NL-11-038, Official Exhibit - ENT000313-00-BD01 - Indian Point, Unit 1, 2, & 3, 2010 Annual Radiological Environmental Operating Report
| ML12339A710 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/16/2011 |
| From: | Conroy P Entergy Nuclear Northeast |
| To: | Atomic Safety and Licensing Board Panel, Document Control Desk |
| SECY RAS | |
| References | |
| RAS 22136, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, NL-11-038 | |
| Download: ML12339A710 (192) | |
Text
{{#Wiki_filter:United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc. In the Matter of: (Indian Point Nuclear Generating Units 2 and 3) ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000313-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn: ENT000313 Rejected: Stricken: Submitted: March 29, 2012 Other: Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB Entergy P,O, Box 249 Buchanan, NY 10511-0249 Tel (914) 734-6710 Patrie W Conroy Director, Nuclear Safety Assurance NL-11-038 May 16,2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001
SUBJECT:
2010 Annual Radiological Environmental Operating Report Indian Point Unit Nos. 1, 2 and 3 Docket Nos. 50-03, 50-247, 50-286 License Nos. DPR-5, DPR-26, DPR-64
Dear Sir or Madam:
Enclosed please find one copy of the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Energy Center (lPEC) Annual Radiological Environmental Operating Report for the period January 1, 2010 to December 31, 2010. This report is submitted in accordance with facility Technical Specification Appendix A section 6 of the provisional operating license for DPR-5 and section 5.6.2 for DPR-26, and DPR-64, Indian Point Unit Nos. 1,2 and 3 respectively. There are no commitments are being made by this report. Should you or your staff have any questions, please contact Mr. Reid Tagliamonte, Radiation Protection Manager at 914-734-5790. Sincerely, PWC/mb cc: next page
NL-11-038 Docket Nos. 50-03, 50-247, 50-286 Page 2 of 2
Enclosure:
- 1. Annual Radiological Environmental Operating Report cc: Mr. William Dean, Regional Administrator, NRC Region 1 Mr. John Boska, Senior Project Manager, NRC NRR DORL IPEC NRC Resident Inspector's Office Mr. Stephen Giebel, IPEC NRC Unit 1 Project Manager Mr. Francis J. Murray, President and CEO, NYSERDA Mr. Paul Eddy, New York State Department of Public Service Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Mgmt, NYSDEC
ENCLOSURE 1 TO NL-11-038 Annual Radiological Environmental Operating Report ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT UNIT 1, 2, and 3 NUCLEAR POWER PLANTS DOCKET Nos. 50-03,50-247, and 50-286
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR INDIAN POINT NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 Docket No. 50-003 Indian Point Unit 1 (IP1) Docket No. 50-247 Indian Point Unit 2 (IP2) Docket No. 50-286 Indian Point Unit 3 (IP3) January 1 - December 31, 2010
TABLE OF CONTENTS Page 1.0 EXECUTIVE
SUMMARY
1-1
2.0 INTRODUCTION
2-1 2.1 Site Description 2-1 2.2 Program Background 2-1 2.3 Program Objectives 2-1 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection 3-1 3.2 Sample Analysis 3-1 3.3 Sample Collection and Analysis Methodology 3-1 3.3.1 Direct Radiation 3-1 3.3.2 Airborne Particulates and Radioiodine 3-2 3.3.3 Hudson River Water 3-2 3.3.4 Drinking Water 3-2 3.3.5 Hudson River Shoreline Soil 3-3 3.3.6 Broad Leaf Vegetation 3-3 3.3.7 Fish and Invertebrates 3-3 3.3.8 Hudson River Aquatic Vegetation 3-3 3.3.9 Hudson River Bottom Sediment 3-4 3.3.10 Preci pitation 3-4 3.3.11 Soil 3-4 3.3.12 Groundwater Samples 3-4 3.3.13 Land Use Census 3-4 3.4 Statistical Methodology 3-6
TABLE OF CONTENTS (continued} Page 4.0 RESUL TS AND DISCUSSION 4-1 4.1 Direct Radiation 4-4 4.2 Airborne Particulates and Radioiodine 4-5 4.3 Hudson River Water 4-5 4.4 Drinking Water 4-6 4.5 Hudson River Shoreline Soil 4-6 4.6 Broad Leaf Vegetation 4-7 4.7 Fish and Invertebrates 4-7 4.8 Aquatic Vegetation 4-7 4.9 Hudson River Bottom Sediment 4-8 4.10 Precipitation 4-8 4.11 Soil 4-9 4.12 Groundwater 4-9 4.13 Land Use Census 4-9 4.14 Conclusion 4-9
5.0 REFERENCES
5-1 APPENDICES: A. ENVIRONMENTAL SAMPLING AND ANALYSIS REQUI REMENTS A-1 B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B-1 RESULTS
SUMMARY
- JAF Environmental Laboratory
- GEL Laboratories Quality Assurance Reports
- TLD Dosimeter Testing ii
LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles) A-5 A-2 Sampling Locations (Greater Than Two Miles) A-6 A-3 Additional Sampling Locations A-7 C-1 Direct Radiation, Annual Summary, 2000 to 2010 C-3 C-2 Radionuclides in Air, 2000 to 2010 C-5 C-3 Radionuclides in Hudson River Water, 2000 to 2010 C-7 C-4 Radionuclides in Drinking Water, 2000 to 2010 C-9 C-5 Radionuclides in Shoreline Soil, 2000 to 2010 C-11 C-6 Broad Leaf Vegetation - Cs-137, 2000 to 2010 C-13 C-7 Fish and Invertebrates - Cs-137, 2000 to 2010 C-15
LIST OF TABLES TABLE TITLE Page A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection Requirements for Environmental Sample Analysis A-8 A-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples A-10 8-1 Summary of Sampling Deviations, 2010 8-3 8-1a 2010 Air Sampling Deviations 8-4 8-1b 2010 TLD Deviations 8-4 8-1c 2010 Other Media Deviations 8-4 8-2 ODCM Annual Summary, 2010 8-5 8-3 2010 Direct Radiation, Quarterly Data 8-9 8-4 Direct Radiation, 2000 through 2010 Data 8-10 8-5 2010 Direct Radiation, Inner and Outer Rings 8-11 8-6 Environmental Airborne Particulate Samples - 2010 Gross 8eta Activity 8-12 8-7 Concentrations of Gamma Emitters in Quarterly Composites of Site Air Particulate Samples, 2010 8-14 8-8 Environmental Charcoal Cartridge Samples - 2010 1-131 Activity 8-16 8-9 Concentrations of Gamma Emitters in Surface Water Samples, 2010 8-18 8-10 Concentrations of Tritium in Surface Water Samples, 2010 8-20 8-11 Concentrations of Gamma Emitters in Drinking Water Samples, 2010 1 2 8-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2010 8-24 8-14 Concentrations of Gamma Emitters in 8road Leaf Vegetation Samples, 2010 8-26 iv
LIST OF TABLES (Continued) TABLE TITLE Page 8-15 Concentrations of Radionuclides in Fish Samples, 2010 8-39 8-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2010 8-43 8-17 Concentrations of Gamma Emitters in 8ottom Sediment Samples, 2010 8-44 8-18 Concentrations of Radionuclides in Rainwater Samples, 2010 8-46 8-19 Concentrations of Gamma Emitters in Soil Samples, 2010 8-48 8-20 Concentrations of Radionuclides in Monitoring Well Samples, 2010 8-49 8-21 Land Use Census - Residence and Milch Animal Results, 8-50 2010 8-22 Land Use Census, 2010 8-51 C-1 Direct Radiation Annual Summary, 2000 to 2010 C-2 C-2 Radionuclides in Air, 2000 to 2010 C-4 C-3 Radionuclides in Hudson River Water, 2000 to 2010 C-6 C-4 Radionuclides in Drinking Water, 2000 to 2010 C-8 C-5 Radionuclides in Shoreline Soil, 2000 to 2010 C-10 C-6 8 road Leaf Vegetation - Cs-13 7, 2000 to 2010 C-12 C-7 Fish and Invertebrates - Cs-137, 2000 to 2010 C-14 0-1 Program Schedule 0-2 0-2 Ratio Agreement 0-3 v
SECTION I EXECUTIVE
SUMMARY
1.0 EXECUTIVE
SUMMARY
This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2010 Radiological Environmental Monitoring Program (REMP) for the Indian Point site. The Indian Point site consists of Units 1, 2 and 3. Units 1, 2 and 3 are owned and operated by Entergy Nuclear Operations, Inc. Unit 1 was retired as a generating facility in 1974 and, as such, its reactor is no longer operated. The REMP is used to measure the direct radiation and the airborne and waterborne pathway activity in the vicinity of the Indian Point site. Direct radiation pathways include radiation from buildings and plant structures, airborne material that might be released from the plant, cosmic radiation, fallout, and the naturally occurring radioactive materials in soil, air and water. Analysis of thermoluminescent dosimeters (TLDs), used to measure direct radiation, indicated that there were no increased radiation levels attributable to plant operations. The airborne pathway includes measurements of air, precipitation, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations. The waterborne pathway consists of Hudson River water, fish and invertebrates, aquatic vegetation, bottom sediment, and shoreline sediment. Measurements of the media comprising the waterborne pathway indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations. This report contains a description of the REMP and the conduct of that program as required by the IPEC Offsite Dose Calculation Manual, herein referred to as ODCM. This 2010 AREOR also contains summaries and discussions of the results of the 2010 program, trend analyses, and potential impact on the environment, land use census, and inter-laboratory comparisons. 1166 samples were obtained out of a planned load of 1178 a has been ongoing since 2005 and continued throughout 2010. This investigation of potential onsite sources of contamination is not the focus of this Annual Radiological Environmental Operating Report; however. in 2006, Entergy agreed to several changes in the REMP to assure that all pathways were being evaluated. Specifically, two new groundwater wells (non-drinking water) were 1-1
designated as "boundary wells" and were sampled as groundwater samples for tritium and strontium-gO analyses and also gamma spectroscopy analysis. These wells (MW-40 and MW-51) were designated as REMP sample stations 104 and 105. In 2010, an offsite well to replace these two wells was established as sample station 106 at the Lafarge plant south of, and adjacent to, Indian Point. Once it was established, further sampling for REMP purposes at MW-40 and MW-51 was suspended. For 2010. only the sampling at the Lafarge plant was conducted - in accordance with the current applicable ODCM revision. A 2006 change was made to the existing fish and invertebrate samples and shoreline sediment samples. The locations and frequency remained the same; however, strontium-gO was added, as also now is Ni-63, to the required analyses. These additions were observed for the sampling and analyses conducted in 2010. These changes were captured in the ODCM. Groundwater sample results for 2010 are summarized in Table 8-20. In summary, the levels of radionuclides in the environment surrounding Indian Point were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, Indian Point operations in 2010 did not result in exposure to the public greater than environmental background levels. 1-2
SECTION 2 INTRODUCTION
2.0 INTRODUCTION
2.1 Site Description The Indian Point site occupies 239 acres on the east bank of the Hudson River on a point of land at Mile Point 42.6. The site is located in the Village of Buchanan, Westchester County, New York. Three nuclear reactors, Indian Point Unit Nos. 1, 2 and 3, and associated buildings occupy approximately 35 acres. Unit 1 has been retired as a generating facility. Units 1, 2, and 3 are owned and operated by Entergy Nuclear. 2.2 Program Background Environmental monitoring and surveillance have been conducted at Indian Point since 1958, which was four years prior to the start-up of Unit 1. The pre-operational program was designed and implemented to determine the background radioactivity and to measure the variations in activity levels from natural and other sources in the vicinity, as well as fallout from nuclear weapons tests. Thus, as used in this report, background levels consist of those resulting from both natural and anthropogenic sources of environmental radioactivity. Accumulation of this background data permits the detection and assessment of environmental activity attributable to plant operations. 2.3 Program Objectives The current environmental monitoring program is designed to meet two primary objectives:
- 1. To enable the identification and quantification of changes in the radioactivity of the area, and
- 2. To measure radionuclide concentrations in the environment attributable to operations of the Indian Point site.
on a regular basis. The radioactivity profile of the environment is established and monitored through routine evaluation of the analytical results obtained. The REMP designates sampling locations for the collection of environmental media for analysis. These sample locations are divided 2-1
into indicator and control locations. Indicator locations are established near the site, where the presence of environmental radioactivity of plant origin is most likely to be detected. Control locations are established farther away (and upwind/upstream, where applicable) from the site, where the level would not generally be affected by plant discharges. The use of indicator and control locations enables the identification of potential sources of detected radioactivity, thus meeting one of the program objectives. Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is another program objective. Verifying projected concentrations through the REMP is difficult since the environmental concentrations resulting from plant releases are consistently too small to be detected. Plant related radionuclides were detected in 2010; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2010 REMP sample results confirms that radiological effluents were well below regulatory limits. 2-2
SECTION 3 PROGRAM DESCRIPTION
3.0 PROGRAM DESCRIPTION To achieve the objectives of the REMP and ensure compliance with the ODCM. sampling and analysis of environmental media are performed as outlined in Table A-1 and described in section 3.3. 3.1 Sample Collection Entergy personnel perform collection of environmental samples for the Indian Point site, with the exception of groundwater and fishlinvertebrate samples. The groundwater (monitoring well) samples are collected by a contracted environmental vendor, GZA Geo Environmental, Inc. Assistance in the collection of fish and invertebrate samples was provided by a contracted environmental vendor - Normandeau Associates, Inc. 3.2 Sample Analysis The analysis of Indian Point environmental samples is performed by the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory in Fulton, New York. The JAFNPP lab at Fulton currently analyzes nearly all samples, except for groundwater samples and some tritium, nickel and strontium analyses on other media. These samples were analyzed at other New York State Department of Health Environmental Laboratory Approval Program (ELAP) certified laboratories. 3.3 Sample Collection and Analysis Methodology 3.3.1 Direct Radiation Direct gamma radiation is measured using integrating calcium sulfate thermoluminescent dosimeters (TLDs), which provide cumulative is sample locations. The inner ring is located near the site boundary at approximately 1 mile (1.6 km). The outer ring is located at approximately 5 miles (8 km) from the site (6.7- 8.0 km), see Figures A-1 and A-2. 3-1
An additional TLD sample site is located at Roseton (20.7 miles north) as a control, and there are eight other TLD sample locations of special interest. In total, there are 41 TLD sample sites, designated DR-1 through DR-41, with two TLDs at each site. TLDs are collected and processed on a quarterly basis. The results are reported as mR per standard quarter (91 days). The mR reported is the average of the two TLDs from each sample site. 3.3.2 Airborne Particulates and Radioiodine Air samples were taken at eight locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control at sampling station 23 (A5) and seven indicator locations. These indicator locations are at sampling stations 4 (A1), 5 (A4), 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown on Figures A-1, A-2, and A-3. The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges. Both are changed on a weekly basis. The filter and cartridge samples are analyzed for gross beta and radioiodine, respectively. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters. 3.3.3 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (sampling station 9, Wa1) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, Wa2); see Figure A-1. An automatic composite sampler is used to take representative samples. On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis, and quarterly for tritium analysis. 3.3.4 Drinking Water water are collected ....... "' .... +.... miles station Mi see Each monthly sample is approximately 4 liters and is analyzed for gamma-emitting radionuclides. They are also composited quarterly and analyzed for tritium. 3-2
3.3.5 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The indicator locations are at sampling stations 53 (Wc1), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-1, A-2, and A-3 show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90. 3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The indicator locations are sampling stations 94 (lc2) and 95 (lc1), and the control location is at Roseton, sampling station 23 (Ic3). See Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways. 3.3.7 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The indicator location (downstream sample point) is designated as sampling station 25 (lb1) and the control location (upstream) is at Roseton, sampling station 23 (lb2). See Figures A-1 and A-2. These samples are collected in season or semiannually if they are not seasonal. The fish and invertebrates sampled are analyzed by gamma spectroscopy, for Sr-90 and for Ni-63. 3.3.8 Hudson River Aquatic Vegetation During the and summer, aquatic vegetation samples are at two indicator locations (sampling location are on availability. These samples are analyzed by gamma spectroscopy. 3-3
3.3.9 Hudson River Bottom Sediment Bottom sediment and benthos are sampled at four locations: three indicator locations (sampling stations 10, 17, and 28) and one control location (84). along the Hudson River. once each spring and summer; see Figure A-3. These samples are obtained using a Peterson grab sampler or similar instrument. The bottom sediment samples are analyzed by gamma spectroscopy. 3.3.10 Precipitation Precipitation samples are continuously collected at one indicator location (sampling station 44) and one control location (23); see Figure A-3. They are collected in sample bottles designed to hinder evaporation. They are composited quarterly and analyzed for tritium. They are also analyzed by gamma spectroscopy. 3.3.11 Soil Soil samples are collected from two indicator locations (sampling stations 94 and 95), and one control location (23) on an annual basis; see Figure A-3. They are approximately 2 kg in size and consist of about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy. 3.3.12 Groundwater Samples Based on recent site hydrology evaluations and the addition of a number of groundwater sampling wells, two monitoring wells were installed in 2006 and designated as REMP sample stations 104 (MW-
- 40) and 105 (MW-51). These wells have sample points at six different elevations which were specifically designed to be representative of groundwater moving towards the site boundary. In 2010, an offsite well at the Lafarge plant (106) was established to replace MW-40 and MW-
- 51. This groundwater sample location is shown in Figure A-3.
Groundwater samples at location were obtained semi-annually at 1 are Each year a land use census consisting of milch animal and residence surveys is conducted during the growing season to determine the current utilization of land within 5 miles (8 km) of the site. These 3-4
surveys are used to determine whether there are changes in existing conditions that warrant changing the sampling program. For example, the milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. This census consists of visual field surveys of the areas where a high probability of milch animals exists and confirmation through personnel such as feed suppliers who deal with farm animals and dairy associations (See Tables 8-21 and 8-22). Visual inspections were made of the 5-mile area around the Indian Point Site during routine sample collections and emergency plan equipment inspections in the area throughout the year. An extensive land survey was conducted of the 5-mile area in an attempt to identify new residential areas, commercial developments and to identify milch animals in pasture. Previous locations were visited and verified by dispatching Nuclear Environmental Technicians to the various locations. Note: These actions were taken while performing quarterly environmental badge change out and field inspections through out the four surrounding counties.
- Orange County was surveyed during through the summer and fall.
- Rockland County was surveyed during summer and fall.
- Putnam County was surveyed during the summer and fall.
- Westchester County was surveyed during the spring, summer and fall.
Although there are presently no animals producing milk for human consumption within 5 miles (8 km) of the site, the census is performed determine if a milk-sampling program needs to be conducted. Point. See Table 8-22. A garden census was not performed, as the ODCM allows sampling of vegetation in two sectors near the site boundary in lieu of a garden census. The sectors are chosen to be in the pre-dominant wind directions. 3-5
Note: An aerial survey was not conducted of the 5-mile area this year. 3.4 Statistical Methodology There is a number of statistical calculation methodologies used in evaluating the data from the Indian Point REMP. These methods include determination of Lower Limits of Detection (LLD) and Critical Levels (Lc), and estimation of the mean and associated propagated error. 3.4.1 Lower Limit of Detection (LLD) and Critical Level (Lcl The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability' of faisely concluding that a blank observation represents a <<rear signal. For a particular measurement system (v.f1ich may include radiochernical separation): 2.71
- - ~O..
1 *! Itl
-'-~,j~ l'jl~(-.}*
IlJ) It ~ I, E liT
- k*}",' e*J.
wtlere: LLD= The lower limit of detection as defined above (as picocurie per unit mass or volume) The sample counting time in minutes s,.,= The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) Ttt = The background count time in minutes E= The counting efficiency (as counts per transformation) V= The sample size (in units of mass or volume) k fr:U'1><:;t,vrrl:'1h'"'tn .. per minute per unit of per y= The fractional radiochemical 3-6
- f. :: The radioactive deC3]' constant for the particular radionudide t:: The elapsed time between midpoint of sample collection and time of counting Note: The above LLD formula accounts for differing background and sample count times.
The RadiologiC31 Environmental Monitoring Program, REMP, uses an LLD formula that assumes equal background and Saliiple count times, in accordance with the RECS.
\'\t'hen the aoove LLD formula is more appropriate for the effluents program, it may be used.
The constants 2.71 and 3.29 and the general LLD equation were derived from the following r.\'o sources:
- 1) Currie, LA "Limits for Qualitative Detection of Quantitative Detemlination". (Anal. Chem.
40:586-593,1968); and,
- 2) Mayer, Dauer HAppliC300n of Systematic Error Bounds to Detection Limits for PractiC31 Counting".
(HP Joumal65(1): 89-9'1,1993) The vaJue of Sb used in the C3lculation of the LLD for a detection system shall be based on the actual observed yariance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionudide determined by gamma ray spectronletry. the background shall include the typical contributions of other radionudides normally present in the samples. Typtcal values of E. V, Y. and t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be 'I.>ithin +/-. one F'VVHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionudide. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement process and not as an a posteriori (after the fact) limit for a particular measurement To handle the a posteriori problem, a decision level must be defined. 'Nhich has been identified as the Critical Level. Following an experimental observation. one must decide whether or not a real signal was, in fact, detected. This type of binary qualitative decision is subject to two kinds of error: deciding that the radioactive material is present when it is not (3: Type I error), and the converse, failing to decide that it is present 'Nhen it is (b: Type II error). The maximum accepta~e Type I error (a), together with the standard deviation, Snet, of the net signal when the net signal equalS zero, establish the Critical level, Lc, upon which decisions may be based. Operationally. an observed signal, S, must exceed Lc to yieki the decision, detected. k =kaSt!( 1+T:JTSIS
~t:l,,..rI::1.n1"1M nomlal distribution and rnrTPcnn.",,,
"r.r,."'nhiJ,,..,., to a 99"" ,..",r,tui,"nr'o To set ~ for L~ detemlination 31 less than 0.05, the equation for the LLD ('Nhich places i! less than or equal to 0.05) should be employed to verify that the C3lculated LLD is less than or equal to the LLDs specified in the RECS. This calculation, jf necessary, will be performed on a case by case basis.
3-7
3.4.2 Determination of Mean and Propagated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, which may be attributed to plant operations, at a value greater than the Le. two recounts are performed to verify the positive results. The recounts are not performed on; air samples with positive results from gross beta analysis. since the results are always positive due to natural background radioactive material in the air, or tritium in water samples, since an outside contractor provides these activities. When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean. In cases where more than one sample result is available. the mean of the sample results and the estimated error for the mean are reported in the Annual Report. The mean (X) and the propagated error (PE) are calculated using the following equations: N IXi
- i=1 X- --
N where: Xi = value of each individual observation N = number of observations PE =-'.-;=_1_ __ N where: ERRi =1 sigma error of the individual analysis N number of observations The averages shown in the summary table (Table B-2) are the averages of the positive values in accordance with the NRC's Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference 14). Samples with "<If values are not included in the averages. 3-8
It should be noted that this statistic for the mean using only positive values tends to strongly bias the average high, particularly when only a few of the data are measurably positive. The REMP data show few positive values; thus the corresponding means are biased high. Exceptions to this include direct radiation measured by TLDs and gross beta radioactivity in air, which show positive monitoring results throughout the year. In the data tables 8-6 through 8-20, values shown are based on the Lc value, unless otherwise noted. If a radionuclide was detected at or above the Lc value in two or more counts, the mean and error are calculated as per Section 3.4.2, and reported in the data table. Values listed as "<" in the data tables are the Lc values for that sample, unless otherwise noted. If multiple counts were performed on a sample and a radionuclide's values are U< Lc " each time, the largest critical level is reported in the data table. The historical data tables contain the annual averages of the positive values for each year. The historical averages are calculated using only the positive values presented for 2000 through 2009. The 2010 average values are included in these historic tables for purposes of comparison. 3-9
SECTION 4 RESULTS AND DISCUSSION
4.0 RESULTS AND DISCUSSION The 2010 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manual ODCM. The ODCM contains requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity. The REMP at Indian Point includes measurements of radioactivity levels in the following environmental pathways. Hudson River Water Shoreline Soil Fish and Invertebrates Aquatic Vegetation Bottom Sediment Airborne Particulates and Radioiodine Precipitation Drinking Water Terrestrial Broad Leaf Vegetation Direct Gamma Radiation Soil Groundwater An annual land use and milch animal census is also part of the REMP. To evaluate the contribution of plant operations to environmental radioactivity levels, other man-made and natural sources of environmental radioactivity, as well as the aggregate of past monitoring data, must be considered. It is not merely the detection of a radionuclide, but the evaluation of the location, magnitude, source, and history of its detection that determines its significance. Therefore, we have reported the data collected in 2010 and assessed the significance of the findings. A summary of the results of the 2010 REMP is presented in Table B-2. This The radionuclides detected in the environment can be grouped into three categories: (1) naturally occurring radionuclides; (2) radionuclides resulting from weapons testing and other non-plant related, anthropogenic sources; and (3) radionuclides that could be related to plant operations. 4-1
The environment contains a broad inventory of naturally occurring radionuclides which can be classified as, cosmic ray induced (e.g., 8e-7, H-
- 3) or geologically derived (e.g., Ra-226 and progeny, Th-228 and progeny, and K-40.) These radionuclides constitute the majority of the background radiation source and thus account for a majority of the annual background dose detected. Since the detected concentrations of these radionuclides were consistent at indicator and control locations, and unrelated to plant operations, their presence is noted only in the data tables and will not be discussed further.
The second group of radionuclides detected in 2010 consists of those resulting from past weapons testing in the earth's atmosphere. Such testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, contributed to the concentrations in the lower atmosphere and ecological systems. Although reduced in frequency, atmospheric weapons testing continued into the 1980's. The resultant radionuclide inventory. although diminishing with time (e.g., through radioactive decay and natural dispersion processes). remains detectable. In 2010. the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-137 in some media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years. The final group of radionuclides detected through the 2010 REMP comprises those that may be attributable to current plant operations. During 2010 Cs-137 and tritium (H-3) were the only potentially plant-related radionuclides detected in some environmental samples. H-3 may be present in the local environment due to either natural occurrence. other man-made sources. or as a result of plant operations. Cs-137 is produced in and released from fission reactors and were introduced into the environment from the accident at Chernobyl in 1986. Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2010, there were three detections of Cs-137 in shoreline soil (2 indicator samples and one control In bottom sediment there were five positive detections of Cs-137 (all or near two discharge canal samples are A sample of aquatic vegetation at Lents Cove showed Cs-137 activity greater than the critical level but less that the lower limit of detection. It is being reported positive, due to its relation to the critical level. but not significant. A sample at Cold Spring (distant location) showed detectable. but not 4-2
significant, Cs-137 activity. The level is the same as that found at Lents Cove. The fact that there was no Cs-134 present (recent plant releases would contain Cs-134) and that there was detection also at a distant location indicates that the activity may be due to atmospheric weapons testing, with some contribution from plant releases from several years past. Strontium-90 (Sr-90) may also be present in the environment from atmospheric testing debris. Due to a desire to improve the sensitivity of Sr-90 in environmental samples, a new analytical technique was pursued, at the end of 2009, for application in 2010. 2009 fishlinvertebrate sample results for Sr-90 were inconclusive. As noted in the 2009 ARE OR, the results for Sr-90 in all fish and invertebrate samples were under review and not reliable. It was noted that when the certified results were available, they would be submitted as an addendum. However, as detailed below, no certifiable results were able to be obtained from the 2009 samples. In a letter dated June 29, 2010, the laboratory identified that due to the extremely low detection level requested, interferences such as radon progeny rendered the 2009 data invalid. Close observation of the analytical method used in 2009 identified the need to improve the technique, to better screen out these contaminants, or proceed in another way. A new technique was adopted at the end of 2009's evaluation, for application in 2010. An attempt was made to re-analyze 2009 fish/invertebrate samples for Sr-90 using the new method, but the media had been consumed in the earlier tests and no further analyses were possible. 2010 samples were analyzed with the new method, with much improved sensitivity and reliability. No Strontium-90 was identified in samples from 2010. 1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in previous years. 1-131 was not detected in 2010 in aquatic vegetation indicator and control locations. are core. Co-58 has a much shorter half-life, its absence "dates" the presence of Co-60 as residual from releases of both radionuclides in the past. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is considered to be from recent releases. When significant concentrations of Co-60 are detected but no Co-58, there is an increased likelihood that the Co-60 is due to residual Co-60 from past 4-3
operations. There was no Co-58 or Co-60 detected in the 2010 REMP. though they (Co-58 and Co-60) can be observed in historical data. In the following sections, a summary of the results of the 2010 REMP is presented by sample medium and the significance of any positive findings discussed. It should be noted that naturally occurring radionuclides are omitted from the summary table (Table 8-2) and further discussion. 4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by AREVA NP via the JAF Laboratory. In 2010, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table 8-2 and all the TLD data are presented in Tables 8-3, 8-4 and 8-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements. Table 8-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. The table also provides the sector for each of the DR sample points. Table 8-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 2000 through 2008. The 2010 means are also presented in Table 8-4. Table 8-5 presents the 2010 TLD data for the inner ring and outer ring of TLDs. The 2010 mean value for the direct radiation sample pOints was 14.0 mR per standard quarter - which represents no change from 2009. At those locations where the 2010 mean value was higher than historical means, they are within historical bounds for the respective locations. The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-
- 16) is close to the site boundary. The outer ring (DR-17 to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The these two rings are provided in Table 8-5. The the was 1 mR standard quarter was 1 The control location average for 2010 was 1 quarter.
Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDs. The 2010 averages are consistent with the historical data. The 2010 and previous years' data show that 4-4
there is no measurable direct radiation in the environment due to the operation of the Indian Point site. 4.2 Airborne Particulates and Radioiodine An annual summary of the results of the 2010 air particulate filter and charcoal cartridge analyses is presented in Table 8-2. As shown, there were no radionuclides detected in the air attributable to plant operations. The results of the analyses of weekly air particulate filter samples for gross beta activity are presented in Table 8-6, and the results of the gamma spectroscopy analyses of the quarterly composites of these samples are in Table 8-7. Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the eight indicator air sample locations was 0.013 pCilm 3 and the average for the control location was 0.013 pCi/m 3 . The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location. Gamma spectroscopy analyses of the quarterly composite air samples showed that no reactor-related radionuclides were detected and that only naturally-occurring radionuclides were present at detectable levels. The mean annual gross beta concentrations and Cs-137 concentrations in air for the past 10 years are presented in Table C-2. From this table and Figure C-2, it can be seen that the average 2010 gross beta concentration was consistent with historical levels. Cs-137 has not been detected since 1987. This is consistent with the trend of decreasing ambient Cs-137 concentrations in recent years. The charcoal cartridge analytical results are presented in Table 8-8.
"Less than" values are presented as sample critical level (Le). There was no 1-131 detected (LLD = 0.07 pCi/m 3 ) in the charcoal cartridge samples, which is consistent with historical trends.
seen that no airborne radioactivity attributable was ael:eCl[ea 4.3 Hudson River Water A summary of the radionuclides detected in the Hudson River water is contained in Table 8-2. Data resulting from analysis of monthly Hudson River water samples for gamma emitters, and H-3 analysis of quarterly composites, are presented in Tables 8-9 and 8-10, respectively. 4-5
Only H-3 was found. The levels are consistent with occasional historical detection of H-3. Additionally, Table C-3 indicates the absence of Cs-137 which is consistent with historical data. 4.4 Drinking Water The annual program summary table (Table 8-2) contains a summary of the 2010 drinking water sample analysis results. Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table 8-11 and results of tritium analysis of quarterly composites are in Table 8-12. Other than naturally occurring radionuclides, no radionuclides were detected in drinking water samples. A summary and illustration of historic trends of drinking water are provided in Table C-4 and Figure C-4, respectively. An examination of the data indicates that operation of the Indian Point units had no detectable radiological impact on drinking water. 4.5 Hudson River Shoreline Soil A summary of the radionuclide concentrations detected in the shoreline soil samples is contained in Table 8-2. Table 8-13 contains the results of the gamma spectroscopic and strontium-gO analyses of the shoreline soil samples. In addition to the naturally occurring radionuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2010. Cs-137 was detected at the Verplanck location in both samples from that location, for a total of two positive values out of eight samples from indicator locations. Cs-137 was detected at the control location (Manitou Inlet) in one of two samples (63 pCi/kg). The average concentration for the indicator locations that had positive indication of Cs-137 was 154 pCi/kg (dry) with a maximum concentration of 174 pCilkg (dry.) and control locations, at a consistent level over the past ten years. Cs-134 and Cs-137 are both discharged from the plant in similar quantities. The lack of Cs-134 activity is an indication that the primary source of the Cs-137 in the shoreline soil is legacy contamination from weapons fallout. 4-6
No Sr-90 was detected in any collected shoreline soil samples. 4.6 8road Leaf Vegetation Table 8-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2010 samples are presented in Table 8-14. Analyses of broad leaf vegetation samples revealed only one instance of Cs-137 at 31 pCi/kg (wet) value. Table C-6 contains an historical summary and Figure C-6 is an illustration of the broad leaf vegetation analysis results. The detection of low levels of Cs-137 has occurred sporadically at both indicator and control locations at relatively low concentrations for the past ten years and not at all in the last five years. The 2010 single detection is comparable to the highest average positive detection of the last ten years. 4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table 8-2. Table 8-15 contains the results of the analysis of fish and invertebrate samples for 2010. There were no plant related radionuclides detected as a result of the GSA. Strontium-90 was added to the analyte list in 2007. Ni-63 was added with an ODCM revision in 2010. No Ni-63, Sr-90 or any other activity aside from naturally-occurring ones was found in any of these samples in 2010. An improved analytical method for Strontium-90 in fish/invertebrates was applied in 2010, improving the sensitivity, and reducing analytical error. This improved analytical technique gave us the required sensitivity and reliable results. A summary of historical fish and invertebrate analytical data is presented in Table C-7 and illustrated in Figure C-7. Available data are consistent with historical trends. 4.8 Aquatic Vegetation The laboratory reported positive Cs-137 (17.6 pCI/kg) at Lents Cove. This is an amount between the Critical Level and the LLD. Activity-free samples would, about 5% of the time, show a positive result due to normal background statistical fluctuations. In the historical record, a 17 4-7
pCilkg result was reported for a 2005 aquatic vegetation sample and also one for 2009 at the same location. A comparable detection at the Cold Spring control location showed 16.8 pCi/kg - a quite similar result. There are about five samples per year, varying from 3 to 10, going back to 2005. No 1-131 was detected. 4.9 Hudson River Bottom Sediment A summary of the Hudson River bottom sediment analysis results is presented in Table B-2. Table B-17 contains the results of the analysis of bottom sediment samples for 2010. Cs-137 was detected at 5 of 6 indicator station samples and not at all at two control station samples. This frequency of detection is not unusual. Cs-134 was not detected in any bottom sediment samples. The lack of Cs-134 suggests that the primary source of the Cs-137 in bottom sediment is from historical plant releases over the years and from residual weapons test fallout. The discharge canal bottom sediments were 418 pCi/kg and 1330 pCi/kg on samples taken three months apart (average = 874 pCilkg.). There is nothing in release data and in monitoring well data that corresponds to this difference. The results are very comparable to the 2009 results - thus corroborating the 2009 results. The average of all indicator detections is 553 pCi/kg (493 pCi/kg in 2009.) This is consistent with historical annual average concentration for indicator locations. This detection of Cs-137 in bottom sediment generally decreased from an average of 1200 pCilkg in the early 1990s to 500 pCi/kg in the mid-1990s to a recent value of about 430 pCi/kg. Cs-134 has not been detected in bottom sediment since 2002. 4.10 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table B-18 contains the results of the precipitation samples for 2010. Other than naturally occurring radionuclides, no radionuclides were detected precipitation samples. A over 1 been detected in both indicator and control precipitation samples in 2000; however, there have been no instances of positive values since that time. 4-8
4.11 Soil A summary of the soil sample analysis results is presented in Table 8-
- 2. Table 8-19 contains the results of the soil samples for 2010. Other than naturally occurring radionuclides, no activity was detected in any of the soil samples.
4.12 Groundwater A summary of the groundwater samples for 2010 is contained in Table 8-2. Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, and Sr-90 are given in Table 8-20. No REMP nuclides other than naturally occurring ones were found in 2010. 4.13 Land Use Census A census was performed in the vicinity of Indian Point in 2010. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables 8-21 and 8-22. The results of the 2010 census were generally same as the 2007 census results. The New York Agricultural Statistic Service showed there were no animals producing milk for human consumption found within 5 miles (8 km) of the plant. Field observations also yielded no milching animal locations within five miles. The second part of this census revealed that the two nearest residences in different sectors are located 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant. The 2010 land use census indicated there were no new residences that were closer in proximity to IPEC. The ODCM allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis results for these two sectors are discussed in Section 4.6 and presented in Table 8-14, Table C-6 and Figure 4.14 The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2010 REMP reveal that operations at the station did not result in an adverse impact on the environment. 4-9
The 2010 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. The results indicate that the fallout from previous atmospheric weapons testing continues to contribute to detection of Cs-137 in some environmental samples. There are infrequent detections of plant related radionuclides in the environs; however, the radiological effects are very low and are significantly less than those from natural background and other anthropogenic sources. 4-10
SECTION 5 REFERENCES
5.0 REFERENCES
- 1. Entergy Nuclear Northeast, Nuclear Environmental Monitoring Procedures, Radiological Support Procedures, Indian Point Station.
- 2. U.S Nuclear Regulatory Commission. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, December 1975.
- 3. Eisenbud, M., Environmental Radioactivity, Academic Press, New York, 1987.
- 4. Glasstone, S., and W. H. Jordan, Nuclear Power and Its Environmental Effects, American Nuclear Society, la Grange Park, Il, 1980.
- 5. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, U.S. NRC Regulatory Guide 1.109, Revision 1, 1977.
- 6. Cohen N., and Eisenbud M., Radiological Studies of the Hudson River, Progress Report Institute of Environmental Medicine, New York University Medical Center, December 1983.
- 7. U.S. Nuclear Regulatory Commission. Regulatory Guide 4.15, Revision 1, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment February 1979.
- 8. J. W. Poston, Cesium-137 and Other Man-Made Radionuclides in the Hudson River: A Review of the Available Literature, Applied Physical Technology, Inc., report to NYPA, September 1977.
- 9. U.S. Environmental Protection Agency Report EPC-520/1 80-012, Upgrading Environmental Radiation Data, August 1980.
- 10. Andrews, Howard L. and lapp, Ralph E. Nuclear Radiation Physics, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1972.
- 11. U.S. Nuclear Regulatory Commission, Branch Technical Position to Regulatory Guide 4.8, An Acceptable Radiological Environmental Monitoring Program, November 1979.
1 Eichholz, Geoffrey G., Environmental Aspects of Nuclear Power, lewis 1 1 and ASTM #698, Philadelphia, PA, 1978.
- 14. Entergy Nuclear Northeast, James A. FitzPatrick Nuclear Power Plant, Radiological and Environmental Services Department Environmental Surveillance Procedures.
- 15. Knoll, Glenn F., Radiation Detection and Measurement, first edition, John Wiley and Sons, New York, 1979.
5-1
- 16. Dixon, Wilfred J., Introduction to Statistical Analysis, third edition, McGraw-Hili Inc., 1969.
- 17. National Council on Radiation Protection. NCRP Report No.94, Exposure of the Population in the United States and Canada from Natural Background Radiation December 1987.
- 18. National Council on Radiation Protection. NCRP Report No. 62, Tritium in the Environment, March 1979.
- 19. IPEC Offsite Dose Calculation Manual, Units 1,2 and 3
- 20. Kuhn, W.,et aI., The Influence of Soil Parameters on Cs-137 Uptake by Plants from Long-Term Fallout on Forest Clearings and Grasslands, Health Physics Journal, 46(5), p. 1083, May 1984.
- 21. Garner, J.,et aI., High Radiocesium Levels in Granite Outcrop Vegetation and Reductions Through Time, Health Physics Journal, 60(4), p. 533, April 1991.
- 22. McGee, E., et aI., The Variability in Fallout Content of Soils and Plants and the Design of Optimum Field Sampling Strategies, Health Physics Journal, 68(3), March 1995.
- 23. Consolidated Edison Company of New York, Safety Evaluation for Amendment #45 to Unit 1 Provisional Operating License, January 1996.
- 24. U.S Nuclear Regulatory Commission, Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, November 1979.
- 25. Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 617, June 2003.
- 26. Office of Environmental Management, Semi-Annual Report of theDepartment of Energy, Quality Assessment Program, EML 618, December 2003.
- 27. McFarland, R.C., et aI., The Counting Room: Special Edition, Radioactivity and Radiochemistry, Caretaker Publications, Atlanta, Georgia, 1994.
- 30. Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC"
- 31. Correspondence: J. M. Raimondi (AREVA) to A. D. Banavali (AREVA):
Low MDC Sr-90 Analysis (6/29/2010) 5-2
APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS
APPENDIX A Environmental media are sampled at the locations specified in Table A-1 and shown in Figures A-1, A-2, and A-3. The samples are analyzed according to criteria established in the ODCM. These requirements include: methods of sample collection; types of sample analysis; minimum sample size required; lower limit of detection, which must be attained for each medium, sample, or analysis type, and environmental concentrations requiring special reports. Table A-1 provides the sampling station number, location, sector, and distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2010 REMP. Three maps are provided to show the locations of REMP sampling. Figure A-1 shows the sampling locations within two miles of Indian Point. Figures A-2 and A-3 show the sampling locations within ten miles of Indian Point. The ODCM required lower limits of detection (LLD) for Indian Point sample analyses are presented in Table A-2. These required lower limits of detection are not the same as the lower limits of detection or critical levels actually achieved by the laboratory. The laboratory's lower limits of detection and critical levels must be equal to or lower than the required levels presented in Table A-2. Table A-3 provides the reporting level for radioactivity in various media. Sample results that exceed these levels and are due to plant operations require that a special report be submitted to the NRC. In addition to the sampling outlined in Table A-1, there is an environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables 8-21 and 8-22 for the milch animal and land use census. A-1
TABLE A*1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SAMPLE LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION Onsile - 3 DR8 Service Center Building Direct Gamma 0.35 Mi (SSE) at 158 0 A1 Onsite - 0.28 Mi (SW) at Air Particulate 4 Algonquin Gas Line A1 234 0 Radioiodine A4 Air Particulate Onsite - 0.88 Mi (SSW) 5 A4 NYU Tower Radioiodine at 208 0 DR10 Direct Gamma 7 Wb1 Camp Field Reservoir 3.4 Mi (NE) at 51 0 Drinking Water 0 8 ** Croton Reservoir 6.3 Mi (SE) at 124 Drinking Water Onsite - 9 Wa1 Plant Inlet (Hudson River Intake)" HRWater 0.16 Mi (W) at 273 0 Wa2 Onsite - HRWater 10 Discharge Canal (Mixing Zone)
** 0.3 Mi (WSW) at 249 0 HR Bottom Sediment Onsite -
14 DR7 Water Meter House Direct Gamma 0.3 Mi (SE) at 1330
** HR Aquatic Vegetation 17 ** Off Verplanck 1.5 Mi (SSW) at 202.5 0 HR Shoreline Soil
** HR Bottom Sediment Cortlandt Yacht Club 20 DR38 1.5 Mi (S) at 1800 Direct Gamma (AKA Montrose Marina)
** Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton* 20.7 Mi (N) at 35r Direct Gamma Ic3 Broad Leaf Vegetation
** Soil Ib2 Fish & Invertebrates 25 Ib1 Downstream Downstream Fish & Invertebrates
** Air Particulate 27 ** Croton Point 6.36 Mi (SSE) at 156 0 Radioiodine DR41 Direct Gamma
*" HR Shoreline Soil DR4 Direct Gamma 28 lent's Cove 0.45 Mi at 069" HR Bottom Sediment HR Aquatic \1I::;~':"<llIU'
** Air Particulate 0
29 ** Grassy Point 3.37 Mi (SSW) at 196 Radioiodine DR39 Direct Gamma
- Control
** :::: Locations listed do not have sample designation locations specified in the aDCM HR :::: Hudson River RlS:::: Reuter Stokes A-2
TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SAMPLE LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053 0 Direct Gamma Onsite - 34 DR9 South East Corner of Site Direct Gamma 0.52 Mi (S) at 179 0 Onsite - 35 DR5 Broadway & Bleakley Avenue Direct Gamma 0.37 Mi (E) at 092 0 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 0 Direct Gamma
** Precipitation 44 ** Peekskill Gas Holder Bldg 1.84 Mi (NE) at 052 0 Air Particulate
** Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 347" HR Shoreline Soil Wc1 HR Shoreline Soil 53 White Beach 0.92 Mi (SW) at 226 0 DR11 Direct Gamma 0
56 DR37 Verplanck - Broadway & 6th Street 1.25 Mi (SSW) at 202 Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005 0 Direct Gamma 0 58 DR17 Route 9D - Garrison 5.41 Mi (N) at 358 Direct Gamma 0 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 032 Direct Gamma Gallows Hill Road & Sprout Brook 60 DR18 5.02 Mi (NNE) at 029 0 Direct Gamma Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 052 0 Direct Gamma Westbrook Drive 62 DR19 5.03 Mi (NE) at 062 0 Direct Gamma (near the Community Center) Lincoln Road - Cortlandt 64 DR20 4.6 Mi (ENE) at 067" Direct Gamma (School Parking Lot) 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 083 0 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 114 0 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 127" Direct Gamma 0 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 188 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 203 0 Direct Gamma Willow Grove Road & Captain DR27 4.97 Mi at 226" Direct Gamma I Faldermeyel Drive ~ 75 DR1 DR31 Shore Drive South Palisades Parkway 1 Mi (WSW) at 252 0 4.65 Mi (NW) at 2250 Direct Direct Gamma 0 76 DR13 West Shore Drive - North 1.21 Mi (W) at 276 Direct Gamma 0 77 DR29 Palisades Parkway 4.15 Mi (W) at 272 Direct Gamma 0 78 DR14 Rt. 9W across from RlS #14 1.2 Mi (WNW) at 295 Direct Gamma
** =Locations listed do not have sample designation locations specified in the ODeM HR :::: Hudson River RfS:::: Reuter Stokes A-3
TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SAMPLE LOCATION DISTANCE SAMPLE TYPES STATION DESIGNATION 79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 296 0 Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 31r Direct Gamma 0 81 DR28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 310 Direct Gamma 82 DR16 Ayers Road 1.01 Mi (NNW) at 334 0 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 339 0 Direct Gamma
** HR Aquatic Vegetation 0
84 ** Cold Spring
- 10.88 Mi (N) at 356 HR Shoreline Soil
** HR Bottom Sediment 88 DR6 Reuter Stokes Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma Highland Ave & Sprout Brook Road 89 DR35 2.89 Mi (NNE) at 025 0 Direct Gamma (near rock cut) 90 DR3 Charles Point 0.88 Mi (NE) at 04r Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 149 0 Direct Gamma A2 Air Particulate A2 Onsite- 0.39 Mi (S) at Radioiodine 94 IPEC Training Center Ic2 193 0 Broad Leaf Vegetation
** Soil A3 Air Particulate A3 Onsite - Radioiodine 95 Meteorological Tower 0 Ic1 0.46 Mi (SSW) at 208 Broad Leaf Vegetation
** Soil 106 ** Lafarge Monitoring Well 0.63 mi SW Groundwater
- Control location
** =Locations listed do not have sample designation locations specified in the aDCM HR ::: Hudson River RlS::: Reuter Stokes A-4
FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point N
~
Rockland County
\lVestchester County 1 mile Verplanck .fJ lj Key:
le# - Sroadleaf Vegetation l:J. - VVatefborne Surface (HR) Wa#
<> HR Shoreline Soi! I/'Jc#
o - Direct Radiation Locahon DR# 101 Fish and Invertebl'ates AlrtJOrr10 A# available A-5
FIGURE A-2 SAMPLING LOCATIONS Greater than Two Miles from Indian Point N
~
111 @ Ic3 Orange county Putnam County Bear Bridae MOLlr1taln
~
Westchester County Smiles Rockland County Key. 103 &oad'eaf Vegetaton o . Waterb{)me l/'*lb# A-6
FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N Roscton (20 l ml Ora nge County 23 P
. ~
Putnam County Cold Spnng 1:1088 ml N) 84
'f' <> ..
8ear ?,Iountain 10 . . 28.'f' <> .. Westchester Indian POWlt County 17" 'f'
<>~---------4~
~G'N 106
\." 94:.
29
- _ _ _" 95.
Rockland County Hudson
- 8 dw' 27
- 1:;;lver 5 lililes Key: - - Air Particulate 8 f';>adIO!OOllie <> - HR ShOft;?hne Soi!
.. - Aquatic Vegetation * - Sod
. . - HR Bottom Sediment OW* ?>Jlonitonng We!l, SVVof p - PreClpltatlon Site Boundary
- Jw Water A-7
TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES I RADIONUCLIDE WATER I PARTIUCLATE AIRBORNE R FISH MILK FOOD PRODUCTS SOIL or SEDIMENT (PCi/m~ (pCi/kg. II ANALYSIS (pCI/l) I GASES wet) (pC ill) (pCilkg. wet) (pCi/kg. dry) Gross Beta 4 0.01 I H-3 2.000 (0) I Mn-54 15 130 Fe-59 30 260 Co-58 15 130 CO-50 15 130 Ni-63 (f) 30 100 Zn-65 30 260 Sr-gO (f) 1 5 5000 Zr-95 15 Nb-95 15 1-131 1 (0) 0.07 1 60 Cs-134 15 005 130 15 60 150 Cs-137 18 0.06 150 18 80 180 8a-140 15 15 La-140 15 15 A-8
TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES (a) This list does not mean that only these nuclides are to be considered Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported In the Annual Radiological Environmental Operating Report pursuant to Specrfication D 5,1. (b) Required detection capabilities for themlOluminescent dOSimeters used for environmental measurements are given in Regulatory Guide 4.13. (c) The llD is defined as the smallest concentration of radioactive material In a sample that \'..111 yield a net count, above system baCKground, that v.111 be detected with 95% prObability ,'11th only 5% probability of falsely conduding that a blank observation represents a "rea'" signal. It should be recognized that the llD is defined as an g plion (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit fOf a particular measurement. Analyses shall be performed in such a manner that the stated lLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nUClides, or other uncontrollable circumstances may render these llDs unachievable. In such cases, the contributing fadors shall be identltied and described in the Annual Radlological Environmental Operating Report pursuant to RECS D 5. i , (d) These LlDs are for drinking water samples, If no drinking water pathway exists, the llDs may be increased to 3,000 for H-3 and 15 for 1-131 (e) These required lower limits of detection are associated only with the REMP requirements, The Radiological Ground Water Monitoring Program may involve unique reporting level criteria. independent of the REMP, and defined in station procedures. (f) Sr-90 and Ni-63 are included in this table due to their historical presence in ground water and possible migration to the environment per References 45 and 46. A-9
TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE FOOD RADIONUCLIOE WATER FISH MILK PARTIUClATE OR PRODUCTS ANALYSIS (pC ilL) GASES IpCilm~) (pCiJl<g, wet) (pCiIl) (pCiikg, wet)
'"1-3 2C.000*
Mn-54 I,OCD 30.DOO Fe-5~ 430 10.000 co---ee 1.003 30.000 co-eo 300 10.000 Ni-e3 ... 20O :.C30 Zrl-65 300 :m.ooo Sr-QO ."w S' 40 ZH~5 400 Nb-95 4110 1-131 2* e.9 3 100 Cs-134 30 10 ~.CDD e*D I.DC,;) Cs-137 50 2D 2.000 70 2,000 93-140 200 300 La-'40 2::10 2DQ Values provided are for drinking wateer pamways. if no drinking wat'H palhway ee(i5ts. h'gheef values are; allowed. as fallows: H-3 3C.QCC* pCUL (This is 3 40 CFR 141 value) Sr-GD 7:2 pCVL 1-131 20pCilL The'S.;.> reporting levels an. assocj;m~d only with ttle REMP re-quirements. The Radio4ogical Ground Water Mon,tcrin'g Prograrr may involve unique reportirg level criteria. Independent clIne REM", and defined in sUtion pn:,,::.i'dures. Sr-90 and f',ti-tl:3 are ircluded in this table due ':0 lheir historical presence In ground water and possible migration to' the emtiror,ment, per References 45 and 4e. A-10
APPENDIX 8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS
SUMMARY
APPENDIX B 8.1 2010 Annual Radiological Environmental Monitoring Program Summary The results of the 2010 radiological environmental sampling program are presented in Tables 8-2 through 8-20. Table 8-2 is a summary table of the sample results for 2010. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8 (Reference 4), and NRC 8ranch Technical Position to Regulatory Guide 4.8 (Reference 14). In addition, the data obtained from the analysis of samples are provided in Tables 8-3 through 8-20. REMP samples were analyzed by various counting methods as appropriate. The methods are; gross beta, gamma spectroscopy analysis, liquid sCintillation, radiochemical analysis, and TLD processing. Gamma spectroscopy analysis was performed for the following radionuclides; 8e-7, K-40, Mn-54, Co-58, Co-60, Fe-59, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Cs-134, Cs-137, 8a/La-140, Ce-141, Ce-144, Ra-226 and AclTh-228. Radiochemical analyses were performed for 1-131, Ni-63 and Sr-90 for specific media and locations as required in the ODCM. 8.2 Land Use Census In accordance with Sections IP2-D3.5.2 and IP3-2.8 of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use census are presented in Tables 8-21 and 8-22, respectively. In lieu of identifying and sampling the nearest garden of greater than 50 m2 , at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table 8-14). 8.3 Sampling Deviations During 2010, environmental sampling was performed for 12 unique media types addressed in the ODCM and for direct radiation. A total of 1166 samples of 1178 scheduled were obtained. Of the scheduled samples, 99.0% were collected and analyzed for the program. Sampling deviations are summarized in Table B-1, discussions the reasons for the deviations are provided in Table a b c media. There were no analytical deviations in 2010. Note: in 2009, twenty-three suspect analyses for Sr-90 in fish resulted in incomplete results for this radionuclide. The vendor's method for analyzing the fish for Sr-gO was inadequate for the required sensitivity. Accordingly, the vendor 8-1
and the method of analysis were changed for 2010. All analyses for Sr-90 in 2010 fish were successfully performed and the required sensitivity was met. B.5 Special Reports No special reports were required under the REMP. B-2
TABLE B-1 Summary of Sampling Deviations - 2010 TOTAL REASON FOR NUMBER OF SAMPLING MEDIA SCHEDULED DEVIATION DEVIATIONS* EFFICIENCY % SAMPLES MEDIA PARTICULATES IN AIR 416 5 98.8% See Table B-1 a CHARCOAL FILTER 416 5 98.8% See Table B-1a TLD 164 1 99% See Table B-1b HUDSON RIVER WATER 32 1 97% See Table B-1c DRINKING WATER 32 0 100% N/A SHORELINE SOIL 10 0 100% N/A BROAD LEAF 100% N/A 58 0 VEGETATION FISH & INVERTEBRATES 24 0 100% N/A AQUATIC VEGETATION 5 0 100% N/A HUDSON RIVER BOTTOM 100% N/A 8 0 SEDIMENT SOIL 3 0 100% N/A PRECIPITATION 8 0 100% N/A IGROU SAMPLES TOTALS 1178 12 99.0'% TOTAL NUMBER OF SAMPLES COLLECTED 1166
- Samples not collected or unable to be analyzed.
B-3
TABLES B-1a I B-1b I B-1c TABLE B-1a 2010 Air Sampling Deviations STATION WEEK PROBLEM I ACTIONS TO PREVENT RECURRENCE Grassy Point 2 lost 145 hours from power interruption Grassy Point 12 lost 74 hours from power interruption Grassy Point 26 lost 65 hours from power interruption Grassy Point 33 lost 161 hours run time from power interruption Grassy Point 43 lost 158 hours; sample pump required replacement Algonquin 11 lost 141 hours due to sample pump failure Algonquin 12,13,14 lost weeks continuously from security fence modifications line cutting Algonquin 34 lost most of week from security fence modifications line cutting NYU Tower 9 lost 122 hours from GFCI trip Training Building 49 Filter media found mis-aligned when retrieved (bypassed) Roseton 9 lost 74 hours from trees falling on power lines Roseton 13 lost 95 hours; GFCI found tripped Roseton 29 lost 40 hours on integrator; sample was running at week's end Note: eight of thirteen could be analyzed; five could not be analyzed TABLE B-1b 2010 TlD Deviations STATIOK QUARTER PROBLEM I ACTIONS TO PREVENT RECURRENCE lent's Cove 3rd TlD was removed from holder; raise installation height TABLE B-1c 2010 Other Media Deviations STATION SAMPLE SCHEDULE eFtOBLEM I ACTIONS TO PREVENT RECURRENCE Surface Water; sample pump found de-energized, grab sample taken and Hudson River Discharge Week 47 pump re-energized 8-4
TABLE B*2 aDCM ANNUAL
SUMMARY
- 2010 LOCATION OF HIGHEST TYPE AND TOTAL , ANNUAl MEAN:
INDICATOR LOCATIONS: NUMBER OF MEDIUM (UNITS) NUMBER OF LOCATIONS AND CONTROL LLD (b) NON*ROUTINE SEE TABLE ANALYSIS '"~ DESIGNATION LOCATION: I "' REPORTS PERFORMED ~
" MEAN (a) " MEAN 'a) MEAN (a)
, RANGE ~
RANGE RANGE Palisades Parkway (Lake DIRECT RADIATION TLD Reads 14.1 (1591160) / Welch Exit) 4.96Mi 13.0 (414) 1 (mR I standard quarter) NJA 0 (WSW) at 310 0 163 10.3 - 21. 1 DR28 11.8 - 13.7 B-3 19.8 (414) 117.3 - 21. 1 AIR PARTICULA rES #29 Grassy Point 0.013 (359/364) 1 0.013 (52152) 1 AND RADIOIODINE G8 (4 11) 0.01 3.37 Mi (SSW) at 196° 0 0.001 - 0.032 0.002-0.027 (pCi/m' ) B-6 , 807. B-8 0.013 (52152) I 0.002-0.032 1-131 (411) 0.07 <Lc <Lc <Lc 0 GSA (32) 0.05 <Lc <Lc <Lc 0 Cs- 134 GSA (32) 0.06 <Lc <Lc <Lc 0 Cs-137 SURFACE HUDSON 428 (214) <Lc RIVER WATER (pCI/L) H-3 (8 ) 3000 (e) <Lc <Le 0 455 B-9, B-l0 GSA (24) Mn~4 15 <Lc <Le <Lc 0 Co-58 15 <Lc <Le <Lc 0 Fe-59 30 <Lc <:Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 Zn -65 30 <Lc <Lc <Lc 0 Zr/Nb-95 15 <Lc <Le <Lc 0
'-131 15 <Lc <Lc <Lc 0 Cs-l34 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 Ba/La-140 15 <Lc <Lc <Lc 0 (a) Positive values above Lc; Groundwater above MDe (b) Requi red a priori LLD; sec Table A-2 (c) Not a dri nking water pathway; the required LLD is 3000 pCi/L 8-5
TABLE B-2 ODCM ANNUAL
SUMMARY
- 2010 LOCATION OF HIGHEST TYPE AND TOTAL ANNUAL MEAN:
INDICATOR LOCATIONS: NUMBER OF MEDIUM (UNITS) NUMBER OF I"OCATIONS AND CONTROL LLD (b) .. NON-ROUTINE SEE TABLE ANALYSIS DESIGNATION LOCATION: REPORTS PERFORMED MEAN (a) MEAN (a) MEAN (al I RAN.GE RANGE RANGE DRINKING WATER (8) 2000 <Lc <Lc N/A 0 (pCi/L) 8-11, 8-12 GSA (24) Mn-54 15 <Lc <Lc N/A 0 Co-58 15 <Lc <Lc N/A 0 Fe-59 30 <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Zn-65 30 <Lc <Lc N/A 0 Zr/Nb-95 15 <Lc <Lc N/A 0 31 15 <Lc <Lc N/A 0 Cs-134 15 <Lc <Lc N/A 0 37 18 <Lc <Lc N/A 0 Ba/La-140 15 <Lc <Lc N/A 0 HUDSON RIVER SHORELINE SOIL G5.1\(10) (pCilkg - dry) 8-13 Cs-134 150 <Lc <Lc <Lc 0
#17 Off Verplanck #50 Manitou Inlet 154 (2/8) 1 Cs-137 180 1.5 Mi (SSW) at 202S 63 (114) 1 0
<L c - 173 154 (212) 1 134 - 173 <L c - 63 Sr-90 (10) 5000 <Lc <Lc <Lc 0 LLD is 3000 pOlL 8-6
TABLE B-2 ODCM ANNUAL
SUMMARY
- 2010
' LOCATION .OF HIGHEST TYPE AND TOTAL ANNUAL MEAN:
MEDIUM (UNITS) INDICATOR LOcATIONS: NUMBER OF NUMBER OF I"OCATIONSAND CONTROL LLO (b) NON-ROUTINE SEE TABLE ANALYSIS DESIGNAnON LOCATION: REPORTS PERFORMED MEAN (a) MEAN (a) MEAN (a) RANGE RANGE RANGE BROAD LEAF VEGETATION GSA (58) (pCi/kg - wet) B-14 31 60 <Lc <Lc <Lc 0 Co-60 N/A <Lc <Lc <Lc 0 34 60 <Lc <Lc <Lc 0
#95 Meteorological Tower 31(1137) 1 0.46 Mi (SSW) at 208*
37 80 <Lc 0
<L c - 31 31(1116) 1
<L c - 31 FISH AND iNVERTEBRATES GSA (24)
(pCi/kg - wet) B-15 Mn-54 130 <Lc <Lc <Lc 0 Co-58 130 <Lc <Lc <Lc 0 Fe-59 260 <Lc <Lc <Lc 0 Ni-53 (24) 100 <Lc <Lc <Lc 0 Co-50 130 <Lc <Lc <Lc 0 Zn-65 260 <Lc <Lc <Lc 0 34 130 <Lc <Lc <Lc 0 37 150 <Lc <Lc <Lc 0 Sr-90 (24) 5 <Lc <Lc <Lc 0 AQUATIC GSAl5} VEGETATION (pCi/kg - WET) B-16 Co-60 NONE <Lc <Lc <Lc 0 1-131 NONE <Lc <Lc <Lc 0 34 NONE <Lc <Lc <Lc 0
#84 Cold Spring
#28 Lents Cove 0 10.88 Mi (N) at 356 Cs-137 NONE 17.6 (114)/ <Lc -17.6 o .45 Mi (ENE) at 069 0 16.8 (1/2) 1 <L c -
0 17.6 (112) 1 <L c - 17.6 16.8 LLD is 3000 pCi/L 8-7
TABLE B-2 ODCM ANNUAL
SUMMARY
- 2010 LOCATION OF HIGHEST TYPE AND TOTAL ANNUAL MEAN:
IN.DICATOR LOCATIONS: NUMBER OF MEDIUM (UNITS) NUMBER OF LOCATIQNS AND CONTROL LLD (b) NON-ROUTINE SEE TABLE ANALYSIS DESIGNATION LOCATION: REPORTS PERFORMED MEAN Cal MEAN {a} MEAN (a) RANGE .RANGE RANGE BOTTOM SEDIMENT GSA/8) (pCI/kg - DRY) B-17 Co-60 NONE <Lc <Lc <Lc 0 34 150 <Lc <Lc <Lc 0
#10 Discharge Canal 0,3 553 (516) /
37 180 MiWSW 874 (212) / 418- <Lc 0
<Lc - 1330 1330 PRECIPITATION GSA(8)
(pCi/L) B-18 (8) 3000 (c) <Lc <Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 34 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 SOIL (pCi/kg - DRY) B-19 Co-60 NONE <Lc <Lc <Lc 0 34 150 <Lc <Lc <Lc 0 Cs-137 180 <Lc <Lc <Lc 0 GROUNDWATER I GSA(2) (pCilL) 8-20 (2) 3000 (c) <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Ni-63 (2) 30 <Lc <Lc N/A 0 Cs-137 18 <Lc <Lc N/A 0 Sr-90 (2) 1 <Lc <Lc N/A 0 LLD is 3000 pOlL 8-8
TABLE B-3 2010 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER) Station 10 Sector 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Mean Yearly DR-01 N 13.54 +/- 0.44 15.57 +/- 0.63 15.80 +/- 0.76 15.94 +/- 1.16 15.2 60.9 DR-02 NNE 13.73 +/- 0.70 14.15 +/- 0.66 16.08 +/- 0.47 14.63 +/- 1.00 14.6 58.6 DR-03 NE 11.14 +/- 0.50 11.70 +/- 0.40 13.12 +/- 0.66 11.80 +/- 0.95 11.9 47.8 DR-04 ENE 12.50 +/- 0.46 13.62 +/- 0.57 0.00
- 0.00 13.48 +/- 1.19 13.2 52.8 DR-OS ENE 13.32 +/- 0.47 14.03 +/- 0.57 15.29 +/- 0.56 13.62 +/- 1.07 14.1 56.3 DR-06 ESE 13.57 +/- 0.48 13.95 +/- 0.66 15.71 +/- 0.75 14.35 +/- 1.07 14.4 57.6 DR-07 SE 14.96 +/- 0.54 15.79 +/- 0.76 17.26 +/- 0.75 16.19 +/- 1.30 16.1 64.2 DR-08 SSE 11.14 +/- 0.31 11.69 +/- 0.50 12.55 +/- 0.72 11.19 +/- 1.17 11.6 46.6 DR-09 S 12.33 +/- 0.45 12.48 +/- 0.50 13.72 +/- 0.66 13.13 +/- 0.97 12.9 51.7 DR-10 SSW 13.22 +/- 0.51 14.88 +/- 0.47 15.38 +/- 0.52 14.09 +/- 1.07 14.4 57.6 DR-11 SW 10.34 +/- 0.51 10.69 +/- 0.50 12.06 +/- 0.62 10.46 +/- 1.07 10.9 43.6 DR-12 WSW 14.52 +/- 0.74 15.69 +/- 0.59 15.46 +/- 0.72 16.22 +/- 1.49 15.5 61.9 DR-13 WSW 18.38 +/- 0.64 17.44 +/- 0.68 17.18 +/- 0.80 17.62 +/- 1.26 17.7 70.6 DR-14 WNW 11.88 +/- 0.66 14.27 +/- 0.73 13.60 +/- 0.57 14.39 +/- 1.24 13.5 54.1 DR-15 NW 11.97 +/- 0.56 13.92 +/- 0.76 14.11 +/- 0.78 14.05 +/- 1.13 13.5 54.1 DR-16 NNW 13.38 +/- 0.68 15.08 +/- 0.48 14.91 +/- 0.61 14.98 +/- 1.28 14.6 58.4 DR-17 N 13.23 +/- 0.40 15.94 +/- 0.81 14.77 +/- 0.54 15.30 +/- 1.07 14.8 59.2 DR-18 NNE 14.04 +/- 0.59 14.71 +/- 0.68 15.78 +/- 0.51 14.56 +/- 0.99 14.8 59.1 DR-19 NE 13.89 +/- 0.42 15.20 +/- 0.66 16.55 +/- 0.48 14.51 +/- 1.16 15.0 60.2 DR-20 ENE 12.28 +/- 0.39 13.23 +/- 0.48 14.46 +/- 0.57 13.07 +/- 1.11 13.3 53.0 DR-21 E 13.15 +/- 0.60 14.33 +/- 0.59 15.62 +/- 0.88 14.15 +/- 1.07 14.3 57.3 DR-22 ESE 10.36 +/- 0.48 11.22 +/- 0.41 12.57 +/- 0.76 11.00 +/- 0.82 11.3 45.2 DR-23 SE 12.73 +/- 0.49 14.04 +/- 0.64 15.44 +/- 0.76 13.61 +/- 1.00 14.0 55.8 DR-24 SSE 13.69 +/- 0.63 14.65 +/- 0.64 15.48 +/- 0.63 13.96 +/- 1.00 14.4 57.8 DR-25 S 11.25 +/- 0.45 12.59 +/- 0.75 12.16 +/- 0.42 12.29 +/- 0.96 12.1 48.3 DR-26 SSW 12.91 +/- 0.37 14.84 +/- 0.67 13.86 +/- 0.84 14.73 +/- 1.24 14.1 56.3 DR-27 SW 12.25 +/- 0.54 14.10 +/- 0.67 13.40 +/- 0.59 14.36 +/- 1.15 13.5 54.1 DR-28 NW 17.26 +/- 0.63 20.42 +/- 0.73 20.31 +/- 0.71 21.07 +/- 1.64 19.8 79.1 DR-29 W 12.28 +/- 0.72 14.69 +/- 0.73 14.54 +/- 0.50 14.96 +/- 1.12 14.1 56.5 DR-30 SNS 12.64 +/- 0.44 15.68 +/- 0.72 14.38 +/- 0.76 14.20 +/- 1.31 14.2 56.9 DR-31 WSW 14.93 +/- 0.56 16.72 +/- 0.58 16.86 +/- 0.52 16.89 +/- 1.38 16.4 65.4 DR-32 NNW 11.61 +/- 0.71 13.20 +/- 0.53 12.94 +/- 0.51 13.48 +/- 1.03 12.8 51.2 DR-33 NE 12.99 +/- 0.41 12.81 +/- 0.48 14.94 +/- 1.05 13.23 +/- 1.05 13.5 54.0 DR-34 SE 11.86 +/- 0.43 12.64 +/- 0.56 13.77 +/- 0.51 12.17 +/- 1.15 12.6 50.4 DR-35 NNE 2.56 +/- 0.57 3.1 +/- 0.59 14.25 +/- 0.69 12.24 +/- 0.94 13.0 52.2 DR-36 NE 14.99 +/- 14.48 +/- 0.52 15.65 +/- 0.57 14.53 +/- .41 14.9 59]
DR-37 SSW 3.41 +/- 14.33 +/- 0.90 5.38 +/- 0.69 3.86 +/- 4.2 DR-3S S .43 +/- 12.83 +/- .0 3.55 +/- 0.51 .50 +/- 0.89 12.3 49.3 DR-39 SSW 4.05 +/- 0.53 15.63 +/- 0.64 15.75 +/- 0.67 6.26 +/- 1 7 5.4 61 DR-40** N 13.30 +/- 0.42 13.72 +/- 0.55 11.78 +/- 0.70 13.13 +/- 1.19 13.0 51.9 DR-41 SSE 12.12 +/- 0.56 13.05 +/- 0.61 13.95 +/- 0.69 12.32 +/- 1.03 12.9 51.4 AVERAGE 13.0 14.2 14.5 14.1 14.0 56.2
- Data not available
- Control Location 8-9
TABLE B-4 DIRECT RADIATION, 2000 THROUGH 2010 DATA (mR per Standard Quarter Basis) Standard Minimum Mean Maximum Value Station 10 Deviation Value 2010 Mean (2000-2009) (2000-2009) (2000-2009) (2000-2009) DR-01 62.4 2.8 58.4 68.0 60.9 DR-02 58.6 2.9 53.6 64.8 58.6 DR-03 47.7 1.8 44.0 50.0 47.8 DR-04 54.2 3.5 46.8 58.8 52.8 DR-05 54.2 2.3 48.4 56.8 56.3 DR-06 54.1 3.2 46.4 57.6 57.6 DR-07 63.8 3.6 55.6 68.8 64.2 DR-08 51.1 2.8 47.2 56.4 46.6 DR-09 53.3 2.8 47.2 58.0 51.7 DR-10 56.9 2.2 53.2 60.0 57.6 DR-11 44.4 2.0 40.8 47.2 43.6 DR-12 66.5 4.2 60.8 76.0 61.9 DR-13 76.1 4.0 68.0 82.0 70.6 DR-14 53.2 1.9 50.0 56.0 54.1 DR-15 52.9 3.1 46.4 57.6 54.1 DR-16 58.6 2.1 55.2 61.6 58.4 DR-17 59.8 3.2 56.4 66.8 59.2 DR-18 56.6 2.2 52.4 58.8 59.1 DR-19 59.4 2.3 55.2 61.6 60.2 DR-20 53.5 3.1 47.6 58.8 53.0 DR-21 54.6 2.3 50.0 57.6 57.3 DR-22 45.6 2.8 40.4 50.8 45.2 DR-23 55.5 2.6 49.6 58.8 55.8 DR-24 56.8 3.0 49.2 60.0 57.8 DR-25 49.4 2.2 44.8 52.8 48.3 DR-26 55.2 2.4 50.4 58.8 56.3 DR-27 54.2 3.2 46.8 59.2 54.1 DR-28 69.0 9.0 57.2 78.8 79.1 DR-29 61.8 7.1 54.8 73.6 56.5 DR-30 60.8 4.9 52.4 68.0 56.9 DR-31 69.2 4.8 62.0 78.4 65.4 DR-32 52.2 3.0 46.0 57.2 51.2 DR-33 48.1 9.4 34.0 55.2 54.0 DR-34 52.4 4.6 43.2 60.8 50.4 DR-35 552 3.4 48.8 52.2 DR-36 52.4 65.6 59.7 DR-37 54.5 2.9 48.8 58.8 57.0 DR-38 52.3 3.3 48.0 58.4 49.3 DR-39 61.2 3.4 55.2 66.0 61.7 DR-40** 63.7 6.4 54.8 75.2 51.9 DR-41 51.4 3.2 44.4 55.2 51.4 Average 56.4 50.4 61.8 56.2
- Control Location B-10
TABLE B-5 2010 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter Basis) Inner Ring Outer Ring Inner Ring Outer Ring Sector 10 10 Annual Average Annual Average DR-01 DR-17 N 60.9 59.2 DR-02 DR-18 NNE 58.6 59.1 DR-03 DR-19 NE 47.8 60.2 DR-04 DR-20 ENE 52.8 53.0 DR-05 DR-21 E 56.3 57.3 DR-06 DR-22 ESE 57.6 45.2 DR-07 DR-23 SE 64.2 55.8 DR-08 DR-24 SSE 46.6 57.8 DR-09 DR-25 S 51.7 48.3 DR-10 DR-26 SSW 57.6 56.3 DR-11 DR-27 SW 43.6 54.1 DR-12 DR-28 WSW 61.9 79.1 DR-13 DR-29 W 70.6 56.5 DR-14 DR-30 WNW 54.1 56.9 DR-15 DR-31 NW 54.1 65.4 DR-16 DR-32 NNW 58.4 51.2 Average 56.0 57.2 B-11
TABLE B-6 IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2010 3 GROSS BET A ACTIVITY pCiI m +/- 1 Sigma SAMPLE STATION # Week Week 5 94 95 23** 27 29 44 Number Date 1 1/4/2010 0.008 +/- 0001 0.013 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- O'()OI 0.015 +/- 0.001 2 1/12!2010 0.007 0.001 0.005 +/- 0.001 0.005 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.001 0.005 +/- 0.001 0.004 +/- 0.001 3 1119/2010 0.018 +/- 0.001 0.023 +/- 0.002 0.018 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 om 8 +/- 0.00 I 0.017 +/- 0.001 0.017 +/- 0.001 4 1!26!2010 0.012 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 5 2/2/20 I 0 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.006 +/- 0.003 0.013 +/- 0.001 6 2/9/2(l10 0.013 +/- 0.001 0.(l13 +/- 0.001 0.013 +/- 0.001 (l.013 +/- 0.001 0.013 +/- 0.00 I 0.015 +/- 0.001 O.(l12 +/- 0.001 0.011 +/- 0.001 7 2116/2010 (UlII +/- 0001 0.008 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 8 2/23/2010 0.005 +/- 0001 0.004 +/- 0.001 0.004 +/- 0.001 0.005 +/- 0.001 0.003 +/- 0.001 0.004 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 9 31212010 0.002 .+/- O.(){) 1 -{).{)01 +/- 0.001 0.001 +/- 0.001 0.003 +/- 0.001 0.000 +/- 0.001 0.002 +/- 0.001 0.002 +/- 0.000 0.002 +/- 0.001 10 3/8/2010 0.013 .T 0.001 0.013 +/- 0.001 0.017 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 11 3!J 5/2010 0.023 .T. 0.005 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0'()01 0.016 +/- 0.001 0'()]6 +/- 0.001 0016 +/- 0.001 12 3123/2010 no data 0.016 +/- 0.001 0.019 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.018 +/- 0.001 0.012 +/- 0.001 0.017 +/- 0.001 13 3!30/2010 110 data 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.008 +/- 0.002 0.012 +/- 0.001 0.014 :l- 0.001 0.015 +/- 0.001 14 4!5/2010 no data 0.004 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.004 :t 0.001 0.004 +/- 0.001 IS 411212010 0.0 I 0 +/- 0.002 0.014 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 16 412012010 0.010 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 17 4/26/201 () O.OJO +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.01 I +/- 0.001 0.011 +/- 0.001 0.015 +/- O.OOl 18 5/4/2010 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 19 511112010 0.008 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 om I +/- 0.00 I 0.010 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 20 511712010 0.010 +/- 0001 0.009 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 21 5!24/2010 0.008 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 22 611/2010 0.011 +/- 0001 0.009 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 23 61712010 O.OI! +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.012 :1: O.OO! 24 611 4/20 Hl 0.007 +/- OJ)OI 0.009 +/- 0.001 0.008 +/- 0.001 0.006 +/- 0.00 I 0.005 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 25 6/21/2010 O'(1I0 +/- O.OOl 0.011 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0001 0.010 +/- O.OOl 26 6/28/2010 0.012 +/- O.OOl 0.012 +/- 0.001
~---
0.015 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001
** location 8-12
TABLE B-6 (Continued) IPEe KNVIRONMKNTAL AIRBORNE PARTICULA TK SAMPLES - 2010 GROSS BET A ACTIVITY pCiI m3 +/- I Sigma SAMPLE STATION # Week Week 4 5 94 95 23** 27 29 44 Number Date 27 7/6/2010 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0,013 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0,001 0,014 +/- 0.001 0,015 +/-. 0,001 i 28 7/12/2010 0.020 +/- 0.002 0.019 +/- 0.002 0.022 +/- 0,002 0,018 +/- 0,001 0,021 +/- 0,002 0.Q20 +/- 0,002 0.Q18 +/- 0,001 0.019 +/- 0,002 29 711912010 0,016 +/- 0,001 0.015 +/- 0.001 0.014 +/- 0,001 0.015 +/- 0,001 0,014 +/- 0,002 0,012 +/- 0,001 0.014 +/- 0,001 0,015 +/- 0.001 30 7126/2010 0016 +/- 0,001 0,016 +/- 0.001 0,015 +/- 0.001 0,015 +/- 0,001 0.014 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0,013 +/- 0,001 31 8/2/2010 0,015 +/- 0,001 0,013 +/- 0,001 0.015 +/- 0,001 0,013 +/- 0.001 0.014 +/- 0,001 0.015 +/- 0,001 0,014 +/- 0,001 0.015 +/- 0,001 32 8/9/2010 0,018 .+/- 0,001 0,015 +/- 0.001 0,017 +/- 0.001 0'(J18 +/- 0,001 0.018 +/- 0,001 0.017 +/- 0,001 0.019 +/- 0.001 0,016 +/- 0,001, 33 8/16/2010 0.026 +/- 0.003 0,021 +/- 0.002 0.016 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0,015 +/- 0,001 0.032 +/- 0.0 IS 0,018 +/- 0,001 34 8/2312010 no data 0.019 +/- 0,001 0,017 +/- 0.001 0,020 +/- 0.001 0,018 +/- 0.001 0,017 +/- 0.001 0.019 +/- 0.001 0.015 +/- O.OOl 35 8/30!20!O (l,008 +/- 0,001 0.005 +/- 0,001 0,009 +/- 0.001 0.009 +/- 0,001 0.009 +/- 0.001 0,007 +/- 0,001 0,009 +/- 0,001 0,008 +/- 0,001 36 91712010 0026 +/- 0,002 0,029 +/- 0,002 0.027 +/- 0.002 0,028 +/- 0,001 0.032 +/- 0.002 0,029 +/- 0,002 0,025 +/- 0,00 I 0,027 +/- 0,002 37 9/13/2010 0,010 +/- 0,001 0.010 +/- 0.001 0,011 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0,001 0,006 +/- 0,001 0,011 +/- 0,001 0,008 +/- 0,001 38 9120/2010 0.009 +/- 0,001 0,011 +/- 0,001 0.012 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0,009 +/- 0,001 0,012 +/- 0,001 0,009 +/- 0001 39 9127/2010 0,017 +/- 0,001 0.Q18 +/- 0.001 0,021 +/- 0,001 0.020 +/- 0.001 0.020 +/- 0,001 0,019 +/- 0,001 0,017 +/- 0.001 0,016 +/- 0,001 40 10/4/2010 0 . 005 +/- 0,001 0,005 +/- 0.001 0,005 +/- 0,001 0,005 +/- 0.001 0,004 +/- 0,001 0.006 +/- 0,001 0,005 +/- 0,001 O,005!: 0,001 41 1011212010 OJllO +/- 0,001 0.Q11 +/- 0001 0,010 +/- 0,001 O.QlI +/- 0.001 0,012 +/- 0,001 0.012 +/- 0,001 0,012 +/- 0,001 0,011 1: O'()Ol 42 10118/2010 0,007 +/- 0.001 0.007 +/- 0,001 0.006 +/- 0,001 0,007 +/- 0,001 0.006 +/- 0,001 0.008 +/- 0,001 0.009 +/- 0,001 0.005 +/- 0,001 43 10/25/2010 0,015 +/- 0.001 0.015 +/- 0,001 0,011 +/- 0.001 0.014 +/- 0.001 0.013 :t 0,001 0,012 +/- 0.001 0.016 +/- 0,009 0,014 +/- 0,001 44 11/1/2010 0,007 +/- 0,001 0.011 +/- 0,001 0,008 +/- 0.001 0.009 +/- 0,001 0,009 +/- 0.001 0,008 +/- 0,001 0,011 +/-. 0,001 0,012 +/- 0,001 45 11/8/2010 0,005 +/- 0,001 0.005 +/- 0,001 0.004 +/- 0.001 0.005 +/- 0,001 0.003 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0,001 0,005 +/- 0,001 46 IJ 115/201 0 0,013 +/- 0,001 0.012 +/- 0,001 0,013 +/- 0.001 0,013 +/- 0,001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.013 +/- O,OOl 47 11122/2010 O,Ol7 +/- 0.001 0,013 +/- 0.001 0.015 +/- 0,001 0.Q18 +/- 0.001 0.014 +/- 0.001 0,015 +/- 0,001 0,017 +/- 0,001 0,015 +/- 0,001 48 11/29/2010 0021 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0,019 +/- 0,001 0.019 +/- 0,001 0.019 +/- 0.001 O,021t O,OOl 0.Ql8 +/- 0,001 49 12/6/2010 0,009 +/- 0,001 0,010 +/- 0.001 no data 0,010 +/- 0.001 0,006 +/- 0,001 0.008 +/- 0,001 0,008 +/- 0.001 0.009 +/- 0,001 50 1211312010 0,007 :l 0,001 0.009 +/- 0,001 0.009 :t: 0.001 0.010 +/- 0,001 0,007 +/- 0.001 0,008 +/- 0,001 0,009 +/- 0,001 0.009 +/- 0,001 51 12/2012010 0,013 -+/- 0,001 0.014 +/- 0.001 0.012 +/- 0,001 0,016 +/- 0.001 0,013 +/- 0,001 0.013 +/- 0.001 0,014 +/- 0,001 0,01 I +/- 0,001 52 12/27120' 0,004 +/- 0,001 0,006 +/- 0,001 0,006 +/- 0.001 0.004 +/- 0.001 0,005 +/- 0,001 0.006 +/- 0.001 0,006 +/- 0,001 0,007 +/- 0,001 sample location 8-13
TABLE B-7 CONCENTRATIONS OF GAMMA EMlTIERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2010 Results in Units of 10E-3 pCil ni +/- 1 Sigma
~~ -.. ~- -~....-- .. --- .. - -- - --- ----
Nuclide AlgonqUin NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 121 H- 13.5 98.7 +1- 11.8 98.9 +1- 11.0 114.8 +1- 13.0 110.4 +/- 14.1 131.1 +1- 12.0 121.7 +!- 133 C5-134 0.9 < 05 < 0.6 < 1.0 <L2 < 0.8 08 Cs-137 < 0.4 < 0.6 < OJ < 02 < 0.6 < 0.2 <' 0.6 Zr-95 1.4 < 0.7 < 0.9 < 2.1 < 2.9 0.6 L2 Nb-95 1.4 < 0.9 < 0.8 < 0.7 < 1.5 l.l < I I Co-58 < 0.8 < 0.6 < 0.5 < 0.7 < L5 < 0.7 0.4 Mn-54 0.4 < 0,6 < 0.6 < 0.8 < 0.9 0.2 0,7 Zn-65 .2 < 1.2 < LI <13 < 2.8 < L5 < 0,9 Co-60 0.7 < 0,9 < OA < 0.7 < 0,5 O.S OA K-40 8,5 4,2 < 4.6 < SA 44,6 +/- 9.5 57.6 +1- 11.2 < 3.3 4.9
- Control Sample
...,._'"-- ~- ~"""'~"---"""',"",
Nuclide Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 13e-7 +/- 14.2 149.2 +1- 15.6 145.8 +1- 15.5 163.4 +1- 14.4 119.9 +1- 138 122.5 +1- IIA !O3,7 +1- 12.6 Cs*134 0.7 < 1.0 < 0.8 < 0.5 < 0.9 < 0.5 0.7 C5-137 06 < 0.7 < 0.7 < OA < 0,6 02 0.5 Zr-95 < 12 < 12 < 23 < 23 < L5 < 1l 12 Nb-95 12 < 1.2 < 2.1 < 1.6 <\.2 1.0 1.4 Co-58 0.7 < 1.0 < 0.8 < 0.6 < 0,8 OJ " 0,5 Mil-54 OJ < 05 < 0,5 < 0.6 < 0.6 < 0.5 OA Zn-65 1.4 < 2.6 < 1.9 < 1.8 < 1.0 IA 1.7 Co-60 0.6 < 0.6 < Ll < 0.8 < 0.7 < 0.4 OS K-40 5.6 < 6A <1.3 50,6 +1- 9.6 < 3.9 5,7 " 5.2
- Control Sample 8-14
TABLE B-7 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2010 Results in Units of 10E-3 pCiJ nf +/- 1 Sigma
..... LS. * * &.JL ....... &.> &-'_'-'~"'a._ ....... ...,.a-....
Nuclide Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 14.0 145.1 +1- 14.1 135.4 +1- 13.0 106.2 +1- 12.7 136.1 +1- 15.0 123.4 +1- 138 145.1 15.0 Cs-134 < 0.6 < 0.6 < 0.6 < 1.0 < 0.8 O.H Cs-137 < 0.3 < 0.2 < 0.4 < 0.5 < 0.6 0.9 Zr-95 < 1.0 < 0.7 < 0.7 < 2.2 < 1.5 l.7 Nb-95 < 1.0 < 0.5 < 1.1 < 1.2 1.5 1.6 Co-58 < OJ < 0.4 < 0.4 < 1.0 0.7 l.l Mn-54 < 0.4 < 0.6 < 0.3 < 0.7 0.7 08 Zn-65 < 14 < 1.6 < L2 < l.l 2.3 20 Co-60 < 0.4 < 0.5 < 0.5 < 0.9 < 0.6 0.5 K-40 10.4 < 6.4 < 6.9 < 4.6 < 12.8 SI.0 +1- 9.8 33.7 9.3
- Control Sample
............... _ ..... &...<............... ~ ..... ~ .......... ' ....
Nuclide Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 12.0 72.7 +1- 11.4 61.1 +1- ILl 93.2 +1- 10.7 50.4 +1- 90 82.3 +1- 9.9 94.2 +1- 12.0 C5-134 < 0.8 < 0.9 < 0.5 < 0.5 < 0.9 1.0 C5-137 OS < 0.6 < 0.7 < 0.6 < 0.3 03 07 Zr-95 15 < 1.5 < 0.7 < 0.8 < 1.1 1.6 2.6 Nb-95 14 < 1.8 < Ll < 0.9 < 1.1 l.3 < 0.7 Co-58 08 < Ll < 0.7 < 0.8 < 0.4 < O.S 1.0 Mn-54 07 < 0.6 < 0.6 < 0.6 < 0.3 0.4 0.6 Zn-65 1.4 < 2.3 < 1.2 < 0.7 < 0.9 2.0 l.l Co-60 0.8 < 0.7 < 0.4 < 0.4 < 0.4 0.7 < 1.0 K-40 5.8 48.9 +/- 9.8 < 6.6 < 4.1 < 4.8 < 8.5 68.8 +/- 12.7
- Control Sample B-15
TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2010 3 1-131 ACTIVITY pCi/ m +/- 1 Sigma SAMPLE STATION # Week End 4 5 94 95 23** 27 29 44 Number Date
< 0.023 < 0.037 < 0.033 < 0.020 < O.oJ5 < 0.Q31 < 0.019 0.029 2 0 < 0.018 < 0.017 < 0.025 < 0.018 < 0.017 < 0.015 < 0.014 0.020 9110 < 0.022 < 0.018 < 0.025 < 0.018 < 0.024 < 0.020 0.021 0.020 4 < 0.017 < 0.015 < 0.017 < 0.015 < 0.019 < 0.017 < 0.027 0.025 5 < 0.020 < 0.016 < O.O2l < 0.020 < 0.021 < 0.020 < 0.065 < 0.031 6 < O.O2l < 0.017 < 0.021 < O.oJ 7 < 0.023 < 0.0\8 < 0.014 0.012
< O.oJ 5 < 0.017 < O.oI8 < O'(Jl 9 < 0.028 < 0.0]5 < 0.022 0.026 8 < 0.021 < 0.018 < 0.020 < 0.014 < 0.026 < 0.017 < 0.031 0.037 9 < 0.026 < 0.061 < 0.023 < 0.015 < 0.035 < 0.028 0.017 0.021
< 0.028 < 0.033 < 0.019 < 0.018 < 0.022 < 0.020 < 0.023 < 0.028
< 0.062 < 0.022 < 0.029 < 0.028 < 0.034 < 0.020 0.016 0.016 no data < 0.030 < 0.017 < 0.025 < 0.026 < 0.017 < 0.056 O.()34 3 no data < 0.023 < 0.020 < 0.021 < 0.057 < 0.019 < 0.030 0.Q38 4 no data < 0.026 < 0.027 < 0.025 < 0.035 < 0.024 0.021 0.021 5 0 0.049 < 0.027 < 0.013 < 0.031 < 0.028 < 0.021 < 0.015 0.023 16 0 < 0.036 < 0.020 < 0.017 < 0.030 < 0.034 < 0.014 < 0.028 < 0.()34 0 < 0.032 < 0.024 < 0.024 < 0.022 < 0.022 < 0.027 0.046 0.023 8 0 < 0.039 < 0.020 < 0.022 < 0.025 < 0.027 < 0.032 < 0.022 0.035 9 1110 < 0.029 < 0.033 < 0.036 < 0.025 < 0.027 < 0.034 < 0.025 0.041 20 0 < 0.016 < 0.005 < 0.037 < 0.015 < 0.020 < 0.028 < 0.019 < 0.036
< O.oJ 8 < 0.019 < 0.025 < 0.023 < 0.021 < 0,016 < 0.016 < 0.017 22 < 0.016 < O.oJ 5 < 0.021 < 0.015 < 0.021 < 0.027 0.022 < 0.023 23 < 0.013 < 0.020 < 0.033 < 0.030 < 0.029 < 0.022 < 0.010 0.028 24 < 0.035 < 0.028 < 0.033 < O.Q35 < 0.027 < 0.020 0.025 0.022 25 < 0.024 < 0.021 < 0.024 < 0.027 < 0.029 < 0.018 < 0.014 0.025 26 < 0.022 < 0.032 < 0.018 < 0.020 < 0.026 < 0.021 < 0'()20 < 0.034
** Control sample location 8-16
TABLE B-8 (continued) IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2010 3 1-131 ACTIVITY pCi! m +/- 1 Sigma SAMPLE STATION # Week Week End 4 5 94 95 23** 27 29 44 Number 27 < 0.027 < 0.017 < 0.025 < 0.032 < 0.030 < 0.015 < 0.025 0.030 28 < 0.044 < 0.039 < 0.033 < 0.026 < 0.032 < 0.037 < 0.025 0.033 29 < 0.029 < 0.016 < 0.020 < 0.024 < 0.037 < 0.018 0.017 0.023 30 < 0.021 < 0.Qi8 < 0.029 < 0.026 < 0.Q21 < 0'()28 < 0.017 0.020 31 < 0.016 < 0.024 < 0.034 < 0.026 < 0.023 < 0.017 0.010 0.024 32 < 0.013 < 0.022 < 0.027 < 0.023 < 0.016 < 0.020 < 0.015 < 0.022 33 < 0.045 < 0.031 < 0.020 < 0.033 < 0.039 < 0.035 < 0.244 0.021 34 no data < 0.019 < 0.027 < 0.021 < 0.021 < 0.026 0.018 0.025 35 < 0.019 < 0.016 < 0.031 < 0.023 < 0.025 < 0.013 < 0.014 < 0.018 36 < 0.034 < 0.019 < 0.024 < 0.030 < 0.018 < 0.031 0.024 0.032 37 < 0.026 < 0.025 < 0.025 < 0.031 < 0.024 < 0.017 < 0.017 < 0.022 38 < 0.025 < 0.018 < 0.026 < 0.019 < 0.023 < 0.020 < 0.016 0.019 39 < 0.026 < 0.025 < 0.021 < 0.017 < 0.029 < 0.024 < 0.018 0.029 40 < 0.020 < 0.017 < 0.Qi8 < 0.Qi8 < 0.025 < 0.017 < 0.023 0.021 41 < 0.032 < 0.020 < 0.027 < 0.025 < 0.026 < 0.017 < 0.014 0.030 42 < 0.019 < 0.021 < 0.024 < 0.020 < 0.022 < 0.019 < 0.047 0.020 43 < 0.022 < 0.015 < 0.023 < 0.Qi8 < 0.024 < 0.014 < 0.01 I 0.019 44 < 0.024 < 0.021 < 0.025 < 0.021 < 0.021 < 0.020 0.010 0.035 45 < 0.026 < 0.017 < 0.028 < 0.018 < 0.020 < 0013 < 0.014 0.034 46 < 0.022 < 0.022 < 0.015 < 0.024 < 0.021 < 0.013 < 0.015 0.025 47 < 0.021 < 0.029 < 0.017 < 0.019 < 0.014 < 0.023 < 0.016 0.027 48 < 0.020 < 0.016 < 0.018 < 0.022 < 0.013 < 0.018 0.018 49 < 0.004 < 0.018 no data < 0.021 < 0.017 < 0.024 < 0.016 < 0.021 50 < 0.037 < 0.036 < 0.026 < 0.032 < 0.033 < 0.022 < 0.024 0.031
< 0.034 < 0.027 < 0.025 < ()'022 < 0.028 < 0.025 0.020 0.024
< 0.019 < 0.019 < 0.023 < 0.021 < 0.016 < 0.023 0.015
** Control sample location 8-17
TABLE B-9 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2010 Results in Units of pCiJliter +/- 1 Sigma
#9 PLANT INLET (HUDSON RIVER INTAKE)
Date 1129/2010 2/26/2010 3/26/2010 4/30/2010 5/24/2010 6/28/2010 NUCLIDE 1-131 5.80 < 4.56 < 3.82 < 6.68 < 2.93 < 3.94 Cs-134 0.80 < 0.83 < 0.58 < 0.77 < 0.71 < 0.64 Cs-137 1.12 < 1.07 < 0.84 < 1.13 < 0.94 < 0.90 Zr-95 2.41 < 2.27 < 1.66 < 2.19 < 1.63 < 1.72 Nb-95 1.81 < 1.55 < 1.08 < 1.49 < 1.05 < 1.34 Co-58 1.43 < 1.11 < 0.99 < 1.13 < 1.06 < 0.95 Mn-54 1.20 < 1.01 < 0.84 < 1.14 < 0.95 < 0.93 Fe-59 4.10 < 3.27 < 2.28 < 3.49 < 2.12 < 2.77 Zn-65 1.83 < 2.84 < 1.82 < 2.62 < 1.10 < 1.14 Co-60 1.15 < 1.16 < 0.82 < 1.09 < 0.90 < 0.91 I K-40 13.72 108.9 +/- 11.45 43.73 +1- 6.81 87.79 +1- 10.97 55.59 +/- 8.21 45.7 +/- 9.05 BalLa-140 4.54 < 2.98 < 2.45 < 2.70 < 1.90 < 2.44 Date 7/26/2010 8/30/2010 9/27/2010 10/25/2010 11129/2010 12/28/2010 NUCLIDE 1-131 4.04 < 3.30 < 3.16 < 2.30 < 3.27 < 3.73 Cs-134 0.98 < 0.76 < 0.66 < 1.04 < 0.61 < 0.58 Cs-137 1.44 < 0.99 < 0.89 < 0.67 < 0.78 < 0.77 Zr-95 2.38 < 1.88 < 1.63 < 1.29 < 1.73 < 1.65 Nb-95 1.66 < 1.28 < 1.19 < 0.79 < 1.18 < 1.03 Co-58 1.36 < 1.06 < 1.07 < 0.74 < 0.96 < 0.81 Mn-54 1.04 < 1.11 < 0.93 < 0.56 < 0.83 < 0.76 Fe-59 3.74 < 2.98 < 2.57 < 1.40 < 2.75 < 2.64 Zn-65 1.88 < 1.34 < 1.12 < 1.44 < 1.84 < 1.77 Co-60 1.09 < 1.05 < 0.90 < 0.63 < 0.85 < 0.77 K-40 1 13.49 140.1 +/- 11.59 55.9 +1- 9.08 129.8 +1- 9.35 42.85 +/- 7.30 91.62 +/- 7.89 BalLa-l 40 < 2.64 < 2.67 < 2.12 < 1.38 < 2.19 < 2.66 8-18
TABLE B-9 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2010 Results in Units of pCilUter +/- 1 Sigma
#10 DISCHARGE CANAL (MIXING ZONE)
Date 1/29/2010 2/26/2010 3/26/2010 4/30/2010 5/24/2010 6/2812010
< 6.69 < 3.32 < 5.09 < 5.34 < 2.81 4.20
< 0.86 < 0.61 < 0.78 < 0.43 < 0.85 < 0.85 1.26 < 0.84 < \.13 < 0.64 < 1.08 < \.08 2.70 < 1.60 < 2.52 < 1.24 < 1.91 2.00 Nb-95 1.79 < 1.06 < 1.73 < 1.03 < 1.34 1.62 1.43 < 0.83 < 1.38 < 0.83 < 1.08 < 1.25 Mn-54 1.26 < 0.87 < 1.20 < 0.70 < 1.19 < 0.99 4.35 < 2.50 < 3.68 < 2.14 < 3.05 3.43 1.86 < 2.06 < 1.47 < 0.80 < 2.75 2.51 Co*60 1.33 < 0.82 < 1.23 < 0.57 < 1.08 \.03 K*40 428 +/. 19.21 114.5 +/- 9.04 426.8 +/- 16.64 52.42 +/- 5.76 83.39 +/- 10.91 118.5 +/- 12.39 BalLa* < 2.73 < 3.19 < 2.81 < 2.49 3.21 8/30/2010 9/27/2010 10/25/2010 NUCLIDE
< 4.23 < 4.10 < 3.19 < 3.20 < 3.26 < 4.21 1.14 < 0.73 < 1.26 < 1.33 < 0.72 0.64 lAO < 1.12 < 1.11 < 1.01 < 1.00 0.84
< 2.87 < 2.20 < 2.13 < 2.28 < 1.91 1.74 1.50 < 1.56 < lAI < 1.39 < 1.27 1.25 1.71 < 1.19 < 1.\2 < 1.\5 < 1.05 \.01 Mn-54 1.73 < 1.24 < 108 < I 10 < 1.07 0.81 Fe-59 3.95 < 2.88 < 3.22 < 3.11 < 2.82 2.63 1.87 < 2.80 < lAO < 2.59 < 1.34 1.55 1.54 < 0.94 < 1.\5 < 1.10 < \.03 091 K-40 232 17.13 81.7 +/- 12.01 135.9 +/- 13.16 83.54 +/- 11.62 88.77 +/- 10.54 48.64 +/- 7.77 BalLa- 3.90 3.28 < 2.07 < 2.76 < 2A6 3.03 8-19
TABLE B-I0 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2010 (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/1 +/- 1 Sigma CODE PERIOD DATE TRITIUM First Quarter 12/31/09 03/26/10 455 INTAKE (HUDSON RIVER) Second Quarter 03/26/10 06/28/10 401 fNLET) ** Third Quarter 06/28110 09/27/10 <409 Fourth Quarter 09/27/10 12/28/1 0 <408 First Quarter 12/31109 03/26/10 <403 CANAL Second Quarter 03126110 06/28/10 <397 MIXING ZONE) Third Quarter 06128/10 09/27/10 <409 Fourth Quarter 09/27110 12/28/10 <408
- location 8-20
TABLE B-11 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2010 Results in Units ofpCilliter +/- 1 Sigma CAMP FIELD RESERVOIR Date 1112/2010 2/8/2010 3115/2010 4/20/2010 511112010 617/2010 NUCLIDE 2.75 < 2.38 < 3.54 < 3.71 < 3.00 4.10 Cs- 1.31 < 1.50 < 2.20 < 3.14 < 2.99 2.17
< 1.45 < 2.14 < 2.48 < 1.35 < 2.61 2.99 2.94 < 2.28 < 4.93 < 3.93 3.94 5.93 Nb-95 < 1.75 < 1.79 < 3.90 < 3.04 < 2.51 3.78 1.48 < 1.79 < 2.71 < 2.49 < 2.31 3.05 Mn-S4 1.75 < 1.62 < 2.59 < 2.60 1.88 < 3.45 4.02 < 4.20 < 5.93 < 5.26 < 5.87 < 6.54 3.72 < 4.36 < 7.54 < 5.04 < 3.94 906 Co-60 2.01 < 1.72 < 3.72 < 1.90 < 1.90 3.52
+/- 15.03 < 13.63 166.4 +/- 35.94 < 24.79 17.54 432.9 +/- SO.30 BalLa- 2.52 < 2.90 < 4.75 < 3.74 < 1.92 4.44 Date 711212010 8/9/2010 9/20/2010 10/18/2010 11115/2010 12/13/2010 NUCLIDE 3.72 < 2.39 < 2.68 < 2.26 < 2.48 3.23 1.65 1.38 < 1.39 < 1.47 < 1.82 2.00 4.02 < 1.88 < 2.02 < 2.11 < 2.68 2.61 4.47 < 2.55 < 3.12 < 2.86 < 2.94 440 Nb-95 3.08 < 1.98 < 1.91 < 2.01 < 2.00 < 2.59 2.88 < 1.95 < 1.81 < 1.62 < 2.06 2.49 Mn-54 3.26 < 1.66 < 1.43 < 1.79 < 2.43 2.40 7.90 < 5.15 < 5.08 < 3.63 < 6.33 4.44 10.42 < 1.85 < 4.69 < 2.16 < 6.79 6.83 3.35 < 2.32 < 1.72 < 1.80 < 2.37 3.01 KAO 26.57 < 19.27 < 16.29 < 20.60 81.54 +1- 21.56 22.62 BalLa- 5.25 < 1.78 < 2.77 < 2.40 < 2.66 2.36 B-21
TABLE B-ll (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES 2010 Results in Units of pCi/liter +/- 1 Sigma NEW CROTON RESERVOIR Date 1/12/2010 2/812010 3/15/2010 4/20/2010 5/1112010 617/2010 NUCLIDE 2.17 < 2.79 < 4.22 < 4.40 < 1.88 2.90 2.25 < 1.67 < 1.92 < 1.63 < 2.97 LSO 2.43 < 2.63 < 3.11 < 2.83 < 2.27 < 2.27 4.16 < 2.61 < 5.70 < 4.10 < 3.24 3.79 2.24 < 2.10 < 2.99 < 2.15 < 2.10 2.41 2.00 < 2.10 < 3.12 < 3.14 < 2,16 2.66 Mn~54 2.11 < 2.33 < 2.53 < 2.37 1.86 2,23 4.60 < 5.53 < 10,07 < 7.25 < 4,86 6.25 3.92 < 5.23 < 7.40 < 3.22 < 4,13 3.05
< 1.74 < 2.46 < 2.93 < 2.74 < 1.97 2.50 K-40 +1- 21.38 72.45 +/- 22.25 337.5 +1- 42.70 125.4 +1- 24.80 < 26,28 412.4 +1- 35.16 BalLa- 2.66 < 3.38 < 3.30 < 4.03 2.98 2.78 Date 7/12/2010 8/912010 9/20/2010 1011812010 11115/2010 12113/2010 NUCLIDE 309 < 2.29 < 2.19 < 2.43 3.26 2.52 2.00 < 1.54 < 2.89 < 2.07 < 1.57 LS7 2.52 < 2.32 < 2.09 < 2.43 2.94 2.09
< 3,25 < 3.24 < 2.97 < 4.30 < 3.77 3.93 2.72 < 1.79 < 2.46 < 2.36 < 2.59 2.05 2.01 < 2.20 < 1.67 < 1.66 < 2,30 2.06 Mn-54 < 1.89 < 2.28 < 1.86 < 1.99 < 2.31 < 2.11 8.10 < 5,54 < 5.40 < 6.13 7.35 5,95 5,59 < 6,27 < 4.14 < 6.53 < 7.48 6. J:\
< 2,13 < 2.08 < 2.18 < 1.74 < 2,13 2.55 K-40 24.80 69,5 +/- 19.33 1/8,6 +1- 23,32 93.1 +/- 2 L05 < 28.62 106,7 +/- 23.43 BalLa- 403 < 2,97 < 3.29 < 1.87 < 4,29 2.67 8-22
TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES - 2010 (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCiJl +/- 1 Sigma STA TJON CODE PERIOD DATE TRITIUM First Quarter 12/15/09 03/15/10 <420 CAMP RESERVOIR Second Quarter 03115110 06/07110 < 406 Third Quarter 06/07110 09120110 < 410 Fourth Quarter 09120110 12/13/10 < 421 First Quarter 12/15/09 03/15/10 < 420 NEW RESERVOIR Second Quarter 03/1511 0 06/07/10 <406 Third Quarter 06/07/10 09120110 < 410 Fourth Quarter 09/20/10 12/13/10 < 409 8-23
TABLEB-13 CONCENTRATIONS OF RADlONUCLIDES IN SHORELINE SOIL SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample COLDSPRING LENTS COVE MANITOU VERPLANCK WHITE BEACH Location SHORELINE SHORELINE SHORELINE SHORELINE SHORELINE Date 6/2/2010 6/2/2010 6/2/2010 6/3/2010 6/3/2010 Client ID ISS842210 ISS282210 ISS502210 ISSl72210 ISS532210 Radionuclide (pCi) Be-7 < 328.2 < 399.9 < 475.2 < 245.8 < 222.7 1-131 < 132.3 < 192.7 < 201.0 < 115.5 < 97.7 Cs-134 75 < 32.2 < 47.1 < 55.8 < 34.7 < 15.3 Cs-137 90 < 27.1 < 41.7 62.7 +1- 39.0 173.2 +1- 28.5 < 20.4 Zr-95 < 56.5 < 68.8 < 106.1 < 65.8 < 58.1 Nb-95 < 52.9 < 70.8 < 78.1 < 43.2 < 36.2 Co-58 < 42.0 < 52.4 < 51.0 < 32.0 < 26.0 Mn-54 < 31.7 < 39.0 < 44.9 < 3404 < 22.1 Zn-65 < 53.0 < 60.0 < 59.0 < 100.3 < 8004 Fe-59 < 117.0 < 116.7 < 149.6 < 99.9 < 56.0 Co-60 < 41.5 < 31.6 < 56.1 < 27.5 < 25.0 BalLa-140 < 70.7 < 114.0 < 107.6 < 46.6 < 32.1 Ru-103 < 43.9 < 52.1 < 61.2 < 34.6 < 31.0 Ru-106 < 332.8 < 41004 < 539.9 < 319.1 < 255.0 Ce-141 < 73.7 < 98.0 < 94.8 < 60.7 < 46.6 , Ce-144 < 226.6 < 314.6 < 276.2 < 176.0 < 129.3 i AcTh-228 869.4 +1- 129.2 1554.0 +1- 164.4 913.8 +1- 188.1 787.5 +1- 116.1 < 81.5 Ra-226 1706.0 +1- 674.7 3861.0 +1- 911.3 2149.0 +1- 682.2 1028.0 +1- 555.6 < 446.2 K40 37710.0 +/- 1156.0 16870.0 +1- 884.1 20910.0 +1- 1178.0 16410.0 +/- 842.1 9909.0 +1- 646.5 Sr-90 3000 < 179 < 199 < 192 < 175 < 148 8-24
TABLE B-13 (Continued) CONCENTRATIONS OF RADIO NUCLIDES IN SHORELINE SOIL SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma - ~----.~--~ Sample COLDSPRING LENTS COVE MANITOU VERPLANCK WHITE BEACH Location SHORELINE SHORELINE SHORELINE SHORELINE SHORELINE Date 9/13/2010 9/13/2010 911312010 9/14/2010 9/14/2010 Client ID ISS843710 ISS283710 ISS503710 ISS173710 ISS533710 Radionuclide (pCi) Be-7 < 287.9 < 302.2 < 291.9 < 214.8 < 2271 1-131 < 55.9 < 56.9 < 87.6 < 43.1 < 53.9 Cs-134 75 < 39.7 < 41.9 < 37.6 < 18.1 < 18.8 Cs-137 90 < 30.8 < 34.8 < 54.9 133.7 +/- 22.5 < 27.3 Zr-95 < 61.1 < 68.3 < 94.4 < 34.6 < 40.4 Nb-95 < 43.5 < 43.6 < 74.9 < 30.1 < 29.5 Co-58 < 29.3 < 34.4 < 45.6 < 14.6 < 24.1 Mn-54 < 29.0 < 34.1 < 56.7 < 21.1 < 29.8 Zn-65 < 91.7 < 54.4 < 62.9 < 83.3 < 83.8 Fe-59 < 104.8 < 95.6 < 99.4 < 68.3 < 95.7 Co-60 < 34.6 < 45.3 < 42.6 < 22.4 < 29.5 BalLa-140 < 42.1 < 66.7 < 77.8 < 30.7 < 55.3 RU-103 < 32.5 < 35.1 < 44.3 < 23.6 < 21.5 Ru-106 < 248.3 < 325.4 < 448.3 < 242.9 < 255.4 Ce-141 < 54.3 < 56.6 < 84.8 < 44.0 < 37.5 Ce-144 < 203.0 < 220.9 < 360.7 < 184.4 < 156.2 AcTh-228 1034.0 +/- 124.1 1455.0 +1- 152.8 1607.0 +1- 223.2 412.2 +/- 88.7 < 100.9 Ra-226 1625.0 +1- 681.4 4792.0 +/- 681.4 4422.0 +/- 1021.0 1810.0 +/- 442.0 < 556.8 K-40 34640.0 +/- 1043.0 15500.0 +/- 858.6 13760.0 +/- 1091.0 15530.0 +/- 683.3 13490.0 +/- 774.2 Sr-90 3000 < 30 < 35 < 37 < 36 < 37 8-25
TABLE B-14 CONCENTRAnONS OF GAMMA EMITTERS IN BROADLEAF VEGET AnON SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#95 Meteorological Tower Sample Location MET TOWER MET TOWER Date 4/26/2010 4/26/2010 Client ID lBV951710SI IBV95 17 lOS 2 Req.CL RAGWEED MUUElN Radionuclide (pCi)
Be-7 774.9 +/- 71.0 1813.0 +/- 116.7 1-131 50 < 9.01 < 10.25 CS-134 50 < 6.17 < 8.07 Cs-137 50 < 8.22 < 10.51 Zr-95 < 10.44 < 14.52 Nb-95 < 7.68 < 10.69 Co-58 < 7.23 < 7.49 Mn-54 < 6.82 < 9.16 Zn-65 < 19.13 < 25.70 Fe-59 < 18.73 < 29.61 Co-60 < 7.02 < 10.67 BalLa-140 < 6.11 < 10.03 Ru-103 < 6.33 < 10.35 Ru-106 < 76.47 < 117.80 Ce-141 < 9.63 < 13.11 Ce-l44 < 40.17 < 48.79 AcTh-228 < 23.75 < 27.19 Ra-226 < 151.80 < 180.00 K-40 4522.0 +/- 191.1 3846.0 +/- 226.2 8-26
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES 2010 Results in Units of pCilkg +/- 1 Sigma
#95 Meteorological Tower Sample MET TOWER MET TOWER Location Date 6/14/2010 6/14/2010 Client ID IBV952410S1 IBV9524lOS2 Req. CL RAGWEED MULLEIN Radionuclide (pCi)
Be-7 749.6 +/- 75.2 531.1 +/- 69.5 1-131 50 < 9.27 < 9.07 Cs-134 50 < 12.71 < 5.81 Cs-137 50 < 8.42 < 7.09 Zr*95 < 15.10 < 12.15 Nb-95 < 8.55 < 8.29 Co-58 < 7.81 < 7.93 Mn*54 < 7.95 < 8.63 Zn-65 < 25.63 < 20.05 Fe-59 < 26.13 < 20.29 Co-60 < 8.69 < 8.59 BalLa*140 < 6.58 < 8.51 Ru-103 < 6.70 < 6.78 Ru-106 < 87.83 < 90.44 Ce-141 < 10.40 < 10.34 Ce-144 < 37.62 < 47.73 AcTh-228 < 33.66 < 31.39 Ra-226 < 142.20 447.8 +/- 119.2 '------~:40 7903.0 +/- 286.2 4656.0 +/- 206.9 8-27
CONCENTRATIONS 01<' GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- I Sigma
#95 Meteorological Tower ~mple MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER location Date 7119/2010 7119/2010 7/19/2010 8/16/2010 8/16/2010 8/16/2010 Client ID lBV'J529 lOS I IBV9529lOS2 IBV9529lOS3 IBV9533 lOS I IBV9533lOS2 lBV953310S3 Req. CL COMMON WILD RYE RAGWEED MULLEIN COTTONWOOD RAGWEED Radionuclide (pCi)
Be-7 1323.0 +/. 112.0 493.4 +/- 83.4 1049.0 +/- 136.6 1970.0 +/- 174.2 1968.0 +/. 121.8 572.5 +/- 93.0 1-131 50 <: 13.15 <: 11.35 < 15.66 < 20.48 < 11.96 < 13.32 Cs-134 50 <: 9.21 < 11.84 < 18.83 < 26.89 < 8.23 < 9.02 Cs-137 50 <: 12.91 < 11.15 < 14.01 < 18.88 < 11.58 31.2 +/- 5.9 Zr-95 <: 19.06 < 21.03 < 28.79 < 26.31 < 17.34 < 16.68 Nb-95 <: 10.62 < 11.56 < 17.65 < 14.80 < 10.16 < 12.57 Co-58 <: 10.42 < 10.00 < 17.80 < 19.79 < 9.09 < 12.00 Mn-54 <: 12.46 < 11.12 < 14.06 < 18.15 < 9.44 < 11.10 Zn-65 <: 32.54 < 37.17 < 53.68 < 52.58 < 28.16 < 31.31 Fe-59 <: 24.79 < 33.58 < 51.73 < 49.48 < 27.86 < 30.89 Co-60 <: 11.11 < 14.04 < 15.21 < 20.97 < 9.98 < 10.52 BalLa-140 <: 16.37 < 9.82 < 16.56 < 22.48 < 11.04 < 12.25 Ru-103 < 10.29 < 9.95 < 14.16 < 16.03 < 8.13 < 10.05 Ru-106 < 126.60 < 120.90 < 143.70 < 161.70 < 99.92 < 101.30 Ce-141 <: 14.74 < 16.24 < 19.81 < 20.47 < 13.94 < 14.49 Ce-144 <: 67.73 < 59.23 < 88.52 < 82.06 < 60.00 < 67.76 AcTh-228 56.4 +/- 34.5 < 44.08 < 52.32 < 72.87 < 38.06 < 46.45 Ra-226 805.2 +1- 188.3 317.4 +/- 124.2 < 269.30 508.8 +/- 236.7 459.6 +/. 165.3 < 219.20 K-40 6733.0 +/- 312.3 6621.0 +/- 331.2 4044.0 +/- 324.2 9322.0 +/- 461.4 3999.0 +/. 231.7 10290.0 +/- 357.0 B-28
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES 2010 Results in Units of pCi/kg +/- 1 Sigma
#95 Meteorological Tower Sample location MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER Date 9/13/2010 9/13/2010 9/13/2010 10112/2010 10/12/2010 1011212010 Client ID IBV953710SI IBV95371OS2 IBV953 71 OS3 IBV954110S1 IBV954110S2 IBV954 1 I OS3 Req.
MULLEIN GRAPE LEAVES RAGWEED RAGWEED MULLEIN COTTONWOOD Radionuclide (pCi) Be*7 1334.9 +1- 99.8 392.0 +/- 77.7 2363.0 +/- 132.9 3436.0 +/- 206.2 2322.0 +/- 172.7 7546.0 +/- 276.4 1-131 50 <: 14.18 < 10.64 < 14.26 < 24.80 < 25.54 < 20.72 Cs*134 50 <: 8.02 < 11.89 < 7.41 < 12.67 < 15.03 < 24.52 Cs-137 50 <: 9.89 < 8.75 < 9.10 < 21.47 < 19.82 < 20.24 Zr-95 <: 14.31 < 18.03 < 16.88 < 37.35 < 30.99 < 40.38 Nb*95 <: 10.37 < 10.57 < 9.90 < 16.95 <: 20.62 <: 20.01 Co-58 <: 10.53 < 9.33 < 11.25 < 20.82 < 19.26 <: 19.14 Mn-54 <: 11.37 <: 8.48 <: 11.17 < 15.19 < 19.02 <: 20.62 Zn-65 <: 30.54 <: 25.63 <: 27.64 < 55.25 < 27.35 <: 23.76 Fe-59 <: 34.83 <: 25.51 < 32.58 < 57.31 <: 55.58 <: 59.07 Co-60 <: 12.32 < 12.68 < 11.83 < 27.38 <: 21.36 < 21.57 Balla-140 <: 10.43 < 12.98 < 10.52 < 27.31 <: 25.06 <: 18.69 I Ru-103 <: 9.25 <: 9.58 < 10.12 < 19.60 <: 20.05 <: 20.26 Ru-106 <: 113.30 < 104.10 <: 111.80 < 202.00 <: 195.80 <: 183.80 Ce-141 <: 14.37 < 11.97 < 14.56 < 23.83 < 25.37 <: 29.22 Ce-144 <: 69.64 <: 51.77 < 58.73 <: 97.88 <: 98.52 <: 107.10 AcTh-228 <: 39.73 < 31.63 <: 40.33 < 79.14 <: 78.52 < 68.08 Ra-226 363.2 +1- 170.1 357.0 +/- 141.5 < 225.60 <: 340.60 <: 365.20 1337.0 +/- 344.0 K-40 8036.0 +1- 316.8 3956.0 +/- 253.5 6852.0 +/- 295.6 10390.0 +/- 514.7 10670.0 +/- 456.8 7828.0 +/- 399.4 B-29
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#94 IPEC Training Center Sample TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Location Date 4/2612010 4/26/2010 412612010 5/17/2010 5/1712010 5/17/2010 Client lD mV941710SI IBV941710S2 lBV9417 IOS3 lBV942010S1 IBV9420 I OS2 IBV9420lOS3 Req. CL ALLROOT MULLEIN MUSTARD RAGWEED EWICK Radiolluclide (pCi)
Be-] 851.1 +/~ 77.9 834.9 +1- 83.9 201.4 +1- 90.1 612.4 +/- 89.6 < 94.83 338.8 +1- 65.1 1-131 50 < 9.42 < 9.92 < 15.50 < 12.36 < 11.67 < 960 Cs-134 50 < 10.77 < 11.87 < 11.20 < 15.97 < 9.35 < 12.56 Cs-137 50 < 7.80 < 8.77 < 14.75 < 12.22 < 11.84 < 7.88 Zr-95 < 14.57 < 16.88 < 23,42 < 23.67 < 18.96 < 15.66 Nb-95 < 807 < 8.25 < 13.70 < 12,41 < 11.00 < 12,47 Co-58 < 7.39 < 9.24 < 12.28 < 10.17 < 9,43 < 10.69 Mn-54 < 8.01 < 10.18 < 14.88 < 12.39 < 9.79 < 11.86 Zn-65 < 22.98 < 26.61 < 38.93 < 28.62 < 25.51 < 23.06 Fe-59 <?4*38 < 26.43 < 36.04 < 43.86 < 31.05 < 31.97 i Co-60 <.9-'-.91 < 9.56 < 14.30 < 17.41 < 12.11 < 9.15 BalLa-140 < 8.55 < 10.26 < 18.53 < 13.91 < 13.79 < 10,41 Ru-103 < 8.73 < 8.93 < 10.12 < 10.87 < 10.53 < 8.26 Ru-106 < 80.20 < 95.65 < 122.50 < 133.20 < 124.50 < 75.11
- Ce-141 < 11.88 < 12.21 < 15.87 < 13.97 < 14.50 < 12.64 Ce-144 < 45.81 < 53.19 < 60.78 < 56.35 < 51.92 < 47.70 AcTh*228 < 28.14 < 33.64 112.0 +/- 38.9 < 44.17 < 37.75 < 39.00 Ra-226 < 151.70 < 172.20 < 241.20 < 204.00 < 199.10 < 168.90 K-40 5573.0 +/~ 241.8 4136.0 +/- 237.7 6262.0 +1- 339.5 9766.0 +/- 383.0 4768.0 +/- 279,4 5890.0 +/- 296.9 8-30
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGET AnON SAMPLES - 2010 Results in Units of pCilkg +/- 1 Sigma
#94 IPEC Training Center Sample Location TRAINING BLDG TRAINING BLDG TRAINING BLDG Date 6114/2010 6/14/2010 6/14/2010 Client lD IBV942410S1 IBV9424IOS2 lBV9424lOS3 Req. CL RAGWEED GRAPEL. VRGCREE Radionuclide (pCi)
Be-7 1021.0 +/- 110.0 686.8 +/- 70.9 1008.0 +/- 92.0 1-131 50 < 12.34 < 9.54 < 8.31 Cs-134 50 < 18.90 < 6.52 < 12.59 Cs-137 50 < 13.73 < 9.61 < 10.67 Zr-95 < 19.24 < 14.36 < 17.20 Nb-95 < 12.76 < 7.41 < 10.22 Co-58 < 13.46 < 7.89 < 8.99 Mn-54 < 15.60 < 8.00 < 11.76 Zn-65 < 42.15 < 25.10 < 26.54 Fe-59 < 45.12 < 26.07 < 29.09 Co-SO < 17.92 < 7.62 < 9.14 BalLa-140 < 14.48 < 8.41 < 11.09 Ru-103 < 12.25 < 7.70 < 8.66 Ru-10S < 119.90 < 89.56 < 95.92 Ce-141 < 15.23 < 11.59 < 12.39 Ce-144 < 70.44 < 55.23 < 50.06 AcTh*228 < 59.06 < 35.63 < 29.15 Ra-22S < 213.10 261.6 +/- 138.0 409.5 +/- 132.2 K-40 8866.0 +/- 438.3 3239.0 +/- 185.4 3086.0 +/- 207.3
- Control Sample Location B-31
TABLE B-14 (Continued) CON CENTRATIONS OF GAMMA EMITTERS IN BROADLEAI<' VEGETA TlON SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#94 IPEC Training Center Sample Location TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Date 711912010 7119/2010 711912010 8/16/2010 8/16/2010 8/16/2010 Client 10 IBV942910S1 IBV942910S2 IBV94291OS3 IBV943310S1 IBV94331OS2 IBV94331OS3 Req. CL CATALP CATALPA GRAPE LEAVES RAGWEED RAGWEED GRAPE Radionuclide (pCi) f3e..7 743.6 +/- 122.8 334.7 +/- 95.9 1567.0 +/- 112.7 2221.0 +/- 135.0 755.5 +/- 105.5 1008.0 +/- 76.2 1-131 50 <: 18.34 < 15.76 < 11.52 < 11.87 < 15.60 < 8.37 Cs-134 50 <: 10.37 < 11.10 < 7.88 < 13.88 < 13.81 < 5.36 CS-137 50 <: 13.74 < 15.12 < 14.02 < 10.34 < 11.28 < 7.56 Zr-95 <: 27.86 < 25.97 < 19.25 < 18.26 < 21.32 < 11.49 Nb-95 <: 14.70 < 16.99 < 13.93 < 9.88 < 14.24 < 7.92 Co-58 <: 15.87 < 16.65 < 13.64 < 10.29 < 12.31 < 6.29 Mn-S4 <: 15.23 < 15.03 < 12.86 < 11.06 < 14.72 < 8.14 Zn-65 <: 47.25 < 37.43 < 35.57 < 31.51 < 19.08 < 22.61 Fe-59 <: 43.14 < 42.72 < 38.76 < 29.19 < 39.73 < 13.82 Co-6O <: 20.35 < 15.55 < 11.35 < 12.71 < 16.00 < 7.16 Ba/La-140 <: 18.82 < 23.66 < 13.07 < 14.21 < 11.32 < 6.32 Ru-103 <: 16.10 < 15.18 < 13.00 < 9.71 < 11.92 < 7.92 Ru-106 <: 189.10 < 160.20 < 155.10 < 97.57 < 121.70 < 82.13 Ce-141 <: 1900 < 20.27 < 15.98 < 14.08 < 15.57 < 8.89 .
Ce-144 <: 81.63 < 76.63 < 64.26 < 53.39 < 63.49 < 34.45 AcTh-228 <: 59.12 < 67.11 < 48.89 < 48.54 < 53.17 < 28.01 Ra-226 460.8 +/- 282.2 416.0 +/- 246.7 624.0 +/- 183.5 < 205.50 < 219.60 320.1 +/- 134.4 K-40 4305.0 +/- 325.6 5403.0 +/- 364.5 9087.0 +/- 350.7 7614.0 +/- 340.3 4962.0 +/- 291.2 2342.0 +/- 154.5 8-32
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES 2010 Results in Units of pCi/kg +/- 1 Sigma
#94 IPEC Training Center Sample Location TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Date 9113/2010 9/13/2010 9/13/2010 10/12/2010 10/12/2010 10/13/2010 Client ID lRV9437 lOS I IBV9437lOS2 IBV943710S3 IBV944110S1 IBV944110S2 lBV944110SJ CATALPA GRAPELE RAGWEED RAGWEED corroNw CATALPA Radionuclide (pei)
Be-7 1886.0 +1- 141.4 1234.0 +/- 140.0 2466.0 +/- 146.0 9988.0 +/- 384.3 4265.0 +/- 228.9 2432.0 +/- 138.4 1-131 50 < 13.37 < 18.59 < 11.53 < 26.82 < 20.41 < 13.06 Cs-134 50 < 9.32 < 10.67 < 14.41 < 18.03 < 15.77 < 10.03 Cs-137 50 <; 9.83 < 17.62 < 12.23 < 27.67 < 16.03 < 13.72 Zr-95 <; 22.69 < 23.89 < 20.21 < 38.66 < 2809 < 22.06 Nb-95 <; 15.08 < 14.46 < 11.38 < 25.74 < 22.04 < 9.26 Co-58 <; 11.33 < 17.20 < 7.86 < 24.29 < 21.33 < 13.05 Mn-54 <; 11.27 < 15.69 < 13.50 < 24.83 < 21.36 < 9.12 Zn-65 < 17.21 < 53.39 < 32.14 < 83.11 < 29.60 < 18.31 Fe-59 <; 32.62 < 53.42 < 35.89 < 82.67 < 32.84 < 28.42 Co-60 <; 11.26 < 20.04 < 11.56 < 34.42 < 22.26 < 12.53 BalLa-140 <; 19.94 < 18.42 < 14.07 < 39.45 < 23.71 < 17.26 Ru-103 <; 9.54 < 17.51 < 12.54 < 24.55 < 18.19 < 10.54 Ru-106 < 111.00 < 171.20 < 123.90 < 288.80 < 133.10 < 145.30 Ce*141 < 18.37 < 18.49 < 14.88 < 30.42 < 25.80 < 16.69 Ce-144 < 67.67 < 79.60 < 61.63 < 134.50 < 102.70 < 76.33 AcTh-228 < 41.88 < 60.85 < 47.25 < 88.66 < 65.86 < 40.39 Ra-226 < 225.60 395.3 +/- 204.5 647.3 +/- 207.4 1146.0 +/- 434.9 595.1 +/- 303.8 424.2 +/- 210.6 K-40 2230.0 +/- 227.6 5314.0 +/- 357.2 7125.0 +/- 348.1 8569.0 +/- 554.0 3571.0 +/- 323.2 1582.Q~ 167.7 8-33
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2010 Results in Units of pCilkg +/- 1 Sigma
#23 Roseton **
Sample location ROSETON ROSETON ROSE TON ROSETON ROSETON ROSETON Date 4126/2010 4/26/2010 4/26/2010 5/17/2010 5/17/2010 5/17/2010 Client ID lBV231710SI IBV23 I 71OS2 IB V23 I71OS3 IBV2320 Ios I IBV2320 IOS2 IBV2320lOS3 Req. CL MULLEIN PENNY WORT RAGWEED MULLEIN BURDOCK Radionuclide (pCi) Be-7 591.6 +/~ 57.3 1010.0 +/- 109.5 790.6 +/- 97.7 740.9 +/- 84.5 914.5 +/- 127.8 1087.0 +/- 105.1 1-131 50 <: 7.98 < 11.51 < 14.14 < 12.42 < 20.08 < 13.86 Cs-134 50 <: 4.41 < 7.80 < 14.76 < 6.15 < 11.70 < 7.98 Cs-137 50 <: 5.94 < 11.55 < 14.09 < 10.17 < 16.12 < 11.91 Zr-95 <: 11.50 < 21.37 < 21.44 < 13.93 < 29.18 < 18.23 Nb-95 <: 694 < 12.44 < 13.12 < 8.25 < 20.10 < 12.39 Co-58 <: 6.82 < 11.85 < 11.01 < 9.73 < 15.85 < 9.94 Mn-54 <: 7.11 < 10.22 < 11.72 < 7.83 < 14.62 < 10.95 Zn-65 < 20.99 < 33.02 < 29.62 < 12.25 < 48.01 < 16.63 Fe-59 <: 16.55 < 29.10 < 30.74 < 28.16 < 42.17 < 25.77 Co-60 < 7.16 < 14.81 < 12.41 < 10.99 < 16.20 < 11.32 BalLa-140 <: 8.63 < 12.53 < 14.83 < 9.06 < 15.82 < 11.64 Ru-103 <: 7.64 <: 9.36 < 11.31 < 8.99 < 16.36 < 8.76 Ru-106 <: 70.54 < 122.40 < 141.20 < 94.10 < 148.50 < 93.93 Ce-141 <: 9.95 < 12.87 < 16.53 < 12.80 < 21.01 < 12.99 Ce-144 <: 38.79 < 64.68 < 61.12 < 60.56 < 78.89 < 59.80 AcTh-228 <: 24.69 < 47.22 71.1 +/- 35.1 94.1 +/- 31.4 < 57.78 < 35.75 Ra-226 <: 136.90 527.9 +/- 163.3 260.7 +/- 164.2 < 194.60 < 284.40 480.6 +/- 166.2 K-40 5:550.0 +1- 192.4 3933.0 +/- 271.5 6080.0 +/- 287.8 6687.0 +/- 269.6 6525.0 +/- 381.5 6467.0 +/- 275.7 Control Sample Location B-34
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#23 Roseton **
Sample Location ROSETON ROSE TON ROSETON Date 6/14/2010 6/14/2010 6/14/2010 10 IBV2324 I OS I IBV23241OS2 IBV23241OS3 Req. CL RAGWEED MULLEIN BURDOCK Radionuclide (pCi) Be-7 501.6 +/- 116.4 876.6 +/- 103.3 309.5 +/- 90.8 1-131 50 < 18.76 < 11.03 < 15.81 Cs-134 50 < 16.73 < 15.21 < 15.33 Cs-137 50 < 14.87 < 11.67 < 12.78 Zr-95 < 34.71 < 20.05 < 22.65 Nb-95 < 18.60 < 12.74 < 12.58 Co-58 < 15.07 < 12.10 < 11,42 Mn-54 < 15.04 < 10.35 < 10.86 Zn-65 < 44.74 < 34.24 < 38.79 Fe-59 < 48.57 < 28.81 < 33.18 Co-60 < 18.02 < 12.87 < 14.08 BalLa-140 < 16.80 < 8.75 < 21.54 Ru-103 < 13.18 < 9,48 < 11.60 Ru-106 < 151.70 < 112.30 < 120.50 Ce-141 < 19.52 < 14.75 < 15.99 Ce-144 < 78.45 < 61.65 < 66.83 AcTh-228 < 54.71 < 44.12 < 50.65 Ra-226 < 284.30 < 201.90 < 232.60 K-40 1000.0 +1- 457,4 5206.0 +/- 3079 6280.0 +/- 333.1 B-35
TABLE B-14 (Continued) CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#23 Roseton **
~-- .- ~- ~----
Sample Location ROSETON ROSETON ROSE TON ROSETON ROSETON ROSETON Date 7/1912010 7119/2010 7/1912010 8/1612010 8116/2010 8/16/2010 Client ID IBV2329lOSI lBV232910S2 lBV232910S3 IBV233310S1 IBV233310S2 lBV2333I OS3 Req. CATALPA BURDOCK RAGWEED MILKWEED RAGWEED COMMON MULLEIN RadlOnuclidc (pCi) Be-7 1513.0 +1- 116.8 1147.0 +/- 117.4 899.9 +/- 113.4 1847.0 +/- 120.8 3557.0 +/- 168.9 976.8 +/- 70.5 1-131 50 <: 11.45 < 16.98 < 17.35 < 12.92 < 13.91 < 7.98 Cs-134 50 <: 16.97 < 15.91 < 18.79 < 9.75 < 9.00 < 5.56 Cs*137 50 <: 9.69 < 12.79 < 14.45 < 10.88 < 10.18 < 6.35 Zr*95 <: 17.47 < 20.14 < 23.27 < 16.89 < 14.51 < 10.57 Nb-95 <: 9.01 < 11.92 < 13.87 < 10.48 < 11.53 < 6.97 Co-58 <: 8.53 < 12.20 < 14.61 < 10.11 < 11.20 < 5.65 Mn-54 <: 11.04 < 13.51 < 15.39 < 12.31 < 10.86 < 6.60 Zn-65 <: 29.65 < 32.85 < 39.00 < 37.42 < 37.87 < 8.60 Fe-59 <: 27.89 < 33.91 < 44.43 < 32.18 < 34.44 < 15.80 Co-60 <: 13.56 < 14.39 < 20.80 < 10.30 < 12.49 < 7.10 BalLa-140 <: 14.85 < 16.07 < 25.15 < 10.13 < 14.06 < 8.93 Ru-103 <: 11.30 < 11.11 < 12.56 < 10.70 < 10.07 < 5.63 Ru-106 <: 115.60 < 153.70 < 137.50 < 131.20 < 97.61 < 67.17 Ce-141 <: 13.27 < 14.93 < 15.84 < 14.42 < 16.68 < 9.00 Ce-144 <: 56.16 < 59.90 < 68.04 < 59.75 < 64.62 < 38.47 AcTh-228 <: 48.04 < 34.24 < 55.42 < 43.67 123.9 +1- 35.1 < 23.69 Ra-226 584.1 +1- 155.4 384.5 +/- 160.5 < 258.10 < 198.20 498.5 +1- 195.7 222.9 +/- 121.3 K-40 8504.0 +1- 348.5 7042.0 +1- 373.5 5212.0 +/- 324.7 8066.0 +/- 343.8 4257.0 +/- 269.9 1929.0 +1- 124.4 .. Control Sample Location 8-36
TABLE B-14 (Continued) CONCENTRATlONS OF GAMMA EMITTERS IN BROADLEAF VEGETA TlON SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#23 Roseton **
Sample ROSETON ROSETON ROSETON ROSETON ROSETON ROSETON Location Date 7119/2010 7/19/2010 7/19/2010 8/16/2010 8/16/2010 8/16/2010 Client ID IBV2.l29lOS I IBV232<JlOS2 IBV23291OS3 IB V2333 IOS I IBV2333IOS2 lBv2331 lOS} Req. CL BURDOCK RAGWEED MILKWEED RAGWEED COMMON MULLEIN CATALPA Rad iOIlUcI ide (pCi) Be-7 1513.0 +1- 116.8 1147.0 +/- 117,4 899.9 +/- 113,4 1847.0 +/- 120.8 3557.0 +/- 168.9 976.8 +/- 70.5 1*131 50 <: 11,45 < 16.98 < 17.35 < 12.92 < 13.91 < 7.98 Cs-134 50 <: 16.97 < 15.91 < 18.79 < 9.75 < 9.00 < 5.56 Cs-137 50 <: 9.69 < 12.79 < 14,45 < 10.88 < 10.18 < 6.35 Zr-95 <: 17,47 < 20.14 < 23.27 < 16.89 < 14.51 < 10.57 Nb-95 <: 9.01 < 11.92 < 13.87 < 10,48 < 11.53 < 6.97 Co-58 <: 8.53 < 12.20 < 14.61 < 10.11 < 11.20 < 5.65 Mn-54 <: 11.04 < 13.51 < 15.39 < 12.31 < 10.86 < 6.60 Zn-65 <: 29.65 < 32.85 < 39.00 < 37,42 < 37.87 < 8.60 Fe-59 <: 27.89 < 33.91 < 44.43 < 32.18 < 34,44 < 15.80 Co-50 <: 13.56 < 14.39 < 20.80 < 10.30 < 12.49 < 7.10 BalLa-140 <: 14.85 < 16.07 < 25.15 < 10.13 < 14.06 < 8.93 Ru-l03 <: 1130 < 11.11 < 12.56 < 10.70 < 10.07 < 5.63 Ru-1OS <: 115.60 < 153.70 < 137.50 < 131.20 < 97.61 <: 67.17 Ce-141 <: 13..27 < 14.93 < 15.84 < 14,42 < 16.68 < 9.00 Ce-l44 <: 56.16 < 59.90 < 68.04 < 59.75 < 64.62 < 38,47 AcTh-228 <: 48.04 < 34.24 < 55,42 < 43.67 123.9 +/- 35.1 < 23.69 Ra-226 584.1 +1- 155,4 384.5 +/- 160.5 < 258.10 < 198.20 498.5 +/- 195.7 222.9 +/- 121.3 K-40 8504.0 +/- 348.5 7042.0 +/- 373.5 5212.0 +/- 324.7 8066.0 +/- 343.8 4257.0 +/- 269.9 1929.0 +/- 124,4 Control Sample Location 8-37
TABLE B-14 (Continued) CONCJ1:NTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#23 Roseton **
Sample Location ROSETON ROSETON ROSE TON ROSETON ROSETON ROSETON Date 9/1312010 9/1312010 9/13/2010 10/1212010 10/1212010 10/12/2010 Client lD IBV2337lOSI IBY2337lOS2 IBV233710S3 IBY234110S1 lBV2341lOS2 IBY23411OS3 Req. CL BITTERSWEET RAGWEED GRAPE LEA YES RAGWEED COMMON MULLE! PORCELAIN BERRY Radionuclide (pei) Be-7 969.4 +/- 126.9 1529.0 +/- 136.7 575.7 +/- 108.1 5955.0 +/- 243.7 1444.0 +/- 145.0 1166.0 +/- 163.2 1-131 50 <: 16.70 < 16.40 < 16.69 < 20.29 < 16.10 < 19.73 Cs*134 50 <: 11.05 < 18.04 < 17.08 < 13.64 < 18.60 < 27.24 Cs-137 50 <: 15.68 < 11.76 < 15.58 < 18.30 < 15.84 < 24.33 Zr-95 < 28.15 < 21.04 < 24.24 < 27.95 < 29.32 < 33.08 Nb-95 <: 15.92 < 14.62 < 14.15 < 17.51 < 17.33 < 21.80 Co-58 <: 13.15 < 13.71 < 15.69 < 14.22 < 18.20 < 19.42 Mn-54 <: 14.55 < 13.22 < 13.03 < 15.74 < 13.81 < 15.48 Zn-65 <: 23.69 < 44.22 < 19.32 < 22.66 < 38.52 < 2877 Fe-59 <: 43.51 < 50.31 < 34.37 < 50.89 < 44.47 < 51.27 Co-60 < 13.44 < 18.11 < 14.50 < 16.53 < 14.25 <: 16.61 Ba/La-140 < 20.83 < 10.83 < 14.76 < 20.27 < 21.59 < 25.70 Ru-103 <: 15.92 < 11.71 < 14.45 < 15.37 < 16.50 < 17.24 Ru-106 <: 147.00 < 138.60 < 157.00 < 166.20 < 140.10 < 233.20 Ce-141 <: 20.37 < 15.22 < 27.14 < 21.71 < 20.52 < 23.05 Ce-144 <: 77.62 < 74.63 < 113.70 < 11510 < 82.59 < 10.00 AcTh-228 < 56.18 < 39.62 117.4 +/- 38.5 125.0 +/- 47.7 89.6 +/- 45.4 < 68.43 Ra-226 < 306.70 416.7 +/- 230.2 767.7 +/- 298.1 < 260.40 703.6 +/- 281.7 636.1 +/- 284.4 K-40 5269.0 +/- 336.0 7287.0 +/- 414.4 6116.0 +/- 303.7 8757.0 +/- 412.4 8261.0 +/- 367.1 4078.0 +/- 359.5 .. Control Sample Location B-38
TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#25 Downstream (Hudson River)
Sample VOl) FISH VOP FISH VOPFISH VOP FISH VOPFISH VOP FISH Location Date 5/14/2010 5/14/2010 5/14/2010 5/2112010 5/2112010 6/1512010 Client lD IFlI25271OS3 IFII2527 1OS5 IFH252710S6 IFH252710S1 IFH2527IOS4 IFH2 5271 OS2 Req. CL SUNFISH WHITE PERCH STRIPED BASS BLUE CRAB AMERICAN EEL Radionuclide (pCi) Be-? <: 239.7 < 218.2 < 211.2 < 260.1 < 289.5 < 233.3 1-131 < 2923.0 < 2631.0 < 2479.0 < 1693.0 < 2004.0 < 223.3 Cs-134 65 <: 12.6 < 15.8 < 15.5 < 11.4 < 22.3 < 10.4 Cs-137 75 <: 18.2 < 13.9 < 18.2 < 18.0 < 189 < 18.7 Zr-95 < 45.6 < 55.2 < 41.1 < 49.9 < 62.6 < 39.0 Nb-95 <: 58.1 < 38.5 < 45.2 < 45.2 < 67.7 < 27.5 Co-58 65 <: 31.2 < 23.0 < 25.3 < 26.4 < 28.2 < 26.4 Mn-54 65 <: 19.1 < 18.7 < 18.9 < 16.2 < 24.5 < 19.0 Zn-65 130 <: 45.8 < 38.0 < 49.4 < 48.2 < 59.5 < 62.4 Fe-59 130 <: 105.2 < 110.8 < 99.5 < 92.3 < 94.9 < 77.6 Co-60 65 13.9 < 15.3 < 17.5 < 15.4 < 16.4 < 19.4 BaJLa-140 <: 659.7 < 559.3 < 384.1 < 302.6 < 4379 < 106.0 Ru-103 <: 49.4 < 32.4 < 42.8 < 39.3 < 41.9 < 29.7 Ru-106 <: 214.6 < 189.4 < 198.3 < 211.5 < 232.2 < 213.9 Ce-141 <: 73.6 < 63.9 < 60.4 < 58.2 < 77.2 < 40.6 Ce-144 <: 111.3 < 90.6 < 17.9 < 109.9 < 105.9 < 101.0 AcTh-228 <: 69.9 < 51.0 < 52.0 < 64.0 < 70.0 < 65.9 Ra-226 <: 363.2 399.9 +/- 200.6 315.3 +/- 191.4 667.9 +/- 263.0 < 358.2 846.3 +/- 270.8 K-40 2980.0 +/- 271.0 2884.0 +/- 287.3 4036.0 +/- 295.5 2713.0 +/- 245.7 5352.0 +/- 397.7 5541.0 +/- 355.4 Ni-63 100 < 62.0 < 64.0 < 55.0 < 74.0 < 64.0 < 62.0 Sr-90 5 <: 2.8 < 2.7 < 3.8 < 4.7 < 2.9 < 3.3 8-39
TABLE B-15 (Continued) CONCENTRATIONS o.F RADIONUCLIDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#25 Downstream (Hudson River)
~--------
- .. -~-
Sample Location VOP FISH VOPFISH VOPFISH VOP FISH VOP FISH VOP FISH Date 8/6/2010 8/13/2010 8/1312010 8/13/2010 8/28/2010 9/9J2010 Client ID IFl1254410SI IFH2 5441 OS3 IFH254410S4 IFH2544 lOSS IFII254410S6 IFl!254410S2 Req. CL CATFISH AMERICAN EEL WlIlTE PERCH STRIPED BASS SUN FISH Radionuclide (pCi) Be-1 <: 211.5 < 179.0 < 142.6 < 229.9 < 204.5 < 249.8 1-131 < ' ' ' flO [) < 15800.0 < 16100.0 < 26680.0 < 7573.0 < 5913.0 Cs-134 65 <: 5.2 < 9.6 < 9.5 < 6.6 < 10.6 < 11.3 Cs-137 75 <: 6.9 < 9.0 < 7A < 8.8 < 10A < 11.8 Zr-95 <: 31.5 < 31.2 < 35.7 < 39.6 < 38.3 < 45.0 Nb-95 <: 41.1 < 40A < 46.1 < 52.6 < 46.5 < 519 Co-58 65 <: 16.3 < 16.0 < 16.1 < 20.3 < 18.8 < 24A Mn-54 65 <: B.6 < 10.1 < 8.5 < 11.7 < 10.6 < 13.6 Zn-65 130 <: 20.4 < 25.1 < 23.2 < 27.3 < 27.6 < 18.6 Fe-59 130 <: 74.2 < 80.3 < 75.5 < 99.9 < 76.6 < 85.9 Co-60 65 <: 6.9 < 7.6 < 8.3 < 8.6 < 9.7 < 10A Ba/La-140 <: 1148.0 < 1076.0 < 834A < 1661.0 < 663.9 < 7165 Ru-103 <: 34.4 < 36.7 < 32.5 < 42.3 < 39.1 < 43.8 Ru-106 <: 98 . 9 < 106.9 < 89A < 131.1 < 111.7 < 131.2 Ce-141 <: 65.4 < 61.3 < 60.6 < 85.2 < 66.2 < 81.3 Ce-144 <: 50.7 < 48.1 < 46.7 < 71.8 < 62.3 < 77.2 AcTh-228 112.7 +1- 22.1 58.7 +/- 21.7 < 29.1 127.2 +/- 28.7 114.5 +/- 29A 123.3 +/- 31.0 Ra-226 603.7 +1- 114.5 < +/- 121.9 329.6 +/- 106.3 757.5 +/- 158.2 996.8 +/- 153.5 1289.0 +/- 192.1 K-40 2718.0 +1- 113.6 4157.0 +/- 153.1 2806.0 +/- 141.1 3607.0 +/- 164.1 7455.0 +/- 191.0 6753.0 +/- 223.8 Ni*63 100 <: 67.0 < 48.0 < 47.0 < 52.0 < 48.0 < 54.0 Sr-90 5 <: 2.9 < 2A < 2.9 < 4.3 < 3.2 < 3.3 8-40
TABLE B-15 (Continued) CONCENTRATIONS OF RADIONUCLlDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#23 Roseton (Control)
-.~-.-
--- ---.. ~~-~- .. -- ---.-- - - -
Sample ROSETON FISH ROSETON FISH ROSETON FISH ROSE TON FISH ROSETON FISH ROSETON FISH Location Date 5/13/2010 5113/2010 5/13/2010 5/1412010 6/1/2010 6/14/2010 Client ID lFH232710SI IFII23271OS3 IFII232710S4 IF1I2327I OS2 IFIl2327I OS5 IFII232710S6 Req. CL SUNFISH BLUE CRAB STRIPED BASS WHlTEPERCH AMERICAN EEL Radionuclide (pCi) Be-7 <: 245.3 < 314.1 < 244.4 < 267.6 < 318.2 < 174.7 1-131 <: 2716.0 < 3284.0 < 2613.0 < 2652.0 < 1034.0 < 179.5 Cs-134 65 < 17.7 < 20.2 < 12.8 < 17.9 < 25.2 < 11.2 Cs-137 75 <: 16.4 < 20.2 < 14.0 < 15.9 < 25.7 < 16.5 Zr-95 < 59.1 < 65.7 < 52.0 < 50.9 < 70.8 < 33.1 Nb-95 <: 61.6 < 60.4 < 59.0 < 49.1 < 55.1 < 25.2 Co-58 65 <: 28.2 < 33.2 < 28.6 < 28.2 < 30.0 < 15.0 i Mn-54 65 <: 11.9 < 20.9 < 19.2 < 14.8 < 24.6 < 14.8 Zn-65 130 <: 55_0 < 50.0 < 50.5 < 37.8 < 75.4 < 37.1 Fe-59 130 <: 114.4 < 116.8 < 96.9 < 106.3 < 77.4 <: 52.2 Co-60 65 <: 11.7 < 19.7 < 16.0 < 23.3 < 23.1 < 10.4 BalLa-140 <: 599.0 < 530.0 < 545.9 < 512.5 < 300.6 < 92.1 Ru-103 <: 48.1 < 52.6 < 45.3 < 40.9 < 61.5 < 21.7 Ru-106 181.9 < 215.6 < 193.4 < 210.3 < 213.4 < 162.2 Ce-141 82.5 < 91.3 < 71.8 < 74.1 < 69.8 < 34.5 Ce-144 <: 106.5 < 116.7 < 89.1 < 99.0 < 118.4 < 88.7 AcTh-228 <: 65.2 130.1 +/- 54.6 < 70.6 < 61.6 141.8 +1- 71.0 < 49.7 Ra-226 . 59'7'.fi +1- 261.4 1447.0 +/- 303.2 < 289.3 454.3 +/- 198.0 615.7 +/- 298.7 579.2 +/- 252.0 K-40 5204.0 +1- 316.4 8134.0 +/- 384.3 3457.0 +/- 298.8 3120.0 +/- 280.7 6528.0 +/- 475.4 3289.0 +/- 258.8 Ni-63 100 <: 54.0 < 63.0 < 68.0 < 64.0 < 64.0 < 76.0 Sr-90 5 <: 3.2 < 3.0 < 4.8 < 2.2 < 3.9 < 4.9 8-41
TABLE B-IS (Continued) CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
#23 Roseton (Control)
Sample ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH Location Date 8/412010 8/412010 8/4/2010 9/1/2010 9/9/2010 9/9/2010 Client ID II'm 3441OS2 IFH234410S3 IFH23441OS6 IFH234410S1 IFH2344lOS4 IFll2344I OSS Req. CL ,IIAFRI(,A N EEL BLUE CRAB CATFISH WHITE PERCH SUNFISH STRIPED BASS Radionuclide (pCi) Be-7 <: 229.6 < 234.5 < 284.7 < 174.6 <: 190.0 <: 259.3 1*131 <: 32260.0 <: 29160.0 < 35420.0 < 3152.0 <: 4895.0 <: 6483.0 Cs-134 65 <: 6.0 <: 6.4 < 11.7 <: 11.2 <: 11.6 < 14.8 Cs-137 75 <: 9.4 <: 7.9 <: 11.0 < 9.4 < 8.9 < 13.6 Zr-95 <: 40.7 <: 40.3 <: 47.5 < 38.6 < 32.0 <: 51.0 Nb-95 <: 50.6 <: 48.9 <: 65.6 <: 46.6 < 42.3 <: 55.5 Co-58 65 <: 19.2 <: 18.3 < 26.9 < 191 <: 20.3 <: 26.4 Mn-54 65 <: 9.5 <: 10.9 <: 12.2 < 10.2 <: 12.7 <: 16.2 Zn-65 130 <: 24.2 < 29.5 <: 16.2 <: 28.0 <: 31.3 <: 41.6 Fe-59 130 <: 79.1 <: 89.2 <: 114.6 <: 88.5 <: 88.5 <: 115.6 Co-60 65 < B.7 <: 8.9 <: 12.0 <: 11.1 <: 12.4 <: 15.9 BalLa-140 <: 1289.0 < 1675.0 < 1765.0 <: 369.7 <: 826.9 <: 868.1 Ru-103 < 42.5 <: 39.0 <: 55.3 <: 26.4 < 31.4 <: 44.4 Ru-106 <118.8 < 107.3 < 129.2 < 120.3 < 111.9 < 168.4 Ce-141 <: 78.6 < 73.5 <: 107.2 <: 56.0 < 63.9 < 70.2 Ce-144 < 63.8 < 49.7 < 73.4 < 69.5 < 63.8 < 68.7 AcTh-228 95.6 fl* 28.1 < 31.7 140.2 +1- 32.9 < 34.6 57.2 +1- 33.1 79.0 +1- 35.3 Ra-226 1079.0 +/- 147.2 436.4 +1- 127.1 814.5 +1- 166.4 493.7 +1- 185.8 753.9 +1- 170.1 757.1 +1- 169.8 K-40 2820.0 +/- 138.2 4161.0 +1- 168.2 5860.0 +1- 198.8 2774.0 +1- 199.7 3345.0 +1- 200.3 5338.0 +1- 244.6 Ni-63 100 <: 55.0 <: 47.0 <: 72.0 <: 48.0 <: 53.0 <: 51.0 Sr-90 5 <: 2.B < 2.6 <: 2.9 <: 2.9 < 3.1 <: 49 8-42
TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUA TIC VEGETATION SAMPLES - 2010 Results in Units ofpCilkg +/- 1 Sigma
~-
Sample Location COLDSPRING COLDSPRING LENTS COVE LENTS COVE VERPLANCK Date 7/112010 9113/2010 7/112010 9/13/2010 6/312010 Client LD IAVS42610 lAV843710 lAV2S2610 IAV283710 lAVl72210 MYRO MYRO MYRO MYRO MYRO Radionuclide (pCi) Be-? 118.8 +/- 35.0 < 50.2 90.3 +/- 37.9 < 53.5 445.0 +/- 69.2 1-131 30 < 8.7 < 9.1 < 9.8 < 10.4 < 16.6 Cs-134 30 < 6.0 < 7.4 < 3.7 < 7.6 < 5.1 Cs-137 40 16.8 +/- 3.1 < 6.5 17.6* +/- 3.4 < 5.1 < 7.6 Zr-95 < 10.4 < 8.8 < 8.2 < 10.1 < 14.6 Nb-95 < 6.1 < 6.6 < 6.0 < 6.9 < 9.0 Co-58 < 5.7 < 6.8 < 5.0 < 6.4 < 10.3 Mn-54 < 4.6 < 5.8 < 5.4 < 6.5 < 9.8 Zn-65 < 11.2 < 16.9 < 13.0 < 9.5 < 30.9 Fe-59 < 14.4 < 16.1 < 14.4 < 13.7 < 35.7 Co-60 < 5.3 < 5.9 < 4.8 < 4.9 < 12.3 BalLa-140 < 7.3 < 9.2 < 7.6 < 11.5 < 17.1 Ru*103 < 5.2 < 6.1 < 4.8 < 6.1 < 8.5 Ru-106 < 40.5 < 53.3 < 60.2 < 61.5 < 87.6 Ce-141 < 8.0 < 9.7 < 8.6 < 8.4 < 12.4 Ce-144 < 31.5 < 33.0 < 38.2 < 32.8 < 49.0 AcTh*228 131.6 +/- 19.0 109.8 +/- 19.9 250.5 +/- 22.0 180.0 +/- 22.2 134.7 +/- 29.4 Ra-226 273.3 +/- 67.0 239.7 +/- 87.1 575.9 +/- 96.6 315.6 +/- 84.4 363.8 +/- 146.3 K-40 4573.0 +/- 145.9 1728.0 +/- 126.1 3162.0 +/- 126.7 1555.0 +1- 108.3 4782.0 +1- 238.9 greater than critical level, but less than LLD 8-43
TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma
~
Sample COLDSPRING COLDSPRING LENTS COVE LENTS COVE VERPLANCK VERPLANCK Ii Location Date 6/2/2010 9/13/2010 6/2/2010 911312010 6/312010 9/14/2010 Client ID IBS842210 lBS843710 IBS282210 IBS283710 lBS 172210 lBSI73710 Req. CL Radionuclide (pCi) Be-7 << 299.5 < 321.1 < 373.1 < 706.9 < 345.6 < 469.0 1-131 << 87.2 < 64.1 < 79.5 < 157.3 < 98.6 < 117.2 Cs-134 75 << 34.2 < 48.5 < 40.9 < 53.8 < 39.5 < 37.1 Cs-137 90 <<~67 < 43.9 338.3 +/- 54.6 < 70.3 327.4 +/- 51.1 349.6 +/- 67.1 Zr-95 << .1?J1 < 87.1 < 65.7 < 122.6 < 82.2 < 109.6 Nb-95 << 47.2 <: 55.3 <: 56.3 <: 79.7 <: 65.8 <: 73.9 Co-58 <: 53.2 <: 47.1 <: 41.9 < 59.5 <: 40.4 <: 58.6 Mn-54 <: 39.7 <: 42.1 <: 48.1 <: 70.6 <: 40.0 <: 83.7 Zn-65 <: 860 <: 70.2 <: 155.2 <: 203.4 <: 149.1 <: 231.9 Fe-59 << 142.6 < 129.8 < 134.7 < 185.8 <: 117.6 < 216.9 Co-60 <: 37.7 < 40.4 <: 52.1 < 101.8 < 54.3 <: 68.1 BalLa-140 <: 51.3 < 57.2 <: 68.4 <: 169.6 <: 56.4 < 122.8 Ru-103 << 45.9 <: 35.0 <: 46.9 <: 67.2 < 53.0 < 70.6 Ru-106 <: 417.1 <: 409.4 < 497.6 <: 539.8 < 471.6 <: 773.5 Ce-141 <: 71.6 < 73.2 < 75.6 < 115.0 < 80.0 < 89.3 Ce-144 <: 277.1 <: 271.1 <: 253.9 < 368.4 < 307.5 <: 388.1 AcTh*228 934.7 +/- 167.5 969.5 +/- 159.7 1373.0 +/- 198.1 1587.0 +/- 296.2 1298.0 +/- 178.4 781.1 +/- 239.5 Ra-226 1539.0 +/- 604.7 2974.0 +/- 721.7 2829.0 +/- 843.8 2429.0 +/- 1117.0 1650.0 +/- 621.9 2772.0 +/- 1055.0 K-40 36350.0 ~1~_ 1527.0 35920.0 +/- 1361.0 20700.0 +/- 1333.0 27570.0 +/- 1825.0 22930.0 +1- 1212.0 26100.0 +/- 1654.0 8-44
CONCENTRATIONS O:F GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma !I Sample location I DISCHARGE CANAL I DISCHARGE CANAL I Date 613/2010 9/14/2010 Client ID lBSI02210 lBSlO3710 Req. CL Radionuclide (pCi) Be-7 < 276.0 < 510.6 1*131 < 56.6 < 95.8 Cs-134 75 < 24.9 < 41.3 Cs-137 90 417.6 +/- 39.7 1330.0 +/- 62.8 Zr-95 < 43.4 < 77.8 Nb*95 < 34.4 < 68.0 Co-58 < 27.1 < 55.9 Mn-54 < 30.9 < 56.3 2:n-65 < 88.5 < 75.2 Fe-59 < 96.0 < 123.8 Co-60 < 31.2 < 51.6 BalLa-140 < 51.2 < 85.7 Ru-103 < 31.6 < 54.3 Ru-106 < 251.9 < 437.1 Ce-141 < 49.2 < 93.8 Ce-144 < 184.8 < 386.5 AcTh-228 386.0 +/- 102.3 1274.0 +/- 210.5 Ra-226 1120.0 +/- 524.1 5143.0 +/- 1068.0 K-40 17640.0 +/- 846.9 23370.0 +/- 1295.0 8-45
TABLE B-18 CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2010 Results in Units of pCi/L +/- 1 Sigma Sample PEEKSKILL PEEKSKILL PEEKSKILL PEEKSKILL Location RAINWATER RAINWATER RAINWATER RAINWATER Date 3/29/2010 6/28/2010 9/27/2010 12/28/2010 Client In Req. CL JRF44QIIO IRl'44Q210 IRF443QIO IRF44Q410 IRadionuclide (pei) H-3 < 403.0 < 397.0 < 409.0 < 408.0 Be-7 < 36.6 < 27.4 < 36.5 < 35.3 1*131 < 27.3 < 19.5 < 19.3 < 34.8 Cs-134 7.5 < 1.6 < 1.5 < 2.7 < 2.7 Cs-137 9 < 2.2 < 2.2 < 2.5 < 2.4 Zr-95 < 7.6 < 5.3 < 6.8 < 7.9 Nb-95 < 4.8 < 4.8 < 5.0 < 5.9 Co-58 < 3.3 < 3.3 < 2.9 < 4.3 Mn-54 < 2.5 < 2.2 < 2.2 < 2.8 Zn-65 < 7.5 < 6.1 < 6.4 < 6.7 Fe-59 < 7.2 < 11.6 < 13.7 < 10.9 Co-60 7.5 < 1.8 < 1.8 < 2.6 < 2.2 BalLa-140 < 9.4 < 13.9 < 14.3 < 18.1 Ru-103 < 4.9 < 4.8 < 4.7 < 5.6 Ru-106 < 27.3 < 25.7 < 22.9 < 25.1 Ce-141 < 9.8 < 8.0 < 9.3 < 10.7 Ce-144 < 21.6 < 15.6 < 18.8 < 19.0 AcTh*228 < 9.3 < 7.5 24.2 +/- 7.3 < 7.7 Ra-226 < 54.7 < 50.6 < 56.9 < 59.7 K-40 86.2 +/- 20.9 82.3 +/- 20.8 407.2 +/- 36.0 407.9 +/- 37.1 B*46
TABLE B-18 (Continued) CONCENTRAnONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 201 0 Results in Units of pCi/L +/- 1 Sigma ROSETON ROSETON ROSETON ROSETON Location RAINWATER RAINWATER RAINWATER RAINWATER Date 3/2912010 6/29/2010 9/27/2010 12/28/2010 Req. CL IRF23QllO IRF23Q21O lRF233QIO IRF23Q410 Radionuclide (pCi) H*3 < 403.0 < 397.0 < 409.0 < 408.0 Be-7 < 33.0 45.6 +/- 23.2 < 42.7 < 47.8 1*131 < 20.4 < 17.6 < 33.7 < 35.2 Cs-134 7.5 < 1.7 < 1.4 < 3.9 < 4.0 Cs-137 9 < 2.2 < 1.8 < 3.4 < 3.6 Zr-95 < 7.0 < 4.8 < 8.6 < 7.2 Nb-95 < 5.1 < 4.0 < 7.8 < 5.0 Co-58 < 4.6 < 2.6 < 4.3 < 4.9 Mn-54 < 2.7 < 1.9 < 3.4 < 3.5 Zn-65 < 6.3 < 4.9 < 10.2 < 11.8 Fe-59 < 14.6 < 6.8 < 18.9 < 20.2 Co-60 7.5 < 2.6 < 1.7 < 2.8 < 3.0 BalLa-140 < 20.1 < 10.3 < 23.9 < 29.3 Ru-103 < 5.1 < 3.3 < 6.2 < 6.6 Ru-106 < 25.3 < 24.0 < 36.1 < 36.8 Ce-141 < 10.1 < 6.9 < 12.5 < 12.3 Ce-144 < 22.3 < 16.1 < 24.3 < 24.1 AcTh*228 < 11.4 9.7 +/- 4.3 < 15.2 < 10.5 Ra*226 < 56.1 64.0 +/- 34.2 < 69.6 141.9 +/- 60.2 K-40 < 24.8 < 19.3 476.1 +/- 47.5 350.9 +/. 44.7 Location 9-47
TABLEB-19 CONCENTRATlONS OF GAMMA EMITTERS IN SOIL SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample Location ROSETON MET TOWER TRAINING BLDG Date 9/2712010 9127/2010 9/27/2010 Client ID IS0233910 IS0953910 IS0943910 Req. CL Radionuclide (pCi) Be-7 < 263.5 < 357.5 < 278.0 1-131 < 42.6 < 48.2 < 37.6 I Cs-134 75 < 34.8 < 28.0 < 23.4 Cs-137 90 < 44.5 < 45.9 < 40.1 Zr-95 < 64.8 < 69.1 < 61.9 Nb-95 < 46.3 < 52.7 < 34.4 Co-58 < 39.4 < 47.6 < 39.0 Mn-54 < 45.5 < 53.5 < 34.5 Zn-65 < 115.6 < 139.5 < 100.8 Fe-59 < 103.6 < 165.4 < 110.8 C0-60 < 44.4 < 57.0 < 41.1 BalLa-140 < 37.2 < 65.4 < 48.8 Ru-103 < 32.1 < 36.7 < 29.6 RU-106 < 378.0 < 493.8 < 361.1 Ce-141 < 57.5 < 55.6 < 49.3 Ce-144 < 266.9 < 236.8 < 194.6 AcTh-228 1073.0 +/- 175.9 573.8 +/- 169.2 594.7 +/- 123.5 Ra-226 2249.0 +/- 691.0 2284.0 +/- 657.7 2296.0 +/- 662.6 K-40 21180.0 +/- 1198.0 26370.0 +/- 1328.0 17820.0 +/- 989.7
~ ~ ... .'
8-48
TABLE B-20 CONCENTRATIONS OF RADIONtJCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/- 3 sigma Monitoring Well MW-LAF MW-LAF-001-013 MW-LAF MW-LAF-002-014 1 Sample Name Sample Date 5/11/2010 11/22/2010 Radionuclide ReQ. MDC H-3 < 163 < 121 Cs-137 18 < 7.6 < 6.8 Co-60 < 6.1 < 6.2 Sr-90 1 < 0.78 < 0.54 Ni-63 < 25.4 < 20.5 Note 1: Less than values "<" are Minimum Detectable Concentration (MOC) values. Note 2: A sample is positive if the result is greater than or equal to the MDC. 8-49
Table 8-21 LAND USE CENSUS* RESIDENCE and MILCH ANIMAL RESULTS 2010 The 2010 land use census indicated there were no new residences that were closer in proximity to IPEC. NEM maintains a complete nearest residence survey with updated distances. No milch animals were observed during this reporting period within the 5-mile zone nor were listed in the New York Agricultural Statistic Service. There are no animals producing milk for human consumption within five miles of Indian Point. 8-50
TABLE B-22 LAND USE CENSUS 2010 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES Distance to Distance to site Distance to site nearest resident, Boundary from Boundary from from Unit 1 Unit 2 Plant Vent Unit 3 Plant Vent superheater Address of nearest resident, Last Sector Compass Point (meters) (meters) (meters) Census 1 N RIVER RIVER 1788 41 River Road Tomkins Cove 2 NNE RIVER RIVER 3111 Chateau Rive Apts. John St. Peekskill 3 NE 550 636 1907 122 Lower South St. Peekskill 4 ENE 600 775 1478 1018 Lower South St. Peekskill 5 E 662 785 1371 1103 Lower South St. Peekskill 6 ESE 569 622 715 461 Broadway Buchanan 7 SE 553 564 1168 223 First St. Buchanan 8 SSE 569 551 1240 5 Pheasant's Run Buchanan 9 S 700 566 1133 320 Broadway Verplanck 1Q SSW 755 480 1574 240 Eleventh St. Verplanck 11 SW 544 350 3016 8 Spring St. Tomkins Cove 12 WSW RIVER RIVER 2170 9 West Shore Dr. Tomkins Cove 13 W RIVER RIVER 1919 712 Rt. 9W Tomkins Cove 14 WNW RIVER RIVER 1752 770 Rt. 9W Tomkins Cove 15 NW RIVER RIVER 1693 807 Rt. 9W Tomkins Cove 16 NNW RIVER RIVER 1609 4 River Rd. Tomkins Cove 8-51
APPENDIX C HISTORICAL TRENDS
APPENDIX C The past ten years of historical data for various radionuclides and media are presented both in tabular form and in graphical form to facilitate the comparison of 2010 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present. Averaging only the positive values in these tables can result in a biased high value, especially, when the radionuclide is detected in only one or two quarters for the year. C-1
TABLE C-1 DIRECT RADIATION ANNUAL
SUMMARY
2000-2010 Average Quarterly Dose (mRlQuarter) Control Year Inner Ring Outer Ring
~.
Location 2000 14.0 15.0 16.0 2001 15.0 15.0 17.0 2002 15.0 15.0 14.0 2003 14.3 13.9 14.7 2004 13.0 13.0 14.0 2005 14.1 14.1 15.9 2006 13.9 14.3 17.5 2007 14.4 14.6 18.8 2008 14.5 14.2 17.3 2009 14.5 14.2 17.3 2010 14.0 14.3 13.0 Historical Average 14.3 14.3 16.2 , 2000-2009 C-2
FIGURE C-1 DIRECT RADIATION, ANNUAL
SUMMARY
2000 to 2010 40.0 _ Inner Ring 35.0 1< 1Outer Ring I - Control Location l _..... _._ .. ... . ..... . _. _.. _._ .. . . 30.0
- 25.0 1
- :
IV
- I o
~ 20.0 C IV Q) ~ 15.0 10.0 5.0 0.0 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 C-3
TABLE C-2 RADIONUCLIDES IN AIR 2000 to 2010 (pCi/m3) Gross Beta Cs-137 All Indicator Control All Indicator Control Year Locations Location Locations Location 2000 0.01 0.01 < Lc < Lc 2001 0.02 0.02 < Lc < Lc 2002 0.02 0.02 < Lc < Lc 2003 0.01 0.01 < Lc < Lc 2004 0.01 0.01 < Lc < Lc 2005 0.02 0.02 < Lc < Lc 2006 0.01 0.01 < Lc < Lc 2007 0.01 0.01 < Lc < Lc 2008 0.01 0.01 < Lc < Lc 2009 0.01 0.01 < Lc < Lc 2010 0.01 0.01 < Lc < Lc Hist()rical Ave,.ag. 0.01 0.01 < Lc < Lc 2000..2009 Critical Level (Lc) is less than the ODCM required LLD. level. C-4
FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 2000 to 2010 0.05
~ Allindicator Locations
, - Control Location 1.... _ .... _........ ._ . _ ...._ .. __ .. ... . . . .. _ ... ... __ . . . .
0.04 0.03
~
o Q. 0.02 0.01 o.00 I",,,,, rc 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010
- Includes ODCM and non-ODCM indicator locations.
Gross Beta ODCM required LLD :: 0.01 pCi/m3 C-5
TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 2000 to 2010 (pCi/L) Tritium (H-3) Cs*137 Year Inlet Discharge Inlet Discharge 2000 190 267 < Lc < Lc 2001 < Lc 323 < Lc < Lc 2002 432 562 < Lc < Lc 2003 < Lc < Lc < Lc < Lc 2004 < Lc 553 < Lc < Lc 2005 < Lc 618 < Lc < Lc 2006 < Lc 386 < Lc < Lc 2007 < Lc < Lc < Lc < Lc 2008 < Lc < Lc < Lc < Lc 2009 < Lc < Lc < Lc < Lc 2010 428 < Lc < Lc < Lc Historical Average 311 452 < Lc < Lc 2000-2009 Critical Level (Lc) is less than the aDCM required LLD. indicates values level. C-6
FIGURE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 2000 to 2010 2000 ,--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------, o Inlet (H-3) 1800
~ Discharge (H-3) 1600 1400 .
1200
...J o:::. 1000 Q.
800 600 400 200 o p o .... K'O un ~IO UC4 VI. rLOI _e, 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Tritium aDCM required LLD =3000 pC ilL C-7
TABLE C-4 RADIONUCLIDES IN DRINKING WATER 2000 to 2010 (pCi/L) Year Tritium (H-3) Cs-137 2000 <Lc < Lc 2001 <Lc < Lc 2002 < Lc < Lc 2003 < Lc < Lc 2004 <Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 <Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 < Lc < Lc Historical Average
< Lc < Lc 2000-2009 , ~
, ~,
Critical Level (Lc) is less than the ODCM required LLD. <Lc indicates no positive values above sample critical level. C-8
FIGURE C-4 RADIONUCLIDES IN DRINKING WATER 2000 to 2010 2000 1800 1600 1400 1200
..J G 1000 Q. NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEARS HISTORY 800 600 400 200 o ~'------------------------~-------r------~--------~------~-------r------------------------~
2000 2002 2003 2004 2005 2006 2007 2008 2009 2010 Tritium ODCM required 2000 pCi/L C-9
TABLE C-S RADIONUCLIDES IN SHORELINE SOIL 2000 to 2010 (pCi/Kg, dry) Cs-134 Cs-137 Year Indicator Control Indicator Control 2000 58 < Lc 179 231 2001 45 < Lc 230 427 2002 < Lc < Lc 221 238 2003 < Lc < Lc 124 73 2004 < Lc < Lc 104 138 2005 < Lc < Lc 156 36 2006 < Lc < Lc 120 < Lc 2007 < Lc < Lc 190 < Lc 2008 < Lc < Lc 187 < Lc 2009 < Lc < Lc 149 < Lc 2010 < Lc < Lc 127 < Lc Historical Average 52 < Lc 166 191 2000-2009 . .. Critical Level (Lc) is less than the RETS required LLD. <Lc indicates no positive values above sample critical level. C-10
FIGURE C-S RADIONUCLIDES IN SHORELINE SOIL 750 I 2000 to 2010 D Indicator (Cs-134) 650 D Control (Cs-134) Indicator (Cs-137) 550 I -Control (Cs-137) L.__ _ _ _ __ _ ._. ___ .___ .. ___ _ 450
~ "tl c) 350 -~ ~
250 150 501_~ :'. ~ 0,
~,.:~
~ ' \. -_..
W ~..
'if 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010
-50 ~--------------------------------------------------------------------------------------------~
Cs-134 ODCM required LLD =150 pCilKg, dry Cs-137 ODCM required LLD =175 pCi/Kg, dry C-11
TABLE C-6 BROAD LEAF VEGETATION - Cs-137 2000 to 2010 (pCi/Kg, wet) Cs-137 Year Indicator Control 2000 28 < Lc 2001 7 < Lc 2002 14 16 2003 14 < Lc 2004 10 < Lc 2005 < Lc <Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 31 < Lc Historical Average 15 16 2000-2009 , Critical Level (Lc) is less than the ODCM required LLD. <Lc indicates no positive values above sample criticalleve!. C-12
FIGURE C-G BROAD LEAF VEGETATION - Cs-137 2000 to 2010 100 (;3 Indicator (Cs-137) o Control (Cs-137) 80
-~
0; 60 x:: (.) Q. 40* 20 0' t ~ i \ ,. AI 1" ','\,1 t~ l A'A A'1 ", J 2000 2002 2003 2004 2005 2006 2007 2008 2009 2010 aDeM required LLD ::: 80 wet C-13
TABLE C-7 FISH AND INVERTEBRATES - Cs-137 2000 to 2010 (pCi/Kg, dry) Cs-137 Year Indicator Control 2000 < Lc < Lc 2001 < Lc < Lc 2002 < Lc < Lc 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 2009 < Lc < Lc 2010 < Lc < Lc HistoriccdAverage 2000-2009 . .
< Lc < Lc Critical Level (Lc) is less than the aDCM required LLD.
<Lc indicates no positive values above sample critical level. C-14
FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 2000 to 2010 200
~ Indicator (Cs-137) 180 o Control (Cs-137) 160 140 -~
120 cil 100
~
(3 Q. 80 NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEARS HISTORY 60 40 20 0 2000 2002 2003 2004 2005 2006 2007 2008 2009 2010 Cs-137 aDCM required 50 pCilKg, wet C-15
APPENDIX D INTERLABORATORY COMPARISON PROGRAM
0.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia. Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the JAF Environmental Laboratory using standard laboratory procedures. Analytics issues a statistical summary report of the results. The JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance. The JAF Environmental Laboratory also analyzes laboratory blanks. The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples. The analysis of analytical blanks also provides information on the adequacy of background subtraction. Laboratory blank results are analyzed using control charts. D-
0.2 Table 01: PROGRAM SCHEDULE SAMPLE PROVIDER SAMPLE LABORATORY ECKERT & ZIEGLER MEDIA ANALYSIS ANALYTICS Water Gross Beta 3 Water Tritium 5 Water /-131 4 Water Mixed Gamma 4 Air Gross Beta 3 Air /-131 4 Air Mixed Gamma 2 Milk /-131 3 Milk Mixed Gamma 3 Soil Mixed Gamma 1 Vegetation Mixed Gamma 2 TOTAL SAMPLE INVENTORY 34 0.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below. 0.3.1 SAMPLE RESULTS EVALUATION Samples provided by Analytics are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by participating laboratory (QC Known
An Environmental Laboratory analytical result is evaluated using the following calculation: The value for the error resolution is calculated. The error resolution = Reference Result Reference Results Error (1 sigma) Using the appropriate row under the Error Resolution column in Table 8.3.1 below, a corresponding Ratio of Agreement interval is given. The value for the ratio is then calculated. Ratio = ac Result of Agreement Reference Result If the value falls within the agreement interval, the result is acceptable. TABLE 02 ERROR RESOLUTION RATIO OF AGREEMENT
<4 No Comparison 4to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 I
51 to 200 0.8 to 1.25
>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria are contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. method is used as the procedurally required assessment method generation a deviation report when results are D 3
0.4 PROGRAM RESULTS
SUMMARY
The Interlaboratory Comparison Program numerical results are provided on Table 8-1. 0.4.1 ECKERT & ZIEGLER ANAL YTICS QA SAMPLES RESULTS Thirty-four QA blind spike samples were analyzed as part of Analytics 2010 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.
- Air Charcoal Cartridge: 1-131
- Air Particulate Filter: Mixed Gamma Emitters, Gross Beta
- Water: 1-131, Mixed Gamma Emitters, Tritium, Gross Beta
- Soil: Mixed Gamma Emitters
- Milk: 1-131, Mixed Gamma Emitters
- Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 129 individual analyses on the 34 QA samples. Of the 129 analyses performed, 129 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.
There were no nonconformities in the 2010 program.
0.4.2 NUMERICAL RESULTS TABLES TABLE 03 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE 1AF ELAB RESuLTS REFERENCE LAB
- DATE IDNO. MEDIUM ANALYSI~ pCi +1 sigma pCi +/-1 sigma RATIO (I) 0611712010 E7090-05 Filter 8.61E+Ol +/- 2.30E+OO GROSS 8. 15E+Ol +/- 2.24E+OO 8.04E+Ol +/- 1.34E+O( l.05 A BETA 8.63E+Ol +/- 2.30E+OO Mean = 8.46E+Ol + I.3IE+OO 0611712010 E7097-09 Filter 5.99E+Ol +/- 1.92E+OO GROSS 5.89E+01 +/- 1.9 I E+OO 5.39E+Ol +/- 9.0IE-01 l.1O A BETA 5.98E+Ol +/- 1. 92 E+OO Mean = 5.95E+Ol + 1.1IE+OO 12/0912010 E7354-05 Filter 9.69E+Ol +/- 1.39E+OO GROSS 9.46E+Ol +/- 1.38E+OO 8.92E+Ol +/- 1.49E+O( 1.07 A BETA 9.39E+Ol +/- 1.37E+OO Mean = 9.51E+01 +/- 7.98E-01 (1) Ratio = Reported!Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable D - 5
TABLE D3 (Continued) Tritium Analysis of Water SAl'v1PLE JAP ELAB REStJLTS REFERENCE LAB
- DATE IDNO. tv1EDIUN ANALYSI~ DCi/liter + I sigma DCi/liter + 1 sigma RATIO_(I) 3/1812010 E7020-05 Water H-3 3.48E+03 +/- 1.53E+02 3.57E+03 +/- 1.53E+02 3.4IE+03 +/- 5.70E+O 1.03 A 3.53E+03 +/- 1.53E+02 Mean = 3.53E+03 +/- 8.83E+01 0611712010 E7089-05 Water H-3 1.14E+03 +/- 1.33E+02 1.I3E+03 +/- 1.32E+02 1.04E+03 +/- 1.32E+02 I.OOE+03 +/- 1.29E+02 9.58E+02 +/- 1.60E+O 1.13 A 1.07E+03 +/- 1.30E+02 1.13E+03 +/- 1.30E+02 Mean = 1.09E+03 +/- 5.35E+Ol 9116/2010 E7 I 87-05 Water H-3 8.82E+02 +/- 1.31E+02 8.54E+02 +/- 1.31E+02 8.96E+02 +/- 1.50E+O 1.01 A
- 9. 74E+02 +/- I. 32E+02 Mean = 9.03E+02 + 7.58E+Ol 12/912010 E7329-09 Water H-3 1.00E+04 +/- 2.04E+02 I.00E+04 +/- 2.04E+02 9.96E+03 +/- 1.66E+O 1.00 A 9.9 I E+03 +/- 2.04E+02 Mean = 9.98E+03 +/- 1.18E+02 12/912010 E7330-09 Water H-3 9.78E+03 +/- 2.03E+02 9.83E+03 +/- 2.03E+02 9.96E+03 +/- 1.66E+O 0.99 A 1.01E+04 +/- 2.05E+02 Mean = 9.90E+03 +/- 1.18E+02 (l) RatIO =ReportedlAnalytlcs.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable
TABLE D3 (Continued) Gross Beta Analysis of Water SAMPLE lAF ELAB RESULTS REFERENCE LAB
- DATE IDNO. MEDIUM ANALYSIS pCi/liter + I sigma pCi/liter +/-I sigma RATIO (I) 03/18/2010 E7023-05 Water 2.58E+02 +/- 2.50E+OO GROSS 2.57E+02 +/- 2.50E+OO 2.60E+02 +/- 4.35E+OO 0.98 A BETA 2.54E+02 +/- 2.50E+OO Mean:: 2.56E+02 +/- I.44E+OO 0611712010 E7095-05 Water 1.78E+02 +/- 2.IOE+00 GROSS 1.78E+02 +/- 2.IOE+OO 1.88E+02 +/- 3.14E+OO 0.95 A BETA 1.79E+02 +/- 2.IOE+OO Mean:: 1.78E+02 +/- 1.21E+OO 09/16/2010 E7192-05 Water 2.30E+02 +/- 2.40E+OO 2.28E+02 +/- 2.40E+OO GROSS 2.26E+02 +/- 2.40E+OO 2. 18E+02 +/- 3.64E+OO 1.04 A BETA 2.25E+02 +/- 2.40E+OO Mean:: 2.27E+02 +/- 1.20E+OO (I) Ratio:: Reported!Analytics.
- Sample provided by Analytics, Inc.
A::Acceptable U::Unacceptable 7
TABLE 03 (Continued) 1*131 Gamma Analysis of Air Charcoal SAMPLE JAF ELAB RESULTS REFERENCE LAB
- DATE IDNO. MEDIUM ANALYSIS pCi +1 sigma pCi +1 sigma RATIO (I) 311812010 E6993-09 Air 8.62E+OI +/- 2.23E+OO 8.27E+Ol +/- 2. 88E+OO 1-131 8.IOE+OI +/- 1.81E+OO 8.S2E+01 +/- 1.42E+OO 0.99 A 8.90E+Ol +/- 3.6SE+OO Mean = 8.47E+Ol +/- 1.37E+OO 06117/2010 E7093-0S Air 7.94E+Oi +/- I.4SE+oO 7.64E+01 +/- 2.98E+OO 1-131 7.98E+Ol +/- 1.33E+OO 0.99 A 8.08E+Ol +/- 3.07E+OO Mean = 7.89E+OI +/- I.SIE+OO 9/16/2010 E7191-05 Air 6.01E+Ol +/- 1.2SE+OO 6.39E+Ol +/- 2.24E+OO 1-131 6.00E+Ol +/- 1.OOE+OO 1.03 A 6.06E+Ol +/- 2.00E+OO Mean = 6.15E+Ol +/- 1.08E+OO 9/1612010 E7183-09 Air 6.09E+Ol +/- 2.23E+OO 6.19E+01 +/- 2.83E+OO 1-131 S.97E+01 +/- 9.97E-01 1.03 A 6.08E+01 +/- 2.98E+OO Mean::: 6.12E+01 +/- 1.S6E+OO (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB* DATE 10:-..10. MEDIUM ANALYSIS pCi /liter +/- 1 sigma pCi/liter +/- 1 sigma RATIO (I) 3/18/2010 E7021-0S Water 2.73E+02 +/- 7.49E+OO 2.71E+02 +/- 3.S3E+OO Ce-141 2.63E+02 +/- 4.40E+OO 1.04 A 2.7SE+02 +/- 7.24E+OO Mean = 2.73E+02 +/- 3.67E+OO 3.42E+02 +/- 2.97E+OI 3.84E+02 +/- 1.29E+OI Cr-51 3.64E+02 +/- 6.08E+OO 1.03 A 3.98E+02 +/- 2.76E+01 Mean = 3.75E+02 +/- 1.42E+OI 2.03E+02 +/- 5.40E+OO 1.91E+02 +/- 5.85E+00 Cs-134 I. 79E+02 +/- 2.99E+OO 1.09 A 1.91 E+02 +/- 3.29E+OO Mean = 1.95E+02 +/- 2.87E+OO 1.64E+02 +/- 5.04E+OO 1.56E+02 +/- 5.67E+OO Cs-137 1.59E+02 +/- 2.66E+OO 1.0! A 1.60E+02 +/- 2.90E+OO Mean = t.60E+02 +/- 2.7 1E+OO I. 47 E+02 +/- 4.50E+OO 1.46E+02 +/- 5.39E+OO Co-58 t.44E+02 +/- 2.40E+OO 1.03 A 1.5IE+02 +/- 2.73E+OO Mean = 1.48E+02 +/- 2.5IE+OO 2.24E+02 +/- 5.62E+OO 2.24E+02 +/- 6.45E+OO Mn-54 2.09E+02 +/- 3.49E+OO I. 07 A 2.22E+02 +/- 3.37E+OO Mean == 2.23E+02 +/- 3.07E+OO 1.48E+02 +/- 5.43E+OO 1.54E+02 +/- 6.52E+OO Fe-59 1.38E+02 +/- 2.3IE+OO 1.09 A 1.52E+02 +/- 3.26E+OO Mean = I.5IE+02 +/- 3.03E+OO 2.92E+02 +/- I. 02 E+OI 2.66E+02 +/- 1.14E+0l Zn-65 2.56E+02 +/- 4.27E+OO 1.09 A 2.77E+02 +/- 5.88E+OO Mean = 2.79E+02 +/- 5.45E+OO 1.85E+02 +/- 3.89E+OO 1.9 I E+02 +/- 4.64E+OO Co-60 1.85E+02 +/- 3.()8E+OO 1.03 A 1.92E+02 +/- 2.41 E+OO Mean: L90E+02 +/- 2.!7E+OO 7.IIE+O! 7.18E-0I 7.
+/-
Mean == 7.36E+OI +/- 9.05E-01 (I) Ratio = Reported! Analytics.
- Sample provided by Analytics. Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB
- DATE 10 NO. MEDIUM ANALYSIS pCi/liter +/-I sigma pCi/liter +/-I sigma RATIO (I) 611712010 E7096-09 Water 1.70E+02 +/- 3.17E+OO 1.74E+02 +/- 2.83E+OO Ce-141 1.61E+02 +/- 2.68E+OO 1.07 A 1.74E+02 +/- 5.76E+OO Mean = 1.73E+02 + 2.39E+OO 5.26E+02 +/- 1.51E+OI 5.12E+02 +/- 1.62E+01 Cr-51 4.94E+02 +/- 8. 25E+OO 0.99 A 4.31E+02 +/- 2.96E+01 Mean = 4.90E+02 +/- 1.23E+01 2.01E+02 +/- 2.33E+OO 1.92E+02 +/- 2.77E+OO Cs-134 1.83E+02 +/- 3.06E+OO 1.08 A 2.02E+02 +/- 5.04E+OO Mean = 1.98E+02 +/- 2.07E+OO 2.26E+02 +/- 2.44E+OO 2.22E+02 +/- 2.74E+OO Cs-137 2. I 8E+02 +/- 3.65E+OO 1.04 A 2.30E+02 +/- 5.25E+OO Mean = 2.26E+02 +/- 2.13E+OO 1.57E+02 +/- 2.IIE+OO 1.55E+02 +/- 2.49E+OO Co-58 1.47E+02 +/- 2.46E+OO 1.07 A 1.61E+02 +/- 4.68E+OO Mean = 1.58E+02 +/- 1.90E+OO
- 2. 71 E+02 +/- 2.63E+OO 2.74E+02 +/- 3.01E+OO Mn-54 2.46E+02 +/- 4.IIE+OO 1.10 A 2.67E+02 +/- 5.56E+OO Mean = 2.71E+02 +/- 2.28E+OO 1.89E+02 +/- 2.77£+00 1.91E+02 +/- 3. 27E+OO Fe-59 1.73E+02 +/- 2. 89E+OO 1.08 A 1.80E+02 +/- 5.96E+OO Mean = 1.87E+02 +/- 2.45E+OO 3.29E+02 +/- 4.42E+OO 3.34E+02 +/- 5.42E+OO Zn-65 3.00E+02 +/- 5.00E+00 1.11 A 3.38E+02 +/- 1.0lE+OI Mean = 3. 34E+02 +/- 4.IOE+OO 2.99E+02 +/- 2.06E+OO 2.99E+02 +/- 2.44E+00 Co-60 2.86E+02 +/- 4.78E+OO 1.05 A 3.00E+02 +/- 4.55E+OO Mean:::: 2.99E+02 +/- 1.85E+OO 8.15E+01 +/- 2.25E+OO
- 2. 76E+OO i7. 1?E+o()
7.94E+OI +/- 3E+OO Mean:::: 8.IIE+01 +/- 1.36E+OO (I) Ratio:::: RtpvH<odl Anahtics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable
TABLE D3 (Continued) I~TERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB
- DATE IDNO. MEDIUM A.1'IlALYSIS pCi/liter +/-l sigma pCi/liter +/-I sigma RATIO (I) 9/1612010 E7188-05 Water 1.77E+02 +/- 5.28E+OO 1.80E+02 +/- 5.73E+OO Ce-141 1.65E+02 +/- 2. 76E+OO 1.09 A 1.8IE+02 +/- 3.26E+OO Mean = 1.79E+02 + 2. 82E+oo 3.44E+02 +/- 2.19E+01 3.07E+02 +/- 2.85E+01 Cr-51 2.97E+02 +/- 4.95E+OO 1.06 A 2.96E+02 +/- 1.48E+Ol Mean = 3.16E+02 +/- 1.30E+01 1.22E+02 +/- 3.92E+OO 1.23E+02 +/- 5.49E+OO Cs-134 1.18E+02 +/- 1.97E+OO 1.05 A I. 27E+02 +/- 2.77E+OO Mean = I. 24E+02 +/- 2.43E+OO 1.26E+02 +/- 3.82E+OO 1.28E+02 +/- 5.01E+OO Cs-137 1.20E+02 +/- 2.00E+OO 1.05 A l.25E+02 +/- 2.61E+OO Mean: I. 26E+02 +/- 2. 27E+OO I.03E+02 +/- 3.43E+OO 1.02E+02 +/- 4.76E+OO Co-58 9.35E+01 +/- 1.56E+OO 1.09 A 1.02E+02 +/- 2.29E+OO Mean = 1.02E+02 +/- 2.IOE+OO 1.75E+02 +/- 4.26E+OO 1.70E+02 +/- 5.72E+OO Mn-54 1.52E+02 +/- 2.53E+OO 1.11 A 1.62E+02 +/- 2.88E+OO Mean: 1.69E+02 + 2.56E+OO l.36E+02 +/- 4.4IE+OO 1.31E+02 +/- 6.05E+OO Fe-59 1.16E+02 +/- I. 93 E+OO 1.13 A 1.25E+02 +/- 3.16E+OO Mean = l.31E+02 + 2.71E+OO 2.98E+02 +/- 8.60E+OO Zn-65 2.99E+02 +/- 1.l8E+Ol 2.59E+02 1.11 A
+/- 4.32E+OO 2.69E+02 +/- 5.86E+OO Mean = 2.89E+02 +/- 5.24E+OO 2.31E+02 +/- 3.65E+OO 2.29E+02 +/- 4.92E+OO Co-60 2.17E+02 +/- 3.62E+OO 1.06 A 2.28E+02 +/- 2.54E+OO Mean = 2. 29E+02 +/- 2.21E+OO 6.90E+Ol +/- 1.37E+OO 6.42E+O 4'lE+tlO
** 6.44E+O +/- .08E+OO IE+O Mean::::: 6.64E+Ol +/- 7.37E-OI
( I) Ratio:::;:; RLp'" ,'-.../ Anal Sample provided by Analytics. Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable D 11
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB
- DATE 10 NO. MEDIUM ANALYSIS pCilliter + 1 sioma pCi/liter + 1 si~ma RATIO (I) 12/912010 E733 1-09 Water 4.91E+02 +/- 2.87E+01 5.43E+02 +/- 3.76E+01 Cr-51 5. 16E+02 +/- 2.87E+01 4.55E+02 +/- 7.59E+OO 1.10 A 4.58E+02 +/- 1.97E+OI Mean = 5.02E+02 +/- 1.47E+OI 1.69E+02 +/- 5.25E+OO 1.67E+02 +/- 6.23E+OO Cs-134 1.65E+02 +/- 4.60E+OO 1.57E+02 +/- 2.62E+OO 1.07 A 1.74E+02 +/- 3.22E+OO Mean = 1.69E+02 + 2.47E+OO 1.75E+02 +/- 4. 94E+OO I. 72E+02 +/- 5.94E+OO Cs-137 1.92E+02 +/- 4.68E+OO 1.86E+02 +/- 3.IOE+OO 0.97 A 1.80E+02 +/- 3.30E+OO Mean = 1.80E+02 +/- 2.40E+OO I.OOE+02 +/- 4.24E+OO
- 9. 84E+O1 +/- 4.80E+OO Co-58 8.82E+01 +/- 3.81E+OO 9.00E+01 +/- 1.50E+OO 1.06 A 9.50E+01 +/- 2.65E+OO Mean = 9.54E+OI +/- 1.98E+OO I.27E+02 +/- 4.46E+OO 1.28E+02 +/- 5.50E+00 Mn-54 1.35E+02 +/- 4.23E+OO 1.19E+02 +/- I. 99E+00 1.09 A 1.29E+02 +/- 3.09E+00 Mean = 1.30E+02 +/- 2.20E+OO 1.45E+02 +/- 5.9 I E+OO 1.52E+02 +/- 7.49E+OO Fe-59 1.63E+02 +/- 5.62E+00 I.31E+02 +/- 2. 18E+OO 1.16 A 1.48E+02 +/- 3.96E+OO Mean = 1.52E+02 +/- 2.94E+OO I. 84E+02 +/- 8.71E+OO 1.98E+02 +/- 1.17E+OI Zn-65 1.78E+02 +/- 8.42E+00 1.74E+02 +/- 2.90E+OO 1.08 A 1.94E+02 +/- 5.99E+OO Mean = 1.89E+02 +/- 4.47E+OO 3.IOE+02 +/- 4.96E+OO 7E+02 6.06E+00 OQF....o7 '100F+f17 +/- :E+OO 3.28E+OO Mean::: 3.12E+02 +/- 2.4 1E+oo 1.02E+02 +/- 4.19E+OO 1.02E+02 +/- 3.81E+OO I-131 1.00E+02 +/- 1.67E+OO 1.0 I A
- 9. 89E+O1 +/- 3.51E+OO Mean = 1.0lE+02 +/- 2. 22E-tOO (I) Ratio = ReportediAnalytlcs.
- Sample provided by Analytics, Inc.
Result determined by Resin Extraction/Gamma "np,"tr," U =U nacceptable
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB
- DATE IDNO. MEDIUl' IANALYSI DCi/liter +1 si!lma DCi/liter + I si!lma RATIO (I) 3118/2010 E6994-09 MILK 2.68E+02 +/- 5.38E+OO 2.57E+02 +/- 5.37E+OO Ce-141 2.68E+02 +/- 1.13E+Ol 2.61E+02 +/- 4.36E+O 1.04 A
- 2. 89E+02 +/- 1.22E+Ol Mean = 2.70E+02 + 4.58E+OO 3.55E+02 +/- 2.53E+Ol 3.72E+02 +/- 2.34E+Ol Cr-51 3.55E+02 +/- 5.27E+01 3.61E+02 +/- 6.03E+O 0.93 A 2.65E+02 +/- 5.45E+Ol Mean - 3.37E+o2 + 2.08E+Ol 1.79E+02 +/- 3.95E+OC 1.79E+02 +/- 4.62E+OC Cs-134 1.88E+02 +/- 9.01E+OC 1.78E+02 +/- 2.97E+O 1.00 A 1.68E+02 +/- 9.01E+OC Mean- 1.78E+02 +/- 3.53E+OC 1.60E+02 +/- 3.88E+OC 1.51E+02 +/- 3.78E+OC Cs-137 1.64E+02 +/- 8.33E+OC 1.58E+02 +/- 2.64E+O 1.02 A 1.68E+02 +/- 8.03E+OC Mean- 1.61E+02 + 3.19E+Of 1.44E+02 +/- 4.03E+OC 1.39E+02 +/- 3.85E+OC Co-58 1.47E+02 +/- 8.42E+OC 1.43E+02 +/- 2.38E+O 1.00 A 1.43E+02 +/- 7.40E+OC Mean = 1.43E+02 +/- 3.13E+OC 2.15E+02 +/- 4.39E+OC 2.22E+02 +/- 4.68E+OO Mn-54 2.24E+02 +/- 9.49E+O( 2.07E+02 +/- 3.46E+O 1.04 A 2.01E+02 +/- 8.96E+OC Mean= 2.15E+02 + 3.64E+OC 1.58E+02 +/- 5.27E+OC 1.44E+02 +/- 5.27E+OC Fe-59 1. 66E+02 +/- 1.03E+Ol 1.37E+02 +/- 2.29E+O 1.08 A 1.25E+02 +/- 9.91E+OC Mean = 1.48E+02 + 4.03E+OC 2.67E+02 +/- 8.17E+OC 2.75E+02 +/- 8.77E+OC Zn-65 2.56E+02 +/- 1.73E+Ol 2.54E+02 +/- 4.24E+O 1.05 A 2.70E+02 +/- I. 75E+O 1 Mean:: 2.67E+02 +/- 6. 84E+()(
1.79E+02 +/- 3.25E+OC
.83E+02 +/- 3.4IE+OC
.73E+OC I.R3E+02 +/- .ooE+O A
+/- 6.34E+O(
Mean::::: 1.8! E+02 + 2.59E+O( 6.62E+01 ::t 7. 99E+O( 7.40E+01 ::t 4.47E+OC 1-131 ** 7.40E+01 +/- 1.24E+O 0.95 A 6.96E+01 +/- 1.09E+Ol Mean:: 6.99E+01 +/- 3.56E+OC (I) RatIo =ReportedlAnalyttcs.
- Sample provided by Analytics. Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable 13
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk S.<\MPLE JAF ELAB RESULTS REFERENCE LAB* DATE IDNO. MEDIUM fu~ALYSIS pCi/liter + 1 sigma pCi/liter + I sigma RATIO (I) 06/1712010 E7091-05 MILK 1.25E+02 +/- 6. 24E+OO 1.12E+02 +/- 3.98E+OO Ce-141 1.IOE+02 +/- 1.84E+OO 1.08 A 1.20E+02 +/- 3.14E+OO Mean = 1.19E+02 +/- 2.68E+OO 3.59E+02 +/- 2.85E+OI 3.27E+02 +/- 2.01E+Ol Cr-51 3.39E+02 +/- 5.66E+OO 1.03 A 3.62E+02 +/- I. 54E+O 1 Mean = 3.49E+02 +/- 1.27E+OI 1.42E+02 +/- 4.64E+OO 1.31E+02 +/- 3.44E+OO Cs-134 1.26E+02 +/- 2.IOE+OO 1.07 A 1.32E+02 +/- 2.43E+OO Mean = 1.35E+02 +/- 2.09E+OO 1.49E+02 +/- 4.82E+OO 1.51E+02 +/- 3.23E+OO Cs-137 1.50E+02 +/- 2.51E+OO 1.00 A 1.48E+02 +/- 2.48E+OO Mean = 1.49E+02 +/- 2.IOE+OO I. 16E+02 +/- 4.40E+OO 1.06E+02 +/- 3.02E+OO Co-58 I.OIE+02 +/- 1.69E+OO 1.09 A 1.09E+02 +/- 2. 34E+OO Mean = 1.IOE+02 + 1. 94E+OO 1.87E+02 +/- 5.30E+OO 1.84E+02 +/- 3.59E+OO Mn-54 1.69E+02 +/- 2.82E+OO 1.09 A 1.82E+02 +/- 2.67E+OO Mean = 1.84E+02 +/- 2.31E+OO 1.34E+02 +/- 5.61E+OO 1.24E+02 +/- 4.IOE+OO Fe-59 1.19E+02 +/- 1.98E+OO 1.10 A I. 34E+02 +/- 3.04E+OO Mean = 1.31E+02 +/- 2.53E+OO 2.37E+02 +/- 8.94E+OO
- 2. 17E+02 +/- 6.80E+OO Zn-65 2.06E+02 +/- 3.44E+OO 1.10 A 2.25E+02 +/- 4.84E+00 Mean = 2.26E+02 +/- 4.08E+OO 1.97E+02 +/- 4.13E+OO 2.05E+02 +/- 2.9IE+00 Co-60 1.97E+02 +/- 3.28E+OO 1.02 A 2.00E+02 +/- 2.21E+OO Mean:::: 2.01E+02 + 1.84E+OO 9.92E+01 +/- 5.23E+OO
- t 3.75E+00 9.89E+O +/- IE+OO 7.87E+O :+/-: 2. 26E+OO 9. .62E+OO 8.03E+01 ::t 2.25E+OO I-I 7.97E+OI +/- 2.65E+00 Mean = 8.91E+01 :+/-: 1.35E+OO (I) Ratio = Reported/Analytlcs.
- Sample provided by Analytics. Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB* DATE IDNa. MEDIUM ANALYSIS nCi/liter + I sigma nCi/liter +/- I sigma RATIO (I) 9116/2010 E7190-0S MILK 1.3SE+02 +/- 4.99E+OO 1.40E+02 +/- 6.52E+OO Ce-141 1.34E+02 +/- 2.58E+OO 1.30E+02 +/- 2.17E+OO 1.0S A 1.3SE+02 +/- 5.26E+OO Mean- 1.36E+02 + 2.S2E+OO 2.49E+02 +/- 2.21E+01 2.27E+02 +/- 2.71E+01 Cr-51 2.33E+02 +/- I.OSE+OI 2.34E+02 +/- 3.90E+OO 0.99 A 2.16E+02 +/- 2.56E+01 Mean- 2.31E+02 + IIIE+OI 9.92E+01 +/- 4.27E+OO 8.97E+01 +/- 4.93E+OO Cs-134 9.70E+01 +/- 1.86E+OO 9.30E+01 +/- I.SSE+OO 1.03 A 9.80E+01 +/- 4.44E+00 Mean = 9.60E+Ol + 2.03E+00 9.91E+01 +/- 3.97E+OO 9.37E+Ol +/- 4.70E+OO Cs-137 9.49E+01 +/- 1.8SE+OO 9.45E+01 +/- 1.58E+OO 1.01 A 9.23E+Ol +/- 4.43E+OO Mean- 9.50E+Ol + 1.95E+OO 8.06E+01 +/- 3.62E+00 7.76E+01 +/- 4.S4E+OO Co-S8 7.SSE+Ol +/- 1.63E+OO 7.37E+01 +/- 1.23E+OO 1.03 A 7.04E+01 +/- 4.30E+OO Mean = 7.60E+Ol +/- 1.8SE+OO 1.22E+02 +/- 4.ISE+OO 1.I8E+02 +/- S.14E+OO Mn-54 1.28E+02 +/- 2.02E+OO 1.19E+02 +/- 1.99E+OO 1.03 A I. 24E+02 +/- S.06E+OO Mean- I ?TP."'O? + 2 14E+OO 9.7SE+01 +/- 4.86E+OO 1.l4E+02 +/- 6.S9E+OO Fe-S9 1.03E+02 +/- 2.32E+OO 9.IIE+Ol +/- I.S2E+OO 1.14 A 1.01E+02 +/- 5.87E+OO Mean:: 1.04E+02 + 2.58E+OO 2.16E+02 +/- 8.69E+OO 1.79E+02 +/- 1.13E+OI Zn-65 2.20E+02 +/- 3.99E+OO 2.04E+02 +/- 3.40E+OO 1.01 A 2.12E+02 +/- 1.05E+01 Mean- 2.07E+0? + 4.54E+OO 1.79E+02 +/- 3.90E+OO
.82E+02 +/- 4.79E+OO
.~~~~
+/- :5E+OO
.70E+02 +/-
Mean = 1.76E+02 + 1.95E+OO 8.62E+01 +/- 1.61E+OO 8.50E+01 +/- L23E+OO 1- 3 9.41E+Ol +/- .57E+OO 0.91 A 8.61E+01 +/- 1.67E+OO Mean = 8.58E+01 + 8.75E-Ol (I) Ratio =Reported/Analyttcs.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable D ~ 5
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB* DATE 10 NO. MEDIUM ANALYSI' oCi +/-I si2ma DCi +1 si2ma RATIO (I) 3/1S/2010 E7022-0S FILTER 2.0SE+02 +/- 3.64E+OO
- 2. I SE+02 +/- 3.SSE+OO Ce-141 2.04E+02 +/- 3.40E+o( LOS A 2.14E+02 +/- 4.19E+OO Mean = 2.13E+02 +/- 2. 26E+OO 2.97E+02 +/- 1.61E+Ol 2.S7E+02 +/- 1.62E+Ol Cr-SI 2.SIE+02 +/- 4.70E+O( 1.02 A 3.07E+02 +/- I.SOE+OI Mean = 2.S7E+02 ... 9. 69E+OO I.5SE+02 +/- 4.9SE+OO 1.50E+02 +/- S.13E+OO Cs-134 1.3SE+02 +/- 2.31E+OC 1.09 A I.4SE+02 +/- S.24E+OO Mean = I.SIE+02 +/- 2.9SE+OO 1.2SE+02 +/- 3.96E+OO I. 32E+02 +/- 4.21E+OO Cs-137 1.23E+02 +/- 2.0SE+O( 1.02 A 1.21E+02 +/- 4.14E+OO Mean = I. 26E+02 ... 2. 37E+OO 1.I6E+02 +/- 3.S9E+OO 1.17E+02 +/- 4.01E+OO Co-SS I.IIE+02 +/- I.S6E+O( 1.0S A 1.ISE+02 +/- 3.93E+OO Mean = 1.17E+02 +/- 2.2SE+OO
- 1. 76E+02 +/- 4.64E+OO I.S4E+02 +/- S.17E+OO Mn-S4 1.62E+02 +/- 2.70E+O( 1.10 A 1.77E+02 +/- 4.98E+OO Mean = 1.79E+02 ... 2.SSE+OO 1.22E+02 +/- 4.SSE+OO 1.16E+02 +/- S.13E+OO Fe-S9 1.07E+02 +/- I.7SE+O( 1.12 A 1.23E+02 +/- 5.2SE+OO Mean = 1.20E+02 + 2. 94E+OO 2.3IE+02 +/- S.72E+OO 2.28E+02 +/- 9.46E+OO Zn-65 1.98E+02 +/- 3.30E+OC 1.12 A 2.05E+02 +/- 8.99E+OO Mean = 2.21E+02 ... 5.23E+OO 1.36E+02 +/- 3.50E+OO I. 37E+02 +/- 3.73E+OO Co-60 1.43E+02 +/- 2.3SE+O( 0.97 A 1.43E+02 +/- 3.59E+OO Mean = 1.39E+02 + 2.08E+OO
( I ) Ratio = Reportedl Anal ytics.
- Sample by Inc.
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB* DATE IDNO. MEDIU1v1 A1"lAL YSIS pCi +/-I sigma pCi +/-I sigma RATIO (I) 9/1612010 E7189-05 FILTER 1.28E+02 +/- 2.65E+OO 1.30E+02 +/- 2.67E+OO Ce-141 1.26E+02 +/- 2.IOE+OO 1.02 A 1.26E+02 +/- 1.38E+OO Mean = 1.28E+02 + 1.34E+OO 2.28E+02 +/- 1.35E+01 2.28E+02 +/- 1.38E+OI Cr-51 2.26E+02 +/- 3.77E+OO 1.01 A 2.31E+02 +/- 6.90E+OO Mean = 2.29E+02 +/- 6.83E+OO 1.02E+02 +/- 3.84E+OO 9.09E+01 +/- 3.81E+OO Cs-134 8.98E+Ol +/- 1.50E+OO 1.10 A 1.04E+02 +/- 1.68E+OO Mean = 9.90E+Ol +/- 1.89E+OO 8.80E+01 +/- 3.28E+OO 8.79E+01 +/- 3.17E+OO Cs-137 9.13E+OI +/- 1.52E+OO 0.98 A
- 9. 29E+OI +/- 1.47E+OO Mean = 8.96E+Ol +/- 1.60E+OO 7.25E+01 +/- 2.96E+OO 7.27E+Ol +/- 2.96E+OO Co-58 7.12E+Ol +/- 1.19E+OO 1.03 A 7.51E+Ol +/- 1.38E+OO Mean = 7. 34E+OI +/- 1.47E+OO 1.24E+02 +/- 3. 84E+OO 1.25E+02 +/- 3.94E+OO Mn-54 1.15E+02 +/- 1.93E+OO 1.09 A 1.26E+02 +/- 1.76E+OO Mean = 1.25E+02 + 1.93E+OO 1.02E+02 +/- 4.39E+OO 1.05E+02 +/- 4.56E+OO Fe-59 8.81E+Ol +/- 1.47E+OO 1.17 A 1.02E+02 +/- I. 92E+OO Mean = 1.03E+02 +/- 2.20E+OO
- 2. 24E+02 +/- 8.24E+OO 2.22E+02 +/- 8.46E+OO Zn-65 1.97E+02 +/- 3.29E+OO 1.14 A 2.27E+02 +/- 3.58E+OO Mean = 2.24E+02 +/- 4.11E+OO 1.70E+02 +/- 3.58E+OO 1.63E+02 +/- 3.54E+OO Co-60 1.65E+02 +/- 2.75E+OO 1.02 A 1.70E+02 +/- 1.56E+OO Mean = 1.68E+02 + I. 76E+OO
( I ) Ratio =Rt;purtedlAnalYi D - 17
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil SAMPLE JAF ELAB RESULTS REFERENCE LAB* DATE lONO. MEDIUM A1\J"ALYSIS pCilg +/- I sigma pCilg +/-I sigma RATIO (I) 6117/2010 E7092-05 SOIL 2.S9E-Ol +/- I.03E-02 2.47E-Ol +/- U3E-02 Ce-14l 2.33E-Ol +/- 2.3SE-02 2.5IE-Ol +/- 4.19E-03 LOS A 2.S7E-Ol +/- 1.09E-02 Mean = 2.64E-Ol +/- S.26E-03 8.52E-OI +/- 5.lSE-02 8.56E-01 +/- 9.6SE-02 Cr-51 7.71E-Ol +/- 1.29E-02 1.13 A 9.16E-Ol +/- 5.34E-02 Mean = 8.7SE-01 +/- 4.06E-02 3.l9E-Ol +/- 7.72E-03 3.23E-01 +/- l.4SE-02 Cs-134 3.45E-OI +/- 2.16E-02 2.86E-Ol +/- 4. 78E-03 LIS A 3.29E-01 +/- 8.49E-03 Mean = 3.29E-01 +/- 7.15E-03 4.44E-OI +/- 8.4SE-03 4.63E-OI +/- UlE-02 Cs-l37 4.52E-01 +/- 2.36E-02 4.32E-Ol +/- 7.21E-03 LOS A 4.52E-01 +/- 9J)4E-03 Mean = 4.S3E-0 I +/- 7.92E-03 2.S4E-OI +/- 6.62E-03 2.62E-OI +/- 1.44E-02 Co-S8 2.36E-Ol +/- 2.06E-02 2.30E-01 +/- 3.84E-03 1.08 A 2.37E-Ol +/- 7.68E-04 Mean = 2.47E-01 + 6.S0E-03 4.l7E-01 +/- 8.49E-03 3.97E-Ol +/- 1.66E-02 Mn-54 4.l5E-01 +/- 2.33E-02 3.S5E-Ol +/- 6.43E-03 1.07 A 4.2IE-Ol +/- 8.54E-03 Mean = 4.13E-Ol +/- 7.76E-03 3.0IE-01 +/- 9.44E-03 3.0IE-01 +/- 1.97E-02 Fe-59 2.7IE-OI +/- 2.89E-02 2.70E-01 +/- 4.5IE-03 1.09 A 3.03E-01 +/- 1.02E-02 Mean = 2.94E-01 +/- 9.4IE-03 S.12E-OI +/- 1.43E-02 4.94E-Ol +/- 2.83E-02 Zn-65 5.36E-OI +/- 4.23E-02 4.68E-O +/- 7.S2E-03 .09
+/-
Mean == 5. 12E-O I +/- 1.37E-02 4.74E-Ol +/- ti6DE.03 4.56E-O +/- .36E-02 Co-60 4.7SE-OI +/- 1.93E-02 4.47E-OI +/- 7.46E-03 A 4.68E-OI +/- 6.79E-03 Mean = 4.69E-OI +/- 6.36E-03 ( I) Ratio = ReportedlAnalytlcs.
- Sample provided by Analytics, Inc.
A=Acceptable
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE lAF ELAB RESULTS REFERENCE LAB
- DATE 10 NO. MEDIUM ANALYSIS pCi/g +/- I sigma pCi/g +/- 1 sigma RATIO (I) 612012010 E7094-05 VEG 2.06E-01 +/- 9.86E-03 2.03E-01 +/- 1.14E-02 Ce-141 2.2IE-01 +/- 3.69E-03 0.94 A 2.15E-01 +/- 6.IOE-03 Mean = 2.08E-OI +/- 5.42E-03 5.72E-OI +/- 4.94E-02 6.32E-01 +/- 6.34E-02 Cr-51 6.80E-01 +/- 1.14E-02 0.88 A 6.00E-OI +/- 3.30E-02 Mean = 6.0IE-01 +/- 2.9OE-02 2.68E-01 +/- 9.60E-03 2.66E-01 +/- 1.36E-02 Cs-134 2.52E-OI +/- 4.2IE-03 1.08 A 2.8IE-OI +/- 7.29E-03 Mean = 2.72E-01 +/- 6.06E-03 2.83E-01 +/- 9. 37E-03 2.9IE-01 +/- 1.23E-02 Cs-137 3.0IE-01 +/- 5.03E-03 0.95 A
- 2. 84E-0I +/- 6.37E-03 Mean = 2.86E-01 + 5.57E-03 2.02E-OI +/- 8.49E-03 2.09E-01 +/- I.IIE-02 Co-58 2.03E-01 +/- 3.39E-03 0.99 A I. 89E-0I +/- 5.44E-03 Mean = 2.00E-01 +/- 5.ooE-03 3.49E-01 +/- 1.04E-02 3.36E-01 +/- I. 35E-02 Mn-54 3.39E-OI +/- 5.66E-03 1.00 A 3.34E-01 +/- 7.03E-03 Mean = 3.40E-01 +/- 6.14E-03 2.33E-01 +/- 1.17E-02 2.25E-01 +/- 1.50E-02 Fe-59 2.38E-0 I +/- 3.97E-03 0.98 A 2.39E-01 +/- 7.96E-03 Mean = 2.32E-01 +/- 6.87E-03 4.18E-01 +/- I. 89E-02 4.27E-01 +/- 2.48E-02 Zn-65 4.12E-01 +/- 6.88E-03 1.02 A 4.16E-01 +/- 1.35E-02 Mean = 4.20E-01 +/- 1.13E-02 3.77E-01 +/- 8.39E-03 3.82E-01 +/- 1.12E-02 Co-60 3.94E-OI +/- 6.58E-03 0.97 A 3.84E-01 +/- 5.8IE-03 Mean = 3.8IE-01 +/- 5.05E-03
!) Ratio := Rl:puftedJAnalytic* o-
TABLE D3 (Continued) INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB'" DATE IDNO. MEDIUM ANALYSIS pCi Ig +/- I sigma pCi/g +/- I sigma RATIO (I) 9116/2010 E7184-09 VEG 4.78E-01 +/- 1.16E-02 S.20E-01 +/- 2.06E-02 Ce-141 S.09E-OI +/- 1.92E-02 4.79E-01 +/- 8.00E-03 LOS A S.OOE-OI +/- 1.4SE-02 Mean = S.02E-01 +/- 8.43E-03 8.8IE-0I +/- S.64E-02 9.73E-01 +/- I.07E*01 Cr-SI 9.4SE-OI +/- 1.01E-01 8.59E-01 +/- 1.43E-02 1.08 A 9.13E-Ol +/- 6.68E-02 Mean = 9.28E-01 +/- 4.28E-02 3.9SE-Ol +/- 1.16E-02 3.54E-01 +/- 2.20E-02 Cs-134 3.88E-Ot +/- 2.19E-02 3.42E-01 +/- S.7tE-03 1.13 A 4.0SE-OI +/- 1.40E-02 Mean: 3.S7E-01 +/- 8.99E-03 3.6IE-01 +/- 1.0SE-02 3.42E-01 +/- I.SSE-02 Cs-137 3.4tE-01 +/- 1.83E-02 3.47E-01 +/- S.79E-03 1.01 A 3.S7E-Ot +/- 1.30E-02 Mean = 3.S0E-01 +/- 7.73E-03 3.03E-01 +/- 1.0 I E-02 2.4SE-OI +/- 1.7SE-02 Co-S8 2.63E-OI +/- 1.83E-02 2.7IE-01 +/- 4.S3E-03 1.03 A 3.07E-OI +/- I. 22E-02 Mean = 2.80E-01 +/- 7.47E-03 S.04E-OI +/- 1.23E-02 4.S3E-01 +/- 2.12E-02 Mn-S4 4.79E-OI +/- 2.12E-02 4.39E-OI +/- 7.33E-03 1.10 A 4.68E-OI +/- 1.42E-02 Mean = 4.S4E-01 +/- S.SSE-03 3.S7E-Ol +/- 1.39E-02 4.2SE-01 +/- 2.64E-02 Fe-S9 3.99E-01 +/- 2.48E-02 3.3SE-01 +/- S.S9E-03 LIS A 3.66E-OI +/- 1.6SE-02 Mean = 3.9SE-OI +/- 1.0SE-02 8.1SE-OI +/- 2.S7E-02 4.46E-02 44RE-02 300E-02 Mean=- 7.91E-0l +/- L86E-02 6.60E-OI +/- 1.I1E-02 6.69E-OI +/- 1.9SE-02 Co-60 6.87E-01 +/- 1.94E-02 6.28E-Ol +/- I.OSE-02 1.06 A 6.39E-OI +/- 1.2SE-02 Mean = 6. 64E-OI +/- 8.0SE-03 ( I) Ratto = ReportedlAnalytlcs. Inc. U=Unacceptable
0.5 REFERENCES
8.5.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia. 8.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969). D ~ 21
Laboratories LLC 2010 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) JANUARY 2010 - DECEMBER 2010 GEL LABORATORIES, LLC PO. Box 30712, Charleston, SC 29417 843.556.8171
[$1 #III Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 2 of 51 2010 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) JANUARY 2010 - DECEMBER 2010 Prepared By: cf!l~1Y\... February 15, 2011 Martha J. Harrison Date Quality Assurance Officer
Laboratories P,O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 3 of 51 TABLE OF CONTENTS
- 1. Introduction ......................................................................................................................5
- 2. Quality Assurance Programs for Inter-laboratory, Intra-Laboratory, and Third Party Cross-Check ..................................................................................................6
- 3. Quality Assurance Program for Internal and External Audits ......................................... 7
- 4. Performance Evaluation Acceptance Criteria for Environmental Sample Analysis .......... 8
- 5. Performance Evaluation Samples ....................................................................................8
- 6. Quality Control Program for Environmental Sample Analysis ..................................... 8
- 7. Summary of Data Results .............................................................................................9
- 8. Summary of Participation in Eckert & Ziegler Analytics Environmental Cross-Check Program .......................................................................................................................... 10
- 9. Summary of Participation in the MAPEP Monitoring Program ...................................... 10
- 10. Summary of Participation in ERA (MRAD) PT Program ................................................. 10
- 11. Summary of Participation in the ERA PT Program ...................................................... 11
- 12. Summary of Participation in the NY ELAP PT Program ............................................... 11
- 13. Quality Control Program for REMP Analyses ................................................................. 12
- 14. Corrective Action and Request Report (CARR) ......................... '" ................................. 12
- 15. References ..................................................................................................................... 12
@ElII Laboratories P.o. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 4 of 51 TABLE OF CONTENTS (CONTINUED) LIST OF TABLES
- 1. 2010 RADIOLOGICAL PROFICIENCY TESTING RESULTS AND ACCEPTANCE CRITERIA
- 2. 2010 ECKERT & ZIEGLER ANAL YTICS PERFORMANCE EVALUATION RESULTS
- 3. 2010 DEPARTMENT OF ENERGY MIXED ANAL YTE PERFORMANCE EVALUATION PROGRAM (MAPEP) RESULTS
- 4. 2010 ERA PROGRAM PERFORMANCE EVALUATION RESULTS
- 5. 2010 ERA PROGRAM (MRAD) PERFORMANCE EVALUATION RESULTS
- 6. 2010 NEW YORK STATE DEPARTMENT OF HEALTH ENVIRONMENTAL LABORATORY APPROVAL PROGRAM (NYSDOH ELAP) PROFICIENCY TEST RESULTS
- 7. GEL 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
INTRA-LABORATORY DATA
SUMMARY
- BIAS AND PRECISION BY MATRIX
- 8. GEL 2010 RADIOLOGICAL INTRA-LABORATORY DATA
SUMMARY
- BIAS AND PRECISION BY MATRIX
- 9. GEL 2010 CORRECTIVE ACTION
SUMMARY
LIST OF FIGURES
- 1. COBALT-60 PERFORMANCE EVALUATION RESULTS AND % BIAS
- 2. CESIUM-137 PERFORMANCE EVALUATION RESULTS AND % BIAS PERFORMANCE RESULTS AND BIAS PERFORMANCE RESULTS AND
- 5. STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND BIAS
- 6. GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS
- 7. GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS
003' Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 5 of 51
- 8. IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
- 1. Introduction GEL Laboratories, LLC (GEL) is a privately owned environmental laboratory dedicated to providing personalized client services of the highest quality. GEL was established as an analytical testing laboratory in 1981. Now a full service lab, our analytical divisions use state of the art equipment and methods to provide a comprehensive array of organic, inorganic, and radiochemical analyses to meet the needs of our clients.
At GEL, quality is emphasized at every level of personnel throughout the company. Management's ongoing commitment to good professional practice and to the quality of our testing services to our customers is demonstrated by their dedication of personnel and resources to develop, implement, assess, and improve our technical and management operations. The purpose of GEL's quality assurance program is to establish policies, procedures, and processes to meet or exceed the expectations of our clients. To achieve this, all personnel that support these services to our clients are introduced to the program and policies during their initial orientation, and annually thereafter during company-wide training sessions. GEL's primary goals are to ensure that all measurement data generated are scientifically and legally defensible, of known and acceptable quality per the data quality objectives (DQOs), and thoroughly documented to provide sound support for environmental decisions. In addition, GEL continues to ensure compliance with all contractual requirements, environmental standards, and regulations established by local, state and federal authorities. GEL administers the QA program in accordance with the Quality Assurance Plan, GL-QS-B-001. Our Quality Systems include all quality assurance (QA) policies and quality control (QC) procedures necessary to plan, implement, and assess the work we perform. GEL's QA Program establishes a quality management system (QMS) that governs all of the activities of our organization. assurance program for aSPjElcts of GEL for 201 This report covers the category of Radiological Environmental ftllnn,fflrt and includes:
- Intra-laboratory QC results analyzed during 2010.
- Inter-laboratory QC results analyzed during 2010 where known values were available.
l13" Laboratories L P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 6 of 51
- 2. Quality Assurance Programs for Inter-laboratory, Intra-laboratory and Third Party Cross-Check In addition to internal and client audits, our laboratory participates in annual performance evaluation studies conducted by independent providers. We routinely participate in the following types of performance audits:
- Proficiency testing and other inter-laboratory comparisons.
- Performance requirements necessary to retain Certifications
- Evaluation of recoveries of certified reference and in-house secondary reference materials using statistical process control data.
- Evaluation of relative percent difference between measurements through SPC data.
We also participate in a number of proficiency testing programs for federal and state agencies and as required by contracts. It is our policy that no proficiency evaluation samples be analyzed in any special manner. Our annual performance evaluation participation generally includes a combination of studies that support the following:
- US Environmental Protection Agency Discharge Monitoring Report, Quality Assurance Program (DMR-QA). Annual national program sponsored by EPA for laboratories engaged in the analysis of samples associated with the NPDES monitoring program. Participation is mandatory for all holders of NPDES permits.
The permit holder must analyze for all of the parameters listed on the discharge permit. Parameters include general chemistry, metals, BOD/COD, oil and grease, ammonia, nitrates, etc.
- Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP). A semiannual program developed by DOE in support of DOE contractors performing waste analyses. Participation is required for all laboratories that perform environmental analytical measurements in support of environmental management activities. This program includes radioactive isotopes in water, soil, vegetation and air filters.
- ERA's MRAD-Multimedia Radiochemistry Proficiency test program. This program is for labs seeking certification for radionuclides in wastewater and solid waste. The program is conducted in strict compliance with USEPA National Standards for Water
- ERA's InterLaB RadCheM for This program the process USEPA EMSL-LV Nuclear Radiation Assessment Division program discontinued in 1998. Laboratories seeking certification for radionuclide analysis in drinking water also use the study. This program is conducted in strict compliance with the USEPA National Standards for Water Proficiency Testing Studies. This program encompasses Uranium by EPA method 200.8 (for drinking water certification in Florida/Primary NELAP). gamma
til 311 Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 7 of 51 emitters, Gross Alpha/Beta, lodine-131, naturally occurring radioactive isotopes, Strontium-89/90, and Tritium.
- ERA's Water Pollution (WP) biannual program for waste methodologies includes parameters for both organic and inorganic analytes.
- ERA's Water Supply (WS) biannual program for drinking water methodologies includes parameters for organic and inorganic analytes.
- New York State Department of Health Environmental Laboratory Approval Program Proficiency Testing Program for Potable Water (PW)
- Environmental Cross-Check Program administered by Eckert & Ziegler Analytics, Inc. This program encompasses radionuclides in water, soil, milk, naturally occurring radioactive isotopes in soil and air filters.
GEL procures single-blind performance evaluation samples from Eckert & Ziegler Analytics to verify the analysis of sample matrices processed at GEL. Samples are received on a quarterly basis. GEL's Third-Party Cross-Check Program provides environmental matrices encountered in a typical nuclear utility REMP. The Third-Party Cross-Check Program is intended to meet or exceed the inter-laboratory comparison program requirements discussed in NRC Regulatory Guide 4.15, revision 1. Once performance evaluation samples have been prepared in accordance with the instructions provided by the PT provider, samples are managed and analyzed in the same manner as environmental samples from GEL's clients.
- 3. Quality Assurance Program for Internal and External Audits During each annual reporting period, at least one internal assessment is conducted in accordance with the pre-established schedule from Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-E001. The annual internal audit plan is reviewed for adequacy and includes the scheduled frequency and scope of quality control actions necessary to GEL's QA program. Intemal audits are conducted at least annually in accordance with a schedule approved by the Quality Systems Director. Supplier audits are contingent upon the categorization of the supplier, and mayor may not be conducted prior to the use of a supplier or subcontractor. Type I suppliers and subcontractors, regardless of how they were initially qualified, are re-evaluated at least once every three years.
In prospective customers audit GEL nr""_(Y\ntr'~('T audits. GEL hosts several external audits each year for both our clients and other nYr>,rtY'O,rnc These include environmental waste The tAliI'M/inn programs may audit GEL at least program.
- National Environmental Laboratory Accreditation Program
- DOECAP, U.S. Department of Energy Consolidated Audit Program
- DOE LAP, U.S. Department of Energy Laboratory Accreditation Program
- DOE QSAS, U.S. Department of Energy, Quality Systems for Analytical Services
- ISOIIEC 17025
(#3 #f , Laboratories P.O. Box 30712. Charleston. SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 8 of 51
- A2LA, American Association for Laboratory Accreditation
- DOD ELAP, US Department of Defense Environmental Accreditation Program
- NUPIC, Nuclear Procurement Issues Committee
- South Carolina Department of Heath and Environmental Control (SC DHEC)
The annual radiochemistry laboratory internal audit (10-RAD-001) was conducted in March 2010. Four findings. one observation. and two recommendations resulted from this assessment. Each finding was closed and appropriate laboratory staff addressed each observation and recommendation. The internal audit closed in June 2010.
- 4. Performance Evaluation Acceptance Criteria for Environmental Sample Analysis GEL utilized an acceptance protocol based upon two performance models. For those inter-laboratory programs that already have established performance criteria for bias (i.e.,
MAPEP, and ERAIELAP). GEL will utilize the criteria for the specific program. For intra-laboratory or third party quality control programs that do not have a specific acceptance criteria (i.e. the Eckert-Ziegler Analytics Environmental Cross-check Program), results will be evaluated in accordance with GEL's internal acceptance criteria.
- 5. Performance Evaluation Samples Performance Evaluation (PE) results and internal quality control sample results are evaluated in accordance with GEL acceptance criteria. The first criterion concerns bias, which is defined as the deviation of anyone result from the known value. The second criterion concerns precision, which deals with the ability of the measurement to be replicated by comparison of an individual result with the mean of all results for a given sample set.
At GEL, we also evaluate our analytical performance on a regular basis through statistical process control acceptance criteria. Where feasible, this criterion is applied to both measures of precision and accuracy and is specific to sample matrix. We establish environmental process control limits at least annually. For Radiochemistry analysis, quality control evaluation is based on static limits rather than those that are statistically derived. Our current process control limits are maintained in GEL's AlphaUMS. We also measure precision with matrix duplicates andlor matrix spike duplicates. The upper and lower control limits (UCL and LCL respectively) for precision are plus or minus three times the standard deviation from the mean of a series of relative percent differences. The static preciSion criteria for radiochemical analyses are 0 - 20%, for levels the contract required detection limit
- 6. Quality Control Program for Environmental Sample Analysis GEL's internal QA is to include QC functions as instrumentation calibration checks insure proper instrument response), blank samples, instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and statistical process controls. Both quality control and qualification analyses samples are used to be as similar as the matrix type of those samples submitted for analysis by the various laboratory clients. These performance test samples (or performance evaluation samples) are either
m311 Laboratories P.O. Box 30712. Charleston. SC 29417 L 2010 ANNUAL QUALITY ASSURANCE REPORT Page 9 of 51 actual sample submitted in duplicate in order to evaluate the precision of laboratory measurements, or fortified blank samples, which have been given a known quantity of a radioisotope that is in the interest to GEL's clients. Accuracy (or Bias) is measured through laboratory control samples and/or matrix spikes, as well as surrogates and internal standards. The UCLs and LCLs for accuracy are plus or minus three times the standard deviation from the mean of a series of recoveries. The static limit for radiochemical analyses is 75 - 125%. Specific instructions for out-of-control situations are provided in the applicable analytical SOP. GEL's Laboratory Control Standard (LCS) is an aliquot of reagent water or other blank matrix to which known quantities of the method analytes are added in the laboratory. The LCS is analyzed exactly like a sample, and its purpose is to determine whether the methodology is in control, and whether the laboratory is capable of making accurate and precise measurements. Some methods may refer to these samples as Laboratory Fortified Blanks (LFB). The requirement for recovery is between 75 and 125% for radiological analyses excluding drinking water matrix. Bias (%) = (observed concentration)
- 100 %
(known concentration) Precision is a data quality indicator of the agreement between measurements of the same property, obtained under similar conditions, and how well they conform to themselves. Precision is usually expressed as standard deviation, variance or range in either absolute or relative (percentage) terms. GEL's laboratory duplicate (OUP or LCSD) is an aliquot of a sample taken from the same container and processed in the same manner under identical laboratory conditions. The aliquot is analyzed independently from the parent sample and the results are compared to measure precision and accuracy. If a sample duplicate is analyzed. it will be reported as Relative Percent Difference (RPD). The RPD must be 20 percent or less, if both samples are greater than 5 times the MOC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%. If one result is above the MDe and the other is below the MDC, then the RPO can be calculated using the MOC for the result of the one below the MOe. The RPD must be 100% or less. In the situation where both results are above the MDe but one result is greater than 5 times the MDe and the other is less than 5 times the MOC, the RPD must be less than or equal to 20%. If both results are below MOe, then the limits on % RPO are not
=
- 1. Summary of Data Results During 2010, forty-three radioisotopes associated with six matrix types were analyzed under GEL's Performance Evaluation program in participation with ERA, MAPEP, NYSDOH ELAP and Eckert & Ziegler Analytics. Matrix types were representative of client analyses performed during 2010. The list below contains the type of matrix evaluated by GEL.
ttl #I!I Laboratories p,o, Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 10 of 51
- Air Filter
- Cartridge
- Water
- Milk
- Soil
- Vegetation Graphs are provided in Figures 1-8 of this report to allow for the evaluation of trends or biases. These graphs include radioisotopes Cobalt-60, Cesium-137, Tritium, Strontium-90, Gross Alpha, Gross Beta, and lodine-131. A summary of GEL's quality control for radiological analyses by isotopic analysis and matrix are represented in Table 8. Each LCS and DUP represents a batch of samples for each isotopic analysis. This summary contains the number of reportable quality control results for our clients.
- 8. Summary of Participation in the Eckert & Ziegler Analytics Environmental Cross-Check Program During 2010, Eckert & Ziegler Analytics provided samples for 106 individual environmental analyses. Of the 106 analyses, 99% (105 out of 106) of all results fell within the PT provider's acceptance criteria. The only analytical failure occurred with the analysis of lron-59 in milk. For the corrective action associated with the Iron-59 failure, refer to CARR 110209-542 (Table 9).
- 9. Summary of Participation in the MAPEP Monitoring Program During 2010, one set of MAPEP samples (MAPEP 22) was analyzed by the laboratory. Of the 66 analyses, 80% (53 out of 66) of all results fell within the PT provider's acceptance criteria. Thirteen analytical failures occurred: Plutonium-238 in water, Uranium-235 in filter, Uranium-238 in filter, Uranium-Total in filter, Americium-241 in filter, Cesium-134 in filter, Cesium-137 in filter, Cobalt-60 in filter, Manganese-54 in filter, Plutonium-239/240 in filter, Uranium-244/243 in filter, Uranium-238 in filter, and Uranium-238 in vegetation.
For the corrective action associated MAPEP 22, refer to CARR100617-496 (Table 9). The ICP-MS analysis of Uranium-235 and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process. The failure for Plutonium-238 was attributed to a data reviewer's error and lack of attention to detail to the of interest that was not included in the data result. Approximately 400 additional counts should have been included. For the isotopiC failures, the error was attributed error and failure follow the from the PT nrn\lIf'I,Pf
- 10. Summary of Participation in the ERA MRaD PT Program During 2010, the ERA MRad program provided samples (MRAD-12 and MRAD-13) for 175 individual environmental analyses. Of the 175 analyses, 96% (169 out of 176) of all results fell within the PT provider's acceptance criteria. Six analytical failures occurred: Uranium-234 in soil, Uranium-238 in soil, Uranium-238 in vegetation, Plutonium-238 in water, Uranium-238 in water, and Bismuth-212 in soil.
00#111 Laboratories P.o. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 11 of 51 For the corrective actions associated with MRAD 12 and MRAD-13, refer to corrective actions CARR100617-497 and CARR101210-527, respectively (Table 9). For MRAD-12, the ICP-MS analysis of Uranium-235 and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process. For Uranium-238 in vegetation, air and water, the failure was attributed to method sensitivity by gamma spectroscopy. Future PT analysis will be performed using a more sensitive method. For MRAD-13, the failure for Bismuth-212 was attributed to a reporting error. The actual result (1660 pCi/kg) was within the acceptance range. The failure of Iron-55 was attributed to matrix interference. An additional recount with a smaller aliquot and fresh reagent rinses removed the interferant.
- 11. Summary of Participation in the ERA PT Program During 2010, the ERA program provided samples (RAD-80 and RAD-82) for 53 individual environmental analyses. Of the 53 analyses, 77% (41 out of 53) of all results fell within the PT provider's acceptance criteria. Twelve analytical failures occurred: Strontium-89 in water, Strontium-90 in water, Barium-133 in water, Cesium-134 in water, Cesium-137 in water, Cobalt-60 in water, Zinc-65 in water, Uranium (Natural) in water, Uranium (Nat) Mass in water, Strontium-90 in water, Cesium-134 in water, and Zinc-65 in water.
For the corrective actions associated with RAD-80 and RAD-82, refer to corrective actions CARR100318-487 and CARR100907-512, respectively (Table 9). For RAD-80, the Gross Alpha failure was attributed to a concentrated iron carrier. The Strontium-89 and Strontium-90 failures were attributed to the associated weights of the carriers utilized during the preparation and analysis. For RAD-82, failures of the Gamma Emitters and the Naturals (Uranium) were attributed to analyst error and failure to follow the instructions from the PT provider. The failure of Strontium-89 and Strontium-90 was attributed to analyst error while diluting the sample.
- 12. Summary of Participation in the New York ELAP PT Program During 2010, the NYSDOH ELAP PT program provided 30 individual tests for radiological analysis. Of the 30 analyses, 83% (25 out of 30) of the results were within the PT provider's acceptance criteria. Five analytical failures occurred: Cesium-134 in water, lodine-131 in water (two), Strontium-89 in water, and Radium-226 in water.
refer corrective action CARR101203-
. Strontium-89 and and Radium-The continues to monitor results In addition, GEL (Lab ID# E87156, Lab Code# SC00012) maintained primary NELAP accreditation from the Florida Department of Health for the following methods in potable water and non-potable water. The radiological analytes and methods are listed below.
- Gross Alpha: EPA 900.0, EPA 198400-02
t'i13! LatJoratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 12 of 51
- Gross Beta: EPA 900.0
- lodine-131: DOE 4.5.2.3, EPA 901.1, EPA 902.0
- Photon Emitters: DOE 4.5.2.3, EPA 901.1
- Radioactive Cesium: DOE 4.5.2.3, EPA 901.1
- Tritium: EPA 906.0
- Radium-226: EPA 903.1, EPA 1984 Ra-04
- Radium-228: EPA 904.0, EPA 1976 PP.24
- Radon: SM 20 7500 Rn, DOE 1990 Sr-02
- Strontium-89: EPA 905.0
- Strontium-90: EPA 905.0
- Uranium (Activity): DOE 1990 U-02, ASTM D5174-97, 02 13, Quality Control Program for REMP Analyses GEL's internal (intra-laboratory) quality control program evaluated 1590 individual analyses for bias and 1591 analyses for precision for standard REMP matrix and radio nuclides. Of the 959 internal quality control analyses evaluated for bias, 100% met laboratory acceptance criteria. In addition, 100% of the 1591 results for precision were found to be acceptable. The results are summarized in Table 8.
GEL performs low-level analysis specifically for Tritium in water. A chart of low activity H-3 spike performance is provided in Figure 8. All 2010 analyses were within the acceptance criteria.
- 14. Corrective Action Request and Report (CARR)
There are two categories of corrective action at GEL. One is corrective action implemented at the analytical and data review level in accordance with the analytical SOP. The other is formal corrective action documented by the Quality Systems Team in accordance with GL-QS-E-002. A formal corrective action is initiated when a nonconformance reoccurs or is so significant that permanent elimination or prevention of the problem is required. GEL includes quality requirements in most analytical standard operating procedures to ensure that data are reported only if the quality control criteria are met or the quality control measures that did not meet the acceptance criteria are documented. A formal corrective action is implemented according to GL-QS-E-002 for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement. Recording and documentation is performed following guidelines stated in GL-QS-E-012 for Client NCR Database Operation. mCllo,<,ee at a nonconformance and that corrective taken. a corrective action team as the team or corrective action are detailed in GL-QS-E-002. the event that correctness or the test results in doubt, the laboratory will take corrective action. If show that the results have been impacted, affected clients will be informed of the issue in writing within five (5) calendar days of the discovery. Table 9 provides the status of CARRs for radiological performance testing during 2010.
Cf 311 Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAl QUALITY ASSURANCE REPORT Page 13 of 51
- 15. References
- 1. GEL Quality Assurance Plan, GL-QS-8-001
- 2. GEL Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-E-001
- 3. GEL Standard Operating Procedure for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement, GL-QS-E-002
- 4. GEL Standard Operating Procedure for AlphaUMS Documentation of Nonconformance Reporting and Dispositioning and Control of Nonconforming Items, GL-QS-E-004
- 5. GEL Standard Operating Procedure for Handling Proficiency Evaluation Samples, GL-QS-E-013
- 6. GEL Standard Operating Procedure for Quality Assurance Measurement Calculations and Processes, GL-QS-E-014
- 7. 40 CFR Part 136 Guidelines Establishing Test Procedures for the Analysis of Pollutants
- 8. ISOIIEC 17025-2005, General Requirements for the Competence of Testing and Calibration Laboratories
- 9. ANSI/ASQC E4-1994, Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs, American National Standard 10.2003 NELAC Standard, National Environmental Laboratory Accreditation Program
- 11. MARLAP, Multi-Agency Radiological Laboratory Analytical Protocols
- 12. 10 CFR Part 21, Reporting of Defects and Noncompliance 13.10 CFR Part 50 Appendix 8, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
- 14. 10 CFR Part 61, Licensing Requirements for Land Disposal and Radioactive Waste
- 15. NRC REG Guide 4.15 and NRC REG Guide 4.8
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 14 of 51 TABLE 1 2010 RADIOLOGICAL PROFICIENCY TESTING RESULTS AND ACCEPTANCE CRITERIA Acceptance Sample Sample Known Rangel Number Quarter 1 Year Media Unit Analyte 1 Nuclide GEL Value value Ratio Evaluation st RAO-80 1 12010 Water pCilL Barium-133 73.5 72.9 61.0 - 80.2 Acceptable RAO- 80 1"/2010 Water pCi/L Cesium-l34 692 63.4 51.5-69.7 Acceptable RAO - 80 1$t/2010 Water pCilL Cesium-137 118.0 120 108- 134 Acceptable RAO- 80 1" 12010 Water pC ill Cobalt-60 87.7 90 81 -101 Acceptable RAD -80 1"/2010 Water pCilL Gross Alpha 51.3 42.5 22.0 - 53.9 Acceptable st RAO- 80 1 /2010 Water pCilL Gross Beta 52.0 54.2 37.0-61.1 Acceptable st pC ill IOOine-131 28.2 23.5 - 33.1 Acceptable RAO- 80 l /2010 Water 30.5 RAD -80 1" 12010 Water pCi/L Radium-226 16.9 17.8 132 - 20.3 AccePtable RAO - 80 1"/2010 Water pCilL Radium-228 20.4 18.2 12.3 - 21.8 Acceptable Not st RAD -80 1 12010 Water pCilL Strontium-89 37.9 53.3 42.3 - 60.9 Acceptable Not st RAD - 80 1 12010 Water pC ill Strontium-90 52.3 42.2 31.1-48.4 Acceptable RAD- 80 1" 12010 Water pC ill Tritium 19200 18700 16400-20600 Acceptable st RAD - 80 1 12010 Water pCi/L Uranium (Nat) 49.0 50.2 40.7 - 55.8 Acceptable Uranium (Nat) st RAD - 80 1 12010 Water ug/L Mass 67.3 73.2 59.4 - 81.4 Acceptable st RAD -80 1 12010 Water pCilL Zinc-65 213.0 210 189 - 246 Acceptable E6922-278 2"" 12010 Cartridge pCi lodine-131 9.02E+Ol 9.39E+Ol 0.96 Acceptable E6924-278 2nd 12010 Milk pCilL IOOine-131 8.25E+Ol 8.73E+Ol 0.95 Acceptable E6925-278 2"" 12010 Water pCi/L lodine-131 1.00E+02 9.61E+01 1.04 Acceptable E6924-278 2"" 12010 Milk pCilL Iron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2nd 12010 Water pCi/L Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2"" 12010 Milk pCilL Manganese-54 1.83E+02 1.78E+02 1.03 Acceptable E6925-278 2nd 12010 Water pCilL Manganese-54 1.90E+02 U9E+02 1.06 Acceptable E6923-278 2"" 12010 Milk pCilL Strontium-89 9.73E+01 1.31E+02 0.75 Ac E6923-278 2"" 12010 Milk j:LCilL Strontium-90 1.38E+01 1.79E+01 0.77 Acceptable E6924-278 2"" 12010 Milk pCi/L Zinc-65 3.68E+02 3.45E+02 107 Acceptable 2M 12010 Water pCilL 7inc-65 3.72E+02 3.48E+02 107 Acceptable 53925-;'7
-278 E6925-278 E6924-278
,i I
I 2"" 12010 tv) 12010 2' ! 2010 2'" J 2010 2'" ! 2010 Milk Water Milk Water Milk pCilL pCilL pCilL pCi/L
! C:i3 rilJrn-141 Cerium-141 Cesium-134 Cesium-l34 Cesium-137 201E+02
?04F+Il?
2.41E+02 2.56E+02 1.71E+02 2.02E+02 2.04E+02
, 'i:1F+f1' 2.S5E+02 179E+02 I
I 0.99 1.00 0.95 1.00 0.96 Acceptable Acceptable Acceptable Acceptable Acceptable I E6925-278 2'" 12010 Water pC ill Cesium-137 1.81E+02 1.81E+02 100 Acceptable E6924-278 2nd 12010 Milk pCjlL Cobalt-58 2.03E+02 2.11 E+02 0.96 Acceptable E6925-278 2M 12010 Water pCjlL Coball-58 2,19E+02 2.13E+02 1.03 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 15 of 51 Acceptance Sample Sample Known Rangel Number Quarter 1 Year Media Unit Analyte 1 Nuclide GEL Value value Ratio Evaluation I E6924-278 2"" 12010 Milk pCilL Cobalt-60 2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2"" 12010 Water pCilL Cobalt-SO 2.67E+02 2.58E+02 1.03 Acceptable E6924-278 2"" 12010 Milk pC ill Cr-51 5.54E+02 5.48E+02 1.01 Acceptable E6925-278 2"" 12010 Water pCilL Cr-51 5.78E+02 5.54E+02 1.04 Acceptable E7054-278 2nd 12010 Milk pCilL Cerium-141 2.61E+02 2.61E+02 1.00 Acceptable E7055-278 2"" 12010 Water pCilL Cerium-141 2.78E+02 2.63E+02 1.06 Acceptable E7054-278 2nd 12010 Milk pCilL Cesium-134 1.76E+02 1.78E+02 0.99 Acceptable E7055-278 2nd 12010 Water pCilL Cesium-134 1.85E+02 1.79E+02 1.03 Acceptable E7054-278 2nd 12010 Milk pCilL Cesium-137 1.61E+02 1.58E+02 1.02 Acceptable E7055-278 2nd 12010 Water pCilL Cesium-137 1.71E+02 1.59E+02 1.07 Acceptabte E7054-278 2"" 12010 Milk pCilL Cobalt-58 1.45E+02 1.43E+02 1.02 Acceptable E7055-278 2nd 12010 Water pCilL Cobalt-58 1.51 E+02 1.44E+02 1.05 Acceptable E7054-278 2"" 12010 Milk pCilL Cobalt-60 1.90E+02 1.83E+02 1.04 Acceptable E7055-278 2"" 12010 Water pCi/L Cobalt-60 1.94E+02 1.85E+02 1.05 Acceptable E7054-278 2nd 12010 Milk pC ill Cr-51 3.81E+02 3.61E+02 1.05 Acceptable E7055-278 2nd 12010 Water pCilL Cr-51 3.86E+02 3.64E+02 1.06 Acceptable E7052-278 2nd 12010 Cartridge pCi lodine-131 8.58E+01 8.54E+01 1.00 Acceptable E7054-278 2"" 12010 Milk oCilL lodine-131 6.91E+01 7.40E+01 0.93 Acceptable E7055-278 2"" 12010 Water pCi/L lodine-131 8.12E+01 7.22E+01 1.12 Acceptable E7054-278 2nd 12010 Milk pCi/L Iron-59 1.60E+02 1.37E+02 1.17 Acceptable E7055-278 2nd 12010 Water pCilL Iron-59 1.60E+02 1.38E+02 1.16 Acceptable E7054-278 2"" 12010 Milk pCi/L Manganese-54 2.10E+02 2.07E+02 1.01 Acceptable E7055-278 2"" 12010 Water pCilL Manoanese-54 2.30E+02 2.09E+02 1.1 Acceptable E7053-278 2"" 12010 Milk pCi/L Strontium-89 7.91E+01 9.28E+01 0.85 Acceptable E7053-278 2nd 12010 Milk pCilL Strontium-OO 1.12E+01 1.27E+01 0.88 Acceptable E7054-278 2nd 12010 Milk pCilL Zinc-65 2.71E+02 2.54E+02 1.07 Acceptable E7055-278 2"" 12010 Water pCiIL Zinc-65 2.97E+02 2.56E+02 1.16 Acceptable nd NY-3323262 2 12010 Water pCilL Barium-133 27.8 25.6 20.6 - 30.5 Acceptable NY-3323262 2"" ! 2010 Water pCilL Cesium-134 14.8 14.0 10.7 - 17.3 Acceptable NY-3323262 2nd I 2010 Water pCilL Cesium-137 124 123 112 -134 Acceptable NY-3323262 i 2"" 12010 Water pCilL Cobal!-60 98.3 99.5 90.3 - 109 I Acceptable I I NY-3323263 2'" ! 2010 Water pCill Gross Alpha i 33.0 268 15.0 - 38.6 I Acceptabte I I NY-3323263 2nd 12010 I Water pCilL Gross Beta 64.6 540 J 413 - 66.7 NY-3323264 2nd f 2010 I Water pCilL I lodine-131 23.4 26.4 21.9 - 31.0 Acceptable NY-3323264 2"" 12010 Water pCiIL ! lodine-131 26.8 26.4 I 21.9 31.0 I Acceptable NY-3323265 I 2nd 12010 Water pCilL Radium-226 12.1 13.2 I 10.4 - 16.0 Acceptable NY-3323265 2"" 12010 Water pCilL Radium-228 9.90 8.91 I 6.08 - 11.7 Acceptable
Laboratories P.O. Box 30712. Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 16 of 51 Acceptance Sample Sample Known Rangel Number Quarter I Year Media Unit Analyte I Nuclide GEL Value value Ratio Evaluation i NY-3323261 ?:" / 2010 Water pCilL Strontium-89 46.7 41.9 33.4*50.4 Acceptable NY*3323261 2'" /2010 Water pCilL Strontium*90 33.9 34.8 27.1*42.5 Acceptable NY*3323266 2"" /2010 Water pCilL Tritium 9610 9490 8390*10600 Acceptable NY-3323265 ?:" / 2010 Water pCilL Uranium (activity) 48.81 44.7 37.9 - 51.4 Acceptable NY*3323262 2'" /2010 Water pCilL Zinc-65 146 139 121 -156 Acceptable MRAD*12 2'" /2010 Soil pCi/kg Actinium-228 1570 1850 1190-2600 Acceptable MRAO-12 2"" /2010 Soil pCi/ka Americium*241 1130 1500 896 - 1930 Acceptable MRAD-12 2'" /2010 Soil pCi/kg Americium-241 1120 1500 896*1930 Acceptable MRAD*12 2'" /2010 Vegetation pCi/kg Americium-241 2410 3140 1790 - 4310 Acceptable MRAD-12 2"" /2010 Vegetation pCi/kg Americium*241 3600 3140 1790 - 4310 Acceptable MRAD-12 2'" /2010 Air Filter pCi/Filter Americium-241 52.7 60.0 35.1 *82.3 Acceptable MRAD*12 2'" /2010 Air Filter pCi/Filter Americium-241 76 60 35.1 - 82.3 Acceptable MRAD-12 2"" /2010 Water pCilL Americium-241 79.1 95.6 65.5 - 129 Acceptable MRAD*12 2'" /2010 Water pC ill Americium-241 123 95.6 65.5*129 Acceptable MRAD*12 2"" /2010 Soil pCi/kg Bismuth-212 1430 1640 430 - 2450 Acceptable MRAO-12 2'" /2010 Soil pCi/kg Bismuth-214 1080 1410 865*2030 Acceptable MRAD-12 2"" /2010 Soil pCi/kg Cesium-l34 3040 3110 2000*3740 Accepjable MRAO-12 2"" /2010 V~etation ~Ci/ka Cesium-l34 1750 1670 956*2310 Acceptable MRAD-12 2"d /2010 Air Filter pCi/Filter Cesium*l34 504 436 284 - 540 Acceptable MRAD*12 2'" /2010 Water pCilL Cesium-l34 454 417 308*479 Acceptable MRAO*12 2"" /2010 Soil pCi/kg Cesium*137 4330 4440 3400*5770 Acceptable MRAO*12 2'" /2010 Vegetation pCi/kg Cesium-137 1550 1470 1080 - 2040 Accepjable MRAD-12 2"" /2010 Air Filter pCi/Filter Cesium-137 785 701 527 - 921 Acceptable MRAD-12 2"" /2010 Water pCi/L Cesium-137 693 654 556 - 783 Accep!able MRAD*12 2"d /2010 Soil pCi/kg Cobalt-60 2120 2140 1560 - 2870 Acceptable MRAD-12 2"" 12010 Vegetation pCi/kg Cobalt-SO 2100 1970 1330*2830 Acceptable MRAD*12 2'" /2010 Air Filter pCi/Filter Cobalt-60 591 523 405 653 Acceptable
=t I
i MRAD*12 2"" /2010 Water pCilL Cobalt-60 813 727 I 633 - 859 Acceptable I i MRAD-12 2"" 12010 Veoetation pCiJkg I 429 528 260 - 822 Acceptable C"""m-'" MRAD-12 I 2"" f 2010 Air Filter pCi/Fil!er Gross Alpha 68.2 79.6 41.3-120 A. I MRAD*12 I 2M i 2010 Air Filter pCI/Filter Gross Beta 72 704 43.4 - 103 i Acceptable I MRAD-12 I 2nd 1201Q Air Feter pel/Filler Iron-55 375 359 158 - 559 I Acceptable I I MRAD-12 2M 12010 Soil pCi/kg lead-212 1540 1520 980 - 2140 Acceptable MRAO-12 2"" 12010 Soil pCi/kq Lead-214 1300 1440 862 - 2140 Acceptable MRAO-12 2"" 12010 Soil pCi/kg Manganese-54 < 22.9 0 ---- Acceptable MRAD-12 2"" 12010 Vegetation pCi/kq Manganese-54 < 9.6 0.00 -- Acceptable
tt¥J1J Laboratories P.O. Box 30712. Charleston. SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 17 of 51
! Acceptance Sample Sample Known I Rangel ~mber Quarter I Year Media Unit I Analyte I Nuclide GEL Value value Ratio Evaluation D-12 2nd /2010 Air Filter pCilFilter Manganese-54 < 5.07 0.00 -- Acceptable MRAO-12 2nd /2010 Water pCi/L Manganese-54 < 7.7 0.00 ~ ....- Acceptable MRAD-12 2nd /2010 Soil ~Vkq Plutonium-238 1360 1330 761 - 1870 Acceptable MRAD-12 2nd 12010 Vegetation Cilkg Plutonium-238 3090 3040 1640 -4450 Acceptable MRAD-12 2nd /2010 Air Filter pCi/Filter Plutonium-238 63.9 64.1 44.0 - 84.3 Acceptable Not MRAD-12 2nd /2010 Waler pCi/L Plutonium-238 79.5 109 82.4 - 135 Acceptable MRAD-12 2nd /2010 Soil pCi/kg Plutonium-239 1220 1260 860 - 1670 Acceptable MRAD-12 2nd /2010 Vegetation pCi/kg Plutonium-239 2830 2800 1740 - 3820 Acceptable MRAD-12 2nd /2010 Air Filter pCi/Filter Plutonium-239 56.6 56.7 41.1 - 73.4 Acceptable MRAD-12 2nd /2010 Water pCi/l Plutonium-239 103 105 81.2 - 130 Acceptable MRAD-12 2nd /2010 Soil pCi/kq Potassium-40 11100 10900 7900 - 14800 Acceptable 25100 -
MRAD-12 2nd /2010 Vegetation pCi/kg Potassium-40 40800 34900 49400 Acceptable MRAD-12 2nd /2010 Soil pCi/kg Strontium-90 7870 8180 2960 - 13300 Acceptable MRAD-12 2"" /2010 Soil pCi/kg Strontium-90 7870 8180 2960 - 13300 Acceptable MRAO-12 2nd /2010 Veqetation pCi/kg Strontium-90 7880 9120 5100*12100 Acceptable MRAD*12 2nd /2010 Air Filter pCI/Filter Strontium-90 178 187 82.3 - 291 Acceptable MRAD-12 2"" /2010 Water pCilL Strontium*gO 708 719 456 - 961 Acceptable MRAD-12 2nd /2010 Soil pCi/kg Thorium-234 1600 1610 511 - 3070 Acceptable nd MRAD*12 2 /2010 Soil pCi/kg Uranium-234 1230 1620 1030-2010 Acceptable MRAD-12 2"" /2010 Veqetation pCi/kq Uranium-234 1680 1720 1180 - 2280 Acceptable MRAD-12 2nd /2010 Air Filter pCilFilter Uranium-234 68.8 62.1 39.1 - 92.0 Acceptable MRAO-12 2nd 12010 Water pC ill Uranium-234 62.4 61.4 46.3 - 79.2 Acceptable Not MRAD-12 2nd 12010 Soil pCi/kq Uranium-234 < 1158 1620 1030 - 2010 Acceptable MRAD-12 2"" /2010 Soil pCi/kq Uranlum-238 1600 1610 984 - 2040 Acceptable Not MRAD-12 2"" /2010 Soil pCi/kg Uranium-238 908 1610 984 - 2040 Acceptable MRAD-12 2nd /2010 Soil pCi/kg Uranium-238 1440 1610 984 - 2040 Acceptable MRAD-12 2"" /2010 Vegetation pCilkq Uranium-238 1604 1710 1200 - 2160 Acceptable MRAD-12 2"" /2010 Vegetation pCi/kq Uranium-238 1770 1710 1200 - 2160 Acceptable I Not MRAD-12 2nd /2010 I Vegetation pCi/kg I Uranium-238 < 1240 1710 1200 - 2160 Acceptable . MRAO*12 "H7~e 2"" 12010 Air Filter pCi/Filter Uranium*238 ~615 61.5 I
,~1=i';~
MRAD-12 i 2"" 12010 AIr Filter 69.5 61.5 39.4 - 87 MRAD-12 2"" 12010 AIr Filter 0( 61.2 61.5 39.4*873 MRj\[):12 2"" ! 2010 Water 67.9 60.9 465*75.5 Acceptable MRAD*12 2"" /2010 Water pCilL . Uranium*238 66.1 60.9 l 46.5 - 75.5 I Acceptable I MRAD*12 2"" 12010 Water pCilL Uranium-238 < 155 60.9 I 46.5 - 75.5 ! Not Acceptable MRAD-12 2"" /2010 Soil pCilkq Uranium-Total 2789 3300 1880*4460 Acceptable MRAO*12 2"" /2010 Vegetation pCi/kg Uranium-Total 3536 3510 2410*4530 Acceptable
Laboratories p,o, Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 18 of 51 Acceptance I Sample Sample Known Rangel Number Quarter I Year Media Unit Analyte I Nuclide GEL Value value Ratio Evaluation Uranium-Total MRAD-12 'Z" 12010 Soil uglkg <mass) 2920 4820 2650 - 6060 Acceptable Uranium-Total MRAD-12 2M 12010 Vegetation uglkg (mass) 5270 5120 3520 - 6610 Acceptable Uranium-Total MRAD-12 2M 12010 Vegetation pCi/kg (mass) 5290 5120 3520 - 6610 Acceptable Uranium-Total MRAD-12 2M 12010 Air Filter uo/Filter I . (mass) 183 184 114 - 264 Acceptable Uranium-Total MRAD-12 'Z" 12010 Nr Filter ug/Filter (mass) 208 184 114-264 Acceptable Uranium-Total MRAD-12 2M 12010 Air Filter uolFilter (mass) 175 184 114 - 264 Acceptable Uranium-Total MRAD-12 2!'" /2010 Water ug/L (mass) 213 182 143 - 225 Acceptable Uranium-Total MRAD-12 2!'" 12010 Water Ug/L (mass) 198 182 143-225 Acceptable MRAD-12 2"" /2010 Soil pCi/kg Zinc-65 2790 2470 1960 - 3310 Acceptable MRAD-12 2!'" 12010 Vegetation pCi/kg Zinc-65 1630 1360 983 - 1860 Acceptable MRAD-12 2M /2010 Nr Filter pCi/Filter Zinc-65 462 389 269 - 539 Acceptable MRAD-12 2!'" 12010 Water pCi/L Zinc-65 632 533 452 -664 Acceptable Not RAD- 82 3,d/ 20 1O Water pCiil Barium-133 112,0 89,1 75,0 - 98,0 Acceptable Not RAD 82 3,dl2010 Water pCiil Cesium-l34 115,0 88,3 72.4 -97,1 Acceptable Not RAD - 82 3 ,d 12010 Water pCiil Cesium-137 271 210 189 - 232 Acceptable Not RAD -82 3 ,d 12010 Water pCi/L Cobalt-60 98.4 72.8 65.5 - 82,5 AccEjptable RAD -82 3'd 12010 Water pCiil Gross Alpha 65,5 61.1 32,0 - 759 Acceptable RAD-82 3,d/ 2010 Water pCi/L Gross Beta 56,7 56.4 38,6- 63,6 Acceptable RAD - 82 3'"/2010 Water pCiil IOOine-131 32,2 28.4 23,6 - 33.3 AccejJtable RAD- 82 3'"/2010 Water pCi/L Radium-226 15,9 17.1 12,7 -19,6 Acceptable m RAD -82 3 12010 Water pCiil Radium-228 18.9 16,1 10.8-19.4 Acceptable RAD- 82 3 ,d /2010 Water pCiil Strontium-89 60,6 55,3 44,1 - 62,9 Acceptable Not RAD - 82 3 ,d 12010 Water pCiil Strontium-gO 47.1 32,8 24,0 - 38,0 Accefltable 17300 - RAD- 82 3'd 12010 Water pCiil Tritium 18500 19800 21700 Acceptable Not RAD - 82 I 3 cd 12010 Water pCiil Uranium (Nat) 58.0 49,6 40.2 - 55.1 Acceptable Uranium (Nat) Not RAD- 82 3 12010 Water ug/L Mass 89,1 72.3 58.7 - 80.4 Acceptable Not RAD*82 3 j 2010 Water pCiil Zinc*55 161 110 99.0*131 Acceptable M;S~2 'v- I ..:5 12010 Soil I 8Q/ku Iirn"ri..-iHm*?41 9,07. 0*90 c--- MAPEp*10- Not RdF22 I 3 12010 Filter Sq/sample , Americium-241 02631 0.146 0.102*0.190 I MAPEP I RdV22 3 '/2010 VeQ.etation Ba/sample Americium-241 0.179 0225 0158-0293 Acceptable MAPEP MaS22 3'°/2010 Soil Bqlkg Cesium-134 74467 733 513-953 Acceptable MAPEP Not RdF22 3 ,d 12010 Filter Ba/sample Cesium-134 4.323 2,13 1.49 - 2,77 Acceptable MAPEP RdV22 I 3 12010 Vegetation Bu/sample Cesium*134 3,098 4,39 307 - 5.71 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 19 of 51 Acceptance Sample Sample Known Rangel I Number Quarter 1Year Media Unit Analyte 1 Nuclide GEL Value value Ratio ' Evaluation MAPEp*l0* MaS22 3'°/2010 Soil BQ/kg Cesium*137 831.7 779 545*1013
!I Acceptable MAPEP*l0* Not RdF22 3 ,d 12010 Filter Bg/sample Cesium*137 3.070 1.53 107*1.99 Acceptable MAPEp*l0*
RdV22 3,d/ 201O Vegetation Bq/sample Cesium*137 2.185 3.06 2.14*3.98 Acceptable MAPEp*10* MaS22 3 ,d 12010 Soil Sq/kg Cobalt*57 536.0 522 365*679 Acceptable MAPEP*l0* RdV22 3'" 12010 Vegetation Bg/sample Cobalt*57 0.009 0.00 ---- Acceptable MAPEP*l0* MaS22 3'd/2010 Soil Bq/kg Cobalt*60 670.3 622 435*809 Acceptable MAPEP*10* Not RdF22 3,d/2010 Filter Bq/sample Cobalt*60 5.187 2.473 1.731*3.215 Acceptable MAPEP*10* RdV22 3,d/2010 Vegetation Bg/sample Cobalt*60 3.076 3.27 2.29*4.25 Acceptable MAPEP*10* GrF22 3 ,d 12010 Filter Bg/sample Gross Alpha 0.303 0.427 >0.0*0.854 Acceptable MAPEp*l(). GrF22 3'd/ 201 O Filter Bq/sample Gross Beta 1.433 1.29 0.65*1.94 Acceptable MAPEp*l0* MaS22 3 ,d 1 2010 Soil Bq/kg Iron*55 83.6 0.00 ---- Acceptable MAPEp*l0* MaS22 3 ,d 12010 Soil Sq/kg Manganese*54 940.7 849 594*1104 Acceptable MAPEp*10* Not RdF22 3'd/ 201O Filter Bg/sample Manganese*54 6.483 3.02 2.11 *3.93 Acceptable MAPEP*l0* RdV22 3" 12010 VegetaUon Bq/sample Manganese-54 0.004 0.00 ---- Acceptable MAPEp*10* MaS22 3 ,d 12010 Soil Bq/kg Nickel-63 489 477 334*620 Acceptable MAPEP-l0-MaS22 3 ,d 12010 Soil BQ/kg Plutonium-238 17.9 24 16.9*31.3 Acceptable MAPEP-l0-RdF22 3,d12010 Filter Bg/sample Plutonium*238 0.010 0.0010 -- Acceptable MAPEp*l0-RdV22 3'0/2010 VegetaUon Bq/sample Plutonium*238 0.149 0.160 0.112 - 0.208 Acceptable MAPEp*l0* Plutonium* MaS22 3,d/2010 Soil Bg/kg 239/240 0.21 0.00 _.- Acceptable MAPEP*l0- Plutonium- 0.0582 - Not RdF22 3 ,d 12010 Filter Bqlsample 239/240 0.164 0.0832 0.1082 Acceptable MAPEp*l0* Plutonium-RdV22 3 ,d /2010 Vegetation Bq/sample 2391240 0.0026 0.0008 ---- Acceptable MAPEp*l0* MaS22 3 ,d /2010 Soil Bg/kg Potassium*40 638.7 559 391 *727 Acceptable MAPEP*l0* I MaS22 3'°12010 Soil Bg/kg Strontium*90 261.0 288 ! 202 - 374 Acceptable I MAPEP*l0* RdF22 I 3,e/2010 Filter Bg/sampie Strontium*90 -0.004 0.00 I I -~-- I Acceptable I MAPEP-10* RdV22 ! 3 'd! 2010 ""mn,i; .on 0.033 0.00 ...- Acceptable ~:;;; 10-3 12010 Soil Sqlkg Technetiv m - QQ -3.0 0.00 I _._- 10-
,I
'¥'nrL..r MaS22 Soil Sq/kg ", ",.,~" lL 3 12010
, II"""" 65.27 60 42 -78 MAPEP*10* Not RdF22 3 12010 Filter
- Bq/sampie !l 0137 0.068 0.048 - 0.088 Acceptable MAPEP-10*
RdV22 MAPEp*10* 3" 12010 Vegetation Bq/sample Uranium*234/233 0.184 0.216 0.151- 0.281 0.0267* I Acceptable Not I RdF22 3,d/2010 Filter uQ/sample Uranium*235 0.0756 0.0381 0.0495 Acceptable MAPEP-10* 00875* RdV22 3 '012010 Vegetation ug/sample Uranium-235 0.090 0.1250 0.1625 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 20 of 51
, Acceptance I Sample Number I Quarter 1 Year Sample Media Unit Analyte 1 Nuclide GEL Value Known value Rangel Ratio Evaluation MAPEP-l0-MaS22 3'dl2010 Soil Bqlkg Uranium-238 70.23 64 45___ 83 Acceptable MAPEP-l0- Not RdF22 3 ,d /2010 Filter ug/sample Uranium-238 10.2 5.7 4.0 - 7.4 Acceptable MAPEP-l0- Not RdF22 3,d/2010 Filter Bq/sample Uranium-238 0.147 0.071 0.050 - 0092 Acceptable MAPEP-l0- Not RdV22 3'" /2010 Vegetation uglsample Uranium-238 12.5 17.9 12.5 - 233 Acceptable MAPEP-l0-RdV22 3 ,d /201 0 Vegetation Bq/sample Uranium-238 0.184 0.223 0.156 - 0.290 Acceptable MAPEp-l0- Not RdF22 3"12010 Filter uglsample Uranium-Total 10.2 5.7 4.0 - 7.4 Acceptable MAPEP-l0-RdV22 3,d/2010 Veaetation uglsample Uranium-Total 13.9 18.0 12.6 - 23.4 Acceptable MAPEP-l0*
MaS22 3 ,d 1201 0 Soil Bq/kg Zinc-65 -2.89 0.0 -.- Acceptable MAPEP-l0-RdF22 3'"12010 Filter Bqlsample Zinc-65 -0.106 0.00 .--- Acceptable MAPEP-l0-RdV22 3 ,d 1201 0 Vegetation Bqlsample Zinc-65 6.844 7.10 4.97 - 9.23 Acceptable E7119-278 3 ,d 12010 Milk pCill Cesium-l34 137E+02 126E+02 109 Acceptable E7119-278 3,d 1 2010 Milk pCill Cesium-137 1.68E+02 1.50E+02 1.12 Acceptable E7119-278 3'd12010 Milk pCill Cobalt-58 1.13E+02 1.01E+02 1.12 Acceptable E7119-278 3 ,d 12010 Milk pC ill Cobalt-60 2.14E+02 1.97E+02 1.09 Acceptable id E7119-278 3 /2010 Milk pCill Cr-51 3.90E+02 3.39E+02 1.15 Acceptable E7117-278 3 ," 12010 Milk pCill lodine-131 7.97E+Ol 8.02E+Ol 0.99 Acceptable E7119-278 3'"/2010 Milk pCi/L lodine-131 1.06E+02 9.69E+Ol 1.09 I Acceptable I Not E7119-278 3 ,d 12010 Milk pC ill Iron-59 1.55E+02 1.19E+02 1.30 Acceptable E7119-278 3'*/2010 Milk pCill Manganese-54 1.99E+02 1.69E+02 1.18 Acceptable E7118-278 3'd/2010 Milk pCill Strontium-89 7.95E+Ol 9.34E+Ol 0.85 Acceptable E7118-278 3'd / 2010 Milk pCill Strontium-OO 1.57E+Ol 1.67E+Ol 0.94 Acceptable E7119-278 3 ,d 12010 Milk pCill Zinc-65 2.40E+02 2.06E+02 1.17 Acceptable 090710N 3'd /201 0 Water pCill Barium-133 86.9 92.9 78.3 - 102 Acceptable Not 09071 ON 3 ," 12010 Water pCi/L Cesium-134 93.8 79.4 65.0 - 87.3 Acceptable 090710N 3,d / 2010 Water pCill Cesium-137 55.5 54.6 49.1 - 62.9 Acceptable 090710N 3'd / 2010 Water pCill Cobalt-60 120.0 117 105 - 131 Acceptable 090710N 3'*/2010 Water pCill Uranium (Nat) 349 33.8 27.3 - 37.8 I Acceptable
, Uranium (Nat) 090710N 3 12010 Water uq/L I Mass 48.6 49.3 39.8 - 55.1 Acceptable
, 090710N 3 12010 Water pCi/l I Zinc-55 I 129 99.5 89.6 119 No! Acceptable
~;~~;10. ,I Bq/!. I I 3 '/2010 Water ~ -.UQ. 091-1.69 Acceptable MAPEP-1O-MaW22 3 12010 Waler I 8q1L Cesium-134 0.027 000 --- Acceptable MAPEp*lO- I MaW22 MAPEp*10-3 12010 Water 8wl I Cesium-137 63.1 60.6 42.4 - 78.8 Acceptable MaW22 3 ,d 12010 Water 8wl Cobalt-57 29.2 28.3 19.8 - 36.8 Acceptable MAPEP-l0-MaW22 3 12010 Water BQ/L Cobalt-GO -0.021 0.00 --- Acceptable
Laboratories p,o, Box 30712, Charleston. SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 21 of 51 I Sample Sample I Known Acceptance Rangel I Number Quarter 1 Year Media Unit Analyte I Nuclide GEL Value value Ratio Evaluation MAPEP-l0-GrW22 3'" 12010 Water BqlL Gross Alpha 0559 0,676 >0,0 - 1,352 Acceptable MAPEP GrW22 3"/2010 Water BQIL Gross Beta 3.110 3,09 1,55 - 4,64 Acceptable MAPEP-l0-MaW22 3'd l 2010 Water BqlL Iron-55 0,24 0,00 --- Acceptable MAPEP MaW22 3'0/2010 Water BQ!t Manganese-54 28.83 26,9 18.8 - 35,0 Acceptable MAPEP MaW22 3"/2010 Water BgIL Nickel-63 57,7 59,9 419 - 779 Acceptable MAPEP-l0- Not MaW22 3"/2010 Water BgIL Plutonium-238 1,213 1,93 1,35 - 2,51 Acceptable MAPEP Plutonium-MaW22 3,d l2 0 10 Water BQIL 2391240 0,026 0,009 --- Acceptable MAPEP MaW22 3'0/2010 Water BqJL Strontium-90 -0,01 0,00 ~- .- Acceptable MAPEP-l0-MaW22 3'" 12010 Water BqlL Technetium-99 -0.4 0,00 -- Acceptable MAPEP-l0-MaW22 3'd 12010 Water BqlL Tritium 107 90,8 63,6 - 118,0 Acceptable MAPEP-l0-MaW22 3'" 12010 Water BqlL Uranium-234/233 1,163 122 0,85 - 1,59 Acceptable MAPEP-l0-MaW22 3 ,d 12010 Water BqlL Uranium-238 1,223 1,25 0,88 - 1.63 Acceptable MAPEP-l0-MaW22 3'd 12010 Water BqJL Zinc-65 45,9 40,7 28,5 - 52,9 Acceptable E7195-278 4" 12010 Milk pC ill Cerium-141 1,39E+02 1,30E+02 1,07 Acceptable E7195-278 4" 12010 Milk pCilL Cesium-134 9,85E+01 9,30E+Ol 1,06 Acceptable E7196-278 4" 12010 Water pCI/L Cesium-l34 1.22E+02 1,18E+02 1,03 AccePtable E7195-278 4" 12010 Milk pCilL Cesium-137 9,87E+Ol 9.45E+01 1,04 Acceptable E7196-278 4'" 12010 Water pCilL Cesium-137 1,24E+02 1,20E+02 1,03 Acceptable E7195-278 41h 12010 Milk pCilL Cobalt-58 7,02E+01 7,37E+Ol 0,95 Acceptable E7196-278 4'" /2010 Water pCilL Cobalt-58 9,63E+01 9,35E+Ol 1,03 Acceptable E7195-278 4'" 12010 Milk pC ilL Cobalt-60 1,77E+02 1,71E+02 1,04 Acceptable E7196-278 4" /2010 Water pCilL Cobalt-60 234E+02 2,17E+02 1,08 Acceptable E7195-278 4" ! 2010 Milk pCilL Cr-51 2.48E+02 2,34E+02 1,06 Acceptable E7196-278 4'" 12010 Water pCiIL Cr-51 3.12E+02 2,97E+02 1,05 Acceptable E7193-278 4'" 12010 CartridQe pCi lodine-131 5.97E+01 6.02E+Ol 0,99 Acceptable E7195-278 4th 12010 Milk Q..CilL lodine-131 101 E+02 9.41E+02 1.07 Acceptable E7196-278 4'" 12010 Water pCilL lodine-131 7,24E+01 6.44E+Ol 1,12 Acceptable E7195-278 I 4'" f 2010 Milk pCilL Iron-59 1,02E+02 9.11E+Ol 1,12 Acceptable I E7196-278 4"'12Q1Q I Waler , pG,ilL !rgn-li9 1,42E+Og 1.161;+02 1 123 ! Accefjtable E7195-218 I 4'" 12010 Milk i pCilL Man9anese-54 120E+02 U9E+02 1.01 I E7196-278 I 4'" 12010 Water pCill I Manganese-54 1.70E+02 1,52E+02 1,12 I i E7194-278 4'" 12010 Milk .pCilL i Strontium-89 7.62E+01 9,28E+01 ' 0.82 ! Acceptable E7194-278
! 4"' 12010 Milk pCilL Strontium-90 1,30E+01 1.47E+Ol 0,88 Acceptable E7195-278 4'" 12010 Milk pCilL Zinc-65 2,37E+02 2,04E+02 1,16 Acceptable E7196-278 4'h 12010 Water pCiIL Zinc-55 2,97E+02 2.59E+02 1,15 Acceptable NY-3373762 I 4'" 12010 Water pCilL I Barium-133 50,5 50.9 43.3 - 59.4 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 22 of 51 II I Acceptance I Sample Number I Quarter I Year Sample Media Unit Analyte I Nuclide GEL Value Known value Rangel Ratio I Evaluation Not NY-3373762 4"' 12010 Water pCilL Cesium-l34 51.0 42.0 358 - 49.2 Acceptable NY-3373762 4'" 12010 Water pCilL Cesium-137 29.3 27.3 22.4 - 32.1 Acceptable NY-3373762 4"' 12010 Water pC ill Cobalt-60 13.6 13.2 9.72 - 16.7 Acceptable NY-3373763 4'" 12010 Water pCilL Gross Alpha 32.8 41.6 24.3 - 58.9 Acceptable NY-3373763 4"' 12010 Water pCilL Gross Beta 29.3 27.5 18.3 - 36.7 Acceptabte Not NY-3373764 4"' 12010 Water pCilL lodine-131 13.4 18.2 14.7- 21.7 Acceptable Not NY-3373764 4"' 12010 Water pCilL lodine-131 13.5 18.2 14.7 - 21.7 Acc Not NY-3373765 4'" 12010 Water pC ill Radium-226 13.2 10.6 8.30 - 12.9 Acceptable NY-3373765 4'" 12010 Water pCilL Radium-228 6.51 6.07 3.91 - 8.22 Acceptabte Not NY-3373761 4"' 12010 Waler pCilL Strontium-89 47.8 61.3 51.3 -71.4 Acceptable NY-3373761 4"' 12010 Water pC ill Strontium-OO 12.0 14.9 11.0 - 18.8 Acceptable 13500 - NY-3373766 4'" 12010 Water pCilL Tritium 14400 15300 17000 Acceptable NY-3373765 4'" 12010 Water pCilL Uranium (activity) 17.5 16.0 13.2-18.7 Acceptable NY-3373762 4"' 12010 Water pCilL Zinc-65 134 122 104 -138 Acceptable l00510N 4'" 12010 Water pCilL Strontium-89 49.9 51.4 40.6 - 58.9 Acceptable 100510N 4'" 12010 Water pCilL Strontium-90 35.4 41.3 30.4 - 47.5 Acceptable RAD-83 4"' 12010 Water pCilL Strontium-90 41.5 43 31.7 - 49.3 Acceptabte 112210Hl 4'" 12010 Water pCi/l Barium-133 66.3 65.9 54.9 - 72.5 Acceptable 112210Hl 4th 12010 Water pCilL Cesium-l34 71.6 71.6 58.4 - 78.8 Acceptable 112210H1 4th 12010 Water pCilL Cesium-137 151 146 131-163 Acceptable 112210Hl 4'" 12010 Water pCi/l Cobalt-60 90.2 84.5 76.0 - 95.3 Acceptable 112210Hl 4'" 12010 Water ,n Zinc-65 207 186 167 - 219 Acceptable 112210H2 4th 12010 Water pCill Plutonium-238 102.0 108 81.7-134 Acceptable 112210H2 4th 12010 Water pCilL Plutonium-239 77.6 86.3 66.8-107 Acceptable MRAD-13 4th 12010 Soil pCVkg Actinium-228 1460 1830 1170 - 2580 Acceptable MRAD-13 4th 12010 Soil pCi/kg Americium-241 845 1120 669 - 1440 Acceptable MRAD-13 4"' 12010 Soil pCi/kg Americium-241 928 1120 669 - 1440 Acceptable MRAD-13 4"' 12010 VeQetation pCi/kg Americium-241 4000 4760 2710 - 6540 Acceptable MRAD-13 i 4th 12010 Air Filter , pCi/Filler Americium-241 70.1 74.1 43.3 - 102 Acceptable I I MRAD-13 4" 12010 Water pCill "'fl 164 176 120 - 238 Acceptable MRAD-13 I 4"'/2010 Water oCi/L ." 178 176 120 - 238 A No! MRAD-13 4'" ! 2010 peiikg Bismuth-212 <: 538 2070 i 543 - 3100 I Acceptable MRAD-13 i 4"'!2010~ pCi/kg Bismu!h-214 818 983 603 - 1410 Acceptable i MRAD-13 + 4 ' " 12010 Soil pCi/kg Cesium-l34 2230 2240 1440 - 2700 I MRAD-13 4" 12010 Vegetation pCi/kg Cesium-134 1200 1040 595 - 1440 Ac MRAD-13 4'" 12010 Air Filter pCi/Filter Cesium-l34 405 388 253 -480 Acceptable MRAD-13 4'" 12010 Water pCilL Cesium-134 495 492 363 - 565 Acceptable
Laboratori P.O. Box 30712, Charleston. SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 23 of 51 Acceptance Sample Sample Known Rangel I Number Quarter I Year Media Unit Analyte 1 Nuclide GEL Value value Ratio Evaluation I MRAD-13 4'" 12010 Soil pCi/kg Cesium-137 3400 3530 2700 - 4580 Ie L'- MRAD-13 4'" 12010 Vegetation pCi/kg Cesium-137 1420 1260 I 924 -17 MRAD*13 4'" 12010 Air Filter pCi/Filter Cesium-137 532 514 386 6 MRAD*13 4'" 12010 Water pC ill esium-137 620 625 531 *749 Acceotable MRAD-13 4"'/2010 Soil pCi/kg Cobalt-60 4580 4780 3480 - 6420 Acceptable MRAD-13 4'" /2010 Vegetation pCi/kg Cobalt-60 1130 1010 683 -1450 Acceptable MRAQ*13 4'" /2010 Air Filter pCi/Filter Cobalt-60 531 479 371 - 598 Acceptable MRAD*13 4'" /2010 Water pCilL Cobalt-60 732 714 622 - 844 Acceptable MRAD-13 4'" /2010 Air Filter pCi/Filter Gross Alpha 74.2 52.3 27.1 - 78.7 Acceptable MRAD*13 4'" /2010 Water pCilL Gross Alpha 145 146 64.8*216 Acceptable MRAD*13 4'" /2010 Air Filter pCi/Filter Gross Beta 55.6 52.7 32.5 - 77.0 Acceptable MRAD-13 4'" /2010 Water pC ill Gross Beta 171 143 83.6 - 210 Acceptable MRAD*13 4th 12010 Air Filter pCi/Filter Iron-55 707 626 275 - 974 Acceptable Not MRAD-13 4'" /2010 Water pCilL Iron*55 1220 825 480 - 1100 Acceptable MRAD*13 4'" /2010 Soil pCi/kg Lead-212 1550 1640 1060 - 2310 Acceptable MRAD*13 4'" 12010 Soil pCi/kg Lead-214 1030 969 580 - 1440 Acc MRAD-13 4th 12010 Soil pCilkg Manganese-54 < 38.0 0.00 ~_M_ Acceptable MRAD*13 4'" 12010 Vegetation pCi/kg Manganese-54 < 39.8 0.00 --- Acceptable MRAD-13 4th 12010 Water pCi/L Manganese-54 <5 0.00 ---- Acceptable MRAD*13 4th 12010 Soil pCi/kg Plutonium-238 1170 1280 733 *1800 Acceptable MRAD*13 4th 12010 Vegetation pCi/kg Plutonium-238 3740 4740 2560 - 6940 Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Plutonium-238 70.8 72.9 50.0*95.8 Acceptable MRAD-13 4th 12010 Water pCilL Plutonium-238 157 162 122 - 201 Acceptable MRAD*13 4th 12010 Soil pCi/kg Plutonium-239 1070 1180 805 *1570 Acceptable MRAD-13 4th 12010 Vegetation pCi/kg Plutonium-239 3590 4470 2770*6100 Acceptable MRAD-13 41h 12010 Air Filter pCi/Filter Plutonium-239 65.6 69.6 50.5 - 90.1 Acceptable MRAD-13 4th 12010 Water pC ill Plutonium-239 136 148 114*183 Acceptable MRAD-13 4'" 12010 Soil pCi/kg Potassium*40 10500 10700 7760*14500 Acceptable I 16200 - MRAD-13 4'" /2010 pCi/kg Potassium-40 29000 22600 ! 32000 Acceptable MRAD-13 4111 12010 Soil pCiikQ Strontium-90 10953 9270 I 3350 - 15100 Acceptable I MRAD*13 4'" 12010 pCi/kg ~!mnl"uY'dll1 9800 t 7810 4360 - 10400 I I
+/-::~
MRAD-13 I 4"' 12010 Air Filter pC!/Filter ! Strontium-90 80.2 70.D 247 Acceptable MRAD-13 I 4th ! 2010 Water oellt ~k"nti"m-90 817 I 585 - 1230 MRAD-13 4" 12010 Soil pCi/kg Thorium-234 1010 1340 425 - 2550 14100 MRAD-13 I 4111 12010 Water pC ill Tritium 20900 21600 31900 Acceptable MRAD-13 4'" 12010 Soil pCi/kg Uranium-234 899 1360 862 - 1690 Acceptable MRAD-13 4'" 12010 Soil pCUkQ Uranium-234 1190 1360 862*1690 Acceptable MRAD-13 4th /2010 Soil pCi/kg Uranium-234 1110 1360 862 - 1690 Acceptable
Laboratories L P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 24 of 51 I ! Acceptance Sample Number 1 Quarter / Year Sample Media Unit I Analyte I Nuclide GEL Value Known value Rangel Ratio Evaluation I MRAD-13 4'" 12010 Vegetation pCi/kg Uranium-234 3600 4010 2750 - 5320 Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Uranlum-234 73.5 71.8 45.2 - 106 Acceptable MRAD-13 4'" f 2010 Air Filter pCi/Filter Uranium-234 69.9 71.8 45.2-106 Acceptable MRAD-13 4'" /2010 Water pCilL Uranium-234 106 109 82.2 - 140 Acceptable MRAD-13 4"' /2010 Water pCiIL Uranium-234 106 109 82.2 - 140 Acceptable MRAD-13 4'" /2010 Water pCilL Uranium-234 104 109 82.2 -140 Acceptable MRAD-13 4th /2010 Soil pCilkg Uranium-238 1010 1340 819-1700 Acceptable MRAD-13 4'" /2010 Soil pCi/kg Uranium-238 1080 1340 819 -1700 Acceptable MRAD-13 4'" /2010 Soil pCi/kg Uranium-238 903 1340 819-1700 Ace MRAD-13 4"' /2010 Soil pCi/kg Uranium-238 1090 1340 819 - 1700 Acceptable MRAD-13 4"' /2010 Vegetation pCi/kg Uranium-238 4000 3980 2800 - 5030 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Uranium-238 75.5 71.2 45.6 -101 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Uranium-238 66.8 71.2 45.6 - 101 Acceptable MRAD-13 4'" /2010 Water pCilL Uranium-238 107 108 82.5 -134 Acceptable MRAD-13 4'" /2010 Water pCi/L Uranium-238 114 108 82.5 - 134 Acceptable MRAD-13 4"' /2010 Water pCilL Uranium-238 108 108 82.5 -134 Acceptable MRAD-13 4'" /2010 Soil pCi/kg Uranium-Total 2027.4 2770 1580 - 3740 Acceptable MRAD-13 4'" /2010 Soil UQ/kg Uranium-Total 2093 2770 1580 - 3740 Acceptable MRAD-13 4'" /2010 Soil pCilkg Uranium-Total 2253 2770 1580 - 3740 Acceptable MRAD-13 4"' /2010 Air Filter pCI/Filter Uranium-Total 149 146 74.6 - 232 Acceptable MRAD-13 4'" /2010 Air Filter pCi/Filter Uranium-Total 142 146 74.6 - 232 Acceptable MRAD-13 4'" /2010 Water pCilL Uranium-Total 218 221 159 - 294 Acceptable MRAD-13 4'" /2010 Waler pC ill Uranium-Total 226.8 221 159 - 294 Acceptable MRAD-13 4'h /2010 Water pCilL Uranium-Total 217 221 159 - 294 Acceptable Uranium-Total MRAD-13 4th /2010 Soil ug/kg (mass) 3240 4040 2220 - 5080 Acceptable Uranium-Total MRAD-13 4th 12010 Soil pCi/kg (mass) 2685 4040 2220 - 5080 Acceptable Uranium-Total MRAD-13 4"' 12010 Soil ug/kg (mass) 3241 4040 2220 - 5080 Acceptable Uranium-Total MRAD-13 ! 4th 12010 Soil ug/kg (mass) 2820 4040 2220 - 5080 Acceptable Uranium-Total MRAD-13 4'" 12010 Veaetation ug/kg (mass) 12000 11900 I 8180 - 15400 Acceptable I Uranium-Total MRAD-13 I 4' 12010 Air Filter ugfFlller (mass) 224.5 213 ! 132 - 306 I I MRAD-13 1 4" 12010 I AirF.lter
,F I
ura~~;~~o!a! 201 213 132 *306 Uramum-To!al , MRAD-13 4' 12010 Air Filter I ugiFilter (mass) 192 213 132 306 Acceptable Uranium-Total MRAD-13 I {" i 2010 Water ugIL (mass) 318 323 253*399 i Acceptable I Uranium-Total MRAD-13 4th 12010 Water ug/L (mass) 342 323 253 - 399 Acceptable Uranium-Total MRAD-13 4'" 12010 Water uglL (mass) 321 323 253 - 399 Acceptable MRAD*13 4'" 12010 Soil pCi/kg Zinc-65 2420 2300 1820 - 3080 Acceptable
[#]§, Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 25 of 51 I II I Acceptance Sample Sample ! Known Rangel Number t Quarter 1 Year Media Unit I Analyte 1 Nuclide GEL Value value Ratio Evaluation MRAD-13 4" 12010 Vegetation pCi/kg Zinc-65 1380 1210 874 -1650 Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Zinc-65 552 465 322 - 644 Acceptable MRAD-13 4'" 12010 Water pCill Zinc-65 557 489 414 - 610 Acceptable 122810P 4'" /2010 Waler pCill Barium-133 70.9 68.9 57.5 - 75.8 Acceptable 122810P 4'" /2010 Waler pCill Cesium-134 43.0 43.2 34.5 - 47.5 Acceptable 122810P 4" /2010 Water pCill Cesium-137 122 123 111-138 Acceptable 122810P 4'" 12010 Water pCill Cobalt-60 58.7 53.4 48.1 - 61.3 Acceptable 122810P 4'" 12010 Water pCill Zinc-65 116 102 91.8-122 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 26 of 51 TABLE 2 2010 ECKERT & ZIEGLER ANALYTICS PERFORMANCE EVALUATION RESULTS
SUMMARY
Acceptance Sample Quarter I Sample Analyte I GEL Known Rangel Number Year Media Unit Nuclide Value value Ratio Evaluation E7054-278 2"" 12010 Milk pCill Cerium-141 2.S1E+02 2.S1E+02 100 Acceptable E7055-278 2nd 12010 Water pCill Cerium-141 2.78E+02 2.S3E+02 1.0S Acceptable ES924-278 2"" 12010 Milk pCill Cerium-141 2.01E+02 2.02E+02 0.99 Acceptable ES925-278 2"" 12010 Water pCill Cerium-141 2.04E+02 2.04E+02 1.00 Acceptable ES924-278 2nd 12010 Milk pCill Cerium-141 2.01E+02 2.02E+02 0.99 Acceptable ES925-278 2"" 12010 Water pCill Cerium-141 2.04E+02 2.04E+02 1.00 Acceptable E7054-278 2nd 12010 Milk pCill Cesium-137 161E+02 1.58E+02 1.02 Acceptable E7055-278 2nd 12010 Water pCill Cesium-137 1.71E+02 1.59E+02 1.07 Acceptable E6924-278 2"" 12010 Milk pCill Cesium-134 2.41E+02 2.53E+02 0.95 Acceptable E6925-278 2nd 12010 Water pCill Cesium-134 2.56E+02 2.55E+02 1.00 Acceptable nd E6924-278 2 12010 Milk pCill Cesium-134 2.41E+02 2.53E+02 095 Acceptable E6925-278 2nd 12010 Water pCilL Cesium-134 2.56E+02 2.55E+02 1.00 Acceptable E7054-278 2nd 12010 Milk pCill Cesium-134 1.76E+02 1.78E+02 0.99 Acceptable E7055-278 2nd 12010 Water pCill Cesium-134 1.85E+02 1.79E+02 1.03 Acceptable E6924-278 2nd 12010 Milk pCiIl Cesium-137 1.71E+02 1.79E+02 0.96 Acceptable E6925-278 I 2nd ! 2010 Water pCill I Cesium-137 1.81E+02 1.81E+02 1.00 Acceptable I I E6924-278 I 2"" 1.2010 Milk pCilL I Cesiurn~ 137 171E+02 1 0.96 i Acceptable E6925-278 2rui /2010 Water pCiIl I Cesium-137 1.81 E+02 i 1.81 E+02 I 100 E7054-278 2nd 12010 Milk pCill I Chromium-51 3.81E+02 3.61E+02 I 1.05 Acceptable I E7055-278 2'~ 12010 Water pCill Chromium-51 3.86E+02 3.64E+02 1.06 Acceptable E6924-278 2nd /2010 Milk pCill Chromium-51 5.54E+02 5.48E+02 1.01 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 27 of 51
, i I I Acceptance Sample Number Quarter 1 Year Sample Media Unit Ana\yte 1 Nuclide I GEL Value Known value Rangel Ratio Evaluation E6924-278 2nd 12010 Milk pCilL Chromium-S1 S.54E+02 S.48E+02 101 Acceptable E692S-278 2nd 12010 Water pCilL Chromium-S1 S.78E+02 5.54E+02 104 Acceptable E7054-278 2'd 12010 Milk pCi/L Cobalt-S8 1.45E+02 1.43E+02 1.02 Acceptable E705S-278 2nd 12010 Water pCilL Cobalt-58 1.S1E+02 1.44E+02 1.0S Acceptable E6924-278 I 2'd 12010 Milk pCilL Cobalt-S8 2.03E+02 2.11E+02 0.96 Acceptable E692S-278 2'd 12010 Water .pCilL Cobalt-S8 2.19E+02 2.13E+02 1.03 Acceptable E6924-278 2"" 12010 Milk pCilL Cobalt* 58 2.03E+02 2.11E+02 0.96 Acceptable E6925-278 2"" 12010 Water pCilL Cobalt-S8 2.19E+02 2.13E+02 1.03 Acceptable E7054-278 2nd 12010 Milk pCilL Cobalt-60 1.90E+02 1.83E+02 1.04 Acceptable E70SS-278 2'd 12010 Water pC ill Cobalt-60 1.94E+02 1.8SE+02 10S Acceptable E6924-278 2'd 12010 Milk pCilL Cobalt-60 2.47E+02 2.S6E+02 0.97 Acceptable E692S-278 2nd 12010 Water pCilL Cobalt-60 2.67E+02 2.S8E+02 1.03 Acceptable E6924-278 2'd 12010 Milk pC ill Cobalt-60 2.47E+02 2.S6E+02 0.97 Acceptable E692S-278 2nd 12010 Water pCilL Cobalt-60 2.67E+02 2.S8E+02 1.03 Acceptable 00 E70S2-278 2 12010 Cartridqe pCi lodine-131 8.S8E+01 8.54E+01 1.00 Acceptable E7054-278 2nd 12010 Milk pC ill lodine-131 6.91E+01 7.40E+01 0.93 Acceptable nd E70SS-278 2 12010 Water pCilL lodine-131 8.12E+01 7.22E+01 1.12 Acceptable E6922-278 2nd 12010 Cartridqe pCi lodine-131 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 . 2'd 12010 Milk pCill lodine-131 B.25E+01 B.73E+01 0.95 Acceptable I """..,,,
II 2M 12010 Water pCill I lodine-131 1.00E+02 I I 9.61 E+Ol
')70 1.04 I E6922-278 2 nd 12010 i lodine-131 9.02E+Ol 9.39E+01 I 0.96 I
E6924-278 2nd 12010 Milk pCilL lodine-131 825E+Ol 8.13E+Ql I 0.95 Acceptable I E692S-278 2nd 12010 Water pCilL lodine-131 1.00E+02 9.61E+01 I 1.04 Acceptable r E7054*278 2'd /2010 Milk pCilL Iron-59 1.60E+02 i 1.37E+02 I 117 Acceptable
CI§JI Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 28 of 51 I Sample I Quarter 1 Sample Analyte 1 GEL I Known I Acceptance Rangel Number I Year Media Unit Nuclide Value value Ratio Evaluation E6924-278 2nd 12010 Milk pCilL Iron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2' 12010 Water pCiIL Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2"d 1 2010 Milk pCilL Iron-59 1.88E+02 1.78E+02 106 Acceptable E6925-278 2"" 12010 Water pCilL Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2"" 12010 Milk pCilL Manganese-54 1.83E+02 1.78E+02 103 Acceptable E6925-278 2"" 12010 Water pCilL Manganese-54 1.90E+02 1.79E+02 1.06 Acceptable E6924-278 2nd 12010 Milk pCilL Manoanese-54 1.83E+02 1.78E+02 1.03 AccE!p!able E6925-278 2"d 12010 Water pCiIL Manganese-54 1.90E+02 1.79E+02 1.06 Acceptable E7054-278 20d 12010 Milk pC ill ManQanese-54 2.10E+02 2.07E+02 1.01 Acceptable E7055-278 2"d 12010 Water pCilL ManQanese-54 2.30E+02 2.09E+02 1.1 Acceptable E7053-278 2 0d 12010 Milk pCilL Strontium-89 7.91E+01 9.28E+01 0.85 Acceptable E6923-278 2nd 12010 Milk pCilL Strontium-89 9.73E+01 1.31E+02 0.75 Acceptable E6923-278 2"" 12010 Milk pCilL Strontium-89 9.73E+01 1.31E+02 0.75 Acceptable E7053-278 2nd 12010 Milk pCiIl Strontium-90 1.12E+01 1.27E+01 0.88 Acceptable E6923-278 2nd 12010 Milk pCilL Strontium-90 1.38E+01 1.79E+01 0.77 Acceptable E6923-278 2nd 12010 Milk pCilL Strontium-90 138E+01 1.79E+01 0.77 Acceptable 0d E6924-278 2 12010 Milk pCilL Zinc-65 3.68E+02 3.45E+02 1.07 Acceptable E692S-278 2"" 12010 Water pCilL Zinc-65 3. 72E+02 3.48E+02 107 Acceptable "'692,,-2"0 2M 12010 Milk pC lit. Zinc-55 3.58E+02 c!4.!>F+02 1.07 E5925-278 20d 12010 Water pC11L Zinc-55 372E+02 3A8E+02 1.07 E7054-278 20d 12010 Milk .flCilL Zinc-65 2.71E+02 2.54E+02 107 Acceptable I E7055-278 2"" 12010 Water pCilt. Zinc-65 2.97E+02 I 2.56E+02 1.16 Acceptable I E7119*278 3'd 12010 Milk pCi!L Cerium-141 1.27E+02 I 1.10E+02 1.15 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 29 of 51 Acceptance Sample Quarter I Sample Analytel GEL I Known Rangel Number Year Media Unit Nuclide Value value Ratio Evaluation E7119-278 3"'/2010 Milk pCilL Cesium-137 1.68E+02 1.50E+02 1.12 Acceptable E7119-278 I 3'" 12010 Milk pCilL Chromium-51 3.90E+02 3.39E+02 1.15 Acceptable E7119-278 3'" 12010 Milk pCilL Cobalt-58 1.13E+02 101E+02 1.12 Acceptable E7119-278 3 cd 12010 Milk pCilL Cobalt-60 2.14E+02 1.97E+02 1.09 Acceptable E7117-278 3 cd 12010 Milk pCilL lodine-131 7.97E+01 8.02E+01 0.99 Acceptable E7119-278 3 cd 12010 Milk pCilL lodine-131 1.06E+02 9,69E+01 1.09 Acceptable E7119-278 3 cd 12010 Milk pCilL Iron-59 1.55E+02 1.19E+02 1.30 Not Acceptable E7119-278 3'" 12010 Milk pC ill Manganese-54 1.99E+02 1,69E+02 1.18 Acceptable E7118-278 3 cd 12010 Milk pC ill Strontium-89 7.95E+01 9.34E+01 0.85 Acceptable E7118-278 3'" 12010 Milk oCilL Strontium-90 1.57E+01 1,67E+01 0.94 Acceptable E7119-278 3 ,d I 2010 Milk pCilL Zinc-65 2.40E+02 2.06E+02 1.17 Acceptable E7195-278 4'" 12010 Milk pCiIL Cerium-141 1,39E+02 1.30E+02 1.07 Acceptable E7196-278 4'" 12010 Water oCi/L Cerium-141 1,74E+02 1.65E+02 1.05 Acceptable E7195-278 4'" 12010 Milk pC ill Cesium-l34 9.85E+01 9.30E+01 1.06 Acceptable E7196-278 4'" 12010 Water pC ill Cesium-134 1.22E+02 1.18E+02 1.03 Acceptable E7195-278 4'" 12010 Milk pCilL Cesium-137 9.87E+01 9.45E+01 1.04 Acceptable E7196-278 4'" 12010 Water pCilL Cesium-137 1.24E+02 1.20E+02 103 Acceptable E7195-278 4'" 12010 Milk oCilL Chromium-51 2.48E+02 2.34E+02 1.06 Acceptable E7196-278 4th 12010 Water pCilL Chromium-51 3.12E+02 2.97E+02 1,05 Acceptable E7195-278 4'" 12010 Milk pCilL Cobalt-58 7.02E+01 7.37E+01 0.95 Acceptable EL196-27J1. ! 4th ! 2010 Water I ('r.,,,... _,,A 963E+Oi 935E+01 1.03 Acceptable E719S-278 4"' 12010 Milk I pCi/L Ii r'. c,,, 1.77E+02 1.7iE+02 104 I ! ~I1~JI. I 4' 12010 Water oCilL I f'd,,,IUm ? ::!4!=+fl? I 2.11E+02 J*98 A I I I I E7193-278 4'" 12010 Cartridge pCi lodifle-131 5.97E+Ol 6.02E+Ol 0.99 Acceptable E719S-278 4'" 12010 Milk pC ill lodine-131 1.01E+02 9.41E+02 107 Acceptable E7196-278 4'" /2010 Water pC ill lodine-131 7.24E+01 6.44E+01 1.12 Acceptable I E7195-278 4'" /2010 Milk pC ill Iron-59 102E+02 9.11E+01 I I 1.12 AccBQtable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 30 of 51 I I Acceptance Sample Number Quarter I Year Sample Media Unit Analyte I Nuclide GEL Value I Known value Rangel Ratio Evaluation I E1195-218 4'" 12010 Milk pCilL Manganese-54 1.20E+02 1.19E+02 1.01 Acceptable E1196-218 4'" 12010 Water pCilL Manganese-54 1.10E+02 1.52E+02 1.12 Acceptable E1194-218 4'" 12010 Milk pCilL Strontium-89 1.62E+01 9.28E+01 0.82 Acceptable E1194-278 4'" 12010 Milk ~('ln I Strontium-90 1.30E+01 1.47E+01 0.88 Acceptable E1195-278 4'" 12010 Milk oCilL Zinc-65 2.37E+02 2.04E+02 1.16 Acceptable E1196-278 4'" 12010 Water pC ill Zinc-65 2.97E+02 2.59E+02 1.15 Acceptable
Laboratories p,o, Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 31 of 51 TABLE 3 2010 DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) RESULTS
SUMMARY
Acceptance I Quarter / Sample GEL Known Rangel Sample Number Year Media Unit Analyte 1 Nuclide Value value Ratio Evaluation MAPEP-10-MaS22 3'" 12010 Soil Bqlko Americium-241 0,07 0,00 ---- Acceptable MAPEP-10-MaS22 3 ,a 1201 0 Soil Bqlkg Cesium-134 744,67 733 513 - 953 Acceptable MAPEP-10-MaS22 3'°/2010 Soil Bqlko Ceslum-137 831,7 779 545 - 1013 Acceptable MAPEP-10-MaS22 3'" / 201 0 Soil Bqlkg Cobalt-57 536,0 522 365 -679 Acceptable MAPEP-10-MaS22 3'" / 201 0 Soil Bq/kq Cobalt-60 670,3 622 435 - 809 Acceptable MAPEP-10-MaS22 3'" 12010 Soil Bqlkg Iron-55 83,6 0,00 --- Acceptable MAPEP-10-MaS22 3'" 12010 Soil Bqlkg Manganese-54 940,7 849 594 -1104 Acceptable MAPEP-10-MaS22 3'" 12010 Soil Bqlkg Nickel-63 489 477 334 - 620 Acceptable MAPEP-10-MaS22 3'" / 201 0 Soil Bq/ko Plutonium-238 17,9 24 16.9 - 31.3 Acceptable MAPEP-10-MaS22 3"' 12010 Soil Bqlkg Plutonium-239/240 0.21 0,00 --- Acceptable MAPEP-10-MaS22 3,d/ 2010 Soil Bq!kg Potassium-40 638.7 559 391 - 727 Acceptable MAPEP-l0-MaS22 3"' 12010 Soil Bqlko Strontium-90 261,0 288 202 - 374 Acceptable MAPEP-10-MaS22 3"' 12010 Soil Bqlkg Technetium-99 -3.0 0,00 ---~- Acceptable MAPEP-10-MaS22 3"' 12010 Soil Bolko Uranium-234/233 65.27 60 42-78 Acceptable MAPEP-10-MaS22 3"'/2010 Soil Bqlkg Uranium-238 70,23 64 45 - 83 Acceptable MAPEP-10-MaS22 3"' 12010 Soil Bq!kg Zinc-65 -2,89 0,0 ---- Acceptable MAPEP-10-MaW22 3'" 12010 Water Bq/L Americium-241 1,0323 1.30 0.91 - 1,69 Acceptable MAPEP-10-MaW22 3"' 12010 Water BoIL Cesium-134 0,027 0.00 --- Acceptable MAPEP-10-MaW22 3'd/2010 Water BqlL Cesium-137 63.1 60,6 42.4 - 78.8 Acceptable MAPEP-10-MaW22 3 fd 12010 Water BoiL Cobalt-57 29.2 28.3 19.8 - 36,8 Acceptable MAPEP-10-MaW22 3"' 12010 Water Bq/L Cobalt-60 -0,021 0,00 -~-- Acceptable MAPEP-10-MaW22 3'" 12010 Water BoiL Hvdrooen-3 107 90.8 I 63.6-118.0 Acceptable MAPEP-10-MaW22 3 fO 12010 Water BoIL Iron-55 0,24 0,00 --- Acceptable MAPEP-10-MaW22 3'°/2010 Water Bq/L Manganese-54 28.83 26.9 18,8 - 35,0 Acceptable MAPEP-10-MaW22 3 ,d /2010 Water Bo/L Nickel-63 57,7 59,9 41.9-77.9 Acceptable
~
MAPEP-10-MaW22 i 3 12010 Water Sq/l 193 1,35 - 2.51 Not Acceptable I MAPEP-l0-MaW22 3 12010 Water Boll I 01. = 0.026 0.009 I --- Acceotable
'~r~ V-Mavv';" 3 12010 I Water BQ/L 0.00 I ---- Acceptable MAPEP-"'Uh\l\l?? 3 12010 Waler Bqll I 0,00 ---
MAPEP-10-MaW22 3 12010 I Water Bq!l Uranium-234/233 1.163 122 0,85 - 1.59 MAPEP-10-MaW22 I 3,°12010 Water BoiL Uranium-238 1,223 1,25 0,88 - 1.63 MAPEP-10-MaW22 3'" 12010 Water Bq/L Zinc-65 459 40,7 28,5 - 52,9 Acceptable MAPEP-10-GrW22 I3 ,0 12010 Water BoiL GrpssAlpha 0.559 0,676 >0.0-1.352 Acceptable MAPEP-10-GrW22 3 ,d 12010 Water Bq/L Gross Beta 3,110 3.09 1.55 - 4,64 Acceptable
m§J11 Laboratories p,o, Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 32 of 51 I Quarter I Sample GEL Known Acceptance Rangel I Sample Number Year Media Unit Analyte I Nuclide Value value Ratio Evaluation MAPEP-10*RdF22 3"' 12010 Filter uglsample Uranium-238 10,2 5.7 4,0 - 7,4 Not Acceptable MAPEP-1O-RdF22 3'"/2010 Filter uglsample Uranium-Total 10,2 5,7 4.0 - 7,4 Not Acceptable MAPEP-10-RdF22 3 ," 12010 Filter Bo/sample Americium-241 0,2637 0,146 0,102 - 0,190 Not Acceptable MAPEP-10-RdF22 3"'/2010 Filter Bolsample Cesium-134 4,323 2,13 1,49 - 2.77 Not Acceptable MAPEp*10-RdF22 3 ," 1201 Filter Bqlsample Cesium-137 3,070 153 1,07 -1,99 Not Acceptable MAPEP-10-RdF22 3'" 12010 Filter Bolsample Cobalt-57 0,0002 0,00 -- Acceptable MAPEP-10-RdF22 3 cd I 2010 Filter Bolsample Cobalt-60 5,187 2.473 1,731 - 3,215 Not Acceptable MAPEP-10-RdF22 3 ,d I 2010 Filter Bo/sample Manoanese-54 6.483 3,02 2,11 - 3,93 Not Acceptable MAPEP-10-RdF22 3"' I 2010 Filter Bg/sample Plutonium-238 0.010 0,0010 --- Acceptable 0,0582 - MAPEP-10-RdF22 3,d / 2010 Filter Bo/sample Plutonium-2391240 0.164 0.0832 0,1082 Not Acceptable MAPEP-10-RdF22 3"' I 2010 Filter Bolsample Strontium-90 -0,004 0,00 -- Acceptable MAPEP-10-RdF22 3"' I 2010 Filter Bolsample Uranium-234/233 0,137 0,068 0.048 - 0,088 Not Acceptable MAPEP-10-RdF22 3 cd 12010 Filter Bq/sample Uranium-238 0,147 0,071 0,050 - 0.092 Not Acceptable MAPEP-10-RdF22 3 cd 12010 Filter Bq/sample Zinc-65 -0.106 0,00 -- Acceptable MAPEP-10-GrF22 3 ,d I 2010 Filter Bolsample Gross Alpha 0.303 0.427 >0.0 - 0.854 Acceptable MAPE P-1 0-GrF22 3'" I 2010 Filter Bq/sample Gross Beta 1.433 1.29 0,65 - 1.94 Acceptable 0,0875 - MAPEP-10-RdV22 3'" 12010 Vegetation uglsampfe Uranium-235 0,090 0,1250 0.1625 Acceptable MAPEP-10-RdV22 3'" I 2010 Vegetation ug/sample Uranium-238 12.5 17.9 12.5 - 23,3 Not Acceptable MAPEP-10-RdV22 3 "'/2010 Vegetation uglsample Uranium-Total 13.9 18,0 12,6 - 23.4 Acceptable MAPEP-10-RdV22 3"' I 2010 V Bolsample Americium-241 0,179 0.225 0.158 - 0.293 Acceptable MAPEP-10-RdV22 3"' I 2010 Vegetation Bqlsample Cesium-134 3.098 4.39 3.07 - 5,71 Acceptable MAPEP-10-RdV22 3 cd /2010 Vegetation Bo/sample Cesium-137 2,185 3,06 2.14 - 3,98 Acceptable MAPEP-10-RdV22 3,dl2010 Vegetation Bolsample Cobalt-57 0,009 0,00 ---- Acceptable MAPE P-1 O-RdV22 3'" /2010 Veaetation Bolsample Cobalt-60 3.076 3.27 2,29 - 425 Acceptable MAPE P-1 0-RdV22 3'd 12010 Veaetation Bq/sample Manganese-54 0.004 0.00 '-- Acceptable MAPE P-1 0-RdV22 3 rd /2010 Vegetation Bolsample Plutonium-238 0.149 0.160 0.112 - 0,208 Acceptable MAPEP-10-RdV22 3 m /2010 Vegetation Bolsample Plutonium-2'<Q/?.dn 0.0026 0.0008 ---- Acceptable MAPEP-10-RdV22 3"'12010 Vegetation Bolsample Strontium-90 0,033 0.00 ! ---- Acceptable
-RdV22 3 12010 Veoetation Bo/sample Uranium-234/233 0.184 0.216 I 0.151 - 0.281 Acceptable MAPEP-l0-RdV22 3 12010 Vegetation Bo/sample Uranium-238 0.184 0.223 0156 - 0.290 Acceptable I MAPEP-l0-RdV22 I3 12010 n Zinc-aS 6.844 7.10 I 4,91 - 9.23 Acceptable I
Laboratories P.O. Box 30712. Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 33 of 51 TABLE 4 2010 ERA PROGRAM PERFORMANCE EVALUATION RESULTS
SUMMARY
Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analyte I Nuclide Value value Rangel Ratio Evaluation RAD- 80 1" 12010 Water pCi/l Barium-133 73.5 72.9 61.0 - 80.2 Acceptable RAD- 80 1" 12010 Water pCi/L Cesium-134 69.2 63.4 51.5 - 69.7 Acceptable RAD-80 1" 12010 Water pC ilL Cesium-137 118.0 120 108 - 134 Acceptable RAD- 80 1st 12010 Water pCi/l Cobalt-60 877 90 81 -101 Acceptable RAD- 80 1" I 2010 Water pCi/L Zinc-65 213.0 210 189-246 Acceptable st RAD - 80 1 12010 Water pCilL Gross Alpha 51.3 42.5 22.0 - 53.9 Acceptable st RAD- 80 1 12010 Water pCi/L Gross Beta 52.0 54.2 37.0 - 61.1 Acceptable I RAD - 80 1" 12010 Water pCi/L Radium-226 16.9 17.8 13.2 - 20.3 Acceptable RAD- 80 1" I 2010 Water pCi/L Radium-228 20.4 18.2 12.3 - 21.8 Acceptable RAD-80 1"/2010 Water pCi/L Uranium (Nat) 49.0 50.2 40.7 - 55.8 Acceptable RAD- 80 1" 12010 Water uQ/L Uranium (Nat) Mass 67.3 73.2 59.4 - 81.4 Acceptable RAD - 80 1" 12010 Water pCi/L Tritium 19200 18700 16400-20600 Acceptable RAD - 80 1" 12010 Water pCi/L Strontium-89 37.9 53.3 42.3 - 60.9 Not Acceptable RAD - 80 1" 12010 Water pCi/L Strontium-90 52.3 42.2 31.1-48.4 Not Acceptable RAD* 80 1st 12010 Water pCi/L lodine-131 30.5 28.2 23.5 - 33.1 Acceptable RAD- 82 3'" 12010 Water pCi/L Barium-133 112.0 89.1 75.0 - 98.0 Not Acceptable RAD-82 3'* 12010 Water pCilL Cesium-134 115.0 88.3 72.4 -97.1 Not Acceptable RAD- 82 3"'/2010 Water pCi/L Cesium-137 271 210 189 - 232 Not Acceptable RAD - 82 3"'/2010 Water pCi/L Cobalt-60 98.4 72.8 65.5 - 82.5 Not Acceptable RAD-82 3'" 12010 Water pCi/L Zinc-65 161 110 99.0 - 131 Not Acceptable RAD - 82 3'" 12010 Water pCi/L Gross Alpha 65.5 61.1 32.0 - 75.9 Acceptable RAD- 82 3'" 12010 Water pC ilL Gross Beta 56.7 56.4 38.6 - 63.6 Acceptable RAD-82 3'" 12010 Water Ci/L Radium-226 15.9 17.1 12.7 - 19.6 Acceptable RAD* 82 3"' 12010 Water ilL Radium-228 189 16.1 10.8 - 19.4 Acceptable a: : : RAD-82 3" 12010 Water pCi/L Uranium (Nat) 58.0 49.6 40.2 - 55.1 Not Acceptable
=+
RAD- 82 3 12010 Water uQ/L Uranium (Nat) Mass 89.1 72.3 58.7 - 80.4 Not Acceptable I I RAD* 82 Tritium i 18500 19800 i 17300 - 21700= = Acceptable I i RAD- 82
"',rn' ' 'm* 60.6 55.3 I
44.1*62.9 Acceptable ~:: 3 f 2010 Water Q'mn!lum.QO 47.1 32.8 24.0 - 38.0 Not Acceptable I 3 12010 Water pCifl looil1e-131 I 32.2 28.4 23.6 - 33.3 Acceptable I 7iON 3"'/2010 Waler pC ill Barium-133 86.9 92.9 783 - 102 Acceptable I 090710N 3 12010 Water peifL Cesium-134 93.8 79.4 65.0 - 87.3 090710N 3"' f2010 Water pCifL Cesium-137 55.5 54.6 49.1-62.9 Acceptable 090710N 3'" I 2010 Water pCilL Cobalt-60 120.0 117 105 - 131 Acceptable I 090710N 3 12010 Water pCifL Zinc*65 129 99.5 89.6 - 119 Not Acceptable
Laboratories P.O. Box30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 34 of 51 Sample Quarter I I Sample GEL Known I Acceptance Number Year I Media Unit Analyte 1 Nuclide I Value value Rangel Ratio Evaluation I 090710N 3'd 12010 I Water uQ/l Uranium (Nat) Mass 48.6 49.3 39.8 - 55.1 Acceptable RAD- 83 4~ 12010 Water pCi/l Strontium-89 65.3 68.5 55.8 - 76.7 Acceptable I RAD- 83 4" 12010 Water pCi/L Strontium-90 415 43 31.7 - 49.3 Acceptable 100510N 4" 12010 Water pCi/l Strontium-89 49.9 51.4 .9 Acceptable 100510N 4" 12010 Water pCi/l Strontium-90 35.4 41.3 30.4 - 47.5 Acceptable 112210H1 4" 12010 Water pCilL Barium-133 66.3 659 54.9 - 72.5 Acceptable 112210H1 4" 12010 Water pCill Cesium-134 71.6 71.6 58.4 - 78.8 Acceptable 112210H1 4" 12010 Water pCill Cesium-137 151 146 131 -163 Acceptable 112210H1 4" 12010 Water pCill Cobalt-60 90.2 84.5 76.0 - 95.3 Acceptable 112210H1 4" 12010 Water pCill Zinc-65 207 186 167 - 219 Acceptable 112210H2 4" 12010 Water pCi/l Plutonium-238 102.0 108 81.7-134 Acceptable 112210H2 4" 12010 Water pCill Plutonium-239 776 86.3 66.8 - 107 Acceptable 122810P 4" 12010 Water pCi/l Barium-133 70.9 68.9 57.5 - 75.8 Acceptable 122810P 4" 12010 Water pCill Cesium-134 43.0 43.2 34.5 - 47.5 Acceptable 122810P 4" 12010 Water pCi/l Cesium-137 122 123 111 -138 Acceptable 122810P 4" 12010 Water pCill Cobalt-60 58.7 53.4 48.1 - 61.3 Acceptable 122810P 4" 12010 Water pCill Zinc-65 116 102 91.8-122 Acceptable
Laboratories P.o. Box 30712, Charleston, SC 29417 2010 ANNUAL QUAUTY ASSURANCE REPORT Page 35 of 51 TABLE 5 2010 ERA PROGRAM (MRAO) PERFORMANCE EVALUATION RESULTS
SUMMARY
Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analyte 1 Nuclide Value value Rangel Ratio Evaluation nd MRAD-12 2 12010 Soil pGilkg Actinium-228 1570 1850 1190-2600 Acceptable MRAD-12 2"" 12010 Soil pCilkg Americium-241 1130 1500 896 -1930 Acceptable MRAD-12 2"" 12010 Soil pCilkQ Bismuth-212 1430 1640 430 - 2450 Acceptable MRAD-12 2"" 12010 Soil pCilkg Bismuth-214 1080 1410 865 - 2030 Acceptable nd MRAD-12 2 12010 Soil I pCilkg Cesium-134 3040 3110 2000 - 3740 Acceptable nd MRAD-12 2 12010 Soil pCilkg Cesium-137 4330 4440 3400 - 5770 Acceptable MRAD-12 2"d 12010 Soil pCilkg Cobalt-60 2120 2140 1560 - 2870 Acceptable nd MRAD-12 2 12010 Soil pCilkg Lead-212 1540 1520 980 - 2140 Acceptable MRAD-12 2"" 12010 Soil pCilk~ Lead-214 1300 1440 862 - 2140 Acceptable MRAD-12 2"" 12010 Soil pCilkg Manganese-54 < 22.9 0 ----- Acceptable MRAD-12 2"d 12010 Soil pCilkg Potassium-40 11100 10900 7900 - 14800 Acceptable nd MRAD-12 2 12010 Soil pCilk~ Thorium-234 1600 1610 511 - 3070 Acceptable nd MRAD-12 2 12010 Soil pCilkg Uranium-238 1600 1610 984 - 2040 Acceptable MRAD-12 2"" 12010 Soil pCilkg Zinc-65 2790 2470 1960 - 3310 Acceptable MRAD-12 2"" 12010 Soil pCilkg Strontium-90 7870 8180 2960 - 13300 Acceptable MRAD-12 2"" 12010 Soil pCilkg Uranium-234 < 1158 1620 1030 - 2010 Not Acceptable MRAD-12 2"" 12010 Soil pCilkg Uranium-238 908 1610 984 - 2040 Not Acceptable nd MRAD-12 2 12010 Soil uQIkQ Uranium-Total (mass) 2920 4820 2650 - 6060 Acceptable nd MRAD-12 2 12010 Soil pCilkg Strontium-90 7870 8180 2960 - 13300 Acceptable nd MRAD-12 2 12010 Soil pCilkg Americium-241 1120 1500 896 -1930 Acceptable MRAD-12 2"" 12010 Soil pCilkg Plutonium-238 1360 1330 761 -1870 Acceptable MRAD-12 2"" 12010 Soil pCilkg Plutonium-239 1220 1260 860 - 1670 Acceptable MRAD-12 2"" 12010 Soil pCilkg Uranium-234 1230 1620 1030 - 2010 Acceptable MRAD-12 2"" 12010 Soil pCilkg Uranium-238 1440 1610 984 - 2040 Acceptable nd MRAD-12 2 12010 Soil pCilkg Uranium-Total 2789 3300 1880 - 4460 Acceptable MRAD-12 2'" /2010 Soil uqlkg Uranium-Total (mass) 4350 4820 2650 - 6060 Acceptable MRAD-12 2"" 12010 Vegetation pCilkg Uranium-238 1604 1710 1200 - 2160 Acceptable MRAJ~:12: 2M i 2010 tjgikg ~Uranium-Tota! (massl 5270 512Q 35:20 6610 I MRAD-12 I 2""! 2010 do. pCilkg . "!lA 1 2410 3140 1790 4310 Acceptable MRAD:12 J 2"" i 2010 .Vegetation ~"rl"m_?.M 429 528 I 260 - 822 I Acceptable ! I
~eQetation MRAD-12 2""! 2010 pCilkg Plutonium-238 3090 3040 1640 - 4450 Acceptable MRAO-12 I 2"" 12010 pCilkg Plutonium-239 2830 2800 1140 - 3820 Acceptable MRAO-12 2"" 12010 Vegetation pCilkg Uranium-234 1680 1720 1180 - 2280 I AccElptable MRAD-12 2"" 12010 Vegetation pCilkg Uranium-238 I 1770 1710 1200 - 2160 I Acceptable
Labo ra to ri es P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 36 of 51 Sample I Quarter 1 Sample 1 GEL Known Acceptance Number Year Media Unit Analyte 1 Nuclide Value value Rangel Ratio Evaluation MRAD-12 2:'d 12010 Vegetation pCilkg Uranium*Total (mass) 5290 5120 3520-6610 Acceptable nd MRAD-12 2 12010 Vegetation pCilkg Americium-241 3600 3140 *. 1790-4310 Acceptable MRAD-12 2:" 12010 Vegetation pCilkg Cesium-134 1750 1670 956 - 2310 Acceptable MRAD-12 2'" 12010 Veqetation pCilkg Cesium-137 1550 1470 1080 - 2040 Acceptable MRAD-12 2:'d 12010 Vegetation pCilkg Cobalt-60 2100 1970 1330 - 2830 Acceptable nd MRAD-12 2 12010 Vegetation pCilkg Manganese-54 < 9.6 0.00 _ww_ Acceptable MRAD-12 2"" 12010 Vegetation pCilkg Potassium-40 40800 34900 25100 - 49400 Acceptable MRAD-12 2'" 12010 Vegetation pCilkg Uranium-238 < 1240 1710 1200-2160 Not Acceptable MRAD-12 2:'d 12010 Vegetation pCilkg Zinc-65 1630 1360 983 -1860 Acceptable MRAD-12 2'" 12010 Vegetation pCilkg Strontium-90 7880 9120 5100 - 12100 Acceptable MRAD-12 2'" 12010 Air Filter pCi/Filter Uranium-238 61.5 61.5 39.4 - 87.3 Acceptable I I MRAD-12 2:'d 12010 Air Filter ug/Filter Uranium-Total (mass) 183 184 114-264 Acceptable MRAD-12 2nd 12010 Air Filter pCi/Fitter Americium-241 52.7 60.0 35.1 - 82.3 Acceptable nd MRAD*12 2 12010 Air Filter pCi/Filter Plutonium-238 63.9 64.1 44.0*84.3 Acceptable MRAD-12 2'" 12010 Air Filter pCilFilter Plutonium-239 56.6 56.7 41.1-73.4 Acceptable MRAD-12 2'" 12010 Air Filter pCilFilter Uranium-234 68.8 62.1 39.1 - 92.0 Acceptable MRAD*12 2'" 12010 Air Filter pCilFilter Uranium-238 69.5 61.5 39.4 - 87.3 Acceptable MRAD-12 2'" 12010 Air Filter pCi/Filter Uranium-Total 141 126 64.4-200 Acceptable MRAD-12 2:'d 12010 Air Filter ug/Filter Uranium-Total (mass) 208 184 114*264 Acceptable 0d MRAD-12 2 12010 Air Filter pCi/Filter Americium-241 76 60 35.1 - 82.3 Acceptable MRAD-12 2nd 12010 Air Filter pCi/Filter Cesium-134 504 436 284-540 Acceptable nd MRAD-12 2 12010 Air Filter pCi/Filter Cesium-137 785 701 527 - 921 Acceptable MRAD-12 2'" 12010 Air Filter pCi/Filter Cobalt-60 591 523 405 - 653 Acceptable MRAD-12 2'" 12010 Air Filter pCilFilter Manganese-54 < 5.07 0.00 ----- Acceptable MRAD-12 2'" 12010 Air Filter pCilFilter Uranium-238 < 61.2 61.5 39.4 - 87.3 Acceptable MRAD*12 2:'d 12010 Air Filter pCi/Filter Zinc-65 462 389 269 - 539 Acceptable od MRAD-12 2 l2010 Air Filter pCilFilter Strontium-90 178 187 82.3 - 291 Acceptable nd MRAD-12 2 12010 Air Filter pCi/Filter Iron-55 375 359 158 - 559 Acceptable MRAD-12 2 nd 12010 Air Filter ug/Filter Uranium-Total (mass) 175 184 114-264 Acceptable I MRAD-12 I MRAD-12 I
;to 12010 2nd ! 2010 Air Filter Air Filter Q.Ci/Filter pCi/Filter Gross Alpha Gross Beta 68.2 72 79.6 70.4 41.3-120 43.4 - 103 i
I i A~~ Acc I
;=t; MRAiJ-12 12010 Uranium-238 679 I 60.9 46.5 - 75.5 I
MRAD-12 12010 I Uranium*Total (mass) 213 182 ! 143 - 225 I I I MRAD-12 12010 Americium-241 79.1 95.6 I 65.5 129 I MRAD-12 2nd 12010 Water pCi!L Plutonium-238 79.5 109 82.4 135 I Not Acceptable I MRAD-12 I 2'" 12010 Water pCilL Plutonium-239 i 103 105 81.2-130 I I Acceptable I MRAD-12 2'" 12010 Water pgl/L Uranium-234 62.4 61.4 46.3 - 79.2 i Acceptable MRAD*12 2'd12010 Waler pCilL Uranium-238 66.1 60.9 46.5 - 75.5 I Acceptable ! MRAD-12 ;td 12010 Waler pCi/L Uranium-Total 131.5 125 90.0 - 166 I Acceptable 1 I
@31J I Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 37 of 51 Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analyte I Nuclide Value value Rangel Ratio Evaluation MRAD-12 2"" 12010 Water pCi/L Americium-241 123 95.6 65.5 -129 Acceptable nd MRAD-12 2 i 2010 Water pCi/L Cesium-134 454 417 308 - 479 Acceptable MRAD-12 2nd 12010 Water pCilL Cesium-137 693 654 556 - 783 Acceptable MRAD-12 2nd 12010 Water pCi/L Cobalt-60 813 727 633 - 859 Acceptable MRAD-12 2nd 12010 Water pCilL Manganese-54 <7.7 0.00 --- Acceptable nd MRAD-12 2 12010 Water pC ilL Uranium-238 < 155 60.9 46.5 - 75.5 Not Acceptable MRAD-12 2"" 12010 Water , pCi/L Zinc-65 632 533 452 - 664 Acceptable MRAD-12 2"d 12010 Water pCilL Strontium-90 708 719 456 - 961 Acceptable MRAD-13 4th 12010 Soil pCilkg Actinium-228 1460 1830 1170 - 2580 Acceptable MRAD-13 4th 12010 Soil pCilkg Americium-241 845 1120 669 - 1440 Acceptable MRAD-13 4'" 12010 Soil pCilkg Bismuth-212 < 538 2070 543 - 3100 Not Acceptable MRAD-13 4"' 12010 Soil pCi/kg Bismuth-214 818 983 603 - 1410 Acceptable MRAD-13 4th 12010 Soil pCi/kg Cesium-134 2230 2240 1440 - 2700 Acceptable MRAD*13 4th 12010 Soil pCilkg Cesium-137 3400 3530 2700 - 4580 Acceptable MRAD-13 4'" 12010 Soil pCilkg Cobalt-60 4580 4780 3480 - 6420 Acceptable MRAD-13 4'" 12010 Soil pCilkg lead-212 1550 1640 1060 - 2310 Acceptable MRAD-13 4"' 12010 Soil pCilkg Lead-214 1030 969 580 - 1440 Acceptable MRAD-13 4'" 12010 Soil pCi/kg Manganese-54 < 38.0 0.00 -_ ...- Acceptable MRAD-13 4'" 12010 Soil pCilkg Potassium-40 10500 10700 7760 - 14500 Acceptable MRAD-13 4"' 12010 Soil pCilkg Thorium-234 1010 1340 425*2550 Acceptable MRAD-13 4'" 12010 Soil pCilkg Uranium-238 1010 1340 819*1700 Acceptable MRAD-13 4"' 12010 Soil pCi/kg Zinc-65 2420 2300 1820 - 3080 Acceptable MRAD-13 4'" 12010 Soil pCilkg Americium-241 928 1120 669 -1440 Acceptable MRAD-13 4'" 12010 Soil pCilkg Plutonium*238 1170 1280 733 - 1800 Acceptable MRAD-13 4'" 12010 Soil pCilkg Plutonium-239 1070 1180 805 - 1570 Acceptable MRAD-13 4th 12010 Soil pCi/kg Uranium-234 899 1360 862 - 1690 Acceptable MRAD-13 4" 12010 Soil pCi/kg Uranium-238 1080 1340 819 - 1700 Acceptable MRAD-13 4'" 12010 Soil pCilkg Uranium-Total 2027.4 2770 1580 - 3740 Acceptable MRAD-13 4th 12010 Soil uQ/kg Uranium-Total (mass) 3240 4040 2220 - 5080 Acceptable 4'" 12010 pCilkg Uranium-234 I r=!
Soil 1190 1360 862 - 1690 Acceptable
=1 4"' 12010 Soil pCilkg Uranium-238 903 1340 819 1700 S~~t Soil ugll<.g Uranium-Total 2093 2770 1580 - 3740 Soil pCiikg I 2685 I 4040 2220 - 5080 I MRA[)'13 I 4:. /
4' 12010 Soil Soil Q(;iikg pCilkg 1= J Uranium-234 Uranium-238 1110 1090 1360 1340 ~ Acceptable Acceptable I MRAD-13 MRAD-13 MRAD-13 MRAD-13 4"' 12010 4'" 12010 4'" 12010 4"' 12010 Soil Soil Soil Soil pCilkg uglkg ugikg pCilkg Uranium-Total Uranium-Total (mass) Uranium-Total (mass) Strontium-90 I i
;+;
10953 9270 1580 2220 - 5080 2220 - 5080 3350 - 15100 Acceptable Acceptable Acceptable Acceptable
ti1:t!l Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 38 of 51 Sample Quarter 1 Sample GEL Known Acceptance t Number Year Media Unit Analyte 1 Nuclide value Rangel Ratio Evaluation MRAD-13 MRAD-13 MRAD-13 4"' 12010 4" 12010 4"' 12010 Vegetation Vegetation Vegetation t:J pCi/kg Pfutonium-238 Plutonium-239 Uranium-234 3740 3590 3600 4740 4470 4010 2560 -6940 2770 - 6100 2750 - 5320 Acceptable Acceptable MRAD*13 4"' 12010 Vegetation pCi/kg Uranium-238 4000 3980 2800 - 5030 table MRAD-13 4" 12010 Vegetation pCi/kg Uranium-Total 7834 8180 5620- 10600 Acceptable MRAD-13 4"' 12010 Vegetation ug/kg Uranium-Total (mass) 12000 11900 8180*15400 Acceptable MRAD*13 4"' 12010 Veaetation pCi/ka Cesium*134 1200 1040 595*1440 Acceptable MRAD*13 4'" 12010 Vegetation pCi/kg Cesium-137 1420 1260 924-1750 Acceptable MRAD*13 4'" 12010 Vegetation pCi/ka Cobalt-60 1130 1010 683 - 1450 Acceptable MRAD-13 4'" 12010 VeQetation pCi/ka Manaanese-54 < 39.8 0.00 -- ..- Acceptable MRAD-13 4"' 12010 Vegetation pCi/kg Potassium-40 29000 22600 16200 - 32000 Acceptable MRAD*13 4'" /2010 Vegetation pCi/ka Zinc-65 1380 1210 874 - 1650 Acceptable MRAD*13 4'" 12010 Veaetation pCi/kQ Strontium-90 9800 7810 4360 - 10400 Acceptable MRAD*13 4'" 12010 Air Filter pCilFilter Uranium*234 73.5 71.8 45.2 -106 Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Uranium-238 75.5 71.2 45.6-101 Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Uranium-Total 149 146 74.6 - 232 Acceptable MRAD-13 4'" 12010 Air Filter uglFilter Uranium*Total (mass) 224.5 213 132 - 306 Acceptable MRAD-13 4"' 12010 Air Filter pCi/Filter Americium-241 70.1 74.1 43.3*102 Acceptable MRAD*13 4"' 12010 Air Filter pCilFilter Plutonium-238 70.8 72.9 50.0 - 95.8 Acceptable MRAD-13 4'" 12010 Air Filter pCilFilter Plutonium-239 65.6 69.6 50.5- 90.1 Acceptable MRAD*13 4'" 12010 Air Filter pCi/Filter Uranium-234 69.9 71.8 45.2 *106 Acceptable MRAD-13 4" 12010 Air Filter pCi/Filter Uranium*238 668 71.2 45.6 - 101 Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Uranium*Total 142 146 74.6 - 232 Acceptable MRAD-13 4th 12010 Air Filter ug/Filter Uranium-Total (mass) 201 213 132 - 306 Acceptable MRAD*13 4"'12010 Air Filter pCi/Filter Cesium-134 405 388 253 - 480 Acceptable MRAD*13 4'" 12010 Air Filter pCi/Filter Cesium*137 532 514 386 - 675 Acceptable MRAD-13 4th 12010 Air Filter pCilFilter Cobalt-60 531 479 371 - 598 Acceptable MRAD*13 4'" 12010 Air Filter pCilFilter Manganese-54 < 3.58 0.00 --- Acceptable MRAD-13 4'" 12010 Air Filter pCi/Filter Zinc-65 552 465 322- 644 Acceptable I MRAD-13 4'" 12010 Air Filter pCi/Fllter Strontium-90 80.2 159 70.0 - 247 Acceptable MRAD*13 4th /2010 Air Filter pCllFilter Iron-55 707 626 275 - 974 Acceptable i MRAD-13 4"'12010 , Air Filter uglFilter Uranium-Total (mass) 192 213 132-306 Acceptable MRAD-13 4" 12010 i Air Filler pCi/Filter Gross Alpha 74,2 52.3 I 27.1 - 78.7 MRAD-13 4' 12010 Air Filler pC,IFilter Gross Bela 556 52.7 ! 32.5 - 77.0 Acceptable MRAD-13 4th 12010 Water pCill Uranium-234 106 109 822 - 140 Acceptable MRAD-13 4th 12010 I Water pCi/L Uranium-238 107 108 82.5 134 Acceptable ~D.13 4" 12010 I Water pCilL Uranium-Total 218 221 159 - 294 Acceptable 0-13 4'" 12010 Water ug/L Uranium-Total (mass) 318 323 253 - 399 Acceptable MRAD-13 4'" 12010 Water pCi/L Americium*241 ,i 164 176 120 - 238 Acceptable
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 39 of 51 Sample Quarter f Sample I GEL Known Acceptance Number I Year Media Unit Analyte 1 Nuclide Value value Rangel Ratio Evaluation MRAD-13 4th 12010 Water pCill Plutonium-239 136 148 114 - 183 Acceptable MRAD-13 4th 12010 Water pCi/l Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4'" 12010 Water pCi/l Uranium-238 114 108 82.5 -134 Acceptable MRAD-13 4th 12010 Water pC;i/l Uranium-Total 226.8 221 159 - 294 Acceptable MRAD-13 4th 12010 Water ug/l Uranium-Total (mass) 342 323 253 - 399 Acceptable MRAD-13 4th 12010 Water pCi/l Americium-241 178 176 120 - 238 Acceptable MRAD-13 4'" 12010 Water pCi/l Cesium-134 495 492 363 - 565 Acceptable MRAD-13 4th 12010 Water pCi/l Cesium-137 620 625 531 - 749 Acceptable MRAD-13 4'" 12010 Water pCill Cobalt-60 732 714 622 - 844 Acceptable MRAD-13 4th 12010 Water pCill Manganese-54 <5 0.00 -_.- Acceptable MRAD-13 4th 12010 Water pCill Zinc-65 557 489 414-610 Acceptable MRAD-13 4'" 12010 Water pCill Strontium-90 817 921 585 - 1230 Acceptable MRAD-13 4'" 12010 Water pCi/l Uranium-234 104 109 82.2 - 140 Acceptable MRAD-13 4'" 12010 Water pCill Uranium-238 108 108 82.5 - 134 Acceptable MRAD*13 4'" 12010 Water pCi/l Uranium-Total 217 221 159 - 294 Acceptable MRAD*13 4'" 12010 Water ug/l Uranium-Total (mass) 321 323 253 - 399 Acceptable MRAD-13 4'" 12010 Water pCi/l Iron-55 1220 825 480-1100 Acceptable MRAD-13 4'" 12010 Water pCi/l Gross Alpha 145 146 64.8 - 216 Acceptable MRAD-13 4'" 12010 Water pCi/l Gross Beta 171 143 83.6 - 210 Acceptable MRAD-13 4'" 12010 Water pCill Tritium 20900 21600 14100 - 31900 Acceptable
t1#j1J Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 40 of 51 TABLE 6 2010 NEW YORK STATE DEPARTMENT OF HEALTH ENVIRONMENTAL LABORATORY APPROVAL PROGRAM (NYSDOH ELAP) PROFICIENCY TEST RESULTS
SUMMARY
f Sample Number I Quarter 1 Sample GEL Known Acceptance Year Media Unit Analyte 1 Nuclide Value value Rangel Ratio Evaluation NY-3323263 ;td 12010 Water p.CilL Gross Alpha 33.0 26.8 15.0 - 38.6 Acceptable NY-3323263 ;td 12010 Water pCi/L Gross Beta 64.6 54.0 41.3-66.7 Acceptable NY-3323262 2'" 12010 Water pCilL Cesium-134 14.8 14.0 10.7 -173 Acceptable NY-3323262 2'" 12010 Water pCilL Barium-133 27.8 25.6 20.6 - 30.5 Acceptable NY-3323262 2'" 12010 Water pCi/L Zinc-65 146 139 121 -156 Acceptable NY-3323262 2'" 12010 Water pCilL Cobalt-60 98.3 99.5 90.3 - 109 Acceptable NY-3323262 2'" 12010 Water pCi/L Cesium-137 124 123 112-134 Acceptable NY-3323264 2'" 12010 Water pCilL IOOine-131 23,4 26,4 21.9 - 31.0 Acceptable NY-3323264 2'" 12010 Water pC ill IOOine-131 26.8 26,4 21.9 - 31.0 Acceptable NY-3323261 2'" 12010 Water pCi/L Strontium-89 46.7 41.9 33,4 - 50,4 Acceptable NY-3323261 2'" 12010 Water pCilL Strontium-90 33.9 34.8 27.1 - 42.5 Acceptable NY-3323266 2'" 12010 Water pCilL Tritium 9610 9490 8390 -10600 Acceptable NY-3323265 2'" 1 2010 Water pCi/L Radium-226 12.1 13.2 10,4 - 16.0 Acceptable NY-3323265 2'" 12010 Water pCilL Radium-228 9.90 8.91 6.08 - 11.7 Acceptable NY-3323265 l'" 1 2010 Water pCilL Uranium (activity) 48.81 44.7 37.9 - 51,4 Acceptable NY-3373763 4'" 12010 Water pCilL Gross Alpha 32.8 41.6 24.3 - 58.9 Acceptable NY-3373763 4'" 12010 Water pCilL Gross Beta 29.3 27.5 18.3 - 36.7 Acceptable NY-3373762 4'" 12010 Water pC ill Cesium-134 51.0 42.0 35.8-49.2 Not Acceptable NY-3373762 4'" 12010 Water pCilL Cesium-137 29.3 27.3 22,4 - 32.1 Acceptable NY-3373762 4'" 12010 Water pCilL Cobalt*60 13.6 13.2 9.72*16.7 Acceptable NY-3373762 4"' 12010 Water pCilL Zinc-65 134 122 104 - 138 Acceptable NY-3373762 4"' 12010 Water p~ilL Barium-133 50.5 50.9 43.3-59,4 Acceptable NY-3373764 4th 12010 Water pCilL IOOine-131 13,4 18.2 14.7 - 21.7 Not Acceptable NY-3373764 4th 12010 Water pCVL IOOine-131 13.5 18.2 14.7 - 21.7 Not Acceptable NY-3373761 ! 4'" 12010 Water pCilL Strontium*89 47.8 61.3 51.3-71,4 Not AcceQtable NY-3373761 4'" 12010 Water pGilL Strontium-90 12.0 14.9 110 - 18.8 Acceptable NY-3373766 4" 12010 Water pCill Tritium 14400 15300 13500 - 17000 Acceptable i NY.3373765 4'" 12010 Water ~i/L Radium-226 13.2 10.6 8.30 - 12.9 Not Acceptable i NY -337 3765 4'" 12010 Waler pQilL I R",,,h un. ??A 651 607 i. 3.91 -822 Acceptable NY-3373765 4" 12010 Waler pCill I Uranium (activity) 11.5 16.0 13.2 - 18.7 Acceptable
[I 3II Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 41 of 51 FIGURE 1 COBALT-60 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Cobalt-60 Performance Evaluation Results and % Bias 150.0 , - - - - - - - - - - - - - - - - - - - - - - - - - - - - , 130.0 110.0 90.0
- __ Co-60 70.0 II)
Lower Control ell 50.0 Limit
.:::5! 30.0 Upper Control Limit 10.0
-10.0
-----~----- --~-------~~---~>>
-30.0
-50.0 ' - - - - - - - - - - - - - - - . . ; . . . . . - - " - - - - - - - - - - - - '
2010 Analytical Date
til ¥J , Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 42 of 51 FIGURE 2 CESIUM-137 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Cesium-137 Performance Evaluation Results and % Bias 100.0 80.0 60.0 .. Cs-137 1/1
.!1! 40.0 Lower Control aJ Limit ~
20.0 Upper Control Limit 0.0
-20.0
-40.0 2010 Analytical Date
Laboratories p,o, Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 43 of 51 FIGURE 3 TRITIUM PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Tritium Performance Evaluation Results and % Bias 50,0 r----------------------------, 30,0
.-,-, H-3 10,0
.m1/1 Lower Control Limit a::I 0~ Upper Control
-10,0 Limit
-300
-50,0 '--_ _ _-"-_ _'---_ _ _ _ _ _ _--'-_ _ _ _ _ _ _ _ _ _ _ _ ~ - - - I 2010 Analytical Date
tt#lll Laboratories L P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 44 of 51 FIGURE 4 STRONTIUM-gO PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Strontium-gO Performance Evaluation Results and % Bias 00,0 ~--------------------------------------------------, 40.0 20.0 __ Sr-gO II) Lower Control
.!l!
Ql o. 0 f-.,....-~--r--~...4---+--~---'........;..,--.~-_-----..f.- __-~"--~~~'----I Limit
,";f!. Upper Control Limit
-20.0
-40.0
-60.0 L -_ _ _ _ _ ~ _ _ _.......;.._ _ _ _ _ _ _....:;..._ _ _ _'___ _"'_____J 2010 Analytical Date
[I #I II Laboratories L P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 45 of 51 FIGURE 5 GROSS ALPHA PERFORMANCE EVALUA TION RESULTS AND % BIAS 2010 Gross Alpha Performance Evaluation Results and % Bias 100.0 80.0 60,0 40,0
- Gross Alpha 20,0 1/1 co Lower Control in 0,0 Limit
~0 Upper Control
-20,0 Limit
-40.0
-60,0
-60,0
-100,0 2010 Analytical Date
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 46 of 51 FIGURE 6 GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Gross Beta Performance Evaluation Results and % Bias 100.0 80.0 60,0 40.0
.. ' Gross Beta 20.0 1/1
.m 0.0 Lower Control Limit CO
~
-20,0 Upper Control Limit
-40,0
-60,0
-80.0
-100,0 2010 Analytical Date
[I 311 Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 47 of 51 FIGURE 7 IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 lodine-131 Performance Evaluation Results and % Bias 40.0 20.0 t/)
.!9 -200 Lower Control co Limit Upper Control
-40.0 Limit
-60.0
-80.0
-100.0 '---_ _ -'-_~ ______________ _c;.~ _ _ _ ___'___1 2010 Analytical Date
Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 48 of 51 TABLE 7 GEL 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) INTRA-LABORATORY DATA
SUMMARY
' BIAS AND PRECISION BY MATRIX Bias Criteria (+1- 25%) Precision Criteria (% RPO ) laboratory Control Sample Duplicate 2010 (lCS) (DU? or lCSD) WITHIN OUTSIDe WITHIN' OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA Air Particulate Gross Alpha/Beta 325 0 326 0 Americium-241 16 0 16 0 lodine-131 247 0 249 0 Gamma 23 0 23 0 Strontium-90 15 0 15 0 Air Cartrida8 , " " lodine-131 11 0 11 0 MUk ' ,':, :' .. Gamma 63 0 64 0 lodine-131 61 0 61 0 Strontium-90 33 0 34 0 Solid :,' " .. Gamma 27 0 29 0 Carbon-14 2 0 2 0 Iron-55 3 0 3 0 Nicke/-63 3 0 3 0 Strontium-90 11 0 11 0 Tissue " Gamma 38 0 36 0 Strontium-90 3 0 3 0 Vegetation " " Gamma (Including Iodine) 59 0 61 0 Strontium-90 3 0 3 0 Water " Carbon-14 2 0 2 0 Gross Alpha/Beta 98 0 99 0 Gamma 177 0 170 0 lodine-131 46 0 47 0 Iron-55 33 0 33 0 Nickei-63 35 , 0 : 35 0 Strontiul11~90 , 80 0 81 0 Tritium I 176 0 174 0 Total: 1590 0 I 1591 0 Note ,The RPD must be 20 percent or less, if both samples are greater than 5 times the MDe, both results are less than 5 times MOe, then the RPO must be equal to or less than 100%. If one result is above the MOe and the other is below the MOe, then the RPO can be calculated using the MOe for the result of the one below the MOe. The RPO must be 100% or less. In the situation where both results are above the MOe but one times the MOe and the other is less than 5 times the MOe, the RPO must be less than or are below MOe, then the limits on % RPD are not
Laboratories LLC P.O . Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 49 of 51 TABLE 8 GEL 2010 RADIOLOGICAL INTRA-LABORATORY DATA
SUMMARY
- BIAS AND PRECISION BY MATRIX lCS OUP lCS DUP LCS DUP LCS OUP ANAlYSIS I STRUMENT FILTER FILTER SWIPE SWIPE SOlID SOUD OL OIl Amerldum-241 Alpha Spec 2 2 47 38 485 477 13 12 Amerldum-243 2 2 1 0 S3 50 2 2 ClIfbon*'. lJquld SdnUlatlon .. 3 l8 32 98 99 9 9 Gamma (lQI1g list of isotopes.) Gamma Spec 283 272 47 42 770 792 27 27 Gross A iphaJBeta Gas Flow III 135 20 18 20 18 42 42 lodin&-129 Gamma SjIIJC 9 9 lodine*131 Gamma Spec 6 4 0 0 0 0 o o Iron-55 J.lguid sdnabuon 8 8 Alpha Spec and Isotopic Plutonium Liquid Scintillation 212 186 82 66 687 683 12 11 Isotopic Strontium Gas Flow 165 136 41 34 365 387 Isotopic Thorium Alpha Spec 82 59 0 0 371 372 o o Alpha Spec and ICP*
Isotopic Uranium MS 137 112 13 10 713 697 24 24 Lead-210 Gas Flow 44 26 o o 33 o 0 Nickel-59 Gamma S!l8c 65 60 28 22 7 7 Nicke1-63 Liquid Scintillation 95 89 39 30 75 74 8 8 Neptunj um-237 Alpha Spec 61 59 32 23 107 107 10 9 POlonium-210 Alpha Spec 18 6 o o 5 8 o 0 Promethiym-137 Liquid Scintillation 8 5 o o 12 11 o 0 Radium-226 Lucas Cell 44 31 o o 167 175 o 0 Radium-228 Gas Flow 29 25 o o 129 124 o 0 Technetium-99 Uquld Sdntillation 87 75 32 24 142 145 12 12 Tritium liquid SondUabon 90 76 42 24 19 19 lCS OUP LCS OUP LCS DUP lCS OUP MlSC MlSC ~ MISe SLUDGE SLUDGE SOUD SOUD UQUJD LIQUID UOUID LIQUID Americium-241 4 4 231 220 22 19 383 Americium-243 Alpha Spec 21 21 5 4 12 11 Carbon-14 5 5 110 108 33 218 175 Gamma (long list of isotopes) Gamma Spec 17 18 280 256 72 68 747 820 Gross AlphalBeta Gas Flow 27 27 112 109 87 80 1189 1180 lodine-129 Gamma 5pGc 88 88 21 21 162 lodine-131 Ga mma~_ o o o o o o 11 14 Iron-55 liquid Scin~n.'on 3 3 74 72 .2 43 123 103 Alpha Spec or Liquid Isotopic Plutonium Scintillation 7 7 143 137 n 70 108 95 Isotopic Strontium Gas Flow 13 13 61 60 80 76 16 12 Isotopic Thorium Alpha Spec 13 13 145 132 8 8 289 359 Isotopic Uranium Alpha Spec 24 24 102 87 39 36 640 557 Lead-210 Gas Flow o o o o o o 114 108 Nickel-59 Gamma Spec o o 68 66 9 9 76 63 N icket~3 Liquid Scintillatio n 5 5 74 72 50 51 172 143 Neptunium-237 Alpha Spec 3 3 o o 16 15 193 168 Polonium-210 Alpha Spec o o o o 3 3 Promethium-137 Liquid Scintillation 5 5 3 3 6 2 Radium-226 Lucas Cell 2 2 25 25 5 5 502 505 Radium-228 Gas Flow o o 27 28 432 426 T echnetium-99 Liquid Scintillation 15 15 179 175 39 40 41 41 Tritium liquid Scintillation 9 9 125 122 8 8 898 824
[lall Laboratories P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 50 of 51 TABLE 9 GEL 2010 CORRECTIVE ACTION
SUMMARY
GEL CORRECTIVE STATUS: ACTION IDENTIFICATION OPENI ISSUE Cause and Disposition CLOSED CARR 110209-542 OPEN Eckert & Ziegler Analytics Monitoring in progress Fe-59 Failure in Milk CARR 100617 -496 CLOSED MAPEP Series 22 PT The ICP-MS analysis of Uranium-235 Failures and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process. The failure for Plutonium-238 was attributed to a data reviewer's error and lack of attention to detail to the region of interest that was not included in the data result. Approximately 400 additional counts should have been included. All analysts have been retrained on attention to detail of the ROI. For the remaining isotopic failures, the error was attributed to analyst error and failure to follow the instructions from the PT provider. CARR 100617 -497 CLOSED MRAD 12 PT Failures The ICP-MS analysis of Uranium-235 and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process. For Uranium-238 in vegetation, air and water, the failure was attributed to method by I "1-" ,:",<.,ul-' y. be performed a analysis method. CLOSED MRAD PT Failures The failure for Bismuth-212 was attributed to a reporting error. The actual result (1660 pCi/kg) was within the acceptance range. The failure of Iron-55 was attributed to matrix interference. An additional recount with a smaller aliquot and fresh reagent rinses removed the interferant.
@§lIi Laboratories P,O. Box 30712. Charleston. SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 51 of 51 CARR100318-487 CLOSED I RAD-80 PT Failures The Gross Alpha failure was attributed II I to a concentrated iron carrier. The . I Strontium-89 and Strontium-90 failures were attributed to the associated weights of the carriers utilized during the preparation and analysis. CARR100907-512 CLOSED RAD-82 PT Failures Failures of the Gamma Emitters and the Naturals (Uranium) were attributed to analyst error and failure to follow the instructions from the PT provider. The failure of Strontium-89 and Strontium-90 was attributed to analyst error while diluting the sample. All analysts were retrained to the proper processes. CARR101203-525 CLOSED NY-337 PT Failures For Cesium-134, lodine-131, Strontium-89 and Strontium-90, and Radium-226. the failures could not be determined. The laboratory continues to monitor results of internal quality control samples.
TABLE 10 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED E-LAB INTERNAL CRITERIA JANUARY - DECEMBER 2010(1), (2) Panasonic 84 100 100 I Environmental (1)This table summarizes results of tests conducted by E-LAB and the Third-party tester. (2)Environmental dosimeter results are free in air. TABLE 11
SUMMARY
OF THIRD PARTY DOSIMETER TESTING JANUARY - DECEMBER 2010(1), (2) (1)Performance criteria are the same as the internal criteria. (2)Results are expressed as the delivered exposure for environmental TLD. ANSI HPS N13.29-1995 (Draft) Category II, High energy photons (Cs-137 or Co-60). TABLE 12 PERCENTAGE OF MEAN DOSIMETER ANALYSES (N=6) WHICH PASSED TOLERANCE CRITERIA JANUARY - DECEMBER 2010(1), (2) the mrn_m*H'\f tester. FIAOMINICORRESIEL 138-10 27}}