ML18096A657

1991 Annual Radiological Environ Operating Rept for Jan-Dec 1991. W/920427 Ltr

ML18096A657
Person / Time
Site:	Salem, Hope Creek
Issue date:	12/31/1991
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N92037, RTL-ENV-91-01, RTL-ENV-91-1, NUDOCS 9205010215
Download: ML18096A657 (173)

Text

• Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations APR 2 1 1992 NLR-N92037 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 As required by Section 6.9.1.10 of Appendix A to Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Units No. 1 and 2, and Section 6.9.1.6 of Appendix A to Facility Operating License NPF-57 for Hope Creek Generating Station, Public Service Electric and Gas hereby transmits one copy of the 1991 Annual Radiological Environmental Operating Report. This report summarizes the results of the radiological environmental surveillance program for 1991 in the vicinity of the Salem and Hope Creek Generating Stations. The result of this program for 1991 were specifically compared to the result of the preoperational program.

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

Sincerely, Enclosure 9205010215 91123f - -

PDR ADOCK 05000272 R PDR

Document Control Desk 2

• APR 2 1 1992 NLR-N92037 c Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem

u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. S. Dembek, Licensing Project Manager U. s. Nuclear Regulatory Commission MS 14 E-21 Washington, DC 20555 Mr. T. P. Johnson (S09)

-~-

USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Divisioh of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

RTL-ENV-91-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM For Salem Generating Station, Unit 1: Docket No. 50-272 Salem Generating Station, Unit 2: Docket No. 50-311 Hope Creek Generating Station: Docket No. 50-354 1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1991 Prepared By

• PUBLIC SERVICE ELECTRIC AND GAS COMPANY RESEARCH AND TESTING LABORATORY APRIL 1992

AR1'1F1CIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM C\ C\

~~l~ITTm c~~r~~

GENERATrnG STATIONS 1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1991

TABLE OF CONTENTS PAGE SUlv'ARY. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 1 INTRODUCTION. . . . . . . . . . . * . . . . . . * . . . . . . . . . . . . . . * . . . . . . . * * * . . . . 3 Radiation Characteristics............................... 3 Radiation Effects. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Sources of Radiation Exposure........................... 4 Nuclear Power Reactors.................................. 7 Containment of Radioactivity *****..*****.****.********** 13 Sources of Radioactive Liquid and Gaseous Effluents ***.* 16 Radioactivity Removal from Liquid and Gaseous Wastes .**. 16 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM **..**.**.* 18 Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Data Interpretation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ . 2o Quality Assurance Program *.*.**....***.********..****.*. 21 Results and Discussion *..*******.*.***********.********* 21 Atmospheric. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Direct Radiation.................................... 25 Terrestrial. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 Aquatic. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 Program Deviations...................................... 39 Canel us ions .....................................* ...... ** . 4o REFERENCES * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 56 APPENDIX A I>~C>c;RAM SUlv'AR'Y' ******************************** 58 APPENDIX B SAMPLE DESIGNATION AND LOCATIONS ****.********** 73 APPENDIX C DATA TABLES . *.*******.*.************...******** 81 APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES **.**.******** 125 APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . * . . . . . . . . . 167 APPENDIX F - SYNOPSIS OF LAND USE CENSUS ..****.************* 175 i

TABLE NUMBER LIST OF TABLES TABLE DESCRIPTION PAGE

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

2. 1991 Artificial Island Radiological Environmental Monitoring Program (Program overview) *.*.***.....*. 42 LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION PAGE

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

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

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

4. Primary PWR Containment Cross-Section (Salem Uni ts 1 & 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

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

• 15

6. Beta in Precipitation and Air Particulate 1973 through 1991 (Quarterly) *..*.*.**..*********.* 46 6A. Beta in Precipitation and Air Particulate 1986 through 1991 (Monthly) ...*.*.*****..*****.**** 47 ii

LIST OF FIGURES (cont'd.)

FIGURE NUMBER FIGURE DESCRIPTION PAGE

7. Ambient Radiation - Offsite Vs Control Station 1973 through 1991 (Quarterly)...................... 48 7A. . Ambient Radiation - Offsite Vs Control Station 1986 through 1991 (Monthly)........................ 49

8. Iodine-131 Activity in Milk 1973 through 1991 (Quarterly)...................... 50 SA. Iodine-131 Activity in Milk 1986 through 1991 (Monthly)........................ 51

9. Gross Beta and Potassium-40 Activity in Surface Water 1973 through 1991 (Quarterly)...................... S2 9A. Gross Beta and Potassium-40 Activity in Surface Water 1986 through 1991 (Monthly)........................ 53

10. Tritium Activity in Surface water 1973 through 1991 (Quarterly)...................... 54 lOA. Tritium Activity in surface. Water 1986 through 1991 (Monthly)...................... 55 iii

SUMMARY

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

Generating Stations are located. The results of the REMP are published annually, providing a summary and interpretation of the data collected. Additional data relating to the releases of radioactive materials to the environment can be obtained in the Radiological Effluent Release Report (RERR) which is published and submitted to the Nuclear Regulatory Commission on a semi-annual frequency.

The PSE&G Research and Testing Laboratory (RTL) has been responsible for the collection and analysis of environmental samples during the period of January 1, 1991, through December 31, 1991, and the results are discussed in this report. The radioactive liquid and gaseous effluents due to the operation of SGS and HCGS during 1991 did not adversely affect the environment around Artificial Island.

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

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

iodine-131 (I-131), gross beta and gross alpha. The results of these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with Technical Specifications (Section 3/4.11) and applicable Federal and State regulations, and to verify the adequacy of radioactive effluent control systems. The results provided in this report are summarized below:

• There were a total of 1850 analyses on 956 environmental samples during 1991. Direct radiation dose measurements were also made using 451 thermoluminescent dosimeters (TLDs).

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• In addition to the detection of naturally-occurring isotopes (i.e. Be-7, K-40, Ra-226 and Th-232), low levels of Sr-90, and Cs-137 were also detected in various media.

The detection of these radionuclides may be attributed to residual fallout from atmospheric weapons testing. Trace levels of Mn-54, Co-58, Co-60, sr-89, Cs-134, and cs-137 were also detected. The concentrations of these nuclides were well below the Technical Specification reporting limit.

• Dose measurements made with TLDs at 41 locations around Artificial Island averaged 61 millirads for 1991. This was comparable to the preoperational phase of the program which had an average of 55 millirads per year 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 into a stable element or go through a series of decays (becoming several different radioisotopes) before eventually becoming a stable element.

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

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

There are essentially two types of exposure to radiation:

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

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

The measurement of dose to man is typically expressed in terms of a unit called the rem. As a better unit of dose, the millirem (mrem; 1 mrem =1/1000 rem) is most often used because the typical dose is usually on the order of thousandths of a rem. Another term used is the collective dose to a population, called a person-rem. A person-rem is calculated by adding up each individual dose to a population (e.g. 0.0001 rem to each person of a population of 10,000 persons= 1 person-rem).

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

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

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

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

Since radon gas is radioactive, it, too, continues to produce, by decay, other radioactive materials referred to as radon daughters. These daughters are solid particles which can stick to surfaces such as dust particles in the air. The dust containing the radon daughter particles can be inhaled and deposited in the lungs. Radon daughters emit high energy alpha*

particles which results in an average dose to the lungs of 300 mrem (0.3 rem to a 10 year old) in the United States. In areas such as New Jersey and Pennsylvania, over a geological formation known as the Reading Prong, doses much higher than 300 rem/yr have been recorded due to natural deposits of uranium. Doses due to radon gas and its daughters are the highest dose contributor to.individuals from all natural sources.

Cosmic rays are high energy electromagnetic rays which originate from outer space. About 300 cosmic rays pass through each person every second. Cosmic rays also interact with atoms in the earth's atmosphere and produce radioactive substances such as carbon-14 (C-14), sodium-22 (Na-22), beryllium-7 (Be-7), and*

tritium (H-3). Some of these radionuclides become deposited on land and water while the rest remain suspended in the atmosphere.

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

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

5

TABLE 1 COMMON SOURCES OF RADIATION*

Approximate Approximate Dose Dose Natural Sources Cmrem/yearl Manmade Sources Cmrem/yearl Cosmic Rays 42 Medical radiation 90 Building Materials 35 Television and Internal 28 consumer products 1-5 Ground 11 Weapons Fallout 2-5 Nuclear Power Plants 1 APPROXIMATE TOTAL 100 100

Reference:

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

Residents of Colorado receive an additional 80 mrem per year due to the increase in cosmic (higher elevation) and terrestrial radiation levels. Transcontinental and intercontinental airline pilots receive 1000 mrem/yr due to the high elevatiou and length of these flights and resultant higher cosmic radiation levels.

In several locations around the world high concentrations of

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

• The average individual is also exposed to radiation from a number of man-made sources. The single largest of these sources comes from medical diagnostic tools such as X-rays, CAT-scans, fluoroscopic examinations and radio-pharmaceuticals.

Approximately 160 million people in the United states are exposed to medical or dental X-rays in any given year. The annual dose to an individual from such medical irradiation averages 90 mrem which is approximately equal to the annual sum of natural radiation. Smaller doses from man-made sources come from consumer products (television, smoke detectors, fertilizer), fallout from prior nuclear weapons tests, and production of nuclear power and its associated fuel cycle.

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

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

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

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

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

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

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

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

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

7

There are three major types of nuclear reactors in operation in the world: the pressurized light-water reactor (PWR), boiling light-water reactor (BWR), and the gas-cooled reactor. The nuclear reactors built and operating on Artificial Island are the BWR (Hope Creek) and the PWR (Salem Units 1 and 2).

Of the two types of light-water reactors (LWR), the BWR has a simpler design. In a BWR the steam desired to generate electricity is produced in the core itself. Here, step by step, is how the BWR works (refer to Figures 1 and 2):

1. Water enters the reactor vessel through the reactor core which consists of 764 fuel assemblies. Each assembly consists of 64 zirconium alloy fuel rods about 13 feet long. Sixty-two of these rods contain-uranium 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 11 thick steam reactor vessel about 75 feet high and weighing 624 tons.

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

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

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

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

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

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

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

8

• FIGURE 1 BWR VESSEL & CORE FEEDWATER FEEDWATER (FROM CONDENSER) "'--'-'--- (FROM CONDENSER)

JET JET PUMP PUMP RECIRCULATION REC IR CU LATI 0 N PUMP PUMP

FIGURE 2 SCHEMATIC OF BWR POWER PLANT

~

DRYWELL -~

(PRIMARY CONTAINMENT) ~

r"'-""

1 SHIELD EWILDING *--=-=::=:::.-:_:::;.-*.::::.-=-.:.:..::::._-.;.___ _

COOLING TOWER CONDENSE!~

-WATER r--~~!Jt='====;;:::====?r=:ir=:::::r=====;F~=\

---

,--~=:Lrr--

~

RECIRC J----J'-...,.J~)'---0---

. ;---.... ~.J---.J----..J~=-

p UMP , J----..J~J----,J----..J--.._<==---= =

PRESSURE SUPPRESSION POOL * )'---.J'---.J'---.J----J---0--..._

COOLING WATEI~

(TORUS)

(f~IVER)

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

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

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

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

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

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

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

5.

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

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

11

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

STEEL (SHELL) LINER PRIMARY SYSTEM SECONDARY SYSTEM l~EACTOR PRIMARY STEAM GENEl~ TURBINE

__D GENERATOR i

REACTOR COOL.ANT ATOR

_ _ :_LJ SYSTEM CONDENSER REACTOR COOLANT PUMP WATER (CONDENSATE)

COOL.ING WATrn (RIVER)

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

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

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

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

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

From here the PWR and BWR differ in structure. The next barrier around a PWR reactor vessel is the containment building which is a four-foot thick, steel-reinforced (Salem Units 1 and 2 also include a steel liner) concrete structure (see Figure 4). It is designed to contain water and gases which may accidentally escape the above barriers. The containment is also designed to with-stand tornadoes, floods, and earthquakes.

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

• 13

FIGlJRE 4 PRIMARY PWR CONTAINMENT CROSS-SECTION (SALEM UNITS 1 & 2) r /

POLAR GANTRY CRANE CONCRE:::

191' 6" 4'-6' STEAM STEAM GENERATOR GENERATOR FAN : FAN COJL : D COIL UNIT 1 UNIT GROUND I GROUr'-!l::*

LEVEL _f LEVC::..

I I

ACCUMULATOR IL.

I I

I i

156'6" 14

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

DRY ----1 WELL I

REC/RC PUMP I

• PRtSSURE SUPPRESS/01\J POOL I 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 waste water. These represent the principal sources of liquid effluents.

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

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

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

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

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

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

THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Artificial Island is the site of Salem and Hope Creek Generating Stations. The Salem Generating Station (SGS) consists of two operating pressurized water nuclear power reactors. Salem Unit One has a net rating of 1115 MWe (3411 MWt), and Salem Unit Two has the same rating at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which has a net rating of 1067 MWe (3293 MWt).

Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic fill from dredging operations. It is located in Lower Alloways Creek Township, Salem County, New Jersey. The environment surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands.

These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agriculture [5,6]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Reports [5,6], Environmental Statements [7,8],

and the Updated Final Safety Analysis Report for SGS [9] and the Final Safety Analysis Report for HCGS [10].

Since 1968, an off-site Radiological Environmental Monitoring

• Program (REMP) has been conducted at the Artificial Island Site.

Starting in December, 1972, more extensive radiological monitoring programs were initiated. The operational REMP was initiated in December, 1976, when Salem Unit 1 achieved criticality. The PSE&G Research and Testing Laboratory (RTL), has been involved in the REMP since its inception. The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983 1 conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL.

From January, 1973, through June, 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results. RMC reports for the the preoperational and operational phase of the program are referenced in this report

[1-3]. on July 1, 1983, the RTL assumed primary responsibility for the analysis of all samples (except TLDs) and the reporting of results. Teledyne Isotopes (TI), Westwood, NJ, at that time was made responsible for third-party QA analyses and TLDs. An additional vendor, Controls for Environmental Pollution Inc. has been retained to provide third-party QA analyses and certain non-routine analyses. RTL reports for the operational phase from 1983 to 1990 are referenced in this report [4].

18

An overview of the 1991 Program is provided in Table 2. Radio-analytical data from samples collected under this program were compared with results from the preoperational phase. Differ-ences 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, 1991, for the Artificial Island Radiological Environmental Monitoring Program.

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

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

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

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

• To detect any change in ambient gamma radiation levels.

• To verify that SGS and HCGS operations have no detrimenta':l.

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 1991 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Artifi-cial 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.

19

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

Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations. Indicator and control station data are also evaluated relative to preoperational data.

Appendix A describes and summarizes, in accordance with Section 6.9.1.10 of the Salem TS and Section 6.9.1.7 of the Hope Creek TS, the entire operational program as performed in 1991. Appendix B describes the coding system which identifies sample type and location. Table B-1 lists the sampling stations and the types of samples collected at each station. These sampling stations are indicated on maps B-1 and B-2.

DATA INTERPRETATION R~sults 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 Regulatory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability, with only 5%

probability of falsely concluding that a blank observation represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count, or of the blank sample count, as appropriate.

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

Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific

• location and instant of time.

20

As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid.

QUALITY ASSURANCE PROGRAM The PSE&G Research and Testing Laboratory (RTL), has a quality assurance program designed to maximize confidence in the analytical procedures used. Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix D.

The quality of the results obtained by the RTL is ensured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Plan [17) and the Environmental and Chemical Services Division Procedures Manual

[18]. The internal quality control activity of the Laboratory includes the quality control of instrument~tion, equipment and reagents: the use of reference standards in c,alibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is implemented through participation in the USEPA Laboratory Intercomparison Studies Program. These results are listed in Tables E-1 through E-5 in Appendix E.

RESULTS AND DISCUSSION The analytical results of the 1991 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1991 REMP are summarized in Appendix A. The data for individual samples are presented in Appendix c. The data collected demonstrates that SGS Units 1 and 2 and HCGS were operated in compliance with Technical Specifications.

The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating Stations Technical Specifications. The summary tables in this report include these additional samples and analyses.

21

ATMOSPHERIC Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on triethylenediamine (TEDA) impregnated charcoal cartridges connected in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure.

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

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

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

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

Air particulate samples were collected at six locations. Each of the 312 weekly samples collected were analyzed for gross alpha (management audit analysis) and gross beta. Quarterly composites of the weekly samples from each station were analyzed for specific

.gamma emitters and a single quarterly composite sample was analyzed for sr-89 and Sr-90 as a management audit analysis.

Total data recovery for the six sampling stations during 1991 was 98.6 percent.

• Gross alpha activity was detected in 195 of the indicator station samples at concentrations ranging from 1.1 x 10-3 to 7.7 x 10-3 pCi/m3. Analysis of the 47 control station samples detected gross alpha activity levels ranging from 0.8 x 10-3 to 4.4 x 10-3 pCi/m3. LLD sensitivities for the remaining 70 indicator and control station samples ranged from <0.7 x 10-3 to <5.0 x 10-3 pCi/m3. Two indicator station samples analyzed by PSE&G did not meet the desired sensitivity of 2 x 10-3 pCi/m3 due to low sample volumes caused by an air sampler malfunction. The LLD sensitivity for the samples analyzed by PSE&G were <6.2 x 10- 3 and <12 x 10-3 pCi/m3. These numbers were not included in any averages. One indicator station was vandalized and the sample lost. One control station sample did not meet sensitivity (<3.8 x 10-3 pCi/m3). It was not included in any averages since the sampling duration was too short. one control sample was lost due to equipment malfunction.

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

22

• Gross beta activity was detected in 255 of the indicator station samples at concentrations ranging from 6 x 10-3 to 45 x 10- 3 pCi/m3 and in 50 control station samples from 8.9 x 10-3 to 36 x 10-3 pCi/m3. The results from four indicator and one control station samples were not included in any averages since the sampling duration was abbreviated.

One indicator station was vandalized with the sample lost.

One control location was lost due to equipment malfunction.

The average for both indicator and control station samples was 23 x 10- 3 pCi/m3. The maximum preoperational level detected was 920 x 10-3 pCi/m3, with an average of 74 x 10- 3 pCi/m3 *

• Gamma spectrometric analysis performed on each of the 24 quarterly composite samples indicated the presence of the naturally-occurring radionuclides Be-7 and K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in all twenty indicator station composites at concentrations ranging from 41 x 10-3 to 114 x 10-3 pCi/m3 and in the four control station composites from 39 x 10-3 to 70 x 10-~ pCi/in3. The *"'*

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

o Potassium-40, a naturally occurring radionuclide, was detected in three of the indicator stations' composites at concentrations ranging from 15 x 10-3 pCi/L to 1320 x 10- 3

• There was no K-40 detected in any control composite samples. No preoperation data is available for comparison.

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

o Strontium-89 was not detected in any of the six composites analyzed. LLD sensitivities for the five indicator station samples ranged from <0.3 x 10-3 to <2.0 x 10-3 pCi/m3 and for the control station at <0.3 x 10-3 pCi/m3 . The maximum preoperational level detected was 4.7 x 10-3 pCi/m3.

o Strontium-90 was not detected in any of the indicator station composites analyzed. LLD sensitivities for the indicator station samples ranged from <0.2 x 10-3 to

<2.0 x 10-3 pCi/m3. The control station sample was

<0.2 x 10-3 pCi/m3. The maximum preoperational level detected was 3.0 x 10-3 pCi/m3.

23

Air Iodine (Table C-4)

Iodine in filtered air samples was collected at six locations.

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

• Iodine-131 was not detected in any of the 310 weekly samples analyzed. One indicator station was vandalized and its sample lost. Two other stations experienced short sampling periods and as a result had higher than normal LLD results.

LLD sensitivities for the remaining 257 indicator station samples ranged from <2.2 x lo-3 to <18 x 10-3 pCi/m3.

One control station sample was lost due to equipment failure and another had an inadequate sample size from an unscheduled power interruption. LLD sensitivities for the 51 control station samples ranged from <3.0 x lo-3 to <12 x 10-3 pCi/m3. The maximum preoperational level detected was 42 x lo- 3 pci/m3.

Precipitation (Tables C-6)

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

• Gross alpha activity was detected in two of the twelve samples at concentrations ranging from 0.9 to 1.3 pCi/L. LLD sensitivities for the remaining eight samples ranged from

<0.8 to <1.7 pCi/L. The maximum preoperational level detected was 4.7 pCi/L.

• Gross beta activity was detected in all of the twelve samples at concentrations ranging from 0.9 to 14 pCi/L, with an average of 4.1 pCi/L. The maximum preoperational level detected was 71 pCi/L, with an average of 19 pCi/L.

• Tritium activity was detected in two of the twelve samples for an average of 150 pCi/L. LLD sensitivities for the samples ranged from <130 to <170 pCi/L. The maximum preoperational level detected was 610 pCi/L, with an average of 216 pCi/L.

• Gamma spectrometric analysis was performed on only eleven of the monthly samples. There was insufficient sample to adequately meet the sensitivity requirements for gamma analysis in the month of February. Analysis indicated the presence of the naturally-occurring radionuclide Be-7 and K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

24

o Beryllium-7, attributed to cosmic ray activity, was detected in eight samples at concentrations ranging from 32 to 74 pCi/L, with an average of 47 pCi/L. The maximum preoperational level detected was 79 pCi/L, with an average of 29 pCi/L. The increase in the naturally-occurring Be-7 activity over preoperational levels is most likely due to spallation reactions in the upper atmosphere.

o Potassium-40 activity was detected in one sample at a concentration of 43 pCi/L. The maximum preoperational level detected was 18 pCi/L. This increase over preoperational levels is most likely due to the sampling stations relatively close proximity to an estuarian environment 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 arounti the Artificial Island Site at various distances.

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

A total of 41 locations were monitored for direct radiation during 1991, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations, 15 off-site indicator stations and 3 control stations. An additional 14 quarterly measurements were taken at schools and population centers, with 3 additional controls beyond the 10 mile zone in Delaware.

• Four readings for each TLD at each location were taken in order to obtain a more statistically valid result. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4.

o The average dose rate for the 15 monthly off-site indicator TLDs was 6.8 millirads per standard month, and the corresponding average control dose rate was 7.3 millirads per standard month. The preoperational average monthly TLD readings was 4.6 millirads per standard month.

o The average dose rate for the 26 quarterl,y off-site indicator TLDs was 5.0 millirads per standard month, and the aver~ge control rate was 5.3 millirads per standard month. The preoperational average quarterly TLD readings was 4.4 millirads per standard month.

25

In Figure 7, the average radiation levels are plotted for the yea~

period through 1991. Figure 7A shows the monthly averages of the off-site indicator stations and the control stations for 1982 through 1991. Ambient radiation levels during 1991 were comparable to those obtained during 1990.

TERRESTRIAL Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Samples were collected in new polyethylene containers and transported in ice chests with no preservatives added.

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

Separate raw and treated potable water samples were composited daily by personnel of the City of Salem water treatment plant.

All samples were collected in new polyethylene containers.

Locally grown vegetable and fodder crops are collected once a year at time of harvest. Such samples are weighed in the field at time of pickup and then pack~a in plastic bags. Grass or green chop is collected from grazing areas, where possible.

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

Game (muskrat) is collected annually (time of year dependent on weather conditions, which affect pelt thickness) from local farms after being trapped, stripped of their pelts and gutted. The carcasses are packed in plastic bags and kept chilled in ice chests during transport.

Milk (Tables C-9, C-10)

Milk samples were collected at four local dairy farms. Samples were collected semi-monthly when cows were on pasture and monthly when cows were not on pasture. Animals are considered on pasture from April to November of each year. Each sample was analyzed for I-131 and gamma emitters. In addition, although not specifically required by the SGS and HCGS Technical Specifications, one sample from each location was analyzed for sr-89 and Sr-90 in order to maintain the data base developed in prior years.

• Iodine-131 was not detected in any of the 80 samples analyzed. LLD sensitivities for the 60 indicator station samples ranged from <0.1 to <0.4. pCi/L and for the 20 control station samples from <0.1 to <0.4 pCi/L. The maximum preoperational level detected was 65 pCi/L which occurred following a period of atmospheric nuclear weapons tests.

26

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

o Potassium-40 was detected in all 80 samples. Concentra-tions for the 60 indicator station samples ranged from 1100 to 1700 pCi/L. The 20 control station sample concentrations ranged from 1300 to 1500 pci/L. The average for all the stations, indicator and control, was 1400 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.

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

o Strontium-89 was not detected in any of the three indicator samples analyzed nor in the control station sample. LLD .sensitivities for the indicator samples .,._.

ranged from <1.0 to <1.5 pCi/L and for the control station at <1.3 pCi/L. The maximum preoperational level de~ected was 14 pCi/L.

o. Strontium-90 was detected in all of the three indicator samples analyzed. Average concentrations for the indicator station samples was 2.7 pCi/L and for the control station sample at 3.0 pCi/L. The average concentration for all samples was 2.7 pCi/L. The maximum preoperational level .detected was 12 pCi/L, with an average of 3.5 pCi/L. The presence of Sr-90 in the samples can be attributed to fallout from nuclear weapons testing.

Well Water (Tables C-11, C-12, C-13}

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

Each sample was* analyzed for gross alpha, gross beta, potassium-40, tritium, I-131 and gamma emitters. Quarterly composites were analyzed for Sr-89 and Sr-90.

• Gross alpha activity was not detected in any of the indicator station samples, and in two of the control station samples at concentrations of 1.2 and 1.0 pCi/L. These values are within the variations of the LLD sensitivities for the remaining 22 samples which ranged from <0.6 to <2.1 pCi/L. The maximum

• preoperational level detected was 9.6 pCi/L.

27

• Gross beta activity was detected in all 24 samples

• Concentrations for the 12 indicator station samples ranged from 3.1 to 8.2 pCi/L and for the 12 control station samples from 9.9 to 11 pCi/L. The average concentration detected for all samples was 7.4 pCi/L. The maximum preoperational level detected was 38 pCi/L, with an average of 9 pCi/L.

• Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples. Concentrations for the 12 indicator station samples ranged from 2.6 to 7.6 pCi/L and for the 12 control station samples from 8.6 to 10 pCi/L. The average concentration detected for all samples was 6.9 pCi/L.

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

• Tritium activity was detected in one of the indicator station samples at a concentration of 260 pCi/L and in two of the control station samples at 190 and 280 pCi/L. The LLD sensitivities for the remaining 21 samples ranged from <130 to <170 pCi/L. The maximum preoperational level detected was 380 pCi/L.

• Gamma spectrometric analysis performed on each of the 12 indicator station and l2 control station water samples indicated the presence of the naturally-occurring radio-nuclide Ra-226. All other gamma emitters searched for were below the Lower Limit of Detection.

o Radium-226 was detected in seven of the indicator station samples at concentrations ranging from 10 to 110 pCi/L and in all twelve control station samples from 110 to 190 pCi/L. LLD sensitivities for the remaining indicator station samples ranged from <2.9 to <9.4 pCi/L. The maximum preoperational level detected was 2.0 pCi/L.

These values are similar to those found last year.

However, as with the 1989 and 1990 results, they are higher values than found in the preoperational program.

We believe that results are higher due to a procedural change in which the samples are no longer boiled down to a 100 ml standard geometry. This change results in less removal of radon (and its daughters) from the sample.

Since Ra-226 is an alpha emitter, its identification by gamma isotopic analysis is obtained by counting the gamma rays from Pb-214, one of its daughter products. We believe that values currently being observed are typical for this geographical area.

• strontium-89 and strontium-90 analyses were performed on quarterly composites of the monthly well water samples.

0 Strontium-89 was not detected in any of the four indicator.

station or four control station composites. LLD sensitivities for the indicator samples ranged from 28

• 0

<0.5 to <1.0 pCi/L and for the control samples from <0.5 to <0.7 pCi/L. The maximum preoperational level detected was <2.1 pCi/L.

Strontium-90 was not detected in any of the four indicator station or four control station composites. LLD

• sensitivities for indicator samples ranged from <0.4 to

<0.7 pCi/L and for the control samples from <0.4 to <0.5 pCi/L. The maximum preoperational level detected was 0.87 pCi/L.

• I-131 was not detected in any of the twelve indicator station samples or control station samples. LLD sensitivities for all the stations, indicator and control samples, ranged from

<0.1 to <0.4 pCi/L.

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

Both raw and treated potable water samples were collected from the Salem water treatment plant. Each consisted of daily aliquots composited into a monthly sample. The raw water source ~or this plant is Laurel Lake and adjacent wells. Each of the 24 individual samples was analyzed for gross alpha, gross beta, K-40, tritium, iodine-131 and gamma emitters. Quarterly composites of monthly raw and treated water samples were analyzed for Sr-89 and Sr-90.

• Gross alpha activity was detected in three raw water samples at concentrations ranging from 0.8 to 2.1 pCi/L and in two treated water samples at 0.8 and 1.0 pCi/L. These values are within the variations of the LLD sensitivities for the remain-ing 19 samples which ranged *from <0.6 to <2.3 pCi/L. The maximum preoperational level detected was 2.7 pCi/L.

• Gross beta activity was detected in all 24 samples at concentrations ranging from 2.8 to 3.8 pCi/L for the raw water and from 2.0 to 3.0 pCi/L for treated water. The average concentration for both raw and treated was 2.9 pCi/L. The maximum preoperational level detected was 9.0 pCi/L, with an average *of 4.2 pCi/L.

• Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples at concentrations ranging from 1.4 to 2.7 pCi/L for the raw water and from 1.4 to 2.3 pCi/L for treated water. The average concentration for both raw and treated was 1.9 pCi/L. The maximum preoperational level detected was 10 pCi/L, with an average of

1. 7 pCi/L.

29

~ Tritium activity was only detected in three raw water samples at concentrations of 140 to 290 pCi/L, and in one treated water sample at 180 pCi/L. LLD sensitivities for the remaining 20 samples ranged from <120 to <170 pCi/L. The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

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

Iodine-131 measurements were below the LLD sensitivities.

The LLD sensitivities ranged from <0.1 to <0.5.

• Gamma spectrometric analysis performed on each of the 24 monthly raw and treated potable water samples indicated the presence of the naturally-occurring radionuclide K-40 in only one sample. All other gamma emitters searched for were below the Lower Limit of Detection.

o Although not as sensitive as atomic absorption, K-40 was detected in that one sample at a concentration of 17 pCi/L. All other results were below LLD. The LLD sensitivities ranged from <ll. to <66 pCi/L. No preoperational data is available for comparison *

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

o strontium-89 was not detected in any of the four raw or treated water composites. LLD sensitivities for the raw water sample composites ranged from <0.5 to <0.7 pCi/L and for the treated water sample composites from <0.6 to <1.3 pCi/L. The maximum preoperational level detected was 1.1 pCi/L.

o strontium-90 was not detected in any of the four raw or treated water sample composites. LLD sensitivities for the four treated water sample composites ranged from <0.5 to <1.0 pCi/L and for the raw water sample composites from

<0.4 to <0.6 pCi/L. The maximum preoperational level detected was 2.1 pCi/L.

Vegetables (Table C-17)

Although vegetables in the region are not irrigated with water into which liquid plant effluents have been discharged, a variety of food products gro\.rn in the area for human consumption were sampled at five indicator stations (12 samples) and three control stations (8 samples). The vegetables collected as management audit samples are analyzed for gamma emitters and included asparagus, cabbage, sweet corn, peppers and tomatoes.

30

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

o Potassium-40 was detected in all twenty samples.

Concentrations for the twelve indicator station samples ranged from 1300 to 4600 pCi/kg-wet and for the eight control station samples from 1400 to 2700 pCi/kg-wet. The average concentration detected for all samples was 2300 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2140 pCi/kg-wet.

Game (Table C-18)

Although not required by the SGS or HCGS Technical Specifi-cations, samples of muskrats, inhabiting the marshlands surrounding the site, are collected. This game is consumed by lo.cal residents. The samples, when available, are collected from two locations once a year as management audit samples and analyzed for gamma emitters. Samples from two locations were collected during the beginning of February to satisfy this requirement.

• Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclides K-40 and Ra-226. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in the indicator station sample at a concentration of 2200 pCi/kg-wet and the control station sample at 2100 pCi/kg-wet. The average for both muskrat samples was 2200 pCi/kg-wet. The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4400 pCi/kg-wet.

o Radium-226 was not detected in the indicator station sample but was detected in the control station at a concentration of 30 pCi/kg-wet. The LLD from the indicator station was <18 pCi/kg-wet. The maximum preoperational level detected was 1000 pCi/kg-wet.

BEEF (Table C-18)

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

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

31

o Potassium-40 was detected at a concentration of 2800 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet.

Fodder Crops (Table C-19)

Although not required by the SGS or HCGS Technical Specifi-cations, eight samples of crops normally used as cattle feed were collected from four indicator stations (7 samples) and one control station (2 samples). It was determined that these products may be a significant element in the food-chain pathway.

Fodder crops are collected as management audit samples and analyzed for gamma emitters. Four of the locations from which samples were collected are milk sampling stations. Samples collected for wet gamma analysis included corn silage and soybeans.

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

0 Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in the chree corn silage samples from the indicator stations at concentrations ranging from 520 to 840 pCi/kg-wet and in the control station silage

• sample at 300 pCi/kg-wet. LLD sensitivities for the remaining four indicator soybean samples ranged from <53 to <170 pCi/kg-wet. The control station soybean sample was <140 pCi/kg-wet. The maximum preoperational level detected was 4700 pCi/kg-wet, with an average of 2000 pCi/kg-wet.

0 Potassium-40 was detected in all nine samples.

Concentrations for the seven indicator station samples ranged from 3000 to 15000 pCi/kg-wet and for the two control station samples at 4000 to 13000 pCi/kg-wet. The average concentration detected for the corn silage samples was 4000 pCi/kg-wet and for the soybean samples was 14000. These levels are comparable to preoperational results, which detected a maximum level of 16000 pCi/kg-wet with an average of 7000 pci/kg-wet.

AQUATIC \

All aquatic samples were collected by Environmental Consulting Services, Inc. and delivered by PSE&G personnel. Surface water samples were collected in new polyethylene containers which were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net and frozen in sealed polyethylene containers before being transported in ice chests.

32

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

Surface Water (Tables C-20, C-21, C-22, C-23)

Surface water samples were collected monthly at four indicator stations and one control station in the Delaware estuary. One location is at the outfall area (which is the area where liquid effluents from the Salem Station are discharged into the Delaware River), another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational control. All surface water samples were analyzed monthly for gross alpha, gross beta, I-131 and gamma emitters. Quarterly composites were analyzed for tritium.

• Gross alpha activity was detected in seven samples from the 48 indicator stations at concentrations ranging from 1.3 to 2.7 pCi/L and in two control station samples at 1.6 and 1.7 pCi/L. These values are within the variations of the LLD sensitivities for the remaining samples which ranged from

<1. o to <3. 6 pCi/L. The maximum preoperational level detect.ea was 27 pCi/L.

• Gross beta activity was detected in all of the 60 samples.

Concentrations for the 48 indicator station samples ranged from 8.2 to 150 pCi/L and for the 12 control station samples from 31 to 110 pCi/L. The average concentration detected for all samples, indicator and control, was 70 pCi/L. The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L.

• Tritium activity was detected in five samples from the four indicator station composites at concentrations ranging from 170 to 630 .pCi/L. There was no tritium detected from the control station composites. LLD sensitivities for the remaining composites ranged from <130 to <160 pCi/L. The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L.

• Iodine-131 was not detected in any of the 48 indicator station or 12 control station surface water samples. LLD concentrations ranged from <0.1 to <0.5 pCi/L for the indicator stations and <0.2 to <0.4 pCi/L for the control station samples. No preoperational data is available for comparison.

33

~ Gamma spectrometric analysis performed on each of the 48 indicator station and 12 control station surface water samples indicated the presence of the naturally-occurring radionuclides K-40 and Ra-226. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in 38 samples from the indicator station samples at concentrations ranging from 36 to 180 pCi/L and in eleven of the control station samples ranging from 35 to 120 pCi/L. The averages for all the locations was 80 pCi/L. LLD sensitivities measured throughout the year for the remaining samples ranged from <19 to <49 pCi/L. The maximum preoperational level detected was 200 pCi/L, with an average of 48 pCi/L.

o Radium-226 was detected in one sample out of the 48 indicator stations at a concentration of 6.8 pCi/L. This value is within the variations of the LLD sensitivities for all remaining samples measured throughout the year which ranged from <1.0 to <8.4 pCi/L. The maximum preoperational level detected was 4.0 pCi/L.

Fish (Table C-24)

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

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator station and one control station samples as management audit analysis. No tritium activity was detected in any of the six samples analyzed; LLD sensitivity was <500 to <1000 pCi/kg-wet. The maximum required LLD sensitivity value is 2000 pCi/kg-wet.

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

o Potassium-40 was detected in all four samples from the two indicator stations at concentrations ranging from 2700 to 3300 pCi/kg-wet and in both of the control station samples at 3200 pCi/kg-wet. The average for both the indicator and control station samples was 3000 pCi/kg-wet. The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2900 pCi/kg-wet.

34

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

o Strontium-89 of the bone was detected in two of the indicator station samples at 78 and 86 pCi/kg-dry and not in either of the control station samples. LLD sensitivities for the remaining samples, indicator and control, ranged from <20 to <74 pCi/kg-dry. The maximwn preoperational level detected was 100 pCi/kg-dry.

o Strontium-90 of the bone was detected in two of the four indicator station samples and in both control station samples. Concentrations in the indicator samples averaged 265 pCi/kg-dry. Concentrations in the two control samples averaged 154 pCi/kg-dry. The average for all samples was 210 pCi/kg-dry. The maximum preoperational level detected was 940 pCi/kg-dry, with an average of 335 pCi/kg-dry.

The presence of Sr-90 in the samples can be attributed to

.fallout from nuclear weapons testing.

o Strontium-89 of the flesh was not detected in any of the six indicator and control station samples. LLD sensi-tivities for the six samples, indicator and control, ranged from <26 to <48 pCi/kg-wet. The preoperational level ranged from <4.1 to <100 pCi/kg-wet.

o Strontium-90 of the flesh was not detected in any of the six indicator and control station samples. LLD sensi-tivities for the six samples, indicator and control,-*

ranged from <16 to <29 pCi/kg-wet. The maximwn preoperational level detected was 67 pCi/kg-wet.

Blue Crab (Table C-25)

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

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator samples and *two control samples as management audit analysis. No tritium activity was detected in any of the four station or control samples analyzed. LLD sensitivities for the four samples, indicator and control, ranged between <500 to <1000 pCi/kg-wet.

35

The maximum required LLD sensitivity value is 2000 pCi/kg-wet. The maximum preoperational level detected was 320 pCi/kg-wet.

Gamma spectrometric analysis on the flesh of each of the two indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclide K-40. All other gamma emitters searched for were below the Lower Limit of Detection.

o Potassium-40 was detected in both indicator station samples at concentrations of 1100 and 1600 pCi/kg-wet and in both of the control station samples at 1200 and 2800 pCi/kg-wet. The average for both the indicator and control station samples was 1700 pCi/kg-wet. The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 pCi/kg-wet.

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

o Strontium-89 of the flesh was not detected in any of the four samples, indicator nor control. LLD sensitivities for all the samples ranged from <38 to <51 pCi/kg-wet.

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

o strontium-89 of the shell was detected in all four of the indicator and control station samples. The concen-tration for the samples, indicator and control, ranged from 37 to 56 pCi/kg-dry. The average for all four station samples was 47 pCi/kg-dry. The maximum preoperational level detected was 210 pCi/kg-dry.

o Strontium-90 of the flesh was not detected in any of the four, indicator or control samples. LLD sensitivities ranged from <22 to <33 pCi/kg-wet. The maximum preoperational level detected was <150 pCi/kg-wet.

o strontium-90 of the shell was detected in both indicator station samples at 85 and 160 pCi/kg-dry and in both control station samples at 160 and 190 pCi/kg-dry. The average for both indicator and control station samples was 150 pCi/kg-dry. The maximum preoperational level detected was 990 pCi/kg-dry, with an average of 614 pCi/kg-dry.

The presence of sr-90 can be attributed to fallout from weapons testing or fallout from the Chernobyl accident.

36

• Sediment (Table C-26)

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

• Strontium-90 was not detected in any of the twelve indicator and control station samples. LLD sensitivities for these samples ranged from <19 to <26 pCi/kg-dry. The maximum preoperational level detected was 320 pCi/kg-dry.

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

In addition to the detection of the naturally-occurring radionuclides K-40, Ra-226 and Th-232, low levels of Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were also detected. All other gamma emitters searched for were <LLD.

o Cobalt-60 was detected in three of the ten indicator stations at concentrations ranging from 41 to 52 pCi/kg-dry. It was not detected at either of the two control stations. LLD sensitivities for the other nine samples, indicator and control, ranged from <6.1 to <34 pCi/kg-dry.

No preoperational data is available for comparison.

o Manganese-54 was detected in four of the ten indicator stations at concentrations ranging from 19 and .28 pCi/kg-dry. These values are within the variations of the LLD -

sensitivities for the other eight samples, indicator and control, which ranged from <4.1 to <36 pCi/kg-dry. No preoperational data is available for comparison.

o Cobalt 58 was detected in four indicator station samples at concentrations ranging from 28 to 58 pCi/kg-dry. The LLD sensitivities for the other eight samples, indicator and control, ranged from <4.8 to <26 pCi/kg-dry. No preoperational data is available for comparison.

o Cesium-134 was detected in one indicator station sample at a concentration of 47 pCi/kg-dry, and in one control station sample at 51 pCi/kg-dry. The LLD sensitivities for the other ten samples, indicator and control, ranged from <2.6 to <76 pCi/kg-dry. No preoperational data is available for comparison.

o Cesium-137 was detected in two indicator station samples at a concentration ranging from 27 to 190 pCi/kg-dry. The LLD sensitivities for the other ten samples, indicator and control, ranged from <4.5 to <55 pCi/kg-dry. The maximum preoperational level detected was 400 pCi/kg-dry.

37

o Potassium-40 was detected in all ten indicator station samples at concentrations ranging from 3100 to 18000 pCi/kg-dry, with an average of 9200 pCi/kg-dry. concen-trations detected in both of the control station samples were at 16000 and 18000 pCi/kg-dry. The average for both the indicator and control station samples was 10000 pCi/kg-dry. The maximum preoperational level detected was 21000 pCi/kg-dry, with an_ average of 15000 pCi/kg-dry.

o Radium-226 was detected in all ten indicator station samples at concentrations ranging from 170 to 810 pCi/kg-dry, with an average of 560 pCi/kg-dry. Concentrations detected in both of the control station samples were at 610 and 660 pCi/kg-dry, with an average of 640 pCi/kg-dry. The average for both the indicator and control station samples was 580 pCi/kg-dry. The maximum preoperational level detected was 1200 pCi/kg-dry, with an average of 760 pCi/kg-dry.

o Thorium-232 was detected in all ten indicator station samples at concentrations ranging from 210 to 1200 pCi/kg-dry, with an average of 680 pCi/kg-dry.

Concentrations detected in both of the control station samples were at 860 and 920 pCi/kg-dry, with an average of 890 pCi/kg-dry. The average for both the indicator and control station samples was 710 pCi/kg-dry. The maximum

• preoperational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.

38

• PROGRAM DEVIATIONS Air particulate and iodine sampler location 3H3, which is located on the roof of the Research and Testing Laboratory, was oper-ational for only 1 1/4 days out of a 7 day sampling period (for the week beginning January 7) due to an unscheduled power inter-ruption by Building Maintenance. We requested that a caution tag be placed on the breaker box in order to ensure timely notif i-cation to make arrangements for replacement power.

Air particulate and iodine sampler location 501 was operational for only 2 1/2 hours out of a 7 day sampling period (for the week beginning January 21) due to an instrument malfunction.

The air particulate filter from sampler location 5Sl became separated from the iodine filter beginning the week of March 18.

Results were invalid for the air particulate filter, as it was only attached for 1/2 day out of a 7 day sampling period.

Air particulate and iodine sampler location lFl was operational for only 3 days out of a 7 day sampling period (for the week beginning April 1) due to an instrument malfunction.

Air particulate and iodine sampler location lFl was operational for only 1 day out of a 7 day sampling period (for the week beginning April 15) due to an instrument malfunction.

Air sampler location 2F2 was vandalized on the week beginning May

6. The air particulate and iodine filter assembly was completely broken off from the conduit. There was no sample available for this week.

Air particulate and iodine filter from location 3H3 became separated from the conduit shortly after installation on the week beginning October 28. Due to the failure of the quick disconnect coupler, no sample was collected for this week. To help prevent a recurrence of this failure, all field personnel have been -

instructed on the importance of properly inspecting the air sampling equipment after servicing a location.

Precipitation (not required by the Technical Specifications) was not run for gamma spectrometric analysis in February due to insufficient sample availability. An identical rain collector was installed adjacent to the existing collector for the purpose of augmenting sample volume in times of low rainfall.

Direct radiation measurement results from location 402 for the first quarter are unavailable; the TLD was missing from the field location.

39

Potable water treated results for iodine-131 were unavailable for the month of January. Due to a computer malfunction, the analysis data/report was not retrievable from the diskette.

Effective on June 1, location 14Fl ceased dairy operations. A replacement dairy farm from the same sector was found and given the location designation of 14F4.

CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial Island was conducted during 1991 in accordance with the SGS and HCGS Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstra-ting that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.

From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment. These results were comparable to the results obtained during the preoperational phase of the program. Ambient radiation levels, as determined by TLDs collected monthly, averaged 7.1 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.

40

• TABLE 2 1991 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT

a. Air Particulate SSl SDl 16El lFl 383 Weekly Gross alpha/weekly 2F2 Gross beta/weekly sr-89 & Sr-90/first quarter**

Gamma scan/quarterly

b. Air Iodine SSl 501 16El lFl 3H3 Weekly Iodine-131/weekly

.t:'- 2F2 N

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

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

_r

~ .'

TABLE 2 (cont'd) 1991 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

a. Thermoluminescent 4D2 9El 2FS 1G3 Quarterly Gamma dose/quarterly Dosimeters (cont'd) 11E2 3F2 lOGl 12El 3F3 16Gl 10F2 12Fl 13F2 13F3 14F2 15F3 16F2 III. TERRESTRIAL ENVIRONMENT

a. Milk 2F7 3Gl Monthly Iodine-131/monthly (when animals Gamma scan/monthly 11F3 are not on pasture) 14Fl/ Semi-monthly Iodine-131/semi-monthly 14F4(1) (when animals Gamma scan/semi~monthly are on sr-89 & Sr-90/July, first pasture) collection**

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

TABLE 2 (cont'd) 1991 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

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

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

~

~

3E3 4F2 2Gl (at harvest)

SF3 14F3

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

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

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

h. Soil 6Sl lODl 16El lFl 3Gl Collect sr-90/on collection 2F4 from each Gamma scan/on collection 2F7 location SFl once every 11F3 three years 14Fl

TABLE 2 (cont'd) 1991 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS IV. AQUATIC ENVIRONMENT

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

b. Edible Fish llAl 7El 12Cl Semi- Tritium (flesh)

~

VI annually Aqueous fraction/on collection**

Sr-89 & sr-90 (bonee)/on collection**

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

Gamma scan (flesh)/on collection

c. Blue Crabs llAl 12Cl Semi- Tritium (flesh) annually Aqueous fraction/on collection**

Sr-89 & Sr-90 (flesh)/on collection Sr-89 & Sr-90 (ehell)/on collection Gamma scan (fleeh)/on collection

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

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

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

(l) On June 1, 1991, location 14F4 replaced 14Fl as our dairy farm.

FIGURE 6 BETA IN PRECIPITATION AND AIR PARTICULATE 1973 THROUGH 1991 LEGEND tt' **

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FIGURE6A BETA IN PRECIPITATION AND AIR PARTICULATE 1986 THROUGH 1991 LEGEND

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FIGURE 7 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1973 THROUGH 1991 10--~~~~~~~~~~~~~~~~~~~~~~~~~~~--~~~~~~~~--

LEGEND

- OFFSITE STATIONS

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- - - CONTROLSTATIONS c 06-17-'r~ 09 QUARTERLY AVERAGE 0 8 E Weapons Test Q9.26.'r6 Weapons Test 03-14-?'8 E

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FIGURE7A AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1986 TllROUGH 1991 LEGEND

- OFFSITE STATIONS 10 - - - *CONTROLSTATIONS MONTHLY AVERAGE

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FIGURES IODINE-131 ACTil"ITY IN MILK 1973 THROUGH 1991 20

.. Wea~ons Test I QUARTERLY AVERAGE 09 6 15 IJ1 0

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Chernobyl 5 - 04-26-86 W~1nsTest 08 :.t 0 A j l

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• FIGURE SA IODINE-131 ACTIVITY IN MILK 1986 THROUGH 1991 20 19 -

18 - I MONTHLY AVERAGE 17 - - Chernobyl 16 - 04-26-86 15 -

14 -

13 -

12 -

11 -

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FIGURE 9 GROSS BETA & K-40 ACTIVITIY IN SURFACE WATER 1973 THROUGH ~991 1000-----------------------------------------------------------------.... LEGEND

- GROSSBETA K-40 Weap0ns Test Weap0ns Test QUARTERLY AVERAGE (16..17-14 I 09-17-17 I Weap0ns Test Weapons Test Chernobyl IJ9.28.1e I 03-14-18 04-28-88 100 ~ * * * * * * * * * * * * * * * * * * * * * * * * * *~* * * * *

• t* * * * * * * * * * * * *

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

~

-., ~2 i

e as . . .

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a..N

~ 0

• -~

t: t-- 0 ~~

o- ~ 0

• 0 I

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0 c) ~

E

~

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as CD D..*-

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!E iii t- rD ~ :co 1975 1979 1983 1987 1991 1973 19n 1981 1985 1989

• --~

FIGURE9A GROSS BETA & K-40 ACTIVITIY IN SURFACE WATER 1986 THROUGH 1991 1000 -----------------------------------------------------------------------

LEGEND

- GROSSBETA

- - - K-40 MONTHLY AVERAGE 100 lJ1 VJ 10 -----

1986 1988 1990 1 1987 1989 1991

FIGURE 10 TRITIUM ACTIVITY IN SURFACE WATER 1973 THROUGH 1991 10000------------------------------------------------------------- QUARTERLY AVERAGE 1000 06-17-14 j Weapons Test Weapons Test

' Weapo s Test 09-17-17 09-26-18 100 le 2 I- .:.. ~

z ~

.... ~

CD 2 ~i c( ... 0

-i~"'

Q (I) 1' -

~

1' 6 th ii .... tb .:e IL I- :i.: ..

.a 0

-z 1i :e= 1i ~u

~~

ZUJ u ~ J! u ~

~~ ....

E I

lI ~

0

~

E I:!0 a.

iOUi E ct

.! .! I II a.

fl) ~ ~

• OJ ~

.c 0 u :::c 1973 1979 1983 1987 1991 1975 1977 1981 1985 1989

FIGURE 10A TRITIUM ACTIVITY IN SURFACE WATER 1986 THROUGH 1991 10000--------------------------------------------~----.----------- MONTHLY AVERAGE 1000 Chernobyl 04-26-86 j

l.J1 l.J1 100 ............................................................................................................................................................................. .

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

1986 1988 1990 1992 1987 1989 1991

REFERENCES

[l] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Annual Reports 1973 through 1982".

[2] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Preoperation summary - 1973 through 1976". RMC-TR-77-03, 1978.

[3] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976".

RMC-TR-77-02, 1977.

[4] PSE&G Research Corporation, Research and Testing Laboratory.

"Artificial Island Radiological Environmental Monitoring Program -

Annual Reports 1983 through 1990".

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

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

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

Salem Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311. 1973.

[8] United States Atomic Energy commission. "Final Environmental Statement -

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

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

[10] Public Service Electric and Gas Company. "Updated Final Safety Analysis Report - Hope Creek Generating Station. 1984.

[ll] 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 et seq).

[12] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix A to Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.1.10 (Amendment 28 et seq).

56

REFERENCES (cont'd)

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

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

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

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

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

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

[19] Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, SGS RERR-28 and RERR Salem Generating Station. 1990.

Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, HCGS RERR-9 and RERR Hope Creek Generating Station. 1990.

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

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

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

57

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND - LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER Ll~IT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS AIRBORNE Afr Particulates Alpha 310 1.0 2.7 (195/259) 16E 1 4. 1 mi NNW 2.9 (50/52) 2.4 (47/51> 0 (10-3 pCi/m3) (1.1-7.7) (1.2-7.7) (0.8-4.4) 0

°'

Beta 310 6.0 23 (255/259) 2F2 8. 7 mi NNE 24 (51/51) 22 (50/51) 0 (6-45) (8.6-40) (8.9-36)

Sr-89 6 0.2 <LLD <LLD <LLD 0 Sr-90 6 0.2 <LLD <LLD <LLD 0 Gamma Be-7 24 6.8 64 (20/20) 5D1 3.5 mi E 105 (2/3) 54 (4/4)

(41-114) (90-120) (39-70) 0 K-40 24 7 .1 536 (3/20) 5D1 3.5 mi E 536 (2/4) <LLD 0 (15-1320) (273-1320)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION HEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS AIRBORNE (Cont'd)

Al r Iodine 1-131 310 13 <LLD <LLD <LLD 0 (10-3 pCl/m3)

°'"' Pree I pit et I on Alpha 12 1.5 1.1 (2/12) 2F2 8. 7 mi NNE 1.1 ( 2/12) No Control D (pCl/L) (0.9-1.3) (0.9-1.3) Location Beta 12 2.0*** 4. 1 (12/12) 2F2 8. 7 mi NNE 4. 1 ( 12/12) No Control 0 (0.9-14) (0.9-14) Location H-3 12 150 150 (2/12) 2F2 8. 7 mi NNE 150 (2/12) No Control 0 (140-160) (140-160) Location Gamma Be-7 11 15 50 (8/11) 2F2 8.7 mi NNE 50 (8/11) No Control 0 (32-74) (32-74) Location II DIRECT Direct Radiation Gemme 288 7.0 (252/252) 11S1 0. 09 mi SW 9.0 (12/12) 7.0 (36/36) 0 (mrad/std. month) Dose (monthly) (4-12) (7-12) (5-9)

Gamma 163 5.0 (139/140) 11S1 0.09 mi SW 7.1 (4/4) 5.0 (24/24) 0 Dose (qtrly. > (3-10) (5-10) (4-6)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR. LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS 111 TERRESTRIAL Milk 1-131 80 0.4 <LLD <LLD <LLD 0 (pCf/L)

Sr-89 4 1.1 <LLD <LLD <LLD

°'

w 0 Sr*90 4 0.9 2.7 (3/3) 2F7 5.7 mi NNE 3.5 (1/1) 3.0 (1/1) 0 (1.2-3.5) (3.5) (3.0)

Gamma K-40 80 120 1400 (60/60) 2F7 5. 7 mi NNE 1400 (20/20) 1400 (20/20) 0 (1100-1700) (1200-1500) (1300-1500)

Ra-226 80 6.6 <LLD <LLD <LLD 0 Well Water Alpha 24 1.2 <LLD 3E1 4.1 mi NE 1.1 (2/12) 1.1 (2/12) 0 CpCf/L) (1.0-1.2) (1.0-1.2)

Beta 24 1.0*** 4.6 (12/12) 3E1 4.1 mi NE 10.3 (12/12) 10.3 (12/12) 0 (3.1-8.2) (9.9-11) (9.9-11)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Ill TERRESTRIAL (Cont'd)

Well Water K-40 24 4.3 (12/12) 3E1 4.1 mi NE 9.5 (12/12) 9.5 (12/12) 0 (pCl/L) (2.6-7.6) (8.6-10) (8.6-10)

°'

.i:-

H-3 24 150 260 (1/12) 2S3 700 ft. NNE 260 (1/12) 240 (2/12) 0 (260) (260) (190-280)

Sr-89 8 1.0 <LLD <LLD <LLD 0 Sr-90 8 0.6 <LLD <LLD <LLD 0 Gamma K-40 24 35 <LLD <LLD <LLD 0 1-131 24 0.6 <LLD <LLD <LLD 0 Ra-226 24 7.4 41 (7/12) 3E1 4.1 mi NE 155 (12/12) 155 (12/12) 0 (10-110) (110-190) (110-190)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANAL YS I Sc AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Ill TERRESTRIAL (Cont'd)

Potable Water Alpha 24 1.0 1.1 (5/24) 2F3 8.0 mi NNE 1.1 (5/24) No Control 0 Raw* Treated

°'

VI (pCi/L)

(0.8*2.1) (0.8-2.1) Location Beta 24 1.0*** 2.9 (24/24) 2F3 8.0 mi NNE 2.9 (24/24) No Control 0 (2.0-3.8) (2.0-3.8) Location K-40 24 1.9 (24/24) 2F3 8.0 mi NNE 1.9 (24/24) No Control 0 (1.4-2. 7) (1.4-2. 7) Location H-3 24 150 210 (4/24) 2F3 8.0 mi NNE 210 (4/24) No Control 0 (140-290) (140-290) Location Sr-89 8 1.0 <LLD <LLD No Control 0 Location Sr-90 8 0.8 <LLD <LLD No Control 0 Location

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS 111 TERRESTRIAL (Cont'd)

Potable Water 1-131 24 0.6 <LLD <LLD No Control 0 Raw-Treated Location

°'

°' Gamma K-40 24 35 17 ( 1/24) 2F3 8.0 mi NNE 17 (1/24) No Control 0 (17) ( 17) Location Ra-226 24 7.4 <LLD 2F3 8.0 mi NNE <LLD No Control 0 Location Fruits & Gamma Vegetables K-40 20 70 2400 (12/12) 5F3 6.4 mi E 4600 (1/1) 2100 (8/8) 0 CpCf/kg-wet) (1300-4600) (4600) (1400-2700)

Game Gamma (pCf/kg-wet) K-40 2 70 2200 (1/1) 3E1 4.1 mi NE 2200 (1/1) 2100 (1/1) 0 (2200) (2200) (2100)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEH COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME HEAN HEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS 111 TERRESTRIAL (Cont'd)

Beef Gamma K-40 70 2800 (1/1) 3E 1 4. 1 mi NE 2800 (1/1) No Control 0 (2800) (2800) Location

°'

Fodder Crops Gamma (pCi/kg-wet) Be-7 9 580 650 (3/9) 2F7 5. 7 mi NNE 840 c1/2) 300 (1/2) 0 (520-840) (840) (300)

K-40 9 85 9600 (7/7) 14F4 7.6 mi WNW 10000 (2/2) 8500 (2/2) 0 (3000-15000) (5100-15000) (4000-13000)

IV AQUATIC surface Water Alpha 60 2.0 1.8 (7/48) 16F1 6.9 mi NNW 2.1 (3/12) 1. 7 (2/12) 0 (pCi/L) (1.3-2. 7) (1.5-2.7) (1.6-1.7)

Beta 60 3.8*** 71 (48/48) 7E1 4.5 mi SE 108 (12/12) 65 (12/12) 0 (8.2-150) (62-150) (31-110)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF

. MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN HEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) HEASUREl4ENTS IV AQUATIC (Cont'd)

Surf ace Water H-3 20 150 320 (5/16) 11A1 0.2 mi SW 390 (3/4) <LLD (pCl/L) (170-630) (170-630) 0

°'

00 1-131 60 0.6 <LLD <LLD <LLD 0 Gamma K-40 60 35 92 (38/60) 7E1 4.5 mi SE 106 (12/12) 85 (11/12) 0 (36-180) (57-160) (35-120)

Ra-226 60 7.4 6.8 (1/48) 11A1 0.2 mi SW 6.8 (1/12) <LLD 0 (6.8) (6.8)

Blue Crabs Sr-89 4 60 49 (2/2) 11A1 0.2 mi SIJ 49 (2/2) 44 (2/2) 0 (pCl/kg-dry) (shells) (42-56) (42-56) (37-52)

Sr-90 4 123 (2/2) 12C1 2.5 mi IJSW 175 (2/2) 175 (2/2) 0 (shells) (85-160) (160-190) (160-190)

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

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

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC (Cont'd)

Blue Crabs Sr-90 4 40 <LLD <LLD <LLD 0 (pCi/kg-wet) (flesh)

°'

\0 Gamma K-40 4 70 1350 (2/2) 12C1 2.5 mi WSW 2000 (2/2) 2000 (2/2) 0 (1100-1600) (1200-2800) (1200-2800)

Edible Fish Sr-89 6 75 82 (2/4) 11A1 0.2 mi SW 86 ( 1/2) <LLD 0 (pCi/kg-dry) (bones) (78-86) (86)

Sr-90 6 25 265 (2/4) 7E1 4. 5 mi SE 280 (1/2) 154 (2/2) 0 (bones) (250-280) (280) (28-280)

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

Sr-89 6 100 <LLD <LLD <LLD 0 (flesh)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF All INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN"* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC (Cont'd)

Edible Fish Sr-90 6 40 <LLD <LLD <LLD 0 (pCl/kg-dry) Cf Lesh) 0 Gamma K-40 6 70 3000 (4/4) 12C1 2.5 mi WSW 3200 (2/2) 3200 (2/2) 0 (2700-3300) (3200) (3200)

Ra-226 6 36 <LLD <LLD <LLD 0 Sediment Sr-90 12 25 <LLD <LLD <LLD 0 CpCl/kg-dry)

Gamma K-40 12 640 9200 (10/10) 12C1 2.5 ml WSW 17000 (2/2) 17000 (2/2) 0 (3100-18000) (16000-18000) (16000-18000)

Mn-54 12 35 25 (4/10) 16A1 0.7 ml NNW 28 (1/2) <LLD 0 (19-28) (28) 15A1 0.3 mi NW 28 (1/2)

(28)

Co-58 12 58 37 (4/10) 11A1 0.2 mi SW 45 (2/2) <LLD 0 (28-58) (32-58)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1991 to DECEMBER 31, 1991 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS IV AQUATIC tCont'd)

Sediment Co-60 12 32 47 (3/10) 11A1 0.2 mi SW 52 (1/2) <LLO 0 CpCi/kg-dry) (41-52> (52)

Cs-134 12 22 47 (1/10) 12C1 2.5 mi WSW 51 (1/2) 51 (1/2) 0 (47) (51) (51)

Cs-137 12 20 109 (2/10) 15A1 0.3 mi NW 190 ( 1/2) <LLD 0 (27-190) (190)

Ra-226 12 40 564 (10/10) 15A1 0.3 mi NW 725 (2/2) 635 (2/2) 0 (170-810) (640-810) (610-660)

Th-232 12 110 675 (10/10) 15A1 0.3 mi NW 970 (2/2) 890 (2/2) 0 (210-1200) (740-1200) (860-920)

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

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

• • • Typical LLD value.

APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 73

APPENDIX B SAMPLE DESIGNATION The PSE&G Research And Testing Laboratory identifies samples by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled.

AIO Air Iodine IDM = Immersion Dose (TLD)

APT = Air Particulates MLK Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)

ESF = Edible Fish PWT = Potable Water (Treated)

ESS = Sediment RWA Rain Water (Precipitation)

FPB Beef SOL Soil FPL = Green Leafy Vegetables SWA = Surface Water FPV Vegetables (Various) VGT Fodder crops (Various)

GAM = Game (Muskrat) WWA = Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clock-wise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant:

s = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-site D 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, *** For example, the designation SA-WWA-3El would indicate a sample in the SGS program (SA), consisting of well water (WWA), which had been collected in sector number 3, centered .at 45° (north east) with respect to the reactor site at a radial distance of 4 to 5 miles off-site, (therefore, radial distance E). The number 1 indicates that this is sampling station #1 in that particular sector *

• 75

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

TABLE B-1 STATION CODE STATION LOCATION SAMPLE TYPES 2S2 0.4 mi. NNE of vent IDM 2S3 700 ft. NNE of vent; fresh water holding tank WWA 5Sl 1.0 mi. E of vent; site access road AIO,APT,IDM 6S2 0.2 mi. ESE of vent; observation building IDM,SOL 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM llSl 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area ECH,ESF,ESS,SWA 15Al 0.3 mi. NW of vent; cooling tower blowdown ESS discharge line outfall 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 12Cl 2.5 mi. WSW of vent; west bank of Delaware River ECH,ESF,ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM,VGT 5Dl 3.5 mi. E of vent; local farm AIO,APT,IDM lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur IDM,SOL llDl 3.5 mi. SW of vent GAM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm IDM 3El 4.1 mi. NE of vent; local farm FPB,GAM,IDM,VGT WWA 3E2 5.7 mi. NE of vent; local farm FPV 76

TABLE B-1 (cont'd)

STATION CODE STATION LOCATION SAMPLE TYPES 3E3 5.6 mi. NE of vent; local farm FPV 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek ESF,ESS,SWA 9El 4.2 mi. s of vent IDM 11E2 5.0 mi. SW of vent IDM 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM 16El 4.1 mi. NNW of vent; Port Penn AIO,APT,IDM,SOL lFl 5.8 mi. N of vent; Fort Elf sborg AIO,APT,IDM,SOL 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA 2F2 8.7 mi. NNE of vent; Salem Substc.tion AIO,APT,IDM,RWA 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm FPV,FPL,SOL 2F5 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southern Training Center IDM 2F7 5.7 mi. NNE of vent; local farm MLK,VGT,SOL 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal IDM Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 5Fl 6.5 mi. E of vent FPV,IDM,SOL 5F3 6.4 mi. E of vent; local farm FPL 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM

• 77

TABLE B-1 (cont'd)

STATION CODE STATION LOCATION SAMPLE TYPES llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 11F3 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT,SOL 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM 13F2 6.5 mi. w of vent; Odessa, Delaware IDM 13F3 9.3 mi. W of vent; Redding Middle School, IDM Middletown, Delaware 13F4 9.8 mi. W of vent; Middletown, Delaware IDM 14Fl 5.5 mi. WNW of vent; local farm MLK,VGT,SOL 14F2 6.6 mi. WNW of vent; Boyas Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV 14F4 7.6 mi. WNW of vent; local farm MLK,VGT,SOL 15F3 16Fl 16F2 5.4 mi. NW of vent 6.9 mi. NNW of vent; C&D Canal 8.1 mi. NNW of vent; Delaware City Public School IDM ESS,SWA IDM lGl 10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of vent; Wilmington, Delaware IDM 2Gl 12 mi. NNE of vent; Mannington Township, NJ FPV 3Gl 17 mi. NE of vent; local farm IDM,MLK,VGT,SOL lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 3Hl 32 mi. NE of vent; National Park, New Jersey IDM 3H3 110 mi. NE of vent; Research and Testing AIO,APT,IDM Laboratory 3H5 25 mi. NE of vent; local farm FPL,FPV 78

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

15 3

5 M UM EXCLUS!

AREA BOUNDA C901 METE )

11 7

N 9

79

MAP 8-2 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM OFF-SITE SAMPLING LOCATION 15 14 12 11 Fl 10 SSE 8 80

• APPENDIX C DATA TABLES

• . 81

APPENDIX C DATA TABLES Appendix C presents the analytical results of the 1991 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1991.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1991 Concentrations of Gross Alpha Emitters ******************** 86 C-2 1991 Concentrations of Gross Beta Emitters ********************* 88 C-3 1991 Concentrations of Strontium-89 and Strontium-90 aud Gamma Emitters in Quarterly Composites ******************** 90 AIR IODINE C-4 1991 Concentrations of Iodine-131 ****************************** 91 DATES c-s 1991 Sampling Dates for Air Samples **************************** 93 PRECIPITATION C-6 1991 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium and Gamma Emitters ...*................**.*...*.... 98 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-7 1991 Quarterly TLD Results ************************************* 99 C-8 1991 Monthly TLD Results *************************************** 100 83

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT MILK C-9 1991 Concentrations of Iodine-131 and Ganuna Emitters *********** 102 C-10 1991 Concentrations of Strontium-89 and Strontium-90 *********** 104 WELL WATER C-11 1991 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium ********************************** 105 C-12 1991 Concentrations of Iodine 131 and Ganuna Emitters *********** 106 C-13 1991 Concentrativns of Strontium-89 and Strontium-90 in Quarter 1 y Composites ************************************** 107 POTABLE WATER C-14 1991 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 108 C-15 1991 Concentrations of Iodine 131 and Ganuna Emitters *********** 109 C-16 1991 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites.. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 110 FOOD PRODUCTS C-17 1991 Concentrations of Gamma Emitters in Vegetables ************ 111 C-18 1991 Concentrations of Gamma Emitters in Beef and Game ********* 112 FODDER CROPS C-19 1991 Concentrations of Gamma Emitters ************************** 113 84

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER C-20 1991 Concentrations of Gross Alpha Emitters ****************.*** 114 C-21 1991 Concentrations of Gross Beta Emitters *****..*.***.******** 115 C-22 1991 Concentrations of Iodine 131 and Gamma Emitters *..****..** 116 C-23 1991 Concentrations of Tritium in Quarterly Composites .*.**..** 118 EDIBLE FISH C-24 1991 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters................................ 119

• C-25 BLUE CRABS 1991 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters............................... 120 SEDIMENT C-26 1991 Concentrations of Strontium-90 and Gamma Emitters ********* 121 SPECIAL TABLES LLDs C-27 1991 PSE&G Research and Testing Laboratory LLDs for Gamma Spectrometry. . * * * * * * * * * * * . * * * * * * * * * * * * . * * * * * * * * * * * *

• 122

• 85

TABLE C-1 1991 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10* 3 pCi/m3 +/- 2 sigma 1t

<--------------------------------- STATION ID 1t 1t MONTH SA-APT-SSl SA-APT-SD! SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JANUARY 3.7+/-1.0 <4.0 2.8+/-0.9 2.8+/-1.0 2. 8+/-1. 0 1. 9+/-0. 8 2.8+/-1.2

1. 9+/-0. 8 <5.0 1. 6+/-0. 8 1.1+/-0. 7 1.9+/-0.7 <3.8 ( 1) 1. 6+/-0. 7 2.4+/-0.9 <5.0 1.8+/-0.8 2.1+/-0.8 2.2+/-0.8 3.0+/-0.9 2.3+/-0.8 2.3+/-0.8 <5.0 ( 2) 4.1+/-0.9 3.6+/-1.0 1. 9+/-0. 7 2.2+/-0.8 2.8+/-1.8

1. 8+/-0. 8 <5.0 3. 4+/-1.0 3.1+/-1.0 3 .1+/-0. 9 2.4+/-0.8 2.8+/-1.2 FEBRUARY 3.5+/-1.0 <5.0 3.1+/-1.0 4.2+/-1.2 4.4+/-1.1 2.2+/-0.9 3.5+/-1.6 2.8+/-0.9 <5.0 2.8+/-0.9 2.8+/-0.9 1. 6+/-0. 7 2 .1+/-0. 7 2.4+/-1.0 2.7+/-1.1 <5.0 1.8+/-1.0 1. 7+/-1.1 2.2+/-1.0 1. 9+/-1.1 2.1+/-0.7 3.4+/-1.0 <5.0 2.3+/-0.9 2.1+/-0.9 2.0+/-0.8 1.1+/-0. 7 2.2+/-1.5 MARCH 3.4+/-1.0 <5.0 4.4+/-1.2 3.6+/-1.2 3.2+/-0.9 2 .9+/-1.0 3.5+/-1.0 00 2.2+/-0.9 <5.0 1. 6+/-0. 9 1.7+/-0.9 1. 6+/-0. 8 1. 4+/-0. 7 1. 7+/-0. 5

°' <12 3.0+/-1.0

( 2) <5.0

<5.0

<1.3 2.2+/-0.9 2.4+/-1.0 3.4+/-1.1 2.4+/-0.9

1. 6+/-0 .8 2.9+/-1.0 2.0+/-0.8 2.3+/-1.2 2.4+/-1.4 APRIL 2.4+/-0.9 <5.0 1. 8+/-0. 9 <1.6 (2) 2.8+/-0.9 2.4+/-0.8 2.4+/-0.7 3.2+/-0.9 <5.0 3. 0+/-1.0 2.6+/-0.9 2.8+/-0.9 3.2+/-0.9 3.0+/-0.5

1. 4+/-0. 8 <5.0 1.2+/-0.8 <6.2 (2) 2.1+/-0.8 1. 5+/-0. 7 1. 6+/-0. 7 2 .1+/-0. 9 <5.0 2.9+/-1.0 1.8+/-0.9 2.7+/-0.9 2.1+/-0.9 2.3+/-0.8 MAY 2.0+/-0.8 <5.0 2.8+/-0.9 2.7+/-0.9 1. 8+/-0. 7 1. 9+/-0. 7 2.2+/-0.9 2 .1+/-0. 8 <5.0 3.1+/-1.l 2.9+/-0.9 ( 3) 2 .1+/-0.9 2.6+/-0.9 2.1+/-0.9 <5.0 2. 4+/-1.0 2.3+/-1.0 2.9+/-1.0 2.6+/-0.9 2.5+/-0.6 3.0+/-1. 0 <5.0 3 .1+/-1.1 2.8+/-1.0 2.6+/-1.0 1. 8+/-0. 9 2.7+/-0.9 JUNE 3.2+/-1.1 <5.0 2. 3+/-1.1 3 .1+/-1.1 4.1+/-1.2 3.4+/-1.1 3.2+/-1.2 2.4+/-0.9 <5.0 3. 6+/-1. 0 2.8+/-0.9 1.8+/-0.8 1.5+/-0.7 2.4+/-1.5

3. 3+/-1. 0 <5.0 3.0+/-1.2 3.5+/-1.0 3.3+/-1.0 2.9+/-0.9 3.2+/-0.4

<1.2 <5.0 1. 7+/-1.0 1. 6+/-0. 9 <1.2 1. 3+/-0. 9 1.4+/-0.4

<0.7 <5.0 <0.9 <0.8 <0.8 0.8+/-0.6

TABLE 1991 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma

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

MONTH SA-APT-5Sl **

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

JULY 1. 3+/-0. 8 <5.0 2.1+/-1.0 1.9+/-0.9 i. 2+/-0. 0 <0.9 1. 5+/-0. 9 2.1+/-0.8 <5.0 2.5+/-0.9 2.2+/-0.8 1. 6+/-0. 7 2.5+/-0.8 2.2+/-0.7 2.4+/-0.9 <5.0 2.8+/-1.0 3.2+/-1.0 2.9+/-1.0 2.0+/-0.8 2.7+/-0.9 2.1+/-0.8 <5.0 2.3+/-1.0 2.2+/-0.9 2.7+/-0.9 2.4+/-0.9 2.3+/-0.4 AUGUST 3.2+/-1.0 <5.0 4.3+/-1.1 4. 6+/-1.1 3.5+/-1.0 1. 3+/-0. 6 3.4+/-2.4 1.8+/-0. 7 <5.0 2.9+/-0.9 2.2+/-0.8 2 .1+/-0. 7 1.8+/-0.7 2.2+/-0.8 3.8+/-1.0 <5.0 2.7+/-0.9 2.4+/-0.8 2.4+/-0.9 1.5+/-0.7 2.6+/-1.5 2.0+/-0.8 <5.0 4. 2+/-1.1 i. 0+/-0. 0 1. 4+/-0. 7 2.0+/-0.8 2.3+/-2.0 SEPTEMBER 1.4+/-0. 7 <5.0 3.4+/-1.1 3.4+/-0.9 4.4+/-1.1 <0.7 2.7+/-2.8

1. 8+/-0. 8 <5.0 4.6+/-1.2 2.6+/-0.9 3.7+/-1.0 3.1+/-0. 9 3.2+/-1.9 00 2.0+/-0.8 <5.0 2.2+/-0.9 1. 6+/-0.8 2.7+/-0.9 1.2+/-0.7 1. 9+/-1. 0

-..J <2.0 <5.0 3.1+/-1.1 3.2+/-1.0 1. 8+/-0. 8 2.6+/-0.9 2. 5+/-1.2 2.2+/-0.8 <5.0 2.0+/-0.8 1.9+/-0.8 1. 4+/-0. 7 <0.7 1. 6+/-1.1 OCTOBER 2.4+/-0.8 <5.0 3.5+/-1.0 2.6+/-0.8 4.2+/-1.0 2.8+/-0.8 3.1+/-1.4

<0.7 <5.0 3-1+/-0.9 2.7+/-0.8 1. 3+/ 6 3.0+/-0.8 2.2+/-2.0 2.8+/-1.0 <5.0 3. 8+/-1. 2 2.9+/-1.0 1. 4+/-0. 8 2.0+/-0.9 2.6+/-1.7 2.3+/-0.8 <5.0 4.1+/-1.0 3.2+/-0.9 3.7+/-1.0 4.4+/-1.0 3.5+/-1.5 NOVEMBER 2.3+/-0.7 <5.0 2.5+/-0.8 2.7+/-0.8 2.6+/-0.8 (4) 2.5+/-0.3 4.7+/-0.9 <5.0 4.5+/-1.0 5.1+/-1.0 4.1+/-0.9 3.2+/-0.8 4.3+/-1.3

4. 7+/-1. l <5.0 7. 7+/-1.4 7. 3+/-1. 3 5.9+/-1.2 4.3+/-1.1 6.0+/-2.8

1. 7+/-0. 8 <5.0 1. 4+/-0. 8 1.4+/-0.8 i. 6+/-0. 0 2 .1+/-0. 9 1. 6+/-0. 5 2.1+/-0.7 <5.0 1. 5+/-0. 7 2.0+/-0.8 3.4+/-0.9 3.3+/-0.9 2.5+/-1.5 DECEMBER 2.8+/-0.8 <5.0 2.8+/-0.9 2.9+/-0.9 3.2+/-0.9 3 .1+/-0. 9 3.0+/-0.3 2 .1+/-0. 7 <5.0 2.2+/-0.8 2.3+/-0.8 3.1+/-0. 9 3.2+/-0.* 9 2. 6+/-1.0 2.6+/-0.8 <5.0 2.3+/-0.7 2.5+/-0.8 1. 9+/-0. 7 3.0+/-0.9 2.5+/-0.7 2.5+/-0.8 <5.0 2.0+/-0.7 1. 9+/-0. 7 2 .1+/-0. 7 2.2+/-0.8 2.1+/-0.4 AVERAGE 2.4+/-1.7 2.8+/-2.3 2.7+/-2.1 2.6+/-2.1 2.3+/-1.7 GRAND AVERAGE 2.5+/-2.0

• Sampling dates can be found in Table c~5.

• • Results by Controls for Environmental Pollution, Inc.

(1) Unscheduled power interruption br Building Maintenance. :Results not included in any averages)

(2) Reduced sampling period due to a r sampler malfunction. (Results not included in any averages)

(3) Air sam~ler location was vandalized. No sample was collected.

(4) Quick disconnect coupler failed causing APT/AIO Holder to separate from conduit shortly after installation. No sample was collected for this week.

TABLE C-2 1991 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Unite of 10*3 pci/m3 +/- 2 sigma 1t

<--------------------------------- STATION ID 1t 1t MONTH SA-APT-5Sl SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JANUARY 29+/-3 26+/-2 28+/-3 32+/-3 29+/-3 28+/-3 29+/-4 19+/-2 18+/-2 16+/-2 17+/-2 20+/-2 37+/-10(1) 18+/-3 21+/-3 21+/-2 20+/-3 20+/-3 20+/-2 23+/-3 21+/-2 32+/-3 <87(2) 32+/-3 31+/-3 31+/-3 29+/-3 31+/-2 32+/-3 27+/-2 30+/-3 35+/-3 31+/-3 34+/-3 32+/-5 FEBRUARY 33+/-3 33+/-2 32+/-3 35+/-3 34+/-3 20+/-2 31+/-10 21+/-2 21+/-2 20+/-2 21+/-2 19+/-2 18+/-2 20+/-2 18+/-3 14+/-2 16+/-2 18+/-3 20+/-3 22+/-3 18+/-5 20+/-3 16+/-2 17+/-3 21+/-3 22+/-3 13+/-2 18+/-6 MARCH 29+/-3 23+/-2 29+/-3 27+/-3 30+/-3 20+/-2 26+/-7 00 14+/-2 12+/-2 16+/-2 16+/-2 15+/-2 15+/-2 15+/-3 00 43+/-20(2) 16+/-2 18+/-3 20+/-3 17+/-2 18+/-2 18+/-3 21+/-2 19+/-2 21+/-3 21+/-3 20+/-2 21+/-2 20+/-2 APRIL 28+/-3 33+/-2 26+/-3 20+/-4(2) 25+/-2 24+/-2 27+/-6 20+/-2 17+/-2 21+/-3 23+/-3 23+/-3 26+/-3 22+/-6 18+/-3 33+/-2 18+/-3 <20(2) 18+/-2 15+/-2 20+/-13 22+/-3 19+/-2 24+/-3 21+/-3 23+/-3 24+/-3 22+/-4 MAY 16+/-2 16+/-2 16+/-3 17+/-2 19+/-2 15+/-2 16+/-3 25+/-3 23+/-2 24+/-3 23+/-2 (3) 16+/-2 22+/-6 21+/-2 17+/-2 24+/-3 21+/-3 23+/-2 26+/-3 22+/-6 22+/-2 24+/-2 25+/-2 24+/-2 25+/-2 20+/-2 23+/-4 JUNE 24+/-3 16+/-2 27+/-3 24+/-3 26+/-3 20+/-3 23+/-8 13+/-2 16+/-2 19+/-2 14+/-2 17+/-2 15+/-2 16+/-4 25+/-2 18+/-2 28+/-3 26+/-3 27+/-3 25+/-2 25+/-7 18+/-2 13+/-2 16+/-3 16+/-3 15+/-2 16+/-2 16+/-3 21+/-2 18+/-2 20+/-3 19+/-2 21+/-2 28+/-3 21+/-7

1991 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10" 3 pCi/m3 +/- 2 sigma

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

MONTH SA-APT-5Sl **

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

JULY 19+/-3 17+/-2 18+/-3 16+/-2 20+/-3 8.9+/-2.0 16+/-7 27+/-3 22+/-2 25+/-3 21+/-2 26+/-2 21+/-2 24+/-5 30+/-3 31+/-2 29+/-3 27+/-3 30+/-3 17+/-2 27+/-10 24+/-2 20+/-2 22+/-3 16+/-2 25+/-2 24+/-2 22+/-6 AUGUST 28+/-3 28+/-2 28+/-3 32+/-3 30+/-3 13+/-2 26+/-13 16+/-2 12+/-2 17+/-3 16+/-2 18+/-2 14+/-2 16+/-4 28+/-3 28+/-2 26+/-3 25+/-2 27+/-3 14+/-2 25+/-10 29+/-3 23+/-2 36+/-4 26+/-3 28+/-3 23+/-3 28+/-9 SEPTEMBER 21+/-2 20+/-2 26+/-3 22+/-2 22+/-2 12+/-2 20+/-9 26+/-3 45+/-4 27+/-3 29+/-3 26+/-3 27+/-3 30+/-14 00 27+/-3 11+/-1 27+/-3 24+/-3 25+/-3 12+/-2 21+/-14

\0 23+/-2 18+/-2 22+/-3 22+/-3 23+/-3 24+/-2 22+/-4 29+/-3 19+/-2 25+/-3 23+/-2 25+/-3 9.0+/-1.8 22+/-13 OCTOBER 24+/-3 6+/-1 26+/-3 21+/-3 26+/-3 28+/-3 22+/-15 7.4+/-1.6 13+/-2 25+/-2 23+/-2 8. 6+/-1. 7 25+/-2 17+/-15 23+/-3 16+/-2 24+/-3 24+/-3 11+/-2 22+/-3 20+/-10 17+/-2 19+/-2 27+/-2 24+/-2 26+/-2 36+/-3 25+/-12 NOVEMBER 25+/-2 24+/-2 25+/-2 26+/-2 26+/-2 (4) 25+/-2 36+/-2 37+/-2 29+/-2 41+/-3 35+/-2 26+/-2 34+/-10 34+/-3 30+/-2 39+/-3 37+/-3 *38+/-3 33+/-3 35+/-6 15+/-2 18+/-1 17+/-2 18+/-2 16+/-2 19+/-2 17+/-3 18+/-2 30+/-3 14+/-2 21+/-2 40+/-3 29+/-3 25+/-18 DECEMBER 30+/-2 26+/-2 29+/-2 28+/-2 28+/-2 28+/-3 28+/-2 26+/-2 19+/-2 22+/-2 13+/-2 23+/-2 31+/-3 22+/-11 25+/-2 20+/-2 26+/-2 24+/-2 23+/-2 24+/-2 24+/-4 16+/-2 16+/-2 15+/-2 14+/-2 18+/-2 33+/-3 19+/-13 AVERAGE 23+/-12 21+/-15 24+/-11 23+/-12 24+/-13 22+/-13 GRAND AVERAGE 23+/-13

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

• • Results by Controls for Environmental Pollution, Inc.

(1) Unscheduled power interruption br building maintenance dept. (Results not included in any averages).

(2) Reduced sampling period due to a r sampler malfunction. (Results not included in any averages) *

(3) Air samrler location was vandalized. No sample was collected.

(4) Quick d sconnect coupler failed causing APT/AIO holder to* separate from conduit shortly after installation. No sample was collected for this week.

TABLE C-3 1991 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* AND GAMMA EMITTERS**

IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 :!: 2 sigma

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

STATION ID SAMPLING PERIOD Sr-89 Sr-90 Be-7 K-40 SA-APT-5S1 12-31-90 to 04-01-91 <0.3 <0.2 66:!:6 <10 SA-APT-5D1 (1) 12-31-90 to 04-01-91 <2.0 <2.0 104:!:17 1320:!:28 SA-APT-16E1 12-31-90 to 04-01-91 <0.3 <0.2 59:!:5 <11 SA-APT-1F1 12-31-90 to 04-01-91 <0.4 <0.2 65:!:5 <16 SA-APT-2F2 12-31-90 to 04-01-91 <0.3 <0.2 66:!:5 <5.1 SA-APT-3H3 (C) 12-31-90 to 04-01-91 <0.3 <0.2 56:!:5 <12 SA-APT-5S1 04-01-91 to 07-01-91 68+/-6 15+/-5 SA-APT-5D1 (1) 04-01-91 to 07-01-91 114+/-22 <51 SA-APT-16E1 04-01-91 to 07-01-91 66+/-4 <3.9 SA-APT-1F1 04-01-91 to 07-01-91 77+/-7 <15 SA-APT-2F2 04-01-91 to 07-01-91 73:!:6 <11 SA-APT-3H3 (C) 04-01-91 to 07-01-91 70:!:6 <10 SA-APT-5S1 07-01-91 to 09-30-91 63:!:6 <5.3 SA-APT-5D1 (1) 07-01-91 to 09-30-91 58:!:7 273:!:16 SA-APT-16E1 07-01-91 to 09-30-91 64:!:6 <5.4 SA-APT-1F1 07-01-91 to 09-30-91 60+/-6 <6.2 SA-APT-2F2 07-01-91 to 09-30-91 63+/-5 <5.1 SA-APT-3H3 CC) 07-01-91 to 09-30-91 50+/-5 <4.8 SA-APT-5S1 09-30-91 to 12-30-91 43+/-4 <5 .0 SA-APT-5D1 (1) 09-30-91 to 12-30-91 43:!:13 <28 SA-APT-16E1 09-30-91 to 12-30-91 41:!:4 <4.7 SA-APT-1F1 09-30-91 to 12-30-91 42:!:4 <4.8 SA-APT-2F2 09-30-91 to 12-30-91 43+/-5 <5.2 SA-APT-3H3 (C) 09-30-91 to 12-30-91 39+/-4 <4.7 AVERAGE 62+/-36

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

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

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

CC) Control Station (1) Results by Controls for Environmental Pollution, Inc.

90

TABLE C-4 1991 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR.

Results in Units of 10-3 pCi/m3

• • <-------------------------------------- STATION ID MONTH SA-AI0-5Sl *sA-AI0-501 SA-AI0-16El SA-AIO-'lFl SA-AI0-2F2 SA-AI0-3H3 (Control)

JANUARY <7.6 <13 <5.1 <11

<10 <5.5 <3.0

<13 <11 <8.3 <6.2 <42 ( 1)

<8.9 <13 <8.0 <7.4 <11

<6.3 <7.1

<400(2) <5.1 <14 <6.8 <5.6

<6.9 <13 <9.1 <11 <12 <10 FEBRUARY <7.7 <13 <7.7 <16

<5.1 <6.4 <7.1

<13 <8.8 <7.8 <5.5 <7.8

<11 <13 <4.8 <12 <11

<9.2 <6.9 l.O <13 <16 <5.8 <6.8 <4.0 I-'

MARCH <7.1 <13 <8.7 <5.4 <5.0 <9.7

<9.8 <13 <4.3 <6.7 <12

<7.9 <13 <4.6

<7.4 <8.7 <7.8 <4.2

<12 <13 <5.6 <3.0 <14 <4.0 APRIL <6.8 <13 <5.8 <17 <6.2 <4.0

<5.8 <13 <10 <8.5 <7.0

<6.0 <8.6

<13 <4.9 <80(2) <6.4 <10

<13 <13 <15 <5.0 <5.6 <7.7 MAY <5.0 <13 <7.9 <6.3 <13 <3.4

<5.8 <13 <11 <9.9 ( 3)

<8.8 <5.0

<13 <9.3 <5.8 <8.0 <5.7

<6.8 <13 <4.6 <7.9 <10 <4.7 JUNE <7.9 <13 <5.1 <11 <16 <8.7

<12 <13 <10 <11 <10

<8.1 <6.7

<13 <14 <5.8 <4.7 <6.9

<9.2 <13 <9.5 <5.7 <13

<6.8 <8.0

<13 <5.6 <6.5 <9.0 <9.3

TABLE C-4 (Cont'd) 1991 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3

<-------------------------------------- STATION ID MONTH SA-AI0-5Sl SA-AI0-501 SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-383 (Control)

JULY <11 <13 <15 <4.6 <14 <1.1

<4.7 <13 <11 <6.4 <4.8 <9.0

<8.1 <13 <8.0 <7.5 <7.4 <8.2

<7.7 <13, <13 <9.4 <8.5 <5.3 AUGUST <7.4 <13 <13 <7.3 <8.9 <4.7

<6.1 <13 <5.2 <12 <7.0 <7.9

<6.4 <13 <5.6 <10 <S.l <8.6

<12 <13 <12 <7.9 <9.0 <12

\0 N SEPTEMBER <6.3 <13 <11 <6.4 <4.0 <7.8

<6.2 <13 <6.6 <7.2 <7.4 <8.2

<12 <13 <5.5 <9.6 <11 <3.4

<3.8 <13 <2.8 <6.0 <6.4 <7.5

<7.6 <13 <4.7 <8.4 <9.9 <4.6 OCTOBER <10 <13 <6.9 <6.6 <9.0 <7.1

<12 <13 <6.2 <8.7 <7.0 <5.0

<5.3 <13 <4.4 <10 <7.6 <3.1

<10 <13 <6.1 <4.2 <8.9 <3.1 NOVEMBER <9.0 <13 <3.4 <4.7 <4.7 (4)

<5.4 <13 <3.0 <2.2 <6.6 <2.7

<5.2 <13 <6.4 <4.4 <4.3 <3.5

<6.6 <20 <5.2 <3.6 <5.3 <5.1

<6.3 <13 <6.2 <8.6 <5.4 <4.3 DECEMBER <5.4 <13 <3.6 <5.2 <18 <3.8

<6.1 <13 <13 <8.9 <5.2 <5.0

<5.8 <13 <7.2 <5.6 <6.1 <4.1

<7.8 <13 <5.1 <11 <5.0 <4.8

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

• • Sampling dates can be found in Table c-s.

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

nadequate sample size due to unscheduled power in rruption.

igh LLD due to reduced sampling period due to a pler malfunction.

o sample collected at this location. Sampler w dalized.

Quick disconnect coupler failed. APT/AIO holder rated from sampler conduit. No sample collected

• TABLE C-5 1991 SAMPLING DATES FOR AIR SAMPLES MONTH <------------------------------------

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

JANUARY 12-31-90 12-31-90 12-31-90 12-31-90 to 12-31-90 12-31-90 to to to to to 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 01-07-91 to 01-07-91 to to to to to (1) 01-14-91 01-14-91 01-14-91 01-14-91 01-14-91 01-08-91 01-14-91 01-14-91 01-14-91 01-14-91 01-14-91 to 01-14-91 to to to to to 01-21-91 01-21-91 01-21-91 01-21-91 . 01-21-91 01-21-91 01-21-91 01-21-91 01-21-91 01-21-91 01-21-91 to 01-21-91 to (2) to to to to

\0 01-28-91 01-21-91 01-29-91 01-28-91 01-28-91 w 01-28-91 01-28-91 01-28-91 01-29-91 01-28-91 01-28-91 to 01-28-91 to to to to to 02-04-91 02-04-91 02-04-91 02-04-91 02-04-91 02-04-91 FEBRUARY 02-04-91 02-04-91 02-04-91 02-04-91 02-04-91 02-04-91 to to to to to 02-11-91 to 02-11-91 02-11-91 02-11-91 02-11-91 02-11-91 02-11-91 02-11-91 02-11-91 02-11-91 02-11-91 to 02-11-91 to to to to to 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 02-19-91 to 02-19-91 to to to to to 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 02-25-91 to 02-25-91 to to to to to 03-04-91 03-04-91 03-04-91 03-04-91 03-04-91 03-04-91 MARCH 03-04-91 03-04-91 03-04-91 03-04-91 03-04-91 to 03-04-91 to to to to to 03..;11-91 03-11-91 03-11-91 03-11-91 03-11-91 03-11-91 03-11-91 03-11-91 03-11-91 03-11-91 03-11-91 to 03-11-91 to to to to to 03-18-91 03-18-91 03-18-91 03-18-91 03-18-91 03-18-91

/

TABLE C-5 (Cont'd) 1991 SAMPLING DATES FOR AIR SAMPLES MONTH 581 5Dl 16El STATION CODE lFl 2F2 3H3 (Control)

MARCH 03-18-91 03-18-91 03-18-91 03-18-91 03-18-91 03-18-91 to ( 2) to to to to to 03-19-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 03-25-91 to to to to to to 04-01-91 04-01-91 04-01-91 04-01-91 04-01-91 04-01-91 APRIL 04-01-91 04-01-91 04-01-91 04-01-91 04-01-91 04-01-91 to to to to (2) to to 04-08-91 04-08-91 04-08-91 04-04-91 04-08-91 04-08-91 04-08-91 04-08-91 04-08-91 04-08-91 04-08-91 04-08-91 to to to to to to

\0 04-15-91 04-15-91 04-15-91 04-15-91 04-15-91 04-15-91

+:'-

04-15-91 04-15-91 04-15-91 04-15-91 04-15-91 04-15-91 to to to to (2) to to 04-22-91 04-22-91 04-22-91 04-16-91 04-22-91 04-22-91 04-22-91 04-22-91 04-22-91 04-22-91 04-22-91 04-22-91 to to to to to to 04-29-91 04-29-91 04-29-91 04-29-91 04-29-91 04-29-91 MAY 04-29-91 04-29-91 04-29-91 04-29-91 04-29-91 04-29-91 to to to to to to 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 05-06-91 to to to to to (4) to 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 05-13-91 to to to to to to 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91 05-20-91

.to to to to to to 05-28-91 05-28-91 05-28-91 05-28-91 05-28-91 05-28-91 JUNE 05-28-91 05-28-91 05-28-91 05-28-91 05-28-91 05-28-91 to to to to to to 06-03-91 06-03-91 06 06-03-91 06-03-91 06-03-91

TABLE C-5 (Cont'd) 1991 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 5Dl 16El STATION CODE

!Fl 2F2 3H3 (Control) 08-20-91 08-20-91 08-20-91 08-20-91 08-20-91 08-20-91 to to to to to to 08-26-91 08-26-91 08-27-91 08-26-91 08-26-91 08-26-91 SEPTEMBER 08-26-91 08-26-91 08-27-91 08-26-91 08-26-91 08-26-91 to to to to to to 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 09-03-91 to to to to to to 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 09-09-91 to to to to to to

\0 09-16-91 09-16-91 09-16-91 09-16-91 09-16-91 09-16-91

°' 09-16-91 to 09-16-91 09-16-91 to 09-16-91 to 09-16-91 to 09-16-91 to to 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 09-23-91 to to to to to to 09-30-91 09-30-91 09-30-91 09-30-91 09-30-91 09-30-91 OCTOBER 09-30-91 09-30-91 09-30-91 09-30-91 09-30-91 09-30-91 to to to to to to 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 10-07-91 to to to to to to 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 10-15-91 to to to to to to 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 10-21-91 to to to to to to 10..:20-91 10-28-91 10-28-91 10-28-91 10-28-91 10-28-91 NOVEMBER 10-28-91 10-28-91 10-28-91 10-28-91 10-28-91 10-28-91 to to to to to t.o ( 5) 11-04-91 11-04-91 11-04-91 11-04-91 11-04-91 10-28-91

TABLE C-5 (Cont'd) 1991 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 501 16El STATION CODE lFl 2F2 3H3 (Control)

JUNE 06-03-91 06-03-91 06-03-91 06-03-91 06-03-91 06-03-91 to to to to to to 06-10-91 06-10-91 06-11-91 06-10-91 06-10-91 06-10-91 06-10-91 06-10-91 06-11-91 06-10-91 06-10-91 06-10-91 to. to to to to to 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 06-17-91 to to to to to to 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 06-24-91 to to to to to to

\() 07-01-91 07-01-91 07-01-91 07-01-91 07-01-91 07-01-91 lJ1 JULY 07-01-91 07-01-91 07-01-91 07-01-91 07-01-91 07-01-91 to to to to to to 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 07-08-91 to to to to to to 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 07-15-91 to to to to to to 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 07-22-91 to to to to to to 07-29-91 07-29-91 07-29-91 07-29-91 07-29-91 07-29-91 AUGUST 07-29-91 07-29-91 07-29-91 07-29-91 07-29-91 07-29-91 to to to to to to 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 08-05-91 to to to to to to 00..:.12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 08-12-91 to to to to to to 08-20-91 08-20-91 08-20-9 08-20-91 08-20-91 08-20-91

TABLE C-5 (Cont'd) 1991 SAMPLING DATES FOR AIR SAMPLES MONTH 5Sl 5Dl 16El STATION CODE lFl 2F2 3H3 (Control)

NOVEMBER 11-04-91 11-'04-91 11-04-91 11-04-91 11-04-91 11-04-91 to to to to to to 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 11-12-91 to to to to to to 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 11-18-91 to to to to to to 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 11-25-91 to to to to to to 12-02-91 12-02-91 12-02-91 12-02-91 12-02-91 12-02-91 DECEMBER 12-02-91 12-02-91 12-02-91 12-02-91 12-02-91 12-02-91 to to to to to to 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 12-09-91 to to to to to to 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 12-16-91 to to to to to to 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 12-23-91 to to to to to to 12-30-91 12-30-91 12-30-91 12-30-91 12-30-91 12-30-91 (1) Unscheduled power interruption by R&T Lab Building Maintenance.

(2) Reduced sampling period due to an air sampler malfunction.

(3) Filter assembly broke off from the AIO column, causing a reduced sampling period for the APT analysis.

(4) Air sampler location 2F2 was vandalized.

( 5) Quick disconnect coupler failed causing APT/AIO holder to seperate from conduit shortly after installation. No sample was collected for this week.

TABLE C-6 1991 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, TRITIUM AND GAMMA EMITTERS* IN PRECIPITATION Results in Units of pCi/L +/- 2 sigma STATION ID: SA-RWA-2F2 GROSS GROSS <--GAMMA EMITTERS-->

SAMPLING PERIOD ALPHA BETA TRITIUM Be-7 K-40 12-31-90 to 01-28-91 0.9+/-0.8 2.4+/-0.7 <160 <11 <20 01-28-91 to 02-25-91 <1.0 14+/-2 160+/-100 (1) (1) 02-25-91 to 04-01-91 <0.8 1.5+/-0.8 <130 43+/-16 <26 04-01-91 to 04-29-91 1.3+/-0.8 6.8+/-1.0 <130 74+/-15 <18 04-29-91 to 05-29-91 <1.4 2.2+/-0.8 <130 74+/-33 <59 05-29-91 to 07-01-91 <1.4 0.9+/-0.6 140+/-80 32+/-14 <20 07-01-91 to 07-29-91 <1.6 5.9+/-1.0 <160 46+/-16 43+/-22 07-30-91 to 08-26-91 <1.1 2.9+/-0.8 <160 43+/-17 <32 08-26-91 to 09-30-91 <1.0 2.2+/-0.8 <170 32+/-10 <18 09-30-91 to 10-28-91 <1.3 5.4+/-1.0 <170 <59 <160 10-28-91 to 12-02-91 <l. 7 2.3+/-0.7 <140 <47 <54 12-02-91 to 12-30-91 <1.6 2.5+/-0.8 <160 52+/-15 <36 AVERAGE - 4.1+/-7.3 - 47+/-37

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

(1) Insufficient sample available to adequately meet sensitivity requirements for gamma analysis.

98

• TABLE C-7 1991 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)

JANUARY APRIL JULY OCTOBER STATION ID to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 5.4+/-0.2 3.6+/-0.4 5.0+/-0.3 5.0+/-0.5 4. 8+/-1. 6 SA-IDM-5Sl 5.0+/-0.2 3.8+/-0.2 4.6+/-0.3 4.7+/-0.4 4.5+/-1.0 SA-IDM-6S2 5.8+/-0.3 4.0+/-0.7 5.1+/-1.1 5.0+/-0.3 5.0+/-1.5 SA-IDM-7Sl 7.2+/-0.7 5.4+/-0.9 6.5+/-0.3 6.5+/-0.4 6.4+/-1.5 SA-IDM-lOSl 7.2+/-0.8 5.5+/-0.7 6.4+/-0.6 5.2+/-0.8 6.1+/-1.8 SA-IDM-llSl 10+/-3 7.3+/-2.0 6. 5+/-1. 0 4.6+/-0.2 7.1+/-4.5 SA-IDM-402 ( 1) 4.6+/-0.5 5.7+/-0.3 4. 7+/-1. 0 5.0+/-1.2 SA-IDM-5Dl .5.6+/-0.4 4.3+/-0.4 5.5+/-0.2 4.9+/-0.3 5.1+/-1.2 SA-IDM-lODl 6 .1+/-0. 5 4.6+/-0.5 5.4+/-0.4 5.6+/-0.3 5.4+/-1.2 SA-IDM-14Dl 5.7+/-0.2 4.1+/-0.3 4.7+/-0.3 4.9+/-0.2 4.9+/-1.3 SA-IDM-2El 5.7+/-0.3 4.1+/-0.5 4.3+/-0.6 4.9+/-0.3 4.8+/-1.4 SA-IDM-3El 5.4+/-0.2 4.0+/-0.5 4.5+/-0.2 4.8+/-0.3 4.7+/-1.2 SA-IDM-9El 6.5+/-0.4 4.6+/-0.2 5.8+/-0.4 5.9+/-0.6 5.7+/-1.6 SA-IDM-11E2 6.3+/-0.4 4.9+/-0.5 5.5+/-0.5 5.9+/-0.4 5. 7+/-1.2 SA-IDM-12El 6.2+/-0.4 5.0+/-1.1 5.3+/-0.3 5.3+/-0.3 5.5+/-1.0 SA-IDM-13El 5.6+/-0.3 3.8+/-0.3 4.2+/-0.5 4.6+/-0.3 4. 6+/-1. 5 SA-IDM-16El 5.7+/-0.4 4.4+/-0.4 5.0+/-0.3 5.2+/-0.3 5.1+/-1.1 SA-IDM-lFl 5.7+/-0.3 4.4+/-0.3 5.0+/-0.4 5.2+/-0.2 5 .1+/-1.1 SA-IDM-2F2 4.9+/-0.4 3.2+/-0.2 3.9+/-0.2 4.0+/-0.4 4.0+/-1.4 SA-IDM-2F5 5.6+/-0.3 4.6+/-0.3 4.9+/-0.2 5.1+/-0.3 5.1+/-0.8 SA-IDM-2F6 5.5+/-0.3 4.2+/-0.4 4.8+/-0.3 5.2+/-0.7 4. 9+/-1.1 0A-IDM-3F2 5.3+/-0.2 3.8+/-0.4 4.4+/-0.3 4.6+/-0.4 4.5+/-1.2 SA-IDM-3F3 5.2+/-0.4 3.9+/-0.2 4.4+/-0.2 4.8+/-0.4 4. 6+/-1.1 SA-IDM-5Fl 5.4+/-0.1 4.0+/-0.3 4.6+/-0.4 5.0+/-0.3 4.8+/-1.2 SA-IDM-6Fl 5.4+/-0.2 3.4+/-0.2 4.2+/-0.3 '4.1+/-0.3 4. 3+/-1. 7 SA-IDM-7F2 4.5+/-0.2 3.2+/-0.1 3.6+/-0.1 4.0+/-0.2 3.8+/-1.1 SA-IDM-10F2 5.9+/-0.3 4.8+/-0.4 5.3+/-0.4 5.5+/-0.6 5.4+/-0.9 SA-IDM-llFl 6.1+/-0.5 4.7+/-0.4 5.2+/-0.7 5.8+/-0.3 5.5+/-1.2 SA-IDM-12Fl 5.6+/-0.3 4.4+/-0.4 5.0+/-0.2 5.3+/-0.4 5.1+/-1.0 SA-IDM-13F2 5.1+/-0.4 4.3+/-0.5 4.4+/-0.3 5.1+/-0.3 4.7+/-0.9 SA-IDM-13F3 5.9+/-0.4 4.6+/-0.5 5.0+/-0.4 5.4+/-0.4 5.2+/-1.1 SA-IDM-13F4 5.6+/-0.4 4.4+/-0.4 4.9+/-0.2 5.1+/-0.3 5.0+/-1.0 SA-IDM-14F2 6.7+/-0.6 5.1+/-0.4 6.0+/-0.2 6.3+/-0.5 6.0+/-1.4 SA-IDM-15F3 6.3+/-0.5 4.7+/-0.3 5.7+/-0.5 5.9+/-0.5 5.7+/-1.4 SA-IDM-16F2 5.3+/-0.3 3.9+/-0.2 4.8+/-0.3 5.1+/-0.3 4.8+/-1.2 SA-IDM-1G3 (C) 6.3+/-0.2 5.0+/-0.3 5.9+/-0.3 5.9+/-0.5 5. 8+/-1.1 SA-IDM-3Gl (C) 6.0+/-0.4 4.6+/-0.3 5.3+/-0.4 5.1+/-0.4 5. 3+/-1. 2 SA-IDM-lOGl (C) 6.0+/-0.3 4.6+/-0.3 5.4+/-0.3 5.4+/-0.3 5. 4+/-1.1 SA-IDM-16Gl (C) 6.2+/-0.5 4.7+/-0.5 5.6+/-0.3 5.8+/-0.5 5.6+/-1.3 SA-IDM-3Hl (C) 5.5+/-0.2 4.0+/-0.6 4.8+/-0.1 4.9+/-0.5 4.8+/-1.2 SA-IDM-3H3 (C) 5.9+/-0.4 4.6+/-0.3 5.3+/-0.4 5.4+/-0.4 5. 3+/-1.1 AVERAGE 5.9+/-1.7 4. 4+/-1. 4 5.1+/-1. 3 5.2+/-1.1 GRAND AVERAGE 5.1+/-1. 7

• The standard month = 30.4 days.

(C) Control Station (1) TLD was missing from the field location *

• 99

TABLE C-8 1991 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)

STATION ID JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 5.0+/-0.3 6.2+/-0.4 5.6+/-0.5 7.7+/-0.5 4.8+/-0.6 6.5+/-0.5 SA-IDM-5Sl 5.1+/-0.8 6.2+/-0.2 5.5+/-0.4 7.4+/-0.3 4.6+/-0.8 5.9+/-0.1 SA-IDM-6S2 5.5+/-0.9 6.8+/-0.3 5.8+/-0.5 7.6+/-0.5 5.2+/-0.5 6.5+/-0.3 SA-IDM-7Sl 6.5+/-0.7 7.9+/-0.7 8. 9+/-1. 3 9.3+/-0.7 6.0+/-0.3 8.1+/-0.9 SA-IDM-10Sl 7.5+/-1.4 8.0+/-0.8 7.6+/-0.8 9.6+/-0.9 6.1+/-0.8 7.8+/-0.9 SA-IDM-llSl 8.7+/-1.9 9. 8+/-1. 7 12+/-2 12+/-2 7.6+/-2.1 9.0+/-2.1 SA-IDM-5Dl 5. 7+/-1.1 6.4+/-0.5 4.9+/-0.6 7.7+/-0.3 4.9+/-0.6 6.6+/-0.5 SA-IDM-lODl 5.8+/-1.1 7.1+/-0.6 6.2+/-0.4 8.5+/-0.4 5.3+/-0.6 7.2+/-1.0 SA-IDM-14Dl 5.6+/-1.2 6.7+/-0.6 6.1+/-0. 3 7.7+/-0.4 5.1+/-0.4 6.4+/-0.4 SA-IDM-2El 5.4+/-1.1 6.6+/-0.4 5.7+/-0.4 8.0+/-0.8 4.6+/-0.6 6.7+/-0.4 t-'

0 SA-IDM-3El 5.1+/-0. 7 6.3+/-0.3 5.6+/-0.4 7.4+/-0.4 4.4+/-0.2 6.2+/-0.6 0

SA-IDM-13El 5.3+/-0.3 6.6+/-0.5 5.8+/-0.4 7.5+/-0.5 4.7+/-0.3 6.3+/-0.4 SA-IDM-16El 5. 4+/-1. 3 6.9+/-0.5 6.1+/-0.3 8.1+/-0.5 5.0+/-0.4 7.0+/-0.5 SA-IDM-lFl 5. 7+/-1. 0 6.9+/-0.4 5.8+/-0.5 8.0+/-0.6 5.0+/-0.6 6.8+/-0.6 SA-IDM-2F2 5.1+/-0.1 6.2+/-0.2 5.1+/-0. 3 6.8+/-0.3 4.2+/-0.3 5.8+/-0.4 SA-IDM-2F6 5. 3+/-1. 2 6.5+/-0.4 5.7+/-0.3 7. 7+/-0. 5 4.8+/-0.9 6.5+/-0.4 SA-IDM-5Fl 5.7+/-0.5 6.1+/-2.0 5.7+/-0.1 7.6+/-0.3 4.7+/-0.3 6.3+/-0.6 SA-IDM-6Fl 5 .1+/-0.1 6.1+/-0.6 5.1+/-0.6 7 .1+/-0. 2 4.2+/-0.3 5.7+/-0.4 SA-IDM-7F2 4.9+/-0.5 5.6+/-0.4 4.9+/-0.4 6.6+/-0.2 3.9+/-0.3 5.4+/-0.3 SA-IDM-llFl 5.8+/-0.9 7.3+/-0.5 6.4+/-0.7 8.4+/-0.6 5.4+/-0.4 6.9+/-0.4 SA-IDM-13F4 5.8+/-0.3 7.1+/-0.4 6.3+/-0.3 8.2+/-1.2 5.2+/-0.5 6. 7+/-0'.4 SA-IDM-3Gl (C) 6.4+/-0.6 6.9+/-0.5 6.1+/-0.3 8.1+/-0.6 5.2+/-0.4 7.0+/-0.5 SA-IDM-3Hl (C) 5.4+/-0.4 6.7+/-0.2 5.8+/-0.2 7.8+/-0.4 5.0+/-0.4 6.3+/-0.3 SA-IDM-3H3 (C) 6.1+/-0.5 7.4+/-0.3 6.6+/-0.4 8.7+/-0.3 5.6+/-0.4 6.6+/-0.5 AVERAGE 5. 7+/-1. 7 6.8+/-1.7 6.2+/-3.0 8.1+/-2.2 5.1+/-1.5 6.7+/-1.6

TABLE C-8 (Cont'd) 1991 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)

STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 7.6+/-1.5 7.8+/-0.3 6.8+/-0.5 7. 7+/-0. 5 8.5+/-0.6 7.7+/-0.6 6.8+/-2.4 SA-IDM-5Sl 6.7+/-0.3 7.3+/-0.4 6.5+/-0.3 7.2+/-0.4 7.7+/-0.3 7.5+/-0.3 6.5+/-2.0 SA-IDM-6S2 7.3+/-0.5 8.1+/-0. 5 6.6+/-0.8 7.6+/-0.5 8.3+/-0.2 7.7+/-0.4 6.9+/-2.0 SA-IDM-7Sl 8.2+/-0.8 9.,U0.6 8.3+/-0.6 8.9+/-0.7 9.8+/-0.8 9.3+/-0.6 8.4+/-2.3 SA-IDM-lOSl 8.4+/-1.0 9.4+/-0.9 7.9+/-0.7 8.9+/-0.9 9.0+/-0.6 8.9+/-0.6 8.3+/-2.0 SA-IDM-llSl 9.1+/-1.7 10+/-2 6.7+/-0.3 7.2+/-0.2 7.8+/-0.2 7.7+/-0.5 9.0+/-3.5 SA-IDM-5Dl 7.0+/-0.6 7.6+/-0.5 6.8+/-0.5 7.5+/-0.5 8.3+/-0.4 8.2+/-0.6 6.8+/-2.3 SA-IDM-lODl 7.5+/-0.5 8.5+/-0.5 7.8+/-0.5 8.3+/-0.5 8.7+/-0.7 8.9+/-0.7 7.5+/-2.4 SA-IDM-14Dl 6.8+/-0.5 7.9+/-0.5 7.0+/-0.2 7.4+/-0.4 8.0+/-1.2 8 .1+/-0. 2 6.9+/-1.9 I-' SA-IDM-2El 6.4+/-0.2 7.7+/-0.7 7.2+/-0.7 7.7+/-0.4 7.7+/-0.9 8.2+/-0. 7. 6.8+/-2.3 0 SA-IDM-3El 7.2+/-0.9 7~8+/-0.9 6.8+/-0.5 7.5+/-0.4 7.7+/-0.3 7.5+/-0.5 6.6+/-2.2 I-'

SA-IDM-13El 6.8+/-0.6 7.8+/-0.3 7 .1+/-0. 4 7.4+/-0.6 7.9+/-0.4 7.6+/-0.4 6.7+/-2.1 SA-IDM-16El 7.3+/-0.6 7.9+/-0.5 7.6+/-0.2 8.1+/-0.5 8.7+/-0.2 8.0+/-0.4 7.2+/-2.3 SA-IDM-lFl 7.4+/-0.4 8.3+/-0.3 7.4+/-0.4 8.0+/-0.4 8.2+/-0.5 8.1+/-0.3 7 .1+/-2. 2 SA-IDM-2F2 6.4+/-0.3 7.2+/-0.4 6.9+/-0.9 7.0+/-0.3 7.3+/-0.5 7 .1+/-0. 8 6.3+/-2.0 SA-IDM-2F6 7.0+/-0.5 7.8+/-0.4 7.4+/-0.3 7.7+/-0.4 8.1+/-0.2 7.7+/-0.3 6.9+/-2.2 SA-IDM-5Fl 6.7+/-0.4 7.9+/-0.4 7.0+/-0.3 7.5+/-0.4 7.8+/-0.4 7.8+/-0.2 6.7+/-2.1 SA-IDM-6Fl 6.4+/-0.4 7.4+/-0.7 6.1+/-0.5 7.2+/-0.2 7.4+/-0.2 6.9+/-0.3 6.2+/-2.1 SA-IDM-7F2 5.8+/-0.3 6.8+/-0.2 6.0+/-0.1 6.8+/-0.5 7.0+/-0.3 6.9+/-0.6 5.9+/-2.0 SA-IDM-llFl 7.8+/-0.4 8.4+/-0.3 7.6+/-0.4 8.4+/-0.6 8.8+/-0.6 8.9+/-0.3 7.5+/-2.3 SA-IDM-13F4 7.3+/-0.6 7.9+/-1.0 7.4+/-0.6 8.2+/-0.4 8.5+/-0.4 8.3+/-0.4 7. 2'+/-2 .1 SA-IDM-3Gl (C) 7.5+/-0.7 8.4+/-0.6 7.7+/-0.3 8.3+/-0.6 8.9+/-0.4 8.5+/-0.4 7.4+/-2.2 SA-IDM-3Hl (C) 7. 6+/-1.1 7.5+/-0.3 7.0+/-0.3 7.8+/-0.3 8.1+/-0.3 8.1+/-0.5 6.9+/-2.2 SA-IDM-3H3 (C) 7.8+/-0.7 8.4+/-0.4 7.9+/-0.8 0. 2+/-0. 5 8.9+/-0.3 8.9+/-0.4 7.6+/-2.3 AVERAGE 7. 3+/-1. 4 8.1+/-1.5 7.1+/-1.2 7.8+/-1.1 8.2+/-1.3 8.0+/-1.3 GRAND AVERAGE 7.1+/-2.6

• The standard month = 30.4 days (C) Control Station

TABLE C-9 1991 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING PERIOD I-131

<----- GAMMA EMITTERS K-40 Ra-226 SA-MLK-2F7 01/07-08/91 <0.2 1400+/-100 <4.4 SA-MLK-11F3 01/07-08/91 <0.2 1200+/-78 <4.8 SA-MLK-14Fl 01/07-08/91 <0.3 1300+/-88 <7.9 SA-MLK-3Gl ( c) 01/06-07/91 <0.3 1300+/-67 <2.7 SA-MLK-2F7 02/04-05/91 <0.4 1200+/-66 <3.5 SA-MLK-11F3 02/04-05/91 <0.2 1100+/-100 <3.4 SA-MLK-14Fl 02/04-05/91 <0.4 1300+/-100 <5.0 SA-MLK-3Gl (C) 02/03-04/91 <0.2 1300+/-85 <2.9 SA-MLK-2F7 03/04-05/91 <0.2 1300+/-100 <3.2 SA-MLK-11F3 03/04-05/91 <0.3 1300+/-100 <4.8 SA-MLK-14Fl 03/04-05/91 <0.3 1300+/-85 <9.8 SA-MLK-3Gl ( C) 03/03-04/91 <0.3 1400+/-85 <4.1 SA-MLK-2F7 04/07-08/91 <0.3 1300+/-66 <3.0 SA-MLK-11F3 04/07-08/91 <0.3 1300+/-92 <4.4 SA-MLK-14Fl 04/07-08/91 <0.2 1400+/-100 <4.7 SA-MLK-3Gl (C) 04/07-08/91 <0.3 1400+/-66 <2.3 SA-MLK-2F7 04/21-22/91 <0.2 1300+/-67 <3.5 SA-MLK-11F3 04/21-22/91 <0.3 1300+/-76 <4.4 SA-MLK-14Fl 04/21-22/91 <0.3 1300+/-100 <5.0 SA-MLK-3Gl (C) 04/21-22/91 <0.3 1300+/-83 <3.4 SA-MLK-2F7 05/05-06/91 <0.2 1400+/-87 <3.8 SA-MLK-11F3 05/05-06/91 <0.2 1300+/-94 <7.5 SA-MLK-14Fl 05/05-06/91 <0.2 1400+/-80 <3.2 SA-MLK-3Gl (C) 05/05-06/91 <0.4 1400+/-87 <3.3 SA-MLK-2F7 05/19-20/91 <0.3 1400+/-70 <3.2 SA-MLK-11F3 05/19-20/91 <0.6 1400+/-87 <2.6 SA-MLK-14Fl 05/19-20/91 <0.3 1300+/-85 <7.6 SA-MLK-3Gl (C) 05/19-20/91 <0.2 1300+/-95 <4.2 SA-MLK-2F7 06/02-03/91 <0.3 1400+/-97 <5.4 SA-MLK-11F3 06/02-03/91 <0.2 1300+/-86 <3.1 SA-MLK-14F4 (1) 06/03-04/91 <0.2 1300+/-86 <3.1 SA-MLK-3Gl (C) 06/02-03/91 <0.3 1400+/-69 <3.6 SA-MLK-2F7 06/16-17/91 <0.1 1400+/-66 <3.0 SA-MLK-11F3 06/16-17/91 <0.3 1700+/-110 <3.5 SA-MLK-14F4 06/16-17/91 <0.2 1400+/-84 <4.0 SA-MLK-3Gl (C) 06/16-17/91 <0.3 1300+/-73 <2.6 SA-MLK-2F7 07/08-09/91 <0.2 1400+/-90 <4.5 SA-MLK-11F3 07/08-09/91 <0.2 1400+/-91 <4.3 SA-MLK-14F4 07/08-09/91 <0.3 1400+/-100 <9.4 SA-MLK-3Gl (C) 07/07-08/91 <0.2 1300+/-66 <2.8 SA-MLK-2F7 07/22-23/91 <0.2 1400+/-99 <6.5 SA-MLK-11F3 07/22-23/91 <0.3 1300+/-83 <4.0 SA-MLK-14F4 07/22-23/91 <0.3 1400+/-86 <4.8 SA-MLK-3Gl (C) 07/21-22/91 <0.3 1400+/-67 <2.7 102

TABLE C-9 (Cont'd) 1991 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING PERIOD I-131

<----- GAMMA EMITTERS K-40 Ra-226 SA-MLK-2F7 08/05-06/91 <0.3 1400+/-97 <5.5 SA-MLK-11F3 08/05-06/91 <0.1 1400+/-79 <3.3 SA-MLK-14F4 08/05-06/91 <0.1 1400+/-88 <4.7 SA-MLK-3Gl (C) 08/04-05/91 <0.1 1400+/-81 <4.2 SA-MLK-2F7 08/19-20/91 <0.3 1400+/-98 <8.8 SA-MLK-11F3 08/19-20/91 <0.1 1400+/-94 <4.8 SA-MLK-14F4 08/19-20/91 <0.3 1400+/-84 <4.8 SA-MLK-3Gl (C) 08/19-20/91 <0.2 1400+/-95 <7.9 SA-MLK-2F7 09/02-03/91 <0.1 1400+/-67 <6.2 SA-MLK-11F3 09/02-03/91 <0.3 1400+/-88 <5.0 SA-MLK-14F4 09/02-03/91 <0.3 1400+/-76 <3.6 SA-MLK-3Gl (C) 09/02-03/91 <0.3 1500+/-100 <7.0 SA-MLK-2F7 09/16-17/91 <0.3 1500+/-100 <5.1 SA-MLK-11F3 09/15-16/91 <0.1 1500+/-80 <3.3 SA-MLK-l4F4 09/15-:16/91 <0.3 1400+/-68 <2.6 SA-MLK-3Gl (C) 09/16-17/91 <0.2 1400+/-86 <4.2 SA-MLK-2F7 *10/06-u7 /91 <0.2 .1400+/-98 <6.2 SA-MLK-11F3 10/07-08/91 <0.2 1300+/-66 <2.4 SA-MLK-14F4 10/06-07/91 <0.3 1400+/-88 <4.0 SA-MLK-3Gl (C) 10/06-07/91 <0.2 1300+/-87 <4.7 SA-MLK-2F7 10/20-21/91 <0.2 1400+/-86 <4.6 SA-MLK-11F3 10/20-21/91 <0.3 1300+/-70 <2.3 SA-MLK-14F4 10/20-21/91 <0.2 1500+/-81 <7.0 SA-MLK-3Gl (C) 10/21-22/91 <0.1 1300+/-91 <5.1 SA-MLK-2F7 11/03-04/91 <0.2 1500+/-98 <5.* 0 SA-MLK-11F3 11/03-04/91 <0.2 1400+/-100 <7.6 SA-MLK-14F4 11/03-04/91 <0.3 1400+/-84 <5.7 SA-MLK-3Gl (C) 11/03-04/91 <0.3 1300+/-82 <4.4 SA-MLK-2F7 11/17-18/91 <0.3 1400+/-86 <3.1 SA-MLK-11F3 11/17-18/91 <0.3 1400+/-98 <4.3 SA-MLK-14F4 11/17-18/91 <0.2 1300+/-67 <1.9 SA-MLK-3Gl (C) 11/17-18/91 <0.2 1400+/-80 <3.9 SA-MLK-2F7 12/09-10/91 <0.4 1300+/-67 <2.0 SA-MLK-11F3 12/08-09/91 <0.3 1300+/-100 <4.5 SA-MLK-14F4 12/09-10/91 <0.2 1400+/-86 <4.3 SA-MLK-3Gl (C) 12/09-10/91 <0.3 1300+/-83 <4.0 AVERAGE 1400+/-160

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

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

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

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

(C) Control Station (1) New Location 14F4 is a replacement for Loe 14Fl as of 6/1/91.

103

TABLE C-10 1991 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* IN MILK**

Results in Units of pCi/L +/- 2 sigma

<--- STRONTIUM --->

STATION ID SAMPLING PERIOD sr-89 sr-90 SA-MLK-2F7 07/08-09/91 <1.5 3.5+/-0.6 SA-MLK-11F3 07/08-09/91 <1.0 1.2+/-0.4 SA-MLK-14F4(1) 07/08-09/91 <1.3 3.0+/-0.5 SA-MLK-3G1 07/07-08/91 <1.3 3.0+/-0.5 (Control)

AVERAGE 2.7+/-2.0

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

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

(1) New milk farm, location 14F4, replacing previous 14F1 location as of 06/01/91.

104

TABLE C-11 1991 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma SAMPLING GROSS GROSS STATION ID DATE ALPHA BETA K-40 TRITIUM SA-WWA-2S3 01-28-91 <0.6 3.5+/-0.8 3.6+/-0.4 <160 SA-WWA-3El (C) 01-28-91 1. 2+/-1. 0 11+/-1 10+/-1 <150 SA-WWA-2S3 02-25-91 <0.9 3.6+/-0.8 2.6+/-0.3 <160 SA-WWA-3El ( C) 02-25-91 <1.0 9.9+/-1 8.6+/-0.9 <160 SA-WWA-2S3 03-25-91 <0.7 4.0+/-0.9 3.6+/-0.4 <130 SA-WWA-3El (C) 03-25-91 <0.8 10+/-1 9.5+/-1.0 <130 SA-WWA-2S3 04-29-91 <0.8 3.4+/-0.8 3.4+/-0.3 <130 SA-WWA-3El ( C) 04-29-91 1. 0+/-0. 8 10+/-1 9.0+/-0.9 <130 SA-WWA-2S3 05-28-91 <1.5 5. 6+/-1. 0 4.8+/-0.5 <130 SA-WWA-3El (C) 05-28-91 <1.5 11+/-1 9.2+/-0.9 <130 SA-WWA-2S3 06-24-91 <1.4 4.2+/-0.9 4.5+/-0.4 <120 SA-WWA-3El ( C) 06-24-91 <1.5 10+/-1 10+/-1 <130 SA-WWA-2S3 07-30-91 <1.5 4.2+/-0.9 4.1+/-0.4 <160 SA-WWA-3El (C) 07-29-91 <1. 7 9.9+/-1.2 9.4+/-0.9 <160 SA-WWA-2S3 08-26-91 <1.2 3.1+/-0.8 3.6+/-0.4 <170 280+/-100 SA-WWA-3El ( C) 08-26-91 <1.2 10+/-1 9.8+/-1.0 SA-WWA-2S3 09-23-91 <1.1 4.5+/-0.9 4.6+/-0.5 <160 SA-WWA-3El (C) 09-23-91 <1.2 11+/-1 9.3+/-0.9 190+/-100 SA-WWA-2S3 10-28-91 <1.3 6 .8+/-1.1 6.1+/-0.6 260+/-110 SA-WWA-3El (C) 10-28-91 <1.3 10+/-1 10+/-1 <160 SA-WWA-2S3 11-25-91 <2.1 3.5+/-0.8 3.6+/-0.4 <140 SA-WWA-3El (C) 11-25-91 <1.9 11+/-1 9.8+/-1.0 <140 SA-WWA-2S3 12-30-91 <1.9 8.2+/-1.2 7.6+/-0.8 <160 SA-WWA-3El (C) 12-30-91 <2.0 9.9+/-1.3 9.3+/-0.9 <160 AVERAGE SA-WWA-2S3 4.6+/-3.1 4.3+/-2.7 SA-WWA-3El (C) 10+/-1 9.5+/-0.9 GRAND AVERAGE 7.4+/-6.3 6.9+/-5.6

( c) Control Station

• 105

TABLE C-12 1991 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING DATE I-131

<---- GAMMA EMITTERS K-40 Ra-226 SA-WWA-2S3 01-28-91 <0.3 <18 <2.9 SA-WWA-3El (C) 01-28-91 <0.2 <22 120+/-8 SA-WWA-2S3 02-25-91 <0.3 <22 <5.5 SA-WWA-3El (C) 02-25-91 <0.1 <20 150+/-9 SA-WWA-2S3 03-25-91 <0.2 <20 33+/-5 SA-WWA-3El (C) 03-25-91 <0.2 <23 190+/-9 SA-WWA-2S3 04-29-91 <0.2 <20 <9.2 SA-WWA-3El (C) 04-29-91 <0.2 <21 190+/-7 SA-WWA-2S3 05-28-91 <0.2 <19 <3.0 SA-WWA-3El (C) 05-28-91 <0.1 <29 150+/-8 SA-WWA-2S3 06-24-91 <0.4 <19 10+/-4 SA-WWA-3El (C) 06-24-91 <0.2 <18 110+/-6 SA-WWA-2S3 07-29-91 <0.3 <17 <9.4

A-WWA-3El (C) 07-29-91 <0.3 <13 110+/-5 SA-WWA-2S3 08-26-91 <0.2 <19 18+/-4 SA-WWA-3El (C) 08-26-91 <0.1 <22 160+/-9 SA-WWA-2S3 09-23-91 <0.2 <23 22+/-6 SA-WWA-3El (C) 09-23-91 <0.2 <23 190+/-9 SA-WWA-2S3 10-28-91 <0.4 <19 44+/-4 SA-WWA-3El (C) 10-28-91 <0.1 <22 140+/-8 SA-WWA-2S3 11-25-91 <0.2 <19 50+/-6 SA-WWA-3El (C) 11-25-91 <0.2 <15 160+/-6 SA-WWA-2S3 12-30-91 <0.2 <21 110+/-6 SA-WWA-3El (C) 12-30-91 <0.3 <18 190+/-7 AVERAGE SA-WWA-2S3 26+/-61 SA-WWA-3El (C) 160+/-62 GRAND AVERAGE 90+/-140

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

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

(C) Control Station 106

TABLE C-13 1991 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90*

IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L

<-- STRONTIUM -->

STATION ID SAMPLING PERIOD Sr-89 Sr-90 SA-WWA-283 01-28-91 to 03-25-91 <0.6 <0.4 SA-WWA-3El (C) 01-28-91 to 03-25-91 <0.7 <0.5 SA-WWA-283 04-29-91 to 06-24-91 <1.0 <0.7 SA-WWA-3El (C) 04-29-91 to 06-24-91 <0.6 <0.5 SA-WWA-2S3 07-30-91 to 09-23-91 <0.7 <0.5 SA-WWA-3E1 (C) 07-29-91 to 09-23-91 <0.6 <0,.4 SA-WWA-2S3 10-28-91 to 12-30-91 <0.5 <0.4 SA-WWA-3El (C) 10-28-91 to 12-30-91 <0.5 <0.4

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

(C) Control Station

• 107

TABLE C-14 1991 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3 SAMPLING GROSS GROSS TYPE PERIOD ALPHA BETA K-40 TRITIUM Raw 01/01-31/91 0.9+/-0.7 3.8+/-0.8 2.3+/-0.2 <170 Treated 01/01-31/91 <0.6 2.4+/-0.7 2 .1+/-0.2 <170 Raw 02/01-28/91 <1.0 3.2+/-0.8 1. 4+/-0.1 <150 Treated 02/01-28/91 1.0+/-0.8 2.5+/-0.7 1.4+/-0.1 <150 Raw 03/01-31/91 0.8+/-0.7 3.4+/-0.9 1.9+/-0.2 <130 Treated 03/01-31/91 <0.7 2.3+/-0.8 1. 6+/-0.2 <130 Raw 04/01-30/91 2 .1+/-1.1 3.4+/-0.8 1.8+/-0.2 <130 Treated 04/01-30/91 0.8+/-0.7 2.5+/-0.7 1. 8+/-0.2 <130 Raw 05/01-31/91 <1.6 3.1+/-0.8 1.4+/-0.1 140+/-80 Trea-.;ed 05/01-31/91 <1.4 2.9+/-0.8 1.8+/-0 .2 <130 Raw 06/01-30/91 <1.5 3.5+/-0.8 1.4+/-0.1 <120 Treated 06/01-30/91 <1.2 2.1+/-0.7 1.6+/-0.2 <120 Raw 07/01-31/91 <1.5 3.0+/-0.8 1.8+/-0.2 290+/-110 Treated 07/01-31/91 <1.4 2.4+/-0.7 1.9+/-0.2 <170 Raw 08/01-31/91 <1.2 2.8+/-0.7 2.4+/-0.2 <140 Treated 08/01-31/91 <1.0 2.8+/-0.7 2.2+/-0.2 180+/-100 Raw 09/01-30/91 <1.0 2.9+/-0.8 1. 9+/-0. 2 230+/-100 Treated 09/01-30/91 <1.0 2.3+/-0.8 2.0+/-0.2 <160 Raw 10/01-31/91 <1.3 3.3+/-0.8 1.6+/-0.2 <160 Treated 10/01-31/91 <1.2 2.0+/-0.7 1. 7+/-0.2 <150 Raw 11/01-30/91 <1.9 3.2+/-0.7 2.7+/-0.3 <140 Treated 11/01-30/91 <1.8 2.6+/-0.7 1.9+/-0.2 <140 Raw 12/01-31/91 <2.0 3.6+/-0.9 2.4+/-0.2 <160 Treated 12/01-31/91 <2.3 3.0+/-0.8 2.3+/-0.2 <160 AVERAGE Raw - 3.3+/-0.6 1. 9+/-0. 9 Treated - 2.5+/-0.6 1. 9+/-0. 5 GRAND AVERAGE - 2.9+/-1.0 1. 9+/-0. 7 108

TABLE C-15 1991 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

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

<------ GAMMA EMITTERS K-40 Ra-226 Raw 01/01-31/91 <0.3 <19 <2.6 Treated 01/01-31/91 (1) <50 <3.4 Raw 02/01-28/91 <0.2 <19 <2.6 Treated 02/01-28/91 <0.2 <51 <2.8 Raw 03/01-31/91 <0.2 <14 <1.8 Treated 03/01-31/91 <0.1 <25 <13 Raw 04/01-30/91 <0.3 <18 <8.1 Treated 04/01-30/91 <0.3 <26 <3.3 Raw 05/01-31/91 <0.2 <20 <7.2 Treated 05/01-31/91 <0.3 <:d <5.3

• Raw Treated Raw Treated 06/01-30/91 06/01-30/91 07/01-31/91 07/01-31/91

<0.5

<0.2

<0.2

<0.2

<20

<16

<37 17+/-6

<3.2

<2.8

<5.4

<1.4 Raw 08/01-31/91 <0.5 <19 <6.9 Treated 08/01-31/91 <0.1 <29 <2.8 Raw 09/01-30/91 <0.1 <19 <5.4 Treated 09/01-30/91 <0.2 <19 <2.8 Raw 10/01-31/91 <0.1 <19 <2.5 Treated 10/01-31/91 <0.2 <15 <4.3 Raw 11/01-30/91 <0.2 <18 <2.0 Treated. 11/01-30/91 <0.3 <66 <3.6 Raw 12/01-31/91 <0.1' <20 <6.3 Treated 12/01-31/91 <0.1 <11 <7.9

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

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

(1) computer malfunction. Analysis Data/Report not retrievable from the diskette. Re-analysis cf the sample was not possible.

109

TABLE C-16 1991 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* IN QUARTERLY COMPOSITES OF RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3

<-- STRONTIUM -->

TYPE SAMPLING PERIOD Sr-89 Sr-90 Raw 01-01-91 to 03-31-91 <0.7 <0.6 Treated 01-01-91 to 03-31-91 <1.3 <1.0 Raw 04-01-91 to 06-30-91 <0.6 <0.4 Treated 04-01-91 to 06-30-91 <1.0 <0.7 Raw 07-01-91 to 09-30-91 <0.5 <0.5 Treated 07-01-91 to 09-30-91 <0.6 <0.5 Raw Treated 10-01-91 to 12-31-91 10-01-91 to 12-31-91

<0.6

<0.7

<0.6

<0.6

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

110

• TABLE C-17 1991 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <- GAMMA EMITTERS ->

STATION ID DATE SAMPLE TYPE K-40 SA-FPV-3E3 05-20-91 Asparagus 2200+/-240 SA-FPV-2G1 (C) 05-07-91 Asparagus 2100+/-220 AVERAGE 2200+/-140 SA-FPL-2F4 07-16-91 Cabbage 2600+/-260 SA-FPL-3H5 (C) 07-16-91 Cabbage 2700+/-240 SA-FPL-5F3 08-06-91 Cabbage 4600+/-340 SA-FPL-14F3 07-30-91 Cabbage 3100+/-400 AVERAGE 3200+/-1800 SA-FPV-2F4 07-16-91 Corn 2500+/-170 SA-FPV-14F3 07-22-91 Corn 2500+/-180 SA-FPV-1G1 (C) 07-16-91 Corn 2700+/-210 SA-FPV-3H5 (C) 07-16-91 Corn 2200+/-170 SA-FPV-3E1 07-30-91 Corn 3100+/-180 AVERAGE 2600+/-660 SA-FPV-3E3 07-30-91 Peppers 1300+/-170 SA-FPV-14F3 08-05-91 Peppers 1500+/-160 SA-FPV-3H5 (C) .07-16-91 Peppers 1400+/-120 SA-FPV-1G1 (C) 07-23-91 Peppers 1900+/-180 SA-FPV-2F4 07-16-91 Peppers 1800+/-150 AVERAGE 1600+/-520 SA-FPV-2F4 07-30-91 Tomatoes 2100+/-180 SA-FPV-14F3 07-22-91 Tomatoes 2100+/-140 SA-FPV-lGl (C) 07-16-91 Tomatoes 2400+/-200 SA-FPV-3H5 (C) 07-16-91 Tomatoes 1700+/-180 AVERAGE 2100+/-570 GRAND AVERAGE 2300+/-1500

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

111

TABLE C-18 1991 CONCENTRATIONS OF GAMMA EMITTERS* IN BEEF AND GAME Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <-- GAMMA EMITTERS -->

STATION ID DATE SAMPLE TYPE K-40 Ra-226 SA-FPB-3El 03-11-91 Beef 2800+/-210 <13 SA-GAM-11D1 02-02-91 Muskrat 2100+/-190 30+/-12 (Control)

SA-GAM-3El 02-09-91 Muskrat 2200+/-190 <18 AVERAGE Muskrat 2200+/-140

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

112

TABLE C-19 1991 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma STATION ID SAMPLING DATE SAMPLE TYPE

<---- GAMMA EMITTERS Be-7 K-40 SA-VGT-2F7 09-07-91 Corn Silage 840+/-140 3000+/-280 SA-VGT-11F3 09-01-91 Corn Silage 580+/-240 3800+/-450 SA-VGT-14F4 09-01-91 Corn Silage 520+/-180 5100+/-520 SA-VGT-3Gl (C) 09-16-91 Corn Silage 300+/-87 4000+/-230 AVERAGE 560+/-440 4000+/-1700 SA-VGT-11F3 11-11-91 Soybeans <170 14000+/-530 SA-VGT-3El 10-26-91 Soybeans <63 14000+/-570 SA-VGT-2F7 11-01-91 Soybeans <160 12000+/-500 SA-VGT-3Gl ( C) 10-25-91 Soybeans <140 13000+/-490 SA-VGT-14F4 10-29-91 Soybeans <53 15000+/-420 AVERAGE 14000+/-2300

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

(C) Control Station 113

TABLE C-20 1991 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING

<----------------------------------- STATION SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El ID -------------------------->

SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-12-91 <1.4 <2.2 <1.4 <1.3 <1.2 02-09-91 <3.6 <1.8 <1.8 <1. 7 <1.8 03-17-91 <1.6 <1.5 <1. 5 2.0+/-1.3 <1.6 t-'

t-' 04-16-91 <1.9 <1.8 <2.8 <1.6 <1.6

.Po 05-10-91 <1.2 <1.3 <1.3 <2.3 <1.2 06-07-91 <1.2 1. 7+/-1.1 <1.1 <1.1 1. 5+/-1.0 07-12-91 1. 3+/-0. 9 1. 6+/-0. 9 1. 4+/-0. 9 <1.0 2.1+/-1.2 1.5+/-0.8 08-12-91 <1.6 <1.4 1.9+/-1.2 <1. 5 2. 7+/-1. 6 09-06-91 <1. 7 <1.6 <1. 7 <1.4 <1.5 10-14-91 <1.6 <1.6 <1.6 <1. 5 <1.6 11-07-91 <2.0 <2.0 <2.4 <1.9 <2.0 12-20-91 <2.2 <2.2 <2.2 <2.2 <2.2

TABLE C-21 1991 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING SA-SWA-llAl SA-SWA-12Cl STATION ID -------------------------->

SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-12-91 62+/-7 47+/-6 62+/-8 22+/-4 29+/-5 44+/-37 02-09-91 62+/-8 31+/-5 78+/-9 8.2+/-3.0 22+/-4 40+/-58 03-17-91 110+/-12 87+/-9 130+/-13 56+/-7 73+/-8 91+/-59 1--'

1--' 04-16-91 74+/-8 60+/-7 90+/-10 37+/-5 lJ1 38+/-5 60+/-46 05-10-91 62+/-7 40+/-5 68+/-8 23+/-4 . 28+/-5 44+/-40 06-07-91 83+/-10 56+/-8 110+/-12 26+/-5 28+/-5 61+/-72 07-12-91 120+/-12 71+/-8 130+/-13 59+/-7 59+/-7 88+/-69 08-12-91 75+/-8 67+/-8 100+/-11 33+/-5 67+/-8 68+/-48 09-06-91 100+/-11 77+/-9 140+/-13 49+/-6 64+/-7 86+/-71 10-14-91 110+/-11 70+/-8 120+/-12 50+/-6 55+/-7 81+/-64 11-07-91 35+/-4 110+/-11 150+/-14 62+/-7 110+/-11 93+/-90 12-20-91 100+/-11 68+/-8 120+/-12 58+/-7 46+/-6 78+/-61 AVERAGE 83+/-51 65+/-42 110+/-57 40+/-36 52+/-51 GRAND AVERAGE 70+/-67

TABLE C-22 1991 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

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

STATION ID DATE I-131 K-40 Ra-226 SA-SWA-llAl 01/12/91 <0.2 83+/-15 <1.9 SA-SWA-12Cl (C) 01/12/91 <0.4 73+/-22 <2.8 SA-SWA-7El 01/12/91 <0.2 96+/-25 <3.1 SA-SWA-1F2 01/12/91 <0.3 <19 <2.6 SA-SWA-16Fl 01/12/91 <0.3 <29 <2.8 SA-SWA-llAl 02/09/91 <0.4 82+/-23 <2.7 SA-SWA-12Cl (C) 02/09/91 <0.3 35+/-14 <2.8 SA-SWA-7El 02/09/91 <0.2 130+/-27 <3.1 SA-SWA-1F2 02/09/91 <0.3 <20 <2.7 SA-SWA-16Fl 02/09/91 <0.4 36+/-14 <2.8 SA-SWA-llAl 03/17/91 <0.1 120+/-26 <2.8 SA-SWA-12Cl (C) 03/17/91 <0.4 81+/-19 <1.0 SA-SWA-7El 03/17/91 <0.2 140+/-28 <2.7 SA-SWA-1F2 03/17/91 <0.4 <29 <2.9 SA-SWA-16Fl 03/17/91 <0.4 83+/-18 <2.6 SA-SWA-llAl 04/16/91 <0.3 71+/-28 <2.6 SA-SWA-12Cl (C) 04/16/91 <0.3 45+/-25 <4.6 SA-SWA-7El 04/16/91 <0.3 57+/-28 <7.9 SA-SWA-1F2 04/16/91 <0.3 46+/-21 <1.7 SA-SWA-16Fl 04/16/91 <0.1 39+/-14 <4.8 SA-SWA-llAl 05/10/91 <0.4 65+/-25 <7.5 SA-SWA-12Cl (C) 05/10/91 <0.3 <45 <2.4 SA-SWA-7El 05/10/91 <0.3 90+/-28 <4.8 SA-SWA-1F2 05/10/91 <0.3 <42 <5.0 SA-SWA-16Fl 05/10/91 <0.4 <47 <5.5 SA-SWA-llAl 06/07/91 <0.2 85+/-24 <2.3 SA-SWA-12Cl (C) 06/07/91 <0.4 78+/-18 <2.0 SA-SWA-7El 06/07/91 <0.4 81+/-26 <8.4 SA-SWA-1F2 06/07/91 <0.5 <29 <2.6 SA-SWA-16Fl 06/07/91 <0.5 <40 <2.2 SA-SWA-llAl 07/12/91 <0.3 160+/-20 <5.3 SA-SWA-12Cl (C) 07/12/91 <0.2 120+/-23 <2.8 SA-SWA-7El 07/12/91 <0.4 120+/-26 <5.8 SA-SWA-1F2 07/12/91 <0.4 72+/-26 <2.9 SA-SWA-16Fl 07/12/91 <0.2 54+/-26 <3.9 116

TABLE C-22 (Cont'd) 1991 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING DATE I-131

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

K-40 Ra-226 SA-SWA-llAl 08/12/91 <0.2 75+/-22 <1. 7 SA-SWA-12Cl ( c) 08/12/91 <0.2 100+/-18 <1.9 SA-SWA-7El 08/12/91 <0.4 91+/-24 <6.1 SA-SWA-1F2 08/12/91 <0.4 <23 <2.9 SA-SWA-16Fl 08/12/91 <0.3 56+/-24 <2.2 SA-SWA-llAl 09/06/91 <0.2 85+/-27 <8.1 SA-SWA-12Cl (C) 09/06/91 <0.2 120+/-33 <3.2 SA-SWA-7El 09/06/91 <0.3 110+/-27 <2.9 SA-SWA-1F2 09/06/91 <0.4 91+/-22 <2.9 SA-SWA-16Fl 09/06/91 <0.4 74+/-20 <2.0 SA-SWA-llAl 10/14/91 <0.3 150+/-29 <3.1 .c SA-SWA-12Cl ( c) 10/14/91 <0.3 52+/-20 <3.7 SA-SWA-7El 10/14/91 <0.2 98+/-21 <2.3 SA-SWA-1F2 10/14/91 <0.2 <49 <2.9 SA-SWA-16Fl 10/14/91 <0.3 120+/-27 <2.7 SA-SWA-llAl 11/07/91 <0.4 180+/-29 <3.4 SA-SWA-12Cl (C) 11/07/91 <0.3 110+/-25 <5.0 SA-SWA-7El 11/07/91 <0.3 160+/-33 <2.7 SA-SWA-1F2 11/07/91 <0.3 64+/-27 <2.6 SA-SWA-16Fl 11/07/91 <0.3 110+/-20 <5.0 SA-SWA-llAl 12/20/91 <0.3 90+/-20 6.8+/-2.0 SA-SWA-12Cl (C) 12/20/91 <0.3 120+/-23 <1.9 SA-SWA-7El 12/20/91 <0.4 98+/-26 <2.4 SA-SWA-1F2 12/20/91 <0.4 91+/-26 <3.5 SA-SWA-16Fl 12/20/91 <0.5 39+/-9 <3.9 AVERAGE 80+/-76

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

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

(C) Control Station 117

Table C-23 1991 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING

<----------------------------------- STATION ID SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE PERIOD (Control) 01-12-91 to <160 <160 210+/-100 <160 <130 03-17-91 04-16-91 t-' to 630+/- 90 <130 <140 <130 <130 t-' 06-07-91 00 07-12-91 to 170+/- 90 <150 <160 <150 <140 09-06-91 10-14-91 to 360+/-100 <160 <150 210+/-100 <160 12-20-91 AVERAGE 330+/-440

TABLE C-24 1991 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90*, TRITIUM AND GAMMA EMITTERS** IN EDIBLE FISH Results in Units of pCi/kg (wet) +/- 2 sigma (Except for strontium in bone analyses which are reported in pCi/kg (dry))

STRONTIUM ***

SAMPLING <-- BONES ---> <---- FLESH---> TRITIUM (FLESH)

STATION ID <-GAMMA EMITTERS (FLESH)->

PERIOD sr-89 sr-90 Sr-89 Sr-90 AQUEOUS FRACTION K-40 SA-ESF-llAl 05/09-12/91 86+/-35 250+/-18 <30 <18 <1000 SA-ESF-12Cl (C) 2700+/-220 05/09-12/91 <74 280+/-17 <26 <16 <1000 3200+/-190

...... SA-ESF-7El 05/09-12/91 78+/-29 280+/-15 <28 <16 <1000

...... 2900+/-170

\0 AVERAGE 79+/-12 270+/-35 2900+/-500 SA-ESF-llAl 09/25-28/91 <20 <14 <48 <29 <500 3300+/-240 SA-ESF-12Cl (C) 09/25-28/91 <26 28+/-8 <43 <26 <500 SA-ESF-7El 3200+/-180 09/25-28/91 <23 <15 <44 <26 <500 3000+/-200 AVERAGE 3200+/-300 GRAND AVERAGE 210+/-240 3000+/-450

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

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

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

(C) Control Station

TABLE C-25 1991 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90*, TRITIUM AND GAMMA EMITTERS** IN BLUE CRABS Results in Unite of pCi/kg (wet) +/- 2 sigma (Except for strontium in shell analyses which are reported in pCi/kg (dry))

<----------- STRONTIUM ----------> *** GAMMA SAMPLING <--- FLESH ---> <--- SHELL ---> TRITIUM (FLESH) EMITTER (FLESH)

STATION ID DATE Sr-89 Sr-90 sr-89 sr-90 AQUEOUS FRACTION K-40 SA-ECH-llAl 06/24-25/91 <51 <33 42+/-10 85+/-8 <1000 1100+/-100 SA-ECH-12Cl (C) 06/24-25/91 <46 <30 37+/-12 160+/-10 <1000 1200+/-160 AVERAGE 40+/-5 120+/-75 1200+/-100

!-..)

0 SA-ECH-llAl 09/25-26/91 <42 <24 56+/-21 160+/-16 <500 1600+/-180 SA-ECH-12Cl ( C) 09/24-25/91 <38 <22 52+/-21 190+/-17 <500 2800+/-240 AVERAGE 54+/-4 180+/-30 2200+/-1200 GRAND AVERAGE 47+/-15 150+/-78 1700+/-1400

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

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

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

(C) Control Station

TABLE C-26 1991 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SEDIMENT Results in Units of pCi/kg (dry) +/- 2 sigma SAMPLING <----------------------------- GAMMA EMITTERS ----------------------------->

STATION ID DATE Sr-90 K-40 Mn-S4 Co-S8 Co-60 cs-134 Cs-137 Ra-226 Th-232 SA-ESS-llAl 06-07-91 <26 6900+/-330 24+/-10 32+/-11 <34 <13 <7.2 430+/-40 Sl0+/-62 SA-ESS-lSAl 06-07-91 <24 SS00+/-220 28+/-10 30+/-10 41+/-14 <Sl <7.3 640+/-2S 740+/-S4 SA-ESS-16Al 06-07-91 <2S 3700+/-240 28+/-11 <26 49+/-2S 47+/-14 <S.8 660+/-42 730+/-66 SA-ESS-12Cl (C) 06-07-91 <19 16000+/-4SO <16 <14 <16 S1+/-14 <8.2 610+/-42 860+/-64 SA-ESS-7El 06-07-91 <22 7900+/-2SO <14 <4.8 <7.9 <S.S <19 670+/-28 6S0+/-44

...... SA-ESS-16Fl 06-07-91 <2S 1SOOO+/-S20 <4.1 <16 <16 <76 <SS S80+/-40 800+/-86 N

...... AVERAGE 600+/-180 720+/-2SO 9200+/-10000 19+/-19 lA-ESS-llAl 11-07-91 <19 3100+/-140 19+/-6 S8+/-9 S2+/-7 <2.6 <4.S 170+/-14 210+/-27 SA-ESS-lSAl 11-07-91. <29 18000+/-690 <36 <21 <21 <22 190+/-30 810+/-70 1200+/-120 SA-ESS-16Al 11-07-91 <24 3S00+/-160 <13 28+/-8 <6.1 <3.S <6.8 460+/-20 400+/-34 SA-ESS-12Cl (C) 11-07-91 <22 18000+/-540 <28 <13 <14 <15 <12 660+/-50 920+/-93 SA-ESS-7El 11-07-91 <20 10000+/-310 <8.6 <8.4 <32 <6.2 27+/-9 600+/-31 590+/-53 SA-ESS-16Fl 11-07-91 <23 18000+/-490 <11 <11 <14 <7.4 <20 620+/-40 920+/-91 AVERAGE 12000+/-14000 5S0+/-440 530+/-690 GRAND AVERAGE 10000+/-12000 580+/-320 620+/-530

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

(C) Control Station

TABLE C-27 1991 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <------------AIR------------> <-------WATER-------> <--------MILK------->

IODINE PARTICULATES GAMMA SCAN IODINE GAMMA SCAN IODINE ACTIVITY: 10-3 pCi/m3 10-3 pCi/M3 pCi/L pCi/L pCi/L pCi/L GEOMETRY: 100 ML 13 FILTERS 3.5 LITER 100 ML 3.5 LITER 100 ML COUNT TIME: 120 MINS 1000 MINS 100 MINS 1000 MINS 500 MINS 1000 MINS DELAY TO COUNT: 2 DAYS 5 DAYS 7 DAYS 3 DAYS 2 DAYS 2 DAYS NUCLIDES BE-7 6.8 15 22 NA-22 0.45 11 4.5 K-40 7 .1 35 120 CR-51 2.9 16 22 MN-54 0.32 1. 7 3.4 C0-58 0.33 1.6 2.9 FE-59 0.79 3.7 7.2 C0-60 0.36 2.1 4.0 ZN-65 0.69 3.9 8.6 NB-95 0.49 3.1 ZR-95 0.44 5.7 ZRNB-95 3 M0-99 550 200 41 RU-103 0.33 1.6 2.5 RU-106 2.9 14 28 AG-100m 0.55 2.0 3.4 SB-125 0.77 4.0 8.2 TE-129m 120 62 99 1-131 13.0 0.98 3.8 0.60 3.2 0.42 TE-132 41 13 3.9 BA-133 3.7 CS-134 0.39 1.8 3.0 CS-136 0.56 2.9 3.3 CS-137 0.28 1.6 3.2 BA-140 2.2 LA-140 BALA-140 15 15 CE-141 0.31 2.3 3.9 CE-144 1.1 9.2 17 RA-226 0.87 7.4 6.6 TH-232 1. 2 7 .1 12 122

TABLE C-27 (cont't) 1991 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <------FOOD PRODUCTS-------> FODDER & BEEF FISH SEDIMENT GREEN CHOP & GAME SHELLFISH & SOIL ACTIVITY pCi/KG WET pCi/kg WET pCi/kg WET pCi/kg WET pCi/kg DRY GEOMETRY: 100 ml 500 ml 500 ml 500 ml 500 ml 500 ml COUNT TIME: 1000 MINS 500 MINS 500 MINS 500 MINS 500 MINS 500 MINS DELAY TO COUNT: 10 DAYS 3 DAYS 7 DAYS 5 DAYS 5 DAYS 30 DAYS NUCLIDES BE-7 0.99 59 580 44 44 185 NA-22 2.1 9.4 15 6.9 6.9 13 K-40 32 70 85 70 70 640 CR-51 9.2 25 100 41 41 155 MN-54 1.2 4.8 10 69 69 35 C0-58 1.8 8.0 13 5.3 5.3 58 FE-59 3.6 16 53 14 14 46 0-60 2.3 7.6 21 6.8 6.8 32

-65 3.6 12 38 14 14 42 2.0 10 16 10 10 36 ZR-95 2.2 27 30 27 27 43 ZRND-95 M0-99 96 95 442 213 213 316000 RU-103 1.0 5.0 7.9 4.9 4.9 24 RU-106 12 49 110 38 38 109 AG-110m 2.2 8.7 19 12 12 21 SB-125 2.8 14 36 12 12 36 TE-129m 4.7 208 539 204 204 586 1-131 2 8.3 28 8.4 8.4 185 TE-132 4.4 8.5 150 15 15 7200 BA-133 CS-134 0.96 6.5 15 5.7 5.7 22 CS-136 1.5 6.1 19 7.5 7.5 46 CS-137 1.4 6.7 19 18 18 20 BA-140 6.0 35 75 35 35 240 LA-140 2.2 15 30 15 15 80 BALA-140 CE-141 1.0 5. 1 9.8 5.2 5.2 26 CE-144 4.2 20 45 24 24 52 RA-226 2.3 15 48 36 36 40 TH-232 6.1 31 74 29 29 110 123

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES

• 125

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by the PSE&G Research and Testing Laboratory and contract laboratories for analyzing the 1991 Artificial Island Radiological Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates *.*****.*.*.*.****.* 129 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131 GROSS BETA PSE&G Analysis of Air Particulates ..*..******...**.*.* 132 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 134 POTASSIUM-40 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 135 TRITIUM PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 136 CEP Analysis of Aqueous Fraction of Fish and Crab *** 137 IODINE-131 PSE&G Analysis of Filtered Air ***.****..************** 138 PSE&G Analysis of Raw Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . 139 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 140 STRONTIUM-89 AND STRONTIUM-90 PSE&G Analysis of Air Particulates .*.*********.*.***** 141 PSE&G Analysis of Raw Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . 144 PSE&G Analysis of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 147 PSE&G Analysis of Vegetation, Meat and Aquatic Samples 150 PSE&G Analysis of Bone and Shell ...**.*******.******** 153 PSE&G Analysis of Soil and Sediment **********.**..***. 156 PSE&G Analysis of Samples for Stable Strontium **.***** 159 127

SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd)

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . 161 PSE&G Analysis of Raw Milk .. . . . . . . . . . . . . . . . . . . . . ~ ..... 162 PSE&G Analysis of Water . . . * . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 PSE&G Analysis of Solids (combined procedures) ****.... 164 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters *****..* 165

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

TI - Teledyne Isotopes 128

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

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

Calculation of Gross Alpha Activity:

Air flow is corrected first by using the following equations:

p = (B-V)./29. 92 p = Pressure correction factor B = Time-averaged barometric pressure during sampling period, "Hg v = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°F, "Hg v = F*P*0.946*0.0283 E F = Uncorrected air flow, ft 3

• 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %

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

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

T = count time of sample and blank, mins.

E = Fractional Am-241 counting efficiency v = Corrected air flow of sample, m3 2.22 = No. of dpm per pei 129

2-sigma error (pCi/m3) = (l.96*(G+B)1/2)*A (G-B)

A = Gross alpha activity, pCi/m+3 G = Sample gross counts B = Background counts (from blank filter)

Calculation of lower limit of detection:

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

LLD(pCi/m3) = 4.66 * (B)1/2 (2.22)*(E)*(V)*(T)

B = Background counts (from blank filter)

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

130 L

• SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF WATER SAMPLES Water samples require pretreatment of all suspended material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample filtrate. The combined sample is then neutralized with dilute ammonium hydroxide. From this point, both sample and blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to 50°C in order to help precipitate barium sulfate. Maintaining the same 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 geometry. The blank is treated in the same manner as the sample.

Calculation of Gross Alpha Activity:

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

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

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

A = Gross alpha activity, pCi/L G = Sample gross counts B = Background counts (from blank sample) 131

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

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

Calculation of Gross Beta Activity:

Air flow is corrected first by using the following equations:

P = (B-V)/29.92 p = Pressure correction factor B = Time-averaged barometric pressure during sampling period, "Hg v = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°F, "Hg v = F*P*0.946*0.0283 E F = Uncorrected air flow, 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 beta activity is computed as follows:

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

T = Count time of sample and blank, mine.

E = Fractional Sr-90 counting efficiency v = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 132

2-sigma error (pCi/m3) = (l.96*(G+B)1/2)*A (G-B)

A Gross beta activity, pCi/m3 G Sample gross counts B = Background counts (from blank filter)

Calculation of lower limit of detection:

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

LLD(pCi/m3) = 4.66 * (B)1/2 (2.22)*(E)*(V)*(T)

B = Background counts (from blank filter)

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

133

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a 1.0 liter portion is removed from the potable, rain or well water container and 250ml taken from each surface water.

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

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

Calculation of Gross Beta Activity:

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

G = Sample gross counts

.B = Background counts (from blank sample)

T = Count time of sample and blank E = Fractional counting efficiency from Sr-90 source v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = (l.96*(G+B)1/2)*A (G-B)

A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank sample) 134

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR POTASSIUM 40 A 60 ml aliquot of water is acidified to pH <2 with concentrated nitric acid and then analyzed for potassium by the following Atomic Absorption Spectrophotometry method: potassium standards of known concentrations (similar to that of the samples) are first prepared. An aliquot of each sample and standard is pipetted into stoppered erlenmeyer flasks. In addition, a duplicate sample, water blank and a quality control sample are likewise pipetted into their respective flasks. A solution consisting of 1%

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

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

Calculation of K-40 Activity:

K-40 Activity (pCi/L) = O.BS*C 0.85 = Proportionality constant for converting ppm to -pei/L c = Potassium concentration, ppm 135

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing Bml of sample, lOml of Instagel, and O.lml-0.2ml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Bml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted.

Activity is computed as follows:

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

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

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

E = (N)*(D)

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

N = C-(G/T) c = CPM of spiked sample G = Gross counts of sample T = Count time (min)

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

1. 96* (G/T2 +B/T2) 1/2 * ( 1000) 2.22*(V)*(E)

Samples are designated LLD if the activity is less than the following value:

LLD (pCi/L) = (4.66)*(8)1/2*(1000) 2.22*(V)*(E)*(T) 136

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

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

The resultant mixture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approximately 30 percent, when counted on a Beclanan 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

• 137

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF AIR IODINE Approximately 300m3 of air is drawn through a SOml bed of triethylenediamine (TEDA)-impregnated charcoal granules at a rate which closely corresponds to the breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing SOml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.

Calculation of Gamma Activity:

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

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

N = Net counts under photopeak D Decay correction factor

>.tl*EXP(>.t2) 1-EXP(->.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition

). = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

v = Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3) = 1.96*(GC+Bc)1/2*R N

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

The LLD (pCi/m3) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 138

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

Calculation of I-131 Activity:

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

N = Net counts under photopeak D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl Acquisition live time t2 Elapsed time from sample

• E collection to start of acquisition A = 0.693/nuclide half life Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, L 2.22 = No. of dpm per pci 2-sigma error (pci/L) = 1.96*(GC+Bc)1/2*R N

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

The LLD (pci/L) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 139

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

Calculation of I-131 Activity:

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

N = Net counts under photopeak D = Decay correction factor

>.tl*EXP(>.t2) 1-EXP(->.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition

). = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

v = Sample volume, L 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1.96*(GC+BC)1/2*R N

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

The LLD (pCi/L) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 140

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

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/m3) = N4/R (2.22)*(E)*(E(lS)fE')*(S6)*(V)*(U)

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

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of Sr-90 efficiency at thickness value of 1Smg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

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

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

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

I2 =1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count 141

t2 Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

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

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

f°i* (X+Y) + (Xl+Yl) *Fl~l 1/2

[ w12 w12 J Again, keeping the same variable definitions,

• (Wl*W2)

(N2-Fl*Nl) the LLD for Sr-90 (pCi/m3) =

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

[ Wl2 W12 J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/m3) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)

= W3 57 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

N6 = Nl - N7*(1 + Rl*Il)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 142

• E(lS)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to 5r-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 EXP ((-0.693/50.S)*t) t Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 =Half-life of 5r-89, days All other quantities are as previously defined.

The 2-sigma error for sr-89 (pCi/m3) = 2

• cs02+592,2

• w3 (Nl - N7*(l+Rl*Il))

SB = tX+Y) + (Xl+Yl) *Fi' 1/2 w12 w12 59 = (Xl+Yl)1/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 5r-89 (pCi/m3) =

4.66*(582+592,112 143

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF RAW MILK Stable strontium carrier is first introduced into a milk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations. These cations are then eluted off with a TRIS-buffered 4N sodium chloride solution into a beaker and precipitated as carbonates. The carbonates are converted to nitrates with 6N nitric acid and, by acidifying further to an overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precip-itation. Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip. The strontium is precipitated as its carbonate, filtered, dried and weighed to determine strontium recovery. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(15)/E')*(S6)*(V)*(U)

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

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

E = Sr-90 counting standard efficiency v = Sample quantity (liters) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl)

Il =1 - EXP ((-0.693/2.667)*tl) 144

I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M +.F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

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

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

~* (X+Y) + (Xl+Yl)*Fl;i1/2 * (Wl*W2)

L. w12 w12 =1 (N2-Fl*Nl)

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

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

[ w12 w1 2 J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)

= W3 57 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

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

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 145

E(lS)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

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

The 2-sigma error for Sr-89 (pCi/L) = 2* (S82+s92)1/2

• W3 (Nl - N7*(l+Rl*Il))

SS =fi_x+Y) + (Xl+Yl)*Fl2 /2

[w12 w12 S9 = (Xl+Yl) 1 /2 All other variables are as previously defined.

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

4.66*(S82+s92)1/2 146

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank are then .. made alkaline and heated to near boiling before precipitating the carbonates. The carbonates are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric hydroxide (yttrium strip) followed by a barium chromate strip.

The strontium is precipitated as a carbonate before being dried and weighed.

The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Since surface waters, as well as some drinking water samples, have been found to contain significant amounts of stable strontium, a separate aliquot from each sample is analyzed for stable strontium. These results are used in correcting the chemical recovery of strontium to its true value.

Calculation of sr-90 Activity:

Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)

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

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness value of 1Smg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = Sr-90 counting standard efficiency v = Sample quantity (liters) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl)

Il =1 - EXP ((-0.693/2.667)*tl) 147

I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

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

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

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

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

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

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

[ w12 w12 J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(lS)fE')*(S7)*(V)*(U)*(F9)

= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

N6 = Nl - N7*(1 + Rl*Il)

N7 = (N2 - Fl*Nl)/Wl (This represents counts due to sr-90) 148

• E(l5)/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)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of Sr-89, days All other quantities are as previously def.ined.

The 2-sigma error for Sr-89 (pCi/L) = 2* (S82+s92)1/2

• W3 (Nl - N7*(l+Rl*Il))

SS =f<X+Y) + (Xl+Yl)*Fl2 1/2

~12 w12 S9 = (Xl+Yl)1/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for sr-89 (pCi/L) =

4.66*(S82+s92)1/2 149

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT, CRAB SHELL AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, before being placed in an oven to dry at 100°C. At the completion of the drying period, samples are again weighed (recorded as "dry" weight) and then pulverized. A measured amount (quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed in a muffle furnace. The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 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 (HNa3). The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming HNa3. After calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroxide followed by coprecipitation on barium chromate. The strontium is precipitated as its carbonate, which is dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/kg wet) = N4/R (2.22)*(E)*(E(15)/E')*(S6)*(V)*(U)

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

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

E = sr-90 counting standard efficiency V = Sample quantity (kg wet)

U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 150

• I1 = 1 - EXP ((-0.693/2.667)*tl)

I2 = 1 - EXP ((-0.693/2.667)*t2) tl Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl =D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

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

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

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

[ w12 w12_ J (N2-Fl*Nl)

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

r;66* (X+Y) + (Xl+Yl)*Fa1/2

[ w12 w1 2 J Calculation of Sr-89 Activity:

sr-89 Results (pCi/kg wet) = N6/R (2.22)*(E)*(E(lS)fE')*(S7)*(V)*(U)*(F9)

= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

N6 = Nl - N7*(1 + Rl*Il) 151

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

E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.S = Half-life of sr-89, days All other quantities are as previously defined.

The 2-sigma error for Sr-89 (pCi/kg wet) = 2* (582+592) 1/2

• W3 (Nl - N7*(l+Rl*Il))

58 =lc°X+Y) + (Xl+Yl)*Fl;i1/2

[!12 w12 :J S9 = (Xl+Y1)1/2 All other variables are as previously defined.

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

4.66*(S82+s92)1/2 152

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE The bone or shell is first physically separated from the rest of the sample before being broken up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontium carrier and cesium holdback carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered.

The sample is then treated with concentrated (70%) nitric acid and boiled until strontium nitrate crystallizes out. The strontium nitrate is freed of calcium by repeated fuming nitric acid recrystallizations. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide followed by coprecipitation with barium chromate. The strontium is precipitated as strontium carbonate, which is dried, weighed, then beta-counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)

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

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

E = Sr-90 counting standard efficiency V = Sample quantity (kg dry)

U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only 153

Wl = ((1 + Rl*I2) - ( 1 + Rl

• I1) *Fl)

I1 1 - EXP ((-0.693/2.667)*tl)

I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

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

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigrna error for Sr-90 (pCi/kg dry) =

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

[ w1 2 w1 2

J (N2-Fl*Nl)

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

~.66* (X+Y) + (Xl+Yl)*Fl3 1 1 2

[ w12 w12 Calculation of Sr-89 Activity:

Sr-89 Results (pCi/kg dry) = N6/R (2.22)*(E)*(E(15)/E')*(S7)*(V)*(U)*(F9)

= W3 S7 = G + H*M + I*M2 (.This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

154

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

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

E(l5)/E' = Ratio of sr-89 efficiency at thickness value of 15mg/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)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

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

The 2-sigrna error for Sr-89 (pCi/kg dry)= 2* (S82+s9 2 ) 1 /2

• W3 (Nl - N7*(l+Rl*Il))

S8 =fix+Y) + (Xl+Yl)*Fl2 1/2

[w1 2 w1 2 S9 = (Xl+Yl) 1 /2 All other variables are as previously defined.

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

4.66*(S82+s9 2 ) 1 /2 155

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

These carbonates are first filtered and then digested with 6N HNc3. Two fuming (90%) HNc3 recrystallizations are then performed to remove calcium.

Subsequently, radioactive impurities are removed by two precipitation steps, using ferric hydroxide and barium chromate as carriers. The strontium is precipitated as strontium carbonate before being dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.). There is a second count at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(lS)fE')*(S6)*(V)*(U)

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

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

E = Sr-90 counting standard efficiency v = Sample quantity (kg dry) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 156

• Il I2 tl

=

=

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

Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

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

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

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

[ w12 w1 2

J (N2-Fl*Nl)

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

~ 66* (X+Y) + (Xl+Yl)*Fl~1/Z

[ w12 w12 J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/kg dry) = N6/R (2.22)*(E)*(E(lS)fE')*(S7)*(V)*(U)*(F9)

= W3 S7 =G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

• N6 = Nl - N7*(1 + Rl*Il) 157

N7 (N2 - Fl*Nl)/Wl (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)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

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

The 2-sigrna error for Sr-89 (pCi/kg dry) = 2* (S82+s92)1/2

• W3 (Nl - N7*(l+Rl*Il))

SB =flx+Y) + (Xl+Yl)*Fl~1/2 t.=w12 w12 _J S9 = (Xl+Y1)1/2 All other variables are as previously defined.

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

4.66*(S82+s92)1/2 158

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Chemical/Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes. In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by ashing 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask.

All the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium. The sample, spiked samples and blank absorbance are determined by Atomic Absorption Spectroscopy (AAS) and are plotted graphically. The true sample concentrations are then extrapolated from this graph. Chemical and ionization interferences are controlled by the addition of 0.1% or more of lanthanum to all samples.

For analysis of wai:er, a 60-ml aliquot of sample is removed, acidified to pH

<2 with hydrochloric or Nitric acid and analyzed by AAS or AES as follows: A series of strontium standards (of similar concentration to the unknowns) is prepared. Then, to 9 ml of each prepared sample, blank and standard, is added 1 ml of lanthanum to achieve a minimum of 0.1\ lanthanum in all solutions.

All results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.

Sample Calculation of Corrected Chemical Recovery of Strontium in Soil and Sediment:

Reported concentration of stable strontium (mg/L):ll9 Volume of specimen (ml):25 (removed from lOOOml of diluted leachate)

Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml flask= (119mg/L) x (.025L/25ml) x (25ml)

2.98mg Sr Since 2.98mg Sr represents the quantity of stable strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample

2.98mg Sr = 119 mg 0.025 159

Net weight of srco3 precipitate (mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (125mg) x (.5935) = 74.2 Corrected chemical recovery of strontium = 74.2 = 0.623 119.0 The calculations follow the same sequence for bone and shell samples.

Sample Calculation of Corrected Chemical Recovery of Strontium in Water:

Reported concentrations of stable strontium (mg/L): 1.65 Volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample = (l.65mg/L) x (2.0L)

= 3.30mg Quantity of strontium carrier added to sample (mg): 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of srco3 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935) = 17.2mg Corrected chemical recovery of strontium= 17.2mg = .738 23.3mg 160

• SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF AIR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a given location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top. The Petri dish is closed and the sample counted on a gamma detector.

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

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

N = Net counts under photopeak D = Decay correction factor Atl*EXP(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, m3 2.22 = No. of dpm per pei 2-sigma error (pCi/m3) = l.96*(GC+BC)1/2*R N

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

The LLD (pCi/m3) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 161

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

Calculation of Gamma Activity:

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

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

N = Net counts under photopeak D = Decay correction factor

). tl*EXP().t2) 1-EXP(-Atl) tl Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition

). = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

v = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1.96*(GC+Bc)1/2*R N

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

The LLD (pCi/L) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 162

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated Marinelli beaker and then counted on a gamma detector.

Calculation of Gamma Activity:

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

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

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

T = Acquisition live time, mins.

V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1.96*(GC+BC)1/2*R N

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

The LLD (pCi/L) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 163

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF SOLIDS Several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required. For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm3), when possible, in a tared aluminum can. The can is weighed, hermetically sealed and counted.

In most cases, a wet sample is prepared (when a lower sensitivity is acceptable) by either grinding/chopping the wet sample or by using a food processor to puree it. The sample is poured into a calibrated, tared clear plastic container, aluminum can, or marinelli beaker until a standard volume is reached for that container. The sample is weighed, sealed, and counted.

Soil and sediment samples are first oven dried until a constant weight is achieved and then pulverized. The sample is added to a tared aluminum can, compacted to a standard volume and weighed. It is hermetically sealed, cured for 30 days to allow for ingrowth, and counted.

Calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma

• error and LLD:

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

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

T = Acquisition live time, mine.

v - Sample volume, kilograms 2.22 = No. of dpm per pCi 2-sigma error (pCi/kg) = 1.96*(GC+BC)1/2*R N

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

The LLD (pCi/kg) = 4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 164

• SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso4 :Dy phosphor. They are first annealed in a 2S0°c oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized Cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are subtracted to allow for transit dose and system back-ground.

The results are computed as follows:

For any given area of the dosimeter, the dose in mR is calculated by the following formula:

DOSE =R * (REDOSE/RR)-AVC R *= Initial reading of the area RR = Second reading of the area

• (after re-irradiation)

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

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

CREDOSE = Re-irradiation dose of the control dosimeter, mR 165

I*

I APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOIVIPARISON STUDIES PROGRAM RESULTS 167

APPENDIX E

SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the 1991 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE E-1 Gross Alpha and Gross Beta Emitters in Water and Air Particulates. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 o E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 171 E-3 Tritium in Water................................. 172 E-4 Iodine in Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 173 E-5 Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products.................... 174 169

TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter)

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 01-91 EPA-WAT-AB319 Water Alpha 5+/-0.6 5+/-5 Beta 5.8+/-0 5+/-5 03-91 EPA-APT-GABS323 APT Alpha 39+/-0.5 25+/-6 Beta 121+/-1. 6 124+/-6 04-91 EPA-WAT-P324 Water Alpha 46+/-0.5 54+/-14 Beta 114+/-6.9 115+/-17 05-91 EPA-WAT-AB327 Water Alpha 26+/-1.2 24+/-6 Beta 46+/-1.7 46+/-5 08-91 EPA-APT-GABS331 APT Alpha 20+/-0.8 25+/-6 Beta 93+/-1.2 92+/-10 09-91 EPA-WAT-AB333 Water Alpha 11+/-0.5 10+/-5 Beta 21+/-1.4 20+/-5 10-91 EPA-WAT-P337 Water Alpha 134+/-1.2 82+/-21 Beta 62+/-2.1 65+/-10

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

• • known value plus or minus one sigma as reported by EPA 170

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

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-91 EPA-WAT-G320 water Ba-133 86+/-2.5 75+/-8 Co-60 45+/-0.9 40+/-5 Zn-65 157+/-7.4 149+/-15 Ru-106 227+/-15 186+/-19 Cs-134 13+/-1. 7 8+/-5 Cs-137 13+/-0.8 8+/-5 03-91 EPA-APT-GABS323 APT Cs-137 39+/-0.5 40+/-5 I

I 04-91 EPA-WAT-P324 Water Cs-134 25+/-1.2 24+/-5 Cs-137 26+/-0.9 25+/-5 :I 04-91 EPA-MLK-GS325 Milk Cs-137 51+/-0.9 49+/-5 K(l) 1660+/-53 1650+/-83 I-131 63+/-0.5 60+/-6 6-91 EPA-WAT-G328 Water Co-60 12+/-0.5 10+/-5 Zn-65 110+/-3.1 108+/-11 Ru-106 155+/-5.7 149+/-15 Cs-134 17+/-1. 7 15+/-5 Cs-137 17+/-0 14+/-5 Ba-133 64+/-2.6 62+/-6 08-91 EPA-APT-GABS331 APT Cs-137 26+/-0.5 30+/-5 09-91 EPA-MLK-GS334 MLK I-131 110+/-2.6 108+/-11 Cs-137 32+/-1.2 30+/-5 K(l) 1670+/-19 1740+/-87 10-91 EPA-WAT-G335 water Co-60 30+/-0.8 29+/-5 Zn-65 74+/-1. 7 73+/-7 Ru-106 215+/-7.4 199+/-20 cs-134 11+/-0.9 10+/-5 Cs-137 12+/-0.8 10+/-5 Ba-133 109+/-1.9 98+/-10 10-91 EPA-WAT-P337 water Co-60 21+/-0.5 20+/-5 Cs-134 11+/-0.8 10+/-5 Cs-137 13+/-1.2 11+/-5 Reported as mg/l of Potassium

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

• known value plus or minus one sigma as reported by EPA 171

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

DATE * **

PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-91 EPA-WAT-H322 Water H-3 5210+/-17 4420+/-440 06-91 EPA-WAT-H329 Water H-3 12370+/-47 12480+/-1250 10-91 EPA-WAT-H336' Water H-3 2270+/-97 2450+/-350

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

• • known value plus or minus one sigma as reported by EPA 172

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

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 02-91 EPA-WAT-I321 Water I-131 79+/-1.9 75+/-8 08-91 EPA-WAT-I330 Water I-131 19+/-0.8 20+/-6

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

• • known value plus or minus one sigma as reported by EPA 173

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

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

DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known 01-91 EPA-WAT-S318 Water Sr-89 5+/-0.6 5+/-5 Sr-90 5+/-0.1 5+/-5 03-91 EPA-APT-GABS323 APT Sr-90 40+/-0.5 40+/-5 04-91 EPA-WAT-P324 Water sr-89 18+/-1.2 28+/-5 Sr-90 25+/-0 26+/-5 04-91 EPA-MLK-GS325 Milk Sr-89 34+/-1.7 32+/-5 Sr-90 28+/-0.8 32+/-5 05-91 EPA-WAT-S326 Water Sr-89 42+/-2.9 39+/-5 Sr-90 27+/-1.6 24+/-5 08-91 EPA-WAT-GABS331 APT Sr-90 32+/-0.5 30+/-5 09-91 EPA-WAT-S332 Water Sr-89 51+/-1.6 49+/-5 Sr-90 24+/-1. 7 25+/-5 09-91 EPA-MLK-GS334 Milk sr-89 22+/-2.l 25+/-5 sr-90 24+/-0.8 25+/-5 10-91 EPA-WAT-P337 Water Sr-89 12+/-0.5 10+/-5 sr-90 10+/-0.5 10+/-5

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

• • known value plus or minus one sigma as reported by EPA 174

• APPENDIX F SYNOPSIS OF LAND USE CENSUS 175

APPENDIX F SYNOPSIS OF 1991 LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 50m2 (500ft2) producing broad leaf vegetation in each of the 16 meteorological sectors.

Tabulated below are the results of these surveys:

Milk Nearest Vegetable Animal Residence Garden Meteorological Sept., 1990 Sept/Oct 1990 Sept/Oct 1990 Sector km (miles) km (miles) km (miles)

N None None None NNE None 6.9 ( 4. 3) None NE None 6.4 ( 4. 0) None ENE None 5.8 (3. 6) None E None 5.4 (3.4) None ESE None None None SE None None None SSE None None None s None 6.6 ( 4 .1) None SSW None 5.5 (3. 4) None SW None 6.9 ( 4. 3) None WSW None 7.1 (4.4) None w 7.8 (4.9) 6.5 ( 4. 0) None WNW None 5.5 (3. 4) None NW None 5.9 (3.7) None NNW None 6.8 ( 4. 2) None 177