ML18102B012

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Annual Radiological Environ Operating Rept for Jan-Dec 1996
ML18102B012
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Site: Salem, Hope Creek  PSEG icon.png
Issue date: 12/31/1996
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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 1996 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1996 Prepared By PUBLIC SERVICE ELECTRIC AND GAS COMPANY MAPLEWOOD TESTING SERVICES APRIL 1997 PS~G

I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM &

HOPE CREEK GENERATING STATIONS 1996 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1996

TABLE OF CONTENTS PAGE

SUMMARY

1 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........

3 Objectives..............................................

4 Data Interpretation.....................................

s Quality Assurance Program...............................

6 Program Changes.................. *.......................

6 Results and Discussion..................................

6 Atmospheric.........................................

7 Direct Radiation.........................,..........

8 Terrestrial.........................................

9 Aquatic..................................... *........

14 Program Deviations......................................

20 Conclusions.............................................

2 O REFERENCES..................................................

31 APPENDIX A -

PROGRAM

SUMMARY

33 APPENDIX B -

SAMPLE DESIGNATION AND LOCATIONS...............

41 APPENDIX C DATA TABLES....................................

4 9 APPENDIX D -

SUMMARY

OF RESULTS FROM USEPA AND ANALYTICS INTERLABORATORY COMPARISON PROGRAMS............

79 APPENDIX E -

SYNOPSIS.OF LAND USE CENSUS....................

89 i

LIST OF TABLES TABLE NUMBER TABLE DESCRIPTION

~

1.

1996 Radiological Environmental Monitoring Program (Program Overview)..................................

21 LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION PAGE

1.

Beta in Air Particulate 1973 through 1996 {Quarterly)......................

24

2.

Ambient Radiation - Offsite Vs Control Station 1973 through 1996 (Quarterly)......................

25

3.

Iodine-131 Activity in Milk 1973 through 1996 (Quarterly)............ :.........

26

4.
  • Gross Beta Activity in Surface Water 1973 through 1996 (Quarterly)......................

27

5.

Tritium Activity in Surface Water 1973 through 1996 (Quarterly)..... *~*******........

28

6.

Cesium-137 Activity in Water Sediment 1977 through 1996 (Semi-Annual)......................

29 6B.

Cobalt-60 Activity in Water Sediment 1977 through 1996 (Semi-Annual)......................

30 ii I

-~

I SUMf'IIARY..

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 Units 1 and 2 (SGS) and Hope Creek (HCGS)

Generating Stations are located.

The results of the REMP are published annually, providing a summary and interpretation of the data collected.

Additional data relating to the releases of radioactive materials to the environment can_be obtained in the Radiological Effluent Release Report (RERR) which is published and submitted to the Nuclear Regulatory Commission on a semiannual (SGS) and annual (HCGS) frequency.

The PSE&G Maplewood Testing Services (MTS) has been responsible for the collection and analysis of environmental samples during the period of January 1, 1996, through December 31, 1996, and the results are discussed in this report.

The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted in accordance with the-SGS and HCGS Technical Specifications.

The Lower Limit of Detection (LLD) values required by the Technical Specifications were achieved for this repor~ing period.

The objectives of the program were also met during this period.

The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.

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 nuc.lear bomb testing.

Measurements made in the vicinity of Salem and Hope Creek Generating Stations 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 dr1nking 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 which ran from 1973 to 1976, we can conclude that the operation of SGS Units One and Two and HCGS had no significant impact on the radiological characteristics of the environs of these stations.

1

To demonstrate compliance with Technical Specifications (Section 3/4.12.1), most samples were analyzed for gamma emitting isotopes, tritium (H-3), strontium-89 (Sr-89) and 90 (Sr-90), iodine-131 (I-131), gross beta and gross alpha.

The results, of these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with Technical Specifications (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 rep9rt are summarized below:

  • There were a total of 1215 analyses on 905 environmental samples during 1996.

Direct radiation dose measurements were also made using 245 thermoluminescent dosimeters (TLDs).

  • In addition to the detection of naturally-occurring isotopes (i. e. Be-7, K-40, Ra-226 and Th-232), low levels of Sr-90 were also detected in various media.

The detection of these radionuclides may be attributed to residual fallout from atmospheric weapons testing.

Trace levels of Mn-54, Co-60, Cs-134, 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 Artificial Island averaged 48 millirems the year 1996.

An average of the control locations (background) for this time was 53 millirems for the year.

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

2 for This which

_J

THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Lower Alloways Creek Township, Salem County, New Jersey is the site of Salem and Hope Creek Generating Stations.

The Salem Generating Station (SGS) consists of two operating pressurized water nuclear power reactors.

Salem Unit One has a net rating of 1115 MWe (3411 MWt), and Salem Unit Two has the same rating at 1115 MWe (3411 MWt).

The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which has a net rating of 1067 MWe (3293 MWt).

Salem and Hope Creek Generating Stations (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 [5,6]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Reports [5, 6] '"--

Environmental Statements [7,8], and the Updated Final Safety.

Analysis Reports for SGS and HCGS [9,10].

Since 1968, an off-site 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.

The PSE&G Maplewood Testing Services (MTS), has been involved in the REMP since its inception.

The 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 the 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 the annual reporting of results.

RMC reports for the preoperational and operational phase of the program are referenced in this report [1-3].

On July 1, 1983, the MTS assumed primary responsibility for the analysis of all samples (except TLDs) and the reporting of results.

Teledyne Brown Engineering Environmental Services (TBE), Westwood, NJ, at that time, took over responsibility for third-party QA analyses and TLDs.

An additional vendor, Controls for Environmental Pollution Inc., had been retained to provide third-party QA analyses and certain non-routine analyses from May 1988 up until June 1, 1992.

At this time, Yankee Atomic Electric Laboratory (YAEL) and Thermo Nutech are our QA vendors.

MTS reports for the operational phase from 1983 to 1994 are referenced in this report [4].

3

An overview of the 1996 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, where applicable, to determine the effects, if any, of station opera~ions. This report summarizes the results from January 1 through December 31, 1996, for the SGS/HCGS Radiological Environmental Monitoring Program.

OBJECTIVES The objectives of the Operational Radiological Environmental Monitoring Program are:

To fulfill the obligations of the Radiological Surveillance sections of the Technical Specifications for the Salem Generating Station (SGS) and the Hope Creek Generating Station (HCGS).

To determine whether any significant increase occurs 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, and Section 6.9.1.6 of the Hope Creek Technical Specifications, summarizes the findings of the 1996 REMP.

Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the SGS/HCGS have been summarized for purposes of comparison with subsequent operational reports [2].

In order to meet the stated objectives, an appropriate operational REMP was developed.

Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms.

The se_lection of sample types was ba.sed 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 from site meteorology, Delaware estuarine hydrology, local demography, and land uses.

I

).

4

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Sampling locations were divided into two classes, indicator and control.

Indicator stations are those which are expected to manifest station effects, if any exist.

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 diiect 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 6.9.1.10 of the Salem TS and Section 6.9.1.7 of the Hope Creek TS, the entire operational program as performed in 1996.

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 all analyses were grouped according to the analysis performed for each type of sample and are presented in the data '"'

tables in Appendix C.

All results above the lower limit of detection (LLD) are at a confidence lev.el 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 one standard deviation of the background count, or of the blank sample count, as appropriate.

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 lower limit of detection is considered to be at that limit.

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 t'o 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~

5

As a result, variation in the radionuclide concentrations of the samples will normally occur.

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

QUALITY ASSURANCE PROGRAM The PSE&G Maplewood Testing Services (MTS), has a quality assurance program designed to maximize confidence in the analytical procedures used.

Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review.

The quality of the results obtained by the MTS is ensured by the implementation of the Quality Assurance Program as described in the Environmental Section Quality Assurance Plan [17] and the Environmental and Chemical Services Division Procedures Manual [18].

The internal quality control activity of the 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 and spiked samples.

The external quality control activity is implemented through participation in the USEPA and Analytics inter-laboratory comparison programs.

These results are listed in Tables D-1 through D-4 in Appendix D.

PROGRAM CHANGES Analyses that 'are not specifically required by the Salem and Hope Creek Technical Specifications were removed from the 1996 REMP.

These include: strontium analysis in air particulates, well and potable waters; gross alpha analysis in air particulates and surface waters; monthly TLD's; gamma spectroscopy in beef; potassium-40 by atomic absorption; and tritium analysis of fish and crab flesh.

RESULTS AND DISCUSSION The analytical results of the 1996 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic.

The analytical results for the 1996 REMP are summarized in Appendix A.

The data for individual samples are presented in Appendix C.

The data collected demonstrates that SGS Units 1 and 2 and HCGS were operated in compliance with Technical Specifications.

The REMP for the SGS/HCGS Site has ;historically included samples and analyses not specifically required by the Stations Technical Specifications.

PSE&G continues to collect and analyze some of these samples in order to maintain personnel proficiency in performing these non-routine analyses.

6

These analyses are referenced throughout the report as Management Audit samples.

The summary tables in this report include these acrditional sampl~s and analyses.

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

Iodine was collected from the air by adsorption on triethylenediamine (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-1, C-2)

Air particulate samples were collected at six locations.

Each of the 318 weekly samples collected 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 six sampling stations during 1996 was 98.5 percent.

Gross beta activity was detected in 260 of the indicator station samples at concentrations ranging from 7 x 10-3 to 41 x 10-3 pCi/m? and in all of the control station samples from 9 x 10- 3 to 33 x 10-3 pCi/m3

  • The average for both indicator.and control station samples was 22 x 10-3 pCifm3 The maximum preoperational level detected was 920 x 10-3 pCi/m3, with an average of 74 x 10-3 pCi/m 3

Gamma spectrometric analysis performed on each of the 24 quarterly composite samples analyzed, indicated the presence of the naturally-occurring radionuclides Be-7, K-40, and Radium.

All. other gamma emitters searched for were below the Lower Limit of Detection.

0 Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in all twenty indicator station composites that were analyzed, at concentrations ranging from 41 x 10- 3 to 102 x 10-3 pCi/m 3

, with an average of 68 x 10-3 pCi/m3

  • It was detected in the four control station composites from 57 x 10-3 to 73 x 10-3 pCi/m3, with an average of 61 x 10-3 pCi/m 3

The maximum preoperational level detected was 330 x 10-3 pCi/m3, with an average of 109 x 10- 3 pCi/m3

  • 0 Potassium-40 activity was detected in nine of the indicator station samples with an average of 13 x 10-3 pCi/m3
  • K-40 was also detected in two control station samples at an average concentration of 14 x 10-3 pCi/m3
  • No preoperational data is available for comparison.

7

0 Radium was detected in two indicator station samples at concentrations of 1.4 x 10-3 and 1.7 x 10-3 pCi/m 3 but not in any of the control station samples.

No preoperational data is available for comparison.

Air Iodine (Table C-3)

Iodine in filtered air samples was collected at six locations.

Each

  • of the 318 weekly samples collected was analyzed for I-131.

Iodine-131 was not detected in any of the 318 weekly samples analyzed.

LLD sensitivities for all the stations, both indicator and control, ranged from <1.2 x 10-3 to <11 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 CaS04 (Tl) thermoluminescent dosimeters (TLDs) supplied and read by YAEL.

Packets for quarterly exposure were placed on and around the Artificial Island Site at.various distances.

Additional Annual TLD's supplied and read by Thermo NUtech were co-located with the quarterly TLD's as a comparison.

These results are included in Table C-4.

k Direct Radiation (Table C-4)

A total of 49 locations were monitored for direct radiation during 1996, 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 TLD's at schools and population centers in the area.

Five readings for each TLD 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.

0 The average dose rate for the 31 quarterly off-site indicator TLDs was 4.0 millirads per standard month, and the averag~ control rate was 4.4 millirads per standard month.

The preoperational average quarterly TLD readings was 4.4 millirads per standard month.

In Figure 2, the quarterly average radiation levels of the offsite indicator stations versus the control stations, are plotted for the year period from 1974 through 1996.

8

TERRESTRIAL Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture.

Samples were collected in new polyethylene containers and transported in ice chests with no preservatives added.

Well water samples were collected monthly by PSE&G personnel.

Separate raw and treated potable water samples were composited daily _

by personnel of the City of Salem water treatment plant.

All samples were collected in new polyethylene containers.

Locally grown vegetable and fodder crops are collected once a year at time of harvest.

Such samples are weighed in the field at time of pickup and then packed in plastic bags.

Grass or green chop is collected from grazing areas, where possible.

Game (muskrat) is collected annually (time of year dependent on weather conditions, which affect pelt thickness) from local farms after being trapped, stripped of their pelts and gutted.

The carcasses are packed in plastic bags and kept chilled in ice chests during transport.

Milk (Tables C-5, C-6)

Milk samples were collected at four local dairy farms.

Samples were collected semi-monthly when cows were on pasture and monthly when cows were not on pasture.

Animals are considered on pasture from April to November of each year.

Each sample was analyzed for I-131 and gamma emitters. In addition, although not specifically required by the SGS and HCGS Technical Specifications, one sample from each location was analyzed for Sr-89 and Sr-90 in order to maintain the data base developed in prior years.

Iodine-131 was not detected in any of the *00 samples analyzed.

LLD sensitivities for the 60 indicator station samples ranged from <0.1 to <0.8 pCi/L and for the 20 control station samples from <0.1 to <0.6 pCi/L.

The maximum preoperational level detected was 65 pCi/L which occurred following a period of atmospheric nuclear weapons tests.

Gamma spectrometric analysis performed on each of the 80 samples indicated the presence of the naturally-occurring radionuclides K-40and Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in all 80 samples.

Concentrations for the 60 indicator station samples ranged from 1200 to 1400 pCi/L, with an average of 1300 pCi/L.

The 20 control station sample concentrations ranged from 1200 to 1500 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.

0 Radium was detected in five of the indicator samples at concentrations ranging from 7.5 to 14 pCi/L with an average of 10 pCi/L.

It was detected in two control station samples with concentrations of 7.4 and 8.8 pCi/L.

LLD sensitivities for the remaining sample locations, both indicator and control, ranged from <2.4 to <13 pCi/L.

The maximum preoperational level,detected was <30 pCi/L.

Strontium-89 and strontium-90 analyses were performeq on three indicator station samples and one control station sample from the first sampling period in July, as management audit samples.

0 Strontium-89 was not detected in any of the three indicator samples analyzed nor in the control station sample.

LLD sensitivities for both the indicator and the control station samples were <1.0 pCi/L.

The maximum preoperational level detected was 14 pCi/L.

0 Strontium-90 was detected in two of the three indicator samples and the one control station sample analyzed.

Average concentrations for the indicator station samples was 2.0 pCi/L.

The Sr-90 concentration in the control station sample was 2.5 pCi/L.

The maximum preoperational level detected was 12 pCi/L, with an average of 3.5 pCi/L.

The presence of Sr-90 in the samples can be attributed to fallout from previous nuclear weapons testing.

Well Water (Ground Water) (Tables C-7, C-8)

Although wells in the vicinity of the Salem and Hope Creek Generating Station are not directly affected by plant operations, water samples.were collected monthly from one well during January

, through December of the year.

Each sample was analyzed for gross alpha, gross beta, tritium, I-131 and gamma emitters.

Gross alpha activity was detected in nine of the well samples

, at concentrations ranging from 0.9 to 2.4 pCi/L and an average of 1.5 pCi/L.

The maximum preoperational level detected was 9.6 p.Ci/L.

There was no preoperational average determined for this analyses.

Gross beta activity was detected in all twelve well samples.

Concentrations for the samples ranged from 2.3 to 11 pCi/L, with an average of 10 pCi/L.

The maximum preoperational level detected was 38 pCi/L, with an average of 9 pCi/L.

Tritium activity was detected in only one of twelve well water samples at a concentration of 170 pCi/L.

The LLD sensitivities ranged from <120 to <140 pCi/L. The maximum preoperational level detected was 380 pCi/L.

Gamma spectrometric analysis performed on each of the twelve well water samples indicated the presence of the naturally-10

occurring radionuclides**K-40 and' Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Radium was detected in all twelve of the well samples at concentrations ranging from 61 to 238 pCi/L with an average of 128 pCi/L.

The maximum preoperational level detected was 2.0 pCi/L.

These values are similar to those found in the past few years. However, as with the 1989 through 1995 results, they are higher values than found in the preoperational program.

We believe that results are higher due to a procedural change in which the samples are no longer boiled down to a 100 ml standard geometry.

This change results in less removal of radon (and its daughters) from the sample.

Since Ra-226 is an alpha emitter, its identification by gamma isotopic analysis is obtained by counting the gamma rays from Pb-214, one of its daughter products.

We believe that values currently being observed are typical for this geographical area.

0 Potassium-40 was detected in one of the samples with a concentration of 67 pCi/L.

The maximum preoperational level detected was 30 pCi/L.

Iodine-131 was not detected in any of the twelve well water samples.

LLD sensitivities for all the samples ranged from

<0.1 to <0.8 pCi/L.

Potable Water (Drinking Water) (Tables C-9, C-10)

Both raw and treated potable water samples were collected from the Salem water treatment plant.

Each consisted of daily aliquots composited into a monthly sample.

The raw water source for this plant is Laurel Lake and adjacent wells.

Each of the 24 individual samples was analyzed for gross alpha, gross beta, tritium, iodine-131 and gamma emitters.

Gross alpha activity was detected in ten raw water samples at concentrations of 0.6 to 2.3 pCi/L and in one treated water sample at 1.0 pCi/L.

The averages for both raw and treated water samples was 1.1 pCi/L.

The maximum pre-operational level detected was 2.7 pCi/L.

Gross beta activity was detected in all 24 samples at concentrations ranging from 2.4 to 4.1 pCi/L for both the raw and treated water.

The average concentration for both raw and treated was 3.3 pCi/L.

The maximum preoperational level detected was 9.0 pCi/L, with an average of 4.2 pCi/L.

Tritium activity was only detected in one raw water sample at a concentration of 200 pCi/L.

LLD sensitivities for the remaining 23 samples ranged from <120 to <150 pCi/L.

The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

11

Iodine-131 measurements to a sensitivity of 1.-o pCi/L were performed.

Since the receiving water body (Delaware River) is brackish, the water is not used for human consumption.

Drinking water supplies are not affected by discharges from the site.

Iodine-131 measurements for all 24 samples were below the LLD sensitivities.

The LLD sensitivities_ranged from <0.1 to <0.4 pCi/L.

Gamma spectrometric analysis performed on each of the 24 monthly water samples indicated the presence of the naturally-occurring radionuclides K-40,Th-232 and Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 The radionuclide K-40 was detected in five of the raw potable water and three treated samples at concentrations ranging from 39 to 67 pCi/L.

There was no preoperational data available fo.r comparison.

0 Radium was detected in three potable raw and in four treated samples at a range of 4 to 18 pCi/L.

LLD sensitivities for both raw and treated waters ranged from <1.5 to <5.8 pCi/L.

The maximum preoperational level detected was 1.4 pCi/L.

0 Thorium-232 was detected in only one potable raw sample at a concentration of 11 pCi/L.

LLD sensitivities for both raw and treated waters ranged from <2 to <10 pCi/L.

There was no preoperational data a,vailable for comp-arison.

Vegetables (Table C-11)

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 four indicator stations (10 samples) and three control stations (8 samples).

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

Gamma spectrometric analysis performed on each of the eighteen samples indicated the presence of the naturally occurring radionuclide K-40,Th-232 and Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in all eighteen samples.

Concentrations for the ten indicator station samples ranged from 1360 to 2530 pCi/kg-wet and averaged 2000 pCi/kg-wet.

Concentrations for the eight control station samples ranged from 1500 to 2740 pCi/kg-wet, and averaged 2200 pCi/kg.:.wet.

The average concentration detected for all samples, both indicator and control, was 2050 pCi/kg-wet.

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

12

0 Radium was detected in four indicator station samples ranging from 24 to 36 pCi/kg-wet.

It was detected in one control station sample at a concentration of 23 pCi/kg-wet.

There was no preoperational data available for comparison.

0 Thorium-232 was detected in only one indicator tomato sample at a concentration of 44 pCi/kg-wet.

LLD sensitivities for all the other vegetables, indicator and control, ranged from <12 to <55 pCi/L.

There was no preoperational data available for comparison.

Game (Table C-12)

Although not required by the SGS or HCGS Technical Specifications, samples of muskrats, inhabiting the marshlands surrounding the site, are collected.

This game is consumed by local residents. *The samples, when available, are collected from two locations once a year as management audit samples and analyzed for gamma emitters.

Gamma spectrometric analysis of the flesh indicated the presence of the. naturally-occurring radionuclides K-40 and Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in the indicator station sample at a concentration of 2490 pCi/kg~wet and the control station sample at 2030 pCi/kg-wet.

The average f0r both muskrat samples was 2260 pCi/kg-wet.

The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4400 pCi/kg-wet.

0 Radium was detected in the one control station sample at a concentration of 49 pCi/kg-wet, but not in the indicator station sample.

The maximum preoperational level detected was 1000 pCi/kg-wet, with no average available for comparison.

Fodder Crops (Table C-13)

Although not required by the SGS or HCGS Technical Specifications, seven samples of crops normally used as cattle feed were collected from three indicator stations (5 samples) and one control station (2 samples).

It was determined that these products may be a significant element in the food-chain pathway.

Fodder crops are collected as management audit samples and analyzed for gamma emitters.

All of the locations from which samples were collected this year are milk sampling stations.

Samples collected for wet gamma analysis were silage and soybeans.

.Gamma spectrometric analysis performed on each of the seven samples indicated the presence of the naturally-occurring radionuclides Be-7, K-40, Th-232 and Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

13

0 Radium was detected -in one of the indicator station soybean samples at a concentrations of 14 pCi/kg-wet and in one of the control station soybean samples at a concentration of 19 pCi/kg-wet.

Radium was not detected in any of the silage samples.

LLD sensitivities for the remaining five indicator and control station samples ranged from <11 to-<14 pCi/kg-wet.

No pre-operational data is available for comparisons.

0 Thorium-232 was detected in only one of the indicator station silage samples at a concentration of 52 pCi/kg-wet.

LLD sensitivities for the remaining six indicator and control station samples ranged from <15 to <29 pCi/kg-wet.

No pre-operational data is available for comparisons.

0 Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in two of the indicator silage samples at concentrations of 1040 and 1390 pCi/kg-wet.

It was detected in the control station silag~ sample at 860 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 detected in one of the indicator station soybean samples at a concentration of 90 pCi/kg-wet.

LLD sensitivities for the remai_ning soybean samples ranged from

<31 to <55 pCi/kg-wet.

The maximum preoperational level detected for soybean samples was 9300 pCi/kg-dry.

0 Potassium-40 was detected in all seven samples.

Con-centrations for the five indicator station samples ranged from 3040 to 15200 pCi/kg-wet and for the two control station samples from 3030 to '18500 pCi/kg-wet.

The average concentration detected for the silage samples (both indicator and control) was 3200 pCi/kg-wet which was comparable to preoperational results which averaged 7000 pci/kg-wet.

Although the Maplewood Testing Services no longer reports results based upon the dry weight of the sample, soybean results were comparable to preoperational studies.

Results averaged 15300 pCi/kg-wet which was comparable to preoperational results of 22000 pCi/kg-dry.

AQUATIC All aquatic samples were collected by Environmental Consulting Services, Inc. and delivered by PSE&G personnel.

Surface water samples were collected in new polyethylene containers which 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 placed in sealed polyethylene containers and frozen before being transported in ice chests.

14

Sediment samples were takeri -*with a bottom grab sampler and frozen in sealed polyethylene containers before being transported in ice chests.

Surface Water (Tables C-14, C-15, C-16)

Surf ace water samples were collected monthly at four 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 th,e 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 12Cl, at the mouth of the Appoquinimink River, serves as the operational control.

All' surface water samples were analyzed monthly for gross beta and gamma emitters.

Quarterly composites were analyzed for tritium.

Gross beta activity was detected in 47 of the indicator station samples ranging from 4 to 151 pCi/L, with an average of 40 pCi/L.

Beta activity was detected in all 12 of the control station samples with concentrations ranging from 6 to 106 pCi/L, with an average of 37 pCi/L.

The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L.

Tritium activity was detected in one of the control station samples at a concentration of 140 pCi/L.

There was no tritium detected in any of the indicator station composites.. LLD sensitivities for the remaining composites, both indicator and control, ranged from <120 to <140 pCi/L.

The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L.

Gamma spectrometric analysis performed on each of_ the forty-eight indicator station and twelve control station surface water samples indicated the presence of the naturally-occurring radionuclides K-40, Th-232 and Radium.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in 34 samples from the indicator station samples at concentrations ranging from 21 to 147 pCi/L and in 11 of the control station samples ranging from 29 to 93 pCi/L.

The average for the indicator station locations was 73 pCi/L, while the average for the control station locations was 67 pCi/L.

The maximum preoperational level detected was 200 pCi/L, with an average of 48 pCi/L.

0 Radium was detected in 9 samples out of the 48 indicator stations with ranges from 4.9 to 11 pCi/L, and an average concentration of 6.2 pCi/L.

It was detected in 4 of the control station samples ranging from 5.1 to 8.6 pCi/L and an average concentration of 6.9 pCi/L.

The maximum preoperational level detected was 4.0 pCi/L.

15

0 Thorium-232 was detected in two indicator station samples at a concentration of 7.1 and 11 pCi/L.. Th-232 was detected*in one of the control station samples at a concentration of

  • 9.8 pCi/L.

LLD sensitivities for the remaining indicator and control station samples were <2.5 to <11 pCi/L.

No preoperational data.available.

Fish (Table C-17)

Edible species of fish locations and analyzed Sr-90 (bones & flesh).

perch and striped bass.

were collected semi-annually at three for gamma emitters (flesh), and for Sr-89 and Samples included catfish, weakfish, white Gamma spectrometric analysis performed on each of the four indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclide K-40.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in all four samples from the two indicator stations at concentrations ranging from 2550 to 4000 pCi/kg-wet for an average of 3310 pCi/kg-wet.

K-40 was detected in both samples from the control station locations at 2270 and 3500 pCi/kg-wet.

The average for the control samples was 2880 pCi/kg-wet.

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

Strontium-89 and strontium-90 analyses were performed by Yankee Atomic Environmental Laboratory (YAEL)on the first semi-annual sample collection (2 indicator and 1 control location).

These are management audit analyses analyzed in recognition of the high bioaccumulation factor of strontium in bone.

0 Strontium-89 was not detected in any of the indicator or control station bone samples.

LLD sensitivities for the samples, both indicator and control, were <2000 pCi/kg-dry.

The maximum preoperational level detected was 100 pCi/kg-dry.

0 Strontium-90 was not detected in any of the indicator or control station bone samples.

LLD sensitivities for the samples, both indicator and control, were <200 pCi/kg-dry.

The maximum preoperational level detected was 940 pCi/kg-dry, with an average of.335 pCi/kg-dry.

0 Strontium-89 of the flesh was not detected in any of the indicator or control station samples.

LLD sensitivities for the three samples, indicator and control, were <2000 pCi/kg-wet.

The preoperational level ranged from <4.1 to <100 pCi/kg-wet.

0 Strontium-90 of the flesh was not detected in any of the indicator or control station samples.

16

LLD

  • sensi ti vi ties for the three. samples, indicator and

.control, were <200 pCi/kg-wet.

The maximum preoperational level detected was 67 pCi/kg-wet.

Blue Crab (Table C-18)

Blue crab samples were collected semi-annually at two locations; one indicator and one control, and the edible portions were analyzed for gamma emitters, Sr-89 and Sr-90(first collection period only).

The crab shells were also analyzed for Sr-89 and Sr-90 (first collection period only).

All strontium analyses were reported by YAEL.

Gamma spectrometric analysis on the flesh of each of the two indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclide K-40.

All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in both indicator station samples at concentrations of 2780 and 2940 pCi/kg-wet and in both of the control station samples at 3060 and 3080 pCi/kg-wet.

The average for both the indicator and control station samples was 3000 pCi/kg-wet.

The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 pCi/kg-wet.

Strontium-89 and strontium-90 analyses were performed on the flesh and shell of each of the indicator station and control station samples, as management audit analyses.

Strontium analysis of the shell is performed because of the reconcentration factor of strontium in crab shells.

0 Strontium-89 of the flesh was not detected in any of the indicator or control samples.

LLD sensitivities for. these samples were <2000 pCi/kg-wet.

The maximum preoperational level detected was <51 pCi/kg-wet.

0 Strontium-89 of the shell was not detected in any of the samples, indicator nor control.

LLD sensitivities for all the samples, indicator and control, were <2000 pCi/kg-dry.

The maximum preoperational level detected was 210 pCi/kg-dry.

0 Strontium-90 of the flesh was not detected in any of the indicator or control samples.

LLD sensitivities for these station samples were <200 pCi/kg-wet.

The maximum preoperational level detected was <150 pCi/kg-wet.

0 Strontium-90 of the shell was not detected in any of the indicator nor control station samples.

LLD sensitivities for these station samples were <200 pCi/kg-dry.

The maximum preoperational level detected was 990 pCi/kg-dry, with an average of 614 pCi/kg-dry.

17

Sediment (Table C-19)

Sediment samples were collected semi-annually from six locations,'

five indicator stations and one control station.

Each of the twelve samples was analyzed by YAEL for Sr-90 (management audit analysis) and gamma emitters.

Although trace levels of man-made nuclides were detected in some sediment samples, these levels were expected and well within the acceptable levels specified in section 3/4.12.1 of the Technical Specifications.

Strontium-90 was not detected in any of the ten indicator station samples nor in any of the control station samples.

LLD sensitivities for these samples, both indicator and control, were <200 pCi/kg-dry.

The maximum preoperational level detected was 320 pCi/kg-dry.

Gamma spectrometric analysis was performed on each of the ten indicator station samples and two control station samples.

In addition to the detection of the naturally-occurring radionuclides Radium, K-40, Be-7 and Th-232, low levels of Mn-54, Co-60, Cs-134, and Cs-137 were also detected.

The presence of these nuclides in the sediment samples may be attributable to radioactive liquid discharges, released within federal and state limits, from Hope Creek and Salem Generating Stations.

All other gamma emitters searched for were <LLD.

0 Manganese-54 was detected in one of the ten indicator stations at a concentration of 37 pCi/kg-dry. It was not detected in any of the control station samples.

LLD sensitivities for the other eleven samples, both indicator and control, ranged from <3.4 to <33 pCi/kg-dry.

No preoperational data is available for comparison.

0 Cobalt-60 was detected in six of the ten indicator stations at concentrations ranging from 18 to 140 pCi/kg-dry, with an average of 68 pCi/kg-dry.

It was not detected in either of the two control stations.

LLD sensitivities for the other six samples, indicator and control, ranged from <7.8 to <14 pCi/kg-dry.

No preoperational data is available for comparison.

0 Cesium-134 was detected in five indicator station samples at concentrations ranging from 56 to 70 pCi/kg-dry, with an average of 62 pCi/kg-dry. It was detected in one control station sample at a concentration of 57 pCi/kg-dry.

LLD sensitivities for the other six samples, indicator and control, ranged from <4.5 to <68 pCi/kg-dry.

No pre-operational data is available for comparison.

0 Cesium-137 was detected in six indicator station samples at concentrations ranging from 14 to 160 pCi/kg-dry.

It was not detected in either control station sample.

The LLD sensitivities for the other six samples, both indicator and control, ranged from <9.9 to <19 pCi/kg-dry.

The maximum preoperational level detected was 400 pCi/kg-dry with an average of 150 pCi/kg-dry.

18

0 Potassium-40 was detected in all ten indicator station samples at concentrations ranging from 2710 to 19200 pCi/kg-dry, with an average of 13750 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 14900 and 18100 pCi/kg-dry.

The average for both the indicator and control station samples was 14000 pCi/kg-dry.

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

0 Radium was detected in all ten indicator station samples at-concentrations ranging from 150 to 1450 pCi/kg-dry, with an average of 700 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 630 and 890 pCi/kg-dry, with an average of 760 pCi/kg-dry.

The average for both the indicator and control station samples was 710 pCi/kg-dry.

The maximum preoperational level detected was 1200 pCi/kg-dry, ~ith an average of 760 pCi/kg-dry.

0 Thorium-232 was detected 'in all ten indicator station samples at concentrations ranging from 185 to 1540 pCi/kg-dry, with an average of 930 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 980 and 1190 pCi/kg-dry, with an average of 1080 pCi/kg-dry.

The average for both the indicator and control station samples was 960 pCi/kg-dry.

The maximum preoperatiorial level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.

0 Beryllium-7.was detected in two of the ten indicator station samples at concentrations of 734 and 1040 pCi/kg-dry but not in either of the control station samples.

The LLD sensitivities for the remaining eleven samples, both indicator and control, ranged from <38 to <285 pCi/kg-dry.

The maximum preoperational level detected was 2300 pCi/kg-dry.

19

PROGRAM DEVIATIONS

1.

The following air samplers were unavailable due to outages and tripped breakers associated with inclement weather and electrical surges (2F6 and 5Dl) and air sampler malfunction (5Sl) :

STATION 5Sl 2F6 5Dl LOCATION 1.0 mi., East of Vent 7.3 mi., NNE of Vent 3.5 mi., East of Vent HOURS UNAVAILABLE 123.4 (1.4%)

380.1 (4.4%)

265.2 (3.0%)

Surge Protectors were installed on all the air samplers to help correct the problem with electrical surges.

The total availability of all air samplers used in the program was 98.5%.

2.

During the period 12/26/95 to 4/01/96, two thermoluminescent dosimeters (.TLD's) were unavailable.

The quarterly and annual dosimeters at location 7F2 (9.1 mi., SE of Vent) were vandalized.

The result for the annual TLD was for three quarters only.

CONCLUSIONS The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted during 1996 in accordance with the SGS and HCGS Technical Specifications.

The Lower Limit of Detection (LLD) values required by the Technical Specifications 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 Units One and Two and HCGS were operated in compliance with Technical Specifications.

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 Salem and Hope Creek Generating Stations 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, we can conclude that the operation of SGS Units One and Two and HCGS had no significant impact on the radiological characteristics of the environs of that area.

20

MEDIUM I. ATMOSPHERIC ENYIRONMENT

a. Air Particulate
b. Air Iodine II. DIRECT RADIATION
a. Thermoluminescent Dosimeters III. Terrestrial Environment
a. Milk TABLE 1 SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE INDICATOR CONTROL 5Sl 501 16El lFl 2F6 5Sl 501 16El lFl 2F6 lSl 2S4 3Sl 4Sl 2S2 501 2El lFl 5Sl 1001 3El 2F2 6S2 1401 13El 2F6 7Sl 1581 1681 4F2 1081 16El 5Fl 6Fl 1181 781 llFl 13F4 4D2 9El 2F5 3F2 11E2 15Dl 12El 3F3 16F2 10F2 12Fl 13F2 13F3 14F2 15F3 2F7 11F3 14F4 3Gl 3H3 3H3 3Gl 3Hl 3H3 1G3 lOGl 16Gl COLLECTION FREQUENCY Weekly Weekly Quarterly Monthly (when animals are on pasture)

Semi-monthly (when animals are on pasture)

TYPE/FREQUENCY* OF ANALYSIS Gross beta/weekly Gamma scan/quarterly Iodine-131/weekly Gamma dose/ quarterly Iodine-131/monthly

  • Gamma scan/monthly Iodine-131/semi-monthly Gamma scan/semi-monthly 8r89 &8r90/July, first collection

N N

MEDIUM

b. Well Water
c. Potable Water (Raw & Treated)
d. Vegetables
e. Game (Muskrat)
f.

Fodder Crops TABLE 1 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE INDICATOR 3El 2F3 3El 2F4 3F5 2F8 14F3 llDl 3El 2F7 11F3 14F4 CONTROL lGl 3H5 3G2 3Gl COLLECTION FREQUENCY Monthly Monthly (composited daily)

Annually (at* harvest)

Semi-annually Annually TYPE/FREQUENCY* OF ANALYSIS Gross alpha/monthly Gross beta/monthly Tritium/monthly Gamma scan/monthly Gross alpha/monthly Gross beta/monthly Tritium/monthly Gamma scan/monthly Gamma.scan/on collection Gamma sca.n/on collection Gamma scan/on collection

MEDIUM IV. AQUATIC ENVIRONMENT

a. Surface Water
b. Edible Fish
c. Blue Crabs
d. Sediment
  • Except for Tlds, the quarter.

TAB:CE 1 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE INDICATOR CONTROL llAl 7El 1F2 12Cl 16Fl llAl llAl llAl 15Al 16Al quarterly 7El 12Cl 16Fl 12Cl 7El 16Fl 12Cl analysis is performed on a COLLECTION FREQUENCY Monthly Semi-annually Semi-annually Semi-annually composite of TYPE/FREQUENCY* OF ANALYSIS Gross beta/monthly Gamma scan/monthly Tritium/quarterly Sr-89 & Sr-90 (bones)/on collection**

Sr-89 & Sr-90 (flesh/on collection**

Gamma scan (flesh)/on collection sr~89 & Sr-90 (flesh)/on collection Sr-89 & Sr-90 (shell)/on collection Gamma scan (flesh)/on collection Sr-90/on collection Gamma scan/on collection individual samples collected during the

    • Management audit analyses, not required by Technical Specifications or by specific commitments to local officials.

FIGURE 1 BETA IN AIR PARTICULATE 1973 THROUGH 1996 1000 --~~~~~~~~~~~~~~~~~~~~~~~~~~~----

Weapons Test

  • 06-17-74 100 10 1

i WeaponeTeot WeaponeTeot 0[6 __ j"'M7

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I-Chernobyl 04-26-86 1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 I QUARTERLY AVERAGE I

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FIGURE 2 AMBIENT RADIATION £0 OFFSITE vs CONTROL STATION 1973 THROUGH 1996 8

Weapons Test 06-17-74 Weapons 1rest 09-26-76 Weapons' Test 03-14-78 Chernobyl 04-26-85 OFf'.. SITE STATIONS CONTROL STATIONS

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1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 I QUARTERLY AVERAGE I

10 N

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0 Weapons Test 06-17-7!

FIGURE 3 iODINEc131 ACTIVITY IN MILK 1973 THROUGH 1996

  • -ct11-Weapons Tut 09-26-76 E:
  • ii (j)

Weapotus Test 09-17-77 03-14-78 l ~aponsT*

&t.ire&f>Yi 1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 I QUARTERLYAVERAGE 1.

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FIGURE 5 TRITIUM ACTIVITY IN SURFACE WATER 1973 THROUGH 1996 Weapons Test Wea~ns ll"est OS-17-74 09-'17-77 Wea:mTea I 09-26-78

+

~

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1000 200 50 FIGURE 6A CESIUM QJ 137 IN WATER SEDIMENT 1977 THROUGH 1996 1977 1979 1981 Ciiemobyi 04-26-86 i

1983 1985 1987 1989 1991 1993 1995 1997 I SEMI-ANNUAL AVERAGE I

w 0

(';

~

--0 Q.

FIGURE6B COBALT... 60 IN WATER SEDIMENT 1977 THROUGH 1996 10000...-----.,_----=-=..---=------=--,,,_,..-=--------

1000 200 50 1977 Weapo111s Test 09-17-77

~

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>-O 0

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1979 1981 1983 Chernobyl 04-28-86

_i 1985 1987 1989 1991 1993 1995 1997 I SEMI-ANNUAL AVERA.GE I

REFERENCES

[l]

Radiation Management Corporation.

"Artificial Island Radiological Environmental Monitoring Program - Annual Reports 1973 through 1982".

[2]

Radiation Management Corporation.

"Artificial Island Radiological Environmental Monitoring Program - Preoperation Summary_- 1973 through 1976".

RMC-TR-77-03, 1978.

[3]

Radiation Management Corporation.

"Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976".

RMC-TR-77-02, 1977.

[4]

PSE&G's Maplewood Testing Services.

"Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program - Annual Reports 1983 through 1995".

[5]

Public Service Electric and Gas Company.

"Environmental Report, Operating License Stage -

Salem Nuclear Generating Station Units 1 and 2".

1971.

[6]

Public Service Electric and Gas Company.

"Environment".ll Report, Operating License Stage -

Hope Creek Generating Station".

1983.

[7]

United States Atomic Energy Commission.

"Final Environmental Statement -

Salem Nuclear Generating Station, Units 1 and 2".

Docket No. 50-272 and 50-311. 1973.

[8]

United States Atomic Energy Commission.

"Final Environmental Statement -

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

[9]

Public Servic.e Electric and Gas Company.

"Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2".

1982.

[10]

Public Service Electric and Gas Company.

"Updated Final Safety Analysis Report - Hope Creek Generating Station.

[11]

Public Service Electric and Gas Company.

"Salem Nuclear Generating Station Unit 1 - Technical Specifications", Appendix A to Operating License No. DPR-70, 1976, Sections 3/4.12 and 6.9.1.10 (Amendment 59 ~ ~).

[12]

Public Service Electric and Gas Company.

"Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix A to Operating License No.

DPR-75, 1981, Sections 3/4.12 and 6.9.1.10 (Amendment 28 ~

~).

[13]

.Public Service Electric and _Gas Company.

"Hope Creek Generating Station Unit 1 - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and *6.9.1.10.

31

REFERENCES (cont'd)

[14]

Public Service Electric and Gas Company.

"Off site Dose Calculation Manual"

- Salem Generating Station.

[15]

Public Service Electric and Gas Company.

"Off site 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]

PSE&G Research and Testing Laboratory.

"Environmental Section Quality Assurance Plan." August, 1994.

[18]

PSE&G Maplewood Testing Services.

"Environmental and Chemical Services Division Procedures Manual."

March, 1996.

[19]

Public Service Electric and Gas Company.

"Radioactive Effluent Release Reports, SGS RERR-40 and RERR Salem Generating Station. 1996.

[20]

Public Service Electric and Gas Company.

"Radioactive-Effluent Release Reports, HCGS RERR-19 and RERR Hope Creek Generating Station. 1996.

[21]

United States Nuclear Regulatory.Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants.

32

APPENDIX A PROGRAM

SUMMARY

33

MEDIUM OR PATHWAY SAMPLE (UNIT OF MEASUREMl;NT I. AIRBORNE Air Particulates (10.a pCi/m3) w lJ1 Air Iodine (10.a pCilm)

II DIRECT Direct Radiation (mrad/sld. month)

Ill TERRESTRIAL Milk

{pCi/L)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 DOCKET NO. 50-353 HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY JANUARY 1, 1996 to DECEMBER 31, 1996 Analysis And Lower All Indicator Locations Location with Hi1:1hest Mean Total Number Limit of Mean Name Mean of Analyses Detection (Range)

Distance and Direction (Range)

Performed (LLD)*

Beta 318 6.0 22 (260 /265 )

5S11.0 mi E 23 (51 /53)

(7-41)

(10-36) 1F1 5.8 mi N Gamma Be?

24 6.8 68 (20 /20) 5S11.0 mi E 76 (4 /4)

(41-102)

(50-102)

K-40 24 0.3 13 (9/20) 16E1 4.1 mi NNW 16 (2/4)

(10-19)

(12-19)

Ra-NAT 24 0.3 1.5 (2 /20) 16E1 4.1 mi NNW 1.7 (1 /4)

(1.4-1. 7)

(1.7-1.7) 1-131 318 13 LLD

<LLD Quarterly 196 4 (172 /172) 7S1 0.12 mi SE 5.4 (4 /4)

Badges (2.4-5.5)

(3.1-7.4) 1-131 80 0.4

<LLD

<LLD Sr-89 4

1.0

<LLD

<LLD Sr-90 4

0.9 2 (2 /3) 3G117miNE 2.5 (1 /1 )

(1.8-2.3)

(2.5-2.5)

Gamma K-40 80 120 1300 (60 /60 )

14F4 7.6mi WNW 1400 (20 /20 )

(1200-1400)

(1200-1400)

Control Location Number of Mean Nonroutine (Range)

Reported Measurements 21 (53 /53) 0 (9-33) 61 (4 /4) 0 (57-73) 14 (2 /4) 0 (13-14)

<LLD 0

<LLD 0

4.4 (24 /24) 0 (3.2-5.4)

<LLD 0

<LLD 0

<LLD 0

1300 (20 /20 )

0 (1200-1500)

MEDIUM OR PATHWAY

  • SAMPLE (UNIT OF MEASUREMENT Ill TERRESTRIAL Milk

.(pCi/L)

Well Water (pCi/L)

UJ

°'

Potable Water (pCi/L)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 DOCKET NO. 50-353 HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY JANUARY 1, 1996 to DECEMBER 31, 1996 Analysis And Lower All Indicator Locations Location with Hi1;1hest Mean Total Number Limit of.

Mean Name Mean of Analyses Detection (Range)

Distance and Direction (Range)

Performed (LLD)*

RA-NAT 80 7.8 10 (5 /60) 14F4 7.6mi WNW 10 (3 /20)

(7.5-14)

(7-12)

Alpha 12 1.2 1.5 (9 /12) 3E1 4.1 mi NE 1.5 (9 /12)

(0.9-2.4)

(0.9-2.4)

Beta 12 1.0***

9.6 (12 /12) 3E1 4.1 mi NE 9.6 (12 /12)

(2.3-11)

(2.3-11)

H-3 12 150

<LLD

.3E1 4.'1 mi NE 170 (1 /12)

(170-170)

Gamma K-40 12 35 67 (1 /12) 3E1 4.1mi NE 67 (1 /12)

(67-67)

(67-67) 1-131 12 0.6

<LLD

<LLD RA-NAT 12 7.4 128 (12 /12) 3E1 4.1mi NE 128 (12 /12)

(61-238)

(61-238)

Alpha 24 1.0 1.1 (11 /24) 2F3 8.0 mi NNE 1.1 (11 /24)

(0.6-2.3)

(0.6-2.3)

Beta 24 1.0***

3.3 (24 /24) 2F3 8.0 mi NNE 3.3 (24 /24)

(2.4-4.1)

(2.4-4.1)

H-3 24 150 200 (1 /24) 21=3 8.0 mi NNE 200 (1 /24)

(200-200)

(200-200)

Gamma K-40 24 35 47 (7 /24) 2F3 8.0 mi NNE 47 (7124)

(20-67)

(20-67) 1-131 24 0.6

<LLD

<LLD RA-NAT 24 7.4 12 (6/24) 2F3 8.0 mi NNE 12 (6 /24)

(4-18)

(4-18)

Th-232 24 7

11 (1 /24) 2F3 8.0 ml NNE 11 (1 /24)

(11-11)

(11-11)

Control Location Number-of Mean Nonroutine (Range)

Reported Measurements 8.1 (2 /20) 0 (7.4-8.8)

No Control 0

Location No Control 0

Location No Control 0

Location No Control 0

Location No Control 0

Location No Control 0

Location No Control 0

Location No Control 0

Location No Control 0 -

Location No Control 0

Location No Control 0

Location No Control 0

Location No Control 0

Location

)

MEDIUM OR PATHWAY SAMPLE (UNIT OF MEASUREMENT Ill TERRESTRIAL Fruit &

Vegetables (pCi/Kg-wet)

Game VJ (pCi/Kg-wet)

Fodder Crops (pCi/Kg-wel)

IV AQUATIC Surface Water (pCi/L)

(

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 DOCKET NO. 50-353 HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY JANUARY 1, 1996 to DECEMBER 31, 1996 Analysis And Lower All Indicator Locations Location with Highest Mean Total Number Limit of Mean Name Mean of Analyses Detection (Range)

Distance and Direction (Range)

Performed (LLD)*

Gamma K-40 18 70 2000 (10 /10) 2G2 13.5 mi NNE 2300 (1 /1 )

(1360-2530)

(2300-2300)

RANAT 18 15 29 (4 /10) 3F5 9.4 mi NE 36 (1 /2)

(24-36)

(36-36)

Th-232 18 31 44 (1 /10) 3F5 9.4 mi NE 44 (1 /2 )

(44-44)

(44-44)

Gamma K-40 2

70 2490 (1 /1 )

3E1 4.1 mi NE.

2490 (1 /1 )

(2490-2490)

(2490-2490)

RANAT 2

15

<LLD 11D1 3.5 mi SW 49 (1 /1 )

(49-49)

Gamma Be-7 7

85 840 (3 /5) 14F4 7.6 mi WNW 1390 (1 /2)

(88-1390)

(1390-1390)

K-40 7

50 9900 (5 /5) 11F3 5.3 mi SW 14100 (1 /1 )

(3040-15200)

(14100-14100)

RA-NAT 7

15 14 (1 /5) 3G1 17 mi NE 19 (1/2)

(14-14)

(19-19)

Th-232 7

31 52 (1 /5) 14f4 7.6 mi WNW (52-52)

Beta 60 3.8 40 (47 148) 7E1 4.5 mi SE 68 (12 /12)

(4-151)

(11-151)

H-3 60 150

<LLD 12C12.5miWSW 140 (1 /4)

(140-140)

Gamma K-40 60 35 74 (33 /48) 7E1 4.5 mi SE 85 (11 /12)

(21-147)

(53-147)

Control Location Number of Mean Nonroutine (Range)

Reported Measurements 2200 (8 /8) 0 (1500-2740) 23 (1 /8)

(23-23)

<LLD 2030 (1 /1 )

0 (2030-2030) 49 (1 /1 )

0 (49-49) 860 (1 /2) 0 (860-860) 10800 (2 /2) 0 (3030-18500)

<LLD 0

<LLD 0

37 (12/12) 0 (6-106) 140 (1 /4) 0 (140-140) 67 (10 /12) 0 (29-93)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION DOCKET 50-272/-311 DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1996 to DECEMBER 31, 1996

w*

l..O MEDIUM OR PATHWAY SAMPLE (UNIT OF MEASUREMENT IV AQUATIC Sediment (pCi/kg-dry)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 DOCKET NO. 50-353 HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY JANUARY 1, 1996 to DECEMBER 31, 1996 Analysis And Lower All Indicator Locations Location with Hi~hest Mean Total Number Limit of Mean Name Mean of Analyses Detection (Range)

Distance and Direction (Range)

Performed (LLD)*

K-40 12 70 13750 (10 /10) 16F1 6.9 mi NNW 18300 (2 /2)

(2710-19200)

(17400-19200)

Mn54 12 28 37 (1/10) 15A1 0.3 mi NW 37 (1 /2 )

(37-37)

(37-37)

Co-60 12 40 68 (6 /10) 16A1 0.7 mi NNW 140 (1 /2)

(18-140)

(140-140)

Cs-134 12 34 62 (5/10) 16A1 0.7 mi NNW 70 (1 /2)

(56-70)

(70-70)

Cs-137 12 25 106 (6 /10) 15A1 0.3 mi NW 156 (2/2)

(14-160)

(152-160)

RA-NAT 12 40 700 (10 /10) 11A10.2miSW 800 (2 /2)

(150-1450)

(150-1450)

Th~232 12 50 930 (10 /10) 12C1 2.5 mi WSW 1080 (2 /2)

(185-1540)

(980-1190)

Control Location Mean (Range) 16500 (2 /2)

(14900-18100)

<LLD

<LLD 57 (1 /2)

(57-57)

<LLD 760 (2 /2)

(630-890) 1080 (2 /2)

(980-1190)

  • 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 the LLD values shown. All strontium results are reported by YAEL.
    • Mean calculated using values above LLD only. Fraction of measurements above LLD are *in parentheses.
      • Typical LLD values.

Number of Non routine Reported Measurements 0

0 0

0 0

0 0

APPENDIX B SAMPLE DESIGNATION AND LOCATIONS

.41

APPENDIX B SAMPLE DESIGNATION The PSE&G Maplewood Testing Services identifies samples by a three part code.

The first two letters are the power station identification code, in this case "SA".

The next three letters are for the media sampled.

AIO Air Iodine

.IDM =

Immersion Dose (TLD)

APT = Air Particulates MLK =

Milk ECH = Hard Shell Blue Crab PWR = *Potable Water (Raw)

ESF = Edible Fish PWT Potable Water (Treated)

ESS = Sediment RWA Rain Water (Precipitation)

FPB = Beef SOL =

Soil FPL Green Leafy Vegetables SWA =

Surf ace 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 the site.

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; i.e., 2=NNE, 3=NE,

  • 4=ENE, etc.
  • The next digit is a letter which represents the radial distance from the plant:

s = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F =

5-10 miles off-site B = 1-2 miles off-site G

10-20 miles off-site c = 2-3 miles off-site H =

>20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,...

For example, the designation SA-WWA-3El would indicate a sample in the SGS program (SA),

consisting of 'well water (WWA), which had been collected in sector number 3, centered at 45° (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.

43

.i:--

.i:--

TABLE B-1 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 Trimble Portable Global Positioning System (GPS) was used to provide the coordinates of sampling locations.

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. 'MIN. SEC DEG. MIN. SEC lSl 0.55mi. N of vent 39 -

28 - 15.8 75 15.6 IDM 2S2 o.4 mi. NNE of vent 39 05.9 75 57.8 IDM 2S4 0.59 mi. NNE of vent 39 -

28 - 17.5 75 56.1 IDM 3Sl

o. 58 mi. NE of vent 39 07.7 75 38.9 IDM 4Sl 0.60 mi. ENE of vent 39 02.6 75 31. 8 IDM 5Sl
1. 0 mi. E of vent; site access road 39 37.5 75 06.9 AIOI APT I IDM 6S2 o.2 mi. ESE of vent; observation building 39 52.0 75 09.2 IDM,SOL 7Sl 0.12 mi. SE of vent; station personnel gate 39 43.6 75 02.6 IDM lOSl 0.14 mi. SSW of vent; inlet cooling water bldg.

39 40.4 75 08.1 IDM llSl 0.09 mi. SW of vent; service water inlet bldg.

39 42.7 75 16.6 IDM 15Sl

.0.57 mi. NW of vent 39 10.3 75 32.8

, IDM 16Sl 0.54 mi. NNW of vent 39 14.0 75 26.0 IDM llAl

o. 2 mi. SW of vent; outfall area 39 59 75 25 ECH,ESF,ESS,SWA 15Al O. 3 mi. NW of vent; cooling tower blowdown 39 -

27 -

67 75 19 ESS discharge line outfall 16Al 0.7 mi. NNW of vent; south storm drain discharge 39 -

28 - 24 75 58 ESS line' 12Cl 2.5 mi. WSW of vent; west bank of Delaware River 39 22 75 08 ECH,ESF,ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road 39 -

28 - 09.1 75 31. 9 IDM,VGT 5Dl 3.5 mi. E of vent; local farm 39 23.9 75 -

28 - 21. 7 AIO,APT, IDM lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur 39 37.4 75 44.2 IDM,SOL llDl

3. 5 'mi. SW of vent 39 52.0 75 24.4 GAM 14Dl 3.4 mi. WNW of vent; Bay View*, Delaware 39 -

29 - 01. 8 75 31. 7 IDM 1501 3.8 mi. NW of vent; Rt. 9, Augustine Beach 39 06.6 75 01. 7 IDM 2El 4.4 mi. NNE of vent; local farm 39 -

27 - 37.5 75 25.2 IDM 3El 4.1 mi. NE of vent; local farm 39 -

30 - 09.3 75 09.2 FPB,GAM,IDM,VGT,WWA 3E2 5.7 mi. NE of vent; local farm 39 20.0 75 01.3 FPV 3E3 5.6 mi. NE of vent; local farm 39 46.0 75 22.0 FPV 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek 39 -

25 - 08 75 -

28 - 64 ESF,ESS,SWA 9El 4.2 mi. S of vent 39 10.2 75 -

32 - 44.2 IDM

STATION CODE 11E2 12El 13El 16El lFl 1F2 2F2 2F3 2F4 2F5 2F6 2F7 2F8 3F2 3F3 3F5 4F2 5Fl 5F3 6Fl 7F2 10F2 11F1 11F3 12Fl 13F2 13F3 13F4 14F2 14F3 14F4 15F3 16Fl 16F2 lGl 1G3 2Gl 2G2 3Gl TABLE B-1 (cont'd)

STATION LOCATION 5.0 mi. SW of vent; Rt. 9 4.4 mi. WSW of vent; Thomas Landing 4.2 mi. W of vent; Diehl House Lab 4.1 mi. NNW of vent; Port Penn 5.8 mi. N of vent; Fort Elfsborg 7.1 mi. N of vent; midpoint of Delaware River 8.7 mi. NNE of vent; Salem Substation 8.0 mi. NNE of vent; Salem Water Company

.6.3 mi. NNE of vent; local farm 7.4 mi. NNE of vent; Salem High School 7.3 mi. NNE of vent; Southern Training Center 5.7 mi. NNE of vent; local farm

5. 3 mi.
  • NNE OF vent; local farm 5.1 mi. NE of vent;Hancocks Bridge Municipal Bld 8.6 mi. NE of vent; Quinton Township School 9.4 mi. NE of vent; local farm.

6.0 mi. ENE of vent; Mays Lane, Harmersville 6.5 mi. E of vent; Canton 6.4 mi. E of vent; local farm 6.4 mi. ESE of vent; Stow Neck Road 9.1 mi. SE of vent; Bayside, New Jersey 5.8 mi. SSW of vent; Rt. 9 6.2 mi. SW of vent; Taylor's Bridge Delaware 5.3 mi. SW of vent; Townsend, Delaware 9.4 mi. WSW of vent; Townsend Elementary School 6.5 mi. W of vent; Odessa, Delaware 9.3 mi. W of vent; Redding Middle School, Middletown, Delaware 9.8 mi. W of vent; Middletown, Delaware 6.6 mi. WNW of vent; Boyds Corner 5.4 mi. WNW of vent; local farm 7.6 mi. WNW of vent; local farm 5.4 mi. NW of vent 6.9 mi. NNW of vent; C&D Canal 8.1 mi. NNW of vent; Delaware City Public School 10.3 mi. N of vent; local farm 19 mi. N of vent; N. Church St. Wilmington, Del 12 mi. NNE of vent; Mannington Township, NJ 13.5 mi. NNE of vent; local farm 17 mi. NE of vent; local farm LATITUDINAL DEG. MIN. SEC 39 -

24 - 21. 8 39 -

28 -

51. 6 39 -

28 -

03.4 39 -

30 - 46.6 39 -

32 44.2 39 -

33 -

08 39 -

33 - 38.2 39 -

33 - 42.1 39 -

33 -

2;i..2

39. 32.1 39 -

32 - 43.1 39 -

32 - 37.3 39 -

31 -

51. 9

'39 -

30 - 24.0 39 -

32 - 34.1 39 -

33 - 27.1 39 29 56.0 39 -

28 - 32.0 39 -

20 - 17.0 39 -

26 - 23.4 39 -

22 - 57.0 39 -

23 - 02.0 39 -

24 - 44.6 39 -

24 - 02.9 39 -

26 -

53.0 39 -

27 - 17.9 39 -

27 - 15.1 39 -

25 - 56.9 39 -

29 - 56.8 39 -

30 - 41. 9 39 -

30 - 41.1 39 -

30 -

58.7 39 -

33 -

55 39 -

34 - 10.3 35 -

36 - 25.1 39 -

44 - 16.8 39 -

37 - 32.4 39 -

38 - 16.2 39 -

35 -

54.2 LONGITUDINAL DEG. MIN.

SEC 75 -

35 - 37.2 75 -

36 - 56.7 75 -

36 - 43.3 75 -

34 - 35.8 75 31 - 05.4 75 -

32 -

54 75 -

28 - 03.9 75 -

27 - 19.6 75 -

30 - 33.8 75 -

28 - 32.1 75 -

28 - 49.2 75 -

30 - 54.6 75 -

29 - 18.5 75 -

27 - 34.6 75 -

24 - 42.8 75 -

24 - 50.6 75 26 04.8 75 -

25 - 00.2 75 -

24 - 16.4 75 -

25 -

09.2 75 -

24 - 15.8 75 -

34 -

09.3 75 -

37 - 38.0 75 -

36 - 19.1 75 -

36 - 55.9 75 -

39 - 21. 3 75 -

42 - 34.5 75 -

40 - 59.9 75 -

39 - 04.1 75 46.0 75 -

40 - 47.2 75 -

36 - 35.7 75 -

34 -

25 75 -

35 - 23.6 75 -

29 - 58.4 75 -

32 - 30.4 75 -

26 - 23.5 75 -

26 - 09.8 75 -

16

-49.3 IDM IDM IDM SAMPLE TYPE AIO, APT, IDM, SOL AIO,APT,IDM,SOL SWA AIO,APT,IDM PWR,PWT FPV,FPL,SOL IDM AIO, APT, IDM MLK,VGT,SOL FPV IDM IDM FPV IDM FPV, IDM I SOL FPL IDM IDM IDM IDM MLK,VGT,SOL IDM IDM IDM IDM IDM FPV MLK,VGT,SOL IDM ESS,SWA IDM FPV IDM FPV FPV IDM,MLK,VGT,SOL

STATION CODE lOGl 16Gl 3Hl 3H3 3H5 TABLE B-1 (cont'd)

STATION LOCATION 12 mi. SSW of vent; Smyrna, Delaware 15 mi. NNW of vent; Greater Wilmington Airport 32 mi. NE of vent; National Park, New Jersey 110 mi. NE of vent; Maplewood Testing Services 25 mi. NE of vent; local farm LATITUDINAL DEG. MIN. SEC 39 12.8 39 -

30 - 46.1 39 35.0 40 24.5 39 47.0 LONGITUDINAL DEG. MIN.

SEC 75 -

36 -

07.0 75 -

34 -

3'5.3 75 05.5 74 -

15 - 10.0 75 -

12 - 22.1 SAMPLE TYPE IDM IDM IDM AIO,APT,IDM 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 39° - 27' - 45.3" and Longitude W 75° - 32' - 09.7".

15 13 11 MAP 8-i ON-SITE SAMPLING LOCATIONS M

UM EXCLUSI AREA BDUNDA

<901 METE

)

1 9

47 T \\JER 5

7 N

MAP B-2 SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM OFF-SITE SAMPLING LOCATION 48

APPENDIX C-DATA TABl'.iES 49

APPENDIX C DATA TABLES Appendix C presents the analytical results of the 1996 Radio-logical Environmental Monitoring Program for the period of January 1 to December 31, 1996.

TABLE NO.

C-1 C-2 C-3 C-4 C-5 C-6 C-7 TABLE OF CONTENTS TABLE DESCRIPTION ATMOSPHERIC ENVIRONMENT AIR PARTICULATES 1996 C9ncentrations of Gross Beta Emitters.....................

1996 Concentrations of Gamma Emitters in Quarterly Commposites.

AIR IODINE 1996 Concentrations of Iodine-131..............................

DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS 1996 Quarterly/Annual TLD Results..............................

TERRESTRIAL ENVIRONMENT MILK 1996 Concentrations of Iodine-131 and Gamma Emitters...........

1996 Concentrations of Strontium-89 and Strontium-90...........

WELL WATER 1996 Concentrations of Gross Alpha and Gross Beta Emitters; and Tritium....................................................

51 54 56 57 59 60 62 63

TABLE NO C-8 C-9 C-10 C-11 C-12 C-13 C-14 C-15 C-16 C-17 C-18 DATA TABLES (cont ' d. )

TABLE DESCRIPTION TERRESTRIAL ENVIRONMENT (cont'd) 1996 Concentrations of Iodine 131 and Gamma Emitters...........

64 POTABLE WATER 1996 Concentrations of Gross Alpha and Gross Beta Emitters; and Tritium....................................................

65 1996 Concentrations of Iodine 131 and Gamma Emitters...........

66 FOOD PRODUCTS 1996 Concentrations of Gamma Emitters in Vegetables.............

67 1996 Concentrations of Gamma Emitters in Game..................

68 FODDER CROPS 1996 Concentrations of Gamma Emitters..........................

69 AQUATIC ENVIRONMENT SURFACE WATER 1996 Concentrations of Gross Beta Emitters.....................

70 1996 Concentrations of Gamma Emitters..........................

71 1996 Concentrations of Tritium in Quarterly Composites.........

73 EDIBLE FISH 1996 Concentrations of Strontium-89 and Strontium-90; Tritium and Gamma Emitters................................ *.............

74 BLUE CRABS 1996 Concentrations of Strontium-89 and Strontium-90; Tritium and Gamma Emitters.............................................

75 52

TABLE NO.

C-19 C-20 DATA TABLES (cont'd.)

TABLE DESCRIPTION SEDIMENT 1996 Concentrations of Strontium-90 and Gamma Emitters..........

76 SPECIAL TABLES LLDs 1996 PSE&G Maplewood Testing Services' LLDs for Gamma Spectrometry....................................................

77 53

TABLE C-1 1996 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma

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

MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F6 SA-APT-3H3 SA-APT-501 SA-APT-5S1 AVERAGE January 15+/-2 13+/-2 20+/-2 24+/-2 20+/-2 21+/-2 19+/-8 32+/-3 31+/-3 31+/-2 25+/-2 30+/-3 29+/-3 30+/-6 30+/-3 37+/-3 32+/-3 31+/-3 34+/-3 41+/-3 34+/-8 19+/-2 20+/-2 21+/-2 19+/-2 21+/-2 21+/-2 20+/-2 17+/-2 13+/-2 16+/-2 18+/-2 13+/-2 18+/-2 16+/-5 February 31+/-3 34+/-3 31+/-2 28+/-2 33+/-3 32+/-3 32+/-5 28+/-2 27+/-2 27+/-2 29+/-2

. 19+/-2 22+/-2 25+/-8 20+/-2 19+/-2 19+/-2 16+/-2 18+/-2 21+/-3 19+/-3 11+/-2 7+/-2 16+/-2 12+/-2 13+/-2 13+/-3 12+/-6 March 23+/-2 24+/-2 23+/-2 31+/-3 24+/-2 24+/-3 25+/-6 U1 23+/-2 22+/-2 (1) 25+/-2 24+/-2 25+/-2 24+/-3

.i:--

26+/-3 27+/-3 27+/-3 25+/-3 28+/-3 25+/-3 26+/-2 19+/-2 21+/-2 20+/-2 16+/-2 19+/-2 20+/-2*

19+/-3 26+/-2 24+/-3 25+/-2 29+/-3 22+/-2 16+/-2 24+/-8 April 26+/-2 25+/-3 26+/-6 13+/-2 22+/-2 22+/-3 22+/-10 21+/-3 20+/-2 15+/-2 21+/-2 22+/-2 24+/-3 20+/-7 23+/-2 22+/-2 23+/-2 16+/-2 21+/-2 17+/-2 20+/-6 21+/-2 21+/-2 23+/-2 22+/-2 22+/-2 24+/-2 22+/-2 May 19+/-2 19+/-3 18+/-2 18+/-2 17+/-2 20+/-3 18+/-2 10+/-2 10+/-2 9+/-2 9+/-2 11+/-2 10+/-2 10+/-2.

21+/-2 20+/-2 19+/-2 19+/-2 13+/-2 19+/-2 19+/-6 23+/-2 24+/-2 16+/-2 24+/-2 (1) 24+/-2 22+/-7' June 19+/-2

. 21+/-3 23+/-3 17+/-3 19+/-3 18+/-2 20+/-4 13+/-2 14+/-2 13+/-2 18+/-2 13+/-2 14+/-2 14+/-4 21+/-2 24+/-2 22+/-2 20+/-3 21+/-2 23+/-2 22+/-3 23+/-2 22+/-2 16+/-2 14+/-2 (1) 20+/-2 19+/-7 17+/-2 16+/-2 17+/-2 15+/-2 14+/-2 15+/-2 16+/-2

~

F TABLE C-1 1996 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma

<--------------------------------------------- ST A Tl 0 N ID --------------------------------------------->

MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F6 SA-APT-3H3 SA-APT-5D1 SA-APT-5S1 AVERAGE July 22+/-2 22+/-2 21+/-3 21+/-3 22+/-3 21+/-3 22+/-1 17+/-2 20+/-2 17+/-3 9+/-2 (1) 23+/-3 17+/-10 25+/-2 27+/-3 (1) 26+/-3 21+/-2 26+/-3 25+/-5 16+/-2 20+/-2 12+/-2 17+/-3 15+/-2 (1) 16+/-6.

August 20+/-2 23+/-3 22+/-3 24+/-3 21+/-2 24+/-3 22+/-3 25+/-2 26+/-3 26+/-3 15+/-2 25+/-2 25+/-2 24+/-8 20+/-2 26+/-2 22+/-2 22+/-3 17+/-2 21+/-2 21+/-6 35+/-3 35+/-3 38+/-3 27+/-3 37+/-3 36+/-3 34+/-8 31+/-3 30+/-3 31+/-3 33+/-3 29+/-3 30+/-3 31+/-3 September 32+/-3 24+/-3 22+/-3 28+/-3 28+/-3 29+/-3 27+/-7 26+/-3 26+/-2 23+/-2 20+/-3 30+/-2 25+/-2 25+/-7 IJ1 25+/-3 29+/-3 28+/-3 26+/-3 27+/-2 31+/-3 28+/-4 IJ1 24+/-2 23+/-3 15+/-2 18+/-2 20+/-3 23+/-3 21+/-7 October 19+/-3 24+/-3 19+/-2 20+/-2 21+/-2 21+/-2 21+/-4 20+/-2 19+/-2 19+/-2 21+/-3 19+/-2 20+/-2 19+/-2 18+/-2 26+/-2 18+/-2 14+/-2 24+/-2 25+/-2 21+/-10 32+/-3 32+/-3 32+/-3 30+/-3 34+/-3 32+/-3 32+/-3 November 25+/-3 28+/-3 28+/-3 25+/-2 25+/-3 27+/-3 26+/-3 19+/-2 17+/-2 19+/-2 16+/-2 16+/-2 17+/-2 17+/-3 20+/-2 21+/-3 21+/-2 19+/-2 21+/-3 23+/-3 21+/-2 24+/-2 25+/-3 25+/-2 22+/-2 26+/-3 22+/-2 24+/-3 18+/-2 13+/-2 20+/-2 18+/-2 12+/-2 18+/-2 16+/-7, December 20+/-2 19+/-2 22+/-2 20+/-2 21+/-2 23+/-2 21+/-3 16+/-2 15+/-2 13+/-2 16+/-2 15+/-2 15+/-2 15+/-2 23+/-2 23+/-2 26+/-2 24+/-3 25+/-2 23+/-2 24+/-2 27+/-3 23+/-3 24+/-2 31+/-3 21+/-2 28+/-2 26+/-8 AVERAGE 22+/-11 23+/-12

.22+/-12 21+/-12 22+/-12 23+/-11 GRAND AVERAGE 22+/-12 (1) Circuit breakers tripped. Results are invalid due to low airflow. Results not included in any averages. (See Program Deviations).

Table C-2 1996 CONCENTRATIONS OF GAMMA EMITTERS*

IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results*in Units of 10*3 pCi/m3 +/- 2 sigma STATION Sampling Period Gamma Emitters ID Start Stop Be-7 K-40 SA-APT-5S1 12/26/95 to 4/1/96 66+/-5

, 12+/-4*

SA-APT-1F1 12/26/95 to 4/1/96 61+/-4 10+/-3 SA-APT-2F6 12/26/95 to 4/1/96 65+/-4 11+/-4

. SA-APT-501 12/26/95 to 4/1/96 65+/-4 12+/-3 SA-APT-16E1 12127/95 to 4/2/96 59+/-4 12+/-3 SA-APT-3H3(C) 12/26/95 to 4/1/96 57+/-5 13+/-4 SA-APT-5S1 4/1/96 to 7/1/96 87+/-6 17+/-5 SA-APT-1F1 4/1/96 to 7/1/96 90+/-4

<4 SA-APT-2F6 4/1/96 to 7/1/96 72+/-6 13+/-4

  • SA-APT-501 4/1/96 to 7/1/96 75+/-6

<6 SA-APT-16E1 4/2/96 to 7/1/96 92+/-6 19+/-5 SA-APT-3H3(C) 4/1/96 to 7/1/96 73+/-6

<5 SA-APT-5S1 7/1/96 to 9/30/96 102+/-6

<3" SA-APT-1F1 7/1/96 to 9/30/96 77+/-4

<4 SA-APT-2F6 7/1/96 to 9/30/96 74+/-6

<6 SA-APT-501 7/1/96 to 9/30/96 88+/-5

<2 SA-APT-16E1 7/1/96 to 10/1/96 75+/-4

<4 SA-APT-3H3(C) 7/1/96 to 9/30/96 57+/-6

<7 SA-APT-5S1 9/30/96 to 12i30/96 50+/-4

<4 SA-APT-1F1 9/30/96 to 12/30/96 44+/-3

<2 SA-APT-2F6 9/30/96 to 12/30/96 41+/-4 14+/-4 SA-APT-501 9/30/96 to 12/30/96 46+/-5

<6 SA-APT-16E1 10/1/96 to 12/30/96 46+/-5

<5 SA-APT-3H3(C) 9/30/96 to 12/30/96 57+/-5 14+/-7 AVERAGE 67+/-33

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table 20.

(C) Control Station 56 RA-NAT

<0.6

<0.5

<0.6

<0.8

<0.6

<1.2 1.4+/-0.5

<0.4

<0.5

<0.6 1.7+/-0.5

<0.6

<0.2

<0.4

<1.6

<0.4

<0.6

<0.8

<0.4

<0.4

<1.3

<0.6

<0.5

<2

TABLE C-3 1996 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10*3 pCi/m3

<------------------------------------------------ ST A Tl 0 N ID ---------------------------------------------->

Control MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F6 SA-APT-3H3 SA-APT-501 SA-APT-5S1 January

<4.6

<4.1

<2.3

<4.5

<1.7

<2.4

<2.1

<2.3

<2.3

<6.2

<2.2

<2.1

<4.4

<5.2

<2.3

<10

<1.9

<2.4

<3.4

<4.1

<2.1

<1.9

<2.9

<3.1

<3.6

<2.5

<2.8

<2.9

<4.6

<4.1 February

<2.4

<5.2

<4.2

<2.1

<2.5

<2.6

<3

<2.3

<2.7

<3.7

<1.9

<2.2

<2

<2.1

<4.7

<4

<1.8

<2

<3.1

<3.8

<3.7

<3.7

<4.4

<3.4 March

<4.2

<4.3

<2

<1.9

<2.2

<2.8 V1

<2.8

<2.5 (1)

<3

<2

<4.9

<3.3

<1.9

<4.7

<4.6

<3

<3.7 I

<1.9

.<3.2

<2.7

<4.5

<1.3

<3.8

<2.2

<2.7

<5.6

<5.2

<4.9

<3.2 April

<1.1

<2.5

<14.7

<3.1

<3.9

<3.7

<3.7

<1.6

<2.6

<7.3

<1.9

<4.6

<4.5

<2.4

<5.3

<5.5

<4.5

<3.7

<1.3

<2.3

<1.6

<3.2

<2

<3 May

<4

<2.6

<2.8

<3.1

<1.9

<7.6

<3.1

<2.2

<1.8

<2.7

<1.7

<2.6

<2.9

<3.7

<1.7

<2.1

<1.4

<6.1

<3.8

<2.5

<3.7

<2.1 (1)

<3 June

<5.9

<12

<7.1

<5.8

<8.7

<8.1

<6.5

<5.4

<6.9

<4.6

<5.6

<4.2

<2.5

<2.1

<2.6

<3.1

<5.1

<2.5

<3.6

<2.1

<3.2

<4 (1)

<3

<3.1

<17

<9.5

<2.9

<3

<5.7

lJ1 00 TABLE C-3 1996 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3

<------------------------------------------------ ST A Tl 0 N ID ---------------------------------------------->

Control MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F6 SA-APT-3H3 SA-APT-5D1 July

<5.3

<2.3

<3.1

<2.4

<5.3

<2.7.

<4.3

<5.8

<3.8 (1)

<3.1

<2.4 (1)

<2.6

<2.1

<3.2

<2.2

<2.8

<6.8

<2.7 August

<6.4

<6.2

<4.7

<5.8

<1.6

<4.5

<4.1

<4.7

<7.2

<4.1

<2.8

<3.6

<5

<5.3

<3.5

<3.1

<3.7

<3.8

<7.4

<3.5

<3.2

<2.9

<4

<2.6

<2.8 September

<4.3

<5.6

<3.7

<3.2

<1.7

<4.7

<2.4

<3.6

<3.1

<3.9

<2.3

<2.6

<2.4

<1.9

<2.6

<1.9

<2.6

<2.8

<5.5

<5.8 October

<1.6

<2.2

<3.1

<4.5

<6.2

<2.5

<5

<5:9

<3.4

<2.4

<2.9

<4

<3.2

<2.7

<2

<2.6

<3.9

<3

<5.3

<2 November

<4.8

<4.1

<3.1

<3

<2.3

<4.1

<3.9

<1.5

<2.4

<1.4

<4.1

<3

<5.5

<4.2

<5.3

<1.9

<3.9

<3.6

<4.1

<5.7

<2.4

<1.7

<4.1

<4.2

<3.5 December

<3.5

<4.3

<1.2

<2.5

<1.7

<2.7

<2.8

<1.9

<3

<2.7

<6.8

<3.8

<2.8

<2.5

<1.3

<2.3

<3.9

<5.5

<11

<5.7

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

(1) Circuit breakers tripped. Results are invalid due to low airflow. See Program Deviations. Results are not included in any averages.

SA-APT-5S1

<2.4

<2.9

<3.7 (1)

<4.5

<3.4

<3.3

<2

<4.1

<6.2

<4

<4.9

<4.5

<2.4

<2

<2.3

<2.8

<5.5

<2.4'

<2.3

<1.7

<4.3

<4.6

<2

<4.3

<4.8

TABLE C-4 1996 DIRECT RADIATION MEASUREMENTS - QUARTERLY /ANNUAL TLD RESULTS Results in mrad/standard month* +/- 2 sigma STATION ID SA-IDM-252 SA-IDM-551 SA-IDM-652 SA-IDM-751 SA-IDM-1051 SA-IDM-1151 SA-IDM-4D2 SA-IDM-5D1 SA-IDM-10D1

-$A-IDM-14D1 SA-IDM-15D1 SA-IDM-2E1 SA-IDM-3E1 SA-IDM-9E1 SA-IDM-11E2 SA-IDM-12E1 SA-IDM-13E1 SA-IDM-16E1 SA-IDM-1F1 SA-IDM-2F2 SA-IDM-2F5 SA-IDM-2F6 SA-IDM-3F2 SA-IDM-3F3 SA-IDM-4F2 SA-IDM-5F1 SA-IDM-6F1 SA-IDM-7F2 (1)

SA-IDM-10F2 SA-IDM-11 F1 SA-IDM-12F1 SA-IDM-13F2 SA-IDM-13F3 SA-IDM-13F4 SA-IDM-14F2 SA-IDM-15F3 SA-IDM-16F2 SA-IDM-1G3 (C)

SA-IDM-3G1 (C)

SA-IDM-10G1(C)

SA-IDM-16G1 (C)

SA-IDM-3H1 (C)

SA-IDM-3H3 (C)

SA-IDM-151 SA-IDM-351 SA-IDM-254 SA-IDM-451 SA-IDM-1551 SA-IDM-1651 AVERAGE JAN to MAR 3.6+/-1.0 3.4+/-1.1 4.5+/-1.3 7.4+/-1.9 6.3+/-1.4 6.3+/-1.3 4.2+/-1.0 3.8+/-1.0 4.2+/-1.1 3.8+/-1.1 4.5+/-1.2 3.8+/-0.9 3.4+/-1.0 4.6+/-1.5 4.3+/-1.2 4.3+/-1.1 3.7+/-1.2 4.1+/-1.5 3.9+/-1.4 3.5+/-1.1 4.1+/-1.0 3.7+/-1.0 3.6+/-1.0 3.5+/-1.3 3.5+/-1.3 3.7+/-1.0 3.1+/-0.8 (1) 4.0+/-1.2 4.4+/-1.3 4.3+/-1.2 3.8+/-2.5 4.1+/-0.9 4.0+/-1.3 4.9+/-1.4 4.5+/-1.2 3.8+/-1.4 4.9+/-1.1 4.1+/-1.3 4.3+/-1.6 4.6+/-1.8 3.5+/-1.2 4.3+/-1.1 3.6+/-1.2 3.1+/-0.8 3.4+/-0.8 3.6+/-1.1 3.4+/-1.0 3.8+/-1.1 4.1_+/-1.6

  • The standard month = 30.4 days.

APR to JUN 4.4+/-1.2 3.8+/-0.8 5.1+/-1.6 6.0+/-1.0 4.6+/-1.2 3.7+/-1.1 4.8+/-1.0 4.3+/-1.3 4.9:!:1.1 4.8+/-1.2 5.0+/-0.9 4.5+/-1.9 3.7+/-1.5 5.3:!:1.4 4.8+/-1.4 4.9+/-1.2 3.9+/-1.0 4.5+/-1.7 4.5+/-1.4 4.0+/-1.2 4.6+/-1.7 4.2+/-1.1 4.0+/-0.7 3.9+/-1.5 3.9+/-1.1 4.1+/-1.1 3.4+/-1.1 3.1+/-1.2 4.5+/-1.1 4.8:!:1.7 4.7+/-1.4 4.4+/-1.2 4.5+/-1.2 4.4:!:1.1 5.5+/-1.2 5.2+/-1.7 4.2+/-0.9 5.4+/-1.5 4.8:!:1.3 4.9+/-1.4 5.1+/-1.1 4.0+/-1.4 4.8+/-1.5 4.5+/-0.8 3.5+/-1.0 4.0+/-0.9 4.1+/-0.9 3.8+/-1.1 4.5+/-1.3 4.5+/-1.2

.. Quarterly Element TLD results by YAEL.

... Annual Element TLD results by Thermo NUtech.

JUL to SEP 4.2+/-1.4 3.4+/-1.5 4.6+/-1.8 5.1+/-1.7 3.5+/-1.3 2.6+/-1.0 4.4+/-1.5 4.0:!:1.5 4.5+/-1.7 3.9+/-2.0 4.6+/-1.9 4.0+/-1.4 3.4+/-1.3 4.9+/-1.8 4.2+/-1.3 4.3+/-1.6 3.6+/-1.2 4.0+/-1.3 4.2+/-1.4 3.5+/-1.1 4.1+/-1.5 3.7+/-1.4 3.5+/-1.2 3.4+/-1.2 3.4+/-1.4 3.6+/-1.4 3.1+/-1.5 2.6+/-1.3 4.2+/-1.5 4.3:!:1.4 4.1+/-1.5 3.9+/-2.0 4.0+/-1.5 4.0+/-1.4 4.9+/-1.6 4.7+/-1.4 3.8+/-1.4 5.0+/-1.9 4.4+/-1.5 4.5+/-1.7 4.5+/-1.7 3.6+/-1.2 4.4:!:1.6 4.1+/-1.4 2.9+/-1.1 3.7+/-1.2 3.8+/-1.4 3.4+/-1.4 4.1+/-1.7 4+/-1.1 OCT to DEC 4.0+/-3.4 3.1+/-3.4 4.5+/-3.4 3.1:!:3.4 2.9:!:3.4 3.5+/-3.4 4.1+/-3.4 3.7+/-3.4 4.1+/-3.4 3.9+/-3.5 4.3+/-3.5 3.8+/-3.4 3.3+/-3.3 4.6+/-3.5 4.0+/-3.4 4.2+/-3.5 3.5+/-3.4 4.0+/-3.6 3.8+/-3.4 3.3+/-3.4 3.9+/-3.4 3.5+/-3.4 3.4+/-3.4 3.3+/-3.4 3.3+/-3.4 3.3+/-3.4 2.9+/-3.4 2.4+/-3.4 3.8+/-3.4 4.1+/-3.4 3.8+/-3.4 3.9+/-3.5 3.9+/-3.5 3.9+/-3.4 4.8+/-3.6 4.4+/-3.5 3.6+/-3.5 4.9+/-3.6 4.1+/-3.4 4.1+/-3.5 4.2+/-3.5 3.2+/-3.4 4.2+/-3.5 3.8+/-3.4 2.8+/-3.4 3.3+/-3.4 3.5+/-3.4 3.2+/-3.5 3.9+/-3.4 3.7+/-1.1 GRAND AVG (1) See Program Deviations. Annual result for 3 quarters only.

59 QTR ELEMENTS AVG 4.1+/-0.7 3.4+/-0.5 4.7+/-0.6 5.4+/-3.7 4.3+/-3.0 4.0+/-3:1 4.4+/-0.6 3.9+/-0.6 4.4:!:0.7 4.1+/-0.9 4.6+/-0.6 4.0+/-0.6 3.4:!:0.4

.4.9:!:0.6 4.3+/-0.7 4.4+/-0.6 3.7+/-0.3 4.1+/-0.4 4.1:!:0.6 3.6+/-0.6 4.2+/-0.6 3.8+/-0.6 3.6:!:0.5 3.5+/-0.6 3.5+/-0.5 3.7+/-0.6 3.1+/-0.5 2.7+/-0.6 4.1+/-0.6 4.4+/-0.6 4.2+/-0.7 4.0+/-0.5 4.1+/-0.5 4.1+/-0.5 5.0+/-0.7 4.7+/-0.7 3.9+/-0.5 5.1+/-0.5 4.3+/-0.6 4.4+/-0.6 4.6+/-0.8 3.6:!:0.6 4.4+/-0.5 4.0+/-0.8 3.1+/-0.7 3.6+/-0.6 3.8+/-0.5 3.4+/-0.5 4.1+/-0.7 4.1+/-1.4 ANNUAL ELEMENTS RESULTS 4.7+/-0.8 3.8+/-0.6 5.1+/-1.0 4.8+/-1.2 3.9+/-0.4 3.5+/-0.5 4.6+/-0.7 4.2+/-1.1 4.7+/-0.2 4.4+/-0.8 4.3+/-0.3 3.9+/-0.8 3.4+/-0.8 5.0+/-0.7 4.8+/-1.3 4.3+/-0.9 3.7+/-0.4 3.9+/-0.7 4.2+/-0.8 3.4+/-0.7 3.9+/-0.6 3.9+/-0.7 3.1+/-0.4 3.2+/-1.0 4.0+/-0.9 3.8+/-0.8 3.1+/-0.4 2.5+/-0.2 4.4+/-0.5 4.7+/-0.6 4.9+/-1.0 4.7+/-1.2 4.0+/-0.8 -

4.5+/-0.8 5.1+/-0.7 5.1+/-0.9 3.3+/-0.3 4.7+/-0.8 4.6+/-0.5 4.8+/-0.2 4.4+/-0.5 4.3+/-0.6 4.8+/-0.6 4.2+/-0.8 3.7+/-0.3 3.6+/-0.4 4.1+/-1.0 3.7+/-0.9 4.2+/-0.5 4.2+/-1.2

TABLE C-5 1996 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD

<--GAMMA EMITTERS->

STATION ID START STOP 1-131 K-40 RA-NAT SA-MLK-2F7 1/1/96 1/2196

<0.2 1400 +/-90

<2.4 SA-MLK-3G1 (C) 111/96 1/2196

<0.2 1300 +/-60

<3.2 SA-MLK-14F4 1/2196 1/3/96

<0.3 1400 +/-70

<3.8 SA-MLK-11 F3 1/2196 1/3/96 *

<0.3 1400 +/-80

<3.9 SA-MLK-2F7 214196 215196

<0.1 1300 +/-80

<3.6 SA-MLK-11 F3 215/96 216196

<0.2 1300 +/-90

<5.4 SA-MLK-14F4 214196 2/5/96

<0.1 1300 +/-70

<3.9 SA-MLK-3G1 (C) 214196 215/96

<0.3 1300 +/-70

<3.4 SA-MLK-2F7 3/3/96 3/4/96

<0.4 1300 +/-80

<7.8 SA-MLK-11F3 3/4/96 3/5/96

<0.2 1300 +/-90

. <4.7 SA-MLK-14F4 3/3/96 3/4/96

<0.2 1400 +/-80

<4.3 SA-MLK-3G1 (C) 3/3/96 3/4/96

<0.3 1400 +/-70

<3.7 SA-MLK-2F7 4/8/96 4/9/96

<0.2 1300 +/-80

<4.4 SA-MLK-11 F3 4/8/96 4/9/96

<0.2 1400 +/-80

<7 SA-MLK-14F4 418i96 4/9/96

<0.2 1400 +/-70

<4.4 SA-MLK-3G1 (C) 417196 4/8/96

<0.3 1400 +/-90

<13 SA-MLK-2F7 4/21/96 4722196

<0.2 1400 +/-80

<4.7 SA-MLK-11 F3 4/21/96 4/22196

<0.3 1300 +/-90

<9 SA-MLK-14F4 4/21/96 4/22/96

<0.3 1400 +/-70

<3.1 SA-MLK-3G1 (C) 4/21/96 4/22196

<0.1 1300 +/-70

<2.9 SA-MLK-2F7 5/5/96 5/6/96

<0.3 1400 +/-60

<3.2 SA-MLK-11 F3 5/6/96 517/96

<0.2 1400 +/-70

<3.7 SA-MLK-14F4 5/6/96 5/7/96

<0.1 1300 +/-90

<5 SA-MLK-3G1 (C) 5/5/96 5/6/96

<0.1 1300 +/-80

<8.5 SA-MLK-2F7 5/20/96 5/21/96

<0.3 1300 +/-80

<3.9 SA-MLK-3G1 (C) 5/19/96 5/20/96

<0.3 1300 +/-80

<4.1 SA-MLK-14F4 5/20/96 5/21/96

<0.1 1400 +/-90

<7.6 SA-MLK-11 F3 5/20/96 5/21/96

<0.2 1400 +/-70

<3.7 SA-MLK-2F7 6/3/96 6/4/96

<0.2 1300 +/-90

<4.2 SA-MLK-11F3 6/3/96 6/4/96

<0.4 1300 +/-90

<3.3 SA-MLK-14F4 6/3/96 6/4/96

<0.5 1400 +/-90

<3.5 SA-MLK-3G1 (C) 6/3/96 6/4/96

<0.6 1400 +/-90

<5.3 SA-MLK-2F7 6/17/96 6/18/96

<0.3 1300 +/-90

<3.8 SA-MLK-11F3 6/17/96 6/18/96

<0.2 1300 +/-70

<3.6 SA-MLK-14F4 6/17/96 6/18/96

<0.8 1300 +/-80 12 +/-5 SA-MLK-3G1 (C) 6/17/96 6/18/96

<0.1 1300 +/-60 7+/-3 SA-MLK-11 F3 717196 7/8/96

<0.3 1400 +/-70

<3.7 SA-MLK-14F4 717196 7/8/96

<0.2 1300 +/-80

<9.8 SA-MLK-2F7 7/14/96 7/15/96

<0.2 1300 +/-80

<3.3 SA-MLK-3G1 (C) 7/14/96 7/15/96

<0.3 1400 +/-60

<2.8 SA-MLK-11 F3 7/21/96 7/22196

<0.2 1200 +/-90

<5.3 SA-MLK-14F4 7/21/96 7122196

<0.1 1300 +/-70

<3 SA-MLK-2F7 7/29/96 7/30/96

<0.3 1400 +/-70

<3.5 SA-MLK-3G1 (C) 7/29/96 7/30/96

<0.5 1300 +/-90 9+/-3 60

\\.

TABLE C-5 1996 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD

<-GAMMA EMITTERS->

STATION ID START STOP 1-131 K-40 RA-NAT SA-MLK-11 F3 8/4/96 8/5/96

<0.2 1300 +/-90

<4.1 SA-MLK-14F4 8/4/96 8/5/96

<0.2 1400 +/-60 7+/-3 SA-MLK-2F7 8111/96 8/12/96

<0.3 1200 +/-90

<4.8 SA-MLK-3G1 (C) 8/11/96 8/12/96

<0.2 1400 +/-70

<3.8 SA-MLK-11 F3 8/19/96 8/20/96

<0.3 1300 +/-90

<5.7 SA-MLK-2F7 8/26/96 8/27/96

<0.3 1300 +/-80

<3.1 SA-MLK-14F4 8/26/96 8/27/96

<0.2 1300 +/-80 9+/-4 SA-MLK-3G1 (C) 8/26/96 8/27/96

<0.2 1300 +/-60

<6.9 SA-MLK-11F3 9/2/96 9/3/96

<0.2 1300 +/-60 9+/-3 SA-MLK-14F4 9/2/96 9/3/96

<0.5 1400 +/-80

<3.9 SA-MLK-2F7 9/8/96 9/9/96

<0.2 1300 +/-70

<3.4 SA-MLK-3G1 (C) 9/8/96 9/9/96

<0.3 1400 +/-90

<5.8 SA-MLK-11F3 9/15/96 9/16/96

<0.2 1400 +/-70

<4.1 SA-MLK-14F4 9/15/96 9/16/96

<0.2 1200 +/-90

<10 SA-MLK-2F7 9/23/96 9/24/96

<0.1 1300 +/-90

<9.6 SA-MLK-3G1 (C) 9/23/96 9/24/96

<0.2 1300 +/-80

<4.9 SA-MLK-11 F3 10/6/96 1017/96

<0.1 1200 +/-80 14+/-5 SA-MLK-14F4 10/6/96 1017/96

<0.2 1400 +/-70

<3.9 SA-MLK-2F7 10/13/96.

10/14/96

<0.2 1300 +/-70

<4.2 SA-MLK-3G1 (C) 10/13/96 10/14/96

<0.2 1400 +/-90

<8.8 SA-MLK-11 F3 10/21/96 10/22/96

<0.3 1200 +/-80

<3.6 SA-MLK-14F4 10/21/96 10/22/96

<0.1 1400 +/-70

<4 SA-MLK-2F7 10/27/96 10/28/96

<0.3 1300 +/-80

<3.8 SA-MLK-3G1 (C) 10/27/96 10/28/96

<0.3 1400 +/-60

<3.5 SA-MLK-11F3 11/3/96 11/4/96

<0.3

.1200 +/-80

<4.2 SA-MLK-14F4 11/3/96 11/4/96

<0.3 1400 +/-70

<4.2 SA-MLK-2F7 11/11/96 11/12/96

<0.3 1300 +/-60

<3.3 SA-MLK-3G1 (C) 11/11/96 11/12/96

<0.4 1200 +/-80

<3.5 SA-MLK-11F3 11/17/96 11/18/96

<0.4 1200 +/-70

<5.9 SA-MLK-14F4 11117/96 11/18/96

<0.3 1200 +/-90

<3.2 SA-MLK-2F7 11/24/96 11/25/96

<0.2 1300 +/-60

<3.6 SA-MLK-3G1 (C) 11/24/96 11/25/96

<0.2 1400 +/-90

<4.3 SA-MLK-11 F3 12/1/96 12/2/96

<0.3 1400 +/-70

<3.3 SA-MLK-14F4 12/1/96 12/2/96

<0.3 1400 +/-80

<2.4 SA-MLK-2F7 12/8/96 12/9/96

<0.3 1200 +/-90

<3.2 SA-MLK-3G1 (C) 12/8/96 12/9/96

<0.3 1500 +/-70

<3.3 AVERAGE 1300 +/-100

  • 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-20.
      • Monthly sample collected during Jan., Feb., March and Dec., when animals are not on pasture (C) Control Station 61

TABLE C-6 1996 CONCENTRATIONS OF STRONTIUM 89* and STRONTIUM 90* IN MILK Results in Units of pCi/L +/- 2 sigma

<--STRONTIUM --->

STATION ID SAMPLING PERIOD Sr-89 Sr-90 SA-MLK-11 F3 7n-8196

<1.0

<0.7 SA-MLK-14F4 7n-8196

<1.0 1.8+/-0.6 SA-MLK-2F7 7/14-15/96

<1.0 2.3+/-0.5 SA-MLK-3G1 (C) 7/14-15/96

<1.0 2.5+/-0.6 AVERAGE 1.8+/-0.8

  • Strontium results are reported by YAEL. Results below the detectable limit are reported as MDC.
    • Management audit analyses, not required by Technical Specifications.

62

TABLE C-7 1996 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, STATION ID*

SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 AVERAGE SA-WWA-3E1 AND TRITIUM IN WELL.WATER Results in Units of pCi/L +/- 2 sigma SAMPLING GROSS DATE ALPHA 1/29/96 2.4+/-1.1 2/26/96 1.1+/-0.9 3/31/96 1.3+/-0.8 4/30/96

<0.9 5/28/96 0.9+/-0.8 6/24/96 1.6+/-0.9 7/30/96 1+/-0.8 8/27/96 1.7+/-0.8 9/30/96

<0.8 10/28/96 1.1+/-0.8 11/25/96

<0.9 12/30/96 2.2+/-1 1.3+/-1.1 63 GROSS BETA 9.4+/-0.8 9.7+/-0.8 11+/-1 9.8+/-0.8 11+/-1 10+/-1 11+/-1 9.5+/-0.7 2.3+/-0.5 11+/-1 11+/-1 10+/-1 10+/-5 TRITIUM

<130

<120

<130

<120

<130

<120

<120

<130

<130

<140

<140 170+/-90

TABLE C-8 1996 CONCENTRATIONS OF IODINE-131* AND GAMMA EMllTERS** IN WELL WATER Results in Units of pCi/L +/- 2 sigma SAMPLING

<-GAMMA EMllTERS ->

STATION ID DATE 1-131 K-40 RA-NAT SA-WWA-3E1 1/29/96

<0.8

<22 228+/-9 SA-WWA-3E1 2126/96

<0.6

<17 175+/-8 SA-WWA-3E1 3/31/96

<0.2

<24 97+/-5 SA-WWA-3E1 4/30/96

<0.2

<18 104+/-7 SA-WWA-3E1 5/28/96

<0.1

<44 139+/-5 SA-WWA-3E1 6/24/96

<0.3

<16 118+/-4 SA-WWA-3E1 7/30/96

<0.2

<17 105+/-4 SA-WWA-3E1 8/27/96

<0.3

<21 62+/-4 SA-WWA-3E1 9/30/96

<0.3

<25 125+/-5 SA-WWA-3E1 10/28/96

<0.2

<19 61+/-5 SA-WWA-3E1 11/25/96

<0.2

<15 82+/-3 SA-WWA-3E1 12/30/96

<0.4 67+/-25 238+/-9 AVERAGE SA-WWA-3E1 128+/-117

  • lodine-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-20.

64

TABLE C-9 1996 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 1/1-31/96 2.3+/-0.8 3.3+/-0.5

<130 TREATED 1/1-31/96 1+/-0.6 2.5+/-0.5

<120 RAW 2/1-29/96 0.7+/-0.5 3.5+/-0.5

<120 TREATED 2/1-29/96

<0.8 3.1+/-0.5

<120 RAW 3/1-31/96 0.7+/-0.5 2.8+/-0.5

<120 TREATED 3/1-31/96

<0.6 2.6+/-0.5

<130 RAW 4/1-30/96 1.2+/-0.6 3.2+/-0.5

<120 TREATED 4/1-30/96

<0.6 2.4+/-0.5

<120 RAW 5/1-31/96 1.6+/-0.7 3.2+/-0.5

<120 TREATED 5/1-31/96

- <0.8 3+/-0.5

<120 RAW 6/1-30/96 0.6+/-0.5 3.1+/-0.5

<120 TREATED 6/1-30/96

<0.7 2.5+/-0.5

<120 RAW 7/1-31/96 0.7+/-0.6 3.6+/-0.5

<120 TREATED 7/1-31/96

<1 2.9+/-0.5

<120 RAW 8/1-31/96 0.9+/-0.5 3.8+/-0.5

<140 TREATED 8/1-31/96

<0.7 3.7+/-0.5

<140 RAW 9/1-30/96 0.6+/-0.5 2.9+/-0.5

<130 TREATED 9/1-30/96

<0.9 3+/-0.5

<130 RAW 10/1-31/96

<0.8 3.6+/-0.5 200+/-90 TREATED 10/1-31/96

<0.7 4+/-0.6

<140 RAW 11/1-30/96

<0.6 3.6+/-0.5

<140 TREATED 11/1-30/96

<0.9 3.9+/-0.5

<140 RAW 12/1-31/96 1.3+/-0.6 4.1+/-0.5

<140 TREATED 12/1-31/96

<0.7 3.6+/-0.5

<150 AVERAGE RAW*

1+/-1 3.4+/-0.8 TREATED 3.1+/-1.1 GRAND AVERAGE 1.1+/-3.3 65

TABLE C-10 1996 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITIERS-IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING GAMMA EMITIERS TYPE PERIOD 1-131 K-40 Th-232 RA-NAT RAW 1/1-31/96

<0.4 54+/-20

<4

<3.1 TREATED 1/1-31/96

<0.1

<14

<6

<2.7 RAW 211-29/96

<0.2

<14

<2

<2 TREATED 211-29/96

<0.1

<11

<2

<1.5 RAW 3/1-31/96

<0.2

<14

<7

<5.4 TREATED 3/1-31/96

<0.2

<14

<3

<5.8 RAW 4/1-30/96

<0.1

<14

<9

<2.4 TREATED 4/1-30/96

<0.1

<21

<5

<3.2 RAW 5/1-31/96

<0.4

<31

<5

<3 TREATED 5/1-31/96

<0.2

'45+/-14

<3 4.8+/-1.6 RAW 6/1-30/96

<0.3 54+/-23

<5

<4.1 TREATED 6/1-30/96

<0.3 49+/-18

<5

<2.6 RAW 7/1-31/96

<0.2

<15

<8

<4.8 TREATED 7/1-31/96

<0.3

<22

<7

<3.3 RAW 8/1-31/96

<0.2.

<15 11+/-4

<3.

TREATED 8/1-31/96

<0.2

<15

<8

<2.4 RAW 9/1-30/96

<0.2

<11

<2

<2.8 TREATED 9/1-30/96

<0.3

<17

<10 16+/-3 RAW 10/1-31/96

<0.3 39+/-19

<3

<2.7 TREATED 10/1-31/96

<0.1

<15

<6 17+/-4 RAW 11/1-30/96

<0.3

<20

<5 8.6+/-3.9 TREATED 11/1-30/96

<0.2

<21

<5 18+/-3 RAW 1211-31/96

<0.3 50+/-15

<8 4+/-1.7 TREATED 1211-31/96

<0.2 67+/-26

<9

<4.9 AVERAGE RAW TREATED GRAND AVERAGE

  • lodirie-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-20.

66

TABLE C-11 1996 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in Units of pCi/kg [I/Vet) +/- 2 sigma SAMPLING

<--GAMMA EMITTERS -->

STATION ID DATE SAMPLE TYPE K-40 RA-NAT Th-232 SA-FPV-2G2 5/20/96 Asparagus 2280+/-210

<10

<45 SA-FPL-3H5 (C) 7/30/96 Cabbage 2680+/-200

<11

<18 SA-FPV-1G1 (C) 7/29/96 Com 2740+/-240

<11

<20 SA-FPV-2F4.

7/31/96 Com 2450+/-160 24+/-10

<16 SA-FPV-2F8 8/1/96 Com 2240+/-230

<22

<18 SA-FPV-14F3 7/31/96 Corn 2070+/-200

<11

<26 SA-FPV-3H5 (C) 7/30/96 Com 2420+/-160

<9

<18 AVERAGE 2380+/-500 SA-FPV-2F4 7/31/96 Peppers 1640+/-220

<13

<55 SA-FPV-2F8 8/1/96 Peppers 1480+/-160 31+/-10

<21 SA-FPV-3F5 7/31/96 Peppers 1640+/-180

<23

<21 SA-FPV-1G1 (C) 7/31/96 Peppers 1510+/-200

<15

<23 SA-FPV-14F3 7/31/96 Peppers 1360+/-160

<18

<23 SA-FPV-3H5 (C) 7/30/96 Peppers 1500+/-200

<18

<32 AVERAGE 1520+/-210 SA-FPV-1G1 (C) 7/31/96 Tomatoes 2310+/-200

<15

<12 SA-FPV-2F4 7/31/96 Tomatoes 2530+/-160 24+/-8

<28 SA-FPV-3F5 7/31/96 Tomatoes 2350+/-150 36+/-17 44+/-22 SA-FPV-14F3 7/31/96 Tomatoes 1990+/-190

<9

<21 SA-FPV-3H5 (C) 7/30/96 Tomatoes 1760+/-190 23+/-10

<21 AVERAGE 2190+/-620 28+/-14 GRAND AVERAGE 2050+/-900

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.

67

STATION ID SA-GAM-3E1 SA-GAM-1101 (C)

AVERAGE TABLE C-12 1996 CONCENTRATIONS OF GAMMA EMITTERS* IN GAME Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING DATE 1/20-27/96 3/4-8/96 SAMPLE TYPE Muskrat Muskrat Muskrat

<-GAMMA EMITTERS->

K-40 RANAT 2490+/-210

<14 2030+/-150 49+/-12 2260+/-650

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.

68

TABLE C-13 1996 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 RA-NAT Th-232 SA-VGT-2F7 9/23/96 Silage 1040+/-80 3040+/-160

<11

<15 SA-VGT-3G1 9/23/96 Silage 858+/-90 3030+/-220

<14

<16 SA-VGT-14F4 10/1/96 Silage 1390+/-100 3610+/-220

<13 52+/-25 AVERAGE 1100+/-540 3200+/-700 SA-VGT-3G1 10/26/96 Soybeans

<31 18500+/-310 19+/-9

<29 SA-VGT-11F3 11/2/96 Soybeans

. <55 14100+/-300

<12

<15 SA-VGT-14F4 11/2/96 Soybeans

<35 15200+/-320

<13

<16 SA-VGT-2F7 11/10/96 Soybeans 88+/-40 13400+/-270 14+/-7

<23 AVERAGE 15300+/-4500

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.

Location 3G1 is the Control Station.

69

C-14 1996 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

<-------------------------------------------------- ST A Tl 0 N ID -------------------------------------------------->

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

January 114+/-9 106+/-9 79+/-7 74+/-7 151+/-11 105+/-62 February 32+/-4 23+/-3 20+/-3 14+/-3 59+/-5 30+/-35 March 29+/-4 27+/-4 6+/-2 10+/-3 39+/-4 22+/-27 April 42+/-5 31+/-4 14+/-3 12+/-3 51+/-5 30+/-34 May 7+/-2 8+/-2 4+/-2 7+/-2 15+/-3 8+/-8 June 40+/-5 39+/-4 25+/-4 21+/-3 59+/-6 37+/-30 0

July 57+/-6 52+/-5 22+/-4 32+/-4 94+/-8 51+/-56 August

. 41+/-5 31+/-4 5+/-3 14+/-3 73+/-7 33+/-53 September 66+/-6 55+/-5 35+/-4 35+/-4 94+/-8 57+/-50 October 41+/-5 41+/-4 23+/-3 20+/-3 78+/-6 41+/-46 November 66+/-6 30+/-4 35+/-4 31+/-4 87+/-8 50+/-51 December 6+/-3 6+/-3

<3.4 4+/-2 11+/-3 6+/-7 AVERAGE 45+/-58 37+/-52 23+/-42 23+/-38 67+/-77 GRAND AVERAGE 39+/-63

C-15 1996 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-1F2 1/5/96 109+/-25

<2.7

<4.6 SA-SWA-7E1 1/5/96 128+/-24 7.7+/-2.2

<3.1 SA-SWA-11A1 1/5/96 146+/-25

<2.6

<7.2 SA-SWA-12C1 (C) 1/5/96 86+/-22 8.2+/-3.2

<3.3 SA-SWA-16F1 1/5/96 68+/-30

<3.1

<5 SA-SWA-1F2 2/11/96

<17

<2.8

<3.3 SA-SWA-7E1 2/11/96 58+/-24

<5.1

<3.1 SA-SWA-11A1 2/11/96 93+/-22

<3.1

<10.4 SA-SWA-12C1(C) 2/11/96 60+/-22

<2.9

<7.8 SA-SWA-16F1 2/11/96

<18 5.5+/-1.8

<5.8 SA-SWA-1F2 3/11/96

<14

<2.2

<2.8 SA-SWA-7E1 3/11/96

<34

<2.9

<4.4 SA-SWA-11A1 3/11/96 79+/-16

<2.5

<5.2 SA-SWA-12C1 (C) 3/11/96 64+/-14

<2.3

<5 SA-SWA-16F1 3/11/96

<24

<2.9

<4.3 SA-SWA-1F2 4/12/96 56+/-23

<2.7

<3.9 SA-SWA-7E1 4/12/96 45+/-18

<2.3

<5.8 SA-SWA-11A1 4/12/96 84+/-24

<3.4

<11.2 SA-SWA-12C1 (C) 4/12/96 64+/-18

<2.7

<3.6 SA-SWA-16F1 4/12/96 54+/-19

<4.9

<3.1 SA-SWA-1F2 5/9/96 39+/-17

<2.5

<5.1 SA-SWA-7E1 5/9/96 67+/-20 7.3+/-1.8

<3.7 SA-SWA-11A1 5/9/96 43+/-22

<2.9

<3.8 SA-SWA-12C1 (C) 5/9/96 29+/-13 8.6+/-2.4

<2.6 SA-SWA-16F1 5/9/96

<21

<3.1

<4.6 SA-SWA-1F2 617/96

<26

<3.2

<4.2 SA-SWA-7E1 617/96 94+/-20

<2.1

<5.3 SA-SWA-11A1 617/96 43+/-18

<2.1

<5.5 SA-SWA-12C1(C) 617/96 61+/-13 5.6+/-1.6

<9.3 SA-SWA-16F1 617/96 45+/-16

<4.9

<2.5 SA-SWA-1F2 7/12/96 76+/-23

<4.3

<4.4 SA-SWA-7E1 7/12/96 131+/-26

<3.6

<5.3 SA-SWA-11A1 7/12/96 54+/-20 5.5+/-1.8

<3.1 SA-SWA-12C1 (C) 7/12/96 49+/-19 5.1+/-1.9.

<6 SA-SWA-16F1 7/12/96 73+/-24

<4.2

<3.6 71..

C-15 1996 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-1F2 8/9/96

<16 5.2+/-2.1

<4.9 SA-SWA-7E1 8/9/96 53+/-24

<3.4

<9.8 SA-SWA-11A1 8/9/96 47+/-19 5.9+/-2.9 7.1+/-3.4 SA-SWA-12C1 (C) 8/9/96 79+/-22

<2 9.8+/-4.5 SA-SWA-16F1 8/9/96

<23

<3.1

<11.7 SA-SWA-1F2 9/5/96 91+/-24

<2.6

<4.7 SA-SWA-7E1 El/5/96 147+/-26

<2.4

<3.8 SA-SWA-11A1 9/5/96 70+/-19

<6.1

<3.8 SA-SWA-12C1 (C) 9/5/96 93+/-22

<2.8

<9.6 SA-SWA-16F1 9/5/96 76+/-13 7.7+/-2.2

<3.9 SA-SWA-1F2 10/14/96

<17

<6.9

<3.4 SA-SWA~7E1 10/14/96 67+/-26

<3.5

<9.7 SA-SWA-11A1 10/14/96

<20

<2.5

<4.3 SA-SWA-12C1 (C) 10/14/96 84+/-22

<2.7

<2.5 SA-SWA-16F1 10/14/96 21+/-19

<2.5

<3.2 SA-SWA-1F2 11n196

<17

<1.8

<4 SA-SWA-7E1 11n196 82+/-20

<2

<4 SA-SWA-11A1 11n/96 74+/-19

<2.3

<4.4 SA-SWA-12C1 (C) 11n196

<46

<2.6

<4.5 SA-SWA-16F1 11nt96

<24

<2.9

<4.7 SA-SWA-1F2 1215/96

<20

<2.4

<4.1 SA-SWA-7E1 1215/96 66+/-15 5.2+/-1.5

<11 SA-SWA-11A1 1215/96 54+/-16

<2

<4.4 SA-SWA-12C1 (C) 1215/96 67+/-19

<2.6

<5 SA-SWA-16F1 1215/96 59+/-16 4.9+/-1.6 11+/-5 AVERAGE 59+/-65

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.

(C) Control Station 72

(.,,.)

TABLE C-16 1996 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER SAMPLING PERIOD 1/5/96 to 3/11/96 4/12/96 to 6/7/96 7/12/96 to 9/5/96 10/14/96 to 12/5/96 Results in Units of pCi/L +/- 2 sigma

<--~------------------------------------------------------ ST AT I 0 N ID ---------------------------------------------

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

<120 140+/-80

<120

<120

<120

<130

<120

<120

<130

<120

<130

<120

<130

<130

<130

<140

<140

<140

<140

<140

.i:--

I STATION ID SA-ESF-7E1 SA-E$F-11A1 SA-ESF-12C1 (C)

AVERAGE SA-ESF-7E1 SA-ESF-11A1 SA-ESF-12C1 (C)

AVERAGE GRAND AVERAGE TABLE C-17 1995 STRONTIUM-89 90* AND GAMMA EMITTERS** IN EDIBLE FISH SAMPLING PERIOD 5/22-25/96 5/22-25/96 5/22-25/96 9/24-25/96 9/24-25/96 9/24-25/96 Results in Units of pCi/kg (wet) +/- 2 sigma (Strontium in bone is reported in pCi/kg (dry))

STRONTIUM

<------ BONES ------>

Sr-89 Sr-90

<2000

<200

<2000

<200

<2000

<200 STRONTIUM

<------- FLESH ------->

Sr-89 Sr-90

<2000

<200

<2000

<200

<2000

<200

  • Strontium results are analyzed and reported by Yankee Atomic Environmental Laboratory on first collection only.
    • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.

(C) Control Station GAMMA EMITTERS (FLESH)

K-40 3200+/-200 2600+/-200 2300+/-200 2700+/-1000 4000+/-200 3500+/-200 3500+/-200 3700+/-600 3200+/-1300

l..rl STATION ID SA-ECH-11A 1 SA-ECH-12C1 (C)

AVERAGE SA-ECH-11A1 SA-ECH-12C1 (C)

AVERAGE GRAND AVERAGE TABLE C-18 1996 CONCENTRATIONS OF STRONTIUM-89 90* AND GAMMA EMITTERS** IN CRABS SAMPLING PERIOD 8/27/96 8/27/96 10/22/96 10/17/96 Results in Units of pCi/kg (wet) +/- 2 sigma (Strontium in shell analyses are reported in pCi/kg (dry))

STRONTIUM

<-------SHELL------->

Sr-89 Sr-90

<2000

<200

<2000

<200 STRONTIUM

<------- FLESH ------->

Sr-89 Sr-90

<2000

<200

<2000

<200

  • Strontium results are analyzed and reported by Yankee Atomic Environmental Laboratory on first collection only.
    • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.

(C) Control Station GAMMA EMITIERS (FLESH)

K-40 2900+/-200 3100+/-200 3000+/-200 2800+/-200 3100+/-200 2900+/-400 3000+/-300

°'

TABLE C-19 1996 CONCENTRATIONS OF STRONTIUM-90** AND GAMMA EMITTERS* IN SEDIMENT Results in Units of pCi/kg (dry) +/- 2 sigma SAMPLING

<------------------------------------------ GAMMA EMITTERS ------------------------------------------>

STATION ID DATE Sr-90 Be-7 K-40 Mn-54 Co-60 SA-ESS-11A1 7/18/96

<200

<100 9600+/-300

<12

<8.7 SA-ESS-15A 1 7/18/96

<200 1040+/-118 17600+/-400 37+/-11 57+/-18 SA-ESS-16A1 7/18/96

<200

<102 7700+/-300

<28

<11 SA-ESS-12C1 (C) 7/18/96

<200

<52 18100+/-500

<9.8

<9 SA-ESS-7E1 713196

<200

<87 13200+/-300

<20 56+/-12 SA-ESS-16F1 7/12/96

<200

<285 17400+/-600

<33

<11 AVERAGE 13900+/-9000 SA-ESS-11A1 11/25/96

<200

<38 2700+/-100

<3.4

  • 18+/-4.9 SA-ESS-15A1 11/25/96

<200

<206 16000+/-500

<29 39+/-15 SA-ESS-16A1 11/25/96

<200 734+/-196 17800+/-600

<26 140+/-24 SA-ESS-12C1(C) 10/23/96

<200

<130 14900+/-400

<24

<14 SA-ESS-7E1 10/23/96

<200

<107 16300+/-400

<7.4 96+/-14 SA-ESS-16F1 11/25/96

<200

<72 19200+/-400

<12

<7.8 AVERAGE 14500+/-12000 52+/-107 GRAND AVERAGE 14000+/-10000

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-20.
    • Strontium results are reported by Yankee Atomic Environmental Laboratory.

(C) Control Station Cs-134 Cs-137 RA NAT

<12

<19 1450+/-30 61+/-16 160+/-14 780+/-20

<47

<12 620+/-30 57+/-18

<9.9 630+/-30

. 58+/-14 62+/-12 830+/-30

<68

<18 550+/-40 810+/-660

<4.5 14+/-4.8 150+/-10 56+/-22 152+/-23 720+/-30 70+/-28 124+/-20 600+/-30

<58

<15 890+/-30 67+/-18 124+/-14 750+/-30

<12

<18 530+/-40 75+/-131 610+/-510 710+/-600 Th-232 1540+/-50 910+/-60 670+/-80 980+/-90 860+/-50 950+/-120 980+/-590 190+/-20 1000+/-90 980+/-80 1190+/-80 1080+/-50 1160+/-50 930+/-750 960+/-650

TABLE C-20 1996 MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE:

<----------AIR------------>

<---------WATER-------->

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

IODINE PARTICULATES GAMMA SCAN IODINE GAMMA SCAN IODINE ACTIVITY:

10-3 pCi/m3 l.0-3 pCi/m3 pCi/L pCi/L pCi/L pCi/L GEOMETRY:

lOOML 13 FILTERS 3.5 LITER 100 ML 3.? LITER l.00 ML COUNT TIME:

120 MINS 500 MINS 10000 MIN 1000 MINS 500 MINS l.000 MINS DELAY TO 2 DAYS 5 DAYS 7 DAYS 3 DAYS 2 DAYS 2 DAYS COUNT:

NUCLIDES BE-7 6.8 10 22 NA-22 0.45 5

4.5 K-40 7.1 35 120 CR-51 2.9 10 22 MN-54 0.32 1.2 3.4 C0-58 0.33 1.0 2.9 FE-59 0.79 2.5 7.2 C0-60 0.36 1.6 4.0 ZN-65 0.69 2.5 8.6 ZRNB-95 2.0 2.0 3.8 M0-99 550 10 30 RU-103 0.33 1.6 2.5 RU-106 2.9 10 22 AG-110M 0.55 2.0 3.4 SB-125 0.77 4.0 8.2 TE-129M 120 40 70 I-131 13.0 0.98 2.5 0.55 3.0 0.48 TE-132 41 7

3.9 BA-133 3.7 2.6 5.0 CS-134 0.39 1.8 3.0 CS-136 0.56 2.2 3.3 CS-137 0.28 1.6 3.2 BALA-140 2.3 8

10 CE-141 0.31 2.3 3.9 CE-144 0.8 7.0 10 RA-NAT 0.7 7.4 6.6 TH-232 1.2 7.1 12 77

TABLE C-20 (cont* d) 1996 PSE&G MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE:

<------FOOD PRODUCTS------->

FOOD &

BEEF FISH SEDIMENT GREEN CHOP

& GAME SHELLFISH

& SOIL ACTIVITY:

pCi/KG WET pCi/kg WET pCi/kg WET pCi/kg pCi/kg DRY GEOMETRY:

lOOml 500 ml 3.5 LITER 500 ml WET 500 ml COUNT TIME:

1000 MINS 500 MINS 500 MINS 500 MINS 500 ml 500 MINS DELAY TO 10 DAYS 3 DAYS 7

DAYS 5 DAYS 500 MINS 30 DAYS COUNT:

5 DAYS NUCLIDES BE-7 0.99 40 4S 44 44 120 NA-22 2.1.

B.O B

6.9 6.9 30 K-40 32 70 so 70 70 70 CR-Sl.

9.2 30 30

41.
41.

12S MN-S4 1..2 4.8 7

6.9 6.9 28 CO-SB 1.. B 8.0 1.0 S.3 S.3 l.S FE-S9 3.6 1.4 l.S 1.0 1.0 46 C0-60 2.3 7.6 1.2 6

6 40 ZN-6S 3.6 B

l.B 20 20 42 NB.:.95 l.S 1.5.

1.2 1.5 1S 40 M0-99 96 9S 1.30 400 400 6SOOOO RU-1.03 1.. 0 5.0 7

4.9 4.9 24 RU-1.06 1.2 38 30 38 38 1.20 AG-1.l.OM 2.2 8.7 l.S 1.2 1.2

21.

SB-1.25 2.8 1.4 2S 1.2 1.2 36 TE-l.29M 4.7 1.60 22S 2SO 2SO 600 I-1.31.

2 6.0 1.2 1.1.. 0 1.1.. 0 l.8S TE-1.32 4.4 6.0 40 60 60 4000 BA-1.33 7.5 1.4. 0 1.2 1.20 1.20 40 CS-1.34 0.96 6.5 1.0 S.7 5.7 34 CS-1.36 l..S 6.1.

1.2 7.S 7.S 46 CS-1.37 1..4 6.7 1.2 1.2 1.2 2S BALA-1.40 2.0 1.2. 0 l.S 3S 3S 1.60 CE-1.41.

1.. 0 s.1.

7.0 S.2 5.2 26 CE-144 4.2 20 22 1.8 1.8 S2 RA-NAT 2.3 l.S 1.5 20 20 40 TH-232 6.1.

31.

30 29 29 so 78

APPENDIX D

SUMMARY

OF RESULTS FROM USEPA AND ANALYTICS INTERLABORATORY COMPARISON PROGRAMS 79

APPENDIX D

SUMMARY

OF USEPA INTERLABORATORY COMPARISON PROGRAM AND ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM Appendix E presents a summary of the analytical results for the 1996 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program and from Analytics Environmental Crosscheck Program.

TABLE NO.

D-1 D-2 D-3 D-4 TABLE OF CONTENTS TABLE DESCRIPTION Gross Alpha and Gross Beta Emitters in Water....

83 Gamma Emitters in Water and Milk.................

84 Tritium and Iodine in Water and Iodine in Air....

86 Strontium-89 and Strontium-90 in Water...........

87 81

JI TABLE D-1 RESULTS FOR USEPA INTERLABORATORY COMPARISON PROGRAM AND ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM Gross Alpha and Gross Beta Analysis of Water (pCi/L)

EPA/ANL Acceptance Criteria DATE PSE&G EPA/ANL Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d.

Known Limit Limit 01-96 EPA-WAT-AB404 Water Alpha 13+/-1.7 12 3.4 20.8 Beta 9.7+/-0.6 7

-1. 7 15.7 04-96 EPA-WAT-P412 Water Alpha 81+/-3.2 75 42.4 107 Beta 173+/-5.6 167 124 210 07-96 EPA-WAT-AB419 Water Alpha 20+/-3.8 24 13.8 35 Beta 44+/-2. 5 45 36.1 53.5 10-96 EPA-APT-P425 Water Alpha 68+/-2.3 59 33.5 84.7 Beta 124+/-7.9 112 82.7 140.9 10-96 EPA-WAT-AB433 Water Alpha 12+/-2.6 10.3 1.6 19 Beta 37+/-1. 0 34.6 25.9 43.3 03-96 ANL-WAT-AB406 Water Beta 116+/-5.6 98 68 128 06-96 ANL-WAT-AB415 Water Beta 202+/-3.0 174 120 228 09-96 ANL-WAT-AB420 Water Beta 88+/-3.0 70 46 94 12-96 ANL-WAT-AB428 Water Beta 253+/-4.0 207 147 267

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

TABLE D-2 RESULTS FOR USEPA INTERLABORATORY COMPARISON PROGRAM AND ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM Gamma Analysis of Water and Milk (pCi/L)

.EPA/ANL Acceptance Criteria DATE PSE&G EPA/ANL Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d.

Known Limit Limit 04-96 EPA-WAT-P412 Water Cs-134 44+/-1.2 46 37.3 54.7 Cs-137 52+/-2.5 so 41.3 58.7 Co-60 33+/-1.2 31 22.3 39.7 06-96 EPA-WAT-G414 Water Ba-133 731+/-24 745 615.1 874.9 Co-60 97+/-2.5 99 90.3 107.7 Zn-65 302+/-5 300 248 352 Cs-134 1

737+/-25 79 70.3 87.7 Cs-137 193+/-4.7 197 179.7 214.3 10-96 EPA-WAT-P425 Water Co-60 15+/-0 15 6.3 23.7 Cs-134 20+/-1.2 20 11.3 28.7 Cs137 32+/-1.2 30 21.3 38.7 11-96 EPA-WAT-G427 Water Ba-133 62+/-1.2 64 53.6 74.~

Co-60 44+/-1.7 44 35.3 52.7 Zn-65 37+/-1. 5 35 26.3 43.7 Cs-134 11+/-1.0 11 2.3 19 *~7 Cs-137 22+/-1. 0 19 10.3 27.7 03-96 ANL-WAT-G408 Water Cr-51 381+/-9.1 322 226 418 Mn-54 43+/-4.0 31 19 43 Co-58 59+/-1.5 48 36 60 Fe-59 105+/-9.5 83 59 107 Co-60 87+/-5.3 76 52 100 Zn-65 129+/-6.2 97 67 127 I-131 47+/-4.4 36 24 48 Cs-134 65+/-4.2 58 40 76 Cs-137 69+/-2.6 64 46 82 Ce-141 97+/-5.0 88 64 112 -,

1 A transcription error occurred which resulted in our reporting the wrong number for cs-134 to EPA.

Our results should have been reported as 74 pCi/L.

  • s.d. -

one standard deviations of three individual analytical results 84

J, TABLE D-2-Con't RESULTS FOR USEPA INTERLABORATORY COMPARISON PROGRAM AND ANALYTICS ENVIRONMENTAL CROSSCHECK PROG~

Gamma Analysis of Water and Milk (pCi/L)

EPA/ANL Acceptance

~

Criteria DATE PSE&G EPA/ANL Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d.

Known Limit Limit 03-96 ANL-MLK-G410 Milk K-40 1624+/-33 1656 696 2616 Cr-51 992+/-25 858 600 1116 Mn-54 92+/-3.5 84 60 108 Co-58 134+/-5.5 128 92 164 Fe-59 275+/-1. 0 223 157 289 Co-60 221+/-0.6 204 144 264 Zn-65 323+/-20 260 182 338 Cs-134 165+/-5.5 154 106 202 Cs-137 186+/-8.7 170 116 224 Ce-141 253+/-7.5 234 162 306 12-93 ANL-WAT-G430 Water Mn-54 205+/-4 202 142 262 Co-58 118+/-4 119 83 155 Co-60 107+/-6 108 78 138 Zn-65 106+/-14 91 61 121 Cs-134 158+/-10 172 118 226 Cs-137 192+/-10 191 131 251 Ce-141 262+/-18 272 188 356

  • s.d. - one standard deviations of three individual analytical results 85

TABLE D-3 RESULTS OF USEPA INTERLABORATORY COMPARISON PROGRAM AND ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM Tritium and Iodine Analysis of Water (pCi/L) and Iodine in Air Samples (pCi/m 3

)

EPA/ANL Acceptance Criteria DATE PSE&G EPA/ANL Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d.

Known Limit Limit 03-96 EPA-WAT-H405 Water H-3 21137+/-155 22002 18192 25812 08-96 EPA-WAT-H426 Water H-3 10460+/-115 10879 8995 12763 *.

02-96 EPA-WAT-I403 Water I-131 64+/-1.5 67 54.9 79.1 10-96 EPA-WAT-I424 Water

  • I-131 28+/-2.5 27 17 37 03-96 ANL-WAT-H407 Water H-3 3053+/-38 2982 2088 3876 03-96 ANL-AIO-I411 AIO I-131 78+/-1. 5 70 46 94 06-96 ANL-AIO-I416 AIO I-131 86+/-0.5 84 60 108 06-96 ANL-WAT-H418 Water H:..3 4777+/-75 4915 3439 6391 09-96 ANL-AIO-I421 AIO I-131 69+/-0.4 60 42 78 09-96 ANL-WAT-H423 Water H-3 2167+/-51 2259.

1581

. 2937.

12-96 ANL-AIO-I429 AIO I-131 89+/-4 79 55 103 12-96 ANL-WAT-H431 Water H-3 2667+/-65 2686 1882 3490

  • s.d. -

one standard deviations of three individual analytical results 86

..J DATE MM-YY 04-96 10-96 07-96 TABLE D-4 RESULTS OF USEPA INTERLABORATORY COMPARISON PROGRAM AND ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM Strontium-89 and Strontium-90 Analysis of Water -(pCi/L)

ENV SAMPLE CODE MEDIUM EPA-WAT-P412 Water EPA-WAT-P425 Water EPA-WAT-S432 Water ANALYSIS Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 PSE&G Mean +/- s.d.

41+/-0 17+/-0 17+/-1.2

.22+/-0. 6 17+/-4.0 10+/-1.2 EPA/ANL Acceptance Criteria EPA/ANL Lower & Upper Known Limit Limit 43 34.3 51.7 16 7.3 24.7 10 1.3 18.7 25 16.3 33.7 25 16.3 33.7 12 3.3 20.7

  • s.d. - one standard deviations of three individual analytical results 87

68 r

SfiSNH~ HSn CJ.NY~ ~o SISdO.NXS

a: XI ClN:!l:d dY r

J

-1 APPENDIX E SYNOPSIS OF 1996 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 animal2 the nearest residence, and the nearest garden of greater than 50m (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, 1996 July, 1996 July, 1996 Sector km (miles) km (miles) km (miles)

N None None None NNE None 6.9 ( 4. 3)

None NE None 6.4 ( 4. 0)

None ENE None 5.8.(3. 6)

None E

None 5.4 (3. 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 91

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