ML20151V811

1987 Annual Radiological Environ Operating Rept

ML20151V811
Person / Time
Site:	Salem, Hope Creek, 05000000
Issue date:	12/31/1987
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NLR-N88057, RTL-ENV-88-01, RTL-ENV-88-1, NUDOCS 8805030194
Download: ML20151V811 (184)

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IARTIFICIAL ISLAND = RADIOLOGICAL -

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.ENVI N ONMENTAL MONITORING PROGRAMS

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Salem = Generating 15tation, Unit 31: Docket No'.'50-272 -

e Salem. Generating' Station, Unit 2: Doct e t . Nra , 50-311.

it Hope.. Creek ! Generatiflg Station: l Dockret. No . 250-354 ..

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t1987. ANNUAL RdDIOLOGICAL ,

L ;E N V I R O N M E N T A L -? O P E R A T I N G R E P O R T

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a Prepared For PUBLIC SERVICE ELECTRIC AND GAS COMPANY By PSEGG RES! 4RCH CORPORATION

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ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL ~ MONITORING PROGRAM

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, 9 _I C ll d l[ 'c s NUCLEAR GENERATING STATIONS 1987 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31,1987 4

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h. ' TABLE OF CONTENTS PAGE L ,

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SUMMARY

..................................................... 1 INTRODUCTION................................................ 3

- Radiation Characteristics............................... 3 Radiation Effects....................................... 4 Sources of Radiation Exposure........................... ,4 Nuclear Power Reactors.................................. 7 Containment of Radioactivity.......................,..... 13 f Sources of Radioactive Liquid and Gaseous Effluents..... 16 Radioactivity Removal from Liquid and Gaseous Wastes.... 16 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM........... 19 Objectives.............................................. 20 Data Interpretation..................................... 21 Quality Assurance Program............................... 22 Program Changes......................................... 22 Results and Discussion.................................. 23 Atmospheric......................'................... 23 Direct Radiation.................................... 26 Terrestrial.... .................................... 27 Aquatic............................................. 32 Program Deviations...................................... 36 Conclusions............................................. 37 REFERENCES.................................................. 52 l

APPENDIX A - PROGRAM

SUMMARY

................................ 55 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS............... 67 l APPENDIX C - DATA TABLES.................................... 75 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES.............. 129 l

l l

l APPENDIX E -

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM l RESULTS........................................ 175 1

t l APPENDIX F - SYNOPSIS OF LAND USE CENSUS.................... 185 i

i

8 LIST OF TABLES n TABLE .

NUMBER TABLE DESCRIPTION PAGE

!! 1. Common Sources of Radiation..............'.......... 6

,. 4 "2. 1987 Artificial Island Radiological Environmental 4 i

Monitoring Program (Program Overview).............. 38 j

LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION PAGE ,

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1. BWR Vessel and Core................................, 9

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

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

4. Primary PWR Containment Cross-Section '

(Salem Units 1 & 2)................................ 14 l S. BWR Mark 1 Primary Containment Cross-Section  !

(Hope Creek)....................................... 15 1

! 6. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1987...........................'....... 42 6A. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, f 1983 through 1987.................................. 43 ii

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LIST OF FIGURES;(cont'd.)

FIGURE NUMBER FIGURE DESCRIPTION PAGE J

7. Average Ambient Radiation Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through 1987....................................... 44 7A, Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 -

through 1987....................................... 45

> 8. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1987,..................................... 46

• 8A. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 through 1987... 47

9. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1987............ 48 9A. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1987............ 49

10. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1987....................................... 50 10A. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1983 through 1987....................................... 51 3

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SUMMARY

During normal operations of a nuclear power generating station there are releases of small aucunts 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

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Radiological Effluent Release Report (RERR) which is published i* and submitted to the Nuclear Regulatory Commission on a semi-annual frequency.

The PSE&G Research Corporation, Research and Testing Laboratory  ;

(RTL) has been responsible for the collection and analysis of environmental samples during the period of January 1, 1987, ,

.through December 31, 1987, and the results are discussed in this report. The radioactive liquid and gaseous effluents due to the

, operation of SGS and HCGS during 1987 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  ;

L 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 t before Salem Unit 1 became operational. Samples of air particu- ,

.lates, air iodine, precipitation, milk, surface, ground and r l drinking water, vegetables, beef, game, fodder crops, fish,  !

crabs, and sediment were collected and analyzed. External l, radiation dose measurements were also made in the vicinity of t Artificial Island using thermoluminescent dosimeters.

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

iodine-131 (I-131), gross beta and gross alpha. The results of these analyses were used to assess the environmental impact of SGS and HCGS operatior.s, thereby demonstrating compliance with  ;

Technical Specifications (Section 3/4.11) and applicable Federal l and State regulations, and to verify the adequacy of radioactive i

effluent control systems. The results provided in this report are summarized below:

e There were a total of 2238 analyses on 1138 environmental samples during 1987. Direct radiation dose measurements were also made using 452 thermoluminescent dosimeters (TLDs).

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e In addition to the detection of natural occurring isotopes (i. e. Be-7, K-40, La-140, Ra-226, and.Th-232), low levels of Mn-54, Co-58, Co-60, Sr-90, Nb-95, Cs-134, Cs-136, and Cs-137 were also detected in various media. The detection of these radionuclides can be attributed to acmospheric weapons fallout, statistically positive results (within the lower limit of detection (LLD) range of the isotope but with a large cargin of error) or coincident sampling at the time a liquid effluent release was in progress.

All of these radionuclides were at concentrations well below Technical Specification reporting levels.

e Dose measurements made with TLDs at 41 locations around Artificial Island averaged between 60 and 70 millirads for 1987. This was comparable to the preoperational phase of the program which had an average of 55 millirads for 1973 to 1976.

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

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

Radioactive decay is measured in terms of "half-life". The half-life may be defined as the amount of time it takes for a radio-active material to decay to half of its original activity. The half-life of a radionuclide depends on the radionuclide and can range anywhere from a fraction of a second to as long as several million years. Each radionuclide also has a unique decay characteristic, both in terms of the energy of its radiation and the types of its radiation. Radionuclides may decay directly l into a stable element or go through a series of decays (becoming l several different radioisotopes) before eventually becoming a stable element, j 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 nillionth of a microcurie and represents 2.2 decays per minute.

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

? amount of radiation must be considered.

There are essentially two types of exposure to radiation:

external and internal. External exposure can involve the. total body, thereby implying exposure to all organs, or parts of the body, such as the arm, foot, or head. Internal exposure, meaning.

the uptake of radioactive elements by inhalation, ingestion, or by.means of a cut, can involve a single selective organ or several organs.

An example of the selectivity of internal exposure i' the uptake of a radiciodine which concentrates in the thyroid gland, versus the uptake of a radiocesium which will collect in the muscle and liver. The quantity of the radionuclide and duration of time a radionuclide remains in the body directly influences the total

' exposure or dose to an organ. The duration of time depends on the amount of radioactive decay and the length of time it takes to remove the radionuclide from the body (biological decay). It should be noted that the biological effect of radiation is independent of the source (internal or external) and dependent on the dose.

The measurement of dose to man is typically expressed in terms of a unit called the rem. As a better unit of dose, the millirem (mrem; 1 mrem =1/1000 rem) is most often used because the typical  ;

dose is usually on the order of thousandths of a rem. Another term used is the collective dose to a population, called a  !

person-rem. A person-rem is calculated by adding up each individual dose to a population (e.g. 0.0001 rem to each person of a population of 10,000 persons = 1 person-rem),

i

) SOURCES OF RADIATION EXPOSURE i

Radioactive elements have existed on our planet (and on every -

thing that has emerged from it) since its formation, including our own bodies. Every second over 7000 atoms undergo radioactive decay in the body of the average adult (or roughly 420,000 disintegrations per minute) from natural background.

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v4ay 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

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(K-40), uranium-238 (U-238), thorium-232 (Th-232), radium-226 (Ra-226), and radon-222 (Rn-222). Some of these radionuclides have half-lives of millions of years and are introduced into the water, soil, and air by such means as volcanoes, weathering, erosion, diffusion, and radioactive decay.

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

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

Since radon gas is radioactive, it, too, continues to produce, by decay, other radioactive materials referred to as radon daughters. These daughters are solid particles which can stick to surfaces such as dust particles in the air. The dust containing the radon daughter particles can be inhaled and deposited in the lungs. Radon daughters emit high energy alpha particles which results in an average dose to the lungs of 300 mrem (0.3 rem to a 10 year old) in the United States. In areas such as New Jersey and Pennsylvania, over a geologicL1 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), sodium-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 Tttle 1.

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TABLE l' 6

COMMON SOURCES oF RADIATION

• Approximate Approximate (

Pore Dose Natural Sources (cr em /vea r l Manmado Sources ( nrem /vea r l Cosmic Rays 42 Medical radiation 90 a Building Materials 35 Television and ,

Internal 28 consumer products 1-5 Ground 11 Weapons Fallout 2-1 #

Nuclear Power Plants 1 APPROXIMATE TOTAL 100 100

• Referenco: NUREG-0558 and EPA Report ORP/SID 72-1 The average individual in the United States receives approxi-mately 100 mrem per year from natural sources. In some areas the -l dose from natural radiaticn is significantly higher. Residents

'of Colorado receive an additional 80 mrem per year due to the increase in cosmic (higher elevation) and terrestrial radiation levels. Transcontinental and intercontinental airline pilots receive 1000 mrem /yr due to the high elevation and length of these flights and resultant higher cosmic radiation levels. In several locations around the world high concentrations of~ mineral 1 deposits give natural background radiation levels of several thousand mrem per year. l 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 l 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.

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There are approximately 200 radionuclides produced in the nuclear weapas 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 surface 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. China continues to test nuclear weapons above ground, the most recent of which occurred in 1982.

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4 NUCLEAR POWER REACTORS

' After World War II and during the development cf 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 (vent 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, e

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 reactio'n. The atom bomb, using large masses of fissionable material, is a chain reaction uncontrolled. Nuclear reactors, on the other hand, use small masses of fissionable material (thus making it impossible for a nuclear explosion), and are therefore able to sustain a controlled chain reaction.

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

Iodine 131 and Xenon 133). Fhen the fission occurs, some neutrons are released to initiate another fiasion 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.

2 7

1 .

r There are three major types of nuclear reactors in operation,in the world the pressurized light-water reactor (PWR), boiling f 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 l In a BWR the steam desired to generate simpler design.

electricity is produced in the core itself. Here, step by step,

)

is how the BWR works (refer to Figures 1 and 2):

1. Weter 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 '

I long. Sixty-two of these rods contain uranium fuel pellets.

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

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

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

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

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

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

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

The fission chain reaction is controlled by the 185 control rods located between the fuel assemblies. These control reds 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

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

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

1. Within the 424-ton reactor vessel at SGS, water flows across_193 fuel assemblies in the reactor core. Each -

assembly consists of 264 fuel rods, each about 15 feet long.

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

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

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

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

5. The exhausted steam from the tu'rbine is channcled 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 1ter drawn from a river, ocean, or lake (at SGS, this is the Delaware River).

About 65 percent of the nuclear power plants in the United States are PWRs and 36 percent are BWRs. The PUR is also used in nuclear submarines and other navel vessels.

11

FIGURE 3 SCHEMATIC OF PWR POWER Pl>NT 7.. ... ................ ...............

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

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

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

The next barrier level is the cooling watet which is circulated around the fuel rods. The fission and activation products (such es radiciodines, 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 th. fuel rods and coolant. The vessel and its coolant systems provide containment for all radionuclides in the coolant.

z 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 dryvell 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 dryvell (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),

1)

ELGURE 4 I

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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 fission products have a very low solubility in the primary coolant and therefore cannot be removed by the demineralizers.

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

Small releases of radioactive liquids from valves, piping, or equipment associated with the primary coolant system may occur in the reactor, auxiliary, and fuel handling buildings. The noble gases become part of the gaseous wastes, while the 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 vaste water. These represent the principal sources of liquid effluents.

RADIOACTIVITY REMOVAL FROM LIOUID 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 t r i t .um) 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-lcw-as-reasonably-achievable (ALARA).

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

j. o.

l 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 vaste 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

E o.

?

THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Artificial Island is the site of Salen 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 (8,9].

More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the

• nvironmental Reports (8,9), Environmental Statements (10,11],

and the Updated Final Safety Analysis Report for SGS (12] and the Final Safety Analysis Report for HCGS (13).

Since 1968, an off-site Radiological Environmental Monitoring Program (REMP) has been conducted at the Artificial Island Site.

Starting in December, 1972, more extensive rediological monitoring programs were initiated. The operational REMP was initiated in December, 1976, when Salem Unit 1 achieved criticality. The Research and Testing Laboratory (RTL), PSE&G Research Corporation, a wholly-owned subsidiary of Public Service Electric and Gas Company, 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 (1-3). On July 1, 1983, the RTL assumed prima *y responsibility for the analysis of all samples (except TLDs) anc 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 1966 are referenced in this report (4-7].

19

.c An overview of the 1987 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, 1987, for the Artificial Island Radiological Environmental Monitoring Program, l

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

e To fulfill the obligations of the Radiological Surveil- l lance sections of the Technical Specifications for the Salem Generating Station (SGS) and the Hope Creek Generating Station (HCGS).

e To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways, e To determine if SGS or HCGS has caused an increase in the radioactive inventory of long-lived radionuclides.

e To detect any change in ambient gamm" radiation levels, e To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on the environment.

This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.1.7 of the Hope Creek Technical Specifications, summarizes the findings of the 1987 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Artificial Island have been summarized for purposes of comparison with subsequent operational reports (2).

In order to meet the stated objectives, an appropriate 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.

20

O 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 evaluatcd 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 eatire operational program as performed in 1987.

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 11-2.

DATA INTERPRETATION Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix C. All results above the lower limit of detection (LLD) are at a confidence level of 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regula-tory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability, with only 5% probability of falsely concluding that a blank observa-tion represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count, or of the blank sample count, as appropriate.

The grouped data were averaged and standard deviations calcu-lated in accordance with Appendix B of Reference 18. Thus, the 2 sigma deviations of the averaged datn 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.

21

~ QUALITY ASSURANCE PROGRAM PSE&G Research Corporation, 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-chech analyses, and data review. The analytical methods utilized in this program are summarized in Appendix D. I The quality of the results obtained by the RTL is insured by the i implementation of the Quality Assurance Program as described in i the Environmental Division Quality Assurance Plan (20) and the l Environmental Division Procedures Manual (21]. The internal  !

quality control activity of the Laboratory includes the quality control of instrumentation, equipment and reagents; the use of '

reference utandards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked saraples. The external quality control activity is implemented through participation in the USEPA Laboratory Intercomparison Studies Program. These results are listed in Tables E-1 through E-5 in Appendix E.

PROGRAM CHAFCES The collection of benthic organism samples, ',*hich are not required by the Technical Specifications, was terminated from the Program as of January 1, 1987.

This action was taken due to the continuous unavailability of a sufficient sample to enable satisfactory gamma sensitivities to be achieved.

22

l ..

RESULTS AND DISCUSSION The analytical results of the 1987 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1907 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 raquired 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 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- t ethylene bottles. 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)

The weekly air particulate samples were analyzed for gross alpha and gross beta. Quarterly composites of the weekly sar..ples f rom each station were analyzed for specific gamma emitters and a single quarterly composite sample was analyzed for Sr-89 and Sr-90. Total data recovery for the eight sampling stations during 1987 was 99.6 percent.

Gross alpha emitter (Table C-1) concentrations were detected in 373 of the 416 weekly samples analyged. Ajphaconcentrations

, ranged from 0.8 x 10-3 to 6.3 x 10- pCi with the grand averageforallstationsbeing2.0x10fmpCi/m . 3 For 1987, 23

+

this average is comparable to the results obtained during the preoperational phase of the program. l Analysis of weekly air particulate samples for gross beta (Table ,

C-2) indicated concentrations were detected in 4143 of the 416 ~

samples ranging from 7.0 x 10-3 to 48 x 10-3 with the grand average for all stations being 9.4 x 10-gCi/m pCi/m,3 For

, 1987, this average is comparable to the results obtained during

the preoperational phase of the program.

Figure 6 indicates the relation between gross beta activity in air particulates and precipitation for the preoperational and operational periods, including the effects of atmospheric 4

veapons testing.

Results of gamma spectrometry indicated detectable levels of  !

Be-7 in'all to110x10-gfthe32monthlycomposites,rangingfromSgx10-3 pCi/m , with an average of 79 x 10-3 pCi/m .

i Bery111um-7 is a naturally-occurring radionuclide attributed to i cosmic ray activity in the atmosphere.

During chis reporting period results of gamma spectrometry clso  :

indicated detectable levels of K-40, La 140, Rp-226, and  !

Th-232. Potassium-40 was detected at 17 x 10 " 3 in one t l LLD sensitivities ranged from <4.7 x 10-gCi/mto <12 x 10-3 "

l sampig;in pCi/m the remaining samples., Lanthgnum-140 was detected in i the control station at 1.0 x 10- pCi LLD sensitivities i

ranged from <0.5 x 10-3 to<1.4x10fm; pCi/m Radigm-226 was

! also detected in only one sample at 1.4 x 10-3 pCi/m . The LLD i sensitivitjesforRa-226jnthegther31samplesrangedfrom

<0.6 x 10- to <8.0 x 10- pCi/m . Thorium-232 was detected in  ;

two sgmples from the same location at 1.1 x 10-3 and 1.3 x 10-3 ,

pCi/m . TheLLDsensitivjtiesfgrtheothersamplesrangedfrom

! <0.C x 10-3 to <2.5 x 10- pCi/m . The detectable values for l La-140, Ra-226 and Th-232 were all within the variations of -

4 their respective LLD sensitivities. All of these radionuclides

! are naturally occurring and were comparable to results obtained i during the preoperational phase of the program. ,

1 i l Strontfum-89 and Sr-90 analyses are no longer required by the ,

Technical Specifications for the Salem or Hope Creek Generating r Stations. In order to maintain documentation of the ambient lev s of Sr-89 and Sr-90 in the air surrounding the stations, stt . lum analyses are performed on the 1st quarterly sample from each location as a management audit sample. Strontium-89 and Sr-90 was not detected in any of the eight monthly  !

compositedsamplesanalyzed.TheLLDsensitjvitiesforSr-89and to <1.0 x 10- pCi/m and from i

Sr-90 ranggdtofrom <2.0<0.3 x 10-3 x 10-3 pCi/m 3

<0.2 x 10- respectively.

I r

I 24 i

4 i

t Air Iodine - (Table C-4 ) - )

Cartridges for'the adsorption of air iodine were conn'ected in series after'each of the air particulate filters. The

' adsorption medic in these cartridges'is.triethylenediamine (TEDA) impregnated charcoal. i Iodine-131resuits'werebelowdetectablelevelsinall416 .

samples analyzed. The samples  !

- rangedfrom<9.0x10-,LLDsensitivigiesfogtheweekl to <34 x 10- pCi/m . One-ind cator

• station had. shortened sampling periods during two consecutive i weeks due to the relocation of the sampling pole and power lines. Th and

<44x10-gsensigivitiesforthesetwoweekswere<57x10-3 pCi/m . The sensitivity of 70 x 10-ge valugs pCi/m were still below the minimum i

Precipitation (Tables C-6, C-7) t

.Although not required by the Technical Specifications, precipi-tation samples were collected at location 2F2 in the town of l

Salem. Monthly samples were analyzed for gross alpha, gross  ;

beta, tritium, and gamma emitters. Gross alpha concentrations 3 were, detected in two of the twelve samples at 0.9 and 1.8 pCi/L. ,

The LLD sensitivities for the remaining samples ranged from <0.6 ,

to <1.8 pCi/L. Beta activity was detected in all twelve monthly samples anc ranged from 1.7 to 12 pCi/L, with an average  !

3 of 4.7 pCi/L. Tritium was detected in one of the twelve samples t analyzad at 210 pC1/L; LLD sensitivities ranged from <140 to  !

<160 pci/L. Preoperational levels of H-3 detected averaged 216 [

pCi/L with a maximum detected concentration of 610 pCi/L. ]

Gamma analysis was performed on each of the monthly samples f

except for the August and October samples when there was insufficient precipitation. Detectable leve3s of the naturally i occurring gamma emitters of Be-7, K-40, Ra-226, and Th-232 were ,

found.

The presence of Be-7 was detected in each of the ten samples at concentrations ranging from 23 tc 83 pCi/L with an average of 55 l pCi/L. Potassium-40 was detected in two samples at a concentration of 42 and 74 pCi/L; LLD sensitivities for the i other samples ranged from <25 to <68 pCi/L A marginal level of  !

Ra-226 was detected in one sample at 4.8 pCi/L during the  !

3 September samplias period. However, this value was within the

< variations of the LLD sensitivities measured throughout the year for the other samples which ranged from <3.9 to <10 pCi/L.

' Thorium-232 was detected in two samples at concentrations of 6.2  :

and 8.9 pCi/L. This value is within the variations of the LLD j sensitivities for the other samples which ranged from <4.5 to

<14 pCi/L. Niobium-95 was also detected in one sample at a

. concentration of 3.8 pCi/L. This is within the variations of j l

i 25

~-w--, ,.,=<,.m. - , , , , , , - ---

" , g ---.,qe--, -ww . >- ~um n -m----- - , - - ,-,ww.y,~ .ew,

the LLD sensitivities fcr the other nine samples which ranged from <l.7 to <8.2'pCi/L. All other gamma emitters searched for were below the LLD.

DIRECT RADIATION Ambient radiation levels in the environs were measured with energy-compensated CaSO4 (Dy) thermoluminescent dosimeters (TLDs) supplied and read by Teledyne Isotopes. Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances.

Direct Radiation (Tables C-8, C-9)

A total of 41 locations were monitored for direct radiation during 1987, 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 and at 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. The average dose rate for the 15 monthly off-site indicator TLDs was 5.9 millirads per standard month, and the corresponding average '

control dose rate was 6.5 millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLDs was 5.0 millirads por standard month, and the average control rate was 5.5. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4.

In Figure 2, the average radiation levels are plotted for the 15 year period through 1987. Figure 2A shows the monthly averages of the off-site indicator stations and the control stations for 1982 thrcugh 1987. Ambient radiation levels during 1987 were comparable to those obtained during 1986 during the preoperational phase of the program.

26

e 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.

New two-gallon polyethylene containers were used for all vater samples.

Locally grown vegetable and fodder crops are collected once a year at time of harvest. Such samples are'veighed 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 bagn 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 carcases; are packed in plastic bags and kept chilled in ice  ;

chests during transport.

Milk (Tables C-10, C-ll, C-12)

Milk samples were collected in accordance with the Salem and Hope Creek Technical Specifications at six local dairy farms.

Samples were collected semi-monthly when cows were on pasture and monthly when cows were not on pasture. 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 120 samples analyzed.

Table C-10 lists the results and shows that LLD sensitivities ranged f rora <0.3 to <0.8 pCi/L. Figures 8 and 8A show the average I-131 activity measured during this year compared to results obtained in previous yetrs.

Gamma spectrometry showed detectable concentrations of naturally-occurring K-40 in all samples. The annual mean ,

concentration measured at the five indicator locations averaged 1300 pCi/L, and the annual mean concentration measured at the control location also averaged 1300 pCi/L. Radium-226 was 27

detected in five of the 100 indicator station samples at concentrations ranging from 5.9 to 8.5 pCi/L. No Ra-226 was detected at the twenty control station samples. The detected Ra-226 values are within the variations of the LLD sensitivities for the other samples which ranged from <4.4 to <9.6 pCi/L.

Thorium-232 was detected in three samples from one station ranging from 13 to 14 pCi/L; LLD sensitivities ranged from <2.7 to <18 pCi/L.

Manganese-54 was detected in one sample at 6.5 pCi/L; LLD sensitivities for all other samples ranged from <2.0 to <5.8 pCi/L. Cesium-134 was detected in two samples at a concentration of 4.1 and 4.9 pCi/L. These values are with5n the variations of the LLD sensitivities for the other samples which ranged from <2.1 to <5.6 pCi/L. Cesium-136 was detected in one sample at 3.1 pCi/L; LLD sensitivities ranged from <2.4 tu <5.3 pCi/L. Cesium-137 was detected in fifteen samples at concentrations which ranged from 2.3 to 6.7 pCi/L. Since the Cs-137 LLDs for all stations ranged from <2.1 to <5.0 pCi/L the positive results are not considered significant. Levels as high as 14 pCi/L vere detected during the preoperational program

[2]. Variations in the Cs-137 levels are attributed to atmospheric weapons testing of the past and the accident at the Chernobyl reactor in the Soviet Union.

All Sr-89 results were below detectable levels; LLD sensitiv-ities ranged from <l.0 to <2.6 pCi/L. Strontium-90 results were detected in five of the six locations at concentrations ranging from 1.7 to 4.1 pCi/L. The LLD sensitivity for the ore indicator location in which Sr-90 was not detected was <1.3 pCi/L. Preoperational levels for Sr-90 averaged 3.5 pCi/L with a maximum detected concentration of 12 pCi/L. Variations in the Sr-90 levels are attributed to atmospheric weapons testing of the past.

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

Although wells in the vicinity cf 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. Each sample was analyzed for gross alpha, gross beta, potassium-40, tritium and gamma l emitters. Quarterly composites were analyzed for l radiostrontium.

Gross alpha concentrations from 0.6 to 1.5 pCi/L were detected in six of +5e indicator station samples and one control station sample, 5he LLD sensitivities for the other samples analyzed ranged from <0.6 to <2.2 pC1/L. Gross The beta activity was mean activity for the I detected in all 36 samples analyzed.

indicator locations was 9.2 pCi/L with a range of 1.6 to 18 pCi/L; the mean activity for the control location was 9.2 pCi/L l l

• 26 1

l 1

with a range of 4.6 to 12 pCi/L. Potassium-40 in each monthly sample was determined by atomic absorption spectroscopy. The mean activity for the indicator locations was 9.3 pCi/L with a range of 2.9 to 14 pCi/L, and a mean activity for the control location was 9.1 pCi/L with a range of 7.4 to.10 pCi/L. All tritium results were at LLD levels ranging from <130 to <160 pCi/L.

Gamma spectrometry was performed on each sample. Potassium-40, Ra-226 and Th-232 were the only guame emitters detected.

Although not as sensitive as atomic absorption, K-40 was detected by ganana scan in ten samples at levels ranging from 21

, to 41 pCi/L. The LLD sensitivities for the other samples ranged from <22 to <46 pCi/L. Radium-226 was detected in twenty of the twenty-four indicator station samples and all twelve of the control station samples at values which ranged from a low of 3.7 pCi/L to n high of 200 pCi/L (control station). These values are similar to those found last year. However, as with the 1986 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 m1 standard geometry. This change results in less removal of radon (and its daughters) from the sample. Since Ra-226 is an alpha emitter, its identification by gamma isotopic analysis is obtained by counting the Pb-214 gamma rays from the daughter products. We believe that values currently being observed are indicative of the concentrations which have always existed. Concentrations of Th-232 were detected in two indicator station samples at 6.9 and 9.6 pCi/L; LLD values for the other thirty-four samples ranged from <4.9 to <10 pCi/L.

Neither Sr-89 nor Sr-90 was detected in any of the samples. The LLD sensitivities for Sr-89 ranged from <0.5 to <0.8 pCi/L, and from <C.4 to <0.7 pCi/L for Sr-90.

Potable Water (Tables C-17, C-18, C-19)

Both raw and treated 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 sample was analyzed for gross alpha, gross beta, K-40, tritium, and gamma emitters. Quarterly composites of raw and treated water were analyzed for Sr-89, Sr-90.

Detectable alpha activity was noted in three water samples at concentrations ranging from 0.8 to 1.0 pCi/L; LLD sensitivities ranged from <0.9 to <1.8 pCi/L (rew), al.d from <0.6 to <1.8 pCi/L (treated). Beta activity was observed in all of the 24 monthly samples, with ranges of 2.2 to 3.9 pCi/L (raw), and 1.7 to 3.1 pCi/L (treated), and averages of 3.1 pCi/L (raw) and 2.5 pCi/L (treated). Potassium-40 concentrations for raw and treated samples were similar but lower than the gross beta activity 29

.* l in all cases. The K-40 average for the raw and treated samples was 1.7 pCi/L in both cases. Tritium ectivity was not detected in any of the twenty-four samples analyzed; LLD sensitivities ranged from <130 to <170 pCi/L. These results are comparable to the results obtained in the preoperational phase of the program.

Gamma spectrometry detected K-10 in one sample at 31 pCi/L, with LLDs ranging from <20 to <43 pCi/L. Ra-226 was detected in three samples at concentrations ranging from 2.6 to 5.7 pCi/L.

The LLD sensitivities for the other twenty-one samples ranged -

from <3.9 to <5.8 pCi/L. Thorium-232 concentrations were detected in four samples ranging from 5.4 to 9.3 pCi/L with LLDs ranging from <4.5 to <9.6 pCi/L. All of these results are comparable to the results obtained in the preoperational phase of the program.

Strontium-89 was detected in one of the eight quarterly composite water samples at a concentration of 0.7 pCi/L; LLD sensitivities ranged from <0.7 to <l.3 pCi/L. Strontium-90 was not detected in any of the water samples and the LLDs ranged from <0.5 to <l.0 pCi/L.

Vegetables (Table C-20)

Although vegetables in the region are not irrigat d with water into shich liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled. These included asparagus, cabbage, sweet corn, peppers, and tomatoes.

All eighteen namples contained naturally-occurring K-40 at concentrations from 1600 to 2500 pCi/kg-wet, with an average for all sampics of 2000 pCi/kg-wet. Concentrations of Ra-226 were i detected in one indicator station sample at 2.7 pCi/kg-wet and two control station samples at 35 and 56 pCi/kg-vet. The LLD sensitivities for Ra-226 ranged from <2.6 to <45 pCi/kg-wet.

Thorium-232 was detected in one pepper sample at 66 pCi/kg-wet; LLD sensitivities for the other seventeen samples ranged from

<5.5 to <100 pCi/kg-wet. The results obtained were comparable to results obtained during the preoperational phase of the program.

• Beef (Table C-21)

Although not required by the SGS or HCGS Technical Specifi-cations, beef samples are collected, when available, twice a year ,

! and analyzed for gamma emitters. The second semi-annual beef sample was not obtained. Farmers, from whose animals the samples are normally obtained, did not slaughter from July through December 1987.

30

l e Analysis of the flesh for gamma emitters indicated the presence of naturally-occurring K-40 in the sample at a concentration of 2200 pCi/kg-wet. All other gamma emitters searched for were below LLD.

Game (Table C-21)

Since muskrats inhabit the marshlands surrounding the site, and since muskrats are consumed by local inhabitants, two muskrat samples were collected and analyzed for gamma emitters. Both samples were collected during the first two months of the year. ,

Gamma scans of the flesh indicated the presence of naturally-occurring K-40 in both samples at concentrations of 2100 and 2300 pCi/kg-wet. All other gamma emitters searched for were <

below LLD.

Fodder Crops (Table C-22)

Samples of crops normally used as cattle feed were collected at seven locations where these products may be a significant element in the food-chain pathway. Six of the locations from which samples were collected are milk sampling stations.

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

Beryllium-7, from the atmosphere, was found in eight of the t eleven samples at concentrations ranging from 160 to 1700 i pCi/kg-wet. LLD sensitivities for Be-7 ranged from <110 to <180 Potassium-40 was detected in all samples at pCi/kg-vet.

concentrations ranging from 2900 to 16000 pCi/kg-wet, with an  !

average of 7400 pCi/kg-wet. Cesium-137 was detected in one  ;

indicator station sample at a concentration of 21 pCi/kg-wet.

This is near or below the sensitivities for the other ten samples which ranged from <17 to <66 pCi/kg-vet. Radium-226 was detected in two indicator station samples at concentrations of 87 and 170 pCi/kg-wet. The LLD sensitivities for Ra-226 ranged from <36 to <67 pCi/kg-wet. Thorium-232 was detected in one .

sample at 83 pCi/kg-wet; LLD sensitivities ranged from <S9 to

<360 pCi/kg-wet. ,

l l

t i

31 T

i AQUATIC ,

t All aquatic samples were collected by V. J. Schuler Associates, 1 Inc., and delivered by pSE&G personnel. Surface water samples  !

vere collected in new containers which were rinsed twice with i the sample medium prior to collection. Edible fish and crabs were taken by net, and frozen in sealed polyethylene containers v

, befort being transported in ice chests. Sediment samplos were i taken with a bottom grab sampler and placed in sealed i polyethylene containers before being transported in ice chests.

Surface Water (Tables C-23, C-24, C-25, C-26)

Surface water samples were collected monthly at five locations in the Delaware estuary. One location is at the outfall area (which is the area where liquid effluents from the Salem Station are discharged into the Delaware River), another is downstream

from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two ,

upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river. Station 12C1, at the  :

mouth of the Appoquinimink River, serves as the operational  ?

control. All surface water samples were analyzed montnly for gross alpha and gross beta emitters, and gamme emitters. i Quarterly composites were analyzed for tritium.

Alpha concentrations were detected in five of the forty-eight '

indicator samples and in two of the twelve control samples, with ,

concentrations for all samples ranging from 0.9 to 1.7 pCi/L; LLD sensitivities ranged from <0.8 to <2.4 pCi/L. Beta concentrations for the indicator stations ranged from 5.4 to 140

) pCi/L, with an average of 55 pCi/L, and for the control station, from 9.3 to 69 pCi/L, with an average of 43 pCi/L. Nearly all of the beta activity was contributed by K-40, a natural component of salt and brackish waters, as illustrated in Figures 9 and 9A, which compares averaged gross beta and K-40 concentrations. The results obtained were comparable to results obtained during the preoperational phase of the program.

• l Gamma spectrometric analysis of surlace water samples showed detectable concentrations of K-40 in 38 of the 48 indicator i

l

station samples. The average K-40 concentration at the indicator stations was 69 pCi/L, with a range of 25 to 130 pCi/L. Average K-40 concentration at the control station, where t i detectable concentrations were found in nine of the twelve l samples, was; 58 pCi/L, with a range of 42 to 91 pCi/L. i Radium-226 was detected in eight indicator station samples, with [

values ranging from 4.0 to 18 pCi/L, and three control station ,

samples from 6.0 to 25 pCi/L. The Ra-226 LLDs ranged f 32

..-. -. -- _- - - _ _ _ . - J

o. j ,

l from <3.3 to <5.4 pCi/L. Radium-226 concentrations in this year's samples were comparable to those found last year.

Concentrations of Th-232 were detected in two indicator station 4

samples at 7.0 to 7.4 pCi/L and in one control sample at 9.5  !

, pCi/L. LLD sensitivities for Th-232 ranged from <4.5 to <10 pCi/L. Gamma spectrometric analysis of the surface water ,

samples also showed detectable concentrations of Co-58, Co-60 and Cs-134s Cobalt-58 and co-60 were each found in one of the January indicator station samples. The Co-58 concentration detected was 15 pCi/L; LLD sensitivities ranged from <1.0 to

<2.6 pCi/L. Cobalt-60 was detected at 7.4 pCi/L, with LLDs  :

ranging from <1.2 to <3.1 pCi/L. Cesium-134 was detected in 5 two samples at concentrations of 2.5 and 2.6 pCi/L; LLD sensitivities ranged from <1.1 to <2.7 pCi/L. The detection of Co-58, Co-60 and Cs-134 are attributed to sampling at tne outfnll area coincident to a liquid effluent release.

Tritium concentrations for the indicator stations ranged from 160 to 1400 pCi/L. The average of the five indicator samples with detectable levels of tritium was 450 pCi/L. Tritium was detected in two of the four control samples at concentrations of 150 and 160 pCi/L. The LLD sensitivities for the remaining '

samples ranged from <140 to <150 pCi/L. A reviev of Station Radioactive Effluent Release Reports indicates that all liquid discharges were below Technical Specification limits. Although '

surface water samples are not potable, the 1400 pCi/L tritium value, observed during the first quarter of 1987, was well below ,

the rep)orting

[14-15 . Levels level forofthe 20,000 yearspCi/L 1973 for drinking through water 1987 are samples plotted in '

Figure 10.

Fish (Tables C-27, C-28) i  !

Edible species of fish were collected semi-annually at three E locations and analyzed for tritium and gamma emitters (flesh) and for Sr-89 and Sr-90 (bones). Samples included bluefish, <

f channel catfish, weakfish, and white perch.

Gamma spectrometry of these samples indicated K-40 in all six samples at an avarage concentration of 2800 pCi/kg-wet, with a '

range of 2000 to 3400 pCi/kg-wet. One of the six samples had a l detectable concentration of Ra-226 at 27 pCi/kg-wet; LLD sensitivities for the other five samples ranged from <20 to <33

pCi/kg-wet.

Strontium-89 was not detected in any of the six bone samples

analyzed. The LLD sensitivities ranged from <26 to <45 pCi/kg-dry. Strontium-90 was detected in all six samples at concentrations ranging from 30 to 117 pCi/kg-dry, with an average of 62 pCi/kg-dry.  ;

, Tritium analyses were performed on the aqueous fraction of the  !

flesh portions of these samples. Two samples collected during '

i j 33

, -~ - . - - . -- --

m the second semi-aanual sampling period (Oct. 1987) had measurable amounts of tritium. The detectable levels vero found in one indicator station at 810'pCi/kg-vet and the control station at 400 pCi/kg-vet. The LLD sensitivity for all other samples was <50 pCi/kg-vet.

Blue Crab (Table C-29)

Blue crab samples were collected semi-annunlly at two locations, and the edible portions were analyzed for gamma emitters, Sr-89 and Sr-90, and tritium in the aqueous fraction. The shells were i also analyzed for Sr-89 and Sr-90.

Potassium-40 was detected in the flesh portion of all four j

samples. Potassium-40 levels ranged from 2300 to 2900 pCi/kg-vet, with an average of 2600 pCi/kg-Vet. The indicator

> station samole, collected during the second semi-annual sampling 1 period .(Oct". 1987), had measurable amounts of Ra-226 and Th-232.

Radium-226 was detected at 44 pCi/kg-vet; LLDs ranged from <24 i to <27 pCi/kg-vet. The Th-232 level detected was 53 pCi/kg-vet, with LLD sensitivities ranging from <29 to <60 pCi/kg-vet.

Strontium-89 was detected in one of the four flesh samples at 33 pCi/kg-vet, with LLD sensitivities ranging from <24 to <30 pCi/kg-vet. All four shell samples had detectable levels of Sr-89 ranging from 68 to 270 pCi/kg-dry (control station), with

.. an average value of 130 pCi/kg-dry. Similar concentrations were observed during the preoperational program [2].

Strontium-90 was not detected in any of the edible flesh portions of the blue crab samples. The LLD sensitivities for these samples ranged from <17 to <22 pCi/kg-vet for Sr-90. All four shell samples had detectable concentrations of Sr-90 '

ranging from 180 to 1000 pCi/kg-dry (control station), with an average of 460 pC1/kg-dry, Tritium activity was detected in the aqueous fraction of the  !

l '

J October indicator station sample at 620 pCi/kg-vet. The LLD sensitivity achieved in the remaining three samples was <50 pCi/kg-vet. Comparable concentrations were observed in previous l years,

e. i

Sediment (Table C-30)

Sediment samples were collected semi-annually from six locations r and analyzed for Sr-90 and gamma emitters. Strontium-90 was f i detected in one indicator station sample at 29 pCi/kg-dry. LLD [

t sensitivities for t.he other eleven samples ranged from <19 to f

<26 pCi/kg-dry. ,

i I

[

34

a.

Results of gamma spectrometry indicated the presence of naturally-occurring K-40 and Th-232 in all twelve samples, with averages of 9600 and 620 pCi/kg-dry, respectively. The range for detectable K-40 was from 2700 to 16000 pCi/ko-dry, while Th-232 was detected at levels from 350 to 970 pCl/kg-dry.

Concentrations of Ra-226 in nine samples ranged from 80 to 980 pct /kg-dry; LLD sensitivities ranged from <30 to <43 pCi/kg-dry. These positive results are attributed to decayed aquatic organisms in the sediment sample, which are capable of concentrating trace elements present in the water by detectable amounts.

Concentrations of the gamma emitters, Mn-54, Co-58, Co-60, and Cs-137 were also detected. Manganese-54 was detected in one sample at 24 pCi/kg-dry, with LLDs ranging from <13 to <27 pCi/kg-dry. Concentrations of Co-58 were detected in three samples, ranging from 23 to 60 pCi/kg-dry. Cobalt-58 LLD sensitivities for the remaining nine samples ranged from <20 to

<31 pCi/kg-dry. Concentrations of Co-60 were detected in eight samples, ranging from 26 to 75 pCi/kg-dry, with the average br ing 47 pCi/kg-dry. Cobalt-60 LLD sensitivities for the remaining four samples ranged from <20 to <38 pCi/kg-dry.

Cesium-137 concentrations were detected in four samples at levels ranging from 29 to 55 pCi/kg-dry, with LLDs ranging from

<l5 to <38 pCi/kg-dry.

l l

l i

l 35 l

.o PROGRAM DEVIATIONS Air particulate filter holder assembly from location SS1 sample, for the week beginning March 23, became faulty after sampling only 1.0 day out of a 7 day sampling week.

Vegetable (asparagus) gamma results from location 3E2 for the May 11 sample are unavailable due to loss of sample during analysis.

Air particulate / iodine sampler location 1F1 for the week beginning July 20 was operational for only 2.9 days out of a 7 day sampling week due to relocation of the sampling pole and power lines (at request of local resident).

Air particulate / iodine sampler location 1F1 for the week beginning July 27, was operational for only 4.0 days out of a 7 day sampling week due to continuation of work being performed to relocate the sampling pole and power lines (at request of local resident).

Precipitation gamma results from location 2F2 for the month of August are unavailable due to insufficient precipitation during the sampling period.

Precipitation gamma results from location 2F2 for the month of October are unavailable due to insufficient precipitation during the sampling period.

The second semi-annual beef sample was not obtained. Farmers, from whose animals the samples are normally obtained, did not slaughter from July through December, 1987.

l l

b l

l ,

l 36 l

CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial Island was conducted during 1987 in accordance with the SGS and HCGS Technical Specifications. The objectives of the program were .tet 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 comparabl.e to the results obtained during the preoperational phase of the program. Ambient radiaticn levels were relatively low, averaging 6.1 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.

i l

i l

l l

37 l

TABLE 2 1987 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPJLM RTATTON mnF COLLECTION MEDIUM INDICATOR CONTROL FRE(.'NCY TYPE / FREQUENCY

• OF ANALYSIS I. ATMOSPUERIC ENVIRONMENT

a. Air Particulate 2S2 SD1 16El 1F1 3H3 Weekly Gross alpha / weekly SS1 10D1 2F2 Gross beta / weekly Sr-89 & Sr-90/first quarterly"*

Gamma scan / quarterly g b. Air Iodine 2S2 SD1 16El 1F1 3H3 Weekly Iodine-131/ weekly 03 551 10D1 2F2

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

a. Thermoluminescent 2S2 SD1 2El 1F1 3G1 3H1 Monthly & Gamma dose / monthly Dosimeters SS1 10D1 3E1 2F2 3H3 Quarterly Gamma dose / quarterly 6S2 14D1 13E1 2F6 7S1 16El SFl lOS1 6F1 llS1 7F2 11F1 13F4 S

9

,,- - -w

~

a ',

TABLE 2 (cont'd) 1987 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RTA?inv ronF COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE / FREQUENCY

• OF ANALYSIS

a. Thermoluminescent 4D2 9El 2F5 1G3 Quarterly Gamma dose / quarterly Dosimetet s (cont'd) 11E2 3F2 10G1 12El 3F3 16G1 10F2 12F1 13F2 13F?

14F2 w 15F3 w

16F2 III. TERRESTRIAL ENVIRONMENT

a. Milk 13E3 2F7 3G1 Monthly Iodine-131/ monthly 5F2 (animals not Gamma scan / monthly llF3 on pasture) 14F1 Semi-monthly Iodine-131/ semi-monthly (animals on Gamma scan / semi-monthly pasture) Sr-89 & Sr-90/ July, first -

collection **

b. '4 ell 'Jater 2S3 SD1 JE1 Monthly Gross alpha / monthly Gross beta / monthly Potassium-40/ monthly Tritium / monthly Gamma scan / monthly Sr-89 & Sr-90/ quarterly

TABLE 2 (cont'd) 1987 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RTATTON conf COLLECTION MEDIUM INDICATOR CONTROL FREQUEMCY TYPE / FREQUENCY

• OF ANALYSIS

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

d. Vegetables 3El IF3 1G1 3HS c3 Annually Gamma scan /on collection 3E2 2F4 2G1 (at harvest)

SF1 14F3

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

f. Game 3El 11D1 Semi- Gamma scan /on collection (Muskrat) annually

g. Fodder Crops 3El 2F7 3G1 Annually Gamma scan /on collection 13E3 SF2 llF3 14F1

-. i

+.

TABLE 2 (cont'd) 1987 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM n?ATTov ronF COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE / FREQUENCY" OF ANALYSIS IV. AQUATIC ENVIRONMENT

a. Surface Water 11A1 7El IF2 12C1 Monthly Gross alpha / monthly 16F1 Gross beta / monthly Gamma scan /montbly Tritium / quarterly

. b. Edible Fish 11A1 7El 12Cl w

Semi- Tritium (flesh) annually Aqueous fraction /on collection Sr-89 & Sr-90 (bones)/on collection Gamma scan (flesh)/on collection

c. Blue Crabs 11A1 12Cl Semi- Tritium (flesh) annually Aqueous fraction /on collection Sr-89 & Sr-90 (shell)/on collection Sr-89 & Sr-90 (flerth)/on collection Gamma scan (flesh)/ca collection

d. Sediment llAl 7El 16F1 12Cl Semi- Sr-90/on collection 15A1 annually Gamma rean/on collection 16Al

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

Management audit analyses, not required by Technical Specifications or by specific commitments to local of ficials.

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g 1983 THROUGH 1987 4

e 5000 - - ---- --- - ------- ------- - - ---- - ---- -- - - --- -- - -- --- - -- - . * ---- -- - -- -- ----- -

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o I t i t t a f f f I t t t t I f f t I f f 1 3 1 I f i t t I 1 1 i i t t t I f f f e a i 1 1 t t t t t t t t I f f f t f 1983 1984 1985 1988 SEMB7

_ . ~ . _ - . . . _ .__ < .. . _ _ _

+ , .*

t b'" iD "

. j

,-. e i i

, a i

l REFERENCES (1) Radiation Management Corporation. "Artificia?. Island Radiological  !

i Environmental Monitoring Program - Annual Reports 1973 through 1982".

(2) Radiation Management Corporation. "Artificial Island Radiological i Environmental Monitoring Program - Preoperation Summary - 1973 through 1976". RMC-TR-77-03, 1978.

j (3) Radiation Management Corporation. "Artificial. Island Radiological L Environmental Monitoring Program - December 11 to December 31, 1976".

RMC-TR-77-02, 1977 t

(4) PSE&G Research Corporation Research and Testing Laboratory.

"Artificial Island Radjological Environmental Monitoring Program - 1983 ,

Annual Reportr. RTL-ENV-84-01, 1984.

j (5) PSE&G Research Corporation, Research and Testing Laboratory.

"Artificial Island Radiological Environtental Monitoring Program + 1984  :

. Annual Report". RTL-ENV-85-01, 1985. l i

[6] PSE&G Research Corporation, Research and Testing Laboratory. t "Artificial Island Radiological Environmental Monitoring Frogram - 1985 i

i i Annual Report". RTL-ENV-86-01, 1986.

i (7) PSE&G Research Corporation, Research and Testing Laboratory.

[*

"Artificial Island Radiological Environmental Monitoring Program - 1986  :

Annual Report", RTL-ENV-07-01, 1987. j (S) Public Service Electric and Gas Company. "Environmental Report,  !

i Operating License Stage - Salem Nuclear Generating Station Units 1 and l 2". 1971. J j

! (9) Public Service Electric and Gas Company. "Environmental Report, operating License Stage - Hope creek Generating Station". 1983. l

[

(10] United States Atomic Energy Commission. "Final Environmental 6tatement - ,

Salem Fuclear Generating Station, Unitt 1 and 2". Docket No. 50-272 and l i 50-311. 1973.

j (11] United States Atomic Energy Commission. "Final Environmental Statement -  ;

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

a i (12] Public Service Electric and Gas Company. "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1982.

I

.(13] Public Service Electric and Gas Company. "Final Safety Analysis Report -  !

Hope Creek Generating Station. 1984. l i

5

) ,

1 52 l

s s

e REFERENCES (cont'd) o (14] public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 1 - Technical Specifications", Appendix A to Operating License No. DPR-70, 1976, Sections 3/4.12 and 6.9.1.10 (Amendment 59 LL LL3).

[15] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix A to Operating

• License No. DPR-75, 1981, Sections 3/4.12 and 6.9.1.10 (Amendment 28 i ci 122).

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

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

[18) Public Service Electric and Gas Company. "Offsite Dose Calculation Manual" - Hope Creek Generating Station.

(19] U. S. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August, 1980. '

(20) PSE&G Research Corporation, Research and Testing Laboratory. "Environ-mental Division Quality Assurance Plan." November, 1986.

[21) PSE&G Research Corporation, Research and Testing Laboratory. "Environ-mental Division Procedures Manual." February, 1981.

[22) Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, SGS RERR-22 and RERR Salem Generating Statior. 1987.

(23] Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, HCGS RERR-3 and RERR Hope Creek Generating Statien. 1987.

[24) Anthony V Nero Jr., "A Guidebook to Nuclear Reactors", University of California Press, 1979.

[25] Eric J. Hr.11, "Radiation & Life", Pergamon Press, 1976.

[26] NCRP Report No. 93, "Ionizing Radiation Exposure of the Population of the United States", 1987, 1

'l L

53

C t

APPENDIX A i

PROGRAM

SUMMARY

55

~. . - _ _..

=.

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MCNITORING PROGRAM

SUMMARY

SALEM GENERATIkG STATION DOCKET N05. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1,1987 to DECEM3ER 31.1987 ANALYSIS AND LOWER NUwSER DF MED!t'M CR PATHWAY 1DTAL NUMBER LIMIT OF Att feTEATOP ferAff0Nt 10 RATION WITM Minursi prAN rey rE0f f " ATION N0nROUTINE SA"' LED OF ANALYSES CETECTION MEAN" NAME MEAN MEAN REPORTED (UNIT OF MEA $ltEEMENT) PERFORMED (LtD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENT $

Air Particulates Alpha 416 0.9 2.1 (324/364) 5D1 3.5 mt E (10'3 pct /m3 ) 2.6 '36/52) 1.9 (49/52) 0 (0.8-6.3) (1.3-6.3) (1.0-4.7)

Beta 416 -

24 (362/364) 501 3.5 mt E 25 (52/52) 23 (52/52) 0 (7.0-48) (13-40) (11-44)

Sr-89 8 0.3 <LLD -

<tLD <LLD 0

-J Sr-90 8 0.2 <tLD -

<tLD <tLD 0 Ganna Se-7 32 -

79 (28/28) 531 3.5 mt E 95 (4/4) 76 (4/4) 3 (56-110) (69-110) (66-94)

K-40 32 4.7 17 (1/28) 501 3.5 mi E 17 (1/4) <LLD 0 (17) (17)

La-140 28 0.5 <LLD 3H3 110 mi NE 1.0 (1/4) 1.J (1/4) 0 (1.0) (1.0)

Ra-226 32 0.6 1.4 (1/18) IF1 5.8 mi N 1.4 (1/4) <tLD 0 (1.4) 11.4)

Th-232 28 0.9 1.3 (2/24) 16El 4.1 mi kNW 1.3 (2/4) <((D 0 (1.1-1.5) (1.1-1.5)

Air Iodine 1-131 416 9.0 <tLD -

<tLD <LLD 0 (10'3 pct /m )

- - _ _ - _ - - - - - - - _ _ . _ = _ _ - ._ _ ~- __. .. - - - - . - . . - . . . . . _ _

l ARTIFICIAL ISLAND RADID10GICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

$ALEM GENERATING STATION DOCKET N05. 50-272/-311 HOPE CREEK GENERATING STATIDW DOCKET NO. 50-354 SALEM COUNTY. NEW JERSEY JANUARY 1,1981 to DECEMBER 31, 1987 i ANALYSIS AND LOWER NUMBER OF ME01UM OR PATHWAY TOTAL NUMBER LIMIT OF A! ! TN1TtAtcR 10CAff0M5 10cAff0M VffM HICuf5T prgy reqvpet terAffeg NCNROUTINE

SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS k

Precipitation Alpha 12 0.6 1.4 (2/12) 2F2 8.7 mi NNE 1.4 (2/12) No Control 0 (pC1/L1 ( 0. 9-1. 8 ) (0. 9- 1.8 ) Location Beta 12 1.0*** 4.7 (12/12) ZF2 8.7 mi NNE 4.7 (12/12) No Control 0 (1.7-1*) (1.7-12) location

. N-3 12 140 210 (1/12) ZF2 8.7 mi NNE 210 (1/12) No Control 0 (n (210) (210) Location m Gama Be-7 10 -

55 (10/10) ZF2 8.7 mi NNE 55 (10/10) No Control 0 j (23-83) (23-83) Location K-40 10 25 58 (2/10) 2F2 8.7 mi NNE SS (2/10) No Control 0 (42-74) (42-74) Location Nb-95 10 1.7 3.8 (1/10) 2F2 8.7 at NNE 3.8 (1/10) No Centrol c (3.9) (3.8) location Ra-226 10 3.9 4.8 (1/10) ZF2 8.7 mi NNE 4.8 (1/10) No Control 0 (4.8) (4.8) Location Th-232 10 4.5 7.6 (2/10) 2i2 8.7 mi NNE 7.6 (2/10) No Control 0 (6.2-8.9) (6.2-8.9) location Direct Radiation Gs,ma 288 -

6.1 (252/252) 751 0.1 at SE 7.1 (12/12) 6.5 (36/36) 0 (mrad /std. month) Dose (monthly) (4.0-9.8) (6.3-8.0) (5.5-7.1)

Gamma 164 -

5.1 (140/140) 751 0.1 mi SE 6.0 (4/4) 5.5 (24/24) 0 4 Dose (qtriy.) (3.2-6.7) (5.2-6.7) (4.5-6.7) 4 4

- - -- . . - - - -. - , . . , -- .w.w,.r, .--m .,e - - - <

.rr 4 , . . -- --.m.,- _-

m

+.

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRDNMENTAL MONITORING PROGRAM

SUMMARY

$aiEM GENERATING STATION DOCKET N05. 50-272/-311 HOPE CREEK CENERATING STATION DOCKET NO. 50-354 5ALEM COUNTY. NEW JERSEY JANUARY 1.1987 to DECEMBER 31. 1987 ANALYSIS AND LOWER WU% ER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF A11 TN"f cATOR t oCAf f 0Ns t oCAf f 04 Wifw prcurti uf AM CONT rot 10rAff04 kCNE00 TINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMtD (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (tANGE) MEASUREMEWT5 -

Milk I-131 120 0.3 <tLD -

<LLD <tLD 0 (pct /L)

$r-89 6 1.0 <LLD -

<tLD <LLD 0

$r-90 6 1.3 2.8 (8/5) 2F7 3.7 at NME 4.1 (1/1) 3.4 (1/1) 0

, (1.7-4.1) (4.1) (3.4) i so Garuna K-40 120 -

1300 (100/100) 13E3 4.9 mr W 1400 (20/20) 1300 (20/20) 0 (1200-1500) (1300-1500) (1200-1400)

Mn-54 120 2.0 6.5 (1/100) 14F1 5.5 at WNW 6.5 (1/20) <ttD 0 (6.5) (6.5)

Cs-134 120 2.1 4.5 (2/100) 14F1 5.5 mi WWW 4.9 (1/20) <tLD 0 (4.1-4.9) (4.9)

Cs-136 120 2.4 3.1 (1/1U0) 5F2 7.0 mi E 3.1 (1/20) <LLD 0 (3.1) (3.1)

Cs-137 120 2.1 4.0 (14/200) 5F2 7.0 mt E 4.7 (9/20) 2.7 (1/20) C (2.3-6.7) ( 3.4-6. 7 ) (2.7)

Ra-226 120 4.4 7.7 (5/100) 5F2 7.0 mi E 8.5 (1/20) <tLD 0 (5.9-8.5) (8.5)

Th-232 120 2.7 14 (3/100) 13E3 4.9 mt W 14 (3/20) <LLD 0 (13-14) (13-14)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MOWTTORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET N05. 50-272/-311 HOPE CREEK GEkERATING STATION DOCKET NO. 50-354 SALEM COUNTY. NEW JERIEY JANUARY 1.1987 to DECEMBER 31, 1987 ANALV515 AND LOWER NUMBER OF -

MEDIUM OR PATWWAY TOTAL NUMBER LIMIT OF Alt 14DfcATOR terAff0NS 10fATYOM WITH MICHFST WFAN CENTrot fefATICE NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUKEMENT) PERFORMED (LLD)* ( R ANGE ) DISTAME AND DIRECTION (RANGE) (RANGE) MEASURE 4EN TS Well Water Alpha 36 0.6 1.1 (6/24) 5D) 3.5 at E 1.3 (3/12) 0.8 (1/12) 0 (pct /L) (0.6-1.5) (1.1-1.5) (0.8)

Beta 36 1.0*** 9.2 (24/24) 501 3.5 at E 13 (12/12) 9.2 {12/12) 0 (1.6-18) (6.4-18) (4.8-12)

K-40 36 -

9.3 (24/24) 501 3.5 mi E 13 (12/12) 9.1 (12/12) O c) (2.9-14) (11-14) (7.4-10)

H-3 36 130 <LLD -

<tLD <LLD 0 Sr-89 12 0.5 <tLD -

<tLD <LLD 0 3r -90 12 0.4 <LLD -

<LLD <tLD 0 Gama K-40 36 22 32 (8/24) 501 3.5 mt E 33 (7/12) 28 (2/12) 0 (24-41) (24-41) (21-35)

Ra-226 36 4.6 38 (20/24) 3E1 4.1 at NE 82 (12/12) 82 (12/12) 0

, (3.7-120) (5.8-200) (5.8-200)

Th-232 36 4.9 8.2 (2/24) 253 700 ft NNE 8.2 (2/12) <LLD 0

( 6. 9-9. 6 ) (6.9-9.6)

Potable Water Alpha 24 0.6 0.9 (3/24) 2F3 6.0 mi hNE 0.9 (3/24) No Control 0 Raw-Treated ( 0. 8-1,0 ) ( 0. 8-1. 0 ) location (pts /L) Bett 24 1.0*** 2.8 (24/24) 2F3 8.0 mi NNE 2.8 (24/24) No Centro 1 0 (1.7-1.9) ( 1. 7-3.9 ) location K-40 24 -

1.7 (24/24) ZF3 8.0 mi NNE  !.7 (24/24) No Control 0 (1.3-2.4) ( 1. 3- 2. 4 ) location H-3 24 133 <tLD -

<tLD M9 Control 0 location -

e

• ARTIFICIAL ISLAND RADIOLDGICAL ENVIRONMENTAL MCNITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET N05. 50-272/-311 NOFE CREEK GENERATING STATION DOCKET NO. 50-354 5ALEM COUNTY NEW JERSEY JANUARY 1,1987 to DECEMBER 31, 1997 ANALYSIS AND LOWE R NUM3ER OF MEDIUM CR P/THWAY TOTAL NUMBER LIMIT OF Aff YN9f f 4fCP f or ATf 0Nt tetATf0N WifM HICHFt* MFAN CONT 90? terATf04 NONROUTINE SAMPLED OF AN/.Y$ES DETECTION MEAN** RAME MEAN MEAN PEPORTED (UNIT Of MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Potable Water cont'd Sr-89 8 0.7 0.7 (1/8) ZF3 8.0 mi NNE 0.7 (1/8) No Control 0 Raw-freated (0.7) (0.7) location (pct /L) Sr-90 8 0.5 <tLD <tLD No Control 0 Location m Gama os K-40 24 20 31 (1/24) ZF3 8.0 mi NME 31 (1/24) No Control 0 (31) (31) Location Ra-226 24 3.9 4.1 (3/24) 2F3 8.0 mi NNE 4.1 (3/24) No Control 0 (2.6-5.7) (2.6-5.7) Location Th-232 24 4.5 7.1 (4/24) 2F3 8.0 mi NNE 7.1 (4/24) No Control 0 (5.4-9.3) (5.4-9.3) location Fruit & Vegetables G amma (pCi/k g-wet ) K-40 18 -

2100 (10/10) 5F1 6.5 mi E 2300 (2/2) 2000 (8/8) 0 (1600-2500) (2100-2500) (1400-2400)

Ra-226 18 2.5 2.7 (1/10) 1G1 10.3 31 N 56 (1/3) 46 (2/8) 0 (2.7) (56) (35-56)

Th-232 18 5.5 66 (1/10) 5F1 6.5 mt E 66 (1/2) <LLD 0 (66) (66)

ARTIFICIAL ISLAND RADIOLOGICAL ENv1f 0NMENTAL MONITORING PROGRAM $UMMARY 5ALEM GEhfRATING STATION DOCAET kOS. 50-172/-311 HOPE CREEK GENERATING STATION DOCKET No. 50-354

$ALEM COUNTY. NEW JER$EV JANUARY 1.1987 to DECEMBER 31, 1987 NUM3ER OF ANALY$15 AND LOWER tecAYYON VffM MYCur$T wfAN CONYPO! !PCATION NONROUTIht MEDIUM OR PATFWAY TOTAL NUMBER LIMIT OF Att Y MO Y E AT E2 10 CAT TON $

NAME MEAN MEAN 2EPORTED

$AMPLED OF ANALYSES DETECTION MEAN**

(RANGE) (RANGE) MEASUREMEN TS PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTIDN (UNIT OF MEASUREMENT)

Beef Gammt 3E1 4.1 at NE 2200 (1/1) No Control 0 (pct /kg-wet) K-40 1 -

2200 (1/1)

(2200) location (2200)

$ Game G aarna 3E1 4.1 et NE 2300 (1/1) 2100 (1/1) 0 (ptt/kg-wet) K-40 2 - 2300 (1/1)

(2300) (2300) (2100)

Fodder Crops Gamma Be-7 11 110 560 (7/9) 13E3 4.9 at W 1700 (1/1) 410 (1/2) 0 (ptilkg-wet)

(160-1700) (1700) (410) 3E1 4.1 mi NE 11000 (1/1) 11000 (2/2) 0 K-40 11 -

6700 (9/9)

(2900-14000) (11000) (5100-16000) 3G1 17 mt NE 11000 (2/2)

(5100-16000)

ZF7 5.7 mi NNE 21 (1/2) <LLD 0 Cs-137 11 17 21 (1/9)

(21) (21) 13E3 4.9 mi W 170 (1/1) <tLD 0 Ra-226 11 36 130 (2/9)

(87-170) (170) 3E1 4.1 mi NE 83 (1/1) <tLD 0 Th-232 11 59 83 (1/9)

(83) (83) e 9 *

- - - . . _ . . - . . . . _ _. __ ~. -- _

_ __ - _ _ _ _ . - ___ - .=. _ _ _ . _ _ _ _ _ . _ _ _ _ _ -. _.. -_

- _ ____._______m_.

_ _ . _ . - . _ _ . . .m ____. .

e e

i ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONNENTAL N0 NIT 0 TING PEOGRAst SteutARY i

5ALEN GENERATING STATION DOCKET N05. 50-2T2/-311 NOPE CREEK GENERATING STATIO!! DCCKET NO. 50-354 5ALEN COUNTY. NEW JER$EY JANUARY 1. 1987 to DECEMBER 31, 1987 ANALYSIS AND LOWER NUISER OF IIEDIUM OF PATHWf.Y TOTAL NUMBER LIMIT OF Aff IMD?tATOR 1OfAffatit 10EAffott Wf TM MirWST sarim C0glitc1 tQt_ATIDRI NON00UTINE I

SAMPLED OF ANALY5ES DETECTION IIEAN" NAfIE MEAN MEM REPCGTED (UNIT Of leEASUREleENT) PERFORNED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) teEASUREMENTS (RANGE)

Surface Water Alpha 60 0.8 1.2 (5/48) 12C1 2.5 at W5W 1.6 (2/12) 1.6 (2/12) 0 _

(pC9/L) (0.9-1.4) 5 (1.6-1.7) (1.6-1.7)

Beta 60 3.d"* 55 (48/48) 7El 4.5 at SE 85 (12/12) 43 (12/12) 0 1

(5.4-140) (17-140) (9.3-69)

H-3 20 140 450 (5/16) 11A1 0.2 mi SW 630 (3/4) 160 (2/4) 0 w (160-1400) (180-1400) (150-160)

Ganma 1 K-40 60 26 69 (38/48) TE1 4.5 al SE 94 (10/12) 58 (9/12) 0 (25-130) (61-130) (42-91)

Co-58 60 1.0 15 (1/48) 11A1 0.2 mt SW 15 (1/12) <tLD 0 (15) (15)

Co-60 60 1.2 7.4 (1/48) 11A1 0.2 at SW 7.4 (1/12) <LLD 0 (7.4) (7.4)

Cs-134 60 1.1 2.6 (2/48) 11A1 0.2 at SW 2.6 (1/12) <tLD 0 (2.5-2.6) (2.6)

Ra-226 60 3.3 9.3 (8/48) 12C1 2.5 mt WSW 18 (3/12) 18 (3/12) 0 l (4.0-18 ) (6.0-25 ) (6.0-25) 3 Th-232 60 4.5 7.2 (2/48) 12C1 2.5 91 W5W 9.5 (1/12) 9.5 (1/12) 0

) ( 7.0-7.4 ) (9.5) (9.5 )

i i ,

i i

i 1

ARTIFTCIAL IstAND RADIOLOGICAL ENVIDONMENTAL MONITORING PROGRAM

SUMMARY

5ALEM GENERATING STATION DOCKET N05. 50-2721-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 5ALEM COUNTY. HEW JER5EY JANUARY 1. 1987 to DECEMBER 31. 1937 ANALYSIS AND LOWER WUw3ER OF MEDIUM CR PATHWAY TOTAL NUMBER ^ LIMIT OF Att TNSYEATC9 10EATicNt 19CATYEN hifM MirursT wrAN regTPct 10tATYEM NON200 TINE SAMPt[D OF ANALY5ES DETECTION MEAN** NAME MEAD ME.*J REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTAMCE AND DIRECilDN (RAEGE ) (RANGE) MEASUREMIhT5 Edible Ftsh Sr-89 6 26 <tLD -

<lLD <ttD 0 (ptt/kg-dry) (bones)

Sr-90 6 -

54 (4/4) 12C1 2.5 at W5W 78 (2/2) 78 (2/2) 0 (bones) (30-117) (46-110) (46-110) g (pC t /k g-wet ) H-1 6 50 810 (1/4) 11A1 0.2 at SW 810 (1/2) 450 (1/2) 0 4 (aqueous) (810) '10 ) (450)

Gamma K-40 6 2900 (4/4) 11A1 0.2 at SW ' - '2/2) 2700 (2/2) 0 (2700-3000) ,Jr e-3000) (2000-3400)

Ra-226 6 20 27 (1/4) 11A1 0.2 mi SW 27 (1/2) <ttD C (27) (27) i e 9

1 4

?

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRO 1 MENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HO?E CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNT /. NEW JERSEY JANUARY 1, 1987 to DECEMBER 31. 1987 ANALYS15 AND LOWER NUMBE OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF Att TNDICATOR 10CATf0NS tOSATYON WTTH HICHFST MFAN CONT 901 10 CATION' NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME- MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEA $lrdMENTS

Blue Crabs Sr-89 4 -

80 (2/2) 12C1 2.5 mi WSW 170 (2/2) 170 (2/2) 0 (pCilk g-dry) (shells) (68-93) (74-270) (74-270) j Sr-90 4 -

300 (2/2) 12C1 2.5 mi WSW

' 620 (2/2) 620 (2/2) 0 (shells) (180-420) (250-1000) (250-1000)

(pC1/k g-wet ) H-3 4 50

' 620 (1/2) 11A1 0.2 mi SW 620 (1/2) <LLD 0

OS (aqueous) (620) (620)

Sr-89 4 24 33 (1/2) 11A1 0.2 mi SW 33 (1/2) <LLD 0 (flesh) (33) (33)

! Sr-90 4 17 <ltD -

<LLD <tLD 0 (flesh)

Gamma K-40 4 -

2500 (2/2) 12C1 2.5 mi WSW 2700 (2/2)' 2700 (2/2) 0 (2300-2700) (2500-2900) (2500-2900)

Ra-226 4 24 44 (1/2) 11A1 0.2 mi SW 44 (1/2) <LLD 0 (44) (44)

Th-232 4 29 53 (1/2) 11A1 0.2 mi SW 53 (1/2). <LLD 0 (53) (53) 1 I

i

?

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MCNITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1987 to DECEMBER 31, 1987 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF All INDICATOR f0 CATIONS ?0 CATION WITH HIG4FSF MFAN CONTR0! 10 CATION 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 19 29 (1/10) 16Al 0.7 mi NNW 29 (1/2) <LLD 0 (pci/kg-dry) (29) (29)

Genma K-40 12 -

8700 (10/10) 16F1 6.9 mi NNW 15000 (2/2) 14000 (2/2) 0 (2700-16000) (14000-16000) (12000-16000)

Mn-54 12 13 24 (1/10) 16F1 6.9 mi NNW 24 (1/2) <LLD 0 CQ (24) (24)

Co-58 12 20 40 (3/10) 15A1 0.3 mi NW 60 (1/2) <tLD 0 (23-60) (60)

Co-60 12 20 47 (8/10) 7El 4.5 mi SE 56 (2/2) <LLD 0 (26-75) (36-75)

Cs-137 12 15 39 (3/10) 12C1 2.5 mi WSW 52 (1/2) 52 (1/2) 0 (29-55) (52) (52)

Ra-226 12 30 500 (7/10) 16Al 0.? 04 NrW 930 (1/2) 640 (2/2) 0 (80-980) (980) (570-700)

Th-232 12 -

600 (10/10) 16F1 6.9 mi NNW 930 (2/2) 720 (2/2) 0 (350-970) (890-970) (570-880)

• LLD listed is the lowest calculated LLD during the reporting period.

=* Mean calculated using valu s above LLD only. Fraction of measurements above LLD are in parentheses.

• • • Typical LLD value.

9 4

• L 1

l l

l APPENDIX B SAMPLE DESIGNATION ANO LOCATIONS l

r i

j 67

. -. . ._. -. __, .. .. .~.,-

APPENDIX B SAMPLE DESIGNATION

.The PSE&G Research Corporat1On identifies samples.by a three part code. The first two letters are the power station identification code, in this case

., "SA". The next three letters are for the media sampled.

AIO = Air Iodine- IDM =

Immersion Dose (TLD)

' APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR =

Potable Water (Raw)

ESF = Edible Fish PWT =

Potable Water (Treated)

ESS = Sediment RWA = Rain Water (Precipitation)

FPB = Beef 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 j.

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 distanco.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 = l-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 i

l The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,... For example, the designation SA-WWA-5D1 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.

h 69 e l  ;

4 SAMPLING LOCATIONS All 1987 sampling locations and specific information about the individual locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations.with respect to the site.

. TABLE B-1 STATION CODE STATION LOCATION- SAMPLE TYPES-2S2 0.4 mi. NNE of vent AIO, APT,IDM 2S3 700 ft. NNE of vent; fresh water holding tank WWA SS1 1.0 mi. E of vent; site acc'ess road AIO, APT,IDM 6S2 0.2 mi. ESE of vent; observation building IDM 7S1 0.12 mi. SE of vent; station personnel gate IDM

, 10S1 0.14 mi. SSW of vent; site shoreline IDM llS1 'O.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area ECH,ESF,ESS,SWA 15Al 0.3.mi. NW of vent; cooling tower blowdown ESS discharge line outfall 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge linc 12Cl 2.5 mi. WSW of vent; west bank of Delaware River ECH,ESF,ESS,SWA f

4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM SD1 3.5 mi. E of vent; local farm AIO, APT,IDM,WWA 10D1 3.9 mi. SSW of vent; Taylor's Bridge Spur AIO, APT,IDM l

l 11D1 3.5 mi. SW of vent GAM 14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm IDM 3El 4.1 mi. NE of vent; local farm FPB,FPV, GAM,IDM, VGT,WWA .

l 3E2 -5.7 mi. NE of vent; local farm FPV i 70

a

.s.

v

. O ._ -3

t.

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 llE2 5.0 mi. SW of vent IDM 12E1 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,VGT 16El 4.1 mi. NNW of vent; Port Penn AIO, APT,IDM 1F1 5.8 mi. N of vent; Fort Elfsborg AIO, APT,IDM 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA

-lF3 5.9 mi. N of vent; local farm FPL,FPV 2F2 8.7 mi. NNE of vent; Salem Substation AIO, APT,IDM, RWA 2F3 8.0 mi. NNE of vent; Salem ' Iter 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 e i

2F7 5.7 mi. NNE of vent; local farm MLK,VGT I

{

3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal IDM 1 Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 5F1 6.5 mi. E cf vent FPV,IDM j 5F2 7.0 mi. E of vent; local farm MLK,VGT l 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM .

7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM 71 i

.c ,

s TABLE B-1-(cont'd)

STATION-CODE STATION LOCATION SAMPLE TYPES-llF1 6.2-mi. SW of vent; Taylor's Bridge Delaware IDM llF3- 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT 12F1 9.4 mi. WSW of vent; Townsend Elementary School IDM 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 13F3 9.3 mi. W of vent; Redding Middle School, IDM Middletown, Delaware 13F4 9.8 mi. W of vent; Middletown, Delaware IDM 14F1 5.5 mi. WNW.of vent; local farm MLK,VGT 14F2 6.6 mi'. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV 15F3 5.4 mi. NW of vent IDM 16F1 6.9 mi NNW of vent; C&D Canal ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public: School IDM 1G1 E10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of V:,t; Wilmington, De!.awr.la IDM 2G1 12 mi. NNE of vent; Mannington Township, NJ FPV 3G1 17 mi. NE of vent; local farm IDM,MLK,VGT 1 )G1 12 mi. SSW of vent; Smyrna, Delaware IDM ISG1 15 mi. NNW of vent; Greater Wilmington Airport IDM 3H1 32 mi. NE of vent; National Park, New Jersey IDM 3H3 110 mi. NE of vent; Research and Testing AIO, APT,IDM Laboratory I

, 3HS 25 mi NE of vent; local farm FPL,FPV 72

e e

8 -

. MAP B-1 ON-SITE SAMPLING LOCATIONS oct2- o

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• APPENDIX C DATA TABLES 75

3 APPENDIX C DATA TABLES Appendix C presents the analytical results of the 1987 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1987.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1987 Concentrations of Gross Alpha Emitters.................... 80 C-2 1987 Concentrations of Gross Beta Emitters..................... 82 C-3 1987 Concentrations of Strontium-89 and Strontium-90 and Gamma Emitters in Quarterly Composites.................... 84 AIR IODINE C-4 1987 Concentrations of Iodine-131.............................. 86 DATES C-5 1987 Sampling Dates for Air Samples............................ 88 PRECIPITATION C-6 1987 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium................................................... 93 C-7 1987 Concentracions of Gamma Emitters.......................... 94 i

l DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-8 1987 Quarterly TLD Results..................................... 95 C-9 1787 Monthly TLD Results....................................... 96 l

l l 77 l

9

$ .N DATA TABLES-(cont'd.)

-TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT MILK C-10 1987 Concentrations of< Iodine-131.............................. 98 C-ll 1987 Concentrations of Strontium-89 and Strontium-90........... 99 C-12 1987 Concentrations of Gamma Emitters.......................... 100-C-13 1987 Sampling Dates for Milk Samples........................... 104 WELL WATER C-14 1987 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 106 i i

C-15 1987 Concentrations of Gamma Enitters;......................... 108 C-16 1987 Conceatrations of Strontium-89 and Strontium-90 in Quarterly Composites...................................... 110 POTABLE WATER C-17 1987 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 111 C-18 1987 Concentrations of Gamma Emitters.......................... 112 C-19 1987 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites...................................... 113 FOOD PRODUCTS C-20 1987 Concentrations of Gamma Emitters in Vegetables............ 114 C-21 1987 Concentrations of Gamma Emitters in Beef and Game......... 115 FODDER CROPS C-22 1987 Concentrations of Gamma Emitters.......................... 116 78

I i

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMEN't ,

SURFACE WATER C-23 1987 Concentrations of Gross Alpha Emitters.................... 117 C-24 1987 Concentrations of Gross Beta Emitters....................., 118 C-25 1987 Concentrations of Tritiu?,in Quarterly Composites......... 119 C-26 1987 Concentrations of Gamma Emitters........'.................. 120 EDIBLE FISH C-27 1987 Concentrations of Strontium-89 and Strontium-90 and

~

Tritium................................................... 122 C-28 1987 Concentrations of Gamma Emitters.. ....................... 123 r

BLUE CRABS C-29 1987 Concentrations of Strontium-89 and Strontium-90; Gamma Emitters and Tritium................................ 124 SEDIMENT C-30 1987 Concentrations of Strontium-90 and Gamma Emitters......... 125 SPECIAL TABLES I LLDs C-31 1987 PSE&G Research Corporation LLDs for Gamma Spectrometry.... 126  ;

79

a TABLE C-1 1987 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCl/m3 1 2 sigma STATION ID MONTH

• SA-APT-252 SA-APT-551 SA-APT-5Di** SA-APT-10D1 SA-APT-16El SA-APT-IF1 SA-APT-2FZ SA-APT-3H3 AVERAGE fcnetro?)

JANUARY 2.120.8 3.321.0 2.711.3 2.3t0.9 2.721.0 3.3 1.0 3.721.0 2.St0.9 2.821.1 1.020.6 2.020.8 2.921.5 2.120.8 1.910.8 1.510.7 1.820.8 1.6t0.7 1.8t1.1 1.420.6 1.320.6 1.921.2 1.520.7 1.li0.6 2.0t0.8 1.620.8 1.110.6 1.510.7 1.220.6 1.110.6 1.311.1 1.720.7 1.9t0.7 1.220.6 1.6t0.7 2.210.8 1.5t0.8 2.310.8 2.310.8 2.121.4 2.521.1 2.6tl.0 2.4t0.9 3.421.1 2.110.8 2.520.8 rEBRUARY 1.320.6 1.410.7 2.8tl.4 1.2t0.7 1.010.7 2.010.3 1.210.7 1.2i0.7 1.521.2 2.220.7 1.5t0.7 4.021.6 2.020.8 1.520.7 1.720.8 1.320.8 1.3t0.6 1.9tl.8 1.710.7 2.It0.7 1.521.3 2.3t0.8 2.2 0.7 2.5t0.9 1.720.7 1.920.8 2.020.9

<1.0 <1.0 <1.0 <1.2 <1.2 <1.1 <1.2 <0.9 -

oo MARCH 1.320.7 2.220.9 2.3tl.6 1.320.9 <1.2 1.420.9 2.621.1 1.320.8 1.721.1 c) 1.720.8 1.520.7 <2.0 1.4+0.9 1.5t0.8 2.220.8 2.120.9 1.810.8 1.820.6 1.420.8 1.621.0 <1.0 <1.3 1.8tl.0 <1.3 <1.4 <1.1 -

1.810.7 <4.5 (1) 1.7 1.2 1.6t0.7 1.220.6 1.620.7 2.420.9 2.810.8 1.921.1 APRIL 0.820.5 1.0t0.6 <1.0 1.010.7 1.220.7 0.910.7 <0.9 1.520.7 1.010.4 2.020.7 1.710.7 2.111.3 1.720.8 1.620.7 2.2t0.8 1.3t0.7 1.420.7 1.8i0.6 1.020.6 0.820.6 <1.0 1.220.8 <0.9 <0.9 1.610.8 1.810.7 1.220.7 1.110.7 <0.9 <1.0 1.220.8 1.4t0.7 1.0 0.7 <1.1 1.020.7 1.120.3 MAY 2.010.8 2.6i0.9 <1.0 2.220.9 2.120.9 1.820.8 2.721.0 2.320.8 2.111.1 2.020.8 1.620.8 2.121.5 1.821.0 3.4tl.1 1.920.8 1.520.9 1.920.8 2.021.2 1.820.7 1.410.7 i.721.4 1.9t0.8 1.710.8 1.520.8 1.7t0.8 1.210.7 1.610.4 2.91G.8 2.310.7 <1.0 1.620.7 2.110.7 2.0t0.7 1.510.'7 2.420.7 2.0tl.2 3.320.9 3.0t0.9 <2.0 2.610.8 2.0t0.7 3.621.0 3.110.9 2.620.8 2.821.2 JUNE 2.210.8 2.Zt0.8 2.311.4 2.120.9 3.021.0 3.8t1.1 2.420.9 2.220.8 2.5 1.2 2.020.8 2.010.9 2.221.4 1.220.9 1.520.9 2.320.9 2.320.9 1.820.8 1.920.8 2.010.8 1.720.8 2.4tl.6 1.420.8 2.020.9 1.820.9 1.420.8 1.420.7 1.8t0.7 2.220.7 1.220.7 2.1 1.4 4.821.1 4.321.0 2.320.8 3.220.9 1.220.7 2.722.7 e

6

• e ,

~

s TABLE C-1 (cont'd) 1987 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES -

Results in Units of 10'3 pC1/m3 2 2 sigma STATION 10 -

MONTH

• SA-APT-252 SA-APT-551 SA-APT-501** SA-APT-1001 SA. APT-16El

SA-APT-1F1 SA-APT-2F2 SA-APT-3H3 AVERAGE fcnntrali JULY 2.020.9 1.820.9 <2,0 1.521.1 1.521.0 1.820.9 '

i 1.3t0.7 1.520.9 <1.0 1.6tl.0 2.120.9 1.8t0.5 2.220.9 1.610.8 1.220.8 1.920.9 1.520.8 1.520.8

-- ~ '

2.510.8 1.620.8 1.8tl.3 1.821.0 1.610.9 1.810.8 3.321.0 2.421.0 2.921.0 1.920.8 2.020.9 2.721.7 2.4t0.9 1.720.8 2.521.8 (2) 2.821.1 1.610.7 1.320.7 2.6t1.6 1.720.9 2.720.9 2.621.0-1.7 0.8 1.9tl.2 1.810.8 1.720.8 1.820.7 i AUGUST 2.2i0.8 2.420.9 1.921.5 2.520.9 1.610.7 2.110.9 2.121.0 4

1.720.7 1.520.7 2.421.4 1.810.8 2.120.6

' 1.220.8 1.9t0.8 1.420.7 2.220.8 2.220.8 1.020.7 1.420.8 2.121.4 3.321.0 1.820.9 l 4.221.0 1.420.7 <1.0 1.820.8 2.022.3

<0.9 <0.9 <1.0 <1.1 1.510.8 <1.0 1.420.8 <0.9 -

co SEPTEMC2R 3.0t0.8 1.820.7 <1.0 1.8t0.8 2.0t0.7 2.620.7 "

. se 1.620.8 1.320.8 2.821.7 1.920.7 2.8to.8 2.121.3 1.4t0.9 1.720.8 1.510.9 1.821.0 1.620.9 1.720.9 2.110.8 1.9to.8 2.121.5 1,810.9 1.920.8 1.0t0.6 1.520.7 2.921.4 2.020.8 1.4t0.7 1.810.8 2.6t0.8 2.420.9 2.510.8 2.320.8 2.420.8 1.820.8 2.320.9 OCTOBER 2.020.8 1.520.7 1.721.4 2.020.8 1.3i0.7 2.2to.7 i 1.220.7 1.520.7 <1.0 1.8 0.8 1.520.7 1.8t0.6 1.720.8 <1.0 1.720.8 1.6 0.8- 1.320.8 1.410.6 2.710.9 2.520.9 2:221.4 2.0t0.9 1.9t0.9 3.621.0 1.610.7 2.6t0.7 <1.0 3.221.1 1.St0.7 2.5 1.3 1.810.7 1.720.7 1.910.7 1.820.7 2.720.9 2.410.8 1.810.7 <2.0 2.020.8 1.921.1 <

2.120.8 2.410.7 2.6 0.9 2.620.8 2.220.6 1

NOVEMBER 4.6tl.0 4.1t0.9 5.622.0 4.621.0 4.421.0- 4.3t1.0 3.821.0 4

2.910.9 3.921.0 3.421.6 2.320.8 4.721.0 4.5 1.1

' 2.721.0 2.920.8 3.121.0 3.520.9 3.121.0 1.810.6 1.7i0.6 2.121.3 1.520.6 ' ' 2.320.8 1.910.7 1.920.8 1.820.8 6.322.7 1.6 0.6 1.6t0.7 1.8 0.5 2.020.8 1.320.7 2.410.9 2.320.8 1.720.7 2.523.2 2

DECEMBER 2.010.8 1.220.7 2.721.4 1.420.9 2.6t1.0 <1.0 2.120.8 1.820.8 4.6 1.9 1.z20.8 1.9t0.9 1.8tl.3 2.110.8 1.220.7 1.5 0.8 1.920.9 1.920.9 2.122.1-1.810.8 0.920.6 1.9tl.2 2.1 0.9 1.6t0.9 2.120.9 2.420.8 2.020.8 1.410.7 1.5 0.8 1.720.8 I 2.121.5 1.820.7 2.310.8 2.420.8 2.410.8 2.120.8 2.220.4 ,

, AVERAGE 1.9 1.4 1.8tl.4 2.222.2 1.921.5 1.921.6 2.021.5 2.021.4 1.921.4 "

• Sampling dates can oe found in Table C-5. GRAND AVERAGE 2.021.6 .

• • Results by Teledyne isotopes. '

(1) High LLD due to low sample volume (faulty samp1tng assembly). Result not included in any averages.

(2) Due to sow sample volume (relocation of sampling equipment), result not included in any averages.

I i

1

.^

TABLE C-2 1987 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pC1/m3 2 2 sigma STATION ID MONTH

• SA-APT-252 SA-APT-551 SA-APT-5D1** SA-APT-10D1 SA-APT-16El SA-APT-IF1 SA-APT-2f2 SA-APT-3H3 AVERAGE IC tip? \

JANUARY 2823 2923 2723 2723 3123 28 3 29t3 2623 2823 2222 2222 2323 23t2 2323 2223 2523 23t3 2322 2012 2022 2323 1823 1922 2323 1923 ' 1922- 20t4 2322 2222 2523 25t2 26t3 25t3 2422 - 2623 -2423 3223 3013 3724 2914 3223 3123 3723 2923. 3226 FEBRUARY 2022 2122 2523 24t3 2223 21 2 2322 2123 2223

'! 2122 2022 24t3 2123 2022 2123 22t3 2122 2122 2022 2022 2123 24t2 2322 2123 21 3 1722 2124 1222- 11t2 1323 1323 1313 12 2 1423 1122 1222 MARCH 25 3 26t3 2413 2423 2623 2523 24t3 2413 2522

[$ 2823 2722 2723 3123 29t3 2623 3023 2923 28 3 1722 1523 1623 16t3 1823 1623 1823 1522 16t2 18t2 <18 (1) 1723 1722 1822 19 2 2123 19 2 1823 APRIL 7.021.7 16t2 1723 1323 1223 1222 1323 1522 13t6 20t2 1712 2123 19t3 2023 20t2 21*3 19t2 2023 1322 13t2 1824 1312 1222 13t2 1222, 1222 1324 1022 1022 15i3 1222 1222 9.1 2.0 14t3 1122 12t4 4

MAY 20t2_ 1922 20t3 2223 2113 1923 1923 2122 2022 2623 2523 24t1 28t4 26i3 2823 2623 I222 26t4

, 2022 1923 1823 2323 23i3 2023 2323 21t2 21i4 1

1622 14t2 1723 14t2 1322 1322 1322 1422 1423 2813 2823 2624 2923 26t3 2723 28 3 3023 2823-JUNE 25 3 2223 24t3 2823 2523 3123 27t3 22t2 2626 3023 2723 2723 3023 28t3 3023 3123 3123 2913 1912 21t2 1823 1922 24 3 1923 21t3 2423 21t5 2122 2022 1523 2823 2623 1922 24 2 1422 21210 4

• O wr . .-- e . ,. -w-,

~

=. .

i TABLE C-2 (cont'd) 1987 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10~3 pC1/m3 2 2 sigma STATION ID

~

MONTH

• SA-APT-252- SA-APT-551 SA-APT-5D1** SA-APT-10D1 SA-APT-16El 5A-APT-1F1 SA-APT-2F2 SA-APT-3H3 AVERAGE

{

. frontenti JULY 1823 1823 2424 2024 1723 2023 1823 23 3 2025- -

2523 2523 25 3 2723 2623 2423 26t3 23t3 2522 2923 26t3 2924 2623 24t3 2623 3023 4523 40:3 2523 27t4-3924 48t3 4023 4916 (2) 32 3 36 3 40211 j 25t3 2723 2623 27t3 23t3 2724 31 3 1913 '2627 '

l AUGUST 3023 2813 3124 3123 29t3 2823 3023

1922 2222 2926 1822 1923 1823 1823 1722 2023 2823 2112 19t2 '-

1 2523 2913 34t3 3423 ?l 3 1422 i 2523 28213 2523 2322 2423 2623 22t3 2123 2613 14t2 23tB SEPTEMBER 2822 25:2 25t3 2823 23 2 7722 1822 8 2523 2923 24t3 25t3 3023 2613 Z323 2823 2522 2213 2526 2515 2923 2814 2723 23t3 28i3 3013 2923 ,2824 2523 2723 2823 32g3 2523 2623 28t3 2523 2725 OCTO8ER 3213 28t3 2724 2523 2423 29t3 2923 2423 1822 2726 2022 16 2 2423 2222 24+2 2523 2222 2126 4724 4223 4024 38t3 4124 4313 43t4 2823 4423 4225 3023 28t3 2923 3023 3523 3313 3423 3125 3123 2923 3114 28t3 3224 2*ti 3023 2523 2914 i

NOVEMBER 3823 3623 3723 3723 3823 3913 4023 3723 3123 3624 4223 38i4 2921 3723 3323 3423 3423 3426 23t2 2322 2223 2222 26t3 2222 23t2 -2223 1923 1722 2323' 1923 1822 1723 18 3 1822 2423 19t4 1 DECEMBER 1722 1722 2123 1623 1723 1522 16t3 '

j 2723 2523 2823 1422 17 4 2422 2422 2623 2623 '2423 2623

! 21i2 1922 2723 17t3 1723 1823 2122 2323 30t3 2027 28r3 34t4 2522 3023- 2923 3123 3423 30 6 AVERAGE 24215 23213 25 13 24214 24214 24214 24214 23214 4 '

• Samp1tng dates can be found in Table C-5. GRAND AVERAGE 24t14

• • Results by Teledyne Isotopes. -

' (1) High LLD due to low sample volume (f aulty sampling assembly). Result not included in any averages.

(2) Due to low sample volume (relocation of samp1tng equipment), result not included in any averages.

e

]

, - - . - - - , , , , , - c-+ , , , . = - . .,,,

, n.. --,. - -- - . . - - - r - - ,-

TABLE C-3

+

i 1987 CONCENTRATIONS OF STRONTIUM-89a AND STRONTIGM-90 AND GAMMA EMITTERSaa IN QUARTERLY COMPOSITES OF AIR PARTICULATES ,

Results in Units of 10 -3 pC1/m3 1 2 sigma l

STATTOM TD 1

SAMPLING PERIOD Sr-89aae Sr-90=aa Be-7 K-40 La-140 Ra-226 Th-232 sA-APT-?n?

12-29-86 to 03-30-87 <0.3 (2.0 7314 (7.8 <1.0 <0.8 . <1.7 03-30-87 to 06-30-87 - -

9215 <6.8 <1.0 <0.7 <1.1 4

06-30-87 to 09-28-87 - -

8514 <5.9 <0.5 <0.6 <0.9 09-28-87 to 12-28-87 - -

6714 (7.6 <0.9 <0.9 <1.8 sA-APT-ss1 12-29-86 to 03-30-87 <0.7 <0.4 7716 <10 <1.3 <1.1- <1.7 03-30-87 to 06-30-87 - -

8216 (12 <0.9 <1.3 <2.3 U$ 06-30-87 to 09-28-87 - -

7815 (8.4 <0.7 <1.0 (1.9 4 09-29-87 to 12-28-87 - -

5815 <9.4 <0.9 <0.9 <1.7 RA-APT-9D1 (1) 12-29-86 to 03-30-87 <1.0 <0.2 9019 <10 ) (7.0 03-30-87 to 06-30-87 - -

110111 <6.0 ) (8.0 i 06-30-87 to 09-28-87 - -

110111 1719 ) <8.0

! 09-28-87 to 12-28-87 - -

6917 <10 J <4.0

, Sh-APT-10D1 12-30-86 to 03-31-07 <0.5 <0.3 7516 <11 <1.2 <1.0 <2.1

, 03-31-87 to 07-01-87 - -

9516 <11 <1.4 <1.3 <2.1

! 07-01-87 to 09-29-87 - -

8816 <12 <1.1 <1.3 <2.1 09-29-87 to 12-29-87 - -

56i5 <10 <1.2 <1.0 <2.1

]

I SA-APT-1 API i 12-30-86 to 03-31-87 <0.6 <0.4 7716 (10 <1.1 <1.0 1.510.9

j 03-31-87 to 07-01-07 - -

8415 <8.6 <1.0 <0.8 <2.0 07-01-87 to 09-29-87 - -

7714 (6.3 <0.5 <0.8 <1.1

]

09-29-87 to 12-29-87 - -

6514 <4.7- <0.6 <0.9 1.110.6 .

j r- --

r - -- '

TABLE C-3 (cont'd) 1987 CONCENTRATIONS OF STRONTIUM-89= AND STRONTIUM-90 AND GAMMA EMITTERSa=

IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pC1/m3 1 2 s19ma STATION Yn SAMPLING PERIOD Sr-89aaa Sr-90aaa Be-7 K-40 La-140 Ra-226 Th-232 SA-APT-irl 12-29-86 to 03-30-87 <0.7 <0.4 7415 <8.8 <1.1 1.410.7 <2.1 03-30-87 to 06-30-87 - -

9015 <7.0 <0.7 <l.0 <2.0 06-30-87 to 09-28-87 - -

7816 (7.8 <1.0 <l.1 <l.8 09-28-87 to 12-28-87 - -

5815 <6.2 <1.2 <l.1 <l.8 SA-APT-?F2 12-29-86 to 03-30-87 (0.3 <0.2 72i5 <8.4 <0.9 <0.9 <l.9 CD 03-30-87 to 07-01-87 - -

9516 (8.0 <l.2 <0.8 <l.0

'" 07-01-87 to 09-28-87 - -

7616 <ll <l.2 <1.3 <2.5 09-28-87 to 12-28-87 - -

6714 <8.8 <0.5 <0.7 (0.9 SA-APT-7H1 (Control) 12-29-86 to 03-30-87 <0.4 <0.3 6715 <8.7 1.010.5 <l.1 <l.8 03-30-87 to 06-29-87 - -

9415 <7.0 <0.8 <0.8 <l.2 06-29-87 to 09-28-87 - -

7615 <7.8 <l.1 <0.7 <1.3 09-28-87 to 12-28-87 - -

6615 (6.2 <l.2 <0.7 <l.2 AVERAGE - -

79127 - - - -

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

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

• • a Mana9ement audit analyses, not required by Technical specifications or by specific commitments to local officials.

(1) Results by Teledyne Isotopes.

(2) Not analyzed by Teledyne Isotopes.

TABLE C-4 1987 CONCENTRATIONS OF 10 DINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3 STATION ID MONTH ** SA-AIO-252 SA-AIO-SSI SA-AIO-5DI*** SA-A10-1001 SA-AIO-16El SA-A10-1F1 SA-A10-2F2 SA-AIO 3H3 (Cnntrn1)

JANUARY <17 <26 <20 <14 <14 <17 <21 <20

<18 <16 <20 <18 <17 <21 <20 <22

<11 <20 <10 <19 <16 <15 <11 <17

<9.6 <18 <20 <11 <15 (18 <18

<17 <21

<23 <10 <29 <22 <22 <34 <19 FEBRUARY <13 <15 <10 <15 <13 <17 <16 <16

<16 <19 <20 <15 <14 <19 <13 <11

<15 <18 <20 <21 <18 <32 <23 (20

<19 (24 <20 <17 <20 <16 <19 <15 MARCH <14 <17 <20 <24 <21 <21 <22 <16

[$ <9.9 <15 <20 <21 <25 <19 <20 <18

<13 <!7 <30 <22 <25 <25 <22 <18

<16 <18 <30 <20 <18 <16 <22 (20 APRIL <16 <22 <10 <20 <20 <18 <18 <15

<16 <12 <20 <26 <27 <20 <22 <10

<15 <22 <20 <24 <25 <18 <27 <16

<13 <17 <20 <19 <16 <16 <21 <19 MAY <9.3 <17 <10 <20 <19 <17 <17

<15 <14

<21 <10 <23 <24 <19 (17

<16 <15

<14 <20 <24 <17 <22 <18

<15 <17

<15 <10 <12 <15 <18 <16

<17 <14

<19 <14 <25 <17 (31 <24 <17 JUNE <18 <19 <10 <26 <31 <28 <26 <17

<15 <17 <10 <18 <14 <18 <13 <21

<13 <23 <20 <16 <21 <24 <19 <14

<13 <20 <10 <20 <13 <12 <13 <15 1 ..

v Og Q

TABLE C-4 (cent *d) 1987 CONCENTRATIONS OF 1001NE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m 3 STATION 10 MONTH ** SA-AIO-252 SA-AIO-551 SA-A10-501*** SA-AIO-10D3 SA-AIO-16El SA-AIO-1F1 SA-AIO-2F2 SA-AIO-3H3 frenirnii JULY <19 <20 <30 <24 <25 <15

<16 <27 (20 <21 16

<20 <28 <20

<14 <12 <20 <13 <20 31 <21 <20

<15 <17 430 <13 <16

<16 <17

<17 <14 <10 <28

<57 (1) <26 <13

<22 <dt <26 <20 AUGUST <15 <17 <20 <23 <18 <22

<11 <16 <20 <22 <23

<22 <21 <21

<22 <18 <10 <17 <22

<10 <15 <14

<20 <10 <10 <16 <14

<23 <19 <21 <19 <11 SEPTEMBER <18 <16 <20 <23 co <18

<23 <14 <26 '13

'J <19 (10 <32 <20

<15 <17 <21 <26 <20

<20 <18 <17

<20 <18 <18 <25 <15

<9.0 <16 <14 <16 <11 <16 OCTOBER <23 <19 <20 <15 <23 (14

<13 <21 <9.0 <21 <16

<13 <23 <21

<17 <22 <20 <13 <16

<15 <19 (21

<16 <11 <30 <27 <18

<16 <12 <20

<19 <19 <20 <10 <17

<23 <22 <15 <34 <20 NOVEMBER <22 <13 <20 <20 <18 <16 <18

<19 <18 <20 (17 <16

<24 <17 <15 <14

<12 <23 (20 <10 <19 <21 <14

<17 <16 <20 <15 <16

<18 <23 <17 (17 DECEMBER <18 <15 <10 <19 <21 <17 <13

<15 <19 <20 <18 <15

<17 (18 (10

<16 <18 <20 <13 <17

<19 (25 <9.3

<!6 <19 <30 <20 <15

<14 (18 <12 <19 i

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

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

• • • Results by Teledyne Isotopes.

(1) High LLD due to low sample volume (relocation of sampling equipment).

TABLE C-5 ,

1987 SAMPLING DATES FOR AIR SAMPLES STATION 10 MONTH 252 551 501 1001 16El IF1 2F2 3H3 JANUARY 12-29-86 12-29-86 12-29-86 12-30-86 12-30-86 12-29-86 12-29-86 12-29-86 to to to to to to to to 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 01-05-87 to to to to to to to to 01-12-87 01-12-87 01-12-87 01-13-87 01-13-87 01-12-87 01-12-87 01-12-87 01-12-87 01-12-87 01-12-87 01-13-87 01-13-87 01-12-87 01-12-87 01-12-87 to to to to to to to to 01-19-87 01-19-87 01-19-87 01-20-87 01-20-87 01-19-87 01-19-87 01-19-87 01-19-87 01-19-87 01-19-87 01-20-87 01-20-87 01-19-87 01-19-87 01-19-87 to to to to to to to to 01-27-87 01-27-87 01-27-87 01-28-87 01-28-87 01-27-87 01-27-87 01-26-87

$ 01-27-87 01-27-87 01-27-87 01-28-87 01-22-87 01-27-87 01-27-87 01-26 to to to to to to to to .

02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 FEBRUARY 02-02-27 02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 02-02-87 to to to to to to to to 02-10-87 02-10-87 02-10-87 02-10-87 02-10-87 02-10-87 02-10-87 02-09-87 i 02-10-87 02-10-87 02-10-87 02-10-87 02-10-87 02-10-87 02-10-87 02-09-87 to to to to to to to to 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 02-17-87 to to to to to to to to 02-24-87 02-24-87 02-24-87 02-25-87 02-25-87 02-24-87 02-24-87 02-23-87 l

4 02-24-97 02-24-87 02-24 87 02-25-87 02-25-87 02-24-87 02-24-87 02-23-87 to to to to to to to to G3-02-87 03-02-87 03-02-87 03-03-87 03-03-87 03-02-87 03-02-87 03-02-87 MARCH 03-02-87 03-02-87 03-02-87 03-03-87 03-03-87 03-02-87 03-02-87 03-02-87 to to to to to to to to d

03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03-09-87 03 09-87 03-09-87 03-09-87 to to to to to to to to 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 .

M

~

1 TABLE C-5 (cont'd) -

{ 1987 SAMPLING DATES FOR AIR SAMPLES i

STATION ID

) MONTH 252 551 501 1001 16El IF1 2F2

! 3H3 3 MARCH 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 03-16-87 j to to 03-16-87 to to to to to j to 03-23-87 03-23-87 03-23-87 03-23-87 03-23-87 03-23-87 03-23-87 4

03-23-87 03-23-87 03-23-87 03-23-87 03-23-87 03-23-87 03-23-87 03-23-R' 03-23-87 i

to to to to to to to to l 03-30-87 03-30-87 03-30-87 03-31-87 03-3; 2" 03-30-87 03-30-87 03-30-87 1 APRIL 03-30-87 03-30-87 03-30-87 03-31-87 03-31-87 03-30-87 03-30-87 i 03-30-87 to to to to to to to to

{ 04-06-87 04-06-87 04-06-87 04-06-87 04-06-87 04-06-87 04-06-81

. 04-06-87 I

04-06-87 04-06-87 04-06-87 04-06-87 04-06-87 04-06-87 04-06-87 to to 04-06-87 to to to to to to 04-13-87 04-13-87 04-13-87 04-13-87 04-13-87 04-13-87 04-13-87 04-13-87 t

0$ 04-13-87 04-13-87 04-13-87 04-13-G7 04-13-37 04-13-87 04-13-87 04-13-87

! to to to to to to to to 4

4 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 04-20-87 to lo to to to to to to 04-27-87 04-27-87 04-27 04-28-87 04-28-87 04-27-87 04-27-87 04-27-87 MAY 04-27-87 04-27-87 04-27-87 04-28-87 04-28-87 04-27-87 04-27-87 04-27-87 to to to to to to to to

, 05-04-87 05-04-87 05-04-87 05-05-87 05-05-87 05-04-87 05-04-87 05-04-87 1

1 05-04-87 05-04-87 05-04-87 05-03-87 05-05-87 05-04-87 05-04-87 05-04-87 i to to to to to to to to 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 05-11-87 to to to to to to to to 05-18-87 05-18-87 05-18-87 05-18-87 05-18-87 05-13-87 05-18-87 05-18-87 05-18-87 05-18-87 05-18-87 05-18-87 05-18-87 15-18-87 05-18-87 05-18-87 to to to to to to to to 05-26-87 05-26-87 05-26-87 05-26-87 05-26-87 05-26-87 05-26-87 05-26-87.

05-26-87 05-26-87 05-26-87 05-26-87 05-26-87 05-26-87 . 05-26-87 05-26-87 to to to to to to . to to 06-01-87 06-01-87 06-01-87 06-02-87 06-02-87 06-01-87 06-01-67 06-01-87

)

-- no.,-..,-, , , ._, e, -n,- ,.n en -,e. , --w-,--,-,w ----a m- .e -,n -v- aw-- -, w e- ,...wqe , =---,,w,

y . . . _

TABLE C-5 (cont'd) 1987 SAMPLING DATES FOR AIR SAMPLES STATION ID MONTH 252 551 SDI -1001 , 16El IF1 2F2 3H3 2 JUNE 06-01-87 06-01-87 06-01-87 06-02-87 06-02-87 06-01-87 06-01-87 06-01-87.

to to to to to to to to

• 06-08-87 06-08-87 06-08-87 06-08-87 06-08-87 06-08-87 06-08-87 06-08-87 i

06-08-67 06-08-87 06-08-87 06-08-87 06-08-87 06-08-87 06-08-87 06-08 to to to to to to to to-06-15-87 06-15-87 06-16-87 06-15-87 06-15-87 06-16-87 06-16-87 06-1b-87 06-15-87 06-15-87 06-16-87 06-15-87 06-15-87 06-16-87 06-16-87 06-15-87 to to to to to to to to 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 -

06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 06-22-87 i to to to to to to to to 06-30-87 06-30-87 06-30-87 07-01-37 07-01-87 06-30-87 07-01-87 06-29-87

} I$ JULY 06-30-87 06-30-87 06-30-87 07-01-87 07-01-87 06-30-87 07-01-87 06-29-87 to to to to to to to to 07-06-87 07-06-87 07-06-87 07-06-87 07-06-87 07-06-87 07-06-87 07-06-87 3

07-06-87 07-06-87 07-06-87 07-66-87 07-06-87 07-0(-87 07-06-87 07-06-87 to to to to to to to to 07-13-87 07-13-87 07-13-87 07-14-87 07-14-87 47-13-87 07-13-87 A 07-13-87 07-13-87 . 07-13-87 07-13-87 07-14-87 07-14-87 07-13-87 07-13-87 07-13-87

]. to to to to -to to to to

07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 r 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 07-20-87 i to to to to to to to. to G7-27-87 07-27-87 07-27-87 07-28-87 07-28-87 07-23-87* 07-27-87 07-27-87 s a,

07-27-87 07-27-87 07-27-87 07-28-87 07-28-87 07-30-87 07-27-87 07-27 87

. to to to to to to to to l C8-03-87 08-03-87 08-03-87 C3-03-87 08-03-87 08-03-87* 08-03-87 08-03-87.

1 I

1 AUGUST 08-03-87 08-03-8T 08-03-87 08-03-87 08-03-87 08-03-87 08-03-87 08-03-87 I to to to to to to to - to j 08-10-87 08-10-87 08-10-87 08-11-87 08-11-87 08-10-87 08-10-87 08-10-87 j 08-10-87 08-10-87 08-10-87 08-11-87 08-11-87 08-10-87 08-10-87 08-10 4 to to to to to to to to l 08-17-87 08-17-87 08-17-87 08-17-87 08-17-8? 08-17-87 08-17-87 08-17-87 O g.'

4 e*

I

-.e..-,_-,-am--- e--.- - - - - _ . _ _ . _ . - - -_ _ . _ . - __v-m.e---e.w-*-,---.--,m --w e -.

• a . q g T, w

TABLE C-5 (cont'd) 1987 $AMPLING DATES FOR AIR SAMPLES STATION 10 MONTH 252 551 501 1001 16El IF1 2F2 3H3 AUGUST 08-17-87 08-17-87 08-17-87 08-17-87 08-17-87 08-17-87 to 08-17-87 08-17 to to to to to to 08-24-87 to 08-24-87 08-24-87 08-25-87 08-25-87 08-24-87 08-24-87 08-24-87 08-24-87 08-24-87 08-24-27 08-25-87 08-25-87 08-24-87 to 08-24-87 08-24-87 to to to to to to to 08-31-87 08-31-87 08-31-87 09-01-87 09-01-87 08-31-87 08-31-87 08-31-87 SEPTEM8ER 08-31-87 08-31-87 08-31-87 09-01-87 09-01-87 08-3.-87 to 08-31-87 08-31-87 to to to to to to 09-08-87 to 09-08-87 09-08-87 09-08-87 09-08-87 03-08-87 09-08-87 09-08-87 09-08-87 09-08-87 09-08-87 09-08-87 09-08-87 09-08-87 to 09-08-87 09-08-87 to to to to to to to 09-14-87 09-14-87 09-14-87 09-15-87 09-15-87 09-14-87 09-14-87 09-14-87

[3 09-14-87 09-14-87 09-14-87 09-15-87 09-15-87 09-14-87 49-14-87 09-14-87 to to to to to to to to 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 09-21-87 to 09-21-87 09-21-87 to to to to to to 09-28-87 to 09-28-87 09-28-87 09-29-87 09-29-87 09-28-87 09-28-87 09-28-87 OCTOBER 09-28-87 09-28-87 09-28-87 09-29-87 09-29-87 09-28-87 to 09-28-87 09-28-87 to to to to to to to 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 10-05-87 to 10-05-87 10-05-87 to to to to to to to 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 10-13-87 to to 10-13-87 to to to to to 10-19-81 to 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 10-19-87 to 10-19-87 10-19-87 to to to to to to to 10-26-87 10-26-87 10-26-87 10-21-87 10-27-87 10-26-87 10-27-87 10-26-87 10-26-87 10-26-87 10-26-87 10-27-87 10-27-87 10-26-87 10-27-87 to to 10-26-87 to to to to to 11-02-87 to 11-02-87 11-02-87 11-02-87 11-02-87 11-02-87 11-02-87 11-02-87

s.

)

TABLE C-5 (cont *d) 1987 SAMPLING DATES FOR AIR SAMPLES

. STATION ID MONTH 232 551 5D1 1001 16El 1F1 ' 2F2 3H3

'}

i NOVEMBER 11-02-87 1*-02-87 11-02-87 11-02-87 11-02-87 11-02-87 11-02-87 11-02-87

' to to to to to to to to 11-09-87 11-09-87 '1-09-87

. 11-10-87 11-10-87 11-09-87 11-09-87 11-09-87

'l 11-09-87 11-09-87 11-09-87 11-10-87 11-10-87 11-09-87 11-09-87 11-09-87 to to to to to to to to 11-16-87 11-16-R7 11-16-87 11-16-87 11-16-87 11-16-87 11-16-87 11-16-87 11-16-87 11-16-87 ~11-16-87 11-16-87 11-16-87 11-16-87 11-16-87 11-16-87

. to to to to to to to to I 11-24-87 11-24-87 11-24-87 11-24-87 11-24-87 11-24-87 11-24-87 11-23 a, 11-24-87 11-24-87 11-24-87 11-24-87 11-24-87 11-24-37 11-24-87 11-23-87 to to to to to to to to 11-30-87 11-30-87 11-30-P7 12-01-87 12-01-87 11-30-87 12-01-87 11-30-87 ND 11-30-87 11-30-87 11-30-87

"# DECEMBER 12-01-87 12-01-87 11-30-87 12-01-87 11-30-87 to to to to to to to to 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 12-07 12-07-87 12-07-87 12-07-87 12-07-87 12-07-87 4 to to to to to to to to 12-14-87 12-14-87 12-14-87 15-87 12-15-87 12-14-87 12-14-87 12-14-87 12-14-87 12-14-87 12-14-87 12-15-87 12-15-87 12-14-87 12-14-87 12-14-87 .

to te to to to to to to 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 l

12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 12-21-87 to to to to to to to to

12-28-87 12-28-87 12-28-87 12-29-87 12-29-87 12-28-87 12-28-87 12-28-87 9

• Shortened collection period due to relocation of samp1tng pole and power lines (at request of local resident).

i b *

,s,,,. mw,,n .. - , - - , . .. . - . ,,.r- m. - - - - ,- . . . - - - - - ,. ,w.,. m,,,, , , - - - - wm ,-w. , --r -

w --14m n -e-em.m ,-. , .-w. - -

1 a  ;

i O

'O TABLE C-6 1987 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION STATION ID: SA-RWA-2F2 Results in Units of pCi/L i 2 sigma SAMPLING PERIOD ALPHA BETA TRITIUM 12-29-86 to 01-27-87 0.910.7 2.0 0.7 <140 01-27-87 to 03-02-87 <1.2 2.810.7 <160 03-02-87 to 03-31-87 <1.1 1.710.6 <140 03-31-87 to 04-28-87 <1.8 3.8 1.3 <150 '

04-28-87 to 06-01-87 1.8kl.5 5.7*0.9 210 90 06-01-87 to 07-01-87 <1.3 9.611.3 <140 07-01-87 to 07-28-87 <1.2 3.010.8 <140 07-28-87 to 08-31-87 <1.0 12 3 <140 08-31-87 to 09-29-87 <0.6 3.310.8 <140 09-29-87 to 10-27-87 <0.6 6.4*1.0 <140 10-27-87 to 12-01-87 <1.5 2.210.8 <140  ;

12-01-87 to 12-29-87 <1.8 3.9*0.9 <140 f AVERAGE -

4.7i6.4 -

93 l

i TABLE C-7 A  :;s.

1987 CONCENTRATIONS OF GAMMA EMITTERS *J IN Po.ECIPITATION '3 STATION ID: SA-RWA-2F2  %. g Results in Units of pCi/L i 2 sigma  ;

SAMPLING PERIOD Be-7 K-40 Nb-95 Ra-226 Th-232 *

12-29-86 to 01-27-87 23 12 <40 <2.9 <6.4' <11 01-27-87 to 03-02-87 49 17 42119 <3.3 <7.7 <14

, 03-02-87 to 03-31-87 61118 <58 3.811.7 <8.7 <13 -

! 03-31-87 to 04-28-87 55 13 74129 <3.6- <10 <14 2

04-28-87 to 06-01-87 74112 <32 <l.7 <4.3 <5.5 l 06-01-87 to 07-01-87 83121 <68 <8.2 <9.6 <13 I 07-01-87 to 07-28-87 42 10 <31 <2.4 <3.9 6.213.6 i 07-28-87 to 08-31-87** - - -

08-31-87 to 09-29-87 4519 <25 <2.2 4.812.4 <4.5 09-29-67 to 10-27-87** - - - - -

4 10-27-87 to 12-01-87 37 11 <31 <3.8 <3.9 8.914.1-12-01-87 to 12-29-87 81120 <64 <5.4 <7.9 <12

~

l i

AVERAGE 55139 - - - -

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

• • Not analyzed due to insufficient precipitation during sampling period.

~

w e

9

TABLE C-8 1987 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad / standard month

• i 2 sigma (Results by Teledyne Isotopes)

JANUARY APRIL JULY OCTOBER STATION ID to to to to AVERAGE MAROH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 5.910.3 4.510.5 5.710.5 4.5i0.4 5.211.5 SA-IDM-5S1 5.120.2 4.220.4 5.110.4 4.010.3 4.611.2 SA-IDM-6S2 5.610.3 4.210.4 5.510.3 4.210.3 4.911.6 SA-IDM-7S1 6.510.4 5.210.5 6.710.5 5.610.E 6.0fl.4 SA-IDH-10S1 5.810.2 5.310.7 6.210.6 5.110.6 5.611.0 SA-IDM-1151 5.110.1 4.610.7 6.611.2 6.611.5 5.712.1 -

SA-IDM-4D2 5.610.2 4.810.3 6.110.3 4.710.4 5.3tl.3 ;

SA-IDM-5D1 5.410.3 4.610.3 5.510.3 4.310.4 4.911.2 SA-IDM-10D1 5.710.3 4.510.3 5.910.4 4.510.4 5.211.5 SA-IDM-14D1 5.620.2 4.510.3 5.820.2 4.510.4 5.121.4 SA-IDM-2El 5.410.2 4.510.3 5.710.6 4.520.6 5.011.2 SA-IDM-3El 5.210.3 4.310.3 5.410.2 4.120.3 4.811.3 SA-IDM-9El 6.010.3 5.310.5 6.610.5 5.210.5 5.811.3 SA-IDM-llE2 6.210.4 5.010.4 6.610.6 5.110.6 5.711.6 SA-IDM-12El 6.010.4 4.710.4 6.210.3 4.910.4 5.411.5 SA-IDM-13El 5.110.3 4.110.2 4.5t0.2 4.110.4 4.410.9 SA-IDM-16El 5.610.3 4.710.2 5.710.2 4.610.3 5.211.2 SA-IDM-lF1 5.710.6 4.210.5 E.810.4 4.410.4 5.011.7 SA-IDM-2F2 4.410.2 3.210.3 4.510.1 3.8 0.7 4.0il.2 SA-IDM-2F5 5.510.3 4.710.4 5.810.5 4.610.5 5.211.2 SA-IDM-2F6 5.510.3 4.510.3 5.510.2 4.710.4 5.010.9 SA-IDM-3F2 5.110.3 4.2 0.2 5.110.3 4.1 0.3 4.611.0 SA-IDM-3F3 5.010.3 4.010.2 6.011.4 4.110.3 4.811.2 SA-IDM-5F1 5.5i0.2 4.120.3 5.410.2 4.210.4 4.811.3 SA-IDM-6F1 4.910.1 3.710.2 4.6!0.2 3.610.3 4.211.3 SA-IDM-7F2 4.610.3 3.510.2 4.410.2 3.910.4 4.111.0 SA-IDM-10F2 5.920.3 4.810.5 6.210.5 4.910.6 5.411.4 SA-IDM-llF1 5.910.5 5.210.4 6.010.2 4.610 6 5.411.3 SA-IDM-12F1 5.810.3 4.7 0.4 5.910.4 4.710.5 5.311.3 SA-IDM-13F2 5.610.4 4.410.3 5.8iO.2 4.510.3 5.111.4 SA-IDM-13F3 5.710.4 4.610.3 5.910.4 4.810.4 5.211.3 SA-IDM-13F4 5.710.5 4.510.4 5.610.4 4.610.5 5.111.3 SA-IDM-14F2 5.810.7 4.710.4 5.710.4 4.410.4 5.211.4 SA-IDM-15F3 6.310.6 5.lt0.5 6.410.5 5.510.6 5.811.2 SA-IDM-16F2 5.310.3 4.510.3 5.310.3 4.210.4 4.811.1 SA-IDM-lG3 (C) 6.710.4 5.210.4 6.510.4 5.110.4 5.921.7 SA-IDM-3G1 (C) 4.910.4 5.010.4 5.910.4 5.010.4 5.210.9 SA-IDM-10G1 (C) 6.010.5 5.110.5 6.010.6 5.010.4 5.511.1 SA-IDM-16G1 (C) 6.410.6 5.210.3 6.510.5 5.210.5 5.811.4 SA-IDM-3H1 C 6.010.5 4.910.2 5.810.4 5.010.4 5.421.1 SA-IDM-3M3 C 6.210.4 4.910.3 5.710.3 4.510.2 5.311.5 AVERAGE 5.611.0 4.611.0 5.811.2 4.6tl.1 GRAND AVERAGE 5.111.5

• The standard month = 30.4 days.

(C) Control station 95

TABLE C-9 1987 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mead / standard months i 2 sigma (Results by Teledyne Isotopca)

STATION ID JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 6.810.8 5.610.3 6.610.2 5.810.4 5.410.3 6.510.6 SA-IDM-SS1 5.810.4 5.010.2 5.910.3 5.110.2 4.610.1 5.910.5 SA-IDM-6S2 6.110.3 5.310.3 6.410.4 5.810.4 5.110.3 6.210.5 SA-IDM-7S1 7.110.6 6.510.4 7.310.6 6.610.5 6.310.6 7.510.7 SA-IDM-10S1 6.610.5 5.910.3 5.910.2 6.210.4 5.610.7 7.411.0 SA-IDM-llS1 5.910.4 4.Eto.3 5.810.3 5.510.4 5.310.6 7.311.2 SA-IDM-SD1 6.210.6 5.110.3 6.210.5 5.510.6 5.010.3 6.210.4 SA-IDM-10D1 6.410.7 5.410.8 6.910.4 5.910.3 5.410.4 6.710.5 SA-IDM-14D1 6.410.7 5.610.3 6.710.5 6.110.3 5.210.3 6.610.4 i SA-IDM-2El 6.110.3 5.310.2 6.110.4 5.510.4 4.310.3 6.410.5 SA-IDM-3E1 6.210.9 5.110.2 6.010.4 5.310.2 4.810.0 6.310.2 q3 SA-IDM-13E1 6.110.4 5.210.3 6.010.4 5.510.5 4.810.4 6.010.5 Ch SA-IDM-16El 6.410.2 5.510.4 6.410.5 5.810.5 5.210.3 6.510.5 SA-IDM-1F1 6.210.6 5.610.4 6.510.4 5.910.5 5.510.4 6.610.5 SA-IDM-2F2 5.410.3 4.910.2 5.5t0.3 5.010.3 4.210.3 5.210.2 SA-IDM-2F6 6.310.4 5.510.3 6.210.? 5.610.4 5.110.5 5.810.6 SA-IDM-5F1 5.710.4 5.110.2 6.710.6 5.310.4 -5.010.3 6.010.3 SA-IDM-6F1 5.310.1 4.610.4 5.4t0.3 4.910.5 4.310.2 5.3io.3 SA-IDM-7F2 5.110.2 4.210.2 4.910.3 4.Sio.1 4.010.1 5.0io.3 SA-IDM-11F1 6.610.7 5.810.4 6.710.4 6.110.5 5.710.4 6.910.4 SA-IDM-13F4 6.610.7 5.310.3 6.510.4 5.910.5 5.310.4 6.410.3 SA-IDM-3G1 (C) 6.511.0 5.510.4 6.410.3 5.910.4 5.510.5 6.810.5 SA-IDM-3H1 (C) 5.910.7 5.810.1 6.610.2 6.310.1 5.610.2 6.710.4 SA-IDM-3H3 (C) 7.110.5 6.410.5 7.010.5 6.510.4 5.710.5 6.910.7 AVERAGE 6.211.0 5.411.0 6.311.1 5.711.0 5.111.1 6.411.3 l

, . - - = .

TABLE C-9 (cont'd) 1987 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad / standard montha i 2 sigma (Results by Teledyne Isotopes)

STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 6.210.7 6.010.5 6.310.4 6.810.3 6.710.8 6.610.3 6.311.0 SA-IDM-SS1 5.610.4 5.3t0.3 5.810.3 5.910.2 5.710.6 6.010.6 5.510.9 SA-IDM-6S2 6.410.7 5.910.4 6.Sio.3 5.610.5 6.011.1 6.610.5 6.1 1.0 SA-IDM-7S1 7.310.5 6.810.5 7.310.6 7.510.6 7.310.2 8.010.6 7.111.0 SA-IDM 10S1 7.511.3 6.310.4 7.010.7 7.610.7 7.310.9 7.811.1 6.811.5 SA -IDM- 11S1 9.012.4 5.910.5 7.2 0.7 8.511.1 8.4i0.8 9.811.6 6.91?.3 SA-IC3-5D1 6.210.5 5.710.4 6.410.4 6.310.4 SJ.-IDM-10D1 6.3 0.4 6.510.3 6.011.0 6.710.5 6.210.6 6.510.4 7.010.5 6.510.8 6.710.4 6.411.1 SA-IDM-14D1 7.811.5 6.410.5 6.910.5 6.910.7 6.910.7 6.8 0.6 6.511.3 SA-IDM-2El 6.310.5 5.910.4 6.410.4 6.310.7 5.910.9 6.610.4 5.911.3 SA-IDM-3El 6.010.7 5.7i0.3 6.110.5 6.310.4 6.010.3 6.010.1 5.811.0 y) SA-IDM-13E1 6.210.5 5.8iO.4 5.910.3 6.310.5 6.oio.6 6.110.5

-J 5.810.9 SA-IDM-16El 6.510.7 6.110.5 6.510.4 7.010.7 6.210.5 6.910.6 6.2 1.1 SA-IDM-lF1 6.810.5 6.2io.4 5.410.5 6.910.6 6.510.6 6.7io.5 6.211.0 SA-IDM-2F2 5.610.2 5.210.2 5.410.3 5.710.3 5.210.5 5.5 0.6 5.210.8 SA-IDM-2F6 5.310.5 6.010.5 6.410.3 3.610.2 5.910.7 6.610.3 5.911.0 SA-IDM-5F1 6.410.6 5.710.4 6.310.7 6.410.2 5.910.4 6.410.5 5.911.1 SA-IDM-6F1 5.810.4 5.110.3 5.710.5 5.810.3 5.410.2 5.510.3 5.210.9 SA-IDM-7F2 5.110.3 4.510.2 5.210.2 5.2io.2 5.010.5 5.310.2 4.810.8 SA-IDM-llF1 7.210.6 6.610.6 7.010.4 7.110.5 6.610.4 7.110.7 6.611.0 SA-IDM-13F4 6.910.6 6.210.4 6.410.5 6.710.0 7.411.1 6.610.7 6.311.2 SA-IDM-3G1 (C) 6.9io.6 6.410.4 6.810.4 6.810.3 6.510.8 6.510.5 6.411.0 SA-IDM-3H1 (C) 6.611.0 6.410.3 7.110.3 7.110.2 6.510.4 6.810.6 6.411.0 SA-IDM-3H3 (C) 7.110.6 6.670.6 6.610.7 7.110.3 5.910.2 6.510.7 6.610.9 AVERAGE 6.6il.7 6.011.1 6.4il.2 6.711.4 6.311.5 6.711.8 GRAND AVERAGE 6.111.6

• The standard month = 30.4 days.

(C) Control station l

I l

TABLE C-10 1987 CONCENTRATIONS OF 10 DINE-131* IN MILK **

Results in Units of pCi/L STATION 10*** JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 <0.4 <0.4 <0.7 <0.4 <0.4 <0.4

- - - <0.6 <0.5 <0.5 SA-MLK-ZF7 40.6 <0.4 <0.5 <0.6 <0.5 <0.5

<0.4 <0.5 <0.7 SA-MLK-5F2 <0.6 <0.6 <0.4 <0.5 <0.7 <0.6

<0.5 <0.6 <0.6 SA-MLK-11F3 <0.6 <0.5 <0.4 <0.3 <0.3 <0.5

<0.5 <0.E <0.4 5A-MLK-14F1 <0.4 <0.5 <0.7 <0.8 <0.5 <0.4

<0.3 <0.5 <0.6 5A-MLK-3G1 <0.6 <0.6 <0.5 <0.5 <0.5 <0.4 (Control) - - -

40.5 <0.5 <0.7 ND C7 STATION ID*** JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 <0.7 <0.5 <0.6 <0.5 <0.6 <0.6

<0.7 <0.5 <0.7 <0.4 <0.6 -

SA-MLK-2F7 <0.6 <0.6 <0.6 <0.5 <0.6 <0.7

<0.4 <0.4 <0.5 <0.6 <0.6 -

5A-MLK-5F2 <0.6 <0.7 <0.5 <0.5 <0.8 <0.5

<0.5 <0.6 <0.4 <0.6 <0.7 -

SA-MLK-11F3 <0.5 <0.4 <0.5 <0.5 <0.8 <0.8

<0.5 <0.5 <0.5 <0.5 <0.4 -

SA-MLK-14F1 <0.8 <0.5 <0.4 <0.5 <0.6 <0.6

<0.7 <0.8 <0.7 <0.7 <0.6 -

SA-MLK-3G1 <0.5 <0.5 <0.6 <0.5 <0.5 <0.6 (Control) <0.4 <0.5 <0.5 <0.6 <0.6 -

• I-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.

• • • Sampilng dates can be found in Table C-13.

S 4

• f TABLE C-ll 1987 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN MILK **

Results in Units of pCi/L i 2 sigma STATION ID SAMPLING PERIOD Sr-89 Sr-90 f

SA-MLK-13E3 07/05-06/87 <l.1 1.710.4 SA-MLK-2F7 07/05-06/87 <2.6 4.110.9 SA-MLK-5F2 07/05-06/87 <l.9 3.710.7 SA-MLK-llF3 07/06-07/87 <l.5 <l.3 SA-MLK-14F1 07/06-07/87 <l.0 1.710.4 SA-MLK-3G1 07/05-06/87 <l.4 3.4 0.5 (Control)

AVERAGE -

2.612.4

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

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

99

~'

TA8LE C 12

.1987 CONCENTRAi!ONS OF GAMMA EM1TTER$* IN MILK J

-Results in Units of PC1/L 2 sigma V

STATION 10** NUCLI0E JANUARY FEBRUARY MARCH MONTHLY MONTHLY' MONTHLY 5A MLK-13E3 K 40 1400 92 1400 76 1400 9<

Mn 54 <3.4 <2.2 <3.1 Cs 134 <3.9 <3.3 <3.6 Cs-136 <4.0 <3.2 <4.0 Cs-137 (4.1 2.321.3 <3.8 Ra-226 <6.6 c5.5 c6.6 Th-232 <15 <10 <!3

• {

SA MLK-2F7 K-40 1300 90 1300292 1300292  !

Mn-54 <2.8 <3.5 <3.4 Cs-134 <3.2 <3.9 <3.8 Cs-136 (4.0 <4.0 <3.8 Cs-137 <3.6 (4.4 (3.5 Ra-226 <6.6 <8.0 <7.0 t Th-232 114 <15 <13  ;

1A MLK-5F2 K-40 1300t94 1200t?3 1300t78 Mn-54 <3.4 <2.9 <5.8 Cs-134 . <5.6 <2.7 <3.6 t 2

Cs-136 <3.5 <4.0 <5.3 ,

Cs 137 <4.7 6.722.2 <5.0 l Ra-226 <7.1 <7.9 <9.6 Th-232 (16 <14 <14

, i 5A MLK-11F3 K-40 1400 78 1400 75 1200 72 '

Mn-54 <2.9 <2.7. <2.5 Cs-134 <2.7 <3.0 <2.9 Cs-136 <3.0 <2.9 <2.7 I Cs 137 <4.0

' <2.9 <3.0 i Ra-226 <7.0 <5.5 <5.9  !

Th 232 <2.7 <11 <9.8

~

)

~

$A-MLK-14F1 K-40 1400277 1400192 1300 81 Mn-54 <2.6 <3.1 <2.7 >

Cs-134 <2.7 <3.5 <3.2 Cs-136 <2.9 <3.7 <3.5

Cs 137 <2.7 <3.8 (4.1 *

"

:!!!  :!6'  :!i ';ii

i SA kLK-3G1 K-40 1300 72 1400293 1200 72 j

, (Control) Mn 54 <2.6 <3.8 <2.3 -

Cs-134 <2.9 <3.5 <3.0 t Cs-136 <3.0 <3.5 <2.6 i Cs-137 <3.0 <3.6 2.721.4

• Ra 226 <5.9 <7.0 <5.9 Th-232 <10 <13 <10 i

i

. AVERAGE K-40 1400:110 1400:170 1300:150 t I

L 100 f m- %, _. -- m -,..

y _

l

.,y . :,f TABLE C-12 (cont'd.)

i 1987 CONCENTRAi!CNS OF GAMMA EMITTER $* IN MILK [

Results in Units of pCl/L 2 sigma j

$TATION 10** NUCLIDE APRIL MAY JUNE SEMI-MONTHLY $EMI-MONTHLY SEMI MONTHLY I

a

. SA-MLK-13E3 K-40 1500:100 1400291 1400195 1500*91 1400281 1400 77

, Nn-54 <3.7 <3.1 <3.4 <3.7 <2.8 <3.6 Cs-134 <3.9 <4.7 <4.9 <3.8 <3.8 <2.9 Cs-136 <5.1 <3.4 <4.3 <4.2 <3.6 <3.4 Cs-137 <4.4 <4.2 <3.3 <4.2 <3,7 <3.1 ,

Ra-226 <8.0 47.0 <7.9 <7.7 <8.1 <7.4 Th 232 <!4 <!! <13 <16 <15 <!3 ,

SA-MLK-2F7 K-40 1300 46 1300tS9 1400194 1300273 1400t92 1400t93 -

Mn-54 <3.3 <4.3 <3.6 <3.6 <4.1 <2.9 '

Cs-134 <3.8 <3.3 44,0 <2.7 <3.5 <3.9 Cs-136 <3.9 <3.5 <3.5 <4.5 <4.2 <3.4 Cs-137 <3.9 <3.9 (4.2 <3.4 <3.9 <4.1 Ra-226 <7.8 <6.5 <8,4 <6.2 <7.2 <7.6 f Th-232 <!3 <12 <12 <16 < 13 - <10

$A-MLK-5F2 K-40 1200290 1300:91 1200273 1300175 1300275 1400 7?

i Mn-54 <3.2 <3.3 <3.3 <2.4 <2.4 <2.6 Cs-134 <4.1 <4.3 <3.5 <2.1 *2.4 4.1 2.0 Cs-136

. <4.1 <3.8 44.6 <3.f 3.121.8 <2.4 i Cs-137 <3.9 4.222.4 <3.1 <3.9 6.012.4 6.012.1 Ra 226 47.4 <8.1 <7.5 <7.6 <8.9 <6.2 Th-232 <12 (15 <11 <!4 <15 <12 i

$A MLK-11F3 K-40 1300279 1300:72 1400273 1300270 1300275 1300271  !

Mn-54 <2.9 <2.2 <2.6 <2.6 <3.5 <2.5  ;

Cs-154 <3.4 <2.7 <3.6 <2.6 <2.8 <3.0 t Cs 136 <3.7 <3.0 <2.9 <2.6 <2.9 <2.5  ;

Cs-137 <3.1 <3.1 <3.1 2.721.5 <3.0 <3.5 '

Ra-226 (8.2 (6.1 <6.9 <7.5 <8.0 <6.5 Th 232 <14 <12 <11 <10 <13 <9.4 i

SA MLK-14F1 K-40 1200274 1400272 1300189 1300271 1400t93 1300274 l Mn-54 <3.5 <3.7 <2.8 <2.1 <3.2 <3.3 Cs-134 <2.5 <2.6 <3.2 <2.2 <3.3 <2.5 l j Cs-136 <3.8 <3.6 <5.0 >2.7 <3.6 <2.9 Cs-137 <4.1 <2.6 <3.4 <3.6 <3.4 <3.6 i

' Ra-226 <7.9 <6.4 <5.8 5.9 3.5 <6.1 <8.2 Th-232 <17 <10 <15 <9.9 <12 <15 i

I

$A-MLK-3G1 K-40 1300 92 1300t71 1200 73 1300271 1300t91 1300294 I (Control) Mn-54 <3.4 <2.6 <4.0 <3.4 <3.3 <4.3  ;

Cs-134 <4.1 <2.4 <2.9 <3.6 <3.6 <3.6 f Cs-136 <3.8 <3.0 <3.7 <3.0 <5.8 (4.0 1 Cs-137 '

<3.8 <3.3 <4.1 <2.8 <3.9 <4.3

Ra-226 (6.6 <6.5 <1.1 <6.0 <6.5 <7.5

< Th 232 <13 <11 <11 <9.2 <18 <18  ;

i -

j AVERAGE K-40 1300:220 13002100 1300tt00 1300:160 1400:110 1400:110 b

101

~*

• TABLE C-1E (cont'd.)

1987 CONCENTRATIONS OF GAMKA EMITTER $* IN MILK Results in Units of pct /L t 2 sigma STATION ID** NUCL10E JULY AUGUST SEPTEMBER SEMI. MONTHLY $ENI-MONTHLY SEMI-MONTHLY

$A-MLK-13E3 K-40 1400t73 1500t14 1400272 1400274 1300281 1400 84 Mn-54 <2.7 <2.4 <2.7 <2.5 <2.6 <2.4 Cs-134 <3.3 <3.4 <3.1 <3.2 <3.8 <3.4 Cs-136 <3.6 <3.1 <3.2 <3.1 <4.0 <3.3 Cs-137 <2.4 <3.4 <3.3 <3.1 <3.9 <3.2 Ra-226 <1.0 <4.6 <4.9 <6.5 <6.1 <7.9 Th-232 (7.9 <12 <8.1 <11 <11 <15

$A-MLK-2F7 K-40 1400282 1400t93 1400182 1300281 1200268 1300282 Mn 54 <2.7 <4.7 (3.5 <2.9 <2.2 <3.6 Cs-134 <3.5 <5.0 <3.5 <3.7 <3.6 <3.6 Cs-136 <3.5 (5.1 <4.1 <3.9 <3.5 <4.2 Cs-137 <3.9 (4.4 <3.3 <4.4 <3.2 <3.7 Ra-226 <7.0 <8.1 <7.5 <7.8 <6.9 <7.3 Th-232 <15 <15 <14 <!4 <11 <16

$A-MLK-5F2 K-40 1300294 1400t91 1400272 1300271 1300t71 1300270 Mn-54 <4.7 <3.4 <2.3 <2.5 <2.3 <2.2 Cs-134 <4.0 <3.7 <2.6 <2.7 <2.3 <2.7 Cs-136 <5.0 <3.5 <4.3 <2.5 <3.6 <2.5 Cs-137 4.122.1 <4.1 4.222.0 <2.7 4.222.1 3.622.0 Ra 226 <7.1 <7.5 <6.2 <7.2 <4.5 <6.2 Th-232 <15 <13 <7.8 <10 <12 49.5

$A-MLK-11F3 K-40 1300275 1300 80 1500286 1400 82 1400276 1300 82 Mn-54 <2.4 <3.6 <3.8 <2.9 <4.8 <3.7 Cs-134 <3.1 <3.5 <3.1 <3.9 <2.2 <3.3 Cs-136 <3.4 <4.7 <3.1 <3.5 <3.9 <3.8 Cs-137 <3.7 <3.1 <4.4 <2.9 3.021.6 <4.4 Ra 226 <7.3 <6.8 47.5 <7.4 <8.2 <7.4 Th-232 <13 <!3 <!4 <15 <14 <13

$A-MLK-14F1 K-40 1300t81 1300t79 1400273 1400272 1400 95 1300 71 Mn-54 <2.9 <4.2 <2.5 <2.4 <3.8 <2.6 Cs-134 <3.8 <3.6 <3.2 (2.9 <4.7 <2.5 Cs-136 <3.3 <3.2 <3.3 <3.4 44.2 <2.7 Os-137 <3.9 <3.4 <3.2 <3.2 (4.2 <2.8 Ra-226 <7.2 <7.5 8.4t3.8 (6.4 <8.4 <6.9 Th-212 <15 <14 <9.9 <8.8 <15 <9.1 SA MLK 3G1 K-40 1300289 1300180 1300180 1400282 1300270 13's0t 70 (Control) Mn-54 <3.2 <3.1 <3.1 <3.0 <2.5 <2.6 Cs-134 <3.9 <3.5 <3.8 <3.3 <2.7 <2.6 Cs-136 <4.3 <3.3 <4.6 <3.5 <d.1 <2.7 Cs-137 <3.6 <3.4 <3.1 <3.4 <2.6 <2.5 Ra-226 <6.2 <8.1 <5.9 <6.5 <6.0 <6.2 l Th 232 <13 <14 <14 <12 <9.8 <9.7 l

l AVERAGE K-40 13002100 1400:160 1400:130 1400:100 13001150 1300182 I

102

TABLE C 12 (cont'd.)

s 1987 CONCENTRATIONS OF GAMMA EMITTER $* IN MILK Results in Units of pct /L 2 2 sigma I STATION 10** NU;L10E OCf08ER NOVEM8ER DECEMBER AVERAGE.

SEMI-MONTHLY SEMI-MONTHLY MONTHLY a-c SA MLK-13E3 K-40 1400281 1500275 1500:100 1400:02 1300273 Mn-54 1400:120

<2.7 <2.8 <3.5 <3.4 < 2. 4 - -

Cs 134 <3.4 <3.3 <5.1 <3.8 <2.2 -

Cs-136 <3.1 <3.0 <4.3 <4.5 <3.0 -

Cs-137 <3.1 3.2tl.8 <4.9 <3.8 <3.2 -

Ra 226 (6.9 7.7 4.3 <7.6 <7.8 <5.4 -

Th-232 14t8 1427 1327 <!! c12 -

SA MLK-2F7 K-40 1400273 1300tB0 1400t96 1400t71 1300t82 1300:120 Mn-54 <3.9 <3.3 <4.1 <2.5 <3.6 -

I Cs-134 <3.7 <3.7 (5.1 <2.8 <3.4 -

Cs-136 <5.0 <4.1 <4.0 <2.4 <3.2 -

Cs-137 <3.6 <3.2 <4.0 <3.0 <3.1 -

, Ra-226 <8.1 <8.2 <6.5 <5.9 <7.1 -

Th 232 <13 <16 <17 <11 <!! -

t 1 t l

SA MLK-5F2 K-40 1300 71 1300270 1300270 1200277 1300t70 Mn 54 1300:120 [

a

<2.7 <2.0 <2.7 <2.7 <2.3 -

Cs-134  :

<2.6 <3.5 <2.6 <3.3 <2.7 - t Cs-136 <2.8 <3.2 <2.9 <2.9 <2.7 -

Cs 137 <2.7 3.4 1.9 <2.4 <4.1 <3.2 -

Ra-226 <6.0 <6.2 <5.5 8.524.2 <5.9 -

Th-232 49.2 <!2 <11 <13 <10 -

l

$A MLK-11F3 K-40 1400 73 1500t74 1500285 1300272 1300271 14002160 Mn-54 <2.5 <2.5 (4.2 <2.2 <2.5 -

. Cs-134 <3.7 <3.4 (3.0 (2.3 <2.9 -

r i

Cs-136 <2.8 <3.6 <3.4 <2.8 <3.4 -

[

Cs-137 <3.3 <3.7 <3.7 <2.5 <2.4 -

4 Ra-226 <6.6 (6.6 <8.1 <6.2 <4.4 -

' Th 232 ell <11 <12 <10 <11 -

k

$A-WLK-14F1 K-40 1300281 1300280 1500274 1300271 1300t76 Mn-54 1300:140  !

<3.7 <2.9 <2.3 <2.7 6.5 2.4 -

Cs 134 <3.4 <3.2 <2.5 4.922.3 <3.3 -

Cs-136 <3.3 <3.3 <3.0 <3.6 <4.8 -

Cs 137 <4.3 <3.4 <2.F (2.1 3.121.8 -  !

Ra-226 c6.4 <6.5 <6.0 <6.4 <1.7 -

Th-232 l

, <13 <13 <11 59.3 <!1 - "

$A MLK-3G1 K-40 1300279 1200 78 1400273 1300 81 1300 80 1300:110 '

(Control) Mn-64 <3.5 <3.1 <2.8 <2.8 <3.4 -

Cs-134 <3.4 (4.5 <3.2 <3.6 <3.1 -

y Cs-136 <4.2 <4.0 <2.6 <3.5 <3.8 -

Cs-137 <4.1 <3.3 <3.1 <3.0 <2.4 - i Ra-226 <7.4 46.9 <5.1 <6.8 <6.7 -  ;

a Th-232 <13 <13 49.4 <11 <14 -

AVERAGE K-40 1400t110 1400:240 1400:160 1300:150 1300200 1300:150 j

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C 31. l 3 ** Sampilng dates can be found in Table C-13. L 103 i

t

. _. _ .- - ~ ~ _ . ~ _ _ _ . - - .- - -

e TABLE C-13 '

1987 SAMPLING DATES FOR MILK SAMPLES STATION CODE MONTH 13E3 ZF7 SF2 11F3 14F1 3G1 JANUARY 01-04-87 01-04-87 01-03-87 01-05-87 01-05-87

~

01-04-87 to to to to . to to 01-05-87 01-05-87 01-05-87 01-06-87 01-06-87 01-05-87 FEBRUARY 02-02-87 02-01-87 01-31-87 02-02-87 02-02-87 102-01-87 to to to to to to 02-02-87 02-02-87 02-02-87 02-03-87 02-03-87 02-02-87 MARCH 03-09-87 03-09-87 03-08-87 03-C8-87 03-08-87 03-09-87 i to to to to to to 03-10-87 03-10-87 03-09-87 03-09-87 03-09-87 03-10-87 APRIL 04-06-87 04-06-87 04-06-87 04-05-87 04-05-87 04-06-87 Se to to to to to to c) 04-07-87 04-07-87 04-07-87 04-06-87 04-06-87 04-07-87

+

04-20-87 04-20-87 04-20-87 04-19-87 04-19-87 04-20-87 to to to to to to 04-21-87 04-21-87 04-21-87 04-20-87 04-20-87 34-21-87 MAY 05-04-87 05-04-87 05-04-87 05-03-87 05-03-87 05-04-87 to to to to to to 05-04-87 05-05-J7 05-05-87 05-04-87 05-04-87 05-05-87  !

05-18-87 05-16-87 05-16-87 05-17-87 05-17-87 05-18-87 1 to to to to to to 05-19-87 05-18-87 05-18-87 05-18-87 05-18-87 05-19-87 JUNE 06-07-87 06-07-87 06-07-87 06-08-87 ~

06-08-87 06-07-87 to to to to to to 4 06-08-87 06-08-87 06-08-87 06-0?-87 06-09-87 06-08-87 06-21-87 06-21-87 06-21-87 06-22-87 06-22-87 06-21-87 to to to to .

to to 06-22-87 06-22-87 06-22-87 06-23-87 06-23-87 06-22-87 l

e*

---

+w m-- -

e-- -v e r-t--w mem-v----rw- .-- -*,w - - - - - - - -- w-- ,-- .--.--v---

TA8LE C-13 (cont'd) .

1987 5AMPLING DATES FOR MILK SAMPLES STATION CODE MONTH 13E3 2F7 5F2 11F3 14F1 3G1 JULY 07-05-87 07-05-87 07-05-87 to 07-06-87 07-06-87 07-05-87 to 07-06-87 to to to 07-06-87 07-06-87 07-07-87 tc 07-07-87 07-06-87 07-19-87 07-19-87 07-19-87 to 07-20-87 07-20-87 07-19-87 to to to to 07-20-87 07-20-87 07-20-87 to 07-21-87 07-21-87 07-20-87 AUGUST 08-02-87 08-02-87 08-02-87 to 08-03-87 08-03-87 08-02-87 to to to 08-03-87 08-03-87 to to 08-03-87 08-04-87 08-04-87 08-03-87 08-16-87 08-16-87 08-16-87 to 08-17-87 08-17-87 08-16-87 to to to 03-17-87 to to 08-18-87 08-17-87 08-18-87 08-18-87 08-17-87

p. SEPTEM9ER 09-07-87 09-07-87 09-07-87 c3 to 09-08-87 09-08-87 09-07-87 om to to to 09-08-87 09-08-87 to to 09-08-87 09-09-87 09-09-87 09-08-87 09-21-87 09-21-87 09-21-87 09-21-87 to to 09-20-87 09-21-87 to to to 09-22-87 09-22-87 09-22-87 09-21-87 to 09-22-87 09-22-87 OCTOBER 10-05-87 10-05-87 10-05-87 to 10-05-87 10-05-87 10-05-87 to to to 10-06-87 10-06-87 to to 10-06-87 10-06-87 10-06-87 10-06-87 10-19-87 10-17-87 10-17-87 10-19-85 to to 10-19-87 10-19-87 to to 10-20-87 to to 10-19-87 10-19-87 10-20-87 10-20-87 10-20-87 NOVEMBER 11-02-87 10-31-87 10-31-87 11-01-87 to to 11-01-87 10-31-87 to to 11-0?-87 to to 11-02-87 11-02-87 11-02-87 11-02-87 11-02-87 11-16-87 11-16-87 11-16-87 11-16-87 to to 11-16-87 11-16-87 to to 11-17-87 to to 11-17-87 11-17-87 11-17-87 11-17-87 11-17-87 DECEMBER 12-06-87 12-06-87 12-06-87 to 12-07-87 12-06-87 12-07-87 to to to 12-07-87 to to 12-07-87 12-07-87 12-08-87 12-07-87 12-07-27

l TABLE C-14 1987 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L i 2 sigma STATTON TD

• RADIOACTIVITY 01-12-87 02-09-87 03-16-87 04-13-87 05-11-87 06-15-87 SA-WWA-?R1 Alpha 0.9 0.8 0.610.6 <1.0 <1.2 <l.7 <l.5 Beta 3.4i0.8 2.8 0.7 6.6 0.9 9.0 1.1 4.4 0.9 5.0 1.0 K-40 2.9 0.3 3.3 0.3 7.4 0.7 8.5 0.9 6.5 0.7 6.2 0.6 H-3 <130 <l50 <150 <140 <150 <140 SA-WWA CD1

Alpha 1.2 0.9 <1.0 <1.1 1.5 1.2 <1.8 <l.6 m Beta 12 1 13 1 12 1 1311 12 1 15 1 K-40 1411 14il 14il 11 1 14 1 14 1 H-3 <130 <l50 <150 <140 <l60 <140 _

SA-WWA-3E1 -

(Control)

Alpha <0.7 <0.6 <1.1 <1.2 <1.8 <1.6 Beta 9.6 1.1 9.2 1.1 8.3 1.0 7.2 1.0 8.4 1.1 9.9 1.2 K-40 9.1 0.9 9.3 0.9 9.6 1.0 7.4 0.7 8.9 0.9 10i1 H-3 <140 <150 <150 <140 <150 <140 AVERAGE Alpha 0.9 0.5 - - - - -

Beta 8.3 8.9 8.3 10 9.0 5.5 9.715.9 8.317.6 10 10 K-40 8.7 11 8.9 11 10 7 9.0 3.7 9.8 7.7 10 8 H-3 - - - - - -

4 TABLE C-14 (cont'd) 1987 CONCENTRATIONS 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 07-13-87 08-10-87 09-14-87 10-13-87 11-09-87 12-14-87 AVERAGE RA-WWA-2S3 Alpha <1.1 <2.0 <l.8 1.2i0.9 <l.0 <l.4 -

Beta 7.011.1 3.610.9 6.011.2 8.0 1.2 4.411.0 1.610.4 5.1 4.4 K-40 6.1 0.6 4.6 0.5 4.210.4 6.710.7 3.010.3 4.2 0.4 5.3 3.7 H-3 <140 <140 <140 <140 <150 <l50 -

RA-WWA-5D1 y; Alpha <1.1 <2.2 <2.2 1.1 1.0 <1.0 <l.6 -

-a Beta 1211 1211 1712 1712 1812 6.4i0.6 13 6 K-40 1311 14 1 1211 1311 1411 1211 13 2 H-3 <l40 <130 <l50 <150 <150 <140 -

RA-WWA-1El (Control)

Alpha <l.1 <2.2 <2.1 0.810.7 <1.0 <l.8 -

Beta 10 1 8.0 1.1 1211 1111 1211 4.810.6 9.2 4.1 K-40 9.010.9 10 1 8.810.9 9.0 0.9 10 1 8.210.8 9.111.5 H-3 <140 <140 <l50 <140 <150 <l50 -

AVERAGE Alpha - - -

1.010.4 - - -

q Beta 9.7 5.0 7.918.4 12111 1219 11 14 4.3 4.9 9.2 8.3 K-40 9.4 6.9 9.519.4 8.3 7.8 9.6 6.4 9.0 11 8.117.8 9.2i7.0 ,

H-3 - - - - - - -

• Station SA-WWA-2S3 was collected on 04-14-87.

• • Station SA-WWA-3El was collected on 09-15-87.

TABLE C-15 1987 CONCENTRATIONS OF GAMMA EMITTERS

• IN WELL WATER Results in Units of pCi/L i 2 sigma ETATION TD **

NUCLIDE 01-12-87 02-09-87 03-16-87 04-13-87 05-11-87 06-15-87 MA-WWA-2S3 K-40 <38 <29 <32 <29 <30 <30 Ra-226 5.9 2.9 <5.3 1513 42 4 15 3 8.9 2.9 Th-232 <8.8 <6.2 <8.5 9.614.0 <7.3 <7.0 RA-WWA-SDI F' K-40 38116 37115 <32 31 15 31117 <39 S$ Ra-226 5615 2213 9315 5114 12016 <7.9 Th-232 <8.0 <8.4 <9.3 <8.6 <10 <9.5 RA-WWA-3E1 (Control)

K-40 <22 <42 <41 <45 <46 <44 Ra-226 1212 110 6 7815 200 8 17 7 160 7 Th-232 <4.9 <10 <8.9 <8.9 <10 <8.8 AVERAGE K-40 - - - - - -

Ra-226 25155 461112 62 83 98 177 511120 591175 Th-232 - - - - - -

~

i J

- - ,,, ,~ - - , . , , . . -

o.

O O .

TABLE C-15 (cont'd) 1987 CONCENTRATIONS OF GAMMA EMITTERS

• IN WELL WATER Results in Units of pCi/L 2 sigma RTATION ID ***

NUCLIDE 07-13-87 08-10-87 09-14-87 10-13-87 11-09-87 12-14-87 AVERAGE RA-WWA-2R1 K-40 <29 <30 <30 <30 <35 29114 -

Ra-226 1313 6.3 2.5 7.212.6 16 3 <4.7 7.112.8 Th-232 <8.0 12 20

<7.0 <7.8 <5.7 <7.4 6.9 3.8 -

w RA-WWA-5DI 4 E$ K-40 41117 <41 <34 24114 27115 <42 Ra-226 8615 4014 35112 4214 <4.6 3.712.0 100 6 52 80 Th-232 <8.3 <7.8 <9.0 <6.6- <6.1 <8.0 -

RA-WWA-3El (Control)

K-40 <46 21112 <40 <43 '35 15 <34 -

Ra-226 14017 5.812.7 7215 4314 22 3 13016 Th-232 <9.8 821130

<6.6 <9.6 <9.3 <5.6 <8.2 -

AVERAGE K-40 - - - -

32 9 - -

Ra-226 801127 17 39 40165 21 39 10120 79 128 Th-232 - - - - -

491104

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

Station SA-WWA-2S3 was collected on 04-14-87.

Station SA-WWA-3El was collected on 09-15-87

TABLE C-16 1987 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L ! 2 s'igma

~

.i 01-12-87 04-13-87** 07-13-87 ' 10-13-87 STATION TD to to to to NUCLIDE 03-16-87 06-15-87 . 09-14-87*** 12-14-87 SA-WWA-7R1 Sr-89 <0.6 <0.6 <0.7 <0.8 Sr-90 <0.5 <0.5 <0.7 <0.6 r

^

$ RA-WWA 85D1 Sr-89 <0.7 <0.5 <0.5 <0.8 Sr-90 <0.5 <0.4 <0.4 <0.6 sA-WwA-1r1 (Control)

Sr-89 <0.6 <0.5 <0.5 <0 . 6 Sr-90 <0.5 <0.4 <0.4 <0.5

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

• • Station SA-WWA-2S3 was collected on 04-14-87.

• • • Station SA-WWA-3El was collected on 09-15-87.

4 6*

,-.,-v ..,-------,,.-mm e, ,n- - , - --c, .,--m- ,-- - - - ~ , - ,, , , , , -, - r-- c..,r--.vw n - , --

, s - - , . . - - - --.-.n-.--,-..-w - , . , - -

TABLE C-17 1987 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERSo POTASSIUM-40 "

AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION ID: SA-PWR/T-2F3 Results in Units of pC1/L i 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE Alpha (Raw) <0.9 <1.2 <1.1 <1.8 <1.6 (1.1 -

(Treated) (0.6 <1.1 1.010.8 <1.7 <1.5 <1.1-Beta (Raw) 3.610.8 3.610.7 3.210.7 2.610.7 3.110.7 2.610.8 (Treated) 2.910.7 3.110.7 1.710.6 2.510.6 3.010.7 2.810.8 K-40 (Raw) 2.110.2 2.110.2 1.410.1 1.810.2 i 2.010.2 1.410.1 (Treated) 1.810.2 2.110.2 1.610.2 1.710.2 2.410.2 1.5 0.1 H-3 (Raw) (130 <140 <l50 <150 (150 '<140 (Treaced) (130 (170 <150 <150 <150 <140 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE l

Alpha (Raw) <1.3 <1.5 0.910.7 <1.0 (1.4 <1.8 -

(Treated) <l.2 <1.3 0.810.7 <0.9 <1.4 <l.8 -

2 l Beta (Raw) 2.210.8 3.610.9 3.010.8 3.310.8 2.310.8 3.910.9 3.111.1 (Treated) 2.210.8 2.010.7 3.110.8 2.110.7 2.610.8 2.410.8 2.510.9 K-40 (Raw) 1.410.1 1.810.2 1.510.2 1.410.2 1.720.2 1.910.2 1.710.6 (Treated) 1.410.1 1.910.2 1.410.1 1.310.1 1.710.2 1.810.2 1.710.6 H-3 (Raw) (140 (140 <140 (140 (150 (150 -

(Treated) (150 <140 (140 <140 <150 (150 -

l

.-- - . _ _ _ _. - . ~ . . . . _ . _ . - - . - _

= --. .-_ -. . .. . _ - . . , _ - . . . = = _ . - - _

. _ . . - - . - . . 7 TABLE 18 1987 CONCENTRATIONS OF GAMMA EMITTERS

• IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L 2 sigma STATION ID 01-01-87 02-01-87 03-01-87 04-01-87 05-01-87 06-01 to to to to to to NUCLIDE 01-31-87 02-28-87 03-31-87 04-30-87 05-31-87 06-30-87 SA-PWR-2F1 K-40 <20 <32 <41 <42 <29 <33 Ra-226 2.6 1 6 <4 0 <4.8 <4.9 3.9 2.1 <5.8 Th-232 <5.5 5.4!3.9 <8.2 <6.9 <5.7 <7.6 SA-PWT-2F3 K-40 31 14 <40 <28 <26 <31 <43 Ra-226 <4.0 <4.7 <5.3 <4.7 <4.8 <4.8 Th-232 <6.2 <9 . 6 <7.7 <7.3 <7.6 <7.1 4 p,

M l

STATION TD 07-01-87 08-01-87 09-01-87 10-01-87 11-01-87 12-01-87

,1 to to to to to to NUCLIDE 07-31-87 08-31-87 09-30-87 10-31-87 11-30-87 12-31-87 SA-PWR-2F1 i K-40 <31 <31 <36 <26 <25 <26 i Ra-226 <4 2 <4 4 <4.4 <3.9 <4.3 <4.6

} Th-232 6.6!3.7 7.1 3.6 <9.1 <4.5 <5.4 <6.9 RA-PWT-2F3 K-40 <40 <28 <26 <38 <34 <30 Ra-226 5.7 2.6 <5.4 <4.7 <S <4.6 <4 . 2 Th-232 <7 . 1 <7.5 <7.4 <6'79 <6.3 9.314.1

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

6

' w w- ne- we e-w-r--ee. e-- rm--v -e r m a e-w-. .--w _-e s,e, -r-em.- ei n -- m e v t--mmr--m1v-*-e-vme-- wr v-t---=-- -

r-w F --

Tw'*-@Wm "r- 9 '-Pw**- CF* Shw2F-**7-WW C 9 m 9 "-

TAELE C-19 ,"

1987 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of pCi/L 1 2 sigma 01-01-87 04-01-87 07-01-87 10-01-87 STATION In to to to to NUCLIDE 03-31-87 06-30-87 09-30-87 12-31-87 SA-PWR-2P1 (Rav)

Sr-89 0.7 0.3 <0.8 <0.7 m Sr-90 <l.3

<0.6 <0.7 <0.6 <1.0 C

SA-PWT-2P3 (Treated)

Sr-89 <0.7 <0.8 <0.7 Sr-90 <1.2

<0.6 <0.7 <0.5 <l.0 Sr-89 results are corrected for decay to sample stop date.

TABLE C-20 1987 CONCENTRATTONS OF GAMMA EMITTERS

• IN VEGETABLES Results in Units of pCi/kg (vet) i 2 sigma COLLECTION STATION ID DATE SAMPLE TYPE K-40 Ra-226 Th-232 SA-FPV-3El 07-29-87 Corn 21001240 <33 <66 SA-FPV-3El 07-29-87 Tomatoes 2100 58 <3.9 <7.2 SA-FPV-3E2** 05-11-87 Asparagus - - -

SA-FPL-lF3 07-28-87 Cabbage 2300 91 <8.0 <l4 SA-FPV-lF3 07-28-87 Peppers 18001270 <44 <100 SA-FPV-lF3 07-28-87 Tomatoes 1700155 <3.2 <7.8 s SA-FPV-2F4 07-29-87 Corn 2200 220 <30 <52

% SA-FPV-5F1 07-28-87 Peppers 2100 240 <45 66 39 SA-FPV-5F1 07-28-87 Tomatoes 2500 61 2.7 1.6 <5.5 SA-FPV-14F3 07-28-87 Corn 2200 250 <36 <77 SA-FPV-14F3 07-28-87 Tomatoes 1600144 <2.6 <5.5 SA-FPV-lG1 (C) 07-28-87 Corn 2000123. <38 <84 SA-FPV-lG1 (C) 07-28-87 Peppers 1800 250 56 33 <68 SA-FPV-lG1 (C) 07-28-87 Tomatoes 2000164 <3.4 <8.2 SA-FPV-2G1 (C) 05-05-87 Asparagus 1900 260 35 20 <62 SA-FPL-3HS (C) 07-28-87 Cabbage 2300il10 <8.2 <20 SA-FPV-3H5 (C) 07-28-87 Corn 2400!230 <40 <64 SA-FPV-3HS (C) 07-28-87 Peppers 1400i200 <26 <53 SA-FPV-3H5 (C) 07-28-87 Tomatoes 1900 57 <3.2 <8.0 AVERAGE 2000 570 - -

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

• • Sample lost during analysis.

(C) Control Station Y

TABLE C-21 1987 CONCENTRATIONS OF GAMMA EMITTERS

• IN BEEP AND GAME Results in Units of pCi/kg (vet) i 2 sigma COLLECTION STATION ID DATE(S) SAMPLE TYPE K-40 SA-FPB-3E1 01-19-87 Beef 22001220 SA-GAM-11D1 02/14-15/87 Muskrat 2100 170 (Control)

SA-GAM-3E1 01/25-30/87 Muskrat 23001180 AVERAGE Beef 2200 220 Muskrat 22001280 >

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

115

TABLE C-22 1987 CONCENTRATIONS OF GAMMA EMITTERS = IN FODDER CROPS Results in Units of pCi/kg (wet) i 2 sigma COLLECTION STATION ID DATE SAMPLE TYPE Be-7 K-40 Cs-137 Ra-226 Th-232 -

SA-VGT-3E1 10-12-87 Soybeans 160175 110001510 <18 <42 83150 SA-VGT-13E3 09-15-87 Corn Silage 17001390 42001810 <66 170175 <360 SA-VGT-2F7 09-08-87 Corn Silage 2601130 29001350 <28 <60 <94 g SA-VGT-2 F7 11-16-87 Soybeans <110 120001420 21 11 <36 (59 cn SA-VGT-5F2 09-14-87 Corn Silage 7601260 46001620 (55 87 52 (180 SA-VGT-llF3 08-20-87 Corn Silage 4401240 54001510 <47 <66 <97 SA-VGT-11F3 09-09-87 Green Chop 260198 35001340 <17 (44 (80 SA-VGT-llF3 11-01-87 Soybeans (180 140001550 (20 <57 <110 SA-VGT-14F1 10-05-87 Corn Silage 3501150 30001430 <29 <67 <l50 SA-VGT-3G1 (C) 09-10-87 Corn Silage 4101140 51001460 <2G <54 (130 SA-VGT-3G1 (C) 11-01-87 Soybeans <1GO 160001640 (23 <44 (120 AVERAGE 4401910 740019700 - - -

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

(C) Control station

~ \

TABLE C-23 ,

1987 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L 2 sigma STATION ID 01-06-87 02-02-87 03-05-87 04-07-87 05-05-87 06-09-87 SA-SWA-11A1 1.4 1.0 1.4 1.0 <0.9 <1.9 <2.3 <2.2 SA-SWA-12C1 <1.2 1.711.0 <0.8 <l.9 <2.3 <2.1 (Control)

SA-SWA-7El <l.2 0.9 0.8 <0.9 <1.9 <2.3 <2.1 SA-SWA-IF2 <l.2 <1.0 <0.8 <1.9 <2.2 <2.1 sa SA-SWA-16F1 1.3 1.0 <l.1 0.9i0.7 <1.9 <2.3 <2.1 0

AVERAGE -

1.2 0.6 - - - -

STATION ID 07-07-87 08-04-87 09-10-87 10-06-87 11-02-87 12-08-87 SA-SWA-llAl <2.2 <l.6 <1.8 <2.4 <1.2 <l.8 SA-SWA-12Cl <2.2 <l.5 <1.9 <2.3 1.6 1.0 <l.7 (Control)

SA-SWA-7El <2.2 <1.8 <l.9 <l.8 <1.2 <l.7 SA-SWA-lF2 <2.2 <1.5 <l.9 <1.8 <l.1 <l.9 SA-SWA-16F1 <2.2 <l.4 <l.9 <2.5 <l.2 <1.7 AVERAGE - - - _ _ _

TAELE C-24 1987 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATEP Results in Units of PCi/L i 2 sigma STATION ID 01-06-87 02-02-87 03-05-87 C4-07-87 05-05-87 06-09-87 SA-SWA-11A1 4816 7218 6718 8.312.6 3415 8319 SA-SWA-12C1 2414 3615 3014 9.312.7 26i4 6918 (Control)

SA-SWA-7El 6417 6818 6417 17 3 20!4 120111 SA-SWA-1F2 1213 3515 2013 5.412.2 1914 4116 he SA-SWA-16F1 1313 3215 2214 5.612.3 2214 4416 ce (D

AVERAGE 32146 49139 41146 9.119.4 24112 71165 STATION ID 07-07-87 08-04-87 09-10-87 10-06-87 11-02-87 12-08-87 AVERAGE SA-SWA-11A1 7718 92110 110111 8419 100110 7018 70157 SA-SWA-12C1 5717 6618 6218 4816 4816 3916 43137 (Control)

SA-SWA-7El 100110 110112 140113 8619 130113 100110 85179 SA-SWA-1F2 3315 3115 5917 2414 4516 3315 30130-SA-SWA-16F1 4916 5617 6618 '3715 5016 3115 36136 AVERAGE 63152 71162 87172 56156 75177 55160 GRAND AVERAGE 53166

- - - - . - - , , - - - - , - - - - . - . ,_ , an -,,,-.....a , , - . _ - . - . - . - --

, _ , . _ , , - - , - . , . , .n.. . - - . , ., ,,.-..e ,-

TACLE C-25 1987 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L i 2 sigma 01-06-87 04-07-87 07-07-87 10-06-87 STATION ID to to to to 03-05-87 AVERAGE 06-09-87 09-10-87 12-08-87 SA-SWA-llAl 1400 110 <l40 320190 180 90 510 1200 SA-SWA-12Cl 160 90 <140 <140 150190 g (Control) -

e SA-SWA-7El <150 <140 <l40 <l40 -

SA-SWA-IF2 <140 <l50 <l40 180i90 -

SA-SWA-16F1 <150 <140 <140 160 80 -

AVERAGE - - -

160136

_, __ _ , " ~

TABLE C-26 1987 CDNCENTRATIONS OF GAMMA [MITTER$* IN SURFACE WATER Results in Units of pct /L 2 2 sigma STATION ID NUCLIDE 01-06-87 02-02-87 03-05-87 04-07-87 05-05-87 06-09-87 5A-5WA-11A1 K-40 55 22 78t19 59:17 <41 60218 73223 Co-58 15t2 <1.6 <1.7 <2.5 <1.7 <2.4 Co-60 7.4 1.9 <1.7 41.6 <2.5 <2.6 <3.0 Cs-134 2.611.3 <2.3 <2.2 <2.2 <2.7 <2.6  ;

Ra-226 <4.0 <4.2 <5.1 5.5t2.4 <4.5 -5.0 1 Th-232 <8.3 47.2 c8.1 < ?. 9 <7.2 <9.9  !

SA-5WA-12C1 K-40 <43 42220 43t22 <26 441 91220 (Control) Co-58 <2.4 <2.0 42.5 <1.8 <2.1 <2.0 Co-60 <2.S <2.2 <2.7 <2.3 <3.1 <1.8 Cs 134 <2.6 <2.5 <2.1 <1.8 <2.2 <1.9 Ra-226 <5.2 <4.4 44.6 6.023.1 24:4 <4.9 Th-232 9.5t5.0 <10 <8.4 <6.6 <7.6 <7.0 po 5A-5WA-7El K-40 61218 110:21 <29 <31 86t17 100t24 ha Co-58 <1.6 <1.4 <1.8 <2.2 <1.2 <2.2 c) Co-60 <!.6 <1.7 <2.1 <2.2 <1.9 <2.3 Cs-134 <1.5 <1.5 <2.0 <1.7 <1.3 <1.9 Ra-226 <3.7 <3.7 <4.4 <4.1 <4.1 <3.5 Th-232 <5.8 <5.8 <6.6 7.023.2 <5.1 <6.4 5A-5WA-1F2 K-40 34:14 72216 70219 <?6 <32 47 16 Co-58 <2.0 <1.8 <1.4 <2.0 <2.1 <1.8 Co-60 <1.9 <1.9 <1.3 <2.0 <2.1 <2.0 Cs-134 42.1 <2.1 <1.5 <2.5 <2.1 2.521.1 Ra-226 <4.4 <4.4 <3.7 5.622.6 <4.9 <5.3 Th-232 <7.1 <7.1 <5.3 <6.9 46.6 7.423.3 5A-5WA-16F1 K-40 <34 66t17 <29 <32 <26 <48 Co-58 <1.0 <1.5 <1.6 <2.2 <2.0 <1.9 Co-60 <2.0 <1.9 <2.3 <2.3 <2.2 <2.0 Cs-134 <1.1 <1.6 <1.3 <1.9 <1.6 <2.3 Ra-226 <5.0 <4.8 44.9 44.7 1813 <4.6 Th-272 <5.8 <5.1 <6.8 <6.4 <8.2 <8.4 AVERAGE K-40 45224 74t49 46236 - -

72248 4

=*

TA8t[ C-16 (cont'd)

• 1987 CONCE :TRATIONI 0F CAba4A E;ITTER5* IN SURFACE WATER Results in Unlis of PCl/L t 2 sigma STATION ID NUCLIDE G7-07-87 08-04-87 09-10-87 10-C6-87 11-02-87 12-08-87 AVERAGE

~

5A-5WA-11A1 K-40 72t18 71219 110:22 Co-58 81121 100t19 55t16 71239

<1.6 <2.1 <1.6 <2.6 Co-60 <1.6 <2.1 <2.1 <2.3 -

<2.4 <2.0 <2.0 <2.5 Cs-134 <1.9 <2.3 <2.5 -

Ra-226 <2.2 <1.5 <1.5 44.5 <4.6 <3.9 44.2 Th-232 <6.1 <7.5 <4.5 <5.0 -

<5.8 <6.9 47.0 <T.4 -

5A-5WA-12C1 K-40 65t19 63t22 65t22 61116 53221 (Control) Co-58 <1.5 <2.5 <2.5 <1.4 42219 53 34 Co-60 <2.3 <2.6 <2.2 <2.5 -

<2.3 <1.9 <2.1 <1.7 Cs-134 <2.0 <2.4 <2.7 -

Ra-226 <1.6 <2.1 <2.1 25t3 <5.0 <5.4 <3.3 Th-232 <8.1 <4.8 <5.1

<8.4 <10 <4.5 <6.7

<6.1 -

pe SA-5WA-7El K-40 96t21 82122 130 19 89221 kJ Co-58 <2.1 <2.6 100t26 82t25 83t60 k' <2.0 <1.9 <2.5 <2.0 Co-60 <2.4 <2.1 <1.5 Cs-134 <1.5 <2.4 <2.8

<2.3 42.0 <1.4 <2.1 Ra-226 <4.9 <4.5 <1.9 42.4 -

4.022.2 44.1 <4.7 <5.3 Th-232 <7.6 <6.6 <5.1 47.3 <8.7 <9.5 -

SA-5WA-1F2 K 40 38214 25t14 81 21 Co-58 29115 46t16 53t16

<1.4 <1.4 <1.8 47237 Co-60 <1.9 <2.2 <1.5

<1.6 <1.4 42.1 <2.1 Cs-134 <1.8 <1.7 <1.9 <1.7 -

<2.4 <2.0 <2.6 <1.9 Ra-226 <4.0 <3.7 54.8 Th-232 <3.7 4.5t2.5 <4.2

<5.8 <5.5 < 7. 8 <6.4

<6.9 <6.9 -

SA-5wA-16F1 K-40 45 21 58:18 65t19 Co-58 45t15 59217 35t16 45228

<2.0 <1.8 <1.7 <1.6 Co-60 <2.9 <1.4 <1.5

<1.7 41.8 <1.7 <1.5 Cs-134 <2.5 <1.3 <1.6 <1.2 -

Ra-226

<1.7 <1.4 <2.1 1623 <h.2 1523 44.8 <3.8 Th-232 < 9. 3 <6.6 47.7 6.1t2.7 -

<7.4 <5.4 <5.2 -

AVERAGE K-40 63147 60t43 90258 61:50 72153 53t36 GRAND AYERAGE K-40 60150

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

1

TABLE C-27 1987 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 AND TRITIUM IN EDIBLE FISH TRITIUM (FLESH)**

STRONTIUM (BONES) AQUEOUS FRACTION pCi/kg (dry) 2 sigma pCi/kg (wet) i 2 sigma STATION ID SAMPLING PERIOD Sr-89 Sr-90 H-3 SA-ESF-llAl 06-17-87 to 06-22-87 <34 30 12 <50 10-06-87 to 10-08-87 <26 35 10 810 450 C

w SA-ESF-12Cl 06-17-87 to 06-19-87 <45 110116 <50 (Control) 10-06-87 to 10-07-87 <28 46 11 4501410 SA-ESF-7El 06-22-87 to 06-23-87 <36 33113 <50 10-06-87 to 10-07-87 <30 117 12 <50 AVERAGE -

62i81 -

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

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

e

~,

~;.

'~

r.

TABLE C-28

.1987 CONCENTRATIONS OF GAMMA EMITTERS

• IN EDIBLE FISH Results in Units of pCi/kg-(vet) i 2 sigma STATION ID SAMPLING PERIOD' .K-40 Ra-226 SA-ESF-llAl 06-17-87 to 06-22-87 3000 240 27 14

'10-06-87'to 10-08-87 3000 260 <30 ,

SA-ESF-12C1 06-17-87 to 06-19-87 2000i200 <30 (Control) 10-06-87 to 10-07-87 3400 240 <33 SA-ESF-7El 06-22-87 to 06-23-87 3000i230 <20 4

10-06-G7'to 10-07-87 2700 220 <27 -

AVERAGE 2800 940 -

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

I 123 l

9

. TABLE C-29 1987 C0;iCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90, GAMMA EMITTER $**

AND TRITIUM IN BLUE CRABS Results in Urits of pCi/kg (wet) 2 2 sigma 1

SAMPLING AQUEOUS FRACTION STATION ID PER10L SAMPLE Sr-89 Sr-90 K-40 Ra-226 Th-232 H-3***

j SA-ECH-11A1 06/16-17/87 Flesh 33 12 <18 27002250 <27 <60 <50 j

Shell (1) 68220 180214 (2) (2) (2) (2)

! 10/06-07/87 Flesh <24 <18 2300t220 44218 53229 6202450

[j She64 (1) 93215 420234 (2) (2) (2) (2)

SA-ECH-12C1 06/16-17/87 Flesh <26 <17 29002190 <24 <29 <50 (Control) Shell (1) 74220 250216 (2) (2) (2) (2) 10/06-07/87 Flesh <30 <22 2500 180 <25 <32 <50 Shell (1) 270233 1000238 (2) (2) (2) (2) i n

t

[ AVERAGE Flesh - -

26002520 - - ' -

j Shell 1302190 4602740 - - - -

l

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

L ** All other gamma emitters searched for were <LLD: typical LLDs are given in Table C-31.

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

j (1) Strontium resul? r in units of pC1/kg (dry).

(2) Gamma art trition analyses not required.

1

-- ,, e , -

-n ,

TABLE C-30 1987 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERSa IN SEDIMENT Results in Units of PCi/kg (dry) i 2 sigma i

STATTON TD DATE Sr-90 K-40 Mn-54 Co-58 Co-60

, .cs-137 Ra-226 Th-232 SA-FRn-11 A1 06-17-87 <23 61001360 (18 <22 39119 34112 10-06-87 <19 27001270 <18 430134 520165 23113 69112 (18 350129 370155 SA-ESS 15&l 06-17-87 <22 65001390 <26 60116 62113 <23 360130 10-06-87 (23 53001300 <13 (20 410157 31113 <l5 <30 350149 RA-FRn-16 A1

s. 06-17-87 29111 66001360 <23 37115 26112- <21 980143 na 10-06-87 <21 93001430 <20 <24 40124 510158 (n (18 (43 700172 SA-Fnn-1?c1 (Control)

! 06-17-87 <24 160001520 (18 <23 <29 <22 570135

10-06-87 <21 120001480 <20 <23 880169

<35 52119 700143 570177 i

SA-Fnn-7R1 i

06-17-87 76001370 d

(21 <17 <24 36116 29114 10-06-87 <20 130001400 <17 (20 75121 (41 480154 I 55113 80135 760160 l

SA-Fns-16F1 i

06-17-87 <26 160001640 <27 <31 <38 <38 10-06-87 <25 140001430 24113 660t51 970195 (20 (20 (21 640136 890164 AVERAGE -

960018900 - -

42135 4101630 -6201430 All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

. . _ . = .

1 9

'4 TABLE C-31 1987 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY AIR WATER FOOD PRODUCTS BEEF AND PARTICULATES ALL TYPES MILK AND FODDER CROPS GAME NUCLIDES (10-3pC1/m3 ) (pCi/L) (pCi/L) (pCi/k9-wet) '( pCi/kg-wet)

GEOMETRY: 13 Filters 3.5 Liter 3.5 Liter 100ml 400ml 100ml 400ml Be-7 a 14 14 8.0 120 37 92 Na-22 0.54 1.8 1.8 1.7 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 Fe Nb-95 0.43 1.7 1.7 1.1 16 5.0 12 S' Zr-95 0.71 3.0 3.0 2.0 28 8.8 21

, ZrNb-95 0.71 3.0 3.0 2.0 28 8.8 21

] Mo-99 12 20 20 51 1300 370 2400 1 4 Ru-103 0.39 1.4 1.4 1.0 16 4.9 12 l Ru-106 4.0 14 14 10 130 42 98 j Ag-110m 0.67 1.5 1.5 1.6 14 7.2 11-1 Sb-125 0.90 4.1 4.1 2.6 39 12 27 j Te-129m 14 63 6? 40 620 183 480 i I-131 G.46 1.8 1.8 1.7 30 9.0 30 1 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

] 3a-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 l' 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 l 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' i

4 L

_ , . . . _ , . . - - .- - . _ . , . . ~

. TABLE C-31-(cont'd) 1987 PSE&G RESEARCH CORPORATION-LLDs FOR GAMMA SPECTROMETRY SEDIMENT AIR FISH SHELLFISH AND SOIL IODINE ~ -!

f- NUCLIDES (pC1/kg-wet) (pCi/kg-wet) (pCi/kg-dry) NUCLIDES' -(10-3pCi/m3 )

i GEOMETRY: 100ml 400ml 100ml 400ml 100ml 100ml i

! Be-7 37 92 142 85 120 I-131 15 j Na-22 5.3 11 21 10 14 I-132 26 K-40 = = = = =. I-133 39 Cr-51 45 107 170 91 150 I-135 1.2 Mn-54 4.4 10 17 10 13 I 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 ps Nb -95 5.0 12 19 10 15 .l

[j Zr-SS 8.8 21 35 20 26 1

ZrNb-SS 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-110m 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 j 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 I

Ba-140 25 71 94 51 105 La-140 11 28 41 20 52 -

BaLa-140 25 71 94 S1 105 Ce-141 5.6 15 22 13 17

Ce-144 18 57 73 56 55 Ra-226 10 23 40 .23 230 Tu-232 17 40 69. 40 48

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

i

,,y _ ._ _ . _ , . . - _ _ . , . , ,-.-,_m__, ,, - s. _ _ , __,.

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 129

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a sp opsis of the analytical procedures utilized by various laboratories for analyzing the 1987 Artificial Island Radiological Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB

• PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates.................... 133 TI Analysis of Air Particulates.................... 135 PSE&G Analysis of Water............................... 136 GROSS BETA PSE&G Analysis of Air Particulates.................... 137 TI Analysis of Air Particulates.................... 139 PSE&G Analysis of Water............................... 140 PO'fASS I UM-4 0 PSE&G Analysis of Water............................... 141 TRITIUM PSE&G Analysis of Water............................... 142 CEP Analysis of Aqueous Fraction of Fish and Crab... 143 p IODINE-131 PSELG Analysis of Filtered Air........................ 144 TI Analysis of Filtered Air........................ 145 PSE&G Analysis of Raw Milk............................ 146 STRONTIUM-89 AND STRONTIUM-90 f

PSE&G Analysis of Air Particulates.................... 147 TI Analysis of Air Particulates.................... 150 PSE&G Analysis of Raw Mi1k............................ 152 PSE&G Analysis of Water............................... 155 PSE&G Analysis of Vegetation, Heat and Aquatic Samples 158 PSE&G Analysis of Bone and Shell...................... 161 PSE&G Analysis of Soil and Sediment................... 164 PSE&G Analysis of Samples for Stable Strontium........ 167 131  !

SYNOPSIS OF ANALYTICAL PROCEDURES-(cont'd)

TABLE OF CONTENTS LAB

• PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY P

PSE&G Analysis of Air Particulates.................... 169 TI 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 ENVIRO!TMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters........ 174 h

• PSE&G - PSE&G Research Corporation TI - Teledyne Isotopes CEP - Controls for Environmental Pollution, Inc.

132

a:

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

The specific alpha activity is computed on the basis of total corrected air 5

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 ga9 meter as well as the gas ,

meter efficiency itself.

Calculation of Gross Alpha. Activity:

Air flow is corrected first by using the following equations:

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

_ "Hg V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at j 32*F, "Hg l

l -V = FaPaO.9/>aO.0283 F = Uncorrected air flow, ft3 ,

0.946 = Temperature correction factor from 60'F to 32*F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %  !

efficiency /100)

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

Result (pci/m 3 ) = (G-B)/T (2.22)*(E)=(V) G = Sample gross counts  ;

l B = Background counts (from blank "

filter)

T = Count time of sample and blank, mins.

E = Fractional Am-241 counting efficiency Vu Corrected air flow of sample, m 3 2.22 = No. of dpm per PCi 133 i l

. _ _ _ _ _~...-...~._ _._ _ .. _ ,. ,-_. _.___. _ ____ _ _ _ - - - - -,_ _ _..._ -

4 i

2-sigma error (pC1/m3 ) = (1.96*(G+B)1/2),g (G-B)

A = Gross alpha activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter)

Calculation of lower. limit of detection:

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

LLD(pci/m 3 ) = 4.66 a (B)1/2 (2.22)a(E)a(V)*(T)

B = Background counts (from blank filter)

E = Fractional Am-241 counting efficiency V = Corrected air flow of sample, m 3 T = Count time of blank, mins.

134

... l I

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GROSS ALPHA AND BETA

)

The air filter is first stored for 2 to 5 days from date of receipt to allow for decay of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with rubber cement. The filter is then counted for beta activity and subsequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.

Gross alpha and beta activity (pCi/m 3) are computed as follows:

A= (G/T -B) i "m*((G/T +B)/T)1/2 (2.22aV*YaDaE) (2.22aVaYaD*E)

Where G = Total sample counts B = Background counts per minute T = Sample count time, mins.

2.22 = dpm/pci V = Sample volume, m3 Y = Chemical yield (Y = 1 in this case)

D = Decay factor from collection to count date (D = 1 in this case)

E = Counter efficiency

1. m = Multiples of counting error If the net activity (G/T -B) is equal to or less than the counting error, tnen the activity is considered to be the minimum detectably level, or MDL.

where MDL = 3a(2aB/T)l/2 (2.22aVaYaDaE)

Variables are as previously defined 135

. l 1

o l l

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS ALPHA ANA'sYSIS 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 lef tover sample residue remains,af ter the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and comb.ned with the sample filtrate. The combined sample is then neutralized with dilute ammonium hydroxide. From this point, both sample and blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to 50'C in order to help precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted on a stainless steel planchet. The sample is then alpha-counted for the appropriate time on a low background gas proportional counter, along with a U-238 source of the same geometrf. The blank is treated in the same manner as the sample.

Calculation of Gross Alpha Activity:

Result (pCi/L) = (G-E)/T (2.22)a(E)a(V)a(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) = (1.96a(G+B)l/2),g (G-B)

A = Gross alpha activity, pCi/L l

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

136

A-l $.

SYNOPSIS OF PSE&G RESEARCH CORPORATION 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 gasiproportional 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 i V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospharic pressure at a

32'F. "Hg V = F*Pa0.946a0.0283 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~ = Cctr ected air flow, m 3 P = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows:

l' Result (pC1/m 3 ) = (G-B)/T (2.22)a(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 e i

efficiency V = Corrected air flow of sample, m 3 2.22 = No. of dpm per pCi 137

4 2-sigma error (PCi/m 3) = (1.96a(G+B)1/2)oA ~~~~

(G-B)

A = Gross beta activity, PCi/m 3 G = Sample gross counts.

j 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 l 4.66 times the standard fleviation of the count on the blank.

LLD(PCi/m3 ) = 4.66 * (B)1/2 (2.22)*(E)*(V)a(T)

B = Background counts (from blank filter)

E = Fractional Sr-90 counting efficiency V = Corrected air flow of sample, m 3 T = Count time of blank, mins.

I 1

P.

138

's SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GROSS ALPHA AND BETA The air filter is first stored for 2 to 5 days from date of receipt to allow for decay of the radon-thoron daughters. It is then placed in a stainless steal planchet which has been coated in the center with rubber cement. The filter _is then counted for beta activity and subsequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.

Gross alpha and beta activity (PCi/m 3) are computed as follows:

A= (G/T -B) i "m*((G/T +B)/T)l/2 (2.22avaYaD*E) (2.22*V*YaD*E)

Where G = Total sample counts B = Background counts per minute T = Sample count time, mins.

2.22 = dpm/pci V = Sample volume, m,'

Y = Chemical yield (Y = 1 in this case)

Ds Decay factor from collection to count date (D = 1 in this case)

E = Counter efficiency

'm = Multiples of counting error If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MCL.

where MDL = 3*(2aB/T)l/2 (2.22aVaYaD*E)

Variables are as previously defined t

l I

139

_ =_. . . __ .

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a 1.0 liter portion is removed fr m the potable, rain or well water container and 250ml taken from each' surface water.

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

1.0 liter blank for 1.0 liter samples nna 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 pC1 2-sigma error (pC1/L) r- (1.96a(G+B)l/2),g [

(G-B)

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

140

' I a

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE f 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 AA instrument used, a calibration curve is prepared from the standards after which the samples are then run. If the absorbance*of any sample is higher than the upper standard used, the sample is then either diluted and re-run, the burner head turned 90', a more concentrated standard added to the calibration curve or a less sensitive wavelength used.

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

Calculation of K-40 Activity:

K-40 Activity (pci/L) = 0.85aC f

0.85 = Proportionality constant for converting ppm to pC1/L C = Potassium concentration, ppm e

f i

i i

f I

I 141 I t

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately 50ml of raw sample is mixed with sodium hydroxide and lotassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with 10ml of Instagel@ liquid scintillation solution,,and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing 8m1 of sample, 10ml of Instagel, and 0.1ml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of 8ml of distilled low-tritiated water and 10ml 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)=(1000) 2.22a(E)*(V)*(T)

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

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

E = (N)*(D)

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

N = C-(G/T)

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

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

1.96a(G/T2 +B/T2 )l/2a(1000) 2.22*(V)*(E)

Samples are designated LLD if the activity is less than the following value:

LLD'(pci/L) = (4.65)a(B)l/2*(1000) 2.22a(V)a(E)*(T) 142

i l

i l

l I

S'INOPSIS 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 aguasol cocktail (NEF-934 Aquaso18 cocktail, manufactured by New England Nuclear Corporation).

The resultant mixture is comprised of 19 percent sample in a clear gel-type aguasol 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.

143

o SYNOPSIS OF PSEGG RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF AIR IODINE Approximately 300m3 of air is drawn through a 50ml bed of triethylenediamine (TEDA)-impregnated charccal granules at a rate which closely corresponds to the breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing 50ml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.

Calculation of Gamma Activity:

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

Result (pCi/m 3) = N*D =R (2.22)*(E)*(A)a(T)*(V)

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

T = Acquisition live time, mins.

V = Sample volume, m 3 2.22 = No. of dpm per pCi 2-sigma error (pci/m3) , y,gg,(GC+BC)l/2,p N

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

The LLD (pCi/m 3 ) = 4.66a(BC)1/2*D (2.22)a(E)a(A)*(T)a(V) 144

• e.

I SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL FILTERS FOR IODINE-131 Charcoal cartridges are analyzed for I-131 using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA mini-computer, in series with the pulse height analyzer, calculates the number of counts (and the- standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volume, collection date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-11 and a Nuclear Data 6620, which perform all the above computations automatically. All resultant spectra are stored on magnetic tape, t

k 4

r l

145 .

o*

[ t r 4 SYNOPSIS OF PSE&G RESEARCH CORPORATION 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.

n Calculation of I-131 Activity:

I-131 Reeults (pC1/L) = (G-B)/Ta(1.05)*(H)

(2.22)*(E)a(V)*(Y) .

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

T = Count time of sample and blank E = E 0 aEXP(-A*M) = efficiency equation where EO = counting efficiency at zero sample thickness A= Self-absorption coefficient M = Sample thickness, mg/cm 2 V = Sample '/olume, liters Y = Chemical recovery =

R

'R1* R2 where R = mg of I~ recovered R1 = 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.

. factor for I-131 decay during counting period J = (0.693/8.05)a(R/1440)

R = Count time, minutes .

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

L = (0.65 '/8.05)*N N = Elapsta time (days) from mid-  ;

point of collection period to beginning of count time.

a 146 l

t SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF AIR FILTERS

-The air filters are'placed in a small beaker and just enough fuming nitric t 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 l carried out to remove the radiostrontium from the filter media. Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The strontium is precipitated as a carbonate, which is dried and weighed. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this -

two count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solse for them. <

4 Calculation of Sr-90 Activity:

Sr-90 Results (pC1/m 3) = N4/R (2.22)*(E)a(E(15)/E')*(S6)a(V)a(U)

= W2 where S6 = A + B*M + cam 2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional [

counter, where A, B and C are regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(15)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90

, counting standard efficiency run at the time of instrument  ;

! calibration (This standard is run with each group of environmental '

strontium samples) i E = Sr-90 counting standard efficiency 1

V = Sample quantity (m 3)

U = Chemical yield l N4 = (N2 - Flan 1)/W1 = net counts due to Sr-90 only '

W1 = ((1 + Rl*I2) - (1 + R1*II)*F1) l Il = 1 - EXP ((-0.693/2.667)*tl) I I2 = 1 - EXp ((-0.693/2.667)at2) tl = Elapsed time from Y-90 strip to first count h -

l 147 i

, , _ _ , , . _ - . , . _ . _ . . . , ,,,_.,m .,_m._, - y.. ..y.__y._,,, .,,m..,. _ , , _ _ . _ , . _ _ . , _ , _ _ _ . , _ . _ . , , , _ _ _ , . , _ _ , . - _ .

l l

t2 = Elapsed time from Y-90 strip to second cdunt 2.667 = Half-life of Y-90, days R1 = D + E=M + FaM2 (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 N1 = X1 - Yl, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ((-0.693/2.667)at2) i R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pC1/m 3 ) =

2a (X+Y) + (X14Yl)aF1 2' 1/2 a (WlaW2)

W1 d Wl d ,

(N2-Flan 1)

Again, keeping the same variable definitions, the LLD for Sr-90 (pC1/m 3 ) =

4.66a (X+Y) + (X1+Yl)aF1 2' 1/2 W1 2 W1 2 .

.l l

Calculation of Sr-89 Activity:

Sr-89 Results (pci/m3 ) = _ _ N6/R (2.22)*(E)a(E(15)/E')a(S7)=(V)=(U)=(F9)

= W3 S7 = G + ham + IaM2 (This is the general form of the normalized Sr-89 l efficiency regression equation for one particular gas proportiona'.

j counter where G, H and I are regression coefficients.) I N6 = N1 - N7a(1 + Rlall) i N7 = (N2 - Flan 1)/W1 (This represents counts due to Sr-90) '

" (15)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90

, counting standard efficiency run at the time of instrument

! calibration (This standard is run with each group of environmental

! strontium samples) l l

148 [

l F9 = EXP ((-0.693/50.5)at) 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 1

All other quantities are as previously defined. '

The 2-sigma error for Sr-89 (pCi/m 3) = 2a (S82 ,gg 2)2 *W3 (N1 - N7a(1+RlaII))

S8 = (X+Y) + [X1+Yl)aF1 2 1/2 d 4 Wl W1 S9 = (X1+Y1)1/2 All other variables are as previously defined.

Keeping2 the2same variable definitions, the LLD for Sr-89 (pCi/m 3 ) ,

4.66*(S8 439 )l/2 149

r SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF COMPOSITED AIR PARTICULATE FILTERS FOR RADIOSTRONTIUM The composited, air filters are leached with concentrated nitric acid, with 1 heating, in the presence of strontium carrier. After adding deionized water,  !

the sample is gravity filtered through a paper filter and the filtrate diluted further with additional deionized water, before being split into two equal parts. One part is put aside for gross alpha analysis and the other part evaporated on a hotplate to a small volume. The sample is transferred to a centrifuge tube and fuming nitric acid added to form the strontium nitrate precipitate. After centrifuging and pouring off the supernate, the precipi-tate is dissolved in deionized water and an iron scavenge performed. This marks the beginning of the Y-90 ingrowth period. Centrifuging and discarding the precipitate, standardized yttrium carrier is added to the supernate and

, the sample is set aside for 5 to 7 days. After this period, the sample is

alkalinized with ammonium hydroxide and heated in a hot water bath to form J

yttrium hydroxide. After cooling, the sample is centrifuged and the supernate i I

sa>ed for Sr-89 determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using [

saturated ammonium oxalate solution. The yttrium oxalate is mounted on a  ;

tared paper filter, oven dried, weighed and counted on a gas proportional '

counter. The sample is then recounted the following day to confirm the decay  !

of Y-90. ,

, The supernate, saved for Sr-89 determination, is treated with saturated }

sodium carbonate solution to precipitate strontium carbonate which is filtered

on a tared glass fiber filter, oven-dried and likewise counted 200 minutes on  ;

a gas proportional counter. These samples, however, are covered with an >

2 80mg/cm aluminum absorber to stop the Sr-90 beta emissions, thus allowing 1

the Sr-89 betas to be counted alone.

i The Sr-89 activity (pC1/m 3) is computed as follows:

l A= (G/T-Be -B,) i 'm*((G/T+B e+B3 )/T)1/2 j (2.22aVaYaDaE) (2.22*VaYaD*E) a l j If the net acti"ity (0/T -B) is less than or equal to the 2a counting error, the activity is considered MDL  !

where MDL = 2a(2aB/T)1/2  ;

i (2.22aVaYaDaE)  !

i where G = Total sample counts l T = Sample count time, mins. i

B a Background rate of counter, cpm e }

Ba = Background addition from Sr-90 and ingrowth of Y-90  !

1 2.22 = dpm/pci l V = Sample volume, m 3 Y = Chemical yield of strontium D = Sr-89 decay factor from midpoint of collection period to counting i date.

E = Sr-89 counting efficiency with 80 mg/cm2 aluminum absorber

'm = Multiples of counting error i .

150

-.-.-,_,,.-._.-.---..._..-.-..---..-.a -

l The Sr-90 activity (pCi/m 3) is computed as follows:

A= (G/T-B) i a m a((G/T+B)/T)1/2 (2.22aVaYaD=E) Il~.I2*V*YaD*E)

Y = Chemical yield of the mount or sample counted D = Decay factor from the collection to the counting date E = Counter efficiency All other variables are as previously defined.

If the net activity (G/T-B) is less than or equal to the 2e counting error, the activity is considered MDL where PDL = 2a(2aB/T)1/2 (2.22aVaYiaY 2 *IaDaE) 151

+

I SYNOPSIS OF PSE&G RESEARCH CORPORATION 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 cid and, by acidifying further to an overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallization is carried out to remove residual

calcium which may have been coprecipitated with the initial strontium precip-  !

I itation. Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip. The strontium is precipitated as its carbonate, filtered, i 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 ur.known quantities requiring two simultaneous equations to solve for ,.

them. ,

I Calculation of Sr-90 Activity: $

Sr-90 Results (PC1/L) = N4/R (2.22)*(E)*(E(15)/E')6(SS)*(V)*(U)

= W2 i

l 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, B and C are regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm 2  !

r

E(15)/E' u 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 a

V = Sample quantity (liters) 1  :

j U ri Chemical yield

N4 = (N2 - FJ*N1)/W1 = net counts due to Sr-90 only [

W1 = ((1 + Rl*I2) - (1 + Rl*II)*F1) 1 Il = 1 - EXP ((-0.693/2.667)*tl) f I

l 152

a .

j':

I2 = 1 - EXP ((-0.693/2.667)at2) 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 R1 = D + E*M + FaM2 (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 N1 = X1 - Yl, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 u No. of dpm per pCi F1 = EXp ((-0.693/2.667)at2)

R = Count time cf sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pci/L) =

2a (X+Y) + (X1+Y1)aF12 1/2 a(WlaW2)

Wl' Wl' (N2-Fl=N1)

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

4.66a (X+Y) + (X1+Yl)=F12' 1/2 W1 2 Wl d Calculation of Sr-89 Activity:

Sr-89 Results (pci/L) = N6/R (2.22)a(E)=(E(15)/E')*(S7)*(V)*(U)a(F9)

= W3 S7 = G ^ ham + IaM2 (This is the general form of the normal. zed Sr-89 efficiency regression equation for one particular gas proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7a(1 + RlaII)

N7 = (N2 - Flan 1)/W1 (This represer.ts counts due to Sr-90) 153

o E(15)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm 2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental stront -m samples)

F9 = EXP ((-0.693/50.5)at) 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) = 2a (S82 +S9 2 )l/2 ,93 (N1 - N7 (1+RlaI1))

S8 = (X+Y) + (X1+Yl).p1 2 1/2 W1' W1' .

S9 = (X1+Yl)l/2 All other variables are as previously defined.

Keepingthesamp2 4.66*(S82 ,392 )1 variable definitions, the LLD for Sr-89 (PCi/L) =

154

. .. . . . . - _ _ - . ~ _- . .. _-. _ _ _ . . - ..

. s.

• 4' SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE

. RADIOSTRONTIUM ANALYSIS OF W%TER  !

c Stable strontium carrier is introduced into a water sample and into a i

, 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- t tion on ferric hydroxide (yttrium strip' followed by a barium chromate strip.

The strontium is precipitated as a carbonate before being dried and weighed.

Tha 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 similitaneous equations to solve for them.

Since surface waters, as well as some drinking water samples, have been found i 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:

j Sr-90 Results (pCi/L) = N4/R ____

j (2.22)a(E)*(E(15)/E')a(S6)a(V)a(U)

^

, = W2 I

where S6 = A + BaM + cam 2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, B and C are regression coefficients.)

I M = Thickness density of strontium carbonate precipitate, mg/cm2 '

4 E(15)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90

! counting standard efficiency run at the time of instrument I

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 l N4 = (N2 - Flan 1)/W1 = net cornts due to Sr-90 only ,

W1 = ((1 + RlaI2) - (1 + RlaII)aF1) ,

t i Il = 1 - EXP ((-0.693/2.667)atl) 155 i

_ _ . . , - , --~._..,-m , - _ .r,__.ne , -~ . _- ,,-- ,,.--- -.-,__ ,c_..

a

• I2 = 1 - EXP ((-0 693/2 667)at2) 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 R1 = D + EaN + FaM2 (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, wher9 D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = X1 - Yl, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = 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) =

2a (X+Y) + (X1+Y1)aF12' l/S. = (WlaW2)

Wl' Wl' .

(N2-Fl*N1)

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

4.66a )X+Y)+(XI+Y1)aF12'1/2 W1 Wl d ,

Calculation of Sr-89 Activity:

Sr-89 Results (pCi/L) = N6/R (2.22)a(E)a(E(15)/E')a(S7)a(V)*(U)a(F9)

= W3 >

S7 = G + ham + I*M2 (Tais is the general form of the nor.malized Sr-89 efficiency regression equation for one particular gas proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7a(1 + RlaII)

N7 = (N2 - Fl=N1)/W1 (This represents counts due to Sr-90) 156

a .

E(15)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 countinq Standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental l strontium samples)

F9 = EXP ((-0.693/50.5)at) 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) = 2a (S8 ,gg2)1/2 2 aW3 (N1 - N7a(1+Rl*II))

S8 = (X+Y) + JX1+Y1)aF12'1/2 d

Wl W1 d -

S9 = (X1+Yl)l/2 All other variables are as previously defined.

Keeping2 the same variable definitions, the LLD for Sr-89 (pci/L) =

4.66a(S8 +S92)1/2 157

SYNOPSIS OF PSE&G RESEARCH CORPORATION 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 100*C. At the completion of the drying period, Staples are again weighed (recorded as "dry" weight) and then pulverized. A ,

measured amount (quantity dependent on desired sensitivity) of the pulverized l 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 to near boiling for 30 minutes, with stirring. The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with 1:1 nitric acid (HNO3 ). The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming HNO 3. 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 i

weighed. The samples are then counted on a low background gas proportional I l counter and, again, at least 14 days later. The basis for this two-count l method is that Sr-90 and Sr-89 are both unknown quantities requiring two ,

I simultaneous equations to solve for them. l Calculation of Sr-90 Activity:

Sr-90 Results (pCi/kg wet) = N4/R (2.22)a(E)a(E(15)/E')a(S6)a(V)a(U)

= V2 where S6 = A + BaM + cam 2 (This is the general form of the normalized Sr-90 efficiency regression equation for one parti'ular gas proportional counter, where A, B and C are regression coefficients.)

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

E = Sr-90 counting standard efficiency V = Sample quantity (kg wet)

U = Chemical yield N4 = (N2 - Fl*N1)/W1 = net counts due to Sr-90 only W1 = ((1 + R1aI2) - (1 + Rl*II)aF1) 158

1 Il = 1 - EXP ((-0.693/2.667)atl) 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-liie of Y-90, days R1 = D + E*M + FaM2 (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 N1 = X1 - Y1, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ((-0.693/2.667)=t2) l R = Count time of sample and blank Using the same vr.?Able definitions as above, the 2-sigma error for Sr-90 (pci/kg wet) =

2e (X+Y) + (X1+Yl)aF12" 1/2 a (WlaW2)

Wl d Wl d ,

(N2-Flan 1)

Again, keeping the same variable definitions, the LLD for Sr-90 (PC1/kg wet) =

4.66a (X+Y) + (X1+Y1)aF1 2 1/2 W1' W1' Calculation of Sr-89 Activity Sr-89 Results (pci/kg wet) = N6/R (2.22)a(E)a(E(15)/E')*(S7)a(V)*(U)a(F9)

= W3 S7 = G + ham + IaM2 (This is the general form of the normalized Sr-89 efficiency re ression equation for one particular gas proportional counter where a, H and I are regression coefficients.)

N6 = N1 - N7a(1 + RlaII) a 4

159

i a

a I

N7 = (N2 - Fl*N1)/W1 (This represents counts due to Sr-90)

E(15)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument  !

calibration (This standard is run with each group of environmental  !

strontium samples)  !

I

F9 = EXp ((-0.693/50.5)at)  ;

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.

L 50.5 = Half-life of Sr-89, days 4'

All other quantities are as previously defined. '

The 2-sigma error for Sr-89 (PC1/kg wet) = 2a (S82 +S92 )1/2 *W3 f L

(N1 - N7*(1+R1aI1))

S8 = IX+Y)+(X1+Y1).F12 1/2 W1 2 W12 .

L S9 = (X1+Y1)1/2 All other variables are as previously defined.

Keeping2the same variable definitions, the LLD for Sr-89 (pci/kg wet) =  ;

4.66a(S8 +392 )1/2 ,

L i

i t

~

P 1

I i

1 f

160 i

. - .- ~_ . . . . . - ~ -. ..

t.=

l

< l SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE l

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 I

-a brief time to digest remaining flesh / collagen material adhering to the sample. After multiple rinses with distilled water, the bone /shell is then l

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 l l 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 l i- on, any radiological impurities are removed by coprecipitation with ferric i 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-09 are both unknown quantities requiring two simultaneous equations to solve for them.

I

. Calculation of Sr-90 Activity:

Sr-90 Results (pC1/kg dry) = N4/R +

(2.22)a(E)a(E(15)/E')*(S6) (y)e(U)  !

= W2 ,

ll where S6 = A + B*M + cam 2 (This is the general form of the normalized Sr-90 4

efficiency regression equation for one particular gas proportional  ;

counter, where A, B and C are regression coefficients.) .

i M = Thickness density of strontium carbonate precipitate, mg/cm2 l i 1 E(15)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm 2 to Sr-90 l

counting standard efficiency run at the time of instrument

calibration (This standard is run with each group of environmental j strontium samples)

E = Sr-90 counting standard efficiency  ;

F j V = Sample quantity (kg dry) [

U = Chemical yield I ,

i l N4 = (N2 - Fl*N1)/W1 = net counts due to Sr-90 only 1 i I

s i >

l 161

a-t W1 = ((1 + R1aI2) - (1 + Rl*II)aF1)

• Il = 1 - EXP ((-0.693/2.667)atl)

I2 = 1 - EXP ((-0.693/2.667)at2) [

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 R1 = D + EaN + FaM2 (This is the general form of the regression  ;

equation for Y-90 off'y/Sr-90 eff'y ratio for one particular gas  !

proportional counter, where D, E and F are regression i coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = X1 - Yl, where X1 and Y1 are initial gross counts and background' r,ounts, respectively 2.22 = No. of dpm per pCi F1 s. EXP ((-0.693/2.667)=t2)

Ra Count time of sample and blank j Using the came variable definitions as above, the 2-sigma error for Sr-90 (pci/kg dry) = l gW1 + (X1+Yl)aF12' 1/2 a(WlaW2) 2a -

q ,

Wl' ,

(N2-Flan 1)

Again, keeping the same variable definitions, f the LLD for Sr-90 (PC1/kg dry) = t 4.66a 2' 1/2 gW1+ (X1+Y1)aF1 Wl' Calculation of Sr-89 Activity

, (i Sr-89 Results (PCi/kg dry) = N6/R (2.22)a(E)*(E(15)/E')=(S7)=(V)a(U)a(yg)  !

= W3' f S7 = 0 + HaN + !=M2 (This is the general form of the normalized Sr-89

^

efficiency regression equation for one particular gas proportional

counter where G, H and I are regression coefficients.)

162  !

• e l

N6 = N1 - N7a(1 + R1=II)

N7 = (N2 - Flan 1)/W1 (This represents counts due to Sr-90)

E(15)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 = EXP ((-0.693/50.5)at) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the olapsed 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) = 2a (S8 +S92)l/2 2 =W3 (N1 - N7a(1+Rl*Ilf)

S8 = (X+Y) + (X1+Yl)aF12'1/2 Wl' Wl' .

S9 = (X1+Y1)1/2 All other variables are as previously defined.

Keeping the2same variable definitions, the LLD for Sr-89 (PCi/kg dry) = '

4.66a(S82 +S9 )l/2 1

a 163

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT f

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 Sm1 of strontium carrier (10mg Sr++/ml). A blalA con-

[

taining only 1/3 - liter concentrated hcl and 5m1 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 HNO . Two 3

fuming (90%) HNO3 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.). Thore is a second count at least 14 days later. The basis for this two-count method i 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)a(E).(E(15)/Es)e(S6)*(V)a(U)

= W2 j where S6 = A + ban + cam 2 (This is the general form of the normalized Sr-90 3 efficiency regression equation for one particular gas proportional  !

counter, where A, B and C are regression coefficients.)

l M = Thickness density of strontium carbonate precipitate, mg/cm 2 E(15)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 f counting standard efficiency run at the time of instrument '

calibration (This standard is run with each group of environmental l strontium samples)  ;

i E = Sr-90 counting standard efficiency .

V = Sample quantity (kg dry)  ;

U = Chemical yield N4 = (N2 - Flan 1)/W1 = net counts due to Sr-90 only  !

W1 = ((1 + R1aI2) - (1 + RleII)aF1) t 164

Il = 1 - EXP ((-0.693/2.667)atl)

I2 = 1 - EXp ((-0.693/2.667)at2) 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 R1 = D + EaM + FaM2 (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 N1 = XI - Yl, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXp ((-0.693/2.667)at2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigra error for Sr-90 (pci/kg dry) =

2a 2" 1/2 a (WlaW2) [

fX+})+(X1+Yl)*F1

,W1 Wl d ,

(N2-FleN1)

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

4.66* X+Y) + (X1+Yl)aF12 '1/2 Wl d Wl d 1

Calculat.'.on of Sr-89 Activityt Sr-89 Results (pci/kg dry) = N6/R (2.22)*(E)a(E(15)/E')*(S7)a(V)*(U)a(F9)

= W3 S7 = 0 + ham + IaM2 (This is the general form of the normalized Sr-89 i efficiency regression equation for one particular gas proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7a(1 + RlaII) r 165 i f

I

=

o N7 = (N2 - FleN1)/W1 (This represents counts due to St-90)

E(15)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm 2 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)at) 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) = 2a (S82 ,392 )1/2 ,y3 (N1 - N7e(1+RI Il})

S8=[X+{}+(X1+YljaF1 1/2 2

W1 W1' S9 = (X1+Y1)1/2 All other variables are as previously defined.

Keepingghesamp2 2 variable definitions, the LLD for Sr-89 (pci/kg dry) =

4.66a(S8 +S9 )1 l

l l

166

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes. In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element (s) of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by ashing 2 g of sample, digesting in 6N HO1, 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 Absorptien 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-m1 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 maaufacturer's recommended instrument parameters.

All results (calculated as milligrams of strontium per liter) are then used to find the truo chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.

Sample Calculation of Corrected Chemical Recovery of Strontium in soll and Sediment:

Reported concentration of stable strontium (mg/L):119 Volume of specimen (ml):25 (removed from 1000ml of diluted leachate)

Proportion of sample used for aliquot 0.025 Milligrams strontium in 25m1 flask = (119mg/L) x (.025L/25ml) x (25ml)

2.98mg Sr Since 2.98mg Sr representc the quantity of stable strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample

2.98mgj[r, = 119 mg 0.025 167

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 = 0.623 119.6 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 = (1.65mg/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 168

?

SYNOPSIS OF PSE&G RESEARCH CORPORATION 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 le 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/m 3 ) = NaD =R (2.22)a(E)a(A)a(T)a(V)

N = Net counts under photopeak D = Decay correction factor Atla EXP( At2) 1-EXP(- Atl) tl = Acquisition live time [

t2 = Elapsed time from sample collection to start of acquisition A= 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, m 3 2.22 = No. of dpm per pCi 2-sigr.a error (pci/m ) 3= 1.96a (GC+BC)1/2,p N

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

The LLD (pC1/m3 ) = 4.66a(BC)1/2=D (2.22)a(E)a(A)=(T)*(V) i l

l

[

t 169

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA Air particulate filters are analyzed for gamma using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer' calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA minicomputer, in series with the pulse height analyzer, calculates the number of counts (and a one standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volume, collec- ,

tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 350. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-11 and Huclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.

i 170 .

s

• s t

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF RAW NILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a r preservative). After stirring, the sample is allowed to reach ambient' te=perature and then counted on a gamna detector.

Calculation of Gamma Activity: i The following are the calcutations performed for the gamma activity, 2-sigma error and LLD:

Result (PC1/L) = NaD =R (2.22)a(E)a(A)a(T)*(V)

N = Net counts under photopeak D = Decay correction factor A tlaEXP( At2) 1-EXP ( - Atl )

t1 = 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) = 1.96a(GC+BC)l/2 aR N

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

L The LLD (pci/L) = 4.65a(BC)1/2aD (2.22)a(E)a(A)a(T)*(V) l i

i 171

SYNOPSIS OF PSE&G RESEARCH CORPORATION 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) = NaD =R (2.22)*(E)a(A)a(T)*(V)

N = Net counts under photopeak D = Decay correction factor Atle 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) = 1.96a(GC+BC)1/2,9 p ,

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

The LLD (PCi/L) = 4.C5a(BC)l/2aD (2.22)a(E)e(A)=(T)a(V) 172

k SYNOPSIS OF PSE&G RESEARCH CORPORATION 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 compres;ed to unit density (19/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) = NaD =R (2.22)*(E)a(A)a(T)*(V)

N = Net counts under photopeak D = Decay correction factor At1*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 = Acquisitien live time, mins.

V = Sample volume, kilograms 2.22 = No. of dpm per pCi 2-sigma error (pci/kg) = 1.96a(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)l/2=D (2.22)a(E)a(A)a(T)a(y) 173 t

O ho SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOS! METERS These devices are rectangular Teflon Wafers impregnated with 25% CaSO4 :Dy phosphor. They are first annealed in a 250'C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized Cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are subtracted to allow for transit dose and system 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 e (REDOSE/RR)-AVC l R = Initial reading of the area RR = Second reading of the area (after re-irradiation)

LEDOSE = Re-irradiation dose, mR AVC = Average of control values, mR i

4N where AVC = ICDOSE/4N ,.

i=1 N = Total number of control dosi-1 meters  :

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CDOSE = CRa(CREDOSE/CRR)

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

CREDOSE = R(-irradiation dose of the c(dtrol dosimeter, mR r

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SUMMARY

OF USEPA -

ENVIRONMENTAL RADIOACTIVITY LABORATORY

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INTERCOMPARISON STUDIES PROGRAM RESULTS L

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APPENDIX E r

SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summar" of the analytical results for the 1987 USEPA Environmental Rad:,oactivity Laboratory Intercomparison l Studies Program, t t

F TABLE OF CONTENTS TABLE i NO. TABLE DESCRIPTION PAGE !

E-1 Gross Alpha and Gross Beta Emitters in Water and Air Part1Culates................................. 178 E-2 Gamma Emitters in Hilk, Water, Air Particulates s

and Food Products................................ 179 E-3 Tritium in Water................................. 181 1 E-4 Iodine in Water and Milk......................... 182 i

E-5 Strontium-89 and Strontium"90 in Air Particulates, s Milk, Water and Food Products.................... 183 '

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O TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY FROGRAM Gross Alpha and Gross Beta Analysis of Water (PC1/L) and Air Particulate (pci/ filter)

DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean i s.d. Known Mean i s.d.

01-87 EPA-WAT-AB207 Water Alpha 811 1110.7 1013 87-175 Beta 811 1018.7 111.1 03-87 EPA-WAT-AB213 Water Alpha 311 318.7 411 87-697 Beta 1211 1318.7 1312 04-87 EPA-APT-GABS 214 APT Alpha 1412 1418.7 1513 87-844 Beta 4411 4318.7 4515 04-87 EPA-WAT-P216 Water Alpha 5114 30114 2819 87-877 Beta 7112 6618.7 6517 05-87 EPA-WAT-AB218 Water Alpha 1711 1118.7 1013 87-1310 Beta 911 718.7 812 07-87 EPA-WAT-AB227 Water Alpha 511 518.7 511 87-2073 Beta Sil 518.7 612 08-87 EPA-APT-GABS 230 APT Alpha 1211 1018.7 1012 87-2453 Beta 3011 3018.7 3014 09-87 EPA-WAT-AB232 Water Alpha 411 418.7 411 87-2600 Beta 1211 1218.7 1212 10-87 EPA-WAT-P235 Water Alpha 3511 28112 2818 87-3309 Beta 8914 7218.7 75110 11-87 EPA-WAT-AB241 Water Alpha 711 718.7 612 87-3670 Beta 2111 1918.7 1914 1

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• 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 res uits of all participating laboratories I

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l TABLE E-2 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pci/L), Air Particulate (pci/ filter) and Food Products (pci/kg)

DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENY ID MEDIUM ANALYSIS Mean i s.d. Known Mean i s.d.

01-87 EPA-ORG-OS208 Food I-131 7912 78114 8116 87-252 Cs-137 8712 84t8.7 8815 K(1) 989113 980185 984171 02-87 EPA-WAT-G209 Water Co-60 4912 5018.7 5014 87-280 2n-65 9111 9118.7 9418 Ru-106 10017 10018.7 95116

( Cs-134 5611 5918.7 5513 i Cs-137 8811 8718.7 8715 i

04-87 EPA-APT-GABS 214 APT Cs-137 711 818.7 912 L 87-844 04-87 EPA-WAT-P216 Water Co-60 711 818.7 912 87-877 Cs-134 1712 2018.7 1813

, Cs-137 1511 1518.7 1612  ;

06-87 EPA-MLK-OS222 Milk I-131 6714 59110 6216 '

87-1809 Cs-137 7611 7418.7 7516 6 K(1) 1600120 15201130 15801110 i

06-87 EPA-WAT-G219 Water Cr-51 4419 4118.7 39114 ,

87-1360 Co-60 6613 6418.7 6514 I Zn-65 1012 1018.7 1112 Ru-106 73120 7518.7 73111 Cs-134 3811 4018.7 3713 Cs-137 8111 0018.7 8015 07-87 EPA-ORG-GS228 Food I-131 74110 80114 8117 87-2095 Cs-137 5111 5018.7 5215 '

K(1) 1700140 16801150 17301150 08-87 EPA-APT-GABS 230 APT Cs-137 911 1018.7 1122 87-2453 i

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0 TABLE E-2 (cont'd)

USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (PC1/L), Air Particulate (pci/ filter) and Food Products (PCi/kg)

DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean i s.d. Known Mean i s.d.

10-87 EPA-VAT-G233 Water Cr-51 6715 7018.7 6919 87-2915 Co-60 1518.7 1518.7 1612 Zn-65 4414 4618.7 4715 Ru-106 5917 6118.7 60110 Cs-134 23x2 2518.7 2412 Cs-137 5012 5118.7 5213 10-87 EPA-MIK-GS236 Milk (2)

)

10-87 EPA-WAT-P235 Water Co-60 1811 1618.7 1712 87-3309 Cs-134 1511 1618.7 1613 Cs-137 2511 2418.7 24t2 I

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

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

• • a s.d. - one standard deviation of acceptable results of all participating laboratories (1) Reported as mg/L of Potassium.

(2) Analysis cancelled by EPA.

180

c' TABLE E-3 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritium Analysis of Water (pci/L)

DATE ENV SAMPLE CODE PSEEG EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean i s.d. Known Mean i s.d.

02-67 EPA-WAT-H210 Watcr H-3 4133184 42091730 41561418 87-317 06-87 EPA-WAT-H220 Water H-3 2973138 28951618 27851293 87-1807 10-87 EPA-WAT-H234 Water H-3 46701160 44921778 43961300 87-2859 i

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

• • known value with control limits, indicating whether results are in agreement or disagreement ase s.d. - one standard deviation of acceptable results of all participating laboratories 181 t -

TABLE E-4 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L) a na ***

DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Xean i s.d. Known Mean i s.d.

02-87 EPA-MLK-I211 Milk (1) I-131 911 911.6 92 87-416 6-87 EPA-WAT-I215 Water (1) I-131 811 711.2 711 87-780 08-87 EPA-WAT-I229 Water I-131 4512 48110 47 5

, 87-2201 12-87 EPA-WAT-I242 Water I-131 2511 26110 2713 87-3701 a

s.d. - one standard deviation of three individual analytical results aa known value with control limits, indicating whether results are in agreement oc disagreement ama s.d. - one standard deviation of acceptable results of all participating laboratories (1) Special EPA /NRC low level study 182

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

Milk, Water (pCi/L) and Food Products (pCi/kg)

DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean i s.d. Known Mean i s.d.

01-87 EPA-WAT-S206 Water Sr-89 24 2 2518.7 23 6 87-174 Sr-90 25 1 2512.6 01-87 EPA-ORG-GS208 Food Sr-89 4414 49117 43110 87-252 Sr-90 04-87 EPA-APT-GABS 214 APT Sr-90 1611 1712.6 18i2

)87-844 04-87 EPA-WAT-P216 Water Sr-89 1611 1918.7 1714

)87-877 Sr-90 911 1012.6 1012 05-87 EPA-WAT-5217 Water Sr-89 38.3 2 4118.7 39i7 7

87-1128 Sr-90 18.311 2012.6 2013 p

06-87 EPA-MLK-GS222 Milk Sr-89 57.414 6918.7 64114 87-1809 Sr-90 29.112 3512.6 3415 07-87 EPA-ORG-GS228 Food Sr-89 17.3 4 20 8.7 2017 87-2095 Sr-90 22.412 3012.6 28i4 m

09-87 EPA-WAT-GABS 230 APT Sr-90 911 1012.6 1012

( 87-2453 i

10-87 EPA-MLK-GS236 Milk Sr-89 (1)

Sr-90 f 10-87 EPA-WAT-P235 Water Sr-89 13.2il 1618.7 1514 j 87-3309 Sr-90 9.911 1012.6 1011 b

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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) Analysis cancelled by EPA.

183

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APPENDIX F SYNOPSIS OF LAND USE CENSUS

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w APPENDIX F SYNOPSIS OF 1987 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 2

nearesg)residenceandthenearestgardenofgreaterthan50m (500ft producing broad leaf vegetation in each of the 16 meteorological sectors.

Tabulated below are the results of these surveys:

Milk Nearest Vegetable Animal Residence Garden i Meteorological Sept., 1987 Sept., 1987 Sept., 1987

) Sector km (miles) km (miles) km (miles)

N None None None l NNE None 6.9 (4.3) None NE None 6.4 (4.0) None ENE None 6.1 (3.8) None E None 5.4 (3.4) None h ESE None None None

}

SE None None None SSE None None None

' S None 6.1 (4.1) None SSW None 5.5 (3.4) None l SW None 6.9 (4.3) None

> WSW None 7.1 (4.4) None W 7.8 (4.9) 6.5 (4.0) None WNW None 5.5 (3.4) None NW None 5.9 (3.7) None NNW None 6.8 (4.2) None 187

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w Pubhc Service Electric and Gas Company

. Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609 339 4199 Vcs President -

Nuc! ear Operatons April 28, 1988 NLR-N88057 9

United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

1987 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272,. 50-311, 50-354 Public Service Electric and Gas Company (PSE&G) hereby submits the 1987 Annual Radiological Environmental Operating Report in accordance with Section 6.9.1.10 of Appendix A to Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2 and section 6.9.1.6 of Appendix A to Facility Operating License NPF-57 for Hope Creek Generating Station. This report summarizes the results of the radiological environmental surveillance program for 1987 in the vicinity of the Salem and Hope Creek Generating Stations. The results of this program for 1987 were specifically compared to the results of the preoperational program.

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

Sincerely, bA d^/

Enclosure

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4-Document Control Desk 2 04-28-88 C Mr. G. W. Rivenbark USNRC Licensing ProjectEManager - Hope Creek Mr. G. W. Meyer USNRC Senior. Resident Inspector - Hope Creek Mr. D. C. Fischer USNRC Licensing Project Manager.- Salem Mr. R. W. Borchard.

USNRC Senior Resident Inspector - Salem Mr. W. T. Russell, Administrator USNRC Region I

.r. D. M. Scott, Chief M

Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 f

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