ML19030A312

1993 Annual Radiological Environmental Operating Report, January 1 to December 31, 1993, Artificial Island Radiological Environmental Monitoring Program for Salem Units 1 & 2, & Hope Creek Generating Station

ML19030A312
Person / Time
Site:	Salem, Hope Creek
Issue date:	04/30/1994
From:	Public Service Electric & Gas Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML19030A312 (164)

Text

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM & HOPE CREEK GENERATING STATIONS 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1993

TABLE OF CONTENTS PAGE

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 Liquld 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 Results and Discussion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Atmospheric . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Direct Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 Terrestrial . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Aquatic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' ........ . 32 Program Deviations ...................................... . 39 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 APPENDIX A - PROGRAM

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS .............. . 65 APPENDIX C - DATA TABLES .................................... . 73 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES .............. 117

.APPENDIX E -

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 159

~ENDIX F - SYNOPSIS OF LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . 167 i

LIST OF TABLES TABLE NUMBER TABLE DESCRIPTION PAGE

1. Common Sources of Radiation........................ 6

2. 1993 Artificial Island Radiological Environmental Monitoring Program (Program Overview).............. 41 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 in Precipitation and Air Particulate 1973 through 1993 (Quarterly)...................... 45

7. Ambient Radiation - Offsite Vs Control Station*

1973 through 1993 (Quarterly)...................... 46

8. Iodine-131 Activity in Milk 1973 through 1993 (Quarterly)...................... 47 ii

LIST OF FIGURES (cont'd.)

• ~

NUMBER FIGURE DESCRIPTION PAGE

9. Gross Beta and Potassium-40 Activity in Surface Water 1973 through 1993 (Quarterly)...................... 48

10. Tritium Activity in Surface Water 1973 through 1993 (Quarterly)...................... 49 llA. Cesium-137 Activity in Water Sediment 1977 through 1993 (Semi-Annual) ...................... 50 llB. Cobalt-60 Activity in Water Sediment 1977 through 1993 (Semi-Annual) ........... *~* ........ 51 iii

SUMMARY

During normal operations of a nuclear power generating station there are releases of small amounts of radioactive material to the environment. To monitor and determine the effects of these releases a radiological environmental monitoring program (REMP) has been established for the environment around Artificial Island where the Salem Units 1 and 2 (SGS) and Hope Creek (HCGS)

Generating Stations are located. The results of the REMP are published annually, providing a summary and interpretation of the data collected. Additional data relating to the releases of radioactive materials to the environment can be obtained in the Radiological Effluent Release Report (RERR) which is published and submitted to the Nuclear Regulatory Commission on a semiannual 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, 1993, through December 31, 1993, and the results are discussed in this report.

Most of the radioactive materials noted in this report are normally present in the environment, either naturally, such as tassium-40, or as a result of non-nuclear generating station tivity such as nuclear bomb testing. Measurements made in the icinity 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 particulates, air iodine, precipitation, milk, surface, ground and drinking water, vegetables, beef, game, fodder crops, soil, 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 Technica-1 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 1738 analyses on 946 environmental samples during 1_993. Direct radiation dose measurements were also made using 411 thermoluminescent dosimeters (TLDs) .

1

I In addition to the detection of naturally-occurring isotop (i. e. Be-7, K-40, Ra-226 and Th-232), low levels of Sr-90, and Cs-137 were also detected in various media. The detection of these radionuclides may be attributed to residual fallout from atmospheric weapons testing. Trace levels of Mn-54, Co-58, Co-60, Sr-89, Cs-134, and Cs-137 were also detected. The concentrations of these nuclides were well below the Technical Specification reporting limit.

• 1 Dose measurements made with quarterly TLDs at 31 offsite locations around Artificial Island averaged 64 millirads for the year 1993. An average of the control locations (background) for this time was 60 millirads for the year.

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

2

INTRODUCTION

• 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.

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) .

dioactive decay is measured in terms of "half-life". The half-fe may be defined as the amount of time it takes for a radioactive 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 disintegrations (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 X 10 12 disintegrations per minute. For the purpose of quantifying-the effluents 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 X 10 6 decays per minute, while the picocurie is one millionth of a microcurie and represents 2.2 decays per minute.

3

RADIATION EFFECTS Radiation effects are measured in terms of the amount of biological damage produced. Biological damage from electromagnetic 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 o the dose.

The measurement of dose to man is expressed in terms of a unit called the rem. 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. 0.0001 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 everything 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 n~tural background.

4

Many sources of radiation exist today and, of them, the most

• 1niversal and least controllable is background radiation from rrestrial radioactivity and cosmic rays. Terrestrial

• adioactivity 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 basements 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 .

nee radon gas is radioactive, it, too, continues to produce, by

• cay, other radioactive materials referred to as radon daughters.

These daughters are solid particles which can stick to surf aces 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 mrem/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 and 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 ses to the human body are trace amounts of uranium and radium in tl inking water and radioactive potassium in milk. Sources of turally-occurring radiation and their average dose contribution are summarized in Table 1.

5

TABLE 1 Natural Sources COMMON SOURCES OF RADIATION*

Approximate Dose (mrem/year) Manmade Sources Approximate Dose (mrem/year)

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 approximately 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 the high elevation and length of these flights and resultant higher cosmic radiation levels. In several locations around the world high concentrations of mineral deposi.

give natural background radiation levels of several.thousand mre~

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, fluoroscopic 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 environment. 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.

6

NUCLEAR POWER REACTORS

~fter 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 heat. When one- fission occurs more neutrons are given off

_ich leads to more atoms to fission, producing more neutrons

-c., 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.

There 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.

7

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 th BWR (Hope Creek) and the PWR (Salem Units 1 and 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 is how the BWR works (refer to Figures 1 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 rod_s 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 steel 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 generato"r, 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 tission 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.

8

• GURE 1 BWR VESSEL & CORE STEAM LINE (TO TURBINE)

STEA~~~Y STEAM SEPARATORS FEEDWATER FEEDWATER (FROM CONDENSER) <L...L.L-- (FROM CONDENSER) t REACTOR CORE RECIRCULATION . RECIRCULATION WATER PUMP PUMP

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

~

1 SHIELD BUILDING STEAM----1> GENERATOR REACTOR~~-.-.-~~-,,~~~~~~-?"

VESSEL COOLING TURBINE TOWER 4---WATER RECIRC PUMP PRESSURE SUPPRESSION POOL (TORUS)

A PWR differs from a BWR in that water inside the reactor vessel system is pressurized to prevent boiling (steam) when heated. This essurized hot water is used to heat a second source of water, at

• lower pressure, which will produce steam to turn the turbines.

The following 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 turbine, cooled ba.ck 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 naval vessels .

• 11

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

LINER PRIMARY SYSTEM SECONDARY SYSTEM

• .*REACTOR

. PRIMARY TURBINE GENERATOR REACTOR  :: COOLANT

• . SYSTEM

• --*'\_

Fl

, ...... J

\. ....... ,

, ....... J

,,,......i, LJ 1* .....

CONDENSER

(-j

\.,,.. ...,

-*-*-*-*~ *-*~.i b-

• REACTOR

... COOLANT PUMP WATER (CONDENSATE)

COOLING WATER (RIVER)

CONTAINMENT OF RADIOACTIVITY

~e 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 radioactivity 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 s radioiodines, strontiums, and cesiums) are soluble and are

'tained in the coolant. These materials can be removed by filter 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 1 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 withstand 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

~eactor building structure (see Figure 2) .

13

FIGURE 4 PRIMARY PWR CONTAINMENT CROSS-SECTION (SALEM UNITS l I: 2)

POLA.I GAN'l'iY CRANE 191' 6" STEAM GENERATOR FAN FAN COIL COIL mm mm GROUND GROUND LEVEL LEVEL ACCUMULATOR ACCUMULATOR 186'6" 14

I I

FIGURE 5

• BWR MARX I PRIMARY CONTAINMENT CROSS-SECTION (HOPE CREEK)

DRY ---l -+-+-+-----++-+-

REACTOR WELL VESSEL RECIRC PUMP

• PRESSURE SUPPRESSION POOL

. 15

SOURCES OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS Under normal operating conditions for nuclear power plants most 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, piping, 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 remaining 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 . -

also become waste water. These represent the principal sources 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. All concentrates produced from the demineral-izers are packaged as solid waste for shipment and burial at a n .

offsite burial facility.

16

At Salem, the circulating water system provides an additional minimum of 185,000 gallons per minute dilution flow for liquid leases. At Hope C~eek, the cooling tower provides an additional

• ,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 radionuclides.

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 Specifications and the U.S. Nuclear Regulatory Commission's regulation in Title 10 of the Code of Federal Regulations, Part 20

'10 CFR 20) . These regulations are based on recommendations of the

.ternational Commission on Radiological Protection (ICRP), the

• tional 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 1115 MWe (3411 MWt) , and Salem Unit Two has the same rating at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which has a net rating of 1067 MWe (3293 MWt) .

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 marshlands, and low-lying meadowlands. These land types make up approximately 85% of the .land area within five miles of the site. Most of the remaining land is used for agriculture [5,6]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Reports [5,6], Environmental Statements [7,8], and the Updated Final Safety Analysis 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 monitqri 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 preoperational and operational phase of the program are referenced in this report [1-3] . 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, took over responsibility for third-party QA analyses and TLDs. An additional vendor, Controls for Environmental Pollution Inc., had been retained to provide third-party QA analyses and certain non-routine analyses from May 1988 up until June 1, 1992. At this time, TI is our sole QA vendor. RTL reports for the operational phase from 1983 to 1992 are referenced in this report [4] .

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An overview of the 1993 Program is provided in Table 2 .

nadioanalytical data from samples collected under this program were pared with results from the preoperational phase. Differences

• ween 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, 1993, 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 Surveillance sections of the Technical Specifications for the Salem Generating Station (SGS) and the Hope Creek Generating Station (HCGS) .

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

• To determine if SGS or HCGS has caused an increase in the radioactive inventory of long-lived radionuclides.

To detect any change in ambient gamma radiation levels.

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

This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.1.7 of the Hope Creek Technical Specifications, summarizes the findings of the 1993 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 comparison with subsequent operational reports [2] .

In order to meet the stated objectives, an appropriate operational REMP was developed. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The 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,

" land uses.

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Sampling locations were divided into two classes, indicator and control. Indicator stations are those which are expected to manifest station effects, if any exist. Control samples are collected at locations which are believed to be unaffected by station operations, usually at 15 to 30 kilometers distance.

Fluctuations in the levels of radionuclides and 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 1993. 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 analyse of the same sample should fall. As defined in Regulatory Guide LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability, with only 5% probability of falsely concluding that a blank observation represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count, or of the blank sample count, as appropriate.

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

Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected 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.

20

As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to

. ~ounterbalance

• one another, the extraction of averages based upon

_etitive grab samples is considered valid.

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 ensured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Plan [17] and the Environmental and Chemical Services 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

~ through E-5 in Appendix E.

RESULTS AND DISCUSSION The analytical results of the 1993 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1993 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 has historically included samples and analyses not specifically required by the Salem and Hope Creek Generating Stations Technical Specifications. PSE&G continues to collect and analyze these samples in order to maintain personnel proficiency in performing these non-routine analyses. These analyses are referenced throughout the report as Management Audit samples. The summary tables in this report include these additional samples and analyses.

ATMOSPHERIC

. particulates were collected on Schleicher-Schuell No. 25 glass

• er filters with low-volume air samplers. Iodine was collected from the air by adsorption on triethylenediamine (TEDA) impregnated 21

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, until June 28, 1993. This collector was automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition. Samples were collected monthly and transferred to new polyethylene 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. As of June 28th, a modified rain collector was fabricated to include the same 95 square inch collection area inside a cylindrical tank with a tapered bottom which drains directly into a 2.5 gallon container inside a refrigerator. No rinsing is required because the taper on the tank bottom allows for constant for gravimetric transfer of the entire rainfall sample into the container. No tritium correction is necessary because the distilled water rinse is not longer used.

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

Air particulate samples were collected at six locations. Each of the 304 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 analy for Sr-89 and Sr-90 as a management audit analysis. Total data recovery for the six sampling stations during 1993 was 97.9 percent.

• Gross alpha activity was detected in 229 of the indicator station ~amples at concentrat~o17s ranging from O*.7 x 10*3 to 4. 3 x 10~ pCi/m . Gross alpha activity was detected in 50 control station samples at levels ranging from O. 9 x 10-3 to 4. 3 x 10-3 pCi/m3

• LLD sensitivities for the remaining 25 indicator and control station samples ranged from <0. 7 x 10-3 to <2. O x 10-3 pCi/m3

• The grand average was 2. 0 X 10-3

• The maximum preoperational level detected was 7. 8 x 10-3 pCi/m3 *

• Gross beta activity was detected in 253 of the indicator station ~amples 0;t concentrations :r:anging from 8. 4 x 10-3 to_ 88 x 10-3 pCi/m and in 51 control station samples from 7. 6 x l_O 3 to 43 x 10-3 pCi/m3

• The average for both indicator and control station samples was 23 x 10-3 pCi/m3

• The maximum pre-operational level detected was 920 x 10-3 pCi/m3 , with an average of 74 x 10-3 pCi/m3 *

• Gamma spectrometric analysis performed on each of the 24 quarterly composite samples analyzed, indicated the presence of the naturally-occurring radionuclide Be-7, and the radionuc-i e Co-58. All other gamma emitters searched for were below th Lower Limit of Detection.

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o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in all twenty indicator station composites that were analyzed, at concentrations ranging from 42 x 10~ to 90 x 10~ pCi/m3 and in the four control station composites from 47 x 10-3 to 92 x 10-3 pCi/m3

• The maximum preoperational level detected was 330 x 10-3 pCi/m3 ,

with an average of 109 x 10-3 pCi/m3

• o Cobalt-58 was detected in one of the indicator stations' composites at a concentration of 1. 2 x 10-3

• It was not detected in any of the control station samples. LLD sensitivities for both the indicator and control station samples ranged from <0.1 to<0.5 pCi/m3

• No preoperational data is available for comparison.

• Strontium-89 and strontium-90 analyses were performed on five indicat.or 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 indicator or the control composites analyzed. LLD sensitivities for both the indicator and control station samples ranged from <0. 3 x 10-3 to < 1. 0 x 10-3 pCi/m3

• The maximum preoperational level detected was 4. 7 x 10-3 pCi/m3

• o Strontium-90 was not detected in any of the indicator or control station composites analyzed. LLD sensitivities for both the indicator and control station samples were <0.2 x 10-3 to <0. 3 x 10-3 pCi/m3

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

• Air Iodine (Table C-4)

Iodine in filtered air samples was collected at six locations. Each of the 304 weekly samples collected was analyzed for I-131.

• Iodine-131 was not detected in any of the 304 weekly samples analyzed. LLD sensitivities for the 253 indicator station samples ranged from <1.4 x 10-3 to <30 x 10-3 pCi/m3

• LLD sensitivities for the 51 control station samples ranged from

<2 .1 x 10-3 to <12 x 10-3 pCi/m3

• The maximum preoperational level detected was 42 x 10-3 pCi/m3

• Precipitation (Table C-6)

Although not required by the SGS or HCGS Technical Specifications, monthly precipitation samples were collected at a location in the town of Salem as management audit samples. Each of the ten monthly mples collected were analyzed for gross alpha, gross beta, tritium gamma emitters.

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• Gross alpha activity was detected in two of the ten samples collected at a concentration of 0.7 and 2.6 pCi/L. LLD sensitivities for the remaining eight samples ranged from <0 to <4.3 pCi/L. The maximum preoperational level detected wa 4.7 pCi/L.

• Gross beta activity was detected in nine samples at concentrations ranging from 0.5 to 4.5 pCi/L, with an average of 1.8 pCi/L. The LLD value of the remaining sample was <0.9 pCi/L. The maximum preoperational level detected was 71 pCi/L, with an average of 19 pCi/L.

• Tritium activity was detected in only one of the ten samples, at a value of 130 pCi/L. LLD sensitivities for the remaining nine samples ranged from <110 to <190 pCi/L. The maximum preoperational level detected was 610 pCi/L, with an average of 216 pCi/L.

• Gamma spectrometric analysis was performed on all ten of the monthly samples. Analysis indicated the presence of the naturally-occurring radionuclides Be-7, K-40 and Radium. All other gamma emitters searched for were below the Lower Limit of Detection.

o Beryllium-7, attributed to cosmic ray activity, was detected in seven of the ten samples at concentrations ranging from 39 to 120 pCi/L, with an average of 50 pCi/L. The maxim-preoperational level detected was 79 pCi/L, with an aver of 29 pCi/L. The increase in the naturally-occurring Be-activity over preoperational levels is most likely due to spallation reactions in the upper atmosphere.

o Potassium-40 activity was detected in two samples at concentrations of 56 and 60 pCi/L. The maximum*

preoperational level detected was 18 pCi/L. This increase over preoperational levels is most likely due to the sampling stations relatively close proximity to an estuarian environment.

o Radium activity was detected in two of the samples at 7.3 and 8.3 pCi/L. The LLD sensitivities measured throughout the year for the remaining eight samples ranged from <1.8 to <11 pCi/L. No preoperational data is available for _.

comparison. However, the presence of Radium is- not attributable to the operations of SGS or HCGS.

DIRECT RADIATION Ambient radiation levels in the environs were measured with energy-compensated CaS0 4 (Dy) thermoluminescent 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.

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Direct Radiation (Tables C-7, C-8) total of 43 locations were monitored for direct radiation during

• 93, 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 6.0 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 averages for the quarterly TLD's were based on only the first three quarters of 1993. The fourth quarter results were invalidated by Teledyne Isotopes (See Program Deviations) . The average dose rate for the 29 quarterly off-site indicator TLDs was 5.3 millirads per standard month, and the average control rate was 5.0 millirads per standard month. The preoperational average quarterly TLD readings was 4.4 millirads per standard month.

In Figure 7, the quarterly average radiation levels of the offsite indicator stations versus the control stations, are plotted for the year period from 1974 through 1993.

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 time of harvest. Such samples are weighed in the field at time pickup and then packed in plastic bags. Grass or green chop is lected from grazing areas, where possible.

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

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

LLD sensitivities for the 60 indicator station samples ranged from <0.1 to <0.8 pCi/L and for the 20 control station samples from <0.2 to <0.8 pCi/L. The maximum preoperational level detected was 65 pCi/L which occurred following a period of atmospheric nuclear weapons tests.

• Gamma spectrometric analysis performed on each of the 80 samples indicated the presence of the naturally-occurring radionuclide K-40. All other gamma emitters searched for below the Lower Limit of Detection.

o Potassium-40 was detected in all 80 samples. Concentrations for the 60 indicator station samples ranged from 930 to 1500 pCi/L, with an average of 1350 pCi/L. The 20 control station sample concentrations ranged from 1200 to 1400 pCi/L, with an average of 1300 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.

• 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 not detected in any of the three indicator samples analyzed nor in the control station sample. LLD sensitivities for the indicator samples ranged -from <0. 8 to

<1.4 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 all of the three indicator samples analyzed. Average concentrations for the indicator station samples was 2.5 pCi/L and for the control station sample at 2.2 pCi/L. The average concentration for all samples was 2.5 pCi/L.

26

The maximum preoperational level detected was 12 pCi/L, with an average of 3.5 pCi/L. The presence of Sr-90 in the samples can be attributed to fallout from previous nuclear weapons testing.

Well Water (Ground Water) (Tables C-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 one indicator well and one control well during January through December of the year. Each sample was analyzed for gross alpha, gross beta, potassium-40, tritium, I-131 and gamma emitters. Quarterly composites were analyzed for Sr-89 and Sr-90.

• Gross alpha activity was detected in one of the indicator station samples at a concentration of 5.9 pCi/L. Activity was detected in two of the control station samples at con-centrations of 1.7 and 1.8 pCi/L. LLD values ranged from <0.4 to <4.7 pCi/L for both the indicator and control station samples. The maximum preoperational level detected was 9.6 pCi/L.

• Gross beta activity was detected in all 24 samples.

Concentrations for the 12 indicator station samples ranged from 2.7 to 4.4 pCi/L, with an average of 3.3 pCi/L.

Concentrations for the 12 control station samples ranged from 8.8 to 11 pCi/L, with an average concentration of 10 pCi/L.

• The combined average for both stations was 6.7 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 24 samples. Concentrations for the 12 indicator station samples ranged from 3.0 to 3.6 pCi/L, with an average of 3.4 pCi/L. Concentrations for the 12 control station samples ranged from 6.5 to 12 pCi/L, with an average of 9.8 pCi/L. The average concentration detected for all samples was 6.6 pCi/L. The maximum preoperational level detected was 19 pCi/L, with an average of 7.8 pCi/L.

• Tritium activity was detected in three of the indicator station samples at concentrations ranging from 140 to 350 pCi/L. There was no Tritium activity detected in any of the control station samples. The LLD sensitivities for the remaining 21 samples ranged from <110 to <210 pCi/L. The maximum preoperational level detected was 380 pCi/L.

• Gamma spectrometric analysis performed on each of the 12 indicator station and 12 control station water samples indicated the presence of the naturally-occurring radionuclides K-40 and Radium. All other gamma emitters searched for were below the Lower Limit of Detection.

27

o Radium was detected in ten of the indicator station samples at concentrations ranging from 9.3 to 150 pCi/L and in al twelve control station samples from 56 to 160 pCi/L. LL sensitivities for the remaining two samples were <4.5 an

<7.4 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 1989 through 1992 results, they are higher values than found in the preoperational program. We believe that results are higher due to a procedural change in which the samples are no longer boiled down to a 100 ml standard geometry. This change results in less removal of radon (and its daughters) from the sample. Since Ra-226 is an alpha emitter, its identification by gamma isotopic analysis is obtained by counting the gamma rays from Pb-214, one of its daughter products. We believe that values currently being observed are typical for this geographical area.

o Potassium-40 was detected in only one of the indicator station samples with a concentration of 64 pCi/L, and not detected in any of the control station samples. LLD values for both stations ranged from <8.9 to <60 pCi/L. The maximum preoperational level detected was 30 pCi/L.

• 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 four indicate station or four control station composites. LLD sensitivities for the indicator samples ranged from <0.6 to

<1.1 pCi/L and for the control samples from <0.5 to <0.8 pCi/L. The maximum preoperational level detected was <2.1 pCi/L.

o Strontium-90 was not detected in any of the four indicator station or four control station composites. LLD sensitivities for indicator samples ranged from <0.5 to <0.8 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.

• Iodine-131 was not detected in any of the twelve indicator station samples or control station samples. LLD sensitivities for all the stations, indicator and control, ranged from <0.1 to <0.4 pCi/L.

Potable Water (Drinking 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.

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Each of the 24 individual samples was analyzed for gross alpha, ss beta, K-40, tritium, iodine-131 and gamma emitters. Quarterly posites of monthly raw and treated water samples were analyzed Sr-89 and Sr-90 .

• Gross alpha activity was detected in five raw water samples at concentrations of 0.8 to 3.2 pCi/L and in three treated water samples at 0.9 to 1.5 pCi/L. The averages for both raw and treated water samples was 1.4 pCi/L. The maximum pre-operational level detected was 2.7 pCi/L .

• Gross beta activity was detected in all 24 samples at concentrations ranging from 1.9 to 4.4 pCi/L for the raw water and from 2.1 to 4.0 pCi/L for treated water. The average concentration for both raw and treated was 3.0 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 1.4 to 2.9 pCi/L for the raw water and from 1.6 to 3.1 pCi/L for treated water. The average concentration for both raw and treated was 2.0 pCi/L. The maximum preoperational level detected was 10 pCi/L, with an average of 1.7 pCi/L .

• Tritium activity was only detected in four raw water samples at concentrations of 150 to 240 pCi/L, and not in any of the treated water samples. LLD sensitivities for the remaining 20 samples ranged from <110 to <200 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 (Delaware River) is brackish, the water is not used for human consumption.

Drinking water supplies are not affected by discharges from the site. Iodine-131 measurements for all 24 samples were below the LLD sensitivities. The LLD sensitivities ranged from <0.1 to <0.6 pCi/L .

• Gamma spectrometric analysis performed on each of the 24 monthly water samples indicated the presence of the naturally-occurring radionuclide Radium. All other gamma emitters searched for were below the Lower Limit of DetectiDn.

o The radionuclide K-40 was not detected in any of the potable water samples. Since gamma analyses does not require the water samples to be concentrated down to a volume of lOOmL, K-40 results obtained through gamma analyses, are not as sensitive as the results obtained from atomic absorption.

The minimum detection value for K-40 analyses as indicated by the LLD, ranged from <12 to <45 pCi/L. No preoperational data is available for comparison.

29

o Radium was only detected in one potable raw sample at a concentration of 27 pCi/L. It was detected in two treate samples at concentrations of 5.2 and 6.8 pCi/L. LLD sensitivities for both raw and treated waters ranged fro

<1.3 to <6.3 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 or treated water composites. LLD sensitivities for the raw water sample composites ranged from <0.6 to <0.8 pCi/L and for the treated water sample composites from <0.5 to <0.8 pCi/L. The maximum preoperational level detected was 1.1 pCi/L.

o Strontium-90 was not detected in any of the four raw or treated water sample composites. LLD sensitivities for the four treated water sample composites *ranged from <0.5 to

<0.6 pCi/L and for the raw water sample composites from <0.5 to <0.6 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 i which liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled at four indicator stations (8 samples) and four control stations (9 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 seventeen samples indicated the presence of the naturally occurring radionuclide K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in all seventeen samples.

Concentrations for the eight indicator station samples ranged from 1300 to 2600 pCi/kg-wet and for the nine control station samples from 1000 to 2800 pCi/kg-wet. The average concentration detected for all samples was 1980 pCi/kg-wet.

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

Game (Table C-18)

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

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

• m two locations were collected during the months of January and February to satisfy this requirement.

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

o Potassium-40 was detected in the indicator station sample at a concentration of 2000 pCi/kg-wet and the control station sample at 2300 pCi/kg-wet. The average for both muskrat samples was 2150 pCi/kg-wet. The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4400 pCi/kg-wet.

BEEF (Table C-18)

Although not required by the SGS or HCGS Technical Specifications, beef samples are collected, when available, as management audit samples and analyzed for gamma emitters. One beef sample from the first half or the year was collected.

Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclide K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in the one beef sample at a concentration of 2600 pCi/kg-wet. The maximum pre-operational level detected was 4800 pCi/kg-wet.

Fodder Crops (Table C-19)

Although not required by the SGS or HCGS Technical Specifications, eight samples of crops normally used as cattle feed were collected from three indicator stations (6 samples) and one control station (2 samples) . It was determined that these products may be a significant element in the food-chain pathway. Fodder crops are collected as management audit samples and analyzed for *gamma emitters. Four of the locations from which samples were collected are milk sampling stations. Samples collected for wet gamma analysis included silage and soybeans.

• Gamma spectrometric analysis performed on each of the eight samples indicated the presence of the naturally-occurring radionuclides Be-7, K-40, and Radium. All other gamma emitters searched for were below the Lower Limit of Detection.

31

o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in the three silage samples f r o -

the indicator stations at concentrations ranging from 53 1100 pCi/kg-wet, with an average of 800 pCi/kg-wet. It detected in the control station silage sample at 940 pCi/kg-wet. The maximum preoperational level detected for silage was 4700 pCi/kg-wet, with an average of 2000 pCi/kg-wet. LLD sensitivities for the remaining three indicator soybean samples ranged from <48 to <150 pCi/kg-wet. The control station soybean sample was <43 pCi/kg-wet. The maximum preoperational level detected for soybean samples was 9300 pCi/kg-dry.

o Potassium-40 was detected in all eight samples.

Concentrations for the six indicator station samples ranged from 2800 to 17000 pCi/kg-wet and for the two control station samples from 6500 to 12000 pCi/kg-wet. The average concentration detected for the corn silage samples was 5100 pCi/kg-wet which was comparable to preoperational results which averaged 7000 pci/kg-wet. Although the Research and Testing Laboratory no longer reports results based upon the dry weight of the sample, soybean results were comparable to preoperational studies. Results averaged 14750 pCi/kg-wet which was comparable to preoperational results of 22000 pCi/kg-dry.

AQUATIC All aquatic samples were collected by Environmental Consulting Services, Inc. and delivered by PSE&G personnel. Surface water samples were collected in new polyethylene containers which were rinsed twice with the sample medium prior to collection. Edible fish and crabs are taken by net and then processed. In processing, the flesh is separated from the bone and shell and placed in sealed polyethylene containers and frozen before being transported in ice chests.

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-20, C-21, C-22, C-23)

Surf ace water samples were collected monthly at four indicator stations and one control station in the Delaware estuary. One location is at the outfall area (which is the area where liquid radioactive effluents from the Salem Station are allowed to be discharged into the Delaware River), another is downstream from the outfall area, *and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations ar the Delaware River and at the mouth of the Chesapeake and Delawa Canal, the latter being sampled when the flow is from the Canal into the river.

32

Station 12Cl, at the mouth of the Appoquinimink River, serves as the erational control. All surface water samples were analyzed thly for gross alpha, gross beta, and gamma emitters. Quarterly posites were analyzed for tritium .

• Gross alpha activity was detected in 15 samples from the 48 indicator stations at concentrations ranging from 1.4 to 4.7 pCi/L and in three control station samples from 2.0 to 2.8 pCi/L. These values are within the variations of the LLD sensitivities for the remaining samples which ranged from <1.3 to <3.7 pCi/L. The maximum preoperational level detected was 27 pCi/L .

• Gross beta activity was detected in 46 of the 48 indicator station samples ranging from 4 to 120 pCi/L, with an average of 53 pCi/L. Beta activity was detected in 11 of the control station samples with concentrations ranging from 6 to 90 pCi/L, with an average of 52 pCi/L. The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L .

• Tritium activity was detected in three samples from the sixteen indicator station composites at concentrations from 130 to 460 pCi/L, with an average of 330 pCi/L. There was no tritium detected in any of the four control station composites. LLD sensitivities for the remaining composites, both indicator and control, ranged from <110 to <200 pCi/L. The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L .

Gamma spectrometric analysis performed on each of the 48 indicator station and 12 control station surf ace water samples indicated the presence of Co-58, Co-60, Cs-137 and the naturally-occurring radionuclides K-40 and Radium. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in 31 samples from the indicator station samples at concentrations ranging from 30 to 15-0 pCi/L and in seven of the control station samples ranging from 48 to 130 pCi/L. The average for the indicator station locations was 85 pCi/L, while the average for the control station locations was 81 pCi/L. LLD sensitivities measured throughout the year for the remaining samples ranged from

<11 to <42 pCi/L. The maximum preoperational level detected was 200 pCi/L, with an average of 48 pCi/L.

o Radium was detected in four samples out of the 48 indicator stations, at an average concentration of 8.5 pCi/L. It was only detected in one of the control station samples at a concentration of 7 pCi/L. The LLD sensitivities for all remaining samples measured throughout the year ranged from

<0.6 to <6.8 pCi/L. The maximum preoperational level detected was 4.0 pCi/L.

33

o Cobalt-58 was detected in one indicator station sample at a concentration of 5.5 pCi/L. LLD sensitivities for the

• remaining indicator and the control station samples measl

• throughout the year ranged from <0.3 to <4.2 pCi/L. The .

presence of Co-58 in this sample can be attributed to sampling during a radioactive liquid effluent release.

o Cobalt-60 was detected in one indicator station sample at a concentration of 4.0 pCi/L. LLD sensitivities for the remaining indicator and the control station samples ranged from <0.3 to <3.2 pCi/L. The presence of Co-60 in this sample can be attributed to sampling during a radioactive liquid effluent release.

o Cesium-137 was also detected in the one indicator station sample at a concentration of 5.4 pCi/L. LLD sensitivities for the remaining indicator and the control station samples ranged from <0.2 to <3.0 pCi/L. The presence of Cs-137 in this sample can be attributed to sampling during a radioactive liquid effluent release.

Fish (Table C-24)

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 & flesh) . Samples inclu~

catfish, weakfish, white perch and striped bass. ~

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the four samples from the two indicator stations and the two samples from the control station as management audit analyses. Tritium activity was detected in one of the four indicator station samples at a concentration of 170 pCi/kg-wet, and in one of the two control station samples at a concentration of 150 pCi/kg-wet. LLD sensitivities for the remaining indicator and control station samples ranged from

<90 to <100 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 radionuclide K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in all four samples from the two indicator stations at concentrations ranging from 2600 to 3100 pCi/kg-wet for an average of 2900 pCi/kg-wet. K-40 was detected in both samples from the control station samples at 2700 and 3500 pCi/kg-wet. The average for the control samples was 3100 pCi/kg-wet. The maximum preoperational.

level detected was 13000 pCi/kg-wet, with an average of pCi/kg-wet.

34

• 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 was not detected in any of the indicator or control station bone samples. LLD sensitivities for the samples, both indicator and control, ranged from <16 to. <70 pCi/kg-dry. The maximum preoperational level detected was 100 pCi/kg-dry.

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

Concentrations in the indicator samples averaged 120 pCi/kg-dry. The concentrations in the control samples was 105 pCi/kg-dry. The average for all samples was 115 pCi/kg-dry. The maximum preoperational 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 previous nuclear weapons testing.

o Strontium-89 of the flesh was not detected in any of the six indicator and control station samples. LLD sensitivities for the six samples, indicator and control, ranged from <25 to <42 pCi/kg-wet. The preoperational level ranged from

<4.1 to <100 pCi/kg-wet .

• o Strontium-90 of the flesh was not detected in any of the six indicator and control station samples. LLD sensitivities for the six samples, indicator and control, ranged from <18 to <29 pCi/kg-wet. The maximum preoperational level detected was 67 pCi/kg-wet.

Blue Crab (Table C-25)

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, while the aqueous fraction was analyzed for tritium. The crab 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. No tritium activity was detected in any of the four station or control samples analyzed. LLD sensitivities for the four samples, indicator and control, ranged between <90 to <100 pCi/kg-wet.

The maximum preoperational level detected was 320 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 radionuclides Radium and K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

35

o Potassium-40 was detected in both indicator station samples at concentrations of 2700 and 2900 pCi/kg-wet and in bot ~

the control station samples at 2200 and 2500 pCi/kg-wet.

The average for both the indicator and control station samples was 2600 pCi/kg-wet. The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 pCi/kg-wet.

• Strontium-89 and strontium-90 analyses were performed on the flesh and shell of each of the indicator station and control station samples, as management audit analyses. Strontium analysis of the shell is performed because of the reconcentration factor of strontium in crab shells.

o Strontium-89 of the flesh was not detected in any of the four samples, indicator nor control. LLD sensitivities for all the samples ranged from <24 to <31 pCi/kg-wet. The maximum preoperational level detected was <51 pCi/kg-wet.

o Strontium-89 of the shell was not detected in any of the four samples, indicator nor control. LLD sensitivities for all the samples, indicator and control, ranged from <37 to

<72 pCi/kg-dry. The maximum preoperati.onal level detected was 210 pCi/kg-dry.

o Strontium-90 of the flesh was not detected in any of the four, indicator or control samples. LLD sensitivities fo these station samples ranged from <15 "to <20 pCi/kg-wet.

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

o Strontium-90 of the shell was detected in both indicator station samples at 180 and 200 pCi/kg-dry and in both of the control station samples at 140 and 200 pCi/kg-dry. The average for both indicator and control station samples was 180 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-26)

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 expected and well within the acceptable levels specified in section 3/4.12.1 of the Technical Specifications.

• Strontium-90 was detected in one of the ten indicatqr stati samples, at a concentration of 48 pCi/kg-dry, but was not detected in any of the control station samples.

36

LLD sensitivities for those remaining samples, both indicator and control, ranged from <22 to <76 pCi/kg-dry. The maximum preoperational level detected was 320 pCi/kg-dry.

Gamma spectrometric analysis was performed on each of the ten indicator station samples and two control station samples. In addition to the detection of the naturally-occurring radionuclides Radium, K-40 and Th-232, low levels of Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were also detected. All other gamma emitters searched for were <LLD.

o Manganese-54 was detected in three of the ten indicator stations at concentrations ranging from 23 to 41 pCi/kg-dry, with an average of 31 pCi/kg-dry. It was not detected in either of the two control station samples. LLD sensitivities for the other nine samples, both indicator and control, ranged from <7.5 to <26 pCi/kg-dry. No preoperational data is available for comparison.

o Cobalt-58 was detected in six indicator station samples at concentrations ranging from 45 to 83 pCi/kg-dry. The LLD sensitivities for the other six samples, indicator and control, ranged from <7.9 to <21 pCi/kg-dry. No preoperational data is available for comparison.

o Cobalt-60 was detected in six of the ten indicator stations at concentrations ranging from 34 to 140 pCi/kg-dry, with an average of 87 pCi/kg-dry. It was not detected at either of the two control stations. LLD sensitivities for the other six samples, indicator and control, ranged from <10 to <38 pCi/kg-dry. No preoperational data is available for comparison.

o Cesium-134 was detected in four indicator station samples at concentrations ranging from 46 to 70 pCi/kg-dry, with an average of 59 pCi/kg-dry. It was detected in one control station sample.at a concentration of 49 pCi/kg-dry. LLD sensitivities for the other seven samples, indicator and control, ranged from <5.2 to <36 pCi/kg-dry. No preoperational data is available for comparison.

o Cesium-137 was detected in six indicator station samples at concentrations ranging from 33 to 180 pCi/kg-dry, but was not detected in either control station sample. *The LLD sensitivities for the other six samples, both indicator and control, ranged from <4.8 to <16 pCi/kg-dry. The maximum preoperational level detected was 400 pCi/kg-dry.

o Potassium-40 was detected in all ten indicator station samples at concentrations ranging from 3200 to 18000 pCi/kg-dry, with an average of 10770 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 13000 and 16000 pCi/kg-dry.

37

The average for both the indicator and control station samples was 11400 pCi/kg-dry. The maximum preoperational.

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

o Radium was detected in all ten indicator station samples at concentrations ranging from 290 to 1900 pCi/kg-dry, with an average of 786 pCi/kg-dry. Concentrations detected in both of the control station samples were at 590 and 860 pCi/kg-dry, with an average of 725 pCi/kg-dry. The average for both the indicator and control station samples was 780 pCi/kg-dry. The maximum preoperational level detected was 1200 pCi/kg-dry, with an average of 760 pCi/kg-dry.

o Thorium-232 was detected in all ten indicator station samples at concentrations ranging from 430 to 1600 pCi/kg-dry, with an average of 852 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 790 and 830 pCi/kg-dry, with an average of 810 pCi/kg-dry. The average for both the indicator and control station samples was 845 pCi/kg-dry. The maximum preoperational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.

38

PROGRAM DEVIATIONS r Particulate and iodine sampler- location 3H3, which is located on

• e roof of the Research and Testing Laboratory, was operational for only 3 l/4 days out of a 7 day sampling period (for the week beginning March l) . This unscheduled power outage was due to severe storm conditions.

Air particulate and iodine sampler location 5Sl experienced an extended power outage beginning on June 12th and lasting until June 25th. This outage was due to Atlantic City Electric Company's Station Feed Transformer experiencing a failure and being replaced.

The duration of this outage was 192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br />, resulting in two weeks of data not being included in any averages.

On several occasions during October and November, the air sampler at location 2F2 experienced several power interruptions. The air sampler was removed, returned to the Research and Testing Laboratory and serviced. During servicing a faulty neutral connection was identified. The poor ground connection resulted in intermittent faults in the power supply outlet circuit. A new ground connection was made and the problem with recurring breaker trips ceased. This problem resulted in four weeks of data not being included in any averages. Although the data from location 2F2 was not available for the periods discussed above, a review of the data from the adjacent air sampling locations collected during this period indicated no ual results. Data recovery for air particulate and air iodine ults for all stations was 97.9%.

Air particulate and iodine sampler location 16El experienced an equipment malfunction shortly after servicing for the week beginning on November 29th. The defective breaker was replaced the following week.

The fourth quarter TLD results were invalidated by Teledyne Brown Engineering - Environmental Services Corporation (formerly Teledyne Isotopes) . The problem was due to a faulty TLD reader which yielded irregular exposure in the different areas of the TLDs.

The data from the fourth quarter could not be salvaged. To prevent reoccurrence, PSE&G has installed an additional set of quarterly TLDs at all locations to be held, in reserve and not normally read.

In the event that any set of TLDs exhibit erratic exposures, the reserve set of TLDs will be read. Results from the monthly TLD!s collected and analyzed during this quarter were reviewed and did not vary significantly from the other three quarters.

39

CONCLUSIONS The Radiological Environmental Monitoring Program for A r t i f i c i a l .

Island was conducted during 1993 in accordance with the SGS and Technical Specifications. The Lower Limit of Detection (LLD) values required by the Technical Specifications were achieved for this reporting period. The objectives of the program were also met during this period. The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.

From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment. No unusual radiological characteristics were observed in the environs of Artificial Island during this reporting period. Since these results were comparable to the results obtained during the preoperational phase of the program which ran from 1973 to 1976, we can conclude that the operation of SGS Units One and Two and HCGS had no significant impact on the radiological characteristics of the environs of Artificial Island.

40

TABLE 2 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE[FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT

a. Air Particulate SSl SDl 16El lFl 3H3 Weekly Gross alpha/weekly 2F2 Gross beta/weekly sr-89 & Sr-90/first quarter**

Gamma scan/quarterly

b. Air Iodine SSl SDl 16Ei lFl 3H3 Weekly Iodine-131/weekly 2F2

c. Precipitation 2F2 Monthly Gross alpha/monthly Gross beta/monthly

..i::--

Tritium/monthly

....... Gamma scan/monthly II. DIRECT RADIATION

a. Thermoluminescent 2S2 SDl 2El lFl 3Gl Monthly Gamma dose/monthly Dosimeters SSl lODl 3El 2F2 3Hl 682 14Dl 13El 2F6 .3H3 7Sl 16El SFl 6Fl 7Fl lOSl llFl 13F4

b. Thermoluminescent 2S2 SDl 2El lFl 3Gl Quarterly Gamma dose/quarterly Dosimeters SSl lODl 3El 2F2 3Hl 6S2 14Dl 13El 2F6 3H3 7Sl 16El SFl 6Fl lGl lOSl 7Fl llFl 13F4 lOGl 4D2 9El *2FS 3F2 16Gl 11E2 1501 12El 3F3 4F2 10F2 12Fl 13F2 13F3 14F2 15F3 16F2

TABLE 2 (cont'd)

ARTIFICIAL ISLAND RADIOLOGICAL ENvIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS III. Terrestrial Environment

a. Milk 2F7 11F3 14F4 3Gl Monthly Iodine-131/monthly (when animals Gamma scan/monthly are on pasture)

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 3El Monthly Gross alpha/monthly N> Gross beta/monthly Potassium-40/monthly Tritium/monthly Gamma scan/monthly sr-89 & sr-90/quarterly

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 3El 2F4 3E3 lGl 3HS Annually Gamma scan/on colle~tion 4F2 5F3 14F3 2Gl (at harvest) 2G2

• TABLE 2 (cont'd)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

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

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

g. Fodder Crops 3El 2F7 11F3 14F4 3Gl Annually Gamma scan/on collection

.i:-

UJ 6Sl lODl 16El lFl 3Gl Collect from Sr-90/on collection

h. ~Soil 2F4 2F7 SFl 11F3 14F4 each location Gamma scan/on collection once every three years IV. AQUATIC ENVIRONMENT

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

TABLE 2 (cont'd)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

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

Sr-89 & Sr-90 (bones)/on collection**

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

Gamma scan (flesh)/on collection

c. Blue Crabs llAl 16Fl 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 lSAl 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.

• BETA IN PRECIPITATION AND AIR PARTICULATE FIGURE 6

• 1973 THROUGH 1993 1000 Weapons Test Weapons Test os-17'-74 09-11-n AIR (fCi/m3)

!Weapons Teat 09-ZJ.76 .,...__J I

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\ ..... 03-14-78 Chernobyl 04-26-86

+

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FIGURE 7 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1973 THROUGH 1993 10 ----------------~------------------~--------~---------------

Weapons Test 06-17-74 Weapons Test OFF-SITE STATIONS 09-11-n 8 Weapons Test Weapons Test CONTROL STATIONS 03-1~78 119-28-761

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• IODINE-131 ACTIVITY IN MILK FIGURE 8 1973 THROUGH 1993 20 --~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---.

.__Weapons Test 09-26-76 10 Weapons Test 11-n

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. 04-26-86 06-17-74 Weapons Test 0

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FIGURE 9 GROSS. BETA & K-40 ACTIVITIY IN SURFACE WATER 1973 THROUGH 1993 GROSS BETA Weapons Test Weapons Test 06-17-7 09-17-77 Weapons Test I Weapons Test Chernobyl K-40 09-26-7166 ;~ 03-14-78 l~

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• TRITIUM ACTIVITY IN SURFACE WATER FIGURE 10

• 1973 THROUGH 1993 10,000 r------------------------------.

Weapons Test Wea ons Test Chernobyl 1 000 06-17-71:4 Weapons Test 09-26-76 09-1 -77

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FIGURE 11A CESIUM - 137 IN WATER SEDIMENT 1977 THROUGH 1993 Wea s Test 1000 09-1 -77 Chernobyl V'1 0

200 04-26-86 50 i

1977 1979 1981 1983 1985 1987 1989 1991 1993 SEMI-ANNUAL AVERAG

FIGURE 118 COBALT-60 IN WATER SEDIMENT 1977 THROUGH 1993 10000 - - - - - - - - - - - - - - - - - - - - - - - -

Weapons Test 1000 09-17-n

~

-a.

0 200 ~ Chernobyl 04-26-86 l

50 1977 1979 1981 1983 .1985 1987 1989 1991 1993 1995 I SEMI-ANNUAL AVERAGE I

[l] Radiation Management Corporation.

REFERENCES "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 19 7 6 II

• RMC-TR- 7 7 - 0 3 19 7 8 .

I

[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 1992".

[5] Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971.

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

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

Salem Nuclear Generating Station, Units 1 and 2 11

• 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 1 and 2". 1982.

[10] Public Service Electric and Gas Company. "Updated Final Safety Analysis Report - Hope Creek Generating Station.

[11] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 1 - Technical Specifications", Appendix A to Operating License No. DPR-70, 1976, Sections 3/4.12 and 6.9.1.10 (Amend~ent 59 et seq) .

[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 et seq) .

52

REFERENCES (cont'd)

[13] Public Service Electric and Gas Company. "Hope Creek Generating Station Unit 1 - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10.

[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.

Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, SGS RERR-35 and RERR Salem Generating Station. 1993.

[20] Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, HCGS RERR-15 and RERR Hope Creek Generating Station. 1993.

[21] 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.

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

53

• APPENDIX A PROGRAM

SUMMARY

55

ARTIFICIAL ISLAND RADIOLOGICAL SALEM GENERATING STATION HOPE CREEK GENERATING STATION ENVIRO~L MONITORING PROGRAM

SUMMARY

DOCKET NOS. 50-272/-311 DOCKET NO. 50-353 SALEM COUNTY, NEY JERSEY JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHYAY TOTAL NUMBER LOYER ALL INDICATOR LOCATIONS LOCATION YITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS (LLD)*

AIRBORNE Air particulates Alpha 304 1.0 2.1 (229/253) 5D1 3.5 mi E 2.2 (38/52) 2.0 (50/51) 0 c1o* pci /m3 > (0.7-4.3) (1.0-3.9) (0.9-4.3) 1F1 5 .8 mi N 2.2 (51/52)

(0.9-4.3) 2F2 8.7 mi NNE 2.2 (45/48)

(1.1-3.6)

V1 Beta 304 6.0 23 (253/253) 16E1 4.1 mi NNY 24 (51/51) 22 (51/51) 0

-....J (8.4-88) (8.7-88) (7.6-43)

Sr-89 6 0.4 <LLD <LLD <LLD 0 Sr-90 6 0.3 <LLD <LLD <LLD 0 Gamma Be-7 24 6.8 67 (20/20) 5D1 3.5 mi E 84 (4/4) 69 (4/4) 0 (42-90) (73-90) (47-92)

Co-58 24 0.3 1.2 (1/20) 5S1 1.0 mi E 1.2 (1/4) <LLD 0 (1.2) (1.2)

Air Iodine 1-131 304 13 <LLD <LLD <LLD 0 (10- 3 pCi/m3 )

Precipitation Alpha 10 1.5 1. 7 (2/10) 2F2 8.7 mi NNE 1.7 (2/10) No Control 0 (pCi/L) (0.7-2.6) (0.7-2.6) Location Beta 10 2.0*** 1.9 (9/10) 2F2 8.7 mi NNE 1.9 (9/10) No Control 0 (0.5-4.5) (0.5-4.5) Location

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS (LLD)*

AIRBORNE (Cont'd)

PRECIPITATION H-3 10 150 130 (1/10) 2F2 8.7 mi NNE 130 (1/10) No Control 0 (pCi/L) (130) (130) Location Gamma 66 (7/10) 2F2 8.7 mi NNE 66 (7/10) No Control 0 Be-7 10 15 (39-120) (39-120) Location K-40 10 58 (2/10) 2F2 8.7 mi NNE 58 (2/10) No Control 0 (56-60) (56-60) Location RA-NAT 10 7.8 (2/10) 2F2 8.7 mi NNE 7.8 (2/10) No Control Vt (7.3-8.3) (7.3-8.3) Location 00 II Direct Direct Radiation Gamma 288 6.2 (252/252) 11S1 0.09 mi SW 8.1 (12/12) 6.5 (36/36)

(mrad/std. month) Dose monthly (3.8-11) (5.9-11) (5.1-8.1)

Gamma 123(1) 5.4 (105/105) 7S1 0.12 mi SE 6.5 (3/3) 5.0 (18/18) . 0 Dose qtrly. (3.0-9.8) (5.6-6.9) (4.1-6.4)

III TERRESTRIAL MILK 1-131 80 0.4 <LLD <LLD <LLD 0 (pCi/L)

Sr-89 4 1. 1 <LLD <LLD <LLD 0 Sr-90 4 0.9 2.5 (3/3) 2F7 5. 7 mi NNE 4.7 (1/1) 2.2 (1/1) 0 (1.1-4.7) (4. 7) (2.2)

Gamma K-40 80 120 1350 (60/60) 11F3 5.3 mi SW 1400 (20/20) 1300 (20/20) 0 (930-1500) (1300-1500) (1200-1400)

• ARTIFICIAL ISLAND RADIOLOGICAL ENVIRON SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY AL MONITORING PROGRAM

SUMMARY

DOCKET NOS. 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS (LLD)*

111 TERRESTRIAL (Cont'd)

Well Water Alpha 24 1.2 5.9 (1/12) 2S3 700 ft. NNE 5.9 (1/12) 1.8 (2/12) 0 CpCi/L) (5.9) (5.9) (1. 7-1.8)

Beta 24 1.0*** 3.3 (12/12) 3E1 4.1 mi NE 10 (12/12) 10.0 (12/12) 0 (2.7-4.4) (8.8-11) (8.8-11.0)

K-40 24 3.4 (12/12) 3E1 4. 1 mi NE 9.8 (12/12) 9.8 (12/12) 0 (3.0-3.6) (6.5-12) (6.5-12)

H-3 24 150 260 (3/12) 2S3 700 ft. NNE <LLD <LLD 0

\J1 (140-350) l.O Sr-89 8 1.0 <LLD <LLD <LLD 0 Sr-90 8 0.6 <LLD <LLD <LLD 0 Gamma K-40 24 35 64 (1/12) 2S3 700 ft NNE 64 (1/12) <LLD 0 (64) (64)

I-131 24 0.6 <LLD <LLD <LLD 0 RA-NAT 24 7.4 56 (10/12) 3E1 4.1 mi NE 107 (12/12) 107 (12/12) 0 (9.3-150) (56-160) (56-160)

Potable Water Raw-Treated Alpha 24 1.0 1.4 (8/24) 2F3 8.0 mi NNE 1.4 (8/24) No Control 0 (pCi/L) (0.8-3.2) (0.8-3.2) Location Beta 24 1.0*** 3.0 (24/24) 2F3 8.0 mi NNE 3.0 (24/24) No Control 0 (1.9-4.4) (1.9-4.4) Location

ARTIFICIAL.ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS (LLD)*

111 TERRESTRIAL (Cont'd)

Potable Water K-40 24 2.0 (24/24) 2F3 8.0 mi NNE 2.0 (24/24) No Control 0 Raw-Treated (1.4-3.1) (1.4-3.1) Location CpCi/L)

H-3 24 150 190 (4/24) 2F3 8.0 mi NNE 190 (4/24) No Control 0 (150-240) (150-240) Location Sr-89 8 1.0 <LLD <LLD No Control 0 Location Sr-90 8 0.8 <LLD <LLD No Control 0

°'

0 Location 1-131 24 0.6 <LLD <LLD No Control 0 Location Gamma K-40 24 35 <LLD <LLD) No Control 0 Location RA-NAT 24 7.4 13 (3/24) 2F3 8.0 mi NNE 13 (3/24) No Control 0 (5.2-27) (5.2-27) Location Fruits & Gamma Vegetables K-40 17 70 2000 (8/8) 3H5 25 mi NE 1900 (4/4) 1900 (9/9) 0 (pCi/kg-wet) (1300-2600) (1000-2800) (1000-2800)

Game Gamma (pCi/kg-wet) K-40 2 70 2000 (1/1) 11D1 3.5 mi SW 2300 (1/1) 2300(1/1) 0 (2000) (2300) (2300)

Beef Gamma (pCi/Kg-wet) K-40 70 2600 (1/1) 3E1 4.1 mi NE 2600 (1/1) No Control 0 (2600) (2600) Location

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRO SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY AL MONITORING PROGRAM

SUMMARY

DOCKET NOS. 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) CRANGE) MEASUREMENTS (LLD)*

Ill TERRESTRIAL (Cont'd)

Fodder Crops Ga11111a (pCi/kg-wet) Be-7 8 150 800 (3/8) 14F4 7.6 mi WNW 1100 (1/2) 940 (1/2) 0 (530-1100) (1100) (940)

K-40 8 85 10000 (6/6) 14F4 7.6 mi WNW 11000 (2/2) 9200 (2/2) 0 (2800-17000) (5800-17000) (6500-12000)

RA-NAT 8 48 47 (2/6) 14F4 7.6 mi WNW 59 (1/2) <LLD 0 (35-59) (59)

°' IV AQUATIC

....... Surface Water Alpha 60 2.0 2.6 (15/48) 16F1 6.9 mi NNW 3.3 (4/12) 2.3 (3/12) 0 CpCi/L) (1.4-4.7) (2.8-4.1) (2.0-2.8)

Beta 60 3.8*** 53 (48/48) 7E1 4.5 mi SE 86 (12/12) 52 (11/12) 0 (4-120) (22-120) (6-90)

H-3 20 150 330 (3/16) 11A1 0.2 mi SW 330 (3/4) <LLD 0 (130-460) (130-460)

Ga11111a K-40 60 35 85 (31/48) 7E1 4.5 mi SE 100 (11/12) 81 (7/12) 0 (30-150) (45-150) (48-130)

RA-NAT 60 7.4 8.5 (4/48) 11A1 0.2 mi SW 9 (3/12) 7 (1/12) 0 (5-15) (5-15) (7)

Co-58 60 1.6 5.5 (1/48) 11A1 0.2 mi SW 5.5 (1/12) <LLD 0 (5.5) (5.5)

Co-60 60 2.1 4.0 (1/48) 11A1 0.2 mi SW 4.0 (1/12) <LLD 0 (4.0) (4.0)

Cs-137 60 1.6 5.4 (1/48) 11A1 0.2 mi SW 5.4 (1/12) <LLD 0

.(5.4)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS (LLD)*

IV AQUATIC (Cont'd) Sr-89 4 60 <LLD <LLD <LLD 0 Blue Crabs Cshel ls)*

CpCi/kg-dry)

Sr-90 4 19D (2/2) 11A1 0.2 mi SW 190 (2/2) 170 (2/2) 0 (shells) (180-200) (180-200) (140-200)

CpCi/kg-wet) H-3 4 100 <LLD <LLD <LLD 0 (aqueous)

<LLD 0 O"I Blue crabs Sr-89 4 100 <LLD <LLD

"" (pCi/kg-wet) (flesh) sr-90 4 40 <LLD <LLD <LLD 0 (flesh)

Ganma K-40 4 70 2800 (2/2) 11A1 0.2 mi SW 2800 (2/2) 2400 (2/2) 0 (2700-2900) (2700-2900) (2200-2500)

Edible Fish Sr-89 6 75 <LLD <LLD <LLD 0 CpCi/kg-dry) (bones)

Sr-90 6 25 120 (4/4) 11A1 0.2 mi SW 170 (2/2) 100 (2/2) 0 (bones) (41-290) (41-290) (30-180)

CpCi/kg-wet) H-3 6 100 170 (1/4) 7E1 4.5 mi SE 170 (1/4) 150 (1/2) 0 (aqueous) (170) (170) (150) sr-89 6 100 <LLD <LLD <LLD 0 (flesh)

Sr-90 6 40 <LLD <LLD <LLD 0 (flesh)

Ganma K-40 6 70 2900 (4/4) 3100 (2/2) 3100 (2/2)

(2600-3100) (2700-3500) (2700-3500)

• ARTIFICIAL ISLAND RADIOLOGICAL SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY ENVIRO~ MONITORING PROGRAM

SUMMARY

DOCKET NOS. 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1993 to DECEMBER 31, 1993 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED DETECTION (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS (LLD)*

IV AQUATIC (Cont'd)

Sediment Sr-90 12 25 48 (1/10) 16A1 0. 7 mi NNW 48 (1/10) <LLD 0 CpCi/kg-dry) (48) (48)

Gal!ITia K-40 12 70 11000 (10/10) 16F1 6.9 mi NNW 18000 (2/2) 14000 (2/2) 0 (3200-18000) (17000-18000) ( 13000-16000)

Mn-54 12 28 31 (3/10) 16A1 0.7 mi NNW 35 (2/2) <LLD 0 (23-41) (29-41)

°'

w Co-58 12 15 61 (6/10) 7E1 4.5 mi SE 83 (1/2) <LLD 0 (45-83) (83)

Co-60 12 32 87 (6/10) 16A1 0.7 mi NNW 120 (2/2) <LLD 0 (34-140) (110-140)

Cs-134 12 22 59 (4/10) 16A1 0.7 mi NNW 70 (1/2) 49 (1/2) 0 (46-70) (70) (49)

Cs-137 12 20 95 (6/10) 15A1 0.3 mi NW 180 (1/2) <LLD 0 (33-180) (180)

RA-NAT 12 40 790 (10/10) 16A1 0.7 mi NNW 1600 (2/2) 720 (2/2) 0 (290-1900) (1200-1900) (590-860)

Th-232 12 110 850 (10/10) 16A1 0.7 mi NNW 1250 (2/2) 810 (2/2) 0 (430-1600) (900-1600) (790-830)

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

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

• • • Typical LLD value.

(1) TLD results for the 4th Quarter were jnvalidated by T.I. (See Program Deviations).

• APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 65

• APPENDIX B 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 Surf ace Water FPV Vegetables (Various) VGT Fodder Crops (Various)

GAM Game (Muskrat) WWA = Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of sixteen angular sectors of 22.5 degrees centered about the

• ctor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant:

s = On-site location E = 4-5 miles off-site A 0-1 miles off-site F 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site c 2-3 miles off-site H >20 miles off-site D 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, ... For example, the designation SA-WWA-3El would indicate a sample in the SGS program (?A) ,

consisting of well water (WWA) , which had been collected in sector number 3, centered at 45° (north east) with respect to the reactor site at a radial distance of 4 to 5 miles off-site, (therefore, radial distance E) . The number 1 indicates that this is sampling station #1 in that particular sector .

67

SAMPLING LOCATIONS All of -the 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 282 0.4 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; inlet cooling water bldg. IDM llSl 0.09 mi. SW of vent; service water inlet bldg. IDM llAl 0.2 mi .. SW of vent; outfall area ECH,ESF,ESS,SW 15Al 0.3 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 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

.15Dl 3.8 mi. NW of vent; Rt. 9, Augustine Beach IDM 2El 4.4 mi. NNE of vent; local farm IDM 3El 4.1 mi. NE of vent; local farm FPB,GAM,IDM,VG.

WWA 3E2 5.7 mi. NE of vent; local farm FPV 68

TABLE B-1 (cont'd)

STATION LOCATION SAMPLE TYPES 3E3 5.6 mi. NE of vent; local farm FPV 7El 4.5 mi. SE of vent; l mi. W of Mad Horse Creek ESF,ESS,SWA 9El 4.2 mi. S of vent IDM llE2 5.0 mi. SW of vent; Rt. 9 IDM l2El 4.4 mi. WSW of vent; Thomas Landing IDM l3El 4.2 mi. W of vent; Diehl House Lab IDM l6El 4.l mi. NNW of vent; Port Penn AIOI APT I IDM I SOL lFl 5.8 mi. N of vent; Fort Elfsborg AIOI APT I IDM I SOL lF2 7.l 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 6.3 mi. NNE of vent; local farm FPV,FPL,SOL 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.l mi. NE of vent; Hancocks Bridge Municipal IDM Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 4F2 6.0 mi. ENE of vent; Mays Lane, Harmersville IDM 5Fl 6.5 mi. E of vent; Canton FPV I IDM, SOL 5F3 6.4 mi. E of vent; local farm FPL 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.l mi. SE of vent; Bayside, New Jersey IDM l0F2 5.8 mi. SSW of vent; Rt. 9 IDM l 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 69

TABLE B-1 (cont'd)

~

STATION CODE STATION LOCATION SAMPLE TYPES 11F3 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 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV 14F4 7.6 mi. WNW of vent; local farm MLK,VGT,SOL 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; N. Church St. Wilmington, IDM Delaware 2Gl 12 mi. NNE of vent; Mannington Township, NJ FPV 2G2 13.5 mi. NNE of vent; local farm 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 AIOI APT I IDM Laboratory 3H5 25 mi. NE of vent; local farm FPL,FPV 70

MAP 8-i ON-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 1

M UM EXCLUSI AREA BOUNDA (901 METE )

11 7

N 9

71

MAP 8-2 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM OFF-SITE SAMPLING LOCATION 15

~

~

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~

. ci l~

.~

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~

- 8

' SE 72

APPENDIX C DATA TABLES 73

APPENDIX C

• DATA TABLES Appendix C presents the analytical results of the 1993 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1993.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1993 Concentrations of Gross Alpha Emitters . . . . . . . . . . . . . . . . . . . . 78 C-2 1993 Concentrations of Gross Beta Emitters . . . . . . . . . . . . . . . . . . . . . 80 C-3 1993 Concentrations of Strontium-89 and Strontium-90 and Gamma Emitters in Quarterly Composites . . . . . . . . . . . . . . . . . . . . 82

• C-4 AIR IODIN;E 1993 Concentrations of Iodine-131 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 DATES C-5 1993 Sampling Dates for Air Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 PRECIPITATION C-6 1993 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium and Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-7 1993 Quarterly TLD Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 1993 Monthly TLD Results... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 75

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT MILK C-9 1993 Concentrations of Iodine-131 and Gamma Emitters . . . . . . . . . . . 94 C-10 1993 Concentrations of Strontium-89 and Strontium-90 . . . . . . . . . . . 96 WELL WATER C-11 1993 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 97 C-12 1993 Concentrations of Iodine 131 and Gamma Emitters . . . . . . . . . . . 98 C-13 1993 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 POTABLE WATER C-14 1993 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 C-15 1993 Concentrations of Iodine 131 and Gamma Emitters . . . . . . . . . . . 101 C-16 1993 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 102 FOOD PRODUCTS C-17 1993 Concentrations of Gamma Emitters in Vegetables . . . . . . . . . . . . 103 C-18 1993 Concentrations of Gamma Emitters in Beef and Game ........ . 104 FODDER CROPS C-19 1993 Concentrations of Gamma Emitters . . . . . . . . . . . . . . . . . . . *...... . 105 76

DATA TABLES (cont'd.}

TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER C-20 1993 Concentrations of Gross Alpha Emitters . . . . . . . . . . . . . . . . . . . . 106 C-21 1993 Concentrations of Gross Beta Emitters . . . . . . . . . . . . . . . . . . . . . 107 C-22 1993 Concentrations of Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . 108 C-23 1993 Concentrations of Tritium in Quarterly Composites . . . . . . . . . 110 EDIBLE FISH C-24 1993 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters.................. . . . . . . . . . . . . . . 111 BLUE CRABS C-25 1993 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 SEDIMENT C-26 1993 Concentrations of Strontium-90 and Gamma Emitters . . . . . . . . . 113 SPECIAL TABLES LLDs C-27 1993 PSE&G Research and Testing Laboratory LLDs for Gamma Spectrometry.*. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 114 77

TABLE C-1 1993 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma

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

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

JANUARY 1.6+/-0.7 2. 3+/-1. 3 1.8+/-0.7 1.5+/-0.8 2.1+/-0.8 1.1+/-0.6 1.7+/-0.9 1.9+/-0.8 1.7+/-1.4 2.7+/-1.0 1.5+/-1.0 2.5+/-0.9 2.2+/-0.9 2.1+/-0.9 2.6+/-0.8 2.6+/-1.3 2.7+/-0.9 1.6+/-0.6 2.1+/-0.8 2.1+/-0.7 2.3+/-0.9 1.8+/-0.7 2. 3 +/-1.1 1.6+/-0.7 2.3+/-0.7 2.0+/-0.7 2.3+/-0.8 2.1+/-0.6 3.2+/-0.8 2.7+/-1.2 2.6+/-0.8 1.9+/-0.7 2.2+/-0.8 1.7+/-0.6 2.4+/-1.1 FEBRUARY 1.8+/-0.7 3.9+/-1.5 2.9+/-0.9 2.5+/-0.8 2.2+/-0.8 2.6+/-0.8 2.7+/-1.4 2.1+/-0.7 <l. 0 1.8+/-0.8 1.1+/-0.6 2.2+/-0.8 2.0+/-0.7 1.7+/-1.0 1.9+/-0.8 1. 7+/-1.1 2.9+/-1.0 1.7+/-0.8 1.6+/-0.8 2.8+/-0.9 2.1+/-1.2 2.4+/-0.8 2.4+/-1.3 3.4+/-0.9 3.0+/-0.8 2.8+/-0.8 3.0+/-0.8 2.8+/-0.8 MARCH 1.2+/-0.7 1.2+/-0.9 2.1+/-0.9 2.1+/-0.8 1.3+/-0.8 (1) 1.6+/-1.0 2.0+/-0.7 1. 6+/-1. 2 0.9+/-0.6 1. 2 +/-0. 6 1.1+/-0.6 0.9+/-0.5 1.3+/-0.9 2.6+/-0.8 3. 3 +/-1. 4 2.4+/-0.9 2.6+/-0.8 2.2+/-0.8 1.9+/-0.7 2.5+/-0.9

<0.8 <0.9 <0.9 <0.8 1.1+/-0.7 1.0+/-0.6 0.9+/-0.2

-....J APRIL <0.7 1.5+/-1.0 1. 3 +/-0. 7 0.9+/-0.6 <0.8 1.0+/-0.6 1.0+/-0.6 00 1.2+/-0.6 1. 3+/-1.1 1.0+/-0.7 1. 3 +/-0. 6 <0.8 1.6+/-0.7 1.2+/-0.6 1.0+/-0.5 <1.0 1. 3 +/-0. 7 2.0+/-0.7 2.0+/-0.7 1.5+/-0.6 1.5+/-0.9 1.8+/-0.7 <0.9 2.2+/-0.8 2.5+/-0.8 2.3+/-0.8 2.3+/-0.8 2.0+/-1.2 MAY 1.8+/-0.7 2. 5+/-1.4 1.8+/-0.9 2.6+/-0.8 2.0+/-0.8 2.6+/-0.8 2.2+/-0.8 1.4+/-0.6 2.4+/-1.4 1.7+/-0.8 1.9+/-0.7 2.6+/-0.9 1.4+/-0.7 1.9+/-1.0 2.3+/-0.7 2.5+/-1.6 2.6+/-0.8 2.9+/-0.8 2.4+/-0.8 2.4+/-0.8 2.5+/-0.4 2.0+/-0.7 2. 0+/-1. 3 2.1+/-0.8 1. 8 +/-0. 7 2 .1+/-0. 7 1.2+/-0.6 1.9+/-0.7 1.7+/-0.7 <l. 0 1. 2 +/-0. 7 1. 2 +/-0. 7 3.1+/-0.9 2.5+/-0.8 1.8+/-1.7 JUNE 2.9+/-1.0 <2.0 2.6+/-1.1 4. 2 +/-1. 1 3.0+/-1.1 <1.1 2.6+/-2.1 2.4+/-0.9 <1. 0 2.4+/-0.9 2.0+/-0.7 1.8+/-0.8 2.6+/-0.8 2.0+/-1.2 (2) 2.2+/-1.1 2.1+/-0.7 2.0+/-0.7 2.3+/-0.7 1.7+/-0.7 2.1+/-0.5 (2) 2.7+/-1.8 1. 7+/-1. 0 1.8+/-0.9 2. 3 +/-1. 0 2.0+/-0.8 2.1+/-0.8

TABLE C-.illllt.nt'd) 1993 CONCENTRATIONS OF GROSS

<-------------------------------- STATION ID A~EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m 3 +/- 2 sigma MONTH SA-APT-5Sl SA-APT-5Dl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JULY 2.0+/-0.7 <2.0 2.3+/-0.8 3.5+/-0.9 2.3+/-0.8 1.6+/-0.6 2.3+/-1.3 3.4+/-1.0 3.9+/-1.8 2.9+/-1.0 3.4+/-1.0 2.8+/-1.0 3. 8+/-1.1 3.4+/-0.9

<l. 0 1.6+/-1.2 <1.2 1.5+/-0.8 1.3+/-0.8 1.2+/-0.8 1.3+/-0.4 2.5+/-0.7 2. 3 +/-1. 2 1.7+/-0.7 2.8+/-0.8 2.3+/-0.7 1.5+/-0.6 2. 2+/-1. 0 AUGUST 2.1+/-0.7 1.7+/-1.2 1.8+/-0.7 2. 4+/-0. 7 1.6+/-0.6 1. 8+/-0. 6 1.9+/-0.6 1.8+/-0.6 1. 3 +/-1. 0 1.4+/-0.7 3.4+/-0.8 3.2+/-0.9 1.9+/-0.7 2. 2+/-1. 8 2.0+/-0.8 1.7+/-1.4 2.2+/-1.1 2.3+/-0.9 2.5+/-0.9 2.6+/-0.8 2.2+/-0.7 1.7+/-0.8 <l. 0 2.1+/-0.8 3.9+/-1.0 1.6+/-0.7 1.7+/-0.7 2.0+/-2.0 2.4+/-0.7 2. 3 +/-1. 3 2.0+/-0.8 2. 4+/-0. 8 2.3+/-0.8 3.1+/-0.8 2.4+/-0.7 SEPTEMBER 2.8+/-0.8 1.8+/-1.1 2.7+/-0.9 2.6+/-0.8 3.6+/-0.9 2.8+/-0.8 2.7+/-1.1

2. 2+/-0. 8 <2.0 2 .4+/-1. 0 1.9+/-0.8 1.6+/-0.8 2.0+/-0.8 2.0+/-0.5 1.7+/-0.7 2.1+/-1.3 <0.9 1.4+/-0.7 1.2+/-0.7 1.6+/-0.7 1.5+/-0.8 1.1+/-0.6 <l. 0 1.9+/-0.8 1.6+/-0.7 1.4+/-0.7 1.1+/-0.6 1.4+/-0.7 OCTOBER 1.6+/-0.7 1.0+/-0.9 1.3+/-0.7 1.8+/-0.8 1. 2 +/-0. 7 1.7+/-0.7 1.4+/-0.6 0.7+/-0.4 1.1+/-0.9 1. 2 +/-0. 5 1.7+/-0.6 (3) 2.5+/-0.7 1. 4+/-1. 4 1.1+/-0.8 2. 6 +/-1. 7 1.0+/-0.7 1.7+/-0.8 <l. 0 1.8+/-0.9 1. 5+/-1. 3 1.9+/-0.6 2.7+/-1.3 2. 4+/-0. 7 2.5+/-0.7 3.2+/-0.8 2.5+/-0.7 2.5+/-0.8

1. 3 +/-0. 6 2.6+/-1.5 1.9+/-0.7 1.8+/-0.7 (3) 1.3+/-0.7 1.8+/-1.1 NOVEMBER 1.9+/-0.7 1.0+/-0.8 2.7+/-0.7 1.0+/-0.6 1.4+/-0.6 1.3+/-0.6 1.6+/-1.3 3.4+/-0.9 3.6+/-1.5 3.6+/-0.9 4.3+/-1.0 (3) 4.3+/-1.0 3.8+/-0.9 2.0+/-0.7 <2.0 2.8+/-0.7 1.4+/-0.6 1. 6 +/-0. 8 1.9+/-0.7 2.0+/-1.0 1.6+/-0.8 <2.0 2.3+/-0.9 1.9+/-0.8 (3) 1.9+/-0.8 1.9+/-0.5 DECEMBER 1.9+/-0.7 <l. 0 (3) 2.3+/-0.8 2.3+/-0.8 2.3+/-0.8 2.0+/-1.l 2.4+/-0.8 2.1+/-1.2 2.8+/-0.8 2.4+/-0.8 2.6+/-0.8 1.9+/-0.8 2.4+/-0.7

2. 2+/-0. 7 3.0+/-1.3 1.5+/-0.6 2.4+/-0.8 2.7+/-0.8 2.3+/-0.7 2.4+/-1.0 1.9+/-0.7 1.9+/-1.1 2.6+/-0.8 2.1+/-0.8 3.2+/-0.9 2.6+/-0.8 2.4+/-1.0 AVERAGE 1. 9+/-1. 3' 2.0+/-1.6 2.0+/-1.3 2.1+/-1.6 2.1+/-1.4 2.0+/-1.4 GRAND AVERAGE 2.0+/-1.4

• Sampling dates can be found in Table C-5

• • Results reported by the QC lab, Teledyne Isotopes Inc.

(1) Power interruption ~o the sampler, caused by storm. Results not included in any averages.

(2) Extended power outage due to Transformer failure. Results not included in any averages.

(3) Equipment malfunction. Results not included in any averages.

TABLE C-2 1993 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma

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

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

JANUARY 18+/-2 22+/-3 19+/-2 19+/-3. 22+/-2 18+/-2 20+/-4 28+/-2 33+/-3 35+/-3 34+/-3 31+/-3 29+/-3 32+/-6 28+/-3 23+/-3 27+/-3 26+/-2 28+/-3 27+/-2 27+/-4 22+/-2 18+/-2 21+/-2 21+/-2 21+/-2 23+/-2 21+/-3 22+/-2 22+/-2 23+/-2 23+/-2 23+/-2 22+/-2 23+/-1 FEBRUARY 28+/-2 24+/-3 24+/-2 27+/-2 28+/-2 28+/-2 27+/-4 18+/-2 17+/-2 20+/-2 12+/-2 21+/-2 16+/-2 17+/-6 24+/-3 8.7+/-2.0 88+/-5 22+/-2 16+/-2 27+/-3 31+/-57 28+/-2 26+/-3 28+/-3 28+/-2 29+/-3 28+/-2 28+/-2 MARCH 22+/-2 32+/-3 26+/-3 30+/-2 19+/-3 ( 1) 26+/-11 18+/-2 17+/-2 18+/-2 17+/-2 13+/-2 16+/-2 17+/-4 30+/-2 25+/-3 30+/-3 29+/-2 25+/-2 28+/-2 28+/-5 9.3+/-1.8 12+/-2 10+/-2 10+/-2 11+/-2 7. 6 +/-1. 8 10+/-3 00 0 APRIL 9.0+/-1.8 11+/-2 8.7+/-2.0 8.8+/-1.7 8.4+/-1.9 9. 7+/-1. 8 9+/-2 12+/-2 16+/-2 11+/-2 10+/-2 14+/-2 14+/-2 13+/-4 15+/-2 13+/-3 18+/-2 16+/-2 10+/-2 15+/-2 15+/-5 22+/-2 23+/-3 20+/-2 22+/-2 24+/-3 19+/-2 22+/-4 MAY 21+/-2 20+/-3 21+/-3 20+/-2 23+/-2 24+/-2 22+/-3 18+/-2 14+/-2 13+/-2 15+/-2 17+/-2 16+/-2 16+/-4 24+/-2 20+/-3 23+/-2 23+/-2 25+/-3 22+/-2 23+/-3 15+/-2 16+/-3 17+/-2 15+/-2 16+/-2 15+/-2 16+/-2 19+/-2 20+/-3 13+/-2 21+/-2 22+/-2 20+/-2 19+/-6 JUNE 19+/-2 18+/-3 26+/-3 22+/-3 21+/-3 14+/-2 20+/-8 22+/-3 19+/-3 22+/-3 21+/-2 20+/-3 20+/-2 21+/-2 (2) 21+/-3 18+/-2 22+/-2 21+/-2 21+/-2 21+/-3 (2) 22+/-3 21+/-3 20+/-3 24+/-3 22+/-2 22+/-3

TABLE c - . n t ' d) 1993 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-5Dl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JULY 25+/-2 23+/-3 26+/-2 28+/-2 26+/-2 19+/-2 25+/-6 33+/-3 32+/-4. 36+/-3 32+/-3 33+/-3 36+/-3 34+/-4 19+/-2 18+/-3 20+/-3 18+/-2 18+/-2 17+/-2 18+/-2 20+/-2 20+/-3 22+/-2 20+/-2 21+/-2 16+/-2 20+/-4 AUGUST 21+/-2 18+/-3 21+/-3 20+/-2 18+/-2 17+/-2 19+/-3 26+/-2 25+/-3 35+/-3 28+/-2 29+/-2 27+/-2 28+/-7 17+/-2 27+/-3 24+/-4 24+/-3 26+/-3 26+/-3 24+/-7 26+/-3 23+/-3 27+/-3 33+/-3 27+/-2 28+/-2 27+/-7 28+/-2 32+/-4 39+/-3 32+/-3 39+/-3 38+/-3 35+/-9 SEPTEMBER 26+/-2 32+/-3 28+/-3 29+/-2 26+/-2 24+/-2 28+/-6 33+/-3 24+/-3 24+/-3 23+/-3 26+/-3 20+/-3 25+/-9 19+/-2 17+/-3 18+/-2 19+/-2 18+/-2 19+/-2 18+/-2 18+/-2 31+/-3 21+/-3 25+/-2 23+/-2 23+/-2 24+/-9 00 t-' OCTOBER 22+/-2 23+/-3 21+/-2 20+/-2 21+/-2 20+/-2 21+/-2 8.5+/-1.6 20+/-3 19+/-2 17+/-2 (3) 22+/-2 17+/-10 26+/-3 28+/-4 25+/-2 28+/-3 28+/-3 24+/-3 27+/-4 20+/-2 26+/-3 17+/-2 21+/-2 24+/-2 20+/-2 21+/-6 18+/-2 26+/-3 23+/-2 17+/-2 ( 3) 17+/-2 20+/-8 NOVEMBER 24+/-2 19+/-3 21+/-2 16+/-2 24+/-2 23+/-2 21+/-6 38+/-3 39+/-4 43+/-3 41+/-3 (3) 43+/-3 41+/-5 23+/-2 25+/-3 24+/-2 23+/-2 25+/-2 24+/-2 24+/-2 20+/-2 24+/-3 27+/-3 29+/-3 (3) 26+/-2 25+/-7 DECEMBER 22+/-2 32+/-4 (3) 28+/-3 23+/-2 30+/-3 27+/-9 36+/-3 35+/-3 36+/-3 40+/-3 35+/-3 32+/-3 36+/-5 18+/-2 19+/-3 18+/-2 20+/-2 22+/-2 19+/-2 19+/-3 28+/-2 25+/-3 26+/-2 24+/-2 27+/-3 23+/-2 26+/-4 AVERAGE 22+/-13 23+/-13 24+/-23 23+/-14 23+/-12 22+/-13 GRAND AVERAGE 23+/-15

• Sampling dates can be found in Table C-5

• • Results reported by the QC lab, Teledyne Isotopes Inc.

(1) Power interruption to the sampler, caused by a storm. Results not included in any averages.

(2) Extended power outage due to Transformer failure. Results not included in any averages.

(3) Equipment malfuncti?n. Results not included in any averages.

TABLE C-3 1993 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* AND GAMMA EMITTERS**

IN QUARTERLY COMPOSITES OF AIR PARTICULATE Results in Uni ts of 10* 3 pCi /m3 +/- 2 sigma STATION ID SAMPLING PERIOD <-- STRONTIUM --> <-- GAMMA EMITTERS -->

SR-89 SR-90 BE-7 C0-58 SA-APT-5S1 12-29-92 to 03-29-93 <0.3 <0.2 57+/-5 <0.1 SA-APT-5D1 (1) 12-29-92 to 03-29-93 <1.0 <0.2 62+/-6 <0.3 SA-APT-16E1 12-28-92 to 03-29-93 <0.3 <0.2 56+/-4 <0.3 SA-APT-1F1 12-29-92 to 03-29-93 <0.3 <0.2 55+/-4 <0.1 SA-APT-2F2 12-29-92 to 03-29-93 <0.4 <0.3 53+/-4 <0.2 SA-APT-3H3 (C) 12-28-92 to 03-29-93 <0.4 <0.3 60+/-5 <0.2 SA-APT-5S1 03-29-93 to 06-28-93 71+/-5 <0.1 SA-APT-5D1 (1) 03-29-93 to 06-28-93 90+/-9 <0.5 SA-APT-16E1 03-29-93 to 06-28-93 78+/-6 <0.1 SA-APT-1F1 03-29-93 to 06-28-93 80+/-5 <0.2 SA-APT-2F2 03-29-93 to 06-28-93 82+/-5 <0.1 SA-APT-3H3 CC) 03-29-93 to 06-28-93 92+/-5 <0.1 SA-APT-5S1 06-28-93 to 09-27-93 68+/-5 <0.2 SA-APT-5D1 (1) 06-28-93 to 09-27-93 90+/-9 <0.5 SA-APT-16E1 06-28-93 to 09-28-93 75+/-6 <0.3 SA-APT-1F1 06-28-93 to 09-27-93 76+/-5 <0.1 SA-APT-2F2 06-28-93 to 09-27-93 74+/-5 <0.2 SA-APT-3H3 (C) 06-28-93 to 09-27-93 75+/-5 <0.1 SA-APT-5S1 09-27-93 to 12-27-93 48+/-4 1.2+/-0.3 SA-APT-5D1 (1) 09-27-93 to 12-27-93 73+/-7 <0.3 SA-APT-16E1 09-28-93 to 12-27-93 52+/-4 <0.2 SA-APT-1F1 09-27-93 to 12-27-93 57+/-3 <0.1 SA-APT-2F2 09-27-93 to 12-27-93 42+/-4 <0.2 SA-APT-3H3 (C) 09-27-93 to 12-27-93 47+/-4 <0.1 AVERAGE 67+/-29

• Strontium results are corrected for decay to sample stop date.

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table c-27

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

(C) Control Station (1) Results by Teledyne Isotopes, Inc.

82

T~4 1993 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3

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

MONTH SA-AI0-581 SA-AI0-5Dl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control)

JANUARY <12 <20 <7.4 <10 <3.4 <4.4

<8.8 <20 <2.8 <9.1 <4.1 <7.6

<8.1 <10 <8.0 <4.0 <11 <2.7

<5.8 <10 <4.0 <3.2 <11 <9.1

<7.1 <20 <4.9 <4.1 <13 <4.1 FEBRUARY <8.8 <20 <7.7 <4.4 <8.7 <5.3

<6.3 <8.0 <7.7 <3.4 <7.5 <2.8

<5.0 <10 <11 <7.6 <8.4 <4.7

<8.2 <9.0 <8.7 <4.2 <12 <6.2 MARCH <9.6 <10 <6.3 <11 <5.1 (1)

<8.7 <20 <9.2 <8.6 <8.9 <3.2

<7.9 <9.0 <6.4 <7.2 <8.8 <6.8 00 w <7.1 <9.0 <5.0 <3.5 <8.1 <5.6 APRIL <6.4 <10 <11 <6.0 <2.2 <12

<6.0 <20 <4.8 <4.4 <11 <3.3

<10 <10 <5.8 <3.2 <5.8 <8.3

<5.6 <10 <4.8 <5.7 <12 <4.7 MAY <6.3 <20 <3.1 <4.5 <7.9 <4.9

<11 <10 <5.3 <3.5 <4.5 <9.4

<4.4 <20 <9.2 <9.8 <7.1 <3.6

<3.8 <20 <4*. 7 <9.6 <5.6 <9.6

<4.6 <20 <4.9 <12 <9.3 <4.7 JUNE <6.6 <20 <14 <3.3 <27 <8.0

<5.2 <20 <5.0 <5.4 <4.6 <2.2 (2) <10 <3.8 <8.0 <3.6 <5.7 (2) <30 <5.8 <5.5 <10 <6.2

TABLE C-4 (Cont'd) 1993 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3

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

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

JULY <4.8 <9.0 <4.8 <8.6 <8.2 <6.2

<9.2 <10 <4.3 <5.8 <10 <3.8

<8.3 <10 <6.1 <7.8 <6.3 <4.9

<12 <20 <11 <2.6 <8.2 <8.4 AUGUST <3.9 <10 <5.6 <6.6 <8.7 <8.2

<3.9 <20 <11 <6.5 <5.9 <6.9

<13 <10 <10 <4.5 <8.5 <6.0

<3.8 <10 <3.6 <11 <16 <2.1

<8.4 <20 <8.1 <6.9 <3.1 <10 SEPTEMBER <6.7 <7.0 <16 <4.1 <1. 9 <4.8

<6.5 <30 <6.0 <6.1 <15 <5.0

<6.7 <9.0 <10 <7.0 <3.8 <3.5

<12 <10 <13 <12 <3.2 <5.9 OCTOBER <19 <10 <2.5 <4.6 <10 <8.4

<4.3 <9.0 <13 <5.8 (3) <4.3

<5.6 <10 <8.6 <11 <6.3 <5.0

<5.6 <10 <7.3 <4.8 <17 <10

<11 <9.0 <3.4 <7.0 (3) <5.1 NOVEMBER <4.7 <10 <3.2 <6.0 <2.7 <2.7

<12 <20 <7.4 <5.6 (3) <4.2

<9.2 <8.0 <8.9 <5.4 <5.5 <2.5

<3.8 <20 <2.9 <2.6 (3) <5.9 DECEMBER <6.2 <20 (3) <7.8 <3.5 <5.7

<1.4 <10 <3.8 <4.5 <2.6 <5.3

<6.4 <10 <5.3 <2.8 <5.5 <5.7

<4.2 <10 <6.2 <6.3 <3.9 <3.7

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

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

• • • Results reported by the QC lab, Teledyne Isotopes Inc.

(1) Power interruption*to the sampler, caused by storm. Results not included in any averages.

(2).ended power outage due to Transformer failur Results not included in any averages .

(3) ipment malfunction. Results not included i averages.

• T 1993 SAMPLING DATES FOR AIR SAMPLES

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

MONTH 5Sl 5Dl 16El lFl 2F2 3H3 (Control)

JANUARY 12-29-92 12-29-92 12-28-92 12-29-92 12-29-92 12-28-92 to to to to to to 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 01-04-93 to to to to to to 01-12-93 01-11-93 01-11-93 01-11-93 01-11-93 01-11-93 01-12-93 01-11-93 01-11-93 01"'-11-93 01-11-93 01-11-93 to to to to to to 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 01-18-93 to to to to to to 01-25-93 01-25-93 01-25-93 01-25-93 01-25-*93 01-25-93 00 01-25-93 01-25-93 01-25-93' 01-25-93 01-25-93 01-25-93 lJ'1 to to to to to to 02-01-93 02-01-93 02-01-93 02-01-93 02-01-93 02-01-93 FEBRUARY 02-01-93 02-01-93 02-01-93 02-01-93 02-01-93 02-01-93 to to to to to to 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 02-08-93 to to to to to to 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 02-16-93 to to to to to to 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 02-22-93 to to to to to to 03-01-93 03-01-93 03-01-93 03-01-93 03-01-93 03-01-93 03-01-93 03-01-93 03-01-93 03.:.01-93 03-01-93 03-01-93 MARCH to to to to to to 03-08-93 03-08-93 03-08-93 03-08-93 03-08-93 0 3 - 0 8 - 9 3 (!)

03-08-93 03-08-93 03-08-93 03-08-93 03-08-93 03-08.-93 to to to to to to 03-15-93 03-15-93 03-15-93 03-15-93 03-15-93 03-15-93

TABLE C-5 (Cont'd) 1993 SAMPLING DATES FOR AIR SAMPLES

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

MONTH 581 5Dl 16El lFl 2F2 3H3 Control MARCH 03-15-93 03-15-93 03-15-93 03-15-93 03-15-93 03-15-93 to to to to to to 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 03-22-93 to to to to to to 03-29-93 03-29-93 03-29-93 03-29-93 03-29-93 03-29-93

• APRIL 03-29-93 03-29-93 03-29-93 03-29-93 03-29-93 03-29-93 to to to to to to 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 04-05-93 to to to to to to 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 04-12-93 to to to to to to 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 04-19-93 to to to to to to 04-26-93 04-26-93 04-27-93 04-26-93 04-26-93 04-26-93 MAY 04-26-93 04-26-93 04-27-93 04-26-93 04-26-93 04-26-93 to to to to to to 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 05-03-93 to to to to to to 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 05-10-93 to to to to to to 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 05-17-93 to. to to to to to 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 05-24-93 to to to to to to 06-01-93 06-01-93 06-01-93 06-01-93 06-01-93 06-01-93

TABLE C.ont'd) 1993 SAMPLING DATES FOR AIR SAMPLES

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

MONTH SSl SDl 16El lFl 2F2 3H3 Control JUNE 06-01-93 06-01-93 06-01-93 06-01-93 06-01-93 06-01-93 to to to to to to 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 06-07-93 to to to to to to 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 06-14-93 to 2 to to to to to 06-22-93 06-22-93 06-22-93 06-22-93 06-22-93 06-21-93 06-22-93 06-22-93 06-22-93 06-22-93 06-22-93 06-21-93 to 2 to to to to to 06-28-93 06-28-93 06-28-93 06-28-93 06-28-93 06-28-93 JULY 06-28-93 06-28-93 06-28-93 06-28-93 06-28-93 06-28-93 to to to to to to 00 07-06-93 07-06-93 07-06-93 07-06-93 07-06-93 07-06-93

-....J 07-06-93 07-06-93 07-06-93 07-06-93 07-06-93 07-06-93 to to to to to to 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 07-12-93 to to to to to to 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 07-19-93 to to to to to to 07-26-93 07-26-93 07-26-93 07-26-93 07-26-93 07-26-93 AUGUST 07-26-93 07-26-93 07-26-93 07-26-93 07-26-93 07-26-93 to to to to to to 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 08-02-93 to. to to to to to 08-10-93 08-10-93 08-11-93 08-10-93 08-10-93 08-09-93

TABLE C-5 (Cont'd) 1993 SAMPLING DATES FOR AIR SAMPLES

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

MONTH 5Sl 5Dl 16El lFl 2F2 3H3 Control AUGUST 08-10-93 08-10-93 08-11-93 08-10-93 08-10-93 08-09-93 to to to to to to 08-17-93 08-17-93 08-16-93 08-16-93 08-16-93 08-16-93 08-17-93 08-17-93 08-16-93 08-16-93 08-16-93 08-16-93 to to to to to to 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 08-23-93 to to to to to to 08-30-93 08-30-93 08-30-93 08-30-93 08-30-93 08-30-93 SEPTEMBER 08-30-93 08-30-93 08-30-93 08-30-93 08-30-93 08-30-93 to to to to to to 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 09-07-93 to to to to to to 00 09-13-93 09-13-93 09-13-93 09-13-93 09-13-93 09-13-93 00 09-13-93 09-13-93 09-13-93 09-13-93 09-13-93 09-13-93 to to to to to t.o 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 09-20-93 to to to to to to 09-27-93 09-27-93 09-28-93 09-27-93 09-27-93 09-27-93 OCTOBER 09-27-93 09-27-93 09-28-93 09-27-93 09-27-93 09-27-93 to to to to to to 10-04-93 10-04-93 10-04-93 10-04-93 10-04-93 10-04-93 10-04-93 10-04-93 lQ-04-93 10-04-93 10-04-93 10-04-93 to to to to to to 10-12-93 10-12-93 10-12-93 10-12-93 10-12-93<3> 10-12-93 10-12-93 10-12-93 10-12-93 10-12-93 10-12-93 10-12-93 to to to to to to 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 10-18-93 to to to to to 10-25-93 10-25-93 10-25-93 10-25-93 10-25-93 10-25-93

TABLE c 1993 SAMPLING DATES FOR AIR SAMPLES

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

MONTH 5Sl 5Dl 16El lFl 2F2 3H3 Control OCTOBER 10-25-93 10-25-93 10-25-93 10-25-93 10-25-93 10-25-93 to to to to to to 11-01-93 11-01-93 11-01-93 11-01-93 11-01-93<3> 11-01-93 11-01-93 11-01-93 11-01-93 11-01-93 11-01-93 11-01-93 NOVEMBER to to to to to to 11-08-93 11-08-93 11-09-93 11-08-93 11-08-93 11-08-93 11-08-93 11-08-93 11-09-93 11-08-93 11-08-93 11-08-93 to to to to to to 11-15-93 11-15-93 11-15-93 11-15-93 11-15-93<3> 11-15-93 11-15-93 11-15-93 11-15-93 11-15-93 11-15-93 11-15-93 to to to to to to 11-22-93 11-22-93 11-23-93 11-22-93 11-22-93 11-22-93 11-22-93 11-22-93 11-23-93 11-22-93 11-22-93 11-22-93 to to to to to to 00 11-29-93 11-29-93 11-29-93 11-29-93 11-29-93<3> 11-29-93

\0 11-29-93 11-29-93 11-29-93 11-29-93 11-29-93 11-29-93 DECEMBER to to to to to to 12-06-93 12-06-93 11-29-93 3 12-06-93 12-06-93 12-06-93 12-06-93 12-06-93 12-06-93 12-06-93 12-06-93 12-06-93 to to to to to to 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 12-13-93 to to to to to to 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 12-20-93 to to to to to 12-27-93 12-27-93 12~27-93 12-27-93 12-27-93 12-27-93

( 1! Power interruption to the sampler,caused by a storm.

(2 Extended power outage due to Transformer failure.

(3 Equipment malfunction.

TABLE C-6 1993 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 EMITTER----->

SAMPLING PERIOD ALPHA BETA TRITIUM BE-7 K-40 RA-NAT 12-29-92 to 01-25-93 2.6+/-2.0 <0.9 130+/-80 66+/-19 60+/-17 <2.4 01-25-93 to 03-01-93 <2.5 1.3+/-0.6 <130 61+/-23 <21 <4.5 03-01-93 to 03-29-93 <2.7 0.9+/-0.6 <140 55+/-10 <14 <1.9 03-29-93 to 04-26-93 <2.8 3.5+/-0.9 <180 120+/-17 56+/-22 <2.3 04-26-93 to 06-01-93 <1.4 4.5+/-0.9 <190 79+/-12 <15 <2.3 06-01-93 to 06-28-93 1 <4.3 2.6+/-0.8 <160 39+/-15 <40 <ll 06-28-93 to 07-26-93 (2) (2) (2) (2) (2) (2) 07-26-93 to 08-30-93 (2) (2) (2) (2) (2) (2) 08-30-93 to 09-27-93 0.7+/-0.5 2.2+/-0.4 <160 <12 <16 8.3+/-2.0 09-27-93 to 11-01-93 <0.6 l. l+/-O .4 <170 <8.8 <15 7.3+/-1.8 11-01-93 to 11-29-93 <0.5 0.5+/-0.3 <110 <17 <18 <l. 8 11-29-93 to 12-27-93 <0.4 0.8+/-0.3 <110 39+/-13 <15 <2.0 AVERAGE 1. 8+/-2. 7 50+/-69

• Management audit analyses, not required by Technical Specifications.

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-27.

(1) Rainwater sampler was moved to location 2F6 on June 28.

(2) Results for these two months were invalidated because of automatic sprinkl system activation near the rain collector. Rainwater sampler was moved ba location 2F2 on August 30.

90

TABLE C-7 1993 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULT 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 4.6+/-0.4 4.6+/-0.6 5.1+/-0.6 (1) 4.8+/-0.6 SA-IDM-5Sl 4.9+/-0.2 3.9+/-0.2 6. 4+/-1. 6 (1) 5.1+/-2.5 SA-IDM-6S2 5.5+/-0.4 4.3+/-0.3 6 .2+/-1. 2 (1) 5.3+/-1.9 SA-IDM-7Sl 6 ;9+/-1.1 5.6+/-0.6 6. 9+/-1. 3 (1) 6. 5+/-1. 5 SA-IDM-lOSl 7.8+/-3.3 5.2+/-0.6 6.2+/-1.0 (1) 6.4+/-2.6 SA-IDM-llSl 9.8+/-2.2 6.1+/-0.8 7.2+/-1.5 (1) 7.7+/-3.8 SA-IDM-4D2 5.7+/-0.5 4.9+/-0.6 6.8+/-1.8 (1) 5.8+/-1.9 SA-IDM-5Dl 5.4+/-0.5 4.5+/-0.3 6.6+/-1.2 (1) 5.5+/-2.1 SA-IDM-lODl 5.6+/-0.5 4.8+/-0.4 6.9+/-0.6 (1) 5.8+/-2.1 SA-IDM-14Dl 5.2+/-0.4 4.8+/-0.3 7. 0+/-1.6 (1) 5.7+/-2.3 SA-IDM-2El 5.4+/-0.5 4.3+/-0.5 7 .1+/-1.1 (1) 5.6+/-2.8 SA-IDM-3El 5.1+/-0.3 3.9+/-0.3 6.3+/-1.0 (1) 5.1+/-2.4 SA-IDM-9El 6.1+/-0.7 5.2+/-0.6 6.6+/-0.5 (1) 6. 0+/-1.4 SA-IDM-11E2 5.9+/-0.6 5.0+/-0.3 8.7+/-2.4 (1) 6.5+/-3.9 SA-IDM-12El 5.2+/-0.5 4.7+/-0.4 6. 9+/-1. 6 (1) 5.6+/-2.3 SA-IDM-13El 4.5+/-0.4 4.0+/-0.4 5 .4+/-1. 5 (1) 4. 6+/-1.4 SA-IDM-16El 5.6+/-0.5 4.1+/-0.2 6.5+/-1.0 (1) 5 .4+/-2 .4

-IDM-lFl 5.6+/-0.2 4.0+/-0.4 6.2+/-0.9 (1) 5.3+/-2.3

-IDM-2F2 4.5+/-0.l 3.2+/-0.3 6.5+/-2.2 (1) 4.7+/-3.3

-IDM-2F5 5.5+/-0.4 4.1+/-0.3 6. 7+/-2. 6 (1) 5.4+/-2.6 SA-IDM-2F6 5.4+/-0.3 4.0+/-0.3 5.2+/-0.6 (1) 4.9+/-1.5 SA-IDM-3F2 5.0+/-0.3 3.8+/-0.2 6.1+/-1.2 (1) 5.0+/-2.3 SA-IDM-3F3 5.0+/-0.3 3.7+/-0.2 5. 7+/-1. 5 (1) 4. 8+/-2. 0 SA-IDM-5Fl 5.3+/-0.3 3.9+/-0.3 6 .2+/-1.8 (1) 5.1+/-2.3 SA-IDM-6Fl 4.7+/-0.3 3.2+/-0.1 6. 2+/-1. 6 (1) 4.7+/-3.0 SA-IDM-7F2 4.3+/-0.1 3.0+/-0.2 4. 7+/-1. 3 (1) 4.0+/-1.8 SA-IDM-10F2 5.8+/-0.4 4.7+/-0.3 6.4+/-1.0 (1) 5.6+/-1.7 SA-IDM-llFl 5.9+/-0.4 4.6+/-0.5 7 .2+/-1.2 (1) 5. 9+/-2. 6 SA-IDM-12Fl 5.5+/-0.3 4.5+/-0.2 6.2+/-0.3 (1) 5. 4+/-1. 7 SA-IDM-13F2 5.4+/-0.3 4.5+/-0.2 5.5+/-0.7 (1) 5 .1+/-1.1 SA-IDM-13F3 5.6+/-0.5 4.4+/-0.3 5. 1+/-1. 6 (1) 5. 0+/-1.2 SA-IDM-13F4 5.5+/-0.5 4.4+/-0.3 4.2+/-0.8 (1) 4.7+/-1.4 SA-IDM-14F2 6.4+/-0.6 5.1+/-0.3 5.4+/-0.6 (1) 5.6+/-1.4 SA-IDM-15F3 5.4+/-0.5 4.9+/-0.4 5.4+/-1.0 (1) 5.2+/-0.6 SA-IDM-16F2 5.2+/-0.4 4.0+/-0.2 4.1+/-0.5 (1) 4.4+/-1.3 SA-IDM-1G3 (C) 6.4+/-0.5 4.9+/-0.5 5.3+/-0.4 (1) 5.5+/-1.6 SA-IDM-3Gl (C) 5.7+/-0.6 4.5+/-0.5 4.8+/-0.7 (1) 5. 0+/-1-. 2 SA-IDM-lOGl (C) 5.8+/-0.5 4.7+/-0.4 4.8+/-0.3 (1) 5 .1+/-1. 2 SA-IDM-16Gl (C) 5.9+/-0.3 4.8+/-0.5 5.1+/-0.5 (1) 5. 3+/-1. l SA-IDM-3Hl (C) 4.3+/-0.3 4.1+/-0.2 4.1+/-0.4 (1) 4.2+/-0.2 SA-IDM-3H3 (C) 5.8+/-0.2 4.6+/-0.3 4.8+/-0.6 (1) 5.1+/-1.3 AVERAGE 5. 6+/-1. 9 4. 4+/-1. 2 6.0+/-2.0 (1)

GRAND AVERAGE 5.3+/-2.2 The standard month + 30.4 days.

\ Control Station (1) The 4th Quarter TLD results were invalidated by Teledyne due to anomalous readings by their instrumentation. (See Program Deviations) 91

TABLE C-8 1993 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 5.9+/-0.5 6.5+/-0.4 6.4+/-0.4 9. 2+/-3 .1 5. 2+/-0. 5 6.6+/-0.6 SA-IDM-5Sl 5.4+/-0.4 5.8+/-0.8 5.2+/-0.3 6.4+/-0.6 4.6+/-0.2 5.4+/-0.3 SA-IDM-6S2 5.9+/-0.7 6.9+/-1.1 5.8+/-0.5 6.9+/-0.6 4.9+/-0.4 6.0+/-0.9 SA-IDM-7Sl 7.2+/-0.6 7.6+/-0.7 7.4+/-0.8 8.0+/-0.9 6.2+/-0.6 7.6+/-0.6 SA-IDM-lOSl 7. 2+/-1. 4 7.8+/-1.0 7.0+/-0.8 7.6+/-0.6 5.6+/-0.5 6.8+/-0.5 SA-IDM-llSl 11+/-3 11+/-3 9.6+/-2.5 8. 3+/-1. 2 6.2+/-1.1 7. 6+/-1. 2 SA-IDM-5Dl 6.0+/-0.6 6.1+/-0.2 6.2+/-0.5 6.7+/-0.3 4.9+/-0.6 6.0+/-0.3 SA-IDM-lODl 6.0+/-0.8 6.6+/-0.6 6.4+/-0.7 7.2+/-0.5 5.5+/-0.5 6.5+/-0.4 SA-IDM-14Dl 5.7+/-0.8 6.3+/-0.3 6.1+/-0.4 6.6+/-0.3 5.0+/-0.3 7.1+/-0.4 SA-IDM-2El 5.6+/-0.7 6.2+/-0.3 6.0+/-0.3 6.7+/-0.6 4.9+/-0.3 6.2+/-0.3

\.0 5.9+/-0.4 5.6+/-0.4 6. 3 +/-0 .1 4.7+/-0.3 5.8+/-0.4 N SA-IDM-3El 5.3+/-0.6 SA-IDM-13El 5.3+/-0.5 6.1+/-0.4 6.0+/-0.2 6.3+/-0.3 4.6+/-0.3 6.1+/-0.4 SA-IDM-16El 5.8+/-0.6 6.4+/-0.4 6.3+/-0.2 6.8+/-0.3 5.3+/-0.3 7.0+/-2.4 SA-IDM-lFl 5.9+/-0.7 6.4+/-0.4 6.2+/-0.6 6.8+/-0.4 5.1+/-0.4 6.2+/-0.6 SA-IDM-2F2 5.1+/-0.5 5.8+/-0.7 5.5+/-0.2 5.8+/-0.3 4.1+/-0.2 5.4+/-0.2 SA--IDM-2F6 5.6+/-0.6 6.0+/-0.3 6.1+/-0.3 6.5+/-0.4 5.1+/-0.4 6.2+/-0.3 SA-IDM-5Fl 5.6+/-0.5 5.9+/-0.4 5.9+/-0.3 6.4+/-0.4 4.7+/-0.3 5.9+/-0.3 SA-IDM-6Fl 5.2+/-0.6 5.4+/-0.3 5.4+/-0.2 5.6+/-0.2 4.1+/-0.2 5.2+/-0.4 SA-IDM-7F2 4.8+/-0.4 4.9+/-0.3 5.3+/-0.2 5.7+/-0.2 3.8+/-0.1 4.9+/-0.2 SA-IDM-llFl 6 .1+/-1. 0 6.7+/-0.3 6.7+/-0.2 7.2+/-0.6 5.7+/-0.6 7.0+/-0.4 SA-IDM-13F4 5.8+/-0.9 6.6+/-0.4 6.5+/-0.3 6.7+/-0.3 5.0+/-0.4 6.3+/-0.2 SA-IDM-3Gl (C) 5.9+/-0.4 6.4+/-0.2 6.8+/-0.7 7.0+/-0.4 5.4+/-0.4 6.7+/-0.5 SA-IDM-3Hl (C) 5.5+/-0.4 6.1+/-0.3 5.5+/-0.3 6.3+/-0.2 5.1+/-0.5 6.3+/-0.2 SA-IDM-3H3 (C) 6.8+/-1.1 7.0+/-0.4 7.1+/-0.4 7.1+/-0.8 5.6+/-0.4 6.7+/-0.3 AVERAGE 6.0+/-2.4 6.5+/-2.3 6. 3+/-1. 8 6.8+/-1.6 5.1+/-1.2 6. 3+/-1. 4

TABLE C-8 Cont'd) 1993 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 5.8+/-0.5 5.7+/-0.6 6.6+/-0.5 7.0+/-0.6 6.1+/-0.6 7.0+/-0.2 6.5+/-2.0 SA-IDM-5Sl 5.1+/-0.5 5.5+/-0.4 5.7+/-0.4 6.6+/-0.8 5.3+/-0.7 6.3+/-0.3 5. 6+/-1. 2 SA-IDM-6S2 5.1+/-0.3 6.1+/-0.4 6.3+/-0.4 6.9+/-0.5 5.7+/-0.5 6.7+/-0.5 6.1+/-1.4 SA-IDM-7Sl 6.5+/-0.9 7.1+/-0.3 7.8+/-0.5 7.9+/-0.6 7.2+/-0.7 8.5+/-0.7 7.4+/-1.3 SA-IDM-lOSl 5.9+/-0.6 6.3+/-0.4 6.8+/-0.6 7.0+/-0.6 6.2+/-0.4 6.9+/-0.4 6.8+/-1.3 SA-IDM-llSl 5.9+/-1.3 7.1+/-0.6 7.8+/-1.2 7.7+/-1.1 6. 6+/-1. 3 8.3+/-1.2 8.1+/-3.4 SA-IDM-5Dl 5.4+/-0.5 5.7+/-0.3 6.0+/-0.6 6.7+/-0.5 5.8+/-0.5 7.0+/-0.6 6. 0+/-1. 2 SA-IDM-lODl 6.4+/-0.9 6.5+/-0.6 7.0+/-0.6 7.5+/-0.5 6.0+/-0.6 7.4+/-0.5 6. 6+/-1. 2 SA-IDM-14Dl 6.1+/-0.6 6.8+/-0.5 7.0+/-0.6 7.7+/-0.3 6.0+/-0.3 7.3+/-0.3 6.5+/-1.5 SA-IDM-2El 5.7+/-0.6 6.0+/-0.6 6.3+/-0.6 6.5+/-0.5 5.6+/-0.3 7.0+/-0.7 6.1+/-1.l

\0 SA-IDM-3El 4.7+/-0.4 5.7+/-0.1 6.0+/-0.8 6.2+/-0.5 5.3+/-0.6 6.2+/-0.1 5.6+/-1.l w SA-IDM-13El 5.9+/-0.2 5.9+/-0.3 5.9+/-0.4 6.8+/-0.3 5.2+/-0.2 7.0+/-0.4 5. 9+/-1. 3 SA-IDM-16El 5.8+/-0.6 6.1+/-0.4 6.2+/-0.3 7.1+/-0.4 5.8+/-0.3 7.5+/-0.2 6.3+/-1.3 SA-IDM-lFl 5.6+/-0.5 6.2+/-0.3 6.6+/-0.6 7.1+/-0.5 6.1+/-0.7 7.2+/-0.6 6.3+/-1.2 SA-IDM-2F2 4.6+/-0.3 5.4+/-0.5 5.4+/-0.2 5.7+/-0.3 4.8+/-0.4 6.5+/-0.4 5.3+/-1.3 SA-IDM-2F6 5.3+/-0.5 5.7+/-0.2 6.4+/-0.6 6.3+/-0.3 5.6+/-0.3 7.1+/-0.4 6.0+/-1.1 SA-IDM-5Fl 5.2+/-0.7 6.0+/-0.8 6.2+/-0.5 6.5+/-0.5 5.4+/-0.3 6.9+/-0.3 5.9+/-1.2 SA-IDM-6Fl 4.4+/-0.5 5.5+/-0.3 5.6+/-0.3 6.2+/-0.6 4.9+/-0.3 6.5+/-0.3 5. 3+/-1. 3 SA-IDM-7F2 4.2+/-0.4 5.0+/-0.4 4.8+/-0.2 5.4+/-0.2 4.5+/-0.4 5.7+/-0.2 A.9+/-1.l SA-IDM-llFl 6.4+/-0.7 6.3+/-0.3 7.0+/-0.6 7.5+/-0.4 6.4+/-0.5 7.8+/-0.7 6.7+/-1.2 SA-IDM-13F4 5.7+/-0.5 6.1+/-0.4 6.7+/-1.0 7.3+/-0.8 6.0+/-0.6 7.3+/-0.3 6. 3+/-1. 3 SA-IDM-3Gl (C) 6.0+/-0.5 6.4+/-0.2 6.8+/-0.3 7.0+/-0.5 6.4+/-0.5 7.5+/-0.4 6.5+/-1.1 SA-IDM-3Hl (C) 6.0+/-1.5 5.9+/-0.3 6.2+/-0.3 6.6+/-0.4 5.7+/-0.4 7.0+/-1.1 6.0+/-1.0 SA-IDM-3H3 (C) 5.9+/-0.9 7.0+/-1.0 7.3+/-0.5 7.5+/-0.2 6.6+/-0.3 8.1+/-0.4 6.9+/-1.3 AVERAGE 5.6+/-1.3 6.1+/-1.1 6.4+/-1.4 6. 9+/-1. 3 5.8+/-1.3 7 .1+/-1.3 GRAND AVERAGE 6.2+/-1.9

• The standard month = ~0.4 days (C) Control Station

TABLE C-9 1993 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID *** <-GAMMA EMITTERS->

SAMPLING PERIOD I-131 K-40 SA-MLK-2F7 01/04-05/93 <0.3 1300+/-87 SA-MLK-11F3 01/03-04/93 <0.4 1400+/-86 SA-MLK-14F4 01/04-05/93 <0.1 1400+/-79 SA-MLK-3Gl (C) 01/04-05/93 <0.3 1300+/-100 SA-MLK-2F7 02/07-08/93 <0.3 1300+/-84 SA-MLK-11F3 02/08-09/93 <0.1 1300+/-85 SA-MLK-14F4 02/08-09/93 <0.3 1500+/-79 SA-MLK-3Gl (C) 02/07-08/93 <0.2 1300+/-99 SA-MLK-2F7 03/07-08/93 <0.3 1400+/-96 SA-MLK-11F3 03/08-09/93 <0.3 1500+/-80 SA-MLK-14F4 03/08-09/93 <0.2 1300+/-84 SA-MLK-3Gl (C) 03/07-08/93 <0.5 1300+/-79 SA-MLK-2F7 04/04-05/93 <0.4 1300+/-98 SA-MLK-11F3 04/04-05/93 <0.3 1400+/-82 SA-MLK-14F4 04/05-06/93 <0.4 1400+/-84 SA-MLK-3Gl (C) 04/04-05/93 <0.3 1400+/-84 SA-MLK-2F7 04/18-19/93 <0.3 1300+/-97 SA-MLK-11F3 04/18-19/93 <0.4 1400+/-67 SA-MLK-14F4 04/19-20/93 <0.4 1400+/-86 SA-MLK-3Gl (C) 04/18-19/93 <0.3 1300+/-84 SA-MLK-2F7 05/02-03/93 <0.2 1400+/-95 SA-MLK-11F3 05/03-04/93 <0.2 1400+/-69 SA-MLK-14F4 05/03-04/93 <0.4 1400+/-86 SA-MLK-3Gl (C) 05/02-03/93 <0.3 1300+/-85 SA-MLK-2F7 05/16-17/93 <0.3 1400+/-99 SA-MLK-11F3 05/17-18/93 <0.3 1400+/-90 SA-MLK-14F4 05/17-18/93 <0.1 1400+/-86 SA-MLK-3Gl (C) 05/16-17/93 <0.2 1300+/-65 SA-MLK-2F7 06/07-08/93 <0.2 1400+/-85 SA-MLK-11F3 06/07-08/93 <0.3 1400+/-67 SA-MLK-14F4 06/07-08/93 <0.4 1300+/-73 SA-MLK-3Gl (C) 06/06-07/93 <0.5 1300+/-97 SA-MLK-2F7 06/21-22/93 <0 .4 1400+/-83 SA-MLK-11F3 06/22-23/93 <0.4 1400+/-86 SA-MLK-14F4 06/21-22/93 <0.3 1400+/-76 SA-MLK-3Gl (C) 06/21-22/93 <0.3 1200+/-100 SA-MLK-2F7 07/06-07/93 <0.2 1300+/-73 SA-MLK-11F3 07/06-07/93 <0.2 1300+/-87 SA-MLK-14F4 07/06-07/93 <0.4 1300+/-85 SA-MLK-3Gl (C) 07/05-06/93 <0.4 1400+/-98 SA-MLK-2F7 07/19-20/93 <0.4 930+/-58 SA-MLK-11F3 07/18-19/93 <0.2 1400+/-89 SA-MLK-14F4 07/18-19/93 <0.2 1400+/-90 SA-MLK-3Gl (C) 07/19-20/93 <0 .4 1300+/-72 94

TABLE C-9 (Cont'd)

• 1993 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK STATION ID Results in Units of pCi/L +/- 2 sigma SAMPLING

<-GAMMA EMITTERS->

PERIOD I-131 K-40 SA-MLK-2F7 08/02-03/93 <0.3 1400+/-96 SA-MLK-11F3 08/02-03/93 <0.2 1400+/-76 SA-MLK-14F4 08/02-03/93 <0.4 1300+/-68 SA-MLK-3Gl (C) 08/01-02/93 <0.3 1300+/-85 SA-MLK-2F7 08/16-17/93 <0.2 1300+/-88 SA-MLK-11F3 08/15-16/93 <0.2 1400+/-79 SA-MLK-14F4 08/15-16/93 <0.1 1400+/-72 SA-MLK-3Gl (C) 08/16-17/93 <0.4 1400+/-65 SA-MLK-2F7 09/07-08/93 <0.7 1400+/-100 SA-MLK-11F3 09/07-08/93 <0.3 1400+/-77 SA-MLK-14F4 09/07-08/93 <0.2 1300+/-68 SA-MLK-3Gl (C) 09/06-07/93 <0.2 1200+/-84 SA-MLK-2F7 09/19-20/93 <0.4 1200+/-87 SA-MLK-11F3 09/20-21/93 <0.2 1400+/-80 SA-MLK-14F4 09/20-21/93 <0.5 1300+/-66 SA-MLK-3Gl (C) 09/19-20/93 <0.2 1200+/-95 SA-MLK-2F7 10/03-04/93 <0.2 1300+/-86 MLK-11F3 10/04-05/93 <0.2 1400+/-77 MLK-14F4 10/04-05/93 <0.2 1300+/-66

• MLK-3Gl (C) 10/03-04/93 <0.8 1300+/-100 SA-MLK-2F7 10/17-18/93 <0.4 1300+/-110 SA-MLK-11F3 10/18-19/93 <0.3 1400+/-81 SA-MLK-14F4 10/18-19/93 <0.2 1300+/-70 SA-MLK-3Gl (C) 10/17-18/93 <0.4 1300+/-87 SA-MLK-2F7 il/08-09/93 <0.2 1200+/-80

. SA-MLK-11F3 11/08-09/93 <0.8 1400+/-64 SA-MLK-14F4 11/08-09/93 <0.2 1300+/-78 SA-MLK-3Gl (C) 11/07-08/93 <0.4 1400+/-98 SA-MLK-2F7 11/22-23/93 <0.3 1200+/-80 SA-MLK-11F3 11/22-23/93 <0.2 1500+/-63 SA-MLK-14F4 11/22-23/93 <0.1 1500+/-110 SA-MLK-3Gl (C) 11/22-23/93 <0.2 1300+/-100 SA-MLK-2F7 12/06-07/93 <0.1 1300+/-74 SA-MLK-11F3 12/06-07/93 <0.2 1300+/-88 ..

SA-MLK-14F4 12/06-07/93 <0.2 1400+/-68 SA-MLK-3Gl (C) 12/06-07/93 <0.2 1300+/-69 AVERAGE 1340+/-170

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

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-27.

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

(C) Control Station.

95

TABLE C-10 1993 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 7/05-06/93 <1.4 4.7+/-0.6 SA-MLK-11F3 7/05-06/93 <0.8 1.1+/-0.3 SA-MLK-14F4 7/06-07/93 <l. 0 1. 8+/-0. 4 SA-MLK-3Gl 7/05-06/93 <1.1 2.2+/-0.4 (Control)

AVERAGE 2.5+/-3~1

• Strontium 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.

96

TABLE C-11 1993 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 01/25/93 <2.4 3.1+/-0.8 3.0+/-0.3 <130 SA-WWA-3El (C) 01/25/93 <0.4 10+/-1 9.8+/-1.0 <130 SA-WWA-2S3 03/1/93 <3.2 2.8+/-0.8 3.3+/-0.3 <140 SA-WWA-3El (C) 03/1/93 <2.9 8. 8+/-1. 2 8.6+/-0.9 <140 SA-WWA-2S3 03/29/93 <l. 7 3.9+/-0.9 3.5+/-0.3 140+/-80 SA-WWA-3El (C) 03/29/93 <2.0 11+/-1 6.5+/-0.6 <130 SA-WWA-2S3 04/26/93 <3.0 2.9+/-0.8 3.6+/-0.4 <140 SA-WWA-3El (C) 04/26/93 <3.2 9. 4+/-1. 2 11+/-1 <140 SA-WWA-2S3 05/24/93 <2.5 4.4+/-0.8 3.5+/-0.3 <200 SA-WWA-3El (C) 05/24/93 <1.8 9.7+/-1.2 9.7+/-1.0 <210 SA-WWA-2S3 06/28/93 <4.5 2.7+/-0.7 3.0+/-0.3 <180 SA-WWA-3El (C) 06/28/93 <4.7 11+/-1 9.3+/-0.9 <180 SA-WWA-2S3 07/27/93 <2.1 3.3+/-0.8 3.2+/-0.3 300+/-110 SA-WWA-3El (C) 07/26/93 <2.4 11+/-1 9.0+/-0.9 <180 SA-WWA-2S3 08/31/93 <0.8 3.1+/-0.5 3.5+/-0.3 <150 41-WWA-3E1

-WWA-2S3 (C) 08/30/93 09/27/93 1.7+/-0.9

<1.5 10+/-1 3.5+/-0.5 11+/-1 3.4+/-0.3

<160 350+/-110

-WWA-3El (C) 09/27/93 <1.5 11+/-1 11+/-1 <170 SA-WWA-2S3 10/25/93 5.9+/-1.8 3.7+/-0.5 3.4+/-0.3 <160 SA-WWA-3El (C) 10/25/93 <l. 7 10+/-1 8.4+/-0.8 <160 SA-WWA-2S3 11/29/93 <15 3.2+/-0.5 3.4+/-0.3 <120 SA-WWA-3El (C) 11/29/93 1. 8+/-1. 2 10+/-1 11+/-1 <120 SA-WWA-2S3 12/27/93 <1.4 3.0+/-0.5 3.6+/-0.4 <110 SA-WWA-3El (C) 12/27/93 <1.3 9.8+/-0.8 12+/-1 <110 AVERAGE 3.3+/-1.0 3.4+/-0.4 SA-WWA-2S3 10+/-1 9.8+/-3.1 SA-WWA-3El (C)

GRAND AVERAGE 6.7+/-7.1 6.6+/-6.9 (C) Control Station 97

TABLE C-12 1993 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN WELL WATER Results in Units of pCi/L +/- 2 sigma

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

STATION ID SAMPLING PERIOD I-131 K-40 RA-NAT SA-WWA-2S3 01/25/93 <0.2 <22 9.3+/-2.0 SA-WWA-3El (C) 01/25/93 <0.2 <19 160+/-7 SA-WWA-2S3 03/01/93 <0.2 <14 84+/-4 SA-WWA-3El (C) 03/01/93 <0.2 <16 56+/-4 SA-WWA-2S3 03/29/93 <0.1 <21 100+/-6 SA-WWA-3El (C) 03/29/93 <0.2 <20 140+/-5 SA-WWA-2S3 04/26/93 <0.4 <8.9 <4.5 SA-WWA-3El (C) 04/26/93 <0.2 <14 96+/-5 SA-WWA-2S3 05/24/93 <0.2 <24 150+/-7 SA-WWA-3El (C) 05/24/93 <0.4 <22 78+/-6 SA-WWA-2S3 06/28/93 <0.1 <19 70+/-5 SA-WWA-3El (C) 06/28/93 <0.1 <19 89+/-5 SA-WWA-2S3 07/27/93 <0.3 <60 14+/-3 SA-WWA-3El (C) 07/26/93 <0.3 <15 83+/-4 SA-WWA-2S3 SA-WWA-3El (C)

SA-WWA-2S3 SA-WWA-3El (C)

SA-WWA-2S3 (C)

SA-WWA-3El 08/31/93 08/30/93 09/27/93 09/27/93 10/25/93 10/25/93

<0.2

<0.3

<0.3

<0.2

<0.3

<0.2

<22

<16 64+/-25

<15

<17

<16 10+/-2 120+/-5 20+/-4 58+/-4

<7.4 150+/-4 SA-WWA-2S3 11/29/93 <0.3 <17 10+/-3 SA-WWA-3El (C) 11/29/93 <0.1 <24 120+/-8 SA-WWA-2S3 12/27/93 <0.2 <22 90+/-5 SA-WWA-3El (C) 12/27/93 <0.2 <21 130+/-8 AVERAGE SA-WWA-2S3 47+/-98 SA-WWA-3El (C) 107+/-70 GRAND AVERAGE 77+/-103

• 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-27.

(C) Control Station 98

TABLE C-13 1993 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 01/25/93 to 03/29/93 <0.6 <0.5 SA-WWA-3El ( C) 01/25/93 to 03/29/93 <0.5 <0.4 SA-WWA-2S3 04/26/93 to 06/28/93 <0.8 <0.5 SA-WWA-3El ( C) 04/26/93 to 06/28/93 <0.8 <0.5 SA-WWA-2S3 07/27/93 to 09/27/93 <1.1 <0.8 SA-WWA-3El ( C) 07/26/93 to 09/27/93 <0.5 <0.4 SA-WWA-2S3 09/27/93 to 12/27/93 <0.8 <0.6 SA-WWA-3El (C) 09/27/93 to 12/27/93 <0.6 <0.5

• Strontium results are corrected for decay to stop date of collection period.

• Control Station 99

TABLE C-14 1993 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 01/1-31/93 <2.8 3.5+/-0.8 2.2+/-0.2 <130 Treated 01/1-31/93 <2.5 3.3+/-0.8 2.2+/-0.2 <130 Raw 02/1-28/93 <3.9 2.9+/-0.7 2.0+/-0.2 <130 Treated 02/1-28/93 <3.7 2.8+/-0.7 1.9+/-0.2 <130 Raw 03/1-31/93 <2.1 4.4+/-0.9 2.2+/-0.2 150+/-80 Treated 03/1-31/93 <l. 8 2.4+/-0.7 2.1+/-0.2 <160 Raw 04/1-30/93 <4.6 3.7+/-0.8 2.2+/-0.2 180+/-90 Treated 04/1-30/93 <2.3 3.3+/-0.8 2.1+/-0.2 <140 Raw 05/1-31/93 3. 2+/-2 .1 3.3+/-0.7 2.1+/-0.2 <200 Treated 05/1-31/93 <1.6 2.8+/-0.7 2.0+/-0.2 <190 Raw 06/1-30/93 <3.8 2.7+/-0.7 1.4+/-0.1 200+/-100 Treated 06/1-30/93 <4.0 2.7+/-0.7 1.6+/-0.2 <160 Raw 07/1-31/93 <2.1 2.9+/-0.8 1.4+/-0 .1 <170 Treated 07/1-31/93 <l. 9 2.8+/-0.8 1.6+/-0.2 <170 Raw 08/1-31/93 1.0+/-0.5 2.3+/-0.4 1.6+/-0.2 <160 Treated 08/1-31/93 0.9+/-0.6 3.0+/-0.5 1.6+/-0.2 <160 Raw 09/1-30/93 0.8+/-0.6 2.5+/-0.4 1.7+/-0.2 <170 Treated 09/1-30/93 <l. 0 2.5+/-0.4 1.7+/-0.2 <160 Raw 10/1-31/93 1.3+/-0.7 1.9+/-0.4 1.8+/-0.2 240+/-110 Treated 10/1-31/93 <1.0 2.1+/-0.4 1.8+/-0.2 <180 Raw 11/1-30/93 <0.8 3.2+/-0.5 2.0+/-0.2 <110 Treated 11/1-30/93 1.5+/-0.8 2.9+/-0.5 2.1+/-0.2 <110 Raw 12/1-31/93 1.0+/-0.6 4.3+/-0.5 2.9+/-0.3 <110 Treated 12/1-31/93 1.2+/-0.8 4.0+/-0.5 3.1+/-0.3 <110 AVERAGE Raw 3 .1+/-1. 5 2.0+/-0.8 Treated 2. 9+/-1. 0 2.0+/-0.8 GRAND AVERAGE 3. 0+/-1. 3 2.0+/-0.8 100

TABLE C-15 1993 CONCENTRATIONS OF IODINE-131* AND GAIV!MA EMITTERS**

IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3 SAMPLING <-------GAIVIMA EMITTERS------>

TYPE PERIOD I-131 K-40 RA-NAT Raw 01/01-31/93 <0.2 <18 <2.3 Treated 01/01-31/93 <0.2 <40 <2.6 Raw 02/01-28/93 <0.2 <22 <5.6 Treated 02/01-28/93 <0.2 <45 <2.2 Raw 03/01-31/93 <0.2 <17 27+/-0.3 Treated 03/01-31/93 <0.4 <20 <2.1 Raw 04/01-30/93 <0.3 <19 <2.5 Treated 04/01-30/93 <0.4 <45 <5.0

-eated Raw w

05/01-31/93 05/01-31/93 06/01-30/93

<0.3

<0.4

<0.3

<21

<17

<14

<2.4

<2.6

<2.0 Treated 06/01-30/93 <0.4 <38 <2.5 Raw 07/01-31/93 <0.4 <14 <6.0 Treated 07/01-31/93 <0.4 <14 <6.3 Raw 08/01-31/93 <0.3 <16 <2.0 Treated 08/01-31/93 <0.6 <14 <6.3 Raw 09/01-30/93 <0.2 <14 <l. 8 Treated 09/01-30/93 <0.2 <14 6. 8+/-1. 9 Raw 10/01-31/93 <0.6 <18 <2.6 Treated 10/01-31/93 <0.2 <14 5. 2+/-1. 9 Raw 11/01-30/93 <0.2 <13 <l. 6 Treated 11/01-30/93 <0.1 <21 <2.2 Raw 12/01-31/93 <0 .4 <15 <1.7 Treated 12/01-31/93 <0.2 <12 <1.3

• 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-27.

101

TABLE C-16 1993 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 01-01-93 to 03-31-93 <0.6 <0.5 Treated 01-01-93 to 03-31-93 <0.6 <0.5 Raw 04-01-93 to 06-30-93 <0.8 <0.6 Treated 04-01-93 to 06-30-93 <0.8 <0.6 Raw 07-01-93 to 09-30-93 <0.7 <0.6 Treated 07-01-93 to 09-30-93 <0.5 <0.5 Raw 10-01-93 to 12-31-93 <0.6 <0.5 Treated 10-01-93 to 12-31-93 <0.6 <0.5

• Strontium results are corrected for decay to stop date of collection period.

102

TABLE C-17 1993 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 SA-FPV-3E3 05/18/93 Asparagus 1800+/-210 SA-FPV-2Gl (C) 05/18/93 Asparagus 1700+/-200 AVERAGE 1750+/-140 SA-FPL-3H5 (C) 08/04/93 Cabbage 2800+/-200 SA-FPL-5F3 08/04/93 Cabbage 2400+/-180 AVERAGE 2600+/-570 SA-FPV-2F4 08/03/93 Corn 2500+/-220 SA-FPV-14F3 08/04/93 Corn 2600+/-160 SA-FPV-lGl (C) 08/03/93 Corn 2400+/-180 SA-FPV-3H5 (C) 08/03/93 Corn 2300+/-210 AVERAGE 2450+/-260 SA-FPV-14F3 08/04/93 Peppers 1300+/-150 SA-FPV-2F4 08/04/93 Peppers 2100+/-170

-FPV-3H5 (C) 08/02/93 Peppers 1000+/-130 PV-lGl (C) 08/03/93 Peppers 1900+/-220 FPV-2G2 (C) 08/04/93 Peppers 1700+/-130 AVERAGE 1600+/-890 SA-FPV-2F4 08/04/93 Tomatoes 1900+/-170 SA-FPV-14F3 08/04/93. Tomatoes 1700+/-160 SA-FPV-lGl (C) 08/03/93 Tomatoes 2000+/-190 SA-FPV-3H5 (C) 08/03/93 Tomatoes 1500+/-160 AVERAGE 1780+/-440 GRAND AVERAGE 1980+/-970

• All other gamma emitters searched for were <LLD; typical LLDS are given in Table C-27.

103

TABLE C-18 1993 CONCENTRATIONS OF GAMMA EMITTERS* IN BEEF AND GAME Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <--GAMMA EMITTERS-->

STATION ID DATE SAMPLE TYPE K-40 SA-FPB-3El 4/19/93 Beef 2600+/-160 SA-GAM-llDl 2/02-06/93 Muskrat 2300+/-160 (Control)

SA-GAM-3El 1/25-29/93 Muskrat 2000+/-200 AVERAGE Muskrat 2150+/-420

• All other gamma emitters searched for were <LLD; typical LLDS are given in Table C-27.

• • • Although not required by Technical Specifications, beef samples are normally collected twice each year. However, due to uncertain availability of the sample, only one beef sample was obtained in 1993.

104

TABLE C-19 1993 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <-------GAMMA EMITTERS--------->

STATION ID DATE SAMPLE TYPE K-40 Be-7 RA-NAT SA-VGT-11F3 09/18/93 Silage 5300+/-210 530+/-61 <28 SA-VGT-2F7 10/03/93 Corn Silage 2800+/-210 760+/-100 35+/-10 SA-VGT-14F4 09/08/93 Silage 5800+/-370 1100+/-150 <26 SA-VGT-3Gl (C) 09/07/93 Silage 6500+/-480 940+/-160 <16 AVERAGE 5100+/-3200 830+/-490 SA-VGT-llF3 11/20/93 Soybeans 16000+/-240 <48 <19 SA-VGT-2F7 11/08/93 Soybeans 14000+/-600 <150 <22 SA-VGT-3Gl (C) 11/07/93 Soybeans 12000+/-510 <43 <15 SA-VGT-14F4 10/03/93 Soybeans 17000+/-690 <48 59+/-22 AVERAGE 14800+/-4400 All other gamma emitters searched for were <LLD; typical LLDS are given in Table C-27.

Control Station 105

TABLE C-20 1993 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

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

SAMPLING SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-19-93 <1.4 <1. 3 <1.3 <1. 3 <1. 3 02-11-93 4.7+/-3.6 <3.7 <3.4 <3.5 <3.5 03-12-93 <3.4 <3.4 <3.2 <3.1 <2.2 04-08-93 <1. 9 <1. 8 2. 2+/-1. 5 <1. 6 4.1+/-2.0 05-07-93 <2.1 <2.6 <2.2 <2.0 <2.1 06-10-93 3.4+/-2.0 2. 0+/-1. 7 2.6+/-1.8 <3.3 3.5+/-2.1 3. 0+/-1. 2 I-' 07-09-93 <2.0 2 .1+/-1. 6 2. 0+/-1. 6 <1. 7 2.9+/-1.8 2.1+/-0.9 0

O"I 1.4+/-1.1 <1.3 <1.7 <1.4 <1. 5 08-06-93 09-09-93 <2.0 <1. 3 <2.2 1.5+/-1.2 <2.7 10-10-93 <2.9 <1.4 <3.9 <1. 5 2.8+/-2.1 11-11-93 2 .1+/-1. 4 2.8+/-2.0 1. 8+/-1.1 1.6+/-1.2 <1.4 1.9+/-1.1 12-09-93 <1.6 <1. 5 <2.8 2.5+/-1.7 <1.4

• 1 1993 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

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

SAMPLING SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-19-93 48+/-7 14+/-4 65+/-8 19+/-4 17+/-5 33+/-45 02-11-93 79+/-9 81+/-9 120+/-12 35+/-5 53+/-7 74+/-64 03-12-93 60+/-7 44+/-6 88+/-9 20+/-4 31+/-5 49+/-53 04-08-93 8.0+/-3.0 <3.5 <3.5 <3.5 4.0+/-2.5 5+/-4 05-07-93 14+/-3 6.2+/-2.4 22+/-4 6. 8+/-2. 5 4.7+/-2.2 11+/-14 06-10-93 45+/-6 53+/-7 85+/-9 26+/-4 36+/-5 49+/-45 07-09-93 91+/-9 76+/-8 97+/-10 46+/-6 56+/-7 73+/-44 1--'

0 08-06-93 110+/-7 90+/-6 120+/-7 71+/-5 52+/-4 89+/-56

-....J 09-09-93 110+/-9 85+/-8 120+/-10 69+/-5 68+/-5 90+/-47 10-10-93 61+/-5 56+/-4 90+/-6 32+/-4 18+/-3 51+/-56 11-11-93 73+/-4 60+/-3 110+/-5 61+/-3 53+/-3 71+/-45 12-09-93 12+/-2 9.3+/-1.8 32+/-3 4.8+/-1.5 5.1+/-1.5 13+/-22 AVERAGE 59+/-71 48+/-65 79+/-81 33+/-48 33+/-46 GRAND AVERAGE 51+/-71

TABLE C-22 SAMPLING 1993 CONCENTRATIONS OF GAMMA EMITTERS*

DATE IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

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

STATION ID K-40 RA-NAT Co-58 Co-60 Cs-137 SA-SWA-llAl 01-19-93 99+/-18 <2.2 <0.9 <0.4 <0.9 SA-SWA-12Cl (C) 01-19-93 <23 <2.2 <0.8 <0.5 <0.9 SA-SWA-7El 01-19-93 45+/-12 <5.4 <0 .*9 <0.8 <0.6 SA-SWA-1F2 01-19-93 <17 <4.0 <0.7 <0.3 <0.8 SA-SWA-16Fl 01-19-93 52+/-24 <2.3 <0.4 <0.5 <0.8 SA-SWA-llAl 02-11-93 <9.2 <1.6 <0.6 <1.4 <0.4 SA-SWA-12Cl (C) 02-11-93 <11 <2.2 <0.6 <0.5 <0.2 SA-SWA-7El 02-11-93 150+/-24 <2.3 <1.1 <1.4 <1.1 SA-SWA-1F2 02-11-93 30+/-9 <0.6 <0.3 <0.4 <0.3 SA-SWA-16Fl 02-11-93 <25 <4.0 <0.5 <0.5 <0.8 SA-SWA-llAl 03-12-93 100+/-19 <2.2 <0.9 <1.1 <l. 0 SA-SWA-12Cl (C) 03-12-93 48+/-18 <1. 9 <0.3 <0.7 <0.6 SA-SWA-7El 03-12-93 110+/-29 <1.6 <1.1 <1.6 <0.8 SA-SWA-1F2 03-12-93 82+/-25 <4.3 <1.0 <0.6 <1.2 SA-SWA-16Fl 03-12-93 66+/-18 <1. 9 <0.7 <0.7 <0.8 SA-SWA-llAl 04-08-93 62+/-25 15+/-2 <1.1 <1.1 <0.7 SA-SWA-12Cl (C) 04-08-93 <19 <2.4 <1.1 <0.5 <0.9 SA-SWA-7El 04-08-93 59+/-23 <6.8 <1.1 <0.7 <3.0 SA-SWA-1F2 04-08-93 <14 <2.0 <0.7 <0.5 <0.7 SA-SWA-16Fl 04-08-93 <13 <2.0 <0.7 <l. 0 <0.9 SA-SWA-llAl 05-07-93 56+/-19 <4.4 <1.6 <0.7 <0.6 SA-SWA-12Cl (C) 05-07-93 <16 <1.9 <1.4 <l. 0 <0.8 SA-SWA-7El 05-07-93 62+/-27 <6.3 <0.6 <1.5 <0.9 SA-SWA-1F2 05-07-93 <19 <2.2 <0.5 <1.1 <0.8 SA-SWA-16Fl 05-07-93 <18 <2.2 <0.9 <0.8 <0.9 SA-SWA-llAl 06-10-93 <29 <3.6 <1.4 <l. 7 <l. 0 SA-SWA-12Cl (C) 06-10-93 110+/-21 <4.1 <1.1 <0.9 <l. 0 SA-SWA-7El 06-10-93 69+/-23 <2.4 <0.5 <0.8 <1.3 SA-SWA-1F2 06-10-93 47+/-17 <l. 7 <0.4 <0.8 <0.4 SA-SWA-16Fl 06-10-93 95+/-18 <2.2 <1.1 <0.9 <0.6 SA-SWA-11Al 07-09-93 72+/-24 <3.1 <0.7 <3.2 <1. 0 SA-SWA-12Cl (C) 07-09-93 70+/-23 <3.4 <0.6 <1.1 <0.5 SA-SWA-7El 07-09-93 150+/-25 <l. 9 <0.7 <0.5 <1.0 SA-SWA-1F2 07-09-93 83+/-21 <1.6 <0.7 <0.8 <l. 0 SA-SWA-16Fl 07-09-93 86+/-33 <2.0 <1.1 <0.6 <l. 0 108

TABLE C-22 (Cont'd) 1993 CONCENTRATIONS OF GAMMA EMITTERS*

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

STATION ID DATE K-40 RA-NAT Co-58 Co-60 Cs-137 SA-SWA-llAl 08-06-93 150+/-21 <2.9 <1. 0 <0.9 <0.4 SA-SWA-12Cl (C) 08-06-93 67+/-23 <2.3 <3.3 <1.2 <1.1 SA-SWA-7E1 08-06-93 140+/-21 <5.8 <0.5 <0.6 <0.5 SA-SWA-1F2 08-06-93 120+/-36 <2.3 <0.9 <1. 0 <1.1 SA-SWA-16F1 08-06-93 93+/-24 <6.5 <0.7 <0.8 <0.7 SA-SWA-11A1 09-09-93 100+/-25 <5.5 5.5+/-1.8 4. 0+/-1. 7 5. 4+/-1. 8 SA-SWA-12C1 (C) 09-09-93 130+/-26 <2.2 <1.2 <1.4 <1.3 sA.:swA-7El 09-09-93 140+/-28 <3.2 <0.9 <0.5 <0.7 SA-SWA-1F2 09-09-93 <18 <3.1 <0.7 <0.8 <0.6 SA-SWA-16F1 09-09-93 51+/-20 <2.3 <0.9 <0.5 <0.5 SA-SWA-11A1 10-10-93 55+/-16 6.5+/-1.8 <0.4 <0.9 <0.3 SA-SWA-12C1 (C) 10-10-93 56+/-20 <2.3 <0.8 <0.3 <1.1 SA-SWA-7E1 10-10-93 61+/-28 <2.0 <0.7 <1.3 <1.1 SA-SWA-1F2 10-10-93 <25 <2.1 <0.5 <1.3 <1.1 SA-SWA-16F1 10-10-93 <21 <4.3 <0.5 <0.6 <0.8

-SWA-11Al 11-11-93 <22 5.4+/-1.8 <4.2 <0.8 <1. 0

-SWA-12C1 (C) 11-11-93 76+/-20 7. 2+/-2. 3 <0.4 <0 .4 <0.8 A-SWA-7E1 11-11-93 110+/-31 <1. 7 <1.2 <1.4 <1.2 SA-SWA-1F2 11-11-93 <42 <2.2 <0.8 <1.2 <2.4 SA-SWA-16F1 11-11-93 55+/-16 7 .4+/-1. 9 <0.8 <0.8 <0.6 SA-SWA-11A1 12-09-93 <16 <5.6 <0.8 <0.6 <0.5 SA-SWA-12C1 (C) 12-09-93 <15 <1. 8 <0.7 <0.6 <0.4 SA-SWA-7E1 12-09-93 <24 <2.3 <0.8 <0.8 <1.5 SA-SWA-1F2 12-09-93 <25 <2.5 <0.5 <1.3 <1. 0 SA-SWA-16F1 12-09-93 <18 <2.3 <0.8 <0.5 <0.4 AVERAGE 61+/-83

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-27.

Control Station 109

TABLE C-23 1993 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L +/- 2 sigma

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

SAMPLING SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE PERIOD (Control) 01-19-93 to 460+/-80 <130 <130 <130 <130 03-12-93 04-08-93 to <170 <170 <190 <200 <170 06-10-93 07-09-93 to 390+/-100 <160 <160 <170 <160 09-09-93 I-'

I-'

C> 10-10-93 to 130+/-70 <110 <110 <110 <110 12-09-93 AVERAGE 290+/-320

1993 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 in bone analyses which are reported in pCi/kg (dry)

STRONTIUM

<--- BONES ---> <---FLESH----> ***

SAMPLING TRITIUM (FLESH) <-GAMMA EMITTERS (FLESH)->

STATION ID PERIOD Sr-89 Sr-90 Sr-89 Sr-90 AQUEOUS FRACTION K-40 SA-ESF-llAl 05/28-30/93 <79 290+/-21 <25 <18 <100 2800+/-220 SA-ESF-12Cl (C) 05/28-30/93 <73 180+/-19 <30 <23 <100 2700+/-200 SA-ESF-7El 05/28-30/93 <51 100+/-13 <42 <29 <100 2600+/-200 AVERAGE 190+/-190 2700+/-200 SA-ESF-llAl 10/20-24/93 <15 41+/-9 <32 <19 <90 3100+/-190

...... SA-ESF-12Cl (C) 10/20-24/93 <41 30+/-11 <30 <19 150+/-70 3500+/-210 i-i SA-ESF-7El 10/20-24/93 <16 48+/-9 <31 <20 170+/-90 3000+/-210 AVERAGE 40+/-18 140+/-83 3200+/-530 GRAND AVERAGE 120+/-200 3000+/-650

• Strontium results are corrected for decay to sample stop date.

• • All other gamma emitters searched for were <LLD; typical LLDS are given in Table C-27.

• • • Tritium results are *reported by Teledyne Isotopes, Inc.

(C) Control Station

TABLE C-25 1993 CONCENTRATIONS OF STRONTIUM-89 AND STRONTIUM-90, TRITIUM AND GAMMA EMITTERS** IN BLUE CRABS Results in Units of pCi/kg (wet) +/- 2 sigma (Except for strontium in shell analyses which are reported in pCi/kg (dry))

<--------STRONTIUM ---------->

STATION ID SAMPLING <---FLESH---> <---SHELL----> *** GAMMA DATE Sr-89 Sr-90 Sr-89 Sr-90 TRITIUM (FLESH) EMITTERS (FLESH)

AQUEOUS FRACTION K-40 RA-NAT SA-ECH-llAl 06/28/93 <24 <15 <72 180+/-23 <100 2700+/-210 <12 SA-ECH-12Cl (C) 06/28/93 <24 <16 <70 200+/-24 <90 2200+/-210 <10 AVERAGE 190+/-20 2400+/-500 SA-ECH-llAl 09/13/93 <31 <19 <40 200+/-14 <100 2900+/-200 <11 SA-ECH-12Cl (C) 09/13/93 <31 <20 <37 140+/-13 <100 2500+/-160 38+/-9 I-'

I-' AVERAGE 170+/-60 2700+/-400 N

G~ AVERAGE 180+/-57 2600+/-600

• Strontium results are corrected for decay to sample stop date.

• • All other gamma emitters searched for were <LLD; typical LLDS are given in Table C-27.

• • • Tritium results by Teledyne Isotopes, Inc.

~ontrol Station '

• TAB 26 1993 CONCENTRATIONS OF STRONTIUM-89 AND STRONTIUM-90 AND GAMMA EMITTERS** IN SEDIMENT Results in Units of pCi/kg (dry) +/- 2 sigma

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

STATION ID SAMPLING DATE Sr-90 K-40 Mn-54 Co-58 Co-60 Cs-134 cs-137 RA-NAT Th-232 SA-ESS-llAl 06/07/93 <22 3200+/-220 <16 45+/-14 46+/-18 <20 <7.3 540+/-27 460+/-43 SA-ESS-15Al 06/07/93 <28 3700+/-180 23+/-8 48+/-8 61+/-10 <5.2 <4.8 290+/-19 430+/-40 SA-ESS-16Al 06/07/93 48+/-14 7000+/-250 41+/-11 46+/-16 110+/-11 <11 <16 1900+/-49 1600+/-86 SA-ESS-12Cl (C) 06/07/93 <25 13000+/-400 <8.4 <9.1 <38 <10 <10 860+/-44 790+/-78 SA-ESS-7El 06/07/93 <27 12000+/-410 <26 83+/-22 130+/-37 <36 94+/-19 620+/-48 790+/-86 SA-ESS-16Fl 06/07/93 <76 17000+/-610 <16 67+/-24 <20 <16 60+/-18 640+/-40 910+/-100 AVERAGE 9300+/-11000 50+/-50 68+/-86 810+/-1100 830+/-850 I-' SA-ESS-llAl 11/23/93 <25 13000+/-500 <22 <21 <19 51+/-21 130+/-17 730+/-40 800+/-120 I-' SA-ESS-15Al 11/23/93 <27 17000+/-460 <8.5 <13 <18 68+/-17 180+/-20 700+/-30 1000+/-79 w SA-ESS-16Al 11/23/93 <26 9700+/-290 29+/-12 74+/-16 140+/-13 70+/-13 71+/-13 1200+/-30 900+/-61 SA-ESS-12Cl (C) 11/11/93 <36 16000+/-360 <7.5 <8.9 <10 49+/-14 <12 590+/-22 830+/-54 SA-ESS-7El 11/11/93 <28 7100+/-320 <14 <7.9 34+/-10 46+/-16 33+/-9 590+/-24 630+/-58 SA-ESS-16Fl 11/23/93 <31 18000+/-440 <24 <9.5 <13 <10 <6.0 650+/-30 1000+/-80 AVERAGE 13500+/-8700 49+/-43 72+/-140 740+/-460 860+/-280 GRAND AVERAGE 11400+/-10400 36+/-56 53+/-94 52+/-110 780+/-830 840+/-600

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-27.

(C) Control Station

TABLE C-27 1993 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <----------AIR------------> <---------WATER--------> <-----------MILK--------->

IODINE PART! CU LATES GAMMA SCAN IODINE GAMMA SCAN IODINE ACTIVITY: 10-3 pCi /m3 10* 3 pCi/m3 pCi/L pCi/L pCi/L pCi/L GEOMETRY: 100ML 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 C0-58 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 BALA-140 15 15 CE-141 0.31 2.3 3.9 CE-144 1.1 9.2 17 RA-NAT 0.87 7.4 6.6 TH-232 1.2 7.1 12 114

• TABLE C-27 (cont'd) 1993 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <------FOOD PRODUCTS-------> FOOD & BEEF FISH SEDIMENT GREEN CHOP & GAME SHELLFISH & SOIL ACTIVITY: pCi/KG WET pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg DRY GEOMETRY: 100ml 500 ml 500 ml 500 ml 500 ml 500 ml COUNT TIME: 1000 MINS 500 MINS 500 MINS 500 MINS 500 MINS 500 MINS DELAY TO COUNT: 10 DAYS 3 DAYS 7 DAYS 5 DAYS 5 DAYS 30 DAYS NUCLIDES BE-7 0.99 59 580 44 44 90 NA-22 2.1 9.4 15 6.9 6.9 30 K-40 32 70 85 70 70 70 CR-51 9.2 25 100 41 41 125 MN-54 1.2 4.8 10 69 69 28 C0-58 1.8 8.0 13 5.3 5.3 15 FE-59 3.6 16 53 14 14 46 C0-60 2.3 7.6 21 6.8 6.8 32 ZN-65 3.6 12 38 14 14 42 2.0 10 16 10 10 36 2.2 27 30 27 27 43 NB-95 96 95 442 213 213 316000 RU-103 1.0 5.0 7.9 4.9 4.9 24 RU-106 12 49 110 38 38 109 AG-100M 2.2 8.7 19 12 12 21 SB-125 2.8 14 36 12 12 36 TE-129M 4.7 208 539 204 204 586 I-131 2 8.3 28 8.4 8.4 185 TE-132 4.4 8.5 150 15 15 7200 BA-133 CS-134 0.96 6.5 15 5.7 5.7 22 CS-136 1.5 6.1 19 7.5 7.5 46 CS-137 1.4 6.7 19 18 18 20 BA-140 6.0 35 75 35 35 240 LA-140 2.2 15 30 15 15 80 BALA-140 CE-141 1.0 5 .1 9.8 5.2 5.2 26 CE-144 4.2 20 45 24 24 52 RA-NAT 2.3 15 48 36 36 40 TH-232 6.1 31 74 29 29 110 115

APPENDIX D SYNOPSES OF ANALYTICAL PROCEDURES 117

APPENDIX D

• SYNOPSES 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 1993 Artificial Island Radiological Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . . . . 121 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123 GROSS BETA PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . . . . 124 PSE&G Analysis of Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126 POTASSIUM-40 Analysis of Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 127 TRITIUM PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 128 TI Analysis of Aqueous Fraction of Biological Material 129 IODINE-131 PSE&G Analysis of Filtered Air . . . . . . . . . . . . . . . . . . . . . . . . *.. . 130 PSE&G Analysis of Raw Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 132 STRONTIUM-89 AND STRONTIUM-90 PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . . . . 133 PSE&G Analysis of Raw Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 136 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 139 PSE&G Analysis of Vegetation, Meat and Aquatic Samples .. . 142 PSE&G Analysis of Bone and Shell . . . . . . . . . . . . . . . . . . . . . . . . . 145 Analysis of Soil and Sediment . . . . . . . . . . . . . . . . . . . . . . 148

-~&G Analysis of Samples for Stable Strontium .......... . 151

.&G 119

SYNOPSES OF ANALYTICAL PROCEDURES (cont'd)

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . . . . 153 PSE&G Analysis of Raw Milk. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 154 PSE&G Analysis of Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 155 PSE&G Analysis of Solids (combined procedures) . . . . . . . . . . . 156 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters . . . . . . . . . . . 157

• PSE&G - PSE&G Research and Testing Laboratory TI - Teledyne Isotopes' 120

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 background gas proportional counter. Along with a set of air particulate samples, clean air filter is included as a blank with an Am-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 (2.22)*(E)*(V) G = Sample gross counts .

B = Background counts (from blank filter)

T = Count time of sample and blank, mins.

E = Fractional Am-241 counting efficiency v = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 121

2-sigma error (pCi/m3 ) = (l.96*(G+B) 112 )*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/m3 ) = 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.

122

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 50°C in order to help precipitate barium sulfate. Maintaining the same te~perature 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 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 thickness 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) 123

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 background 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 e.fficiency 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 a 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, mine.

E = Fractional sr-90 counting efficiency v = Corrected air flow of sample, 2.22 = No. of dpm per pCi m'*

124

igma error (pCi/m3) = (l.96*(G+B) 11 2 )*A (G-B)

A = Gross beta activity, pCi/m3 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/m3) = 4.66 * (B) 1/2 (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, mins.

125

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a 1.0 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)*(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 Sr-90 source V = Sample volume, liters S = Normalized efficiency regressio equation as a function of thick 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = (1.96*(G+B) 1/ 2 )*A (G-B)

A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank sample) 126

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 concentrations (similar to that of the samples) are first prepared. An aliquot of each sample and standard is pipetted into stoppered erlenmeyer flasks. In addition, a duplicate sample, water blank and a quality control sample are likewise pipetted into their respective flasks.

A solution consisting of 1% sodium is added to all flasks to achieve a minimum of 2,000mg/L of sodium in the final sample volume. The spectrophotometer generates the calibration curve based upon standard absorbance and sample absorbance is converted to concentration automatically. If the concentration of any sample is greater than the highest standard, the sample is either diluted, the burner head is rotated 90°, or a less sensitive wavelength is selected.

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.SS*C 0.85 = Proportionality constant for converting ppm to pCi/L C = Potassium concentration, ppm 127

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 Sml of sample, lOml of Instagel, and O.lml-0.2ml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Sml 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.

J 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 spike 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:

1.96*(G/T2 +B/T 2 ) 112 *(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 12 *(1000) 2.22*(V)*(E)*(T) 128

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS A weighed aliquot of fish or crab flesh is placed in a suitable flask or container having a connection to a vacuum system. Water is removed from the sample by vacuum distillation. Three or ten milliliters (depending on the total volume of water distilled) are added to a scintillating cocktail to a total of 20 milliliters.

The resultant mixture is counted in a Packard automatic sample changing liquid scintillator for at least 100 minutes. The efficiency of the counting system is determined with a tritium standard traceable to NIST. A quench correction to the counting efficiency is automatically applied to the results. The calculation of the tritium activity is related to the original, equivalent weight of the sample in units of pCi/g (wet).

129

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF AIR IODINE Approximately 300m3 of air is drawn through a SOml 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 SOml 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/m3 ) = 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 collection to start of acquisition J. = 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 = No. of dpm per pCi 2-sigma error (pCi/m3 ) = 1.96*(GC+BC) 112*R N

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

The LLD (pCi/m3 ) = 4.66*(BC) 1 / 2 *D (2.22)*(E)*(A)*(T)*(V) 130

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 SOml 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:

Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V)

N = Net counts under photopeak D = Decay correction factor Atl*EXP(l.t2) 1-EXP(-ltl) 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, L 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1. 96* (GC+BC) 1' 2 *R .

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

The LLD (pCi/L) = 4. 66* (BC) 112 *D (2.22)*(E)*(A)*(T)*(V) 131

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR IODINE-131 Stable iodine carrier is equilibrated with Sodium Bisulfite in a 4-liter volume of water, and then filtered, before two separate SOml batches of anion exchange resin are introduced to extract iodine. After each batch has been stirred in the water .

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:

Result (pCi/L) = N*D =R (2.22)*(E)*(A)*(T)*(V)

N = Net counts under photopeak D = Decay correctio? factor Atl*EXP(lt2) 1-EXP(-?,.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A= 0.693/nuclide half l' E = Detector efficiency A = Gamma abundance factor (no. o photons per disintegration)

T = Acquisition live time, mins.

v = Sample volume, L 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1.96*(GC+BC) 1' 2 *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)*(E)*(A)*(T)*(V) 132

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 strontium 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/m3 ) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)

= W2 e 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(15)/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 133

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 Fare regression coefficients.)

N2 = X - Y, where X and Y are re.count 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 ) =

2* (X+Y) + (Xl+Yl)*Fl 2 1 1 2 1 * (Wl*W2)

[ W1 2 . W1 2 1 (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for sr-90 (pCi/m3 ) =

4.66* (X+Y) + (Xl+Yl)*Fl~ 1/2

[

W12 W1 2 J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/m3 ) = 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 normal*ized 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) 134

.5)/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/m3 ) = 2 * <sa 2+s9 2 >2

• W3 (Nl - N7*(l+Rl*Il))

SS =~X+Y) + (Xl+Yl)*Fl~l/2

[w1 2 w1 2 J

S9 = (Xl+Yl) 112 All other variables are as previously defined.

ing the same variable definitions, the LLD for Sr-89 (pCi/m3 )

4. 66* csa 2+s9 2 >1 12 135

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 precipitation. 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')*(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(lS)/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) 136

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*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 ng the sarrie variable definitions as above, 2-sigma error for Sr-90 (pCi/L) =

12* (X+Y) + (Xl+Yl)*Fl2 ll/Z * (Wl*W2)

~ w12 w1 2 J (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) =

~

.66* (X+Y) + (Xl+Yl)*Fl 2 1/2 w1 2 w1 2

~

Calculation of Sr-89 Activity:

Sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(15)/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)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) 137

E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to S r - 9 0 .

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 (pqi/L) = 2* (S8 2 +s9 2 ) 1 / 2

• W3 (Nl - N7*(l+Rl*Il))

2 SS =[(X+Y) + (Xl+Yl)*Fl 1 w1 2 w1 2 S9 = (Xl+Yl) 112 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 ) 11 2 138

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 coprecipitation 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.

Calculation of Sr-90 Activity:

sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E')*(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(lS)/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) - (l + Rl*Il)*Fl)

Il = 1 - EXP ((-0.693/2.667)*tl) 139

I2 =

tl =

t2 =

1 - EXP ((-0.693/2.667)*t2)

Elapsed time from Y-90 strip to first count 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/L) =

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

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

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) =

G- 66* (X+Y) + (Xl+Yl) *Flj112 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 57 = 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.)

NG N7

=

=

Nl - N7*(1 + Rl*Il)

(N2 - Fl*Nl)/Wl (This represents counts due to sr-90)

• 140

. *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 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* (S8 2+s9 2 ) 1/ 2

• W3 (Nl - N7*(l+Rl*Il))

SS = [ (X+Y) + (Xl+Yl)*F~ 112 L w12 w1 2

J S9 = (Xl+Y1) 1 12 All other variables are as previously defined.

ping the same variable definitions, the LLD for Sr-89 (pCi/L) =

• 66* <sa2+s92 >112 141

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT, CRAB SHELL AND AQUATIC The samples are weighed (recorded as "wet" weight) as received, before being placed in an oven to dry at 100°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 9006C for 1/2 hour. After removal from the furnace, the melt is cooled, pulverized and added to 500ml 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 HN03

• After calcium removal 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(15)/E')*(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 i5mg/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 = JN2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 142

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*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 wet) =

1~* (X+Y) + (Xl+Yl)*Fl~ 1/2 * (Wl*W2)

L w1 2

w1 2 ~ (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kg wet) =

r!* 66* (X+Y) + (Xl+Yl) *Fl~ 1/2

[ w1 2 w1 2

J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/kg wet) = 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.)

NG Nl - N7*(1 + Rl*Il) 143

N7 =

E(l5)/E' =

(N2 - Fl*Nl)/Wl (This represents counts due to Sr-90)

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.S)*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* (S8 2 +s9 2 ) 112

• W3 (Nl - N7*(l+Rl*Il))

sa [cx+Y)

= + (Xl+Yl) *Flj l/ 2 w1 2 w12 I S9 = (Xl+Yl) 1 12 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg wet)

4. 66* ( 582 +59 2 ) l/Z 144

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 betacounted 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:

s~-90 Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(l5)/E')*(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(lS)/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 145

Wl =

Il =

I2 =

1

((1 + Rl*I2) - (l + Rl*Il)*Fl)

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

I (Xl+Yl)*Fl~11 2 r 2* (X+Y) +

w1 2 w1 2 J Again, keeping the same variable definitions,

• (Wl*W2)

(N2-Fl*Nl) the LLD for Sr-90 (pCi/kg dry) =

'4. 66* (X+Y) + (Xl+Yl) *Fl_~J 1/2

[ w1 2 w1 2 J calculation of sr-89 Activity:

Sr-89 Results (pCi/kg dry) = N6/R

--~(2~.~2~2~)~*~(=E~)*..,....,..,,(E~(~l~5~)~/E=-=-')~*~(~S=7~)~*~(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 proportion counter where G, Hand I are regression coefficients.)

146

• N6 N7 E(lS)/E'

=

=

Nl - N7*(1 + Rl*Il)

(N2 - Fl*Nl)/Wl (This represents counts due to sr-90)

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.S)*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.

so.s = Half-life of Sr-89, days All other quantities are as previously defined.

The 2-sigma error.for sr-89 (pCi/kg dry) = 2* csa2+s9 2 )1/2

• W3 (Nl .- N7*(l+Rl*Il))

SB =r(X+Y) + (Xl+Yl)*Fl2 1/2 1* w1 2 w1 2

• S9 = (Xl+Yl) 112 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg dry) 4.66*(SB2+s9 2 ) 112 147

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 SOgm aliquot is added to approximately 1/3 - liter concentrated hydrochloric acid (HCl),

containing Sml of strontium carrier (lOmg sr++/ml). A blank containing only 1/3 - liter concentrated HCl and Sml 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 HN03

• Two fuming (90%) HN03 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')*(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(lS)/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) 148

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*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 ng the same variable definitions as above, he 2-sigma error for Sr-90 (pCi/kg dry) =

r;. (X+Y) + (Xl+Yl)*Fl~ 112 * (Wl*W2)

[ Wl 2 Wl 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)*Fl2 11 2 r- w12 w1 2 Calculation of Sr-89 Activity:

sr-89 Results (pCi/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) 149

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.S)*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* (S8 2 +s9 2) 1/2

• W3 (Nl - N7*(l+Rl*Il))

SS = [(X+Y) + (Xl+Yl) *Fl2 1 1

2 w1 2 w1 2 S9 = (Xl+Yl) 11 2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg dry) =

4. 66* <s82 +s9 2 >112 150

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 absorbance are determined by Atomic Absorption Spectroscopy (AAS) and are plotted graphically. The true sample concentrations are then extrapolated from this graph. Chemical and ionization interferences are controlled by the addition of 0.1% or more of lanthanum to all samples.

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 series 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

~thanum to achieve a minimum of 0.1% lanthanum in all solutions.

~; 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)

2.98mg 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 0.025 151

Net weight of srco3 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 srco3 precipitate (mg): 28. 9 Percent of Sr in precipitate: 5_9.35 Quantity of strontium recovered= (28.9mg) x (.5935) = 17.2mg Corrected chemical recovery of strontium = 17.2mg = .738 23.3mg 152 /

_ _J

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-sigma error and LLD:

Result (pCi/m3) = N*D =R (2.22)*(E)*(A)*(T)*(V)

N = Net counts under photopeak D = Decay correction factor Atl *EXP (A t2 )

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, mins.

v = Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3 ) = l.96*(GC+BC) 1' 2 *R N

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

The LLD (pCi/m3 ) = 4. 66* (BC) 1' 2 *D (2.22)*(E)*(A)*(T)*(V) 153

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANAL.YSIS OF RAW MILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker. The sample is brought to ambient temperature and then counted on a gamma detector.

Calculat-ion 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

.i\tl*EXP(lt2) 1-EXP (-(?.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 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) 1/ 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) 154

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

\. tl *EXP (~t2) 1-EXP(-'),.tl) 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, rnins.

V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1. 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)1/2*D (2.22)*(E)*(A)*(T)*(V) 155

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF SOLIDS Several methods are employed in preparing solids for gamma analysis, dependin 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 constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm3 ), 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 = Acqciisition 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) 1/ 2 *D (2.22)*(E)*(A)*(T)*(V) 156

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOdJMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% CaS04 :Dy phosphor. They are first annealed in a 250°C oven prior to exposure in 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 background.

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)

REDOSE =Re-irradiation dose, mR AVC =Average of control values, mR 4N where AVC = ~CDOSE/4N i=l N =Total number of control dosimeters CDOSE = CR*(CREDOSE/CRR)

CDOSE =Control area dose, mR CR =Initial reading of control area CRR =Second reading of the control area (after re-irr~diation)

CREDOSE=Re-irradiation dose of the control dosimeter, mR 157

APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 159

• APPENDIX E

SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the 1993 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 . ................ ~ . . . . . . . . . . . . . . . 162 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 E-3 Tri ti um in Water . ............................... . 164 Iodine in Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 165 Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products ........*........... 166 161

TABLE E-1

• USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON 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 01-93 EPA-WAT-AB359 1 Water Alpha 15+/-3 34+/-9 Beta 39+/-0.5 44+/-5 04-93 EPA-WAT-P361 Water Alpha 110+/-5 95+/-24 Beta 168+/-2.4 177+/-27 07-93 EPA-WAT-AB365 Water Alpha 16+/-0.5 15+/-5 Beta 40+/-2.6 43+/-6.9 08-93 EPA-APT-GABS366 APT Alpha 22+/-0 19+/-5 Beta 48+/-0.5 47+/-5 10-93 EPA-WAT-P369 Water Alpha 55+/-1. 2 40+/-10 Beta 57+/-1.2 58+/-10 10-93 EPA-WAT-AB372 Water Alpha Beta 18+/-2.4 20+/-1. 2 20+/-5 15+/-5 (1) The PSE&G results for the January 93 gross alpha in water were not within the EPA limit values of 34 +/- 17.3 (two sigma). An examination of the analyses and counting parameters showed no apparent discrepencies in how the results were developed. A review of the performance of other participants in the cross check program indicated that 65% of the responding laboratories developed results outside the EPA control limits with a grand average value of 17.1 pCi/L. In conversations with the EPA it was determined that the Agency recently switched over to using Th-230 as the gross alpha reference standard. Previously the EPA and PSE&G used Am-241. The difference in detector response to Am-241 and Th-230 is approximately a factor of two for our instruments. If Th-230 was used as the gross reference standard the calculated response would have been doubled. A Th-230 sta.ndard was obtained from EPA in order to develope a new self-absorption curve and to recalibrate the detectors. Subsequent results have been in agreement.

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

• • known value plus or minus one sigma as reported by EPA 162

TABLE E-2 ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L) and Air Particulate (pCi/filter)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 06-93 EPA-WAT-G363 Water Ba-133 94+/-2 .1 99+/-10 Co-60 15+/-0.5 15+/-5 Zn-65 103+/-2.9 103+/-10 Ru-106 100+/-3.7 119+/-12 Cs-134 7+/-1.6 5+/-5 Cs-137 7+/-0.9 5+/-5 04-93 EPA-WAT-P361 Water Cs-134 27+/-1. 2 27+/-5 Cs-137 31+/-1.2 32+/-5 Co-60 41+/-1.6 39+/-5 08-93 EPA-APT-GABS366 APT Cs-137 11+/-0.5 9+/-5

.9-93 EPA-MLK-GS367 Milk Cs-137 K(l)

I-131 48+/-1. 2 1640+/-16 117+/-1.4 49+/-5 1680+/-84 120+/-12 10-93 EPA-WAT-P369 Water Co-60 11+/-0.5 10+/-5 Cs-134 10+/-0 12+/-5 Cs-137 11+/-0 10+/-5 11-93 EPA-WAT-G371 Water Co-60 31+/-0.9 30+/-5 Zn-65 155+/-2.6 150+/-15 Ru-106 200+/-9.5 201+/-20 Cs-134 57+/-0.9 59+/-5 Cs-137 42+/-0.5 40+/-5 Ba-133 76 +/-1. 7 79+/-8 (1) Reported as mg/l of Potassium

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

• • known value plus or minus one sigma as reported by EPA 163

TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Tritium Analysis of Water (pCi/L)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 06-93 EPA-WAT-H362 Water H-3 9260+/-258 9840+/-980 11-93 EPA-WAT-H370 Water H-3 7030+/-33 7400+/-740 s.d. - one standard deviation of three individual analytical results known value plus or minus one sigma as reported by EPA 164

TABLE E-4 SEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Iodine Analysis of Water (pCi/L)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-93 EPA-WAT-I360 1 Water I-131 125+/-3.3 100+/-10 10-93 EPA-WAT-I368 Water I-131 106+/-1. 9 117+/-12

1) The PSE&G results for the February 1993 I-131 in water did not agree with the EPA known. An evaluation indicated a difference in the counting geometry which altered the results by a factor of 25%. The sample counting geometry was realigned and subsequent results have been in agreement. Previous results were not effected by this error.

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

• • known value plus or minus one sigma as reported by EPA 165

TABLE E-5 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter) ,

Milk (pCi/L) and Water (pCi/L)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 01-93 EPA-WAT-S358 Water Sr-89 16+/-0.4 15+/-5 Sr-90 9+/-0.2 10+/-5 04-93 EPA-WAT-P361 Water Sr-89 44+/-5.1 41+/-5 Sr-90 28+/-1.4 29+/-5 07-93 EPA-WAT-S364 Water Sr-89 35+/-2.5 34+/-5 Sr-90 25+/-0.8 25+/-5 08-93 EPA-APT-GABS366 APT Sr-90 18+/-0.9 19+/-5 09-93 EPA-MLK-GS367 Milk Sr-89 27+/-0.9 30+/-5 Sr-90 24+/-0.5 25+/-5 10-93 EPA-WAT-P369 Water Sr-89 13+/-0 15+/-5 Sr-90 10+/-0.5 10+/-5 s.d. - one standard deviation of three individual analytical results known value plus or minus one sigma as reported by EPA 166

l91 snsN~~ ~sn CI.mi'~ ao SISdONXS a XICIN:B:ddY

• APPENDIXF SYNOPSIS OF 1993 LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50m2 (500ft 2 )

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

Tabulated below are the results of these surveys:

Milk Nearest Vegetable Animal Residence Garden Meteorological Aug., 1993 Aug., 1993 Aug., 1993 Sector km (miles) km (miles) km (miles)

N None None None NNE None 6.9 ( 4. 3) None NE None 6.4 (4. 0) None ENE None 5.8 ( 3. 6) None E None 5.4 ( 3. 4) None ESE None None None SE None None None SSE None None None s None None None SSW None 5.5 (3. 4) None SW None 6.9 (4. 3) None WSW None 7.1 (4. 4) None w 7.8 (4. 9) 6.5 (4. 0) None WNW None 5.5 (3. 4) None NW None 5.9 (3. 7) None NNW None 6.8 (4. 2) None 169