Text

2009 Annual Radiological Environmental Operating Report
	ML101241151
Person / Time
Site:	Salem, Hope Creek
Issue date:	04/23/2010
From:	Eilola E, Wagner L; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LR-N10-01239, FOIA/PA-2011-0113
	Download: ML101241151 (136)
	v • d • e

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 PSEG NuclearLLC Technical Specification Section 6.9.1.7 (Salem)

Technical Specification Section 6.9.1.6 (Hope Creek)

APR 2 3 2010 LR-N10-0139 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 Salem Nuclear Generating Station, Unit Nos. land 2 Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311

Subject:

2009 Annual Radiological Environmental Operating Report As required by Section 6.9.1.7 of Appendix A to Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station Unit Nos. 1 and 2, and Section 6.9.1.6 of Appendix A to the Operating License NPF-57 for Hope Creek Generating Station, PSEG Nuclear hereby transmits one copy of the 2009 Annual Radiological Environmental Operating Report. This report summarizes the results of the radiological environmental surveillance program for 2009 in the vicinity of the Salem and Hope Creek Generating Stations. The result of this program for 2009 was specifically compared to the result of the pre-operational program.

There are no regulatory commitments contained in this correspondence.

Document Control Desk LR-N10-0139 Page 2 If you have any questions or comments on this transmittal, please contact Jon Sears at (856) 339-1773.

Sincerely, Lawrence M. Wag in E la Plant Manager - Hope Creek P d t Manager - Salem 009 Annual Radiological Environmental Operating Report

Document Control Desk LR-N10-0139 Page 3 cc: Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager Salem & Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 BlA Washington, DC 20555-0001 Mr. Joseph T. Furia, NRC Inspector - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Charles H. Eccleston Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Licensing Renewal, Project Manager One White Flint North Washington, DC 20555-0001 Roberta Hurley Earth Tech, Project Manager AECOM/Earth Tech 10 Patewood Dr, Building VI, Suite 500 Greenville, SC 29615 USNRC Senior Resident Inspector - Hope Creek (X24)

USNRC Senior Resident Inspector - Salem (X24)

Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 Ms. J. Chomiszak Delaware Emergency Management Agency 165 Brick Store Landing Road Smyrna, DE 19977 Hope Creek Commitment Coordinator (H02) w/o Attachment Salem Commitment Coordinator (X25) w/o Attachment Corporate Commitment Coordinator (N21) w/o Attachment

SPSEG Power LLC RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM For Salem Generating Station, Unit 1: Docket No. 50-272 Salem Generating Station, Unit 2: Docket No. 50-311 Hope Creek Generating Station : Docket No. 50-354 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 2009 Prepared by PSEG POWER LLC MAPLEWOOD TESTING SERVICES APRIL 2010

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM & HOPE CREEK GENERATING STATIONS 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 2009

TABLE OF CONTENTS PAGE S U MMA R Y ......................................................................... ............ 1...........

THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............. 5 O bje ctiv e s .......................................................................................... 6 D ata Inte rpretation .............................................................................. . 8 Quality Assurance Program............... ................................................... 8 Results and Discussion ........................................................... 11 Atm o sp he ric ................................................................................ 12 D ire ct R ad iatio n ......................................................................... 13 T e rre stria l.............................................................................. .... 15 Aq u a tic ......................................................... ........................ .... 23 Program Deviations. .................................. . ......................................... 30 Annotations to Previous AREOR .............................. ................................... 30 Hope Creek Technical Specification Limits for Primary Water Iodine C o nce ntratio ns ............................................................................................. 30 C o nclusio ns .................................................................................... .... . 31 R E F E R E N C E S ...................................... .... ............................................ '43 APPENDIX A - PROGRAM

SUMMARY

............................... 47 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS ........................... 53 APPENDIX C - DATA TABLES............. ......................................................... 61 APPENDIX D -

SUMMARY

OF RESULTS FROM ANALYTICS, ENVIRONMENTAL RESOURCE ASSOCIATES, AREVA E-LAB INTERLABORATORY COMPARISON PROGRAMS .................................. 89 APPENDIX E - SYNOPSIS OF LAND USE CENSUS ...................................... 97 APPENDIX F - RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM 101 i

LIST OF TABLES TABLE NUMBER TABLE DESCRIPTION PAGE

1. Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program .............................................. 32 LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION PAGE

1. Gross Beta Activity in Air Particulate 1989 through 2009 (Quarterly) .............................. 37

2. Ambient Radiation - Off-site vs Control Station 1989 through 2009 (Q uarterly) ...................................................... 38

3. Iodine-131 Activity in Milk 1989 through 2009 (Q uarterly) ............... I....................................... 39

4. Gross Beta Activity in Surface Water 1989 through 2009 (Q uarterly) ....................................................... 40

5. Tritium Activity in Surface Water 1989 through 2009 (Q uarterly) ...................................................... 41

6. Cesium-137 and Cobait-60 Activity in Aquatic Sediment 1989 through 2009 (Sem i-Annual) ................................................. 42 ii

SUMMARY

During normal operations of a nuclear power generating station there are releases of small amounts of radioactive material to the environment. To monitor and determine the effects of these releases a Radiological Environmental Monitoring Program (REMP) has been established for the environment around Artificial Island where the Salem Generating Station (SGS) and Hope Creek Generating Station (HCGS) are located. The results of the REMP are published annually, providing a summary and interpretation of the data collected [10].

PSEG's Maplewood Testing Services (MTS) has been responsible for the collection and analysis of environmental samples during the period of January 1, 2009, through December 31, 2009, and the results are discussed in this report. During the period of August 10 through September 8, 2009, AREVA- NP Environmental Laboratory performed the analysis of various REMP samples. These samples are identified via footnotes in Appendix C tables. MTS diverted sample analysis to AREVA-NP E-Lab in order to best manage resources that were needed to respond to the New Jersey Department of Environmental Protection, Office of Quality Assurance (NJDEP-OQA) concerns with laboratory certification. PSEG Nuclear has provided oversight and assistance in addressing the NJDEP-OQA's concerns regarding laboratory certification.

The REMP was conducted in accordance with the SGS and HCGS Technical Specifications (TS) and Offsite Dose Calculation Manual (ODCM) [14,15,17, 21]. The Lower Limit of Detection (LLD) values required by the Technical Specifications and ODCM were achieved for the 2009 reporting period. The REMP objectives were also met during this period. The data that was collected in 2009 assists in demonstrating that SGS and HCGS were operated in compliance with Technical Specifications and ODCM.

Most of the radioactive materials noted in this report are normally present-in the environment, either naturally, such as potassium-40, or as a result of non-nuclear generating station activity, such as nuclear weapons, testing. Measurements made in the vicinity of SGS/HCGS were compared to background or control measurements and the preoperational REMP study performed before Salem Unit 1 became operational.

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Samples of air particulates; air iodine; milk; surface, ground and drinking water; vegetables; fodder crops; fish; crabs; and sediment were collected and analyzed. External radiation dose measurements were also made in the vicinity of SGS/HCGS using thermoluminescent dosimeters (TLD).

From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment.

The concentration of radioactive material in the environment that could be attributable to Salem and Hope Creeks stations operations was only a small fraction of the concentration of naturally occurring and man-made radioactivity. Since these results were comparable to the results obtained during the preoperational phase of the program [7,8,9],-:and with historical results collected since commercial operation [10], we can conclude that the operation of SGS and HCGS had no significant radiological impact on the environment.

To demonstrate compliance with Technical Specifications and ODCM (Sections 3/4.12.1 &

6.8.4.h -1,2,3) [14,15], samples were analyzed for one or more of the following: gamma emitting isotopes, tritium (H-3), iodine-131 (1-131), gross beta and gross alpha. The results of these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with Technical Specifications and ODCM (Section 3/4.11) and applicable Federal and State regulations [19,20,21], and to verify the adequacy of radioactive effluent control systems. The results provided in this report for the REMP are summarized below:

There were a total of 1221 analyses on 865 environmental samples during 2009. Direct radiation dose measurements were made using 196 sets of thermoluminescent dosimeters (TLDs).

In addition to the detection of naturally - occurring isotopes (i.e. Be-7, K-40, Radium and Th-232), trace levels of H-3, Cs-1 37 and Mn-54 were also detected. The tritium concentration detected in surface water samples was slightly above minimum detectable concentrations. The Cs-137 concentrations detected in two river sediments were below the ODCM LLD value of 180 pCi/kg-dry.

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The Mn-54 concentration was slightly above MDC in one sediment sample collected near the HC south storm drain discharge line.

Dose measurements made with quarterly TLDs at offsite locations around the SGS/HCGS site averaged 51 milliroentgen for the year 2009. The average of the dose measurements at the control locations (background) was 51 milliroentgen for the year.

This was comparable to the levels prior to station operation which had an average of 55 milliroentgen per year for 1973 to 1976.

Appendix F contains the annual report on the status of the Radiological Groundwater Protection Program (RGPP) conducted at Salem and Hope Creek Stations. The RGPP was initiated by PSEG to determine whether groundwater at and in the vicinity of Salem and Hope Creek Stations had been adversely impacted by any release of radionuclides that was not previously identified. The RGPP is being implemented by PSEG in conjunction with a nuclear industry initiative and associated guidance. The results provided in Appendix F for the RGPP are summarized below:

Salem

The 2009 results of the laboratory analysis indicated that tritium was detected in nine of thirteen RGPP monitoring wells at Salem and all results were less than 2300 pCi/L.

Hope Creek

The 2009 results of the laboratory analysis indicated that tritium was detected in seven of thirteen RGPP monitoring wells at Hope Creek and all results were less than 8000 pCi/L.

The results are shown in Appendix F, in Tables 4A and 4B. The tritium concentrations measured in the onsite monitoring wells were below the U.S. Nuclear Regulatory Commission Reporting Levels.

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PSEG Nuclear is continuing remedial actions for tritium identified in shallow groundwater at Salem Station, conducted in accordance with a Remedial Action Work Plan that was approved by the New Jersey Department of Environmental Protection - Bureau of Nuclear Engineering (NJDEP-BNE) in November 2004. The Groundwater Recovery System (GRS) is in operation, providing hydraulic control of the plume and effectively removing tritium contaminated groundwater. The tritium contaminated groundwater is disposed of in accordance with Salem Station's liquid radioactive waste disposal program. There is no evidence or indication that tritium contaminated water above Ground Water Quality Criteria (GWQC) levels [GWQC is

<20,000 pCi/L] has migrated to the station boundary or the Delaware River.

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THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Lower Alloways Creek Township, Salem County, New Jersey is the site of Salem (SGS) and Hope Creek (HCGS) Generating Stations. SGS consists of two operating pressurized water nuclear power reactors. Salem Unit One has a net rating of 1195 megawatt electric (MWe) and Salem Unit Two has a net rating of 1196 MWe. The licensed core power for both units is 3459 megawatt thermal (MWt). HCGS is a boiling water nuclear power reactor, which has a net rating of 1265.MWe (3840 MWt).

SGS/HCGS are located on a man-made peninsula on the east bank of the Delaware River.

It was created by the deposition of hydraulic fill from dredging operations. The environment surrounding SGS/HCGS is characterized mainly by the Delaware River Estuary and Bay, extensive tidal marshlands, and low-lying meadowlands. These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agriculture [1,21. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Reports [1,2],

Environmental Statements [3,4], and the Updated Final Safety Analysis Reports for SGS and HCGS [5,6].

Since 1968, a radiological environmental monitoring program (REMP) has been conducted at the SGS/HCGS Site [22]. Starting in December, 1972, more extensive radiological monitoring programs were initiated [7,8,9]. The operational REMP was initiated in December, 1976, when Salem Unit 1 achieved criticality. PSEG's Maplewood Testing Services (MTS) has been involved in the REMP since its inception. MTS is responsible for the collection of all radiological environmental samples and, from 1973 through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by MTS.

From January, 1973, through June, 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of-all samples under the SGS/HCGS REMP and annual reporting of results.

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RMC reports for the preoperational and operational phase of the program are referenced in this report [7, 8, 9]. On July 1, 1983, MTS assumed primary responsibility for the analysis of all samples (except TLDs) and the reporting of results. Teledyne Brown Engineering Environmental Services (TBE), assumed responsibility for third-party QA analyses and TLD processing. An additional vendor, Controls for Environmental Pollution Inc. (CEP), was retained to provide third-party QA analyses and certain non-routine analyses from May, 1988, until June 1, 1992. Currently, AREVA-NP, Inc. Environmental Laboratory (AREVA) is the third party QA vendor and the laboratory which performs the TLD processing. MTS reports for the operational phase from 1983 to 2008 are referenced in this report [10].

An overview of the 2009 REMP is provided in Table 1, Salem and Hope Creek Generating Stations Radiological Environmental Monitoring Program. Radioanalytical data from samples collected under this program were compared with results from the preoperational phase and historical results during operations. Differences between these periods were examined statistically to determine the effects of station operations. This report presents the results from January 1 through December 31, 2009, for the SGS/HCGS REMP.

OBJECTIVES The objectives of the operational REMP are:

To fulfill the requirements of the Radiological Surveillance sections of the Technical Specifications and ODCM for SGS/HCGS.

To determine whether any significant increase occurred in the concentration of radionuclides in critical pathways.

To determine if SGS or HCGS has caused an increase in the radioactive inventory of

-long-lived radionuclides.

To detect any change in ambient gamma radiation levels.

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To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on the environment.

This report, as required by Section 6.9.1.7 of the Salem Technical Specifications [12] and ODCM [14] and Section 6.9.1.6 of the Hope Creek Technical Specifications [13] and ODCM

[15], summarizes the findings of the 2009 REMP. Results from the formal 1973 through.

1976 preoperational program were summarized by RMC and have been used for comparison with subsequent. operational reports [8].

In order to meet the objectives, an operational REMP was developed. Samples of various media were selected for monitoring due to the radiological dose impact to human and other organisms. The selection of samples was based on: (1), established critical pathways for the transfer of radionuclides through the environment to man, and, (2), experience gained during the preoperational phase. Sampling locations Were determined based on site meteorology,. Delaware estuarine hydrology, local demography, and land uses.

Sampling locations were divided into two classes, indicator and control. Indicator stations are those which are expected to manifest station effects. Control samples are collected at locations which are believed to be unaffected by station operations, usually at 15 to 30 kilometers distance. Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations.

Indicator and control station -data are also evaluated relative to preoperational data.

Appendix A, Program Summary, describes and summarizes the analytical results in accordance with Section 6.9.1.7 of the Salem TS and Section 6.9.1.6 of the Hope Creek TS

[25,26,27]. Appendix B, Sample Designation, describes the coding system which identifies sample type and location. Table B-1 On-site Sampling Locations lists the station codes, stations location, latitude, longitude, and the types of samples collected at each station.

These sampling stations are indicated on Maps B-i, Onsite Sampling Locations and B-2, Offsite Sampling Locations.

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DATA INTERPRETATION Results of analyses are grouped according to sample type and presented in Appendix C, Data Tables. All results above the Lower Limit of Detection (LLD) are at a confidence level of 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, LLD is 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".

LLD is normally calculated as 4.66 times the standard deviation of the background counting rate, or of the blank sample count, as appropriate, divided by counting efficiency, sample size, 2.22 (dpm per picocurie), the radiochemical yield when applicable, the radioactive decay constant and the elapsed time between sample collection and time of counting. The Minimum Detectable Concentration (MDC) is defined as the smallest concentration of radioactive material that can be detected at a given confidence level. The MDC differs from the LLD in that the MDC takes into consideration the interference caused by the presence of other nuclides while the LLD does not.

The grouped data were averaged and standard deviations calculated in accordance with Appendix B of Reference 16. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. For reporting and calculation of averages, any result occurring at or below the LLD is considered to be at that level. When a group of data was composed of 50% or more LLD values, averages were not calculated.

QUALITY ASSURANCE PROGRAM MTS has a quality assurance program designed to ensure confidence in the analytical program. Approximately 10 -15% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review/evaluation.

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The quality of the results obtained by MTS is ensured by the implementation of the Quality Assurance Program as described in the Maplewood Testing Services Quality Assurance Manual [11 a], the Maplewood Testing Services Mechanical Division Quality Assurance/Control Plan [11 b], and the Maplewood Testing Services Mechanical Division Environmental/Radiological Group Procedure Manual [1ic].

The internal quaiity control activity of MTS includes the quality control of instrumentation, equipment and reagents, the use of reference standards in calibration, documentation of established procedures and computer programs, analysis of blank samples, and analysis of duplicate samples. The external quality control activity is implemented through participation in the Analytics Environmental Cross Check (ECC), AREVA and the Environmental Resource Associates: (ERA) Interlaboratory Comparison Programs. MTS's internal QC results are evaluated in accordance with the NRC Resolution Criteria [18, 24]. This criteria is also used for the Analytics Environmental Crosscheck Program results. ERA's RadCheMTM Proficiency Testing (PT) studies have been evaluated by comparing MTS results to the acceptance limits and evaluation criteria contained in the NELAC standards, National Environmental Laboratory Accreditation Conference (NELAC) PT Field of Testing list (October 2007). (The results of these three Interlaboratory Comparison Programs are listed in Tables D-1 through D-4 in Appendix D "Summary Of Results From Analytics, Environmental Resource Associates, AREVA E-Lab Interlaboratory Comparison Programs")

A total of 89 analysis results were obtained in the Cross Check, Interlaboratory Comparison and Proficiency Testing programs. Eighty-six (86) passed the applicable criteria, this translates to a 97% acceptance rate.

The Three medias and analysis which disagreed with the criteria were: water/gross alpha, water/gross beta, and water/ Zn-65 Gamma Spec. The cause for these disagreements and the corrective actions are provided below.

The result disagreement for the gross alpha in water analysis for the ERA PT Study was attributed to the incorrect alpha then beta counting mode being chosen in the MTS counting procedure for ERA PT samples.

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(This was the first ERA PT sample counted after the new Eclipse V3.12 software was installed on our Tennelec GPC in November of 2008). When the PT sample was recounted later in the correct simultaneous counting mode, the gross alpha result from the recount was within the ERA's Acceptance Limits. All of the MTS Tennelec counting procedures were then checked to verify that the correct simultaneous counting mode box was chosen.

The result disagreement for the gross beta in the Analytics second quarter ECC was attributed to using the lower Sr-90 Beta Counting Efficiency and Calibration Curve derived in our Annual Calibration of the Tennelec XLB GPC in August 2009. This caused our sample results to be biased high. A re-calibration was done resulting in a higher counter efficiency and a recount of the ECC AB720 sample was then shown to be in agreement with the known value.

The result disagreement for the gamma spec Zinc-65 nuclide for the ERA RAD 77 water was attributable to the software calculated peak being broad and misshaped. The peak parameters were satisfactory at Full Width Half Max (FWHM). Only the Zn-65 nuclide was the outlier of the five spiked nuclides contained in this sample. M.TS personnel considered this an isolated occurrence since additional ECC samples containing this nuclide were analyzed and found to be acceptable throughout this year.

The Quality Assurance program for environmental TLDs includes independent third party performance testing by the Pacific Northwest National Laboratory and- internal performance testing conducted .by the AREVA Laboratory Quality Assurance Officer.

Under these programs, sets of six dosimeters are irradiated to ANSI N545, Performance Testing and Procedural Specifications for Thermoluminescent Dosimetry (Environmental)

[29], and submitted for processing as "unknowns.." The bias and precision of TLD processing is measured against the guidance in U. S. Nuclear Regulatory Commission Regulatory Guide 4.13 Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications [23] and is trended over time to indicate changes in TLD processing performance.

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The AREVA Lab conducted internal performance tests on environmental TLDs in 2009.

These tests were conducted on fourteen separate sets of six environmental dosimeters. All of the fourteen TLD test sets passed the mean bias criteria.

Of the eighty-four individual measurements, all of the individual dosimeter evaluations met the E-LAB bias and precision tolerance limits (see Table D-5 "Percentage of Individual TLD Results That Met AREVA E-Lab Tolerance Limits").

The Pacific Northwest National Laboratory performed third party performance tests for the AREVA Lab. The third party dosimeters were irradiated and analyzed along with client dosimeters. Both sets of six dosimeters passed the mean bias criteria. The mean percent bias and standard deviation for the two groups of six dosimeters are shown in Table D-6 "Third Party TLD Testing Performance Results".

RESULTS AND DISCUSSION The analytical results of the 2009 REMP samples are divided into categories based on exposure pathways: atmospheric, direct radiation, terrestrial, and aquatic. The analytical results for the 2009 REMP are summarized in Appendix A, Program Summary. The data for individual samples are presented in Appendix C, Data Tables. The data are compared to the formal pre-operational environmental monitoringprogram data (1973-1976) and to historical data during operations. The data collected demonstrates that the SGS and HCGS REMP was conducted in compliance with the Technical Specifications and ODCM.

The REMP for the SGS/HCGS Site has historically included samples and analyses not specifically required by these Stations' Technical Specifications and ODCM. These, analyses are referenced throughout the report as Management Audit samples. MTS continues to collect and analyze these samples in order to maintain personnel proficiency in performing these non-routine analyses. The summary tables in this report include these additional samples and analyses.

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ATMOSPHERIC Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers.

Iodine was collected from the air by adsorption on triethylene-diamine (TEDA) impregnated charcoal cartridges connected in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters. The displayed volumes were corrected to standard temperature and pressure.

Air Particulates (Tables C-1, C-2)

Air particulate samples were collected weekly, at 6 locations. Each of the samples (see Program Deviations) collected for the year were analyzed for gross beta. Quarterly composites of the weekly samples from each station were analyzed for specific gamma emitters. Total air sampler availability for the 6 sampling stations in 2009 was 99.8 percent.

Gross beta activity was detected in all of the indicator station samples collected at concentrations ranging from 6.7 x 103 to 34 x 10-3 pCi/m 3 and in all of the control station samples from 7.8 x 10-3 to 31 x 10-3 pCi/m 3 . The average for both the indicator and control station samples was 18 x 10-3 pCi/m 3 . The maximum 3

preoperational level detected was 920 x 10 pCi/rn , with an average of 74 x 10-3 3

pCi/m 3 . Results for gross beta analysis from 1989 to current year are plotted on Figure 1 as quarterly averages. Included along with this plot, for purposes of comparison, is an inset depicting a continuation of this plot from the current year to 1973.

Gamma spectroscopy, performed on each of the 24 quarterly composite samples analyzed, indicated the presence of the naturally-occurring radionuclides Be-7 and K-40. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

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Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in all 20 indicator station composites that were analyzed, at concentrations ranging from 62 x 10-3 to 106 x 10-3 pCi/m 3, with an average of 84 x 10-3 pCi/m 3 . It was x 10-3 detected in the 4 control station composites ranging from 67 x 10-3 to 105 pCi/m 3 , with an average of 85 x 10-3 pCi/m 3 . The maximum preoperational level detected was 330 x 10-3 pCi/m 3, with an average of 109 x 10-3 pCi/m 3 .

Potassium-40 activity was detected in all 20 of the indicator station samples, with concentrations ranging from 9.0 x 10-3 to 15 x 10-3 pCi/m 3 and it was also detected in all 4 control station samples, at concentrations of 10 X 10-3 to 16 x 10.3 pCi/m 3 . The average for all stations was 12 X 10-3 pCi/m 3 . No preoperational data is available for comparison. However, the average of all 3 3.

positive values for all stations for the years 1988 to 2008 was 12 X10- pCi/m Air Iodine (Table C-3)

Iodine in filtered air samples was collected weekly, at 6 locations. Each of the samples collected (see Program Deviations) for the year was analyzed for 1-131.

Iodine-1 31 was not detected above minimum detectable concentrations in any of the weekly samples analyzed. Minimum detectable concentrations for all the stations, both indicator and control, ranged from <1.1 x 10-3 to <9.9 x 10-3 pCi/m 3 . The maximum preoperational level detected was 42 x 10-3 pCi/m 3 .

DIRECT RADIATION Ambient radiation levels in the environs were measured with a pair of Panasonic thermoluminescent dosimeters (TLDs) supplied and processed by AREVA NP E-Lab.

Packets containing TLDs for quarterly exposure were placed in the owner-controlled area and around the Site at various distances and in each land based meteorological sector.

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Emphasis was placed on special interest areas such as population centers, nearby residences, and schools.

Direct Radiation (Table C-4)

A total of 49 locations were monitored for direct radiation during 2009, including 12 on-site locations, 31 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles.

Each location gets a pair of Panasonic TLDS packaged together. This pair consist of 1 UD-801 TLD which contains 2 lithium and 2 calcium elements and 1 UD-814 TLD which contains 1 lithium and 3 calcium elements. To calculate the stations exposure, AREVA averages the-5 calcium elements to obtain a more statistically valid result. Then they perform a T test to identify any outliers. These outliers are removed and would reduce the number of elements used. For these measurements, the rad and roentgen is considered equivalent to the rem, in accordance with 10CFR20.1004.

The average dose rate for the 31 quarterly off-site and 12 quarterly on-site indicator TLDs was 4.2 milliroentgen per standard month. The average control TLD dose rate was similar at 4.3 milliroentgen per standard month. The preoperational average for the quarterly TLD readings was 4.4 milliroentgen per standard month.

In Figure 2, the quarterly average radiation levels of the off-site indicator stations versus the control stations, are plotted for the period 1989 through 2009, with an inset graph depicting the period 1973 to 2009.

The results of the direct radiation measurements for 2009 confirmed that the radiation levels in the vicinity of the Salem and Hope Creek Generating Stations were similar to previous years.

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TERRESTRIAL Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Animals are considered on pasture from April to November of each year. Samples were collected in polyethylene containers and transported in ice chests with no preservatives added to the milk.

A well water sample was collected monthly. Separate raw and treated potable water samples were composited daily at the City of Salem Water and Sewer Department. All samples were collected in new polyethylene containers.

Locally grown vegetable and fodder crops were collected at the time of harvest from Management Audit sample locations. Ornamental and broad leaf cabbage and kale were collected from on-site gardens. MTS personnel planted, maintained and harvested these broadý leaf crops in the late summer and fall from three locations on site and one across the river. All samples were weighed and packed in plastic bags.

Milk (Table C-5)

Milk samples were collected at 4 local dairy farms (2 farms in NJ and 2 in Delaware). Each sample was analyzed for 1-131 and gamma emitters.

Iodine-131 was not detected above minimum detectable concentration in any of the 80 samples analyzed. LLD's for both the indicator and the control station samples ranged from <0.1 to <1.0 pCi/L. The maximum preoperational level detected was 65 pCi/L which occurred following a period of atmospheric nuclear weapons tests.

Results from 1989 to 2009 are plotted on Figure 3, with an inset graph depicting the period 1973 to 2009.

Gamma spectroscopy performed on each of the 80 samples indicated the presence of the naturally-occurring radionuclides K-40 and RA-NAT.

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All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Potassium-40 was detected in all 80 samples. Concentrations for the 60 indicator station samples ranged from 1240 to 1540 pCi/L, with an average of 1370 pCi/L. The 20 control station sample concentrations ranged from 1210 to 1790 pCi/L, with an average of 1340 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.

RA-NAT was detected in two of the indicator station samples at concentrations of 5.8 and 8.5 pCi/L. It was not detected above the minimum detectable concentration in any of the control station samples. The preoperational samples had an average concentration of 3.8 pCi/L and a range of 1.5 to 11 pCi/L.

Well Water (Ground Water) (Tables C-6, C-7)

Although wells in the vicinity of SGS/HCGS are not directly affected by plant operations, Water samples were collected monthly from one farm's well (3E1) during January through December of the year. This well is located upgradient of the stations aquifer. Samples from this well are considered Management Audit samples and each was analyzed for gross alpha, gross beta, tritium, and gamma emitters.

Gross alpha activity was detected in one of the well water samples at a concentration of 0.5 pCi/L. LLD's ranged from <0.5 to 1.1 pCi/L. The maximum preoperational level detected was 9.6 pCi/L. There was no preoperational average determined for this analysis. The average of all positive results for gross alpha for well samples for the years 1988 to 2008 was 2 pCi/L.

0 Gross beta activity was detected in 6 well water samples. Concentrations for the samples ranged from 0.7 to 8.8 pCi/L, with an average of 2.4 pCi/L.

16-

Except for the January result, the 2009 gross beta results are lower than the previous years. In addition, the 2009 gross beta results were lower than the preoperational results which ranged from <2.1 to 38 pCi/L, with an average value of 9 pCi/L. The downward trend may be attributed to the farmer installing a water treatment system for this well in February, 2009.

Tritium activity was not detected above the minimum detectable concentration in any of the well water samples. The MDC ranged from <124 to <144 pCi/L. The maximum preoperational level detected was 380 pCi/L. There was no preoperational average determined for this analysis. The average of all the positive tritium results from 1988 to 2008 was 218 pCi/L.

Gamma spectroscopy performed on each of the 12 well water samples indicated the presence of the naturally-occurring radionuclides K-40 and RA-NAT. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Potassium-40 was detected in 6 of the samples at concentrations ranging from 33 to 63 pCi/L with an average of 46 pCi/L. The maximum preoperational level detected was 30 pCi/L. There was no preoperational average determined for this analysis. The average of the positive K-40 results from 1988 to 2008 was 58 pCi/L.

RA-NAT was detected in 11 of the well water samples at concentrations ranging from 36 to 174 pCi/L with an average of 123 pCi/L. The maximum preoperational level detected was 2.0 pCi/L. There was no preoperational average determined for this analysis. These values are similar to those found in the past 20 years. The average of all the positive RA-NAT well results from 1988 through 2008 was 99.8 pC/L. These higher than preoperational results are due to a procedural change instituted in 1986 for water sample preparation.

17

This change results in less removal of radon (and its daughter products) from the sample, which causes the higher numbers recorded annually. It is reasonable to conclude that values currently observed are typical for this region. [28]

Potable Water (Drinking Water) (Tables C-8, C-9)

Both raw and treated potable water samples were collected and composited by The City of Salem Water and Sewer Department personnel. Each sample consisted of daily aliquots composited into a monthly sample. The raw water source for this plant is Laurel Lake and its adjacent wells. These -are management audit samples as no liquid effluents discharged from SGS/HCGS will directly affect this pathway. Each of the 24 individual samples was analyzed for gross alpha, gross beta, tritium, iodine-131 and gamma emitters.

Gross alpha activity was detected in 2 raw water samples at concentrations of 0.5 and 0.7 pCi/L. It was not detected in any of the treated water samples. Minimum detectable concentrations for the remaining 22 samples (both treated and raw) ranged from <0.3 to <0.8 pCi/L. The maximum preoperational level detected was 2.7 pCi/L. There was no preoperational average determined for this analysis. The average of all the positive alpha results from 1988 to 2008 was 1.1 pCi/L.

Gross beta activity was detected in all 24 of the raw and treated water samples. The raw samples were at concentrations ranging from 2.3 to 5.6 pCi/L. Concentrations for the treated water ranged from 2.2 to 4.9 pCi/L. The average concentration for both raw and treated was 3.3 pCi/L. The maximum preoperational level detected was 9.0 pCi/L, with an average of 4.2 pCi/L.

Tritium activity was not detected above minimum detectable concentration in any of the raw or treated potable water samples. MDC's for the raw and treated samples ranged from <125 to <145 pCi/L. The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

Iodine-1 31 measurements were performed to an LLD of 1.0 pCi/L.

18

lodine-131 measurements for all 24 samples were below the minimum detectable concentration. These values ranged from <0.1 to <1 pCi/L. There was no preoperational data available for comparison since 1-131 was not analyzed as a specific nuclide until 1989. Since that time, all results have been below the MDC.

Gamma spectroscopy performed on each of the 24 monthly water samples indicated the presence of the naturally-occurring radionuclides K-40, Th-232 and RA-NAT. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

SThel.radionuclide K-40 was detected in 4 of the treated potable waters at concentrations ranging from 33 to 72 pCi/L. It was detected in 4 of the raw potable water samples at concentrations from 33 to 72 pCi/L. The average for both raw and treated results was 47 pCi/L. LLD's for the remaining 16 potable water samples were <9.6 to <51 pCi/L. There was no preoperational data available for comparison. The average of the positive K-40 results from 1988 to 2008was 47 pCi/L.

The radionuclide Thorium-232 was detected in only one sample of raw potable water at a concentration of 12 pCi/L. LLD's for the remaining 23 potable samples were <1.6 to <16 p.Ci/L. There was no preoperational data available for comparison, however, the combined average for the positive potable water samples analyzed for Th-232 from 1988 to 2008 was 9.0 pCi/L which is comparable to this years value.

RA-NAT was detected in 7 of the treated potable waters at concentrations ranging from 4.8 to 88 pCi/L and an average of 24 pCi/L. It was not detected in any of the raw potable water samples. LLD's for the remaining 17 samples were <1.6 to <9.2 pCi/L. The maximum preoperational level detected was 1.4 pCi/L. There was no preoperational average determined for this analysis.

19

The higher results are due to the procedural change for sample preparation, as discussed in the Well Water section. The average of all the positive RA-NAT results from 1988 to 2008 was 28 pCi/L.

Vegetables (Table C-10)

Although vegetables in the region are not irrigated with water into which liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled These samples were from 5 indicator stations (18 samples) and 4 control stations (15 samples). The vegetables from the local farms are collected as management audit samples.

In addition, cabbage and kale were grown from seed by MTS and pianted at two on site locations. Vegetables grown on site are collected in lieu of having a milk farm within 5 km.(See Fodder Crops) All samples (vegetable and broadleaf) were analyzed for gamma emitters and included asparagus, cabbage, kale, sweet corn, peppers, and tomatoes. The results for these samples are discussed below:

Gamma spectroscopy performed on each of the 33 samples indicated the presence of the naturally-occurring radionuclides K-40, RA-NAT and Be-7. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Potassium-40 was detected in all 33 samples. Concentrations for the 18 indicator station samples ranged from 1340 to 4810 pCi/kg-wet and averaged 2370 pCi/kg-wet. Concentrations for the 15 control station samples ranged from 1090 to 2820 pCi/kg-wet, and averaged 1890 pCi/kg-wet. The average concentration detected for all samples, both indicator and control, was 2150 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2140 pCi/kg-wet.

20

RA-NAT was not detected in any of the 18 indicator station samples. It was detected in two control locations (corn and pepper) at concentrations of 12 and 18 pCi/kg-wet. LLD's for the remaining 31 samples were <4.8 to <23 pCi/kg-wet.

There was no preoperational data available for comparison. The combined average for the positive vegetable samples analyzed for RA-NAT from 1988 to 2008 was 30 pCi/kg-wet.

Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in four of the indicator station samples at concentrations of 157 to 414 pCi/kg-wet and an average of 277. pCi/kg-wet. It was not detected is any of the control locations.

No preoperational data is available for comparison. However, the combined average for the positive vegetable samples analyzed for Be-7 from 1988 to 2008 was 244 pCi/kg-wet.

Fodder Crops (Table C-1 1)

Although not required by the SGS or HCGS Technical Specifications and ODCM, 6 samples of crops normally used as cattle feed (silage and soybeans) were collected from three indicator stations (4 samples) and one control station (2 samples). It was determined that these products may be a significant element in the food-chain pathway. These fodder crops are collected as management audit samples and analyzed for gamma emitters. All four locations from which samples were collected this year are milk sampling stations.

In addition to the silage and soybean, ornamental cabbage was planted and maintained by MTS personnel at 3 locations on site and 1 in Delaware, at 3.9 miles. Two of these 4 samples (locations 1S1 and 16S1) were grown in the same area as the on-site vegetable samples as mentioned in Table C-1 0. The 4 ornamental cabbage samples were harvested in December. These broad leaf vegetation samples were collected since there are no longer any milk farms operating within the 5 km radius of SGS/HCGS. The closest milk farm (13E3) is located in Odessa, DE at 4.9 miles (7.88 km).

21-

Gamma spectroscopy performed on each of the 10 samples indicated the presence of the naturally-occurring radionuclides Be-7 and K-40.

All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in 3 of the indicator silage samples at concentrations from 422 to 732 pCi/kg-wet. It was detected in the control station silage sample at 1310 pCi/kg-wet. The maximum preoperational level detected for silage was 4700 pCi/kg-wet, with an average of 2000 pCi/kg-wet.

Be-7 was not detected in either the indicator nor control station soybean samples.

LLD results for these two samples were <88 and <95 pCi/kg-wet. The maximum preoperational level detected for soybean samples was 9300 pCi/kg-dry.

Be-7 was detected in all 4 of the ornamental cabbage samples at concentrations of 160 to 482 pCi/kg-wet and an average of 310 pCi/kg-wet. There was no preoperational data available for comparison with this type of sample; on site vegetation was not available until 2005. However, the average for ornamental cabbage for the previous 4 years was 246 pCi/kg-wet.

Potassium-40 was detected in all 10 of the vegetation station samples. The combined average for the indicator station samples was 4620 pCi/kg-wet with the average concentrations from 2380 to 14800 pCi/kg-wet. The control station concentrations were 5130 and 13300 pCi/kg-wet with an average for of 9220 pCi/kg-wet.

The average concentration of K-40 detected for the silage samples (3 indicator and 1 control) was 3580 pCi/kg-wet. Indicator station samples were at concentrations of 2480 to 3460 pCi/kg-wet while the control station had a concentration of 5130 pCi/kg-wet. Preoperational results averaged 7000 pCi/kg-wet.

22

K-40 results for the soybean samples (indicator and control) was 14050 pCi/kg-wet.

Preoperational soybean results averaged 22000 pCi/kg-dry.

The average concentration of K-40 for the 4 ornamental cabbage samples was 3250 pCi/kg-wet. There was no preoperational data available for comparison with these samples as MTS started planting vegetation on site in 2005. However, the average K-40 concentration for ornamental cabbage for the previous 4 years was 3742 pCi/kg-wet.

AQUATIC Environmental Consulting Services, Inc (ECSI) collected all aquatic samples (with the exception of the 6S2 shoreline sediment). This sample set includes edible fish, shoreline sediment, surface water and crab.

Surface water samples were collected offshore. The technicians collect the samples in new polyethylene containers that are rinsed twice with the sample medium prior to collection.

The surface water samples are transported to MTS for analysis.

Edible fish are taken by gill nets while crabs are caught in commercial traps. These samples are then processed where the flesh is separated from the bone and shell. The flesh is placed in sealed containers and frozen before being transported in ice chests to MTS for analysis.

Sediment samples collected by ECSI were taken with a bottom grab sampler and frozen in sealed polyethylene containers before being transported in ice chests to MTS. For the river bottom sediment, a marine GPS locates the correct site and the sampling boat is maneuvered over the area until the correct amount of sample is obtained (grabbed) with the sediment dredge. Personnel from MTS collect and prepare location 6S2 shoreline sediment (an onsite location) for analysis at MTS. For this location, a square area, measuring 1 meter on each side is staked out and then divided into a grid of 9 smaller boxes, 3 per side.

23

A 1 inch deep scoop from the center of each of the small grids is taken. All the aliquots are combined and the total sample transported in the ice chest to MTS.

Surface Water (Tables C-12, C-13, C-14)

Surface water samples were collected monthly at 4 indicator stations and one control station in the Delaware estuary. One location (1 1A1) is at the outfall area (which is the area where liquid radioactive effluents from the Salem Station are discharged into the Delaware River), another is downstream from the outfall area (7E1), and another is directly west of the outfall area at the mouth of the Appoquinimink River (12C1). Two upstream locations are in the Delaware River (1 F2) and at the mouth of the Chesapeake and Delaware Canal (16F1), the latter being sampled when the flow is from the Canal into the river.

Station 12C1, directly west, at the mouth of the Appoquinimink River, serves as the operational control. Location 12C1 was chosen as the control location because the physical characteristics of this station more closely resemble those of the outfall area than do those at the farther upstream location (11F2). As discussed in the pre-operational summary report, due to the tidal nature of this Delaware-River-Bay estuary, there are flow rate variations and variations in salinity levels. These variations will account for differences in concentrations of potassium and associated gross beta from K-40. All surface water samples were analyzed monthly for gross beta, tritium and gamma emitters.

Gross beta activity was detected in 44 of the 48 indicator station samples ranging from 9 to 384 pCi/L, with an average of 74 pCi/L. Beta activity was detected in all 12 of the control station samples with concentrations ranging from 16 to 127 pCi/L, with an average of 53 pCi/L. The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L. Quarterly results for all locations are plotted on Figure 4, for the years 1989 to 2009, with an inset graph depicting the current period 1973 to 2009.

Tritium activity was detected in 4 of the indicator station samples at concentrations from 154 to 340 pCi/L and an average of 246 pCi/L. These levels were only slightly above the minimum detectable concentration range.

24

Tritium was not detected in any of the control station samples. Minimum detectable concentrations for the remaining station samples, both indicator and control, ranged from <132 to <156 pCi/L. The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L. Positive results from 1989 to 2009 are plotted on Figure 5, with an inset graph depicting the period 1973 to 2009.

Gamma spectroscopy performed on each of the 48 indicator station and 12 control station surface water samples indicated the presence of the naturally-occurring radionuclides K-40, Th-232 and RA-NAT. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Potassium-40 was detected in all 48 samples of the indicator stations at concentrations ranging from 34 to 147 pCi/L and in all 12 of the control station samples ranging from 51 to 117 pCi/L. The average for the indicator station locations was 82 pCi/L, while the average for the control station locations was 70 pCi/L. The maximum preoperational level detected for K-40 was 200 pCi/L, with an average of 48 pCi/L.

" Thorium-232 was detected in only 2 of the indicator station samples at concentrations of 10 and 13 pCi/L. It was not detected in any of the control station samples. LLD sensitivities for the rest of the station samples, both indicator and control, ranged from <2.1 to <11 pCi/L. There was no pre-operational data available for this nuclide. However, the combined average for the positive surface water samples analyzed for Th-232 from 1988 to 2008 was 8.5 pCi/kg-wet.

RA-NAT was detected in 9 of the indicator stations at concentrations from 5 to 11 pCi/L and an average of 7 pCi/L. It was detected in only 1 of the control location samples at 7 pCi/L. MDC's for the remaining station samples, both indicator and control, ranged from <1.5 to <4.5 pCi/L. The maximum preoperational level detected was 4 pCi/L with no average determined. All positive results for RA-NAT from 1988 to 2008 were averaged for a concentration of 7.7 pCi/L.

25

Fish (Table C-15)

Edible species of fish were collected semi-annually at 2 indicator (7E1, 1AW) and 1 control (12C1) station, and analyzed for gamma emitters in flesh.

Samples included channel catfish, white catfish, bluefish, white perch, summer flounder, black drum and striped bass. (See explanation of controls in the surface water section).

The 4 indicator and 2 control station samples from both semi-annual collections, indicated the presence of the naturally-occurring radionuclides K-40 and RA-NAT. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Potassium-40 was detected in all 4 samplesfrom the indicator stations at concentrations ranging from 3230 to 3430 pCi/kg-wet for an average of 3320 pCi/kg-wet. K-40 was detected in both samples from the control location at 2980 and 3350 pCi/kg-wet. The average for the control samples was 3165 pCi/kg-wet.

The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2900 pCi/kg-wet.

RA-NAT was detected in only 1 sample from the second semi-annual collection. It was not detected in any of the indicator station samples. The control station positive result was at a concentration of 12 pCi/kg-wet. MDC's for the remaining 5 samples both indicator and control ranged from <5.9 to <14 pCi/kg-wet. The maximum preoperational level detected was 130 pCi/kg-wet, with no average determined. All positive results for RA-NAT from 1988 to 2008 were averaged for a concentration of 26 pCi/kg-wet.

Blue Crab (Table C-16)

Blue crab samples were collected twice during the season at 2 locations, 1 indicator and 1 control, and the edible portions were analyzed for gamma emitters. (See explanation of controls in the surface water section).

26

Gamma spectroscopy performed on the flesh of the indicator station samples and the control station samples indicated the presence of the naturally-occurring radionuclides K-40 and RA-NAT. All other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Potassium-40 was detected in both indicator station samples at concentrations of 1430 and 1560 pCi/kg-wet. It was detected in both control station samples at 1770 and 2300 pCi/kg-wet. The average for both the indicator and control station samples was 1770 pCi/kg-wet. The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 pCi/kg-wet.

RA-NAT was detected in 1 of the indicator stations for the first semi-annual collection at a Concentration of 21 pCi/kg-wet. It was detected in only 1 of the control location samples during the same collection at 18 pCi/kg-wet. Minimum detectable concentrations for the remaining station samples, both indicator and control for the second semi-annual collection, ranged from <19 to <20 pCi/kg-wet. The maximum preoperational level detected was 33 pCi/kg-wet with no average determined. All positive results for RA-NAT from 1988 to 2008 were averaged for a concentration of 27 pCi/kg-wet.

Sediment (Table C-17)

Sediment samples were collected semi-annually from 7 locations, including 6 indicator stations and 1 control station. (Location 6S2 is the only shoreline sediment and it is directly affected by tidal fluctuations) Each of the 14 samples was analyzed for gamma emitters. In addition to the naturally-occurring radionuclides K-40, Be-7, Th-232 and RA-NAT, trace amounts of Cs-1 37 were detected in two samples (16F1 and 1 WA)and Mn-54 was detected in one sample (16A1). (See explanation of controls in the surface water section) 27-

Gamma spectroscopy was performed on each of the 12 indicator station samples and 2 control station samples. Except for the radionuclides listed above, all other gamma emitters searched for in the nuclide library used by nuclear plants were below the minimum detectable concentration.

Cesium-137 was detected in 2 of the indicator samples at concentrations of 52 and 63 pCi/kg-dry. It was not detected in either control location. MDC's for the remaining 12 samples, both indicator and control, ranged from <2.7 to <15 pCi/kg-dry. The maximum preoperational level detected was 400 pCi/kg-dry, with an average of 150 pCi/kg-dry. Positive results from 1989 to 2009 are plotted on Figure 6, with an inset graph depicting the current year back to 1977.

" Manganese-54 was detected in one indicator station sample at a concentration of 27 pCi/kg-dry just above maximum MDC values. Mn-54 was not detected in any control station samples. The MDC range for both indicator and control samples was <3.1 to

<25 pCi/kg-dry. There was no preoperational data available for this nuclide. All positive results for Mn-54 from 1988 to 2008 were averaged for a concentration of 30 pCi/kg-dry.

" Beryllium-7 was detected in 1 of the indicator station samples at a concentration of 135 pCi/kg-dry. It was not detected in either control location above minimum detectable concentration. The maximum preoperational level detected was 2300 pCi/kg-dry. There was no preoperational average determined for this nuclide. All positive results for Be-7 from 1988 to 2008 were averaged for a concentration of 523 pCi/kg-dry.

Potassium-40 was detected in all 12 indicator station samples at concentrations ranging from 1290 to 16500 pCi/kg-dry, with an average of 7048 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 13500 and 15000 pCi/kg-dry.

28

The average for the control station samples was 14250 pCi/kg-dry. The maximum preoperational level detected was 21000 pCi/kg-dry, with an average of 15000 pCi/kg-dry.

RA-NAT was detected in all 12 indicator station samples at concentrations ranging from 73 to 826 pCi/kg-dry, with an average of 426 pCi/kg-dry. Concentrations detected in both of the control station samples were at 537 and 563 pCi/kg-dry, with an average of 550 pCi/kg-dry. The average for both the indicator and control station samples was 443 pCi/kg-dry. The maximum pre-operational level detected was 1200 pCi/kg-dry, with an average of 760 pCi/kg-dry.

Thorium-232 was detected in all 12 indicator station samples at concentrations ranging from 81 to 1110 pCi/kg-dry, with an average of 611 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 1000 and 1050 pCi/kg-dry, with an average of 1025 pCi/kg-dry. The average for both the indicator and control station samples was 670 pCi/kg-dry. The maximum pre-operational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.

. 29

PROGRAM DEVIATIONS Location 14G1 (11.8 miles WNW) air iodine & filter assembly was removed from the filter/cartidge assembly and then reinstalled back into the assembly on Feb. 17, 2009. The new filter and cartridge was inadvertently brought back to the Lab and analyzed. When the results on the filter were reviewed on February 1 9 th the error in the filter/cartridge replacement was realized. MTS and PSEG Nuclear made the decision to extend the sampling period to two weeks. The justification was there would be no collection time lost and the sampling period would remain consistent between 144 to 192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br />, when divided by two weeks. Results for this location were comparable to the concentrations for the other five locations during the same sampling period. Corrective action was to verify the assembly has a new white filter showing, before leaving the serviced air sampler location, in order to prevent this program deviation from occurring in the future.

ANNOTATIONS TO PREVIOUS AREOR The 2008 AREOR contained a typographical error. In table 1, the program overview, there was a typographical error regarding the sediment sample locations which omitted the location 16F1. The sediment sample locations have been, and continue to be, 6S2, 1 1A1, 15A1, 16A1, 12C1, 7E1, and 16F1, as consistently shown on Table B-1 in the 2006, 2007 and 2008 REMP reports. The tables with Concentration of Gamma Emitters (Tables C-17 or C-1 8) are also correct for each year and reflect the same sample points as in Table B-I.

This error has been corrected in the 2009 AREOR.

HOPE CREEK TECHNICAL SPECIFICATION LIMIT FOR PRIMARY WATER IODINE CONCENTRATIONS The Hope Creek primary water chemistry results for 2009 were reviewed. The specific activity of the primary coolant did not exceed 0.2 microcuries per gram Dose Equivalent 1-131. Therefore, the iodine concentrations in the primary coolant did not exceed the Tech Spec limit specified in section 3.4.5.

30

CONCLUSIONS The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted during 2009 in accordance with the SGS and HCGS Technical Specifications and ODCM. The LLD values required by the Technical Specifications and ODCM were achieved for this reporting period (See Appendix A and Appendix C). The objectives of the program were also met during this period. The data collected assists in demonstrating that SGS and HCGS were.operated in compliance with Technical Specifications and ODCM requirements.

From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment.

The concentration of radioactive material in the environment that could be attributable to Salem and Hope Creeks stations operations was only a small fraction of the concentration of naturally occurring and man-made radioactivity. Since these results were comparable to the results obtained during the preoperational phase of the program, which ran from 1973 to 1976, and with historical results collected since commercial operation, PSEG Nuclear Personnel have concluded that the operation of the Salem and Hope Creek Stations had no significant radiological impact on the environment.

31

TABLE 1 SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Program Overview)

EXPOSURE PATHWAY AND/OR NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND SAMPLESAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY* OF FREQUENCY ANALYSIS

1. DIRECT

. RADIATION Forty-nine routine monitoring stations Quarterly Gamma dose/ quarterly with two or more dosimeters placed as Thermoluminescent follows:

Dosimeters An inner ring of stations, one in each land based meteorological sector (not bounded by water) in the general area of the site boundary: IS1, 2S2, 2S4, 3S1, 4S1, 5S1, 6S2, 7S1, 10SI, 1lS1, 15S1, 16S1.

An outer ring of stations, one in each land-based meteorological sector in the 5 - 11 km range (3.12 - 6.88 miles) from the site (not bounded by or over water): 4D2, 5D1, 1ODI, 14D1, 15D1, 2E1, 3E1, 11E2, 12E1, 13E1, 16Ei, 1F1, 3F2, 4F2, 5F1, 6F1, 9FI, 10F2, lIF1, 13F2, 14F2, 15F3.

The balance of the stations to be placed in special interest areas such as population centers, nearby residences, and schools: 2F2, 2F5, 2F6, 3F3, 7F2, 12F1, 13F3, 13F4, 16F2, 1G3, 10G1, 16G1, 3HI. and in two areas to serve as control stations: 3G1, 14G1.

TABLE 1 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND SAMPLE SAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY* OF FREQUENCY ANALYSIS

2. ATMOSPHERIC Samples from 6 locations:

a. Air Particulate 1 sample from close to the Site Boundary Continuous sampler Gross Beta / weekly 5S1 operation with Gamma isotopic analysis 3 Samples in different land based sectors: sample collection / quarterly composite IF1, 2F6, 5DI. weekly or more frequently if 1 Sample from the vicinity of a community: Iodine-131 / weekly

b. Air Iodine required by dust 16E1. loading 1 Sample from a control location, as for WO example 15-30 km distant and in the least prevalent wind direction: 14G1.

3. TERRESTRIAL Samples from milking animals in 3 locations within 5 km distance. If there are none, then, 1 sample from milking

a. Milk animals in each of 3 areas between 5 - 8 Semi-monthly Gamma scan / semi-km (3.12 - 5 miles) distant: 13E3, 14F4, (when animals are on monthly 2G3. (1) pasture) Iodine-131 / semi-monthly 1 Sample from milking animals at a control Monthly location 15 - 30 km distant (9.38 - 18.75 (when animals are Gamma scan/ monthly miles): 3G1. not on pasture) Iodine-131 / monthly

b. Well Water Samples from one or two sources only if (Ground) likely to be affected. (Although wells in the vicinity of SGS/HCGS are not directly Monthly Gamma Scan / monthly affected by plant operations, we sample Gross alpha / monthly 3E1 farm's well, as management audit) Gross beta / monthly Tritium / monthly

TABLE 1 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE SAMPLING AND AND/OR SAMPIE LOCATIONS COLLECTION TYPE/FREQUENCY*

FREQUENCY OF ANALYSIS

c. Potable Water One sample of the nearest water supply (Drinking Water) affected by its discharge (No potable water Monthly (composited Gross alpha / monthly samples are required as liquid effluents daily) discharged from SGS/HCGS do not directly Gross beta / monthly affect this pathway) However, for Tritium / monthly management audit samples, one raw and one Gamma scan / monthly treated sample from a public water supply Iodine-131 / monthly (City of Salem Water and Sewer Department) is collected: 2F3 C,)

d. Vegetables One sample of each principal class of food products from area that is irrigated by Annually (at Gamma scan/on collection water in which liquid plant wastes have harvest) been discharged (The Delaware River at the location of SGS/HCGS is a brackish water source and is not used for irrigation of food products). Management audit samples are collected from various locations during harvest: 2F9, 2F10, 3F6, 3F7, 1GI, 2G2, 9G2, and 3H5. In addition, the vegetables cabbage and kale were harvested from two on-site locations: IS1 and 16S1

e. Fodder Crops Broad leaf vegetation (ornamental cabbage) was planted & collected onsite in lieu of Annually (at Gamma scan/on collection having a milk farm within 5 km of the Site harvest)

(1): 1ODI, lS1, 15S1, 16S1. Although not required by SGS/HCGS ODCM, samples of crops normally used as cattle feed (silage-soybeans) were collected as management audit samples: 14F4, 3G1, 2G3, 13E3, 14G3.

TABLE 1 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE SAMPLING AND SAMPLE LOCATIONS COLLECTION TYPE /FREQUENCY*

FREQUENCY OF ANALYSIS.

f. Soil Although not required by SGS/HCGS ODCM, samples of soil are collected as management Every 3 years Gamma scan/on audit samples: 6S2, 2F9, 5F1, 1ODI, 16E1, (2007-2010-2013) collection 13E3, 14F4, 2G3, 3G1 (Not sampled during 2009)

4. AQUATIC ENVIRONMENT One sample upstream: 1F2 One sample downstream: 7E1 Monthly Gross Beta/monthly

a. Surface Water One sample outfall: IIAI Gamma scan/monthly (4 One sample cross-stream (mouth of Tritium/monthly**

CT, Appoquinimink River): 12C1 (2)

And an additional location in the Chesapeake & Delaware Canal: 16FI

b. Edible Fish One sample of each commercially and recreationally important species in Semi- Gamma scan (flesh)/ on vicinity of plant discharge area: 11Al annually collection One sample of same species in area not influenced by plant discharge: 12C1 (2)

And an additional location downstream: 7E1 One sample of each commercially and

c. Blue Crabs recreationally important species in Semi-Gamma scan (flesh)/ on vicinity of plant discharge area: 11A1 annually collection One sample of same species in area not influenced by plant discharge: 12C1 (2)

TABLE 1 (cont ' d)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE COLLECTION TYPE/FREQUENCY*

EXPOSURE PATHWAY LOCATIONS FREQUENCY OF ANALYSIS AND/OR SAMPLE

d. Sediment One sample from downstream area: 7E1 Semi - Gamma scan/on One sample from cross-stream area/One2 annually collection sample from a control location:-12Cl( )

One sample from outfall area: IIAl One sample from upstream, the C & D Canal: 16F1 One sample from shoreline area: 6S2 One sample from Cooling Tower Blowdown: 15AI And an additional location of south storm drain discharge line: 16A1 0)

Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.

- Tech Specs and ODCM require quarterly analysis but due to0the tritium leak at Salem, it was decided to analyze surface waters on a monthly basis for tritium.

(1) While these milk locations are not within the 5 km range, they are the closest farms in the Site vicinity.

Since broad leaf vegetation is acceptable in lieu of milk. collections, MTS personnel planted and harvested ornamental cabbage (Brassica oleracea) at three locations on Site (1SI, 15S1, 16S1) and one across the river in Delaware (10DI). In addition, the vegetables cabbage and kale were grown from seed by MTS and then planted at two locations on Site (IS1 & 16SI).

(2) Station 12C1 was made the operational control (1975) for aquatic samples since the physical characteristics of this station more closely resemble those of the outfall area than":d 'those at the upstream location originally chosen. This is due to the distance from Liston Point, which is the boundary between the Delaware River and Delaware Bay. As discussed extensively in the SGS/HCGS Pre-operational reports, the sampling locations further upstream show significantly lower background levels due to estuarine tidal flow.

FIGURE 1 GROSS BETA ACTIVITY INAIR PARTICULATE 1989 THROUGH 2009 1000 GROSS BETA INAIR PARTICULATE 1973 THROUGH 2009 1000 100 1 10 100 1976 1982 1988 1994 2000 2006 2009 4?

R 10 I

1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 iQUARTERLY AVERAGEI

FIGURE 2 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1989 THROUGH 2009 .,

10.0 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1973 THROUGH 2009 10-8-

6-8.0 4-2-

0-1976 1982 1988 1994 2000 2OO6 6.0 E 4.0 2.0 OFF-SITE STATIONS

-- ' CONTROL STATIONS V .

0.0 1988 1990 1992 1994 1996 1998' 2000 2002 2004 2006 2008 IQUARTERLY AVERAGE1

FIGURE 3 IODINE - 131 ACTIVITY IN MILK 1989 THROUGH 2009 20 IODINE-131 ACTIVITY IN MILK 1973 THROUGH 2009 30.001 20.00 10.00-10 1976 1982 1988 1994 2000 2006 co CO

-J 0

-10 -i I I I I I J I II F I I I I I I I I I I I I I I I I I I 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 QUARTERLY AVERAGE I

FIGURE 4 GROSS BETA ACTIVITY IN SURFACE WATER 1989 THROUGH 2009 1000 GROSS I 1000 100 10 -immi ...17 1976 1982 100 10-1 8 Ii 1

90 l11 19 iI 9 l IIii i III 2I 1988 1990 1992 1994 1996 " '99g8 ... 2000 2C 02 2004 2006 2008 1QUARTERLY AVERAGE

FIGURE 5 TRITIUM ACTIVITY IN SURFACE WATER 1989 THROUGH 2009 10,000 TRITIUM ACTMVTY IN SURFACE WATER 1973 Through 2003 10000 1000 100 1976 1982 1988 1994 2000 2006 1,000 Effluent Discharge near 1 0

, 05

-J 100 10 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 IQUARTERLY AVERAGE1

FIGURE 6 CESIUM-137 & COBALT-60 ACTIVITY IN AQUATIC SEDIMENT 1989 THROUGH 2009 10000 CESIUM-137 & COBALT40 ACTIVITY INAQUATIC SEDIMENT 1977 THROUGH 2009 there U has not been any Co4.O detected above MDC since 2002

- CS-137

-co-o *,

1001 100 1000i , ~ u u i r Ig~ ,II L I. I , l0oo I 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 ISEMI-ANNUAL AVERAGE

REFERENCES

[;] Public Service Enterprise Group. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971.

[2] Public Service Enterprise Group. "Environmental Report, Operating License Stage - Hope Creek Generating Station". 1983.

[3] United States Atomic Energy Commission. "Final Environmental Statement -

Salem Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311. 1973.

[4] United States Atomic Energy Commission. "Final Environmental Statement -

Hope Creek Generating Station", Docket No. 50-354. 1983.

[5] Publ'ic Service Enterpr;;ise Group. "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2".

[6] Public Service Enterprise Group. "Updated Final Safety Analysis Report - Hope Creek, Generating Station.

[7] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Annual Reports 1973 through 1982".

[8] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Preoperation Summary - 1973 through 1976".

RMC-TR-77-03, 1978.

[9] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program- December 11 to December 31, 1976". RMC-TR-77-02, 1977.

[10] Maplewood Testing Services. "Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program - Annual Reports 1983 through 2008".

[1 1a] Maplewood Testing Services. "Quality Assurance Manual." December 2009

[11b] Maplewood Testing Services. Mechanical Division "Quality Assurance / Control Plan".

December 2009.

[11c] Maplewood Testing Services. Mechanical Division Environmental/Radiological Group "Procedures Manual". December 2009.

[12] Public Service Enterprise Group. "Salem Nuclear Generating Station Technical Specifications", Appendix A to Operating License No. 'DPR-70, 1976, Sections 6.8.4.h - 1,2,3 and 6.9.1.7.

43

REFERENCES (cont'd)

[13] Public Service Enterprise Group. "Hope Creek Generating Station Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 6.8.4.h - 1,2,3 and 6.9.1.6.

[14] Public Service Enterprise Group. "Offsite Dose Calculation Manual"- Salem Generating Station. Revision 24.

[15] Public Service Enterprise Group. "Offsite Dose Calculation Manual"- Hope Creek Generating Station. Revision 24.

[16] U.S. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August 1980.

[17] U.S. Nuclear Regulatory Commission. "Environmental Technical Specifications For Nuclear Power Plants." Regulatory Guide 4.8, December 1975.

[18] U.S. Nuclear Regulatory Commission "NRC Inspection Manual". Inspection Procedure 84750, Issue Date 3/15/94.

[19] U.S. Nuclear Regulatory Commission: Code of Federal Regulations, Title 10 Part 20.1301 Standards for Protection Against Radiation.

[20] U.S. Nuclear Regulatory Commission: Code of Federal Regulations, Title 10 Part 50, Appendix A, General Design Criterion 64, Monitoring Radioactivity Releases.

[21] U.S. Nuclear Regulatory Commission: Code of Federal Regulations, Title10, Part 50, Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operations to meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents".

[22] U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants: Regulatory Guide 4.1, Rev. 1.

[23] U.S. Nuclear Regulatory Commission: Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Regulatory Guide 4.13, Rev. 1..

[24] U.S. Nuclear Regulatory Commission: Quality Assurance for Radiological Monitoring Programs (Normal Operations) Effluent Streams and Environment, Regulatory Guide 4.15, Rev. 1.

44

REFERENCES (cont'd)

[25] U.S. Nuclear Regulatory Commission: Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Boiling Water Reactors, NUREG -1302, April 1991.

[26] U.S. Nuclear Regulatory Commission: Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG -

1301, April 1991.

[27] U.S. Nuclear Regulatory Commission: Radiological Assessment Branch Technical

..Position, Revision 1, November 1979.

[28] NJDEP : "A South Jersey Homeowner's Guide to Radioactivity in Drinking Water:

Radium" Revised April 2004.

[29] American Nuclear Standards Institute, ANSI N545-1975, Performance Testing and Procedural Specification for Thermoluminescent Dosimetry (Environmental).

45

THIS PAGE INTENTIONALLY LEFT BLANK APPENDIX A PROGRAM

SUMMARY

47

THIS PAGE INTENTIONALLY LEFT BLANK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 2009 to DECEMBER 31, 2009 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Highest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD) ** Measurements I. AIRBORNE Air Particulates Beta 311 6.0 18 (260/260) 1F1 5.8 mi N 19 (52/52) 18 (51/52) 0 (10.1 pui/m)

(6.7-34) (6.7-34) (7.8-31) 5S1 0.86 mi E 19 (52/52)

(7-34)

Gamma Be7 24 2.0 84 (20/20) IF1 5.8 mi N 87 (4/4) 85 (4/4) 0~

(62-106) (72-106) (67-105)

K-40 24 9.0 12 (20/20) 2F6 7.3 mi NNE 13 (4/4) 12 (4/4) 0 (0 (9-15) (9-1!) (10-16)

Air Iodine 1-131 311 9.9 <LLD <LLD <LLD 0 (10-3 pCi/m 3)

II DIRECT Direct Radiation Quarterly 196 4.2 (172 /172) 1F1 5.8 mi N 5.6 (4/4) 4.3 (24/24) 0 (mrad/std. month) Badges (2.7-6.1) (5.2-6.1) (3.1-5.1)

Ill TERRESTRIAL Milk 1-131 80 1.0 <LLD <LLD <LLD 0 (pCi/L)

Gamma K-40 80 34 1370 (60/60) 14F4 7.6 mi WNW 1400 (20/20) 1340 (20/20) 0 (1240-1540) (1310-1470) (1210-1790)

RA-NAT 80 5.5 7.2 (2/60) 2G3 12 mi NNE 8.5 (1/20) <LLD 0 (5.8-8.5) (8.5-8.5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 2009 to DECEMBER 31, 2009 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Highest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT: of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)- Measurements III TERRESTRIAL Well Water Alpha .12 1.2 0.5 (1/12) 3E1 4.1 mi NE 0.5 (1112) No Control 0 (pCi/L) (0.5-0.5) (0.5-0.5) Location Beta 12 1..1" 2.4 (6/12) 3E1 4.1 mi NE 2.4 (6/12) No Control 0 (0.7-8.8) (0.7-8.8) Location H-3 12 144 <LLD . <LLD No Control 0 Location Gamma K-40 12 34 46 (6/12) 3E1 4.1mi NE 46 (6/12) No Control 0 (33-63) (33-63) Location (J, RA-NAT 12 6.6 123 (11/12) 3E1 4.1mi NE 123 (11/12) No Control 0 (36-174) (36-174) Location Potable Water Alpha 24 0.7 0.6 (2/24) 2F3 8.0 mi NNE 0.6 (2/24) No Control 0 (pCi/L) (0.5-0.7) (0.5-0.7) Location Beta 24 1.0- 3.3 (24/24) 2F3 8.0 mi NNE 3.3 (24/24) No Control 0 (2.2-5.6) (2.2-5.6) Location H-3 24 145 <LLD <LLD No Control 0 Location Gamma K-40 24 34 47 (8/24) 2F3 8.0 mi NNE 47 (8 124) No Control 0 (33-72) (33-72) Location 1-131 24 0.4 <LLD <LLD No Control 0 Location RA-NAT 24 6.6 24 (7/24) 2F3 8.0 mi NNE 24 (7/24) No Control 0 (4.8-88) (4.8-88) Location Th-232 24 11 12 (1/24) 2F3 8.0 mi NNE 12 (1/24) No Control 0 (12) (12) Location Fruit & Gamma Vegetables K-40 33 70 2370 (18/18) 16S1 0.57 mi NNW 3960 (2 /2) 1890 (15/15) 0 (pCi/Kg-wet) (1340-4810) (3110-4810) (1090-2820)

RA-NAT 33 22 <LLD 9G2 10.7 mi S 18 (1/5) 15 (2/15) 0 (18) (12-18)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 2009 to DECEMBER 31, 2009 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Highest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT: of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)' Measurements III TERRESTRIAL Fruit & Vegetables Be-7 33 51 277 (4/18) *16S1 0.57 mi NNW 299 (2/2) <LLD 0 (pCi/Kg-wet) (157-414) (183-414)

Fodder Crops Gamma (pCi/Kg-wet) Be-7 10 75 410 (7/8) 3G1 16.5 mi NE 1310 (1/2) 1310 (1/2) 0 (160-732) (1310) " (1310-1310)

K-40 10 32 4620 (8/8) 3G1 16.5 mi NE 9220 (2/2) 9220 (2/2) 0 (2380-14800) (5130-13300) .(5130-13300) 21 tn.

IVAQUATIC Surface Water Beta 60 9.7 74 (44/48) 7E1 4.5 mi SE 139 (12/12) 53 (12/12) 0 (pCi/L) (9-384) (47-384) (16-127)

H-3 60 150 246 (4/48) 7E1 4.5 mi SE 331 (2/12) <LLD 0 (154-340) (322-340)

Gamma K-40 60 34 82 (47/48) 7E1 4.5 mi SE 109 (12/12) 70 (12/12) 0 (34-147) (62-147) (51-117)

RA-NAT 60 6.6 7 (9/48) 1F2 7.1 mi N 11 (1/12) 7 (1/12) 0 (5-11) (11-11) (7-7)

.Th-232 60 11.0 11 (2/48) 11A1 0.2 mi SW 13 (1/12) <LLD 0 (10-13) (13)

Blue Crabs Gamma (pCi/kg-wet) K-40 4 55 1495 (2 /2) 12C1 2.52 mi. WSW 2035 (2/2) 2035 (2/2) 0 (1430-1560) (1770-2300) (1770-2300)

RA-NAT 4 24 21 (1/2) 11A1 0.2 mi. SW 21 (1/2) 18 (1/2) 0 (21) (21) (18)

Edible Fish Gamma (pCi/kg-wet) K-40 6 55 3320 (4/4) 11A1 0.2 mi. SW 3410 (2/2) 3165 (2/2) 0 (3230-3430) (3390-3430) (2980-3350)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 2009 to DECEMBER 31, 2009 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Highest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT . of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)- Measurements IVAQUATIC Edible Fish RA-NAT 6 24 <LLD 12C1 2.5 mi. WSW 12 (1/2) 12 (1/2) 0 (pCi/kg-wet) (12) (12)

Sediment (pCi/kg-dry) Gamma Be-7 14 135 135 (1/12) 6S2 0.2 mi. ESE 135 (1/2) <LLD 0 (135-135) (135-135)

K-40 14 55 7048 (12/12) 12C1 2.5 mi. WSW 14250 (212) 14250 (2/2) 0 (1290-16500) (13500-15000) (13500-15000)

Co-60 14 21 <LLD <LLD <LLD 0 Cs-137 14 15 58 (2/12) 11A1 0.2 mi. SW 63 (1/2) <LLD 0 (52-63) (63)

Mn-54 14 2.5 27 (1112) 16A1 0,7 mi. NNW 27 (1/2) <LLD 0 (27) (27)

RA-NAT 14 5.0 426 (12/12) 7E1 4.5 mi. SE 663 (2/2) 550 (2/2) 0 (73-826) (652-673) (537-563)

Th-232 14 8.1 611 (12/12) 12C1 2.5 mi. WSW 1025 (21/2) 1025 (2/2) 0 (81-1110) (1000-1050) (1000-1050)

LLD listed is the lower limit of detection which we endeavored to achieve during this reporting period. In some instances nuclides were detected at concentrations above/below the LLD values shown.

Mean calculated using values above LLD only. Fraction of measurements above LLD are in parentheses.

Typical LLD values.

APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 53

THIS PAGE INTENTIONALLY LEFT BLANK APPENDIX B SAMPLE DESIGNATION The PSEG's Maplewood Testing Services identifies samples by a three part code. The first two letters are the program identification code. Because of the proximity of the Salem and Hope Creek Stations a common environmental surveillance program is being conducted. The identification code, "SA", has been applied to Salem and Hope Creek stations. The next three letters are for the media sampled.

AIO = Air Iodine IDM = Immersion Dose (TLD)

APT = Air Particulate MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)

ESF = Edible Fish PWT = Potable Water (Treated)

ESS = Sediment SOL = Soil.

FPL= Green Leaf Vegetables SWA = Surface Water FPV = Vegetables (Various) VGT = Fodder Crops (Various)

GAM= Game (Muskrat) WWA= Well Water The last four symbols are a location code based on direction and distance from a standard reference point. The reference point is located at the midpoint between the center of the Salem 1 and Salem 2 containments. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction as follows:

1=N 5=E 5 = ES 9=S 13 = W 2 =NNE 6=ESE 10 =SSW 14 = WNW 3= NE 7=SE 11 SW 15= NW 4 =ENE 8 = SSE 12 =WSW 16 = NNW The next digit is a letter which represents the radial distance from the reference point:

S On-site location E = 4-5 miles off-site A 0-1 miles off-site F = 5-10 miles off-site B 1-2 miles off-site G = 10-20 miles off-site C 2-3 miles off-site H = >20 miles off-site D 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g.,

1,2,3,... For example, the designation SA-WWA-3E1 would indicate a sample in the Salem and Hope Creek program (SA), consisting of well water (WWA), which had been collected in sector number 3, centered at 45 degrees (north east) with respect to the midpoint between Salem 1 and 2 containments at a radial distance of 4 to 5 miles off-site, (therefore, radial distance E). The number I indicates that this is sampling station

1 in that particular sector.

55

TABLE B-I SAMPLING LOCATIONS Specific information about the individual sampling locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations with respect to the Site. A Portable Global Positioning System (GPS) was used to provide the coordinates of sampling locations.

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. FT DEG. MIN. FT I15 0.57mi. N 39 260 75 222 IDM, VGT 2S2 0.4 mi. NNE; Lamp Pole 65 Near HC Switch Yard 39 98 75 - 32 - 10 IDM 2S4 0.6 mi. NNE 39 110 75 - 31 - 992 IDM 3S1 0.58 mi. NE 39 140 75 - 31 - 678 IDM 4S1 0.60 mi. ENE 39 023 75 - 31 - 544 IDM

5SI 0.86 mi. E; site access road 39 668 75 - 31 - 187 AIO,APT,IDM 6S2 0.23mi. ESE; area around Helicopter Pad 39 719 75 912 IDM, SOL,ESS 7S1 0.12 mi. SE; station personnel gate 39 720 75 - 32 15 IDM Cn

0) 10SI 0.14 mi. SSW; inlet cooling water bldg. 39 700 75 - 32 - 160 IDM 1I11 0.09 mi. SW; service water inlet bldg. 39 719 75 - 32 - 225 IDM 15SI 0.57 mi. NW 39 161 75 - 32 - 525 IDM,VGT 16S1 0.57 mi. NNW 39 215 75 - 32 - 432 1 1A1 0.2 mi. SW; outfall area 39 59 75 - 32 - 25 ECH,ESF,ESS,SWA 1 IAIA 0.15 mi. SE; Located at the plant barge slip 39 - 27 - 41 75 - 32 - 02 Alternate SWA 15A1 0.65 mi. NW; cooling tower blow down discharge 39 67 75 32 - 19 ESS line outfall 16A1 0.24 mi. NNW; south storm drain discharge line 39 24 75 - 32 - 58 ESS 12C1 2.5 mi. WSW; west bank of Delaware River 39. - 27 - 22 75 - 34 - 08 ECH,ESF,ESS,SWA 12CIA 3.7 mi. WSW; Located at the tip of Augustine 39 17 75 - 34 - 48 Alternate SWA Beach Boat Ramp 4D2 3.7 mi. ENE; Alloway Creek Neck Road 39 292 75 - 28 175 IDM 5D1 3.5 mi. E; local farm 39 396 75 - 28 - 334 AIO,APT, IDM 1OD1 3.9 mi. SSW; Taylor's Bridge Spur 39 24 - 613 75 - 33 733 IDM, SOL,VGT 14D1 3.4 mi. WNW; Bay View, Delaware 39 26 75 - 35 - 521 IDM 15D1 3.8 mi. NW; Rt. 9, Augustine Beach 39 125 75 - 35 28 IDM

TABLE B-I (cont' d)

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. FT DEG. MIN. FT 2E1 4.4 mi. NNE; local farm 39 380 75 428 IDM 3E1 4.2 mi. NE; local farm 39 - 30 098 75 646 IDM, WWA 7El 4.5 mi. SE; 1 mi. W of Mad Horse Creek 39 - 25 - 08 75 64 ESF,ESS,SWA 7EIA 8.87 mi. SE; Located at the end of Bayside Road 39 - 22 57 75 24 Alternate SWA 11E2 5.0 mi. SW; Rt. 9 39 24 - 328 75 35 - 546 IDM 12El 4.4 mi. WSW; Thomas Landing 39 26 862 75 36 - 968 IDM 13E1 4.2 mi. W; Silver Run Road (Rt. 9) 39 27 - 989 75 36 - 735 IDM 13E3 5.0 mi. W; Local Farm, Odessa, DE 39 27 - 17 75 30 MLK,VGT, SOL 16El 4.1 mi. NNW; Port Penn 39 30 762 75 580 AIO,APT,IDM, SOL 1F1 5.8 mi. N; Fort Elfsborg 39 32 - 693 75 31 - 124 AIO,APT,IDM 1F2 7.1 mi. N; midpoint of Delaware River 39 33 - 08 75 32 - 54 SWA 2F2 8.5 mi. NNE; Pole at Corner of 5 th & Howell, 39 34 522 75 120 IDM Salem 2F3 8.0 mi. NNE; Salem Water Company 39 33 40 75 18 PWR,PWT 2F5 7.4 mi. NNE; Salem High School 39 33 - 448 -15 514 IDM O

4 2F6 7.3 mi. NNE; Southern Training Center 39 33 - 713 75 819 AIO,APT, IDM 2F9 7.5 mi. NNE; Local Farm , Tilbury Rd, Salem 39 33 - 55 75 30 FPV, FPL,SOL 2F10 9.2 mi. NNE; Local Farm, South Broadway .(Rt. 49) 39 35 - 35 75 35 FPV, FPL Pennsville 3F2 5.1 mi. NE;Hancocks Bridge Municipal Bld 39 30 - 410 75 578 IDM 3F3 8.6 mi. NE; Quinton Township School 39 32 - 616 75 735 IDM 3F6 6.5 mi. NE; Local Farm, Salem/Hancocks Bridge 39 32 - 03 75 . 00 FPV, FPL Road 3F7 7.2 mi. NE; Local Farm, Beasley Neck Road, RD#3 39 32 - 07 75 46 FPV, FPL 4F2 6.0 mi. ENE; Mays Lane, Harmersville 39 29 - 953 75 076 IDM 5FI 6.5 mi. E; Canton 39 28 - 360 75 031 IDM, SOL 6F1 6.4 mi. ESE; Stow Neck Road 39 26 - 396 75 148 IDM 7F2 9.1 mi. SE; Bayside, New Jersey 39 22 - 971 75 261 IDM 9F1 5.3 mi. S; D.P.A.L. 48912-30217 39 23 - 042 75 95 IDM 10F2 5.8 mi. SSW; Rt. 9 39 23 - 034 75 34 - 152 IDM 11F1 6.2 mi. SW; Taylor's Bridge Delaware 39 24 - 766 75 37 - 632 IDM 12Fl 9.4 mi. WSW; Townsend Elementary School 39 23 - 778 75 41 - 311 IDM 13F2 6.5 mi. W; Odessa, Delaware 39 27 - 297 75 39 - 372 IDM

TABLE B-1 (cont'd)

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. FT DEG. MIN. FT 13F3 9.3 mi. W; Redding Middle School, Middletown, 39 - 27 215 75 543 IDM Delaware 13F4 9.8 mi. W; Middletown, Delaware 39 - 26 - 857 75 43 - 111 IDM 14F2 6.7 mi. WNW; Boyds Corner 39.- 29 - 979' 75 39 - 042 IDM 14F4 7.6 mi. WNW; local farm 39 - 30 - 44 75 40 - 52 MLK,VGT, SOL 15F3 5.4 mi. NW 39 - 30 - 987 75 36 - 586 IDM 15F4 7.0 mi. NW; local farm; Port Penn Road; Delaware 39 - 31 - 21 75 38 - 31 FPV 16F1 6.9 mi. NNW; C&D Canal 39 - 33 - 55 75 34 - 25 ESS,SWA 16FlA 6.84 mi. NNW; Located at the C&D Canal tip 39 - 33 - 34 75 33 - 56 Alternate SWA 16F2 8.1 mi. NNW; Delaware City Public School 39 - 34 - 314 75 35 - 429 IDM IGl 10.9 mi. NNE; Rte. 49, South Broadway 39 - 37 - 113 75 30 - 178 FPV 1G3 19 mi. N; N. Church St. Wilmington, Del (Old 39: - 44 - 287 75 32 - 512 IDM Swedish Church Yard Park) 2G2 13.5 mi. NNE; Local Farm; Pointers Auburn Road (Rt. 39 - 38 - 19 75 26 - 10 FPV 540), Salem, NJ 08079 2G3 11.8 mi. NNE; Local Milk Farm, Corner of Routes 540 39 - 36 - 21 75 24 - 53 MLK, FPV,VGT, SOL

& 45, Mannington, NJ Co 2G4 11.3 mi. NNE; large family garden;.,Rt 45 & 39 - 36 - 02 75 25 21 FPV Welchville Rd,Mannington, NJ 3G1 16.5 mi. NE; Milk Farm; Daretown-Alloway Road, 39 35 - 913 75 16 - 804 IDM,MLK, VGT,SOL Woodstown 9G1 10.3 mi. S; Local Farm, Woodland Beach Rd., Smyrna, 39 - 18 - 47 75 33 50 FPV Delaware 9G2 10.7 mi. S; Local Farm, woodland Beach Road, 39 - 18 - 39 75 34 - 11 FPV, FPL Smyrna, Delaware 10G1 12 mi. SSW; Smyrna, Delaware 39 223 75 36 - 095 IDM 14G1 11.8 mi. WNW; Rte. 286/Bethel Church Road; Delaware 39 -'31 - 290 75 46 - 495 AIO,APT, IDM 16G1 15 mi. NNW; Across from Greater Wilmington Airport 39 - 40 - 637 75 35 - 570 IDM 3H1 32 mi. NE; National Park, New.Jersey 39 - 51 - 599 75 11 - 96 IDM 3H5 25 mi. NE; Farm Market, Rt 77 39 - 41 - 040 75 12 - 380 FPL,FPV NOTE: All station locations are referenced to the midpoint of the two Salem Units' Containments. The coordiinates of this location are: Latitude N 390 - 27' - 46.5" and Longitude W 750.- 32' - 10.6".

All Vegetables(FPV & FPL) and Vegetation (VGT), are management audit samples. Theyýare not required by the Salem &

Hope Creek Stations'. Tech Specs nor listed in the Station's ODCM. Vegetable samples are not always collected4in, consecutive years from the same farmer since they rotate the type of crop they grow.

MAP B-i TING STATIONS GENERA AND HOPE CREEK MONITORING PROGRAM SALEM RADIOLOGICAL ENVIRONMENTAL L OCA TIONS ON-SITE SAMPLING 1

16 HOPE CREEK GENERATING 155 RIVE DELWAR

~GENERATING s7 4

16S9 HOP CREEK 2S ATIN GENE STATION Cr Ic G~\Pro lee C S

60 APPENDIX C DATA TABLES 61

APPENDIX C DATA TABLES Appendix C presents the analytical results of the 2009 Radiological Environmental Monitoring Program for the period of January 1 to December 31, 2009.

TABLE NUMBER TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 2009 Concentrations of Gamma Emitters in Quarterly Composites of A ir Particulates ............................................................................................ . 65 C-2 2009 Concentrations of Gross Beta Emitters in Air Particulates .......................... 66 AIR IODINE C-3 20.09 Concentrations of Iodine-1 31 in Filtered Air .............................................. 68 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-4 2009 Direct Radiation Measurements - Quarterly TLD Results .............................. 70 TERRESTRIAL ENVIRONMENT MILK C-5 2009 Concentrations of Iodine-131 and Gamma Emitters in Milk ........................... 71 WELL WATER C-6 2009 Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in W ell Water .................................................................................. . 73 C-7 2009 Concentrations of Gamma Emitters in Well Water ....................................... 74 62

DATA TABLES (cont'd.)

TABLE NUMBER TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT (cont'd)

POTABLE WATER C-8 2009 Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in Raw and Treated Potable W aters .................................................. 75 C-9 2009 Concentrations of Iodine 131 and Gamma Emitters in Raw and Treated Potable Water .......................................... 76 FOOD PRODUCTS C-10 2009 Concentrations of Gamma Emitters in Vegetables ....................................... 77 FODDER CROPS C-1 1 2009 Concentrations of Gamma Emitters in Fodder Crops ................................... 78 AQUATIC ENVIRONMENT SURFACE WATER C-12 2009 Concentrations of Gross Beta Emitters in Surface Water ........................... . 79 C-1 3 2009 Concentrations of Gamma Emitters in Surface Water ............................... 80 C-14 2009 Concentrations of Tritium in Quarterly Composites of Surface

.Water ... ..................................... ............ 82 EDIBLE FISH C-15 2009 Concentrations of Gamma Emitters in Edible Fish ....................................... 83 BLUE CRABS C-16 2009 Concentrations of Gamma Emitters in Crabs ............................................... 84 SEDIMENT C-1 7 2009 Concentrations of Gamma Emitters in Sediment ......................................... 85 63

DATA TABLES (cont'd.)

TABLE NUMBER TABLE DESCRIPTION PAGE SPECIAL TABLES LLDs C-1 8 2009 PSEG Maplewood Testing Services' LLDs for Gamma S p e ctrosco py ..................................................................................................... 86 C-1 9 2009 PSEG Maplewood Testing Services' LLDs for Gross Alpha, Gross Beta and T ritium in A ir and Water ..................................................................................... 88 64

Table C-1 2009 CONCENTRATIONS OF GAMMA EMITTERS*

IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m 3 +/- 2 sigma STATION Sampling Period <--- Gamma Emitters--->

ID Start Stop Be-7 K-40 SA-APT-5S! 12/29/2008 to 3/30/2009 99+/-5 15+/-3 SA-APT-1 Fi 12/29/2008 to 3/30/2009 106+/-5 10+/-3 SA-APT-2F6 12/29/2008 to 3/30/2009 96+/-5 15+/-3 SA-APT-5D1 12/29/2008 to 3/30/2009 99+/-5 14+/-3 SA-APT-16E1 12/29/2008 to 3/30/2009 99+/-5 13+/-3 SA-APT-14G1(C) 12/29/2008 to 3/30/2009 105+/-6 10+/-3 SA-APT-5Sl 3/30/2009 to 6/29/2009 91+/-5 8+/-3 SA-APT-1 F1 3/30/2009 to 6/29/2009 81+/-4 10+/-2 SA-APT-2F6 3/30/2009 to 6/29/2009 92+/-5 13+/-3 SA-APT-5D1 3/30/2009 to 6/29/2009 85+/-5 12+/-3 SA-APT-16E1 3/30/2009 to 6/29/2009 79+/-5 13+/-4 SA-APT-14G1 (C) 3/30/2009 to 6/29/2009 91+/-5 14+/-4 SA-APT-5S1 6/29/2009 to 9/28/2009 81+/-6 14+/-4 SA-APT-1 F1 6/29/2009 to- 9/28/2009 88+/-6 14+/-3 SA-APT-2F6 6/29/2009 to 9/28/2009 85+/-5 13+/-3 SA-APT-5DI 6/29/2009 to 9/28/2009 87+/-5 10+/-3 SA-APT-16E1 6/29/2009 to 9/28/2009 84+/-5 14+/-3 SA-APT-14G1 (C) 6/29/2009 to 9/28/2009 78+/-5 11+/-3 SA-APT-5S1 9/28/2009 to 12/29/2009 64+/-4 10+/-3 SA-APT-1 F1 9/28/2009 to 12/29/2009 72+/-4 10+/-3 SA-APT-2F6 9/28/2009 to 12/29/2009 63+/-4 9+/-2 SA-APT-5D1 9/28/2009 to 12/29/2009 70+/-4 14+/-3 SA-APT-16E1 9/28/2009 to 12/29/2009 62+/-4 10+/-2 SA-APT-14G1(C) 9/28/2009 to 12/29/2009 67+/-5 16+/-4 AVERAGE 84+/-26 12+/-4

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18.

(C) Control Station 65

TABLE C-2 2009 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCilmr +1-2 sigma

< ~STATION ID .

Control MONTH SA-APT-14G1 SA-APT-16E1 SA-APT-1F1 SA-APT-2F6 SA-APT-5D1 SA-APT-5S1 AVERAGE January 24+/-2 26+/-2 25+/-2 26+/-2 24+/-2 26+/-2 25+/-2 21+/-2 19+/-2 19+/-2 20+/-2 16+/-2 24+/-2 20+/-6 22+/-2 *21+/-2 20+/-2 23+/-2 24+/-2 25+/-2 22+/-4 31+/-2 27+/-2 31+/-2 32+/-2 27+/-2 34+/-2 30+/-5 24+/-2 23+/-2 31+/-2 29+/-2 24+/-2 28+/-2 26+/-7 February 20+/-2 21+/-2 27+/-2 20+/-2 21+/-2 26+/-2 23+/-6 (1) 13+/-2 17+/-2 17+/-2 16+/-2 18+/-2 16+/-4 18+/-1 17+/-2 20+/-2 19+/-2 21+/-2 20+/-2 19+/-3 19+/-2 18+/-2 24+/-2 24+/-2 23+/-2 22+/-2 22+/-5 March 25+/-2 25+/-2 28+/-3 26+/-3 24+/-3 25+/-2 26+/-3 0)

0) 21+/-2 20+/-2 21+/-2 15+/-2 21+/-2 24+/-2 20+/-6 23+/-2 21+/-2 26+/-2 21+/-2 22+/-2 27+/-2 23+/-5 11+/-2 10+/-2 8+/-2 11+/-2 12+/-2 9+/-2 10+/-3 April 13+/-2 11+/-2 14+/-2 14+/-2 12+/-2 13+/-2 13+/-2 22+/-2 18+/-2 21+/-2 20+/-2 17+/-2 22+/-2 20+/-4 19+/-2 19+/-2 20+/-2 19+/-2 20+/-2 25+/-2 20+/-4 17+/-2 15+/-2 19+/-2 15+/-2 15+/-2 17+/-2 16+/-4 May 17+/-2 16+/-2 17+/-2 20+/-2 19+/-2 20+/-2 18+/-3 11+/-2 9+/-1 10+/-2 10+/-2 9+/-2 9+/-2 9+/-2 15+/-2 10+/-2 16+/-2 14+/-2 14+/-2 15+/-2 14+/-4 16+/-2 13+/-2 19+/-2 17+/-2 14+/-2 16+/-2 16+/-4 11+/-2 9+/-2 9+/-2 9+/-1 ,8+/-1 7+/-1 9+/-2 June 11+/-2 11+/-2 8+/-2 14+/-2 12+/-2 16+/-3 12+/-6 11+/-2 12+/-2 14+/-2 12+/-2 11+/-2 12+/-2 12+/-2 8+/-2 7+/-2 7+/-2 7+/-2 7+/-2 7+/-2 7+/-1 16+/-2 14+/-2 17+/-2 17+/-2 16+/-2 16+/-2 16+/-2

TABLE C-2 2009 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m 3 +/- 2 sigma

- STATION ID Control MONTH SA-APT-14G1 SA-APT-16E1 SA-APT-1F1 SA-APT-2F6 SA-APT-5D1 SA-APT-5S1 AVERAGE July 15+/-2 17+/-2 14+/-2 13+/-2 16+/-2 16+/-2 15+/-3 11+/-2 13+/-2 13+/-3 11+/-2 13+/-2 13+/-2 12+/-2 23+/-2 19+/-2 20+/-2 21+/-2 21+/-2 22+/-2 21+/-3 15+/-2 18+/-2 16+/-2 18+/-2 15+/-2 15+/-2 16+/-3 10+/-2 13+/-2 14+/-2 17+/-2 12+/-2 13+/-2 13+/-4 August (2) 21+/-2 25+/-2 22+/-2 17+/-2 23+/-2 24+/-2 22+/-6 27+/-4 26+/-4 34+/-4 28+/-4 27+/-4 34+/-4 29+/-7 25+/-4 23+/-4 19+/-4 20+/-4 21+/-4 23+/-4 22+/-5 18+/-4 17+/-4 19+/-4 18+/-4 13+/-4 21+/-4 18+/-6 September (2) 23+/-5 22+/-5 19+/-5 28+/-6 25+/-5 25+/-5 24+/-6 C) 13+/-2 14+/-2 20+/-2 12+/-2 13+/-2 17+/-2 15+/-6 23+/-2 21+/-2 22+/-2 19+/-2 20+/-2 18+/-2 21+/-4 17+/-2 14+/-2 13+/-2 16+/-2 14+/-2 15+/-2 15+/-3 October 17+/-2 17+/-2 17+/-2 16+/-2 14+/-2 17+/-2 16+/-2 16+/-2 15+/-2 15+/-2 16+/-2 15+/-2 20+/-2 16+/-4 16+/-2 13+/-2 15+/-2 15+/-2 14+/-2 14+/-2 14+/-2 24+/-2 21+/-2 24+/-2 24+/-2 20+/-2 21+/-2 22+/-3 10+/-2 11+/-2 11+/-2 12+/-2 12+/-2 13+/-2 11+/-2 November 19+/-2 18+/-2 18+/-2 20+/-2 17+/-2 15+/-2 18+/-3 20+/-2 15+/-2 19+/-2 21+/-2 18+/-2 21+/-2 19+/-4 19+/-2 17+/-2 20+/-2 17+/-2 18+/-2 18+/-2 18+/-2 16+/-2 14+/-2 15+/-2 16+/-2 15+/-2 17+/-2 15+/-2 December 13+/-2 14+/-2 16+/-2 14+/-2 13+/-2 16+/-2 14+/-2 27+/-2 22+/-2 28+/-2 31+/-2 23+/-2 30+/-2 27+/-8 23+/-2 21+/-2 25+/-2 20+/-2 19+/-2 23+/-2 22+/-4 15+/-2 14+/-2 15+/-2 17+/-2 17+/-2 14+/-2 15+/-3 AVERAGE 18+/-11 17+/-10 19+/-12 18+/-11 17+/-10 19+/-12 18+/-11 GRAND AVERAGE 18+/-11 (1) Location 14G1 result was for the two week duration of 2/9-23/09. See Program Deviations.

(2) All weekly samples from 8/10-9/08/09 were analyzed by AREVA-NP Laboratory.

TABLE C-3 2009 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR 3

Results in Units of 10"3 pCil/

< STATION ID Control MONTH SA-AIO-14G1 SA-AIO-16E1 SA-AIO-1F1 SA-AIO-2F6 SA-AIO-5D1 SA-AIO-5S1 January <1.8 <4.1 <3.8 <5.7 <3.1 <3.2

<2.1 <2 <2 <4.8 <2.8 <2.5

<2.8 <5.1 <2.3 <3.7 <2.1 <3.1

<4.8 <3.7 <2.2 <2.2 <2.5 <4

<3.8 <5.5 <3.2 <4.1 <4.4 <2.5 February <2.1 <4.4 <3.7 <2 <2.2 <2.3 (1) <3.2 <2.2 <2.8 <5.2 <4.3

<2.1 <5.7 <2.9 <4.8 <4.1 <6

<4.2 <2.3 <2.7 <1.2 <2.6 <2.2 March <3 <3.5 <2.4 <5.8 <4.3 <3.9

<1.7 <1.5 <2.5 <1.6 <2.7 <2.5

0) <4.1 <3.5 <1.8 <3.2 O, <2.9 <3.1

<3.7 <3 <1.8 <2.3 <3.5 <1.9 April <2 <3.5 <3.4 <2.1 <4.1 <4.8

<4.4 <2.7 <1.6 <3.6 <5 <2.9

<3.3 <5.5 <1.9 <1.5 <4 3.1

<3.4 <6.3 <3.9. <3.1 <4 <3.6 May <3.1 <3.7 <3.7 <1.6 <5.2 <4.2

<2.3 <2 <5.8 <8.1 <2.1 <2.9

<3.3 <4 <1.7 <5.2 <1.5 <3.2

<2.5 <2.3 <1.5 <4.8 <6 <2.2

<4 <1.6 <4.1 <3.7 <5.1 <2.1 June <5.2 <4.8 <3.3 <4.5 <5.4 <5.5

<4.7 <2 <1.7 <2.5 <3.3 <2

<4 <4.2 <3.4 <2 <1.9 <2.5

<4.9 <2.6 <2 <4.7 <3.5 <2

TABLE C-3 2009 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR 3

Results in Units of 10-3 pCl/m S.-.-.-------- STATION ID - -------------- -

Control MONTH SA-AIO-14GI SA-AIO-16E1 SA-AIO-1F1 SA-AIO-2F6 SA-AIO-5D1 SA-AIO-5S1 July <2.3 <3.4 <2.4 <1.4 <2.6 <2.1

<6.1 <2.2 <2.9 <9.7 <8.2 <6.6

<1.7 <1.9 <3.7 <2.1 <2.6 <4.1

<4.1 <4.9 <3.7 <3.9 <2.7 <2

<2.2 <3.8 <4.8 <1.9 <2.3 <5.9 August (2) <2.6 <2.4 <4.8 <7.6 <2.8 <1.9

<9.1 <8.5 <9.1 <8.9 <9 <8.6

<8.1 <9.5 <9.4 <8.7 <9.9 <9.5

<9.3 "<9.4 <9.8

<9.7 <9.9 <9.2

<9.2 September (2) <9.8 <8.2 <9.5 <9.6 <9.7.

<5.2 <4.6 <5.3 <1.6

<6.2 <4.1

0) <2.2 <1.3 <1.6 <1.7 <2.7 <3.3 to <3.9 <1.5 .<3 <2.3 <4.2 <3.5 October <2.5 <4.8 <2.7 <4.4 <5.1 <3.7

<3.9 <2.2 <1.7 <3.8 <2.3 <3.2

<2.7 <2.3 <2.8 <3.2 <5.3 <2.8

<4.3 <3.2 <3.9 <6 <3 <3.6

<5.4 <8.1 <5.8 <2.7 <4.2 <3.2 November <4.3 <1.7 <2.1 <6.3 <2.3 <2.6

<3.3 <3 <4.5 <4 <2.5 <5.1

<2.7 <,*.2

<2.2 <1.6 <2.1 <4.6

<5.7 <1.9 <2.5 <3.9 <3.6 <1.9 December <2.7 <1.7 <3.6 <2 <4.4 <1.1

<4.1 <3.9 <5.4 <2.6 <2.8 <2.8

<3.6 <4 <1.7 <2.2 <2.7 <2

<1.5 <2.3 <2.7 <4.3 <4.3 <3.1

1-131 results are corrected for decay to sample stop date.

(1) Location 14G1 result was for the two week duration of 2/9-23/09. See Program Deviation.

(2) Weekly AIO Samples from 8/10-9/08/09 were analyzed by AREVA-NP Laboratory.

TABLE C-4 2009 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mR/standard month* +/- 2 sigma JAN APR JUL OCT -QTR STATION to to to to ELEMENTS ID MAR JUN SEP DEC AVG SA-IDM-1S1 4.4+/-0.6 4.8+/-0.4 4.8+/-0.5 5.2+/-0.5 4.8+/-0.6 SA-IDM-2S2 4.7+/-0.5 5.3+/-0.4 5.0+/-0.6 5.4+/-0.7 5.1+/-0.6 SA-IDM-2S4 3.9+/-0.4 4.3+/-0.4 3.8+/-0.6 4.1+/-0.4 4.0+/-0.5 SA-IDM-3S1 2.9+/-0.4 3.4+/-0.6 3.2+/-0.4 3.7+/-0.4 3.3+/-0.7 SA-IDM-4S1 3.8+/-0.4 4.2+/-0.5 3.9+/-0.7 4.2+/-0.4 4.0+/-0.4 SA-IDM-5S1 3.2+/-0.4 3.6+/-0.3 3.5+/-0.4 3.9+/-0.4 3.6+/-0.6 SA-IDM-6S2 4.9+/-0.7 5.5+/-0.6 5.0+/-0.6 5.2+/-0.4 5.2+/-0.5 SA-IDM-7S1 5.2+/-0.5 6.0+/-0.5 5.3+/-0.9 5.6+/-0.5 5.5+/-0.7 SA-IDM-10S1 3.4+/-0.4 4.0+/-0.3 3.5+/-0.6 4.7+/-0.6 3.9+/-1.2 SA-IDM-11S1 3.0+/-0.5 3.8+/-0.4 3.3+/-0.4 4.4+/-0.5 3.6+/-1.3 SA-IDM-15S1 3.3+/-0.3 3.7+/-0.4 3.4+/-0.4 3.7+/-0.3 3.5+/-0.4 SA-IDM-16S1 4.0+/-0.5 4.5+/-0.3 4.1+/-0.4 4.7+/-0.4 4.3+/-0.7 SA-IDM-4D2 4.2+/-0.5 4.9+/-0.4 4.3+/-0.5 4.7+/-0.5 4.5+/-0.6 SA-IDM-5D1 3.6+/-0.4 4.2+/-0.3 3.7+/-0.5 4.1+/-0.5 3.9+/-0.6 SA-IDM-10D1 4.3+/-0.4 4.7+/-0.3 4.8+/-0.6 4.9+/-0.8 4.7+/-0.6.

SA-IDM-14D1 3.7+/-0.4 4.6+/-0.8 3.8+/-0.5 4.3+/-0.6 4.1+/-0.8 SA-IDM-15D1 4.4+/-0.5 4.7+/-0.5 4.4+/-0.6 4.8+/--0.4 4.6+/-0.4 SA-IDM-2E1 3.9+/-0.4 4.4+/-0.3 4.1+/-0.5 4.4+/-0.5 4.2+/-0.5 SA-IDM-3E1 3.1+/-0.4 3.6+/-0.3 3.4+/-0.4 3.6+/-0.3 3.4+/-0.4 SA-IDM-1 1E2 4.3+/-0.4 4.8+/-0.4 4.4+/-0.6 4.8+/-0.6 4.6+/-0.6 SA-IDM-12E1 4.3+/-0.6 4.8+/-0.4 4.5+/-0.7 4.9+/-0.5 4.6+/-0.5 SA-IDM-13E1 3.4+/-0.5 3,8+/-0.5 3.5+/-0.6 4.0+/-0.6 3.7+/-0.6 SA-IDM-16E1 4.2+/-0.4 4.5+/-0.4 4.7+/-0.5 4.6+/-0.6 4.5+/-0.4 SA-IDM-1F1 5.2+/-0.5 6.1+/-0.7 5.6+/-0.5 5.6+/-0.6 5.6+/-0.7 SA-IDM-2F2 3.3+/-0.4 3.7+/-0.6 3.6+/-0.6 3.8+/-0.6 3.6+/-0.4 SA-IDM-2F5 4.1+/-0.5 4.5+/-0.5 4.3+/-0.8 4.5+/-0.4 4.3+/-0.4 SA-IDM-2F6 3.7+/-0.4 4.2+/-0.6 4.0+/-0.5 4.1+/-0.3 4.0+/-0.4 SA-IDM-3F2 3.5+/-0.4 3.8+/-0.4 3.8+/-0.5 3.9+/-0.3 3.7+/-0.4 SA-IDM-3F3 3.5+/-0.3 3.8+/-0.4 3.8+/-0.5 4.0+/-0.5 3.8+/-0.4 SA-IDM-4F2 3.2+/-0.3 3.9+/-0.4 3.6+/-0.4 3.9+/-0.5 3.6+/-0.7 SA-IDM-5F1 3,5+/-0.4 4.1+/-0.4 3.8+/-0.5 4.0+/-0.5 3.8+/-0.5 SA-IDM-6F1 2.9+/-0.5 3.3+/-0.3 3.0+/-0.7 3.4+/-0.4 3.2+/-0.4 SA-IDM-7F2 4.2+/-0.4 3.0+/-0.4 2.9+/-0.4 2.9+/-0.3 3.3+/-1.3 SA-IDM-9F1 4.5+/-0.5 5.0+/-0.4 4.8+/-0.5 5.1+/-0.5 A.8+/-0.5 SA-IDM-10F2 2.7+/-0.3 4.5+/-0.4 4.4+/-0.5 4.8+/-0.5 4.1+/-1.9 SA-IDM-11 F1 4.3+/-0.5 3.8+/-0.5 4.3+/-0.4 5.0+/-0.5 4.3+/-1.0 SA-IDM-12F1 4.1+/-0.5 4.5+/-0.4 4.2+/-0.6 4.5+/-0.4 4.3+/-0.4 SA-IDM-13F2 3.9+/-0.6 4.4+/-0.5 4.1+/-0.5 4.5+/-0.5 4.2+/-0.5 SA-IDM-13F3 4.1+/-0.5 4.5+/-0.3 4.2+/-0.5 4.6+/-0.5 4.4+/-0.4 SA-IDM-13F4 4.6+/-0.4 5.1+/-0.4 4.7+/-0.5 5.0+/-0.5 4.8+/-0.5 SA-IDM-14F2 4.5+/-0.4 4.8+/-0.7 4.7+/-0.6 5.5+/-0.6 4.9+/-0.9 SA-IDM-15F3 4.3+/-0.5 4.9+/-0.6 4.7+/-0.5 5.1+/-0.4 4.7+/-0.6 SA-IDM-16F2 3.6+/-0.5 4.4+/-0.4 3.8+/-0.5 4.2+/-0.5 4.0+/-0.7 SA-IDM-1G3 (C) 4.9+/-0.7 4.8+/-0.6 4.0+/-0.6 4.6+/-0.4 4.6+/-0.8 SA-IDM-3G1 (C) 4.0+/-0.4 4.7+/-0.4 4.3+/-0.6 4.6+/-0.6 4.4+/-0.6 SA-IDM-10G1(C) 4.1+/-0.5 4.6+/-0.5 4.4+/-0.5 4.8+/-0.4 4.5+/-0.6 SA-IDM-14G1(C) 4.1+/-0.5 4.9+/-0.4 4.4+/-0.6 4.8+/-1.0 4.5+/-0.8 SA-IDM-16G1(C) 3.7+/-0.4 4.1+/-0.4 3.8+/-0.4 4.2+/-0.5 4.0+/-0.5 SA-IDM-3H1 (C) 3.1+/-0.5 3.7+/-0.3 3.4+/-0.7 4.0+/-0.3 3.5+/-0.7 AVERAGE 3.9+/-1.2 4.4+/-1.3 4.1+/-1.2 4.5+/-1.2 GRAND AVG 4.2+/-1.3

Results are reported in millroentgen (mR) with the standard month = 30.4 days.

Quarterly Element TLD results by AREVA - NP Environmental Laboratory.

(C) Control Station 70

TABLE C-5 2009 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +1-2sigma SAMPLING PERIOD <---- GAMMA EMITTERS ---- >

STATION ID START STOP 1-131 K-40 RA-NAT SA-MLK-2G3 1/4/2009 1/5/2009 <0.2 1360 +/-74 <3 SA-MLK-13E3 1/4/2009 1/5/2009 <0.2 1410 +/-69 <3 SA-MLK-14F4 1/4/2009 1/5/2009 <0.1 1350 +/-70 <3.2 SA-MLK-3G1 (C) 1/4/2009 1/5/2009 <0.3 1360 +/-75 <3.1 SA-MLK-2G3 2/1/2009 2/2/2009 <0.2 1350 +/-73 <3.5 SA-MLK-13E3 2/1/2009 2/2/2009 <0.2 1350 +/-73 <3.4 SA-MLK-14F4 2/1/2009 2/2/2009 <0.2 1440 +/-69 <3.1 SA-MLK-3G1 (C) 2/1/2009 2/2/2009 <0.2 1290 +/-70 <3 SA-MLK-2G3 3/2/2009 3/3/2009 <0.2 1270 +/-73 <3.4 SA-MLK-13E3 3/2/2009 3/3/2009 <0.2 1380 +/-72 <2.8 SA-MLK-14F4 3/2/2009 3/3/2009 <0.2 1370 +/-78 <2.9 SA-MLK-3G1 (C) 3/2/2009 3/3/2009 <0.2 1340 +/-71 <3.1 SA-MLK-2G3 4/5/2009 4/6/2009 <0.2 1240 +/-65 <3.9 SA-MLK-13E3 4/5/2009 4/6/2009 <0.2 1360 +/-70 <4.3 SA-MLK-14F4 4/5/2009 4/6/2009 <0.2 1370 +/-54 <2.8 SA-MLK-3G1 (C) 4/5/2009 4/6/2009 <0.2 1360 +/-74 <3 SA-MLK-2G3 4119/2009 4/20/2009 <0.2 1250 +/-73 <5.5 SA-MLK-13E3 4/19/2009 4/20/2009 <0.2 1290 +/-73 <3.3 SA-MLK-14F4 4/19/2009 4/20/2009 <0.2 1420 +/-72 <3.2 SA-MLK-3G1 (C) 4/19/2009 4/20/2009 <0.2 1230 +/-63 <3.6 SA-MLK-2G3 5/3/2009 5/4/2009 <0.2 1280 +/-73 8.5 +/-3 SA-MLK-13E3' 5/2/2009 5/3/2009 <0.2 1430 +/-76 5.8 +/-2 SA-MLK-14F4 5/3/2009 5/4/2009 <0.2 1420 +/-72 <4 SA-MLK-3G1 (C) 5/3/2009 5/4/2009 <0.2 1330 +/-74 <3.2 SA-MLK-2G3 5/17/2009 5/18/2009 <0.2 1360 +/-66 <3.8 SA-MLK-13E3 5/17/2009 5/18/2009 <0.2 1270 +/-67 <3.8 SA-MLK-14F4 5/17/2009 5/18/2009 <0.2 1380 +/-72 <3.2 SA-MLK-3G1 (C) 5/17/2009 5/18/2009 <0.2 1330 +/-73 <2.8 SA-MLK-2G3 6/11/2009 6/2/2009 <0.2 1280 +/-69 <3.5 SA-MLK-13E3 6/1/2009 6/2/2009 <0.2 1360 +/-68 <3.7 SA-MLK-14F4 6/1/2009 6/2/2009 <0.2 1420 +/-75 <3 SA-MLK-3G1 (C) 6/1/2009 6/2/2009 <0.2 1320 +/-72 <3.1 SA-MLK-2G3 6/14/2009 6/15/2009 <0.2 1310 +/-70 <4.1 SA-MLK-13E3 6/14/2009 6/15/2009 <0.2 1380 +/-73 <3 SA-MLK-14F4 6/14/2009 6/15/2009 <0.2 1360 +/-77 <2.9 SA-MLK-3G1 (C) 6/14/2009 6/15/2009 <0.2 1480 +/-75 <3.1 SA-MLK-2G3 7/5/2009 7/6/2009 <0.3 1330 +/-72 <3.3 SA-MLK-13E3 7/5/2009 7/6/2009 <0.3 1390 +/-73 <2.9 SA-MLK-14F4 7/5/2009 7/6/2009 <0.3 1450 +/-75 <3.1 SA-MLK-3G1 (C) 7/5/2009 7/6/2009 <0.3 1290 +/-71 <4.1 SA-MLK-2G3 7/19/2009 7/20/2009 <0.3 1390 +/-70 <4.1 SA-MLK-13E3 7119/2009 7/20/2009 <0.2. 1400 +/-73 <3.1 SA-MLK-14F4 7/19/2009 7/20/2009 <0.2 1440 +/-76 <2.6 SA-MLK-3G1 (C) 7/19/2009 7/20/2009 <0.3 1270 +/-75 <2.6 71

TABLE C-5 2009 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD <---- GAMMA EMITTERS ---- >

STATION ID START STOP 1-131 K-40 RA-NAT SA-MLK-2G3 8/2/2009 8/3/2009 <0.3 1330 +/-73 <3.6 SA-MLK-13E3 8/2/2009 8/3/2009 <0.2 1350 +/-73 <2.9 SA-MLK-14F4 8/2/2009 8/3/2009 <0.2 1460 +/-74 <3.4 SA-MLK-3G1 (C) 8/2/2009 8/3/2009 <0.3 1310 +/-72 <4.2 SA-MLK-2G3 (1) 8/16/2009 8/17/2009 <0.8 1540 +/-170 <18 SA-MLK-13E3 8/16/2009 8/17/2009 <0.8 1520 +/-140 <16 SA-MLK-14F4 8/16/2009 8/17/2009 <1 1380 +/-120 <9.4 SA-MLK-3G1 (C) 8/16/2009 8/17/2009 <1 1290 +/-220 <21 SA-MLK-2G3 (1) 9/7/2009 9/8/2009 <1 1520 +/-190 <21 SA-MLK-13E3 9/7/2009 9/8/2009 <0.9 1480 +/-110 <9.5 SA-MLK-14F4 9/7/2009 9/8/2009 <0.9 1470 +/-210 <20 SA-MLK-3G1 (C) 9/7/2009 9/8/2009 <1 1790 +/-150 <24.

SA-MLK-2G3 9/20/2009 9/21/2009 <0.2 1330 +/-69 <3.7 SA-MLK-13E3 9/20/2009 9/21/2009 <0.2 1480 +/-79 <2.8 SA-MLK-14F4 9/20/2009 9/21/2009 <0.3 1370 +/-74 <3.8 SA-MLK-3G1 (C) 9/20/2009 9/21/2009 <0.2 1340 +/-72 <4.9 SA-MLK-2G3 10/4/2009 10/5/2009 <0.2 1400 +/-75 <3.1 SA-MLK-13E3 10/4/2009 10/5/2009 <0.3 1320 +/-73 <2.9 SA-MLK-14F4 10/4/2009 10/5/2009 <0.2 1310 +/-68 <3.8 SA-MLK-3G1 (C) 10/4/2009 10/5/2009 <0.3 1210 +/-68 <3.6 SA-MLK-2G3 10/25/2009 10/26/2009 <0.2 1240 +/-68 <5.8 SA-MLK-13E3 10/25/2009 10/26/2009 <0.2 1390 +/-74 <4.5 SA-MLK-14F4 10/25/2009 10/26/2009 <0.2 1420 +/-75 <3.1 SA-MLK-3G1 (C) 10/25/2009 10/26/2009 <0.2 1310 +/-73 <3.1 SA-MLK-2G3 11/1/2009 .11/2/2009 <0.2 1350 +/-74 <3.6 SA-MLK-13E3 11/1/2009 11/2/2009 <0.3 1290 +/-69 <3.8 SA-MLK-14F4 11/1/2009 11/2/2009 <0.2 1320 +/-70 <5.1 SA-MLK-3G1 (C) 11/1/2009 11/2/2009 <0.3 1360 +/-71 <4.4 SA-MLK-2G3 11/15/2009 11/16/2009 <0.3 1330 +/-73 <3.9 SA-MLK-13E3 11/15/2009 11/16/2009 <0.2 1490 +/-80 <2.6 SA-MLK-14F4 11/15/2009 11/16/2009" <0.2 1370 +/-74 <3 SA-MLK-3G1 (C) 11/15/2009 11/16/2009 <0.3 1320 +/-71 <3.3 SA-MLK-2G3 12/6/2009 12/7/2009 <0.2 1290 +/-71 <3.7 SA-MLK-13E3 12/6/2009 12/7/2009 <0.2 1380 +/-72 <5.4 SA-MLK-14F4 12/6/2009 12/7/2009 <0.2 1390 +/-70 <4.1 SA-MLK-3G1 (C) 12/6/2009 12/7/2009 <0.3 1240 +/-69 <3.7 AVERAGE - 1360 +/-170

Iodine-1 31 results are corrected for decay to stop date of collection period & analyzed to an LLD of 1.0 pCi/L.

- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18 Monthly sample collected during Jan., Feb., March and Dec., when animals are not on pasture.

(C) Control Station (1) Results from August 16th through September 8th for all locations by AREVA-NP Laboratory 72

TABLE C-6 2009 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN WELL WATER (Ground Water)*

Results in Units of pCi/L +/-2 sigma SAMPLING GROSS GROSS STATION ID DATE ALPHA BETA TRITIUM SA-WWA-3E1 1/26/2009 <0.5 8.8+/-0.8 <143 SA-WVA-3E 1 2/23/2009 <0.8 1.7+/-0.6 <138 SA-WWA-3E 1 3/30/2009 0.5+/-0.4 <0.7 <136 SA-WWA'-3E1 4/27/2009 <1.1 <1.3 <134 SA-VWVA-3E 1 5/26/2009 <0.8 1.4+/-0.7 <136 SA-WWA-3E1 6/29/2009 <0.9 <1.4 <132 SA-VWVA-3E1 7/27/2009 <0.6 <1.2 <130 SA-WWA-3E1 8/31/2009 <0.7 0.9+/-0.6 <132 SA-WWA-3E1 9/28/2009 <0.7 <0.9 <136 SA-WWA-3E1 10/26/2009 <0.5 <0.9 <139 SA-WWA-3E1 11/30/2009 <0.8 0.7+/-0.5 <124 SA-WWA-3E1 12/29/2009 <0.7 1+/-0.6 <144 AVERAGE

Management Audit Sample: not required by ODCM.

73

TABLE C-7 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN WELL WATER*"

Results in Units of pCi/L +/- 2 sigma SAMPLING <----GAMMA EMITTERS .... >

STATION ID DATE K-40 RA-NAT SA-WWA-3E1 1/26/2009 63+/-28 172+/-4 SA-WWA-3E1 2/23/2009 <17 154+/-6 SA-WWA-3E1 3/30/2009 <15 124+/-4 SA-WWA-3E1 4/27/2009 40+/-20 139+/-4 SA-WWA-3E1 5/26/2009 33+/-14 151+/-6 SA-WWA-3E1 6/29/2009 <19 108+/-5 SA-WWA-3E1 7/27/2009 51+/-22 174+/-6 SA-WWA-3E1 (1) 8/31/2009 <46 <7.8 SA-WWA-3E1 9/28/2009 33+/-14 36+/-4 SA-WWA-3E1 10/26/2009 54+/-14 39+/-4 SA-WWA-3E1 11/30/2009 <24 128+/-6 SA-WWA-3E1 12/29/2009 <15 128+/-6 AVERAGE 113+/-111

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18.

- Management Audit Samples: not required by ODCM.

(1) Results for August gamma sample by AREVA-NP Environmental Laboratory.

74

TABLE C-8 2009 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS AND TRITIUM IN RAW AND TREATED POTABLE WATER (2F3)*

Results in Units of pCi/L +/- 2 sigma SAMPLING GROSS GROSS TYPE PERIOD ALPHA BETA TRITIUM RAW 1/1-31/2009 0.5+/-0.3 3.1+/-0.6 <141 TREATED 1/1-31/2009 <0.3 2.6+/-0.6 <141 RAW 2/1-28/2009 <0.4 2.3+/-0.5 <134 TREATED 2/1-28/2009 <0.4 2.7+/-0.6 <139 RAW 3/1-31/2009 <0.3 2.4+/-0.5 <136 TREATED 3/1-31/2009 <0.3 2.3+/-0.5 <135 RAW 4/1-30/2009 <0.6 3.9+/-0.9 <133 TREATED 4/1-30/2009 <0.8 4.7+/-1 <134 RAW 5/1-31/2009 <0.5 5.6+/-0.9 <139 TREATED 5/1-31/2009 <0.7 4.9+/-0.9 <135 RAW 6/1-30/2009 <0.5 3.1+/-0.6 <132 TREATED 6/1-30/2009 <0.5 4.4+/-1 <126 RAW 7/1-31/2009 <0.4 3.2+/-0.8 <137 TREATED 7/1-31/2009 <0.4 3.3+/-0.8 <133 RAW 8/1-31/2009 <0.4 3.2+/-0.6 <135 TREATED 8/1-31/2009 <0.4 2.7+/-0.6 <133 RAW 9/1-30/2009 <0.3 3.1+/-0.5 <135 TREATED 9/1-30/2009 <0.5 4+/-0.7 <135 RAW 10/1-31/2009 <0.3 2.3+/-0.5 <145 TREATED 10/1-31/2009 <0.3 2.2+/-0.5 <142 RAW 11/1-30/2009 0.7+/-0.4 3.3+/-0.6 <125 TREATED 11/1-30/2009 <0.6 3.6+/-0.6 <125 RAW 12/1-31/2009 <0.4 2.6+/-0.5 <140 TREATED 12/1-31/2009 <0.4 2.6+/-0.5 <143 AVERAGE RAW - 3.2+/-1.8 -

TREATED - 3.3+/-1.9 GRAND AVERAGE 3.3+/-1.8

Managemnent Audit Sample: not required by ODCM.

75

TABLE C-9 2009 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

IN RAW AND TREATED POTABLE WATER (2F3)***

Results in Units of pCi/L +/- 2 sigma SAMPLING < -....--GAMMA EMITTERS ----.-- >

TYPE PERIOD 1-131 K-40 RA-NAT Th-232 RAW 1/1-31/2009 <0.3 <16 <2 <5.3 TREATED 1/1-31/2009 <0.2 <13 4.8+/-2 <4.6 RAW 2/1-28/2009 <0.3 <16 <1.9 <4.4 TREATED 2/1-28/2009 <0.3 <19 <1.8 <4.2 RAW 3/1-31/2009 <0.1 40+/-18 <3 <7.4 TREATED 3/1-31/2009 <0.3 <9.6 <1.6 <11 RAW 4/1-30/2009 <0.2 <17 <2 <3.9 TREATED 4/1-30/2009 <0.3 <26 8.6+/-2 <1.6 RAW 5/1-31/2009 <0.2 43+/-14 <2.2 <4.5 TREATED 5/1-31/2009 <0.2 48+/-17 24+/-3 <4.4 RAW 6/1-30/2009 <0.3 <39 <1.7 12+/-5 TREATED 6/1-30/2009 <0.1 62+/-18 7.4+/-1 <13 RAW 7/1-31/2009 <0.3 <16 <2.2 <4.4 TREATED 7/1-31/2009 <0.3 <36 14+/-2 <10 RAW (1) 8/1-31/2009 <1 <51 <9.2 <16 TREATED (1) 8/1-31/2009 <0.9 <30 <5 <8.4 RAW 9/1-30/2009 <0.2 34+/-11 <2 <11 TREATED 9/1-30/2009 <0.2 45+/-12 20+/-2 <11 RAW 10/1-31/2009 <0.4 <16 <2.4 <4.3 TREATED 10/1-31/2009 <0.1 <23 <2.3 <4.5 RAW 11/1-30/2009 <0.2 <16 <2.3 <4.3 TREATED 11/1-30/2009 <0.3 <18 88+/-3 <4.2 RAW 12/1-31/2009 <0.3 72+/-18 <2.4 <4.3 TREATED 12/1-31/2009 <0.4 33+/-12 <2.4 <4.3 AVERAGES RAW TREATED GRAND AVERAGE

Iodine-131 analyzed to an LLD of 1.0 pCi/L.

- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18 Management Audit Sample: not required by ODCM.

(1) Results for August sample by AREVA-NP Environmental Laboratory.

76

TABLE C-10 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES**

Results in Units of pCi/kg (Wet) +/- 2 sigma SAMPLING <--.... GAMMA EMITTERS -....... >

STATION ID DATE SAMPLE TYPE K-40 RA-NAT Be-7 SA-FPV-2F9 5/16/2009 Asparagus 1820+/-153 <11 <23 SA-FPV-3F6 (C) 5/16/2009 Asparagus 1580+/-135 <9.1 <22 SA-FPL-2G2 (C) 5/16/2009 Asparagus 1720+/-141 <9.4 <30 AVERAGE 1710+/-240 - -

SA-FPL-2F9 6/19/2009 Cabbage 2160+/-153 <5 <54 SA-FPL-3H5 (C) 6/28/2009 Cabbage 2820+/-188 <8 .<42 SA-FPL-3F6 7/6/2009 Cabbage 2010+/-163 <7.5 <36 SA-FPL-3F7 7/28/2009 Cabbage 2370+/-164 <6.3 <38 SA-FPL-9G2 7/28/2009 Cabbage 2520+/-177 <7.1 <31 SA-FPL-1S1 9/28/2009 Cabbage 2440+/-120 <4.9 157+/-37 SA-FPL-16S1 9/28/2009 Cabbage 3110+/-116 <4.8 183+/-27 AVERAGE 2490+/-750 - -

SA-FPL-1 S1 9/28/2009 Kale 4570+/-191 <7,4 353+/-54 SA-FPL-16S1 9/28/2009 Kale 4810+/-158 <6.1 414+/-37 AVERAGE 4690+/-340 - 384+/-86 SA-FPV-3H5 (C) 6/28/2009 Corn 2470+/-170 <6.7 <58 SA-FPV-2F9 7/2/2009 Corn 2160+/-164 <6:8 <31 SA-FPV-2G2 (C) 7/17/2009 Corn 2210+/-150 <7.2 <29 SA-FPV-2F10 7/28/2009 Corn 2530+/-170 <8.4 <29 SA-FPV-9G2 (C) 7/28/2009 Corn 2030+/-145 <23 <27 SA-FPV-1G1 (C) 7/28/2009 Corn 1990+/-133 12+/-6 <19 AVERAGE 2230+/-450 - -

SA-FPV-2F9 7/2/2009 Peppers 1340+/-137 <10 <25 SA-FPV-2G2 (C) 7/17/2009 Peppers 1400+/-146 <12 <35 SA-FPV-3F7 7/28/2009 Peppers 1510+/-136 <8.5 <29 SA-FPV-9G2 (C) 7/28/2009 Peppers 1370+/-139 18+/-6 <29 SA-FPV-2F10 7/28/2009 Peppers 1610+/-162 <13 <32 SA-FPV-1G1 (C) 7/28/2009 Peppers 1090+/-129 <13 <29 AVERAGE 1390+/-350 -

SA-FPV-3H5 (C) 6/28/2009 Tomatoes 1460+/-129 <6.4 <26 SA-FPV-9G2 (C) 6/28/2009 Tomatoes 1920+/-139 <11 <20 SA-FPV-2F9 7/2/2009 Tomatoes 2520+/-185 <8.4 <32 SA-FPV-2G2 (C) 7/17/2009 Tomatoes 2000+/-154 <6.7 <14 SA-FPV-2F10 7/28/2009 Tomatoes 2340+/-150 <10 .<25 SA-FPV-3F7 7/28/2009 Tomatoes 2030+/-146 <12 <21 SA-FPV-9G2 (C) 7/28/2009 Tomatoes 1630+/-134 <6.6 <26 SA-FPV-1G1 (C) 7/28/2009 Tomatoes 1700+/-129 <7.6 <42 SA-FPV-3F6 7/28/2009 Tomatoes 1830+/-128 <16 <22 AVERAGE 1940+/-670 - -

GRAND AVERAGE 2150+/-1600

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18.

Management Audit Sample:. not required by ODCM.

(C) Control Station (1) On site cabbage and.kale grown from seeds and planted by MTS Personnel.

77

TABLE C-11 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS **

Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <---GAMMA EMITTERS ---- >

STATION ID DATE SAMPLE TYPE Be-7 K-40 SA-VGT-1S1 12/29/2009 Ornamental Cabbage 256+/-42 3200+/-249 SA-VGT-10 D1 12/29/2009 Ornamental Cabbage 482+/-56 3630+/-170 SA-VGT-15S1 12/29/2009 Ornamental Cabbage 342+/-56 3780+/-183 SA-VGT-16S1 12/29/2009 Ornamental Cabbage 160+/-26 2380+/-107 AVERAGE 310+/-270 3250+/-1260 SA-VGT-2G3 10/12/2009 Silage 732+/-68 3460+/-175 SA-VGT-3G1 (C) 10/12/2009 Silage 1310+/-103 5130+/-241 SA-VGT-13E3 10/12/2009 Silage 422+/-51 2480+/-130 SA-VGT-14F4 10/12/2009 Silage 477+/-50 3260+/-146 AVERAGE 740+/-810 3580+/-2230 SA-VGT-14F4 11/20/2009 Soybeans <88 14800+/-268 SA-VGT-3G1 (C) 11/18/2009 Soybeans <95 13300+/-257 AVERAGE 14050+/-2121 GRAND AVERAGE 440+/-730 5130+/-13300

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18.

- Management Audit Sample: not required by ODCM.

(C) Control Station 78

TABLE C-12 2009 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING SA-SWA-11A1 SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1 F2 SA-SWA-7E1 AVERAGE DATE (Control)

January 38+/-9 16+/-7 <11 <11 65+/-10 27+/-50 February 106+/-12 69+/-10 52+/-9 40+/-8 99+/-12 73+/-58 March 73+/-12 55+/-10 50+/-10 36+/-9 95+/-13 62+/-45 April 20+/-7 20+/-7 15+/-7 11+/-6 47+/-8 23+/-28 May 59+/-12 58+/-12 37+/-11 25+/-11 123+/-16 60+/-76 June 76+/-13 48+/-11 35+/-11 23+/-10 123+/-15 61+/-80

-4 July 119+/-15 67+/-12 51+/-12 37+/-11 174+/-18 90+/-113 August 33+/-7 19+/-7 <10 <10 71+/-9 28+/-52 September 166+/-19 127+/-15 50+/-9 32+/-8 384+/-34 152+/-282 October 89+/-10 69+/-9 46+/-8 36+/-7 215+/-19 91+/-145 November 102+/-11 53+/-8 31+/-6 21+/-6 200+/-17 81+/-147 December 25+/-6 31+/-6 27+/-6 9+/-5 71+/-8 32+/-46 AVERAGE 75+/-87 53+/-61 34+/-34 24+/-25 139+/-189 GRAND AVERAGE 65+/-126

TABLE C-13 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING <---GAMMA EMITTERS ---------- >

STATION ID DATE K-40 RA-NAT Th-232 SA-SWA-1 F2 1/5/2009 50+/-13 <1.8 <4 SA-SWA-7E1 1/5/2009 90+/-18 <1.8 <4 SA-SWA-11A1 1/5/2009 80+/-20 <4.5 <4.4 SA-SWA-12C1(C) 1/5/2009 62+/-13 <2.2 <5 SA-SWA-16F1 1/5/2009 53+/-19 <2.4 <4.7 SA-SWA-1 F2 2/6/2009 85+/-14 <2.1 <4.4 SA-SWA-7E1 2/6/2009 103+/-19 5+/-2 <3.7 SA-SWA-11A1 2/6/2009 126+/-22 <2.1 <5.1 SA-SWA-12C1 (C) 2/6/2009 96+/-17 <1.8 <4.4 SA-SWA-16F1 2/6/2009 94+/-19 <1.5 <3.7 SA-SWA-1 F2 3/5/2009 71+/-14 <1.6 <4.3 SA-SWA-7E1 3/5/2009 142+/-22 <1.6 <6.8 SA-SWA-11A1 3/5/2009 122+/-20 <2 <4.5 SA-SWA-12C1(C) 3/5/2009 61+/-16 <1.8 <4.5 SA-SWA-16F1 3/5/2009 97+/-21 5.6+/-1 <7.4 SA-SWA-1 F2 4/9/2009 48+/-14 <1.6 <4.4 SA-SWA-7E1 4/9/2009 101+/-21 6.3+/-1 <9.2 SA-SWA-11A1 4/912009 62+/-15 <1.5 13+/-4 SA-SWA-12C1(C) 4/9/2009 59+/-14 <2.4 <4.8 SA-SWA-16F1 4/9/2009. 67+/-15 <2.5 <4.7 SA-SWA-1 F2 5/4/2009 60+/-20 <1.8 <11 SA-SWA-7E1 5/4/2009 89+/-21 <1.7 <4.5 SA-SWA-11A1 5/4/2009 93+/-21 6.8+/-1 <8.9 SA-SWA-12C1(C) 5/4/2009 51+/-15 <2.4 <4.6 SA-SWA-16F1 5/4/2009 42+/-17 <2.4 <4.5 SA-SWA-1 F2 6/1/2009 56+/-16 <1.8 <4.2 SA-SWA-7E1 6/1/2009 72+/-19 <2.2 <5.7 SA-SWA-11A1 6/1/2009 95+/-17 <2.6 <4.1 SA-SWA-12C1(C) 6/1/2009 71+/-16 <1.7 <11 SA-SWA-16F1 6/1/2009 55+/-14 <1.7 <4.1 SA-SWA-1 F2 7/9/2009 <23 <1.8 <4.8 SA-SWA-7E1 7/9/2009 127+/-17 <1.6 <2.8 SA-SWA-11A1 7/9/2009 100+/-21 5.9+/-1 <9 SA-SWA-12C1(C) 7/9/2009 81+/-14 <2.6 <4.2 SA-SWA-16F1 7/9/2009 73+/-17 <2.6 <4 80

TABLE C-13 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING' <----GAMMA EMITTERS -----

STATION ID DATE K-40 RA-NAT Th-232 SA-SWA-1 F2 8/6/2009 57+/-14 <3.5 <3.9 SA-SWA-7E1 8/6/2009 112+/-20 <2.5 <4.3 SA-SWA-11A1 8/6/2009 82+/-16 <1.7 <8.8 SA-SWA-12C1(C) 8/6/2009 58+/-16 7+/-2 <8.3 SA-SWA-16F1 8/6/2009 72+/-17 <1.7 <4.7 SA-SWA-1 F2 9/8/2009 75+/-16 <1.8 <4.5 SA-.SWA-7E1 9/8/2009 147+/-22 <1.8 <5.1 SA-SWA-11A1 9/8/2009 144+/-22 6.7+/-2 <8.9 SA-SWA-12C1 (C) 9/8/2009 117+/-16 <2.3 <4.5 SA-SWA-16F1 9/812009 81+/-13 <2.7 <4.5 SA-SWA-1 F2 10/9/2009 57+/-13 <2.6 <4.5 SA-SWA-7E1 10/9/2009 127+/-21 6.3+/-2 10+/-4 SA-SWA- 11A1 10/9/2009 63+/-18 <2.3 <4.4 SA-SWA-12C1(C) 10/9/2009 58+/-17 <2.6 <4.6 SA-SWA-16F1 10/9/2009 35+/-15 <2.3 <4.7 SA-SWA-1 F2 11/2/2009 63+/-13 <2.3 <4.6 SA-SWA-7E1 11/2/2009 137+/-20 <1.6 <2.1 SA-SWA-11A1 11/2/2009 77+/-18 <2.7 <4.1 SA-SWA-12C1 (C) 11/2/2009 74+/-15 <2.7 <4.4 SA-SWA-16F1 11/2/2009 69+/-16 <2.6 <4.9 SA-SWA-1 F2 12/8/2009 72+/-18 11+/-3 <4.9 SA-SWA-7E1 12/8/2009 62+/-18 <2.3 <4.6 SA-SWA-11A1 12/8/2009 55+/-15 6.9+/-2 <3.9 SA-SWA-12C1 (C) 12/8/2009 58+/-21 <1.6" <3.3 SA-SWA-16F1 12/8/2009 34+/-17 <1.6 <4.9 AVERAGE 79+/-58

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-18 (C) Control Station 81

TABLE C-14 2009 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

<- ------ STATION ID ,>

SAMPLING SA-SWA-11A1 SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1F2 SA-SWA-7E1 AVERAGE PERIOD (Control)

January <142 <142 <141 <142 <142 February <155 <143 <152 <156 <147 March <136 <143 <142 <143 <140 April <157 <135 <146 <151 340+/-97 00 May <133 <133 <132 <132 <132 June 168+/-92 <143 <144 <147 <144 July <143 <144 <142 <141 <141 August <143 <143 <140 <141 <145 September <133 <140 <132 <132 <133 October 154+/-93 <135 <134 <136 322+/-93 November <141 <142 <145 <140 <142 December <134 <134 <134 <137 <138

TABLE C-15 2009 CONCENTRATIONS OF GAMMA EMITTERS** IN EDIBLE FISH Results in Units of pCi/kg (wet) +/- 2 sigma

<--- GAMMA EMITTERS ---- >

(FLESH)

SAMPLING STATION ID PERIOD K-40 RA-NAT SA-ESF-7E1 7/28/2009 3230+/-180 <5.9 SA-ESF-11A1. 7/8-30/2009 3390+/-170 <8.1 SA-ESF-12C1 (C) 7/8-14/2009 2980+/-190 <6 AVERAGE 3200+/-410 SA-ESF-7E1 10/22-26/2009 3240+/-170 <14 SA-ESF-1 1A1 10/22-26/2009 3430+/-180 <8.6 SA-ESF-12C1 (C) 10/22-26/2009 3350+/-180 12+/-5 AVERAGE 3340+/-190 GRAND AVERAGE 3270+/-330

- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 8 (C) Control Station 83

TABLE C-16 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN CRABS Results in Units of pCi/kg (wet) +1-2 sigma

<--- GAMMA EMITTERS -- >

SAMPLING (FLESH)

STATION ID PERIOD K-40 RANAT 1430+/-130 21+/-7 SA-ECH-11A1 7/7-7/15/2009 SA-ECH-12C1 (C) 7/7-7/15/2009 2300+/-160 18+/-6 AVERAGE 1870+/-1230 20+/-4 SA-ECH-11A1 (1) 8/24-8/28/09 1560+/-640 <19 SA-ECH-12C1 (C) (1) 8/24-8/28/09 1770+/-730 <21 AVERAGE 1670+/-300 -

GRAND AVERAGE 1770+/-770

All other gamma emitters searched for were <LLD; Typical LLDs are given in Table C-18.

(C) Control Station (1) Second semi-annual collection: 8/24-8/28/09 gamma samples analyzed by AREVA 84

TABLE C-17 2009 CONCENTRATIONS OF GAMMA EMITTERS* IN SEDIMENT Results in Units of pCi/kg (dry) +/- 2 sigma SAMPLING STATION ID DATE Be-7 K-40 Co-60 Cs-137 Mn-54 RA-NAT Th-232 SA-ESS-6S2 6/30/2009 <59 ,1460+/-113 <4.1 <2.7 <3.1 73+/-7 88+/-20 SA-ESS-7E1 6/25/2009. <129 11100+/-306 <13 <15 <13 652+/-21 838+/-43 SA-ESS-11A1 6/25/2009 <74 7060+/-287 <6. <11 <14 346+/-14 545+/-44 SA-ESS-15A1 6/25/2009 <76 3710+/-185 <6.1 <7 <10 233+/-11 360+/-34 SA-ESS-16A1 6/25/2009 <111 8150+/-259 <20 <6.3 27+/-10 826+/-29 1110+/-48 SA-ESS-12C1 (C) 6/25/2009 <103 15000+/-377 <9.1 <8.8 <8.1 563+/-20 1000+/-56 SA-ESS-16F1 6/25/2009 <81 16500+/-462 <11 52+/-14 <6.1 583+/-22 1090+/-63 AVERAGE 9000+/-11130 - 468+/-523 719+/-792 SA-ESS-6S2 11/5/2009 135+/-42 1290+/-97 <2.3 <3.3 <11 86+/-9 81+/-16 SA-ESS-7E1 10/28/2009 <77 9330+/-285 <6.4 <8.5 <16 673+/-20 744+/-48 SA-ESS-11A1- 10/28/2009 <80 13900+/-393 <5.5 63+/-10 <25 643+/-23 1070+/-59 SA-ESS-1 5A1 10/28/2009 <98 3580+/-167 <6.1 <4.8 <4.1 285+/-12 385+/-31 SA-ESS-16A1 10/28/2009 <68 4340+/-221 <15 .<4.7 <5.8 418+/-28 610+/-63 SA-ESS-12C1 (C) 10/28/2009 <78 13500+/-373 <21 <7.1 <11 537+/-19 1050+/-71 SA-ESS-16F1 10/28/2009 <55 4160+/-187 <5.8 <5.2 <4.6 289+/-12 413+/-42 AVERAGE - 7160+/-10150 - 419+/-428 622+/-726 GRAND AVERAGE - 8080+/-10410 - 443+/-462 670+/-740

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 8 (C) Control Station 85-

TABLE C-18 2009 MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROSCOPY SAMPLE TYPE: < ------------ AIR ---------------> WATER-------------

<------------ > MILK---------------

IODINE PARTICULATES GAMMA SCAN IODINE GAMMA SCAN IODINE ACTIVITY: 10-3 pCi/m3 10-3 pCi/m3 pCi/L pCi/L pCi/L pCi/L.

GEOMETRY: 47 ML 13 FILTERS 3.5 LITERS 100 ML 3.5 LITERS 100 ML COUNT TIME: 120 MINS 500 MINS 1000 MINS 1000 MINS 500 MINS 1000 MINS DELAY TO COUNT: 2 DAYS 5 DAYS 7 DAYS 3 DAYS 2 DAYS 2 DAYS NUCLIDES BE-7 2 12 21 NA-22 0.5 2.7 5.7 K-40 9 34 34 CR-51 3.1 19 19 MN-54 0.44 1.5 3.9 CO&58 0.4 2.2 4.2 FE-59 0.75 5.5 9.7 CO-60 0.44 3.4 5.7 ZN-65 0.55 4.5 14 ZRNB-95 0.6 3.7 6.9 MO-99 88 77 76 RU-103 0.23 1 2.6 RU-106 1.9 20 35 AG- IOM 0.33 2 4.6 SB-125 0.56 3.3 6.5 TE-129M 11 57 103 1-131 9.9 0.8 4.2 0.39 2.7 0.34 TE-132 3.5 3.6 6.2 BA-133 0.26 2.0 2.2 CS-134 0.33 1.7 2 CS- 136 0.54 1.4 3.6 CS-137 0.35 1.6 3.7 BALA-140 1.4 5.4 7.6 CE-141 0.26 2.4 2.8 CE- 144 0.97 7.7 12 RA-NAT 0.71 3.6 5.5 TH-232 1.8 11 17 86

TABLE C-18 (Cont'd) 2009 MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROSCOPY SAMPLE TYPE: FOOD PRODUCTS VEGETATION FISH & CRAB SEDIMENT GAMMA SCAN GAMMA SCAN GAMMA SCAN GAMMA SCAN ACTIVITY: pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg DRY GEOMETRY: 500 mi 3.5 LITER' 500 ml 500 ml COUNT TIME: 500 MINS 500 MINS 500 MINS 500 MINS DELAY TO COUNT: 3 DAYS 7 DAYS 5 DAYS 30 DAYS NUCLIDES BE-7 55 75 47 135 NA-22 10 7.1 8.2 26 K-40 70 32 55 55 CR-51 44 40 37 186 MN-54 9.4 4.4 5.2 27 CO-58 6.4 5.1 9.1 7.8 FE-59 13 10 17 39 CO-60 13 9.7 11 21 ZN-65 21 20 1o 27 ZRNB-95 10 6.4 12 33 MO-99 206 318 418 133000 RU- 103 3.8 6.4 4.2 11 RU- 106 56 58 45 69 AG-110M 11 6.6 8.9 21 SB-125 12 10 8.9 30 TE-129M 262 144 168 459 1-131 11 9.6 36 120 TE- 132 62 28 88 5620 BA-133 7.9 5.4 3.8 9.2 CS-134 8.7 5 3.6 7.4 CS-136 12 7.7 25 46 CS-137 14 18 9.4 15 BALA- 140 31 30 50 135 CE-141 8.9 15 6.8 30 CE- 144 22 19 17 41 RA-NAT 22 13 14 5 TH-232 51 29 39 8.1 87

TABLE C-19 2009 MAPLEWOOD TESTING SERVICES LLDs FOR GROSS ALPHA, GROSS BETA AND TRITIUM IN AIR AND WATER SAMPLE TYPE: AIR PARTICULATES WELL/POTABLE WATERS SURFACE WATERS ACTIVITY: pCi/m 3 pCi/L pCi/L Gross Alpha 1.1 Gross Beta (1) 1.4 II Tritium 145 156 (1) There were no air particulate gross beta results that were below LLD. All results were positive.

(2) The Salem/Hope Creek ODCM LLD value is for drinking water. MTS has set a value of 10 pCi/L for surface water LLDs to meet.

88

APPENDIX D

SUMMARY

OF RESULTS FROM ANALYTICS, ENVIRONMENTAL RESOURCE ASSOCIATES, AND AREVA E- LAB INTERLABORATORY COMPARISON PROGRAMS 89

THIS PAGE INTENTIONALLY LEFT BLANK APPENDIX D

SUMMARY

OF RESULTS FOR ANALYTICS, ENVIRONMENTAL RESOURCE ASSOCIATES, AND AREVA E-LAB INTERLABORATORY COMPARISON PROGRAM Appendix D presents a summary of the analytical results for the 2009 Analytics and Environmental Resource Associates (ERA) Interlaboratory Comparison Program plus the TLD QA Data for AREVA E-LAB.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE D-1 Analytics Results: Gross Alpha/Beta in Water, Gross Beta 92 in Air Particulate filters, Iodine in Air Samples, and Tritium in Water Samples D-2 Analytics Results: Gamma Emitters in Water and Milk 93 Samples D-3 Analytics Results: Gamma Emitters in Air Particulate and 94 Soil Samples D-4 ERA Results: Gamma Emitters in Water, Gross Alpha/Beta 95 in Water, Tritium Analysis in Water, and Iodine Analysis in Water Samples D-5 Percentage of Individual TLD Results That Met AREVA- E- 96 Lab Tolerance Limits D-6 Third Party TLD Testing Performance Results 96 91

TABLE D-1 RESULTS FOR ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM Gross Alpha and Gross Beta Emitters In Water (pCi/L), Iodine In Air Samples (pCi/m 3 ),

Gross Beta In Air Particulate Filter (pCi/m 3 ), And Tritium Analysis In Water (pCi/L)

MTS MTS Ratio Date Sample Sample Reported Known MTS/

MM-YY Code Media Nuclide Value Value Resolution Analytics Evaluation 03-2009 B711 APT Beta 81 75 60 1.09 Acceptable 03-2009 H712 WAT H-3 4422 4480 60 0.99 Acceptable 03-2009 1715 A1O 1-131 77 79 60 0.97 Acceptable 06-2009 B719 APT Beta 81.7 87 60 0.94 Acceptable 06-2009 AB720 WAT Alpha 287.6 281 60 1.02 Acceptable Beta 206.1 141 60 1.46 Disagree 06-2009 1721 AIO 1-131 94.6' 95 60 0.99 Acceptable 06-2009 W723 WAT H-3 13174 13300 60 0.99 Acceptable 09-2009 1726 AIO 1-131 92.9 91.6 60 1.02 Acceptable 09-2009 H728 WAT H-3 13799 14100 60 0.98 Acceptable 09-2009 AB729' WAT Alpha 349 324 60 1.08 Acceptable Beta 340 287 60 1.18 Acceptable 01-2010 AB734 WAT Alpha 279 258 60 1.08 Acceptable Beta 284 230 60 1.24 Acceptable 01-2010 1735 A1O 1-131 92 93 60 0.99 Acceptable 01-2010 H733 WAT H73 13514 14200 60 0.95 Acceptable 01-2010 B737 APT Beta 108 97 60 1.12 Acceptable 92

TABLE D-2 RESULTS FOR ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM Gamma Emitters in Water And Milk (pCi/L)

MTS MTS Ratio Date Sample Sample Reported Known MTS/

MM-YY Code Media Nuclide Value Value Resolution Analytics Evaluation 03-2009 G713 WAT Cr-51 388 387 60 1.00 Acceptable Mn-54 170 162 60 1.05 Acceptable Co-58 154 151 60 1.02 Acceptable Fe-59 136 127 60 1.07 Acceptable Co-60 169 180 60 1.05 Acceptable Zn-65 211 197 60 1.07 Acceptable 1-131 69 69 60 1.01 Acceptable Cs-134 112 119 60 0.94 Acceptable Cs-137 149 141 60 1.06 Acceptable Ce-141 123 120 60 1.02 Acceptable 03-2009 G716 MILK Cr-51 306 305 60 1.00 Acceptable Mn-54 131 125 60 1.02 Acceptable Co-58 118 119 60 .0.99 Acceptable Fe-59 107 *100 60 1.07 Acceptable Co-60 148 142 60 1.04 Acceptable Zn-65 161 156 60 1.03 Acceptable 1-131 80 79 60 1.01 Acceptable Cs-1 34 88 94 60 0.94 Acceptable Cs-137 113 111 60 1.02 Acceptable Ce-1 41 92 95 60 0.96 Acceptable 01-2010 G736 WAT Cr-51 253 244 60 1.04 Acceptable Mn-54 206 197 60 1.04 Acceptable Co-58 176 173 60 1.02 Acceptable Fe-59 127 115 60 1.10 Acceptable Co-60 308 305 60 1.01 Acceptable Zn-65 380 373 60 1.02 Acceptable 1-131 101 103 60 0.98 Acceptable Cs-1 34 282 295 60 0.95 Acceptable Cs-137 227 216 60 1.05 Acceptable Ce-141 105 104 60 1.01 Acceptable 93

TABLE D-3 RESULTS FOR ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM Gamma Emitters in Soil (pCi/g-dry) And Air Particulate Samples (pCi/m )

MTS MTS Ratio Date Sample Sample Reported Known MTS/

MM-YY Code Media Nuclide Value Value Resolution Analytics Evaluation 03-2009 G714 Soil Cr-51 0.528 0.517 60 1.02 Acceptable Mn-54 0.232 0.216 60 1.08 Acceptable Co-58 0.206 0.202 60 1.02 Acceptable Fe-59 0.189 0.169 60 1.12 Acceptable C6-60 0.254 0.241 60 1.05 Acceptable Zn-65 0.275 0.264 60 1.04 Acceptable Cs-134 0.141 0.159 60 0.89 Acceptable Cs-137 0.294 0.283 60 1.04 Acceptable Ce-141 0.166 0.161 60 1.03 Acceptable 06-2009 G722 APT Cr-51 272 269 60 1.01 Acceptable Mn-54 95 92 60 1.03 Acceptable Co-58 62 62 60 1.01 Acceptable Fe-59 92 82 60 1.12 Acceptable Co-60 205 210 60 0.97 Acceptable Zn-65 130 118 60 1.10 Acceptable Cs-134 89 111 60 0.8 Acceptable Cs-137 130 129 60 1.01 Acceptable Ce-141 185 191 60 0.97 Acceptable 09-2009 . G727 SOIL Cr-51 0.513 0.518 60 0.99 Acceptable Mn-54 0.502 0.483 60 1.04 Acceptable Co-58 0.236 0.233 60 1.01 Acceptable Fe-59 0.367 0.345 60 1.06 Acceptable Co-60 0.376 0.375 60 1.00 Acceptable Zn-65 0.511 0.477 60 1.07 Acceptable Cs-1 34 0.268 0.288 60 0.93 Acceptable Cs-137 0.540 0.526 60 1.03 Acceptable Ce-141 0.629 0.644 60 0.98 Acceptable 94

TABLE D-4 RESULTS FOR ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) PROFICIENCY TESTING PROGRAM Gamma Emitters in Water (pCi/L), Gross Alpha and Beta in Water (pCi/L), Iodine-131 Analysis in Water.(pCi/L), and Tritium in Water (pCi/L),

MTS MTS ERA Date Sample Sample Reported Assigned Acceptance MM-YY Code Media Nuclide Value Value Limits Evaluation 01-2009 AB710 WAT Alpha 14.9 52.3 27.3-65.5 Disagree Beta 43.7 46.1 31.0-53.3 Acceptable 04-2009 H718 WAT H-3 19510 20300 17800 -22300 Acceptable 04-2009 1717 WAT 1-131 28.8 26.1 21.7-30.8 Acceptable 07-2009 G725 WAT Ba-1 33 70.1 70.2 58.6-77.2 Acceptable Co-60 101.1 101 90.9-113.0 Acceptable Cs-1 34 86.4 88.7 72.8-97.6 Acceptable Cs-137 92.3 88.4 79.6-99.8 Acceptable Zn-65 101.6 77.7 69.8-93.6 Disagree 7-2009 AB724 WAT Alpha 34.5 55.3 28.9 -69.0 Acceptable Beta 62.6 64.7 44.8-71.3 Acceptable 10-2009 AB731 WAT Alpha 12.8 23.2 11.6-31.1 Acceptable Beta 26.0 26.0 16.2 - 33.9 Acceptable 10-2009 1730 WAT 1-131 23.2 22.2 18.4-26.5 Acceptable 10-2009 H732 WAT H-3 16369.0 16400 14300- 18000 Acceptable 95

TABLE D-5 PERCENTAGE OF INDIVIDUAL TLD RESULTS THAT MET AREVA E-LAB TOLERANCE LIMITS Dosimeter Type Number % Passed Bias % Passed Precision Tested Criteria Criteria Panasonic Environmental TLDs 84 100 100 (1) This table summarizes results of tests conducted by E-LAB and the Third-party tester.

(2) Environmental Dosimeter results are free in air.

TABLE D-6 THIRD PARTY TLD TESTING PERFORMANCE RESULTS (1) Performance criteria are the same as the internal criteria.'

(2) Results are expressed as the delivered exposure for environmental TLD. ANSI HPS N13.29-1995 (Draft)

Category II, High Energy photons (Cs-1 37 or Co-60) 96

APPENDIX E SYNOPSIS OF LAND USE CENSUS 97

THIS PAGE INTENTIONALLY LEFT BLANK APPENDIX E SYNOPSIS OF 2009 LAND USE CENSUS A land use census was conducted in each of the 16 meteorological sectors to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50m 2 (500ft2) producing broad leaf vegetation. In accordance with Salem and Hope Creek ODCMs the census was performed using a door to door survey, visual survey and by consulting with local agriculture authorities.

Milk Nearest Vegetable Animal Residence Garden Meteorological Oct, 2009 Oct, 2009 Oct, 2009 Sector Km (miles) Km (miles) Km (miles)

N None None None NNE None None None NE None 6.2 (3.9) None ENE None 6.2(3.9) None E None None None ESE None None None SE None None None SSE None None None S None None None SSW None 6.2 (3.9) None SW None 6.9 (4.3) 7.3(4.6)

WSW None 7.1 (4.4) 7.1 (4.4)

W 7.8 (4.9) 6.5 (4.0) None WNW None 5.5(3.4) None NW None 5.9 (3.7) None NNW None 6.8 (4.2) None The 2009 Land Use Census results are summarized in the above table. A comparison of the identified locations from the 2009 table with the 2008 table shows that no new nearest milk animal, nearest resident, or nearest vegetable garden (500 Ft 2) with broadleaf vegetation were identified. Therefore, no formal dose evaluation or changes to the ODCMs are required.

99

APPENDIX F RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM (RGPP) 101

THIS PAGE INTENTIONALLY LEFT BLANK 2009 Radiological Groundwater Protection Program (RGPP)

Table of Contents I. INTRODUCTION 105 II. GROUNDWATER PATHWAYS 106 A. Objectives for the Radiological Ground water Protection Program 107 III. LONG-TERM GROUND WATER SAMPLING PROGRAM DESCRIPTION 107 A. Sample Collection 107 B. Sample-Analysis 108 C. Data Evaluation 109 IV. RESULTS AND DISCUSSION 112 A. Groundwater Results 113 B. Investigations 115 C. RGPP Status 118 D. Impacts to Groundwater: Past Spills and Leaks 119 V. REFERENCES 119 Tables 1 Hope Creek RGPP Monitoring.Wells: Construction Details 2 Salem RGPP Monitoring Wells: Construction Details 3 Relevant Groundwater Evaluation Criteria: Salem and Hope Creek Generating Stations 4A Analytical Results for Tritium in Groundwater: Hope Creek Generating Station 4B Analytical Results for Tritium in Groundwater: Salem Generating Station 5 Salem and Hope Creek 10CFR 50.75(g) Data Figures 1 Hope Creek RGPP Monitoring Well Locations 2 Salem RGPP Monitoring Well Locations 3 Hope Creek Tritium Trends: Wells BH, BI, BJ, BK, BM, BN, BQ 4 Salem Tritium Trends: Wells AL, BB, BD, BE, BG, T, U, Y, Z 103

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104

I. Introduction This is the annual report on the status of the Radiological Groundwater Protection Program (RGPP) conducted at Salem and Hope Creek Generating Stations. This report covers the RGPP groundwater samples collected from the PSEG site in 2009. This report also describes any changes to this program and provides the radiochemical analysis results for groundwater samples collected during the 2009 reporting year. The 2006 PSEG Annual Radiological Environmental Operating Report (AREOR) was the first report that provided a description of the RGPP (PSEG, 2007). Both the 2006, 2007 and 2008 AREORs contained information and detailed descriptions of the RGPP in Appendix F (PSEG 2007, 2008, 2009). This report contains the results of the 2009 long-term groundwater-sampling program.

The RGPP was initiated by PSEG in 2006 to determine whether groundwater at and in the vicinity of Salem and Hope Creek Stations had been adversely impacted by any releases of radionuclides related to nuclear station operations. The RGPP is a voluntary program implemented by PSEG in conjunction .with the nuclear industry initiatives and associated guidance (NEI, 2007). Although it is designed to be a separate program, the RGPP complements the existing Radiological Environmental Monitoring Program and Radioactive Effluent Technical Specification Program. The long-term groundwater-sampling program is one of the key elements of the RGPP that provides for early leak detection. The other key elements that comprise the RGPP and contribute to public safety are spill/leak prevention, effective remediation of spills and leaks, and effective stakeholder communication.

In 2002, operations personnel at Salem Generating Station identified a release of radioactive liquids from the Unit 1 Spent Fuel Pool to the environment. PSEG developed a Remedial Action Work Plan (RAWP). This RAWP was reviewed by the United States Regulatory Commission (USNRC) and approved by the New Jersey Department of Environmental Protection (NJDEP) Bureau of Nuclear Engineering (BNE). In 105

accordance with the RAWP, a Groundwater Recovery System (GRS) has been installed and is in operation to remove the groundwater containing tritium. This system was designed to reduce the migration of the tritium plume towards the plant boundary. The GRS is fully discussed in the quarterly Remedial Action Progress Reports (RAPR) provided to the state and the U.S. Nuclear Regulatory Commission by PSEG. The information and data associated with the GRS is not included in the annual RGPP reports.

It should be noted that five shared monitoring wells (Well IDs AL, T, U, Y and Z) are included in both the GRS monitoring and RGPP long-term sampling programs to ensure that the two programs are comprehensive.

II. Groundwater Pathways PSEG's Salem and Hope Creek Generating Stations are located in a flat, largely undeveloped region of southern New Jersey. The Sites are bordered on the west and south by the Delaware River Estuary and on the east and north by extensive marshlands.

Both of the sites obtain'cooling water from the Delaware River Estuary and discharge it back to this Estuary.

The two sites are underlain by over 1,000 feet of inter-layered sand, silt and clay.

The Salem and Hope Creek sites derive potable and sanitary water from deep wells in the Potomac-Raritan-Magothy (PRM) formations, greater than 600 feet below the surface.

There are no potable wells off-site within at least one mile. The nearest potable supply well is located 3.65 miles away in the state of Delaware. In the vicinity of the site there are no public water supply wells or private wells that can be impacted by radionuclides associated with nuclear station operations.

106

A. Objectives for the RGPP The long-term sampling program objectives are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment or potential drinking water sources can occur.

2. Understand the local hydro-geologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

3. Perform routine water sampling from strategic locations and evaluate radiochemical analysis results.

4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.

5. Regularly evaluate analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

III. Long-term Groundwater Sampling Program Description A. Sample Collection This section describes the general sampling methodologies used to collect water samples from monitoring wells for the Salem and Hope Creek Generating Stations RGPP. In 2006, the RGPP monitoring wells (Tables 1 and 2, Monitoring Well Construction Details) were installed and developed for both Salem and Hope Creek as part of the Site Investigation Report (ARCADIS, 2006A and 2006B). Groundwater samples are 107

collected from all new monitoring wells, as well as the five pre-existing wells located at Salem (AL, T, U, Y & Z). Test Engineers and Laboratory Technicians from PSEG Maplewood Testing Services (MTS) collect the groundwater samples. Sampling protocols are consistent with USEPA and NJDEP guidance; a modified low-flow sampling methodology is used. This methodology is consistent with protocols established for the Salem GRS investigation. In May 2006, after the Site Hydrological Investigation was completed the long-term groundwater-sampling program was initiated.

The program includes sampling all 26 wells at least semi-annually.

The Hope Creek RGPP monitoring wells are currently sampled semi-annually (BL, BT, BO, BP, BR and BS) and quarterly (BH, BI, BJ, BK, BM, BN and BQ). The Salem RGPP monitoring wells are currently sampled semi-annually (BA, BB, BC, BD, BE, BF, BG and BU), quarterly (AL, T and U) and monthly (Y and Z). The sampling frequencies that are specified in the RGPP procedures may be modified by the PSEG RGPP Manager for purposes of adaptive management of the RGPP. However, sampling and analysis shall not occur less frequently than semi annually.

B. Sample Analysis This section describes the general analytical methodologies used to analyze the water samples for radioactivity for the Salem and Hope Creek Generating Stations RGPP.

Groundwater samples were analyzed for plant-related gamma emitting radionuclides (semi-annually), tritium (every sample) and total strontium (annually) by a radiochemical analytical laboratory. In order to achieve the stated RGPP objectives, the long-term groundwater-sampling program includes the following measurements and analyses:

" Concentrations of gamma emitting radionuclides in water by gamma spectroscopy.

" Concentrations of tritium in water by filtration/distillation and liquid scintillation.

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Concentrations of strontium in water by chemical separation and liquid scintillation.

The tritium analysis results reported in Tables 4A and 4B were obtained from PSEG MTS laboratory located in Maplewood, NJ. The gamma spectroscopy and total Sr analysis results are obtained from Teledyne Brown Engineering (TBE) Laboratory located in Knoxville, TN. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs. The inter-laboratory cross-check program for.

the RGPP samples is conducted between the PSEG MTS laboratory and the TBE laboratory (tritium analysis only). Station personnel review and evaluate all analytical data deliverables obtained from these laboratories upon receipt (typically within 30 days after the water samples are received by the laboratory).

C. Data Evaluation This section describes the method used to evaluate the analytical results for RGPP samples obtained at the Salem and Hope Creek Generating Stations site. Analytical data results are reviewed for adverse trends or anomalous data. Investigations and notification are made as required by RGPP program procedures. The radiological data for groundwater collected during the preoperational phase of the stations were used as a baseline with which current operational data were compared. Several factors are important in the interpretation and evaluation of the radiological data:

1. Lower Limit-of Detection The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical method. The Lower Limit of Detection (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 109

observation represents a "real" signal.

The environmental LLD is specified for the detectibility of each isotope that may be produced by Salem or Hope Creek stations in the Offsite Dose Calculation Manual (ODCM). A fact of particular interest to the industry, state and public is the LLD of tritium of which the station ODCM LLD is 3000 pCi/L in water. The station procedure was modeled after the ODCMs for environmental LLDs, however, for the RGPP tritium analyses are performed with the lower LLD of 200 pCi/L.

For 2009, the RGPP analytical sensitivities for all analysis met or were below the LLDs specified by the station procedure for H-3, Mn-54, Co-60, Zn-65, Cs-134 and Cs-137 in water. During 2009 12 samples did not meet LLDs for Co-58 and Fe-59, nineteen samples did not meet the LLDs for La-l40 and Ba-140 and three samples did not meet LLDs for Zr-95, Nb-95 and Fe-55. The reason for the missed LLDs is attributed to extended delay between sampling and analysis which resulted in inaccurate counting statistics. The stations have taken actions to address this issue to ensure the time between sampling and analysis is minimal.

The station reviewed the extent of condition and identified that in the reporting years 2006, 2007 and 2008 the LLDs were not met for BA-140.and LA-140. In addition, the LLD was not achieved for Nb-95 for one sample in 2006. And the LLD was not achieved for Zr-95 for seven samples in 2006. The missed LLDs were procedural non-conformances for the stations and corrective actions are being implemented to prevent reoccurrence. There is no regulatory impact, as the radiological ground water protection program is a voluntary industry initiative.

2. Laboratory Measurements Uncertainty Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from the counting system measurement, calibration standards, sample volume or weight measurements, sampling uncertainty and other factors.

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Analytical uncertainties are reported at the 95% confidence level in this RGPP report to be consistent with the uncertainties reported in the AREOR for the REMP.

3. Groundwater Data Quality Analysis Groundwater samples generally consist of at least four aliquots. One of the groundwater sample aliquots is submitted to the respective station's onsite chemistry laboratory for tritium and gamma spectroscopy analysis. If these screening analyses indicated that tritium concentrations are below 10,000 pCi/L and no plant-related gamma emitters were present, then the samples are released for shipment to the offsite environmental laboratories. The on-site Chemistry laboratory's screening analysis for all 2009 RGPP groundwater samples were below 10,000 pCi/L for tritium and no plant-related gamma emitters were present above the associated LLDs specified in the ODCM.

The second sample aliquot is sent to the MTS Laboratory for tritium analysis. The third sample aliquot is submitted to the TBE Laboratory for tritium, gamma spectroscopy and total Strontium (Sr) analysis. During 2009, the tritium concentration results for those wells that had results above the minimum detectable concentrations were compared. The PSEG, MTS and TBE tritium results on split samples were found to have a relative percent difference within + 30%.

The fourth sample aliquot is held as a back-up sample until all the analytical results were received and determined to be valid. In the event that the results were believed to be questionableor sample results were lost, the back-up sample would be submitted for analysis. In addition, this back-up sample can be used to verify any elevated analytical result.

All radionuclide results are compared to the limitations within the RGPP:

Internal Administrative Control Limits are defined within the RGPP procedures, they are develop based on the historical baseline concentrations of tritium in each specific well and are used to identify tritium concentrations that warrant further I11"1

investigation for that specific well. Exceeding Administrative Control Limits does not initiate any external reporting.

" Courtesy Communication Control Limit is a tritium concentration established below regulatory requirements based on agreements with NJDEP-BNE and/or USNRC and other stakeholders, to ensure the stakeholders are cognizant. PSEG has verbally agreed to provide a courtesy communication by telephone no later than the end of the next business day to NJDEP-BNE for any confirmed tritium result that exceeds 3,000 pCi/L. The NRC Site Resident is also informed. This is not a required communication.

" Voluntary Communication Limits are those concentrations of radionuclides that require voluntary communication and reporting to regulators and/or stakeholders based on NEI 07-07 and ODCM.

Reporting Level is the concentration of plant produced radioactive material in an environmental sampling medium (averaged over any calendar quarter) from a specified location that requires a 30-day written report to the Nuclear Regulatory Commission and is identified in the ODCM.

IV. Results and Discussion The locations of the RGPP monitoring wells are illustrated on the maps for Hope Creek and Salem in Figures 1 and 2, respectively. (Note: The 2008 AREOR, Appendix F contained an editorial error in the Figure 2 Salem RGPP well locations. The position of RGPP wells Y and Z were incorrect. These positions have been corrected in the 2009 AREOR, Appendix F.) The Monitoring Well Construction Details for Hope Creek and Salem including monitoring interval below ground surface are provided in Table 1 Hope Creek RGPP Monitoring Wells: Construction Details and Table 2 Salem RGPP Monitoring Wells: Construction Details. The relevant radiological groundwater parameters used to evaluate the groundwater data are provided in Table 3 Relevant Groundwater Evaluation Criteria: Salem and Hope Creek Generating Stations.

The 2009 Groundwater Tritium Analytical Results for Hope Creek Generating Station are 112

shown in Table 4A. The 2009 Groundwater Tritium Analytical Results for Salem Generating Station are shown in Table 4B.

A. Groundwater Results Samples were collected from RGPP monitoring wells during 2009 in accordance with the station and MTS procedures for the radiological groundwater protection program with the exception of three RGPP monitoring wells BC, BL and BQ.

The Salem monitoring well BC, which is sampled semi-annually, could not be sampled during the October 2009 sampling campaign due to a security modification. This modification prevented safe access to the well. This safety concern has been address and the well will be sampled as scheduled in 2010.

The Hope Creek Well BL which is required to be sampled semi-annually was collected as required (March and October). These semi annual samples are to receive both tritium and gamma analysis. The tritium sample was sent to offsite laboratories (Maplewood Testing Services and TBE) in March 2009. However, due to communication error, the second sample collected in March for gamma analysis and the retained sample were discarded before being sent off site for analysis at Teledyne Brown Engineering. The October 2009 samples were collected and analyzed as required. In order to obtain a second gamma analysis for 2009, the station collected an additional sample from well BL in December 2009. The gamma analysis results for this second sample were, less than Minimum Detectable Concentrations.

The third quarter sampling for Hope Creek Well BQ was missed. This was caused by an oversight made by sampling personnel. The well was sampled in the fourth quarter, analysis results were less than the Administrative Limit of 200 pCi/L for tritium.

The MTS Laboratory in Maplewood, NJ analyzed the groundwater samples for tritium.

TBE Laboratory in Knoxville, TN analyzed the groundwater samples for plant-related 113

tritium (back-up and split samples), gamma emitters and total strontium. Analytical results and anomalies, if any, are discussed below.

Tritium Concentrations at Hope Creek Generating Station The results of the laboratory analysis indicate that tritium was detected, i.e, reported at a concentration above the RGPP LLD of 200 pCi/L, in seven RGPP monitoring wells at the Hope Creek site. The tritium concentrations measured at wells BH, BI, BJ, BK, BM, BN and BQ ranged from <200 pCi/L to 7778 pCi/L during 2009 as shown on Table 4A.

There were two sample events for which a Courtesy Communication was performed to NJDEP-BNE and the NRC. In March 2009, Well BH indicated a tritium concentration of 4,517 pCi/L. Monthly sampling was initiated and no positive trend was observed. The subsequent two samples were below 300 pCi/L and the elevated tritium concentration of 4,517 pCi/L, was never reproduced in 2009. In November 2009, Well BJ indicated a tritium concentration Of 7,778 pCi/L. Monthly sampling was initiated and no positive trend was observed. The December analysis was 628 pCi/L and the elevated tritium concentration has not been reproduced. Increased sample frequency has been maintained on these wells to ensure the elevated results were anomalous.

As a result of the elevated tritium results seen in March of 2009 the station put the following wells on a monthly sampling schedule: BH, BI, BJ, BK, BM and BN. These wells were sampled on a monthly frequency from March 2009 through December 2009.

Analysis results for wells BH, BI, BJ, BK, BM, and BN were less than 526 pCi/L for tritium, during the April 2009 through October 2009 monthly sampling events. In November of 2009 wells BI, BJ and BK showed a spike in tritium concentrations which were 895, 7,778 and 1324 pCi/L respectively. The December sampling event showed a decreased tritium concentration in these wells; BI 472 pCi/L; BJ 628 pCi/L; BK 852 pCi/L. In addition, the December sampling for well BH showed a spike at 1,082 pCi/L.

Trending of the well results can be seen in Figure 3 - Hope Creek Tritium Trends: Wells BH, BI, BJ, BK, BM, BN, and BQ. The concentrations of tritium are being tracked to 114

determine if any trend can be observed.

Tritium at Salem Generating Station The results of the laboratory analysis indicate that tritium was detected, i.e., reported at a concentration above the RGPP LLD of 200 pCi/L, in nine RGPP monitoring wells at the Salem site. The tritium concentrations measured at wells AL, BB, BD BE, BG, T, U, Y and Z ranged from <200 pCi/L to 2,259 pCiIL during 2009.

These low concentrations of tritium were evaluated and determined not to be indicative of an adverse trend as shown in Figure 4 - Salem Tritium Trends: Wells AL, BD, BE, BG, T,U,Y, Z. There were no analytical results for which Courtesy Communication (greater than 3,000 pCi/L tritium) was required. The tritium concentrations in these wells are being monitored and trended.

Gamma Emitters No plant-related gamma emitters were detected in any RGPP well sampled in 2009.

Naturally occurring Potassium-40. was detected in several of the wells sampled during 2009.

Strontium Total strontium, including Sr-89 and Sr-90, was not detected in any RGPP well sampled during 2009.

B. Investigations Hope Creek Unit 2 Emergency Sump Investigation As discussed in the 2008 AREOR, an elevated tritium concentration was measured in the water from the Unit 2 Turbine Building Emergency Sump at Hope Creek Station. This 115

resulted in a Tritium Investigation being conducted during the last quarter of 2008 and into 2009.

On November 7, 2008, as part of a station evaluation for an increase in plant water usage, water in the Unit 2 Emergency Sump was sampled. The results identified a tritium concentration of 40,990 pCiiL in the water from the Unit 2 Emergency Sump. One of the purposes for this sump is to collect the condensation from the Unit 2 Turbine Building HVAC. It was determined that this sump had been drained on or about November 3, 2008 and released through cooling tower blowdown to the Delaware River. Operations Department personnel were notified immediately. Equipment Operators tagged out the sump preventing any more inadvertent discharges.

A Prompt Investigation was initiated and a team was formed. The team's charter was to investigate and determine the source (s) of Tritium to the sump. The team evaluated eleven failure modes for the source of the Tritium in the Unit 2 Emergency Sump. Of the eleven failure modes identified, three were determined by the team to be the greatest potential sources of Tritium. In addition, the team performed a review of P&IDs drawings and visually inspected all potential sources to the sump. No anomalous inputs to the sump were identified.

The team determined that the elevated levels of Tritium found in the Unit 2 Emergency Sump were determined to be from the condensate line coming from the Admin Building HVAC System with contributing components from groundwater seepage and floor concrete leaching. (PSEG Hope Creek, 2008.) The Unit 2 Emergency Sump is being administratively controlled to ensure radiological monitoring prior to discharge.

Elevated Tritium Results in RGPP Wells Investigation The station increased the sampling frequency of some of the Hope Creek and Salem RGPP wells during 2009. Several locations are under investigation for the fluctuating tritium concentrations.

116

Specifically, the station placed six of the Hope Creek RGPP wells on an increased sampling frequency from March 2009 through December 2009. (Station wells BH, BI, BJ, BK, BM and BN were placed on a monthly sampling campaign.)

As a result of the fluctuating sample analysis results, the station set forth to investigate the potential causes for the elevated analysis results via the use of a Failure Mode Causal Table (FMCT) and team of Subject Matter Experts (SMEs). Evaluation of the Site Conceptual Model and the hydrological transport mechanism confirm that the transport of water containing tritium is retarded by the subsurface configuration. Therefore, the observed rate of change in tritium concentrations would not be expected to originate from a spill or a leak.

The station identified seven failure modes that could have potentially contributed to the elevated tritium levels. Some of these failure modes examine systems structures and components which have the potential to leak radiological isotopes to the environment, sample contamination, tritium recapture and run off, etc. The FMCT is still underway.

Actions taken to date include a visual inspection of the RGPP wells by Maplewood Testing services technicians (completed October 2009), replacing the well caps with new sealing well caps (completed February 2010), well pump inspections performed by well contractors (Arcadis) which includes a full internal inspection of the wells (pumps, seals, casing) (completed March 2010) and a precipitation study is which planned for spring of 2010.

Salem RGPP wells also experienced elevated tritium levels during the 2009 sampling campaign. Well Y had sample analysis results of 2,259 pCi/L during the March 2009 sampling campaign. Other wells with analysis results over 1000 pCi/L included wells BG and Z. Salem has increased the sampling frequency and continues to monitor these wells.

Actions taken to date include a visual inspection of the RGPP wells by Maplewood Testing services technicians (completed October 2009), replacing the well caps with new sealing well caps (completed February 2010), and a precipitation study is which planned for spring of 2010.

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C. RGPP 2009 Status The RGPP long-term sampling program will be modified as required in 2010 to effect changes as a result of the recent tritium concentrations and to adaptively manage the program to meet the RGPP objectives. Baseline sampling and analysis of groundwater will continue on the following schedule:

" Tritium will be analyzed at least semi-annually each calendar year to an LLD of 200 pCi/L;

Plant-related gamma emitters will be analyzed semi-annually to the Environmental LLDs specified in the ODCM;

Strontium will be analyzed annually as total strontium; if the total strontium is greater than 2.0 pCi/L separate analysis for strontium-89 and strontium-90 will be performed; and,

RGPP monitoring well sample frequency will be adjusted based on analytical results, but in no event less than twice per year.

2009 USNRC Inspection of the RGPP On March 9 -13, 2009 the NRC's Division of Reactor Projects performed an inspection of the PSEG Radiological Groundwater Protection Program (NRC 2009). The purpose of this inspection was to verify that PSEG implemented the voluntary industry Groundwater Protection Initiative (GPI). The GPI was unanimously approved by the senior members of Nuclear Energy Institute (NEI) namely, the Chief Nuclear Officers from the participating Nuclear Utilities in the US. This inspection was performed using the NRC Inspection Manual Temporary Instruction 2515/173 Review of the Implementation of the Industry Ground Water Protection Voluntary Initiative by a Senior Health Physicist from Region I (http:H/adamswebsearch2.nrc.gov/idtnws/doccontent.dll?iibrary=PU ADAMSAPBNTADOI &lD=083080274).

The NRC Inspector verified that the NEI-07--07 Objectives for the GPI were documented in the PSEG RGPP plans and procedures.

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2009 NEI Peer Assessment of the RGPP In accordance with the NEI 07-07 Industry Groundwater Protection Initiative, the stations underwent a peer assessment by NEI from January 2009 through December 2009 (NEI

.20 10). The purpose of this peer assessment was to evaluate Salem/Hope Creek's implementation of NEI 07-07 Industry Groundwater Protection Initiative - Final Guidance Document. The NEI team which was composed of SMEs from other nuclear utilities determined that Salem/Hope Creek site has satisfactorily met the majority of the NEI 07-07 Objective/Acceptance Criteria. Identified improvements and enhancements are being addressed.

D. Impacts to Groundwater: Past Spills and Leaks Historical unplanned and unmonitored releases on site are listed in Table 5, Salem and Hope Creek IOCFR50.75 (g) Data. There are currently no known active releases into the groundwater at Salem or Hope Creek Stations.

In conclusion, the operation of Salem and Hope Creek Stations has had minimal adverse radiological impact on the environment from unmonitored or unplanned releases of radionuclides.

V. References

1. ARCADIS, 2006A. Site Investigation Report July 2006. PSEG Nuclear LLC. Hope Creek Generating Station, Hancock's Bridge, New Jersey.

2. ARCADIS, 2006B. Site Investigation Report July 2006. PSEG Nuclear LLC. Salem Generating Station, Hancock's Bridge, New Jersey.

3. NEI, 2007. NEI 07-07, Industry Groundwater Protection Initiative- Final Guidance Document, Nuclear Energy Institute, Washington, DC, June 2007.

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4. PSEG, 2007. 2006 Annual Radiological Environmental Operating Report, January 1 to December 31, 2006, Salem Generating Station Unit I and 2 and Hope Creek Generating Station, April 2007.

5. PSEG, 2008. 2007 Annual Radiological Environmental Operating Report, January 1 to December 31, 2007, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2008.

6. PSEG, 2009. 2008 Annual Radiological Environmental Operating Report, January 1 to December 31, 2008, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2009.

7. PSEG Hope Creek, 2008. Tritium Investigation Unit 2 Turbine Bldg Sump, Apparent Cause Evaluation, 70091569.

8. PSEG Hope Creek, 2009. BH Well High Tritium Results, Failure Mode Causal Table, 70099170.

9. NRC, 2009. NRC Inspection Report 05000354/2009002: Hope Creek Generating Station - NRC Integrated Inspection Report, April 27, 2009.

10. NEI, 2010. NEI 07-07 NEI Groundwater Protection Initiative Pier Assessment Report, January 21, 2010.

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Table I Hope Creek RGPP Monitoring Wells: Construction Details Total Installation Construction Diameter Depth Monitoring MP MP Monitoring Well ID Date Details (inches) (feet bgs) Interval Elevation Elevation Purpose Source Targets (feet bgs) (feet RPD) (feet msl)

Well BH May-06 Sch-40 PVC 4 37.0 27 - 37 97.92 8 Perimeter NA Well BI May-06 Sch-40 PVC 4 38.5 28.5 - 38.5 99.6 9.68 Source Facilities; Piping Well BJ May-06 Sch-40 PVC 4 38.0 28 - 38 Source Condensate Storage &

100.23 10.31 Transfer; Facilities; Piping Well BK May-06 Sch-40 PVC 4 38.5 28.5 - 38.5 98.19 8.27 Perimeter NA Well BL May-06 Sch-40 PVC 4 35.0 25 - 35 99.71 9.79 Perimeter NA Well BM May-06 Sch-40 PVC 4 38.0 28- 38 99.76 9.84 Source Facilities; Piping Well BN May-06 Sch-40 PVC 4 12.5 7.5- 12.5 Source Auxiliary Boiler Building; 102.64 12.72 Piping Well BO May-06 Sch-40 PVC 4 36.0 26 - 36 97.98 8.06 Perimeter/Source Building Sewage Well BP May-06 Sch-40 PVC 4 38.0 28-38 99.06 9.14 Perimeter/Source Building Sewage Well BQ May-06 Sch-40 PVC 4 42.0 32 -42 Source Auxiliary Boiler Building; Dry 102.16 12.24 Cask Storage Building; Piping Well BR May-06 Sch-40 PVC 4 40.5 30.5 - 40.5 Perimeter/Source Piping; Dry Cask Storage

104.28 14.36 Building Well BS May-06 Sch-40 PVC 4 35.0 25 - 35. 100.55 10.63 Upgradient NA Well BT May-06 Sch-40 PVC 4 38.5 28.5 - 38.5 99.60 9.68 Upgradient NA Notes:

MP Measuring Point bgs Below ground surface RPD Relative to plant datum msl Relative to mean sea level (NAVD 1988)

NA Not applicable NAD 83 North American Datum 1983 121

Table 2. Salem RGPP Monitoring Wells: Construction Details Constructio Installation n Diameter Total Depth Monitoring MP MP Monitoring Well Io Date Details (inches) (feet bgs) Interval Elevation Elevation Purpose Source Targets (feet bgs) (feet RPD) (feet msl)

Well T Jun-03 Sch-40 PVC 2 31.2 21.2-31.2 104.13 14.21 Source Facilities; House Heating BIr Well U May-03 Sch-40 PVC 2 32.2 27.2 - 32.2 98.57 8.65 Source Facilities; House Heating Bir Well Y Sep-03 Sch-40 PVC 2 37.0 27.0-35.0 101.81 11.89 Perimeter NA Well Z Sep-03 Sch-40 PVCSc-4 2 37.5 27.5-37.5 PCPerimeter 101.86 11.94 Perimeter NA Well AL Jan-04 Sch-4 PVC 2 25.3 15.3 - 25.3 99.13 9.21 NA Well BA May-06 Sch-40 PVC 4 39.5 29.5-39.5 101.07 11.15 Perimeter NA Well BB May-06 Sch-40 PVC 4 47.0 37-47 99.38 9.46 Perimeter NA Well BC May-06 Sch-40 PVC 4 38.0 28 - 38 Source / Perimeter Facilities; RAP Tanks; 98.78 8.86 Piping Well BD May-06 Sch-40 PVC 4 40.5 30.5 - 40.5 Source Facilities; RAP Tanks; 98.78 8.86 Piping Well BE May-06 Sch-40 PVC 4 37.0 27 -37 98.31 8.39 Perimeter NA Well BF May-06 Sch-40 PVC 4 42.5 32.5-42.5 99.11 9.19 Perimeter NA Well BG May-06 Sch-40 PVC 4 37.0 27-37 100 10,08 Perimeter NA Well BU May-06 Sch-40 PVC 4 36.0 26- 36 100.16 10.24 Upgradient NA Notes:

Measuring MP Point bgs Below ground surface RPD Relative to plant datum msl Relative to mean sea level (NAVD 1988)

NA Not applicable NAD 83 North 'American Datum 1983 122

Table 3. Relevant Groundwater Evaluation Criteria: Salem and Hope Creek Generating Stations PSEG ODCM Isotope RGPP LLD (pCilL) Reporting Level (pCilL)

Tritium 200 30,000 Total Strontium 2.0 8 Mn-54 15 1000 Fe-59 30 .400 Co-60 15 300 Zn-65 30 300 Nb-95 15 400 Zr-95 15 200 Cs-1 34 15 30 Cs-1 37 18 50 Ba-140 60 200 La-140 15 200 123

Table 4A. Analytical Results for Tritium in Groundwater:

Hope Creek Generating Station Sample Tritium Sample Tritium Well ID Date Conc. Well ID Date Conc.

(pCi/L) (pCi/L)

-t .f" -- -

03/10/2009 918.46 03/10/2009 4,517.62 04/27/2009 <200 04/23/2009 272.56 05/19/2009 <200 05/19/2009 292.23 06/15/2009 309.83 06/15/2009 317.50 07/27/2009 <200 BH 07/27/2009 526.36 BM 08/20/2009 255.50 08/19/2009 <200 09/23/2009 <200 09/14/2009 <200. 10/27/2009 <200 10/14/2009 <200 11/19/2009 <200 11/20/2009 337.62 12/29/2009 <200 12/29/2009 1,082

03/10/2009 1,469 03/19/2009 760 04/27/2009 217 06/18/2009 240 05/19/2009 485 07/29/2009 322 06/15/2009 366 08/25/2009 274 BN 7/27/2009 817 09/17/2009 270 BI 08/20/2009 235 10/30/2009 <200 09/14/2009 <200 11/20/2009 <200 09/14/2009 <200 12/30/2009 393 10/27/2009 485 11/19/2009 895 BO B 04/16/2009 <200 12/10/2009 472 10/13/2009 <200 03/10/2009 917 BP 04/16/2009 <200 04/27/2009 <200 10/13/2009 <200 05/19/2009 <200 06/15/2009 214 03/19/2009 720 07/27/2009 <200 BQ 06/18/2009 <200 BJ 08/20/2009 241 10/30/2009 <200 09/14/2009 436 10/27/2009 411 04/16/2009 <200 11/19/2009 7,778 0BR 10/13/2009 <200 12/04/2009 628 04/16/2009 <200 BS 03/10/2009 576 10/13/2009 <200 05/19/2009 230 06/15/2009 j 233 BT 04/16/2009 <200 07/27/2009 274 10/13/2009 <200 BK 08/19/2009 309 09/14/2009 <200 03/10/2009 <200 10/14/2009 -<200 BL 10/14/2009 <200 11/20/2009 1,324 12/23/2009 <200 12/10/2009 852 Bold concentration value indicates tritium level above200 pCi/L. NS- Not Sampled 124

Table 4B Analytical Results for Tritium in Groundwater:

Salem Generating Station Tritium Tritium Well ID Sample Date Conc. Well ID Sample Date Conc.

(pCi/L) (pCi/L) 01/19/2009 568 01/19/2009 266 04/08/2009 441 <200 T 06/10/2009 AL 06/10/2009 452 07/16/2009 <200 07/21/2009 598 10/20/2009 <200 10/20/2009 686 01/19/2009 <200 04/13/2009 <200 06/29/2009 282 BA 10/21/2009 ] <200 U 07/16/2009 <200 10/20/2009 <200 04/13/2009 <200 BB 01/20/2009 <200 10/21/2009 206 02/25/2009 <200 04/29/2009 <200 03/30/2009 2,259 BC 04/27/2009 <200 05/20/2009 <200 380 06/10/2009 <200 BD 04/13/2009 10/27/2009 <200 07/22/2009 <200 08/18/2009 <200 04/13/2009 448 09/24/2009 <200 06/29/2009 <200 10/27/2009 <200 BE 11/19/2009 <200 10/27/2009 636 12/30/2009 <200 BF 1 04/13/2009 [ <200 01/20/2009 276 10/27/2009 <200 02/25/2009 244 03/30/2009 1,042

. 04/29/2009 354 04/27/2009 225 BG 06/15/2009 <200 05/20/2009 288 11/19/2009 1,590 z 06/10/2009 249 07/22/2009 398 BU I 04/16/2009 10/13/2009

[ <200 08/18/2009 299

<200 09/24/2009 314 10/27/2009 369 11/19/2009 368 12/30/2009 210 Bold concentration value above 200 pCi/L. NS -Not Sampled 125

Table 5. Salem and Hope Creek 10CFR 50.75(g) Data QuantitySpilled I Location of Spill/Discharge Discharged Spill/Discharge Description Apr-95 88 mCi Hope Creek and Salem Steam from the Decon Solution Evaporator released from Hope Creek's South Plant Vent Jun-01 ~5Ci Unit 1 RWST Salem Unit 1 RWST Nozzle Leak Sep-02 -5 Ci Ground west of Unit 1 Blockage of the Spent.Fuel Pool Spent Fuel Building liner's "tell-tales" caused"backup of contaminated water'"thirough building seams Jan-05 No discharge to the Hope Creek rooms 3133, Water from inside the Waste environment 3135, 3129 and 5102 Sludge Phase Separator Tank Room appeared to be leaking through the crack in the wall May-07 2.8 milli Curies of Cs 137 In front of Salem Unit 2 Burst site glass during operation.

condensate polisher Resin blown through wall into switchyard 126

Figure 1 Hope Creek RGPP Monitoring Well Locations 0 230 460 920 1,380 1,84F0 I Feet W+E S

Figure 2 Salem RGPP Monitoring Well Locations 7-u BU 0 200 400 800 1,200 1600 I ý ---Feet

Figure 3 Hope Creek Tritium Trends: Wells BH, BI, BJ, BK, BM, BN and 1B3 HC RGPP Tritium Trend 2006-2009 10000 9000 o

(3 8000 7000 6000 0 5000 0

4000 E

3000 2000 1000 0

CO .O CO C C O co 0) (3) C 0)) 0)

IN 0)

Sample Date

- HC Well BH -a--- HC Well BI HC Well BJ -. HC Well BK w* HC Well BM a.- HC Well BN i.-- HG Well BQI 129

Figure 4 Salem Tritium Trends: Wells AL, BD, BE, BG, T, U; Y, Z Salem RGPP Tritium Trend 2006-2009 3000 j 2500 L 2000 o1500 0

1000

' 500 0

No No No No No N co C CO OO CO cO C 0) 00 c 000000 N

N N N N ~ _

~ N

~'-.

cc~ N) oCO NI Sample Date Salem Well AL -w-Salem Well BID _.Salem Well BE Salem Well BG )K Salem Well Z

--e--Salem Well T -i- Salem Well U - Salem Well Y 130

LR-N10-0123, 2009 Annual Radiological Environmental Operating Report

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LR-N10-0123, 2009 Annual Radiological Environmental Operating Report

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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