Text

Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report for Cy 2022
	ML23130A146
Person / Time
Site:	North Anna
Issue date:	04/19/2023
From:	; Dominion Energy Co, Virginia Electric & Power Co (VEPCO)
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	23-084
	Download: ML23130A146 (1)
	v • d • e

Dominion Energy North Anna Power Station Radiological Environmental Monitoring Program January 1, 2022 to December 31, 2022 Prepared by Dominion Energy, North Anna Power Station

Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2022 to December 31, 2022 Prepared by:

Supervisor Radiological Analysis and Instrumentation Dominion Energy North Anna Power Station

, Approved by:

George . Simmons Manager Radiological Protection and Chemistry .

Dominion Energy North Anna Power Station 2

Table of Contents

1. EXECUTIVE

SUMMARY

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

2. PROGRAM DESCRIPTION ............................................................................................................ 6 2.1 Introduction ............................................................................................................................. 6 2.2 Sampling and Analysis Program ............................................................................................. ?

3. ANALYTICAL RESULTS ............................................................................................................ 21 3.1 Summary of Results .............................................................................................................. 21 3.2 Analytical Results of2022 REMP Samples ........................................................................ .28

4. DISCUSSION OF RESULTS ......................................................................................................... 56 4.1 Gamma Exposure Rate ......................................................................................................... 56 4.2 Airborne Gross Beta .............................................................................................................. 57 4.3 Airborne Radioiodine ............................................................................................................. 58 4.4 Air Particulate Gamma ......................................................................................................... 59 4.5 Air Particulate Strontium ...................................................................................................... 59 4.6 Soil ........................................................................................................................................ 59 4.7 Precipitation .......................................................................................................................... 59 4.8 Cow Milk .............................................................................................................................. 59 4.9 Food Products and Vegetation .............................................................................................. 59 4.10 Well Water .......................................................................................................................... 59 4.11 River Water ...................................... .'.................................................................................. 60 4.12 Surface Water ....................................................................................................................... 60 4.13 Bottom Sediment ................................................................................................................ 61 4.14 Shoreline Soil .................................... : ................................................................................. 62 4.15 Fish ...................................................................................................................................... 62

5. PROGRAM EXCEPTIONS ........................................................................................................... 63 REFERENCES .................................................................................................................................... 64 APPENDICES ..................................................................................................................................... 65 APPENDIX A: LAND USE CENSlJS ........................................................................................... 66 APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS ............................... 68 3

1. EXECUTIVE

SUMMARY

This document is a detailed report of the 2022 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2. Radioactivity levels from January 1 through December 31, 2022, in water, silt, shoreline sediment, 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 are monitored within a 25-mile radius of the station. North Anna Power Station (NAPS) personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. Control samples are collected from areas that are beyond the measurable influence of North Anna Power Station (NAPS) or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station (NAPS), can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.

Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline." Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident, Fukushima Daiichi or natural variation.

Mirion Technologies provided thermoluminescent dosimetry (TLD) services and Teledyne Brown Engineering Environmental Services provided radioanalytical services. Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy.

Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires equipment used for radiological environmental monitoring 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 2022 airborne results were similar to previous years. Fallout or natural radioactivity levels remained at levels consistent with past years' results.

Water and aquatic exposure pathway samples include precipitation, surface, river and well water, silt and shoreline sediments, and fish. The average tritium activity in surface water for 2022 was 6508 pCi/liter. No other plant related isotopes were reported in any surface or river water. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 5518 pCi/liter. No plant related isotopes were detected in quarterly precipitation samples. Silt samples indicated the presence of naturally 4

occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background. Plant related isotope, Cs-137, was not identified in any indicator sample during the reporting period. The detection of Cs-13 7 in bottom sediment is historically common with positive indication usually apparent in both indicator and control samples. Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels. No plant related isotope was detected in the indicator or control locations in shoreline soil. No plant related isotope was detected in fish samples from either Lake Anna or the control location, Lake Orange.

Soil samples, which are collected every three years from twelve stations, were collected in 2022. During the preoperational phase Cs-13 7 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. Cs-137 was detected in five of eleven indicator location samples obtained during the reporting period with an average of 227.83 pCi/Kg and ranged from 59.06 to 322.60 pCi/Kg.

The terrestrial exposure pathway includes milk and food/vegetation products. No milk samples were obtained during the reporting period since the last operating dairy farm within the sampling area closed on O1/01/2018 rendering milk samples unavailable. No plant related isotope was detected in any vegetation sample. Low levels of Cs-137 have been detected intermittently in past years due to weapons testing, Chernobyl, and Fukushima.

The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years.

During 2022, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2022 was 0.874 millirem. For reference, this dose may be compared to the 620 millirem average ammal exposure to every person in the United States from natural and man-made sources. Natural background sources in the environment provide approximately 50% ofradiation exposure to man, while medical uses provide approximately 48%. By comparison, nuclear power contributes less than 0.1 %. These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.

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2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2022 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).

The North Anna Power Station of Virginia Electric and Power Company (Dominion Energy) 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 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.

The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications which address the release of radioactive effluents. In-plant monitoring is used to ensure release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in the North Anna Power Station Offsite Dose Calculation Manual (ODCM).

North Anna Power Station is responsible* for collecting the various indicator and control environmental samples. Mirion Technologies is utilized for processing the TLDs. Teledyne Brown Engineering Environmental Services (TBE) is utilized for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes. Data collected prior to station operation is used to indicate the degree of nah1ral variation to be expected. The pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.

Occasionally samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFRS0, 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 2022 and satisfies the following objectives of the program:

To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public resulting from station operations.

To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.

To identify changes in radioactivity in the environment.

6

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 2022 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 2022.

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TABLE2-1 North Anna Power Station - 2022 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 Dosimetry (TLD) Fredericks Hall 02 5.30 SSW 203° Quarterly & Annually Mineral, Va 03 7.10 WSW 243° Quarterly & Annually Wares Crossroads 04 5.10 WNW 287° Quarterly & Annually Route 752 05 4.20 NNE 20° Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N 110 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-1/33 0.06 N 10° Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 110 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 1380 Quarterly Route 701 (Dam Entrance) SE-14/46 5.88 SE 137° Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 158° Quarterly Elk Creek SSE-16/48 2.33 SSE 165° Quarterly NAPS Access Rd. S-17/49 0.36 s 173° Quarterly 8

TABLE2-1 North Anna Power Station - 2022 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sam pie Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 s 178° Quarterly Thermoluminescent NAPS Access Rd. SSW-19/51 0.24 SSW 197° Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 205° Quarterly 500kv Tower SW-21/53 0.60 SW 218° Quarterly Route 700 SW-22/54 3.96 SW 232° Quarterly NAPS SE Switchyard 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 1.40 WNW 303° Quarterly North Gate - Laydown Area NW-29/61 0.52 NW 321° Quarterly Lake Anna Campground NW-30/62 2.54 NW 319° Quarterly

1/#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-5/6 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 0lA 0.64 SE 1380 Weekly Fredericks Hall 02 5.30 SSW 203° Weeldy Mineral, VA 03 7.10 WSW 243° Weeldy Wares Crossroads 04 5.10 WNW 287° Weeldy Route 752 05 4.20 NNE 20° Weekly Sturgeon's Creek Marina 05A 2.04 N 110 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 - 2022 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° Weeldy 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 0IA 0.64 SE 138° Quarterly (Well Water)

Precipitation Biology Lab 0IA 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 NAPS 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 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 10

TABLE2-1 North Anna Power Station - 2022 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sam pie Media Location Station Distance Direction Degrees Frequency Remarks Bumpass, VA 07 7.30 SSE 167° Once/3 years Soil 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 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

TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA EREQUEN~X ANALXS!S LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)

(84 TLDs) Quarterly Gamma Dose 2mR+/-2mR mR/std. Month (12 TLDs) Annually Gamma Dose 2mR+/-2mR mR/std. Month Airborne Radioiodine Weekly I-131 0.07 pCi/m3 Airborne Particulate Weekly Gross Beta 0.01 pCi/m3 Quarterly (a) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 2nd 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 2nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)

River 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

LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

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TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUE~CY ANALYSIS LLD REPOBI !l~!IS 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 1-131 l0(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-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 (d)

Cs-134 15 Cs-137 18 Ba-140 (d)

La-140 (d)

Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.

(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

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TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Soil Once per 3 years Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Sr-89 (b) pCi/kg (dry)

Sr-90 (b)

Milk Monthly, if 1-131 1 pCi/L available Monthly, if Gamma Isotopic available 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 I-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, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.

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Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Map Environmental Station Designation Identification Designation Identification 1 (a) Ol,NE-5/37 7/8 C-7/8 IA OlA,SE-13/45 1/33 N-1/33 2 (a) 02,SSW-20/52 31/63 NNW-31/63 3 (a) 03,C-5/6 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) 05 7/39 ENE-7/39 5A (a) 05A,N-2/34 9/41 E-9/41 6 (a) 06,ESE-12/44 11/43 ESE-11/43 7 (a) 07, C-1/2 17/49 S-17/49 8 OS-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 14B 14B-Vegetation 16/48 SSE-16/48 15 15-Vegetation 14/46 SE-14/46 16 16-Vegetation 22/54 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 station, annual and quarterly TLD, Triennial soil.

(b) In Orange (c) In Lake Orange 15

SSW Legend

Rael Erwironmantal bing Sinon TLD Loe lions Scale

3J8 inc:h

2~ fl Figure 1. North Anna Site Radiological Monitoring Locations 16

TSYLYANIA North Anna Environmental Map e FIXed Environmental Sampfng location

- TLD Sampling

- Garden Residents 1801 ~ ADCaf Alaandria. Inc~ 84406-al GrNnWay, VA22312. USED wmt PERMISSION. Na adlar ,wprocl,otion

. n permiaion of ADC.

17

North Anna Environmental Map

- FD<ed Environmental Sampling Location e no Sampling

- Garden Residents 9 Meat Animals 0 0 1911 tJr ADC ot

0440 GePl!lal GI ~

AJeg)dtta, VA22312. US NOOlhel tqllOCIIClltll ffllll'llemildewm!IU GIAIDC.

18

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l 1-a Environmental Fixed Environmental Sampling Location TLD Sampling

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19

LA North Anna Environmental Map

- Fixed Environmental Samp ing Location 4t TLD Sampling

- Garden Residents ltCKHAIII 9 MeatAnimals DRNUI & Ollghlll C 19111 1¥ ADC ot Alemllllla, n:... o+IO Galetal GIC'.aJ ~

.,~ . AIISal1dfll, VA 22312. USED WITH PEFMSSION. ND Olhel le(:IIOClll:lkll fflli¥ tie mNe WIIIOUI IIH'IIJefl pefflllSAan 0, A C. .

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3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM. For radioanalytic analyses, the values listed in the columns indicated as "Mean/Range" include any results above the Minimum Detectable Concentration, MDC. Results are considered true positives when the measured value exceeds both the MDC and the 2I 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.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Page 1 of 6 RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

NORTH ANNA NUCLEAR POWER STATION. LOUISA COUNTY, VIRGINIA 2022 Docket No. 50-338/339 2022 Medium or Indicator Indicator Control \\'on-Routine Pathway Analysis Total LLD* Locations Location \-.ritl, Highest Mean Locations Reported Sampled Type Numbez Distance Mean Mean Measurement (Units)

Direct Radiation Gamma 253 2 Mean (fQnge) 3.7 (2531253}

Numberl 28161 Direction 0.52M1.

I (Range) 6.4 (8/8)

(Range) 3.0 (16116} 0 (mR.std. Month} Dose (0.6-7.5) NW (4.7-7.5) (2.3-4.0)

(Sector Tl.Da) tt G3/4, -718 U!Sed for control locatians Direct Radiation Gamma 32 2 2.3 (16/16) C-112 7.30Mi. 2.8 (16/16) 3.0 (16116} 0 (mR.atd. Month) Dose (0.9-3.0) SSE (2.3-3.0) (2..3-4..0)

{Pte-<lperational TLDs}

tt G314, -718 used for control looafions Direct Radiation Gamma 40 2 4.6(40/40} EPSP 0.37Mi. 6J) (8/8) 3.0 (16116) 0 (mR.sld. Month} Dose (2.0-8.4) 09/10 ENE (5.0-8A) (2..3-4...0)

(Emergency Sector Tl.Os) tt c:;&14, -718 used for control locaficms Direct Radiation Gamma 48 2 3.0 (44/44) STA-23 0.93 Mi. 4.6 (4/4) 2.6 (414) 0 (mRatd. Month} Dose (iA-62) SSE (2.3-2.9) (2..3--2.9}

(Environmental TLDs)

Direct Radiation Gamma 12 2 3.1 (11/11) STA-23 0.93 Mi. 4.6 (1/1) 3.1 (1/1) 0 (mR.std. Month) Dose (1.4-4.6) SSE (4.6) (3.1)

(Annual TLDs)

Arr Particulat.e GR-B 662 0.01 16.1 (612/612) 23 0.93Mi. 17.4 (51/51) 16.5 (50/50} 0 (10e *3 pCifm 3 ) (5.75..34..7) SSE (S.69-29.6) (8.25-3o.9)

GM'IMA 52 BE-7 52 131.7 (48148) 23 D.93 Ml. 145.7(4/4) 134.9 (4/4) D

{78.8-174) SSE (100.7-174) (101.6-1525)

Cs-134 52 0.05 (0/48) NIA NIA NIA (0/4) 0 Cs-137 52 0.06 (0/48) NIA NIA NIA (0/4) 0 Sr-89 13 0.01 (0/48) NIA NIA NIA (0/4) a Sr-90 13 0.01 (0/48) NIA NIA NIA (0/4) 0

.Air Iodine 1-131 662 0.07 (0/612) NIA NIA NIA (0/50) 0 (10e"3 pCilm 3 )

Soil""" GAMMA 12 (pCilkg d,y wt.) K-40 12 11978 (11/11) 01 0.20Mi. 24060 (1/1} 23200 (111) 0 (4905-24060} NE (24060) (23200)

CS-134 12 150 (0/11) NIA NIA NIA (0/1) 0 CS--137 12 180 227.83 (5/11) 02 5.3Mi. 322.60 (1/1) (011} 0 (59.060-322.60) SSW (322.6)

Ra-226 12 2193.8 (4/11) 23 0.93Mi. 3095.0 (1/1 ) (0/1) 0 (1357.0-3095.0) SSE (3095.0}

"' UD identifed in ODCM

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

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Page 2 of 6 RAOIOLOCIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2022 Docket No. 50-338/339 2022 Medium or Indicator Indicator Control Non-Routine Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Reported Measurement Sampled (Units}

Soil...., (cont'd)

Type Th-228 Numbe1 12 Mean (Range) 1066.0 (11/11)

Numberl 06 Distance Diraotion 4.7MI.

I Mean (Range}

1958.0 {1/1)

Mean (Range}

185.10 (1/1} 0 (pCiA<g dry wt.) (185.90-1958.0) ESE (1958.0) (185.10)

Th-232 12 1232.4 (9/11) 06 4.7Mi. 1852.0 (1/1) (0/1) 0 (581.00-1852.0) ESE (1852.0)

Sr-89 12 (0/11) NIA NIA NIA {0111} D Sr-90 12 (0111) NIA NIA NIA (0/1) 0

- - soil samples are obtained triennially.

Pr-ecipbtion GR-B 12 4 4.3 (10/12) 01A 0.64 ML 4.3 (10112) NIA 0 (pCVlifer} (1..8-10.8) SE (1.8-10.8)

H-3 12 2000 (0/12) NIA NIA NIA NIA 0 GAl',,MA 2

Be--7 2 (0/2) NIA NIA NIA NJA 0 Mn--54 2 15 (012) NIA NIA NIA NIA 0 Fe-59 2 30 (0/2) NIA NIA NIA NIA 0 Co-58 2 15 (0/2) NIA NIA NIA NJA 0 Co-60 2 15 (0/2) N/A NIA NIA NIA 0 2 30 (0/2} N/A NIA NIA NIA 0 Zr-95 2 30 (0/2) NIA NIA NIA NIA 0 Nb-95 2 15 (0/2) NIA NIA NIA NIA D Cs-134 2 15 (012) NIA NIA NIA NIA 0 Cs-137 2 18 (0/2) NIA NIA NIA NIA 0 B.a-140 2 60 (0/2) NIA NIA NIA NIA D La-140 2 15 (0/2) NIA NIA NIA NIA D 1-131 2 10 (0/2) NIA NIA NIA NIA 0

LLD identifed in ODCM 23

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Page 3 of 6 RADIOLOOIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY. VIRGINIA 2022 Docket No. 51J-338/339 2022 Medium or Indicator Indicator Control Non-Routine Pathway Analysis Total LLD* Locations Location with Highest Mean Locations Reported Sampled Type Numbel Mean Distance Mean Mean Measurement (Units)

Precipitation (cont'd) Th-228 2 (Range)

{012)

Number!

N/A Direction NIA I (Range)

NIA (Range}

N/A 0 (pCVfder)

Fruits & Vegetables GAMMA 35 (pCilkg wet wt.J B~7 35 - 2482 (28/28) 23 0.Q3Mi. 2866 (lll) 2119 (111) 0 (591.3-10330) SSE (591.3-7708) (792.7-31175)

K-40 35 - 4358 (28/28} 148 1.22 ML 6042(Jll) 4452 [lll) 0 (2025-6185) NNE (3552-6185) (3358-5736, 1-131 35 60 (0/28) NIA NIA NIA (017) 0 Cs-134 35 60 (0128) NIA NIA NIA (017) 0 Cs-137 35 80 (0128) NIA NIA NIA (017) 0 Th-228 35 - 134.7 (3/28) 23 0.93Mi. 135.0 (217) 47.70 (1/7) 0 (103.2-166.8) SSE {103.2-166..8) (47.70)

Th-232 35 - (0/28} NIA NIA NIA (017) 0 Well Water H-'3 4 2000 (0/4} NIA NIA NIA NIA 0

{pCilliterj GAMM.A 4 Mn-54 4 15 {0/4) NIA NIA NIA NIA 0 Fe-59 4 30 (Ol4) NIA NIA NIA NIA 0 Co-68 4 15 (014) NIA NIA NIA NIA 0 Co-60 4 15 (0/4) NIA NIA NIA NIA 0 Zn-65 4 30 {0/4) NIA NIA NIA NIA 0 Zr-95 4 30 (014) NIA NIA NIA NIA 0 Nb-95 4 15 (0/4) NIA NIA NIA NIA 0 1-131 4 10 (0/41 NIA NIA NIA NIA 0 Cs-134 4 15 {0/4) N/A NIA NIA NIA 0 Cs-137 4 18 (0/4) NIA NIA NIA N/A 0

LLD identifed in ODCM 24

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Page 4 of 6 RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

NORTH ANNA NUCLEAR POWER STATION. LOUlSA COUNTY, VIRGINIA 2022 Docket No. 50-338/339 2022 Medium or Indicator Indicator Control Non-Routine Pathway Analysis Tot.al LLD" Locations Location with Highest Mean Locations Reported Sampled Type Number Mean Distance Mean Mean Measurement (Units)

Well Water (cont'd} Ba-140 4 60 (Range)

{0/4)

Number!

NIA Direction NIA I (Range)

NIA (Range}

NIA 0 (pCiffder)

La-140 4 15 (0/4) NIA NIA NIA NIA 0 Sr-89 {0/1) NIA NIA NIA NIA 0 Sr-90 (0/'i) NIA NIA NIA N/A 0 River-Water H-3 4 2000 5518(4/4) 11 5.S ML 5518 (4/4) NIA 0 (pCifftf.er) (4680-6940) SE (4680-6940)

GAMl'.'l:A 12 Mn-54 12 15 (0112) NIA NIA NJA NIA 0 Fe-69 12 30 (0/12) NIA NIA NIA NIA 0 Co-58 12 15 (0112) NIA NIA NJA NIA 0 Co-60 12 15 (0/12) NIA NIA NIA NIA 0 Zn-65 12 30 (0/12} NIA NIA NIA WA 0 Zr--95 12 30 {0112) NIA NIA NIA NIA D Nb-95 12 15 (01112) NIA NIA N/A NIA 0 1-131 12 (0/12) NIA NIA N/A NIA 0 Cs-134 12 15 (0/12) NIA NIA NIA NIA 0 Cs-137 12 18 (0/112) NIA NIA NIA NIA 0 Ba-140 12 60 (0/12) NIA NIA NJA NIA 0 La-140 12 15 (0/12) NIA NIA NIA NIA 0 Sr-89 (0/1) NIA NIA NIA NIA 0 Sr-90 (0/1) NIA NIA NIA NIA 0

LLD identifed in ODCM

-25

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Page 5 of 6 RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM

SUMMARY

NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY. VIRGINIA 2022 Coaket No_ 50-338/339 2022 Medium or lndfca1or Indicator Conirol Non-Routine Pathv.r.ay Analysis Total LLC" Locations Location \'Vitti Highest Mean Locations Reported Sampled Type Number MeasUTement (Units)

Surface Water H-3 8 2000 Mean (Range) 65D8(4/4}

Numberl 08 Distance Direction 3.37Mt.

I Mean (Range) 6508(4/4)

Mean (Range)

(014! 0 (pCilliter) (4170-8440) SSE {4170-8440)

GAMMA 24 Mn-64 24 15 (0/12) NIA NIA NIA (0/12) 0 Fe-59 24 30 (0/12) NIA NIA NIA (0/12) 0 Co-58 24 15 (0/12} NIA NIA NIA (0/i2) 0 Co-60 24 15 (0112) NIA NIA NIA (O/t2) 0 Zn-65 24 30 (0/12) NIA N/A NJA (0/12) 0 Zr-95 24 30 (0/12) NIA NIA NIA (0/12) 0 Nb-95 24 30 (0/12) NIA NIA N/A (O/i2) 0 1-131 24 1 (0/12) NIA NIA NIA (0/12) 0 Cs-134 24 15 (0/12) NIA NIA NIA (0/12) 0 Cs-137 24 18 (0/112) NIA NIA NIA (0112) 0 Ba-140 24 60 (0/12) N/A NIA NIA (0/12) 0 La-140 24 15 (0/12) NIA NIA NIA (0/12) 0 Sr-89 2 (0/1) NIA NIA NIA (0/1) 0 Sr-90 2 (0/1) NIA NIA NIA (0!1) 0 Sediment Silt GAMMA 6 (pCilkg dry wt} K-40 6 9799(414) 11 5_80Mi. 17830 (2/2) 13960(2/2) 0 (11716--18050) SE (17610-18050) (13340-14580)

Cs-134 6 150 (0/4) NIA NIA NIA (0/2) 0 Cs-137 e 180 (0/4) NIA NIA NIA (0/2J 0 Ra--226 6 (0/4) NIA NIA NIA {0/2) 0

LLD identifed in ODCM 26

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Page 6 of 6 RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM SUMll.'IARY NORTH ANNA NUCLEAR POWER STATION. LOUISA COUNTY. VIRGINIA 2022 Docket No. 50--338/339 2022 Medium or Indicator Indicator Control tl.'on-Routine P.athway Analysis Total LLD" Locations Location with Highest Mean Lccations Reported Sampled Type Numb& Mean Distance Measurement (Units)

Sediment Silt {cont'd) Th-228 6 (Range) 672.8 (2/4)

Numberl 11 Direction 5.80Mi.

I Mean (Range) 672.8 (212}

Mean (Range) 165.9 (212) 0 (pCi/kg dry wt.) . (635..4-710.2) SE (635.4-710.2) (90.94--240.8)

Th-232 6 - 952.3 (1/4) 11 5.80 Mi. 952.3 (1/2} (0/2) 0 (952.3) SE (952.3)

Sr-89 3 - (012) NIA NIA NIA (0111} 0 (Annually)

Sr-90 3 - (012.) NIA NIA NIA (0111) 0 (Amually)

Shoreline Soil GAMMA 2 (pCilkg dry v.,f..} K-40 2 - 1266(2/2) 08 3.37 fl.fi. 1266 (212) NIA 0 (1011-1521) SSE (11011-11521)

Cs-134 2 150 (012) NIA NIA NIA NIA 0 Cs-137 2 180 (0/2) NIA NIA NIA NIA 0 Ra-226 2 - {0/2} NIA NIA NIA NIA 0 Th-228 2 - QQ.27 (1/2) OB 3.37Ml. 99.27 (112) NIA 0 (99.27) SSE {99.27)

Th-232 2 - (012) NIA NIA NIA NIA 0 Sr-ag* 1 - (0111} NIA NIA NIA NIA 0 (Jl.11ml13lly)

Sr-90 1 - (0/1) N/A NIA NIA NIA 0

{Amually)

Fish-Other GAMMA 8 (pCilkg wet wt.) K-40 8 1097 (4/4} oa 3.37 Mi. 1097 (414} 1631 (414) 0 (648.1-1457} SSE (648.:1-1457) (1349-2006)

Mn-54 8 130 [0/4) NIA NIA NIA (0/4) D Fe-69 B 260 (0/4) NIA NIA NIA (W4) D Co-5B 8 13!1 (0/4) NIA NIA NIA {0/4) 0 Co-00 8 130 (0/4) NIA NIA NIA (0/4) 0 Zn-65 8 260 (014) NIA NIA NIA (0/4) 0 Cs-134 B 130 (0/4) NIA NIA NIA (0/4) 0 Cs-137 B 150 (0/4) NIA NIA NIA (0/4) 0

" LLD identifed in ODCM 27

3.2 Analytical Results of 2022 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 2I: error.

Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data1* 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, WeeklyI-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. RiverWater

12. Surface Water

13. Bottom Sediment/Silt

14. Shoreline Soil

15. Fish 1

Analytical results are handled as recommended by HASL ("Reporting ofAnalytical Results from HASL, "letter by Leo B.

Higginbotham) and NUREG/CR-4007 (Sept. 1984).

28

TABLE3-2 QUARTERLY

.GAMMA EXPOSURE RATE (mR/std. Month) +/- 2 Sigma F1JSt Quarter Second Quarter Third Quarter Fourth Quarter 12128/2021- 312£1!2022- 6/28/2022- 9/28/2022- Quarterly Average*

station 312£1/2022 6/28/2022 9/28/2022 12127/2022 (+/-)2S.D.

N-1 3.3 4.3 4.6 4.3 42 (+/-) 1.1 N-33 3.3 4.7 4.3 4.6 N-2 20 3.0 3.0 2.9 2.6 (+/-) 0.7 N-34 2.3 2.7 2.3 2.3 NNE-3 4.7 5.7 5.0 5.8 5.2 (+/-) 1.3 NNE-35 4.0 5.3 5.6 5.8 NNE-4 3.0 4.0 4.0 4.1 3.7 (+/-) 1.0 NNE-36 3.0 4.0 3.3 4.1 NE-5 3.3 4.3 4.0 3.8 3.8 (+/-) 0.7 NE-37 3.3 3.7 3.6 4.1 NE-6 2.3 3.0 3.0 32 3.0 (+/-) 0.6 NE-38 3.0 3.0 3.0 3.5 ENE-7 4.0 4.3 5.0 5.5 4.8 (+/-) 1.4 ENE-39 3.7 5.3 5.0 5.5 ENE-8 2.0 2.3 1.7 1.2 1.7 (+/-) 0.9 ENE-40 2.0 1.3 1.7 1.7 E-9 3.3 4.7 4.3 52 4.5 (+/-) 1.6 E-41 3.3 4.3 5.0 5.5 E-10 3.0 4.0 3.3 4.1 3.6 (+/-) 1.0 E-42 3.0 3.7 3.6 4.3 ESE-11 3.3 4.3 4.0 3.8 3.8 (+/-) ns ESE-43 3.0 3.7 4.0 4.1 ESE-12 3.0 4.0 3.3 4.3 3.7 (+/-) 12 ESE-44 3.0 4.3 3.6 4.3 SE-13 3.0 3.7 4.0 3.5 3.6 (+/-) 0.8 SE-45 3.0 4.0 3.6 4.1 SE-14 4.3 5.7 4.6 52 5.0 (+/-) 1.3 SE-46 4.0 5.3 5.0 5.8 SSE-15 3.7 5.3 5.3 52 4.5 (+/-) 1.7 SSE-47 3.3 4.0 4.0 5.2 SSE-16 (a} 2.3 2.6 2.6 2.4 (+/-) 0.3 SSE-48 {a) 2.3 2.3 2.3 S-17 3.3 4.3 4.0 4.6 4.4 (+/-) 1.1 S-49 4.0 4.7 4.6 52 (a) 1LD was missing and unable to be analyzed.

"Average or collocated 11-Ds 29

TABLE3-2 QUARTERLY GAMMA EXPOSURE RATE (mR/Std. Month}+/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter 12/28/2021- 3/29/2022- 6/28/2022- 9/28/2022- Quarterly Average" Station 3/29/2022 6/28/2022 9/28/2022 12/27/2022 (+/-)2S.D.

S-18 2.0 (a) 2.3 2.0 20 (+/-) 0.3 S-50 2.0 2.0 2.0 1.7 SSW-19 4.3 5.7 5.9 7.2 5.8 (+/-) 23 SSW-51 4.0 6.0 5.9 72 SSW-20 1.7 20 2.3 1.7 2.0 (+/-) 0.5 SSW-52 2.0 2.0 2.3 1.7 SW-21 2.7 3.7 3.0 3.5 3.3 (+/-) 0.8 SW-53 3.0 3.7 3.6 3.5 SW-22. 3.0 4.0 4.0 4.6 . 3.8 (+/-) 1.1 SW-54 3.0 3.7 4.0 4.1 WSW-23 3.0 4.0 4.3 4.3 42 (+/-) 1.7 WSW-55 3.3 4.7 4.0 5.8 WSW-24 3.0 4.0 3.3 3.8 3.3 (+/-) 0.9 WSW-56 2.7 3.0 3.3 3.5 W-2!5 4.3 5.7 5.9 6.1 5.5 (+/-) 1.6 W-57 4.3 5.7 5.9 6.4 W-26 2.3 2.7 3.0 2.6 25 (+/-) 0.8 W-58 2.0 3.0 2.6 20 WNW-"ll 2.3 2.7 3.0 32 27 (+/-) 0.7 WNW-59 2.3 3.0 3.0 23 WNW-28 2.0 3.0 3.3 2.9 2.7 (+/-) 0.9 WNW-60 2.3 3.0 2.3 2.9 NW-29 4.7 7.0 6.9 72 6.4 (+/-) 2.0 NW-61 5.3 6.7 5.9 7.5 NW-30 1.7 2.0 1.7 1.4 1.6 (+/-) 0.9 NW-62 1.7 2.0 1.7 0.6 NNW-31 3.0 3.3 3.6 4.6 3.6 (+/-) 12 NNW-63 3.0 3.7 3.3 4.3 NNW-32 2..7 3.3 3.3 2.9 3.1 (+/-) 0.6 NNW-64 3.0 3.7 3.3 2.9 Mean 3.7 (+/-) 2.6 (a} 11.D was missing and unable to be analyzed.

Average of collocated TLDs I

30

TABLE3-2 QUARTERLY GAMMA EXPOSURE RATE (mR/std_ Month) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter 12/28/2021- 3/29/2022- 6/28/2022- 9/28/2022- Quarterly Average*

station 3/29/2022 6/28/2022 9/28/2022 12fll/2022 (+/-)28-D_

C-1 2_3 3_0 3_0 2_9 28 (+/-) 0_6 ,

C-2 2.3 3_0 3_0 2_9 C-3"" 2_3 3_0 26 2_9 27 (+/-) 0-4 e4tt 2_7 27 2.6 2-6 C-5 1-7 20 1-7 1-7 1-9 (+/-) 1-1 C-6 2_0 27 23 0.9 e-r 2_7 3.7 4_0 3_5 3_3 (+/-) 1.0 C-SH- 2_7 3_0 3.6 3_5 Indicator Mean 23 (+/-) 1.3 Control Mean 3_0 {+/-) 1.0 EPSA-01 ...... 3_7 4_0 3_6 4_3 4_0 (+/-) 0.7 EPSA-02""" 3_7 4.0 4_0 4_6 EPSF-03...... 3_0 4_0 3_6 3_8 3_6 {+/-) 0.8 EPSF-04_, 3_0 3.7 4_0 3_8 EPSR-05....* 5_0 6_3 5_0 5_5 52 {+/-) 1.4 EPSR-OF 4_0 5.7 4_6 5_5 EPSJ-07.,.... 27 3-7 20 32 3.1 {+/-) 12 EPSJ-08*** 2-7 3_3 3-3 3_8 EPSP-09""* 5_0 7.7 5_3 8-4 6.9 {+/-) 2_8 EPSP-10....-. 5_0 7.7 6_6 8-4 Mean 4.6 {+/-) 3_1 (a) 1LD was missing and unable to be analyzed_

Average of collocated 1LDs

- Control Location

- - Emergency Plan TI.Ds_

31

TABLE3-2 QUARTERLY GAMMA EXPOSURE RATE (mR/Std. M:lnth) +/-2Sigma First Quarter Second Quarter Third Quarter Fourth Quarter 12/28/2021- 3/29/2022- 6/28/2022- 9/28/2022- Quarterly Average* Annual station 3/29'2022 6/28/2022 9/28/2022 12/27/2022 (+/-)2S.D. llD STA-01 3.3 3.7 4.3 4.1 18 (+/-) 0.8 3.4 STA-02 1.7 1.7 2.3 1.7 1.8 (+/-) 0.6 24 STA-03 1.7 20 2.0 1.4 1.8 (+/-) 0.5 1.4 STA-04 1.7 20 2.3 1.4 1.9 (+/-) 0.8 23 STA-05 2.3 3.3 3.3 2.9 3.0 (+/-) 0.9 32 STA-05A 2.3 27 2.3 31 26 (+/-) 0.8 2.7 STA-06 3.0 4.0 4.0 4.6 3.9 (+/-) 1.3 3.9 STA-07 2.0 27 3.3 32 2.8 (+/-) 12 3.1 STA-21 23 3.0 3.3 32 3.0 (-t/-) 0.9 3.4 STA-22 27 4.0 3.0 4.3 3.5 (-t/-) 1.6 3.7 STA-23 3.3 52 5.1 4.6 4.6 (-t/-) 1.7 4.6 STA-24** 2.7 27 23 2.9 26 (-t/-) 0.5 3.1 Mean Indicator Locations 3.0 (-t/-) 20 3.1 (-t/-) 1.7

Average of collocated llDs

- Control 32

TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (10"3 pCifm3 )

LOCATIONS PER10D ENDING 01 02 03 04 05 06 07 21

(+/-) (+/-) (+/-) (+/-) (+J-) (+/-) (+/-) {+/-)

01/05122 13.00 2.400 12.60 2.950 12.10 2.910 12.40 2.950 15.20 2.790 15.20 3.120 15.70 2.620 12.30 2.930 01/12122 21.90 3.180 22.20 3.750 18.40 3.380 21.70 3270 21.80 3.180 21.90 6280 22.70 3.220 15.60 3.720 01118/22 18.40 3,.340 15.70 3.120 15.60 3.130 11.00 2.850 21.10 3.420 21.00 3.420 22.30 3.480 19.30 3.330 01125/22 19.10 2:930 23.40 3280 16.30 2.780 23.80 3.160 21.60 3.060 18.20 2.880 17.80 2.850 24.90 3.360 02/01/22 19.90 3.180 19.70 3.180 17.50 3.070 18.20 3.160 19.10 3.150 13.90 2.890 16.80 3.040 19.20 3.160 02108/22 14.70 2.760 13.10 2.670 15.10 2.780 17.30 2.900 12.00 2.600 14.80 2.760 17.70 2.920 13.70 2.700 02115/22 22.50 3.120 20.00 3.110 20.50 3.130 23.00 3260 21.60 3.200 21.40 3.200 19.30 3.060 19.20 3.100 02122J22 19.60 3,.100 16.90 3.020 15.50 2.960 20.20 3.14ID 16.50 2.970 16.20 2.970 19*.00 3.130 18.20 3.040 03101/22 13.30 2.890 12.20 2.830 11.DO 2.760 14.20 2.940 14.10 2.920 9.520 2.680 15.60 3.010 11.20 2.770 03/08122 19.10 2.940 16.00 2.770 17.70 2.870 19.50 2.960 19.70 2.970 20.90 3.170 17.60 2.850 19.60 2.960 03/15122 14.10 2.650 13.90 2.640 14.00 2.760 11.10 2.470 12.80 2.560 13.00 2.580 12.00 2.530 12.20 2.540 03122{22 14.50 2.730 12.00 2.630 16.10 2.820 14.40 2.720 13.60 2.690 21.30 4.340 14.90 2.750 10.70 2.500 03/29/22 9.350 2.470 10.40 2.500 11.10 2.550 9.960 2.480 7.420 2.320 9220 2.430 10.60 2.510 8.510 2.400 04105/22 14.70 2.730 10.70 2.530 12.00 2.610 15.50 2.800 10.90 2.540 15.50 2.920 13.00 2.660 14.60 2.750 04/12f22 8.100 2.320 10.10 2.450 8.760 2.360 8.060 2.370 7.92D 2.400 7.300 2.260 11.50 2.53D 8.910 2.370 04/'19/22 13.00 2.830 8.140 2.560 12.40 2.810 12.50 2.810 11.BO 2.800 15.10 2.970 12.40 2.810 9.610 2.650 04126/22 18.70 2.920 16.70 2.810 21.00 3.030 21.30 3.050 17.70 2.850 16.30 2.790 21.80 3.070 10.80 2.480 05/03/22 19.20 2.920 18.70 2.900 19.10 2.920 19.70 2.950 20.30 2.990 20.90 3.020 19.00 2.920 19.00 2.910 05/10122 14.70 2.800 9.200 2.480 6.710 2.310 9.220 2.480 11.50 2.620 11.80 2.660 11.50 2.610 11.20 2.600 05/-17/22 10.90 2.540 5.750 2.210 7.850 2.350 8.610. 2.400 8.520 2.390 6.960 2.280 1020 2.500 8.070 2.360 05124/22 17.80 3.11)10 7.530 2.430 16.70 2960 15.30 2.880 16.50 2.960 14.70 2.860 11.30 2.660 14.40 2.840 05/31/22 7.140 2.340 8.630 2.430 6.89D 2.320 9.390 2.480 7.650 2370 9.460 2.480 10.30 2.540 9.160 2.460 06/07/22 17.00 2.850 15.60 2.780 15.80 2.790 16.10 2.810 20.40 3.020 16.40 2.820 16.20 2.820 17.10 2.860 06114/22 16.80 2.76Cl 12.50 2.510 15.20 2.660 19.30 2.890 15.90 2.690 14.40 2.610 15.90 2.700 12.20 2.490 06122122 14.ClO 2.420 12.10 2.310 12.40 2.330 12.50 2.330 13.60 2.410 13.50 2.430 13.70 2.400 11.90 2.300 oa128m 10.60 2.620 10.SO 2.700 11.30 2.770 12.90 2.850 11.80 2.000 12.70 2.650 9.000 2.640 11.00 2.690 33

TABLE3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (10"3 pCi/mi)

LOCATIONS PERIOD ENIDIN*G 01 02 03 04 05 06 07 21

(+I-) (+/-) (+/;.} {+/-) (+t-) (+/-) (+/-) (+!/-)

07/05122 17;90 3.190 13.00 2.920 12.50 2.810 12.60 2.830 13.10 2:.840 19.70 3.190 12.60 2.840 13.40 2.910 D7t12l22 {a)'

07!21lf22 18.70 2.960 13.80 2.730 15.50 2820 1.8.70 2.960 13.60 2.740 18.30 2.930 15.70 2.830 14.80 2.780 07126122 18.90 3.85D 13.30 3.590 18.20 3.810 15.10 3.670 14.40 3.620 20.40 3.900 14.30 3.640 12.90 3,560 08102122 15.10 2.840 16.20 2.900 13.80 2770 16.80 2.930 16.30 2.910 15.10 2.850 13.70 2.760 12.90 2.730 08/09122 12;90 2.580) 11.80 2.510 1UJO 2.460 11.30 2.480 15.40 2.710 12.00 2.520 1:3.20 2.SBO 10.00 2.400 08116122 *12.20 2720 10.60 2.640 13.20 2.770 13.30 2.780 16.60 2.940 15.00 2.860 12.30 2.730 12.30 2.730 08123122 12.70 2.630 18.20 2.920 13.10 2.650 13.80 2.690 16.90 2.870 18.20 2.930 14~90 2750 *t4.10 2.710 08/30/22 28.50 3.450 25.60 3.330 29.90 3.510 31.10 3.570 27.40 3.4*to 24.80 3.290 28.10 3.430 27.90 3.430 09/06122 10.10 2.440 16.10 2.770 13.90 2.660 16.50 2.790 16.50 2.790 17.20 2.820 14.00 2.650 11.00 2.490 09/13122 9.090 2.490 8.850 2.470 9.420 2.500 11.40 2.610 8.960 2470 9.840 2.520 9.020 2.490 7;910 2.420 09!21lf22 26.40 3250 23.50 3.130 26.50 3.260 29.20 3.380 23.70 3.150 24.60 3.190 21.70 3.050 23.30 3.120 09/28/22 23.40 2.800 22.00 2.730 25.90 2870 25.90 2.880 21.10 2.680 25.70 2.890 27.00 2.950 11.90 2.200 10104/22 8D3Cl 2.560 6.480 2.470 8.510 2670 8.990 2.670 8.370 2.600 9.050 2~650 6.730 2.490 6.140 2.450 10/11/22 18.60 2.910 15.70 2.750 18.00 2.870 18.40 2.890 1820 2.870 14.80 2.700 15.00 2.720 7.620 2290 10118/22 24.70 3.200 28.50 3.370 24.60 3.200 20.30 3:000 21.60 3.090 25.40 3.250 24.30 3.190 21.70 3.070 10.125122 18.30 2.920 16.91) 2.850 16.70 2.840 18.00 2.900 17.30 2870 19.70 2.880 13.90 2.690 15.80 2.800 11/02122 15.50 2.380 8.910 2.070 14.80 2.350 16.50 2.440 12.50 2:.220 17.00 2.460 14.80 2.350 12.30 2.210 11/09122 :2:3.20 3.100 21.70 3.040 19.40 2.930 22.60 3.080 15.60 2:.740 23.70 3.130 14.90 2.700 19.20 2.920 11t15/22 9 .150 1

2.810 11.10 2.970 7.760 2.710 11.CI{) 2.910 10.20 2.850 9.930 2.840 11.60 3.000 6.7:20 2.650 111221'22 20.90 3.020 22.00 3.080 17.30 2850 17.80 2.870 19.70 2.970 11.60 2.550 18.70 2.910 18.20 2.890 11129122 25.00 3220 23.80 3.160 22.10 3.080 23.90 3.170 23..BD 3.150 20.70 3.010 22.90 3.120 22.30 3;090 1:w7/22 24J30 2.880 22.40 2.780 22.20 2770 25.50 2.820 21.70 2.750 22.70 2.800 24-.30 2.870 23.60 2.830 12/13122 19.40 3.46 19.00 3.440 19.00 3.440 23.00 3.630 19.00 3..430 16.80 3.310 22.30 3.000 18.20 3.410 12120122 15.40 2.760 14.60 2.840 16.10 2.800 15.90 2.790 14.10 2:.840 18.00 3:050 14.50 2.840 12.30 2.590 1:2127122 23.90 2.860 26.50 3.090 20.40 2.680 22.20 2.770 23.10 2:.940 23.90 2.980 23.60 2.850 23.30 2.830 Mean 16.76 2.863 15.45 2.825 15.62 2.827 16.82 2.882 16.06 2:.846 16.58 2.966 16.13 2.841 14.56 2.780 (a) Week!ly ~et was lost in transit and unable to be analyzed.

34

TABLE 3-3 AIR PARTICULATES GROSS BETA RADIOACTIVITY (10-3 pCUm 3 )

LOCATIONS PERIOD ENDING 22 23 24" 01A 05A

(+I-) (+/-) (of>/-) {+/-) (of>/-)

01/05122 13.90 2.460 18.50 3.270 14.40 2.480 15.50 . 2.530 15.10 3.070 01/12122 18.80 3.020 16.30 6.250 20.90 3.130 20.40 3.090 24.30 3.610 01118/22 19.80 3.350 25.00 3.630 15.60 3.130 18.90 3.300 18.20 3.270 01/25122 2Ul0 3.020 26.20 3.420 22,00 3.070 20.10 2.980 22.30 3.090 02101/22 17.40 3.070 W.20 3.210 22~00 3.300 18.:20 3.110 17.50 3.080 02.108/22 13.10 2.670 16.70 2.860 16.10 2..830 16.80 2.870 12.60 2.640 02/15/22 16.90 2.970 20.30 2.940 18.10 2..910 15.00 2.860 18.70 3.040 021'22!22 16.50 2.940 19.90 3.340 19.30 3.080 18.10 3.160 21.00 3.210 03/01/22 12.20 2..830 13.80 2.920 16.20 3.020 11.80 2.820 13.40 2.890 03/08/22 17.40 2.850 19.80 3.090 17.40 2..860 17.(]0 2.940 18.70 3.031]

031'15/22 13.70 2.630 15.30 2.840 14.40 2..660 13.50 2;1310 14.00 2.740 03/22122 15.80 2..800 16.30 2.940 16.00 2..830 13.80 2.690 17.80 2..920 03/29122 1220 2.620 11.40 2.580 9.930 2.470 10.00 2.500 10.70 2..520 04/ll5/22 13.40 2.68(] 17.20 3.000 14.4(] 2.740 10.80 2.520 11.90 2..600 04/12/22 7.94(] 2.310 9.250 2.400 8.670 2.340 9.180 2.390 8.500 2:.340 04/19122 11.9(] 2.760 7.240 2.500 10.90 2.750 10.60 2.700 1UO 2750 04126/22 1820 2.890 2UO 3.080 19.10 2.930 21.40 3.060 18.BO 2910 05103/22 21.90 3.060 2'1.50 3.040 20.20 2.990 21.30 3.030 22.70 3.110 05/10/22 10.30 2.55 12.10 2.660 13.90 2.750 *t4.10 2.780 11.70 2.620 05l17!22 7.050 2290 11110 2.490 10,00 2..460 9.000 2.420 12.iO 2.610 05124!22 14.40 2.840 16.30 2.940 14.30 2.850 12.30 2.720 15.60 2.910 05/31/22 8.630 2.430 10.10 2.520 8250 2.410 6;060 2270 11.60 2.620 06.107/22 17.70 2.890 18.50 2.930 20.20 3.010 17.00 2.650 16.50 2.820 06/14/22 14.10 2.610 14.80 2.650 18.40 2.820 15.30 2.680 7.190 2150 06122/22 10.10 2.190 13.00 2.360 8.920 2.120 H.20 2250 13.40 2.390 06.128/22 9.500 2.570 10.00 ~.690 10.20 2.730 12.60 2.950 11.40 2.780 "Control Station 35

TABLES-3 AIR PARTICULATES GROSS BETA RADLOACTIVITY (10.;i pCl!m 3 )

LOCATIONS PERIOD ENDING 22 23 24" 01A 05A

(+/-) (+/-) (+I-) (+/-) (+/-)

07105122 16.10 3.4)70 19.10 3.:200 9:170 2.600 18.50 3.210 12.70 2820 07112122 {a) 07/20122 14.00 2.740 14.40 2.780 15.20 2.820 17.30 2.900 17.60 2930 07/26/22 11.30 3.480 15.:Srl 3.69{1 19.7CJ 31170 15.20 3.670 17.40 3.770 08/02122 17.40 2.960 15.00 2.860 14.30 2.810 '15.20 2.860 18.40 3.020 08109122 11.60 2.500 13.40 2.600 14.40 2650 12.50 2.550 13.40 2600 08/16122 13.20 2.770 15.00 2.860 12.90 2730 12.50 2.730 14,00 2.800 08/23122 14.70 2.740 14.70 2.740 14.30 2760 14.90 2.750 19.20 2.960 08/30122 29.50 3.500 29.60 3.500 30.90 3.550 14.90 2.830 34.70 3.700 09/06122 "14.80 2.700 17.90 2.860 17.50 2840 15.30 2.730 1520 2.730 09/13122 6280 2.320 9.440 2.510 9210 2480 8.370 2.450 7.550 2.390 09/20122 23.20 3.100 19.40 2.930 25.80 3.250 27.70 3.310 29.10 3.390 09/28122 21i.DO 2.680 24.30 2.820 24.20 2.820 22.50 2.760 23.10 2770 10/04122 6.590 2.490 6.690 2.500 9.500 2.680 9.860 2,690 9.310 266 10/11122 15.20 2.730 18.00 2.880 19.20 2.910 16.30 2.790 23.20 3.110 101181'22 24.00 3.170 24.70 3.:200 23.60 3.180 26.20 3.270 30.10 3.460 10/25,122 '.)16.40 2.830 19.00 2.980 17.70 2.890 16.80 2.840 14.50 2720 11/02122 16.60 2.4401 18.00 2.520 15.80 2.400 13.00 2.250 15.70 2410 1119122 20:90 3.000 22.30 3,060 20.50 2980 19.40 2.930 22.70 3.090 H/15122 8.590 2.830 9.740 2:900 10.30 2840 9.240 2.810 11.30 2.920 11122122 '.18.80 2.920 22.50 3.'100 23.00 3.140 14.70 2.710 20.00 2.980 11/29122 19.70 2.970 27.80 3.340 20.90 3.020 20.20 2:990 25..60 3.240 12107122 18.40 2.590 24.20 2.860 19.40 2.650 20.80 2.700 24.60 2.880 12113122 20.00 3.490 18.30 3.410 22.60 3.590 15.80 3.280 19.60 3.450 12120122 13.00 2.630 18.10 2.91!JO 15,00 2.7S0 8.780 2.400 17.9(1 3.000 12127122 19.90 2.650 25.70 3.050 (b) 23.40 2.940 23.40 2.840 Mean 15.39 2.796, '17.38 2.992 16.50 2.858 15.48 2.812 17.20 2910

corntrol Station Mean Ill !ndicr::ilfor locations '.16.25 2870 (a) Weekly set was lost in transit andl unable to be arnaL'yzed.

(b) Due to a pump malfunction run tfme was 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

36

TABLE:3-4 AIRBORNE IODINE (1WpCi/m3)

LOCATIONS PERIOD END!NG 01 02

- - 03 04 05 06 07 21 01/05.122 < 38A4 < 51.68 < 51.47 < 21.72 < 44.40 < 13.28 < 24.40 < 3127 01/12122 < 50.75 < 64.15 < 59.99 < 42.55 < 40.74 < 43.61 < 40.60 < 58.32 01118.122 < *lCJ.55 < 22..52 < 22.57 < 22.57 < 22..57 < 19.53 < 19.45 < 19.49 01/25122 <20.08 < 10.43 < 20.08 < 20.08 < 20.12 < 16.9\Z < 16...92 < 18.20 02101122 < 17.51 < 17.54 < 17.54 < 26.13 < 26.18 < 10.98 < 26.13 < 26.13 02/08122 < 7.981 < 13.54 < 13.54 < '13.57 < 13..52 < 11.49 < 11.49 < 11.49 02115/22 < 65.94 < 69.58 < 69.32 < 46.90 < 47Jl8 < 47.25 < 19.49 < 47.60 02/22122 < 17.20 < 17.73 < 8.439 < 17.29 < 17.47 < 17.61 < 17.73 < 17.30 03/01/22 < 18.30 < 8.651 < 18.27 < 18.27 < 1820 < 20.82 < 20.82 < 20.86 03/08122 < 20.39 < 20.32 < 9.263 < 20.36 < 20.36 < 21.31 < 13.28 < 19.89 03115122 < 42.13 < 4213 < 44.65 < 28.70 < 28.50 < 28.50 < 28.70 < 24.10 03,122/22 <20.52 < 20.52 < 20.52 < 20;52 < 8.652 < 21.40 < 31.06 < 31.06 03/29122 < 14.24 < 33.42 <33.42 < 33.48 < 33.42 < 19.24 < *t9.20 < 19.30 04105.122 < 19.33 < 19.60 < 19.64 < 23.85 < 23.90 < 10.59 < 23.85 <23.n 04/12122 < 14.59 < 14.54 < 14.54 < 20.79 < 9.665 <2021 < 20.24 < 2021 04119122 <1124 < 11.34 < 11.34 < 11.32 < 6.729 < 13.39 < 19.91 < 19.B8 04126122 < 12.50 < 1248 < 12.48 < 1248 < 12.44 < 33.76 < 33.76 < 1421 05/03/22 <24.26 < 24.26 <24.26 < 24.22 < 1021 < 16.39 < 19.59 < 19.52 05/10.i'.22 <25.00 < 25.75 <25.75 < 18.29 < 18.26 < 15.52 < 18.26 < 18.29 05117,122 < 19.64 < 8.953 < 19.68 < 19.64 < 19.61 < 17.28 < 14.58 <H.34 05124.122 < 19.71 < '[9.74 < 19.74 < 19.74 < 13.28 < 9.582 < 20.95 < 2Cl.95 051'311'22 < 14.12 < 116.82 < 16.82 < 16.82 < 16.82 < 17.51 < 8.971 * < 17.51 06107122 < 45.00 < 18.91 < 45;08 < 45.08 < 45.00 < 14.03 < 30.83 < 30.73 06114/22 < 28.21 < 28.06 < 28.06 < 12.16 < 26.50 <26.59 < 26.68 <26.73 06/22/22 < 36.50 < 36.50 < 36.50 < 36.45 < 15.40 < 13.32 < 25.48 < 25.48 06.128122 < 39.43 < 40.89 <17A7 < 41.23 < 41..57 < 16.34 < 38.72 < 38.09 37

TABLE3-4 AIRBORNE IODINE (10"3 pCitm3)

LOCATIONS PERIOD ENrnNG 01 02 03 04 05 06 07 21 07/05.f.22 < 13.33 < 12.93 < 30.42 < 30.68 < 30.42 < 18.18 < 18.24 < 18.47 07112122 (a}

07120/22 < 23.45 < 11.38 < 23.56 < 23.45 < 23,.67 < 28.21 < 14.54 <28.47 07126122 <20.42 < 9.311 < 20.42 < 20.42 < 20.34 < 27.92 < 11.78 <28.03 08102122 < 25.1:9 < 25.19 < 25.19 < 25.19 < 10.62 < 27.85 <Z"f.70 < 11.70 08/09/22 < 19.52 < 19.45 < 19.45 < 9.365 < 22.29 < 22.33 < 22.33 < 22.33 08/16/22 < 15.22 < 15.22 < 15.22 <8.992 < 21.33 < 21.29 < 21.44 < 21.44 08/23/22 < 21.29 < 21.36 < 10.91 < 21.36 < 21.51 < 8.708 < 19.04 <19.04 08/30122 < 22.41 < 22.37 < 22.41 < 10.86 < 22.37 < 23.34 < 23.34 < 23.38 09106/22 < 36.04 < 15.14 < 36.10 < 35.97 < 35.97 < 33.97 < 33.97 < 33.97 09/13122 < 18.35 < 43.59 < 43.59 < 43.59 < 43.44 < 44.28 < 18.67 < 44.36 09/20/22 < 17.62 < 17.71 < 17.71 < 17.71 <8.114 < 14.34 < 17.0D < 17.00 09*/28122 < 13.44 < 31.74 < 31.07 < 31.40 < 31.69 <11.19 < 26.68 < 26.68 10/04/22 < 31.61 6 < 31a92 < 13.78 < 32.38 <3Ul8 < 20.11 < 20.07 < 20.07 10111122 < 12.11 < 24.99 < 24.99 < 24.99 < 24.82 < 19.10 < 19.20 < 19.20 10l18122 < 17.58 < 17.65 < 17.65 <23.15 < 9.810 < 23.27 < 23.15 < 23.15 10/25122 < 39.00 < 39.00 < 16.42 < 39.00 < 38:94 <24.44 < 24.44 < 24.49 11!02/22 < 26.54 < 11.15 < 26.58 < 26.58 < 25;.59 < 14.79 < 35.28 < 35.22 11i09!22 < 25.00 < 25.05 < 25:05 < 25.05 < 10i.50 < 33.02 < 33.02 <32.96 11115122 < 39.116 < 39.99 < 39.07 < 23.05 < 23.00 < 22.91 < 9.894 <23.05 11122122 < 14.37 <3Hl3 < 31a63 < 31.63 < 31.74 < 22.38 < 26.52 < 26.56 11129122 < 13.27 < 31.64 <31.64 < 31.64 < 31.53 < 20.96 < 21.00 < 21.00 12/07122 < .22.15 < 22.19 < 22.15 < 29.34 < 1234 < 29.43 < 29.39 < 29.34 12/13122 < 15.01 < 35.79 < 35.79 < 35.79 < 35.57 < 23.44 < 23.63 < 1123 12/20!22 < 15.95 < 16.96 < 15.95 < 15.95 < 8.137 < 7.421 < 15.20 < 14.24 12127/22 < 31.84 < 33.79 < 31.90 < 31.90 < 14.33 < 10.11 < 20.78 < 20.74 (a) Weekly set was lost in transit and unable to IJe analyzed.

38

TI\BLE:3-4 AIRBORNE [ODINE (10"3 pCitm3)

LOCATIONS PERIOD 24-~

ENDING 22 23

- 01A

- 05A 01/05/22 -< 23.39 <31.15 <27.46 < 27.46 < 36.58 01112122 < 25.74 < 33.50 < 25.88 < 25.74 < 29.72 01/18122 < 19.45 < 8.208 < 81!88 < 8.880 < 8.898 01/25122 < 16.92 < 9.295 '<.15.56 < 15.56 < 15.56 02/01122 < 20.53 < 20.53 <20.57 < 9.326 < 20.57 02108/22 < 11.47 < 11.47 <30.56 < 30.67 < 30.61 02/15122 < 28.73 < 25.98 < 22.73 < 28.78 < 28.41 02/22122 < 1721 <9246 <20.53 < 21.84 <20.94 03/01/22 < 20.86 < 13.95 < 18.12 < 18.38 < 18.25 03/08/22 < 19.89 < 21.07 < 15.29 < 16,11 < 16.08 03/15122 < 33.61 < 35.82 < 15.18 < 33.61 < 35.42 03122/22 < 31.06 < 32.91 < 2024 < 20.10 < 2021 03/291.22 < 19.30 < 16.26 < 23.74 < 24.02 < 23.78 04/05122 < 14.64 < 15..50 < 14.75 < 12.25 < 14.75 04/12122 <24.71 <24-71 <24.37 < 24.71 < 10.29 04/19122 < 19.74 < 19..81 < 18.12 < 17.77 < 18.06 04/26/22 < 33.87 < 33.82 < 6.758 < 6.805 < 6.758 05103122 < 19.56 < 19.56 < *16.39 < 16.30 < 16.39 05110J.22 < 21.86 < 21.86 < 91!96 < 21.98 < 2:1.75 05117122 < 17.31 < 17.31 < 20.78 < 20;85 < 20.81 05124122 < 20.95 < 20.95 < 21.42 < 21.23 < 21.38 05/31/22 < 17.51 < 17.51 < 16.-40 < 16AO < 16.46 06107/22 < 30.73 < 30.73 < 28.06 <28.11 < 28.06 06/14122 < 27.64 < Zl.79 < 27.50 <27.89 < 18.40 06122122 < 25.40 < 25.40 < 23.04 < 22.93 < 23.14 06/28/22 < 37.86 < 38.17 < 38.92 <40~04 < 3827 "Comrm Station 39

TABI..E3-4 AIRBORNE lODlNE (10-3 pCifm3)

LOCATIONS PER!OD ENDING 22 23 24" 01A 05A 07105/22 < 8.-477 < 18.50 < 30.46 < 32.10 < 30.78 07/12122 {a}

07/20/22 < 28.38 < 28.64 < 2.5.45 < 25.13 < 25..33 07126122. < 28.03 < 28.03 < 2.5.84 < 25.95 < 25.84 08/02/22 < 27.70 < 27.70 < 24.39 <24.43 < 24.39 08/09/22 < 29.43 < 29.38 < 29.23 < 29.43 < 1228 08/16/22 < 18.39 < 18.39 -,: 15.20 < 18.36 < 18.29 08/23/22 < 19.04 < 19.04 < 17.26 < 16.93 < 17.05 08/30122 < 23.38 < 11.09 < 22.99 < 22.99 <2295 09/06/22 < 34.03 < 14.27 < 25.39 < 2.5.39 < 25.48 09113/22 <44.51 <44.44 < 40.49 <40.92 < 40.77 09/20122 < 16.91 < 16.97 < 19.65 < 19.37 < 19.61 09/28122 <26.68 < 26.60 < 26.53 < 26.73 < 26.57 10/04122 < 20,15 < 16.89 < 28.01 < 27.83 < 27:95 10/111.22 < 27.32 < 27.32 < 11.32 < 27.32 < 27.08 10/18122 < 116.07 < 16.10 < 16.33 < 7.624 < 16.24 10/25122 < 10.31 < 24.49 < 29.49 < 29.49 < 29.44 11102/22 < 35,22 < 35.28 < 18.79 < 18.76 < 18..88 11/091.22 < 13.82 < 32.96 < 23.50 < 23.46 < 23.50 11115122 < 31.72 < 31.72 < 30.48 < 30.92 < 12.92 11122122 < 26.5:6 < 26.56 < 27.88 < 27.63 < 27.73 11/29/22 < 21.00 < 14.04 < 19.99 < 20.06 < 19.99 12/07/22 < 18.19 < 18.19 < 18.2.5 < 15.27 < 18.25 12/13122 < 23.63 < 23.63 < 23.00 < 23.18 < 23.00 12/20122 < 1427 < 14.27 < 2120 <21.16 < 22.54 12/27/22 < 20.74 < 21.97 (b) < 26.67 < 25.08

'\Control Station (a) Weekly set was rost in transit and unable to be analyzed.

(b) Due to a pump malfunction run time was 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

40

TABLE3-5 AIR PARTfCULA.TES (10-a pCi/m3)

GAl\1lMA SPECTRA- OTR 1 {12128/21 - 03129/22}

LOCOiTION Be-7 Cs-134 Cs-137

(+/-)

01 146.70 22.110 < 1.1610 < 0.6558 02 106.70 24.860 < 127:50 < 0.8541 03 140.00 2:5.160 < 1.4070 < 1.0860 04 129.80 1 21210 < 1.2020 < 0.9061 05 14220 28.860 < 1.3170 < 1.4670 06 121.20 26.310 < 1.1430 < 1.0090 07 156.70 30.390 < 1.7070 < 1.7800 21 150.80 28.020 < 1.1770 < 0.9580 22 107.00 23.170 < 0.9635 < 0.8978 23 154.90 28.350 < 1.1480 < 0.9796 24.. 15250 22.010 < 0.8287 < 0.6876 01A 103.40 23.500 < 1.0310 < 0.9434 05A 152.30 29.940 < 1.8880 < 1.3310 GAM1i\1A SPECTRA. AND STRONTIUM 89/90- QTR 2 (03129122 - 06!28/22)

LOCATION Be-7 Cs-134 Cs-137 Sr-89 Sr-90

(+/-}

01 141.20 26.410 < 1.7590 < 1.87:50 < 9.4100 < 3.7100 02 132.10 .22.940 < 1.2940 < 0.8569 < 7.8100 < 4.2500 03 17220 22.820 < 0.9318 < 0.9674 < 8.6000 < 4.0800 04 148.10 27.9:50 < 1.9660 < 1.7460 < 9.3600 < 4.0200 05 136.40 22.900 < 1.13:50 < 0.9706 < 9.0600 < 4.2800 06 144.60 23.330 < 1.3900 < 1.3850 < 92800 < 4,1700 07 158.00 30.840 < 1.6490 < 0.9719 < 9.300{) < 3.6000 21 14220 21.730 < 1.0520 < 1.2780 < 8.7700 < 4.8300 22 118.60 19.090 < 0.8579 <: 0.8938 < 9.5000 < 5.5600 23 174.00 24.180 < 1.2690 < 1.1080 < 9.6100 < 4.2100 24" 151.70 29.910 < 1.9400 < 1.4570 < 8.3100 < 4.1800 01A 125.70 20.340 < 1.0870 < 0.7541 < 9.6700 < 3.9700 05A 148.60 26.040 < 1.1940 < 1.0070 < 9.7600 < 0.9600

" Control Location 41

TABLE3-5 AIR PARTICULATES (10-3 pCitm3 )

GAMMZI. SPECTRA- OTR 3 (06128122 - 09J28122}

LOCATION Be-7 Cs-134 Cs-137

(+/-)

01 158.10 28.860 < 1.2500 < 0.8641 02 151.80 27.380 < 1.2430 < 1.1850 03 166.50 34.400 < 1.8300 < 2.0750 04 139.50 27.070 < 1.0160 < 0.7964 05 134.10 26.730 < 0.8645 < 1.1200 06 141.80 27.910 < 1.210D < 0.8691 07 156.80 24.360 < 1.3800 < 0.9361 21 119.60 28.640 < 1.2790 < 1.5550 22 134.70 27.050 < 1.3450 < 0.8991 23 153.20 28.140 < 1.4070 <1-179D 24" 133.70 35.900 < 1.666{) < 1.2980 01A 139.20 26.340 < 1.1720 < 0.9337 05A 153.20 25.740 < 1.3870 < 0.7364 GAMMA SPECTRA- QTR 4 (09128122- 12/27122)

Annual Mean LOCATION Be-7 Cs-134 Cs-137 Be-7

(+/-) {+/-)

01 108'.90 19.300 < 1.2140 < 0.99~2 138.73 24.17 02 100.90 22.620 < 1.0180 < 1.1350 122.88 24.45 03 92.520 19.260 < 1.1190 < 0.8909 143.06 25.41 04 115.10 22.450 < 1.2900 < 1.0020 133.13 24.67 05 78.750 16.610 < 1.449D < 0.7666 122.86 23.78 06 95.950 18.760 < 1.0240 < 0.7673 125.89 24.08 07 105.10 22.420 < 1.2230 < 0.6274 144.15 27.00 21 97.520 20.500 < 1.5930 < 1.3320 127.53 24.72 22 11200 26.070 < 1.9740 < 1.4110 118.08 23.85 23 100.70 22.820 < 0.8962 < 1.0030 145.70 25.87 24"' 101.60 21.440 < 1.0600 < 1.1560 134.88 27.32 01A 108.10 17.880 < 1.1670 < 1.1890 119.10 22.02 05A 103.50 19.750 < 1.0390 < 0.8355 139.40 25.37 Mean of AD Indicator Locations 131.71 24.615

Control Location 42

TABLEJ.6 Soil (pCLfkg dry wt)

COLLECTION LOCATION DATE Sr--89 Sr-90 K-40 Cs-134 Cs-137 Ra-226

(+/-) {+/-,--* (+/-}

01 07/05122 < 1120.0 < 36.600 24060 2027.0 < 78.050 < 78.830 < 1431.0 02 07/05122 < 2110.D < 35.300 10020 1437.0 < 91.440 322.60 92.190 1918.0 1137.0 03 07105122 < 1340.0 < 40.000 5401.0 1160;0 < 89.130 168.30 78.270 < 1946.0 04 07/05/22 < 2300.0 < 37.900 5718.0 1263.0 < 109.30 < 147.60 < 2139.0 05 07/05/22 < 2050.D < 33.300 13000 1963.0 < 108.20 269.90 110.70 < 1965.0 06 07/05122 < 1910.0 < 29.900 9652.0 1687.0 < 145.60 < 140.00 < 2471.0 07 07/05/22 < 2090.0 < 29.900 4905.0 1148.0 < 122.40 < 135.30 < 1983.0 21 07105/22 < 2060.0 < 30.300 10120 1527.0 < 93.620 319.30 99.200 < 1779.0 22 07/05/22 < 1900.0 < 35.000 16560 1063.0 < 66.250 < 67.900 2405.0 1165.0 23 07105122 < 2710.0 < 31.100 23470 1369.0 < 71.470 < 64.750 3095.0 817.10 24* 07105122 < 1360.0 < 20.700 23200 1243.0 < 47.840 < 45.300 < 865.00 05A 07105/22 < 1750.D < 28.300 8857.0 77620 < 50.750 59.060 28.140 1357.0 643.30 Mean 12914 1388.6 227.83 81.700 2193.8 940.60 COLLECTION LOCATION DATE

-----* Th-228 Th-232

(+/-) --,+i:j 01 07/05/22 185.90 145.1D < 315.80 02 07105/22 762.90 179.20 715.00 187.00 03 07105/22 480.40 147.10 581.00 209.00 04 07/05/22 781.00 139.70 < 539.10 05 07/05/22 1155.0 170.20 1350.0 277.80 Oi6 07105/22 1958.0 190.60 18520 335.20 07 07/05/22 1106.0 225.30 1374.0 224.10 21 07105122 1118.0 147.50 1215.0 231.40 22 07105/22 1672.0 97.430 1553.0 124.70 23 07105/22 1768.0 86.77D 1718.0 173.50 24* 07/05/22 185.10 58.590 < 214.10 05A 07105122 738.90 74.780 733.00 107.90 Mean 99260 138.52 1232.40 207.84

" Control Location 43

TABLE 3-7 Precipitation (pCi/l)

LOCATION 01A COLLECTION DATE Gr-B H-3 RainFafl (inches)

(+/-) --------------

01/25/22 1.8 1.0 * < 878 5.48 02/22/22 < 1.6 < '1020 1.38 03/29/22 2.6 1.1 < 923 4.26 04/26/22 2.7 'L 1 < 942 2.30 05/31/22 4A 1.3 < 1010 4.87 06/28/22 2.7 1.1 < 936 4.07 07/26/22 10.8 1.8 < 961 2.88 08/30/22 5.3 1.4 < 934 5.30 09/28/22 4.5 1.4 < 961 3.26 10/25/22 < 1.5 < 939 2.44 11/29/22 2.6 1.2 < 1020 2.83 12/27/22 5.2 1.3 < 1180 4.76 Mean 4.3 1.3 Tota! 43.83 44

TABLE3-7 Precfp[tation (pCiJL)

LOCATION 01A COLI.ECTJON DATE Be-7 Mn-54 Fe-59 C0-58 Co-60 Zn-65 Zr-95 06/28/22 < 86.08 < 1.423 < 28.55 < 4.863 < 1.115 < 2.916 < 11.79 12.fll/22 < 44.92 < 1.759 < 12.12 < 3.792 < 1.619 < 3.813 < 7.186 Mean COLI.ECTJON DATE Nb-95 Cs-134 Cs-137 Ba--140 La-140 1-131 Th-228 06/28/22 < 6.922 < 1.274 < 0.982 < 78240 (a} <27250 (a) < 539000 (a) <2277 12lll/22 < 4.141 < 1.826 < 1.570 < 1220 < 396.4 < 8490 < 3.180 Mean (a) Laboratory scheduled composite fate causing the results to be higher than typ[caL 45

TABLE3-6 MU<

(pCifL)

COLLECTION LOCATION DATE K-40 Sr-90 Cs-137"

MHk samples could not be obtained in 2022 due to the Back of dairy farms within the sampling a.rea.

LLD ld!enliffied 111 OOCM 46

TABLE.3-9 Food and Vogolalion

{p,Cllk!:I wet wt.)

LOCATION 146 COLLECTION DATE Be-7 K-40 1-131ff Cs-134""" Cs-137".. Th-228

(+/-) (+/-) (+/-)

04/12122 10330 770.0 3552 667.8 < 52.00 < 47.98 < 40.91 134.2 80.15 05/10122 1072 259.5 4644 607.3 < 33.20 < 29.55 < 20.14 < 41.91 06/14122 1458 265.9 5851 577.2 <49.40 < 27.11 < 26.43 < 46.94 07/12122 1946 507.6 564i0 1062 < 44.50 < 47.87 <52.79 < 99.97 08/09122 1335 305.1 5414 658.2 < 57.10 < 24.14 < 31.26 < 57.79 09/13122 1074 343.4 4005 653.1 < 31.40 < 31.01 < 26.47 < 55.12 10/11/22 1878 521.8 6185 947.2 < 29.30 < 54.25 < 52.10 < 71.34 Me:in 2728 424.8 5042 739.0 134.2 60.15 LOCATION15 COLLECTION DATE Be-7 K-40 l-131H Cs-134"'"" Cs-137""

(+/-) (+/-}

04l12rz2 4755 625.1 5479 846.6 < 38.10 < :36.86 < 37.62 05/10122 1015 362.7 5084 750.5 < 32.10 < 45.41 < 40.98 06/14/22 1848 391.5 5514 795.0 < 34.20 < 35.25 < 26.19 07112/22 960.9 337.5, 5536 908.4 < 44.30 < 48.68 < 41.73 08,09122 1467 308.7 5480 816.9 < 47..00 < 31.86 < :31.83 09113122 742.9 277.3 4691 723.6 < 42.00 < 30.51 < 30.24 10/11/22 2126 313.9 2025 471.8 < 26.40 < :36.36 < 31.90 Mean 1845 373.8 4830 759.0 LOCATION 1ss-COLLECTION

DATE . Be-7

(+/-)

K-40

(+/-)

1-131 ... Cs-134".. Cs-137"* Th-228

(+/-)

04/12122 3175 442.0 5147 849.7 < 43.00 < 37.94 < :39.46 < 73.13 05/10122 7927 224.5 3811 552.7 < 31.50 < 30.05 < 28.41 < 45.08 06/14/22 2669 422.6 5147 743.3 < 42.50 c: 36.22 < 34.41 < 67.65 07/12/22 3081 535.5 5736 848.5 < 41.SO < 48.14 < 40.41 < 92.48 08/09122 843.9 264.9* 3461 602.3 < 43.90 < 26.77 < 30.60 47.70 37.17 09/13/22 1380 268.6 3358 492.3 < 42.70 < 25.30 < 27.83 < 46.70 10/11/22 2890 402.5 4505 638.5 < 22.90 < 30.87 < 33.66 < 67.58 Mean 2119 365.8 4452 675.3 47.70 37.17

--control Station t t LLD identifed in ODCM 47

TABLE:3-9 Food and Vegetation (pC-1/kg wet wt)

LOCJI.TJON 23 COLLECTION DATE Be-7 K-40 1-131"' Cs-134"* Cs-1371:fr Th-226

(+!-)

- (+/-) (+/-}

04/12/22 7708 645.3 3538 595.6 < 48.50 < 45.53 <3826 166.8 75.65 D5/10f22 591.3 247.1 5142 696.0 < 46.00 < 40.3D < 34.26 < 47.04 D6114f22 1973 375.2 4246 642.2 < 38.60 < 36.27 < 35.43 < 59.26 D7/12/22 593.8 311.4 5325 890.7 < 3920 < 44.07 < 39.99 < 77.08 D8/09f22 3230 504.0 3984 800.4 < 58.70 < 45.35 < 40.47 < 70.70 09/13f22 3254 439.3 2473 531.6 < 46.40 < 40.11 < 33.10 103.2 58.43 10/11f22 2713 416.6 3463 572.9 < 25.00 < 34.77 < 34.95 < 79.18 Me:m 2866 419.8 4027 675.6 - - - 135.0 67.04 LOCATJON26 COLLECTION Cs-134"~ Cs-137""

- - DATE

13e-7

(+!-)

K-40

(+/-)

1-131'"'

04/12/22 7308 665.1 3296 719.8 < 53.10 < 43.97 < 34.92 D5/10f22 751.4 365.9 4782 659.5 < 19.9[1 < 26.06 < 31.43 06/14f22 1572 237.6 3513 459.2 < 36.30 < 24.56 < 24.22 07/12/22 1683, 348.1 4012 671.0 < 52.40 < 32.79 < 43.40 D8/09f22 2002 326.1 3159 596.2 < 42.SO < 27.70 < 36.29 09/13/22 1260 350.2 3100 806.3 < 47.30 < 32.47 <29.70 10111122 2856, 533.1 2857 619'.0 < 20.10 < 43.57 < 38.81 Mean 2490 4D6.6 3531 647.3 13e-7 K-40 l-131..., Cs-134° Cs-137"' Th-226

(+/-) (+/-) (+/-)

All Indicator Mean 2482 4D6.3 4358 705.2 - - - 134.7 134.7

""LLD identifed in ODCM 48

TABLE:3-10 WELL \'!/'ATER

{pCi/L}

COLLECTION LOCATION D..i\TE H-3 .... Sr-89 Sr-SO Mn-54 . Fe-59 Co-58 Co-60 ... Zn-65 01A 03/29122 < 921 (a) (a) < 8.52 < 14.2 < 9.08 < 8.92 < 18.1 06/28122 < 931 < 3.73 < 0.808 < 6.70 < 14.1 < 6.94 < 7.79 < 15.9 09/28122 < 957 (a) (a) < 5.86 < 11.5 < 5.35 < 7.24 < 12.6 12/27/22 < 1190 {a) (a) < 6.57 < 14.9 < 7.45 < 8.14 < 16.3 Mean COLLECTION LOCATION DATE Zr-95 Nb-95

~----- 1-131

------ Cs-134 . Cs-137 Ba-140 La-140 01A 03/29122 < 14.7 < 10.7 < 9.46 < 8.60 < 8.37 < 32.6 < 13.6 06/28122 < 12.7 < 9.81 < 9.,85 < 7.6,6 < 7.37 <28.6 < 10.0 0912.8122 < 9.28 < 7.82 <8.84 < 5.18 < 5.86 < 24.4 < 7.82 12/27/22 < 13.1 < 9.15 < 9.78 < 8.51 < 7.97 <29.6 < 10.3 r1.1iearn (a} Sr-89190 analyses performed on the second ,q1mrter samp[e.

49

TABlE:3-11 River Water

{pCi/L)

LOCATION11 COUECTION DATE H-3 Sr-89 Sr-90 Mn--54.. Fe--59" Co-58" Co-60* Zn-65*

r-;;:;-- -* -*

01/12/22. (a) (b) (b) < 5.538 < 10..96 < 5.484 < 5.659 < 14.02 02/15122 {a) (b) (b) < 4.818 < 7.197 < 4.094 < 4.414 < 9.321 031'15122 4680 857.0 (b) (b) < 4.623 < 8.991 < 4.024 < 6.118 < 9.141 04/121.22 (a} {b) (b) < 6.155 < 14.46 < 5.101 < 5.140 < 10.58 05/17122 (a} (b) (b) < 5.257 < 1264 < 6.068 < 7.538 < 11.38 06/14122 5120 902.0 <4.700 < 0.,874 <4.204 < 8.122 <4.953 < 6.233 < 9.332 07126122. (a) (b) (b) < 7.937 < 11.96 < 7..202 < 9.687 < 14.9!2 08/16.122 {a) (b) (b) < 4.615 < 8.733 < 4.878 < 5.285 < 11.54 09/131'22 5330 8920 (b) (b) < 5.302 <11.94 < 6.453 < 9.192 < 8.477 10/11122 {a) (b) (b) < 1.678 < 3.689 < 1.977 < 1.925 < 3.369 11/15122 {a) (b} (b) < 4.662 < 9.791 < 5.049 <7.461 < 11.61 12/13122 6940 972.0 (b) (b) < 5.584 < 1232 < 5.087 < 6.466 < 11.66 rv~an 5518 905.8 Nb-95"" Zr-95" 1-131" Cs-134" Cs-137" Ba-140* La-140" 0111~..a < 5.472 < 10.28 < 0.427 < 6.006 < 6.311 < 24.48 < 9.000 02/15122 < 4.713 < 8.468 < 01125 < 5.486 < 5.164 < 26.18 < 6.604 031'15122 < 4.079 < 9.833 < 0.775 < 4.190 < 5.368 < 21.63 < 8.527 041121.22 < 6283 < 10.30 < 0.751 < 6.275 < 7.051 < 26.86 < 13.444 05/17122 < 5.7r.r/ < 10.72 < 0.827 < 6.100 < 4.822 < 23.84 < 8.002 06/14/22. < 4.374 < 6.342 < 0.712 < 5.818 < 5.788 < 24.34 < 7.141 07/26122 < 7.288 < 1255 < D.:852 < :8.857 < 4.194 < 23.95 < 10.99 08/16/22. < 4.584 < 7.664 < 0.794 < 4.338 < 5.053 < 20.56 < 5.052 09/131'22 < 6.451 < 11.57 < 01154 < 6.992 < 5.981 < 22.66 < 9.192 10/11122 < 1.710 < 2.825 < 0.320 < 1.746 < 1.701 < 6.496 <2099 11/15122 < 5.493 < 10.06 < 0.985 < 6.181 < 7.007 < 25.82 < 7.902 12/131'22 < 5.469 < 11.17 < 0.920 < 6.162 < 7.024 < 22.13 < 6.497 t\/ieoo

" LLD identiliec!I in OOCM.

{a) Tmium analyses on quarterty composite.

Sr-89/90 perfom,ed on 2nd quarter composite sample.

50

TABLE3-12 SUrface Water (pCi/L)

LOCATION OB COU..ECTION DATE Mn-54" Fe-59""

H-3

{+/-}

Sr-89 Sr-90 Co-58*

, - Co-60* 2n-65*

01/12/22 (a) (b) (b) < 4.601 < 8.796 < 5.429 < 7.196 < 11.75 02/15/22 (a) {b) (b) < 4.890 < 10.94 < 4.805 < 5.618 < 10.95 03/15/22 4170 831.0 {b) (b) < 4.486 < 12.02 < 4.500 < 4.745 < 11.44 04/12/22 (a) (b) (b) < 5,544 < 15.33 < 6.333 < 5.071 < 13.57 05/17/22 (a} (b) (b} < 6.888 < 13.41 < 7.139 <7206 < 8.779 06/14/22 7750 1020 < 3.460 < 0.901 < 6.350 < 14.04 < 7.071 < 8.001 < 15.31

,QJl2B/22 (a) (b} (b} < 5.954 < 10.68 < 5.505 < 6.609 < 13.8:9 08116/22 (a} (b} (b) < 5.612 < 10.16 < 6.940 < 7.412 < 13.68 09/13122 5670 908.0 (b) (b) < 6.'f37 < 14.80 < 6.041 < 7.716 < 14.43 110/11/22 {a) (b} (b} < 3.044 < 6.222 < 3.384 < 3.764 < 6.401 11/15/22 (a) (b) (b) < 6.794 < 15.23 < 6.914 < 5..596 < 13.22 112/13122 8440 1040 (b) (b) < 4.327 < 11.10 < 7.389 < 5.789 < 10.93 Mean 6508 949.8 NIJ.-95 .. CS-134* Ba-140..

2r-95* 1-131"'

1 I Cs-137"'

* ... la-140" 01/12122 < 5.162 < 7.977 < 0.730 < 5.668 < 5.810 < 21.61 < 5.244 02115/22 < 5.898 < 10.82 < 0.724 < 5.389 < 5.603 < 23.35 < 8.395 03115/22 < 6.333 < 7.744 < D.837 < 6.610 < 4.678 < 31.18 < 8.381 04/12/22 < 8.348 < 11.69 < 0.B31 < 6.519 < 7.259 < 25J)7 <6-767 05/17/22 <6247 < 9.926 < 0.872 < 8.978 < 6.568 < 24.69 < 9.780 06/14/22 < 8.972 < 10.33 < 0.820 < 6.203 < 6.689 < 26.46 <7235 07/26/22 < 4.827 < 12.73 < 0.871 < 6.916 < 6.110 < 23.36 < 9286 08116/22 < 6.787 < 12.07 < 0.696 < 5.996 < 7.036 < 22.32 < 7.100 09113!22 < 7.589 < 12.92 < 0.834 < 5.105 < 5.141 < 21.26 < 5.672 10/11/22 < 2.757 < 5.009 < 0.922 < 2.871 < 3.247 < 10.85 < 4.189 11/15122 < 6.480 < 12.13 < 0.B27 < 6.729 < 6.946 < 25.66 < 6.863 12/13122 < 5.863 < 10.89 < 0.887 < 8.035 < 7.531 < 21.14 < B.290 Mean

" llD identified in ODCM.

(a) Tmum analyses on quarterly oomposll:e.

(b) Sr-89/90 performed on 2nd quairter composite sample.

51

TABlE3-12 SUrface Water (pCi/L)

LOCAT[ON 09A-COUJECT!ON DATE H-3 Sr-89 Sr-90 Mn-54"' Fe-59"' Co-58.. Co-60" 2n-65*

01/12122 (a) (b} (b) < 7.158 < 12.09 < 7.2fll < 7.924 < 16.10 02fl5/22 {a) {b) (b) < 4.987 < 11.46 < 4.613 < 6.083 < 12.49 03/15122 <954 {b) (b) < 4.433 < 10.77 <4208 <4.000 < 10.56 041112'22 (a) (b} (b) < 7.319 < 14.:39 < 6.191 < 5.729 < 12.73 05/17/22 (a) (b) (b) < 6.017 < 10.05 < 6.660 < 5.635 < 13.72 06/14r..d2 < 1010 < 4.300 < 0.806 < 6.867 < 12.04 < 6241 < 9.396 < 8.959 07J26122 (a) (b) (b) < 6.277 < 9.120 < 5.734 < 6.110 < 10.74 0&(16/22 {3) {b) (b) < 6.70'3 < 10.01 < 5.357 < 6.002 < 15.02 09/13122 < 964 {b} (b) < 6.301 < 11J52 < 5.65 < 5.750 < 13.97 10/11122 (a} {b) (b) < 3.080 < 5.969 < 2.640 < 3.36.B < 6.117 11115122 (a} (b) (b) < 5.837 < 1215 < 6.532 < 7.493 < 9..547 12£13122 <984 {b) (b) < 7:1'72 < 13.53 < 6.543 < 7.937 < 12.78 Mean Nb-95"" zr-95* 1-131" Cs-134* Cs-137" Ba-140" I ... La-140" 01/12'22 < 6.898 < 11.74 < 0.369 < 7.-439 < 7J)95 < 22.81 < 5.92B 02£15122 <5200 <10.00 < 0.782 < 5.189 < 5.507 < 22.76 < 9.534 03/15122 < 4.522 < 8.827 < 0.877 < 5.495 < 5.029 < 23.32 < 8.740 04!12122 < 5.246 < 11.64 < 0.880 < 5.824 < 5.052 < 17.05 < 9.231 05117122 < 7.220 < 11.19 < 0.803 < 8.092 < 7.521 < 20.47 < 8.864 06/14122 <4.876 < 9.037 < 0.77:9 < 6,033 < 5.593 < 18.11 <8269 07126l22 < 5.742 < 8.953 < OJ382 < 7.159 < 5.503 < 23.43 < 7.006 08/16/22 < 5.180 < 10.53 <0]24 < 6,170 < 6.756 < 23.79 < 8.765 09113122 < 6.151 < 9.520 < 0.797 < 5.840 < 5.982 < 20.62 < 7.647 10/111122 < 2.780 < 4.689 <0.327 < 2.983 < 3.466 < 111.34 < 4.276 11/15.122 < 5.897 < 7.724 < 0.878 < 7.394 < 6.140 < 16.31 < 8.670 12/13/.22 < 7.806 < 1276 <0.fJ ,3 < .8.615 < 7.599 < 30.36 < 6.56 Mean

" LLD Identified in O:DCM.

-eontrol location.

(a) Ttffium analyses on quartell'fy composite.

(b) Sl"-89/90 performed on 2nd quarter oomposite sample.

52

TABLE3-13 Sedimentsm (pCf/kg dry wt.)

LOCATION COLLECT[ON DATE ,________

Sr-89 Sr-90

* K40 Cs-134

- Cs-137 Ra-226

{+/-)

08 04/12122 (a) {a) 1716 517.6 <4274 < 31.34 < 917.5 09N 04/12122 (a) (a} 14580 1482 < 53.91 < 52.93 < 1065 11 04/12122 (a) (a) 17610 1829 < 89.23 < 73.39 < 1797 08 10117122 < 1750 < 30.30 1819 681.4 < 46.23 < 48.1:5 < 899.1 09N 10/17122 < 1810 < 29.70 13340 1677 < 68.58 < 70.64 < 1304 11 10/17122 < 1680 < 32.30 18G50 1692 < .86.90 <7294 < 1321 Indicator l\i'!ean 9799 1180 Control Mean 13960 1580 COLLECTION LOCATION 08 DATE 04/12122

- To-228

(+/-)

< 68.22 Th-232

(+/-)

< 133.3 09N 04112r22 90.94 58.49 < 279.3 11 04/12122 635A 118.7 <445.5 08 10/17122 < 76.41 < 239.5 09A"' 10/17122 240.8 93.43 < 38il1 11 10/17122 7102 114.7 952.3 205.7 Indicator Mean 672.S 116.7 952.3 205.7 Control Mean 165.9 75.96 (a) Sr-89/90 analyses preformed annuany.

" Gonlrol locatron, Background location 53

TABLE3-14 Shoreiim~ So!!

(pCrJ:kg dry wt.)'

LOCATIONS COLLECTION LOCATION DATE Sr-89

. Sr-90 K-40

(+/-)

Cs-137* Ra-226 08 04/12122 (Ci) {a) 1521 571.0 < 45.44 < 48.63 < 789.6 08 10/17122 <1780 < 45.1(} 1011 548.0 < 64.21 < 48.69 < 967.3 Mean 1266 5595 COLLECTION LOCATION DATE Th-228 Th-232

(+/-)

08 04/12122 9927 56.17 < 265.2 08 10/17/22 < 86.09 < 184.4 Mean 99.27 56.17

LLD identified on ODCM (a) Sr-89/00 a11alyiles performed annually.

54

TABLE:3-15 As.ti

{pCimg wet'Wt)

COLLECTION LOCATl,ON FillhType DATE .K-40 Mn-54"" Fe-59,t- Co,..S,&r Co-60* Zn-65"

(+/-)

08 (a) 05109/22 1166 3002 < 19.48 < 41.25 < 18.74 < 20.81 <41.73 (b) 05109122 1457 382.3 < 23.14 < 48.86 < 23.72 < 23.13 < 47.58 (a) 11102/22 1117 351.7 < 23.9'3 < 5'9.71 < 22.75 < 28.05 < 50.78 (b) 11/02122 648.1 405.6 < 31.85 < 61.01 < 33.96 < 29.15 < 61.93 25.... (a) 05111/22 1350 820.3 < 57.54 < 109;2 < 73.26 < 64.77 < 136.8 (b) 05111/22 1728 993.3 < 66.65 < 125.6 < 64.84 < 48.22 < 103.9 (a) 11128/22 1349 694.8 -< 52.61 < 102.2 < 63.59 < 69.73 < 103.6 (b) 11129/22 2096 1098 < 67.21 < 181.0 < 77.62 < 81.00 < 152.2 Mean 1:364 630.8 Indicator Mean 1097 360.0 ComrolMean 1631 901.6 COLLECTION LOCATION DATE Cs-134"" Cs-137" 06 (a) 05109/22 <21.24 < 20.66 (b) 05'09122 < 24.45 < 25.25 (a) 11!02/22 <24.48 < 24.52 (b) 11!02122 < 34.07 < 35.94 2&" (a) 05111/22 < 61.59 < 53.92 (b) 05111/22 < 63.66 < 55.S-4 (a) 11128/22 < 58.51 < 52.57 (b) 11/29/22 < 74.92 < 76.3-B Mean Indicator Mean Corntrol Mean

LLD fdentified in ODCM

"*Control Station (al Non-bottom dweamg 6peeies of gameffsh.

(b) aottom divelling .f.llpecies offi6h.

55

4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2022 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 Interlaboratory Comparison Programs are provided in Appendix B.

The predominant radioactivity detected throughout 2022 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. In the past, Cs-137, a plant related nuclide, has been detected in soil and aquatic sediment samples at levels corresponding to levels associated with fallout from nuclear weapons tests.

The following is a discussion and summary of the results of the environmental measurements taken during the 2022 reporting period.

4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. TLDs are placed in two concentric rings around the station. The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population areas and nearby residences. Additional TLDs serve as controls. Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.

The results of the analyses are presented in Table 3-2. Figure 4-1 shows 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 CaSO4:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs. This will continue to be monitored.

56

9.0 8.0 r 7.0

~

C 0 6.0

~

V 5.0

~ - Environmental TLD E 4.0

- sectorTLD 3.0 2.0 1.0 0.0

~~~~o~NMV~~~~~o~NM~~~~~~o~NM~~~~~~o~N

~~~~~~~~~~~~~~0000000000----------NNN ccccccccccccccccccccccccccccccccccccc rorororororororororororororororo~~~~~~~~~~~~~~~~~~~~ro

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

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 3.7 mR/standard month with a range of 0.6 to 7.5 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61. This value was 6.4 mR/standard month. This location is on site on the Laydown Area north gate. 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 3.0 mR/standard month with a range of 1.4 to 5.2 mR/standard month. The average annual reading for these locations was 3.1 mR/standard month with a range from 1.4 to 4.6 mR/standard month. The control location showed a quarterly average of 2.6 mR/standard month with a range of 2.3 to 2.9 mR/standard month. Its annual reading was 3.1 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 4.6 mR/standard month with EPSP-9/10 having the highest quarterly average of 6.9 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 .0 mR/ standard month, while Station C-1/2 and C-5/6 had a quarterly average of 2.3 mR/standard month with a range of 0.9 to 3.0 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.

4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3 . A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. The drop indicated in 2009 is a function of a return to the vendor used from 1988 until 2001. Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.

Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady. During the preoperational period of July 1, 1974 through March 31 , 1978 gross beta activities ranged from a low of 0.005 pCifm3 to a high of 0.75 pCifm3 .

57

0.12 0.1 0.08 m

E

,. - control uQ. 0.06

- Indicator

- Average Pre-Op 0.04 Requi red LLD 0.02 0

Figure 4-2 Historical Gross Beta in Air Particulates 3.00E-02 2.SOE-02 2.00E-02 m

E

,. 1.SOE-02 - control u0.

- lncicator l.OOE-02 5.00E-03 O.OOE+OO rn en en

~C ~C:

'<t 0

" "5" ~I ID 00 N

~ .-1

~ ~

'<t

.-1 :;i ~I .-1 ID

.-1 .-1 .-1 ~ 1... .-1 .-1 N 0

N 2-. N N

... ... ... ... ... =

... ... = ... ... ... ...

I I I I I I I I _!. I C:

IV "S C

IV "S C:

IV C:

IV

, IV "5 C:

IV

, C:

IV IV "S Figure 4-3 2022 Gross Beta in Air Particulates (pCilm 3) 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.

58

4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy. The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected. The results of these analyses indicate the lack of station effects on the environment.

4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations. There has been no detection of these fission products at any of the indicator or control stations in recent years.

4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2022. Cs-137 was identified in 5 of 11 indicator samples. The average for indicator stations was 227.83 pCi/Kg. No plant related isotopes were identified in the sample from the control station. During the preoperational phase Cs-13 7 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout. No other plant related isotopes were identified in Soil samples during 2022.

4. 7 Precipitation A sample ofrain water was collected monthly, when available, at on-site station 0lA and analyzed for gross beta activity and H-3. The results are presented in Table 3-7. Twelve precipitation samples were obtained in 2022. 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 not 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 2022 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter.

4.8 CowMilk Milk samples were unavailable during the reporting period due to the closure of the final operating dairy within the sampling area on 1/1/18.

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. Naturally occurring potassium-40 and cosmogenic beryllium-7 were detected in all samples.

Naturally occurring thorium-228 was detected in four of thirty five samples. No plant related isotopes were identified in any vegetation sample during 2022.

4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory. These samples were analyzed for gamma 59

radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, I-131, and gamma emitters. The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period.

4.11 River Water Samples of water from the North Anna River were collected monthly. The analyses are presented in Table 3-11. All monthly samples are analyzed by gamma spectroscopy. The monthly samples are composited quarterly and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90 in accordance with program requirements. There has been no detection of these fission products at any of the indicator or control stations in recent years.

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 5518 pCi/liter and a range of 4680 to 6940 pCi/liter, see Figure 4-4. No river water samples were collected during the pre-operational period.

10000 9000 8000 7000 6000

...J uC.

5000 -Tritium 4000 ---Required LLD 3000

-2000 1000 0 ~------------------

~ ~ ~ffl ~~ ~~ ~~ ~~ ~~ ~8 o~

~~~~~~~~~~~~~~~00000000000000000000000 a~~~~~~~~~~~~~~~~~~~

~~---------NNNNNNNNNNNNNNNNNNNNNNN Figure 4-4 Tritium in River water 4.12 Suiface 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. Tritium was not detected in any sample at the control location. The average level of tritium activity at the indicator location was 6508 pCi/L with a range of 4170 to 8440 pCi/L.

60

20000 18000 16000 14000

....1 12000

~ 10000 -Tritium 8000 -Required LLD 6000 -Avg. Pre-Op 4000 2000 0

N M "<t" .,... u, u, r--- r--- r--- .,...

co co 0 0

~ "<t" N N N N u >-.~ '°.:. '°OJI M

.,... .,... .- .,... °' .:...

.:. 0.. .D. °'

°'u N N

,._ ~

>,, +J '":" '":" N C: C:

nl :J

-, -, ~ ,:_a. 6...

z <( Vl LL -,

1J a, a, :5 a, nl u nl ::J Cl :EO :E <(

nl ::J ~ a. OJ a, -,

C: C:

-, -, z <( Vl LL

J a, Cl nl u t:JJl C: C:

nl :J nl :J

E 0 :E <( -, -,

Figure 4.5 Tritium in Su,face Water 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup ofradionuclides in the environment due to the operation of the station. Buildup ofradionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.

Sediment samples were collected during April and October from each of three locations and were analyzed by gamma spectroscopy. The October samples were analyzed for strontium-89 and strontium-90. The results are presented in Table 3-13.

No plant related isotopes were detected in 2022. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented.

During the pre-operational period sediment samples were also analyzed by gamma spectroscopy. Figure 4-6 shows the historical trend of Cs-13 7 in sediments.

Neither Strontium-89 nor Strontium-90 was detected in any samples of aquatic sediment/silt in 2022. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests. Several naturally occurring radioisotopes were detected in these samples at background levels.

61

.-----*-; ~------- --~-~-~-::=*~:- .---. :~~=:**=--=:--~~ :::~-=:=---~-=~:-=.:=-*==--:~*=-=~~:.: ------* .. ***---------** ----. --.

I 300 --- -------- - --------*- ----------- -------------**-*-***--*-

250

~

5 200 u -station OS C.

150 - - .. -- -.. --** -----* .. -control Sta 09A

-stationll 100 50 0

0 .-1 N rl'l U"l r-- Cl) 0 rl'l s:1- U"l l.O r-- co Cl) 0 .-1 N 0

I 0 0 0 0 0 0 .-1 .-1 .-I .-1 .-1 ...; .-I .-1 N N N I I I I I I I I I I I I I I I I

..0 (JJ

..c (JJ

..0.

(JJ

..0 (JJ

..c (JJ

..0 (JJ

..c (JJ

..c (JJ u.. u.. u.. u.. u.. u... u.. u.. u.. u.. u.. u... u.. u.. u... u... u... u..

L__ _ --------

Figure 4-6 Cs-137 in Sediment/Silt 4.14 Shoreline Soil Shoreline soil/sediment, unlike bottom sediment, may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses.

Samples of shoreline soil were collected in April and October from indicator station 08. The samples were analyzed by gamma spectroscopy. The October sample was analyzed for strontium-89 and strontium-90. The results are presented in Table 3-14.

Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities. No plant related isotopes were detected in any indicator samples analyzed. Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is attributed to accumulation ofresidual 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 2022 and analyzed by gamma spectroscopy. Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately. The results are presented in Table 3-15. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected. Cs-137 was measured in pre-operational environmental fish samples.

62

5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2022 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14B, 15, 16,23,26 Vegetation 01/12/22 Seasonal unavailability 14B,15,16,23,26 Vegetation 02/08/22 Seasonal unavailability 14B,15,16,23,26 Vegetation 03/08/22 Seasonal unavailability 14B, 15, 16,23,26 Vegetation 11/09/22 Seasonal unavailability 14B,15,16,23,26 Vegetation 12/13/22 Seasonal unavailability TLD's missing due to power pole SSE-16/48 TLD 03/29/22 being replaced 01-07,01A,05A AP I Charcoal 07/25/22 Shipping container damaged, 21-24 samples lost Shipping container damaged, 08,09A,11 Surface Water 07/25/22 samples lost. Re-sampled River Water 7/26/22.

TLD was misplaced by vendor S-18 TLD 06/28/22 for 2nd Quarter 2022 Air sampler malfunction.

24 AP I Charcoal 12/27/22 Insufficient sample volume to meet required LLD.

63

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 10CFRS0, 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 0472, "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.

64

APPENDICES 65

APPENDIX A: LAND USE CENSUS Year2022 LAND USE CENSUS North Anna Power Station Louisa County, Virginia January 1 to December 31, 2022 Direction Distance (miles)

Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden(> Meat Milch Milch Boundary 50m2) Animal Cow Goat N 0.87 1.3 2.75 NONE NONE NONE NNE 0.85 0.9 3.25 1.6 NONE NONE NE 0.82 0.9 1.6 1.6 NONE NONE ENE 0.81 2.37 2.4 2.49 NONE NONE E 0.83 1.25 2.05 3.5 NONE NONE ESE 0.85 1.53 1.7 NONE NONE NONE SE 0.88 1.4 1.9 1.4 NONE NONE SSE 0.91 1.0 2.66 1.6 NONE NONE s 0.94 1.03 1.48 2.0 NONE NONE SSW 1.01 1.11 2.00 2.0 NONE NONE SW 1.06 1.56 3.96 NONE NONE NONE WSW 1.09 1.62 2.26 NONE NONE NONE w 1.06 1.5 1.96 NONE NONE NONE WNW 1.02 1.1 2.67 NONE NONE NONE NW 0.97 0.98 1.09 NONE NONE NONE NNW 0.90 1.0. 1.33 2.3 NONE NONE 66

2021 to 2022 Land Use Census Changes 2021 2022 Nearest Direction Distance Distance Resident ESE 1.70 1.53 SW 1.65 1.56 Site Boundary NONE Garden ESE 1.70* 1.70*

SE 1.40 1.90 w 1.93 1.96 Meat Animal NONE Milch Cow NONE Milch Goat NONE

Physical Address Changed, Distance Stayed the Same 67

APPENDIX B:

SUMMARY

OF INTERLABORATORY COMPARISONS YEAR2022 Summary of Results - Inter-laboratory Comparison Program (ICP)

The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate (AP), air iodine, milk, soil, vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

A. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria.

B. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the US EPA, National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

C. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

Acceptable (flag = "A") - result within +/- 20% of the reference value

Acceptable with Warning (flag = "W') - result falls in the +/- 20% to +/- 30% of the reference value

Not Acceptable {flag = "N") - bias is greater than 30% of the reference value 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.

For the TBE laboratory, 142 out of 150 analyses performed met the specified acceptance criteria. Eight analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program. NOTE: Two analyses (soil for Tc-99 and U-238) that did not meet acceptance criteria was performed for TBE information and is not on the list of required /GP analyses.

A summary is found below:

1. The Analytics March 2022 AP Ce-141 result was evaluated as Not Acceptable. The reported value for Ce-141 was 60.9 pCi and the known result was 42.0 pCi/L (1.45 ratio of reported result vs. known; TBE's internal acceptance range is 0. 70 - 1.30). This sample was used as the workgroup duplicate with a result of 45. 7 (109% of known) and was also counted on a different detector with a result of 50.9 (121% of known). This was TBE's first failure for AP Ce-141. (NCR 22-04)

2. The MAPEP February 2022 Urine U-234 & U-238 results were evaluated as Not Acceptable.

68

TBE's reported values of 0.142 and 0.0254 were above the known upper ranges of 0.0096 and 0.0134 respectively for U-234 and U-238. These spiked values were below TBE's typical MDC for urine client samples. The samples were re-prepped using a larger sample aliquot and counted for 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months as opposed to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The recount results were 0.00732 for U-234 and 0.0119 for U-238 (both within acceptable range). MAPEP urine samples will be flagged to use a larger sample aliquot and counting time than typical client samples. MAPEP did not include any urine cross-check samples in August. (NCR 22-05)

3. The ERA MRAD September 2022 AP Pu-238 was evaluated as Not Acceptable. The reported value was 38.8 pCi and the known result was 29.9 (acceptance range 22.6 -36.7). The AP filter was cut in half prior to digestion (shared with Fe-55) but should have been complete digested together and aliquotted afterwards like typical client samples. This is the first failure for AP Pu-238. (NCR 22-19)

4. The ERA October 2022 water Uranium result was evaluated as Not Acceptable. The reported value was 10.54 pCi/L and the known was 8.53 (acceptance range 6.60-9.88) or 124% of the known (acceptable for TBE QC). The 2-sigma error was 3.2, placing the reported result well within the acceptable range. This sample was used as the workgroup duplicate with a result of 8.2 +/- 2.9 pCi/L (also within the acceptable range). All other QA was reviewed with no anomalies. (NCR 22-20)

5. The Analytics AP Co-60 result was evaluated as Not Acceptable. The reported value was 207 pCi and the known was 147 (141% of the known). TBE's internal QC acceptance is 70 - 130%. All QA was reviewed with no anomalies. This sample was used as the workgroup duplicate and counted on a different detector with a result.of 167 pCi (114% of the known). This is the first failure for AP Co average result ratio compared to the known is 109%. (NCR 22-21)

6. The MAPEP August 2022 water Tc-99 result was evaluated as Not Acceptable. The reported value was 1.86 +/- 0.414 Bq/L for this "false positive" test. The evaluation of the submitted result to the 3 times the uncertainty indicated a slight positive. This sample was used as the workgroup duplicate with a result of 0.88 +/- 0.374 Bq/L. All QC was reviewed, and no anomalies found.

This is the first unacceptable since the resumption of reporting water Tc-99 for the 3rd quarter of 2020. TBE to known ratios have ranged from 94-109% during this time. (NCR 22-22)

The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.

69

Analytics Environmental Radioactivity Cross Check Program Teledl!:ne Brown En9ineerin9 Environmental Services TBE Identification Known Ratio of TBE to MonthNear MatriX Nuclide Units Reported Evaluation Cbl Number Value caJ Analytics Result Value March2022 E13706 Milk Sr-89 pCi/L 80.3 96.8 0.83 A Sr-90 pCi/L 127 12.6 1.01 A E13707 Milk Ce-141 pCi/L 623 65 0.96 A Co-58 pCi/L 158 164 0.96 A Co-60 pCi/L 286 302 0.95 A Cr-51 pCi/L 314 339 0.93 A Cs-134 pCi/L 155 182 0.85 A Cs-137 pCi/L 210 223 0.94 A Fe-59 pCi/L 211 185 1.14 A 1-131 pCi/L 88.0 96.7 0.91 A Mn-54 pCi/L 169 164 1.03 A Zn-65 pCi/L 238 246 0.97 A E13708 Charcoal 1-131 pCi 79.9 87.1 0.92 A E13709 AP Ge-141 pCi 60.9 42.0 1.45 NC1J Co-58 pCi 118 107 1.11 A Co-60 pCi 218 196 1.11 A Cr-51 pCi 251 221 1.14 A Cs-134 pCi 129 118 1.09 A Cs-137 pCi 156 145.0 1.07 A Fe-59 pCi 124 120.0 1.03 A Mn-54 pCi 120 "107 1.12 A Zn-65 pCi 162 160 1.01 . A E13710 Soil Ce-141 pCi/g 0.123 0.103 1.19 A Co-58 pCi/g 0.254 0.263 0.97 A Co-60 pCi/g 0.493 0.483 1.02 A Cr-51 pCi/g 0.603 0.543 1.11 A Cs-134 pCi/g 0.268 0.292 0.92 A Cs-137 pCi/g 0.399 0.431 0.93 A Fe-59 pCi/g 0.320 0.296 1.08 A Mn-54 pCi/g 0.263 0.263 1.00 A Zn-65 pCi/g 0.407 0.395 1.03 A E13711 AP Sr-89 pCi 83.2 97.4 0.85 A Sr-90 pCi 12.7 12.7 1.00 A (a) The Analytics known value fr: equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A =Acceptable - reported result fa/fa within ratio limits of 0.80-1.20 W =Acceptable with warning- reported result falls within 0.70-0.80 or 1.20-1.30 N =Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1.30 70

Analytics Environmental Radioactivity Cross Check Program Teledlne Brown Engineerin9 Environmental Services TEE Knovm Identification Ratio of TEE to MonthNear Matrix Nuclide Units Reported Evaluation Cb>

Number Value<a> Analytics Result Value September 2022 E13712 Milk Sr-89 pCi/L 71.1 89.1 0.80 A Sr-90 pCi/L 12.0 13.6 0.88 A E13713 Milk Ce-141 pCi/L 148 161 0.92 A Co-58 pCUL 178 189 0.94 A Co-60 pCi/L 229 260 0.88 A Cr-51 pCi/L 486 456 1.07 A Cs-134 pCi/L 220 252 0.87 A Cs-137 pCi/L 203 222 0.92 A Fe-59 pCi/L 174 173 1.01 A 1-131 pCi/L 75.9 94.2 0.81 A Mn-54 pCi/L 269 282 0.95 A Zn-65 pCi/L 364 373 0.97 A E13714 Charcoal 1-131 pCi 81.4 83.6 0.97 A E13715 AP Ce-141 pCi 102 91 1.12 A Co-58 pCi 118 107 1.11 A Co-60 pCi 207 147 1.41 N(2l Cr-51 pCi 310 257 121 w Cs-134 pCi 148 142 1.04 A Cs-137 pCi 137 125 1.10 A Fe-59 pCi 115 98 1.18 A Mn-54 pCi 168 159 1.05 A Zn-65 pCi 240 211 1.14 A E13716 Soil Ce-141 pCUg 0288 0.284 1.01 A Co-58 pCi/g 0.320 0.334 0.96 A Co-60 pCi/g 0.445 0.459 0.97 A Cr-51 pCUg 0.883 0.805 1.10 A Cs-134 pCUg 0.410 0.446 0.92 A Cs-137 pCUg 0.447 0.465 0.96 A Fe-59 pCUg 0.314 0.305 1.03 A Mn-54 pCUg 0.489 0.499 0.98 A Zn-65 pCUg 0.666 0.660 1.01 A E13717 AP Sr-89 pCi 87.5 98.3 0.89 A Sr-90 pCi 126 15.0 0.84 A (a) The Analytics known value fa equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measuremenfa made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0. 70-0.B0 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1.30 71

DOE's Mixed Analyte Perfonnance Evaluation Program {MAPEP)

T eled:r:ne Brown En~ineerini Environmental Services Identification TBE Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation {b)

Number Value (a) Range Value February 2022 22-GrF46 AP Gross Alpha Sq/sample 0.402 1.20 0.36-2.04 A Gross Beta Sq/sample 0.669 0.68 0.341 -1.022 A 22-Ma846 Soil Ni-63 Sq/kg 645 780 546-1014 A Tc-99 Bq/1,g 526 778 545 -1011 N!3l 22-MaSU46 Urine Cs-134 Bq/L 1.67 1.77 1.24-2.30 A Cs-137 Bq/L 1.50 1-56 1.09-2.03 A Co-57 Bq/L 4.93 5.39 3.77- 7.01 A Co-60 Bq/L 2.13 2.06 1.44-2.68 A Mn-54 Bq/L 4.83 5.08 3.56-6.60 A U-234 Bq/l 0.0074 N(4J 0.142 0.0052 - 0.0096 U-238 Bq/L 0.0254 0.0103 0.0072 - 0.0134 N(4J Zn-65 Bq/L 4.71 4.48 3.14-5.82 A 22-MaW46 Water Ni-63 Bq/L 28.6 34.0 23.8-44.2 A Tc-99 Bq/L 8.59 7.90 5.5-10.3 A 22-RdV46 Vegetation Cs-134 Bq/sample 6.61 7.61 5.33-9.89 A Cs-137 Sq/sample 1.50 1.52 1.06-1.98 A Co-57 Sq/sample 5.11 5.09 3.56-6.62 A Co-60 Sq/sample 0.0162 (1) A Mn-54 Sq/sample 2.42 2.59 1.81- 3.37 A Sr-90 Bq/sample 0.684 0.789 0.552 - 1.026 A Zn-65 Sq/sample 1.44 1.47 1.03-1.91 A August2022 22-MaS47 Soil Ni-63 Bq/kg 14.6 (1) A Tc-99 Bq/kg 994 1000 700-1300 A 22-MaW47 Water Ni-63 Bq/L 24.4 32.9 23.0 428 A Tc-99 Bq/L 1.9 (1) NC5J 25-RdV47 Vegetation Cs-134 Sq/sample 0.032 (1) A Cs-137 Sq/sample 0.891 1.08 0.758 -1.408 A Co-57 Sq/sample 0.006 (1) A Co-60 Sq/sample 4.04 4.62 3.23-6.01 A Mn-54 Sq/sample 2.01 2.43 1.70-3.16 A Sr-90 Sq/sample 1.25 1.60 1.12-2.08 w Zn-65 Sq/sample 6.16 7.49 5.24-9.74 A (a) The MAPEP known value is equal to 10(}% of the parameter present in the standard as detennined by gravimetric and/or volumetric measurements made during standard preparation (b) DOEIMAPEP evaluation:

A = Acceptable - reported re:::ult falls within ratio limits of 0.8(}..1.20 W = Acceptable with warning- reported result falls within 0. 70-0.80 or 1.20-1.30 N =Not Acceptable - reported re:iult faffs outside the ratio limit:11 of< 0. 70 and > 1.30 (1) False positive te:,t (2) Sensitivity evaluation (3) To-99 soil cross-checka done for TBE information only- not required (4) See NCR 22-05 72

ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services Identification TBE Reported Knovm Acceptance MonthNear Matrix Nuclide Units Evaluation (bl Number Value Value<3 l Limits March2022 MRAD-36 Water Am-241 pCi/L 68.3 74.6 51.2- 95.4 A Fe-55 pCi/L 797 1140 670-1660 A Pu-238 pCi/L 146 147 88.4-190 A Pu-239 pCi/L 69.9 71.9 44.5-88.6 A Soil Sr-90 pCi/k9 8050 6720 2090-10500 A AP Fe-55 pCi/filter 148 127 46.4-203 A Pu-238 pCilfilter 29.9 29.6 22.3-36.4 A Pu-239 pCi/filter 51.6 49.7 37.2-60.0 A U-234 pCilfilter 59.9 67.3 49.9-78.9 A U-238 pCi/filter 59.0 66.7 50.4-79.6 A GR-A pCi/filter 95.6 94.2 49.2-155 A GR-B pCi/filter 71.2 66.8 40.5-101 A April2022 RAD-129 Water Ba-133 pCi/L 61.7 62.9 52.3-69.2 A Cs-134 pCi/L 80.9 81.6 68.8-89.8 A Cs-137 pCi/L 37.4 36.6 32.1-43.3 A Co-60 pCi/L 103 97.4 87.7-109 A Zn-65 pCi/L 318 302 272-353 A GR-A pCi/L 26.9 20.8 10.4-28.3 A GR-8 pCi/L 49.7 51.0 34.7-58.1 A U-Nat pCi/L 56.3 6B.9 56.3-75.8 A H-3 pCi/L 17,000 18.100 15.800 - 19,000 A Sr-89 pCi/L 65.3 67.9 55.3-76.1 A Sr-90 pCi/L 42.1 42.7 31.5-49.0 A 1-131 pCi/L 25.7 26.2 21.8-30.9 A September 2022 MRAD-37 Water Am-241 pCi/L 111 96.2 66.0 - 123 A Fe-55 pCi/L 850 926 544-1350 A Pu-238 pCi/L 62.1 52.6 31.6-68.2 A Pu-239 pCi/L 139.5 117 72.5-144 A Soil Sr-90 pCi/kg 3350 6270 1950-9770 A U-234 pCi/kg 1684 3350 1570-4390 A U-238 pCi/kg 1658 3320 1820-4460 N~'

AP Fe-55 pCi/filter 71.9 122 44.5-195 A Nll)

Pu-238 pCi/filter 38.8 29.9 22.6-36.7 Pu-239 pCi/filter 14.5 13.0 9.73-15.7 A U-234 pCiffilter 78.0 71.5 53.0-83.8 A U-238 pCi/filter 79.7 70.9 53.5-84.6 A GR-A pCi/filter 62.8 55.5 29.0-91.4 A GR-8 pCi/filter 70.9 64.8 39.3-97.9 A October 2022 RAD-'131 Water Ba-133 pCi/L 76.2 79.4 66.6-87.3 A Cs-134 pCi/L 28.0 30.5 23.9-33.6 A Cs-137 pCi/L 202 212 191 -235 A Co-60 pCi/L 52.4 51.4 46.3-59.1 A Zn-65 pCi/L 216 216 194-253 A GR-A pCi/L 19.7 16.9 8.28-23.7 A GR-8 pCi/L 49.8 53.0 36.1 -60.0 A U-Nat pCi/L 10.54 8.53 6.60-9.88 NI')

H-3 pCi/L 13,900 15.100 13,200 - 16,600 A Sr-89 pCi/L 59.7 64.5 52.3-72.5 A Sr-90 pCi/L 32.9 37.3 27.4-43.0 A 1-131 pCi/L 26.9 24.4 20.2-28.9 A (a) The ERA lmoym value is equal to 10W/4 of the parameter pre:;ent in the :;tandard a:; determined by gravimetric and/or volumetric mea:;urement:; made during :;fandard preparation.

(b) ERA evaluation:

A = Acceptable - Reported value fall:; within the Acceptance Umit:;

N = Not Acceptable - Reported value falls outside oflhe Acceptance Limit:;

(1) See NCR 22-19 (2) U :roil cro:;:;-clledr:; done for 1BE infomation ooly- not required (3) See NCR 22-20 (Page 1 of 1) 73

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