ML24110A146
| ML24110A146 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/18/2024 |
| From: | Hilbert L Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 24-034 | |
| Download: ML24110A146 (1) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 18, 2024 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.24-034 NAPS:
CNC Docket Nos.
50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION UNIT NOS.1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2, enclosed is the 2023 Annual Radiological Environmental Operating Report.
The Radiological Environmental Operating Report provides the details associated with the Radiological Environmental Monitoring Program.
If you have any questions or require additional information, please contact Mr. Marcus A Hofmann at (540) 894-2100.
Vzl~
Lisa Hilbert Site Vice President Enclosure Commitments made in this letter: None
cc:
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station Serial No.24-034 NAPS Annual Radiological Environmental Operating Report Page 2 of 2
Dominion Energy North Anna Power Station Radiological Environmental Monitoring Program January 1, 2023 to December 31, 2023 Prepared by Dominion Energy, North Anna Power Station
Prepared by:
Reviewed by:
Approved by:
Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2023 to December 31, 2023 Bryantanrique Supervisor Radiological Analysis and Instrumentation Dominion Energy North Anna Power Station WilsnYarbrough Superintendent Health Physics Technical Services 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............................................................................................. 7
- 3. ANALYTICAL RESULTS............................................................................................................ 21 3.1 Summary ofResults.............................................................................................................. 21 3.2 Analytical Results of 2023 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 Strontiu1n...................................................................................................... 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 CENSUS........................................................................................... 66 APPENDIXB:
SUMMARY
OF INTERLABORATORY COMPARISONS............................... 68 3
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2023 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 Janumy 1 through December 31, 2023, 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 m*e 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-mi 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 rep01iing 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 patiiculates, and precipitation. The 2023 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 2023 was 5483 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 5428 pCi/liter. No plant related isotopes were detected in qumierly 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-13 7, was identified in one indicator sample during the reporting period at a level of 222.4 pCi/kg. The detection of Cs-13 7 in bottom sediment is historically common with positive indication usually apparent in both indicator and control samples. During the pre-operational period sediment samples were also analyzed by gamma spectroscopy. Levels during this phase varied by location and date and averaged 360 pCi/kg. 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 not scheduled to be collected in 2023. 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 terrestrial exposure pathway includes milk and food/vegetation products. No milk samples were obtained during the reporting period since the last operating dairy fmm within the sampling area closed on O 1/01/2018 rendering milk samples unavailable. No plant related isotope was detected in any vegetation sample.
The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years.
During 2023, 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 boundmy due to liquid and gaseous effluents released from the station during 2023 was 0.566 millirem. For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural background sources in the environment provide approximately 50% of radiation exposure to man, while medical uses provide approximately 48%. By comparison, nuclear power contributes less than 0.1 %. These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent control at North Anna Power Station.
5
- 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2023 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).
No1ih Anna Power Station is responsible for collecting the various indicator and control environmental samples.
Mirion Technologies is utilized for processing the TLDs.
Teledyne Brown Engineering Environmental Services (TBE) is utilized for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control levels, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes. Data collected prior to station operation is used to indicate the degree of natural variation to be expected. The pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.
Occasionally samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 1 0CFR50, 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 2023 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 2023 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 2023.
7
TABLE 2-1 North Anna Power Station - 2023 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. I Collection Sam~le Media Location Station Distance Direction Degrees Freguency 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° Qumterly & Annually Wares Crossroads 04 5.10 WNW 287° Quarterly & Annually Route 752 05 4.20 NNE 20° Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N
11° Qumterly & Annually Levy, VA 06 4.70 ESE 115° Qumterly & Annually Bumpass, VA 07 7.30 SSE 167° Qumterly & 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° Qumterly & 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
11° Qumterly 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° Qumterly 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° Qumterly DVP Biology Lab SE-13/45 0.64 SE 138° Qumterly Route 701 (Dam Entrance)
SE-14/46 5.88 SE 137° Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 158° Qumterly Elk Creek SSE-16/48 2.33 SSE 165° Quarterly NAPS Access Rd.
S-17/49 0.36 s
173° Quarterly 8
TABLE 2-1 North Anna Power Station - 2023 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sam~le Media Location Station Distance Direction Degrees Freguenc:y 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° Qumierly 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° Qumierly Route 208 NNW-32/64 2.21 NNW 344° Qumierly Bumpass Post Office C-1/2 7.30 SSE 167° Quatierly Orange, VA C-3/4 22.00 NW 325° Qumierly Control Mineral, VA C-5/6 7.10 WSW 243° Quarterly Louisa, VA C-7/8 11.54 WSW 257° Qumierly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 42° Weekly and Radioiodine Biology Lab 0lA 0.64 SE 138° Weekly Fredericks Hall 02 5.30 SSW 203° Weekly Mineral, VA 03 7.10 WSW 243° Weekly Wares Crossroads 04 5.10 WNW 287° Weekly Route 752 05 4.20 NNE 20° Weekly Sturgeon's Creek Marina 05A 2.04 N
11 ° Weekly Levy, VA 06 4.70 ESE 115° Weekly Bumpass, VA 07 7.30 SSE 167° Weekly 9
TABLE 2-1 North Anna Power Station-2023 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Samele Media Location Station Distance Direction Degrees Freguencr Remarks Airborne Particulate End of Route 685 21 1.00 WNW 301 ° Weekly and Radioiodine Route 700 22 1.00 WSW 242° Weekly "Aspen Hills" 23 0.93 SSE 158° Weekly Orange, VA 24 22.00 NW 325° Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 148° Monthly (Second Cooling Lagoon)
Lake Anna (upstream) 09A 12.90 WNW 295° Monthly Control (Route 669 Bridge)
River Water North Anna River (downstream) 11 5.80 SE 128° Monthly Ground Water Biology Lab OJA 0.64 SE J38o Quarterly (Well Water)
Precipitation Biology Lab OJA 0.64 SE 138° Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon)
Lake Anna (upstream) 09A 12.90 WNW 295° Semi-Annually Control (Route 669 Bridge)
No1ih 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
Sam~le Media Soil Fish Food Products (Vegetation)
TABLE 2-1 North Anna Power Station-2023 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Location Station Distance Direction Degrees Freguency Bumpass, VA 07 7.30 SSE 167° Once/3 years End of Route 685 21 1.00 WNW 301 ° Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 242° Once/3 years "Aspen Hills" 23 0.93 SSE 158° Once/3 years Orange, VA 24 22.00 NW 325° Once/3 years Waste Heat Treatment Facility 08 3.37 SSE 148° Semi-Annually (Second Cooling Lagoon)
Lake Orange 25 16.5 NW 312° Semi-Annually 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 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 Remarks Control Control Control
SAMPLE MEDIA Thermoluminescent Dosimetry (TLD)
(84 TLDs)
(12 TLDs)
Airborne Radioiodine Airborne Particulate Surface Water River Water TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQUENCY ANALY~I~
LLD Quarterly Gamma Dose 2mR+/-2mR Annually Gamma Dose 2mR+/-2mR Weekly I-131 0.07 Weekly Gross Beta 0.01 Quarterly (a)
Gamma Isotopic Cs-134 0.05 Cs-137 0.06 2nd Quarter Sr-89 (b)
Composite Sr-90 (b)
Monthly I-131 l(c)
Gamma Isotopic 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 2nd Quarter Sr-89 (b)
Composite Sr-90 (b)
Monthly I-131 l(c)
Gamma Isotopic 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 REPORT UNITS mR/std. Month mR/std. Month pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L
- LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.
(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90
( c) LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.
12
SAMPLE MEDIA River Water Ground Water (Well Water)
Aquatic Sediment Precipitation Shoreline Soil TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQUENCY ANALYSIS LLD Quarterly(a)
Tritium (H-3) 2000 2nd Quarter Sr-89 (b)
Composite Sr-90 (b)
Quarterly Gamma Isotopic Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 l0(c)
Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly(a)
Tritium (H-3) 2000 2nd Quarter Sr-89 (b)
Sr-90 (b)
Semi-Annually Gamma Isotopic Cs-134 150 Cs-137 180 Annually Sr-89 (b)
Sr-90 (b)
Monthly Gross Beta 4
Semi-Annual Gamma Isotopic Composite Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 (d)
Cs-134 15 Cs-137 18 Ba-140 (d)
La-140 (d)
Semi-Annually Gamma Isotopic Cs-134 150 Cs-137 180 Annually Sr-89 (b)
Sr-90 (b)
REPQRT UNITS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/kg (dry) pCi/kg (dry)
- LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.
(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter
( d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.
13
SAMPLE MEDIA Soil Milk Fish Food Products (Broadleaf Vegetation)
TABLE2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM FREQUENCY ANALYSIS LLD Once per 3 years Gamma Isotopic Cs-134 150 Cs-137 180 Sr-89 (b)
Sr-90 (b)
Monthly, if I-131 available Monthly, if Gamma Isotopic available Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (b)
Sr-90 (b)
Semi-Annually Gamma Isotopic Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Monthly, if Gamma Isotopic available, or Cs-134 60 at harvest Cs-137 80 I-131 60 REPORT UNITS pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L pCi/kg (wet) pCi/kg (wet)
- LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.
(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90
( c) LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, since this is a semi-annual composite no LLD is applied for these nuclides due to their short half-lives.
14
Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Environmental Station Designation Identification 1
(a) 01,NE-5/37 lA 0lA,SE-13/45 2
(a) 02,SSW-20/52 3
(a) 03,C-5/6 4
(a) 04 5
(a) 05 5A (a) 05A,N-2/34 6
(a) 06,ESE-12/44 7
(a) 07, C-1/2 8
08-Water, Fish, Sediment, Shoreline Soil 9A 09A-Water sample, Sediment 11 11-River Water, Sediment 14B 14B-Vegetation 15 15-Vegetation 16 16-Vegetation 21 (a) 21,WNW-27/59 22 (a) 22,WSW-24/56 23 (a) 23-SSE-15/4 7,Vegetation 24 (a)(b) 24,C-3/4 25 (c) 25-Fish 26 26-Vegetation (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.
(b) In Orange (c) In Lake Orange 15 Map Environmental Station Designation Identification 7/8 C-7/8 1/33 N-1/33 31/63 NNW-31/63 29/61 NW-29/61 3/35 NNE-3/35 7/39 ENE-7/39 9/41 E-9/41 11/43 ESE-11/43 17/49 S-17/49 19/51 SSW-19/51 21/53 SW-21/53 23/55 WSW-23/55 16/48 SSE-16/48 14/46 SE-14/46 22/54 SW-22/54 26/58 W-26/58 28/60 WNW-28/60 32/64 NNW-32/64 8/40 ENE-8/40 4/36 NNE-4/36 10/42 E-10/42
Legend Fixed Environmental Monitoring Slati.on 11.D Loca1ions Scare - 3/8 inch = 235 ft.
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CB32!12G;
- 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 trne 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 Summaiy Table because of the basic limitation of data summanes.
21
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Page 1 of 6 RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM
SUMMARY
NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2023 Docket No. 50-338/339 2023 Medium or Pathway Analysis Total Sampled Type Number (Units)
Direct Radiation (mR.std. Month)
(Sector TLDs)
Gamma 256 Dose "C3/4, -7/8 used for control locations Direct Radiation Gamma 32 (mR.std. Month)
Dose (Pre-0perational TWs)
"C3/4, -7/8 used for control locations Direct Radiation Gamma 40 (mR.std. Month)
Dose (Emergency Sector TWs)
"C3/4, -718 used for control locations Direct Radiation Gamma 48 (mR.std. Month)
Dose (Environmental TWs)
Direct Radiation Gamma 12 (mR.std. Month)
Dose (Annual TlDs)
Air Particulate GR-B 676 (10e-3 pCi/m 3)
GAMMA 52 BE-7 52 Cs-134 52 Cs-137 52 Sr-89 13 Sr-90 13 Air Iodine 1-131 676 (10e-3 pCilm 3 )
Soil GAMMA 0
(pCi/kg dry wt.)
K-40 0
CS-134 0
CS-137 0
Ra-226 0
- UD idontifed in ODCM
.. C-3/4,-7/8 used as control locations LLD' 2
2 2
2 2
0.01 NA 0.05 0.06 0.01 0.01 0.07 150 180 Indicator Indicator Locations Location with Hiahest Mean Mean Numberl (Range) 4.2 (256/256) 29161 (1.4-9.4) 2.7 (16116)
C-1I2 (1.4-4.0) 5.2 (40140)
EPSP (2.7-10.0) 09110 3.4 (44144)
STA-23 (1.7-6.0) 3.0 (11111)
STA-23 (2.0-4.8) 17.9 (6241624) 01 (5.19-42.9) 130.4 (48/48) 04 (87.6-191.9)
(0148)
NIA (0148)
NIA (0148)
NIA (0148)
NIA (01624)
NIA NIA NIA NIA NIA NIA NIA NIA NIA 22 Distance I Direction 0.52M1.
NW 7.30 Mi.
SSE 0.37Mi.
ENE 0.93Mi.
SSE 0.93Mi.
SSE 0.20 Mi.
NE 5.10 Mi.
WNW NIA NIA NIA NIA NIA NIA NIA NIA NIA Mean (Range) 7.2 (818)
(6.1-9.4) 3.3 (8/8)
(2.4-4.0) 8.0 (8/8)
(6.4-10.0) 5.2 (414)
(4.7-6.0) 4.8 (111)
(4.8) 19.5 (52152)
(5.93-38.8) 149.6 (414)
(114.7-191.9)
NIA NIA NIA NIA NIA NIA NIA NIA NIA Control Locations Mean (Range) 3.4(16116)
(2.0-4.7) 3.4 (16116)
(2.0-4.7) 3.4 (16116)
(2.0-4.7) 2.9 (414)
(1.8-4.3) 2.6 (111)
(2.6) 16.9 (52/52)
(6.43-33.2) 119.0 (414)
(94.5-145.2)
(014)
(014)
(014)
(014)
(0152)
NIA NIA NIA NIA Non-Routine Reported Measurement 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Page 2 of 6 Medium or Pathway Sampled (Units)
Sorl (cont'd)
(pCi/kg dry wt.)
RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM
SUMMARY
NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2023 Docket No. 50-338/339 2023 Indicator Indicator Analysis Total LLD*
Locations Location with Hiahest Mean Type Number Mean Numberl Distance I Mean (Range)
Direction (Range)
Th-228 0
... Soil samples ere obtained triennially.
Precipitation GR-8 12 4
4.1 (10112) 01A 0.64Mi.
4.1 (10112)
(pCilliter)
(1.7-16.1)
SE (1.7-15.1)
H-3 12 2000 (0/12)
Be-7 2
(0/2)
15 (0/2)
NIA NIA N/A Fe-59 2
30 (0/2)
NIA NIA N/A Co-58 2
15 (0/2)
15 (0/2)
30 (0/2)
30 (0/2)
NIA NIA N/A Nb-95 2
15 (0/2)
15 (0/2)
18 (012)
60 (0/2)
15 (0/2)
10 (0/2)
NIA 0
NIA 0
NIA 0
NIA 0
NA 0
NIA 0
NIA 0
N/A 0
NIA 0
NIA 0
N/A 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Page 3 of 6 Medium or Pathway Sampled (Units)
Precipitation (cont'd)
(pCit7iter)
Fruits & Vegetables (pCilkg wet wt)
Well Water (pCilliter)
SUMMARY
NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2023 Docket No. 50-338/339 2023 Indicator Indicator Analysis Total LLD*
Locations Location with Hiahest Mean Type Number Mean Numberl Distance I Mean (Range)
Direction (Range)
Th-228 2
(012)
NIA NIA NIA GAMMA 35 Ba-7 35 1168 (22/28) 23 0.93 Mi.
1458 (517)
(454.6-2567)
SSE (626.5-2567)
K-40 35 4461 (28/28) 148 122 Mi.
5079 (J/7)
(2308-0709)
N (2599-0632) 1-131 35 60 (0/28)
NIA NIA NIA Cs-134 35 60 (0/28)
NIA NIA NIA Cs-137 35 80 (0/28)
NIA NIA NIA Th-228 35 75.94 (3/28) 23 0.93Mi.
112.0 (1/7)
(52.39-112.0)
SSE (112.0)
Th-232 35 110.4 (1/28) 26 1.15Mi.
110.4 (1/7)
(110.4) s (110.4)
H-3 4
2000 (014)
Mn-54 4
15 (014)
30 (014)
15 (014)
15 (014)
30 (014)
30 (014)
15 (014)
10 (014)
15 (014)
18 (014)
NIA NIA NIA 24 Control Non-Routine Locations Reported Mean Measurement (Range)
NIA 0
1332 (5/7) 0 (1010-1734) 4972 (J/7) 0 (3473-7137)
(0/7) 0 (0/7) 0 (0/7) 0 44.18 (217) 0 (36.26-52.10)
<LLD 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Page 4 of 6 Medium or Pathway Sampled (Units)
Well Water (cont'd)
(pCilliter)
River Water (pCillfter)
SUMMARY
NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2023 Docket No. 50-338/339 2023 Indicator Indicator Analysis Total LLD' Locations Location with Highest Mean Type Number Mean Numberl Distance I Mean (Range)
Direction (Range)
Ba-140 4
60 (014)
15 (014)
2000 5428(414) 11 5.80Mi.
5428 (414)
(4660-6590)
SE (4660-6590)
GAMMA 12 Mn--54 12 15 (0112)
NIA NIA NIA Fe-59 12 30 (0/12)
NIA NIA NIA Co-58 12 15 (0/12)
NIA NIA NIA Co-60 12 15 (0112)
NIA NIA NIA Zn-65 12 30 (0112)
NIA NIA NIA Zr-95 12 30 (0112)
NIA NIA NIA Nb-95 12 15 (0112)
NIA NIA NIA Cs-134 12 15 (0112)
NIA NIA NIA Cs-137 12 18 (0112)
NIA NIA NIA Ba-140 12 60 (0112)
NIA NIA NIA La-140 12 15 (0112)
N/A NIA NIA 25 Control Non-Routine Locations Reported Mean Measurement (Range)
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
NIA 0
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Page 5 of 6 Medium or Pathway Sampled (Units)
Surface Water (pCi/liter)
Sediment Silt (pCi/kg dry wt.)
SUMMARY
NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2023 Docket No. 50-338/339 2023 Analysis Total Type Numbe H-3 8
GAMMA 24 Mn-54 24 Fe-59 24 Co-58 24 Co-60 24 Zn-65 24 Zr-95 24 Nb-95 24 1-131 24 Cs-134 24 Cs-137 24 Ba-140 24 La-140 24 Sr-89 2
Sr-90 2
GAMMA 6
K-40 6
Cs-134 6
Cs-137 6
Ra-226 6
Indicator LLD*
Locations Mean (Range) 2000 5483 (4/4)
(4150-6350) 15 (0112) 30 (0112) 15 (0112) 15 (0112) 30 (0112) 30 (0112) 30 (0112)
(0112) 15 (0112) 18 (0112) 60 (0112) 15 (0112)
(0/1)
(0/1) 10795 (4/4)
(944.7-20660) 150 (0/4) 180 222.4 (1/4)
(222.4) 3059 (1/4)
(3059)
Indicator Location 'Mth Hiqhest Mean Number!
Distance Direction 08 3.37M1.
SSE NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA N/A NIA NIA 11 5.80Mi.
SE 11 5.80Mi.
SE 26 I
Mean (Range) 5483 (4/4)
(4150-6350)
NIA NIA N/A N/A NIA NIA NIA NIA NIA NIA N/A N/A N/A NIA 20110 (2/2)
(19560-20660)
N/A 222.4 (1/2)
(222.4) 3059 (112)
(3059)
Control Non-Routine Locations Reported Mean Measurement (Range)
(014) 0 (0/12) 0 (0/12) 0 (0/12) 0 (0112) 0 (0112) 0 (0112) 0 (0/12) 0 (0112) 0 (0112) 0 (0112) 0 (0112) 0 (0112) 0 (011) 0 (011) 0 14535 (2/2) 0 (13760-15310)
(0/2) 0 (0/2) 0 (012) 0
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Page 6 of 6 Medium or Pathway Sampled (Units)
Sediment Silt (cont'd)
(pCi/kg dry wt.)
Shoreline Soil (pCi/kg dry wt.)
Fish - Other (pCilkg wet wt.)
- UD idantlfed In ODCM RADIOLOCIAL ENVIRONMENT MONITORING PROGRAM
SUMMARY
NORTH ANNA NUCLEAR POWER STATION, LOUISA COUNTY, VIRGINIA 2023 Docket No. 50-338/339 2023 Indicator Indicator Analysis Total LLD' Locations Location with Hiohest Mean Type NumbeI Mean Number!
Distance I Mean (Range)
Direction (Range)
Control Locations Mean (Range)
Th-228 6
1268 (314)
(257.2-2051) 11 5.80 M1.
1774 (2/2) 158.5 (2/2)
SE (1497-2051)
(100.2-216.7)
Th-232 6
1535 (2/4) 11 5.80 Mi.
1535 (2/2)
(012)
(1417-1653)
SE (1417-1653)
Sr-89 3
(0/2)
(Annually)
Sr-90 3
(0/2)
(Annually)
GAMMA 2
K-40 2
1282 (212) 08 3.37 Mi.
1282 (2/2)
NIA (1093-1471)
SSE (1093-1471)
Cs-134 2
150 (0/2)
180 (0/2)
(0/2)
136.9 (1/2) 08 3.37Mi.
136.9 (1/2)
NIA (136.9)
SSE (136.9)
Th-232 2
(0/2)
Sr-90 (011)
GAMMA 8
K-40 8
1941 (414) 08 3.37Mi.
1941 (414) 2180 (414)
(1758-2268)
SSE (1758-2268)
(1974-2418)
Mn-54 8
130 (014)
Fe-59 8
260 (014)
Co-58 8
130 (014)
Co-60 8
130 (014)
Zn-65 8
260 (0/4)
Cs-134 8
130 (014)
NIA NIA N/A (014)
Cs-137 8
150 (014)
NIA NIA NIA (014) 27 Non-Routine Reported Measurement 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
3.2 Analytical Results of 2023 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 repo1ied in the following tables are strictly counting statistics. The repmied 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 Nmth AnnaODCM.
Data are given according to sample type as indicated below.
- 1.
Gamma Exposure Rate
- 2.
Air Particulates, Gross Beta Radioactivity
- 3.
Air Particulates, Weekly I-131
- 4.
Air Particulates, Quantitative Gamma Spectra
- 5.
Air Particulate Strontium
- 6.
Soil
- 7.
Precipitation
- 8.
Cow Milk
- 9.
Food Products and Vegetation
- 10.
Well Water
- 11.
River Water
- 12.
Surface Water
- 13.
Bottom Sediment/Silt
- 14.
Shoreline Soil
- 15.
Fish 1 Analytical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL," letter by Leo B.
Higginbotham) and NUREG/CR-4007 (Sept. 1984).
28
TABLE 3-2 QUARTERLY GAMMA EXPOSURE RATE (mR/std. Month)+/- 2 Sigma First Quarter Secoocl Quarter Third Quarter Fourth Quarter 1/11/2023-4/12/2023-7/5/2023-10/3/2023-Quarterly Average*
station 4/12/2023 7/5/2023 10/3/2023 1l2/2024
(+filS.D. __
N-1 4.7 4.7 3.4 6.7 4.8 (+/-) 24 N~33 5.3 3.6 3.7 6.0 N~2 3.3 2.5 2.7 4.3 3.1 (+{-) 1.6 N-34 3.0 2.5 2.0 4.0 NNE-3 7.3 5.1 4.7 7.3 6.0 (+/-) 25 NNE-35 6.0 5.1 5.1 7.7 NNE-4 4.3 4.3 3.4 5.7 4.5 (+/-) 1.8 NNE-36 5.0 4.0 3.4 5.7 NE~
4.3 4.3 3.7 5.3 4.3 (+/-) 1.6 NE-37 4.7 4.0 3.0 5.3 NE~
3.7 2.9 1.4 5.3 3.4 (+/-) 24 NE-38 3.7 3.3 2.7 4.3 ENE-7 5.7 4.7 4.1 7.7 5.6 (+/-) 28 ENE-39 7.3 4.7 4.4 6.3 ENE-8 3.0 2.5 1.7 3.0 2.4 (+/-) 1.2 ENE-40 23 1.8 1.7 3.0 E-9 5.3 4.3 3.7 7.3 5.0 (+/-) 26 E-41 5.3 4.3 3.4 6.0 E-10 4.3 3.3 3.0 5.7 4.0 (+/-) 21 E-42 4.3 3.3 2.7 5.0 ESE-11 5.0 3.6 3.4 5.3 4.4 (+{-) 1.5 ESE-43 5.0 4.0 4.1 5.0 ESE-12 4.7 3.6 3.4 5.0 4.1 (+/-) 1.7 ESE-44 4.7 2.5 4.4 4.7 SE-13 5.3 3.6 3.4 5.7 4.3 (+/-) 22 SE-45 4.0 3.6 3.0 5.7 SE-14 5.7 4.0 5.1 6.7 5.6 (+/-) 21 SE-46 5.7 5.1 5.4 7.3 SSE-15 5.3 3.6 3.4 6.3 4.5 (+/-) 23 SSE-47 5.0 3.3 4.1 5.3 SSE-16 3.3 2.2 2.0 4.7 3.0 (+/-) 1.9 SSE-48 3.7 2.9 2.0 3.3 S-17 5.0 3.6 3.4 7.3 4.9 (+/-) 28 S-49 5.3 4.0 4.4 6.3
- Average of collocated TLDs 29
TABLE3-2 QUARlERLY GAMMA. EXPOSURE RATE (mR/std. Month) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter 1/11/2023-4/12/2023-7/5/2023-10/3/2023-Quarterly Average*
Station 4/12/2023 7/512JJ23 10/3/2023 1/2/2024
(+/ES.D. --
s~s--
3.0
2.2 ---
____ u
_ __ 1]"" ___
2.3 (+/-) 1.0 8-50 23 1.8 2.0 2.7 SSW-19 7.0 5.4 6.1 7.7 6.5 (+/-) 1.8 SSW-51 7.0 5.4 5.7 7.3 SSW-20 2.7 1.8 1.7 3.3 2.3 (+/-) 1.2 SSW-52 23 2.2 1.7 2.7 SW-21 4.7 3.3 3.4 5.3 4.0 (+/-) 1.7 SW-63 4.0 3.3 3.0 4.7 SW-22 4.3 4.3 3.4 4.7 4.2 (+/-) 0.9 SW-54 4.3 3.6 4.1 4.7 WSW-23 5.0 3.6 4.7 5.7 4.8 {+/-) 1.7 WSW-55 5.7 4.0 4.1 5.7 WSW-24 3.7 4.0 3.0 4.7 4.0 {+/-) 1.3 WSW-56 4.7 3.6 3.4 4.7 W-25 7.7 6.2 5.7 7.0 6.7 (+/-) 21 W-ol 6.3 5.8 6.1 8.7 W-26 3.3 2.5 2.4 4.0 2.8 (+/-) 1.3 W-58 27 2.2 2.4 3.3 WN>N-27 3.3 2.9 2.0 4.0 3.0 (+/-) 1.3 WN>N-59 3.0 2.9 2.4 3.7 WN>N-28 3.7 2.5 2.7 3.7 32 (+/-) 1.4 WN>N-00 3.3 2.9 2.4 4.3 NW-29 7.0 6.5 6.1 9.4 72 {+/-) 26 NW-61 6.7 6.5 6.1 9.0 NW-30 20 1.4 1.7 3.3 2.0 {+/-) 1.3 NW-62 20 1.4 1.7 2.7 NNW-31 4.7 2.9 2.0 4.7 3.7 (+/-) 2.0 NNW-63 4.0 2.9 3.4 4.7 NNW-32 4.0 3.3 2.7 3.3 3.5 (+/-) 1.1 NNW-64 3.7 3.6 3.0 4.3 Mean 42 (+/-) 3.1
- Average of collocated TI.Os 30
First Quarter 1/11/2023-station 4/12/2023 c::i---
3.3 C-2 3.7 C-3"*
3.3 C-4..
3.3 C-5 23 C-6 27 C-7"*
4.3 C-8" 3.7 EPSA-01"'**
4.3 EPSA-02"**
5.0 EPSF-03"**
4.0 EPSF--04"**
5.0 EPSR-05*"*
6.0 EPSR-06***
5.7 EPSJ-07"**
4.7 EPSJ-08..
- 4.0 EPSP-09***
8.7 EPSP-10"'
8.4
- Average of collocated TI.Os
.. Control Location Emergency Plan TLDs.
Second Quarter 4/12/2023-7/5/2023 3.3 2.9 2.9 2.5 1.4 1.8 3.6 3.3 4.0 3.6 3.6 3.6 5.4 5.1 2.9 3.3 6.5 6.9 TABLE3-2 QUARTERLY GAMMA. EXPOSURE RATE (mR/Std. Month) +/- 2 Sigma Third Quarter Fourth Quarter 7/5/2023-10/3/2023-Quarterly Average*
10/3/2023 1/2/2024
___ (+/-} 2 S.D.
- --- 2.4 ---
--- 4.0 ---
3.3 (+/-) 1.2 2.7 4.0 2.0 3.7 3.0 (+/-) 1.2 2.4 3.7 1.7 2.3 2.1 (+/-) 0.9 2.0 2.7 4.1 4.7 3.9 (+/-) 1.0 3.4 4.3 lndicator Mean 2.7 (+/-) 1.6 Control Mean 3.4 (+-/-) 1.5 3.7 5.7 4.6 (+/-) 1.6 4.4 5.7 2.7 4.3 3.9 (+/-) 1.5 3.4 4.7 5.1 6.3 5.6 (+/-) 1.4 4.7 6.7 3.0 5.0 3.8 {+/-) 1.8 2.7 4.7 6.4 10.0 8.0 (+/-) 29 7.1 9.7 Mean 5.2 (+/-) 3,.6 31
First Quarter 1/11/2023-Station 4/1212023 sfl1/4l1-4.7 STA-02 3.0 STA-03 27 STA-04 3.7 STA-05 3.3 STA-05A 3.3 STA-06 4.3 STA-07 3.3 STA-21 3.0 STA-22 4.0 STA-23 5.3 STA-24**
3.3
- Average of collocated TLDs
.. Control Second Quarter 4/1212023-7/512023 4.3 22 1.8 2.2 2.9 2.5 4.0 2.9 2.5 2.5 4.7 1.8 TABLE3-2 QUARTERLY GAMMA EXPOSURE RATE (mR/Std. Month)+/- 2 Sigma Third Quarter Fourth Quarter 7/5/2023-10l3!2023-Quartefly Average*
Annual 10/3/2023 1/212024
___ (+/-) 2 S.D.
- --- 3.0 ---
5.0 4.3 (+{-) 1.7 3.6 2.4 2.7 2.6 (+{-) 0.7 2.1 1.7 2.7 22 (+/-) 1.1 2.0 2.0 2.7 2.6 (+{-) 1.5 2.4 3.0 3.7 32 (+{-) 0.7 2.0 2.4 3.7 3.0 (+/-) 1.3 2.5 3.0 4.3 3.9 (+/-) 1.2 42 3.0 5.0 3.6 (+{-) 20 2.8 2.7 3.7 3.0 (+{-) 1.0 2.9 3.4 5.0 3.7 (+{-) 21 3.8 4.7 6.0 5.2 (+{-) 1.2 4.8 2.0 4.3 2.9 (+/-) 2.4 2.6 Mean Indicator Locations 3.4 (+{-) 2 1 3.0 (+{-) 1.9 32
TABLE3-3 AIR PARTI0UI..AlES GROSS BETA IRAOI0ACTMlY (10"3 pCifm3)
LOCATIONS PERIOD ENDING 01 02 03 04 05 06 07 21
(+/-) -
(+/-)
(+/-)
(+/~)
{+/-)
(+/-)
,(+/-)
(+/-}
01/03123 18.70 2.960 1720 2940 15.80 2.870 16.40 2.900 17.20 2.940 20.70 3.100 17.70 2960 19.90 3.070 01/11/23 18.30 2.430 17.10 2320 18.10 2.350 20.50 2570 18.90, 2.500 14.90 2200 14.90 2.200 15.10 2.210 01/18123 18.10 2.870 9.560 2400 13.10 2.650 1320 2640 17.60 2.840 18.40 2880 16.20 2.770 14.50 2.670 01/24/23 12.50 2.890 9.360 2780 8.880 2.750 9.910 2780 10.10 2.830 9.320 2780 120(}
2.930 9.140 2.790 01/31/23 14.80 2.690 1520 2.790 1270 2.530 1420 2630 15.00 2.670 18.80 2980 13.10 2560 14.60 2.610 02/07/23 18.10 2.no 20.40 2990 17.00 2.700 16.10 2650 14.10 2.540 23.60 3.170 19.90 2.850 18.40 2.770 02/14/23 19.90 3.090 17:90 2.880 14.80 2.670 18.50 2.880 18.60 2.900 22.60 3.220 18.601 2.910 14.10 2.570 02/21/23 18.40 2:950 13.60 2690 13.30 2.670 18.:30 2'.930 15.40 2.790 18;50 2940
- 15.001 2.760 14.40 2.730 02/28/23 18.70 2.8901 17:30 2'.810 15.20 2.690 1
17.90 2;830 7.980' 2.270 17.30 2800 19.701 2.930 18.10 2.840 03/07123 18.00 2.720 18.80 2890
- 1220, 2.470 15.10 2620 15.40 2.610 20.00 2960
'18.50 2.770 14.80 2.560 03/14/23 5;9301 2220 H.40 2670 9230 2.550 8.460 2'.380 9.000 2.530 6.480 2250 8.470 2.370 8.760, 2.390 03/21/23 13.30 2.940 13.50 2.950 19.70
- 3_330, 19.50 3.280 20.70 3.390 16.60 3.140
'14.40 3.000 11.70 2.720 03/28/23 20.40 3.090 21.00 3.010 20.30' 2.970 1920 2920 18.40 2.880 10.80 2470 15.501 2.730 13.00 2.590 04/05/23 17.00 2.590 18.50 2770 18.20 2.750, 16.60 2570 19.00 2.790 18.00 2730 n.101 2.410 15.00 2.490 04/11123 23.10 3.660 21.70 3.600 23.00 3.660 2320 3.670 25.90 3.800 17.70 3.250 15.201 3.110 18.70 3.290 04/19123 16.30 2.500 20.50 2740 20.40 2.830 19,90 2700 19.60 2.710 15.70 2530 n.101 2.430 16.30 2.550 04/25123 24.50 3.820 19.60 3.460 24.70 3.820 23.60 3.730 20.60 3.530 23.70 3.680 18.001 3.240 19.10 3.300 05(02/23 14.20 2.850 11.50 2580 n.60 2.820 R950 2.430 8.950, 2.430 H.60 2590 9.9601 2.490 9.600 2.470 05/09!23 9.700 2.340 8.730 2'.280 1230 2.600 12.20 2.590 9.020 2.300 8,61)0 2270 9.5301 2.330 9.400 2.320 05/16/23 22.90 3.160 15.90 2.830 20l40 3.050 19;90 3.030 19.30 1
2.9901 H'.20 2560
'12301 2.630 15.70 2.810 05/23/23 17.50 2.820 13.70 2'.620 15.30 2.700 1420 2640
- m50, 2.4501 14.80 2630 14.001 2.630 16.80, 2.780 05/30/23 10.80 2.570 1020 2.540 10l901 2.690 13.00 2800 9.980 2.530 9.900 2520 9.4701 2.500 10.10 2.490 06/06/23 14.30 2.600 12.00 2450 15,.00 2.640 10.80 2400 13.80 2.560 15.10 2630 1210 2460 1200 2.500 06/13123 13.80 2.920 12.60 2780 8.780 2.570 13.40 2'.960 15.30 2.910 17.70 3.160 15.40 2.920 14.70 3.030 06/20/23 25.40 3.330 2020 2.970 23.60 3.250 22.20 3.170 15.40 2.740 21.20 3.030 15.50 2.730 17.20 2.940 06/27/23 12.70 2.680 6.140 2280 9.750 2.530 10.70 2580 8.690 2.440 9.780 2500 5.190 2.220 6.450 2.310 33
TABLE 3-3 AIR PARTICULATES GROSS BETA RADrOACTilVI~
( 10-1 pCifm3 }
LOCATIONS PERIOD ENDING 01 02 03 04 05 ll6 07 21
(+/-)
,(+/-)
(+/~)
,(+/-)
(+/-)
{+/-)
(+/-)
(+/~)
07/05123 16.00 2.670 17.60 2.730 13.80 2500 1520 2.580 13.90 2.:540 18.80 2;790 11.00 2.370 14.90 2.470 07/11/23 22.40 3.270 22.10 3.290 26.30 3.. 660 30.30 3.840 24.50 3.400 24.00 3.370 23.10 3._340 18.70 3.110 07/18n3 20.40 3.040 1320 2.680 25.50 3.. 320 21.00 3.100 15.30 2.800 19.90 3.030 15.50 2.810 19AO 2.990 07125/23 19.40 3.010 13.30 2.700 20.90 3.210 19.30 2.990 13_80 2.730 16.70 2.880 11.20 2.580 17.90 2.940 08101/23 26.80 3.250 22.70 3.060 25.70 3.220 28.40 3.340 26.30 3220 23.70 3.110 22.90 3.070 26.20 3220 08108123 19.00 3,060 15.60 2.750 17.20 2800 19.80 3.080 15.70 2.880 14.80 2.710 16.90 2.820 15.60 2.760 08116123 26.30 2.950 21.10 2.710 24.. 90 2920 28.00 3.040 25AO 2.900 18.00 2.560 23.50 2.820 22.90 2.800 08122/23 21.60 3.420 19.40 3.320 21.00 3.. 380 15.30 3.070 18.60 3.300 20.60 3.390 16.80 3.160 17.50 3220 08129/23 23.30 3.240 19.40 3.050 20.20 3.110 22.90 3.230 22.90 3210 1820 2.990 15.30 2.850 19'.30 3.050 09105/23 16.50 2.820 12,80 2.630 23.. 40 3.280 15.30 2.750
.21.10 3200 19.70 2.990 13, 10 2.650 17.70 2.890 09112123 29.00 3.360 26.00 3.210 33.. 90 3.. 560 32.00 3.500 32.00 3.460 25.90 3.200 24.80 3.160 27.20 3270 09120/23 20.90 2.840 17.30 2.690 23.. 70 3.090 27.10 3.240 21.40 2.890 20.10 2.820 17.70 2.710 19'.20 2.770 09126123 15.90 3.090 12.80 2.900 11.10 2.,830 15.60 3.090 12.70 2.890 14.10 2.970 9.060 2.680 11.50 2.830 10/03/23 13.00 2.790 7.920 2.520 10.50 2.590 11.10 2.650 10.90 2.660 6.980 2.450 10.30 2.630 10.60 2.650 10/10/23 22.40 3.300 18.50 3.140 20.90 3.310 22.40 3.350 22..00 3280 17.10 3.080 13.60 2.900 16.20 3.020 10/17123 25.70 3.280 19.40 3.000 37.20 6.380 25.10 3.240 23,60 3200 22.80 3.150 17.50 2.900 21.90 3.1.20 10/24/23 12.00 2.730 12.30 2;750 13.80 2.880 17.40 3.030 12.70 2.770 14.90 2.890 11.60 2.710 13.70 2.820 11/01/23 24.00 3,.100 1720 2.810 18.70 2.860 22.90 3.040 24.90 3.140 18.30 2.860 15.20 2.720 19.30 2.900 11/08/23 38.80 3.890 32.80 3.650 40.10 3.930 42.90 4.030 40.60 3.950 35.40 3.750 31.30 3.590 37.50 3.840 11115/23 17.60 2.950 13.60 2.750 18.00 3.000 16.90 2.940 18.. 60 3.000 15.10 2.820 14.30 2.78.0 13.8.0 2.760 11/21/23 25.40 3.590 19.:50 3.320 23.90 3.510 21.80 3.410 2.3.70 3.:530 20.70 3.390 20.. 30 3.360 20.00 3280 11/28/23 17.90 2.850 14.50 2.660 16.20 2.780 16.00 2.770 16.80 2.780 19.50 2.920 12.80 2.570 17.10 2.840 12105/23 32.70 3.510 23.10 3.100 35.90 3.. 620 36.30 3.710 31.70 3.480 26.80 3.360 23.80 3.130 32.60 3.460 12112/23 22.30 2.990 20.:50 2.890 25.. 30 3.150 24.80 3.120 23.20 3.010 2320 3.010 14.70
.2.590
.22.90 3.060 12119/23 26.30 3.260 1920 2.920 20.50 2.990 2.1.60 3.040 21.60 3.060 17.60 2.860 16.00 2.no 19.70 2.950 12126123 21.50 3.190 18.10 3.030 21.40 3.190 2220 3.230 14.90 2.880 19.10 3.080 15.70 2.920 20.70 3.150 Mean 19.51 2.996 16.61 2.852 19.16 3.042 19.41 2.994 18.1'5 2.924 17.83 2.912 15.50 2.785 16.96 2.846 34
TABLE S--3 AIR PARTICULATES GROSS BETA RADl:OACTIVIITY (10-3 pCi/m3)
LOCATIONS PERIIOD ENDING 22 2'3 24*
01A 0SA
(+.I-)
(+!-)
(+t-)
(+/-)
(+/-)
01/03123 17.50 2.950 18;50 3.130 18.30 2990 1620 3.030 21.80 3.150 01.111123 15.00 2.200 12'.60 2.060 15.40 2230 18.30 2.490 18.10 2.370 01/18123 16.30 2.78.0 17.30 2.840 16.90 2800 19.00 3.020 15.00 2.700 01124123 11.30 2.920 12.40 2.930 7.840 2700 12.00 3.020 12.90 3.000 01/31123 13.20 2.540 13.90 2.710 12.8.0 2540 1720 2.940 12.20 2.510 02/07123 15.80 2.630 15.90 2.640 19.10 2810 18.40 2.890 20.40 2.880 02114!23 17.1 2.830 16.70 2.790 12_10 2.55 20.00 3.100 11.00 2.490 02121123 13.40 2.690 15.5 2.800 12.0.0 2.60 15.50 2.930 16.90 2.860 2128123 16.30 2.750 19.60 2.920 19,_oo 2.880 17.30 2.8m 16.9!0 2.780 03/07!23 18.10 2.850 19.70 2.950 17.60 2850 15.10 2.680 17.70 2.850 03/14.123 6.360 2.250 9.. 130 2.420 9.620 2.550 7.540 2.440 9.590 2.580 03/21.123 15.40 3.070 17.60 3.170 15.80 3.070 15.80 3.090 14.70 2.880 03128/23 20.40 3.000 21.70 3.160 17.00 2.850 18.30 3.010 22.90 3240 04105.123 17.30 2.700 20.50 2.880 14.40 2.450 17.10 2.690 15.50 2.500 04111!23 24.90 3.750 23.40 3.690 14.. 50 3.060 13.60 3.030 18.40 3.410 04119.123 11.rno 2.580 21.7[]
2.920 19.. 80 2.830 18.70 2.670 24.20 3.030 04/25.123 23.20 3.680 22.5[]
3.640 19'.80 3.510 14.60 3.Cl60 26JJO 3.8rno 0510212.3 12.70 2.650 10.30 2.520 10.6'[1 2.53 9,.. 980 2.500 11.10 2.560 05109.123 11.50 2.560 15.00 2.760 11.10 2.420 9,_120 2.310 9.530 2.330 05116!23 17.20 2.890 18.30 2.940 15.. 80 2.81 18.40 3.080 19.. 60 3.000 05123/23 15.80 2.770 16.10 2.740 12.60 2.570 14.70 2.670 19.30 2.920 05130!23 12.10 2.640 11.00 2.580 11.80 2.63 8.430 2.430 9.540 2.500 06106.123 15.60 2.670 17.40 2.760 11.20 2.410 10.50 2.380 15.50 2.650 06113123 13.20 2.950 12.10 2.890 15.60 2.900 15.00 3.050 15..50 2.920 06120.12.3 17.10 2.800 20.80 3.110 22.30 3.090 2120 3.010 20.. 90 3.020 06/21!23 8.580 2.440 10.60 2.560 6.430 2.300 9c300 2.480 11.20 2.590
- co11lrol S.talion 35
TABLE 3-3 AIR PARTICULATES GROSS BETA RADl:OACTIVIITY (1 0-1 pCiifm3 )
LOCATIONS PERIIOD ENDING 22 23 24" 01A 05A
(+/-)
,(+/-)
(+/:--}
,(+/--)
(+J--)
07(05123 16-30 2_670 9.. 680 6_360 9-180 2270 14.:30 2-460 21-10 2_890 07/11123 22_60 3_310 24_40 3-400 21-70 3.380 16-70 2_960 24_30 3_380 07118123 18-40 2_950 2220 3_130 21-10 3.100 15_40 2_800 21..70 3_120 07125f23 19-50 3_010 19_80 3_030 17_60 2920 13_00 2_680 17Ji0 2_940 08/rl1123 27_10 3-270 26.90 3_260 27.. 30 3-270 19.60 2_910 21.70 3.010 08.1[]8123 15_50 2-740 18.90 2_910 14.80 2.690 12_00 2.550 19.40 2.940 08/16123 22_60 2.780 26.40 2_950 24.00 2850 18.70 2_600 22.30 2.760 OSf.22123 18.80 3280 16.00 3_120 18.. 90 3.310 15.90 3_130 22.40 3_480 08/29123 19-80 3JJ60 1920 3.050 2CL10 3.080 15.30 2.860 15.fl.O 2.880 09!05123 14~70 2.730 21.:50 3.070 16.70 2.830 1120 2_530 17.61{)
2_900 09/12123 28-10 3_310 33.00 3_520 27~90 3.290 24.90 3_180 29.*10 3.:340 09120/23 19-20 2-770 20.90 2_840 17~90 2.720 15.90 2-610 28.00 3_170 09126123 16_00 3_{)9{)
13.:30 2_940 13.10 2.910 11.80 2_860 15.10 3.030 10:ID3t23 11-70 2.710 1 1.7 2_700 10.10 2.590 8.710 2.560 11.10 2.680 10/10123 18.50 3.140 19-60 3_200 15.. 70 3.020 14.70 2_9,30 24.70 3.430 10/17123 26_70 3._320 26_80 3_3.20 20-20 3-030 19.10 3_040 17_60 2.910 10/24123 13_30 2_790 1 4.7 2_870 12.90 2.790 8_140 2_520 13.. 6-0 2_820 11fil1.123 19-40 2_91 0 24_10 3_1 00 18_90 2.880 14_60 2_690 23_6!0 3_080 11!08123 39-40 3.910 39.10 3_900 33-20 3.670 27.:30 3-440 40_10 3.930 11/1 5123 15_60 2Jl50 21.5 3_150 15.40 2840 1 2.:3 2_680 18-40 2_990 11121(23 18_60 3-260 24_90 3_570 21_50 3.420 2020 3_340 24.6!0 3.:570 11128123 14_80 2.6-90 17.:50 2.830 15.10 2700 11.90 2.530 20.510 2.970 12!05123 32_1 0 3.480 35.50 3.620 27.70 3-310 22_30 3_050 34.. 00 3.:580 12/12123 26_1 0 3.170 172Q 2.730 20.60 2880 20.:30 2_890 26.. 30 3_150 12119123 22_80 3_100 21_80 3-320 20.90 3.030
- 17. 1 2_820 22..610 3_100 12126123 19-20 3_080 23.:5 3_280 19*.50 3.. 100 18.40 3_050 15.40 2.900 Meaim 18-06 2_924 19.:35 3.071 16.96 2.862 15.60 2_817 19*.14 2.971 Mean all limdicator l'ocatlom;,
17.94 2.927
- ooimlro1 Station 36
TABLE3-4 AIRBORNE IODINE
( 1a'3 pCi/m3) lOCATIONS PERIOD ENDI.NG 01 02 03 04 05 06, 07 21 01/03/23
< 16.57
< 7-751
< 17.03
< 17.03
< 17.00
< 18Bil
< 18.51
<W.54 01111/23
< 33.21
< 32.25
< 13.22
< 33.8,
< 34!.13
< 30.311
< 30.31
< 11273 01/18/23
< 35.70
< 35-70
< 15.35
< 36.34
< 35.64
< 3t.4!3
< 31.54
< 31.49 01/24/23
< 24!.00
< 24.73
< 24.78
<24.43
< 12.68
< 16.93
< 16.86
< 114!.33 01/31/23
< 28.75
< 12.51
< 28.09
< 28.34!
< 28.14
< 13.49
< 1273
< 110.52 02107/23
< 20.94
< 10.73
< 20.87
< 20.87
< 20.87
< 9.580
< 17.55
< 117.55 02/14/23
< 16.59
< 37.41
< 36.51
< 36.83
< 37.15
< 37.36
< 35.33
< 113.99 02/21/23
< 18.62
< 44.1)9
<44.02
< 44!.09
<44.17
< 25.38
< 25.25
<25.38, 02/28/23
< 15.12
< 31.00
< 30.93
< 30.99
< 30i.:93
< 21.06
< 10;801
< 21.06, 03/07/23
< 23.05
< 10.34
< 24.02
<.23.72
< 23.46
< 28.37
< 26.67
< 26,53 03114/23
< 20.10
< 10.92
< 21.38
<20.10
< 21.34
<34.29
< 14.33
< 34.17 03/21/23
< 24.04
< 24.00
< 24.74
<24.17
< 11.78
< 23.99
< 35.40
< 33.29 03/28/23
< 10.81
< 24.37
< 24.37
< 24.37
< 24!.42
< 17.65
< 17.65,
< 117.61 04105/23
< 37.50
< 39.71
< 16.68
< 37.39
< 39.7il
< 34.67
< 3276
< 3296, 04/11/23
< 20.74
< 20.83
< 20.78
< 20.78
< 9.859
< 19.57
< 19.53
<19.49 04/19/23
< 31.86
< 32.69
< 14!.411
< 32.44
< 3284
< 34.13
< 34.29
< 34.03 04/25/23
< 13.58
< 30.99
< 32..24
< 31.88
< 31.26
< 35.111
< 3296,
< 32:.96, 05102/23
< 33.78
< 3 11.83
< 14.17
< 31.83
< 31.83
< 25.93
< 25.93
< 25.93 05109/23
< 27.31
< 27.22
< 28.83
< 1211
< 27.22
< 19.69
< 19.65,
< 119.69 05116/23
< 44.16
< 44.31
< 44.3il
<H.67
< 41.90
< 411.90
< 4212
< 42'.12 05/23/23
< 21.98
< 22.02
< 22.02
<21.98
< 14.89
< 23.86
< 24.45
< 24.40 05130/23
< 35.08
< 35.08
< 15.62
< 37.03
< 35.14
< 17.19
< 40.98
< 40.14 06/06/23
< 36.75
< 36.44
< 36.88
< 51.21
< 50~59
< 50~59
< 50.59
< 21.74 06/13123
< 33.68
< 32.50
< 32.44
< 114.49
< 32.44
< 31.07
< 29.32
< 31.24 06/20/23
< 25.05
< 23.69
< 25.05
<40.56,
< 38.83
< 38.76
< 38.56
< H.17 06/27/23
< 29.45
< 29.34
< 29.65
< 13.65,
< 29.62
< 29.62
< 29.68
<29,73 37
TABLE 3-4 AIIRBORNE IODINE (1&1' pCi/tnJ) lOCAllONS PBRIOD ENDIMG 01 02 03 04 05, 06 07 21 07/05/23
< 33.23
< 32_85
< 32.22
< 2tt59
< 29.05
< 1220
< 28-86
< 27_03 07/11/23
< 40.53
< 41-11
- <:: 18.51
<43_84
< 40.94
<37_04
< 37-27
< 17-71 07/18/23
< 22.86
< 22_86
-::9_844
< 23_23
< 22..'98
< 8-951
< 21_31
<21-23 07/25/23
< 42.68
< 42-83
<t9.n1
<4238
-:: 42.83
< 19-60
< 46_65
<46,_65 08/01/23
< 26-.89
< 26_84
< 27_12
< 1278
< 30,_16
< 3D_16
< 30,_16
< 30-21 08/08123
< 12.30
< 27_42
< 26,.99
< 28-94
< 29.27
<H_m
< 26,-30
<26,26, 08/16/23
< 26.55
< 26_51
< 12-79
<26,80
< 26,.39
< 22!98
< 23J)8,
< 1.0,52 08122123
< 21.53
<21-62
< 21.40
< 21_36,
< 14-55
< 8-922
< 18-33
< 1.8-29 08129/23
< 19.32
< 19-25
< 21.51
< 19_42
< 19.25
< 23;94
< 23.94
< 23.9B 09/05/23
< 20.90
< 2R98
< 2218
< 2{126
< 11-18
< 20.47
< 20.47
<.20.47 09/12123
< 26.18
< 25_90
< 26.08
< 20.04
< 25*.81
< 29-59
< 29.75,
<29.75 09/20/23
< 31.32
< 31-51
< 33.37
< 14,02.
< 31 _71
< 17.77
< 23.26
<23.23 09/26/23
< 30.16
< 29-98
< 23_12
< 30,35
< 29:92
< 40.35
< 40c44
<40.52 10/03/23
< 17.75
< 17_81
< 17.15
<H.38
< 17.59
< 13.44
< 17.62
<H.65 10/10/23
< 22..06
< 22-25
< 17.38
< 2258
< 22.06
< 3320
< 33.14
< 33.03 10/17/23
< 30.19
< 3o_35
< 67.53
< 1258
< 30,.25
< 28.25
< 28c35,
< Ul.99 10/24/23
< 24.49
< 24.49
< 10.59
<24.80
< 24;58
< 8-671
< 18.99
< 18..99 11/01/23
< 26--11
< 26J1
< 25,.92
< 3201
< 16.47
< 32.25
< 32'.25
<3225 11/08/23
< 19.74
< 14_98
< 1'9.67
< 1'9.67
< 19.67
< 33.45
< 33.45
< 33.45 11/15/23
< 61.43
< 61.43
< 25,_04
< 6208
< 61.32
< 48.34
< 48.51
<48-51 11/21/23
< 26.53
< 26_69
-:: 26.42
< 26.42
< 13.66
< 30.66
< 301.54
<2265 11/28/23
< 24_12
< 23_95
< 26,.90
< 24.29
< 23a95
< 23.16
< 23.24
< 10.06, 12/05/23
< 22.. 23
< 22_31
< 22..08
<2208
< 24.79
< 12.04
< 28_36,
<27_72 12/12123
< 22.31
< 22.24
< 24.89
<.22A7
< 22.08
< 2L98
< 22.13
< 15.18 12/19/23
< 33.48
< 33.37
< 33.37
< 33.37
< 25,_64
< 15a35
< 33.49
< 33.49 12126/23
< 32 __ 11
< 32.'17
< 32.17
< 32'.22
< 24.63
< 14.. 97
< 35.69
< 35.56 38
TABLE 3-4 AIRBORNE IODINE (10'3 pCilm3)
LOCATIONS.
PBRIOD
.§'J.!?fil.§_
22 23 24*
01A 05A 01/03/23
< 18.54
< 13J4
< 23.54
< 25.22
< 23"54 01/11/23
< 30.31
< 30.22
< 24.02
< 25.82
< 24.05 01118/23
< 31.60
< 13.30
< 22.61
< 23.87
< 22.57 01/24/23
< 17.04
< 16.73
< 21.42
<22.01
< 21 ;38 01/31/23
< 12.58
< 13.52
< 19.17
< 20,75,
< 19.17 02/07/23
< 17.55
< 17.58
< 29.69
< 31.61
< 29.69 02/14/23
< 35.15
< 34.97
< 36.37
< 38.80
< 36.43 02121/23
< 25.47
< 17.04
< 21.05
< 2251
< 21.09 02/28123
< 21.10
<2UO
< 40.94
< 41.15
< 41.01 03/07123
< 2821
< H.90
< 21133
< *19_99,
< 20;33 03114/23
< 34.41
< 34.47
< 20.71
< 20,87
< 20"98 03121/23
< 35.. 80
< 35.54
< 30.07
< 30,35
< 28.23 03128/23
< 18..63
< 9.531
< 22.13
< 23.76,
< 23.71 04/05123
< 14.57
< 35.07
< 32.96
< 34.89
< 32.91 04/11/23
< 20.72
< 20.21
< 18.85
< 19.01
< 19,99 04/19/23
< 33.87
< 15.10
< 31.46
< 29.63
< 31.46 04/25123
< 35.34
< 14.85
< 23.79
< 2219
< 23.64 05/02/23
< 25.98
< 10.90
< 30.33
< 30.38,
< 30;33 05/09/23
< 8.763
< 20.89
< 28.28
< 28'38.
< 2828 05/16/23
< 35.15
< 35.09
< 35.03
< 37.38,
< 14.69 05123/23
< 10.45
< 24.40
< 21.66
< 21.51
< 21.66 05/30/23
< 40.. 91
< 40.84
< 29.02
< 29.02
< 29.07 06/06/23
< 37.76
< 37.76
< 37.63
< 37.82
< 15.73 06/13/23
< 31.24
< 15.11
< 28.39
< 30.78
< 28.74 06/20/23
< 41.88
< 44.61
< 42.63
<H.57
< 42.48 06/27/23,
< 34.35
< 34.41
< 3422
< 34.28
< 22.85
- Control station 39
TABLE 3-4 AIRBORNE IODINE
{10'3 pCi/mJ) lOCATIONS PIBRIOD ENDING 22 23 24*
01A 05A 07/05/23
< 25.90
< 40.20
< 25.86
< 24.43
< 25.78 07/11/23
< 37.19
< 37.19
< 37.25
< 34.67
< 35.10 07/18/23
< 21.27
<21.27
< 28.34
< 2tl.09
<2824 07/25/23
< 46.57
< 46.57
< 33.95
< 33.89
< 34.07 08/01/23
< 28.47
< 28.47
< 28.47
< 28.42
< 13.46 08/08/23
< 26..21
< 26.17
< 21.67
< 21.82
< 21.82 08/16123
< 23.12
< 23.12
< 25.34
<25.38
< 12,88 08/22/23
< 18.26
< 18.22
< 22.36
< 22.13
< 22.:36 08/29/23
< 24.02
< 10.16
< 16,.25
< 16,31
< 116,.25 09/05/23
< 28.07
< 28.02
< 28D7
< 28,.07
< 13.43 09112/23
< 22.78
< 29.91
< 39.15
< 39.64
< 39.09 09:/2{]/23
< 23.19
< 23.16
< 28.45
< 28.19
< 28.:54 09f26/23
< 40.60
< 17.06
< 45,.76
<46.14
< 45.76 10/03/23
< 22.. 34
< 22.30
< 10.45
< 22.57
< 22.34 10/10/23
< 33.14
< 13.95
< 301.06
< 29.59
< 30.06 10l17/23
< 28.30
< 28.25
< 26.55
< 27.40
< 26,.64 10l24.123
< 18.99
< 19.02
< 10.70
< 10.64
< 10.66 11/01123
< 39.17
< 39.17
< 16,.40
< 39.17
< 39.17 11/08/23
< 14.05
< 33.51
< 23.54
<23.62
< 23.54 11/15/23
< 48.. 51
< 32.56
< 66.19
< 66.31
< 66-.19 11121/23
< 30.41
< 30.41
< 29.68
<29.50
< 29.74 11/28/23
< 23.32
< 23.32
< 20.32
< 20.42
< 20.24 12/05/23
< 28.26
< 28.26
< 22.18
< 22.03
< 2222 12/12/23
< 22.21
< 22.21
< 24.69
< 24.95,
< 24.69 12/1'9!23
< 33.49
< 33.49
< 28.10
< 27.86,
<28.05 12/26/23
< 35.63
< 35.63
< 40.81
< 40.81
< 40.81
- Control Station 40
lOCAllON Be-7
(+/.:)
m 118.40 23.480 02 123.30 22.770 03 10520 27.390 04 114.70 24.140 05 108.30 24.180 06 119.40 23.0301 07 123.70 32.500 21 119.80 22.190 22 115.50 26.3801 23 14020 24.680 24*
117.60 20.990 01A 15-2.50 26.400 05A 114.70 24.070 lOCAllON Be-7
--('+i=f-- -
01 164;50 31.300 02 141.90 30.370 03 174.80
.25.040 04 19i1 :90 26.180 05 148.80 21.510 06 141.70 22.610 07 127:30 25.120 21 143:90 24.780 22 155:90 23.810 23 17420 26.300 24*
14520 20.7901 01A 133.50 26.160 05A 147.40 27.040
- Control location C&-134 ---
< 0.19889
< 0.9802
< 11.8520
< 0:9696
< 0.
19304
< 0.7701
< 1.7800
< 11.1430
< 11.1770
< 1.7320
< 1.0:reo
< 0.8745
<U110 TABLE ~5 AIR PARTICULATES (1 fr1 pCilhlJ)
GAMMA SPECTRA-QliR 1 (12127122 - 03J28f23)
~137
< 1.0730
< 0.9023
< 1.3720
< 0.8353
< 1.0590
< 0.8948
< 1.2510
< 0.8833
< U840
< 1.4290
< 0.7676
< 0.7815
< 0.9172 GAMMA SPECTRA AND STRONTIUM 89190- QTIR 2 (03/28/23 - 06127/23)
Cs-134
~137 Sr-89 Sr-90
< 11.7990
< 1.9210
< 7.3800
< 2:.1900
< 11.7260
< 1.6770
< 6.8100
< 2:.3200
< 11.4670
< 1JJ490
< 7.2000
< 29300
< 1.0090
< 0.636,1
< 7.8600
< 2:.5200
<U540
< 0.8637
< 7.3300
< 2:.6200*
< 0.8846
< 0.7342
< 7.7600
< 22100
<1.1220
< 0.8793
< 8.5700
< 2:.4400
<U570
< 1.0380
< 7.8500
< 2:.1200
< 1.3190
< 1.2330
< 6,3400
< 1.9000
< 0.9894
< 1.2260
< 7.7400
< 1.9300
<U830
< 1.0350
< 7.9500
< 23000
< 11.6480
< 1.11570 19.7200
< 2:.6300
< 11.4900
< 1.5150
< 8.8500
< 2:.1600 41
LOCATION Be-7
(+/-}
01 117.90 26.8901 02 116.80 22.100 03 153.60 25.510 04 153.40 24.950 05 154.40 29.5901 06 127.00 22.430 07 119.50 19.4001 21 11020 24.5601 22 145.40 23.1901 23 162.40 30.4601 24*
118.60 21.2701 01A 88.530 19.210 05A 150.60 25.170 LOCATION Be-7
(+/-)
01 126.30
- 29_390, 02 95.210 17.070 03 110.30 19.380 04 138.50 23.580 05 127.80 21.750 06 88.470 19.620, 07 102.80 17.720, 21 11420 22.320 22 113.00 22.920*
23 119.60 23.380 24*
94.510 19.550 01A 87.560 21.7901 05A 134.10 21.370
- Control location C&-134
< 0.8944
< 1.4740
< 1.1830
< U370
< 2.0220
< 1.3830
< U750
< 1.5020
< L4030
< 1.4560
< 0.9644
< 0.9637
< 0.6442 C&-134
< 1.6350
< 12540
< 1.3230
< 12320
< 1.1880
< 1-5840
< 0.6922
< 1.5590
< 1.4880
< 1.3320
< 1.1870
< 1.4480
< 1.1910 TABLE3-5 AIR PARTICULATES
( 1 o-3 pCi/m3)
GAMMA SPECTRA - QTR 3 (06/27123 - 09/26/23)
Os-137
< 0.8446
< 1.2530
< 1.0660
< 1.0000
< 1.8990
< 1.0020
< 0.9492
< 0.9421
< 1.3070
< 1.4260
< 1.0960
< 1.0020
< 0.6558 GAMMA SPECTRA-QTR 4 (09/26123 - 12J26123)
AmualMean C&-137 Be-7
(+/~}
< 1.3400 131.78 27.77
< 0.8564 119.30 23.08
< 1.0040 135.98 24.33
< 1.0830 149.63 24.71
< 0.9611 134.83 2426
< 1.2690 119.14 21.92
< 0.8550 118.33 23.69
< 1.6170 122.03 23.46
< 1.2980 132.45 24.08
< 0.9235 149.10 2621
< U 220 118.98 20.65
< 1.5040 115.52 23.39
< 0.8299 136.70 24.41 Mean of All lnclicator Locations 130.40 24275 42
COLLECTION LOCATION DATE 01 02 03 04 05 06 07 21 22 23 24*
05A COLLECTION LOCATION DATE 01 02 03 04 05 06 07 21 22 23 24*
05A Mean
- Control Location Sr--89 Sr-90 TABLE l-6 So~
(pCi/kg dry wt.)
K--40
(+/-)
Cs-134 Cs-137
(+{-)
Soil sampled on Triennial basis. Not requir,ed in 2023 Th-228 To-232
(+/-}
-<<T-5 43 Ra-226
(+/-)
TABLE 3-7 Precipitation (pCi/L)
LOCATION 01A COLLECTION DATE Gr-B H-3 Rainfall (inches)
- r+-7:,-- -------
01/31/23 2.0 1.1
< 942 2.53 02/28/23
< 1.7
< 1060 3.34 03/28/23 1.7 1.1
< 1010 1.28 04/25/23 5.2 1.4
< 939 1.66 05/30/23 1.7 1.0
< 994 5.40 06/27/23 3.6 1.1
< 1240 2.96 07/25/23 4.9 1.4
< 878 4.43 08/29/23 15.1 1.8
< 1220 2.34 09/26/23
< 1.6
< 1190 4.06 11/01/23 2.7 1.1
< 1310 1.31 11/28/23 2.2 1.1
< 1300 2.27 12/26/23 2.1 1.1
< 1220 4.71 Mean 4.1 1-2 Total 36.29 44
TABLE3-7 Precipitation (pCi/L}
LOCATION 01A COL.l..ECTION DATE Be-7 Mn-54 Fe-89 Co-58 Co-60 nn-65 Zr-95 00/27123
< 41.'97
< 1.432
< 1Hl8
< 3215
< 1.382
< 3.129
< 6.512 12J'JJ3123
< 35.83
< 1.406
< '9.564
< 2.785
< 1.419
< 3.365
< 5.712 Mean COL.l..ECTION DATE Nb-95 Cs-134 Cs-137 Ba-140 L.a-140
[-131 To-228 00/27/'23
< 3.816
< *LJ31
< 1.087
< 1985
< 695.3
< 24310
< 3.138 12126J23
< 3.371
< 1.441
< 1.20,3
<8512
< 267.8
< 6042
<2.491 Mean 45
COLLECTION!
LOCATIOJ\\I DATE
(+/-)
TABLE3-8 MILK (pCilL) 11-131*
Cs-134*
Cs-137" Ba-140*
.. Milk samples could not be obtained in 2023 due to the lack of dairy farms within the sampling area.
46 La-140"
TABLE3-9 Food and Vegetatiori (pCilkg wet wt. l LOCATION 14B COLLECHON OATE Be-7 K-40 1-131..
Cs-134..
Cs-137"*
(+/-)
{+J-)
04/11/23 785.7 299.2 6512 790.6
< 43.90
< 30.91
< 34.63 05109/23
<409.0 4568 777.0
< 37.70
< 38.90
< 40.97 06/13/23 604.7 235.6 6632 718.9
< 43.00
< 32.73
< 35.71 07111/23 2414 335.9 5067 584.1
< 4420
< 30.98
< 20.52 08/08/23 720.9 195.8 4711 570.5
<48.80
< 29.92
< 23.36 09/12123 757.7 259.3 5462 668.7
< 36.90
< 33.26
< 30.05 10/10123 1262 235.5 2599 449.6
< 39.50
< 27.65
< 23.11 Mean 1091 260.2 5079 651.3 LOCATION15 COLLECHON OATE Be-7 K-40 1-131'"'
Cs-134'"'
Cs-137"*
(+/-)
(+/-)
(+/-)
04/11/23 1246 422.5 6709 1127
< 30.30
< 58.44
< 4279
< 80.68 05/09/23
< 365.0 3042 593.9
< 43.00
< 37.48
< 30'"94
< 65.56 06/13/23
< 462.0 3845 766.7
< 48.60
< 31.98
< 37.04
< 65.59 07/11123 1833 350.6 4223 632.1
< 34.70
< 36.13
< 23.51
< 5298 08/08/23 590.1 193.0 4217 562.5
< 4520
< 30.90
< 29.93
< 4200 09/12123 570.0 157.8 3548 413.6
< 44.10
< 18;59
< 17.39
< 30.93 10/10/23 484.8 208.2 3353 518.9
< 48.40
< 24.27
< 25.36 52.39 40.02 Mean 944.8 266.4 4134 659.2 52.39 40.02 LOCATION 16*
COLLECHON OATE Be-7 K-40 1-131**
C-s-134:U-Cs-137"*
(+/-)
(+/-)
(+/-)
04/11123 1145 285.8 5859 680.6
< 41.80
< 33.16
< 31..79
< 57.65 05109123
<487.5 4190 851.6
< 47.60
< 37.60
< 37.41
< 66.83 06/13123
< 461.9 7137 922.6
< 50.00
< 40;33
< 38.57
< 57.58 07111/23 1734 317.2 5908 702.1
< 36.80
< 31.59
< 20.79
< 46.27 08/08/23 1688 230.0 4203 486.8
< 46.40
< 20.71
< 20.08 36.26 24.41 09/12123 1083 312.7 3473 616.3
< 3520
< 29.86
< 30.60
< 50.33 10/10/23 1010 205.0 4031 502.1
< 32.10
< 28.42
< 26.50 52.10 36.09 Mean 1332 270.1 4972 680.3 44.18 30.25
- coribol Station
- L'LD identified in ODCM 47
TABLE3-9 Food and Vegetation
{pCilkgwetwt.)
LOCATIONl23 COLLECTION DATE Be-7 K-40 1-131...
Cs.-134...
Cs-137,..
lh-228
(+/-}
,(+I-}
(+/-)
04/11123 1096 328.5 5439 747.9*
< 37.50
< 37.ff/
< 36.78
< 63.28 05109/23 626.5 374.3 3949 858.3
< 48.20
< 39.89
< 37.31
< 75..1)6 06/13/23 2567 406.0 5837 659.8
< 41.40
< 37.91
< 36.49 112.0 n.24 07111/23 1537 253.4 3905 442.5
< 47.60
< 28.:54
< 22.69
< 53.33 08108/23 1463 286.4 4057 508.2
< 48.oo
< 23.15
< 24.22
< 5227 09/12123
< 307.5 3804 622.7
< 38.80
< 33.70
< 27.11
< 48.15 10J10/23
< 251.1 2671 401.0
< 53.50
< 25.67
< 24.26
< 53.67 Mean 1458 329.7 4237 605.8 112.D n.24 LOCATIONl26 COLLECTION DATE Be-7 K-40 1-131...
Cs.-134...
Cs-137<*
lh-228 lh-232
(+/-}
{+/-)
(+/-)
(+/-)
04/11/23 1714 362.2 6525 754.6
< 19.00
< 43.05
< 33.57
< 68.71
< 171.0 05109/23 582.5 334.7 3296 711.3
< 48.30
< 36.74
< 37.22
< 64.69
< 188.0 06/13/23
< 468.9 4638 901.3
< 38.20
< 38.09
< 43.48
< 63.91
< 190.9 07/11/23 2140 258.2 5358 549.3
< 45.10
< 39.07
< 3212
< 51.83
< 128.5 08/08/23 1774 228.1 4832 501.1
< 49.00
< 24.24
< 18.82 63.42 31.10 110.4 44.. 59 09/12123 455 125.6 3809 306.5
< 40.00
< 16.08
< 15.98
< 26.88
< 66.58 10/10/23 477 201.3 2308 418.9*
< 33.00
< 28.16
< 26.28
< 48.67
< 104.6 Mean 1190 251.7 4395 591.9 63.42 31.10 110.4 44.59 Be-7 K-40 1-131...
CS-134...
CS-137"*
Tih-228 Th-232
{+/-}
{+/-)
(+/-)
(+/-)
All Indicator Mean 1168 275.1 4461 627.1 75.94 47.79 110.4 44.59
TABLE3-10 WELL WATER (pCi/L)
COLLECTION LOCATION!
DAlE H~
Sr-89 Sr-90 Mn-54 Fe-59 C0-58 Co-60 Zn-65 01A 03/28123
< 1010 (a)
(a)
< 5.74
< 13.7
< 5.32
< 6.69
< 13.8 06/27i'23
< 1240
< 4.71
< 0.801
< 1.51
< 3.17
< 1.60
< 1.67
< 3_11 09/26123
< 1220 (a)
(a)
< 6.12
< 12.2
< 6.17
< 7.85
< 13.8 12/27i'23
< 1220 (a)
(a)
< 4.51
< 10.5
< 4.91
< 4.98
< 11.9 Mean COLLECTION LOCATION DAlE Zr-95 Nb.95 l'-131 Cs-134 Cs-137 Ba--140 La-140 01A 03/28123
< 11.1
< 7.86
< 9.20
< 7.01
< 6.41
< 31.6
< 10.2 06/27123
< 2.59
< 1.67
< 3.10
< 1.65
< 1.63
< 8.33
< 2.81 09/26123
< 7.74
< 6.80
< 9.96
< 6.59
< 5.77
< '29.7
< 11.3 12/27123
< 8.70
< 6.08
< 8.24
< 5.52
<4.93
< 22.4
< 8.45 Mean (a) Sr-89/90 analyses perfomied,on the seoond qm11tersample.
49
TABLE3-11 RiverWater (pCi/1..)
LOCATION 11 COLLECTION!
DATE IH-3 Sr-89 Sr090 Mn-54" Fe-59*
Co-58*
C<HiO" Zn-65*
(+~)-
01/18123 (a)
(bl (b)
< 3.754
< 6.569
< 3240
< 3.528
<7.065 02/14123 (a)
(bl
{b)
< 7.953
< 13.70
< 6.408
< 7.334
< 13.17 03/14123 4660 851.0 (bl
{b)
< 4.916
< 12.67
<4.731
< 4.881
< 7.7,n 04/11123 (a)
(bl (b)
< 4.502
< 1021
< 5205
< 5.356
< 10.51 05/16/23 (a)
(bl
{b)
< 7.448
< 10.37
< 5.883
< 8.383
< 9.045 06/13123 5000 1070
< 4270
< 0.754
< 4.235
< 12.51
< 6.071
< 6.407
< 9.790 07/11123 (a)
(b)
(b)
< 5.282
< 12.05
< 6.470
< 6.277
< 13.03 08/16/23 (a)
(bl (b)
< 5.525
< 9.488
< 4.558
< 6.198
< 8.971 09/12123 6590 1020 (bl (b)
< 6.083
< 12.96
< 4.804
< 6.199
< 11.90 10,17123 (a)
(bl (b)
< 4.691
< 10.62
< 5.101
< 4.107
< 10.42 11/15123 (a)
(bl (b)
< 3.371
< 7.870
< 2.801
< 4.121
< 8.021 12/12123 5460 977.0 (b)
(b)
< 7.240
< 15.11
< 7.125
< 6.743
< 19.68 Mean 5428 979.5 Nb-95*
Zr0 95*
1-131*
es-134*
Cs-137" sa-140*
L.a-140*
01/18123
< 3.437
< 5.660
< 0.810
< 4.485
< 4.038
< 13.08
< 4.054 02/14123
< 7.783
< 12.58
< 0.741
< 7.765
< 5.750
< 23.77
< 6.116 03/14123
< 6.629
< 11.09
< 0.842
< 6.481
< 5.471
< 25.72
< 7.338 04/11123
< 6.791
< 9.180
< 0.789
< 4.711
< 4.993
< 26.08
< 1124 05/16/23
< 6.371
< 7.481
< 0.864
< 6.294
< 5.107
< 30.61
< 9.649 06/13123
< 5.436
< 8.338
< 0.695
< 5.211
< 5.175
< 27.45
< 7.597 07111123
< 5.947
< 8.496
< 0.901
< 5.437
< 5.153
< 28.79
< 11.58 08/16/23
< 5.059
< 7.717
< 0.749
< 4.782
< 4.717
< 19.36
< 5.770 09/12123
< 5.101
< 10.22
< 0.896
< 7.556
< 5.941
< 23.64
< 7.607 10/17123
< 4.678
< 8.366,
< 0.834
< 5.885
< 4.888
< 20.18
< 8.710 11/15123
< 3.842
< 6.468
< 0.849
< 3.105
< 2844
< 23.67
< 8.796 12/12123
< 9.896
< 10.77
< 0.859
< 8.362
< 6.374
< 27.59
<7.m Mean
- U.D identified in ODCM.
(a) Tritium analyses on quartefly coo,posite.
(b) -Sr-89/90 performed on 2nd quarter composite sample.
50
TABLE 3-12 Surtaoe Water (pCi/L)
LOCATION 08 COLLECTION DATE H-3 Sr-89 Sr-90 Mn-54*
Fe-59*
Co-58*
Co-60" Zn-65*
(+/-)
01/18/23 (a)
(bl
{b)
< 3.294'
< 5.525
< 3;530
< 3.230
< 5.841 02114/23 (a)
(bl
{b)
< 6.169
< 12.26
< 5.513
< 7.220
< 12.37 03/14/23 5650 899.0 (bl
{b)
< 4.878
< 13:90
<5.526
< 6.599
< 7.635 04/11/23 (a)
(bl
.(b)
< 5.569
< 9.659
< 5.070
< 6.257
< 13.18 05(16123 (a)
(b)
(b)
< 6.343
< 16.20
< 4.541
< 7.906
< 8.962 06/13/23 4150 1000
< 4.190
< 0.836
< 6.234
< 11.93
< 5_,945
< 6.747
< 15.87 07/H/23 (a)
(b)
(b)
< 4.905,
< 8.389
< 5.012
< 5.857
<9380 08(16/23 (a)
(bl
{b)
< 4.562
< 11.83
< 5.816
< 6.317
< 10.43 09/12/23 6350 moo (bl (b)
< 5.793
< 11.25
<4.819
< 7.115
< 11.00 10/17/23 (a)
(bl (b)
< 4.293
< 10.64
< 3.345
< 5.260
< 12.20 11/15123 (a)
(bl
{b)
< 3.204
< 7.830
< 3.797
< 3.681
< 7.521 12/12/23 5780 979.0
< 6.266
< 10.16
< 5.259
< 6.634
< 11.99 Mean 5483 969.5 Nb-95*
Zfc95*
1-131*
es-134*
Os-137" Ba-140*
L.a-140" 01/18/23
< 2.967
< 5.747
< 0.824
< 3.656
< 3.300
<12.85
< 3.882 02/14/23
< 5.805
< 10.27
< 0.810
< 6.317
< 7.069
< 29.38
< 7.983 03/14/23
< 5.940
< 6.n9
< 0.850
< 7.319
< 6.080
< 23.57
< 5.187 04/11/23
< 5.741
< 9.601
< 0.861
< 5.318
< 5.880
< 25.77
< 6.392 05(16123
< 5.369
< 13.79
< 0.825
< 7.635
< 6.159
< 29_30,
< 8.948 06/13/23
< 7.602
< 9.498
< 0.848
< 7.152
< 6.270
< 27.39
< 11.02 07/11/23
< 5.189
< 7.493
< 0.803
< 5.000
< 4.375
< 24.45
< 10.13 08(16123
< 5.910
< 9.157
< 0.871
< 5.858
< 6,077
< 25.73
< 7.482 09/12/23
< 4.604
< 9.507
< 0.913
< 5.200
< 6.702
< 16.86
< 8.555 10/17/23
< 5.577
< 8.726
< 0.910
< 4.519
< 3.775
< 19.77
< 7.954 11/15/23
< 3.803
< 7.151
< 0.937
< 3.607
< 3.680
< 22.97
< 7.681 12/12/23
< 8.171
< 11.29
< 0.700
< 7.228
< 5.709
< 25.64
< 8.485 Mean
{a) Tritium analyses on quarterly composite.
(b) Sr-89/90 performed on 2nd quarter composite sample.
51
TABLE3-12 Surface Water (pCi/l)
LOCATION 09A..
COll.ECTION DATE
Fe-59~
Co-58*
Co-60" Zn-65*
01/18123 (a)
(b)
(b)
< 4.369
< 10.68
< 4;307
< 4.576
< 9.900 02/14123 (a)
(b)
(b)
< 6.734
< 11.81
< 5.330
< 6.682
< 13.60 03/14/23
< 942.0 (b)
(b)
< 5.314
< 15.57
< 5.821
< 6.427
< 14.24 04/11/23 (a)
(b)
(b)
< 6.190
< 13.38
< 7.501
< 6.260
< 15.21 05/16123 (a)
(I>)
(b)
< 6.168
< 13.42
< 6.072
< 5.458
< 7.982 06/13123
< 894.0
< 4.480
< 0.833
< 6_829,
< 14.96
< 8.123
< 7.709
< 11.63 07(11/23 (a)
(b)
(b)
< 5.391
<,9.790
< 5.075
< 5.218
< 10.38 08(16123 (a)
(b)
(b)
< 6.042
< 12.57
< 5.730
< 6.234
< 12.76 09/12123
< 1200 (b)
(b)
< 6.453
< 11.14
< 6.063
< 5.816
< 10.19 10/17/23 (a)
(b)
(b)
< 5.151
< 10.97
< 3.769
< 5.307
< 9206 11/15123 (a)
(b)
(b)
< 3.480
< 7.480
< 3.809
< 4.150
< 8.687 12/12123
< 1250
< 8.577
< 14.76
<4.803
< 5.485
< 16.31 Mean Nb--95*
Zr-95' 1-131' Cs,c134*
Cs-137*
Ba-140*
La-140*
01/18123
< 5.577
< 9.749
< 0.837
< 6.106
< 6.098
< 23.66
< 7.375 02/14/23
< 6.447
< 10.20
< 0.801
< 7261
< 6.304
<.26.47
< 9.192 03114/23
< 6.985
< 11.84
< 0.823
< 6.559
< 7.447
< 31.06
< 8.249 04/11/23
< 6.666
< 11.68
< 0.804
< 6.091
< 6.065
< 30.21
< 7.133 05/16123
< 7221
< 11.73
< 0.772
< 5.935
< 5.096
< 24.59
< 12.55 06/13123
< 5.713
< 12.10
< 0.893
< 8.056
< 5.116
< 31.38
< 9.481 07/11/23
< 6.125
< 8.144
< 0.841
< 5.168
< 5.589
< 26.25
< 5.672 08(16123
< 5.445
< 7.502
< 0.723
< 6.893
< 4.789
< 25.45
< 11.52 09/12123
< 6.967
< 10.56
< 0.830
< 7.143
< 7.266
< 25.88
< 8.098 10/17123
< 5272
< 8.496
< 0.788
< 6.513
< 5.368
<.22.77
< 5.409 11/15123
< 3.701
< 6.449
< 0.943
< 4.077
< 3.689
< 23.33
< 7.161 12/12123
< 6.494
< 9.445
< 0.758
< 5.043
< 7.799
< 22.07
< 8.670 Mean
.. Control localioo.
(a) Tritium analyses on quarte,ty composite.
(b) Sr-00,00 performed on 2nd quarter composite sample.
52
LOCATION 08 09A*
11 08 09A*
11 LOCATION 08 09A*
11 08 09A*
11 COLl!..ECTION
!DATE 0510-2/23 05102/23 05102/23 10/11123 10/11123 10/11123 Indicator Mean Control Mean COLLECTION
!DATE 05102/23 05102/23 05102/23 10/11123 10/11123 10/11123 Indicator Mean Control Mean Sr-,89 (a)
(a)
(a)
< 531.0
< 1200
< 618.0 To-228
(+/-)
< 79.60 1002 82.36 1497 143.3 257.2 101.5 216.7 120.7 2051 156.7 1268 133.8 158.5 101.5 (a) Sr-89/90 analyses perfonned annually.
- Control location, Background location TABl!..E3-13 Sediment Silt (pCi/kg dry wt.)
Sr-90 K-40 Cs-134 Cs-137 Ra-226
(+/-) -
,.;;:r-(+/-)
(a) 944-7 501.1
< 43.91),
< 47.. 69
< 924.9 (a) 13760 1682
< 69.37
< 60.43
< 1076 (a) 19560 2144
< 1112 222.4 9520
< 1918
< 16.60 20,17 838.5
< 102.4
< 82.54
< 1749
< 38.50 15310 1986
< 81.62
< 61.94
< 1519
< 39.50 20660 1703
< 1092
<9529 3059 1518 10795 1297 222.4 95.20 3059 1518 14535 1834 Th-232
(-+Pj
< 176.8
< 281.9 1417 256.4
< 362.1
<443.9 1653 209.4 1535 2329 53
COLLECTION LOCATLON DATE Sr-89 06 05/02/23 (a) 06 10111.123
< 910.0 Mean OOLLECTl:ON LOCATION DATE Ths228
(+/-)
08 05/02123
< 160.1 06 10f11.12.3 136.9 75.25 Mean 136.9 75.25
Sr-90 (a}
< 43AO Th-232
< 310.0
< 251.3 TABLE 3-14 Shoreline Sorn (pCilkg drywt.)
LOCATIO!llS K-40
(+/-)
1471 957.1 1093 547-5 1262 752.3 54 Cs-134*
< 73.87
< 66.62 Cs-137*
< 77.63
< 62.32 Ra-226
< 1545
< 1276
COLLECTION LOCATION
. Fish Type, DATE K-40
(+/-)
08 (a) 05123123 1758 823.8
,(b) 05/23123 1946 835.9
,(11) 11101/23 2268 1382
[b) 11101123 1790 792.8 25..
(a) 05/10123 2058 847.8 (b) 05/10123 2268 750.2 (11) 11/16123 2418 857.2 (b) 11/16123 1974 911.3 Mean 2060 900.1 Indicator Mean 1941 958.6 Control Mean 2180 841.6 COLLECTION LOCATION DATE Cs-134*
08 (11) 05/23123
< 79.75 (b) 05/23123
< 48.33 (11) 11101123
< 95.61 (b) 11101123
< 76.80 25" (11) 05/10123
< 72.86 (b) 05/10123
< 49.91 (11) 11/16123
< 76.85
,(b) 11/16123
< 58.11 Mean Indicator Mean Control Mean
- Control Station (a) Non-bottom dwelling species of gamefish.
(b) Bottom dwelling species of fish.
TABLE3-15 Fish (pCi/kg wet wt.)
Mn-54*
< 68.02
< 54.25
< 74.36
< 70.46
< 66.67
< 48.93
< 52.28
< 58.93 Cs-137*
< 75.06
< 53.30
< 83.60
< 72.70
< 66.79
< 51.86
< 58.50
< 61.09 Fe-59"
< 137.2
< 111.6
< 214.8
< 217.7
< 111.6
< 95.46
< 157.3
< 150.0 55 Co--58*
Oo-60*
Zn-65*
< 63.60
< 55.61
< 145.3
< 69.10
< 60.43
< 77.08
< 87.32
< 102.6
< 177.0
< 83.57
< 64.41
< 176.3
< 46.80
< 64.99
< 125.7
< 41.57
< 52.84
< 101.1
< 63.62
< 83.45
< 134.2
< 78.25
< 99.01
< 140.6
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2023 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 2023 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. Cs-13 7, a plant related nuclide, was detected in one aquatic sediment sample in 2023 at a level of 222.4 pCi/kg. In the past, Cs-13 7, 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 2023 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 7.0
.i::.
+-'
C:
6.0 0
~
"C
+-'
5.0 V) 0:: E Environment al TLD 4.0 sector TLD 3.0 2.0 1.0 0.0 Figure 4-1 TLD (mrem/Standard Month)
Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The average level of these 32 sector TLD locations (two badges at each location) was 4.2 mR/standard month with a range of 1.4 to 9.4 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61. This value was 7.2 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 3.4 mR/standard month with a range of 1.7 to 6.0 mR/standard month. The average annual reading for these locations was 3.0 mR/standard month with a range from 2.0 to 4.8 mR/standard month. The control location showed a quarterly average of 2.9 mR/standard month with a range of 1.8 to 4.3 mR/standard month. Its annual reading was 2.6 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.2 mR/standard month with EPSP-9/10 having the highest quarterly average of 8.0 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 quatierly average of 3.4 mR/ standard month, while Station C-1/2 and C-5/6 had a quarterly average of 2. 7 mR/standard month with a range of 1.4 to 4.0 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 pCi/m3.
57
0.12 ---
0.1 0.08
("(')
E
~ 0.06 0.04 0.02 0
<Xl
<Xl C:
(0 3.00E-02 2.S0E-02 2.00E-02
("(')
E 1.S0E-02 u c..
1.00E-02 5.00E-03 0.00E+OO O'l
.-i
<Xl q,
- a.
Q)
(0 v')
~
N N
.-i 1 C:
- I (0
4.3 Airborne Radioiodine control Indicator Average Pre-Op Required LLD m
'SI' I.I)
<Xl O'l
.-i rn
'SI' I.I)
<Xl O'l
.-i rn
'SI' I.I)
<Xl O'l
.-i rn O'l O'l q,
O'l O'l 9 0
0 9
0 0
';i
.-i
';i
';i
.-i
.-i C')I N
I I
I I
C:
I I
- a.
C:
I I
I C
- 0.
C
- 0. >
- 0. >
C
- 0. >
C
- 0. >
C (0
Q)
(0 (0
Q)
(0 (0
Q)
(0
~
Q)
(0
~
Q)
(0 (0
Q)
(0 (0
v')
~....,
v')
~....,
v')
~
v')
~
v')
~....,
v')
~....,
Figure 4-2 Historical Gross Beta in Air Particulates control Indicator m m
'SI'
'SI' I.I')
I.I')
I.I)
I.I) r-.
r-.
<Xl
<Xl O'l O'l 0
0
.-i
.-i N
N rn rn
.-i
.-i
.-i 1
.-i 1
.-i 1
.-i 1
.-i 1
.-i 1 N
N N 1 N 1 N 1 I
I C:
I I
I C:
I I
I C:
I C
~
C
- I
- I C
~
C
~
C
~
~
C :5 C
- I
~
C
- I (0
(0 (0
~
~
(0
~
~
(0 (0
(0 Figure 4-3 2022 Gross Beta in Air Particulates (pCi/rtf)
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 not scheduled for collection in 2023.
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.
- 4. 7 Precipitation A sample of rain 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 2023. 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 2023 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 rep01iing period due to the closure of the final operating daily 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-13 7, attributable to fallout, have been seen periodically in vegetation samples. Cosmogenic beiyllium-7 was detected in twenty seven of thirty five samples. Naturally occtming potassium-40 was detected in all samples. Naturally occmTing thorium-228 was detected in four of thirty five samples.
No plant related isotopes were identified in any vegetation sample during 2023.
4.10 Well Water Water was sampled quaiierly from the onsite well at the metrology laborat01y. These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, 1-131, and gamma emitters. The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. No gamma emitting isotopes were detected during the pre-operational period.
59
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 5428 pCi/liter and a range of 4660 to 6590 pCi/liter, see Figure 4-4. No river water samples were collected during the pre-operational period.
10000 9000 8000 7000 ------
6000
..I 5000 u
Tritium C.
4000 Required LLD 3000 2000 1000 0
Figure 4-4 Tritium in River water 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma spectroscopy and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium.
Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90. There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.
No non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the samples. Tritium was not detected in any sample at the control location. The average level of tritium activity at the indicator location was 5483 pCi/L with a range of 4150 to 6350 pCi/L.
60
20000 18000 16000 14000
~ 12000 u
- a. 10000 8000 6000 4000 2000 0
N N
.-I j C:
~
4.13 Bottom Sediment C"O C"O
"<I"
"<I" U1
.-I
.-I
.-I j
.-I C:
C:
C:
re re
~
Tritium Required LLD Avg. Pre-Op U1
<O
<O r--
r--
00 00 en en 0
0
.-I
.-I N
N C"O C"O
.-I '? j
.-I
.-I '? j
.-I
.-I l";J N
N N
l";J 1 N
N C:
I I
C:
C:
C:
C:
C:
C:
C:
~
~
re re re re re
~
Figure 4.5 Tritium in Surface Water Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.
Sediment samples were collected during 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.
Cs-137 was detected in one indicator sample in 2023 at a level of 222.4 pCi/kg. 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-13 7 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. Levels during this phase varied by location and date and averaged 360 pCi/kg. 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 2023. 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 occuning radioisotopes were detected in these samples at background levels.
61
500 450 400 350
?I 300
~
station OS u 250 C.
station 09A 200 station ll 150 Pre-Operational 100 50 0
ro LI')
<.O r--
00 en 0
.-i N
ro LI')
<.O r--
00 en 0
.-i N
ro 0
0 0
0 0
0
.-i T-;i T-;i T-;i T-;i
.-i.-i
.-i.-i N
N N
N
.6
.6.6.6.6.6.6 I
I I
I I
I.6.6
.0.0.0
.0.0.0.0.0.0.0 Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
Q)
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Q)
- u.
- u. u. u. u. u. u. u. u. u.
- u. u. u. u. u. u. u..
u..
u..
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 2023 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-13 7 was measured in pre-operational environmental fish samples.
62
- 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2023 - North Anna Location Description Date of Sampling Reason( s) for Loss/Exception 14B,15,16,23,26 Vegetation 01/11/23 Seasonal unavailability 14B,15,16,23,26 Vegetation 02/14/23 Seasonal unavailability 14B,15,16,23,26 Vegetation 03/14/23 Seasonal unavailability 14B,15,16,23,26 Vegetation 11/15/23 Seasonal unavailability 14B, 15, 16,23,26 Vegetation 12/12/23 Seasonal unavailability 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 (1 0CFR50), "Domestic Licensing of Production and Utilization Facilities".
United States Nuclear Regulatory Commission Regulat01y Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I",
October, 1977.
United States Nuclear Regulato1y 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 Laborato1y, "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
Direction Distance (miles)
Nearest Site Boundary N
0.87 NNE 0.85 NE 0.82 ENE 0.81 E
0.83 ESE 0.85 SE 0.88 SSE 0.91 s
0.94 SSW 1.01 SW 1.06 WSW 1.09 w
1.06 WNW 1.02 NW 0.97 NNW 0.90 APPENDIX A: LAND USE CENSUS Year 2023 LAND USE CENSUS North Anna Power Station Louisa County, Virginia January 1 to December 31, 2023 Nearest Nearest Resident Garden(>
50m2) 1.3 2.75 0.9 3.25 0.9 1.6 2.37 2.4 1.25 2.05 1.53 1.7 1.4 1.9 1.0 2.66 1.03 1.48 1.11 2.00 1.56 2.16 1.62 2.26 1.5 1.96 1.1 2.05 0.98 1.09 1.0 1.33 66 Nearest Nearest Nearest Meat Milch Milch Animal Cow Goat NONE NONE NONE 1.6 NONE NONE 1.6 NONE NONE 2.49 NONE NONE 3.5 NONE NONE NONE NONE NONE 1.4 NONE NONE 1.6 NONE NONE 2.0 NONE NONE 2.0 NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE 2.3 NONE NONE
2022 to 2023 Land Use Census Changes 2022 2023 Nearest Direction Distance Distance Resident NONE Site Boundary NONE Garden WNW SW Meat Animal NONE Milch Cow NONE Milch Goat NONE 2.67 3.96 67 2.05 2.16
APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS Year 2023 The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate (AP), air iodine, milk, soil, vegetation, and water matrices that represent test & matrix combinations available for REMP programs. 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 Laborato1y Accreditation Conference (NELAC), state-specific Perfonnance Testing (PT) program requirements or ERA's SOP for the Generation of Perfo1mance 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 regulato1y document.
C. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of perf01mance:
- 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 Perfonnance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not always resemble typical environmental samples obtained at commercial nuclear power facilities.
For the TBE laboratory, 124 out of 131 analyses performed met the specified acceptance criteria. Seven analyses did not meet the specified acceptance criteria and were addressed through the TBE Con-ective Action Program. A summaiy is found below:
- 1. The MAPEP February 2023 Soil Ni-63 result was evaluated as Not Acceptable. TBE's rep01ied value was 294 Bq/kg and the known result was 1130 Bq/kg (range 791 - 1469). The sample was reprepped by a different (senior) lab technician with results of 1120 & 1250 Bq. It was determined that there was a difference between the two techs during the sample prep (technique) and the procedure was revised to reflect these differences including using a specific aliquot amount.
(NCR23-08)
- 2. The MAPEP February 2023 vegetation Sr-90 result was evaluated as Not Acceptable. The reported value was 0.05 Bq (not detected) and the known result was a "false positive". This was considered to be a statistical failure because TBE's rep01ied result with 3 times the uncertainty resulted in a slightly positive net result (0.03194 Bq/kg). The rep01ied result was significantly below TBE's average detection limit for vegetation samples. (NCR 23-09)
- 3. The ERA RAD February 2023 water Ba-133 result was evaluated as Not Acceptable. The reported value was 26.0 pCi/L and the known was 22.3 (acceptance range 17.1 - 25.8 pCi) or 117% of the known (acceptable for TBE QC). The sample was used as the workgroup duplicate with a result of 25.4 (114%). The sample had also 68
been counted on a different detector with a result of 21.9 (98% ). The was TBE' s first failure for Ba-133. (NCR 23-10)
- 4. The MAPEP August 2023 soil Fe-55 result was evaluated as Not Acceptable. The reported value was 346 Bq/kg and the known result was 1280 (acceptance range of 896-1664 Bq/kg). This was TBE's initial evaluation for Fe-55 in soils.
The result was received at the end of December and the root cause in under investigation. No client samples were associated with this cross-check. (CAR 23-31)
- 5. The Analytics September 2023 milk Sr-90 result was evaluated as Not Acceptable. The reported result was 7.28 pCi/L and the known result was 12.8 (57% of known). This sample was used as the workgroup duplicate and the carrier yields for both samples were 107% and 75%. The LCS recovery for the workgroup was at 106%. The ERA drinking water Sr-90 cross check that was analyzed around the same time was acceptable at 108%. There was no explanation for the failure.
This is the first low biased failure for Sr-90 milk. The last failure (high) was in 2016. (NCR 23-24)
- 6. The ERA RAD October 2023 water Gross Alpha result was evaluated as Not Acceptable. The reported result was 53.2 pCi/L and the known result was 70.6 (acceptable range of 54.0- 87.2 pCi/L). The reported result was the workgroup duplicate and was within 75% of the known value (within TBE QC range). The original result was 63.3 pCi/L (90% of the known). Because the LCS result was biased slightly high, the decision was made to report the lower value. (NCR 23-20)
- 7. The ERA RAD October 2023 water I-131 result was evaluated as Not Acceptable. The reported value was 23.5 pCi/L and the known result was 29.7 (acceptable range of25.8 - 33.6) The reported result was 79% of the known, which is within the acceptable TBE QC range. The workgroup was reviewed with no anomalies found. The LCS/LCSD results were 109% and 86.1 %. The sample was not processed in a timely manner as per the ERA instructions which stated to analyze shortly after receipt due to the short half-life. Going forward, the QA &/or Lab Mgr. will ensure that this analysis is started sooner. (NCR 23-21)
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 Cto$$ Check Program TeledJ:rie Brown Ensineering Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value (ii)
Analytics Result EvaluaUon (b}
Value March 2023 E13826 Milk Sr-89 pClll 70.5 93.1 0.76 w
Sr-90 pCIJL 12.3 14.7 0.84 A
E13827 Milk Ce-141 pCi/L 127 139 0.91 A
Co,.58 pCIJL 119 131 0.91 A
Co-60 pCIJL 250 279 0.90 A
Cr-51 pCIJL 246 302 0.82 A
Cs-134 pCi/L 172 200 0.86 A
Cs-137 pClll 125 140 0.89 A
Fe-59 pCIJL 122 122 1.00 A
1-131 pCIJL 70.2 82.0 0.86 A
Mn-54 pCIJL 165 180 0.92 A
Zn-6-5 pCIJL 306 306 1.00 A
E13828 Charcoal 1-131 pCi 79.0 89.9 0.88 A
E13829 AP Ce-141 pCi 91.9 87.8 LOS A
Co-58 pCi 87.5 82:.S 1.06 A
Co-60 pCi 199 178 U3 A
Cr-51 pCi 218 191 U4 A
Cs-134 pCi 119 128 0.94 A
Cs-137 pCi 92.4 88.7 1.04 A
Fe-59 pCi 95.5 76.9 1.24 w
Mn-54 pCi 120 113 1.06 A
2n-65 pCi 179 193 0.93 A
E13830 Soil Ce-141 pCi/g 0.224 0.220 1.02 A
Co-58
,pCi/g 0.19-3 0.207 0.93 A
Co-60 pCi/g 0.406 0.-441 0.92 A
Cr-51 pCi/g 0.464 0..477 0.97 A
Cs-134 pCi/g 0.334 0.316 1.06 A
Cs-137 pCi/g 0.270 0.288 0.94 A
Fe-59 pCi/g 0.183 0.193 0.95 A
Mn-54 pCi/g 0.263 0.284 0.93 A
Zn-65 pCi/g 0.475 0.484 0.98 A
E13831 AP Sr-89 pCi 99.4 90.. 8 1.09 A
Sr-90 pCi 14.8 14.3 1.02 A
(a) The Amitytics known vahJ& is equal to 1003/4 of the parameter present in the sta-ndaro as determined by gravimetric 8J'ld/or volumetric measurements made during standard preparation (b) Analytics evaluallcm based on TSE internal QC limits:
A = Acceptabre
- reported result falls within ratio {irnifs of 0. 80-1.20 W = AC{;epfabre with warning - reported result rails within 0.7().(J.80 or 1.20-1.30 70
AnalytiC$ EnvironmentaJ Radioactivity Cross Check Program Teled:r;ne Brown EngineerinS EnvironmentaJ Services Identification mE Known Ratio,of l'BE to MonlhNear Number Malrix Nuclide Units Reported Value c;;)
An~lytlcs Result Evaluation (b)
Value N,. Not Ae,ceptab/e
- reporlBd result falls outside tile ratio limits of< 0. 70 and > 1.30 september 2023 E13832 Milk Sr-89 pCi/L 49.8 71.4 0.70 w
Sr-90 pCi/L 7.28 12.8 0.57 N (1)
E13833 Milk Ce-141 pCi/L 93.4 104 0.90 A
Co-58 pCi/L 58.2 85.8 0.88 A
eo-eo pCi/L 190 223 0.85 A
Cr-51 pCi/L 207 205 1.01 A
Cs-134 pCi/L 96.0 114 0.84!
A Cs-137 pCi/L 121 141 0.86 A
Fe-59 pCi/L 78.8 78.8 1.00 A
1-131 pCi/L 27.9 37.4 0.75 w
Mn-54 pCi/L 128 146 0.88 A
Zn-6-5 pCi/L 185 203 0.91 A
E13834 Charcoal 1-131 pCi 76.9 78.7 0.98 A
E13835 AP Ce-141 pCi 91.9 87.. 1 1.05 A
Co-58 pCi 58.7 55.2 1.06 A
Co-60 pCi 200 187 1.07 A
Cr-51 pCi 192 172 U2 A
Cs-134 pCi 89.6 96 0.94 A
Cs-137 pCi 109 119 0.92 A
Fe-59 pCi 68.3 66.1 1.03 A
Mn-54 pCi 129 123 1.05 A
Zn-65 pCi 163 171 0.96 A
E13836 Soil Ce-141 pCi/g 0.228 0.184 1.24 w
Co-58 pCi/g o.rna 0.116 0.89 A
Co-60 pCi/g 0.364 0.394 0.92 A
Cr-51 pCi/g 0.371 0.362 1.02 A
Cs-134 pCi/g 0.176 0.202 0.87 A
Cs-137 pCi/g 0.285 0.315 0.90 A
Fe-59 pCi/g 0.140 0.139 1.00 A
Mn-54 pCi/g 0.237 0.259 0.92 A
Zn-65 pCi/g 0.349 0.359 0.97 A
E13837 AP Sr-89 pCi 74.6 80.2 0.93 A
Sr-90 pCI 13.9 14.4 0.96 A
(a) The Analytics known value is equal to 1003/4 of the parameter present in the standard as determined.by gravimetric and/or volume1Jic measurements 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 waming
- reported result falls within 0.70-0.80 or 1.20-1.30 N "' Not Acceptable
- report.ed result falls outside the ratio limits of< 0. 70 and > 1.30 71
MonlhNear (1) See NCR.23*2A AnalytiC$ Envitonmentat Radioactivity Cross Che(:k Program T etedyne Brown Engineering Environmental Services ldentlflcatlon Number Malrix TBE Known Ratio of TBE to Nuclide Units Reported Value 1.,>
An~lytics Result Value 72 Evaluation (b}
DOE's Mixed Analyte Perfonnance Evall,lillion Program (MAPEP)
Teledl!!e Brown Engineeri!!a Environmental services Identification TBE Known Acceptance l\\r1onth/Y ear Matrix Nuclide UnilS Reported Evalualion !bl Number Value Value 1~>
Range February 2023 23-1\\.18848 Soil Ni-63 Bq/kg1 294 1130 791 - 1469 w3>
23-MaSU48 Urine Cs-134 Sq/l 9.92 10 6.7-12.4 A
Cs-137 Bq/l 0.0994 (1)
A Co-57 Sq/l 9.35 8.67 6.07-11.27 A
Co-60 Sq/l 9.0-3 8.13 5.69-10.57 A
Mn-54 Sq/L 11.80 10.0 7.0- 13.0 A
U-234 Sq/L 0.01 Nol spiked U-238 Sq/L 0.01 Nots,plked Zn-65 Sq/L 10.60 9.29 6.50-12.08 A
23-MaW48 Water Ni-63 Sq/l 23.1 27.3 19.1 - 35.5 A
23-RdV48 Vegetation Cs-134 Bq/sample 5.6 7.6 5.32
- 9.88 w
Cs-137 Bq/sample 0.03 (1)
A Co-.57 Sq/sample 5.9 6.9 4.85
- 9.01 A
Co-60 Bq/sample 5.00 6.51 4.56
- 8.46 w
Mn-54 Bq/sample 6.08 8.03 5.62 - 10.44 w
Sr-90 Bq/sample 0.05 (1) rJ4)
Zn-65 Bq/s.ample 5.49 7.43 5.20-9.,68 w
August2023 23-MaS49 Soil Fe-55 Bqlkg 346 1280 896 -1864 N
Ni-63 Bqlkg 1260 1370 959 - 1781 A
23-MaW49 Water Ni-63 Bq/l LO 1
(2)
A 23-RdV49 Vegetation Cs-134 Sq/sample 3.860 4.98 3.49
- 6.47 w
Cs-137 Bq/sample 0.027 (1)
A Co-57 Bq/sample 3.88 4.24 2.97 -5.51 A
Co-60 Sq/sample 2.37 2.79 1.95 -3.63 A
Mn-54 Bq/s.ample 2.04 2.56 1.79
- 3.33 w
Sr-90 Sq/sample 0.96 U7 0.82 -1.52 A
Zn-65 Bq/sample
-0.514 (1)
A (a} The MAPEP f<flCiWil value*.$ equal to 100% of the paramet&r pteM.nl in the* standard as (MMmi/nea.by (JfaVriMtrfc and/Or VOlunM!ric mitaSUntlrntnts made during.s.Jandard prepa.rali<<J (b} DOEIMAPEP evatuarion:
A = Accaptable - repo.rted result fads Within ralitJ limits of 0.80-1.20 W = ~ptabM with wamNlg -repo.rtM reWJt fads within 0.70-0.80 or 1. 2(M.30 N = Not A<<eptabte -.repo.rt~Cl result fa/ts outside thtt ratitJ limits of-< o. 70 and> 1.30 (1} Fal.sef>0$11ill:8 l8SI (2) SensitMty evatualion (3) See NCR 28-08 (4) See NCR 28-09 (5) Initial evaluation ~ See CAR 23-31 73
ERA Envlronmental Radioactivity Cross Check Program Teledyne Brown Engineering Envlronmental Services Month/Year ldentmcalion Matrix Nuclide Units TBE Reported Known Acceptance Evaluation (bl Number Value Vatue C")
Limits March 2023 MRAD-38 Water Am-241 pCifL 28.1 321 22.0 - 41.0 A
Fe-55 pCill 1100 1380 811 - 2010 A
Pu-238 pCi/L 65.6 70.7 42.5 - 91.6 A
Pu-239 pCill 82.9 924 57.2 - 114 A
Soil Sr-90 pCVkg 2630 2580 803 - 4020 A
AP GR-A pCi/filter 69.6 76.8
-40.1
- 127 A
GR-B pCi/filter 36.8 328 19.9-49.6 A
April 2023 RAD-133 Water Ba-133 pCilL 26.0 223 17.1 -25.8 N(tl Cs-134 pCiJL 72.1 77.6 63.4 - 85.4 A
Cs-137 pCill.
62.1 63.1 56.8 - 72.2 A
Co.so pCill 32.6 30.3 26.7 - 36.1 A
Zn-65 pCiJL 253 242 218 - 283 A
GR-A pCiJL 34.2 29.2 14.9 - 38.2 A
GR-8 pCill 64.3 60.7 41.8 - 67.4 A
U-Nat pCill 61.75 627 51.2 - 69.0 A
H..J pCiJL 13,300 12700 11, 100 - 14,000 A
Sr-89 pCiJL 67.0 61.1 49.2 - 69.0 A
Sr-90 pCi/L 36.5 36.0 26.4 - 41.5 A
1-131 pCi/L 24.3 28.7 23.9 - 33.6 A
September 2023 MRAD-39 Water Am-241 pCi/L 54.0 71.0 48.7 - 90.8 A
Fe~ss pCi/L 2430 2630 1550 - 3830 A
Pu-238 pCi/L 172 177 106 - 229 A
Pu-239 pCifL 171 182 113 - 224 A
Soil Sr-90 pCVkg 9580 6800 2120 - 10,600 A
AP GR-A pCi/filter 82.2 79.8 41.7 - 131 A
GR-B pCi/filter 54.3 426 25.8 - 64.4 A
October 20.23 RAD-135 Water Ba-133 pCi/L 86.3 922 73.8
- 111 A
Cs-134 1pCiJL 38.4 41.2 27.9 - 54.5 A
Cs-137 1pCill 194 199 161
- 237 A
!pCi/L 49.5 47.8 33.8 - 61.8 A
Zn-65 pCiJL 59.7 57.0 23.7 - 90.3 A
GR-A pCill 53.2 70.6 54.0
- 87.2 N (2l GR-8 pCiJL 46.9 422 30.5 - 53.9 A
U-Nat pCiJL 51.26 51.7 45.9-57.5 A
H..J pCilL 20,100 22,900 19,700 - 26,100 A
Sr-89 pCill 51.1 38.2 25.2 - 51.2 A
Sr-90 pCil.L 31.7 35.7 30.3 - 41.1 A
1-131 pCiJL 23.5 29.7 25.8 - 33.6 N(3)
(a) The ERA known val1.1t1 Is equal to 1003/4, of the paramitter pras&nt in I/le standard as determiMd by gravimetti<; and/or volumeltic measu,ements made during stal'lllatd prttparatiO_n.
(b) ERA eva!Uation:
A = Acceptabia - Report.lid val.ue falls Wilhm the Acceptaoo, limits N = Not* Acceptable " Report<<d value fallS outside of the Acceptance Limi.'ls (1) S. NCR 23*10 (2) S. NCR 23*20 (3) SH NCR 23*21 74