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| number = ML14118A037 | | number = ML14118A037 | ||
| issue date = 04/22/2014 | | issue date = 04/22/2014 | ||
| title = | | title = Independent Spent Fuel Storage Installation (Isfsi), Submittal of 2013 Annual Radiological Environmental Operating Report | ||
| author name = Bischof G | | author name = Bischof G | ||
| author affiliation = Virginia Electric & Power Co (VEPCO) | | author affiliation = Virginia Electric & Power Co (VEPCO) | ||
| addressee name = | | addressee name = | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#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/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) | ||
Document Control Desk NAPS/ | NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) | ||
NORTH ANNA POWER STATION UNIT NOS. 1 AND | 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. | ||
Very truly yours,Gerald T. | 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 RadiologicalEnvironmentalMonitoringProgram Januaty1, 2013 to December 31, 2013 Preparedby Dominion, North Anna Power Station | |||
Annual RadiologicalEnvironmentalOperatingReport North Anna Power Station January1, 2013 to December 31, 2013 Preparedby: | |||
Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Reviewed by: | |||
C 'eorge R. Simmons Supervisor Health Physics Technical Services Dominion North Anna Power Station Approved by: | |||
Robert B. Evans'dr. | |||
Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2 | |||
Table of Contents | |||
: 1. EX ECU TIV E SU M M A RY ....................................................................................................... 4 | |||
: 2. PRO G RAM D ESCRIPTION ...................................................................................................... 7 2.1 Introduction .............................................................. | |||
57 ý; | 57 ý; | ||
Table 3- | |||
[pCi/Kg] | Table 3-14 Shoreline Soil Gamma Spectra, and Strontium | ||
+/- 7.52E+02 6.OOE+01 | [pCi/Kg] | ||
< 6.83E+ | page 1 of 1 Sample I | ||
+/- 1.16E+02 7.05E+02 | Date I Sr-89 Sr-90 I K-40 I Cs-134* I Cs-137* | ||
+/- 1.48E+ | 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 | ||
+/- 8.46E+ | < 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* | ||
+/- 1.12E+03 8.29E+02 | 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 Sr-89 Sr-90 K-40 Cs-134* Cs- 137* | ||
+/- 9.51 E+01 7.46E+02 | +/- +/- 2.65E+03 +/- 7.99E+02 +/- +!- | ||
+/- 1.45E+ | Ra-226 Th-228 Th-232 1.52E+03 +/- 1.44E+03 8.19E+02 +/- 1.06E+02 7.26E+02 +/- 1.47E+02 | ||
+/- 7.99E+02+/-+!-Ra- | * LLD identified in ODCM | ||
+/- 1.44E+03 8.19E+02 | [a] Sr-89/90 analyses performed annually. | ||
+/- 1.06E+02 7.26E+02 | 58 | ||
+/- 1.47E+02* LLD identified in ODCM[a] Sr-89/90 analyses performed annually. | |||
58 Table 3- | Table 3-15 Fish page Gamma Spectra 1 of 1 | ||
+/- 9.20E+02 | [pCi/Kg] | ||
< 5.75E+01 | Fish [a] | ||
< 1.28E+02 | 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** | ||
< 5.92E+01 | Date I K-40 I Mn-54* I Fe-59* I Co-58* I Co-60" Zn-65* I Cs-134* I Cs-137* | ||
< 4.77E+01 | 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] | ||
< 9.95E+01 | 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** | ||
< 4.30E+01 | 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* | ||
< 5.56E+ | 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 | ||
+/- 1.06E+03 | * LLD identified in ODCM | ||
< 7.34E+01 | ** Control Station | ||
< 1.73E+02 | [a] Non-bottom dwelling species of gamefish. | ||
< 7.51E+01 | [b] Bottom dwelling species of fish. | ||
< 6.84E+01 | 59 | ||
< 1.18E+02 | |||
< 6.44E+01 | 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. | ||
< 7.22E+ | The results of the Interlaboratory Comparison Programs are provided in Appendix B. | ||
+/- 1.31E+03 | 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. | ||
< 7.19E+01 | The following is a discussion and summary of the results of the environmental measurements taken during the 2013 reporting period. | ||
< 1.88E+02 | 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. | ||
< 1".08E+02 | 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. | ||
< 5.60E+01 | 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 | ||
< 1.63E+02 | |||
< 9.28E+01 | dose with the replacement TLDs is lower than that of the previously used TLDs. | ||
< 8.41E+ | This will continue to be monitored. | ||
+/- 8.46E+02 | 9.0 8.0 7.0 6.0 5.0 4.0 Environ-nental TLDs | ||
< 6.01E+01 | -0u- Sector TLDs 3.0 -Avg. Pre-op 2.0 1.0___ _ | ||
< 1.49E+02 | 0.0 I | ||
< 6.60E+01 | %. 0 0O r-J 1 O 0 0ý ~ 0 0 S=C = C C C C a C C C Figure4-1 TLD (mrem/StandardMonth) | ||
< 6.75E+01 | 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 | ||
< 1.26E+02 | |||
< 5.40E+01 | were pre-operational controls, were collected quarterly from four locations. | ||
< 6.50E+ | 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. | ||
+/- 1.03E+03 | 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. | ||
< 7.04E+01 | Gross beta activity found during the pre-operational and early operating period of North Anna Power Station was higher because of nuclear weapons testing. | ||
< 1.57E+02 | 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 . | ||
< 6.24E+01 | 0.12 - | ||
< 6.04E+01 | 0.1 E 0.08 - | ||
< 8.73E+01 | : 0.06 - | ||
< 5.83E+01 | 0 0.04 - | ||
< 5.10E+ | 0.02 - | ||
+/- 9.12E+02 | 0- | ||
< 6.70E+01 | - Control G'ta-24 Indicator Average Pre-op - Required LLD Figure 4-2 HistoricalGross Beta in Air Particulates 62 | ||
< 1.64E+02 | |||
< 6.84E+01 | 2.50E-02 4L 2.00E-02 1.50E-02 1.OOE-02 5.00E-03 O.OOE+O0 ..... | ||
< 6.66E+01 | r m 0 0 | ||
< 1.46E+02 | - -# or 2 - 0- z -I | ||
< 6.50E+01 | *-4-Control Sta 24 -Ul-Indicators Figure4-3 2013 Gross Beta in Air Particulates(pCi/rm3) 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. | ||
< 7.29E+ | 4.4 Air ParticulateGamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy. | ||
+/- 8.99E+02 | The results are listed in Table 3-5. The results indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. | ||
< 5.76E+01 | 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. | ||
< 1.13E+02 | 63 | ||
< 5.22E+01 | |||
< 6.99E+01 | 4.5 Air ParticulateStrontium 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. | ||
< 1.22E+02 | 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. | ||
< 4.65E+01 | 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- | ||
< 5.06E+ | : 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. | ||
+/- 9.71E+02 | 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 | ||
< 7.12E+01 | |||
< 1.22E+02 | 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. | ||
< 7.67E+01 | 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. | ||
< 5.76E+01 | 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. | ||
< 1.36E+02 | 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. | ||
< 6.OOE+01 | 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. | ||
< 6.66E+ | 4.10 Well Water Water was sampled quarterly from the onsite well at the metrology laboratory. | ||
+/- 9.94E+ | 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. | ||
+/- 9.81E+ | 65 | ||
+/- 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 | 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. | ||
In addition | There has been no detection of these fission products at any of the indicator or control stations in recent years. | ||
Participation in | No gamma emitting radioisotopes were positively identified in any of the samples. There was no measured activity of strontium-89 or strontium-90. | ||
The results of the Interlaboratory Comparison Programs are provided | 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 | |||
Naturally occurring nuclides such as Be-7, K-40, Th-228 and Th-232 were detected in numerous samples. | -J 3000 3000 4&2500 2500 -- $-tritium 2000 -- I-Req LLD 2000 1500 1500 1000 1000 Figure4-4Tritium in River water 66 | ||
Th-228 & Th-232 | |||
The following is a discussion and summary of the results of the environmental measurements taken during the 2013 reporting period.4.1 Gamma Exposure | 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. | ||
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 | 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 | ||
TLDs are also placed in | .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. | ||
Additional TLDs serve as controls. | 67 | ||
Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout | |||
Control and indicator averages indicate a steady relationship. | 10000 1000 | ||
Two dosimeters made of CaF and | _j 100 a. | ||
These | -Required LLD Average Pre-op Tritium 10 rt Co C 40 fl Co M M4 Ch 0) - a) D C3 U - 0 a LL Co 0 w 0 Z Figure4.5Tritium 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. | ||
9. | 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. | ||
The average | 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 | ||
This | |||
For the eleven indicator locations within 10 miles of the station the average quarterly reading was 3. | 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. | |||
Stations C-3/4 and C-7/8 are designated controls. | 1600 - Station-1400 8 1200 | ||
These had a quarterly average of 3.6, while Station C-1/2 and C-5/6 had a quarterly average of 2. | .91000 9 800 | ||
The drop indicated in 2009 may be a | . 600 Control 400 -Sta-09A 200 9 20--Station-o~ Cc W o MZ -' LCi)W L -) Z M M O0 5C Figure4-6 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. | ||
Gross beta activity found during the pre-operational and early operating | 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. | ||
In | 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 | ||
.....r m 0 0-# or 0- z -I Sta 24 -Ul-Indicators | |||
Once a week | attributed to accumulation of residual global fallout from past atmospheric weapons testing. | ||
The results of the analyses are presented in Table 3-4. These results are similar to pre-operational data and the | 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. | ||
The results are listed in Table 3-5. The results indicate the presence | 70 | ||
Examination of pre-operational data indicates comparable measurements | : 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2013 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception 14B,15,16,23, Vegetation 01/08/13 Seasonal unavailability 26 14B, 15,16,23, Vegetation 02/13/13 Seasonal unavailability 26 14B,15,16,23, 26 Vegetation 03/12/13 Seasonal unavailability STA 5 AP/Char 03/12/13 Sampler not ruiming. Power pole damaged by snow storm. | ||
The results of these analyses indicate the lack | STA 5 Annual/Qua 03/12/13 TLDs missing due to power pole damage from rterly TLD snow storm. | ||
63 4.5 Air | STA 2 AP/Char 04/09/13 Sampler not running/ replaced. Minimum volume not met. | ||
There has been | 14B,15,16,23, Vegetation 11/13/13 Seasonal unavailability. | ||
26 14B,15,16,23, Vegetation 12/12/13 Seasonal unavailability 26 71 | |||
No other plant related isotopes were identified in | |||
No plant related isotopes were | REFERENCES References Dominion, North Anna Power Station Technical Specifications, Units 1 and 2. | ||
Naturally occurring gamma emitting radioisotopes were detected. | Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications. | ||
No positive H-3 result | Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual". | ||
During the pre-operational period gross beta activity in rain | 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". | |||
4.8 Cow | 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 10CFR50, Appendix I", October, 1977. | ||
This pathway also | United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975. | ||
Therefore, this | USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. | ||
Gamma spectroscopy did not detect the presence of | NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982. | ||
These occurrences were attributed to | HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 2 7 th Edition, Volume 1, February 1992. | ||
Naturally occurring K-40 was detected in all samples.Once each quarter a sample from the collection station is analyzed | NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984. | ||
Neither Sr-89 nor Sr-90 was detected. | 72 | ||
Sr- | |||
It should be noted that strontium-90 is not | APPENDICES 73 | ||
Its detection is the product of nuclear | |||
This conclusion can be made based upon the fact that Sr- | APPENDIX A: LAND USE CENSUS Year 2013 74 | ||
The results of the analyses are presented in Table 3-9.Low levels of Cs- 137, attributable to fallout, have been seen periodically | |||
As expected, naturally occurring potassium-40 | LAND USE CENSUS North Anna PowerStation 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 | |||
These samples were analyzed for gamma radiation and for tritium. | |||
The | 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 | ||
The results of these analyses are presented in Table 3-10. | |||
No gamma emitting isotopes were | APPENDIX B: | ||
The monthly samples were composited quarterly | ==SUMMARY== | ||
Additionally, the second quarter samples are analyzed | 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: | ||
There has been no detection of these fission products at any of the indicator | 77 | ||
There was no measured activity of strontium-89 or strontium-90. | |||
Tritium was measured in all four samples with an average | E & Z Analytics: | ||
Milk for gamma emitters, Iodine-131, Fe-55, Sr-89 and Sr-90 analyses once per quarter. | |||
A quarterly composite from | 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. | ||
Additionally, the | 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. | ||
There | Water for gross alpha and beta during the 1 st and 3rd quarters. | ||
No tritium was detected at the | Air particulates and vegetation for gamma, Iodine-131, U-233/234, U-238, transuranics, Sr-90 analyses during the .1st and 3rd quarters. | ||
The average level of tritium activity at the indicator station was | |||
Levels of tritium | |||
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. | |||
Neither Strontium-89 nor Strontium-90 was detected in any samples of | |||
The | |||
The results | |||
No plant related isotopes were detected in | |||
Strontium-90 is often detected in | |||
Each sample set consisted of a sample of game species and | |||
No plant related isotopes were detected. | |||
Cs- 137 was measured | |||
: 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis during 2013 -North | |||
Power pole damaged | |||
replaced. | |||
Title 10 Code of Federal Regulation, Part 50 (10CFR50), | |||
"Domestic Licensing of Production | |||
United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation | |||
December 1975.USNRC Branch Technical | |||
Rev. 1, November 1979.NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," | |||
Definition and Elaboration of a | |||
September 1984.72 APPENDICES 73 APPENDIX A: LAND USE | |||
-Environmental Services as required by technical specifications for the Radiological Environmental Monitoring Program (REMP). TBE | |||
This includes: | |||
77 E & Z Analytics: | |||
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. | Air filter for gross alpha and beta analyses during the 1st and 3rd quarters. | ||
78 | 78 | ||
Any sample analysis result that does not pass the criteria | |||
Seven analyses (Sr-89 and Sr-90 | 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. | ||
[two low warning in a row]) did not meet | 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: | ||
NCR 13- | : 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 | ||
NCR 13- | : 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 | ||
The two nuclides would never have been | : 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 | ||
MAPEP evaluates results based on | |||
MAPEP spiked the soil sample with an extremely | 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- | NCR 13-14 | ||
The correct Sr-90 activity of 322 Bq/ | : 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 | |||
NCR 13- | : 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 | ||
A negative number would never | |||
NCR 13- | 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. | ||
With | 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. | ||
Delineated in the table for each of the media/analysis combinations, are: the specific radionuclide; its result; analytical date; the | 81 | ||
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 Milk Sr-89 pCi/L 120 99.7 1.20 A Sr-90 pCi/L 9.21 11.0 0.84 A E10478 Milk 1-131 pCi/L 87.1 100 0.87 A Ce-141 pCi/L 186 187 0.99 A Cr-51 pCi/L 463 472 0.98 A Cs-134 pCi/L 201 214 0.94 A Cs-137 pCi/L 262 266 0.98 A Co-58 pCi/L 200 208 0.96 A Mn-54 pCi/L 215 208 1.03 A Fe-59 pCi/L 266 252 1.06 A Zn-65 pCi/L 311 301 1.03 A Co-60 pCi/L 384 400 0.96 A E10480 AP Ce-141 pCi 95.3 95.6 1.00 A Cr-51 pCi 264 241 1.10 A Cs-134 pCi 123 109 1.13 A Cs-137 pCi 142 136 1.04 A Co-58 pCi 112 106 1.06 A Mn-54 pCi 115 106 1.08 A Fe-59 pCi 139 129 1.08 A Zn-65 pCi 163 153 1.07 A Co-60 pCi 212 204 1.04 A El 0479 Charcoal 1-131 pCi 90.1 92.6 0.97 A E10481 Water Fe-55 pCi/L 1840 1890 0.97 A June 2013 E10564 Milk Sr-89 pCi/L 110 95.0 1.16 A Sr-90 pCi/L 15.8 17.0 0.93 A E10545 Milk 1-131 pCi/L 92.6 95.5 0.97 A Ce-141 pCi/L 83.1 90.4 0.92 A Cr-51 pCi/L 253 250 1.01 A Cs-1 34 pCi/L 118 125 0.94 A Cs-1 37 pCi/L 143 151 0.95 A Co-58 pCi/L 87.1 94.0 0.93 A 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 E10549 Water Fe-55 pCi/L 1610 1610 1.00 A September 2013 E10646 Milk Sr-89 pCi/L 63.9 96.0 0.67 N (1) | |||
Sr-90 pCi/L 8.88 13.2 0.67 N (1) | |||
E10647 Milk 1-131 pCi/L 93.9 98.3 0.96 A Ce-141 pCi/L NA (2) | |||
A | Cr-51 pCi/L 272 277 0.98 A Cs-1 34 pCi/L 150 172 0.87 A Cs-1 37 pCi/L 125 131 0.95 A Co-58 pCi/L 105 108 0.97 A Mn-54 pCi/L 138 139 0.99 A Fe-59 pCi/L 125 130 0.96 A Zn-65 pCi/L 264 266 0.99 A Co-60 pCi/L 187 196 0.95 A E10672 AP Ce-141 pCi NA (2) | ||
Cr-51 pCi 208 223 0.93 A Cs-134 pCi 143 139 1.03 A Cs-137 pCi 106 105 1.01 A Co-58 pCi 97.0 86.5 1.12 A Mn-54 pCi 116 112 1.04 A Fe-59 pCi 98.6 105 0.94 A Zn-65 pCi 219 214 1.02 A Co-60 pCi 166 158 1.05 A E10648 Charcoal 1-131 pCi 76.3 71.7 1.06 A E10673 Water Fe-55 pCi/L 1790 1690 1.06 A December 2013 E10774 Milk Sr-89 pCi/L 97.3 93.8 1.04 A Sr-90 pCi/L 13.3 12.9 1.03 A E10775 Milk 1-131 pCi/L 89.7 96.1 0.93 A Ce-141 pCi/L 99.8 110 0.91 A Cr-51 pCi/L 297 297 1.00 A Cs-134 pCi/L 129 142 0.91 A 84 | |||
A= | 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 Engineeringreportedresult. | |||
(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation. | |||
(c) Ratio of Teledyne Brown Engineering to Analytics results. | |||
(d) Analytics evaluationbased 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 Bq/L 21.0 24.4 17.1-31.7 A Cs-137 Bq/L 0.0446 (1) A Co-57 Bq/L 28.3 30.9 21.6 - 40.2 A Co-60 Bq/L 18.2 19.56 13.69 - 25.43 A H-3 Bq/L 506 507 355 - 659 A Mn-54 Bq/L 25.7 27.4 19.2 - 35.6 A K-40 Bq/L 2.09 (1) A Sr-90 Bq/L 10.5 10.5 7.4 - 13.7 A Zn-65 Bq/L 29.2 30.4 21.3 - 39.5 A 13-GrW28 Water Gr-A Bq/L 2.74 2.31 0.69 - 3.93 A Gr-B Bq/L 15.6 13.0 6.5- 19.5 A 13-MaS28 'Soil Cs-1 34 Bq/kg 859 887 621-1153 A Cs-1 37 Bq/kg 633 587 411-763 A Co-57 Bq/kg 0.256 (1) A Co-60 Bq/kg 738 691 484 - 898 A Mn-54 Bq/kg 0.671 (1) A K-40 Bq/kg 714 625.3 437.7 - 812.9 A Sr-90 Bq/kg 442 628 440 - 816 W Zn-65 Bq/kg 1057 995 697 - 1294 A 13-RdF28 AP Cs-1 34 Bq/sample 1.73 1.78 1.25-2.31 A Cs-137 Bq/sample 2.73 2.60 1.82-3.38 A Co-57 Bq/sample 2.38 2.36 1.65- 3.07 A Co-60 Bq/sample 0.0302 (1) A Mn-54 Bq/sample 4.36 4.26 2.98 - 5.54 A Sr-90 Bq/sample 1.43 1.49 1.04- 1.94 A Zn-65 Bq/sample 3.14 3.13 2.19-4.07 A 13-GrF28 AP Gr-A Bq/sample 0.767 1.20 0.36-2.04 A Gr-B Bq/sample 0.871 0.85 0.43-1.28 A 13-RdV28 Vegetation Cs-134 Bq/sample -0.197 (1) A Cs-1 37 Bq/sample 7.39 6.87 4.81 -8.93 A Co-57 Bq/sample 9.87 8.68 6.08-11.28 A 86 | |||
1 Co-60 Bq/sample 6.08 5.85 4.10 - 7.61 A Mn-54 Bq/sample -0.0104 (1) A Sr-90 Bq/sample 1.28 1.64 1.15-2.13 W Zn-65 Bq/sample 6.84 6.25 4.38 - 8.13 A September 2013 13-MaW29 Water Cs-134 Bq/L 29.1 30.0 21.0 - 39.0 A Cs-137 Bq/L 34.5 31.6 22.1-41.1 A Co-57 Bq/L 0.0358 (1) A Co-60 Bq/L 24.6 23.58 16.51 - 30.65 A H-3 Bq/L 2.45 (1) A Mn-54 Bq/L 0.0337 (1) A K-40 Bq/L 0.193 (1) A Sr-90 Bq/L 9.12 7.22 5.05 - 9.39 W Zn-65 Bq/L 38.1 34.6 24.2 - 45.0 A 13-GrW29 Water Gr-A Bq/L 1.13 0.701 0.210-1.192 A Gr-B Bq/L 7.61 5.94 2.97- 8.91 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 Bq/kg 1150 1172 820-1524 A Cs-1 37 Bq/kg 1100 977 684-1270 A Co-57 Bq/kg 670 (1) N (2) | |||
Co-60 Bq/kg 502 451 316-586 A Mn-54 Bq/kg 758 674 472- 876 A K-40 Bq/kg 796 633 443-823 W Sr-90 Bq/kg 664 460 322-598 N (2) | |||
Zn-65 Bq/kg 210 (1) N (2) 13-RdF29 AP Cs-134 Bq/sample -0.570 (1) N (2) | |||
Cs-1 37 Bq/sample 2.85 2.7 1.9- 3.5 A Co-57 Bq/sample 3.30 3.4 2.4 - 4.4 A Co-60 Bq/sample 2.41 2.3 1.6-3.0 A Mn-54 Bq/sample 3.65 3.5 2.5 - 4.6 A Sr-90 Bq/sample 1.40 1.81 1.27-2.35 W Zn-65 Bq/sample 2.90 2.7 1.9-3.5 A 13-GrF29 AP Gr-A Bq/sample 0.872 0.9 0.3-1.5 A Gr-B Bq/sample 1.57 1.63 0.82 - 2.45 A 13-RdV29 Vegetation Cs-134 Bq/sample 5.29 5.20 3.64 - 6.76 A Cs-1 37 Bq/sample 7.48 6.60 4.62 - 8.58 A Co-57 Bq/sample 0.0129 (1) A Co-60 Bq/sample 0.0523 (1) A Mn-54 Bq/sample 8.78 7.88 5.52- 10.24 A Sr-90 Bq/sample 1.63 2.32 1.62- 3.02 W (2) | |||
Zn-65 Bq/sample 3.18 2.63 1.84- 3.42 W (1) Falsepositive 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 incorrectresults 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 it appears that the carrierwas double spiked into the sample, resultingin the low activity for this sample. NCR 13-04 (a) Teledyne Brown Engineeringreported result. | |||
(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation. | |||
(c) DOEIMAPEPevaluation: 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 pCi/L 48.3 41.3 31.6-48.4 A Sr-90 pCi/L 19.3 23.9 17.2 - 28.0 A Ba-1 33 pCi/L 81.9 82.1 69.0 - 90.3 A Cs-134 pCi/L 40.9 42.8 34.2 -47.1 A Cs-137 pCi/L 44.0 41.7 37.0 - 48.8 A Co-60 pCi/L 61.9 65.9 59.3 - 75.0 A Zn-65 pCi/L 202 189 170 - 222 A Gr-A pCi/L 34.2 40.8 21.1 -51.9 A Gr-B pCi/L 18.0 21.6 13.0-29.7 A 1-131 pCi/L 23.8 23.8 19.7-28.3 A U-Nat pCi/L 60.4 61.2 49.8 - 67.9 A H-3 pCi/L 3970 4050 3450-4460 A MRAD-18 Filter Gr-A pCi/filter Lost during processing November 2013 RAD-95 Water Sr-89 pCi/L 25.5 21.9 14.4-28.2 A Sr-90 pCi/L 14.3 18.1 12.8-21.5 A Ba-133 pCi/L 57.2 54.2 44.7-59.9 A Cs-1 34 pCi/L 83.3 86.7 71.1-95.4 A Cs-1 37 pCi/L 201 206 185-228 A Co-60 pCi/L 104 102 91.8-114 A Zn-65 pCi/L 361 333 300- 389 A Gr-A pCi/L 29.5 42.8 22.2- 54.3 A Gr-B pCi/L 30.1 32.2 20.8- 39.9 A 1-131 pCi/L 23.1 23.6 19.6-28.0 A U-Nat pCi/L 5.53 6.24 47.0- 7.44 A H-3 pCi/L 17650 17700 15500- 19500 A MRAD-19 Filter Gr-A pCi/filter 33.0 83.0 27.8 - 129 A (a) Teledyne Brown Engineeringreported result. | |||
(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation. | |||
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the ControlLimits. CE= Check for Error.Reported result falls within the Control Limits and outside the Warning Limit. | |||
89}} | |||
Latest revision as of 20:43, 5 February 2020
| ML14118A037 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/22/2014 |
| From: | Gerald Bichof 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 RadiologicalEnvironmentalMonitoringProgram Januaty1, 2013 to December 31, 2013 Preparedby Dominion, North Anna Power Station
Annual RadiologicalEnvironmentalOperatingReport North Anna Power Station January1, 2013 to December 31, 2013 Preparedby:
Leonard E. Oakes Supervisor Radiological Analysis and Instrumentation Dominion North Anna Power Station Reviewed by:
C 'eorge R. Simmons Supervisor Health Physics Technical Services Dominion North Anna Power Station Approved by:
Robert B. Evans'dr.
Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2
Table of Contents
- 1. EX ECU TIV E SU M M A RY ....................................................................................................... 4
- 2. PRO G RAM 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 Analytical Results of 2013 REM P Sam ples ................................................................... 32
- 4. DISCU SSION O F RESU LTS ................................................................................................... 60 4.1 Gam ma Exposure Rate ................................................................................................... 60 4.2 Airborne G ross Beta ......................................................................................................... 62 4.3 A irborne Radioiodine ...................................................................................................... 63 4.4 A ir Particulate G amm a ................................................................................................. n ...... 63 4.5 Air Particulate Strontium ................................................................................................. 64 4 .6 S o il ........................................................................................................................................ 64 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 FEREN CES .................................................................................................................................... 72 A PPEN D ICES ..................................................................................................................................... 73 APPEN D IX A : LAN 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 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".
This report documents the results of the Radiological Environmental Monitoring Program for 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 Location Station Distance Direction Degrees Frequency Remarks Environmental NAPS Sewage Treatment Plant 01 .,0.20 . NE 420 Quarterly & Annually Thermoluminescent Fredericks Hall 02 5.30 SSW 2030 Quarterly & Annually Dosimetry (TLD) Mineral, Va 03 7.10 WSW 2430 Quarterly & Annually Wares Crossroads 04 5.10 WNW 2870 Quarterly & Annually Route 752 05 4.20 NNE 200 Quarterly & Annually Sturgeon's Creek Marina 05A 2.04 N 110 Quarterly & Annually Levy, VA 06 4.70 ESE 1150 Quarterly & Annually Bumpass, VA 07 7.30 SSE 1670 Quarterly & Annually End of Route 685 21 1.00 WNW 3010 Quarterly & Annually Route 700 22 1.00 WSW 2420 Quarterly & Annually "Aspen Hills" 23 0.93 SSE 1580 Quarterly & Annually Orange, VA 24 22.00 NW 3250 Quarterly & Annually Control Bearing Cooling Tower N-1/33 0.06 N 100 Quarterly Sturgeon's Creek Marina N-2/34 2.04 N 110 Quarterly Parking Lot "C" (on-site) NNE-3/35 0.24 NNE 320 Quarterly Good Hope Church NNE-4/36 3.77 NNE 250 Quarterly Parking Lot "B" NE-5/37 0.20 NE 420 Quarterly Lake Anna Marina (Bogg's Dr) NE-6/38 1.46 NE 340 Quarterly Weather Tower Fence ENE-7/39 .0.36 ENE 740 Quarterly Route 689 ENE-8/40 2.43 ENE 650 Quarterly Near Training Facility E-9/41 0.30 E 910 Quarterly "Morning Glory Hill" E-10/42 2.85 E 930 Quarterly Island Dike ESE-l 1/43 0.12 ESE 1030 Quarterly Route 622 ESE- 12/44 4.70 ESE 1150 Quarterly DVP Biology Lab SE-13/45 0.64 SE 1380 Quarterly Route 701 (Dam Entrance) SE-14/46 5.88 SE 1370 Quarterly "Aspen Hills" SSE-15/47 0.93 SSE 1580 Quarterly Elk Creek SSE-16/48 2.33 SSE 1650 Quarterly NAPS Access Rd. S-17/49 0.36 S 1730 Quarterly 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 NAPS Access Rd. SSW- 19/51 0.24 SSW 1970 Quarterly Dosimetry (TLD) Route 618 SSW-20/52 5.30 SSW 2050 Quarterly 500kv Tower SW-21/53 0.60 SW 2180 Quarterly Route 700 SW-22/54 3.96 SW 2320 Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW 2370 Quarterly Route 700 (Exclusion Boundary) WSW-24/56 1.00 WSW 2420 Quarterly South Gate Switchyard W-25/57 0.32 W 2790 Quarterly Route 685 W-26/58 1.55 W 2740 Quarterly End of Route 685 WNW-27/59 1.00 WNW 3010 Quarterly Route 685 WNW-28/60 1.40 WNW 3030 Quarterly North Gate - Laydown Area NW-29/61 0.52 NW 3210 Quarterly Lake Anna Campground NW-30/62 2.54 NW 3190 Quarterly
- 1/#2 Intake NNW-31/63 0.07 NNW 3490 Quarterly Route 208 NNW-32/64 2.21 NNW 3440 Quarterly Bumpass Post Office C-1/2 7.30 SSE 1670 Quarterly Orange, VA C-3/4 22.00 NW 3250 Quarterly Control Mineral, VA C-5/6 7.*O WSW 2430 Quarterly Louisa, VA C-7/8 11.54. WSW 2570 Quarterly Control Airborne Particulate NAPS Sewage Treatment Plant 01 0.20 NE 420 Weekly and Radioiodine Biology Lab O0A 0.64 SE 1380 Weekly Mineral, VA 03 7.10 WSW 2430 Weekly Wares Crossroads 04 5.10 WNW 2870 Weekly Route 752 05 4.20 NNE 200 Weekly Sturgeon's Creek Marina 05A 2.04 N 110 Weekly Levy, VA 06 4.70 ESE 1150 Weekly Bumpass, VA 07 7.30 SSE 1670 Weekly 10
TABLE 2-1 North Anna Power Station - 2013 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 NO. 1 UNIT 2013
- STATION Collection FROM Station Sample Media Location Station SAMPLING Distance Power Direction Degrees Frequency DIRECTION Remarks Airborne Particulate End of Route 685 21 AND Anna TABLE RADIOLOGICAL North DISTANCE 1.00 WNW 3010 Weekly and Radioiodine Route 700 22 1.00 WSW 2420 Weekly "Aspen Hills" 23 0.93 SSE 1580 Weekly Orange, VA 24 22.00 NW 3250 Weekly Control Surface Water Waste Heat Treatment Facility 08 3.37 SSE 1480 Monthly (Second Cooling Lagoon)
Lake Anna (upstream) 09A 12.90 WNW 2950 Monthly Control (Route 669 Bridge)
River Water North Anna River (downstream) 11 5.80 SE 1280 Monthly Ground Water Biology Lab 01A 0.64 SE 1380 Quarterly (Well Water)
Precipitation Biology Lab 01A 0.64 SE .1380 Monthly Aquatic Sediment Waste Heat Treatment Facility 08 3.37 "SSE .1480 Semi-Annually (Second Cooling Lagoon)
Lake Anna (upstream) 09A 12.90 WNW 2950 Semi-Annually Control (Route 669 Bridge)
North Anna River (downstream) 11 5.80 SE 1280 Semi-Annually Shoreline Soil Waste Heat Treatment Facility 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)
Soil NAPS Sewage Treatment Plant 01 0.20 NE 420 Once/3 years Fredericks Hall 02 5.30 SSW 2030 Once/3 years Mineral, VA 03 7.10 WSW 2430 Once/3 years Wares Crossroads 04 5.10 WNW 2870 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 05A 2.04 N 110 Once/3 years Levy, VA 06 4.70 ESE 1150 Once/3 years Bumpass, VA 07 7.30 SSE 1670 Once/3 years End of Route 685 21 1.00 WNW 3010 Once/3 years Route 700 (Exclusion Boundary) 22 1.00 WSW 2420 Once/3 years "Aspen Hills" 23 0.93 SSE 1580 Once/3 years Orange, VA 24 22.00 NW 3250 Once/3 years Control Milk Lakeside Dairy 12A 7.50 NW 3100 Monthly Fish Waste Heat Treatment Facility 08 3.37 SSE 1480 Semi-Annually (Second Cooling Lagoon)
Lake Orange 25 16.5 NW .3120 Semi-Annually Control Food Products (Vegetation) Stagecoach Road 14B 1.22 NNE 400 Monthly if available or at harvest Route 614 15 1.37 SE 1330 Monthly if available or at harvest Route 629/522 16 -12.60 NW 3140 Monthly if available or at harvest Control Aspen Hills 23 0.93 SSE 1580 Monthly if available or at harvest "Historic Lane" 26 1.15 S 1720 Monthly if available or at harvest 12
TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREOUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)
(84 TLDs) Quarterly Gamma Dose 2 mR+2mR mR/std. Month (12 TLDs) Annually Gamma Dose 2 mR+2mR mR/std. Month 3
Airborne Radioiodine Weekly 1-131 0.07 pCi/mi 3
Airborne Particulate Weekly Gross Beta 0.01 pCi/mi 3
Quarterly (a) Gamma Isotopic pCi/m Cs-134 0.05 Cs-137 0.06 3 2 nd Quarter Sr-89 (b) pCi/mi Composite Sr-90 (b)
Surface 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 La-140 15 Quarterly(a) Tritium (H-3) 2000 pCi/L 2 d Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)
River Water Monthly 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 La- 140 15 River Water Quarterly(a) Tritium (H-3) 2000 pCi/L 2 nd Quarter Sr-89 (b) pCi/L Composite Sr-90 (b)
Ground Water Quarterly Gamma Isotopic pCi/L (Well Water) Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 10(c)
Cs- 134 15 Cs-137 18 Ba-140 60 La- 140 15 Quarterly(a) Tritium (H-3) 2000 pCi/L 2 nd Quarter Sr-89 (b) pCi/L Sr-90 (b)
Aquatic Sediment .. Seni-Annually Gamma Isotopic pCi/kg (dry)
Cs- 134 150 Cs-137 180 Annually Sr-89 (b) pCi/kg (dry)
Sr-90 (b)
Precipitation Monthly Gross Beta 4 pCi/L Semi-Annual Gamma Isotopic pCi/L Composite " Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15
-13 134d Cs- 134 15 Cs-137 18 Ba- 140"'.
La- 14 0 1d)
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 ANALYSIS LLD REPORT UNITS Annually Sr-89 (b) pCi/kg (dry)
Sr-90 (b)
Soil Once per 3 years Gamma Isotopic pCi/kg (dry)
Cs-134 150 Cs-137 180 Sr-89 (b) pCi/kg (dry)
Sr-90 (b)
Milk Monthly 1-131 1 pCi/L Monthly Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La- 140 15 Quarterly Sr-89 (b) pCi/L Sr-90 (b)
Fish Semi-Annually Gamma Isotopic pCi/kg (wet)
Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs- 134 130.
Cs-137 150:.
Food Products Monthly, if Gamma Isotopic pCi/kg (wet)
(Broadleaf available, or Cs-134 60 Vegetation) at harvest Cs-137 80 1-131 60
- LLDs indicate those levels to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than the listed values.
(a) Quarterly composite of each location's samples are used for the required analysis (b) There are no required LLDs for Sr-89/90 (c) LLD for non-drinking water is 10 pCi/liter (d) LLD applied are those for water samples. However, 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 Environmental Station Map Environmental Station Designation Identification Designation Identification 1 (a) 01,NE-5/37 7/8 C-7/8 1A OIA,SE-13/45 1/33 N-1/33 2 (a) 02,SSW-20/52 31/63 NNW-31/63 3 (a) 03,C-5/6 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) 05 7/39 ENE-7/39 5A (a) 05A,N-2/34 9/41 E-9/41 6 (a) 06,ESE-12/44 11/43 ESE- 11/43 7 (a) 07, C-1/2 17/49 S-17/49 8 08-Water, Fish, Sediment, 19/51 SSW-19/51 Shoreline Soil 21/53 SW-21/53 9A 09A-Water sample, Sediment 23/55 WSW-23/55 12 11 -River Water, Sediment 12A 12A-Milk 25/57 W-25/57 14B 14B-Vegetation 16/48 SSE- 16/48 15 15-Vegetation 14/46 SE- 14/46 16 16-Vegetation 22/54 SW-22/54 21 (a) 21 ,WNW-27/59 26/58 W-26/58 22 (a) 22,WSW-24/56 28/60 WNW-28/60 23 (a) 23-SSE- 15/47,Vegetation 32/64 NNW-32/64 24 (a)(b) 24,C-3/4 8/40 ENE-8/40 25 (c) 25-Fish 4/36 NNE-4/36 26 26-Vegetation 10/42 E- 10/42 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil.
(b) In Orange (c) In Lake Orange 16
ESE Awmuta
- Rxed E 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 S .
Residents Meat Animals SSE Original 0 iS by ADC of Aardfut., inc, 6440 General Green VW ianmddi VA 22312. USED YVTHPERIISSION No otr repoduclon nwj be made withWot the wfitten permisslon of ADC.
19
North Anna Environmental Map Fixed Environmental Sampling Location I TLD Sampling Garden Residents
. Meat Animals Ofginal 0Mi byAOC ofVA*xkr, Inc. 8440 General Green Why, Al a, VA22312. USEDWT TH PERMISSION. No ohreprodtion
&Ium 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 wNwfltme wrVitenperrnsIon 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-1 Medium or Analysis Locations with Hi 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 Gamma 256 2 4.6(256/256) 29/61 0.52 mi. 7.7(8/8) 3.9(16/16)* 0 (mR/std. Month) Dose (1.6-9.2) NW (5.9-9.2) (3.3-4.4)
(Sector TLDs)
Direct Radiation Gamma 32 2 2.5(16/16) C-7/8 11.54 3.8 (8/8) 3.6(16/16)* 0 mi. (2.7-4.4)
(mR/std. Month) Dose (1.1-3.7) WSW (3.3-4.4)
(Pre-operational TLDs)
Direct Radiation Gamma 40 2 5.4(40/40) EPSP- 0.37 mi. 7.8(8/8) 3.5(16/16)* 0 (mR/std. Month) Dose (3.5-9.9) 09/10 ENE (6.0-9.9) (2.7-4.4)
(Emergency Sector TLDs)
Direct Radiation Gamma 48 2 3.8(44/44) 23 0.93 mi. 5.4(4/4) 3.4(4/4) 0 (mR/std. month) Dose (1.9-6.3) SSE (4.8-6.3) (2.9-3.9)
(Environmental TLDs)
Direct Radiation Gamma 12 2 3.4(11/11) 23 0.93 mi. 4.8(1/1) 3.4(1/1) 0 (mR/std. Month) Dose (2.3-4.8) SSE (4.8) (3.4)
(Annual TLDs)
Airborne Gross 676 0.01 15.4(620/624) 05 0.2 mi. 17.7(48/52) 14.8(52/52) 0 Particulates Beta (3.03-36.8) NNE (7.84-37.8) (5.90-35.7)
(IE-03 pCi/m 3 )
Air Iodine 1-131 676 0.07 (0/624) N/A N/A. N/A N/A 0 3
(pCi/m )
Airborne Gamma 52 Particulates (IE-03 pCi/m 3 ) Be-7 52 126(48/48) 04 1.0 mi. 132.8(4/4) 117(4/4) 0 (102-161) WNW (102-161) (101-140)
Cs-134 52 0.05 (0/48) N/A N/A N/A (0/4) 0 (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 Cs-137 52 0.06 (0/48) N/A N/A N/A (0/4) 0 Particulates Sr-89 13 (0/12) N/A N/A N/A (0/1) 0 (IE-03 pCi/m 3 )
Sr-90 13 (0/12) N/A N/A N/A (0/1) 0 Soil* Triennial (pCi/Kg) (dry) Gamma 12 K-40 12 15255 (11/11) 23 N/A 29000(1/1) 4660 (1/1) 0 (6320-29000) (29000) (4660)
Cs-134 12 150 N/A N/A N/A N/A N/A 0 Cs-137 12 180 208.9(10/11) 02 5.30 mi. 539(1/1) 329(1/1) 0 (93.1-539) SSW (539) (329)
Ra-226 12 - 2461 (10/11) 22 1.00 mi 3600(1/I) 3390 (1/1) 0 (1570-3600) WSW 3600 3390 Th-228 12 - 1314(11/11) 06 4.70 mi 2270(1/1) 1710(1/1) 0 (504-2270) ESE (2270) (1710)
Th-232 12 - 1191 (11/11) 06 4.70 mi 2200(I/1) 1340(1/1) 0 (530-2200) ESE (2200) (1340)
Sr-89 12 - N/A N/A N/A N/A N/A 0 Sr-90 12 N/A N/A N/A N/A N/A 0 Precipitation Monthly (pCi/liter) Gross 12 4 6.42(9/12) 01A 0.64 mi. 6.42(9/12) N/A 0 Beta (2.27-19.6) SE (2.27-19.6)
H-3 2 2000 (0/2) N/A N/A N/A N/A 0 Semiannual 2 Gamma Be-7 2 - 66(1/2) 01A 0.64 mi. 66 (1/2) N/A 0 (66) SE (66)
Mn-54 2 15 (0/2) N/A N/A N/A N/A 0 Fe-59 2 30 (0/2) N/A N/A N/A N/A 0 Co-58 2 15 (0/2) N/A N/A N/A N/A 0
- 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 Co-60 2 15 (0/2) N/A N/A N/A N/A 0 (pCi/liter)
Zn-65 2 30 (0/2) N/A N/A N/A N/A 0 Zr-95 30 (0/2) N/A N/A N/A N/A 0 Nb-95 15 (0/2) N/A N/A N/A N/A 0 1-131 10 (0/2) N/A N/A N/A N/A 0 Cs- 134 15 (0/2) N/A N/A N/A N/A 0 Cs-137 18 (0/2) N/A N/A N/A N/A 0 Ba- 140 (0/2) N/A N/A N/A N/A 0 La- 140 (0/2) N/A N/A N/A N/A 0 Th-228 (0/2) N/A N/A N/A N/A 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) 12A 7.50 mi. 1350(12/12) N/A 0
(.1220-1710) NW (1220-1710) 1-131 12 1 (0/12) 12A N/A. N/A N/A 0 Cs-137 12 18 (0/12) N/A N/A N/A N/A 0 Ba-140 12 60 (0/12) N/A N/A N/A N/A 0 La-140 12 15 (0/12) N/A N/A N/A N/A 0 Sr-89 4 (0/4), N/A N/A N/A N/A 0 (Quarterly)
Sr-90 4 (0/4) N/A N/A N/A N/A 0 (Quarterly) 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 Gamma 35 Vegetation (pCi/kg) (wet) Be-7 35 1500(28/28) 26 1.15ri 1740(7/7) 1130(7/7) 0 (368-3160) S (1210-2930) (681-1670)
K-40 35 5755(28/28) 14B 1.22mi 6110(7/7) 6110(7/7) 0 (2680-10400) NNE (4910-8300) (3970-10400) 1-131 35 60 (0/28) N/A N/A N/A (0/7) 0 Cs- 134 35 60 (0/28) N/A N/A N/A (0/7) 0 Cs-137 35 80 (0/28) 23 0.93 (0/28) (0/7) 0 Ground Tritium 4 2000 (0/4) N/A N/A N/A N/A 0 Well Water (pCi/liter) Gamma 4 Mn-54 4 15 (0/4) N/A N/A N/A N/A 0 Fe-59 4 30 (0/4) N/A N/A N/A N/A 0 Co-58 4 15 (0/4) N/A N/A N/A N/A 0 Co-60 4 15 (0/4) N/A N/A N/A N/A 0 Zn-65 4 30 (0/4) N/A N/A N/A N/A 0 Zr-95 4 30 (0/4) N/A N/A N/A N/A 0 Nb-95 4 15 (0/4) N/A N/A N/A N/A 0 1-131 4 10 (0/4) N/A N/A N/A N/A 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 Cs-134 15 (0/4) N/A N/A N/A N/A 0 Well Water (pCi/liter) Cs-137 18 (0/4) N/A N/A N/A N/A 0 Ba- 140 60 (0/4) N/A N/A N/A N/A 0 La- 140 15 (0/4) N/A N/A N/A N/A 0 Sr-89 (0/1) N/A N/A N/A N/A 0 Sr-90 (0/1) N/A N/A N/A N/A 0 River Water Tritium 2000 4010(4/4) II 5.80 mi. 4010(4/4) (0/4)* 0 (pCi/liter) (3750-4330) SE (3750-4330)
Gamma Mn-54 15 (0/12) N/A N/A N/A (0/12)* 0 Fe-59 30 (0/12) N/A N/A N/A (0/12)* 0 Co-58 15 (0/12) N/A N/A N/A (0/12)* 0 Co-60 15 (0/12) N/A N/A N/A (0/12)* 0 Zn-65 30 (0/12) N/A N/A N/A (0/12)* 0 Zr-95 12 30 (0/12) N/A N/A N/A (0/12)* 0 Nb-95 12 15 (0/12) N/A N/A N/A (0/12)* 0 1-131 12 1 (0/12) N/A N/A N/A (0/12)* 0 Cs-134 12 15 (0/12) N/A N/A N/A (0/12)* 0 Cs-137 12 18 (0/12) N/A N/A N/A (0/12)* 0
- 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 Ba-140 12 60 (0/12) N/A N/A N/A (0/12)* 0 (pCi/liter)
La-140 12 15 (0/12) N/A N/A N/A (0/12)* 0 Sr-89 I - (0/1) N/A N/A N/A (0/1)* 0 Sr-90 I - (0/1) N/A N/A N/A (0/1)* 0 Tritium 8 2000 4080(4/4) 08 3.37 mi. 4080(4/4) (0/4) 0 Surface Water (pCi/L) (3850-4370) SSE (3850-4370)
Ganmima 24 Mn-54 24 15 (0/12) N/A N/A N/A (0/12) 0 Fe-59 24 30 (0/12) N/A N/A N/A (0/12) 0 Co-58 24 15 (0/12) N/A N/A N/A (0/12) 0 Co-60 24 15 (0/12) N/A N/A N/A (0/12) 0 Zn-65 24 30 (0/12) N/A N/A N/A (0/12) 0 Zr-95 24 30 (0/12) N/A N/A N/A (0/12) 0 Nb-95 24 30 (0/12) N/A N/A N/A (0/12) 0 1-131 24 1 (0/12) N/A N/A N/A (0/12) 0 Cs-134 24 15 (0/12) N/A N/A N/A (0/12) 0 Cs-137 24 18 (0/12) N/A N/A N/A (0/12) 0 Ba-140 24 60 (0/12) N/A N/A N/A (0/12) 0 La- 140 24 15 (0/12) N/A N/A N/A (0/12) 0
- 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 Sr-89 1 (0/1) N/A N/A N/A (0/1) 0 (pCi/liter) 1 Sr-90 (0/1) N/A N/A N/A (0/1) 0 Sediment Silt Gamma 6 (pCi/kg) K-40 6 - 10990(4/4) 11 5.80 mi. 15900(2/2) 12250(2/2) 0 (2340-16000) SE (15800-(12000-12500) 16000)
Cs-134 6 150 (0/4) N/A N/A N/A (0/2) 0 (176)
Cs-137 6 180 (0/4) N/A N/A. N/A 112(1/2) 0 (112)
Ra-226 6 - 2132.5(4/4) 11 5.80 mi. 2345(2/2) 2220(2/2) 0 (1820-2540) SE (2150-2540) (2090-2350)
Th-228 6 1214(4/4)- 1 5.80 mi. 1565(2/2) 561(2/2) 0 (548-1760) SE (1370-1760) (548-574)
Th-232 6 1014.5 (4/4) 11 5.80 mi. 1265(2/2) 618.5(2/2) 0 (506-1310) SE (1220-1310) (506-731)
(Annually)
Sr-89 3 (0/2) N/A N/A N/A (0/1) 0 Sr-90 3 - (0/2) N/A N/A N/A (0/1) 0 Shoreline Soil Gamma 2 (pCi/kg) (dry) K-40 2 2650(2/2) 08 3.37 mi. 2650(2/2) N/A 0 (1360-3940) SSE (1360-3940)
Cs- 134 2 150 (0/2) N/A NA (0/2) N/A 0 Cs-137 2 180 (0/2) N/A NA (0/2) N/A 0 Ra-226 2 1520(1/2) 08 3.37 mi. 1520(1/2) N/A 0 (1520) 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 IDirection Range Range ments Shoreline Soil (pCi/kg) (dry)
Th-228 2 819(2/2) 08 3.37 mi. 819(2/2) N/A 0 (809-829) SSE (809-829)
Th-232 2 725.5 (2/2) 08 3.37 mi. 725.5(2/2) N/A 0 (705-746) SSE (705-746)
(Annually)
Sr-89 (0/1) N/A N/A N/A N/A 0 1
Sr-90 (0/1) N/A N/A N/A N/A 0 Gamma 8 Fish (pCi/kg) (.wet)
K-40 8 2450(4/4) 8 3.37 mi. 2450(4/4) 2447.5(4/4) 0 (2240-2650) SSE (2240-2650) (1370-2850)
Mn-54 8 130 (0/4) N/A N/A N/A (0/4) 0 Fe-59 8 260 (0/4) N/A N/A N/A (0/4) 0 Co-58 8 130 (0/4) N/A N/A N/A (0/4) 0 Co-60 8 130 (0/4) N/A N/A N/A (0/4) 0 Zn-65 8 260 (0/4) N/A N/A N/A (0/4) 0 Cs-134 8 130 (0/4) N/A N/A N/A (0/4) 0 Cs-137 8 150 (0/4) N/A N/A N/A (0/4) 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 RESLJLTS Page mR/Std. Month (30.4 days) +/- 2 Sigma 1 of 4 First Quarter Second Quarter Third Quarter Fourth Quartei Quarterly*
Station Average
+/- 2 s.d.
N-1 5.3 4.4 5.5 5.7 5.4 + 1- 1.3 N-33 6.2 4.7 5.4 6.2 N-2 3.8 2.5 2.8 4.4 3.3 +/- 1.3 N-34 3.3 2.5 3.6 3.3 NNE-3 7.7 5.6 6.9 7.4 6.8 + 1- 1.5 NNE-35 7.1 5.9 6.4 7.3 NNE-4 4.6 3.6 4.6 4.2 4.4 +/- 0.9 NNE 36 4.5 3.9 5.0 4.8 NE-5 5.2 4.4 3.6 4.2 4.7 +/- 1.6 NE-37 5.5 4.5 4.1 6.0 NE-6 3.3 2.6 3.3 4.3 3.4 + 1-i.2 NE-38 3.5 2.7 3.6 4.2 ENE-7 6.0 4.7 4.3 5.4 5.3 + 1-i.6 ENE-39 6.6 4.5 6.0 5.2
- 2.8 ENE-8 2.2 2.3 3.5 2.7 + 1- 1.0 ENE-40 2.7 2.4 2.4 3.4
'E-9 - 6.1 3.9 5.4 4.9 5.2 +/- 1.7 E-41 6.1 4.1 5.4 5.9 E-10 5.5 3.9 4.7 5.1 4.9 + 1- 1.4 E-42 5.7 3.9 4.8 5.5 ESE-1 1 4.3 4.6 4.5 5.3 4.6 +/- 1.0 ESE-43 4.6 3.7 4.8 5.0 ESE-12 5.8 4.9 5.0 5.0 5.0 +/- 1.0 ESE-44 5.4 4.1 4.5 5.1 SE-13 5.8 3.8 5.0 5.3 4.8 +/- 1.6 SE-45 4.6 4.4 3.7 5.8 SE-14 8.0 5.1 5.9 7.6 6.7 +1- 2.0 SE-46 7.1 6.5 6.1 7.6 SSE-15 6.3 5.0 5.2 5.0 5.2 +/- 1.3 SSE-47 5.1 4.1 5.4 5.7 SSE-16 4.3 2.1 3.0 3.6 3.0 + 1- 1.5 SSE-48 3.1 2.5 2.3 3.3
- Average of collocated TLDs.
33
TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS Page mRJStd. Month (30.4 days) +/- 2 Sigma 2 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly*
Station Average
+/- 2 s.d.
S-17 5.7 3.9 4.8 6.2 5.1 +/- 1.4 S-49 4.9 5.3 4.6 5.0 S-18 3.1 1.7 2.6 2.9 2.7 +/- 1.1 S-50 2.8 2.1 2.6 3.4 SSW-19 7.4 5.7 5.3 5.8 6.2 +/- 1.6 SSW-51 7.0 5.3 6.9 6.2 SSW-20 2.8 2.0 2.8 3.1 2.7 +/- 1.0 SSW-52 2.5 2.1 3.1 3.5 SW-21 4.6 4.1 4.8 5.4 4.7 +/- 1.1 SW-53 5.3 3.7 4.8 4.7 SW-22 5.7 3.6 4.7 5.3 4.6 +/- 1.5 SW-54 4.2 3.6 4.8 4.5 WSW-23 5.3 4.8 5.5 6.2 5.5 +/- 1.5 WSW-55 6.8 4.5 5.4 5.6 WSW-24 5.5 3.9 4.4 4.9 4.6 +/- 1.4 WSW-56 5.5 3.6 4.3 4.7 W-25 8.6 7.6 5.8 8.0 7.4 +/- 2.3 W-57 8.5 5.8 6.9 8.3 W-26. 3.7 2.8 3.1 3.8 3.3 +/- 1.0 W-58 3.7 2.5 3.6 3.0 WNW-27 4.1 3.0 2.8 4.2 3.4 +/- 1.1 WNW-59 3.8 2.8 3.3 3.1 WNW-28 3.3 2.7 2.3 3.6 3.0 +/- 0.9 WNW-60 3.3 2.6 2.6 3.3 NW-29 7.4 7.7 7.5 8.6 7.7 +/- 2.3 NW-61 8.6 5.9 6.3 9.2 NW-30 2.5 1.7 2.0 3.0 2.2 +/- 1.1 NW-62 2.3 1.9 1.6 2.9 NNW-31 4.5 2.8 2.8 4.7 3.8 +/- 1.5 NNW-63 4.1 3.1 4.0 4.2 NNW-32 3.5 3.3 3.8 5.0 3.8 +/- 1.2 NNW-64 3.7 3.1 4.3 3.9 Mean 4.6 +/- 1.5
- Average of collocated TLDs.
34
TABLE 3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS Page mR/Std. Month (30.4 days) +/- 2 Sigma 3 of 4 First Quarter Second Quarter Third Quarter Fourth Quarter Qua rterly*
Station Average
+/- 2 s.d.
C-1 4.1 2.7 2.8 3.4 3.3 +/- 1.1 C-2 4.0 2.7 2.9 3.5 C-3"* 3.4 2.8 2.9 4.2 3.3 +/- 1.0 C-4"* 3.3 2.7 3.1 3.8 C-5 2.4 2.1 2.4 3.4 2.5 +/- 1.0 C-6 2.9 2.0 1.9 2.9 C-7"* 3.9 4.4 3.8 4.3 3.8 +/- 0.8 C-8"* 4.0 3.3 3.3 3.5 2.9 +/- 1.3 3.5 +/- 1.1 EPSA-01** 5.3 4.9 3.7 5.2 4.9 +/- 1.3 EPSA-02*** 5.2 4.1 5.3 5.5 EPSF-03*** 4.5 4.2 4.4 5.2 4.5 +/- 1.2 EPSF-04*** 5.5 4.0 3.7 4.6 EPSR-05*** 4.9 5.4 4.4 7.0 5.3 +/- 1.7 EPSR-06t** 5.2 4.5 5.3 5.8 EPSJ-07***' 6.0--. 3.7 4.0 3.8 .4.4 +/- 1.7 EPSJ-08*A." 4.5 3.5 4.3 EPSP-09*** 9.9 8.5 6.0 7.9. 7.8 +/- 2.8 EPSP-1 0*** 9.1 6.5 6.5 8.2 Mean 5.4 +/- 3.1
- 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 page Gross Beta Radioactivity 1 of 4
[10.3 pCi/m3],
Period Station Station Station Station Station Station Station Ending 01 02 03 04 05 06 07 01/02/13 1.08E+01 +/- 2.70E+00 1.48E+01 +/- 2.92E+00 1.26E+01 +/- 2.86E+00 1.09E+01 +/- 2.74E+00 1.55E+01 +/- 2.96E+00 1.36E+01 +/- 2.86E+00 1.17E+01 +/- 2.77E+00 01/08/13 3.08E+01 +/- 3.90E+00 2.14E+01 +1- 3.44E+00 3.23E+01 +/- 3.96E+00 3.26E+01 +/- 3.97E+00 3.78E+01 +/- 4.19E+00 3.06E+01 +/- 3.88E+00 3.39E+01 +/- 4.03E+00 01/16/13 1.92E+01 +/- 2.76E+00 2.05E+01 +/- 2.82E+00 1.83E+01 +/- 2.72E+00 2.28E+01 +/- 2.92E+00 2.40E+01 +/- 2.98E+00 2.33E+01 +/- 2.95E+00 1.77E+01 +/- 2.69E+00 01/22/13 1.59E+01 +/- 3.15E+00 1.65E+01 +/- 3.20E+00 1.61E+01 +/- 3.18E+00 1.76E+01 +- 3.26E+00 2.30E+01 +/- 3.53E+00 1.93E+01 +/- 3.34E+00 1.82E+01 +/- 3.28E+00 01/29/13 2.24E+01 +/- 3.18E+00 2.33E+01 +/- 3.22E+00 2.68E+01 +/- 3.38E+00 2.66E+01 +/ 3.37E+00 2.73E+01 +/- 3.40E+00 2.49E+01 +/- 3.29E+00 2.53E+01 +/- 3.31E+00 02/05/13 2.52E+01 +/- 3.47E+00 2.28E+01 +1- 3.36E+00 1.96E+01 +1- 3.22E+00 2.54E+01 +/ 3.48E+00 2.36E+01 +/- 3.40E+00 2.05E+01 +/- 3.26E+00 2.22E+01 +/- 3.33E+00 02/13/13 1.43E+01 +/- 2.53E+00 1.20E+01 +/- 2.41E+00 1.49E+01 +/- 2.56E+00 1.89E+01 +/ 2.76E+00 1.78E+01 +/- 2.70E+00 1.80E+01 +/- 2.72E+00 1.38E+01 +/- 2.51 E+00 02/20/13 1.10E+01 +/- 2.65E+00 1.42E+01 +/- 2.88E+00 1.17E+01 +/- 2.74E+00 1.28E+01 +/ 2.79E+00 1.41E+01 +/- 2.86E+00 1.45E+01 +/- 2.87E+00 1.20E+01 +/- 2.77E+00 02/27/13 6.27E+00 +/- 2.47E+00 6.93E+00 +/- 2.49E+00 8.59E+00 +/- 2.46E+00 8.69E+00 +/- 2.61E+00 1.20E+01 +/- 2.80E+00 1.15E+01 +/- 2.78E+00 7.51 E+00 +/- 2.52E+00 03/05/13 7.84E+00 +/- 2.79E+00 5.93E+00 +/- 2.62E+00 5.35E+00 +/- 2.52E+00 1.01E+01 +- 2.86E+00 8.40E+00 +/- 2.76E+00 7.38E+00 +/- 2.70E+00 7.59E+00 +/- 2.72E+00 03/12/13 7.88E+00 +/- 2.34E+00 6.77E+00 +/- 2.66E+00 9.60E+00 +/- 2.66E+00 7.99E+00 +/ 2.39E+00 1.06E+01 +/- 2.85E+00 6.45E+00 +/- 2.24E+00 03/19/13 1.35E+01 +/- 2.94E+00 1.46E+01 +/- 2.99E+00 1.04E+01 +/- 2.77E+00 1.25E+01 +/ 2.88E+00 1.59E+01 +/- 3.06E+00 1.09E+01 +/ 2.81E+00 03/26113 1.28E+01 +/- 2.67E+00 1.13E+01 +/- 2.58E+00 1.08E+01 +/- 2.49E+00 1.41E+01 +/ 2.69E+00 1.27E+01 +/- 2.64E+00 1.41E+01 +/- 2.72E+00 04/02/13 9.78E+00 +/- 2.68E+00 9.93E+00 +/- 2.69E+00 1.02E+01 +/- 2.63E+00 9.91E+00 +/ 2.64E+00 9.16E+00 +/- 2.63E+00 7.26E+00 +/- 2.52E+00 04/09/13 1.04E+01 +/- 2.63E+00 1.61E+01 +/- 32tE+00 1.60E+01 +/- 2.98E+00 2.03E+01 +- 3.18E+00 1.86E+01 +1- 3.58E+00 1.69E+01 +/- 3.00E+00 2.03E+01 +/- 3.20E+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 1.33E+01 +/- 2.39E+00 1.47E+01 +/- 2.47E+00 1.25E+01 +1 2.32E+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 1.57E+01 +/- 3.28E+00 1.61E+01 +/ 3.34E+00 1.35E+01 +1 3.29E+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 1.20E+01 +- 2.84E+00 1.12E+01 +1 2.80E+00 8.74E+00 +- 2.62E+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 1.21E+01 +/ 2.34E+00 1.20E+01 +/- 2.34E+00 8.97E+00 +1 2.18E+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 1.24E+01 +- 2.94E+00 1.37E+01 +1 3.01E+00 1.22E+01 +/ 2.87E+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 1.97E+01 +/ 3.07E+00 2.03E+01 +1 3.11E+00 1.31E+01 +- 2.74E+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 1.44E+01 +/ 2.68E+00 1.50E+01 +- 2.71E+00 1.41E+01 +/ 2.66E+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 1.60E+01 +- 2.70E+00 1.41E+01 +/ 2.59E+00 1.51E+01 +/ 2.65E+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 1.09E+01 +/ 2.51E+00 1.21E+01 +/- 2.58E+00 6.18E+00 +- 2.21 E+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 1.80E+01 +- 2.92E+00 1.50E+01 +/ 2.76E+00 1.34E+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 1.07E+01 +- 2.60E+00 8.58E+00 +1 2.48E+00 8.42E+00 +/- 2.49E+00
- Sample not obtained due to sampler not operating.
37
Table 3-3 Air Particulate page Gross Beta Radioactivity 2 of 4
[10.3 pCi/m 3]
Period Station Station Station Station Station Station Ending 21 22 23 _:I 24* 01A 05A I 01/02/13 9.27E+00 +/- 2.62E+00 9.95E+00 +/- 2.66E+00 1.05E+01 +/- 2.692+00 1.35E+01 +/- 2.86E+00 1.02E+01 +/- 2.67E+00 1.52E+01 +/- 2.95E+00 01/08/13 3.34E+01 +/- 4.01E+00 3.33E+01 +/- 4.00E+00 3.20E+01 +/- 3.95E+00 3.57E+01 4/- 4.11E+00 2.99E+01 +/- 3.85E+00 3.42E+01 +/ 4.04E+00 01/16/13 2.19E+01 +/- 2.89E+00 1.82E+01 +/- 2.71E+00 2.06E+01 +/- 2.83E+00 2.18E+01 +/- 2.88E+00 1.83E+01 +/- 2.72E+00 2.13E+01 +/ 2.86E+00 01/22/13 1.46E+01 +/- 3.08E+00 1.82E+01 +/- 3.28E+00 1.47E+01 +/- 3.09E+00 .1.52E+01 +/- 3.12E+00 1.39E+01 +/- 3.05E+00 1.30E+01 +/- 3.01 E+00 01/29/13 2.67E+01 +/- 3.37E+00 2.07E+01 +/- 3.09E+00 2.78E+'O1 +/- 3.42E+00 2.52E+01 +/- 3.31E+00 2.19E+01 +/- 3.15E+00 2.33E+01 +/- 3.22E+00 02105113 1.80E+01 +/- 3.14E+00 1.90E+01 +/- 3.19E+00 2.22E+01 +/- 3.33E+00 2.12E+01 +/- 3.29E+00 1.29E+01 +/- 2.89E+00 2.00E+01 4/- 3.23E+00 02/13/13 1.74E+01 +/- 2.69E+00 1.42E+01 +/- 2.53E+00 1.57E+01 +/- 2.60E+00 1.38E+01 +/- 2.51E+00 1.33E+01 +/- 2.48E+00 1.69E+01 +/- 2.66E+00 02/20/13 1.27E+01 +/- 2.80E+00 9.43E+00 +/- 2.61E+00 1.22E+01 +/- 2.76E+00 1.20E+01 +/ 2.77E+00 1.04E+01 +/- 2.62E+00 1.07E+01 +/- 2.68E+00 02/27/13 7.37E+00 +/- 2.56E+00 7.52E+00 +/- 2.57E+00 8.71 E+00 +/- 2.58E+00 7.47E+00 +/ 2.57E+00 8.56E+00 +/- 2.61E+00 8.61E+00 +/- 2.62E+00 03/05/13 5.85E+00 +/- 2.55E+00 8.36E+00 +/- 2.72E+00 7.68E+00 +/- 2.76E+00 5.91E+00 +/ 2.55E+00 6.64E+00 +/- 2.70E+00 8.55E+00 +/- 2.76E+00 03/12/13 6.14E+00 +/- 2.29E+00 9.31 E+00 4/- 2.43E+00 7.03E+00 +/- 2.34E+00 5.90E+00 +/ 2.22E+00 8.62E+00 +/ 2.38E+00 6.95E+00 +/- 2.29E+00 03/19/13 1.33E+01 +- 2.92E+00 1.07E+01 +/- 2.79E+00 1.55E+01 +/- 3.03E+00 <3.55E+00 1.40E+01 +/- 2.97E+00 1.30E+01 +/- 2.91 E+00 03/26/13 1.15E+01 +/ 2.58E+00 1.33E+01 +/- 2.68E+00 1.27E+01 +/- 2.64E+00 1.21E+01 +/- 2.60E+00 7.97E+00 +/- 2.38E+00 8.18E+00 +/- 2.37E+00 04/02/13 8.66E+00 +/ 2.60E+00 8.21E+00 +/ 2.57E+00 1.14E+01 +/ 2.75E+00 1.26E+01 +/- 2.80E+00 1.09E+01 +/ 2.73E+00 8.25E+00 +/- 2.57E+00 04/09/13 1.34E+01 4/- 2.87E+00 2.05E+01 +/ 3.21E+00 - 1.73E+01 +/ 3.05E+00 1.81E+01 +/ 3.09E+00 1.68E+01 +/- 2.96E+00 1.43E+01 +/- 2.88E+00 04/17/13 1.12E+01 +/- 2.25E+00 1.24E+01 +/ 2.32E+00 1.34E+01 +/ 2.37E+00 1.42E+01 +/- 2.42E+00 9.74E+00 4/- 2.17E+00 1.23E+01 +/- 2.33E+00 04/23/13 1.07E+01 +/- 3.16E+00 1.52E+01 +/ 3.26E+00 1.45E+01 +/ 3.40E+00 1.27E+01 +/- 3.14E+00 1.22E+01 +/- 3.09E+00 1.23E+01 +/- 3.15E+00 04/30/13 1.05E+01 +/- 2.75E+00 9.25E+00 +/- 2.68E+00 1.04E+01 +/ 2.70E+00 1.01E+01 +/- .2.74E+00 9.34E+00 +/- 2.76E+00 9.97E+00 +/ 2.73E+00 05/08/13 8.99E+00 +/- 2.17E+00 8.59E+00 4/- 2.14E+00 1.06E+01 4/- 2.29E+00 7.94E+00 +/- 2.10E+00 9.09E+00 +/- 2.13E+00 8.34E+00 +/ 2.13E+00 05/14/13 1.34E+01 +/- 3.00E+00 1.16E+01 +/- 2.90E+00 1.38E+01 +/- 2i95E+00 1.11E+01 +/- 2.87E+00 1.01E+01 +/- 2.77E+00 9.53E+00 +/ 2.76E+00 05/21/13 1.50E+01 +/- 2.83E+00 1.63E+01 +/- 2.90E+00 1.53E+01 +/- 2.86E+001 1.33E+01 +/- 2.75E+00 1.47E+01 +/- 2.83E+00 1.39E+01 +/ 2.78E+00 05/28/13 8.71E+00 +/- 2.34E+00 1.06E+01 +/- 2.46E+00 1.33E+01 +/- 2.62E+00 1.47E+01 4/- 2.70E+00 1.22E+01 +/- 2.55E+00 1.27E+01 +/ 2.58E+00 06/04/13 1.39E+01 +/- 2.58E+00 1.39E+01 +/- 2.58E+00 1.16E+01 +/- 2.45E+00 1.91E+01 +/- 2.87E+00 1.29E+01 +/- 2.53E+00 1.24E+01 4/- 2.49E+00 06/11/13 7.77E+00 +/- 2.33E+00 8.21 E+00 +/- 2.35E+00 8.98E+00 +/- 2.39E+00 7.82E+00 +/ 2.32E+00 6.32E+00 +/- 2.22E+00 9.13E+00 +/- 2.40E+00 06/18/13 1.20E+01 +/- 2.59E+00 1.38E+01 +/- 2.70E+00 1.60E+01 +/- 2.82E+00 .1.23E+01 +/ 2.62E+00 1.14E+01 +/- 2.57E+00 1.47E+01 +/- 2.75E+00 06/25/13 6.44E+00 +/ 2.33E+00 9.15E+00 +/- 2.50E+00 7.43E+00 +/- 2.44E+00 1.07Et01 +/- 2.56E+00 8.42E+00 +/- 2.53E+00 7.49E+00 +/- 2.41 E+00
- Control Station 38
Table 3-3 Air Particulate page Gross Beta Radioactivity 3 of 4 3
[10 pCi/m 3]
Period Station Station Station Station Station Station Station Ending I I I 03 I I I I 07 I 07/03/13 1.41 E+01 2.35E+00 1.43E+01 2.38E+00 1.25E+01 2.28E+00 1.23E+01 2.27E+00 1.37E+01 2.34E+00 1.13E+01 2.21E+00 1.49E+01 2.40E+00 07/09/13 7.47E+00 2.47E+00 9.32E+00 2.62E+00 9.46E+00 2.73E+00 8.30E+00 2.59E+00 7.84E+00 2.55E+00 6.19E+00 2.43E+00 6.93E+00 2.47E+00 07/16/13 1.14E+01 2.64E+00 1.24E+01 2.71 E+00 1.15E+01 2.62E+00 9.71 E+00 2.58E+00 1.28E+01 2.71E+00 8.95E+00 2.51E+00 1.04E+01 2.60E+00 07/24/13 1.61E+01 2.62E+00 1.71E+01 2.67E+00 1.64E+01 2.63E+00 1.80E+01 2.71E+00 1.70E+01 2.66E+00 1.58E+01 2.60E+00 1.55E+01 2.59E+00 07/31/13 1.30E+01 2.63E+00 1.74E+01 2.87E+00 1.39E+01 2.71E+00 1.42E+01 2.67E+00 1.61E+01 2.82E+00 1.44E+01 2.72E+00 1.56E+01 2.78E+00 08/06/13 1.25E+01 3.04E+00 1.59E+01 3.22E+00 1.80E+01 3.33E+00 1.76E+01 3.31E+00 1.53E+01 3.19E+00 1.81E+01 3.34E+00 1.43E+01 3.14E+00 08/14/13 1.75E+01 2.67E+00 1.75E+01 2.67E+00 2.26E+01 +1- 2.91 E+00 1.79E+01 2.69E+00 2.34E+01 2.94E+00 2.11E+01 2.84E+00 2.02E+01 2.80E+00 08/20/13 5.32E+00 2.58E+00 9.07E+00 2.82E+00 1.05E+01 2.90E+00 8.64E+00 2.80E+00 1.13E+01 2.96E+00 8.81 E+00 2.81E+00 9.07E+00 2.82E+00 08/27/13 1.48E+01 2.72E+00 1.42E+01 2.66E+00 1.40E+01 2.61E+00 1.46E+01 2.67E+00 1.23E+01 2.54E+00 1.65E+01 2.78E+00 1.61E+01 2.76E+00 09/03/13 2.22E+01 3.10E+00 2.94E+01 3.46E+00 2.52E+01 3.31E+00 2.70E+01 3.36E+00 2.65E+01 3.35E+00 2.76E+01 3.39E+00 2.86E+01 3.43E+00 09/10/13 1.69E+01 2.82E+00 2.16E+01 3.07E+00 1.92E+01 2.96E+00 1.86E+01 2.92E+00 2.00E+01 2.99E+00 1.80E+01 2.89E+00 2.31E+01 3.15E+00 09/17/13 1.46E+01 2.90E+00 2.49E+01 3.37E+00 2.40E+01 3.28E+00 2.36E+01 3.30E+00 2.93E+01 3.54E+00 2.46E+01 3.35E+00 2.42E+01 3.33E+00 09/24/13 1.47E+01 2.73E+00 1.84E+01 2.91E+00 1.17E+01 2.51E+00 1.59E+01 2.76E+00 1.39E+01 2.66E+00 1.85E+01 2.91 E+00 1.52E+01 2.74E+00 10/02/13 1.37E+01 2.50E+00 1.56E+01 2.55E+00 1.74E+01 2.74E+00 1.75E+01 2.72E+00 1.80E+01 2.73E+00 1.65E+01 2.65E+00 1.40E+01 2.53E+00 10/08/13 2.26E+01 3.35E+00 3.29E+01 3.87E+00 2.44E+01 +/- 3.53E+00 3.08E+01 3.79E+00 3.33E+01 3.91E+00 2.85E+01 3.68E+00 3.30E+01 3.88E+00 10/16/13 1.07E+01 2.20E+00 1.33E+01 2.33E+00 1.39E+01 2.33E+00 1.04E+01 2.15E+00 1.43E+01 2.37E+00 1.16E+01 2.22E+00 1.21E+01 2.25E+00 10/22/13 1.54E+01 3.13E+00 2.25E+01 3.56E+00 1.76E+01 +/- 3.34E+00 1.96E+01 3.42E+00 2.36E+01 3.63E+00 1.65E+01 3.26E+00 2.10E+01 3.48E+00 10/30/13 1.94E+01 2.75E+00 2.52E+01 3.00E+00 2.46E+01 2.94E+00 2.64E+01 3.04E+00 2.47E+01 2.96E+00 2.57E+01 3.01E+00 2.17E+01 2.84E+00 11/05/13 2.92E+01 3.75E+00 2.38E+01 3.52E+00 2.16E+01 3.47E+00 2.74E+01 3.71E+00 2.49E+01 3.61E+00 2.84E+01 3.77E+00 1.71E+01 3.18E+00 11/13/13 1.OOE+01 2.26E+00 1.31E+01 2.43E+00 1.64E+01 2.61 E+00 1.54E+01 2.56E+00 1.54E+01 2.56E+00 1.94E+01 2.76E+00 1.67E+01 2.62E+00 11/20/13 1.48E+01 2.71E+00 1.47E+01 2.71E+00 1.04E+01 2.46E+00 1.66E+01 2.81E+00 1.41E+01 2.67E+00 1.26E+01 2.59E+00 1.55E+01 2.75E+00 11/26/13 1.82E+01 3.24E+00 1.53E+01 3.07E+00 1.33E+01 2.95E+00 1.61E+01 3.12E+00 1.37E+01 2.98E+00 1.48E+01 3.04E+00 1.48E+01 3.04E+00 12/03/13 1.91E+01 2.99E+00 2.40E+01 3.24E+00 2.05E+01 3.07E+00 2.07E+01 3.08E+00 2.34E+01 3.21 E+00 2.43E+01 3.25E+00 2.38E+01 3.22E+00 12/11/13 2.20E+01 2.86E+00 1.80E+01 2.68E+00 1.26E+01 2.41E+00 2.22E+01 2.87E+00 1.68E+01 2.62E+00 2.00E+01 2.77E+00 1.36E+01 2.46E+00 12/17/13 2.82E+01 3.98E+00 1.67E+01 3.45E+00 1.78E+01 3.46E+00 2.23E+01 3.76E+00 1.70E+01 3.43E+00 2.36E+01 3.78E+00 2.12E+01 3.67E+00 12/23/13 1.58E+01 3.22E+00 1.44E+01 3.13E+00 1.46E+01 +/- 3.14E+00 1.80E+01 3.32E+00 1.56E+01 3.20E+00 1.79E+01 3.33E+00 1.62E+01 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 page Gross Beta Radioactivity 4 of 4
[10-3 pCi/m 3]
Period Station Station Station Station Station Station Endin0// 21 I22 23 24* I 01A 05A 07/03/13 1.03E+01 +/- 2.14E+00 1.44E+01 +/- 2.38E+00 1.35E+01 +/- 2.33E+00 1.43E+01 +/- 2.38E+00 1.13E+01 +/- 2.252+00 1.062+01 +/- 2.17E+00 07/09/13 5.70E+00 +/- 2.40E+00 6.91E+00 +/- 2.52E+00 7.11E+00 +/- 2.46E+00 6.25E+00 +/- 2.482+00 <3.15E+00 4.86E+00 +/- 2.352+00 07/16/13 1.16E+01 +/- 2.65E+00 9.56E+00 +/- 2.54E+00 1.21E+01 +/- 2.68E+00 1.04E+01 +/- 2.59E+00 9.63E+00 +/- 2.54E+00 9.52E+00 +/- 2.53E+00 07/24/13 1.55E+01 +/- 2.59E+00 1.21 E+01 +/- 2.42E+00 1.57E+01 +/- 2.60E+00 1.04E+01 +/- 2.33E+00 1.37E+01 +/- 2.50E+00 1.382+01 +/- 2.50E+00 07/31/13 1.62E+01 +/- 2.84E+00 9.41E+00 +/- 2.39E+00 1.36E+01 +/- 2.67E+00 1.20E+01 +/- 2.57E+00 1.43E+01 +/- 2.71 E+00 1.012+01 +/- 2.47E+00 08/06/13 1.51E+01 +/- 3.18E+00 1.56E+01 +/- 3.21E+00 1.69E+01 +/- 3.27E+00 1.09E+01 +/- 2.94E+00 1.032+01 +/- 2.91 E+00 1.23E+01 +/- 3.02E+00 08/14/13 2.18E+01 +/- 2.88E+00 1.71 E+01 +/- 2.66E+00 2.01E+01 +/- 2.79E+00 1.89E+01 +/- 2.74E+00 1.602+01 +/- 2.60E+00 1.94E+01 +/- 2.76E+00 08/20/13 6.60E+00 +/- 2.66E+00 8.43E+00 +/- 2.77E+00 5.85E+00 +/- 2.62E+00 8.46E+00 +/- 2.79E+00 5.41 E+00 +/- 2.59E+00 8.64E+00 +/- 2.80E+00 08/27/13 1.54E+01 +/- 2.69E+00 1.36E+01 +/- 2.60E+00 1.34E+01 +/- 2.63E+00 1.642+01 +/- 2.74E+00 1.19E+01 +/- 2.55E+00 1.34E+01 +/- 2.60E+00 09/03/13 2.67E+01 +/- 3.38E+00 2.13E+01 +/- 3.12E+00 2.50E+01 +/- 3.25E+00 2.49E+01 +/- 3.31 E+00 2.312+0 1 +/- 3.16E+00 2.06E+01 +/- 3.08E+00 09/10/13 1.71E+01 +/- 2.85E+00 1.89E+01 +/- 2.95E+00 1.81E+01 +/- 2.89E+00 1.72E+01 +/- 2.852+00 1.582+01 +/- 2.76E+00 1.65E+01 +/- 2.81 E+00 09/17/13 2.70E+01 +/- 3.40E+00 1.86E+01 +/- 3.18E+00 2.08E+01 +/- 3.19E+00 2.12E+01 +/- 3.14E+00 2.13E+01 +/- 3.23E+00 1.95E+01 +/- 3.09E+00 09/24/13 1.34E+01 +/- 2.64E+00 1.41 E+01 +/- 2.73E+00 1.92E+01 +/- 2.94E+00 1.48E+01 +/- 2.71E+00 1.10E+01 +/- 2.51 E+00 1.69E+01 +/- 2.85E+00 10/02/13 1.01E+01 +/- 2.32E+00 1.20E+01 +/- 2.43E+00 1.48E+01 +/- 2.58E+00 1.21E+01 +/- 2.43E+00 1.24E+01 +/- 2.442+00 1.28E+01 +/- 2.472+00 10/08/13 1.62E+01 +/- 3.13E+00 2.74E+01 +/- 3.67E+00 2.35E+01 +/- 3.432+00 1.74E+01 +/- 3.17E+00 1.97E+01 +/- 3.202+00 2.98E+01 +/- 3.76E+00 10/16/13 7.78E+00 +/- 1.97E+00 1.02E+01 +/- 2.12E+00 1.02E+01 +/- 2.16E+00 1.10E+01 +/- 2.16E+00 8.85E+00 +/- 2.092+00 1.31 E+01 +/- 2.30E+00 10/22/13 1.13E+01 +/- 2.98E+00 1.56E+01 +/- 3.23E+00 1.79E+01 +/- 3.302+00 1.55E+01 +/- 3.252+00 1.77E+01 +/- 3.262+00 2.04E+01 +/- 3.48E+00 10/30/13 1.33E+01 +/- 2.40E+00 2.02E+01 +/- 2.75E+00 1.79E+01 +/- 2.67E+00 1.58E+01 +/- 2.52E+00 1.85E+01 +/- 2.71 E+00 2.09E+01 +/- 2.78E+00 11/05/13 2.29E+01 +/- 3.53E+00 2.07E+01 +/- 3.41 E+00 2.58E+01 +/- 3.60E+00 2.09E+01 +/- 3.45E+00 1.902+01 +/- 3.25E+00 2.44E+01 +/- 3.59E+00 11/13/13 1.38E+01 +/- 2.48E+00 1.68E+01 +/- 2.63E+00 1.64E+01 +/- 2.61 E+00 1.63E+01 +/- 2.592+00 1.542+01 +/- 2.56E+00 1.63E+01 +/- 2.60E+00 11/20/13 1.19E+01 +/- 2.55E+00 1.66E+01 +/- 2.81E+00 1.26E+01 +/- 2.59E+00 1.86E+01 +/- 2.92E+00 1.17E+01 +/- 2.53E+00 1.302+01 +/- 2.61 E+00 11/26/13 1.32E+01 +/- 2.94E+00 1.02E+01 +/- 2.75E+00 1.33E+01 +/- 2.95E+00 1.09E+01 +/- 2.80E+00 1.26E+01 +/- 2.91 2+00 1.54E+01 +/- 3.08E+00 12/03/13 1.60E+01 +/- 2.84E+00 2.43E+01 +/- 3.25E+00 2.47E+01 +/- 3.27E+00 2.32E+01 +/- 3.20E+00 2.00E+01 +/- 3.04E+00 2.22E+01 +/- 3.152+00 12/11/13 1.45E+01 +/- 2.56E+00 1.80E+01 +/- 2.74E+00 1.76E+01 +/- 3.37E+00 1.98E+01 +/- 2.76E+00 1.622+01 +/- 2.59E+00 1.36E+01 +/- 2.46E+00 12/17/13 1.79E+01 +/- 3.50E+00 2.11E+01 +/- 3.66E+00 2.65E+01 +/- 3.92E+00 1.612+01 +/- 3.41E+00 2.16E+01 +/- 3.672+00 1.77E+01 +/- 3.46E+00 12/23/13 1.25E+01 +/- 3.03E+00 1.98E+01 +/- 3.42E+00 1.59E+01 +/- 3.22E+00 1.88E+01 +/- 3.36E+00 1.24E+01 +/- 3.032+00 1.26E+01 +/- 3.03E+00 MEAN 1.39E+01 +/- 2.77E+00 1.47E+01 +/- 2.81E+00 1.56E+01 +/- 2.87E+00 1.48E+01 +/- 2.83E+00 1.35E+01 +/- 2.75E+00 1.452+01 +/- 2.802+00 Mean - A11Indicator Locations 1.54E+01 +/- 2.85E+00
- Control Station 40
Table 3-4 Airborne Iodine page 1-131 1 of 4
[10-3 pCi/m 3]
Period Station Station Station Station Station Station Station S05 S06 Endin0/2 01 12 02 S.E03 J2 04 i207 -I
" 1.24E+01 < 3.21E+01 < 3.29E+01 " 3.25E+01 " 3.22E+01 " 2.49E+01 " 2.49E+01 01/02/13 01/08/13 " 6.62E+01 C 6.61E+01 6.62E+01 " 6.62E+01 " 3.54E+01 " 3.54E+01 " 3.54E+01 01/16/13 " 2.73E+01 6.15E+01 6.15E+01 " 6.15E+01 " 6.15E+01 " 2.37E+01 " 2.37E+01 C(
01/22/13 " 4.59E+01 4.61E+01 4.61E+01 " 4.61E+01 " 4.01E+01 " 4.01E+01 " 4.01E+01 C
01/29/13 " 1.91E+01 4.30E+01 4.30E+01 4.30E+01 " 4.30E+01 " 3.87E+01 " 3.87E+01 C
02/05/13 " 3.37E+01 3.37E+01 3.37E+01 3.37E+01 " 1.98E+01 " 1.98E+01 " 1.98E+01 C
02/13/13 " 1.19E+01 3.07E+01 3.07E+01 3.07E+01 " 3.07E+01 " 2.72E+01 " 2.72E+01 02/20/13 " 2.18E+01 C 2.23E+01 2.22E+01 2.22E+01 " 1.66E+01 " 1.65E+01 " 1.67E+01 02/27/13 " 1.85E+01 3.55E+01 3.63E+01 3.58E+01 " 3.60E+01 " 2.43E+01 " 2.39E+01 03/05/13 " 2.87E+01 2.82E+01 2.75E+01 2.78E+01 " 2.27E+01 " 2.28E+01 " 2.29E+01
" 3.74E+01 C C " 4.53E+01 " 3.83E+01 03/12/13 4.56E+01 4.16E+01 3.83E+01 C: C:
- 03/19/13 " 3.44E+01 3.44E+01 3.44E+01 3.44E+01 " 2.42E+01 " 2.42E+01 C:
- 03/26/13 2.52E+01 2.52E+01 2.44E+01 2.46E+01 " 2.77E+01 " 2.77E+01 C(
C
- 04/02/13 1.35E+01 3.48E+01 3.37E+01 3.40E+01 " 2.73E+01 " 2.73E+01 C(
04/09/13 8.67E+00 2.53E+01 2.29E+01 2.29E+01 " 2.79E+01 " 2.29E+01 " 2.33E+01
,C 04/17/13 2.24E+01 8.71 E+00 2.21E+01 2.26E+01 " 2.26E+01 " 2.53E+01 " 2.49E+01
,C 04/23/13 1.34E+01 3.46E+01 3.54E+01 3.53E+01 " 3.45E+01 " 2.13E+01 " 2.21E+01
,C 04/30/13 2.55E+01 2.42E+01 9.59E+00 2.48E+01 " 2.47E+01 " 2.81E+01 " 2.75E+01
,C 05/08/13 1.44E+01 2.72E+01 2.67E+01 2.68E+01 " 2.67E+01 " 3.22E+01 " 3.25E+01 C
05/14/13 2.27E+01 2.24E+01 2.32E+01 8.39E+00 " 2.30E+01 " 2.62E+01 " 2.56E+01 C
05/21/13 1.68E+01 4.31 E+01 4.29E+01 4.31E+01 " 4.31E+01 " 3.43E+01 " 3.43E+01 C
05/28/13 4.60E+01 4.61 E+01 4.61E+01 4.61E+01 " 1.89E+01 " 3.18E+01 " 3.18E+01 C:
06/04/13 8.10E+00 2.09E+01 2.08E+01 2.09E+01 " 2.09E+01 " 1.96E+01 " 1.96E+01 C:
06/11/13 2.98E+01 2.98E+01 3.OOE+01 2.98E+01 " 3.07E+01 " 1.29E+01 " 3.07E+01 C:
06/18/13 1.73E+01 4.43E+01 4.42E+01 4.43E+01 " 4.43E+01 " 4.05E+01 " 4.05E+01 06/25/13 2.32E+01 2.27E+01 2.17E+01 < 2.24E+01 " 2.91E+01 " 2.92E+01 " 1.23E+01
- Sample not obtained due to sampler not operating 41
Table 3-4 Airborne Iodine page 1-131 2 of 4
[10-3 pCi/m 3]
Period Station Station Station Station Station Station Ending 21 22 23 3.28E+01 I 24*.
3.29E+01 01A 05A -A 01/02/13 2.49E+01 2.49E+01 < < 3.28E+01 3.29E+01 01/08/13 1.49E+01 3.54E+01 < 2.70E+01 " 2.70E+01 2.70E+01 2.70E+01 01/16/13 2.37E+01 2.37E+01 < 4.OOE+01 " 3.99E+01 3.99E+01 3.99E+01 01/22/13 3.99E+01 2.35E+01 < 5.60E+01 " 5.62E+01 5.60E+01 5.62E+01 01/29/13 3.87E+01 3.87E+01 < 4.OOE+01 < 4.OOE+01 4.OOE+01 4.OOE+01 02/05/13 1.98E+01 2.62E+01 < 1.10E+01 " 2.62E+01 2.62E+01 2.62E+01 02/13/13 2.72E+01 2.72E+01 < 2.80E+01 " 2.80E+01 2.80E+01 2.80E+01 02/20/13 1.67E+01 2.10E+01 < 2.10E+01 < 8.84E+00 2.05E+01 2.09E+01 02/27/13 2.44E+01 2.44E+01 < 2.44E+01 " 2.51E+01 2.48E+01 2.49E+01 03/05/13 2.24E+01 2.89E+01 < 3.OOE+01 " 2.88E+01 1.06E+01 2.93E+01 03/12/13 3.97E+01 3.84E+01 < 2.69E+01 " 2.64E+01 2.61E+01 2.63E+01 03/19/13 2.42E+01 2.42E+01 < 3.05E+01 " 3.05E+01 3.05E+01 1.58E+01 03/26/13 2.77E+01 2.77E+01 < 2.49E+01 " 2.48E+01 2.51E+01 2.48E+01 04/02/13 2.74E+01 2.73E+01 < 2.33E+01 " 2.32E+01 2.35E+01 2.32E+01 04/09/13 2.33E+01 2.33E+01 < 1.83E+01 " 1.82E+01 1.77E+01 1.81E+01 04/17/13 2.49E+01 2.49E+01 < 1.98E+01 " 1.98E+01 1.98E+01 2.OOE+01 04/23/13 2.24E+01 2.10E+01 < 2.08E+01 " 1.95E+01 1.94E+01 1.98E+01 04/30/13 2.79E+01 2.79E+01 < 2.10E+01 " 2.16E+01 2.22E+01 2.16E+01 05/08/13 3.21E+01 3.21E+01 < 3.28E+01 " 3.21E+01 3.14E+01 3.22E+01 05/14/13 2.63E+01 2.63E+01 < 2.71E+01 < 2.81E+01 2.77E+01 2.80E+01 05/21/13 3.42E+01 3.42E+01 < 5.15E+01 " 5.13E+01 5.15E+01 5.13E+01 05/28/13 3.18E+01 3.18E+01 < 4.41E+01 < 4.41E+01 4.41E+01 4.41E+01 06/04/13 1.96E+01 1.96E+01 " 1.77E+01 < 1.77E+01 1.77E+01 1.77E+01 06/11/13 3.09E+01 3.09E+01 < 1.78E01- < 3.28E+01 3.27E+01 3.28E+01 06/18/13 4.03E+01 4.03E+01 < 3.55E+01 < 3.55E+01 3.56E+01 3.54E+01 06/25/13 2.89E+01 2.89E+01 < 3.16E+01 < 3.04E+01 3.19E+01 3.09E+01
- Control Station 42
Table 3-4 Airborne Iodine page 1-131 3 of 4 3
[10-3 pCi/m ]
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 page 1-131 4 of 4
[10-1 pCi/m 3]
Period Statioin Station Station Station Station Station Ending I 05A 21 3822 !
23 S 24* 01A !
" 3.81E+01 3.21E+01 " 3.22E+01 3.31E+01 < 3.22E+01 07/03/13 3.81E+01 07/09/13 1.57E+01 < 3.80E+01 3.00E+01 < 3.11E2+01 2.98E+01 < 3.06E+01 07/16/13 2.62E+01 < 2.62E+01 3.94E+01 < 3.94E+01 3.94E+01 < 3.93E+01 07/24/13 2.96E+01 < 1.24E+01 2.632+01 < 2.64E+01 2.63E+01 < 2.63E+01 07/31/13 6.64E+01 < 6.64E+01 5.34E+01 < 5.33E+01 5.34E+01 < 5.39E+01 08/06/13 3.55E+01 < 3.60E+01 1.51E+01 < 3.60E+01 3.60E+01 < 3.60E+01 08/14/13 3.37E+01 < 3.37E+01 2.90E+01 < 2.90E+01 2.90E+01 < 2.90E+01 08/20/13 3.02E+01 < 2.73E+01 2.74E+01 < 1.15E+01 2.74E+01 < 2.74E+01 08/27/13 3.73E+01 < 3.73E+01 3.72E+01 < 3.60E+01 3.73E+01 < 3.65E+01 09/03/13 4.40E+01 < 4.09E+01 4.01E+01 < 4.12E+01 1.67E+01 < 4.07E+01 09/10/13 3.27E+01 < 3.41E+01 3.39E+01 < 3.40E+01 3.38E+01 < 1.42E+01 09/17/13 4.09E+01 < 4.35E+01 4.15E+01 < 4.02E+01 4.18E+01 < 1.71E+01 09/24/13 4.60E+01 < 4.72E+01 5.25E+01 < 5.26E+01 5.29E+01 " 5.33E+01 10/02/13 3.67E+01 < 3.66E+01 4.30E+01 < 4.29E+01 4.27E+01 < 4.29E+01 10/08/13 3.06E+01 < 3.02E+01 3.15E+01 < 3.23E+01 3.10E+01 < 3.19E+01 10/16/13 4.23E+01 < 4.23E+01 4.87E+01 < 4.73E+01 4.92E+01 < 4.79E+01 10/22/13 6.46E+01 " 6.46E+01 5.08E+01 " 5.26E+01 5.02E+01 < 5.18E+01 10/30/13 2.55E+01 " 2.55E+01 3.20E+01 < 3.11E+01 3.21E+01 < 3.15E+01 11/05/13 3.70E+01 " 3.70E+01 4.50E+01 < 4.69E+01 4.48E+01 < 4.61E+01 11/13/13 4.40E+01 < 4.40E+01 5.65E+01 < 5.63E+01 5.65E+01 < 5.65E+01 11/20/13 5.02E+01 < 5.02E+01 4.62E+01 < 4.62E+01 4.62E+01 < 4.62E+01 11/26/13 4.72E+01 < 4.72E+01 6.71E+01 < 6.69E+01 6.71E+01 " 6.71E+01 12/03/13 4.68E+01 < 4.68E+01 4.34E+01 < 4.35E+01 4.34E+01 " 4.34E+01 12/11/13 3.30E+01 < 3.30E+01 5.37E+01 < 3.83E+01 3.83E+01 " 3.83E+01 12/17/13 6.73E+01 < 6.54E+01 6.55E+01 < 6.55E+01 6.50E+01 < 2.72E+01 12/23/13 3.04E+01 < 3.04E+01 6.91E+01 < 6.87E+01 6.91E+01 < 6.90E+01
- Control Station 44
Table 3-5 Airborne Particulate page Gamma Spectra 1 of 2
- 0. pCi/m3]'
[Oi Sampling Quarter 1 Location Be-7 Cs-134* I Cs-1 37* 1 1
Be-7 01 1.12E+02 +1- 2.95E+01 < 1.50E+00. < 1.41E+00 01A 1.45E+02 +/- 3.35E+01 < 1.60E+00 < 1.15E+00 02 9.96E+01 +/- 2.53E+01 < 1.38E+00 < 1.05E+00 03 9.16E+01 +1- 3.83E+01 < 2.08E+00 < 1.86E+00 04 1.02E+02 +1- 3.86E+01 < 1.56E+00 < 1.64E+00 05 9.02E+01 +1- 3.47E+01 < 1.63E+00 < 1.43E+00 05A 1.07E+02 +1- 4.40E+01 < 2.24E+00 < 1.93E+00 06 1.24E+02 +1- 3.77E+01 < 2.31E+00 < 1.94E+00 07 1.11E+02 +1- 3.49E+01 < 1.70E+00 < 1.12E+00 21 1.11E+02 +1 3.10E+01 < 1.44E+00 < 1.02E+00 22 1.31E+02 +1- 2.84E+01 < 1.35E+00 < 1.32E+00 23 1.38E+02 +/- 2.82E+01 < 1.62E+00 < 1.36E+00 24** 1.01E+02 +/- 2.75E+01 " 1.35E+00 < 8.39E-01 Sampling Quarter 2 Location 1.15E+02 Be-7
+/- 2.73E+01 I
Cs-134 1.21E+00 I
Cs-137*
8.69E-01 Sr-89 5.39E+00 I <
Sr-90 1.71E+00 01
" 1.57E+00 < 1.54E+00 01A 1.46E+02 +- 2.97E+01 < 5.31E+00 < 2.11E+00 02 1.52E+02 +- 4.08E+01 " 1.61E+00 ..* . 1.41E+00 < 6.25E+00 " 2.13E+00 03 1.80E+02 +1 3.43E+01 < 1.39E+00 . < 1.13E+00 < 6.48E+00 < 2.23E+00 04 1.61 E+02 +/- 3.51E+01 < 1.49E+00, < 1.45E+00 < 6.39E+00 < 2.15E+00 05 1.77E+02 +/- 4.22E+01 < 2.06E+00 < 2.06E+00 < 6.69E+00 < 2.17E+00 05A 1.41 E+02 +/- 2.66E+01 < 1.38E+00 < 1.42E+00 < 5.96E+00 < 1.69E+00 06 1.61 E+02 +/- 2.39E+01 5 1.14E+00 < 1.13E+00 " 5.69E+00 " 1.73E+00 07 1.35E+02 +/- 3.78E+01 < 1.33E+00 < 9.74E-01 " 5.82E+00 < 1.97E+00 21 1.16E+02 +/- 3.35E+01 < 1.43E+00 < 1.02E+00 " 6.00E+00 < 2.19E+00 22 1.39E+02 +/- 2.96E+01 < 1.38E+00 < 1.21E+00 " 5.56E+00 < 2.22E+00 23 1.47E+02 +/- 3.26E+01 < 1.03E+00 < 1.04E+00 < 5.55E+00 < 2.15E+00 24** 1.40E+02 +/- 3.31E+01 < 1.79E+00 < 1.47E+00 < 6.62E+00 < 2.25E+00
- Control Station 45
Table 3-5 Airborne Particulate page Gamma Spectra 2 of 2
[10-3 pCi/m3]
Sampling Quarter 3 Location Be-7 Cs-134* I . Cs-137*
01 1.05E+02 +1- 2.40E+01 < 1.22E+00 < 1.22E+00 01A 1.04E+02 +/- 2.09E+01 < 1.06E+00 < 1.09E+00 02 1.52E+02 +/- 2.43E+01 < 1.67E+00 < 1.39E+00 03 1.43E+02 +1- 3.38E+01 < 1.58E+00 < 1.38E+00 04 1.32E+02 +/- 3.07E+01 < 1.24E+00 < 9.80E-01 05 1.36E+02 +/- 2.88E+01 < 1.14E+00 < 1.17E+00 05A 1.11E+02 +/- 2.65E+01 < 1.25E+00 < 8.87E-01 06 1.09E+02 +/- 3.31E+01 " 1.70E+00 < 1.86E+00 07 1.63E+02 +/- 3.45E+01 < 1.39E+00 < 1.20E+00 21 1.67E+02 +/- 3.18E+01 < 1.73E+00 < 1.65E+00 22 1.22E+02 +/- 2.98E+01 < 2.06E+00 < 1.44E÷00 23 1.14E+02 +/- 2.57E+01 < 1.06E+00 < 1.25E+00 24** 1.09E+02 +/- 2.61E+01 < 9.69E-01 < 1.12E+00 MEAN Sampling MEAN Quarter 4 Location Be-7 Cs-134* Cs-137* Be-7 I !
01 1.11E+02 +1 1.99E+01 < 1.05E+00 < 8.45E-01 1.11E+02 +1- 2.52E+01 01A 1.03E+02 +/- 2.39E+01 < 1.52E+00' < 1.12E+00 1.25E+02 +1" 2.70E+01 02 1.26E+02 +/- 3.04E+01 < 1.35E+00 < 1.38E+00 1.32E+02 +1- 3.02E+01 03 1.01E+02 +/- 2.20E+01 < 1.33E+00 < 1.24E+00 1.29E+02 +1- 3.21E+01 04 1.36E+02 +/- 3.78E+01 < 1.77E+00 < 1.57E+00 1.33E+02 +1" 3.56E+01 05 1.09E+02 +/- 2.15E+01 " 1.44E+00 < 1.08E+00 1.28E+02 +1- 3.18E+01 05A 1.13E+02 +/- 3.18E+01 < 1.66E+00 < 1.34E+00 1.18E+02 +1- 3.22E+01 06 1.20E+02 +/- 2.83E+01 < 1.52E+00 < 1.46E+00 1.29E+02 +1- 3.08E+01 07 1.15E+02 +1- 2.53E+01 < 1.24E+00 < 8.56E-01 1.31E+02 +1- 3.31E+01 21 1.04E+02 +1 2.65E+01 < 1.81E+00 < 1.40E+00 1.25E+02 +1- 3.07E+01 22 1.02E+02 +/- 2.11E+01 < 1.08E+00 < 9.81E-01 1.24E+02 +1" 2.72E+01 23 1.30E+02 +/- 2.89E+01 " 1.54E+00 < 1.80E+00 1.32E+02 +1- 2.89E+01 24* 1.18E+02 +/- 2.69E+01 " 1.51E+00 < 1.28E+00 1.17E+02 + 2-2.84E+01 Mean of Ali Indicator Location: 1.26E+02 +- 3.04E+01
- Control Station 46
Table 3-6 Soil
[pCi/kg]
Sample Station I Sr-89 I Sr-90. I K-40 I Cs- 134 Date Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC 7/16/13 01 6.58E+01 2.420E+02 4.59E+02 -8.21E-01 1 .59E+01 2.62E+01 2.60E+04 1.18E+03 3.09E+02 -2.20E+01 2.69E+01 3.64E+01 7/16/13 02 2.32E+01 2.71 E+02 5.42E+02 1.93E+01 1.67E+01 2.63E+01 1.10E+04 1.41E+03 5.90E+02 -2.36E+01 4.65E+01 6.30E+01 7/16/13 03 2.76E+02 3.35E+02 5.56E+02 2.14E+01 2.29E+01, 3.64E+01 6.57E+03 1.11E+03 6.59E+02 -9.23E+00 5.21E+01 7.04E+01 7/16/13 04 -6.50E+01 2.27E+02 5.02E+02 -1.04E+01 2.09E+01 3.51 E+01 6.32E+03 7.58E+02 3.81 E+02 -1.57E+01 3.19E+01 4.29E+01 7/16/13 05 -1.75E+01 2.54E+02 5.28E+02 1.68E+01 1.65E+01 2.62E+01 1.76E+04 1.56E+03 4.90E+02 9.16E+00 4.36E+01 6.39E+01 7/16/13 05A -2.77E+01 2.87E+01 5.99E+02 -1.24E+01 1.91E+01 3.21 E+01 1.07E+04 1.05E+03 3.96E+02 -8.81 E-01 3.03E+01 4.38E+01 7/16/13 06 2.93E+02 3.23E+02 5.26E+02 6.08E+00 1.99E+01 3.24E+01 1.03E+04 1.15E+03 4.25E+02 -5.22E+01 5.17E+01 6.71E+01 7/16/13 07 1.05E+02 3.OOE+02 5.60E+02 -9.92E+00 1.91 E+01 3.20E+01 7.31 E+03 1.09E+03 4.96E+02 -2.35E+01 4.20E+01 5.59E+01 7/16/13 21 9.02E+01 2.89E+02 5.46E+02 2.84E+01 2.03E+01 3.19E+01 2.16E+04 1.61E+03 4.24E+02 -1.82E+01 3.63E+01 4.87E+01 7/16/13 22 -1.39E+02 2.21 E+02 5.28E+02 1.83E+00 1.85E+01 3.03E+01 2.14E+04 1.62E+03 5.35E+02 5.01 E+00 4.55E+01 6.57E+01 7/16/13 23 -9.98E+00 2.63E+02 5.44E+02 2.16E+01 1.64E+01 2.58E+01 2.90E+04 1.62E+03 5.01 E+02 3.OOE+01 4.03E+01 5.99E+01 7/16/13 24* 1.22E+02 2.97E+02 5.52E+02 1.14E+01 1.78E+01 2.87E+01 4.66E+03 1.12E+03 7.67E+02 -5.25E+01 5.73E+01 7.51 E+01 1.53E+04 MEAN Indicator Control 4.66E+03
- Control Station Sample Station I Cs-137 Ra-226 Th-228 Th-232 Date Acivity Conc 2 Sigma MDC Acivit' Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC Acivity Conc 2 Sigma MDC 7/16/13 01 2.78E+01 2.89E+01 5.06E+01 1.99E+03 8.58 E+02 9.03E+02 1.13E+03 7.39E+01 7.35E+01 1.17E+03 1.10E+02 1.60E+02 7/16/13 02 5.39E+02 9.62E+01 6.75E+01 9.14E+02 1.27E+03 1.24E+03 5.04E+02 8.73E+01 1.07E+02 5.30E+02 2.34E+02 4.33E+02 7/16/13 03 2.65E+02 9.78E+01 7.28E+01 1.79E+03 1.57E+03 1.52E+03 8.03E+02 1.22E+02 1.24E+02 8.78E+02 1.98E+02 2.48E+02 7/16/13 04 2.79E+02 5.93E+01 4.78E+01 2.32E+03 1.26E+03 9.56E+02 8.16E+02 7.72E+01 7.25E+01 7.44E+02 1.32E+02 1.62E+02 7/16/13 05 1.70E+02 6.46E+01 7.50E+01 3.06E+03 1.44E+03 1.41E+03 1.66E+03 1.21 E+02 1.08E+02 1.41E+03 2.11E+02 5.90E+02 7/16/13 05A 1.35E+02 7.04E+01 4.78E+01 2.18E+03 8.82E+02 8.57E+02 8.24E+02 7.70E+01 7.09E+01 7.34E+02 1.19E+02 1.57E+02 7/16/13 06 1.67E+02 9.33E+01 7.08E+01 3.26E+03 1.41E+03 1.80E+03 2.27E+03 1.30E+02 1.33E+02 2.20E+03 1.79E+02 2.09E+02 7/16/13 07 2.13E+02 6.18E+01 6.73E+01 2.08E+03 1.50E+03 1.62E+03 1.42E+03 1.08E+02 1.18E+02 1.24E+03 2.03E+02 4.63E+02 7/16/13 21 9.31E+01 5.65E+01 4.83E+01 1.57E+03 9.64E+02 1.11E+03 1.09E+03 9.41 E+01 8.88E+01 1.03E+03 1.56E+02 1.94E+02 7/16/13 22 1.07E+02 5.35E+01 8.09E+01 3.60E+03 1.19E+03 1.47E+03 2.23E+03 1.43E+02 1.11E+02 1.82E+03 2.54E+02 6.16E+02 7/16/13 23 1.21E+02 5.11E+01 7.68E+01 2.76E+03 1.43E+03 1.30E+03 1.71 E+03 1.14E+02 9.77E+01 1.35E+03 1.92E+02 4.73E+02 7/16/13 24* 3.29E+02 1.02E+02 8.19E+01 3.39E+03 2.06E+03 1.72E+03 1.71E+03 1.57E+02 1.37E+02 1.34E+03 2.02E+02 2.91E+02 Indicator 2.09E+02 2.46E+03 1.31E+03 1.19E+03 Control 3.29E+02 3.39E+03 1.71 E+03 1.34E+03
- Control Station 47
Table 3-7 Precipitation Gross Beta
[pCi/L] page 1 of 2 Sampling Date Gross Beta I H-3 I Rainfall I (inches) 01/29/13 3.25E+00 +/- 1.42E+00 <8.65E+01 3.42 02/27/13 5.79E+00 1.50E+00 <7.21 E+02 2.48 03/26/13 < 1.74E+00 <8.75E+02 3.00 04/30/13 2.27E+00 1.17E+00 <8.54E+02 3.50 05/28/13 6.43E+00 1.39E+00 <6.84E+02 2.20 06/25/13 2.73E+00 1.48E+00 <7.26E+02 7.08 07/31/13 1.96E+01 2.11 E+00 <8.09E+02 4.23 08/27/13 2.63E+00 1.37E+00 * <7.91 E+02 5.21 09/24/13 9.63E+00 1.70E+00 <9.35E+02 1.72 10/30/13 <1.99E+00 <7.96E+02 3.05 11/26/13 5.41 E+00 +/- 1.60E+00 <8.54E+02 1.03 12/31/13 <1.57E+00 <8.31 E+02 0.00 Mean 6.42E+00 +/- 1.58E+00 Total 36.92 48
Table 3-7 Precipitation page Gamma Spectra 2 of 2
[pCi/L]
Sampling Location Be-7 Mn-54 Fe-59 Co-58 Co-60 01A 06/25/13 3.57E+01 < 9.50E-01 < 9.76E+00 < 2.37E+00 < 7.96E-01 12/31/13 6.60E+01 +/- 3.68E+01 < 1.94E+00 < 1.79E+01 < 4.80E+00 < 1.51 E+00 Zn-65 Zr-95 Nb-95 nI Cs-134 Cs-137 OIA 06/25/13 2.25E+00 " 4.92E+00 < 3.19E+00 < 8.46E-01 8.22E-01 12/31/13 3.94E+00 < 8.84E+00 < 5.37E+00 " 1.67E+00 1.75E+00 nI La- 140 Ba-140 1-131 Th-228 01A 06/25/13 2.30E+03 7.89E+02 4.07E+04 1.60E+00 12/31/13 2.92E+03 9.15E+02 3.71 E+04 3.87E+00 49
Table 3-8 Milk page Gamma Spectra & Strontium 1 of 1
[pCi/L]
Sampling Station 12A Date I K-40 I Sr-89 I Sr-90 1-131* I Cs-134* I Cs-137* Ba-140 I La-140*
01/16/13 1.23E+03 +/- 1.45E+02 [a] [a] < 9.22E-01 < 6.33E+00 < 6.83E+00 < 4.42E+01 < 1.27E+01 02/19/13 1.39E+03 +/- 8.80E+01 [a] [a] < 6.60E-01 < 3.52E+00 < 4.40E+00 < 1.96E+01 < 5.52E+00 03/19/13 1.27E+03 +/- 1.11E+02 < 3.51E+00 < 1.84E+00 < 4.84E-01 < 4.42E+00 < 5.56E+00 < 2.34E+01 < 7.43E+00 04/17/13 1.22E+03 +/- 1.42E+02 [a] [a] < 9.76E-01 < 6.06E+00 < 7.27E+00 < 4.52E+01 < 1.13E+01 05/21/13 1.32E+03 +I- 1.33E+02 [a] [a] < 8.42E-01 < 6.11E+00 < 7.14E+00 < 5.06E+01 < 1.36E+01 06/18/13 1.71E+03 +/- 1.86E+02 < 3.95E+00 < 1.63E+00 < 8.57E-01 < 6.53E+00 < 8.11E+00 < 3.96E+01 < 1.44E+01 07/16/13 1.27E+03 +/- 1.41E+02 [a] [a] " 6.07E-01 < 5.66E+00 < 5.77E+00 < 3.05E+01 < 1.03E+01 08/20/13 1.39E+03 +/- 1.08E+02 [a] [a] " 8.93E-01 < 3.72E+00 < 4.24E+00 < 3.15E+01 < 8.34E+00 09/17/13 1.32E+03 +/- 1.62E+02 < 2.97E+00 < 8.30E-01 " 5.71E-01 < 5.96E+00 < 6.44E+00 < 3.23E+01 < 1.05E+01 10/16/13 1.48E+03 +/- 1.09E+02 [a] [a] " 7.53E-01 < 3.68E+00 < 4.09E+00 < 3.54E+01 < 8.13E+00 11/20/13 1.36E+03 +/- 1.60E+02 [a] [a] " 7.15E-01 < 6.46E+00 < 7.42E+00 < 5.26E+01 < 1.32E+01 12/17/13 1.29E+03 +/- 1.49E+02 < 3.77E+00 < 1.03E+00 < 5.38E-01 < 4.20E+00 < 5.70E+00 < 5.OOE+01 < 1.42E+01 Sta. Mean 1.35E+03 +/- 1.36E+02
[a] Sr-89/90 analyses performed on the last monthly sample of each quarter.
50
Table 3-9 Food and Vegetation Gamma Spectra page
[pCi/kg] 1 of 2 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*
16- 04/09/13 1.43E+03 +/- 1.74E+02 6.30E+03 4.41 E+02 2.38E+01 1.71E+01 1.83E+01 05/14/13 6.87E+02 +/- 2.06E+02 4.06E+03 4.22E+02 4.21E+01 2.OOE+01 2.05E+01 06/11/13 1.47E+03 +/- 2.42E+02 5.62E+03 5.30E+02 2.21E+01 2.OOE+01 2.37E+01 07/09/13 1.67E+03 +/- 2.94E+02 4.70E+03 5.70E+02 3.57E+01 2.40E+01 2.91 E+01 08/14/13 6.81E+02 +/- 3.06E+02 1.04E+04 1.10E+03 2.95E+01 4.65E+01 4.98E+01 09/10/13 5.28E+02 7.69E+03 1.11E+03 5.86E+01 5.69E+01 5.95E+01 10/08/13 8.66E+02 +/- 6.15E+02 3.97E+03 8.22E+02 3.20E+01 3.55E+01 3.85E+01 Mean 1.13E+03 +/- 3.38E+02 6.11E+03 +/- 7.14E+02 +/- +/- +/-
- Control Station 51
Table 3-9 Food and Vegetation page Gamma Spectra 2 of 2
[pCi/kg]
Sampling Sampling Location Date Be-7 - K-40
- 1-131* Cs-134* Cs-137*
23 04/09/13 1.57E+03 3.73E+02 6.77E+03 +7- 8.02E+02 2.70E+01 3.57E+01 4.03E+01 05/14/13 5.47E+02 2.75E+02 4.54E+03 6.24E+02 4.16E+01 2.77E+01 3.09E+01 06/11/13 9.45E+02 2.52E+02 5.25E+03 5.80E+02 1.87E+01 2.19E+01 2.72E+01 07/09/13 1.48E+03 1.12E+02 4.98E+03 2.18E+02 5.57E+01 9.73E+00 1.06E+01 08/14/13 2.22E+03 3.83E+02 8.80E+03 8.90E+02 2.67E+01 4.24E+01 4.86E+01 09/10/13 2.03E+03 4.35E+02 2.68E+03 7.42E+02 5.84E+01 4.27E+01 4.37E+01 10/08/13 1.26E+03 5.95E+02 5.75E+03 1.03E+03 3.72E+01 5.85E+01 6.91E+01 Mean 1.44E+03 +/- 3.46E+02 5.54E+03 +/- 6.98E+02 +/- +/- +/-
Sampling Sampling Location Date Be-7 K-40 1-131* Cs-134* Cs-137*
26 04/09/13 2.23E+03 4.19E+02 8.93E+03 7.60E+02 2.62E+01 4.67E+01 4.92E+01 05/14/13 1.49E+03 2.95E+02 6.63E+03 7.30E+02 3.51E+01 3.15E+01 3.37E+01 06/11/13 1.43E+03 3.38E+02 5.23E+03 6.63E+02 2.11E+01 3.19E+01 3.57E+01 07/09/13 1.60E+03 2.60E+02 4.30E+03 5.72E+02 4.16E+01 2.09E+01 2.49E+01 08/14/13 1.21E+03 2.64E+02 4.41 E+03 5.20E+02 2.57E+01 2.76E+01 3.OOE+01 09/10/13 1.30E+03 5.25E+02 2.84E+03 7.90E+02 4.01 E+01 5.38E+01 5.84E+01 10/08/13 2.93E+03 6.69E+02 4.83E+03 8.80E+02 3.34E+01 5.76E+01 5.96E+01 Mean 1.74E+03 3.96E+02 5.31E+03 7.02E+02 Indicator locations 1.50E+03 +/- 3.51 E+02 5.76E+03 +/- 6.93E+02
Table 3-10 Well Water page Gamma Spectra, Strontium, and Tritium 1 of 1
[pCi/L]
Sampling Station 01A Date H-3 Sr-89 Sr-90 Mn-54 Fe-59 Co-58 Co-60 Zn-65 03/26/13 " 8.75E+02 [a] [a] < 5.15E+00 < 1.12E+01 < 4.54E+00 < 5.17E+00 < 8.77E+00 06/25/13 " 7.25E+02 < 4.11E+00 < 7.72E-01 < 2.91E+00 < 6.20E+00 < 3.40E+00 < 2.62E+00 < 4.99E+00 09/24/13 " 9.45E+02 [a] [a] < 4.48E+00 < 1.13E+01 < 5.40E+00
- 4.51 E+00 < 9.30E+00 12/31/13 < 8.30E+02 [a] [a] < 6.60E-01 < 1.30E+00 " 6.26E-01 < 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 < 8.99E+00 < 7.07E+00 < 9.20E-01 < 4.40E+00 < 5.53E+00 < 2.63E+01 < 7.90E+00 06/25/13 < 5.27E+00 " 3.23E+00 < 6.92E-01 < 2.79E+00 < 3.03E+00 < 1.99E+01 < 5.69E+00 09/24/13 < 8.64E+00 < 5.73E+00 < 6.OOE-01 < 4.47E+00 < 5.45E+00 < 2.68E+01 < 7.74E+00 12/31/13 < 9.82E-01 " 6.58E-01 < 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 page Gamma Spectra, Strontium, and Tritium 1 of 1
[pCi/L]
Sampling Station 11 Date H-3 Sr-89 Sr-90 Mn-54* Fe-59* Co-58* Co-60* Zn-65*
01/15/13 [a] [b] [b] < 2.25E+00 6.16E+00 2.58E+00 < 2.19E+00 < 4.93E+0 02/12/13 [a] [b) [b] < 4.39E+00 9.52E+00 4.54E+00 < 4.05E+00 < 8.50E+0 03/11/13 3.87E+03 +/- 7.92E+02 [b] [b] < 1.49E+00 3.29E+00 1.56E+00 < 1.58E+00 < 2.89E+0 04/16/13 [a] [b] [b] < 4.96E+00 1.07E+01 5.28E+00 < 4.91 E+00 < 1.07E+0 05/13/13 [a] [b] [b] < 5.70E+00 1.31E+01 4.95E+00 < 3.96E+00 < 1.OOE+0 06/10/13 4.33E+03 +/- 7.54E+02 4.76E+00 < 8.34E-01 < 4.09E+00 7.68E+00 3.93E+00 < 4.31 E+00 < 6.12E+0 07/14/13 [a] [b] [b] 4.46E+00 7.24E+00 4.01 E+00 < 3.70E+00 < 8.97E+0 08/12/13 [a] [b] [b] < 6.18E+00 1.42E+01 5.36E+00 < 5.68E+00 < 1.14E+0 09/16/13 3.75E+03 +/- 7.44E+02 [b] [b] < 1.64E+00 4.04E+00 1.62E+00 < 1.61E+00 < 3.47E+0 10/14/13 [a] [b] [b] < 1.93E+00 4.90E+00 2.08E+00 < 1.96E+00 < 3.98E+0 11/12/13 [a] [b] [b] " 1.65E+00 4.36E+00 2.04E+00 " 1.66E+00 < 3.18E+0 12/17/13 4.09E+03 +/- 7.84E+02 [151 [b] < 1.46E+00 3.81 E+00 1.72E+00 < 1.59E+00 < 3.16E+0 MEAN 4.01E+03 +/- 7.69E+02 +/- +/-
Sampling Date Nb-95* Zr-95* 1-131" Cs-134* Cs-137* Ba-140* La-140*
01/15/13 4.56E+00 < 2.62E+00 < 9.31E-01 < 2.28E+00 < 2.55E+00 < 1.75E+01 " 5.97E+00 02/12/13 8.93E+00 < 4.28E+00
- 6.89E-01 < 4.52E+00 < 5.28E+00 < 2.74E+01 < 7.58E+00 03/11/13 2.82E+00 < 1.66E+00
- 7.85E-01 " 1.52E+00 " 1.62E+00 < 1.01E+01 < 2.56E+00 04/16/13 9.29E+00 < 5.84E+00
- 7.35E-01 " 5.32E+00 < 5.24E+00 < 4.16E+01 " 7.11E+00 05/13/13 8.94E+00 < 5.66E+00
- 5.31E-01 " 4.59E+00 " 5.94E+00 < 2.81 E+01 < 1.14E+01 06/10/13 7.59E+00 " 4.48E+00 < 3.91E-01 " 3.68E+00 " 3.86E+00 " 2.07E+01 < 5.89E+00 07/14/13 6.36E+00 < 4.09E+00 < 6.48E-01 " 3.67E+00 < 4.51E+00 " 2.34E+01 < 6.92E+00 08/12/13 9.23E+00 " 6.43E+00 < 5.97E-01 < 4.66E+00 " 5.90E+00 " 4.23E+01 < 1.49E+01 09/16/13 3.27E+00 < 1.90E+00 < 5.81E-01 < 1.57E+00 " 1.78E+00 " 1.24E+01 < 4.09E+00 10/14/13 3.90E+00 " 2.22E+00 < 4.85E-01 < 1.76E+00 " 1.95E+00 < 1.78E+01 < 5.82E+00 11/12/13 3.14E+00 " 2.05E+00 < 5.29E-01 " 1.55E+00 " 1.78E+00 < 1.95E+01 " 6.43E+00 12/17/13 3.19E+00 < 1.80E+00
- 4.02E-01 " 1.43E+00 " 1.66E+00 < 1.40E+01 " 4.87E+00 MEAN
- LLD identified in ODCM [a] Tritium analyses on quarterly composite. [b] Sr-89/90 performed annually on 2 ndquarter composite sample.
54
Table 3-12 Surface Water page Gamma Spectra, Strontium, Tritium 1 of 2
[pCi/L]
Sampling Station 08 Date H-3* Sr-89 Sr-90 Mn-54* Fe-59* Co-58" Co-60" Zn-65*
01/15/13 [a] [b] [b] < 1.19E+00 < 2.93E+00 < 1.29E+00 < 1.21E+00 < 2.61E+00 02/12/13 [a] [b] [b] < 3.53E+00 < 8.99E+00 < 3.96E+00 < 3.48E+00 < 8.07E+00 03/11/13 4.37E+03 +/- 8.23E+02 [b] [b] < 1.55E+00 " 3.60E+00 < 1.57E+00 < 1.75E+00 < 3.25E+00 04/16/13 [a] [b] [b] < 3.58E+00 < 8.84E+00 < 4.65E+00 " 3.87E+00 < 8.54E+00 05/13/13 [b] [b] < 3.61 E+00 " 7.85E+00 < 3.57E+00 " 3.68E+00 < 7.48E+00 06/10/13 4.OOE+03 +/- 7.42E+02 < 4.27E+00 < 7.82E-01 < 3.34E+00 " 7.19E+00 < 3.88E+00 < 3.69E+00 < 7.92E+00 07/14/13 [a] [b] [b] < 4.32E+00 " 7.84E+00 < 4.04E+00 < 4.04E+00 < 7.15E+00 08/12/13 [a] [b] [b] < 4.76E+00 " 1.32E+01 < 4.56E+00 " 4.90E+00 < 9.33E+00 09/16/13 3.85E+03 +/- 7.54E+02 [b] [b] < 2.32E+00 " 5.89E+00 < 2.55E+00 " 2.50E+00 < 4.68E+00 10/14/13 [a] [b] [b] 1.56E+00 " 4.14E+00 < 1.75E+00 < 1.61E+00 < 3.27E+00 11/12/13 [a] [b] [b] < 1.87E+00 " 4.85E+00 < 2.09E+00 < 1.78E+00 < 3.79E+00 12/17/13 4.08E+03 +/- 7.79E+02 [b] [b] < 1.56E+00 < 3.94E+00 < 1.69E+00 < 1.64E+00 < 3.13E+00 Mean 4.08E+03 +/- 7.75E+02 Sampling Date Zr-95" Nb-95* 1-131* Cs-134* Cs-137" Ba-140* La-140*
01/15/13 2.44E+00 " 1.41E+00 < 8.08E-01 " 1.14E+00 " 1.35E+00 < 9.26E+00 < 2.87E+00 02/12/13 7.16E+00 < 4.17E+00 " 7.10E-01 < 3.78E+00 " 4.24E+00 < 2.16E+01
- 7.40E+00 03/11/13 2.84E+00 < 1.70E+00 " 7.33E-01 < 1.51E+00 " 1.66E+00 " 9.06E+00
- 3.13E+00 04/16/13 8.18E+00 < 4.35E+00 < 5.99E-01 " 3.65E+00 " 3.90E+00 " 3.21E+01
- 7.77E+00 05/13/13 6.58E+00 " 3.24E+00 < 6.30E-01 " 3.39E+00 " 3.50E+00 " 1.80E+01 < 5.31 E+00 06/10/13 6.32E+00 < 3.92E+00 < 4.59E-01 " 3.34E+00 " 3.65E+00 " 1.65E+01
- 4.49E+00 07/14/13 5.68E+00 < 3.31 E+00 < 6.20E-01 " 3.53E+00 " 3.84E+00 " 1.79E+01 < 6.35E+00 08/12/13 9.79E+00 " 5.49E+00 < 7.39E-01 " 4.60E+00 < 4.97E+00 < 3.14E+01 < 1.16E+01 09/16/13 4.46E+00 " 2.55E+00 " 5.63E-01 " 2.13E+00 < 2.28E+00 < 1.60E+01 < 5.51 E+00 10/14/13 3.18E+00 < 1.90E+00 " 4.48E-01 < 1.58E+00 < 1.72E+00 < 1.59E+01 < 4.59E+00 11/12/13 3.57E+00 < 2.07E+00 < 5.98E-01 < 1.74E+00 < 1.81E+00 < 2.10E+01 < 6.51 E+00 12/17/13 3.17E+00 < 1.80E+00 < 4.25E-01 < 1.55E+00 < 1.73E+00 < 1.48E+01 < 4.20E+00 Mean LLD identified in [a] Tritium analyses on quarterly composite.
ODCM [b] Sr-89/90 performed annually on 2 nd quarter composite sample.
55
Table 3-12 Surface Water page Gamma Spectra, Strontium, Tritium 2 of 2
[pCi/L]
Sampling Station 09A Date H-3* Sr-89 Sr-90 Mn-54* Fe-59* Co-58" Co-60" Zn-65*
01/15/13 [a] [b] [b] < 1.47E+00 < 3.49E+00 < 1.60E+00 < 1.60E+00 < 3.00E+00 02/12/13 [a] [b] [b] < 5.67E+00 < 1.19E+01 < 6.60E+00 < 6.03E+00 < 1.10E+01 03/11/13 < 8.83E+02 [b] [b] < 1.39E+00 < 3.24E+00 < 1.52E+00 < 1.36E+00 < 2.75E+00 04/16/13 [a] [b] [b] < 3.70E+00 < 1.05E+01 < 4.53E+00 < 4.25E+00 < 9.35E+00 05/13/13 [b] [b] < 3.77E+00 < 6.74E+00 < 3.34E+00 < 3.74E+00 < 7.24E+00 06/10/13 < 8.02E+02 < 3.75E+00 < 8.04E-01 " 3.57E+00 < 6.92E+00 < 4.03E+00 < 3.78E+00 < 8.33E+00 07/14/13 [a] [b] [b] < 3.10E+00 < 7.30E+00 < 3.27E+00 < 3.14E+00 < 6.34E+00 08/12/13 [a] [bi [b] *< 4.26E+00 < 9.23E+00 < 3.80E+00 < 4.60E+00 < 8.82E+00 09/16/13 < 7.67E+02 [b] [b] ,< 1.94E+00 < 4.35E+00 < 2.05E+00 < 1.81E+00 < 3.62E+00 10/14/13 [a] [b] [b] < 1.48E+00 < 3.32E+00 < 1.55E+00 " 1.43E+00 < 2.83E+00 11/12/13 [a] [b] [b] < 1.76E+00 < 4.61E+00 " 2.03E+00 < 1.89E+00 < 3.59E+00 12/17/13 < 8.12E+02 [b] [b] < 1.91E+00 < 5.23E+00 " 2.30E+00 < 2.15E+00 < 3.93E+00
+/- +1- +/- +1- +1- +/- +1- +1-Mean Sampling Date Zr-95* Nb-95* 1-131* Cs-i!34" Cs-137" Ba-140* La-140*
01/15/13 < 3.10E+00 < 1.67E+00 " 9.23E-01 * . 1.56E+00 < 1.60E+00 < 1.19E+01 < 3.57E+00 02/12/13 < 9.99E+00 < 5.97E+00 < 7.75E-01 < 6.07E+00 < 6.36E+00 < 3.38E+01 < 1.43E+01 03/11/13 < 2.70E+00 < 1.66E+00 < 5.76E-01 < 1.44E+00 < 1.57E+00 " 9.21E+00 < 2.62E+00 04/16/13 < 8.68E+00 " 4.84E+00 < 7.64E-01 " 4.50E+00 < 4.16E+00 " 3.41E+01 " 7.94E+00 05/13/13 < 6.04E+00 < 3.70E+00 < 5.62E-01 " 3.55E+00 < 3.95E+00 < 1.80E+01 < 6.62E+00 06/10/13 < 7.37E+00 < 3.60E+00 < 4.44E-01 " 3.84E+00 < 3.84E+00 " 1.92E+01 < 4.78E+00 07/14/13 < 6.32E+00 < 3.55E+00 < 6.32E-01 " 3.09E+00 " 3.99E+00 " 1.88E+01 < 5.26E+00 08/12/13 < 8.47E+00 < 4.74E+00 < 7.70E-01 " 4.OOE+00 < 4.44E+00 " 3.74E+01 < 1.27E+01 09/16/13 < 3.57E+00 < 2.12E+00 < 5.51E-01 < 1.93E+00 " 2.05E+00 < 1.51E+00 < 3.97E+00 10/14/13 < 3.OOE+00 < 1.63E+00 < 3.74E-01 " 1.39E+00 " 1.57E+00 " 1.41E+01 " 4.46E+00 11/12/13 < 3.66E+00 < 2.20E+00 < 6.44E-01 " 1.68E+00 < 1.87E+00 < 2.07E+01 < 6.29E+00 12/17/13 < 4.06E+00 < 2.34E+00 < 4.32E-01 1.79E+00 < 2.05E+00 < 1.73E+01 " 5.83E+00
+1- +/- +1- +1- +1- +1-Mean LLD identified in [a] Tritium analyses on quarterly composite.
ODCM [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 Indicator 2.13E+03 +/- 1.23E+03 1.21E+03 +/- 1.12E+02 1.01E+03 +/- 146E+02 Control 2.22E+03 +I- 8.61E+02 5.61E+02 +/- 8.72E+01 6.19E+02 +I- 1.25E+02
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 Sr-89 Sr-90 K-40 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
[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
- 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 Figure4-1 TLD (mrem/StandardMonth)
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 -
0-
- Control G'ta-24 Indicator Average Pre-op - Required LLD Figure 4-2 HistoricalGross 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 2 - 0- z -I
- -4-Control Sta 24 -Ul-Indicators Figure4-3 2013 Gross Beta in Air Particulates(pCi/rm3) 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 ParticulateGamma 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 ParticulateStrontium 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 -- I-Req LLD 2000 1500 1500 1000 1000 Figure4-4Tritium 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 40 fl Co M M4 Ch 0) - a) D C3 U - 0 a LL Co 0 w 0 Z Figure4.5Tritium 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 MZ -' LCi)W L -) Z M M O0 5C Figure4-6 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 Description Date of Sampling Reason(s) for Loss/Exception 14B,15,16,23, Vegetation 01/08/13 Seasonal unavailability 26 14B, 15,16,23, Vegetation 02/13/13 Seasonal unavailability 26 14B,15,16,23, 26 Vegetation 03/12/13 Seasonal unavailability STA 5 AP/Char 03/12/13 Sampler not ruiming. Power pole damaged by snow storm.
STA 5 Annual/Qua 03/12/13 TLDs missing due to power pole damage from rterly TLD snow storm.
STA 2 AP/Char 04/09/13 Sampler not running/ replaced. Minimum volume not met.
14B,15,16,23, Vegetation 11/13/13 Seasonal unavailability.
26 14B,15,16,23, Vegetation 12/12/13 Seasonal unavailability 26 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 10CFR50, Appendix I", October, 1977.
United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975.
USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.
NUREG 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 PowerStation 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 Milk Sr-89 pCi/L 120 99.7 1.20 A Sr-90 pCi/L 9.21 11.0 0.84 A E10478 Milk 1-131 pCi/L 87.1 100 0.87 A Ce-141 pCi/L 186 187 0.99 A Cr-51 pCi/L 463 472 0.98 A Cs-134 pCi/L 201 214 0.94 A Cs-137 pCi/L 262 266 0.98 A Co-58 pCi/L 200 208 0.96 A Mn-54 pCi/L 215 208 1.03 A Fe-59 pCi/L 266 252 1.06 A Zn-65 pCi/L 311 301 1.03 A Co-60 pCi/L 384 400 0.96 A E10480 AP Ce-141 pCi 95.3 95.6 1.00 A Cr-51 pCi 264 241 1.10 A Cs-134 pCi 123 109 1.13 A Cs-137 pCi 142 136 1.04 A Co-58 pCi 112 106 1.06 A Mn-54 pCi 115 106 1.08 A Fe-59 pCi 139 129 1.08 A Zn-65 pCi 163 153 1.07 A Co-60 pCi 212 204 1.04 A El 0479 Charcoal 1-131 pCi 90.1 92.6 0.97 A E10481 Water Fe-55 pCi/L 1840 1890 0.97 A June 2013 E10564 Milk Sr-89 pCi/L 110 95.0 1.16 A Sr-90 pCi/L 15.8 17.0 0.93 A E10545 Milk 1-131 pCi/L 92.6 95.5 0.97 A Ce-141 pCi/L 83.1 90.4 0.92 A Cr-51 pCi/L 253 250 1.01 A Cs-1 34 pCi/L 118 125 0.94 A Cs-1 37 pCi/L 143 151 0.95 A Co-58 pCi/L 87.1 94.0 0.93 A 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 E10549 Water Fe-55 pCi/L 1610 1610 1.00 A September 2013 E10646 Milk Sr-89 pCi/L 63.9 96.0 0.67 N (1)
Sr-90 pCi/L 8.88 13.2 0.67 N (1)
E10647 Milk 1-131 pCi/L 93.9 98.3 0.96 A Ce-141 pCi/L NA (2)
Cr-51 pCi/L 272 277 0.98 A Cs-1 34 pCi/L 150 172 0.87 A Cs-1 37 pCi/L 125 131 0.95 A Co-58 pCi/L 105 108 0.97 A Mn-54 pCi/L 138 139 0.99 A Fe-59 pCi/L 125 130 0.96 A Zn-65 pCi/L 264 266 0.99 A Co-60 pCi/L 187 196 0.95 A E10672 AP Ce-141 pCi NA (2)
Cr-51 pCi 208 223 0.93 A Cs-134 pCi 143 139 1.03 A Cs-137 pCi 106 105 1.01 A Co-58 pCi 97.0 86.5 1.12 A Mn-54 pCi 116 112 1.04 A Fe-59 pCi 98.6 105 0.94 A Zn-65 pCi 219 214 1.02 A Co-60 pCi 166 158 1.05 A E10648 Charcoal 1-131 pCi 76.3 71.7 1.06 A E10673 Water Fe-55 pCi/L 1790 1690 1.06 A December 2013 E10774 Milk Sr-89 pCi/L 97.3 93.8 1.04 A Sr-90 pCi/L 13.3 12.9 1.03 A E10775 Milk 1-131 pCi/L 89.7 96.1 0.93 A Ce-141 pCi/L 99.8 110 0.91 A Cr-51 pCi/L 297 297 1.00 A Cs-134 pCi/L 129 142 0.91 A 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 Engineeringreportedresult.
(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.
(c) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluationbased 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 Bq/L 21.0 24.4 17.1-31.7 A Cs-137 Bq/L 0.0446 (1) A Co-57 Bq/L 28.3 30.9 21.6 - 40.2 A Co-60 Bq/L 18.2 19.56 13.69 - 25.43 A H-3 Bq/L 506 507 355 - 659 A Mn-54 Bq/L 25.7 27.4 19.2 - 35.6 A K-40 Bq/L 2.09 (1) A Sr-90 Bq/L 10.5 10.5 7.4 - 13.7 A Zn-65 Bq/L 29.2 30.4 21.3 - 39.5 A 13-GrW28 Water Gr-A Bq/L 2.74 2.31 0.69 - 3.93 A Gr-B Bq/L 15.6 13.0 6.5- 19.5 A 13-MaS28 'Soil Cs-1 34 Bq/kg 859 887 621-1153 A Cs-1 37 Bq/kg 633 587 411-763 A Co-57 Bq/kg 0.256 (1) A Co-60 Bq/kg 738 691 484 - 898 A Mn-54 Bq/kg 0.671 (1) A K-40 Bq/kg 714 625.3 437.7 - 812.9 A Sr-90 Bq/kg 442 628 440 - 816 W Zn-65 Bq/kg 1057 995 697 - 1294 A 13-RdF28 AP Cs-1 34 Bq/sample 1.73 1.78 1.25-2.31 A Cs-137 Bq/sample 2.73 2.60 1.82-3.38 A Co-57 Bq/sample 2.38 2.36 1.65- 3.07 A Co-60 Bq/sample 0.0302 (1) A Mn-54 Bq/sample 4.36 4.26 2.98 - 5.54 A Sr-90 Bq/sample 1.43 1.49 1.04- 1.94 A Zn-65 Bq/sample 3.14 3.13 2.19-4.07 A 13-GrF28 AP Gr-A Bq/sample 0.767 1.20 0.36-2.04 A Gr-B Bq/sample 0.871 0.85 0.43-1.28 A 13-RdV28 Vegetation Cs-134 Bq/sample -0.197 (1) A Cs-1 37 Bq/sample 7.39 6.87 4.81 -8.93 A Co-57 Bq/sample 9.87 8.68 6.08-11.28 A 86
1 Co-60 Bq/sample 6.08 5.85 4.10 - 7.61 A Mn-54 Bq/sample -0.0104 (1) A Sr-90 Bq/sample 1.28 1.64 1.15-2.13 W Zn-65 Bq/sample 6.84 6.25 4.38 - 8.13 A September 2013 13-MaW29 Water Cs-134 Bq/L 29.1 30.0 21.0 - 39.0 A Cs-137 Bq/L 34.5 31.6 22.1-41.1 A Co-57 Bq/L 0.0358 (1) A Co-60 Bq/L 24.6 23.58 16.51 - 30.65 A H-3 Bq/L 2.45 (1) A Mn-54 Bq/L 0.0337 (1) A K-40 Bq/L 0.193 (1) A Sr-90 Bq/L 9.12 7.22 5.05 - 9.39 W Zn-65 Bq/L 38.1 34.6 24.2 - 45.0 A 13-GrW29 Water Gr-A Bq/L 1.13 0.701 0.210-1.192 A Gr-B Bq/L 7.61 5.94 2.97- 8.91 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 Bq/kg 1150 1172 820-1524 A Cs-1 37 Bq/kg 1100 977 684-1270 A Co-57 Bq/kg 670 (1) N (2)
Co-60 Bq/kg 502 451 316-586 A Mn-54 Bq/kg 758 674 472- 876 A K-40 Bq/kg 796 633 443-823 W Sr-90 Bq/kg 664 460 322-598 N (2)
Zn-65 Bq/kg 210 (1) N (2) 13-RdF29 AP Cs-134 Bq/sample -0.570 (1) N (2)
Cs-1 37 Bq/sample 2.85 2.7 1.9- 3.5 A Co-57 Bq/sample 3.30 3.4 2.4 - 4.4 A Co-60 Bq/sample 2.41 2.3 1.6-3.0 A Mn-54 Bq/sample 3.65 3.5 2.5 - 4.6 A Sr-90 Bq/sample 1.40 1.81 1.27-2.35 W Zn-65 Bq/sample 2.90 2.7 1.9-3.5 A 13-GrF29 AP Gr-A Bq/sample 0.872 0.9 0.3-1.5 A Gr-B Bq/sample 1.57 1.63 0.82 - 2.45 A 13-RdV29 Vegetation Cs-134 Bq/sample 5.29 5.20 3.64 - 6.76 A Cs-1 37 Bq/sample 7.48 6.60 4.62 - 8.58 A Co-57 Bq/sample 0.0129 (1) A Co-60 Bq/sample 0.0523 (1) A Mn-54 Bq/sample 8.78 7.88 5.52- 10.24 A Sr-90 Bq/sample 1.63 2.32 1.62- 3.02 W (2)
Zn-65 Bq/sample 3.18 2.63 1.84- 3.42 W (1) Falsepositive 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 incorrectresults 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 it appears that the carrierwas double spiked into the sample, resultingin the low activity for this sample. NCR 13-04 (a) Teledyne Brown Engineeringreported result.
(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.
(c) DOEIMAPEPevaluation: A=acceptable, W=acceptable with warning, N=not acceptable.
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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 pCi/L 48.3 41.3 31.6-48.4 A Sr-90 pCi/L 19.3 23.9 17.2 - 28.0 A Ba-1 33 pCi/L 81.9 82.1 69.0 - 90.3 A Cs-134 pCi/L 40.9 42.8 34.2 -47.1 A Cs-137 pCi/L 44.0 41.7 37.0 - 48.8 A Co-60 pCi/L 61.9 65.9 59.3 - 75.0 A Zn-65 pCi/L 202 189 170 - 222 A Gr-A pCi/L 34.2 40.8 21.1 -51.9 A Gr-B pCi/L 18.0 21.6 13.0-29.7 A 1-131 pCi/L 23.8 23.8 19.7-28.3 A U-Nat pCi/L 60.4 61.2 49.8 - 67.9 A H-3 pCi/L 3970 4050 3450-4460 A MRAD-18 Filter Gr-A pCi/filter Lost during processing November 2013 RAD-95 Water Sr-89 pCi/L 25.5 21.9 14.4-28.2 A Sr-90 pCi/L 14.3 18.1 12.8-21.5 A Ba-133 pCi/L 57.2 54.2 44.7-59.9 A Cs-1 34 pCi/L 83.3 86.7 71.1-95.4 A Cs-1 37 pCi/L 201 206 185-228 A Co-60 pCi/L 104 102 91.8-114 A Zn-65 pCi/L 361 333 300- 389 A Gr-A pCi/L 29.5 42.8 22.2- 54.3 A Gr-B pCi/L 30.1 32.2 20.8- 39.9 A 1-131 pCi/L 23.1 23.6 19.6-28.0 A U-Nat pCi/L 5.53 6.24 47.0- 7.44 A H-3 pCi/L 17650 17700 15500- 19500 A MRAD-19 Filter Gr-A pCi/filter 33.0 83.0 27.8 - 129 A (a) Teledyne Brown Engineeringreported result.
(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the ControlLimits. CE= Check for Error.Reported result falls within the Control Limits and outside the Warning Limit.
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