LR-N07-0089, Units 1 and 2 - 2006 Annual Radiological Environmental Operating Report

Units 1 and 2 - 2006 Annual Radiological Environmental Operating Report

ML071230112
Person / Time
Site:	Salem, Hope Creek
Issue date:	04/26/2007
From:	Fricker C, Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, NRC/NRR/ADRO
References
FOIA/PA-2010-0209, LR-N07-0089
Download: ML071230112 (130)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 APR 2,6 2007 0PSEG Nuclear LLC LR-N07-0089 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 Docket No. 50-354 Salem Nuclear Generating Station, Unit Nos. 1 And 2 Facility Operating Licenses DPR-70 And DPR-75 NRC Docket Nos. 50-272 and 50-311

Subject:

2006 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 Facility Operating License NPF-57 for Hope Creek Generating Station, PSEG Nuclear hereby transmits one copy of the 2006 Annual Radiological Environmental Operating Report. This report summarizes the results of the radiological environmental surveillance program for 2006 in the vicinity of the Salem and Hope Creek Generating Stations. The result of this program for 2006 was specifically compared to the result of the pre-operational program.

If you have any questions or comments on this transmittal, please contact James Clancy at (856) 339-3144.

Sincerely, John F. Perry CarJ. Fricker Plant Manager - Hope Creek Pla t Manager- Salem Attachment 95-2168 REV. 7/99

Page 2 LR-N07-0089 C Mr. S. Collins, Administrator - Region 1 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 08B1 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Hope Creek (X24)

USNRC Senior Resident Inspector - Salem (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 086 Mr. K. Kille Delaware Emergency Management Agency 165 Brick Store Landing Road Smyrna, DE 19977

o PSEG 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 2006 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 2006 Prepared by PSEG SERVICE CORPORATION MAPLEWOOD TESTING SERVICES APRIL 2007

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM & HOPE CREEK GENERATING STATIONS 2006 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 2006

TABLE OF CONTENTS PAGE

SUMMARY

...................................................... 1 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3 Objectives ................................... 4 Data Interpretation .......................... 5 Quality Assurance Program .................... 5 Program Changes .............................. 6 Results and Discussion ....................... 6 Atmospheric .............................. 6 Direct Radiation ......................... 8 Terrestrial .............................. 8 Aquatic .................................. 14 Program Deviations ........................... 18 Conclusions .................................. 18 REFERENCES ....................................... 30 APPENDIX A - PROGRAM

SUMMARY

..................... 33 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS... 39 APPENDIX C DATA TABLES ........................ 47 APPENDIX D -

SUMMARY

OF RESULTS FROM ANALYTICS & ENVIRONMENTAL RESOURCE ASSOCIATES INTERLABORATORY COMPARISON PROGRAMS ....................................... 77 APPENDIX E SYNOPSIS OF LAND USE CENSUS .................... 85 APPENDIX F Radiological Groundwater Protection Program ... 89 i

LIST OF TABLES TABLE NUMBER TABLE DESCRIPTION PAGE

1. Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program 19 LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION PAGE

1. Gross Beta Activity in Air Particulate 1986 through. 2006 (Quarterly) .......................... 24

2. Ambient Radiation - Off-site vs Control Station 1986 through 2006 (Quarterly) .......................... 25

3. Iodine-131 Activity in Milk 1986 through 2006 (Quarterly) .......................... 26

4. Gross Beta Activity in Surface Water 1986 through 2006 (Quarterly) .......................... 27

5. Tritium Activity in Surface Water 1986 through 2006 (Quarterly) ......................... 28

6. Cesium-137 and Cobalt-60 Activity in Aquatic Sediment 1986 through 2006 (Semi-Annual) ......................... 29 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 Stations (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.

PSEG's Maplewood Testing Services (MTS) has been responsible for the collection and analysis of environmental samples during the period of January 1, 2006, through December 31, 2006, and the results are discussed in this report. The REMP for SGS/HCGS was conducted in accordance with the SGS and HCGS Technical Specifications/Offsite Dose Calculation Manual. The Lower Limit of Detection (LLD) values required by the Techpical Specifications/ODCM were achieved for this reporting period. 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/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 bomb 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. Samples of air particulates, air iodine, milk, surface, ground and drinking water, vegetables, game, 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.

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. No unusual radiological characteristics were observed in the environs of SGS/HCGS during this reporting period. Since these results were comparable to the results obtained during the preoperational phase of the program, and with historical results collected since commercial operation, we can conclude that the operation of SGS and HCGS had no significant impact on the radiological characteristics of the environs of these stations.

To demonstrate compliance with Technical Specifications/ODCM (Sections 3/4.12.1 & 6.8.4.h -1,2,3), 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.

1

The results of these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with Technical Specifications/ODCM (Section 3/4.11) and applicable Federal and State regulations, and to verify the adequacy of radioactive effluent control systems.

The results provided in this report are summarized below:

" There were a total of 1444 analyses on 1112 environmental samples during 2006, including direct radiation dose measurements made using 196 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 and Cs-137 were also detected. The concentrations of these nuclides were well below the Technical Specification reporting limit.

" Dose measurements made with quarterly TLDs at 31 offsite locations around the SGS/HCGS site averaged 50 millirems for the year 2006. The average of the dose measurements at the control locations (background) was 52 millirems for the year.

This was comparable to the preoperational phase of the program which had an average of 55 millirems per year for 1973 to 1976.

Appendix F contains the first 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 releases of radionuclides and not previously identified. The RGPP is a voluntary program implemented by PSEG in conjunction with industry initiatives and guidance. It was concluded that the operation of Salem and Hope creek Stations has had no adverse radiological impact on the environment from unmonitored or unplanned releases of radionuclides to groundwater.

During 2006, PSEG Nuclear continued remedial actions for tritium identified in shallow groundwater at Salem Station. These remedial actions have been 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 GRS is in operation, providing hydraulic control of the plume and effectively removing tritium contaminated groundwater, all monitoring wells are below 100,000 pCi/L at this time. 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.

2

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 1169 megawatt electric(MWe) and Salem Unit Two has a net rating of 1155 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 1091 MWe (3339 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 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 [1,2]. 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. Starting in December, 1972, more extensive radiological monitoring programs were initiated. 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. RMC reports for the preoperational and operational phase of the program are referenced in this report [7-9]. 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 TLDs. 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, Framatome ANP, Inc. Environmental Laboratory (Framatome) is the third party QA vendor and the laboratory which performs the TLD analyses. MTS reports for the operational phase from 1983 to 2004 are referenced in this report

[10.]

3

An overview of the 2006 Program is provided in Table 1.

Radioanalytical data from samples collected under this program were compared with results from the preoperational phase. 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, 2006, 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/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.

" 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/ODCM and Section 6.9.1.6 of the Hope Creek Technical Specifications/ODCM, summarizes the findings of the 2006 REMP.

Results of the four-year preoperational program have been summarized 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 describes and summarizes, in accordance with Section 6.9.1.7 of the Salem TS and Section 6.9.1.6 of the Hope Creek TS, the operational program as performed in 2006.

4

Appendix B describes the coding system which identifies sample type and location. Table B-1 lists the sampling stations and the types of samples collected at each station. These sampling stations are indicated on Maps B-1 and B-2.

DATA INTERPRETATION Results of analyses are grouped according to sample type and presented in Appendix C. 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 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.

Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur.

Since these variations will tend to counterbalance one another, averages based upon repetitive grab samples is considered valid.

QUALITY ASSURANCE PROGRAM MTS has a quality assurance program designed to ensure confidence in the analytical program. Approximately 15% of the total analytical effort is spent on quality control, including process quality 5

control, instrument quality control, interlaboratory cross-check analyses, and data review.

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 Plan [11] and the Environmental and Chemical Division Procedures Manual. The internal quality 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, and analysis of duplicate samples. The external quality control activity is implemented through participation in both the Analytics and the Environmental Resource Associates Interlaboratory Comparison Programs. The results of these Interlaboratory Comparison Programs are listed in Tables D-1 through D-4 in Appendix D.

PROGRAM CHANGES There were no game (muskrat) samples available for analysis this year. Our Delaware contact moved and the NJ contact is no longer trapping, an alternative trapper was not identified. These samples are not required by the SGS or HCGS Technical Specifications/ODCM.

The muskrats were collected once a year as management audit samples because of their inhabiting the marshlands surrounding the Site. If an alternative trapper can be identified, these management samples will resume.

RESULTS AND DISCUSSION The analytical results of the 2006 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 2006 REMP are summarized in Appendix A. The data for individual samples are presented in Appendix C. The data collected demonstrates that the SGS and HCGS REMP was conducted in compliance with the Technical Specifications/ODCM.

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

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

6

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 and were corrected to standard temperature and pressure.

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

Air particulate samples were collected weekly, at 6 locations. Each of the 310 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 data recovery for the 6 sampling stations in 2006 was 98.7 percent.

" Gross beta activity was detected in all of the indicator station samples collected at concentrations ranging from 6 x 10-3 to 38 x 10-3 pCi/m 3 and in all of the control station samples from 11 x 10-3 to 35 x 10-3 pCi/m3 . The averages for the indicator and control station samples were 21 and 22 x i0-3 pCi/m 3 , respectively. The maximum preoperational level detected was 920 x 10-3 pCi/m 3, with an average of 74 X 10-3 pCi/m 3 . Results from 1986 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 all the way back 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 were below the LLD.

0 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 59 x 10-3 to 95 x 10-Y pCi/m3, with an average of 80 x 10-3 pCi/m 3 . It was detected in the 4 control station composites ranging from 62 x 10-3 to 94 x 10-3 pCi/m 3, with an average of 80 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 .

o Potassium-40 activity was detected in 15 of the indicator station samples, with concentrations ranging from 2.6 x i0-to 14 x 10 pCi/m 3 , with an average of 9.4 x 10-3 pCi/m 3 .

K-40 was also detected in 2 control station samples, at a concentration of 10 x 10-3 for both samples. No preoperational data is available for comparison.

7

Air Iodine (Table C-3)

Iodine in filtered air samples was collected weekly, at 6 locations.

Each of the 310 samples collected (see Program Deviations) for the year was analyzed for 1-131.

Iodine-131 was not detected in any of the weekly samples analyzed.

LLD sensitivities for all the stations, both indicator and control, ranged from <1.1 x 10-3 to <9.5 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 energy-compensated CaSO 4 (Tl) thermoluminescent dosimeters (TLDs) supplied and read by AREVA NP EL. 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. Special 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 2006, including 12 on-site locations, 31 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Effort was made to locate TLDs at schools and population centers in the area.

Five readings for each TLD (ie; 5 elements) at each location were taken in order to obtain a more statistically valid result. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.1004.

The average dose rate for the 31 quarterly off-site indicator TLDs was 4.2 millirads per standard month, while the on-site average was also 4.2 millirads per standard month. The average control rate was similar at 4.3 millirads per standard month. The preoperational average for the quarterly TLD readings was 4.4 millirads 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 1986 through 2006, with an inset graph depicting the current year back to 1973.

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.

8

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

Locally grown vegetable and fodder crops were collected at the time of harvest with the exception of ornamental cabbage. MTS personnel planted, maintained and harvested this broad leaf crop in the 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.

N Iodine-131 was not detected in any of the 80 samples analyzed.

LLD sensitivities for both the indicator and the control station samples ranged from <0.1 to 0.4 pCi/L. The maximum preoperational level detected was 65 pCi/L which occurred following a period of atmospheric nuclear weapons tests.

Results from 1986 to 2006 are plotted on Figure 3, with an inset graph depicting the current year back to 1973.

• Gamma spectroscopy performed on each of the 80 samples indicated the presence of the naturally-occurring radionuclides K-40 and Radium. All other gamma emitters searched for were below the LLD.

o Potassium-40 was detected in all 80 samples. Concentrations for the 60 indicator station samples ranged from 1160 to 1450 pCi/L, with an average of 1330 pCi/L. The 20 control station sample concentrations ranged from 1120 to 1420 pCi/L, with an average of 1300 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.

O Radium was detected in 4 indicator station samples at concentrations ranging from 9 to 13 pCi/L, with an average of 11 pCi/L. The 1 positive control station sample had a concentration of 7.8 pCi/L. The preoperational had an average 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 during January through December of the year. Each sample was analyzed for gross alpha, gross beta, tritium, and gamma emitters.

N Gross alpha activity was detected in 1 of the well water samples at a concentration of 0.7 pCi/L.

9

The maximum preoperational level detected was 9.6 pCi/L. There was no preoperational average determined for this analysis.

" Gross beta activity was detected in all 12 well water samples.

Concentrations for the samples ranged from 9.7 to 12 pCi/L, with an average of 11 pCi/L. The 2006 gross beta results are comparable with the preoperational results which ranged from

<2.1 to 38 pCi/L, with an average value of 9 pCi/L.

" Tritium activity was not detected in any of the well water samples. The LLD sensitivities ranged from <151 to <165 pCi/L.

The maximum preoperational level detected was 380 pCi/L. There was no preoperational average determined for this analysis.

" Gamma spectroscopy performed on each of the 12 well water samples indicated the presence of the naturally-occurring radionuclides K-40 and Radium. All other gamma emitters searched for were below the LLD.

o Radium was detected in all 12 of the well water samples at concentrations ranging from 48 to 252 pCi/L with an average of 117 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 17 years. However, as with the 1989 through 2006 results, they are higher than those found in the preoperational program.

These results are due to a procedural change for sample preparation. The change results in less removal of radon (and its daughter products) from the sample. It is reasonable to conclude that values currently observed are typical for this region.

O Potassium-40 was detected in 5 of the samples at concen-trations ranging from 41 to 62 pCi/L and an average of 524 pCi/L. The maximum preoperational level detected was 30 pCi/L. There was no preoperational average determined for this analysis.

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

Both raw and treated potable water samples were collected and composited by Salem water treatment plant 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.

0 Gross alpha activity was only detected in 6 raw water samples at concentrations of 0.4 to 1.1 pCi/L with an average of 0.7 pCi/L.

10

The maximum preoperational level detected was 2.7 pCi/L. There was no preoperational average determined for this analysis.

• Gross beta activity was detected in all 24 of the raw and treated water samples. The raw samples were at concentrations ranging from 2.9 to 4.8 pCi/L. Concentrations for the treated water ranged from 2.5 to 4.4 pCi/L. The average concentration for both raw and treated was 3.5 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 in any of the raw or treated potable water samples. LLD sensitivities for the raw and treated samples ranged from <139 to <156 pCi/L. The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

• Iodine-131 measurements were performed to a sensitivity of 1.0 pCi/L, even though the drinking water supplies are not affected by discharges from the Site since the receiving water body (Delaware River) is brackish and therefore the water is not used for human consumption. Iodine-131 measurements for all 24 samples were below the LLD sensitivities. These sensitivities ranged from <0.1 to <0.4 pCi/L. There was no preoperational data available for comparison.

N Gamma spectroscopy performed on each of the 24 monthly water samples indicated the presence of the naturally-occurring radionuclides K-40 and Radium. All other gamma emitters searched for were below the LLD.

o The radionuclide K-40 was detected in 8 of the treated potable waters at concentrations ranging from 40 to 56 pCi/L. It was detected in 9 of the raw potable water samples at concentrations from 32 to 50 pCi/L. The average for both raw and treated results was 44 pCi/L. LLD sensitivities for the remaining 7 potable water samples were <15 to <26 pCi/L. There was no preoperational data available for comparison.

o Radium was detected in 6 of the treated potable waters at concentrations ranging from 4 to 22 pCi/L. It was detected in 2 of the raw potable water samples at concentrations of 5.2 and 74 pCi/L. The average for all the positive potable water samples was 20 pCi/L. LLD sensitivities for the remaining 16 samples were <1.5 to <4.6 pCi/L. The maximum preoperational level detected was 1.4 pCi/L. There was no preoperational average determined for this analysis. The higher results in the three measurable samples are due to the procedural change for sample preparation, as discussed in the Well Water section.

11

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 at 6 indicator stations (19 samples) and 2 control stations (8 samples).

The vegetables collected as management audit samples were analyzed for gamma emitters and included asparagus, cabbage, sweet corn, peppers, and tomatoes.

Gamma spectroscopy performed on each of the 27 samples indicated the presence of the naturally-occurring radionuclide K-40 and in one sample radium. All other gamma emitters searched for were below the LLD.

Potassium-40 was detected in all 27 samples. Concentrations for the 19 indicator station samples ranged from 1310 to 2980 pCi/kg-wet and averaged 2100 pCi/kg-wet. Concentrations for the 8 control station samples ranged from 1640 to 2740 pCi/kg-wet, and averaged 2090 pCi/kg-wet. The average concentration detected for all samples, both indicator and control, was 2100 pCi/kg-wet.

The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2140 pCi/kg-wet.

Radium was detected in 1 of the indicator tomato samples at a concentration of 9.1 pCi/l. LLD sensitivities for all the remaining vegetable samples, both indicator and control, ranged from <5.8 to <13 pCi/L. There was no preoperational data available for comparison.

Fodder Crops (Table C-11)

Although not required by the SGS or HCGS Technical Specifications/ODCM, 3 samples of crops normally used as cattle feed (silage and soybeans) were collected from three indicator stations (3 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. These samples were harvested in December (except for one location that was eaten by animals). These broad leaf vegetation samples were deemed necessary since there are no longer any milk farms operating within the 5 km radius of SGS/HCGS.

The closest milk farm we have is located in Odessa, DE at 4.9 miles (7.88 km).

12

Gamma spectroscopy performed on each of the 8 samples indicated the presence of the naturally-occurring radionuclides Be-7 and K-40 plus trace amounts of Cs-137 in the ornamental cabbage samples. All other gamma emitters searched for were below the LLD.

Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in two of the indicator silage samples at concentrations of 243 and 1480 pCi/kg-wet. It was detected in the control station silage sample at 968 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. The maximum preoperational level detected for soybean samples was 9300 pCi/kg-dry. Be-7 was detected in all 3 of the ornamental cabbage samples at concentrations of 266 to 417 pCi/kg-wet with a combined average of 320 pCi/kg-wet. There was no preoperational data available for comparison with these samples.

Potassium-40 was detected in all 8 of the vegetation station samples. The average for the indicator station samples was 6150 pCi/kg-wet. The average for the 2 control station vegetation samples was 9000 pCi/kg-wet. The average concentration detected for the silage samples (both indicator and control) was 3190 pCi/kg-wet. Preoperational results averaged 7000 pci/kg-wet.

Results for the soybean samples (indicator and control) was 16900 pCi/kg-wet. Preoperational soybean results averaged 22000 pCi/kg-dry. The average concentration of K-40 for the 3 ornamental cabbage samples was 3840 pCi/kg-wet. There was no preoperational data available for comparison with these samples.

Cesium-137 was detected in the 3 ornamental cabbage samples at concentrations ranging from 111 to 134 pCi/kg-wet. It was not detected in any of the silage or soybean samples. The pre-operational report shows that Cs-137 was found in fodder crops at a maximum value of 111 pCi/kg. There was no preoperational average determined for this analysis.

[After cesium was found in these ornamental cabbage samples, a sample of the root ball soils plus a separate soil sample from the area adjacent to where the cabbage was planted was collected.

The rootball soil did contain positive Cs-137 values. However, the soil adjacent to the plants did not. Since this years cabbage plants had been purchased from a different nursery than those from 2005 (which did not show positive for Cs-137), and planted in basically the same holes as the previous years plants, PSEG concludes that these plants had been exposed to the Cs-137 from the soil in which they had originally been grown in and not from any discharge from the SGS/HCGS. Soil is currently sampled in the vicinity of the plant on a three year cycle (2007 will be the next). Cs-137 has historically been reported in these samples at decreasing levels, as well as preoperational samples of soil, beef, vegetables, and precipitation].

13

AQUATIC Environmental Consulting Services, Inc (ECS) collected all aquatic samples (with the exception of the 6S2 shoreline sediment).

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

Edible fish and crabs are taken by net and then processed. In processing, the flesh is separated from the bone and shell and The flesh placed in sealed containers and frozen before being transported in ice chests.

Sediment samples collected by ECS were taken with a bottom grab sampler and frozen in sealed polyethylene containers before being transported in ice chests. MTS personnel collect location 6S2 shoreline sediment on the beach behind the observation building.

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 is at the outfall area (which is the area where liquid radioactive effluents from the Salem Station are allowed to be discharged into the Delaware River), another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river.

Station 12C1, at the mouth of the Appoquinimink River, serves as the operational control. [Location 12C1 was chosen because the physical characteristics of this station more closely resemble those of the outfall area than do those at the farther upstream location (1F2).

As discussed in the pre-operational summary report, due to the tidal nature of this Delaware-River-Bay estuary, there are flow rate variations. The further the distance from the boundary between the Delaware River and the Delaware Bay (Liston Point), the lower the background levels, the lower the salinity, lower K-40(AA) and lower concentrations of soluble gross beta emitters.] All surface water samples were analyzed monthly for gross beta, tritium and gamma emitters.

" Gross beta activity was detected in 45 of the indicator station samples ranging from 5.1 to 243 pCi/L, with an average of 59 pCi/L. Beta activity was detected in all 12 of the control station samples with concentrations ranging from 5.7 to 96 pCi/L, with an average of 46 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 1986 to 2006, with an inset graph depicting the current year back to 1973.

• Tritium activity was detected in one of the control station samples at 180 pCi/L.

14

It was also detected in 1 of the indicator station samples at a concentration of 180 pCi/L. LLD sensitivities for the remaining station samples, both indicator and control, ranged from <150 to

<170 pCi/L. The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L. Positive results from 1986 to 2006 are plotted on Figure 5, with an inset graph depicting the current year back to 1973.

• 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. All other gamma emitters searched for were below the LLD.

o Potassium-40 was detected in 46 samples from the indicator stations at concentrations ranging from 29 to 144 pCi/L and in all 12 of the control station samples ranging from 49 to 112 pCi/L. The average for the indicator station locations was 78 pCi/L, while the average for the control station locations was 73 pCi/L. The maximum preoperational level detected was 200 pCi/L, with an average of 48 pCi/L.

Fish (Table C-15)

Edible species of fish were collected semi-annually at 3 locations, 2 indicator and 1 control, and analyzed for gamma emitters in flesh.

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

• Gamma spectroscopy performed on each of the 4 indicator station samples and 2 control station samples indicated the presence of the naturally-occurring radionuclide K-40. All other gamma emitters searched for were below the LLD.

0 Potassium-40 was detected in all 4 samples from the indicator stations at concentrations ranging from 3250 to 3640 pCi/kg-wet for an average of 3443 pCi/kg-wet. K-40 was detected in both samples from the control location at 3430 and 3750 pCi/kg-wet. The average for the control samples was 3590 pCi/kg-wet. The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2900 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).

Gamma spectroscopy performed on the flesh of the indicator station samples and the control station samples indicated the presence of 15

the naturally-occurring radionuclide K-40. All other gamma emitters searched for were below the LLD.

Potassium-40 was detected in both indicator station samples at concentrations of 2690 and 3000 pCi/kg-wet. It was detected in both control station samples at 2490 and 3160 pCi/kg-wet. The average for both the indicator and control station samples was 2840 pCi/kg-wet. The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 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. Although trace levels of the man-made nuclide, Cs-137, were detected in 3 sediment locations, these levels were well within the acceptable levels specified in section 3/4.12.1 of the Technical Specifications/ODCM. (See explanation of controls in the surface water section)

Gamma spectroscopy was performed on each of the 12 indicator station samples and 2 control station samples. In addition to the detection of Cs-137, the naturally-occurring radionuclides Radium, K-40, Be-7 and Th-232 were also detected. All other gamma emitters searched for were below the LLD.

Cesium-137 was detected in 3 indicator station samples at concentrations ranging from 39 to 72 pCi/kg-dry. It was not detected in any of the control station samples. The maximum preoperational level detected was 400 pCi/kg-dry with an average of 150 pCi/kg-dry. Results from 1986 to 2006 are plotted on Figure 6, with an inset graph depicting the current year back to 1973.

Cobalt-60 was not detected in any of the sediment samples. LLD sensitivities for the 14 samples, indicator and control, ranged from <2.7 to <25 pCi/kg-dry. Results of all the positive values from 1986 to 2006 are plotted on Figure 6, with an inset graph depicting the current year back to 1973. There was no preoperational data available for comparison.

Beryllium-7 was detected in 3 of the indicator station samples at concentrations from 303 to 904 pCi/kg-dry with and average of 631 pCi/kg-dry. It was not detected in either control location. The maximum preoperational level detected was 2300 pCi/kg-dry. There was no preoperational average determined for this nuclide.

Potassium-40 was detected in all 12 indicator station samples at concentrations ranging from 2410 to 17300 pCi/kg-dry, with an average of 8525 pCi/kg-dry. Concentrations detected in both of the control station samples were at 16100 and 16300 pCi/kg-dry.

16

The average for the control station samples was 16200 pCi/kg-dry.

The maximum preoperational level detected was 21000 pCi/kg-dry, with an average of 15000 pCi/kg-dry.

Radium was detected in all 12 indicator station samples at con-centrations ranging from 178 to 689 pCi/kg-dry, with an average of 450 pCi/kg-dry. Concentrations detected in both of the control station samples were at 487 and 522 pCi/kg-dry, with an average of 500 pCi/kg-dry. The grand average for both the indicator and control station samples was 460 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 317 to 1100 pCi/kg-dry, with an average of 686 pCi/kg-dry. Concentrations detected in both of the control station samples were at 865 and 982 pCi/kg-dry, with an average of 924 pCi/kg-dry. The grand average for both the indicator and control station samples was 720 pCi/kg-dry. The maximum pre-operational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.

17

PROGRAM DEVIATIONS The following air sampler was unavailable due to power loss:

STATION LOCATION HOURS UNAVAILABLE 5SI 1.0 mi. E of vent 610.5 (7.1% for year)

Two air particulate samples and two air iodine samples were lost (See Tables C-2 and C-3 in Appendix C). This power outage was attributable to a downed pole wire from the 4kv supply line.

Because of this air sampler's location, (Along the site access road along the river by the old boat ramp) it is subjected to high winds quite frequently. This is the primary cause of this air samplers unavailability. Overall availability for this air sampling location was 92.9% for the year 2006.

A broadleaf vegetation sample (Ornamental Cabbage) was not available from location 1S1. MTS personnel found the plants had been eaten down to the ground by some kind of animal.

CONCLUSIONS The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted during 2006 in accordance with the SGS and HCGS Technical Specifications/ODCM. The LLD values required by the Technical Specifications/ODCM were achieved for this reporting period. 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/ODCM.

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. No unusual radiological characteristics were observed in the environs of SGS/HCGS during this reporting period. 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, we can conclude that the operation of the Salem and Hope Creek Stations had no significant impact on the radiological characteristics of the environs of that area.

18

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 SAMPLE SAMPLE 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: lSl, 2S2, 2S4, 3S1, 4S1, 5S1, 6S2, 7S1, 10S1, 11SI, 15S1, 16SI.

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, 10D1, 14D1, 15D1, 2E1, 3E1, 11E2, 12E1, 13E1, 16E1, IF1, 3F2, 4F2, 5F1, 6F1, 9FI, 10F2, lIFI, 13F2, 14F2, 14F3, 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, 14F4, 16F2, IG3, 10G1, 16GI, 3H1. and in one or 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 4 Samples - one sample from close to the Continuous sampler Gross Beta / weekly Site Boundary : 5S1 operation with Gamma isotopic analysis 3 Samples in different land based sectors: sample collection / quarterly composite 1F1, 2F6, 5D1. weekly or more frequently if 1 Sample from the vicinity of a community: Iodine-131 / weekly

b. Air Iodine required by dust 16EI.

loading 1 Sample from a control location, as for example 15-30 km distant and in the least t0 prevalent wind direction: 14G1.

C>

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

a. Milk Semi-monthly Gamma scan / semi-animals in each of 3 areas between 5 - 8 (when animals are on monthly km (3.12 - 5 miles) distant: 13E3, 14F4, 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 SAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY*

FREQUENCY OF ANALYSIS

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

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: 2F4, 2F9, 3F7, 6F2, 14F3, IG4, 2G2, 9G1, 3H5.

f. Fodder Crops Although not required by SGS/HCGS ODCM, samples of crops normally used as cattle Annually (at Gamma scan/on collection feed (silage-soybeans) were collected as harvest) management audit samples: 14F4, 3GI. Broad leaf vegetation (ornamental cabbage) was planted & collected in lieu of having a milk farm within 5 km of the Site "

1ODI, ISl, 15S1, 16S1

TABLE I (cont'd)

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

FREQUENCY OF ANALYSIS

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

a. Surface Water One sample outfall: 11Al Gamma scan/monthly One sample cross-stream (mouth of Tritium/monthly**

Appoquinimink River): 12C1 (2)

And an additional location in the Chesapeake & Delaware Canal: 16F1 t'J

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

c. Blue Crabs 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)

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: 12C1 annually collection One sample from outfall area: IIAl One sample from upstream area: 1F2 One sample from a control location: 12C1(2)

One sample from shoreline area: 6S2 One sample from Cooling Tower Blowdown: 15A1 And an additional location of south storm drain discharge line: 16A1

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

• • Tech Specs/ODCM require quarterly analysis but due to the 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 (ISl, 15S1, 16S1) and one across the river in Delaware (10DI).

(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 do 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 plus lower K40 and Beta Activity.

FIGURE 1 GROSS BETA ACTIVITY IN AIR PARTICULATE 1986 THROUGH 2006 1000 GROSS BETA INAIR PARTICULATE 1973 THROUGH 2006 1000 -- - I Chernobyl 04-26-86 100 10 100- 1976 1982 1988 1994 2000 2006 C.)

t~-;~ ~.

-~ £v~

a Iiiiii Jill III 10-Hope Creek Criticality 06-28-86 1 I I I I 111111 I I 1111111 I 11111111 I F I I I IIirr~IirrI I I I I I I I I 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 IQUARTERLY AVERAGEI

FIGURE 2 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1986 THROUGH 2006 inn AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1973 THROUGH 2006 10 -

8-6 - l 8.0 - 4 .

04-26-86 2 0

1976 1982 1988 1994 2000 2006 6.0 0

k) E E 4.0 Hope 06-28-86

"- OFF-SITE STATIONS 2.0 -

-- CONTROL STATIONS 0.0 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 IQUARTERLY AVERAGE

FIGURE 3 IODINE - 131 ACTIVITY IN MILK 1986 THROUGH 2006 20 IODINE-131 ACTMITY IN MILK 1973 THROUGH 2006 30.00 -r

ý&U.uu U.uu,.-p i1A A

.LIU!

Chemobyl 04-26-86 10- 1976 1982 1988 1994 2000 2006

-J ,eHope Creek Critl cality 06-28-86 0-

-1 0 . . . . . . . I..

. .. 1990 1I II I I I 199I iii IlI II I I I0 II0 I ll]tlllll* I I I 1990 1992 1994 1996 1998 2000 2002 2004 2006 1986 1988 I QUARTERLY AVERAGE I

FIGURE 4 GROSS BETA ACTIVITY IN SURFACE WATER 1986 THROUGH 2006 1000 GROSS BETA ACTIVITY INSURFACE WATER 1973 THROUGH 2006 Chernobyl 04 1976 1982 1988 1994 2000 2006 100-C0 CL 10-Hope Creek Criticality 06-28-86 1 i I I I I I I I I I I I III I I I I I I I I I I I I I 11 1 I 1 I I I I I 1 1I 1 1I I I I III 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 IQUARTERLY AVERAGEI

FIGURE 5 TRITIUM ACTIVITY IN SURFACE WATER 1986 THROUGH 2006 10,000 TRITIUM ACTIVITY IN SURFACE WATER 1973 Through 2006 10000 1000 100 10 1976 1982 1988 1994 2000 2006 1,000-Chernobyl 04 Effluent Discharge near time of sampling: 07-07-05

-J 100-Hope Creek Criticality 06-28-86 10 i I r H I I I I I I II I I I I II I Ii i I , , , I Il IlI I I I I I Il III l l 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 IQUARTERLY AVERAGE I

FIGURE 6 CESIUM-137 & COBALT-60 ACTIVITY INAQUATIC SEDIMENT 1986 THROUGH 2006 10000 CESIUM-137 & COBALT-60 ACTIVITY INAQUATIC SEDIMENT 1973 THROUGH 2006

- CS-137 10000

- CO-60 1000 100 1000 1976 1982 1988 1894 2000 2006

• • Chemobyl a.. 04-26-86 100 Hope Creek Criticality 06-26-86 10 . . .

I . . . . . . . I I i 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 ISEMI-ANNUAL AVERAGEI

REFERENCES

[1] 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] Public Service Enterprise Group . "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1982.

[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 2005".

[11] Maplewood Testing Services. "Quality Assurance Plan."

February, 2004

[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.

'[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.

30

REFERENCES (cont' d)

[15] Public Service Enterprise Group "Offsite Dose Calculation Manual"

- Hope Creek Generating Station.

[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.

31

APPENDIX A PROGRAM

SUMMARY

33

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, 2006 to DECEMBER 31, 2006 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 310 6.0 21 (258/258) 16E1 4.1 mi NNW 22 (52/52) 22 (52/52) 0 (10-3 pCi/m3) (11-34) (11-35)

(6-38) 14G1 11.8 mi WNW 22 (52/52)

(11-35)

Gamma Be7 24 2.0 80 (20/20) 2F6 7.3 mi NNE 82 (4/4) 80 (4/4) 0 (59-95) (66-94) (62-94) 5D1 3.5mi E 82 (4/4)

(59-95)

K-40 24 11.0 9.4 (15/20) 5S1 1 mi E 10 (3/4) 10 (2/4) 0 (2.6-14) (9.5-12) (10-10) 1F1 5.8 mi N 10 (3/4)

(6.1-14) 16E1 4.1 mi NNW 10 (3/4)

(8.3-12) 14G1 11.8 mi WNW 10 (2/4)

(10-10)

Air Iodine 1-131 310 9 <LLD <LLD <LLD 0 (10-3 pCi/m3)

II DIRECT Direct Radiation Quarterly 196 4.2 (172 /172) 2S2 0.4 mi NNE 5.9 (4/4) 4.3 (24/24) 0 (mrad/std. month) Badges (2.9-7.3) (5.2-7.3) (3.5-5.3)

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, 2006 to DECEMBER 31, 2006 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 Milk 1-131 80 0.4 <LLD <LLD <LLD 0 (pCi/L)

Gamma K-40 80 32 1330 (60 /60) 13E3 4.9 mi W 1350 (20/20) 1300 (20/20) 0 (1160-1450) (1160-1450) (1120-1420)

RA-NAT 80 8.5 11 (4/60) 14F4 7.6 mi WNW 13 (1/20) 7.8 (1/20) 0 (9-13) (13-13) (7.8-7.8)

ON Well Water Alpha 12 2.6 0.7 (1/12) 3E1 4.1 mi NE 0.7 (1/12) No Control 0 (pCi/L) (0.7-0.7) (0.7-0.7) Location Beta 12 1.0- 11 (12/12) 3E1 4.1 mi NE 11 (12/12) No Control 0 (9.7-12) (9.7-12) Location H-3 12 165 <LLD <LLD No Control 0 Location Gamma K-40 12 31 52 (5/12) 3E1 4,1mi NE 52 (5/12) No Control 0 (41-62) (41-62) Location RA-NAT 12 4.7 117 (12/12) 3E1 4,1mi NE 117 (12/12) No Control 0 (48-252) (48-252) Location Potable Water Alpha 24 1.5 0.7 (6/24) 2F3 8.0 mi NNE 0.7 (6/24) No Control 0 (pCi/L) (0.4-1.1) (0.4-1.1) Location Beta 24 1.0"** 3.5 (24/24) 2F3 8.0 mi NNE 3.5 (24/24) No Control 0 (2.5-4.8) (2.5-4.8) Location H-3 24 156 <LLD <LLD No Control 0 Location Gamma K-40 24 31 44 (17/24) 2F3 8.0 mi NNE 44 (17/24) No Control 0 (32-56) (32-56) Location

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, 2006 to DECEMBER 31, 2006 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 1-131 24 0.4 <LLD <LLD No Control 0 Potable Water Location (pCi/L) RA-NAT 24 4.7 20 (8/24) 2F3 8.0 mi NNE 20 (8/24) No Control 0 (4-74) (4-74) Location Fruit & Gamma Vegetables K-40 27 55 2100 (19/19) 2F9 7,5 mi NNE 2560 (3/3) 2090 (8/8) 0 (pCi/Kg-wet) (1310-2980) (2260-2980) (1640-2740)

RA-NAT 27 17 9.1 (1/19) 14F3 5.4 mi WNW 9.1 (1/3) LLD 0 (9.1-9.1) (9.1-9.1)

Fodder Crops Gamma (pCi/Kg-wet) Be-7 8 81 540 (5/6) 2G3 12 mi NNE 1480 (1/1) 968 (1/2) 0 (243-1480) (1480) (968-968)

K-40 8 32 6150 (6/6) 14F4 7.6 mi WNW 18100 (1/1) 9000 (2/2) 0 (3000-18100) (18100-18100) (2300-15700)

Cs-137 8 6 324 (3/6) 16S1 0.54 mi NNW 134 (1/1) <LLD 0 (111-134) (134-134)

IVAQUATIC Surface Water Beta 60 11 59 (45/48) 7E1 4.5 mi SE 102 (12/12) 46 (12/12) 0 (pCi/L) (5-243) (14-243) (6-96)

H-3 60 170 180 (1/48) 7E1 4.5 mi SE 180 (1/12) 180 (1/12) 0 (180) (180) (180)

Gamma K-40 60 31 78 (47/48) 7E1 4.5 mi SE 92 (12/12) 73 (12/12) 0 (29-144) (50-144) (49-112)

Th-232 60 9 <LLD <LLD 0 RA-NAT 60 4.7 <LLD <LLD 0

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, 2006 to DECEMBER 31, 2006 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 Blue Crabs Gamma (pCi/kg-wet) K-40 4 55 2845 (2/2) 11A1 0.2 mi. SW 2845 (2/2) 2825 (2/2) 0 (2690-3000) (2690-3000) (2490-3160)

Edible Fish Gamma (pCi/kg-wet) K-40 6 55 3443 (4/4) 12C1 2.5 mi. WSW 3590 (2/2) 3590 (2/2) 0 (3250-3640) (3430-3750) (3430-3750)

Sediment W (pCi/kg-dry) Gamma Be-7 14 127 631 (3/12) 16F1 6.9 mi. NNW 796 (2/2) <LLD 0 (303-904) (687-904)

K-40 14 55 8525 (12/12) 16F1 6.9 mi. NNW 16400 (2/2) 16200 (2/2) 0 (2410-17300) (15500-17300) (16100-16300)

Co-60 14 25 <LLD <LLD 0 Cs-137 14 54 55 (3/12) 16F1 6.9 mi. NNW 63 (2/2) <LLD 0 (39-72) (54-72)

RA-NAT 14 5.0 450 (12/12) 7E1 4.5 mi. SE 680 (2/2) 500 (2/2) 0 (178-689) (672-689) (487-522)

Th-232 14 8.1 668 (12/12) 16F1 6.9 mi. NNW 984 (2/2) 924 (2/2) 0 (317-1100) (868-1100) (865-982)

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 39

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 Leafy 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. 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; e.g., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the reference point:

S = On-site location 4-5 miles off-site A = 0-1 miles off-site 5-10 miles off-site B = 1-2 miles off-site 10-20 miles off-site C = 2-3 miles off-site >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 450 (north east) with respect to the reactor site at a radial distance of 4 to 5 miles off-site, (therefore, radial distance E). The number 1 indicates that this is sampling station #1 in that particular sector.

41

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. The Datem used was WGS 84.

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. SEC DEG. MIN. SEC I15 0.55mi. N of vent 39 - 28 - 16 75 13 IDM,VGT 2S2 0.4 mi. NNE of vent; Lamp Pole 65 Near HC Switch 39 07 75 00 IDM Yard 2S4 0.59 mi. NNE of vent 39 18 75 - 31 - 54 IDM 3S1 0.58 mi. NE of vent 39 08 75 - 31 - 41 IDM 4S1 0.60 mi. ENE of vent 39 02 75 - 31 - 33 IDM 5SI 1.0 mi. E of vent; site access road 39 38 75 - 31 - 08 AIO,APT, IDM 6S2 0.2 mi. ESE of vent; observation building 39 43 75 - 31 - 55 IDM,SOL,ESS 7S1 0.12 mi. SE of vent; station personnel gate 39 44 75 - 32 - 03 IDM 10SI 0.14 mi. SSW of vent; inlet cooling water bldg. 39 41 75 - 32 - 10 IDM 1I15 0.09 mi. SW of vent; service water inlet bldg. 39 43 75 - 32 - 12 IDM 15SI 0.57 mi. NW of vent 39 10 75 - 32 - 32 IDM,VGT 16S1 0.54 mi. NNW of vent 39 13 75 - 32 - 26 IDM,VGT 1 1A1 0.2 mi. SW of vent; outfall area 39 59 75 - 32 - 25 ECH,ESF,ESS,SWA 15A1 0.3 mi. NW of vent; cooling tower blowdown 39 67 75 - 32 - 19 ESS discharge line outfall 16A1 0.7 mi. NNW of vent; south storm drain discharge 39 24 75 - 32 - 58 ESS line 12C1 2.5 mi. WSW of vent; west bank of Delaware River 39 27 - 22 75 - 34 08 ECH,ESF,ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road 39 29 - 18 75 - 32 IDM 5D1 3.5 mi. E of vent; local farm 39 28 - 24 75 - 28 22 AIO,APT,IDM 1ODI 3.9 mi. SSW of vent; Taylor's Bridge Spur 39 24 - 37 75 - 33 44 IDM, SOL,VGT 14D1 3.4 mi. WNW of vent; Bay View, Delaware 39 29 - 02 75 - 35 31 IDM 15D1 3.8 mi. NW of vent; Rt. 9, Augustine Beach 39 30 - 08 75 - 35 02 IDM 2E1 4.4 mi. NNE of vent; local farm 39 31 - 23 75 - 30 26 IDM 4.1 mi. NE of vent; local farm 39 07 75 41 GAM, IDM,VGT,WWA,FPV 3E1

TABLE B-I (cont' d)

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. SEC DEG. MIN. SEC 7E1 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek 39 08 75 - 28 - 64 ESF,ESS,SWA 11E2 5.0 mi. SW of vent; Rt. 9 39 - 24 - 20 75 - 35 - 33 IDM 12E1 4.4 mi. WSW of vent; Thomas Landing 39 - 26 - 52 75 - 36 - 59 IDM 13E1 4.2 mi. W of vent; Diehl House Lab 39 - 27 - 59 75 - 36 - 44 IDM 13E3 4.9'mi. W of vent; Joseph Vari, Odessa, DE 39 - 27 - 17 75 - 37 - 30 MLK, FPV,VGT,SOL 16El 4.1 mi. NNW of vent; Port Penn 39 30 - 47 75 - 34 - 34 AIO,APT, IDM, SOL IF1 5.8 mi. N of vent; Fort Elfsborg 39 32 - 43 75 - 31 - 05 AIO,APT,IDM 1F2 7.1 mi. N of vent; midpoint of Delaware River 39 33 - 08 75 - 32 - 54 SWA 2F2 8.7 mi. NNE of vent; Corner of 5 th & Howell, 39 38 75 - 28 - 04 IDM Salem 2F3 8.0 mi. NNE of vent; Salem Water Company 39 40 75 - 27 18 PWR, PWT 2F4 6.3 mi. NNE of vent; local farm 39 - 33 - 21 75 - 30 33 FPV 2F5 7.4 mi. NNE of vent; Salem High School 39 27 75 - 28 31 IDM 2F6 7.3 mi. NNE of vent; Southern Training Center 39 43 75 - 28 48 AIO,APT, IDM 2F9 7.5 mi. NNE of vent; Tilbury Farms , 45 S. 39 - 33 - 5S 75 - 29 30 FPV, FPL,SOL Tilbury Rd, Salem 2Fl0 9.2 mi. NNE of vent; Lewis Messer Farm, 1027 39 - 35 - 35 75 - 29 - 35 FPV, FPL South Broadway (Rt. 49) Pennsville 3F2 5.1 mi. NE of vent;Hancocks Bridge Municipal Bld 39 25 75 - 27 - 36 IDM 3F3 8.6 mi. NE of vent; Quinton Township School 39 38 75 - 24 - 45 IDM 3F6 6.5 mi. NE of vent; #324 Salem/Hancocks Bridge 39 - 32 - 03 75 - 28 - 00 FPV, FPL Road 3F7 7.2 nal. NE of vent; Beasley Neck Road 39 - 32 - 07 75 25 - 46 FPV, FPL 4F2 6.0 n21. ENE of vent; Mays Lane, Harmersville 39 58 75 26 - 03 IDM 5F1 6.5 nU-. E of vent; Canton 39 22 75 24 - 59 IDM, SOL 6F1 6.4 nU-. ESE of vent; Stow Neck Road 39 24 75 25 - 09 IDM 7F2 9.1 na]-.SE of vent; Bayside, New Jersey 39 56 75 24 - 17 IDM 9F1 5.3 n11. S of vent; D.P.A.L. 48912-30217 39 - 23 - 03 75 32 - 32 IDM 10F2 5.8 na. SSW of vent; Rt. 9 39 01 75 34 - 09 IDM 1IF1 6.2 na. SW of vent; Taylor's Bridge Delaware 39 44 75 37 - 37 IDM 12Fl 9.4 mii. WSW of vent; Townsend Elementary School 39 47 75 41 - 18 IDM 13F2 6.5 ma. W of vent; Odessa, Delaware 39 18 75 39 - 21 IDM 9.3 mi. W of vent; Redding Middle School, 39 14 75 - 42 - 32 IDM 13F3 Middletown, Delaware

TABLE B-i (cont'd)

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. SEC DEG. MIN. SEC 13F4 9.8 mi. W of vent; Middletown, Delaware 39 51 75 43 - 07 IDM 14F2 6.6 mi. WNW of vent; Boyds Corner 39 - 30 - 00 75 38 - 59 IDM 14F3 5.4 mi. WNW of vent; local farm 39 - 29 - 33 75 37 - 55 FPV, FPL 14F4 7.6 mi. WNW of vent; local farm 39 - 30 - 44 75 40 - 52 MLK,VGT,SOL 15F3 5.4 mi. NW of vent 39 - 30 - 58 75 36 - 36 IDM 16F1 6.9 mi. NNW of vent; C&D Canal 39 - 33 - 55 75 34 - 25 ESS,SWA

-18 16F2 8.1 mi. NNW of vent; Delaware City Public School 39 - 34 75 35 - 25 IDM 1G3 19 mi. N of vent; N. Church St. Wilmington, Del 39 - 44 16 75 32 - 31 IDM (Old Swedish Church Yard Park) 1G4 10.8 mi. N of vent; (Dads Produce) Rte. 49, South 39 - 37 - 55 75 - 30 - 44 FPV Broadway, Pennsville 2G2 13.5 mi. NNE of vent; Moore's Market; 324 Pointers 39 - 38 - 19 75 10 FPV Auburn Road (Rt. 540), Salem, NJ 08079 2G3 12 mi. NNE of vent; Asa Caldwallader, Waldac Farms, 39 21 75 53 MLK,FPV,VGT Corner of Routes 540 & 45, Mannington, NJ 3G1 17 mi. NE of vent; Mr. Lee Williams Farm 39 35 - 56 75 - 16 - 47 IDM, MLK, VGT, SOL 10GI 12 mi. SSW of vent; Smyrna, Delaware 39 18 - 13 75 - 36 - 05 IDM 14G1 11.8 mi. WNW of vent; Rte. 286; Bethel Church Road; 39 31 - 18 75 - 46 - 30 AIO,APT, IDM Delaware 16G1 15 mi. NNW of vent; Across from Greater Wilmington 39 38 75 35 IDM Airport 3H1 32 mi. NE of vent; National Park, New Jersey 39 36 75 - 12 - 06 IDM 3H5 25 mi. NE of vent; Sorbello Girl's Market 39 - 41 - 02 75 - 12 - 23 FPL, FPV NOTE: All station locations are referenced to the midpoint of the two Salem Units' Vents. The coordinates of this location are: Latitude N 390 - 27' - 45.3" and Longitude W 750 - 32' - 09.7".

All Game (GAM), Vegetables(FPV & FPL) and Vegetation (VGT), are management audit samples. They are not required by the Salem & Hope Creek Stations' Tech Specs nor listed in the Station's ODCM. Vegetable samples are not always collected in consecutive years from the same farmer since they rotate the type of crop they grow.

MN? j3,1 I-ocp:Týotjs SpojpotslG ot4'st've 12 5

6 10 9 45

MAP B-2 SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM OFF-SITE SAMPLING LOCATION NNW rA-a. 1, AMD N I 2 N; 46

APPENDIX C DATA TABLES 47

APPENDIX C DATA TABLES Appendix C presents the analytical results of the 2006 Radio-logical Environmental Monitoring Program for the period of January 1 to December 31, 2006.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-I 2006 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates ............................................ 53 C-2 2006 Concentrations of Gross Beta Emitters in Air Particulates. 54 AIR IODINE C-3 2006 Concentrations of Iodine-131 in Filtered Air ................. 56 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-4 2006 Direct Radiation Measurements - Quarterly TLD Results ..... 58 TERRESTRIAL ENVIRONMENT MILK C-5 2006 Concentrations of Iodine-131 and Gamma Emitters in Milk... 59 WELL WATER C-6 2006 Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in Well Water ...................................... 61 C-7 2006 Concentrations of Gamma Emitters in Well Water ................ 62 49

DATA TABLES (cont'd.)

TABLE NO TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT (cont'd)

POTABLE WATER C-8 2006 Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in Raw and Treated Potable Waters ...................... 63 C-9 2006 Concentrations of Iodine 131 and Gamma Emitters in Raw and Treated Potable Water .......................................... 64 FOOD PRODUCTS C-10 2006 Concentrations of Gamma Emitters in Vegetables ................ 65 FODDER CROPS C-lb 2006 Concentrations of Gamma Emitters in Fodder Crops ............. 66 AQUATIC ENVIRONMENT SURFACE WATER C-12 2006 Concentrations of Gross Beta Emitters in Surface Water .... 67 C-13 2006 Concentrations of Gamma Emitters in Surface Water ............ 68 C-14 2006 Concentrations of Tritium in Quarterly Composites of Surface Wa ter ...... .... ..... ................... .... .... .. .. ............ 70 EDIBLE FISH C-15 2006 Concentrations of Gamma Emitters in Edible Fish ............... 71 BLUE CRABS C-16 2006 Concentrations of Gamma Emitters in Crabs ..................... 72 SEDIMENT C-17 2006 Concentrations of Gamma Emitters in Sediment .................. 73 50

DATA TABLES (cont'd.)

TABLE NO TABLE DESCRIPTION PAGE SPECIAL TABLES LLDs C-18 2006 PSE&G Maplewood Testing Services' LLDs for Gamma Spectroscopy .................................................. 74 51

Table C-1 2006 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-5S1 12/27/2005 to 3/27/2006 73+/-5 12+/-3 SA-APT-1 F1 12/27/2005 to 3/27/2006 75+/-4 11+/-2 SA-APT-2F6 12/27/2005 to 3/27/2006 79+/-5 3+/-0 SA-APT-5D1 12/27/2005 to 3/27/2006 80+/-5 7+/-3 SA-APT-16E1 12/27/2005 to 3/27/2006 76+/-4 10+/-3 SA-APT-14G1(C) 12/27/2005 to 3/27/2006 75+/-4 10+/-3 SA-APT-5S1 3/27/2006 to 6/26/2006 88+/-4 9+/-2 SA-APT-1 F1 3/27/2006 to 6/26/2006 83+/-5 6+/-3 SA-APT-2F6 3/27/2006 to 6/26/2006 94+/-4 10+/-2 SA-APT-5D1 3/27/2006 to 6/26/2006 95+/-5 11+/-3 SA-APT-16E 1 3/27/2006 to 6/26/2006 94+/-5 12+/-3 SA-APT-14G1(C) 3/27/2006 to 6/26/2006 94+/-5 10+/-4 SA-APT-5S1 6/26/2006 to 9/25/2006 93+/-5 <4 SA-APT-1 F1 6/26/2006 to 9/25/2006 86+/-4 <4 SA-APT-2F6 6/26/2006 to 9/25/2006 90+/-4 <2 SA-APT-5D1 6/26/2006 to 9/25/2006 93+/-5 <6 SA-APT-16E1 6/26/2006 to 9/25/2006 88+/-5 <6 SA-APT-14G1(C) 6/26/2006 to 9/25/2006 90+/-4 <4 SA-APT-5S1 9/25/2006 to 12/26/2006 64+/-4 10+/-3 SA-APT-1 F1 9/25/2006 to 12/26/2006 66+/-5 14+/-3 SA-APT-2F6 9/25/2006 to 12/26/2006 66+/-4 10+/-3 SA-APT-5D1 9/25/2006 to 12/26/2006 59+/-4 8+/-3 SA-APT-16E1 9/25/2006 to 12/26/2006 62+/-4 8+/-2 SA-APT-14G1(C) 9/25/2006 to 12/26/2006 62+/-4 <4 AVERAGE 80+/-24 8+/-7

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9.

(C) Control Station 53

TABLE C-2 2006 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 January 25+/-3 23+/-3 22+/-3 21+/-3 21+/-3 23+/-3 23+/-2 15+/-2 14+/-2 15+/-2 15+/-2 16+/-2 18+/-3 15+/-3 20+/-2 17+/-2 19+/-2 19+/-2 20+/-2 19+/-2 19+/-2 17+/-2 16+/-2 16+/-2 17+/-2 15+/-2 18+/-2 17+/-2 17+/-2 18+/-2 16+/-2 15+/-2 17+/-2 18+/-2 17+/-2 February 18+/-2 15+/-2 16+/-2 16+/-2 15+/-2 16+/-2 16+/-2 16+/-2 15+/-2 18+/-2 16+/-2 18+/-2 17+/-3 17+/-2 23+/-2 20+/-2 23+/-2 20+/-2 22+/-2 (1) 21+/-3 25+/-2 28+/-2 24+/-2 24+/-2 27+/-2 (1) 26+/-3 March 19+/-2 22+/-2 21+/-2 20+/-2 21+/-2 17+/-2 20+/-3 24+/-2 18+/-2 21+/-2 21+/-2 21+/-2 18+/-2 21+/-4 19+/-2 21+/-2 21+/-2 19+/-2 20+/-2 21+/-2 20+/-2 11+/-2 12+/-2 6+/-2 9+/-2 6+/-2 9+/-2 9+/-5 April 28+/-2 23+/-2 24+/-2 20+/-2 19+/-2 20+/-2 22+/-7 18+/-2 18+/-2 20+/-2 21+/-2 20+/-2 20+/-2 19+/-2 21+/-2 20+/-2 21+/-2 22+/-2 24+/-2 20+/-2 21+/-3 11+/-2 12+/-2 11+/-2 11+/-2 12+/-2 11+/-2 12+/-1 May 20+/-2 18+/-2 16+/-2 18+/-2 18+/-2 17+/-2 18+/-2 24+/-2 23+/-2 23+/-2 22+/-2 23+/-2 21+/-2 23+/-2 16+/-2 16+/-2 15+/-2 14+/-2 13+/-2 13+/-2 14+/-2 11+/-2 12+/-2 13+/-2 12+/-2 15+/-2 14+/-2 13+/-3 26+/-2 26+/-2 29+/-2 27+/-2 22+/-2 20+/-2 25+/-7 June 18+/-2 18+/-2 16+/-2 17+/-2 14+/-2 17+/-2 17+/-3 15+/-2 14+/-2 14+/-2 14+/-2 14+/-2 13+/-2 14+/-1 24+/-2 21+/-2 20+/-2 20+/-2 21+/-2 19+/-2 21+/-3 21+/-2 18+/-2 19+/-2 20+/-2 19+/-2 18+/-2 19+/-3

TABLE C-2 2006 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-11F1 SA-APT-2F6 SA-APT-5D1 SA-APT-5S1 AVERAGE July 19+/-2 18+/-2 17+/-2 18+/-2 18+/-2 16+/-2 18+/-2 21+/-2 22+/-2 23+/-2 23+/-2 23+/-2 18+/-2 22+/-4 28+/-2 24+/-2 22+/-2 26+/-2 23+/-2 22+/-2 24+/-5 26+/-2 28+/-2 26+/-2 29+/-2 28+/-2 26+/-2 27+/-3 31+/-2 31+/-2 32+/-3 30+/-3 29+/-3 30+/-3 30+/-3 August 35+/-3 34+/-2 37+/-3 33+/-2 38+/-3 35+/-3 35+/-4 33+/-2 25+/-2 17+/-2 20+/-2 17+/-2 17+/-2 22+/-13 28+/-2 25+/-2 31+/-2 32+/-2 30+/-2 32+/-2 30+/-5 34+/-2 30+/-2 28+/-2 28+/-2 33+/-3 28+/-2 30+/-5 September 13+/-2 11+/-2 15+/-2 15+/-2 14+/-2 14+/-2 14+/-3 27+/-3 26+/-2 16+/-2 22+/-2 20+/-3 23+/-2 22+/-8 15+/-2 14+/-2 15+/-2 17+/-2 14+/-2 14+/-2 15+/-2 22+/-2 23+/-2 19+/-2 23+/-2 22+/-2 22+/-2 22+/-3 October 22+/-2 21+/-2 21+/-2 23+/-2 21+/-2 23+/-2 22+/-2 22+/-2 21+/-2 20+/-2 22+/-2 21+/-2 20+/-2 21+/-2 28+/-2 28+/-2 28+/-2 27+/-2 26+/-2 24+/-2 27+/-3 21+/-2 19+/-2 19+/-2 22+/-2 21+/-2 21+/-2 21+/-2 13+/-2 15+/-2 13+/-2 14+/-2 12+/-2 13+/-2 13+/-2 November 26+/-2 28+/-2 27+/-2 26+/-2 26+/-2 25+/-2 26+/-2 32+/-3 31+/-3 30+/-3 32+/-3 28+/-3 31+/-3 31+/-3 28+/-3 21+/-3 24+/-3 24+/-3 22+/-3 22+/-3 23+/-5 20+/-2 20+/-2 17+/-2 17+/-2 17+/-2 18+/-2 18+/-3 December 26+/-2 24+/-2 24+/-2 27+/-2 23+/-2 26+/-3 25+/-3 34+/-2 28+/-2 32+/-3 31+/-3 30+/-3 28+/-3 30+/-5 31+/-2 26+/-2 26+/-2 27+/-2 25+/-2 26+/-2 27+/-4 23+/-2 22+/-2 24+/-2 22+/-2 22+/-2 26+/-2 23+/-3 AVERAGE 22+/-13 21+/-11 21+/-12 21+/-11 21+/-12 20+/-11 23+/-3 GRAND AVERAGE 21+/-12 (1) Power outage; results not included in averages. See program deviations.

TABLE C-3 2006 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10.3 pCilm 3

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

Control MONTH SA-AIO-14G1 SA-AIO-16E1 SA-AIO-1F1 SA-AIO-2F6 SA-AIO-5D1 SA-AIO-5S1 January <3.8 <3.6 <1.8 <2.3 <4 <1.8

<1.9 <4.6 <2.4 <5 <1.8 <9.5

<2.1 <3.6 <3.4 <4 <3.1 <3.7

<3.7 <2.6 <2.3 <3.4 <2 <4.3

<3.8 <5.5 <4.9 <2.2 <1.7 <2.8 February <3.7 <2.8 <1,6 <2.6 <5.7 <3.1

<3.3 <4.2 <5.3 <2.8 <2.2 <3.4

<3.2 <3.6 (1)

<2.3 <2.9 <3.2

<3.1 <3.4 <2.7 (1)

<4.2 <4.3 March <6.3 <3.4 <3.6 <4.6 <2 <3

<4.5 <5.2 <4.4 <2.3 <2.6 <3

<1.3 <2.7 <1.8 <2.3 <3.5 <3.3

<4.1 <5.2 <5.7 <5.2 <2.4 <4.3 April <4 <3 <6.6 <3 <2 <1.6

<1.7 <3.6 <2.5 <1.5 <3.6 <1.7

<4.7 <1.9 <4.7 <1.5 <2.1 <3.8

<3.9 <4.3 <1.6 <3.2 <4.6 <5.8 May <6.3 <3.1 <4.8 <3.8 <2.6 <5.5

<2.6 <6.8 <4.1 <4 <2.3 <3.6

<3.2 <3.9 <1.8 <3.9 <1.7 <2.5

<3.8 <3.7 <4.1 <1.7 <1.8 <2.6

<2.4 <1.9 <4.6 <3.2 <4.6 <2.1 June <2.2 <6.3 <3.4 <1.1 <3.5 <1.8

<3.1 <2.3 <8.9 <5.7 <4.6 <3.4

<2.2 <3.2 <5.7 <2.1 <3.3 <3.5

<7.4 <4.2 <3.4 <2.4 <3.9 <4.6

TABLE C-3 2006 CONCENTRATIONS OF IODINE-131* IN3 FILTERED AIR Results in Units of 103- pCilm

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

Control MONTH SA-AIO-14G1 SA-AIO-16E1 SA-AIO-1F1 SA-AIO-2F6 SA-AIO-5D1 SA-AIO-5S1 July <9.2 <4.5 <6.4 <3.2 <2.6 <2.5

<2.4 <2 <2.4 <3.8 <1.4 <2.6

<3.6 <7.2 <2.3 <2.2 <2.1 <1.9

<3.8 <3.9 <2.6 <3.6 <3.4 <3

<5.9 <4 <4.1 <4.1 <2.4 <5.7 August <3.1 <3.1 <5.2 <4.6 <1.3 <5.2

<2.1 <7.6 <2.8 <5.1 <4 <8.6

<3.9 <3.8 <5.5 <2.4 <5 <4.7

<4 <2.6 <4.4 <4.7 <3.9 <2.8 September <2.6 <1.8 <4.8 <2.4 <2.7 <2.5

<2.4 <3.9 <2.9 <5.3 <5.3 <3.9

<1.7 <5 <5.1 <2.1 <4.4 <5

<3 <5.9 <3.9 <2.4 <2.3 <1.9 October <6.4 <3 <4.1 <5.4 <2.3 <1.4

<2.3 <2.8 <2 <1.5 <4.2 <2.9

<2.6 <1.6 <2.8 <3.5 <5.8 <3.5

<6.3 <2.4 <5.6 <3.2 <6 <2.6

<2.5 <2.3 <8.4 <1.3 <7.2 <2.4 November <3.4 <4.9 <7.3 <2.3 <2.1 <8.3

<2.5 <2.9 <4 <3.7 <4.6 <4

<1.6 <1.6 <2.3 <2.2 <2.5 <2.4

<3.8 <5.4 <6.1 <1.2 <2.5 <1.9 December <1.9 <1.9 <3.1 <5.5 <3.6 <3.6

<1.9 <2.6 <2.3 <4.1 <5 <3.2

<1.6 <2.9 <6 <2.3 <5.9 <3.4

<1.2 <1.6 <2.8 <3 <1.9 <2.5

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

(1) Power Outage: See program deviations.

TABLE C-4 2006 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma JAN APR JUL OCT QTR STATION to to to to ELEMENTS ID MAR JUN SEP DEC AVG SA-IDM-2S2 7.3+/-0.5 5.2+/-0.4 5.8+/-0.5 5.2+/-0.6 5.9+/-2.0 SA-IDM-5S1 3.5+/-0.3 3.5+/-0.4 3.7+/-0.4 3.4+/-0.3 3.5+/-0.3 SA-IDM-6S2 5.1+/-0.5 4.9+/-0.4 5.4+/-0.5 5.0+/-0.5 5.1+/-0.4 SA-IDM-7S1 5.6+/-0.5 5.5+/-0.4 6.0+/-1.2 5.6+/-0.5 5.7+/-0.4 SA-IDM-10S1 3.6+/-0.4 3.6+/-0.4 3.7+/-0.4 3.7+/-0.3 3.7+/-0.1 SA-IDM-11S1 3.6+/-0.5 3.2+/-0.4 3.4+/-0.4 3.6+/-0.4 3.4+/-0.4 SA-IDM-4D2 4.2+/-0.3 4.3+/-0.5 4.6+/-0.5 4.2+/-0.3 4.3+/-0.4 SA-IDM-5D1 3.7+/-0.4 3.8+/-0.4 4.1+/-0.4 3.8+/-0.3 3.9+/-0.4 SA-IDM-10D1 4.4+/-0.5 4.6+/-0.5 4.9+/-0.5 4.4+/-0.4 4.6+/-0.5 SA-IDM-14D1 3.8+/-0.3 4.0+/-0.4 4.1+/-0.5 3.9+/-0.5 4.0+/-0.2 SA-IDM-15D1 4.4+/-0.4 4.7+/-0.5 4.9+/-0.5 4.4+/-0.4 4.6+/-0.5 SA-IDM-2E1 3.8+/-0.6 4.1+/-0.6 4.2+/-0.5 4.0+/-0.4 4.0+/-0.3 SA-IDM-3E1 3.4+/-0.4 3.6+/-0.4 3.6+/-0.5 3.7+/-0.6 3.6+/-0.3 SA-IDM-9F1 4.4+/-0.4 4.9+/-0.4 5.1+/-0.4 4.5+/-0.3 4.7+/-0.7 SA-IDM-11E2 4A4+/-0.3 4.5+/-0.4 4.6+/-0.7 4.5+/-0.4 4.5+/-0.2 SA-IDM-12E1 4.3+/-0.3 4.5+/-0.5 4.8+/-0.5 4.4+/-0.4 4.5+/-0.4 SA-IDM-13E1 3,4+/-0.2 3.6+/-0.4 3.9+/-0.4 3.6+/-0.4 3.6+/-0.4 SA-IDM-16E1 4.2+/-0.4 4.4+/-0.4 4.6+/-0.5 4.4+/-0.6 4.4+/-0.4 SA-IDM-1 F1 5.4+/-0.5 5.9+/-0.5 5.8+/-0.5 5.4+/-0.5 5.6+/-0.5 SA-IDM-2F2 3,4+/-0.2 3.8+/-0.5 3.9+/-0.4 3.7+/-0.4 3.7+/-0.4 SA-IDM-2F5 4.2+/-0.4 4.5+/-0.4 4.5+/-0.5 4.2+/-0.4 4.4+/-0.4 SA-IDM-2F6 3.7+/-0.4 4.1+/-0.4 4.2+/-0.6 4.0+/-0.4 4.0+/-0.5 SA-IOM-3F2 3.6+/-0.5 3.9+/-0.4 3.8+/-0.5 3.8+/-0.3 3.8+/-0.3 SA-IDM-3F3 3.6+/-0.3 3.8+/-0.5 3.9+/-0.6 3.6+/-0.3 3.7+/-0.3 SA-IDM-4F2 3.4+/-0.4 4.0+/-0.4 3.6+/-0.4 3.4+/-0.4 3.6+/-0.5 SA-IDM-5F1 3.7+/-0.4 4.0+/-0.4 4.2+/-0.4 3.8+/-0.4 3.9+/-0.4 SA-IDM-6F1 3.1+/-0.3 3.3+/-0.3 3.2+/-0.4 3.3+/-0.3 3.2+/-0.2 SA-IDM-7F2 2.9+/-0.4 3.0+/-0.4 3.0+/-0.3 3.1+/-0.4 3.0+/-0.2 SA-IDM-10F2 4.4+/-0.4 4.6+/-0.6 4.7+/-0.4 4.4+/-0.5 4.5+/-0.3 SA-IDM-11F1 4.6+/-0.4 4.7+/-0.4 5.0+/-1.0 5.1+/-1.0 4.8+/-0.5 SA-IDM-12F1 4.3+/-0.4 4.3+/-0.3 4.5+/-0.4 4.2+/-0.3 4.3+/-0.2 SA-IDM-13F2 4.2+/-0.5 4.1+/-0.4 4.5+/-0.6 4.2+/-0.4 4.3+/-0.3 SA-IDM-13F3 4.4+/-1.0 4.4+/-0.5 4.4+/-0.4 4.1+/-0.3 4.3+/-0.3 SA-IDM-13F4 4.1+/-0.4 4.1+/-0.5 4.4+/-0.4 4.3+/-0.3 4.2+/-0.2 SA-IDM-14F2 4.4+/-0.4 4.7+/-0.7 4.8+/-0.5 4.5+/-0.4 4.6+/-0.4 SA-IDM-15F3 4.8+/-0.5 5.1+/-0.7 5.1+/-0.5 4.9+/-0.3 5.0+/-0.3 SA-IDM-16F2 3.9+/-0.4 4.1+/-0.5 4.0+/-0.5 3.9+/-0.3 4.0+/-0.2 SA-IDM-1G3 (C) 5.2+/-0.4 5.2+/-0.4 5.3+/-0.7 5.1+/-0.4 5.2+/-0.2 SA-IDM-3G1 (C) 4.4+/-0.4 4.5+/-0.4 4.7+/-0.9 4.3+/-0.4 4.5+/-0.3 SA-IDM-10GI(C) 4.3+/-0.4 4.5+/-0.4 4.5+/-0.4 4.2+/-0.3 4.4+/-0.3 SA-IDM-16G1(C) 3.7+/-0.5 4.3+/-0.9 4.1+/-0.6 3.8+/-0.4 4.0+/-0.5 SA-IDM-3H1 (C) 3.5+/-0.4 3.6+/-0.5 3.6+/-0.3 3.5+/-0.3 3.5+/-0.1 SA-IDM-1S1 4.4+/-0.5 4.1+/-0.5 4.3+/-0.6 4.0+/-0.3 4.2+/-0.4 SA-IDM-3S1 3.5+/-0.3 3.4+/-0.4 3.5+/-0.3 3.3+/-0.4 3.4+/-0.2 SA-IDM-2S4 4.0+/-0.4 4.2+/-0.4 4.4+/-0.5 4.0+/-0.4 4.1+/-0.4 SA-IDM-4S1 4.0+/-0.3 3.9+/-0.4 4.1+/-0.4 3.9+/-0.3 4.0+/-0.2 SA-IDM-15S1 3.6+/-0.2 3.6+/-0.4 3.7+/-0.5 3.4+/-0.4 3.6+/-0.2 SA-IDM-16S1 4.3+/-0.6 4.0+/-0.4 4.6+/-0.4 4.0+/-0.5 4.2+/-0.5 SA-IDM-14G1(C) 4.4+/-0.6 4.6+/-0.6 4.7+/-0.5 4.4+/-0.5 4.5+/-0.3 AVERAGE 4.1+/-1.5 4.2+/-1.2 4.4+/-1.3 4.1+/-1.1 GRAND AVG 4.2+/-1.3

• The standard month = 30.4 days.

• • Quarterly Element TLD results by AREVA - NP Environmental Laboratory.

(C) Control Station 58

TABLE C-5 2006 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 RANAT SA-MLK-2G3 1/3/2006 1/4/2006 <0.2 1330 +/-80 <2.7 SA-MLK-13E3 1/2/2006 1/312006 <0.2 1300 +/-70 <4.3 SA-MLK-14F4 1/2/2006 1/3/2006 <0.3 1270 +/-70 <2.1 SA-MLK-3G1 (C) 1/2/2006 1/3/2006 <0.2 1120 +/-70 <2.7 SA-MLK-2G3 2/5/2006 2/6/2006 <0.2 1290 +/-70 <3.7 SA-MLK-13E3 2/6/2006 2/7/2006 <0.1 1360 +/-80 <2.2 SA-MLK-14F4 2/5/2006 2/6/2006 <0.3 1280 +/-70 <3.3 SA-MLK-3G1 (C) 2/5/2006 2/6/2006 <0.3 1240 +/-70 <2.7 SA-MLK-2G3 3/5/2006 3/6/2006 <0.2 1450 +/-80 <2.6 SA-MLK-13E3 3/5/2006 3/6/2006 <0.2 1430 +/-80 <2.7 SA-MLK-14F4 3/5/2006 3/6/2006 <0.3 1280 +/-70 <3.6 SA-MLK-3G1 (C) 3/5/2006 3/6/2006 <0.3 1210 +/-60 <3.3 SA-MLK-2G3 4/3/2006 4/4/2006 <0.4 1360 +/-80 <4.8 SA-MLK-13E3 4/2/2006 4/3/2006 <0.3 1260 +/-80 <3.2 SA-MLK-14F4 4/2/2006 4/3/2006 <0.3 1330 +/-80 <2.9 SA-MLK-3G1 (C) 4/2/2006 4/3/2006 <0.2 1270 +/-70 <3.7 SA-MLK-2G3 4/16/2006 4/17/2006 <0.2 1330 +/-70 <3.7 SA-MLK-13E3 4/16/2006 4/17/2006 <0.3 1430 +/-70 <3.7 SA-MLK-14F4 4/16/2006 4/17/2006 <0.3 1380 +/-80 <3.3 SA-MLK-3G1 (C) 4/16/2006 4/17/2006 <0.2 1250 +/-70 <2.7 SA-MLK-2G3 5/1/2006 5/2/2006 <0.2 1310 +/-70 9 +/-3 SA-MLK-13E3 5/1/2006 5/2/2006 <0.3 1450 +/-80 <3.4 SA-MLK-14F4 5/1/2006 5/2/2006 <0.4 1340 +/-80 <2.8 SA-MLK-3G1 (C) 5/1/2006 5/2/2006 <0.2 1270 +/-70 <4.4 SA-MLK-2G3 5/14/2006 5/15/2006 <0.2 1310 +/-70 <4.1 SA-MLK-13E3 5/14/2006 5/15/2006 <0.2 1330 +/-80 <2.9 SA-MLK-14F4 5115/2006 5/16/2006 <0.2 1410 +/-80 <4.8 SA-MLK-3G1 (C) 5/14/2006 5/15/2006 <0.2 1330 +/-70 <3.3 SA-MLK-2G3 6/4/2006 6/5/2006 <0.2 1320 +/-70 <4 SA-MLK-13E3 6/4/2006 6/5/2006 <0.3 1290 +/-70 <2.7 SA-MLK-14F4 6/4/2006 6/5/2006 <0.2 1280 +/-70 <2.4 SA-MLK-3G1 (C) 6/4/2006 6/5/2006 <0.2 1380 +/-70 <3.2 SA-MLK-2G3 6/19/2006 6/20/2006 <0.2 1360 +/-80 <5.9 SA-MLK-13E3 6/19/2006 6/20/2006 <0.2 1380 +/-80 <2.9 SA-MLK-14F4 6/19/2006 6/20/2006 <0.3 1250 +/-70 <2.8 SA-MLK-3G1 (C) 6/20/2006 6/21/2006 <0.2 1350 +/-70 <4 SA-MLK-2G3 7/9/2006 7/10/2006 <0.2 1350 +/-70 <3.7 SA-MLK-13E3 7/9/2006 7/10/2006 <0.3 1380 +/-80 <2.7 SA-MLK-14F4 7/9/2006 7/10/2006 <0.2 1300 +/-70 <3.4 SA-MLK-3G1 (C) 7/9/2006 7/10/2006 <0.2 1420 +/-70 <2.9 SA-MLK-2G3 7/23/2006 7/24/2006 <0.3 1260 +/-70 <7.4 SA-MLK-1 3E3 7/23/2006 7/24/2006 <0.2 1160 +/-60 <3.2 SA-MLK-14F4 7/23/2006 7/24/2006 <0.3 1390 +/-70 <3.4 SA-MLK-3G1 (C) 7/24/2006 7/25/2006 <0.3 1370 +/-70 <8.5 59

TABLE C-5 2006 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 RANAT SA-MLK-2G3 8/7/2006 8/8/2006 <0.2 1330 +/-80 10 +/-3 SA-MLK-1 3E3 8/6/2006 8/7/2006 <0.2 1330 +/-80 <2.6 SA-MLK-14F4 8/6/2006 8/7/2006 <0.2 1340 +/-70 <2.9 SA-MLK-3G1 (C) 8/7/2006 8/8/2006 <0.2 1320 +/-70 <3.4 SA-MLK-2G3 8/21/2006 8/22/2006 <0.2 1260 +/-70 10 +/-3 SA-MLK-13E3 8/20/2006 8/21/2006 <0.2 1370 +/-80 <2.9 SA-MLK-14F4 8/20/2006 8/21/2006 <0.2 1360 +/-80 <3.3 SA-MLK-3G1 (C) 8/21/2006 8/22/2006 <0.2 1270 +/-70 <3.3 SA-MLK-2G3 9/5/2006 9/6/2006 <0.2 1300 +/-80 <5.9 SA-MLK-13E3 9/4/2006 9/5/2006 <0.2 1400 +/-70 <3.4 SA-MLK-14F4 9/4/2006 9/5/2006 <0.2 1240 +/-70 <2.5 SA-MLK-3G1 (C) 9/5/2006 9/6/2006 <0.2 1380 +/-70 <3.5 SA-MLK-2G3 9/18/2006 9/19/2006 <0.2 1310 +/-70 <4.8 SA-MLK-13E3 9/17/2006 9/18/2006 <0.2 1350 +/-70 <2.8 SA-MLK-14F4 9/17/2006 9/18/2006 <0.2 1320 +/-80 <2.8 SA-MLK-3G1 (C) 9/18/2006 9/19/2006 <0.2 1250 +/-70 <3.5 SA-MLK-2G3 10/1/2006 10/2/2006 <0.3 1300 +/-80 <4.6 SA-MLK-13E3 10/1/2006 10/2/2006 <0.2 1330 +/-70 <3.8 SA-MLK-14F4 10/1/2006 10/2/2006 <0.3 1250 +/-70 13 +/-3 SA-MLK-3G1 (C) 10/11/2006 10/2/2006 <0.2 1340 +/-70 8 +/-2 SA-MLK-2G3 10/15/2006 10/16/2006 <0.2 1310 +/-70 <3.2 SA-MLK-13E3 10/15/2006 10/16/2006 <0.2 1310 +/-70 <3.1 SA-MLK-14F4 10/15/2006 10/16/2006 <0.3 1350 +/-70 <4.6 SA-MLK-3G1 (C) 10/15/2006 10/16/2006 <0.2 1310 +/-70 <3.7 SA-MLK-2G3 11/5/2006 11/6/2006 <0.3 1290 +/-70 <3.2 SA-MLK-13E3 11/5/2006 111/6/2006 <0.2 1300 +/-70 <3.1 SA-MLK-14F4 11/5/2006 11/6/2006 <0.2 1320 +/-70 <3.6 SA-MLK-3G1 (C) 11/5/2006 11/6/2006 <0.2 1300 +/-80 <2.9 SA-MLK-2G3 11/19/2006 11/20/2006 <0.3 1260 +/-70 <3.1 SA-MLK-13E3 11/20/2006 11/21/2006 <0.2 1450 +/-80 <2.2 SA-MLK-14F4 11/20/2006 11/21/2006 <0.2 1290 +/-70 <3.1 SA-MLK-3G1 (C) 11/19/2006 11/20/2006 <0.3 1260 +/-70 <2.9 SA-MLK-2G3 12/4/2006 12/5/2006 <0.2 1350 +/-70 <3.5 SA-MLK-13E3 12/3/2006 12/4/2006 <0.3 1400 +/-80 <3.2 SA-MLK-14F4 12/3/2006 12/4/2006 <0.2 1250 +/-80 <2.6 SA-MLK-3G1 (C) 12/4/2006 12/5/2006 <0.2 1380 +/-70 <3.4 AVERAGE - 1320 +/-120 -

• lodine-131 results are corrected for decay to midpoint of collection period & analyzed to a sensitivity of 1.0 pCi/L.

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-19 Monthly sample collected during Jan., Feb., March and Dec., when animals are not on pasture.

(C) Control Station 60

TABLE C-6 2006 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma SAMPLING GROSS GROSS STATION ID DATE ALPHA BETA TRITIUM SA-WWA-3E1 1/31/2006 <0.9 11+/-0.9 <152 SA-WWA-3E1 2/28/2006 <0.9 10+/-0.8 <151 SA-WWA-3E1 3/27/2006 <1.8 10+/-0.8 <152 SA-WWA-3E1 4/24/2006 <0.9 9.7+/-0.8 <153 SA-WWA-3E1 5/31/2006 <1.2 10+/-0.8 <151 SA-WWA-3E1 6/27/2006 <1.9 11+/-1 <159 SA-WWA-3E1 7/25/2006 <1.6 11+/-0.9 <154 SA-WWA-3E1 8/28/2006 0.7+/-0.6 11+/-0.9 <164 SA-WWA-3E1 9/25/2006 <1.2 11+/-0.9 <165 SA-WWA-3E1 10/30/2006 <1.4 11+/-0.9 <159 SA-WWA-3E1 11/27/2006 <1.3 11+/-0.9 <164 SA-WWA-3E1 12/26/2006 <0.8 12+/-0.9 <161 AVERAGE 11+/-1 -

61

TABLE C-7 2006 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 1/31/2005 48+/-17 135+/-5 SA-WWA-3E1 2/22/2005 <12 108+/-5 SA-WWA-3E1 3/28/2005 <6.3 164+/-5 SA-VWVA-3E1 4/25/2005 <31 87+/-4 SA-WWA-3E1 5/31/2005 <19 123+/-4 SA-WWA-3E1 6/27/2005 <19 48+/-3 SA-WWA-3E1 7/25/2005 <18 94+/-4 SA-WWA-3E1 8/29/2005 <16 135+/-4 SA-WWA-3E 1 9/26/2005 62+/-25 100+/-3 SA-WVA-3E1 10/24/2005 41+/-13 70+/-5 SA-WWA-3E1 11/28/2005 55+/-25 252+/-8 SA-WWA-3E1 12/27/2005 54+/-21 91+/-5 AVERAGE 117+/-106

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9.

62

TABLE C-8 2006 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS AND TRITIUM IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING GROSS GROSS TYPE PERIOD ALPHA BETA TRITIUM RAW 1/1-31/2006 0.6+/-0.4 3.3+/-0.6 <147 TREATED 1/1-31/2006 <0.5 3.1+/-0.6 <148 RAW 2/1-28/2006 0.8+/-0.4 3.2+/-0.6 <147 TREATED 2/1-28/2006 <0.5 2.8+/-0.6 <152 RAW 3/1-31/2006 1.1+/-0.6 3.1+/-0.6 <155 TREATED 3/1-31/2006 <0.9 2.5+/-0.6 <152 RAW 4/1-30/2006 0.7+/-0.4 2.9+/-0.5 <151 TREATED 4/1-30/2006 <0.4 3+/-0.5 <154 RAW 5/1-31/2006 <0.7 3.5+/-0.6 <147 TREATED 5/1-31/2006 <1.1 3.7+/-0.6 <148 RAW 6/1-30/2006 <0.8 3.5+/-0.6 <154 TREATED 6/1-30/2006 <1.1 3.5+/-0.7 <157 RAW 7/1-31/2006 <0.6 3.4+/-0.6 <160 TREATED 7/1-31/2006 <0.9 4.3+/-0.7 <157 RAW 8/1-31/2006 0.4+/-0.3 2.9+/-0.6 <150 TREATED 8/1-31/2006 <0.3 4+/-0.6 <150 RAW 9/1-30/2006 <0.4 3.5+/-0.6 <163 TREATED 9/1-30/2006 <0.8 4.4+/-0.6 <162 RAW 10/1-31/2006 <0.6 3.2+/-0.6 <159 TREATED 10/1-31/2006 <0.7 3.5+/-0.6 <148 RAW 11/1-30/2006 <0.5 4.8+/-0.7 <182 TREATED 11/1-30/2006 <0.6 3.8+/-0.6 <177 RAW 12/1-31/2006 0.5+/-0.3 3.2+/-0.6 <169 TREATED 12/1-31/2006 <0.3 3.9+/-0.6 <156 AVERAGE RAW 0.7+/-0.4 3.4+/-1 TREATED - 3.5+/-1.2 GRAND AVERAGE 3.5+/-1.1 63

TABLE C-9 2006 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING <---GAMMA EMITTERS --->

TYPE PERIOD 1-131 K-40 RA-NAT RAW 1/1-31/2006 <0.2 46+/-17 <2 TREATED 1/1-31/2006 <0.2 40+/-13 16+/-3 RAW 2/1-28/2006 <0.2 34+/-13 <2 TREATED 2/1-28/2006 <0.2 45+/-15 22+/-2 RAW 3/1-31/2006 <0.3 <20 <2 TREATED 3/1-31/2006 <0.3 <24 4+/-1 RAW 4/1-30/2006 <0.2 <15 <2 TREATED 4/1-30/2006 <0.2 <22 <2 RAW 5/1-31/2006 <0.2 <19 74+/-3 TREATED 5/1-31/2006 <0.2 <26 11+/-2 RAW 6/1-30/2006 <0.4 42+/-16 <2 TREATED 6/1-30/2006 <0.2 51+/-13 <1 RAW 7/1-31/2006 <0.2 34+/-11 <2 TREATED 7/1-31/2006 <0.1 51+/-14 18+/-2 RAW 8/1-31/2006 <0.2 33+/-14 <2 TREATED 8/1-31/2006 <0.2 <22 <2 RAW 9/1-30/2006 <0.2 45+/-15 <2 TREATED 9/1-30/2006 <0.2 56+/-13 11+/-2 RAW 10/1-31/2006 <0.1 50+/-14 <2 TREATED 10/1-31/2006 <0.2 49+/-17 <5 RAW 11/1-30/2006 <0.1 32+/-14 5+/-2 TREATED 11/1-30/2006 <0.2 53+/-17 <2 RAW 12/1-31/2006 <0.3 40+/-15 <2 TREATED 12/1-31/2006 <0.2 51+/-17 <2 AVERAGES RAW - 34+/-23 -

TREATED 41+/-27 8+/-15 GRAND AVERAGE 37+/-25 -

• Iodine-131 analyzed to a sensitivity of 1.0 pCi/L.

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9.

64

TABLE C-10 2006 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 RANAT SA-FPV-2F9 5/1/2006 Asparagus 2440+/-215 <12 SA-FPV-3F6 5/1/2006 Asparagus 2150+/-208 <12 SA-FPV-2G2 (C) 5/22/2006 Asparagus 2190+/-190 <8 AVERAGE 2260+/-310 -

SA-FPL-2F9 7/18/2006 Cabbage 2980+/-188 <8.1 SA-FPL-2F10 7/18/2006 Cabbage 2210+/-129 <5.1 SA-FPL-3F6 7/18/2006 Cabbage 2870+/-176 <9.1 SA-FPL-3H5 (C) 7/18/2006 Cabbage 2740+/-135 <5.8 AVERAGE 2700+/-680 -

SA-FPV-2F4 7/18/2006 Corn 2450+/-182 <8.5 SA-FPV-2F9 7/18/2006 Corn 2260+/-175 <8.3 SA-FPV-2F10 7/18/2006 Corn 2610+/-178 <7.5 SA-FPV-3F6 7/18/2006 Corn 2290+/-167 <8.6 SA-FPV-2G2 (C) 7/18/2006 Corn 2190+/-173 <6.5 SA-FPV-3H5 (C) 7/18/2006 Corn 2420+/-167 <13 SA-FPV-14F3 7/19/2006 Corn 2170+/-175 <7.3 AVERAGE 2340+/-320 -

SA-FPV-2F10 7/18/2006 Peppers 1650+/-163 <10 SA-FPV-3F6 7/18/2006 Peppers 1600+/-154 <11 SA-FPV-3F7 7/18/2006 Peppers 1630+/-167 <7.4 SA-FPV-2G2 (C) 7/18/2006 Peppers 1740+/-168 <9.3 SA-FPV-3H5 (C) 7/18/2006 Peppers 1640+/-155 <7.7 SA-FPV-14F3 7/19/2006 Peppers 1310+/-135 <10 AVERAGE 1600+/-290 -

SA-FPV-2F4 7/18/2006 Tomatoes 1670+/-142 <7.8 SA-FPV-2F10 7/18/2006 Tomatoes 2000+/-164 <12 SA-FPV-3F6 7/18/2006 Tomatoes 1890+/-140. <8.1 SA-FPV-3F7 7/18/2006 Tomatoes 1740+/-136 <6.4 SA-FPV-2G2 (C) 7/18/2006 Tomatoes 1910+/-150 <8.3 SA-FPV-3H5 (C) 7/20/2006 Tomatoes 1910+/-150 <8.8 SA-FPV-14F3 7/19/2006 Tomatoes 2060+/-162 9.1+/-6 AVERAGE 1880+/-270 -

GRAND AVERAGE 2100+/-840 -

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9 (C) Control Station 65

TABLE C-ll 2006 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 Cs-1 37 SA-VGT-10D1 12/27/2006 Ornamental Cabbage 417+/-97 3000+/-230 117+/-15 SA-VGT-1 5S1 12/15/2006 Ornamental Cabbage 290+/-84 4180+/-300 111+/-15 SA-VGT-16S1 12/15/2006 Ornamental Cabbage 266+/-87 4340+/-280 134+/-18 SA-VGT-1 S1 (1) (1) (1) (1) (1)

AVERAGE 320+/-160 3840+/-1460 120+/-20 SA-VGT-2G3 10/15/2006 Silage 1480+/-92 3560+/-190 <3 SA-VGT-3G1 (C) 10/15/2006 Silage 968+/-66 2300+/-140 <5 SA-VGT-13E3 10/12/2006 Silage 243+/-48 3710+/-170 <4.4 AVERAGE 900+/-1240 3190+/-1550 SA-VGT-14F4 12/5/2006 Soybeans <80 18100+/-350 <5.8 SA-VGT-3G1 (C) 12/15/2006 Soybeans <66 15700+/-290 <4 AVERAGE 16900+/-3390

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9.

(C) Location 3G1 is the Control Station.

(1) Not Available. See program deviations.

66

TABLE C-12 2006 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SA-SWA-12C1 ----- STATION ID ---------------------------

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

January 15+/-7 12+/-7 <11 12+/-7 39+/-8 20+/-26 February 5+/-2 6+/-2 5+/-2 <3 14+/-3 7+/-8 March 82+/-5 62+/-4 45+/-4 22+/-3 92+/-5 61+/-57 April 88+/-7 74+/-7 60+/-6 53+/-6 112+/-8 78+/-47 May 63+/-6 52+/-6 36+/-5 29+/-5 128+/-10 61+/-79 June 81+/-7 52+/-6 41+/-5 17+/-4 127+/-10 64+/-85 July 29+/-5 11+/-4 11+/-4 <6 44+/-6 24+/-32 August 133+/-11 96+/-9 70+/-7 46+/-6 243+/-17 118+/-154 September 100+/-9 62+/-7 50+/-6 33+/-5 160+/-12 81+/-101 October 74+/-7 51+/-6 18+/-4 20+/-4 103+/-9 53+/-72 November 59+/-6 42+/-5 25+/-5 20+/-4 88+/-8 47+/-56 December 40+/-5 30+/-5 19+/-4 12+/-4 69+/-7 34+/-45 AVERAGE 64+/-74 46+/-55 33+/-42 23+/-30 102+/-122 GRAND AVERAGE 53+/-90

TABLE C-13 2006 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 1/6/2006 60+/-13 <3.7 <4.7 SA-SWA-7E1 1/6/2006 62+/-17 <2 <4 SA-SWA-11A1 1/6/2006 53+/-12 <2.2 <4 SA-SWA-12C1(C) 1/6/2006 52+/-14 <1.6 <3.8 SA-SWA-16F1 1/6/2006 82+/-15 <2.1 <4.4 SA-SWA-1 F2 2/7/2006 81+/-18 <2.1 <4.1 SA-SWA-7E1 2/7/2006 53+/-18 <1.8 <5 SA-SWA-11A1 2/7/2006 49+/-12 <2.4 <3.5 SA-SWA-12C1(C) 2/7/2006 49+/-14 <1.7 <4.1 SA-SWA-16F1 2/7/2006 39+/-12 <1.6 <4.8 SA-SWA-1F2 3/6/2006 63+/-15 <1.4 <4.2 SA-SWA-7E1 3/6/2006 97+/-19 <1.7 <4 SA-SWA-11A1 3/6/2006 99+/-18 <2.1 <4 SA-SWA-12C1(C) 3/6/2006 112+/-17 <2.2 <8.6 SA-SWA-16F1 3/6/2006 33+/-15 <1.6 <4 SA-SWA-1 F2 4/5/2006 70+/-14 <1.7 <4.2 SA-SWA-7E1 4/5/2006 144+/-20 <1.7 <4.7 SA-SWA-11A1 4/5/2006 123+/-22 <1.5 <5.1 SA-SWA-12C1(C) 4/5/2006 72+/-18 <2 <4 SA-SWA-16F1 4/5/2006 64+/-18 <1.9 <4.2 SA-SWA-1F2 5/4/2006 64+/-15 <1.8 <4.4 SA-SWA-7E1 5/4/2006 62+/-19 <2 <4.6 SA-SWA-11A1 5/4/2006 55+/-14 <4.5 <5 SA-SWA-12C1(C) 5/4/2006 56+/-17 <1.6 <4.5 SA-SWA-16F1 5/4/2006 74+/-16 <1.4 <4.4 SA-SWA-1 F2 6/5/2006 43+/-12 <1.5 4+/-0 SA-SWA-7E1 6/5/2006 133+/-23 <2.9 <4.4 SA-SWA-11A1 6/5/2006 71+/-18 <1.7 <4.6 SA-SWA-12C1(C) 6/5/2006 52+/-16 <1.8 <4.7 SA-SWA-16F1 6/5/2006 78+/-16 <2.6 <4.4 SA-SWA-1 F2 7/7/2006 29+/-12 <3.4 <6 SA-SWA-7E1 7/7/2006 50+/-18 <1.6 <4.5 SA-SWA-11A1 7/7/2006 63+/-13 <4.1 <4.6 SA-SWA-12C1(C) 7/7/2006 60+/-14 <1.8 <4 SA-SWA-16F1 7/7/2006 52+/-13 <2.1 <4.6 68

TABLE C-13 2006 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 8/9/2006 94+/-15 <1.8 <4.7 SA-SWA-7E1 8/9/2006 133+/-23 <3.1 <4 SA-SWA- 11A1 8/9/2006 118+/-18 <1.8 <4.6 SA-SWA-12C1(C) 8/9/2006 105+/-16 <2.1 <4.1 SA-SWA-16F1 8/9/2006 69+/-17 <3.6 <4.2 SA-SWA-1 F2 9/6/2006 66+/-15 <1.8 <5.5 SA-SWA-7E1 9/6/2006 119+/-21 <1,9 <4.1 SA-SWA-11A1 9/6/2006 121+/-2 <1.9 <7.5 SA-SWA-12C1(C) 9/6/2006 85+/-17 <2.2 <4 SA-SWA-16F1 9/6/2006 90+/-16 <2.6 <4.3 SA-SWA-1F2 10/2/2006 73+/-14 <1.8 <4.2 SA-SWA-7E1 10/2/2006 84+/-22 <1.6 <4.8 SA-SWA-11A1 10/2/2006 106+/-19 <1.8 <3.4 SA-SWA-12C1(C) 10/2/2006 76+/-15 <2 <2.8 SA-SWA-16F1 10/2/2006 71+/-19 <2 <5.4 SA-SWA-1F2 11/6/2006 69+/-15 <1.9 <3.4 SA-SWA-7E1 11/6/2006 106+/-22 <2.2 <7.6 SA-SWA-11A1 11/6/2006 94+/-17 <2.1 <4.6 SA-SWA-12C1(C) 11/6/2006 97+/-18 <1.8 <4.1 SA-SWA-16F1 11/6/2006 57+/-17 <1.6 <3.9 SA-SWA-1F2 12/5/2006 <58 <1.6 <3.7 SA-SWA-7E1 12/5/2006 63+/-17 <1.6 <3.9 SA-SWA-11A1 12/5/2006 75+/-14 <1.9 <4 SA-SWA-12C1(C) 12/5/2006 61+/-15 <1.7 <4.5 SA-SWA-16F1 12/5/2006 <47 <2 <4.1 AVERAGE 76+/-53 -

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9 C) Control Station 69

TABLE C-14 2006 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

< SAMPLING.S.-W-lA-WA-i----2C---- ------------------- >

STATION ID -------------------------------------------

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

January <150 <150 <150 <150 <150 February <160 <150 <150 <160 <160 March <150 <150 <150 <150 <150 April <150 <150 <150 <160 <150 May <160 <150 <160 <150 180+/-90 0

June <150 <150 <150 <150 <150 July <150 <160 <150 <170 <160 August <150 <150 <150 <150 <150 September <160 180+/-100 <160 <160 <150 October <165 <160 <160 <160 <160 November <160 <160 <160 <160 <160 December <170 <170 <170 <170 <170

TABLE C-15 2006 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 SA-ESF-7E1 5/3-4/2006 3640+/-210 SA-ESF-11A1 5/3-4/2006 3450+/-200 SA-ESF-12C1 (C) 5/3-4/2006 3750+/-200 AVERAGE 3610+/-300 SA-ESF-7E1 8/29-10/02/2006 3250+/-180 SA-ESF-11A1 8/29-10/02/2006 3430+/-180 SA-ESF-12C1 (C) 8/29-10/02/2006 3430+/-180 AVERAGE 3370+/-210 GRAND AVERAGE 3490+/-350

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-19 (C) Control Station 71

TABLE C-16 2006 CONCENTRATIONS OF GAMMA EMITTERS* IN CRABS Results in Units of pCi/kg (wet) +/- 2 sigma GAMMA EMITTER SAMPLING (FLESH)

STATION ID PERIOD K-40 SA-ECH-11A1 7/11-18/2006 2690+/-170 SA-ECH-12C1 (C) 7/11-18/2006 2490+/-170 AVERAGE 2590+/-280 SA-ECH-11A1 9/11-15/2006 3000+/-190 SA-ECH-12C1 (C) 9/11-15/2006 3160+/-180 AVERAGE 3080+/-230 GRAND AVERAGE 2840+/-600

• All other gamma emitters searched for were <LLD; Typical LLDs are given in Table C-19.

(C) Control Station 72

TABLE C-17 2006 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-1 37 RA NAT Th-232 SA-ESS-6S2 7/11/2006 303+/-53 2410+/-136 <3.8 <6.8 184+/-10 327+/-25 SA-ESS-7E1 7/7/2006 <75 12900+/-373 <17 <34 672+/-32 975+/-57 SA-ESS- 11A1 7/7/2006 <78 8400+/-284 <4.6 <8.1 374+/-19 612+/-49 SA-ESS-1 5A1 7/7/2006 <65 3470+/-167 <3.4 <10 231+/-10 317+/-28 SA-ESS-16A1 7/7/2006 <59 7960+/-297 <18 <12 650+/-23 949+/-66 SA-ESS-12C1(C) 7/7/2006 <109 16300+/-431 <12 <7.2 522+/-22 982+/-53 SA-ESS-16F1 7/7/2006 687+/-105 15500+/-414 <25 54+/-12 518+/-28 868+/-60 AVERAGE 9600+/-11100 - 450+/-390 720+/-600 SA-ESS-6S2 10/30/2006 <109 3030+/-148 <3.2 <6.1 178+/-11 348+/-28 SA-ESS-7E1 10/27/2006 <96 12500+/-346 <20 <23 689+/-20 844+/-49 SA-ESS-1 WA 10/27/2006 <53 5760+/-225 <2.7 <5.1 382+/-13 525+/-43 SA-ESS-1 5A1 10/27/2006 <51 8350+/-276 <12 39+/-12 494+/-21 758+/-52 SA-ESS-16A1 10/27/2006 <120 4720+/-194 <9.7 <5.7 383+/-19 612+/-36 SA-ESS-12C1(C) 10/27/2006 <127 16100+/-415 <10 <9 487+/-18 865+/-53 SA-ESS-16F1 10/27/2006 904+/-150 17300+/-487 <12 72+/-13 668+/-25 1100+/-84 AVERAGE 9700+/-11300 470+/-350 720+/-500 GRAND AVERAGE 9600+/-10800 460+/-360 720+/-530

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-1 9 (C) Control Station 73

TABLE C-18 2006 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 1OO 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 2.0 19 32 NA-22 0.48 3.2 4.8 K-40 11 31 32 CR-5" 1.5 12 17 MN-:)4 0.32 2.3 4.0 CO-58 0.27 2.0 3.1 FE-59 0.96 4.8 13 CO-60 0.28 1.9 7.0 ZN-65 0.59 3.7 12 ZRNM-*,-95 0.38 3.9 4.5 MO-99 30 265 35 RU-103 0.32 1.9 2.1 RU- 106 1.9 13 33 AG-110M 0.54 2.5 3.8 SB-125 0.58 6.4 4.9 TE-129M 10 93 163 1-131 9.2 0.41 2.8 0.36 2.1 0.41 TE- 132 1.4 15 2.9 BA-133 0.21 1.4 3.5 CS-134 0.24 1.2 2.1 CS-136 0.40 2.4 3.5 CS-137 0.29 2.4 3.9 BALA- 140 1.5 8.4 13 CE- 141 0.21 2.7 5.6 CE- 144 0.76 9.3 16 RA-NAT 0.94 4.7 8.5 TH-232 1.1 8.7 19 74

TABLE C-18 (Cont'd) 2006 MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROSCOPY SAMPLE TYPE: <----------

FOOD PRODUCTS ----------

> <-VEGETATION-> <-----

GAME -----

> <-FISH & CRAB-> <--SEDIMENT-->

GAMMA SCAN GAMMA SCAN GAMMA SCAN GAMMA SCAN GAMMA SCAN GAMMA SCAN ACTIVITY: pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg DRY GEOMETRY: 3.5 LITER 500 ml 3.5 LITER 500 ml 500 ml 500 ml COUNT TIME: 500 M[NS 500 MINS 500 MINS 500 MINS 500 MINS 500 MINS DELAY TO COUNT: 3 DAYS 3 DAYS 7 DAYS 5 DAYS 5 DAYS 30 DAYS NUCLIDES BE-7 65 60 81 60 127 NA-22 9 14 10 11 29 K-40 32 55 32 55 55 CR-51 60 40 33 45 121 MN-54 7.5 7.4 3.0 8.8 21 CO-58 8 7.9 7.7 10 15 FE-59 23 22 21 20 43 CO-60 10 14 13 15 25 ZN-65 28 27 14 16 22 ZRNB-95 22 12 20 9 20 MO-99 255 213 96 282 87000 RU- 103 7.6 5.7 4.2 4.6 12 RU- 106 83 45 46 62 127 AG-110M 10 11 16 13 17 SB- 125 17 18 12 14 28 TE- 129M 249 369 178 171 378 1-131 9 7 4.2 7.4 92 TE-132 21 12 8.5 16 4720 BA-133 7.4 6.2 3.7 4.5 8.7 CS- 134 8.4 4.9 4.1 4.1 10 CS-136 10 6.4 6.1 7.0 42 CS-137 4.9 8.0 6 9 54 BALA-140 34 31 25 29 174 CE-141 8.3 6.9 5.9 4.6 20 CE- 144 44 25 29 26 48 RA-NAT 17 13 8 8 5.0 TH-232 85 49 26 48 8.1 75

APPENDIX D

SUMMARY

OF RESULTS FROM ANALYTICS AND ENVIRONMENTAL RESOURCE ASSOCIATES INTERLABORATORY COMPARISON PROGRAMS 77

APPENDIX D

SUMMARY

OF RESULTS FOR ANALYTICS AND ENVIRONMENTAL RESOURCE ASSOCIATES INTERLABORATORY COMPARISON PROGRAM Appendix D presents a summary of the analytical results for the 2006 Analytics and Environmental Resource Associates (ERA)

Interlaboratory Comparison Program.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE D-1 Gross Alpha and Gross Beta Emitters in Water and Gross Beta in Air Particulates 81 D-2 Gamma Emitters in Water and Milk ................. 82 Gamma Emitters in Air and Soil ................... 83 D-4 Tritium Analysis in Water and Iodine Analysis in Air and Water ................................. 84 79

TABLE D-1 RESULTS FOR ANALYTICS AND ERA INTERLABORATORY COMPARISON PROGRAM Gross Alpha and Gross Beta Emitters In Water (pCi/L) and Gross Beta in Air Particulate Filter (pCi/mr3 )

ANALYTICS/ERA Acceptance

• ANALYTICS Criteria DATE PSEG PSEG ERA Lower & Upper MM-YY SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 06-2006 ANL-WAT-AB638 Water Alpha 4 6+/- 6 64 51 76 Beta 182+/-5 169 135 203 06-2006 ANL-APT-B651 APT Beta 71+/-0.4" 67 53 80 07-2006 ERA-WAT-AB642 Water Alpha 6.2+/-1.2 10 1 19 Beta 8. 1+/-0. 6 8.9 0.2 18 09-2006 ANL-WAT-AB646 Water Alpha 80+/-5 69 56 83 Beta 273 218 328 304+/-8 10-2006 ERA-WAT-AB653 Water Alpha 22+/-2 29 16 41 Beta 21 12 30 19+/-2 12-2006 ANL-WAT-AB647 Water Alpha 80+/-4 75 60 90 Beta 25 9+/-5 225 180 270 12-2006 ANL-APT-B654 APT Beta 97+/-2 88 70 106

• s.d. - one standard deviation of three individual analytical results 81

TABLE D-2 RESULTS FOR ANALYTICS AND ERA INTERLABORATORY COMPARISON PROGRAM Gamma Emitters In Water and Milk (pCi/L)

ANALYTICS/ERA Acceptance

• ANALYTICS Criteria DATE PSEG PSEG ERA Lower & Upper MM-YY SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 03-2006 ANL-WAT-G632 Water Cr-51 235+/-5 234 187 281 Mn-54 82+/-2 78 62 94 Fe-59 75+/-5 72 58 87 Co-60 105+/-2 107 86 128 Zn-65 150+/-3 148 118 178 1-131 64+/-1 67 54 81 Cs-134 94+/-1 101 81 121 Cs-137 76+/-3 74 59 89 Ce-141 88+/-2 87 69 104 Co-58 88+/-1 88 70 105 03-2006 ANL-MLK-G630 Milk Cr-51 277+/-9 280 224 336 Mn-54 95+/-0.7 93 75 112 Fe-59 92+/-2 87 69 104 Co-60 125+/-2 128 102 154 Zn-65 174+/-5 176 141 211 1-131 73+/-1 78 62 94 Cs-134 113+/-1 120 97 145 Cs-137 90+/-2 89 71 107 Ce-141 102+/-1 104 83 125 Co-58 106+/-2 105 84 126 07-2006 ERA-WAT-G637 Water Ba-133 85+/-1 88 73 103 Co-60 101+/-1 100 91 108 Cs-134 53+/-0.5 54 45 63 Cs-137 235+/-4 238 217 259 Zn-65 126+/-3 121 100 142 12-2006 ANL-WAT-G649 Water Cr-51 394+/-23 421 337 505 Mn-54 112+/-4 108 86 130 Fe-59 84+/-4 77 62 93 Co-60 258+/-14 273 219 327 Zn-65 166+/-5 159 127 191 Cs-134 131+/-5 143 114 172 Cs-137 231+/-10 230 184 276 Ce-141 274+/-10 286 229 343 Co-58 81+/-4 81 65 98

• s.d. - one standard deviation of three individual analytical results 82

TABLE D-3 RESULTS OF ANALYTICS AND ERA INTERLABORATORY COMPARISON PROGRAM Gamma Emitters In Soil (pCi/kg-dry) and Air Particulate Samples (pCi/m3)

ANALYTICS/ERA Acceptance ANALYTICS Criteria DATE PSEG PSEG ERA Lower & Upper MM-YY SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 03-2006 ANL-SOL-G633 Soil Cr-51 4 08+/-6 402 322 482 Mn-54 148+/-5 134 107 161 Co-58 151+/-2 150 120 180 Fe-59 141+/-8 124 99 149 Co-60 191+/-0 183 146 220 Zn-65 275+/-13 253 202 304 Cs-137 2 63+/-3 227 182 272 Ce-141 15 9+/- 6 149 119 179 Cs-134 163+/-10 173 138 208 06-2006 ANL-APT-G6407 APT Cr-51 20 3+/- 4 193 155 231 Mn-54 127+/-6 109 87 131 Co-60 101+/-1 96 76 115 Fe-59 86+/-2 70 56 83 Zn-65 163+/-7 138 110 166 Cs-134 83+/-2 94 75 113 Cs-137 99+/-4 87 70 105 Ce-141 151+/- 6 136 109 163 Co-58 81+/-4 74 60 89 09-2006 ANL-SOL-G644 Soil Cr-51 4 3 9+/-20 423 339 507 Mn-54 190+/-11 169 135 203 Co-58 167 +/-4 164 131 197 Fe-59 84+/-3 66 53 79 Co-60 2 02+/-3 201 161 241 Zn-65 224 +/-13 218 174 262 Cs-137 37 7+/- 63 4 362 290 434 Ce-141 12 9+/-4 129 105 153 Cs-134 12 5+/-12 128 102 154

• s.d. - one standard deviation of three individual analytical results 83

TABLE D-4 RESULTS OF ANALYTICS AND ERA INTERLABORATORY COMPARISON PROGRAM Tritium Analysis In Water (pCi/L)

Iodine-131 Analysis In Water (pCi/L)

And Iodine In Air Samples (pCi/m 3 )

ANALYTICS/ERA Acceptance

• ANALYTICS Criteria DATE PSEG PSEG ERA Lower & Upper MM-YY SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 03-2006 ANL-WAT-H631 Water H-3 4330+/-21 4210 3370 5050 03-2006 ANL-AIO-I634 AIO 1-131 85+/-2 85 68 103 04-2006 ERA-WAT-H636 Water H-3 8404+/-123 8130 6722 9538 04-2006 ERA-WAT-1635 Water 1-131 20+/-1 19 14 24 06-2006 ANL-AIO-I639 AIO 1-131 67+/-0. 6 66 53 79 06-2006 ANL-WAT-H641 Water H-3 5931+/-95 6000 4800 7200 09-2006 ANL-AIO-I643 AIO 1-131 94+/-1 92 74 110 09-2006 ANL-WAT-H645 Water H-3 11250+/-349 11000 8798 13202 10-2006 ERA-WAT-I652 Water 1-131 24+/-2 22 17 27 12-2006 ANL-AIO-I648 AIO 1-131 83+/-1 86 69 102 12-2006 ANL-WAT-H650 Water H-3 15107+/-768 14800 11842 17758

• s.d. - one standard deviation of three individual analytical results 84

APPENDIX E SYNOPSIS OF LAND USE CENSUS 85

APPENDIX E SYNOPSIS OF 2006 LAND USE CENSUS A land use census was conducted 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 50m2 (500ft 2 )

producing broad leaf vegetation, in each of the 16 meteorological sectors.

Tabulated below are the results of these surveys:

Milk Nearest Vegetable Animal Residence Garden Meteorological July, 2006 July, 2006 July, 2006 Sector km (miles) km (miles) km (miles)

N None None None NNE None None None NE None 6.4 (4.0) None ENE None 5.8 (3.6) None E None 8.7 (5.4) None ESE None None None SE None None None SSE None None None S None None None SSW None 5.5 (3.4) None SW None 6.9 (4.3) None WSW None 7.1 (4.4) None 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 87

APPENDIX F RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM (RGPP) 89

Table Of Contents I. Summary and Conclusions ................................... 94 II. Introduction .............................................. 97 A. Objectives of the RGPP ................................ 97 B. Implementation of the Objectives ...................... 98 C. Program Description .................................. 108 D. Characteristics of Tritium (H-3) ..................... 110 III. Program Description ..................................... 113 A. Sample Analysis ...................................... 113 B. Data Interpretation .......................... ........ 114 C. Background Analysis .................................. 116 IV. Results and Discussion ................................... 121 A. Groundwater Results .................................. 121 D. Leaks, Spills, and Releases .......................... 123 E. Trends ............................................... 124 F. Investigations ....................................... 124 G. Projected RGPP Activities ............................ 124 91

Table Of Contents (cont)

Tables 1 Hope Creek Monitoring Well Construction Details 2 Salem Monitoring Well Construction Details 3 Relevant Groundwater Screening Criteria 4 Groundwater Tritium Analytical Results 5 Groundwater Elevations 6 Hope Creek RGPP Systems 7 Salem RGPP Systems Figures 1 Hope Creek Well Locations and Station Layout 2 Salem Well Locations and Station Layout 3 Potentiometeric Surface Contour Map 4 Stratigraphy Column 92

I. Summary and Conclusions This is the first annual report on the status of the Radiological Groundwater Protection Program (RGPP) conducted at Salem and Hope Creek Stations. As such, this report contains significant background information and programmatic descriptions. Subsequent annual reports will reflect changes to this program and provide the data and information representative of the reporting year.

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 releases of radionuclides and not previously identified. The RGPP is a voluntary program implemented by PSEG in conjunction with industry initiatives and guidance that is designed to complement the existing Radiological Environmental Monitoring Program and Radioactive Effluent Release Report programs. This report covers the RGPP groundwater samples collected from the environment in 2006. The monitoring was conducted in two phases, Phase 1 monitoring was part of the comprehensive study that included potential source identification and areal hydrogeology, and installation of monitoring wells to encompass reasonable groundwater release pathways based on the evaluation. The results of Phase 1 were made available to state and federal regulators as well as the public in the Salem Generating Station and Hope Creek Generating Station Site Investigation Reports (SIR). Phase 2 of the RGPP was conducted by PSEG and contract laboratory personnel to follow up of Phase 1 monitoring and continue the long-term RGPP monitoring program. All analytical results from both the Phase 1 and Phase 2 monitoring are included in Table 2.

93

Salem Generating Station identified a release from the Unit 1 Spent Fuel Pool in 2002, and has implemented the Remedial Action Work Plan (RAWP) reviewed by the USNRC and approved by the New Jersey Department of Environmental Protection (NJDEP) Bureau of Nuclear Engineering (BNE) . Only tritium activity was identified from this release, neither Strontium nor plant-related gamma emitters were identified in monitoring well water samples. In accordance with the RAWP, a Groundwater Recovery System (GRS) has been installed and is in operation to remove the tritiated water and maintain containment of the contaminated plume to prevent migration to the plant boundary. The GRS is fully discussed in the quarterly Remedial Action Plan Reports (RAPR) provided to the regulatory agencies and the information is not included in the RGPP. Five specific monitoring wells are included in both the GRS monitoring and RGPP to ensure program comprehensiveness.

In assessing all the data gathered for this report, it was concluded that the operation of Salem and Hope Creek Stations has had no adverse radiological impact on the environment from unmonitored or unplanned releases of radionuclides to groundwater. There are no know active releases into the groundwater at Salem or Hope Creek Stations.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Environmental Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater samples. In the case of tritium, PSEG specified that it's laboratories achieve a lower limit of detection significantly lower than that required by federal regulation.

Strontium-89/90 was not detected at a concentration greater 94

than the LLD of 2.0 picoCuries per liter (pCi/L) in any of the groundwater samples tested.

Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 9 of the 26 groundwater monitoring locations. The tritium concentrations were all below the Environmental LLD specified in the ODCM. Most of the tritium that was detected in groundwater at Salem is believed to be the result of isolated historical releases and at Hope Creek an investigation is underway to aggressively ensure the limited data set does not indicate an increasing trend or an unmonitored release pathway to the groundwater. To facilitate trending, additional samples are being collected to ensure the trend analysis has a robust basis.

95

This page intentionally blank.

96

II. Introduction PSEG's Salem and Hope Creek generating stations are located in a flat, largely undeveloped region of southern New Jersey. The Stations are bordered on the west and south by the Delaware River Estuary and on the east and north by extensive marshlands. The Stations both obtain cooling water from and discharge cooling water to the Delaware River. The Stations are underlain by over 1,000 feet of interlayered sand, silt and clay. The uppermost 55 feet of these geologic formations does not transmit appreciable quantities of groundwater. The Stations draw potable water from wells greater than 300 feet below ground surface.

There are no off-site wells within at least one mile of the site. The nearest potable supply well is located 3.65 miles away in the state of Delaware.

Investigation into a release of tritiated water from the spent fuel pool at Salem was initiated in 2002. The mechanism for the release and pathway taken by the tritiated water have been identified and controlled. Groundwater remediation began in 2004 with the Groundwater Recovery System (GRS) and is ongoing. Tritium has not migrated to the property boundary nor to geologic formations deeper that the shallow water-bearing unit on site, and there is no complete exposure pathway to humans or biota resulting from this release. The GRS and related results are reported separately to the regulatory agencies and are not included in this report.

A. Objective of the RGPP The long-term objectives of the RGPP are as follows:

1. Identify suitable locations to monitor and evaluate 97

potential impacts from station operations before significant radiological impact to the environment or potential drinking water sources can occur.

2. Understand the local hydrogeologic 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 and radiological analysis of water from selected locations.

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives The objectives identified have been implemented at Salem and Hope Creek Generating Stations as discussed below:

1. PSEG personnel performed a systematic analysis of all structures, systems and system components that handle plant-related radionuclides to identify which of these posed a potential risk with respect to the release of radiological contaminants to the environment. The program was designed to ensure that PSEG fully understands the safety and reliability of the equipment 98

that stores, processes, and conveys radioactively contaminated water, and to satisfy PSEG, its stakeholders, and the surrounding community that PSEG operates and maintains station equipment and systems with a high degree of integrity.

The systems risk evaluation was performed to determine which systems at the stations have the most significant potential to release radionuclides to the environment.

Each of the 97 Salem and 137 Hope Creek facility systems was analyzed by the system engineers and system managers to identify and rate the potential risk of release of radionuclides. Detailed evaluation criteria, including the potential exposure for all piping, tanks, valves, sumps, and water bodies, were used to evaluate each system and system component. The system components were rated based upon: 1) the degree of severity of a potential release, based upon concentration, flow rate or volume, if a release occurred from the specified component, 2) likelihood of the occurrence of such a failure, and 3) the ability to detect the release should such a failure occur. All systems and components that screened in were targeted as potential sources during development of the monitoring program. There were 16 Salem systems and 24 Hope Creek systems that screened in for further evaluation. These systems are identified in Tables 6 and 7.

2. PSEG Salem and Hope Creek Generating Stations performed evaluations and measurements to determine the geological and hydrogeological characteristics applicable to meeting the objective of the RGPP. The following sections provide information regarding the setting of the stations, including land use, environmental setting, precipitation and drainage, local geology and local hydrogeology.

99

a. Land Use PSEG Nuclear LLC owns and/or controls an approximately 740-acre area of Artificial Island that includes the stations. This area contains administrative and support facilities used by both the Salem and Hope Creek Stations, including the Salem and Hope Creek Switch Yards, Administrative Support Buildings and 367 acres of uncommitted, undeveloped land. The zoning classification for the stations is industrial. The land adjacent is zoned for industrial and residential or agricultural use.

b. Environmental Setting Beginning in the early twentieth century, The United States Army Corps of Engineers (USACE) created the land upon which the stations are located. So-called Artificial Island was created by depositing hydraulic dredge spoils from a shipping channel in the Delaware River Estuary into a diked area established around a natural sand bar in the estuary. The stations are located on that portion of Artificial Island bordering the Delaware Estuary. The entire area of Artificial Island is within the Delaware River's estuarine zone, as defined by the Delaware River Basin Commission (Zone 5). In the vicinity of the stations, water in the estuary is tidal and brackish, with the salinity varying with both the tides and seasonally from almost freshwater to almost saltwater. Prior to construction, the property known as Artificial Island was undeveloped, low-lying land.

100

c. Topography and Station Drainage The topography at the stations is essentially flat with limited local relief. The average elevation of the site is approximately 9 ft above mean sea level (msl) . Stormwater is managed in accordance with the New Jersey Pollutant Discharge Elimination System (NJPDES) permits and Storm Water Pollution Prevention Plan. Stormwater is collected in storm drains and routed to the Delaware River for discharge. Stormwater from the major petroleum storage handling areas is routed to an oil/water separator prior to discharge.

d. Climate and Precipitation Salem County is located in southwestern New Jersey. The county's climate is considered to be humid and temperate, as the climate in this county is readily influenced by its proximity to the Delaware Bay. Coastal storms are not uncommon in this region and can produce high winds and heavy rainfall, which can result in wind damage and flooding in low-lying areas.

Wind direction in this region is dependent upon the season; during the summer, winds are typically from the southwest while during the winter winds are commonly from the northwest. Temperatures vary by season and the maximum expected high temperature for a given year is 100 degrees Fahrenheit, while the minimum expected yearly low temperature is minus 2 degrees Fahrenheit. The average annual precipitation total is 39.9 inches.

101

e. Geology The stations are located in the Atlantic Coastal Plain Physiographic Province. This area is characterized by relatively flat to gently undulating terrain, underlain by unconsolidated sediments that increase in thickness to the southeast. These sediments range in age from Holocene to Cretaceous (0 to 146 million years old), are primarily comprised of clay, silt, sand, and gravel, and are generally classified as continental, coastal, or marine in nature.

Published geologic mapping indicates that the basement rock beneath these sediments (in the area of the stations) is metamorphic schist of the Wissahickon Formation, which is Pre-Cambrian in age (570 to 900 million years old). The Atlantic Coastal Plain Physiographic Province, which is characterized by a southeasterly dipping wedge of unconsolidated sediments consisting of clays, silts, sands, and gravels that thicken in a seaward direction. The Cretaceous and Tertiary age sediments that overlie the bedrock strike northeast-southwest and dip gently to the southeast between 10 and 60 feet per mile.

The unconsolidated overburden at the Salem and Hope Creek portions of Artificial Island consist of approximately 25 feet of dredge spoils, engineered fill material, tidal marsh deposits and riverbed deposits. The engineered fill, composed mainly of silt, silty clay, sand, and gravel, was used to replace the dredge spoils during the construction period of the stations. Due to the composition and nature of the engineered fill, the hydraulic conductivity of this material is 102

expected to be very low, thus limiting the ability of the subsurface materials to transmit a significant quantity of groundwater. Below the engineered fill there is an approximate five-foot layer of tidal marsh deposits consisting of silty peat, and organic silt and meadow mat, which is semi-confining. Beneath the tidal marsh deposits are approximately ten feet of discontinuous Quaternary Age riverbed deposits consisting of sand and gravel. The engineered fill, the tidal marsh deposits, and the riverbed deposits combine to form the shallow water-bearing zone. Beneath the shallow water-bearing zone, in order of increasing depth, are the following geologic formations (Figure 4):

Kirkwood Formation - The Kirkwood Formation in the vicinity of the site consists of dark, gray to brown clay, with some silt and layers of fine-grained micaceous quartz sand. It is approximately 15 feet thick and occurs from approximately 40 to 55 feet below ground surface (bgs).

Vincentown Formation - The Vincentown Formation occurs from a depth of approximately 55 feet bgs to a depth of 135 feet bgs and consists of a competent, greenish-gray, fine to medium sand with some silt, shell fragments, feldspar and glauconite.

Hornerstown Formation - The Hornerstown Formation is a highly glauconitic, clayey, dark green sand that contains small percentages of quartz grains and apatite pellets. The Hornerstown Formation 103

unconformably overlies the Navesink Formation and is unconformably overlain by the Vincentown Formation. The Hornerstown Formation occurs from approximately 135 to 145 feet bgs.

Navesink Formation - The Navesink Formation is characteristically glauconitic sand with varying amounts of silt and clay. It is brown or dark green to blue-black and has a shell bed at its base. The upper part of the formation is less glauconitic, more clayey, more micaceous, and lighter in color than the deeper strata. The Navesink Formation conformably overlies the Mount Laurel Sand (State of New Jersey Department of Conservation and Economic Development, 1969). The contact with the overlying Hornerstown Formation is gradational. The Navesink Formation is encountered from approximately 145 to 170 feet bgs.

Mount Laurel-Wenonah Formation - The Mount Laurel-Wenonah Formation consists of clayey, medium-grained sand with some gravel, feldspar and glauconite. In the vicinity of the stations, the Mount Laurel-Wenonah Formation is approximately 100 feet thick and occurs from 170 to 270 feet bgs.

Beneath the Mount Laurel-Wenonah Formation, more than 1,000 feet of Upper Cretaceous sediments overlie the crystalline bedrock. The Upper Cretaceous sediments include in descending order:

the Marshalltown Formation (gray, fine sand); the Englishtown Formation (yellow-brown, fine sand);

the Woodbury Clay (dark gray, stiff, silty clay);

the Merchantville Formation (dark green clay); the 104

Magothy Formation (coarse to fine silt with little fine sand); and the Raritan and Potomac Formations (interbedded sand, gravelly sand and clay).

f. Hydrogeology There are four primary water-bearing zones underlying the stations, the shallow water-bearing zone and three aquifers: 1) the Vincentown Formation; 2) the Mount Laurel-Wenonah Formations; and, 3) the Potomac-Raritan-Magothy Formations.

The shallow water-bearing zone, which consists of the dredge spoils, engineered fill, tidal marsh deposits and the discontinuous Quaternary riverbed deposits, occurs between approximately 10 and 40 feet bgs. In general, the dredge spoils, engineered fill and tidal marsh deposits are characterized by high porosity and low permeability. Occasional lenses of sand within the dredge spoils may contain perched water within a few feet of the ground surface. The groundwater in the shallow water-bearing zone is generally brackish, with flow generally to the southwest under a gradient of approximately 0.007 feet/foot.

The Kirkwood Formation is encountered at approximately 40 feet bgs. in the vicinity of the stations. In this location, The Kirkwood Formation consists of Miocene clays and acts as a confining layer, separating the shallow water-bearing zone from the underlying Vincentown Formation. The Kirkwood Formation in this vicinity may be discontinuous due to excavation that was conducted to enable the construction.

105

The Vincentown Formation, which occurs from approximately 55 to 135 feet bgs in this vicinity, is a semi-confined to confined aquifer.

Groundwater in the Vincentown Formation generally flows from north to south under a gradient of approximately 0.003 feet/foot. The Vincentown Formation supplies potable water to domestic wells located upgradient in eastern Salem County, where groundwater in the aquifer is moderately hard with high iron content. Saltwater intrusion into the aquifer occurs along the Delaware River in western Salem County however, rendering water quality brackish and non-potable. The Hornerstown and Navesink confining units separate the Vincentown Formation from the Mount Laurel-Wenonah Formations. The Mount Laurel-Wenonah aquifer occurs from approximately 135 to 170 feet bgs.

Both potable and fire-water supply wells at the stations are screened in this formation as well as the PRM aquifer.

g. Groundwater Use As described above, several geologic formations beneath Artificial Island contain transmissive units and are capable of supplying a useable quantity of water. The shallow and manmade geologic units beneath the Station are not transmissive and groundwater within the shallow zone is not used for potable or non-potable purposes. Moreover, in the general vicinity of the station there are no public water supply wells or private wells completed in the Vincentown Formation. The station derives its potable and sanitary water from the Mount Laurel-Wenonah and/or PRM formations, where supply wells 106

for both Salem and Hope Creek are completed at depths of approximately 300 to 1,100 ft bgs. The nearest public water supply well is located approximately 3.5 miles from the station in Delaware.

3. Field activities included drilling soil borings and logging soil cores to determine target depths and screened intervals for the proposed monitoring wells.

This allowed for installation of 21 new RGPP monitoring wells on both Stations to provide a means to evaluate groundwater quality in the shallow water-bearing zone.

Of the 21 new wells, 8 wells were installed to monitor groundwater quality at Salem to supplement the five existing wells and 13 were installed at Hope Creek.

Following installation, each well was developed, sampled by trained technicians using low-flow groundwater sampling techniques, and the samples analyzed by a laboratory qualified to perform analyses for tritium, strontium, and plant-related radionuclides. Tables 1 and 2 provide construction details for the monitoring wells. Sampling was conducted approximately two weeks following installation of the wells and again in the fall of 2006. PSEG has proceduralized the commitment to sample the RGPP monitoring wells twice per year for tritium and plant related gamma isotope concentrations and annually for strontium. The results of analyses performed in 2006 are discussed in Section 4 and included in Table 4.

Samples of surface water from the Delaware River water are collected monthly by PSEG Nuclear as part of the existing site REMP program. Therefore, it was not considered necessary to incorporate Delaware River sampling into the RGPP.

107

4. PSEG Nuclear has implemented new procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner. No new leaks, spills, or other detections with potential radiological significance to stakeholders were identified in 2006.

5. PSEG Nuclear regularly assesses analytical results to identify adverse trends. The investigation initiated at Hope Creek exemplifies this commitment, where Hope Creek initiated the investigation at tritium concentrations in groundwater significantly below the ODCM Environmental LLD with limited data for trending to ensure timely and effective response to unexplained results. The RGPP has been implemented through a procedural program to maintain consistency and ensure programmatic components are integrated..

6. PSEG Nuclear will take all necessary corrective actions to protect groundwater resources.

C. Radionuclide Evaluation Strategies

1. Evaluation Strategy for Tritium The strategy approved in the Salem GRS RAWP is applied to the interpretation of tritium data generated during the RGPP:

If tritium is detected in groundwater samples from Station monitoring wells at concentrations above 3,000 pCi/L (ODCM LLD), further evaluation of the source and extent of tritium, strontium and plant-related gamma emitters will be completed. Additionally, PSEG has 108

implemented procedures defining escalating investigations at tritium concentrations between 200 pCi/L and 3,000 pCi/L. These procedures define the investigative criteria for each specific monitoring well based on the background tritium concentration to ensure the proper investigation is initiated to meet the objectives of the RGPP.

2. Evaluation Strategy for Strontium PSEG made a decision to add total Strontium (Sr) as an analyte for groundwater samples. Analyses were performed for total Sr, which includes both Strontium 89 and Strontium 90. The detection of Strontium above 2.0 pCi/L (the lower quantitation limit) was established by PSEG as a further investigation criterion; detections at or above this concentration would result in implementation of the investigative measures outlined above.

3) Evaluation Strategy for Plant-Related Gamma Emitters Plant related gamma emitters are analyzed by multi-channel gammaspectroscopy to the Environmental LLD specified in the ODCM. The results of the analyses would also be used to assess any plant-related radionuclides detected in groundwater. If analytical results suggest specific sources are likely, these sources will be further investigated to enable mitigation of releases to the environment. The ODCM Environmental LLDs were applied and no detections above these concentrations have occurred. Any detection of a plant-related gamma emitter above the ODCM concentration would be investigated.

109

D. Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

110

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (He-3) . This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium.

Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

111

This page intentionally blank.

112

III. Program Description A. Sample Analysis This section describes the general analytical methodologies used to analyze the environmental samples for radioactivity for the Salem and Hope Creek Generating Station RGPP in 2006.

In order to achieve the stated objectives, the current program includes the following analyses:

" Concentrations of gamma emitters in groundwater.

" Concentrations of strontium in groundwater.

" Concentrations of tritium in groundwater.

As noted above, samples of surface water from the Delaware River water are collected monthly by PSEG Nuclear as part of the existing site REMP program.

Therefore, Delaware River sampling is not incorporated into the RGPP.

1. Sampling Following installation and development of the monitoring wells, groundwater samples were collected from all new monitoring wells as well as the five preexisting wells located within Salem.

These samples were collected by PSEG Maplewood Testing Laboratory Technicians. Consistent with USEPA and NJDEP guidance, a modified low-flow sampling methodology was used. This methodology 113

is consistent with protocols established for the Salem GRS investigation. The initial groundwater sampling round began approximately two weeks following well development activities.

Groundwater samples were analyzed for plant-related gamma emitting radionuclides, tritium and total strontium by a qualified laboratory.

Samples were again collected in October/November of 2006 for the same parameters from all 26 RGPP wells.

The 26 wells in the RGPP are sampled at a minimum of twice per year. Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and industry cross-check programs. Station personnel review and evaluate all analytical data deliverables as data are received. Analytical data results are reviewed for adverse trends or anomalous data, field measurements are reviewed to monitor for changes to hydrogeologic conditions.

B. Data Interpretation The radiological data collected during the history of the stations in the groundwater were used as a baseline with which current operational data were compared.

114

Several factors are important in the interpretation of the 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 parameter. The Environmental LLD specified in the ODCM for tritium is 3,000 pCi/L (ODCM Table 14.12-1 for Salem and Table 14.12.1-1 for Hope Creek).

For the RGPP all tritium analyses are performed with the LLD of 200 pCi/L.

2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

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 calibration standards, sample volume or weight measurements, sampling uncertainty and other factors.

Analytical uncertainties are reported at the 95%

confidence level in this report for reporting consistency with the AREOR.

3. Groundwater Quality Data Analysis Groundwater samples generally consisted of at 115

least four aliquots, denoted as "A", "B", and "C" samples and the NJDEP-BNE split sample. These samples were either submitted to a laboratory or held as back up samples as described in the following section.

Groundwater "A" samples were submitted to the station's onsite chemistry laboratory for tritium and gamma scans. If these scans indicated that tritium concentrations were below 10,000 pCi/L and no plant-related gamma emitters were present (all RGPP samples met this criteria), then the "B" samples were submitted to Teledyne-Brown analytical laboratory for low level analysis. "C" samples were held as back up until the analytical results were received and determined to be accurate and valid. In the event that the results were believed to be questionable, the "C" samples were submitted for analysis. Sample aliquots were also periodically transmitted to the PSEG Maplewood Testing Services laboratory for comparison and quality verification.

Additionally a split sample from each well was submitted to the NJDEP-BNE designated laboratory, Eberline Services, for analysis regardless of the screening concentration, according to the request of the BNE. Results for these samples will be provided by Eberline Services to the NJDEP-BNE.

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The pre-operations REMP did not adequately address the groundwater at the facility 116

from a radionuclide standpoint. Subsequent natural and anthropogenic events and activities, such as half-life, nuclear bomb testing, and Chernobyl, have altered the radiological environmental character. Some of the anthropogenic impacts were clearly identified during the Salem GRS investigation by age-dating characterization of low-level tritium concentrations.

Anthropogenic impacts have also been historically noted in AREORs.

Background evaluation for each monitoring well was conducted using adjacent well concentrations, upgradient concentrations, areal gradient impacts from construction, and similar factors. A factor to be considered in the RGPP is the very low level of tritium in the groundwater and the inability to reasonably perform reproducible analyses at a lower level than 200 pCi/L. Since plant-related radionuclides have not been detected in the groundwater, even in the known area at the Salem GRS, the only background value is 'not detected" and there is essentially no comparative data.

1. Creation of Tritium Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e.,

man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the 117

radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere.

The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

2. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of 118

thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time.

Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.

119

This page intentionally blank.

120

IV. Results and Discussion The locations of the wells relative to major plant components is shown in Figures 1 and 2. The analytical results are shown on Table 4.

A. Groundwater Results Samples were collected from RGPP monitoring wells throughout the year in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below.

Table 4 presents the ground water quality analytical results from the 26 RGPP wells. The groundwater samples were analyzed for tritium, strontium and plant-related gamma emitters by Teledyne-Brown. The lower quantitation limits for tritium and strontium were 200 pCi/L and 2.0 pCi/L, respectively. Gamma emitting isotopes were analyzed to the LLD shown in Table 3, plant-related gamma emitters were not detected during the investigation.

Tritium at Salem Generating Station The results of the laboratory analysis indicate that tritium was detected (i.e, reported at a concentration above the lower quantitation limit of 200 pCi/L) in groundwater within the shallow water-bearing zone (i.e., riverbed deposits) in three of the Salem monitoring wells sampled. The sampled wells included all of the new "B Series" wells, and existing wells T, U, Y, Z and AL. One detection of tritium occurred in 121

well BD, which is located just outside the cofferdam.

This well is screened at a depth of 30.5 to 40.5 ft.

bgs in riverbed deposits. The tritium concentration in well BD was reported as 431 pCi/L, approximately twice the quantitation limit. Well BD was installed to monitor groundwater quality adjacent to and downgradient of the Refueling, Auxiliary, and Primary water storage (RAP) tank area. Additionally, during one sample event, tritium was detected in Wells BB and U at 232 pCi/L and 210 pCi/l respectively, slightly above the detection levels.

The concentration of tritium detected in these wells is nearly an order of magnitude below the ODCM LLD of 3,000 pCi/L. The tritium concentrations are being monitored and trended in these wells through semi-annual sampling. No adverse trend has been observed.

Tritium at Hope Creek Generating Station Hope Creek Generating Station has observed low concentrations of tritium in certain wells and anomalous tritium concentrations in other specific wells.

Tritium was detected (concentration greater than 200 pCi/L) in wells BM, BN, and BQ at concentrations ranging from 200 pCi/L to 269 pCi/L. Tritium was detected in the range of 358 to 436 pCi/l at Well BJ, located down gradient of the CST. These low concentrations of tritium were evaluated and determined not to be indicative of an adverse trend, these wells are being monitored semi-annually and the results will continue to be evaluated.

Wells BH, BI, and BK have presented anomalous tritium 122

concentrations, ranging from < 200 pCi/L to 2600 pCi/L during this reporting period. Confirmatory analyses were inconclusive and more recent analyses show a significant reduction in the reported tritium concentrations. Laboratory quality assurance and quality control have been evaluated and determined not to be the source of the anomalous data.

These tritium concentrations are all below the ODCM LLD of 3,000 pCi/L. Monitoring is underway of alternate sources considered to be a potential contributor to the anomalous results, such as analysis of the Delaware estuary, the yard drainage systems, the service water system, the precipitation from the roof areas near the plant vents, and other similar potential sources. To ensure adequate trending and evaluations, sampling frequency for these wells has been increased to quarterly for at least the next two quarters. These analytical results will be evaluated to determine if there is a potentially adverse trend and to identify the source of the anomaly.

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

Gamma Emitters No plant-related gamma emitters were detected in any RGPP well samples. Naturally occurring Potassium-40 was detected in 10 of the wells sampled.

B. Leaks, Spills, and Releases 123

No significant leaks, spills or releases occurred or were detected during this monitoring period.

C. Trends There have been no adverse trends identified through the RGPP during this reporting period.

D. Investigations The tritium detections at Salem Generating Station were evaluated and determined to be approximately an order of magnitude below the Further Investigation Criteria. The investigation included validation of the results through independent analysis and is continuing through semi-annual monitoring of the wells for tritium concentration and evaluation of the results.

E. Projected RGPP Activities The RGPP will be continued in 2007, being modified as required to adaptively manage the program to meet the objectives. Sampling will continue on the following schedule (in addition to the specific wells being sampled quarterly for tritium concentration at Hope Creek):

• Tritium will be analyzed at least twice each calendar year to an LLD of 200 pCi/L;

• Plant-related gamma emitters will be analyzed semi-annually to the ODCM Environmental LLD; and,

• Strontium will be analyzed annually as total strontium; if the total strontium is greater than 2.0 pCi/L a separate analysis will be performed specifically for strontium-89 and strontium-90; 124

Table 01. Monitoring Well Construction Details, Hope Creek Generating Station Installation Construction Diameter Total Depth Monitoring MP MP Monitoring Date Details (inches) (feet bgs) Interval Elevation Elevation Purpose Source Targets Well ID (feet bgs) (feet RPD) (feet msl)

May-06 Sch-40 PVC 4 37.0 27- 37 97.92 8 Perimeter NA Well BH May-06 Sch-40 PVC 4 38.5 28.5 - 38.5 99.6 9.68 Source Facilities; Piping Well BI Well BJ May-06 Sch-40 PVC 4 38.0 28- 38 100.23 10.31 Source Condensate Storage & Transfer: Facilities; Piping May-06 Sch-40 PVC 4 38.5 28.5 -38.5 98.19 8.27 Perimeter NA Well BK May-06 Sch-40 PVC 4 35.0 25 -35 99.71 9.79 Perimeter NA Well BL May-06 Sch-40 PVC 4 38.0 28 - 38 99.76 9.84 Source Facilities; Piping Well BM Well BN May-06 Sch-40 PVC 4 12.5 7.5- 12.5 102.64 12.72 Source Auxiliary Boiler Building; 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 32-42 102.16 12.24 Source Auxiliary Boiler Building: Dry Cask Storage Building: Piping Well BR May-06 Sch-40 PVC 4 40.5 30.5-40.5 104.28 14.36 Perimeter/Source Piping; Dry Cask Storage Building May-06 Sch-40 PVC 4 35.0 25-35 100.55 10.63 Upgradient NA Well BS May-06 Sch-40 PVC 4 38.5 28.5-38.5 99.60 9.68 Upgradient NA Well BT 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 Page 125

Table 02. Monitoring Well Construction Details, Salem Generating Station Hancock's Bridge, New Jersey Installation Construction Diameter Total 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 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 PVC 2 37.5 27.5-37.5 101.86 11.94 Perimeter NA Well AL Jan-04 Sch-40 PVC 2 25.3 15.3- 25.3 99.13 9.21 Perimeter 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 98.78 8.86 Source I Perimeter Facilities; RAP Tanks; Piping Well BD May-06 Sch-40 PVC 4 40.5 30.5 - 40.5 98.78 8.86 Source Facilities; RAP Tanks; 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:

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 Page 126

Table 03. Relevant Groundwater Screening Criteria, Salem and Hope Creek Generating Stations PSEG Reporting Level Isotope RGPP LLD (pCi/L) (pCiIL)

Tritium Conc. (pCi/L) 200 3000*

Total Strontium (pCi/L) 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-134 15 30 Cs-137 18 50 Ba-140 60 200 La-140 15 200

• Informal Report, ODCM Report at 30,000 pCi/L Page 127

Table 04. Groundwater Tritium Analytical Results, Salem and Hope Creek Generating Stations May 2009 ctober 2006 Well ID Station Tritium Conc. Tritium Conc.

(pCi/L) (pCi/L)

T Salem <200 <200 U Salem <200 210 Y Salem <200 <200 Z Salem <200 <200 AL Salem <200 <200 BA Salem <200 <200 BB Salem <200 232 BC Salem <200 <200 BD Salem 431 327 BE Salem <200 <200 BF Salem <200 <200 BG Salem <200 <200 BH Hope Creek <200 1450 BI Hope Creek <200 2600 BJ Hope Creek 358 436 BK Hope Creek <200 1340 BL Hope Creek <200 <200 BM Hope Creek <200 244 BN Hope Creek 269 236 BO Hope Creek <200 <200 BP Hope Creek <200 <200 BQ Hope Creek <200 214 BR Hope Creek <200 <200 BS Hope Creek <200 <200 BT Hope Creek <200 <200 BU Salem <200 <200 Page 128

Table 05. Groundwater Elevations, Salem and Hope Creek Generating Stations Depth to Depth to Well Location Reference Point Water Water-Level Water-Level Water Water-Level Water-Level Identification Elevation (ft btoc) Elevation (ft rpd) Elevation (ft msl) (ft btoc) Elevation (ft rpd) Elevation (ft msl)

(NGVD 1988) 16-May-06 16-May-06 16-May-06 28-Sep-06 28-Sep-06 28-Sep-06 Well T SGS 14.21 11.77 92.36 2.44 11.62 92.51 2.59 Well U SGS 8.65 6.05 92.52 2.6 7.2 91.37 1.45 Well Y SGS 11.89 11.04 90.77 0.85 10.96 90.77 0.85 Well Z SGS 11.94 11.54 90.32 0.4 11.01 90.85 0.93 Well AL SGS 9.21 9.11 90.02 0.1 UTM UTM UTM Well BA SGS 11,15 10.23 90.84 0.92 9.95 91.12 1.2 Well BB SGS 9.46 9.46 89.92 0 9.25 90.13 0.21 Well BC SGS 8&86 7.99 90.79 0.87 7.52 91.26 1.34 Well BD SGS 8.86 7.31 91.47 1.55 7.16 91.62 1.7 Well BE SGS 8.39 7.01 91.3 1.38 6.63 91.68 1.76 Well BF SGS 9.19 7.75 91.36 1.44 7.47 91.64 1.72 Well BG SGS 10.08 7.97 92.03 2.11 7.81 92.19 2.27 Well BH HCGS 8 6.38 91.54 1.62 NA NA NA Well BI HCGS 9.68 5.54 94.06 4.14 6.93 92.67 2.75 Well BJ HCGS 10.31 7.85 92.38 2.46 7.15 93.08 3.16 Well BK HCGS 8.27 6.3 91.89 1.97 5.95 92.24 2.32 Well BL HCGS 9.79 8.21 91.5 1.58 7.91 91.8 1.88 Well BM HCGS 9.84 7.65 92.11 2.19 7.67 92.09 2.17 Well BN HCGS 12.72 NA NA NA 6.82 95.82 5.9 Well BO HCGS 8.06 6.75 91.23 1.31 6.18 91.8 1.88 Well BP HCGS 9.14 8.07 90.99 1.07 8.09 90.97 1.05 Well BQ HCGS 12.24 9.6 92.56 2.64 NA NA NA Well BR HCGS 14.36 12.61 91.67 1.75 12.36 91.92 2 Well BS HCGS 10.63 7.91 92.64 2.72 7.72 92.83 2.91 Well BT HCGS 9.68 6.52 93.08 3.16 6.49 93.11 3.19 Well BU SGS 10.24 7.61 92.55 2.63 UTM UTM UTM Notes ft bgs Feet below ground surface.

ft rpd Elevation (in feet) relative to plant datum.

ft amsl Feet above mean sea level (NAVD 1988).

Mean tide level at Artificial Island is 0.11 feet (NAVO 1988).

NA Data not available UTM Unable to monitor (No access)

Page 129

Table 06. List of Systems of RGPP Interest and General Location and Description of System, Hope Creek Generating Station System Name System ID System Description/Location Core Spray System BE Provides support to nuclear reaction process; housed within the Containment Dome.

Reactor Core Isolation System BD Provides support to nuclear reaction process; housed within the Containment Dome.

Fuel Pool Cooling and Cleanup EC Provides support to nuclear reaction process; housed within the Containment Dome.

Filtration, Recirculation, and GU Provides support to nuclear reaction process; housed within the Containment Dome.

Ventilation System (FRVS)

Containment Atmosphere Control GS Provides support to nuclear reaction process; housed within the Containment Dome.

System Reactor Building HVAC System GR Provides support to nuclear reaction process; housed within the Containment Dome.

Lube Oil Storage and Transfer CF Located within the Outer Containment Building.

System Reactor Building Pressure Relief SL Located within the Outer Containment Building.

System Auxiliary Building HVAC System GH Located at the boundary between the Outer Containment Building and the Hope (Radwaste Area) Creek Service/Radwaste Building.

Liquid Radwaste System HB Located within the Radwaste Building.

Radioactive Laundry HH Located within the Radwaste Building.

Auxiliary Building HVAC System GL Located within the Radwaste Building.

(Service Area)

Building and Equipment Drains HG Located within the Turbine Building.

Turbine Building HVAC System GE Located within the Turbine Building.

Condensate Storage and Transfer AP/BN Contains and transfers water used in cooling applications; located outside of the System sheetpile adjacent to the Outer Containment Building.

Residual Heat Removal System BC Contains and transfers water used in cooling applications; located outside of the sheetpile adjacent to the Outer Containment Building.

Service Water System EA Provides raw water from the Delaware River; located within sheetpile trench.

Storm Drainage System LB Collects precipitation runoff.

Building Sewage System LA Processes waste water generated from sink drains and other comfort facilities at the Station.

Auxiliary Boilers FA/FB Provide additional power to Station.

Circulating Water System DA Supports cooling process; located within containment trenches and containment sleeves.

Cooling Tower DB Supports cooling process for steam turbines.

Low Volume Oily Waste LE Oily water from oil storage tank contaminant basins High Pressure Cooling Injection BJ Cooling support to nuclear reaction process System I Page 130

Table 07. List of Systems of RGPP Interest and General Location and Description of System, Salem Generating Station System Name System ID System Description/Location Auxiliary Feedwater AF Provides feedwater to supplement steam generation process. Storage tanks located on the west side of the Auxiliary Building, situated above the cofferdam.

Building and Yard Drains BD Located within and around the Turbine Building and throughout the Station yard.

Feedwater and CN/FW Contains and transfers water transported to steam generator from turbines; located inside the Condensate Turbine Building and between the Containment Dome and the Turbine Building.

Condensate Polishing CP Contains and transfers condensate from the Turbine Building to the proximally located

_Condensate Polishing Buildings.

Chemical Volume CVC Provides support to the nuclear process water management systems; housed within and Control adjacent to the Auxiliary Building and within the Containment Domes.

Circulating Water CW Non contact cooling water for the condensation process; runs from the Delaware River to the Turbine Building.

Demineralized Water DM Provides support to Reactor Coolant System; located adjacent to the Auxiliary Building.

Steam Generator Drains GBD Provides support to the steam generation process; located within the Containment Domes and and Blowdown runs to the Waste Basin to the south and to the Turbine Building.

House Heating Boiler HHB Steam source for building heating; located to the north of the Turbine Building Non-Radioactive Liquid LW Liquid Waste lines that run from the Turbine Building south and east to Clarifiers I and 2 and Waste the equalization basin. -

Main Steam MS Contains and transfers steam from the Generator to the Turbines; located within the Containment Domes and run to the Turbine Building.

Spent Fuel Pool Cooling SF Supports storage and transfer of spent fuel; located within the Fuel Handling Buildings.

Safety Injection SJ Provides support to the nuclear reaction process; storage tanks located on the west side of the Auxiliary Building, situated above the cofferdam.

Service Water SW Provides raw water from the Delaware River; located south and east of the Containment Domes.

Radioactive Liquid WD Located within the Auxiliary Building.

Drains Waste Liquid WL Radioactive liquid waste system, located primarily in the Containment Dome and the I_ _ Auxiliary Building.

Page 131

BL A wmctlN 1WEL (IETAuED INmwu 200)

~-. 0

! WELL TO MONI1MIE 1W SCREED 01 M SI4A.0OW, WAT-ERARM4 UNIT (X M THEh MIS OFTHE COFFEURid. 35 FEET0EBM1WIMCA 4o, IN .D- SWEE PILE 77z SERVICEWTWER PIPING RWUL11N4G WARER OUTLE 4

PIIG o m SE~W.1GWlER141.E

• MNI1OL (mmltSEWER)

RCP RIIWFORCE CON~~ PPE MTL MEAN TIOELEVEL

- 9AEOt4C WALL X NOTE' WELLF, WELL M ýM WELL M LOCA1 ONHOPE MM(E PROPEMl STATION GEN4ERATING SALIM Off ASOCITED YAM1 I,

PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION ITwfyowu shIN STATION LAYOUT 1MA- osi.Pa154 Tel: XM5.IMM Fat 2mUMSI10 moolumm Page 132 ml

J,£gmB

~~ABU~ PROPRITY 11L"R BL4 MNImR wELL (bmTm INA. 2m01)

\\ 0 OWELLTTL I ,

riLzjj12I~

V*:LL k

• MONITORING WELL SCREENED IN THE ENGINEERED FILL WITHIN THE COFFERDIAM, 20 FEET DEEP (WELLS M. N. 0. R)

WELL SO MONITORING WELL SCREENED IN THE SHALLOW, WATER TABLE AQUIFER OUTSIDE THE COFFERDAM, 35 FEET DEEP

/ - "a ELL K (WELLS S. T, U. W)

- W/ELL V WELL LO MONITORING WELL SCREENED IN THE VINCENTOWN FORMATION, 80 FEET DEEP (WELLS K. L. P, 0, V.)

NOTE:

1. WELL BF, WELL BG AND WELL BU LOCATED ON HOPE CREEK GENERATING STATION PROPERTY BUT ASSOCIATED WITHSALEM UNIT II INVESTIGATION.

II a I ------1 I:

I ID-I I

~ELLQ I'

S N- it- S PSEG NUCLEAR, LLC SALEM GENERATING STATION ARCAoiS STATION LAYOUT Td3IhIUIF ZWIS4 Wwmolemmm Page 133

2Ci.j

- 7N~~.2

.I S

s.c 9 1,000~

,0Im U,* 0~

0go 0,O 0

8.1

• IMM4.E (SM 3wl)

W- MONITORING; WELL SCREENED IN SIIi 'RE ENGIEEE FILL WITHIN THE COIFFMA 20 FEEr DEEP 13 (WELLS M. N. 0. R)

II WELL SO0 MONITORING WELL SCREENED IN ThE SMLLOW. WOUER TABLE I p l~b

/0 ,

• 1X

\ WELL LO AOWFER OUTSIDE 1TE COFFERDA 35 FEET DEEP (WELLS S. T. U. W)

MONITORING WELL SCREENED IN Ii

• WV 11M %INCENTOWN4 FORWXTIO 9480 FEM DEEP (WELLS K, L. P$Q. V.)

ii 1. M WAN TAX ILM OFTIE 09MMWM E9 MMiii SIAM U 0.11 Fr PM"e Ii U

// . t,!

L* /A t

ur lm Mo NI a 101m o AMO MEM MAMB NIM IMS)

PSEG NUCLEAR, LLC ¶1=

PSEG NUC.LEAR U.C SM.EM I HOPE CREEK GENERAlING STATION POTENTIOMETRIC SURFACE MAP SEPTEMBER 28, 2006 N~NW^ Ps ism4 T.1:T5.IUO Fac25719U1U1-8 Page 134 HANCOCK'S BRIDGE, NEW JERSEY WIIAGIA

__DELTA I SHELF I

U..

WDRUC FIL I I 10 1l 11 i

-50" _ _ _ _ _ _

-100' F.~

-150.

Dowm -U-

-200.

-250.

-300- Num*mo

-350.

mwý 3 C-) -400.

a -450m. uMAW AGM Wa, minin 2 z

-500" 0

I

-550.

m

-600- .R.

tA-LI -650' LL

-700-i -750-

-800-' IUM M*

-850 -- u Ir

-900 I.

I. 1.000 m.E m*- AY 2iS 1,050 1.100-

-1150-PAM-WE A-R

-1,200 A I A- - L - - -1 A -.-. ~ .L A A __________

PSEG NUCLEAR, LLC SALEM STRATIGRAPHY COLUMN Page 135 Tel:237iU5-I80 Fux261fl518O NCOCICS BRIDGE, SALEM COUNTY, NEW JEF