Text

Lr Hearing - Documents Sent to Nmfs.Remp 2010
	ML11293A347
Person / Time
Site:	Indian Point
Issue date:	09/23/2011
From:	; - No Known Affiliation
To:	; Division of License Renewal
References
	Download: ML11293A347 (2)
	v • d • e

IPRenewal NPEmails From: ncunningham@goodwinprocter.com Sent: Friday, September 23, 2011 10:33 PM To: Turk, Sherwin; Stuyvenberg, Andrew

Subject:

Documents sent to NMFS.REMP 2010

Dear Messrs. Turk and Stuyvenberg:

I attach a zip file with the documents from Elise Zoli and BJ Trach that did not go through by email earlier.

Please do not hesitate to let me know if you have any issues opening these documents.

Nancy Cunnigham, Senior Litigation Paralegal, Goodwin Procter File(s) will be available for download until 13 October 2011:

File: REMP 2010.zip, 10,366.37 KB You have received attachment link(s) within this email sent via the Goodwin Procter Secure File Transfer System. To retrieve the attachment(s), please click on the link(s).

IRS CIRCULAR 230 DISCLOSURE: To ensure compliance with requirements imposed by the IRS, we inform you that any U.S. tax advice contained in this communication (including any attachments) is not intended or written to be used, and cannot be used, for the purpose of (i) avoiding penalties under the Internal Revenue Code or (ii) promoting, marketing or recommending to another party any transaction or matter addressed herein.

This message is intended only for the designated recipient(s). It may contain confidential or proprietary information and may be subject to the attorney-client privilege or other confidentiality protections. If you are not a designated recipient, you may not review, copy or distribute this message. If you receive this in error, please notify the sender by reply e-mail and delete this message. Thank you.

1

Hearing Identifier: IndianPointUnits2and3NonPublic_EX Email Number: 2987 Mail Envelope Properties (ls09rd.w5ueul)

Subject:

Documents sent to NMFS.REMP 2010 Sent Date: 9/23/2011 10:33:14 PM Received Date: 9/23/2011 10:33:19 PM From: ncunningham@goodwinprocter.com Created By: ncunningham@goodwinprocter.com Recipients:

"Turk, Sherwin" <Sherwin.Turk@nrc.gov>

Tracking Status: None "Stuyvenberg, Andrew" <Andrew.Stuyvenberg@nrc.gov>

Tracking Status: None Post Office: sft.goodwinprocter.com Files Size Date & Time MESSAGE 1818 9/23/2011 10:33:19 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Enteray Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB

%-Entergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Patric W Conroy Director, Nuclear Safety Assurance NL-1 1-038 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 (IPEC) 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 617 cc: next page

(~LkA

NL-1 1-038 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 Precipitation 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 3.4.1 Lower Limit of Detection and Critical Level 3-6 3.4.2 Determination of Mean and Propagated Error 3-8 3.4.3 Table Statistics 3-8 i

TABLE OF CONTENTS (continued)

Page 4.0 RESULTS 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 REQUIREMENTS A-1 B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B-1 RESULTS

SUMMARY

C. HISTORICAL TRENDS C-1 D. INTERLABORATORY COMPARISON PROGRAM D-1

" 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-1i1 C-6 Broad Leaf Vegetation - Cs-137, 2000 to 2010 C-13 C-7 Fish and Invertebrates - Cs-137, 2000 to 2010 C-1 5 iii

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 B-1 Summary of Sampling Deviations, 2010 B-3 B-Ia 2010 Air Sampling Deviations B-4 B-lb 2010 TLD Deviations B-4 B-Ic 2010 Other Media Deviations B-4 B-2 ODCM Annual Summary, 2010 B-5 B-3 2010 Direct Radiation, Quarterly Data B-9 B-4 Direct Radiation, 2000 through 2010 Data B-10 B-5 2010 Direct Radiation, Inner and Outer Rings B-11 B-6 Environmental Airborne Particulate Samples - 2010 Gross Beta Activity B-12 B-7 Concentrations of Gamma Emitters in Quarterly Composites of Site Air Particulate Samples, 2010 B-14 B-8 Environmental Charcoal Cartridge Samples - 2010 1-131 Activity B-1 6 B-9 Concentrations of Gamma Emitters in Surface Water Samples, 2010 B-1 8 B-10 Concentrations of Tritium in Surface Water Samples, 2010 B-20 B-1 1 Concentrations of Gamma Emitters in Drinking Water Samples, 2010 B-21 B-12 Concentrations of Tritium in Drinking Water Samples, 2010 B-23 B-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2010 B-24 B-14 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples, 2010 B-26 iv

LIST OF TABLES (Continued)

TABLE TITLE Page B-15 Concentrations of Radionuclides in Fish Samples, 2010 B-39 B-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2010 B-43 B-17 Concentrations of Gamma Emitters in Bottom Sediment Samples, 2010 B-44 B-18 Concentrations of Radionuclides in Rainwater Samples, 2010 B-46 B-19 Concentrations of Gamma Emitters in Soil Samples, 2010 B-48 B-20 Concentrations of Radionuclides in Monitoring Well Samples, 2010 B-49 B-21 Land Use Census - Residence and Milch Animal Results, B-50 2010 B-22 Land Use Census, 2010 B-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 Broad Leaf Vegetation - Cs-1 37, 2000 to 2010 C-12 C-7 Fish and Invertebrates - Cs-137, 2000 to 2010 C-14 D-1 Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 Interlaboratory Comparison Program D-5 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.

During 2010, a total of 1166 samples were obtained out of a planned load of 1178 samples. Table B-1 presents a summary of the collected sampling results.

An investigation of groundwater contamination with tritium and other radionuclides 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-90 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-90 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 B-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.

To identify changes in activity, the environmental sampling schedule requires that analyses be conducted for specific environmental media 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 fish/invertebrate 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 measurements of radiation exposure (i.e., total integrated exposures in milli-roentgen, mR) for a given period. The area surrounding the Indian Point site is divided into 16 compass sectors. Each sector has two TLD 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 (AM) and seven indicator locations.

These indicator locations are at sampling stations 4 (Al), 5 (A4), 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown on Figures A-i, 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, Wal) 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 Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, sample station 7, sample designation Wbl) and New Croton Reservoir (6.3 Mi SE, sample station 8); see Figure A-

3. 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 (Wcl), 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 (Ic2) and 95 (Icl), 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 (Iblb) and the control location (upstream) is at Roseton, sampling station 23 (Wb2). 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 spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations (sampling stations 17 and 28) and one control location (84); see Figure A-3.

Samples of aquatic vegetation are obtained depending on sample 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 Lafarge (106.) Samples are analyzed for tritium, Sr-90, Ni-63 and by gamma spectroscopy.

3.3.13 Land Use Census 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 B-21 and B-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 to determine if a milk-sampling program needs to be conducted.

A residence census is also performed to identify the nearest residence(s) to the site in each of the 16 sectors surrounding Indian Point. See Table B-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 (L,), and estimation of the mean and associated propagated error.

3.4.1 Lower Limit of Detection (LLD) and Critical Level (Lc The LLD is the smallest concentration of radioactive material ina sample that will be detected with 95% probability with 5%probability of falsely concluding that a blank obser-ation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

2.71 1 '-3.29s * 'I -

LLD,- T where:

LLD = The lower limit of detection as defined above (as picocurie per unit mass or volume)

T = The sample countng time in minutes so = The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

T, = 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= A constant for the number of transformations per minute per unit of activity (normally, 2-22E+6 dpm per 1LCi)

Y The fractional radiochemical yield (-when applicable) 3-6

,= The radioactive decay constant for the particular radionuclide 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 Radiological Environmental Monitoring Program, REMP, uses an LLD formula that assumes equal background and sample count times, in accordance with the RECS.

When the above 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 vwere derived from the following two sources:

1) Currie, L.A. "Limits for Qualitative Detection of Quantitative Determination". (Anal. Chem.

40:586-593, 1968); and,

2) Mayer, Dauer "Application of Systematic Error Bounds to Detection Limits for Practical Counting".

(HP Journal 65(1): 89-91, 1993)

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance 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 radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides nomally present in the samples. Typical 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 detemlined to be within + one F-MHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

It should be recognized that the LLD is defined as an a orio (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 postenori problem, adecision level must be defined, which 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 (a: Type I error), and the converse, failing to decide that it is present when it is (b: Type It error). The maximum acceptable 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 L: to yield the decision, detected.

Le kas*(+Tf)'sf where:

k, is related to the standardized normal distribution and corresponds to a probability level of 1-a.

For instance, selection of a = 0.01 corresponds to a 99%/6 confidence level that activity is present.

When determining the Lc for different measurement processes, it is allowable to set a at less than or equal to 0.05 as long as the following condition is met:

To set a for Lc determination at less than 0.05, the equation for the LLD (which places a less than or equal to 0.05) should be employed to verify that the calculated LLD is less than or equal to the LLDs specified in the RECS. This calculation, ifnecessary, 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 Lc, 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 Exi X= i=1 N

where: Xi value of each individual observation N number of observations Z(ERRX)

PE = =

N where: ERRN = 1 sigma error of the individual analysis N = number of observations 3.4.3 Table Statistics 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 "<" 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 B-6 through B-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 "< L, " 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 Table lists the mean and range of all positive results obtained for each of the media sampled at ODCM indicator and control locations. Discussions of these results and their evaluations are provided below.

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., Be-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 sample). In bottom sediment there were five positive detections of Cs-1 37 (all at indicator stations or near to plant.) The two discharge canal samples are consistent with historical values.

A sample of aquatic vegetation at Lents Cove showed Cs-1 37 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 fish/invertebrate sample results for Sr-90 were inconclusive. As noted in the 2009 AREOR, 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.

Co-58 and Co-60 are activation/corrosion products also related to plant operations. They are produced by neutron activation in the reactor core. As 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 B-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 B-2 and all the TLD data are presented in Tables B-3, B-4 and B-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table B-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 B-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 B-4. Table B-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 results for these two rings of TLDs are provided in Table B-5. The annual average for the inner ring was 14.0 mR per standard quarter and also average for the outer ring was 14.3 mR per standard quarter.

The control location average for 2010 was 13.0 mR per standard 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 B-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 B-6, and the results of the gamma spectroscopy analyses of the quarterly composites of these samples are in Table B-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 pCi/m 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-1 37 concentrations in recent years.

The charcoal cartridge analytical results are presented in Table B-8.

"Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/mi3 ) in the charcoal cartridge samples, which is consistent with historical trends.

From the data, it can be seen that no airborne radioactivity attributable to the operation of Indian Point was detected in 2010.

4.3 Hudson River Water A summary of the radionuclides detected in the Hudson River water is contained in Table B-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 B-9 and B-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 B-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 B-11 and results of tritium analysis of quarterly composites are in Table B-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 B-2. Table B-13 contains the results of the gamma spectroscopic and strontium-90 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 pCi/kg (dry.)

An historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table C-5 and Figure C-5. Cs-137 has been and continues to be present in this media, both at indicator 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 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2010 samples are presented in Table B-14. Analyses of broad leaf vegetation samples revealed only one instance of Cs-1 37 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 B-2. Table B-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 A summary of the aquatic sample analysis results is presented in Table B-2. Table B-16 contains the results of the analysis of aquatic vegetation samples for 2010.

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

pCi/kg 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-1 34 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 pCi/kg.).

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 pCi/kg 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 in precipitation samples.

A review of historical data over the last 10 years indicates tritium had 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 B-

2. Table B-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 B-2. Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, and Sr-90 are given in Table B-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 B-21 and B-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 B-14, Table C-6 and Figure C-6.

4.14 Conclusion 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.

12. Eichholz, Geoffrey G., Environmental Aspects of Nuclear Power, Lewis Publishers, Inc., Chelsea, Michigan, 1985.

13. Kelly, J. J. (Ed.), Effluent and Environmental Radiation Surveillance, ASTM STP #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-Hill 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 al., 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 al., High Radiocesium Levels in Granite Outcrop Vegetation and Reductions Through Time, Health Physics Journal, 60(4), p. 533, April 1991.

22. McGee, E., et al., 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 al., The Counting Room: Special Edition, Radioactivity and Radiochemistry, Caretaker Publications, Atlanta, Georgia, 1994.

28. Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw Hill, 1969.

29. ENN-LI-102, Corrective Action Process

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-i, 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-I, there is an environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables B-21 and B-22 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SAMPLE .,

STATION DESIGNATION ,LOCATION DISTANCE SAMPLETYPES 3 DR8 Service Center Building Onsite - Direct Gamma 0.35 Mi (SSE) at 1580ire Gammat 4 Al Algonquin Gas Line Onsite - 0.28 Mi (SW) at Air Particulate Al 2340 Radioiodine A4 Air Particulate 5 A4 NYU Tower Onsite at 2080 - 0.88 Mi (SSW) Radioiodine DR1 0 Direct Gamma 7 Wbl Camp Field Reservoir 3.4 Mi (NE) at 510 Drinking Water

8. Croton Reservoir 6.3 Mi (SE) at 1240 Drinking Water 9 Wal Plant Inlet (Hudson River Intake)* Onsite - HR Water 0.16 Mi (W) at 273' RWae Wa2 Onsite -

nie-HWar HR Water 10 Wa2 Discharge Canal (Mixing Zone) 0* D0.3 Mi (WSW) at 2490 HR Bottom Sediment 14 DR7 Water Meter House OnsiteDirect Gamma 0.3 Mi (SE) at 1330

- - HR Aquatic Vegetation 17 ** iOf Verplanck 1.5 Mi (SSW) at 202.50 HR Shoreline Soil

- HR Bottom Sediment Cortlandt Yacht Club 20 DR38 (AKA Montrose Marina) 1.5 Mi (5) at 180° Direct Gamma

- Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton* 20.7 Mi (N) at 3570 Direct Gamma Ic3 Broad Leaf Vegetation

- Soil Ib2 Fish & Invertebrates 25 Ibl Downstream Downstream Fish & Invertebrates

- Air Particulate 27 ** Croton Point 6.36 Mi (SSE) at 156' Radioiodine DR41 Direct Gamma

- HR Shoreline Soil DR4 Direct Gamma 28 Lent's Cove 0.45 Mi (ENE) at 0690

- HR Bottom Sediment

- - HR Aquatic Vegetation

- Air Particulate 29 ** Grassy Point 3.37 Mi (SSW) at 1960 Radioiodine DR39 Direct Gamma

=Control location

= Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River RJS = Reuter Stokes A-2

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SAMPLE

' STATION DESIGNATION: i NLOCAION DISTANCE SA MPLE TYPES 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 0530 Direct Gamma 34 DR9 South East Corner of Site Onsite 0.52 - at 1790 Mi (5) Direct iet Gamma am 35 DR5 Broadway & Bleakley Avenue Onsite - Direct Gamma 0.37 Mi (E) at 0920 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 Direct Gamma

- Precipitation 44 ** Peekskill Gas Holder Bldg 1.84 Mi (NE) at 0520 Air Particulate

- Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 3470 HR Shoreline Soil Wcl HR Shoreline Soil 53 White Beach 0.92 Mi (SW) at 226H DR11 Direct Gamma 56 DR37 Verplanck - Broadway & 6th Street 1.25 Mi (SSW) at 202' Direct Gamma 57 DR1 Roa Hook 2 Mi (N) at 005° Direct Gamma 58 DR1 7 Route 9D - Garrison 5.41 Mi (N) at 358' Direct Gamma 59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 0320 Direct Gamma 60 DR18 Gallows Hill Road & Sprout Brook 5.02 Mi (NNE) at 0290 Direct Gamma Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 0520 Direct Gamma 62 DR1 9 Westbrook Drive Direct Gamma 62 ____D___19__ (near the Community Center) 5.03 Mi (NE) at 0620 Lincoln Road - Cortlandt 64 DR20 (School Parking Lot) 4.6 Mi (ENE) at 0670 Direct Gamma 66 DR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 0830 Direct Gamma 67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 114' Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 1270 Direct Gamma 71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 1880 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 2030 Direct Gamma 73 DR27 Willow Grove Road & Captain Direct Gamma Faldermeyer Drive 4.97 Mi (SW) at 2260 74 DR1 2 West Shore Drive - South 1.59 Mi (WSW) at 2520 Direct Gamma 75 DR31 Palisades Parkway 4.65 Mi (NW) at 2250 Direct Gamma 76 DR1 3 West Shore Drive - North 1.21 Mi (W) at 2760 Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 272' Direct Gamma 78 DR14 Rt. 9W across from RJS #14 1.2 Mi (WNW) at 2950 Direct Gamma

= Control location

- = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River RJS = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS SAMPLING SAMPLE ,C, D* SAMPLE TYPES

-STATION DESIGNATION LOCATIONISTANCE ___S _LE___

79 DR30 Anthony Wayne Park 4.57 Mi (WNW) at 2960 Direct Gamma 80 DR15 Route 9W South of Ayers Road 1.02 Mi (NW) at 317° Direct Gamma 81 DR28 Palisades Pkwy - Lake Welch Exit 4.96 Mi (WSW) at 310' Direct Gamma 82 DR1 6 Ayers Road 1.01 Mi (NNW) at 3340 Direct Gamma 83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 3390 Direct Gamma

- HR Aquatic Vegetation 84 ** Cold Spring

10.88 Mi (N) at 3560 HR Shoreline Soil

- HR Bottom Sediment 88 DR6 Reuter Stokes Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma 89 DR35 Highland Ave & Sprout Brook Road 2.89 Mi (NNE) at 0250 Direct Gamma 89_DR35 _ (near rock cut) 90 DR3 Charles Point 0.88 Mi (NE) at 0470 Direct Gamma 92 DR24 Warren Road - Cortlandt 3.84 Mi (SSE) at 149' Direct Gamma A2 Air Particulate 94 A2 IPEC Training Center Onsite- 0.39 Mi (S) at Radioiodine Ic2 1930 Broad Leaf Vegetation

- Soil A3 Air Particulate A3 Meteorological Onsite - Radioiodine Icl 0.46 Mi (SSW) at 2080 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 ODCM HR = Hudson River R/S = Reuter Stokes A-4

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point N

Peekskill Rockland County Westchester County 1 mile Key:

lco - Broadleaf Vegetatlion A - Waterborne.: Surface (HR) Wait - HR Shoreline Soil VNc#

O- Direct Radiation Sample Location DR# Ibi - Fish arid Invertebrates O - Airborne Particulate and Radiojodine A# (where available dowrnslream)

A-5

FIGURE A-2 SAMPLING LOCATIONS Greater than Two Miles from Indian Point Roseton (20 7 in. 11) N E] (D l10 U~pstream- 12b2 Orange County Putnam County

0 Westchester County 0

5 miles Rockland County Key: 0 Direct Radiatiori Sartiple Location DRO lo3 - Stoadleaf Vegetat~on

[3 Airborrne Sampling Location A# o - Waterbome.- Drinking Vb

< Hudsorn

-0p River Shoreline Sail Wc# 1br2 - Ftsh and Inivertebrates (where available urtstrearn)

A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N

Poseton (20.7 mi. N), 23 - p *

Orange County Putnam County Cold Spring (10 88 mi, N) 84 v < 41' Bear Mountain Bridge 10.: 40 Westchester 17: V County 106 2910 Rockland County 27T 0 8: dw 5 miles Key: i - Air Particulate & Radionodine - HR Shoreline Soil V - Aquatic Vegetation * -Soil 4W - HR Bottom Sediment GW. Monitoring Well, SW of p - Precipitation Site Boundary

,1- Drinking Water A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLES FOOD SOIL or RADIONUCLIDE WATER AIRBORNE FISH MILK PRODUCTS SEDIMENT ANALYSISANALYSIS (pCIIL)

(pCi/L) GARTIUESAT GASES (pCi/m°)R wet),

wet) (pCi/L) (pCiikg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2.000 (d)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Ni-63 () 30 100 Zn-65 30 260 Sr-90 (f) 1 5 5000 Zr-95 15 Nb-95 15 1-131 1 (d) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-1 37 18 0.06 150 18 80 180 Ba-140 15 15 La-1140 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 Specification D 5.1.

(b) Required detection capabilities for them~oluminescent 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 will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

It should be recognized that the LLD is defined as an a Enori (before the fact) limit representing the capability of a measurement system and not as an a ppsteriori (after the fact) limit for a particular measurement. Analyses shall be perfonrned in such a manner that the stated LLDs A11 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 factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to RECS D 5.1.

(d) These LIDs 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 l-131.

(e) These required lower limits of detection are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reportiuig 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 RADIONUCLIDE WATER AIRBORNE FISH MILK FOOD PARTIUCLATE OR PRODUCTS ANALYSIS (pCi/L) GASES (pCilm (pCiikg, wet) (pCi/L) (pCiikg, wet) 20,0001 Mn-54 1,000 30,000 Fe-5g 400 10,000 Co-ee 1,013G0 30,200 Co-eo 300 10,000 Ni-e,3 3-300 120 Zn-300 20.000 Sr-90 -"* 9.40 Zr-05 400 Nb4-5 440 1-131 2 " 9 3 100 Cs-134 30 10 1.C00 80 1,000 Cs- 137 50 20 2.0X0 70 2.000 Ba-140 230 300 La- 140 200 300 Values provided are for drinking water pathways. If no drinking water pathway exists, higher values are allowed, as follows:

H-3 30,000 pCL/L (This is a 40 CFR 141 value) 12 pCVL 1-131 20 pCiL These reporting levels are associated only with the REMP requirements. The Radiological Ground Water Monitoring Program may involve unique reporting level criteria, independent of the REMP. anld defined in station procedures.

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 40:

A-IO

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B,1 2010 Annual Radiological Environmental Monitoring Program Summary The results of the 2010 radiological environmental sampling program are presented in Tables B-2 through B-20. Table B-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 Branch Technical Position to Regulatory Guide 4.8 (Reference 14). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-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; Be-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, Ba/La-140, Ce-141, Ce-144, Ra-226 and Ac/Th-228. Radiochemical analyses were performed for 1-131, Ni-63 and Sr-90 for specific media and locations as required in the ODCM.

B.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 B-21 and B-22, respectively. In lieu of identifying and sampling the nearest garden of greater than 50 M 2 , 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 B-14).

B.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 of the reasons for the deviations are provided in Table B-ia for air samples, B-i b for TLDs and B-ic for other environmental media.

B.4 Analytical Deviations 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-90 was inadequate for the required sensitivity. Accordingly, the vendor B-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 S. NUMBER OF SAMPLING REASON FOR MEDIA

- :. ::* ,:*,-**SAMPLES.,,:: DEVIATIONS*

SHEDULED ; ,::::: EFFICIENCY % DEVIATION

'i:: :--

MEDIA PARTICULATES IN AIR 416 98.8% See Table B-la CHARCOAL FILTER 416 98.8% See Table B-la TLD 164 99% See Table B-lb HUDSON RIVER WATER 32 97% See Table B-ic DRINKING WATER 32 100% N/A SHORELINE SOIL 10 100% N/A BROAD LEAF 58 100% N/A VEGETATION FISH & INVERTEBRATES 24 100% N/A AQUATIC VEGETATION 5 100% N/A HUDSON RIVER BOTTOM 8 100% N/A SEDIMENT SOIL 3 100% N/A PRECIPITATION 8 100% N/A GROUNDWATER 2 100% N/A SAMPLES TOTALS 1178 12 99.0%

TOTAL NUMBER OF SAMPLES COLLECTED = 1166

Samples not collected or unable to be analyzed.

B-3

TABLES B-1la!I B-lb / B-Ic TABLE B-la 2010 Air Sampling Deviations STATION WEEK PROBLEM I ACTIONS TO PREVENT RECURRENCE Grassy Point 2 Lost 145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months from power interruption Grassy Point 12 Lost 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months from power interruption Grassy Point 26 Lost 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months from power interruption Grassy Point 33 Lost 161 hours0.00186 days 0.0447 hours 2.662037e-4 weeks 6.12605e-5 months run time from power interruption Grassy Point 43 Lost 158 hours0.00183 days 0.0439 hours 2.612434e-4 weeks 6.0119e-5 months ; sample pump required replacement Algonquin 11 Lost 141 hours0.00163 days 0.0392 hours 2.331349e-4 weeks 5.36505e-5 months due to sampte 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 hours0.00141 days 0.0339 hours 2.017196e-4 weeks 4.6421e-5 months from GFCI trip Training Building 49 Filter media found mis-atigned when retrieved (bypassed)

Roseton 9 Lost 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months from trees falling on power lines Roseton 13 Lost 95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months ; GFCt found tripped Roseton 29 Lost 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months on integrator; sample was running at week's end Note: eight of thirteen could be analyzed; five coutd not be analyzed TABLE B-lb 2010 TLD Deviations

>STATION-, .. ,QUARTER. , PROBLEMI ACTiON .TO PREVENT RECURRENCE Lent's Cove 3rd TLD was removed from holder; raise installation height TABLE B-Ic 2010 Other Media Deviations TATIO < SAMPLE SCHEDU~LE PRqOBLEM/ ACTIONS TO PREVENT RECURRENCE'~

Hudson River Discharge Week 47 Surface Water; sample pump found de-energized, grab sample taken and pump re-energized B-4

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2010

~ > ~LOCATIO'N OF HIGHEST

TYPE AND TOTAL INDICATOR LOCATIONS: ANNUALOMEAN: NUMBER OF MEDIUM (UNITS) NUMBER OF LLD (b) LOCATIONS AND CONTROL NON-ROUTINE S~EE TABLE ANALYSIS DESIGNATION LOCATION: REOT PERFORMED MEAN (a) MEAN (a) MEAN (a)

__________ ________ _____RANGE , RANGE . RANGE _____

IO Palisades Parkway (Lake (mR / standard quarter) TLD Reads N/A 14.1 (159/160) / Welch Exit) 4.96 Mi 13.0 (4/4) /

B-R 163 10.3 -21.1 (WSW) at 310' DR28 11.8 -13.7 B-3 19.8 (4/4)117.3 - 21.1 AIR PARTICULATES #29 Grassy Point AND RADIOIODINE GB (411) 0.01 0.001- 0.03253 3.37 Mi (SSW) at 1960 0.002-0.027 0 0.013 (52/52) / 0.002-0.032 (pCi/m3 ) B-6, B-7, B-8 1-131 (411) 0.07 <Lc <Lc <Lc 0 GSA (32) 0.05 <Lc <Lc <Lc 0 Cs-1 34 GSA (32) 0.06 <Lc <Lc <Lc 0 Cs-1 37 SURFACE HUDSON 428(2/4) <Lc RIVER WATER (pCi/L) H-3 (8) 3000 (c) <Lc <Lc 4)5 0 B-9, B-10 GSA (24)

Mn-54 15 <Lc <Lc <Lc 0 Co-58 15 <Lc <Lc <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 <Lc <Lc 0 1-131 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 Ba/La-140 15 <Lc <Lc <Lc 0 (a) Positive values above L,; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2010

~LOCATION OF:LHIGHEST MEDIUM TYPE AND TOTAL AAANNUAL MEAN: NUMBER.OF MEDIUM(UNITS)o ANUMABER'L0I LD* *b .OCATIONS Ž*, AND CONTROL. NON-ROUTINE SEE TABLE NULSM F L )h DESIG.NATIOND- LOCATIONR:E PORTS PEFRE -MEAN (a) ' MEAN (a) MEAN (a),EPRT

": 'RANGEPERFORMED " 'ANa , , ,RANGa RANGE _a DRINKINGH-3 (8) 2000 <Lc <Lc N/A 0 (pCi/L) B-11, B-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 1-131 15 <Lc <Lc N/A 0 Cs-134 15 <Lc <Lc N/A 0 Cs-137 18 <Lc <Lc N/A 0 Ba/La-140 15 <Lc <Lc N/A 0 HUDSON RIVER SHORELINE SOIL GSA (10)

(pCi/kg - dry) B-13 Cs-134 150 <Lc <Lc <Lc 0

17 Off Verplanck #50 Manitou Inlet Cs-137 180 <L5 -8173 1.5 Mi (SSW) at 202.50 63(1/4)! 0

<L, - 173 154 (2/2)! 134 -173 <L, - 63 Sr-90 (10) 5000 <Lc <Lc <Lc 0 (a) Positive values above L,; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-6

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2010 LOCATION~iOF"1HI1GHEST;:

TYPE AND TOTAL ANNUAL MEAN" NUMBER OF

,MEDIUM (UNITS) NUMBER OFIDCTRLCTOS LOCATIONS .(b)

AND CONTROL NO-UTE LLE NON-ROUTINE SEE TABLE ANALYSIS *LLD DESIGAION. .,LOCATIONN- REPORTS PERFORMED! MEAN (a) MEAN (a) MEAN (a)

RANGE RANGE RANGE.......

BROADLEAF VEGETATION GSA (58)

(pCi/kg - wet) B-14 1-131 60 <Lc <Lc <Lc 0 Co-60 N/A <Lc <Lc <Lc 0 Cs-134 60 <Lc <Lc <Lc 0

95 Meteorological Tower Cs-1 37 80 31(1/37)! 0.46 Mi (SSW) at 208' <Lc 0

<L, - 31 31(1/16)!

<L, - 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-63 (24) 100 <Lc <Lc <Lc 0 Co-60 130 <Lc <Lc <Lc 0 Zn-65 260 <Lc <Lc <Lc 0 Cs-134 130 <Lc <Lc <Lc 0 Cs-137 150 <Lc <Lc <Lc 0 Sr-90 (24) 5 <Lc <Lc <Lc 0 AQUATIC VEGETATION GSA(5)

(pCi/kg - WET)

B-16 Co-60 NONE <Lc <Lc <Lc 0 1-131 NONE <Lc <Lc <Lc 0 Cs-1 34 NONE <Lc <Lc <Lc 0

84 Cold Spring

28 Cove#8CodSrn

28 Lents entsCove 10.88 Mi (N) at 3560 Cs-137 NONE 17.6 (1/4)!/ <L, -17.6 0.45 Mi (ENE) at 069° 16.8(N) at 3 0 17.6(1/2)/ <Lc-17.6 16.8 16.8 (a) Positive values above L,; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-7

TABLE B-2 ODCM ANNUAL

SUMMARY

- 2010 TYPE AND TOTAL ANNUAL MEAN:

MEDIUM (UNITS) NUMBER OF LDb' .LOCATIONS ANDL CONTROL NON-ROUTINE'

§SEE'TABLE ANALYSIS~ DESIGNATION 7LOCATION:* EOT PERFORMED >MEAN

-, (a) ~ MEAN (a) MEANI~a)

________________ 14!ANGE ..RANGE >RANGE ____

BOTTOM SEDIMENT GA8 (pCi/kg - DRY) GSA(8.

B-17 Co-60 NONE <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0 553 (5/6)1 #10 Discharge Canal 0.3 Cs-137 180 <Lc - 1330 Mi WSW 874 (212) 418 - <Lc 0 1330 PRECIPITATION GSA(8)

(pCi/L)

B-18 H-3 (8) 3000 (c) <Lc <Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 SOIL (pCi/kg - DRY) GSA(3)

B-19 Co-60 NONE <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0 Cs-137 180 <Lc <Lc <Lc 0 GROUNDWATER GSA(2)

(pCi/L) B-20 H-3 (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 (a) Positive values above L.; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L B-8

TABLE B-3 2010 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER)

Station ID Sector lit'Quarter. 2nd Quarter 3d 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-05 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 12.56 +/- 0.57 13.11 +/- 0.59 14.25 +/- 0.69 12.24 +/- 0.94 13.0 52.2 DR-36 NE 14.99 +/- 0.65 14.48 +/- 0.52 15.65 +/- 0.57 14.53 +/- 1.41 14.9 59.7 DR-37 SSW 13.41 +/- 0.61 14.33 +/- 0.90 15.38 +/- 0.69 13.86 +/- 0.96 14.2 57.0 DR-38 S 11.43 +/- 0.47 12.83 +/- 1.10 13.55 +/- 0.51 11.50 +/- 0.89 12.3 49.3 DR-39 SSW 14.05 +/- 0.53 15.63 +/- 0.64 15.75 +/- 0.67 16.26 +/- 1.17 15.4 61.7 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 B-9

TABLE B-4 DIRECT RADIATION, 2000 THROUGH 2010 DATA (mR per Standard Quarter Basis)

Mean-:;. Standard , Minimum... Maximum VI Station ID, Mean 'Deviation VManMaimmValue 2010 Mean (2000-2009) (2000-2009) (0020)

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 55.2 3.4 48.8 60.8 52.2 DR-36 59.7 3.6 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 uter Ring.

ID iD St 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-1I 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 GROSS BETA ACTIVITY pCi/ M 3 +/- 1 Sigma SAMPLE STATION #

Week, Week End 4 94 95 23** 27 29 44 NumberI Date I I 1 I I I I 1 1/4/2010 0.008 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 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 1/19/2010 0.018 +/- 0.001 0.023 +/- 0.002 0.018 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.018 +/- 0.001 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 2/2/2010 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 2/9/2010 0.013 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 7 2/16/2010 0.011 +/- 0.001 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 +/- 0.001 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 3/2/2010 0.002 +/- 0.001 -0.001 +/- 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 +/- 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 3/15/2010 0.023 +/- 0.005 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 12 3/23/2010 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 no data 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.008 +/- 0.002 0.012 +/- 0.001 0.014 +/- 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 +/- 0.001 0.004 +/- 0.001 15 4/12/2010 0.010 +/- 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 4/20/2010 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 4/26/2010 0.010 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 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 5/11/2010 0.008 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 20 5/17/2010 0.010 +/- 0.001 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 6/1/2010 0.011 + 0.001 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 6/7/2010 0.011 +/- 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 +/- 0.001 24 6/14/2010 0.007 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.006 +/- 0.001 0.005 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 25 6/21/2010 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 26 6/28/2010 0.012 +/- 0.001 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

- Control sample location B-12

TABLE B-6 (Continued)

IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2010 3

GROSS BETA ACTIVITY pCi! m I Sigma

[Week,14 1 Number Week End Dat 51 I

94 SAMPLE STATION #

95 I

I 23* 1 27 I 1

29 1

44 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 28 7/12/2010 0.020 +/- 0.002 0.019 +/- 0.002 0.022 +/- 0.002 0.018 +/- 0.001 0.021 +/- 0.002 0.020 +/- 0.002 10.018 +/- 0.001 0.019 +/- 0.002 29 7/19/2010 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 7/26/2010 0.016 +/- 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 0.018 +/- 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 +/- 0.015 0.018 +/- 0.001 34 8/23/2010 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 +/- 0.001 35 8/30/2010 0.008 +/- 0.001 0.005 +/- 0.001 0.009 +/-0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.009 :b 0.001 0.008 +/- 0.001 36 9/7/2010 0.026 +/- 0.002 0.029 +/- 0.002 0.027 +/-0.002 0.028 +/- 0.001 0.032 +/- 0.002 0.029 +/- 0.002 0.025 +/- 0.001 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 9/20/2010 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 +/- 0.001 39 9/27/2010 0.017 +/- 0.001 0.018 +/- 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 0.005 +/- 0.001 41 10/12/2010 0.010 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 42 10/18/2010 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 +/- 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 11/15/2010 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 +/- 0.001 47 11/22/2010 0.017 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 48 11/29/2010 0.021 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.001 0.018 +/- 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 12/13/2010 0.007 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 51 12/20/2010 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 ,0.011 +/- 0.001 52 12/27/2010 0.004 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.004 +/- 0.001 0.005 +/- 0.0011 0.006 +/- 0.001 10.006 +/- 0.001 10.007 +/- 0.001

- Control sample location B-13

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2010 Results in Units of 10E-3 pCi/ d +/- 1 Sigma SAMPLE LOCATIONS - 1ST QTR 2010 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 121.7 +/- 15.9 139.8 +/- 13.5 98.7 +/- 11.8 98.9 +/- 11.0 114.8 +/- 13.0 110.4 +/- 14.1 131.1 +/- 12.0 121.7 +/- 13.3 Cs-134 < 1.3 < 0.9 < 0.5 < 0.6 < 1.0 < 1.2 < 0.8 < 0.8 Cs-137 < 0.7 < 0.4 < 0.6 < 0.3 < 0.2 < 0.6 < 0.2 < 0.6 Zr-95 ,1.2 < 1.4 < 0.7 < 0.9 < 2.1 < 2.9 < 0.6 < 1.2 Nb-95 < 1.8 < 1.4 < 0.9 < 0.8 < 0.7 < 1.5 < 1.1 < 1.1 Co-58 < 1.7 < 0.8 < 0.6 < 0.5 < 0.7 < 1.5 < 0.7 < 0.4 Mn-54 < 0.8 < 0.4 < 0.6 < 0.6 < 0.8 < 0.9 < 0.2 < 0.7 Zn-65 < 2.0 < 1.2 < 1.2 < 1.1 < 1.3 < 2.8 < 1.5 < 0.9 Co-60 <-0.6 < 0.7 < 0.9 < 0.4 < 0.7 < 0.5 < 0.5 < 0.4 K-40 < 8.5 < 4.2 < 4.6 < 5.4 44.6 +/- 9.5 57.6 +/- 11.2 < 3.3 < 4.9

- Control Sample Location SAMPLE LOCATIONS - 2ND QTR 2010 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 111.0 +/- 14.7 131.2 +/- 14.2 149.2 +/- 15.6 145.8 +/- 15.5 163.4 +/- 14.4 119.9 +/- 13.8 122.5 +/- 11.4 103.7 +/- 12.6 Cs-134 < 1.1 < 0.7 < 1.0 < 0.8 < 0.5 < 0.9 < 0.5 < 0.7 Cs-137 < 0.4 < 0.6 < 0.7 < 0.7 < 0.4 < 0.6 < 0.2 < 0.5 Zr-95 < 2.9 < 1.2 < 1.2 < 2.3 < 2.3 < 1.5 < 1.1 < 1.2 Nb-95 < 1.7 < 1.2 < 1.2 < 2.1 < 1.6 < 12 < 1.0 < 1.4 Co-58 < 0.8 < 0.7 < 1.0 < 0.8 < 0.6 < 0.8 < 0.3 < 0.5 Mn-54 < 0.8 < 0.3 < 0.5 < 0.5 < 0.6 < 0.6 < 0.5 < 0.4 Zn-65 < 1.0 < 1.4 < 2.6 < 1.9 < 1.8 < 1.0 < 1.4 < 1.7 Co-60 < 0.7 < 0.6 < 0.6 < 1.1" < 0.8 < 0.7 < 0.4 < 0.8 K-40 < 5.8 < 5.6 < 6.4 < 7.3 50.6 +/- 9.6 < 3.9 < 5.7 < 5.2

- Control Sample Location B-14

TABLE B-7 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2010 Results in Units of IOE-3 pCi/ nd+/- 1 Sigma SAMPLE LOCATIONS - 3RD QTR 2010 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 116.1 +/- 15.4 132.1 +/- 14.0 145.1 +/- 14.1 135.4 +/- 13.0 106.2 +/- 12.7 136.1 +/- 15.0 123.4 +/- 13.8 145.1 +/- 15.0 Cs-134 < 0.6 < 0.8 < 0.6 < 0.6 < 0.6 < 1.0 < 0.8 < 0.8 Cs-137 < 0.7 < 0.8 < 0.3 < 0.2 < 0.4 < 0.5 < 0.6 < 0.9 Zr-95 < 2.3 < 2.3 < 1.0 < 0.7 < 0.7 < 2.2 < 1.5 < 1.7 Nb-95 < 2.6 < 1.3 < 1.0 < 0.5 < 1.1 < 1.2 < 1.5 < 1.6 Co-58 < 1.7 < 1.0 < 0.5 < 0.4 < 0.4 < 1.0 < 0.7 < 1.1 Mn-54 < 0.4 < 0.7 < 0.4 < 0.6 < 0.3 < 0.7 < 0.7 < 0.8 Zn-65 < 2.6 < 2.2 < 1.4 < 1.6 < 1.2 < 1.1 < 2.3 < 2.0 Co-60 < 0.6 < 0.9 < 0.4 < 0.5 < 0.5 < 0.9 < 0.6 < 0.5 K-40 < 9.0 41.1 +/- 10.4 < 6.4 < 6.9 < 4.6 < 12.8 51.0 +/- 9.8 33.7 +/- 9.3

- Control Sample Location SAMPLE LOCATIONS - 4TH QTR 2010 Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Roseton #23 ** Grassy Point #29 Peekskill #44 Be-7 78.2 +/- 10.4 106.6 +/- 12.0 72.7 +/- 11.4 61.1 +/- 11.1 93.2 +/- 10.7 50.4 +/- 9.0. 82.3 +/- 9.9 94.2 +/- 12.0 Cs-134 < 0.3 < 0.4 < 0.8 < 0.9 < 0.5 < 0.5 < 0.9 < 1.0 Cs-137 < 0.3 < 0.5 < 0.6 < 0.7 < 0.6 < 0.3 < 0.3 < 0.7 Zr-95 < 1.1 < 1.5 < 1.5 < 0.7 < 0.8 < 1.1 < 1.6 < 2.6 Nb-95 < 0.9 < 1.4 < 1.8 < 1.1 < 0.9 < 1.1 < 1.3 < 0.7 Co-58 < 0.4 < 0.8 < 1.1 < 0.7 < 0.8 < 0.4 < 0.5 < 1.0 Mn-54 < 0.7 < 0.7 < 0.6 < 0.6 < 0.6 < 0.3 < 0.4 < 0.6 Zn-65 < 1.0 < 1.4 < 2.3 < 1.2 < 0.7 < 0.9 < 2.0 < I.1 Co-60 < 0.5 < 0.8 < 0.7 < 0.4 < 0.4 < 0.4 < 0.7 < 1.0 K-40 < 5.3 < 5.8 48.9 +/- 9.8 < 6.6 < 4.1 < 4.8 < 8.5 68.8 +/- 12.7

- Control Sample Location B-15

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2010 1-131 ACTIVITY pCi/rn 3 +/- 1 Sigma

______SAMPLE STATION #____

Week Week End 45 94 95 23** 27 29 44 Number Date 101/04/10 < 0.023 < 0.037 < 0.033 < 0.020 < 0.015 < 0.031 < 0.019 < 0.029 2 01/12/10 < 0.018 < 0.017 < 0.025 < 0.018 < 0.017 < 0.015 < 0.014 < 0.020 3 01/19/10 < 0.022 K 0.018 < 0.025 < 0.018 < 0.024 < 0.020 < 0.021 < 0.020 4 01/26/10 < 0.017 < 0.015 < 0.017 < 0.015 < 0.019 < 0.017 < 0.027 < 0.025 5 02/02/10 < 0.020 < 0.016 < 0.021 < 0.020 < 0.021 < 0.020 < 0.065 < 0.031 6 02/09/10 < 0.021 < 0.017 < 0.021 < 0.017 < 0.023 < 0.018 < 0.014 < 0.012 7 02/16/10 < 0.015 < 0.017 < 0.018 < 0.019 < 0.028 < 0.015 < 0.022 < 0.026 8 02/23/10 < 0.021 < 0.018 < 0.020 < 0.014 < 0.026 < 0.017 < 0.031 < 0.037 9 03/02/10 < 0.026 < 0.061 < 0.023 < 0.015 < 0.035 < 0.028 < 0.017 < 0.021 10 03/08/10 < 0.028 < 0.033 < 0.019 < 0.018 < 0.022 < 0.020 < 0.023 < 0.028 11 03/15/10 < 0.062 < 0.022 < 0.029 < 0.028 . 0.034 < 0.020 < 0.016 < 0.016 12 03/23/10 no data K 0.030 < 0.017 < 0.025 < 0.026 < 0.017 < 0.056 < 0.034 13 03/30/10 no data K 0.023 < 0.020 < 0.021 < 0.057 < 0.019 < 0.030 < 0.038 14 04/05/10 no data K 0.026 K 0.027 < 0.025 < 0.035 < 0.024 < 0.021 < 0.021 15 04/12/10 < 0.049 < 0.027 < 0.013 < 0.031 < 0.028 < 0.021 < 0.015 < 0.023 16 04/20/10 < 0.036 < 0.020 < 0.017 < 0.030 < 0.034 < 0.014 < 0.028 < 0.034 17 .04/26/10 < 0.032 < 0.024 < 0.024 < 0.022 < 0.022 < 0.027 < 0.046 < 0.023 18 05/04/10 < 0.039 < 0.020 < 0.022 < 0.025 < 0.027 < 0.032 < 0.022 < 0.035 19 05/11/10 < 0.029 < 0.033 < 0.036 < 0.025 < 0.027 < 0.034 < 0.025 < 0.041 20 05/17/10 < 0.016 < 0.005 < 0.037 < 0.015 < 0.020 < 0.028 < 0.019 < 0.036 21 05/24/10 < 0.018 < 0.019 < 0.025 < 0.023 < 0.021 < 0.016 < 0.016 < 0.017 22 06/01/10 < 0.016 < 0.015 < 0.021 < 0.015 < 0.021 < 0.027 < 0.022 < 0.023 23 06/07/10 < 0.013 < 0.020 < 0.033 < 0.030 < 0.029 < 0.022 < 0.010 < 0.028 24 06/14/10 < 0.035 < 0.028 < 0.033 < 0.035 < 0.027 < 0.020 < 0.025 < 0.022 25 06/21/10 < 0.024 < 0.021 < 0.024 < 0.027 < 0.029 < 0.018 < 0.014 < 0.025 26 06/28/10 < 0.022 < 0.032 K 0.018 K 0.020 K 0.026 K 0.021 K 0.020 K 0.034

- Control sample location B-i16

TABLE B-8 (continued)

IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2010 1-131 ACTIVITY pCi/M-3 +/- 1 Sigma SAMPLE STATION #

Week Week End 4 5 94 95 23** 27 29 44 Number Date I I I I I I T 27 07/06/10 0.027 0.017 0.025 0.032 0.030 K 0.015 0.025 K 0.030 28 07/12/10 0.044 0.039 K 0.026 K 0.025 K 0.033 0.033 0.032 0.037 29 07/19/10 K K 0.018 K:

0.029 0.016 0.020 0.024 0.037 0.017 0.023 30 K K K:

07/26/10 0.021 0.018 0.029 0.026 0.021 0.028 0.017 0.020 31 K K 0.017 K 0.024 08/02/10 0.016 0.024 0.034 0.026 0.023 0.010 32 K < K7 08/09/10 0.013 0.022 0.027 0.023 0.016 0.020 0.015 0.022 K 0.033 K K:

33 08/16/10 0.045 0.031 0.020 0.039 0.035 0.244 0.021 K <K 0.026 K 34 08/30/10 data 0.019 0.027 0.021 0.021 0.018 0.025 09/07/10 K K K*

35 0.019 0.016 0.031 0.023 0.025 0.013 0.014 0.018 36 < K K:

09/13/10 0.034 0.019 0.024 0.030 0.018 0.031 0.024 0.032 K <K <K 37 09/20/10 0.026 0.025 0.025 0.031 0.024 0.017 0.017 0.022 38 K K <K 09/27/10 0.025 0.018 0.026 0.019 0.023 0.020 0.016 0.019 K K: 0.024 K 39 10/04/10 0.026 0.025 0.021 0.017 0.029 0.018 0.029 40 10/12/10 K K K: 0.021 0.020 0.017 0.018 0.018 0.025 0.017 0.023 41 10/18/10 K K K 0.030 0.032 0.020 0.027 0.025 0.026 0.017 0.014 42 10/25/10 K K K:

0.019 0.021 0.024 0.020 0.022 0.019 0.047 0.020 43 11/01/10 < K 0.014 K 0.022 0.015 0.023 0.018 0.024 0.011 0.019 44 < K: 0.020 K:

11/08/10 0.024 0.021 0.025 0.021 0.021 0.010 0.035 45 11/15/10 K K 0.013 K 0.034 0.026 0.017 0.028 0.018 0.020 0.014 46 11/22/10 0.022 0.022 0.024 0.021 K 0.015 K: 0.025 0.015 0.013 47 11/29/10 0.029 <K K 0.027 0.021 0.017 0.019 0.014 0.023 0.016 48 K 0.018 K 0.018 12/06/10 0.020 0.016 0.018 0.022 0.013 49 12/13/10 0.004 0.018 nO data 0.021 0.017 K 0.024 0.016 K 0.021 50 K K K7 0.031 12/20/10 0.037 0.036 0.026 0.032 0.033 0.022 0.024 51 K K K 0.024 12/27/10 0.034 0.027 0.025 0.022 0.028 0.025 0.020 52 < K 0.013 K: 0.015 01/04/11 0.019 0.019 0.023 0.021 0.016 0.023 I

______ = _________ = ______ 2 ______ I ______ & ______ _______ I ______ i ______

- Control sample location B-17

TABLE B-9 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2010 Results in Units of pCi/liter +/- 1 Sigma

9 PLANT INLET (HUDSON RIVER INTAKE)

Date [ 1/29/2010 2/26/2010 3/26/2010 4/3 0/2010 T-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 K-40 162.6 +/- 13.72 108.9 +/- 11.45 43.73 +/- 6.81 87.79 +/- 10.97 55.59 +/- 8.21 45.7 +/- 9.05 Ba/La-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 11/29/2010 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 94.11 +/- 13.49 140.1 +/- 11.59 55.9 +/- 9.08 129.8 +/- 9.35 42.85 +/- 7.30 91.62 +/- 7.89 BaiLa-140 < 2.64 < 2.67 < 2.12 < 1.38 < 2.19 . < 2.66 B-1 8

TABLE B-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2010 Results in Units of pCi/liter +/- 1 Sigma

10 DISCHARGE CANAL (MIXING ZONE)

Date 1/29/2010 2/26/2010 3/26/2010 4/30/2010 5/24/2010 6/28/2010 NUCLIDE 1-131 < 6.69 < 3.32 < 5.09 < 5.34 < 2.81 < 4.20 Cs-134 < 0.86 < 0.61 < 0.78 < 0.43 < 0.85 < 0.85 Cs-137 < 1.26 < 0.84 < 1.13 < 0.64 < 1.08 < 1.08 Zr-95 < 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 Co-58 < 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 Fe-59 < 4.35 < 2.50 < 3.68 < 2.14 < 3.05 < 3.43 Zn-65 < 1.86 < 2.06 < 1.47 < 0.80 < 2.75 < 2.51 Co-60 < 1.33 < 0.82 < 1.23 < 0.57 < 1.08 < 1.03 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 Ba/La-140 < 3.70 < 2.73 < 3.19 < 2.81 < 2.49 < 3.21 Date 7/26/2010 8/30/2010 9/27/2010 10/25/2010 11/29/2010 12/28/2010 NUCLIDE 1-131 < 4.23 < 4.10 < 3.19 < 3.20 < 3.26 < 4.21 Cs-134 < 1.14 < 0.73 < 1.26 < 1.33 < 0.72 < 0.64 Cs-137 < 1.40 < 1.12 < 1.11 < 1.01 < 1.00 < 0.84 Zr-95 < 2.87 < 2.20 < 2.13 < 2.28 < 1.91 < 1.74 Nb-95 < 1.50 < 1.56 < 1.41 < 1.39 < 1.27 < 1.25 Co-58 < 1.71 < 1.19 < 1.12 < 1.15 < 1.05 < 1.01 Mn-54 < 1.73 < 1.24 < 1.08 < 1.10 < 1.07 < 0.81 Fe-59 < 3.95 < 2.88 < 3.22 < 3.11 < 2.82 < 2.63 Zn-65 < 1.87 < 2.80 < 1.40 < 2.59 < 1.34 < 1.55 Co-60 < 1.54 < 0.94 < 1.15 < 1.10 < 1.03 < 0.91 K-40 123.2 +/- 17.13 81.7 +/- 12.01 135.9 +/- 13.16 83.54 +/- 11.62 88.77 +/- 10.54 48.64 +/- 7.77 Ba/La-140 < 3.90 < 3.28 < 2.07 < 2.76 < 2.46 < 3.03 B-19

TABLE B-10 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2010 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM First Quarter 12/31/09 03/26/10 455 PLANT INTAKE (HUDSON RIVER) Second Quarter 03/26/10 06/28/10 401 (09, INLET) ** Third Quarter 06/28/10 09/27/10 <409 Fourth Quarter 09/27/10 12/28/10 <408 First Quarter 12/31/09 03/26/10 <403 DISCHARGE CANAL Second Quarter 03/26/10 06/28/10 <397 (10, MIXING ZONE) Third Quarter 06/28/10 09/27/10 <409 Fourth Quarter 09/27/10 12/28/10 <408

- Control Sample location B-20

TABLE B-11 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2010 Results in Units of pCi/liter +/- 1 Sigma CAMP FIELD RESERVOIR Date 1/12/2010 2/8/2010 3/15/2010 4/20/2010 5/11/2010 6/7/2010 NUCLIDE 1-131 < 2.75 < 2.38 < 3.54 < 3.71 < 3.00 < 4.10 Cs-134 < 1.31 < 1.50 < 2.20 < 3.14 < 2.99 < 2.17 Cs-137 < 1.45 < 2.14 < 2.48 < 1.35 < 2.61 < 2.99 Zr-95 < 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 Co-58 < 1.48 < 1.79 < 2.71 < 2.49 < 2.31 < 3.05 Mn-54 < 1.75 < 1.62 < 2.59 < 2.60 < 1.88 < 3.45 Fe-59 < 4.02 < 4.20 < 5.93 < 5.26 < 5.87 < 6.54 Zn-65 < 3.72 < 4.36 < 7.54 < 5.04 < 3.94 < 9.06 Co-60 < 2.01 < 1.72 < 3.72 < 1.90 < 1.90 < 3.52 K-40 45.93 +/- 15.03 < 13.63 166.4 +/- 35.94 < 24.79 < 17.54 432.9 +/- 50.30 Ba/La- 140 < 2.52 < 2.90 < 4.75 < 3.74 < 1.92 < 4.44 Date 7/12/2010 8/9/2010 9/20/2010 10/18/2010 11/15/2010 12/13/2010 NUCLIDE 1-131 < 3.72 < 2.39 < 2.68 < 2.26 < 2.48 < 3.23 Cs-134 < 1.65 < 1.38 < 1.39 < 1.47 < 1.82 < 2.00 Cs-137 < 4.02 < 1.88 < 2.02 < 2.11 < 2.68 < 2.61 Zr-95 < 4.47 < 2.55 < 3.12 < 2.86 < 2.94 < 4.40 Nb-95 < 3.08 < 1.98 < 1.91 < 2.01 < 2.00 < 2.59 Co-58 < 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 Fe-59 < 7.90 < 5.15 < 5.08 < 3.63 < 6.33 < 4.44 Zn-65 < 10.42 < 1.85 < 4.69 < 2.16 < 6.79 < 6.83 Co-60 < 3.35 < 2.32 < 1.72 < 1.80 < 2.37 < 3.01 K-40 109.7 +/- 26.57 < 19.27 < 16.29 < 20.60 81.54 +/- 21.56 < 22.62 Ba/La-140 < 5.25 < 1.78 < 2.77 < 2.40 < 2.66 < 2.36 B-21

TABLE B-11 (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 2/8/2010 3/15/2010 4/20/2010 5/11/2010 T 6/7/2010 NUCLIDE 1-131 < 2.17 < 2.79 < 4.22 < 4.40 < 1.88 < 2.90 Cs-134 < 2.25 < 1.67 < 1.92 < 1.63 < 2.97 < 1.50 Cs-137 < 2.43 < 2.63 < 3.11 < 2.83 < 2.27 < 2.27 Zr-95 < 4.16 < 2.61 < 5.70 < 4.10 < 3.24 < 3.79 Nb-95 < 2.24 < 2.10 < 2.99 < 2.15 < 2.10 < 2.41 Co-58 < 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 Fe-59 < 4.60 < 5.53 < 10.07 < 7.25 < 4.86 < 6.25 Zn-65 < 3.92 < 5.23 < 7.40 < 3.22 < 4.13 < 3.05 Co-60 < 1.74 < 2.46 < 2.93 < 2.74 < 1.97 < 2.50 K-40 113.7 +/- 21.38 72.45 +/- 22.25 337.5 +/- 42.70 125.4 +/- 24.80 < 26.28 412.4 +/- 35.16 Ba/La-140 < 2.66 < 3.38 < 3.30 < 4.03 < 2.98 < 2.78 Date 7/12/2010 8/9/2010 9/20/2010 10/18/2010 11/15/2010 12/13/2010 NUCLIDE 1-131 < 3.09 < 2.29 < 2.19 < 2.43 < 3.26 < 2.52 Cs-134 < 2.00 < 1.54 < 2.89 < 2.07 < 1.57 < 1.57 Cs-137 < 2.52 < 2.32 < 2.09 < 2.43 < 2.94 < 2.09 Zr-95 < 3.25 < 3.24 < 2.97 < 4.30 < 3.77 < 3.93 Nb-95 < 2.72 < 1.79 < 2.46 < 2.36 < 2.59 < 2.05 Co-58 < 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 Fe-59 < 8.10 < 5.54 < 5.40 < 6.13 < 7.35 < 5.95 Zn-65 < 5.59 < 6.27 < 4.14 < 6.53 < 7.48 < 6.13 Co-60 < 2.13 < 2.08 < 2.18 < 1.74 < 2.13 < 2.55 K-40 < 24.80 69.5 +/- 19.33 118.6 +/- 23.32 93.1 +/- 21.05 < 28.62 106.7 +/- 23.43 Ba/La-140 < 4.03 < 2.97 < 329 < 1.87 < 4.29 < 2.67 B-22

TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES - 2010 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM First Quarter 12/15/09 03/15/10 < 420 CAMP FIELD RESERVOIR Second Quarter 03/15/10 06/07/10 < 406 Third Quarter 06/07/10 09/20/10 < 410 Fourth Quarter 09/20/10 12/13/10 < 421 First Quarter 12/15/09 03/15/10 < 420 NEW CROTON RESERVOIR Second Quarter 03/15/10 06/07/10 < 406 Third Quarter 06/07/10 09/20/10 " < 410 Fourth Quarter 09/20/10 12/13/10 < 409 B-23

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample COLD SPRING 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 ISS172210 1SS532210 Req. CL Radionuclide (pCi) I 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 +/- 39.0 173.2 +/- 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 < 34.4 < 22.1 Zn-65 < 53.0 < 60.0 < 59.0 < 100.3 < 80.4 Fe-59 < 117.0 < 116.7 < 149.6 < 99.9 < 56.0 Co-60 < 41.5 < 31.6 < 56.1 < 27.5 < 25.0 Ba/La-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 < 410.4 < 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 Ach-228 869.4 +/- 129.2 1554.0 +/- 164.4 913.8 +/- 188.1 787.5 +1- 116.1 < 81.5 Ra-226 1706.0 +/- 674.7 3861.0 +/- 911.3 2149.0 +/- 682.2 1028.0 +/- 555.6 < 446.2 K-40 37710.0 +/- 1156.0 16870.0 +/- 884.1 20910.0 +/- 1178.0 16410.0 +/- 842.1 9909.0 +/- 646.5 Sr-90 3000 < 179 < 199 < 192 < 175 < 148 B-24

TABLE B-13 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample COLD SPRING LENTS COVE MANITOU VERPLANCK WHITE BEACH Location SHORELINE SHORELINE SHORELINE SHORELINE SHORELINE Date 9/13/2010 9/13/2010 9/13/2010 9/14/2010 9/14/2010 Client ID ISS843710 ISS283710 ISS503710 ISS173710 ISS533710 Req. CL Radionuclide (pCi)

Be-/ < 287.9 < 302.2 < 291.9 < 214.8 < 227.1 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 Ba/La-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 +/- 152.8 1607.0 +/- 223.2 412.2 +/- 88.7 < 100.9 Ra-226 1625.0 +/- 681.4 4792.0 +/- 681.4 4422.0 +/- 1021.0 1810.0 +/- 442.0 < 556.8 K-40 134640.0 +/- 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 B-25

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma

95 Meteorological Tower Sample Sample MET TOWER MET TOWER Location Date 4/26/2010 4/26/2010 Client ID IBV951710SI IBV951710S2 Req. CL RAGWEED MULLEIN Radionuclide (pCi) I _I 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 BaILa-140 < 6.11 < 10.03 Ru-103 < 6.33 < 10.35 Ru-106 < 76.47 < 117.80 Ce-141 < 9.63 < 13.11 Ce-144 < 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 B-26

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 MET TOWER MET TOWER Location Date 6/14/2010 6/14/2010 Client ID IBV952410SI 1BV952410S2 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 Ba/La-140 < 6.58 < 8.51 Ru-1 03 < 6.70 < 6.78 Ru-1 06 < 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 K-40 7903.0 +/- 286.2 4656.0 +/- 206.9 B-27

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg + 1 Sigma

95 Meteorological Tower Sample MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER MET TOWER Location Date 711912010 7119/2010 7/19/2010 8/16/2010 8/16/2010 8/16/2010 Client ID IBV952910SI 1BV95291OS2 IBV952910S3 IBV953310S1 IBV953310S2 IBV953310S3 Req. CL RAGWEED MULLEIN COTTON WOOD RAGWEED COMMON WILD RYE Radionuclide (pCi) I I I I II_ I Be-7 1323.0 +/- 112.0 493.4 +/- 83.4 1049.0 +/- 136.6 1970.0 +1- 174.2 1968.0 +1- 121.8 572.5 +1- 93.0 1-131 so < 13.15 < 11.35 < 15.66 < 20.48 < 11.96 < 13132 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 Ba/La-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-1 44 < 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 +/- 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 +1- 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 10/12/2010 10/12/2010 10/12/2010 Client ID IBV953710S1 IBV953710S2 IBV953710S3 IBV9541IOSI IBV954110S2 IBV954110S3 Req. CL MULLEIN GRAPE LEAVES RAGWEED RAGWEED MULLEIN COTTON WOOD Radionuclide (pCi) II__ I __ _ _____

Be-7 934.9 +/- 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 Ba/La-140 < 10.43 < 12.98 < 10.52 < 27.31 < 25.06 < 18.69 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 +/- 170.1 357.0 +/- 141.5 < 225.60 < 340.60 < 365.20 1337.0 +/- 344.0 K-40 8036.0 +/- 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 4/26/2010 4/26/2010 4/26/2010 5/17/2010 5/17/2010 5/17/2010 Client ID IBV941710S1 IBV941710S2 IBV941710S3 IBV942010SI IBV942010S2 IBV942010S3 Req. CL RAGWEED MULLEIN MUSTARD RAGWEED EWICK ALLROOT Radionuclide (pCi) _ I Be-7 851.1 +/- 77.9 834.9 +/- 83.9 201.4 +/- 90.1 612.4 +/- 89.6 < 94.83 338.8 +/- 65.1 1-131 50 < 9.42 < 9.92 < 15.50 < 12.36 < 11.67 < 9.60 Cs-134 50 < 10.77 < 11.87 < 11.20 < 15.97 < 9.35 < 1256 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 < 8.07 < 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 < 24.38 < 26.43 < 36.04 < 43.86 < 31.05 < 31.97 Co-60 < 6.91 < 9.56 < 14.30 < 17.41 < 12.11 < 9.15 Ba/La-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 +/- 339.5 9766.0 +/- 383.0 4768.0 +/- 279.4 5890.0 +/- 296.9

- Control Sample Location B-30

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 Date 6/14/2010 6/14/2010 6/14/2010 Client ID IBV942410S1 IBV942410S2 IBV942410S3 Req. CL eRAGWEED GRAPE L. VRG CREE Radionuclide (lo7i)RA EE 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-60 < 17.92 < 7.62 < 9.14 Ba/La-140 < 14.48 < 8.41 < 11.09 Ru-103 < 12.25 < 7.70 < 8.66 Ru-106 < 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-226 < 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)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma

94 IPEC Training Center SampleTRIIGB G Location TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG TRAINING BLDG Date 7/19/2010 7/19/2010 7/19/2010 8/16/2010 8/16/2010 8/16/2010 Client ID IBV942910SI IBV942910S2 IBV942910S3 1BV943310S 1 IBV943310S2 1BV943310S3 Req. CL CATALPA GRAPE LEAVES RAGWEED RAGWEED GRAPE CATALP Radionuclide (pCi)

Be-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 C0-58 < 15.87 < 16.65 < 13.64 < 10.29 < 12.31 < 6.29 Mn-54 < 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-60 < 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 < 19.00 < 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 B-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 9/13/2010 9/13/2010 9/13/2010 10/12/2010 10/12/2010 10/13/2010 Client ID IBV943710SI 1BV943710S2 1BV943710S3 1BV9441 IOSI IBV9441 10S2 IBV9441 10S3 Req. CL CATALPA GRAPE LE RAGWEED RAGWEED COTFON W CATALPA Radionuclide (pCi) GRAPE LE 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 < 28.09 < 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 Ba/La-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 1582.0 +/- 167.7 B-33

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 ROSETON ROSETON ROSETON ROSETON Date 4/26/2010 4/26/2010 4/26/2010 5/17/2010 5/17/2010 5/17/2010 Client ID IBV231710SI IBV231710S2 lBV231710S3 IBV232010SI IBV232010S2 1BV232010S3 Req. CL RAGWEED MULLEIN PENNY WORT RAGWEED MULLEIN BURDOCK Radionuclide (pCi) _ II__III _

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 < 6.94 < 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 BaILa-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 +1- 166.2 K-40 15550.0 +/- 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 +/- I Sigma

23 Roseton **

Sample OE ROSETON N ROSETON ROSETON Location Date 6/14/2010 6/14/2010 6/14/2010 Client ID IBV232410S1 IBV232410S2 IBV232410S3 (p CL Req.

Req 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 Ba/La-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 +/- 457.4 5206.0 +/- 307.9 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 ROSETON ROSETON ROSETON ROSETON Date 7/19/2010 7/19/2010 7/19/2010 8/16/2010 8/16/2010 8/16/2010 Client ID IBV232910S1 IBV232910S2 IBV232910S3 IBV233310S1 IBV233310S2 IBV233310S3 Re CL BURDOCK RAGWEED MILKWEED RAGWEED COMMON MULLEIN CATALPA Radionuclide (pCi) _________ _________

Be-7 1513.0 +/- 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 Ba/La-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 +/- 35.1 < 23.69 Ra-226 584.1 +/- 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 B-36

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- I Sigma

23 Roseton **

Sample Location ROSETON ROSETON ROSETON ROSETON ROSETON ROSETON Date 7/19/2010. 7/19/2010 7/19/2010 8/16/2010 8/16/2010 8/16/2010 Client ID IBV232910S1 IBV232910S2 IBV232910S3 IBV233310S1 IBV233310S2 1BV233310S3 Req. CL BURDOCK RAGWEED MILKWEED RAGWEED COMMON MULLEIN CATALPA Radionuclide (pCi) I I _I Be-7 11513.0 +/- 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 Ba/La-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 +/- 35.1 < 23.69 Ra-226 584.1 +/- 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 B-37

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 ROSETON ROSETON ROSETON ROSETON Date 9/13/2010 9/13/2010 9/13/2010 10/12/2010 10/12/2010 10/12/2010 Client ID IBV233710S1 IBV233710S2 IBV233710S3 1BV234110S1 IBV2341 10S2 IBV2341 10S3 Req. CL BITTERSWEET RAGWEED GRAPE LEAVES RAGWEED COMMON MULLEI PORCELAIN BERRY Radionuclide (pCi) _ I I _I 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 < 28.77 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 < 115.10 < 82.59 < 10.00 AcTh-228 < 56.18 < 39.62 117.4 +1- 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 Location VOP FISH VOP FISH VOP FISH VOP FISH VOP FISH VOP FISH Date 5/14/2010 5/14/2010 5/14/2010 5/21/2010 5/21/2010 6/15/2010 Client ID IFH252710S3 IFH252710S5 IFH252710S6 [FH252710S1 IFH252710S4 IFH252710S2 Req. CL CATFISH WHITE PERCH STRIPED BASS BLUE CRAB AMERICAN EEL SUNFISH Radionuclide (pCi) I Be-7 < 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 < 18.9 < 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 Ba/La-140 < 659.7 < 559.3 < 384.1 < 302.6 < 437.9 < 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 < 77.9 < 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 B-39

TABLE B-15 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma

25 Downstream (Hudson River)

Sample Location VOP FISH VOP FISH VOP FISH VOP FISH VOP FISH VOP FISH Date 8/6/2010 8/13/2010 8/13/2010 8/13/2010 8/28/2010 9/9/2010 Client ID IFH1254410SI IFH254410S3 IFH254410S4 IFH254410S5 IFH254410S6 1FH254410S2 Req. CL BLUE CRAB CAT FISH AMERICAN EEL WHITE PERCH STRIPED BASS SUN FISH Radionuclide (pCi)

Be-7 < 211.5 < 179.0 < 142.6 < 229.9 < 204.5 < 249.8 1-131 < 25560.0 < 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 < 7.4 < 8.8 < 10.4 < 11.8 Zr-95 < 31.5 < 31.2 < 35.7 < 39.6 < 38.3 < 45.0 Nb-95 < 41.1 < 40.4 < 46.1 < 52.6 < 46.5 < 51.9 Co-58 65 < 16.3 < 16.0 < 16.1 < 20.3 < 18.8 < 24.4 Mn-54 65 < 8.6 < 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 < 10.4 Ba/La-140 < 1148.0 < 1076.0 < 834.4 < 1661.0 < 663.9 < 716.5 Ru-103 < 34.4 < 36.7 < 32.5 < 42.3 < 39.1 < 43.8 Ru-106 < 98.9 < 106.9 < 89.4 < 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 +/- 22.1 58.7 +/- 21.7 < 29.1 127.2 +/- 28.7 114.5 +/- 29.4 123.3 +/- 31.0 Ra-226 603.7 +/- 114.5 < +/- 121.9 329.6 +/- 106.3 757.5 +/- 158.2 996.8 +/- 153.5 1289.0 +/- 192.7 K-40 2718.0 +/- 113.6 4157.0 +1- 153.1 2806.0 +/- 141.1 3607.0 +/- 164.1 7455.0 +/- 197.0 6753.0 +/- 223.8 Ni-63 100 < 67.0 < 48.0 < 47.0 < 52.0 < 48.0 < 54.0 Sr-90 5 < 2.9 < 2.4 < 2.9 < 4.3 < 3.2 < 3.3 B-40

TABLE B-15 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton (Control)

Sample Location ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH Date 5/13/2010 5/13/2010 5/13/2010 5/14/2010 6/1/2010 6/14/2010 Client ID IFH232710SI IFH232710S3 IFH232710S4 IFH232710S2 IFH232710S5 IFH232710S6 Req. CL CATFISH STRIPED BASS WHITE PERCH AMERICAN EEL SUNFISH BLUE CRAB Radionuclide (pCi) I IIIII 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 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 < 17.7 < 19.7 < 16.0 < 23.3 < 23.1 < 10.4 Ba/La-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 +/- 71.0 < 49.7 Ra-226 597.5 +/- 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 < 64.0 < 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 B-41

TABLE B-15 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton (Control)

Sample Lation Location ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH ROSETON FISH Date 8/4/2010 8/4/2010 8/4/2010 9/1/2010 9/9/2010 9/9/2010 Client ID IFH234410S2 IFH234410S3 IFH234410S6 IFH234410SI IFH234410S4 IFH234410S5 Req. CL AMERICAN EEL STRIPED BASS BLUE CRAB CAT FISH WHITE PERCH SUNFISH Radionuclide (pCi) _ __ 1 1_1_1_ 1 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 < 19.1 < 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 < 8.7 < 8.9 < 12.0 < 11.1 < 12.4 < 15.9 Ba/La-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 +/- 28.1 < 31.7 140.2 +/- 32.9 < 34.6 57.2 +/- 33.1 79.0 +/- 35.3 Ra-226 1079.0 +/- 147.2 436.4 +/- 127.1 814.5 +/- 166.4 493.7 +1- 185.8 753.9 +/- 170.1 757.1 +1- 169.8 K-40 2820.0 +/- 138.2 4161.0 +/- 168.2 5860.0 +/- 198.8 2774.0 +/- 199.7 3345.0 +/- 200.3 5338.0 4/- 244.6 Ni-63 100 < 55.0 < 47.0 < 72.0 < 48.0 < 53.0 < 51.0 Sr-90 5 < 2.8 < 2.6 < 2.9 < 2.9 < 3.1 < 4.9 B-42

TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample Location COLD SPRING COLD SPRING LENTS COVE LENTS COVE VERPLANCK Date 7/1/2010 9/13/2010 7/1/2010 9/13/2010 6/3/2010 Client ID IAV842610 IAV843710 IAV282610 IAV283710 .IAV172210 Req. CL MYRO MYRO MYRO MYRO MYRO Radionuclide (pCi) I IIIII Be-7 118.8 +/- 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 Ba/La-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 +1- 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 +1- 126.1 3162.0 +/- 126.7 1555.0 +/- 108.3 4782.0 +/- 238.9

. greater than critical level, but less than LLD B-43

TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample Location COLD SPRING COLD SPRING LENTS COVE LENTS COVE VERPLANCK VERPLANCK Date 6/2/2010 9/13/2010 6/2/2010 9/13/2010 6/3/2010 9/14/2010 Client ID IBS842210 IBS843710 IBS282210 IBS283710 IBS172210 IBS173710 Req. CL Radionuclide (pCi) I 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 < 36.7 < 43.9 338.3 +/- 54.6 < 70.3 327.4 +1- 51.1 349.6 +/- 67.1 Zr-95 < 75.9 < 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 < 86.0 < 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 Ba/La-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 < 407.1 < 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 +1- 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 +/- 1527.0 35920.0 +/- 1361.0 20700.0 +/- 1333.0 27570.0 +/- 1825.0 22930.0 +/- 1212.0 26100.0 +/- 1654.0 B-44

CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample DISCHARGE CANAL DISCHARGE CANAL Location Date 6/3/2010 9/14/2010 Client ID IBS102210 IBS103710 Req. CL Radionuclide (pCi) I _I Be-7 < 276.0 < 510.6 1-131 < 56.6 < 95.8 Cs-134 75 < 24.9 < 41.3 Cs-1 37 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 Zn-65 < 88.5 < 75.2 Fe-59 < 96.0 < 123.8 Co-60 < 31.2 < 51.6 Ba/La-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 4/- 524.1 5143.0 +/- 1068.0 K-40 17640.0 +/- 846.9 23370.0 +/- 1295.0 B-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 3/29/201.0 6/28/2010 9/27/2010 12/28/2010 Client ID Req. CL IRF44QI10 IRF44Q210 IRF443QI0 IRF44Q410 Radionuclide (pCi) I_ I 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 BaILa-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)

CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2010 Results in Units of pCi/L +/- 1 Sigma Sample ROSETON ROSETON ROSETON ROSETON Location RAINWATER RAINWATER RAINWATER RAINWATER Date 3/29/2010 6/29/2010 9/27/2010 12/28/2010 Client ID Req. CL IRF23Q110 lRF23Q210 IRF233QI0 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-1 34 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 Ba/La-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 Control Location B-47

TABLE B-19 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL SAMPLES - 2010 Results in Units of pCi/kg +/- 1 Sigma Sample Location ROSETON MET TOWER TRAINING BLDG Date 9/27/2010 9/27/2010 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 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 Co-60 < 44.4 < 57.0 < 41.1 Ba/La-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 Roseton: Control Location B-48

TABLE B-20 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L + 3 sigma Monitoring Well MW-LAF MW-LAF Sample Name MW-LAF-001-013 MW-LAF-002-014 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 (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

B-49

Table B-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.

B-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 I Unit 2 Plant Vent Unit 3 Plant Vent superheater Address of nearest resident, Last Sector Compass Point (meters) (meters) (meters) Census Il 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 i E 662 785 1371 1103 Lower South St. Peekskill

_______ % 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 10 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 B-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 (rnRJQuar-ter)

Year, Inner Ring Outer Ring, co.ti*o Loca~tidh.

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

-O. 0-2O' ;* *14.3 14.3 16.2 C-2

FIGURE C-1 DIRECT RADIATION, ANNUAL

SUMMARY

2000 to 2010 40.0 35.0 30.0 25.0 0

I 20.0 E

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 YaAll Indicator Control All Indicator Control Locations Location Locations, Loc.ation I 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

.. Historical A.e.a. . 0.01 0.01A 21006-2009 00 .1 c<L Critical Level (Lj)is less than the ODCM required LLD.

<L, indicates no positive values above sample critical level.

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 2000 to 2010 0.05

.1 MAll Indicator Locations

-Control Location 0.04 0.03 C-.

0.

0.02 0.01 0.00 1--

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-1*371, Year, Inlet Discharge Inlet Discharge 2000 190 267 < Lc < Lc 2001 < Lc 323 < Lc < Lc 2002 432 562 < Lc < Lc 2003 < Lc < Lc < Lc < LK 2004 < Lc 553 < Lc < Lc 2005 < Lc 618 < LC < Lc 2006 < Lc 386 < Lc < Lc 2007 < Lc < Lc < Lc < Lc 2008 < Lc < Lc < LK < Lc 2009 < Lc < Lc < Lc < Lc 2010 428 < Lc < Lc < Lc IHistorical Average, 31 42.L<

20-24< LC < L Critical Level (Lj)is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-6

FIGURE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 2000 to 2010 2000 1800 1600 1400 1200 1000 a.

800 600 400 200 0

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Tritium ODCM required LLD = 3000 pCi/L C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 2000 to 2010 (pCi/L)

.'Year Tritium (H-3) C"s-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 Ave~rage <L <K 2000r-20,09 Critical Level (Lj)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 0.

1000 NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEARS HISTORY 800 600 400 200 0

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Tritium ODCM required LLD = 2000 pCi/L C-9

TABLE C-5 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 < L6 2010 < Lc < Lc 127 < Lc 1-istorical Average 2O2O 52 < c166 191 Critical Level (Lc) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 750 EIndicator (Cs-1 34) 650

= Control (Cs- 134)

=Indicator (Cs-1 37) 550

- Control (Cs-137) 450 350 0,.

250 150 50

-50 Cs-134 ODCM required LLD = 150 pCi/Kg, dry Cs-137 ODCM required LLD = 175 pCi/Kg, dry C-1l

TABLE C-6 BROAD LEAF VEGETATION - Cs-137 2000 to 2010 (pCiIKg, wet)

CS-I 37

, Year Indicator Control C'],

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.11

,QOO-2009 O

Critical Level (L,) is less than the ODCM required LLD.

<L, indicates no positive values above sample critical level.

C-12

FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 2000 to 2010 100 80 60 G)

C-)

a.

40 20 0

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 ODCM required LLD = 80 pCi/Kg, wet C-1 3

TABLE C-7 FISH AND INVERTEBRATES - Cs-137 2000 to 2010 (pCi/Kg, dry)

.>1*,wg;l~K9 2Cs-137:

Year .Indator . 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 <L 2010 < LC < LC Historical Average 2000-2009, Critical Level (Lc) is less than the ODCM 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 El Indicator (Cs-137) n 180 El Control (Cs- 137) 160-140 120 80 NO IDENTIFIED Cs-137 IN PREVIOUS TEN YEARS HISTORY 60 40 20 0

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Cs-137 ODCM required LLD = 150 pCi/Kg, wet C-1 5

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

D.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 bythe 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- 1

D.2 Table D1: PROGRAM SCHEDULE SAMPLE PROVIDER VIEER SAMPLE LABORATORY ECKERT MEDIA MEDI ANAYSISECKERT ANALYSISANLTS & ZIEGLER ANALYTICS Water Gross Beta 3 Water Tritium 5 Water 1-131 4 Water Mixed Gamma 4 Air Gross Beta 3 Air 1-131 4 Air Mixed Gamma 2 Milk 1-131 3 Milk Mixed Gamma 3 Soil Mixed Gamma 1 Vegetation Mixed Gamma 2 TOTAL SAMPLE INVENTORY 34 D.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.

D.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 the participating laboratory (0C result) to the Vendor Laboratory Known value (reference result).

D- 2

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 QC Result of Agreement Reference Result If the value falls within the agreement interval, the result is acceptable.

TABLE D2 ERROR RESOLUTION RATIO OF AGREEMENT

<4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 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. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

.D- 3

D.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8-1.

D.4.1 ECKERT & ZIEGLER ANALYTICS 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.

D- 4

D.4.2 NUMERICAL RESULTS TABLES TABLE D3 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter JAF ELAB RESULTS REFERENCE LAB*

nCi +/-1 sigma nCi +/-1 qioma I RATIO (1) 8.61EE+0I1 +/- 2.30E+00 8.15E+01 +/- 2.24E+00 804E+01 +/- 1.34E+0( 1.05 A 8.63E+O1 +/- 2.30E+00 8.46E+01 +/- 1.3 1E+00 5.99E+01 +/- i.92E+00 5.89E-OI +/- 1.9 1E+00 5.39E+01 +/- 9.01E-01 1.10 A 5.98E+O1 +/- 1.92E+00 5.95E+O1 +/- 1.11. E+00 I 9.69E+O I +/- 1.39E+00 9.46E+0 1 1.38E--00 8.92E+O I +/-- 1.49E+0( 1.07 A 9.39E+0 1 +/- 1.37E+i00

+/-

9.5 1E+01 7.98E-0 I (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 5

TABLE D3 (Continued)

Tritium Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIT pCi/liter +/-+ sigma pCi/liter +/-1 sigma RATIO (1) 3/18/2010 E7020-05 Water H-3 3.48E+03 +/- 1.53E+02 3.57E+03 +/- 1.53E+02 3.41E+03 +/- 5.70E+01 1.03 A 3.53E+03 +/- 1.53E+02 Mean= 3.53E+03 +/- 8.83E+01 06/17/2010 E7089-05 Water H-3 1.14E+03 +/- 1.33E+02 1.13E+03 +/- 1.32E+02 1.04E+03 +/- 1.32E+02 1.00E+03 +/- 1.29E+02 9.58E+02 _ 1.60E+01 1.13 A 1.07E+03 +/- 1.30E+02 1.13E+03 t 1.30E+02 Mean = 1.09E+03 +/- 5.35E+0 I 9/16/2010 E7187-05 Water H-3 8.82E+02 +/- 1.31E+02 8.54E+02 +/- 1.3 1E2 896E+02 +/- 1.50E+01 1.01 A 9.74E+02 +/- 1.32E+02 Mean= 9.03E+02 +/- 7.58E+01 12/9/2010 E7329-09 Water H-3 1.00E+04 +/- 2.04E+02 1.00E+04 +/- 2.04E+02 996E+03 +/- I 66E+0 1.00 A 9.91E+03 +/- 2.04E+02 Mean = 9.98E+03 +/- 1.18E+02 12/9/2010 E7330-09 Water H-3 9.78E+03 +/- 2.03E+02 9.83E+03 +/- 2.03E+02 9.96E+03 +/- 1.66E+01 0.99 A 1.01E+04 +/- 2.05E+02 Mean = 9.90E+03 +/- 1.18E+02 I, ) lKatlo = IKeporteul Analytlcs.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 6

TABLE D3 (Continued)

Gross Beta Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO (1) 03/18/2010 E7023-05 Water 2.58E+02 +/- 2.50E+00 GROSS 2.57E+02 +/- 2.50E+00 2.60E+02 +/- 4.35E+00 0.98 A BETA 2.54E+02 +/- 2.50E+00 Mean = 2.56E+02 +/- 1.44E+00 06/17/2010 E7095-05 Water 1.78E+02 +/- 2. 1OE+00 GROSS 178E+02 +/- 2.OE+00 1.88E+02 +/- 3.14E+00 0.95 A BETA 1.79E+02 +/- 2.1OE+00 Mean= 1.78E+02 +/- 1.21E+00 09/16/2010 E7192-05 Water 2.30E+02 +/- 2.40E+00 GROSS 2.28E+02 +/- 2.40E+00 2.26E+02 +/- 2.40E+00 2.18E+02 +/- 3.64E+00 1.04 A BETA 2.25E+02 +/- 2.40E+00 Mean = 2.27E+02 +/- 1.20E+00 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 7

TABLE D3 (Continued) 1-131 Gamma Analysis of Air Charcoal SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi +/-1I sigma pCi +/-1 sigma RATIO (1) 3/18/2010 E6993-09 Air 8.62E+O I +/- 2.23E+00 8.27E+01 +/- 2.88E+Oj 1-131 8. 1OE+-01 +/- 1.81EE+00 8.52E+01 -+/- 1.42E+00 0.99 A 8.90E+OI +/- 3.65E+00 Mean = 8.47E+Ol + 1.37E+00 06/17/2010 E7093-05 Air 7.94E+0I +/- 1.45E+00 1-131 7.64E+OI +/- 2.98E+00 798E+01 +/- 1.33E+00 0.99 A 8.08E+OI +/- 3.07E+00 Mean= 7.89E+O I +/- 1.5 1E+00 9/16/2010 E7191-05 Air 6.01E+01 +/- 1.25E+00 1-131 6.39E+O I +/- 2.24E+00 6.00E+0 I +/- 1.00E+00 1.03 A 6.06E+01 +/- 2.00E+00 Mean= 6.15E+0O1 +/- 1.08E+00 9/16/2010 E7183-09 Air 6.09E+01 _+/- 2.23E+00 1-131 6.19E+5. +/- 2.83E+00 5 97E+01 +/- 9.97E-01 1.03 A 6.08E+01 +/- 2.98E+00 Mean= 6.12E+01 +/- 1.56E+00 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 8

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water I SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. [MEDIUM IANALYSIS pCi/liter +/- I sigma pCi/liter +/- I sigma RATIO (1) 3/18/2010 E7021-05 Water 2.73E+02 + 7.49E+00 2.7 IE+02 -+/- 3.53E+00 Ce- 141 +- 2.63E+02 +/- 4.40E+00 1.04 A 2.75E+02 7.24E+00

+-

Mean = 2.73E+02 3.67E+00 3.42E+02 +/- 2.97E+01 Cr-51 3.84E+02 +/- i.29E+01 3.64E+02 +/- 6.08E+00 1.03 A 3.98E+02 +/- 2.76E+01 Mean = 3.75E+02 +/- 1.42E+01 2.03E+02 5401E+00 Cs-134 1.91E+02 +/- 5.85E+00 1.79E+02 +/- 2.99E+00 1.09 A 1.9 1E+02 +/- 3.29E+00 Mean = 1.95E+02 +/- 2.87E+00 1.64E+02 _ 5.04E+00 CsI1 .56E+02 +/- 5.67E+00 Cs-137 1 1.60E+02 +/- 5.67E+00 2.90E+00 1.59E+02 +/- 2.66E+00 1.01 A Mean = 1.60E+02 +/- 2.7 1E+00 1.47E+02 +/- 4.50E+00 1.46E+02 +/- 5.39E+00 Co-58 1.44E+02 +/- 2.40E+00 1.03 A 1.51E+02 +/- 2.73E+00 Mean = 1.48E+02 +/- 2.51E+00 2.24E+02 +/- 5.62E+00 2.24E+02 +/- 6.45E+00 Mn-54 2.22E+02 +/- 3.37E+00 2.09E+02 +/- 3.49E+00 1.07 A Mean'= 2.23E+02 +/- 3.07E+00 1.48E+02 +/- 5.43E+00 Fe-59 1.54E+02 +/- 6.52E+00 1.38E+02 +/- 2.3 IE+00 1.09 A 1.52E+02 +/- 3.26E+00 Mean = 1.5 1E+02 +/- 3.03E+00 2.92E+02 11.02E+0I Zn-652.66E+02 +/- .14E+01 2.56E+02 +/- 4.27E+00 1.09 A 2.77E+02 +/- 5.88E+00 Mean = 2.79E+02 +/- 5.45E+00 1.85E+02 +/- 3.89E+00 Co-60 1.91 E+02 1.92E+02 +/- 4.64E+00 2.41E+00

+/- 1.85E+02 - 3.08E+00 1.03 A 1.92E+02 +/- 2.41E+00

________Mean = I.90E+02 +/- 2.17E+0O0 _________

7.I iE+OI +- 7.18E-01 7.53E+0 I +/- 1.91 E+00 1-131** +-

7.22 E+0 I +/- 1.21 E+00 1.02 A 7.43E+0I 1.79E+00 Mean = 7.36E+01 +/- 9.05E-0 I (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D- 9

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. IMEDIUMIANALYSIS1 pCi/liter +/- 1 sigma pCi/liter +/-1 sigma RATIO (1) 6/17/2010 E7096-09 Water 1.70E+02 + 3.17E+00 1.74E+02 2.83E+00 Ce- 141 1.61E+02 +/- 2.68E+OC 1.07 A 1.74E+02 +/- 5.76E+00 Mean = 1.73E+02 + 2.39E+00 5.26E+02 +/- 1.5 IE+01 Cr-51 5.12E+02 +/- 1.62E-e-I 4.94E+02 +/- 8.25E+00 0.99 A 4.3 IE+02 +/- 2.96E+OI Mean = 4.90E+02 +/- 1.23E+O1 2.01EE+02 +/- 2.33E+00 1.92E+02 +/-_ 2.77E+00 Cs-134 1.2E02 2.02E+02 +/- 27E40 1.83E+02 5.04E+00 +/- 3.06E+00 1.08 A Mean = 1.98E+02 +/- 2.07E+00 2.26E+02 +/- 2.44E+00 Cs- 137 2.22E+02 +/- 2.74E+00 2.18E+02 +/- 3.65E+00 1.04 A 2.30E+02 +/- 5.25E+00 Mean= 2.26E+02 +/- 2.13E+00 1.57E+02 +/- 2.11E+00 Co-58 1.55E+02 +/- 2.49E+00 1.47E+02 +/- 2.46E+00 1.07 A 1.61E+02 +/- 4.68E+00 Mean = 1.58E+02 +/- 1.90E+00 2.71EE+02 +/- 2.63E+00 Mn-54 2.74E+02 3.01E+00 2.46E+02 +/- 4.11E+00 1.10 A 2.67E+02 +/- 5.56E+00 Mean= 2.71E+02 +/- 2.28E+00 1.89E+02 +/- 2.77E+00 Fe-59 1.91E+02 +/- 3.27E+00 1.73E+02 +/- 2.89E+00 1.08 A 1.80E+02 +/- 5.96E+00 Mean = 1.87E+02 +/- 2.45E+00 3.29E+02 +/- 4.42E+00 3.34E+,02 +/- 5.42E+00 Zn-65 3.OOE+02 +/- 5.00E+00 1.11 A 3.38E+02 +/- 1.01E+01 Mean= 3.34E+02 +/- 4.1OE+00 2.99E+02 +/- 2.06E+00 Co-60 2.99E202 +/- 2.44E.O 2.86E+02 +/- 4.78E+00 1.05 A 3.OOE+02 +/- 4.55E+00 Mean = 2.99E+02 +/- 1.85E+00 8.15E+01 +/- 2.25E400 t

8.24E+01 + 2.76E+00 1-131** 7.89E+01 +/- 1.32E+00 1.03 A 7.94E1+0 1 4-

+ 4.13E+00 Mean= 8.11E+OI i .36E+00 a a _________ & a (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D- 10

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. IMEDIUMjANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO (I) 9/16/2010 E7188-05 Water 1.77E+02 _+ 5.28E+00

-t 1.80E+02 5.73E+00 Ce- 141 1.65E+02 +/- 2.76E+00 1.09 A 1.8 1E+02 +, 3.26E+-00 Mean = 1.79E+02 + 2.82E+00 3.44E+02 +/- 2.19E+0I Cr-51 3.07E+02 2.85E-I 2.97E+02 +/- 4.95E+00 1.06 A 2.96E+02 _ 1.48E+01 Mean= 3.16E+02 11.30E+01 1.22E+02 +/- 3.92E+00 Cs- 134 1.23E+02 +/- 5.49E100 I I8E+02 +/- 1.97E+00 1.05 A 1.27E+02 +/- 2.77E+00 Mean = 1.24E+02 +/- 2.43E+00 1.26E+02 +/- 3.82E+00 Cs-137 1.28E+02 +/- 5.01E+00 1.20E+02 +/- 2.00E+00 1.05 A 1.25E+02 +/- 2.6 1E+00 Mean = 1.26E+02 +/- 2.27E+00 1.03E+02 +/- 3.43E+00 Co-58 1.02E+02 +/- 4.76E+00 9.35E+01 +/- 1.56E+00 1.09 A 1.02E+02 +/- 2.29E+00 Mean= 1.02E+02 +/- 2.10E+00 1.75E+02 +/- 4.26E+00 Mn-54 +/- 5.72E+00 1.70E+02 I.52E+02 +/- 2.53E+00 1.11 A 1.62E+02 +/- 2.88E+00 I Mean = 1.69E+02 +/- 2.56E+00 1.36E+02 +/- 4.41E+00 Fe-59 .31E+02 +/- 6.05E+00 1.16E+02 +/- 1.93E+00 1.13 A 1.25E+02 +/- 3.16E+00 Mean= 1.31EE+02 +/- 2.71E+00 2.98E+02 +/- 8.60E+00 Zn-65 2.99E+02 +/- 1.18E+01 2.59E+02 +/- 4.32E+00 1.11 A 2.69E+02 +/- 5.86E+00 Mean = 2.89E+02 +/- 5.24E+00 2.3 1E+02 +/- 3.65E+00 Co-60 2.29E+02 +/- 4.92E+00 2.17E+02 +/- 3.62E+00 1.06 A 2.28E+02 +/- 2.54E+00 Mean= 2.29E+02 +/- 2.21E+00 6.90E+0 1 +/-

1.37E+00 6.42E+0 I +_ 1.45E+00 1-131 ** +/- 6.44E+0 I +/- 1.08E+00 1.03 A 6.61 E+O I 9.53E-01

+/-

Mean = 6.64E+01 7.37E-0 1 (1)Ratio = Reported/Analytics.

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* I DATE I ID NO. JMEDIUMIANALYSIS1 pCi/Iiter +/-t sigma I pCi/liter +/-1 sigma I RATIO(1) 12/9/2010 E7331-09 Water 4.9 1E+02 + 2.87E+O I 5.43E+02 +/- 3.76E+0 I Cr-51 5.16E+02 + 2.87E+O I 4.55E+02 +/- 7.59E+00 1.10 A 4.58E+02 -+ I .97E+0 I Mean = 5.02E+02 1.47E+01I 1.69E+02 +/- 5.25E+00 1.67E+02 +/- 6.23E+00 Cs-134 1.65E+02 +/- 4.60E+00 1.57E+02 +/- 2.62E+00 1.07 A 1.74E+02 +/- 3.22E+00 Mean= 1.69E+02 +/- 2.47E+00 1.75E+02 +/- 4.94E+00 1.72E+02 +/- 5.94E+00 Cs-137 1.92E+02 +/- 4.68E+00 1.86E+02 +/- 3.10E+00 0.97 A 1.80E+02 +/- 3.30E+00 Mean= 1.80E+02 +/- 2.40E+00 1.00E+02 +/- 4.24E+00 9.84E+01 _+/- 4.80E+00 Co-58 8.82E+01 +/- 3.81E+00 9.OOE+01 +/- 1.50E+00 1.06 A 9.50E+01 _+/- 2.65E+00 Mean = 9.54E+01 +/- 1.98E+00 1.27E+02 +/- 4.46E+00 1.28E+02 +/- 5.50E+00 Mn-54 1.35E+02 +/- 4.23E+00 1.19E+02 +/- 1.99E+00 1.09 A 1.29E+02 +/- 3.09E+00 Mean= 1.30E+02 +/- 2.20E+00 1.45E+02 +/- 5.91E+00 1.52E+02 +/- 7.49E+00 Fe-59 1.63E+02 +/- 5.62E+00 1.31E+02 +/- 2.18E+00 1.16 A 1.48E+02 +/- 3.96E+00 Mean= 1.52E+02 +/- 2.94E+00 1.84E+02 +/- 8.7 1E+00 1.98E+02 +/- 1.17E+01 Zn-65 1.78E+02 +/- 8.42E+00 1.74E+02 +/- 2.90E+00 1.08 A 1.94E+02 +/- 5.99E+00 Mean = 1.89E+02 +/- 4.47E+00

3. 1OE+02 +/- 4.96E+00 3.17E+02 +/- 6.06E+00 Co-60 3.09E+02 +/- 4.57E+00 3.OOE+02 +/- 5.01E+00 1.04 A 3.11E+02 +/- 3.28E+00 Mean= 3.12E+02 +/- 2.41EE+00 1.02E+02 +/- 4.19E+00 1.02E+02 +/- 3.81 E+00 1-131** 1.00E+02 +/- 1.67E+00 1.01 A 9.89E+01 --+ 3.5 1E+00

_+/-

Mean= 1.01E+02 2.22E+00 (I) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D- 12

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk I SAMPLE L E JAF ELAB RESULTS REFERENCE LAB*

DATE 4 ID NO. MEDIUI4ANALYSI: pCi/liter +/-1 sigma pCi/liter+/-1 sigma RATIO(l) 3/18/2010 E6994-09 MILK 2.68E+02 +/- 5 .38E-i-(

2.57E+02 5.37E+0(

Ce- 141 2.68E+02 +/- 1.13E+0 I 2.6IE+02 +/- 4.36E+00~ 1.04 A 2.89E+02 _+ 1.22E-e-0I Mean = 2.70E+02 +/- 4.5 X+fl{

3.55E+02 +/- 2.53E+01 3.72E+02 +/- 2.34E+0I Cr-51 3.55E+02 +/- 5.27E+0I 3.61E+02 +/- 6.03E+01 0.93 A 2.65E+02 +/- 5.45E+01 Mean= 3.37E+02 +/- 2.08E+01 1.79E+02 +/- 3.95E+0(

1.79E+02 +/- 4.62E+0(

Cs-134 1.88E+02 +/- 9.01E+00 i.78E+02 +/- 2.97E+00 1.00 A 1.68E+02 +/- 9.01E+0(

I Mean = 1.78E+02 +/- 3.53E+0(

1.60E+02 +/- 3.88E+O 1.51E+02 +/- 3.78E+0(

Cs-137 1.64E+02 +/- 8.33E+0* 1.58E+02 +/- 2.64E+0 1.02 A 1.68E+02 +/- 8.03E+0(

Mean= 1.61E+02 +/- 3.19E+0(

1.44E+02 +/- 4.03E+0(

1.39E+02 +/- 3.85E+0(

Co-58 1.47E+02 +/- 8.42E+0( 1.43E+02 +/- 2.38E+0 1.00 A 1.43E+02 +/- 7.40E+0(

Mean= 1.43E+02 +/- 3.13E+0(

2.15E+02 +/- 4.39E+0(

2.22E+02 +/- 4.68E+0(

Mn-54 2.24E+02 +/- 9.49E+0( 2.07E+02 +/- 3.46E+0 1.04 A 2.01E+02 +/- 8.96E+0(

Mean= 2.15E+02 +/- 3.64E+0(

1.58E+02 +/- 5.27E+0(

1.44E+02 +/- 5.27E+0(

Fe-59 1.66E+02 +/- 1.03E+0I 1.37E+02 +/- 2.29E+0 1.08 A 1.25E+02 +/- 9.9 1E+0C Mean = 1.48E+02 +/- 4,03E+0(

2.67E+02 +/- 8.17E+0(

2.75E+02 +/- 8.77E+0C Zn-65 2.56E+02 +/- 1.73E+01 2.54E+02 +/- 4.24E+0 1.05 A 2.70E+02 +/- 1.75E+0I Mean = 2.67E+02 +/- 6.84E +_

1.79E+02 +/- 3.25E+(

1.83E+02 +/- 3.41E+0C Co-60 1.81E+02 +/- 6.73E+0C 1.83E+02 +/- 3.06E+0 0.99 A 1.82E+02 +/- 6.34E+-0 Mean= 1.81E+02 +/- 2.59E+-0 6-62E+i0 I + 7.99E+0C 1-131** 7.40E+0 I + 4.47E+OC 7.40E+01 +/- 1.24E+0H) 0.95 A 6.96E+0 I + I .09E+0 I

-+

3.56E+OC (I) Ratio = Reported/Analytics. Mean = 6 9()E-4..()!

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D- 13

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. IMEDIUMI ANALYSISI pCi/liter +/-1 sigma pCi/liter +/-1 sigma I RATIO (I) 06/1 7/20 10 E7091-05 MILK 1.25E+02 +/- 6.24E+00 I. 12E+02 + 3.98E+00 Ce- 141 1.1OE-i02 +/- 1.84E+OV 1.08 A 1.20E+02 -- + 3.14E+00 Mean = 1. 19E+02 +/- 2.68E+00 3.59E+02 +/- 2.85E+01 Cr-51 3.27E+02 +/- 1.O1E+01 3.39E+02 + 5.66E+00 1.03 A 3.62E+02 +/- 1.54E+01 Mean= 3.49E+02 +/- 1.27E+01 1.42E+02 +/- 4.64E+00 Cs-134 1.31E+02 +/- 3.44E+00 1.26E+02 _ 2.1OE+00 1.07 A 1.32E+02 +/- 2.43E+00 Mean 1.35E+02 +/- 2.09E+00 1.49E+02 +/- 4.82E+00 Cs-137 1.51E+02 +/- 3.23E+00 1.50E+02 +/- 2.5 1E+00 1.00 A 1.48E+02 +/- 2.48E+00 Mean= 1.49E+02 + 2.1OE+00 1.16E+02 +/- 4.40E+00 Co-58 1.06E3+02 3.02E+00 1.OIE+02 1I.69E+00 1.09 A 1.09E+02 +/- 2.34E+00 Mean= 1.1OE+02 _ 1.94E+00 1.87E+02 +/- 5.30E+00 Mn-54 1.84E+02 3.59E+00 1.69E+02 _ 2.82E+00 1.09 A 1.82E+02 +/- 2.67E+00 Mean= 1.84E+02 . 2.31E+00 1.34E+02 +/- 5.6 1E+00 Fe-59 1.24E+02 +/- 4..OE+00 1 19E+02 +/- 1.98E+00 1.10 A 1.34E+02 +/- 3.04E+00 Mean= 1.31E+02 +/- 2.53E+00 2.37E+02 +/- 8.94E+00 Zn-65 2.17E-02 +/- 6.80E+00 206E+02 +/- 3.44E+00 1.10 A 2.25E+02 +/- 4.84E+00 Mean = 2.26E+02 +/- 4.08E+00 1.97E+02 +/- 4.13E+00 2.05E+02 +/- 2.91E+00 Co-60 2.05E+02 +/- 2.2 1E+00 1.97E+02 +/- 3.28E+00 1.02 A 2.O0E+02 +/- 2.2 1E+00 Mean = 2.0 1E+02 +/- 1.84E+00

+/-

9.92E+01I 5.23E+00 1-131 9.79E+0 I 3.75E+00 9.89E+01I +/- 2.61 E+00

+

7.87E+01I 2.26E+00 9.69E+01 +/- 1.62E+00 0.92 A 8.03E+01I -+l 2.25E+00 1-131**

7.97E+01I +/- 2.65E+00 a a a a Mean= 8.91E+01 1.35E+00 a &

(I) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D- 14

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE MEIMJAF ELAB RESULTS REFERENCE LAB*

DATE 1 ID NO. AMEDIUMNALYSIS pCi/liter +/-! sigma pCi/liter I1sigma I RATIO (1) 9/16/2010 El 190-05 MILK 1.35E+02 +/- 4.99E+00 1.40E+02 6.52E+00 Ce- 141 1.34E+02 2.58E+00 1.30E+02 +/- 2.17E+00 1.05 A 1.35E+02 +/- 5.26E+00 Mean = I 36F.4-09 2 52 F.4-fl 2.49E+02 +/- 2.21E+O1 2.27E+02 +/- 2.7 1E+O1 Cr-51 2.33E+02 +/- 1.05E+0I 2.34E+02 +/- 3.90E+00 0.99 A 2.16E+02 +/- 2.56E+01 Mean= 2.31E+02 +/- 1.IIE+0I 9.92E+01 +/- 4.27E+00 8.97E+01 t+/- 4.93E+00 Cs-134 9.70E+0I +/- 1.86E+00 9.30E+01 +/- 1.55E+00 1.03 A 9.80E+01 +/- 4.44E+00 Mean= 9.60E+01 +/- 2,03E+00 9.91E+01 +/- 3.97E+00 9.37E+01 +/- 4.70E+00 Cs-137 9.49E+01 +/- 1.85E+00 9.45E+01 +/- 1.58E+00 1.01 A 9.23E+0 I +/- 4.43E+00 Mean= 9.50E+01 +/- 1.95E+00 8.06E+-0 I +/- 3.62E+00 7.76E+01 +/- 4.54E+00 Co-58 7.55E+01 +/- 1.63E+00 7.37E+01 +/- 1.23E+00 1.03 A 7.04E+O1 +/- 4.30E+00 Mean= 7.60E+01 +/- 1.85E+00 1.22E+02 +/- 4.15E+00

1. 18E+02 +/- 5.14E+00 Mn-54 1.28E+02 +/- 2.02E+00 1.19E+02 +/- 1.99E+00 1.03 A i.24E+02 +/- 5.06E+00 Mean= 1.23E+02 +/- 2.14E+00 9.75E+01 +/- 4.86E+00 1.14E+02 +/- 6.59E+00 Fe-59 1.03E+02 +/- 2.32E+00 9.1IE+01 +/- 1.52E+00 1.14 A 1.01E+02 +/- 5.87E+00 Mean = 1.04E+02 +/- 2.58E+00 2.16E+02 +/- 8.69E+00 1.79E+02 +/- 1.13E+01 Zn-65 2.20E+02 +/- 3.99E+00 2.04E+02 +/- 3.40E+00 1.01 A 2.12E+02 +/- 1.05E+01 Mean= 2.07E+02 +/- 4.54E+00 1.79E+02 +/- 3.90E+00 1.82E+02 +/- 4.79E+00 Co-60 1.73E+02 +/- 1.78E+00 1.71E+02 _ 2.85E+00 1.03 A 1.70E+02 +/- 4.43E+00 Mean = 1,76E+02 +/- 1.95E+00_

8.62E+01 +/- 1.6 I E+00 8.50E+O 1 1.23E+00 1-131** 9.41E+01 +/- 1.57E+0¢ 0.91 A 8.61E+01 + 1.67E+00 Mpazn R F-*-flI g R 7 1F--1 Mean RiRP-j4l (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D- 15

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPAR[SON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUIJANALYSLI pCi +/- I sigma pCi +/-I sigma RATIO (1) 3/18/2010 E7022-05 FILTER 2.08E+02 +/- 3.64E+00 2.18E+02 3.88E+00 Ce- 141 2.04E+02 +/- 3.40E+O( 1.05 A 2.14E+02 t 4.19E+00 Mean= 2.13E+02 2.26E+00 2.97E+02 +/- 1.61E+01 Cr-51 2.57E-02 +/- 1.62E+01 2.81E+02 +/- 4.70E+0( 1.02 A 3.07E+02 +/- 1.80E+01 Mean = 2.87E+02 +/- 9.69E+00 1.55E+02 +/- 4.98E+00 Cs-134 1.50E+02 +/- 5.13E+00 1.38E+02 +/- 2.31E+0( 1.09 A 1.48E+02 +/- 5.24E+00 Mean= 1.51E+02 +/- 2.95E+00 1.25E+02 +/- 3.96E+00 Cs-137 1,32E+02 +/- 4.21E+00 1.23E+02 +/- 2.05E+0( 1.02 A 1.21E+02 +/- 4.14E+00 Mean= 1.26E+02 +/- 2.37E+00 1.16E+02 +/- 3.89E+00 Co-58 1..17E+02 +/- 4.01E+00 1 11E+02 +/- 1.86E+0( 1.05 A 1.18E+02 +/- 3.93E+00 Mean= 1.17E+02 +/- 2.28E+00 1.76E+02 +/- 4.64E+00 Mn-54 1.84E+02 +/- 5.17E+00 1.62E+02 +/- 2.70E+0( 1.10 A 1.77E+02 +/- 4.98E+00 Mean= 1.79E+02 +/- 2.85E+00 1.22E+02 +/- 4.88E+00 Fe-59 1.16E+02 +/- 5.13E+00 1.07E+02 +/- 1.78E+0 1.12 A 1.23E+02 +/- 5.25E+00 I Mean = 1.20E+02 +/- 2.94E+00 2.31E+02 +/- 8.72E+00 Zn-65 2.28E+02 +/- 9.46E+00 I.98E+02 +/- 3.30E+0 1.12 A 2.05E+02 +/- 8.99E+00 Mean = 2.21E+02 +/- 5.23E+00 I 1.36E+02 -+

3.50E+00 1.37E+02 +/-

Co-60 3.73E+00

+/- 1.43E+02 +/- 2.38E+0( 0.97 A 1.43E+02 3.59E+00

_____________ a _____________ I Mean = I.39E+02 +

209F+00 B (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D - 16

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE SMEDIUMI ID NO. ANALYSISI pCi +/-1 sigma pCi +/-1 sigma RATIO (1) 9/1 6/2010 E7189-05 FILTER. 1.28E+02 +/- 2.65E+00 1.30E+02 +/- 2.67E+00 Ce- 141 1.26E+02 +/- 12.10E+00 1.02 A 1.26E+02 + 1.38E+00 Mean = 1.28E+02 1.34E+00 2.28E+02 +/- 1.35E+O1 2.28E+02 +/-- 1.38E+01 Cr-51 2.31E+02 2.31IE+02 6.90E+00 2.26E+02 +/- 3.77E+00

+/- 6.90E+00

+/- 1.01 A Mean = 2.29E+02 +/- 6.83E+00 1.02E+02 +/- 3.84E+00 Cs-134 9.09E+OI +/- 3.81E+0 8.98E+01 +/- 1.50E+00 1.10 A 1.04E+02 +/- 1.68E+00 Mean = 9.90E+01 .+/- 1.89E+00 8.80E+O1 +/- 3.28E+00 Cs-137 8.79E+9. +/- 3.17E+00 9.13E+01 +/- 1.52E+00 0.98 A 9.29E+01 +/- 1.47E+00 Mean = 8.96E+OI +/- 1.60E+00 7.25E+OI +/- 2.96E+00 Co-58 7.27E+7. +/- 2.96E+00 7.12E+01 +/- 1.19E+00 1.03 A 7.5 1E+01 +/- 1.38E+00 Mean = 7.34E+01 +/- 1.47E+00 1.24E+02 +/- 3.84E+00 Mn-54 1.25E+02 +/- 3.94E+00 1.15E+02 +/- 1.93E+00 1.09 A 1.26E+02 +/- 1.76E+00 Mean = 1.25E+02 +/- 1.93E+00 1.02E+02 +/- 4.39E+00 Fe-59 1.05E+02 .456E+00 8.81E+01 +/- 1.47E+00 1.17 A 1.02E+02 1I.92E+00 Mean = 1.03E+02 +/- 2.20E+00 2.24E+02 +/- 8.24E+00 Zn-65 2.22E+02 +/- 8.46E+00 1.97E+02 +/- 3.29E+00 1.14 A 2.27E+02 +/- 3.58E+00 Mean = 2.24E+02 +/- 4.1 IE+00

+

1.70E+02 3.58E+00

+

1.63E+02 3.54E+00 Co-60 "+ 1.65E+02 +/- 2.75E+00 1.02 A 1.70E+02 i .56E+00

+/-

Mean = 1.68E+02 1.76E+00 (I) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analy tics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 17

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil SAMPLE JAF ELAB RESULTS REFERENCE LAB* I DATE ID NO. 4MEDIUMjIANALYSISJ. pCi/g +/-1 sigma pCi/g +/-1 sigma I RATIO (1) 6/17/2010 E7092-05 SOIL 2.89E-01 +/- 1.03E-02 2.47E-0 I + 11.73E-02 Ce- 141 2.33E-01 + 2.38E-02 2.5 1E-0 I +/- 4.19E-03 1.05 A 2.87E-0I +/- 1.09E-02 Mean = 2.64E-01 + 8.26E-03 8.52E-01 +/- 5.18E-02 Cr-51 8.56E-0I +/- 9.65E-02 7.7E-01 +/- 1.29E-02 1.13 A 9.16E-01 +/- 5.34E-02 Mean = 8.75E-0 1 +/- 4.06E-02 3.19E-01 +/- 7.72E-03 3.23E-01 +/- 1.48E-02 Cs-134 3.45E-01 +/- 2.16E-02 2.86E-01 +/- 4.78E-03 1.15 A 3.29E-01 +/- 8.49E-03 Mean= 3.29E-01 +/- 7.15E-03 4.44E-01 +/- 8.48E-03 4.63E-01 +/- 1.71E-02 Cs-137 4.52E-01 +/- 2.36E-02 4.32E-01 +/- 7.21E-03 1.05 A 4.52E-01 +/- 9.04E-03

_ Mean = 4.53E-0I +/- 7.92E-03 2.54E-01 +/- 6.62E-03 2.62E-01 1.44E-02 Co-58 2.36E-01 +/- 2.06E-02 2.30E-01 +/- 3.84E-03 1.08 A 2.37E-01 +/- 7.68E-04 Mean = 2.47E-0I +/- 6.50E-03 4.17E-01 +/- 8.49E-03 3.97E-01 +/- 1.66E-02 Mn-54 4.15E-01 +/- 2.33E-02 3.85E-01 +/- 6.43E-03 1.07 A 4.21E-01 +/- 8.54E-03 Mean = 4.13E-01 +/- 7.76E-03 3.01E-01 +/- 9.44E-03 3.01E-01 +/- 1.97E-02 Fe-59 2.71E-01 +/- 2.89E-02 2.70E-01 + 4.51E-03 1.09 A 3.03E-01 +/- 1.02E-02 Mean= 2.94E-0I +/- 9.41E-03 5.12E-01I 1.43E-02 4.94E-01 +/- 2.83E-02 Zn-65 5.36E-01 +/- 4.23E-02 4.68E-01 +/- 7.82E-03 1.09 A 5.07E-01 +/- 1.48E-02 Mean = 5.12E-01I 1.37E-02 4.74E-01 +

6.60E-03 4.56E-0 I 1.36E-02 Co-60 4.78E-0 I +/-

1.93E-02 4.47E-0 I +/- 7.46E-03 1.05 A 4.68E-01 ::1 6.79E-03 Mean = 4.69E-01 6.36E-03 (1) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 18

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB* I DATE ID NO. IMEDIUM ANALYSISI pCi/g +/-1 sigma pCi/g +/-1 sigma RATIO (1) 6/20/2010 E7094-05 VEG 2.06E-0 I + 9.86E-03 2.03E-0 I + I. 14E-02 Ce- 141 2.21E-01 +/- 3.69E-03 0.94 A 2.15E-01 + 6.1 OE-03 Mean = 2.08E-01 + 5.42E-03 5.72E-01 +/- 4.94E-02 Cr-51 6.32E-0I +/- 6.34E-02 6.80E-01 +/- 1.14E-02 0.88 A 6.00E-01 -+/- 3.30E-02 Mean = 6.0 1E-0 I +/- 2.90E-02 2.68E-01 +/- 9.60E-03 Cs-134 2.66E-0 I 1.36E-02 252E-01 +/- 4.21E-03 1.08 A 2.81E-01 +/- 7.29E-03 Mean= 2.72E-01 +/- 6.06E-03 2.83E-01 +/- 9.37E-03 Cs-137 2.91E-0 I 1.23E-02 3.01E-01 +/- 5.03E-03 0.95 A 2.84E-01 .+/- 6.37E-03 Mean = 2.86E-01 _+/- 5.57E-03 2.02E-01 +/- 8.49E-03 Co-58 2.09E-0 1.89E-0I1 +/- 1.11E-02 1.14E-03

+/- 2.03E-01 +/- 3.39E-03 0.99 A 1.89E-01 +/- 5.44E-03 Mean = 2.OOE-01 +/- 5.OOE-03 3.49E-01 +/- 1.04E-02 Mn-54 3.36E-0 I 1.35E-02 3.39E-01 +/- 5.66E-03 1.00 A 3.34E-01 +/- 7.03E-03 Mean = 3.40E-0I +/- 6.14E-03 2.33E-01 +/- 1.17E-02 Fe-59 2.25E-01 1.50E-02 2.38E-01 +/- 3.97E-03 0.98 A 2.39E-01 +/- 7.96E-03 Mean = 2.32E-01 +/- 6.87E-03 4.18E-01 1.89E-02 Zn-65 4.27E-0 I 2.48E-02 4.12E-01 +/- 6.88E-03 1.02 A 4.16E-01 +/- 1.35E-02 Mean = 4.20E-01 +/- 1.13E-02 3.77E-0 I +

8.39E-03 3.82E-01 1. 12E-02 Co-60 3.94E-01 +/- 6.58E-03 0.97 A 3.84E-0 I +/- 5.8 IE-03 Mean= 3.81E-01 5.05E-03 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 19

TABLE D3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. IMEDIUM JANALYSIS I pCi/g +/- 1 sigma pCi/g +/- I sigma I RATIO (1) 9/1612010 E7184-09 VEG 4.78E-01 +/- 1.16E-02 5.20E-0 I +/- 2.06E-02 Ce- 141 5.09E-0 I +/- 1.92E-02 4.79E-01 +/- 8.OOE-03 1.05 A 5.OOE-01 +/- 1.45E-02 Mean = 5.02E-01 +/- 8.43E-03 8.81E-O +/- 5.64E-02 9.73E-01 11.07E-01 Cr-51 9.45E-01 +/- LOIE-0l 8.59E-01 +/- 1.43E-02 1.08 A 9.13E-01 +/- 6.68E-02 Mean = 9.28E-01 +/- 4.28E-02 3.98E-01 +/- 1.16E-02 3.54E-01 +/- 2.20E-02 Cs- 134 3.88E-01 +/- 2.19E-02 3.42E-01 +/- 5.71E-03 1.13 A 4.08E-01 +/- 1.40E-02 Mean = 3.87E-01 +/- 8.99E-03 3.6 1E-0I +/- 1.05E-02 3.42E-01 +/- 1.85E-02 Cs-137 3.41E-01 +/- 1.83E-02 3.47E-01 +/- 5.79E-03 1.01 A 3.57E-01 +/- 1.30E-02 Mean = 3.50E-61 - 7.73E-03 3.03E-01 +/- 1.01E-02 2.48E-01 +/- 1.75E-02 Co-58 2.63E-01 +/- 1.83E-02 2.71E-01 +/- 4.53E-03 1.03 A 3.07E-01 +/- 1.22E-02 Mean = 2.80E-01 +/- 7.47E-03 5.04E-01 +/- 1.23E-02 4.83E-01 +/- 2.12E-02 Mn-54 4.79E-01 +/- 2.12E-02 4.39E-01 +/- 7.33E-03 1.10 A 4.68E-01 +/- 1.42E-02 Mean = 4.84E-01 +/- 8.85E-03 3.87E-01 - 1.39E-02 4.28E-01 +/- 2.64E-02 Fe-59 3.99E-01 +/- 2.48E-02 3.35E-01 +/- 5.59E-03 1.18 A 3.66E-01 +/- 1.65E-02 Mean = 3.95E-01 +/- 1.05E-02 8.15E-01 +/- 2.57E-02 8.02E-0 I +/- 4.46E-02 Zn-65 7.65E-01 +/- 4.48E-02 7.49E-01 +/- 1.25E-02 1.06 A 7.82E-01 +/- 3.00E-02 Mean= 7.91E-01 +/- 1.86E-02 6.60E-0 I 1.11E-02 1.

6.69E-0 1 +/- 1.95E-02 Co-60 6.87E-01 +/- 1.94E-02 6.28E-01 +/-t 1.05E-02 1.06 A 6.39E-01 11.25E-02 Mean = 6.64E-0 I +/- 8.05E-03 (I) Ratio = Reported/Analytics.

I I I h (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable D- 20

D.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 P.O. Box 30712, Charleston, SC 29417 843.556.8171

Laboratories LLC 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: February 15, 2011 Martha J. Harrison Date Quality Assurance Officer Approved By: February 15, 2011 Robert L. Pullano Date Director, Quality Systems

I!Laboratories LLC 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 C ross-C heck ............................................................................................ ..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 P rog ra m .......................................................................................................................... 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 . R efere nce s .................................................................................................................... 12

Laboratories LLC 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 ANALYTICS PERFORMANCE EVALUATION RESULTS

3. 2010 DEPARTMENT OF ENERGY MIXED ANALYTE 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

3. TRITIUM PERFORMANCE EVALUATION RESULTS AND % BIAS

4. IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS

5. STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND % BIAS

6. GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS

7. GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS

Laboratories LLC 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 servicelab, 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.

This report entails the quality assurance program for the proficiency testing and environmental monitoring aspects of GEL for 2010. GEL's QA Program is designed to monitor the quality of analytical processing associated with environmental, radiobioassay, effluent (10 CFR Part 50), and waste (10 CFR Part 61) sample analysis.

This report covers the category of Radiological Environmental Monitoring Program (REMP) and includes:

" Intra-laboratory QC results analyzed during 2010.

Inter-laboratory QC results analyzed during 2010 where known values were available.

Laboratories LLC 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 Proficiency study.

" ERA's InterLaB RadCheM Proficiency Testing Program for radiological analyses.

This program completes the process of replacing the 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

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 7 of 51 emitters, Gross Alpha/Beta, Iodine-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-EO01. 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. Internal 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 may or 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 addition, prospective customers audit GEL during pre-contract audits. GEL hosts several external audits each year for both our clients and other programs. These programs include environmental monitoring, waste characterization, and radiobioassay. The following list of programs may audit GEL at least annually or up to every three years depending on the program.

NELAC, National Environmental Laboratory Accreditation Program

DOECAP, U.S. Department of Energy Consolidated Audit Program

DOELAP, U.S. Department of Energy Laboratory Accreditation Program

DOE QSAS, U.S. Department of Energy, Quality Systems for Analytical Services

ISO/IEC 17025

I Laboratories LLC 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 ERA/ELAP), 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 any one 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 AlphaLIMS. We also measure precision with matrix duplicates and/or 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 activity levels exceeding the contract required detection limit (CRDL).

6. Quality Control Program for Environmental Sample Analysis GEL's internal QA Program is designed to include QC functions such as instrumentation calibration checks (to 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

I Laboratories LLW P.O. Box 30712, Charleston, SC 29417 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 (DUP 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 MDC. 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 MDC and the other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below the MDC. The RPD must be 100%

or less. In the situation where both results are above the MDC but one result is greater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to 20%. If both results are below MDC, then the limits on % RPD are not applicable.

Difference (%) = (high duplicate result - low duplicate result)

100 %

(average of results)

7. 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.

Laboratories LLC 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 Iodine-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 Iron-59 in milk. For the corrective action associated with the Iron-59 failure, refer to CARR1 10209-542 (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 region of interest that was not included in the data result. Approximately 400 additional counts should have been included. For the remaining isotopic failures, the error was attributed to analyst error and failure to follow the instructions from the PT provider.

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.

Laboratories LLC P.O. Box 30712, C hiareston, 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 CARRIO0318-487 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, Iodine-1 31 in water (two), Strontium-89 in water, and Radium-226 in water.

For the corrective actions associated with NY-337, refer to corrective action CARR101203-525 (Table 9). For Cesium-134, Iodine-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.

In addition, GEL (Lab ID# E87156, Lab Code# SCO0012) 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 906.0, EPA 1984 00-02

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 12 of 51

" Gross Beta: EPA 900.0

Iodine-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 radionuclides. 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.

Any employee at GEL can identify and report a nonconformance and request that corrective action be taken. Any GEL employee can participate on a corrective action team as requested by the QS team or Group Leaders. The steps for conducting corrective action are detailed in GL-QS-E-002. In the event that correctness or validity of the laboratory's test results in doubt, the laboratory will take corrective action. If investigations 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.

! Laboratories LLC 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-B-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 AIphaLIMS 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. ISO/IEC 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 B, 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 LLC 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 Range/

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation RAD - 80 1"/2010 Water pCi/L Barium-133 73.5 72.9 61.0- 80.2 Acceptable RAD - 80 1"/2010 Water pCi/L Cesium-134 69.2 63.4 51.5- 69.7 Acceptable RAD - 80 1"/2010 Water pCi/L Cesium-137 118.0 120 108- 134 Acceptable RAD - 80 1" / 2010 Water pCi/L Cobalt-60 87.7 90 81 - 101 Acceptable RAD - 80 1"t /2010 Water pCi/L Gross Alpha 51.3 42.5 22.0 - 53.9 Acceptable RAD - 80 1"/2010 Water pCi/L Gross Beta 52.0 54.2 37.0-61.1 Acceptable RAD - 80 1"s/2010 Water pCi/L Iodine-131 30.5 28.2 23.5-33.1 Acceptable RAD - 80 11"/2010 Water pCi/L Radium-226 16.9 17.8 13.2-20.3 Acceptable RAD - 80 1 /2010 Water pCi/L Radium-228 20.4 18.2 12.3- 21.8 Acceptable Not RAD - 80 lt /2010 Water pCi/L Strontium-89 37.9 53.3 42.3-60.9 Acceptable Not RAD - 80 1" / 2010 Water pCi/L Strontium-90 52.3 42.2 31.1 - 48.4 Acceptable RAD - 80 1" /2010 Water pCi/L Tritium 19200 18700 16400-20600 Acceptable RAD - 80 1I / 2010 Water pCi/L Uranium (Nat) 49.0 50.2 40.7 - 55.8 Acceptable Uranium (Nat)

RAD - 80 1V"/2010 Water ug/L Mass 67.3 73.2 59.4- 81.4 Acceptable RAD - 80 1" / 2010 Water pCi/L Zinc-65 213.0 210 189-246 Acceptable E6922-278 2d / 2010 Cartridge pCi Iodine-131 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 2"d / 2010 Milk pCi/L Iodine-131 8.25E+01 8.73E+01 0.95 Acceptable E6925-278 2d /2010 Water pCi/L Iodine-131 1.OOE+02 9.61E+01 1.04 Acceptable E6924-278 2rd /2010 Milk pCi/L Iron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2d /2010 Water pCi/L Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2r / 2010 Milk pCi/L Manganese-54 1.83E+02 1.78E+02 1.03 Acceptable E6925-278 2" /2010 Water pCi/L Manqanese-54 1.90E+02 1.79E+02 1.06 Acceptable E6923-278 2rd /2010 Milk pCi/L Strontium-89 9.73E+01 1.31E+02 0.75 Acceptable E6923-278 2"' / 2010 Milk pCi/L Strontium-90 1,38E+01 1.79E+01 0.77 Acceptable E6924-278 2d / 2010 Milk pCi/L Zinc-65 3.68E+02 3.45E+02 1.07 Acceptable E6925-278 2 "d/ 2010 Water pCi/L Zinc-65 3.72E+02 3.48E+02 1.07 Acceptable E6924-278 24 /2010 Milk pCi/L Cerium-141 2.01E+02 2.02E+02 0.99 Acceptable E6925-278 2r" /2010 Water pCi/L Cerium-141 2,04E+02 2.04E+02 1.00 Acceptable E6924-278 24 /2010 Milk pCi/L- Cesium-134 2.41E+02 2,53E+02 0.95 Acceptable E6925-278 2" / 2010 Water pCi/L Cesium-134 2.56E+02 2,55E+02 1.00 Acceptable E6924-278 2'" /2010 Milk pCi/L Cesium-137 1.71E+02 1.79E+02 0.96 Acceptable E6925-278 2" / 2010 Water pCi/L Cesium-137 1.81E+02 1.81E+02 1.00 Acceptable E6924-278 2r / 2010 Milk pCi/L Cobalt-58 2.03E+02 2.11 E+02 0.96 Acceptable E6925-278 2 nr / 2010 Water pCi/LI Cobalt-58 2.19E+02 2.13E+02 1.03 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 15 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation E6924-278 2nd /2010 Milk pCiA/ Cobalt-60 2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2 nd /2010 Water pCi/L Cobalt-60 2.67E+02 2.58E+02 1.03 Acceptable E6924-278 2" /2010 Milk pCi/L Cr-51 5.54E+02 5.48E+02 1.01 Acceptable E6925-278 2 'd /2010 Water pCi/L Cr-51 5.78E+02 5.54E+02 1.04 Acceptable E7054-278 2rd /2010 Milk pCi/L Cerium-141 2.61E+02 2.61E+02 1.00 Acceptable E7055-278 21 / 2010 Water pCi/L Cerium-141 2.78E+02 2.63E+02 1.06 Acceptable E7054-278 2'd /2010 Milk pCi/L Cesium-134 1.76E+02 1.78E+02 0.99 Acceptable E7055-278 2nd /2010 Water pCi/L Cesium-134 1.85E+02 1.79E+02 1.03 Acceptable E7054-278 2 "d /2010 Milk pCi/L Cesium-137 1.61 E+02 1.58E+02 1,02 Acceptable E7055-278 2 nd /2010 Water pCi/L Cesium-137 1.71E+02 1.59E+02 1.07 Acceptable E7054-278 2 n' /2010 Milk pCi/L Cobalt-58 1.45E+02 1.43E+02 1.02 Acceptable E7055-278 2 rd /2010 Water pCi/L Cobalt-58 1.51E+02 1.44E+02 1.05 Acceptable E7054-278 2 rd / 2010 Milk pCi/L Cobalt-60 1.90E+02 1.83E+02 1.04 Acceptable E7055-278 2e / 2010 Water pCi/L Cobalt-60 1.94E+02 1.85E+02 1.05 Acceptable E7054-278 2d* /2010 Milk pCi/L Cr-51 3.81E+02 3.61E+02 1.05 Acceptable E7055-278 2 rd / 2010 Water pCi/L Cr-51 3.86t+02 3.64E+02 1.06 Acceptable E7052-278 2 na / 2010 Cartridge pCi Iodine-131 8.58E+01 8.54E+01 1.00 Acceptable E7054-278 2 rd / 2010 Milk pCi/L Iodine-131 6.91E+01 7.40E+01 0.93 Acceptable E7055-278 2e / 2010 Water pCi/L Iodine-131 8.12E+01 7.22E+01 1.12 Acceptable E7054-278 2n' /2010 Milk pCi/L Iron-59 1.60E+02 1.37E+02 1.17 Acceptable E7055-278 2nd / 2010 Water pCi/L Iron-59 1.60E+02 1.38E+02 1.16 Acceptable E7054-278 2 d /2010 Milk pCi/L Manganese-54 2.10E+02 2.07E+02 1.01 Acceptable E7055-278 2 nd / 2010 Water pCi/L Manganese-54 2.30E+02 2.09E+02 1.1 Acceptable E7053-278 2 d /2010 Milk pCi/L Strontium-89 7.91E+01 9.28E+01 0.85 Acceptable E7053-278 2 nd / 2010 Milk pCi/L Strontium-90 1.12E+01 1.27E+01 0.88 Acceptable E7054-278 2rd / 2010 Milk pCi/L Zinc-65 2.71E+02 2.54E+02 1.07 Acceptable E7055-278 2e / 2010 Water pCi/L Zinc-65 2.97E+02 2.56E+02 1.16 Acceptable NY-332 3262 2 "d / 2010 Water pCi/L Barium-133 27.8 25.6 20.6- 30.5 Acceptable NY-332 3262 2nd / 2010 Water pCi/L Cesium-134 14.8 14.0 10.7 - 17.3 Acceptable NY-332 3262 2 nd / 2010 Water pCi/L Cesium-137 124 123 112- 134 Acceptable NY-332 3262 2 rd / 2010 Water pCi/L Cobalt-60 98.3 99.5 90.3 - 109 Acceptable NY-332 3263 2"d / 2010 Water pCi/L Gross Alpha 33.0 26.8 15.0-38.6 Acceptable NY-332 3263 2r" / 2010 Water pCi/L Gross Beta 64.6 54.0 41.3-66.7 Acceptable NY-332 3264 2"d / 2010 Water pCi/L Iodine-131 23.4 26.4 21.9-31.0 Acceptable NY-332 3264 2d /2010 Water pCi/L Iodine-131 26.8 26.4 21.9-31.0 Acceptable NY-332 3265 2"d / 2010 Water pCi/L Radium-226 12.1 13.2 10.4 - 16.0 Acceptable NY-332 3265 2e / 2010 Water pCi/L Radium-228 9.90 8.91 6.08 - 11.7 Acceptable

Laboratories LLG P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 16 of 51 Acceptance Sample Sample Known Range]

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation NY-332 3261 2e / 2010 Water pCi/L Strontium-89 46.7 41.9 33.4 - 50.4 Acceptable NY-332 3261 2n /2010 Water pCi/L Strontium-90 33.9 34.8 27.1 -42.5 Acceptable NY-332 3266 2 "d/2010 Water pCi/L Tritium 9610 9490 8390- 10600 Acceptable NY-332 3265 2e /2010 Water pCi/L Uranium (activity) 48.81 44.7 37.9-51.4 Acceptable NY-332 3262 2"' /2010 Water pCi/L Zinc-65 146 139 121-156 Acceptable MRAD-12 2d / 2010 Soil pCi/kg Actinium-228 1570 1850 1190- 2600 Acceptable MRAD-12 2d / 2010 Soil pCi/kq Americium-241 1130 1500 896-1930 Acceptable MRAD-12 2 4 /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 2nd / 2010 Vegetation pCi/kg Americium-241 3600 3140 1790-4310 Acceptable MRAD-12 2 nd/ 2010 Air Filter pCi/Filter Americium-241 52.7 60.0 35.1 - 82.3 Acceptable MRAD-12 2rd / 2010 Air Filter pCi/Filter Americium-241 76 60 35.1 -82.3 Acceptable MRAD-12 2nd /2010 Water pCi/L Americium-241 79.1 95.6 65.5- 129 Acceptable MRAD-12 2d /2010 Water pCi/L Americium-241 123 95.6 65.5- 129 Acceptable MRAD-12 2r / 2010 Soil pCi/kg Bismuth-212 1430 1640 430-2450 Acceptable MRAD-12 2'd /2010 Soil pCi/kg Bismuth-214 1080 1410 865-2030 Acceptable MRAD-12 2 "d/2010 Soil pCi/kg Cesium-134 3040 3110 2000-3740 Acceptable MRAD-12 2 "d/ 2010 Vegetation pCi/kg Cesium-134 1750 1670 956-2310 Acceptable MRAD-12 2 n / 2010 Air Filter pCi/Filter Cesium-134 504 436 284 - 540 Acceptable MRAD-12 2nd / 2010 Water pCi/L Cesium-134 454 417 308-479 Acceptable MRAD-12 2rd / 2010 Soil pCi/kg Cesium-1 37 4330 4440 3400-5770 Acceptable MRAD-12 2d* /2010 Vegetation pCi/kg Cesium-137 1550 1470 1080-2040 Acceptable MRAD-12 2nd / 2010 Air Filter pCi/Filter Cesium-137 785 701 527-921 Acceptable MRAD-12 2"d / 2010 Water pCi/L Cesium-137 693 654 556-783 Acceptable MRAD-12 2e / 2010 Soil pCi/kg Cobalt-60 2120 2140 1560-2870 Acceptable MRAD-12 2 4 / 2010 Vegetation pCi/kg Cobalt-60 2100 1970 1330-2830 Acceptable MRAD-12 2" /2010 Air Filter pCi/Filter Cobalt-60 591 523 405-653 Acceptable MRAD-12 2 "d/ 2010 Water pCi/L Cobalt-60 813 727 633-859 Acceptable MRAD-12 2d / 2010 Vegetation pCi/kg Curium-244 429 528 260-822 Acceptable MRAD-12 2" /12010 Air Filter pCi/Filter Gross Alpha 68.2 79.6 41.3- 120 Acceptable MRAD-12 2nd / 2010 Air Filter pCi/Filter Gross Beta 72 70.4 43.4- 103 Acceptable MRAD-12 2n / 2010 Air Fiter pCi/Filter Iron-55 375 359 158-559 Acceptable MRAD-12 2d"/ 2010 Soil pCi/kg Lead-212 1540 1520 980-2140 Acceptable MRAD-12 2 'd 12010 Soil pCi/kg Lead-214 1300 1440 862-2140 Acceptable MRAD-12 2d /2010 Soil pCi/kg Manganese-54 < 22.9 0 --- Acceptable MRAD-12 2nd / 2010 Ve getation pCi/kg Manganese-54 <9.6 0.00 --- Acceptable

ILaboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 17 of 51 Acceptance Sample Sample Known Range/

Number Quarter I Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation MRAD-12 2'* /2010 Air Filter pCi/Filter Manganese-54 < 5.07 0.00 -- Acceptable MRAD-12 2nd /2010 Water pCi/L Manganese-54 < 7.7 0.00 --- Acceptable MRAD-12 2nd / 2010 Soil pCVkg Plutonium-238 1360 1330 761 - 1870 Acceptable MRAD-12 2 nd / 2010 Vegetation pCi/kg Plutonium-238 3090 3040 1640 -4450 Acceptable MRAD-12 2rd /2010 Air Filter pCi/Filter Plutonium-238 63.9 64.1 44.0- 84.3 Acceptable Not MRAD-12 2'd /2010 Water 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 2r4 /2010 Vegetation pCi/kg Plutonium-239 2830 2800 1740-3820 Acceptable MRAD-12 2 " / 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 2d /2010 Soil pCi/kg Potassiurm-40 11100 10900 7900- 14800 Acceptable 25100-MRAD-12 2nd / 2010 Vegetation pCi/kg Potassium-40 40800 34900 49400 Acceptable MRAD-12 2 nd /2010 Soil pCi/kg Strontium-90 7870 8180 2960- 13300 Acceptable MRAD-12 2M /2010 Soil pCi/kg Strontium-90 7870 8180 2960- 13300 Acceptable MRAD-12 2d* / 2010 Vegetation pCi/kg Strontium-90 7880 9120 5100-12100 Acceptable MRAD-12 2 "d /2010 Air Filter pCi/Filter Strontium-90 178 187 82.3-291 Acceptable MRAD-12 2 'r /2010 Water pCi/L Strontium-90 708 719 456-961 Acceptable MRAD-12 2rd /2010 Soil pCi/kg Thorium-234 1600 1610 511 -3070 Acceptable MRAD-12 2d / 2010 Soil pCi/kg Uranium-234 1230 1620 1030-2010 Acceptable MRAD-1 2 2 d / 2010 Vegetation pCi/kg Uranium-234 1680 1720 1180 - 2280 Acceptable MRAD-12 2d / 2010 Air Filter pCi/Filter Uranium-234 68,8 62.1 39.1 -92.0 Acceptable MRAD-12 2 nd / 2010 Water pCi/L Uranium-234 62.4 61.4 46.3-79.2 Acceptable Not MRAD-12 2M /2010 Soil pCi/kg Uranium-234 < 1158 1620 1030-2010 Acceptable MRAD-12 2 rd / 2010 Soil pCi/kg Uranium-238 1600 1610 984 -2040 Acceptable Not MRAD-12 24 / 2010 Soil pCi/kg Uranium-238 908 1610 984-2040 Acceptable MRAD-12 2"' / 2010 Soil pCi/kg Uranium-238 1440 1610 984-2040 Acceptable MRAD-12 24d / 2010 Vegetation pCi/kg Uranium-238 1604 1710 1200-2160 Acceptable MRAD-12 2n /2010 Vegetation pCi/kg Uranium-238 1770 1710 1200-2160 Acceptable Not MRAD-12 2 nd /2010 Vegetation pCi/kg Uranium-238 < 1240 1710 1200-2160 Acceptable MRAD-12 2V / 2010 Air Filter pCi/Filter Uranium-238 61.5 61.5 39.4-87.3 Acceptable MRAD-12 2 4 / 2010 Air Filter pCi/Filter Uranium-238 69.5 61.5 39.4-87.3 Acceptable MRAD-12 2"d / 2010 Air Filter pCi/Filter Uranium-238 < 61.2 61.5 39.4-87.3 Acceptable MRAD-12 2 /12010 Water pCi/ft Uranium-238 67.9 60.9 46.5- 75.5 Acceptable MRAD-12 2d /2010 Water pCi/L Uranium-238 66.1 60.9 46.5-75.5 Acceptable Not MRAD-12 2r" / 2010 Water pCi/L Uranium-238 < 155 60.9 46.5- 75.5 Acceptable MRAD-12 2'n /2010 Soil pCi/kg. Uranium-Total 2789 3300 1880 -4460 Acceptable MRAD-12 2'd /2010 Vegetation pCi/kg Uranium-Total 3536 3510 2410-4530 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 18 of 51 Acceptance Sample Sample Known Rangel Number Quarter / Year Media Unit Analvte I Nuclide GEL Value value Ratio Evaluation Uranium-Total MRAD-12 2" / 2010 Soil uojkg (mass) 2920 4820 2650-6060 Acceptable Uranium-Total MRAD-12 2"" /2010 Vegetation ug/kg (mass) 5270 5120 3520 -6610 Acceptable Uranium-Total MRAD-12 2nd / 2010 Vegetation pCi/kg (mass) 5290 5120 3520- 6610 Acceptable Uranium-Total MRAD-12 2"d /2010 Air Filter ug/Filter (mass) 183 184 114- 264 Acceptable Uranium-Total MRAD-12 2d / 2010 Air Filter ug/Filter (mass) 208 184 114- 264 Acceptable Uranium-Total MRAD-12 24 12010 Air Filter ug/Filter (mass) 175 184 114 -264 Acceptable Uranium-Total MRAD-12 2r4 /2010 Water u,/L (mass) 213 182 143-225 Acceptable Uranium-Total MRAD-12 2" / 2010 Water ug/L (mass) 198 182 143 - 225 Acceptable MRAD-12 2"" / 2010 Soil pCVkg Zinc-65 2790 2470 1960- 3310 Acceptable MRAD-12 2" / 2010 Vegetation pCi/kg Zinc-65 1630 1360 983-1860 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Zinc-65 462 389 269-539 Acceptable MRAD-12 21 / 2010 Water pCi/L Zinc-65 632 533 452 - 664 Acceptable Not RAO - 82 3 1I2010 Water pCi/L Barium-133 112.0 89.1 75.0 - 98.0 Acceptable Not RAD - 82 3"' / 2010 Water pCi/L Cesium-134 115.0 88.3 72.4 -97.1 Acceptable Not RAD - 82 3 / 2010 Water pCi/L Cesium-137 271 210 189- 232 Acceptable Not RAD - 82 3 'd / 2010 Water pCi/L Cobalt-60 98.4 72.8 65.5- 82.5 Acceptable RAD - 82 3 'I /2010 Water pCi/L Gross Alpha 65.5 61.1 32.0- 75.9 Acceptable RAD - 82 3d /2010 Water pCi/L Gross Beta 56.7 56.4 38.6-63.6 Acceptable RAD - 82 3 'd 2010 Water pCi/L Iodine-131 32.2 28.4 23.6- 33.3 Acceptable RAD - 82 3 rd/2010 Water pCi/L Radium-226 15,9 17.1 12.7- 19.6 Acceptable PAD - 82 3 /d2010 Water pCiiL Radium-228 18.9 16.1 10.8-19.4 Acceptable RAD - 82 3 rd /2010 Water pCi/L Strontium-89 60.6 55.3 44.1 - 62.9 Acceptable Not RAD - 82 3 Id f 2 0 1 0 Water pCi/L Strontium-90 47.1 32.8 24.0-38.0 Acceptable 17300-RAD - 82 3 / 2010 Water pCi/L Tritium 18500 19800 21700 Acceptable Not RAD - 82 3 rd/ 2010 Water pCi/L Uranium (Nat) 58.0 49.6 40.2-55.1 Acceptable Uranium (Nat) Not RAD - 82 3 rd 12010 Water ug/L Mass 89.1 72.3 58.7 -80.4 Acceptable Not RAD - 82 3 "'/2010 Water pCi/L Zinc-65 161 110 99.0-131 Acceptable MAPEP MaS22 3 "'/ 2010 Soil Sq/kq Americium-241 0.07 0.00 --- Acceptable MAPEP Not RdF22 3 d/ 2010 Filter Bg/sample Americium-241 0.2637 0.146 0.102 - 0.190 Acceptable MAPEP RdV22 3 "d/2010 Vegetation Bq/sample Americium-241 0.179 0.225 0.158 - 0.293 Acceptable MAPEP MaS22 3 Id 12010 Soil Bq/kg Cesium-134 744.67 733 513-953 Acceptable MAPEP Not RdF22 3 "I/2010 Filter Bq/sample Cesium-134 4.323 2.13 1.49-2.77 Acceptable MAPEP RdV22 3 Id /2010 Vegetation Bq/sample Cesium-134 3.098 4.39 3.07- 5.71 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 19 of 51 Acceptance Sample Sample Known Range/

Number Ouarter / Year Media Unit Analvte / Nuclide GEL Value value Ratio Evaluation MAPEP MaS22 3 rd /1 2 0 10 Soil Bq/kg Cesium-137 831.7 779 545-1013 Acceptable MAPEP Not RdF22 3 d / 2010 Filter Bq/sample Cesium-137 3.070 1.53 1.07- 1.99 Acceptable MAPEP-1 0-RdV22 3 rd/2010 Vegetation Bq/sample Cesium-137 2.185 3.06 2.14-3.98 Acceptable MAPEP MaS22 3 rd/2010 Soil Bq/kg Cobalt-57 536.0 522 365 -679 Acceptable MAPEP RdV22 3 rd / 2010 Vegetation Bq/sample Cobalt-57 0.009 0.00 -- Acceptable MAPEP MaS22 3 d, 2010 Soil Bq/kg Cobalt-60 670.3 622 435 - 809 Acceptable MAPEP Not RdF22 3 rd 20 10 Filter Bq/sample Cobalt-60 5.187 2.473 1.731 - 3.215 Acceptable MAPEP RdV22 3 Id / 2010 Vegetation Bq/sample Cobalt-60 3.076 3.27 2.29-4.25 Acceptable MAPEP GrF22 3rd/ 2010 Filter Sq/sample Gross Alpha 0.303 0.427 >0.0 - 0.854 Acceptable MAPEP GrF22 3 ,d /2010 Filter Bq/sample Gross Beta 1.433 1.29 0.65- 1.94 Acceptable MAPEP MaS22 3 / 2010 Soil Bq/kg Iron-55 83.6 0.00 -- Acceptable MAPEP MaS22 3 'd / 2010 Soil Bq/kg Manganese-54 940.7 849 594- 1104 Acceptable MAPEP Not RdF22 3 rd / 2010 Filter Bq/sample Manganese-54 6.483 3.02 2.11 -3.93 Acceptable MAPEP RdV22 3 'd/ 2010 Vegetation Bq/sample Manganese-54 0.004 0.00 -- Acceptable MAPEP MaS22 3 '* / 2010 Soil Bq/kg Nickel-63 489 477 334 -620 Acceptable MAPEP MaS22 3 d / 2010 Soil Bq/kg Plutonium-238 17.9 24 16.9 - 31.3 Acceptable MAPEP RdF22 3 rd / 2 0 1 0 Filter Bq/sample Plutonium-238 0.010 0.0010 -- Acceptable MAPEP-1 0-RdV22 3 r / 2010 Vegetation Bq/sample Plutonium-238 0,149 0.160 0.112 - 0.208 Acceptable MAPEP Plutonium-MaS22 3 'd /2010 Soil Bq/k 239/240 0.21 0.00 -- Acceptable MAPEP Plutonium- 0.0582 - Not RdF22 3 'd / 2010 Filter Bq/sample 239/240 0.164 0.0832 0.1082 Acceptable MAPEP Plutonium-RdV22 3 ,d / 2010 Vegetation Bq/sample 239/240 0.0026 0.0008 -- Acceptable MAPE P MaS22 3 Id/ 2010 Soil Bq/kg Potassium-40 638.7 559 391 - 727 Acceptable MAPEP MaS22 3 Id / 2010 Soil Bq/kg Strontium-90 261.0 288 202- 374 Acceptable MAPEP RdF22 3 'd / 2010 Filter Bq/sample Strontium-90 -0.004 0.00 Acceptable MAPEP RdV22 3 rd / 2010 Vegetation Bq/sample Strontium-90 0.033 0.00 Acceptable MAPEP MaS22 3 rd/ 2010 Soil Bq/k9 Technetium-99 -3.0 0.00 Acceptable MAPEP MaS22 3 rd / 2010 Soil Bq/kg Uranium-234/233 65.27 60 42-78 Acceptable MAPEP Not RdF22 3 rd/2010 Filter Bq/sample Uranium-234/233 0.137 0.068 0.048 - 0.088 Acceptable MAPEP RdV22 3 Id / 2010 Vegetation Bq/sample Uranium-234/233 0.184 0.216 0.151 - 0.281 Acceptable MAPEP 0.0267 - Not RdF22 3 d / 2010 Filter ug/sample Uranium-235 0.0756 0.0381 0.0495 Acceptable MAPEP 0.0875 -

RdV22 .d 3 / 2010 Vegetation ug/sample Uranium-235 0.090 0.1250 0.1625 Acceptable

~I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 20 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation MAPEP MaS22 3 ,d/2010 Soil Bq/kg Uranium-238 70.23 64 45-83 Acceptable MAPEP Not RdF22 3 ,d/2010 Filter ug/sample Uranium-238 10.2 5.7 4.0-7.4 Acceptable MAPEP Not RdF22 3 rd / 2010 Filter Bq/sample Uranium-238 0.147 0.071 0.050 - 0.092 Acceptable MAPEP-1 0- Not RdV22 3 , 12010 Vegetation ug/sample Uranium-238 12.5 17.9 12.5-23.3 Acceptable MAPEP RdV22 3 rd / 2010 Vegetation Bq/sample Uranium-238 0.184 0.223 0.156 - 0.290 Acceptable MAPEP Not RdF22 3 r,/2010 Filter ug/sample Uranium-Total 10.2 5.7 4.0-7.4 Acceptable MAPEP RdV22 3 d/ 2010 Vegetation ug/sample Uranium-Total 13.9 18.0 12.6-23.4 Acceptable MAPEP MaS22 3 dj/2010 Soil B,/kg - Zinc-65 -2.89 0.0 -- Acceptable MAPEP RdF22 3d / 2010 Filter Bq/sample Zinc-65 -0.106 0.00 -- Acceptable MAPEP RdV22 3 d /2010 Vegetation Bqlosample Zinc-65 6.844 7.10 4.97 -9.23 Acceptable E7119-278 3 rd/ 20 10 Milk pCi/L Cesium-134 1.37E+02 1.26E+02 1.09 Acceptable E7119-278 3 rd / 2010 Milk pCiiL Cesium-137 1.68E+02 1.50E+02 1.12 Acceptable E7119-278 3 Id,/2010 Milk pCi/L Cobalt-58 1.13E+02 1.01E+02 1.12 Acceptable E7119-278 3 'd/ 2010 Milk pCi/L Cobalt-60 2.14E+02 1.97E+02 1.09 Acceptable E7119-278 3d/2010 Milk pCi/L Cr-51 3.90E+02 3.39E+02 1.15 Acceptable E7117-278 3Vd/ 2 0 10 Milk pCi/L Iodine-131 7.97E+01 8.02E+01 0.99 Acceptable E7119-278 3 'd / 2010 Milk pCi/L lodine-131 1.06E+02 9.69E+01 1.09 Acceptable Not E7119-278 3 d / 2 0 10 Milk pCi/L Iron-59 1.55E+02 1.19E+02 1.30 Acceptable E7119-278 3 rd / 2010 Milk pCi/L Manqanese-54 1.99E+02 1.69E+02 1.18 Acceptable E7118-278 3 rd / 2010 Milk pCi/L Strontium-89 7.95E+01 9.34E+01 0.85 Acceptable E7118-278 3 rd / 2 0 1 0 Milk pCi/L Strontium-90 1.57E+01 1.67E+01 0.94 Acceptable E7119-278 3 Id /2010 Milk pCi/L." Zinc-65 2.40E+02 2.06E+02 1.17 Acceptable 090710N 3 rd / 2010 Water pCi/iL Barium-133 86.9 92.9 78.3- 102 Acceptable Not 090710N 3 rd / 2010 Water pCi/L Cesium-1 34 93.8 79.4 65.0-87.3 Acceptable 090710N 3 rd /2010 Water pCi/L Cesium-137 55.5 54.6 49.1 -62.9 Acceptable 090710N 3 d / 2 0 10 Water pCi/LI Cobalt-60 120.0 117 105-131 Acceptable 090710N 3 rd/ 2010 Water pCi/LI Uranium (Nat) 34.9 33.8 27.3 - 37.8 Acceptable Uranium (Nat) 09071 ON 3 ,d12010 Water ug/L Mass 48.6 49.3 39.8-55.1 Acceptable Not 090710N 3 d / 2010 Water pCi/L Zinc-65 129 99.5 89.6-119 Acceptable MAPEP MaW22 3d 3 / 2010 Water Bq/L Americium-241 1.0323 1.30 0.91 -1.69 Acceptable MAPEP-i0-MaW22 3 " / 2010 Water Bq/L Cesium-1 34 0.027 0.00 -- Acceptable MAPEP MaW22 3 rd / 2010 Water Bq[L Cesium-137 63.1 60.6 42.4- 78.8 Acceptable MAPEP MaW22 3 rd /2010 Water Bq/L Cobalt-57 29.2 28.3 19.8-36.8 Acceptable MAPEP MaW22 3 rd/ 2010 Water Bq/L Cobalt-60 -0.021 0.00 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 21 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analve INuclide GEL Value value Ratio Evaluation MAPEP GrW22 3"/ 2010 Water Bq/L Gross Alpha 0.559 0.676 >0.0 - 1.352 Acceptable MAPEP GrW22 3 rd12010 Water Bq/L Gross Beta 3.110 3.09 1.55 -4.64 Acceptable MAPEP MaW22 3 rd / 2010 Water Bq/L Iron-55 0.24 0.00 --- Acceptable MAPEP MaW22 3 rd /2010 Water Bq/L Manganese-54 28.83 26.9 18.8 -35.0 Acceptable MAPEP MaW22 3rd / 2010 Water Bq/L Nickel-63 57.7 59.9 41.9 - 77.9 Acceptable MAPEP-lO- Not MaW22 3 d /12010 Water Bq/L Plutonium-238 1.213 1.93 1.35- 2.51 Acceptable MAPEP Plutonium-MaW22 3 rd /2010 Water ..Bq/L 239/240 0.026 0.009 -- Acceptable MAPEP MaW22 3 rd/ 2010 Water Bq/L Strontium-90 -0.01 0.00 -- Acceptable MAPEP MaW22 3 '/ 2010 Water Bq/L Technetium-99 -0.4 0.00 -- Acceptable MAPEP MaW22 3 ,d / 2 0 10 Water Bq/L Tritium 107 90.8 63.6-118.0 Acceptable MAPEP MaW22 3 ,d / 2010 Water Bq/L Uranium-234/233 1.163 1.22 0.85- 1.59 Acceptable MAPEP MaW22 3 rd / 2010 Water Bq/L Uranium-238 1.223 1.25 0.88-1.63 Acceptable MAPEP MaW22 3 ,d / 2010 Water Bq/L Zinc-65 45.9 40.7 28.5- 52.9 Acceptable E7195-278 4" /2010 Milk pCi/L Cerium-141 1.39E+02 1.30E+02 1.07 Acceptable E7195-278 4" 12010 Milk pO/i Cesium-134 9.85E+01 9.30E+01 1.06 Acceptable E7196-278 4" /2010 Water pCi/L Cesium-134 1.22E+02 1.18E+02 1.03 Acceptable E7195-278 4" /2010 Milk pCi/L Cesium-137 9.87E+01 9,45E+01 1.04 Acceptable E7196-278 4=" /2010 Water pCi/L Cesium-137 1.24E+02 1.20E+02 1.03 Acceptable E7195-278 4" / 2010 Milk pCi/L Cobalt-58 7.02E+01 7.37E+01 0.95 Acceptable E7196-278 4" / 2010 Water pCi/L Cobalt-58 9.63E+01 9.35E+01 1.03 Acceptable E7195-278 40 /2010 Milk pCi/L Cobalt-60 1.77E+02 1.71E+02 1.04 Acceptable E7196-278 4" / 2010 Water pCi/I Cobalt-60 2.34E+02 2.17E+02 1.08 Acceptable E7195-278 4" /2010 Milk pCi/L Cr-51 2,48E+02 2.34E+02 1.06 Acceptable E7196-278 4" / 2010 Water pCi/L Cr-51 3,12E+02 2.97E+02 1,05 Acceptable E7193-278 4t" /2010 Cartridge pCi Iodine-131 5.97E+01 6,02E+01 0.99 Acceptable E7195-278 4" /2010 Milk pCi/L Iodine-131 1.01 E+02 9.41E+02 1.07 Acceptable E7196-278 4h / 2010 Water pCi/L lodine-131 7.24E+01 6A44E+01 1.12 Acceptable E7195-278 4" /2010 Milk pCi/L Iron-59 1.02E+02 9,11E+01 1.12 Acceptable E7196-278 4" / 2010 Water pCi/L Iron-59 1.42E+02 1.16E+02 1.23 Acceptable E7195-278 4" /2010 Milk pCi/L Manganese-54 1.20E+02 1.19E+02 1.01 Acceptable E7196-278 4" / 2010 Water pCi/L Manganese-54 1,70E+02 1.52E+02 1.12 Acceptable E7194-278 4" /2010 Milk pCi/L Strontium-89 7.62E+01 9.28E+01 0,82 Acceptable E7194-278 40 /2010 Milk pCi/A Strontium-90 1.30E+01 1.47E+01 0.88 Acceptable E7195-278 4' /2010 Milk pCi/L Zinc-65 2.37E+02 2.04E+02 1.16 Acceptable E7196-278 4 /12010 Water pCiAI. Zinc-65 2.97E+02 2.59E+02 1.15 Acceptable NY-337 3762 4" / 2010 Water pCi/L Barium-133 50.5 50.9 43.3 - 59.4 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 22 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analvte / Nuclide GEL Value value Ratio Evaluation Not NY-337 3762 4" /2010 Water pCi/L Cesium-134 51.0 42.0 35.8 - 49.2 Acceptable NY-337 3762 4"' / 2010 Water pCi/L Cesium-137 29.3 27.3 22.4-32.1 Acceptable NY-337 3762 4"' / 2010 Water pCi/L Cobalt-60 13.6 13.2 9.72- 16.7 Acceptable NY-337 3763 4" / 2010 Water pCi/L Gross Alpha 32.8 41.6 24.3-58.9 Acceptable NY-337 3763 4" /2010 Water pCi/L Gross Beta 29.3 27.5 18.3- 36.7 Acceptable Not NY-337 3764 4h" /2010 Water pCi/L Iodine-131 13.4 18.2 14.7-21.7 Acceptable Not NY-337 3764 4" /2010 Water pCi/L Iodine-131 13.5 18.2 14.7-21.7 Acceptable Not NY-337 3765 4"h / 2010 Water pCi/L Radium-226 13.2 10.6 8,30- 12.9 Acceptable NY-337 3765 4"h / 2010 Water pCi/L Radium-228 6.51 6.07 3.91 - 8.22 Acceptable Not NY-337 3761 4h / 2010 Water pCi/L Strontium-89 47.8 61.3 51.3-71.4 Acceptable NY-337,3761 4h /2010 Water pCi/L Strontium-90 12.0 14.9 11.0- 18.8 Acceptable 13500-NY-337 3766 4" / 2010 Water pCi/L Tritium 14400 15300 17000 Acceptable NY-337 3765 4"h / 2010 Water pCi/L Uranium (activity) 17.5 16.0 13.2-18.7 Acceptable NY-337 3762 4"' / 2010 Water pCi/L Zinc-65 134 122 104 - 138 Acceptable 10051 ON 4" / 2010 Water pCi/L Strontium-89 49.9 51.4 40.6 - 58.9 Acceptable 10051 ON 4" / 2010 Water pCi/L Strontium-90 35.4 41.3 30.4-47.5 Acceptable RAD - 83 4" / 2010 Water pCi/L Strontium-90 41.5 43 31.7- 49.3 Acceptable 112210H1 4' /2010 Water pCi/L Barium-133 66.3 65.9 54.9- 72.5 Acceptable 112210H1 4t" /2010 Water pCi/L Cesium-134 71.6 71.6 58.4-78.8 Acceptable 112210H1 4' /2010 Water pCi/L Cesium-137 151 146 131 -163 Acceptable 112210H1 4h /2010 Water pCi/L Cobalt-60 90.2 84.5 76.0- 95.3 Acceptable 112210H1 4"' /2010 Water pCi/L Zinc-65 207 186 167-219 Acceptable 112210H2 4"' /2010 Water pCi/L Plutonium-238 102.0 108 81.7-134 Acceptable 112210H2 4"' / 2010 Water pCi/L Plutonium-239 77.6 86.3 66.8- 107 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Actinium-228 1460 1830 1170-2580 Acceptable MRAD-13 4"h / 2010 Soil pCi/kg Americium-241 845 1120 669- 1440 Acceptable MRAD-13 4"' /2010 Soil pCi/kg Americium-241 928 1120 669- 1440 Acceptable MRAD-13 4"' / 2010 Vegetation pCi/kg Americium-241 4000 4760 2710- 6540 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Americium-241 70.1 74.1 43.3- 102 Acceptable MRAD-13 4h / 2010 Water pCi/L Amerfcium-241 164 176 120-238 Acceptable MRAD-13 4"' / 2010 Water pCi/L Americium-241 178 176 120-238 Acceptable Not MRAD-13 4"' / 2010 Soil pCi/kg Bismuth-212 < 538 2070 543 -3100 Acceptable MRAD-13 4" /2010 Soil pCi/kg Bismuth-214 818 983 603- 1410 Acceptable MRAD-13 4"` / 2010 Soil pCi/kg Cesium-134 2230 2240 1440-2700 Acceptable MRAD-13 4' / 2010 Vegetation pCi/kq Cesium-134 1200 1040 595- 1440 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Cesium-134 405 388 253-480 Acceptable MRAD-13 4" / 2010 Water pCi/L Cesium-134 495 492 363-565 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 23 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation MRAD-13 4" /2010 Soil pCi/kq Cesium-137 3400 3530 2700- 4580 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Cesium-137 1420 1260 924-1750 Acceptable MRAD-13 4t /2010 Air Filter pCi/Filter Cesium-137 532 514 386-675 Acceptable MRAD-13 40 /2010 Water pCi/L Cesium-137 620 625 531 -749 Acceptable MRAD-13 40 / 2010 Soil pCi/kg Cobalt-60 4580 4780 3480 - 6420 Acceptable MRAD-13 4"h /2010 Vegetation pCi/kg Cobalt-60 1130 1010 683-1450 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Cobalt-60 531 479 371 -598 Acceptable MRAD-13 4t /2010 Water pCi/L 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 4h / 2010 Water pCi/L 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 pCi/L Gross Beta 171 143 83.6 - 210 Acceptable MRAD-13 4h /2010 Air Filter pCi/Filter Iron-55 707 626 275-974 Acceptable Not MRAD-13 4" / 2010 Water pCi/L Iron-55 1220 825 480-1100 Acceptable MRAD-13 4" /2010 Soil pCi/kg Lead-212 1550 1640 1060-2310 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Lead-214 1030 969 580- 1440 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Manganese-54 < 38.0 0.00 --- Acceptable MRAD-13 4" / 2010 Vegetation pCi/kg Manganese-54 < 39.8 0.00 -- Acceptable MRAD-13 4h / 2010 Water pCi/L Manganese-54 <5 0.00 --- Acceptable MRAD-13 4" / 2010 Soil pCi/kg Plutonium-238 1170 1280 733- 1800 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Plutonium-238 3740 4740 2560- 6940 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Plutonium-238 70.8 72.9 50.0-95.8 Acceptable MRAD-13 4" /2010 Water pCi/L Plutonium-238 157 162 122-201 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Plutonium-239 1070 1180 805-1570 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Plutonium-239 3590 4470 2770-6100 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Plutonium-239 65.6 69.6 50.5- 90.1 Acceptable MRAD-13 4" / 2010 Water pCi/L Plutonium-239 136 148 114- 183 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Potassium-40 10500 10700 7760- 14500 Acceptable 16200-MRAD-13 4" /2010 Vegetation pCi/kg Potassium-40 29000 22600 32000 Acceptable MRAD-13 4" /2010 Soil pCi/kg I Strontium-90 10953 9270 3350- 15100 Acceptable MRAD-13 4"' / 2010 Vegetation pCi/kg Strontium-90 9800 7810 4360- 10400 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Strontium-90 80.2 159 70.0-247 Acceptable MRAD-13 4" /2010 Water pCi/L Strontium-90 817 921 585- 1230 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Thorium-234 1010 1340 425-2550 Acceptable 14100-MRAD-13 4" / 2010 Water pCi/LI Tritium 20900 21600 31900 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Uranium-234 899 1360 862-1690 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Uranium-234 1190 1360 862-1690 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-234 1110 1360 862- 1690 Acceptable

~I Laboraiories LLC P.0, Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 24 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analvte / Nuclide GEL Value value Ratio Evaluation MRAD-13 4" /2010 Vegetation pCi/kg Uranium-234 3600 4010 2750-5320 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-234 73.5 71.8 45.2- 106 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Uranium-234 69.9 71.8 45.2- 106 Acceptable MRAD-13 4" / 2010 Water pCiA/ Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4h /2010 Water pCi/L Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4h /2010 Water pCi/L Uranium-234 104 109 82.2- 140 Acceptable MRAD-13 4"' ./2010 Soil pCi/kg Uranium-238 1010 1340 819- 1700 Acceptable MRAD-13 4h /2010 Soil pCi/kq Uranium-238 1080 1340 819-1700 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Uranium-238 903 1340 819- 1700 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-238 1090 1340 819- 1700 Acceptable MRAD-13 4h / 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 4h" / 2010 Air Filter pCi/Filter Uranium-238 66.8 71.2 45.6-101 Acceptable MRAD-13 4" / 2010 Water pCi/L Uranium-238 107 108 82.5-134 Acceptable MRAD-13 4h" / 2010 Water pCi/L Uranium-238 114 108 82.5-134 Acceptable MRAD-13 4" / 2010 Water pCi/L 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" 1/2010 Soil ugikg Uranium-Total 2093 2770 1580 -3740 Acceptable MRAD-13 4h" /2010 Soil pCi/kg 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 4h" / 2010 Air Filter pCi/Filter Uranium-Total 142 146 74.6-232 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-Total 218 221 159-294 Acceptable MRAD-13 4" / 2010 Water pCi/L Uranium-Total 226.8 221 159-294 Acceptable MRAD-13 4' / 2010 Water pCi/L Uranium-Total 217 221 159-294 Acceptable Uranium-Total MRAD-13 4h" / 2010 Soil ug/kg (mass) 3240 4040 2220- 5080 Acceptable Uranium-Total MRAD-13 4" / 2010 Soil pCi/kg (mass) 2685 4040 2220-5080 Acceptable Uranium-Total MRAO-13 4h" /2010 Soil uq/kg (mass) 3241 4040 2220-5080 Acceptable Uranium-Total MRAD-13 4" / 2010 Soil ug/kg (mass) 2820 4040 2220- 5080 Acceptable Uranium-Total MRAD-13 4' / 2010 Vegetation ug/kg (mass) 12000 11900 8180- 15400 Acceptable Uranium-Total MRAD-13 4" / 2010 Air Filter ug/Filter (mass) 224.5 213 132-306 Acceptable Uranium-Total MRAD-13 4" /2010 Air Filter ug/Filter (mass) 201 213 132-306 Acceptable Uranium-Total MRAD-13 4h / 2010 Air Filter ug/Filter (mass) 192 213 132-306 Acceptable Uranium-Total MRAD-13 4" / 2010 Water uq/L (mass) 318 323 253-399 Acceptable Uranium-Total MRAD-13 4" /2010 Water ug/L (mass) 342 323 253-399 Acceptable Uranium-Total MRAD-13 4" /2010 Water ug/L (mass) 321 323 253 - 399 Acceptable MRAD-13 4" /2010 Soil pCi/kg Zinc-65 2420 2300 1820-3080 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 25 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation MRAD-13 4' / 2010 Veetation pCi/kg Zinc-65 1380 1210 874- 1650 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Zinc-65 552 465 322- 644 Acceptable MRAD-13 4t' / 2010 Water pCi/L Zinc-65 557 489 414-610 Acceptable 122810P 4t' /2010 Water pCi/L Barium-133 70.9 68.9 57.5-75.8 Acceptable 122810P 4h / 2010 Water pCi/L Cesium-134 43.0 43.2 34.5-47.5 Acceptable 122810P 4" / 2010 Water pCi/L Cesium-1 37 122 123 111 -138 Acceptable 122810P 4" /2010 Water pCi/L Cobalt-60 58.7 53.4 48.1 -61.3 Acceptable 122810P 4" /2010 Water pCi/I Zinc-65 116 102 91.8- 122 Acceptable

Laboratories LLC 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 / GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E7054-278 2r" / 2010 Milk pCi/L Cerium-141 2.61E+02 2.61E+02 1.00 Acceptable E7055-278 2 nd /2010 Water pCi/L Cerium-141 2.78E+02 2.63E+02 1.06 Acceptable E6924-278 26 /2010 Milk pCi/L Cerium-141 2.01E+02 2.02E+02 0.99 Acceptable E6925-278 2d /2010 Water pCi/L, Cerium-141 2.04E+02 2.04E+02 1.00 Acceptable E6924-278 2"d /2010 Milk pCi/L Cerium-141 2.01E+02 2.02E+02 0.99 Acceptable E6925-278 2d /12010 Water pCi/L Cerium-141 2.04E+02 2.04E+02 1.00 Acceptable E7054-278 2 "d /2010 Milk pCi/JL Cesium-137 1.61E+02 1.58E+02 1.02 Acceptable E7055-278 2 d / 2010 Water pCiA. Cesium-137 1.71E+02 1.59E+02 1.07 Acceptable E6924-278 2d /2010 Milk pCi/L Cesium-134 2.41E+02 2.53E+02 0.95 Acceptable E6925-278 2 n"d/2010 Water pCi/L Cesium-134 2.56E+02 2,55E+02 1.00 Acceptable E6924-278 2 nd / 2010 Milk pCi/L Cesium-134 2.41E+02 2,53E+02 0.95 Acceptable E6925-278 2 rd /2010 Water pCi/L Cesium-134 2.56E+02 2,55E+02 1.00 Acceptable E7054-278 2 nd /2010 Milk pCi/L Cesium-134 1.76E+02 1.78E+02 0.99 Acceptable E7055-278 2 d / 2010 Water pCi/L Cesium-134 1.85E+02 1.79E+02 1.03 Acceptable E6924-278 2d /2010 Milk pCi/L Cesium-137 1.71E+02 1.79E+02 0.96 Acceptable E6925-278 2d /2010 Water pCi/L Cesium-137 1.81E+02 1.81E+02 1.00 Acceptable E6924-278 2d 12010 Milk pCi/& Cesium-137 1,71E+02 1.79E+02 0.96 Acceptable E6925-278 2'" /2010 Water pCi/L Cesium-137 1.81E+02 1.81 E+02 1.00 Acceptable E7054-278 2r" / 2010 Milk pCi/L Chromium-51 3.81E+02 3.61 E+02 1.05 Acceptable E7055-278 2 r" / 2010 Water pCi/L Chromium-51 3.86E+02 3.64E+02 1.06 Acceptable E6924-278 2 d / 2010 Milk pCi/ll Chromium-51 5.54E+02 5.48E+02 1.01 Acceptable

!Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 27 of 51 Acceptance Sample Quarter / Sample Analyte I GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E6924-278 2 "d / 2010 Milk pCi/I Chromium-51 5.54E+02 5.48E+02 1.01 Acceptable E6925-278 2rd / 2010 Water pCi/L Chromium-51 5.78E+02 5.54E+02 1.04 Acceptable E7054-278 2 nd /2010 Milk pCi/LI Cobalt-58 1.45E+02 1.43E+02 1.02 Acceptable E7055-278 2 nd /2010 Water pCi/L Cobalt-58 1.51E+02 1.44E+02 1.05 Acceptable E6924-278 2d /2010 Milk pCi/L Cobalt-58 2.03E+02 2.11E+02 0.96 Acceptable E6925-278 2nd /2010 Water pCi/L Cobalt-58 2.19E+02 2.13E+02 1.03 Acceptable E6924-278 2 rd /2010 Milk pCi/LI Cobalt-58 2.03E+02 2.11E+02 0.96 Acceptable E6925-278 2rd /2010 Water pCi/L Cobalt-58 2.19E+02 2.13E+02 1.03 Acceptable E7054-278 2d /2010 Milk pCi/L Cobalt-60 1.90E+02 1.83E+02 1.04 Acceptable E7055-278 2nd / 2010 Water pCi/L Cobalt-60 1.94E+02 1.85E+02 1.05 Acceptable E6924-278 2nd / 2010 Milk pCi/L Cobalt-60 2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2nd / 2010 Water pCi/LI Cobalt-60 2,67E+02 2.58E+02 1.03 Acceptable E6924-278 2 "d / 2010 Milk pCi/L Cobalt-60 2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2 nd / 2010 Water pCi/L Cobalt-60 2.67E+02 2.58E+02 1.03 Acceptable E7052-278 2"d /2010 Cartridge pCi Iodine-131 8.58E+01 8.54E+01 1.00 Acceptable E7054-278 2nd / 2010 Milk pCi/L Iodine-131 6.91E+01 7.40E+01 0.93 Acceptable E7055-278 2r' / 2010 Water pCi/L Iodine-131 8.12E+01 7,22E+01 1.12 Acceptable E6922-278 2d / 2010 Cartridge pCi Iodine-131 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 2nd / 2010 Milk pCi/L Iodine-131 8.25E+01 8.73E+01 0.95 Acceptable E6925-278 2 "d / 2010 Water pCi/L Iodine-131 1.OOE+02 9.61 E+01 1.04 Acceptable E6922-278 2 nd / 2010 Cartridge pCi Iodine-131 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 2rd /2010 Milk pCi/L Iodine-131 8.25E+01 8.73E+01 0.95 Acceptable E6925-278 2d /2010 Water pCi/L Iodine-131 1.OOE+02 9.61E+01 1.04 Acceptable E7054-278 2"d /2010 Milk pCi/L Iron-59 1.60E+02 1.37E+02 1.17 Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 28 of 51 Acceptance Sample Quarter / Sample Analyte I GEL Known Range/

Number Year Unit Nuclide Value value Ratio Evaluation u6924-278 2 Yd

/2010 Milk pai/L. ron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2"' /2010 Water pCilL Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2nd /2010 Milk pCiIL Iron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2"* /2010 Water pCi/L Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2" / 2010 Milk pCi/L Manganese-54 1.83E+02 1.78E+02 1.03 Acceptable.

E6925-278 2" / 2010 Water pCi/L Manganese-54 1.90E+02 1.79E+02 1.06 Acceptable E6924-278 2"d / 2010 Milk pCi/A. Manganese-54 1.83E+02 1.78E+02 1.03 Acceptable E6925-278 26 /12010 Water pCi/L Manganese-54 1.90E+02 1.79E+02 1.06 Acceptable E7054-278 2" /12010 Milk pCi/L Manganese-54 2.10E+02 2.07E+02 1.01 Acceptable E7055-278 2"d (2010 Water pCi/L. Manganese-54 2.30E+02 2.09E+02 1.1 Acceptable E7053-278 2 d / 2010 Milk pCi/L Strontium-89 7.91E+01 9.28E+01 0.85 Acceptable E6923-278 2"" / 2010 Milk pCi/iL Strontium-89 9.73E+01 1.31E+02 0.75 Acceptable E6923-278 2d"/ 2010 Milk pCi/L Strontium-89 9.73E+01 1.31E+02 0.75 Acceptable E7053-278 2"1 12010 Milk pCi/L Strontium-90 1.12E+01 1.27E+01 0.88 Acceptable E6923-278 2" /12010 Milk pCi/L Strontium-90 1.38E+01 1.79E+01 0.77 Acceptable E6923-278 2" /12010 Milk pCi/L Strontium-90 1.38E+01 1.79E+01 0.77 Acceptable E6924-278 2d' / 2010 Milk pCi/L Zinc-65 3.68E+02 3.45E+02 1.07 Acceptable E6925-278 2nd /2010 Water pCi/L Zinc-65 3.72E+02 3.48E+02 1.07 Acceptable E6924-278 2"0 / 2010 Milk pIi/L Zinc-65 3.68E+02 3.45E+02 1.07 Acceptable E6925-278 2"d / 2010 Water pCi/L Zinc-65 3.72E+02 3.48E+02 1.07 Acceptable E7054-278 2"" / 2010 Milk pCi/L Zinc-65 2.71E+02 2.54E+02 1.07 Acceptable E7055-278 2' /12010 Water p i/L Zinc-65 2.97E+02 2.56E+02 1.16 Acceptable E7119-278 3"'/2010 Milk pCi/L Cerium-141 1.27E+02 1.10E+02 1.15 Acceptable

Laboratories LLW P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 29 of 51 Acceptance Sample Quarter / Sample Analyte / GEL Known Range/

Number Year Media IUnit Nuclide Value value Ratio Evaluation E7119-278 3 d/ 2010 Milk pCi/L Cesium-137 1.68E+02 1.50E+02 1.12 Acceptable E7119-278 3Vd /2010 Milk pCi/L Chromium-51 3.90E+02 3.39E+02 1.15 Acceptable E7119-278 3 rd/ 2 0 10 Milk pCi/L Cobalt-58 1.13E+02 1.01E+02 1.12 Acceptable E7119-278 3rd /2010 Milk pCi/L Cobalt-60 2.14E+02 1.97E+02 1,09 Acceptable E7117-278 3 'd / 2010 Milk pCi/L Iodine-131 7.97E+01 8.02E+01 0.99 Acceptable E7119-278 3 'd /2010 Milk pCi/L Iodine-131 1.06E+02 9.69E+01 1.09 Acceptable E7119-278 3 rd / 20 10 Milk pCi/L Iron-59 1.55E+02 1.19E+02 1.30 Not Acceptable E7119-278 3 r' / 2 0 10 Milk pCi/L Manganese-54 1.99E+02 1.69E+02 1.18 Acceptable E7118-278 3 'd / 2010 Milk pCi/L Strontium-89 7.95E+01 9.34E+01 0.85 Acceptable E7118-278 3 "' /2010 Milk pCi/L Strontium-90 1.57E+01 1.67E+01 0.94 Acceptable E7119-278 3 / 2010 Milk pCi/L Zinc-65 2.40E+02 2.06E+02 1.17 Acceptable E7195-278 4" /2010 Milk pCiiL Cerium-141 1.39E+02 1.30E+02 1.07 Acceptable E7196-278 4h' /2010 Water pCi/L Cerium-141 1.74E+02 1.65E+02 1.05 Acceptable E7195-278 4= /2010 Milk pCl/L Cesium-134 9.85E+01 9.30E+01 1.06 Acceptable E7196-278 4h /2010 Water pCi/L Cesium-134 1.22E+02 1.18E+02 1.03 Acceptable E7195-278 4"' /2010 Milk pCi/L Cesium-137 9.87E+01 9.45E+01 1.04 Acceptable E7196-278 4" /2010 Water pCi/L Cesium-137 1 24E+02 1.20E+02 1.03 Acceptable E7195-278 4" /2010 Milk pCi/L Chromium-51 2.48E+02 2.34E+02 1.06 Acceptable E7196-278 4= /2010 Water pCi/L Chromium-51 3.12E+02 2.97E+02 1.05 Acceptable E7195-278 4" / 2010 Milk pCi/L Cobalt-58 7.02E+01 7.37E+01 0.95 Acceptable E7196-278 4" /2010 Water pCi/L Cobalt-58 9.63E+01 9.35E+01 1.03 Acceptable E7195-278 4t /2010 Milk pCi/L Cobalt-60 1.77E+02 1.71E+02 1.04 Acceptable E7196-278 4" / 2010 Water pCi/k Cobalt-60 2.34E+02 2.17E+02 1.08 Acceptable E7193-278 40 /2010 Cartridge pCi Iodine-131 5.97E+01 6.02E+01 0.99 Acceptable E7195-278 4" / 2010 Milk pCi/L Iodine-131 1.01E+02 9.41E+02 1.07 Acceptable E7196-278 4" /2010 Water pCi/L Iodine-131 7.24E+01 6.44E+01 1.12 Acceptable E7195-278 4h /2010 Milk pCi/L Iron-59 1.02E+02 9.11E+01 1.12 Acceptable

! Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 30 of 51 Acceptance Sample Quarter I Sample Analyte I GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E7195-278 4" /2010 Milk- pCiLa Manganese-54 1.20E+02 1.19E+02 1.01 Acceptable E7196-278 4th /2010 Water pCi/L Manganese-54 1.70E+02 1.521E+02 1.12 Acceptable E7194-278 4" /2010 MilkW pCi/L Strontium-89 7.62E+01 9.28E+01 0.82 Acceptable E7194-278 4" /2010 Milk pCi/L Strontium-90 1.30E+01 1.47E+01 0.88 Acceptable E7195-278 4" /2010 Milk pCi/L Zinc-65 2.37E+02 2.04E+02 1.16 Acceptable E7196-278 4h /2010 Water pCi/L Zinc-65 2.97E+02 2.59E+02 1.15 Acceptable

Laboratories LLC 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 Quarter / Sample GEL Known Range/

Sample Number Year Media Unit Analyte / Nuclide Value value Ratio Evaluation MAPEP-10-MaS22 3 d/ 2010 Soil Bq/kg Americium-241 0.07 0.00 -- Acceptable MAPEP-10-MaS22 3 'd/ 2010 Soil Bq/kg Cesium-134 744.67 733 513-953 Acceptable MAPEP-10-MaS22 3 d / 2010 Soil Bq/kg Cesium-137 831.7 779 545- 1013 Acceptable MAPEP-10-MaS22 3 rd /2010 Soil Bq/kg Cobalt-57 536.0 522 365 -679 Acceptable MAPEP-10-MaS22 3 d / 2010 Soil Bq/kg Cobalt-60 670.3 622 435-809 Acceptable MAPEP-10-MaS22 3 rd / 2010 Soil Bq/kg Iron-55 83.6 0.00 -- Acceptable MAPEP-10-MaS22 3 'ý / 2010 Soil Bq/kg Manganese-54 940.7 849 594 - 1104 Acceptable MAPEP-10-MaS22 3 d / 2010 Soil Bq/kg Nickel-63 489 477 334-620 Acceptable MAPEP-10-MaS22 3 'd /2010 Soil Bq/kg Plutonium-238 17.9 24 16.9-31.3 Acceptable MAPEP-10-MaS22 3 r / 2010 Soil Bq/kg 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-10-MaS22 3 ,d/ 2010 Soil Bq/kg Strontium-90 261.0 288 202 - 374 Acceptable MAPEP-10-MaS22 3 d/ 2 0 1 0 Soil Bq/kg Technetium-99 -3.0 0.00 --- Acceptable MAPEP-10-MaS22 3 rd / 2010 Soil Bq/kg Uranium-234/233 65.27 60 42-78 Acceptable MAPEP-10-MaS22 3 , / 2010 Soil Bq/kg Uranium-238 70.23 64 45-83 Acceptable MAPEP-10-MaS22 3 rd / 2010 Soil Bqf/g Zinc-65 -2.89 0.0 --- Acceptable MAPEP-10-MaW22 3 d / 2010 Water Bq/L Arnericium-241 1.0323 1.30 0.91 -1.69 Acceptable MAPEP-10-MaW22 3 d / 2010 Water :/ Cesium-134 0.027 0.00 ---- Acceptable MAPEP-10-MaW22 3 d/2010 Water Bq/L Cesium-137 63.1 60.6 42.4-78.8 Acceptable MAPEP-10-MaW22 3 " / 2010 Water Bq/L Cobalt-57 29.2 28.3 19.8-36.8 Acceptable MAPEP-10-MaW22 3 rd/ 2010 Water Bq/L Cobalt-60 -0.021 0.00 --- Acceptable MAPEP-10-MaW22 3 r / 2010 Water Bq/L Hydrogen-3 107 90.8 63.6-118.0 Acceptable MAPEP-10-MaW22 3 ,d/ 2010 Water Bq/L I ron-55 0.24 0.00 --- Acceptable MAPEP-10-MaW22 3 ,d/ 2010 Water Bq/L Manganese-54 28.83 26.9 18.8 -35.0 Acceptable MAPEP-10-MaW22 3 'd / 2010 Water Bq/L Nickel-63 57.7 59.9 41.9-77.9 Acceptable MAPEP-10-MaW22 3 rd /2010 Water Bq/L Plutonium-238 1.213 1.93 1.35-2.51 Not Acceptable MAPEP-10-MaW22 3 'd / 2010 Water Bq/L Plutonium-239/240 0.026 0.009 -- Acceptable MAPEP-10-MaW22 3 , / 2010 Water Bq/L Strontium-90 -0.01 0.00 --- Acceptable MAPEP-10-MaW22 3 rd /2010 Water Bq/L Technetium-99 -0.4 0.00 -- Acceptable MAPEP-10-MaW22 3 rd /2010 Water Bq/L Uranium-234/233 1.163 1.22 0.85-1.59 Acceptable MAPEP-10-MaW22 3 rd/2010 Water Bq/L Uranium-238 1.223 1.25 0.88-1.63 Acceptable MAPEP-10-MaW22 3 rd / 2010 Water Bq/L Zinc-65 45.9 40.7 28.5 - 52.9 Acceptable MAPEP-10-GrW22 3 ,d/2 010 Water Eq/L Gross Alpha 0.559 0.676 >0.0 - 1.352 Acceptable MAPEP-10-GrW22 3 W / 2010 Water BqgL Gross Beta 3.110 3.09 1.55-4.64 Acceptable

! Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 32 of 51 Acceptance Quarter I Sample GEL Known Range/

R2mnln Number Year Media Unit Analvte I Nuctide Value value I Ratio Evaluation

.m..e NumerF 3ear /201 Fit.

M N/e .u3.. 5. 7 4.0 -7.4... Not Accctab MAPEP-10-RdF22 3 rd / 2010 Filter ug/sample Uranium-238 10.2 5.7 4.0 - 7.4 Not Acceptable MAPEP-10-RdF22 3 r' / 2010 Filter ug/sample Uranium-Total 10.2 5.7 4.0 -7.4 Not Acceptable MAPEP-10-RdF22 3 d/ 2 0 10 Filter Bq/sample Americium-241 0.2637 0.146 0.102 - 0.190 Not Acceptable MAPEP-10-RdF22 3 d/ 2 0 10 Filter Bq/sample Cesium-134 4.323 2.13 1.49-2.77 Not Acceptable MAPEP-10-RdF22 3 Id / 20 10 Filter Bq/sample Cesium-137 3.070 1.53 1.07-1.99 Not Acceptable MAPEP-10-RdF22 3 ,d / 2010 Filter Bq/sample Cobalt-57 0.0002 0.00 -- Acceptable MAPEP-10-RdF22 3 r* / 2010 Filter Bq/sample Cobalt-60 5.187 2.473 1.731 - 3.215 Not Acceptable MAPEP-10-RdF22 3 rd / 2 0 10 Filter Bq/sample Manganese-54 6.483 3.02 2.11 -3.93 Not Acceptable MAPEP-10-RdF22 3 rd / 2010 Filter Bq/sample Plutonium-238 0.010 0.0010 -- Acceptable 0.0582 -

MAPEP-10-RdF22 3 d/ 2010 Filter Bq/sample Plutonium-239/240 0.164 0.0832 0.1082 Not Acceptable MAPEP-10-RdF22 3 ,d /2010 Filter Bq/sample Strontium-90 -0.004 0.00 -- Acceptable MAPEP-10-RdF22 3 d / 2 0 10 Filter Bq/sample Uranium-234/233 0.137 0.068 0.048 - 0.088 Not Acceptable MAPEP-10-RdF22 3 'd / 2 0 10 Filter Bq/sample Uranium-238 0.147 0.071 0.050 - 0.092 Not Acceptable MAPEP-10-RdF22 3 ' / 2010 Filter Bq/sample Zinc-65 -0.106 0.00 -- Acceptable MAPEP-10-GrF22 3 rd12010 Filter Bq/sample Gross Alpha 0.303 0.427 >0.0 - 0.854 Acceptable MAPEP-10-GrF22 3 rd / 2010 Filter Bq/sample Gross Beta 1.433 1.29 0.65 - 1.94 Acceptable 0.0875 -

MAPEP-10-RdV22 3 rd/ 2 0 10 Vegetation ug/sample Uranium-235 0.090 0.1250 0.1625 Acceptable MAPEP-10-RdV22 3 d/ 2010 Vegetation ug/sample Uranium-238 12.5 17.9 12.5 - 23.3 Not Acceptable MAPEP-10-RdV22 3 d / 2 0 10 Vegetation ug/sample Uranium-Total 13.9 18.0 12.6-23.4 Acceptable MAPEP-10-RdV22 3 rd / 2010 Vegetation Bq/sample Americium-241 0.179 0.225 0.158 - 0.293 Acceptable MAPEP-10-RdV22 3 rd / 2010 Vegetation Bq/sam ple Cesium-134 3.098 4.39 3.07-5.71 Acceptable MAPEP-10-RdV22 3 'd / 2010 Vegetation Bql/sample Cesium-137 2.185 3.06 2.14-3.98 Acceptable MAPEP-10-RdV22 3 ,d / 2010 Vegetation Bq/sample Cobalt-57 0.009 0.00 --- Acceptable MAPEP-10-RdV22 3 d / 2010 Vegetation Bg/sample Cobalt-60 3.076 3.27 2.29-4.25 Acceptable MAPEP-10-RdV22 3 'd / 2010 Vegetation Bq/sample Manganese-54 0.004 0.00 -- Acceptable MAPEP-10-RdV22 3 'd/ 2 0 10 Vegetation Bq/sample Plutonium-238 0.149 0.160 0.112-0.208 Acceptable MAPEP-10-RdV22 3 rd / 2010 Vegetation Bq/sample Plutonium-239/240 0.0026 0.0008 --- Acceptable MAPEP-10-RdV22 3 m / 2010 Vegetation Bq/sample Strontium-90 0.033 0.00 ---- Acceptable MAPEP-10-RdV22 3 'd / 2010 Vegetation Bq/sample Uranium-234/233 0.184 0.216 0.151 - 0.281 Acceptable MAPEP-10-RdV22 3 rd /2010 Vegetation Bq/sample Uranium-238 0.184 0.223 0.156 - 0.290 Acceptable MAPEP-10-RdV22 3 rd / 2010 Vegetation Bg/sample Zinc-65 6.844 7.10 4.97 - 9.23 Acceptable

Laboratories LLC 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/ Sample GEL Known Acceptance Number Year Media Unit Analyte / Nuclide Value value Range/Ratio Evaluation RAD - 80 1 /2010 Water pCi/L Barium-133 73.5 72.9 61.0 -80.2 Acceptable RAD - 80 1" / 2010 Water pCi/L Cesium-134 69.2 63.4 51.5-69.7 Acceptable RAD- 80 1" / 2010 Water pCi/L Cesium-137 118.0 120 108-134 Acceptable RAD - 80 1" / 2 0 10 Water pCi/L Cobalt-60 87.7 90 81 - 101 Acceptable t

RAD - 80 l" /2010 Water pCi/L Zinc-65 213.0 210 189-246 Acceptable RAD - 80 It /2010 Water pCi/L Gross Alpha 51.3 42.5 22.0-53.9 Acceptable RAD - 80 1" / 2010 Water pCi/L Gross Beta 52.0 54.2 37.0 - 61.1 Acceptable RAD - 80 1 st 2 0 10 Water pCi/L Radium-226 16.9 17.8 13.2-20.3 Acceptable RAD - 80 1" /2010 Water pCi/L Radium-228 20.4 18.2 12.3-21.8 Acceptable RAD - 80 1ý /2010 Water pCi/L Uranium (Nat) 49.0 50.2 40.7-55.8 Acceptable RAD - 80 1" 12010 Water ug/L Uranium (Nat) Mass 67.3 73.2 59.4 - 81.4 Acceptable RAD - 80 1l"/ 2010 Water pCi/L Tritium 19200 18700 16400-20600 Acceptable RAD - 80 1' / 2010 Water pCi/L Strontium-89 37.9 53.3 42.3-60.9 Not Acceptable RAD - 80 l'/ 2010 Water pCi/L Strontium-90 52.3 42.2 31.1 -48.4 Not Acceptable RAD - 80 1t/2010 Water pCi/L Iodine-131 30.5 28.2 23.5- 33.1 Acceptable RAD - 82 3 ,d/ 2 0 1 0 Water pCi/L Barium-133 112.0 89.1 75.0-98.0 Not Acceptable RAD - 82 358 /2010 Water pCi/L Cesium-134 115.0 88.3 72.4 -97.1 Not Acceptable RAD - 82 3 5/2010 Water pCi/L Cesium-137 271 210 189-232 Not Acceptable RAD - 82 358 / 2010 Water pCi/L Cobalt-60 98.4 72.8 65.5-82.5 Not Acceptable RAD - 82 358 / 2010 Water pCi/L Zinc-65 161 110 99.0- 131 Not Acceptable RAD - 82 3 / 2010 Water pCi/L Gross Alpha 65.5 61.1 32.0 - 75.9 Acceptable RAD - 82 3 8 / 2010 Water pCi/L Gross Beta 56.7 56.4 38.6 - 63.6 Acceptable RAD - 82 3 r / 2010 Water pCi/L Radium-226 15.9 17.1 12.7- 19.6 Acceptable RAD- 82 3d / 2010 Water pCi/L Radium-228 18.9 16.1 10.8- 19.4 Acceptable RAD - 82 3d / 2010 Water pCi/L Uranium (Nat) 58.0 49.6 40.2 - 55.1 Not Acceptable RAD - 82 3 r' / 2010 Water uq/l Uranium (Nat) Mass 89.1 72.3 58.7-80.4 Not Acceptable RAD - 82 3 d /2010 Water pCi/L Tritium 18500 19800 17300 - 21700 Acceptable RAD - 82 3 "/2010 Water pCi/L Strontium-89 60.6 55.3 44.1 -62.9 Acceptable RAD - 82 3 "d/ 2010 Water pCi/L Strontium-90 47.1 32.8 24.0-38.0 Not Acceptable RAD - 82 35 / 2010 Water pCi/L Iodine-131 32.2 28.4 23.6-33.3 Acceptable 090710N 3,d / 2010 Water pCi/L Barium-133 86.9 92.9 78.3 - 102 Acceptable 090710N 3 "d/ 2010 Water pCi/L Cesium-134 93.8 79.4 65.0 - 87.3 Not Acceptable 090710N 3,, / 2010 Water pCi/L Cesium-137 55.5 54.6 49.1 -62.9 Acceptable 090710N 3" / 2010 Water pCi/L Cobalt-60 120.0 117 105- 131 Acceptable 090710N 3d/2010 Water pCi/L Zinc-65 129 99.5 89.6- 119 NotAcceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 34 of 51 Sample Quarter / Sample GEL Known Acceptance Number Year Media Unit I'Analvte / Nuclide Value value Ranae/ Ratio Evaluation 09071 ON 3 ,d / 2010 Water ucQ/L Uranium (Nat) Mass 48.6 49.3 39.8 - 55.1 Acceptable RAD - 83 40 /2010 Water pCi/L Strontium-89 65.3 68.5 55.8- 76.7 Acceptable RAD - 83 4" /2010 Water pCi/L Strontium-90 41.5 43 31.7 - 49.3 Acceptable 10051 ON 4" /2010 Water pCi/L Strontium-89 49.9 51.4 40.6- 58.9 Acceptable 10051ON 4" /2010 Water pCi/L Strontium-90 35.4 41.3 30.4-47.5 Acceptable 112210H1 4" /2010 Water pCi/L Barium-133 66.3 65.9 54.9- 72.5 Acceptable 112210H1 4h /2010 Water pCi/L Cesium-134 71.6 71.6 58.4- 78.8 Acceptable 112210H1 4" /2010 Water pCi/L Cesium-137 151 146 131-163 Acceptable 11221OH1 4" /2010 Water pCi/L Cobalt-60 90.2 84.5 76.0-95.3 Acceptable 112210H1 4" /2010 Water pCi/L Zinc-65 207 186 167-219 Acceptable 112210H2 4" /2010 Water pCi/L Plutonium-238 102.0 108 81.7- 134 Acceptable 112210H2 4" / 2010 Water pCi/L Plutonium-239 77.6 86.3 66.8-107 Acceptable 122810P 4" /2010 Water pCi/L Barium-133 70.9 68.9 57.5- 75.8 Acceptable 122810P 4" / 2010 Water pCi/L Cesium-134 43.0 43.2 34.5-47.5 Acceptable 122810P 4" /2010 Water pCi/L Cesium-137 122 123 111 -138 Acceptable 122810P 4" /2010 Water pCi/L Cobalt-60 58.7 53.4 48.1 -61.3 Acceptable 122810P 4" /2010 Water pCi/L Zinc-65 116 102 91.8- 122 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 35 of 51 TABLE 5 2010 ERA PROGRAM (MRAD) PERFORMANCE EVALUATION RESULTS

SUMMARY

Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analyte / Nuclide Value value Range/Ratio Evaluation MRAD-12 2nd /2010 Soil pCi/kg Actinium-228 1570 1850 1190 - 2600 Acceptable MRAD-12 21d / 2010 Soil pCi/kg Americium-241 1130 1500 896 -1930 Acceptable MRAD-12 2' 12010 Soil pCi/kq Bismuth-212 1430 1640 430-2450 Acceptable MRAD-12 2"d /2010 Soil pCi/kg Bismuth-214 1080 1410 865-2030 Acceptable MRAD-12 2"d /2010 Soil pCi/kg Cesium-134 3040 3110 2000-3740 Acceptable MRAD-12 2 d /2010 Soil pCi/kg Cesium-137 4330 4440 3400 -5770 Acceptable MRAD-12 2"d /2010 Soil pCi/kg Cobalt-60 2120 2140 1560-2870 Acceptable MRAD-12 2"d /12010 Soil pCi/kg Lead-212 1540 1520 980-2140 Acceptable MRAD-12 2d / 2010 Soil pCikg/ Lead-214 1300 1440 862-2140 Acceptable MRAD-12 2"d /2010 Soil pCi/kg Manganese-54 < 22.9 0 .... Acceptable MRAD-12 2 "' /2010 Soil pCi/kq Potassium-40 11100 10900 7900- 14800 Acceptable MRAD-12 2"d /2010 Soil pCi/kg Thorium-234 1600 1610 511 -3070 Acceptable MRAD-12 2nd / 2010 Soil pCi/kg Uranium-238 1600 1610 984- 2040 Acceptable MRAD-12 2"' / 2010 Soil pCi/kg Zinc-65 2790 2470 1960-3310 Acceptable MRAD-12 2d / 2010 Soil pCi/kg Strontium-90 7870 8180 2960 - 13300 Acceptable MRAD-12 2e /2010 Soil pCi/kg Uranium-234 < 1158 1620 1030-2010 Not Acceptable MRAD-12 2e /12010 Soil pCi/kg Uranium-238 908 1610 984 - 2040 Not Acceptable MRAD-12 2"d / 2010 Soil ug/kg Uranium-Total (mass) 2920 4820 2650 -6060 Acceptable MRAD-12 2"d / 2010 Soil pCi/kg Strontium-90 7870 8180 2960- 13300 Acceptable MRAD-12 2nd / 2010 Soil pCi/kg Americium-241 1120 1500 896 - 1930 Acceptable MRAD-12 2d /2010 Soil pCi/kg Plutonium-238 1360 1330 761 -1870 Acceptable MRAD-12 2" / 2010 Soil pCi/kg Plutonium-239 1220 1260 860- 1670 Acceptable MRAD-12 2" /2010 Soil pCi/kg Uranium-234 1230 1620 1030- 2010 Acceptable MRAD-12 2"d /2010 Soil pCi/kg Uranium-238 1440 1610 984-2040 Acceptable MRAD-12 2"d /2010 Soil pCil/kg Uranium-Total 2789 3300 1880- 4460 Acceptable MRAD-12 2"d / 2010 Soil uq/k - Uranium-Total (mass) 4350 4820 2650 -6060 Acceptable MRAD-12 2" / 2010 Vegetation pCi/kg Uranium-238 1604 1710 1200-2160 Acceptable MRAD-12 2"' / 2010 Vegetation ug/kg Uranium-Total (mass) 5270 5120 3520-6610 Acceptable MRAD-12 21d /2010 Vegetation pCi/kg Americium-241 2410 3140 1790-4310 Acceptable MRAD-12 2"e / 2010 Vegetation oCi/kg Curium-244 429 528 260-822 Acceptable MRAO-12 2" /2010 Vegetation pCi/kg Plutonium-238 3090 3040 1640-4450 Acceptable MRAD-12 2" / 2010 Vegetation pCi/kg Plutonium-239 2830 2800 1740-3820 Acceptable MRAD-12 2" /2010 Vegetation pCi/kg Uranium-234 1680 1720 1180-2280 Acceptable MRAD-12 2"" / 2010 Vegetation pCi/k I Uranium-238 1770 1710 1200-2160 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 36 of 51 Sample Quarter / Sample GEL Known Acceptance Number Year Media Unit Aalyte I Nuclide Value value Range/ Ratio Evaluation MRAD-12 2"d /2010 Vegetation pCi/kg Uranium-Total (mass) 5290 5120 3520-6610 Acceptable MRAD-12 2"d /2010 Vegetation pCi/kg Americium-241 3600 3140 1790-4310 Acceptable MRAD-12 24 / 2010 Vegetation pCi/kg Cesium-134 1750 1670 956-2310 Acceptable MRAD-12 2e /2010 Vegetation pCi/kg Cesium-137 1550 1470 1080-2040 Acceptable MRAD-12 2"d /2010 Vegetation pCi/kg Cobalt-60 2100 1970 1330-2830 Acceptable MRAD-12 2"d /2010 Vegetation pCi/kg Manganese-54 < 9.6 0,00 .... Acceptable MRAD-12 2"' /2010 Vegetation pCi/kg Potassium-40 40800 34900 25100 - 49400 Acceptable MRAD-12 2" /2010 Vegetation pCi/kg Uranium-238 < 1240 1710 1200-2160 Not Acceptable MRAD-12 2' / 2010 Vegetation pCi/kg Zinc-65 1630 1360 983-1860 Acceptable MRAD-12 2" / 2010 Vegetation pCi/kg Strontium-90 7880 9120 5100- 12100 Acceptable MRAD-12 2" /2010 Air Filter pCi/Filter Uranium-238 61.5 61.5 39.4 -87.3 Acceptable MRAD-12 2"d / 2010 Air Filter ug/Filter Uranium-Total (mass) 183 184 114-264 Acceptable MRAD-12 2"d /2010 Air Filter pCi/Filter Americium-241 52.7 60.0 35.1 - 82.3 Acceptable MRAD-12 2"d / 2010 Air Filter pCi/Filter Plutonium-238 63.9 64.1 44.0-84.3 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Plutonium-239 56.6 56.7 41.1 -73.4 Acceptable MRAD-12 2' / 2010 Air Filter pCi/Filter Uranium-234 68.8 62.1 39.1 -92.0 Acceptable MRAD-12 2" /12010 Air Filter pCi/Filter Uranium-238 69.5 61.5 39.4-87.3 Acceptable MRAD-12 2d / 2010 Air Filter pCi/Filter Uranium-Total 141 126 64.4 -200 Acceptable MRAD-12 2"d / 2010 Air Filter ug/Filter Uranium-Total (mass) 208 184 114 - 264 Acceptable MRAD-12 2"d / 2010 Air Filter pCi/Filter Americium-241 76 60 35.1 -82.3 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Cesium-134 504 436 284- 540 Acceptable MRAD-12 2" / 2010 Air Filter pCi/Filter Cesium-137 785 701 527-921 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Cobalt-60 591 523 405-653 Acceptable MRAD-12 2" / 2010 Air Filter pCi/Filter Manganese-54 < 5.07 0.00 --- Acceptable MRAD-12 2' / 2010 Air Filter pCi/Filter Uranium-238 < 61.2 61.5 39.4-87.3 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Zinc-65 462 389 269-539 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Strontium-90 178 187 82.3-291 Acceptable MRAD-12 2"d / 2010 Air Filter pCi/Filter Iron-55 375 359 158-559 Acceptable MRAD-12 2"n /2010 Air Filter ug/Filter Uranium-Total (mass) 175 184 114-264 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Gross Alpha 68.2 79.6 41.3- 120 Acceptable MRAD-12 2"' / 2010 Air Filter pCi/Filter Gross Beta 72 70.4 43.4- 103 Acceptable MRAD-12 2" / 2010 Water pCi/L Uranium-238 67.9 60.9 46.5-75.5 Acceptable MRAD-12 2r" / 2010 Water ug/L Uranium-Total (mass) 213 182 143-225 Acceptable MRAD-12 2" / 2010 Water pCi/L Americium-241 79.1 95.6 65.5- 129 Acceptable MRAD-12 2" /12010 Water pCi/L Plutonium-238 79.5 109 82.4-135 Not Acceptable MRAD-12 2"d /2010 Water pCi/L Plutonium-239 103 105 81.2-130 Acceptable MRAD-12 2' /2010 Water pCi/l Uranium-234 62.4 61.4 46.3-79.2 Acceptable MRAD-12 2"d /2010 Water pCi/L Uranium-238 66.1 60.9 46.5-75.5 Acceptable MRAD-12 2"d / 2010 Water pCi/L Uranium-Total 131.5 125 90.0- 166 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 37 of 51 Sample Quarter / Sample GEL Known Acceptance Number Year Media Unit Analte / Nuclide Value value IRanae/ Ratio Evaluation MRAD-12 2rd / 2010 Water pCi/L Americium-241 123 95.6 65.5-129 Acceptable MRAD-12 2"d / 2010 Water pCi/L Cesium-134 454 417 308 -479 Acceptable MRAD-12 2"d /2010 Water pCiIL Cesium-137 693 654 556 -783 Acceptable MRAD-12 2"M/ 2010 Water pCi/L Cobalt-60 813 727 633 - 859 Acceptable MRAD-12 2"d / 2010 Water pCi/L Manganese-54 < 7.7 0.00 --- Acceptable MRAD-12 2n" / 2010 Water pCi/L Uranium-238 < 155 60.9 46.5-75.5 Not Acceptable MRAD-12 2d' /2010 Water pCi/L Zinc-65 632 533 452-664 Acceptable MRAD-12 2"d / 2010 Water pCi/L Strontium-90 708 719 456-961 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Actinium-228 1460 1830 1170-2580 Acceptable MRAD-13 4h /2010 Soil pCi/kg Americium-241 845 1120 669-1440 Acceptable MRAD-13 4" /2010 Soil pCi/kg Bismuth-212 <538 2070 543-3100 Not Acceptable MRAD-13 4" /2010 Soil pCi/kg Bismuth-214 818 983 603-1410 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Cesium-1 34 2230 2240 1440-2700 Acceptable MRAD-13 4" /2010 Soil pCi/kg Cesium-137 3400 3530 2700-4580 Acceptable MRAD-13 4" /2010 Soil pCi/kg Cobalt-60 4580 4780 3480-6420 Acceptable MRAD-13 4" 12010 Soil pCi/kg Lead-212 1550 1640 1060-2310 Acceptable MRAD-13 4" /2010 Soil pCi/kg Lead-214 1030 969 580- 1440 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Manganese-54 < 38.0 0.00 ---- Acceptable MRAD-13 4"'/ 2010 Soil pCi/kg Potassium-40 10500 10700 7760- 14500 Acceptable MRAD-13 4h /2010 Soil pCi/kg Thorium-234 1010 1340 425-2550 Acceptable MRAD-13 4' /2010 Soil pCi/kg Uranium-238 1010 1340 819- 1700 Acceptable MRAD-13 4" /2010 Soil pCi/kg Zinc-65 2420 2300 1820-3080 Acceptable MRAD-13 4t /2010 Soil pCi/kg Americium-241 928 1120 669-1440 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Plutonium-238 1170 1280 733- 1800 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Plutonium-239 1070 1180 805- 1570 Acceptable MRAD-13 4' /12010 Soil pCi/kg Uranium-234 899 1360 862- 1690 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-238 1080 1340 819- 1700 Acceptable MRAD-13 4h /2010 Soil pCi/t Uranium-Total 2027.4 2770 1580-3740 Acceptable MRAD-13 4t /2010 Soil ug/kg Uranium-Total (mass) 3240 4040 2220-5080 Acceptable MRAD-13 4"' /2010 Soil pCi/kg Uranium-234 1190 1360 862-1690 Acceptable MRAD-13 4h / 2010 Soil pCi/kg Uranium-238 903 1340 819- 1700 Acceptable MRAD-13 4" /2010 Soil ug/kg Uranium-Total 2093 2770 1580- 3740 Acceptable MRAD-13 4" / 2010 Soil pCi/kg Uranium-Total (mass) 2685 4040 2220 - 5080 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-234 1110 1360 862-1690 Acceptable MRAD-13 4t /2010 Soil pCi/kg Uranium-238 1090 1340 819- 1700 Acceptable MRAD-13 4t / 2010 Soil pCi/kg Uranium-Total 2253 2770 1580 -3740 Acceptable MRAD-13 4h /2010 Soil ug/kg Uranium-Total (mass) 3241 4040 2220-5080 Acceptable MRAD-13 4" / 2010 Soil Iu1k I Uranium-Total (mass) 2820 4040 2220-5080 Acceptable MRAD-13 4t / 2010 Soil pCi/kg Strontium-90 10953 9270 3350- 15100 Acceptable

! Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 38 of 51 Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analvte / Nuclide Value value Range/ Ratio Evaluation MRAD-13 4"`/ 2010 Vegetation pCi/kg Plutonium-238 3740 4740 2560 -6940 Acceptable MRAD-13 4"' /2010 Vegetation pCi/kg Plutonium-239 3590 4470 2770 -6100 Acceptable MRAD-13 4" / 2010 Vegetation pCi/kg Uranium-234 3600 4010 2750-5320 Acceptable MRAD-13 4-'/ 2010 Vegetation pCi/kg Uranium-238 4000 3980 2800-5030 Acceptable MRAD-13 4"'/ 2010 Vegetation pCi/kg Uranium-Total 7834 8180 5620- 10600 Acceptable MRAD-13 4' /2010 Vegetation ug/kg Uranium-Total (mass) 12000 11900 8180- 15400 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Cesium-134 1200 1040 595- 1440 Acceptable MRAD-13 4" 12010 Vegetation pCi/kg Cesium-137 1420 1260 924- 1750 Acceptable MRAD-13 4"' /2010 Vegetation pCi/kg Cobalt-60 1130 1010 683- 1450 Acceptable MRAD-13 4" / 2010 Vegetation pCi/kg Manganese-54 < 39.8 0.00 --- Acceptable MRAD-13 4' / 2010 Vegetation pCi/kg Potassium-40 29000 22600 16200 - 32000 Acceptable MRAD-13 4" / 2010 Vegetation pCi/kg Zinc-65 1380 1210 874- 1650 Acceptable MRAD-13 4h' /2010 Vegetation pCi/kg Strontium-90 9800 7810 4360- 10400 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Uranium-234 73.5 71.8 45.2 - 106 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-Total 149 146 74.6-232 Acceptable MRAD-13 4"' / 2010 Air Filter ug/Filter Uranium-Total (mass) 224.5 213 132-306 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Americium-241 .70.1 74.1 43.3 - 102 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Plutonium-238 70.8 72.9 50.0- 95.8 Acceptable MRAD-13 4"' 12010 Air Filter pCi/Filter Plutonium-239 65.6 69.6 50.5-90.1 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Uranium-234 69.9 71.8 45.2-106 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Uranium-238 66.8 71.2 45.6- 101 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Uranium-Total 142 146 74.6-232 Acceptable MRAD-13 4" /2010 Air Filter ug/Filter Uranium-Total (mass) 201 213 132-306 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Cesium-134 405 388 253 - 480 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Cesium-137 532 514 386-675 Acceptable MRAD-13 4h / 2010 Air Filter pCi/Filter Cobalt-60 531 479 371- 598 Acceptable MRAD-1 3 4"' / 2010 Air Filter pCi/Filter Manganese-54 < 3.58 0.00 --- Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Zinc-65 552 465 322 - 644 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Strontium-90 80.2 159 70.0-247 Acceptable MRAD-13 4h / 2010 Air Filter pCi/Filter Iron-55 707 626 275-974 Acceptable MRAD-13 4"h / 2010 Air Filter ug/Filter Uranium-Total (mass) 192 213 132-306 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Gross Alpha 74.2 52.3 27.1 -78.7 Acceptable MRAD-13 4h /2010 Air Filter pCi/Filter Gross Beta 55.6 52.7 32.5- 77.0 Acceptable MRAD-13 4"' / 2010 Water pCi/L Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4"' /2010 Water pCi/L Uranium-238 107 108 82.5- 134 Acceptable MRAD-13 4h /2010 Water pCi/L Uranium-Total 218 221 159-294 Acceptable MRAD-13 4' / 2010 Water ug/L Uranium-Total (mass) 318 323 253-399 Acceptable MRAD-13 4"' /2010 Water pCi/L Americium-241 164 176 120-238 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 39 of 51 Sample Quarter / Sample GEL Known IAcceptance Number Year Media Unit Analvte / Nuclide Value value IRanae/ Ratio Evaluation MRAD-13 4h /2010 Water pCi/L Plutonium-239 136 148 114- 183 Acceptable MRAD-13 4' / 2010 Water pCi/L Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-238 114 108 82.5- 134 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-Total 226.8 221 159-294 Acceptable MRAD-13 4" /2010 Water ug/L Uranium-Total (mass) 342 323 253-399 Acceptable MRAD-13 4" 12010 Water pCi/L Americium-241 178 176 120-238 Acceptable MRAD-13 4" /2010 Water pCi/L Cesium-1 34 495 492 363- 565 Acceptable MRAD-13 4" /2010 Water pCi/L Cesium-137 620 625 531 -749 Acceptable MRAD-13 4' /2010 Water pCi/L Cobalt-60 732 714 622- 844 Acceptable MRAD-13 4" / 2010 Water pCi/L Manganese-54 <5 0.00 ---- Acceptable MRAD-13 4" /2010 Water pCi/L Zinc-65 557 489 414-610 Acceptable MRAD-13 4" /2010 Water pCi/L Strontium-90 817 921 585- 1230 Acceptable MRAD-13 4t /2010 Water pCi/L Uranium-234 104 109 82.2- 140 Acceptable MRAD-13 4"' /2010 Water pCi/L Uranium-238 108 108 82.5- 134 Acceptable MRAD-13 4" / 2010 Water pCi/L Uranium-Total 217 221 159- 294 Acceptable MRAD-13 4" / 2010 Water ug/L Uranium-Total (mass) 321 323 253-399 Acceptable MRAD-13 4" / 2010 Water pCi/L Iron-55 1220 825 480- 1100 Acceptable MRAD-13 4h /2010 Water pCi/L Gross Alpha 145 146 64.8 -216 Acceptable MRAD-13 4" / 2010 Water pCi/L Gross Beta 171 143 83.6-210 Acceptable MRAD-13 4" / 2010 Water pCi/L Tritium 20900 21600 14100 - 31900 Acceptable

Laboratories LLC 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

Quarter / Sample GEL Known Acceptance Sample Number Year Media Unit Analye / Nuclide Value value Range) Ratio Evaluation NY-332 3263 2" /12010 Water pCi/L Gross Alpha 33.0 26.8 15.0- 38.6 Acceptable NY-332 3263 2"" /2010 Water pCi/L Gross Beta 64.6 54.0 41.3 - 66.7 Acceptable NY-332 3262 2r / 2010 Water pCi/L Cesium-134 14.8 14.0 10.7-17.3 Acceptable NY-332 3262 2"' /2010 Water pCi/L Barium-133 27.8 25.6 20.6 - 30.5 Acceptable NY-332 3262 2" /.2010 Water pCi/L Zinc-65 146 139 121 -156 Acceptable NY-332 3262 2"" / 2010 Water pCiVL Cobalt-60 98.3 99.5 90.3- 109 Acceptable NY-332 3262 2r4 / 2010 Water pCi/L Cesium-137 124 123 112- 134 Acceptable NY-332 3264 2" / 2010 Water pCi/I Iodine-131 23.4 26.4 21.9-31.0 Acceptable NY-332 3264 2' / 2010 Water pCi/L Iodine-131 26.8 26.4 21.9- 31.0 Acceptable NY-332 3261 2nd / 2010 Water PCVL Strontium-89 46.7 41.9 33.4- 50.4 Acceptable NY-332 3261 2"d /2010 Water pCi/L Strontium-90 33.9 34.8 27.1-42.5 Acceptable NY-332 3266 2"d 2010 Water pCi/L Tritium 9610 9490 8390- 10600 Acceptable NY-332 3265 2ý / 2010 Water pCi/L Radium-226 12.1 13.2 10.4- 16.0 Acceptable NY-332 3265 2"" / 2010 Water pCi/L Radium-228 9.90 8.91 6.08- 11.7 Acceptable NY-332 3265 2" /2010 Water pCi/L Uranium (activity) 48.81 44.7 37.9-51.4 Acceptable NY-337 3763 4" / 2010 Water pCi/L Gross Alpha 32.8 41.6 24.3-58.9 Acceptable NY-337 3763 4h / 2010 Water pCi/L Gross Beta 29.3 27.5 18.3 -36.7 Acceptable NY-337 3762 4" /2010 Water pCi/L Cesium-134 51.0 42.0 35.8-49.2 Not Acceptable NY-337 3762 4h /2010 Water pCi/L Cesium-137 29.3. 27.3 22.4- 32.1 Acceptable NY-337 3762 4" /2010 Water pC./L Cobalt-60 13.6 13.2 9.72- 16.7 Acceptable NY-337 3762 4" / 2010 Water pCi/L Zinc-65 134 122 104- 138 Acceptable NY-337 3762 4h / 2010 Water pCi/L Barium-133 50.5 50.9 43.3 -59.4 Acceptable NY-337 3764 4" / 2010 Water pCi/L Iodine-131 13.4 18.2 14.7-21.7 Not Acceptable NY-337 3764 4" /2010 Water pCi/L Iodine-131 13.5 18.2 14,7-21.7 Not Acceptable NY-337 3761 4" / 2010 Water pCi/L Strontium-89 47.8 61.3 51.3-71.4 Not Acceptable NY-337 3761 4" /2010 Water pCi/ll Strontium-90 12.0 14.9 11.0-18.8 Acceptable NY-337 3766 4" / 2010 Water pCi/L Tritium 14400 15300 13500 - 17000 Acceptable NY-337 3765 4" / 2010 Water pCi/L Radium-226 13.2 10.6 8.30- 12.9 Not Acceptable NY-337 3765 4h / 2010 Water pCi/L Radium-228 6.51 6.07 3.91 -8.22 Acceptable NY-337 3765 4h 12010 Water pCi/L Uranium (activity) 17.5 16.0 13.2- 18.7 Acceptable

Laboratories LLC 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 Cobaft-60 Performance Evaluation Results and % Bias 150.0 ** :*,,* :=*= = :: .***, ,: .,.*:*

130.0 90.0 -,::h * **;:!.,

70.0 "

30.0 -- - - - - Lir

-10.0

-30.0 4

-50.0 2010 Analytical Date

Laboratories LLC 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 0-- Cs-1 37 cc 40. 0 Lower Control Limit Upper Control 20.'0 Limit 0.i0

-20.10

-40.10 2010 Analytical Date

Laboratories LLC 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

7 --------------------- Loe oto Limit

.- . UpperControl I -500.0 2010 Analytical Date

IM Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 44 of 51 FIGURE 4 STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND % BIAS I* 2010 Strontium-90 Performance Evaluation Results and % Bias 60.0.~ .

40.0 Sr-90

20. Lower Control Limit

-60.0+::3 U)> =!

Upper Control Limit

-20.

-40.0 2010 Analytical Date

ILaboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 45 of 51 FIGURE 5 GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Gross Alpha Performance Evaluation Results and % Bias 100.0 4 ~ -~ .",

80.0 1/4. ,4 60.0 j~W * , .

40.0 a---- Gross Alpha 20.0

. Lower Control 0.0 Limit UpperControl

-20.0 Limit

-40.0

-60.0 1

->~-~. -

-80.0

-100.0 2010 Analytical Date

Laboratorles LLC 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 - .'. 3/4

.4 ~, -K 1>

- A

'A .

60.0 K N A .~ '0.~~

U...

4 ,.. <. t 40.0 4 A -o-- Gross Beta 20.0 '-K.. ~A 4 4* ~ .~ Lower Control 0.0 Limit

.4% A~ ~ ~

-- - Upper Control

-20.0 Limit

~

-40.0

-60.0 A ~.74A '.4,,

-80.0

-100.0 2010 Analytical Date

Laboratories LL.

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 Iodine-131 Performance Evaluation Results and % Bias

.4.4

,.44. .'4~.4.4~4~<4 4.4.. .4..4...4.4 .4 .4 .'~ .4.4",.>.

40.0

.4 .4 4 ~.4.4 "".4 .4

.4.4.44.4.4 .4.4.44.4 4.4.44 .444<44.4.4~ .4

.4.4 4. ~ .4 .'.44 44.4.4 4 .4.444> 4.~4.44. 44.>

20.0 .4.4.4

>..'.4.4 4.4 4.4.44.4.4.4.4.4.4.4 4- .4 4 .4 -

.4. 4.4.4.4<4.44.. .4.4444 (44 4.4.4 4 .4 4.4.4.4.44.4.4.4.44.44

~.'.'.4.4< .4~ .4 4.44 .4. 4 ~ .44.:.

0.0 *-- 1-131

.4.44.4.444>.444.44.' .44 .44.44.4 .'44

<44...

-20.0

.4.4.4A~-'~* .. 4~ ~

.44.4.4-1 4~.4 7

Lower Control a Limit 4~k44'4.4

.4.4.4 .44 Upper Control

-40.0 .y*.4.4 .4 .4.4.4....'.

44~.4,44'> .4.4.444 .4.. 4.44 A..>, ~ 4.~44 A ',

Limit 4....4.44.4.4 4,~ ~ ~ .444~~ .4 .4~.

~.4.4 A . ~ '44 ~4.4~ 4#4A.4'.444

-60.0 '444.'< .

4 4 -.

4

.44.444 ~~4<gŽ. 4 4<4.~, *A "4 "' ~'"~ ~ *4 4 I....U4AA<.4W 4 .

.4, 4 . .4 .4.4 4

.44"1 ~'~~'4-,4',..>..t44. AA.4.'4

-80.0 A~~4'O, 444 .4.4

.4~44.4~44 4. 4<4.~~4.4.4>4.44.~.4

...44,4.44..44 .4> 4 4A4A~1/4....4;.4A..4

.4.44.4.4.4.44.4 .4.4.44.4.'

.4.

.4 4 ~>4.4 4.4.'44.

-100.0 2010 Analytical Date

.1

Laboratories LLC 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! (.- 25%) Precisioi.n Critbria (% RPD1 )

P

Laboratory Control'Sample. D~uplicate 1

'2010& (LCS)j DUP orLCSD)

. ......... WITHIN >OUTSIDE... WITHIN... OUTSIDE

________________I 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 tkricd4_______________ _______ ___________

Iodine-131 11 0 11 0 Gamma 63 0 64 0 Iodine-131 61 0 61 0 Strontium-90 33 0 34 0 solid,> ,i ___ ______________

Gamma 27 0 29 0 Carbon-14 2 0 2 0 Iron-55 3 0 3 0 Nickel-63 3 0 3 0 Strontium-90 11 0 11 0 Gamma 38 0 36 0 Strontium-90 3 0 3 0

~etation___________ . .

Gamma (Including Iodine) 59 0 61 0 Strontium-90_ _3 0 3 0 r

Wat&:0:3.0.*t Carbon-14 2 0 2 0 Gross Alpha/Beta 98 0 99 0 Gamma 177 0 170 0 Iodine-131 46 0 47 0 Iron-55 33 0 33 0 Nickel-63 35 0 35 0 Strontium-90 80 0 81 0 Tritium 176 0 174 0 Total 1590 0 1591 0 Note 1: The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%. Ifone result is above the MDC and the other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below the MDC. The RPD must be 100% or less. In the situation where both results are above the MDC but one result is greater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to 20%. If both results are below MDC. then the limits on % RPD are not applicable.

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

~ANALYSIS INTUMN CS DUP LCS DUP LCs DUP LCS DUP I..TR: : NT ', FILTER FILTER SWIPE <SWIPE SOLID SOLID OILV OIL' Americium-241 Alpha Spec 2 2 47 38 485 477 13 12 Americium-243 Alpha Spec 2 2 1 0 53 50 2 2 Carbon-14 Liquid Scintillation 4 3. 38 32 98 99 9 9 Gamma (long list of isotopes) Gamma Spec 283 272 47 42 770 792 27 27 Gross Alpha/Beta Gas Flow 111 135 20 18 20 18 42 42 Iodine-129 Gamma Spec 99 88 28 28 28 28 9 9 Iodine-131 Gamma Spec 6 4 0 0 0 0 0 0 Iron-55 Liquid Scintillation 89 8 30 24 46 48 8 8 Alpha Spec and Isotopic Plutonium Liquid Scintillation 212 186 82 66 687 683 12 11 Isotopic Strontium Gas Flow 165 136 41 34 365 367 1 1 Isotopic Thorium Alpha Spec 82 59 0 0 371 372 0 0 Alpha Spec and ICP-Isotopic Uranium MS 137 112 13 10 713 697 24 24 Lead-210 Gas Flow 44 26 0 0 33 34 0 0 Nickel-59 Gamma Spec 65 60 28 22 64 64 7 7 Nickel-63 Liquid Scintillation 95 89 39 30 75 74 8 8 Neptunium-237 Alpha Spec 67 59 32 23 107 107 10 9 Polonium-210 Alpha Spec 18 6 0 0 5 6 0 0 Promethium-137 Liquid Scintillation 8 5 0 0 12 11 0 0 Radium-226 Lucas Cell 44 31 0 0 167 175 0 0 Radium-228 Gas Flow 29 25 0 0 129 124 0 0 Technetium-99 Liquid Scintillation 87 75 32 24 142 145 12 12 Tritium Liquid Scintillation 90 76 42 24 358 359 19 19 AN....L.YSIS........

.. ....... U-= ____DU LCS __ __

bUP>%,LCS "DLJP" ICS DUP' ANALYSIST MISC <MISC MISC <MISC>

<'2SLUDGE SLUDGE SOLID KSOLID LIQUID LIQUID~ LIQUID ~LIQUIDl Americium-241 Alpha Spec 4 4 231 220 22 19 383 335 Americium-243 Alpha Spec 1 1 21 21 5 4 12 11 Carbon-14 Liquid Scintillation 5 5 110 108 34 33 218 175 Gamma (long list of isotopes) Gamma Spec 17 18 260 256 72 68 747 820 Gross Alpha/Beta Gas Flow 27 27 112 109 87 80 1169 1180 Iodine-129 Gamma Spec 1 1 88 88 21 21 162 94 Iodine-131 Gamma Spec 0 0 0 0 0 0 11 14 Iron-55 Liquid Scintillation 3 3 74 72 42 43 123 103 Alpha Spec or Liquid Isotopic Plutonium Scintillation 7 7 143 137 77 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 0 0 0 0 0 0 114 108 Nickel-59 Gamma Spec 0 0 68 66 9 9 76 63 Nickel-63 Liquid Scintillation 5 5 74 72 50 51 172 143 Neptunium-237 Alpha Spec 3 3 0 0 16 15 193 168 Polonium-210 Alpha Spec 0 0 1 1 0 0 3 3 Promethium-137 Liquid Scintillation 1 1 5 5 3 3 6 2 Radium-226 Lucas Cell 2 2 25 25 5 5 502 505 Radium-228 Gas Flow 0 0 27 28 1 1 432 426 Technetium-99 Liquid Scintillation 15 15 179 175 39 40 41 41 Tritium Liquid Scintillation 9 9 125 122 8 8 898 824

Laboratories LLC 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 OPEN/ ISSUE Cause and Disposition CLOSED CARRI 10209-542 OPEN Eckert & Ziegler Analytics Monitoring in progress Fe-59 Failure in Milk CARR100617-496 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.

CARR100617-497 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 sensitivity by gamma spectroscopy. Future PT analysis will be performed using a more sensitive method.

CARR1O1210-527 CLOSED MRAD 13 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.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 51 of 51 CARR100318-487 CLOSED RAD-80 PT Failures 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 carders 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.

CARR1O1203-525 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)

(1This 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)

(')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)

('This table summarizes results of tests conducted by E-LAB and the Third-party tester.

(2)Environmental dosimeter results are free in air.

F:1/4DMIN\CORRES\EL 138-10 27

Measurement of strontium-90 (90Sr) and other radionuclides in edible tissues and bone/carapace of fish and blue crabs from the lower Hudson River, New York Lawrence C. Skinner Timothy J. Sinnott New York State Department of Environmental Conservation Division of Fish, Wildlife and Marine Resources 625 Broadway Albany, New York 12233 November 2009

Table of Contents INTRODUCTION .......................................................................................................................... 2 METHODS ..................................................................................................................................... 2 RESULTS ....................................................................................................................................... 4 DISCUSSION ................................................................................................................................. 5 CONCLUSIONS............................................................................................................................. 8 ACKNOWLEDGMENTS .............................................................................................................. 8 REFERENCES CITED ................................................................................................................... 9 Table 1: 90Sr concentrations in edible tissues of fish taken from the lower Hudson River in 2006

....................................................................................................................................................... 11 Table 2: 90Sr and other radionuclide concentrations in edible tissues of fish and blue crab from three locations on the lower Hudson River in June 2007. ............................................................ 12 Table 3: 90Sr and other radionuclide concentrations in bone of fish and carapace of blue crab from three locations on the lower Hudson River in June 2007..................................................... 13 Table 4: Radionuclide concentrations measured in bone of fish from three locations on the lower Hudson River in June 2007. .......................................................................................................... 14 Table 5: Comparison of 90Sr concentrations in bone and edible flesh of fish. ............................. 15 Figure 1 ......................................................................................................................................... 16 1

INTRODUCTION In 2005, Entergy Nuclear Operations, Inc. (Entergy), the owner of the Indian Point Nuclear Power Plant located at Buchanan, NY on the Hudson River, discovered a spent fuel pool water leak to groundwater while installing a new crane to facilitate transfer of Unit 2 spent fuel to dry cask storage. This leak was determined to have generated a groundwater plume of tritium (3H).

During efforts to track the 3H plume, 90Sr was discovered in a downgradient portion of the plume and traced back to a leak in the Unit 1 spent fuel pool.

Because site groundwater flows to the Hudson River, the 2006 Radiological Environmental Monitoring Program (REMP) conducted by Entergy was modified to include 90Sr as an analyte in fish samples. 90Sr was detected in four of 10 samples of fish taken from the river in the vicinity of the power plant, and in three of five samples from an upstream reference location near the Roseton Generating Station in Newburgh, NY (Table 1). The tissues analyzed were composites of edible flesh from fish representing several species.

The data was reviewed by Entergy and compared with data for other facilities and historical information. Entergy concluded that the 90Sr levels were low and may be indistinguishable from background levels from fallout from nuclear weapons testing in the 1950s and 1960s (Entergy 2007). The New York State Departments of Health (NYSDOH) and Environmental Conservation (NYSDEC) (the Agencies) concurred. However, the Agencies were concerned that the home ranges of several sampled species, and all striped bass, may overlap at the two sampling sites. In order to assure independence of sampling sites, the Agencies initiated this one time enhanced radiological surveillance for 2007.

The objectives of the enhanced radiological monitoring effort were to:

gain information about the levels, impacts, and possible 90Sr sources at the reference locations and the indicator station,

determine if significant spatial differences in 90Sr concentrations were present,

to assess whether or not 90Sr concentrations in the bones and flesh of fish signify heightened risk either to aquatic life in the Hudson River, and

provide information for an independent assessment of potential public health impacts.

METHODS Part of Entergys REMP requirements is to conduct routine radiological surveillance using composite samples of edible tissues of fish two or more important commercial and/or recreational fish or invertebrate species. Possible target species include striped bass (Morone saxatilis), white perch (Morone americana), American eel (Anguilla rostrata), white catfish (Ictalurus catus) or channel catfish (Ictalurus punctatus), sunfishes including pumpkinseed (Lepomis gibbosus), bluegill (L. macrochirus) or redbreast sunfish (L. auritus), and blue crab (Callinectes sapidus). Sampling occurs in spring and fall of each year at two locations, i.e., in 2

the vicinity of Indian Point Nuclear Power Plant (approximately river mile 42) and the vicinity of Roseton Generating Station (the traditional reference station at approximate river mile 65). One composite sample of each species is collected at each location and is analyzed for a host of radionuclides.

Sampling is conducted by Normandeau Associates, Inc. under contract with Entergy, and samples consist of by-catch of fish or blue crabs taken as a consequence of sampling for other purposes. All samples were collected in June 2007 and were frozen (- 20º C) in a locked freezer until prepared for shipment for chemical analyses. The prepared sample mass is a minimum of 1600 g and a maximum of 2000 g. This sample mass is split three ways. The first split of 1000 g went to Entergys contract laboratory, AREVA, Inc. The second split of 300 to 500 g went to the Nuclear Regulatory Commission for analysis at the Oak Ridge Institute for Science and Education (ORISE). The third split (300 to 500 g) was sent to the NYSDOH Wadsworth Center for Labs and Research. Collection records and chain of custody are maintained for all samples (Appendix A).

The one-time design modifications for the 2007 effort included: the addition of carp (Cyprinus carpio) - a benthic feeder - to the target species list; adding 90Sr to the list of radionuclide analytes; analysis of fish bone or crab carapace; and sampling fish at a third location, i.e., the Catskill Region between river miles 107 and 125 (Figure 1). This upstream location assures appropriate separation of fish populations that are resident to the river, and, consequently, assures isolation of resident fish populations from the potential influence of the Indian Point Nuclear Power Plant.

Normandeau Associates, Inc. prepared the samples of edible portions of fish and blue crabs.

Skinless filets were excised from each specimen, composites by species were made, and each composite was thoroughly ground and homogenized. Subsamples were developed for each laboratory. These were double packaged in food grade plastic bags, labeled, frozen, and shipped to each participating laboratory.

The remaining carcasses of the fish and blue crabs were provided to the NYSDECs laboratory at the Hale Creek Field Station, Gloversville, NY where they were prepared for radiological analyses by the NYSDOH Wadsworth Center for Labs and Research. In addition to the required species, samples of other fish species were provided to Hale Creek including yellow perch (Perca flavescens), rock bass (Ambloplites rupestris), smallmouth bass (Micropterus dolomieui),

largemouth bass (Micropterus salmoides), black crappie (Pomoxis nigromaculatus), and brown bullhead (Ameiurus nebulosus).

Preparation of bone and carapace samples was conducted in several steps. First, the samples were cleaned to remove as much muscle, skin, scales or other tissues as possible. The resulting bone samples were placed in a fume hood and air dried for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then each sample was individually bagged, labeled and stored in a locked freezer until they were sent for further cleaning by dermestid beetles maintained by the New York State Museum at their Rensselaer Technology Park offices in Troy, NY. Each bone sample was maintained in an individual labeled sample container while undergoing dermestid cleaning. Following this process, each sample was frozen to kill the dermestids, rethawed, and the frass (dermestid larval carcasses and 3

fecal material) was removed from the bone. Finally, the skeletal and cranial bones (fins were excluded) were placed in food grade plastic bags, labeled and submitted to the NYSDOH Wadsworth Center for Labs and Research. Continuing chain of custody was maintained throughout the process (Appendix B).

Analysis of radionuclides were conducted by NYSDOH using two methods:

90 Sr analyses of fish bone were conducted by USEPA Method 905.0 (Krieger and Whittaker 1980b). Steps in this method include isolation of strontium, measurement of total strontium, hold the strontium for decay to allow time for the ingrowth of the yttrium-90 daughter, isolate and measure yttrium-90.

Common indicator radionuclides (134Cs, 137Cs, 60Co, and 40K) were analyzed using USEPA Method 901.1 (Krieger and Whittaker 1980a).

Concentrations reported in Tables are the value for the sample +/- the analytical standard error.

For example, a value of 8 +/- 2 pCi/kg would mean the best estimate concentration is 8 pCi/kg although the concentration may be as little as 6 pCi/kg or as much as 10 pCi/kg.

Statistical tests for spatial differences in concentrations employed the Kruskal-Wallis test when there were three comparisons. The Mann-Whitney test was used when there were only two comparisons (Conover 1980). These non-parametric tests were chosen because of their ability to reduce the influence of outlier data. A difference was considered significant when the probability was less than 0.05 (P < 0.05).

RESULTS Edible Tissue Samples 90 Sr was detected in only one sample of edible tissues, i.e., 8 +/- 3 pCi/kg in blue crab taken from the vicinity of the Indian Point facility. Detection limits ranged between 3 and 6 pCi/kg (Table 2). Only the determinations made by the NYSDOH Wadsworth Center for Labs and Research are reported since their analytical methods were the most sensitive of the three laboratories conducting the analyses. No detectable radionuclides were reported by the other two laboratories.

Bone and Carapace Samples 90 Sr concentrations in bone of fish or the carapace of blue crabs are shown in Table 3. 90Sr concentrations are relatively consistent among all fish species, including striped bass, within locations. Mean and standard deviation concentrations for all fish at the three locations were:

4

90 Location n Sr Concentration (pCi/kg)

Indian Point 10 199 +/- 58 Roseton 10 222 +/- 67 Catskill 10 271 +/- 69 The single blue crab sample, taken from the Roseton area, had 760 pCi/kg of 90Sr in the carapace. This is the highest 90Sr concentration reported, and twice the highest fish concentration of 360 pCi/kg in yellow perch from the Catskill area.

Among other radionuclides analyzed, 134Cs, 137Cs, 58Co and 60Co were not detected in bone or carapace of any sample. Detection limits ranged from 0.2 to 80 pCi/kg for 134Cs, 137Cs and 60Co, and an order of magnitude greater for 58Co. 40K was present in nearly all samples within a limited range of concentrations and with mean and standard concentrations by area in fish as follows:

40 Location n K Concentration (pCi/kg)

Indian Point 9 2840 +/- 678 Roseton 10 3540 +/- 978 Catskill 10 2740 +/- 614 Table 4 presents concentrations of other radionuclides that were detected in bones of fish.

DISCUSSION 90 Sr in bone versus edible tissues Whicker et al. (1990) compared 90Sr concentrations in bone and edible flesh of fish taken from a cooling water pond at the USDOE Savannah River nuclear power plant. Similar comparisons were made for fish in waters downstream of the Nuclear Fuels Services Inc. nuclear waste treatment plant in West Valley, NY, and in Lake Ontario (NYSDEC 1971) (Table 5). In these studies the ratio of 90Sr in bone to that in edible fish tissue (90Sr bone:flesh ratio) ranged from less than one to 1198. The highest value is considered an outlier. The mean 90Sr bone:flesh ratio, excluding the outlier, was about 35. (The mean must be viewed with caution since the West Valley study did not indicate whether the 90Sr quantification method was the same as that used in the Savannah River study; wet weight versus dry mass in flesh, or original mass versus ash weight of bone. If the methods used are not the same the ratios may not be comparable.) If it is assumed that the two studies are comparable, and we apply this ratio to bone in the present study, the 90Sr concentration in edible tissues would very near or below the detection limit. This tends to confirm the reported lack of detection of 90Sr in edible flesh of fish from the lower Hudson River (Tables 2 and 5) in 2007.

5

Spatial differences There were no significant differences (P = 0.096) in 90Sr concentrations between the three locations for resident fish. Looking at reference stations only, there was no significant difference in 90Sr at Catskill and Roseton. Inclusion of striped bass, a migratory fish species, would not have changed the overall conclusion because of the similarity of 90Sr concentrations.

In contrast, 40K was statistically greater (P = 0.018) at the Roseton station than at either Indian Point or Catskill (which were equivalent) despite the small difference in average 40K concentrations. Inclusion of striped bass would not have changed the finding. 40K is a naturally occurring primordial radionuclide (Copplestone et al. 2001) which is expected to be found at these concentrations in fish and is not associated with nuclear waste for power production or fallout from weapons testing (Eisler 1994). The differing levels, albeit they are small differences, have no known significance.

Lastly, there were no differences between stations for 224Ra. There were insufficient data to assess spatial differences for other radionuclides.

Relationship to criteria The U.S. Department of Energy (USDOE) developed ecological standards for the protection of terrestrial animals, terrestrial plants, and aquatic animals based on published literature reviews of the effects of ionizing radiation on biota (NCRP 1991; IAEA 1992; UNSCEAR 1996). The standard for the protection of aquatic animals is:

The absorbed dose to aquatic animals should not exceed 1 rad/day (10 mGy/day or 400 µGy/hr1) from exposure to radiation or radioactive material releases into the aquatic environment.

This dose is specified in DOE Order 5400.5 (USDOE 2002). This standard is designed to protect populations of aquatic organisms, not individuals. At absorbed dose rates below the standard, populations will be maintained but some individual animals can suffer adverse impacts.

USDOE (2002) provides dose conversion factors (DCF) which can be used to estimate the absorbed dose from the internal abundance/activity of a radionuclide accumulated by an aquatic organism. The DCF calculations are conservative in that they assume all of the energies of radioactive decay are retained in the tissue of the organism, and that the radionuclides were presumed to be homogenously distributed in tissue. They are expressed in units of Rad/day per pCi/g wet weight. Using the DCFs it is possible to estimate the absorbed dose from the internal radionuclide concentration. Additional conversions were employed to express the total dose in 1

A Gray (Gy) is a standard international unit of absorbed dose of radiation adopted by the International Commission on Radiological Protection in 1977. 1 Rad = 0.01 Gy; conversely, 1 Gy = 100 Rads.

6

the Standard International (SI) units for chronic absorbed dose rates of µGy/hr. USDOE (2002) did not report DCFs for 224Ra and 40K.

The highest tissue/bone concentrations of radionuclides listed in Tables 1 - 4 are the upper bound concentrations (i.e., measured concentration plus the 95% confidence interval) of 809 pCi/kg of 90Sr from blue crab carapace (Table 3), 370 pCi/kg of 238U and 320 pCi/kg 232Th measured in the bones of striped bass (Table 4). All three samples were collected from the Roseton Generating Station (River Mile 65). Using the DCFs from (USDOE 2002), these concentrations can be converted to an internal dose rates:

809 pCi/kg of 90Sr would result in an estimated internal dose rate of 0.02 µGy/hr; 370 pCi/kg of 238U would result in an estimated internal dose rate of 0.7 µGy/hr; and 320 pCi/kg of 232Th would result in an estimated internal dose rate of 5.5 µGy/hr.

All of these dose rates range from about two to five orders of magnitude below the USDOE (2002) standard of protection for aquatic animals. While the highest internal dose to striped bass from a single radionuclide was from 232Th. However, to estimate the total internal dose, the internal doses from all radionuclides present must be summed. Using the upper bound concentrations for 226Ra, 232Th, and 238U with the DCFs from (USDOE 2002), the total internal dose to striped bass collected at the Roseton Power Generating Station can be estimated to be 8.4

µGy/hr. A DCF for 224Ra is not available, probably because this is a short-lived radionuclide with a half-life of only 3.7 days (Eisler 1994). 224Ra disintegrates rapidly through a series of seven daughter radionuclides to the stable nuclide 208Pb with a total half-life for the whole series of about 65 minutes (Nebergall et al. 1968).

The standards of protection published in USDOE (2002) were derived from a qualitative evaluation of radiological effects data. The European Union (EU) took a more quantitative approach to deriving ecological standards. EU assembled a large database of the impacts of ionizing radiation to biota and evaluated the studies to identify critical toxicity endpoints. Once the critical toxicity endpoints were determined, they were used with standard EU risk assessment protocols to derive a chronic Predicted-No-Effect-Dose Rates (PNEDR) screening value of 10

µGy/hr for freshwater, terrestrial, and marine/estuarine ecosystems (Garnier-Laplace and Gilbin 2006). The total absorbed dose from the internal concentration of 232Th, 226Ra, and 238U in striped bass is less than the chronic screening no effects dose rate derived by the EU.

The internal dose rate conversion factors from USDOE (2002) are conservative, but they do not take into account absorbed doses received from external sources, such as radionuclides in the water and sediment. There is no way to estimate those dose rates without measurements.

USDOE (2002) provides a method for estimating the total absorbed dose to biota from both external and internal sources. This approach uses Biota Concentration Guides (BCG)s which are concentrations of 23 different radionuclides in water, soil, and sediment. If the BCG concentrations are not exceeded, the total absorbed dose will not exceed the USDOE (2002) standards of protection. In order to utilize this method, simultaneous samples of water and sediment must be collected and analyzed in the immediate vicinity of suspected unregulated releases of radioactive materials into the Hudson River.

7

No excursions above ecological standards for the protection of aquatic animals appear to have occurred. However, the current monitoring effort does not allow for the full assessment of risks to aquatic animals. To fully evaluate the risks, the concentrations of the full range of 23 radionuclides listed in USDOE (2002) in both water and sediment samples collected from the same location simultaneously should be sampled. This would allow for the full use of the Graded Approach for Evaluating Radiation Doses to Aquatic and Terrestrial Biota as described in USDOE (2002) to be employed to evaluate and assess risks to aquatic biota.

The 23 radionuclides which should be sampled include: 241Am, 144Ce, 135Cs, 137Cs, 60Co, 154Eu, 155 Eu, 3H, 129I, 131I, 239Pu, 226Ra, 228Ra, 125Sb, 90Sr, 99Tc, 232Th, 233U, 234U, 235U, 238U, 65Zn, and 95 Zr.

CONCLUSIONS Two conclusions can be made.

1. There are no apparent excursions above criteria for the protection of biota based on the radionuclide data available. The levels of radionuclides - including 90Sr - were two to five orders of magnitude lower than criteria established for protection of freshwater ecosystems.

2. There were no spatial differences in concentrations of 90Sr and 224Ra in resident fish from the three locations sampled in the lower Hudson River (i.e., Indian Point Nuclear Power Plant, and the reference sites at the Roseton Generating Station and at Catskill). In contrast, 40K levels were somewhat greater in the vicinity of Roseton Generating Station, but the differing concentrations have no known significance.

ACKNOWLEDGMENTS The authors gratefully acknowledge the assistance and cooperation of a number of people during the conduct of this study. These include: Michael Ritchie and his staff at Normandeau Associates Inc. who provided the carcasses of fish and blue crabs used in this study; Anthony Gudlewski, Brian Buanno and John Finn at the NYSDECs Hale Creek Field Station who conducted the initial cleaning and drying of carcass samples; and Joseph Bopp of the NYS Museum who maintained and oversaw use of the dermestid beetle colony. Helpful comments on manuscript were provided by Larry Rosenman (NYSDEC), Anthony Forti, Edward Horn, Robert Snyder and Stephen Gavitt (NYSDOH), and Kathleen Skinner (Russell Sage College).

8

REFERENCES CITED Conover, W. J. 1980. Practical Nonparametric Statistics, second edition. John Wiley and Sons, New York.

Copplestone, D., S. Bielby, S. R. Jones, D. Patton, P. Daniel, and I. Gize. 2001. Impact Assessment of Ionizing Radiation on Wildlife. R&D Publication 128. Environment Agency, Bristol, UK. Updated March 2003. ISBN: 1 85705590 X. 222 pp.

Eisler, R. 1994. Radiation hazards to fish, wildlife and invertebrates: A synoptic review.

Biological Rep. 29, National Biological Service, US Department of the Interior, Washington, DC. 124 p.

Entergy. 2007. Annual Radiological Environmental Operating Report. January 1 - December 31, 2006. Entergy, Indian Point Energy Center, Buchanan, NY.

Garnier-Laplace, J., and Gilbin R. (Eds), 2006. ERICA Deliverable 5: Derivation of Predicted-No-Effect-Dose-Rate values for ecosystems (and their sub-organizational levels) exposed to radioactive substances. ERICA contract number FI6R-CT-2004-508847, date of issue: 28 2006, Project Coordinator: Swedish Radiation Protection Authority.

IAEA, 1992. Effects of Ionizing Radiation on Plants and Animals at Levels Implied by Current Radiation Protection Standards. International Atomic Energy Agency Technical Reports Series No. 332, Vienna, 1992.

Joshi, S. R. 1991. Radioactivity in the Great Lakes. The Science of the Total Environment 100:61-104.

Krieger, H. L., and E. L. Whittaker. 1980a. Prescribed procedures for measurement of radioactivity in water. Section 4. Gamma emitting radionuclides in drinking water. Method 901.1. EPA-600/4-80-032. US Environmental Protection Agency, Cincinnati, OH.

Krieger, H. L., and E. L. Whittaker. 1980b. Prescribed procedures for measurement of radioactivity in water. Section 9. Radioactive strontium in drinking water. Method 905.0.

EPA-600/4-80-032. US Environmental Protection Agency, Cincinnati, OH.

NCRP. 1991. Effects of Ionizing Radiation on Aquatic Organisms. National Council on Radiation Protection and Measurements (NCRP) Report No. 109, NCRP, Bethesda, Md.

9

Nebergall, W. H., F. C. Schmidt, and H. F. Holtzclaw, Jr., 1968. General Chemistry, Third Edition. D. C. Heath and Company, Lexington, Massachusetts.

Neel, J. W., and K. H. Larson. 1963. Biological availability of strontium-90 to small native animals in fallout patterns from the Nevada test site. Pp. 45-49. In: V. Schultz and A. W.

Klement, Jr. (eds.), Radioecology. Reinhold, NY.

NYSDEC. 1971. 1970 Annual report of environmental radiation in New York State. New York State Department of Environmental Conservation, Albany, NY. 58 p.

USDOE, 2002. A Graded Approach for Evaluating Radiation Doses to Aquatic and Terrestrial Biota. U.S. Department of Energy, DOE-STD-1153-2002, July 2002.

UNSCEAR, 1996. Sources and effects of ionizing radiation. United Nations Scientific Committee on the Effects of Atomic Radiation, UNSCEAR 1996 Report to the General Assembly, with Scientific Annex. United Nations, New York, 1996.

Whicker, F. W., W. C. Nelson, and A. F. Gallegos. 1972. Fallout 137Cs and 90Sr in trout from mountain lakes in Colorado. Health Physics 23:519-527.

Whicker, F. W., E. Pinder III, J. W. Bowling, J. J. Alberts, and I. L. Brisbin, Jr. 1990.

Distribution of long-lived radionuclides in an abandoned reactor cooling reservoir. Ecological Monographs 60:471-496.

Wrenn, M. E., J. E. Lentsch, M. Eisenbud, G. J. Lauer, and G. P. Howells. 1971. Radiocesium distribution in water, sediment, and biota in the Hudson River estuary from 1964 through 1970.

Pp. 334-343. In: D. J. Nelson (ed.), Radionuclides in ecosystems. Volume 1. Proceedings of the Third National Symposium on Radioecology, 10-12 May 1971, Oak Ridge, TN.

10

90 Table 1: Sr concentrations in edible tissues of fish taken from the lower Hudson River in 2006.

90 Sr concentration (pCi/kg wet weight)

Measured Location Species detection limit Sample1 (DL)

Indian Point Striped bass 8.5 <DL Nuclear Power Plant Blue crab 5.7 <DL (indicator site) American eel 7.1 <DL Catfish 6.4 <DL Sunfish 15 <DL White perch 9.0 18.8 Roseton Generating Striped bass 4.2 <DL Station Blue crab 11.0 13.6 (reference site) American eel 4.3 <DL Catfish 7.6 <DL Sunfish 9.6 17.1 White perch 8.7 24.5 1

Analyses by Entergy Nuclear Operations, Inc. contract laboratory, i.e., AREVA, Inc.

11

90 Table 2: Sr and other radionuclide concentrations in edible tissues of fish and blue crab from three locations on the lower Hudson River in June 1

2007 .

No. in Concentration (pCi/kg wet weight)2 Location Species 90 134 137 58 60 40 sample Sr Cs Cs Co Co K Indian Point Blue crab 62 8+/-3 <3 <3 <3 <4 2510 +/- 180 Nuclear Power Striped bass 7 <4 <1.9 <2 <2 <2 2400 +/- 150 Plant White perch 57 <3 <2 <3 <3 <3 2750 +/- 170 (RM 42)3 Catfish 15 <4 <1.9 <2 <3 <2 2580 +/- 150 American eel 19 <4 <2 <3 <3 <2 2320 +/- 150 Carp 2 <5 <1.7 <2 <3 <1.8 2590 +/- 150 Sunfishes 79 <6 <2 <2 <3 <2 2660 +/- 170 Roseton Striped bass 1 NA4 NA NA NA NA NA Generating White perch 116 <5 <2 <3 <3 <2 2440 +/- 160 Station Catfish 45 <3 <1.8 <2 <2 <1.8 2620 +/- 150 (RM 65) American eel 15 <4 <2 <3 <3 <2 2490 +/- 160 Carp 4 <4 <1.7 <1.9 <3 <1.8 2480 +/- 150 Sunfishes 30 <3 <3 <3 <3 <3 2590 +/- 170 Catskill Region White perch 108 <4 <2 6+/-3 <3 <2 2390 +/- 160 (RM 107 - 125) Catfish 18 <3 <1.9 9+/-3 <3 <1.9 2640 +/- 160 American eel 15 <4 <2 <3 <3 <2 2000 +/- 140 Carp 2 <4 <2 <2 <3 <2 2450 +/- 150 Sunfishes 18 <4 <2 <3 <3 <2 2620 +/- 170 1

All analyses by the New York State Department of Healths Wadsworth Center for Labs and Research.

2 A less than (<) value indicates the concentration is less than the specified detection limit for the sample.

3 RM = Approximate location in river mile(s).

4 NA = Not analyzed. Analyses by the Nuclear Regulatory Commissions laboratory, Oak Ridge Institute for Science and Education

[ORISE], reported 90Sr at <4 pCi/kg, and 134Cs, 137Cs, 58Co and 60Co as <10 pCi/kg each; no analyses were conducted of 40K.

90 Table 3: Sr and other radionuclide concentrations in bone of fish and carapace of blue crab from three locations on the lower Hudson River in June 2007.

No. in Concentration (pCi/kg wet weight)1 Location Species 90 134 137 58 60 40 sample Sr Cs Cs Co Co K Indian Point Nuclear Striped bass 7 96 +/- 89 <4 <4 <21 <4 2710 +/- 190 Power Plant White perch 28 190 +/- 34 <5 <4 <21 <3 2240 +/- 170 (River Mile 42) Yellow perch 27 240 +/- 50 <7 <6 <30 <6 2600 +/- 200 Brown bullhead 8 220 +/- 62 <7 <6 <30 <6 4100 +/- 300 Channel catfish 1 230 +/- 48 nd nd nd nd nd White catfish 7 160 +/- 46 <5 <4 <20 <5 3000 +/- 200 American eel 21 150 +/- 31 <9 <9 <41 <8 3200 +/- 300 Carp 2 290 +/- 62 <3 <3 <17 <3 1670 +/- 130 Pumpkinseed 5 250 +/- 58 <20 <16 <100 <19 2800 +/- 400 Sunfishes 35 160 +/- 32 <7 <6 <30 <6 3200 +/- 300 Roseton Generating Blue crab 6 760 +/- 49 <11 <9 <90 <9 3800 +/- 300 Station Striped bass 1 140 +/- 57 <7 <5 <60 <6 2030 +/- 160 (River Mile 65) White perch 55 270 +/- 62 <9 <7 <80 <8 3100 +/- 300 White perch 70 270 +/- 39 <8 <8 <70 <8 3000 +/- 300 Brown bullhead 6 250 +/- 72 <5 <4 <40 <4 3110 +/- 180 Brown bullhead 33 220 +/- 63 <6 <6 <60 <5 3400 +/- 300 Channel catfish 5 130 +/- 79 <6 <6 <60 <6 4900 +/- 300 American eel 15 140 +/- 78 <10 <9 <90 <10 3500 +/- 300 Perch 9 260 +/- 42 <12 <10 <100 <10 3100 +/- 300 Sunfishes 26 210 +/- 66 <10 <10 <90 <8 3900 +/- 400 Rock bass 1 330 +/- 310 <80 <60 <600 <80 5400 +/- 100 Catskill Region White perch 74 310+/- 46 <8 <6 <70 <6 2300 +/- 200 (River Miles 107 - 125) Brown bullhead 6 300 +/- 50 <10 <7 <90 <8 2700 +/- 200 Channel catfish 11 220 +/- 83 <4 <4 <60 <4 2800 +/- 200 American eel 16 120 +/- 77 <11 <8 <90 <9 3300 +/- 300 Sunfishes 23 290 +/- 95 <10 <8 <90 <10 4000 +/- 400 Carp 2 260 +/- 31 <4 <4 <40 <3 2050 +/- 180 Largemouth bass 6 220 +/- 38 <3 <2 <40 <2 2530 +/- 130 Smallmouth bass 2 330 +/- 45 <10 <13 <170 <15 2800 +/- 300 Black crappie 1 300 +/- 120 <30 <20 <200 <20 3000 +/- 400 Perch 17 360 +/- 41 <12 <9 <140 <10 1900 +/- 200 1

A less than (<) value indicates the concentration is less than the specified detection limit for the sample. nd = not determined.

13

Table 4: Radionuclide concentrations measured in bone of fish from three locations on the lower Hudson River in June 2007.

No. in Concentration (pCi/kg wet weight)

Location Species 224 226 232 238 sample Ra Ra Th U Indian Point Nuclear Striped bass 7 26 +/- 9.0 21 +/- 9.0 47 +/- 15 Power Plant White perch 28 33 +/- 9.0 25 +/- 9.0 (River Mile 42) Yellow perch 27 31 +/- 13 30 +/- 14 Brown bullhead 8 23 +/- 10 22 +/- 12 White catfish 7 17 +/- 8.0 Roseton Generating Striped bass 1 105 +/- 14 153 +/- 19 290 +/- 30 290 +/- 80 Station White perch 55 31 +/- 17 28 +/- 17 (River Mile 65) White perch 70 47 +/- 16 Brown bullhead 33 24 +/- 11 50 +/- 20 Perch 9 59 +/- 17 34 +/- 18 Catskill Region White perch 74 40 +/- 20 (River Miles 107 - 125) Brown bullhead 6 60 +/- 20 Sunfishes 23 48 +/- 18 Carp 2 16 +/- 7.0 19 +/- 9.0 Perch 17 21 +/- 18 <20 50 +/- 30 14

Table 5: Comparison of 90Sr concentrations in bone and edible flesh of fish.

Concentration Ratio State/Site Location Species n Reference Bone Edible flesh bone:flesh South Carolina/ Pond B Largemouth bass 28 ~ 14.5 Bq/g ash 0.47 Bq/g dm1 31 Whicker et al. 1990 USDOE Savannah Yellow bullhead 28 ~ 13 0.086 151 River Plant New York/ Cattaraugus Cr. NYSDEC 1971 Nuclear Fuel Services, - Rt. 16 bridge Suckers nr2 228 pCi/kg 82 pCi/kg 2.8 Inc.

- Springville Dam Suckers nr 10491 1679 6.2 Suckers nr 31000 500 62

- mouth (Sunset Bay) Rainbow trout nr 127 3 42 Carp nr 606 23 26 Suckers nr 9587 8 1198 Salmon nr 173 246 0.7 New York/ Buttermilk Cr. Trout nr 320,000 pCi/kg 5400 pCi/kg 59 NYSDEC 1971 Nuclear Fuel Services, - at Bond Road Suckers nr 620,000 12,000 52 Inc. Suckers nr 89,537 14,456 6.2 New York Lake Ontario Bass nr 1410 pCi/kg < DL nc4 NYSDEC 1971

- at Brockwood Bluegill nr 312 62 pCi/kg 5.0 (Wayne County) Bullhead nr 330 24 14 Sunfish nr 89 17 5.3 Perch nr 3516 40 88 Sucker nr 497 15 33 Black crappie nr 671 < DL3 nc Perch nr 271 29 9.3 Largemouth bass nr 408 10 41 Rock bass nr 270 25 11 Silver bass nr 485 13 37 Carp nr 898 15 60 New York/Indian Point Hudson River 5 species 5 204 <6 34 This study Nuclear Power Plant New York/Roseton Hudson River 4 species 5 204 <5 41 This study Generating Station New York Hudson River 5 species 5 240 <4 60 This study

- at Catskill 1 2 3 4 dm = dry mass. nr = Not reported. DL = Detection limit. nc = Not calculated; detection limit not reported.

15

Figure 1 16

17 18 19 20 21 22 23 24 25 26 27 28 29 30

ML11293A347

Text

Subject:

Dear Messrs. Turk and Stuyvenberg:

Subject:

SUBJECT:

Dear Sir or Madam:

Enclosure:

SUMMARY

2.0 INTRODUCTION

5.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

2.0 INTRODUCTION

5.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search