ML081280636
| ML081280636 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/28/2008 |
| From: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 08-0124 | |
| Download: ML081280636 (85) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 2008 United States Nuclear Regulatory Commission Serial No.
08-0124 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. I AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSl)
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 Specifications, enclosed is the 2007 Annual Radiological Environmental Operating Report.
If you have any questions or require additional information, please contact Page Kemp at (540) 894-2295.
Very truly yours, Daniel G. Stoddard Site Vice President Enclosure Commitments made in this letter: None cc:
U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station
Dominion North Anna Power Station Radiological Environmental Monitoring Program January 1, 2007 to December 31, 2007 Prepared by Dominion, North Anna Power Station
Annual Radiological Environmental Operating Report North Anna Power Station January 1, 2007 to December 31, 2007 Prepared by:
Reviewed by:
Approved by:
George R. Simmons Supervisor Radiological Analysis Dominion North Anna Power Station Erich W. Dreyer Supervisor Health Physics Technical Services Dominion North Anna Power Station Robert'B. Evans, Jr.
Manager Radiological Protection and Chemistry Dominion North Anna Power Station 2
Table of Contents
- 1. EXECU TIVE SUM M A RY..........................................................................................................
4
- 2. PRO G RA M D ESCRIPTION.........................................................................................................
7 2.1 Introduction.............................................................................................................................
7 2.2 Sam pling and A nalysis Program........................................................................................
8
- 3. ANALYTICAL RESULTS...................................................................................................22 3.1 Sum m ary of Results..............................................................................................................
22 3.2 Analytical Results of 2007 REM P Sam ples..................................................................
32
- 4. D ISCU SSION OF RESULTS..................................................................................................
60 4.1 G am m a Exposure Rate.....................................................................................................
60 4.2 A irborne G ross Beta........................................................................................................
62 4.3 Airborne Radioiodine...............................................
63 4.4 A ir Particulate G am m a.....................................................................................................
63 4.5 A ir Particulate Strontium................................................................................................
63 4.6 Soil........................................................................................................................................
64 4.7 Precipitation...........................................................................................................................
64 4.8 Cow M ilk..............................................................................................................................
64 i
4.9 Food Products and Vegetation..........................................
65 4.10 W ell W ater..........................................................................................................................
65 4.11 River W ater.........................................................................................................................
66 4.12 Surface W ater......................................................................................................................
66 4.13 Bottom Sedim ent................................................................................................................
67 4.14 Shoreline Soil.................................................................
..................................................... 68 4.15 Fish......................................................................................................................................
69
- 5. PRO GRA M EX CEPTIO N S.......................................................................................................
70 REFEREN CES....................................................................................................................................
77 APPEND ICES......................................................................................................................................
73 APPEND IX A : LAND 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 2007 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 5.5.2b. Radioactivity levels from January 1 through December 31, 2007, 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 is 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. The first type, 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 or natural variation.
Global Dosimetry Solutions provided thermoluminescent dosimetry (TLD) services and AREVA Environmental Laboratory provided radioanalytical services.
Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy.
Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for 4
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 2007 airborne results were similar to previous years.
No plant related radioactivity was detected and fallout or natural radioactivity levels remained at levels consistent with past years' results.
Water and aquatic exposure pathway samples include surface, river and well water, silt and shoreline sediments, and fish.. No plant related isotopes were detected in Lake Anna surface water except for tritium.
The average tritium activity in surface water for 2007 was 3810 pCi/liter. River water collected from the North Anna River, 5.8 miles downstream of the site had an average tritium level of 3638 pCi/liter. No plant related radioisotopes were detected in well water.
This trend is consistent throughout the environmental operational monitoring program.
Both silt samples indicated the presence of naturally occurring potassium-40 and thorium-228 at levels consistent with the natural background.
Shoreline soil, which may provide a direct exposure pathway, indicated the presence of K-40 and Th-228 also at levels consistent with natural levels. Cs-137 was detected in the control location sediment sample at 86 pCi/kg. Cs-137 was detected in one shoreline soil sample at 134 pCi/kg.
This Cs-137 level is consistent with historic levels. The terrestrial exposure pathway includes milk and food/vegetation products. Iodine-131 was not detected in any 2007 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident.
No plant related radioisotopes were detected in any milk samples.
Naturally occurring beryllium-7, potassium-40 and thorium 228 were detected at environmental levels consistent with historical data. No plant related isotopes were detected.
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 2007, as in previous years, operation of the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) created no adverse r*
environmental effects or health hazards. The maximum dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous 5
effluents released from the station during 2007 was 0.62 millirem. For reference, this dose may be compared to the 360 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.
0 6
- 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2007 North Anna Power Station operational Radiological Environmental Monitoring Program (REMP).
The North Anna Power Station of Dominion Virginia Power Company 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 was designed with a gross electrical output of 979 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 is 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 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 responsible for processing the TLDs. AREVA Environmental Laboratory is responsible 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. This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.
Occasional samples of environment media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and 7
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 2007 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 2007 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 AREVA Environmental Laboratory for North Anna Power Station during the year 2007.
8
TABL--1 North Anna Power Station - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 0
Collection Sample Media Environmental Thermoluminescent Dosimetry (TLD).
Location NAPS Sewage Treatment Plant Fredericks Hall Mineral, Va Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685
.Route 700 "Aspen Hills" Orange, VA Bearing Cooling Tower Sturgeon'sCreek Marina Parking Lot "C" (on-site)
Good Hope Church Parking Lot "B" Lake Anna Marina (Bogg's Dr)
Weather Tower Fence Route 689 Near Training Facility "Morning Glory Hill" Island Dike Route 622 DVP Biology Lab Route 701 (Dam Entrance)
"Aspen Hills" Elk Creek NAPS Access Rd.
Station 01 02 03 04 05 05A 06 07 21 22 23 24 N-1/33 N-2/34 NNE-3/35 NNE-4/36 NE-5/37 NE-6/38 ENE-7/39 ENE-8/40 E-9/41 E-10/42 ESE-11/43 ESE-12/44 SE-13/45 SE-14/46 SSE-15/47 SSE-16/48 S-17/49 Distance 0.20 5.30 7.10 5.10 4.20 2.04 4.70 7.30 1.00 1.00 0.93 22.00 0.06 2.04 0.24 3.77 0.20 1.46 0.36 2.43 0.30 2.85 0.12 4.70 0.64 5.88.
0.93 2.33 0.47 Direction NE SSW WSW WNW NNE N
N NNE NNE NE NE ENE ENE E
Degrees 420 2030 2430 2870 200 110 1150 1670 3010 2420 1580 3250 100 110 320 250 420 340 740 650 910 930 1030 1150 1380 1370 1580 1650 1730 Frequency Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly & Annually Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control
- In October 1991 the Surface Water Sample location at station 09 was moved to 09A.
- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.
- Air Sample Station at 01A was added in October 2007 9
TABL#
North Anna Power Station - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 is Sample Media Environmental Thermoluminescent Dosimetry (TLD)
Location Elk Creek Church NAPS Access Rd.
Route 618 500kv Tower Route 700 NAPS Radio Tower Route 700 (Exclusion Boundary)
South Gate Switchyard Route 685 End of Route 685 Route 685 North Gate - Construction Side Laydown Area Lake Anna Campground
- 1/#2 Intake Route 208 Bumpass Post Office Orange, VA Mineral, VA Station S-18/50 SSW-19/51 SSW-20/52 SW-21/53 SW-22/54 WSW-23/55 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 NW-29/61 NW-30/62 NNW-31/63 NNW-32/64 C-1/2 C-3/4 C-5/6 C-7/8 Distance 1.55 0.42 5.30 0.6 3.96 0.38 1.00 0.32 1.55 1.00 1.40 0.45 2.54 0.07 2.21 7.30 22.00 7.10 11.54 Direction S
W WNW WNW NW NW NNW NNW SSE NW WSW WSW Degrees 1780 1970 2050 2180 2320 2370 2420 2790 2740 3010
.3030 3210 3190 3490 3440 1670 3250 2430 2570 Collection Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Remarks Control Control Control Control Louisa, VA Airborne Particulate and Radioiodine NAPS Sewage Treatment Plant Biology Lab***
Mineral, VA Wares Crossroads Route 752 Sturgeon's Creek Marina Levy, VA Bumpass, VA 01 OIA 03 04 05 05A 06 07 0.20 0.64 7.10 5.10 4.20 2.04 4.70 7.30 NE SE" WSW WNW NNE N
ESE SSE 420 1380 2430 2870 200 110 1150 1670 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly
- In October 1991 the Surface Water Sample location at station 09 was moved to 09A.
- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.
- Air Sample Station at 01A was added in October 2007 10
0 TABLO1 North Anna Power Station - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Airborne Particulate and Radioiodine Location End of Route 685 Route 700 "Aspen Hills" Orange, VA Station 21 22 23 24 Distance 1.00 1.00 0.93 22.00 Direction WNW WSW SSE NW Degrees 3010 2420 1580 3250 Collection Frequency Weekly Weekly Weekly Weekly Remarks Control Surface Water River Water Ground Water (Well Water)
Precipitation Aquatic Sediment Waste Heat Treatment Facility (Second Cooling Lagoon)
- Lake Anna (upstream)
(Route 669 Bridge) 08 3.37 SSE 1480 Monthly 09A 12.90 WNW 2950 Monthly 5.80 SE 1280 Monthly 0.64 SE 1380 Quarterly Control North Anna River (downstream) 11 Biology Lab Biology Lab 01A 01A 0.64 3.37 SE 1380 Monthly Waste Heat Treatment Facility (Second Cooling Lagoon)
Lake Anna (upstream)
(Route 669 Bridge)
North Anna River (downstream)
Waste Heat Treatment Facility (Second Cooling Lagoon)
NAPS Sewage Treatment Plant Fredericks Hall Mineral, VA Wares Crossroads 08 SSE 1480 Semi-Annually 09A 12.90 WNW 2950 Semi-Annually 5.80 SE 1280 Semi-Annually Control 11 Shoreline Soil Soil 08 **
3.37 SSE 1480 Semi-Annually 01 02 03 04 0.20 5.30 7.10 5.10 NE SSW WSW WNW 420 2030 2430 2870 Once/3 years Once/3 years Once/3 years Once/3 years
- In October 1991 the Surface Water Sample location at station 09 was moved to 09A.
- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.
- Air Sample Station at 01A %vas added in October 2007 11
TABL#
North Anna Power Station - 2007 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Soil Route 752 05 4.20 NNE 200 Once/3 years Sturgeon's Creek Marina Levy, VA Bumpass, VA End of Route 685 Route 700 (Exclusion Boundary)
"Aspen Hills" Orange, VA Holladay Dairy (R.C. Goodwin)
Terrell's Dairy (Fredericks Hall)
Anderson's Farm Waste Heat Treatment Facility (Second Cooling Lagoon)
Lake Orange 05A 06 07 21 22 23 24 2.04 4.70 7.30 1.00 1.00 0.93 22.00 N
ESE SSE WNW WSW SSE NW 110 1150 1670 3010 2420 1580 3250 3100' 2050 660 Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Once/3 years Control Milk Fish 12 13 27 08 25 14 15 16 23 8.30 NW 5.60 SSW 2.49 ENE 3.37 SSE 16.5 NW Monthly Monthly Monthly 1480 Semi-Annually 3120 Semi-Annually Control Food Products (Broadleaf Vegetation)
Bel Aire Plantation 1.20 NE 430 Monthly if available or at harvest 1.37 SE 1330 Monthly if available or at harvest Route 614 Route 629/522 12.60 NW 0.93 SSE 3140 Monthly if available or at harvest 1580 Monthly if available or at harvest Control Aspen Hills
- In October 1991 the Surface Water Sample location at station 09 was moved to 09A.
- Shoreline soil was changed from station 09 to 08 effective with the August 1996 sample.
- Air Sample Station at 01A was added in October 2007 12
TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Thermoluminescent Dosimetry (TLD)
(84 TLDs)
(12 TLDs)
Airborne Radioiodine Airborne Particulate Quarterly Annually Weekly Weekly Gamma Dose Gamma Dose 2 mR+2mR mR/std. Month 2 mR+2mR mR/std. Month 1-131 Gross Beta Surface Water Quarterly (a) 2 "d Quarter Composite Monthly Quarterly(a) 2nd Quarter Composite Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)
Sr-89 Sr-90 1-131 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 0.07 0.01 0.05 0.06 (b)
(b) 1(c) 15 30 15 15 30 30 15 15 18 60 15 2000 (b)
(b) 1(c) 15 30 15 15 30 30 15 15 18 60 15 pCi/mi 3
pCi/rn 3
pCi/m 3
pCi/rn 3
pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L River Water Monthly 0
- 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.
13
TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA River Water FREQUENCY Quarterly(a) 2nd Quarter Composite ANALYSIS Tritium (H-3)
Sr-89 Sr-90 Ground Water (Well Water)
Quarterly Quarterly(a) 2nd Quarter Semi-Annually Aquatic Sediment Annually Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium (H-3)
Sr-89 Sr-90 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 Gross Beta Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Gamma Isotopic Cs-134 Cs-137 Sr-89 Sr-90 LLD 2000 (b)
(b) 15 30 15 15 30 30 15 1(c) 15 18 60 15 2000 (b)
(b)
REPORT UNITS pCi/L pCi/L Precipitation Monthly Semi-Annual Composite pCi/L pCi/L pCi/L 150 180 (b)
(b) 4 15 30 15 15 30 30 15 1(c) 15 18 60 15 pCi/kg (dry) pCi/kg (dry) pCi/L pCi/L Shoreline Soil Semi-Annually 150 180 (b)
(b) pCi/kg (dry) pCilkg (dry)
Annually
- LLDs indicate those levels to which environmental samples are required to be analyzed.
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.
14 Actual analysis of samples may
TABLE 2-2 North Anna Power Station SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD REPORT UNITS Soil Once per 3 years Gamma Isotopic pCi/kg (dry)
Milk Monthly Monthly Quarterly Cs-134 Cs-137 Sr-89 Sr-90 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 150 180 (b)
(b) 1 15 18 60 15 (b)
(b) 130 260 130 130 260 130 150 pCi/kg (dry) pCi/L pCi/L Fish Semi-Annually pCi/kg (wet)
Food Products (Broadleaf Vegetation)
Monthly, if available, or at harvest pCi/kg (wet) 60 80 60 0
- 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.
15
Legend For The North Anna Power Station.
Environmental Monitoring Stations Overview Maps Map Designation Environmental Station Identification Map Designation 1
IA 2
3 4
5 5A 6
7 8
9A 11 12 13 14 15 16 21 22 23 24 25 26 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a) 01,NE-5/37 01A,SE-13/45 02,SSW-20/52 03,C-5/6 04 05 05A,N-2/34 06,ESE-12/44 07,C-1/2 08-Water, Fish Sediment, Shoreline Soil 09A-Water sample, sediment 11-River Water, Sediment 12-Milk 13-Milk 14-Vegetation, NE-6/38 Vegetation Vegetation 21,WNW-27/59 22,WSW-24/56 23-SSE-15/47 24,C-3/4 25-Fish 26-Vegetation 27 7/8 1/33 31/63 29/61 3/35 7/39 9/41 11/43 17/49 19/51 21/53 23/55 25/57
.16/48 18/50 14/46 22/54 26/58 28/60 32/64 8/40 4/36 10/42 Environmental Station 27-Milk C-7/8 N-1/33 NNW-31/63 NW-29/61 NNE-3/35 ENE-7/39 E-9/41 ESE-11/43 S-17/49 SSW-19/51 SW-21/53 WSW-23/55 W-25/57 SSE-16/48 S-18/50 SE-14/46 SW-22/54 W-26/58 WNW-28/60 NNW732/64 ENE-8/40 NNE-4/36 E-10/42 (a)
(a)
(a)
(a)(b)
(c)
(a) Indicates air sample station, annual and quarterly TLD, Triennial soil.
(b) In Orange (c) In Lake Orange 16
I Figure 1. Norlh Anna Site Radiological Monitoring Locations 17
0 C82M~
18
Me hJ 46MWiElbb 9ry I1 4
V I
ESE IM Nort Anna Environmental Map
.Fixed EnvixronmUt Sampkig Location
- Garden
- Residnfts Meg Anknaft O"W 121 WICI~AMO~*k Us. 644fUMA GMNW*
ANNNWW2D231I UmU SSK 16Ob awrx awn~
e.uftWmds uft pwwW=WA=
S SSE 19
0 0
0 North Anna Environmental Map Fbced Envk'omenwt Suaq*ig LocaIon
- M TIDO
- Gawe
- Rude*W Meat Aknmals mqlr Uvewrn al
,*SAM 20
0 0
Moxd BEn=oMns 8waIin Location TLD SunpOV
- Garden Od"*M1IYAWiMAinasmo MO-sr QVA 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 f indicated as "Mean/Range" include only positive results. Results are considered positive when the measured value exceeds 1.5 times the listed 2(y error (i.e., the measured value exceeds 3y). 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 - 2007 Docket No. 50-338/339 Page 1 of 9 All Indicator Co; Lnalysis Locations Location with Highest Mean Loc Direct Radiation (mR/std. Month)
(Sector TLDs)
Gamma 288 Dose 5.2(256/256) 19/51"'
0.42 mi.
(1.3-47.3)
SSW 31.9(8/8) 3.1(32/32)
(17.2-47.3)
(2.0-4.1)
Direct Radiation (mR/std. Month)
(Emergency Sector TLDs)
Direct Radiation (mR/std. month)
(Environmental TLDs)
Direct Radiation (mR/std. Month)
(Annual TLDs)
Airborne Particulates (1E-03 pCi/m 3 )
Gamma 40 Dose 2
4.9(40/40) 09/10 0.37 mi.
(2.8-9.1)
ENE 7.2(8/8)
(5.4-9.1) 3.1(32/32)
(2.0-4.1) 0 Gamma 48 Dose Gamma 12 Dose Gross 637**
Beta 2
3.4(44/44)
(1.3-5.8) 2 3.4(11/11)
(1.8-5.2) 0.01 28.8(585/585)
(9.6-70.2) 23 0.93 mi.
4.9(4/4)
SSE (4.4-5.6) 23 0.93 mi.
./
5.2(1/1)
(5.2) 3.4(4/4)
(3.0-3.8) 3.3(1/1)
(3.3) 26.4(52/52)
(6.1-43.4) 0 0
0 01A 0.64 mi.
35.9(13/13)
SE (17.1-53.3)
Air Iodine (pCi/m 3) 1-131 637 0.07 (0/585)
N/A N/A N/A (0/52) 0 Airborne Particulates (1E-03 pCi/m 3)
Gamma 50**
Be-7 50**
Cs-134 50**
Cs-137 50**
148.8(45/45)
(91-218) 03 7.1 mi.
176(4/4) 127.8(4/4)
WSW (150-210)
(91-150)
I 1
1 0.05 0.06 (0/45)
(0/45)
N/A N/A N/A N/A N/A N/A (0/4)
(0/4)
S (1) 19/51 located onsite near ISFSI.
- Analysis of 08/15/07 sample from Station 21 included in total number of analyses, but not in calculation of means or ranges.
23
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 2 of 9 All Indicator Control Non-Medium or Analysis Locations Location 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 Airborne Particulates (1E-03 pCi/m 3)
Sr-89 12 Sr-90 12 (0/11)
N/A N/A N/A N/A N/A N/A (01)
(0/1) 0 0
(0/11)
Soil (pCiIKg) (dry)
Triennial Gamma 12 Be-7 12 10725(2/11)
(850-20600) 05A 2.04 mi.
20600(1/1)
N (20600)
(0/1)
K-40 12 12264(11/11)
(4670-23800) 21 1.00 mi.
23800(1/1) 5900(1/1)
WNW (23800)
(5900)
Cs-134 12 150 (0/11)
Cs-137 12 180 270(3/11) 186-325 Th-228 12 1056(11/11)
(440-2170)
N/A N/A 03 7.1 mi.
WSW 22 0.93 mi.
SSE N/A N/A N/A 325(1/1)
(325) 2170(1/1)
(2170)
N/A (0/1) 0 0
0 0
0 0
0 (0/1) 1110(1/1)
(1110)
(0/1)
Sr-89 13
,Sr-90 13 N/A 400(2/12)
(390-410)
Precipitation (pCi/liter)
Monthly Gross Beta Semiannual Gamma 05 4.2 mi.
400(2/12)
NNE 390-410 01A 0.64 mi.
12.2(9/12)
SE (7-22.5)
(0/1)
N/A 12 4
12.2(9/12)
(7-22.5) 0 2
2 Be-7 24.0(1/2)
(24.0) 01A 0.64 mi.
24.0(1/2)
SE (24.0)
Mn-54 2
15 (0/2)
Fe-59 2
30 (0/2)
Co-58 2
15 (0/2)
Co-60 2
15 (0/2)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0
0 0
0 0
24
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 3 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)
Total (pCi/unit)
Mean Name Distance Mean Mean Measure-Type No.
Range Direction Range Range ments Precipitation (pCi/liter)
Zn-65 2
30 (0/2)
Zr-95 2
30 (0/2)
Nb-95 2
15 (0/2) 1-131 2
10 (0/2)
Cs-134 2
15 (0/2)
Cs-137 2
18 (0/2)
Ba-140 2
60 (0/2)
La-140 2
15 (0/2)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0
0 0
N/A N/A N/A N/A N/A 0
0 0
0 0
0 Milk (pCi/liter)
Gamma 24 K-40 24 1384(24/24)
(1210-1600) 12 8.3 mi.
1415(12/12)
NW (1230-1600) 1-131 24 1
(0/24)
Cs-134 24 15 (0/24)
Cs-137 24 18 (0/24)
Ba-140 24 60 (0/24)
La-140 24 15 (0/24)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0
0 0
0 0
0 0
Sr-89 (Quarterly) 8 (0/8) 25
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 4 of 9 All Indicator Control Non-Medium or Analysis Locations Location 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 Milk (pCi/liter)
Food Vegetation (pCi/kg) (wet)
Sr-90 8
(Quarterly)
Gamma 30 Be-7 30 K-40 30 (0/8)
N/A N/A N/A N/A 0
2599(23/24)
(1060-8350) 8128(23/24)
(3320-17600) 14 varies 3073(6/6)
NE (1560-8350) 14 varies 9613(6/6)
NE (3320-17600) 3533(6/6)
(1650-7330) 9982(6/6)
(4540-23600) 0 1-131 30 60 (0/24)
Cs-134 30 60 (0/24)
Cs-137 30 80 (0/24)
N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/6)
(0/6)
(0/6) 278(1/6)
(278)
N/A 0
0 0
0 0
0 0
Th-228 30 338(8/24)
(210-770)
(0/4) 23 varies 373(4/6)
SSE (210-770)
Ground Well Water (pCi/liter)
Tritium 4
2000 01A 0.64 mi.
SE N/A Gamma 4
Mn-54 4
15 (0/4)
Fe-59 4
30 (0/4)
Co-58 4
15 (0/4)
Co-60 4
15 (0/4)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0
0 0
0 26
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 5 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)
Total (PCi/unit)
Mean Name Distance Mean Mean Measure-Type INo.
Range I
Direction Range Range ments Ground Well Water (pCi/liter) 0 Zn-65 4
30 (0/4)
Zr-95 4
30 (0/4)
Nb-95 4
15 (0/4) 1-131 4
1 (0/4)
Cs-134 4
15 (0/4)
Cs-137 4
18 (0/4)
Ba-140 4
60 (0/4)
La-140 4
15 (0/4)
Sr-89 1
(0/1)
Sr-90 1
(0/1)
Tritium 4
2000 3638(4/4)
(2900-4400)
Gamma 12 Mn-54 12 15 (0/12)
Fe-59 12 30 (0/12)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A River Water (pCi/liter) 11 5.80 mi.
3638(4/4)
SE (2900-4400)
(0/4)*
0 N/A N/A N/A N/A N/A N/A (0/12)*
(0/12)*
0 0
0 Results of surface water taken at Location 09A used as control value for river water.
27
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 6 of 9 All Control Non-Medium or Analysis Indicator Location with Highest Mean Location routine Locations Pathway LLD Reported Sampled (Unit)
Total (pCi/unit Mean Name Distance Mean Mean Measure-I Type INO.
I Range Direction Range Range ments River Water (pCi/liter)
Co-58 12 Co-60 12 Zn-65 12 Zr-95 12 Nb-95 12 1-131 12 Cs-134 12 Cs-137 12 Ba-140 12 La-140 12 Sr-89 1
Sr-90 1
15 15 30 30 15 1
15 18 60 15 (0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/1)
(0/1)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)
(0/12)
(0/i2)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/1)
(0/1) 0 28
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 7 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCLunit)
Mean Name Distance Mean Mean Measure-(Unit)
Type No. I Range Direction Range Range ments Surface Water (pCi/liter) s Tritium Gamma Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 8
2000 3810(4/4)
(3300-4500) 08 3.37 mi.
SSE 3810(4/4)
(3300-4500)
(0/4) 24 24 24 24 24 24 24 24 24 24 24 24 15 30 15 15 30 30 15 1
15 18 60 (0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12)
(0/12) 0 0
29
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 8 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled Total (pCi/unit)
Mean Name Distance Mean Mean Measure-(Unit)
Type No.
Range Direction Range Range ments Surface Water (pCi/liter)
La-140 Sr-89 Sr-90 Gamma K-40 24 15 (0/12) 1 1
(0/1)
(0/1)
N/A N/A N/A N/A N/A N/A N/A (0/12)
N/A N/A (0/1)
(0/1) 0 0
0 Sediment Silt (pCi/kg) (dry) 6 6
150 6
180 6
12650(4/4)
(6300ý 15700)
(0/4)
(0/4) 1245(4/4)
(930-1890)
I 11 5.80 mi.
SSE 14300(2/2)
(13500-15100) 10750(2/2)
(9800-11700) 0 N/A N/A N/A (0/2)
N/A N/A N/A 86(1/2)
(86) 08 3.37 mi.
1410(2/2) 630(2/2)
SSE (930-1890)
(580-680) 0 0
0 Sr-89 (Annually)
Sr-90 (Annually) 3 (0/2)
(0/2)
N/A N/A N/A N/A N/A N/A (0/1) 0 (0/1) 0 Shoreline Soil (pCi/kg) (dry)
Gamma K-40 Th-228 Cs-134 Cs-137 3
2 2
2 2280(2/2)
(2250-2310) 08 3.37 mi.
2280(2/2)
SSE (2250-2310) 08 3.37 mi.
440(1/2)
SSE (440)
N/A 0
440(1/2)
(440)
N/A 0
2 150 (0/2)
N/A N/A N/A N/A N/A 0
0 2
180 134(1/2)
(134) 08 3.37 mi.
134(1/2)
SSE (134) 30
TABLE 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 2007 Docket No. 50-338/339 Page 9 of 9 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD Reported Sampled (Unit)
Total (pR/unit)
Mean Name Distance Mean Mean Measure-
_Type] No. IRange IDirectioni Range Range ments Shoreline Soil (pCi/kg) (dry)
Fish (pCi/kg) (wet)
Sr-89 (Annually)
Sr-90 (Annually)
Gamma K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 1
1 (0/1)
(0/1)
N/A N/A N/A N/A N/A N/A N/A N/A 0
0 130 260 130 130 260 130 1430(4/4)
(1120-1820)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4) 08 N/A N/A N/A N/A N/A N/A 3.37 mi.
SSE N/A N/A N/A N/A N/A N/A 1430(4/4)
(1120-1820)
N/A N/A N/A N/A N/A N/A 1363(4/4)
(1150-1610)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4) 0 0
0 0
0 0
0 31
3.2 Analytical Results of 2007 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 (20) 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 positive when the measured value exceeds 1.5 times the listed 2cy error (i.e., the measured value exceeds 3(y).
Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data'. For the purposes of this report all valid data are presented in order to indicate any background biases. AREVA Environmental Laboratory'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 of Analytical Results from HASL,," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept. 1984).
0 32
TABLE #3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) +/- 2 Sigma Page 1 of 4 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly*
01/03/2007 03/28/2007 06/28/2007 09/27/2007 Average 03/28/2007 06/28/2007 09/27/2007 12/27/2007
+/- 2 s.d.
N-1 4.1 4.0 3.5 5.0 4.3 1.8 N-33 4.2 3.4 3.8 6.1 N-2 2.6 3.2 3.0 4.1 3.1 +/-1.2 N-34 2.6 2.3 2.8 3.8 NNE-3 6.8 4.2 5.1 7.1 6.0 2.4 NNE-35 6.7 5.5 5.1 7.6 NNE-4 3.9 5.5 3.9 6.0 4.6 _ 1.6 NNE 36 4.0 4.7 4.0 4.8 NE-5 4.6 3.9 3.3 5.1 4.5 1.6 NE-37 4.6 3.7 4.7 5.7 NE-6 3.3 2.5 3.4 4.3 3.4 _ 1.5 NE-38 3.7 2.4 3.4 4.4 OENE-7 6.4 4.1 5.4 6.2 5.3 +/- 2.2 ENE-39 4.6 3.7 5.3 6.7 ENE-8 2.6 2.2 3.1 4.4 2.9 +/- 1.6 ENE-40 2.6 1.8 2.9 3.6 E-9 5.5 5.3 4.9 6.6 5.3 +/- 2.1 E-41 5.4 3.3 4.9 6.5 E-10 3.9 4.8 4.5 6.2 4.7 +/- 1.9 E-42 4.6 3.3 4.3 5.7 ESE-11 3.7 3.4 4.0 5.1 4.2 +/- 1.6 ESE-43 5.1 3.3 4.1 5.2 ESE-12 3.9 4.9 4.2 5.6 4.7 +/- 1.3 ESE-44 4.5 4.3 4.6 5.6 SE-13 3.6 3.4 4.2 5.5 4.2 +/- 1.7 SE-45 4.4 3.0 4.2 5.2 SE-14 5.8 6.3 6.1 8.0 6.7 +/- 1.7 SE-46 6.9 6.6 5.8 7.8 SSE-15 4.6 4.3 4.7 5.6 4.8 +/- 1.3 SSE-47 4.8 3.9 4.8 6.0 SSE-16 2.7 2.6 2.8 3.8 3.2 +/- 1.1 SSE-48 3.3 3.0 3.0 4.1
- Average of collocated TLDs.
33
TABLE #3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mR/Std. Month (30.4 days) t 2 Sigma Page 2 of 4 Station Name First Quarter Second Quarter Third Quarter Fourth Quarter Quarterly*
01/03/2007 03/28/2007 06/28/2007 09/27/2007 Average 03/28/2007 06/28/2007 09/27/2007 12/27/2007
+/- 2 s.d.
S-17 6.7 8.0 8.3 8.7 7.7 _ 1.5 S-49 7.9 6.6 7.4 8.1 S-18 2.1 2.1 1.3 3.1 2.1 1.3 S-50 2.0 1.3 2.4 2.7 SSW-19 46.9 18.3 17.2 19.0 31.9 +/-28.9 SSW-51 47.3 39.3 47.3 19.9 SSW-20 2.0 2.9 1.8 2.8 2.4 _ 1.0 SSW-52 2.3 2.3 2.0 3.3 SW-21 4.3 4.9 4.4 5.5 4.7 +/- 1.1 SW-53 3.9 4.6 4.4 5.5 SW-22 4.9 4.0 4.3 4.7 4.3 +/-1.1 SW-54 3.7 3.5 4.2 4.9 O
WSW-23 4.6 4.6 5.0 6.2 5.3 1.5 WSW-55 5.0 5.8 5.0 6.5 WSW-24 3.9 3.9 4.2 4.8 4.4 +/- 0.8 WSW-56 4.6 4.8 4.3 4.9 W-25 7.1 5.5 6.5 7.6 6.6 +/- 1.7 W-57 7.2 5.4 6.0 7.1 W-26 2.6 2.5 2.9 3.6 2.9 +/- 1.0 W-58 2.5 2.5 2.8 3.7 WNW-27 2.7 2.8 3.1 4.0 3.1 1.1 WNW-59 2.7 2.5 3.2 3.8 WNW-28 3.1 2.7 2.8 3.3 3.0 +/- 0.6 WNW-60 2.6 3.1 3.1 3.5 NW-29 5.8 5.3 6.3 7.6 6.2 +/- 1.9 NW-61 5.5 5.0 6.8 7.3 NW-30 2.0 1.6 2.3 3.0 22 +/-1.2 NW-62 3.0 1.4 2.3 2.0 NNW-31 3.4 2.6 3.1 3.9 3.4 +/- 1.4 NNW-63 3.0 2.7 3.7 4.7 NNW-32 3.1 3.0 3.9 5.1 3.8 1.5 NNW-64 4.2 3.0 3.5 4.3 Average 5.2 + 5.6 34
TABLE #3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mRIStd. Month (30.4 days) +/- 2 Sigma Page 3 of 4 Station Name First Quarter 01/03/2007 03/28/2007 Second Quarter 03/28/2007 06/28/2007 Third Quarter 06/28/2007 09/27/2007 Fourth Quarter 09/27/2007 12/27/2007 Quarterly*
Average
+/- 2 s.d.
EPSA-Ol **
EPSA-02**
EPSF-03**
EPSF-04**
EPSR-05**
EPSR-06**
EPSJ-07**~
EPSJ-08**
EPSP-09**
EPSP-1 0*
Average 4.7 4.2 4.1 4.6 4.2 4.3 3.6 5.1 7.1 8.4 3.8 3.6 3.8 3.6 3.5 3.5 3.2 2.8 5.4 5.6 4.1 4.6 4.7 4.2 5.0 3.8 3.8 4.6 6.8 6.6 5.9 5.4 5.4 5.2 4.8 5.4 4.8 4.9 8.9 9.1 4.5
+/-
1.6 4.5
+/-
1.2 4.3
+/-
1.4 4.1
+/-
1.8 7.2
+/-
2.9 4.9
+/-
1.5 3.3
+/-
0.8 2.9
+/-
1.4 2.6
+/-
0.8 3.6
+/-
0.8 3.1
+/-
1.2 C-1 C-2 C-3 C-4 C-5 C-6 C-7 C-8 3.7 2.6 2.8 2.8 2.6 2.1 4.0 3.8 3.2 3.0 2.7 2.3 2.8 2.0 3.3 3.1 3.1 3.2 2.3 2.4 2.6 2.3 3.3 3.3 3.6 3.8 4.1 4.0 3.1 3.0 4.0 4.1 Average
- Average of collocated TLDs
35
TABLE #3-2 DIRECT RADIATION MEASURMENTS - SECTOR QUARTERLY TLD RESULTS mRPStd. Month (30.4 days) +/- 2 Sigma Page 4 of 4 Station Name STA-01 STA-02 STA-03 STA-04 STA-05 STA-05A STA-06 STA-07 STA-21 STA-22 STA-23 First Quarter 01/03/2007 03/28/2007 4.1 2.5 2.0 2.4 2.9 2.5 4.8 4.0 2.4 5.1 4.4 Second Quarter 03/28/2007 06/28/2007 3.5 1.3 1.3 1.6 3.1 3.3 4.0 3.2 2.1 4.3 5.2 Third Quarter 06/28/2007 09/27/2007 3.3 1.6 2.3 2.5 3.7 2.3 4.6 3.1 2.7 4.4 4.4 Fourth Quarter 09/27/2007 12/27/2007 4.8 3.3 3.1 3.3 4.2 3.6 5.8 4.2 3.6 4.8 5.6 Location Average
+/- 2 s.d.
3.9 +/- 1.4 2.2 +/- 1.8 2.2 +/- 1.5 2.5 +/- 1.4 3.5+/-1.2 2.9 +/- 1.2 4.8+/- 1.5 3.6 +/- 1.1 2.7 +/- 1.3 4.7 +/- 0.7 4.9 +/- 1.2 3.4+2.6 3.4 +/-0.9 AnnualTLD 4.0 2.4 1.8 2.0 3.4 2.6 4.5 3.6 3.3 4.3 5.2 3.4+2.2 3.3 Average +/- 2 s.d.
STA-24*
- Control 3.7 3.0 3.0 3.8 36
0 Table 3-3 Air Particulate Gross Beta Radioactivity
[X 10-3 p i/rn3]
Period Endinci Station 01 Stationti)
Station 02 Station I03 Station 04 Station Station 05 05OA 01/03/07 44.5 01/10/07 21.3 01/17/07 21.5 01/24/07 15.8 02/01/07 36.6 02/08/07 43.1 02/15/07 34.3 02/21/07 28.5 03/01/07 19.8 03/07/07 23.2 03/14/07 35 03/21/07 22 03/28/07 26.3 04/04/07 28.1 04/11/07 22.4 04/18/07 14.2 04/25/07 22.4 05/02/07 21.3 05/10/07 14.7 05/17/07 18.3 05/23/07 20.3 05/30/07 32 06/07/07 22.7 06/13/07 20 06/20/07 22.5 06/27/07 28.8
+- 5.5
+- 4.7
+- 4.5
+- 4.5
+- 2.7
+- 5.4
+* 5.3
+* 5.3
+- 4.0
+- 5.2
+- 5.1
+- 4.6
+- 4.7
+- 4.8
+- 4.6
+- 4.3
+- 4.5
+- 4.5
+-
3.5
+-
4.6
+-
4.9
+-
5.6
+- 4.1
+-
5.2
+- 4.6
+- 4.9 35.5
+-
5.0 23
+-
4.9 22
+-
4.7 18.3
+-
4.6 33.8
+-
2.6 35.2
+-
5.2 32.5
+-
5.3 28.6
+-
5.3 18.1
+-
4.0 22.6
+-
5.2 36
+-
5.1 17.9
+-
4.5 25
+-
4.6 28.5
+-
4.9 20.8
+-
4.5 15.1
+-
4.4 21.9
+-
4.5 22.9
+-
4.6 15.7
+-
3.5 19.5
+-
4.8 24.5
+-
5.1 32.7
+-
5.2 26.4
+-
4.3 26.7
+-
5.6 24.4
+-
4.8 28.6
+-
4.4 32.8
+-
4.9 23
+-
4.8 19.5
+-
4.5 22.6
+-
4.8 30.7
+-
2.5 35
+-
5.2 21.9
+-
4.7 15.2
+-
4.5 19.9
+-
4.0 24.7
+-
5.3 31.3
+-
4.9 22.2
+-
4.7 28.9
+-
4.8 29.1
+-
4.9 26.4
+-
4.8 20.7
+-
4.6 22.6
+-
4.6 26.3
+-
4.7 17.3
+-
3.6 25.1
+-
4.9 26.4
+-
5.2 36.5
+-
5.5 21.2
+-
4.0 24.8
+-
5.4 23.9
+-
4.8 23.5
+-
4.5 40.2
+/
22.1
+/
23.8
+/
21.6
÷/
34.4
+/
32.7
+/
14.6
+/
31
+/
18.6
+/
28.1
+/
28.8
+/
21
+/
18.8
+/
9.6 22.3
+/
17.7
+/
23.2
+/
24.9
+/
16.9
+/
20.3
+/
21.4
+/
36.2
+/
24.3
+/
24.8
+/
23.9
+-
24.9
+/
5.2 4.8 4.7 4.7 2.6 5.1 4.3 5.3 4.0 5.5 4.8 4.6 4.3 4.1 4.7 4.5 4.6 4.7 3.6 4.7 5.0 5.4 4.2 5.4 4.8 4.5 34.7
+-
18.8
+/
21
+/
15.2
+/
26.2
+/
34.1
+/
23.3
+/
23.7
+/
20
+/
19.6
+/
33.5
+/
19.4
+/
28.8
+/
24.7
+/
26.8
+/
13
+/
18.9
+/
23.3
+/
16.3
+/
20.2
+/
24.7
+/
31.4
+/
25.7
+/
26.5
+/
25.2
+/
30.3
+/
5.0 4.7 4.6 4.4 4.7 5.1 4.7 5.0 4.0 5.0 5.0 4.5 4.8 4.7 4.9 4.2 4.4 4.6 3.6 4.7 5.2 5.2 4.2 5.5 4.9 4.8 33.8
+-5.0 21
+-
4.8 24.4
+-
4.7 24.4
+-
4.8 22.4
+-2.3 35.3
+-
5.2 29
+-
5.0 26.5
+-
5.2 17.5
+-
3.9 25.8
+-
5.3 38.2
+-
5.2 27.5
+-4.9 27
+-4.7 34.8
+-5.2 29.6
+-5.0 14.2
+-
4.3 23.9
+-4.6 28.3
+-
4.8 19.6
+-
3.8 28.7
+-
5.1 26.8
+-
5.3 41.7
+-
5.6 29.8
+-
4.4 31
+-
5.8 22.9
- +-
4.8 29.5
+-4.7 (1) Sampler installed in October 2007
- Station 2 collected 06/28/07 37
Table 3-3 Air Particulate Gross Beta Radioactivity Period Ending Station 06 Station 07 Station 21 Station 22 Station I23 Station I 24 01/03/07 01/10/07 01/17/07 01/24/07 02/01/07 02/08/07 02/15/07 02/21/07 03/01/07 03/07/07 03/14/07 03/21/07 03/28/07 04/04/07 04/11/07 04/18/07 04/25/07 05/02/07 05/10/07 05/17/07 05/23/07 05/30/07 06/07/07 06/13/07 06/20/07 06/27/07*
36.8
+/
19.5
+/
17.7
+/
16.1
+/
35
+/
30.3
+/
27.3
+/
31.7
+/
21.6
+/
27.4
+/
27.2
+/
23.1
+/
24.3
+/
26.1
+/
19.1
+/
11.3
+/
19.5
+/
26.2
+/
14.2
+/
22.4
+/
23.7
+/
28.7
+/
22
+/
24.6
+/
22
+/
26.9
+-
5.1 4.7 4.4 4.4 2.7 4.9 4.9 5.4 4.2 5.4 4.7 4.7 4.6 4.8 4.5 4.1 4.4 4.8 3.4 4.8 5.1 5.1 4.1 5.5 4.7 4.3 35.2
+-
5.0 19.4
+-
4.7 23.9
+-
4.7 22.8
+-
4.8 24.4
+-
2.4 34
+-
5.1 33
+-
5.4 36.1
+-
5.7 20.6
+-
4.1 23.5
+-
5.2 30
+-
4.9 24.7
+-
4.8 26.2
+-
4.7 24.8
+-
4.7 23.3
+-
4.7 12.5
+-
4.2 25.1
+-
4.6 20.5
+-
4.5 12.9
+-
3.4 20.4
+-
4.8 23.1
+-
5.0 30
+-
5.1 19.7
+-
3.9 24.2
+-
5.5 24.5
+-
4.8 25.2
+-
4.3 28.2
+-
4.7 19
+-
4.7 22.7
+-
4.6 19
+-
4.6 31.9
+-
2.6 21.4
+-
4.5 30.6
+-
5.0 31
+-
5.4 16.5
+-
3.9 23.9
+-
5.3 32.8
+-
5.0 23.5
+-
4.7 32.3
+-
5.0 28.4
+-
4.8 24.3
+-
4.7 14.7
+-
4.3 22.8,+/
4.6 15.9
+-
4.2 17.1
+-
3.6 22.7
+-
4.8 22.4
+-
5.0 27.8
+-
5.2 22.8
+-
4.1 18.7
+-
5.2 19.4
+-
4.5 25.9
+-
4.7 31.6
+/
19.6
+/
21.7
+/
20.2
+/
35.3
+/
38.5
+/
28.8
+/
26.7
+/
20.4
+/
22.8
+/
31.2
+/
23.5
+/
27.4
+/
30.6
+/
25.8
+/
16.4
+/
21.5
+/
32.5
+/
23.3
+/
29.1
+/
25.9
+/
29.1
+/
27.9
+/
25.9
+/
24
+/
23.3
+-
4.9 4.7 4.6 4.6 2.7 5.3 5.0 5.2 4.0 5.2 4.9 4.7 4.7 4.9 4.8 4.4 4.5 5.1 4.0 5.1 5.2 5.2 4.3 5.5 4.7 4.6 35.2
+-
5.2 17.6
+-
4.6 21.8
+-
4.6 23.1
+-
4.8 32.2
+-
2.6 40.9
+-
5.4 27.1
+-
5.6 30.3
+-
5.7 20
+-
4.0 23
+-
5.2 29.6
+-
4.9 24.2
+-
4.7 34.3
+-
5.1 28.1
+-
4.8 30.5
+-
5.0 18
+-
4.5 24
+-
4.5 23
+-
4.6 17.1
+-
3.6 28.8
+-
5.2 24.4
+-
5.1 38.7
+-
5.6 30
+-
4.5 22.2
+-
5.4 21.9
+-
4.6 24.9
+-
4.6 32.9
+/
26.7
+/
27.1
+/
26.2
+/
39.2
+/
39
+/
28.9
+/
28.8
+/
18.2
+/
22.7
+/
39.5
+/
21.3
+/
25.6
+/
21.7
+/
21.9
+/
14.7
+/
21.1
+/
25
+/
6.1
+/
9.3
+/
4.7
+/
10.1
+/
25
+/
20.2
+/
22.4
+/
21.1
+/
4.9 5.0 4.9 4.9 2.8 5.4 5.0 5.3 4.0 5.2 5.3 4.6 4.6 4.6 4.6 4.3 4.5 4.7 3.2 4.1 4.1 4.9 4.3 5.2 4.8 4.4
- Stations 06 & 07 collected 06/28/07 38
0 Table 3-3 Air Particulate Gross Beta Radioactivity
[X 10-3 pCi/rn 3]
Period Endina Station 01 Stationt1 )
01A Station I 02 I
Station 03 Station 04 Station 05 Station I
05A 07/04/07 39.2
+-
5.4+-
07/11/07 63.9
+-
6.2+-
07/18/07 38.7
+-
5.3+-
07/26/07 28.6
+-
4.5+-
08/01/07 29.5
+-
5.2+-
08/08/07 41.9
+-
5.4+1 08/15/07 23.8
+-
4.6+-
08/23/07 28.6
+-
4.8+-
08/29/07 20.6
+-
4.7+-
09/05/07 31.1
+-
5.1+-
09/12/07 39.9
+-
5.4 09/19/07 24.5
+-
4.7 09/27/07 29.8
+-
4.8 10/03/07 23.4
+-
3.3 29.2 10/10/07 22.2
+-
4.5 21.7
+
10/17/07 39.4 5/.5 45.4 10/24/07 46.6 5.8 5.8
.4 11/01/07 20.2
+-
4.3 17.1 11/07/07 30.2
+-
5.2 33.1
+
11/15/07 50.6
+-
5.4 49.1
/
11/21/07 40.1
+-
5.7 34.0
/
11/28/07 32.3
+-
5.0 35.6
/
12/05/07 42.5
+-
5.4 35.0
/
12/12/07 43
+-
5.4 46.1
/
12/19/07 28
+-
4.7 22.3
/
12/26/07 32.1
+-
5.1 53.3
~
(1)
Sampler installed October 2007 08/22/2007 Stations 02 & 03 sampled on 08/23/07 09/26/2007 Station 02 sampled on 09/27/07 18.4 30.1 37.1 22.6 27.7 45.4 27.9 21.6 23 34.2 40.6 27.1 29.3 27.7 29.5 39.3 41.7 17.6 27.4 41.8 24.1 27.2 32.4 43.5 23.1 50.5
+-4.9
+- 4.9
+-5.3
+- 4.2
+-
5.0
+- 5.5
.+- 4.8
+-
4.3
+- 5.2
+-
5.2
+- 5.3
+- 4.9
+- 4.3
+-
3.8
+-
5.0
+- 5.5
+- 5.6 4.1
+-
5.0
+- 5.0
+-
5.2
+-
4.6
+- 4.9
+-
5.4
+-
4.5
+- 5.7 23.2
+-
35.1
+/
29.1
+-
21.1
+-
28.7
+-
43.6
+/
19
+-
26.3
+/
29.9
+/
28.8
+-
42.9
+/
23.4
+/
33.1
+-
33.7
+-
19.7
+-
30
+/
39.6
+-
17.1
+-
29.3
+-
41.6
+/
27.6
+/
25.9
+/
33.4
+/
40.2
+/
18.3
+/
39.6
+/
4.8 5.1 5.0 4.1 5.1 5.5 4.3 4.4 5.6 4.9 5.5 4.6 5.0 3.6 4.5 5.1 5.5 4.1 5.1 5.0 5.2 4.6 5.0 5.3 4.2 5.3 18
+-4.5 33.9
+-
5.1 26.7
+-4.8 23.4
+-4.2 30.6
+-5.3 35.7
+-
5.1 22.7
+-
4.5 21.6
+-
4.6 15.2
+-
4.4 29.6
+-
5.0 38.6
+-5.3 18.9
+-
4.5 37.8
+-
5.1 30.6
+-3.6 23.2
+-4.7 33.6.
+-
5.2 40.1
+-
5.5 14.1
+-
4.0 35.4
+-
5.4 46.5
+-
5.2 27.9
+-
5.3 30.7
+-
4.8 39.3
+-
5.3 36.5
+-
5.0 19.2
+-
4.2 40.7
+-
5.4 20.5
+-
4.6 42.1
+-
5.4 33
+-
5.1 24
+-4.2 29.6
+-5.2 51.1
+-
5.8 24.2
+/.
4.6 26.8
+-
4.9 26.3
+-
4.9 38.7
+-
5.4 41.3
+-
5.4 26.7
+-
4.8 28.6
+-
4.6 35.3
+-
3.7 25.9
+-4.8 38.3
+-
5.4 41.4
+-
5.5 16.8
+-
4.1 22.7
+-4.7 47.9
+-5.2 22.8
+-
5.0 30.2
+-
4.8 28.8
+-
4.7 42.5
+-
5.3 26
+-
4.6 43.1
+-
5.4 25.2 33.7 35.4 24.4 33.9 52 24 26.3 19.8 33.4 42.6 24.4 34.4 33.3 26.6 32.9 46.9 21.8 32.6 41.5 33.2 27.6 38.2 32 25.4 45.6
+- 4.8
+-
5.1
+- 5.2
+- 4.3
+- 5.4
+- 5.8
+- 4.5
+/: 4.9
+- 4.6
+- 5.2
+- 5.5
+- 4.7
+- 5.0
+- 3.6
+- 4.8
+- 5.2
+- 5.8
+- 4.3 5.
+- 5.0
+- 5.5
+- 4.7
+- 5.2
/-
4.9
+- 4.6
+- 5.6 9.1 4.6 6.0 5.7 4.1 5.3 5.3 5.5 5.1 5.0 5.5 4.4 5.9 39
(2)
Table 3-3 Air Particulate Gross Beta Radioactivity
[X 10- pCi/rn 3]
Period Endinci Station 06 Station 07 Station 21 Station 22 Station 23 Station 24 I
07/04/07 18.3
+-
4.9 18.2
+-
5.0 20.8
+-
4.6 19.3
+-
07/111/07 31.5
+-
5.0 33.3
+-
5.1 31.1
+-
4.9 37.2
+-
07/18/07 32.9
+-
5.1 32
+-
5.1 30.7
+-
5.0 27
+-
07/26/07 20.5
+-
4.1 21.5
+-
4.1 22.4
+-
4.2 21.7
+-
08/01/07 27.8
+-
5.1 25.7
+-
4.9 28.2
+-
5.1 27.8
+-
08/08/07 44.9
+-
5.5 43.4
+-
5.5 37.4
+-
5.2 48.5
+-
08/15/07 17.9
+-
4.2 21.3
+-
4.4 1720*
4-/-
70.0 28.6
+-
08/23/07 25.1
+-
4.9 24.2
+-
4.9 18.5
+-
4.9 27.9
+-
08/29/07 14.5
+-
4.2 17
+-
4.3 23
+-
5.3 22.7
+-
09/05/07 48.3
+-
5.3 39.6
+-
5.4 33.3
+-
5.1 37.9
+-
09/12/07 37.2
+-
5.3 39.1
+-
5.3 34.6
+-
5.2 1.5
+-
09/19/07 24.8
+-
4.8 25.1
+-
4.8 28.4
+-
4.9 70.2
+-
09/27/07 32.1
+-
4.8 36.8
+-
5.0 30.7
+-
4.8 41.4
+-
10/03/07 30.8
+-
3.6 40.7
+-
3.9 34.4
+-
3.7 31
+-
10/10/07 22.6
+-
4.6 20.8
+-
4.6 17.6
+-
4.4 26.3
+/
10/17/07 35.1
+-
5.3 31.9
+-
5.2 34.2
+-
5.3 33.2
+/
10/24/07 39.9
+-
5.4 43.2
+-
5.6 42.4
+-
5.6 38.7
+/
11/01/07 18.1
+-
4.2 15.7
+-
4.1 22
+-
4.3 17.9
+/
11/07/07 23.2
+-
4.8 21.8
+-
4.7 26.3
+-
5.0 31.6
+/
11/15/07 46.7
+-
5.2 31.2
+-
4.6 44.1
+-
5.1 48
+/
11/21/07 32.7
+-
5.6 25.2
+-
5.2 27.2
+-
5.1 33.1
+/
11/28/07 28.3
+-
4.7 24.9
+-
4.5 32.8
+-
5.0 25
+/
12/05/07 34.9
+-
5.0 26.9
+-
4.6 31.1
+-
4.8 35.8
+/
12/12/07 47.4
+-
5.6 43.1
+-
5.4 35.4
+-
5.0 40.9
+/
12/19/07 18.1
+-
4.2 23.2
+-
4.4 21.4
+-
4.4 24.7
+/
12/26/07 40.4
+-
5.3 30.6
+-
4.9 44
+-
5.5 32.5
+/
08/15/2007 Station 21 had low volume.
08/22/2007 Stations 21 & 23 sampled on 08/23/07 09/26/2007 Stations 22 & 23 sampled on 09/27/07
- Not included in average. Greater than 10 times average. Gamma spectromnetry performed on filter.
4.5 21.6
+-
4.8 19.4
+-
4.5 5.2 33.9
+-
5.1 34.3
+-
5.1 4.8 37.1
+-
5.4 31
+-
5.0 4.1 21.5
+-
4.1 22
+-
4.2 5.1 32.7
+-
5.3 27.9
+-
5.2 5.7 46.6
+-
5.6 43.4
+-
5.5 5.1 22.1
+-
4.5 22.1
+-
4.4 4.8 21.9
+-
4.3 21.1
+-
4.6 4.8 24.9
+-
5.3 21
+-
3.6 5.3 39.3
+-
5.5 36.6
+-
5.3 3.5 40.3
+-
5.3 36.2
.+-
5.3 6.6 23.4
+-
4.7 28.4
+-
4.9 4.9 32.2
+-
4.5 27.4
+-
4.6 4.0 30
+-
3.9 28.8
+-
3.5 4.7 34.2
+-
4.9 31.9
+-
5.0 5.2 33
+-
5.2 36
+-
5.3 5.4 40
+-
5.5 38.9
+-
5.4 4.1 17.3
+-
4.1 21.8
+-
4.3 5.3 30.4
+-
5.3 27.6
+-
5.0 5.3 44.4
+-
5.0 41.6
+-
5.0 5.4 24
+-
5.1 27.9
+-
5.4 4.6 31.5
+-
4.8 26.3
+-
4.5 5.1 31.2
+-
4.9 23.2
+-
4.4 5.3 33.2
+-
4.9 43
+-
5.3 4.5 26.9
+-
4.7 14.8
+-
4.0 5.1 40.5
+-
5.5 38.8
+-
5.3 40
0 Table 3-4 Airborne Iodine I-131
[x 10-3 pCi/m 3]
Period Station Ending I 01 01/03/07
-3
+/-
14 01/10/07 0
+/-
13 01/17/07
-8
+/-
16 01/24/07 6
+--
15 02/01/07 0
+
16 02/08/07 1
+/-
14 02/15/07
-6
+/-
16 02/21/07
-2
+/-
20 03/01/07
-3
+/-
13 03/07/07
-11
+/-
13 03/14/07
-2
+/-
17 03/21/07
-3
+/-
17 03/28/07
-8
+/-
15 04/04/07.
1
+/-
13 04/11/07 5
+/-
14 04/18/07 5
+/-
14 04/25/07
-2
+/-
17 05/02/07 17
+/-
21 05/10/07 9
+/-
16 05/17/07
- -6
+/-
14 05/23/07 2
+/-
15 05/30/07
-2
+/-
14 06/07/07 1
+/-
15 06/13/07
-4
+/-
12 06/20/07 3
+/-
22 06/27/07*
-12
+/-
24 (1) Sampler installed October 2007,
- Station 2 Collected 06/28/07 Station(1)
S 01A Station S 02
-2
+/-
13
-3
+/-
15 6
+/-
17
-8
+/-
16 5-
+/-
14 4
+/-
14
-4
+/-
15 2
+/-
18 12
+/-
15 2-
+/-
14 6
+/-
16
-2
+/-
18
-5
+/-
19
-4
+/-
15 5
+/-
16
-8
+/-
13 17
+/-
15 6
+/-
19 11
+/-
14
-9
+/-
18 2
+/-
18 2
+/-
16 4
+/-
13 0.3
+/-
9.5 5
+/-
24 13
+/-
20 Station S03
-2
+/-
-3
+/-
5
+/-
-9
+/-
5
+/-
3
+/-
-6
+/-
9
+/-
-4
+/-,
5
+/-
-6
+/-
7
+/-
-25
+/-
4
+/-
9
+/-
-2
+/-
12
+/-
-2
+/-
-12
+/-
9
+/-
-9
+/-
-16
+/-
-4
+/-
4
+/-
-29
+/-
20
+/-
Station 04 11
-6
-9
-9 0
7
-9 2
-5
-8
-8 2
-8
-15 3
2 3
-7 3
-1
-2
-7 9
-12 0
-7 2
-2 3
-14
-6 4
0 0
3 6
-2 3
-3 6
-8 6
-13
-13
-2 3
11 7
-14
-3 8
2 Station Station 05 05A
+/-
15
-6
+/-
+/-
17 2
+/-
18 11
+/-
+/-
17
-3
+/-
+/-
24
-3
+/-
+/-
11 8
+/-
+/-
15
-7
+/-
+/-
21
-14
+/-
+/-
13
-1
+/-
+/-
14 3
+/-
+/-
15
-2
+/-
+/-
15
-12
+/-
+/-
18 8
+/-
+/-
14
-6
+/-
+/-
18
-13
+/-
+/-
15
-9
+/-
+/-
13
-8
+/-
+/-
19
-2
+/-
+/-
15 3
+/-
+/-
14
-6
+/-
+/-
16
-31
+/-
+/-
13 12 *
+/-
13
-3
+/-
+/-
12
-5
+/-
-/-
29 0
+/-
+/-
20 0
+/-
17 20 17 16 12 14 15 23 14 12 15 18 16 14 19 17 17 18 11 13 18 18 11 13 29 27 41
1 Table 3-4 Airborne Iodine I-131
[x 10,3 pCi/m 3]
Period Endina Station Station 06 I
07 Station 21 Station 22 Station Station 23 I
24 01/03/07 01/10/07 01/17/07 01/24/07 02/01/07 02/08/07 02/15/07 02/21/07 03/01/07 03/07/07 03/14/07 03/21/07 03/28/07 04/04/07 04/11/07 04/18/07 04/25/07 05/02/07 05/10/07 05/17/07 05/23/07 05/30/07 06/07/07 06/13/07 06/20/07 06/27/07*
-3
+/-
3
+/-
-8
+/-
-6
+/-
-3
+/-
1
+/-
3
+/-
-17
+/-
-4
+/-
11
+/-
-6
+/-
-14
+/-
+/-
-1.5
+/-
5
+/-
3
+/-
0
+/-
-8
+/-
12
+/-
8
+/-
4
+/-
-7
+/-
-14
+/-
4
+/-
-16
+/-
6
+/-
13
-3
+/-
17 15
-2
+/-
15 16
-11
+/-
14 15 0
+/-
18 14 3
+/-
13 10 1
+/-
16 12
-12
+/-
16 19 6
+/-
20 13
-1
+/-
12 16
-1
+/-
18 16 5
+/-
17 16 2
+/-
13 14 8
+/-
17 10 3
+/-
13 16 3
+/-
14 15
-8
+/-
18 16 12
+/-
18
- 16.
4
+/-
16 16 14
+/-
15 17 10
+/-
14 18 4
+-/-
13 18 3
+/-
16 15 3
+/-
14 12
-6
+/-
16 24
-5
+/-
24 18
-6
+/-
20 5
+/-
5
+/-
3
+/-
5
+/-
10
-/-
9
+/-
1
+/-
4
-3
+/-
-7
+/-
5
+/-
-2
+/-
3
+/-
0
+/-
-5
+/-
0
+/-
2
+/-
2
+/-
-8
+/-
-9
+/-
-13
+/-
-7
+/-
-4
+/-
-5
+/-
-8
+/-
16
+/-
15
-3
+/
16 3
+/
15
-3
+/-
17 9
+/-
12 0
+/-
15
-6
+/-
17 16
+/-
21 4
+/-
14 3
+/-
15 15
+/-
14 16
+/-
15
-3
+/-
18 16
+/-
16
-3
+/-
16
-8
+/-
16 8
+/
18
-14
+-
16
-2
+/
15 6
+/
13 7
+/
17
-31
+/
17 9
+/
13
-4
+/
14
-11
+/
25 8
+/
22 9
+/-
14
-2
+/
14 0
+/
18
-6
+/-
19 3
+/-
11 3
+/-
12
-1
+/-
16 3
+/-
21
-13
+/-
13
-9
+/-
18
-11
+/-
14
-3
+/-
17 0
+/-
15 3
+/-
16
-1
+/
14 5
+/
15
-16
+/
19 2
+/
18 21
+/
16 11
+/
15 3
+/
18 18
+/
15
-2
+/
14
-5
+/
15 0
+/
20
-16
+/
24
-14
+/-
17
-17
+/-
18 16
+/-
18 6
+/-
14
-8
+/
12 1
+/
12
-1
+/-
16
-1
+/
27 12
+/
14 7
+/-
16
-7
+/
14
-6
+/-
17 11
+/
14 6
+/-
15 5
+/-
17 8
+/-
16 6
+/-
17 3
+/-
16 2
+/-
12 25
+/-
17
-3
+/-
15 4
+/-
18 8
+/-
12 2
+/-
14
-3
+/-
21 5
+/-
25 7
+/-
16 18 16 14 14 15 13 21 15 15 13 17 16 13 15 16 19 15 29 10 16 21 15 16 21 24
- Stations 06 &07 collected 06/28/07 42
0 0
Table 3-4 Airborne Iodine I-131
[x 10,3 pCi/m 3]
Period Ending 07/04/07 07/11/07 07/18/07 07/26/07 08/01/07 08/08/07 08/15/07 08/22/07 08/29/07 09/05/07 09/12/07 09/19/07 09/26/07 10/03/07 10/10/07 10/17/07 10/24/07 11/01/07 11/07/07 11/15/07 11/21/07 11/28/07 12/05/07 12/12/07 12/19/07 12/26/07 0
-2 4
0
-18 2
13 6
2
-2
-2 4
0
-8 7
0
-6 0
-5
-7 0
-4 14 6
-26 Station Station(1 )
01 01A
+/-
21
+/-
16
+/-
18
+/-
14
+-/-
23
+/-
13
+/-
14
+/-
14
+/-
17
+/-
17
+/-
15
+/-
12
+/-
15
+/-
14 5
+/-
+1-14 16
+/-
+/-
16 2
+/-
-/-
14 3
+/-
+/-
12 0
+/-
+/-
12 0
+/-
+/-
17
-2
+/-
+/-
22
-11
+/-
+/-
22
-14
+/-
+/-
17 5
+/-
+/-
26
-2
+/-
+/-
26
-8
+/-
Station 0 2 15
+/-
19 9
+/-
21 15
+/-
15 0
+/-
15
-6
+/-
21
-6
+/-
14
-9
+/-
17 0
+/-
11 10
+/-
20
-5
+/-
16 10
+/-
15
-13
+/-
15 9
+/-
15 0
+/-
19
-6
+/-
14
-1
+/-
12
-4
+/-
12 10
+/-
13 0
4-/-
14 14
+/-
19
-14
+/-
23
-10
+/-
17
-6
+/-
17
-28
+/-
24 2
+/-
27 Station S 03
-9
+/"
6
+/-
2
+/-
7
+/-
-9
+/-
-12
+/-
6
+/-
13
+/-
-21
+/-
0
+/-
11
+/-
-10
+/-
-13
+/-
3
+/-
-1
+/-
0
+/-
-10
+/-
9
+/-
-5
+/-
-5
+/-
-14
+/-
-10
+/-
-13
+/-
0
+I-
-10
+/-
I I
l Station 04
-13
-2 0
-10
-19
-3
-13
-2 6
2 11
-1 2
-10
-12
-3
-4
-6 21 2
25 2
0 16
-4 Station 25 15 20 12 23 14 15 13 14 19 15 16 14 15 14 15 13 13 14 18 25 16 17 21 28 05 3
+/-
-13
+/-
-7
+/-
-3
+/-
-9
+/-
2
+/-
0
+/-
13
+/-
-15
+/-
17
+/-
8
+/-
-1
+/-
-14
+/-
-2
+/-
-3
+/-
0
+/-
9
+/-
-9
+/-
-9
+/-
14
+/-
-14
+/-
-3
+/-
-13
+/-
18
+/-
-8
+/-
31 16 20 18 24 16 15 19 18 20 13 15 20 13 13 14 15 17 15 18 28 19 17 20 28 Station I
05A 7
+/-
6
+/-
2
+/-
9
+/-
-9
+/-
8
+/-
8
+/-
-17
+/-
-8
+/-
-9
+/-
16
+/-
-1
+/-
2
+/-
-3
+/-
6
+/-
-1
+/-
-9
+/-
1
+/-
-2
+/-
7
+/-
0
+/-
10
+/-
6
+/-
4
+/-
8
+/-
19 16 18 13 26 14 17 13 19 17 15 15 17 16 15 12 14 14 15 13 25 21 18 22 29 36 15 14 12 13 14 16 22 21 19 19 26 9
+/-
26 20
+/-
26
-17
+/-
20
-7
+/-
24 4
+/-
20 4
+/-
21
-4
+/-
21 (1) Sampler installed October 2007 08/22/2007 St-ations 02 & 03 sampled on 08/23/07 09/26/2007 Station 02 sampled on 09/27/07 43
Table 3-4 Airborne Iodine I-131
[x 10-3 pCi/m 3]
Period Endincg Station 06 Station 07 I
Station 21 Station I
22 Station 23 Station 24 07/04/07
-20
+/-
25 07/11/07 17
+/-
19 07/18/07
-2
+/-
22 07/26/07 12
+/-
14 08/01/07
-15
+/-
20 08/08/07 6
+/-
16 08/15/07 5
+/-
12 08/22/07 3
+/-
10 08/29/07 12
+/-
19 09/05/07 10
+/-
33 09/12/07 7
+/-
15 09/19/07 0
+/-
12 09/26/07 2
+/-
17 10/03/07
-7
+/-
17 10/10/07
-7
+/-
12 10/17/07
-4
+/-
16 10/24/07 3
+/-
12 11/01/07
-4
+/-
16 11/07/07 1
+/-
16 11/15/07 0
+/-
12 11/21/07
-3
+/-
27 11/28/07 3
+/-
18 12/05/07 6
+/-
15 12/12/07 4
+/-
21 12/19/07 6
+/-
29 12/26/07 7
+/-
19 08/15/2007 Station 21 had low volume.
6
-6
-2
-3 18 2
-10 3
-10 0
-3 7
-7 0
0
-3
-7 1
-7
-5 6
-2
-11 0
12 24 2
2 0
-2 25 11 90
-2 4
-14 7
0 6
6 7
6
-7 4
5 12
-8
-7 0
-2 8
-11
+/-
17
-15
+/-
22 4
+/-
20
-2
+/-
22
+/-
20
-11
+/-
16 6
+/-
16 13
+/-
17
+/-
18 11
+/-
16 10
+/-
17 2
+/-
19
+/-
12
-3
+/-
17 11
+/-
15
-4
+/-
14
+/-
28
-16
+/-
24
-21
+/-
22
-13
+/-
20
+/-
15
-6
+/-
15 3
+/-
13 8
+/-
15
+/-
2300
-5
+/-
15 10
+/-
15 16
+/-
15
+/-
13 0
+/-
17 7
+/-
13
-5
+/-
15
+/-
22
-12
+/-
19 6
+/-
20 8
+/-
20
+/-
14
-7
+/-
16
-4
+/-
14 3
+/-
15
+/-
18
-7
+/-
16
-10
+/-
14 7
+/-
15
+/-
15 12
+/-
16
-1
+/-
12
-1
+/-
14
+/-
18 2
+/-
14
-6
+/-
17
-19
+/-
18
+/-
16 16
+/-
17 11
+/-
17 5
+/-
21
+/-
16
-1
+/-
13 3
+/-
13 1
+/-
13
+/-
14
-13
+/-
14
-1
+/-
14 16
+/-
16
+/-
15 6
+/-
14
-1
+/-
16 3
+/-
15
+/-
13
-3
+/-
17
-3
+/-
15 3
+/-
16
+/-
14
-10
+/-
16
-1
+/-
17
-11
+/-
16
+/-
17
-7
+/-
11 0
+/-
19 6
+/-
19
+/-
29 8
+/-
16
-17
+/-
25
-3
+/-
22
+/-
20
-2
+/-
18 2
+/-
20
-5
+/-
16
+/-
19
-5
+/-
19 3
+/-
18 5
+/-
17
+/-
23
-8
+/-
21 6
+/-
19 0
+/-
19
+/-
28 14
+/-
23
-8
+/-
27 17
+/-
27
+/-
22
-23
+/-
22
-9
+/-
23 4
+/-
27 08/22/2007 Stations 21 & 23 sampled on 08/23/07 09/26/2007 Stations 22 & 23 sampled on 09/27/07 44
I Table 3-5 Airborne Particulate Gamma Spectra and Strontium
[x 10-3 pCi/m 3]
Sampling Location 01 Quarter 1 1
Be-7 160
+/-
72-iK-40
-2.4
+/-
8.4 L2Cs-134 i
-0.25
+/-
0.62 Cs-137 0.39
+/-
0.69 I 01A*
02 03 04 05 05A 06 07 21 22 23 24
+/-
150
+/- 33 150
+/- 34 129
+/-
33 138
+-
32 135
+/-
34 112
+/-
29 136
+/-
33 140
+/-
32 132
+/-
33 156
+/-
35 140
+/-
36'
+/-
-8.9
+/-
9.4 1.7
+/-
8.9
-13.0
+/-
8.0
-8.2
+/-
8.7 0.2
+/-
7.6
-6
+/-
10
-1
+/-
8.9
-2
+/-
10
-9.3
+/-
6.7
-8.2
+/-
6.3
-12.9
+/-
8.9 0.18
-0.13
-0.55
-0.25
-0.06 0.04
-0.33
-0.47
-0.38 0.52 0.17
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-0.71 0.73 0.71 0.73 0.56 0.52 0.78 0.61 0.50 0.76 0.64 0.09
-0.29 0.29 0.37
-0.68 0.09 0.15 0.05 0.71 0.8 0.09
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-0.73 0.69 0.72 0.88 0.70 0.73 0.47 0.51 0.58 0.68 0.72 Sampling Location 01 Quarter 2 16 Be-7 163
+/-
38 XK-40 I
Cs-134 10
+/-
11
-0.23
+/-
0.77 01A*
+/-
02 174
+/-
39 03 210
+/-
42 04 196
+/-
40 05 165
+/-
40 05A 218
+/-
43 06 164
+/-
37 07 130
+/-
37 21 148
+/-
37 22 175
+/-
41 23 202
+/-
43 24 150
+/-
38
- Sampler installed October 2007 Sr-89/90 sampled in 2nd Qtr.
+/-
-6.4
+/-
-5.2
+/-
5
+/-
0
+/-
6
+/-
0.3
+/-
2
+/-
3
+/-
5.7
+/-
0.2
+/-
1.7
+/-
8.6 8.3 11 10 11 9.2 10 9.4 9.5 8.5 9.5 0.14
-0.44
-0.37 0.29
-0.01 0.61 0.41
-0.16 0.49
-0.24
-0.06
+/-
+/-
0.48
+/-
0.75
+/- 0.59
+/- 0.69
+/- 0.77
+/- 0.73
+/-
0.78
+/-
0.60
+/-
0.63
+/-
0.70
+/- 0.60 S
-0.08
+/-
0.62
+/-
-0.45
+/-
0.57 0.02
+/-
0.65
-0.71
+/-
0.81
-0.09
+/-
0.68
-0.14
+/-
0.45
-0.03
+/-
0.080
-0.28
+/- 0.68 0.02
+/- 0.65
-0.09
+/- 0.68 0.2
+/- 0.70 0.24
+/- 0.61 S
Sr-89
-20.3
+/-
8.8 x
+/-
y
-9.1
+/-
7.0
-18
+/-
10
-16.1
+/-
7.7
-15.2
+/-
8.7
-9.7
+/-
9.6
-24.5
+/-
9.5
-11.8
+/-
8.7
-21
+/-
10
-13
+/-
11
-15
+/-
13
-22.9
+/- 9.9 S
-0.3
+/-
1.8 x
+/-
y
-0.4
+/-
1.4
-1
+/-
2.2
-0.7
+/-
1.6
-0.1
+/-
1.7
-0.7
+/-
2.1
-1.9
+/-
1.8
-0.6
+/-
1.7
-0.4
+/-
2.0
-0.3
+/-
2.2
-1
+/-
2.6
-0.3
+/- 2.0 I
45
0 0
Table 3-5 Airborne Particulate and Strontium Gamma Spectra
[x 10-3 pCi/m 3]
Sampling L1ocation 01 01A*
02 03 04 05 05A 06 07 21 22 23 24 Quarter 3 I
Be-7 K-40 152
+/-
56 14
+/-
I 8
9134 15 0.28
+/-
0.96 0Cs-137 0.8
+/-
1.1 I 179 177 124 146 125 119 147 168 205 125 130
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-53 44 31 46 38 36 40 36 46 38 38
+1-/
2
+/-
2
+/-
-2.3
+/-
0
+/-
-3.3
+/-
-1
+/-
0
+/-
-2.5
+/-
0 44-2
+/-
10
+/-
15 11 7.6 11 7.2 5.6 12
,8 11 10 12 Sampling Lcation 1 Be-7 01 110
+/- 45 01A 111
+/- 49 02 117
+/- 46 03 167
+/- 48 04 109
+/- 46 05 151
+/- 48 05A 116
+/- 40 06 148
+/- 50 07 91
+/- 40 21 113
+/- 40 22 109
+/-
43 23 158
+/-
50 24 91
+/-
41
- Sampler installed October 2007 S
K-40 15
+/-
6
+/-
-5
+/-
-1
+/-
-5.0
+/-
-5
+/-
6.0
+/-
-8.3
+/-
-5
+/-
1
+/-
2
+/-
-6
+/-
-1
+/-
+1-/
0.28
+/-
0.96 0.25
+/-
0.83 0
+/-
0.53 0.19
+/-
0.82
-0.9
+/-
1.1 0.37
+/- 0.83
-0.34
+/-
0.72 0.29
+/-
0.71 0.001
+/- 0.067 0.16
+/-
0.69
-0.48
+/-
0.78 I
Cs-134
-0.45
+/-
0.92 0.63
+/-
0.88 0.07
+/-
0.88
-0.12
+/-
0.79 0.3
+/-
1.3 0.5
+/-
1.1 1.2
+/-
1.1 0.6
+/-
0.83
-0.12
+/-
0.79 0.43
+/- 0.90
-0.08
+/-
1.2
-0.63
+/- 0.99 0.76
+/-
0.76
+/-
-0.06
+/- 0.78 0.43
+/- 0.70
-0.22
+/- 0.64
-0.17
+/- 0.77
-0.15
+/- 0.30 0.31
+/-
0.76
-0.2
+/-
0.59 0.04
+/-
0.53 0
+/-
0.69 0.29
+/-
0.59 0.43
+/-
0.70 I
-0.23
+/- 0.74
-0.08
+/-
0.85
-0.1
+/-
0.93
-0.4
+/-
0.82
-0.08
+/-
0.80 0.5
+/-
1.0
-0.58
+/-
0.89
-0.25
+/-
0.88 0.7
+/-
1.0
-0.05
+/-
0.65
.0.43
+/-
0.71 0.91
+/-
0.75 0.43
+/-
0.70 IJ Quarter 4 16 13 13 11 11 13 11 4.6 11 10 15 6.7 13 46
Table 3-5.
Airborne Particulate and Strontium Gamma Spectra
[x 10-3 pCi/m 3]
Station Averages Sampling Location I
Be-7 I
K-40 I
Cs-134 I
Cs-137 01 146.3 +/- 42.8 O0A 111.0 +-12.3 02 155.0 +/-42.8 03 176.0 +/- 42.0 04 139.5 +/- 37.5 05 150.0 +/- 41.5 05A 148.5+/- 38.8 06 135.8 +/- 38.0 07 126.0 +/- 37.5 21' 154.0 +/- 34.3 22 155.3 +/- 40.8 23 160.3 +/- 41.5 Average 148.8 +/- 37.5 Control Location.
24 127.8 +/- 41.5 Sampling Location Be-7 K-40 Cs-134 Cs-137 21" 6700 +/- 2300 700 +/- 3400 200 +/- 180 120 +/- 180
- AP filter analysis of 08/15/07 sample due to high gross beta.
47
Table 3-6 Soil Gamma Spectra and Strontium
[pCi/kgl Station I
Sr-89 01
-50
+/-
270 02
-660
+/-
560 03
-200
+/-
200 04
-410
+/-
540 05*
-190
+/-
230 05A
-260
+/-
220 06
-470
+/-
350 07 30
+--
370 21
-270
+/-
380 22
-110
+/-
460 23 190
+/-
310 Average 24
-190
+1-350
-60 120
ý20 50 390 70 200 20 80 60 110 390 Sr-90
+/-
+/-
+/-
+/-
+/-
+1-
+/-
+/-
+1--
+/-
+/-
+/-
I Be-7 K-40 I
Cs-134 I
Cs-137 I
Th-228 130 150 120 140 150 120 140 140 130 120 110 132 200 60 180 180 850 20600 550 70
- 540 210
-110 10725
+/-
300 16000
+/-
1500
-7
+/-
29 43
+/-
36 440
+/-
140
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-210 310 300 280 1800 600 300 430 400 430 487 9110 5230 4670 14230 7900 11200 4860 23800 17100 20800
+/-
760
+/-
920
+/-
860
+/-
890
+/-
1700
+/-
.1600
+/-
810
+/-
1900
+/-
1500
+/-
1700
-43
-29
-17 1
-33 20 0
6
-21 58
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-
+1-86 29 27 73 74 46 29 42 41 48 300
+/-
45 551
+/-
99 325
+/-
68 620
+/-
150 186
+/-
63 690
+/-
150 15
+/-
22 585
+/-
82 17
+/-
75 720
+/-
320 75
+/-
62 1420
+/-
250 80
+/-
56 1330
+/-
150
-55
+/-
45 1080
+/-
210 25
+/-
54 2170
+/-
200 75
+/-
72 2010
+/-
210
.270
+/-
54 1056
+/-
178 3
+-
52 1110
+/-
210 12264
+/-
1285 Control Location
-10
+1-120
-310 1-400 5900
+/-
1100
-8 1-36 05* Re-analysis of Sample performed 10/14/07 Sr-89: -240+/-290 Sr-90: 410+/-160 48
Table 3-7 Precipitation Gamma Spectra
[pCi/L]
06/28/2007 Sampling Location Be-7 I
K-40 I
Cr-51 I
Mn-54 I
Fe-59 I
Co-58 I
Co-60 I
01A 14
+/-
10 7
+/-
12 1
+/-
15 0.45
+/-
0.65 Ru-103 0.5
+/-
2.5 0.26
+/-
0.88
-0.31 +/-
0.68 Zn-65 Zr-95 Nb-95
- Ru-106 Sb-125 0
+/-
6.5 0.7
+/-
1.8 2
1-131
-4
+/-
20 IJ 01A
-0.2
+/-
1.5
-0.3
+/-
1.6 0.7
+/-.
1.6
-0.5
+/-
1.2 0.Cs-134 0.1
+-
06 02 Cs-137 0.27
+/-
0.66 0
Ba-140 o.9 7/- 5.6 La-140 Th-228 1
+/-
6.4 3.2
+/-
2.3 I
01A 12/26/2007 Sampling Location Be-7 I
K-40 I
Cr-51 I
Mn-54 I
Fe-59 I
Co-58 I
Co-60 I
01A 24
+/-
13 5
+/-
44 3
+/-
21.0
-0.9
+/-
2.3 1.1
+/-
5.4
-0.2
+/-
2.3 2.2
+/-
2.8 Zn-65 Zr-95
-5
+/-
5.0 2.4
+/-
4.8
' Nb-95
-1.3 7/--2.9 Ru-103 Ru-106 Sb-125 0
+/-
2.5 5
+/-
20
-1.7
+/-
5.5 0
1-131 0.8
+/-
5.4 I
01A I
Cs-134 I
Cs-137 I
Ba-140 I
La-140 I
Th-228 I
01A
-0.6
+/-
2.4 1.5
+/-
2.1 4
+/-
7.0 4
+/-
7.0 6.2
+/-
8.0 49
Table 3-7 Precipitation Gross Beta
[pCi/LI Sampling Date 01/31/07 03/01/07 03/28/07 04/25/07 05/30/07 06/28/07 07/26/07 08/29/07 09/27/07 11/01/07 11/28/07 12/26/07 Gross Beta 7
+/-
8.3
+/-
0
+/-
2.7
+/-
22.5
+/-
19.5
+/-
11
+/-
12
+/-
9.9
+/-
1.4
+/-
10.5
+/-
9
+/-
I 2.3 2.4 1.5 1.9 3.5 3.3 2.7 2.6 2.6 1.7 2.6 2.6 Rainfall (inches) 3.37 1.65 3.56 2.86 2.10 2.03 1.55 2.72 1.07 5.12 0.91 1.52 Total 28.46 Average 12.2
+/-
2.7 50
Table 3-8 Milk Gamma Spectra and Strontium
[pCi/L]
Date I
K-40 I
Sr-89 I
Sr-90 I
01/17/07 02/21/07 03/21/07 04/18/07 05/23/07 06/20/07 07/18/07 08/22/07 09/19/07 10/24/07 11/21/07 12/19/07 1490 1440 1380 1330 1395 1440 1400 1600 1580 1280 1230 1420 130 150 160 130 83 110 130 240 200 170 110 130
-0.113 0.18 0.7
+/- 4.4 0.9
+/-
1.1 0.14
-0.207
-0.14 0.1
+/- 4.4 0
+/- 0.95 0.11 0.31
-0.073
-0.4 +/- 2.9 0.86
+/- 0.62
-0.178 0.16 0.08 0.7
+/- 2.8
-0.57
+/- 0.98 0.09 1-131 0.039 0.30 0.31 0.068 0.046 0.32 0.45 0.025 0.048 0.39 0.38 0.34 I
Cs-134 4.2
+/-
3.7
-3.1
+/-
3.8 1.2
+/-
5.0 1.5
+/-
3.3 1.3
+/-
2.5 3.5
+/-
3.4 3.9
+/-
3.5 1.6
+/-
5.7
-3.1
+/-
6.2
-2.4
+/-
5.2 2.4
+/-
3.1 0.2
+/-
3.2 I
Cs-137 1.1
+/-
-3
+/-
0.3
+/-
0.6
+/-
0.5
+/-
1.3
+/-
0.5
+/-
-1
+/-
0.2
+/-
1
+/-
2.6
+/-
1.8
+/-
3.2 3.9 4.8 4.0 2.2 2.8 3.4 6.4 4.7 4.7 2.7 3.4 I
Ba-140
-0.4
+/-
6.0 1.6
+/-
6.1 6.6- +/-
7.7
-2.4
+/-
4.7
-1.7
+/-
4.1 0.4
+/-
6.0 0.5
+/-
6.5 4.3
+/-
6.9 0.9
+/-
6.4
-4.7
+/-
6.3
-2.3
+/-
7.8 0.5
+/-
6.5 Station 12 S
La-140
-0.5
+/
6.9 1.8
+
7.0 7.5
+
8.8
-2.8
÷ 5.4
-2
+-
4.7 0.5
+
6.9 0.6
+
7.5 4.9
+-
7.9 1
+-
7.3
-4.7
+-
6.3
-2.3
+-
7.8 0.5
+-
6.5 I
Average 1415
+/-
145 Date I
K-40 I
Sr-89 I
Sr-90 I
1-131 I
Cs-134 I
Cs-137 I
Ba-140 I
Station 13 La-140 01/17/07 02/21/07 03/21/07 04/18/07 05/23/07 06/20/07 07/18/07 08/22/07 09/19/07 10/24/07 11/21/07 12/19/07 1380 1460 1380 1240 1257 1410 1430 1210 1460 1420 1310 1274 110 160 120 130 79 110 160 130 160 180 120 86 0.02 0.11 1.3
+/- 4.4 1.2
+/-
1.1 0.28 0.13
-0.07
-0.6
+/-
4.4 0.63
+/-
0.98
-0.07 0.01
-0.073
-2.6 +/-
4.6
-0.3
+/-
1.0
-0.115 0.16
-0.02
-0.2 +/-
3.1 0.52
+/-
0.90 0.34 0.27 0.31 0.42 0.42 0.23 0.27 0.29 0.025 0.039 0.38 0.20 0.52
-0.6
+/-
3.1
-0.4
+/-
4.3
-1.4
+/-
3.4 3.1
+/-
3.7 0
+/-
2.3 0.5
+/-
3.2
-1.5
+/-
4.2 1.5
+/-
3.6
-0.3
+/-
4.6
-1.5
+/-
5.5 2.1
+/-
3.5
-0.3
+/-
2.4 1.1 0.2 0.6
-0.2
-0.5 0.9
-1.2 0.8 2.3
-0.9
-0.4
-0.6 3.1 3.9 3.3 3.9 2.1 3.0 4.0 3.5 4.0 4.2 3.7 1.9 2.8
+/-
4.2 0.6
+/-
6.7 0
+/-
6.3 1
+/-
5.8 3.1
+/-
3.9 3.7
+/-
6.2 4.5
+/-
6.7
-2.3
+/-
6.6
-2.3
+/-
6.3
-3.5+/- 5.0 4.7
+/-
7.8
-4.7
+/-
6.8 3.2
-0.7 0
1.1 3.6 4.3 5.2
-2.7
-2.6
-3.5 4.7
-4.7
+/-
4.8
+/-
7.7
+/-
7.3
+/-
6.7
+/-
4.4
+/-
7.1
+/-
7.7
+/-
7.6
+/-
7.2
+/-
5.0
+/-
7.8
+/-
6.8 Average 1353
+/-
129 Overall Avg.
1384
+/-
137 51
0 Table 3-9 Food and Vegetation Gamma Spectra
[pCi/kg]
0 Sampling ISampling Location Date Be-7 I
K-40 I
1-131 I
Cs-134 I
Cs-137 I
Th-228 I
14 15 23 26 14 15 23 26 14 15 23 26 14 15 23 26 14 15.
23 26 14 15 23 26 05/10/07 8350 1510 4290 5250 06/13/07 2020 1060 2410 1330 07/11/07 2570 3920 3170 4080 08/08/07 2360 3640 2390 2150 09/12/07 1560 1810 2220 2130 10/10/07 1580 1380 750 1240 510 340 510 510 560 410 570 400 420 390 490 650 410 560 460 360 430 430 350 350 370 400 660 330 5530
+/-
10990
+/-
8850
+/-
10240
+/-
16500
+/-
11080
+/-
8950
+/-
1070
+/-
17600
+/-
11210
+/-
8500
+/-
11000
+/-
7900
+/-
7990
+/-
9550
+/-
7500
+/-
5150
+/-
6010
+/-
5040
+/-
4150
+/-
5000
+/-
4780
+/-
3320
+/-
2210
+/-
640 770 770 770 1100 930 990 940 1100 720 890 1100 870 980 830 630 680 650 500 510 640 730 710 580 3
+/-
24
-1
+/-
26
-13
+/-
20 3
+/-
20 12
+/-
25 16
+/-
26 32
+/-
34 11
+/-
23
-4.8
+/-
2.1 15
+/-
28
-10
+/-
13 2
+/-
15 14
+/-
24 0
+/-
18 4
+/-
24 9
+/-
27
-4
+/-
27
-21
+/-
20
-31
+/-
22
-3
+/-
26
-17.9
+/-
5.8
-2
+/-
23 8
+/-
20
-7
+/-
18 22
+/-
28 37
+/-
26 29
+/-
32
-1
+/-
33 31
+/-
36 24
+/-
32 37
+/-
35 27
+/-
32 11
+/-
32 14
+-
.26
-10
+/-
33 47
+/-
38 16
+/-
34 33
+/-
34 31'+/-
34 20
+/-
25 26
+/-
29 13
+/-
26
-1
+/-
22 25
+/-
27 2
+/-
21 14
+/-
29 52
+/-
36
-14
+/-
32 17
+/-
24
-5
+/-
26
-8
+/-
27 35
+/-
31 42
+/-
41
-2
+/-
26 37
+/-
34 4
+/-
26 18
+/-
28 5
.+/-
24 26
+/-
28
-2
+/-
35 17
+/-
29
-33
+/-
38
-15
+/-
28 26
+/-
25
-32 +/-
28
-11
+/-
25
-1
+/-
20
-14
+/-
27
-14
+/-
25
-5
+/-
32
-2
+/-
35
-17
+/-
25 310
+/-
110 150
+/-
150 210
+/-
130 150
+/-
140 20
+/-
150 90
+/-
150 70
+/-
180 310
+/-
110 120
+/-
160 140
+/-
110 220
+/-
120 60
+/-
160 80
+/-
170 140
+/-
190 290
+/-
130 110
+/-
120 400
+/-
120 160
+/-
120 61
+/-
97 564
+/-
86 100
+/-
110 180
+/-
150 770
+/-
130
-30
+/-
100 338
+/
133 Average 2599
+/-
450 8128
+/-
794 52
0 Table 3-9 Food and Vegetation Gamma Spectra
[pCi/kg]
Indicator Location Averages I Sample Location I
Be-7 I
K-40 I
1-131 I
Cs-1 34 I
Cs-137 I
Th-228 I
14 15 23 26 3073
+/-
450 2220
+/-
422 2896
+/-
508 2697
+/-
433 9613
+/-
838 8678
+/-
797 7368
+/-
782 7020
+/-
755
+/-
+/-
+/-
+/-
+1--
+/-
+/-
+/-
+/-
+/-
+/-
+/-
355.0
+/-
137
+/-
372.5
+/-
131 250.0
+/-
119 Control Location I
Be-7 I
K-40 I
1-131 I
Cs-134 I
Cs-137 I
Th-228 I
16 05/10/07 5720
+/-
550 4540
+/-
670
-19
+/-
15
-11
+/-
33 6
+/-
34 140
+/-
140 06/13/07 3030
+/-
50 11230
+/-
940 8
+/-
26 25
+/-
35
-28
+/o 30 90
+/-
190 07/11/07 7330
+/-
460 5420
+/-
560 12
+/-
25 32
+/-
26 16
+/-
25 120
+/-
130 08/08/07 1650
+/-
350 9080
+/-
710
-13
+/-
20 13
+/-
28
-16
+/-
24 278
+/-
91 09/12/07 1650
+/-
420 23600
+/-
1100 2
+/-
28
-3
+/-
33 25
+/-
29 160
+/-
150 10/10/07 1820
+/-
500 6020
+/-
910 2
+/-
25 29
+/-
33
-9
+/-
29 180
+/-
160 Average 3533
+/-
388.3 9982
+/-
815 278
+/-
143.5 53
0 0
Table 3-10 Well Water Gamma Spectra, Strontium, and Tritium
[pCi/L]
Sampling Date Station 01A Th-228 H-3 I
Be-7 I
K-40 I
Sr-89 I
Sr-90 I
1-131 1
Ba-140 I
I 03/28/07 06/28/07 09/27/07 12/26/07
-20
+/-
870 570
+/-
830
-640
+/-
880 280
+/-
900
-23
+/- 26
-0.7
+/-
7.4
-8
+/-
19 17
+/-
16 7
+/-
44 6
+/-
13
-18
+/-
29 48
+/-
32
[a]
[a]
1.2 +/-
5.8 2.3
+/-
4.2
-2.4 +/- 4.4 0.51
+/- 0.91 3.2 +/- 4.3 1
+/-
2.3
[a]
[a]
-1.7 +/-
5.1 2.4
+/-
4.8
[a]
[a]
0.7 +/- 5.4
-1.1
+/-
5.4 0
+/-
11
-1.2
+/-
3.8
-2.5
+/-
6.1 6
+/-
13
[a] Sr-89/90 analyses performed on the second quarter sample.
54
0 Table 3-11 River Water Gamma Spectra, Strontium, and Tritium
[pCi/L]
Sampling Date H-3 I
Be-7 I
1-131 I
Cs-1 37 1
Station 11 Ba-140 Th-228 01/11/07 02/15/07 03/13/07 04/12/07 05/14/07 06/14/07 07/13/07 08/13/07 09/13/07 10/15/07 11/15/07 12/19/07
[b]
[b]
4400
+/-
[b]
[b]
3740
+/-
[b]
[b]
2900
+/-
[b]
[b]
3510
+/-
1200 960 1000 990 1
+/-
9
+/-
38
+/-
-1
+/-
0
+/-
1
+/-
-5.1
+/-
-15
+/-
-1
+/-
-4
+/-
1 +/-
1 +/-
14 16 25 14 8.7 11 7.6 23 18 20 16 26 14
+/-
22
-5
+/-
35
-6
+/-
47
-3
+/-
23 6
+/-
13 3
+/-
14 5
+/-
12 28
+/-
43
-7
+/-
25 0
+/-
37 2
+/-
29 80
+/-
40
[a]
[a]
[a]
[a]
[a]
-0.6 +/- 4.4
[a]
[a]
[a]
[a]
[a]
[a]
[a]
-0.181
+/-
[a]
-0.53
+/-
[a]
0.14
+/-
[a]
-0.05
+/-
[a]
0.12
+/-
0.45 +/- 0.88
-0.09
+/-
[a]
0.33
+/-
[a]
-0.08
+/-
[a]
0.15
+/-
[a]
-0.076
+/-
[a]
-0.1
+/-
[a]
0.07
+/-
0.062 0.52 0.33 0.25 0.43 0.21 0.51 0.027 0.45 0.022 0.25 0.34 0.2
+/-
2
+/-
0.8
+/-
0.7
+/-
-0.74
+/-
0.4
+/-
0.57
+/-
-1.7
+/-
0.3
+/-
-1.3
+/-
-1.1
+/-
-0.8
+/-
1.5 2.0 2.8 1.5 0.88 1.0 0.74 2.9 1.6 2.1 2.4 2.8 1.1
+/-
3.4
-1.7
+/-
4.7
-0.9
+/-
4.5 0.3
+/-
4.4 1.1
+/-
2.7 0.7
+/-
3.1 1
+/-
2.1
-4.2
+/-
4.2
-2.4
+/-
3.9 2.7
+/-
4.4 1.9
+/-
4.7 3.8
+/-
6.5
-2.7 6.3
-4
-1.9 2.4 2.8 3.3
-6 2.3
-3.5 5.4 7
6.2
+/" 6.9
+/"
11.0
+/-
6.8
+/-
3.2
+/" 3.5
+/-
2.4
+/-
10.0
+/" 6.4
+/" 9.7
+/-
9.1
+/" 11.0 Average 3638
+/-
1038 38
+/-
25
[a] Sr-89/90 analyses performed on the second quarter sample.
[b] Tritium analyses on quarterly composite.
55
0 Table 3-12 Surface Water Gamma Spectra, Strontium, Tritium 4
[pCi/L]
H-3 I Sr-89 I
Sr-90 I
Be-7 I
I 1-131 I
Cs-137 1
Ba-140 I
01/11/07 02/15/07 03/13/07 04/12/07 05/14/07 06/14/07 07/13/07 08/13/07 09/13/07 10/15/07 11/15/07 12/19/07
[b]
[b]
4500
+/-
[b]
[b]
3440
+/-
[b]
[b]
3300
+/-
[b]
[b]
4000
+/-
1200 960 1000 1000
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
-1.4 +/- 4.8 0.4 +/-
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
1.0 3
3
-4 0
21
-21 2
19 12
-2
-1 9
19 27 26 20 18 22 24 35 23 21 20 26 29
-4
-5 5
5
-9 24 31 20 12 16
-32 33 43 48 26 28 33 43 57 41 50 39 58
-0.176
+/- 0.060 0.25
+/- 0.46 0.14
+/- 0.33 0.14
+/- 0.46 0.42
+/- 0.55 0
+/- 0.28 0.08
+/- 0.27
-0.083
+/- 0.028 0.24
+/- 0.49
-0.072
+/- 0.021 0.14
+/- 0.43
-0.115
+/- 0.046 0.1
+/- 2.0 1.5
+/- 2.9
-1.3
+/- 3.1
-0.4 +/-
1.6 0.2
+/-
1.6
-0.7 +/- 2.1 2.6
+/- 2,3
-0.5 +/- 3.9 1.2
+/- 2.9 0.7
+/- 2.4
-0.1
+/- 2.0 2
+/- 2.8
-1 +/- 4.6 1.3
+/- 5.8
-4.1
+/- 5.9
-2.3 +/- 4.7 3.6
+/- 5.2 0.7
+/- 5.4 2.9
+/- 6.3
-4.3 +/- 5.4 9.1
+/- 6.4 0.9
+/- 5.3 0
+/- 4.4
-5.5
+/- 6.9 2
-6
-5
-1.7
-1.2
-2.4 3
6
-4 12.8
-1.6
-4 10 12 12 7.0 6.7 7.9 9.0 15 9.6 9.9 9.3 14 Average 3810
+/-
1040 Station 09A Th-228 Date I
H-3 I
Sr-89 I
Sr-90 I
Be-7 I
K-40 I
1-131 I
Cs-137 I
Ba-140 I
01/11/07 02/15/07 03/13/07 04/12/07 05/14/07 06/14/07 07/13/07 08/13/07 09/13/07 10/15/07 11/15/07 12/19/07
[b]
[b]
-570
+/-
[b]
[b]
600
+/-
[b]
[b]
-340
+/-
[b]
[b]
620
+/-
940 850 890 880
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
-8.1 +/- 4.1 0.41
+/- 0.81
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
[a]
11 4
-36
-5
-8 9
-5
-14 4
1 3
-12
+/-
18
+/-
26
+/-
32
+/-
24
+/-
17
+/-
20
+/-
17
+/-
30
+/-
19
+/-
22
+/-
24
+/-
22 4
14
-3
-12
-13 0
-38 6
-4 12
-1 3
+/-
31
+/-
39
+/-
59
+/-
41
+/-
21
+/-
28
+/-
24
+/-
68
+/-
22
+/-
48
+/-
41
+/-
44
-0.176
+/- 0.060
-0.02 +/- 0.27
-0.089
+/- 0.032
-0.11
+/- 0.27 0.22
+/- 0.50 0.1
+/- 0.38 0.33
+/- 0.45
-0.01
+/- 0.22
-0.21
+/- 0.22 0.07
+/- 0.30 0.03
+/- 0.38
-0.03 +/- 0.27 0.7
+/- 2.1 0.9
+/- 2.5
-0.4
+/- 5.0 1.6
+/- 2.6
-0.3
+/- 1.8 1.7
+/- 1.8 0.2
+/- 2.0
-1.8
+/- 3.9 0.6
+/- 1.9 0.5
+/- 2.8
-0.6
+/- 2.8 0.7
+/- 2.6 2
+/- 4.2 1.6
+/- 4.6 0.8
+/- 6.5 4.6
+/- 6.6
-1.2
+/- 4.7 4.1
+/- 5.8
-1.6
+/- 6.0 0.1
+/- 5.1 1.4
+/- 4.0 0.9
+/- 4.5
-7.5
+/- 6.0 4.3
+/- 5.3 6.6 4
0
-2
-0.6
-1 2.9
-5 2.9
-5 12 1
7.6 14 17 12 6.6 8.1 8.5 15 7.0 12 11 11
[a] Sr-89/90 analyses performed on the second quarter sample.
[b] Tritium analyses on quarterly composite.
56
0 0
Table 3-13 Sediment Silt Gamma Spectra and Strontium
[pCi/Kg]
Datei 03/13/2007 10/15/2007 Station 09A*
Sr-89 I
Sr-90 I
Be-7 I
K-40 I
[a]
-230
+/-
200
[a]
40
+/-
130 120
+/-
410 10
+/-
270 Average Station 08 Station 11 Average
[a]
-80
+/-
230
[a]
-110
+/-
230
[a]
-30
+/-
170
[a]
-30
+/-
150 210
+/-
370 320
+/-
410
-90
+/-
440
-150
+/-
380 9800
+/-
1800 11700
+/-
1000 10750
+/-
1400 6300
+/-
1300 15700
+/-
1800 13500
+/-
2300 15100
+/-
1400 12650
+/-
1700
-6
+/-
51 27
+/-
31 47
+/-
48 55
+/-
56 69
+/-
60
-11
+/-
40 7
Date 03/13/2007 10/15/2007 Co-58 I
Co-60 I
Cs-1 34 I
Cs-137 I
Th-228 Station 09A*
-25
+/-
37
-26
+/-
29
-12
+/- 46
-10
+/- 26 0
+/-
81 29
+/-
37 Average Station 08 Station 11 17
+/-
48 86
+/-
42 86
+/-
42 7
+/-
55 26
+/-
55 19
+/-
66
-12
+/-
45 0
+/-
40
-7
+/-
53
-14
+/-
51
-51
+/- 42 0
+/- 44
-56
+/- 48 5
+/- 61 27
+/- 38 20
+/-
44 32
+/-
53 21
+/-
58 39
+/-
45 580
+-
230 680
+/-
130 630
+/-
180 930
+/-
250 1890
+/-
260 1140
+/-
330 1020
+/-
180 1245
+/-
255 Average
- Control Location
[a] Sr-89/90 analyses performed annually.
57
0 Table 3-14 Shoreline Soil Gamma Spectra and Strontium
[pCi/Kg]
Sample Date Sr-89 I
Sr-90 I
Be-7 I
K-40 I
Mn-54 03/13/2007 10/15/2007 Station 08
[a]
[a]
70
+/-
190 2310
+/-
510 5
+/-
24
-60
+/-
280
-10
+/-
150 90
+/- 200 2250
+/-
500 2
+/-
23 Average 2280
+/-
505 Sample Date j
Co-58 Co-60 Cs-134 Cs-137 Th-228 03/13/2007 10/15/2007 Station 08
-29
+/-
22 10
+/-
24 4
+/-
21 32
+/-
23
-9
+/-
22 0
+/-
21 134
+/-
40
-4
+/-
23 134
+/-
40 440
+/-
100 440
+/-
100 440
+/-
100 Average
[a] Sr-89/90 analyses performed annually.
58
0 0
Table 3-15 Fish Gamma Spectra
[pCi/Kg]
Sampling Date Fish [a]
Mn-54 I
Fe-59 I
Co-58 I
Co-60 I
Zn-65 I
Cs-134 03/13/07 1570
+/-
510 5
+/-
19 31
+/- 57
-7
+/-
23 15
+/- 23
-17
+/-
46 10
+/-
24 1
+/- 23 10/16/07 1820
+/-
570
-12
+/-
24
-14
+/- 57
-5
+/- 18 11
+/- 17
-13
+/-
45 22
+/-
18 23
+/- 23 Average 1695
+/-
540 Fish [a]
Sampling Station 25 Date K Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 03/14/07 1150
+/- 390
-13
+/-
21 14
+/-
37 5
+/-
20 3
+/-
16
-17
+/- 41 0
+/- 22
-4
+/-
15 10/17/07 1610
+/-
610 4
+/-
25
-59
+/-
75 3
+/-
22 11
+/-
22 0
+/- 55 2
+/- 28
-3
+/- 22 Average 1380
+/-
500 Catfish [b]
Sampling Station 08 Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-i 37 03/14/07 1120
+/-
440
-7
+/-
18
-5
+/- 42 15
+/-
18 1
+/- 19 0
+/-
43 4
+/-
18 2
+/-
19 10/17/07 1210
+/-
640 15
+/-
30 15
+/- 66
-21
+/- 27
-31
+/- 25
-8
+/-
73
-29
+/-
22 31
+/-
31 Average 1165
+/-
540 Catfish [b]
Sampling Station 25 Date K-40 Mn-54 Fe-59 Co-58 Co-6o Zn-65 Cs-134 Cs-137 03/14/07 10/19/07 1080
+/-
470 1610
+/-
650
-6 4/-
19 6
+/-
24 41
+/-
48 17
+/-
53 14
+/-
20 8
+/-
29 7
+/-
24 2
+/-
29
-15
+/-
45
-24
+/-
62
-19
+/-
20
-20
+/-
21
-12
+/-
21 0
+/-
23 Average 1345
+/-
560
- [a] Non-bottom dwelling species of gamefish.
[b] Bottom dwelling species of fish.
59
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2007 and tabulated in Section 3, are discussed below. Except for TLDs, AREVA Environmental Laboratory analyzed all samples throughout the year. The procedures and specifications followed for these analyses are as required in the AREVA Environmental Laboratory 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 2007 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, and Th-228 were detected in numerous samples. Th-228 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 2007 reporting period.
4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. TLDs are placed in two concentric rings around the station.
The inner ring is located at the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population areas and nearby residences. Additional TLDs serve as controls. Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.
The results of the analyses are presented in Table 3-2.
Figure 4-1 shows the historical trend of TLD exposure rate measurements.
Control and indicator averages indicate a steady relationship.
Two dosimeters made of CaF and LiF sensitive elements are deployed at each sampling location. These TLDs replaced the previously used CaSO4:Dy in Teflon TLDs in January 2001. The dose with the replacement TLDs is lower than that of the previously used TLDs.
This will continue to be monitored.
60
Figure 4-1: Environmental Radiation - TLDs 10.0 I
z 1.0 0
W W
W 0
- irl I
.l r-c1 0 i i
i cI i
00 0
00 0
0 00 0
0 0
0 0
I - Environmental TLDs
- Sector TLDs -
-- Ave. Pre-op.
W 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 5.2 mR/standard month with a range of 1.3 to 47.3 mR/standard month. The highest quarterly average reading for any single location was obtained at location SSW-19/51. These values were 31.9 mR/standard month. This location is on site directly across the access road from the Independent Spent Fuel Storage Facility. The higher values can thus be attributed to the spent fuel stored in the ISFSI. Quarterly and annual TLDs are also located at each of the twelve environmental air sampling stations. For the eleven locations within 10 miles of the station the average quarterly reading was 3.4 mR/standard month with a range of 1.3 to 5.8 mR/standard month. The average annual reading for these locations was 3.4 mR/standard month with a range of from 1.8 to 5.2 mR/standard month. The control location showed a quarterly average of 3.4 mR/standard month with a range of 3.0 to 3.8 mR/standard month. Its annual reading was 3.3 mR/standard month. Eight other TLDs, designated C-I thru C-8, were collected quarterly from four locations and showed an average reading of 3.1 mR/standard month with a range of 2.0 to 4.1 mR/standard month. During the pre-operational period (starting in 1977) the doses were measured between 4.3 and 8.8 mR/standard month.
0 61
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. 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.
One anomalous result was observed on 08/15/07 sample at Station 21. A value of 1.72 pCi/mn3 was obtained.
The sample was analyzed for gamma emitters.
Only Be-7, a naturally occurring isotope, was identified as being present at a level of 6.7 pCi/m 3. During this collection period this sampler had also malfunctioned, and the volume was estimated at 3 m 3, which could have lead to the apparently high results. A review of the releases that occurred during this time period did not indicate any releases which could have contributed to these results.
Figure 4-2: Gross Beta in Air Particulates 1
0.1-------------------------------------------
- 0. 0
.1 0.00 1 1986 1993 1999 2006
~---,*
Control Sta-24 ----
Indicator
- Average Pre-op
-Required LLD 62
0 Figure 4-3
-"=
Indicator NORTH ANNA AIR PARTICULATE A - ControlI 2006 Gross Beta Radioactivity pCI/m 3
0.050 0.040 0.030Il x
A A
V 0.020 XA 0.010 0.000 1/3 2/3 3/3 4/3 5/3 6/3 7/3 8/3 9/3 10/3 11/3 12/3 4.3 Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine.
Once a week the samples are collected and analyzed. The results of the analyses are presented in Table 3-4.
All results are below the lower limit of detection with no positive activity detected. 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.
4.4 Air Particulate Gamma The air particulate filters that are utilized for the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectrometry.
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. No other positive results were seen. As discussed in section 4.2 above one weekly sample was analyzed for gamma emitters and only Be-7 was detected.
These analyses indicate the lack of station effects.
4.5 Air Particulate Strontium Strontium-89 and 90 analyses were performed on the second quarter composites of air particulate filters from all twelve monitoring stations. The results are listed in Table 3-5.
There was no detection of these fission products at any of the indicator or control stations.
63
4.6 Soil Soil samples, which are collected every three years from twelve stations, were collected in 2007 and the results displayed on Table 3-6. The soil indicated positive results for naturally occurring Be-7, K-40, and Th-228. Low levels of Cs-137 ranging from 186 - 325 pCi/kg were detected on 3 of 11 samples from indicator locations. Cs-137 is typically seen in some of these samples.
The number of locations at which Cs-137 has been seen and the levels at which it has been detected has decreased steadily over the life of the plant.
This is an indication that the Cs-137 being detected is due to fallout from atmospheric weapons testing and not attributable to plant activities. Sr-90 was detected in one location at a level of 390 pCi/kg. The sample was re-analyzed and the value was confirmed at a level of 410 pCi/kg. Sr-90 has been detected at comparable levels in some previous years' samples.
No analyses of gaseous effluents showed a positive indication for Sr-90, and the likely origin is fallout from past atmospheric weapons testing.
4.7 Precipitation A sample of rain water was collected monthly at on-site station 01A and analyzed for gross beta activity. The results are presented in Table 3-7.
12 precipitation samples were obtained in 2007. Nine of the twelve precipitation samples showed positive results in 2007. The average annual gross beta activity was 12.2 pCi/liter with a range from 7 to 22.5 pCi/liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes.
No positive indications of plant related gamma emitting radioisotopes were observed in the semi-annual composite samples for 2007. Naturally occurring Be-7 was detected at a level of 24 pCi/L in one sample. 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 can not be made to the 2007 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, in combination with the fact that consumption of milk is significant, results in this pathway usually being a critical pathway from the plant release viewpoint.
This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media 64
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.
All results show no detectable 1-131 above the LLD of 1 pCi/1. Results of gamma ray spectroscopy indicate no detectable plant related radioactivity in the milk samples. Naturally occurring K-40 was detected in all samples.
In years past, Cs-137 has been detected sporadically. The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2007.
Once each quarter a sample from each of the two collection stations 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 spectrometry. The results of the analyses are presented in Table 3-9. No plant related isotopes were detected in any samples.
As expected, naturally occurring potassium-40 was detected in all samples, cosmogenic beryllium-7 was detected in most samples, and thorium-228 was detected in some samples.
4.10 Well Water Water was sampled quarterly from the on site well at the metrology laboratory.,
These samples were analyzed for gamma radiation and for tritium. The second quarter sample was analyzed for strontium-89 and strontium-90. The results of these analyses are presented in Table 3-10. Consistent with past monitoring, no plant related radioactivity was detected. No gamma emitting isotopes were detected during the pre-operational period.
65
4.11 River Water A sample of water from the North Anna River was 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, the second quarter samples were additionally analyzed for strontium-89 and strontium-90. No gamma emitting radioisotopes were detected 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 3638 pCi/liter and a range of 2900 to 4400 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.
Figure 4-4: Tritium in River Water 10000 e
C 1000 M
t-00 Oý0tr O
r-00 M'
r 00 0
00 0
O.
O ON, 0.
CN O\\
- 0.
CN 07 0
0ý ON O\\
ON ON. 0, ON' ON 0ý C% ON R'
- 0.
0 0
0 0
0 0
=---
N N
C14 N' Ns N4 N4
- Tritium Required LLDI 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 ray spectrometry and for iodine-131 by radiochemical separation. A quarterly composite from each station was prepared and analyzed for tritium, and the second quarter samples were additionally analyzed for strontium-89 and strontium-90.
The results are 66
presented in Table 3-12.
Neither gamma emitting radioisotopes nor 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 3810 pCi/liter with a range of 3300 to 4500 pCi/liter.
Levels of tritium have been increasing 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.
Figure 4-5: Tritium in Surface Water 10000 0
z10 0oo 100 W~ 00 W~ WU Ch aU C%
CU I-.~~~~~
.~
~4,4,4,-
,I,-
~1 Tritium - - U Required LLD -
Average Pre-op 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 spectrometry. The October samples were analyzed for strontium-89 and strontium-90. The results are presented in Table 3-
- 13. Figure 4-6 shows the historical trend of Cs-137 in sediments.
67
Figure 4-6: Cesium-137 in Sediment Silt 10000
~~
100 10 In O,
O(O 0
0 Z0,
_0 2~
c~
00000000ZZ C'
00000 0C00 Station-8
Station-9
-A -Control-Sta-09A
-X-Station-l
- Average Pre-Op - Required LLD's No Cesium-137 was detected in the indicator locations. In 2007, one sediment sample from the control location showed Cs-137 level of 86 pCi/kg. The detection of Cs-137 in bottom sediment is historically common with positive indications usually apparent in both indicator and control samples. The detection of Cs-137 is the result of accumulation and runoff into the lake of residual weapons testing fallout; its global presence has been well documented. During the pre-operational period sediment samples were analyzed by gamma ray spectroscopy.
There was no measurable amount of strontium-89 or 90 in aquatic sediment/silt.
A number of naturally occurring radioisotopes were detected in these samples at background levels.
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 March and October from indicator station 08. The samples were analyzed by gamma ray spectrometry. The October sample was analyzed for strontium-89 and strontium-90.
The results are presented in Table 3-14.
68
Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities.
The activities of these radioisotopes indicate a steady trend. Cesium-137 was detected in 2007 in one sample at a level of 134 pCi/kg, but has also been detected intermittently in the past at comparable levels.
No Strontium was detected. Strontium-90 is often detected in this media, however as discussed previously, the presence of Sr-90 and Cs-137 is attributed to accumulation of residual global fallout from past atmospheric weapons testing.
4.15 Fish Four sample sets of fish, two from Lake Anna and two from the control station, Lake Orange, were collected during 2007 arid 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. Except for naturally occurring K-40, no other nuclide was observed in this media in 2007. Only Cs-137 was measured in pre-operational environmental fish samples.
69
- 5. PROGRAM EXCEPTIONS REMP Exceptions for Scheduled Sampling and Analysis During 2007 - North Anna Location Description Date of Sampling Reason(s) for Loss/Exception Sta. 14-16, 23, 26)
Sta. 27 Sta. 05 Sta. 14-16, 23, 26 Sta. 27 Sta. 14-16, 23, 26 Sta. 27 Sta. 14-16, 23, 26 Sta. 27 Sta. 24 Sta. 24 Sta. 24 Sta. 07 Sta.21 Sta.06 Sta.01A Sta. 14-16, 23, 24 Sta. 14-16, 23, 24 Vegetation Milk Air Particulate and Iodine Vegetation Milk Vegetation Milk Vegetation Milk Air Particulate and Iodine Air Particulate and Iodine Air Particulate and Iodine Air Iodine and Particulate Air Particulate and Iodine Air Particulate and Iodine Air Particulate and Iodine Vegetation Vegetation 01/10/07 01/17/07 02/01/07 02/14/07 02/21/07 03/14/07 03/21/07 04/11/07 04/18/07 05/10/07 05/23/07 05/30/07 07/04/07 08/15/07 09/05/07 10/03/07 11/14/07 12/12/07 Seasonal Unavailability.
Milk animal no longer present.
Sampler malfunction.
LLD. achieved.
Seasonal Unavailability.
Milk animal no longer present.
Seasonal Unavailability.
Milk animal no longer present.
Seasonal Unavailability.
Milk animal no longer present.
Sampler malfunction. LLD achieved.
Breaker/GFCI failure. LLD achieved.
Sampler malfunction. LLD achieved.
Sampler malfunction. LLD achieved.
Sampler malfunction. LLD not achieved Sampler malfunction. LLD achieved Initial Sampler startup. Low volume - Particulate LLD not achieved.
Seasonal Unavailability.
Seasonal Unavailability.
70
REFERENCES 71
References
- 1.
Dominion, North Anna Power Station Technical Specifications, Units 1 and 2.
- 2.
Dominion, North Anna Power Station Independent Spent Fuel Storage Installation Technical Specifications.
- 3.
Dominion, Station Administrative Procedure, VPAP-2103N, "Offsite Dose Calculation Manual".
- 4.
Virginia Electric and Power Company, North Anna Technical Procedure, HP-305 1.010, "Radiological Environmental Monitoring Program".
- 5.
Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities".
- 6.
United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October, 1977.
- 7.
United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants",
December 1975.
- 8.
USNRC Branch Technical
- Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.
- 9.
NUREG 0472, "Radiological Effluent Technical Specifications for PWRs",
Rev. 3, March 1982.
- 10.
'"Technical Specifications for North Anna Independent Spent Fuel Storage Installation (ISFSI)".
- 11.
HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.
- 12.
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 2007 74
LAND USE CENSUS North Anna Power Station North Anna County, Virginia January I to December 31, 2007 Direction Distance (miles)
Nearest Nearest Nearest Nearest Nearest Nearest Site Resident Garden Meat Milch Milch IBoundary
(> 50m2)
Animal Cow Goat N
0.9 1.5 1.8 None None None NNE 0.9 0.9 3.1 1.5 None None NE 0.8 0.9 0.9 1.5 None None ENE 0.8 2.1 2.1 2.5 None None E
0.8 1.3 1.3 3.5 None None ESE 0.9 1.7 1.7 None None None SE 0.9 1.4 1.4 1.5 None None SSE 0.9 1.0 1.0 2.8 None None S
0.9 1.1 1.0 2.8 None None SSW 1.0 1.4 1.4 1.9 None None SW 1.1 1.7 3.1 None None None WSW 1.1 1.6 1.6 1.6 None None W
1.1 1.5 1.5 None None None WNW 1.0 1.1 2.6 3.9 None None NW 1.0 1.0 1.6 None None None NNW 0.9 1.0 1.1 None None None 75
2006 to 2007 Land Use Census Changes 2006 2007 Nearest Direction Distance Distance Site Boundary None Resident None Garden NNE 3.4 3.1 S
1.2 1.0 SW 3.9 3.1 WSW 2.7 1.6 W
2.0 15 WNW 1.7 2.6 NW 1.1 1.6 Meat Animal None Milch Cow None Milch Goat None 0
76
APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS YEAR 2007 77
12VTRODUCTION This appendix covers the Intercomparison Program of the AREVA ANP Environmental Laboratory as required by technical specifications for the Radiological Environmental Monitoring Program (REMP).
AREVA uses QA/QC samples provided by Eckert & Zeigler Analytics, Inc to monitor the quality of analytical processing associated with the REMP.
The suite of E & Z Analytics QA/QC samples are designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclides.
It was modified to more closely match the media mix presently being processed by AREVA and includes:
> milk for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses once per
- quarter,
> milk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,
> water for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses during the 1st and 3rd quarters,
> water for Sr-89 and Sr-90 analyses during the 4th quarter,
> water tritium analysis during the 2nd and 4th quarters,
> air filter for gamma (9 nuclides) analyses during the 2nd quarter, and
> air filter for gross beta analysis during the 1 st and 3rd quarters.
In addition to the E & Z Analytics Intercomparison Program, AREVA ANP also participates in other intercomparsion programs which include radionuclides and media similar to those required by the REMP. These programs are the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (PT)
Program, the Department of Energy (DOE) Quality Assessment Program (QAP),
and the Mixed Analyte Performance Evaluation Program (MAPEP).
RESULTS Intercomparison program results are evaluated using AREVA ANP's internal bias acceptance criterion.
The criterion is defined as within 25% of the known strontium value for samples containing both Sr-89 and Sr-90 and within 15% of the known value for other radionuclides, or within two sigma of the known value.
Any sample analysis result that does not pass the criteria is investigated by AREVA ANP.
Eckert and Ziegler Analytics Intercomparison Program results are included on pages 80 through 85 for the 4th quarter of 2006 through the fourth quarter of 2007. There were two disagreements on the results received to date. Condition reports 08-01, 08-02, 08-10 and 08-11 were generated. CR 08-01 remains open.
78
The mean bias (-17.7%) for gross alpha on the third quarter 2007 E & Z Analytics Environmental Cross Check filter samples was outside the E-Lab accuracy criterion of +/- 15%. An eight year historical trend of this analysis showed a mean bias of approximately -4%. The 4t quarter 2007 filter samples were within the acceptance criteria. A review and reanalysis of the third quarter samples is in progress. CR 08-02 remains open. The mean biases on E & Z Analytics 2nd quarter 2007 Environmental Cross Check samples were outside the E-Lab +/-
15% accuracy criterion for two gamma emitting radionuclides, Cr-51 on the filter
(-15.75%) and Ce-141 in milk (-16.25%). A review and reanalysis of the samples is in progress. CR-08-10 remains open. The Sr-89/90 results on the 4th quarter 2007 filter analysis being 0.45 and 0.44 of known value. An investigation is in progress. CR 08-11 remains open. The mean biases for Fe-59, Zn-65 and Co-60 on the 4t quarter 2007 filter analysis were outside the E-Lab +/- 15% at -17%.
An investigation is in progress.
Condition Report 06-16 was generated in 2006 and was still open at the time of the 2006 report. CR 06-16 was re-eluted and acceptable results were obtained.
This CR has been closed, with the corrective action being to update background and blanks on a more frequent basis. In the DOE program all results were in agreement. Condition Reports 06-19, 06-20, and 06-21 were generated in 2006 and were open at the time of the 2006 report. 06-19 error was attributed to a non-homogeneous sample. The corrective action was to count these samples on an elevated geometry to reduce these effects. CR 06-20 was closed on 11/29/2007. After ruling out detector operation, efficiency calibration, and counting statistics as reasons for the failure, the apparent cause was postulated to be an incorrect weight used in the original analysis. The chemist was coached to take greater care in preparing samples for analysis. 06-21 was closed on 11/29/2007. The original Sr-90 analysis of an MAPEP filter sample fell within the MAPEP "Warning" range. A review of previous third party QC filter analyses for Sr-90 did not show a history of failures. An additional MAPEP filter was obtained and analyzed with acceptable results. A review of the original analysis did not identify a cause for the original low bias.
The results of the any analyses not available at the time of submission of this report and any open corrective actions will be included in the 2008 report.
0 79
0 ECKERT & ZIEG LER ANALYT'iO!$ AADi6LOGIC AL ENV IRONaM ETAL,,PROS. CHECK,...
Ratio Sample Quarter/
Sample Reported Known E-LAB/
Number Year Media Nuclide Units Value Value Analytics Evaluation E5222-162 4th12006 Water H-3 pCi/L 14570 14800 0.99 Agreement E5223-162 4th]2006 Water Sr-89 pCi/L 68.8 72.6 0.95 Agreement E5223-162 4th/2006 Water Sr-90 pCi/L 5.56 5.9 0.94 Agreement E5224-162 4th/2006 Filter Gross Alpha Pci 63.3 67.2 0.94 Agreement E5224-162 4th/2006 Filter Gross Beta pCi 209.6 203 1.03 Agreement E5225-162 41th2006 Filter Ce-141 pCi 179.0 185 0.97 Aqreement E5225-162 4th/2006 Filter Cr-51 Pci 277.9 273 1.02 Agreement E5225-162 4th12006 Filter Cs-134 pCi 89.1 92.7 0.96 Agreement E5225-162 4thI2006 Filter Cs-137 pCi 158.8 149 1.06 Agreement E5225-162 4th/2006 Filter Co-58 Pci 54.0 52.8 1.02 Agreement E5225-162 4th/2006 Filter Mn-54 pCi 71.2 69.8 1.02 Agreement E5225-162 4th12006 Filter Fe-59 pCi 51.0 50.2 1.02 Agreement E5225-162 4th/2006 Filter Zn-65 pCi 104.3 103 1.01 Agreement E5225-162 4th/2006 Filter Co-60 pCi 166.7 177 0.94 Agreement E5226-162 4th/2006 Filter Sr-89 pCi 69.5 74.2 0.94 Agreement E5226-162 4th12006 Filter Sr-90 pCi 6.46 6.06 1.07 Agreement E5227-162 4th/2006 Milk 1-131LL pCiIL 71.0 70.8 1.00 Agreement E5227-162 4th12006 Milk 1-131 pCifl 64.8 70.8 0.91 Agreement E5227-162 4th/2006 Milk Ce-141 pCi/L 277.7 294 0.94 Agreement E5227-162 4th12006 Milk Cr-51 pCi/L 430.7 433 0.99 Agreement E5227-162 4thI2006 Milk Cs-134 pCi/L 141.4 147 0.96 Agreement E5227-162 4th12006 Milk Cs-137 pCi/L 233.9 237 0.99 Agreement E5227-162 4th12006 Milk Co-58 pCi[L 83.1 83.8 0.99 Agreement E5227-162 4th/2006 Milk Mn-54 pCiIL 110.6 111 1.00 Agreement E5227-162 4th/2006 Milk Fe-59 pCi/L 82.3 79.7 1.03 Agreement E5227-162 4th/2006 Milk Zn-65 pCiIL 171.4 164 1.05 Agreement E5227-162 4th12006 Milk Co-60 pCiIL 273.1 281 0.97 Agreement E5228-162 4th/2006 Charcoal 1-131 pCi 84.2 87.1 0.97 Agreement 0
0 80
~~AREVA 2007* ENVIRO0NME{*NTAL,LAi3OiRATRY EKERT &ZELRANALYTICS' ENVIRONMEtNTAL CROSS§1 CHECK PROGRRAM1 PERFORMANCE EVALUATION Ratio Sarnple Quarterd Sample Reported Known E-LABI Number Year Media Nuclide Units Value Value Anally5cs Evatuationr E5238-162 1stJ20D7 Wa.er Gross Atha pQJL 117.
112 1_05 Agreement E5238-162 lst/2007 Wa"er Gross Beta pCi 104 10O
.I-4 Agreement E5239-162 lstJ2007 Waeer 1-131LL pCY.
88,3 89.8 0.98 Agreement E5239-102 1stI2007 Wa"er 1-131 pCY_
74.3 89.8 0.83 Agreement E-2*.2-162 lst/2007 Water Ce-141 pQ&
257 258 t.00 Agreement E5239-162 1st120D7 Water Cr-51 PCý_
218 213 1-02 Agreement E52.3-162 lstV2007 Water Cs-134 pCYL 93.6 97.1 0.96 Agreement E522-9-162 lstFM2D7 Water Cs-137 pCY.
197 204 0.97 Agreement E523g-162 1st,2007 Water Co-,5 0CUL 80-2 85.8 t.00 Agreement E5239-182 1st,2017 Wat.er n-54 pCYL 155 158 0.98 Agreement E5239-162 lst/2DD7 WaIer Fe-59 pC8&
87.1 91.7 0-95 Agreement E5230-182 lst,20D7 Water Zn-05 pC_
8866 869 1.02 Agreement E5239-162 lst/2017 Water Co-e0 pC-iL 131 132 0-99 Agreement E5240-182 1st,20137 Water Sr-SO pCW.
127 137 0.92 Agreement E5240-162 1sti20D7 Water ST-go pCYL 9.39 9.99 0-94 Agreement E5241-162 tst'2017 Charoal 1-131 pa 67.6 70.2 0.96 Agreement E5242-162 1 st2007 Filter Gross Alpha pQ 67.2 69.1 0.97 Agreement E5242-162 lstM20D7 Filter Gross Beta p6.4 61.9 t.12 Agreement E5243-162 1st)2007 Milk 1-131LL pCYL 85.1 85.2 1.00 Agreement E5243-162 lst2007 Milk 1-131 pC&L 75.4 85.2 0.88 Agreement E5243-162 1st 2DO7 Milk Ce-141 pCU.
294 297 0.99 Agreement E5243-162 lst'20D7 Milk Cr-51 pD.
226 245 0.92 Agreement E5243-162 lstJ2OD7 Milk Cs-134 pcýL 104 112 0.93 Agreement E5243-162 1stW2007 Milk Cs-137 PCY_
228 234 0.97 Agreement E5243-162 1st20D7 Milk Co-51 pCY_
98.1 G8a 0.99 Agreement E5243-162 lstV2007 Milk tin-54 pCYI 184 182 1.01 Agreement E5243-162 1sti2007 Milk Fe-59 pCYL 10 I0G 1.03 Agreement E5243-162 1stV2MD7 Milk Zn-85 pC*L 1041 1001) 1-04 Agreement E5243-162 1sV20D7 Milk Co-WD pCIYL 148 152 0.98 Agreement E5244-162 1st'2007 Milk Sr-SO 12 137 6.92 Agreement E5244-162 1st'2007 Milk Sr-GO pCWL 8.85 10 0.88 Agreement 81
AREVA 2007 ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Ratio Sample Quarterl Sample Reported Known E-IABl Number Year Media Nuclide Units Vatue Value Analytics Evatuation E5334-162 2rd)20D7 Water H-3 pC*L 8520 OD40 0-94 Agreement E5335-162 2ndJ20D7 Fitter Gross Alpha pCi 122.7 125 G-93 Agreement E5335-162 2nd20D7 Fitter Gross Beta pCi 127 112 1.13 Agreement E533-13r2 2nWZ3,i FIlter Ce-141 pCi 94.1 107
.M Agreement E5335-162 2nd.JO7 Fitter Cr-5I pCi 230 273 G.84 Non-Agreement (1)
E5335-162 2ndr20D7 Filter Cs-134 pCi 1 14.3 129 0.69 Agreement E5335-162 2nd, r2007 Fitter Cs-137 oCi 86_3 90.1 0.90 Agreement E5335-162 2nd)20D7 Filter Co-58 pCi 98A 108 0.93 Agreement U5335-162 2nd/20D7 Fitter Mn-54 pCi 83.3 8.5 0-94 Agreement E5335-162 Id)20D7 Filter Fe-59 pCi 79 69.0 0.G9 Agreement E5335-162 2urZD007 Fitter Zn-65 Pci 167 178 0.94 Agreement E5335-162 2ndr20D7 Fitter CoCO fCi 112 127
.6.9 Ageereent E5337-162 2ndr20D7 FiTter Sr-8s pCi 71A 01.2 0.78 Agreement
_5337-162 2ndr20D7 Fitter Sr-90 pCi 10.1 12.4 0.82 Agreement F5338-162 2ndr20D7 Mlc 1-131LL pCUgL 73.5 70.1 1.05 Aareerent
_5338-U 2rV2007 MUr
-131 p_ L 10 70.1 Agreement E5338-182 2ndr20D7 MQ Ce-141 pCiL 16a 200 0.84 Ncri-A*ec-men F2-F5338-162 2ndM2,D7 1 MEk Cr-51 0pL 447 512 0.87 Agreement E5338-162 2ndr20D7 MDC Cs-134 pCi/L 223 242 0.92 Agreement E5338-162 2ndJ2007 MUC Cs-137 pQ*/L 1M 169 0.93 Agreement E5338-162 2ndJ2007 MUC Co-68 pCUIL 203 198 1.02 Agreement E5338-162 2ndJ20D7 MD I
Mn-54 pCiVL 178 155 1.07 Anreement E5338-1e2 2nd*,2 07 MU Fe-59 pCdL 170 167 1.02 Agreement E5338-162 21r-20D7 MEk Zn-5 pCvL 343 334 1.03 Agreermed F5338-162 2nwd20D7 MD I
Co-CO pCiYL 233 238 1_00 Agreement (1) CF-51 on fiter outside, of acoepancefint. CR 0-0-02 generated.
(2) Ce-141 En milk outside of acceptance limit. CR 03-02 generated.
82
AREVA 2007 ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION' Ratio Sample Quarter[
Sample Reported Known E-LABI Number Year Media Nuclide Units Vatue Value Analytcs Evaluation F5430-182 3rd 12007 Water Gross Al he Ci'L 112 109 1.03 Anreement
=
3W
=
Water Gross Beta pOrL 2
214 1.02 Agreement E5431-162 3rd 12007 Water 1-131LL pCi/L 83.4 80.1 1.04 Agreement 65431-182 3rd 12007 Water 1-131 pCOIL 802 80.1 1.00 Aareement 65431-162 3rd 12007 Water Ce-141 pCitL 178 182 0.97 Agreement E5431-162 3rd 12007 Water Cr-r1 p1CL 228 249 0.02 Agreement E5431-162 3rdQ2007 Water Cs-134 pCi_
111 127 0-87 Agreement E5431-162 3rd120D7 Water Cs-137 pCilL 112 112 1.00 Agreement F5431-162 3rd 120D7 Water Co-68 pCl_
94.3 98.1 0.95 Agreement E5431-182 3rd 12007 Water Mn-54 pOCiL 141 144 0.93 Aareement E5431-162 3rd 12007 Water Fe-59 pCiL 94-8 95.1 1.00 Agreement E5431-162 3rd 120D7 Water Zn-65 pCilL 188 174 1.07 Agreement E5431-162 3rd 120D7 Water Co-CO pCL 120 127 0.94 Agreement
.5432-182 3rd 12007 Charcoal 1-131 pCi a".
69.6 0.95 Agreement E5433-162 3rd 12007 Filter Gross Alpha pCi 88.4 105 0.82 Non-Agreement (3)
E5433-162 3rd 12007 Filter Gross Beta pCi 190 195 0.97 Agreement E5434-182 3rd 120D7 Mrk 1-131LL pCi/L 87.2 65.2 1.02 A eement
=,62 3rd 2D 7 MLk 1-131
-p=
82.9 M.2 Agreemen F5434-162 3rd120D7 MEk Ce-141 pOCiL 198 211 0.93 Agreement E5434-12 3rd 2007 M*k Cr-51 pCi/l 22 289 0-97 Agreement M 12
=
W
=7
/
ME Cs-134 p
1 14 r47 OTW Agreement 65434-182 3rd 02007 Mk Cs-137 pCi/L 128 131 0.95 Agreement U5434-162 3rd 12007 MtEk Co-68 pCiL 111 114 0.97 Agreement E5434-162 3rd 12007 Mk "
Mn-54 pColL 171 168 1.02 Aareement 65434-162 3rd)2007 MR -
Fe-59 pClL 112 111 1.01 Agreement E5434-182 3rd 12007 MEk Zn-5 pC4 212 202 1.05 Agreement E5434-182 3rd 2007 MEO Co-CO pCiUL 145 148 0.98 Agreement E5435-162 3rd 12007 MEk Sr-89 pUlL 892 94.9 0.94 Agreement E5435-182 3rd 12007 MEk Sr-90 CL
- 12.
13.1 0.9-3 Agreement (3) Gross alpha on filter ou-side oa acceptance limit. CR 08-01gwenerated.
83
0 AREVA 2007 ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK SP.ERFORMANCE EVALUATION, Ratio Sample Quarter/
Sample Reported Known E-LAB/
Number Year Media Nuclide Units Value Value Analytics Evaluation E5527-162 4 TH/2 0 0 7 Water H-3 pCi/L 9003 9030 1.00 Agreement E5528-162 4TH/2007 Water Sr-89 pCi/L 87.1 94.9 0.92 Agreement E5528-162 4 TH/2 0 0 7 Water Sr-90 pCi/L 14.4 15.4 0.93 Agreement E5530-162 4 TH/2 0 0 7 Filter Gross Alpha pCi 102.7 120 0.86 Agreement E5530-162 4 TH/2 0 0 7 Filter Gross Beta pCi 166.1 152 1.09 Agreement E5531-162 4 TH/2 0 0 7 Filter Ce-141 pCi 84.1 98.4 0.85 Agreement E5531-162 4TrH/2007 Filter Cr-51 pCi 311.7 358 0.87 Agreement E5531-162 4TH/2 0 0 7 Filter Cs-134 pCi 82.3 96.1 0.86 Agreement E5531-162 4 TH/ 2 0 0 7 Filter Cs-137 pCi 108.9 116 0.94 Agreement E5531162 4TH/2 0 0 7 Filter Co-58 pCi 107.5 122 0.88 Agreement E5531-162 4TH/2007 Filter Mn-54 pCi 117.2 133 0.88 Agreement E5531-162 4TH/2007 Filter Fe-59 pCi 86.6 104 0.83 Non -A.reement(2)
E5531-162
- 1/007 Filter Zn-65 pCi 135.3 164 0.83 Non-A.reementý25 E5531-162 4 TH/2 0 0 7 Filter Co-60 pCi 123.1 148 0.83 Non-Agreement-I E5532-162 4 TH/ 2 0 0 7 Filter Sr-89 pCi 45.9 102 0.45 Non-Agreement")
E5532-162 4 TH/2 0 0 7 Filter Sr-90 pCi 7.2 16.5 0.44 Non-Agreement (I)
E5533-162 4Tf/2007 Milk 1-131LL pCi/L 59.2 60.8 0.97 Agreement E5533-162 4772667 Milk 1-131 pCi/L 58.5 60.8 0.96 Agreement E5533-162 4T /2 0 0 7 Milk Ce-141 pCi/L 136.0 141 0.97 Agreement E5533-162 4T'/2007 Milk Cr-51 pCi/L 516.7 512 1.01 Agreement E5533-162 4 TH/ 2 0 0 7 Milk Cs-134 pCi/L 137.0 137 1.00 Agreement E5533-162 4 TH/2 0 0 7 Milk Cs-137 pCi/L 166.2 166 1.00 Agreement E5533-162 4 TH/2 0 0 7.
Milk Co-58 pCi/L 166.5 174 0.96 Agreement E5533-162 4TH/2007 Milk Mn-54 pCi/L 200.9 190 1.06 Agreement E5533-162 4 TH/ 2 0 0 7 Milk Fe-59 pCi/L 155.0 148 1.05 Agreement E5533-162 4 TH/ 2 0 0 7 Milk Zn-65 pCi/L 222.9 234 0.95 Agreement E5533-162 4TH/ 2 0 0 7 Milk Co-60 pCi/L 205.1 211 0.97 Agreement E5533-162 4 TH/2 0 0 7 Charcoal 1-131 pCi 69.8 73.4 0.95 Agreement (1) Sr-89/90 results low. CR 08-10 generated.
(2) Low bias, - 17%. CR 08-11 generated.
84