ML18101B347

Radiological Environ Monitoring Program for Salem & Hope Creek Generating Stations 1995 Annual Radiological Environ Operating Rept Jan-Dec 1995.

ML18101B347
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Site:	Salem, Hope Creek
Issue date:	12/31/1995
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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 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

• JANUARY 1 TO DECEMBER 31, 1995 Prepared By PUBLIC SERVICE ELECTRIC AND GAS COMPANY MAPLEWOOD TESTING SERVICES APRIL 1996 9605070278 960430 PDR ADOCK 05000272 R PDR

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM & HOPE

• CREEK GENERATING STATIONS 1995 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1995

- _j

TABLE OF CONTENTS PAGE

• SU'MMARY ......* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1 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 Program Changes. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

• Results and Discussion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Atmospheric. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Direct Radiation.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Terrestrial. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

21 22 23 24 Aqua.tic. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Program Deviations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 Conclusions... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 APPENDIX A - PROGRAM

SUMMARY

............................... 53 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS ........_. . . . . . 63 APPENDIX C - DATA TABLES.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES.. . . . . . . . . . .. . 109 APPENDIX E -

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 151

~PENDIX F - SYNOPSIS OF LAND USE CENSUS . . . . . . . . . . . . . . . . . . . 159 APPENDIX G - SUPPLEMENTAL SECTION/TABLES . . . . . . . . . . . . . . . . . . . . 163 i

LIST OF TABLES TABLE NUMBER TABLE DESCRIPTION

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

• 6

2. 1995 Radiological Environmental Monitoring Program (Program Overview) ................................ . 39 LIST OF FIGURES FIGURE NUMBER FIGURE DESCRIPTION ~

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

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

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

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

5. BWR Mark 1 Primary Containme~t Cross-Section (Hope Creek) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

6. Beta in Air Particulate 1973 through 1995 (Quarterly)...................... 43

7. Ambient Radiation - Offsite Vs Control Station 1~73 through 1995 (Quarterly)...................... 44

8. Iodine-131 Activity in Milk ,

1973 through 1995 (Quarterly)...................... 45 ii

LIST OF FIGURES (cont'd.)

FIGURE NUMBER FIGURE DESCRIPTION

9. Gross Beta and Potas.sium-40 Activity in Surface Water 1973 through 1995 (Quarterly) . . . . . . . . . . . . . . . . . . . . . . 46 .

10. Tritium Activity in Surface Water 1973 through 1995 (Quarterly)...................... 47 llA. Cesium-137 Activity in Water Sediment 1977 through 1995 (Semi-Annual) . . . . . . . . . . . . . . . . . . . . . . 48 llB. Cobalt-60 Activity in Water Sediment 1977 through 1995 (Semi-Annual) . . . . . . . . . . . . . . . . . . . . . . 49 ., '

12. Strontiun-90 and Cesium-137 Activity in Soil 1974 through 1995 (Yearly) . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 iii

SUMMARY

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

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

The PSE&G Maplewood Testing Services (MTS) has* been responsible for the collection and analysis of environmental samples during the period of January 1, 1995, through December 31, 1995, and the results are discussed in this report. The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted in accordance with the SGS and HCGS .- Technical Specifications. The Lower Limit of Detection (LLD) values required by the Technical Specifications were achieved for this reporting period. The objectives of the program were also met during this period. The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.

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 Salem and Hope Creek Generating Stations were compared to background or control measurements and the preoperational REMP study performed before Salem Unit 1 became operational. Samples of air particulates, air iodine, precipitation, milk, surface, ground and drinking water, vegetables, beef, game, fodder crops, soil, fish, crabs, and sediment were collected and analyzed.

External radiation dose measurements were also made in the vicinity of SGS/HCGS using thermoluminescent dosimeters.

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

~GS Units One and Two and HCGS had no significant impact on the

~radiological characteristics of the environs of these stations.

1

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 1752 analyses on 949 environmental samples during 1995. Direct radiation dose measurements were also made using 506 thermoluminescent dosimeters (TLDs) .

• 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 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 quarterly TLDs at 31 offsite locations around Artificial Island averaged 53 millirems for I

the year 1995. An average of the control locations I

(background) for this time was 55 millirems for the year. This was comparable to the preoperational phase of the program which I had an average of 55 millirems per year for 1973 to 1976 .

2

INTRODUCTION This section gives a brief description of the characteristics,*

effects, and sources of radiation and the operation of a nuclear generating station, both a boiling water reactor and a pressurized water reactor.

• RADIATION CHARACTERISTICS The word "radioactive" describes the state of the nucleus of an atom containing an excess of energy. The excessive energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom. To release this excess energy the atom emits electromagnetic or particulate radiation to become stable (non-radioactive). This process is called radioactive decay. Part of the electromagnetic spectrum consi~ts of gamma-rays arid 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 haye no charge at all (neutron) .

adioactive decay is measured in terms of "half-life". The half-life may be defined as the amount of time it takes for 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 disintegrations (decays) of the source of radiation. per unit of time. The unit of this measurement is called the curie. One curie equates to 2.2 X 12 10 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 6

millionth of a curie and represents 2.2 X 10 decays per minute, while the picocurie is one millionth of a microcurie and represents 2.2 decays per minute .

• 3

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

There are essentially two types of exposure to radiation: external and internal. External exposure can involve the total body, thereby implying exposure to ali organs, or part9 of the bQdy, 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 radiDcesium 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 expressed in terms of a unit called the rem. A better unit of dose, the millirem (mrem; 1 mrem =1/1000 rem) is most often used because the typical dose is usually on the order of thousandths of a rem. Another term used is the collective dose to a population, called a person-rem.

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

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

4

• Many sources of radiation exist today and, of them, the most universal and least controllable is background radiation from terrestrial radioactivity and cosmic rays. Terrestrial

• 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 t~e ground from the radioactive decay of radium (from the decay of uranium and thorium) and emitted into the air. Because of the use of lime and gypsum (which would contain radium) in its production, building materials such as cinder block, sheet rock, and concrete are also radon gas sources. Concentrations of radon gas are dependent on the concentrations of radium (uranium and thorium) in the soil, altitude, soil permeability, temperature, pressure, soil moisture, rainfall, snow cover, atmospheric conditions, and season. The gas can move' through cracks and openings into basements of buildings, become trapped 'in a small air volume indoors and result in higher concentrations than found outdoors. Radon can also be. dissolved in well water and contribute to airborne radon in houses when released through showers or washing.

ince radon gas is radioactive, it, too, continues to produce, by ecay, other radioactive materials referred to as radon daughters.

These daughters are solid particles which can stick to surf aces such as dust particles in the air. The dust containing the radon daughter particles can be inhaled and deposited in the lungs.

Radon daughters emit high energy alpha particles which results in an average dose to the lungs of 300 mrem (0.3 rem to a 10 year old) in the United States. In areas such as New Jersey and Pennsylvania, over a geological formation known as the Reading Prong, doses much higher than 300 mrem/yr have been recorded due to natural deposits of uranium. The average dose rate for radon

_is considered to be 200 mrem/yr. 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 rinking water and radioactive potassium in-milk. Sources of '

aturally-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 (mrem/yearl Manmade Sources (mrem/yearl Cosmic Rays 42 Medical radiation 90 Building Materials 35 Television and Internal 28 consumer products 1-5 Ground 11 Weapons Fallout 2-5 Radon 200 Nuclear Power Plants 1 APPROXIMATE TOTAL 300 100

Reference:

NUREG-0558, EPA Report ORP/SID 72-1 and Nuclear Energy Overview 3/27/95.

The average individual in the United States receives approximately 300 mrem per year from natural sources. In ~ome areas the dose from natural radiation is significantly higher. Residents of Colorado receive an additional 80 mrem per year due to the increase in cosmic (higher elevation) and terrestrial radiation levels. Transcontinental and intercontinental airline pilots receive 1000 mrem/yr due to the high elevation and length of these flights and resultant higher cosmic radiation levels. In several locations around the world high concentrations of mineral 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 surf ace by rain or snow and is dispersed throughout the environment. The radionuclides found in fallout which produce most of the fallout radiation exposures to man are I-131, Sr-89, Sr-90, and Cs-137. There have been no atmospheric weapons tests

• in this country since 1964.

6

NUCLEAR POWER REACTORS

• 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 f heat. When one fission occurs more neutrons are given off hich 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  :;1 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 ma]or 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 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" thick steel reactor vessel about 75 feet high and weighing 624 tons.

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

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

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

5. The shaft spins inside a 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 16cated 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

___J

IGURE 1 BWR VESSEL & CORE STEAM LINE (TO TURBINE)

~/

FEEDWATER FEEDWATER (FROM *CONDENSER) LL-L-'-~ (FROM CONDENSER)

JET PU;MP RECIRCULATION WATER RECIRCULATION PUMP PUMP

\

l ' ~ !

FIGURE 2 SCHEMATIC :OF BWR POWER PLANT

)

DRYWELL (PRIMARY CONTAINMENT)

~

l SHIELD BUILDING

...... STEAM~ GENERATOR 0

REACTOR.--~,,-~~-,--,,-~~~~~-?'

VESSEL COOLING TURBINE TOWER t-WATER RECIRC PUMP ~*===~

~

PRESSURE SUPPRESSION POOL COOLING WATER (TORUS) (RIVER)

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

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

The following outline indicates how *the PWR works (see Figure 3):

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

2. The water flows along the fuel rods. When the 53 control rods are raised, the fissioning process begins and the water is heated to about 600°F by the nuclear fission proc~ss.

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 call~d 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

...... .*REACTOR STEAM N PRIMARY GENER- TURBINE GENERATOR REACTOR *:COOLANT ATOR SYSTEM

~*

. , ...... J

!"'../

\. CONDENSER

.-~*-*-*~- *---i REACTOR COOLANT V*

PUMP WATER (CONDENSATE)

COOLING WATER (RIVER)

CONTAINMENT OF RADIOACTIVITY

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

There are a series of several barriers to contain_ the radioactivity present in a light water reactor. The first of these is the nuclear fuel itself. The fission products are trapped inside the ceramic fuel pellets that are designed to retain them. Th~ 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 withstand tornadoes, floods, and earthquakes.

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

• 13

FIGURE 4 PIUMARY PWR CONTAINMENT CROSS-SECTION (SALEM UNITS 1 le 2)

POW GAHTIY CRANE CONCllETE 4'-il' 191' 6" FAN FAN COIL COIL mm 100T GROUND GROUND LEVEL LEVEL ACCUMIJLATOR

- - - - - - - - - - - . 156'6" 14

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

DRY --l

-+----+-+-+-

REACTOR WELL VES SEL RECIRC PUMP

• PRESSURE SUPPRESSION POOL 15

SOURCES OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS Under normal operating conditions for nuclear power plants most o f .

the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products are able to diffuse or migrate through the fuel cladding and into the primary coolant. Trace quantities of the component and structure surfaces, which have been activated, also get into the primary coolant water. Many of the soluble fission and activation products, such as radioactive iodines, strontiums, cobalts, and cesiums are removed by demineralizers in the purification system of the primary coolant. The noble gas fission products have a very low solubility in the primary coolant and therefore cannot be removed by the demineralizers.

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

Small releases of radioactive liquids from valves, piping, or equipment associated with the primary coolant system may occur in the reactor, auxiliary, and fuel handling buildings. The noble gases become part of the gaseous wastes, while the remaining radioactive liquids are collected in floor and equipment drains and sumps and are processed prior to release. Processed primary co.olant- water that does meet chemical specificat~on~ for reuse m a y .

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. All concentrates produced from the demineral-izers are packaged as solid waste for shipment and burial at an offsite burial facility.

16

At Salem, the circulating water system provides an additional minimum of 100,000 gallons per minute dilution flow for liquid releases. At Hope Creek, the cooling tower provides an additional 12,000 gallons per minute dilution flow prior to discharge to the Delaware River. The average flow rate of the Delaware River is five million gallons per minute and provides additional dilution.

In SGS, the waste gases collected by the vent header system are first routed to the gas compressors which compress the gases into waste gas decay tanks. After a waste gas decay tank is filled, the tank contents may be stored for a period up to 90 days (generally) to allow for decay of the shorter-lived radionuclides.

In HCGS, the waste gases from the main condenser air ejectors are collected and delayed from release in the offgas system. The discharge of all waste gases at HCGS and SGS is made through high efficiency particulate air (HEPA) filters and charcoal filters prior to release. The filters are rated to be 95% efficient for iodines and greater thanr99% efficient for removal of particulates. Noble gases, however, cannot be removed by these filters. Gaseous effluents are discharged through elevated vents which enhances atmospheric dispersion and dilution.

Radioactive effluent releases are limited and controlled by release concentrations and dose limits, per Technical Specifications and the U.S. Nuclear Regulatory Commission's regulation in Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20) . These regulations are based on recommendations of the International 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 Lower Alloways Creek Township, Salem County, New Jersey 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) .

Salem and Hope Creek Generating Stations (SGS/HCGS) are located on a man-made peninsula on the east bank of the Delaware River. It was created by the deposition of hydraulic fill from dredging operations. The environment surrounding SGS/HCGS 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 Reports for SGS and HCGS [9,10].

Since 1968, an off-site Radiological Environmental Monitoring

• Program (REMP) has been conducted at the SGS/HCGS Site. Starting December, 1972, more extensive radiological monitoring programs we~

initiated. The operational REMP was initiat~d in December, 1976, when Salem Unit 1 achieved criticality. The PSE&G Maplewood Testing Services (MTS), has been involved in the REMP since its inception.

The MTS is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary-laboratory were also analyzed by the MTS.

From January, 1973, through June, 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of all samples under the SGS/HCGS REMP and the annual reporting of results.

RMC reports for the preoperational and operational phase of the program are referenced in this report [1-3]. On July 1, 1983, the MTS assumed primary responsibility for the analysis of all samples (except TLDs) and the reporting of results. Teledyne Brown Engineering Environmental Services (TBE), Westwood, NJ, at that time, took ove~ responsibility for third-party QA analyses and TLDs.

An additional vendor, Controls for Environmental Pollution Inc., had been retained to provide third-party QA analyses and certain non-routine analyses from May 1988 up until June 1, 1992. At this time, Yankee Atomic Electric Laboratory (YAEL) and Thermo Nutech are our QA vendors. MTS reports for the operational phase from 1983 to 1994 are referenced in this report [4] .

18

An overview of the 1995 Program is provided in Table 2.

'Radioanalytical data from samples collected under this program were compared with results from the preoperational phase. Differences

• between these periods were examined statistically, where applicable, to determine the effects, if any, of station operations. This report summarizes the results from January 1 through December 31, 1995, for the SGS/HCGS Radiological Environmental Monitoring Program.

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

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

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

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

• To detect any change in ambient gamma radiation levels.

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

This report, as required by Section 6.9.1.7 of the Salem Technical Specifications, and Section 6.9.1.6 of the Hope Creek Technical Specifications, summarizes the findings of the 1995 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the SGS/HCGS have been summarized for purposes of comparison with subsequent operational reports [2] .

In order to meet the stated objectives, an appropriate operational REMP was developed. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The selection of sample types was based on: (1),

established critical pathways for the transfer of radionuclides through the environment to man, and, (2), experience gained during the preoperational phase. Sampling locations were determined from site meteorology, Delaware estuarine hydrology, local demography, 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 1995. 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 sta~ions are indicated on maps B-1 and B-2.

DATA INTERPRETA'J;'JON Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix C. All results above the lower limit of detection (LLD) are at a confidence level of 2 sigma. This represents the range of values into whic~ 95% of repeated analyses.

of the same sample should fall. As defined in Regulatory Guide 4.

LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above.system background) that will be detected with 95% probability, with only 5% probability of falsely concluding that a blank observation represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count, or of the blank sample count, as appropriate.

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

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

20

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

QUALITY ASSURANCE PROGRAM The PSE&G Maplewood Testing Services (MTS), 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 MTS 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 th~ MTS includes the quality control of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is -1 implemented through participation in the USEPA Laboratory Intercomparison Studies Program. These results are listed in Tables E-"l through E-5 in Appendix E .*

PROGRAM CHANGES Location 2F2 Air Sampling Station was relocated from the roof-top at the Salem Laboratory Annex, in the town of Salem, to the Southern Training Center (behind the building and below the microwave tower)

This location is 1.4 miles closer to the site. The reason for relocation was cancellation of a long term lease with Atlantic Electric Company.

RESULTS AND DISCUSSION The analytical results of the 1995 REMP samples are divided into categories based on exposure pathways: -atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1995 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 SGS/HCGS* Site has historically included samples and analyses not specifically required by the Stations Technical Specifications. PSE&G continues to collect and analyze these amples in order to maintain personnel proficiency in performing hese non-routine analyses. These analyses are referenced throughout the report as Management Audit samples. The summary tables in this report include these additional samples and analyses.

21

---

E::~**; ---------

ATMOSPHERIC Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected

• from the air by adsorption on triethylenediamine (TEDA) impregnate 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.

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

Air particulate samples were collected at six locations. Each of the 317 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 1995 was 98.5 percent.

• Gross alpha activity was detected in 252 of the indicator station samples at concentrations ranging from 0.9 x 10- 3 to 3 3 7.4 x 10- pCi/m Gross alpha activity was detected in 50 control station samples at levels ranging from 1.0 x 10- 3 to 3 3 3

4. 2 x 10- pCi/m

• The grand average was 2. 4 X 10-

• The 3 3 maximum preoperational level detected was 7.8 x 10- pCi/m 3 3 with an average of 1.1 x 10- pCi/m *

• Gross beta activity was detected in 261 of the indicator station samples at concentrations ranging from 6 x 10- to 3 3 73 x 10- pCi/m and in 52 control station samples from 3

9 x 10- 3 to 37 x 10- pCi/m3

• The average for both indicator and control station samples was 22 x 10- pCiLm3

• The maximum preoperational level detected was 920 x 10- 3 3

3 3 3 pCi/m3 , with an average of 74 x 10- pCi/m *

• Gamma spectrometric analysis performed on each of the 24 quarterly composite samples analyzed, indicated the presence of the naturally-occurring radionuclides Be-7, K-40, Radium, and Th-232. 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 all twenty indicator station composites that were analyzed, at concentrations ranging 3 3 from 32 x 10- to 87 x 10- pCi/m , with an average of 3 3 63 x 10- pCi/m

• It was detected in the four control 3 3 station composites from 42 x 10- to 70 x 10- pCi/m3 , with 3 3 an average of 62 x 10- pCi/m

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

. x 10- pCi/m

• 0 Potassium-40 activity was detected in seven of the indicator station samples with an average of 15 x 10- 3 pCi/m3

• 22

K-40 was also detected in one control station sample at a concentration of 17 x 10- 3 pCi/m3

• No

• 0 preoperational data is available for comparison.

Radium was detected in five indicator station samples at concentrations of O. 7 x 10- 3 to 1. 7 x 10- 3 3

pCi/m and in two of the control station samples at 3 3 3

1. 3 x 10- and 1. 5 x.10- pCi/m -No preoperational data is available for comparison.

0 Thorium-232 activity was detected in two of the indicator 3 3 samples at an average 1. 7 x.10- pCi/m There was no Th-232 detected in any of the control locations. No preoperational data is available.

• 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.

0 Strontium-89 was not detected in any of the indicator or the control composites analyzed. LLD sensitivities for both the indicator and control station samples ranged from <0.1 x 3 3 3 10- to < 0. 2 x 10- pCi/m

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

• 0 Strontium-90 was not detected in any of the indicator or control station composites analyzed. LLD sensitivities for both the indicator and control station samples were all

<0.2 x io- pCi/m

• The maximum preoperational level 3 3 3 3 detected was 3. 0 x 10- pCi/m

• Air Iodine (Table C-4)

Iodine in filtered air samples was collected at six locations. Each of the 317 weekly samples collected was analyzed for I-131.

• Iodine-131 was not detected in any of the 317 weekly samples analyzed. LLD sensitivities for all the stations, both 3

indicator and control; ranged from <1.1 x 10- to <16 x 10- 3 3 3 pCi/m

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

• DIRECT RADIATION Ambient radiation levels in the environs were measured with energy-compensated CaS0 4 (Tl) thermoluminescent dosimeters (TLDs) supplied and read by YAEL. Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances. Additional Annual TLD's supplied and read by TMA/Eberline were co-located with the quarterly TLD's as a omparison. These results are included in Table C-5.

23

Direct Radiation (Tables C-5, C-6)

A total of 43 locations were monitored for direct radiation d u r i n g .

1995, including 6 on-site locations, 31 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 16 quarterly measurements were taken at schools and population centers, with 3 additional controls .beyond the 10 mile zone in

. Delaware.

• Five 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 10CFR20.1004.

0 The average dose rate for the 15 monthly off-site indicator TLDs was 3.7 millirads per standard month, and the corresponding average control dose rate was 4.0 millirads per standard month. The preoperational average monthly TLD readings was 4.6 millirads per standard month.

0 The average dose rate for the 31 quarterly off-site indicator TLDs was 4.4 millirads per standard month, and the average control rate was 4.6 millirads per standard month.

The preoperational average quarterly TLD readings was 4.4 millirads per standard month.

In Figure 7, the quarterly average radiation levels of the offsite indicator stations versus the control stations, are plotted for the year period from 1974 through 1995.

TERRESTRIAL

/

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

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

Separate raw and treated potable water samples were composited daily by personnel of the City of Salem water treatment plant. All samples were collected in new polyethylene containers.

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

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 ~elts and gutted. The carcasses are packed in plastic bags and kept chilled in ice chests during transport.

24

Milk (Tables C-7, C-8)

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 <0.7 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.

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

0 Potassium-40 was detected in all 80 samples. Concentrations for the 60 indicator station* samples ranged from 1200 to 1500 pCi/L, with an average of 1300 pCi/L. The 20 control station sample concentrations ranged from 1100 to 1400 pCi/L, with an average of 1300 pCi/L. The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.

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

0 Strontium-89 was not detected in any of the three indicator samples analyzed nor in the control station sample. LLD sensitivities for both the indicator and the control station samples ranged from <0.9 to <1.0 pCi/L. The maximum preoperational level detected was 14 pCi/L.

0 Strontium~90 was detected in two of the three indicator samples analyzed. Average concentrations for the indicator station samples was 1.2 pCi/L. There was no Sr-90 detected in the control station sample. The maximum preoperational level detected was 12 pCi/L, with an average of 3.5 pCi/L.

The presence of Sr-90 in the samples can be attributed to fallout from previous nuclear weapons testing.

Well Water (Ground Water) (Tables C-9, C-10, C-11) lthough wells in the vicinity of the Salem and Hope Creek enerating Station are not directly affected by plant operations, water samples were collected monthly from one well during January through December of the year.

25

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

• analyzed for Sr-89 and Sr-90.

• Gross alpha activity was detected in all twelve of the well samples at concentrations ranging from 1.3 to 3.4 pCi/L. The maximum preoperational level detected was 9.6 pCi/L. There was no preoperational average determined for this analyses.

• Gross beta activity w~s detected in all twelve well samples.

Concentrations for the samples ranged from 9.5 to 137 pCi/L, with an average of 10 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 twelve samples. Concentrations for samples ranged from 8.4 to 13 pCi/L, with an average of 9.4 pCi/L. The maximum preoperational.level detected was 19 pCi/L, with an average of 7.8 pCi/L.

• Tritium activity was not detected in any of twelve well water samples. The LLD sensitivities ranged from <110 to <170 pCi/L.

The maximum preoperational level detected was 380 pCi/L. -

• Gamma spectrometric analysis performed on each of the twelve well water samples indicated the presence of the naturally-occurring radionuclides K-40 and Radium. All other gamma

• emitters searched for were below-the Lower Limit of Detection 0 Radium was detected in all twelve of the well samples at

• concentrations ranging* from 28 to 247 pCi/L with an average of 114 pCi/L. The maximum preoperational level detected was 2.0 pCi/L.

These values are similar to those found in the past few years. However, as with the 1989 through 1994 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.

0 Potassium-40 was detected in one of the samples with a concentration of 67 pCi/L. The maximum preoperational level detected was 30 pCi/L.

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

0 Strontium-89 was not detected in any of the four well water composites.

26

LLD sensitivities for the samples ranged from <0.5 to <0.6 pCi/L. The maximum preoperational level detected was <2.1

• 0 pCi/L.

Strontium-90 was not detected in any of the four well water composites. LLD sensitivities for all the samples were <0.4 pCi/L.

pCi/L.

The maximum preoperational level detected was 0.87

• Iodine-131 was not detected in any of the twelve well water samples. LLD sensitivities for all the samples ranged from

<0.Z to <0.3 pCi/L.

Potable Water (Drinking Water) (Tables C-12, C-13, C-14)

Both raw and treated potable water samples were collected from the Salem water treatment plant. Each consisted of daily aliquots composited into a monthly sample. The raw water source for this plant i's 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 eleven raw water samples at concentrations of 0.6 to 1.8 pCi/L and in eight treated water samples at 0.7 to 1.5 pCi/L. The averages for both raw .

and treated water samples was 1.0 pCi/L.

operational le~~l detected was 2.7 pCi/L.

The maximum pre-Gross beta activity was detected in all 24 samples at concentrations ranging from 1.9 to 4.4 pCi/L for both the raw and treated water. The average concentration for both raw and treated was 3.0 pCi/L. The maximum preoperational level detected was 9.0 pCi/L, with an average of 4.2 pCi/L.

• Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples at concentrations ranging from l.2 to 2.8 pCi/L for the raw water and from 1.2 to 2.7 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.

• 'Tritium activity was only detected in . one

. . raw

. \ water sample at a concentration of 120 pCi/L. LLD sensi t.1 vi ties for the remaining 23 samples ranged from <120 to <130 pCi/L. The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.

• Iodine-131 measurements to a sensitivity of 1.0 pCi/L were performed. Since the receiving water body (Delaware River) is brackish, the water is not used for human consump~ion.

Drinking water supplies are not affected by discharges from the site. Iodine*-131 measurements for all 24 samples were below

-the LLD sensitivities. The LLD sensitivities ranged from <0.2 to <l. 0 pCi/L.

27

• Gamma spectrometric analysis performed on each of the 24 monthly water samples indicated the presence of the naturally-.

occurring radionuclides K-40 and Radium. All other gamma emitters searched for were below the Lower Limit of Detection.

0 The radionuclide K-40 was detected in five of the raw potable water and five treated samples at a concentration ranging from 26 to 69 pCi/L. Since gamma analyses do not require the water samples to be concentrated down to a volume. of lOOmL, K-40 results, obtained through gamma analyses, are not as sensitive as the results obtained from atomic absorption. There was no preoperational data available for comparison.

0 Radium was detected in six potable raw and in five treated samples at a range of 4.5 to 13 pCi/L. LLD sensitivities for both raw and treated waters ranged from <2.1 to <7.9 pCi/L. The maximum preoperational level detected was 1.4 pCi/L.

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

0 Strontium-89 was not detected in any of the four raw or

. treated water composites. LLD sensitivities for both the raw and treated water sample composites ranged from <0.5 to

<0.7 pCi/L. The maximum preoperational level detected was 1.1 pCi/L.

0 Strontium-90 was not detected in any of the four raw or treated water sample composites. LLD sensitivities for both the raw and treated water sample composites ranged from <0.4 to <0.5 pCi/L. The maximum preoperational level detected was 2.1 pCi/L.

Vegetables (Table C-15)

Although vegetables in the region are not irrigated with water into which liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled at

• three indicator stations (10 samples) and two 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.

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

0 Potassium-40 was detected in all eighteen samples.

• Concentrations for the ten indicator station samples range from 1720 to 3160 pCi/kg-wet and averaged 2~90 pCi/kg-wet.

28

Concentra~ions for the eight control station samples ranged from 1730 to 2800 pCi/kg-wet, and averaged 2220 pCi/kg-wet.

The average concentration detected for all samples, both

• indicator and control, was 2370 pCi/kg-wet. The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2140 pCi/kg-wet.

Game (Table C-16)

)

Although not required by the SGS or HCGS Technical Specifications, samples of muskrats, inhabiting the marshlands surrounding the site, are collected. This game is consumed by local residents. rhe samples, when available, are collected from two locations once a year as management audit samples and analyzed for gamma emitters.

Samples from two locations were collected during the month of February to satisfy this requirement. *

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

other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in the indicator station sample at a concentration of 3010 pCi/kg-wet and the control station sample at 2630 pCi/kg-wet. The average for both muskrat samples was 2710 pCi/kg-wet. The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4400 pCi/kg-wet.

BEEF (Table C-16)

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.

0 Potassium-40 was*detected in the one beef sample at a concentration of 2490 pCi/kg-wet. The maximum pre-operational level detected was 4800 pCi/kg-wet.

Fodder Crops (Table C-17)

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

29

- All of the locations from which samples were collected this year are milk sampling stations. Samples collected for wet gamma analysis included silage and soybeans.

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

0 Radium was detected in two of the indicator station samples at concentrations of 31 and 40 pCi/kg-wet, but it was not detected in any of the control station samples. LLD sensitivities for the remaining six indicator and control station samples ranged from <3.1 to <24 pCi/kg-wet. No pre-operational data is available for comparisons.

0 Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in two of the three indicator silage samples at concentrations ranging from 770 to 910 pCi/kg-wet, with an average of 840 pCi/kg-wet. It was detected in the control station silage sample at 620 pCi/kg.-

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

Be-7 was not detected in any of the indicator or control station soybean sampl_es. LLD sensitivities for* the sqybean samples ranged from <27 to <29 pCi/kg-wet. The maximum preoperational level detected for soybean samples was 9 3 0 0 .

pCi/kg-dry.

0 Potassium-40 was detected in all eight samples. Con-centrations for the six indicator station samples ranged from 5060 to 14500 pCi/kg-wet and for the two control station samples from 5900 to 13300 pCi/kg-wet .. The average concentration detected for the silage samples was 5170 pCi/kg-wet which was comparable to preoperational results which averaged 7000 pci/kg-wet. Although the Maplewood Testing Services no longer reports results based upon the dry weight of the sample, soybean results were comparable to preoperational studies. Results averaged 11700 pCi/kg-wet which was comparable to preoperational results of 22000 pCi/kg-dry.

SOIL (Table C-18)

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

• Strontium-90 was detected eight of the indicator station

• samples in concentrations ranging from 35 to 63 Pci/kg~dry,

• and in the control station sample at 63 pCi/kg-dry. The average for the indicator stations was 43 pCi/kg-dry.

30

The maximum preoperational level detected was 1100 pCi/kg-dry, with an average of 260 pCi/kg-dry .

• • Gamma spectrometry of these samples showed detectable 0

concentrations of the naturally-occuring radionuclides K-40, Th-232 and Radium, and the fission product Cs-137.

Potassium-40 was detected in all nine of the indicator station samples ranging from 4750 to 14~00 pCi/kg-dry, with an average of 9840 pCi/kg-dry. The control station sample-was 8670 pCi/kg-dry. The maximum preoperational level detected was 24000 pCi/kg-dry with an average of lOQOO pCi/kg-dry.

0 Cesium-137 was detected in all nine of the indicator station samples ranging from 58 to 1670 pCi/kg-dry, and had an average of 410 pCi/kg-dry. The control station sample showed a concentration of 179 pCi/kg-dry. The maximum preoperational level detected was 2800 pCi/kg-dry with an average of 800 pCi/kg-dry.

0 Radium was detected in all nine of the indicator station samples in ranges of 478 to 1290 pCi/kg-dry, and had ah average of 900 pCi/kg-dry. The control location showed a concentration of 930 pCi/kg-dry. The maximum preoperational level detected was 1500 pCi/kg-dry and an average of 870 pCi/kg-dry .

• 0 Thorium-232 was detected in all nine of the indicator station samples in ranges of 438 to 1270 pCi/kg-dry, and had an average of 890 pCi/kg-dry. The control station sample showed a concentration of 869 pCi/kg-dry. The maximum preoperational level detected was 1400 pCi/kg-dry with an average of 740 pCi/kg-dry.

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

polyethylene containers and frozen before being transported in ice chests.

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

Surface Water (Tables C-19, C-20, C-21, C-22) urf ace water samples were collected monthly at four indicator tations and one control station in the Delaware estuary.

31

One location is at the outfall area (which is the area where liquid radioactive effluents from the Salem Station are allowed to be dis.charged into the Delaware River), another is downstream from t h e .

outfall area, and another is dir.ectly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are 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 anaiyzed monthly for gross alpha, gross beta, and gamma -emitters.

Quarterly composites were analyzed for tritium.

• Gross alpha activity was detected in 9 samples from the 48 indicator stations at concentrations ranging from 1.6 to 3.4 pCi/L and in 3 control station samples at 1.5 to 2.8 pCi/L.

The maximum preoperational level detected was 27 pCi/L.

• Gross beta activity was detected in all 48 of the indicator station samples ranging from 14 to 184 pCi/L, with an average

• of 71 pCi/L. Beta activity was detected in all 12 of the control station samples with concentrations ranging from 26 to 121 pCi/L, with an average of 66 pCi/L. The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L.

• Tritium activity was detected in six samples from the sixteen indicator station composites at concentrations from 120 to 490 pCi/L, with an average of 195 pCi/L. There was no tritium detected in any of the four control station composites. LLD sensitivities for the remaining composites, both indicator an control, ranged from <120 to <130 pCi/L. The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L.

• Gamma spectrometric analysis performed on each of the forty-eight indicator station and twelve control station surface water samples indicated the presence of the naturally-occurring radionuclides K-40, Th-232 and Radium. All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in 43 samples from the indicator station samples* at concentrations ranging from 38 to 218 pCi/L and in 11 of the control station samples ranging from 33 to"130 pCi/L. The average for the indicator station locations was 90 pCi/L, while the average for the control station locations was 75 pCi/L. The maximum preoperational level detected was 200 pCi/L, with art average of 48 pCi/L.

0 Radium was detected in 12 samples out of the 48 indicator stations with ranges from 4.3 to 8.7 pCi/L, and an average concentration of 6.4 pCi/L. It was detected in 6 of the control station samples ranging from 4.3 to 8 pCi/L and an average concentration of 6.3 pCi/L. The maximum preoperational level detected was 4~0 pCi/L.

32

0 Thorium-232 was detected in nine indicator station samples at a range of 8.4 to 9.8 pCi/L and an average concentration

• of 9 pCi/L. Control station were all Lower Limit of Detection. No preoperational data available.

Fish (Table C-23)

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 catfish, weakfish, white perch and striped bass.

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the four samples from the two indicator stations and the two samples from the control station as management audit analyses. Tritium activity was not detected in any of the indicator or control station samples.

LLD sensitivities for these station samples ranged from <820 to

<1600 pCi/kg-wet.

• Gamma spectrometric analysis performed on each of the four indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclide K-40 and Radium, and the nuclide Cs-137. All other gamma emitters searched for were below the Lower Limit of Detection.

0 Potassium-40 was detected in all four samples from the two indicator stations at concentrations ranging from 2900 to 3520 pCi/kg-wet for an average of 3340 pCi/kg-wet. K-40 was detected in both samples from the control station samples at 2870 and 3890 pCi/kg-wet. The average for the control samples was 3380 pCi/kg-wet. The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2900 pCi/kg-wet.

0 Radium was detected in one of the four indicator station samples at a concentration of 26 pCi/kg-wet. It was not detected in either of the two control station samples. LLD sensitivities for the remaining indicator and control station samples ranged from <9 to <22 pCi/kg-wet. The maximum preoperational level detected was 130 pCi/kg-wet, with no average determined.

0 Cesium-137 was detected in two of the four indicator station samples at a range of 14 to 15 pCi/kg-wet.

It was not detected in either of the two control station samples. LLD sensitivities for the remain-ing samples ranged from <4.8 to <ll pCi/kg-wet. The maximum preoperational level detected was ll pCi/kg--

wet, with no average determined.

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

33

These are management audit analyses analyzed in recognition of the high bioaccumulation factor of strontium in bone .

0 Strontium-89 was not detected in any of the indicator or control station bone samples.

LLD sensitivities for the samples, both indicator and control, ranged from <25 to <46 pCi/kg-~ry. The maximum preoperational level detected was 100 pCi/kg-dry.

0 Strontium-90 was detected in two of the four indicator station bone samples and in one control station bone samples. Concentrations in the indicator samples were 76 and 137 pCi/kg-dry. The concentration in the control sample was 176 pCi/kg-dry. The average for all samples was 130 pCi/kg-dry. The maximum preoperational level detected was 940 pCi/kg-dry, with an average of 335 pCi/kg-dry. The presence of Sr-90 in the samples can be attributed to fallout from previous nuclear weapons testing.

0 Strontium-89 of the flesh was not detected in any of the six indicator and control station samples. LLD sensitivities for the six samples, indicator and control, ranged from <20 to <23 pCi/kg-wet. The preoperational level ranged from

<4.1 to <100 pCi/kg-wet.

0 Strontium-90 of the flesh was not detected in any of the s -

• indicator and control station samples. LLD sensitivities for the six samples, indicator and control, ranged from <l to <16 pCi/kg-wet. The maximum preoperational level detected was 67 pCi/kg-wet.

Blue Crab (Table C-24)

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

• Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator samples and two control samples as management audit analysis. No tritium activity was detected in any of the four station or control samples analyzed. LLD sensitivities for the four samples, indicator and control, ranged _between <430 to <1600 pCi/kg-wet.

The maximum preoperational level detected was 320 pCi/kg-wet.

• Gamma spectrometric analysis on the flesh of each of the two indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclides Radium and K-40. All other gamma emitters

• searched for were below the Lower Limit of Detection.

34

0 Potassium-40 was detected in both indicator station samples at concentrations of 2560 and 3070 pCi/kg-wet and in both of

• the control station samples at 2970 and 3240 pCi/kg-wet.The average for both the indicator and control station samples was. 2960 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.

0 Strontium-89 of the flesh was not detected in any of the four indicator or control samples. LLD sensitivities for these samples ranged from <20 to <27 pCi/kg-wet. The maximum preoperational level detected was <51 pCi/kg-wet.

0 Strontium-89 of the shell was not detected in any of the four samples, indicator nor control. LLD sensitivities for all the samples, indicator and control, ranged from <32 to

<42 pCi/kg-dry. The maximum preoperational level detected was 210 pCi/kg-dry.

0 Strontium-90 of the flesh was not detected in any of the four, indicator or control samples. LLD sensitivities for these station samples ranged from <17 to <19 pCi/kg-wet.

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

0 Strontium-90 of the shell was detected in both indicator station samples at 57 and 94 pCi/kg-dry and in both of the control station samples at 65 and 221 pCi/kg-dry. The average for both indicator and control station samples was 110 pCi/kg-dry. The.maximum preoperational level detected was 990 pCi/kg-dry, with an average of 614 pCi/kg-dry. The presence of Br-90 can be attributed to fallout from weapons testing or fallout from the Chernobyl accident.

Sediment (Table C-25)

Sediment samples were collected semi-annually from six locations, five indicator stations and one control station. Each of the twelve samples was analyzed for Sr-90 (management audit analysis) and gamma emitters. Although trace levels of man-made nuclides were detected in some sediment samples, these levels were expected and well within the acceptable levels specified in section 3/4.12.1 of the Technical Specirications.

• Strontium-90 was not detected in any of the ten indicator station samples nor in any of the control station samples. LLD sensitivities for these samples, both indicator and control, ranged from <16 to <20 pCi/kg-dry. The maximum preoperational level detected was 320 pCi/kg-dry.

35

• Gamma spectrometric analysis was performed on each of the ten indicator station samples and two control station samples.In addition to the detection of the naturally-occurring *

• radionuclides Radium, K-40, Be-7 and Th-232, low levels of

• Mn-54, Co-58, Co-60, Cs-134, Cs-137 and Zn-65 were also detected. The presence of these nuc1ides in the sediment samples may be attributable to radioactive liquid discharges, released within federal and state limits, from Hope Creek and Salem Generating Stations. All other gamma emitters searched for were <LLD.

0 Manganese-54 was detected in two of the ten indicator stations at concentrations ranging from 27 to 57 pCi/kg-dry.

It was not detected in either of the two control station samples. LLD sensitivities for the other ten samples, both indicator and control, ranged from <7.8 to <31 pCi/kg-dry.

No preoperational data is available for comparison.

0 Cobalt-58 was detected in two indicator station samples at concentrations ranging from 21 to 40 pCi/kg-dry. It was not detected in either of the two control station samples. The LLD sensitivities for the other ten samples, indicator and control, ranged from <8.3 to <20 pCi/kg-dry. No

• preoperational data is available for comparison.

0 Cobalt-60 was detected in four of the ten indicator stations at concentrations ranging from 37 to 112 pCi/kg-dry, with a average of 58 pC~/kg-dry. It was not detected in either o the two control stations. LLD sensitivities for the other eight samples, indicator and control, ranged from <7.2 to

<21 pCi/kg-dry. No preoperational data is available for comparison.

0 Cesium-134 was detected in three indicator station samples at concentrations ranging from 26 to 71 pCi/kg-dry, with an average of 47 pCi/kg-dry. It was not detected in either control station sample. LLD sensitivities for the other nine samples, indicator and control, ranged from <6.7 .to <15 pCi/kg-dry. No pre-operational data is available for comparison.

0 Cesium-137 was detected in six indicator station samples at concentrations ranging from 18 to 171 pCi/kg-dry. It was not detected in either control station sample. The LLD sensitivities for the other six samples, both indicator and control, ranged from <9.2 to <19 pCi/kg-dry. The maximum preoperational level detected was 400 pCi/kg-dry with an average of 150 pCi/kg-dry.

0 Zinc-65 was detected in one of the ten indicator station samples at a concentratiom of 37 pCi/kg-dry, but not in either of the control station samples. LLD sensitivities for the remaining eleven samples, both indicator and *

.control, ranged from <5. 6 to <57 pCi/kg-dry. No pre-operational data is available for comparison.

36

0 Potassium-40 was detected in all ten indicator station samples at concentrations ranging from 5030 to 17500 pCi/kg-dry, with an average of 12095 pCi/kg-dry.Concentratipns detected in both of the control station samples were at 16500 and 18300 pCi/kg-dry. *The average for both the indicator and control station samples was 13~00 pCi/kg-dry.

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

0 Radium was detected in all ten indicator station samples at concentrations ranging from 306 to 897 pCi/kg-dry, with an average of 650 pCi/kg-dry. Concentrations detected in both of the control station samples were at 614 and 675 pCi/kg-dry, with an average of 645 pCi/kg-dry. The average for both the indicator and control station samples was 650 pCi/kg-dry. The maximum preoperational level detected was 1200 pCi/kg-dry, with an average of 760 pCi/kg-dry.

0 Thorium-232 was detected in all ten indicator station samples at concentrations ranging from 287 to 1040 pCi/kg-dry, with an average of 790 pCi/kg-dry. Concentrations detected in both of the control station samples were at 820 and 911 pCi/kg-dry, with an average of 870 pCi/kg-dry. The average for both the indicator and control station. samples was 800 pCi/kg-dry. The maximum preoperational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.

0 Beryllium-7 was detected in one of the ten indicator station samples at a concentration of 507 pCi/kg-dry but not in either of the control station samples.

The LLD sensitivities for the remaining eleven samples, both indicator and control, ranged from <52 to <153 pCi/kg-dry. The maximum preoperational level detected was 2300 pCi/kg-dry .

• 37

PROGRAM DEVIATIONS

1. The following air samplers were unavailable due to electrical problems associated with the pumps:

~

STATION LOCATION HOURS UNAVAILABLE 5Sl 1.0 mi., East of Vent 312.3 (5.5%)

5Dl 3.5 mi., East of Vent 234.2 (3.0%)

To prevent reoccurrence of this problem, the air sampling pumps were replaced with newer units that run cooler and are less likely to overheat. The total availability of all air samplers used in the program was 98.5%.

2. During the period 9/30/95 - 12/28/95, two thermoluminescent dosimeters (TLD's) were unavailable. The dosimeter at location 2F2 (8.7 mi., NNE of Vent) was vandalized and the dosimeter at location 2F5 (7.4 mi., NNE of Vent) was damaged by construction equipment working at the location. Both dosimeters were damaged beyond repair.

To prevent reoccurrence of this problem, the TLD holders at all locations were replaced with waterproof, neutral colored plastic bags. The replacement was necessary to make the TLD's less visible and less prone to damage from construction equipment o vandalism..

• CONCLUSIONS The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted during 1995 in accordance with the SGS and HCGS Technical Specifications. The Lower Limit of Detection (LLD) values required by the Technical Specifications were achieved for this reporting period. The objectives of the program were also met during this period. The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in

. compliance with Technical Specifications.

From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for* an estuarine environment. No unusual radiological characteristics were observed in the environs of Salem and Hope Creek Generating Stations during this reporting period. Since these results were comparable to the results obtained during the preoperational phase of the program which ran from 1973 to 1976, we can conclude that the operation. of SGS Units One and Two and HCGS had no significan~_impact on the radiological characteristics of th environs of that area.

38

2 SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENYIRONMENT

a. Air Particulate SSl SD1 16E1 1F1 3H3 Weekly Gross alpha/weekly 2F2 Gross beta/weekly 8r-89 & 8r-90/first quarter**

Gamma scan/quarterly

b. Air Iodine 581 5Dl 16El lFl 3H3 Weekly Iodine-131/weekly 2F2 II. DIRECT RADIATION

a. Thermoluminescent 282 SD1 2E1 1F1 3Gl Monthly Gamma dose/monthly Dosimeters 581 lODl 3El 2F2 3Hl 682 14Dl 13E1 2F6 3H3 781 16El 5Fl 6Fl ?Fl 1081 llFl 13F4

b. Thermoluminescent 282 5Dl 2El lFl 3Gl Quarterly Gamma dose/quarterly Dosimeters 581 lODl 3El 2F2 3Hl 682 14Dl 13El 2F6 3H3 781 16El 5Fl 6Fl lGl 1081 7F1 11F1 13F4 10Gl 4D2 9El 2F5 3F2 16Gl 11E2 15Dl 12El 3F3 4F2 10F2 12Fl 13F2 13F3 14F2 15F3 16F2

TABLE 2 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS III. Terrestrial Environment

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

Semi-monthly Iodine-131/semi-monthly (when animals Gamma scan/semi-monthly are on Sr-89 & Sr-90/July, first pasture) collection

b. Well Water 3El Monthly Gross alpha/monthly Gross beta/monthly Potassium-40/monthly

• Tri ti um/monthly Gamma scan/monthly Sr-89 & Sr-90/quarterly

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

d. Vegetables 3El 2F4 3F4 lGl Annually Gamma scan/on collection 4F3 (at harvest)

• TABLE SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

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

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

g. Fodder Crops 2F7 11F3 14F4 3Gl Annually Gamma scan/on collection 6Sl lODl 16El lFl 3Gl Collect from Sr-90/on collection

h. Soil 2F4 2F7 5Fl 11F3 14F4 each location Gamma scan/on collection

• once every th;r-ee years IV. AQUATIC ENVIRONMENT

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

TABLE 2 (cont 'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS

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

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

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

Gamma scan (flesh)/on collection

c. Blue Crabs llAl 16Fl 12Cl Semi- Tritium (flesh) annually Aqueous fraction/on collection**

Sr-89 & Sr-90 (flesh)/on collec~ion Sr-89 & Sr-90 (shell)/on collection Gamma scan (flesh)/on collection

d. Sediment llAl 7El 16Fl 12Cl Semi- Sr-90/on collection lSAl annually Gamma scan/on collection 1:6Al

• 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 specific commitments to local officials.

• FIGURE 6 BETA IN AIR PARTICULATE 1973 THROUGH 1995 1000 .--~------~~~----------------------~--~------~-----

Weapons Test 06-17-74 Weapons Test Weapons Test i L~ .

09-29-76 09-17-77 Chernobyl 04-26-86 100 i

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FIGURE 7 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1973 THROUGH 1995 10 Weapons Test Weapons Test 06-17-74 09-17-77 OFF-SITE STATIONS 8 Weapons Test Weapons Test CONTROL STATIONS 0~~7] -.-----

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FIGURE 8 IODINE-131 ACTIVITY IN *MILK

• 1973 THROUGH 1995

..._weapons Test 09-26-76 10 .......................... ;. **************************************************************************************************************************************************

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FIGURE 9 GROSS BETA & K-40 ACTIVITIY IN SURFACE WATER 1973 THROUGH 1995 -

GROSS BETA Weapons Test Weapons Test 06-17-7 09-17-77 Chernobyl

est I weal""" Test 04-28-86 K-40 100 .

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• FIGURE 10 TRITIUM ACTIVITY IN SURFACE WATER 1973 THROUGH 1995 10,000 .--------~~--~--------~------------------------------~

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. 1,000 WeaJ>ons Test 06-17-74 Weapons Test 09-17-77 D+2T Wea~BTm 09-26-76 I

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FIGURE 11A CESIUM -137 IN WATER SEDIMENT 1977 THROUGH 1995 Wea ons Test 1000 09-1 -77 Chernobyl 200 04-26-86

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

FIGURE 118 COBALT- 60 IN WATER SEDIMENT 1977 THROUGH 1995 Weapons Test

~1-n 1000 Chernobyl 04-26-86

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

FIGURE 12 CONCENTRATIONS OF Sr-90 AND Cs-137 IN SOIL

.1974 THROUGH 1995 Sr-90 Cs-137 1000

--~-------------~--------------------

Ln 0

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Weapons Test 09-29-76 J

1974 1977 1983 1986 1989 1992 1995 IYEARLY AVERAGE I

REFERENCES

[1] 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's Maplewood Testing Services. "Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program - Annual Reports 1983 through 1994".

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

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

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.

[11] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 1 - Technical Specifications", Appendix A to Operating License No.

DPR-70, 1976, Sections 3/4.12 and 6.9.1.10 (Amendment 59 et~).

[12] Public Service Electric a:nd 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).

[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.

51

REFERENCES (cont'd).

[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 Section Quality Assurance Plan." August, 1994.

[18] PSE&G Research and Testing Laboratory. "Environmental and Chemical Services Division Procedures Manual." September, 1994.

[19] Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, SGS _RERR-36 and RERR-37 -.Salem Generating Station. 1995.

[20] Public Service Electric and Gas Company. "Radioactive Effluent Release Reports, HCGS RERR-17 and RERR Hope Creek Generating Station. 1995.

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

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

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

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

52

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• RADIOLOGICAL ENVIRONMENTAL SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY RING PROGRAM DOCKET 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower Alf Indicator Locations Location with Highest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements I.AIRBORNE Air Particulat~s Alpha 317 1.0 2.5 (252 /265 ) 2F6 7.3 mi NNE 2.7 (51 /53) 2.3 (50 /52) 0 (10., pCi/m") (0.9-7.4) (0.9-5.9) (1-4.2)

Beta 317 6.0 22 (2611265) 1F1 5.8 mi N 24 (52 /53) 22 (52152) 0 (6-73) (8-73) (9-37)

Sr89 6 0.5 LLD <LLD <LLD 0 Sr90 6 0.5 LLD <LLD <LLD 0 vi lJ1 Gamma Be7 24 6.8 63 (20/20) 2F6 7.3 mi NNE; 68 (414) 62 (414) 0 (32-87) (46-87) (42-70)

K-40 24 0.3 15 (7 /20) 2F6 7 .3 mi NNE 19. (214) 17 (1/4) 0 (5.9-21) (18-21) (17-17)

Ra-NAT 24 0.3 1.2 (5 /20) 3H3 110 mi NE .1.4 (2/4) 1.4 (2 /4) 0 (0.7-1.7) (1.3-1.5) (1.3-1.5)

Th-232 24 1.2 1.7 (2 /20) 5S11.0 mi E 1.9 (1 /4) <LLD 0 (1.6-1.9) (1.9-1.9)

Air Iodine 1-131 317 13 LLD <LLD <LLD. 0 II DIRECT Monthly 288 3.8 (251 /251 ) 7S1 0.12 mi SE 5.1 (12/12) 4 (36 /36) 0 Direct Radiation Badges (1.3-6.1) (3.8-6.1) (2.2-5.1)

(mrad/std. month)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Highest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements Direct Radiation Quarterly 180 4.4 (126 /126) 9E1 4.2 mi S 5.3 (5 /5) 4.6 (24 /24) 0 (mrad/std. month) Badges (2.2-8.'1) (4.4-8.1) (3.2-5.5) 1G3 19 mi N 5.3 (4 /4) 4.6 (24 /24) 0 (4.6-5.5) (3.2-,?.5) 14F2 6.6 mi WNW 5.3 (4 /4) 4.6 (24 /24) 0 (4.6-5.6) (3.2-5.5)

Ill TERRESTRIAL Milk 1-131 80 0.4 <LLD <LLD <LLD 0 (pCl/L)

Sr-89 4 1.0 <LLD <LLD <LLD 0 LTI CJ'\ Sr-90 4 0.9 1.2 (2 /3) 2F7 5. 7mi NNE 1.2 (1 /1 ) <LLD 0 (1.2-1.2) (1.2-1.2) 14F4 7.6 mi WNW 1.2 (1 /1 ) <LLD 0 (1.2-1.2)

Gamma K"40 80 120 1300 (60 /60 ) 2F7 5. 7mi NNE 1300 (20 /20 ) 1300 (20 /20 ) 0 (1200-1500) (1200-1400) (1100-1400) 3G117miNE 1300 (20 /20 ) 1300 (20 /20 ) 0 (1100-1400) (1100-1400) 11 F3 5.3mi SW 1300 (20 /20 ) 1300 (20 /20 ) 0 (1200-1400) (1100-1400) 14F4 7.6mi WNW 1300 (20 /20 ) 1300 (20 /20 ) 0 (1.200-1500) (1100-1400)

RA-NAT 80 6.6 11 (5 /60) 14F4 7.6mi WNW 18 (1/20) 12 (2/20) 0 (7.8-18) (18-18) (6.5-18)

(

• RADIOLOGICAL ENVIRONMENTAL SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY ING PROGRAM DOCKET 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Hi!!liest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Non routine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements Ill TERRESTRIAL Well Water Alpha 24 1.2 2.1 (12/12) 3E1 4.1 mi NE 2.1 (12/12) No Control 0 (pCi/L) (1.3-3.4) (1.3-3.4) Location Beta 24 1.0*** 10 (12 /12) 3E1 4.1 mi NE 10(12/12) No Control 0 (9.5-13) (9.5-13) Location K-40 24 1.0 9.4 (12/12) 3E1 4.1 mi NE 9.4 (12/12) No Control 0 (8.4-13) (8.4-13) Location H-3 24 150 <LLD <LLD No Control 0 Location Sr-89 8 1.0 <LLD <LLD No Control 0 l.J1 Location

'-I Sr-90 8 0.6 <LLD <LLD No Control 0 Location Gamma K-40 24 35 67 (1 /12) 3E1 4.1mi NE 67 (1 /12) No Control 0 (67-67) (67-67) Location 1-131 24 0.6 <LLD <LLD No Control 0 Location RA-NAT 24 7.4 114(12/12) 3E1 4.1mi NE 114 (12/12) No Control 0 (28-247) (28-247) Location Potable Water Alpha 24 1.0 1.1 (19 /24 ) 2F3 8.0 mi NNE 1.1 (19/24) No Control 0 (pCi/L) (0.6-1.8) (0.6-1.8) Location Beta 24 1.0*** 3 (24 /24) 2F3 8.0 mi NN~ ' 3 (24 /24) No Control 0 (1.9-4.4) (1.9-4.4) Location K-40 24 1.9 (24 /24) 2F3 8.0 mi NNE 1.9 (24 /24) No Control 0 (1.2-2.8) (1.2-2.8) Location H-3 24 150 120 (1 /24) 2F3 8.0 mi NNE 120 (1 /24) No Control ( 0 (120-120) (120-120) Location

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Hi9hest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Non routine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements Ill TERRESTRIAL Sr-89 8 1.0 LLD <LLD No Control 0 Potable Water Location (pCl/L) Sr-90 8 0.8 LLD <LLD No Control 0 Location Gamma K-40 24 35 52 (10 /24) 2F3 8.0 mi NNE 52 (10 /24) No Control 0 (26-69) (26-69) Location 1-131 24 0.6 <LLD <LLD No Control 0 Location RA-NAT 24 7.4 7 (11 /24) 2F3 8.0 mi NNE 7 (11 /24 ) No Control 0 U1 (4.5-13) (4.5-13) Location 00 Fruit & Gamma Vegetables K-40 17 70 2490 (10 /18) 2F4 6.3 mi NNE 2810 (3 /3) 2220 (8 /8) 0 (pCi/Kg-wet) (1720-3160) (2760-2840) (1730-2800)

Game Gamma (pCi/Kg-wet) K-40 2 70 3010 (1 /1 ) 3E1 4.1 mi NE 3010 (1 /1 ) 2630 (1 /1 ) 0 (3010-3010) (3010-3010) (2630-2630)

Beef Gamma (pCi/Kg-wet) K-40 70 2490 (1 /1 ) 3E1 4.1 mi NE 2490 (1 /1 ) No Control 0 (2490-2490) (2490-2490) Location

RADIOLOGICAL ENVIRONMENTAL SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY RING PROGRAM DOCKET 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1995 to DECEMBER31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Hi!lhest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name ' Mean Mean Non routine (UNIT OF MEASUREMENT '*of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements Ill TERRESTRIAL Gama Fodder Crops Be-7 8 85 840 (2 /6) 11F3 5.3 mi SW 910 (1/2) 620 (1 /2) 0 (pCi/Kg-wet) (770-910) (910-910) (620-620)

K-40 8 50 8040 (6 /6) 11F3 5.3 mi SW 10710 (2 /2) 9600 (2 /2) 0 (5060-14500) (6920-14500) (5900-13300)

RA-NAT 8 15 36 (2/6) 11F3 5.3 mi SW 40 (1 /2) <LLD 0 (31-40) (40-40)

SOIL (pCi/Kg-dry) Sr-90 10 22 43 (8 /9) 10D1 3.9 mi SSW 63 (1 /1 ) 30 (1 /1 ) 0 Ln (35-63) (63-63) (30-30)

\0 Gamma K-40 10 70 9840 (9 /9) 14F4 7.6 mi WNW 14800 (1 /1 ) 8670 (1 /1 ) 0 (4750-14800) (14800-14800) (8670-8670)

Cs-137 10 20 410 (9 /9) 1F1 5.8 mi N 1670 (1 /1 ) 179 (1 /1 ) 0 (58-1670) (1670-1670) (179-179)

RA-NAT 10 30 900 (9 /9) 11F3 5.3 mi SW 1290 (1 /1 ) 930 (1 /1 ) 0 (478-1290) (1290-1290) (930-930)

Th-232 10 30 890 (9 /9) 11 F3 5.3 mi SW 1270 (1 /1 ) 869 (1 /1 ) 0 (438-1270) (1270-1270) (869-869)'

IV AQUATIC Surface Water Alpha 60 2.0 2.3 (9 /48) 16F1 6.9 mi NNW 2.9 (3 /12) 2.3 (3 /12) 0 (pCUL) (1.6-3.4) (2.2-3.4) (1.5-2.8)

Beta 60 3.8 71 (48 /48) 7E1 4.5 mi SE 106 (12112) 66 (12 /12) 0 (14-184) . (54-184) (26-121)

H-3 60 150 195 (6 /16) 11A1 0.2 mi SW 490 (1 /4) <LLD 0 (120-490) (490-490)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Hi!i!hest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements

(

IV AQUATIC Gamma Surface Water K-40. 60 35 90 (43 /48) 7E1 4.5 mi SE 131(11/12) 75 (11 /12) 0 (pCUL) (38-218) (27-218) (33-130)

RA-NAT 60 7.4 6.4 (12 /48) 11A1 0.2miSW 7.5 (5112) 6.3 (6 /12) 0 (4.3-8.7) (6.7-8.7) (4.3-8)

Th-232 60 1.6 9 (4 /48) 16F1 6.9 mi NNW 9.8 (1 /12) <LLD 0 (8.4-9.8) (9.8-9.8)

Blue Crabs /Sr-89 4 160 <LLD <LLD <LLD 0 (pCi/kg-dry) (shells)

O"I Sr-90 4 76 (2 /2) 12C1 2.5 mi WSW 143 (2 /2) 143 (2 /2) 0 0 (shells) (57-94) (65-221) (65-221)

Blue* crabs H-3 4 100 <LLD <LLD <LLD 0 (pCi/kg-wet) (aqueous)

Sr-89 4 100 34 (1 /2) 11A1 0.2 mi SW 34 (1 /2) <LLD 0 (flesh) (34~34) (34-34)

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

Gamma K-40 .4 70 2815 (2 /2) 12C1 2.5 mi WSW 3105 (2 /2) 3105 (2 /2) 0 (2560-3070) (2970-3240) (2970-3240)

RA-NAT 4 20.0 31 (1 /2 ) 11A1 0.2 mi SW 31 (1 /2 ) (/) 0 (31-31) (31-31) (-)

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

Sr-90 6 75 106 (2 /4) 12C1 2.5 mi WSW 176 (1 /2) 176 (1 /2 ) 0 (bones) (76-137) (176-176) (176-176)

• RADIOLOGICAL ENVIRONMENTAL SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY RING PROGRAM DOCKET 50-272/-311 DOCKET NO. 50-353 JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Hi11hest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed (LLD)* Measurements IV AQUATIC H-3 6 100 <LLD <LLD <LLD 0 Edible Fish (aqueous)

(pCi/kg-wet) Sr-89 6 100 <LLD <LLD <LLD 0 (flesh)

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

Gamma 0 K-40 6 70 3340 (4 /4) 7E1 4.5 mi SE 3465 (2 /2) 3380 (2 /2)

(2900-3520) (3410-3520) (2870-3890)

Cs-137 6 18 14 (2 /4) 7E1 4.5 mi SE 15 (1 /2) <LLD O"I (14-15) (15-15)

I-' RA-NAT 6 20 26 (1 /4) 11A1 0.2 mi SW 26 (1 /2) <LLD (26-26) .. (26-26)

Sediment Sr-90 12 125 <LLD . <LLD 0 (pCi/kg-dry)

Gamma Be-7 12 90 507 (1 /10) 15A1 0.3 mi NW 507 (1 /2) <LLD 0 (507-507) (507-507)

K-40 12 28 *12095 (10 /10) 12C1 2.5miWSW 17400 (2 /2) 17400 (2 /2) 0 (5030-17500) (16500-18300) (16500-18300)

Mn54 12 28 42 (2 /10) 15A1 0.3 mi NW 57 (1 /2) <LLD 0 (27-57) (57-57)

Co-58 12 15 30 (2 /10) 15A1 0.3 mi NW 40 (1 /2) <LLD 0 (21-40) (40-40)

Co-60 12 32 58 (4 /10) 7E1 4.5 mi SE 112 (1 /2) <LLD 0 (37-112) (112-112)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION DOCKET 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1995 to DECEMBER 31, 1995 MEDIUM OR PATHWAY Analysis And Lower All Indicator Locations Location with Hi~hest Mean Control Location Number of SAMPLE Total Number Limit of Mean Name Mean Mean Nonroutine (UNIT OF MEASUREMENT of Analyses Detection (Range) Distance and Direction (Range) (Range) Reported Performed. (LLD)* Measurements IV AQUATIC Cs-134 12 22 47 (3 /10) 15A1 0.3 mi NW 71 (1 /2) <LLD 0 Sediment (26-71) (71-71)

(pCi/kg-dry) Cs-137 12 20 106 (6 /10) 15A1 0.3 mi NW 182 (2/2) <LLD 0 (18-171) (166-198)

RA-NAT 12 40 650 (10 /10) 16A1 0.7 mi NNW 680 (2 /2) 645 (2 /2) 0 (306-897) (666-700) (614-675)

Th-232 12 110 790 (10 /10) 15A1 0.3 mi NW 990 (2 /2) 870 (2 /2) 0 (287-1040) (936-1040) (820-911)

Zn-65 12 42 37 (1 11 o*) 16A1 0.7 mi NNW 37 (1 /2) <LLD 0 (37-37) (37-37)

°'

N

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

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

• • • Typical LLD values.

• APPENDIX B*

SAMPLE DESIGNATION AND LOCATIONS 63

• APPENDIX B SAMPLE DESIGNATION The PSE&G Maplewood Testing Services 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 istance 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 clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant:

s = On-site location E 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B 1-2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, ... For example, the designation SA-WWA-3El would indicate a sample in the SGS program (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 6f 4 to 5 miles off-site, (therefore, radial distance E) . The number 1 indicates that this is sampling station #1 in that particular sector .

• 65

TABLE B-1 SAMPLING LOCATIONS Specific information about the individual sampling locations are given in Table B~l. Maps B-1 and B-2 show the locations of sampling stations with respect to.the site. A Trimble Portable Global Positioning System (GPS) was used to provide the coordinates of key sampling locations.

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. SEC DEG. MIN. SEC 2S2 0.4 mi. NDE of vent 39 05.9 75 57.8 IDM 5Sl 1. 0 mi'. E of vent; site access road 39 37.5 75 - 31 - 06.9 AIOI APT I IDM 6S2 0.2 mi. ESE of vent; observation building 39 52.0 75 09.2 IDM,SOL 7Sl 0 .12 MI. SE of vent; station personnel gate (1) (1) IDM lOSl O.14 mi. SSW of vent; inlet cooling water bldg. (1) (1) IDM llSl O. 09 mi. SW of vent; service water inlet bldg. (1) (1) IDM llAl o. 2 mi. SW of vent; outfall area (1) (1) ECH,ESF,ESS,SWA 15Al 0. 3 mi. NW of vent; cooling tower blowdown (1) (1) ESS 0\. discharge line outfall 0\ 16Al 0.7 mi. NNw of vent; south storm drain discharge (1) (1) ESS line 12Cl 2.5 mi. WSW of vent; west bank of Delaware River (1) (1) ECH,ESF,ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road 39 09.1 75 31. 9 IDM,VGT 5Dl 3.5 mi. R of vent; local farm 39 23.9 75 21. 7 AIO,APT,IDM lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur (1) (1) IDM,SOL llDl 3.5 mi. SW of vent 39 52.0 75 24.4 GAM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware 39 01. 8 75 31. 7 IDM 15Dl 3.8 mi. NW of vent; Rt. 9, Augustine Beach 39 06.6 75 01. 7 IDM 2El 4.4 mi. NNE of vent; local farm 39 37.5 75 25.2 IDM 3El 4.1 mi. NE of vent; local farm 39 09.3 75 09.2 FPB,GAM,IDM,VGT,WWA 3E2 5.7 mi. NE of vent; local farm (1) (1) FPV 3E3 5.6 mi. NE of vent; local farm (1) (1) FPV 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek (1) (1) ESF,ESS,SWA 9El 4.2 mi. s of vent 39 10.2 75 44.2 IDM 11E2 5.0 mi. SW of vent; Rt. 9 (1) (1) IDM 12El 4.4 mi. WSW of vent; Thomas Landing (1) (1) IDM 13El 4.2 mi. W of vent; Diehl House Lab 39. 03.4 75 43.3 IDM 16El 4.1 mi. NNW of vent; Port Penn 39 - 30 - 46.6 75 35.8 AIOI APT I IDM I SOL lFl 5.8 mi. N of vent; Fort Elfsborg 39 - 32 - 44.2 75 05.4 AID,APT,IDM,SOL

TABLE (cont'd)

STATION CODE STATION LOCATION LATITUDINAL LONGITUDINAL SAMPLE TYPE DEG. MIN. SEC DEG. MIN. SEC 1F2 7.1 mi. N of vent; midpoint of Delaware River (1) (1) SWA 2F2 8.7 mi. NNE of vent; Salem Substation 39 38.2 75 03.9 AIO,APT,IDM 2F3 8.0 mi. NNE of vent; Salem Water Company 39 42.1 75 19.6 PWR,PWT 2F4 6.3 mi. NNE of vent; local farm 39 21. 2 75 33.8 FPV,FPL,SOL 2F5 7.4 mi. NNE of vent; Salem High School 39 32.1 75 32.1 IDM 2F6 7.3 mi. NNE of vent; Southern Training Center 39 43.1 75 49.2 AIO,APT,IDM 2F7 5.7 mi. NNE of vent; local farm 39 37.3 75 54.6 MLK,VGT,SOL 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal Bld (1) (1) IDM 3F3 8.6 mi. NE of vent; Quinton Township School (1) (1) IDM 4F2 6.0 mi. ENE of vent; Mays Lane, Harmersville 39 56.0 75 -26 - 04.8 IDM 5Fl 6.5 mi. E of vent; Canton 1 39 32.0 75 - 25 - 00.2 FPV, IDM, SOL 5F3 6.4 mi. E of vent; local farm 39 17.0 75 - 24 - 16.4 FPL 6Fl 6.4 mi. ESE of vent; Stow Neck Road 39 23.4 75 - 25 - 09.2 IDM 7F2 9.1 mi. SE of vent; Bayside, Ne~ Jersey 39 57.0 75 - 24 - 15.8 IDM 10F2 5.8 mi. SSW of vent; Rt. 9 39 02.0 75 - 34 - 09.3 IDM llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware 39 44.6 75 - 37 - 38.0 IDM 11F3 5.3 mi. SW of vent; Townsend, Delaware 39 02.9 75 - 36 - 19.1 MLK,VGT,SOL 12Fl 9.4 mi. WSW of vent; Townsend Elementary School 39 53.0 75 - 36 - 55.9 IDM 13F2 6.5 mi. W of vent; Odessa, Delaware 39 17.9 75 - 39 - 21. 3 IDM 13F3 9.3 mi. W of vent; Redding Middle School, 39 15.1 75 - 42 - 34.5 IDM Middletown, Delaware 13F4 9.8 mi. W of vent; Middletown, Delaware 39 56.9 75 59.9 IDM 14F2 6.6 mi. WNW of vent; Boyds Corner (1) (1) IDM 14F3 5.4 mi. WNW of vent; local farm (1) (1) FPV 14F4 7.6 mi. WNW of vent; local farm 39 41.1 75 - 401 - 47.2 MLK,VGT,SOL 15F3 5.4 mi. NW of vent 39 58.7 75 35.7 IDM 16Fl 6.9 mi. NNW of vent; C&D Canal 39 10.3 75 23.6 ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public School (1) (1) IDM lGl 10.3 mi. N of vent; local farm 35 25.1 75 58.4 FPV 1G3 19 mi. N of vent; N. Church St. Wilmington, Del 39 16.8 75 30.4 IDM 2Gl 12 mi. NNE of vent; Mannington Township, NJ 39 32.4 75 23.5 FPV 2G2 13.5 mi. NNE of vent; local farm 39 16.2 75 09.8 FPV 3Gl 17 mi. NE of vent; local farm 39 54.2 75 49.3 IDM,MLK,VGT,SOL lOGl 12 mi. SSW of vent; Smyrna, Delaware 39 12.8 75 - 3? - 07.0 IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport 39 46.1 75 35.3 IDM 3Hl 32 mi. NE of vent; National Park, New Jersey 39 35.0 75 05.5 IDM 3H3 110 mi. NE of vent; Maplewood Testing Services 40 24.5 74 10.0 AIO,APT,IDM 3H5 25 mi. NE of vent; local farm (1) (1) FPL,FPV (1) MTS is still in the Process of determining locations with the GPS.

MAP 8-i ON-SITE SAMPLING LOCATIONS 13 9

68

MAP B-2

,ARTTFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONFTORING PROGRAM OFF-SITE SAMPLING LOCATION

APPENDIX C DATA TABLES

• 71

APPENDIX C DATA TABLES Appendix C presents the analytical results of the 1995 Radio-logical Environmental Monitoring Program for the period of January 1 to December 31, 1995.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1995 Concentrations of Gross Alpha Emitters . . . . . . . . . . . . . . . . . . . . 76 C-2 1995 Concentrations of Gross Beta Emitters . . . . . . . . . . . . . . . . . . . . . 78 C-3 1995 Concentrations of Strontium-89 and Strontium-90 and Gamma Emitters in Quarterly Composites .......*...*........ 80 AIR IODINE C-4 1995 Concentrations of Iodine-131 . . . . . . . . . . . . . . . . . . . . . * . . . . . . . . 81 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-5 1995 Quarterly/Annual TLD Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 C-6 1995 Monthly TLD Results . . . . . . . . . . . . . . . . . . . . . . . . * . . . . . . . . . . . . . . 84 TERRESTRIAL ENVIRONMENT MILK 86

.C-8 C-7 1995 Concentrations of Iodine-131 and Gamma Emitters .......... .

1995 Concentrations of Strontium-89 and Strontiurn-90 .......... . 88 73

DATA TABLES (cont'd.)

TABLE NO TABLE DESCRIPTION PAGE.

TERRESTRIAL ENVIRONMENT (cont'd)

WELL WATER C-9 1995 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium ..**..*.....................*..... 89 )

C-10 1995 Concentrations of Iodine 131 and Garmna Emitters . . . . . . . . . . . 90 C-11 1995 Concentrations of Strontium-89 and Strontium-90 in Quarterly Cornposi tes . . . . . . . . * . . . . . . . . . . * . . . . . . . . . . . . . * . . . . 91 POTABLE WATER C-12 1995 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium . . . . . . . . . . . . . . . * . . . . . . . . . . . . . . . . . . 92 C-13 1995 Concentrations of Iodine 131 and Garmna Emitters . . . . . . . . . . . 93 C-14 1995 Concentrations of Strontium-89 and Strontium-90 in Quarterly Cornposi tes . . . . . . . * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 FOOD PRODUCTS C-15 1995 Concentrations of Gamma Emitters in Vegetables . . . . . . . . . . . . 95 C-16 1995 Concentrations of Gamma Emitters in Beef and Game *........ 96 FODDER CROPS C-17 1995 Concentrations of Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . 97 SOIL C-18 1995 Concentrations of Strontium 90 and Gamma Emitters 98 AQUATIC ENVIRONMENT SURFACE WATER C-19 1995 Concentrations of Gross Alpha Emitters . . . . . . . . . . . . . . . . . . . . 99 74

. DATA TABLES (cont'd.)

TABLE NO . TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT (cont'd)

C-20 1995 Concentrations of Gross Beta Emitters ..*......*........*.. 100 C-21 1995 Concentrations of Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . 101 C-22 1995 Concentrations of Tritium in' Quarterly Composites ......*.. 103 EDIBLE FISH C-23 1995 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters . * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104 BLUE CRABS c-.::24 1995 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 SEDIMENT C-25 1995 Concentrations of Strontium-90 and Gamma Emitters ......*.. 106 SPECIAL TABLES LLDs C-26 1995 PSE&G Research and Testing Laboratory LLDs for Gamma Spectrometry ..................*...................... 107 75

TABLE C-1 1995 CONCENTRATIONS OF (3ROSS ALPHA EMITTERS IN AIR PARTICULATES 3 3 Results in LI.nits of 10- pCi/m +/- 2 sigma

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

_r MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F2/2F6 SA-APT-3H3 SA-APT-501 SA-APT-5S1 AVERAGE January 2.6+/-0.7 2+/-0.7 2.6+/-0.7 2.5+/-0.8 2.1+/-0.7 2.3+/-0.7 2.3+/-0.6 2+/-0.8 1.8+/-0.8 2.1+/-0.8 2+/-0.8 1.8+/-0.8 2.5+/-0.8 2+/-0.5 1.2+/-0.7 1.2+/-0.8 0.9+/-0.6 2.3+/-0.9 2.3+/-0.8 <0.85 1.5+/-1.3

<0.81 <0.96 <0.81 <'0.9 <0.87 <0.85 0.5+/-0.3 1.6+/-0.7 1.8+/-0.8 1.8+/-0.7 1.3+/-0.7 1.9+/-0.7 2.3+/-0.8 1.8+/-0.6 February 2.4+/-0.8 2+/-0.9 2.3+/-0.8 2.8+/-0.9 2.9+/-1 1.7+/-0.8 2.4+/-0.9 3+/-0.8 3.4+/-0.9 3.9+/-0.9 2.4+/-0.7 3+/-0.9 3.2+/-0.8 3.2+/-1 2.8+/-0.8 3.4+/-1 3.5+/-0.9 3.9+/-0.9 2.7+/-1 ' 2.6+/-0.8 3.2+/-1.1 0.9+/-0.6 1.8+/-0.9 1.2+/-0.7 2.1+/-0.9 <1.31 1.9+/-0.8 1.5+/-1 March 2.7+/-0.9 2+/-0.9 1.6+/-0.7 2.1+/-0.8 1.4+/-0.7 1.5+/-0.8 1.9+/-1 1.8+/-0.7 2.3+/-0.9 3+/-0.8 3.4+/-0.9 2.7+/-0.8 2.9+/-0.9 2.7+/-1.1 2.4+/-0.8 2.1+/-0.9 2.9+/-0.8 2.3+/-0.8 1.9+/-0.7 2.5+/-0.9 2.4+/-0.7 2.4+/-0.7 2+/-0.8 2.4+/-0.7 1.4+/-0.6 2.1+/-0.7 2.6+/-0.8 2.1+/-0.9

-....J

°" April 2.8+/-0.9 2.8+/-0.9 2.5+/-0.9 2.1+/-0.8 1.9+/-0.7 (2) 2.4+/-0.9 (1) 7.4+/-1.9 4.8+/-1.5 5.9+/-1.7 4.1+/-1.2 6.2+/-1.9 (1) 2.8+/-1.3 4.9+/-2 4.3+/-2 2.8+/-0.9 3.7+/-1.5 3.1+/-1.4 4.5+/-2.9 4.8+/-1 3.1+/-1 3.1+/-1 2.8+/-0.9 2.2+/-0.7 2.3+/-1.3 3.1+/-1.9 2.4+/-0.8 2.3+/-0.9 3+/-1 1.9+/-0.8 2.3+/-0.7 1.6+/-0.7 2.2+/-1 1.8+/-0.7 1+/-0.7 2.2+/-0,9 <0.83 2.1+/-0.7 <0.85 1.4+/-1.6 May 1.8+/-0.8 2.2+/-0.9 2.2+/-0.9 2.2+/-0.8 2.4+/-0.7 1.8+/-0.8 2.1+/-0.5 1.1+/-0.7 1.5+/-0.9 1.5+/-0.8 1+/-0.7 1.3+/-0.6 1.1+/-0.8 1.3+/-0.4 3.4+/-0.9 1.1+/-0.8 3.1+/-1 2.7+/-0.9 1.4+/-0.7 (2) 2.3+/-2 1.6+/-0.7 1.7+/-0.9 1.5+/-0.8 1.1+/-0.6 1.8+/-0.6 2+/-0.7 1.6+/-0.7 June 1+/-0.8 1.8+/-1.1 1.8+/-1 2+/-0.8 . (2) 1.2+/-0.8 *. 1.5+/-0.8 1.8+/-0.7 2.2+/-0.9 2.2+/-0.9 1.9+/-0.8 (2) 1.6+/-0.7 1.9+/-0.5 2.6+/-0.8 2.7+/-1.1 3.1+/-1 3.2+/-0.9 2.7+/-0.9 2.6+/-0.9 2.8+/-0.5 2.9+/-0.8 2.9+/-0.9 '2.5+/-0.8 2.5+/-0.7 2.3+/-0.7 2.7+/-0.8 2.6+/-0.6

TA.-1 1995 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES 3 3 Results in Units of 1ff pCi/m +/- 2 sigma

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

MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F2 SA-APT-3H3 SA-APT-5D1 SA-APT-5S1 AVERAGE July 2.8+/-0.9 2.1+/-0.9 3.2+/-1 1.8+/-0.7 1.3+/-0.7 1.9+/-0.8 2.2+/-1.4 3.2+/-0.8 2.5+/-0.9 3.3+/-1 2.1+/-0.7 . 2.5+/-0.8 2.7+/-0.8 1.6+/-0.7 5.1+/-1.2 2+/-1 4.3+/-1.2 4.2+/-1.1 1.6+/-0.8 3.9+/-1.2 1.5+/-0.8 3.2+/-1 3.6+/-1.2 3.7+/-1.1 2.8+/-0.9 3+/-1 2.5+/-0.9 3.2+/-0.9 2.8+/-0.8 3.5+/-1 2.5+/-0.9 2+/-0.8 2.6+/-0.8 2.8+/-0.5 August 1.8+/-0.7 1.7+/-0.7 2.7+/-0.9 2.4+/-0.8 1.7+/-0.8 1.6+/-0.8 2.6+/-0.6 2+/-0.9 1.9+/-0.8 1.7+/-0.8 1.7+/-0.8 1.6+/-0.8 1.7+/-0.8 2.2+/-1.4 2.8+/-0.9 2.2+/-0.8 2.8+/-1 2.7+/-0.9 2.8+/-0.9 4.3+/-1.1 2.7+/-0.9 3.2+/-0.8 2.2+/-0.7 3.5+/-1 2'.3+/-0.8 1.9+/-0.7 2.1+/-0.8 3.5+/-2.8 September 3.3+/-0.8 3.2+/-0.7 3.3+/-0.8 2.8+/-0.7 2.5+/-0.7 2.6+/-0.7 3.1+/-0.9 2.5+/-0.9 3.2+/-0.9 3.5+/-1.1 2.5+/-0.9 2.9+/-1 2.6+/-1 2.8+/-1.1 1.6+/-0.7 1.1+/-0.6 <1.01 1.9+/-0.8 . 1.8+/-0.8 1.9+/-0.8 2+/-0.9 1.8+/-0.7; 1.5+/-0.7 1.2+/-0.7 1.9+/-0.8 1.9+/-0.7 2+/-0.8 1.8+/-0.3

-...J

-...J October 3.4+/-1 3.3+/-0.9 3.6+/-1 3.6+/-0.9 3+/-0.8 2.9+/-1 2.9+/-1.4 2.5+/-0.8 5+/-1 5.3+/-1.2 2.3+/-0.8 2.4+/-0.7 1.5+/-0.8 2.5+/-1.3 1.7+/-0.8 2.1+/-0.8 2.3+/-1 2.5+/-1 2.1+/-0.8 1.8+/-0.8 3+/-0.7 1.1+/-0.7 2+/-0.7 1.6+/-0.8 2.3+/-0.9 2.2+/-0.8 1.9+/-0.8 2.9+/-0.8 2.6+/-0.8 2.3+/-0.7 ) 2.1+/-0.8 2.8+/-0.9 1.8+/-0.7 2+/-0.8 1.5+/-0.8 November 2.5+/-0.8 1.8+/-0.7 2.6+/-0.9 1.9+/-0.9 1.5+/-0.7 1.8+/-0.9 1.7+/-0.6 1.5+/-0.7 2+/-0.8 2.3+/-0.9 2+/-0.8 2+/-0.7 2;5+/-1" 3.3+/-0.6 2.3+/-0.7 2.3+/-0.7 2.9+/-0.8 1.2+/-0.7 1.6+/-0.6 2.2+/-0.7 3.2+/-3.2 3+/-0.8 2+/-0.8 3.4+/-1 3.7+/-1.2 2.8+/-0.9 4.1+/-1.1 2.1+/-0.6 December 2.8+/-0.8 2.5+/-0.8 1.5+/-0.7 1.9+/-0.9 2.6+/-0.8 3.2+/-0.9 1.9+/-0.9 1.7+/-0.8 2.5+/-0.8 2.1+/-0.8 2.3+/-0.8 2.6+/-0.9 2.8+/-0.9 2.3+/-0.8 '

3.5+/-0.9 3.3+/-0.9 3.5+/-0.8 2.4+/-0.8 2.4+/-0.8 3.1+/-0.9 2+/-0.8 2.2+/-0.6 1.5+/-0.6 2.3+/-0.7 1.7+/-0.7 2.7+/-0.7 2.6+/-0.7 2+/-0.7 AVERAGE 2.5+/-2.2 2.3+/-1.8 2.7+/-2.1 2.3+/-1.5 2.2+/-1.3 2.3+/-1.9 GRAND AVERAGE 2.4+/-1.8 (1) Due to un-planned Airborne release from Hope Creek Station, all locations except 3H3 were sampled twice in the week of 4/3-10/95.

(2) Circuit Breakers tripped. Results are invalid due to low airflow. Results not included in any aver~mes.

I .,,,

TABLE C-2 1995 CONCENTRATIONS OF GROSS BETA EMIT)"ERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma

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

MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F2/2F6 SA-APT-3H3 SA-APT-501 SA-APT-5S1 AVERAGE January 22+/-2 21+/-3 25+/-2 25+/-3 24+/-2 23+/-2 23+/-3 27+/-3 27+/-3 21+/-3 25+/-3 24+/-3 25+/-3 25+/-4 21+/-2 17+/-2 18+/-2 23+/-3 20+/-2 16+/-2 19+/-5 6+/-2 8+/-2 8+/-2 10+/-2 9+/-2 9+/-2 8+/-2 22+/-2 21+/-2 22+/-2 18+/-2 22+/-2 .21+/-2 21+/-3 February 23+/-2 20+/-3 22+/-2 19+/-2 26+/-3 22+/-2 22+/-5 25+/-2 30+/-3 31+/-2 21+/-2 29+/-3 29+/-2 27+/-8 29+/-3 30+/-3 26+/-2 30+/-3 30+/-3 24+/-2 28+/-5 17+/-2 20+/-3 26+/-3 27+/-3 24+/-3 22+/-3 23+/-8 March 22+/-3 19+/-3 22+/-2 22+/-2 22+/-2 24+/-2 22+/-2 17+/-2 20+/-3 24+/-2 25+/-2 24+/-2 22+/-3 22+/-2 28+/-3 24+/-3 26+/-2 24+/-2 23+/-2 . 21+/-2 24+/-3 21+/-2 20+/-3 20+/-2 16+/-2 20+/-2 21+/-2 20+/-3 00 April 25+/-2 26+/-3 24+/-3 28+/-3 24+/-2 (2) 25+/-4 (1) 34+/-5 34+/-4 39;t5 - 28+/-3 34+/-5 (1) 23+/-4 73+/-7 30+/-5 24+/-2 19+/-4 27+/-4 33+/-29 22+/-2 21+/-3 20+/-3 20+/-2 21+/-2 22+/-4 21+/-2 22+/-2 23+/-3 20+/-3 17+/-2 16+/-2 18+/-2 19+/-5 19+/-2 18+/-2 25+/-3 14+/-2 18+/-2 14+/-2 18+/-8 May 21+/-2 24+/-3 21+/-3 24+/-2 17+/-2 21+/-2 21+/-5 11+/-2 9+/-2 11+/-2 9+/-2 10+/-2 10+/-2 10+/-2 22+/-2 13+/-2 23+/-3 24+/-2 19+/-2 (2) 20+/-9 18+/-2 17+/-2 20+/-2 14+/-2 18+/-2 19+/-2 17+/-4 June 17+/-3 13+/-3 15+/-3 17+/-2 (2) 16+/-2 16+/-3 17+/-2 21+/-3 11+/-1 27+/-3 (2) 14+/-2 18+/-13 21+/-2 19+/-3 21+/-3 23+/-2 19+/-2 21+/-2 21+/-3 14+/-2 14+/-3 16+/-3 21+/-2 16+/-2 15+/-2 16+/-5

-2 1995 CONCENTRATIONS OF GROSS BE ,. ITTERS IN AIR PARTICULATES Results in Units of 10- pCi/m3 +/- 2 sigma 3

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

MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F2/2F6 SA-APT-3H3 SA-A!pT-501 SA-APT-581 AVERAGE July 13+/-2 12+/-3 11+/-2 13+/-2 11+/-2 11+/-2 12+/-2 18+/-2 19+/-3 20+/-3 13+/-2 19+/-2 19+/-2 18+/-5 34+/-3 16+/-3 35+/-3 37+/-3 14+/-2 27+/-3 27+/-20 30+/-3 32+/-4 32+/-3 26+/-3 33+/-3 26+/-3 30+/-6 30+/-3 30+/-3 31+/-3 35+/-3 27+/-3 28+/-3 30+/-5 August 17+/-2 14+/-2 21+/-3 23+/-3 23+/-3 15+/-2 19+/-8 22+/-3 21+/-2 21+/-3 21+/-3 19+/-2 19+/-3 20+/-2 23+/-3 25+/-2 26+/-3 26+/-3 25+/-3 \ 26+/-3 25+/-2 17+/-2 20+/-2\ 19+/-3 19+/-2 16+/-2 18+/-2 18+/-3 September 30+/-3 29+/-2 28+/-3 29+/-2 27+/-2 27+/-3 28+/-2 30+/-3 30+/-3 32+/-3 30+/-3 . 28+/-3 34+/-4 31+/-4 19+/-2 18+/-2 19+/-3 20+/-2 22+/-3 21+/-3 20+/-3 18+/-2 17+/-2 15+/-2 16+/-2 \ 13+/-2 14+/-2 15+/-4

\.0 October 31+/-3 29+/-3 26+/-3 29+/-3 27+/-3 31+/-3 29+/-4 23+/-2 69+/-3 28+/-3 22+/-2 18+/-2 28+/-3 31+/-37 25+/-3 35+/-3 36+/-4 36+/-4 31+/-3 27+/-3 32+/-9 16+/-2 23+/-2 22+/-3 19+/-3 18+/-2 15+/-2 19+/-7 23+/-2 20+/-2 18+/-3 23+/-3 17+/-2 22+/-3 21+/-5 I

November 22+/-2 26+/-3 25+/-3 22+/-3 22+/-2 22+/-3 23+/-4 22+/-2 26+/-3 25+/-3 19+/-3 17+/-2 24+/-3 22+/-7 19+/-2 20+/-2 21+/-2 14+/-2 18+/-2 20+/-2 19+/-5 29+/-3 30+/-3 30+/-3 30+/-3 31+/-3 29+/-3 30+/-2

.December 23+/-2 24+/-2 23+/-2 25+/-3 24+/-2 27+/-2 24+/-3 25+/-3 24+/-2 25+/-2 23+/-2 24+/-2 24+/-2 24+/-2 27+/-3 18+/-2 22+/-2 18+/-2 15+/-2 22+/-3 20+/-8 22+/-2 18+/-2 20+/-2 18+/-2 20+/-2 20+/-2 20+/-3 AVERAGE 22+/-11 24+/-23 23+/-13 22+/-12 21+/-11 22+/-11 GRAND AVERAGE 22+/-14 (1) Due to un-planned Airborne release from Hope Creek Station, all locations except 3H3 were sampled twice in the week of 4/3-10/95.

(2) Circuit Breakers tripped. Results are invalid due to low airflow. Results not included in any averages.

Table C-3 1995 CONCENTRATIONS OF STRONTIUM 89 90 AND GAMMA EMITTERS-IN QUARTERLY COMPOSITES OF AIR PARTICULATES 3

Results in Units of 10-3 pCi/m +/- 2 sigma STATION Sampling Period Strontium <-----Gamma Emitters--->

ID Start Stop Sr-89 Sr-90 Be-7 K-40 RA-NAT Th-232 SA-APT-16E1 12/27/94 to 3/27/95 <0.2 <0.2 60+/-4 <3.4 0.7+/-0.2 <0.5 SA-APT-1F1 12/27/94 to 3/27/95 <0.2 <0.2 63+/-4 <4.1 <0.2 <0.4 SA-APT-2F2 12127/94 to 3/27/95 <0.1 <0.2 65+/-6 . <4.9 0.9+/-0.4 <0.8 SA-APT-3H3(C} 12/27/94 to 3/27/95 <0.2 <0.2 70+/-6 17+/-5 1.3+/-0.5 <1 SA-APT-501 12/27/94 to 3/27/95 <0.2 <0.2 66+/-5 <4.6 <0.9 <1.6 SA-APT-5S1 12/27/94 to 3/27/95 <0.2 <0.2 41+/-3 <5.6 <0,5 <0.4 SA-APT-16E1 3/27/95 to 6/26/95 79+/-4 <3.4 <0.9 <0.7

. SA-APT-1 F1 3/27/95 to 6/26/95 59+/-6 5.9+/-5 <0.4 <0.8 SA-APT-2F6 . 3/27/95 to 6/26/95 87+/-6 21+/-5 <0.6 <1.1 SA-APT-3H3(C} 3/27/95 to 6/26/95 67+/-5 <5 <0.6 <2.2 SA-APT-501 3/27/95 to 6/26/95 75+/-5 <4.9 <1.1 <0.6 SA-APT-5S1 3/27/95 to 6/26/95 72+/-7 . 14+/-4 <0.5 <1.4 SA-APT-16E1 6/26/95 to 9/26/95 75+/-4 <3.6 <0.5 <0.7 SA-APT-1F1 6/26/95 to 9/25/95 69+/-5 <5.1 1+/-0.5 <0.4 SA-APT-2F6 6/26/95 to 9/25/95 72+/-6 18+/-5 1.7+/-0.6 <1.3

/

SA-APT-3H3(C} 6/26/95 to 9/25/95 70+/-5 <5.2 <0.7 <0.9 SA-APT-501 6/26/95, to 9/25/95 79+/-5 <4.6 <1 <0.9 SA-APT-5S1 6/26/95 to 9/25/95 71+/-6 15+/-4.5 <0.4 <0.8 SA-APT-1F1 9/25/95 to 12/26/95 46+/-4 20+/-5 1.6+/-0.6 <1.1 SA-APT-2F6 9/25/95 to 12/26/95 47+/-4 <4.6 <0.5 1.6+/-0.8 SA-APT-3H3(C} 9/25/95 to 12/26/95 46+/-5 <5.4 1.5+/-0.7 <0.4 SA-APT-501 9/25/95 to 12/26/95 42+/-3 <3.3 <1 <0.5 SA-APT-5S1 9/25/95 to 12/26/95 46+/-4 14+/-4 <0.5 1.9+/-0.9 SA-APT-16E1 9/26/94 to 12127/95 32+/-4 <5.2 <1.2 <1 AVERAGE 62+/-29

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table 26.

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

(C} Control Station 80

• 1995 CONCENTRATIONS OF IC TA -4

-131* IN FILTERED AIR 3

Results in Units of 10- pCi/m 3

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

Control MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F2/2F6 SA-APT-3H3 SA-APT-501 SA-APT-5S1 January <2.4 <4.3 <3.9 <5.1 <2.9 <2.3

<4.2 <4.7 <4.3 <3.9 <2.9 <6.4

<4.5 <3.2 <2.7 <1.3 <1.3 <3.5

<3.2 <3.9 <4.8 <7.2 <2.2 <2.3

<4.1 <3.5 <6.6 <2 <2.3 <4.5 February <1.6 <4.5 <3.6 <1.4 <3.6 <4.2

<1.6 <4.3 <2.1 <2.2 <4.2 <3.3

<1.7 <3.3 <2.5 <2.7 <3.1 <5

<3.2 <4 <2.6 <2.2 <3.7 <2.8 March <4.3 <5.6 <2.5 <2.9 <1.7 <4

<3.9 <4 <1.8 <1.9 <2.4 <4.1

<2.9 <2.1 <5.3 <2.6 <2.7 <4.3

<1.1 <5 <4.7 <3.6 <1.7 <3.1 00 April <1.8 <3.5 <3.5 <2 <5.1 (2)

(1) <9.6 <10.5 <6.3 <4.2 <8 (1) <10.4 <32.4 <15.6 <2.5 <6.2 <6.1

<3.7 <2.6 <5.8 <5.2 <4.8 <5.2

<4.9 <3.4 <4.5 <2.9 <2.1 <4.5

<2.6 <6.9 <4.2 <4.4 <1.9 <5.1 May <5.2 <2.3 <5.5 <2.6 <1.4 <2:3

<3.6 <5.8 <4.7 <3.1 <2.4 <4.1

<2.6 <4.1 <3 <2.3 <1.8 (2)

<4 <1.4 <3.4 <5 <2 <1.3 June <3.9 <4 <6.9 <4.3 (2) <5.2

<2 <5.9 <1.8 <5.8 (2) <4.6

<3.1 <3.1 <6.8 <3.5 <6.1 <4.1

<5.3 <4.8 <7.5 <2.8 <4.7 <3

TABLE C-4 1995 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR 3 3 Results in Units of 10- pCi/m

<------------------------------------------------ STATION *10 ---------------------------------------------->

Control MONTH SA-APT-16E1 SA-APT-1F1 SA-APT-2F2/2F6 SA-APT-3H3 SA-APT-5D1 SA-APT-581 July <4.6 <8.2 <5.1 <2.9 <4.3 <5.5

<4.6 <4.3 <6 <3.3 <2.2 <3.3

<5.3 <7.2 <6.1 <2.6 <5.7 <3.1

<3.7 <3.6 <3.6 <3.3 <3.3 <5.3

<2.5 <3.4 <2.5 <4.8 <2.2 <5.6 August <3.1 <2.8 <4.8 <5.9 <2.7 <7.4

<3.7 <2.3 <2.5 <2.8 <3.2 <4.1

<3.3 <3.6 <3.7 <2.6 <3.6 <3.3

<3.3 <4.8 <3.3 <6.1 <5.4 <4 September <3.1 <4.4 <3.9 <4.2 <3 <2.9

<5 <4 <7.3 <8 <4.1 <12.1

<3.4 <3.2 <5.8 <4.9 <2 <3.1

<3.7 <3.7 <7.5 <8.5 <3.7 <6.4 00 N October <3.7 <5 <4 <3.6 <3.5 <7.3

<2.9 <3:7 <2.5 <5.6 <3.9 <6.5

<5.1 <4.1 <7.8 <4.2 <4 <6.5

<2.7 <5 <4.2 <11.4 <5.9 <3.8

<6.1 <5.8 <4 <4.9 <2 <9.3 November <4.1 <3 <4.3 <3.3 <3.4 <3.6

<3.2 <3.2 <2.6 <6.1 <5.5 <4.3

<1.9 <4 <2.3 <3.3 <2.9 <4.7

<2.3 <7.2 <2.6 <3.2 <4.6 <2.9 December <3.1 <2.7 <4.5 <3.9 <4.7 <3.4

<2.5 <4.4 <2.2 <6 ) <1.5 <5.9

<5.4 <5.8 <2.9 <2 <3.9 <3.5

<3.6 <1.7 <3.1 <1.6 <2.2 <4.4

• 1-131 results are corrected for decay to sample stop date.

(1) Due to un-planned Airborne release from Hope Creek Station, all locations except 3H3 were sampled twice in the week of 4/3-10/95.

(2) Circuit breakers tripped. Results are invalid due to low.airflow. Results are not included in any averages.

TABLE C-5 1995 DIRECT RADIATION MEASUREMENTS - QUARTERLY /ANNUAL TLD RESULTS Results in mrad/standard month* +/- 2 sigma JAN MAR.27 APR JUL OCT QTR ANNUAL STATION to to to to to ELEMENTS ELEMENTS J ID MAR APR.11 JUN SEP DEC AVG RESULTS 5A-IOM-252 3.8+/-0.3 6.5+/-1.1 4.7+/-0.5 4.6+/-0.4 4.2+/-0.4 4.3+/-0.8 5.0+/-0.4 5A-IOM-551 3.0+/-0.3 5.9+/-1~0 3.6+/-0.3 3.6+/-0.4 3.8+/-0.3 3.5+/-0.7 4.1+/-0.9 5A-IOM-652 3.6+/-0.4 6.1+/-1.1 4.4+/-0.3 4.3+/-0.3 4.4+/-0.4 4.2+/-0.8 5.2+/-0.7 5A-IDM-7S1 4.9+/-0.5 7.7+/-0.9 5.4+/-0.3 5.8+/-0.4 4.7+/-0.4 . 5.2+/-1.0 5.8+/-0.4 5A-IOM-1051 3.7+/-0.3 6.1+/-1.2 4.2+/-0.3 4.2+/-0.4 3.4+/-0.3 3.9+/-0.8 5.4+/-1.5 5A-IOM-1151 2.6+/-0.3 5.1+/-1.4 3.5+/-0.6 3.4+/-0.3 3.2+/-0.4 3.2+/-0.8 3.6+/-1.0 5A-IOM-402 4.3+/-0.4 5.1+/-0.6 5.1+/-0.4 5:0+/-0.7 4.9+/-0.8 5.1+/-0.6 5A-IOM-501 3.6+/-0.4 4.5+/-0.5 4.3+/-0.3 4.3+/-0.4 4.2+/-0.8 5.1+/-1.5 5A-IOM-1001 4.1+/-0.3 7.1+/-1.4 4.5+/-0.5 5.2+/-0.3 4.8+/-0.5 4.7+/-0.9 5.2+/-0.9 5A-IDM-1401 3.7+/-0.5 4.6+/-0.5 4.4+/-0.3 4.7+/-0.6 4.4+/-0.9 4.8+/-0.6 5A-IOM-1501 3.8+/-0.6 5.3+/-0.6 5.3+/-0.4 5.0+/-0.6 4.9+/-1.4 2.9+/-1.0 SA-IDM-2E1 3.2+/-0.4 4.6+/-0.5 4.6+/-0.4 4.4+/-0.5 4.2+/-1.3 4.6+/-0.3 SA-IOM-3E1 2.9+/-0.3 4.1+/-0.5 4.0+/-0.3 3.8+/-0.3 3.7+/-1.1 4.6+/-0.6 SA-IDM-9E1 4.4+/-0.5 8.1+/-1.2 5.3+/-0.3 6.0+/-0.9 5.4+/-0.4 5.3+/-1.3 5.7+/-0.8 5A-IDM-11E2 4.1+/-0.4 7.3+/-1.2 4.7+/-0.3 5.0+/-0.4 4.8+/-0.4 4.7+/-0.8 5.1+/-0.5 5A-IDM-12E1 3.8+/-0.4 4.9+/-0.6 5.1+/-0.4 5.0+/-0.4 4.7+/-1.2 4.9+/-0.4 5A-IDM-13E1 3.4+/-0.3 4.3+/-0.5 4.3+/-0.3 4.1+/-0.4 4.0+/-0.9 4.4+/-1.0 SA-IOM-16E1 3.9+/-0.3 4.7+/-0.6 4.8+/-0.4 4.6+/-0.6 4.5+/-0.8 5.2+/-0.8 5A-IOM-1F1 3.7+/-0.3 4.6+/-0.5 4.8+/-0.3 4.6+/-0.4 4.4+/-1.0 4.8+/-0.9 5A-IDM-2F2 3.1+/-0.3 4.1+/-0.5 4.0+/-0.4 (2) 3.7+/-1.1 5A-IOM-2F5 3.7+/-0.5 4.8+/-0.5 4.7+/-0.5 (2) 4.4+/-1.2 4.9+/-0.7 5A-IOM-2F6 3.2+/-0.3 4.3+/-0.6 4.2+/-0.3 4.1+/-0.4 4.0+/-1.0 . 4.4+/-0.8 5A-IDM-3F2 3.1+/-0.4 4.2+/-0.5 4.4+/-0.3 4.0+/-0.4 3.9+/-1.1 4.3+/-0.9 5A-IDM-3F3 3.1+/-0.4 4.2+/-0.5 4.1+/-0.4 4.0+/-0.4 3.9+/-1.0 4.1+/-0.7 5A-IOM-4F2 3.0+/-0.3 4.0+/-0.5 4.2+/-0.5 3.9+/-0.4 3.8+/-1.1 6.0+/-1.2 5A-JOM-5F1 3.2+/-0.3 4.3+/-0.6 4.3+/-0.4 4.2+/-0.4 4.0+/-1.1 4.5+/-0.8 5A-IDM-6F1 2.6+/-0.3 3.6+/-0.4 3.5+/-0.3 3.6+/-0.4 3.3+/-1.0 3.6+/-1.1

. 5A-IDM-7F2 2.2+/-0.4 3.2+/-0.4 3.0+/-0.3 3.2+/-0.3 2.9+/-1.0 3.4+/-0.2 SA-IDM-10F2 3.8+/-0.4 6.9+/-1.3 4.4~0.4 5.0+/-0.4 4.8+/-0.5 4.5+/-1.1 5.4+/-1.1 5A-IOM-11F1 4.0+/-0.3 5.1+/-0.6 5.0+/-0.4 4.9+/-0.4 4.8+/-1.0 5.0+/-0.6 5A-IDM-12F1 3.7+/-0.3 4.8+/-0.5 4.7+/-0.4 4.7+/-0.5 4.5+/-1.0 4.8+/-0.8 5A-IOM-13F2 3.6+/-0.3 4.7+/-0.6 4.6+/-0.3 4.3+/-0.4 4.3+/-1.0 4.9+/-1.1 5A-IDM-13F3 3.7+/-0.3 4.9+/-0.6 4.8+/-0.4 4.6+/-0.5 4.5+/-1.1 4.8+/-1.7 5A-IDM-13F4 3.5+/-0.4 4.5+/-0.5 4.4+/-0.3 4.4+/-0.5 4.2+/-0.9 4.6+/-1.0 5A-IDM-14F2 4.6+/-0.4 5.6+/-0.7 5.6+/-0.5 5.5+/-0.5 5.3+/-1.0 5.0+/-1.5 5A-IOM-15F3 4.3+/-0.5 5.3+/-0.6 5.3+/-0.4 5.0+/-0.6 5.0+/-0.9 5.5+/-1.2 5A-IDM-16F2 3.5+/-0.4 4.4+/-0.5 4.4+/-0.4 4.2+/-0.5 4.1+/-0.9 5.0+/-1.1 5A-IDM-1~3 (C) 4.6+/-0.4 5.5+/-0.6 5.5+/-0.8 5.4+/-0.5 5.3+/-0.9 5.1+/-1.2 5A-IOM-3G1 (C) 3.9+/-0.3 5.0+/-0.6 4.8+/-0.4 4.8+/-0.4 4.6+/-1.0 5.1+/-0.9 5A-IDM-10G1(C) 4.0+/-0.4 4.9+/-0.5 4.8+/-0.3 4.8+/-0.4 4.6+/-0.8 5.3+/-1.3 5A-IOM-16G1(C) 4.3+/-0.4 5.2+/-0.6 5.1+/-0.4 4.8+/-0.4 4.9+/-0.8 5A-IDM-3H1 (C) 3.2+/-0.3 4.4+/-0.6 3.9+/-0.3 4.0+/-0.4 3.9+/-1.0 4.9+/-1.0.

5A-IOM-3H3 (C) 3.9+/-0.4 5.0+/-0.6 4.9+/-0.4 4.7+/-0.4 4.6+/-1.0 5.4+/-1.9

.AVERAGE 3.6+/-1.1 6.7+/-1.8 4.6+/-1.1 4.6+/-1.3 4.4+/-1.1 4.8+/-1.3 GRAND AVG 4.4+/-1.8

=

• The standard month 30.4 days.

• • Quarterly Element TLD results by YAEL

• • • Annual Element TLD results by Thermo NUtech.

(1) Special samples due to unplanned airborne release from HC station. Results differ from other

' J issue periods due to short field time & the effect of the transit erro[.

(2) See Program Deviations.

83

TABLE C-6 1995 DIRECT RADIATION MEASUREMENTS - MONTHLY I TLD RESULTS Results in mrad/standard month "' +/- 2 sigma (Results by Yankee Atomic Energy Laboratory)

STATION ID JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 4.2+/-0.2 4.7+/-0.6 3+/-1 3.9+/-0.5 4.2+/-0.6 5.4+/-1 SA-IDM-5S1 2.9+/-0.2 4+/-0.4 1.9+/-0.5 3.1+/-0.4 2.9+/-0.4 4.4+/-0.6 SA-IDM-6S2 3.7+/-0.2 4.4+/-0.7 2.6+/-0.5 3.8+/-0.5 3.8+/-0.5 5.1+/-0.9 SA-IDM-7S1 5.1+/-0.3 6.1+/-0.7 3.8+/-0.5 . 5.1+/-0.9 5+/-0.5 6.1+/-0.6 SA-IDM-1051 3.8+/-0.3 4.7+/-0.5 2.4+/-0.4 3.6+/-0.4 3.5+/-0.5 4.6+/-0.6 SA-IDM-11S1 2.7+/-0.2 3.9+/-1.1 1.6+/-0.5 2.5+/-0.4 2.7+/-0.4 4.1+/-0.6 SA-IDM-501 4+/-0.7 4.4+/-0.6 2.3+/-0.7 3.7+/-0.5 3.5+/-0.4 4.6+/-0.8 SA-IDM-1001 *4.3+/-0.4 4.8+/-0.5 2.8+/-0.6 4+/-0.5 4.4+/-0.4 5+/-0.8 SA-IDM-1401 3.8+/-0.3 4.6+/-0.5 2.5+/-0.5 3.7+/-0.8 3.7+/-0.6 4.5+/-0.8 SA-IDM-2E1 3.6+/-0.2 4.4+/-0.4 2.6+/-0.6 3.5+/-0.5 3.4+/-0.4 4.6+/-0.7 SA-IDM-3E1 3.2+/-0.3 4+/-0.4 2.2+/-0.5 3.4+/-0.7 3.1+/-0.4 4.2+/-0.8 SA-IDM-13E1 3.5+/-0.4 4.3+/-0.6 2.4+/-0.5 3.4+/-0.6 3.5+/-0.6 4.3+/-0.9 SA-IDM-16E1 4.1+/-0.3 4.7+/-0.6 2.8+/-0.5 3.8+/-0.4 3.8+/-0.5 4.7+/-0.6 00 SA-IDM-1F1 3.9+/-0.3 4.5+/-0.5 2.6+/-0.5 3.6+/-0.6 3.7+/-0.6 4.8+/-1

.i:- SA-IDM-2F2 3+/-0.3 4.3+/-0.5 2.2+/-0.9 2.9+/-0.5 3.2+/-0.4 4.1+/-0.7 SA-IDM-2F6 3.5+/-0.3 4.3+/-0.8 2.5+/-0.9 3.4+/-0.4 3.4+/-0.4 4.5+/-0.9 SA-IDM-5F1 3:4+/-0.4 4.4+/-0.5 2.4+/-0.5 3.4+/-0.5 3.7+/-0.9 4.4+/-0.6 SA-IDM-6F1 2.8+/-0.3 3.5+/-0.4 1.7+/-0.5 2.8+/-0.5 2.9+/-0.6 3.7+/-0.5 SA-IDM-7F2 2.3+/-0.2 3.3+/-0.7 1.3+/-0.6 2.4+/-0.4 2.4+/-0.5 3.3+/-0.8 SA-IDM-11 F1 4.4+/-0.4 4.7+/-0.4 2.8+/-0.5 4.2+/-0.5 4.2+/-0.4 4.7+/-0.9 SA-IDM-13F4 3.9+/-0.3 4.4+/-1.1 2.5+/-0.5 3.6+/-0.6 3.9+/-0.5 4.5+/-1 SA-IDM-3G1 (C) 4+/-0.3 4.7+/-0.5 2.8+/-0.9 4+/-0.4 4.1+/-0.5 5+/-0.6 SA-IDM-3H1 (C) 3.4+/-0.3 3.8+/-0.5 2.2+/-0.5 4+/-0.5 3.3+/-0.4 4.1+/-0.6 SA-IDM-3H3 (C) 4.3+/-0.4 4.8+/-0.9 2.8+/-0.5 4+/-0.4 4+/-0.5 4.9+/-0~8 AVERAGE 3.7+/-1.3 4.4+/-1.1 2.4+/-1 3.6+/-1.2 3.6+/-1.2 4.6+/-1.1

"' The standard month =30.4 days.

(C trol Station.

• TA

• 1995 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS I

Results in mrad/standard month * +!- 2 sigma (Results by Yankee Atomic Energy Laboratory)

STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 3.6+/-0.5 4.8+/-0.4 4.6+/-0.9 3.6+/-0.5 4.3+/-0.5 3.5+/-0.4 4.2+/-1.3 SA-IDM-5S1 2.9+/-0.5 3.8+/-0.6 3.6+/-0.6 2.9+/-0.5 4.1+/-0.6 3.3+/-0.7 3.3+/-1.4 SA-IDM-6S2 3.6+/-0.~, 4.3+/-0.4 4.4:1:1.3 3.3+/-0.4 4.5+/-0.5 4.1+/-0.5 4+/-1.3 SA-IDM-7S1 5+/-0.9 5.6+/-0.5 5.3+/-0.5 4.6+/-0.5 5.8+/-0.7 3.9+/-0.5 5.1+/-1.5 SA-IDM-1OS1 3.5+/-0.7 4.3+/-0.6 3.7+/-0.3 3.4+/-0.7 4.2+/-0.5 2.6+/-0.4 3.7+/-1.4 SA-IDM-11S1 2.6+/-0.6 3.5+/-0.6 3+/-0.5 2.5+/-0.4 3.7+/-0.8 3.2+/-0.6 3+/-1.4

. SA-IDM-501 3.7+/-0.5 4 ..2+/-0.6 4+/-0.4 3.3+/-0.6 4.4+/-0.3 3.9+/-0.5 3.8+/-1.2 SA-IDM-10D1 4.1+/-0.g 5.2+/-0.3 . 5+/-0.8 4.1+/-0.6 4.7+/-0.6 4.4+/-0.7 4.4+/-1.3 SA-IDM-1401 3.7+/-0.4 4.4+/-0.5 4.2+/-0.5 3.4+/-0.6 4.6+/-0.6 4+/-0.5 3.9+/-1.2 SA-IDM-2E1 4.1+/-0.9 4.4+/-0.7 4.3+/-0.3 3.3+/-0.5 4.7+/-0.4 4.1+/-0.8 3.9+/-1.3 SA-IDM-3E1 3.2+/-0.6 4.1+/-0.5 3.5+/-0.5 2.8+/-0.5 4.1+/-0.5 3.4+/-0.7 3.4+/-1.2 SA-IDM-13E1 3.4+/-0.7 4+/-0.4 3.9+/-0.9 3.2+/-0.7 4.4+/-1.1 3.7+/-0.4 3.7+/-1.1 SA-IDM-16Ef 4+/-0.6 4.7+/-0.5 4.3+/-0.6 3.5+/-0.4 4.5+/-0.6 4.2+/-0.5 4.1+/-1.1 00 SA-IDM-1F1 4+/-0.7 4.6+/-0.5 4.3+/-0.4 3.7+/-0.5 4.8+/-1.1 4+/-0.9 4+/-1..2 V1 SA-IDM-2F2 3.4+/-0.4 3.7+/-0.4 3.4+/-0.3 2.8+/-0.5 (1) 3.4+/-0.6 3.3+/-1.2 SA-IDM-2F6 3.6+/-0.5 4+/-0.6 3.9+/-0.6 3.3+/-0.4 4.4+/-0.5 3.6+/-0.4 3.7+/-1.1 SA-IDM-5F1 3.6+/-0.7 4.1+/-0.3 3.9:i:0.6 3.2+/-0.5 4.2+/-0.6 . 3.7+/-0.7 3.7+/-1.1 SA-IDM-6F1 2.9+/-0.6 3.4+/-0.5 3.2+/-0.4 2.6+/-0.4 3.5+/-0.7 3.1+/-0.5 3+/-1.1 SA-IDM-7F2 2.4+/-0.5 3+/-0.5 2.8+/-0.3 2.2+/-0.3 3.2+/-0.9 2.5+/-0.4 2.6+/-1.1 SA-IDM-11 F1 4.1+/-0.5 5.1+/-0.4 4.8+/-0.6 4.1+/-0.4 4.7+/-0.8 4.4+/-0.6 4.4+/-1.2 SA-IDM-13F4 3.6+/-0.5 4.3+/-0.6 4+/-0.4 3.4+/-0.6 4.4+/-0.5 3.8+/-0.4 3.9+/-1.1 SA-IDM-3G1 (C) 4+/-0.4 4.8+/-0.4 4.5+/-0.4 3.7+/-0.4 4.6+/-0.7 4+/-0.4 4.2+/-1.2 SA-IDM-3H1 (C) 3.3+/-0.6 4.3+/-0.6 3.9+/-0.5 3.2+/-0.5 3.9+/-0.4 3.5+/-0.4 - 3.6+/-1.1 SA-IDM-3H3 (C) 3.9+/-0.7 5.1+/-0.4 4.5+/-0.5 3.6+/-0.5 4.7+/-0.3 4.2+/-0.7 4.2+/-1.3 AVERAGE 3.6+/-1.1 4.3+/-1.2 4+/-1.2 3.3+/-1.1 4.4+/-1 3.7+/-1 GRAND AVERAGE 3.8+/-1.2 (1) Location 2F2 TLD was missing from the pole.

• The standard montn =30.4 days.

(C) Control* Station.

TABLE C-7 1995 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS- IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD < - GAMMA EMITTERS~--->

STATION ID START STOP - 1-131 ~-40 RA-NAT SA-MLK-3G1 (C) 1/2195 1/3/95 <0.2 1400 +/-100 18 +/-6 SA-MLK-14F4 1/2195 1/3/95 <0.2 1400 +/-80 <3.8 SA-MLK-2F7 1/2195 1/3/95 <0.2 1300 +/-90 <4.4 SA-MLK-11 F3 1/3/95 1/4/95 <0.5 1300 +/-70 12 +/-3

-SA-MLK-2F7 \ 215/95 216/95 <0.2 1300 +/-80 <5.4 SA-MLK-3G1 (C) 215/95 216/95 <0.2 1300 +/-90 <4.5 SA-MLK-14F4 216/95 217/95 <0.3 1400 +/-60 <6.9 SA-MLK-11 F3 216/95 217/95 <0.2 1400 +/-90 <3.9 SA-MLK-2F7 3/5/95 3/6/95 <0.2 1300 +/-90 <2.5 SA-MLK-11 F3 3/5/95 3/6/95 <0.3 1400 +/-60 <3.3 SA-MLK-14F4 - 3/5/95 3/6/95 <0.3 1300 +/-80 18 +/-6 SA-MLK-3G1 (C) 3/6/95 317/95 <0.3 1400 +/-70 <3.6 SA-MLK-2F7 4/2195 4/3/95 <0.2 1400 +/-90 <3.7 SA-MLK-11 F3 4/3/95 4/4/95 <0.3 1300 +/-80 <4.1 SA-MLK-14F4 4/3/95 4/4/95 <o.3 1200 +/-90 <3.3 SA-MLK-3G1 (C) 4/2195 4/3/95 <0.2- 1300 +/-60 7+/-3 SA-MLK-2F7 4/16/95 4/17/95 <0.3 1300 +/-70 <3.9 SA-MLK-11 F3 4/16/95 4/17/95 <0.2 1400 +/-110 <3.2 SA-MLK-14F4 4/17/95 4/18/95 <0.3" 1400 +/-90 <4.1 SA-MLK-3G1 (C) 4/16/95 4/17/95 <0.4 1300 +/-80 <3.5 SA-MLK-2F7 517/95 5/8/95 <0.2 1300 +/-90 <3.5 SA-MLK-11 F3 517/95 5/8/95 <0.1 1300 +/-60 <3.5 SA-MLK-14F4 5/8/95 5/9/95 <0.2 1400 +/-100 <4.2 SA-MLK-3G1 (C) 517/95 5/8/95 <0.2 1300 +/-60 <7.5 SA-MLK-2F7 5/22195 5/23/95 <0.4 1300 +/-80 <3.4 SA-MLK-11 F3 5/22195 5/23/95 <0.2 1400 +/-70 <4 SA-MLK-14F4 5/22195 5/23/95 <0.2 1300 +/-90 <8.1 SA-MLK-3G1 (C) 5/21/95 5/22195 <0.2 1300 +/-100 <9.4

_SA-MLK-2F7 6/5/95 6/6/95 - <0.3 1300 +/-80 <4.9 SA-MLK-11 F3 6/5/95 6/6/95 <0.1 1400 +/-80 <9.2 SA-MLK-14F4 6/5/95 6/6/95 <0.1 1400 +/-70 <3.8 SA-MLK-3G1 (C) 6/4/95 6/5/95 <0.1 1400 +/-60 <2.5 SA-MLK-2F7 6/19/95 6/20/95 <0.2 1200 +/-110 <2.2 SA-MLK-11 F3 6/18/95 6/19/95 <0.1 1300 +/-70 <3.9 SA~MLK-14F4 6/19/95 6/20/95 <0.2 1500 +/-100 <3.4 SA-MLK-3G1 (C) 6/19/95 6/20/95 <0.3 1300 +/-80 <5.3 SA-MLK-2F7 7/9/95 7/10/95 <0.4 1200 +/-80 <4.6 SA-MLK-3G1 (C) 7/9/95 7/10/95 <0.3 1100 +/-80 <6.9 SA-MLK-11 F3 7/10/95 7/11/95 <0.2 1400 +/-70 <4.5 SA-MLK-14F4 7/10/95 7/11/95 - <0.1 1300 +/-90 <4.8 SA-MLK-2F7 7/23/95 7/24/95 <0.2 1300 +/-80 <10.5 SA-MLK-14F4 7/23/95 7/24/95 <0.7 1300 +/ <3.6 SA-MLK-3G1 (C) 7/23/95 7/24/95 <0.3 1300 +/-100 <5.4 SA-MLK-11F3 7124/95 7/25/95 <0.2 1300 +/-60 <3.5 86

TABLE C-7 1995 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING PERIOD <-GAMMA EMITTERS->

STATION ID START STOP 1-131 K-40 RA-NAT SA-MLK-2F7 8/6/95 817/95 <0.1

• 1200 +/-80 <8.6 SA-MLK-3G1 (C) 8/6/95 817/95 <0.4 1300 +/-100 <4.2 SA-MLK-11 F3 817/95 8/8/95 <0.2 1300 +/-60 <3.4 SA-MLK-14F4 817/95 8/8/95 <0.1 1400 +/-80 <15.1 SA-MLK-2F7 8/20/95 8/21/95 <0.3 1200 +/-60 <3.5 SA-MLK-3G1 (C) 8/20/95 8/21/95 <0.2 1300 +/-80 <4.1 SA-MLK-14F4 8/20/95 8/21/95 <0.1 1300 +/-80 <3.8 SA-MLK-11 F3 8/21/95 8/22/95 <0.3 1500 +/-70 <3.8 SA-MLK-2F7 9/5/95 9/6/95 <0.3 1300 +/-90 <4.1 SA-MLK-3G1 (C) 9/4/95 9/5/95 <0.2 1300 +/-110 <3.3 SA-MLK-14F4 9/5/95 9/6/95 <0.2 1300 +/-90 <4 SA-MLK-11 F3 9/5/95 9/6/95 <0.1 1300 +/-60 8 +/-3 SA-MLK-2F7 9/17/95 9/18/95 <0.2 1300 +/-70 <3 SA-MLK-3G1 (C) 9/17/95 9/18/95 <0.2 1300 +/-100 <4.3 SA-MLK-14F4 9/17/95 9/18/95 <0.2 1300 +/-80 <7.2 SA-MLK-11 F3 9/18/95 9/19/95 <0.2 1300 +/-60 <2.8 SA-MLK-2F7 10/1/95 10/2/95 <0.2 1300 +/-60 9+/-3 SA-MLK-3G1 (C) 10/1/95 10/2/95 <0.2 1300 +/-80 <12.5 SA-MLK-11 F3 10/2/95 10/3/95 <0.2 1400 +/-70 <3.8 SA-MLK-14F4 10/2/95 10/3/95 <0.2 1200 +/-80 <5.1 SA-MLK-2F7 10/15/95 . 10/16/95 <0.3 1200 +/-60 10+/-4 SA-MLK-3G1 (C) 10115/95 10/16/95 <0.2 1200 +/-70 <3.4 SA-MLK-11 F3 10/16/95 10117/95 <0.2 1200 +/-80 <4.2 SA-MLK-14F4 10/16/95 10/17/95 <0.2 1300 +/-80 <6.1 SA-MLK-2F7 11/5/95 11/6/95 <0.2 1200 +/-90 <2.7 SA-MLK-3G1 (C) 11/5/95 11/6/95 <0.2 1300 +/-100 <4.3 SA-MLK-14F4 11/5/95 11/6/95 <0.2 1300+/-80 <3.8 SA-MLK-11F3 11/5/95 11/6/95 <0.1 1300 +/-70 <5.2 SA-MLK-2F7 11/20/95 11/21/95 <0.3 1400 +/-90 <4.1 SA-MLK-3G1 (C) 11/20/95 11/21/95 <0.3 1400 +/-100 <3.9 SA-MLK-14F4 11/20/95 11/21/95 <0.2 1300 +/-80 <4 SA-MLK-11F3 11/20/95 11/21/95 <0.2 1300 +/-70 <9.3 SA-MLK-2F7 12/4/95 12/5/95 <0.3 1200 +/-80 <9.1 SA-MLK-11 F3 12/4/95 . 12/5/95 <0.2 1300 +/-60 <3.2 SA-MLK-14F4 12/4/95 12/5/95 <0.3 1300 +/-90 <5.3 SA-MLK-3G1 (C) 12/4/95 12/5/95 <0.3 1300 +/-100 <4.2 AVERAGE 1300 +/-100

• lodine-131 results are corrected for decay to midpoint of collection period & analyzed to a sensitivity of 1.0 pCi/L.

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-26 .

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

(C) Control Station 87

TABLE C-8 1995 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-11 F3 7/10-11/95 <0.9 <0.8 SA-MLK-14F4 7/10-11/95 <1 1.2+/-0.4 SA-MLK-2F7 7/09-10/95 <1 1.2+/-0.4 SA-MLK-3G1 (C) 7/09-10/95 <1 <0.9 AVERAGE 1.2+/-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.

88

TABLE C-9 1995 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-3E1 (C) 1/30/95 1.3+/-0.9 9.9+/-0.8 9+/-1 <170 SA-WWA-3E1 (C) 2/27/95 1.9+/-1 10+/-0.8 9.7+/-1 <110 SA-WWA-3E1 (C) 3/27/95 3.4+/-1.2 10+/-0.8 9+/-0.9 <110 SA-WWA-3E1 (C) 4/24/95 2.5+/-1 9.7+/-0.8 8.5+/-0.8 <110 SA-WWA-3E1 (C) 5/30/95 2.6+/-1.1 9.9+/-0.8 13+/-1.3 <120 SA-WWA-3E1 (C) 6/26/95 1.7+/-0.9 9.5+/-0.8 9.2+/-0.9 <120 SA-WWA-3E1 (C) 7/31/95 2.4+/-0.9 9.8+/-0.8 9.7+/-1 <120 SA-WWA-3E1 (C) 8/28/95 1.3+/-0.5 13+/-0.9 8.7+/-0.9 <130

_/

SA-WWA-3E1 (C) 9/25/95 1.3+/-0.9 10+/-0.8 8.7+/-0.9 <130 SA-WWA-3E1 (C) 10/31/95 2.9+/-1.1 9.8+/-0.8 9+/-0.9 <120 SA-WWA-3E1 (C) 11/27/95 2+/-1.1 11+/-0.8 9.7+/-1 <'120 SA-WWA-3E1 (C) \

12/26/95 2.2+/-1.3 9.5+/-0.8 8.4+/-0.8 <130 AVERAGE SA-WWA-3E1 (C) 2.1+/-1.3 10+/-2 9.4+/-2.3

. ( C ) Control Station 89

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-26.

(C) Con!rol Station 90

TABLE C-11 1995 CONCENTRATIONS OF STRONTIUM-89* AND 90*

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

<--STRONTIUM-->

SAMPLING PERIOD STATION ID START STOP Sr-89 Sr-90 SA-WWA-3E1 1/30/95 3/27/95 <0.5 <0.4 SA-WWA-3E1 4/24/95 6/26/95 <0.6 <0.4 SA-WWA-3E1 7/31/95 9/25/95 <0.5 <0.4 SA-WWA-3E1 10/31/95 12/26/95 <0.5 <0.4

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

Control Station.

91

TABLE C-12

• 1995 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER SAMPLING PERIOD Results in Units of pCi/L +/- 2 sigma GROSS GROSS TYPE START STOP ALPHA BETA K-40 TRITIUM RAW 1/1/95 1/31/95 1.6+/-0.6 4.3+/-0.6 2.4+/-0.2 <120 TREATED 1/1/95 1/31/95 0.7+/-0.5 3.1+/-0.5 2.2+/-0.2 <120 RAW 2/1/95 2128/95 1.7+/-0.7 4.4+/-0.6 2.2+/-0.2 <120 TREATED 211/95 2128/95 0.8+/-0.6 2.9+/-0.5 2+/-0.2 <120 RAW 3/1195 3/31/95 1+/-0.5 3.4+/-0.5 2+/-0.2 <120 TREATED 3/1/95 3/31/95 1.2+/-0.7 - 3+/-0.5 1.9+/-0.2 <120 RAW 4/1/95 4/30/95 1+/-0.5 2.8+/-0.5 1.8+/-0.2 <120 TREATED 4/1/95 4/30/95 0.7+/-0.5 2.5+/-0.5 1.8+/-0.2 <120 RAW 5/1/95 5/31/95 0.8+/-0.6 3.2+/-0.5 2.5+/-0.2 <120 TREATED 5/1/95 5/31/95 1.2+/-0.8 2.7+/-0.5 2.5+/-0.3 <120 RAW 6/1/95 6/30/95 0.7+/-0.5 *2.5+/-0.4 1.2+/-0.1 <120 TREATED 6/1/95. 6/30/95 <0.7 2.1+/-0.4 1.2+/-0.1 <120 RAW 7/1/95 7/31/95 0.6+/-0.4 2.6+/-0.5 1.6+/-0.2 <120 TREATED 7/1/95 7/31/95 0.9+/-0.6 2.2+/-0.4 1.5+/-0.2 <120 RAW 8/1/95 8/31/95 0.9+/-0.4 2.7+/-0.5 1.5+/-0.2 <130 TREATED 8/1/95 8/31/95 1+/-0.6 2.1+/-0.5 1.6+/-0.2 <130 RAW 9/1/95 9/30/95 <0.6 1.9+/-0.4 1.4+/-0.1 120+/-80 TREATED 9/1/95 9/30/95 <0.9 2.3+/-0.5 1.5+/-0.1 <120 RAW 10/1/95 10/31/95 1+/-0.5 3.1+/-0.5 1.6+/-0.2 <130 TREATED 10/1/95 10/31/95 <0.8 2.5+/-0.5 1.7+/-0.2 <130 RAW 11/1/95 11/30/95 1.8+/-0.7 4.2+/-0.5 2.8+/-0.3 <120 TREATED 11/1/95 11/30/95 1.5+/-0.8 3.3+/-0.5 2.7+/-0.3 <120 RAW 12/1/95 12/31/95 1.3+/-0.7 4.1+/-0.5 2.4+/-0.2 <130 TREATED 1211/95 12/31/95 <1.1 3.4+/-0.5 2.3+/-0.2 <130 AVERAGE RAW 1.1+/-0.8 3.3+/-1.6 2+/-1 TREATED 1+/-0.5 2.7+/-0.9 1.9+/-0.9 GRAND AVERAGE 1+/-0.7 92 3+/-1.4 1.9+/-0.9

TABLE C-13 .

• 1995 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**

IN RAW AND TREATED POTABLE WATER SAMPLING PERIOD Results in Units of pCi/L +/- 2 sigma

<-GAMMA EMITTERS->

.1YPE START STOP 1-131 K-40 RA-NAT RAW 1/1/95 1/31/95 <0.2 <13 7.4+/-1.9 TREATED 1/1/95 1/31/95 <0.6 <13 <2.7 RAW 2/1/95 2/28/95 <0.2 <15 5.7+/-2 TREATED 2/1/95 2128/95 <0.2 54+/-20 9.4+/-3.7 RAW 3/1/95 3/31/95 <0.3 <23 6.8+/-2 TREATED 3/1/95 3/31/95 <0.4 <22 <3 RAW 4/1/95 4/30/95 <0.3 65+/-23 <2.5 TREATED 4/1/95 4/30/95 <0.2 <15 8.5+/-3.2 RAW 5/1/95 5/31/95 <0.2 47+/-22 4.5+/-1.9 TREATED 5/1/95 5/31/95 <0.2 43+/-18 <2.3 RAW 6/1/95 6/30/95 <0.4 <21 <3.1 TREATED 6/1/95 6/30/95 <0.4 57+/-21 <3.9

'RAW 7/1/95 7/30/95 <0.3 <16 <2.5 TREATED 7/1/95 7/30/95 <0.2 <46 <5 RAW 8/1/95 8/31/95 <0.2 66+/-19 . 6.6+/-2.8 TREATED 8/1/95 8/31/95 <0.2 <14 6.2+/-1.8 RAW 9/1/95 9/30/95 <0.2 49+/-19 8.8+/-2.6 TREATED 9/1/95 9/30/95 <0.3 69+/-30 6+/-3 RAW 10/1/95 10/31/95 <0.3 26+/-12 <2.3 TREATED 10/1/95 10/31/95 <0.2 <42 <3 RAW 11/1/95 11/30/95  :<0.2 <17 <8 TREATED 11/1/95 11/30/95 <0.3 <16 13+/-2 RAW 12/1/95 12131/95 <0.2 <14 <2.1 TREATED 12/1/95 12131/95 <0.4 48+/-21 <2.7 AVERAGE RAW 5+/-5 TREATED GRAND AVERAGE lodine-131 analyzed to a sensitivity of 1.0 pCi/L.

All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-26.

(C) Control Station 93

TABLE C-14 1995 CONCENTRATIONS OF STRONTIUM-89* AND 90*

IN QUARTERLY COMPOSITES OF RAW AND TREATED POTABLE WATER Results in Units of pCi/L STATION ID: SA-PWR/T-2F3

< - - STRONTIUM ----->

SAMPLING PERIOD TYPE START STOP Sr-89 Sr-90 RAW 1/1/95 3/31/95 <0.6 <0.4 TREATED 1/1/95 3/31/95 <0.6 <0.4 RAW 4/01/95 6/30/95 <0.6 <0.4 TREATED 4/01/95 6/30/95 . <0.7 <0~5 RAW 7/1/95 9/30/95 <0.5 <0.4 TREATED 7/1/95 9/30/95 <0.5 <0.4 RAW 10/1/95 12/31/95 <0.6 <0.5 TREATED 10/1/95 12131/95 <0.5 <0.5

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

94

TABLE C-15 1995 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in Units of pCi/kg (>Net) +/- 2 sigma SAMPLING GAMMA EMITTERS STATION ID DATE SAMPLE TYPE K-40 SA-FPV-3F4 5/23/95 Asparagus 1780+/-177 SA-FPL-1G1 (C) 7/18/95 Cabbage 2180+/-114 SA-FPL-3F4 7/18/95 Cabbage 2990+/-124 SA-FPL-3H5 (C) 7/18/95 Cabbage 2270+/-106 AVERAGE 2480+/-890 SA-FPV-14F3 7/24/95 Com 2370+/-175 SA-FPV-1G1 (C) 8/21/95 Com 2400+/-229 SA-FPV-2F4 7/18/95 Com 2840+/-184 SA-FPV-3F4 7/18/95 Com 2620+/-189 SA-FPV-3H5 (C) 7/18/95 Com 2210+/-157 AVERAGE 2490+/-490

• SA-FPV-1G1 (C)

SA-FPV-2F4 SA-FPV-3F4 SA-FPV-3H5 (C) 7/18/95 8/21/95 7/18/95 7/18/95 Peppers Peppers Peppers Peppers 1730+/-207 2760+/-250 1810+/-155 2370+/-183 AVERAGE 2170+/-970 SA-FPV-14F3 7/24/95 Tomatoes 1720+/-185 SA-FPV-1G1 (C) 7/18/95 Tomatoes 2800+/-239 SA-FPV-2F4 8/21/95 Tomatoes 2830+/-269 SA-FPV-3F4 7/18/95 Tomatoes 3160+/-192 SA-FPV-3H5 (C) 7/18/95 Tomatoes 1790+/-170 AVERAGE 2460+/-1320 I

./

GRAND AVERAGE 2370+/-940

.II other gamma emitters sea~ched for were <LLD; typical LLDs are given in Table C-26.

95

TABLE C-16 1995 CONCENTRATIONS OF GAMMA EMITTERS* INBEEF "* AND GAME Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING GAMMA EMITTERS STATION ID DATE SAMPLE TYPE K-40 SA-FPB~3E1 4/24/95 Beef 2490+/-210 SA-GAM-1101 (C) 2/21-28/95 Muskrat 2630+/-170 SA-GAM-3E1 1/28-2/4/95 Muskrat 3010+/-220 AVERAGE Muskrat 2710+/-540

• All other gamma emitters searched for were <l:.LD; typical LLDs are given in Table C-26.

• • Although not required by Technical Specifications, beef samples are normally collected twice each year. However, due to uncertain availability of the sample, only one beef sample was obtained in 1995.

96

TABLE C-17

~

1995 CONCENTRATIONS OF GAMMA EMITIERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING <---*-GAMMA EMITTERS---->

STATION ID DATE SAMPLE TYPE Be-7 K-40 RA-NAT SA-VGT-3G1 9/4/95 Silage 624+/-85 5900+/-290 <23.8 SA-VGT-11 F3 9/5/95 Silage 908+/-137 6920+/-456 40+/-19 SA-VGT-14F4 9/5/95 Silage <71 5800+/-306 <14 SA-VGT-2F7 10/1/95 Silage 770+/-113 2070+/-234 31+/-15 AVERAGE 590+/-730 5170+/-4260 SA-VGT-3G1 10/30/95 Soybeans <27 13300+/-263 <8.2 SA-VGT-11F3 10/31/95 Soybeans <27 14500+/-254 <8.5 SA-VGT-2F7 11/6/95 Soybeans <28 5060+/-110 <3.1 SA-VGT-14F4 11/19/95 Soybeans <29 13900+/-307 <22 AVERAGE 11700+/-8890

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-26.

Location 3G1 is the Control Station.

97

TABLE-18 1995 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SOIL Results in Units of pCi/kg (dry) +/- 2 sigma SAMPLING STATION ID DATE Sr-90 K-40 Cs-137 RANAT Th-232 SA-SOL-682 10/11/95 <16 7900+/-342 58+/-12 535+/-26 575+/-61 SA-SOL-10D1 10/10/95 63+/-11 9780+/-355 416+/-19 946+/-28 952+/-66 SA-SOL-16E1 10/10/95 45+/-10 14100+/-386 143+/-16 1060+/-32 1230+/-87 SA-SOL-1F1 10/11/95 47+/-8 5460+/-230 1670+/-32 478+/-23 438+/-46 SA-SOL-2F4 10/10/95 40+/-8 7960+/-350 366+/-26 864+/-34 775+/-78 SA-SOL-2F7 10/10/95 37+/-8 11000+/-525 141+/-19 1150+/-39 1080+/-106 SA-SOL-5F1 10/10/95 42+/-9 4750+/-221 591+/-20 676+/-33 494+/-37 SA-SOL-11F3 10/10/95 37+/-9 12800+/-523 195+/-24 1290+/-65 1270+/-119

\0 00 SA-SOL-14F4 10/10/95 35+/-9 14800+/-479 116+/-18 1090+/-50 1220+/-84 SA-SOL-3G1 (C) 10/10/95 30+/-8 8670+/-328 179+/-14 930+/-27 869+/-62 AVERAGE 40+/-20 9700+/-7000 390+/-960 900+/-500 890+/-630

• All other gamma emitters searched for were <LLD; typical L~Ds are given in Table C-26.

(C) Control Station

• 1995 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

<------------------~------------------------------- STAT I0 N ID ------------------------------------------------7->

SAMPLING SA-SWA-11A1 SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1F2 SA-SWA-7E1 AVERAGE DATE (Control)

January <1.3 <1.2 <1.3 <1.2 <2.4 February <2 <2.1 <2 <2 <2.1 March <1.9 <4.8 <2.5 <2.3 <2.3 April <3 <2.3 <2.2 <2 <1.9 May <2.3 <2.2 <2 <2.2 <2.2 June <2 <2.1 3.4+/-2 <2.2 <2.1

. \0

\0 July 2.9+/-1.6 2.8+/-1.9 <1.5 <1.5 <1.6 August <3.1 <2.9 <2.7 <2.7 <2.7 September 1.8+/-1.1 1.5+/-1.1 <1.4 1.7+/-1.2 1.6+/-1.1 1.6+/-0.4 October <2.4 <2.2 <2.2 <2 <2.4 November 2.7+/-1.3 2.6+/-1.2 2.3+/-1.2 2.2+/-1.2 1.8+/-1.1 2.3+/-0.7 December <2.6 <2.6 <2.6 <2.4 <2.5

C-20 1995 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma

<-------------------------------------------------- STAT I0 N ID -------------------------------------------------->

SAMPLING SA-SWA..:11A1 SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1F2 SA-SWA-7E1 AVERAGE DATE (Control)

January 78+/-6 39+/-4 34+/-4 26+/-4 83+/-7 52+/-52 February 65+/-6 68+/-6 51+/-5 20+/-3 80+/-7 57+/-46 March 75+/-6 39+/-4 40+/-4 14+/-3 64+/-6 46+/-47 April 45+/-5 40+/-4 21+/-3 16+/-3 75+/-6 39+/-47 May 122+/-9 80+/-7 62+/-6 45+/-5 144+/-11 91+/-83

...... June 93+/-8 83+/-7 37+/-5 47+/-5 108+/-9 74+/-61 0

0 July 77+/-7 70+/-7 47+/-5 45+/-5 120+/-10 72+/-60 August 112+/-8 77+/-7 73+/-6 65+/-6 138+/-10 93+/-62 September '132+/-11 113+/-9 92+/-8 80+/-7 146+/-11 113+/-55 October 141+/-10 121+/-9 92+/-8 99+/-8 184+/-12 127+/-74 November 55+/-6 26+/-4 18+/-3 14+/-3 73+/-7 37+/-51 December 51+/-5 33+/-4 20+/-3 26+/-4 54+/-6 37+/-31 AVERAGE 87+/-65 66+/-63 49+/-52 41+/-56 106+/-81 GRAND AVERAGE 70+/-78

C-21

• 1995 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING < GAMMA EMITTERS >

STATION ID DATE .K-40 RA-NAT Th-232 SA-SWA-11A1 1/9/95 70+/ 8.7+/-2.5 <3.5 SA-SWA-12C1 (C) 1/9/95 75+/-19 <2.7 <4.3 SA-SWA-16F1 1/9/95 38+/-15 <5 <2.4 SA-SWA-1F2 1/9/95 50+/-19 <2.8 <5 SA-SWA-7E1 1/9/95 132+/-23 <5 <5.6 SA-SWA-11A1 2/9/95 117+/-19 <2.5 <3.7 SA-SWA-12C1 (C) 2/9/95 56+/-17 <5.6 <3.4 SA-SWA-16F1 2/9/95 86+/-20 <8.4 <12 SA-SWA-1F2 2/9/95 70+/-23 <2.5 - <4.5 SA-SWA-7E1 2/9/95 <27 <4.1 <3.7 SA-SWA-11A1 3/11/95 136+/-25 <2.7 <4.8 SA-SWA-12C1 (C) 3/11/95 <25 5.6+/-1.5 11.4+/-3.8

. SA-SWA-16F1 3/11/95 72+/-15 <2.3 <2.8 SA-SWA-1F2 3/11/95 <18 <2.1 <4.9 SA-SWA-7E1 3/11/95 59+/-20 <3.3 <12.1

• sA-SWA-11A1 4/7/95 40+/-19 7+/-1.9 <9.6 SA-SWA-12C1 (C) 4/7/95 33+/-14 4.3+/-1.6 <6.5 SA-SWA-16F1 417/95 <22 <2.9 <9.8 SA-SWA-1F2 4/7/95 65+/-23 <2 <4.9 SA-SWA-7E1 417/95 119+/-26 <2.7 <4 SA-SWA-11A1 5/11/95 151+/-31 <2.2 <3.1 SA-SWA-12C1 (C) 5/11/95 76+/-18 6.3+/-1.8 <3.1 SA-SWA-16F1 5/11/95 111+/-21 <2.7 <3.4 SA-SWA-1F2 5/11/95 <45 <3.2 <4.2 SA-SWA-7E1 5111/95 169+/-30 6.2+/-2.6 <5.2 SA-SWA:11A1 6/8/95 85+/-20 <4.5 <5.8 SA-SWA-12C1 (C) 6/8/95 69+/-27 <3.2 <6.8 SA-SWA-16F1 6/8/95 69+/-15 <2.7 <4 SA-SWA-1F2 6/8/95 99+/-21 <2.2 <6.6 SA-SWA-7E1 6/8/95 103+/-22 <5.7 8.4+/-3 SA-SWA-11A1 7/6/95 154+/-32 <3 <4.5 SA-SWA-12C1 (C) 7/6/95 67+/-17 7.2+/-3.4 7.2+/-3 SA-SWA-16F1 7/6/95 102+/-21 <2.7 <3.1 SA-SWA-1F2 7/6/95 58+/-28 <2.7 <6.3 SA-SWA-7E1 7/6/95 130+/-20 6.1+/-3 <2.7 101

C-21 1995 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING < ,_ _ _ _ GAMMA EMITTERS----->

STATION ID DATE K-40 RA-NAT Th-232 SA-SWA-11A1 8/10/95 99+/-17 7.8+/-2.1 <3.8 SA-SWA-12C1 (C) 8/10/95 92+/-19 <2.5 <7.1 SA-SWA-16F1 8/10/95 54+/-18 <5.4 <8.2 SA-SWA-1F2 8/10/95 98+/-21 <2.9 <5 SA-SWA-7E1 8/10/95 218+/-44 <3.1 <8.4 SA-SWA-11A1 9fi/95 167+/-25 <2.5 <5.5 SA-SWA-12C1 (C) 9fi/95 130+/-23 <2.6 <2.8 SA-SWA-16F1 9fi/95 74+/-28 4.6+/-1.6 9.8+/-4.2 SA-SWA-1F2 9nt95 69+/-19 4.3+/-2 <3.2 SA-SWA-7E1 9nt95 167+/-30 <3.2 <3 SA-SWA-11A1 10/6/95 93+/-17 7.1+/-1.9 <7.4 SA-SWA-12C1 (C) 10/6/95 97+/-18 6.3+/-2.3 <6.5 SA-SWA-16F1 10/6/95 63+/-26 <2.9 <3.8 SA-SWA-1F2 10/6/95 128+/-24 <2.9 <5 SA-SWA-7E1 10/6/95 174+/-32 <4.1 <5.5 SA-SWA-11A1 11/10/95 47+/-20 6.7+/-2.4 8.5+/-4 SA-SWA-12C1 (C) 11/10/95 57+/-18 <3 <3 SA-SWA-16F1 11/10/95 48+/-19 <2.8 <5.3 SA-SWA-1F2 11/10/95 71+/-22 5.8+/-2.2 <5 SA-SWA-7E1 11/10/95 106+/-26 <4.4 <6.4 SA-SWA-11A1 12nt95 83+/-18 <3 <6.1 SA-SWA-12C1 (C) 12nt95 68+/-16 8+/-2.5 <2.9 SA-SWA-16F1 12nt95 <26 <3.2 <13.3 SA-SWA-1F2 12nt95 84+/-21 5.6+/-2.4 <5.1 SA-SWA-7E1 12nt95 69+/-19 7.1+/-2.4 9.4+/-3.3 AVERAGE 86+/-86

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-26.

(C) Control Station 102

1995 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER

}

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

/

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

SAMPLING SA-SWA-11A1 SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1F2 SA-SWA-7E1 AVERAGE PERIOD (Control) 1/9/95 to <120 <120 160+/-70 130+/-70 <120 3/11/95 417195 to <120 <120 <120 <120 <120 6/8/95 I-'

0 w 716195 to 490+/-80 <120 <120 140+/-70 130+/-70 200+/-330 917/95 10/6/95 to <120 <130 <120 <130 120+/-80 12/7/95

-- - _ _ _ _ _ _ _1L:__*------------------------~

TABLE C-23 1995 STRONTIUM-89 90*, TRITIUM AND GAMMA EMITTERS** IN EDIBLE FISH Results in Units of pCi/kg (wet) +/- 2 sigma (Strontium in bone is reported in pCi/kg (dry))

STRONTIUM STRONTIUM ***

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

SAMPLING AQUEOUS (FLESH)

STATION ID PERIOD Sr-89 Sr-90 Sr-89 Sr-90 FRACTION K-40 Cs-137 RA-NAT SA-ESF-7E1 5/4-5/95 <39 137+/-12 <22 <13 <820 3410+/-207 15+/-6 <20 SA-ESF-11A1 5/4-5/95 <35 76+/-10 <20 <12 <820 2900+/-163 14+/-6 26+/-10 SA-ESF-12C1 (C) 5/4-5/95 <46 176+/-14 <23 <15 <820 2870+/-224 <6 <15 AVERAGE 130+/-100 3060+/-610 12+/-10 0

+:'- (

SA-ESF-7E1 9/12-16/95 <25 <15 <23 <16 <1600 3520+/-232 <5.6 <9 SA-ESF-11A1 9/12-16/95 <25 <16 <21 <15 '<1300 3520+/-280 <11 <9.3 SA-ESF-12C1 (C) 9112-16/95 <26 <17 <21 <15 <1600 3890+/-187 <4.8 <22 AVERAGE 3640+/-430 GRAND AVERAGE 3350+/-790

• 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-26.

• • • Tritium results are reported by Yankee Atomic Electric Laboratory. Results are reported as MDC.

(C) Control Station

• 1995 CONCENTRATIONS OF STRONTIUM-89 90'\ TRITIUM AND GAMMA EMITTERS** IN CRABS Results in Units of pCi/kg (wet) +/- 2 sigma (Strontium in shell analyses are reported in pCi/kg (dry))

STRONTIUM STRONTIUM ***

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

SAMPLING AQUEOUS (FLESH)

STATION ID PERIOD Sr-89 Sr-90 Sr-89 Sr-90 FRACTION K-40 RA-NAT

\

SA-ECH-11A1 6/28/95 <34 57+/-10 <26 <19 <440 3070+/-230 <12 SA-ECH-12C1 (C) 6/28/95 <36 65+/-11 <27 <19 <430 3240+/-294 <13 AVERAGE 60+/-10 3160+/-240 I-'

0 SA-ECH-11A1 9/25/95 <32 94+/-10 <20 <16 <1500 2560+/-159 31+/-11 Lr!

SA-ECH-12C1 (C) 9/24/95 <42 221+/-15 <20 <17 <1600 2970+/-193 <26 AVERAGE 160+/-180 2770+/-580 GRAND AVERAGE 110+/-150 2960+/-580

• 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-26.

• • • Tritium results are reported by Yankee Atomic Electric Laboratory. Results are reported as MDC.

(C) Control Station '

TABLE-25 1995 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 Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 RANAT Th-232 Zn-65 SA-ESS-11A1 5/26/95 <16 <52 5030+/-223 <7.8 21+/-7 40+/-8 26+/-11 32+/-10 306+/-16 287+/-39 <9.4 SA-ESS-15A1 5/26/95 <20 <153 16900+/-586 <31 <11 <13 71+/-22 198+/-26 609+/-46 1040+/-10 <57 SA-ESS-16A1 5/26/95 <20 <62 5210+/-260 <18 <20 <21 <10 <19 700+/-26 529+/-51 <17 SA-ESS-12C1 (C) 5/26/95 <18 <73 16500+/-494 <8.9 <14 <14 <13 <9.8 675+/-30 820+/-70 <13 SA-ESS-7E1 5/26/95 <18 <63 17500+/-405 <8.2 <8.3 112+/-16 <13/ 171+/-14 801+/-31 997+/-82 <14 SA-ESS-16F1 5/26/95 <20 <70 16100+/-446 <26 <10 <7.2 44+/-11 <9.5 469+/-33 958+/-76 <41 AVERAGE 12900+/-12000 590+/-360 770+/-600 I-' SA-ESS-11A1 11/17/95 <16 <77 8000+/-234 <16 <20 <8 <9 <11 897+/-21 826+/-49 <5.6 0 SA-ESS-15A 1 11/17/95 <18 507+/-110 16200+/-393 57+/-16 40+/-18 37+/-12 <11 166+/-15 713+/-26 936+/-63 <37

°' SA-ESS-16A1 11/17/95 <17 <59 5410+/-205 27+/-7 <14 45+/-8 <6.7 18+/-7 666+/-17 598+/-37 37+/-16 SA-ESS-12C1(C) 11/16/95 <16 <90 18300+/-456 <8.8 <9.9 <8.8 <13 <9.2 614+/-24 911+/-86 <43 SA-ESS-7E1 11/16/95 <16 <105 14900+/-463 <12 <13 <16 <15 49+/-13 791+/-32 909+/-98 <18 SA-ESS-16F1 11/16/95 <18 <77 15700+/-409 <14 <9.1 <10 <11 <14 559+/-37 814+/-53 <37 AVERAGE 13100+/-10000 710+/-250 830+/-250 GRAND AVERAGE 13000+/-11000 650+/-320 800+/-440

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-26.

(C) Control Station

TABLE C-26 1995 MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <----------AIR------------> Z---------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: lOOML 13 FILTE.RS 3.5.LITER 100 ML 3.5 LITER 100 ML COUNT TIME: 120 MINS 500 MINS 10000 MIN 1000 MINS 500 MINS 1000 MINS DELAY TO 2 DAYS 5 DAYS 7 DAYS 3 DAYS 2 DAYS 2 DAYS COUNT:

NUCLIDES BE-7 6.8 10 22 NA-22 0.45 5 4.5 K-40 7.1 35 120 CR-51 2.9 10 22 MN-54 0.32 1.2 3.4 C0-58 -0.33 1. 0 2.9 FE-59 0.79 2.5 7.2 C0-60 0.36 1.6 4.0

-65 0.69 2.5 8.6 B-95 2.0 2.0 3.8 550 10 30 RU-103 0.33 1. 6 2.5 RU-106 2.9 10 22 AG-llOM 0.55 2.0 3.4 SB-125 0.77 4.0 8.2 TE-129M 120 40 70 I-131 13.0 0.98 2.5 3.0 0.48 TE-132 - 41 7 3.9 BA-133 3.7 2.6 0.55 5.0 CS-134 -::- 0.39 1. 8 3.0 CS-136 0.56 2.2 3.3 CS-137 0.28 1. 6 3.2 BALA-140 2.3 8 10 CE-141 0.31 2.3 3.9 CE-144 0.8 7.0 10 RA-NAT 0.7 7.4 6.6 TH-232 1.2 7.1 12 107

TABLE C-26 (cont'd)

.1995 PSE&G MAPLEWOOD TESTING SERVICES LLDs FOR GAMMA SPECTROMETRY SAMPLE TYPE: <------FOOD PRODUCTS-------> FOOD & BEEF FISH SEDIMENT GREEN CHOP & GAME SHELLFISH & SOIL ACTIVITY: pCi/KG WET pCi/kg WET pCi/kg WET pCi/kg _pCi/kg DRY GEOMETRY: lOOml 500 ml 3.5 LITER 500 ml WET 500 ml COUNT TIME: 1000 MINS 500 MINS 500 MINS 500 MINS 500 ml 500 MINS DELAY TO 10 DAYS 3 DAYS 7 DAYS 5 DAYS 500 MINS 30 DAYS COUNT: 5.., DAYS NUCLIDES BK-7 0.99 40 45 44 44 90 NA-22 2.1 8.0 8 6.9 6.9 30 K-40 32 70 50 70 70 70 CR-51 9.2 30 30 41 41 125 MN-54 1.2 4.8 7 6.9 6.9 28 C0-58 1. 8 8.0 10 5.3 5.3 15 FE-59 3.6 14 15 10 10 46 C0-60 2.3 7.6 12 6 6 32 ZN-65 3.6 8 18 20 20 42 NB-95 15 15 12 15 15 40 M0-99 96 95 130 400 400 650000 RU-103 1. 0 5.0 7 4.9 4.9 24 RU-106 12 38 30 38 38 120 AG-110M 2.2 8.7 15 12 12 21 SB-125 2.8 14 25 12 12 36 TE-129M 4.7 160 225 250 250 600 I-131 2 6.0 12 11. 0 11. 0 185 TE-1;32 4.4 6.0 40 60 60 4000 BA-133 7.5 14.0 12 120 120 40 CS-134 0.96 .6.5 10 5.7 5.7 22 CS-136 1.5 6.1 12 7.5 7.5 46 CS-137 1.4 6.7 12 12 12 20 BALA-140 2.0 12.0 15 35 35 160 CE-141 1. 0 5.1 7.0 5.2 5.2 26 CE-144 4.2 20 22 18 18 52 RA-NAT 2.3 15 *15 20 20 30 TH-232 6.1 31 30 29 29 30 108

• APPENDIX D SYNOPSES OF ANALYTICAL PROCEDURES 109

APPENDIX D SYNOPSES OF ANALYTICAL PROCEDURES Appendix D presents a synopsis-of the analytical procedures utilized by the PSE&G Maplewood Testing Serv~ces and contract laboratories for analyzing the 1995 Radiologicar Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . . . . 113 PSE&G Analysis of Water ...... o **** G...................... 115 GROSS BETA PSE&G Analysis of Air Particulates....................... 116 PSE&G Analysis of Water.................................. 118 POTASSIUM-40 Analysis of Water.................. . . . . . . . . . . . . . . . . 119.

TRITIUM PSE&G Analysis of Water................... . . . . . . . . . . . . . . . . 120 YAEL Analysis of Aqueous Fraction of Biological Material 121

_J IODINE-131 PSE&G Analysis of Filtered Air... . . . . . . . . . . . . . . . . . . . . . . . . 122 PSE&G _Analysis of~Raw Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123 PSE&G Analysis of Water ................. ~ . . . . . . . . . . . . . . . . 124 STRONTIUM-89 AND STRONTIUM-90 PSE&G Analysis of Air Particulates. . . . . . . . . . . . . . . . . . . . . . . 125 PSE&G Analysis of Raw Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 128 PSE&G Analysis of Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131 PSE&G Analysis of Vegetation, Meat and Aquatic Samples ... 134 PSE&G Analysis - of Bone and Shell. . . . . . . . . . . . . . . . . . . . . . . . . 137 PSE&G Analysis of Soil and Sediment . . . . . . . . . . . . . . . . . . . . . . 140 PSE&G Analysis of Samples for Stable Strontium ... -........ 143 111

SYNOPSES OF ANALYTICAL PROCEDURES (cont'd)

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates ....................... 145 PSE&G Analysis of Raw Milk . . . . . . . . . . . . . . . . . . . . . . . ; . . . . . . . 14 6 PSE&G Analysis of Water. . . . . . . . . * * . . . . . . . . . . . . . . . . . . . . . . . 14 7 PSE&G Analysis of Solids (combined procedures) ........... 148 ENVIRONMENTAL DOSIMETRY YAEL Analysis of Thermoluminescent Dosimeters ........... 149 TNUt Analysis of Thermoluminescent Dosimeters ........... 150

• PSE&G - PSE&G Maplewood Testing Services YAEL - Yankee Atomic Electric Laboratory TNUt - Thermo Nutech 112

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low background gas proportional counter. Along with a set of air particulate samples, clean ~ir 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, rnins.

E Fractional Arn-241 counting efficiency v = Corrected air flow of sample, m3 2.22 No. of dpm'-per pCi 113

2-sigma error {pCi/m3) = {1. 96* {G+B) 112 ) *A (G-B)

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

Calculation of lower limit of detection:

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

112 LLD {pC:i/m3 ) = 4.66 * (B)

(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.

114

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 handl~d 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, weighe~ 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:

esult (pCi/L) (G-B) /T (2.22)*(E)*(V)*(~)

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

T Count time of sample and blank E Fractional counting efficiency from U-238 source V = Sample volume, liters S = Normalized efficiency regression equation as a function of thickness 2.22 = No. of dpm per pCi 112 2-sigma error (pCi/L) (1. 96* (G+B) )A (G-B)

A Gross alpha activity, pCi/L G = Sample gross counts B Background counts (from blank sample) 115

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

The gross beta activity is computed on the basis of total corrected air flow sampled during the collection period. This .corrected air, flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of .the temperature-corrected gas meter as well as the gas meter 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-average.d 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, ~3 p Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows:

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

T Count time of sample and blank, mins.

E Fractional Sr-90 counting efficiency v Corrected air flow of sample, m3 2.22 No. of dpm per pCi 116

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

117

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 150ml 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 150ml for 150ml 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 geomeEry.

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 thickne 2.22 No. of dpm per pCi 2-sigma error (pCi/L) (l.96*(G+B)V 2 )*A (G-B)

A = Gross beta, activity, pCi/L G Sample gross counts B = Background counts (from blank sample) 118

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 erlenrneyer 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) = 0.85*C 0.85 Proportionality constant for converting ppm to pCi/L c Potassium concentration, ppm 119

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately 50rnl of* raw sample is mixed with sodium hydroxide *and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with lOrnl of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing 8ml 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 8ml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination. This is done for each set 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 = (NJ* (DJ 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:

l.96*(G/T 2 +B/T 2 )u 2 *(1000) 2 .22*(V)*(E)

Samples are designated LLD if the activity i*s less than the following value:

LLD (pCi/L) (4.66)*(BJU 2 *(1000J

2. 22* (V) * (E) * (T) 120

YAEL H-3 In Fish, Crabf lesh The determination of tritium in fish and crabflesh basically involves a sample preparation step followed by distillation and analysis of the pure distillate by liquid scintillation spectrometry. The tritium counting efficiency is determined using an absolute efficiency value generated from a NIST traceable calibration

~tandard. -

The sample preparation step involves extracting H-3 from a ground 25 g wet material in the presence of aqua regia and allowing for sufficient equilibration time so that a complete transposition of tritium with stable hydrogen has occurred .

• 121

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 (2.22) * (E) *(A)* (T) * (V)

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

T Acquisition live time, mins.

v Sample volume, m3 2.22 No. of dpm per pCi 2-sigma error (pCi/m 3

) 1. 96* (GC+BC) 112 *R N

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

The LLD (pCi/m3 ) = 4. 66* (BC) 112 *D (2.22)*(E)*(A)*(T)**(V) 122

SYNOPSIS OF PSE&G RESEARCH AN~ 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 (2.22)*(E)*(A)*(T)*(V)

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

T Acquisition live time, mins.

v Sample volume, L 2.22 No. of dpm per pCi 2-sigma error (pCi/L) = 1. 96* (GC+BC) 112 *R N

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

The LLD (pCi/L) = 4.66*(BC)u 2 *D (2.22) * (E) *(A)* (T) * (V) 123

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR IODINE-131 Stable iodine carrier is equilibrated with Sodium Bisulfite in a 4-liter volume of water, and then filtered, before two separate 50ml 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 (2.22) * (E) *(A)* (T) * (V)

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

1-EXP(-A.tl) tl = Acquisition live time t2 Elapsed time from sample collection to start of acquisition A.= 0.693/nuclide half life E Detector efficiency A Gamma abundance factor (no. of photons per disintegration)

T Acquisition live time, mins.

v = Sample volume, L 2.22 No. of dpm per pCi 2-sigrna error (pCi/L) l.96*(GC+BC)V 2 *R N

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

The LLD (pCi/L) = 4.66*(BC)V 2 *D (2.22)*(E)*(A)*(T)*(V) 124

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 radiostrontiurn 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 ls that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/m3 ) = N4/R (2.22)*(E)*(E(15)/E')*(S6)*(V)*(U)

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

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

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

µ = Chemical yield N4 (N2 Fl*Nli /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 125

t2 = Elapsed time from Y-90 strip to second count

2. 667 Half-life of Y-90, days Rl D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and Fare regression coefficients.)

N2 X - Y, where X and Y are recount gross counts and background counts, re~pectively 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/m3 ) =

2* (X+Y) + (Xl+Yl) *Fl~ 112 * (Wl*W2)

[ Wl 2

Wl J (N2-Fl*Nl)

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

~. 66* (X+Y) + (Xl +Yl) *Fl;i 112 L W12 W1 2

J Calculation of Sr-89 Activity:

Sr-89 Results (pCi/m3 ) = 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 whe_re G, H and I are regression coefficients.)

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

N7 (N2 - Fl*Nl)/Wl (This represents counts due to sr~90) 126

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

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

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

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

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

S9 = (Xl+Y1) 112 All other variables are as previously defined.

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

. 66* (S8 2 +S9 2 ) 112

• 127

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.

Stro,ntium recrystallization is carried out to remove residual calcium which may h~ve been coprecipitated with the initial strontium precipitation. Another recrystallization removes ingrown Y-90, marking the time of. the yttrium strip.

The strontium is precipitated as its carbonate, filtered, dried and weighed to determine strontium recovery. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)

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

M Thickness density of strontium carbon~te 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) 128

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 sing the same variable definitions as above, 2-sigma error for Sr-90 (pCi/L) =

~.* (X+Y) + (Xl+Yl) *F1 2

2 112

• (Wl*W2)

[ W1 Wl (N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) f4:_ 66* (X+Y) + (Xl+Yl) *F;!l 112 L- Wl Wl Calculation of Sr:-89 Activity:

Sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(15)/E')*(S7)*(V)*(U)*(F9)

W3 S7 G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one parti*cular gas proportional counter where G, H and I are regression coeff.icients. )

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

N7 (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 129

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

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

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

The 2-sigma error for Sr-89 (pCi/L) 2* (S8 2 +S9 2 ) 112

• W3 (Nl - N7*(l+Rl*Il))

SB = UX+Y) + (Xl+Yl) *E'.J!fi.12 -

~

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

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

4. 66* (S8 2 +S9 2 ) 112 130

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRO~TIUM ANALYSIS OF WATER Stable strontium carrier is .introduced into a water sample and into a distillea water sample of the same volume which is used as a blank. The sample(s) and blank are then made alkaline and heated to near boiling before precipitating the carbonates. The carbonates_ are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium.

Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromat.e 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 requlring two simultaneous equations to solve for th!=m.

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(15)/E')*(S6)*(V)*(U)

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

M Thickness density of strontium carbonate precipitate, mg/cm2

. E(15)/E' Ratio* of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard i~ run with each group of environmental strontium ~amples)

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)

• 131

I2 tl t2 1 - EXP ((-0.693/2.667)*t2)

Elapsed time from Y-90 strip to first count Elapsed time from Y-90 strip to second count

2. 667 Half-life of Y-90, days Rl D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients. )

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

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

~* (X+Y) + {Xl+Yl) *Fl~ I112 * {Wl*W2)

L Wl 2

Wl J {N2-Fl*Nl)

Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) fi_ 66* {X+Y) + {Xl+Yl) *F12J 1 12 L Wl Wl -1 Calculation of Sr-89 Activity:

Sr-89 Results {pCi/L) = N6/R

{2.22)*{E)*(E(15)/E')*{S7)*{V)*(U)*(F9)

W3 S7 = G + H*M + I*M2 {This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

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

N7 (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 132

.(15)/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 ((-0.693/50.5)*t) t Elapsed time from rriidpoint_ 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/L) 2*. (S8 2 +59 2 ) 112

• W3 (Nl - N7*(1+Rl*Il))

58 + (Xl+Yl)*F1~ 112 Wl -1 112 59 = (Xl+Yl)

All other variables are as previously defined.

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

. 66* (S8 2 +59 2 ) 112 133

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 cornpleti,en 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 pulveri-zed 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 900oC for 1/2 hour. After removal from the furnace, the melt is cooled, pulverized and added to SOOrnl distilled water and heated to near boiling for 30 minutes, with stirring. The sample is filtered (filtrate dis carded) *and the carbonates on the filter dissolved with 1: 1 nitric acid (HN0 3 )

• The resultant nitrates are heated to dryness and are dissolved in 20rnl distilled water before adding 60rn1 fuming HN03

• After calcium removal with anhydrous acetone, radioactive interfer~nces 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') * ( S 6) * (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(15)/E' Ratio of Sr-90 efficiency at thickness value of 15rng/crn2 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) 134

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

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

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

R Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/kg wet) ri:- (X+Y) + (Xl+Yl)*Frl 112 * (Wl*W2)

LW1 2

Wl =i (N2-Fl*Nl)

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

~ 66* (X+Y) + (Xl+Yl) *F;!l 112 cwl Wl J Calculation of Sr-89 .Activity:

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

W3 S7 G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

N6 Nl - N7*(1 + Rl*Il) 135

E(15)/E' N7 (N2 - ,Fl*Nl) /Wl (This represents counts due to Sr-9.0)

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

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

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

The 2-sigma error for Sr-89 (pCi/kg wet) = 2* (S8 2 +S9 2 ) 112

• W3 (Nl - N7*(1+Rl*Il))

112 SB + (Xl+Yl)*F;;)

Wl ]

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

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

4. 66* (S8 2 +S9 2 ) 112 I

136

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 hold.back carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered.

The sample is then treated with concentrated (70%) nitric acid and boiled until strontium nitrate crystallizes out. The strontium nitrate is freed of calcium by repeated fuming nitric acid recrystallizations. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide followed by coprecipitation .with barium chromate. The strontium is precipitated as strontium carbonate, which is dried, weighed, then betacounted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of Sr-90 Activity:

r. -90 Results (pCi/kg dry) = 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 dry)

U Chemical yield N4 (N2 - Fl*Nl) /Wl net counts due to Sr-90 only 137

Wl Il 12 =

((1 + Rl*I2) -

1 (1 + Rl*Il)*Fl)

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

2. 667 Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90.eff'y ratio for one particular gas proportional counter, where D, E and Fare regression coefficients.)

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

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

L (X+Y) + (Xl+Yl) *Flj"'

• Wl 2

Wl (Wl*W2)

(N2-Fl*Nl)

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

4.66* (X+Y) + (Xl+Yl)*F1 2 U 2 Wl Wl 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.)

138

• E(15)/E' N6 N7 Nl - N7*(1 + Rl*Il)

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

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

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

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

The 2-sigma error for Sr-89 (pCi/kg dry) = 2* (S8 2 +S9 2 ) 112

• W3 (Nl - N7*(1+Rl*Il))

ss = IJ.x+Yl + (Xl+Yl) *Fd 112 LWF Wl J

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

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

4. 66* ( s 8 2 +59 2 ) 112 139

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a 50gm aliquot is added to approximately 1/3 - liter concentrated hydrochloric acid {HCl), .

containing Sml of strontium carrier ( lOmg Sr++ /ml) . A blank containing only 1/3 - liter concentrated HCl and Sml strontium carrier is run in parallel with the sample. The samples are stirred vigorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable strontium. The remaining sample is alkalinized with

• ammonium hydroxide to precipitate all the transitional elements. After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontium and calcium carbonate. These carbonates are first filtered and then digested with 6N HN03

• Two fuming (90%) HN03 recrystallizations are then performed to remove calcium. Subsequently, radioactive impurities are removed by two precipitation steps, using ferric hydroxide and barium chromate as carriers. The strontium is precipitated as strontium carbonate before being dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending o~ 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(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 envirorimental 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) 140

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

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

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

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

~

• (X+Y) + (Xl+Yl) *F~ 112 * "(Wl*W2)

W1 2 Wl '

(N2-Fl*Nl)

Again, keeping the s~me variable definitions, the LLD for Sr-90 (pCi/kg dry) =

r:;. 66* (X+Y) + (Xl+Yl) *Fa 112 t.== Wl Wl =i Calculation of Sr-89 Activity:

Sr-89 Results (pCi/kg dry) = 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) 141

N7 = (N2 - Fl*Nl) /Wl (This represents counts du.e 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.~93/50.5)*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 previous~y defined.

The 2-sigma error for Sr-89 (pCi/kg dry) = 2* (S8 2 +S9 2 ) 112

• W3 (Nl - N7*(1+Rl*Il))

+ (Xl+Yl) *Fl_:l 1 12 Wl J S9 = (Xl+Yl) 112 All other variables are as previously defined.

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

4. 66* (S8 2 +S9 2 ) 112 142

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 ~he stable isotopes. In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/o'r acid leaching is performed to extrac't 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 gra~h._ Chemical and ionization interferences are controlled by the addition of 0.1% or more of lanthanum to all samples.

For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH <2 with hydrochloric 9r 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 anthanum to achieve a minimum of 0.1% lanthanum in all solutions.

1 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) :119 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 0.025 143

Net weight of SrC03 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 cal'culations follow the same sequence for bone and shell samples.

Sample Calculation of Corrected Chemical Recovery of Strontium in Water:

Reported concentrations of stable strontium (mg/L): 1.65 Volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample (1.65mg/L) x (2.0L) 3.30mg Quantity of strontium carrier added to sample (mg): 20.0 Total amount of-strontium in sample (mg): 20.0 + 3.30 = 23.3rng Net weight of Sr~0 3 precipi~ate (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 144

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 (2.22)*(E)*(A)*(T)*(V)

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

T Acquisition live time, mins.

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

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

The LLD (pCi/m3 ) = 4. 66* (BC) 112 *D (2.22)*(E)*(A)*(T)*(V) 145

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 temp~rature 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 (2.22)*(E)*(A)*(T)*(V)

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

T Acquisition live time, mins.

V Sample volume, liters 2.22 No. of dpm per pCi 2-sigma error (pCi/L) l.96*(GC+BC)V 2 *R N

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

The LLD (pCi/L) = 4.66*(BC)V 2 *D (2.22)*(E)*(A)*(T)*(V) 146

SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sampre 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 (2. 22) * (E) *(A)* (T) * (V)

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

T Acquisition live time, mins.

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

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

The LLD (pCi/L) = 4.66*(BC)u 2 *D (2.22)*(E)*(A)*(T)*(V) 147

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-sigrna error and LLD:

Result (pCi/kg) N*D (2.22)*(E)*(A)*(T)*(V)

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

T Acquisition live time, rnins.

v Sample volume, kilograms 2.22 = No. of dpm per pCi 2~sigrna error (pCi/kg) l.96*(GC+BC)v 2 *R N

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

The LLD (pCi/kg) = 4.66*(BC)V 2 *D (2.22) * (E) *(A)* (T) * (V) 148

YAEL Processing of Environmental TLDs The purpose of an environmental radiation monitoring program is to assess the external radiation exposure received at a given location over a given time interval. The Environmental Thermoluminescent Dosimeter (TLD) program at the Environmental Laboratory provides Pa.nasonic TLD badges containing CaS0 4 (Tm) and Li 2 B40 7 (Cu) phosphor elements to the participating plants for posting in the field.

Following receipt at the Environmental Laboratory, the Dosimetry Services Group (DSG) processes these dosimeters to determine the amount of radiation to which each badge was exposed.

In estimating the exposure received at the posting location, the raw TLD results are corrected for individual element sensitivity and reader sensitivity as determined by QC results. Transit exposures are subtracted and the fade of the thermoluminescent response is compensated for. A report is issued to the plant staff listing specifics of the posting period and processing-file as well as the corrected results of the transit TLD's and the individual field stations.

149

Thermo NUtech Processing of Environmental TLDs Thermo NUtech has developed a family of dosimeters for use in detecting and quantifying ionizing radiation exposures. The Thermo Nutech.environmental dosimeters (TLD-100) are a single badge design based upon using lithium floride (LiF) chips. The benefit of this dosimeter is its ability to detect x-ray and gamma ray as well as beta and neutron doses. They are sensitive, withstand most environmental stresses and suffer negligible fading.

Thermoluminescence is a solid-state phenomenon. In an insulating crystal such as LiF, the outer shell electrons are bound to individual atoms in an energy band called the Valence Band. Ionizing radiation can give them sufficient energy to cross into the Conduction Band. They quickly collapse back down toward the valence band, but some are trapped by the Mg and Ti dopants in the crystal.

There they remain until they can get sufficient energy to return to the conduction band and then decay to ground (valence). These trapped electrons comprise a record of the absorbed dose. Heat is applied at readout, which provides the necessary energy. The collapse to ground is accompanied by a photon of visible light, which is registered in the reader as a "count."

Becau.se the crystal* responds differently to different kinds and energies of ionizing radiation, certain calibrations must be performed. The crystals are calibrated against 137 Cs photons for gamma or x-ray. Beta response has a default calibration factor of

1. 3.

150

APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 151

APPENDIX E

SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the 1995 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTLON ~

E-1 Gross Alpha and Gross Beta Emitters in Water and Air Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 154 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 155 E-3 Tritium in Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 156 E-4 Iodine in Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ; 157 E-5 Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products . . . . . . . . . . . . . . . . . . . . 158

• 153

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)

\

EPA Acceptance

• Criteria DATE PSE&G EPA Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 01.-95 EPA-WAT-AB389 Water Alpha 6. 6+/-1.. 0 5 -3.7 1.3. 7 Beta 6.3+/-1..2 5 -3.7 1.3. 7 04-95 EPA-WAT-P392 Water Alpha 59+/-4.8 48 26.9 68 .1.

Beta 91.+/-1..5 87 69.3 1.03 07-95 EPA-WAT-AB395 Water Alpha 1.8+/-1.. 0 28 1.5.5 39.5 Beta 21.+/-1..5 1.9 1.0. 7 08-95 EPA-APT-GABS397 APT Alpha 35+/-2.0 25 1.4.1. 35.9 Beta 86+/-0.6 87 69.3 103 10-95 EPA-WAT-P400 Water Alpha 1.30+/-5.5 99 56.3 1.42 Beta 1.29+/-2.6 1.41. 1.04.0 1.77 1.0-95 EPA-WAT-AB401. Water Alpha 22+/-2.0 51. 29.0 73.4 Beta 30+/-1..5 25 1.6. 1. 33.5

• s.d. - two standard deviations of three individual analytical results 154

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

Acceptance

• Criteria DATE PSE&G EPA Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 04-95 EPA-WAT-P392 Water Cs-134 20+/-1.5 20 11.3 28.7 Cs-137 11+/-0.6 11 2.3 19.7 Co-60 30+/-0.6 29 20 .3 37.3 06-95 EPA-WAT-G393 Water Ba-133 77+/-2.6 79 65.1 92.9 Co-60 39+/-1.0 40 31.3 48.7 Zn-65 76+/-1. 5 76 62.1 89.9 Cs-134 47+/-3.8 50 41.3 58.7 Cs-137 34+/-0.6 35 26.3 43.7 8-95 EPA-APT-GABS397 APT Cs-137 20+/-1.0 25 16.3 33.7 09-95 EPA-MLK-GS398 Milk Cs-137 51+/-1.0 so 41. 3 58.7 K(1) 1683+/-35 1654 1510 1798 I-131 106+/-1.7 99 81.7 116.3 10-95 EPA-WAT-P400 Water Co-60 50+/-1.0 49 40.3 57.7 Cs-134 /

38+/-1.2 40 31. 3 48.7 Cs-137 29+/-1.7 30 21.3 38.7 11-95 EPA-WAT-G402 Water Ba-133 103+/-3.6 99 81. 7 116.3 Co-60 58+/-2.5 60 51.3 68.7 Zn-65 124+/-4.2 125 102.5 147.5 Cs-134 38+/-1. 5 40 31.3 48.7 Cs-137 50+/-2.1 49 40.3 57.7

1) Reported as mg/l of Potassium

• s.d. - two standard deviations of three individual an~lytical results 155

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

EPA Acceptance

• Criteria DATE PSE&G EPA Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 03-95 EPA-WAT-H391 Water H-3 7087+/-64 7435 6146 8724 08-95 EPA-WAT-H396 Water H-3 4677+/-90 4872 4029 5715

• s.d. - two standard deviations of-three individual analytical results

-156

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

EPA Acceptance

• Criteria DATE PSE&G EPA Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 02-95 EPA-WAT-I390 Water I-131 96+/-2 100 82.7 117.3 10-95 EPA-WAT-I399 Water I-131 123+/-2.5 148 122.0 174.0

• s.d. - two standard deviations of three individual analytical results 157

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)

EPA Acceptance

• Criteria DATE PSE&G EPA Lower & Upper MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d. Known Limit Limit 01-95 EPA-WAT-8388 Water Sr-89 19+/-1.5 20 11.3 28.7 Sr-90 14+/-0.6 15 6.3 23.7 04-95 EPA-WAT-P392 Water Sr-89 21+/-0 20 11.3 28.7 Sr-90 14+/-0.6 15 6.3 23.7 07-95 EPA-WAT-8394 Water Sr-89 18+/-0.6 20 11.3 28.7 Sr-90 7+/-0.6 8 -0.7 08-95 EPA-APT-GABS397 APT Sr""'.90 30+/-0.6 30 21.3 38.7 09-95 EPA-MLK-GS3398 Milk Sr-89 7+/-0.6 20 11.3 28.7 Sr-90 9+/-0.6 15 6.3 23.7 10-95 EPA-WAT-P400 Water Sr-89 16+/-2.5 20 11.3 28.7 Sr-90 10+/-1.0 10 1.3 18.7

• s.d. - two standard deviations of three individual analytical results 158

651 SfiSNS~ ssn CINY~ ao SISdONXS a XICINSddY

APPENDIX F SYNOPSIS OF 1995 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 animali the nearest residence, and the nearest garden of greater than SOm (500ft 2 )

producing broad leaf vegetation, in each of the f 6 meteorological sectors.

Tabulated below are the results of these surveys:

Milk Nearest Vegetable Animal Residence Garden Meteorological July, 1995 July, 1995 July, 1995 Sector km (miles) km (miles) km (miles)

N None None None NNE None 6.9 (4. 3) None NE None 6.4 (4. 0) None ENE None 5.8 ( 3. 6) None E None 5.4 (3. 4) None ESE None None None SE None None None SSE None None None s None None None SSW None 5.5 (3. 4) None SW None 6.9 (4. 3) None WSW None 7.1 (4. 4) None w 7.8 ( 4. 9) 6.5 (4. 0) None WNW None 5.5 (3. 4) None NW None 5. 9 ,(3. 7) None NNW None 6.8 (4. 2) None

• 161 '

APPENDIX G SUPPLEMENTAL SECTION

• 163

APPENDIX G SUPPLEMENTAL REPORT/DATA TABLES Appendix G presents the background, overview and discussi-on of the unplanned airborne release from Hope Creek Generating Station, plus.the analytical results from this April 5, 1995 release.

TABLE OF CONTENTS I. BACKGROUND. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 7 II. OVERVIEW/INITIAL DISCUSSION AND RESPONSE ..... ~--*............. 167 III. DISCUSSION OF RESULT.......................................... 169 FIG Gl MAP OF COLLECTION LOCATIONS................................... 171 DATA TABLE OF CONTENTS LE

0. TABLE DESCRIPTION VEGETATION G-+ Concentrations of Beryllium-7 in Grass Samples................. 174 G-2 Concentrations of Potassium~40 in Grass Samples................ 175 G-3 Concentrations of Chromium-51 in Grass Samples .................. 176 G-4 Concentrations of Manganese-54 in Grass Samples ................. 177 G-5 Concentrations of Cobalt-58 in Grass Samples .................... 178 G-6 Concentrations of Iron-59 in Grass Samples ...................... 179 G-7 - Concentrations of Cobalt-60 in Grass Samples .................... 180 G-8 Concentrations of Zinc-65 in Grass Samples ...................... 181 G-9 Concentrations of Gamma Emitters in Grass Samples (Routine REMP Sampling Locations) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 182 165

DATA TABLES (cont'd.)

TABLE

.....NQ_ TABLE DESCRIPTION PAGE

• SOIL G-lO Concentrations of Gamma Emitters in Soil Samples (Selected Soil Sampling Locations) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l83

~

G-ll Concentrations Beryllium-7 in Soil Samples ...................... l84 G-l2 Concentrations of Potassium-40 in Soil Samples .................. l85 G-l3 Concentrations of Manganese-54 in Soil Samples .................. l86 G-l4 Concentrations of Cobalt-SB in Soil Samples ..................... l87 G-lS Concentrations of Iron-59 in Soil Samples ....................... l88 G-16 Concentrations of Cobalt~60 in Soil Samples ................. : ... l89 G-l7 Concentrations of Zinc-65 in Soil Samples ....................... l90 G-l8 Concentrations of Cesium-l34 in Soil Samples .................... l91 G-19 Concentrations of Cesium-l37 in Soil S~mples ..................... l92 G-20 Concentrations of Gamma Emitters in Soil Samples (Selected Soil

_Sampling Locations) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l93 SURFACE WATER G-21 Concentrations of Gamma Emitters in Surface Water Samples (Selected Surface Water Locations) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l94 AIR PARTICULATE G-22 Concentrations of Gamma Emitters in Air Filter Samples (Selected REMP Sampling Locations) ..............~ ............... l96 166

Supplemental to the 1995 Annual Radiological Environmental Operating Report - A review of the April 5, 1995 accidental release from the Hope Creek Generating Station I. Background On April 5, 1995, two unplanned releases occurred from the south plant vent of the Hope Creek Generating Station. The first release occurred at 0021 hour2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> when the Reactor Building Vent System Exhaust and the Radwaste.Exhaust System duct monitors went into an alarm state, and the second release occurred at 0049 when these monitors registered a marked increase. The source of the releases was an evaporator used to concentrate waste streams collected in the chemical waste tank. *After accumulating in the chemical waste tank, these wastes are neutralized, buffered if required, and then processed by the evaporator. The purpose of the evaporator is to reduce the volume of radioactive waste from these sources. The concentrate is then discharged to another waste tank for radioactive decay and vapor is routed to the south.plant vent through a 6 11 vent pipe. Water droplets were directed into the south plant vent when the evaporator system experienced two pressure transients, due to a clogged demister, which caused the pressure to increase from 3 psig to 6 psig at 0021 hr and from 3 psig to 8 psig at 0049 hr. When the spray to reduce pressure was secured and operational, it caused a rapid depressurization to occur in the evaporator. This rapid depressurization within the evaporator system, combined with the high flow rate in the south plant vent, momentarily permitted 6 to 7 gallons of water to become entrained in the air flow directed to the south plant vent.

The second depressurization event caused an estimated 18 to 19 gallons of water to be released. The total amount of radioactive material released was estimated to be 85 mCi.

The water released into the atmosphere contained levels of radioactive corrosion and activation products that were normal for the routine operation of the evaporator.

II. Overv.iew and Discussion of the Initial Environmental

Response

At the time of the releases, the wind was northwesterly at 25 to 30 miles per hour.

167

Since the releases were due to relatively heavy water ,-*

droplets becoming entrained in the south plant vent air, much of the material and the radioactivity associated with it was deposited on the plant site near the south vent release point. The activity was found to be dispersed on the site in a well defined plume to the southeast of the plant. Radioactive contamination was found on various roofs and yard areas, walkways, and building surfaces in the direction of the prevailing winds. Once it was determined that the area outside the protected area was contaminated, additional envi:i;-onmental monitoring of soil and grass samples was initiated on April 6th and cont1nued for several weeks in order to confirm the initial evaluation of the environmental impact of the release. Initially a series of soil and vegetation samples was collected at locations which were referred to as location numbers 1, 2, 3, 4, 5 and 6.

In order to differentiate the soil samples from the vegetation samplE:s the letters S or G were _µsed as a pref ix for the various samples collected. For example, the soil samples were noted as stations Sl through SlO, while the vegetation samples were noted as locations Gl though GlO.

Sample location #1 was selected at a.location along the Delaware River shoreline, directly across from the building known as the old Main Guard House, by the dock. From that i location, one hundred feet was measured and the next sampling location was selected and noted as #2. The locations 3 through 6 were selected using the same criteria.

After location 6, t'he distance was increased to every 300 feet in order to roughly coincide with the locations of the telephone poles. Later, an additional location (lA) was added to the program and was located mid-way between locations 1 and 2.

The soil samples were ~ollected with a shovel in which just the top few inches of soil were removed. Since vegetation was being sampled specifically, all vegetation was removed from all of the soil samples collected. The vegetation samples were collected by clipping the top portion of any vegetation noted along the shoreline at the locations specified.

168

• A series of samples was also collected from routine environmental sampling locations lODl, llDl, 12El, 1401, 9El, 15D2, 7ElA, and 9Fl for reference information.

G-1 shows the locations where samples were collected.

Figure On April 7th. the scope of the environmental surveillance was broadened to include the following:

~

1) Change out of selected TLD's (10 locations-See Appendix C; Table C-5 for results) .

2) Gamma isotopic analyses of two additional sets of routine REMP surface water samples plus a set of*

alternate locations.

3) Gamma isotopic analyses of* air filters used in the routine REMP.

III. Discussion of Results The first few soil and vegetation samples collected were crucial in confirming the extent of the contamination.

The activity and ratio of the predominant nuclides present in the grass sample collected from location Gl on 4/6/95 is presented in Table 1.

Table 1 - Analysis of Environmental Grass Sample Activity Isotope Concentratiqn Ratio pCi/kg-wet CrSl 2.49E+03 14%

Mn54 8.37E+03 47%

Co58 1. 24E+03 79,,-

0 .

Fe59 2.08E+03 12%

Co60 2.15E+03 12%

Zn65 1. 39E+03 8%

Total Activity 17.7E+03 100%

The activity concentration and ratio of predominant nuclides obtained from the analysis of the decontamination solution evaporator bottom liquid during April 4-6, 1995 period is presented in Table 2.

169

Table 2 - Analysis of Evaporator Bottom Liquid Isotope Activity Concentration uCi/ml Ratio Cr51 3.l8E-2 7%

Mn.54 2.20E-1 47%

Co58 4.43E-2 9%

Fe59 l.61E-2 3%

Co60 7.34E-2 16%

Zn65

• 7.57E-2 16%

AgllOm 5.39E-3 1%

Total Activity 4.67E-1 100%

The ratio of the nuclides detected in the* analyses of the in-plant decontamination solution evaporator bottom liquid compares favorably with the results of the environmental grass samples. The environmental surveillance program, as conducted after the April 5th release, confirmed that the activity detected was from the discharge of liquid from the decontamination solution evaporator bottom liquid.

A total of 78 soil samples and 108 grass samples were collected during this period. A gamma spectrometric analysis was- performed on each of these samples. This is in addition to the ten extra TLD's (See Table C-5), the five air particulate filters and the 17 extra surface water samples collected and analyzed. Results for these samples can be viewed in tables G-1 through G-22.'

170

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TABLE G-1 CONCENTRATIONS OF BERYLLIUM-? IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <-------------------------------------------------------------- STATl 0 N. --------------------------------------------------------------->

DATE G1 G1A G2 G3 G4 G5 G6 G7 GB G9 G10 4/6/95 7000 N/S 2530 10200 4690 . 964 9830 <4350 7080 10100 1660 4110/95 <828 N/S 2530 5150 <2360 1680 4080 5930 7430 11700 907 4/13/95 4450 7500 1750 4160 5440 1810 6610 4/18/95 4770 10700 <304 11500 9350 730 8270 4/24/95 882 762 <170 1180 910 455 1020 5/1/95 2470 882 488 1860 1060 458 2090 I-' 5/8/95 1080 1150 565 3170 2480 627 2260

-.....J

..i:- 5/15/95 890 2490 <167 3180 5890 509 3120 5/22/95 1590 910 1950 3260 2360 5/31/95 2730 <258 950 4720 631 6/5/95 899 811 1020 1810 6/12/95 3710 2970 1660 3350 6/19/95 2060 1240 6/26/95 2580 2050 7/3/95 1560 . 1530 7/10/95 1610 1750 7/17/95 2370 1350

• TA CONCENTRATIONS OF POTASSIUM-40 IN GRASS SAMPLES .

DELAWARE RIVER SHORELINE LOCATIONS

-2 (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N -------------------------------------------------------------------->

DATE G1 G1A G2 G3 G4 G5 G6 G7 GS G9 G10 4/6/95 3970 N/S 6980 3930 4960 5580 <862 2350 4340. 2720 5630 4/10/95 5420 N/S 6670 3580 4830 5540 6530 4840 4440 1990 6520 4/13/95 4150 2090 4810 2040 2260 3860 961 4/18/95 5280 4650 7550 3020 4440 6770 4240 4/24/95 5580 6300 6090 5390 4790 4400 6670.

5/1/95 6940 6320 6750 5050 4510 4590 6090 t-' 5/8/95 8460 6020 <495 5730 5540 5500 6950

-....J V1 5/15/95 4850 4230 <710 2920 1820 4060 1490 5/22/95 5760 6410 I 6340 6320 6500 5/31/95 6130 6730 5860 3320 5570 6/5/95 8170 6620 7350 6260 6/12/95 5840 9340 6980 7500 6/19/95 9670 <1530 6/26/95 8730 8250 ~

7/3/95 9650 11100 7/10/95 7640 9960 7/17/95 10100 9090

TABLE G-3 CONCENTRATIONS OF CHROMIUM-51 IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATION -------------------------------------------------------------------->

DATE G1 G1A G2 G3 G4 G5 G6 G7 GB G9 G10 4/6/95 2490 N/S 2540 <1140 ' <193 <87 <91 <180 <255 <79 <125 4/10/95 1430 N/S 2360 801 <112 <131 <109 <117 <72 <232 <51 4/13/95 2130 2290 1170 <234 <222 <80 <126 4/18/95 2460 3640 1270 1180 <402 <78 <145

. 4/24/95 <183 441 <124 <145 <94.6 <104 <109 5/1/95 637 <133 <133 <401 <67.9 <58 <184 t-'

5/8/95 <204 .<191 <118 <151 <115 <84 <86

"°' 5/15/95 <130 404 <129 <105 <148 <65 <120 5/22/95 <119 <127 <132 <122 <65.4 5/31/95 <436 <125 <139 <144 <131 6/5/95 <95.5 <69.6 <51.6 <78.4 6/12/95 <280 <225 <238 <421 - -

6/19/95 <528 <239 6/26/95 <269 <249 7/3/95 <148 <91 7/10/95 <289 <128 7/17/95 <88.9 <157

TAB CONCENTRATIONS OF MANGANESE-54 IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATION -------------------------------------------------------------------->

DATE G1 G1A G2 G3 G4 G5 G6 .G7 GB G9 G10 4/6/95 8370 N/S 7670 4030 870 305 156 <30 <24 <!15 <14 4/10/95 4640 N/S 8860 3090 700 425 78.8 <21 <16 <35 <25 4/13/95 7400 15500 4130 1.110 700 295 100 4/18/95 11300 24400 5530 4270 1350 <19.5 168 4/24/95 1000 1870 748 410 128 143 <11.3 5/1/95 3460 1650 556 752 97.3 <33.2 <70.7 I-' 5/8/95 1310 2550 471 908 279 <35.8 <50.7

........ -5/15/95 640 4160 91 304 422 41.3 <27.6 5/22/95 962 529 796 336 *94.9 5/31/95 1800 201 <39 186 <17.5 6/5/95 84 162 62 84 6/12/95 2290 2150 <53 <127 6/19/95 905 153 6/26/95 1140 203 7/3/95 1080 <74 7/10/95 751 220 7/17/95 <32 <27

TABLE G-5 CONCENTRATIONS OF COBALT-58 IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N -------------------------------------------------------------------->

DATE G1 G1A G2 G3 G4 G5 G6 G7 GB G9 G10 4/6/95 1240 N/S 1420 817 189 78 <42 <14 <12 <14 <14

\

4/10/95 489 N/S 915 426 104 75 <22 <16 <14 <29 <20 4/13/95 961 2550 456 192 146 54 <38 4/18/95 1720 4020 502 669 167 <9 <23 4/24/95 141 <44 89 <22 <15 . <24 <14 5/1/95 497 181 55 83 <18 <11 <26 t-' <24 <7 <12

-...J 5/8/95 165 342 66 157 00 5/15/95 81 558 <12 <18 82 <8 <6 5/22/95 123 101 68 47 <33 5/31/95 205 <21 <17 60 <19 6/5/95 <15 <20 <9 <10 6/12/95 430 263 <36 <101 6/19/95 <170 <28 6/26/95 <38 <32 7/3/95 <40 <52 7/10/95 <53 <44 7/17/95 <33 . <22

TA CONCENTRATIONS OF IRON-59 IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCiikg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N -------------------------------------------------------------------->

DATE G1 G1A G2 G3 G4 G5 G6 G7 GB G9 G10 4/6/95 2080 N/S 2380 1420 <218 <36 <53 <109 <59 <18 <32 4/10/95 1560 N/S 2950 869 162 <61 <24 <34 <30 <31 <36 4/13/95 2100 3920 1300 303 <172 <74 <38 4/18/95 2860 5940 1850 1280 <130 <32 <78 4/24/95 275 510 240 153 <72 61 <16 5/1/95 903 390 182 227 <32 <13 <42 t-' 5/8/95 296 408 117 336 <88 <11 <13

-....J

\0 5/15/95 176 696 <25 <71 <24 <16 <9 5/22/95 267 135 237 66 <35 5/31/95 419 <64 <42 <140 <58

\

6/5/95 <28 <40 <24 <30 6/12/95 <370 377 <65 <73 6/19/95 <117 <56 6/26/95 <123 <77 7/3/95 197 <62

\

7/10/95 <122 <66 7/17/95 <60 <67

TABLE G-7 CONCENTRATIONS OF COBALT-60 IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N -------------------------------------------------------------------->

PERIOD G1 G1A G2 G3 G4 G5 G6 G7 GB G9 G10 4/6/95 2150 N/S 2310 945 242 106 <35 <25 <13 <64 <10 4/10/95 957 N/S 1670 724 179 107 <32 <11 <10 <38 <27 4/13/95 1740 4030 865 305 270 76 24 4/18/95 2720 6450 957 1190 <85 <18 52 182 112 <26 51

<22 4/24/95 241 375 5/1/95 975 404 150 194 <22 <27 <18 t-' 659 90 276 120 <14 <20 00 5/8/95 481 0

5/15/95 193 1110 <15 115 139 <11 <7 5/22/95 261 158 199 87 37 5/31/95 497 63 <20 <47 <13 6/5/95 34 <31 <12 38 6/12/95 528 623 <42 <73 6/19/95 237 <29

~

6/26/95 <87 <97 \

7/3/95 262 127 7/10/95 283 <97 7/17/95 <24 <58

• • TA CONCENTRATIONS OF ZINC-65 IN GRASS SAMPLES DELAWARE RIVER SHORELINE LOCATIONS

-8 (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N -------------------------------------------------------------------->

PERIOD G1 G1A G2 G3 G4 G5 G6 G7 GS G9 G10 4/6/95 1390 N/S 1800 <818 <292 <41 <41 <39 <39 <46 <33 4/10/95 633 N/S 1350 606 142 <84 <99 <56 <30 <54 <62 4/13/95 1310 3100 689 296 225 <89 <41 4/18/95 2190 5010 833 1110 <450 <25 <84 4/24/95 215 250 146 113 <57 <48 <34 -

5/1/95 710 314 122 338 <44 <11 <25 t-'

00 5/8/95 427 599 <103 267 104 <28 <36 t-'

5115/95 150 995 <71 <94 <97 <15 <13 5/22/95 112 209 <185 69 <102 5/31/95 439 <56 <31 <35 <27 6/5/95 <30 <26 <25 <28 6/12/95 681 621 <77 <125 6/19/95 <203 <88 6/26/95 <149 <99 7/3/95 <105 <133' 7/10/95 236 <173 7/17/95 <58 <83

TABLE G-9 CONCENTRATIONS OF GAMMA EMITTERS IN GRASS SAMPLES ROUTINE REMP SAMPLING LOCATIONS (Results in Units of pCi/kg-wet}

SAMPLING ------------------------------------------------------------------ STATl 0 N ------------------------------------------------------------------------

NUCLIDE PERIOD 1001 1101 12E1 1401 9E1 1502 9F1 G7E1A 8e-7 417195 5960 7920 5610 5400 4670 K-40 4/7/95 4490 3380 4300 4850 4050 Cr-51 417195 <97 <132 <72 <113 <181 Mn-54 417195 <15 <17 <15 <9 <19 Co-58 417195 <17 <13 <7 <8 <24 Fe-59 4/7/95 <18 <38 <29 <21 <40

- <17 <18 <11 <27 <40 Co-60 417195 00 N Zn-65 417195 <22 <41 <64 <50 <49 Be-7. 4/10-12/95 6150 13100 8350 7230 5860 15100 7430 10300 K-40 4/10-12/95 3160 3050 3330 4920 6550 1010 1900 2840 Cr-51 4/10-12/95 <121 <230 <162 <141 <75 <371 <349 <166 Mn-54 4/10-12/95 <14 <24 <21 <16 <22 <31 <35 <30 Co-58 4/10-12/95 <11 <22 <10 <8 <21 <16 <25 <30 Fe-59 4/10-12/95 <13 <90 <23 <16 <29 <49 <123 <48

• Co-60 4/10-12/95 <13 <43 <28 <22 <17 <33 <34 <24 Zn-65 4/10-12/95 <28 <120 <65 <26 <27 <127 <133 <38

TAB 10 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL SAMPLES AT SELECTED SOIL SAMPLING LOCATIONS TOP SOIL VS 6-INCH PLUGS \~

(Results in Units of pCi/kg-wet)

' ' 1 '

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

2 NUCLIDE G1-6 G1A G1A-6 G2-6 G3-6 G4-6 Be-7 <76 <122 <70 <161 <91 <79 <74 <61 <73 ' <78 K-40 6550 7060 8380 11000 8850 8100 6160 9560 7470 9850 Mn-54 36 42 59 53 51 18 <8 <11 <12 61 Co-58 <7 <7 <8 <10 '<8 <3 <6 <7 <4 <19 Fe-59 <13 <14 <19 <20 <19 <13 <22 <14 <17 <22 t-'

00 Co-60 <12 <12 <26 51 15 <10 <6 <17 <8 <11 v.>

Zn-65 <24 <31 <21 <21 <21 <24 <26 <30 <16 <40 Cs-134 <19 <6 <10 <11 <7 <7 24 54 <39 37 Cs-137 18 <24 37 , 87 108 38 21 118 59 35 (1) Sampling Date: 5/1 /95 (2) These samples consisted of 3-inch plugs.

TABLE G-11 CONCENTRATIONS OF BERYLLIUM-7 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATION ----------------------------------------------------------------------->

PERIOD S1 S1A S2 S3 84 S5 S6 S7 88 89 810 4/6/95 <155 N/8 <64 <48 <91 <39 <29 207 <58 134 <56 4/10/95 154 N/S 91 <37 92 <64 <80 <50 <39 86 84 4/13/95 134 130 <111 106 <64 <93 110 4/18/95 <80 1030 <28 98 4/24/95 133 .109 <65 <57 5/1/95 171 <77 110 64 t--'

CX>

~ 5/8/95 <37 69 <79 120 5/15/95 102 <62 <48 68 5/22/95 <43 129 <103 63 5/31/95 <35 <94 83 48 6/5/95 132 <67 115 <42 6/12/95 <108 <67 <99 <65

i TAB CONCENTRATIONS OF POTASSIUM-40 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS 12 (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N --------------------::~--~-------------------------------*----------->

PERIOD S1 S1A S2 S3 S4 S5 S6 S7 SB S9 S10 4/6/95 1450 N/S 1840 2840 1750 1180 2680 2670 2420 2980 4390 4/10/95 1700 N/S 2500, '2620 2460 1140 2620 2750 2270 3230 3870 4/13/95 1640 1490 1460 2610 2030 1520 2620 4/18/95 1430 17900 2860 2190 4/24/95 1830 1570 2280 2930 5/1/95 1650 1550 2480 1340 I-'

00 U'I 5/8/95 1650 1630 2350 3070 5/15/95 1550 1450 2290 2390 5/22/95 1390 2060 1720 1910 5/31/95 2050 1740 1800 2550 6/5/95 1420 1550 1610 2340 6/12/95 1720 1440 1940 3120

TABLE G-13 CONCENTRATIONS OF MANGANESE-54 IN SOIL SAMPLES DELAWARE RIVER SHORELINE-LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STA Tl 0 N -------------------------------------------------------------------->

PERIOD S1 S1A S2 S3 S4 S5 S6 S7 SB S9 S10 J

4/6/95 139 N/S 215 35 11 <5 <9 <5 <8 <5 <3 4/10/95 162 N/S 63.8 70 25 <3 <3 <4 <4 <7 <3 4/13/95 132 198 <13 38 <7 <4 <4 4/18/95 117 599 16 65

~

4/24/95 61 32 36 21 I-' 5/1/95 90 34 38 13 00

°' 5/8/95 67 25 20 16 5/15/95 28 <12 21 14 5/22/95 32 17 17 11 5/31/95 22 <5 17 9 6/5/95 16 <9 22 <11 6/12/95 <29 <15 <24 <6

TAB 14 GONCENTRATIONS OF COBALT-58 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <-------------------*-------------------------------------------------- STA Tl 0 N ---------------------------------------------------------~---------->

PERIOD S1 S1A S2 S3. S4 S5 S6 S7 SB S9 S10 4/6/95 . 22 N/S 40 <4 <2 <4 <3 <4 <8 <2 <3 4/10/95 31 N/S 15 <6 <2 <3 <2 <3 <4 <2.29 <4 4/13/95 20 32 <5 <7 <3 <2 <5 4/18/95 18 158 <4 9 4/24/95 <4 <5 12 <6 I-' 5/1/95 <6 <9 <9 <3 00 5/8/95 16 <3 <8 <3 5/15/95 10 <4 <5 <3 5/22/95 <9 <5 <9 <4 5/31/95 <6 <6 <5 <0.04 6/5/95 <4 <5 <5 <6 6/12/95 <9 <8 <6 <9

TABLE G-15 CONCENTRATIONS OF IRON-59 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS

(Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATl 0 N -------------------------------------------------------------------->

PERIOD S1 S1A *s2 S3 S4 SS S6 S7 SB S9 810 4/6/95 69 N/S 74 <8 <3 <6 <4 <8 <7 <15 <5 4/10/95 32 N/S 12 <33 <15 <6 <15 <7 <8 <6 <7 4/13/95 79 50 <6 <12 <16 <5 <8 4/18/95 41 <174 <6 17 4/24/95 <16 N/S <8 <9 t-'

00 5/1/95 <11 <5 <14 <8 00 5/8/95 <16 <4 <13 <6 5/15/95 <6 <6 <14 <5 5/22/95 <5 <4 <10 <5 5/31/95 <8 <6 <6 <4 6/5/95 <5 <11 <8 <8 6/12/95 <16 <20 <13 <18

TAB.16 CONCENTRATIONS OF COBALT-60 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING ------------------------------------------------------------------------ STATl 0 N -------------------------------------------------------------------------->

PERIOD S1 S1A S2 S3 S4 S5 S6 ST SB S9 S10 4/6/95 45 N/S 62 <5 <3 <5 <4 <21 <17 <7 ' <4 4/10/95 44 N{S 25 28 9 <5 <8 <11 <5 <1 <6 4/13/95 28 49 <7 13 <5 <3 <4 ~

4/18/95 <10 210 <10 21 '

4/24/95 23 N/S <7 <8 I-' 5/1/95 <9 21 14 <4 00

"° 5/8/95 22 12 21 11 5/15/95 18 <6' <8 11 ' -

5/22/95 <10 <6 <9 <4 5/31/95 <5 <6 <4 <4 6/5/95 14 <8 <6 <7 6/12/95 <7 <12 <18 15

TABLE G-17 CONCENTRATIONS OF ZINC-65 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <-------------------------------------------~------------------------- STATION -------------------------------------------------------------------->

81 S1A 82 83 84

• 85 86 87 88 89

• PERIOD 810 4/6/95 <34 N/8 <38 <8 <11 <7 <9 <22 <10 <22 <13 4/10/95 46 N/8 <9 <35 <6 <14 <12 <4 <20 <16 <8 4/13/95 <13 33 <29 <9 <12 <11 <15 4/18/95 <13 269 <9 <16 4/24/95 16 <12 <17 <14 1--' 5/1/95 <21 <20 <11 <7

~

0 5/8/95 <21 <13 <19 <7 5/15/95 <13 <7. <31 <7 5/22/95 <8 <17 <14 <12 5/31/95 <16 <4 <14 <12 6/5/95 <10 <5 <19 <8 6/12/95 <21 <26 <18 <17

TAB.18 CONCENTRATIONS OF CESIUM-134 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STAT I0 N ----------------------"--------------------------------------------->

PERI.OD S1 S1A S2 S3 S4 S5 S6 S7 SB S9 S10 4/6/95 <5 N/S <5 <16 <3 <9 <3 <6 <16 <4 <11 4/10/95 <10 N/S 16 <14 <5 <4 <14 <6 <22 <5 <12 4/13/95 18 23 <28 <9 <20 <4 <18 4/18/95 <7 121 <8 12 4/24/95 <11 <6 25 <14 I-' 5/1/95 <12 <17 I 16 <13

\,()

I-'

5/8/95 <6 <4 <7 <8 5/15/95 10 <6 21 <4 5/22/95 '13 15 <7 <10 5/31/95 <4 <7 <5 <10 -

6/5/95 <5 <5 <15 <6 6/12/95 <14 <25 <9 <11

• TABLE G-19 ) '

\

CONCENTRATIONS OF CESIUM-137 IN SOIL SAMPLES DELAWARE RIVER SHORELINE LOCATIONS (Results in Units of pCi/kg-wet)

SAMPLING <--------------------------------------------------------------------- STATION -------------------------------------------------------------------->

PERIOD S1 S1A S2 S3 S4 S5 S6 S7 SB S9 S10 4/6/95 <5 N/S <18 <18 22 <4 17 21 29 30 19 4/10/95 21 N/S 20 20 21 <5 28 21 18 18 17 4113/95 <6 12 <18 <6 27 <3 20 4/18/95 15 108 18 23 4/24/95 <4 <6 24 <7 t-' 5/1/95 <6 <6 14 <5

\0 N> 5/8/95 13 11 20 19 5/15/95 12 9 23 11 5/22/95 <9 <12 21 13 5/31/95 11 <7 15 13 6/5/95 <9 <10 22 17 6/12/95 <18 28 <17 <25

TABLE G-20 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL SAMPLES AT SELECTED SOIL SAMPLING LOCATIONS (Results in Units of pCi/kg-wet) 1 3 NUCLIDE 1502 G7E1A Be-7 222 <24 131 K-40 10100 2950 704 Mn-54 <7 <4 <3 Co-58 <7 <2 <3 Fe-59 <7 <5 <3 Co-60 <8 <3 <3 Zn-65 <16 <13 <2 Cs-134 <15 <5 <3 Cs-137 <7 22 <5 (1) Sampling Period of 4/10/95.

(2) Sampling Period of 4/11/95.

(3) Sampling Period of 4/12/95 .

• 193

• TAB.21 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES AT SELECTED SURFACE WATER SAMPLING LOCATIONS (Results in Units of pCi/L)

<------------------------------------------------------------ STAT I0 N ------------------------------------------------------------

1 1 NUCLIDE DATE 11A1 12C1 16F1 1F2 7E1 1A1 1A2 2

Co-60 4/7/95 <1 <0.8 <2 <1 <0.9 <1.2 <0.8 4/11/95 . <0.6 <2.7 <0.7 <0.6 <0.8 4/14/95 <1.9 <1.1 <0.8 <1.2 <0.7 3

4/10/95 <1.9 <0.6 <0.4 <1.4 <1.3 2

Zri-65 4/7/95 <2.9 <1.7 <1.6 <2.8 <5 <2 <1 4/11/95 <2.6 <1.6 <1 <2.3 <2.4 4/14/95 <2.5 <0.7 <1.5 <1.8 <1.8 3

4/10/95 <1.4 <2.3 <1 <2.9 <2 I-'

\()

VI Cs-134 ' 4/7/95 2 <0.5 <1.1 <1.3 <1.2 <1.6 <1.3 <0.6 4/11/95 <1.7 <0.6 <0.9 <1 <0.9 4/14/95 <1.9 <1.3 <0.7 <1.5 <1.1 3

4/10/95 <0.9 <0.7 <0.6 <1.5 <1.3 2

Cs-137 4/7/95 <0.5 <1 <0.9 <1.1 <0.5 <1 <1 4/11/95 '<1.6' <1.1 <1.2 <1.2 <1.2 4/14/95 <1.6 ' <0.5 <0.9 <2.5 <0.6 3

4/10/95 <0.6 <0.9 <1.4 <1.6 <1.2 (1) Surface water locations corresponding*to nearby soil locations S1 & S1A; Sampled 4/24/95.

(2) This was the routine monthly collection period for the REMP surface water samples.

(3) Alternate surface water sampling locations along shoreline that were established in 1994.

TABLE G-22 CONCENTRATIONS OF GAMMA EMITIERS IN AIR FILTER SAMPLES AT SELECTED AIR FILTER SAMPLING LOCATIONS 3 3 (Results in Units of 10- pCi/m )

<----------------------------------------------------------'-------- STATION ------------------~----------------------------------------->

1 2 2 2 1 NUCLIDE 16E1 1F1 2F6 501 581 Be-7 184 209 245 184 149 K-40 <48 '<58 <70 <40 <59 Mn-54 <1 <2 <3 <1 <2 1--'

"° <1 <1 <1 <2 <3

°' Co-58 Fe-59 <5 <4 <8 <2 <6 Co-60 <6 <2 <4 . <1 <4 Zn-65 <5 <4 <12 <4 <8 Cs-134 <3 <4 <4 <1 <3 Cs-137 <2 <3 <3 <1 <3

)

(1) Sampling Period 4/3/95 to 4/6/95.

(2) Sampling Period 4/3/95 to 4/7/95.