+-Ol < 4.4iE+-Ol < 4.49E+-Ol 21115 < 4..!!:IB+(IJ. < 4.l!:l:E-+01 < 4.I7E+Ol < 4. l l!E+Ol < 4.liE+Ol < 4.l 7E4-0l Ol!.OP/115 < 2 46E+-01 < 2 46E-t-Ol < 2~+01 < l OIE+-01 < 29EE+o1 < 3.0IE+ol Ol!.1171115 < 3.00E+-01 < 3.00E-t-01 < 2 l!OE-t-01 < 2 7~+0] < 2JNE +-Ol < 2.79E+-Ol Ol!.1141115 < 4.93E+-Ol < 4.93E+-01 < 14/E-+-01 < 14EE+Ol < 3-4SE+m < 3.4BE+-Ol Ol!.13M 15 < i 77E+-01 < i 77E+-01 < 4.91E+Ol < 4. &llE+-01 < 4..93E.;-Ol < 4.&8E+Ol 09.06fl6 < 4.0iE+-01 < L23E+-01 < 117E+Ol < 11 iE+-01 < 3-liE+ol < 3.17E+Ol 09.1141115 < BOE+-01 < 3.31E+-01 < lOOE+ol < l 7EE+ol < 3.9JE+-Ol < 3.&3Bl-Ol 09ll M 6 < i lOE+-01 < i C9E+-Ol < i51E-t-Ol < i53E+<ll < 55IE+Ol < 55 2E+Ol 09.Ql!.116 < 4.23E+-01 < 4.22E+-Ol < 4.*fil E-t-01 < 4.*62E+<ll < 4JIS4E+01 < 4,62E+Ol 10.-04.116 < 4.llE+-01 < 154E+ol < l 55E+-01 < l53E+Ol < U iE+Ol < 3..54E+Ol 10.llltliS < 4.13E+Ol < 4.b""E+ol < 1 1!9E+ol < l&llE+Ol < 3.ZIEt-01 < 3.B9E+Ol 1M 9J1.15 < :lSOE+-01 < 2 43E-t-Ol < l )l)E+ol < lll!E.;-01 < 3..2'.lE+Ol < 3.10E+Ol Ul.l.l51115 < 4.64E+-01 < i&SE+-01 < 1315E+Dl < i91E.;-01 < 5.75E+-01 < 5.76E+Ol Il.02'1115 < 1 79FH-01 < 17PB+Ol < 2 ,l!fill+-01 < 2 *6iE-i-Ol < 2'61E-+-01 < 2.68E+Ol llll 5116 < :l lfiE+-01 < lli'E+Ol < 1 03E+Ol < 102E+<ll < 3.0E+-01 < 3.02:E-+-Ol lli22Jl6 < 1 31E+-Ol < 131E-'-Ol < 135E+ol < l35E+Ol < 3.35E+Ol < 3.35B-Ol 111.291115 < 4.-0E+Ol < L93E+-Ol < H l E+-01 < 4. 5g£.;-01 < 4J6IE+Ol < 4.151E+Ol 12071115 < 2 52E+Ol < 252E+ol < 231E+Ol < 13 1E+fil < 23 1E+ol < 231E+<ll 12114.116 < 2 24E+Ol < 224E+Ol < 291E+Dl < :l92E+Ol: < 291E+-01 < 292Bt-Ol 12'20116 < 3. llE+Ol < lllE+Ol < 4.17E+ol < 4.HE+-01 < 4.liE+-01 < 4.14E+-Ol 12Q7116 < 3.40E+Ol < 138E+Ol < 163E+Ol < 153E+Ol < 3.6iE+-Ol < 35 8E+Ol MB.l\N +I- 4.21E+ol - 4.21E+Ol +I- l f!ra+-01 - H llE+Ol 33"-E+ol - 3.68E4-0l Imica1D! Lca*ti.cns M'21 +I- 35 3E+<ll ** Control Station 43 Tabl e3- 5 Airborne Particulate page Gamma Spectra l of2 [10 ~ pCilm>) s-.pLm_g Quarter i Location B!-i C!-134" Q...13 .. 01 l.3E+<a2 +J- ll<E-l-01 < LliSE-+<00 < !1..468-0l OlA U!!Et-02 2.i EE+Ol 7Et00 }_19E+{Yl +!- 2. EE+Ol < L66E-+<OO < l.22B+OO 05 UlE;-02: 402Elt-01 < 19i'B!"OO < L56E+OO 05A U llB!-00: + 2.4mt-Ol 9.17E-Ol < Ll7E+OO IS l.22B+ID: l ll!E+Ol < L42E+OO < U EE+OO 07 IU!9E+ill + .3.l'.lE+Ol +. 9.32EOl < !.:26E+OO 21 LO'lE+ol + 35SE+Ol < 1.26E+OO < L49E+<O 22 9.61E+ol +. 25iE+Ol < L23E-+<OO < LC6E+oo 23 8.46E+-Ol +. L9iE+Ol < LltSE+-00 < LOSE+(() 24"" U 4E+Q2 .. 2.4(£+-0l < L40E-+<OO < 9.@B-01 Sowpli.ll_g Quarter 2 Locaticn B!-i Cs-134* Cs- 13
Sr-&9 Sr-90 01 L42E+02 25EE-+<Ol < L23E+OO < 8. 5B-Ol < 5.*6BE+<Xl < L93E-!OO OlA l.52E-+Ol +. 2.i <E+-01 < Ll9E+OO < L20E+OO < R 3E+OO < il lE-!00 02 U lE-+-02: + 291E+-Ol < l-26E+<OO < UOEtOO < 5.71E+-OO < 2R<E-+OO 03 ]. 7lE+-O:l: +!- lOIE+Ol < l.16B+OO < IJIEtOO < SZE+OO < 24g:;;;oo 04 1.42El-02 + 26$1-0l < 8...@B-01 < UlE+OO < 4..21!E+()() < 2 03Ei00 05 l.50E+<n +. 23!;E+Ol < LllE+OO < .S3B-Ol < 4.R3E+<XI < 24:iE OSA l.49E+-Ot.2 2.IStE--01 < L~ < 32B-Ol < &J4E-+iXl < 3.1 ~-!00 IS Lm"E+m + 2 fE+.01 < L29E+OO < UOE+OO < 15.. e oo < &l!E+OO 0 LiBE-n<ll +!- lOEE-+-01 < 1.50E-+<OO < Ul!E;.00 < 4.65E!(() < 255E+OO 21 l.50E-n<ll +. 2.4EE-+-Ol < Ll9E+OO < LCPE+<Xl < 4.738+00 < L92E-+00 22 L42E+m +~ 2.21E. 1 < l.GiE+OO < L02E+<Xl < 4. J!E+(X) < LlnE+OO 23 L4iEt-02 ... 2.nE+-01 < Ll3E+OO < UllE+OO < S.4~ < 26!1E+OO 24.... '.l:.a5Et-02 +!- 1 tE+ol < l.33E+OO < LHIB+OO < 4.R!E+OO < 21SfE-tOO

ll.D id!!!irtifii!d in th! OD CM
CM.i!rol Station 44
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$-01 02 Ll3E+oo: +!- lftE+Ol < 939&-01 < U tE-+00 03 l.54E!+-<12 HiE+-01 < U EE+OO < l42E+OO 04 l..liE+02 ~(.. 245E+-01 < U 6E+OO < ..OfE-01 05 l .6f!e;<l2 +!- ll!'iE+Ol < U 6E+OO < Li l!E-+00 0 5A 15.SE-+<D: 3.42E+Ol < l..13E-+OO < l5'iE.;00 06 Ll4E+c!2 '24!E+Ol < l.53E-+OO < USE..00 07 U 3E+oo 1 448+0} < l.JSE+OO < DllE+OO 21 LO'EE-+<00 15'iE+Ol < 9.llSB-01 < LOIE+OO 22 l.l<E+m 1348+01 < L44Et00 < U3Ei00 23 UiE+oo +,l . 1 4tE+Ol < l.58Et<OO < U5E+OO 2 4++ U i3E+<l2 +.I- HiE+ol < Ll.5Er00 < l3 1lE-tOO MBAN SznpHnr; ME.AN Quarte.r 4 Loclltioo Be- Q..134* Q..131" Be-01 l-1$-02 +.I- lC<E+Ol < 8..95E-01 < 9. m-01 l32E-f02 +/- 235E+Ol OlA L0(!&.-02 19:IB+ol < U i3E+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 < Ll fE-!-00 144E.;ol +/- 1.94E+Ol 0 5A 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 ;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
Table 3-6 Sofl page ![pOi/ lcg) 1 of 1 I I I I Samp.le ~ 9-89 S-9J ~ Cs-134 Date Acivity Core 2 Sigma MOC Acivity Core 2Sjgma MOC Acivity Co.r e 2 Sigma MOC Aciv ity Cone 2Sigma MOC 7/12116 0 < 6.749<12 < 3 .:368-01 1.60E'4-04 +/- 217Et<l3 < 6 .91E+01 7/12116- 02 < .5.38E+02 < 2 .00E!-01 S.73E+C3 +/- 221E+03 < S.91.E+01 7112116 ()3 *< 7.20902 < 4.06.E+01: 6.04E-+i03 +I- 1.24E+03 < 7.94E+01 7/12116 04 *< 6.5 58!-02 < 2 .448<01 4.00E-+03 +/- 1.29E+03 < 8 .88E+O 7112116* ()5 < 6.SOE+02 < 2 .92E+<l1 1.10E'4-04 +I- 1.93Ef(l3 < 7.45E-+(11 7112116 C5A < 5.4SE+02 < 2 .70E+01 1.41E+<04 +/- 1.S8Ef(l3 < 8 .75E+Cl1 7112116 06 < 5.348+02 < 2 .488-01 1.0SE"l-04 +I- 1.56903 < 1.-42E+C2 7/12116 ()7 < 4.928t02 < 2 .228-01 1.:22E +C4 +I- 1.63.8+03 < 9 .35E+01 7112/16 21 < 7.62E+02 < 3.46E+01 1.08E-+ill4 +I- 220903 < 1.039<02 7112/16 22 < 6.42E+02 *< 3.028-01 1.00E+04 +I- 232903 < 9 .23E+<l 7112116 23 *< 6.24E+02 < 4.1'0E+01* 3.24E+<04 +/- 26281()3 *< 9 .1'8E+01 7112116 2~ < 3.96E+02 < 2 .25E+01 3.0ee+o4 +/- 24381()3 < 7.61E+0*1 I I I I Sample station C5-137 Ra-2213 Th-228 ~232 Date Aciv ity Core 2Sgma MDC Aciv ity Core 2Sjgma MOC Acivity Cone 2 Sigma MOC Aciv ity Co.r e 2Sigma MOC 7112116 ()1 < S.S:3Ei<l1 3.89E+o3 -+I- 3 .77E+03 9.:24E+C2 +I- 1.55Bt-02 S.S2E+02 *+I- 2 .88 E+02 7112116 02 4.59E+C2 +I- 1.52Et112 < 3.21 E+03 5.0.3E+C2 +/- 205E+02 *< 7.998'-02 7112116 03 1.78E+o2 +I- 1.08&02 < 1.71E+03 6.30E+-02 +I- 1.24Et<J2 5.1~ -ti- 3 .00E+0.2 7112116 04 1.77E+o2 +I- 9.70E+01 250E+o3 +I- 2 .43E+03 6.4e8-02 +I- 280Etill2 < 5 .31E+02 7112116 05 4. 4~E-*'02 +I- 1.24 9-02 < 2.10E+03 4.S7E+C2 +I- 1.44E't02 7.31 E+o2 Tl- 3 .10 E+0:2 7112116 05A < 9.94E+01* 5.0SE-+03 +I- 2.24E+03 3.:3eE+03 +l - 205.Etill2 3.4<f!E+03 c+f- 3 ..559<0:2 7112116 06 6.<<!E+-02 +!- 1.408!-02 < 2 .518!-03 7.91E+C2 +I- 2108!-02 9.0.0E+02 +f- 1.!99E+02 7112116 07 < 1.319'02 3. 4~+03 -+!- 2 .818!-03 257E+o3 +/- 2088!-02 24eE+o3 -+I- 2 .778-02 7/12116 21 < 1.52&02 3.S2E+o3 +I- 2 .27E+03 290E+-03 +I- 3.03E+(]2 249E+03 +I- 4.418-02 7112116 22 < 1.13B-02 5.51 E+o3 +I- 2 ..55E+03 3.6~+()3 +/- 246E+o2 3. 11E+03 +I- 4.04E+02 7112116 23 26!3E+-02 +I- 7.41E+01 24CE+o3 +I- 1.57E+03 1.6 2E+o3 +I- ,..54'6 t02 1.41E+03 c+f- 2 .009-02 7112116 2~ < S.29E+01 < 1.82E+03 209E+o2 +I- 1:.236t02 < 4.04902 ~mol Statio 46 Table3-7 Precipitation Gross Bet!. [pCitL] page t .o f 2 S<ampl:il!g D~ Gross Beu I H-3 I Ra i.!iall ( UI:h!s)
01. ....7l16 >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 30.1 16 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 Precipitati on p.l~i! Gamma Spectra :2of2 [pCi/L] SBi:;lill:g l<<alioo I ~ !.{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-I3 7 OU 6'281ll5 < 3..£2E..00 < 7.se<O < 4.54E+OO < L4JE+OO 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.i rn 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
M ilk 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" 01119 116 l .40E+03 +. 6.73E+Ol '[*) {*] < 8.14E+O l < 2J4E,i.()0 < 2. l E+OO < l.23E+Ol < 3.6 1E.;-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 015.121 1115 l .46E+03 +.~ 2 J9E...-OZ < 4.415E...OO < l .09E...00 < .22E-Ol < 557E.;-00 < *l5.60B-+OO < 3.42E+O l < 1J4E+O l 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.fl 6 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 + 11 9E+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!l 6 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-13 1* Cs-134* C&-137" 13 6 l .45E+03 +I- l. ilE-+02 554E-t03 < 3. '9E'!O l < l .96E+Ol < ....Ol E+Ol 14B l .44E-+-03 +I- 3. 6E-+02 i.41E-T!l3 +.I- Al3E-+(!fl < l.IOE-1{) 1 < 333E+Ol < 3.Bl E-+-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-i0 1 < 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 .i 4E+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 04.1 13 6 8i66E-+<ltl + l- l.54E-+<02 6!69B-!03 +.I, - 3 .48E+Ol < 3.6JE-i0 1 < l .55E-o-Ol < l .64E+Ol 05t l 0116 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 .1 5E-!-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 4.0 lE"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 .- 5 19E"'l-O:.. < 21 5E-!O l < 2.94E+Ol < 3. E-+-01 1 11 6 3 1 6E-+-03 +I- 4. 2E+Ct2 5.2 8E'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-i0 1 < l .Tira+ol < U4E+Ol Mean 2 11E+03 +I- 324E4i00: 5.46E-!03 +.'- 5.55E4-02 +!- +t- +.I-5'11JJ>lmg Sa.m p ling Lot1tioo Datt Bt- K-40 I-13 1" 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 < JJ l E-+-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 +!- 3.1 7E-!02 4.l!l:E-ii03 +.I- 5.53E+02 +I- +I-
LID i.62mifi~ in ODCM
.... Comm! Stltioo 50 Table3-9 Food and Vegeta tion page Gamma Spectra 2of2 [pCilkg] 'Samlp~ S2m-;p'lil!lg Locatm Dae<! I Be-1 I K-40 I I-13 1" I Cs-134" I Cs-137" I 23 04113116 l.55R-ilill:l + ,<. 235R;tfil 697E+m ~ 53 1E""°2 < 4.49E'!Ol < 23JE..;i] < 2.46E'11(1l 05'110/16 I. iiE-i-03 + ,I- J.5e:+m 511E+ID +.<- 6.20E.;;02 < l.&8E'l-Oll < 321E-ii01 < J .64E'!Ol OD/14.t16 l..24ET03 + ,<. l. B4E-+-02 71 0Bi03 ~ 3.&0E'l!{)2 < 4!11E'!Ol < l.7:8E.;(ll < lJ!PE.;ol 071121115 BfE.;-OJ +..:. . 3..9iE-+<<! 439H'+m 6 .l2E""°2 < 2.SlE.;(11 < 326E-401 < 3.45E-+0] 0&@/16 Lm-+m + .'- 3.9fE-+O'l 4.ni:;+-03 """' +.<-" 6 .i"iE,+02 < 2.4DE"ll01 < 398E-l01 < 3.56B"llOl 09114/l !S 6.71E-il-O? + ,l. 271E+m 593!!'+03 +,:. 6911E"'6l < 252E+ol < J .08E-!01 < 3 .17B"'IO] l M l t l lS 4.4!!E+m +I- 4.83E+m 3.05E*m ~ 625E""62 < L83E'I01 < 332E-!Ol < 3.4PE.,+0] ll110/l iS 5. i~-il-0? +$- L91JE+a:l 554B:l-03 +,:. 457B"'6l < 2.70Eil01 < 2.05E...01 < 2.UE-i!O] ~~n l. 81E+03 + ,<. J.14E-+02 52:9B'I03 +.<. 5.15E~ + _,:. +l- +. Simp,lil!; S'arrllJ'ling Locm:icm D.V- I Be-7 I K-40 I I-13 1+ I Cs-134.. I C&-137" I 26 04113116 6.53E..;<<l + ,I- 1.71£-i& 5.6:2:B+IOO ..,._ 3!ISllE'!O"l < 332E'l()l < L88E...Ol < 2.0:i-"E-i!Ol 051l0/11S l .OJE-ilill:l +I- 25!E-+02 511ETm ~ 5.77B""62 < U OE-l-01 < J .lOE.,+01 < 3 .l iSE"\IG] 0 6.114/ 16 5.33E+02 +I- 274E+m 6 .00~ +..<- 752E.;!(t2 < 495E.,;01 < 2.61E..01 < J .OOE-!01 07112111) 1. 7!!ET03 +i- 2~-+-02 7.00:&!03 -+.'- 5 .2JE'l!{)2 < J .Ol E-i!Ol < 230E'IO] < 2.A54E.,;ol 0!1.119/16 1. 741!:.;.(E + .<:. 5.Sl!E-i& 4.7JE+ffi -+.'- U 3E-i!03 < 1.87E-10l < 5.&fil!-T.0] < 'iS.9.lE...01 09.114.lliS l.66H-TID +l- J.OlE-+'02 5.46"Bil<IB ~ 5.47E-i!Ol < 3.Bl E..01 < J.06E-i0] < J.:25E'!Ol 10/l l /l iS 21!!lE-TID +,"- 4.91E.;.(l? 3 .OOl!ifiOO +.!- 6 .1 11E-i!02: < 1.00E-i!Ol < J .44E'!Ol < 3 .41SE-+0] H llOt l lS .UJE+m +l- 2.0IJB,;;(12 J.81ETm ~ 3.i9E..+02 < 2.49E-+01 < Ll!4E-!Ol < 2..23E+!I] i\tin l.43Eil-03 +I- 3.1.1!8+02 5.20H+IOO -#- '6.12E+ll2 +I- +I- +.~ Indica!Dr locations l.65E+03 +J!. 3.l iE+G:!: 53RB'+ffi -#- 597E.;G2 + J!. + J!. +.I.. .. LID :id!!m:ifi~ :in ODCM 51 TabJe3-10 Vlell Water page Gamma Spectra. Strontium. and Tritium 1 of l [pCi>'LJ Siall'...plilllg Staticm OL4. Da~ H-3 Sr-&9 I Sr-90 I Mt-54 I Fe-59 I Co-5& Co~OO I Zn-65 0312'!1116 < 1.915E+03 [* ) (*) < 3.7iE+OO < 8.46E+oo < 4 J5E+OO < 4.72E-+OO < 8.37E-+00 015!2&116 < l.04E-+-03 < 3 .4 iE+oo < 5.92.E-Ol < 4..95E+OO < 6.23E-+OO < 2 5 0E+OO < 4.68E+oo < 7.94E+OO @!2&116 < 9.23E'l-02 I*I {*) < 5.44E+oo < l .06E-+ill < 5.48E+OO < 5.54E+oo < l.OiE+Ol 12/27116 < 8.J5E-+0"2 [a) {a) < 4.34E-l-OO < !U 7E-l-OO < 5.1 2E+OO < 4.JBE-+00 < l.09E+Ol M!!a Sillmpli:f:lg Dat'.!! Zc-95 I Nb-:95 I I-13 1 I Cs-134 I Cs-137 I Ba-140 I La-140 03129116 < 7.67E400 < 4 .7 7E+oo < 6.46E--OI < 4.71E-i-OO < 4 .44E+OO < 2 .00E.;-Ol < 6.1?15E-+OO 0512&/16 < 6. 78E'li!IO < 4.61E-+OO < 5 .57E-Ol < 5.32E"IOO < 499E+OO < 3 .O l E-+01 < 9.J5E+oo 0012&11,15 < 8.32E-il-OO < 6J9E+oo < 8..26E--Ol < 5.20E+OO < 5 .03E+OO < 2.65E.;-01 < l.OOE +-01 l21Z71l 6 < '!U5E.;-OO < 5.HlE+OO < 7.74E-Ol < 5.JBE-!-00 < 490E+oo < .2 .l 7E-!-Ol < 6.73E+oo M~an l[a) St-&'9,9 0 lllllll1}-s!S p!!lfo:lm!!don th! ~rood quarta-sa.1T,PI!! . 52 Table*3-11 River W ater page GammaS pectra, Strontium , and T ritium 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- 1.11 Ei!!l3 ll!JJ < 5. 95E't-OO < 1.1 fif+(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 A f.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--0 1 < .(..6(E+<JO < &.5BE+o:J < 4..03E-+<ll0 < .U:4E+<l0 < 1..0SE+Q1 07f 11t1 6 3] lllJ < U iO'E+<JO < 1..0.C:.E+-01 < U4E+<JO < U5E+QO < 11.ME+oo Ol!.*1511 6 (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.Ei f +(J(J < 7.fi6f'+oo 10f1(1,1 16 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 < 5.5 1E.+-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 < 6.6 4E+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 < 1.71 E;()!) < 8.63800 < 2.648t00 05'13'16 < 8 .7UE+OO < 5. t2.E;{K) < 5 .10E-01 < 4.51 900 < 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 < 21 4B01 < 5.90900 0711'1'116 ., 8 .178 -00 < 4.92E +OO < 3.99E..()1 < 4.048-00 < 4.81E-100* < 2 51 E!{)1 < 8 .8 181-00 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 < 4.61 E-t00 < 524E..()1 < :3.SEE+OO < :3.82E..,i{)() < 2.4 1Bli!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 < 4.0 38-00 < 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 < 21 2801 < 8 .298-00 ME AN ~'* +I- 41- +I- +/.. +f..
LLD id'entifia:I i OOOM [ Ti i1iumanalyses on ua1sly ccmpcs ite. (bl Sr-S9'SO ?frlCJ"med a mually on2"' arter ccmpcs ite sample.
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E
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~~ t :E E ~ ~ ~ ~ I!! ~ ~ ~ !: e "'~ M fl1 ~ ~ m~
p. i"
~ ~ til ~ iii 15 r:; l:l § 8 88 88 88 88 83 s ss s s s i fj ~ ~ 3 1 ,.. t /\ /\ e: ... -~ /\ /\ /\ /\ /\ /\ /\ /\ /\ ~ .ti t :!!: :2 ~ ~~ ~ /\ ~~ ~~~ ~ ~ fl .,. ~ !!.'. ...... ~ r::i~ ~ r* ~ l>' I:. ...... J* 8 8 8 8 i8 I'! I'! ~ l"1 ~ s 8'"" 8 8 8 8'"" 3 8 ... /\ /\ /\ ...i ,...... ,.. /\ /\ /\ /\ /\ /\ /\ /\ /\ ~ *t :!!: ~~ :2: 'il' :2: /\
2: 'il' ~~ ::i!:
.. (:;) p..J ~ ~ p. ~~~ ~ iii ~ la ~ ~ ;a ~ ...~ ...b g !... ...b g :ti ~ ~ ~ tr.I ...lo 'O 0 (/l ~ ;!; ~n .r.n~ B~~;- J! *,* ,,. ~ /\ /\ *,t /\ /\ {\ /\ /\ /\ /\ /\ ...... ... c ...t* ,..... c ~. /\ 0 ~ /\ /\ {\ /\ /\ /\ /\ /\ /\ {\ /\ /\ If ~ .___. g ~ 'f (JI ~ fl! c,,. "'~ ~ ~ !" ~ ~ ,.. c c ... c ~ i" *t er. ~ ~ "'~ ;;;~ t;J~ 8 :-" !.1 1-.o ~ ~ ~ ~ ~ ~ ~ fl1 Iii @ .~ Iii t;I .. ~ ~ tll ~ tJ ~ ~ .. .~ i ~ t0 0 0 t<> i!; 0 0 0 t t0 30 il; 0 t 0 ii; i!; ;!; 0 0 0 il; 0 t0 ii; 0 0 0 0 30 1-3
i.
CT. j +.. /\ {\ /\ /\ /\ /\ /\ /\ /\ /\ {\ /\ + .. /\ /\ /\ {\ /\ /\ /\ /\ /\ /\ /\ /\ c 9 ... t: : ... e ,,. 0 fj ~ ~ ~ ~ ~ t: t: l:. t* b I,,. t: I"' ig r:; ~ ~ ig b ; ~ <>~ ~ ;!;~ t4 fl1 ~ "e. fl1 @ M ~ ~ "' ~ ~ I'll ~ iil ~ ~ ~ ~ ~ ~ 1 t0 0 i.!; ;!; <!; 0 0 0 0 0 i.!; ;!; 0 0 0 0 0 - 30 0 i.!; 0 0 t t 0 0 t 0 0 0 i td 0 ~ 1" /\ t* lo /\ /\ r; ~ /\ /\ /\ t:. t*~ /\ t> /\ r* /\ /\ /\ /\ "'t t /\ /\ /\ /\ /\ /\ /\ /\ /\ /\ /\ /\ :-!. I;. I'" t:. '" ~ i ~ ;:: ~ ~ rs f.~*1 t" ~ i;? !i: a ~ lo i iii ~ iii s'"" ~ ~ ~~ ~ iii ~ ~ ...~ fl1 ~ 8888i 8'"" 8 8 8'"" ~ t /\ /\ /\ /\ /\ /\ /\ /\ /\ /\ /\ + /\ /\ /\ /\ /\ /\ /\ /\ /\ i .- y * ~ Table 3-12 Smface \llater page Gamma Spectra, Strontium, Tritium 2 of2 [pCi/L] S3mJiit?g Sbtion t09A Dot!! I H-3* I *!i-1111 I SrJOO I :r.fa.54* I Fe-59'" I eo,s.fi<' I ec_.,ro* I Zn>*W I OFJ:21I6 {a] (ti fb] < 3. i2E+<OO l < *6.1'1E-+-OO < 613E+oo < I.1:2E+ot 1:1116 fa) [ti ~ < L14E+OO < 3.148+00 < UIE+OO < 135E+OO < ll3B+OO a) {b] {l:f < 536E+OO < UID-01 < 5_4g::,.;00 < S:Jg::.;.oo < UEE+-01 < 9.S9E+<l2 < 4. f!.1E+OO < 5:..w-01 < 4,154EJ;<<) < 9.61.E+OO < 4..9SE+OO < IS.14E+OO < 8.72B+OO (a] (b] (ij < 4,151E+(() < l.02E+Ol < 4.l!:E-+00 < i4IE+OO < Ul'l.E+-01 (a] l[ b] fb] < 5..92E+OO < 1348-01 < *t5.13E-+OO < i5SE+OO < U IIB+Ol < 9.37E+-02 l[ b] I.bl < 3.22E+OO < *t5.45E+oo < 3.04E+oo < 3A51E+OO < 5.55Et00 1[a] '[b] [b] < 3.3;E+OO < 75IE-+OO < 3.~ < :L153E+OO < 7.74E+<O 11114.116 (a] [1b] I.bl < *6.l2E+OO < l.4fE-+-Ol < 5.4SE+OO < *IS.4<E+oo < l.43E+o1 12:11211.6 < &.<t~iE+-02 [b] :fb] < 5.l.9E+OO < l.91EIOO < 4.928+00 < iOSE+oo < UXlE+ol ME.i\N +.'- +.* # +.f... +.'- + +. S.l!!ll$1-it?g Dat;! Zr-9)* N1>-95* I-131
es.-134* C;-13i * :&-140" J.a.140" IDYWio < 8. I>E+OO < 4.l!3E+OO < 6..B:!E-01 < 6.a>E+OO < 4.12E+OO < 23<E+-01 < 142E+Ol 62:1115.!115 < fn4E+OO < 4.3$+<00 < 3..f!iE-01 < 3,154E+O) < 4.66E+OD < l.91E+-Ol < 15.SIE+OO 03.1 14.rl < 9. 5EE+OO < .15. 7iE-t<OO < 3..fm-01 < 6~ < 5.i<IE+oo < 23~1 < 9.3 1!E+OO
< 2 50'.E+OO < l 45E+<OO < 4.C!lE:-01 < l.16E+-OO < 1.1t!E+oo < 9..91!E-+-OO < 3.11E+OO < 9.@E-!(() < *l5.3!JE+OO < i51E-Ol < 5.m.Etro < 5.5(!E;OO < 2.7~+0! < i.93E+<OO < 1.mE+OO E+OO < 5.5 iE-+-00 < 2.51E+-Ol < BSfE+OO < 1!.1i56E-t<OO < i3iE+OO < 4.SIE-01 < 4.33E+OO < 4.!l!E!OO < 2.2m+<Ol < 73 iE+OO < lO'lE+ol < i!EE+OO < i~ l < 5.04E+OO < 5.95E+OO < 2-956+-01 < !Ot'E+OO 'l.2Jl6 < ,15.51!E!((l < 3..54E+OO < 15.0lE-Ol < 3.1i'E-t<OO < 3.<6/E+OO < L9tE+-Ol < *IS.3iE+OO 10'1Mt5 < i79E+<O < 3..54E+OO < 3..11lE-Ol < 3,00Bt-00 < 3.7CE+OO < l.6tE+-Ol < *ll.HE+OO 11114116 < 9..8l5Et<OO < I il!E+OO < 4. 7EE-01 < 636EtiX) < i'.12E!-OD < 3.12E+<ll < B.85E+OO 12:112Jl6 < 9.9iE+(() < *tl'.lSE+OO < 4.51E-Ol < 4~ < 5.438+00 < lliE+-01 < *ll.5 fE+OO ME.:\N +.'- +. + .t . +1- +.:'-
UD ilt!ntifi~ill a::x::M (a] Tritil!.m amt}'>!:.oo qmt'.!flycaDpc:gite. (b] Sr-1!9.00p!!!fumedi amial.ly m2"' qmt~ com po~ Rl!f.{e.
55 Table3-13 Sediment Silt Gamma Spectra, and Strontium [pCilK:g] p!ge Sam~ ld l Oat! 4121. 16 Sr..&9 Sr-'00 K-4!l CS-134* Cs-13 ~ I 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 < *Q13E+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 'Stalim ~~ Stalim 11 U E+-02 201E+-02 L83E+OO: 3..3/E+-01 .15IB+ol 1 71E-+-01 Li'2E+03 +!- 1.3 t!E-i-04 +!- 2.lEE-i-04 +, 4.&E+-0'2 L44E-!-03 l ..25B+-03 < 4.C2E+<ll < 8.J3B+Ol < 6.3<JE+ol 130E+<ll Ql3E+<ll i 96B+-Ol Ra-226 I Th-2:28 I T!i-'l li 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 uni:: am Sr~ +!-
Sr-00
+. 8,84E+G2 I C.s-134* Cs- 13~ + Catlrd +.I- +, 1.54E-!-03 + Ra-2215 8.93E+-Ol I Th-2:28 Th-232 !mkalD! l ..2:2E+<l3 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 Table3-14 Shoreline Soil Gamma Spectra, .a nd Strontium [pCiJKg] page 1 of ] Sllmpl!! Date Sr-&9 &-90 K-40 C~B4" c~u 1* 4121 16 Sbltic OB [a) (a] 53lE-+0"2 +'.- 4.00E-+02 < 3.4&E-l-Ol < 3 .i'6E,i01 R.'11-226 Th-228 Th-2J2 < 8.49E+-02 < 6.79E+Ol < l.IUE'I02 Slfi!.ipl!! Oat~ Sr-&9 S!"-90 K-40 C~l34" C~l3 7 * ]OiH /20] 6 Static OB < 2D2E+02 < 4.26E-+Ol 1.0811:-t-03 +.~ 6.31E+02 < 4. 5 E-l-Ol < 4 .90E-<!Ol R.'11-226 Th-228 Th-232 < 9.88E+OZ < 91155E+o] < 2.0JE-'!02 MEAN S~-&9 Sr-90 K-40 C~l34" Cs-13 * +I- +J.. .S.06E+o2 +I- 5.?6E-t-02 +.11.. -#- R.'11-226 Th-228 Th-232 +** +!-
LID i.demtifiM ill ODCM (a) s,.-. 89!90 :amtym p!fi<<imd 2!ll!IU!lly.
57 Table3-15 Fish page Gamma Spectra l of 1 [pCi1Kg} F1'3h [~] Sampfuig S tafion OS Dat!! 1SY16 I U2E+o3 K-40 +I- 5.SSIH-02 I < Mn-54* 4.42E+ol I < Fe-59* 1.248+02 I C<>-58* < 5S7Bf-Ol I Co-©* < 53U!:+ol I < Zn-65* 92.2E.;-01 I < c~-134* 5.6JE+ol I < C!!-l37* 5..tS5E+Ol .0'1~16 1.74E+o3 +I- 535E-l-Ol < 3.48E+ol < S..59E+ol < 296E-:-01 < 3.93E+o1 < 7 j'JE.;-01 < 3.95E+ol < 4.148-l-Ol b:npl.ing S b.fion 25** Dat!! I K-40 I l\iJn-54* I Fe-59* I C<>-58* I Co-©* I Zn-65* I Cs-134* I Cs-137* 1~16 t 44E+o3 +!- 2.89E+o'l < 2.laE-i-01 < 5.0t'iEi-01 < 2.41Bi-Ol < 2<bl!+ol < 4.7SE-t01 < 200E+ol < 2!2E+Ol 10'1 ~'16 U1E+o3 +I- 6.1SE+o'l < 4.49E+ol < 7.23E+Ol < 4.82E+Ol < 3.77E+ol -58* I Co-©* I Zn-65
I C:1-l34* I C!i-137*
04!1~ 16 200E+o3 +I'- 6.43E-l-Ol < 4.97.E:+ol < 1.04E+o2 < 453B+Ol < 4.84E+ol < 6.07E.;-O l < 3.84E+ol < 5.6SE+Ol 1 0'1~16 l.75E+o3 +I- 8.C6E+02 < 5.19E+ol < l.OSBl-02 < 6J C!Et-01 < 3.63E+ol < 659E.;-01 < 5.S(E+ol < 537&-0l Sampl.ing S ta:lion 25** Daf!! K40 Mn-54* I Fe-59* I C<>-58* I Co-@* I Zn-65
I Cs-134* I C!i-137*
04! 1~1 6 H4E+o3 +,L 8.03E+02 < 5.42E+ol < L29B+-02 < 5.65El-Ol < 4.9'7E+ol < 9 .7U!:.;-Ol < 4"66E+ol < 5..5SE+Ol 10'1~1*6 l..4CE+o3 +I- 8.17E-l-02 < 6.76Ei-Ol < l .448+02 < 7.49ET01 < 733E+ol < L73E-+02 < 7.laE+Ol < 7.S9E+O Mam L75&0.3 +I- 6.45B+-02 Imiakir L75B-l-03 +I- 6.43BT-02 Cccfrcl L 62Et03 +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. 58 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 soi l, 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 wi ll 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 I 00 00 C: "'C: "'C: "'""C: "'"'C: 0 N 00 a;> c 0 9 c N 9 c ""0 c I "'c 0 I 00 0 0 .-1 c I N .-1 c I ""c "'C: .-1 I .-1 00 .-1 c' 0 N 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 ana lyses 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 co ,._ co ,._ co ~I Ol C> N <<) l[) CD Ol C> ~ N <<) ~ l[) CD Ol C> N <<) ~ l[) co co Ol Ol Ol Ol Ol Ol Ol Ol Ol C> C> C> C> C> C> C> C> C> C> ~ ~ ~ ~ ~ I I I I I I I I I I I I I C:: ,ro ,ro , ,ro ,ro ,ro , ,ro , , , ,ro , , , , , ,ro , , ,ro , , ,ro , ,ro ,ro ,C::ro C:: C:: (1) C:: C:: C:: c ro C:: c ro c ro c ro C:: c ro c ro c ro c ro c ro C:: c ro c ro C:: c ro c ro C:: c ro C:: C:: - - c ontrol Sta. 24 - - Indicator Average Pre-Op - - Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 2.SOE-02 2.00E-02 l.SOE-02 l .OOE-02 5 .00E-03 0.00E+OO 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 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 resu lts 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 twe lve 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 samp les 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 ~ Tritium Cl. 2500 2500 - Requ ired LLD 2000 1500 1000 1000 l/\ ID ccu ccu ccu ccu c .c c c c cc c c c c c c c c c c c c c . .c cc c c c r-- 00 C1l 0 r i N C't\ '¢ l/\ ID r-- 00 en 0 00 00 00 00 00 en en en en en en en C1l en en 0 ri 0 N 0 C't\ 0 '¢ l/\ 0 0 ID 0 r-- 00 0 cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu cu 0 C1l 0 c 0 ri c ri ri N ri C't\ ri '¢ l/\ ID ri ri ri cu cu cu cu cu cu cu ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Figure 4-4 Tritimn in River water 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma 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~~ u * & . I v . 1000 I . 1 (\/ I ...J /J - - Tritium t;100 a. Required LLD --+- Average Pre-op 10 1 ..... ,., ..... ,., r-- en r-- co r-- en 'o:t <D co r-- r-- co co lO ~ ~ 0 en N en 'o:t al <D en en 0 0 lO 0 0 0 N ..... ..... ..... ..... N0
t. .!. >. ...!.
u u ,;,. >. ...!. 0.. > ,;,. .!. c

0.. > c:
I I .!. t. bi t; ....,ro ro ro ...., Cl) Cl) ro ....,::; Cl) 0 Cl) Q. ....,::; (f) z0 ....,ro ::2:ro ....,::; <(::; 0 Cl)
2: ::2: 0 0 LL ::2: (f) z LL <(
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 sa mples 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 historicall y common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumu lation and runoff into the lake of residual weapons testi ng 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 bee n detected occasionally in the past at both the indicator and control locations and is attributable to fa llout 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 Apri l and October from indicator station 08. The samples were analyzed by gamma spectroscopy. The October sample was ana lyzed 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 resu lts 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 LAND USE CENSUS North Anna Power Station Louisa County, Virginia January 1 to December 31 , 201 6 Direction Distance (miles) Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden(> Meat Milch Milch Boundary 50m 2) Animal Cow Goat N 0.9 1.3 1.56 2. 9 NONE NONE NNE 0.9 0.9 1.22 3.1 N ONE NONE NE 0. 8 0.9 1.6 1.6 N ONE NONE ENE 0.8 2. 37 2.4 2.49 N ONE NONE E 0. 8 1.3 2.04 3. 5 N ONE NONE ESE 0. 9 1.7 1.7 NONE N ONE NONE SE 0.9 1.4 1.54 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 N ONE NONE s 0. 9 1.03 1.14 2.0 N ONE NONE SSW 1 1.27 1.33 2.0 N ONE NONE SW 1.1 1.65 1.65 NONE NONE NONE WSW 1.1 1.62 2.22 NONE NONE NONE w 1.1 1.5 1.93 NONE NONE NONE WNW 1 1.1 2.67 4.98 N ONE NONE NW 1 1.0 1.28 NONE N ONE NONE NNW 0.9 1.0 2.54 2. 3 N ONE NONE 71 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

t r Eckert &Ziegler Anafytfcs HIO SMbOlnl lndllllrill IM!. Atlt~ GA IOIU. UM RESULTS OF RADIOCHEMISTRY CROSSCHECK PROGRAM lST QUARTER 2016 (Ref. Date 19 FEB 16) REVISED

~ .~ ,.; '-'r ,,

L. Tkavadze;.N~c1e-Sr Metr0iog1st - ANALYTICS RATIO VALUE VALUE SAM.P LE ANALYSIS microCi/cc microCilcc RESOLUTION COMPARISON A31518 Tritium -6.79E-04 7.40E-04 0.92 12.5 AGREEMENT LIQUID A3l519* Sr-89 2.04E-03 2.46E-03 0.8.1 17 AGREEMENT FILTER Sr-90 l.OSE-04 2.68E-04 0.78 12.S AGREEMENT

microCi 75

~ m Eckert &Ziegler 1\na1';tics l i &O Sa.:iboard ll'ciUJh'l ai e<vt!. A.tlar.n, GA 30Sla, USi\ T;?I~ 40ol*i!SH6i7 foic: 404-352-2837 RESULTS OP RADlOCHElVUSTRY CROSS CHECJ( .PROGRAM 3.RD Q ARTER 2016 ( Ref. Date 12 AUG .l6)

t. ~ H o. i lG L. Tkav~ltb;<'., Nuclea r Mctrnlogist ANALYTICS RATIO VALUE VALVE SAMPLE ANALYSIS microCi mic:roCI RESOLUl'lON COMPARISON A3203S 8~9 l.83E-03 0.96 17 AGREEMENT FILTER Sr-:90 2.64E-04 0.94 12.5 AGREEMENT A32034 3.67E-03 2.76E--03 1.33 J'ILTER

..........."'****"'****"**"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 ElAnalytics Evaluation !d) March 2016 E11 476 Milk Sr-89 pCifL 97 86. 7 1.12 A Sr-90 pCifL *15 11.4 1.32 N(2) E 11 477 Milk 1-1 31 pCifL 85.9 82.2 1.05 A Ce-14 1 pCifL 106 98.4 1.08 A Cr-51 pCifL 255 243 1.05 A Cs-134 pCifL 134 130 1.03 A Cs-137 pCifL 174 16 1 1.08 A Co-58 pCifL 123 117 1.05 A M1-54 pCifL 141 117 121 w Fe-59 pCifL 152 131 1.16 A Zn-65 pCifL 193 179 1.08 A C0-80 pCifL 259 244 1.06 A E1 1184 AP Ce-14 1 pCi 69 8 1.1 0.85 A Cr-51 pCi 242 201 120 w Cs-1 34 pCi 98 .1 107.0 0.92 A Cs-1 37 pCi 136 133 1.02 A C0-58 pCi 9 1.9 97 0.95 A rk!-54 pCi 98.6 96.2 1.02 A Fe-59 pCi 98.8 108 0.91 A Zn-65 pCi 131 147 0.89 A C0-80 pCi 209 2{) 1 1.04 A E1 1478 Charcoal 1-13 1 pCi 85.3 88.3 0.97 A E 111 85 W ater Fe-55 pCifL 1800 1666 1.08 A Ju ne 20 16 E 11 537 Milk Sr-89 pCifL 94.4 94 .4 1.00 A Sr-90 pCifL 13.4 15.4 0.87 A E11 538 Milk 1-131 pCifL 96.8 94. 5 1.02 A Ce-141 pCifL 129 139 0:93 A Cr-51 pCifL 240 27 6 0.87 A Cs-1 34 pCifL 157 174 0.90 A Cs-1 37 pCifL 117 120 0.98 A C0-58 pCifL 131 142 0.92 A rvtl-54 pCifL 128 125 1-02 A Fe-59 pCifL 132 122 1.08 A Zn-65 pCifL 235 235 1.00 A C0-80 pCifL 169 173 0:98 A {a) Ta"'ffyne Brown Engineering reporfa d rewlf. {b) The Ana!yrics known valu e is equal to 100% o f Ifie p arameter present irt /he standani a:; determined .by gravimetric and.lw

\iOlumeln*c measurements mao'e during :standard preparat>o n.

(c} Ra fro of Teledyne Brown Engineerirr-9 lo Anafytic:s re-:sulf:s . (d) Anarytic:; evafuaifon based on rBE intern al 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
ANALYTICS ENVIHONMENT AL RAIJIOACT IVlTY CROSS CHECK PROG RAM TE LEDYN 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 0.96 A E11540 AP Ce-141 pCi 105 99.8 1.05 A Cr-51 pCi 216 198.0 1.09 A Cs-134 pCi 113 125 0.90 A Cs-137 pCi 94.5 86.'6 1.09 A Co-58 pCi 101 102 0.99 A rvti-54 pCi 88.8 90.2 0.98 A Fe-59 pCi 82 87.5 0.94 A Zn-65 pCi 174 169 1.03 A Co-60 pCi 143 124 1.15 A E11185 Water Fe-55 pCi/l 1'64 186 0.88 A September 2016 E 116-09 Milk Sr-89 pCifL 90 90.9 0.99 A Sr-90 pCi/l 13. 3 13.7 0:97 A Milk 1-131 pCi/L 80.4 7 1.9 1.12 A Ce-141 pCifl 8 1.3 93 0.87 A Cr-51 pCifL 198 236 0.84 A Cs-134 pCifL 122 135 0.90 A Cs-137 pCifL 11 9 119 1.00 A Co-58 pCifL 92.2 97.4 0.95 . A Ml-54 pCifL 156 152 1.03 A Fe-59 pCifL 97.5 90.6 1.08 A Zn-65 pCifl 189 179 1.06 A Co-60 pCifL 131 135 0.97 A E 11 511 Charcoa l 1-131 pCi 52.4 599 0..87 A E11612 AP Ce-141 pCi 67.5 63.6 1.06 A Cr-51 pCi 192 161 .0 1.19 A Cs-134 pCi 91 .4 92 .6 0.99 A Cs-137 pCi 93 _9 80.8 1.16 A Co-58 pCi 66 66.4 0:99 A Ml-54 pCi 104 104 1.00 A Fe-59 pCi 60.5 61.8 0.98 A Zn-65 pCi 140 122 1.15 A Co-60 pCi 11 9 91 .9 1.29 w (a) Tekdyne Brown Eng ineffing reported result. (b) Tlt.e AnaJylics known value .':s equal to 100% of the parameter present in lh e :standard a:s de-.'"errnined by gravimetric am!* volume lric 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
ANALYTIC S ENVlRO NMENTAL RAD OACTIVITY C RO SS C HECK PROGRAM T ELEDYNE BROWN ENGINEER ING ENVIRONM ENT AL SERVI CES (PAG E 3 O F 31 Reported Known Ratio (c) Mont '!'ear Mawix u Ude nits Va lue (a) Va l'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 0.3S B 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 Mi lk Sr-S9 pCitL 95 7 .2 1.28 w Sr-90 pCi/L 4.7 1.47 (3} E l 17 Mi lk 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 El 7 1 Ch;mxlal 1-13 pCi 9 .e gs .9 A El 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 El 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 10 1 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"" DO E's MIXED ANALYTE PERFORMANCE EVALUATION PROG RAM (MA PEP) TELEDYN E BROWN ENG INEERI NG ENVI RONMENTAL SERVICES (PAG E 1O F 1) Iden ca hon Reported kn o111n Acceptance MonthJY.ear Number Media Nuclide* Units Valu e (a) Value {b) Ran<Je Evalua -Oil {c ) March 2016 16-MaW34 Water Am-241 Bq/L 0.008 { 1) A Ni-63 Bq/L 12.4 12.3 8.6-16 .0 A Pu-238 Bq/L 1.4900 1..2440 0.871-1 _617 A Pu-239/240 Bq/L 0.729 0.641 0.449-0.833 A 16-MaS34 Soil Ni-63 Bq/kg 1140 1250.0 875-1625 A Sr-90 Bq/kg 8 .15 { 1) A 16-RdF34 AP U-2341233 Bqlsample 0. 1620 0.1650 0.116-0.215 A U-238 Sqls3mple 0.163 0.172 0.120-0.224 A 16-GrF34 AP Gr~A Sqlsample 0_608 1-2{) 0 .36-2.04 A Gr-8 Sq/sample 08060 0_79 0.40-1 .19 A 16-RdV34 Vegetation Cs- 134 Sq/sample rn. 10 10.62 7.43-13.81 A Cs-1 37 Sq/sample 6 .0 5_62 3.93-7.31 A Co-57 Sq/sample 13.3000 11 .8 8.3-15.3 A Co-£0 Sq/sample 0_013 ( 1) A tvtl-54 Sq/sample 0.0150 { 1) A Sr-90 Sq/sample 0.301 (1) N(4) Zn~5 Sq/sample 10 .500 9.6 6.7-12 .5 A Sep ernller 2016 16-MaW35 Water Am-241 Bq/L 0_626 0.814 .570-1058 w Ni-63 Bq/L 12.4 17.2 12.0-22.4 A Pu-238 Bq/L 1.23 1-13 0.79-1.47 w Pu-239/240 Bq/L 0.0318 0.013 { 1) A 16-MaS35 Soil Ni-63 Bqlkg 724 990 693-1287 A Sr-90 Bq/kg 747 894 626-1 162 A 16-RdF35 AP U-234/233 Sq/sample 0.160 0.15 0.1 05-0.195 A U-238 Sq/sample 0.157 0.156 0.1 09-0.203 A 16-RdV35 Veget3tion CS-134 Sq/sample 1 03 { 1) A CS- 137 Sq/s3mple 5 .54 5.54 3.88-7 .20 A Co-57 Sq/sample 7.38 6_81 4.77-8.85 A Co-£0 Sq/sample 4 .81 4_86 3.40-6.32 A tvti-54 Sqlsample 7.4 7.27 5.09-9.45 A Sr-90 Sq/sample 0.774 0_8{) 0.56-1 .04 A Zn~5 Sq/sample 5 .46 5.4 3.78-7 .02 A ( 1) Fakle positive tesi. (a) Tekdyrre Brow Eng ine-ering reported r ew!t. (b) The MA PEP 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=a c oeplabi'e w'i!ti warning, ~/=not acoeptabre. {4)NCR 1&-14 was - ~~';; fed 80
-~ ' ERA ENVIRONMENT AL RADIOACTIVITY CROSS CH EOK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVIC ES {PAG E t O F 1) Iden tlcahon Reported Known Acceptance Wlonth!Year Number ~1e di a Nuclide Units Value (a) Value {b) Limits Evalua *oo (c} May2016 RAD-105 Water Sr-89 pCifl 48.9 48.2 37.8 - 55.6 A Sr-90 pCifL 25.0 28.5 20.7 - 33.1 A Ba-133 pCifL 53.1 58.8 48.7 - 64.9 A Cs-134 pCill 40.9 43.3 34.6 -47.6 A Cs-137 pCi/l 84 .8 78.4 70.6 - 88.9 A Co-60 pCi/l 1{)8 102 91.8 - 114 A Zn--65 pCill 226 214 193 - 251 A Gr-A pCi/l 38.9 62.7 32.9 - 77.8 A Gr-B pCill 4 1.9 39.2 26.0 - 46.7 A 1-131 pCill 24 .1 26.6 22.1 - 31.3 A U- at pCi/l 4.68 4.64 3.39- 5.68 A H-3 pCill 7720 7840 6790- 8620 A vember 2016 RAD-107 Water Sr-89 pCifL 43.0 43.3 33.4-50.5 A Sr-90 pCi/l 30.0 33.6 24.6-38.8 A Ba-1 33 pCifl 47.8 54.9 45.4-60.7 A Cs-134 pCi/l 72.9 8 1.8 67.G-90.0 A Cs-137 pCi/l 189 210 189-233 A Co-60 pCi/l 58.4 64. 5 58.0-73.4 A Zn-65 pCi/l 243 245 220-287 A Gr-A pCi/l 372 68 .4 35.9-84 .5 A Gr-8 pCi/l 35.1 33.9 22.1 -41.6 A 1-131 pCill 23.5 26.3 21 .9-31.() A u a pCi/l 492 51.2 41 .6-56.9 A H-3 pCi/l 918 *9820 8540-10800 N(5) MRAD-25 AP Gr-A pCi/Fil er 56.8 7 1.2 23.9- 11 1 A (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 m ao'e dlfrirtg standard preparatio n.

(c) ERA evaluation: A =acoept:able. Reported rewJt faffs within h-P W;;m

g Um.~s. NA =n~ ~epta l:; 'e. R epone<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 'la ming Umit.

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

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