ML18094A401

1988 Annual Radiological Environ Operating Rept

ML18094A401
Person / Time
Site:	Salem, Hope Creek, 05000000
Issue date:	12/31/1988
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N89073, NUDOCS 8905080150
Download: ML18094A401 (183)

Text

{{#Wiki_filter:* ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUCLEAR GENERATING STATIONS 1988 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1988

TABLE OF CONTENTS

SUMMARY

0 INTRODUCTION ******************.............................. Radiation Characteristics. Radiation Effects ********** Radiation Exposure ** Sources of Nuclear Power 0 Reactors ******* Containment of Radioactivity......... Radioactive Liquid and Sources of Radioactivity Removal from Liquid Gaseous Effluents ** and Gaseous Wastes ** THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..*****. Objectives ********** Data Interpretation **** Quality Assurance Program ** Program Results Changes *** ~ *****.. and Discussion ** Atmospheric *************........... Direct Radiation. Terrestrial **... 0 **

• c * * * * * *
• Aquatic *****

Program Deviations ** e

• e G G e e e e e o e Conclusions.................................

. REFERENCES.................................................. APPENDIX A PROGRAM

SUMMARY

. * * * * * * * *

• e * * * * * * * * * * * * * * * * * * * *
• APPENDIX B SAMPLE DESIGNATION AND LOCATIONS...............

APPENDIX C DATA TABLES ***********************. ~*........... APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES ************ APPENDIX E -

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS * *********************************** APPENDIX F - SYNOPSIS OF LAND USE CENSUS.................... i PAGE 1 3 3 4 4 7 13 16 16 18 19 20 21 21 22 22 26 27 35 42 43 58 61 73 81 135 175 185

TABLE NUMBER

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2.

FIGURE NUMBER

1.

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3.

4.

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LIST OF TABLES TABLE DESCRIPTION Common Sources of Radiation ***.*.***.****.**.*.**** 1988 Artificial Island Radiological Environmental Monitoring Program (Program Overview) *.*****.**..*. LIST OF FIGURES FIGURE DESCRIPTION BWR Vessel and Core e ****** o *************** Cil ******** Schematic of BWR Power Plant.**************..**..** Schematic of PWR Power Pl.ant ***************.***..*. Primary PWR Containment Cross-Section

• csalem Units 1 & 2) *****.***.*..******.**.***.****.

BWR Mark 1 Primary Containment Cross-Section (Hope Creek) **.***** e ************* ". o **************

6.

Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, PAGE 6 44 PAGE 9 10 12 14 15 1973 through 1988............ Cl ******** o *********** " 48 6A. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 through 1988 Gae a a a a a a a ea a a a a a a O a Ca a a a a a a a a a a a a ii 49

LIST OF FIGURES (cont'd.) FIGURE NUMBER FIGURE DESCRIPTION PAGE

7.

Average Ambient Radiation Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through 19 8 8...... e ******************* e ****** 0 5 0 7A. Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 through 19 8 8.......... a ******** 0 ************** e 51

8.

Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1988 *.*. o... G *********** o................. 52 BA. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 through 1988... 53

9.

Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vic'inity of Artificial Island, 1973 through 1988..**..******

• 54 9A.

Average Concentrations* of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1988............ 55

10.

Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1988................... o***oeceo********.*o* 56 lOA. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1983 through 1988....,.... o*****o****o******************* 57 iii

lsUMMARYI During normal operations of a nuclear power generating station there are releases of small amounts of radioactive material to the environment. To monitor and determine the effects of these releases a radiological environmental monitoring 'program (REMP) has been established for the environment around Artificial Island where the Salem Units 1 and 2 (SGS) and Hope Creek (HCGS) Generating Stations are located. The results of the REMP are published annually, providing a summary and interpretation of the data collected. Additional data relating to the releases of radioactive materials to the environment can be obtained in the Radiological Effluent Release Report (RERR) which is published and submitted to the Nuclear Regulatory Commission on a semi-annual frequency. The PSE&G Research and Testing Laboratory (RTL) has been responsible for the collection and analysis of environmental samples during the period of January 1, 1988, through December 31, 1988, and the results are discussed in this report. The radioactive liquid and gaseous effluents due to the operation of SGS and HCGS during 1988 did not adversely affect the environment around Artificial Island. Most of the radioactive materials noted in this report are normally present in the environment, either naturally, such as potassium-40, or as a result of non-nuclear generating station* activity such as nuclear bomb testing. Measurements made in the vicinity of Artificial Island were compared to background or control measurements and the preoperational REMP study performed before Salem Unit 1 became operational. Samples of air particu-lates, air iod~ne, precipitation,. milk,.surface, ground and drinking water, vegetables, beef, game, fodder crops, fish, crabs, and sediment were collected and analyzed. External radi~tion dose measurements were also made in the vicinity of Artificial Island using thermoluminescent dosimeters. To demons~rate 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 -0f these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with Technical Specifications (Section 3/4.11) and applicable Federal and State regulations, and to verify the adequacy of radioactive effluent control systems. T~e results provided in this report are summarized below: There were a total of 2360 analyses on 1392 environmental samples during 1.988. Direct radiation dose measurements were also made using 451 thermolurninescent dosimeters (TLDs). 1

In addition to the detection of natural-occurring isotopes (i. e. Be-7, K-40, Ra-226 and Th-232), low levels of Mn-54, Co-58, Co-60, Zn-65, Sr-89, Sr-90, Sb-125, Te-129m and Cs-137 were also detected in various media. The detection of these radionuclides can be attributed to atmospheric weapons fallout, statistically positive results (within the lower limit of detection (LLD) range of the isotope but with a large margin of error) or coincident sampling at the time a effluent release was in progress. All of these radionuclides were at concentra-tions well below Technical Specification reporting levels. Dose measurements made with TLDs at 41 locations around Artificial Island averaged 61 millirads for 1988. This was comparable to the preoperational phase of the program which had an average of 55 millirads for 1973 to 1976. 2

I INTRODUCTION I This section gives a brief description of the characteristics, effects, and sources of radiation and the operation of a nuclear generating station, both a boiling water reactor and a pressurized water reactor. It is hoped that this will provide the reader with a better understanding of this report. RADIATION CHARACTERISTICS The word "radioactive" describes the state of the nucleus of an atom containing an excess of energy. The excessive energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom. To release this excess energy the atom emits electromagnetic or particulate radiation to become stable (non-radioactive). This process is called radioactive decay. Part of the electromagnetic spectrum consists of gamma-rays and x-rays, which are similar in nature to light and microwaves. 'Particulate radiation may be in the form of electrically charged particles such as alpha (2 protons plus 2* neutrons) and beta (1 electron) particles, o~ have no charge at all (neutron). Radioactive decay is measured in terms of "half-life". The half-life may be defined as the amount of time it takes for a radio-active material to decay to half of its original activity. The half-life of a radionuclide depends on the radionuclide and can range anywhere from a fraction of a second to as long as several million years. Each radionuclide also has a unique decay characteristic, both in terms of the energy of its radiation and the types.of its radiation. Radionuclides may decay directly into a stable element or go through a series of decays (becoming several different radioisotopes) before eventually becoming a stable element. Radioactivity is measured by the number of nuclear disintegra-tions (decays) of the source of radiation per unit of time. The unit of this measurement is called the curie. One curie equates to 2.2 trillion disintegrations per minute. For. the purpose of quantifying the 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 million 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 electro-magnetic and particulate radiation is produced by ionizing an atom, breaking a chemical bond, or altering the chemistry of a living cell. To assess biological damage, the type, energy, and amount of radiation must be considered. There are essentially two types of exposure to radiation: external and internal. External exposure can involve the total body, thereby implying exposure to all organs, or parts of the body, such as the arm, foot, or head. Internal exposure, meaning the uptake of radioactive elements by inhalation, ingestion, or by means of a cut, can involve a single selective organ or several organs. An example of the selectivity of internal exposure is the uptake of a radioiodine which concentrates in the thyroid gland, versus the uptake of a radiocesium which will collect in the muscle and liver. The quantity of the radionuclide and duration of time a radionuclide remains in the body directly influences the total exposure or dose to an organ. The duration of time depends on the amount of radioactive decay and the length of time it takes to remove the radionuclide from the body (biological decay). It should be noted that the biological effect of radiation is independent of the source (internal or external) and dependent on the dose. The measurement of dose to man is typically expressed in terms of a unit called the rem. As a better un~t of dose, the millirem (mrem; 1 mrem =1/1000 rem) is most of ten 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 every-thing that has emerged from it) since its formation, including our own bodies. Every second over 7000 atoms undergo radioactive decay in the body of the average adult (or roughly 420,000 disintegrations per min~te) from natural background. 4

Many sources of radiation exist today and, of them, the most universal and least controllable is background radiation from terrestrial radioactivity and cosmic rays. Terrestrial radio-activity originates from such radionuclides as potassium-40 (K-40), uranium-238 (U-238), thorium-232 (Th-232), radium-226 (Ra-226), and radon-222 (Rn-222). Some of these radionuclides have half-lives of millions of years and are introduced into the water, soil, and air by such means as volcanoes, weathering, erosion, diffusion, and radioactive decay. One naturally-occurring terrestrial radionuclide is a significant source of radiation exposure to the general public---radon gas. Radon gas (Rn-222) is an inert gas produced in the ground from. the radioactive decay of radium (from the decay of uranium and thorium) and emitted into the air. Because of the use of lime and gypsum (which would contain radium) in its production, building materials such as cinder block, sheet rock, and concrete are also radon gas sources. Concentrations of radon gas are dependent on the concentrations of radium (uranium and thorium) in the soil, altitude, soil permeability, temperature, pressure, soil moisture, rainfall, snow cover, atmospheric conditions, and season. The gas can move through cracks and openings into base-ments of buildings, become trapped in a small air volume indoors and result in higher concentrations than found outdoors. Radon can also be dissolved in well water and contribute to airborne radon in houses when released through showers or washing. Since radon gas is radioactive, it, too, continues to produce, by decay, other radioactive mate~ials referred to as radon daughters. These daughters are solid particles which can stick to surfaces such as dust particles in the air. The dust containing the radon daughter particles can be inhaled and deposited in the lungs. Radon daughters emit high energy alpha particles which results in an average dose to the lungs of 300 mrem (0.3 rem to a 10 year old) in the United States. In areas such as New Jersey and Pennsylvania, over a geological formation known as the Reading Prong, doses much higher than 300 rem/yr have been recorded due to natural deposits of uranium. Doses due to radon gas and its daughters are the highest dose contributor to individuals from all natural sources. Cosmic rays are high energy electromagnetic rays which originate from outer space. About 300 cosmic rays pass through each person every second. Cosmic rays also interact with atoms in the earth's atmosphere and produce radioactive substances such as carbon-14 (C-14), sodi.um-22 (Na-22), beryllium-10 (Be-10), and tritium (H-3). Some of these radionuclides become deposited on land and water while the rest remain suspended in the atmosphere. Other naturally-occurring sources of radiation which contribute to doses to the human body are trace amounts of uranium and radium in drinking water and radioactive potassium in milk. Sources of naturally-occurring radiation and their average dose contribution are summarized in Table 1. 5

Natural Sources Cosmic Rays Building Materials Internal Ground APPROXIMATE TOTAL TABLE 1 COMMON SOURCES OF RADIATION* Approximate Dose (mrem/yearl 42 35 28 11 100 Manmade Sources Medical radiation Television and consumer products Weapons Fallout Nuclear Power Plants

Reference:

NUREG-0558 and EPA Report ORP/SID 72-1 Approximate Dose Cmrem/year) 90 1-5 2-5 1 100 The average individual in the United States receives approxi-mately 100 mrem per year from natural sources. In some areas the dose from natural radiation is significantly higher. Residents of Colorado receive an additional 80 mrem per year due to the increase in cosmic (higher elevation) and terrestrial radiation lev~ls. 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

• deposits give natural background radiation levels of several thousand.mrem per year.

The average individual is also exposed to radiation from a number of man-made sources. The single largest of these sources comes from medical diagnostic tools such as X-rays, CAT-scans, fluoro-scopic examinations and radio-pharmaceuticals. Approximately 160 million people in the United States are exposed to medical or dental X-rays in any given year. The annual dose to an individual from such medical irradiation averages 90 mrem which is approximately equal to the annual sum of natural radiation. Smaller doses from man-made sources come from consumer products (television, smoke detectors, fertilizer), fallout from prior nuclear weapons tests, and production of nuclear power and its associated fuel cycle. There are approximately 200 radionuclides produced in the nuclear weapons detonation process; a number of these are detected in fallout. Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of nuclear weapons. Fallout can be washed down to the earth's surf ace by rain or snow and is dispersed throughout the environ-ment. The radionuclides found in fallout which produce most of the fallout radiation exposures to man are I-131, Sr-89, Sr-90, and Cs-137. There have been no atmospheric weapons tests in this country since 1964. 6

NUCLEAR POWER REACTORS ~After World War II and during the development of atomic weapons, an understanding of the great energy potential from atomic chain reactions was realized and put to peaceful use. Among the most successfully developed peaceful uses were nuclear power reactors. It was known that the fission reactions in an atomic weapon detonation generated large amounts of energy and heat~ If that energy and heat could be harnessed, electricity could be produced. As a comparison, one pound of uranium-235 (the fuel of a nuclear reactor) could produce the heat of 1,500 tons of coal. So, at the University of Chicago, under the direction of Enrico Fermi, the world's first nuclear reactor began operation (went critical) on December 2, 1942. It wasn't until 1957 that the nuclear reactor was first used to commercially produce electricity in Shippingport, Pennsylvania. Today there are over 100 reactors for public power generation of electricity in this country and 300 in the world. The function of a nuclear reactor is to generate heat to produce electricity. The generation of heat is accomplished by permitting.self-sustaining, controlled nuclear fissions. Nuclear fission is the splitting of an atom when hit by a neutron, which, in turn, produces two entirely different atoms, as well as generating a lot of heat. When one fission occurs more neutrons are given off which leads to more atoms to fission, producing more neutrons etc., thus giving rise to a chain reaction. The atom bomb, using large masses of fissionable material, is a chain reaction uncontrolled. Nuclear reactors, on the other hand, use small masses of fissionable materia.l (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. Uranil,lin-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 the 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, step by step, 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 rods contain uranium fuei pellets. The fuel pellets have been enriched so that the U-235-to-U-238 ratio is now one atom of U-235 to every 20 to 40 atoms of U-238. The core is contained in a 6" thick steam reactor vessel about 75 feet high and weighing 624 tons.

2.

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

3.

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

4.

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

5.

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

6.

A second separate water system, carrying cooling water from an outside source (e.g. the cool~ng tower located on Artificial Island), condenses the steam back to water.

7.

The condensed water is then pumped back into the reactor vessel to start the entire cycle again. The fission chain reaction is controlled by the 185 control rods located between the fuel assemblies. These* control rods contain material which absorbs neutrons and controls the rate of fissioning. By moving. the control rods up or down, the reactor can.sustain a chain reaction at desired power levels. By inserting them all the way into the reactor core, fissioning can be completely stopped. 8

\\0 FIGURE 1 FEEDWATER (FROM CONDENSER) REC IR CU LA Tl 0 N PUMP BWR VESSEL & CORE STEAM STEAM~ STEAM SEPARATORS REACTOR CORE WATER FEEDWATER ~~ (FROM CONDENSER) RECIRCULATION PUMP

0 FIGURE 2 SCHEMATIC OF BWR POWER.PLANT DRYWELL (PRIMARY CONTAINMENT) 1 ~ SHIELD BUILDING STEAM ---l> REA CT OR ~-,..,----,-,,.----------/ VESSEL PRESSURE SUPPRESS/ON POOL (TORUS) TURBINE 1-WATER RECIRC PUMP GENERATOR COOLING TOWER ~ ~<:=== ~*=====OI ~ COOLING WATER (RIVER)

A PWR differs from a BWR in that water inside the reactor vessel system is pressurized to prevent boiling (steam) when heated. This pressurized hot water is used to heat a second source of water, at a lower pressure, which will produce steam to turn the turbines. The following step-by-step outline indicates how the PWR works (see Figure 3):

1.

2.

3.

5.

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. 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. 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. 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. The exhausted steam from the* turbine is channeled into the condensor below the turbine, cooled back into water and returned to the steam generators. The cooling action *of .* the condensor is provided by a third (tertiary coolant) system of circulating water drawn from a river, ocean, or lake (at SGS, this i~ the Delaware River). About 65 percent of the nuclear power plants in the' United States are PWRs and 35 percent are BWRs. The PWR is also used in nuclear submarines and other navel vessels. 11

FIGURE 3 STEEL (SHELL) LINER REACTOR REACTOR PRIMARY COOLANT SYSTEM REACTOR COOLANT PUMP STEAM GENER-ATOR SCHEMATIC OF PWR POWER PLANT OUTER CONCRETE (CONTAINMENT SHIELD) PRIMARY SYSTEM SECONDARY SYSTEM TURBINE GENERATOR CONDENSER WATER (CONDENSATE) COOLING WATER (RIVER)

• CONTAINMENT OF RADIOACTIVITY The radioactivity present in a nuclear reactor is not just derived from U-235 fuel and the fission products generated from the chain reaction.

Other radioactive substances are generated by means of activation. Activation products are corrosion materials, from component and structural surfaces in the coolant water, that become radioactive. The materials become radioactive or activated when hit by neutrons from the fission reaction. There are a series of several barriers to contain the radio-activity present in a light water reactor. The first of these is the nuclear fuel itself. The fission products are trapped inside the ceramic fuel pellets that are designed to retain them. The fission products that are gaseous or volatile migrate out of the fuel. Encasing the fuel pellets are metal fuel rods (known as fuel cladding) designed to reta~n the fuel pellets. The small fraction of fission products that might leave the fuel pellets (such as the gaseous products) are collected here in small gaps between the fuel pellets and cladding. The next barrier level is the cooling water which is circulated around the fuel rods. The fission and activation products (such as radio~odines, strontiums, and cesiums) are soluble and are retained in the coolant. These materials can be removed by filter and purification systems used for the coolant. The next level is the reactor vessel. The reactor vessel is a steel structure (6 to 8 inches thick) which contains the fuel rods and coolant. The vessel and its coolant systems provide containment for all radionuclides in the coolant. From here the PWR and BWR differ in structure. The next barrier around a PWR reactor vessel is the containment building which is a four-foot thick, steel-reinforced (Salem Units 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 with-stand tornadoes, floods, and earthquakes. In a BWR, the reactor vessel is contained in a drywell and pressure suppression chamber (see Figure 5). This system is designed to reduce the pressure and water build-up that may occur during a break in the steam piping. The walls of the drywell (which are two feet thick) consist of concrete with a steel containment shield over the reactor vessel top. The reactor vessel and drywell system is surrounded by a steel reinforced reactor building structure (see Figure 2). 13

FIGURE 4 PRIMARY PWR CONTAINMENT CROSS-SECTION (SALEM UNITS 1 & 2) 191' 6" GROUND LEVEL FAN COIL UNIT STEAM GENERATOR ACCUMULATOR POLAR GANTRY CRANE 156'6" 14 STEAM GENERATOR ACCUMULATOR FAN COIL UNIT CONCRETE 4'-6' GROUND LEVEL

DRY WELL FIGURE 5 BWR MARK I PRIMARY CONTAINMENT CROSS-SECTION (HOPE CREEK) REC I RC PUMP PRESSURE SUPPRESSION POOL 15

SOURCES OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS Under normal operating conditions for nuclear power plants most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products are able to diffuse or migrate through the fuel cladding and into the primary coolant. Trace quantities of the component and structure surfaces, which have been activated, also get into the primary coolant water. Many of the soluble fission and activation products, such as radioactive iodines, strontiums, cobalts, and cesiums are removed by demineralizers in the purification system of the primary coolant. The noble gas* f issipn products have a very low solubiliti in the primary coolant and therefore cannot be removed by the demineralizers. Instead, they are released as a gas when the primary coolant is depressurized and are collected by a system designed for gas collection and decay. This represents the principal source of gaseous effluents. Small releases of radioactive liquids from valves, p1p1ng, or equipment associated with the primary coolant system may occur in the reactor, auxiliary, and fuel handling buildings. The nob~e gases become part of the gaseous wastes, while the remain-ing radioactive liquids are collected in floor and equipment drains and sumps and are processed prior to release. Processed primary coolant water that does meet chemical specifications for reuse may also become waste water. These represent the principal sou~ces *of liquid effluents. RADIOACTIVITY REMOVAL FROM LIQUID AND GASEOUS WASTES In a nuclear power plant, radioactive liquid and gaseous wastes are collected, stored, and processed through processing systems to remove or reduce most of the radioactivity (exclusive of tritium) prior to reuse within the plant or discharge to the environment. These primary systems are required by Technical Specifications to be installed and operable and help to ensure that all releases of radioactive liquid and gaseous effluents are as-low-a$-reasonably-achievable (ALARA). At both SGS and HCGS, liquid waste is routed through demineral-izers and filters which clean the water for recycling. If the demineralized water does not meet the requirements for reuse, the water is stored in tanks for sampling and then analyzed for radioactivity and chemical content before being discharged to the Delaware River. If the water does not meet the requirements for release to the environment, then the liquid wastes are processed through the appropriate portions of the liquid waste treatment 16

system to provide assurance that the releases of radioactive liquid effluents will be kept ALARA. All concentrates produced from the demineralizers are packaged as solid waste for shipment and burial at an offsite burial facility. At Salem, the circulating water system provides an additional minimum of 185,000 gallons per minute dilution flow for liquid releases. At Hope Creek, the cooling tower provides an additional 19,000 gallons per minute dilution flow prior to discharge to the Delaware River. The average flow rate of the Delaware River is five million gallons per minute and provides additional dilution. In SGS, the waste gases collected by the vent header system are first routed to the gas compressors which compress the gases into waste gas decay tanks. After a waste gas decay tank is filled,. the tank contents may be stored for a period up to 90 days (generally) to allow for decay of the shorter-lived radio-nuclides. In HCGS, the waste gases from the main condenser air ejectors are collected and delayed from release in the offgas system. The discharge of all waste gases at HCGS and SGS is made through high efficiency particulate air (HEPA) filters and charcoal filters prior to release. The filters are rated to be 95% efficient for iodines and greater than 99% efficient for removal of particulates. Noble gases, however, cannot be removed by these filters. Gaseous effluents are discharged through elevated vents which enhances atmospheric dispersion.and dilution. Radioactive effluent releases are limited and controlled by release concentrations and dose limits, per Technical Specifica-tions and the U.S. Nuclear Regulatory Commission's regulation in Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20). These regulations are based on recommendations of the Inter-national Commission on Radiological Protection (ICRP), the National Council on Radiation Protection and Measurements (NCRP) and the Federal Radiation Council (FRC) for basic radiation protection standards and guidance. The operations of the Hope Creek and Salem Generating Stations (Units 1 and 2), and their associated effluent releases, were well within the 10 CFR 20 limits and maintained ALARA

• 17

ITHE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' Artificial Island is the site of Salem and Hope Creek Generating Stations. The Salem Generating Station (SGS) consists of two operating pressurized water nuclear power reactors. Salem Unit One has a net rating of 1090 MWe (3338 MWt), and Salem Unit Two is rated at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which has a net rating of 1067 MWe (3293 MWt). Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic fill from dredging operations. It is located in Lower Alloways Creek Township, Salem County, New Jersey. The environment surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marsh-lands, and low-lying 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 monitoring programs were initiated. The operational REMP was initiated in December, 1976, when Salem Unit 1 achieved. criticality. The PSE&G Research an~ Testing Laboratory (RTL), has been. involved in the REMP since its inception. The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL. From January, 1973, through June, 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results. RMC reports for the the preoperational phase from 1973 to 1976 and for the operational phase from 1976 through 1982 are referenced in this report [l-3]. On July 1, 1983, the RTL assumed primary responsibility for'the analysis of all samples (except TLDs) and the reporting of results. Teledyne Isotopes (TI), Westwood, NJ, at that time was made responsible for third-party QA analyses and TLDs. RTL reports for the operational phase from 1983 to 1987 are referenced in this report [4]. 18

An overview.of the 1988 Program is provided in Table 2. Radio-analytical data from samples collected under this program were compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to determine the effects, if any, of station . operations. This report summarizes the results from January 1 through December 31, 1988, for the Artificial Island Radiological Environmental Monitoring Program. OBJECTIVES The objectives of the Operational Radiological Environmental Monitoring Program are: To fulfill the obligations of the Radiological Surveil-lance sections of the Technical Specifications for the Salem Generating Station {SGS) and the Hope Creek Generating Station {HCGS). To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways. To determine if SGS or HCGS has caused an increase in the radioactive inventory of long-lived radionuclides. To detect any change in ambient gamma radiation levels. To verify that SGS and HCGS operations have no detrimental effects on the health and safety o! 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 1988 REMP.

~esults of the four-year preoperational program which was conducted prior to the operation of any reactors on the Artificial Island have been summarized for purposes of compari-son with subsequent operational reports [2]. In order to meet the stated objectives, an appropriate oper-ational REMP* was developed. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The selection of sample types was based on: (1), established critical pathways for the transfer of radionuclides through the environment to man, and, (2), experience gained during the preoperational phase. Sampling locations were determined from site meteorology, Delaware .estuarine hydrology, local demography, and land uses. 19

Sampling locations were divided into two classes, indicator and control. Indicator stations are those which are expected to manifest station effects, if any exist; control samples are collected at locations which are believed to be unaffected by station operations. Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations. Indicator and control station data are also evaluated relative to preoperational data. Appendix A describes and summarizes, in accordance with Section 6.9.1.10 of the Salem TS and Section 6.9.1.7 of the Hope Creek TS, the entire operational program as performed in 1988. Appendix B describes the coding system which identifies sample type and location. Table B-1 lists the sampling stations and the types of samples collected at each station. These sampling. stations are indicated on maps B-1 and B-2. DATA INTERPRETATION Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix c. All results above the lower limit of detection (LLD) are at a confidence level of +/- 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regula-tory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will* yield a net count (above system background) that will be detected with 95% probability, with only 5% probability of falsely concluding that a blank observa-tion represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count, or of the blank sample count, as appropriate. The grouped data were averaged and standard deviations ~alcu lated in accordance with Appendix B of Reference 16. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. When a group of data was composed of 50% or more LLD values, averages were not calculated. Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid. 20

QUALITY.ASSURANCE PROGRAM .The PSE&G Research and Testing Laboratory (RTL), has a quality assurance program designed to maximize confidence in the analytical procedures used. Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix D. The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Plan [17] and the Environmental Division Procedures Manual [18]. The internal quality control activity of the Laboratory includes the quality control of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is implemented through participation in the USEPA Laboratory Interco~parison Studies Program. These results are listed in Tables E-1 through E-5 in Appendix E. PROGRAM CHANGES Two milk locations (13E3 and 5F2) were deleted from the Program, effective March 9, 1988, due*to budgetary cutbacks in the Company. However, this action did not affect the Program since all requirements of the SGS and HCGS Technical Specifications are still being fulfilled. Two air particulate/iodine locations (2S2 and lODl) were deleted from the Program, effective March 28-29, 1988, due to budgetary cutbacks in the Company. However, this action did not affect the Program since all requirements of the SGS and HCGS Technical Specifications are still being fulfilled

• 21

RESULTS AND DISCUSSION The analytical results of the 1988 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1988 REMP are summarized in Appendix A. The data for.individual samples are presented in Appendix c. The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating Stations Technical Specifications. The summary tables in this report include these additional samples and analyses. ATMOSPHERIC Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on triethylenediamine (TEDA) impregnated charcoal cartridges connected in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure. Precipitation was collected in a Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area. The collector is automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition. Samples were collected monthly and transferred to new poly-ethylene containers. The collector was*rinsed with distilled water to include residual particulates in the precipitation samples. Tritium results were corrected for the tritium content of the distilled water. Air Particulates (Tables C-1, C-2, C-3) Air particulate samples were collected at eight locations during January, February and March, and from six locations for the remainder of the year. Each of the 336 weekly samples collected were analyzed for gross alpha (management audit analysis) and gross beta. Quarterly composites of the weekly samples from each station were analyzed for specific gamma emitters and a single quarterly composite sample was analyzed for Sr-89 and Sr-90 as a management aµdit analysis. Total data recovery for the eight sampling stations during 1988 was 99.1 percent

• 22
• Gross alpha activity was detected in 245 of the indicator station samples at concentrations ranging from 0.7 x 10-3 to 5.5 x 10-3 pCi/m3 and in all 52 control station samples from 1.0 x 10-3 to 4.4 x 10-3 pCi/m3
• LLD sensitivities for the remaining 38 indicator and control station samples ranged from

<O. 9 x* 10-3 to <5. O x 10-3 pCi/m3

• In addition, one indicator station sample did not meet the minimum sensitivity of 2 x 10-3 pCi/m3 due to a low sample volume caused by an air sampler malfunction.

The LLD sensitivity for this sample was <8.6 x 10-3 pCi/m3

• The maximum preoperational level detected was 7.8 x lo-3 pCi/m3.
• Gross beta activity was detected in 283 of the indicator station samples at concentrations ranging from 10 x lo-3 to 64 x 10-3 pCi/m3 and in all 52 control station samples from 11 x 10-3 to 45 x 10-3 pCi/m3
• The averaoe for both indicator and control station samples was 25 x 10-3 pCi/m3
• In addition, one indicator station sample detected a concentration of 54+/-17 x 10-3 pCi/m3
• The high uncertainty was due to a low sample volume caused by an air sampler malfunction The maximum preoperational level detected was 920 x 10-3 pCi/m3, with an average of 74 x 10-3 pCi/m3.

e Gamma spectrometric analysis performed on each of the 26 quarterly composite samples indicated the presence of Te-129m, Cs-137 and the naturally-occurring radionuclides Be-7, Ra-226 and Th-232. All other gamma emitters searched for were below LLD. 0 0 0 Tellurium-129m was detected in one indicator station composite at a concentration of 10 x 10-3 pCi/m3, with a 2 sigma detection error of 60%. This value is within the LLD sensitivities for the remaining samples, both indicator and control, which ranged from <8. 6. x 10-3 to <26 x 10-3 pCi/m3. Cesium-137 was detected in one control station composite.at a concentration of 0.6 x 10-3 pCi/m3, with a 2 sigma detection error of 33%. This value is within the LLD sensitivities for the remaining samples, both indicator and control, which ranged from <0.2 x 10-3 to <2 x 10-3 pCi/m3

• The maximum preoperational level detected was 11 x lo-3 pCi/m3
• Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in 19 of the 22 indicator station com~osites at concentrations ranging from 51 x 10-3 to 90 x 10-pCi§m3 and in the four control station composites from 57 x 10-to 90 x lo-3 pCi/m3
• The LLD sensitivities for the three indicator composites were <30 x 10-3 pCi/m3 for each.

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

• 23

o Radium-226 was detected in two composites from two indicator stations at concentrations of 0.7 x 10-3 and 0.8 x 20-3 pCi/m3

• These values are within the LLD sensitivities for the remaining samples, both indicator and control, which ranged from <0.5 x 10-3 to <7 x 20-3 pCi/m3
• The maximum preoperational level detected was 16 x 20-3 pCi/m3
• o Thorium-232 was detected in one indicator station composite at a concentration of 1.0 x 10-3 pCi/m3 and in one control composite at 1.6 x 10-3 pCi/m3
• These values are within the LLD sensitivities for the remaining samples, both indicator and control, which ranged from <0.8 x 10-3 to

<2.2 x 10-3 pCi/m3. The maximum preoperational level detected was 3.1 x 10-3 pCi/m3.

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

o Strontium-89 was not detected in any of the eight composites analyzedo LLD sensitivities for the seven indicator station samples ranged from <0.2 x io-3 to <l.O x 10-3 pCi/m3 and for the control station at <0.3 x lo-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 eight composites analyzed.

LLD sensitivities for the seven indicator station samples ranged from <0.1 x 10-3 to <0.2 x 10-3 pCi/m3 and for the control station at <0.2 x 10-3 pCi/m3

• The maximum preoperational level detected was 3.0 x 10-3 pCi/m3
• Air Iodine. (Table C-4)

Iodine in filtered air samples was collected at eight locations during January, February and March, and from six locations for the remainder of the year. Each of the 337 weekly samples was analyzed for I-131.

• Iodine-131 was not detected in any of the 337 weekly samples analyzed.

LLD sensitivities for the 284 indicator station samples ranged from <7.0 x 10-3 to <36 x 10-3 oCi/m3 and for the 52 control station samples from <6.1 x io-3 to <35 x 10-3 pCi/m3

• In addition, one indicator station sam!?le did not meet the minimum sensitivity of 70 x 10-3 pCi/m due to a low sample volume caused by an air sampler malfunction.

The LLD sensitivity for this sample was <400 x 10-3 pCi/m3 3 The maximum preoperational level detected was 42 x io-pCi/m3

• 24

Precipitation (Tables C-6, C-7) Although not required by the SGS or HCGS Technical Specif i-cations, monthly precipitation samples were collected at a location in the town of Salem as management audit samples. Each of the ten monthly samples collected were analyzed for gross alpha, gross beta, tritium and gamma emitters. No samples were available for the months of April and June. The April monthly sample was not available due to a precipitation sampler malfunction during the only period of any appreciable rain. June's sample was not available due to insufficient precipi-tation during the sampling period.

• Gross alpha activity was detected in two of the ten samples at concentrations of 2.5 and 3.7 pCi/L.

LLD sensitivities for the remaining eight samples ranged from <1.0 to <2.4 pCi/L. The maximum preoperational level detected was 4.7 pCi/L.

• Gross beta activity was detected in all ten samples at concentrations ranging from 1.2 to 36 pCi/L, with an average of 8.9 pCi/L.

The maximum preoperational level detected was 71 pCi/L, with an average of 19 pCi/L.

• Tritium a*ctivity was detected in two of the ten samples at concentrations of 150 and 180 pCi/L.

LLD sensitivities for the remaining eight samples ranged from <140 to <160 pCi/L. The *maximum preoperational level detected was 610 pCi/L, with an average of 216 pCi/L.

• Gamma spectrometric analysis performed on monthly samples indicated the presence of occurring radionuclides Be-7 and Ra-226.

emitters searched for were below LLD. each of the*ten the naturally-All other gamma o Berylliurn-7, attributed to cosmic ray activity in the atmosphere, was detected in all ten samples at concen-trations ranging from*47 to 250 pCi/L, with an average of 88 pCi/L. The maximum preoperational level detected was 79 pCi/L, with an average of 29 pCi/L. The increase in the naturally-occurring Be-7 activity over preoperational levels is mo~t likely due to spallation reactions in the upper atmosphere and is not attributable to the operations of SGS or HCGS. o Radium-226 was detected in three of the samples at concen-trations ranging from 6.7 to 22 pCi/L. These values are within the variations of the LLD sensitivities measured throughout the year for the remaining eight samples which ranged from <5.1 to <29 pCi/L. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS. 25

DIRECT RADIATION Ambient radiation levels in the environs were measured with energy-compensated Caso (Dy) thermolurninescent dosimeters (TLDs) supplied and read by Teledyne Isotopes. Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances. Direct Radiation (Tables C-8, C-9) A total of 41 locations were monitored for direct radiation during 1988, 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 6.1 millirads per standard month, and the corresponding average control dose rate was 6.6 millirads per standard month. The preoperational average monthly TLD readings was 4.6 millirads per standard month. o The averag~ dose rate for the 29 quarterly off-site indicator TLDs was* 4.9 millirads per standard month, and the average control rate was 5.5. The preoperational average quarterly TLD readings was 4.4 millirads per standard month. In Figure 7, the average radiation levels are plotted for the 16 year period through 1988. Figure 7A shows the monthly averages of the off-site indicator stations and the control stations for 1982 through 1988. Ambient radiation levels during 1988 were comparable to those obtained during 1987. 26

TERRESTRIAL Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Samples were collected in new polyethylene containers and transported in ice chests with no preservatives added. Well water samples were collected monthly by PSE&G personnel and separate raw and treated potable water samples were composited daily by personnel of the City of Salem water treatment plant. All samples were collected in new polyethylene containers. Locally grown vegetable and fodder crops are collected once a year at time of harvest. Such samples are weighed in the field at time of pickup and then packed in plastic bags. Grass or green chop is collected from grazing areas, where possible. Beef is collected semi-annually, when possible, from farm animals*at time of slaughter. The meat is weighed, then packed in plastic bags and kept chilled in ice chests during transport. Game (muskrat) is collected annually (time of year dependent on weather conditions, which affect pelt thickness) from local farms after being trapped, stripped of their pelts and gutted. The carcasses are packed in plastic bags and kept chilled. in ice chests during transport. Milk (Tables C-10, C-11, C-12) Milk samples were collected at six local dairy farms during January, February and March, and from four farms for the remainder of the year. Samples were collected semi-monthly when cows were on pasture and monthly when cows were not on pasture. Animals are considered on pasture !rom 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 86 samples analyzed.

LLD sensitivities for the 66 indicator station samples ranged from <0.3 to <0.7 pCi/L and for the 20 control station samples from <0.3 to <0.6 pCi/L. The maximum preoperational level detected was 65 pCi/L which occurred following a period of atmospheric nuclear weapons tests.

• Gamma spectrometric analysis performed on each of the 86 samples indicated the presence of Cs-137 and the naturally-occurring radionuclides K-40, Ra-226 and Th-232.

All other gamma emitters searched for were below.LLD. 27

o Cesium-137 was detected in four samples from three indicator stations at concentrations ranging from 2.9 to 4.4 pCi/L, with a 2 sigma detection error ranging from 43% to 60%. These values are within the variations of the LLD sensitiv-ities for the remaining 82 samples which ranged from <2.3 to <4.6 pCi/L. The maximum preoperational level of Cs-137 detected was 14 pCi/L. The possible presence of Cs-137 in the samples can be attributed to fallout from nuclear weapons testing. o Potassium-40 was detected in all 86 samples. Concentra-. tions for the 66 indicator station samples ranged from 1200 to 1500 pCi/L. The 20 control station sample concentra-tions ranged from 1200 to 1400 pCi/L. The average for both the indicator and control station samples was 1300 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L. o Radium-226 was detected in seven samples from three indicator stations at concentrations ranging from 5.2 to 12 pCi/L. LLD sensitivities for the remaining 79 samples ranged from <5.1 to <8.6 pCi/L. The maximum preoperational level detected was <30 pCi/L. o Thorium-232 was detected in two samples from two indicator stations at concentrations of 7.5 and 15 pCi/L and one control station sample at 19 pCi/L. These values are near or below the LLD sensitivities for the remaining 83 samples which ranged from <7.7 to <18 pCi/kg-wet. No preoper-ational data is available for comparison. However; the presence of Th-232 is not attributable to the operations of SGS or HCGS.

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

o Strontium-89 was not detected in any of the four samples analyzed. LLD sensitivities for the three indicator station samples ranged from <1.1 to <1.3 pCi/L and for the control stat.ion at <l. 3 pCi/L. The maximum preoperational level detected was 14 pCi/L. o Strontium-90 was detected in all four samples analyzed. Concentrations for the three indicator station samples ranged from 1.1 to 1.6 pCi/L and for the con~rol station sample at 2.3 pCi/L. The average concentration for all samples was 1.6 pCi/L. The maximum preoperational level detected was 12 pCi/L, with an average of 3.5 pCi/L. The presence of Sr-90 in the samples can be attributed to fallout from nuclear weapons testing. 28

Well Water (Tables C-14, C-15, C-16) .*. Although wells in the vicinity of the Salem and Hope Creek Generating Station are not anticipated to be affected by plant operations, water samples were collected monthly from two indicator wells and one control well. One January indicator station sample was not available because the premises were unoccupied during the entire month. Each sample was analyzed for gross alpha, gross beta, potassium-40, tritium and gamma emitters. Quarterly composites were analyzed for Sr-89 and Sr-90.

• Gross alpha activity was detected in four of the two indicator station samples at concentrations ranging from 1.9 to 2.4 pCi/L and in three of the control station samples from 0.9 to 1.5 pCi/L.

These values are within the variations of the LLD sensitivities for the remaining 28 samples which ranged from <0.6 to <3.5 pCi/L. The maximum preoperational level detected was 9.6 pCi/L.

• Gross beta activity was detected in all 35 samples.

Concentrations for the 23 indicator station samples ranged from 3.7 to 18 pCi/L and for the 12 control station samples from 9.5 to 12 pCi/L. The average concentration detected for all samples was 11 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 35 samples. Concentrations.for the 23 indicator station samples ranged from 2.4 to 17 pCi/L and for the 12 control station samples from 7.5 to 12 pCi/L. The average concentration detected for all samples was 9.4 pCi/L. The maximum preoperational level detected was 19 pCi/L, with an average of 7.8 pCi/L.

• Tritium activity was detected in one indicator station sample at. a concentration of 160 pCi/L.

This value is within the variations of the LLD sensitivities for the remaining 34 samples which ranged from <140 to <160 pCi/L. The maximum preoper~tional level det*ected was 380 pCi/L. e Gamma spectrometric analysis performed on each of the 23 indicator station *and 12 control station water samples indicated the presence of the naturally-occurring radio-nuclides K-40, Ra-226 and Th-232. All other gamma emitters searched for were below LLD. 0 Potassium-40 was detected in four of the two indicator station samples at concentrations ranging from 30 to 38 pCi/L. These values are within the variations of the LLD sensitivities measured throughout the year for the remaining samples which ranged from <24 to <45 pCi/L.. The maximum preoperational level detected was 30 pCi/L. 29

o Radium-:-226 was detected in eighteen of the two indicator station samples at concentrations ranging from 4.0 to 160 pCi/L and in eleven control station samples from 27 to 100 pCi/L. LLD sensitivities for the remaining indicator and control station samples ranged from <3.9 to. <5.7 pCi/L. The maximum preoperational level detected was 2.0 pCi/L. These values are similar to those found last year. However, as with the 1987 results, they are higher values than found in previous years. We believe that results are higher due to a procedural change in which the samples are no longer boiled down to a 100 ml standard geometry. This change results in less removal of radon (and its daughters) from the sample. Since Ra-226 is an alpha emitter, its identi-fication by gamma isotopic analysis is obtained by counting the gamma rays from Pb-214, one of its daughter products; We believe that values currently being observed are typical for this geographical area. o Thorium-232 was detected in three of the two indicator station samples at concentrations ranging from 5.4 to 8.2 pCi/L and in two control station samples at 5.5 and 8.0 pCi/L. LLD sensitivities for the remaining indicator and control station samples ranged from <3.8 to <11 pCi/L. No preoperational data is available for comparison.

However, the presence of Th-232 is not attributable to the operations of SGS or HCGS.

• Strontium-89 and strontium-90 analy.ses were performed on quarterly composites of the monthly well water samples o

Strontium-89 was not detected in any of the eight indicator station or four control station composites. LLD sensitiv-ities for indicator samples range~ from <0.4 to <1.6 pCi/L and for the control samples from <0.3 to <1.2 pCi/L. The maximum preoperational level detected was <2.1 pCi/L. o Strontium-90 was not detected in any of the eight indicator station or four control station composites. LLD sensitiv-ities for indicator samples ranged from <0.2 to <0.9 pCi/L and for the control samples from <0.3 to <0.7 pCi/L. The maximum preoperational level detected was 0.87 pCi/L. Potable Water (Tables C-17, C-18, C-19) Both raw and treated potable water samples were collected from the Salem water treatment plant. Each consisted of daily aliquots composited into a monthly sample. The raw water source for this plant is Laurel Lake and adjacent wells. Each of the 24 individual samples was analyzed for gross alpha, gross beta, K-40, tritium and gamma emitters. Quarterly composites of monthly raw and treated water samples were analyzed for Sr-89 and Sr-90. 30

• Gross alpha activity was detected in four raw water samples at concentrations ranging from 1.2 to 2.2 pCi/L and in three treated water samples from 0.9 to 1.4 pCi/L.

These values are within the variations of the LLD sensitivities for the remaining 17 samples which ranged from <0.9 to <2.7 pCi/L. The maximum preoperational level detected was 2.7 pCi/L.

• Gross beta activity was detected in all 24 samples at concentrations ranging from 2.2 to 4.8 pCi/L for the raw water and from 1.9 to 3.8 pCi/L for treated water.

The average concentration for both raw and treated was 3.3 pCi/L. The maximum preoperational level detected was 9.0 pCi/L, with an average of 4.2 pCi/L.

• Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples at concentrations ranging from 0.9 to 2.7 pCi/L for the raw water and from 0.8 to 2.6 pCi/L for treated water.

The average concentration for both raw and treated was 1.9 pCi/L. The maximum preoperational level detected was 10 pCi/L, with an average of 1.7 pCi/L.

• Tritil,llll activity was detected in one raw water sample at a concentration of 180 pCi/L and in three treated water samples from 150 to 190 pCi/L.

LLD sensitivities for the remaining ~O samples ranged from <140 to <160 pCi/L. The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

• Gamma spectrometric analysis performed on each of the 24 monthly raw and treated potable water samples indicated the presence of Mn-54 and the naturally-occurring radionuclides Ra-226 and Th-232.

All other gamma emitters searched for were below LLD. o Manganese-54 was detected in one of the twelve treated water* samples at a concentration of 1.4 pCi/L, with a 2 sigma detection error of 50%. This value is within the variations of the LLD sensitivities measured throughout the year for the remaining eleven samples which ranged from <1.2 to <2.1 pCi/L. LLD sensitivities for the 12 raw water samples ranged from <1.3 to <4.2 pCi/L. The Technical Specifications reporting level for Mn-54 is 1000 pCi/L. o Radium-226 was detected in one of the.treated water samples at a concentration of 5.9 pCi/L. LLD sensitivities measured throughout the year for the remaining eleven samples ranged from <3.4 to <5.7 pCi/L. LLD sensitivities for the 12 raw water samples ranged from <3.8 to <8.2 pCi/L. The maximum preoperational level detected was 1.4 pCi/L

• 31

o Thorium-232 was detected in* two of the raw wa*ter samples at concentrations of 10 and 14 pCi/L and two treated water samples at*8.5 pCi/L for both. LLD sensitivities for the remaining twenty samples ranged from <4.3 to <8.6 pCi/L. No preoperational data is available for comparison.* However, the presence of Th-232 is not attributable to the operations of SGS or HCGS

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

o Strontium-89 was not detected in any of the four raw water composites or four treated water composites. LLD sensitivities for the raw water sample composites ranged from <0.5 to <1.2 pCi/L and for the treated water sample composites from <0.5 to <1.0 pCi/L. The maximum preoper-ational level detected was 1.1 pCi/L. o Strontium-90 was detected in one raw water sample composite at a concentration of 0.4 pCi/L and in one treated water sample composite at 0.9 pCi/L. LLD sensitivities for the remaining raw water sample composites ranged from <0.4 to <0.9 pCi/L and for the treated water sample composites from <0.4 to <0.6 pCi/L. The maximum preoperational level detected was 2.1 pCi/L. Vegetables (Table C-20) Although vegetables in the region are not irrigated with water into which liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled at seven indicator stations (12 samples) and three control stations (8 samples) *. The vegetables collected as management audit samples and analyzed for gamma emitters inc~uded asparagus, cabbage, sweet corn, peppers and tomatoes.

• Gamma spectrometric analysis performed on each of the twenty samples. indicated the presence of Cs-137 and the naturally-occurrjng radionuclides K-40, Ra-226 and Th-232 *. All other gamma emitters searched for were below LLDo o

Cesium-137 was detected in two samples from two indicator stations at concentrations of 1.3 and 20 pCi/kg-wet, with a 2 sigma detection error of 47% and 53% respectively. These values are within the variations of the LLD sensitivities for the remaining eighteen samples which ranged from <1.3 to <30 pCi/kg-wet. The maximum preoperational level detected was 59 pCi/kg-wet. The possible presence of Cs-137 in the samples can be attributed to fallout from nuclear weapons testing. 32

o Potassium-40 was detected in all twenty samples. Concen-trations for the twelve indicator station samples ranged from 1200 to 2800 pCi/kg-wet and for the eight control station samples from 1300 to 2400 pCi/kg-wet. The average concentration detected for all samples was 1900 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2141 pCi/kg-wet. o Radium-226 was detected in four samples from four indicator stations at concentrations ranging from 37 to 67 pCi/kg-wet and one control station sample at 60 pCi/kg-wet. LLD sensi tiv.i ties for the remaining fifteen samples ranged from <1.9 to <46 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS. o Thorium-232 was detected in one indicator station sample at a concentration of 140 pCi/kg-wet. LLD sensitivities for the remaining samples ranged from <4.4 to <72 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS. Beef (Table C-21) Although not required by the SGS or HCGS Technical Specif i-at.ions, beef samples are collected, when available, from two farms twice a year as management audit samples and analyzed for gamma emitters. Only one beef sample from the first semi-annual sampling period was collected. Samples from the second semi-annual sampling period were not available. Farmers, from whose animals the samples are normally obtained, did not slaughter from July through December 1988.

• Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclide K-40.

All other gamma emitters searched for were below LLD. o Potassium-40 was detected in the single indicator station sample at a concentration of 2400 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet. Game (Table C-21) Although not required by the SGS or HCGS Technical Specif i-cations, samples of muskrats inhabiting the marshlands surrounding the site are collected. This game is consumed by local residents. The samples, when available, are collected from two locations once a year as management audit samples and . analyzed for gamma emitters. Samples from two locations were collected during the month of February to satisfy this requirement. 33

• Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclide K-40 in both samples.

All other gamma emitters searched for were below LLD. o Potassium-40 was detected in the indicator station sample at *a concentration of 3000 pCi/kg-wet and the control station sample at 2400 pCi/kg-wet. The average for both muskrat samples was 2700 pCi/kg-wet. The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4444 pCi/kg-wet. Fodder Crops (Table C-22) Although not required by the SGS or HCGS Technical Specif i-cations, eight samples of crops normally used as cattle feed were collected from four 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 corn 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 Ra-226.

All other gamma emitters searched for were below LLD. o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in three samples from three indicator stations at concentrations ranging from 290 to 1100 pCi/kg-wet and in one control station sample at 1100 pCi/kg-wet. LLD_sensitivities for the remaining four samples ranged from <170 to <320 pCi/kg-wet. The maximum preoperational level detected was 4700 pCi/kg-wet, with an average of 2000 pCi/kg-wet. o Potassium-40 was detected in all eight samples. Concentra-tions for the six indicator station samples ranged from 3600 to 16000 pCi/kg-wet and for the two control station samples at 4900 and 15000 pCi/kg-wet. The average concen-tration detected for all samples was 9400 pCi/kg-wet. These levels are comparable to preoperational results, which also detected a maximum level of 16000 pCi/kg-wet

• 34

0

• Radium-226 was detected in two samples from one indicator station at concentrations of 39 and 54 pCi/kg-wet and in one control station sample at 30 pCi/kg-wet.

These values are within the variations of the LLD sensitivities for the remaining five samples which ranged from <42 to <94 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Ra-226 is not attributable to the operations of SGS or HCGS. AQUATIC All aquatic samples were collected by Environmental Consulting Services, Inc. (formerly v. J. Schuler Associates, Inc.) and delivered by PSE&G personnel. *Surface water samples were collected in new polyethylene containers which were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net and frozen in sealed polyethylene containers before being transported in ice chests. Sediment samples were taken with a bottom grab sampler and frozen in sealed polyethylene containers before being transported in ice chests. Surface Water (Tables C-23, C-24, c.-25, C-26) Surf ace water samples were collected monthly at four indicator stations and one control station in the Delaware estuary. One location is at the outfall area (which is the area where liquid effluents from the Salem Station ar.e discharged into the Delaware River), another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow.is from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink

• River, serves as the operational control.

All surface water samples were analyzed monthly for gross alpha, gross beta and gamma emitters *. Quarterly composites were analyzed for tritium.

• Gross alpha activity was detected in three samples from two indicator stations at concentrations ranging from 1.6 to 1.8 pCi/L and in one control station sample at l.6_pCi/L.

These values are within the variations of the LLD sensitivities for the remaining 56 samples which ranged from <1.2 to <2.8 pCi/L. The maximum preoperational level detected was 27 pCi/L. 35

• Gross beta activity was detected in all 60 samples.

Concentrations for the 48 indicator station samples ranged from 7.3 to 130 pCi/L and for the 12 control station samples from 25 to 80 pCi/L. The average concentration detected for all samples was 55 pCi/L. The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L.

• Tritium activity was detected in four samples from three indicator station composites at concentrations ranging from 150 to 1700 pCi/L, with an average for the four composites of 830 pCi/L.

Concentrations were detected in two of the control station composites at 180 pCi/L for both. LLD sensitivities for the remaining composites ranged from <140 to <160 pCi/L. The maximum preoperational level detected was 600 pCi/L. A review of Station Radioactive Effluent Release Reports indicates that all liquid discharges were below Technical Specification limits. Although surface water samples are not potable, the 1300 and 1700 pCi/L tritium values detected in one of the indicator station samples, were well below the reporting level of 20,000 pCi/L for drinking water samples [11,12] *. The high tritium concentrations can be attributed to sampling during a liquid effluent release.

• Gamma spectrometric analysis performed on each of the 48 indicator station and 12 control station surf ace water samples indicated the presence of Co-58, Co-60, and the naturally-occurring radionuclides K-40, Ra-226 and Th-232.

All other gamma emitters search~d for were below LLD. o Cobalt-58 was detected in one indicator station sample at a concentration of 7.6 pCi/L. LLD sensitivities for all remaining samples measured throughout the year ranged from <l. 2 to <3."O pCi/L ~ -The presence of Co-58 in the sample can be attributed to sampling during a liquid effluent release. o Cobalt-60 was detected in* one control station sample at a concentration of 3.0 pCi/L, with a 2 sigma detection error of 43%. This* value is within the variations of the LLD sensitivities for all remaining samples measured throughout the year which ranged from <1.1 to <;3.1 pCi/L. o Potassium-40 was detected in 40 samples from the four indicator station samples at concentrations ranging from 25 to 120 pCi/L and in eight of the control station samples ranging from 42 to 75 pCi/L. LLD sensitivities measured throughout the year for the remaining samples ranged from <24 to <44 pCi/L. The maximum preoperational level detected was 200 pCi/L, with an average of 48 pCi/L

• 36

o Radium-:-226 was detected in six samples. from the t'our indicator stations at concentrations ranging from 3.8 to 7.8 pCi/L and in two control station samples at 4.4 and 5.9 pCi/L. LLD sensitivities for the remaining indicator and control station samples ranged from <3.0 to.<5.5 pCi/L. The maximum preoperational level detected was 4.0 pCi/L. o Thorium-232 was detected in eight samples from the four indicator stations at concentrations ranging from 6.0 to 10 pCi/L and in four control station samples from 6.0 to 8.2 pCi/L. These values are within the variations of the LLD sensitivities for all remaining samples measured throughout the year which ranged from <4.7 to <11 pCi/L. No preoper-ational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS. Fish (Tables C-27, C-28) Edible species of fish were collected semi-annually at three locations and analyzed for tritium (aqueous), gamma emitters (flesh), and for Sr-89 and Sr-90 (bones). Samples included bluefish, channel catfish, weakfish and white perch.

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator station and one control station samples as management audit analysis.

No tritium activity was detected in any of the six samples analyzed; LLD sensitivities ranged from <50 to <1000 -pCi/kg-wet. The maximum required LLD sensitivity value is 2000 pCi/kg-wet.

• Gamma spectrometric analysis performed on each of the four indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclides K-40 and Th-232.

All other gamma emitters searched for were below LLD. o Potassium-40 was detected i.n all four samples from the two indicator stations at concentrations ranging from 2700 to 3400 pCi/kg-wet and in both of the control station samples at 2700 and 3200 pCi/kg-wet. The average for both the indicator and control station samples was 3000 pCi/kg-wet. The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2914 pCi/kg-wet. 0 Thorium-232 was detected in one indicator station sample at a concentration of 35 pCi/kg-wet. This value is within the variations of the LLD sensitivities for the remaining five samples, both indicator and control, which ranged from <41 to <58 pCi/kg-wet. No preoperational data is available for comparison. However, the presence of Th-232 is not attributable to the operations of SGS or HCGS. 37

• Strontium-89 and strontium-90 analyses were performed on each of the four indicator station and two control station samples.

These are management audit analyses analyzed in recognition of the high bioaccumulation factor of strontium in bone. o Strontium-89 of the bone was detected in each of the three first semi-annual samples. The detected concentrations for the two indicator station samples were 100 and 110 pCi/kg-dry, with a 2 sigma detection error of 39% and 31% respectively. The detected concentration for the control station sample was 150 pCi/kg-dry, with a 2 sigma detection error of 27%. LLD sensitivities for the three second semi-annual samples, indicator and control, ranged from <40 to <90 pCi/kg-dry. The maximum preoperational level detected was 100 pCi/kg-dry. o Strontium-90 of the bone was detected in all four indicator station samples and in both control station samples. Concentrations in the four indicator samples ranged from 35 to 330 pCi/kg-dry, with an average of 160 pCi/kg-dry. Concentrations in the two control samples were 27 and 330 pCi/kg-dry, with an average of 180 pCi/kg-dry. The average for all samples was 170 pCi/kg-dry. The maximum preoper-ational level detected was 940 pCi/kg-dry, with an average of 335 pCi/kg-dry. The presence of Sr-90 in the samples can be attributed to fallout from nuclear weapons testi~g * . Blue Crab (Table C-29) Blue crab samples were collected semi-annually at two locations, one indicator and one control, and the edible portions were analyzed for gamma emitters, Sr-89 and Sr-90, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89 and Sr-90.

• Tritium analysis was performed on the aqueous fraction. of the flesh portions of each of the *two indicator samples and two control samples as management audit analysis.

Tritium activity was detected in one of the control samples at 140 pCi/kg-wet. LLD sensitivities for the remaining three samples, indicator and control, ranged from <50 to <1000 pCi/kg-wet. The maximum required LLD ;sensitivity value is 2000 pCi/kg-wet.

• Gamma spectrometric analysis on the flesh of each of the two indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclides K-40 and Ra-226.

All other gamma emitters searched for were below LLD. 38

o Potassium-40 was detected in both indicator station samples at concentrations of 2100 to 2600 pCi/kg-wet and in both of the control station samples at 2400 and 2500 pCi/kg-wet. The average for both the indicator and control station samples was 2400 pCi/kg-wet. The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 pCi/kg-wet. o Radium-226 was detected in one indicator station sample at a concentration of 35 pCi/kg-wet and one control station sample at 30 pCi/kg-wet. LLD sensitivities for the remaining indicator sample was <30 pCi/kg-wet and for the control station, <23 pCi/kg-wet. The maximum preopera-tional level detected was 33 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 reconcen-tration factor of strontium in crab shells. o Strontium-89 of the flesh was not detected in any of the four samples; LLD sensitivities ranged from <29 to <42 pCi/kg-wet. The maximum preoperational level detected was <51 pCi/kg-wet. Strontium-89 of the shell was detected in one indicator station sample at 41 pCi/kg-dry and in both control samples at 45 and 92 pCi/kg-dry. The LLD sensitivity for the remaining indicator sample was <220 pCi/kg-dry. The maximum required LLD sensitivity value is 500 pCi/kg-dry. The maximum preoperational level detected was 210 pCi/kg-dry. o Strontium-90 of the flesh was not detected in any of the four samples; LLD sensitivities ranged from <17 to <23 pCi/kg-wet. The maximum preoperational level detected was <150 pCi/kg-wet. Strontium-90 of the shell was detected in both indicator stat.ion samples at 220 and 2800 pCi/kg-dry and in both control station samples at 190 and 360 pCi/kg-dry. The average for both indicator and control station samples was 890 pCi/kg-dry. The maximum preoperational level detected was 990 pCi/kg-dry, with an average of 614 pCi/kg-dry. 39

Sediment {Table C-30) Sediment samples were collected semi-annually from six locations, five indicator stations and one control station. Each of the twelve samples was analyzed for Sr-90 {management audit analysis) and gamma emitters. Although trace levels of man-made nuclides were detected in some sediment samples, these levels were well within the acceptable levels specified in section 3/14.12.1 of the Technical Specifications.

• Strontium-90 was detected in one indicator station sample at 34 pCi/kg-dry.

LLD sensitivities for the other eleven samples, indicator and control, ranged from <12 to <21 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 Be-7, K-40, Ra-226 and Th-232, low levels of Mn-54, Co-58, Co-60, Zn-65, Sb-125 and Cs-137 were also detected. All other gamma emitters searched* for were <LLD. o Zinc-65 was detected in one indicator station sample at a concentration of 320 pCi/kg-dry. LLD sensitivities for the other eleven samples, indicator and control, ranged from <30 to <73 pCi/kg-dryo Trace levels of Zn-65 were 'discharged from both SGS and HCGS during the year. o Cobalt-60 was detected in seven samples from four indicator stations at concen*trations ranging from 29 to 110 pCi/kg-dry. LLD sensitivities for the other five samples, indicator and control, ranged from <23 to <55 pCi/kg-dry. Trace levels of Co-60 were discha~ged from both SGS and HCGS during the year. o Manganese-54 was detected in three samples from three indicator stations at concentrations ranging from 18 to 42 .pCi/kg-dry, with a 2 sigma detection error ranging from 31% to.56%. These values are within the variations of the LLD sensitivities for the other nine samples, indicator and control, which ranged from <18 to <43 pCi/kg-dry. o Cobalt 58 was detected in one indicator station sample at a concentration of 32 pCi/kg-dry, with a 2 sigma detection error of 47%. This value is within the variations of the LLD sensitivities for the other eleven samples, indicator and control, which ranged from <17 to <39 pCi/kg-dry

• 40

/

o Antimony-125 was detected in one indicator station sample at a concentration of 90 pCi/kg-dry, with a 2 sigma detection error of 53%. This value is within the variations of the LLD sensitivities for the other eleven samples, indicator and control, which ranged from <32 to <100 pCi/kg-dry. The maximum preoperational level detected was 270 pCi/kg-dry. o Cesium-137 was detected in one of the two control station samples at a concentration of 33 pCi/kg-dry, with a 2 sigma detection error of 33%. This value is within the variations of the LLD sensitivities for the other eleven samples, indicator and control, which ranged from <17 to <37 pCi/kg-dry. The maximum preoperational level detected was 400 pCi/kg-dry. o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in one indicator station sample at a concentration of 280 pCi/kg-dry. This value is within the variations of the LLD sensitivities for the other eleven samples, indicator and control, which ranged from <120 to <320 pCi/kg-dry. The maximum preoperational level detected was 2300 pCi/kg-dry. o Potassium-40 was detected in all indicator station samples at concentrations ranging from 3900 to 15000 pCi/kg-dry, with an average of 7500 pCi/kg-dry. Concentrations dete-cted in both of the control station samples were at . 140-00 and 16000 pCi/kg-dry, with an average of 15000 pCi/kg-dry. The average for both the indicator and control station samples was 8800 pCi/kg-dry. The maximum preoperational level detected was 21000 pCi/kg-dry, with an average of 15000 pCi/kg-dry. o Radium-226 was detected in all indicator station samples at concentrations ranging from 310 to 1200 pCi/kg-dry, with.an average of 580 pCi/kg-dry. Concentrations detected in both of the control station samples were at 630 and 740 pCi/kg-dry, with an average of 680 pCi/kg-dry. The average for both the indicator and control station samples was 600 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 indicator station samples at concentrations ranging from 350 to 1000 pCi/kg-dry, with an average of 610 pCi/kg-dry. Concentrations detected in both of the control station samples were at 800 and 920 pCi/kg-dry, with an average of 860 pCi/kg-dry. The average for both the indicator and control station samples was 650 .pCi/kg-dry. The maximum preoperational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry. 41

PROGRAM DEVIATIONS Air particulate results from location 5Sl for the week beginning January 25, are unavailable due to a faulty filter holder assembly. First quarter gamma, Sr-89 and Sr-90 results are based on a composite of all weekly filters except for the week beginning January 25. Well water results from location 5Dl for the month of January

• are unavailable because the premises were unoccupied during the entire month.

First quarter Sr-89 and Sr-90 results are based on a composite of the February and March samples only. Air particulate/iodine sampler location 5Sl for the week beginning March 21, was operational for only 5.5 days out of a 7 day sampling week due to a loss of electrical service caused by construction work. In addition, the following week's sampling period was delayed by approximately one day until the electrical service was restored. Precipitation (not required by the Technical Specifications) results from location 2F2 for the month of April are unavailable due to a precipitation sampler malfunction during the only period of any appreciable rain. Precipitation (not required by the Technical Specifications) results from location 2F2 for the month of June are unavailable du~ to insufficient precipitation during the sampling period. Air particulate/iodine results from location lFl, for the week beginning August 15, are unavailable due to an air sampler malfunction which occurred shortly after servicing. Third quarter gamma results are based on a composite of all weekly filters except for the week beginning August 15. Air particulate/iodine sampler location 2F2, for the week beginning December 12, was operationa1 for only 0.8 days out.of an 8 day s*ampling period due to an air sampler malfunction. As a result of the short sampling period, weekly results were affected as follows: Gross alpha (not required by the Technical Specifications) results did not meet the sensitivity. Gross beta results had a high uncertainty. Iodine-131 results did not meet the required sensitivity. Direct radiation measurement results from location 14F2 for the fourth quarter are unavailable; TLDs were missing from the field location. The second semi-annual beef samples were not obtained.

Farmers, from whose animals the samples are normally obtained, did not slaughter from July through December, 1988.

42

CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial Island was conducted during 1988 in accordance with the SGS and HCGS Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications. From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment. These results were comparable to the results obtained during the preoperat_ional phase of the program. Ambient radiation levels were relatively low, averaging 6.3 mrad/std. month. No unusual radiological characteristics were observed in the environs of Artificial Island. The operation of SGS Units One and Two and HCGS had no significant impact on the radiological characteristics of the environs of Artificial Island. 43

I.

a.

~

b.

~

c.

II.

a.

TABLE 2 1988 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S!A'.UCH CODE MEDIUM INDICATOR ATMOSPHERIC ENVIRONMENT Air Particulate 2S2 5Dl 16El lFl 5Sl lODl 2F2 Air Iodine 282 501 16El lFl 5Sl lODl 2F2 Precipitation 2F2 DIRECT RADIATION Thermoluminescent 2S2 5Dl 2El lFl Dosimeters 5Sl lODl 3El 2F2 6S2 1401 13El 2F6 7Sl 16El 5Fl lOSl 6Fl llSl 7F2 llFl 13F4 CONTROL 3H3 3H3 3Gl 3Hl 3H3 COLLECTION FREQUENCY Weekly Weekly Monthly Monthly & Quarterly TYPE/FREQUENCY* OF ANALYSIS Gross alpha/weekly Gross beta/weekly Sr-89 & sr-90/first quarterly** Gamma scan/quarterly Iodine-131/weekly Gross alpha/monthly Gross beta/monthly Tritium/monthly Gamma scan/monthly Gamma dose/monthly Gamma dose/quarterly

TABLE 2 (cont'd) 1988 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MEDIUM

a.

Thermoluminescent 4D2 Dosimeters (cont'd) STATTON CODE INDICATOR CONTROL 9El 11E2 12El 2F5 3F2 3F3 10F2 12Fl 13F2 13F3 14F2 15F3 16F2 1G3 lOGl 16Gl III. TERRESTRIAL ENVIRONMENT

a.

Milk

b.

Well Water 13E3 2F7 5F2 11F3 14Fl 2S3 5Dl 3Gl 3El COLLECTION FREQUENCY Quarterly Monthly (animals not on pasture) Semi-monthly (animals on pasture) Monthly TYPE/FREQUENCY* OF ANALYSIS Gamma dose/quarterly Iodine-+31/monthly Gamma scan/monthly Iodine-131/semi-monthly Gamma scan/semi-monthly Sr-89 & Sr-90/July, first collection** Gross alpha/monthly Gross beta/monthly

• Potassium-40/monthly Tr*itium/rrionthly Gamma scan/monthly Sr-89 & sr-90/quarterly

TABLE 2 (cont'd) 1988 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S:I8:IIQH CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

c.

Potable Water 2F3 Monthly Gross alpha/monthly (Haw & Treated) (composited Gross beta/monthly daily) Potassium-40/monthly Tritium/monthly Gamma scan/monthly sr-89 & Sr-90/quarterly .s:o. d

• Vegetables 3El 1F3 lGl 3H5 Annually Gamma scan/on collection

°' 3E2 2F4 2Gl (at harvest) 11E3 5Fl 14F3

e.

Beef 3El Semi-Gamma scan/on collection annually

f.

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

g.

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

~ -.J . TABLE 2 (cont'd) 1988 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S'.1!~'.l!IIJli CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY IV. AQUATIC ENVIRONMENT

a.

b.

c.

d.

Surf ace Water llAl 7El 1F2 12Cl Monthly 16Fl Edible Fish llAl 7El 12Cl Semi-annually Blue Crabs llAl 12Cl Semi-annually Sediment llAl 7El 16Fl 12Cl Semi-15Al annually 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.

TYPE/FREQUENCY* OF ANALYSIS Gross alpha/monthly Gross beta/monthly Gamma scan/monthly Tritium/quarterly Tritium (flesh) Aqueous fraction/on collection Sr-89 & Sr-90 (bones)/on collection Gamma scan (flesh)/on collection Tritium (flesh) Aqueous fraction/on collection* Sr-89 & Sr-90 (flesh)/on collection Sr-89 & Sr-90 (shell)/on collection Gamma scan (flesh)/on collection sr-90/on collection Gamma scan/on collection

500 100 50 10 5 FIGURE 6 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND AIR PARTICULATES 1973 THROUGH 1988

• LEGEND AIR 1E-3 pCi/m**3 0

0 RAIN pCi/L +-----+ I 11\\.L.Cl-C"" I I I I . *I*.. J. I.............. * *......... * * *. * * * *........................... I +' I I I i -1\\ Al I I

• • • • • • • • ~: 1***1-r *rt**,*

I I I I I I I I I I I I "I II I I >I\\ I \\

....., + t I

+" I ,r t -l-I I ~ I r-.;_/ + I I \\ t ID I I I / ~ ............. ~.. 't......... /........ l..... f ~..**.*......*.*****.**. '.. *.................... \\ I \\ f"'""'

• /

I ~, I\\ .. -;:,.. *:*.......... -~.. /... I \\ I I I I i;: I I+ + " \\ \\ I + s;!' I + -k I I I \\ \\ A- ' ID ~...... I +~ /.... ~ ****r i"... *l*\\/ ~ \\* **~***\\~--~---~*"/r 1*t11*y-;-*~-;-**** I \\ ~ +..... ~.................. 1 1 S.973 t- ~ t-t- m ~ t-1 + \\ ~ '>f!' \\ I I r.\\._ I WmH mm Hm I 1 >-1 a: w w d, a: w \\ 1 \\ I ilJl-t-m 0 m 1-,... t-m N °o t-o T \\/ w~mi- ~,._...,... ~,... mr-- J, Nm mm + I I a:<m ocb ~~ or!.~.!, o

.l.:r\\i ~J, I/

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01 .c .µ c 0 E u .µ (J) (J) E QJ (._ E* FIGURE 7A COMPARISON OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1988 10-..-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-- 10 LES END OFF-SITE STATIONS 9--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-10 0 9 CONTROL STATIONS +------+ B-t-~~~~~~~~~-ffl'-~~~~~--,-+~~~~~~~~~~~~~~~~~~~~~~~+-~~+- B n II II ~ H

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30 28 26 24 22 20 18 t11 N _J 16 -rl tJ 14 a 12 10 8 6 4 2 0 FIGURE B IN MILK ISLAND AVERAGE CONCENTRATIONS OF IODINE-i3i IN THE VICINITY OF ARTIFICIAL 1974 THROUGH iSBB 30 28 26 24 22 20 I-UI w I- ~ UI I'- ZI 0

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30 28 26 24 22 20 18 U1 (A) ~ 16 ~ u 14 a 12 10 8 6 4 2 FIGURE BA AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK IN.THE VICINITY OF ARTIFICIAL ISLAND 1983 THROUGH 1988 28 26 24 22 20 I I I m m I m N I ~ 0 ~ m 0 ff w I u ~ H

• • • • • ..J u

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500 100 U1 50 ll=>o ...J. -r1 u a 10 5 FIGURE 9 AVERAGE CONCENTRATIONS OF BETA EMITTERS & K-40 IN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1973 THROUGH i9BB I + I I j!: *..*.*...*.....*....*.. j!: iii .... "f gi 'I 01"-

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01 01 _J -rt LI a. FIGURE 9A AVERAGE CONCENTRATIONS OF BETA EMITTERS & K-40 IN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1983 THROUGH 1988. 1000--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--~~~~~~~---. 500 100 50 10 5 I I I

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FIGURE 10 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE.RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1973 THROUGH 1988 5000 1000 500 100 50 /\\ I,... ........... * * * * * *. *. * * * * *. * * * * * *. * * * * * * * *

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01 -.J _J orl u a FIGURE iOA AVERAGE~CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1983 THROUGH i988 5000 1000 500 100 50 .................................................................... "... r................................................... 1= I '.::l *************************************************** CD ~ m '-' IH CD I-NH I a: "'I"' 0 ..I ill W CD m a: m o u I ~ w re ltJ a.. I

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REFERENCES [l] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Annual Reports 1973 through 1982". * [2] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Preoperation Summary - 1973 through 1976". RMC-TR-77-03, 1978. [3] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - December ll 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 1987". [5] Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units l and 2". l97l. [6] Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Hope Creek Generating Station". 1983.

• [7]

United States Atomic Energy Commission. "Final Environment;al Statement - Salem Nuclear Generating Station, Units land 2 11

• Docket No. 50-272 and 50-3ll. 1973.

[8] United States Atomic Energy Commission. "Final Environmental Statement - Hope Creek Generating.Station, Docket No. 50-354. 1983. [9] Public Service Electric and Gas Company. "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units l and 2". 1982. [lO] Public Service Electric and Gas Company. "Final Safety Analysis Report - Hope Creek Generating Station. 1984. [ll] Pub.lie Service Electric and Gas Company. "Salem Nuclear Generating Station Unit l - Technical Specifications", Appendix A to Operating License No. DPR-70, 1976, Sections 3/4.12 and 6.9.l.lO (Amendment 59 .e.t..Q.e.S1 ) * [l2] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix A to Operating License No. DPR-75, l98l, Sections 3/4.12 and 6.9.l.lO (Amendment 28 .e.t..Q.e.S1 )

• 58

[13] REFERENCES (cont'd) Public Service Electric and Gas company. "Hope Creek Generating Station Unit l - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10. [14] Public Service Electric and Gas Company. "Offsite Dose Calculation Manual" - Salem Generating Station.

• [15]

Public Service Electric and Gas company. "Offsite Dose calculation Manual" - Hope Creek Generating Station. [16] u. s. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August, 1980. [17] PSE&G Research and Testing Laboratory. "Environmental Division Quality Assurance Plan." November, 1986. [18] PSE&G Research and Testing Laboratory. "Environmental Division Procedures Manual." February, 1981. [19] Public Service Electric and Gas Company. "Radioactive Effluent Rele~se Reports, SGS RERR-24 and RERR Salem Generating Station. 1988. [20] Public Service Electric and Gas company. "Radioactive Effluent Release Reports, HCGS RERR-5 and RERR Hope creek Generating Station. 1988. [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. 59

APPENDIX A PROGRAM

SUMMARY

61

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALI IHDICAICR ICCAIICHS LCCAIICH WIIH HIGHESI MEAH CCHIRCI ICCAIICH NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Particulates Alpha 336 0.9 2.2 (245/284) 5Dl 3.5 ml E 2.4 (17/52) 2.3 (52/52) 0 (10-3 pC 1!m3) (0.7-5.5) (1.4-4.3) (1.0-4.4) Beta 336 25 (283/284) 2S2 0.4 mi NNE 28 ( 13/13) 26 ( 52/52) 0 (10-64) (16-40) ( 11-45) CT\\ Sr-89 8 0.2 <LLD <LLD <LLD 0 w Sr-90 8 0.1 <LLD <LLD <LLD 0 Gama Be-7 26 30 71 ( 19/22) 2S2 0.4 mi NNE 81 (1/1) 71 (4/4) 0 (51-90) (81) (57-90) Te-129m 22 8.6 10 ( 1/18) 2F2 8.7 mi NNE 10 (1/4) <LLD 0 ( 10) ( 10) Cs-137 26 0.2 <LLD 3H3 110 mi NE 0.6 (1/4) 0.6 (1/4) 0 (0. 6) (0.6) Ra-226 26 0.5 0.8 (2122) lFl 5.8 mi N 0.8 (1/4) <LLD 0 (0.7-0.8) (0.8) Th-232 22 0.8 1.0 ( 1/18) 3H3 110 mi NE 1.6 (1/4) 1.6 (1/4) 0 ( 1. 0) ( 1. 6) ( 1.6) Air Iodine 1-131 337 6.1 <LlD <LLD <LLD 0 (10-3 pC i /m3)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY l, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL IUDIC8IDB IDC8IIDUS IDC8IIDU WIIU UIGUESI ME8U CDUIBDI IDC8IIDU NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Precipitation Alpha 10 1.0 3.1 (2/10) 2F2 8.7 mi NNE 3.1 (2/10) No Control 0 ( pC i IL) (2.5-3.7) (2.5-3.7) Location Beta 10 1.0*** 8.9 (10/10) 2F2 8.7 mi NNE 8.9 (10/10) No Control 0 (1.2-36) ( 1. 2-36) Location H-3 10 140* 160 (2/10) 2F2 8.7 mi NNE 160 (2/10) No Control 0 C1'I (150-180) (150-180) Location Gamma Be-7 10 88 (10/10) 2F2 8.7 mi NNE 88 (10/10) No Control 0 (47-250) (47-250) Location Ra-226 10 5.1 13 (3/10) 2F2 8.7 mi NNE 13 (3/10) No Control 0 (6.7-22) (6.7-22) Location Direct Radiation Gamma 288 6.3 (252/252) llSl 0.09 mi SW 7.9(12/12)* 6.6 (36/36) 0 (mrad/std. month) Dose (monthly) (4.1-9.8) (6.1-9.8) (5.4-8.2) Gamma 163 5.0 (139/139) llSl 0.09 mi SW 6.4 (4/4) 5.5 (24/24) 0 Dose (qtrly.) * (3.5-6.6) (5.9-6.6) (4.8-6.4)

ARTIFICIAL I.SLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I IHDICAICH ICC6IICHS ICCAIICH ~IIU UIGUESI MEAH CCHIHCI ICCAIICH NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* .(RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Milk 1-131 86 0.3 <LLD <LLD <LLD 0 (pCi/L) Sr-89 4 1.1 <LLD <LLD <LLD 0 Sr-90 4 1.3 (3/3) 3Gl 17 mi NE 2.3 (1/1) 2.3 (1/1) 0 (1.1-1.6) (2.3) (2.3) CJ'\\ Gamma (11 K-40 86 1300 ( 66/66) 13E3 4.9 mi W 1400 (3/3) 1300 (20/20) 0 (1200-1500) (1300-1400) (1200-1400) 11F3 5. 3 mi SW 1400 (20/20) (1300-1500) Cs-137 86 2.3 3.5 (4/66) 14Fl 5.5 mi WNW 4.4 (1/20) <LLD 0 (2.9-4.4) (4.4) Ra-226 86 5.1 9.1 (7/66) 14Fl 5.5 mi WNW 9.9 (5/20) <LLD 0 (5.2-12) (7.7-12) Th-232 86 7.7 11 (2/66) 3Gl 17 mi NE 19 ( l / 20) 19 ( 1/20) 0 (7.5-15) (19) (19)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I I~DICAIDR ICCAIIC~S ICCAIIC~ WIIU HIGUESI MEA~ cc~rec1 ICCAIIC~ NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Well Water Alpha 35 0.6 2.0 (4/23) 5Dl 3.5 mi E 2.1 (3/11) 1.2 (3/12) 0 ( pC ill) ( 1. 9-2. 4) (1.9-2.4) ( 0. 9-1. 5) Beta 35 1.0*** 11 (23/23) 5D1 3.5 mi E 16 (11/11) 10 ( 12/12) 0 (3.7-18) (14-18) (9.5-12) K-40 35 9.4 (23/23) 5D1 3.5 mi E 14 (11/11) 9.4 (12/12) 0 CTI (2.4-17) (12-17) (7.5-12) CTI H-3 35 140 160 (1/23) 2S3 700 ft NNE 160 (1/12) <LLD 0 (160) (160) Sr-89 12 0.3 <LLD <LLD <LLD 0 Sr-90 12 0.2 <LLD <LLD <LLD 0 Gamma K-40 35 24 34 (4/23) 2S3 700 ft NNE 38 (1/12) <LLD 0 (30-38) (38) Ra-226 35 3.9 45 (18/23) 5D1 3.5 mi E 67 (11/11) 63 (11/12) 0 (4.0-160) (14-160) (27-100) Th-232 35 3.8 7.2 (3/23) 5D1 3.5 mi E 8.1 (1/11) 6.8 (2/12) 0 (5.4-8.2) ( 8.1) (5.5-8.0) Potable Water Alpha 24 o.. 9 *

1. 4 ( 7 / 24) 2F3 8.0 mi NNE

1. 4 ( 7 /24)

No Control 0 Raw-Treated (0.9-2.2) (0.9-2.2) Location (pCi/L) Beta 24 1.0*** 3.3 (24/24) 2F3 8.0 mi NNE

3. 3 ( 24/24)

No Control 0 (1.9-4.8) ( 1. 9-4. 8) Location K-40 24

1. 9 (24/24) 2F3 8.0 mi NNE 1.9 (24/24)

No Control 0 (0.8-2.7) .(0.8-2. 7") Location H-3 24 140 170 (4/24) 2F3 8.0 mi NNE 170 (4/24) No Control 0 (150-190) **- (150-190) Location

• ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENE~ATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I I~DICAICB LCCAIIC~S ICCAIIC~ WIIH HIGHESI ~EA~ CC~IBCI ICCAIIC~ NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Potable Water cont'd Sr-89 8 0.5 <LLD <LLD No Control 0 Raw-Treated Location ( pC i IL) Sr-90 8 0.4 0.6 (2/8) 2F3 8.0 mi NNE 0.6 (2/8) No Control 0 (0.4-0.9) (0.4-0.9) Location O"I Ganma -...J Mn-54 24 1.2 . 1.4 (1/24) 2F3 8.0 mi NNE 1.4 ( 1/24) No Control 0 ( 1. 4) ( 1. 4) Location Ra-226 24 3.4 5.9 (1/24) 2F3 8.0 mi NNE 5.9 (1/24) No Control 0 ( 5. 9) (5.9) Location Th-232 24 4.3 10 (4/24) 2F3 8.0 mi NNE 10 (4/24) No Control 0 (8.5-14) (8.5-14) Location Fruit & Vegetables Ganma (pCi/kg-wet) K-40 20 1900 ( 12/12) 2F4 6.3 mi NNE 2300 (1/1) 1800 (8/8) 0 (1200-2800) (2300) (1300-2400) Cs-137

20.

1. 3 11 (2/12) 3E2 5.7 mi NE 20 (1/3)

<LLD 0 (1.3-20) (20) Ra-226 20

1. 9 46 (4/12) 3E2 5.7 mi NE 67 (1/3) 60 ( 1/8) 0 (37-67)

(67) (60) Th-232 20 4.4 140 (1/12) 3E2 5.7 mi NE 140 (1/3) <LLD 0 ( 140) (140)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I IUDICAICR ICCAIICUS ICCAIICU WIIU UIGUESI MEAU CCUIRCL LCCAIICU NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Beef Ganma (pC1/kg-wet) K-40 1 2400 (1/1) 3El 4.1 mi NE 2400 (1/1) No Control 0 (2400) (2400) Location C7\\ CX> Game Ganma (pCi/kg-wet) K-40 2 3000 (1/1) 3El 4.1 mi NE 3000 (1/1) 2400 (1/1) 0 (3000) (3000) (2400) Fodder Crops Ganma (pC1/kg-wet) Be-7 8 170 740 (3/6) 14Fl 5.5 mi WNW 1100 (1/1) 1100 (112) 0. ( 290-1100) ( 1100) ( 1100) 3Gl 17 mi NE 1100 ( 1/2) ( 1100) K-40 8 9200 (6/6) 3El 4.1 mi NE 12000 (1/1) 10000 ( 2/2) 0 (3600-16000) ( 12000) (4900-15000) Ra-226 8 42 46 (2/6) 2F7 5. 7 mi NNE 46 (2/2) 30 (1/2) 0 (39-54) (39-54) ( 30)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY l, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I IUDICAIDH IDCAIIDUS IDCAIIDU ~IIU UI6UESI MEAU CDUIHDI IDCAIIDU NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS su*rface Water Alpha 60

1. 2

1. 7 (3/48) 7El 4.5 mi SE

1. 7 (2112) 1.6 (1/12) 0

( pC i IL) ( 1.6-1.8) ( 1.6-1.8) ( 1.6) Beta 60 3.8*** 56 (48/48) 7El 4.5 mi SE 88 ( 12/12) 51 (12/12) 0 (7.3-130) (45-130) (25-80) °' H-3 20 140 830 (4/16) llAl 0. 2 mi SW 1500 (2/4) 180 (214) 0 \\D (150-1700) ( 1300-1700) (180-180) Gamma K-40 60 24 66 (40/48) 7El 4.5 mi SE 92 (12/12) 64 (8/12) 0 (25-120) (46-120) (42-75) Co-58 60

1. 2 7.6 (1/48) llAl 0. 2 mi SW 7.6 (1/12)

<LLD 0 (7.6) (7.6) Co-60 60 1.1 <LLD 12Cl 2.5 mi WSW 3.0 (1/12) 3.0 (1/12) 0 ( 3. 0) (3.0} Ra-226 60 3.0 5.0 (6/48) 16F 1 6. 9 mi NNW 7.8 (1/12) 5.2 (2/12) 0 (3.8-7.8) ( 7. 8} (4.4-5.9) Th-232 60 4.7 7.3 (8/48) 7El 4.5 mi SE 8.. 9 (2/12) 6.8 (4/12) 0 (6.0-10) (7.8-10) (6.0-8.2)

-...J 0 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT) Edible Fish (pCi/kg-dry) (pCi/kg-wet) ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION HOPE CREEK GENERATING STATION DOCKET NOS. 50-272/-311 DOCKET NO. 50-354 SALEM COUNTY,.NEW JERSEY JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER TOTAL NUMBER LIMIT OF OF ANALYSES DETECTION PERFORMED (LLD)* Sr-89 6 40 (bones) Sr-90 6 (bones) H-3 6 50 (aqueous) Garrma K-40 6 Th-232 6 41 AIL INDICATOR LOCATIONS MEAN** (RANGE) 100 (Z/4) ( 100-110) 160 (4/4) (35-330) <LLD 3100 (4/4) (2700-3400) 35 (1/4) (35) IOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION (RANGE) 12Cl 2.5 mi WSW 150 (1/2) (150) 11A1 0.2 mi SW 190 ( Z/2) (58-330) <LLD 7E1 4.5 mi SE 3100 (2/2) (3100-3100) 7E1 4.5 mi SE 35 (1/2) (35) NUMBER OF CONTROL IOCATION NONROUTINE MEAN REPORTED (RANGE) MEASUREMENTS 150 (1/2) 0 ( 150) 180 (212) 0 (27-330) <LLD 0 3000 (212) 0 (2700-3200) <LLD 0

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1988 to.DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Al I I~DICAICB lCCAIIa~s lCCAIIC~ ~IIH HIGHESI MEA~ ca~real ICCAIIC~ NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Blue Crabs Sr-89 4 220 41 (112) 12Cl 2.5 mi WSW 68 ( 212) 68 (212) 0 ( pC i/kg-dr y) (shells) (41) (45-92) (45-92) Sr-90 4 1500 (212) llAl 0.2 mi SW 1500 (212) 280 (2/2) 0 (shells) (220-2800) (220-2800) (190-360) .....i (pCi/kg-wet) H-3 4 50 <LLD 12Cl 2.5 mi WSW 140 (1/2) 140 (1/2) 0 (aqueous) (140) ( 140) Sr-89 4 29 <LLD <LLD <LLD 0 (flesh) Sr-90 4 17 <LLD <LLD <LLD 0 (flesh)

• Gamma K-40 4

2400 (2/2) llAl 0.2 mi SW 2400 (212) 2400 (212) 0 (2100-2600) (2100-2600) (2400-2500) 12Cl 2.5 mi WSW 2400 (212) (2400-2500) Ra-226 4 23 35 (1/2) llAl 0.2 mi SW 35 (1/2) 30 (1/2) 0 (35) (35) (30)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY

• JANUARY 1, 1988 to DECEMBER 31, 1988 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF

!11 IUDIC!ICH ICC!IICUS ICC!IICU ~IIH HI6HESI ME!U CCUIHCI ICC!IICU NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Sediment Sr-90 12 12 34 (1/10) 16A1 0. 7 mi NNW 34 (1/2) <LLD 0 ( pC i/kg-dr y) (34) (34) Ganma Be-7 12 120 280 (1/10) 16F1 6.9 mi NNW 280 (1/2) <LLD 0 (280) (280) -..J K-40 12 7500 (10/10) 12Cl 2.5 mi WSW 15000 (2/2) 15000 (2/2) 0 (3900-15000) (14000-16000) (14000-16000) Mn-54 12 18 28 (3/10) 16Al 0.7 mi NNW 42 (1/2) <LLD 0 (18-42) (42) Co-58 12 17 32 (1/10) 15A1 0.3 mi NW 32 (1/2) <LLD 0 (32) (32) Co-60 12 23 56 (7/10) 16A1 0. 7 mi NNW 92 (2/2) <LLD 0 (29-110) (74-110) Zn-65 12 30 320 (1/10) 16A1 0.7 mi NNW 320 (1/2) <LLD 0 (320) (320) Sb-125 12 32 90 ( 1/ 10) 16A1 o.7 mi NNW 90 ( 1/ 2) <LLD 0 ( 90) ( 90) Cs-137 12 17 <LLD 12Cl 2.5 mi WSW 33 (1/2) 33 (1/2) 0 (33) (33) Ra-226 12 580 ( 10/10) 16Al 0. 7 mi NNW 1200 (2/2) 680 (212) 0 ( 310-1200) ( 1100-1200) (630-740) Th-232 12 610 (10/10) 16Al 0.7 mi NNW 920 ( 2/ 2) 860 (212) 0 (350-1000) ( 830-1000) (800-920)

• LLD listed is the lowest calculated LLD during the reporting period.
  • Mean calculated using values above LLD only.

Fraction of measurements above LLD are in parentheses. ical LLD value.

I APPENDIX 8 SAMPLE DESIGNATION AND LOCATIONS 73

I APPENDIX BI SAMPLE DESIGNATION The PSE&G Research And Testing Laboratory identifies samples by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled. AID = 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 SWA* = Surface Water FPL = Green Leafy Vegetables VGT = Fodder Crops (Various) FPV = Vegetables (Various) WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clock-wise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant: s

on-site location E = 4-5 miles off-site A

0-1 miles off-site F

5-10 miles off-site B

1-2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, *** For example, the designation SA-WWA-5Dl would indicate a sample in the SGS program (SA), consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radial distance' of 3 to 4 miles off-site, (therefore, radial distance D). The number 1 indicates that this is sampling station #1 in that particular sector. 75

SAMPLING LOCATIONS All 1988 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. STATION CODE 2S2 2S3 5Sl 6S2 7Sl lOSl llSl llAl l5Al 16Al 12Cl 4D2 5Dl lODl llDl 14Dl 2El 3El TABLE B-1 STATION LOCATION 0.4 mi. NNE of vent 700 ft. NNE of vent; fresh water holding tank 1.0 mi. E of vent; site access road 0.2 mi. ESE of vent; observation building 0.12 mi. SE of vent; station personnel gate 0.14 mi. SSW of vent; site shoreline 0.09 mi. SW of vent; site shoreline 0.2 mi. SW of vent; outfall area 0.3 mi. NW of vent; cooling tower blowdown discharge line outfall 0.7 mi. NNW of vent; south storm drain discharge line 2.5 mi. WSW of vent; west bank of Delaware River 3.7 mi. ENE of vent; Alloway Creek Neck Road 3.5 mi. E of vent; local farm 3.9 mi. SSW of vent; Taylor's Bridge Spur 3.5 mi. SW of vent 3.4 mi. WNW of vent;. Bay View, Delaware 4.4 mi. NNE of vent; local farm 4.1 mi. NE of vent; local farm SAMPLE TYPES AIO,APT,IDM

• WWA AIO,APT,IDM IDM IDM IDM IDM ECH,ESF,ESS,SWA ESS ESS ECH,ESF,ESS,SWA nJM AIO,APT,IDM,WWA AIO,APT,IDM GAM IDM IDM FPB,FPV,GAM,IDM, VGT,WWA 3E2 5.7 mi. NE of vent; local farm FPL,FPV
• 76

TABLE B-1 (cont'd) STATION CODE STATION LOCATION SAMPLE TYPES 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek ESF,ESS,SWA 9El 4.2 mi. s of vent IDM 11E2 5.0 mi. SW of vent IDM 11E3 5.1 mi. SW of vent FPL 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. w of vent; Diehl House Lab IDM 13E3 4.9 mi. w of vent; local farm MLK 16El 4.1 mi. NNW of vent; Port Perin AIO,APT,IDM lFl 5.8 mi. N of vent; Fort Elfsborg AIO,APT,IDM 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA 1F3 5.9 mi. N of vent; local farm FPL,FPV 2F2 8.7 mi. NNE of vent; Salem Substation AIO,APT*, IDM,RWA 2F3 a.a mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm FPV 2F5 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southern Training Center IDM 2F7 5.7 mi. NNE of vent; local farm MLK,VGT 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal IDM Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 5Fl 6.5 mi. E of vent FPV,IDM 5F2 7.0 mi. E of vent; local farm MLK 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 77

STATION CODE . lOF2 llFl llF3 l2Fl l3F2 l3F3 l3F4 l4Fl l4F2 l4F3 l5F3 l6Fl l6F2 lGl lG3 2\\}l 3Gl lOGl 16Gl 3Hl 3H3 3H5 TABLE B-l (cont'd) STATION LOCATION 5.8 mi. SSW of vent 6.2 mi. SW of vent; Taylor's Bridge Delaware 5.3 mi. SW of vent; Townsend, Delaware 9.4 mi. WSW of vent; Townsend Elementary School 6.5 mi. w of vent; Odessa, Delaware 9.3 mi. W of vent; Redding Middle School, Middletown, Delaware 9.8 mi. W of vent; Middletown, Delaware 5.5 mi. WNW of vent; local farm 6.6 mi. WNW of vent; Boyds Corner 5.4 mi. WNW Of vent; local farm 5.4 mi. NW of vent 6.9 mi. NNW Of vent; C&D canal 8.l mi. NNW of vent; Delaware City Public School l0.3 mi. N of vent; local farm l9 mi. N of vent; Wilmington, Delaware l2 mi. NNE Of vent; Mannington Township, NJ l7 mi. NE of vent; local farm 12 mi. SSW of vent; Smyrna, Delaware l5 mi. NNW of vent; Greater Wilmington Airport 32 mi. NE of vent; National Park, New Jersey llO mi. NE of vent; Research and Testing Laboratory 25 mi. NE of vent; local farm 78 SAMPLE TYPES IDM IDM MLK,VGT IDM IDM IDM IDM MLK,VGT IDM FPV IDM ESS,SWA IDM FPV IDM FPV IDM,MLK,VGT IDM IDM IDM AIO,APT,IDM FPL,FPV

__ L,,,,,..__ I NEW JERSEY I 13 g g g 8 "'~o.,,. ~ N teer j J I I i J i i

( 0 I db.i SCALI "MAP 8-2 OFF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND \\ \\ \\ \\ \\ \\ \\ \\ \\ \\ \\ \\ \\ Of Ml&.11 \\ \\ \\ \\ 80

---

~-

APPENDIX C DATA TABLES 81

I APPENDIX c I DATA TABLES Appendix C presents the analytical results of the 1988 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1988. TABLE NO. C-1 C-2 C-3 C-4 C-5 TABLE OF CONTENTS TABLE DESCRIPTION ATMOSPHERIC ENVIRONMENT AIR PARTICULATES ~988 Concentrations of Gross Alpha Emitters ******************** 1988 Concentrations of Gross Beta Emitters ********************* 1988 Concentrations of Strontium-89 and Strontium-90 and Gamma Emitters in Quarterly composites ******************** AIR IODINE 1988 Concentrations of Iodine-131 ****************************** DATES 1988 Sampling Dates for Air Samples **************************** PRECIPITATION PAGE 86 88 90 92 94 C-6 1988 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium................................................... 99 C-7 1988 Concentrations of Gamma Emitters ************************** 100 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-8 1988 Quarterly TLD Results ************************************* 101 C-9 1988 Monthly TLD Results *************************************** 102 83

TABLE NO. MILK DATA TABLES (cont'd.) TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT C-10 1988 Concentrations of Iodine-131..............................

• 104 C-11 1988 Concentrations of Strontium-89 and Strontium-90 *******.*.*

105 C-12 1988 Concentrations of Gamma Emitters *****************.******** 106 C-13 1988 Sampling Dates for Milk Samples ********.****************** 110 WELL WATER C-14 1988 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 112 C-15 1988 concentrations of Gamma Emitters ***************.**.******* 114 C-16 1988 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites *...*.**.*...**..**..*.**............. 116 POTABLE WATER C-17 1988 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 117 C-18 1988 Concentrations of Gamma Emitters ****************.********* 118 C-19 1988 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites ************************************** 119 FOOD PRODUCTS C-20 1988 concentrations of Gamma Emitters in Vegetables ************ 120 C-21 1988 Concentrations of Gamma Emitters in Beef and Game ********* 121 FODDER CROPS C-22 1988 Concentrations of Gamma Emitters ************************** 122 84

DATA TABLES (cont'd.) TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER C-23 1988 Concentrations of Gross Alpha Emitters ************.*.***** 123 C-24 1988 Concentrations of Gross Beta Emitters *******************.* 124 C-25 1988 Concentrations of Tritium in Quarterly composites *****.*** 125 C-26 1988 Concentrations of Gamma Emitters ************************** 126 EDIBLE FISH C-27 1988 Concentrations of Strontium-89 and Strontium-90 and Tritium*************e************************************* 128 C-28 1988 Concentrations of Gamma Emitters ************************** 129 BLUE CRABS C-29 1988 Concentrations of Strontium-89 and Strontium-90; Gamma Emitters and Tritium................................ 130 SEDIMENT* C-30 1988 concentrations of Strontium-90 and Gamma Emitters ******** ** 131 SPECIAL TABLES LI,.Ds C-31 1988 PSE&G Research and Testing Laboratory LLDs for Gamma Spectrometry........................................ 132 85

TABLE C-1 1988 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION ID MONTH SA-APT-2S2 SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE JANUARY 2.3+/-0.8 2.0+/-0.7

1. 7+/-1. 2 2.7+/-0.8 2.8+/-0.9 2.7+/-0.9 3.3+/-0.8 2.4+/-0.7 2.5+/-1.0

2. 8+/-1. 0 2.6+/-1.0

1. 9+/-1. 3

3. 2+/-1. 0 2.2+/-0.9

3. 7+/-L 1 2.4+/-0.9 2.0+/-0.6 2.6+/-1.2

2. 9+/-1. 0 2.1+/-0. 9 4.3+/-1.8 1.7+/-1.0 1.8+/-1.0 2.5+/-1.0 2.8+/-0.9 3.3+/-1.1 2.7+/-1.7 2.1+/-0.7

1. 9+/-0. 7 3.8+/-1. 7

1. 2+/-0. 5

1. 9+/-0.6

1. 7+/-0.6 1.3+/-0.6 2.0+/-0.7 2.0+/-1.6 3.6+/-0.9

( 1) 2.5+/-1.4

1. 9+/-0. 7 2.4+/-0.7 2.0+/-0.8 3.0+/-0.8 2.3+/-0.8 2.5+/-1.2 FEBRUARY 3.0+/-0.9 3.1+/-0.9 1.4+/-1.1

3. 4+/-1. 0 2.8+/-0.9 3.5+/-0.9 3.1+/-0.8 3.4+/-0.9 3.0+/-1.3 2.3+/-0.8

1. 9+/-0. 7 1.8+/-1. 2

1. 2+/-0. 7 2.1+/-0.8

1. 9+/-0.8 1.6+/-0.6 2.5+/-0.9

1. 9+/-0.8 2.3+/-0.9

1. 5+/-0. 7

2. 4+/-1. 8 2.3+/-0.8 2.6+/-0.8 2.0+/-0.8

1. 4+/-0. 7 2.4+/-0.9 2.1+/-0.9

1. 8+/-0. 7

1. 9+/-0. 7 2.3+/-1.4 2.4+/-0.8 2.0+/-0.7

1. 6+/-0. 7 1.3+/-0.6 2.7+/-0.8 2.0+/-0.9 MARCH 2.6+/-0.8 2.6+/-0.8 2.5+/-1.4 2.5+/-0.8 3.4+/-0.9 3.2+/-0.8 2.9+/-0.8 3.4+/-0.9 2.9+/-0.8 CX>

2.4+/-0.9 1.3+/-0.7. 1.9+/-1.4 1.6+/-0. 7 1.8+/-0.8

1. 4+/-0. 8 2.2+/-0.8

1. 7+/-0. 8 1.8+/-0.8 C'\\

2.0+/-0.7 1.4+/-0.6

1. 7+/-1. 2 1.8+/-0.6 2.3+/-0.7 1.6+/-0. 7 1.6+/-0.7

1. 5+/-0. 7

1. 7+/-0. 6

1. 6+/-0. 7 3.7+/-1.1

2. 9+/-1.4 3.0+/-0.8 3.2+/-0.9 2.9+/-0.9 2.6+/-0.8 2.3+/-0.8 2.8+/-1.2 APRIL (2)

1. 2+/-0.8 4.2+/-2.0 (3)

1. 6+/-0. 8 2.1+/-0. 9 2.4+/-0.9 1.7+/-0.8 2.2+/-2.1

1. 3+/-0. 7

<2.0 1.1+/-0.6

1. 5+/-0. 9 1.8+/-0.8

1. 0+/-0. 7

1. 4+/-0. 8 2.0+/-0.8 2.5+/-1.3

1. 2+/-0. 7 2.0+/-0.8 1.7+/-0.7

1. 4+/-0. 8

1. 8+/-0. 9

1. 9+/-0.6

( 1. 0

1. 7+/-0.6 2.0+/-0.7 2.1+/-0.6 1.8+/-0.6 1.8+/-0. 8 0.8+/-0.6

<2.0 2.2+/-0.7 1.4+/-0.7 1.1+/-0.6 1.5+/-0.8 1.5+/-1.0 MAY 2.0+/-0.7 ( 1. 0

1. 4+/-0. 7 1.8+/-0.8 1.3+/-0.6

1. 5+/-0. 8

1. 5+/-0. 7 1.1+/-0.8

<2.0 0.9+/-0.6 1.6+/-0. 8 1.5+/-0.8

1. 7+/-0. 8 1.5+/-0.8 0.9+/-0.6

1. 4+/-1.1 0.7+/-0.5

<0.9 1.4+/-0.6

1. 2+/-0. 7 1.1+/-0. 6 2.1+/-0.7 2.6+/-1.3 2.3+/-0.7 2.5+/-0.8 2.3+/-0.7 4.4+/-1.0 2.7+/-1.7 JUNE 2.2+/-0.9

<5.0

1. 3+/-0. 8

3. 2+/-1. 2 2.7+/-0.9 1.4+/-0.8 2.6+/-2.7 3.7+/-1.0

<5.0 5.5+/-1.0 4.1+/-1.0 2.4+/-0.8 3.2+/-1.0 4.0+/-2.3 2.4+/-0.8 <5.0 1.8+/-0.8 2.3+/-1.0 2.2+/-0.8 2.6+/-0.9 2.7+/-2.3 3.6+/-1.0 <5.0 4.8+/-1.0 3.7+/-1.1 3.0+/-0.9 2.9+/-1.0 3.8+/-1.8

CX> -...J MONTH SA-APT-2S2 JULY (2) AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE 2.4+/-1.1 TABLE ~oot'd) 1988 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCitm3 +/- 2 sigma SA-APT-551 SA-APT-5Dl STATION ID SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 1.1+/-0.6 2.7+/-0.9 2.0+/-0.8

1. 2+/-0. 7 3.0+/-1.0 2.3+/-0.9

1. 4+/-0. 7 2.8+/-0.8 2.7+/-0.8 1.8+/-0.6 1.9+/-0.8 2.1+/-0.7 1.5+/-0.6 1.6+/-0.7 1.6+/-0.6

1. 7+/-0. 7 0.8+/-0.6 1.8+/-0.8 2.5+/-0.8 1.4+/-0.7 2.4+/-0.8 2.0+/-0.8 2.0+/-0.7 3.2+/-0.8 4.2+/-0.9 2.6+/-0.9 2.1+/-1.6

<5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <4.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 <5.0 (3) 1.5+/-0.8

2. 2+/-1.4

3. 4+/-1. 0 2.3+/-1.0 1.1+/-0.6 2.0+/-0.9 2.5+/-0.9 3.0+/-0.9 2.0+/-0.8 2.9+/-0.8 1.7+/-0.7 1.6+/-0.7 2.9+/-0.9 2.5+/-0.8

1. 9+/-0. 9 4.1+/-0.9 2.1+/-0.9

<0.9 2.0+/-0.8

2. 1+/-0. 8 0-.9+/-0.6 2.2+/-0.8 1.7+/-0.7 2.4+/-0.9 3.4+/-0.9 2.7+/-0.9 3.0+/-0.9 2.2+/-1.9 1.5+/-0.8

3. 9+/-1.1 2.0+/-1.0 1.5+/-0.8 2.6+/-1.1

1. 7+/-0. 9 1.6+/-0.9

( 4) 2.5+/-0.9 2.5+/-0.7 1.8+/-0.8 3.3+/-1.0

1. 5+/-0. 7 2.0+/-0.8 1.5+/-0.6

1. 9+/-0.8

<0.9 2.0+/-0.8

1. 9+/-0.8 0.9+/-0.6

1. 7+/-0. 7

1. 6+/-0. 7 2.2+/-0.8 3.5+/-0.9 4.1+/-1.0 2.1+/-0.8 2.2+/-1.7 0.8+/-0.6

3. 2+/-1. 0 2.6+/-0.9

1. 7+/-0. 8 2.1+/-0.8

1. 8+/-0. 8

1. 8+/-0. 8 2.3+/-0.8 2.8+/-0.8

1. 9+/-0. 7

1. 4+/-0. 7 2.4+/-0.8 2.0+/-0.7 2.0+/-0.8

1. 9+/-0. 6 2.9+/-0.9 1.4+/-0. 7 2.5+/-0.9

1. 8+/-0. 7 1.0+/-0.6 2.4+/-0.8 2.2+/-0.8 2.3+/-0.8 3.4+/-0.9

<8.6 (5) 2.0+/-0.8 2.1+/-1.3 SA-APT-3H3

2. 9+/-1.1 4.2+/-1.2 3.0+/-1.0 1.0+/-0.7 2.4+/-0.9

1. 7+/-0. 8 1.8+/-0.9 2.2+/-0.8 2.8+/-0.9 2.2+/-0.7

1. 4+/-0. 8 2.9+/-0.9 2.2+/-0.8

1. 7+/-0. 8 2.0+/-0.7

1. 7+/-0.8

1. 3+/-0. 8 2.6+/-0.9 2.2+/-0.8

1. 2+/-0. 7 2.5+/-0.8 2.4+/-0.9

1. 8+/-0. 8 4.2+/-1.0 2.9+/-0.9 3.2+/-0.9 2.3+/-1.6 GRAND AVERAGE

• Sampling dates can be found in Table C-5.
  • Results for 12-28-87 to 05-31-88 samples by Teledyne Isotopes.

Results for 05-31-88 to 12-27-88 samples by Controls for Environmental. Pollution, Inc. (1) No sample collected due to a faulty filter holder assembly. (2) Station SA-APT-2S2 was deleted from the Program, effective March 28, 1988 (see Program Changes section). (3) Station SA-APT-lODl was deleted from the Program, effective March 29, 1988 (see Program Changes section). (4) No sample collected due to an air sampler malfunction. (5) High LLD due to low sample volume (sampler malfunction). Result not included in any averages. AVERAGE 2.1+/-3.2 3.7+/-1.6 2.8+/-2.3

1. 9+/-3.1 2.8+/-2.2 2.5+/-2.5 2.4+/-2.8 2.9+/-2.5 3.1+/-1.9 2.5+/-2.5 2.0+/-2.0

.3.1+/-2.0 2.4+/-2.6 2.4+/-2.6 2.7+/-3.0 2.6-2.6 2.6+/-2.4 2.6+/-2.4 1.7+/-3.2 2.7+/-2.3 2.5+/-2.5 2.6+/-2.4 3.8+/-1.4

3. 8+/-1. 9 3.0+/-2.2 2.4+/-2.2

TABLE C-2 1988 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION ID MONTH SA-APT-2S2 SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE JANUARY 33+/-2 33+/-2 29+/-3 28+/-2 35+/-3 30+/-3 35+/-2 34+/-2 32+/-5 33+/-3 31+/-3 20+/-3 34+/-3 38+/-3 32+/-3 34+/-3 28+/-2 31+/-11 40+/-3 33+/-3 35+/-3 29+/-3 34+/-3 39+/-3 37+/-3 45+/-3 36+/-10 24+/-3 22+/-3 24+/-3 23+/-2 19+/-2 21+/-2 19+/-2 21+/-3 22+/-4 34+/-3 ( 1) 32+/-3 30+/-2 30+/-2 21+/-3 30+/-2 29+/-3 29+/-8 FEBRUARY 31+/-3 26+/-3 23+/-3 27+/-3 33+/-3 30+/-3 27+/-2 32+/-3 29+/-7 34+/-3 36+/-3 31+/-3 29+/-2 27+/-2 28+/-3 32+/-2 32+/-3 31+/-6 22+/-3 26+/-3 27+/-4 22+/-3 23+/-3 27+/-3 26+/-3 29+/-3 25+/-5 Z8+/-3 25+/-2 24+/-3 22+/-2 24+/-2 25+/-3 24+/-2 25+/-3 25+/-3 MARCH 28+/-3 26+/-3 24+/-3 22+/-3 27+/-3 21+/-2 25+/-2 26+/-3 25+/-5 CX> 23+/-2 21+/-2 23+/-3 18+/-2 20+/-2 21+/-3 21+/-2 21+/-2 21+/-3 CX> 16+/-2 17+/-2 17+/-3 16+/-2 18+/-2 16+/-2 14+/-2 '17+/-2 16+/-2 22+/-3 20+/-3 23+/-3 23+/-2 23+/-3 64+/-4 23+/-2 21+/-3 27+/-30 APRIL ( 2) 22+/-3 28+/-3 ( 3) 19+/-3 23+/-3 22+/-2 22+/-3 23+/-6 14+/-2 16+/-3 12+/-2 16+/-3 14+/-2 12+/-2 14+/-4 14+/-2 16+/-3 16+/-2 16+/-2 16+/-2 14+/-2 15+/-2 22+/-2 21+/-3 19+/-2 23+/-3 18+/-2 18+/-2 20+/-4 14+/-2 18+/-3 15+/-2 16+/-2 14+/-2 19+/-3 16+/-4 MAY 17+/-2 18+/-3 19+/-2" 21+/-3 20+/-2 18+/-2 19+/-3 21+/-3 26+/-3 18+/-2 23+/-3 19+/-2 20+/-3 21+/-6 13+/-2 14+/-2 13+/-2 13+/-3 12+/-2 11+/-2 13+/-2 22+/-2 24+/-3 22+/-2 23+/-2 21+/-2 38+/-3 25+/-13 JUNE 23+/-3. 12+/-2 18+/-3 25+/-4 22+/-3 23+/-3 20+/-10 26+/-3 21+/-3 34+/-3 28+/-3 26+/-3 26+/-3 27+/-8 38+/-3 40+/-3 37+/-3 45+/-4 41+/-3 41+/-3 40+/-6 35+/-3 34+/-3 35+/-3 34+/-3 32+/-3 31+/-3 34+/-3

1988 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of io-3 pCitm3 +/- 2 sigma STATION ID MONTH SA-APT-2S2 SA-APT-5S1 SA-APT-5D1 SA-APT-10D1 SA-APT-16E1 "SA-APT-1F1 SA-APT-2F2 SA-APT-3H3 AVERAGE JULY ( 2) 16+/-2 10+/-2 ( 3) 14+/-2 17+/-2 15+/-2 24+/-3 16+/-9 37+/-3 34+/-3 40+/-3 43+/-4 37+/-3 38+/-4 38+/-6 33+/-3 21+/-2 32+/-3 38+/-3 32+/-3 39+/-3 32+/-13 17+/-2 20+/-2 19+/-2 19+/-3 19+/-2 16+/-2 18+/-3 37+/-3 32+/-2 38+/-3 44+/-4 39+/-3 43+/-3 39+/-9 AUGUST 22+/-2 15+/-2 18+/-2 25+/-3 24+/-3 27+/-3 22+/-9 23+/-2 13+/-2 24+/-2 .* 23+/-3 22+/-2 30+/-3 22+/-11 27+/-3 18+/-2 24+/-3 (4) 26+/-2 26+/-3 24+/-7 32+/-3 30+/-2 29+/-3 30+/-3 31+/-3 26+/-3 30+/-4 SEPTEMBER 21+/-2 21+/-2 20+/-2 21+/-2 22+/-2 24+/-2 22+/-3 CX> 24+/-3 -22+/-2 23+/-2 21+/-3 22+/-2 23+/-3 22+/-2 U) 23+/-3 19+/-2 21+/-3 22+/-3 22+/-2 23+/-3 22+/-3 23+/-2 18+/-2 22+/-2 23+/-3 21+/-2 25+/-3 22+/-5 OCTOBER 28+/-3 26+/-2 28+/-3 33+/-3 28+/-3 32+/-3 29+/-5 20+/-2 17+/-2 25+/-2 19+/-2 20+/-2 18+/-2 20+/-6 21+/-3 15+/-2 22+/-3 23+/-3 19+/-2 22+/-3 20+/-6 17+/-2 13+/-2 14+/-2 16+/-2 16+/-2 15+/-2 15+/-3 28+/-3 23+/-2 24+/-2 26+/-3 28+/-3 28+/-3 26+/-4 NOVEMBER 26+/-2 25+/-2 26+/-3 26+/-3 25+/-2 30+/-3 26+/-4 . 19+/-2 14+/-2 19+/-2 18+/-2 19+/-2 19+/-2 18+/-4 24+/-2 23+/-2 24+/-2 24+/-3 26+/-2 26+/-3 24+/-2 26+/-2 18+/-2 28+/-2 29+/-3 27+/-3 37+/-3 28+/-12 DECEMBER 28+/-2 26+/-2 28+/-3 30+/-3 28+/-2 28+/-3 28+/-2 35+/-3 27+/-2 35+/-3 37+/-3 34+/-3 34+/-3 34+/-7 35+/-2 34+/-2 36+/-3 36+/-3 54+/-17 (5) 32+/-3 35+/-3 36+/-3 27+/-2 36+/-3 26+/-3 33+/-3 35+/-3 32+/-9 AVERAGE 28+/-13 25+/-14 23+/-14 25+/-10 25+/-15 26+/-19 25+/-14 26+/-16 GRAND AVERAGE 25+/-15

• Sampling dates can be found in Table C-5.
  • Results for 12-28-87 to 05-31-88 samples by Teledyne Isotopes.

Results for 05-31-88 to 12-27-88 samples by Controls for Environmental Pollution, Inc. ( 1) No sample collected due to a faulty filter holder assembly. ( 2) Station SA-APT-2S2 was deleted from the Program, effective March 28, 1988 (see Program Changes sect*ion). (3) Station SA-APT-10D1 was deleted from the Program, effective March 29, 1988 (see Program Changes section). (4) No sample collected due to an air sampler malfunction. ( 5) High uncertainty due to low sample volume (sampler malfunction). Result not included in any averages.

TABLE C-3 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 AND GAMMA EMITTERS*"' IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma S!A!ICH ID SAMPLING PERIOD Sr-89 Sr-90 Be-7 Te-129m cs-137 Ra-226 Th-232 SA-AE!-2S2 12-28-87 to 03-28-88 <0.3 <0.2 81+/-5 <14 <0.5 <0.8 <1.0 {i~ SA-AE!-5Sl 12-28-87 to 03-26-88 (2) <0.3 <0.2 73+/-6 <23 <0.5 <1.0 <1.9 03-29-88 to 06-27-88 89+/-5 <13 <0.4 0.7+/-0.4 <1.1 \\.0 06-27-88 to 09-26-88 74+/-5 <13 <0.4 <0.6 <0.9 0 09-26-88 to 12-27-88 51+/-4 <12 <0.4 <0.9 <1.4 SA-AE!-5Dl (3) 12-28-87 to 03-28-88 <1.0 <0.1 74+/-7 !il <0.3 <4 m 03-28-88 to 06-27-88 <30 <2 <7 06-27-88 to 09-26-88 <30 <2 <7 09-26-88 to 12-27-88 <30 <2 <7 SA-AE!-JCDJ 12-29-87 to 03-29-88 <0.3 <0.2 55+/-3 <9.2 <0.3 <0.6 <0.9 ~i} SA-AE!-JfiEJ 12-29-87 to 03-29-88 <0.3 <0.2 71+/-5 <18 <0.4 <0.8 <1.8 03-29-88 to 06-28-88 78+/-4 <10 <0.2 <0.7 <0.8 06-28-88 to 09-27-88 80+/-5 <13 <0.5 <0.9 <1.5 09-27-88 to 12-27-88 58+/-5 <16 <0.4 <0.9 <1.8

\\D TABLE C-3 (cont'd) 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM~90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF AIR PARTICULATES STATION ID SAMPLING PERIOD SA-APT-JFJ 12-28-87 to 03-28-88 (7) 03-28-88 to 06-27-88 06-27-88 to 09-26-88 09-26-88 to 12-27-88 SA-APT-2F2 12-28~87 to 03-28-88 03-28-88 to 06-27-88 06-27-88 to 09-26-88 09-26-88 to 12-27-88 SA-APT-3H3 (Control) 12-28-87 to 03-28-88 03-28-88 to 06-27-88 06-27-88 to 09-26-88 09-26-88 to 12-27-88 AVERAGE Sr-89 <0.3 <0.2 <0.3 Results in Units of io-3 pCi/rn3 +/- 2 sigma Sr-90 Be-7 Te-129rn <0.2 70+/-6 <26 90+/-6 <20 77+/-6 <21 51+/-4 <11 <0.2 65+/-4 <8.6 88+/-5 <13 77+/-5 <12 52+/-4 10+/-6 <0.2 70+/-5 <16 90+/-5 <11 68+/-4 <12 57+/-4 <14 66+/-36

• Sr-89 results are c'orrected for decay to sample stop date.
  • All other gamna emitters searched for were <LLD; typical LLDs are given in Table C-31.

Cs-137 Ra-226 <0.5 <1.1 <0.5 <1.2 <0.4 0.8+/-0.5 <0.3 <0.8 <0.2 <0.6 <0.4 <0.9 <0.4 <0.8 <0.3 <0.7 <0.4 <0.7 0.6+/-0.2 <0.8 <0.3 <0.7 <0.3 <0.5 Th-232 <2.2 <2.1 <2.1 <1.6 <1.2 <1.6 <1.6 1.0+/-0.6 <1.6 <1.0 <1.0 1.6+/-0.8

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

(1) Station SA-APT-2S2 was deleted from the Program, effective March 28, 1988 (see Program Changes section). (2) Quarterly composite of all weekly filters except for the fifth week in January, which was unavailable due to a faulty filter holder assembly. (3) Results for first quarter samples by Teledyne Isotopes. Results for the second, third and fourth quarter samples by Controls for Environmental Pollution, Inc. (4) Not analyzed by Teledyne Isotopes. (5) Not analyzed by Controls for Environmental Pollution, Inc. (6) Station SA-APT-1001 was deleted from the Program, effective March 29, 1988 (see Program Changes section)." (7) Quarterly composite of all weekly filters except for the third week in August, which was unavailable due to an air sampler malfunction.

TABLE C-4 1988 CONCENTRATIONS OF IOOINE-131* IN FILTERED AIR Results in Units of 10-3 pCitm3 STATION ID MONTH SA-AI0-2S2 SA-AI0-5Sl SA-AI0-501 SA-AI0-1001 SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 JANUARY <14 <16 <9.0 <9.0 <21 <17 <12 <6.1 <15 <21 <20 <13 <16 <18 <24 <11 <19 <15 <10 ( 17 <16 <16 <10 <16 <14 <20 <10 <18 <15 <15 <12 <20 <20. <21 <10 <15 <15 <23 <15 <14 FEBRUARY <22 <13 <10 <22 <27 <19 <14 <21 <17 < 10 <20 <22 <15 <23 <13 <13 <20 <19 <20 <21 <22 <27 <22 <35 <24 <21 <10 <12 <21 <18 <13 <16 l.D MARCH <22 <19 <20 <22 <18 <18 <17 <17 I\\.) <21 <22 <20 <21 <24 <18 <17 <15 <18 <20 <30 0< 16 <15 <15 <12 <14 <17 <25 <20 <17 <12 <20 <12 <13 APRIL ( 1) <16 <20 ( 2) <23 <17 <12 <13 <21 <20 <9.0 <23 <20 <17 <20 <20 <15 <18 <19 <17 . < 13 <20 <25 <20 <21 <22 <16 <20 <14 <23 <27 <21 MAY <20 <10 <21 <16 <23 <11 <26 <20 <19 <16 <15 <13 <18 < 10 <12 <28 <26 <16 <16 <8.0 <16 <14 <18 <17 JUNE <18 <7.0 <36 <29 <18 <13 <13 <7.0 <15 <20 <19 <13 <19 <7.0 <19 <22 <14 <23 <20 <7.0 <18 <18 <14 <17

\\.0 w TABLE C-4 (cont'd) 1988 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCitm3 STATION ID MONTH SA-AI0-2S2 SA-AI0-5Sl SA-AI0-5Dl SA-AIO-lODl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 JULY ( 1 ) <13 <7.0 ( 17 <7.0 <20 <7.0 <20 <7.0 <18 <7.0 AUGUST <17 <7.0 <19 <7.0 <17 <7.0 <13 <7.0 SEPTEMBER <15 <7.0 <17 <7.0 <17 <7.0 <21 <7.0 OCTOBER <22 <7.0 <18 <7.0 <18 <7.d < 10 <7.0 <20 <7.0 NOVEMBER <15 <7.0 <15 <7.0 <12 <7.0 <16 <7.0 DECEMBER <17 <7.0 <14 <7.0 <12 <7.0 <18 <7.0

• I-131 results are corrected for decay to sample stop date.
  • Sampling dates can be found in Table C-5.

( 2)

• • • Results for 12-28-87 to 05-31-88 samples by Teledyne Isotopes.

<15 <16 <15 <27 <19 <23 <14 <26 <17 <22 <17 <21 <25 <16 <19 ( 3) <12 <20 <15 <17 <13 <20 <19 <16 <15 <24 <14 <23 <17 <17 <33 <28 <19 <17 <19 <19 <17 <19 <12 <13 <13 <14 ( 11 <20 <23 <14 <17 <16 < 20 <12 <15 <13 Results for 05-31-88 to 12-27-88 samples by Controls for Environmental Pollution, Inc. (1) Station SA-AI0-2S2 was deleted from the Program, effective March 28, 1988 (see Program Changes section). (2) Station SA-AIO-lODl was deleted from the Program, e~fective March 29, 1988 (see Program Changes section). (3) No sample collected due to an air sampler malfunction. (4) High LLD due to low sample volume (sampler malfunction). <15 <20 <20 ( 13 <13 <9.4 <8.2 <12 <11 <18 <15 ( 11 <19 <21 <13 <17 <16 <18 <10 ( 18 <16 < 16 <9.9 <19 <400 (4) <14 / ( SA-AI0-3H3 <14 <19 <21 <22 <13 <25 <20 <19 <8.9 <16 <20 <15 <13 <18 < 13 <24 <15 < 17 <14 <14 <13 <14 <19 <16 < 17 <14

TABLE C-5 1988 SAMPLING DATES FOR AIR SAMPLES STATION CODE MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 JANUARY 12-28-87 12-28-87 12-28-87 12-29-87 12-29-87 12-28-87 12-28-87 12-28-87 to to to to to to to to 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-04-88 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-04-88 to to to to to to to to 01-11-88 01-11-88 01-11-88 01-12-88 01-12-88 01-11-88 01-11-88 01-11-88 01-11-88 01-11-88 01-11-88 01-12-88. 01-12-88 01-11-88 01-11-88 01-11-88 to to to to to to to to 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 01-18-88 to to to to to to to to 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 \\0 ~ 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 01-25-88 to to to to to to to to 02-01-88 02-01-88 02-01-88 02-02-88 02-02-88 02-01-88 02-01-88 02-01-88 FEBRUARY 02-01-88 02-01-88 02-01-88 02-02-88 02-02-88 02-01-88 02-01-88 02-01-88 to to to to to to to to 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 to to to to to to to to 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 02-16-88 to, to to to to to to to 02-22-88 02-22-88 02-22-88 02-23-88 02-23-88 02-22-88 02-22-88 02-22-88 02-22-88 02-22-88 02-22-88 02-23-88 02-23-88 02-22-88 02-22-88 02-22-88 to to to to to to to to 02-29-88 02-29-88 02-29-88 03-01-88 03-01-88 02-29-88 02-29-88 02-29-88 MARCH 02-29-88 02-29-88 02-29-88 03-01-88 03-01-88 02-29-88 02-29-88 02-29-88 to to to to to to to to 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 03-07-88 to to to to to to to to 03-14-88 03-14-88 03-14-88 03-14-88 03-14-88 03-14-88 03-14-88 03-14-88 -~ _/

TAB.LE nt'd) 1988 SAMPLING DATES FOR AIR SAMPLES STATION CODE MONTH 2S2 5Sl 501 1001 16El lFl 2F2 3H3 MARCH (cont'd) 03-14-88 03-14-88 03-14-88. 03-14-88 03-14-88 03-14-88 03-14-88 03-14-88 to to to to to to to to 03-21-88 03-21-88 03-21-88 03-22-88 03-22-88 03-21-88 03-21-88 03-21-88 03-21-88 03-21-88 03-21-88 03-22-88 03-22-88 03-21-88 03-21-88 03-21-88 to to to to to to to to 03-28-88 03-26-88 ( 1) 03-28-88 03-29-88 03-29-88 03-28-88 03-28-88 03-28-88 APRIL (2) 03-29-88 03-28-88 ( 3) 03-29-88 03-28-88 03-28-88 03-28-88 to to to to to to 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 04-04-88 to to to to to to 04-11-88 04-11-88 04-12-88 04-11-88 04-11-88 04-11-88 U) 01 04-11-88 04-11-88 04-12-88 04-11-88 04-11-88 04-11-88 to to to to to to 04-18-88 04-18-88. 04-18-88 04-18-88 04-18-88 04-18-88 04-18-88 04-18-88 04-18-88 04-18-88 04-18-88 04-18-88 to to to to to to 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 04-25-88 to to to to to to 05-02-88 05-02-,88 05-03-88 05-02-88 05-02-88 05-02-88 MAY 05-02-88 05-02-88 05-03-88 05-02-88 05-02-88 05-02-88 to to to to to* to 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 05-09-88 to to to to to to 05-16-88 05-16-88 05-17-88 05-16-88 05-16-88 05-16-88 05-16-88 05-16-88 05-17-88 05-16-88 05-16-88 05-16-88 to to to to to to 05-23-88 05-23-88 05-24-88 05-23-88 05-23-88 05-23-88 05-23-88 05-23-88 05-24-88 05-23-88 05-23-88 05-23-88 to to to to to to 05-31-88 05-31-88 06-01-88 05-31-88 05-31-88 05-31-88

TABLE C-5 (cont'd) 1988 SAMPLING DATES FOR AIR SAMPLES STATION CODE MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 JUNE (2) 05-31-88 05-31-88 ( 3) 06-01-88 05-31-88 05-31-88 05-31-88 to to to to to to 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 06-06-88 to to to to to to 06-13-88 06-13-88 06-14-88 06-13-88 06-13-88 06-13-88 06-13-88 06-13-88 06-14-88 06-13-88 06-13-88 06-13-88 to to to to to to 06-20-88 06:_20-88 06-20-88 06-20-88 06-20-88 06-20-88 06-20-88 06-20-88 06-20-88 06-20-88 06-20-88 06-20-88 to to to to to to 06-27-88 06-27-88 06-28-88 06-27-88 06-27-88 06-27-88 \\0 °' JULY 06-27-88 06-27-88 06-28-88 06-27-88 06-27-88 06-27-88 to to to to to to 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 07-05-88 to to to to to to 07-11-88 07-11-88 07-12-88 07-11-88 07-11-88 07-11-88 07-11-88 07-11-88 07-12-88 07-11-88 07-11-88 07-11-88 to to to to to to 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 07-18-88 to to to to to to 07-25-88 07-25-88 07-26-88 07-25-88 07-25-88 07-25-88 07-25-88 07-25-88 07-26-88 07-25-88 07-25-88 07-25-88 to to to to to to 08-01-88 08-01-88 08-01-88 08-01-88 08-01-88 08-01-88 AUGUST 08-01-88 08-01-88 08-01-88 08-01-88 08-01-88 08-01-88 to to to to to to 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 08-08-88 to to to to to to 08-15-88 08-15-88 08-16-88 08-15-88 08-15-88 08-15-88

TABLE C nt'd) 1988 SAMPLING DATES FOR AIR SAMPLES STATION CODE MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 AUGUST (con't) (2) 08-15-88 08-15-88 ( 3) 08-16-88 (4) 08-15-88 08-15-88 to to to to to 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 08-22-88 to to to to to to 08-29-88 08-29-88 08-30-88 08-29-88 08-29-88 08-29-88 SEPTEMBER 08-29-88 08-29-88 08-30-88 08-29-88 08-29-88 08-29-88 to to to to to to 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 09-06-88 to to to to to to 09-12-88 09-12-88 09-13-88 09-12-88 09-12-88 09-12-88 \\0 ...J 09-12-89 09-12-88 09-13-88 09-12-88 09-12-88 09-12-88 to to to to to to 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 09-19-88 to to to to to to 09-26-88 09-26-88 09-27-88 09-26-88 09-26-88 09-26-88 OCTOBER 09-26-88 09-26-88 09-27-88 09-26-88 09-26-88 09-26-88 to to to to to to 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 10-03-88 to to to to to to 10-11-88 10-11-88 10-12-88 10-11-88 10-11-88 10-11-88 10-11-88 10-11-88 10-12-88 10-11-88 10-11-88 10-11-88 to to to to to to 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 10-17-88 to to to to

• to to 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 10-24-88 to to to to to to 10-31-88 10-31-88 10-31-88 10-3i-88 10-31-88 10-31-88

l.D CX> TABLE C-5 (cont'd) 1988 SAMPLING DATES FOR AIR SAMPLES STATION CODE MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 NOVEMBER ( 2) 10-31-88 10-31-88 (3) 10-31-88 10-31-88 10-31-88 to to to to to 11-07-88 11-07-88 11-07-88 11-07-88 11-07-88 11-07-88 11-07-88 11-07-88 11-07-88 11-07-88 to to to to to 11-14-88 11-14-88 11-14-88 11-14-88 11-14-88 11-14-88 11-14-88 11-14-88 11-14-88 11-14-88 to to to to to 11-21-88 11-21-88 11-21-88 11-21-88 11-21-88 11-21-88 11-21-88 11-21-88 11-21-88 11-21-88 to to to to to 11-28-88 11-28-88 11-29-88 11-28-88 11-28-88 DECEMBER 11-28-88 11-28-88 11-29-88 11-28-88 11-28-88 to to to to to 12-05-88 12-05-88 12-05-88 12-05-88 12-05-88 12-05-88 12-05-88 12-05-88 12-05-88 12-05-88 to to to to to 12-12-88 12-12-88 12-12-88 12-12-88 12-12-88 12-12-88 12-12-88 12-12-88 12-12-88 12-12-88 to to to to to 12-20-88 12-20-88 12-20-88 12-20-88 12-13-88 12-20-88 12-20-88 12-20-88 12-20-88 12-20-88 to to to to to 12-27-88 12-27-88 12-27-88 12-27-88 12-27-88 (1) Reduced sampling period due to a power interruption. (2) Station SA-APT-2S2 was deleted from the Program, effective March 28, 1988 (see Program Changes section). (3) Station SA-APT-lODl was deleted from the Program, effective March 29, 1988 (see Program Changes section). (4) No sample collected due to an air sampler malfunction. (5) Reduced sampling period due to an air sampler malfunction. 3H3 10-31-88 to 11-07-88 11-07-88 to 11-14-88 11-14-88 to 11-21-88 11-21-88 to 11-28-88 11-28-88 to 12-05-88 12-05-88 to 12-12-88 12-12-88 to (5) 12-19-88 12-19-88 to 12-27-88

TABLE C-6 1988 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION STATION ID: SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD ALPHA BETA 12-29-87 to 02-02-88 <1.8 3.0+/-0.9 02-02-88 to 02-29-88 <1.2 5.6+/-1.0 02-29-88 to 03-29-88 <1.2 4.4+/-1.0 03-29-88 to 05-02-88 ( 1) 05-02-88 to 06-01-88 3.7+/-1.8 36+/-4 06-01-88 to 06-27-88 ( 2) 6-27-88 to 08-01-88 <1.3 12+/-1 08-01-88 to 08-30-88 <1.0 4.5+/-0.9 08-30-88 to 09-26-88 <1.3 4.5+/-1.5 09-26-88 to 10"."'"31-88 2.5+/-1-.5 13+/-3 10-31-88 to 11-28-88 <2.4 1.2+/-0.6 11-28-88 to 12-27-88 <1.2 5.0+/-1.6 AVERAGE 8.9+/-20 (1) No sample collected due to a precipitation sampler malfunction. (2) Not analyzed due to insufficient precipitation during sampling period. 99 TRITIUM <150 <160 <160 150+/-90 180+/-90 <140 <140 <150 <160 <150

TABLE C-7 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN PRECIPITATION STATION ID: SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD Be-7 Ra-226 12-29-87 to 02-02-88 47+/-19 9.2+/-4.2 02-02-88 to 02-29-88 58+/-20 <8.6 02-29-88 to 03-29-88 76+/-17 <7.4 03-29-88 to 05-02-88 (1) 05-02-88 to 06-01-88 250+/-73 <29 06-01-88 to 06-27-88 ( 2) 06-27-88 to 08-01-88 120+/-21 <8.3 08-01-88 to 08-30-88 48+/-11 <5.1 08-30-88 to 09-26-88 76+/-18 6.7+/-3.7 09-26-88 to 10-31-88 110+/-48 22+/-9 10-31-88 to 11-28-88 48+/-17 <8.1 11-28-88 to 12-27-88 52+/-16 <7.3 AVERAGE 88+/-120

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(1) No sample collected due to a precipitation sampler malfunction. (2) Not analyzed due to insufficient precipitation during sampling period. 100

TABLE C-8 1988 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Tel*edyne Isotopes) JANUARY APRIL STATION ID to to MARCH JUNE SA-IDM-2S2 5.4+/-0.2 4.5+/-0.4 SA-IDM-5Sl 4.7+/-0.l 4.0+/-0.2 SA-IDM-6S2 5.1+/-0.5 4.7+/-0.3 SA-IDM-7Sl 5.6+/-0.4 5.6+/-0.4 SA-IDM-lOSl 6.0+/-0.5 5.2+/-0.4 SA-IDM-llSl 6.6+/-1.0 5.9+/-0.6 SA-IDM-4D2 5.4+/-0.3 4.8+/-0.3 SA-IDM-5Dl 5.0+/-0.4 4.4+/-0.2 SA-IDM-lODl 5.5+/-0.6 4.7+/-0.5 SA-IDM-14Dl 5.4+/-0.3 4.7+/-0.4 SA-IDM-2El 5.1+/-0.4 4.7+/-0.3 SA-IDM-3El 4.7+/-0.1 4.4+/-0.3 SA-IDM-9El 5.9+/-0.5 5.2+/-0.6 SA-IDM-11E2 5.7+/-0.4 5.1+/-0.6 SA-IDM-12El 5.5+/-0.4 5.1+/-0.5 SA-IDM-13El 4.9+/-0.2 4.2+/-0.3 SA-IDM-16El 5".2+/-0.3 4.8+/-0.2 SA-IDM-lFl 5.2+/-0.3 4.3+/-0.4 SA-IDM-2F2 4.3+/-0.2 3.6+/-0.l SA-IDM-2F5 5.1+/-0.4 5.0+/-0.4 SA-IDM-2F6 5.1+/-0.3 4.5+/-0.2 SA-IDM-3F2 4.8+/-0.3 4.0+/-0.3 SA-IDM-3F3 4.7+/-0.4 4.0+/-0.3 SA-IDM-5Fl 4.8+/-0.3 4.3+/-0.4 SA-IDM-6Fl 4.4+/-0.2 3.9+/-0.4 SA-IDM-7F2 4.1+/-0.0 3.5+/-0.l SA-IDM-10F2 5.5+/-0.4 5.0+/-0.5 SA-IDM-llFl 5.4+/-0.3 4.9+/-0.3 SA-IDM-12Fl 5.3+/-0.4 4.7+/-0.4 SA-IDM-13F2 5.5+/-0.7 4.5+/-0.4 SA-IDM-13F3 5.4+/-0.3 4.6+/-0.3 SA-IDM-13F4 .5.1+/-0.3 4.8+/-0.4 SA-IDM-14F2 5.2+/-0.3 4.8+/-0.3 SA-IDM-15F3* 5.8+/-0.6 5.2+/-0.5 SA-IDM-16F2 5.0+/-0.2 4.5+/-0.2 SA-IDM-1G3 ~C~ 6.3+/-0.5 5.5+/-0.4 SA-IDM-3Gl C 5.6+/-0.4 5.1+/-0.4 SA-IDM-lOGl* ~ C~ 5.6+/-0.4 5.1+/-0.4 SA-IDM-16Gl C 6.2+/-0.5 5.5+/-0.3 SA-IDM-3Hl ~C~ 5.6+/-0.3 4.8+/-0.1 SA-IDM-3H3 C 5.4+/-0.3 5.1+/-0.4 AVERAGE 5.3+/-1.0 4.7+/-1.0 The standard month = 30.4 days. control station TLD missing from field location

• 101 JULY OCTOBER to to SEPTEMBER DECEMBER 5.2+/-0.2 4.5+/-0.5 4.6+/-0.2 4.0+/-0.2 5.2+/-0.4 4.6+/-0.4 6.1+/-0.5 5.6+/-0.6 5.8+/-0.4 5.4+/-0.3 6.6+/-0.8 6.5+/-0.8 5.5+/-0.5 5.2+/-0.4 5.2+/-0.2 4.7+/-0.3 5.7+/-0.4 5.2+/-0.5 5.5+/-0.6 4.8+/-0.4 5.4+/-0.5 4.9+/-0.4 4.4+/-0.4 4.5+/-0.3 6.1+/-0.8 5.6+/-0.8 6.0+/-0.6 5.4+/-0.8 5.7+/-0.4 5.3+/-0.4 5.0+/-0.3 4.4+/-0.4 5.5+/-0.5 4.7+/-0.3 5.5+/-0.4 4.8+/-0.5 4.2+/-0.l 3.7+/-0.1 5.4+/-0.3 4.7+/-0.3 5.2+/-0.2 4.8+/-0.3 4.7+/-0.3 4.3+/-0.3 4.7+/-0.2 4.5+/-0.3 5.0+/-0.3 4.4+/-0.3 4.5+/-0.3 4.0+/-0.4 4.1+/-0.2 3.6+/-0.1 5.9+/-0.5 5.1+/-0.7 5.8+/-0.5 5.2+/-0.5 5.7+/-0.4 5.0+/-0.4 5.5+/-0.3 4.8+/-0.5 5.6+/-0.2 5.1+/-0.7 5.6+/-0.4 4.8+/-0.4 5.5+/-0.4 (1) 6.0+/-0.5 5.4+/-0.6 5.2+/-0.2 4.5+/-0.4 6.4+/-0.3 5.5+/-0.4
• 5.6+/-0.2 5.1+/-0.6 5.9+/-0.4 4.9+/-0.4 6.1+/-0.5 5.4+/-0.7 5.7+/-0.4 5.0+/-0.2 5.4+/-0.2 5.1+/-0.6 5.4+/-1.1 4.9+/-1.1 GRAND AVERAGE AVERAGE 4.9+/-0.9 4.3+/-0.8 4.9+/-0.6 5.7+/-0.5 5.6+/-0.7 6.4+/-0.7 5.2+/-0.6 4.8+/-0.7 5.3+/-0.9 5.1+/-0.8 5.0+/-0.6 4.5+/-0.3 5.7+/-0.8 5.5+/-0.8 5.4+/-0.5 4.6+/-0.8 5.0+/-0.7 4.9+/-1.0 4.0+/-b.7 5.0+/-0.6 4.9+/-0.6 4.4+/-0.5 4.5+/-0.6 4.6+/-0.6 4.2+/-0.6 3.8+/-0.6 5.4+/-0.8 5.3+/-0.8 5.2+/-0.8 5.1+/-1.0 5.2+/-0.9 5.1+/-0.8 5.2+/-0.7 5.6+/-0.7 4.8+/-0.7 5.9+/-1.0 5.3+/-0.6 5.4+/-0.9 5.8+/-0.8 5.3+/-0.9 5.2+/-0.3 5.1+/-1.2

TABLE C-9 1988 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes) STATION ID JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 6.2+/-0.6 6.8+/-0.5 6.7+/-0.3 5.8+/-0.6 6.0+/-0.3 7.7+/-0.5 SA-IDM-5Sl 5.1+/-0.3 5.8+/-0.9 6.0+/-0.4 5.2+/-0.3 5.4+/-0.4 7.0+/-0.4 SA-IDM-6S2 5.7+/-0.4 6.1+/-0.4 6.5+/-0.4 5.7+/-0.6 5.9+/-0.3 7.7+/-0.5 SA-IDM-7Sl 7.1+/-0.7 7.0+/-0.8 7.8+/-0.7 6.7+/-0.7 6.9+/-0.3 8.4+/-0.7 SA-IDM-lOSl 6.4+/-0.5 6.9+/-0.9 7.9+/-1.2 6.7+/-0.6 6.7+/-0.5 8.0+/-0.6 SA-IDM-llSl 6.3+/-0.6 8.1+/-1.4 9.8+/-2.2 8.2+/-0.8 7.1+/-0.4 8.1+/-0.6 SA-IDM-5Dl 5.6+/-0.5 5.9+/-0.4 . 6.6+/-0. 3 5.5+/-0.4 5.7+/-0.4 7.2+/-0.7 SA-IDM-lODl 6.1+/-0.2 6.2+/-0.4 7.0+/-0.5 6.0+/-0.5 6.1+/-0.3 7.7+/-0.7 SA-IDM-14Dl 5.8+/-0.6 6.4+/-0.4 6.9+/-0.4 6.1+/-0.6 6.5+/-0.3 8.1+/-0.8 SA-IDM-2El 5.8+/-0.6 5.8+/-0.5 6.6+/-0.4 5.5+/-0.4 5.9+/-0.7 7.6+/-0.5 SA-IDM-3El 5.7+/-0.5 5.7+/-0.5 6.2+/-0.3 5.5+/-0.7 5.6+/-0.3 7.2+/-0.5 SA-IDM-13El 5.4+/-0.3 5.8+/-0.5 6.3+/-0.5 5.5+/-0.4 5.7+/-0.3 7.5+/-0.8 0 SA-IDM-16El 6.2+/-0.5 6.2+/-0.6 6.9+/-0.6 5.6+/-0.4 5.3+/-0.3 7.6+/-0.5 to..) SA-IDM-lFl 6.1+/-0.6 6.1+/-0.5 6.7+/-0.5 5.7+/-0.5 6.2+/-0.4 7.6+/-0.4 SA-IDM-2F2 5.0+/-0.4 5.2+/-0.2 5.8+/-0.3 4.8+/-0.2 5.1+/-0.2 6.6+/-0.2 SA-IDM-2F6 5.9+/-0.6 6.l+/-Q.3 6.8+/-0.3 5.5+/-0.4 6.0+/-0.4 7.5+/-0.4 SA-IDM-5Fl 5.5+/-0.2 5.7+/-0.3 6.4+/-0.4 5.4+/-0.4 5.5+/-0.4 7.3+/-0.5 SA-IDM-6Fl 5.0+/-0.3 5.2+/-0.3 5.8+/-0.4 4.9+/-0.2 5.2+/-0.3 6.9+/-0.4 SA-IDM-7F2 4.6+/-0.1 5.0+/-0.2 5.6+/-0.2 4.4+/-0.3 4.8+/-0.l 6.3+/-0.3 SA-IDM-llFl 5.4+/-0.1 6.4+/-0.5 7.0+/-0.5 6.2+/-0.9 6.4+/-0.5 8.1+/-0.6 SA-IDM-13F4 5.8+/-0.3 6.1+/-0.6 6.7+/-0.3 5.9+/-0.4 6.2+/-0.3 7.8+/-0.4 SA-IDM-3Gl (C) 6.0+/-0.4 6.3+/-0.5 7.1+/-0.5 6.0+/-0.6 6.1+/-0.4 7.8+/-0.5 SA-IDM-3Hl (C) 6.3+/-0.2 6.4+/-0.4 6.0+/-0.6 6.2+/-0.6 6.3+/-0.2 8.0+/-0.5 SA-IDM-3H3 (C) 6.5+/-0.8 6.7+/-0.5 7.1+/-0.5 6.3+/-0.4 6.3+/-0.5 8.1+/-0.6 AVERAGE 5.8+/-1.1

6. 2+/-1. 3 6.8+/-1.7

5. 8+/-1. 5

6. 0+/-1.1 7.6+/-1. 0

TABLE C-9 (cont'd) 1988 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 6.5+/-0.5 5.9+/-0.7 4.9+/-0.6 6.2+/-0.2 6.8+/-0.5 7.4+/-0.5 6.4+/-1.5 SA-IDM-5Sl 5.6+/-0.2 5.2+/-0.4 4.6+/-0.4 5.6+/-0.3 6.0+/-0.4 6.9+/-0.3 5.7+/-1.4 SA-IDM-6S2 6.3+/-0.3 5.9+/-0.6 5.1+/-0.5 6.1+/-0.5 6.4+/-0.5 7.5+/-0.4

6. 2+/-1. 5 SA-IDM-7Sl 7.3+/-0.6 7.7+/-1.5 5.8+/-0.4 7.4+/-0.6 7.6+/-0.6 8.4+/-0.6

7. 3+/-1.4 SA-IDM-lOSl 7.0+/-0.6 6.4+/-0.6 5.2+/-0.2 7.5+/-0.7 7.2+/-0.4 8.3+/-0.6 7.0+/-1. 7 SA-IDM-llSl

8. 3+/-1.6 7.0+/-1.0 6.1+/-0.6 8.5+/-1. 0.

8.6+/-1.2 8.9+/-1.l 7.9+/-2.2 SA-IDM-5Dl 5.9+/-0.9 5.4+/-0.5 5.3+/-0.4 6.3+/-0.7 6.4+/-0.5 7.2+/-0.4 6.1+/-1. 3 SA-IDM-lODl 6.8+/-0.8 6.5+/-0.8 5.6+/-0.4 7.0+/-0.6 6.8+/-0.9 8.4+/-0.9 6.7+/-1.6 SA-IDM-14Dl 6.7+/-0.6 6.3+/-0.8 5.6+/-0.7 6.5+/-0.5 6.6+/-0.6 7.8+/-0.5 6.6+/-1.4 SA-IDM-2El 6.2+/-0.5 6.0+/-0.7 5.2+/-0.7 6.1+/-0.6 6.3+/-0.5 7.2+/-0.5 6.2+/-1.4 SA-IDM-3El 5.8+/-0.5 5.6+/-0.4 4.8+/-0.5 5.9+/-0.5 6.0+/-0.6 7.2+/-0.5 5.9+/-1.4 SA-IDM-13El 5.9+/-0.3 5.5+/-0.4 4.9+/-0.3 5.8+/-0.5 6.0+/-0.5 7.5+/-0.5 6.0+/-1.6 0 SA-IDM-16El 6.6+/-0.6 5.9+/-0.7 5;4+/-0.5 6.4+/-0.5 6.6+/-0.5 7.6+/-0.5 6.4+/-1.5 w SA-IDM-lFl 6.2+/-0.6 6.2+/-0.6 5.4+/-0.6 6.4+/-0.5 6.6+/-0.3 7.7+/-0.5 6.4+/-1.4 SA-IDM-2F2 5.3+/-0.5 5.1+/-0.5 4.3+/-0.4 5.2+/-0.3 4.6+/-0.l 6.7+/-0.2 5.3+/-1.4 SA-IDM-2F6 6.0+/-0.2 6.2+/-0.3 5.3+/-0.4 6.2+/-0.5 6.5+/-0.4

7. 5+/-1.2 6.3+/-1.4 SA-IDM-5Fl 5.7+/-0.4 5.7+/-0.3 4.8+/-0.3 5.9+/-0.3 6.0+/-0.5 7.1+/-0.6 5.9+/-1.4 SA-IDM-6Fl 5.2+/-0.3 5.1+/-0.3 4.5+/-0.0 5.1+/-0.2 5.7+/-0.2 6.8+/-0.4 5.4+/-1. 5 SA-IDM-7F2

. 4.9+/-0.l 4.7+/-0.3 4.1+/-0.2 4.9+/-0.2 5.4+/-0.2 6.3+/-0.3 5.1+/-1.4 SA-IDM-llFl 6.9+/-0.7 6.9+/-0.7 5.6+/-0.7 6.8+/-0.7 7.1+/-0.7 8.3+/-0.8 6.8+/-1. 7 SA-IDM-13F4 6.4+/-0.6 6.2+/-0.5 5.2+/-0.3 6.3+/-0.7 6.5+/-0.5 8.1+/-0.6 6.4+/-1.6 SA-IDM-3Gl (C) 6.7+/-0.5 6.5+/-0.5 5.4+/-0.6 6.7+/-0.5 6.8+/-0.6 7.8+/-0.5 6.6+/-1.4 SA-IDM-3Hl (C) 6.4+/-0.6 6.3+/-0.3 5.7+/-0.7 6.6+/-0.5 6.9+/-0.4 7.8+/-0.5 6.6+/-1.4 SA-IDM-3H3 (C) 6.7+/-0.4 6.3+/-0.4 5.9+/-0.5 6.5+/-0.7 6.9+/-0.6 8.2+/-0.5 6.8+/-1.4 AVERAGE 6.3+/-1.5 6.0+/-1.4

5. 2+/-1. 0

6. 3+/-1.6 6.5+/-1..5 7.6+/-1.2 GRAND AVERAGE 6.3+/-1.9

• The standard month = 30.4 days.

(C) Control station

I-' 0 ~ TABLE C-10 1988 CONCENTRATIONS 6F IODINE-131* IN MILK** Results in Units of pCi/L STATION ID*** JANUARY FEBRUARY MARCH APRIL MAY SA-MLK-13E3 <0.4 <0.4 <0.5 ( 1) ( 1) SA-MLK-2F7 <0.4 <0.5 <0.4 <0.5 <0.6 <0.5 <0.5 SA-MLK-5F2 <0.6 <0.7 <0.6 (2) (2) SA-MLK-11F3 <0.4 <0.4 <0.4 <0.7 <0.4 <0.5 <0.6 SA-MLK-14Fl <0.4 <0.5 <0.4 <0.4 <0.5 <0.4 <0.6 SA-MLK-361 <0.6 <0.4 <0.5 <0.5 <0.6 (Control) <0.6 <0.5 STATION ID*** JULY AUGUST SEPTEMBER OCTOBER NOVEMBER SA-MLK-13E3 (1) ( 1) SA-MLK-2F7 <0.6 <0.6 <0.5 <0.3 <0.5 <0.6 <0.4 <0.4 <0.4 <0.4 SA-MLK-5F2 ( 2) ( 2) SA-MLK-11F3 "<0.6 <0.4 <0.3 <0.6 <0.5 <0.5 <0.5 <0.5 <0.4 <0.5 SA-MLK-14Fl <0.7 <0.4 <0.4 <0.4 <0.6 <0.5 <0.4 <0.4 <0.4 <0.4 SA-MLK-361 <0.3 <0.6 <0.5 <0.4 <0.4 (Centro l) <0.5 <0.3 <0.4 <0.4 <0.4

• 1-131 results are corrected for decay to midpoint of collection period.
  • Monthly sample collected during Jan., Feb., March and Dec., when animals are not on pasture.
    • Sampling dates can be found in Table C-13.

(1) Station SA-MLK-13E3 was deleted from the Program, effective March 9, 1988 (see Program Changes section). (2) Station SA-MLK-5F2 was deleted from the Program, effective March 9, 1988 (see Program Changes section). JUNE <0.6 <0.5 <0.4 <0.4 <0.3 <0.5 <0.5 <0.6 DECEMBER <0.4 <0.6 <0.4 <0.3

TABLE C-11 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN MILK** Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING PERIOD Sr-89 SA-MLK-2F7 07/05-06/88 <1.1 SA-MLK-11F3 07/05-06/88 <1.2 SA-MLK-14Fl 07/05-06/88 <1.3 SA-MLK-3Gl 07/05-06/88 <1.3 (Control) AVERAGE Sr-89 results are corrected for decay to midpoint of collection period. Sr-90 1.1+/-0.4 1.6+/-0.4 1.2+/-0.5 2.3+/-0.5 1.6+/-1.1 . ** Management audit analyses, not required by Technical. Specifications or by specific cqrnrnitments to local officials. 105

TABLE C-12 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE JANUARY FEBRUARY MARCH MONTHLY MONTHLY MONTHLY SA-MLK-13E3 K-40 1400+/-82 1300+/- 77 1400+/-72 Cs-137 <3.7 <4.1 <3.5 Ra-226 <7.0 <5.8

5. 2+/-3. o*

Th-232 <11 <14 <9. 5. SA-MLK-2F7 K-40 1200+/-90 1300+/-92 1300+/-80 Cs-137 <4.0 <4.3

2. 9+/-1. 7 Ra-226

<8.0 <8.0 <7.4 Th-232 <14 <14 <13 SA-MLK-5F2 K-40 1400+/-83 1200+/-74 1300+/-76 Cs-137 <3.8 <4.2 <3.5 Ra-226 <6.9 <7.8 8.6+/-4.6 Th-232 <13 <15 <14

• SA-MLK-11F3 K-40 1400+/-71 1300+/-91 1300+/-70 Cs-137

<2.8 <3.8 <2.6 Ra-226 <5.9 <6.0 <6.7 Th-232 <7.8 <14 <11 SA-MLK-14Fl K-40 1500+/-98 1300+/-88 130.0+/-80 Cs-137 <4.2 <3.5 <3.3 Ra-226 <8.6 11+/-5 <6.8 Th-232 < 14 <13 <16 SA-MLK-3Gl K-40 1300+/-74 1400+/-71 1400+/-95 (Control) Cs-137 <3.0 <3.6 <4.0 Ra-226 <7.9 <6.3 <7.9 Th-232 <13 <8.3 <17 AVERAGE K-40 1400+/-210 1300+/-130 1300+/-100 106

TABLE C-12 (cont'd.) 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE APRIL MAY JUNE SEMI-MONTHLY SEMI-MONTHLY SEMI-MONTHLY SA-MLK-13E3 K-40 ( 1) Cs-137 ( 1) Ra-226 ( 1) Th-232 ( 1) SA-MLK-2F7 K-40 1300+/-79 1200+/-56 1400+/-73 1300+/-80 1400+/-81 1300+/-81 Cs-137 <4.0 <3.0 <3.0 <4.0 <3.9 <3.1 Ra-226 <7.9 <5.1 <5.7 <7.5 <7.6 <6.4 Th-232 <15 < 10 <7.7 <13 <11 <10 SA-MLK-5F2 K-40 (2) Cs-137 ( 2) Ra-226 ( 2) Th-232 (2) SA-MLK-11F3 K-40 1300+/-76 1300+/-65 1400+/-94 1300+/-76 1300+/-76 1400+/-96 Cs-137 <3.6 <2.6 <3.3 <3.4 3.5+/-2.l <4.2 Ra-226 <6.9 <5.2 <8.0 <6.9 <8.5 <8.3 Th-232 <.13 <9. 5 <16 <12 <13 <18 SA-MLK-14Fl K-40 1400+/-72 1400+/-91 1300+/-82 1400+/-71 1300+/-89 1300+/-71 Cs-137 <3.1 <3.3 <3.1 <3.2 <3.3 <2.9 Ra-226 <6.0 <7.7 <6.8 <5.6 <6.1 <5.3 Th-232 <8.2 < 16 < 13 < 11 <15 <12 SA-MLK-3Gl K-40 1400+/-96 1300+/-71 1300+/-89 1400+/-95 1300+/-94 1400+/-91 (Control) Cs-137 <4.4 <3.0 <4.2 <3.4 <4.4 <3.0 Ra-226 <7.0 <5.9 <7.8 <7.2 ( 7. 1 <6.6 Th-232 < 15 <8.2 <10 < 15 <14 <9.8 AVERAGE K-40 1400+/-120 1300+/-160 1400+/-120 1400+/-120 1300+/-100 1400+/-120 107

TABLE C-12 (cont'd.) 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE JULY AUGUST SEPTEMBER SEMI-MONTHLY SEMI-MONTHLY SEMI-MONTHLY SA-MLK-13E3 K-40 ( 1) Cs-137 ( 1) Ra-226 ( 1) Th-232 ( 1) SA-MLK-2F7 K-40 1200+/-91 1300+/-77 1400+/-91 1300+/-88 1300+/-90 1400+/-91 Cs-137 <3.9 <3.7 <3.2 <3.7 <4.3 <4.2 Ra-226 <7.7 <5.2 <8.6 <6.8 <7.7 <7.3 Th-232 <13 <11 <17 <15 <15 <18 SA-MLK-5F2 K-40 (2) Cs-137 ( 2) Ra-226 ( 2). Th-232 (2) SA-MLK-11F3 K-40 1400+/-72 1300+/-82 1500+/-100 1400+/-96 1300+/-81 1400+/-83 Cs-137 <2.4 <3.8 <4.3 <3.9 <3.5 3.1+/-1.7 Ra-226 <5.4 <7.7 <7.7 <7.8 <8.1 <7.4 Th-232 <13 <12 <13 <15 <14 <14 SA-MLK-14Fl K-40 1400+/-91 1300+/-93 1300+/-71 1300+/-83 1200+/-69 1300+/-93 Cs-137 <3.6 <4.0 <3.0 <3. 4* 4.4+/-1.9 <4.6 Ra-226 <7.8 <8.0 10+/-4 <8.3 <6.5 12+/-5 Th-232 <15 <15 <11 < 14 <10 <13 SA-MLK-3Gl K-40 1200+/-78 1300+/-94 1300+/-78 1400+/-73 1300+/-92 1400+/-73 (Control) Cs-137 <3.4 <4.0 <3.5 <2.3 <4.3 <2.7 Ra-226 <7.6 <7.9 <8.0 <5.3 <7.8 <5.5 Th-232 <15 <15 < 11 < 10 <16 <11 AVERAGE K-40 1300+/-230 1300+/-0 1400+/-190 1400+/-120 1300+/-100 1400+/-100 108

TABLE C-12,(cont'd.) 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE OCTOBER NOVEMBER DECEMBER AVERAGE SEMI-MONTHLY SEMI-MONTHLY MONTHLY SA-MLK-13E3 K-40 ( 1) 1400+/-120 Cs-137 ( 1) Ra-226 ( 1) Th-232 ( 1) SA-MLK-2F7 K-40 1300+/-70 1400+/-82 1200+/-79 1300+/-72 1400+/-89 1300+/-140 Cs-137 <2.6 <3.9 <4.1 <3.0 <4.3 Ra-226 <5.4 <7.4 <7.4 <6.1 <6.5 Th-232 <11 <14 <14 <8.8 <12 SA-MLK-5F2 K-40 (2) 1300+/-200 Cs-137 (2) Ra-226 (2) Th-232 (2) SA-MLK-11F3 K-40 1500+/-96 1300+/-93 1300+/-95 1400+/-97 1400+/-73 1400+/-140 Cs-137 <4.2 <4.2 <4.6 <3.3 <2.5 Ra-226 <6.8 <6.4 <7.6 <7.1 <6.6 Th-232 <16 <14 <16 <14 7.5+/-4.5 SA-MLK-14Fl K-40 1300+/-80 1300+/-78 1300+/-87 1300+/-79 1300+/-70 "1300+/-130 Cs-137 <3.3 <3.2 <3.3 <3.8 <3.3 Ra-226 <7.3 7.7+/-4.2 <6.8 <8.0 9.0+/-3.5 Th-232 <12 <11 15+/-7 <11 <6.9 SA-MLK-3Gl K-40 1300+/-90 1300+/-81 1200+/-77 1400+/-93 1300+/-88 1300+/-130 (Control) Cs-137 <3.1 <3.7 <3.6 <3.5 <3.7 Ra-226 <7.0 <7.9 <7.3 <5.5 < 7. 1 Th-232 <14 . < 11 <14 19+/-8 <8.9 AVERAGE K-40 1400+/-200 1300+/-100 1200+/-120 1400+/-120 1400+/-120 1300+/-140

• A 11 other garrma emitters searched for were <LLD; typical LLDs are given in Table C-31.
  • Sampling dates can be found in Table C-13.

Station SA-MLK-13E3 was deleted from the Program, effective March 9, 1988 (see Program Changes se~tion). Station SA-MLK-5F2 was deleted from the Program, effective March 9, 1988 (see Pro gr am Changes sect.ion). 109

TABLE C-13 l988 SAMPLING DATES FOR MILK SAMPLES STATION CODE MONTH 13E3 2F7 5F2 11F3 14Fl 3Gl JANUARY 01-05-88 01-05-88 01-05-88 01-05-88 01-05-88 01-03-88 to to to to to to 01-06-88 01-06-88 01-06-88 01-06-88 01-06-88 01-05-88 FEBRUARY 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 02-08-88 to to to to to to 02-09-88 02-09-88 02-09-88 02-09-88 02-09-88 02-09-88 MARCH 03-07-88 03-05-88 03-07-88 03-07-88 03-07-88 03-07-88 to to to to to to 03-08-88 03-07-88 03-08-88 03-08-88 03-08-88 03-08-88 APRIL (1) 04-04-88 (2) 04-03-88 04-04-88 04-04-88 I-' to to to to I-' 04-05-88 04-04-88 04-05-88 04-05-88 0 04-18-88 04-18-88 04-18-88 04-18-88 to to to to 04-19-88 04-19-88 04-19-88 04-19-88 MAY 05-08-88 05-09-88 05-08-88 05-08-88 to to to to 05-09-88 05-10-88 05-09-88 05-09-88 05-22-88 05-23-88 05-22-88 05-22-88 to to to to 05-23-88 05-24-88 05-23-88 05-23-88 JUNE 06-05-88 06-06-88 06-05-88 06-05-88 to to to to 06-06-88 06-07-88 06-06-88 06-06-88 .. 06-19-88 06-20-88 06-19-88 06-19-88 to to to to 06-20-88 06-21-88 06-20-88 06-20-88

TABLE cont'd) 1988 FOR MILK SAMPLES STATION CODE MONTH 13E3 2F7 5.F2. 11F3 14Fl 07-05-88 ( 2) 07-05-88 07-05-88 to to to JULY ( 1) 07-06-88 07-06-88 07-06-88 07-17-88 07-17-88 07-17-88 to to to 07-18-88 07-17-88 07-18-88 AUGUST 08-08-88 08-08-88 08-08-88 to to to 08-09-88 08-09-88 08-09-88 08-20-88 08-22-88 08-22-88 to to to 08-22-88 08-23-88 08-23-88 SEPTEMBER 09-05-88 09-05-88 09-05-88 to to to 09-06-88 09-06-88 09-06-88 09-19-88 09-19-88 09-19-88 to to to 09-20-88 09-20-88 09-20-88 OCTOBER 10-03-88 10-03-88 10-03-88 to to to 10-04-88 10-04-88 10-04-88 10-17-88 10-17-88 10-17-88 to to to 10-18-88 10-18-88 10-18-88 NOVEMBER 10-31-88 10-31-88 10-31-88 to to to 11-01-88 11-01-88 11-01-88 11-14-88 11-14-88 11-14-88 to to to ll-'15-88 11-15-88 11-15-88 DECEMBER 12-04-88 12-04-88 12-04-88 to to to 12-05-88 12-05-88 12-05-88 (1) Station SA-MLK-13E3 was deleted from the Program, effectiv7 March 9, 1988 (see Program Changes section). (2) Station SA-MLK-5F2 was deleted from the Program, effective March 9, 1988 (see Program Changes section). 3Gl 07-05-88 to 07-06-88 07-17-88 to 07-18-88 08-08-88 to 08-09 08-22-88 to 08-23-88 0 9-05-88 to 09-06-88 09-19-88 to 09-20-88 10-03-88 to 10-04-88 10-17-88 to 10-18-88 10-31-88 to H-01-88 11-14-88 to 11-15-88 12-04-88 to 12-05-88

TABLE C-14 1988 CONCENT~TIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID RADIOACTIVITY 01-11-88 02-16-88. 03-14-88 04-11-88 05-16-88 06-13-88 SA-WWA-2S3 Alpha <2.0 <1.6 <3.5 <1.2 1.9+/-1.2 <1.4 Beta 5.9+/-1.0 5.5+/-1.0 5.6+/-1.0 5.2+/-1.0 6.1+/-1.0 8.2+/-1.1 K-40 5.4+/-0.5 2.4+/-0.2 3.7+/-0.4 5.1+/-0.5 5.0+/-0.5 7.8+/-0.8 H-3 <150 160+/-90 <150 <140 <140 <140 SA-WWA-5Dl Alpha (1) <1.6 <1.3 <1.2 2.4+/-1.4 <1.4 I-' Beta (1) 17+/-2 17+/-2 16+/-2 18+/-2 15+/-1 ~ K-40 ( 1) 12+/-1. 12+/-1 16+/-2 16+/-2 16+/-2 H-3 ( 1) <150 <160 <140 <140 <140 SA-WWA-3El (C) Alpha <1.8 <1.6 <1.8 <1.3 1.5+/-1.1 <1.4 Beta 10+/-1 10+/-1 11+/-1 11+/-1 12+/-1 10+/-1 K-40 9.3+/-0.9 7.5+/-0.8 8.1+/-0.8 12+/-1 11+/-1 11+/-1 H-3 <150 <150 <160 <140 <140 <140 AYEBAGE Alpha 1.9+/-0.9 Beta 8.0+/-5.8 11+/-12 11+/-11 11+/-11 12+/-12 11+/-7 K-40 7.4+/-5.5 7.3+/-9.6 7.9+/-8.3 11+/-11 11+/-11 12+/-8 H-3

w TABLE C (cont'd) 1988 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER STATION ID RADIOACTIVITY 07-11-88 SA-WWA-2S3 Alpha <0.6 Beta 5.0+/-0.9 K-40 4.0+/-0.4 H-3 <140 SA-~A-5Dl Alpha 2.0+/-1.l Beta 17+/-2 K-40 14.+/-1 H-3 <150 SA-~A-3El (C) Alpha 0.9+/-0.8 Beta 9.8+/-1.2 K-40 9.4+/-0.9 H-3 <150 A~EBAGE Alpha 1.2+/-1.5 Beta 11+/-12 K-40 9.1+/-10 H-3

• Station SA-WWA-5Dl
  • Station SA-WWA-5Dl

( C) Control Station ( 1) January sample was entire month. was was not Results in Units of pCi/L +/- 2 sigma 08-15-88. 09-12-88 10-11-88 11-07-88 12-12-88 <1.3 <l. 0 <1.2 <1.2 <2.4 4.5+/-0.9. 6.3+/-1.0 9.2+/-1.2 3.7+/-0.9 5.9+/-1.0 3.9+/-0.4 6.4+/-0.6 7.5+/-0.7 2.9+/-0.3 5.7+/-0.6 <160 <140 <140 <160 <160 <1.4 1.9+/-1.1 <1.4 <1.4 <2.7 15+/-1 16:fl 16+/-2 14+/-1 16+/-1 13+/-1 17+/-2 12+/-1 13+/-1 15+/-2 <150 <140 <140 <160 <160 <1.5 1.3+/-0.8 <1.4 <1.3 <2.4 9.5+/-1.2 11+/-1 10+/-1 11+/-1 10+/-1 9.2+/-0.9 8.5+/-0.8 8.5+/-0.8 8.6+/-0.8 . 10+/-1 <160 <140 <150 <160 <160 1.4+/-0.9 10+/-10 11+/-10 12+/-7 10+/-10 11+/-10 8.7+/-9.1 11+/-11 9.3+/-4.7 8.2+/-10* 10+/-9 collected on ff2-17-88. collected on 04-12-88. available because the premises were unoccupied during AVERAGE 5.9+/-3.0 5.0+/-3.4 16+/-2 14+/-4 10+/-1 9.4+/-2.7 11+/-9 9.4+/-8.2 the

TABLE C-15 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE 01-11-88 02-16-88 03-14-88 04-11-88 05-16-88 06-13-88 SA-WWA-2S3 K-40 <39 <24 <31 <33 <26 <26 Ra-226 <5.4 9.1+/-2.6 7.4+/-2.7 6.7+/-2.7 9.4+/-2.5 <3.9 Th-232 <7.9 5.4+/-2.6 <5.7 8.2+/-3.6 <6.4 <3.8 SA-WWA-5Dl K-40 ( 1) 30+/-18 32+/-17 <27 <29 <31 Ra-226 (1) 130+/-6 46+/-4 58+/-4 52+/-4 38+/-4 ~ Th-232 ( 1) <9.4 <7.7 <7.8 <6.6 <7.9 SA-WWA-3El (C) K-40 <33 <45 <40 <44 <40 <39 Ra-226 98+/-5 90+/-6 35+/-4 100+/-6 51+/-4 42+/-4 Th-232 8.0+/-4.4 <11 <8.8 <10 <9.5 <8.9 AYE RAGE K-40 Ra-226 76+/-120 29+/-40 55+/-93 37+/-49 28+/-42 Th-232

TABLE C-15 (cont'd) 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE 07-11-88 08-15-88 09-12-88 10-11-88 11-07-88 12-12-88 AVERAGE SA-HHA-2S3 K-40 <33 <37 <30 38+/-21 <29 <29 Ra-226 <5.7 <4.7 4.0+/-2.3 22+/-3 <4.3 13+/-3 8.0+/-10 Th-232 <5.3 <5.4 <5.3 <6.1 <7.0 <6.2 SA-WWA-5Dl K-40 <34 <42 38+/-21 <42 <25 <37 Ra-226 39+/-4 14+/-3 160+/-7 130+/-6 14+/-3 56+/-4 67+/-99 U1 Th-232 <6.6 <10 <9.2 <10 <7.5 8.1+/-4.7 SA-HHA-3El (C) K-40 <40 <36 <37 <31 <32 <32 Ra-226 43+/-4 78+/-5 63+/-5 27+/-3 <4.6 62+/-4 58+/-59 Th-232 <8.5 <6.9 <9.0 <6.6 5.5+/-3.1 <6.0 A~ERAGE K-40 Ra-226 29+/-41 32+/-80 76+/-160 60+/-120 44+/-53 44+/-83 Th-232

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
  • Station SA-WWA-5Dl was collected on 02-17-88.
    • Station SA-WWA-5Dl was collected on 04-12-88.

( C) Control Station (1) January sample was not available because the premises were unoccupied during the entire month.

TABLE C-16 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF WELL WATER STATION ID NUCLIDE SA-WWA-2S3 Sr-89 Sr-90 SA-WwA-5Dl Sr-89 Sr-90 SA-WWA-3El (C) Sr-89 Sr-90 Results in Units of p~i/L 01-11-88 to 03-14-88 <1.6 <=0.9 <l. 0 ( 1) <0.6 <1.2 <0.7 04-11-88 to 06-13-88 <0.5 <0.3 <0.4 <0.2 <0.5 <0.3

• Sr-89 results are corrected for decay to sample stop date.
  • Station SA-WWA-5Dl was collected on 04-12-88.

(C) Control Station 07-11-88 to 09-12-88 <0.4 <0.3 <0.4 <0.3 <0.3 <0.3 (1) Quarterly composite consisted only of February and March samples. 10-11-88 to 12-12-8-S <0.6 <0.3 <0.5 <0.3 <0.4 <0.3 January sample was not available because the premises were unoccupied during the entire month.

TA*-.17 1988 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION ID: SA-PWR/T-2F3 Results in Units of pCi/L +/- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE Alpha (Raw) <1.6 2.2+/-1.4 <1.2 1.3+/-1.0 <1.4 1.2+/-0.9 (Treated) <1.6 <1.2 <1.2 1.2+/-1.0 <1.4 0.9+/-0.8 Beta (Raw) 3.4+/-0.8 4.4+/-0.9 4.5+/-0.9 4.8+/-0.9 4.3+/-0.8 4.1+/-0.8 (Treated) 3.4+/-0.8 3.8+/-0.9 3.3+/-0.8 3.8+/-0.9 3.6+/-0.8 3.0+/-0.8 K-40 (Raw) 0.9+/-0.l 2.0+/-0.2 2.3+/-0.2 2.0+/-0.2

1. 9+/-0. 2 2.0+/-0.2 (Treated) 0.8+/-0.l

1. 7+/-0. 2 2.0+/-0.2 2.1+/-0.2

1. 9+/-0. 2 2.0+/-0.2

.....J H-3 (Raw) <150 <150 <160 <140 <150 180+/-90 (Treated) <150 <150 <160 <140 <140 <140 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw)

1. 7+/-1.2

<1.0 <1.2 <1.1 <2.7 <2.6 (Treated) <1.2 <0.9 <1.3 <1.0 <2.6 1.4+/-1.0 Beta (Raw) 2.7+/-0.7 3.6+/-0.8 2.2+/-0.7 2.8+/-0.8 3.0+/-0.7 3.9+/-0.8 3.6+/-1.6 (Treated) 2.3+/-0.7 2.6+/-0.7 1.9+/-0.7 1.9+/-0.7 3.2+/-0.7 2.2+/-0.7 2.9+/-1.4 K-40 {Raw) 1.3+/-0.l . 1.9+/-0.2

1. 9+/-0. 2 1.4+/-0.1 2.4+/-Q.2 2.7+/-0.3 1.9+/-1.0

{Treated) 1.4+/-0.l 2.3+/-0.2 1.8+/-0.2 1.6+/-0.2 2.6+/-0.2 2.6+/-0.3 1.9+/-1.0 H-3 (Raw) <140 <140 <140 <150 <160 <170 (Treated) 190+/-90 <140 150+/-90 160+/-90 <150 <160

TABLE 18 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma 01-01-88 02-01-88 03-01-88 04-01-88 05-01-88 06-01-88 STATIOH ID to to to to to to NUCLIDE 01-31-88 02-29-88 03-31-88 04-30-88 05-31-88 06-30-88 SA-EHB-2E3 Mn-54 <1.4 <1.8 <2.0 <1.6 <1.3 <1.7 Ra-226 <4.2 <4.5 <4.8 <4.4 <4.0 <4.0 Th-232 <4.8 <7.b <7.6 10+/-4 <4.3 <7.4 SA-EH:I:-2E3 Mn-54 <1.5 <2.0 1.4+/-0. 7 <1.3 <2.1 <1.2 Ra-226 <4.2 <5.7 <3.9 5.9+/-2.4 <3.4 <4.1 Th-232 <7.6 8.5+/-4.5 <5.3 8.5+/-3.1 <7.6 <5.5 CD 07-01-88 08-01-88 09-01-88 10-01-88 11-01-88 12-01-88 STATIOH ID to. to to to to to NUCLIDE 07-31-88 08-31-88 09-30-88 10-31-88 11-30-88 12-31-88 SA-EHB-2E3 Mn-54 <1.5 <1.5 <4.2 <1.7 <1.5 <1.6 Ra-226 <3.9 <3.8 <8.2 <4.0 <4.1 <5.2 Th-232 <7.4 <8.6 14+/-6 <6.3 <7.2 <6.4 SA-EHT-2E3 Mn-54 <1.9 <1.8 <1.5 <1.5 <1.3 <1.4 Ra-226 <5.0 <4.2 <4.8 <4.9 <5.0 <4.5 Th-232 <8.4 <7.5 <5.8 <7.2 <5.9 <5.6

• All other gamma emitters searched for were <LLD~ typical LLDs are given in Table C-31 *

~ ~ \\D STATIQli ID NUCLIDE SA-EWR-2E3 (Raw) Sr-89 Sr-90 SA-PWT-2F3 (Treated) Sr-89 Sr-90 TABLE C-19 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF RAW AND T~EATED POTABLE WATER . Results in Units of pCi/L +/- 2 sigma 01-01-88 to 03-31-88 <1.2 <0.9 <1.0 0.9+/-0.3 04-01-88* to 06-30-88 <0.5 0.4+/-0.2 <0.5 <0.4 07-01-88 to 09-30-88 <0.8 <0.5 <0.8 <0.5

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

10-01-88 to 12-31-88 <0.6 <0.4 <0.7 <0.6

I\\.) 0 TABLE C-20 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION ID DATE SAMPLE TYPE K-40 Cs-137 Ra-226 Th-232 SA-FPV-3El 08-02-88 Corn 2200+/-170 <10 <23 <40 SA-FPV-3E2 05-09-88 Asparagus 2000+/-290 <28 67+/-37 140+/-62 SA-FPL-3E2 07-25-88 Cabbage 2800+/-270 20+/-11 <40 <68 SA-FPV-3E2 08-08-88 Peppers 1500+/-180 <13 <27 <56

• sA-FPL-llE3 07-26-88 Cabbage 2000+/-260

<22 39+/-21 <66 SA-FPL-1F3 07-25-88 Cabbage 1700+/-200 <17 <35 <60 SA-FPV-1F3 07-25-88 Peppers 1200+/-200 <15 37+/-17 <55 SA-FPV-1F3 07-25-88 Tomatoes 2000+/-44 1.3+/-0.6 <1.9 <4.4 SA-FPV-2F4 07-25-88 Corn 2300+/-220 <13 41+/-16 <50 SA-FPV-5Fl 07-25-88 Peppers 1600+/-210 <18 <32* <58 SA-FPV-14F3 07-25-88 Corn 2200+/-180 <30 <24 <52 SA-FPV-14F3 07-25-88 Tomatoes 1700+/-47 <1.6 <2.7 <5.2 SA-FPV-lGl (C) 07-25-88 Corn 2400+/-200 <12 60+/-16 <39 SA-FPV-lGl (C) 07-25-88 Peppers 1600+/-210 <13 <32 <42 SA-FPV-lGl ( C) 07-25-88 Tomatoes 2100+/-58 <1.3 <2.6 <7.2 SA-FPV-2Gl ( C) 05-10-88 Asparagus 1900+/-270 <24 <46 <72 SA-FPL-3H5 ( C) 08-01-88 Cabbage 1300+/-250 <19 <43 <65 SA-FPV-3H5 (C) 08:--01-88 Corn 2300+/-200 <11 <24 <48 SA-FPV-3H5 (C) 08-01-88 Peppers 1400+/-190 <12 <35 <44 SA-FPV-3H5 (C) 08-01-88 Tomatoes 1800+/-48 <1.6 <2.7 <5.1 AVERAGE 1900+/-820

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(C) Control Station

TABLE C-21 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN BEEF AND GAME STATION ID SA-FPB-3El SA-GAM-llDl (Control) SA-GAM-3El AVERAGE Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION DATE 01-18-88 02-07-88 02-06-88 SAMPLE TYPE Beef Muskrat Muskrat Beef Muskrat K-40 2400+/-200 2400+/-230 3000+/-250 2400+/-200 2700+/-850

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

121

I-' N N TABLE C-22 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION ID DATE SAMPLE TYPE Be-7 K-40 Ra-226 SA-VGT-3El 10-12-88 Soybeans <200 12000+/-560 <46 SA-VGT-2F7 09-18-88 Corn Silage 840+/-120 5500+/-370 54+/-24 SA-VGT-2F7 11-27-88 Soybeans. <320 13000+/-560 39+/-17 SA-VGT-11F3 09-01-88 Corn Silage 290+/-170 4900+/-480 <64 SA-VGT-11F3 11-08-88 Soybeans <170 16000+/-580 <42 SA-VGT-14Fl 09-06-88 Corn Silage 1100+/-150 3600+/-340 <42 SA-VGT-3Gl ( C) 09-18-88

• corn Silage 1100+/-220 4900+/-560

<94 SA-VGT-3Gl ( C) 10-30-88 Soybeans <200 15000+/-590 30+/-18 AVERAGE 9400+/-10000

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(C) Control Station

TABLE C-23 1988 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION ID 01-04-88 02-08-88 03-08-88 04-05-88 05-09-88 06-08-88 SA-SWA-llAl <1.6 <1.5 <1.4 <1.9 <1.8 <2.0 SA-SWA-12Cl <1.7 <1.5 <1.6 <2.0 <1.8 <2.1 (Control) SA-SWA-7El <1.5 <1.6 <1.2 <1.9 <1.7 <2.1 SA-SWA-1F2 <1.6 <1.5 <1.3 <1.6 <1.7 <2.0 SA-SWA-16Fl <1.6 <1.5 ~ <1.6 <1.7 <1.8 <2.0 w AVERAGE STATION ID 07-05-88 08-08-88 09-08-88 10-06-88 11-03-88 12-08-88 SA-SWA-llAl <1.7 . <1. 8 <1.4 <1.7 <2.8 <1.4 SA-SWA-12Cl <2.0 <2.1 <1.7 <1.9 <2.6 1.6+/-1.1 (Control) SA-SWA-7El <1.8 <1.5 <1.8 1.8+/-1.4 <2.5

1. 6+/-1.1 SA-SWA-1F2

<1.7 <1.6 <1.6 <1.6 <1.9 <1.3 SA-SWA-16Fl <1.8 <1.4 <1.4 <1.6 <1.9 1.6+/-1.1 AVERAGE

1. 5-+/-0. 3

TABLE C-24 1988 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units *Of pCi/L +/- 2 sigma STATION ID 01-04-88 02-08-88 03-08-88 04-05-88 05-09-88 06-08-88 SA-SWA-llAl 100+/-11 58+/-7 57+/-7 26+/-4 64+/-7 53+/-7 SA-SWA-12Cl 80+/-9 28+/-5 28+/-5 25+/-4 53+/-7 42+/-6 (Control) SA-SWA-7El 110+/-12 77+/-9 90+/-10 57+/-7 87+/-10 45+/-6 SA-SWA-1F2 46+/-6 16+/-4 20+/-4 13+/-3 32+/-5 43+/-6 SA-SWA-16Fl 53+/-7 7.3+/-2.9 N 19+/-4 13+/-3 35+/-6 37+/-5 ~ AVERAGE 78+/-56 37+/-59 43+/-61 27+/-36 54+/-45 44+/-12 STATION ID 07-05-88 08-08-88 09-08-88 10-06-88 11-03-88 12-08-88 AVERAGE SA-SWA-llAl 63+/-8 69+/-8 120+/-11 84+/-9 91+/-9 56+/-7 70+/-50 SA-SWA-12Cl 57+/-7 36+/-5 52+/-7 74+/-8 80+/-9 61+/-7 51+/-40 (Control) SA-SWA-7El 68+/-8 83+/-9 110+/-11 130+/-12 100+/-11 100+/-10 88+/-48 SA-SWA-1F2 44+/-6 22+/-4 49+/-6 38+/-6 43+/-6 42+/-6 34+/-26 SA-SWA-16Fl 50+/-6 22+/-4 42+/-6 52+/-7 24+/-4 39+/-5 33+/-31 AVERAGE 56+/-19 46+/-56 75+/-74 76+/-71 68+/-65 60+/-49 GRAND AVERAGE 55+/-58

• N 01 TA

-25 1988 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER STATION ID SA-SWA-llAl SA-SWA-12Cl (Control) SA-SWA-7El SA,...SWA-1F2 SA-SWA-16Fl AVERAGE Results in Units of pCi/L +/- 2 ~igma 01-04-88 to 03-08-88 1700+/-120 180+/-100 <150 150+/-90 <160 470+/-1400 04-05-88 to 06-08-88 <140 <140 <140 <140 <150 07-05-88 to 09-08-88 1300+/-100 180+/-80 170+/-90 <140 <150 390+/-1000 10-06-88 to 12-08-88 <150 <150 <160 <160 <160

TABLE C-26 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results 1n Units of pC1/L +/- 2 sigma STATION ID NUCLIDE 01-04-88 02-08-88 03-08-88 04-05-88 05-09-88 06-08-88 SA-SWA-llAl K-40 100+/-18 53+/-17 34+/-18 <44 57+/-19 82+/-20 Co-58

7. 6+/-1. 3

<2:0 <2.3 <2.3 ( 1. 8 ( 1. 8 Co-60 ( 1. 3 <2.0 <2.4 <2.6 <2.3 <2.1 Ra-226 5.8+/-2.6 <3.9 <5.0 <5.1 <4.2 <4.9 Th-232 6.8+/-3.2 <7.0 <7.7 <9.0 7.7+/-4.1 <7.1 SA-SWA-12C1 K-40 70+/-20 <35 <43. <30 <44 42+/-15 (Control) Co-58 <2.0 <2.2 <2.2 <3.0 <2.1 ( 1. 3 Co-60 <1. 9 <2.5 <2.0 <2.3 <2.2 < 1. 8 Ra-226 <4.6 <4.0 <5.4 <4.6 <5.4 <3.3 Th-232 6.7+/-3.6 <7.8 <7.9 6.5+/-3.7 8.2+/-4.4 <5.9 SA-SWA-7E1 K-40 110+/-23. 46+/-23 85+/-21 52+/-18 97+/-24 110+/-24 I\\) Co-58 <2.2 <2.0 <2.6 <1.6 <1.6 < 1. 8 O"I Co-60 < 1. 7 <2.4 <2.1 <2.6 <2.6 <2.3 Ra-226 <4.1 <5.1 <3.3 <4.1 <4.3 4.2+/-2.3 Th-232 <6.4 7.8+/-4.6 <7.7 <7.2 <7.1 <8.1 SA-SWA-1F2 K-40 57+/-16 <30 25+/-14 26+/-12 <35 39+/-18 Co-58 < 1. 7 ( 1. 9 < 1. 4 ( 1. 8 < 1. 8 < 1. 8 Co-60 <2.1 <2.2 < 1.1 < 1. 5 < 1. 6 <2.0 Ra-226 4.2+/-2.4 <4.5 <3.1 <3.0 <4.3 <5.3 Th-232 <8.3 <7.9 <5.0 <4.7 6.0+/-3.1 <1.1 SA-SWA-16F1 K-40 38+/-20 <24 <30 <34 48+/-16 47+/-22 Co-58 <2.0 < 1. 2 < 1. 6 < 1. 7 < 1. 7 < 1. 7 Co-60 <2.7 ( 1. 3 ( 1. 5 <2.0 ( 1. 7 ( 1. 7 Ra-226 <5.5 <3.8 <5.0 <5.0 <4.6 <4.9 Th-232 <6.6 7.6+/-2.6 <6.5 <7.2 <7. 0 <1.1 AVERAGE K-40 75+/-60 43+/-48 56+/-48 64+/-62

1988 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION ID NUCLIDE 07-05-88 08-08-88 09-08-88 10-06-88 11-03-88 12-08-88 AVERAGE SA-SWA-11A1 K-40 84+/-19 41+/-19 97+/-22 87+/-23 110+/-19. 50+/-21 70+/-52 Co-58 <1.6 ( 1. 5 ( 1. 7 < 1. 8 <4.1 <2.0 Co-60 <1.8 <2.1 <2.3 <3.1 <1. 6 <2.5 Ra-226 <4.8 <5.3 <4.8 <4.4 <4.0 4.4+/-2.6 Th-232 <5.2 6.2+/-3.6 <8.1 <7.9 <4.7 <7.3 SA-SWA-12Cl K-40 75+/-20 46+/-22 73+/-23 72+/-21 65+/-21 67+/-21 55+/-33 (Control) Co-58 <2.1 <2.1 <2.4 < 1. 9 <2.1 < 1.4 Co-60 < 1. 7 <2.2 <2.2 < 1. 9 3.0+/-1.3 < 1. 9 Ra-226 <S.O 4.4+/-2.6 5.9+/-2.8 <4.6 <5.1 <4.6 Th-232 6.0+/-3.5 <9.7 <8.0 <9.3 <5.6 <7.9 SA-SWA-7E1 K-40 110+/-22 90+/-18 120+/-21 110+/-21 90+/-21 85+/-21 92+/-46 ~ Co-58 ( 1. 8 < 1. 9 < 1. 6 <1.8 <2.1 <1.8 -..J Co-60 <1.8 <"1. 4 <2.2 <2.4 <2.3 <2.4 Ra-226 <5.3 3.8+/-1. 7 <4.6 <4.1 <4.8 <5.5 Th-232 <5.7 10+/-4 <7.0 <7.4 <8.1 <6.9 SA-SWA-1F2 K-40 36+/-20 3"9+/-21 47+/-18 38+/-18 34+/-15 <32 36+/-18 Co-58 <2.7 <1.8. <1. 9 <2.5 <1.8 <1.6 Co-60 <2.5 <2.1 ( 1. 9 <2.3 ( 1. 6 < 1. 7 Ra-226 <5.0 <3.5 <4.2 <5.1 <4.3 <4.6 Th-232 <7.9 <5.6 <7.7 <7.2 <5.8 <6.5 SA-SWA-16F1 K-40 50+/-23 <30 71+/-15 74+/-16 46+/-15 34+/-17 44+/-31 Co-58 <3.0 ( 1. 5 ( 1. 4 <1.6 <1.6 <1. 7 Co-60 <2.7 ( 1. 7 < 1. 4 ( 1. 5 < 1. 3 <2.6 Ra-226 7.8+/-2.7 <4.3 <"5. 2 <4.3 <3.3 <5.0 Th-232 <11 <8.7 <4.8 <5.7 <6.8 6.6+/-3.6 AVERAGE K-40 71+/-58 49+/-47 82+/-56 76+/-52 69+/-62 54+/-45 GRAND AVERAGE K-40 60+/-54

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

TABLE C-27 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 AND TRITIUM IN EDIBLE FISH STATION ID SA-ESF-llAl SA-ESF-12Cl (Control) SA-ESF-7El AVERAGE SAMPLING PERIOD 05-09-88 to 05-13-88 10-03-88 to 10-04-88 05-09-88 to 05-10-88 10-03-88 to 10-04-88 05-09-88 to 05-11-88 10-03-88 to 10-04-88 STRONTIUM (BONES) pCi/kg (dry) +/- 2 sigma Sr-89 Sr-90 100+/-39 <90 150+/-40 <40 110+/-34 <44 330+/-19 58+/-19 330+/-19 27+/-10 220+/-15 35+/-10 170+/-290

• Sr-89 results are corrected for decay to sample stop date.
  • Tritium results by Controls for Environmental Pollution, Inc.

TRITIUM (FLESH) AQUEOUS FRACTION pCi/kg (wet) +/- 2 sigma H-3 <50 <1000 <50 <1000 <50 <1000

'TABLE C-28 1988 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH STATION ID SA-ESF-llAl SA-ESF-12Cl (Control) SA-ESF-?El VE RAGE Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING PERIOD 05-09-88 to 05-13-88 10-03-88 to 10-04-88 05-09-88 to 05-10-88 10-03-88 to 10-04-88 05-09-88 to 05-11-88 10-03-88 to 10-04-88 K-40 2700+/-230 3400+/-270 2700+/-220 3200+/-250 3100+/-200 3100+/-230 3000+/-560 Th-232 <41 <46 <53 <58 35+/-20 <43

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

129

w 0 . TABLE C~29 1988 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90, GAMMA EMITTERS** AND TRITIUM IN BLUE CRABS Results in Units of pCi/kg (wet) +/- 2 sigma STATION ID SA-ECH-llAl SA-ECH-12Cl (Control) AVERAGE SAMPLING PERIOD 06/22-23/88 10/04-05/88 06/22-23/88 10/04-05/88 SAMPLE Flesh Shell Flesh Shell Flesh Shell Flesh Shell Flesh Shell (1) (1) ( 1) (1) Sr-89 Sr-90 <29 <17 41+/-12 220+/-14 <42 <23 <220 2800+/-120 <33 <20 45+/-13 190+/-15 <40 <22 92+/-39 360+/-33 100+/-170 890+/-2500

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

K-40 2100+/-210 (2) 2600+/-240 (2) 2400+/-180 (2) 2500+/-180 ( 2) 2400+/-430 Ra-226 35+/-16 (2) <30 ( 2) 30+/-16 (2) <23 (2)

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table c-31.
    • Tritium results by Controls for Environmental Pollution, Inc.

(1) Strontium results in units of pCi/kg (dry). (2) Gamma and tritium analyses not required

• TRITIUM (FLESH)

AQUEOUS FRACTION H-3 <50 (2) <1000 (2) 140+/-80 ( 2) <1000 (2)

T--30 1988 CONCENTRATIONS OF STRONTIUM~90 AND GAMMA EMITTERS* IN SEDIMENT Results in Units of pCi/kg (dry) 2 sigma srnrrnM IO DATE Sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 Zn-65 Sb-125 Cs-137 -Ra-226 Th-232 Sll-ESS-1 lAl 05-24-88 <12 <180 6300+/-360 24+/-11 <20 <23 <46 <39 < 17 310+/-28 430+/-56 10-24-88 <19 <120 3900+/-280 <18 < 17 69+/-11 <30 <36 <18 310+/-28 350+/-51 SA-ESS-15Al 05-24-88 <14 < 170 5200+/-330 <23 32+/-15 32+/-14 <36 <32 <20 380+/-31 430+/-58 10-24-88 <19 <170 8100+/-390 18+/-10 <20 29+/-11 <47 <57 <21 450+/-33 380+/-58 SA-ESS-l6Al w 05-24-88 <16 <300 4600+/-330 <34 <22 110+/-17 <54 90+/-48 <27 1200+/-56 1000+/-93 10-24-88 34+/-11 < 140 4300+/-270 42+/-13 <26 74+/-18 320+/-36 <53 <22 1100+/-45 830+/-68 SA-ESS-lZCl (Control) 05-24-88 <16 <220 16000+/-570 <23 <24 <30 <49 <41 <20 630+/-41 920+/-77 10-24-88 <19 <170 14000+/-440 <22 <21 <27 <40 <46 33+/-11 740+/-37 800+/-69 SA-ESS-ZEl 05-24-88 <13 <210 7900+/-470 <29 <26 45+/-20 <51 <44 <26 560+/-39 590+/-74 10-24-88 <18 <200 5800+/-420 <23 <29 33+/-20 <50 <48 <29 440+/-37 390+/-65 SA-ESS-l6El 05-24-88 <18 <320 15000+/-730 <43 <39 <55 <73 <100 <37 560+/-51 900+/-110 10-24-88 <21 280+/-120 14000+/-530 <24 <25 <38 <43 <54 <29 540+/-39 760+/-79 AVERAGE 8800+/-9300 47+/-52 600+/-570 650+/-490

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

TABLE C-31 1988 PSE&G RESEARCH AND TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY AIR WATER FOOD PRODUCTS BEEF AND PARTICULATES ALL TYPES MILK AND FODDER CROPS GAME NUCLIDES (l0-3pCi/m3 ) (pCi/L) (pCi/L) (pCi/kg-wet) (pCi/kg-wet) GEOMETRY: 13 Filters 3.5 Liter 3.5 Liter lOOml 400ml lOOml 400ml Be-7 14 14 8.0 120 37 92 Na-22 0.54 1.8 1.8 1.2 15 5.3 11 K-40 8.0 32 Cr-51 2.8 12 12 9.5 140 45 107 Mn-54 0.38 1.4 1.4 1.0 14 4.4 10 Co-58 0.39 1.6 1.6 0.99 15 4.5 11 Fe-59 0.83 3.2 3.2 2.4 32 10 24 Co-60 0.46 2.0. 2.0 1.1 16 5.0 11 Zn-65 0.86 3.3 3.3 2.0 31 9.0 22 I-' Nb-95 0.43

1. 7

1. 7 1.1 16 5.0 12 w

Zr-95 0.71 3.0 3.0 2.0 28 8.8 21 !\\.) ZrNb-95

o. 71 3.0 3.0 2.0 28 8.8 21 Mo-99 12 20 20 51 1300 370 2400 Ru-103 0.39 1.4 1.4 1.0 16 4.9 12 Ru-106 4.0 14 14 10 130 42 98 Ag-llOm 0.67 1.5 1.5 1.6 14 7.2 11 Sb-125 0.90 4.1 4.1 2.6 39 12 27 Te-129m 14 63 63 40 620 183 480 I-131 0.46 1.8 1.8 1.7 30 9.0 30 Te-132 0.89 2.1 2.1 3.9 99 26 170 Cs-134 0.51

1. 7

1. 7 1.3 13 5.7 9.3 Cs-136 0.49 1.9 1.9 1.3 22 6.4 20 Cs-137 0.35 1.7 1.7 1.0 17 4.4 12 Ba-140 1.6 6.2 6.2 5.0 82 25 71 La-140 0.73 2.3 2.3 2.2 32 11 28 BaLa-140 1.6 6.2 6.2 5.0 82 25 71 Ce-141 0.42 2.4 2.4 1.2 19 5.6 15 Ce-144 1.4 10 10 4.1 79 18 57 Ra-226 0.86 4.0 4.0 2.2 32 10 23 Th-232 1.7 6.8 6.8 3.8 54 17 40

TABLE C-31 (cont'd) 1988 PSE&G RESEARCH AND TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SEDIMENT AIR FISH SHELLFISH AND SOIL IODINE NU CL IDES (pCi/kg-wet) (pCi/kg-wet) (pCi/kg-dry) NUCLIDE (l0-3pCi/m3 ) GEOMETRY: lOOml 400ml lOOml 400ml lOOml lOOml Be-7 37 92 142 85 120 I-131 15 Na-22 5.3 11 21 10 14 K-40

It

It

~

It

It Cr-51 45 107 170 91 150 Mn-54 4.4 10 17 10 13 Co-58 4.5 11 18 10 14 Fe-59 10 24 41 22 36 Co-60 5.0 11 19 11 15 Zn-65 9.0 22 35 22 25 Nb-95 5.0 12 19 10 15 w

Zr-95 8.8 21 35 20 26 w ZrNb-95 8.8 21 35 20 26 Mo-99 370 2400 1200 530 13000 Ru-103 4.9 12 19 11 14 Ru-106 42 98 160 97 120 Ag-llOm 7.2 11 28 10 19 Sb-125 12 27 46 27 28 Te-129m 183 480 720 430 600 I-131 9.0 30 33 18 52 Te-132 26 170 85 49 650 Cs-134 5.7 9.3 22 9 12 Cs-136 6.4 20 24 14 31 Cs-137 4.4 12 17 12 12 Ba-140 25 71 94 51 105 La-140 11 28 41 .20 52 BaLa-140 25 71 94 51 105 Ce-141 5.6 15 22 13 17 Ce-144 18 _57 73 56 55 Ra-226 10 23 40 23 230 Th-232 17 40 69 40 48

• Indicates a positive concentration was measured in all samples analyzed.

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 135

I APPENDIX DI SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by the PSE&G Research and Testing Laboratory and contract laboratories for analyzing the 1988 Artificial Island Radiological Environmental Monitoring Program samples. LAB* PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G CEP PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G SE&G TABLE OF CONTENTS PROCEDURE DESCRIPTION GROSS ALPHA Analysis of Air Particulates **********.********* Analysis of Water................................ GROSS BETA Analysis of Air Particulates ****************.*** Analysis of Water *****************************.* POTASSIUM-40 Analysis of Water.......... Cl ********************. TRITIUM Analy~is of Water *** ~**************************** Analysis of Aqueous Fraction of Fish and Crab *** IODINE-131 Analysis of Filtered Air *****************, ******

• Analysis of Raw Milk ********************.**.****

STRONTIUM-89 AND STRONTIUM-90 Analysis of Air Particulates *****************.** Analysis of Raw Milk *****.*****************.**** Analysis of Water.. :............................ Analysis of Vegetation, Meat and Aquatic Samples Analysis of Bone and Shell ********************** Analysis of Soil and Sediment ************.****** Analysis -of Samples for Stable Strontium ******** 137 PAGE 139 141 142 144 145 146 147 148 149 150 153 156 159 162 165 168

SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd) TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates *.*.***..*.*.*...... 170 PSE&G Analysis of Raw Milk............................ 171 PSE&G Analysis of Water *** *********.*.******....*..... 172 PSE&G Analysis of Solids (combined procedures)...***.. 173 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters ***...** 174

• PSE&G -

PSE&G Research and Testing Laboratory CEP - Controls for Environmental Pollution, Inc. TI Teledyne Isotopes 138

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES After a11*owing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an 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, V = F*P*0.946*0.0283 E "Hg v = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure 32°F, "Hg F = Uncorrected air flow, ft 3 o.946.= Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= % efficiency/100) m3 v = corrected air flow, 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) at T = count time Of sample and blank, mins. E = Fractional Am-241 counting efficiency m3 v = Corrected air flow Of sample, 2.22 = No. of dpm per pCi 139

2-sigma error (pCi/m3) = (l.96*(G+B) 1/2)*A (G-B) Calculation of lower limit of detection: A = Gross alpha activity, pCi/m3 G Sample gross counts B = Background counts (from blank filter) 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) 140 B E v T = = = = Background counts (from blank filter) Fractional Am-241 counting efficiency Corrected air flow of sample, m3 Count time Of blank, mins.

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF WATER SAMPLES Water samples require pretreatment of all suspended material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample filtrate. The combined sample is then neutralized with dilute ammonium hydroxide. From this point, both. sample and blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to so 0c in order to help precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then filtered onto a membrane filter, dried under ~n 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 g~s 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: (pCi/L) = (G-B)/T (2.22)*(E)*(V)*(S) G = Sample gross counts B = Background counts (from blank sample) T = Count time of sample and blank E = Fractional counting efficiency from U-238 source v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = (l.96*(G+B) 112 )*A (~-B) 141 A = Gross alpha activity, pCi/L G = Sample

• gro*ss counts B = Background counts (from blank sample)

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an sr-90 air filter geometry beta counting standard. The gross beta activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. calculation of Gross Beta Activity: Air flow is corrected first by using the following equations.: P = (B-V)/29.92 P = Pressure correction factor B = Time-averaged barometric pressure during sampling period, "Hg v = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°F, "Hg V = F*P*0.946*0.0283 E F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= % .efficiency/100) V = corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows: Result (pCi/m3 ) = (G-B)/T (2.22)*(E)*(V) G = Sample gross counts B = Background counts (from blank filter) T = count time of sample and blank, mins. E = Fractional Sr-90 counting efficiency V = corrected air flow of sample, m3

• 2.22 = No. of dpm per pCi 142

2-sigma error {pCi/m3 ) (l.96*(G+B) 1/ 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)l/2 (2.22)*(E)*(V)*(T) 143 B E v T = = = = Background counts (frpm blank filter) Fractional Sr-90 counting efficiency Corrected air flow of sample, m3 Count time Of blank, mins.

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a l.O liter portion is removed from the potable, rain or well water container and 250ml taken from each surface water. A deionized water blank is prepared for each different volume of sample (e.g. l.O liter blank for l.O 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 regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2~sigrna error (pCi/L) = (1:96*(G+B) 112 )*A (G-B) 144 A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR POTASSIUM 40 A 60 ml aliquot of water sample (with the exception of rain water) received by the Research and Testing Laboratory is first acidified to pH <2 with con-centrated nitric acid and then analyzed for potassium by the following Atomic Absorption Spectrophotometry method: potassium standards of known concentra-tion (similar to that of the unknowns) are first prepared. An aliquot of each sample and standard is pipetted into stoppered flasks. In addition, a duplicate sample, ERA standard and blank water sample are likewise pipetted into their respective flasks. A solution consisting of 4% sodium is diluted 1:1 with water and then added to all the flasks. Depending on the A~ instrument used, a calibration curve is prepared from the standards after which the samples are then run. If the absorbance of any sample is higher than the upper_ standard used, the sample is then either diluted and re-run, the burner head turned 90°, a more concentrated standard added to the calibration curve or a less sensitive wavelength used. The results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program. calculation of K-40 Activity: K-40 AcUvity (pCi/L) = 0.85,.C 0.85 - Proportionality constant for converting ppm to pCi/L C = Potassium concentration, ppm 145

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately 50ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing Bml of sample, lOml of Instagel, and O.lml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Bml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted. Activity is computed as follows: A (pCi/L) = (G-B)*(lOOO) 2.22*(E)*(V)*(T) Efficiency (E) is computed as follows: E = (N)*(D) A' N is determined as follows: N = C-(G/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 N D A' = = = Net CPM of spiked sample Decay factor.of spike DPM of spike C = CPM of spiked sample G = Gross counts of sample T = count time (min) The associated error is expressed at 95% confidence limit, as follows: l.96*(G/T2+B/T2 )1/ 2*(1000) 2.22*(V)*(E) Samples are designated LLD if the activity is less than the following value: LLD (pCi/L) = (4.66)*(B) 1/ 2*(1000) 2.22*(V)*(E)*(T) 146

SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL POLLUTION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliquot of fish or crab flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation. Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear Corporation). The resultant mixture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approximately 30 percent, when counted on a Beckman LS-100 Liquid Scintillation Spectrometer. The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted. The counting efficiency is determined from these standards which are equal in activity but vary in the amount of quenching. All samples are counted for 500 minutes each

• 147

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF AIR IODINE Approximately 300m3 of air is drawn through a 50ml bed of triethylenediamine (TEDA)-impregnated charcoal granules at a rate which closely corresponds to the breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing 50ml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/m3 ) = 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 collection to start of

• acquisition

>.. = 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) 112*R N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/m3 ) = 4.66*(BC) 112*D (2.22)*(E)*(A)*(T)*(V) 148

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF RAW MILK FOR IODINE-131 Stable iodine carrier is equilibrated in a 4-liter volume of raw milk before two separate 50ml batches of anion exchange resin are introduced to extract iodine. After each batch has been stirred in the milk for an appropriate time, both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick. The can is hermetically sealed and then counted on a gamma detector. calculation of I-131 Activity: I-131 Results (pCi/L) = (G-B)/T*(l.05)*(H) (2.22)*(E)*(V)*(Y) G = Sample gross counts B = Background counts (from blank sample) T = Count time of sample and blank E = Eo*EXP(-A*M) = efficiency equation where Eo = counting efficiency at zero sample thickness A = Self-absorption coefficient M = Sample thickness, mg/cm2 V = Sample volume, liters Y = Chemical recovery = R Rl+R2 where R = mg of I recovered Rl = mg of I carrier added R2 = mg of intrinsic stable I measured in sample 1.05 = Correction factor for protein-bound iodine H = J/(1-K)*EXP(L) = correction J = R = factor for I-131 decay during counting period (0.693/8.05)*(R/l440) count time, minutes 1440 = No. of minutes per day Half-life of I-131, days EXP(-J) 8.05 K L N 149 = = = = (0.693/8.05)*N Elapsed time (days) from mid-point of collection period to beginning of count time.

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 ~wo 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 where S6 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.) M*= Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' =Ratio of sr-90 efficiency at thickness.value of 15mg/cm2 to sr-90 counting standard.efficiency *run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E = sr-90 counting standard efficiency (m3 )" v =.Sample quantity u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) Il = 1 - EXP ( (-0.693/2.667).*tl) I2 = 1 - EXP ((-0.693/2.667)*t2) to sr-90 only tl = Elapsed time from Y-90 strip to first count 150

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/m3 ) = 2*[(X+~) + (Xl+Yl~*Fl 2] 1f2 * (Wl*W2) Wl Wl j (N2-~l*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/m3 ) = 4.66*r(x+Y) + (Xl+Yl *Fl2 1/2. [ Wl~ Wl 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 normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.) N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) E(l5)/E' = Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) 151

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 ) SB = [cx+Y) + (Xl+Yl~*Fl 21112 [ w12 Wl ] S9 = (Xl+Y1) 1/ 2 2* (ss2+s92 )2 *W3 (Nl - N7*(l+Rl*Il)) All other variables are as previously defined. Keeping the same variable definitions, the LLD for Sr-89 (pCi/m3 ) = 4.66*(SB2+s92 )1/ 2 152

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 calcittm. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium preciP.- itation. Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip. The strontium is precipitated as its carbonate, filtered, dried and weighed to determine strontium recovery. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. Calculation of Sr-90 Activity: Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U) = W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band Care regression coefficients.) M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm~ 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) 153

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 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-sigrna error for Sr-90 (pCi/L) = 2* UX+Q) + (Xl+Yl~*Fl 2] 1/2 *. (Wl*W2} [w1 Wl J (N2-Fl*Nl) Again, keeping th.e same variable definitions, the LLD for sr-90 (pCi/L) ~ 4.66* [cx+2> + cx1+n~*F12]1/2 [ Wl Wl j calculation of Sr-89 Activity: Sr-89 Results {pCi/L) = N6/R. (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9) = W3 S7 = G + H*M + I*M2 (This is the general form of the normalized sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.) N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) 154

E(lS)/E' = Ratio of Sr-89 efficiency at thickness value of l5mg/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/L) = 2* (S82+s92)l/2 *W3 (Nl - N7*(l+Rl*Il)) S9 = (Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for Sr-89 (pCi/L) = 4.66*(S82+s92 )l/2 155

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank are then made alkaline and heated to near boiling before precipitating the carbonates. The carbonates are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The strontium is precipitated as a carbonate before being dried and weighed. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. Since surface waters, as well as some drinking water samples, have been found to contain significant amounts of stable strontium, a separate aliquot from each sample is analyzed for stable strontium. These results are used in correcting the chemical recovery of strontium to its true value. 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(l5)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency v = Sample quantity (liters) u = Chemical yield N4 = (N2 Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (l + Rl*Il)*Fl) Il = 1 - EXP ((-0.693/2.667)*tl) 156

12 1 - EXP ((-0.693/2.667}*t2} tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*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} = , 2* lix+Y} + (Xl+Yl~ *Fl 21112* (Wl*W2) [w12 Wl J (N2-Fl*Nl} Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L} = 4.66* UX+Y} + (Xl+Yl~*F1 2] 112 [ Wl 2 Wl ] calculation of Sr-89 Activity: Sr-89 Results (pCi/L} = N6/R (2.22}*(E}*(E(l5}/E'}*(S7}*(V}*(U}*(F9} = W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.} N6 = Nl - N7*(l + Rl*Il} N7 = (N2 - Fl*Nl}/Wl (This represents counts due to Sr-90) 157

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/L) = 2* (s82+s92)l/2 *W3 (Nl - N7*(l+Rl*Il)) SB = UX+Y) + (Xl+Yl~*Fl 2]1/2 L w12 w1 J S9 = (Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for Sr-89 {pCi/L) = 4.66*(ss2+s92 )112 158

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, before being placed in an oven to dry at l00°C. At the completion of the drying period, samples are again weighed (recorded as "dry" weight) and then pulverized. A measured amount (quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed in a muffle furnace. The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 900°C for 1/2 hour. After removal from the furnace, the melt is cooled, pulverized and added to 500ml distilled water and heated ta 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 (HN03). 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~9o Results (pCi/kg wet) = 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 regre*ssion equation for one particular gas proportional counter, where A, Band Care regression coefficients.) M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E = sr-90 counting standard efficiency v = Sample quantitY. (kg wet) u = Chemical yield N4 = (N2 Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 159

Il = 1 - EXP ((-0.693/2.667)*tl) I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*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 apm 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) = 2* [ex+~) + (Xl+Yl~ *Fl 2] 112* (Wl*W2) [w1 Wl ] (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for. sr-90 (pCi/kg wet) =

4. 66* ~ X+~) + (Xl+Yl ~*Fl 2]. 1/2 Wl Wl 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.) N6 = Nl - N7*(1 + Rl*Il) 160

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of l5mg/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 reaount 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* (ss2+s92 )1/ 2 *W3 (Nl - N7*(l+Rl*Il)) se = Ux+Y) + (Xl+Yl L Wl 2 Wl

• Fl2 1/2 S9 = (Xl+Yl)l/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg wet) = 4.66*(S82+s92 )1/ 2 161

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE AND SHELL The bone.or shell is first physically separated from the rest of the sample before being broken up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontium carrier and cesium holdback carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered. The sample is then treated with concentrated (70%) nitric acid and boiled until strontium nitrate crystallizes out. The strontium nitrate is freed of calcium by repeated fuming nitric acid recrystallizations. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide followed by coprecipitation with barium chromate. The strontium is precipitated as strontium carbonate, which is dried, weighed, then beta-counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous eq~ations 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(l5)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E = sr-90 counting standard efficiency v = Sample quantity (kg dry) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to sr-90 only 162

Wl = ((l + Rl*I2) - (l + Rl*Il)*Fl) Il = l - EXP ((-0.693/2.667)*tl) I2 = l - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count-t2 Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.) N2 = X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr~90 (pCi/kg dry) = Xl+Yl *Fl2 l/2* (Wl*W2) Wl (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kg dry) = 4.66* [cx+Y) + cxi+n~*F12]3:/2 l Wl2 Wl ] 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.) 163

N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of Sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/kg dry) = 2* (s82+s92 )1/ 2 *W3 (Nl - N7*(l+Rl*Il)) Xl+Yl *Fl2 l/2 Wl S9 = (Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg dr-y) = 4.66*(S82+s92 )112 164

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a 50gm aliquot is added to approximately 1/3 - liter concentrated. hydrochloric acid (HCl), containing 5ml of strontium carrier (lOmg sr++/ml). A blank con-taining only 1/3 - liter concentrated HCl and 5ml strontium carrier is run in parallel with the sample. The samples are stirred vigorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable strontium. The remaining sample is alkalinized with ammonium hydroxide to precipitate all the transitional elements. After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontium and calcium carbonate. These carbonates are first filtered and then digested with 6N 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(l5)/E' = ~atio 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) 165

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 dry) = 2* fcx+Y) + (Xl+Yl~*Fl 2] 1/2 * {Wl*W2) [w12 Wl J (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kg dry) = 4.66* UX+Y) + [w12 Xl+Yl *Fl2 l/2 Wl 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) 166

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) E(l5)/E' = Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of Sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/kg dry) = 2* (ss2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) SB=~+ [Wiz-Xl+Yl *Fl2 l/2 Wl 89 = (Xl+Yl) 1/ 2 All other_ variables are as previously oefined. Keeping the same variable definitions, the LLD for sr-89 (pCi/kg dry) = 4.66*(S82+s92 )1/ 2 167

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 analyz~d 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(s) of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdraw! 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. Absorbances for sample, spiked samples and blank are determined by Atomic Absorption Spectroscopy (AAS) and are then plotted graphically and the true concentration is then extrapolated. Chemical and ionization interferences are controlled by adding 1% or more of lanthanum as chloride to all samples to be analyzed. Stable strontium is then determined by AAS in the air-acetylene flame at the 460.7 nm line. For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH<2 with hydrochloric acid and analyzed by AAS as follows: A group of strontium standards (of similar concentration to the unknowns) is prepared. Then, to 9 ml of each prepared sample, blank and standard, is added 1 ml of lanthanum oxide solution. These are analyzed at 460.7 nm by air-acetylene* AAS, following the manufacturer's recommended instrument parameters. All results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil*and sediment~ and the quantity of strontium intrinsic to the sample *. Samp~e calculation of Corrected Chemical Recovery of Strontium in Soil and Sediment: Reported concentr~tion of stable strontium (mg/L):ll9 Volume of _specimen (ml):25 (removed from lOOOml of diluted leachat~) 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 0.025 168

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: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935) = 17.2mg Corrected chemical recovery of strontium= 17.2mg =.738 23.3mg 169

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 >..tl*EXP(>..t2) 1-EXP(->..tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition >.. = 0.693/nqclide half life E = Detector efficiency A = Gamma abundance factor (no. of T v 2.22 = = = photons per disintegration) Acquisition live time, mins. Sample volume, m3 No. of dpm per pCi 2-sigma error (pCi/m3 ) = l.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) 112*D (2.22)*(E)*(A)*(T)*(V) 170

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF RAW MILK A well mixed 3.5-11ter sample of raw milk is poured into a calibrated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative) *. After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V) 2-sigma error (pCi/L) N = Net counts under photopeak D = Decay correction factor A tl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration) T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi = 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)1/2.D (2.22)*(E)*(A)*(T)*(V) 171

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated Marinelli beaker and then counted on a gamma detector. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration) T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc) 112*R N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD {pCi/L) = 4.66*(BC) 1/ 2*D (2.22)*(E)*(A)*(T)*(V) 172

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF SOLIDS several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required. For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm3 ), whenever possible, in a tared aluminum can. The can is weighed and then hermetically sealed and counted on a gamma detector. In most cases, a wet sample is prepared (assuming sensitivity can be.met) by using a food processor to puree it. The sample is then poured into a cali-brated and tared clear plastic container until a standard volume is reached. The sample is weighed and then sealed with a screw cap before gamma counting. 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 and gamma 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 tl = t2 = >.. = E = A = T = v = >..tl*EXP(>..t2) J:-EXP ( ->..tl) Acquisition live time Elapsed time from sample collec-tion to start of acquisition 0.693/nuclide half life Detector efficiency Gamma abundance factor (no. of photons per disintegration) Acquisition live time, mins. 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) 173

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso4 :Dy phosphor. They are first annealed in a 25o 0 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 back-ground. The results are computed as follows: For any given area of the dosimeter, the dose in mR is calculated by the following formula: DOSE = R * (REDOSE/RR)-AVC R = Initial reading of the area RR = Second reading of the area (after re-irradiation) REDO SE = Re-irradiation dose, mR AVC = Average 4N where AVC = ~CDOSE/4N i=l of control values, mR N = Total number of control dosi-meters CDOSE = CR*(CREDOSE/CRR) CDOSE = Control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation) CREDOSE = Re-irradiation dose of the control dosimeter, mR 174

APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 175

I APPENDIX E I

SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the 1988 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program. TABLE NO. E-1 TABLE OF CONTENTS TABLE DESCRIPTION G:oss Al~ha and Gross Beta Emitters in Water and Air Particulates...... o ******* o ** o **** ID ********** PAGE 178 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products................................ 179 E-3 Tritium in Watero*************o*o**o************** 181 E-4 Iodine in Water and Milk *.**..*.*..**............ 182 E-5

• strontium-89 and Strontium-90 in Air Particulates,
• Milk, Water and Food Products ****.*..**..*.......

183 177

TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM DATE MM-YY 01-88 03-88 03-88 04-88 05-88 07-88 08-88 09-88 10-88 11-88 Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter) ENV SAMPLE CODE ENV ID MEDIUM ANALYSIS EPA-WAT-AB245 Water Alpha 88-246 Beta EPA-WAT-AB251 Water Alpha 88-246 Beta EPA-APT-GABS252 APT Alpha 88-1284 Beta EPA-WAT-P254 Water Alpha 88-1714 Beta EPA-WAT-AB256 88-1896 Water EPA-WAT-AB261 Water 88-2452 EPA-APT-GABS264 APT 88-2643 EPA-WAT-AB266 Water 88-2931 EPA-WAT-P269 Water 88-2981 EPA-WAT-AB271 Water 88-3343 Alpha Beta Alpha Beta Alpha Beta Alpha Beta Alpha Beta Alpha Beta PSE&G Mean +/- s.d. 4.1+/-0.6 9.1+/-0.4 5.9+/-0.5 13.3+/-1.0 23.7+/-0.8 52.9+/-1.5 40.8+/-1.3 60.7+/-2.2 8.5+/-0.1 13.4+/-0.8 15.6+/-1.4 5.6+/-0.4 10.7+/-0*.3 39.5~0.6 7.1+/-0.3 10.7+/-0.1 45.7+/-4.0 57.3+/-1.2 10.3+/-1.2 9.7+/-0.9 EPA Known 4+/-8.7 8+/-8.7 6+/-8.7 13+/-8.7 20+/-8.7 50+/-8.7 46+/-19.1 57+/-8.7 11+/-8.7 11+/-8. 7 15+/-8.7 4+/-8.7 8+/-8.7 29+/-8.7 8+/-8.7 10+/-8.7 41+/-17.3 54+/-8.7 9+/-8.7 9+/-8.7 GRAND AVG Mean +/- s.d. 3.87+/-1.6 8.30+/-2.1

5. 58+/-1. 7 12.90+/-2.2 22.6+/-4.7 53.3+/-6.0 44.8+/-12.3 57.8+/-6.3 9.40+/-2.6

11. 88+/-2. 2

.12.21+/-2.9

5. 73+/-1.9

8. 89+/-1. 8 28.7+/-3.5 7.58+/-2.0 10.45+/-2.2 39.0+/-9.3 50.4+/-5.9 8.83+/-2.4 9.66+/-2.3

• s.d. -

one standard deviation of three individual analytical results

• • known value with control limits, indicating whether results are in agreement or disagreement
    • s.d. -

one standard deviation of acceptable results of all participating laboratories 178

TABLE E-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM DATE MM-YY 01-88 02-88 03-88

• 4-88 06-88 06-88 07-88 08-88 Gamma Analysis of Milk, Water {pCi/L), Air Particulate

{pCi/filter) and Food Products (pCi/kg) ENV SAMPLE CODE ENV ID MEDIUM ANALYSIS EPA-ORG-GS246 88-466 Food I-131 Cs-137 K(l) EPA-WAT-G247 88-258 Water Co-60 EPA-APT-GABS252 APT 88-1284 EPA-WAT-P254 water 88-1714 EPA-MLK-GS260 Milk 88-2269 EPA-WAT-G257 water 88-2049 EPA-ORG-GS262 Food 88-2461 EPA-APT-GABS264 APT 88-2643 Zn-65 Ru-106 Cs-134 Cs-137 Cs-137 Co-60 Cs-134 Cs-137* I-131 Cs-137 K(l) Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 I-131 Cs-137 K(l) Cs-137 179 PSE&G Mean +/- s.d. 95.5+/-1.6 90.3+/-1.4 1220+/-21.0 70.8+/-2.1 98.5+/-4.5 107+/-7. 9 65.6+/-3.7 96.5+/-4.9 15.2+/-0.1 47.4+/-1.6 7.1+/-0.6 7.5+/-0.5 93.8+/-1. 8 53.0+/-0.7 1650+/-8.4 296+/-10 15.3+/-1.2 101+/-2.6 197+/-19 19.0+/-1.6 25.7+/-1.2 104+/-3.8 49+/-0.l 1190+/-20

11. 2+/-0. 4 EPA Known 102+/-17.7 91+/-8.7 1230+/-106 69+/-8.7 94+/-16.3 105+/-18.2 64+/-8.7 94+/-8.7 16+/-8.7 50+/-8.7 7+/-8.7 7+/-8.7 94+/-15.6 51+/-8.7 1600+/-140 302+/-52 15+/-8.7 101+/-17.3 195+/-34.6 20+/-8.7 25+/-8.7 107+/-19.1 49+/-8.7 1240+/-170 12+/-8.7 GRAND AVG Mean +/- s.d.

99+/-8 91+/-6 1218+/-122 69.3+/-5.1 96.1+/-7.3 99.6+/-12.7 60.7+/-5.0 94.2+/-6.3 17.7+/-3.0 50.8+/-4.0 7.2+/-1.6 8.0+/-1.6 96+/-8.9 51.9+/-3.6 1567+/-138 305+/-32 16.0+/-2.2 103+/-7 191+/-16 19.3+/-2.0 25.9+/-3.0 108+/-8 48+/-3 1225+/-50 12.6+/-2.7

TABLE E-2 (cont'd) USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM DATE MM-YY 10-88 10-88 10-88 Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (pCi/kg) ENV SAMPLE CODE PSE&G EPA ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known EPA-WAT-G267 water Cr-51 254+/-2.0 251+/-43.3 88-2392 Co-60 26+/-0.8 25+/-8.7 Zn-65 154+/-3.3 151+/-26 Ru-106 152+/-4.6 152+/-26 Cs-134 25.3+/-0.5 25+/-8.7 Cs-137 16+/-0.8 15+/-8.7 EPA-WAT-P269 water Cs-134 14.0+/-0.8 15+/-8.7 88-2981 Cs-137 15.7+/-0.5 15+/-8.7 EPA-MLK-GS270 Milk I-131 91.7+/-4.5 91+/-15.6 Cs-137

48. 7+/-1. 7 50+/-8.7 K(l) 1564+/-18 1600+/-139 GRAND AVG Mean +/- s.d.

234+/-24 25.5+/-2.4 152+/-9.2 144+/-18 24.0+/-2.2 15.8+/-2.3

14. 3+/-1. 7 15.7+/-1.7 90+/-8 50+/-4 1622+/-100

• s.d. -

one standard deviation of three individual analytical results

• • known value with control limits, indicating whether results are in agreement or disagreement.
    • s.d. -

one standard deviation of acceptable results of all participating laboratories (1) Reported as mg/L of Potassium. 180

TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritium Analysis of Water (pCi/L) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 02-88 EPA-WAT-H248 Water H-3 3727+/-82 3327+/-627 3358+/-338 88-787 06-88 EPA-WAT-H258 Water H-3 5760+/-54 5565+/-965 5394+/-50"5 88-2084 10-88 E~A-WAT-H268 Water H-3 2433+/-70 2316+/-606 2318+/-239 88-2980 s.d. - one standard deviation of three individual analytical. results known value with control limits, indicating whether results are in agreement or disagreement s.d. - one standard deviation of acceptable results of all participating laboratories 181

TABLE E-4 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 02-88 EPA-MLK-I249 Milk(l) I-131 3.7+/-0.2 4+/-0.7 4.2+/-0.9 88-788 04-88 EPA-WAT-I253 Water(l) I-131 7.7+/-0.3 8+/-1.3

7. 5+/-1. 2 88-1616 08-88 EPA-WAT-I263 Water I-131 64.6+/-0.5 76+/-14 77.3+/-7.6 88-2534 12-88 EPA-WAT-I272 Water I-131 110+/-0.5 115+/-21 116+/-15 88-3842

"' s.d. - one standard deviation of thr~e individual analytical results "'"' known value with control limits, indicating whether results are in agreement or disagreement "'"'"' s.d. - one standard deviation of acceptable results of all participating laboratories (1) Special EPA/NRC low level study 182

c TABLE E-5 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter), Milk, Water (pCi/L) and Food Products (pCi/kg)

t DATE MM-YY ENV SAMPLE CODE PSE&G ENV ID MEDIUM ANALYSIS Mean +/- s.d.

01-88 EPA-WAT-S244 Water 88-38 01-88 EPA-ORG-GS 246 88-466 Food 03-88 04-88 05...:.99 07-88 08-88 10-88 10-88 EPA-APT-GABS252 88-1284 EPA-WAT-P254 88-1714 EPA-WAT-S255 88-1895 APT Water Water EPA-MLK-GS260 Milk 88-2269 EPA-ORG-GS262 Food 88-2461 EPA-WAT-GABS264 APT 88-2643 EPA-MLK-GS270 88-3125 EPA-WAT-P269 88-2981 Milk Water Sr-89 sr-90 Sr-89 Sr-90 Sr-90 Sr-89 sr-90 Sr-89 Sr-90 Sr-89 Sr-90 sr-89 Sr-90 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 32.7+/-0.6 13.7+/-0.8 51.0+/-3.6 45.6+/-1.0 (1) 4.9+/-0.4 4.6+/-0.2 22.5+/-2.4 16.2+/-0.8 40.1+/-1.3 52.5+/-0.8

32. 6+/-1'. 8 28.3;1:0.5 7.0+/-0.6 (1)

(1) 9.3+/-0.9 9.3+/-0.5

t ;t EPA Known 30+/-8.7 15+/-2.6 46+/-8.7 55+/-4.8 5.0+/-8.7 5.0+/-2.6 20+/-8.7 20+/-2~6 41+/-8.7 60+/-5.2 33+/-8.7 34+/-3.5 8+/-2.6 11+/-8.7 10+/-2.6 GRAND AVG Mean +/- s.d.

27.8+/-5.6

14. 3+/-1.6 41.5+/-12.9 52.6+/-5.7 5.61+/-1.9 5.13+/-1.0 20.3+/-1.9 19.1+/-1.6 33.9+/-11.9 56.2+/-10.1 25.8+/-10.7

31. 4+/-5. 9

7. 8+/-1.6 9.9+/-2.8 95.+/-1.3

i s.d. -

one standard deviation of three individual analytical results

t;t known value with control limits, indicating whether results are in agreement or disagreement

i;t;t s.d. -

one standard deviation of acceptable results of all participating laboratories

1) Analysis cancelled by PSE&G.

183

APPENDIX F SYNOPSIS OF LAND USE CENSUS 185 I I

I APPENDIX FI SYNOPSIS OF 1988 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 (500ft2 ) producing broad leaf vegetation in each of the 16 meteorological sectors. Tabulated below are the results of these surveys: Meteorological Sector N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Milk Animal Aug., 1988 km (miles) None None None None None None None None None None None None 7*.8 (4.9) None None None 187 Nearest Residence Aug., 1988 km (miles) None 6.9 (4.3) 6.4 (4.0) 5.8 (3.6) 5.4 (3.4) None None None 6.6 (4.1) 5.5 (3.4) 6.9 (4.3) 7.1 (4.4) 6.5 (4.0) 5.5 (3.4) 5.9 (3.7) 6.8 (4.2) Vegetable Garden Aug., 1988 km (miles) None None None None None None None None None

• None None None None None None None}}