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{{#Wiki_filter:VIRGINmI ELECTRIC AND POWER | {{#Wiki_filter:VIRGINmI ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 2014 United States Nuclear Regulatory Commission Serial No. 14-129 Attention: | ||
Document Control Desk NAPS/ | Document Control Desk NAPS/JHL Washington, D. C. 20555 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) | ||
NORTH ANNA POWER STATION UNIT NOS. 1 AND | 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 5.5.2c, enclosed is the 2013 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 Page Kemp at (540) 894-2295.Very truly yours, Gerald T. Bischof Site Vice President Enclosure Commitments made in this letter: None Serial No. 14-129 NAPS Annual Radiological Environmental Operating Report cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station Dominion North Anna Power Station Radiological Environmental Monitoring Program Januaty 1, 2013 to December 31, 2013 Prepared by Dominion, North Anna Power Station Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2013 to December 31, 2013 Prepared by: Reviewed by: Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station C 'eorge R. Simmons Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B. Evans'dr.Manager Radiological Protection and Chemistry Dominion North Anna Power Station Approved by: 2 Table of Contents 1. EX ECU TIV E SU M M A RY ....................................................................................................... | ||
Very truly yours,Gerald T. | 4 2. PRO G RA M D ESCRIPTION | ||
Manager Radiological Protection and Chemistry Dominion North Anna Power | |||
...................................................................................................... | ...................................................................................................... | ||
7 2.1 Introduction | |||
............................................................................................................................. | ............................................................................................................................. | ||
7 2.2 Sam pling and A nalysis Program ........................................................................................ | |||
8 3. A N A LY TICA L RESU LTS ........................................................................................................ | |||
22 3.1 Sum m ary of Results ........................................................................................................ | |||
22 3.2 A nalytical Results of 2013 REM P Sam ples ................................................................... | |||
32 4. D ISCU SSION O F RESU LTS ................................................................................................... | |||
60 4.1 G am m a Exposure Rate ................................................................................................... | |||
60 4.2 A irborne G ross Beta ......................................................................................................... | |||
62 4.3 A irborne Radioiodine | |||
...................................................................................................... | ...................................................................................................... | ||
63 4.4 A ir Particulate G am m a ................................................................................................. | |||
n ...... | n ...... 63 4.5 A ir Particulate Strontium | ||
................................................................................................. | ................................................................................................. | ||
64 4 .6 S o il ........................................................................................................................................ | |||
6 | 6 4 4.7 Precipitation | ||
.......................................................................................................................... | .......................................................................................................................... | ||
64 4.8 Cow M ilk .............................................................................................................................. | |||
64 4.9 Food Products and V egetation | |||
........................................................................................ | ........................................................................................ | ||
65 4.10 W ell W ater .......................................................................................................................... | |||
65 4.11 River W ater ......................................................................................................................... | |||
66 4.12 Surface W ater .............................................................................................................. | |||
........ | ........ 67 4.13 Bottom Sedim ent ................................................................................................................ | ||
68 4.14 Shoreline Soil ...................................................................................................................... | |||
69 4.15 Fish ....................................................................... | |||
70 5. PRO G RA M EX CEPTION S ..................................................................................................... | |||
71 RE FERE N CES .................................................................................................................................... | |||
72 A PPEN D ICES ..................................................................................................................................... | |||
73 A PPEN D IX A : LA N D U SE CEN SU S ...................................................................................... | |||
74 APPENDIX B: | |||
==SUMMARY== | |||
OF INTERLABORATORY COMPARISONS | |||
.......................... | .......................... | ||
77 3 | |||
: 1. EXECUTIVE | : 1. EXECUTIVE | ||
The REMP | ==SUMMARY== | ||
no undue environmental effects occur and the health | This document is a detailed report of the 2013 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2. Radioactivity levels from January 1 through December 31, 2013, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized. | ||
The program also detects any unexpected environmental processes that could allow radiation accumulations in | 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. | ||
North Anna Power Station personnel collect a variety | The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.Radiation and radioactivity in the environment is monitored within a 25-mile radius of the station. North Anna Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. | ||
Control samples are collected from areas that | Control samples are collected from areas that are beyond the measurable influence of North Anna Power Station or any other nuclear facility. | ||
These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna | These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. | ||
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. | ||
These samples show how | Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a"pre-operational baseline." Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident, Fukushima Daiichi or natural variation. | ||
Indicator samples | Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and Teledyne Brown Engineering Environmental Services provided radioanalytical services. | ||
Prior to station operation, samples were collected and analyzed to determine | Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. | ||
Analysis results from the indicator samples | Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods.4 Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible. | ||
The NRC also mandates a reporting level for certain radionuclides. | |||
Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) | Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, water, aquatic, terrestrial, and direct radiation exposure. | ||
Participation in an Interlaboratory Comparison Program provides | The airborne exposure pathway includes radioactive airborne iodine and particulates, and precipitation. | ||
Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods.4 Because of this, the Nuclear Regulatory Commission (NRC) requires | The 2013 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 2013 was 4080 pCi/liter. | ||
The NRC also mandates a reporting level for | 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 4010 pCi/liter. | ||
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 | No plant related isotopes were detected in quarterly precipitation samples. Silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background. | ||
The airborne exposure pathway includes radioactive | No plant related isotope was identified in any sample. Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels. No plant related isotope was detected in the indicator or control locations in shoreline soil. No plant related isotope was detected in fish samples from either Lake Anna or the control location, Lake Orange.Soil samples, which are collected every three years from twelve stations, were collected in 2013. Cs- 137 was identified in 10 of 11 indicator samples and the control sample. For the indicator stations the average was 208.9 pCi/Kg while for the control station the average was 329 pCi/Kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout.No other plant related isotope was identified in soil samples during 2013.5 The terrestrial exposure pathway includes milk and food/vegetation products. | ||
The 2013 airborne results were | No plant related radioisotope was detected in any milk samples. Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data. No plant related isotope was detected in any vegetation sample. Low levels of Cs- 137 have been detected intermittently in past years.The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years.During 2013, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2013 was 0.45 millirem. | ||
For reference, this dose may be compared to the 625 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%.These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive | |||
No other plant related isotopes | 'effluent control at North Anna Power Station.6 | ||
No plant related isotopes were detected in quarterly precipitation samples. | |||
Silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the | |||
No plant related isotope was identified in any sample. Shoreline soil, which may provide a direct exposure | |||
Levels during | |||
Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium | |||
The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid | |||
Natural sources in the environment provide approximately 82% | |||
'effluent control at North | |||
: 2. PROGRAM DESCRIPTION | : 2. PROGRAM DESCRIPTION | ||
===2.1 Introduction=== | ===2.1 Introduction=== | ||
This report documents the 2013 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).The North Anna Power Station of Virginia Electric and Power Company (Dominion) is located on Lake Anna in Mineral, | This report documents the 2013 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).The North Anna Power Station of Virginia Electric and Power Company (Dominion) is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia. | ||
The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. | 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 | 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. | ||
To ensure these criteria are met, the operating license | In-plant monitoring is used to ensure release limits are not exceeded. | ||
In-plant monitoring is used to ensure | As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in the North Anna Power Station Offsite Dose Calculation Manual (ODCM).North Anna Power Station is responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions is utilized for processing the TLDs. Teledyne Brown Engineering Environmental Services (TBE)is utilized for sample analyses. | ||
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 | |||
Global Dosimetry Solutions is utilized | |||
The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. | 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 | 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 | 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 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- | Occasionally samples of environmental media show the presence of man-made isotopes. | ||
As a method of referencing the measured radionuclide concentrations | 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 7 reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 1OCFR50, 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 2013 and satisfies the following objectives of the program:To provide measurements of radiation and of radioactive materials | This report documents the results of the Radiological Environmental Monitoring Program for 2013 and satisfies the following objectives of the program: To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public resulting from station operations. | ||
To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits...To identify changes in radioactivity in the environment. | To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits...To identify changes in radioactivity in the environment. | ||
> To verify that station operations have no detrimental effect on the | > 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 2013 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 2013.8 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Environmental Thermoluminescent Dosimetry (TLD)Location NAPS Sewage Treatment Plant Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700"Aspen Hills" Orange, VA Bearing Cooling Tower Sturgeon's Creek Marina Parking Lot "C" (on-site)Good Hope Church Parking Lot "B" Lake Anna Marina (Bogg's Dr)Weather Tower Fence Route 689 Near Training Facility"Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)"Aspen Hills" Elk Creek NAPS Access Rd.Station Distance Direction Degrees Frequency Remarks 01 .,0.20 .NE 420 Quarterly | ||
The North Anna Radiological Monitoring Locations maps | & Annually 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-l 1/43 ESE- 12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46.0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.36 SSW WSW WNW NNE N ESE SSE WNW WSW SSE NW N N NNE NNE NE NE ENE ENE E E ESE ESE SE SE SSE SSE S 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Quarterly | ||
The locations are color coded | & Annually Quarterly | ||
Good Hope | & Annually Quarterly | ||
"Aspen Hills"Elk | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly | ||
& | & Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control 9 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 S 1780 Ouarterlv Thermoluminescent Dosimetry (TLD)NAPS Access Rd.Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate -Laydown Area Lake Anna Campground | ||
& | #1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NAPS Sewage Treatment Plant Biology Lab Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA SSW- 19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 0.24 5.30 0.60 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.52 2.54 0.07 2.21 7.30 22.00 11.54.SSW SSW SW SW WSW WSW W W WNW WNW NW NW NNW NNW SSE NW WSW WSW 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control Control Airborne Particulate and Radioiodine 01 O0A 03 04 05 05A 06 07 0.20 0.64 7.10 5.10 4.20 2.04 4.70 7.30 NE SE WSW WNW NNE N ESE SSE 420 1380 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly 10 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Airborne Particulate and Radioiodine Location End of Route 685 Route 700"Aspen Hills" Orange, VA Station 21 22 23 24 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)Precipitation Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream) | ||
& | Biology Lab Biology Lab Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream) | ||
& | Waste Heat Treatment Facility (Second Cooling Lagoon)NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 3.37 SSE 1480 Monthly 09A 11 01A 01A 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE .1380 Monthly Control 08 3.37 09A 12.90 11 5.80"SSE.1480 Semi-Annually WNW 2950 Semi-Annually SE 1280 Semi-Annually Control Shoreline Soil Soil 3.37 SSE 1480 Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years 11 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)"Aspen Hills" Orange, VA 05A 06 07 21 22 23 24 2.04 4.70 7.30 1.00 1.00 0.93 22.00 N ESE SSE WNW WSW SSE NW 110 1150 1670 3010 2420 1580 3250 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Control Milk Fish Lakeside Dairy 12A 7.50 NW 3.37 SSE 16.5 NW 3100 Monthly 1480 Semi-Annually | ||
& | .3120 Semi-Annually Waste Heat Treatment Facility 08 (Second Cooling Lagoon)Lake Orange 25 Control Food Products (Vegetation) | ||
South Gate Switchyard Route | Stagecoach Road Route 614 Route 629/522 Aspen Hills"Historic Lane" 14B 15 16 23 26 1.22 1.37-12.60 0.93 1.15 NNE SE NW SSE S 400 1330 3140 1580 1720 Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Control 12 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)(84 TLDs)(12 TLDs)Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Weekly Gamma Dose Gamma Dose 1-131 Gross Beta 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month 0.07 0.01 Surface Water Quarterly (a)2 nd Quarter Composite Monthly Quarterly(a) 2 d Quarter Composite Gamma Isotopic Cs-134 0.05 Cs-137 0.06 Sr-89 (b)Sr-90 (b)1-131 1(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 Tritium (H-3) 2000 Sr-89 (b)Sr-90 (b)pCi/mi 3 pCi/mi 3 pCi/m 3 pCi/mi 3 pCi/L pCi/L pCi/L pCi/L River Water Monthly 1-131 1 (c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60*LLDs indicate those levels to which environmental samples are required to be analyzed. | ||
#1/#2 | 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. | ||
(Route 669 Bridge)North Anna River (downstream) | 13 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS River Water Ground Water (Well Water)Quarterly(a) 2 nd Quarter Composite Quarterly Quarterly(a) 2 nd Quarter Seni-Annually La- 140 Tritium (H-3)Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs- 134 Cs-137 Ba-140 La- 140 Tritium (H-3)Sr-89 Sr-90 Gamma Isotopic Cs- 134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95-13 134d Cs- 134 Cs-137 Ba- 140"'.La- 1 4 0 1d)15 2000 (b)(b)15 30 15 15 30 30 15 10(c)15 18 60 15 2000 (b)(b)pCi/L pCi/L pCi/L pCi/L pCi/L Aquatic Sediment ..150 180 (b)(b)pCi/kg (dry)pCi/kg (dry)Annually Precipitation Monthly Semi-Annual Composite | ||
Biology | " 4 pCi/L pCi/L 15 30 15 15 30 30 15 15 18 Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)Cs-134 150 Cs-137 180*LLDs indicate those levels to which environmental samples are required to be analyzed. | ||
(Route 669 Bridge)North Anna River (downstream) | 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. | ||
Waste Heat Treatment Facility(Second Cooling Lagoon)NAPS Sewage Treatment | 14 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY Annually Once per 3 years Soil Milk Monthly Monthly Quarterly ANALYSIS Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La- 140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs- 134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 LLD (b)(b)150 180 (b)(b)1 15 18 60 15 (b)(b)130 260 130 130 260 130.150:.REPORT UNITS pCi/kg (dry)pCi/kg (dry)pCi/kg (dry)pCi/L pCi/L Fish Semi-Annually Monthly, if available, or at harvest pCi/kg (wet)Food Products (Broadleaf Vegetation) pCi/kg (wet)60 80 60*LLDs indicate those levels to which environmental samples are required to be analyzed. | ||
"Aspen Hills"Orange, | 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. | ||
.3120 Semi-Annually Waste Heat Treatment Facility 08(Second Cooling Lagoon)Lake Orange | 15 Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation Environmental Station Identification 1 (a)1A 2 (a)3 (a)4 (a)5 (a)5A (a)6 (a)7 (a)8 9A 12 01,NE-5/37 OIA,SE-13/45 02,SSW-20/52 03,C-5/6 04 05 05A,N-2/34 06,ESE-12/44 07, C-1/2 08-Water, Fish, Sediment, Shoreline Soil 09A-Water sample, Sediment 11 -River Water, Sediment 12A-Milk 14B-Vegetation 15-Vegetation 16-Vegetation 21 ,WNW-27/59 22,WSW-24/56 23-SSE- 15/47,Vegetation 24,C-3/4 25-Fish 26-Vegetation 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE- 11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 12A 14B 15 16 21 (a)22 (a)23 (a)24 (a)(b)25 (c)26 25/57 16/48 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 W-25/57 SSE- 16/48 SE- 14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E- 10/42 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.(b) In Orange (c) In Lake Orange 16 ESE* Rxed E Awmuta Man~ritarimgsbgo | ||
Stagecoach | * ThD LoaAnSO Scale- 3/ inh | ||
Actual analysis of samples | * 3ft-Figure 1. North Anna Site Radiological Monitoring Locations 17 18 K !~~~ynwrrous LA V 10>1/4E COF North Anna Environmental Map S Fixed Environmental Sampling Location O TLD Sampling t Garden Residents.Meat Animals S SSE Original 0 iS by ADC of Aardfut., inc, 6440 General Green VW ianmddi VA 22312. USED YVTH PERIISSION No otr repoduclon nwj be made withWot the wfitten permisslon of ADC.19 North Anna Environmental Map Fixed Environmental Sampling Location TLD Sampling Garden Residents.Meat Animals I Ofginal 0Mi byAOC Inc. 8440 General Green Why, Al &Ium a, VA22312. USED WT TH PERMISSION. | ||
No ohreprodtion may be made wAiout the written permisseon arADC.C83233D 20 6 uNNW North Anna Environmental Map O Fixed Environmental Sampling Location O TLD Sampling , Garden Residents O Meat Animals OftraC 01991 byADC of/Amnddt. | |||
13 TABLE 2- | Inc. 6440 General GreenWy Nww.cidg VA 22312. USED TH PERMISSION. | ||
.. | No oWer reproduction may be made wNwflt me wrViten perrnsIon of ADC.COMO10 21 | ||
Actual analysis of samples | : 3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM.For radioanalytic analyses, the values listed in the columns indicated as"Mean/Range" include any results above the Minimum Detectable Concentration, MDC. Results are considered true positives when the measured value exceeds both the MDC and the 2(y error. For TLDs the mean and range include all values.A more detailed analysis of the data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries. | ||
22 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
14 TABLE 2- | |||
==SUMMARY== | |||
Actual analysis of samples | North Anna Nuclear Power Station, Louisa County, Virginia 2013 Docket No. 50-338/339 Page 1 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Hi 1 hest Mean Location routine Pathway LLD"o Mean Reported Sampled (Unit) Total (PCi/unit) | ||
Range Name Distance Mean Mean Measure-Typ No. Direction Range Range ments Direct Radiation (mR/std. Month)(Sector TLDs)Direct Radiation (mR/std. Month)(Pre-operational TLDs)Direct Radiation (mR/std. Month)(Emergency Sector TLDs)Direct Radiation (mR/std. month)(Environmental TLDs)Direct Radiation (mR/std. Month)(Annual TLDs)Airborne Particulates (IE-03 pCi/m 3)Air Iodine (pCi/m 3)Airborne Particulates (IE-03 pCi/m 3)Gamma Dose 256 2 4.6(256/256) | |||
15 Legend For The North Anna Power | (1.6-9.2)29/61 0.52 mi. 7.7(8/8)NW (5.9-9.2)3.9(16/16)* | ||
* ThD | (3.3-4.4)0 Gamma 32 Dose 2 2.5(16/16) | ||
* 3ft-Figure 1. North Anna | C-7/8 11.54 mi.(1.1-3.7) | ||
.Meat | WSW 3.8 (8/8) 3.6(16/16)* | ||
inc, 6440 General Green | (2.7-4.4)(3.3-4.4)0 Gamma Dose 40 2 5.4(40/40) | ||
.Meat | EPSP- 0.37 mi. 7.8(8/8)(3.5-9.9) 09/10 ENE (6.0-9.9)3.5(16/16)* | ||
USED WT TH PERMISSION. | (2.7-4.4)0 Gamma 48 2 3.8(44/44) 23 0.93 mi. 5.4(4/4)3.4(4/4)(2.9-3.9)0 Dose (1.9-6.3)SSE (4.8-6.3)Gamma Dose Gross Beta 12 2 3.4(11/11) | ||
No ohreprodtion may be made wAiout the written permisseon arADC. | (2.3-4.8)23 0.93 mi.SSE 4.8(1/1)(4.8)3.4(1/1)(3.4)0 676 0.01 15.4(620/624) | ||
Inc. 6440 General | (3.03-36.8) 05 0.2 mi. 17.7(48/52) 14.8(52/52) | ||
No oWer reproduction may be made wNwflt me wrViten perrnsIon of ADC. | |||
: 3. ANALYTICAL | |||
Rev. 1, November 1979. The LLD listed value is taken from the ODCM.For radioanalytic | |||
22 Table 3- | |||
Range Name Distance Mean Mean Measure-Typ No. Direction Range Range | |||
Month)(Sector TLDs)Direct Radiation (mR/std. | |||
Month)(Pre-operational TLDs)Direct Radiation (mR/std. | |||
Month)(Emergency | |||
month)(Environmental TLDs)Direct Radiation (mR/std. | |||
Month)(Annual TLDs) | |||
(1.6-9.2) 29/61 0.52 mi. 7.7(8/8)NW (5.9-9.2) 3.9(16/16)* | |||
(3.3-4.4) | |||
C-7/8 11. | |||
(2.7-4.4) | |||
(3.3-4.4) | |||
EPSP- 0.37 mi. 7.8(8/8)(3.5-9.9) 09/10 ENE (6.0-9.9) 3.5(16/16)* | |||
(2.7-4.4) | |||
SSE (4.8-6.3) | |||
(2.3-4.8) 23 0.93 mi. | |||
(3.03-36.8) | |||
NNE (7.84-37.8) | NNE (7.84-37.8) | ||
(5.90-35.7) | (5.90-35.7) 0 1-131 676 0.07 (0/624) N/A N/A.N/A N/A 0 Gamma 52 Be-7 52 126(48/48) 04 1.0 mi. 132.8(4/4) 117(4/4)(102-161)WNW (102-161) | ||
WNW (102-161) | (101-140)0 0 Cs-134 52 0.05 (0/48)N/A N/A N/A (0/4)(I) mR/std month for TLDs* C-3/4, -7/8 used as control locations 23 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
(101-140) | |||
- | ==SUMMARY== | ||
Mean Name Distance Mean Mean Measure-Typ No. Range Direction Range Range | North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 2 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) (pCi/unit) | ||
(dry)Triennial | Mean Name Distance Mean Mean Measure-Typ No. Range Direction Range Range ments Airborne Particulates (IE-03 pCi/m 3)Cs-137 52 0.06 Sr-89 13 Sr-90 13 (0/48)(0/12)(0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)(0/1)(0/1)0 0 0 Soil*(pCi/Kg) (dry)Triennial Gamma K-40 12 12 15255 (11/11)(6320-29000) | ||
N/ | N/A 23 N/A 29000(1/1) | ||
(29000)N/A N/A N/ | (29000)N/A N/A N/A Cs-134 12 150 Cs-137 12 180 208.9(10/11) | ||
(93.1-539) | (93.1-539) | ||
Ra-226 12 -2461 (10/11)(1570-3600) | Ra-226 12 -2461 (10/11)(1570-3600) | ||
| Line 194: | Line 155: | ||
(504-2270) | (504-2270) | ||
Th-232 12 -1191 (11/11)(530-2200) | Th-232 12 -1191 (11/11)(530-2200) | ||
Sr-89 12 -N/ | Sr-89 12 -N/A 02 5.30 mi.SSW 22 1.00 mi WSW 06 4.70 mi ESE 06 4.70 mi ESE N/A N/A N/A N/A 539(1/1)(539)3600(1/I)3600 2270(1/1)(2270)2200(I/1)(2200)N/A N/A 4660 (1/1)(4660)N/A 329(1/1)(329)3390 (1/1)3390 1710(1/1)(1710)1340(1/1)(1340)N/A 0 0 0 0 0 0 0 0 0 0 Sr-90 12 Monthly N/A Precipitation (pCi/liter) | ||
(2270)2200(I/1) | Gross Beta 12 4 6.42(9/12) | ||
(2200)N/ | |||
(1710)1340(1/1) | |||
(1340)N/ | |||
(2.27-19.6) 01A 0.64 mi. 6.42(9/12) | (2.27-19.6) 01A 0.64 mi. 6.42(9/12) | ||
SE (2.27-19.6) | SE (2.27-19.6) | ||
N/ | N/A N/A N/A H-3 Semiannual Gamma 2 2000 (0/2)N/A N/A N/A 2 Be-7 2 -66(1/2)(66)Mn-54 2 15 (0/2)Fe-59 2 30 (0/2)Co-58 2 15 (0/2)01A 0.64 mi.SE N/A N/A N/A N/A N/A N/A 66 (1/2)(66)N/A N/A N/A N/A N/A 0 0 0 0 N/A N/A* Soil Samples required triennially. | ||
Samples obtained in 2013.24 Table 3- | Samples obtained in 2013.24 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
Mean Name Distance Mean Mean Measure-Type al Range Direction Range Range | |||
Co- | ==SUMMARY== | ||
- | North Anna Nuclear Power Station, Louisa County, Virginia 2013 Docket No. 50-338/339 Page 3 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Tot (pCi/unit) | ||
Mean Name Distance Mean Mean Measure-(Unit) Type No. _ -Range I Direction Range Range | Mean Name Distance Mean Mean Measure-Type al Range Direction Range Range ments No. I I I I___Precipitation (pCi/liter) | ||
Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs- 134 Cs-137 Ba- 140 La- 140 Th-228 2 2 15 30 30 15 10 15 18 (0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 0 0 0 25 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
==SUMMARY== | |||
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 4 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit) | |||
Mean Name Distance Mean Mean Measure-(Unit) Type No. _ -Range I Direction Range Range ments Gamma 12 Milk (pCi/liter) | |||
K-40 12 -1350(12/12) | K-40 12 -1350(12/12) | ||
(.1220-1710) 1-131 12 1 (0/12)Cs-137 12 18 (0/12)Ba-140 12 60 (0/12)La-140 12 15 (0/12)12A 7.50 mi. | (.1220-1710) 1-131 12 1 (0/12)Cs-137 12 18 (0/12)Ba-140 12 60 (0/12)La-140 12 15 (0/12)12A 7.50 mi.NW 12A N/A.N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1350(12/12) | ||
(1220-1710) | (1220-1710) | ||
N/ | N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 Sr-89 (Quarterly) | ||
Sr-90(Quarterly) | Sr-90 (Quarterly) 4 4 (0/4), (0/4)26 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
- | |||
Mean Name Distance Mean Mean Measure-Type No. I, Range I Direction Range Range | ==SUMMARY== | ||
(wet) | North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 5 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit) | ||
Mean Name Distance Mean Mean Measure-Type No. I, Range I Direction Range Range ments Food Vegetation (pCi/kg) (wet)Gamma Be-7 35 35 K-40 35 1500(28/28) | |||
(368-3160) 5755(28/28) | (368-3160) 5755(28/28) | ||
(2680-10400) | (2680-10400) | ||
(0/28)(0/28)1- | (0/28)(0/28)1-131 Cs- 134 35 35 60 60 26 1.15ri S 14B 1.22mi NNE N/A N/A N/A N/A 23 0.93 N/A N/A 1740(7/7)(1210-2930) 6110(7/7)(4910-8300) | ||
(1210-2930) 6110(7/7) | N/A N/A 1130(7/7)(681-1670) 6110(7/7)(3970-10400) | ||
(4910-8300) | (0/7)(0/7)0 0 0 0 0 Cs-137 35 80 (0/28)Ground Well Water (pCi/liter) | ||
N/ | Tritium 4 2000 Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 4 4 4 4 4 4 4 4 4 15 30 15 15 30 30 15 10 (0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/28)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/7)0 N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 0 27 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
(681-1670) 6110(7/7) | |||
(3970-10400) | ==SUMMARY== | ||
(0/7)(0/7) | North Anam Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 6 of 9 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled Total (PCi/un Mean Name Distance Mean Mean Measure-(Unit) Type No. it) Range Direction Range Range ments Ground Well Water (pCi/liter) | ||
Tritium 4 | Cs-134 Cs-137 Ba- 140 La- 140 Sr-89 Sr-90 Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 15 (0/4)18 (0/4)60 (0/4)15 (0/4)(0/1)(0/1)2000 4010(4/4)(3750-4330) | ||
- | N/A N/A N/A N/A N/A N/A II N/A N/A N/A N/A N/A N/A 5.80 mi.SE N/A N/A N/A N/A N/A N/A 4010(4/4)(3750-4330) | ||
Cs- | River Water (pCi/liter) 15 30 15 15 30 (0/12)(0/12)(0/12)(0/12)(0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Zr-95 12 30 (0/12) N/A N/A Nb-95 1-131 12 12 15 1 (0/12)(0/12)N/A N/A N/A N/A Cs-134 12 15 (0/12) N/A Cs-137 12 18 (0/12) N/A N/A N/A*Results of surface water taken at Location 09A used as control value for river water 28 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
(3750-4330) | |||
N/ | ==SUMMARY== | ||
(3750-4330) | North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 7 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit) | ||
River Water(pCi/liter) | Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments River Water (pCi/liter) | ||
- | Ba-140 12 60 (0/12) N/A La-140 12 15 (0/12) N/A Sr-89 I -(0/1) N/A Sr-90 I -(0/1) N/A Tritium 8 2000 4080(4/4) 08 (3850-4370) | ||
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range | N/A Surface Water (pCi/L)Ganmima Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 24 24 15 24 30 24 15 24 15 24 30 24 30 24 30 24 1 24 15 24 18 24 60 N/A N/A N/A 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A N/A 4080(4/4)(3850-4370) | ||
Ba-140 12 60 (0/12) N/ | (0/12)*(0/12)*(0/1)*(0/1)*(0/4)0 0 0 0 0 (0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)0 0 0 0 0 0 0 0 0 0 0 0 La- 140 24 15 N/A N/A*Results of surface water taken at Location 09A used as control value for river water 29 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
N/ | |||
(3850-4370) | ==SUMMARY== | ||
(0/12)*(0/12)*(0/1)*(0/1)*(0/4) | North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 8 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit) | ||
- | Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Surface Water (pCi/liter) | ||
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range | Sediment Silt (pCi/kg)Sr-89 Sr-90 1 1 (0/1)(0/1)N/A N/A N/A N/A N/A N/A (0/1)(0/1)Gamma 6 K-40 6-10990(4/4) 11 5.80 mi. 15900(2/2) | ||
Sediment Silt(pCi/kg)Sr- | |||
(2340-16000) | (2340-16000) | ||
SE (15800-16000)50 (0/4) N/A N/A N/ | SE (15800-16000)50 (0/4) N/A N/A N/A Cs-134 6 1 Cs-137 6 1 80 12250(2/2) | ||
(12000-12500) | (12000-12500) | ||
(0/2)(176)112(1/2)(112)2220(2/2) | (0/2)(176)112(1/2)(112)2220(2/2)(2090-2350) | ||
(2090-2350) | (0/4)N/A N/A.N/A Ra-226 6 -2132.5(4/4) | ||
(0/4)N/A N/A.N/ | |||
(1820-2540) | (1820-2540) | ||
Th-228 | Th-228 6 Th-232 6 (Annually) | ||
Sr- | Sr-89 Sr-90 3 3 1214(4/4)- | ||
(548-1760) 1014.5 (4/4)(506-1310) | (548-1760) 1014.5 (4/4)(506-1310) | ||
(0/2)-(0/2)2650(2/2) | (0/2)-(0/2)2650(2/2)(1360-3940) 11 5.80 mi. 2345(2/2)SE (2150-2540) 1 5.80 mi. 1565(2/2)SE (1370-1760) 11 5.80 mi. 1265(2/2)SE (1220-1310) 561(2/2)(548-574)618.5(2/2) | ||
(1360-3940) 11 5.80 mi. 2345(2/2) | (506-731)(0/1)(0/1)0 0 0 0 0 0 0 0 0 0 0 0 0 0 N/A N/A N/A N/A N/A N/A Shoreline Soil (pCi/kg) (dry)Gamma 2 K-40 2 08 3.37 mi. 2650(2/2)SSE (1360-3940) | ||
SE (2150-2540) 1 5.80 mi. 1565(2/2) | Cs- 134 2 150 (0/2)N/A NA N/A NA (0/2)(0/2)N/A N/A N/A N/A Cs-137 2 180 (0/2)Ra-226 2 1520(1/2)(1520)08 3.37 mi. 1520(1/2)SSE (1520)30 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | ||
SE (1370-1760) 11 5.80 mi. 1265(2/2) | |||
SE (1220-1310) 561(2/2)(548-574) 618.5(2/2) | ==SUMMARY== | ||
(506-731) | North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 9 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (PCi/unit) | ||
(0/1)(0/1) | Mean Name Distance Mean Mean Measure-(Unit) Type No. Range I Direction Range Range ments Shoreline Soil (pCi/kg) (dry)Th-228 2 Th-232 2 819(2/2)(809-829)725.5 (2/2)(705-746)(0/1)(0/1)08 3.37 mi.SSE 08 3.37 mi.SSE N/A N/A N/A N/A 819(2/2)(809-829)725.5(2/2) | ||
(dry)Gamma | (705-746)N/A N/A N/A N/A N/A N/A 0 0 0 0 (Annually) | ||
SSE (1360-3940) | Sr-89 Sr-90 1 Fish (pCi/kg) (.wet)Gamma 8 K-40 8 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 8 8 8 8 8 8 8 130 260 130 130 260 130 150 2450(4/4)(2240-2650) | ||
Cs- 134 2 150 (0/2)N/A | (0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)8 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 2450(4/4)(2240-2650) | ||
(1520)08 3.37 mi. 1520(1/2) | N/A N/A N/A N/A N/A N/A N/A 2447.5(4/4) | ||
SSE (1520)30 Table 3- | |||
- | |||
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range I Direction Range Range | |||
(dry)Th-228 | |||
(0/1)(0/1)08 3.37 mi. | |||
(705-746) | |||
N/ | |||
Sr- | |||
(.wet)Gamma | |||
(2240-2650) | |||
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)8 3.37 mi. | |||
(2240-2650) | |||
N/ | |||
(1370-2850) | (1370-2850) | ||
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4) | (0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0 0 0 0 0 0 0 31 3.2 Analytical Results of 2013 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The data reported in the following tables are strictly counting statistics. | ||
The data reported in | The reported error is two times the standard deviation (2G) of the net activity. | ||
The reported error is two times the | 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 2a error.Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For clarity of this report only detectable results are presented. | ||
Unless otherwise noted, the overall error (counting, | TBE's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the North Anna ODCM.Data are given according to sample type as indicated below.1. Gamma Exposure Rate 2. Air Particulates, Gross Beta Radioactivity | ||
TBE's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical | : 3. Air Particulates, Weekly 1- 131 4. Air Particulates, Quantitative Gamma Spectra 5. Air Particulate Strontium 6. Soil 7. Precipitation | ||
: 8. Cow Milk 9. Food Products and Vegetation | |||
(November 1979, Revision | : 10. Well Water 11. River Water 12. Surface Water 13. Bottom Sediment/Silt | ||
: 14. Shoreline Soil 15. Fish Analytical results are handled as recommended by HASL ("Reporting ofAnalytical Resultsfr'om HASL." letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).32 TABLE 3-2 DIRECT RADIATION MEASURMENTS | |||
: 3. Air Particulates, Weekly 1- | -SECTOR QUARTERLY TLD RESL mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quartei Station N-1 N-33 N-2 N-34 NNE-3 NNE-35 NNE-4 NNE 36 NE-5 NE-37 NE-6 NE-38 ENE-7 ENE-39 ENE-8 ENE-40'E-9 -E-41 E-10 E-42 ESE-1 1 ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 5.3 6.2 3.8 3.3 7.7 7.1 4.6 4.5 5.2 5.5 3.3 3.5 6.0 6.6*2.8 2.7 6.1 6.1 5.5 5.7 4.3 4.6 5.8 5.4 5.8 4.6 8.0 7.1 6.3 5.1 4.3 3.1 4.4 4.7 2.5 2.5 5.6 5.9 3.6 3.9 4.4 4.5 2.6 2.7 4.7 4.5 2.2 2.4 3.9 4.1 3.9 3.9 4.6 3.7 4.9 4.1 3.8 4.4 5.1 6.5 5.0 4.1 2.1 2.5 5.5 5.4 2.8 3.6 6.9 6.4 4.6 5.0 3.6 4.1 3.3 3.6 4.3 6.0 2.3 2.4 5.4 5.4 4.7 4.8 4.5 4.8 5.0 4.5 5.0 3.7 5.9 6.1 5.2 5.4 3.0 2.3 5.7 6.2 4.4 3.3 7.4 7.3 4.2 4.8 4.2 6.0 4.3 4.2 5.4 5.2 3.5 3.4 4.9 5.9 5.1 5.5 5.3 5.0 5.0 5.1 5.3 5.8 7.6 7.6 5.0 5.7 3.6 3.3 JLTS Quarterly* | ||
Average+/- 2 s.d.5.4 + 1- 1.3 3.3 +/- 1.3 6.8 + 1- 1.5 4.4 +/- 0.9 4.7 +/- 1.6 3.4 + 1- i.2 5.3 + 1- i.6 2.7 + 1- 1.0 5.2 +/- 1.7 4.9 + 1- 1.4 4.6 +/- 1.0 5.0 +/- 1.0 4.8 +/- 1.6 6.7 +1- 2.0 5.2 +/- 1.3 3.0 + 1- 1.5 Page 1 of 4*Average of collocated TLDs.33 TABLE 3-2 DIRECT RADIATION MEASURMENTS | |||
: 8. Cow | -SECTOR QUARTERLY TLD RESULTS mRJStd. Month (30.4 days) +/- 2 Sigma Page 2 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Station S-17 S-49 S-18 S-50 SSW-19 SSW-51 SSW-20 SSW-52 SW-21 SW-53 SW-22 SW-54 WSW-23 WSW-55 WSW-24 WSW-56 W-25 W-57 W-26.W-58 WNW-27 WNW-59 WNW-28 WNW-60 NW-29 NW-61 NW-30 NW-62 NNW-31 NNW-63 NNW-32 NNW-64 Quarterly* | ||
: 10. Well | Average+/- 2 s.d.5.7 4.9 3.1 2.8 7.4 7.0 2.8 2.5 4.6 5.3 5.7 4.2 5.3 6.8 5.5 5.5 8.6 8.5 3.7 3.7 4.1 3.8 3.3 3.3 7.4 8.6 2.5 2.3 4.5 4.1 3.5 3.7 3.9 5.3 1.7 2.1 5.7 5.3 2.0 2.1 4.1 3.7 3.6 3.6 4.8 4.5 3.9 3.6 7.6 5.8 2.8 2.5 3.0 2.8 2.7 2.6 7.7 5.9 1.7 1.9 2.8 3.1 3.3 3.1 4.8 4.6 2.6 2.6 5.3 6.9 2.8 3.1 4.8 4.8 4.7 4.8 5.5 5.4 4.4 4.3 5.8 6.9 3.1 3.6 2.8 3.3 2.3 2.6 7.5 6.3 2.0 1.6 2.8 4.0 3.8 4.3 6.2 5.0 2.9 3.4 5.8 6.2 3.1 3.5 5.4 4.7 5.3 4.5 6.2 5.6 4.9 4.7 8.0 8.3 3.8 3.0 4.2 3.1 3.6 3.3 8.6 9.2 3.0 2.9 4.7 4.2 5.0 3.9 5.1 +/- 1.4 2.7 +/- 1.1 6.2 +/- 1.6 2.7 +/- 1.0 4.7 +/- 1.1 4.6 +/- 1.5 5.5 +/- 1.5 4.6 +/- 1.4 7.4 +/- 2.3 3.3 +/- 1.0 3.4 +/- 1.1 3.0 +/- 0.9 7.7 +/- 2.3 2.2 +/- 1.1 3.8 +/- 1.5 3.8 +/- 1.2 4.6 +/- 1.5 Mean*Average of collocated TLDs.34 TABLE 3-2 DIRECT RADIATION MEASURMENTS | ||
: 14. Shoreline | -SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Qua Page 3 of 4 rterly*Station C-1 C-2 C-3"*C-4"*C-5 C-6 C-7"*C-8"*4.1 4.0 3.4 3.3 2.4 2.9 3.9 4.0 2.7 2.7 2.8 2.7 2.1 2.0 4.4 3.3 2.8 2.9 2.9 3.1 2.4 1.9 3.8 3.3 3.4 3.5 4.2 3.8 3.4 2.9 4.3 3.5 Average+/- 2 s.d.3.3 +/- 1.1 3.3 +/- 1.0 2.5 +/- 1.0 3.8 +/- 0.8 2.9 +/-3.5 +/-1.3 1.1 EPSA-01**EPSA-02*** | ||
-SECTOR QUARTERLY TLD | |||
Average+/- 2 s.d.5.4 + 1- 1. | |||
-SECTOR QUARTERLY TLD | |||
Average+/- 2 s.d.5. | |||
-SECTOR QUARTERLY TLD | |||
EPSA-02*** | |||
EPSF-03*** | EPSF-03*** | ||
EPSF-04*** | EPSF-04*** | ||
| Line 300: | Line 242: | ||
EPSR-06t** | EPSR-06t** | ||
EPSJ-07***' | EPSJ-07***' | ||
EPSJ-08*A." EPSP-09*** | |||
EPSP-1 0***5.3 | |||
Additional TLDs serve as controls. | Additional TLDs serve as controls. | ||
Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout | 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. | Control and indicator averages indicate a steady relationship. | ||
Two dosimeters made of CaF and | Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location. | ||
These | These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001. The 60 dose with the replacement TLDs is lower than that of the previously used TLDs.This will continue to be monitored. | ||
9. | 9.0 8.0 7.0 6.0 5.0 4.0 Environ-nental TLDs-0u- Sector TLDs 3.0 -Avg. Pre-op 2.0 1.0___ _0.0 I%. 0 0O r-J 1 O 0 0ý ~ 0 0 S=C = C C C C a C C C 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 | The average level of the 32 locations (two badges at each location) was 4.6 mR/standard month with a range of 1.6 to 9.2 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61. | ||
This | This value was 7.7 mR/standard month. This location is on site on the north gate of the construction side laydown area. Quarterly and annual TLDs are also located at twelve environmental air sampling stations. | ||
For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3. | For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3.8 mR/standard month with a range of 1.9 to 6.3 mR/standard month. The average annual reading for these locations was 3.4 mR/standard month with a range from 2.3 to 4.8 mR/standard month. The control location showed a quarterly average of 3.4 mR/standard month with a range of 2.9 to 3.9 mR/standard month. Its annual reading was 3.6 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.4 mR/standard month with EPSP-9/ 10 having the highest quarterly average of 7.8 mR/standard month. Eight other TLDs, designated C-1 thru C-8, which 61 were pre-operational controls, were collected quarterly from four locations. | ||
Stations C-3/4 and C-7/8 are designated controls. | Stations C-3/4 and C-7/8 are designated controls. | ||
These had a quarterly average of 3.6, while Station C-1/2 and C-5/6 had a quarterly average of 2. | These had a quarterly average of 3.6, while Station C-1/2 and C-5/6 had a quarterly average of 2.5 mR/standard month with a range of 1.1 to 3.7 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged. | ||
The drop indicated in 2009 may be a | The drop indicated in 2009 may be a function of a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this is in fact the case. Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable. | ||
Gross beta activity found during the pre-operational and early operating | 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 | In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.0.12 -0.1 E 0.08 -: 0.06 -0 0.04 -0.02 -Control G'ta-24 Indicator Average Pre-op -Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 62 2.50E-02 4L 2.00E-02 1.50E-02 1.OOE-02 5.00E-03 O.OOE+O0 .....r m 0 0-# or 0- z -I Sta 24 -Ul-Indicators Figure 4-3 2013 Gross Beta in Air Particulates (pCi/rm 3)4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine. | ||
.....r m 0 0-# or 0- z -I Sta 24 -Ul-Indicators Figure 4-3 2013 Gross Beta in Air Particulates (pCi/ | Once a week the samples are collected and analyzed. | ||
Once a week | The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl and the effect of the Fukushima Daiichi event.4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy. | ||
The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the | The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. | ||
The results are listed in Table 3-5. The results indicate the presence | Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected. | ||
Examination of pre-operational data indicates comparable measurements | The results of these analyses indicate the lack of station effects on the environment. | ||
The results of these analyses indicate the lack | |||
63 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. | 63 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 | There has been no detection of these fission products at any of the indicator or control stations in recent years.4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2013. Cs-137 was identified in 10 of 11 indicator samples and the control sample. For the indicator stations the average was 208.9 pCi/Kg while for the control station the average was 329 pCi/Kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout. No other plant related isotopes were identified in Soil samples during 2013.4.7 Precipitation A sample of rain water was collected monthly at on-site station 01A and analyzed for gross beta activity and H-3. The results are presented in Table 3-7. Twelve precipitation samples were obtained in 2013. 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. | |||
No other plant related isotopes were identified in | |||
No plant related isotopes were | |||
Naturally occurring gamma emitting radioisotopes were detected. | Naturally occurring gamma emitting radioisotopes were detected. | ||
No positive H-3 result | No positive H-3 result was reported. | ||
During the pre-operational period gross beta activity in rain | 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 2013 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter. | ||
4.8 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. | |||
4.8 Cow | This pathway also shows 64 measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any plant effect.Analysis results for cow milk are contained in Table 3-8. No sample indicated positive results. Gamma spectroscopy did not detect the presence of any isotopes related to the operation of North Anna. In years past, Cs-137 has been detected sporadically. | ||
This pathway also | These occurrences were attributed to residual global fallout from past atmospheric weapons testing. Naturally occurring K-40 was detected in all samples.Once each quarter a sample from the collection station is analyzed for strontium-89 and strontium-90. | ||
Therefore, this | |||
Gamma spectroscopy did not detect the presence of | |||
These occurrences were attributed to | |||
Naturally occurring K-40 was detected in all samples.Once each quarter a sample from the collection station is analyzed | |||
Neither Sr-89 nor Sr-90 was detected. | Neither Sr-89 nor Sr-90 was detected. | ||
Sr- | Sr-90 has been observed in the past. Pre-operational levels of 2.2 to 5.4 pCi/liter were measured for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents. | ||
It should be noted that strontium-90 is not | Its detection is the product of nuclear weapons testing fallout. This conclusion can be made based upon the fact that Sr-89 and Sr-90 have not been detected in gaseous effluents released from the station in many years, and the trend of consistent declining levels since the pre-operational period.4.9 Food Products and Vegetation Food/vegetation samples were collected from five locations and analyzed by gamma spectroscopy. | ||
Its detection is the product of nuclear | The results of the analyses are presented in Table 3-9.Low levels of Cs- 137, attributable to fallout, have been seen periodically in vegetation samples. As expected, naturally occurring potassium-40 and cosmogenic beryllium-7 were detected in most samples, and thorium-228 and other natural products, including Bi-214, were detected in some samples. No plant related isotopes were identified in any Vegetation sample during 2013.4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory. | ||
This conclusion can be made based upon the fact that Sr- | 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 the analyses are presented in Table 3-9.Low levels of Cs- 137, attributable to fallout, have been seen periodically | The results of these analyses are presented in Table 3-10. No plant related isotopes were detected. | ||
As expected, naturally occurring potassium-40 | No gamma emitting isotopes were detected during the pre-operational period.65 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 were composited quarterly and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90 in accordance with program requirements. | |||
These samples were analyzed for gamma radiation and for tritium. | 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. | ||
The | Tritium was measured in all four samples with an average annual concentration of 4010 pCi/liter and a range of 3750 to 4330 pCi/liter. | ||
The results of these analyses are presented in Table 3-10. | These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were collected during the pre-operational period.River Water 4500 4500 4000 4000 3500 4 3500-J 3000 3000 4&2500 2500 --$-tritium 2000 2000 --I-Req LLD 1500 1500 1000 1000 Figure 4-4Tritium in River water 66 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. | ||
No gamma emitting isotopes were | A quarterly composite from each station was prepared and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90. | ||
There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.No non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the samples. No tritium was detected at the control location. | |||
The monthly samples were composited quarterly | The average level of tritium activity at the indicator station was 4080 pCi/liter with a range of 3850 to 4370 pCi/liter. | ||
Additionally, the second quarter samples are analyzed | Levels of tritium have increased since 1978 when the average level was below 300 pCi/liter. | ||
There has been no detection of these fission products at any of the indicator | Levels.measured at the indicator location (Station 8) are comparable to those measured since 1986, see Figure 4-5. During the pre-operational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter. | ||
There was no measured activity of strontium-89 or strontium-90. | 67 10000 1000_j 100 a.-Required LLD Average Pre-op Tritium 10 rt Co C fl 40 Co M 4 M Ch 0) -a) D C3 U -0 a LL Co 0 w 0 Z Figure 4.5Tritium in Surface Water 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectroscopy. | ||
Tritium was measured in all four samples with an average | The October samples were analyzed for strontium-89 and strontium-90. | ||
The results are presented in Table 3-13.No plant related isotopes were detected in 2013. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the 68 result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented. | |||
A quarterly composite from | During the pre-operational period sediment samples were also analyzed by gamma spectroscopy. | ||
Additionally, the | |||
There | |||
No tritium was detected at the | |||
The average level of tritium activity at the indicator station was | |||
Levels of tritium | |||
Levels.measured at the indicator location (Station | |||
67 | |||
Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels | |||
The October | |||
The results are presented | |||
The detection of Cs-137 is | |||
During the pre-operational period sediment samples were also analyzed by | |||
Figure 4-6 shows the historical trend of Cs- 137 in sediments. | Figure 4-6 shows the historical trend of Cs- 137 in sediments. | ||
Neither Strontium-89 nor Strontium-90 was detected in any samples of | Neither Strontium-89 nor Strontium-90 was detected in any samples of aquatic sediment/silt in 2013. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests. A number of naturally occurring radioisotopes were detected in these samples at background levels.1600 -Station-1400 8 1200.91000 9 800.600 Control 400 -Sta-09A 200 9 20--Station-o~ Cc W o M -' Z LCi)W L -) Z M M O0 5C 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 | The October sample was analyzed for strontium-89 and strontium-90. | ||
The results | 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 | No plant related isotopes were detected in any indicator or control samples analyzed. | ||
Strontium-90 is often detected in | Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is 69 attributed to accumulation of residual global fallout from past atmospheric weapons testing.4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2013 and analyzed by gamma spectroscopy. | ||
Each sample set consisted of a sample of game species and | Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately. | ||
The results are presented in Table 3-15. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected. | |||
Cs- 137 was measured in pre-operational environmental fish samples.70 | |||
No plant related isotopes were detected. | : 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2013 -North Anna Location 14B,15,16,23, 26 14B, 15,16,23, 26 14B,15,16,23, 26 STA 5 STA 5 STA 2 14B,15,16,23, 26 14B,15,16,23, 26 Description Vegetation Vegetation Vegetation AP/Char Annual/Qua rterly TLD AP/Char Vegetation Vegetation Date of Sampling 01/08/13 02/13/13 03/12/13 03/12/13 03/12/13 04/09/13 11/13/13 12/12/13 Reason(s) for Loss/Exception Seasonal unavailability Seasonal unavailability Seasonal unavailability Sampler not ruiming. Power pole damaged by snow storm.TLDs missing due to power pole damage from snow storm.Sampler not running/ replaced. | ||
Cs- 137 was measured | Minimum volume not met.Seasonal unavailability. | ||
: 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2013 -North | Seasonal unavailability 71 REFERENCES References Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications. | ||
Power pole damaged | Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010,"Radiological Environmental Monitoring Program".Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities". | ||
replaced. | United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of E;valuating Compliance with 1 OCFR50, Appendix I", October, 1977.United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975.USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 2 7 th 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 1984.72 APPENDICES 73 APPENDIX A: LAND USE CENSUS Year 2013 74 LAND USE CENSUS North Anna Power Station Louisa County, Virginia January I to December 31, 2013 Direction Distance (miles)Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden (> Meat Milch Milch Boundary 50rrm) Animal Cow Goat N 0.9 1.3 1.78 2.9 NONE NONE NNE 0.9 0.9 1.2 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.37 2.4 2.7 NONE NONE E 0.8 1.3 2.0 3.5 NONE NONE ESE 0.9 1.7 1.7 NONE NONE NONE SE 0.9 1.4 1.5 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE S 0.9 1.0 .1.0 2.0 NONE NONE SSW 1 1.3 1.33 2.0 NONE NONE SW 1.1 1.65 1.65 NONE NONE NONE WSW 1.1 1.6 2.4 1.6 NONE NONE W 1.1 1.5 1.9 4.4 NONE NONE WNW 1 1.1 2.6 5.0 NONE NONE NW 1 1.0 2.0 NONE NONE NONE NNW 0.9 1.0 1.2 2.3 NONE NONE 75 2012 to 2013 Land Use Census Changes 2012 2013 Nearest Direction Distance Distance Resident NONE Site Boundary NONE Garden N 1.72 1.78 SSW 2.34 1.33 Meat Animal NONE Milch Cow NONE Milch Goat NONE 76 APPENDIX B: | |||
Seasonal unavailability 71 REFERENCES References | |||
==SUMMARY== | |||
OF INTERLABORATORY COMPARISONS YEAR 2013 INTRODUCTION This appendix covers the Intercomparison Program of the Teledyne Brown Engineering | |||
Title 10 Code of Federal Regulation, Part 50 (10CFR50), | -Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). TBE uses QA/QC samples provided by Eckeri & Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) and Environmental Resource Associates, (ERA) to monitor the quality of analytical processing associated with the REMP. The suite of samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides. | ||
"Domestic Licensing of Production | This includes: 77 E & Z Analytics: | ||
United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation | Milk for gamma emitters, Iodine-131, Fe-55, Sr-89 and Sr-90 analyses once per quarter.Air particulate for gamma emitters once per quarter Charcoal for 1-131 once per quarter ERA Water for tritium, gamma, Iodine- 131, Sr-89, Sr-90, gross alpha and beta during the 2nd and 4th quarters.Water for natural uranium during the 2nd quarter DOE Water and soil for gamma, Iodine-131, U-233/234, U-238, transuranics, tritium, Fe-55, Ni-63, Sr-90 and Tc-99 analyses during the 1st quarter.Water for gross alpha and beta during the 1 st and 3rd quarters.Air particulates and vegetation for gamma, Iodine-131, U-233/234, U-238, transuranics, Sr-90 analyses during the .1st and 3rd quarters.Air filter for gross alpha and beta analyses during the 1st and 3rd quarters.78 RESULTS Interlaboratory comparison program results are evaluated using TBE's criterion. | ||
December 1975.USNRC Branch Technical | Any sample analysis result that does not pass the criteria is investigated by TBE. Nonconformance Reports were generated and corrective actions taken as a result of this program.For the TBE laboratory, 178 out of 185 analyses performed met the specified acceptance criteria. | ||
Seven analyses (Sr-89 and Sr-90 in milk, Co-57, Zn-65 and Sr-90 in soil, Cs-134 in air particulate and Sr-90 in vegetation | |||
Rev. 1, November 1979.NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," | [two low warning in a row]) did not meet the specified acceptance criteria or internal QA requirements for the following reason: 1. Teledyne Brown Engineering's Analytics September 2013 Sr-89 in milk result of 63.9 pCi/L was lower than the known value of 96.0 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15 2. Teledyne Brown Engineering's Analytics September 2013 Sr-90 in milk result of 8.88 pCi/L was lower than the known value of 13.2 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15 3. & 4. Teledyne Brown Engineering's MAPEP September 2013 Co-57 and Zn-65 in soil were evaluated as failing the false positive test. While MAPEP evaluated the results as failures, the gamma software listed the results as non identified 79 nuclides. | ||
The two nuclides would never have been reported as detected nuclides to a client. MAPEP does not allow laboratories to put in qualifiers for the submitted data nor"less than" results. MAPEP evaluates results based on the relationship between the activity and the uncertainty. | |||
Definition and Elaboration of a | MAPEP spiked the soil sample with an extremely large concentration of Eu- 152, which was identified by the gamma software as an interfering nuclide, resulting in forced activity results that were evaluated by MAPEP as detected Co-57 and Zn-65. No client samples were affected by these failures.NCR 13-14 5. Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in soil result of 664 Bq/kg was higher than the known value of 460 Bq/kg, exceeding the upper control limit of 598 Bq/kg. An incorrect Sr-90 result was entered into the MAPEP database. | ||
September 1984.72 APPENDICES 73 APPENDIX A: LAND USE | The correct Sr-90 activity of 322 Bq/kg would have been evaluated as acceptable with warning. No client samples were affected by this failure. NCR 13-14 6. Teledyne Brown Engineering's MAPEP September 2013 Cs-134 in air particulate activity of -0.570 Bq/sample was evaluated as a failed false positive test, based on MAPEP's evaluation of the result as a significant negative value at 3 standard deviations. | ||
-Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). TBE | A negative number would never have been reported as a detected nuclide to a client, therefore no client samples were affected by this failure. NCR 13-14 7. Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in vegetation result was investigated due to two low warnings in a row. It appears the September sample was double 80 spiked with carrier, resulting in a low activity. | ||
This includes: | With a recovery of around 50% lower, the Sr-90 result would have fallen within the acceptance range. No client samples were affected by this issue. NCR 13-14 A summary of TBE's results is provided in the tables on the following pages for the required sample matrix types and isotopic distribution. | ||
77 E & Z Analytics: | Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result; analytical date; the known values supplied by the providers; pass or fail criteria.81 4 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2013 E10477 E10478 E10480 Milk Milk AP Sr-89 pCi/L 120 Sr-90 pCi/L 9.21 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 87.1 186 463 201 262 200 215 266 311 384 95.3 264 123 142 112 115 139 163 212 99.7 11.0 100 187 472 214 266 208 208 252 301 400 95.6 241 109 136 106 106 129 153 204 92.6 1890 95.0 17.0 95.5 90.4 250 125 151 94.0 1.20 0.84 0.87 0.99 0.98 0.94 0.98 0.96 1.03 1.06 1.03 0.96 1.00 1.10 1.13 1.04 1.06 1.08 1.08 1.07 1.04 0.97 0.97 1.16 0.93 0.97 0.92 1.01 0.94 0.95 0.93 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A El 0479 E10481 June 2013 E10564 E10545 Charcoal 1-131 pCi 90.1 Water Milk Milk Fe-55 pCi/L 1840 Sr-89 pCi/L 110 Sr-90 pCi/L 15.8 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 92.6 83.1 253 118 143 87.1 82 Mn-54 pCi/L 171 172 0.99 A Fe-59 pCi/L 125 120 1.04 A Zn-65 pCi/L 220 217 1.01 A Co-60 pCi/L 169 175 0.97 A E10547 AP Ce-141 pCi 56.8 56.7 1.00 A Cr-51 pCi 168 157 1.07 A Cs-134 pCi 85.2 78.4 1.09 A Cs-137 pCi 101 94.6 1.07 A Co-58 pCi 62.7 58.9 1.06 A Mn-54 pCi 125 108 1.16 A Fe-59 pCi 85.7 75.0 1.14 A Zn-65 pCi 169 136 1.24 W Co-60 pCi 116 110 1.05 A E10546 Charcoal 1-131 pCi 86.5 89.7 0.96 A 83 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)Value Month/Year Number Matrix Nuclide Units Value (a) (b) TBE/Analytics Evaluation (d)June 2013 September 2013 E10549 E10646 E10647 Water Fe-55 pCi/L 1610 Milk Milk Sr-89 pCi/L 63.9 Sr-90 pCi/L 8.88 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 93.9 272 150 125 105 138 125 264 187 208 143 106 97.0 116 98.6 219 166 E10672 E10648 E10673 E10774 E10775 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi 1610 96.0 13.2 98.3 277 172 131 108 139 130 266 196 223 139 105 86.5 112 105 214 158 71.7 1690 93.8 12.9 96.1 110 297 142 0.67 0.67 0.96 0.98 0.87 0.95 0.97 0.99 0.96 0.99 0.95 N (1)N (1)A NA (2)A A A A A A A A 1.00 A Charcoal 1-131 pCi 76.3 Water Fe-55 pCi/L 1790 0.93 1.03 1.01 1.12 1.04 0.94 1.02 1.05 1.06 1.06 1.04 1.03 0.93 0.91 1.00 0.91 NA (2)A A A A A A A A December 2013 Milk Milk Sr-89 pCi/L 97.3 Sr-90 pCi/L 13.3 A A A A A A A A 1-131 Ce-141 Cr-51 Cs-134 pCi/L pCi/L pCi/L pCi/L 89.7 99.8 297 129 84 I Cs-137 pCi/L 126 126 1.00 A Co-58 pCi/L 116 112 1.04 A Mn-54 pCi/L 167 168 0.99 A Fe-59 pCi/L 117 110 1.06 A Zn-65 pCi/L 757 741 1.02 A Co-60 pCi/L 141 147 0.96 A E10777 AP Ce-141 pCi 85.1 88.0 0.97 A Cr-51 pCi 278 238 1.17 A Cs-134 pCi 123 114 1.08 A Cs-137 pCi 102 101 1.01 A Co-58 pCi 84.4 89.9 0.94 A Mn-54 pCi 132 135 0.98 A Fe-59 pCi 101 88.3 1.14 A Zn-65 pCi 506 595 0.85 A Co-60 pCi 118 118 1.00 A ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)December 2013 E10776 Charcoal 1-131 pCi 84.7 80.5 1.05 A E10778 Water Fe-55 pCi/L 2010 1910 1.05 A (1) Milk, Sr-89/90 -The failure was due to analyst error. No client samples were affected by this failure. NCR 13-15 (2) The sample was not spiked with Ce- 141 (a) Teledyne Brown Engineering reported result.(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) Ratio of Teledyne Brown Engineering to Analytics results.(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20. | ||
Milk for gamma emitters, Iodine-131, Fe-55, Sr-89 and Sr-90 analyses once | |||
Water for natural uranium during the 2nd | |||
Air particulates and vegetation for gamma, Iodine-131, U-233/234, U-238,transuranics, Sr-90 analyses during the .1st and 3rd quarters. | |||
Air filter for gross alpha and beta analyses during the 1st and 3rd quarters. | |||
78 | |||
Any sample analysis result that does not pass the criteria | |||
Seven analyses (Sr-89 and Sr-90 | |||
[two low warning in a row]) did not meet | |||
NCR 13- | |||
NCR 13- | |||
The two nuclides would never have been | |||
MAPEP evaluates results based on | |||
MAPEP spiked the soil sample with an extremely | |||
NCR 13- | |||
The correct Sr-90 activity of 322 Bq/ | |||
NCR 13- | |||
A negative number would never | |||
NCR 13- | |||
With | |||
Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result; analytical date; the | |||
81 | |||
-The failure was due to analyst error. No client samples were affected by this failure. | |||
NCR 13-15(2) The sample was not spiked with Ce- 141(a) Teledyne Brown Engineering reported result.(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/ | |||
(c) Ratio of Teledyne Brown Engineering to Analytics results.(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20. | |||
W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30. | W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30. | ||
N = Not Acceptable, | N = Not Acceptable, reported result falls outside the ratio limits of < 0.70 and > 1.30.85 I DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Value Month/Year Number Media Nuclide Units Value (a) (b) Range Evaluation (c)March 2013 13-MaW28 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 21.0 0.0446 28.3 18.2 506 25.7 2.09 10.5 29.2 24.4 17.1-31.7 (1)30.9 21.6 -40.2 19.56 13.69 -25.43 507 355 -659 27.4 19.2 -35.6 (1)10.5 7.4 -13.7 30.4 21.3 -39.5 A A A A A A A A A A A 13-GrW28 Water 13-MaS28 'Soil 13-RdF28 AP Gr-A Gr-B 2.74 15.6 2.31 13.0 0.69 -3.93 6.5- 19.5 Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 859 633 0.256 738 0.671 714 442 1057 1.73 2.73 2.38 0.0302 4.36 1.43 3.14 0.767 0.871-0.197 7.39 9.87 887 621-1153 587 411-763 (1)691 625.3 628 995 1.78 2.60 2.36 4.26 1.49 3.13 484 -898 (1)437.7 -812.9 440 -816 697 -1294 1.25-2.31 1.82-3.38 1.65- 3.07 (1)2.98 -5.54 1.04- 1.94 2.19-4.07 A A A A A A W A A A A A A A A A A A A A 13-GrF28 AP Gr-A Bq/sample Gr-B Bq/sample 1.20 0.36-2.04 0.85 0.43-1.28 (1)6.87 4.81 -8.93 8.68 6.08-11.28 13-RdV28 Vegetation Cs-134 Cs-1 37 Co-57 Bq/sample Bq/sample Bq/sample 86 1 September 2013 13-MaW29 Water Co-60 Mn-54 Sr-90 Zn-65 Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 6.08-0.0104 1.28 6.84 29.1 34.5 0.0358 24.6 2.45 0.0337 0.193 9.12 38.1 5.85 4.10 -7.61 (1)1.64 1.15-2.13 6.25 4.38 -8.13 30.0 21.0 -39.0 31.6 22.1-41.1 (1)23.58 16.51 -30.65 (1)(1)(1)7.22 5.05 -9.39 34.6 24.2 -45.0 A A W A A A A A A A A W A 13-GrW29 Water Gr-A Gr-B Bq/L Bq/L 1.13 0.701 0.210-1.192 7.61 5.94 2.97- 8.91 A A 87 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Value Month/Year Number Media Nuclide Units Value (a) (b) Range Evaluation (c)September 2013 13-MaS29 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 13-RdF29 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1150 1100 670 502 758 796 664 210-0.570 2.85 3.30 2.41 3.65 1.40 2.90 0.872 1.57 5.29 7.48 0.0129 0.0523 8.78 1.63 3.18 1172 820-1524 977 684-1270 (1)451 316-586 674 472- 876 633 443-823 460 322-598 (1)13-GrF29 AP Gr-A Bq/sample Gr-B Bq/sample 2.7 3.4 2.3 3.5 1.81 2.7 0.9 1.63 5.20 6.60 7.88 2.32 2.63 (1)1.9- 3.5 2.4 -4.4 1.6-3.0 2.5 -4.6 1.27-2.35 1.9-3.5 0.3-1.5 0.82 -2.45 3.64 -6.76 4.62 -8.58 (1)(1)5.52- 10.24 1.62- 3.02 1.84- 3.42 A A N (2)A A W N (2)N (2)N (2)A A A A W A A A A A A A A W (2)W 13-RdV29 Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample (1) False positive test.(2) Soil, Co-57 & Zn-65 identified by gamma software as not detected, MAPEP evaluated as failing the false positive test. A large concentration of Eu-152 was spiked into the sample, causing interference in the analysis. | ||
' | Gamma software irecognized the interference and identified them as not detected. | ||
Gamma software irecognized the interference and identified them | |||
MAPEP does not allow clients to enter non-detect designation. | MAPEP does not allow clients to enter non-detect designation. | ||
Soil, Sr-90 -incorrect results were submitted to MAPEP. Should have been 332 bq/kg, which would have passed.AP, Cs-134 -MAPEP evaluated the -0.570 as a failed false positive test. No client samples were affected by these failures. | Soil, Sr-90 -incorrect results were submitted to MAPEP. Should have been 332 bq/kg, which would have passed.AP, Cs-134 -MAPEP evaluated the -0.570 as a failed false positive test. No client samples were affected by these failures. | ||
NCR 13- | NCR 13-04 Vegetation, Sr-90 -it appears that the carrier was double spiked into the sample, resulting in the low activity for this sample. NCR 13-04 (a) Teledyne Brown Engineering reported result.(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) DOEIMAPEP evaluation: | ||
(c) DOEIMAPEP evaluation: | |||
A=acceptable, W=acceptable with warning, N=not acceptable. | A=acceptable, W=acceptable with warning, N=not acceptable. | ||
88 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK | 88 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)May 2013 RAD-93 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 48.3 19.3 81.9 40.9 44.0 61.9 202 34.2 18.0 23.8 60.4 3970 41.3 23.9 82.1 42.8 41.7 65.9 189 40.8 21.6 23.8 61.2 31.6-48.4 17.2 -28.0 69.0 -90.3 34.2 -47.1 37.0 -48.8 59.3 -75.0 170 -222 21.1 -51.9 13.0-29.7 19.7-28.3 49.8 -67.9 A A A A A A A A A A A A 4050 3450-4460 MRAD-18 Filter Gr-A pCi/filter Lost during processing November 2013 RAD-95 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 25.5 14.3 57.2 83.3 201 104 361 29.5 30.1 23.1 5.53 17650 21.9 18.1 54.2 86.7 206 102 333 42.8 32.2 23.6 6.24 17700 14.4-28.2 12.8-21.5 44.7-59.9 71.1-95.4 185-228 91.8-114 300- 389 22.2- 54.3 20.8- 39.9 19.6-28.0 47.0- 7.44 15500- 19500 A A A A A A A A A A A A A MRAD-19 Filter Gr-A pCi/filter 33.0 83.0 27.8 -129 (a) Teledyne Brown Engineering reported result.(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) ERA evaluation: | ||
(c) ERA evaluation: | |||
A=acceptable. | A=acceptable. | ||
Reported result falls within the Warning Limits. NA=not acceptable. | Reported result falls within the Warning Limits. NA=not acceptable. | ||
Reported | Reported result falls outside of the Control Limits. CE= Check for Error. Reported result falls within the Control Limits and outside the Warning Limit.89}} | ||
Revision as of 17:02, 9 July 2018
| ML14118A037 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/22/2014 |
| From: | Bischof G T Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| 14-129 | |
| Download: ML14118A037 (91) | |
Text
VIRGINmI ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 2014 United States Nuclear Regulatory Commission Serial No.14-129 Attention:
Document Control Desk NAPS/JHL Washington, D. C. 20555 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with North Anna Units 1 and 2 Technical Specification 5.6.2 and the North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c, enclosed is the 2013 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 Page Kemp at (540) 894-2295.Very truly yours, Gerald T. Bischof Site Vice President Enclosure Commitments made in this letter: None Serial No.14-129 NAPS Annual Radiological Environmental Operating Report cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station Dominion North Anna Power Station Radiological Environmental Monitoring Program Januaty 1, 2013 to December 31, 2013 Prepared by Dominion, North Anna Power Station Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2013 to December 31, 2013 Prepared by: Reviewed by: Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station C 'eorge R. Simmons Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert B. Evans'dr.Manager Radiological Protection and Chemistry Dominion North Anna Power Station Approved by: 2 Table of Contents 1. EX ECU TIV E SU M M A RY .......................................................................................................
4 2. PRO G RA M D ESCRIPTION
......................................................................................................
7 2.1 Introduction
.............................................................................................................................
7 2.2 Sam pling and A nalysis Program ........................................................................................
8 3. A N A LY TICA L RESU LTS ........................................................................................................
22 3.1 Sum m ary of Results ........................................................................................................
22 3.2 A nalytical Results of 2013 REM P Sam ples ...................................................................
32 4. D ISCU SSION O F RESU LTS ...................................................................................................
60 4.1 G am m a Exposure Rate ...................................................................................................
60 4.2 A irborne G ross Beta .........................................................................................................
62 4.3 A irborne Radioiodine
......................................................................................................
63 4.4 A ir Particulate G am m a .................................................................................................
n ...... 63 4.5 A ir Particulate Strontium
.................................................................................................
64 4 .6 S o il ........................................................................................................................................
6 4 4.7 Precipitation
..........................................................................................................................
64 4.8 Cow M ilk ..............................................................................................................................
64 4.9 Food Products and V egetation
........................................................................................
65 4.10 W ell W ater ..........................................................................................................................
65 4.11 River W ater .........................................................................................................................
66 4.12 Surface W ater ..............................................................................................................
........ 67 4.13 Bottom Sedim ent ................................................................................................................
68 4.14 Shoreline Soil ......................................................................................................................
69 4.15 Fish .......................................................................
70 5. PRO G RA M EX CEPTION S .....................................................................................................
71 RE FERE N CES ....................................................................................................................................
72 A PPEN D ICES .....................................................................................................................................
73 A PPEN D IX A : LA N D U SE CEN SU S ......................................................................................
74 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS
..........................
77 3
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2013 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). It is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.2 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2. Radioactivity levels from January 1 through December 31, 2013, in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized.
The REMP is designed to confirm that radiological effluent releases are As Low As Reasonably Achievable (ALARA), no undue environmental effects occur and the health and safety of the public are protected.
The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.Radiation and radioactivity in the environment is monitored within a 25-mile radius of the station. North Anna Power Station 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 or any other nuclear facility.
These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained.
These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.
Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a"pre-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.
Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and Teledyne Brown Engineering Environmental Services provided radioanalytical services.
Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy.
Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods.4 Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as possible.
The NRC also mandates a reporting level for certain radionuclides.
Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, water, aquatic, terrestrial, and direct radiation exposure.
The airborne exposure pathway includes radioactive airborne iodine and particulates, and precipitation.
The 2013 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 2013 was 4080 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 4010 pCi/liter.
No plant related isotopes were detected in quarterly precipitation samples. Silt samples indicated the presence of naturally occurring potassium-40 and thorium and uranium decay daughters at levels consistent with the natural background.
No plant related isotope was identified in any sample. Shoreline soil, which may provide a direct exposure pathway, indicated the presence of potassium-40 and thorium and uranium decay daughters also at levels consistent with natural levels. No plant related isotope was detected in the indicator or control locations in shoreline soil. No plant related isotope was detected in fish samples from either Lake Anna or the control location, Lake Orange.Soil samples, which are collected every three years from twelve stations, were collected in 2013. Cs- 137 was identified in 10 of 11 indicator samples and the control sample. For the indicator stations the average was 208.9 pCi/Kg while for the control station the average was 329 pCi/Kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout.No other plant related isotope was identified in soil samples during 2013.5 The terrestrial exposure pathway includes milk and food/vegetation products.
No plant related radioisotope was detected in any milk samples. Naturally occurring beryllium-7, potassium-40 and radionuclides associated with the uranium and thorium series were detected at environmental levels consistent with historical data. No plant related isotope was detected in any vegetation sample. Low levels of Cs- 137 have been detected intermittently in past years.The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially constant over the years.During 2013, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2013 was 0.45 millirem.
For reference, this dose may be compared to the 625 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%.These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive
'effluent control at North Anna Power Station.6
- 2. PROGRAM DESCRIPTION
2.1 Introduction
This report documents the 2013 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).The North Anna Power Station of Virginia Electric and Power Company (Dominion) is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia.
The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation.
Each unit has a gross electrical output of 1029 megawatts electric (MWe). Unit 1 achieved commercial operation on June 6, 1978 and Unit 2 on December 14, 1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications, which address the release of radioactive effluents.
In-plant monitoring is used to ensure release limits are not exceeded.
As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in the North Anna Power Station Offsite Dose Calculation Manual (ODCM).North Anna Power Station is responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions 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 7 reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 1OCFR50, 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 2013 and satisfies the following objectives of the program: To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed member of the public resulting from station operations.
To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits...To identify changes in radioactivity in the environment.
> To verify that station operations have no detrimental effect on the health and safety of the public.2.2 Sampling and Analysis Program Table 2-1 summarizes the 2013 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 2013.8 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Environmental Thermoluminescent Dosimetry (TLD)Location NAPS Sewage Treatment Plant Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700"Aspen Hills" Orange, VA Bearing Cooling Tower Sturgeon's Creek Marina Parking Lot "C" (on-site)Good Hope Church Parking Lot "B" Lake Anna Marina (Bogg's Dr)Weather Tower Fence Route 689 Near Training Facility"Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)"Aspen Hills" Elk Creek NAPS Access Rd.Station Distance Direction Degrees Frequency Remarks 01 .,0.20 .NE 420 Quarterly
& Annually 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-l 1/43 ESE- 12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46.0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88 0.93 2.33 0.36 SSW WSW WNW NNE N ESE SSE WNW WSW SSE NW N N NNE NNE NE NE ENE ENE E E ESE ESE SE SE SSE SSE S 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly
& Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control 9 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Elk Creek Church S-18/50 1.55 S 1780 Ouarterlv Thermoluminescent Dosimetry (TLD)NAPS Access Rd.Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate -Laydown Area Lake Anna Campground
- 1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Louisa, VA NAPS Sewage Treatment Plant Biology Lab Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA SSW- 19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 0.24 5.30 0.60 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.52 2.54 0.07 2.21 7.30 22.00 11.54.SSW SSW SW SW WSW WSW W W WNW WNW NW NW NNW NNW SSE NW WSW WSW 1970 2050 2180 2320 2370 2420 2790 2740 3010 3030 3210 3190 3490 3440 1670 3250 2430 2570 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Control Control Airborne Particulate and Radioiodine 01 O0A 03 04 05 05A 06 07 0.20 0.64 7.10 5.10 4.20 2.04 4.70 7.30 NE SE WSW WNW NNE N ESE SSE 420 1380 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly 10 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Airborne Particulate and Radioiodine Location End of Route 685 Route 700"Aspen Hills" Orange, VA Station 21 22 23 24 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)Precipitation Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream)
Biology Lab Biology Lab Waste Heat Treatment Facility (Second Cooling Lagoon)Lake Anna (upstream)(Route 669 Bridge)North Anna River (downstream)
Waste Heat Treatment Facility (Second Cooling Lagoon)NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 3.37 SSE 1480 Monthly 09A 11 01A 01A 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly 0.64 SE .1380 Monthly Control 08 3.37 09A 12.90 11 5.80"SSE.1480 Semi-Annually WNW 2950 Semi-Annually SE 1280 Semi-Annually Control Shoreline Soil Soil 3.37 SSE 1480 Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years 11 TABLE 2-1 North Anna Power Station -2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)"Aspen Hills" Orange, VA 05A 06 07 21 22 23 24 2.04 4.70 7.30 1.00 1.00 0.93 22.00 N ESE SSE WNW WSW SSE NW 110 1150 1670 3010 2420 1580 3250 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Control Milk Fish Lakeside Dairy 12A 7.50 NW 3.37 SSE 16.5 NW 3100 Monthly 1480 Semi-Annually
.3120 Semi-Annually Waste Heat Treatment Facility 08 (Second Cooling Lagoon)Lake Orange 25 Control Food Products (Vegetation)
Stagecoach Road Route 614 Route 629/522 Aspen Hills"Historic Lane" 14B 15 16 23 26 1.22 1.37-12.60 0.93 1.15 NNE SE NW SSE S 400 1330 3140 1580 1720 Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Monthly if available or at harvest Control 12 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)(84 TLDs)(12 TLDs)Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Weekly Gamma Dose Gamma Dose 1-131 Gross Beta 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month 0.07 0.01 Surface Water Quarterly (a)2 nd Quarter Composite Monthly Quarterly(a) 2 d Quarter Composite Gamma Isotopic Cs-134 0.05 Cs-137 0.06 Sr-89 (b)Sr-90 (b)1-131 1(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 Tritium (H-3) 2000 Sr-89 (b)Sr-90 (b)pCi/mi 3 pCi/mi 3 pCi/m 3 pCi/mi 3 pCi/L pCi/L pCi/L pCi/L River Water Monthly 1-131 1 (c) pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60*LLDs indicate those levels to which environmental samples are required to be analyzed.
Actual analysis of samples may be lower than the listed values.(a) Quarterly composite of each location's 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 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS River Water Ground Water (Well Water)Quarterly(a) 2 nd Quarter Composite Quarterly Quarterly(a) 2 nd Quarter Seni-Annually La- 140 Tritium (H-3)Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs- 134 Cs-137 Ba-140 La- 140 Tritium (H-3)Sr-89 Sr-90 Gamma Isotopic Cs- 134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95-13 134d Cs- 134 Cs-137 Ba- 140"'.La- 1 4 0 1d)15 2000 (b)(b)15 30 15 15 30 30 15 10(c)15 18 60 15 2000 (b)(b)pCi/L pCi/L pCi/L pCi/L pCi/L Aquatic Sediment ..150 180 (b)(b)pCi/kg (dry)pCi/kg (dry)Annually Precipitation Monthly Semi-Annual Composite
" 4 pCi/L pCi/L 15 30 15 15 30 30 15 15 18 Shoreline Soil Semi-Annually Gamma Isotopic pCi/kg (dry)Cs-134 150 Cs-137 180*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 TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY Annually Once per 3 years Soil Milk Monthly Monthly Quarterly ANALYSIS Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La- 140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs- 134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 LLD (b)(b)150 180 (b)(b)1 15 18 60 15 (b)(b)130 260 130 130 260 130.150:.REPORT UNITS pCi/kg (dry)pCi/kg (dry)pCi/kg (dry)pCi/L pCi/L Fish Semi-Annually Monthly, if available, or at harvest pCi/kg (wet)Food Products (Broadleaf Vegetation) pCi/kg (wet)60 80 60*LLDs indicate those levels to which environmental samples are required to be analyzed.
Actual analysis of samples may be lower than the 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.
15 Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation Environmental Station Identification 1 (a)1A 2 (a)3 (a)4 (a)5 (a)5A (a)6 (a)7 (a)8 9A 12 01,NE-5/37 OIA,SE-13/45 02,SSW-20/52 03,C-5/6 04 05 05A,N-2/34 06,ESE-12/44 07, C-1/2 08-Water, Fish, Sediment, Shoreline Soil 09A-Water sample, Sediment 11 -River Water, Sediment 12A-Milk 14B-Vegetation 15-Vegetation 16-Vegetation 21 ,WNW-27/59 22,WSW-24/56 23-SSE- 15/47,Vegetation 24,C-3/4 25-Fish 26-Vegetation 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE- 11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 12A 14B 15 16 21 (a)22 (a)23 (a)24 (a)(b)25 (c)26 25/57 16/48 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 W-25/57 SSE- 16/48 SE- 14/46 SW-22/54 W-26/58 WNW-28/60 NNW-32/64 ENE-8/40 NNE-4/36 E- 10/42 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.(b) In Orange (c) In Lake Orange 16 ESE* Rxed E Awmuta Man~ritarimgsbgo
- ThD LoaAnSO Scale- 3/ inh
- 3ft-Figure 1. North Anna Site Radiological Monitoring Locations 17 18 K !~~~ynwrrous LA V 10>1/4E COF North Anna Environmental Map S Fixed Environmental Sampling Location O TLD Sampling t Garden Residents.Meat Animals S SSE Original 0 iS by ADC of Aardfut., inc, 6440 General Green VW ianmddi VA 22312. USED YVTH PERIISSION No otr repoduclon nwj be made withWot the wfitten permisslon of ADC.19 North Anna Environmental Map Fixed Environmental Sampling Location TLD Sampling Garden Residents.Meat Animals I Ofginal 0Mi byAOC Inc. 8440 General Green Why, Al &Ium a, VA22312. USED WT TH PERMISSION.
No ohreprodtion may be made wAiout the written permisseon arADC.C83233D 20 6 uNNW North Anna Environmental Map O Fixed Environmental Sampling Location O TLD Sampling , Garden Residents O Meat Animals OftraC 01991 byADC of/Amnddt.
Inc. 6440 General GreenWy Nww.cidg VA 22312. USED TH PERMISSION.
No oWer reproduction may be made wNwflt me wrViten perrnsIon of ADC.COMO10 21
- 3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the North Anna Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. The LLD listed value is taken from the ODCM.For radioanalytic analyses, the values listed in the columns indicated as"Mean/Range" include any results above the Minimum Detectable Concentration, MDC. Results are considered true positives when the measured value exceeds both the MDC and the 2(y error. For TLDs the mean and range include all values.A more detailed analysis of the data is given in Section 4 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries.
22 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia 2013 Docket No. 50-338/339 Page 1 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Hi 1 hest Mean Location routine Pathway LLD"o Mean Reported Sampled (Unit) Total (PCi/unit)
Range Name Distance Mean Mean Measure-Typ No. Direction Range Range ments Direct Radiation (mR/std. Month)(Sector TLDs)Direct Radiation (mR/std. Month)(Pre-operational TLDs)Direct Radiation (mR/std. Month)(Emergency Sector TLDs)Direct Radiation (mR/std. month)(Environmental TLDs)Direct Radiation (mR/std. Month)(Annual TLDs)Airborne Particulates (IE-03 pCi/m 3)Air Iodine (pCi/m 3)Airborne Particulates (IE-03 pCi/m 3)Gamma Dose 256 2 4.6(256/256)
(1.6-9.2)29/61 0.52 mi. 7.7(8/8)NW (5.9-9.2)3.9(16/16)*
(3.3-4.4)0 Gamma 32 Dose 2 2.5(16/16)
C-7/8 11.54 mi.(1.1-3.7)
WSW 3.8 (8/8) 3.6(16/16)*
(2.7-4.4)(3.3-4.4)0 Gamma Dose 40 2 5.4(40/40)
EPSP- 0.37 mi. 7.8(8/8)(3.5-9.9) 09/10 ENE (6.0-9.9)3.5(16/16)*
(2.7-4.4)0 Gamma 48 2 3.8(44/44) 23 0.93 mi. 5.4(4/4)3.4(4/4)(2.9-3.9)0 Dose (1.9-6.3)SSE (4.8-6.3)Gamma Dose Gross Beta 12 2 3.4(11/11)
(2.3-4.8)23 0.93 mi.SSE 4.8(1/1)(4.8)3.4(1/1)(3.4)0 676 0.01 15.4(620/624)
(3.03-36.8) 05 0.2 mi. 17.7(48/52) 14.8(52/52)
NNE (7.84-37.8)
(5.90-35.7) 0 1-131 676 0.07 (0/624) N/A N/A.N/A N/A 0 Gamma 52 Be-7 52 126(48/48) 04 1.0 mi. 132.8(4/4) 117(4/4)(102-161)WNW (102-161)
(101-140)0 0 Cs-134 52 0.05 (0/48)N/A N/A N/A (0/4)(I) mR/std month for TLDs* C-3/4, -7/8 used as control locations 23 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 2 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) (pCi/unit)
Mean Name Distance Mean Mean Measure-Typ No. Range Direction Range Range ments Airborne Particulates (IE-03 pCi/m 3)Cs-137 52 0.06 Sr-89 13 Sr-90 13 (0/48)(0/12)(0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)(0/1)(0/1)0 0 0 Soil*(pCi/Kg) (dry)Triennial Gamma K-40 12 12 15255 (11/11)(6320-29000)
N/A 23 N/A 29000(1/1)
(29000)N/A N/A N/A Cs-134 12 150 Cs-137 12 180 208.9(10/11)
(93.1-539)
Ra-226 12 -2461 (10/11)(1570-3600)
Th-228 12 -1314(11/11)
(504-2270)
Th-232 12 -1191 (11/11)(530-2200)
Sr-89 12 -N/A 02 5.30 mi.SSW 22 1.00 mi WSW 06 4.70 mi ESE 06 4.70 mi ESE N/A N/A N/A N/A 539(1/1)(539)3600(1/I)3600 2270(1/1)(2270)2200(I/1)(2200)N/A N/A 4660 (1/1)(4660)N/A 329(1/1)(329)3390 (1/1)3390 1710(1/1)(1710)1340(1/1)(1340)N/A 0 0 0 0 0 0 0 0 0 0 Sr-90 12 Monthly N/A Precipitation (pCi/liter)
Gross Beta 12 4 6.42(9/12)
(2.27-19.6) 01A 0.64 mi. 6.42(9/12)
SE (2.27-19.6)
N/A N/A N/A H-3 Semiannual Gamma 2 2000 (0/2)N/A N/A N/A 2 Be-7 2 -66(1/2)(66)Mn-54 2 15 (0/2)Fe-59 2 30 (0/2)Co-58 2 15 (0/2)01A 0.64 mi.SE N/A N/A N/A N/A N/A N/A 66 (1/2)(66)N/A N/A N/A N/A N/A 0 0 0 0 N/A N/A* Soil Samples required triennially.
Samples obtained in 2013.24 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia 2013 Docket No. 50-338/339 Page 3 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Tot (pCi/unit)
Mean Name Distance Mean Mean Measure-Type al Range Direction Range Range ments No. I I I I___Precipitation (pCi/liter)
Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs- 134 Cs-137 Ba- 140 La- 140 Th-228 2 2 15 30 30 15 10 15 18 (0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)(0/2)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 0 0 0 25 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 4 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) Type No. _ -Range I Direction Range Range ments Gamma 12 Milk (pCi/liter)
K-40 12 -1350(12/12)
(.1220-1710) 1-131 12 1 (0/12)Cs-137 12 18 (0/12)Ba-140 12 60 (0/12)La-140 12 15 (0/12)12A 7.50 mi.NW 12A N/A.N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1350(12/12)
(1220-1710)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 Sr-89 (Quarterly)
Sr-90 (Quarterly) 4 4 (0/4), (0/4)26 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 5 of 9 All Indicator Indicator Location Control Non-Medium or Anal sis Locations with Highest Mean Location routine Pathway LLD Reported Sampled (Unit) Total (pCi/unit)
Mean Name Distance Mean Mean Measure-Type No. I, Range I Direction Range Range ments Food Vegetation (pCi/kg) (wet)Gamma Be-7 35 35 K-40 35 1500(28/28)
(368-3160) 5755(28/28)
(2680-10400)
(0/28)(0/28)1-131 Cs- 134 35 35 60 60 26 1.15ri S 14B 1.22mi NNE N/A N/A N/A N/A 23 0.93 N/A N/A 1740(7/7)(1210-2930) 6110(7/7)(4910-8300)
N/A N/A 1130(7/7)(681-1670) 6110(7/7)(3970-10400)
(0/7)(0/7)0 0 0 0 0 Cs-137 35 80 (0/28)Ground Well Water (pCi/liter)
Tritium 4 2000 Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 4 4 4 4 4 4 4 4 4 15 30 15 15 30 30 15 10 (0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/28)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/7)0 N/A N/A N/A N/A N/A N/A N/A N/A 0 0 0 0 0 0 0 0 27 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anam Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 6 of 9 All Indicator Location Control Non-Medium or Analysis Indicator with Highest Mean Location routine Locations Pathway LLD Reported Sampled Total (PCi/un Mean Name Distance Mean Mean Measure-(Unit) Type No. it) Range Direction Range Range ments Ground Well Water (pCi/liter)
Cs-134 Cs-137 Ba- 140 La- 140 Sr-89 Sr-90 Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 15 (0/4)18 (0/4)60 (0/4)15 (0/4)(0/1)(0/1)2000 4010(4/4)(3750-4330)
N/A N/A N/A N/A N/A N/A II N/A N/A N/A N/A N/A N/A 5.80 mi.SE N/A N/A N/A N/A N/A N/A 4010(4/4)(3750-4330)
River Water (pCi/liter) 15 30 15 15 30 (0/12)(0/12)(0/12)(0/12)(0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/4)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*(0/12)*0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Zr-95 12 30 (0/12) N/A N/A Nb-95 1-131 12 12 15 1 (0/12)(0/12)N/A N/A N/A N/A Cs-134 12 15 (0/12) N/A Cs-137 12 18 (0/12) N/A N/A N/A*Results of surface water taken at Location 09A used as control value for river water 28 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 7 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments River Water (pCi/liter)
Ba-140 12 60 (0/12) N/A La-140 12 15 (0/12) N/A Sr-89 I -(0/1) N/A Sr-90 I -(0/1) N/A Tritium 8 2000 4080(4/4) 08 (3850-4370)
N/A Surface Water (pCi/L)Ganmima Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 24 24 15 24 30 24 15 24 15 24 30 24 30 24 30 24 1 24 15 24 18 24 60 N/A N/A N/A 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A N/A 4080(4/4)(3850-4370)
(0/12)*(0/12)*(0/1)*(0/1)*(0/4)0 0 0 0 0 (0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)(0/12)0 0 0 0 0 0 0 0 0 0 0 0 La- 140 24 15 N/A N/A*Results of surface water taken at Location 09A used as control value for river water 29 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 8 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Surface Water (pCi/liter)
Sediment Silt (pCi/kg)Sr-89 Sr-90 1 1 (0/1)(0/1)N/A N/A N/A N/A N/A N/A (0/1)(0/1)Gamma 6 K-40 6-10990(4/4) 11 5.80 mi. 15900(2/2)
(2340-16000)
SE (15800-16000)50 (0/4) N/A N/A N/A Cs-134 6 1 Cs-137 6 1 80 12250(2/2)
(12000-12500)
(0/2)(176)112(1/2)(112)2220(2/2)(2090-2350)
(0/4)N/A N/A.N/A Ra-226 6 -2132.5(4/4)
(1820-2540)
Sr-89 Sr-90 3 3 1214(4/4)-
(548-1760) 1014.5 (4/4)(506-1310)
(0/2)-(0/2)2650(2/2)(1360-3940) 11 5.80 mi. 2345(2/2)SE (2150-2540) 1 5.80 mi. 1565(2/2)SE (1370-1760) 11 5.80 mi. 1265(2/2)SE (1220-1310) 561(2/2)(548-574)618.5(2/2)
(506-731)(0/1)(0/1)0 0 0 0 0 0 0 0 0 0 0 0 0 0 N/A N/A N/A N/A N/A N/A Shoreline Soil (pCi/kg) (dry)Gamma 2 K-40 2 08 3.37 mi. 2650(2/2)SSE (1360-3940)
Cs- 134 2 150 (0/2)N/A NA N/A NA (0/2)(0/2)N/A N/A N/A N/A Cs-137 2 180 (0/2)Ra-226 2 1520(1/2)(1520)08 3.37 mi. 1520(1/2)SSE (1520)30 Table 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia -2013 Docket No. 50-338/339 Page 9 of 9 All Indicator Indicator Location Control Non-Medium or Analysis Locations with Highest Mean Location routine Pathway LLD Reported Sampled Total (PCi/unit)
Mean Name Distance Mean Mean Measure-(Unit) Type No. Range I Direction Range Range ments Shoreline Soil (pCi/kg) (dry)Th-228 2 Th-232 2 819(2/2)(809-829)725.5 (2/2)(705-746)(0/1)(0/1)08 3.37 mi.SSE 08 3.37 mi.SSE N/A N/A N/A N/A 819(2/2)(809-829)725.5(2/2)
(705-746)N/A N/A N/A N/A N/A N/A 0 0 0 0 (Annually)
Sr-89 Sr-90 1 Fish (pCi/kg) (.wet)Gamma 8 K-40 8 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 8 8 8 8 8 8 8 130 260 130 130 260 130 150 2450(4/4)(2240-2650)
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)8 3.37 mi.SSE N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 2450(4/4)(2240-2650)
N/A N/A N/A N/A N/A N/A N/A 2447.5(4/4)
(1370-2850)
(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)(0/4)0 0 0 0 0 0 0 0 31 3.2 Analytical Results of 2013 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The data reported in the following tables are strictly counting statistics.
The reported error is two times the standard deviation (2G) 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 2a error.Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For clarity of this report only detectable results are presented.
TBE's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the North Anna ODCM.Data are given according to sample type as indicated below.1. Gamma Exposure Rate 2. Air Particulates, Gross Beta Radioactivity
- 3. Air Particulates, Weekly 1- 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 Analytical results are handled as recommended by HASL ("Reporting ofAnalytical Resultsfr'om HASL." letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).32 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESL mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quartei Station N-1 N-33 N-2 N-34 NNE-3 NNE-35 NNE-4 NNE 36 NE-5 NE-37 NE-6 NE-38 ENE-7 ENE-39 ENE-8 ENE-40'E-9 -E-41 E-10 E-42 ESE-1 1 ESE-43 ESE-12 ESE-44 SE-13 SE-45 SE-14 SE-46 SSE-15 SSE-47 SSE-16 SSE-48 5.3 6.2 3.8 3.3 7.7 7.1 4.6 4.5 5.2 5.5 3.3 3.5 6.0 6.6*2.8 2.7 6.1 6.1 5.5 5.7 4.3 4.6 5.8 5.4 5.8 4.6 8.0 7.1 6.3 5.1 4.3 3.1 4.4 4.7 2.5 2.5 5.6 5.9 3.6 3.9 4.4 4.5 2.6 2.7 4.7 4.5 2.2 2.4 3.9 4.1 3.9 3.9 4.6 3.7 4.9 4.1 3.8 4.4 5.1 6.5 5.0 4.1 2.1 2.5 5.5 5.4 2.8 3.6 6.9 6.4 4.6 5.0 3.6 4.1 3.3 3.6 4.3 6.0 2.3 2.4 5.4 5.4 4.7 4.8 4.5 4.8 5.0 4.5 5.0 3.7 5.9 6.1 5.2 5.4 3.0 2.3 5.7 6.2 4.4 3.3 7.4 7.3 4.2 4.8 4.2 6.0 4.3 4.2 5.4 5.2 3.5 3.4 4.9 5.9 5.1 5.5 5.3 5.0 5.0 5.1 5.3 5.8 7.6 7.6 5.0 5.7 3.6 3.3 JLTS Quarterly*
Average+/- 2 s.d.5.4 + 1- 1.3 3.3 +/- 1.3 6.8 + 1- 1.5 4.4 +/- 0.9 4.7 +/- 1.6 3.4 + 1- i.2 5.3 + 1- i.6 2.7 + 1- 1.0 5.2 +/- 1.7 4.9 + 1- 1.4 4.6 +/- 1.0 5.0 +/- 1.0 4.8 +/- 1.6 6.7 +1- 2.0 5.2 +/- 1.3 3.0 + 1- 1.5 Page 1 of 4*Average of collocated TLDs.33 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS mRJStd. Month (30.4 days) +/- 2 Sigma Page 2 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Station S-17 S-49 S-18 S-50 SSW-19 SSW-51 SSW-20 SSW-52 SW-21 SW-53 SW-22 SW-54 WSW-23 WSW-55 WSW-24 WSW-56 W-25 W-57 W-26.W-58 WNW-27 WNW-59 WNW-28 WNW-60 NW-29 NW-61 NW-30 NW-62 NNW-31 NNW-63 NNW-32 NNW-64 Quarterly*
Average+/- 2 s.d.5.7 4.9 3.1 2.8 7.4 7.0 2.8 2.5 4.6 5.3 5.7 4.2 5.3 6.8 5.5 5.5 8.6 8.5 3.7 3.7 4.1 3.8 3.3 3.3 7.4 8.6 2.5 2.3 4.5 4.1 3.5 3.7 3.9 5.3 1.7 2.1 5.7 5.3 2.0 2.1 4.1 3.7 3.6 3.6 4.8 4.5 3.9 3.6 7.6 5.8 2.8 2.5 3.0 2.8 2.7 2.6 7.7 5.9 1.7 1.9 2.8 3.1 3.3 3.1 4.8 4.6 2.6 2.6 5.3 6.9 2.8 3.1 4.8 4.8 4.7 4.8 5.5 5.4 4.4 4.3 5.8 6.9 3.1 3.6 2.8 3.3 2.3 2.6 7.5 6.3 2.0 1.6 2.8 4.0 3.8 4.3 6.2 5.0 2.9 3.4 5.8 6.2 3.1 3.5 5.4 4.7 5.3 4.5 6.2 5.6 4.9 4.7 8.0 8.3 3.8 3.0 4.2 3.1 3.6 3.3 8.6 9.2 3.0 2.9 4.7 4.2 5.0 3.9 5.1 +/- 1.4 2.7 +/- 1.1 6.2 +/- 1.6 2.7 +/- 1.0 4.7 +/- 1.1 4.6 +/- 1.5 5.5 +/- 1.5 4.6 +/- 1.4 7.4 +/- 2.3 3.3 +/- 1.0 3.4 +/- 1.1 3.0 +/- 0.9 7.7 +/- 2.3 2.2 +/- 1.1 3.8 +/- 1.5 3.8 +/- 1.2 4.6 +/- 1.5 Mean*Average of collocated TLDs.34 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma First Quarter Second Quarter Third Quarter Fourth Quarter Qua Page 3 of 4 rterly*Station C-1 C-2 C-3"*C-4"*C-5 C-6 C-7"*C-8"*4.1 4.0 3.4 3.3 2.4 2.9 3.9 4.0 2.7 2.7 2.8 2.7 2.1 2.0 4.4 3.3 2.8 2.9 2.9 3.1 2.4 1.9 3.8 3.3 3.4 3.5 4.2 3.8 3.4 2.9 4.3 3.5 Average+/- 2 s.d.3.3 +/- 1.1 3.3 +/- 1.0 2.5 +/- 1.0 3.8 +/- 0.8 2.9 +/-3.5 +/-1.3 1.1 EPSA-01**EPSA-02***
EPSF-03***
EPSF-04***
EPSR-05***
EPSR-06t**
EPSJ-07***'
EPSJ-08*A." EPSP-09***
EPSP-1 0***5.3 5.2 4.5 5.5 4.9 5.2 6.0--.4.5 9.9 9.1 4.9 4.1 4.2 4.0 5.4 4.5 3.7 3.5 8.5 6.5 3.7 5.3 4.4 3.7 4.4 5.3 4.0 4.3 6.0 6.5 5.2 5.5 5.2 4.6 7.0 5.8 3.8 7.9.8.2 4.9 +/- 1.3 4.5 +/- 1.2 5.3 +/- 1.7.4.4 +/- 1.7 7.8 +/- 2.8 5.4 +/- 3.1 Mean*Average of collocated TLDs.** Control Station Emergency Plan TLDs.35 TABLE 3-2 DIRECT RADIATION MEASURMENTS
-SECTOR QUARTERLY TLD RESULTS Page mR/Std. Month (30.4 days) +/-2 Sigma 4 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly Station 12/26/2012 3/26/2013 6/25/2013 9/24/2013 Average Annual TLD 3/26/2013 6/25/2013 9/24/2013 12/31/2013
+/- 2 s.d.STA-01 5.1 4.9 4.2 5.8 5.0 +/- 1.3 4.4 STA-02 3.0 2.8 2.7 3.2 2.9 +/- 0.4 2.5 STA-03 2.3 2.0 2.1 3.4 2.5 +/- 1.3 2.5 STA-04 3.7 1.9 2.4 2.5 2.6 +/- 1.5 2.8 STA-05 ** 2.7 2.8 3.0 2.8 +1- 0.3 2.3 STA-05A 4.2 2.4 2.6 3.9 3.3 +/- 1.8 2.5 STA-06 5.4 4.6 4.4 5.4 5.0 +/- 1.1 4.2 STA-07 4.1 2.5 3.4 3.9 3.5 +/- 1.4 3.3 STA-21 3.2 3.2 3.9 3.3 3.4 +/- 0.7 3.3 STA-22 5.4 4.5 4.4 4.9 4.8 +/- 0.9 4.4 STA-23 6.3 5.5 4.8 5.1 5.4 +/- 1.3 4.8 STA-24* 3.7 2.9 3.0 3.9 3.4 +/- 0.5 3.6 Mean -Indicator Locations 3.8 +/- 1.2 3.4 +/- 1.9*Control** TLD lost when power pole was replaced following storm 36 Table 3-3 Air Particulate Gross Beta Radioactivity
[10.3 pCi/m3], page 1 of 4 Period Ending 01/02/13 01/08/13 01/16/13 01/22/13 01/29/13 02/05/13 02/13/13 02/20/13 02/27/13 03/05/13 03/12/13 03/19/13 03/26113 04/02/13 04/09/13 Station 01 Station 02 Station 03 Station 04 Station 05 Station 06 Station 07 1.08E+01 3.08E+01 1.92E+01 1.59E+01 2.24E+01 2.52E+01 1.43E+01 1.10E+01 6.27E+00 7.84E+00 7.88E+00 1.35E+01 1.28E+01 9.78E+00 1.04E+01+/- 2.70E+00+/- 3.90E+00+/- 2.76E+00+/- 3.15E+00+/- 3.18E+00+/- 3.47E+00+/- 2.53E+00+/- 2.65E+00+/- 2.47E+00+/- 2.79E+00+/- 2.34E+00+/- 2.94E+00+/- 2.67E+00+/- 2.68E+00+/- 2.63E+00 1.48E+01 2.14E+01 2.05E+01 1.65E+01 2.33E+01 2.28E+01 1.20E+01 1.42E+01 6.93E+00 5.93E+00 6.77E+00 1.46E+01 1.13E+01 9.93E+00 1.61E+01+/- 2.92E+00 1.26E+01 +/- 2.86E+00 1.09E+01+1- 3.44E+00 3.23E+01 +/- 3.96E+00 3.26E+01+/- 2.82E+00 1.83E+01 +/- 2.72E+00 2.28E+01+/- 3.20E+00 1.61E+01 +/- 3.18E+00 1.76E+01+/- 3.22E+00 2.68E+01 +/- 3.38E+00 2.66E+01+1- 3.36E+00 1.96E+01 +1- 3.22E+00 2.54E+01+/- 2.41E+00 1.49E+01 +/- 2.56E+00 1.89E+01+/- 2.88E+00 1.17E+01 +/- 2.74E+00 1.28E+01+/- 2.49E+00 8.59E+00 +/- 2.46E+00 8.69E+00+/- 2.62E+00 5.35E+00 +/- 2.52E+00 1.01E+01+/- 2.66E+00 9.60E+00 +/- 2.66E+00 7.99E+00+/- 2.99E+00 1.04E+01 +/- 2.77E+00 1.25E+01+/- 2.58E+00 1.08E+01 +/- 2.49E+00 1.41E+01+/- 2.69E+00 1.02E+01 +/- 2.63E+00 9.91E+00+/- 32tE+00 1.60E+01 +/- 2.98E+00 2.03E+01+/- 2.74E+00+/- 3.97E+00+/- 2.92E+00+- 3.26E+00+/ 3.37E+00+/ 3.48E+00+/ 2.76E+00+/ 2.79E+00+/- 2.61E+00+- 2.86E+00+/ 2.39E+00+/ 2.88E+00+/ 2.69E+00+/ 2.64E+00+- 3.18E+00 1.55E+01 +/- 2.96E+00 3.78E+01 +/- 4.19E+00 2.40E+01 +/- 2.98E+00 2.30E+01 +/- 3.53E+00 2.73E+01 +/- 3.40E+00 2.36E+01 +/- 3.40E+00 1.78E+01 +/- 2.70E+00 1.41E+01 +/- 2.86E+00 1.20E+01 +/- 2.80E+00 8.40E+00 +/- 2.76E+00 1.86E+01 +1- 3.58E+00 1.33E+01 +/- 2.39E+00 1.57E+01 +/- 3.28E+00 1.20E+01 +- 2.84E+00 1.21E+01 +/ 2.34E+00 1.24E+01 +- 2.94E+00 1.97E+01 +/ 3.07E+00 1.44E+01 +/ 2.68E+00 1.60E+01 +- 2.70E+00 1.09E+01 +/ 2.51E+00 1.80E+01 +- 2.92E+00 1.07E+01 +- 2.60E+00 1.36E+01 3.06E+01 2.33E+01 1.93E+01 2.49E+01 2.05E+01 1.80E+01 1.45E+01 1.15E+01 7.38E+00 1.06E+01 1.59E+01 1.27E+01 9.16E+00 1.69E+01 1.47E+01 1.61E+01 1.12E+01 1.20E+01 1.37E+01 2.03E+01 1.50E+01 1.41E+01 1.21E+01 1.50E+01 8.58E+00+/- 2.86E+00+/- 3.88E+00+/- 2.95E+00+/- 3.34E+00+/- 3.29E+00+/- 3.26E+00+/- 2.72E+00+/- 2.87E+00+/- 2.78E+00+/- 2.70E+00+/- 2.85E+00+/- 3.06E+00+/- 2.64E+00+/- 2.63E+00+/- 3.00E+00+/- 2.47E+00+/ 3.34E+00+1 2.80E+00+/- 2.34E+00+1 3.01E+00+1 3.11E+00+- 2.71E+00+/ 2.59E+00+/- 2.58E+00+/ 2.76E+00+1 2.48E+00 1.17E+01 +/-3.39E+01 +/-1.77E+01 +/-1.82E+01 +/-2.53E+01 +/-2.22E+01 +/-1.38E+01 +/-1.20E+01 +/-7.51 E+00 +/-7.59E+00 +/-6.45E+00 +/-1.09E+01 +/1.41E+01 +/-7.26E+00 +/-2.03E+01 +/-1.25E+01 +1 1.35E+01 +1 8.74E+00 +-8.97E+00 +1 1.22E+01 +/1.31E+01 +-1.41E+01 +/1.51E+01 +/6.18E+00 +-1.34E+01 +/8.42E+00 +/-2.77E+00 4.03E+00 2.69E+00 3.28E+00 3.31E+00 3.33E+00 2.51 E+00 2.77E+00 2.52E+00 2.72E+00 2.24E+00 2.81E+00 2.72E+00 2.52E+00 3.20E+00 2.32E+00 3.29E+00 2.62E+00 2.18E+00 2.87E+00 2.74E+00 2.66E+00 2.65E+00 2.21 E+00 2.68E+00 2.49E+00 04/17/13 1.16E+01 +/- 2.28E+00 1.74E+01 +/- 2.58E+00 1.15E+01 +/- 2.25E+00 1.34E+01 +/- 2.39E+00 04/23/13 1.23E+01 +/- 3.10E+00 1.67E+01 +/- 3.34E+00 1.23E+01 +/- 3.16E+00 1.26E+01 +/- 3.16E+00 04/30/13 1.27E+01 +/- 2.95E+00 1.34E+01 +/- 2.87E+00 1.16E+01 +/- 2.82E+00 1.14E+01 +/- 2.82E+00 05/08/13 7.49E+00 +/- 2.03E+00 1.16E+01 +/- 2.34E+00 8.38E+00 +/- 2.12E+00 8.81E'+00
+/- 2.16E+00 05/14/13 1.11E+01 +/- 2.83E+00 1.54E+01 +/- 3.06E+00 1.25E+01 +/- 2.96E+00 1.47E+01 +/- 3.05E+00 05/21/13 1.30E+01 +/- 2.74E+00 1.94E+01 +/ 3.06E+00 1.69E+01 +/- 2.93E+00 1.65E+01 +/- 2.91E+00 05/28/13 1.40E+01 +/ 2.65E+00 1.42E+01 +/- 2.67E+00 1.22E+01 +/- 2.55E+00 1.17E+01 +/- 2.52E+00 06/04/13 1.46E+01 +/- 2.62E+00 1.59E+01 +/- 2.70E+00 1.23E+01 +/- 2.48E+00 1.32E+01 +/- 2.54E+00 06/11/13 8.08E+00 +/ 2.33E+00 1.13E+01 +/ 2.53E+00 1.21E+01 +/- 2.58E+00 9.64E+00 */- 2.43E+00 06/18/13 1.57E+01 +/ 2.81E+00 1.43E+01 +/ 2.73E+00 1.84E+01 +/- 2.94E+00 1.35E+01 +/- 2.68E+00 06/25/13 1.01E+01 +/- 2.63E+00 1.02E+01 +/ 2.59E+00 1.31E+01 +/- 2.67E+00 1.37E+01 +/- 2.76E+00* Sample not obtained due to sampler not operating.
37 Table 3-3 Air Particulate Gross Beta Radioactivity
[10.3 pCi/m 3]page 2 of 4 Period Ending Station 21 Station 22 Station 23_:I Station 24*Station 01A Station 05A I 01/02/13 9.27E+00 +/- 2.62E+00 01/08/13 01/16/13 01/22/13 01/29/13 02105113 02/13/13 02/20/13 02/27/13 03/05/13 03/12/13 03/19/13 03/26/13 04/02/13 04/09/13 04/17/13 04/23/13 04/30/13 05/08/13 05/14/13 05/21/13 05/28/13 06/04/13 06/11/13 06/18/13 06/25/13 3.34E+01 +/- 4.01E+00 2.19E+01 +/- 2.89E+00 1.46E+01 +/- 3.08E+00 2.67E+01 +/- 3.37E+00 1.80E+01 +/- 3.14E+00 1.74E+01 +/- 2.69E+00 1.27E+01 +/- 2.80E+00 7.37E+00 +/- 2.56E+00 5.85E+00 +/- 2.55E+00 6.14E+00 +/- 2.29E+00 1.33E+01 +- 2.92E+00 1.15E+01 +/ 2.58E+00 8.66E+00 +/ 2.60E+00 1.34E+01 4/- 2.87E+00 1.12E+01 +/- 2.25E+00 1.07E+01 +/- 3.16E+00 1.05E+01 +/- 2.75E+00 8.99E+00 +/- 2.17E+00 1.34E+01 +/- 3.00E+00 1.50E+01 +/- 2.83E+00 8.71E+00 +/- 2.34E+00 1.39E+01 +/- 2.58E+00 7.77E+00 +/- 2.33E+00 1.20E+01 +/- 2.59E+00 6.44E+00 +/ 2.33E+00 9.95E+00 +/- 2.66E+00 1.05E+01 +/- 2.692+00 3.33E+01 +/- 4.00E+00 3.20E+01 +/- 3.95E+00 1.82E+01 +/- 2.71E+00 2.06E+01 +/- 2.83E+00 1.82E+01 +/- 3.28E+00 1.47E+01 +/- 3.09E+00 2.07E+01 +/- 3.09E+00 2.78E+'O1
+/- 3.42E+00 1.90E+01 +/- 3.19E+00 2.22E+01 +/- 3.33E+00 1.42E+01 +/- 2.53E+00 1.57E+01 +/- 2.60E+00 9.43E+00 +/- 2.61E+00 1.22E+01 +/- 2.76E+00 7.52E+00 +/- 2.57E+00 8.71 E+00 +/- 2.58E+00 8.36E+00 +/- 2.72E+00 7.68E+00 +/- 2.76E+00 9.31 E+00 4/- 2.43E+00 7.03E+00 +/- 2.34E+00 1.07E+01 +/- 2.79E+00 1.55E+01 +/- 3.03E+00 1.33E+01 +/- 2.68E+00 1.27E+01 +/- 2.64E+00 8.21E+00 +/ 2.57E+00 1.14E+01 +/ 2.75E+00 2.05E+01 +/ 3.21E+00 -1.73E+01 +/ 3.05E+00 1.24E+01 +/ 2.32E+00 1.34E+01 +/ 2.37E+00 1.52E+01 +/ 3.26E+00 1.45E+01 +/ 3.40E+00 9.25E+00 +/- 2.68E+00 1.04E+01 +/ 2.70E+00 8.59E+00 4/- 2.14E+00 1.06E+01 4/- 2.29E+00 1.35E+01 +/- 2.86E+00 1.02E+01 +/- 2.67E+00 1.52E+01 +/- 2.95E+00 3.57E+01 2.18E+01.1.52E+01 2.52E+01 2.12E+01 1.38E+01 1.20E+01 7.47E+00 5.91E+00 5.90E+00<3.55E+00 1.21E+01 1.26E+01 1.81E+01 1.42E+01 1.27E+01 1.01E+01 7.94E+00 4/- 4.11E+00+/- 2.88E+00+/- 3.12E+00+/- 3.31E+00+/- 3.29E+00+/- 2.51E+00+/ 2.77E+00+/ 2.57E+00+/ 2.55E+00+/ 2.22E+00+/- 2.60E+00+/- 2.80E+00+/ 3.09E+00+/- 2.42E+00+/- 3.14E+00+/- .2.74E+00+/- 2.10E+00+/- 2.87E+00+/- 2.75E+00 4/- 2.70E+00+/- 2.87E+00+/ 2.32E+00+/ 2.62E+00+/- 2.56E+00 2.99E+01 +/-1.83E+01 +/-1.39E+01 +/-2.19E+01 +/-1.29E+01 +/-1.33E+01 +/-1.04E+01 +/-8.56E+00 +/-6.64E+00 +/-8.62E+00 +/1.40E+01 +/-7.97E+00 +/-1.09E+01 +/1.68E+01 +/-9.74E+00 4/-1.22E+01 +/-9.34E+00 +/-9.09E+00 +/-1.01E+01 +/-1.47E+01 +/-1.22E+01 +/-1.29E+01 +/-6.32E+00 +/-1.14E+01 +/-8.42E+00 +/-3.85E+00 2.72E+00 3.05E+00 3.15E+00 2.89E+00 2.48E+00 2.62E+00 2.61E+00 2.70E+00 2.38E+00 2.97E+00 2.38E+00 2.73E+00 2.96E+00 2.17E+00 3.09E+00 2.76E+00 2.13E+00 2.77E+00 2.83E+00 2.55E+00 2.53E+00 2.22E+00 2.57E+00 2.53E+00 3.42E+01 2.13E+01 1.30E+01 2.33E+01 2.00E+01 1.69E+01 1.07E+01 8.61E+00 8.55E+00 6.95E+00 1.30E+01 8.18E+00 8.25E+00 1.43E+01 1.23E+01 1.23E+01 9.97E+00 8.34E+00 9.53E+00 1.39E+01 1.27E+01 1.24E+01 9.13E+00 1.47E+01 7.49E+00+/ 4.04E+00+/ 2.86E+00+/- 3.01 E+00+/- 3.22E+00 4/- 3.23E+00+/- 2.66E+00+/- 2.68E+00+/- 2.62E+00+/- 2.76E+00+/- 2.29E+00+/- 2.91 E+00+/- 2.37E+00+/- 2.57E+00+/- 2.88E+00+/- 2.33E+00+/- 3.15E+00+/ 2.73E+00+/ 2.13E+00+/ 2.76E+00+/ 2.78E+00+/ 2.58E+00 4/- 2.49E+00+/- 2.40E+00+/- 2.75E+00+/- 2.41 E+00 1.16E+01 +/- 2.90E+00 1.38E+01 +/- 2i95E+00 1.11E+01 1.63E+01 +/- 2.90E+00 1.53E+01 +/- 2.86E+001 1.33E+01 1.06E+01 +/- 2.46E+00 1.33E+01 +/- 2.62E+00 1.47E+01 1.39E+01 +/- 2.58E+00 1.16E+01 +/- 2.45E+00 1.91E+01 8.21 E+00 +/- 2.35E+00 8.98E+00 +/- 2.39E+00 7.82E+00 1.38E+01 +/- 2.70E+00 1.60E+01 +/- 2.82E+00 .1.23E+01 9.15E+00 +/- 2.50E+00 7.43E+00 +/- 2.44E+00 1.07Et01* Control Station 38 Table 3-3 Air Particulate Gross Beta Radioactivity
[10 3 pCi/m 3]page 3 of 4 Period Ending 07/03/13 07/09/13 07/16/13 07/24/13 07/31/13 08/06/13 08/14/13 08/20/13 08/27/13 09/03/13 09/10/13 09/17/13 09/24/13 10/02/13 10/08/13 10/16/13 10/22/13 10/30/13 11/05/13 11/13/13 11/20/13 11/26/13 12/03/13 12/11/13 12/17/13 12/23/13 Station Station Station Station Station Station I I I 1.41 E+01 7.47E+00 1.14E+01 1.61E+01 1.30E+01 1.25E+01 1.75E+01 5.32E+00 1.48E+01 2.22E+01 1.69E+01 1.46E+01 1.47E+01 1.37E+01 2.26E+01 1.07E+01 1.54E+01 1.94E+01 2.92E+01 1.OOE+01 1.48E+01 1.82E+01 1.91E+01 2.20E+01 2.82E+01 1.58E+01 2.35E+00 2.47E+00 2.64E+00 2.62E+00 2.63E+00 3.04E+00 2.67E+00 2.58E+00 2.72E+00 3.10E+00 2.82E+00 2.90E+00 2.73E+00 2.50E+00 3.35E+00 2.20E+00 3.13E+00 2.75E+00 3.75E+00 2.26E+00 2.71E+00 3.24E+00 2.99E+00 2.86E+00 3.98E+00 3.22E+00 1.43E+01 9.32E+00 1.24E+01 1.71E+01 1.74E+01 1.59E+01 1.75E+01 9.07E+00 1.42E+01 2.94E+01 2.16E+01 2.49E+01 1.84E+01 1.56E+01 3.29E+01 1.33E+01 2.25E+01 2.52E+01 2.38E+01 1.31E+01 1.47E+01 1.53E+01 2.40E+01 1.80E+01 1.67E+01 1.44E+01 2.38E+00 2.62E+00 2.71 E+00 2.67E+00 2.87E+00 3.22E+00 2.67E+00 2.82E+00 2.66E+00 3.46E+00 3.07E+00 3.37E+00 2.91E+00 2.55E+00 3.87E+00 2.33E+00 3.56E+00 3.00E+00 3.52E+00 2.43E+00 2.71E+00 3.07E+00 3.24E+00 2.68E+00 3.45E+00 3.13E+00 1.25E+01 9.46E+00 1.15E+01 1.64E+01 1.39E+01 1.80E+01 2.26E+01 1.05E+01 1.40E+01 2.52E+01 1.92E+01 2.40E+01 1.17E+01 1.74E+01 2.44E+01 1.39E+01 1.76E+01 2.46E+01 2.16E+01 1.64E+01 1.04E+01 1.33E+01 2.05E+01 1.26E+01 1.78E+01 1.46E+01 03+1-+/-+/-+/-I I I I Station 07 I 2.28E+00 2.73E+00 2.62E+00 2.63E+00 2.71E+00 3.33E+00 2.91 E+00 2.90E+00 2.61E+00 3.31E+00 2.96E+00 3.28E+00 2.51E+00 2.74E+00 3.53E+00 2.33E+00 3.34E+00 2.94E+00 3.47E+00 2.61 E+00 2.46E+00 2.95E+00 3.07E+00 2.41E+00 3.46E+00 3.14E+00 1.23E+01 8.30E+00 9.71 E+00 1.80E+01 1.42E+01 1.76E+01 1.79E+01 8.64E+00 1.46E+01 2.70E+01 1.86E+01 2.36E+01 1.59E+01 1.75E+01 3.08E+01 1.04E+01 1.96E+01 2.64E+01 2.74E+01 1.54E+01 1.66E+01 1.61E+01 2.07E+01 2.22E+01 2.23E+01 1.80E+01 2.27E+00 2.59E+00 2.58E+00 2.71E+00 2.67E+00 3.31E+00 2.69E+00 2.80E+00 2.67E+00 3.36E+00 2.92E+00 3.30E+00 2.76E+00 2.72E+00 3.79E+00 2.15E+00 3.42E+00 3.04E+00 3.71E+00 2.56E+00 2.81E+00 3.12E+00 3.08E+00 2.87E+00 3.76E+00 3.32E+00 1.37E+01 7.84E+00 1.28E+01 1.70E+01 1.61E+01 1.53E+01 2.34E+01 1.13E+01 1.23E+01 2.65E+01 2.00E+01 2.93E+01 1.39E+01 1.80E+01 3.33E+01 1.43E+01 2.36E+01 2.47E+01 2.49E+01 1.54E+01 1.41E+01 1.37E+01 2.34E+01 1.68E+01 1.70E+01 1.56E+01 2.34E+00 2.55E+00 2.71E+00 2.66E+00 2.82E+00 3.19E+00 2.94E+00 2.96E+00 2.54E+00 3.35E+00 2.99E+00 3.54E+00 2.66E+00 2.73E+00 3.91E+00 2.37E+00 3.63E+00 2.96E+00 3.61E+00 2.56E+00 2.67E+00 2.98E+00 3.21 E+00 2.62E+00 3.43E+00 3.20E+00 1.13E+01 6.19E+00 8.95E+00 1.58E+01 1.44E+01 1.81E+01 2.11E+01 8.81 E+00 1.65E+01 2.76E+01 1.80E+01 2.46E+01 1.85E+01 1.65E+01 2.85E+01 1.16E+01 1.65E+01 2.57E+01 2.84E+01 1.94E+01 1.26E+01 1.48E+01 2.43E+01 2.00E+01 2.36E+01 1.79E+01 2.21E+00 2.43E+00 2.51E+00 2.60E+00 2.72E+00 3.34E+00 2.84E+00 2.81E+00 2.78E+00 3.39E+00 2.89E+00 3.35E+00 2.91 E+00 2.65E+00 3.68E+00 2.22E+00 3.26E+00 3.01E+00 3.77E+00 2.76E+00 2.59E+00 3.04E+00 3.25E+00 2.77E+00 3.78E+00 3.33E+00 1.49E+01 6.93E+00 1.04E+01 1.55E+01 1.56E+01 1.43E+01 2.02E+01 9.07E+00 1.61E+01 2.86E+01 2.31E+01 2.42E+01 1.52E+01 1.40E+01 3.30E+01 1.21E+01 2.10E+01 2.17E+01 1.71E+01 1.67E+01 1.55E+01 1.48E+01 2.38E+01 1.36E+01 2.12E+01 1.62E+01 2.40E+00 2.47E+00 2.60E+00 2.59E+00 2.78E+00 3.14E+00 2.80E+00 2.82E+00 2.76E+00 3.43E+00 3.15E+00 3.33E+00 2.74E+00 2.53E+00 3.88E+00 2.25E+00 3.48E+00 2.84E+00 3.18E+00 2.62E+00 2.75E+00 3.04E+00 3.22E+00 2.46E+00 3.67E+00 3.23E+00 MEAN 1.491E+01
+/- 2.81E+00 1.63E+01 +/- 2.90E+00 1.54E+01 +/- 2.84E+00 1.65E+01 +/- 2.90E+00 1.77E+01 +/- 2.97E+00 1.68E+01 +/- 2.92E+00 1.56E+01+/- 2.85E+00 39 Table 3-3 Air Particulate Gross Beta Radioactivity
[10-3 pCi/m 3]page 4 of 4 Period Endin0//07/03/13 07/09/13 07/16/13 07/24/13 07/31/13 08/06/13 08/14/13 08/20/13 08/27/13 09/03/13 09/10/13 09/17/13 09/24/13 10/02/13 10/08/13 10/16/13 10/22/13 10/30/13 11/05/13 11/13/13 11/20/13 11/26/13 12/03/13 12/11/13 12/17/13 12/23/13 MEAN Station Station 21 I22 1.03E+01 +/- 2.14E+00 1.44E+01 +/- 2.38E+00 1.35E+01 5.70E+00 +/- 2.40E+00 6.91E+00 +/- 2.52E+00 7.11E+00 1.16E+01 +/- 2.65E+00 9.56E+00 +/- 2.54E+00 1.21E+01 1.55E+01 +/- 2.59E+00 1.21 E+01 +/- 2.42E+00 1.57E+01 1.62E+01 +/- 2.84E+00 9.41E+00 +/- 2.39E+00 1.36E+01 1.51E+01 +/- 3.18E+00 1.56E+01 +/- 3.21E+00 1.69E+01 2.18E+01 +/- 2.88E+00 1.71 E+01 +/- 2.66E+00 2.01E+01 6.60E+00 +/- 2.66E+00 8.43E+00 +/- 2.77E+00 5.85E+00 1.54E+01 +/- 2.69E+00 1.36E+01 +/- 2.60E+00 1.34E+01 2.67E+01 +/- 3.38E+00 2.13E+01 +/- 3.12E+00 2.50E+01 1.71E+01 +/- 2.85E+00 1.89E+01 +/- 2.95E+00 1.81E+01 2.70E+01 +/- 3.40E+00 1.86E+01 +/- 3.18E+00 2.08E+01 1.34E+01 +/- 2.64E+00 1.41 E+01 +/- 2.73E+00 1.92E+01 1.01E+01 +/- 2.32E+00 1.20E+01 +/- 2.43E+00 1.48E+01 1.62E+01 +/- 3.13E+00 2.74E+01 +/- 3.67E+00 2.35E+01 7.78E+00 +/- 1.97E+00 1.02E+01 +/- 2.12E+00 1.02E+01 1.13E+01 +/- 2.98E+00 1.56E+01 +/- 3.23E+00 1.79E+01 1.33E+01 +/- 2.40E+00 2.02E+01 +/- 2.75E+00 1.79E+01 2.29E+01 +/- 3.53E+00 2.07E+01 +/- 3.41 E+00 2.58E+01 1.38E+01 +/- 2.48E+00 1.68E+01 +/- 2.63E+00 1.64E+01 1.19E+01 +/- 2.55E+00 1.66E+01 +/- 2.81E+00 1.26E+01 1.32E+01 +/- 2.94E+00 1.02E+01 +/- 2.75E+00 1.33E+01 1.60E+01 +/- 2.84E+00 2.43E+01 +/- 3.25E+00 2.47E+01 1.45E+01 +/- 2.56E+00 1.80E+01 +/- 2.74E+00 1.76E+01 1.79E+01 +/- 3.50E+00 2.11E+01 +/- 3.66E+00 2.65E+01 1.25E+01 +/- 3.03E+00 1.98E+01 +/- 3.42E+00 1.59E+01 1.39E+01 +/- 2.77E+00 1.47E+01 +/- 2.81E+00 1.56E+01 Station 23 Station 24*I Station 01A Station 05A+/- 2.33E+00+/- 2.46E+00+/- 2.68E+00+/- 2.60E+00+/- 2.67E+00+/- 3.27E+00+/- 2.79E+00+/- 2.62E+00+/- 2.63E+00+/- 3.25E+00+/- 2.89E+00+/- 3.19E+00+/- 2.94E+00+/- 2.58E+00+/- 3.432+00+/- 2.16E+00+/- 3.302+00+/- 2.67E+00+/- 3.60E+00+/- 2.61 E+00+/- 2.59E+00+/- 2.95E+00+/- 3.27E+00+/- 3.37E+00+/- 3.92E+00+/- 3.22E+00 1.43E+01 +/- 2.38E+00 6.25E+00 +/- 2.482+00 1.04E+01 +/- 2.59E+00 1.04E+01 +/- 2.33E+00 1.20E+01 +/- 2.57E+00 1.09E+01 +/- 2.94E+00 1.89E+01 +/- 2.74E+00 8.46E+00 +/- 2.79E+00 1.642+01 +/- 2.74E+00 2.49E+01 +/- 3.31 E+00 1.72E+01 +/- 2.852+00 2.12E+01 +/- 3.14E+00 1.48E+01 +/- 2.71E+00 1.21E+01 +/- 2.43E+00 1.74E+01 +/- 3.17E+00 1.10E+01 +/- 2.16E+00 1.55E+01 +/- 3.252+00 1.58E+01 +/- 2.52E+00 2.09E+01 +/- 3.45E+00 1.63E+01 +/- 2.592+00 1.86E+01 +/- 2.92E+00 1.09E+01 +/- 2.80E+00 2.32E+01 +/- 3.20E+00 1.98E+01 +/- 2.76E+00 1.612+01 +/- 3.41E+00 1.88E+01 +/- 3.36E+00 1.13E+01<3.15E+00 9.63E+00 1.37E+01 1.43E+01 1.032+01 1.602+01 5.41 E+00 1.19E+01 2.312+0 1 1.582+01 2.13E+01 1.10E+01 1.24E+01 1.97E+01 8.85E+00 1.77E+01 1.85E+01 1.902+01 1.542+01 1.17E+01 1.26E+01 2.00E+01 1.622+01 2.16E+01 1.24E+01+/- 2.252+00 1.062+01 4.86E+00+/- 2.54E+00 9.52E+00+/- 2.50E+00 1.382+01+/- 2.71 E+00 1.012+01+/- 2.91 E+00 1.23E+01+/- 2.60E+00 1.94E+01+/- 2.59E+00 8.64E+00+/- 2.55E+00 1.34E+01+/- 3.16E+00 2.06E+01+/- 2.76E+00 1.65E+01+/- 3.23E+00 1.95E+01+/- 2.51 E+00 1.69E+01+/- 2.442+00 1.28E+01+/- 3.202+00 2.98E+01+/- 2.092+00 1.31 E+01+/- 3.262+00 2.04E+01+/- 2.71 E+00 2.09E+01+/- 3.25E+00 2.44E+01+/- 2.56E+00 1.63E+01+/- 2.53E+00 1.302+01+/- 2.91 2+00 1.54E+01+/- 3.04E+00 2.22E+01+/- 2.59E+00 1.36E+01+/- 3.672+00 1.77E+01+/- 3.032+00 1.26E+01+/- 2.17E+00+/- 2.352+00+/- 2.53E+00+/- 2.50E+00+/- 2.47E+00+/- 3.02E+00+/- 2.76E+00+/- 2.80E+00+/- 2.60E+00+/- 3.08E+00+/- 2.81 E+00+/- 3.09E+00+/- 2.85E+00+/- 2.472+00+/- 3.76E+00+/- 2.30E+00+/- 3.48E+00+/- 2.78E+00+/- 3.59E+00+/- 2.60E+00+/- 2.61 E+00+/- 3.08E+00+/- 3.152+00+/- 2.46E+00+/- 3.46E+00+/- 3.03E+00+/- 2.87E+00 1.48E+01 +/- 2.83E+00 Mean -A 1.35E+01 +/- 2.75E+00 1.452+01 +/- 2.802+00 11 Indicator Locations 1.54E+01 +/- 2.85E+00* Control Station 40 Table 3-4 Airborne Iodine 1-131[10-3 pCi/m 3]page 1 of 4 Period Endin0/2 01/02/13 01/08/13 01/16/13 01/22/13 01/29/13 02/05/13 02/13/13 02/20/13 02/27/13 03/05/13 03/12/13 03/19/13 03/26/13 04/02/13 04/09/13 04/17/13 04/23/13 04/30/13 05/08/13 05/14/13 05/21/13 05/28/13 06/04/13 06/11/13 06/18/13 06/25/13 Station 01" 1.24E+01" 6.62E+01" 2.73E+01" 4.59E+01" 1.91E+01" 3.37E+01" 1.19E+01" 2.18E+01" 1.85E+01" 2.87E+01" 3.74E+01" 3.44E+01 Station 12 02< 3.21E+01 Station S.E03< 3.29E+01 Station J2 04" 3.25E+01" 6.62E+01" 6.15E+01" 4.61E+01 C C(C*C C C 2.52E+01 1.35E+01 8.67E+00 2.24E+01 1.34E+01 2.55E+01 1.44E+01 2.27E+01 1.68E+01 4.60E+01 8.10E+00 2.98E+01 1.73E+01 2.32E+01 6.61E+01 6.15E+01 4.61E+01 4.30E+01 3.37E+01 3.07E+01 2.23E+01 3.55E+01 2.82E+01 4.56E+01 3.44E+01 2.52E+01 3.48E+01 2.53E+01 8.71 E+00 3.46E+01 2.42E+01 2.72E+01 2.24E+01 4.31 E+01 4.61 E+01 2.09E+01 2.98E+01 4.43E+01 2.27E+01 6.62E+01 6.15E+01 4.61E+01 4.30E+01 3.37E+01 3.07E+01 2.22E+01 3.63E+01 2.75E+01 4.16E+01 3.44E+01 2.44E+01 3.37E+01 2.29E+01 2.21E+01 3.54E+01 9.59E+00 2.67E+01 2.32E+01 4.29E+01 4.61E+01 2.08E+01 3.OOE+01 4.42E+01 2.17E+01 C C: C(C(,C ,C ,C ,C C C C C: C: C: 4.30E+01 3.37E+01 3.07E+01 2.22E+01 3.58E+01 2.78E+01 3.83E+01 3.44E+01 2.46E+01 3.40E+01 2.29E+01 2.26E+01 3.53E+01 2.48E+01 2.68E+01 8.39E+00 4.31E+01 4.61E+01 2.09E+01 2.98E+01 4.43E+01 Station S05" 3.22E+01" 3.54E+01" 6.15E+01" 4.01E+01" 4.30E+01" 1.98E+01" 3.07E+01" 1.66E+01" 3.60E+01" 2.27E+01 C C: *C: *C *" 2.79E+01" 2.26E+01" 3.45E+01" 2.47E+01" 2.67E+01" 2.30E+01" 4.31E+01" 1.89E+01" 2.09E+01" 3.07E+01" 4.43E+01" 2.91E+01 Station S06" 2.49E+01" 3.54E+01" 2.37E+01" 4.01E+01" 3.87E+01" 1.98E+01" 2.72E+01" 1.65E+01" 2.43E+01" 2.28E+01" 4.53E+01" 2.42E+01" 2.77E+01" 2.73E+01" 2.29E+01" 2.53E+01" 2.13E+01" 2.81E+01" 3.22E+01" 2.62E+01" 3.43E+01" 3.18E+01" 1.96E+01" 1.29E+01" 4.05E+01" 2.92E+01 Station i207" 2.49E+01" 3.54E+01" 2.37E+01" 4.01E+01" 3.87E+01" 1.98E+01" 2.72E+01" 1.67E+01" 2.39E+01" 2.29E+01" 3.83E+01" 2.42E+01" 2.77E+01" 2.73E+01" 2.33E+01" 2.49E+01" 2.21E+01" 2.75E+01" 3.25E+01" 2.56E+01" 3.43E+01" 3.18E+01" 1.96E+01" 3.07E+01" 4.05E+01" 1.23E+01-I< 2.24E+01* Sample not obtained due to sampler not operating 41 Table 3-4 Airborne Iodine 1-131[10-3 pCi/m 3]page 2 of 4 Period Ending 01/02/13 01/08/13 01/16/13 01/22/13 01/29/13 02/05/13 02/13/13 02/20/13 02/27/13 03/05/13 03/12/13 03/19/13 03/26/13 04/02/13 04/09/13 04/17/13 04/23/13 04/30/13 05/08/13 05/14/13 05/21/13 05/28/13 06/04/13 06/11/13 06/18/13 06/25/13!Station 21 2.49E+01 1.49E+01 2.37E+01 3.99E+01 3.87E+01 1.98E+01 2.72E+01 1.67E+01 2.44E+01 2.24E+01 3.97E+01 2.42E+01 2.77E+01 2.74E+01 2.33E+01 2.49E+01 2.24E+01 2.79E+01 3.21E+01 2.63E+01 3.42E+01 3.18E+01 1.96E+01 3.09E+01 4.03E+01 2.89E+01!Station 22 2.49E+01 3.54E+01 2.37E+01 2.35E+01 3.87E+01 2.62E+01 2.72E+01 2.10E+01 2.44E+01 2.89E+01 3.84E+01 2.42E+01 2.77E+01 2.73E+01 2.33E+01 2.49E+01 2.10E+01 2.79E+01 3.21E+01 2.63E+01 3.42E+01 3.18E+01 1.96E+01 3.09E+01 4.03E+01 2.89E+01!Station 23< 3.28E+01< 2.70E+01< 4.OOE+01< 5.60E+01< 4.OOE+01< 1.10E+01< 2.80E+01< 2.10E+01< 2.44E+01< 3.OOE+01< 2.69E+01< 3.05E+01< 2.49E+01< 2.33E+01< 1.83E+01< 1.98E+01< 2.08E+01< 2.10E+01< 3.28E+01< 2.71E+01< 5.15E+01< 4.41E+01" 1.77E+01< 1.78E01-< 3.55E+01< 3.16E+01 I Station 24*.< 3.29E+01" 2.70E+01" 3.99E+01" 5.62E+01< 4.OOE+01" 2.62E+01" 2.80E+01< 8.84E+00" 2.51E+01" 2.88E+01" 2.64E+01" 3.05E+01" 2.48E+01" 2.32E+01" 1.82E+01" 1.98E+01!Station 01A 3.28E+01 2.70E+01 3.99E+01 5.60E+01 4.OOE+01 2.62E+01 2.80E+01 2.05E+01 2.48E+01 1.06E+01 2.61E+01 3.05E+01 2.51E+01 2.35E+01 1.77E+01 1.98E+01 1.94E+01 2.22E+01 3.14E+01 2.77E+01 5.15E+01 4.41E+01 1.77E+01 3.27E+01 3.56E+01 3.19E+01!Station 05A 3.29E+01 2.70E+01 3.99E+01 5.62E+01 4.OOE+01 2.62E+01 2.80E+01 2.09E+01 2.49E+01 2.93E+01 2.63E+01 1.58E+01 2.48E+01 2.32E+01 1.81E+01 2.OOE+01 1.98E+01 2.16E+01 3.22E+01 2.80E+01 5.13E+01 4.41E+01 1.77E+01 3.28E+01 3.54E+01 3.09E+01-A" 1.95E+01" 2.16E+01" 3.21E+01< 2.81E+01" 5.13E+01< 4.41E+01< 1.77E+01< 3.28E+01< 3.55E+01< 3.04E+01* Control Station 42 Table 3-4 Airborne Iodine page 1-131 3 of 4[10-3 pCi/m 3]Period Station Station Station Station Station Station Station Ending I 01 I 02 I I 04 I 05 I 06 I 07 07/03/13 < 2.69E+01 < 2.71E+01 < 2.72E+01 < 2.72E+01 < 1.61E+01 < 3.82E+01 < 3.81E+01 07/09/13 < 2.88E+01 < 2.92E+01 < 3.07E+01 < 2.97E+01 < 3.75E+01 < 3.73E+01 < 3.72E+01 07/16/13 < 1.35E+01 < 3.50E+01 < 3.42E+01 < 3.53E+01 < 3.46E+01 < 2.64E+01 < 2.64E+01 07/24/13 < 4.26E+01 < 4.26E+01 < 4.26E+01 < 4.27E+01 < 2.94E+01 < 2.95E+01 < 2.95E+01 07/31/13 < 3.13E+01 < 5.23E+01 < 5.32E+01 < < 5.16E+01 < 5.29E+01 < 6.69E+01 < 6.67E+01 08/06/13 < 4.10E+01 < 4.10E+01 < 4.10E+01 < 4.10E+01 < 3.55E+01 < 3.55E+01 < 3.55E+01 08/14/13 < 1.08E+01 < 2.79E+01 < 2.80E+01 < 2.79E+01 < 2.79E+01 < 3.35E+01 < 3.35E+01 08/20/13 < 3.31E+01 < 3.31E+01 < 3.29E+01 < 3.31E+01 < 3.03E+01 < 3.03E+01 < 3.03E+01 08/27/13 < 9.39E+00 < 1.56E+01 < 1.53E+01 < 1.56E+01 < 1.55E+01 < 3.78E+01 < 3.79E+01 09/03/13 < 4.85E+01 < 4.91E+01 < 5.00E+01 < 4.94E+01 < 4.37E+01 < 4.36E+01 < 4.34E+01 09/10/13 < 3.15E+01 < 3.16E+01 < 3.17E+01 < 3.16E+01 < 3.25E+01 < 3.25E+01 < 3.25E+01 09/17/13 < 4.06E+01 < 3.99E+01 < 3.89E+01 < 3.96E+01 < 4.16E+01 < 4.18E+01 < 4.19E+01 09/24/13 < 2.65E+01 < 6.77E+01 < 6.66E+01 < 6.70E+01 < 6.76E+01 < 4.60E+01 < 4.60E+01 10/02/13 < 2.01E+01 < 5.04E+01 < 5.30E+01 < 5.25E+01 < 5.21E+01 < 3.66E+01 < 3.66E+01 10/08/13 < 1.30E+01 < 3.40E+01 < 3.49E+01 < 3.42E+01 < 3.44E+01 < 2.96E+01 < 2.96E+01 10/16/13 < 6.00E+01 < 2.29E+01 < 5.77E+01 < 5.87E+01 < 5.84E+01 < 4.30E+01 < 4.30E+01 10/22/13 < 2.28E+01 < 5.99E+01 < 6.10E+01 < 6.02E+01 < 6.04E+01 < 6.39E+01 < 6.36E+01 10/30/13 < 3.22E+01 < 3.19E+01 < 1.22E+01 < 3.18E+01 < 3.16E+01 < 2.56E+01 < 2.57E+01 11/05/13 < 1.83E+01 < 4.79E+01 < 4.90E+01 < 4.81E+01 < 4.86E+01 < 3.65E+01 < 3.64E+01 11/13/13 < 5.61E+01 < 5.61E+01 < 5.61E+01 < 2.18E+01 < 5.61E+01 < 4.40E+01 < 4.40E+01 11/20/13 < 1.97E+01 < 5.07E+01 < 5.07E+01 < 5.07E+01 < 5.07E+01 < 5.02E+01 < 5.02E+01 11/26/13 < 5.05E+01 < 5.05E+01 < 5.04E+01 < 5.05E+01 < 2.12E+01 < 4.73E+01 < 4.73E+01 12/03/13 < 1.82E+01 < 4.70E+01 < 4.71E+01 < 4.70E+01 < 4.70E+01 < 4.67E+01 < 4.67E+01 12/11/13 < 1.31E+01 < 3.13E+01 < 3.13E+01 < 3.13E+01 < 3.13E+01 < 3.19E+01 < 3.19E+01 12/17/13 < 6.28E+01 < 6.36E+01 < 6.23E+01 < 6.42E+01 < 6.67E+01 < 6.71E+01 < 6.74E+01 12/23/13 < 6.62E+01 < 6.59E+01 < 6.58E+01 < 6.58E+01 < 3.05E+01 < 3.05E+01 < 1.81E+01 43 Table 3-4 Airborne Iodine 1-131[10-1 pCi/m 3]page 4 of 4 Period Ending 07/03/13 07/09/13 07/16/13 07/24/13 07/31/13 08/06/13 08/14/13 08/20/13 08/27/13 09/03/13 09/10/13 09/17/13 09/24/13 10/02/13 10/08/13 10/16/13 10/22/13 10/30/13 11/05/13 11/13/13 11/20/13 11/26/13 12/03/13 12/11/13 12/17/13 12/23/13 Statioi 21 n 3.81E+01 1.57E+01 2.62E+01 2.96E+01 6.64E+01 3.55E+01 3.37E+01 3.02E+01 3.73E+01 4.40E+01 3.27E+01 4.09E+01 4.60E+01 3.67E+01 3.06E+01 4.23E+01 6.46E+01 2.55E+01 3.70E+01 4.40E+01 5.02E+01 4.72E+01 4.68E+01 3.30E+01 6.73E+01 3.04E+01 Station 3822" 3.81E+01< 3.80E+01< 2.62E+01< 1.24E+01< 6.64E+01< 3.60E+01< 3.37E+01< 2.73E+01< 3.73E+01< 4.09E+01< 3.41E+01< 4.35E+01< 4.72E+01< 3.66E+01< 3.02E+01< 4.23E+01" 6.46E+01" 2.55E+01" 3.70E+01< 4.40E+01< 5.02E+01< 4.72E+01< 4.68E+01< 3.30E+01< 6.54E+01< 3.04E+01!Station 23 3.21E+01 3.00E+01 3.94E+01 2.632+01 5.34E+01 1.51E+01 2.90E+01 2.74E+01 3.72E+01 4.01E+01 3.39E+01 4.15E+01 5.25E+01 4.30E+01 3.15E+01 4.87E+01 5.08E+01 3.20E+01 4.50E+01 5.65E+01 4.62E+01 6.71E+01 4.34E+01 5.37E+01 6.55E+01 6.91E+01 Station S 24*" 3.22E+01< 3.11E2+01< 3.94E+01< 2.64E+01< 5.33E+01< 3.60E+01< 2.90E+01< 1.15E+01< 3.60E+01< 4.12E+01< 3.40E+01< 4.02E+01< 5.26E+01< 4.29E+01< 3.23E+01< 4.73E+01" 5.26E+01< 3.11E+01< 4.69E+01< 5.63E+01< 4.62E+01< 6.69E+01< 4.35E+01< 3.83E+01< 6.55E+01< 6.87E+01 Station 01A 3.31E+01 2.98E+01 3.94E+01 2.63E+01 5.34E+01 3.60E+01 2.90E+01 2.74E+01 3.73E+01 1.67E+01 3.38E+01 4.18E+01 5.29E+01 4.27E+01 3.10E+01 4.92E+01 5.02E+01 3.21E+01 4.48E+01 5.65E+01 4.62E+01 6.71E+01 4.34E+01 3.83E+01 6.50E+01 6.91E+01 Station I 05A< 3.22E+01< 3.06E+01< 3.93E+01< 2.63E+01< 5.39E+01< 3.60E+01< 2.90E+01< 2.74E+01< 3.65E+01< 4.07E+01< 1.42E+01< 1.71E+01" 5.33E+01< 4.29E+01< 3.19E+01< 4.79E+01< 5.18E+01< 3.15E+01< 4.61E+01< 5.65E+01< 4.62E+01" 6.71E+01" 4.34E+01" 3.83E+01< 2.72E+01< 6.90E+01!* Control Station 44 Table 3-5 Airborne Particulate Gamma Spectra[Oi 0. pCi/m3]'page 1 of 2 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24**Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24**Cs-134* I Cs-1 37* 1 Be-7 Quarter 1 1 Be-7 1.12E+02 1.45E+02 9.96E+01 9.16E+01 1.02E+02 9.02E+01 1.07E+02 1.24E+02 1.11E+02 1.11E+02 1.31E+02 1.38E+02 1.01E+02 1.15E+02 1.46E+02 1.52E+02 1.80E+02 1.61 E+02 1.77E+02 1.41 E+02 1.61 E+02 1.35E+02 1.16E+02 1.39E+02 1.47E+02 1.40E+02+1- 2.95E+01+/- 3.35E+01+/- 2.53E+01+1- 3.83E+01+1- 3.86E+01+1- 3.47E+01+1- 4.40E+01+1- 3.77E+01+1- 3.49E+01+1 3.10E+01+1- 2.84E+01+/- 2.82E+01+/- 2.75E+01 Be-7+/- 2.73E+01+- 2.97E+01+- 4.08E+01+1 3.43E+01+/- 3.51E+01+/- 4.22E+01+/- 2.66E+01+/- 2.39E+01+/- 3.78E+01+/- 3.35E+01+/- 2.96E+01+/- 3.26E+01+/- 3.31E+01< 1.50E+00.< 1.60E+00< 1.38E+00< 2.08E+00< 1.56E+00< 1.63E+00< 2.24E+00< 2.31E+00< 1.70E+00< 1.44E+00< 1.35E+00< 1.62E+00" 1.35E+00< 1.41E+00< 1.15E+00< 1.05E+00< 1.86E+00< 1.64E+00< 1.43E+00< 1.93E+00< 1.94E+00< 1.12E+00< 1.02E+00< 1.32E+00< 1.36E+00< 8.39E-01 Quarter 2 I Cs-134 I Cs-137*< 1.21E+00 < 8.69E-01" 1.57E+00 < 1.54E+00" 1.61E+00 ..* .1.41E+00< 1.39E+00 .< 1.13E+00< 1.49E+00, < 1.45E+00< 2.06E+00 < 2.06E+00< 1.38E+00 < 1.42E+00 5 1.14E+00 < 1.13E+00< 1.33E+00 < 9.74E-01< 1.43E+00 < 1.02E+00< 1.38E+00 < 1.21E+00< 1.03E+00 < 1.04E+00< 1.79E+00 < 1.47E+00!Sr-89< 5.39E+00< 5.31E+00< 6.25E+00< 6.48E+00< 6.39E+00< 6.69E+00< 5.96E+00" 5.69E+00" 5.82E+00" 6.00E+00" 5.56E+00< 5.55E+00< 6.62E+00 I Sr-90< 1.71E+00< 2.11E+00" 2.13E+00< 2.23E+00< 2.15E+00< 2.17E+00< 1.69E+00" 1.73E+00< 1.97E+00< 2.19E+00< 2.22E+00< 2.15E+00< 2.25E+00!* LLD identified in the ODCM** Control Station 45 Table 3-5 Airborne Particulate Gamma Spectra[10-3 pCi/m3]page 2 of 2 Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24**MEAN Sampling Location 01 01A 02 03 04 05 05A 06 07 21 22 23 24*Be-7 1.05E+02 +1- 2.40E+01 1.04E+02 +/- 2.09E+01 1.52E+02 +/- 2.43E+01 1.43E+02 +1- 3.38E+01 1.32E+02 +/- 3.07E+01 1.36E+02 +/- 2.88E+01 1.11E+02 +/- 2.65E+01 1.09E+02 +/- 3.31E+01 1.63E+02 +/- 3.45E+01 1.67E+02 +/- 3.18E+01 1.22E+02 +/- 2.98E+01 1.14E+02 +/- 2.57E+01 1.09E+02 +/- 2.61E+01!Cs-134*< 1.22E+00< 1.06E+00< 1.67E+00< 1.58E+00< 1.24E+00< 1.14E+00< 1.25E+00" 1.70E+00< 1.39E+00< 1.73E+00< 2.06E+00< 1.06E+00< 9.69E-01 Quarter 3 I .Cs-137*< 1.22E+00< 1.09E+00!< 1.39E+00< 1.38E+00< 9.80E-01< 1.17E+00< 8.87E-01< 1.86E+00< 1.20E+00< 1.65E+00< 1.44E÷00< 1.25E+00< 1.12E+00 Be-7 1.11E+02 +1 1.99E+01 1.03E+02 +/- 2.39E+01 1.26E+02 +/- 3.04E+01 1.01E+02 +/- 2.20E+01 1.36E+02 +/- 3.78E+01 1.09E+02 +/- 2.15E+01 1.13E+02 +/- 3.18E+01 1.20E+02 +/- 2.83E+01 1.15E+02 +1- 2.53E+01 1.04E+02 +1 2.65E+01 1.02E+02 +/- 2.11E+01 1.30E+02 +/- 2.89E+01 1.18E+02 +/- 2.69E+01 Cs-134* Cs-137*< 1.05E+00 < 8.45E-01< 1.52E+00'
< 1.12E+00< 1.35E+00 < 1.38E+00< 1.33E+00 < 1.24E+00< 1.77E+00 < 1.57E+00" 1.44E+00 < 1.08E+00< 1.66E+00 < 1.34E+00< 1.52E+00 < 1.46E+00< 1.24E+00 < 8.56E-01< 1.81E+00 < 1.40E+00< 1.08E+00 < 9.81E-01" 1.54E+00 < 1.80E+00" 1.51E+00 < 1.28E+00 Mean of Ali Indicator Location: I MEAN Be-7 1.11E+02 +1- 2.52E+01 1.25E+02 +1" 2.70E+01 1.32E+02 +1- 3.02E+01 1.29E+02 +1- 3.21E+01 1.33E+02 +1" 3.56E+01 1.28E+02 +1- 3.18E+01 1.18E+02 +1- 3.22E+01 1.29E+02 +1- 3.08E+01 1.31E+02 +1- 3.31E+01 1.25E+02 +1- 3.07E+01 1.24E+02 +1" 2.72E+01 1.32E+02 +1- 2.89E+01 1.17E+02 + 2- 2.84E+01 1.26E+02 +- 3.04E+01 Quarter 4!* LLD Identified in ODCM** Control Station 46 Table 3-6 Soil[pCi/kg]Sample Date 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 Station I 01 02 03 04 05 05A 06 07 21 22 23 24*Acivity Conc 6.58E+01 2.32E+01 2.76E+02-6.50E+01-1.75E+01-2.77E+01 2.93E+02 1.05E+02 9.02E+01-1.39E+02-9.98E+00 1.22E+02 Sr-89 2 Sigma 2.420E+02 2.71 E+02 3.35E+02 2.27E+02 2.54E+02 2.87E+01 3.23E+02 3.OOE+02 2.89E+02 2.21 E+02 2.63E+02 2.97E+02 MDC 4.59E+02 5.42E+02 5.56E+02 5.02E+02 5.28E+02 5.99E+02 5.26E+02 5.60E+02 5.46E+02 5.28E+02 5.44E+02 5.52E+02 Acivity Conc-8.21E-01 1.93E+01 2.14E+01-1.04E+01 1 .68E+01-1.24E+01 6.08E+00-9.92E+00 2.84E+01 1.83E+00 2.16E+01 1.14E+01 I Sr-90.2 Sigma 1 .59E+01 1.67E+01 2.29E+01, 2.09E+01 1.65E+01 1.91E+01 1.99E+01 1.91 E+01 2.03E+01 1.85E+01 1.64E+01 1.78E+01 MDC 2.62E+01 2.63E+01 3.64E+01 3.51 E+01 2.62E+01 3.21 E+01 3.24E+01 3.20E+01 3.19E+01 3.03E+01 2.58E+01 2.87E+01 Acivity Conc 2.60E+04 1.10E+04 6.57E+03 6.32E+03 1.76E+04 1.07E+04 1.03E+04 7.31 E+03 2.16E+04 2.14E+04 2.90E+04 4.66E+03 1.53E+04 4.66E+03 I K-40 2 Sigma 1.18E+03 1.41E+03 1.11E+03 7.58E+02 1.56E+03 1.05E+03 1.15E+03 1.09E+03 1.61E+03 1.62E+03 1.62E+03 1.12E+03 MDC 3.09E+02 5.90E+02 6.59E+02 3.81 E+02 4.90E+02 3.96E+02 4.25E+02 4.96E+02 4.24E+02 5.35E+02 5.01 E+02 7.67E+02 Acivity Conc-2.20E+01-2.36E+01-9.23E+00-1.57E+01 9.16E+00-8.81 E-01-5.22E+01-2.35E+01-1.82E+01 5.01 E+00 3.OOE+01-5.25E+01 I Cs- 134 2 Sigma 2.69E+01 4.65E+01 5.21E+01 3.19E+01 4.36E+01 3.03E+01 5.17E+01 4.20E+01 3.63E+01 4.55E+01 4.03E+01 5.73E+01 MDC 3.64E+01 6.30E+01 7.04E+01 4.29E+01 6.39E+01 4.38E+01 6.71E+01 5.59E+01 4.87E+01 6.57E+01 5.99E+01 7.51 E+01 MEAN Indicator Control*Control Station Sample Date 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 7/16/13 Station I Cs-137 Ra-226 Th-228 Th-232 01 02 03 04 05 05A 06 07 21 22 23 24*Acivity Conc 2.78E+01 5.39E+02 2.65E+02 2.79E+02 1.70E+02 1.35E+02 1.67E+02 2.13E+02 9.31E+01 1.07E+02 1.21E+02 3.29E+02 2 Sigma 2.89E+01 9.62E+01 9.78E+01 5.93E+01 6.46E+01 7.04E+01 9.33E+01 6.18E+01 5.65E+01 5.35E+01 5.11E+01 1.02E+02 MDC 5.06E+01 6.75E+01 7.28E+01 4.78E+01 7.50E+01 4.78E+01 7.08E+01 6.73E+01 4.83E+01 8.09E+01 7.68E+01 8.19E+01 Acivit' Conc 1.99E+03 9.14E+02 1.79E+03 2.32E+03 3.06E+03 2.18E+03 3.26E+03 2.08E+03 1.57E+03 3.60E+03 2.76E+03 3.39E+03 2.46E+03 3.39E+03 2 Sigma 8.58 E+02 1.27E+03 1 .57E+03 1.26E+03 1.44E+03 8.82E+02 1.41E+03 1.50E+03 9.64E+02 1.19E+03 1.43E+03 2.06E+03 MDC 9.03E+02 1.24E+03 1.52E+03 9.56E+02 1.41E+03 8.57E+02 1.80E+03 1.62E+03 1.11E+03 1.47E+03 1.30E+03 1.72E+03 Acivity Conc 1.13E+03 5.04E+02 8.03E+02 8.16E+02 1.66E+03 8.24E+02 2.27E+03 1.42E+03 1.09E+03 2.23E+03 1.71 E+03 1.71E+03 1.31E+03 1.71 E+03 2 Sigma 7.39E+01 8.73E+01 1.22E+02 7.72E+01 1.21 E+02 7.70E+01 1.30E+02 1.08E+02 9.41 E+01 1.43E+02 1.14E+02 1.57E+02 MDC 7.35E+01 1.07E+02 1.24E+02 7.25E+01 1.08E+02 7.09E+01 1.33E+02 1.18E+02 8.88E+01 1.11E+02 9.77E+01 1.37E+02 Acivity Conc 1.17E+03 5.30E+02 8.78E+02 7.44E+02 1.41E+03 7.34E+02 2.20E+03 1.24E+03 1.03E+03 1.82E+03 1.35E+03 1.34E+03 1.19E+03 1.34E+03 2 Sigma 1.10E+02 2.34E+02 1.98E+02 1.32E+02 2.11E+02 1.19E+02 1.79E+02 2.03E+02 1.56E+02 2.54E+02 1.92E+02 2.02E+02 MDC 1.60E+02 4.33E+02 2.48E+02 1.62E+02 5.90E+02 1.57E+02 2.09E+02 4.63E+02 1.94E+02 6.16E+02 4.73E+02 2.91E+02 Indicator Control*Control Station 2.09E+02 3.29E+02 47 Table 3-7 Precipitation Gross Beta[pCi/L]page 1 of 2 Sampling Date I I Rainfall I (inches)Gross Beta H-3 01/29/13 02/27/13 03/26/13 04/30/13 05/28/13 06/25/13 07/31/13 08/27/13 09/24/13 10/30/13 11/26/13 12/31/13 Mean 3.25E+00 5.79E+00< 1.74E+00 2.27E+00 6.43E+00 2.73E+00 1.96E+01 2.63E+00 9.63E+00<1.99E+00 5.41 E+00<1.57E+00 6.42E+00+/- 1.42E+00 1.50E+00<8.65E+01 1.17E+00 1.39E+00 1.48E+00 2.11 E+00 1.37E+00 1.70E+00<7.21 E+02<8.75E+02<8.54E+02<6.84E+02<7.26E+02<8.09E+02* <7.91 E+02<9.35E+02<7.96E+02<8.54E+02<8.31 E+02 3.42 2.48 3.00 3.50 2.20 7.08 4.23 5.21 1.72 3.05 1.03 0.00 36.92+/- 1.60E+00+/- 1.58E+00 Total 48 Table 3-7 Precipitation Gamma Spectra[pCi/L]page 2 of 2 Sampling Location Be-7 Mn-54 Fe-59 Co-58 Co-60 01A 06/25/13 12/31/13 OIA 06/25/13 12/31/13 01A 06/25/13 12/31/13 6.60E+01 +/-Zn-65 3.57E+01 3.68E+01< 9.50E-01< 1.94E+00 Zr-95< 9.76E+00< 1.79E+01 Nb-95< 2.37E+00< 4.80E+00 nI Cs-134< 7.96E-01< 1.51 E+00 Cs-137 Ba-140 2.25E+00 3.94E+00" 4.92E+00< 8.84E+00 nI La- 140< 3.19E+00< 5.37E+00 1-131< 8.46E-01" 1.67E+00 Th-228 8.22E-01 1.75E+00 2.30E+03 2.92E+03 7.89E+02 9.15E+02 4.07E+04 3.71 E+04 1.60E+00 3.87E+00 49 Table 3-8 Milk Gamma Spectra & Strontium[pCi/L]page 1 of 1 Sampling Date I K-40 I Sr-89 I Sr-90 01/16/13 1.23E+03 +/- 1.45E+02 [a] [a]02/19/13 1.39E+03 +/- 8.80E+01 [a] [a]03/19/13 1.27E+03 +/- 1.11E+02 < 3.51E+00 < 1.84E+00 04/17/13 1.22E+03 +/- 1.42E+02 [a] [a]05/21/13 1.32E+03 +I- 1.33E+02 [a] [a]06/18/13 1.71E+03 +/- 1.86E+02 < 3.95E+00 < 1.63E+00 07/16/13 1.27E+03 +/- 1.41E+02 [a] [a]08/20/13 1.39E+03 +/- 1.08E+02 [a] [a]09/17/13 1.32E+03 +/- 1.62E+02 < 2.97E+00 < 8.30E-01 10/16/13 1.48E+03 +/- 1.09E+02 [a] [a]11/20/13 1.36E+03 +/- 1.60E+02 [a] [a]12/17/13 1.29E+03 +/- 1.49E+02 < 3.77E+00 < 1.03E+00 Sta. Mean 1.35E+03 +/- 1.36E+02* LLD identified in ODCM[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.Station 12A 1-131* I Cs-134* I Cs-137* Ba-140 I La-140*< 9.22E-01 < 6.33E+00 < 6.83E+00 < 4.42E+01 < 1.27E+01< 6.60E-01 < 3.52E+00 < 4.40E+00 < 1.96E+01 < 5.52E+00< 4.84E-01 < 4.42E+00 < 5.56E+00 < 2.34E+01 < 7.43E+00< 9.76E-01 < 6.06E+00 < 7.27E+00 < 4.52E+01 < 1.13E+01< 8.42E-01 < 6.11E+00 < 7.14E+00 < 5.06E+01 < 1.36E+01< 8.57E-01 < 6.53E+00 < 8.11E+00 < 3.96E+01 < 1.44E+01" 6.07E-01 < 5.66E+00 < 5.77E+00 < 3.05E+01 < 1.03E+01" 8.93E-01 < 3.72E+00 < 4.24E+00 < 3.15E+01 < 8.34E+00" 5.71E-01 < 5.96E+00 < 6.44E+00 < 3.23E+01 < 1.05E+01" 7.53E-01 < 3.68E+00 < 4.09E+00 < 3.54E+01 < 8.13E+00" 7.15E-01 < 6.46E+00 < 7.42E+00 < 5.26E+01 < 1.32E+01< 5.38E-01 < 4.20E+00 < 5.70E+00 < 5.OOE+01 < 1.42E+01 50 Table 3-9 Food and Vegetation Gamma Spectra[pCi/kg]Sampling Sampling Location Date I Be-7 I K-40 I 1-13* I Cs-134* I Cs-137*04/09/13 1.12E+03 +1- 1.91E+01 7.87E+03 +/- 4.68E+02 < 2.87E+01 < 1.71E+01 < 1.90E+01 14B 05/14/13 5.79E+02 +/- 2.53E+02 5.33E+03 +/, 4.90E+02 < 4.10E+01 < 1.86E+01 < 2.01E+01 06/11/13 1.56E+03 +/- 2.32E+02 5.22E+03 +/- 4.27E+02 < 1.98E+01 < 1.47E+01 < 1.95E+01 07/09/13 1.62E+03 +/- 2.89E+02 4.93E+03 +/- 5.17E+02 < 5.74E+01 < 2.44E+01 < 2.73E+01 08/14/13 5.64E+02 +/- 2.18E+02 8.30E+03 +/- 5.60E+02 < 2.49E+01 < 2.34E+01 < 2.46E+01 09/10/13 1.79E+03 +/- 6.51E+02 4.91E+03 +/- 9.24E+02 < 4.53E+01 < 5.89E+01 < 5.96E+01 10/08/13 1.89E+03 +/- 5.02E+02 6.23E+03 +/- 8.41E+02 < 3.49E+01 < 4.24E+01 < 4.57E+01 Mean 1.30E+03 +/- 3.09E+02 6.11E+03 +/- 6.04E+02 +/- +/- +/-Sampling Sampling Location Date I Be-7 I K-40 I 1-131" I Cs134* I Cs-137*15 04/09/13 1.45E+03 +/- 2.81E+02 7.11E+03 +/- 6.15E+02 < 3.51E+01 < 2.39E+01 < 2.90E+01 05/14/13 3.68E+02 +/- 2.15E+02 5.34E+03 +/- 6.79E+02 < 3.63E+01 < 3.19E+01 < 3.19E+01 06/11/13 1.54E+03 +/- 3.26E+02 6.13E+03 +/- 7.40E+02 < 1.96E+01 < 2.84E+01 < 3.53E+01 07/09/13 1.25E+03 +/- 2.97E+02 4.92E+03 +/- 6.46E+02 < 4.72E+01 < 2.39E+01 < 2.69E+01 08/14/13 1.47E+03 +/- 4.11E+02 6.74E+03 +/- 9.14E+02 < 2.81E+01 < 4.16E+01 < 4.69E+01 09/10/13 3.16E+03 +/- 4.77E+02 5.75E+03 +/- 7.63E+02 < 5.78E+01 < 4.74E+01 < 5.12E+01 10/08/13 1.30E+03 +/- 4.65E+02 6.45E+03 +/- 1.01E+03 < 3.75E+01 < 5.26E+01 < 4.69E+01 Mean 1.51 E+03 +/- 3.53E+02 6.06E+03 +/- 7.67E+02 +/- +/- +/-Sampling Sampling Location Date I Be-7 K-40 I 1-131 I Cs-134 I Cs_137*page 1 of 2 16-04/09/13 05/14/13 06/11/13 07/09/13 08/14/13 09/10/13 10/08/13 1.43E+03 +/-6.87E+02 +/-1.47E+03 +/-1.67E+03 +/-6.81E+02 +/-8.66E+02 +/-1.74E+02 2.06E+02 2.42E+02 2.94E+02 3.06E+02 5.28E+02 6.15E+02 6.30E+03 4.06E+03 5.62E+03 4.70E+03 1.04E+04 7.69E+03 3.97E+03 4.41 E+02 4.22E+02 5.30E+02 5.70E+02 1.10E+03 1.11E+03 8.22E+02 2.38E+01 4.21E+01 2.21E+01 3.57E+01 2.95E+01 5.86E+01 3.20E+01 1.71E+01 2.OOE+01 2.OOE+01 2.40E+01 4.65E+01 5.69E+01 3.55E+01 1.83E+01 2.05E+01 2.37E+01 2.91 E+01 4.98E+01 5.95E+01 3.85E+01 Mean* LLD identified in ODCM** Control Station 1.13E+03 +/- 3.38E+02 6.11E+03 +/- 7.14E+02+/-+/-+/-51 Table 3-9 Food and Vegetation Gamma Spectra[pCi/kg]page 2 of 2 Sampling Sampling Location Date Be-7-K-40 *1-131*Cs-134*Cs-137*23 04/09/13 05/14/13 06/11/13 07/09/13 08/14/13 09/10/13 10/08/13 1.57E+03 5.47E+02 9.45E+02 1.48E+03 2.22E+03 2.03E+03 1.26E+03 3.73E+02 2.75E+02 2.52E+02 1.12E+02 3.83E+02 4.35E+02 5.95E+02 6.77E+03 4.54E+03 5.25E+03 4.98E+03 8.80E+03 2.68E+03 5.75E+03+7-8.02E+02 6.24E+02 5.80E+02 2.18E+02 8.90E+02 7.42E+02 1.03E+03 2.70E+01 4.16E+01 1.87E+01 5.57E+01 2.67E+01 5.84E+01 3.72E+01 3.57E+01 2.77E+01 2.19E+01 9.73E+00 4.24E+01 4.27E+01 5.85E+01 4.03E+01 3.09E+01 2.72E+01 1.06E+01 4.86E+01 4.37E+01 6.91E+01 Mean Sampling Sampling Location Date 1.44E+03 +/- 3.46E+02 Be-7 5.54E+03 +/- 6.98E+02 K-40+/-+/-+/-1-131*Cs-134*Cs-137*26 04/09/13 05/14/13 06/11/13 07/09/13 08/14/13 09/10/13 10/08/13 Mean 2.23E+03 1.49E+03 1.43E+03 1.60E+03 1.21E+03 1.30E+03 2.93E+03 1.74E+03 4.19E+02 2.95E+02 3.38E+02 2.60E+02 2.64E+02 5.25E+02 6.69E+02 3.96E+02 8.93E+03 6.63E+03 5.23E+03 4.30E+03 4.41 E+03 2.84E+03 4.83E+03 5.31E+03 7.60E+02 7.30E+02 6.63E+02 5.72E+02 5.20E+02 7.90E+02 8.80E+02 7.02E+02 2.62E+01 3.51E+01 2.11E+01 4.16E+01 2.57E+01 4.01 E+01 3.34E+01 4.67E+01 3.15E+01 3.19E+01 2.09E+01 2.76E+01 5.38E+01 5.76E+01 4.92E+01 3.37E+01 3.57E+01 2.49E+01 3.OOE+01 5.84E+01 5.96E+01 1.50E+03 +/- 3.51 E+02 5.76E+03 +/- 6.93E+02 Indicator locations* LLD identified in ODCM 52 Table 3-10 Well Water Gamma Spectra, Strontium, and Tri Sampling Date[pCi/L]Mn-54 page tium 1 of 1 Station 01A Fe-59 Co-58 Co-60 Zn-65 H-3 Sr-89 Sr-90 03/26/13 06/25/13 09/24/13 12/31/13" 8.75E+02" 7.25E+02" 9.45E+02< 8.30E+02[a] [a]< 4.11E+00 < 7.72E-01[a] [a][a] [a]< 5.15E+00 < 1.12E+01< 2.91E+00 < 6.20E+00< 4.48E+00 < 1.13E+01< 6.60E-01 < 1.30E+00< 4.54E+00< 3.40E+00< 5.40E+00" 6.26E-01< 5.17E+00 < 8.77E+00< 2.62E+00 < 4.99E+00* 4.51 E+00 < 9.30E+00< 5.87E-01 < 1.29E+00 Sampling Date Zr-95 I Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 03/26/13 06/25/13 09/24/13 12/31/13< 8.99E+00< 5.27E+00< 8.64E+00< 9.82E-01< 7.07E+00" 3.23E+00< 5.73E+00" 6.58E-01< 9.20E-01 < 4.40E+00 < 5.53E+00 < 2.63E+01 < 7.90E+00< 6.92E-01 < 2.79E+00 < 3.03E+00 < 1.99E+01 < 5.69E+00< 6.OOE-01 < 4.47E+00 < 5.45E+00 < 2.68E+01 < 7.74E+00< 1.39E+00 < 6.04E-01 < 7.04E-01 < 4.03E+00 < 1.15E+00[a] Sr-89/90 analyses performed on the second quarter sample.53 Table 3-11 River Water Gamma Spectra, Strontium, and Tritium[pCi/L]Sampling Date 01/15/13 02/12/13 03/11/13 04/16/13 05/13/13 06/10/13 07/14/13 08/12/13 09/16/13 10/14/13 11/12/13 12/17/13 MEAN Sampling Date 01/15/13 02/12/13 03/11/13 04/16/13 05/13/13 06/10/13 07/14/13 08/12/13 09/16/13 10/14/13 11/12/13 12/17/13 MEAN H-3[a][a]3.87E+03 +/-[a][a]4.33E+03 +/-[a][a]3.75E+03 +/-[a][a]4.09E+03 +/-4.01E+03 +/-Nb-95*Sr-89 7.92E+02 7.54E+02 7.44E+02 7.84E+02 7.69E+02 4.56E+00 8.93E+00 2.82E+00 9.29E+00 8.94E+00 7.59E+00 6.36E+00 9.23E+00 3.27E+00 3.90E+00 3.14E+00 3.19E+00[b][b)[b][b][b][b][b][b][b][b][151 4.76E+00 Zr-95*< 2.62E+00< 4.28E+00< 1.66E+00< 5.84E+00< 5.66E+00" 4.48E+00< 4.09E+00" 6.43E+00< 1.90E+00" 2.22E+00" 2.05E+00< 1.80E+00 Sr-90[b][b][b][b][b]< 8.34E-01[b][b][b][b][b][b]1-131"< 9.31E-01* 6.89E-01* 7.85E-01* 7.35E-01* 5.31E-01< 3.91E-01< 6.48E-01< 5.97E-01< 5.81E-01< 4.85E-01< 5.29E-01* 4.02E-01 Mn-54*< 2.25E+00< 4.39E+00< 1.49E+00< 4.96E+00< 5.70E+00< 4.09E+00 4.46E+00< 6.18E+00< 1.64E+00< 1.93E+00" 1.65E+00< 1.46E+00 Cs-134*< 2.28E+00< 4.52E+00" 1.52E+00" 5.32E+00" 4.59E+00" 3.68E+00" 3.67E+00< 4.66E+00< 1.57E+00< 1.76E+00" 1.55E+00" 1.43E+00 Fe-59*6.16E+00 9.52E+00 3.29E+00 1.07E+01 1.31E+01 7.68E+00 7.24E+00 1.42E+01 4.04E+00 4.90E+00 4.36E+00 3.81 E+00+/-Co-58*2.58E+00 4.54E+00 1.56E+00 5.28E+00 4.95E+00 3.93E+00 4.01 E+00 5.36E+00 1.62E+00 2.08E+00 2.04E+00 1.72E+00+/-Co-60*< 2.19E+00< 4.05E+00< 1.58E+00< 4.91 E+00< 3.96E+00< 4.31 E+00< 3.70E+00< 5.68E+00< 1.61E+00< 1.96E+00" 1.66E+00< 1.59E+00 La-140*" 5.97E+00< 7.58E+00< 2.56E+00" 7.11E+00< 1.14E+01< 5.89E+00< 6.92E+00< 1.49E+01< 4.09E+00< 5.82E+00" 6.43E+00" 4.87E+00 page 1 of 1 Station 11 Zn-65*< 4.93E+0< 8.50E+0< 2.89E+0< 1.07E+0< 1.OOE+0< 6.12E+0< 8.97E+0< 1.14E+0< 3.47E+0< 3.98E+0< 3.18E+0< 3.16E+0 Cs-137*< 2.55E+00< 5.28E+00" 1.62E+00< 5.24E+00" 5.94E+00" 3.86E+00< 4.51E+00" 5.90E+00" 1.78E+00" 1.95E+00" 1.78E+00" 1.66E+00 Ba-140*< 1.75E+01< 2.74E+01< 1.01E+01< 4.16E+01< 2.81 E+01" 2.07E+01" 2.34E+01" 4.23E+01" 1.24E+01< 1.78E+01< 1.95E+01< 1.40E+01* LLD identified in ODCM[a] Tritium analyses on quarterly composite.
[b] Sr-89/90 performed annually on 2 nd quarter composite sample.54 Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium page 1 of 2 Sampling Date 01/15/13 02/12/13 03/11/13 04/16/13 05/13/13 06/10/13 07/14/13 08/12/13 09/16/13 10/14/13 11/12/13 12/17/13 Mean H-3*[a][a]4.37E+03 +/- 8.23E+02[a]4.OOE+03 +/- 7.42E+02[a][a]3.85E+03 +/- 7.54E+02[a][a]4.08E+03 +/- 7.79E+02 4.08E+03 +/- 7.75E+02 Sampling Date 01/15/13 02/12/13 03/11/13 04/16/13 05/13/13 06/10/13 07/14/13 08/12/13 09/16/13 10/14/13 11/12/13 12/17/13 Mean LLD identified in ODCM Sr-89[b][b][b][b][b]< 4.27E+00[b][b][b][b][b][b]Nb-95*" 1.41E+00< 4.17E+00< 1.70E+00< 4.35E+00" 3.24E+00< 3.92E+00< 3.31 E+00" 5.49E+00" 2.55E+00< 1.90E+00< 2.07E+00< 1.80E+00 Sr-90[b][b][b][b][b]< 7.82E-01[b][b][b][b][b][b]1-131*< 8.08E-01" 7.10E-01" 7.33E-01< 5.99E-01< 6.30E-01< 4.59E-01< 6.20E-01< 7.39E-01" 5.63E-01" 4.48E-01< 5.98E-01< 4.25E-01[pCi/L]Mn-54*< 1.19E+00< 3.53E+00< 1.55E+00< 3.58E+00< 3.61 E+00< 3.34E+00< 4.32E+00< 4.76E+00< 2.32E+00 1.56E+00< 1.87E+00< 1.56E+00 Fe-59*< 2.93E+00< 8.99E+00" 3.60E+00< 8.84E+00" 7.85E+00" 7.19E+00" 7.84E+00" 1.32E+01" 5.89E+00" 4.14E+00" 4.85E+00< 3.94E+00 Cs-137"" 1.35E+00" 4.24E+00" 1.66E+00" 3.90E+00" 3.50E+00" 3.65E+00" 3.84E+00< 4.97E+00< 2.28E+00< 1.72E+00< 1.81E+00< 1.73E+00 Co-58"< 1.29E+00< 3.96E+00< 1.57E+00< 4.65E+00< 3.57E+00< 3.88E+00< 4.04E+00< 4.56E+00< 2.55E+00< 1.75E+00< 2.09E+00< 1.69E+00 Ba-140*< 9.26E+00< 2.16E+01" 9.06E+00" 3.21E+01" 1.80E+01" 1.65E+01" 1.79E+01< 3.14E+01< 1.60E+01< 1.59E+01< 2.10E+01< 1.48E+01 Co-60"< 1.21E+00< 3.48E+00< 1.75E+00" 3.87E+00" 3.68E+00< 3.69E+00< 4.04E+00" 4.90E+00" 2.50E+00< 1.61E+00< 1.78E+00< 1.64E+00 La-140*< 2.87E+00* 7.40E+00* 3.13E+00* 7.77E+00< 5.31 E+00* 4.49E+00< 6.35E+00< 1.16E+01< 5.51 E+00< 4.59E+00< 6.51 E+00< 4.20E+00 Station 08 Zn-65*< 2.61E+00< 8.07E+00< 3.25E+00< 8.54E+00< 7.48E+00< 7.92E+00< 7.15E+00< 9.33E+00< 4.68E+00< 3.27E+00< 3.79E+00< 3.13E+00 Zr-95" 2.44E+00 7.16E+00 2.84E+00 8.18E+00 6.58E+00 6.32E+00 5.68E+00 9.79E+00 4.46E+00 3.18E+00 3.57E+00 3.17E+00 Cs-134*" 1.14E+00< 3.78E+00< 1.51E+00" 3.65E+00" 3.39E+00" 3.34E+00" 3.53E+00" 4.60E+00" 2.13E+00< 1.58E+00< 1.74E+00< 1.55E+00[a] Tritium analyses on quarterly composite.
[b] Sr-89/90 performed annually on 2 nd quarter composite sample.55 Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium[pCi/L]page 2 of 2 Sampling Date 01/15/13 02/12/13 03/11/13 04/16/13 05/13/13 06/10/13 07/14/13 08/12/13 09/16/13 10/14/13 11/12/13 12/17/13 Mean Sampling Date 01/15/13 02/12/13 03/11/13 04/16/13 05/13/13 06/10/13 07/14/13 08/12/13 09/16/13 10/14/13 11/12/13 12/17/13 Mean LLD identified in ODCM H-3*[a][a]< 8.83E+02[a]< 8.02E+02[a][a]< 7.67E+02[a][a]< 8.12E+02+/-Zr-95*< 3.10E+00< 9.99E+00< 2.70E+00< 8.68E+00< 6.04E+00< 7.37E+00< 6.32E+00< 8.47E+00< 3.57E+00< 3.OOE+00< 3.66E+00< 4.06E+00+1-Sr-89[b][b][b][b][b]< 3.75E+00[b][bi[b][b][b][b]+1-Nb-95*< 1.67E+00< 5.97E+00< 1.66E+00" 4.84E+00< 3.70E+00< 3.60E+00< 3.55E+00< 4.74E+00< 2.12E+00< 1.63E+00< 2.20E+00< 2.34E+00+/-Sr-90[b][b][b][b][b]< 8.04E-01[b][b][b][b][b][b]+/-1-131*" 9.23E-01< 7.75E-01< 5.76E-01< 7.64E-01< 5.62E-01< 4.44E-01< 6.32E-01< 7.70E-01< 5.51E-01< 3.74E-01< 6.44E-01< 4.32E-01+1-Mn-54*< 1.47E+00< 5.67E+00< 1.39E+00< 3.70E+00< 3.77E+00" 3.57E+00< 3.10E+00* < 4.26E+00 ,< 1.94E+00< 1.48E+00< 1.76E+00< 1.91E+00+1-Cs-i!34"* .1.56E+00< 6.07E+00< 1.44E+00" 4.50E+00" 3.55E+00" 3.84E+00" 3.09E+00" 4.OOE+00< 1.93E+00" 1.39E+00" 1.68E+00 1.79E+00+1-Fe-59*< 3.49E+00< 1.19E+01< 3.24E+00< 1.05E+01< 6.74E+00< 6.92E+00< 7.30E+00< 9.23E+00< 4.35E+00< 3.32E+00< 4.61E+00< 5.23E+00+1-Cs-137"< 1.60E+00< 6.36E+00< 1.57E+00< 4.16E+00< 3.95E+00< 3.84E+00" 3.99E+00< 4.44E+00" 2.05E+00" 1.57E+00< 1.87E+00< 2.05E+00 Co-58"< 1.60E+00< 6.60E+00< 1.52E+00< 4.53E+00< 3.34E+00< 4.03E+00< 3.27E+00< 3.80E+00< 2.05E+00< 1.55E+00" 2.03E+00" 2.30E+00+/-Ba-140*< 1.19E+01< 3.38E+01" 9.21E+00" 3.41E+01< 1.80E+01" 1.92E+01" 1.88E+01" 3.74E+01< 1.51E+00" 1.41E+01< 2.07E+01< 1.73E+01+1-Co-60"< 1.60E+00< 6.03E+00< 1.36E+00< 4.25E+00< 3.74E+00< 3.78E+00< 3.14E+00< 4.60E+00< 1.81E+00" 1.43E+00< 1.89E+00< 2.15E+00+1-La-140*< 3.57E+00< 1.43E+01< 2.62E+00" 7.94E+00< 6.62E+00< 4.78E+00< 5.26E+00< 1.27E+01< 3.97E+00" 4.46E+00< 6.29E+00" 5.83E+00+1-Station 09A Zn-65*< 3.00E+00< 1.10E+01< 2.75E+00< 9.35E+00< 7.24E+00< 8.33E+00< 6.34E+00< 8.82E+00< 3.62E+00< 2.83E+00< 3.59E+00< 3.93E+00+1-[a] Tritium analyses on quarterly composite.
[b] Sr-89/90 performed annually on 2 nd quarter composite sample.56 Table 3-13 Sediment Silt Gamma Spectra, and Strontium[pCi/Kg]page Sample 1 of 1 Date I Sr-89 Sr-90 I K-40 Cs-134 I Cs-137" 4/22/2013 Station 08 [a] [a] 7.30E+03 +/- 9.19E+02 < 4.07E+01 < 4.50E+01 Station 09A** [a] [a] 1.25E+04 +/- 1.31E+03 < 5.42E+01 < 6.49E+01 Station 11 [a] [a] 1.58E+04 +I- 1.62E+03 < 8.85E+01 < 8.83E+01 Ra-226 I Th-228 I Th-2 2 I 4/22/2013 Station 08 1.82E+03 +/- 8.38E+02 9.44E+02 +/- 7.81E+01 8.31E+02 +/- 1.09E+02 Station 09A** 2.35E+03 +/- 8.61E+02 5.48E+02 +/- 9.39E+01 7.31E+02 +/- 1.27E+02 Station 11 2.54E+03 +/- 1.65E+03 1.76E+03 +/- 1.97E+02 1.31E+03 +/- 1.97E+02 Sample Date I Sr-89 Sr-90 ,K-40 I Cs-134 I Cs-137" 10/14/2013 Station 08 < 4.66E+02 < 2.79E+01 2.34E+03 +/- 7.35E+02 < 4.93E+01 < 6.05E+01 Station 09A** < 3.25E+02 < 2.61E+01 1.20E+04 +/- 1.17E+03 < 4.68E+01 < 5.74E+01 Station 11 < 4.05E+02 < 3.67E+01 1.60E+04 +/- 1.23E+03 < 4.99E+01 < 517E+01 Ra-226 I Th-228 I Th-232 I 101/2013 Station 08 2.02E+03 +I- 9.69E+02 7.80E+02 +/- 8.40E+01 6.97E+02 +/- 1.19E+02 Station 09A** 2.09E+03 +/- 1.20E+03 5.74E+02 +/- 8.04E+01 5.06E+02 +/- 1.23E+02 Station 11 2.15E+03 +/- 1.07E+03 1.37E+03 +/- 8.88E+01 1.22E+03 +/- 1.59E+02 MEAN I Sr-89 Sr-90 I K-40 I Cs-134 I Cs-137" Indicator
+/- +1- 1.04E+04 +/- 1.13E+03 +1- +/-Control+I-+/-1.23E+04 +/- 1.24E+03 +/- +/-Ra-226 I Th-228 I Th-232 I 2.13E+03 +/- 1.23E+03 1.21E+03 +/- 1.12E+02 1.01E+03 +/- 146E+02 2.22E+03 +I- 8.61E+02 5.61E+02 +/- 8.72E+01 6.19E+02 +I- 1.25E+02 Indicator Control* LLD identified in ODCM** Control Station[a] Sr-89/90 analyses performed annually.57 ý;
Table 3-14 Shoreline Soil Gamma Spectra, and Strontium[pCi/Kg]page 1 of 1 Sample I Date I Sr-89 Sr-90 I K-40 I Cs-134* I Cs-137*4/22/2013 Station 08 [a] [a] 1.36E+03 +/- 7.52E+02 6.OOE+01 < 6.83E+01 Ra-226 I Th-228 Th-232< 1.44E+03 8.09E+02 +/- 1.16E+02 7.05E+02 +/- 1.48E+02 Sample Date I Sr-89 Sr-90 K-40 I Cs-134" Cs-137*10/14/2013 Station 08< 3.34E+02 2.68E+01 3.94E+03 +/- 8.46E+02 5.29E+01 5.77E+01 Ra-226 Th-228 Th-232 1.52E+03 +/- 1.12E+03 8.29E+02 +/- 9.51 E+01 7.46E+02 +/- 1.45E+02 MEAN K-40 Sr-89 Sr-90 Cs-134*Cs- 137*+/-+/-2.65E+03 +/- 7.99E+02+/-+!-Ra-226 Th-228 Th-232 1.52E+03 +/- 1.44E+03 8.19E+02 +/- 1.06E+02 7.26E+02 +/- 1.47E+02* LLD identified in ODCM[a] Sr-89/90 analyses performed annually.58 Table 3-15 Fish page Gamma Spectra 1 of 1[pCi/Kg]Fish [a]Sampling Station 08 Date I K-40 I Mn-54* I Fe-59* I Co58* I Co-60" I Zn-65* I Cs-134* I Cs-137-04/24/13 2.65E+03 +/- 9.20E+02 < 5.75E+01 < 1.28E+02 < 5.92E+01 < 4.77E+01 < 9.95E+01 < 4.30E+01 < 5.56E+01 10/15/13 2.24E+03 +/- 1.06E+03 < 7.34E+01 < 1.73E+02 < 7.51E+01 < 6.84E+01 < 1.18E+02 < 6.44E+01 < 7.22E+01 Sampling Station 25**Date I K-40 I Mn-54* I Fe-59* I Co-58* I Co-60" Zn-65* I Cs-134* I Cs-137*04/23/13 2.75E+03 +/- 1.31E+03 < 7.19E+01 < 1.88E+02 < 1".08E+02
< 5.60E+01 < 1.63E+02 < 9.28E+01 < 8.41E+01 10/16/13 2.85E+03 +/- 8.46E+02 < 6.01E+01 < 1.49E+02 < 6.60E+01 < 6.75E+01 < 1.26E+02 < 5.40E+01 < 6.50E+01 catfish [b]Sampling Station 08 Date I K-40 I Mn-54* I Fe-59* I Co_58* I Co-60" I Zn-65* I Cs-134* I Cs-137" 04/24/13 2.32E+03 +/- 1.03E+03 < 7.04E+01 < 1.57E+02 < 6.24E+01 < 6.04E+01 < 8.73E+01 < 5.83E+01 < 5.10E+01 10/18/13 2.59E+03 +/- 9.12E+02 < 6.70E+01 < 1.64E+02 < 6.84E+01 < 6.66E+01 < 1.46E+02 < 6.50E+01 < 7.29E+01 Sampling Station 25**Date I K-40 I Mn-54* I Fe-59* I Co-58* I Co-60" I Zn-65* I Cs-134* I Cs-137*04/23/13 2.82E+03 +/- 8.99E+02 < 5.76E+01 < 1.13E+02 < 5.22E+01 < 6.99E+01 < 1.22E+02 < 4.65E+01 < 5.06E+01 10/17/13 1.37E+03 +/- 9.71E+02 < 7.12E+01 < 1.22E+02 < 7.67E+01 < 5.76E+01 < 1.36E+02 < 6.OOE+01 < 6.66E+01 Mean 2.45E+03 +/- 9.94E+02 Indicator 2.45E+03 +/- 9.81E+02 Control 2.45E+03 +/- 1.01E+03* LLD identified in ODCM** Control Station[a] Non-bottom dwelling species of gamefish.[b] Bottom dwelling species of fish.59 DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2013 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 2013 was that from external sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides.
Naturally occurring nuclides such as Be-7, K-40, Th-228 and Th-232 were detected in numerous samples. Th-228 & Th-232 results were variable and are generally at levels higher than plant related radionuclides.
The following is a discussion and summary of the results of the environmental measurements taken during the 2013 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 60 dose with the replacement TLDs is lower than that of the previously used TLDs.This will continue to be monitored.
9.0 8.0 7.0 6.0 5.0 4.0 Environ-nental TLDs-0u- Sector TLDs 3.0 -Avg. Pre-op 2.0 1.0___ _0.0 I%. 0 0O r-J 1 O 0 0ý ~ 0 0 S=C = C C C C a C C C 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 the 32 locations (two badges at each location) was 4.6 mR/standard month with a range of 1.6 to 9.2 mR/standard month. The highest quarterly average reading for any single location was obtained at location NW-29/61.
This value was 7.7 mR/standard month. This location is on site on the north gate of the construction side laydown area. Quarterly and annual TLDs are also located at twelve environmental air sampling stations.
For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3.8 mR/standard month with a range of 1.9 to 6.3 mR/standard month. The average annual reading for these locations was 3.4 mR/standard month with a range from 2.3 to 4.8 mR/standard month. The control location showed a quarterly average of 3.4 mR/standard month with a range of 2.9 to 3.9 mR/standard month. Its annual reading was 3.6 mR/standard month. 10 emergency sector TLDs, which are all located onsite had a quarterly average of 5.4 mR/standard month with EPSP-9/ 10 having the highest quarterly average of 7.8 mR/standard month. Eight other TLDs, designated C-1 thru C-8, which 61 were pre-operational controls, were collected quarterly from four locations.
Stations C-3/4 and C-7/8 are designated controls.
These had a quarterly average of 3.6, while Station C-1/2 and C-5/6 had a quarterly average of 2.5 mR/standard month with a range of 1.1 to 3.7 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.4.2 Airborne Gross Beta Results of the weekly gross beta analyses are presented in Table 3-3. A review of the historical plot in Figure 4-2, indicates gross beta activity levels have remained relatively unchanged.
The drop indicated in 2009 may be a function of a return to the vendor used from 1988 until 2001. This will be monitored in the future to see if this is in fact the case. Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4-3). This indicates that any station contribution is not measurable.
Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing.During that time, nearly 740 nuclear weapons were tested worldwide.
In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady. During the preoperational period of July 1, 1974 through March 31, 1978 gross beta activities ranged from a low of 0.005 pCi/m 3 to a high of 0.75 pCi/m 3.0.12 -0.1 E 0.08 -: 0.06 -0 0.04 -0.02 -Control G'ta-24 Indicator Average Pre-op -Required LLD Figure 4-2 Historical Gross Beta in Air Particulates 62 2.50E-02 4L 2.00E-02 1.50E-02 1.OOE-02 5.00E-03 O.OOE+O0 .....r m 0 0-# or 0- z -I Sta 24 -Ul-Indicators Figure 4-3 2013 Gross Beta in Air Particulates (pCi/rm 3)4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine.
Once a week the samples are collected and analyzed.
The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl and the effect of the Fukushima Daiichi event.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.
63 4.5 Air Particulate Strontium Strontium-89 and 90 analyses are performed on the second quarter composites of air particulate filters from all monitoring stations.
There has been no detection of these fission products at any of the indicator or control stations in recent years.4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2013. Cs-137 was identified in 10 of 11 indicator samples and the control sample. For the indicator stations the average was 208.9 pCi/Kg while for the control station the average was 329 pCi/Kg. During the preoperational phase Cs-137 was routinely detected and was attributed to fallout. Levels during this phase varied by location and date and ranged from 88 to 1390 pCi/Kg. The average was 645 pCi/kg. The current levels are also varied significantly by location and date. The decrease in the average, and the fact that the averages for the control location and the indicator locations are similar is indicative of fallout. No other plant related isotopes were identified in Soil samples during 2013.4.7 Precipitation A sample of rain water was collected monthly at on-site station 01A and analyzed for gross beta activity and H-3. The results are presented in Table 3-7. Twelve precipitation samples were obtained in 2013. Semi-annual composites are prepared and analyzed for gamma emitting isotopes in accordance with program requirements.
No plant related isotopes were reported in any precipitation water sample at the indicator location.
Naturally occurring gamma emitting radioisotopes were detected.
No positive H-3 result was reported.
During the pre-operational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison cannot be made to the 2013 period. During the pre-operational period, tritium was measured in over half of the few quarterly composites made. This tritium activity ranged from 100 to 330 pCi/liter.
4.8 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment.
This pathway also shows 64 measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any plant effect.Analysis results for cow milk are contained in Table 3-8. No sample indicated positive results. Gamma spectroscopy did not detect the presence of any isotopes related to the operation of North Anna. In years past, Cs-137 has been detected sporadically.
These occurrences were attributed to residual global fallout from past atmospheric weapons testing. Naturally occurring K-40 was detected in all samples.Once each quarter a sample from the collection station is analyzed for strontium-89 and strontium-90.
Neither Sr-89 nor Sr-90 was detected.
Sr-90 has been observed in the past. Pre-operational levels of 2.2 to 5.4 pCi/liter were measured for Sr-90. There has been a long-term activity trend for Sr-90 showing a continuous decline. It should be noted that strontium-90 is not a part of station effluents.
Its detection is the product of nuclear weapons testing fallout. This conclusion can be made based upon the fact that Sr-89 and Sr-90 have not been detected in gaseous effluents released from the station in many years, and the trend of consistent declining levels since the pre-operational period.4.9 Food Products and Vegetation Food/vegetation samples were collected from five locations and analyzed by gamma spectroscopy.
The results of the analyses are presented in Table 3-9.Low levels of Cs- 137, attributable to fallout, have been seen periodically in vegetation samples. As expected, naturally occurring potassium-40 and cosmogenic beryllium-7 were detected in most samples, and thorium-228 and other natural products, including Bi-214, were detected in some samples. No plant related isotopes were identified in any Vegetation sample during 2013.4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory.
These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed by vendor for Sr-89, Sr-90, H-3, 1-131, and gamma emitters.
The results of these analyses are presented in Table 3-10. No plant related isotopes were detected.
No gamma emitting isotopes were detected during the pre-operational period.65 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 were 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 4010 pCi/liter and a range of 3750 to 4330 pCi/liter.
These levels are comparable to those observed in previous years, see Figure 4-4. No river water samples were collected during the pre-operational period.River Water 4500 4500 4000 4000 3500 4 3500-J 3000 3000 4&2500 2500 --$-tritium 2000 2000 --I-Req LLD 1500 1500 1000 1000 Figure 4-4Tritium in River water 66 4.12 Surface Water Samples of surface water were collected monthly from two stations, an indicator station located at the discharge lagoon and a control station located 12.9 miles WNW. The samples were analyzed by gamma spectroscopy and for iodine-131 by radiochemical separation.
A quarterly composite from each station was prepared and analyzed for tritium. Additionally, the second quarter samples are analyzed for strontium-89 and strontium-90.
There has been no positive indication of these fission products at any of the indicator or control stations in recent years. The results are presented in Table 3-12.No non-naturally occurring gamma emitting radioisotopes, including iodine were detected in any of the samples. No tritium was detected at the control location.
The average level of tritium activity at the indicator station was 4080 pCi/liter with a range of 3850 to 4370 pCi/liter.
Levels of tritium have increased since 1978 when the average level was below 300 pCi/liter.
Levels.measured at the indicator location (Station 8) are comparable to those measured since 1986, see Figure 4-5. During the pre-operational period tritium was measured in several samples with concentrations between 90 and 250 pCi/liter.
67 10000 1000_j 100 a.-Required LLD Average Pre-op Tritium 10 rt Co C fl 40 Co M 4 M Ch 0) -a) D C3 U -0 a LL Co 0 w 0 Z Figure 4.5Tritium in Surface Water 4.13 Bottom Sediment Bottom sediment or silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Buildup of radionuclides in bottom sediment could indirectly lead to increasing radioactivity levels in fish.Sediment samples were collected during March and October from each of three locations and were analyzed by gamma spectroscopy.
The October samples were analyzed for strontium-89 and strontium-90.
The results are presented in Table 3-13.No plant related isotopes were detected in 2013. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the 68 result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented.
During the pre-operational period sediment samples were also analyzed by gamma spectroscopy.
Figure 4-6 shows the historical trend of Cs- 137 in sediments.
Neither Strontium-89 nor Strontium-90 was detected in any samples of aquatic sediment/silt in 2013. Strontium-90 has been detected occasionally in the past at both the indicator and control locations and is attributable to fallout from past bomb tests. A number of naturally occurring radioisotopes were detected in these samples at background levels.1600 -Station-1400 8 1200.91000 9 800.600 Control 400 -Sta-09A 200 9 20--Station-o~ Cc W o M -' Z LCi)W L -) Z M M O0 5C 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 or control samples analyzed.
Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is 69 attributed to accumulation of residual global fallout from past atmospheric weapons testing.4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2013 and analyzed by gamma spectroscopy.
Each sample set consisted of a sample of game species and a sample of bottom-dwelling species, which were analyzed separately.
The results are presented in Table 3-15. Naturally occurring K-40 was detected in all samples. No plant related isotopes were detected.
Cs- 137 was measured in pre-operational environmental fish samples.70
- 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2013 -North Anna Location 14B,15,16,23, 26 14B, 15,16,23, 26 14B,15,16,23, 26 STA 5 STA 5 STA 2 14B,15,16,23, 26 14B,15,16,23, 26 Description Vegetation Vegetation Vegetation AP/Char Annual/Qua rterly TLD AP/Char Vegetation Vegetation Date of Sampling 01/08/13 02/13/13 03/12/13 03/12/13 03/12/13 04/09/13 11/13/13 12/12/13 Reason(s) for Loss/Exception Seasonal unavailability Seasonal unavailability Seasonal unavailability Sampler not ruiming. Power pole damaged by snow storm.TLDs missing due to power pole damage from snow storm.Sampler not running/ replaced.
Minimum volume not met.Seasonal unavailability.
Seasonal unavailability 71 REFERENCES References Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications.
Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".Virginia Electric and Power Company, North Anna Technical Procedure, HP-3051.010,"Radiological Environmental Monitoring Program".Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities".
United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of E;valuating Compliance with 1 OCFR50, Appendix I", October, 1977.United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975.USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 2 7 th 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 1984.72 APPENDICES 73 APPENDIX A: LAND USE CENSUS Year 2013 74 LAND USE CENSUS North Anna Power Station Louisa County, Virginia January I to December 31, 2013 Direction Distance (miles)Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden (> Meat Milch Milch Boundary 50rrm) Animal Cow Goat N 0.9 1.3 1.78 2.9 NONE NONE NNE 0.9 0.9 1.2 3.1 NONE NONE NE 0.8 0.9 1.6 1.6 NONE NONE ENE 0.8 2.37 2.4 2.7 NONE NONE E 0.8 1.3 2.0 3.5 NONE NONE ESE 0.9 1.7 1.7 NONE NONE NONE SE 0.9 1.4 1.5 1.4 NONE NONE SSE 0.9 1.0 1.0 1.6 NONE NONE S 0.9 1.0 .1.0 2.0 NONE NONE SSW 1 1.3 1.33 2.0 NONE NONE SW 1.1 1.65 1.65 NONE NONE NONE WSW 1.1 1.6 2.4 1.6 NONE NONE W 1.1 1.5 1.9 4.4 NONE NONE WNW 1 1.1 2.6 5.0 NONE NONE NW 1 1.0 2.0 NONE NONE NONE NNW 0.9 1.0 1.2 2.3 NONE NONE 75 2012 to 2013 Land Use Census Changes 2012 2013 Nearest Direction Distance Distance Resident NONE Site Boundary NONE Garden N 1.72 1.78 SSW 2.34 1.33 Meat Animal NONE Milch Cow NONE Milch Goat NONE 76 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS YEAR 2013 INTRODUCTION This appendix covers the Intercomparison Program of the Teledyne Brown Engineering
-Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). TBE uses QA/QC samples provided by Eckeri & Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) and Environmental Resource Associates, (ERA) to monitor the quality of analytical processing associated with the REMP. The suite of samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides.
This includes: 77 E & Z Analytics:
Milk for gamma emitters, Iodine-131, Fe-55, Sr-89 and Sr-90 analyses once per quarter.Air particulate for gamma emitters once per quarter Charcoal for 1-131 once per quarter ERA Water for tritium, gamma, Iodine- 131, Sr-89, Sr-90, gross alpha and beta during the 2nd and 4th quarters.Water for natural uranium during the 2nd quarter DOE Water and soil for gamma, Iodine-131, U-233/234, U-238, transuranics, tritium, Fe-55, Ni-63, Sr-90 and Tc-99 analyses during the 1st quarter.Water for gross alpha and beta during the 1 st and 3rd quarters.Air particulates and vegetation for gamma, Iodine-131, U-233/234, U-238, transuranics, Sr-90 analyses during the .1st and 3rd quarters.Air filter for gross alpha and beta analyses during the 1st and 3rd quarters.78 RESULTS Interlaboratory comparison program results are evaluated using TBE's criterion.
Any sample analysis result that does not pass the criteria is investigated by TBE. Nonconformance Reports were generated and corrective actions taken as a result of this program.For the TBE laboratory, 178 out of 185 analyses performed met the specified acceptance criteria.
Seven analyses (Sr-89 and Sr-90 in milk, Co-57, Zn-65 and Sr-90 in soil, Cs-134 in air particulate and Sr-90 in vegetation
[two low warning in a row]) did not meet the specified acceptance criteria or internal QA requirements for the following reason: 1. Teledyne Brown Engineering's Analytics September 2013 Sr-89 in milk result of 63.9 pCi/L was lower than the known value of 96.0 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15 2. Teledyne Brown Engineering's Analytics September 2013 Sr-90 in milk result of 8.88 pCi/L was lower than the known value of 13.2 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15 3. & 4. Teledyne Brown Engineering's MAPEP September 2013 Co-57 and Zn-65 in soil were evaluated as failing the false positive test. While MAPEP evaluated the results as failures, the gamma software listed the results as non identified 79 nuclides.
The two nuclides would never have been reported as detected nuclides to a client. MAPEP does not allow laboratories to put in qualifiers for the submitted data nor"less than" results. MAPEP evaluates results based on the relationship between the activity and the uncertainty.
MAPEP spiked the soil sample with an extremely large concentration of Eu- 152, which was identified by the gamma software as an interfering nuclide, resulting in forced activity results that were evaluated by MAPEP as detected Co-57 and Zn-65. No client samples were affected by these failures.NCR 13-14 5. Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in soil result of 664 Bq/kg was higher than the known value of 460 Bq/kg, exceeding the upper control limit of 598 Bq/kg. An incorrect Sr-90 result was entered into the MAPEP database.
The correct Sr-90 activity of 322 Bq/kg would have been evaluated as acceptable with warning. No client samples were affected by this failure. NCR 13-14 6. Teledyne Brown Engineering's MAPEP September 2013 Cs-134 in air particulate activity of -0.570 Bq/sample was evaluated as a failed false positive test, based on MAPEP's evaluation of the result as a significant negative value at 3 standard deviations.
A negative number would never have been reported as a detected nuclide to a client, therefore no client samples were affected by this failure. NCR 13-14 7. Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in vegetation result was investigated due to two low warnings in a row. It appears the September sample was double 80 spiked with carrier, resulting in a low activity.
With a recovery of around 50% lower, the Sr-90 result would have fallen within the acceptance range. No client samples were affected by this issue. NCR 13-14 A summary of TBE's results is provided in the tables on the following pages for the required sample matrix types and isotopic distribution.
Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result; analytical date; the known values supplied by the providers; pass or fail criteria.81 4 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2013 E10477 E10478 E10480 Milk Milk AP Sr-89 pCi/L 120 Sr-90 pCi/L 9.21 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 87.1 186 463 201 262 200 215 266 311 384 95.3 264 123 142 112 115 139 163 212 99.7 11.0 100 187 472 214 266 208 208 252 301 400 95.6 241 109 136 106 106 129 153 204 92.6 1890 95.0 17.0 95.5 90.4 250 125 151 94.0 1.20 0.84 0.87 0.99 0.98 0.94 0.98 0.96 1.03 1.06 1.03 0.96 1.00 1.10 1.13 1.04 1.06 1.08 1.08 1.07 1.04 0.97 0.97 1.16 0.93 0.97 0.92 1.01 0.94 0.95 0.93 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A El 0479 E10481 June 2013 E10564 E10545 Charcoal 1-131 pCi 90.1 Water Milk Milk Fe-55 pCi/L 1840 Sr-89 pCi/L 110 Sr-90 pCi/L 15.8 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 92.6 83.1 253 118 143 87.1 82 Mn-54 pCi/L 171 172 0.99 A Fe-59 pCi/L 125 120 1.04 A Zn-65 pCi/L 220 217 1.01 A Co-60 pCi/L 169 175 0.97 A E10547 AP Ce-141 pCi 56.8 56.7 1.00 A Cr-51 pCi 168 157 1.07 A Cs-134 pCi 85.2 78.4 1.09 A Cs-137 pCi 101 94.6 1.07 A Co-58 pCi 62.7 58.9 1.06 A Mn-54 pCi 125 108 1.16 A Fe-59 pCi 85.7 75.0 1.14 A Zn-65 pCi 169 136 1.24 W Co-60 pCi 116 110 1.05 A E10546 Charcoal 1-131 pCi 86.5 89.7 0.96 A 83 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)Value Month/Year Number Matrix Nuclide Units Value (a) (b) TBE/Analytics Evaluation (d)June 2013 September 2013 E10549 E10646 E10647 Water Fe-55 pCi/L 1610 Milk Milk Sr-89 pCi/L 63.9 Sr-90 pCi/L 8.88 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 93.9 272 150 125 105 138 125 264 187 208 143 106 97.0 116 98.6 219 166 E10672 E10648 E10673 E10774 E10775 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi 1610 96.0 13.2 98.3 277 172 131 108 139 130 266 196 223 139 105 86.5 112 105 214 158 71.7 1690 93.8 12.9 96.1 110 297 142 0.67 0.67 0.96 0.98 0.87 0.95 0.97 0.99 0.96 0.99 0.95 N (1)N (1)A NA (2)A A A A A A A A 1.00 A Charcoal 1-131 pCi 76.3 Water Fe-55 pCi/L 1790 0.93 1.03 1.01 1.12 1.04 0.94 1.02 1.05 1.06 1.06 1.04 1.03 0.93 0.91 1.00 0.91 NA (2)A A A A A A A A December 2013 Milk Milk Sr-89 pCi/L 97.3 Sr-90 pCi/L 13.3 A A A A A A A A 1-131 Ce-141 Cr-51 Cs-134 pCi/L pCi/L pCi/L pCi/L 89.7 99.8 297 129 84 I Cs-137 pCi/L 126 126 1.00 A Co-58 pCi/L 116 112 1.04 A Mn-54 pCi/L 167 168 0.99 A Fe-59 pCi/L 117 110 1.06 A Zn-65 pCi/L 757 741 1.02 A Co-60 pCi/L 141 147 0.96 A E10777 AP Ce-141 pCi 85.1 88.0 0.97 A Cr-51 pCi 278 238 1.17 A Cs-134 pCi 123 114 1.08 A Cs-137 pCi 102 101 1.01 A Co-58 pCi 84.4 89.9 0.94 A Mn-54 pCi 132 135 0.98 A Fe-59 pCi 101 88.3 1.14 A Zn-65 pCi 506 595 0.85 A Co-60 pCi 118 118 1.00 A ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)December 2013 E10776 Charcoal 1-131 pCi 84.7 80.5 1.05 A E10778 Water Fe-55 pCi/L 2010 1910 1.05 A (1) Milk, Sr-89/90 -The failure was due to analyst error. No client samples were affected by this failure. NCR 13-15 (2) The sample was not spiked with Ce- 141 (a) Teledyne Brown Engineering reported result.(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) Ratio of Teledyne Brown Engineering to Analytics results.(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.
W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30.
N = Not Acceptable, reported result falls outside the ratio limits of < 0.70 and > 1.30.85 I DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Value Month/Year Number Media Nuclide Units Value (a) (b) Range Evaluation (c)March 2013 13-MaW28 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 21.0 0.0446 28.3 18.2 506 25.7 2.09 10.5 29.2 24.4 17.1-31.7 (1)30.9 21.6 -40.2 19.56 13.69 -25.43 507 355 -659 27.4 19.2 -35.6 (1)10.5 7.4 -13.7 30.4 21.3 -39.5 A A A A A A A A A A A 13-GrW28 Water 13-MaS28 'Soil 13-RdF28 AP Gr-A Gr-B 2.74 15.6 2.31 13.0 0.69 -3.93 6.5- 19.5 Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 859 633 0.256 738 0.671 714 442 1057 1.73 2.73 2.38 0.0302 4.36 1.43 3.14 0.767 0.871-0.197 7.39 9.87 887 621-1153 587 411-763 (1)691 625.3 628 995 1.78 2.60 2.36 4.26 1.49 3.13 484 -898 (1)437.7 -812.9 440 -816 697 -1294 1.25-2.31 1.82-3.38 1.65- 3.07 (1)2.98 -5.54 1.04- 1.94 2.19-4.07 A A A A A A W A A A A A A A A A A A A A 13-GrF28 AP Gr-A Bq/sample Gr-B Bq/sample 1.20 0.36-2.04 0.85 0.43-1.28 (1)6.87 4.81 -8.93 8.68 6.08-11.28 13-RdV28 Vegetation Cs-134 Cs-1 37 Co-57 Bq/sample Bq/sample Bq/sample 86 1 September 2013 13-MaW29 Water Co-60 Mn-54 Sr-90 Zn-65 Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 6.08-0.0104 1.28 6.84 29.1 34.5 0.0358 24.6 2.45 0.0337 0.193 9.12 38.1 5.85 4.10 -7.61 (1)1.64 1.15-2.13 6.25 4.38 -8.13 30.0 21.0 -39.0 31.6 22.1-41.1 (1)23.58 16.51 -30.65 (1)(1)(1)7.22 5.05 -9.39 34.6 24.2 -45.0 A A W A A A A A A A A W A 13-GrW29 Water Gr-A Gr-B Bq/L Bq/L 1.13 0.701 0.210-1.192 7.61 5.94 2.97- 8.91 A A 87 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Value Month/Year Number Media Nuclide Units Value (a) (b) Range Evaluation (c)September 2013 13-MaS29 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 13-RdF29 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1150 1100 670 502 758 796 664 210-0.570 2.85 3.30 2.41 3.65 1.40 2.90 0.872 1.57 5.29 7.48 0.0129 0.0523 8.78 1.63 3.18 1172 820-1524 977 684-1270 (1)451 316-586 674 472- 876 633 443-823 460 322-598 (1)13-GrF29 AP Gr-A Bq/sample Gr-B Bq/sample 2.7 3.4 2.3 3.5 1.81 2.7 0.9 1.63 5.20 6.60 7.88 2.32 2.63 (1)1.9- 3.5 2.4 -4.4 1.6-3.0 2.5 -4.6 1.27-2.35 1.9-3.5 0.3-1.5 0.82 -2.45 3.64 -6.76 4.62 -8.58 (1)(1)5.52- 10.24 1.62- 3.02 1.84- 3.42 A A N (2)A A W N (2)N (2)N (2)A A A A W A A A A A A A A W (2)W 13-RdV29 Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample (1) False positive test.(2) Soil, Co-57 & Zn-65 identified by gamma software as not detected, MAPEP evaluated as failing the false positive test. A large concentration of Eu-152 was spiked into the sample, causing interference in the analysis.
Gamma software irecognized the interference and identified them as not detected.
MAPEP does not allow clients to enter non-detect designation.
Soil, Sr-90 -incorrect results were submitted to MAPEP. Should have been 332 bq/kg, which would have passed.AP, Cs-134 -MAPEP evaluated the -0.570 as a failed false positive test. No client samples were affected by these failures.
NCR 13-04 Vegetation, Sr-90 -it appears that the carrier was double spiked into the sample, resulting in the low activity for this sample. NCR 13-04 (a) Teledyne Brown Engineering reported result.(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) DOEIMAPEP evaluation:
A=acceptable, W=acceptable with warning, N=not acceptable.
88 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)May 2013 RAD-93 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 48.3 19.3 81.9 40.9 44.0 61.9 202 34.2 18.0 23.8 60.4 3970 41.3 23.9 82.1 42.8 41.7 65.9 189 40.8 21.6 23.8 61.2 31.6-48.4 17.2 -28.0 69.0 -90.3 34.2 -47.1 37.0 -48.8 59.3 -75.0 170 -222 21.1 -51.9 13.0-29.7 19.7-28.3 49.8 -67.9 A A A A A A A A A A A A 4050 3450-4460 MRAD-18 Filter Gr-A pCi/filter Lost during processing November 2013 RAD-95 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 25.5 14.3 57.2 83.3 201 104 361 29.5 30.1 23.1 5.53 17650 21.9 18.1 54.2 86.7 206 102 333 42.8 32.2 23.6 6.24 17700 14.4-28.2 12.8-21.5 44.7-59.9 71.1-95.4 185-228 91.8-114 300- 389 22.2- 54.3 20.8- 39.9 19.6-28.0 47.0- 7.44 15500- 19500 A A A A A A A A A A A A A MRAD-19 Filter Gr-A pCi/filter 33.0 83.0 27.8 -129 (a) Teledyne Brown Engineering reported result.(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) ERA evaluation:
A=acceptable.
Reported result falls within the Warning Limits. NA=not acceptable.
Reported result falls outside of the Control Limits. CE= Check for Error. Reported result falls within the Control Limits and outside the Warning Limit.89