ML18094B444

Artificial Island Radiological Environ Monitoring Program for Salem Generating Station Units 1 & 2 & Hope Creek Generating Station,1989 Annual Radiological Environ Operating Rept. W/900430 Ltr

ML18094B444
Person / Time
Site:	Salem, Hope Creek
Issue date:	12/31/1989
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N90080, NUDOCS 9005070235
Download: ML18094B444 (179)

Text

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Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1100 Vice President and Chief Nuclear Officer APR 3 0 1990 NLR-N90080 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 1989 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 As required by Section 6.9.1.10 of Appendix A to facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Uni ts No. 1 and 2, and Section 6. 9. 1 ~. 6 of Appendix A to Facility Operating License NPF-57 for Hope Creek Generating Station, Public Service Electric and Gas hereby transmits one copy of the 1989 Annual Radiological Environmental Operating Report. This report summarizes the results of the radiological environmental surveillance program for 1989 in the vicinity of the Salem and Hope Creek Generating Stations. The result of this program for 1989 were specifically compared to the result of the preoperational program.

Should you have any questions or comments regarding this submittal, please do not hesitate to contact us.

sincerely, Enclosure

I - -- *

.*f' Document Control Desk 2 APR 3 O 1990 NLR-N90080 C Mr. J. c. Stone Licensing Project Manager - Salem Mr. C. ~. Shiraki Licensing Project Manager - Hope Creek Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

RTL-ENV-90-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM For Salem Generating Station, Unit 1: Docket No. 50-272 Salem Generating St~tion, Unit 2: Docket No. 50-311 Hope Creek Generating Station: Docket No. 50-354

• 1989 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1989 Prepared By PUBLIC SERVICE ELECTRIC AND GAS COMPANY RESEARCH AND TESTING LABORATORY APRIL 1990

AR1'1F'ICIAL ISLAND RADIOLOGICAL ENVIRONMEN'TAL MONITORING PROGRAM GENERATmG STATIONS 1989 ANNUAL RADIOLOGICAL ENVIRONMEN'TAL OPERATING REPORT JANUARY 1 TO DECElVIBER 31, 1989

SUMMARY

TABLE OF CONTENTS PAGE 1

INTRODUCTION. .. . . . . . . ... .. . . . . . .. .. . . ..... ... . .. . . . . .. . . . . . . 3 Radiation Characteristics ** 3 Radiation Effects ********* ........... ... 4 Sources of Radiation Exposure ** .. 4 Nuclear Power Reactors ******** 7 Containment of Radioactivity ** ..... 13 Sources of Radioactive Liquid and Gaseous Effluents. 16 Radioactivity Removal from Liquid and Gaseous Wastes ** 16 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ******** 18 Objectives *********** 19 Data Interpretation ** 20 Quality Assurance Program ** 21

• Program Changes ******** 21 Results and Discussion. 22 Atmospheric ****** 22 Direct Radiation ** 26 Terrestrial ** 27 Aquatic ****** 37 Program Deviations ** ..... . . . . . 44 Conclusions. . . . . . .. . . . . . . . . . . 45 REFERENCES ** ... . . . . . ..... . . . .. . .. .. .... .. .. . . . . . . . . . . . . . . . .. 60 APPENDIX A PROGRAM

SUMMARY

. ..... ...... .... .. . . . . . . . . . . . . .. 63 APPENDIX B SAMPLE DESIGNATION AND LOCATIONS. 77 APPENDIX C DATA TABLES. ..... . ................ ......... ... . 85 APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES. . .. . . . . . . . . 131 APPENDIX E -

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS * *********************************** 169 APPENDIX F SYNOPSIS OF LAND USE CENSUS ******************** 177 i

TABLE NUMBER LIST OF TABLES TABLE DESCRIPTION PAGE

1. Conunon Sources of Radiation **..*..*.*.***...*****.. 6

2. 1989 Artificial Island Radiological Environmental Monitoring Program (Program Overview) ****..***.**** 46 LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION PAGE

1. BWR Vessel and Core .*. .**************.*.*.**.**.**. 9

2. Schematic of BWR Power Plant ...*.*..*****.*...*.*.* 10

3. Schematic of PWR Power Plant **.***.*****..**.**..** 12

4. Primary PWR Containment Cross-Section (Salem units 1 & 2) ******************************** 14

5. BWR Mark 1 Primary Containment Cross-Section (Hope Creek) ***.***.**.***.**....*****..**.***..*.. 15

6. Beta Activity in Precipitation and Air Particulates 1973 through 1989 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 6A. Beta Activity in Precipitation and Air Particulates 1986 through* 1909 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 1

• I ii

• LIST OF FIGURES '(Cont Id.)

FIGURE NUMBER FIGURE DESCRIPTION PAGE

7. Ambient Radiation - Offsite Vs Control Station TLDs 1973 through 1989 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 7A. Ambient Radiation - Offsite Vs Control Station TLDs 1986 through 1989 ********************************* 53

a. Iodine-131 Activity in Milk 1973 through 1989 . . . .. 54 BA. Iodine-131 Activity in Milk 1986 through 1989 . . ... 55

9. Gross Beta and Potassium-40 Activity in Surface Water 1973 through 1989 * * * * * * * * * * * * . * * . . . * * * * * * * * . * * * * * . 56 9A. Gross Beta and Potassium-40 Activity in Surface Water 1986 through 1989 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57

10. Tritium Activity in Surface Water, 1973 through 1989 . . . . . . . . . . . . . . . . . . . . . * . . . . . . . . . . . . . . . . . . . . . . . . 58 lOA. Tritium Activity in Surface Water, 1986 through 1989 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59

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SUMMARY

I.

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 semi-annual frequency.

The PSE&G Research and Testing Laboratory (RTL) has been responsible for the collection and analysis of environmental samples during the period of January 1, 1989, through December 31, 1989, and the results are discussed in this report. The radioactive liquid and gaseous effluents due to the operation of SGS and HCGS during 1989 did not adversely affect the environment around Artificial Island.

Most of the radioactive materials noted in this report are normally present in the environment, either naturally, such as potassium-40, or as a result of non-nuclear generating station activity such as nuclear bomb testing. Measurements made in the vicinity of Artificial Island were compared to background or control measurements and the preoperational REMP study performed before Salem Unit 1 became operational. Samples of air particu-lates, air iodine, precipitation, milk, surface, ground and drinking water, vegetables, beef, game, fodder crops, fish, crabs, and sediment were collected and analyzed. External radiation dose measurements were also made in the vicinity of Artificial Island using thermoluminescent dosimeters.

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 report are summarized below:

• There were a total of 2351 analyses on 1375 environmental samples during 1989. Direct radiation dose measurements were also made using 451 thermoluminescent dosimeters (TLDs).

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• In addition to the detection of natural-occurring isotopes (i. e. Be-7, K-40, Ra-226 and Th-232), low levels of Mn-54, Co-58, Co-60, Sr-90, Cs-136, Cs-137 and BaLa-140 were also detected in various media. The detection of these radionuclides can be attributed to atmospheric weapons fallout, statistically positive results (within the lower limit of detection (LLD) range of the isotope but with a large margin of error) or coincident sampling at the time a effluent release was in progress. All of these radionuclides were at concentrations well below Technical Specification reporting levels.

• Dose measurements made with TLDs* at 41 locations around Artificial Island averaged 62 millirads for 1989. This was comparable to the preoperational phase of the program which had an average of 55 millirads for 1973 to 1976.

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jINTRODUCTIONI This section gives a brief description of the characteristics, effects, and sources of radiation and the operation of a nuclear generating station, both a boiling water reactor and a pressurized water reactor. It is hoped that this will provide the reader with a better understanding of this report.

RADIATION CHARACTERISTICS The word "radioactive" describes the state of the nucleus of an atom containing an excess of energy. The excessive energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom. To release this excess energy the atom emits electromagnetic or particulate radiation to become stable (non-radioactive). This process is called radioactive decay. Part of the electromagnetic spectrum consists of gamma-rays and x-rays, which are similar in nature to light and microwaves. Particulate radiation may be in the form of electrically charged particles such as alpha (2 protons plus 2 neutrons) and beta (1 electron) particles, or have no charge at

• all (neutron).

Radioactive decay is measured in terms of "half-life". The half-life may be defined as the amount of time it takes for a radio-active material to decay to half of its original activity. The half-life of a radionuclide depends on the radionuclide and can range anywhere from a fraction of a second to as long as several million years. Each radionuclide also has a unique decay characteristic, both in terms of the energy of its radiation and the types of its radiation. Radionuclides may decay directly into a stable element or go through a series of decays (becoming several different radioisotopes) before eventually becoming a stable element.

Radioactivity is measured by the number of nuclear disintegra-tions (decays) of the source of radiation per unit of time. The unit of this measurement is called the curie. One curie equates to 2.2 trillion disintegrations per minute. For the purpose of quantifying the effluerits of a nuclear power reactor this unit is broken down into a microcurie and a picocurie. The microcurie is one millionth of a curie and represents 2.2 million decays per minute, while the picocurie is one millionth of a microcurie and represents 2.2 decays per minute.

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RADIATION EFFECTS Radiation effects are measured in terms of the amount of biological damage produced. Biological damage from electro-magnetic and particulate radiation is produced by ionizing an atom, breaking a chemical bond, or altering the chemistry of a living cell. To assess biological damage, the type, energy, and amount of radiation must be considered.

There are essentially two types of exposure to radiation:

external.and internal. External exposure can involve the total body, thereby implying exposure to all organs, or parts of the body, such as the arm, foot, or head. Internal exposure, meaning the uptake of radioactive elements by inhalation, ingestion, or by means of a cut, can involve a single selective organ or several organs.

An example of the selectivity of internal exposure is the uptake of a radioiodine which concentrates in the thyroid gland, versus the uptake of a radiocesium which will collect in the muscle and liver. The quantity of the radionuclide and duration of time a radionuclide remains in the body directly influences the total exposure or dose *to an organ. The duration of time depends on the amount of radioactive decay and the length of time it takes to remove the radionuclide from the body (biological decay). It should be noted that the biological effect of radiation is independent of the source (internal or external) and dependent on the dose.

The measurement of dose to man is typically expressed in terms of a unit called the rem. As a better unit of dose, the millirem (mrem; 1 mrem =1/1000 rem) is most often used because the typical dose is usually on the order of thousandths of a rem. Another term used is the collective dose to a population, called a person-rem. A person-rem is calculated by adding up each individual dose to a population (e.g. O.OOOl*rem to each person of a population of 10,000 persons= 1 person-rem).

• SOURCES OF RADIATION EXPOSURE Radioactive elements have existed on our planet (and on every-thing that has emerged from it) since its formation, including our own bodies. Every second over 7000 atoms undergo radioactive decay in the body of the average adult (or roughly 420,000 disintegrations per minute) from natural background.

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• Many sources of radiation exist today and, of them, the most universal and least controllable is background radiation from terrestrial radioactivity and cosmic rays. Terrestrial radio-activity originates from such radionuclides as potassium-40 (K-40), uranium-238 (U-238), thorium-232 (Th-232), radium-226 (Ra~226), and radon-222 (Rn-222). Some of these radionuclides have half-lives of millions of years and are introduced into the water, soil, and air by such means as volcanoes, weathering, erosion, diffusion, and radioactive decay.

One naturally-occurring terrestrial radionuclide is a significant source of radiation exposure to the general public---radon gas.

Radon gas (Rn-222) is an inert gas produced in the ground from the radioactive decay of radium (from the decay of uranium and thorium) and emitted into the air. Because of the use of lime and gypsum (which would contain radium) in its production, building materials such as cinder block, sheet rock, and concrete are also radon gas sources. Concentrations of radon gas are dependent on the concentrations of radium (uranium and thorium) in the soil, altitude, soil permeability, temperature, pressure, soil moisture, rainfall, snow cover, atmospheric conditions, and season. The gas can move through cracks and openings into-base-ments of buildings, become trapped in a small air volume indoors and result in higher concentrations than found outdoors~ Radon can also be dissolved in well water and contribute to airborne radon in houses when released through showers or washing

• Since radon gas is radioactive, it, too, continues to produce, by decay, other radioactive materials referred to as radon daughters. These daughters are solid particles which can stick to surfaces such as dust particles in the air. The dust containing the radon daughter particles can ,be inhaled and deposited in the lungs. Radon daughters emit high energy alpha particles which results in an average dose to the lungs of 300 mrem (0.3 rem to a 10 year old) in the United States. In areas such as New Jersey and Pennsylvania, over a geological formation known as the Reading Prong, doses much higher than 300 rem/yr have been recorded due to natural deposits of uranium. Doses due to radon gas and its daughters are the highest dose contributor to individuals from all natural sources.

Cosmic rays are high energy electromagnetic rays which originate from outer space. About 300 cosmic rays pass through each person every second. Cosmic rays also interact with atoms in the earth's atmosphere arid produce radioactive substances such as carbon-14 (C-14), sodium-22 (Na-22), beryllium-7 (Be-7), and tritium (H-3). Some of these radionuclides become deposited on land and water while the rest remain suspended in the atmosphere.

Other naturally-occurring sources of radiation which contribute to doses to the human body are trace amounts of uranium and radium in drinking water and radioactive potassium in milk.

Sources of naturally-occurring radiation and their average dose contribution are summarized in Table 1.

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TABLE 1 COMMON SOURCES OF RADIATION*

Approximate Approximate Dose Dose Natural Sources Cmrem/vearl Manmade Sources Cmrem/yearl Cosmic Rays 42 Medical radiation 90 Building Materials 35 Television and

- Internal 28 consumer products 1-5 Ground 11 Weapons Fallout 2-5 Nuclear Power Plants 1 APPROXIMATE TOTAL 100 100

Reference:

NUREG-0558 and EPA Report ORP/SID 72-1 The average individual in the United States receives approxi-mately 100 mrem per year from natural sources. In some areas the dose from natural radiation is significantly higher. Residents of Colorado receive an additional 80 mrem per year due to the increase in cosmic (higher elevation) and terrestrial radiation levels. Transcontinental and intercontinental airline pilots receive 1000 mrem/yr due to ~he high elevation and length of these flights and resultant higher cosmic radiation levels. In several locations around the world high concentrations of mineral deposits give natural background radiation levels of several thousand mrem per year.

The average individual is also exposed to radiation from a number of man-made sources. The single largest of these sources comes from medical diagnostic tools such as X-rays, CAT-scans, fluoro-scopic examinations and radio-pharmaceuticals. Approximately 160 million people in the United States are exposed to medical or dental X-rays in any given year. The annual dose to an individual from such medical irradiation averages 90 mrem which is approximately equal to the annual sum of natural radiation.

Smaller doses from man-made sources come from consumer products (television, smoke detectors, fertilizer), fallout from prior nuclear weapons tests, and production of nuclear power and its associated fuel cycle.

There are approximately 200 radionuclides produced in the nuclear weapons detonation process; a number of these are detected in fallout. Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of nuclear weapons. Fallout can be washed down to the earth's .

surf ace by rain or snow and is dispersed throughout the environ-ment. The radionuclides found in fallout which produce most of the fallout radiation exposures to man are I-131, Sr-89, Sr-90, and cs-137. There have been no atmospheric weapons tests in

• this country since 1964.

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• NUCLEAR POWER REACTORS After World War II and during the development of atomic weapons, an understanding of the great energy potential from atomic chain reactions was realized and put to peaceful use. Among the most successfully developed peaceful uses were nuclear power reactors.

It was known that the fission reactions in an atomic weapon detonation generated large amounts of energy and heat. If that energy and heat could be harnessed, electricity could be produced. As a comparison, one pound of uranium-235 (the fuel of a nuclear reactor) could produce the heat of 1,500 tons of coal. So, at the University of Chicago, under the direction of Enrico Fermi, the world's first nuclear reactor began operation (went critical) on December 2, 1942.

It wasn't until 1957 that the nuclear reactor was first used to commercially produce electricity in Shippingport, Pennsylvania.

Today there are over 100 reactors for public power generation of electricity in this country and 300 in the world.

The function of a nuclear reactor is to generate heat to produce electricity. The generation of heat is accomplished by permitting self-sustaining, controlled nuclear fissions. Nuclear fission is the splitting of an atom when hit by a neutron, which, in turn, produces two entirely different atoms, as well as generating a lot of heat. When one fission occurs more neutrons are given off which leads to more atoms to fission, producing more neutrons etc., thus giving rise to a chain reaction. The atom bomb, using large masses of fissionable material, is a chain reaction uncontrolled. Nuclear reactors, on the other hand, use small masses of fissionable material (thus making it impossible for a nuclear explosion), and are therefore able to sustain a controlled chain reaction.

The best known and most widely used material for the fission reaction is uranium-235. Most uranium exists in the form U-238 (238 refers to the atomic mass, i.e., the number of protons and neutrons combined). However, it also exists in the form of uranium-235 which is in a proportion of one atom per 140 atoms of U-238. Uranium-235 becomes very unstable when its nucleus is struck by a neutron. To overcome the instability, the uranium atoms split (fission) and become two fission products (e.g.

Iodine 131 and Xenon 133). When the fission occurs, some neutrons are released to initiate another fission and start a chain reaction.

Th~re are several different ways to control the rate of a chain reaction. Some of these means are the use of moderators, varying the size of a reactor vessel, and using neutron absorbing materials (such as cadmium) as control rods.

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There are three major types of* nuclear reactors in operation in the world: the pressurized light-water reactor (PWR), boiling light~water reactor (BWR), and the gas-cooled reactor. The nuclear reactors built and operating on Artificial Island are the BWR (Hope Creek) and the PWR (Salem Units land 2).

Of the two types of light-water reactors (LWR), the BWR has a simpler design. In a BWR the steam desired to generate electricity is produced in the core itself. Here, step by step, is how the BWR works (refer to Figures l and 2):

1. Water enters the reactor vessel through the reactor core which consists of 764 fuel assemblies. Each assembly consists of 64 zirconium alloy fuel rods about 13 feet long. Sixty-two of these rods contain uranium fuel pellets.

The fuel pellets have been enriched so that the U-235-to-U-238 ratio is now one atom of U-235 to every 20 to 40 atoms of U-238. The core is contained in a 6" thick steam reactor vessel about 75 feet high* and weighing 624 tons.

2. The water flows along the fuel rods. Then, when the 185 control rods (containing cadmium) are withdrawn, the fissioning process in the fuel rods generates heat that causes the water passing through the core to boil into steam in the reactor vessel.

3. The steam flows through the steam lines at the top of the reactor directly into a turbine generator (see Figure 2).

4. In the turbine, the force of the steam striking the blades attached to a shaft causes the shaft to spin.

5. The shaft spins inside a generator, causing a magnetic field to move through coils of wire to produce electricity.

6. A second separate water system, carrying cooling water

• from an outside source (e.g. the cooling tower located on Artificial Island), condenses the steam back to water.

7. The condensed water is then pumped back into the reactor vessel to start the entire cycle again.

The fission chain reaction is controlled by the 185 control rods located between the fuel assemblies. These control rods contain material which absorbs neutrons and controls the rate of fissioning. By moving the control rods up or down, the reactor can sustain a chain reaction at desired power levels. By inserting them all the way into the reactor core, fissioning can be completely stopped.

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FIGURE 1 BWR VESSEL & CORE STEAM FEEDWATER FEEDWATER (FROM CONDENSER) ~~ (FROM CONDENSER)

RECIRCULATION RECIRCULATION PUMP PUMP

FIGURE 2 SCHEMATIC OF BWR POWER PLANT DRYWELL (PRIMARY CONTAINMENT)

~

l SHIELD BUILDING I-'

0 STEAM - GENERATOR REACTOR . - - - - . . - - - , - - - - - - , - - - - - - 7 VESSEL COOLING TURBINE TOWER

+-WATER RECIRC PUMP

~

PRESSURE SUPPRESSION POOL COOLING WATER (TORUS) (RIVER)

A PWR differs from a BWR in that water inside the reactor vessel system is pressurized to prevent boiling (steam) when heated.

This pressurized hot water is used to heat a second source of water, at a lower pressure, which will produce steam to turn the turbines. The following step-by-step outline indicates how the PWR works (see Figure 3):

1. Within the 424-ton reactor vessel at SGS, water flows across 193 fuel assemblies in the reactor core. Each assembly consists of 264 fuel rods, each about 15 feet long.

2. The water flows along the fuel rods. When the 53 control rods are raised, the fissioning process begins and the water is heated to about 600°F by the nuclear fission process. This water is referred to as the primary coolant. The primary coolant is maintained at about 2000 psi of pressure to keep the water from boiling, hence a pressurized water system.

3. The primary coolant flows from the reactor as a hot liquid to tubes in the steam generators where the water gives up its heat {cooled) to the water in the steam generator.

The water in the steam generator is called secondary coolant. The primary water, after giving up its heat, is returned to the reactor core to start the process over *

• 4. The secondary coolant in the steam generator is not under high pressure and turns to steam because of the primary coolant heat-up. This steam is sent through steam lines to the turbine generator to generate electricity in the same method as outlined in the BWR description above.

5. The exhausted steam from the turbine is channeled into the condenser below the tur~ine, cooled back into water .and returned to the steam generators. The cooling action of the condenser is provided by a third {tertiary coolant) system of circulating water drawn from a river, ocean, or lake {at SGS, this is the Delaware River).

About 65 percent of the nuclear power plants in the United States are PWRs and 35 percent are BWRs. The PWR is also used in nuclear submarines and other navel vessels *

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FIGURE 3 SCHEMATIC OF PWR POWER PLANT OUTER CONCRETE (CONTAINMENT SHIELD)

STEEL (SHELL)

PRIMARY SYSTEM SECONDARY SYSTEM

• • • REACTOR STEAM

.. PRIMARY GENER- TURBINE GENERATOR REACTOR *.COOLANT ATOR SYSTEM CONDENSER

• .... :REACTOR COOLANT PUMP WATER (CONDENSATE)

COOLING WATER (RIVER)

CONTAINMENT OF RADIOACTIVITY The radioactivity present in a nuclear reactor is not just derived from U-235 fuel and the fission products generated from the chain reaction. Other radioactive substances are generated by means of activation. Activation products are corrosion materials, from component and structural surfaces in the coolant water, that become radioactive. The materials become radioactive or activated when hit by neutrons from the fission reaction.

There are a series of several barriers to contain the radio-activity present in a light water reactor. The first of these is the nuclear fuel itself. The fission products are trapped inside the ceramic fuel pellets that are designed to retain them. The fission products that are gaseous or volatile migrate out of the fuel.

Encasing the fuel pellets are metal fuel rods (known as fuel cladding) designed to retain the fuel pellets. The small fraction of fission products that might leave the fuel pellets (such as the gaseous products) are collected here in small gaps between the fuel pellets and cladding.

The next barrier level is the cooling water which is circulated around the fuel rods. The fission and activation products (such as radioiodines, strontiums, and cesiums) are soluble and are retained in the coolant. These materials can be removed by filter and purification systems used for the coolant.

The next level is the reactor vessel. The reactor vessel is a steel structure (6 to 8 inches thick) which contains the fuel rods and coolant. The vessel and its coolant systems provide containment for all radionuclides in the coolant.

From here the PWR and BWR differ in structure. The next barrier around a PWR reactor vessel is the containment building which is a four-foot thick, steel-reinforced (Salem Units l and 2 also include a steel liner) concrete structure (see Figure 4). It is designed to contain water and gases which may accidentally escape the above barriers. The containment is also designed to with-stand tornadoes, floods, and earthquakes.

In a BWR, the reactor vessel is contained in a drywell and pressure suppression chamber (see Figure 5). This system is designed to reduce the pressure and water build-up that may occur during a break in the steam piping. The walls of the drywell (which are two feet thick) consist of concrete with a steel containment shield over the reactor vessel top. The reactor vessel and drywell system is surrounded by a steel reinforced reactor building structure (see Figure 2).

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FIGURE 4 PRIMARY PWR CONTAINMENT CROSS-SECTION (SALEM UNITS 1 & 2)

POLAR GANTRY CRANE CONCRETE 191' 6" 4'-6' STEAM STEAM GENERATOR GENERATOR FAN FAN COIL COIL UNIT UNIT GROUND GROUND LEVEL LEVEL ACCUMULATOR ACCUMULATOR 156'6" 14

FIGURE 5 BWR MARK I PRIMARY CONTAINMENT CROSS-SECTION (HOPE CREEK)

DRY --1 ------1--i--+-----++-+-

REACTOR WELL VES SE L REC IRC PUMP PRESSURE SUPPRESSION' POOL

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SOURCES OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS Under normal operating conditions for nuclear power plants most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products are able to diffuse or migrate through the fuel cladding and into the primary coolant. Trace quantities of the component and structure surfaces, which have been activated, also get into the primary coolant water. Many of the soluble fission and activation products, such as radioactive iodines, strontiums, cobalts, and cesiums are removed by demineralizers in the purification system of the primary coolant. The noble gas fission products have a very low solubility in the primary coolant and therefore cannot be removed by the demineralizers.

Instead, they are released as a gas when the primary coolant is depressurized and are collected by a system designed for gas collection and decay. This represents the principal source of gaseous effluents.

Small releases of radioactive liquids from valves, p1p1ng, or equipment associated with the primary coolant system may occur in the reactor, auxiliary, and fuel handling buildings. The noble gases become part of the gaseous wastes, while the remain-ing radioactive liquids are collected in floor and equipment drains and sumps and are processed prior to release. Processed primary coolant water that does meet chemical specifications for reuse may also become waste water. These represent the principal sources of liquid effluents.

RADIOACTIVITY REMOVAL FROM LIQUID AND GASEOUS WASTES In a nuclear power plant, radioactive liquid and gaseous wastes are collected, stored, and processed through processing systems to remove or reduce most of the radioactivity (exclusive of tritium) prior to reuse within the plant or discharge to the environment. These primary systems are required by Technical Specifications to be installed and operable and help to ensure that all releases of radioactive liquid and gaseous effluents are as-low-as-reasonably-achievable (ALARA).

At both SGS and HCGS, liquid waste is routed through demineral-izers and filters which clean the water for recycling. If the demineralized water does not meet the requirements for reuse, the water is stored in tanks for sampling and *then analyzed for radioactivity and chemical content before being discharged to the Delaware River. If the water does not meet the requirements for release to the environment, then the liquid wastes are processed through the appropriate portions of the liquid waste treatment 16

system to provide assurance that the releases of radioactive liquid effluents will be kept ALARA. All concentrates produced from the demineralizers are packaged as solid waste for shipment and burial at an offsite burial facility.

At Salem, the circulating water system provides an additional minimum of 185,000 gallons per minute dilution flow for liquid releases. At Hope Creek, the cooling tower provides an additional 19,000 gallons per minute dilution flow prior to discharge to the Delaware River. The average flow rate of the Delaware River is five million gallons per minute and provides additional dilution.

In SGS, the waste gases collected by the vent header system are first routed to the gas compressors which compress the gases into waste gas decay tanks. After a waste gas decay tank is filled, the tank contents may be stored for a period up to 90 days (generally) to allow for decay of the shorter-lived radio-nuclides. In HCGS, the waste gases from the main condenser air ejectors are collected and delayed from release in the offgas system. The discharge of all waste gases at HCGS and SGS is made through high efficiency particulate air (HEPA) filters and charcoal filters prior to release. The filters are rated to be 95% efficient for iodines and greater than 99% efficient* for removal of particulates. Noble gases, however, cannot be removed by these filters. Gaseous effluents are discharged through elevated vents which enhances atmospheric dispersion and dilution.

Radioactive effluent releases are limited and controlled by release concentrations and dose limits, per Technical Specifica-tions and the U.S. Nuclear Regulatory Commission's regulation in Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 2-0).

These regulations are based on recommendations of the Inter-national Commission on Radiological Protection (ICRP), the National Council on Radiation Protection and Measurements (NCRP) and the Federal Radiation Council (FRC) for basic radiation protection standards and guidance. The operations of the Hope Creek and Salem Generating Stations (Units 1 and 2), and their associated effluent releases, were well within the 10 CFR 20 limits and maintained ALARA *

• 17

[THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM!

Artificial Island 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 1090 MWe (3338 MWt), and Salem Unit Two is rated 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).

Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic fill from dredging operations. It is located in Lower Alloways Creek Township, Salem County, New Jersey. The environment surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marsh-lands, and low-lying rneadowlands. 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 Report for SGS [9] and the Final Safety Analysis Report for HCGS [10].

Since 1968, an off-site Radiological Environmental Monitoring Program (REMP) has been conducted at the Artificial Island 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 Research and Testing Laboratory (RTL),

has been involved in the REMP since its inception. The RTL 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 RTL.

From January, 1973, through June, 1983, Radiation Management

~- Corporation (RMC) had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results. RMC reports for the the preoperational

.and operational phase of the program are referenced in this report [l-3]. On July 1, 1983, the RTL assumed primary responsibility for the analysis of all samples (except TLDs) and the reporting of results. Teledyne Isotopes (TI), Westwood, NJ, at that time was made responsible for third-party QA analyses and TLDs. An additional vendor, Controls for Environmental Pollution Inc. has been retained to provide third-party QA

.analyses and certain non-routine analyses. RTL reports for the operational phase from 1983 to 1988 are referenced in this report [4].

18

An overview of the 1989 Program is provided in Table 2. Radio-analytical 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 operations.

This report summarizes the results from January 1 through December 31, 1989, for the Artificial Island Radiological Environmental Monitoring Program.

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

• To fulfill the obligations of the Radiological Surveil-lance 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 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.1.7 of the Hope Creek Technical Specifications, summarizes the findings of the 1989 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Artificial Island have been summarized for purposes of compari-son with subsequent operational reports [2].

In order to meet the stated objectives, an appropriate oper-ational 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 selection of sample types was based on: (1), established critical pathways for the transfer of radionuclides through the environment to man, and, (2),

experience gained during the preoperational phase. Sampling locations were determined from site meteorology, Delaware estuarine hydrology, local demography, and land uses.

19

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. Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations.

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

Appendix A describes and summarizes, in accordance with Section 6.9.1.10 of the Salem TS and Section 6.9.1.7 of the Hope Creek TS, the entire operational program as performed in 1989.

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 level of +/- 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regula-tory 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 observa-tion 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 calcu-lated in accordance with Appendix B of Reference 16. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. When a group of data was composed of 50% or more LLD values, averages were not calculated.

Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid.

20

• QUALITY ASSURANCE PROGRAM The PSE&G Research and Testing Laboratory (RTL), 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 analytical methods utilized in this program are summarized in Appendix D.

The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Plan [17] and the Chemical/ Environmental Division Procedures Manual [18]. The internal quality control activity of the Laboratory 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 Laboratory Intercomparison Studies Program. These results are listed in Tables E-1 through E-5 in Appendix E.

PROGRAM CHANGES Six soil locations (5Dl, 2El, 2F2, 5F2, 2Fl and 3H3) were deleted from the program effective March 9, 1988. These samples were collected once every three years but are not required to be evaluated in the SGS or HCGS Technical Specifications. There are still ten samples evaluated for the REMP.

One well water location (5Dl) was deleted from the program effective April 1, 1989 due to unreliable access to the samples on a monthly basis. However, there were still two other well water sample locations maintained as required by the SGS and HCGS Technical Specifications *

• 21

RESULTS AND DISCUSSION The analytical results of the 1989 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1989 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 Artificial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating Stations Technical Specifications. The summary tables in this report include th.ese additional samples and analyses.

ATMOSPHERIC Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on triethylened~amine (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.

Precipitation was collected in a Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area.

The collector is automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition.

Samples were collected monthly and transferred to new poly-ethylene containers. The collector was rinsed with distilled water to include residual particulates in the precipitation samples. Tritium results were corrected for the tritium content of the distilled water.

Air Particulates (Tables C-1, C-2, C-3)

Air particulate samples were collected at six locations. Each of the 312 weekly samples collected were analyzed for gross alpha (management audit analysis) and gross beta. Quarterly composites of the weekly samples from each station were analyzed for specific gamma emitters and a single quarterly composite sample was analyzed for Sr-89 and Sr~90 as a management audit analysis. Total data recovery for the six sampling stations during 1989 was 99.1 percent.

22

• Gross alpha activity was detected in 195 of the indicator station samples at concentrations ranging from 0.9 x 10- 3 to 5.8 x 10- 3 pCi/m3

• Analysis of the 49 control station samples detected gross alpha activity levels ranging from 0.9 x 10- 3 to 4.1 x 10- 3 pCi/m3

• LLD sensitivities for the remaining 68 indicator and control station samples ranged from <0.9 x 10- 3 to <5.0 x 10- 3 pCi/m3

• Two indicator station samples analyzed by PSE&G did not meet the desired sensitivity of 2 x 10- 3 pCi/m3 due to low sample volumes caused by an air sampler malfunction. The LLD sensitivity for the samples analyzed by PSE&G were <2.1 x io- 3 and <3.6 x 10- 3 pCi/m3

• Samples analyzed by Controls for Environmental Pollution Inc., as part of the interlaboratory comparison program, ranged from <5.0 x 10 - 3 to <7.0 x 10- 3 pCi/m3 and are not included in the calculations for determining the year1y mean. The maximum preoperational level detected was 7.8 x 10- 3 pCi/m3.

• Gross beta activity was detected in 259 of the indicator station samples at concentrations ranging from 7 x 10- 3 to 55 x io- 3 pCi/m3 and in all 52 control station samples from 9 x io- 3 to 60 x io- 3 pCi/m3

• The averaqe for both indicator and control station samples was 25 x io- 3 pCi/m3

• The maximum preoperational level detected was 920 x io- 3 pCi/m3 , with an average of 74 x io- 3 pCi/m3.

• • Gamma spectrometric analysis performed on each of the 26 quarterly composite samples indicated the presence of and the naturally-occurring radionuclides Be-7, K-40 and Ra-226. All other gamma emitters searched for were below LLD.

o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in 17 of the 20 indicator station composites at concentrations ranging from 55 x io- 3 to.73 x 10- 3 pCi/m3 and in the four control station composites from 60 x io- 3 to 68 x 10- 3 pCi/m3

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

• o Potassium-40, a naturally occurring radionuclide, was not detected in any of the indicator stations' composites however it was detected in one control composite sample at a concentration of 8.6 x io- 3 pCi/m3

• This value is within the LLD sensitivities for the remaining samples, both indicator and control, which ranged from <4.5 x 10- 3 to <12 x 10- 3 pCi/m3. No preoperation data is available for comparison *

• 23

o Radium-226 was detected in one composites from the control station at a concentrations of 0.5 x 10- 3 pCi/m3. This value is within the LLD sensitivities for the remaining samples, both indicator and control, which ranged from <0.4 x 10- 3 to <1.0 x 10- 3 pCi/m3

• The maximum preoperational level detected was 16 x lo-3 pCi/m3.

• Strontium-89 and strontium-90 analyses were performed on five indicator station composites and one control station composite from the first quarter composites as management audit analyses.

o Strontium-89 was not detected in any of the six composites analyzed. LLD sensitivities for the seven indicator station samples ranged from <0.2 x 10- 3 to <2.0 x 10-3 pCi/m3 and for the control station at <0.3*x 10- 3' pCi/m3.

The maximum preoperational level detected was 4.7 x lo-3 pCi/m3

• o Strontium-90 was not detected in any of the six composites analyzed. LLD sensitivities for the six indicator station samples ranged from <0.2 x io- 3 to <2.0 x 10- 3 pCi/m3 and for the control station at <0.2 x 10- 3 pCi/m3

• The maximum preoperational level detected was 3.0 x 10-3 pCi/m3.

Air Iodine (Table C-4)

Iodine in filtered air* samples was collected at six locations.

Each of the 312 weekly samples was analyzed for I-131 **

• • Iodine-131 was not detected in any of the 312 weekly samples analyzed. LLD sensitivities for the 260 indicator station samples ranged from <4.8 x lo- 3 to <41 x lo- 3 oCi/m3 and for the 52 control station samples from <7.7 x 10- 3 to <22 x lo-3 pCi/m 3

• The maximum preoperational level detected was 42 x lo- pCi/m3

• 3 24

• Precipitation (Tables C-6)

Although not required by the SGS or HCGS Technical Specif i-cations, monthly precipitation samples were collected at a location in the town of Salem as management audit samples. Each of the twelve monthly samples collected were analyzed for gross alpha, gross beta, tritium and gamma emitters.

• Gross alpha activity was detected in three of the twelve samples at concentrations ranging from 0.9 and 3.6 pCi/L. LLD sensitivities for the remaining eight samples ranged from <1.1 to <2.3 pCi/L. The maximum preoperational level detected was 4.7 pCi/L.

• Gross beta activity was detected in nine samples at concentrations ranging from 3.0 to 8.5 pCi/L, with an average of 4.7 pCi/L. The maximum preoperational level detected was 71 pCi/L, with an average of 19 pCi/L.

• Tritium activity was not detected in any of the twelve samples. LLD sensitivities for the samples ranged from <130 to <160 pCi/L. The maximum preoperational level detected was 610 pCi/L, with an average of 216 pCi/L.

• Gamma spectrometric analysis performed on each of the monthly samples indicated the presence of the naturally- occurring

• radionuclides Be-7, K-40, and Ra-226. All other gamma emitters searched for were below LLD.

o Beryllium-7, attributed to cosmic ray activity, was detected in ten samples at concentrations ranging from 26 to 81 pCi/L, with an average of 52 pCi/L. The maximum preoperational level detected was 79 pCi/L, with an averag~

of 29 pCi/L. The increase in the naturally-occurring Be-7 activity over preoperational levels is most likely due to spallation reactions in the upper atmosphere and is not attributable to the operations of SGS or HCGS.

o Potassium-40 was detected in three of the samples at concentrations of 46, 68 and 295 pCi/L. The LLD sensitivities measured throughout the year ranged from <30 to <83. The 295 pCi/L result has been investigated. The 1460.75 keV photopeak, characteristic of K-40, was confirmed as being present in the sample. Trace levels of K-40 were detected in the preoperational program at a maximum level of 18 pCi/L. However, the presence of K-40 is not attributable to the operations of SGS or HCGS.

b Radium-226 was detected in two of the samples at concen-trations ranging from 9.1 to 23 pCi/L. The LLD sensitivities measured throughout the year for the remaining ten samples which ranged from <1.2 to <10 pCi/L.

No preoperational data is available for comparison *.

However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS.

25

DIRECT RADIATION Ambient radiation levels in the environs were measured with energy-compensated caso 4 (Dy) thermolurninescent dosimeters (TLDs) supplied and read by Teledyne Isotopes. Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances.

Direct Radiation (Tables C-7, C-8)

A total of 41 locations were monitored for direct radiation during 1989, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations, 15 off-site indicator stations and 3 control stations. An additional 14 quarterly measurements were taken at schools and population centers, with 3 additional controls beyond the 10 mile zone in Delaware.

• Four 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 10CFR20.4.

o The average dose rate for the 15 monthly off-site indicator TLDs was 5.9 millirads per standard month, and the corresponding average control dose rate was 6.5 millirads per standard month. The preoperational average monthly TLD readings was 4.6 millirads per standard month.

o The average dose rate for the 29 quarterly off-site indicator TLDs was 5.0 millirads per standard month, and the average control rate was 5.7. The preoperational average quarterly TLD readings was 4.4 millirads per standard month.

• In Figure 7, the average radiation levels are plotted for the 16 year period through 1989. Figure 7A shows the monthly averages of the off-site indicator stations and the control stations for 1982 through 1989. Ambient radiation levels during 1989 were comparable to those obtained during 1988.

26

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.

Beef is collected semi-annually, when possible, from farm animals at time of slaughter. The meat is weighed, then packed in plastic bags and kept chilled in ice chests during transport.

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-9, C-10)

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 Specif i-cations, one sample from each location was analyzed for Sr-89 and Sr-90 in order to maintain the data base developed in prior years.

e Iodine-131 was not detected in any of the 80 samples analyzed. LLD sensitivities for the 60 indicator station samples ranged from <0.3 to <0.6 pCi/L and for the 20 control station samples from <0.3 to <0.5 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 Cs-137 and the naturally-occurr ing radionuclides K-40, Ra-226 and Th-232. All other gamma emitters searched for were below LLD *.

27

o Cesium-137 was detected in one sample at a concentration ranging of 4.0 pCi/L with a detection error of 52% at the two sigma confidence level. This value is within the variations of the LLD sensitivities for the remaining 80 samples which ranged from <1.0 to <6.2 pCi/L. The maximum preoperational level of Cs-137 detected was 14 pCi/L. The possible presence of Cs-137 in the samples can be attributed to fallout from nuclear weapons testing.

o Potassium-40 was detected in all 80 samples. Concentra-tions for the 60 indicator station samples ranged from 1200 to 1500 pCi/L. The 20 control station sample concentra-tions ranged from 1200 to 1500 pCi/L. The average for the indicator station was 1300 pCi/L. The average for the control station sample was 1300 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.

o Radium-226 was detected in four samples from three indicator stations at concentrations ranging from 9.9 to 14 pCi/L and one control station at 6.7 pCi/L. LLD sensitivities for the remaining 75 samples ranged from <3.0 to <8.8 pCi/L. The maximum preoperational level detected was <30 pCi/L.

o Thorium-232 was detected in two samples from one indicator stations at concentrations of 15 and 16 pCi/L and one control station sample at 14 pCi/L. These values are near or below the LLD sensitivities for the remaining 77 samples which ranged from <8.0to <20 pCi/kg-wet. No preoper-ational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS.

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

o Strontium-89 was detected in one of the three indicator samples analyzed at 1.2 pCi/L, with a detection error of 42% at the two sigma confidence level. LLD sensitivities for the three indicator station samples ranged from <1.1 to

<1.2 pCi/L and for the control station at <1.1 pCi/L. The maximum preoperational level detected was 14 pCi/L.

o Strontium-90 was detected in one of the three indicator samples analyzed. Concentrations for the indicator station sample was 1.8 pCi/L and for the control station sample at 2.2 pCi/L. The average concentration for all samples was 2.0 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 nuclear weapons testing.

28

• Well Water (Tables C-11, C-12, C-13)

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 two indicator wells and one control well during January through March of the year and from one indicator location and one control location during the rest of the year. Location 5Dl was terminated at the end of March due to unreliable availability of

. the sample. The tenant at location 5Dl chose not to participate in our sampling program. Each sample was analyzed for gross alpha, gross beta, potassium-40, tritium and gamma emitters.

Quarterly composites were analyzed for Sr-89 and Sr-90.

• Gross alpha activity was detected in three of the indicator station samples at concentrations ranging from 0.5 to 1.6 pCi/L and in three of the control station samples from 0.3 to 1.3 pCi/L. These values are within the variations of the LLD sensitivities for the remaining 28 samples which ranged from

<l to <2.1 pCi/L. The maximum preoperational level detected was 9.6 pCi/L.

• Gross beta activity was detected in all 27 samples.

Concentrations for the 15 indicator station samples ranged from 3.6 to 14 pCi/L and for the 12 control station samples from 4.7 to 14 pCi/L. The average concentration detected for all samples was 8.1 pCi/L. The maximum preoperational level detected was 38 pCi/L, with an average of 9 pCi/L.

• Potassium-40 activity (determined by atomic absorption) was detected in all 27 samples. Concentrations for the 15 indicator station samples ranged from 3.2 to 16 pCi/L and for the 12 control station samples from 8.5 to 11 pCi/L. The average concentration detected for all samples was 7.8 pCi/L.

The maximum preoperational level detected was 19 pCi/L, with an average of 7.8 pCi/L.

• Tritium activity was detected in two indicator station samples at a concentrations of 170 and 190 and one control station at 250 pCi/L. The LLD sensitivities for the remaining 24 samples which ranged from <140 to <170 pCi/L. The maximum preoperational level detected was 380 pCi/L.

• Gamma spectrometric analysis performed on each of the 15 indicator station and 12 control station water samples indicated the presence of the naturally-occurring radio-nucl ides K-40, Ra~226 and Th-232. All other gamma emitters searched for were below LLD.

29

o Potassium-40 was detected in three samples from the two indicator stations with concentrations ranging from 9 to 33 pCi/L. These values are ~ithin the variations of the LLD sensitivities measured throughout the year for the remaining samples which ranged from <24 to <42 pCi/L. The maximum preoperational level detected was 30 pCi/L.

o Radium-226 was detected in eight of the two indicator station samples at concentrations ranging from 4.6 to 160 pCi/L and in eleven control station samples from 11 to 130 pCi/L. LLD sensitivities for the remaining indicator and control station samples ranged from <1.0 to <4.7 pCi/L. The maximum preoperational level detected was 2.0 pCi/L.

These values are similar to those found last year. However, as with the 1988 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 identi- f ication 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.

o Thorium-232 was detected in two samples from the two indicator stations with concentrations of 9.1 and 6.5 pCi/L and all <LLD values in control station samples. LLD sensitivities for the remaining indicator and control station samples ranged from <1.0 to <11 pCi/L. No preoperational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS, as it is a naturally occurring radionuclide.

• .Strontium-89 and strontium-90 analyses were performed on quarterly composites of the monthly well water samples o Strontium-89 was not detected in any of the six indicator station or four control station composites. LLD sensitiv-ities for indicator samples ranged from <0.9 to <1.5 pCi/L and for the control samples from <0.9 to <1.3 pCi/L. The maximum preoperational level detected was <2.1 pCi/L.

o Strontium-90 was not detected in any of the six indicator station or four control station composites. LLD sensitiv-ities for indicator samples ranged from <0.5 to <0.6 pCi/L and for the control samples from <0.4 to <0.5 pCi/L. The

• maximum preoperational level detected was 0.87 pCi/L.

30

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

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, K-40, tritium, iodine-131 and gamma emitters. Quarterly composites of monthly raw and treated water samples were analyzed for Sr-89 and Sr-90.

• Gross alpha activity was detected in two raw water samples at concentrations ranging from 1.7 to 3.6 pCi/L and in three treated water samples from 0.7 to 1.7 pCi/L. These values are within the variations of the LLD sensitivities for the remaining 19 samples which ranged from <1.1 to <2.5 pCi/L.

The maximum preoperational level detected was 2.7 pCi/L.

• Gross beta activity was detected in all 24 samples at concentrations ranging from 2.7 to 4.6 pCi/L for the raw water and from 2.9 to 4.0 pCi/L for treated water. The average.

concentration for both raw and treated was 3.5 pCi/L. The maximum preoperational level detected was 9.0 pCi/L, with an average of 4.2 pCi/L.

• Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples at concentrations ranging from 1.6 to 3.3 pCi/L for the raw water and from 1.6 to 2.9 pCi/L for treated water. The average concentration for both raw and treated was 2.4 and 2.5 pCi/L respectively. The maximum preoperational level detected was 10 pCi/L, with an average of 1.7 pCi/L.

• Tritium activity was detected in four raw water samples at concentrations ranging from 130 to 180 pCi/L and in one treated water sample at a concentration of 140 pCi/L. LLD sensitivities for the remaining 19 samples ranged from <130 to

<190 pCi/L. The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

• Iodine-131 measurements to a sensitivity of 1.0 pCi/L were performed. Since the receiving water body is brackish, the water is not used for human consumption. Drinking water supplies are not affected by discharges from the site.

Iodine-131 measurements were below the LLD sensitivities. The LLD sensitivites ranged from <0.3 to <0.7.

• Gamma spectrometric 'analysis performed on each of the 24 monthly raw and treated potable water samples indicated the presence of the naturally-occurring radionuclides, K-40 and Ra-226. All other gamma emitters searched for were below LLD *

• 31

o Although not as sensitive as atomic absorption, K-40 was detected in four samples at concentrations ranging from 20 to 52 pCi/L. The LLD sensitivities ranged from <12 to

<41 pCi/L. No preoperation data is available for comparison. However, the presence of trace levels of K-40 is not attributable to the operations of SGS or HCGS.

o Radium-226 was detected in two of the raw water samples at a concentration of 2.8 and 4.7 pCi/L and at a concentration of 4.7 pCi/L in one treated water sample. LLD sensitivities measured throughout the year for the remaining ten samples ranged from <2.7 to <5.0 pCi/L. LLD sensitivities for the 10 treated water samples ranged from

<2.5 to <4.9 pCi/L. The maximum preoperational level detected was 1.4 pCi/L.

• Strontium-89 and strontium-90 analyses were performed on quarterly composites of the daily raw and treated water samples.

o Strontium-89 was not detected in any of the four.raw water composites or four treated water composites. LLD sensitivities for the raw water sample composites ranged from <0.6 to* <1.5 pCi/L and for the treated water sample composites from <0.7 to <2.0 pCi/L. The maximum preoper-ational level detected was 1.1 pCi/L.

o Strontium-90 was detected in one treated water sample composite at a concentration of 0.6 pCi/L. The two sigma error associated with this value was 50%. LLD sensitivities for the remaining treated water sample composites ranged from <0.6 to <1.1 pCi/L and for the raw water sample composites from <0.5 to <0.8 pCi/L. The maximum preoperational level detected was 2.1 pCi/L.

Vegetables (Table C-17)

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 five indicator stations (11 samples) and two control stations (7 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 twenty samples indicated the presence of naturally- occurring radionuclides K-40, Ra-226 and Th-232. All other gamma emitters searched for were below LLD.

32

• o Potassium-40 was detected in eighteen samples.

Concentrations for the eleven indicator station samples ranged from 1500 to 2600 pCi/kg-wet and for the seven control station samples from 1300 to 2500 pCi/kg-wet. The average concentration detected for all samples was 1800 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2141 pCi/kg-wet.

o Radium-226 was detected in three samples from two control stations at concentrations ranging from 9.0 to 38 pCi/kg-wet. All indicator station results were below the LLD value. LLD sensitivities for the remaining samples ranged from <1.8 to <46 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the *operations of SGS or HCGS.

o Thorium-232 was detected in one indicator and one control station sample at a concentration of 34 and 13 pCi/kg-wet respectively. LLD sensitivities for the remaining samples ranged from <4.0 to <73 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS.

Beef (Table C-18)

Although not required by the SGS or HCGS Technical Specifi-cations, beef samples are collected, when available, from two farms twice a year as management audit samples and analyzed for gamma emitters. Only one beef sample from the second semi-annual sampling period was collected. Samples from the first semi-annual sampling period were not available. Farmers, from whose animals the samples are normally obtain'ed, did not slaughter.

• Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclide K-40. *All other gamma emitters searched for were below LLD.

o Potassium-40 was detected at a concentration of 2400 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet.

33

Game (Table C-18)

Although not required by the SGS or HCGS Technical Specif i-cations, 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. Samples from two locations were collected during the month of February to satisfy this requirement.

• Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclides K-40, Ra-226 and Th-232. All other gamma emitters searched for were below LLD.

o Potassium-40 was detected in the indicator station sample at a concentration of 1900 pCi/kg-wet and the control station sample at 1700 pCi/kg-wet. The average for both muskrat samples was 1800 pCi/kg-wet. The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4444 pCi/kg-wet.

o Radium-226 was detected in the indicator sample at a concentration of 23 pCi/Kg-wet and at a concentration of 24 pCi/Kg-wet for the control station sample. The average for both muskrat samples was 24 pCi/kg-wet. The maximum preoperational level detected was 1000 pCi/kg-wet.

o Thorium-232 was detected in one control sample at a concentration of 44 pCi/kg-wet with an error of 50% at the two sigma confidence level. The result at the indicator location was <31 pCi/kg-wet. The maximum preoperational level detected was 140 pCi/kg-wet.

Fodder Crops (Table C-19)

Although not required by the SGS or HCGS Technical Specif i-cations, eight samples of crops normally used as cattle feed were collected from five indicator stations (8 samples) and one control station (3 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. Four of the locations from which samples were collected are milk sampling stations.

Samples collected for wet gamma analysis included corn silage,green chop, feed corn, and soybeans.*

• Gamma spectrometric analysis performed on each of the eight samples indicated the presence of the naturally-occurring radionuclides Be-7, K-40, Ra-226, and Th-232. Cs-137 was also detected. All other gamma emitters searched for were below LLD.

34

• o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in three samples from three indicator stations at concentrations ranging from 520 to 1600 pCi/kg-wet and in two control station sample rnging from 360 to 1200 pCi/kg-wet. LLD sensitivities for the remaining six samples ranged from <100 to <200 pCi/kg-wet.

The maximum preoperational level detected was 4700 pCi/kg-wet, with an average of 2000 pCi/kg-wet.

o Potassium-40 was detected in all eleven samples.

Concentrations for the eight indicator station samples ranged from 2000 to 15000 pCi/kg-wet and for the three control station samples at 2700 to 15000 pCi/kg-wet. The average concen- tration detected for all samples was 7300 pCi/kg-wet. These levels are comparable to preoperational results, which also detected a maximum level of 16000 pCi/kg-wet.

o Cs-137 was detected in one indicator station at 19 pCi/kg-wet with an error of 42% at the two sigma confidence level. The LLD sensitivity for the remaing samples ranged from <14 to <70 pCi/kg-wet. No preoperational data is available for comparison. The presence of Cs-137 can be attributed to fallout from weapons testings or fallout from the Chernobyl accident *

• o Radium-226 was detected in one sample from one indicator station at a concentration of 42 pCi/kg-wet and in two control station samples at 39 to 54 pCi/kg-wet. These values are within the variations of the LLD sensitivities for the remaining eight samples which ranged from <25 to

<65 pCi/kg- wet. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS.

o Th-232 was detected in one sample from each of two indicator stations at concentration of 73 to 85 pCi/kg-wet. The LLD sensitivity for the remaing samples ranged from <38 to <100 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS.

Soil (Table C-20)

Soil is now sampled every three years at 10 stations, including one control, and analyzed for Sr-90 and gamma emitters. Samples are collected at each station in areas that have been relatively undisturbed since the last collection in order to determine any change in the radionuclide inventory of the area.

35

The concentrations of Sr-90 for the indicator stations ranged from 51 to 150 pCi/kg-dry with an average of 78 pCi/kg-dry. The control station yielded a results of 21 pCi/kg-dry. Since the purpose of these samples is to determine if the operation of the nuclear stations is resulting in an increase in the inventory of long lived reactor produced radionuclides in the environment, the values obtained were compared to data reported in previous years. Averages for the indicator stations were 220 pCi/kg in 1977, 149 pCi/kg in 1980, 125 pCi/kg in 1983, and 78 pCi/kg in 1986. Averages for the control stations were.430 pCi/kg in 1977, 195 pCi/kg, 93 pCi/kg in 1983 and 1986. The gradual decrease is perhaps attributable to the wash-out and decay of weapons testing fall-out from the 1950's to the 1960's.

• Gamma spectrometry of these samples showed detectable concentrations of the naturally occurring radionuclides (K-40, Ra-226, and Th-232) and the fission product Cs-137.

o Potassium-40 was detected in all ten samples.

Concentrations for the nine indicator station samples ranged from 3800 to 13000 pCi/kg-dry and for the one control station sample at 7700 pCi/kg-dry. The average concentration detected for all samples was 9300 pCi/kg-wet. These levels are comparable to preoperational results, which also detected a maximum level of 16000 pCi/kg-dry.

o Cesium-137 was detected in all ten samples. The Cs-137 at the indicator stations ranged from 110 to 1300 pCi/kg with an average of 450 pCi/kg. The control station was 290 pCi/kg. Averages for the indicator stations were 710 pCi/kg in 1977, 445 pCi/kg in 1980 and 440 pCi/kg in 1983 and 393 pCi/kg for 1986. Averages for the control stations were 620 pCi/kg in 1977, 650 pCi/kg in 1980, 615 pCi/kg in 1983, and 450 pCi/kg in 1986. The presence of Cs-137 can be attributed to fallout from weapons testing or fallout from the Chernobyl accident.

o Radium-226 was detected in all ten samples Concentrations for the nine indicator stations ranged from 300 to 1200 pCi/kg-dry and in the control station sample at 750 pCi/kg-dry. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS.

o Th-232 was detected in all ten samples. Concentrations for the nine indicator stations ranged from 290 to 1200 pCi/kg-dry. The control station sample yielded a result of 710 pCi/kg-dry. No preoperational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS.

36

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 were taken by net and frozen in sealed polyethylene containers before being transported in ice chests.

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

Surface Water (Tables C-21, C-22, C-23, C-24)

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 effluents from the Salem Station are discharged into the Delaware River), another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational control. All surface water samples were analyzed monthly for gross alpha, gross beta and gamma emitters. Quarterly composites were analyzed for tritium.

• Gross alpha activity was detected in nine samples from four indicator stations at concentrations ranging from 1.0 to 7.7 pCi/L and in three control station samples ranging from o*.8 to 2.8 pCi/L. These values are within the variations of the LLD sensitivities for the remaining 48 samples which ranged from

<0.7 to <4.2 pCi/L. The maximum preoperational level detected was 27 pCi/L *.

• Gross beta activity was detected in 59 of 60 samples.

Concentrations for the 48 indicator station samples ranged from 3.7 to 130 pCi/L and for the 12 control station samples from 11 to 85 pCi/L. The average concentration detected for all samples was 46 pCi/L. The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L.

• Tritium activity was detected in eight samples from four indicator station composites at concentrations ranging from 160 to 1600 pCi/L, with an average for the eight composites of 270 pCi/L. Concentrations were detected in one of the control station composites at 190 pCi/L. LLD sensitivities for the remaining composites ranged from <120 to <160 pCi/L. The maximum preoperational level detected was 600 pCi/L.

37

A review of Station Radioactive Effluent Release Reports indicates that all liquid discharges were below Technical Specification limits. Although surface water samples are not potable, the 1000 and 1600 pCi/L tritium values detected in one of the indicator station samples, were well below the reporting level of 20,000 pCi/L for drinking water samples

[11,12]. The detection of tritium can be attributed to sampling during a liquid effluent release.

• Gamma spectrometric analysis performed on each of the 48 indicator station and 12 control station surf ace water samples indicated the presence of Co-58, Co-60, and the naturally-occurring radionuclides Be-7, K-40, Ra-226 and Th-232. All other gamma emitters searched for were below LLD.

o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in one sample from four indicator stations at a concentration of 13 pCi/L and in no control station samples. LLD sensitivities for the remaining 59 samples ranged from <8.7 to <28 pCi/L.

o Potassium-40 was detected in 32 samples from the four indicator station samples at concentrations ranging from 29 to 150 pCi/L and in seven of the control station samples ranging from 52 to 99 pCi/L. LLD sensitivities measured throughout the year for the remaining samples ranged from

<26 to <42 pCi/L. The maximum preoperational level detected was 200 pCi/L, with an average of 48 pCi/L.

o Cobalt-58 was detected in one indicator station sample at a concentration of 2.6 pCi/L with an error of 39% at the two sigma confidence level. LLD sensitivities for all remaining samples measured throughout the year ranged from

<1.2 to <3.0 pCi/L. The presence of Co-58 in the sample can be attributed to sampling during a liquid effluent release. The concentration of Co-58 detected is near the LLD value of 1.6 pCi/L for this analysis.

o Cobalt-60 was detected in indicator station sample at a concentration of 2.7 pCi/L, with a 2 sigma detection error of 56%. The concentration of Co-60 detected is near the LLD value of 2.1 pCi/L. This value* is within the variations of the LLD sensitivities for all remaining samples measured throughout the year which ranged from <1.1 to <3.1 pCi/L.

o Radium-226 was detected in five samples from the four indicator stations at concentrations ranging from 4.1 to 14 pCi/L and in one control station samples at 4.9 pCi/L. LLD sensitivities for the remaining indicator and control station samples ranged from <2.9 to <5.6 pCi/L. The maximum preoperational level detected was 4.0 pCi/L

• 38

o Thorium-232 was detected in four samples from the four indicator stations at concentrations ranging from 4.8 to 63 pCi/L. These values are within the variations of the LLD sensitivities for all remaining samples measured throughout the year which ranged from <4.1 to <10 pCi/L. No preoper-ational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS.

Fish (Tables C-25)

Edible species of fish were collected semi-annually at three locations and analyzed for tritium (aqueous), gamma emitters (flesh), and for Sr-89 and Sr-90 (bones). Samples included bluefish, channel catfish, weakfish and white perch.

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator station and one control station samples as management audit analysis. No tritium activity was detected in any of the six samples analyzed; LLD sensitivity was <1000 pCi/kg-wet. The maximum required LLD sensitivity value is 2000 pCi/kg-wet.

• Gamma spectrometric analysis performed on each of the four indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclides K-40 and Ra-226. Cesium-137 was also detected in one sample. All other gamma emitters searched for were below LLD.

o Cesium-137 was detected at one indicator location at a concentration of 16 pCi/Kg-wet. The error associated with this result was 56%. The concentration of Cs-137 detected is near the LLD value of 15 pCi/Kg for this analysis.. The continued presence of Cs-137 can be attributed to weapon testing or fallout from the Chernobyl accident. The maximum preoperational level detected was 11 pCi/Kg-wet with an associated error of 54%.

o Potassium-40 was detected in all four samples from the two indicator stations at concentrations ranging from 2600 to 3300 pCi/kg-wet and in both of the control station samples at 2400 and 3500 pCi/kg-wet. The average for both the indicator and control station samples was 3000 pCi/kg-wet.

The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2914 pCi/kg-wet.

o Radium-226 was detected in three indicator station samples at an average concentration of 30 pCi/kg-wet and one control station at 19 pCi/kg-dry. The LLD sensitivities for the remaining samples, both indicator and control,

• ranged from <22 to <25 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS.

39

• Strontium-89 and strontium-90 analyses were performed on each of the four indicator station and two control station samples. These are management audit analyses analyzed in recognition of the high bioaccumulation factor of strontium in bone.

o Strontium-89 of the bone was not detected* in any of the six indicator and control station samples. LLD sensitivities for the six samples, indicator and control, ranged from <35 to <50 pCi/kg-dry. The maximum preoperational level detected was 100 pCi/kg-dry.

o Strontium-90 of the bone was detected in two of four indicator station samples and in both control station samples.

Concentrations in the four indicator samples ranged from 280 to 290 pCi/kg-dry, with an average of 280 pCi/kg-dry.

Concentrations in the two control samples were 45 and 330 pCi/kg-dry, with an average of 190 pCi/kg-dry. The average for all samples was 160 pCi/kg-dry. The maximum preoper-ational level detected was 940 pCi/kg-dry, with an average of 335 pCi/kg-dry. The presence of Sr-90 in the samples can be attributed to fallout from nuclear weapons testing.

Blue Crab (Table C-26)

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, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89 and Sr-90.

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator samples and two control samples as management audit analysis. Tritium activity was detected in none of the two control or 4 indicator samples. LLD sensitivities for the six samples, indicator and control, were <1000 pCi/kg-wet. The maximum required LLD sensitivity value is 2000 pCi/kg-wet.

• 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 LLD.

o Potassium-40 was detected in both indicator station samples at concentrations of 2200 and 2700 pCi/kg-wet and in both of the control station samples at 1800 and 2100 pCi/kg-wet. The average for both the indicator and control station samples was 2200 pCi/kg-wet. The maximum preoperational level detected was 12000 pCi/kg-wet, with an

• average of 2835 pCi/kg-wet.

40

• 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 reconcen-tration factor of strontium in crab shells.

o Strontium-89 of the flesh was not detected in any of the four samples; LLD sensitivities ranged from <35 to <100 pCi/kg-wet. The maximum preoperational level detected was

<51 pCi/kg-wet.

Strontium-89 of the shell was detected in one indicator station sample at 58 pCi/kg-dry and in one control sample at 82 pCi/kg-dry. The LLD sensitivity for the remaining indicator sample was <57 pCi/kg-dry. The maximum required LLD sensitivity value is 500 pCi/kg-dry. The maximum preoperational level detected was 210 pCi/kg- dry.

o Strontium-90 of the flesh was not detected in any of the four samples; LLD sensitivities ranged from <17 to <41 pCi/kg-wet. The maximum preoperational level detected was

<150 pCi/kg-wet.

Strontium-90 of the shell was detected in both indicator station samples at 310 and 200 pCi/kg-dry and in both control station samples at 540 and 510 pCi/kg-dry. The average for both indicator and control station samples was 390 pCi/kg-dry. The maximum preoperational level detected was 990 pCi/kg-dry, with an average of 614 pCi/kg-dry. The presence of Sr-90 can be attributed to fallout from weapons testing or fallout from the Chernobyl accident.

Sediment (Table C-27)

Sediment samples were collected semi-annually from six locations, five indicator stations and one control station. Each of the twelve samples was analyzed 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 well within the acceptable levels specified in section 3/14.12.1 of the Technical Specifications.

• Strontium-90 was not detected in any of the twelve indicator and control station samples. LLD sensitivities for the other eleven samples, indicator and control, ranged from <18 to <28 pCi/kg-dry. The maximum preoperational level detected was 320 pCi/kg-dry.

41

• 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 Be-7, K-40, Ra-226 and Th-232, low levels of Mn-54, Co-58, Co-60, and Cs-137 were also detected. All other gamma emitters searched for were <LLD.

o Cobalt-60 was detected in seven samples from five indicator stations at concentrations ranging from 32 to 64 pCi/kg-dry, and at one control station at 41 pCi/kg-dry. Analysis uncertainties averaged 50% at the two sigma confidence level. The concentrations of Co-60 detected are near the LLD value. LLD sensitivities for the other four samples, indicator and control, ranged from <40 to <52 pCi/kg-dry.

Trace levels of Co-60 were discharged from both SGS and HCGS during the year.

o Manganese-54 was detected in two samples from two indicator stations at concentrations ranging from 20 and 25 pCi/kg-dry, with a 2 sigma detection error of 49% and 55%.

Respectively these values are within the variations of the LLD sensitivities for the other nine samples, indicator and control, which ranged from <19 to <27 pCi/kg-dry.

o Cobalt 58 was detected in four indicator station samples at concentrations ranging from 35 to 50 pCi/kg-dry with 2 sigma detection errors ranging from 26% to 41%. The LLD sensitivities for the other eight samples, indicator and control, ranged from <23 to <35 pCi/kg-dry.

o Cesium-137 was detected in eight indicator stations samples at a concentrationa ranging from 14 to 65 pCi/kg-dry with 2 sigma detection errors ranging from 17% to 57%. The LLD sensitivities for the other four samples, indicator and control, ranged from <18 to <27 pCi/kg-dry. The maximum preoperational level detected was 400 pCi/kg-dry.

o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in two indicator station sample at a concentration of 200 and 440 pCi/kg-dry. The LLD sensitivities for the other ten samples, indicator and control, ranged from <120 to <320 pCi/kg-dry. The maximum preoperational level detected was 2300 pCi/kg-dry.

o Potassium-40 was detected in all indicator station samples at concentrations ranging from 3700 to 16000 pCi/kg-dry, with an average of 11000 pCi/kg-dry. Concentrations detected in both of the control station samples were at 13000 and 14000 pCi/kg-dry. The average for both the indicator and control station samples was 10000 pCi/kg-dry. The maximum preoperational ~evel detected was 21000 pCi/kg-dry, with an average of 15000 pCi/kg-dry

• 42

• o Radiurn-226 was detected in all indicator station samples at concentrations ranging from 270 to 800 pCi/kg-dry, with an average of 550 pCi/kg-dry. Concentrations detected in both of the control station samples were at 580 and 630 pCi/kg-dry, with an average of 600 pCi/kg-dry. The average for both the indicator and control station samples was 560 pCi/kg-dry. The maximum preoperational level detected was 1200 pCi/kg-dry, with an average of 760 pCi/kg-dry.

o Thoriurn-232 was detected in all indicator station samples at concentrations ranging from 310 to 860 pCi/kg-dry, with an average of 610 pCi/kg-dry. Concentrations detected in both of the control station samples were at 590 and 700 pCi/kg-dry, with an average of 640 pCi/kg-dry. The average for both the indicator and control station samples was 620 pCi/kg-dry. The maximum preoperational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry *

• 43

PROGRAM DEVIATIONS Air particulate and iodine sampler location 5Sl for week beginning May 1, was operational for only 1.4 days out of a 7 day sampling period due to a power interruption.

Air particulate and iodine sampler location !Fl for the week beginning June 19 was operational for only 4.5 days out a 7 day sampling period due to a power interruption.

Air particulate and iodine sampler location lFl for the week beginning June 26, was operational for only 3.9 days out of a 7 day sampling period due to a power interruption and instrument malfunction.

Although it is unlikely that ground water would be affected by discharges from the stations, local wells are sampled. Well water samples from location 5Dl were available only through the first quarter of 1989. Effective April 1, sampling from this location was discontinued. Sampling was terminated due to the unpredictable availability of samples from this location.

Precipitation (not required by the Technical Specifications) results from location 2F2 for the month of February did not meet the sensitivity requirements for BaLa-140. The sensitivity was not met due to insufficient sample size.

Although not required by Technical Specifications, beef samples are normally collected twice each year. The first semi annual beef sample was not obtained since the local farmer did not slaughter from January throught June 1989. However a beef sample was obtained from location 3El in December 1989 for the second semi annual collection period.

44

CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial Island was conducted during 1989 in accordance with the SGS and HCGS Technical Specifications. The objectives of the program were 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. These results were comparable to the results obtained during the preoperational phase of the program. Ambient radiation levels, as determined by TLDs collected monthly were relatively low, averaging 6.2 mrad/std. month. No unusual radiological characteristics were observed in the environs of Artificial Island. The operation of SGS Units One and Two and HCGS had no significant impact on the radiological characteristics of the environs of Artificial Island.

45

TABLE 2 1989 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S'.1:~'.l:IOH CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT

a. Air Particulate 5Sl 501 16El lFl 3H3 Weekly Gross alpha/weekly 2F2 Gross beta/weekly Sr-89 & Sr-90/f irst quarter**

Gamma scan/quarterly

b. Air Iodine 5Sl 5Dl 16El lFl 3H3 Weekly Iodine-131/weekly ti=-

2F2

°'

c. Precipitation 2F2 Monthly Gross alpha/monthly Gross beta/monthly Tritium/monthly Gamma scan/monthly II. DIRECT RADIATION

a. Thermoluminescent 2S2 5Dl 2El lFl 3Gl 3Hl Monthly & Gamma dose/monthly Dosimeters 5Sl lODl 3El 2F2 3H3 Quarterly Gamma dose/quarterly 6S2 14Dl 13El 2F6 7Sl 16El 5Fl lOSl 6Fl llSl 7F2 llFl 13F4

TABLE 2 {cont'd) 1989 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S'.I:A'.I:IOH CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

a. Thermoluminescent 402 9El 2F5 1G3 Quarterly Gamma dose/quarterly Dosimeters {cont'd) 11E2 3F2 lOGl 12El 3F3 16Gl 10F2 12Fl 13F2 13F3 14F2 15F3 16F2

-...J III. TERRESTRIAL ENVIRONMENT

a. Milk 2F7 3Gl Monthly Iodine-131/monthly

{when animals Gamma scan/monthly 11F3 are not on pasture) 14Fl Semi-monthly Iodine-131/semi-monthly

{when animals Gamma scan/semi-monthly are on Sr-89 & Sr-90/July, first pasture) collection**

b. Well Water 2S3 501 3El Monthly Gross alpha/monthly Gross beta/monthly Potassium-40/monthly Tritium/monthly Gamma scan/monthly sr-89 & Sr-90/quarterly

TABLE 2 (cont'd) 1989 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S:I:!!I!ICH CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

c. Potable Water 2F3 Monthly Gross alpha/monthly (Raw & Treated) (composited Gross beta/monthly daily) Potassium-40/monthly Tritium/monthly Gamma scan/monthly Sr-89 & Sr-90/quarterly

d. Vegetables 2F4 lGl 3H5 Annually Gamma scan/on collection

~

3E2 4F2 2Gl (at harvest)

OJ 11E3 5Fl 14F3

e. Beef 3El Semi- Gamma scan/on collection annually

f. Game 3El llDl Semi- Gamma scan/on collection (Muskrat) annually

g. Fodder Crops 4D2 3El 2F7 3Gl Annually Gamma scan/on collection 11F3 14Fl

h. Soil 681 lODl 16El lFl 3Gl Collect Sr-90/on collection 2F4 from each Gamma scan/on collection 2F7 location 5Fl once every 11F3 three years 14Fl

TABLE 2 (cont'd) 1989 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S:I:~:I:ICH CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS IV. AQUATIC ENVIRONMENT

a. Surface Water llAl 7El 1F2 12Cl Monthly Gross alpha/monthly 16Fl Gross beta/monthly Gamma scan/monthly Tritium/quarterly

b. Edible Fish llAl 7El 12Cl Semi- Tritium (flesh) ts:-. annually Aqueous fraction/on collection

\0 Sr-89 & Sr-90 (bones)/on collection Sr-89 & Sr-90 (flesh) (on 2nd collection)

Gamma scan (flesh)/on collection

c. Blue Crabs llAl 12Cl Semi- Tritium (flesh) annually Aqueous fraction/on collection Sr-89 & Sr-90 (flesh)/on collection Sr-89 & Sr-90 (shell)/on collection Gamma scan (flesh)/on collection

d. Sediment llAl 7El 16Fl 12Cl Semi- sr-90/on collection 15Al annually Gamma scan/on collection 16Al

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

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

FIGURE 6 BETA ACTIVITY IN PRECIPITATION AND AIR PARTICULATES 1973 THROUGH 1989 1000 LEGEND 500-I AIR (fCi\m3) ft PRECIPITATION

~ ~ ~

pCi/L r'

r'I 100--I I \ n I\ t I I

Ir 'I 50--; I

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• FIGURE 6A BETA ACTIVITY IN PRECIPITATION AND AIR PARTICULATES 1986 THROUGH 1989 1000-LEGEND 500- AIR (f Ci/m J 3

PRECIPITATION (pCi/L) 100 ....................................................................................................................................................................... .

50 01

~ I 10 ............ .1.'** ~

\, ******** , ..................................., ..................................

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1986 1987 1988 1989 1990

FIGURE 7 AMBIENT RADIATION OFFSITE VS CONTROL STATION TLD 1973 THROUGH 1989 10 LEGEND 9 OFF-SITE STATIONS CONTROL STATIONS 8

7 -****************************************** .. *****************************************************************.. ******* .. *************************************** .. *********

.i=.

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FIGURE 7A AMBIENT RADIATION OFFSITE VS CONTROL STATION TLD 1986 THROUGH 1989 10 LEGEND 9 CONTROL STATIONS OFF-SITE STATIONS 8

..c:

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FIGURE 8 IODINE-131 ACTIVITY IN MILK 1973 THROUGH 1989

~ """llJcu ~,>-t; """llJ

.., !'c:::.!

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2 Q -'-'........,,_..~~,.._~~~i==;,_.,~,4-l""F"'....-i-P"P"'F;:::;.oi,........,...;-p=P"i""Ff""FP.......'i""'?';=;=:::-r-r..-r-r--..--.--r-r--.-.....~..-.-r-I 1973 1975 1977 1979 1981 1983 1985 1987 1989

FIGURE BA IODINE-131 ACTIVITY IN MILK 1986 THROUGH 1989 c:::

11:1 Cr)

.t..:I"'-"

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FIGURE 9 GROSS BETA & K-40 ACTIVITY IN SURFACE WATER 1973 THROUGH 1989 1000-r--~~~~~~~~~~~~~~~~----~~-,.-------------- ....

LEGEND 500- GROSS BETA K-40 100 U1 _J I ,~

....~ r-, I I

I i A\ . (\ JA A ,,

m --...... 50

• rl t..J c.

1 Q - - - 1 1 1 1 1 1 1 1 1 I l l D t l l l l 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1 I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 f l l t t l t 1 1 1 1 1 1 1 1 1 1 1 l l l t l I I l l I l t l t l l l I 1111111111111111111111111

°"'.J c::: .µ It> Cl) II) >- I . >-

QJ "'"'I II) >o II) II)

.µ II)

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FIGURE 9A GROSS BETA & K-40 ACTIVITY IN SURFACE WATER 1986 THROUGH 1989 LEGEND 500- K-40 GROSS BETA 100 01

_J

• r-f tJ c.

10 ..................................................................................................................................................................... .

~....,

r-t QJ ....

>- QJ ....

.Q t. ca 0

c t.

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0 t.

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• FIGURE lOA TRITIUM ACTIVITY IN SURFACE WATER 1986 THROUGH 1989 10000 5000

_J c.J c.

1000 01

\.0 500 100 1986 1987 1988 1989 1990

[l]

REFERENCES 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 Research Corporation, Research and Testing Laboratory.

"Artificial Island Radiological Environmental Monitoring Program -

Annual Reports 1983 through 1988".

[5] Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units l and 2". 1971.

[6] Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Hope Creek Generating Station". 1983.

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

• Salem Nuclear Generating Station, Units l 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 Service Electric and Gas Company. "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units l and 2". 1982.

[10] Public Service Electric and Gas Company. "Final Safety Analysis Report -

Hope Creek Generating Station. 1984.

[11] Public service Electric and Gas Company. "Salem Nuclear Generating Station Unit l - Technical Specifications", Appendix A to Operating License No. DPR-70, 1976, sections 3/4.12 and 6.9.1.10 (Amendment 59

.e..t ~).

[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

.e..t ~).

60

• [13]

REFERENCES (cont'd)

Public Service Electric and Gas Company. "Hope Creek Generating Station Unit l - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10.

[14] Public Service Electric and Gas Company. "Offsite Dose calculation Manual" - Salem Generating Station.

[15] Public Service Electric and Gas Company. "Offsite Dose calculation Manual" - Hope Creek Generating Station.

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

[17] PSE&G Research and Testing Laboratory. "Environmental Division Quality Assurance Plan." November, 1986.

[18] PSE&G Research and Testing Laboratory. "Chemical/ Environmental Division Procedures Manual." February, 1981.

[19] Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, SGS RERR-26 and RERR Salem Generating Station. 1989 *

• [20]

[21]

Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, HCGS RERR-7 and RERR Hope Creek Generating Station. 1989.

Anthony v. Nero Jr., "A Guidebook to Nuclear Reactors", University of california Press, 1979.

[22] Eric J. Hall, "Radiation & Life", Pergamon Press, 1976.

[23] NCRP Report No. 93, "Ionizing Radiation Exposure of the Population of the United States", 1987.

61

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-27 2/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF 6LL IliDICAICe ICCAIICliS LCCAIICli ~IIH HIGHESI MEAli CCliieQI IQCAIIQli NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS I AIRBORNE Air Particulates Alpha 312 0.9 2.2 (195/260) 2F2 8.7 mi NNE 2.3 (49/52) 2.1 (49/52) 0 (10- 3 pCitm3 ) (0.9-5.8) (0.9-5.8) (0.9-4.1) 0 16E1 4.1 mi NNW 2.3 (48/52)

CTI (1.0-4.8)

U1 Beta 312 25 (259/260) 5S1 1.0 mi E 26 (51/52) 25 ( 52/52) 0 (7-55) (8-52) (9-60) 2F2 8.7 mi NNE 26 (52/52)

(10-55)

Sr-89 6 0.2 <LLD <LLD <LLD 0 Sr-90 6 0.1 <LLD <LLD <LLD 0 Ganma Be-7 24 30 64 ( 17 /20) 5S1 1.0 mi E 65 (4/4)

(55-73) (59-68) 64 (4/4) 0 2F2 8.7 mi NNE 65 (4/4) (60-68)

(59-73)

K-40 24 8.0 <LLD <LLD 8.6 (1/4) 0 (8 .6)

Cs-134 24 0.6. <LLD <LLD <LLD 0 Ra-226 24 0.5 <LLD <LLD _0.5 (1/4) 0 (0.5)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al L IHDICaIDR IDCAIIDUS IDCAIIDH WIIH HIGHESI MEAH CDHIRDL LDCAIIDH NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS I AIRBORNE (Cont'd)

Air Iodine 1-131 312 30 <LLD <LLD <LLD 0 (10- 3 pCitm3 )

Precipitation Alpha 12 1. 5 2.0 (3/12) 2F2 8.7 mi NNE 2.0 (3/12) No Control 0 CTI CTI (pC i IL) (0.9-3.6) (0.9-3.6) Location Beta 12 2.0*** 5.6 (9/12) 2F2 8.7 mi NNE 5.6 (9/12) No Control 0 (3.0-8.5) (3.0-8.5) Location H-3 12 150 <.LLD 2F2 8.7 mi NNE <LLD No Control 0 Location Gamma Be-7 12 15 51 (10/12) 2F2 8.7 mi NNE 51 (10/12) No Control 0 (26-81) (26-81) Location Ra-226 12 5.1 16 (2/12) 2F2 8.7 mi NNE 16 (2112) No Control 0 (9.1-23) (9.1-23) Location K-40 12 35 140 (3/12) 2F2 8.7 mi NNE 140 (3/12) No Control 0 (46-295) (46-295) Location

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I I~DICAIOe LOCAIIOUS IOCAIIOU ~IIli liIGliESI MEAU caurea1 LDCAIID~ NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS II DIRECT Direct Radiation Garrma 288 6.1 (252/252) llSl 0.09 mi SW 7 .8 (12/12) 6.5 (36/36) 0 (mrad/std. month) Dose (monthly) (4.2-9.5) (5.9-9.5) (5.3-8.0)

O"I Garrma 164 5.1 (140/140) llSl 0.09 mi SW 6.6 (4/4) 5.7 (24/24) 0

-...J Dose (qtrly.) (3.5-7.2) (5.2-7.2) (4.8-6.6)

II I TERRESTRIAL Soil Sr-90 10 24 85 (8/9) 5Fl 6.5 mi E 150 (1/1) 21 (1/1) 0 (pCi/kg-dry) (51-150) (150) (21)

K-40 10 9300 (9/9) 16El 6.1 mi NNW 13000 ( 1/1) 7700 ( 1/1) 0 (3800-13000) (13000) ( 7700) 14Fl 5.5 mi WNW 13000 (1/1)

( 13000)

Cs-134 10 20 <LLD <LLD <LLD 0 Cs-137 ' 10 450 (9/9) lFl 5.8 mi N 1300 190 (1/ 1) 0 (110-1300) (1300) ( 190)

Ra-226 10 870 (9/9) 16El 6 mi NNW 1200 (1/1) 750 (1/1) 0 (300-1200) (1200) (750)

Th-232 10 840 (9/9) 16El 6 mi NNW 1200 (1/1) 710 (1/1) 0 (290-1200) ( 1200) (710)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-:154 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALI IHDICAICR ICCAIICHS ICCAIICH ~IIH UIGHESI MEAH CCHIRCL ICCAIICH NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS III TERRESTRIAL (Cont'd)

Milk I-131 80 0.3 <LLD <LLD <LLD 0 (pCi/L)

Sr-89 4 1.1 1.2 (1/3) 14F1 5.5 mi WNW 1.2 (1/3) <LLD 0 O"I CX> Sr-90 4 0.9 2.0 (1/3) 3G1 17 mi NE 2.2 (1/1) 2.2 (111) 0

( 1.8-2 .2) (2.2) (2.2)

Gamma K-40 80 120 1300 (60/60) 11F3 5.3 mi SW 1400 (20/20) 1300 (20/20) 0 (1200-1500) (1300-1500) (1200-1400)

Cs-134 80 4.0 <LLD <LLD <LLD 0 Cs-137 80 2.3 4.0 (1/60) 11F3 5.3 mi SW 4.0 (1/20) <LLD 0 (3.4-4.0) (4.0)

Ra-226 80 5.1 10 (3/60) 2F7 5.7 mi NNE 10 (1/20) 6. 7 ( 1/20) 0 (9.9-10) ( 10) (6. 7)

Th-232 80 7.7 16 (2/60) 14F1 5.5 mi WNW 16 (2160) 14 (1/20) 0 (15-16) (15-16) (14)

• ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF AIL IUDICAIDH ICCAIICUS ICCAIIDU ~II~ ~I6~ESI MEAU CD~IeCI IDCAIID~ NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS III TERRESTRIAL (Cont'd)

Well Water Alpha 27 1.2 0.9 (3/15) 2S3 700 ft NNE 0.9 (3/12) 0.9 (3/12) 0 (pCi/L) (0.5-1.6) (0.5-1.6) (0.3-1.3)

Beta 27 1.0*** 6.8 (15/15) 5Dl 3.5 mi E . 11 (3/3) 9.7 (12/12) 0 O'I (3.6-14) (10-14) (4.7-14)

\.0 K-40 27 6.4 (15/15) 5Dl 3 .5 mi E 12 (3/3) 9.4 (12/12) 0 (3.2-16) (6.2-16) (8.5-11)

H-3 27 150 180 (2/15) 3El4.lmiNE 250 (8/12) 250 ( 1112) 0 (170-190) (250) (250)

Sr-89 9 1.0 <LLD <LLD <LLD 0 Sr-90 9 0.6 <LLD <LLD <LLD 0 Gamma K-40 27 24 21 (2/15) 2S3 700 ft NNE 21 (2/15) 26 (2/12) 0 (9-33) ( 9-33) ( 26-27)

I-131 24 0.8 <LLD <LLD <LLD 0 Cs-134 27 3.0 <LLD <LLD <LLD 0 Ra-226 27 3.9 34 (8/15) 5Dl 3.5 mi E 102 (2/3) 60 (10/12) 0 (4.6-160) (48-160) (11-130)

Th-232 27 3.8 7.8 (2/15) 2S3 700 ft NNE 7 ,8 (2/12) <LLD 0 (6.5-9.1) (6.5-9.1)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I IHDICAIDB IDCAIIDHS LDCAIIDH ~IIH HIGHESI MEAH CDHIRDI IDCAIIDH NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS III TERRESTRIAL (Cont'd)

Potable Water Alpha 24 0.9 1. 7 (5/24) 2F3 8.0 mi NNE 1. 7 (5/24) No Control 0 Raw-Treated (0.7-3.6) (0.7-3.6) Location (pC i IL)

-..J Beta 24 1.0*** 3.5 (24/24) 2F3 8.0 mi NNE 3.5 (24/24) No Control 0 0 (2.7-4.6) (2.7-4.6) Location K-40 24 2.4 (24/24) 2F3 8.0 mi NNE 2.4 (24/24) No Control 0 (1.6-3.3) (1.6-3.3) Location H-3 24 150 150 (5/24) 2F3 8.0 mi NNE 150 (5/24) No Control 0 (130-180) (130-180) Location Sr-89 8 1.0 <LLD <LLD No Control 0 Location Sr-90 8 0.8 0.6 (1/8) 2F3 8.0 mi NNE 0.6 (118) No Control 0 (0.6) (0.6) Location

• ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL I~DICAICR ICCAIIC~S NUMBER OF SAMPLED OF ANALYSES DETECTION ICCAIIC~ ~IIH HIGHESI MEA~ CC~IRCI ICCAIIC~

MEAN** NAME NON ROUTINE (UNIT OF MEASUREMENT) PERFORMED (LLD)* MEAN MEAN REPORTED (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS III TERRESTRIAL (Cont'd)

Potable Water Ganma Raw-Treated K-40 24 20 36 ( 4/24)

(pCi/L) 2F3 8.0 mi NNE 36 (4/24) No Control (20-52) 0

-..J I-131 24 <0.8 (20-52) Location

....... <LLD 2F3 8.0 mi NNE <LLD No Control 0 Cs-134 24 3.0 <LLD Location Ra-226 24 3.4 <LLD <LLD 0 4.1 (3/24) 2F3 8.0 mi NNE 4.1 ( 3/24)

(2.8-4. 7) No Control 0 Fruits & Ganma (2. 8-4. 7) Location Vegetables K-40 18 1900 (11/11)

(pCi/kg-wet) 2F4 6.3 mi NNE 2000 (4/4) 2100 (6/6)

(1500-2600) 0 Cs-134 18 19 (1500-2600) (1800-2500)

<LLD Ra-226 18 1.9 <LLD <LLD 0

<LLD 2Gl 12 mi NNE 38 (1/1) 24 (3/7) 0 Th-232 20 4.4 (38) (9-38) 34 (1/12) 2F4 6.3 mi NNE 34 (114) 13(117) 0 (34) (34) ( 13)

Beef Ganma (pCi/kg-wet) K-40 1 2400 (1/1) 3E14.lmiNE 2400 (1/1) No Control (2400) 0 (2400) Location Game Ganma (pCi/kg-wet) K-40 2 1900 (111) 3El 4.1 mi NE 1900 (1/1) 1700 (1/1)

(1900) 0 Ra-226 2 15 (1900) ( 1700) 23 (1) 3El 4.1 mi NE 23 (1/1)

(23) 24 (1/1) 0 (23) (24)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-27 2/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL I~DICAICR ICCAIIC~S

• NUMBER OF SAMPLED ICCAIIC~ ~IIH HIGHESI MEA~ CC~IRCI ICCAIIC~

OF ANALYSES DETECTION MEAN** NAME NONROUTINE (UNIT OF MEASUREMENT) PERFORMED MEAN MEAN REPORTED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS III TERRESTRIAL (Cont'd)

Beef Ganma (pCi/kg-wet) K-40 1 2400 (1/1) 3El 4.1 mi NE 2400 (1/1) No Control (2400) 0

-....J (2400) Location I'\)

Game Gamma (pCi/kg-wet) K-40 2 1900 (1/1) 3E1 4.1 mi NE 1900 (1/1) 1700 (1/1)

( 1900) 0 (1900) ( 1700)

Ra-226 2 15 23 ( 1) 3E14.1miNE 23 (1/1) 24 (1/1) 0 (23) (23)

Fodder Crops Gamma ( 24)

(pCi/kg-wet) Be-7 11 170 1000 ( 3/8) 11F3 5. 3 mi SW 1600 (1/1) 800 (213)

(520-1600) 0 (1600) (360/1200)

K-40 11 7200 (8/8) 11F3 5. 3 mi SW 6900 (3/3) 7400 (3/3) 0 (2000-15000) (2500-15000) (2700-15000)

Cs-134 11 19 <LLD <LLD <LLD 0 Ra-226 11 42 42 (1/8) 3E1 4.1 mi NE 42 (1/8) 46 (2/3) 0 (42) (42) ( 39-54)

Th-232 11 70 79 (218) 2F7 5.7 mi NNE 85 (1/2) <LLD 0 (73-85) (85)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I IUCICAIQR IQCAIIQUS NUMBER OF SAMPLED OF ANALYSES DETECTION IQCAIIQU ~IIH HIGHESI MEAU CQUIRQI IQCAIIQU NON ROUTINE MEAN** NAME MEAN (UNIT OF MEASUREMENT) PERFORMED (LLD)* MEAN REPORTED (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC Surface Water Alpha 60 1.2 (pCi/L) 2.5 (11/48) llAl 0.2 mi SW 3.9 (3/12) 1.4 (3/12) 0 (1-7.7) ( 1. 9-7. 7) (0.8-2.8)

.....i Beta 60 3.8*** 47 (47/48) w 7El 4.5 mi SE 76 (12/12) 46 (12/12)

(3.7-133) 0 (24-133) (11-85)

H-3 20 150 440 (8/16) llAl 0.2 mi SW 900 (3/4) 190 (114)

(160-1600) 0 (170-1600) (190)

Gamma K-40 60 24 74 (32/48) 7El 4.5 mi SE 87 (10/12) 70 (7/12)

(29-150) 0 (45-140) (52-99)

Cs-134 60 3.0 <LLD <LLD <LLD 0 Co-60 60 1.1 2. 7 ( 1/48) 16Fl 6.9 mi NNW 2.7 (1/12) <LLD (2. 7) 0

( 2. 7)

Ra-226 60 3.0 6.4 (5/48) 16Fl 6.9 mi NNW 10 (2112) 4.9 (1112)

(4.0-14) 0 (5.5-14) (4.9)

Th-232 60 4.7 5.6 (4/48) 1F2 7.1 mi N 6.3 (1112) <LLD (4.8-6.3) 0 (6.3)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF 611 IUDICAIOR IOCAIIOUS IOCAIIOU WIIH HIGHESI MEAU COUIROL LDCAIIDU NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC (Cont'd)

Blue Crabs Sr-89 4 60 58 (1/2) 12Cl 2.5 mi WSW 82 (112) 82 (1/2) 0 (pCi/kg-dry) (shells) (58) (82) (82)

Sr-90 4 260 (2/2) 12Cl 2.5 mi WSW 530 (2/2) 530 (2/2) 0

.....i (shells) (200-310) (510-540) (510-540)

(pCi/kg-wet) H-3 4 1000 <LLD <LLD 0 (aqueous)

Sr-89 4 100 <LLD <LLD 0 (flesh)

Sr-90 4 40 <LLD <LLD 0 (flesh)

Gamma K-40 4 2400 (212) llAl 0.2 mi SW 2400 (212) 1900 (2/2) 0 (2200-2700) (2200-2700) (1800-2100)

• ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-27 2/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I I~CICAICB ICCAIIC~S ICCAIIC~ ~IIH HIGHESI MEA~ CC~IBCI LCCAIIC~ NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC (Cont'd)

Edible Fish Sr-89 6 40 <LLD <LLD 0

( pC i /kg-dry) (bones)

-..J Sr-90 6 25 280 (214) 7El 4.5 mi SE 290 (1/2) 190 ( 2/2) 0 U1 (bones) (280-290) ( 290) (45-330)

(aqueous) H-3 6 1000 <LLD <LLD 0 (pCi/kg-wet)

Gamma K-40 6 3000 (4/4) 7El 4.5 mi SE 3200 (2/2) 3000 (2/2) 0 (2600-3300) (3100-3300) (2400-3500)

Cs-134 6 10 <LLD <LLD <LLD 0 Cs-137 6 14 16 (1/4) 7El 4.5 mi SE 16 (1/2) <LLD 0 (16) ( 16)

Ra-226 6 22 30 (3/4) llAl 0.2 mi SW 43 (1/2) 19 (1/2) 0 (23-43) (43) (19)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-2721-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1989 to DECEMBER 31, 1989 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL IHDICAIDB IDCAIIDHS IDCAIIDH WIIU UI6UESI MEAH CDHIBDI LllCAIIDli NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC (Cont'd)

Sediment Sr-90 12 20 <LLD <LLD 0 (pCi/kg-dry)

Gamna

-..J C'I Be-7 12 120 320 (2110) 16Fl 6.9 mi NNW 440 (1/2) <LLD 0 (200-440) (440)

K-40 12 9200 (10/10) 16Fl 6.9 mi NNW 14000 (212) 14000 (212) 0 (3700-16000) (13000-16000) (13000-14000)

Mn-54 12 18 22 (2110) 16Fl 6.9 mi NNW 25 ( 1/2) <LLD 0 (20-25) ( 25)

Co-58 12 25 42 (4/10) llAl 0 .2 mi SW 50 (1/2) <LLD 0 (35-50) (50)

Co-60 12 40 43 (7/10) 7E1 4.5 mi SE 58. (212) 41 (1/2) 0 (31-64) (53-64) (41)

Cs-134 12 20 <LLD <LLD <LLD 0 Cs-137 12 17 33 (8/10) 7E1 4.5 mi SE 47 (212) <LLD 0 (14-65) (43-51)

Ra-226 12 550 (10/10) 7El 4.5 mi SE 730 (212) 600 (212) 0 (270-800) (270-800) (580-630)

Th-232 12 610 (10/10) 16F1 6.9 mi NNW 760 (212) 640 (212) 0

( 310-860) (740-790) (590-700)

• LLD listed is the lower limit of detection which was generally achieved during this reporting period.

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

• • • Typical LLD value .

IAPPENDIX BI SAMPLE DESIGNATION The PSE&G Research And Testing Laboratory 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 = Surface Water FPV = Vegetables (Various) VGT = Fodder Crops (Various)

GAM = Game (Muskrat) WWA = Well Water The last four symbols are a location code based on direction and distance from 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 clock-wise 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-5Dl would indicate a sample in the SGS program (SA), consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial distance D). The number 1 indicates that this is sampling station #1 in that particular sector.

79

SAMPLING LOCATIONS All 1989 sampling locations and specific information about the individual locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations with respect to the site.

TABLE B-1 STATION CODE STATION LOCATION SAMPLE TYPES 2S2 o.4 mi. NNE of vent IDM 2S3 700 ft. NNE of vent; fresh water holding tank WWA 5Sl 1.0 mi. E of vent; site access road AIO,APT;IDM 6S2 0.2 mi. ESE of vent; observation building IDM,SOL 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM llSl 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area ECH,ESF,ESS,SWA 15Al o.3 mi. NW of vent; cooling tower blowdown ESS discharge line outfall 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 12Cl 2.5 mi. WSW of vent; west bank of Delaware River ECH,ESF,ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM,VGT 5Dl 3.5 mi. E of vent; local farm AIO,APT,IDM,WWA lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur IDM,SOL llDl 3.5 mi. SW of vent GAM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm IDM 3El 4.1 mi. NE of vent; local farm FPB,GAM,IDM,VGT WWA 3E2 5.7 mi. NE of vent; local farm FPV 80

• STATION CODE TABLE B-1 (cont'd}

STATION LOCATION SAMPLE TYPES 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek ESF,ESS,SWA 9El 4.2 mi. s of vent IDM 11E2 5.0 mi. SW of vent IDM 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM 16El 4.1 mi. NNW of vent; Port Penn AIO,APT,IDM,SOL lFl 5.8 mi. N of vent; Fort Elfsborg AIO,APT,IDM,SOL 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA 2F2 8.7 mi. NNE of vent; Salem Substation AIO,APT,IDM,RWA 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm FPV,FPL,SOL 2F5 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southern Training Center IDM 2F7 5.7 mi. NNE of vent; local farm MLK,VGT,SOL 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal IDM Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 4F2 5.1 MI. ENE of vent, local farm FPL 5Fl 6.5 mi. E of vent FPV,IDM,SOL 5F2 7.0 mi. E of vent; local farm MLK 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 81

TABLE B-1 (cont'd)

STATION CODE STATION LOCATION SAMPLE TYPES 10F2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW Of vent; Taylor's Bridge Delaware IDM llF3 5.3 mi. SW Of vent; Townsend, Delaware MLK,VGT,SOL 12Fl 9.4 mi. WSW Of vent; Townsend Elementary School IDM 13F2 6.5 mi. w Of vent; Odessa, Delaware IDM 13F3 9.3 mi. W of vent; Redding Middle School, IDM Middletown, Delaware 13F4 9.8 mi. w of vent; Middletown, Delaware IDM 14Fl 5.5 mi. WNW of vent; local farm MLK,VGT,SOL 14F2 6.6 mi. WNW Of vent; Boyds Corner. IDM 14F3 5.4 mi. WNW Of vent; local farm FPV 15F3 5.4 mi. NW of vent IDM 16Fl 6.9 mi. NNW of vent; C&D canal ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM lGl 10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of vent; Wilmington, Delaware IDM 2Gl 12 mi. NNE of vent; Mannington Township, NJ FPV 3Gl 17 mi. NE of vent; local farm IDM,MLK,VGT,SOL lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 3Hl 32 mi. NE of vent; National Park, New Jersey IDM 3H3 110 mi. NE of vent; Research and Testing AIO,APT,IDM Laboratory 3H5 25 mi. NE of vent; local farm FPL,FPV 82

MAP B-i ON-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 1

15 3 GE O::'.

w O::'.

M UM EXCLUSI AREA BDUNDA C901 METE )

R ER 11 7

N 9

83

MAP 8-2 OFF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND

.I

' \

'\

\

\

ICALI O.~.~.-,-.~.~.'--~~-'--~~~ \

' \

84

APPENDIX C DATA TABLES 85

• IAPPENDIX c I DATA TABLES Appendix C presents the analytical results of the 1989 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1989.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1989 Concentrations Of Gross Alpha Emitters ******************** 90 C-2 1989 Concentrations of Gross Beta Emitters *.**.*.*..**.....*.*. 92 C-3 1989 Concentrations Of Strontium-89 and strontium-90 and Gamma Emitters in Quarterly Composites ******************** 94 AIR IODINE C-4 1989 Concentrations of Iodine-131 ****************************** 95 DATES C-5 1989 Sampling Dates for Air Samples **************************** 97 PRECIPITATION C-6 1989 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium and Gamma Emitters................................ 102 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-7 1989 Quarterly TLD Results *****.*.*..***....**.**.*.***.*.***** 103 C-8 1989 Monthly TLD Results ****************************.********** 104

• 87

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT MILK C-9 1989 Concentrations of Iodine-131 and Gamma Emitters *********** 106 C-10 1989 Concentrations of Strontium-89 and Strontium-90 *********** 108 WELL WATER C-11 1989 Concentrations of Gross Alpha and Gross Beta Emitters1 Potassium-40 and Tritium.................................. 109 C-12 1989 Concentrations of Iodine 131 and Gamma Emitters *********** 110 C-13 1989 concentrations of Strontium-89 and Strontium-90 in Quarterly Composites...................................... 111 POTABLE WATER C-14 1989 Concentrations of Gross Alpha and Gross Beta Emitters1 Potassium-40 and Tritium ********.******************. o***** 112 C-15 1989 Concentrations of Iodine 131 and Gamma Emitters *********** 113 C-16 1989 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites *..****.*****.**.*...*.*..*.....****.. 114 FOOD PRODUCTS C-17 1989 Concentrations of Gamma Emitters in Vegetables ************ 115 C-18 1989 Concentrations of Gamma Emitters in Beef and Game ********* 116 FODDER CROPS C-19 1989 Concentrations of Gamma Emitters ************************** 117 SOIL C-20 1989 concentrations of Strontium 90 and Gamma Emitters ********* 118.

88

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER C-21 1989 Concentrations of Gross Alpha Emitters ******************** 119 C-22 1989 Concentrations of Gross Beta Emitters ********************* 120 C-23 1989 Concentrations of Tritium in Quarterly Composites ********* 121 C-24 1989 Concentrations of Gamma Emitters ************************** 122 EDIBLE FISH C-25 1989 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters................................ 124 BLUE CRABS C-26 1989 Concentrations of Strontium-89 and Strontium-90; Gamma Emitters and Tritium .......*...*.......*.....* o***** 125 SEDIMENT C-27 1989 concentrations of Strontium-90 and Gamma Emitters ********* 126 SPECIAL TABLES LLDs C-28 1989 PSE&G Research and Testing Laboratory LLDs for Gamma Spectrometry........................................ 127

• 89

TABLE C-1 1989 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m 3 +/- 2 sigma

It

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

lt:lt MONTH SA-APT-5Sl SA-APT-5Dl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JANUARY 2.3+/-0.8 <5.0 2.5+/-0.9 2.9+/-1.0 2.7+/-0.9 2.5+/-0.9 3.0+/-2.0 2.2+/-1.0 <5.0 1. 9+/-0. 8 1.8+/-0 .9 1.9+/-0.9 1. 9+/-0. 8 2.5+/-2.5 3 .1+/-1.0 <5.0 1. 7+/-0.8 2.5+/-0.9 1.9+/-0.8 2.2+/-1.0 2.7+/-2.4

1. 9+/-0. 8 <5.0 3.1+/-1.0 2.6+/-0.9 1.7+/-0.8 2.1+/-0.8 2.7+/-2.4 3.3+/-0.9 <5.0 3. 7+/-1.0 3 .8+/-1.0 3.3+/-0.9 4.1+/-1. 2 3 .9+/-1. 3 FEBRUARY 1.1+/-0. 8 <5.0 <1.1 1.8+/-0 .9 2.0+/-0.9 1.4+/-0.8 2.1+/-3.0 1.6+/-0.6 <5.0 1.8+/-0.6 0.9+/-0.6 2.0+/-0.7 1.8+/-0.6 2.1+/-2.8 3.2+/-1.0 <5.0 3.6+/-0.9 3.1+/-0.9 2.4+/-0.8 2.5+/-0.8 2.7+/-2.6 2.3+/-0.9 <5.0 2.1+/-0.8 2.0+/-0.9 2.4+/-0.9 1.9+/-0.8 3.0+/-2.2 MARCH 2.6+/-0.9 <5.0 2.3+/-0.8 2.5+/-0.8 2.5+/-0.8 3.1+/-0.8 2.8+/-2.1

\D 2.5+/-0.8 <5.0 2.5+/-0.7 2.9+/-0.9 2.9+/-0.8 2.6+/-0.8 3.0+/-1.9 0 1.6+/-0. 8 <5.0 1.8+/-0.8 2.2+/-0.9 2.6+/-0.9 1.7+/-0.8 2.8+/-2.3 1.1+/-0.6 <5.0 1.4+/-0. 7 1.8+/-0.8 1.2+/-0.7 2.3+/-0.8 2.3+/-2.7 APRIL 1.6+/-0.8 <5.0 1.4+/-0. 7 1. 7+/-0. 7 1.6+/-0. 7 1.2+/-0.6 2.1+/-2.8 2.0+/-0.7 <5.0 2.1+/-0.7 1.4+/-0.6 1.6+/-0.6 1.9+/-0.6 2.2+/-2.7 2.0+/-0.8 <5.0 2.3+/-0.9 1.4+/-0.8 2.6+/-0.9 1. 3+/-0. 7 2.4+/-2.6 3.4+/-0.9 <5.0 3.8+/-0.9 3.3+/-0.9 3.7+/-1.0 3.7+/-0.9 3 .8+/-1.2 1.2+/-0.7 <5.0 1.7+/-0.8 1. 9+/-0. 8 2.0+/-0.9 1.9+/-0.7 2.3+/-2.7 MAY <3.6 (1) <5.0 1.0+/-0. 7 1.2+/-0. 7 1.0+/-0.6 <0.7 2.1+/-3.6 0.9+/-0.6 <5.0 1.0+/-0.7 0.9+/-0.6 <0.9 1.1+/-0.7 1.6+/-3. 3 1.5+/-0.7 <5.0 2.1+/-0.8 2 .6+/-1.0 1.7+/-0.8 1.7+/-0.7 2.4+/-2.6 1.4+/-0. 7 <5.0 1.4+/-0.8 1.3+/-0.7 1.8+/-0.9 1.8+/-0.8 2.1+/-2.9 JUNE 2.0+/-0.8 . <7.0 2.5+/-1.0 1.8+/-0.9 1.4+/-0. 8 1.6+/-0. 8 2.4+/-2.7 1.2+/-0.7 <5.0 <1.1 <0.9 1.3+/-0.8 <0.8 1.7+/-3.2 1.2+/-0.7 <5.0 1.2+/-0.9 1.6+/-0.8 1.6+/-0. 8 1.3+/-0.7 2.0+/-3.0

<0.9 <5.0 <1.0 <1.4 1.1+/-0. 8 1.6+/-0. 7 1. 8+/-3 .1

• TABLE C-1 (Cont'd) 1989 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m 3 +/- 2 sigma

It

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

MONTH SA-APT-5Sl **

SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JULY 2.3+/-0.9 <5.0 3.7+/-1.1 <2.1 (2) 3. 0+/-1. 0 2.6+/-0.9 3.1+/-2.2 2.8+/-0.8 <5.0 2.3+/-0.8 2.3+/-0.8 2.1+/-0.8 2.3+/-0.7 2.8+/-2.2 2.1+/-0.9 <5.0 2. 7+/-1.0 2.4+/-0.9 3.0+/-0.9 2.2+/-0.8 2.9+/-2.2 2.1+/-0.7 <5.0 2.6+/-0.8 2.1+/-0.7 1. 7+/-0. 7 1.5+/-0.6 2.5+/-2.6 4.9+/-1. 3 <5.0 3.4+/-1.1 4.0+/-1.2 3.0+/-1.0 3.2+/-0.9 3 .9+/-1. 7 AUGUST 2.8+/-0.9 <5.0 3.3+/-1.0 3.0+/-0.9 2.5+/-0.9 2.3+/-0.7 3.2+/-1.9 1.1+/-0.6 <5.0 1.2+/-0.7 1.8+/-0.8 <0.8 1.1+/-0.6 1. 8+/-3. 2 1.0+/-0.6 <5.0 1.2+/-0.7 1. 8+/-0. 8 1.7+/-0.8 1.8+/-0. 7 2.1+/-2.9 1.5+/-0.7 <5.0 3.0+/-0.9 2.1+/-0.8 2.6+/-0.9 2.5+/-0.8 2.8+/-2.4 U) SEPTEMBER 2.7+/-0.8 <5.0 1.7+/-0.8 2.0+/-0.8 1.9+/-0.8 1.8+/-0. 7 2.5+/-2.5 I-' 1.6+/-0.9 <5.0 3.8+/-1.2 3 .0+/-1.2 1.7+/-1.0 2.1+/-0.9 2.9+/-2.7 1.2+/-0.9 <5.0 <1.3 <1.2 <1.2 <1.0 1.8+/-3.1 1.6+/-0. 7 <5.0 1.1+/-0.7 <0.9 0.9+/-0.6 0.9+/-0.6 1. 7+/-3 .2 OCTOBER 1.2+/-0.8 <5.0 1. 3+/-0 .9 1.4+/-0.9 1.2+/-0.9 <0.9 1. 8+/-3 .1 1.0+/-0.6 <5;.0 1. 5+/-0 .8 1.4+/-0.8 1.3+/-0.8 1.1+/-0.6 1.9+/-3 .1 4.9+/-0.1 <5.0 4.8+/-0.1 4.5+/-1. 3 3.9+/-1.3 3.1+/-0.9 4.4+/-1.5 1.3+/-0.6 <5.0 2.5+/-0.9 1.2+/-0.7 2.3+/-0.8 1. 7+/-0. 7 2.3+/-2.8 4.8+/-1.1 <5.0 4.8+/-1.1 3. 7+/-1.0 5.8+/-1.3 3.9+/-0.9 4. 7+/-1. 5 NOVEMBER 2.9+/-0.9 <5.0 2.4+/-1.0 3 .9+/-1.1 3.1+/-1.0 3.2+/-0.9 3.4+/-1.8 2.3+/-0.9 <5.0 2.0+/-0.9 1.4+/-0.8 1.8+/-0.9 1.6+/-0.7 2.4+/-2.7 2.3+/-0.8 <5.0 1. 7+/-0 .8 1.5+/-0.9 1.9+/-0.8 1. 7+/-0. 8 2.4+/-2.7 2.0+/-0.0 <5.0 1.4+/-0.7 1.8+/-0.9 2 .1+/-1. 3 1.9+/-0. 7 2.4+/-2.6 DECEMBER 2.8+/-0.8 <5.0 3.3+/-1.0 2.4+/-0.9 3.6+/-1.0 3.1+/-0.8 3 .4+/-1.8 1.8+/-0.8 <5.0 2.7+/-0.9 1.8+/-1.0 2.2+/-1.0 2.9+/-0.9 2.7+/-2.4 3.2+/-0.9 <5.0 3.9+/-1.0 3.4+/-0.9 3 .9+/-1.1 3.9+/-1.0 3.9+/-1.2 2.0+/-0.0 <5.0 1.5+/-0. 7 1.4+/-0. 7 2. 7+/-1.0 1.8+/-0. 7 2.4+/-2.7 AVERAGE 2.1+/-2.0 2.3+/-2.0 2 .2+/-1. 7 2. 3+/-1.8 2.1+/-1.6 GRAND AVERAGE 2 .2+/-1. 7 11 Sampling dates can be found in Table C-5.

1111 Results by Controls for Environmental Pollution, Inc.

High LLD due to low sample volume. Result not included in any averages.

g~ Air sampler malfunction.

TABLE C-2 1989 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m 3 +/- 2 sigma

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

MONTH SA-APT-5Sl **

SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JANUARY 42+/-3 34+/-2 46+/-3 46+/-4 42+/-3 43+/-3 42+/-9 23+/-3 23+/-2 27+/-3 26+/-3 24+/-3 26+/-3 25+/-3 35+/-3 22+/-2 25+/-3 29+/-3 27+/-3 33+/-3 29+/-10 27+/-3 21+/-2 28+/-3 25+/-2 26+/-3 30+/-3 26+/-6 40+/-3 32+/-2 40+/-3 41+/-3 37+/-3 40+/-4 38+/-7 FEBRUARY 29+/-3 30+/-2 28+/-3 29+/-3 30+/-3 30+/-3 29+/-2 33+/-3 28+/-2 32+/-2 22+/-2 32+/-2 29+/-2 29+/-8 29+/-3 27+/-2 27+/-3 31+/-3 30+/-3 28+/-3 29+/-3 27+/-3 23+/-2 30+/-3 26+/-3 28+/-3 24+/-3 26+/-5

\0 MARCH 33+/-3 25+/-2 32+/-3 31+/-3 31+/-3 33+/-3 31+/-6 I\) 26+/-3 24+/-2 25+/-2 29+/-3 28+/-3 28+/-3 27+/-4 22+/-3 20+/-2 17+/-2 24+/-3 22+/-3 27+/-3 22+/-7 13+/-2 13+/-2 15+/-2 18+/-3 14+/-2 19+/-2 15+/-5 APRIL 15+/-3 15+/-2 14+/-2 17+/-2

• 15+/-2 15+/-2 15+/-2 20+/-2 16+/-2 18+/-2 20+/-3 19+/-2 20+/-2 19+/-3 19+/-3 13+/-2 20+/-3 23+/-3 19+/-3 20+/-2 19+/-7 29+/-3 25+/-2 29+/-3 28+/-3 29+/-3 28+/-3 28+/-3 18+/-2 16+/-2 16+/-2 19+/-2 21+/-3 15+/-2 18+/-5 MAY <13 (1) 11+/-2 13+/-2 11+/-2 13+/-2 14+/-2 12+/-3 11+/-2 12+/-2 10+/-2 11+/-2 12+/-2 10+/-2 11+/-2 22+/-2 18+/-2 22+/-3 21+/-3 22+/-3 19+/-2 21+/-4 22+/-2 17+/-2 19+/-2 24+/-2 19+/-3 20+/-2 20+/-5 JUNE 30+/-3 24+/-2 31+/-4 28+/-3 32+/-3 26+/-3 29+/-6 15+/-2 11+/-1 16+/-3 14+/-2 16+/-2 11+/-2 14+/-5 21+/-3 7 .0+/-1.0 16+/-3 20+/-3 20+/-3 21+/-2 18+/-11 17+/-2 12+/-2 17+/-3 15+/-3 17+/-3 22+/-2 17+/-7

TABLE C-2 (Cont'd) 1989 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of lo- 3 pCi/m 3 +/- 2 sigma

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

MONTH SA-APT-581 **

SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JULY 23+/-3 15+/-2 26+/-3 22+/-4 21+/-2 26+/-3 22+/-8 20+/-2 16+/-2 25+/-3 22+/-2 21+/-3 23+/-2 21+/-6 23+/-3 20+/-2 21+/-3 23+/-3 24+/-3 20+/-2 22+/-3 18+/-2 16+/-2 18+/-2 19+/-2 21+/-2 16+/-2 18+/-4 25+/-3 23+/-2 21+/-3 22+/-3 27+/-3 29+/-3 25+/-6 AUGUST 29+/-3 26+/-1 34+/-3 30+/-3 32+/-3 31+/-3 30+/-5 8.0+/-2.0 13+/-1 11+/-2 9.1+/-2.3 9.6+/-2.3 9.2+/-2.0 10+/-4 20+/-3 14+/-2 23+/-3 20+/-3 20+/-3 19+/-2 19+/-6 30+/-3 25+/-2 25+/-3 24+/-3 28+/-3 26+/-3 26+/-5

\D SEPTEMBER 28+/-2 22+/-2 28+/-3 27+/-3 31+/-3 24+/-2 27+/-6 w 34+/-3 22+/-2 32+/-3 34+/-4 31+/-3 30+/-3 31+/-9 19+/-3 12+/-2 17+/-3 16+/-3 18+/-3 14+/-2 16+/-5 9.2+/-2.1 10+/-2 9.5+/-2.5 7.6+/-2.4 10+/-2 9.0+/-2.1 9.2+/-2 OCTOBER 25+/-3 22+/-2 26+/-3 27+/-3 25+/-3 24+/-2 25+/-4 22+/-2 22+/-2 22+/-3 23+/-2 23+/-3 20+/-2 22+/-2 52+/-4 50+/-3 48+/-4 50+/-4 47+/-4 40+/-3 48+/-8 18+/-2 16+/-2 21+/-3 17+/-2 18+/-2 16+/-2 18+/-4 51+/-3 46+/-2 49+/-4 45+/-4 55+/-4 60+/-3 51+/-11 NOVEMBER 27+/-3 28+/-2 23+/-3 32+/-3 30+/-3 33+/-3 29+/-7 31+/-3 28+/-2 32+/-3 31+/-3 32+/-3 31+/-3 31+/-3 34+/-3 31+/-2 32+/-3 34+/-3 31+/-3 28+/-3 32+/-5

. 24+/-3 21+/-2 21+/-3 22+/-3 20+/-4 22+/-2 22+/-3 DECEMBER 30+/-3 26+/-2 28+/-3 30+/-3 29+/-3 26+/-2 28+/-4 28+/-3 23+/-2 28+/-3 29+/-3 28+/-3 33+/-3 28+/-6 41+/-3 37+/-2 41+/-3 42+/-3 40+/-4 44+/-3 41+/-5 32+/-3 34+/-2 32+/-3 30+/-3 40+/-3 28+/-2 33+/-8 AVERAGE 26+/-19 22+/-17 25+/-18 25+/-18 26+/-18 25+/-19 GRAND AVERAGE 25+/-18

• sampling dates can be found in Table C-5.

• • Results by Controls for Environmental Pollution, Inc.

High LLD due to low sample volume (air sampler malfunction). Result not included in any averages.

g~ Air sampler malfunction *.

TABLE C-3 1989 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 AND GAMMA EMITTERS**

IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10- 3 pCitm3 +/- 2 sigma

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

STATION ID SAMPLING PERIOD Sr-89 Sr-90 Be-7 K-40 Ra-226 SA-APT-5Sl 12-27-88 to 03-27-89 <0.3 <0.2 68+/-5 <6.9 <0.7 SA-APT-5Dl (1) 12-27-88 to 03-27-89 <2.0 <2.0 <LLD <LLD <LLD SA-APT-16El 12-27-88 to 03-28-89 <0.3 <0.2 57+/-4 <7.5 <0.8 SA-APT-1F1 12-27-88 to 03-27-89 <0.3 <0.2 65+/-4 <6.4 <0.8 SA-APT-2F2 12-27-88 to 03-27-89 <0.4 <0.3 59+/-4 <8.2 <0.8 SA-APT-3H3 (C} 12-27-88 to 03-27-89 <0.3 <0.2 68+/-5 <7.3 <1.0 SA-APT-5S1 03-27-89 to 06-26-89 66+/-5 <8.1 <0.8 SA-APT-5D1 (1) 03-27-89 to 06-26-89 <LLD <LLD <LLD SA-APT-16E1 03-28-89 to 06-26-89 62+/-5 <8.6 <0.8 SA-APT-1Fl 03-27-89 to 06-23-89 (2) 63+/-4 <6.6 <0.7 SA-APT-2F2 03-27-89 to 06-26-89 68+/-5 <8.1 <0.9 SA-APT-3H3 (C} 03-27-89 to 06-26-89 60+/-4 8.6+/-2.7 <0.7 SA-APT-5S1 06-26-89 to 09-25-89 68+/-5 <7.6 <0.7 SA-APT-5Dl (1) 06-26-89 to 09-25-89 <LLD <LLD <LLD SA-APT-16E1 06-26-89 to 09-25-89 72+/-4 <6.3 <0.9 SA-APT-1Fl 06-26-89 to 09-25-89 69+/-5 <6.9 <0.9 SA-APT-2F2 06-26-89 to 09-25-89 73+/-5 <8.0 <0.7 SA-APT-3H3 (C} 06-26-89 to 09-25-89 67+/-4 <5.5 0.5+/-0.3 SA-APT-5S1 09-25-89 to 12-26-89 59+/-4 <10 <0.6 SA-APT-5Dl (1) 09-25-89 to 12-26-89 60+/-10 <LLD <LLD SA-APT-16E1 09-25-89 to 12-26-89 58+/-6 <12 <0.6 SA-APT-1F1 09-25-89 to 12-26-89 55+/-6 <5.8 <0.5 SA-APT-2F2 09-25-89 to 12-26-89 61+/-7 <6.4 <0.5 SA-APT-3H3 (C} 09-25-89 to 12-26-89 60+/-6 <4.5 <0.4 AVERAGE 64+/-10

• Sr-89 results are corrected for decay to sample stop date.

• • All other ganma emitters searched for were <LLD; typical LLDs are given in Table C-28.

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

(C) Control Station (1) Results by Controls for Environmental Pollution, Inc. Undetected ganma emitters are reported as <LLD.

(2) Reduced sampling period for the final weekly filter due to an air sampler malfunction.

94

TABLE C-4 1989 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of lo- 3 pCi/m 3

<-------------------------------------- STATION ID MONTH SA-AI0-5Sl SA-AI0-5Dl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control)

• JANUARY <20 <7.0 <21 <16 <13 <15

<24 <13 <17 <22 <11 <16

<24 <13 <17 <26 <23 <16

<20 <13 <17 <20 <16 <16

<9.6 <13 <20 <11 <14 <20 FEBRUARY <18 <13 <24 <21 <16 <12

<15 <13 <11 <17 <15 <17

<16 <13 <19 <22 <20 <13

<18 <13 <17 <19 <20 <15

\0 MARCH <14 <13 <15 <11 <25 <12 U1 <17 <13 <13 <16 <14 <13

<18 <13 <17 <23 <20 <15

<16 <13 <11 <17 <16 <7.7 APRIL <25 <13 <14 <19 <15 <11

<14 <13 <14 <17 <23 <12

<19 <13 <16 <20 <17 <14

<19 <13 <18 <18 <20 <22

<16 <13 <14 <18 <18 <14 MAY <23 ( 1) <13 <16 <19 <22 <22

<30 <13 <15 <16 <20 <15

<18 <13 <16 <18 <20 <16

<21 <13 <23 <15 <20 <13 JUNE <16 <13 <29 <26 <23 <14

<14 <13 <18 <15 <16 <12

<24 <13 <22 <17 <22 <17

<25 <13 <16 <41 (1) <20 <14

TABLE C-4 (Cont'd) 1989 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10- 3 pCi/m 3

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

MONTH SA-AI0-5Sl ***

SA-AI0-5Dl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control)

JULY <7.7 <13 <12 <28 (1) <7.5 <13

<14 <13 <16 <13 <19 <13

<11 <13 <9.6 <12 <13 <14

<12 <13 <23 <12 <16 <10

<24 <13 <18 <21 <24 <10 AUGUST <20 <13 <16 <24 <20 <13

<17 <13 <13 <14 <15 <18

<21 <13 <20 <12 <18 <16

<15 <13 <12 <17 <21 <10

\D SEPTEMBER <21 <13 <11 <22 <17 <19 C"I <18 <13 <13 <24 <19 <15

<21 <13 <16 <21 <18 <12

<15 <13 <23 <22 <12 <14 OCTOBER <17 <13 <18 <22 <17 <16

<14 <13 <12 <16 <22 <11

<24 <13 <15 <30 <25 <16

<15 <13 <20 <16 <11 <12

<19 <13 <9.6 <20 <25 <13 NOVEMBER <17 <1-3 <16 <12 <13 <16

<14 <13 <23 <15 <19 <9.3

<16 <13 <11 <19 <18 <15

<13 <13 <18 <11 <36 <10 DECEMBER <15 <13 <16 <19 <22 <9.6

<6.2 <13 <5.2 <13 <14 <13

<12 <13 <7.2 <5.8 <7.8 <13

<9.3 <13 <7.8 <4.8 <5.6 <8.8

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

• • sampling dates can be found in Table C-5.

• • • Results by Controls for Environmental Pollution, Inc.

(1) Air sampler malfunction *

• TABLE C-5 1989 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 5Dl 16El STATION CODE ------------------------------------>

lFl 2F2 3H3 (Control)

JANUARY 12-27-88 12-27-88 12-27-88 12-27-88 12-27-88 12-27-88 to to to to to to 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 01-03-89 to to to to to to 01-09-89 01-09-89 01-10-89 01-09-89 01-09-89 01-10-89 01-09-89 01-09-89 01-10-89 01-09-89 01-09-89 01-10-89 to to to to to to 01-16-89 01-16-89 01-17-89 01-16-89 01-16-89 01-16-89 01-16-89 01-16-89 01-17-89 01-16-89 01-16-89 01-16-89 to to to to to to 01-23-89 01-23-89 01-24-89 01-23-89 01-23-89 01-23-89

\D

-...J 01-23-89 01-23-89 01-24-89 01-23-89 01-23-89 01-23-89 to to to to to to 01-30-89 01-30-89 01-31-89 01-30-89 01-30-89 01-30-89 FEBRUARY 01-30-89 01-30-89 01-31-89 01-30-89 01-30-89 01-30-89 to to to to to to 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 02-06-89 to to to to to to 02-14-89 02-14-89 02-14-89 02-14-:89 02-14-89 02-14-89 02-14-89 02-14-89 02-14-89 02-14-89 02-14-89 02-14-89 to to to to to to 02-21-89 02-21-89 02-22-89 02-21-89 02-21-89 02-21-89 02-21-89 02-21-89 02-22-89 02-21-89 02-21-89 02-21-89 to to to .to to to 02-27-89 02-27-89 02-28-89 02-27-89 02-27-89 02-27-89 MARCH 02-27-89 02-27-89 02-28-89 02-27-89 02-27-89 02-27-89 to to to to to to 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 03-06-89 to to to to to to 03-13-89 03-13-89 03-14-89 03-13-89 03-13-89 03-13-89

TABLE C-5 (Cont'd) 1989 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 5Dl 16El STATION CODE ------------------------------------>

lFl 2F2 3H3 (Control)

MARCH 03-13-89 03-13-89 03-14-89 03-13-89 03-13-89 03-13-89 to to to to to to 03-20-89 03-20-89 03-21-89 03-20-89 03-20-89 03-20-89 03-20-89 03-20-89 03-21-89 03-20-89 03-20-89 03-20-89 to to to to to to 03-27-89 03-27-89 03-28-89 03-27-89 03-27-89 03-27-89 APRIL 03-27-89 03-27-89 03-28-89 03-27-89 03-27-89 03-27-89 to to to to to to 04-03-89 04-03-89 04-03-89 04-03...:99 04-03-89 04-03-89 04-03-89 04-03-89 04-03-89 04-03-89 04-03-89 04-03-89 to to to to to to

\C 04-10-89 04-10-89 04-11-89 04-10-89 04-10-89 04-10-89 CX>

04-10-89 04-10-89 04-11-89 04-10-89 04-10-89 04-10-89 to to to to to to 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 04-17-89 to to to to to to 04-24-89 04-24-89 04-25-89 04-24-89 04-24-89 04-24-89 04-24-89 04-24-89 04-25-89 04-24-89 04-24-89 04-24-89 to to to to to to 05-01-89 05-01-89 05-02-89 05-01-89 05-01-89 05-01-89 MAY 05-01-89 05-01-89 05-02-89 05-01-89 05-01-89 05-01-89 to to to to to to 05-03-89 (l) 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 05-08-89 to to to to to to 05-15-89 05-15-89 05-15-89 05-15-8~ 05-15-89 05-15-89 05-15-89 05-15-89 05-15-89 05-15-8~ 05-15-89 05-15-89 to to to to to to 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 05-22-89 to to to to to to 05-30-89 05-30-89 05- 05-30-89 05-30-89 05-3

TABLE C-5 (Cont'd) 1989 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 5Dl 16El STATION CODE ------------------------------------>

lFl 2F2 3H3 (Control)

JUNE 05-30-89 05-30-89 05-30-89 05-30-89 05-30-89 05-30-89 to to to to to to 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 06-05-89 to to to to to to 06-13-89 06-13-89 06-12-89 06-12-89 06-12-89 06-12-89 06-13-89 06-13-89 06-12-89 06-12-89 06-12-89 06-12-89 to to to to to to 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 06-19-89 to to to to to to 06-26-89 06-26-89 06-26-89 06-23-89 (1) 06-26-89 06-26-89

\D

\D JULY 06-26-89 06-26-89 06-26-89 06-26-89 06-26-89 06-26-89 to to to to to to 07-03-89 07-03-89 07-03-89 06-30-89 (1) 07-03-89 07-03.-89 07-03-89 07-03-89 07-03-89 07-03-89 07-03-89 07-03-89 to to to to to to 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 07-10-89 to to to to to to 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 07-17-89 to to to to to to 07-25-89 07-25-89 07-25-89 07-25-89 07-25-89 07-24-89 07-25-89 07-25-89 07-25-89 07-25-89 07-25-89 07-24-89 to to to to to to 07-31-89 07-31-89 08-01-89 07-31-89 07-31-89 07-31-89 AUGUST 07-31-89 07-31-89 08-01-89 07-31-89 07-31-89 07-31-89 to to to to to to 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 08-07-89 to to to to to to 08-14-89 08-14-89 08-15-89 08-14-89 08-14-89 08-14-89

TABLE C-5 (Cont'd) 1989 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 501 16El STATION CODE ------------------------------------>

lFl 2F2 3H3 (Control)

AUGUST 08-14-89 08-14-89 08-15-89 08-14-89 08-14-89 08-14-89 to to to to to to 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 08-21-89 to to to to to to 08-28-89 08-28-89 08-29-89 08-28-89 08-28-89 08-28-89 SEPTEMBER 08-28-89 08-28-89 08-29-89 08-28-89 08-28-89 08-28-89 to to to to to to 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 09-05-89 to to to to to to

...... 09-11-89 09-11-89 09-12-89 09-11-89 09-11-89 09-11-89 0

0 09-11-89 09-11-89 09-12-89 09-11-89 09-11-89 09-11-89 to to to to to to 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 09-18-89 to to to to to to 09-25-89 09-25-89 09-25-89 09-25-89 . 09-25-89 09-25-89 OCTOBER 09-25-89 09-25-89 09-25-89 09-25-89 09-25-89 09-25-89 to to to to to to 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 10-02-89 to to to to to to 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 10-10-89 to to to to to to 10-16-89 10-16-89 10-16-89 10-16-89.;

10-16-89 10-16-89 10-16-89 10-16-89 10-16-89 10-16-89_ 10-16-89 10-16-89 to to to to . ' to to 10-23-89 10-23-89 10-24-89 10-23-89 10-23-89 10-23-89 10-23-89 10-23-89 10-24-89 10-23-89 10-23-89 10-23-89 to to to to to to 10-30-89 10-30-89 10- 10-30-89 10-30-89 10-3

.educed sampling period due to an air sampler m tion.

TABLE C-5 (Cont'd) 1989 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 5Dl 16El STATION CODE ------------------------------------>-

lFl 2F2 3H3 (Control)

NOVEMBER 10-30-89 10-30-89 10-31-89 10-30-89 10-30-89 10-30-89 to to to to to to 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 11-06-89 to to to to to to 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 11-13-89 to to to to to to 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 11-20-89 (1) 11-20-89 to to to to to to

...... 11-27-89 11-27-89 11-28-89 11-27-89 11-24-89 11-27-89 0

...... DECEMBER 11-27-89 11-27-89 11-28-89 11-27-89 11-27-89 11-27-89 to to to to to to 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 12-04-89 to to to to to to 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 12-11-89 to to to to to to 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 12-18-89 to to to to to to 12-26-8~ 12-26-89 12-26-89 12-26-89 12-26-89 12-26-89 (1) Reduced sampling period due to an air sampler malfunction.

TABLE C-6 1989 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, TRITIUM AND GAMMA EMITTERS* IN PRECIPITATION Results in Units of pCi/L +/- 2 sigma STATION ID: SA-RWA-2F2 GROSS GROSS <-------- GAMMA EMITTERS -------)

SAMPLING PERIOD ALPHA BETA TRITIUM Be-7 K-40 Ra-226 12-27-88 to 01-31-~9 <1.4 3.6+/-0.9 <160 55+/-18 <61 <7.8 01-31-89 to 02-28-89 <1.4 4.7+/-0.9 <160 57+/-20 68+/-26 <10 02-28-89 to 03-27-89 0.9+/-0.7 6.5+/-1.8 <150 74+/-16 46+/-28 <7.5 03-27-89 to 05-01-89 1.5+/-1.0 5.1+/-1.5 <160 <30 <76 9.1+/-4.7 05-01-89 to 05-30-89 <1.5 6. 7+/-1.0 <160 26+/-9 <30 <3.7 0

05-30-89 to 06-26-89 <1.5 3.0+/-0.8 <160 33+/-11 <39 <4.5

"-> <1.2 4.4+/-0.8 <150 43+/-12 <34 <4.5 06-26-89 to 08-01-89 08-01-89 to 08-29-89 3.6+/-1.4 <2.2 <160 47+/-17 <83 <8.1 08-29-89 to 09-25-89 <1.1 <2.1 <160 54+/-17 . <57 <8.1 09-25-89 to 10-30-89 <1.7 8.5+/-1.8 <130 81+/-21 <76 <1.2 10-30-89 to 11-27-89 <2.3 <1.9 <140 42+/-18 <54 <6.8 11-27-89 to 12-26-89 <1.3 8.2+/-2.7 <130 <77 295+/-75 23+/-11 AVERAGE 4.7+/-4.6 52+/-37

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.

TABLE C-7 1989 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)

JANUARY APRIL JULY OCTOBER STATION ID to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 5.3+/-0.4 4.9+/-0.5 5.5+/-0.4 4.3+/-0.7 5 .0+/-1.1 SA-IDM-5Sl 4.8+/-0.3 4.0+/-0.3 4.9+/-0.2 4.2+/-0.4 4.5+/-0.9 SA-IDM-6S2 5.4+/-0.4 4.3+/-0.3 5.3+/-0.3 4.4+/-0.3 4.9+/-1.2 SA-IDM-7Sl 6.3+/-0.7 5.7+/-0.5 6.5+/-0.4 5.4+/-0.5 6.0+/-1.0 SA-IDM-lOSl 6.2+/-0.7 5.5+/-0.5 6.2+/-0.5 5.2+/-0.5 5.8+/-1.0 SA-IDM-llSl 7 .2+/-1.5 7 .0+/-1.2 6.9+/-1.l 5.2+/-0.7 6.6+/-1.9 SA-IDM-4D2 5.4+/-0.5 4.8+/-0.6 5.7+/-0.4 4.9+/-0.7 5.2+/-0.8 SA-IDM-5Dl 5.2+/-0.4 4.7+/-0.5 5.4+/-0.3 4.5+/-0.6 5.0+/-0.8 SA-IDM-1001 5.7+/-0.7 4.8+/-0.9 6.0+/-0.3 5.1+/-0.8 5.4+/-1.1 SA-IDM-1401 5.1+/-0.3 4.2+/-0.2 5.4+/-0.3 4.6+/-0.4 4.8+/-1.1 SA-IDM-2El 5.2+/-0.2 4.6+/-0.4 5.4+/-0.3 4.6+/-0.3 5.0+/-0.8 SA-IDM-3El 5.1+/-0.2 4.0+/-0.3 5.2+/-0.3 4.7+/-0.2 4. 8+/-1.1 SA-IDM-9El 5.9+/-0.6 5.4+/-0.8 6.2+/-0.4 5.5+/-0.6 5.8+/-0.7 SA-IDM-11E2 5.8+/-0.5 5.4+/-0.7 6.2+/-0.4 5.3+/-0.6 5.7+/-0.8 SA-IDM-12El 5.8+/-0.5 4.8+/-0.6 6.2+/-0.4 5.1+/-0.6 5.5+/-1.3 SA-IDM-13El 4.9+/-0.3 4.2+/-0.4 5.1+/-0.3 4.3+/-0.4 4.6+/-0.9 SA-IDM-16El 5.5+/-0.4 4.7+/-0.5 5.7+/-0.4 4.8+/-0.6 5.2+/-1.l SA-IDM-lFl 5.5+/-0.4 4.6+/-0.6 5.6+/-0.3 4.6+/-0.4 5.1+/-1.1 SA-IDM-2F2 3.9+/-0.l 3.6+/-0.l 4.5+/-0.1 3.7+/-0.3 3.9+/-0.8 SA-IDM-2F5 5.6+/-0.3 4.7+/-0.6 5.6+/-0.3 4.9+/-0.5 5.2+/-0.9 SA-IDM-2F6 5.5+/-0.2 4.4+/-0.3 5.6+/-0.3 5.0+/-0.5 5.1+/-1.1 SA-IDM-3F2 4.8+/-0.3 4.2+/-0.3 4.8+/-0.4 4.3+/-0.3 4.5+/-0.6 SA-IDM-3F3 4.9+/-0.2 4.3+/-0.2 4.9+/-0.3 4.2+/-0.3 4.6+/-0.8 SA-IDM-5Fl 5.2+/-0.3 4.2+/-0.4 5.2+/-0.4 4.4+/-0.4 4.8+/-1.l SA-IDM-6Fl 4.5+/-0.3 3.8+/-0.2 4.5+/-0.2 3.7+/-0.2 4.1+/-0.9 SA-IDM-7F2 4.3+/-0.2 3.6+/-0.2 4.5+/-0.2 3.5+/-0.1 4.0+/-1.0 SA-IDM-10F2 5.8+/-0.5 4.7+/-0.5 6.0+/-0.5 4.8+/-0.5 5. 3+/-1. 3 SA-IDM-llFl 5.7+/-0.4 5.0+/-0.4 6.2+/-0.5 4.9+/-0.5 5.5+/-1.2 SA-IDM-12Fl 5.6+/-0.5 4.7+/-0.4 6.1+/-0.5 4.3+/-0.4 5.2+/-1.6 SA-IDM-13F2 5.4+/-0.3 4.5+/-0.6 5.7+/-0.5 4.5+/-0.4 5.0+/-1.2 SA-IDM-13F3 5.5+/-0.l 4.7+/-0.4 6.0+/-0.9 4.7+/-0.5 5.2+/-1.3 SA-IDM-13F4 5.6+/-0.4 4.8+/-0.4 5.2+/-0.3 4.8+/-0.4 5.1+/-0.8 SA-IDM-14F2 5.6+/-0.4 4.8+/-0.6 6.6+/-0.7 5.7+/-0.6 5. 7+/-1.5 SA-IDM-15F3 5.9+/-0.4 4.9+/-0.3 6.2+/-0.9 5.3+/-0.6 5.6+/-1.2 SA-IDM-16F2 5.1+/-0.5 4.4+/-0.2 5.5+/-0.3 4.4+/-0.5 4.9+/-1.1 SA-IDM-1G3 ~Cl 6.4+/-0.6 5.6+/-0.5 6.6+/-0.4 5.8+/-0.4 6.1+/-1.0 SA-IDM-3Gl C 5.7+/-0.4 4.9+/-0.5 6.0+/-0.3 5.0+/-0.6 5.4+/-1.1 SA-IDM-lOGl ~Cl 5.7+/-0.5 5.3+/-0.5 6.3+/-0.5 5.1+/-0.5 5.6+/-1.1 SA-IDM-16Gl C 6.3+/-0.5 5.4+/-0.7 6.5+/-0.5 5.6+/-0.7 6.0+/-1.1 SA-IDM-3Hl ~Cl 5.6+/-0.4 4.8+/-0.4 6.1+/-0.3 5.0+/-0.4 5.4+/-1.2 SA-IDM-3H3 C 5.7+/-0.2 5.0+/-0.5 6.3+/-0.4 5.0+/-0.4 5.5+/-1.3 AVERAGE 5.5+/-1.2 4.7+/-1.3 5. 7+/-1.2 4.8+/-1.1 GRAND AVERAGE 5.2+/-1.1

• The standard month = 30.4 days.

(C) Control Station

• 103

TABLE C-8 1989 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month~ +/- 2 sigma (Results by Teledyne Isotopes)

STATION ID JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 6.1+/-0.6 5.4+/-0.4 5.6+/-0.5 5.3+/-0.6 5.7+/-0.5 6.9+/-0.5 SA-IDM-5Sl 5.5+/-0.4 5.0+/-0.3 5.4+/-0.3 4.8+/-0.4 5.3+/-0.2 6.4+/-0.4 SA-IDM-6S2 6.3+/-0.4 5.6+/-0.4 5.7+/-0.6 5.5+/-0.4 5.8+/-0.6 7.0+/-0.4 SA-IDM-7Sl 7.3+/-0.7 6.5+/-0.5 6.9+/-0.5 6.2+/-0.7 6.7+/-0.5 7.9+/-0.7 SA-IDM-lOSl 6.7+/-0.6 6.1+/-0.6 7.1+/-0.9 6.3+/-0.9 6.9+/-0.9 7.7+/-0.6 SA- IDM-llSl 7.3+/-1.0 6.1+/-0.7 9.5+/-2.4 8.9+/-1. 7 9.2+/-1.4 8.6+/-1.0 SA-IDM-5Dl 6.1+/-0.6 5.3+/-0.4 5.6+/-0.4 5.1+/-0.4 5.7+/-0.4 6.7+/-0.5 SA-IDM-1001 6.4+/-0.6 5.9+/-0.7 6.4+/-0.7 5.9+/-0.6 6.4+/-0.9 7.4+/-0.6 SA-IDM-1401 5.9+/-0.6 5.6+/-0.5 5.5+/-0.2 5.0+/-0.2 5.9+/-0.6 7.1+/-0.5 SA-IDM-2El 6.1+/-0.6 5.4+/-0.4 5.6+/-0.3 5.3+/-0.6 5.6+/-0.4 6.8+/-0.7 SA-IDM-3El 5.9+/-0.8 5.2+/-0.4 5.5+/-0.4 5.1+/-0.4 5.5+/-0.4 6.6+/-0.4 I-' 5.5+/-0.6 0

SA-IDM-13El 5.6+/-0.6 5.3+/-0.5 5.2+/-0.4 5.7+/-0.6 6.7+/-0.5

~ SA-IDM-16El 6.2+/-0.8 5.7+/-0.6 6.0+/-0.4 5.5+/-0.6 5.8+/-0.4 7.2+/-0.4 SA-IDM-lFl 6.2+/-0.8 5.8+/-0.5 6.3+/-0.6 5.2+/-1.0 5.9+/-0.6 7.1+/-0.6 SA-IDM-2F2 5.5+/-0.4 4.7+/-0.2 4.8+/-0.2 4.4+/-0.7 5.0+/-0.3 6.2+/-0.4 SA-IDM-2F6 6.1+/-0.7 5.4+/-0.6 5.0+/-0.5 5.1+/-1.1 5.8+/-0.5 7.0+/-0.5 SA-IDM-5Fl 5.2+/-0.4 5.5+/-0.5 5.4+/-0.2 5.4+/-0.5 5.7+/-0.3 6.7+/-0.2 SA-IDM-6Fl 5.5+/-0.5 4.9+/-0.4 5.1+/-0.4 4.9+/-0.4 5.3+/-0.3 6.2+/-0.3 SA-IDM-7F2 5.1+/-0.5 4.5+/-0.2 4.6+/-0.2 4.4+/-0.3 4.7+/-0.2 5.6+/-0.3 SA-IDM-llFl 6.6+/-0.7 6.2+/-0.7 6.2+/-0.5 5.7+/-0.6 6.3+/-0.5 7.4+/-0.5 SA-IDM-13F4 6.5+/-0.7 6.1+/-0.6 6.1+/-0.5 5.9+/-0.5 6.2+/-0.3 7.4+/-0.6 SA-IDM-3Gl (C) 6.3+/-0.6 5.6+/-0.5 5.9+/-0.4 5.8+/-0.6 5.9+/-0.5 7.0+/-0.3 SA-IDM-3Hl (C) 6.5+/-0.5 5.8+/-0.7 6.2+/-0.2 5.8+/-0.4 6.1+/-0.5 6.9+/-0.2 SA-IDM-3H3 (C) 6.8+/-0.7 6.1+/-0.6 6.2+/-0.8 6.4+/-0.4 6.5+/-0.4 7.3+/-0.5 AVERAGE 6.2+/-1.2 5.6+/-1.0 5.9+/-2.0 5.5+/-1.8 6.0+/-1. 7 7 .0+/-1.2

TABLE C-8 (Cont'd) 1989 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)

STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 5.o+/-o.5 6.0+/-0.5 5.8+/-0.3 5.6+/-0.5 7.1+/-0.4 6.3+/-0.5 5.9+/-1.2 .

SA-IDM-5Sl 4.7+/-0.3 5.4+/-0.6 6.1+/-0.5 5.2+/-0.3 6.9+/-0.5 5.8+/-0.5 5.5+/-1.3 SA-IDM-6S2 5.3+/-0.4 5.8+/-0.3 6.9+/-0.5 5.0+/-0.4 7.7+/-0.6 6.6+/-0.6 6.2+/-1.4 SA-IDM-7Sl 6.1+/-0.5 7.0+/-0.6 8.0+/-0.8 6.6+/-0.5 8.3+/-0.7 7.1+/-0.6 7.1+/-1.4 SA-IDM-lOSl 6.1+/-0.6 6.6+/-0.7 7.5+/-0.6 6.4+/-0.5 0.on.o 6.8+/-1.0 6.9+/-1.2 SA- IDM-llSl 7.1+/-1.5 7.5+/-0.9 7 .9+/-1.l 6.8+/-0.8 8.3+/-0.9 5.9+/-0.4 7.8+/-2.3 SA-IDM-5Dl 5.2+/-0.4 5.9+/-0.5 6;7+/-0.3 5.6+/-0.4 7.1+/-0.7 6.3+/-0.8 5.9+/-1.2 SA-IDM-lODl 5.7+/-0.5 6.4+/-0.7 7.5+/-0.8 6.2+/-0.6 7.9+/-0.4 6.6+/-0.7 6.6+/-1.3 SA-IDM-14Dl 5.2+/-0.4 6.1+/-0.6 7.2+/-0.2 5.7+/-0.4 7.6+/-0.6 6.7+/-0.5 6.1+/-1.6 SA-IDM-2El 5.1+/-0.5 6.0+/-0.7 7.1+/-0.5 5.3+/-0.4 7.3+/-0.7 6.1+/-0.5 6.0+/-1.4

. SA-IDM-3El 5.0+/-0.4 5.5+/-0.5 6.4+/-0.4 5.5+/-o.5 7.1+/-0.6 6.2+/-0.6 5.8+/-1.3

...... SA-IDM-13El 5.1+/-0.4 5.8+/-0.5 6.6+/-0.3 5.6+/-0.4 7.3+/-0.7 6.0+/-0.6 5.9+/-1.3 0

U1 SA- IDM-16El 5.2+/-0.4 6.1+/-0.4 7.4+/-0.4 5.6+/-0.4 7.4+/-0.5 6.4+/-0.8 6.2+/-1.4 SA-IDM-lFl 5.4+/-0.6 6.0+/-0.6 6.9+/-0.5 5.8+/-0.4 7.6+/-0.6 6.5+/-0.7 6.2+/-1.3 SA-IDM-2F2 4.6+/-0.2 5.2+/-0.3 5.9+/-0.5 4.7+/-0.4 6.6+/-0.1 5.6+/-0.4 5. 3+/-1. 3 SA-IDM-2F6 5.2+/-0.3 6.1+/-0.6 7.0+/-0.6 5.8+/-0.5 7.5+/-0.6 6.3+/-0.4 6.0+/-1.6 SA-IDM-5Fl 5.0+/-0.4 5.7+/-0.5 6.4+/-0.5 5.3+/-0.7 1.0+/-0.5 6.1+/-0.6 5.8+/-1.2 SA-IDM-6Fl 4.5+/-0.3 5.4+/-0.6 6.0+/-0.4 4.9+/-0.2 6.5+/-0.6 5.5+/-0.5 5.4+/-1.1 SA- IDM-7F2

• 4.2+/-0.2 5.0+/-0.4 5.6+/-0.3 4.6+/-0.3 6.2+/-0.2 5.2+/-0.2 5.0+/-1.1 SA- IDM-llFl 5.1+/-0.9 6.3+/-0.7 7.1+/-0.5 6.4+/-0.7 8.2+/-1.1 7.0+/-0.7 6 .5+/-1. 5 SA-IDM-13F4 5.5+/-0.3 6.3+/-0.6 7.0+/-0.5 6.1+/-0.6 7.4+/-0.5 6.8+/-0.8 6.4+/-1.1 SA-IDM-3Gl (C) 5.5+/-0.4 6.6+/-0.4 7.1+/-0.3 6.1+/-0.6 6.7+/-0.8 6.8+/-0.8 6.3+/-1.l SA-IDM-3Hl (C) 5.3+/-0.5 6.5+/-0.6 6.9+/-0.4 6.0+/-0.4 7.6+/-0.6 6.9+/-0.7 6.4+/-1.2 SA-IDM-3H3 (C) 5.9+/-0.3 6.8+/-0.6 7.3+/-0.5 6.2+/-0.5 8.0+/-0.7 7.0+/-0.5 6. 7+/-1.2 AVERAGE 5. 3+/-1. 2 6.1+/-1.2 6.8+/-1.3 5. 7+/-1.1 7 .4+/-1.1 6 .4+/-1.0 GRAND AVERAGE 6. 2+/-1. 8

• The standard month = 30.4 days.

(C) Control Station

TABLE C-9 1989 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results ;n Un;ts of 10- 3 pC;/m 3 +/- 2 sigma SAMPLING <---------------- GAMMA EMITTERS ---------------->

STATION ID PERIOD 1-131 Be-7 K-40 Cs-137 Ra-226 Th-232 SA-MLK-2F7 01/03-04/89 <0.5 <23 1400+/-83 <2.8 <7.5 <12 SA-MLK-11F3 01/03-04/89 <0.6 <21 1400+/-80 4.0+/-2.1 <7.6 <10 SA-MLK-14Fl 01/03-04/89 <0.4 <21 1300+/-71 <3.1 14+/-4 <9.2 SA-MLK-3Gl (C) 01/03-04/89 <0.3 <19 1300+/-93 <3.3 <7.2 <14 SA-MLK-2F7 02/06-07/89 <0.6 <23 1400+/-83 <3.8 <8.4 <14 SA-MLK-11F3 02/06-07/89 <0.6 <20 1400+/-90 <4.0 <7.1 <15 SA-MLK-14Fl 02/06-07/89 <0.4 <21 1300+/-93 <3.7 9.9+/-4.1 15+/-8 SA-MLK-3G 1 ( C) 02/06-07/89 <0.4 <19 1200+/-76 <2.7 <5.8 <13 SA-MLK-2F7 03/05-06/89 <0.4 <23 1300+/-92 <4.0 <6.4 <17 SA-MLK-11F3 03/06-07/89 <0.4 35+/-14 1400+/-90 <3.3 <7.9 <12 SA-MLK-14Fl 03/06-07/89 <0.4 <18 1400+/-80 <2.7 <7.0 <12 SA-MLK-3Gl (C) 03/06-07/89 <0.4 <25 1300+/-82 <3.3 <7.4 14+/-7 SA-MLK-2F7 04/02-03/89 <0.3 "<16 1300+/-70 <2.2 <6.7 <11 SA-MLK-11F3 04/03-04/89 <0.3 <25 1300+/-94 <3.8 <7.3 <15 SA-MLK-14Fl 04/03-04/89 <0.4 <20 1300+/-77 <3.9 <8.2 <12 SA-MLK-3G 1 ( C) 04/03-04/89 <0.4 <22 1300+/-82 <2.9 <8.2 <12 SA-MLK-2F7 04/16-17/89 <0.5 <21 1200+/-79 <4.0 <7.7 <13 SA-MLK-11F3 04/17-18/89 <0.6 <23 1300+/-77 <3.2 <6.5 <12 SA-MLK-14Fl 04/17-18/89 <0.4 <21 1400+/-90 <3.5 <7.0 16+/-7 SA-MLK-3Gl (C) 04/17-18/89 <0.4 <24 1300+/-92 <4.1 <6.0 <14 SA-MLK-2F7 05/07-08/89 <0.5 <22 1300+/-80 <3.1 <7.9 <13 SA-MLK-11F3 05/08-09/89 <0.5 <19 1300+/-78 <2.7 <7.2 <11 SA-MLK-14Fl 05/07-08/89 <0.4 <21 1400+/-90 <3.4 <6.2 <15 SA-MLK-3Gl (C) 05/07-08/89 <0.4 <21 1300+/-94 <5.2 <7.8 <14 SA-MLK-2F7 05/21-22/89 <0.4 <21 1300+/-90 <3.6 <5.9 <11 SA-MLK-11F3 05/21-22/89 <0.4 <30 1400+/-95 <3.5 <8.0 <12 SA-MLK-14Fl 05/21-22/89 <0.4 <18 1300+/-78 <2.7 <6.7 <13 SA-MLK-3G 1 ( C) 05/21-22/89 <0.4 <24 1200+/-78 <3.6 <7.9 <12 SA-MLK-2F7 06/04-05/89 <0.4 <27 1300+/-79 <3.5 <6.4 <11 SA-MLK-11F3 06/04-05/89 <0.6 <24 1300+/-94 <3.5 <6.9 <15 SA-MLK-14Fl 06/04-05/89 <0.6 <25 1200+/-75 <3.1 <6.9 <14 SA-MLK-3Gl (C) 06/04-05/89 <0.5 <21 1300+/-80 <4.2 <8.2 <15 SA-MLK-2F7 06/18-19/89 <0.4 <21 1300+/-77 <3.2 <7.3 <11 SA-MLK-11F3 06/18-19/89 <0.4 <25 1400+/-94 <3.7 <6.8 <15 SA-MLK-14Fl 06/18-19/89 <0.4 <29 1200+/-75 <3.7 <6.5 <13 SA-MLK-3Gl (C) 06/18-20/89 <0.4 <27 1300+/-78 <2.8 <7.7 <15 SA-MLK-2F7 07/02-03/89 <0.4 <23 1400+/-96 <3.9 10+/-4 <15 SA-MLK-11F3 07/02-03/89 <0.6 <22 1400+/-96 <3.5 <7.6 <16 SA-MLK-14Fl 07/02-03/89 <0.5 <23 1400+/-96 <3.9 10+/-4 <15 SA-MLK-3Gl (C) 07/02-03/89 <0.3 <18 1400+/-71 <3.3 <5.7 <9.0 SA-MLK-2F7 07/16-17/89 <0.5 <21 1300+/-93 <4.0 <7.3 <14 SA-MLK-11F3 07/16-17/89 <0.4 <20 1400+/-75 <2.6 <5.3 <11 SA-MLK-14Fl 07 /16-17 /89 <0.4 <22 1400+/-73 <3.4 <5.4 <12 SA-MLK-3Gl (C) 07/16-17/89 <0.3 <28 1400+/-90 <3.4 <7.6 <11 106

• TABLE C-9 (Cont'd) 1989 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of 10- 3 pCitm3 +/- 2 sigma SAMPLING <---------------- GAMMA EMITTERS ---------------->

STATION ID PERIOD I-131 Be-7 K-40 Cs-137 Ra-226 Th-232 SA-MLK-2F7 08/06-07/89 <0.6 <26 1300+/-91 <4.2 <7.1 <12 SA-MLK-11F3 08/07-08/89 <0.3 <20 1400+/-91 <3.4 <6.4 <12 SA-MLK-14Fl 08/07-08/89 <0.3 <15 1200+/-69 <2.9 <6.5 <8.7 SA-MLK-3G 1 ( C) 08/07-08/89 <0.5 <20 1300+/-78 <3.6 <6.8 <9.7 SA-MLK-2F7 08/20-21/89 <0.6 <24 1400+/-95 <4.6 <8.8 <16 SA-MLK-11F3 08/21-22/89 <0.4 <20 1500+/-93 <3.3 <8.5 <12 SA-MLK-14Fl 08/21-22/89 <0.5 <16 1300+/-71 <2.9 <6.2 <15 SA-MLK-3Gl (C) 08/21-22/89 <0.5 <22 1300+/-79 <3.4 <6.8 <11 SA-MLK-2F7 09/04-05/89 <0.5 <27 1300+/-91 <3.9 <7.9 <20 SA-MLK-11F3 09/04-05/89 <0.6 <21 1400+/-89 <3.7 <7.7 <13 SA-MLK-14Fl 09/04-05/89 <0.4 <24 1200+/-69 <2.4 <6.3 <8.7 SA-MLK-3Gl (C) 09/04-05/89 <0.4 <2.7 1300+/-79 <3.8 <7.2 <13 SA-MLK-2F7 09/18-19/89 <0.5 <26 1300+/-92 <4.6 <7.3 <15 SA-MLK-11F3 09/18-19/89 <0.5 <26 1400+/-91 <3.2 <7.8 <15 SA-MLK-14Fl 09/18-19/89 <0.4 <21 1300+/-69 <2.1 <6.1 <8.2 SA-MLK-3G 1 ( C) 09/18-19/89 <0.6 <19 1300+/-80 <3.3 <5.4 <10 SA-MLK-2F7 10/01-02/89 <0.5 <31 1300+/-93 <4.2 <7.7 <14 SA-MLK-11F3 10/02-03/89 <0.4 <24 1300+/-90 <3.8 <6.2 <14 SA-MLK-14Fl 10/02-03/89 <0.4 <24 1300+/-69 <2.7 <5.3 <13 SA-MLK-3G 1 ( C) 10/02-03/89 <0.3 <21 1200+/-76 <2.9 <6.3 <11 SA-MLK-2F7 10/15-16/89 <0.4 <23 1300+/-79 <3.8 <6. 7. <12 SA-MLK-11F3 10/16-17 /89 <0.4 <14 1400+/-72 <2.5 <5.5 <11 SA-MLK-14Fl 10/ 16-17 /89 <0.5 <14 1300+/-65 <2.9 <7.2 <12 SA-MLK-3Gl (C) 10/16-17/89 <0.4 <30 1400+/-88 <3.6 6.7+/-2.9 <10 SA-MLK-2F7 11/05-06/89 <0.6 <19 1300+/-86 <4.6 <5.9 <15 SA-MLK-11F3 11/05-06/89 <0.6 <25 1500+/-91 <2.8 <6.4 <11 SA-MLK-14Fl 11/05-06/89 <0.3 <22 1300+/-71 <2.6 <7.3 <10 SA-MLK-3G 1 ( C) 11/05-06/89 <0.4 <16 1300+/-72 <2.4 <6.6 <9 SA-MLK-2F7 11/19-20/89 <0.4 <26 1300+/-90 <3.9 <7.2 <14 SA-MLK-11F3 11/19-20/89 <0.4 <24 1500+/-93 <3.8 <7.0 <15 SA-MLK-14Fl 11/19-20/89 <0.4 <16 1300+/-70 <2.4 <4.9 <9 SA-MLK-3G 1 ( C) 11/19-20/89 <0.4 <23 1400+/-72 <2.9 <6.0 <9 SA-MLK-2F7 12/03-04/89 <0.3 <7 1300+/-94 <2.3 <3.0 <9 SA-MLK-11F3 12/03-04/89 <0.4 <13 1300+/-88 <1.5 <4.4 <18 SA-MLK-14Fl 12/03-04/89 <0.3 <10 1300+/-97 <1.0 <10 <8 SA-MLK-3G 1 ( C) 12/03-04/89 <0.5 <19 1300+/-94 <1.9 <5.1 <5 AVERAGE 1300+/-140

• lodine-131 results are corrected for decay to midpoint of collection period.

lodine-131 analyzed to a sensitivity of 1.0 pCi/liter.

• • All other ganma emitters searched for were <LLD; typical LLDs are given in Table C-28.

• • • Monthly sample collected during Jan., Feb., March and Dec., when animals are not on pasture.

(C) Control Station

• 107

TABLE C-10 1989 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-2F7 07/02-03/89 <1.1 1.8+/-0.4 SA-MLK-11F3 07/02-03/89 <1.2 <0.9 SA-MLK-14Fl 07/02-03/89 1. 2*+/-0. 5 <0.8 SA-MLK-3Gl 07/02-03/89 <1.1 2.2+/-0.4

{Control)

AVERAGE 1.4+/-1.3

• Sr-89 results are corrected for decay to midpoint of collection period.

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

• 108

TABLE C-11 1989 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma SAMPLING GROSS GROSS STATION ID DATE ALPHA BETA K-40 TRITIUM SA-WWA-2S3 01-09-89 <1.0 5. 7+/-1.0 5.7+/-0.6 <150 SA-WWA-5Dl 01-09-89 <1.2 10+/-1 6.2+/-0.6 <150 SA-WWA-3El (C) 01-09-89 1.1+/-0.9 14+/-1 10+/-1 <150 SA-WWA-2S3 02-14-89 <1.3 8.7+/-1.2 5.5+/-0.6 190+/-100 SA-WWA-5Dl 02-15-89 <1.4 14+/-1 14+/-1 <160 SA-WWA-3El (C) 02-14-89 <1.5 4.7+/-0.9 9.9+/-1.0 <150 SA-WWA-2S3 03-13-89 <1.0 5 .2+/-1.0 5.5+/-0.6 <150 SA-WWA-5Dl 03-13-89 <1.0 14+/-1 16+/-2 <150 SA-WWA-3El (C) 03-13-89 <1.1 9.6+/-1.2 11+/-1 <150 SA-WWA-2S3 . 04-10-89 0.5+/-0.4 6.7+/-1.0 7.4+/-0.7 <160 SA-WWA-5Dl (1) (1) (1) (1) (1)

SA-WWA-3El (C) 04-10-89 1.3+/-0.9 10+/-1 10+/-1 <160 SA-WWA-2S3 05-15-89 <1.0 4.8+/-0.9 4.8+/-0.5 <150 SA-WWA-5Dl SA-WWA-3El (C) 05-15-89 <1.2 9. 7+/-1.2 9.5+/-1.0 <150 SA-WWA-2S3 06-13-89 <1.4 4.5+/-0.8 4.8+/-0.5 <150 SA-WWA-5Dl SA-WWA-3El (C) 06-13-89 <1.7 10+/-1 8.8+/-0.9 <150 SA-WWA-2S3 07-10-89 0.1+/-0.6 4.7+/-009 4.4+/-0.4 <150 SA-WWA-5Dl SA-WWA-3El (C) 07-10-89 0.3+/-0.4 9.1+/-1.2 9.4+/-0.9 <150 SA-WWA-2S3 08-14-89 <1.4 4.6+/-0.9 3.5+/-0.3 <150 SA-WWA-5Dl SA-WWA-3El (C) 08-14-89 <1.1 10+/-1 9.1+/-0.9 250+/-100 SA-WWA-2S3 09-11-89 <1.1 4.3+/-0.9 4.9+/-0.5 <160 SA-WWA-5Dl SA-WWA-3El (C) 09-11-89 <1.2 9.1+/-1.2 8.6+/-0.9 <160 SA-WWA-2S3 10-10-89 1.6+/-1.l 4.6+/-0.9 4.4+/-4.4 170+/-100 SA-WWA-5Dl SA-WWA-3El (C) 10-10-89 <1.2 9.9+/-1.2 8.9+/-0.9 <170 SA-WWA-2S3 11-13-89 <1.4 7 .1+/-1.1 6.2+/-0.6 <140 SA-WWA-5Dl SA-WWA-3El (C) 11-13-89 <1.4 9.5+/-1.2 9.1+/-0.9 <140 SA-WWA-2S3 12-12-89 <2.l 3.6+/-0.9 3.2+/-0.3 <130 SA-WWA-5Dl SA-WWA-3El (C) 12-12-89 <1.8 11+/-1 8.5+/-0.9 <130 AVERAGE SA-WWA-2S3

• 5.4+/-2.6 5.0+/-2.1 SA-WWA-5Dl 13+/-5 12+/-10 SA-WWA-3El (C) 9.7+/-3.8 9.4+/-1.3 GRAND AVERAGE 8.1+/-6.4 7.8+/-6.2

~cl Control Station 1 Station SA-WWA-5Dl was deleted from the Program, effective March 14, 1989

• (see Program Changes section).

109

TABLE C-12 1989 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING DATE I-131

<----- GAMMA EMITTERS K-40 Ra-226 Th-232 SA-WWA-2S3 or-09-89 <34 14+/-3 9.1+/-4.4 SA-WWA-5Dl 01-09-89 <41 48+/-4 .<10 SA-WWA-3El (C) 01-09-89 <33 60+/-5 <6.8 SA-WWA-2S3 02-14-89 <0.4 <29 14+/-3 6.5+/-3.3 SA-WWA-5Dl 02-15-89 <0.4 <41 160+/-7 <9.3 SA-WWA-3El (C) 02-14-89 <0.5 <37 130+/-6 <7.3 SA-WWA-2S3 03-13-89 <0.4 <33 <4.3 <6.l SA-WWA-5Dl 03-13-89 <0.5 <31 <4.7 <7.2 SA-WWA-3El (C) 03-13-89 <0.4 <36 16+/-3 <9.l SA-WWA-2S3 04-10-89 <0.7 <40 <5.1 <8.2 SA-WWA-5Dl (2) (2) (2) (2) (2)

SA-WWA-3El (C) 04-10-89 <0.2 <28 <4.7 <6.5 SA-WWA-2S3 05-15-89 <0.6 <37 13+/-3 <6.8 SA-WWA-5Dl SA-WWA-3El (C) 05-15-89 <0.4 <33 130+/-6 <7.0 SA-WWA-2S3 06-13-89 <0.3 <33 <5.3 <6.4 SA-WWA-5Dl SA-WWA-3El (C) 06-13-89 <0.3 <33 70+/-5 <9.6 SA-WWA-2S3 07-10-89 <0.4 <32 <4.5 <7.0 SA-WWA-5Dl SA-WWA-3El (C) 07-10-89 <0.4 <24 11+/-2 <4.6 SA-WWA-2S3 08-14-89 <0.4 <30 5.6+/-2.5 <5.3 SA-WWA-5Dl SA-WWA-3El (C) 08-14-89 <0.4 <42 93+/-5 <ll SA-WWA-2S3 09-11-89 <0.5 <35 4.6+/-2.3 <7.3 SA-WWA-5Dl SA-WWA-3El (Cf 09-11-89 <0.4 26+/-14 65+/-4 <6.3 SA-WWA-2S3 10-10-89 <0.5 33+/-17 <5.0 <6.9 SA-WWA-5Dl SA-WWA-3El (C). 10-10-89 <0.4 27+/-13 11+/-2 <6.6 SA-WWA-2S3 11-13-89 <0.4 <35 15+/-3 <7.3 SA-WWA-501 SA-WWA-3El (C) 11-13-89 <0.4 <30 19+/-3 <7.l SA-WWA-2S3 12-11-89 <0.4 9.0+/-4 <l.O <l.O SA-WWA-5Dl SA-WWA-3El (C) 12-11-89 <0.3 <7.0 <l.O <l.O AVERAGE SA-WWA-2S3 7.6+/-8.9 SA-WWA-501 70+/-150 SA-WWA-3El (C) 51+/-86 GRAND AVERAGE 34+/-90

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

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

~

c~ control Station 1 Iodine-131 analysis started with the February sample.

2 Station SA-WWA-5Dl was deleted from the Program, effective March 14, 1989 (see Program Changes section).

110

• TABLE C-13 1989 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L

<-- STRONTIUM -->

STATION ID SAMPLING PERIOD Sr-89 Sr-90 SA-WWA-2S3 01-09-89 to 03-13-89 <1.0 <0.6 SA-WWA-5Dl 01-09-89 to 03-13-89 <0.9 <0.5 SA-WWA-3El (C) 01-09-89 to 03-13-89 <0.9 <0.5 SA-WWA-2S3 04-10-89 to 06-13-89 <1.0 <0.6 SA-WWA-5Dl (1) to (1) (1) (1)

SA-WWA-3El (C) 04-10-89 to 06-13-89 <0.9 <0.5 SA-WWA-2S3 07-10-89 to 09-11-89 <1.5 <0.5 SA-WWA-5Dl to SA-WWA"."'"3El (C) 07-10-89 to 09-11-89 <1.3 <0.4 10-10-89 to 12-11-89 <1.4 <0.6 e

SA-WWA-2S3 SA-WWA-501 to SA-WWA-3El (C) 10-10-89 to 12-11-89 <1.2 <0.5

• Sr-89 results are corrected for decay to midpoint of collection period.

(C) Control Station (1) Station SA-WWA-501 was deleted from the Program, effective March 14, 1989 (see Program Changes section).

111

TABLE C-14 1989 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3 SAMPLING GROSS GROSS TYPE PERIOD ALPHA BETA K-40 TRITIUM Raw 01/01-31/89 <1.4 3.4+/-0.8 2.9+/-0.3 <180 Treated 01/01-31/89 <1.5 2.9+/-0.8 2.9+/-0.3 <190 Raw 02/01-28/89 <1.3 3.6+/-0.8 2.1+/-0.2 180+/-100 Treated 02/01-28/89 <1.4 4.0+/-0.8 2.2+/-0.2 <160 Raw 03/01-31/89 3.6+/-1.9 3.5+/-0.8 2.7+/-0.3 <160 Treated 03/01-31/89 o.7+/-0.7 3.4+/-0.8 2.9+/-0.3 *H50**

Raw 04/01-30/89 <1.2 3.4+/-0.8 2.1+/-0.2 <150 Treated 04/01-30/89 <1.2 3.3+/-0.8 2.6+/-0.3 <160

Raw 05/01-31/89 <1.8 3.8+/-0.8 1.6+/-0.2 <160 Treated 05/01-31/89 <1.6 3.2+/-0.7 1.6+/-0.2 <160 e

Raw 06/01-30/89 1. 7+/-0.9 3.9+/-0.8 2.1+/-0.2 <160 Treated 06/01-30/89 1.0+/-0.9 3.0+/-0.8 2.1+/-0.2 <140 Raw 07/01-31/89 <1.2 3.9+/-0.8 2.5+/-0.2 <160 Treated 07/01-31/89 <1.2 4.0+/-0.8 2.6+/-0.2 <150 Raw 08/01-31/89 <1.1 3.8+/-0.8 2.2+/-0.2 <160 Treated 08/01-31/89 1.7+/-1.l 3.7+/-0.8 2.5+/-0.2 <160 Raw 09/01-30/89 <1.2 3.9+/-0.8 2.5+/-0.2 <160 Treated 09/01-30/89 <1.1 3.4+/-0.8 2.5+/-0.2 <170 Raw 10/01-31/89 <1.4 4.6+/-0.9 2.5+/-0.2 150+/-80 Treated 10/01-31/89 <1.4 3.3+/-0.8 2.5+/-0.2 140+/-80 Raw 11/01-30/89 <2.1 3.8+/-0.9 3.3+/-0.3 130+/-80 Treated 11/01-30/89 <2.5 3.2+/-0.8 2.5+/-0.2 <130 Raw 12-/01-31/89 <1.6 2.7+/-0.8 2.5+/-0.2 150+/-80 Treated 12/01-31/89 <1.5 3.3+/-0.8 2.6+/-0.3 <130 Raw 3.7+/-0.9 2.4+/-0.9 Treated 3.4+/-0.7 2.5+/-0.7 GRAND AVERAGE 3.5+/-0.8 2.4+/-0.8 112

TABLE C-15 1989 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3 TYPE SAMPLING PERIOD I-131

<------ GAMMA EMITTERS K-40 Ra-226 Raw 01/01-31/89 <0.4 <31 <4.7 Treated 01/01-31/89 <0.6 <32 <4.2 Raw 02/01-28/89 <0.5 <31 <4.5 Treated 02/01-28/89 <0.5 <32 <4.2 Raw 03/01-31/89 <0.5 <41 ...

<4.7 Treated 03/01-31/89 <0.5 <31 <4.2 Raw 04/01-30/89 <0.7 <39 <5.0 Treated 04/01-30/89 <0.5 <27 <4.9 Raw 05/01-31/89 <0.6 <29 <4.6 Treated 05/01-31/89 <0.3 <39 4.7+/-2.3 Raw 06/01-30/89 <0.7 52+/-14 <3.1 Treated 06/01-30/89 <0.5 <37 <4.9 Raw 07/01-31/89 <0.6 <15 2 .8+/-1.1 Treated 07/01-31/89 <0.4 20+/-12 <3.7 Raw 08/01-31/89 <0.6 <30 <4.2 Treated 08/01-31/89 <0.6 28+/-14 <3.7 Raw 09/01-30/89 <0.6 <27 4.7+/-2.2 Treated 09/01-30/89 <0.5 <23 <4.6 Raw 10/01-31/89 <0.3 <23 <3.9 Treated 10/01-31/89 <0.4 <27 <3.5 Raw 11/01-30/89 <0.5 <17 <3.3 Treated 11/01-30/89 <0.7 <12 <2.5 Raw 12/01-31/89 <0.4 42+/-19 <2.7 Treated 12/01-31/89 <0.3 <24 <3.5

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.

113

TABLE C-16 1989 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3

<-- STRONTIUM -->

TYPE SAMPLING PERIOD Sr-89 Sr-90 Raw 01-01-89 to 03-31-89 <1.1 <0.8 Treated 01-01-89 to 03-31-89 <0.8 0.6+/-0.3 Raw 04-01-89 to 06-30-89 <1.1 <0.8 Treated 04-01-89 to 06-30-89 <0.7 <0.6 Raw 07-01-89 to 09-30-89 <0.6 <0.5 Treated 07-01-89 to 09-30-89 <1.2 <0.8 Raw 10-01-89 to 12-31-89 <1.5 <0.8 Treated 10-01-89 to 12-31-89 <2.0 <1.1

• Sr-89 results are corrected for decay to midpoint of collection period.

114

TABLE C-17 1989 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <---- GAMMA EMITTERS ----->

STATION ID DATE SAMPLE TYPE K-40 Ra-226 Th-232 SA-FPV-3E2 OS-22-89 Asparagus 2100+/-2SO <46 <72 SA-FPV-2Gl (C) 04-17-89 Asparagus 2200+/-190 38+/-1S <73 AVERAGE 2200+/-70 SA-FPL-2F4 07-26-89 cabbage 2600+/-110 <8.S 34+/-9 SA-FPL-4F2 07-31-89 cabbage 1800+/-130 <13 <26 SA-FPL-3HS (C) 07-26-89 cabbage 2000+/-78 9.0+/-3.9 13+/-6 AVERAGE 2100+/-830 24+/-21 SA-FPV-2F4 .08-01-89 Corn 2000+/-220 <2S <67 SA-FPV-14F3 07-2S-89 corn 2300+/-240 <26 <S4 SA-FPV-lGl (C) 07-2S-89 Corn 2SOO+/-l90 <26 <39 SA-FPV-3HS (C) 07-2S-89 Corn 2S00+/-2SO <31 <SS AVERAGE 2300+/-SOO SA-FPV-3E2 07-31-89 Peppers 1S00+/-240 <3S <70 SA-FPV-2F4 08-01-89 Peppers 1S00+/-210 <34 <59 SA-FPV-14F3 08-01-89 Peppers 1600+/-220 <31 <63 SA-FPV-3HS (C) 07-2S-89 Peppers 1300+/-210 24+/-14 <61 AVERAGE 1S00+/-2SO SA-FPV-2F4 08-07-89 Tomatoes 2100+/-54 <2.7 <6.1 SA-FPV-5F2 08-08-89 Tomatoes 2000+/-4S <1.9 <S.7 SA-FPV-14F3 08-01-89 Tomatoes 1700+/-38 <1.8 <4.0 SA-FPV-lGl (C) 07-2S-89 Tomatoes 1800+/-SO <2.6 <6.1 SA-FPV-3HS (C) 07-25-89. Tomatoes 1800+/-50 <2.0 <6.6 AVERAGE 1800+/-300 GRAND AVERAGE 2000+/-740

• All other gamma emitters searched for were <LLD; typical LLDs are given

• in Table C-28.

(C) Control Station 115

TABLE C-18 1989 CONCENTRATIONS OF GAMMA EMITTERS* IN BEEF AND GAME Results in Units of pCi/kg (wet) +/- 2 sigma STATION ID SAMPLING DATE SAMPLE TYPE

<----- GAMMA EMITTERS K-40 Ra-226 Th-232 SA-FPB-3El 12-18-89 Beef (1) 2400+/-240 <13 <32 SA-GAM-llDl 02-12-89 Muskrat 1700+/-170 24+/-13 44+/-22 (Control)

SA-GAM-3El 02-13-89 Muskrat 1900+/-170 23+/-11 <31 AVERAGE Muskrat 1800+/-280 24+/-1 31+/-31

• All other gamma emitters searched for were <LLD~ typical LLDs are given in Table C-28.

(1) No first semi-annual beef samples were obtained.

116

• TABLE C-19 1989 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma STATION ID SAMPLING DATE SAMPLE TYPE

<----------------- GAMMA EMITTERS Be-7 K-40 Cs-137 Ra-226 Th-232 SA-VGT-11F3 10-03-89 Green Chop 1600+/-140 2500+/-270 <15 <41 <72 SA-VGT-3Gl (C) 09-23-89 Green Chop 1200+/-140 4600+/-370 <18 <46 <73 AVERAGE 1400+/-600 3600 3000 SA-VGT-4D2 10-15-89 Feed corn <150 3100+/-270 <14 <37 <57

.....i SA-VGT-2F7 10-15-89 Corn Silage 960+/-200 5900+/-540 <29 <65 <100 SA-VGT-11F3 09-01-89 Corn Silage <100 3100+/-200 <12 <25 <38 SA-VGT-14Fl 10-01-89 Corn Silage 520+/-77 2000+/-180 <13 <28 <59 SA-VGT-3Gl (C) 09-29-89 Corn Silage 360+/-87 2700+/-260 <14 39+/-18 <62 AVERAGE 420+/-690 3400+/-300 SA-VGT-3El 10-17-89 Soybeans <200 12000+/-380 19+/-8 42+/-16 <55 SA-VGT-2F7 11-19-89 Soybeans <140 14000+/-450 <50 <35 85+/-34 SA-VGT-11F3 12-02-89 Soybeans <150 15000+/-470 <78 <33 73+/-42 SA-VGT-3Gl (C) 11-18-89 Soybeans <130 15000+/-490 <46 54+/-18 <59 AVERAGE 11000+/-2800 GRAND AVERAGE 7300+/-1000

• All other gamma emitters searched for were <LLD1 typical LLDs are given in Table C-28.

(C) Control Station

TABLE C-20 1989 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SOIL Results in Units of pCi/kg (dry) +/- 2 sigma STATION ID SAMPLING DATE Sr-90

<------------ GAMMA EMITTERS K-40 Cs-137 Ra-226 Th-232 SA-SOL-6Sl 09-20-89 <24 10000+/-370 110+/-12 510+/-30 660+/-56 SA-SOL-lODl 09-20-89 120+/-13 8700+/-410 470+/-27 1000+/-46 960+/-78 SA-SOL-16El 09-20-89 58+/-10 13000+/-480 180+/-21 1200+/-52 1200+/-87

..... SA-SOL-lFl 09-20-89 110+/-11 3800+/-300 1300+/-40 300+/-30 290+/-50 CX>

SA-SOL-2F4 09-19-89 69+/-10 7300+/-360 310+/-22 870+/-42 770+/-66 SA-SOL-2F7 09-21-89 67+/-11 8900+/-350 300+/-19 1100+/-40 880+/-60 SA-SOL-5Fl 09-19-89 150+/-13 6900+/-380 1100+/-37 760+/-40 730+/-70 SA-SOL-11F3 09-20-89 51+/-10 12000+/-400 160+/-16 1100+/-41 1100+/-65 SA-SOL-14Fl 09-20-89 51+/-11 13000+/-530 1~0+/-19 1000+/-46 950+/-85 SA-SOL-3Gl (C) 09-19-89 21+/-9 7700+/-380 190+/-18 750+/-38 710+/-69 AVERAGE 72+/-84 9100+/-5900 430+/-850 860+/-570 820+/-510

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.

(C) Control Station

TABLE C-21 1989 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING

<----------------------------------- STATION ID SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (control) 01-09-89 1.9+/-0.9 o.9+/-0.6 2 .0+/-1.0 1.5+/-0.9 2.0+/-0.9 1.7+/-.94 02-08-89 <1.4 <1.4 <1.4 <1.4 <1.4 03-13-89 <1.6 <1.8 <1.6 <1.6 <1.7

\D 04-05-89 2.2+/-1.1 <l.O 1.0+/-0.8 1.4+/-0.9 1. 3+/-1.0 1.4+/-.98 05-08-89 <0.8 0.8+/-0.7 <0.8 <0.7 <0.8 06-12-89 <1.7 <1.6 <1.7 <L6 <1.6 07-10-89 <1.7 <1.7 <1.4 <2.2 <2.0 08-07-89 <1.6 <1.3 <1.6 <2.2 <1.6 09-05-89 <1.9 <2.1 <2.6 <2.0 <1.9 10-06-89 7.7+/-4 2.8+/-2 <1.6 3.5+/-2 3.1+/-2 11-10-89 <2.3 <2.2 <2.1 <2.1 <2.1 12-11-89 <2.8 <3.0 <4.2 <3.3 <3.2

TABLE C-22 1989 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING

<----------------------------------- STATION ID SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El sA~swA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-09-89 80+/-9 62+/-8 130+/-12 70+/-8 58+/-7 80+/-58 02-08-89 68+/-8 42+/-6 110+/-11 36+/-5 49+/-6 61+/-60 03-13-89 99+/-10 85+/-9 130+/-12 47+/-6 66+/-7 86+/-63 04-05-89 28+/-4 24+/-4 46+/-6 12+/-3 23+/-4 27+/-25 05-08-89 9.9+/-3.1 11+/-3 24+/-4 <3.4 6.0+/-2.7 11+/-15 06-12-89 45+/-6 22+/-4 35+/-5 3.7+/-2.4 16+/-4 24+/-29

~

0 07-10-89 22+/-4 19+/-4 37+/-6 5.9+/-2.8 7.8+/-3.0 18+/-23 08-07-89 48+/-6 36+/-5 65+/-8 18+/-4 27+/-4 39+/-34 09-05-89 29+/-5 74+/-8 100+/-11 41+/-6 52+/-7 59+/-51 10-06-89 54+/-7 55+/-7 60+/-7 15+/-3 21+/-4 41+/-39 11-10-89 49+/-7 41+/-6 56+/-7 21+/-4 23+/-4 38+/-28 12-11-89 71+/-8 77+/-9 110+/-11 43+/-6 49+/-6 70+/-48 AVERAGE 50+/-52 46+/-50 76+/-77 26+/-42 33+/-41 GRAND AVERAGE 46+/-62

TABLE C-23 1989 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L +/- 2 sigma

<----------------------------------- STATION ID SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE SAMPLING PERIOD (Control) 01-09-89 to 1000+/-110 <150 160+/-90 <150 <150 03-13-89 04-05-89

...... to 170+/-90 <150 190+/-90 180+/-100 <160 170+/-50

~

...... 06-12-89 07-10-89 to <160 <160 <160 170+/-100 <160 09-05-89 10-06-89 to 1600+/-110 190+/-80 <140 <120 180+/-80 440+/-1900 12-11-89 AVERAGE 730+/-1400 160+/-160 160+/-150 GRAND AVERAGE 280+/-710

TABLE C-24 1989 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN SURFACE WATER Results in Units of 10- 3 pCi/L +/- 2 sigma SAMPLING <.------------------------------ GAMMA EMITTERS -------------------------------->

STATION ID DATE I-131 Be-7 K-40 Co-58 Co-60 Ra-226 Th-232 SA-SWA-llAl 01/04/89 - <11 120+/-21 2.6+/-1 <2.0 <4.7 <6.4 SA-SWA-12Cl (C) 01/09/89 - <15 73+/-20 <1.6 <2.4 . <5 .1 <6.6 SA-SWA-7El 01/09/89 - <14 130+/-25 <2.2 <2.1 <4.5 <6.7 SA-SWA-1F2 SA-SWA-16Fl 01/09/89 - <13 56+/-18 ( 1. 7 ( 1. 7 <4.2 <7.0 01/09/89 - <18 88+/-23 <1. 9 2. 7+/-1.5 <4.7 <7.1 SA-SWA-llAl 02/08/89 <0.6 <28 110+/-22 <2.0 <2.5 <4.2 SA-SWA-12Cl (C) 02/08/89 <1.0 <12 <10 64+/-20 <1. 9 ( 1. 5 <5.0 <10 SA-SWA-7El 02/08/89 <0.6 <13 120+/-21 <1. 7 <1. 9 <4.3 SA-SWA-1F2 02/08/89 <0.8 <13 36+/-16 <6.4

<1. 7 <1. 9 <4.6 <5.8 SA-SWA-16Fl 02/08/89 <0.7 <16 61+/-21 <1.9 <1. 9 14+/-2.9 <9.5 SA-SWA-llAl 03/13/89 <0.6 <13 100+/-26 <2.2 <2.3 4.1+/-2.4 SA-SWA-12Cl (C) 03/13/89 <0.4 <14 55+/-19 <8.7

...... <1.4 <2.3 4.9+/-4.1 <7.2 SA-SWA-7El 03/13/89 <0.4 <13 140+/-20 <1.2 <1. 5 <3.2 I\)

SA-SWA-1F2 03/13/89 <0.3 <12 <6.9 I\) 43+/-18 <1. 7 <2.2 <3.8 <5.6 SA-SWA-16Fl 03/13/89 <0.5 <12 46+/-7.0 <1.6 <1.4 <0.4 <6.8 SA-SWA-llAl 04/05/89 <0.6 <18 29+/-16 <1.6 <1. 7 4.0+/-2.4 SA-SWA-12Cl (C) 04/05/89 <0.7 <20 <32 <5.7

<2.3 <2.3 <4.6 <6.5 SA-SWA-7El 04/05/89 <0.5 <18 74+/-20 <2.3 <3.1 <4.6 SA-SWA-1F2 04/05/89 <0.8 <13 <7.6 30+/-14 <2.1 <2.2 <4.5 6.3+/-3.6 SA-SWA-16Fl 04/05/89 <0.7 <9. 7 <26 <1.3 <1.2 <3.0 <5.2 SA-SWA-llAl 05/08/89 <0.5 <12 <28 <1.6. ( 1. 9 <4.3 SA-SWA-12Cl (C) 05/08/89 <0.5 <16 <33 <6.6

<1. 5 <2.0 <4.1 <6.9 SA-SWA-7El 05/08/89 <0.6 <14 45+/-20 <2.2 <2.2 4.6+/-2.4 SA-SWA-1F2 05/08/89 <0.6 <16 <35 <9.2

<1.4 <2.0 <4.3 5.2+/-3 SA-SWA-16Fl 05/08/89 <0.3 <12 24+/-14 <1. 3 ( 1.1 <3.5 <4.1 SA-SWA-llAl 06/12/89 <0.6 <13 56+/-21 <1.9 <2.7 <4.7 <8.5 SA-SWA-12Cl (C) 06/12/89 <0.6 <17 <29 <2.0 <1.6 <4.4 <6.2 SA-SWA-7El 06/12/89 <0.3 <18 45+/-17 <1.6 <1.8 <4.8 <6.5 SA-SWA-1F2 06/12/89 <0.5 <13 <31 <1.4 <1.6 <4.1 <6.8 SA-SWA-16Fl 06/12/89 <0.7 <11 <31 ( 1. 7 <1. 7 <4.1 4.8+/-2.5

• TABLE C-24 1989 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN SURFACE WATER Results in Units of 10- 3 pCl/L +/- 2 sigma SAMPLING <------------------------------ GAMMA EMITTERS -------------------------------->

STATION ID DATE 1-131 Be-7 K-40 Co-58 Co-60 Ra-226 Th-232 SA-SWA-11A1 07/10/89 <0.5 <16 45+/-21 <2.0 <1.8 <4.4 <9. 2 SA-SWA-12C1 ( C) 07/10/89 <0.6 <20 <36 <1. 9 <2.1 <4.0 <7.9 SA-SWA-7El 07/10/89 <0.4 <15 <42 <2.2 <2.8 <4.6 <7.4 SA-SWA-1F2 07/10/89 <0.5 <13 <40 <2.0 <2.1 <4.6 <10 SA-SWA-16Fl 07/10/89 <0.6 <19 <33 <2.1 <2.0 <4.8 <6.9 SA-SWA-11Al 08/07/89 <0.4 <16 <32 <1. 5 <1. 7 <4.0 <7.8 SA-SWA-12C1 (C) 08/07/89 <0.4 <14 <39 <1. 9 <2.5 <4.2 <9.5 SA-SWA-7E1 08/07/89 <0.3 <12 67+/-19 <1. 5 <1. 7 <4.6 <7.1 SA-SWA-1F2 08/07/89 <0.5 <13 <38 <1.8 <2.1 <4.5 <8.1 SA-SWA-16F1 08/07/89 <0.6 <20 <37 <2.1 <2.7 5.5+/-2.4 <8.5 SA-SWA-11A1 09/05/89 <0.8 <15 79+/-18 <1.6 <1. 9 <4.4 <5.5

..... SA-SWA-12Cl (C) 09/05/89 <0.5 <13 91+/-23 <2.1 <2.8 <4.8 <7.2 tJ SA-SWA-7E1 09/05/89 <0.5 <14 120+/-24 <2.1 <2.6 <4.1 <7.9 w SA-SWA-1F2 09/05/89 <0.4 <9. 7 67+/-15 <1.4 <1. 9 <5.6 <5.0 SA-SWA-16F1 09/05/89 <0.6 <13 65+/-17 <1. 5 <1. 5 <4.8 <5.8 SA-SWA-11A1 10/06/89 <0.4 13+/-7 97+/-21 <1.8 <1.8 <4.9 <5.6 SA-SWA-12C1 (C) 10/06/89 <0.7 <10 54+/-15 <1.4 <1.8 <3.2 <4.4 SA-SWA-7E1 10/06/89 <0.7 <14 58+/-17 <2.1 <1. 7 <4.0 <6.2 SA-SWA-1F2 10/06/89 <0.7 <13 <36 <2.4 <2.1 <4.4 <7.5 SA-SWA-16F1 10/06/89 <0.8 <13 <29 ( 1. 7 <2.0 <4.7 <6.9 SA-SWA-11A1 11/10/89 <0.7 <14 62+/-15 <1. 5 <1. 7 <3.8 <5.8 SA-SWA-12Cl (C) 11/10/89 <0.7 <13 52+/-16 <1. 5 <1. 7 <4.2 <6.0 SA-SWA-7El 11/10/89 <1.0 <12 <31 <3.0 <2.0 <3.7 <6.7 SA-SWA-1F2 11/10/89 <0.5 <13 <29 <1.6 <1.6 <3.9 <5.4 SA-SWA-16Fl 11/10/89 <0.9 <12 34+/-11 <1.1 <1.4 <5.2 <4.7 SA-SWA- llAl 12/11/89 <0.3 <9.3 110+/-26 <0.7 <1. 2 <4.1 <4.2 SA-SWA-12Cl (C) 12/11/89 <0.4 <8.9 99+/-26 <0.5 <1.6 <2.9 <5.8 SA-SWA-7El 12/11/89 <0.3 <8.7 150+/-26 <1. 3 <1. 7 <2.8 <4.3 SA-SWA-1F2 12/11/89 <0.3 <14 60+/-15 <1. 5 <1. 3 <3.4 <6.6 SA-SWA-16F1 12/ 11/89 <0.3 <10 62+/-16 <1. 2 <1. 3 <4.7 6+/-2.4 AVERAGE - - 60+/-65

• lodine-131 results are corrected for decay to midpoint of collection period.

Iodine-131 analyzed to a sensitivity of 1.0 pCi/liter. Starting 2/89

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.

(C) Control Station

TABLE C-25 1989 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90, TRITIUM AND GAMMA EMITTERS** IN EDIBLE FISH Results in Units of pCi/kg (wet) +/- 2 sigma (Except for strontium analyses which are in pCi/kg (dry)

SAMPLING STRONTIUM (BONES) TRITIUM (FLESH) < GAMMA EMITTERS (FLESH) >

STATION ID PERIOD sr-89 sr-90 AQUEOUS FRACTION K-40 Cs-137 Ra-226 SA-ESF-llAl 04/21-24/89 <50 280+/-17 <1000 2600+/-230 <15 43+/-15 SA-ESF-12Cl (C) 04/21-22/89 <49 330+/-18* <1000 2400+/-200 <13 <25 SA-ESF-7El 04/21-22/89 <43 290+/-15 <1000 3100+/-230 16+/-9 23+/-12

...... AVERAGE 300+/-47 2700+/-640 30+/-20 l&:oo SA-ESF-llAl 09/27-28/89 <36 <25 <1000 3100+/-220 <11 <22 SA-ESF-12Cl (C) 09/27-28/89 <36 45+/-11 <1000 3500+/-190 <14 19+/-io SA-ESF-7El 09/27-28/89 <35 <21 <1000 3300+/-250 <12 24+/-11 AVERAGE 3300+/-360 22+/-5 GRAND AVERAGE 160+/-300 3000+/-840 26+/-17

• Sr-89 results are corrected for decay to sample stop date.

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.

• • • Tritium results by Controls for Environmental Pollution, Inc.

(C) Control station

TABLE C-26 1989 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90, TRITIUM AND GAMMA EMITTERS** IN BLUE CRABS Results in Units of pCi/kg (wet) +/- 2 sigma

<----------- STRONTIUM ----------> *** GAMMA SAMPLING <--- FLESH ---> <--- SHELL ---> TRITIUM (FLESH) EMITTER STATION ID DATE Sr-89 Sr-90 Sr-89 Sr-90 AQUEOUS FRACTION K-40 pCi/kg (dry) ~

SA-ECH-llAl 06-23-89 <36 <17 <57 310+/-17 <1000 2200+/-210 SA-ECH-12Cl (C) 06-23-89 <35 <17 <87 540+/-25 <1000 1800+/-180 l'J AVERAGE 420+/-270 2000+/-460 U1 SA-ECH-llAl 09/27-28/89 <100 <43 58+/-24 200+/-15 <1000 2700+/-230 SA-ECH-12Cl (C) 09/27-28/89 <98 <41 82+/-22 510+/-19 <1000 2100+/-180 AVERAGE 70+/-34 360+/-360 2400+/-690 GRAND AVERAGE 71+/-31 390+/-320 2200+/-250

• sr-89 results are corrected for decay to sample stop date.

• • All other gamma emitters searched for were <LLD1 typical LLDs are given in Table C-28.

• • • Tritium results by controls for Environmental Pollution, Inc.

(C) Control Station

TABLE C-27 1989 CONCENTRATIONS

. OF STRONTIUM-90 AND GAMMA EMITTERS*

. IN SEDIMENT Results in Units of pCi/kg (dry) :1: 2 sigma SAMPLING <----------------------------------- GAMMA EMITTERS ----------------------------------->

STATION ID DATE Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-137 Ra-226 Th-232 SA-ESS-11A1 06-07-89 <22 <150 3700+/-260 <19 50+/-13 42+/-14 14:1:8 270+/-25 310+/-46 SA-ESS-15Al 06-07-89 <23 200+/-100 5500+/-310 20+/-10 45+/-13 32+/-10 21+/-11 560+/-34 520+/-58 SA-ESS-16Al 06-07-89 <27 <200 9900+/-470 <22 <27 38+/-19 <23 700+/-40 860+/-80 SA-ESS-12C1 (C) 06-07-89 <24 <190 13000:1:500 <26 <23 41:1:20 <21 630+/-36 700+/-68 SA-ESS-7E1 06-07-89 <22 <170 9900+/-470 <27 <25 53+/-20 43+/-16 660+/-42 650+/-79 SA-ESS-16F1 06-07-89 <28 440+/-140 13000+/-570 <25 39+/-16 <40 24+/-13 460+/-41 740+/-83 O"I AVERAGE 9200+/-7700 41+/-14 24+/-20 550:1:320 630:1:380 SA-ESS-11Al 10-30-89 <19 <120 7400+/-330 <18 <20 <52 65:1:11 390+/-29 520+/-52 SA-ESS-15Al 10-30-89 <20 <190 7000+/-330 <16 <29 39+/-16 20:1:11 410+/-27 480+/-49 SA-ESS-16A1 10-30-89 <23 <210 8100:1:350 <18 35+/-14 31+/-15 26+/-10 630+/-34 460+/-54 SA-ESS-12Cl (C) 10-30-89 <19 <150 14000:1:450 <21 <25 <49 <18 580:1:35 590:1:57 SA-ESS-7El 10-30-89 <19 <180 12000:1:410 <17 <23 64+/-16 51+/-11 800+/-36 760:1:60 SA-ESS-16F1 10-30-89 <18 <320 16000:1:600 25:1:14 . <35 <45 <27 640+/-44 790+/-80 AVERAGE 11000+/-7600 47+/-23 35:1:38 580+/-310 600+/-290 GRAND AVERAGE 10000:1:7500 44+/-22 29+/-36 560+/-300 620+/-270

• All other ganma emitters searched for were <LLD: typical LLDs are given in Table C-28.

(C) Control Station

TABLE C-28 1989 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <------------AIR------------> <-------WATER-------> <--------MILK------->

IODINE PARTICULATES GAMMA SCAN IODINE GAMMA SCAN IODINE ACTIVITY: 10-3 pCi/m3 10-3 pCi/M3 pCi/L pCi/L pCi/L pCi/L GEOMETRY: 100 ML 13 FILTERS 3.5 LITER 100 ML 3.5 LITER 100 ML COUNT TIME: 120 MINS 1000 MINS 100 MINS 1000 MINS 500 MINS 1000 MINS DELAY TO COUNT: 2 DAYS 5 DAYS 7 DAYS 3 DAYS 2 DAYS 2 DAYS NUCLIDES BE-7 6.8 15 22 NA-22 0.45 11 4.5 K-40 7 .1 35 120 CR-51 2.9 16 22 MN-54 0.32 1. 7 3.4 co-58 0.33 1.6 2.9 FE-59 0.79 3.7 7.2 C0-60 0.36 2.1 4.0 ZN-65 0.69 3.9 8.6 NB-95 0.49 3 .1 ZR-95 0.44 5.7 ZRNB-95 3 M0-99 550 200 41 RU-103 0.33 1.6 2.5 RU-106 2.9 14 28 AG-100m 0.55 2.0 3.4 SB-125 0.77 4.0 8.2 TE-129m 120 62 99 1-131 13.0 0.98 3.8 0.60 3.2 0.42 TE-132 41 13 3.9 BA-133 3.7 CS-134 0.39 1.8 3.0 CS-136 0.56 2.9 3.3 CS-137 0.28 1.6 3.2 BA-140 2.2 LA-140 1 BALA-140 11 11 CE-141 0.31 2.3 3.9 CE-144 1. 1 9.2 17 RA-226 0.87 7.4 6.6 TH-232 1.2 7 .1 12

• 127

I TABLE C-28 (cont'd) 1989 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <------FOOD PRODUCTS-------> FODDER & BEEF FISH SEDIMENT GREEN CHOP & GAME SHELLFISH & SOIL ACTIVITY pCi/KG WET pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg DRY GEOMETRY: 100 ml 400 ml 400 ml 400 ml 400 ml 100 ml COUNT TIME: 1000 MINS 1000 MINS 1000 MINS 1000 MINS 1000 MINS 1000 MINS DELAY TO COUNT: 10 DAYS 3 DAYS 3 DAYS 10 DAYS 10 DAYS 30 DAYS NUCLIDES BE-7 0.99 96 96 84 84 200 NA-22 2.1 14 14 13 13 27 IC-40 32 84 84 84 84 640 CR-S1 9.2 83 83 78 78 220 MN-S4 1.2 13 13 11 11 20 CO-S8 1.8 12 12 11 11 23 FE-S9 3.6 26. 26 24 24 S1 C0-60 2.3 16 16 1S 1S 30 ZN-6S 3.6 30 30 26 26 42 NB-9S 2.0 12 12 11 11 36 ZR-9S 2.2 24 24 19 19 43 ZRND-9S M0-99 96 320 320 S40 S40 290000 RU-103 1.0 9.4 9.4 9.2 9.2 22 RU-106 12 100 100 82 82 180 AG-110m 2.2 22 22 9.S 9.S 32 SB-12S 2.8 26 26 22 22 43 TE-129m 4.7 460 460 400 400 920 1-131 2 1S 1S 19 19 220 TE-132 4.4 22 22 SS SS 11000 BA-133 CS-134 0.96 10 10 8.3 8.3 14 CS-136 1.S 16 16 16 16 86 CS-137 1.4 22 22 1S 1S 22 BA-140 6.0 49 49 so so 270 LA-140 2.2 19 19 20 20 97 BALA-140 CE-141 1.0 13 13 11 11 39 CE-144 4.2 46 46 49 49 88 RA-226 2.3 27 27 2S 2S 46 TH-232 6.1 S3 S3 41 41 122 128

6ZT SilfficmraOHcl '1VOLLX'1VNV L!IO SISclON.~S a XICIN![cicIV

IAPPENDIX DI SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by the PSE&G Research and Testing Laboratory and contract laboratories for analyzing the 1989 Artificial Island Radiological Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB* ANALYTICAL PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Air Particulates ******************************* 1"33 PSE&G Water **********************************.******* 135 GROSS BETA PSE&G Air Particulates ******************************* 136 PSE&G Water ***** ************************************* 138

• PSE&G POTASSIUM-40 Water * ***************************************** 139 TRITIUM PSE&G Water * ***************************************** 140 CEP Aqueous Fraction of Fish and Crab ************** 141 IODINE-131 PSE&G Filtered Air .................................. . 142 PSE&G Raw Milk . ....*............*....*.......*......* 143 STRONTIUM-89 AND STRONTIUM-90 PSE&G Air Particulates ******************************* 144 PSE&G Raw Milk ...*.................*...............*. 147 PSE&G Water * ***************************************** 150 PSE&G Vegetation, Meat, Crab Shells and Aquatic Samples ............................. . 153 PSE&G Bone and Shell ********************************* 156 PSE&G Soil and Sediment ****************************** 159 PSE&G Samples for Stable Strontium ******************* 162 131

SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd)

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY PSE&G Air Particulates ******************************* 164 PSE&G Raw Milk ..********.******.***.******.***.***..* 165 PSE&G Water ****************************************** 166 PSE&G Solids (combined procedures) ******************* 167 ENVIRONMENTAL DOSIMETRY TI Thermoluminescent Dosimeters ********** ********** 168

• PSE&G - PSE&G Research and Testing Laboratory CEP - Controls for Environmental Pollution, Inc.

TI - Teledyne Isotopes 132

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an Arn-241 air filter geometry alpha counting standard.

The specific alpha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.

calculation of Gross Alpha Activity:

Air flow is corrected first by using the following equations:

p = (B-V)/29.92 p = Pressure correction factor B = Time-averaged barometric pressure during sampling period, "Hg v = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°F, "Hg V = F*P*0.946*0.0283 E F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60°F.to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %

efficiency/100) v= Corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows:

Result (pCi/m3 ) = (G-B)/T G = Sample gross counts B = Background counts (from blank filter)

T = count time of sample and blank, mins.

E = Fractional Arn-241 counting efficiency v = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 133

2-sigma error (pCi/m3 ) = (l.96*(G+B)l/2 )*A (G-B)

A = Gross alpha activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter) calculation of lower limit of detection:

A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.

LLD(pCi/m 3 ) = 4.66 * (B)l/2 (2.22)*(E)*(V)*(T)

B = Background counts (from blank filter)

E = Fractional Am-241 counting efficiency v = Corrected air flow of sample, m3 T = Count time of blank, mins.

134

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF WATER SAMPLES Water samples require pretreatment of all suspended material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample filtrate. The combined sample is then neutralized with dilute ammonium hydroxide. From this point, both sample and blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to so 0 c in order to help precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period,~, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted on a stainless steel planchet. The sample is then alpha-counted for the appropriate time on a low background gas proportional counter, along with a U-238 source of the same r geometry. The blank is treated in the same manner as the sample.

calculation Of Gross Alpha Activity:

Result (pCi/L) = (G-B)/T (2.22)*(E)*(V)*(S)

G = Sample gross counts B = Background counts (from blank sample)

T = count time of sample and blank E = Fractional counting efficiency from U-238 source v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = (l.96*(G+B) 1 / 2 )*A (G-B)

A= Gross alpha activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)

• 135

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an Sr-90 air filter geometry beta counting standard.

The gross beta activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.

calculation of Gross Beta Activity:

Air flow is corrected first by using the following equations:

P = (B-V)/29.92 P = Pressure correction factor B = Time-averaged barometric pressure during sampling period,

- "Hg V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°F, "Hg V = F*P*0.946*0.0283 E F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %

efficiency/100)

V = Corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows:

Result (pCi/m3 ) = (G-B)/T (2.22)*(E)*(V) G = Sample gross counts B = Background counts (from blank filter)

T = Count time of sample and blank, mins.

E = Fractional Sr-90 counting efficiency V = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 136

2-sigma error (pCi/rn 3 ) = (l.96*(G+B) 1 /2)*A (G-B)

A = Gross beta activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter) calculation of lower limit of detection:

A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.

LLD(pCi/m 3 ) = 4.66 * (B)l/ 2 (2.22)*(E)*(V)*(T)

B = Background counts (from blank filter)

E = Fractional Sr-90 counting efficiency v= Corrected air flow of sample, m3 T = Count time of blank, rnins.

137

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a l.O liter portion is removed from the potable, rain or well water container and 250ml taken from each surface water.

A deionized water blank is prepared for each different volume of sample (e.g.

1.0 liter blank for 1.0 liter samples and 250ml for 250ml samples). All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml. At that point, the samples and blanks are transferred to tared stainless steel ribbed planchets and evaporated to dryness under an infrared heat lamp. They are subsequently cooled in a desiccator, weighed and counted on a low background gas proportional counter along with an Sr-90 source of the same geometry.

calculation of Gross Beta Activity:

Result (pCi/L) = (G-B)/T (2.22)*CE)*V)*CS)

G = Sample gross counts B = Background counts (from blank sample)

T = Count time of sample and blank E = Fractional counting efficiency from Sr-90 source v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = (l.96*(G+B) 112 )*A (G-B)

A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank sample) 138

• SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR POTASSIUM 40 A 60 ml aliquot of water is acidified to pH <2 with concentrated nitric acid and then analyzed for potassium by the following Atomic Absorption Spectrophotometry method: potassium standards of known concentration (similar to that of the unknowns) are first prepared. An aliquot of each sample and standard is pipetted into stoppered flasks. In addition, a duplicate sample, ERA standard and blank water sample are likewise pipetted into their respective flasks. A solution consisting of 4% sodium is diluted 1:1 with water and then added to all the flasks. Depending on the AA instrument used, a calibration curve is prepared from the standards after which the samples are then run. If the absorbance of any sample is higher than the upper standard used, the sample is then either diluted and re-run, the burner head turned 90°, a more concentrated standard added,,to the"'

calibration curve or a less sensitive wavelength used.

The results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program.

calculation of K-40 Activity:

K-40 Activity (pCi/L) = o.BS*C a.es = Proportionality constant for converting ppm to pCi/L c = Potassium concentration, ppm 139

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing Bml of sample, lOml of Instagel, and o.1m1-o.2m1 of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Bml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted.

Activity is computed as follows:

A (pCi/L) = (G-B)*(lOOO) 2.22*(E)*(V)*(T)

A = Activity B = Background count of sample G = Gross count of sample E = counting Efficiency v = Aliquot volume (ml)

T = Count time (min) 2.22 = DPM/pCi 1000 = Number of ml per L Efficiency (E) is computed as follows:

E = (N)*(D)

A' N = Net CPM of spiked sample D = Decay factor of spike A' = DPM of sp1ke N is determined as follows:

N = C-(G/T)

C = CPM of spiked sample G = Gross counts of sample T = count time (min)

The associated error is expressed at 95% confidence limit, as follows:

l.96*(G/T2 +B/T2 ) 1 / 2 *(1000) 2.22*(V)*(E) samples are designated LLD if the activity is less than the following value:

LLD (pCi/L) = (4.66)*(B) 1 / 2 *(1000) 2.22*(V)*(E)*(T) 140

SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL POLLUTION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliquot of fish or crab flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation.

Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear Corporation).

The resultant mixture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approximately 30 percent, when counted on a Beckman LS-100 Liquid Scintillation Spectrometer.

The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted.

The counting efficiency is determined from these standards which are equal in activity but vary in the amount of quenching. All samples are counted for 500 minutes each *

• 141

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF AIR IODINE Approximately 300m 3 of air is drawn through a 50ml bed of triethylenediamine (TEDA)-impregnated charcoal granules at a rate which closely corresponds to the breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing 50ml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.

Calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/m 3 ) = N*D = R (2.22)*CE)*CA)*(T)*CV)

N = Net counts under photopeak D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, rnins.

V = Sample volume, rn 3 2.22 =No. of*dprn per pCi 2-sigma error (pCi/rn 3 ) = l.96*(GC+Bc) 1 12 *R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD {pCi/rn 3 ) = 4.66*(Bc) 1 / 2 *D (2.22)*CE)*CA)*(T)*(V) 142

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF RAW MILK FOR IODINE-131 Stable iodine carrier is equilibrated in a 4-liter volume of raw milk before two separate 50ml batches of anion exchange resin are introduced to extract iodine. After each batch has been stirred in the milk for an appropriate time, both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick. The can is hermetically sealed and then counted on a gamma detector.

calculation of I-131 Activity:

I-131 Results (pCi/L) = (G-B)/T*(l.05)*(H)

(2.22)*(E)*(V)*(Y)

G = Sample gross counts B = Background counts (from blank sample)

T = Count time of sample and blank E = Eo*EXP(-~*M) = efficiency equation where E0 = counting efficiency at zero sample thickness

~ = Self-absorption coefficient M = Sample thickness, mg/cm 2 V = Sample volume, liters Y = Chemical recovery =

R Rl+R2 where R = mg of I- recovered Rl = mg of I- carrier added R2 = mg of intrinsic stable I- measured in sample

1. 05 = Correction factor for pr.otein-bound iodine H = J/(1-K)*EXP(L) = correction factor for I-131 decay during counting period J = (0.693/8.05)*(R/1440)

R = Count time, minutes 1440 = No. of minutes per day 8.05 = Half-life of I-131, days K = EXP(-J)

L = (0.693/8.05)*N N = Elapsed time (days) from mid-point of collection period to beginning of count time.

143

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF AIR FILTERS The air filters are placed in a small beaker and just enough fuming nitric acid is added to cover the filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then introduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The strontilim is precipitated as a carbonate, which is dried and weighed. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is that sr-90 and Sr-89 are both unknown quantities,,requiring two simultaneous equations to solve for them.

calculation of Sr-90 Activity:

Sr-90 Results (pCi/m 3 ) = N4/R (2.22)*(E)*(E(l5)/E 1 )*(S6)*(V)*(U)

= W2 where S6 =A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = Sr-90 counting standard efficiency v = Sample quantity (m3)

U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl)

Il =1 - EXP ((-0.693/2.667)*tl)

I2 =1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count 144

t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl =D+ E*M + F*M 2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 =X- Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/m3) =

(Xl+Yl)*Fl~l/2 r2* (X+Y) + * (Wl*W2)

L w1 2 w1 2 J (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/m3) =

~.66* (X+Y) + (Xl+Yl)*Fl ~ l/2 t w1 2 w1 2 j calculation of sr-89 Activity:

sr-89 Results (pCi/m3 ) = N6/R (2.22)*(E)*(E(l5)/E 1 )*(S7)*(V)*(U)*(F9)

= W3 S7 =G+ H*M + I*M2 (This is the general form of the normalized Sr-89 *

• efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

N6 = Nl - N7*(1 + Rl*Il)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90)

• E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) 145

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of Sr-89, days All other quantities are as previously defined.

The 2-sigma error for sr-89 (pei/m 3 ) = 2 * (sa2+s92)2

• W3 (Nl - N7*(l+Rl*Il))

SS =lcx+Y) + (Xl+Yl)*Fl~l/2

[w1 2 w1 2 j S9 = (Xl+Yl)l/ 2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/m 3 ) =

4.66*(ss 2 +s9 2 ) 112 146

• SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF RAW MILK Stable strontium carrier is first introduced into a milk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations. These cations are then eluted off with a TRIS-buffered 4N sodium chloride solution into a beaker and precipitated as carbonates. The carbonates are converted to nitrates with 6N nitric acid and, by acidifying further to an overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precip-itation. Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip. The strontium is precipitated as its carbonate, filtered, dried and weighed to determine strontium recovery. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

calculation of Sr-90 Activity:

Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E 1 )*(S6)*(V)*(U)

=~

where S6 =A+ B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipita~e, mg/cm 2 E(l5)/E' = Ra~io of Sr-90 efficiency at thickness value of 15mg/cm2 to* Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = sr-90 counting standard efficiency v = Sample quantity (liters) u = Chemical yield N4 = (N2 Fl*Nl)/Wl = net counts due to sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl)

Il = 1 - EXP ((-0.693/2.667)*tl) 147

I2 = l - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M 2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/L) =

G* (X+Y) + (Xl+Yl)*Fl~l/2 * (Wl*W2)

[ w1 2 w1 2 J (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) =

r4.66* (X+Y) + (Xl+Yl)*Fl2 1/2 t w1 2 w1 2 calculation of sr-89 Activity:

Sr-89 Results (pCi/L) = N6/R (2.22)*CE)*CE(15)/E 1 )*CS7)*CV)*(U)*(F9)

= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.) -

N6 = Nl - N7*(1 + Rl*Il)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 148

E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 = EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of Sr-89, days All other quantities are as previously defined.

The 2-sigma error for sr-89 (pCi/L) = 2* (s82+s9 2 ) 1 / 2

• W3 (Nl - N7*(l+Rl*Il))

se = ~X+Y) + (X1+Yl)*F12l112 w1 2 w1 2 j S9 = (Xl+Yl) 1 / 2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/L) =

4.66*(S8 2 +s9 2 ) 1 / 2 149

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank are then made alkaline and heated to near boiling before precipitating the carbonates. The carbonates are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric hydroxide (yttrium strip) followed by a barium chromate strip.

The strontium is precipitated as a carbonate before being dried and weighed.

The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Since surface waters, as well as some drinking water samples, have been found to contain significant amounts of stable strontium, a separate aliquot from each sample is analyzed for stable strontium. These results are used in correcting the chemical recovery of strontium to its true value.

ca1cu1ation of sr-90 Activity:

Sr-90 Results (pCi/L) = , N4/R (2.22)*(E)*(E(l5)/E 1 )*(S6)*(V)*(U)

= W2 where S6 =A + B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = sr-90 counting standard efficiency v = sample quantity (liters) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl)

Il =1 - EXP ((-0.693/2.667)*tl) 150

12 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl =D+ E*M + F*M 2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 =X- Y, where X and Y are recount gross counts and background counts, respectively Hl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = Ho. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/L) =

12* (X+Y) + (Xl+Yl)*Fl 2 l/2 * (Wl*W2)

~ w1 2 w1 2 (H2-Fl*Hl)

Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) =

r4.66* (X+Y) + (Xl+Yl)*Fl~l/2 L w1 2 w1 2 J calculation of sr-89 Activity:

sr-89 Results (pCi/L) = N6/R .

(2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)

= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

H6 = Hl - H7*(~ + Rl*Il)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) 151

E(15)/E' = Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For aii other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of Sr-89, days All other quantities are as previously defined.

The 2-sigma error for sr-89 (pCi/L) = 2* css 2+s9 2 ) 112

• w3 (Nl - N7*(l+Rl*I1))

SS = lcx+Y) + (Xl+Yl)*Fl ~ 1/2

[wi 2 wi 2 j S9 = (X1+Y1) 1 / 2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/L) =

4.66*(ss 2 +s9 2 ) 1 12 152

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT, CRAB SHELL AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, before being placed in an oven to dry at l00°C. At the completion of the drying period, samples are again weighed (recorded as "dry" weight) and then pulverized. A measured amount (quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed in a muffle furnace. The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 900°C for 1/2 hour. After removal from the furnace, the melt is cooled, pulverized and added to SOOml distilled water and heated to near boiling for 30 minutes, with stirring. The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with 1:1 nitric acid (HN0 3 ). The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming HN0 3

• After calcium ~emoval with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroxide followed by coprecipitation on barium chromate. The strontium is precipitated as its carbonate, which is dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

calculation of sr-90 Activity:

Sr-90 Results (pCi/kg wet) = N4/R (2.22)*(E)*(E(l5)/E 1 )*(S6)*(V)*(U)

= W2 where S6 =A+ B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = Sr-90 counting standard efficiency v = Sample quantity (kg wet) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 153

Il =l -E~ ((-0.693/2.667)*tl)

I2 =l -E~ ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life Of Y-90, days 2

Rl =D+ E*M + F*M {This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and Fare regression coefficients.)

N2 =X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = ~ ((-0.693/2.667)*t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for sr-90 {pCi/kg wet) = _

r2* {X+Y) + {Xl+Yl)*Fl~l/2 * {Wl*W2)

L w1 2

w1 2 J {N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for sr-90 {pCi/kg wet) =

~-66* {X+Y) + {Xl+Yl)*Fl~l/2 t w1 2 w1 2 j calculation of sr-89 Activity:

Sr-89 Results {pCi/kg wet) = N6/R (2.22)*(E)*(E(l5)/E 1 )*(S7)*(V)*(U)*(F9)

= W3 S7 =G+ H*M + I*M2 {This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional

• counter where G, Hand I are regression coefficients.)

154

1 I

I N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90)

E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of sr-89, days All other quantities are as previously defined.

The 2-sigma error for Sr-89 (pCi/kg wet) = 2* (se2+s9 2 )1/2

• W3 (Nl - N7*(l+Rl*Il))

SB =rcX+Y) + (Xl+Yl)*Fl~l/2

[w1 2 w1 2 J S9 = (Xl+Y1) 1 f 2 All other variables are as previously*defined.

Keeping 2the 2same 4.66*(se +s9 ) 112 variable definitions, the LLD for Sr-89 (pCi/kg wet) =

155

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE The bone or shell is first physically separated from the rest of the sample before being broken up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontium carrier and cesium holdback carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered.

The sample is then treated with concentrated (70%) nitric acid and boiled until strontium nitrate crystallizes out. The strontium nitrate is freed of calcium by repeated fuming nitric acid recrystallizations. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide followed by coprecipitation with barium chromate. The strontium is precipitated as strontium carbonate, which is dried, weighed, then beta-counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

calculation of sr-90 Activity:

sr-90 Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(l5)/E 1 )*(S6)*(V)*(U)

= W2 where S6 =A+ B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = sr-90 counting standard efficiency v = sample quantity (kg dry)

U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to sr-90 only 156

Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl)

Il =1 - EXP ((-0.693/2.667)*tl)

!2 =1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time.from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl =D+ E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 =X- Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/kg dry) =

r2* (X+Y) + (Xl+Yl)*Fl 2ll/2 * (Wl*W2)

[ w1 2 w1 2 J (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kg dry) =

4.66* (X+Y) + (Xl+Yl)*Fl 2ll/2

[ w1 2 . w1 2 J calculation of Sr-89 Activity:

sr-89 Results (pCi/kg dry) = N6/R

-c-2-.2-2-)_*_C_E_)_*-cE""""(_l_S_)_/.....

E-*-)*-("""s"""7...)-*"""C""'"v-)*-(""u""')....*""'("""F""'9~)

= W3

=G+ H*M + I*M2 (This is the general form of the normalized Sr-89 S7 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

157

N6 = Nl - N7*(1 + Rl*Il)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90)

E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of Sr-89, days All other quantities are as previously defined.

The 2-sigma error for sr-89 (pCi/kg dry) = 2* (sa2+s92)1/2

• W3 (Nl - N7*(l+Rl*Il))

SB =fcx+Y) + (Xl+Yl)*Fl~l/ 2

[w1 2 w1 2 J 89 = (Xl+Yl) 1 / 2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg dry) =

4.66*(sa 2 +s9 2 ) 112 158

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a 50gm aliquot is added to approximately 1/3 - liter concentrated hydrochloric acid (HCl), containing 5ml of strontium carrier (lOmg sr++/ml). A blank con-taining only 1/3 - liter concentrated HCl and 5ml strontium carrier is run in parallel with the sample. The samples are stirred vigorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable strontium. The remaining sample is alkalinized with ammonium hydroxide to precipitate all the transitional elements. After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontium and calcium carbonate.

These carbonates are first filtered and then digested with 6N HN0 3

• Two fuming (90%) HN0 3 recrystallizations are then performed to remove calcium.

Subsequently, radioactive impurities are removed by two precipitation steps, using ferric hydroxide and barium chromate as carriers. The strontium is precipitated as strontium carbonate before being dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.). There is a second count at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them *

• calculation of Sr-90 Activity:

Sr-90 Results (pCi/kg dry) = . N4/R (2.22)*(E)*(E(l5)/E 1 )*(S6)*(V)*(U)

= W2 where S6 = A + B*M + C*M 2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band Care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm 2 E(l5)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = sr-90 counting standard efficiency v = Sample quantity (kg dry) u = Chemical yield N4 = (N2 Fl*Nl)/Wl = net counts due to sr-90 only

• Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 159

Il = 1 - EXP ((-0.693/2.667)*tl)

I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life Of Y-90, days Rl = D + E*M + F*M 2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 =X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/kg dry) =

[

2* (X+Y) + (Xl+Yl)*F1 2ll/ 2 * (Wl*W2) w1 2 w1 2 J (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pei/kg dry) =

'4.66* (X+Y) + (Xl+Yl)*Fl211/2 L w1 2 w1 2 J calculation of sr-89 Activity:

Sr-89 Results (pei/kg dry) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)

= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

N6 = Nl - N7*(1 + Rl*Il) 160

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90)

E(l5)/E' = Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of Sr-89, days All other quantities are as previously defined.

The 2-sigma error for sr-89 (pCi/kg <tty) = 2* (ss2+s92)1/2

• W3 (Nl - N7*(l+Rl*Il))

SS =[(X+Y) + (Xl+Yl)*Fl ~ 1/2 w1 2 w1 2 J S9 = (Xl+Yl) 1 / 2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for sr-89 (pCi/kg dry) =

4.66*(ss 2+s9 2 ) 112 161

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Chemical/Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes. In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by ashing 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask.

All the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium. The sample, spiked samples and blank are determined by Atomic Absorption Spectroscopy (AAS) or Atomic Emission Spectroscopy (AES) and are plotted graphically. The true concentration is then extrapolated. Chemical and ionization interferences are controlled by adding 1% or more of lanthanum as chloride to all samples to be analyzed.

For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH

<2 with hydrochloric or Nitric acid and analyzed by AAS or AES as follows: A group of strontium standards (of similar concentration to the unknowns) is prepared. Then, to 9 ml of each prepared sample, blank and standard, is added 1 ml of lanthanum oxide solution.

All results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.

Sample calculation of Corrected Chemical Recovery of Strontium in Soil and Sediment:

Reported concentration of stable strontium (mg/L):ll9 Volume of specimen (ml):25 (removed from lOOOml of diluted leachate)

Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml flask*= (119mg/L) x (.025L/25ml) x (25ml)

2.9Smg Sr Since 2.98mg Sr represents the quantity of stable strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample

2.98mg Sr = 119 mg 0.025 162

Net weight of srco 3 precipitate (mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (125mg) x (.5935) = 74.2 Corrected chemical recovery of strontium = 74.2 = 0.623 119.0 The calculations follow the same sequence for bone and shell samples.

Sample calculation of Corrected Chemical Recovery of Strontium in Water:

Reported concentrations of stable strontium (mg/L): 1.65 Volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample = (l.65mg/L) x (2.0L)

= 3.30mg Quantity of strontium carrier added to sample (mg): 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of srco 3 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935) = 17.2mg Corrected chemical recovery of strontium = 17.2mg = .738 23.3mg 163

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF AIR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a given location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top. The Petri dish is closed and the sample counted on a gamma detector.

The following are the calculations performed for the gamma activity, 2-sigrna error and LLD:

Result (pCi/m 3 ) = N*D =R (2.22}*(E}*(A)*(T)*(V)

N = Net counts under photopeak D = Decay correction factor A.tl*EXP ( A.t2) 1-EXP(-A.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A. = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, m3 2.22 = Ho. of dpm per pCi 2-sigrna error (pCi/m 3 ) = l.96*(GC+Bc)l/2*R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pCi/m 3 ) = 4.66*(Bc)l/2*D (2.22)*(E)*(A)*(T)*(V) 164

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF RAW MILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is brought to ambient temperature and then counted on a gamma detector.

calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/L) = N*D =R (2.22)*(E)*(A)*(T)*(V)

N = Net counts under photopeak D = Decay correction factor A. tl*EXP(A.t2) 1-EXP(-A.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A. = Q.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

v = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc)l/2*R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pCi/L) = 4.66*(Bc) 1 12 .D

{2.22)*(E)*(A)*(T)*(V)

• 165

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated Marinelli beaker and then counted on a gamma detector.

calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/L) = N*D =R

{2.22)*{E)*(A)*(T)*(V)

N = Net counts under photopeak' D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, liters 2.22 = No. of dprn per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc) 112 *R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pCi/L) = 4.66*(Bc) 1 / 2*D

{2.22)*CE)*(A)*CT)*CV) 166

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF SOLIDS several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required. For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm 3 ), when possible, in a tared aluminum can. The can is weighed, hermetically sealed and counted.

In most cases, a wet sample is prepared (when a lower sensitivity is acceptable) by either grinding/chopping the wet sample or by using a food processor to puree it. The sample is poured into a calibrated, tared clear plastic container, aluminum can, or marinelli beaker until a standard volume is reached for that container. The sample is weighed, sealed, and counted.

Soil and sediment samples are first oven dried until a constant weight is achieved and then pulverized. The sample is added to a tared aluminum can, compacted to a standard volume and weighed. It is hermetically sealed., cured for 30 days to allow for ingrowth, and counted.

calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result {pCi/kg) = N*D =R (2.22)*(E)*(A)*(T)*(V)

N = Net counts under photopeak D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

v = Sample volume, kilograms 2.22 = No. of dpm per pCi 2-sigma error {pCi/kg) = l.96*(GC+BC) 1 / 2*R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

• The LLD {pCi/kg) = 4.66*(BC) 112 *D (2.22)*(E)*(A)*(T)*(V) 167

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso :Dy phosphor. They are first annealed in a 25o 0 c oven prior to exposure in 4 the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized Cs-137 source and the four areas are read again. calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are sUbtracted to allow for transit dose and system back-ground.

The results are computed as follows:

For any given area of the dosimeter, the dose in mR is calculated by the following formula:

DOSE = R * (REDOSE/RR)-AVC R = Initial reading of the area RR = Second reading of the area (after re-irradiation)

RE~OSE = Re-irradiation dose, mR AVC = Average of control values, mR 4N where AVC = ECDOSE/4N i=l N = Total number of control dosi-meters CDOSE = CR*(CREDOSE/CRR)

CDOSE =Control area dose~*mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation)

CREDOSE = Re-irradiation dose of the control dosimeter, mR 168

APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCO:MPARISON STUDIES PROGRAM RESULTS 169

IAPPENDIX EI

SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results fo'r the 1989 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE E-1 Gross Alpha and Gross Beta Emitters in Water and Air Particulates .... ............................ . 172 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products................................ 173 E-3 Tritium in Water .............. c****************** 174 E-4 Iodine in Water and Milk ************************* 175 E-5 Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products **.***************** 176

• 171

TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 01-89 EPA-WAT-AB275 Water Alpha 7.4+/-0.8 8.0+/-8.7 Beta 4.9+/-1 7.0+/-8.7 03-89 EPA-APT-GABS281 APT Alpha 27+/-1 21+/-8.7 Beta 62+/-2 62+/-8.7 04-89 EPA-WAT-P282 Water Alpha 29+/-3 29+/-12 Beta 59+/-1 57+/-8.7 05-89 EPA-WAT-AB285 Water Alpha Beta 26+/-2 62+/-1 50+/-8._

30+/-14 08-89 EPA-APT-GABS290 APT Alpha 7+/-1 6+/-8.

Beta (1) (1) 09-89 EPA-WAT-AB292 Water Alpha 4.3+/-1 4+/-8.7 Beta 7+/-1 6+/-8.7 10-89 EPA-WAT-P296 Water Alpha 51+/-2 49+/-21 Beta 33+/-2 32+/-8.7 (1) Analysis cancelled by EPA

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

• • known value with control limits, indicating whether results are in agreement or disagreement 172

TABLE E-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (pCi/kg)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-89 EPA-WAT-G277 Water Cr-51 237+/-8 235+/-42 Co-60 11+/-2 10+/-8.7 Zn-65 162+/-7 159+/-28 Ru-106 184+/-20 178+/-31 Cs-134 9+/-1 10+/-8.7 Cs-137 11+/-1 10+/-8.7 03-89 EPA-:APT-GABS281 APT Cs-137 18+/-1 20+/-2.6 04-89 EPA-WAT-P282 Water Cs-134 19+/-1 20+/-8.7 Cs-137 20+/-1 20+/-8.7

• 04-89 06-89 EPA-MLK-GS283 EPA-WAT-G286 Milk Water Cs-137 K(l)

Co-60 Zn-65 Ru-106 48+/-2 1570+/-22 31+/-1 160+/-5 113+/-2 50+/-8.7 1600+/-40 31+/-8.7 165+/-29 128+/-22 Cs-134 37+/-1 39+/-8.7 Cs-137 20+/-1 20+/-8.7 08-89 EPA-APT-GABS290 APT Cs-137 8+/-1 10+/-8.7 10-89 EPA-WAT-G294 Water Ba-133 57+/-1 59+/-10.4 Co-60 32+/-1 30+/-8.7 Zn-65 131+/-5 129+/-22.5 Ru-106 163+/-9 161+/-27.7 Cs-134 28+/-2 29+/-8.7 Cs-137 64+/-1 59+/-8.7 04-89 EPA-WAT-P296 Water Cs-134 6+/-1 5+/-8.7 Cs-137 7+/-1 5+/-8.7 (1) Reported as mg/1 of Potassium

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

• • known value with control limits, indicating whether results are in agreement or disagreement 173

TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritium Analysis of Water (pCi/L)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-89 EPA-WAT-H279 Water H-3 3180+/-140 2750+/-620 06-89 EPA-WAT-H287 Water H-3 5140+/-85 4500+/-780 10-89 EPA-WAT-H295 Water H-3 4280+/-170 3500+/-630

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

• • known value with control limits, indicating whether results are in agreement or disagreement 174

• TABLE E-4 .

USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-89 EPA-WAT-I278 Water I-131 97+/-1 106+/-19 08-89 EPA-WAT-I289 Water I-131 82+/-1 83+/-14

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

• • known value with control limits, indicating whether results are in agreement or disagreement 175

TABLE E-5 ..

USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter),

Milk, Water (pCi/L) and Food Products (pCi/kg)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 01-89 EPA-WAT-S274 Water Sr-89 41+/-3 40+/-8.7 sr-90 23+/-1 25+/-2.6 03-89 EPA-APT-GABS281 APT Sr-90 18+/-1 20+/-2.6 04-89 EPA-WAT-P282 Water Sr-89 10+/-1 8+/-8.7 sr-90 8+/-1 8+/-2.6 04-89 EPA-MLK-GS283 Milk Sr-89 38+/-2 39+/-8.7 Sr-90 51+/-1 55+/-5.2 05-89 EPA-WAT-S284 Water sr-89 6+/-1 6+/-8.7 Sr-90 6+/-1 6+/-2.6 08-89 EPA-WAT-GABS290 APT sr-90 (1) (1) 09-89 EPA-WAT-S291 Water Sr-89 15+/-1 14+/-8.7 sr-90 10+/-1 10+/-2.6 10-89 EPA-WAT-P296 Water sr-89 15+/-1 15+/-8.7 SR-90 6+/-1 7+/-2.6 (1) Sr analysis not requested by EPA

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

• • known value with control limits, indicating whether results are in agreement or disagreement 176

APPENDIX F SYNOPSIS OF LAND USE CENSUS 177

IAPPENDIX FI SYNOPSIS OF 1989 LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 50m 2 (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 Aug., 1989 Aug., 1989 Aug., 1989 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 6.6 (4.1) 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 179