ML18100A336
| ML18100A336 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 12/31/1992 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N93055, NUDOCS 9305070340 | |
| Download: ML18100A336 (170) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department APR 3 0 1993 NLR-N93055 United States Nuclear Regulatory commission Document Control Desk Washington, DC 20555 Gentlemen:
1992 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 As required by Section 6.9.1.7 of Appendix A to Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Units No. 1 and 2, and Section 6.9.1.6 of Appendix A to Facility Operating License NPF-57 for Hope Creek Generating Station, Public Service Electric and Gas hereby transmits one copy of the 1992 Annual Radiological Environmental Operating Report.
This report summarizes the results of the radiological environmental surveillance program for 1992 in the vicinity of the Salem and Hope Creek Generating Stations.
The result of this program for 1992 were specifically compared to the result of the preoperational program.
Should you have any questions or comments regarding this submittal, please do not hesitate to contact us.
Enclosure 070022
_ -~ _ The power is in your hands. __
9305070340 921231 PDR ADOCK 05000272 R
PDR Sincerely,
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~~';~na Y F ~* ~
Vice President -
Nuclear Engineering
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'fl 95-2168 REV. 11/91
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Document Control Desk NLR-N93055 2
c Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager -
Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. s. Dembek, Licensing Project Manager
- u. s. Nuclear Regulatory Commission MS 14 E-21 Washington, DC 20555 Mr. T. P. Johnson {S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 APR 3 0 1993
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ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM For Salem Generating Station, Unit 1: Docket No. 50-272 Salem Generating Station, Unit 2: Docket No. 50-311 Hope Creek Generating Station: Docket No. 50-354 1992 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1992 Prepared By PUBLIC SERVICE ELECTRIC AND GAS COMPANY RESEARCH AND TESTING LABORATORY APRIL 1993
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ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM &
HOPE CREEK GENERATING STATIONS 1992 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31, 1992
TABLE OF CONTENTS
~
PAGE
SUMMARY
1 INTRODUCTION.................................................
3 Radiation Characteristics.**.*.**..***.****. ** * * *. * *. * * *.
3 Radiation Effects.......................................
4 Sources of Radiation Exposure...........................
4 Nuclear Power Reactors..................................
7 Containment of Radioactivity..*.....**..**..*..********.
13 Sources of Radioactive Liquid and Gaseous Effluents *****
16 Radioactivity Removal from Liquid and Gaseous Wastes **..
16 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.*.*...**.*
18 Objectives........................................... _...
19 Data Interpretation.....................................
2 o Quality Assurance Program.**.*......*..***.*, *.*.*..*....
- 21 Program Changes........ *..................................
21 Results and Discussion..................................
22 Atmospheric.........................................
22 Direct Radiation.**..*...***...*.*..**...***********
25 Terrestrial............................ *.............
25 Aquatic........................................... ~.
3 3 Program Deviations......................................
39 Conclusions.............................................
39 REFERENCES. * * * * * * * * * * * * *. * * * * * * * * * * *. * * * * * * * * * *.. * * * * * * * * * * * *
- 5 2 APPENDIX A APPENDIX B APPENDIX C APPENDIX D APPENDIX E PROGRAM SUM:r-IARY. * * * * * * * *. * * * * * * * * * * * * * * * * * * * * *
- 55 SAMPLE DESIGNATION AND LOCATIONS.**.*********..
65 DATA TABLES.......... * * *................ *. * * *.
- 7 3 SYNOPSIS OF ANALYTICAL PROCEDURES *...**.***.*.. 119
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS........................................ 161
~APPENDIX F -
SYNOPSIS OF LAND USE CENSUS.*****..****.*****.. 169 i
TABLE NUMBER
- 1.
- 2.
FIGURE NUMBER
- 1.
- 2.
- 3.
LIST OF TABLES TABLE DESCRIPTION Common Sources of Radiation..............*....*....
1992 Artificial Island Radiological Environmental Monitoring Program (Program Overview).........*...*
LIST OF FIGURES FIGURE DESCRIPTION BWR. Vessel and Core................................
Schematic of BWR Power Plant.......................
Schematic of PWR. Power Plant..................**...
- 4.
Primary PWR Containment Cross-Section PAGE 6*
40 PAGE
.9 10 12 (Salem Units 1 & 2)................................
14
- 5.
BWR. Mark 1 Primary Containment Cross-Section (Hope Creek)........................................
15
- 6.
Beta in Precipitation and Air Particulate 1973 through 1992 (Quarterly)......*.**..**..*.*..*
44
- 7.
Ambient Radiation -
Off site Vs Control Station 1973 through 1992 (Quarterly)......................
45
- 8.
Iodine-131 Activity in Milk 1973 through 1992 (Quarterly)....................**
46 ii
LIST OF FIGURES (cont'd.)
FIGURE NUMBER FIGURE DESCRIPTION PAGE
- 9.
Gross Beta and Potassium-40 Activity in Surface Water 1973 through 1992 (Quarterly)......................
47
- 10.
Tritium Activity in Surface Water
- 1973 through 1992 (Quarterly). ~...... *.. *..........
48 11A.
cesium-137 Activity in Water Sediment 1977 through 1992 (Semi-Annual)...................... 49 11B.
Cobalt-60 Activity in Water Sediment 1977 through 1992 (Semi-Annual).....*.......*...*.... 50
- 12.
Strontium-90 and.Cesium-137 Activity in Soil 1974 through 1992 (Yearly).**...****.*.*....*.*.*.*** 51 iii
SUMMARY
During normal operations of a nuclear power generating station there are releases of small amounts of radioactive material to the environment.
To monitor and determine the effects of these releases a radiological environmental monitoring program (REMP) has been established for the environment around Artificial Island where the Salem Units 1 and 2 (SGS) and Hope Creek (HCGS)
Generating Stations are located.
The results of the REMP are published annually, providing a summary and interpretation of the data collected.
Additional data relating to the releases of radioactive materials to the environment can be obtained in the Radiological Effluent Release Report (RERR) which is published and submitted to the Nuclear Regulatory Commission on a semiannual frequency.
The PSE&G Research and Testing Laboratory (RTL) has been responsible for the collection and analysis of environmental samples during the period of January 1, 1992, through December 31, 1992, and the results are discussed in this report.
The radioactive liquid and gaseous effluents due to the operation of SGS and HCGS during 1992 did not adversely affect the environment around Artificial Island.
Most of the radioactive materials noted in this report are normally present in the environment, either naturally, such as potassium-40, or as a result of non-nuclear generating station activity such as nuclear bomb testing.
Measurements made in the vicinity of Artificial Island were compared to background or control measurements and the preoperational REMP study performed before Salem Unit 1 became operational.
Samples of air particulates, air iodine, precipitation, milk, surface, ground and drinking water, vegetables, beef, game, fodder crops, soil, fish, crabs, and sediment were collected and analyzed.
External radiation dose measurements were also made in the vicinity of Artificial Island using thermoluminescent dosimeters.
To demonstrate compliance with Technical Specifications (Section 3/4.12.1), most samples were analyzed for gamma emitting isotopes, tritium (H-3), strontium-89 (Sr-89) and 90 (Sr-90), iodine-131 (I-131), gross beta and gross alpha.
The* results of these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with 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:
I There were a total of 1903 analyses on 963 environmental samples during 1992.
Direct radiation dose measurements were also made using 452 thermoluminescent dosimeters (TLDs).
1
In addition to the detection of naturally-occurring isotopes (i.e. Be-7, K-40, Ra-226 and Th-232), low levels of Sr-90, and cs-137 were also detected in various media.
The detection of these radionuclides may be attributed to residual fallout from atmospheric weapons testing.
Trace levels of Mn-54, Co-58, Co-60, Sr-89, Cs-134, and Cs-137 were also detected.
The concentrations of these nuclides were well below the Technical Specification reporting limit.
I Dose measurements made with quarterly TLDs at 29 offsite locations around Artificial Island averaged 67 millirads for 1992.
An average of the control locations for this time was 70 millirads.
This was comparable to the preoperational phase of the program which had an average of 55 millirads per year for 1973 to 1976.
2
INTRODUCTION This section gives a brief description of the characteristics, effects, and sources of radiation and the operation of a nuclear generating station, both a boiling water reactor and a pressurized water reactor.
RADIATION CHARACTERISTICS The word "radioactive" describes the state of* the nucleus of an atom containing an excess of energy.
The excessive energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom.
To release this excess energy the atom emits electromagnetic or particulate radiation to become stable (non-radioactive).
This process is called radioactive decay.
Part of the electromagnetic spectrum consists of gamma-rays and x-rays, which are similar in nature to light and microwaves.
Particulate radiation may be in the form of electrically charged particles such as alpha (2 protons plus 2 neutrons) and beta (1 electron) particles, or have no charge at all (neutron)
- Radioactive decay is measured in terms of "half-life".
The half-life may be defined as the amount of time it takes for a radioactive material to decay to half of its original activity.
The half-life of a radionuclide depends on the radionuclide and can range anywhere from a fraction of a second to as long as several million years.
Each radionuclide also has a unique decay characteristic, both in terms of the energy of its radiation and the types of its radiation.
Radionuclides may decay directly into a stable element or go through a series of decays (becoming several diffe~ent 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 trillion disintegrations per minute. For the purpose of quantifying the effluents of a nuclear power reactor this unit is broken down into a microcurie and a picocurie.
The microcurie is one millionth of a curie and represents 2.2 million decays per minute, while the picocurie is one millionth of a microcurie and represents 2.2 decays per minute.
3
RADIATION EFFECTS Radiation effects are measured in terms of the amount of biological-damage produced..
Biological damage from electromagnetic and particulate radiation is produced by ionizing an atom, breaking a chemical bond, or altering the chemistry of a living cell.
To assess biological damage, the type, energy, and amount of radiation* must be considered.
There are essentially two types of exposure to radiation: external and internal.
External exposure can involve the total body, thereby implying exposure to all organs, or parts of the body, such as the arm, foot, or head.. Internal exposure, meaning the uptake of radioactive elements by inhalation, ingestion~ or by means of a cut, can involve a single selective organ or several organs.
An example of the selectivity of internal exposure is the uptake of a radioiodine which concentrates in the thyroid gland, versus the uptake of a radiocesium which will collect in the muscle and liver.
The quantity of the radionuclide and duration of time a radionuclide remains in the body directly influences the total exposure or dose to an organ.
The duration of time depends on the amount of radioactive decay and the length of time it takes to remove the radionuclide from the body (biological decay). It should be noted that the biological effect of radiation is independent of the source (internal or e~ternal) and dependent on the dose.
The measurement of dose to man is typically expressed in terms of a unit called the rem.
As a better unit of dose, the millirem (mrem; 1 mrem =1/1000 rem) is most often used because the typical dose is usually on the order of thousandths of a.rem.
Another term used is the collective dose to a population, called a person-rem.
A person-rem is calculated by adding up each individual dose to a population (e.g. 0.0001 rem to each person of a population of 10,000 persons= 1 person-rem).
SOURCES OF RADIATION EXPOSURE Radioactive elements have existed on *our planet (and on 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
1*
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), thcirium-232 (Th-232), radium-226 (Ra-226), and radon-222 (Rn-222).
Some of these radionuclides have half-lives of millions of years and are introduced into the water, soil, and air by such means as volcanoes, weathering, erosion, diffusion, and radioactive decay.
One naturally-occurring terrestrial radionuclide is a significant source of radiation exposure to the general public---radon gas.
Radon gas (Rn-222) is an inert gas produced in the ground from the radioactive decay of radium (from the decay of* uranium and thorium) and emitted into the air.
Because of the use of lime and gypsum (which would contain radium) in its production, building materials such as cinder block; sheet rock, and concrete are also radon gas sources.
Concentrations of radon gas are dependent on the concentrations of radium (uranium and thorium) in the soil, altitude, soil permeability, temperature, pressure, soil moisture, rainfall, snow cover, atmospheric conditions, and season.
The gas can move through cracks and openings into basements of puildings, become trapped in a small air volume indoors and result in higher concentrations than found outdoors.
Radon can also be dissolved in well water-and contribute to airborne radon in houses when released through showers or washing.
Since radon gas is radioactive, it, too, continues to produce, by decay, other radioactive materials referred to as radon daughters.
These daughters are solid particles which can stick to surfaces such as dust particles in the air.
The dust containing the radon daughter particles can be inhaled and deposited in the lungs.
Radon daughters emit high energy alpha particles which results.in an average dose to the lungs of 300 mrem (0.3 rem to a 10 year old) in the United States.
In areas such as New Jersey and Pennsylvania, over a geological formation known as the Reading Prong, doses much higher than 300 mrem/yr have been recorded due to natural deposits of uranium.
Doses due to radon gas and its daughters are the highest dose contributor to individuals from all natural sources.
Cosmic rays are high energy electromagnetic rays which originate from outer space.
About 300 cosmic rays pass through each person every second.
Cosmic rays also interact with atoms in the earth's atmosphere and produce radioactive substances such as carbon-14 (C-14), sodium-22 (Na-22), beryllium-7 (Be-7), and tritium (H-3).
Some of these radionuclides become deposited on land and water while the rest remain suspended in the atmosphere.
Other naturally-occurring sources of radiation which contribute to doses to the human body are trace amounts of uranium and radium in drinking water and radioactive potassium in milk.
Sources of naturally-occurring radiation and their average dose contribution are summarized in Table 1.
5
Natural Sources Cosmic Rays Building Materials Internal Ground Radon APPROXIMATE TOTAL TABLE 1 COMMON SOURCES OF RADIATION*
Approximate Dose Cmrem/yearl 42 35 28 11 300 400 Manmade Sources Medical radiation Television and consumer products Weapons Fallout Nuclear Power Plants
Reference:
NUREG-0558 and EPA Report ORP/SID 72-1 Approximate.
Dose Cmrem/yearl 90 1-5 2-5 1
100 The average individual in the United States receives approximately 100 mrem per year from natural sources.
In some areas the dose from natural radiation is significantly higher.
Residents of Colorado receive an additional 80 mrem per year due to the increase in cosmic (higher elevation) and terrestrial radiation levels.
Transcontinental and intercontinental airline pilots receive 1000 mrem/yr due to the high elevation and length of these flights and resultant higher cosmic radiation levels.
In several
.locations around the world high concentrations of mineral 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 of heat.
When one fission occurs more neutrons are given off which leads to more atoms to fission, producing more neutrons etc., thus giving rise to a chain reaction.
The atom bomb, using large masses of fissionable material, is a chain reaction uncontrolled.
Nuclear reactors, on the other hand, use small masses of fissionable material (thus making it impossible for a nuclear explosion), and are therefore able to sustain a controlled chain reaction~
The best known and most widely used material for the fission reaction is uranium-235.
Most uranium exists in the form U-238 (238 refers to the atomic mass, i.e., the number of protons and neutrons combined). *However, it also exists in the form of uranium-235 which is in a proportion of one atom per 140 atoms of U-238.
Uranium~235 becomes very unstable when its nucleus is struck by a neutron.
To overcome the instability, the uranium atoms.split (fission) and become two fission products (e.g. Iodine 131 and Xenon 133).
When the fission occurs, some neutrons are released to initiate another fission and start a chain reaction.
There are several different ways to control the rate of a chain reaction.
Some of these means are the use of moderators, varying the size of a reactor vessel, and using neutron absorbing materials (such as cadmium) as control rods.
7
There are three major types of nuclear reactors in operation in the world:
the pressurized light-water reactor (PWR), boiling light-water reactor (BWR), and the gas-cooled reactor.
The nuclear reactors built and operating on Artificial Island are the BWR (Hope Creek) and the PWR (Salem Units 1 and 2).
Of the two types of light-water reactors (LWR), the BWR has a simpler design.
In a BWR the steam desired to generate electricity is produced in the core itself.
Here, step by step, is how the BWR works (refer to Figures 1 and 2):
- 1.
Water enters the reactor vessel through the reactor core which consists of 764 fuel assemblies.
Each assembly consists of 64 zirconium alloy fuel rods about 13 feet long.
Sixty-two of these rods contain uranium fuel pellets. The fuel pellets have been enriched so that the U-235-to-U-238 ratio is now one atom of U-235 to every 20 to 40 atoms of U-238.
The core is contained in a 6" thick steam reactor vessel about 75 feet high and weighing 624.tons.
- 2.
The water flows along the fuel rods.
Then, when the 185 control rods (containing boron carbide) are withdrawn, the fissioning process in. the fuel rods generates heat that causes the water passing through the core to boil into steam in the reactor vessel.
- 3.
The steam flows through the steam lines at the top of the
. reactor directly into a turbine generator (see Figure 2).
- 4.
In the turbine, the force of the steam striking the blades attached to a shaft causes the shaft to spin.
- 5.
The shaft spins inside a generator, causing a magnetic field to move through coils of wire to produce electricity.
- 6.
A second separate water system, carrying cooling water from an outside source (e.g. the cooling tower located on Artificial Island), condenses. the steam back to water.
- 7.
The condensed water is then pumped back into the reactor vessel to start the entire cycle again.
The fission chain reaction is controlled by the 185 control rods located between the fuel assemblies.
These control rods contain material which absorbs neutrons and controls the rate of fissioning.
By moving the control rods up or down, the reactor can sustain a chain reaction at desired power levels.
By inserting them all the way into the reactor core, fissioning can be completely stopped.
8 1'.1
FEEDWATER (FROM CONDENSER)
REC IR CU LA Tl 0 N PUMP BWR VlSSEL & CURl JET PUMP REClf~CULATION PUMP
I-'
0 FIGURE. 2 SCHEMATIC OF BWR POWER PLANT DRYWELL (PRIMARY CONTAINMENT) 1
~
SHIELD BUILDING STEAM -------1>
REACTOR ~-..----.---i,------~
VESSEL PRESSURE SUPPRESSION POOL (TORUS)
TURBINE t-WATER RE Cl RC PUMP GENERATOR COOLING TOWER
A PWR differs from a BWR in that water inside the reactor vessel system is pressurized to prevent boiling (steam) when heated. This pressurized hot water is used to heat a second source of water, at a lower pressure, which will produce steam to turn the turbines.
The following step-by-step outline indicates how the PWR works (see Figure 3):
- 1.
Within the 424-ton reactor vessel at SGS, water flows across 193 fuel assemblies in the reactor core.
Each assembly consists of 264 fuel rods, each about 15 feet long.
2 *. The water flows.along the fuel rods.
When the 53 control rods are raised, the fissioning process begins and the water is heated to about 600~F by the nuclear fission process.
This water is referred to as the primary coolant.
The primary coolant is maintained at about 2000 psi of pressure
- to keep the water from boiling, hence a pressurized water system.
- 3.
The primary coolant flows from the reactor as a hot liquid to tubes in the steam generators where the water gives up its heat (cooled) to the water in the steam generator.
The water in the steam generator is called secondary coolant.
The primary water, after giving up its heat, is returned to the reactor core to start the process over.
- 4.
The secondary coolant in the steam generator is not under high pressure and turns to steam because of the primary coolant heat-up.
This steam is sent through steam lines to the turbine generator to generate electricity in the same
-method as outlined in the BWR description above.
- 5.
The exhausted steam from the turbine is channeled into the condenser below the turbine, cooled back into water and returned to the steam generators.
The cooling action of the condenser is provided by a third (tertiary coolant) system of circulating water drawn from a river, ocean, or lake (at SGS, this is the Delaware River).
About 65 percent of the nuclear power plants in the United States are PWRs and 35 percent are BWRs.
The PWR is also used in nuclear submarines and other naval vessels
- 11
FIGURE 3 STEEL (SHELL) LINER REACTOR
. REACTOR
. PRIMARY COOLANT SYSTEM REACTOR
-: COOLANT PUMP STEAM GENER-ATOR SCHEMATIC OF PWR POWER PLANT OUTER CONCRETE (CONTAINMENT SHIELD)
PRIMARY SYSTEM SECONDARY SYSTEM TURBINE CONDENSER WATER (CONDENSATE)
[ -111
. ---llJ GENERATOR 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.
The fission products that are gaseous or volatile migrate out of the fuel.
Encasing the fuel pellets are metal fuel rods (known as fuel cladding) designed to retain the fuel pellets.
The small fraction of fission products that might leave the fuel pellets (such as the gaseous products) are collected here in small gaps between the fuel pellets and cladding.
The next barrier level is the cooling water which is circulated around the fuel rods.
The fission and activation products (such as radioiodines, strontiums, and cesiums) are soluble and are retained in the coolant.
These materials can be removed by filter and purification systems.used for the coolant.
The next level is the reactor vessel.
The reactor vessel is a steel structure (6 to 8 inches thick) which contains the fuel rods and coolant.
The vessel and its coolant systems provide containment for all radionuclides.in the coolant.
From here the PWR and BWR differ in structure.
The next barrier around a PWR reactor vessel is the containment building which is a four-foot thick, steel-reinforced (Salem Units 1 and 2 also include a steel liner) concrete structure (see Figure 4).
It is designed to contain water and gases which may accidentally escape the above barriers.
The containment is also designed to withstand tornadoes, floods, and earthquakes.
In a BWR, the reactor vessel is contained in a drywell and pressure suppressioQ chamber (see Figure 5).
This system is designed to reduce the pressure and water build-up that may occur during a break in the steam piping.
The walls of the drywell (which are two feet thick) consist of concrete with a steel containment shield over the reactor vessel top.
The reactor vessel and drywell system is surrounded by a steel reinforced reactor building structure (see Figure 2)
- 13
FIGURE 4 PRIMARY PWR CONTAINMENT CROSS-SECTION (SALEM UNITS 1 & 2) 191' 6" GROUND LEVEL FAN COIL UNIT STEAM GENERATOR POLAR GANTRY CRANE 156'6" 14 STEAM GENERATOR ACCUMULATOR FAN COIL UNIT CONCREE 4'-6'.
GROUND LEVEL.
DRY WELL FIGURE 5 BWR MARK I PRIMARY CONTAINMENT CROSS-SECTION (HOPE CREEK)
I REC I RC PUMP
\\ PRESSUR~ SUPPRESSION POOL 15
SOURCES OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS Under normal operating conditions for nuclear power plants most of the fissiori 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 dem_ineralizers in the purification system of the primary coolant.
The noble gas fission products have a very low solubility in the primary coolant and therefore cannot be removed by the demineralizers.
Instead, they are released as a gas when the primary coolant is depressurized and are collected by a system designed for gas collection and decay.
This represents the principal source of gaseous effluents.
Small releases of radioactive liquids from valves, piping, or equipment associated with the primary coolant system may occur in the reactor, auxiliary, and fuel handling buildings.
The noble gases become part of the gaseous wastes, while the remaining radioactive liquids are collected in floor and equipment drains and sumps and are processed prior to release.
Processed primary coolant water that does meet chemical specifications for reuse may
.. also become waste water.
These represent the principal sources of liquid effluents.
RADIOACTIVITY REMOVAL FROM LIQUID AND GASEOUS WASTES In a nuclear power plant, radioactive liquid and gaseous wastes are collected, stored, and processed through processing systems to remove or reduce most of the radioactivity (exclusive of tritium) prior to reuse within the plant or discharge to the environment.
These primary systems are required by Technical Specifications to be installed and operable and help to ensure that all releases of radioactive liquid and gaseous effluents are as-low-as-reasonably-achievable (ALARA).
At both SGS and HCGS, liquid waste is routed through demineralizers and fil te.rs which clean the water for recycling.
If the demineralized water does not meet the requirements for reuse, the water is stored in tanks for sampling and then analyzed for radioactivity and chemical content before being discharged to the Delaware River.
If the water does not meet the requirements for release to the environment, then the liquid wastes are processed through the appropriate portions of the liquid waste treatment system to provide assurance that the releases of radioactive liquid effluents will be kept ALARA.
All 16
concentrates produced from the demineralizers a.re packaged as solid waste for shipment and burial at an offsite burial facility.
At Salem, the circulating water system provides an additional minimum of 185,000 gallons per minute dilution flow for liquid releases.
-At Hope Creek, the cooling tower provides a minimum of 19,000 gallons per minute dilution flow prior to discharge to the Delaware River.
The average flow rate of the Delaware River is five million gallons per minute and provides additional dilution.
In SGS, the waste gases collected by the vent header system are first routed to the gas compressors which compress the gases into waste gas decay tanks.
After a waste gas decay tank is filled, the tank contents may be stored for a period up to 90 days (generally) to allow for decay of the shorter-lived radionuclides.
In HCGS, the waste gases from the mairi condenser air ejectors are collected and delayed from release in the offgas system.
The discharge of most waste gases at HCGS and SGS is made through high efficiency particulate air (HEPA} filters and charcoal filters prior to release.
The filters are rated to be 95% efficient for iodines and greater than 99%.efficient for removal of particulates.
Noble gases, however, cannot be removed by these filters.
Gaseous effluents are discharged through elevated vents which enhances atmospheric dispersion and dilution.
Radioactive effluent releases are limited and contr.olled by release concentrations and dose limits, per Technical Specifications and the U.S. Nuclear Regulatory Commission's regulation in Titl~ 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
'l'HE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Artificial Island is the site of Salem and Hope Creek Generating stations.
The Salem Generating station (SGS) consists of two operating pressurized water nuclear power reactors.
Salem Unit One has a net rating of 1115 MWe (3411 MWt), and Salem Unit Two has the same rating at 1115 MWe (3411 MWt).
The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which has a net rating of 1067 MWe (3293 MWt)
- Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic fill from dredging operations. It is located in Lower Alloways Creek Township, Salem County, New Jersey.
The environment surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands.
These land types make up approximately 85% of the land area within five miles of the site.
Most of the remaining land is used for agriculture [5,6]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Reports [5,6], Environmental Statements [7,8], and the Updated Final Safety Analysis Report for SGS [9] and the Final Safety Analysis Report for HCGS [10].
Since 1968, an off-site Radiological Environmental Monitoring Program (REMP) has been conducted at the Artificial Island Site.
Starting in December, 1972, more extensive radiological monitoring programs were initiated.
The operational REMP was initiated in December, 1976, when Salem Unit-1 achieved criticality.
The PSE&G Research and Testing Laboratory (RTL), has been involved in the REMP since its inception.
The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL.-
From January, 1973, through Jtine, 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results.
RMC reports for the the preoperational and operational phase of the program are referenced in this report [1-3].
On July 1, 1983, the RTL assumed primary responsibility for the analysis of all samples (except TLDs) and the reporting of results.
Teledyne Isotopes (TI), Westwood, NJ, at that time, took over responsibility for third-party QA analyses and TLDs.
An additional vendor, Controls for Environmental Pollution Inc., had been retained to provide third-party QA analyses and certain non-routine analyses from May 1988 up until June 1, 1992.
At this time, TI is our sole QA vendor.
RTL reports for the operational phase from 1983 to 1991 are referenced in this report [4]~
18
~-----
An overview of the 1992 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, 1992, for the Artificial Island Radiological Environmental Monitoring Program.
OBJECTIVES The objectives of the Operational Radiological Environmental Monitoring Program are:
To fulfill the obligations of the Radiological surveillance sections of the Technical Specifications for the Salem Generating Station (SGS) and the Hope Creek Generating Station (HCGS).
To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways.
To determine if SGS or HCGS has caused an increase in the radioactive inventory of long-lived radionuclides.
To detect any change in ambient gamma radiation levels.*
To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on the environment.
This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.1.7 of the Hope Creek Technical Specifications, summarizes the findings of the 1992 REMP.
Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Artificial Island have been summarized for purposes of comparison with subsequent operational reports [2].
In order to meet the stated objectives, an appropriate operational REMP was developed.
Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms.
The selection of sample types was based on: (1),
established critical pathways for the transfer of radionuclides through.the environment to man, and, (2), experience gained during the preoperational phase.
Sampling locations were determined from site meteorology, Delaware estuarine hydrology, local demography, and land uses.
19
Sampling locations were divided into twd 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 1992.
Appendix B describes the coding system which identifies sample type and location.
Table B-1 lists the sampling stations and the types of samples collected at each station.
These sampling stations are indicated on maps B-1 and B-2.
DATA INTERPRETATION Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix c.
All results above the lower limit of detection (LLD) are at a confidence level of 2 sigma.
This represents the range of values into which 95% of repeated analyses of the same sample should fall.
As defined in Regulatory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability, with only 5% probability of falsely concluding that a blank observation represents a "real signal".
LLD is normally calculated as 4.66 times one standard deviation of the background count, or of the blank sample count, as appropriate.
The grouped data were averaged and standard.deviations calculated in acco~dance with Appendix B of Reference 16.
Thus, the 2 sigma deviations of the averaged data represent sample and not analytical var1ability.
For reporting and calculation of averages, any result occurring at or below the lower limit of detection is considered to be at that limit.
When a group of data was composed of 50% or more LLD values, averages were not calculated.
Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium.
This method, however, is only representative of the sampled medium for that specific location and instant of time.
20
As a result, variation in the radionuclide concentrations of the samples will normally occur.
since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid.
QUALITY ASSURANCE PROGRAM The PSE&G Research and Testing Laboratory (RTL), has a quality assurance program designed to maximize confidence in the analytical procedures used.
Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review.
The analytical methods utilized in this program are summarized in Appendix D.
The quality of the results obtained by the RTL is ensured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Plan [17] and the
- Environmental and Chemical Services Division Procedures Manual [18].
The internal quality control activity of the Laboratory includes the quality contror of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spike'd samples.
The external quality control activity is implemented through participation in the USEPA Laboratory Intercomparison Studies Program.
These results are listed in Tables E-1 through E-5 in Appendix E.
PROGRAM CHANGES Effective on June 1, 1992, Controls for Environmental Pollution, Inc. (CEP) was replaced as our QA vendor laboratory by Teledyne Isotopes, Inc. (TI).
In order to eliminate ambiguity, the technical specifications for the Salem Generating Stations were changed to reflect the guidance provided in the USNRC Branch Technical position on detection capabilities.
The Branch Technical position provided a table which lists detection requirements for I-131 analyses in water when a pathway to the public exists, and when a pathway does not exist.
A footnote to the table indicates that a LLD for I-131 analyses of 1 pCi/L should be achieved wherever a drinking water pathway prevails.
Since this footnote was missing from Table 4.12-1 of our Salem Technical Specifications, it was recommended by our Quality Assurance Department that, high sensitivity I-131 analyses should be performed on all water samples.
As a result, until the Salem Technical Specifications could be changed, PSE&G elected to analyze brackish surface water samples for I-131 to a sensitivity of 1.0 pCi/L.
The Salem Generating Station Unit 1 Technical Specifications were amended on June 8, 1992 and high sensitivity I-131 analyses were not performed on surf ace water samples collected after August 1992
- 21
RESULTS AND DISCUSSION The analytical results of the 1992 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic.
The analytical results for the 1992 REMP are summarized in Appendix A.
The data for individual samples are presented in Appendix c.
The data collected demonstrates that SGS Units 1 and 2 and HCGS were operated in compliance with Technical Specifications.
The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating Stations Technical Specifications.
The summary tables in this report include these additional samples and analyses.
ATMOSPHERIC Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers.
Iodine was collected from air by adsorption on triethylenediamine (TEDA) impregnated charcoal cartridges connected in series after the air particulate filters.
Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure.
Precipitation was collected in a Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area.
The collector is automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition.
Samples were collected monthly and transferred to new polyethylene containers.
The collector was rinsed with distilled water to include residual particulates in the precipitation samples.
Tritium results were corrected for the tritium content of the distilled water.
Air Particulates (Tables C-1, C-2, c~J)
Air particulate samples were collected at six locations.
Each of the 312 weekly samples collected were analyzed for gross alpha (management audit analysis} and gross beta.
Quarterly composites of the weekly samples from each station were analyzed for specific gamma emitters and a single quarterly composite sample was analyzed for Sr-89 and Sr-90 as a management audit analysis.
Total data recovery for the six sampling stations during 1992 was 99.7 percent.
I Gross alpha activity was detected in 212 of the indicator station samples at concentrations ranging from 0.7 10-3 to 5.2 10-3 pCi/m3
- Gross alpha activity was detected in 50 control station samples at levels ranging from 1.0 x 10-3 to 5.2 x 10-3 pCi/m3
- LLD sensitivities for the remaining 49 indicator and control station samples ranged from <0.7 x 10-3 to <5.0 x 10-3 pCi/m3
- 22
I I
One weekly sample from indicator station 5Dl, was lost by our vendor laboratory, Teledyne Isotopes, before being analyz'ed.
Samples analyzed by Controls for Environmental Pollution Inc.,
as part of the interlaboratory comparison program, were all
<5.0 x 10-3 pCi/m3 and are not included in the calculations for determining the yearly mean.
The grand average was 2.2 X 10-3 The maximum preoperational level detected was 7.8 x 10-3 3
pCi/m
- Gross beta activity was detected in 259 of the indicator station samples at concentrations ranging from 2.5 x 10-3 to 37 x 10-3 pCi/m3 and in 52 control station samples from 9 x 10-3 to 42 x 10-3 pCi/m3
- One weekly sample from indicator station 5Dl, was lost by Teledyne Isotopes before being analyzed.
The avera¥~ for both indicator and control station _
samples was 21 x 10-8Ci/m3
- The maximum preoperational level detected was 920 x 10-pCi/m3, with an average of 74 x 10-3 pCi/m3
- Gainma spectrometric analysis performed on each* of the 23 quarterly composite samples analyzed (location 5Dl for the first quarter was lost by CEP), indicated the presence of the naturally-occurring radionuclides Be-7 and K-40.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Beryllium-7, attributed to cosmic ray activity in the atmosphere, was detected in all nineteen indicator station composites that were analyzed, at concentrations ranging from 54 x 10-3 to 95 x 10-3 pCi/m3 and in the four control station composites from 55 x 10-3 to 81 x 10-3 pCi/m3
- The maximum preoperational level detected was 330 x 10-3 pCi/m3,
with an average of 109 x 10-3 pCi/m3
- o Potassium-40, a naturally occurring radionuclide, was detected in four of the indicator stations' composites at concentrations ranging from 11 x 10-3 pCi/L to 18 x 10-3 K-40 was detected in two of the control comfosite samples at concentrations of 10 X 10-3 and 12 X 10-pCi/m3
- No preoperation data is available for comparison.
I Strontium-89 and strontium-90 analyses were performed on four indicator station composites and one control station composite from the first quarter composites as management audit analyses.
o Strontium-89 was detected in one of the indicator composites analyzed at a concentration of 0.4 X 10-3 pCi/m3, and one control composite at 0.3 X 10-3
- LLD sensitivities for the indicator station samples were <O. 3 x 10-3 pCi/m3 The maximum preoperational level detected was 4.7 x 10-3 pCi/m3
- o strontium-90 was not detected in any of the indicator station composites analyzed.
LLD sensitivities for both the indicator and control station samples were <0.2 x 10-3
- The maximum preoperational. level detected. was 3. o x 10-3 pCi/m3
- 23
Air Iodine (Table C-4)
Iodine in filtered air samples was collected at six locations.
of the 311 weekly samples collected was analyzed for I-131.
I Iodine-131 was not detected in any of the 311 weekly samples analyzed.
LLD sensitivities for the remaining 259 indicator station samples ranged from <2.4 x 10-3 to <40 x 10-3 pCi/m3
- LLD sensitivities for the 52 control station samples ranged from.* <1. 9 x 10-3 to <13 x 10-3 pCi/m3
- The maximum preoperational level detected was 42 x 10-3 pCi/m3
- Precipitation (Tables C-6)
Although not required by the SGS or HCGS Technical Specifications, monthly precipitation samples were collected at a location in the town of Salem as management audit samples.
Each of-the twelve monthiy samples collected were analyzed for gross alpha, gross beta, tritium and gamma emitters.
I Gross alpha activity was detected in two.of the twelve samples at a concentration of 1.4 pCi/L.
LLD sensitivities for the remaining eight samples ranged from <0.8 to <3.7 pCi/L.
The maximum preoperational level detected was 4.7 pCi/L.
I Gross beta activity was detected. in all twelve samples at concentrations ranging from 1.1 to 15 pCi/L, with an average of 4.6 pCi/L.
The maximum preoperational level detected was 71 pCi/L, with an average of 19 pCi/L.
I Tritium activity was detected in five of the twelve samples for an average of 330 pCi/L.
LLD sensitivities for the samples ranged from <130 to <170 pCi/L.
The maximum preoperational level detected was 610 pCi/L, with an average of 216 pCi/L.
I Gamma spectrometric analysis was performed on all twelve of the monthly samples.
Analysis indicated the presence of the naturally-occurring radionuclide Be-7 and K-40.
All other gamma emitters searched for were below the Lower Limit of Detection. -
o Beryllium-7, attributed to cosmic ray activity, was detected
- in all twelve samples at concentrations ranging from 43 to 160 pCi/L, with an average of 84 pCi/L.
The maximum preoperational level detected was 79 pCi/L, with an average of 29 pCi/L.
The increase in the naturally-occurring Be-7 activity over preoperational levels is most likely due to spallation reactions in the upper atmosphere.
o Potassium-40 activity was detected in three samples at concentrations ranging from 56 to 140 pCi/L.
The maximum preoperational level detected was 18 pCi/L.
This increase over preoperational levels is most likely due to the sampling stations relatively close proximity to an estuarian environment.
24
DIRECT RADIATION Ambient radiation levels in the environs were measured with energy-compensated caso4 (Dy) thermoluminescent dosimeters (TLDs) supplied and read by Teledyne Isotopes.
Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances.
Direct Radiation (Tables C-7, C-8)
A total of 41 locations were monitored for direct radiation during 1992, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations, 15 off-site indicator stations and 3 control stations.
An additional 14 quarterly measurements were taken at schools and population centers, with 3 additional controls beyond the 10 mile zone in Delaware.
I Four readings for.each TLD at each location were taken in order to obtain a more statistically valid result.
For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4.
o The average dose rate for the 15 monthly off-site indicator TLDs was 7.0 millirads per standard month, and the corresponding average control dose rate was 7.6 millirads per standard month.
The preoperational average monthly TLD readings was 4.6 millirads per standard month.
o The average dose rate for the 29 quarterly off-site indicator TLDs was 5.6 millirads per standard month, and the average control rate was 5.8 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 1992.
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.
25
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 pelts and gutted.
The carcasses are packed in plastic bags and kept chilled in ice chests during transport.
Soil is sampled every three years at ten locations including one control.
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 or the area.
Milk (Tables C-9, C-10)
Milk samples were collected at four local dairy farms.
Samples were collected semi-monthly when cows were on pasture and monthly when cows were not on pasture.
Animals are considered on pasture from April to November of each year.
Each sample was analyzed for I-131 and gamma emitters. In addition, although not specifically required by the.SGS and HCGS Technical Specifications, one sample from each location was analyzed for Sr-89 and Sr-90 in order to maintain the data base developed in prior years.
I 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 1 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.
I Gamma spectrometric analysis performed on each of the 80 samples indicated the presence of the naturally-occurring radionuclide K-40.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Potassium-40 was detected in all 80 samples.
Concentrations for the 60 indicator station samples ranged from 1100 to 1600 pCi/L, with an average of 1390 pCi/L.
The 20 control station sample concentrations ranged from 1100 to 1400 pCi/L, with an average of 1330 pCi/L.
The maximum preoperational level detected was 2000 pCi/L, with an average of 1437 pCi/L.
I Strontium-89 and strontium-90 analyses were performed on three indicator station samples and one control station sample from the first sampling period in July, as management audit samples.
o Strontium-89 was not detected in any of the three indicator samples analyzed nor in the control station sample.
26
LLD sensitivities for the indicator samples ranged from <1.0 to <1.2 pCi/L and for the control station at <1.2 pCi/L.
The maximum preoperational level detected was 14 pCi/L.
o Strontium-90 was detected in all of the three indicator samples analyzed.
Average concentrations for the indicator station samples was 2.1 pCi/L and for.the control station sample at 2.4 pCi/L.
The average concentration for all samples was 2.2 pCi/L.
The maximum preoperational level detected was 12 pCi/L, with an average of 3.5 pCi/L.
The presence of Sr-90 in the samples can be attributed to fallout from previous nuclear weapons testing.
Well Water (Tables C-11, C-12, C-13)
Although wells in the vicinity of the Salem and Hope Creek Generating Station are not directly affected by plant operations, water samples were collected monthly from one indicator well and one control well during January through December of the year.
Each sample was analyzed for gross alpha, gross beta, potassium-40, tritium, I-131 and gamma emitters.
Quarterly composites were analyzed for Sr-89 and Sr-90.
I Gross alpha activity was detected in one of the indicator station samples at a concentration of 2.4. pCi/L.
Activity was not detected in any of the control station samples.
LLD values ranged from <0.8 to <3.5 pCi/L.
The maximum preoperational level detected was 9.6 pCi/L.
I Gross beta activity was detected in all 24 samples.
Concentrations for the 12. indicator station samples ranged from 2.2 to 7.8 pci/L, with an average of 4.1 pCi/L.
Concentrations for the 12 control station samples ranged from 8.7 to 11 pCi/L, with an average concentration of 10 pCi/L.
The combined average for both stations was 7.0 pCi/L.
The maximum preoperational level detected was 38 pCi/L, with an average of 9 pCi/L.
I Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples.
Concentrations for the 12 indicator station samples ranged from 2.0 to 10 pCi/L, with an average of 4.6 pCi/L.
Concentrations for the 12 control station samples ranged from 5.6 to 21 pCi/L, with an average of 10.8 pCi/L. The average concentration detected for all samples was 7.7 pCi/L.
The maximum preoperational leve.1 detected was 19 pCi/L, with an average of 7.8 pCi/L.
I Tritium activity was not detected in. any of the indicator station samples, and in one of the control station samples at at a concentration of 210 pCi/L.
The LLD sensitivities for the remaining 23 samples ranged from <130 to <190 pCi/L.
The maximum preoperational level detected was 380 pCi/L.
27
I Gamma spectrometric analysis performed on each of the 12 indicator station and 12 control station water samples
- indicated the presence of the naturally-occurring radionuclides.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Radium-226 was detected in ten of the indicator station samples at concentrations ranging from 2 to 45 pCi/L eleven control stati~n samples from 11 to 180 pCi/L.
sensitivities for the remaining three samples ranged
<2.2 to <2.9 pCi/L. The maximum preoperational level detected was 2.0 pCi/L.
and in LLD from These values are similar to those found last year. However, as with the 1989, 1990 and 1991 results, they are higher values than found in the preoperational program.
We believe that results are higher due to a procedural change in which the samples are no longer boiled down to a 100 ml standard geometry.
This change results in less removal of radon (and its daughters) from the sample.
Since Ra-226 is an alpha emitter, its identification by gamma isotopic analysis is obtained by counting the gamma rays from Pb-214, one of its daughter products.
We believe that values currently being observed are typical for this geographical area.
o Potassium-40 was detected in three indicator station samples with concentrations ranging from 48 to 58 pCi/L, and an average of 52.7 pCi/L.
K-40 was detected in three control station samples ranging from 55 to 75 pCi/L, and an*average
.of 66. 3 pCi/L.
The maximum preoperational level detected was 30 pCi/L.
I Strontium-89 and strontium-90 analyses were performed on quarterly composites of the monthly well water samples.
o strontium-89 was not detected in any of the four indicator station or four control station composites.
LLD sensitivities for the indicator samples ranged from <0.5 to
<0.6 pCi/L and for the control samples from <0.5 to <0.6 pCi/L.
The maximum preoperational level detected was <2.1 pCi/L.
o strontium-90 was not detected in any of the four indicator station or four control station composites.
LLD sensitivities for indicator samples ranged from <0.4 to <0.5 pCi/L and for the control samples from <0.4 to <0.5 pCi/L.
The maximum preoperational level detected was 0.87 pCi/L.
I Iodine-131 was not detected in any of the twelve indicator station samples or control station samples.
LLD sensitivities for all the stations, indicator and control samples, ranged from <0.1 to <0.8 pCi/L.
28
Potable Water (Tables C-14, C-15, C-16)
Both raw and treated potable water samples were collected from the Salem water treatment plant.
Each consisted of daily aliquots composited into a monthly sample.
The raw water source for this plant is Laurel Lake and adjacent wells.
Each of the 24 individual samples was analyzed for gross alpha, gross beta, K-4o; 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 two raw water samples at concentrations of 1.1 and 1.4 pCi/L and in one treated water sample at 1.9 pCi/L.
These values are within the variations of the LLD sensitivities for the remaining 21 samples which ranged from <0.8 to <3.6 pCi/L.
The maximum preoperational level detected was 2.7 pCi/L.
Gross beta activity was detected in all 24 samples at concentrations ranging from 2.2 to 4.9 pCi/L for the raw water and from 1.7 to 3.8 pCi/L for treated water.
The average concentration for both raw and treated was 3.0 pCi/L.
The maximum preoperational level detected was 9.0 pCi/L, with an average of 4.2 pci/L.
Potassium-40 activity (determined by atomic absorption) was detected in all 24 samples at concentrations ranging from 1.2 to 3.3 pCi/L for the raw water and from 1.0 to 3.2 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 four raw water samples at concentrations of 180 to 320 pCi/L, and in one treated water sample at 230 pCi/L.
LLD sensitivities for the remaining 19 samples ranged from <120 to <190 pCi/L.
The maximum preoperational level detected was 350 pCi/L, with an average of 179 pCi/L.
Iodine-131 measurements to a sensitivity of 1.0 pCi/L were performed.
Since the receiving water body is brackish, the water is not used for human consumption.
Drinking water supplies are not affected by discharges from the site.
Iodine-131 measurements for all 24 samples were below the LLD sensitivities.
The LLD sensitivities ranged from <0.2 to <0.7.
I Gamma spectrometric analysis performed on each of the 24 monthly water samples indicated the presence of the naturally-occurring radionuclide Ra-226 in one sample, and K-40 in seven samples.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Since gamma analy~es does not required 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.
29
Although K-40 was detected in seven samples at concentrations ranging from 39 to 65 pCi/L with an average of 54.9 pCi/L, the minimum detection value for K-40 analyses as indicated by the LLD, ranged from <7.8 to <60 pCi/L.
No preoperational data is availabe for comparison.
o Radium-226 was only detected in one potable raw sample at a concentration of 7.9 pCi/L.
LLD sensitivities ranged from
<1.8 to <9.4 pCi/L.
The maximum preoperational level detected was 1.4 pCi/L.
I Strontium-89 and strontium-90 analyses were performed on quarterly composites of the daily raw and treated water samples.
o Strontium-89 was not detected in any of the four raw or treated water composites.
LLD sensitivities for the raw water sample composites ranged from <0.5 to <1.1 pCi/L and for the treated water sample composites from <0.5 to <0.7 pCi/L.
The maximum preoperational level-detected was 1.1 pCi/L.
o Strontium-90 was not detected in any of the four raw or
-treated water saniple composites.
LLD sensitivities for the four treated water sample composites ranged from <0.5 to
<0.6 pCi/L and for the raw water sample composites from <0.5 to <0.9 pCi/L.
The maximum preoperational level detected was 2.1 pCi/L.
Vegetables (Table C-17)
Although vegetables in the region are not irrigated with water into which liquid plant effluents have been discharged, a variety of food products grown in the are~ for human consumption were sampled at five indicator stations (12 samples) and three control stations (7 samples).
The vegetables collected as management audit samples are analyzed for gamma emitters and included asparagus, cabbage, sweet corn, peppers and tomatoes.
Gamma spectrometric analysis performed on each of the seventeen samples indicated the presence of the naturally
- occurring radionuclide K-40 and Be-7.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Potassium-40 was detected in all nineteen samples.
Concentrations for the twelve indicator station samples ranged from 1500 to 5600 pCi/kg-wet and for the eight control station samples from. 1700 to 3700 pCi/kg-wet.
The average concentration detected for all samples was 2753 pCi/kg-wet.
The maximum preoperational level detected was 4800 pCi/kg-wet, with an average of 2140 pCi/kg-wet.
30
o *Beryllium-7 was detected in only one of the indicator station samples at a concentration of 360 pCi/kg-wet, but was not detected in any of the control station samples.
LLD sensitivities for the indicator station samples ranged from
<13 to <340 pCi/kg-wet, and for the control station samples from <17 to <100 pCi/kg-wet.
No preoperational data is available for comparison.
Game (Table C-18)
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.
The samples, when available, are collected from two locations once a year as management audit samples and analyzed for gamma emitters.
Samples from two locations w~re collected during the month of February to satisfy this requirement.
I Gamma spectrometric analysis of the flesh indicated the presence of the naturally-occurring radionuclide K-40.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Potassium-40 was detected in the indicator station sample at a concentration of 2400 pCi/kg-wet and the control station sample at 2200 pCi/kg-wet.
The average for both muskrat samples was 2300 pCi/kg-wet.
The maximum preoperational level detected was 27000 pCi/kg-wet, with an average of 4400 pCi/kg-w_et.
Fodder Crops (Table C-19)
Although not required by the SGS or HCGS Technical Specifications, nine samples of crops normally used as cattle feed were collected from four indicator stations (7 samples) and one control station (2 samples). It was determined that these products may be a significant element in the food-chain pathway.
Fodder crops are collected as management audit samples and analyzed for gamma emitters.
Four of the locations from which samples were collected are milk sampling stations.
Samples collected for wet gamma analysis included silage and soybeans.
I Gamma spectrometric analysis performed on each of the nine samples indicated the presence of the naturally-occurring radionuclides Be-7 and K-40.
All other gamma emitters searched for were below the Lower Limit of Detection.
o Beryllium-7, attributed to cosmic ray activity in the atmosphere., was detected in the three silage samples from the indicator stations at concentrations ranging from 640 to 700 pCi/kg-wet, with an average of 635 pCi/kg-wet.
It was detected in the control station silage sample at 520 pCi/kg-wet.
31
The maximum preoperational level detected for silage was 4700 pCi/kg-wet, with an average of 2000 pCi/kg-wet.
LLD sensitivities for the remaining four indicator soybean samples ranged from <52 to <120 pCi/kg-wet.
The control station soybean sample was <46 pCi/kg-wet. The maximum preoperational level detected for soybean samples was 9300 pCi/kg-dry.
o Potassium-40 was detected in all nine samples.
Concentrations for the seven indicator station samples ranged from 3400 to 15000 pCi/kg-wet and for the two control station samples from 4100 to 12000 pCi/kg-wet.
The average concentration detected for the corn silage samples was 4225 pCi/kg~wet which was comparable to preoperational results which averaged 7000 pci/kg-wet.
Although the company no longer reports results based upon the dry weight of the sample, soybean results were comparable to preoperational studies.
Results averaged 13600 pCi/kg-wet which was comparable to preoperational results of 22000 pCi/kg-dry.
SOIL (Table C-20)
Soil is sampled every three years at 10 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.
I Strontium-90 was detected in eight of the indicator station samples in concentrations ranging from 38 to 190 pCi/kg-dry, and in the control station sample at 26 pCi/kg-dry.
The average for the indicator stations was 74 pCi/kg-dry.
The maximum preoperational level detected was 1100 pCi/kg-dry, with an average of 260 pCi/kg-dry.
I Gamma spectrometry of these samples showed detectable concentrations of the naturally occuring radionuclides (K-40, Ra-226, and Th-232) and the fission product Cs-137.
o Potassium-40 was detected in all nine of the indicator station samples ranging from 4600 to 14000 pCi/kg-dry, with an average of 9600 pCi/kg-dry.
The control station sample was 9000 pCi/kg-dry.
The maximum preoperational level detected was 24000 pCi/kg-dry with an average of 10000 pCi/kg-dry.
o Cesium-137 was detected in all nine of the indicator station samples ranging from 110 to 1400 pCi/kg-dry, and had an average of 464 pCi/kg-dry.
The control station sample showed a concentration of 200 pCi/kg-dry.
The maximum preoperational level detected was 2800 pCi/kg-dry with an average of 800 pCi/kg-dry.
32
o Radium-226 was detected in all nine of the indicator station samples in ranges of 430 to 1200 *pci/kg-dry, and had an average of 872 pCi/kg-dry.
The control location showed a concentration of 980 pCi/kg-dry.
The maximum preoperational level detected was 1500 pCi/kg-dry and an average of 870 pCi/kg-dry.
o Thorium-232 was detected in all nine of the indicator station -samples in ranges of 410 to 1200 pCi/kg-dry, and had an average of 880 pCi/kg-dry.
The control station sample showed a concentration of 840 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 polyethylepe containers before being transported in ice chests.
Surface Water (Tables c-21, c-22, C-23, C-24)
Surf ace water samples were collected monthly at four indicator stations and one control station in the Delaware estuary.
One location is at the outfall area (which is the area where liquid effluents from the Salem Station are discharged into the Delaware River), another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimirtk River.
Two upstream locations are in the Delaware River and at the' mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into_ the river.
Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational control.
All surface water samples were analyzed monthly for gross alpha, gross beta, I-131 (See Program Changes) and gamma emitters.
Quarterly composites were analyzed for tritium.
I Gross alpha activity was detected in six samples from the 48 indicator stations at concentrations ranging from 1.3 to 1.8 pCi/L and in three control station samples at 1.3 to 2.2 pCi/L.
These values are within the variations of the LLD sensitivities for the remaining samples which ranged from <1.1 to <3.8 pCi/L.
The maximum preoperational level detected was 27 pCi/L.
33
I Gross beta activity was detected in all of the 60 samples.
Concentrations for the 48 indicator station samples ranged from.
13 to 140 pCi/L, with and average of 55 pCi/L; and for the 12 -
control station samples from 27 to 97 pCi/L, with an average of 55 pCi/L.
The maximum preoperational level detected was 110 pCi/L, with an average of 32 pCi/L.
I Tritium activity was detected in two samples from the sixteen indicator station composites at concentrations of 180 and 240 pCi/L, and an average of 210 pCi/L.
There was tritium detected in two of the four control station composites at concentrations of 200 and 210 pCi/L, with an average of 205 pci/L.
LLD sensitivities for the remaining composites, both indicator and control, ranged from <130 to <190 pCi/L.
The maximum preoperational level detected was 600 pCi/L, with an average of 210 pCi/L.
I Iodine-131 was not detected in any of the 32 indicator station or 8 control station surface water samples analyzed for this nuclide (See Program Changes).
LLD concentrations ranged from
<0.1 to <0.7 pCi/L for the indicator stations and <0.1 to <0.5 pCi/L for the control station samples.
No preoperational data is available for comparison.
I Gamma spectrometric analysis performed on each of the 48 indicator station and 12 control station surface water samples indicated the presence of the naturally-occurring radionuclides K-40 and Ra-226, and in one sample Th-232.
All other gamma emitters searched for were below the Lower Limit_ of Detection.
o Potassium-40 was detected in 41 samples from the indicator station samples at concentrations ranging from 46 to 350 pCi/L and in nine of the control station samples ranging from 30 to 130 pCi/L.
The average for the indicator station locations was 97 pCi/L, while the average for the control station locations was 94 pCi/L.
LLD sensitivities measured throughout the year for the remaining samples ranged from
<16 to <38 pCi/L.
The maximum preoperational level detected was 200 pCi/L, with an average of *48 pCi/L.
o Radiwn-226 was detected in five samples out of the 48 indicator stations, at an average concentration of 24 pCi/L.
It was only detected in one of the control station samples at a concentration of 25 pCi/L.
The LLD sensitivities for all remaining samples measured throughout the year ranged from <0.8 to <9.3 pCi/L.
The maximum preoperational level detected was 4.0 pCi/L.
0 Thorium-232 was detected in one indicator station sample at a concentration of 7.5 pCi/L.
This value was within the range of LLD sensitivities for all remaining samples, both indicator and control, measured throughout the year of <2.2 to <12 pCi/L.
No preoperational data is available for comparison.
34
Fish (Table C-25)
Edible species of fish were collected semi-annually at three locations and analyzed for tritium (aqueous), gamma emitters (flesh), and for sr-89 and Sr-90 (bones & flesh).
Samples included bluefish, channel catfish, weakfish and white perch.
I Tritium analysis was performed on the aqueous fraction of the flesh portions of each of the two indicator station and one control station samples as management audit analysis.
No tritium activity was detected in any of the six samples analyzed.
LLD sensitivity ranged from <60 to <300 pCi/kg-wet.
The maxi.mum required LLD sensitivity value is 2000 pCi/kg-wet.
I Gamma spectrometric analysis performed on each of the four indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclide K-40".
All other gamma emitters searched for were below the Lower Limit of Detection.
o Potassium-40 was detected.in all four samples from the two indicator stations at concentrations ranging from 3100 to 3700 pCi/kg-wet and in both of the control station samples at 2900 and 3600 pCi/kg-wet.
The average for both the indicator and control station samples was 3300 pCi/kg-wet.
The maximum preoperational level detected was 13000 pCi/kg-wet, with an average of 2900 pCi/kg-wet.
Strontium-89 and strontium-90 analyses were performed on each of the.four indicator station and two control station samples.
These are management audit analyses analyzed in recognition of the high bioaccumulation factor of strontium in bone.
o Strontium-89 of the bone was not detected in any of the indicator or control station samples.
LLD sensitivities for the samples, both indicator and control, ranged from <25 to
<70 pCi/kg-dry.
The maximum preoperational level detected was 100 pCi/kg-dry.
o Strontium-90 of the bone was detected in two of the four indicator station samples and in one control station samples.
Concentrations in the indicator samples averaged 235 pCi/kg-dry.
The concentration in the one control sample was 420 pCi/kg-dry.
The average for all samples was 297 pCi/kg-dry.
The maximum preoperational level detected was 940 pCi/kg-dry, with an average of 335 pCi/kg-dry.
The presence of Sr-90 in the samples can be attributed to fallout from previous nuclear weapons testing.
o Strontium-89 of the flesh was not detected in any of the six indicator and control station samples.
LLD sensitivities for the six samples, indicator and control, ranged from <21 to <57 pCi/kg-wet.
The preoperational level ranged from
<4.1 to <100 pCi/kg-wet
- 35
o Strontium-90 of the flesh was not detected in any of the six indicator and control station samples.
LLD sensitivities for the six samples, indicator and control, ranged from <15
- to <33 pCi/kg-wet.
The maximum preoperational level detected was 67 pCi/kg-wet.
Blue Crab (Table C-26)
Blue crab samples were collected semi-annually at two locations, one indicator and one control, and the edible portions were analyzed for gamma emitters, Sr-89 and Sr-90, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89 and Sr-90.
I 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 <100 to <300 pCi/kg-wet.
The maximum required LLD sensitivity value is 2000. pCi/kg-wet.
The maximum preoperational level detected was 320 pCi/kg-wet.
I Gamma spectrometric analysis on the flesh of each of the two indicator station samples and two control station samples indicated the presence of the naturally-occurring radionuclide K-40.
All other gamma emitters searched for were below the Lower Limit of Detection. * *
~
o Potassium-40 was detected in both indicator station samples at concentrations of 3100 and 3200 pCi/kg-wet and in both of the control station samples at 2900 and 3200 pCi/kg-wet.
The average for both the indicator and control station samples was 3100 pCi/kg-wet.
The maximum preoperational level detected was 12000 pCi/kg-wet, with an average of 2835 pCi/kg-wet.
I Strontium-89 and strontium-90 analyses were performed on the flesh and shell of each of the indicator station and control station samples, as management audit analyses.
Strontium analysis of the shell is performed because of the reconcentration factor of strontium in crab shells.
o Strontium-89 of the flesh was not detected in any of the four samples, indicator nor control.
LLD sensitivities for all the samples ranged from <19 to <36 pCi/kg-wet.
The.
maximum preoperational* level detected was <51 pCi/kg-wet.
o Strontium-89 of the shell was not detected in any of the four samples, indi~ator nor control.
LLD sensitivities for all the samples, indicator and control, ranged from <23 to
<82 pCi/kg-dry.
The maximum preoperational level detected was 210 pCi/kg-dry.
- 36.
o Strontium-90 of the flesh was not detected in any of the four, indicator or control samples.
LLD sensitivities ranged from <14 to <20 pCi/kg-wet.
The maximum preoperational level detected was <150 pCi/kg-wet.
o Strontium-90 of the shell was detected in both indicator station samples at 88 and 110 pCi/kg-dry and in one control station samples at 93 pCi/kg-dry.
The average for both indicator and control station samples was 97 pCi/kg-dry.
The maximum preoperational level detected was 990 pCi/kg-dry, with an average of 614 pCi/kg-dry.
The presence of Sr-90 can be attributed to fallout from weapons testing or fallout from the Chernobyl accident.
Sediment (Table C-27)
Sediment samples were collected semi-annually from six locations, five indicator stations and one control station.
Each of the twelve samples was analyzed for Sr-90 (management audit. analysis) and gamma emitters.
Although trace levels of man-made nuclides were detected in some sediment samples, these levels were well within the acceptable levels specified in section 3/14.12.1 of the Technical Specifications.
I Strontium-90 was detected in one of the ten indicator station samples, at a concentration of 44 pCi/kg-dry, but was not detected in any of the control station samples.
LLD sensitivities for those remaining samples, both indicator and control, ranged from <20 to <28 pCi/kg-dry.
The maximum preoperational level detected was 320 pCi/kg-dry.
I Gamma spectrometric analysis was performed on each of the ten indicator station sa~ples and two control station samples.
In addition to the detection of the naturally-occurring radionuclides K-40, Ra-226 and Th-232, low levels of Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were also detected.
All other gamma emitters searched for were <LLD.
o Cobalt-60 was detected in four of the ten indicator stations at concentrations ranging from 32 to 92 pCi/kg-dry, with an average of 62 pCi/kg-dry.
It was not detected at either of the two control stations.
LLD sensitivities for the other eight samples, indicator and control, ranged from <9.1 to
<57 pCi/kg-dry.
No preoperational data is available for comparison.
o Manganese-54 was detected in three of the ten indicator stations at concentrations ranging from 27 to 48 pCi/kg-dry, with an average of 34 pCi/kg-dry.
It was not detected at either of the two control station samples.
LLD sensitivities for the other nine samples, both indicator and control, ranged from <8.4 to <36 pCi/kg-dry.
No preoperational data is available for comparison
- 37
o Cobalt-58 was detected in six indicator station samples at concentrations ranging from 38 to 120*pCi/kg-dry.
The LLD sensitivities for the other six samples, indicator and control, ranged from <6.2 to <82 pCi/kg-dry.
No preoperational data is available for comparison.
o Cesium-134 was detected in six indicator station samples at concentrations ranging from 30 to average of 50 pCi/kg-dry.
It was station samples at concentrations and an average of 58 pCi/kg-dry.
available for comparison.
~
80 pCi/kg-dry, with an detected in both control of 54 and 61 pCi/kg-dry, No preoperational data is o
Cesium-137 was detected in two indicator station samples at concentrations of 39 and 100 pCi/kg-dry, but was not detected in either control station sample.
The LLD sensitivities for the other ten samples, both indicator and control, ranged from <4.1 to <27 pCi/kg-dry.
The maximum preoperational level detected was 400 pCi/kg-dry.
o Potassium-40 was detected in all ten indicator station samples at concentrations ranging from 2700 to 18000 pCi/kg-dry, with an average of 9260 pCi/kg-dry.
Concentrations detected in both of the control station samples were at 14000 and 16000 pCi/kg-dry.
The average for both the indicator and control station samples was 10217 pCi/kg-dry.
The maximum preoperational level detected was 21000 pCi/kg-dry, with an average of 15000 pCi/kg-dry.
o Radium-226 was detected in all ten indicator station samples at concentrations ranging from 150. to 1800 pCi/kg-dry, with an average of 646 pCi/kg-dry.
Concentrations detected in both of the control station samples were at 620 and 680 pCi/kg-dry, with *an average of 646 pCi/kg-dry.
The average for both the indicator and control station samples was 647 pCi/kg-dry.
The maximum preoperational level detected was 1200 pCi/kg-dry, with an average of 760 pCi/kg-dry.
o Thorium-232 was detected in all ten indicator station samples at concent~ations ranging from 180 to 1600 pCi/kg-dry, with an* average of 745 pCi/kg-dry.
Concentrations detected in both of the control station samples were at 830 and 850 pCi/kg-dry, with an average of 840 pCi/kg-dry.
The average for both the indicator and control station samples was 761 pCi/kg-dry.
The maximum preoperational level detected was 1300 pCi/kg-dry, with an average of 840 pCi/kg-dry.
38
PROGRAM DEVIATIONS Gamma isotopic and strontium 89 & 90 analyses weren't performed on the composite air filters from location 5Dl during the first quarter 1992 by the vendor laboratory.
Controls for Environmental Pollution, Inc. (CEP) stated that the air filters (location 5Dl) were never_logged into their system to be run for a gamma composite or. for strontium analysis.
Results for gamma isotopic analysis for the second quarter 1992 on location 501 air 'particulates, are based on only 9 filters.
According to CEP, their counting room experienced a higher than normal turnover in personnel in May, and they misplaced 3 air filters.
These filters were from the weeks beginning on April *13, April 20, and April 27.
According to Teledyne Isotopes, Inc.* (who June 1, 1992) their lab misplaced the air for the week beginning on June 22, 1992.
alpha/beta analysis done for this week.
became our vendor lab on filter from location 501 Therefore, there was no While preparing the combination air filter/ air iodine cartridge assembly for installation for the week beginning on November 9, 1992, the field service technician assumed that he had previously installed a cartridge in the 5Dl assembly when in reality he had not.
As a result, there are no air iodine results available for this week.
All group personnel were instructed on the mandatory use of a gauge bar which will verify the presence of an air iodine cartridge during servicing of the field assemblies~
Although the data from location 5Dl was not available for the periods discussed above, a review of the data from the adjacent air sampling locations collected during this period indicated no usual results.
Data recovery for air particulate and air iodine results were well over 99%.
CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial Island was conducted during 1992 in accordance with the SGS and HCGS Technical Specifications.
The objectives of the program were met during this period.
The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.
From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment.
These results were comparable to the results obtained during the preoperational phase of the program.
No unusual radiological characteristics were observed in the environs of Artificial island.
The operation of SGS Units One and Two and HCGS had no significant impact on the radiological characteristics of the environs of Artificial Island.
39
~
0 TABLE 2 1992 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE MEDIUM INDICATOR I.
ATMOSPHERIC ENVIRONMENT
- a.
Air Particulate 5Sl 5Dl 16El lFl 2F2
- b.
Air Iodine 581 501 16El lFl 2F2
- c.
Precipitation 2F2 II.
DIRECT RADIATION
- a.
Thermoluminescent 2S2 5Dl 2El lFl Dosimeters SSl lODl 3El 2F2 6S2 14Dl i3El 2F6 7Sl 16El 5Fl lOSl 6Fl llSl 7F2 llFl 13F4 CONTROL 3H3 3H3 3Gl 3Hl 3H3 COLLECTION FREQUENCY Weekly Weekly Monthly Monthly &
.Quarterly TYPE/FREQUENCY* OF ANALYSIS Gross alpha/weekly Gross beta/weekly Sr-89 & Sr-90/first quarter Gamma scan/quarterly Iodine-131/weekly Gross alpha/monthly Gross beta/monthly Tritium/monthly Gamma scan/monthly Gamma dose/monthly Gamma dose/quarterly
TABL cont'd) 1992 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- a.
Thermo luminescent 4D2 9El 2FS 1G3 Quarterly Gamma dose/quarterly Dosimeters (cont'd) 11E2 3F2
.lOGl 12El 3F3' 16Gl 10F2 12Fl 13F2 13F3 14F2 15F3 16F2
~
I-'
III.
TERRESTRIAL ENVIRONMENT
- a.
Milk 2F7 3Gl Monthly Iodine-131/monthly (when animals Gamma scan/monthly 11F3 are not on pasture) 14F4 Semi-monthly Iodine-131/semi-monthly (when animals Gamma scan/semi-monthly are on Sr-89 & sr-90/July, first pasture) collection **
- b.
Well Water 2S3 3El Monthly Gross alpha/monthly Gross beta/monthly Potassium-40/monthly Tritium/monthly Gamma scan/monthly Sr-89 & Sr-90/quarterly
TABLE 2 (cont'd) 1992 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- c.
Potable water 2F3 Monthly Gross alpha/monthly (Raw & Treated)
(composited Gross beta/monthly daily)
Potassium-40/monthly Tritium/monthly Gamma scan/monthly sr-89 & sr-90/quarterly
- d.
Vegetables 3El 2F4 lGl 3H5 Annually Gamma scan/on collection 3E3 4F2 2Gl (at harvest)
SF3 2G2 14F3
~
N
- e.
Beef 3El Semi-Gamma scan/on collection annually
- f.
Game 3El llDl semi-Gamma scan/on collection
(~uskrat) annually
- g.
Fodder Crops 3El 2F7 3Gl Annually Gamma scan/on collection 11F3 14F4
- h.
Soil 6Sl lODl 16El lFl 3Gl Collect Sr-90/on collection 2F4 from each Gamma scan/on collection
(
2F7 location 5Fl once every 11F3 three years 14F4
.i::--
w (cont'd) 1992 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY IV.
AQUATIC ENVIRONMENT
- a.
- b.
- c.
- d.
Surf ace Water llAl 7El 1F2 12Cl Monthly 16Fl Edible Fish llAl 7El 12Cl Semi-annually Blue Crabs llAl 12Cl Semi-annually Sediment llAl 7El 16Fl 12Cl Semi-15Al annually 16Al
- Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.
- Management audit analyses, not required by* Technical Specifications or by specific commitments to local officials.
TYPE/FREQUENCY* OF ANALYSIS Gross alpha/monthly Gross beta/monthly Gamma scan/monthly Tritium/quarterly Tritium (flesh)
Aqueous fraction/on collection **
Sr-89 & Sr-90 (bones)/on collection sr-89 & sr-90 (flesh)/on collection **
Gamma scan (flesh)/on collection Tritium (flesh)
Aqueous fraction/on collection **
Sr-89 & Sr-90 (flesh)/on collection sr-89 & Sr-90 (shell)/on collection Gamma scan (flesh)/on collection sr-90/on collection Gamma scan/on collection
100 10 1
FIGURE 6 BETA IN PRECIPITATION AND AIR PARTICULATE 1973 THROUGH 1992 I
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i 1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 I QUARTERLY AVERAGE I
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E FIGURE 7 AMBIENT RADIATION - OFFSITE VS CONTROL STATION 1973 THROUGH 1992 8
6 4
2 Weapons Test 08-17-74 Weapons Test 09-17-77
~~
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~
'ii tn Weapons Test 03-14-78
~o 0
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... 0 0.
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- a.
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tn OFFSITE STATIONS CONTROL STATIONS
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... (0 Oo
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- c 0 -..~~--~~~--~~---~~--~~--'-~~--~~---i~~~.i-~~-i-~~~
1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 I QUARTERLY AVERAGE I
20 10 0
Weapons Test 116-17-r A
I I
FIGURE 8 IODINE-131 ACTIVITY IN MILK.
1973 THROUGH 1992
~weapons Test 09-26-76 Weapons Test 09-17-77 4
, r-WeaponsTeal I
03-14-78 j lA J
I
~'° en i"fi1 i 0 I~
";- I!.-;
- 1~=s
- t::....
m
.. N
.. 0 ""'
-m o....
0 c.,..
8"'
0 0 *-cl>
I I
- a.
!. :eo E
~
E i oO 1ii
- z
- C I
01 I
I I
I Chernobyl 04-26-88 I
I I
1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 I QUARTERLY AVERAGE I
..J 0
D.
FIGURE 9 GROSS BETA & K-40 ACTIVITY IN SURFACE WATER 1973 THROUGH 1992 GROSS BETA 100 Weapons Test Weapons Test 06-17-7 09-17-77
- ':=
18
. ~--=-__.er~ Test I I r ' I '
10 f~j~
. co
~co
'iii ":'
(ft II~
U>
('I o...
.S:!
~...
..:.:: th ii...
CD
- t:: 0 0
0
""N
~
0
{!.-
~~*
o.-
T"'
0
~ 8.
0 'iii I
l*~
- E I
II G
i!
- t 01
'iii
'ii
- c 0 en en 1973 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 I QUARTERLY AVERAGE I
~
FIGURE 10 TRITIUM ACTIVITY IN SURFACE WATER 1973 THROUGH 1992 10000 --------------------------------------------------------------
1000 Weap00s Test Wea ons Test 0&-17-1144 0&-1 -77 Weapons Test 09-26-76 Chernobyl 04-26-86 00 0
100 a..
1973 1975
~~
n~
-N
- I::....
0 y-I E Cl ii
- 1977
~
!~ m
~
m c
~
0 a.
0 i i!
1979
~o o
- J' co IS "1 j 10 "1
~:& t-d
._o
.lllC: 0
- ~
0 N
0 0 fl I
- a.
I i
!.=E
'ii oo
- c 1981 1983 1985 1987 1989 1991 1993
. I QUARlEALYAVEAAGE I
1000 200 50 1977 FIGURE 11A CESIUM -137 IN WATER SEDIMENT 1977 THROUGH 1992 Test 1979 1981 1983 Chernobyl 04-26-86 l
1985 1987 1989 1991 1993 I SEMI-ANNUAL AVERAGE I
U1 0
1000 200 50 1977 FIGURE 118 COBALT-60 IN WATER SEDIMENT 1977 THROUGH 1992 Weapons Test 09-17-77 1979 1981 1983 1985 Chernobyl 04-26-88 1
1987 1989 1991 1993 I SEMI-ANNUAL AVERAGE I
~
FIGURE 12 CONCENTRATIONS OF Sr-90 AND Cs-137 IN SOIL 1974 THROUGH 1992 Sr-90 1000 Cs-137
... --... ----- -~----~---------~-----------~-----
6 100 1------------------
- a.
1974 Weapons Test 09-29-76 1977 1983 1986 1989 1992 I YEARLY AVERAGE I
REFERENCES
[l]
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program -
Annual Reports 1973 through 1982".
[2]
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program -
Preoperation Summary -
1973 through 1976".
RMC-TR-77-03, 1978.
[3]
Radiation Management Corporation.
"Artificial Islan~ Radiological Environmental Monitoring Program -
December 11 to December 31, 1976".
RMC-TR-77-02, 1977.
[4]
PSE&G Research Corporation, Research and Testing Laboratory.
"Artificial Island Radiological Environmental Monitoring Program ~ Annual Reports 1983 through 1990".
[5]
Public Service Electric and Gas Company.
"Environmental Report, Operating License Stage -
Salem Nuclear Generating Station Units 1 and 2".
1971.
[6]
Public Service Electric and Gas Company.
"Environmental Report, Operating License Stage -
Hope Creek Generating.Station".
1983.
[7]
United States Atomic Energy Commission.
"Final Environmental Statement -
Salem Nuclear Generating Station, Units 1 and 2".
Docket No. 50-272 and 50-311. 1973.
[8]
United States Atomic Energy COinf!!ission.
"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 seq).
[12]
Public Service Electric and Gas Company.
"Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix A to Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.1.10 (Amendment 28 et seq).
52 e1
REFERENCES (cont'd)
(13]
Public Service Electric and Gas Company.
"Hope Creek Generating Station Unit 1 -
Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10.
(14]
Public Service Electric and Gas Company.
"Offsite Dose Calculation Manual" -
Salem Generating Station.
[15]
Public Service Electric and Gas Company.
"Offsite Dose Calculation Manual" -
Hope Creek Generating Station.
[16] u. s. Environmental Protection Agency.
"Prescribed Procedures for Measurement of Radioactivity in Drinking Water."
EPA-600/4-80-032, August, 1980.
[ 17]
PSE&G Research and T*esting Laboratory.
"Environmental Division Quality Assurance Plan."
November, 1986.
(18]
PSE&G Research and Testing Laboratory.
"Chemical/ Environmental Division Procedures Manual."
February, 1981.
9]
Public Service Electric and Gas Company.
"Radioactive Effluent Release Reports, SGS RERR-33 and RERR Salem Generating Station. 1992.
[20]
Public Service Electric and Gas Company.
"Radioactive Effluent Release Reports, HCGS RERR-13 and RERR Hope Creek Generating Station. 1992.
[21]
Anthony V. Nero Jr., "A Guid~book to Nuclear Reactors", University of California Press, 1979.
[22]
Eric J. Hall, "Radiation & Life", Pergamon Press, 1976.
[23]
NCRP Report No. 93, "Ionizing Radiation Exposure of the Population of the United States", 1987
- 53
APPENDIX A PROGRAM
SUMMARY
55
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS (LLD)*
AIRBORNE A;r part;culates Alpha 311 1.0 2.3 (212/259) 16E1 4.1 mi NNW 2.4 (48/52) 2.2 (50/52) 0 (1 o-* pe i tm'>
(0.7-5.2)
(0.7-5.2)
(1.0-5.2) 5S1 1.0 mi E 2.4 (47/52)
(1.1-4.8)
Beta 311 6.0 21 (259/259) 2F2 8.7 mi NNE 22 (52/52) 21 (52/52) 0 (2.5-37)
(10-35)
(9-42)
V1 Sr-89 5
0.2 0.4 (1/5) 16E1 4.1 mi NNW 0.4 (1/5) 0.3 (1/1) 0
-....J (0.4)
(0.4)
(0.3)
Sr-90 5
0.2
<LLD
<LLD
<LLD 0
Gamma Be-7 23 6.8 70 (19/20) 5S1 1.0 mi E 72 (4/4) 68 (4/4) 0 (54-95)
(60-87)
(55-81) 16E1 4.1 mi NNW 72 (4/4)
(56-81 2F2 8.7 mi NNE 72 (4/4)
(59-95)
K-40 23 7.1 13 (4/19) 5S1 1.0 mi E 18 (1/4) 11 (2/4) 0 (11-18)
( 18)
(10-12)
Air Iodine 1-131
.311 13
<LLD
<LLD
<LLD 0
c10-* pCi/m')
Precipitation Alpha 12 1.5 1.4 (2/12) 2F2 8.7 mi NNE 1.4 (2/12)
No Control 0
(pCi/L)
(1.4)
(1.4)
Location Beta 12 2.0***
4.6 (12/12) 2F2 8.7 mi NNE 4.6 (12/12)
No Control 0
(1.1-15)
(1.1-15)
Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50*272/*311 HOPE CREEK GENERATING STATION DOCKET NO. 50*353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL.INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS (LLD)*
AIRBORNE (Cont'd)
PRECIPITATION H*3 12 150 330 (5/12) 2F2 8.7 mi NNE 330 (5/12)
No Control 0
(pCi/L)
(160*810)
(160*810)
Location GaRlll8 84 (12/12) 2F2 8.7 mi NNE 84 (12/12)
No Control 0
Be*7 12 15 (43*160)
(43*160)
Location II Direct Direct Radiation GaRlll8 288 7.2 (252/252) 7S1 0.12 mi SE 8.5 (12/12) 7.6 (36/36) 0 (mrad/std. month)
Dose monthly (4*13)
(6*10)
(5*10) lJl 00 GaRlll8 164 5.6 (140/140) 7S1 0.12 mi SE.
7.3 (4/4) 5.8 (24/24) o*
Dose qtrly.
(4*9.5)
(6.3*8.6)
(4.8*7)
Ill TERRESTRIAL MILK 1*131 80 0.4
<LLD
<LLD
<LLD 0
(pCi/L)
Sr*89 4
1.1
<LLD
<LLD
<LLD 0
Sr*90 4
0.9 2.1 (3/3) 2F7 5.7 mi NNE 3.4 (1/1) 2.4 (1/1) 0 (1.1*3.4)
(3.4)
(2.4)
GaRlll8 K*40 80 120 1390 (60/60) 2F7 5.7 mi NNE 1400 (20/20) 1330 (20/20) 0 (1100-1600)
(1200-1600)
(1100-1400)
Ra-226 80 6.6
<LLD
<LLD
<LLD 0
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 11, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM.OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN""*
NAME MEAN MEAN
,REPORTED (UNIT OF ME~SUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
CRAN GE)
MEASUREMENTS (LLD)""
Ill TERRESTRIAL (Cont'd),
2S3 700 ft.
2.4 (1/12)
Well Water Alpha 24 1.2 2.4 (1/12)
NNE
<LLD 0
CpCi/L)
(2.4)*
(2.4)
Beta 24 1.0*""*
4.1 (12/12) 3E1 4.1 mi NE 10.0 (12/12) 10.0 (12/12) 0 (2.2-7.8)
(8.7-11.0)
(8. 7-11.0)
K-40 24 4.6 (12/12) 3E1 4.1 mi NE 10.8 (12/12) 10.8 (12/12) 0 (2.0-10)
(5.6-21)
(5.6-21) ll1 H-3 24 150
<LLD 3E1 4.1 mi NE 210 (1/12) 210 (1/12) 0
\\()
(210)
(210)
Sr-89 8
1.0
<LLD
<LLD
<LLD 0
Sr*90 8
0.6
<LLD
<LLD
<LLD 0
Ganrna K-40 24 35 53 (3/12) 3E1 4.1 mi NE 66 (3/12) 66 (3/12) 0 (48-58)
(55-75)
(55-75) 1-131 24 0.6
<LLD
<.LLD
- <LLD 0
Ra-226 24 7.4 18 (10/12) 3E1 4.1 mi NE 106 (11/12) 106 (11/12) 0 (2-45)
(11-180)
(11-180)
Potable Water Raw-Treated Alpha 24 1.0 1.5 (3/24) 2F3 8.0 mi NNE 1.5 (3/24)
No Control 0
(pCi/L)
(1.1-1.9)
(1.1-1.9)
Location Beta 24 1.0***
3.0 (24/24) 2F3 8.0 mi NNE 3.0 (24/24)
No Control
- 0 (1.7-4.9)
(1.7-4.9)
Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS (LLD)*
111 TERRESTRIAL (Cont'd)
Potable Water K~40 24 1.9 (24/24) 2F3 8.0 mi NNE 1.9 (24/24)
No Control 0
Raw-Treated (1.0-3.3)
(1.0-3.3)
Location (pCi/L)
H-3 24 150 244 (5/24) 2F3 8.0 mi NNE
. 244 (5/24)
No Control 0
(180-320)
(180-320)
Location Sr-89 8
1.0
<LLD
<LLD No Control 0
Location
°'
0 Sr-90 8
0.8
<LLD
<LLD No Control 0
Location 1-131 24 0.6
<LLD
<LLD.
No Control 0
Location Ganma K-40 24 35 55 (7/24) 2F3 8.0 mi NNE 55 (7/24) '
No Control 0
(39-65)
(39-65)
Location Ra-226 24 7.4 7.9 (1/24) 2F3 8.0 mi NNE 7.9 (1/24)
No Control 0
(7.9)
(7.9)
Location Fruits &
Ganma Vegetables K-40 19 70 2860 (12/12) 5F3 6.4 mi E 5600 (1/1) 2570 (7/7) 0 (pCi/kg-wet)
(1500-5600)
(5600)
(1700-3700)
Game Gamma CpCi/kg-wet)
- 2 70 2400 (1/1) 3E1 4.1 mi NE 2400 (1/1) 2200(1/1) 0 (2400)
(2400)
(2200)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW.JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS (LLD)*
Ill TERRESTRIAL (Cont'd)
Fodder Crops Ganrna (pCi/kg-wet)
Be-7 9
580 670 (4/9) 2F7 5.7 mi NNE 700 (1/2) 520 (1/2) 0 (640-700)
(700)
(520)
K-40 9
85 9800 (7/7) 2F7 5.7 mi NNE 7800 (3/3) 8000 (2/2) 0 (3400-15000)
(4600-14000)
(4100-12000)
Soil Sr-90 10 22 74 (8/9) 5F1 6.5 mi E 190 (1/1) 26 (1/1) 0
°'
CpCi/kg-dry)
(38-190)
(190)
(26)
Ganrna K-40 10 640 9600 (9/9) 14F4 7.6 mi WNW 14000 (1/1) 9000 (1/1) 0 (4600-14000)
(14000)
(9000)
Cs-137 10 20 460 (9/9) 1F1 5.8 mi N 1400 (1/1) 200 (1/1) 0 (110-1400)
(1400)
(200)
Ra-226 10 40 870 (9/9) 11F3 5.3 mi SW 1200 (1/1) 980 (1/1) 0 (430-1200)
(1200)
(980) 14F4 7.6 mi WNW 1200 (1/1)
(1200)
Th-232 10 110 880 (9/9) 16E1 4.1 mi NNW 1200 (1/1)
(410-1200)
(1200) 11F3 5.3 mi SW 1200 (1/1) 840 (1/1) 0 (1200)
(840) 14F4 7.6 mi WNW 1200 (1/1)
(1200)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN.**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
.PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS (LLD)*
IV AQUATIC Surf ace Water Alpha 60
~-0 1.5 (6/48) 12C1'2.5 mi WSW 1.7 (3/12) 1.7 (3/12) 0 (pCi/L)
(1.3-1.8)
(1.3-2.2)
(1.3-2.2)
Beta 60 3.8***
55 (48/48) 7E1 4.5 mi SE 85 (12/12) 55 (12/12) 0 (13-140)
(53-140)
(27-97)
H-3 20 150 210 (2/16) 1F2 7.1 mi N 210 (2/4) 205 (2/4) 0
( 180-240)
(180-240)
(200-210) 0\\
1-131 60 0.6
<LLD
<LLD
<LLD 0
N Gamma K-40 60 35 97 (41/48) 7E1 4.5 mi SE 113 (11/12) 94 (9/12) 0 (46-350)
(50-150)
(30-130)
Ra-226 60 7.4 24 (5/48) 1 F2 7.1 mi N 46 (2/12) 25 ( 1/12) 0 (7-69)
(23-69)
(25)
Th-232 60 7.1 7.5 (1/48) 11A1 0.2 mi SW 7.5 (1/48)
<LLD 0
(7.5)
(7.5)
Blue Crabs Sr-89 4
60
<LLD
- <LLD
<LLD 0
(pCi/kg*dry)
(shells)
. Sr-90 4
99 (2/2) 11A1 0.2 mi SW 99 (2/2) 93 (1/2) 0 (shells)
(88-110)
(88-110)
(93)
(pCi/kg-wet)
H-3 4
1000
<LLD
<LLD
<LLD 0
(aqueous)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LIMIT OF MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS (LLD)*
IV AQUATIC (Cont'd)
Blue crabs Sr-89 4
100
<LLD
<LLD
<LLD 0
(pCi/kg-wet)
(flesh)
Sr-90 4
40
<LLD
<LLD
<LLD 0
(flesh)
Gaflll18
°'
K-40 4
70 3150 (2/2) 11A1 0.2 mi SW 3150 (2/2) 3050 (2/2) 0 w
(3100-3200)
(3100-3200)
(2900-3200)
Edible Fish Sr-89 6
75
<LLD
<LLD
<LLD 0
(pCi/kg-dry)
(bones)
Sr-90 6
25 235 (2/4) 12C1 2.5 mi WSW 420 (1/2) 420 (1/2) 0
"(bones)
(210-260)
(420)
(420)
CpCi/kg-wet)
H-3 6
1000
<LLD
<tLD
<LLD 0
(aqueous)
Sr-89 6
100
<LLD
<LLD
<LLD 0
(flesh)
Sr-90 6
40
<LLD
<LLD
<LLD 0
(flesh)
Gamma K-40 6
70 3350 (4/4) 11A1 0.2 mi SW 3400 (2/2) 3250 (2/2) 0 (3100-3700)
(3100-3700)
(2900-3600)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-353 SALEM COUNTY, NEW JERSEY JANUARY 1, 1992 to DECEMBER 31, 1992 ANALYSIS AND MEDIUM OR PATHWAY TOTAL NUMBER LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION SAMPLED OF ANALYSES LIMIT OF MEAN**
NAME MEAN MEAN (UNIT OF MEASUREMENT)
PERFORMED DETECTION (RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
(LLD)*
IV AQUATIC (Cont'd)
Sediment Sr-90 12 25 44 (1/10) 16A1 0.7 mi NNW 44 (1/10)
<LLD (pCi/kg-dry)
(44)
(44)
Ga nm a K-40 12 640 9260 (10/10) 16F1 6.9 mi NNW 17500 (2/2) 15000 (2/2)
(2700-18000)
(17000-18000)
(14000-16000)
Mn-54 12 35 34 (3/10) 16A1 0.7 mi NNW 38 (2/2)
<LLD (27-48)
(28-48)
°'
+:'-
Co-58 12 15 73 (6/10) 16A1 0.7 mi NNW 82 (2/2)
<LLD (38-120)
(43-120)
Co-60 12 32 62 (4/10) 16A1 0.7 mi NNW 92 (1/2)
<LLD (32-92)
(92)
Cs-134 12 22 50 (6/10) 12C1 2~5 mi WSW 58 (2/2) 58 (2/2)
(30-80)
(54-61)
(54-61)
Cs-137 12 20 70 (2/10) 11A1 0.2 mi SW 100 (1/2)
<LLD (39-100)
(100)
Ra-226 12 40 646 (10/10) 16A1 0.7 mi NNW 1090 (2/2) 650 (2/2)
(150-1800)
(380-1800)
(620-680)
Th-232 12 110 745 (10/10) 16A1 0.7 mi NNW 1110 (2/2) 840 (2/2)
(180-1600)
(620-1600)
(830-850)
LLD listed is the lower limit of detection which we endeavored to achieve during this reporting period.
In some instances nuclides were detected at concentrations above the LLD values shown.
Mean calculated using values above LLD only.
Fraction of measurements above.LLD are in parentheses.
- Typical LLD value.
NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0
0 0
0
- o 0
0 0
0
APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 65
APPENDIX B SAMPLE DESIGNATION The PSE&G Research* And Testing Laboratory identifies samples by a three part code.
The first two letters are the power station identification code, in this case "SA".
The next three letters are for the media sampled.
AIO = Air Iodine IDM = Immersion Dose (TLD)
APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)
ESF = Edible Fish PWT = Potable Water (Treated)
ESS = Sediment RWA = Rain Water (Precipitation)
FPB = Beef SOL = Soil FPL = Green Leafy Vegetables SWA = Surf ace Water FPV = Vegetables (Various)*. VGT = Fodder Crops (Various)
GAM = Game (Muskrat)
WWA = Well Water The last four symbols are a location code based on direction and distance from the site.
Of these, the first two represent each of 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-3E1 would indicate a sample in the SGS program (SA),
consisting of well water (WWA), which had been collected in sector number 3, centered at 45° *(north east) with respect to the reactor site at a radial distance of 4 to 5 miles off-site, (therefore, radial distance E).
The number 1 indicates that this is sampling station #1 in that particular sector.
67
SAMPLING LOCATIONS All of the sampling locations and specific information about the individual locations are given in Table B-1.
Maps B-1 and B-2 show the locations of sampling stations with respect to the site.
STATION CODE 2S2 2S3 SSl 6S2 7Sl lOSl llSl llAl lSAl 16Al 12Cl 4D2
!?Dl
.lODl llDl 14Dl 2El 3El 3E2 3E3 TABLE B-1 STATION LOCATION 0.4 mi. NNE of vent 700 ft. NNE of vent; fresh water holding tank 1.0 mi. E of vent; site access road 0.2 mi. ESE of vent; observation building 0.12 mi. SE of vent; station personnel gate 0.14 mi. SSW of vent; site shoreline 0.09 mi. SW of vent; site shoreline 0.2 mi. SW of vent; outfall area 0.3 mi. NW of vent; cooling tower blowdown discharge line outfall 0.7 mi. NNW of vent; south storm drain discharge line 2.5 mi. WSW of vent; west bank of Delaware River 3.7 mi. ENE of vent; Alloway Creek Neck Road 3.5 mi. E of vent; local farm 3.9 mi. SSW of vent; Taylor's Bridge Spur 3.5 mi. SW of vent 3.4 mi. WNW of vent; Bay View, Delaware 4.4 mi. NNE of vent; local farm 4.1 mi. NE of vent; local farm 5.7 mi. NE of vent; local farm 5.6 mi. NE of vent; local farm 68 SAMPLE TYPES IDM WWA AIO,APT,IDM IDM,SOL IDM IDM IDM ECH,ESF,ESS,SWA ESS ESS ECH,ESF,ESS,SWA IDM,VGT AIO,APT,IDM IDM,SOL GAM IDM IDM FPB,GAM,IDM,VGT WWA FPV FPV
TABLE B-1 (cont'd)
STATION CODE STATION LOCATION SAMPLE TYPES 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek ESF,ESS,SWA 9El 4.2 mi. s of vent IDM 11E2 5.0 mi. SW of vent IDM 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM 16El 4.1 mi. NNW of vent; Port Penn AIO,APT,IDM,SOL lFl 5.8 mi. N of vent; Fort Elfsborg AIO,APT,IDM,SOL 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA 2F2 8.7 mi. NNE of vent; Salem Substation AIO,APT,IDM,RWA 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm FPV,FPL,SOL 2F5 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southern Training Center IDM 2F7 5.7 mi. NNE of vent; local farm MLK,VGT,SOL 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal IDM Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 5Fl 6.5 mi. E of vent FPV,IDM,SOL 5F3 6.4 mi. E of vent; local.farm FPL 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 11F3 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT,SOL 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM 69
STATION CODE 13F2 13F3 13F4 14F2 14F3 14F4 15F3 16Fl 16F2 lGl 1G3 2Gl 2G2 3Gl lOGl 16Gl 3Hl 3H3 3H5 TABLE B-1 (cont'd)
STATION LOCATION 6.5 mi. w of vent; Odessa, Delaware 9.3 mi. W of vent; Redding Middle School, Middletown, Delaware 9.8 mi. W of vent; Middletown, Delaware 6.6 mi. WNW of vent; Boyds Corner 5.4 mi. WNW of vent; local farm 7.6 mi. WNW of vent; local farm 5.4 mi. NW of vent 6.9 mi. NNW of vent; C&D Canal 8.1 mi. NNW of vent; Delaware City Public School 10.3 mi. N of vent; local farm 19 mi. N of vent; Wilmington, Delaware 12 mi. NNE of vent; Mannington Township, NJ 13.5 mi. NNE of vent; local farm 17 mi. NE of vent; local farm 12 mi. SSW of vent; Smyrna, Delaware 15 mi. NNW of vent; Greater Wilmington Airport 32 mi. NE of vent; National Park, New Jersey
- 110 mi. NE of vent; Research and Testing Laboratory 25 mi. NE of vent; local farm 70 SAMPLE TYPES IDM IDM IDM IDM FPV MLK,VGT,SOL IDM ESS,SWA IDM.
FPV IDM FPV FPV IDM,MLK,VGT,SOL IDM IDM IDM
15 O:'.:
w >
11 MAP 8-1 ON-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 1
M UM EXCLUSI
. AREA BDUNDA C901 METE
)
9 71
'w'ER 5
7 N
15 14 12 1 1 1
MAP 8*2 MTIF'ICIAL ISLAND RADIOLOGIC.AL. ENVIRONMENT AL MONITORING PROGRAM OFF'*SITE SAMPLING LOCATION I
I 19 SSE 72 8
3 NE H
su*-
APPENDIX C DATA TABLES 73
APPENDIX C DATA TABLES Appendix c presents the analytical results of the 1992 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1992.
TABLE NO.
C-1 C-2 C-3 C-4 C-5 C-6 C-7 C-8 TABLE OF CONTENTS TABLE DESCRIPTION ATMOSPHERIC ENVIRONMENT AIR PARTICULATES 1992 Concentrations of Gross Alpha Emitters *****.****.***.*****
1992 Concentrations of Gross Beta Emitters **********.*.********
1992 concentrations of Strontium-89 and Strontium-90 and Gamma Emitters in Quarterly Composites ***********.********
AIR IODINE 1992 Concentrations of Iodine-131 ******************************
DATES 1992 Sampling Dates for Air Samples ****************************
PRECIPITATION 1992 concentrations of Gross Alpha and Gross Beta Emitters and Tritium and Gamma Emitters ********************************
DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS 1992 Quarterly TLD Results *****.*****.**********.**************
1992 Monthly TLD Results ************************** * *************
75 PAGE 78 80 82 83 85 91 92 93
TABLE NO.
C-9 C-10 C-11 C-12 C-13 C-14 C-15 C-16 C-17 C-18 C-19 C-20 DATA TABLES (cont'd.)
TABLE DESCRIPTION TERRESTRIAL ENVIRONMENT MILK 1992 Concentrations of Iodine-131 and Gamma Emitters.**********
1992 Concentrations of Strontium-89 and Strontium-90 *.*********
WELL WATER 1992 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium ************************.*********
1992 Concentrations of Iodine 131 and Gamma Emitters ***********
1992 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites *************************.**.*********
POTABLE WATER 1992 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium ************.**.***.**.***********
1992 Concentrations of Iodine 131 and Gamma Emitters **.********
1992 Concentrations of Strontium-89 and Strontium-90 in Quarterly Composites ****************.**********************
FOOD PRODUCTS 1992 Concentrations of Gamma Emitters in Vegetables ************
1992 Concentrations of Gamma Emitters in Beef and Game *********
FODDER CROPS 1992 Concentrations of Gamma Emitters **************************
SOIL 1992 Concentrations of Strontium 90 and Gamma Emitters *********
76 PAGE 95 97 98 99 100 101 102 103 104 105 106 107
TABLE NO.
C-21 C-22 C-23 C-24 c-25 C-26 C-27 C-28 DATA TABLES (cont'd.)
TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER 1992 Concentrations of Gross Alpha Emitters ********************
108 1992 Concentrations of Gross Beta Emitters ****.****************
109 1992 Concentrations of Iodine 131 and Gamma Emitters ***********
110 1992 Concentrations of Tritium in Quarterly Composites *********
111 EDIBLE FISH 1992 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters................................
113 BLUE CRABS 1992 Concentrations of Strontium-89 and Strontium-90 and Tritium and Gamma Emitters *******************************
114 SEDIMENT 1992 Concentrations of Strontium-90 and Gamma Emitters *********
115 SPECIAL TABLES LLDs 1992 PSE&G Research and Testing Laboratory LLDs for Gamma Spectrometry. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 116 77
TABLE C-1 1992 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma
<--------------------------------- STATION ID --------------------------------->
MONTH SA-APT-5Sl SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)
JANUARY 3.0+/-0.8
<5 2.5+/-0.8 2.6+/-0.8 2.9+/-0.9 2.4+/-0*8 2.7+/-0.5 2.5+/-0.8
<5 3.3+/-0.9 2.8+/-0.9 2.2+/-0.8 2.2+/-0.8 2.6+/-0.9 3.9+/-1.0
<5 4.2+/-1.0 3.7+/-1.0
- 4. 8+/-1.1 3.8+/-0.9 4.1+/-0.9 3.9+/-0.9
<5 4.2+/-0.9 3.9+/-1.0
- 4. 0+/-1. 0 3.2+/-0.8 3.8+/-0.8 3.1+/-0. 9
<5 3.0+/-0.9 2.2+/-0.9 2.0+/-0.8 3.4+/-0.9 2.7+/-1.2 FEBRUARY 2.3+/-0.8
<5 2.6+/-0.8 2.3+/-0.8
- 1. 6+/-0. 7 2.0+/-0.7 2.2+/-0.8
- 1. 6+/-0. 7
<5 1.1+/-0. 6 2.4+/-0.8 2.3+/-0.8 2.2+/-0.7 1.9+/-1. l 2.7+/-1.0
<5 3.4+/-1.0 3.6+/-1.0
- 3. 3+/-1.0 3.0+/-1.0 3.2+/-0.7 2.1+/-0.8
<5 2.6+/-0.8 2.4+/-0.8 2.8+/-0.8 2.2+/-0.8 2.4+/-0.6 MARCH 2.7+/-0.9
<5 1.9+/-0. 7 2.4+/-0.8 2.0+/-0.7 3.0+/-0.8 2.4+/-0.9 3.3+/-1.0
<5 2.7+/-0.8 3~0+/-0.9 3.4+/-0.9 1.4+/-0. 7 2.8+/-1.6 4.0+/-1.0
<5 3.4+/-0.8
- 3. 2+/-1. 0 3.6+/-0.9 3.4+/-0.9 3.5+/-0.6 00 3.0+/-0.8
<5 2.7+/-0.7 2.5+/-0.8 3.1+/-0.8
- 1. 9+/-0. 8 2.6+/-1.0 APRIL
- 4. 8+/-1. 3
<5 2.6+/-0.9
- 3. 5+/-1.1
- 2. 7+/-1.0 2.9+/-0.9 3.3+/-1.8 3.8+/-1.0
<5 4.5+/-1.0 3.2+/-0.9 4.0+/-0.9 5.2+/-1. 5 4.1+/-1.5
- 1. 9+/-0. 8
<5 0.7+/-0.5
- 1. 6+/-0. B 1.2+/-0.6 1.1+/-0. 6
- 1. 3+/-0. 9
<0.9
<5 0.9+/-0.6
<0.8
<0.8
<1.3 0.9+/-0.4 MAY 1.8+/-0.9
<5
- 1. 6+/-0. 7
- 1. 3+/-0.8 1.5+/-0.7 1.5+/-0.8 1.5+/-0.4
- 1. 6+/-0. 8
<5
- 1. 0+/-0. 6
- 1. 6+/-0. 7 1.3+/-0.7
- 1. 2+/-0. 6
- 1. 3+/-0. 5 1.7+/-0.8
<5
- 1. 4+/-0. 6 1.5+/-0.7 l.5:t:0.7 1.1+/-0. 7
- 1. 4+/-0. 4
- 1. 8+/-0. 8
<5 2.1+/-0. 8 1.4+/-0.7 1.3+/-0.7
- 1. 6+/-0. 8
- 1. 6+/-0. 6 1.3+/-0.7 2.8+/-1.5
- 1. 6+/-0. 7 1.5+/-0.7 1.5+/-0.7 1.7+/-0.7
- 1. 7+/-1.1 JUNE
<1.1
<1.0
<0.9
<1.0
- 1. 0+/-0. 7 1.1+/-0.7 1.0+/-0.2 2.1+/-0.8 2.0+/-1.4
. 2.1+/-0. 7 0.9+/-0.6 2.3+/-0.8
- 1. 9+/-0. 7 1.9+/-1.0
- 1. 3+/-0. B
- 3. rnl.6 2.3+/-0.B 2.1+/-0. 9
- 1. 6+/-0.8 2.1+/-0.8 2.2+/-1.6 2.6+/-0.8 2.6+/-0.7-2.3+/-0.7
- 1. 8+/-0. 6 1.8+/-0.6 2.2+/-0.8
'-l
\\.0 MONTH JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE TABLE C-1 (Cont'd) 1992 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES
. Results in Units of 10*3 pCi/m3 +/- 2 sigma
<--------------------------------- STATION ID ---------------------------~----->
SA-APT-SSl SA-APT-SDl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 (Control) 2.4+/-0.9 1.6+/-1.0 3.3+/-0.9 2.1+/-0.8 3.2+/-0.9 2.6+/-0.8 2.7+/-0.9 1.3+/-1.0 2.9+/-0.9 2.6+/-0.8
- 1. 7+/-0. 7 2.2+/-0.8 1.9+/-0.9
- 3. 0+/-1. 5
- 1. 4+/-0. 7 2.7+/-0.9 1.4+/-0.7 2.3+/-0.8 1.8+/-0.8
<1.0 1.2+/-0.6 1.8+/-0. 7 2.0+/-0.7
- 1. 6+/-0. 7 2.1+/-0. 9
- 1. 0+/-0. 8 2.0+/-0.8
- 1. 9+/-0. 8 1.9+/-0.8 1.4+/-0. 7 4.0+/-1.0 1.3+/-1.0
- 1. 8+/-0. 7
- 1. 7+/-0. 7 2.6+/-0.8
- 1. 5+/-0. 6
<1.1
<1.0 1.5+/-0.8
<1.0 1.3+/-0.7
- 1. 3+/-0. 7 1.9+/-0.8
<0.9 2.7+/-0.9 2.9+/-1.0 2.1+/-0. 7 2.0+/-0.7 2.7+/-0.8 3.2+/-1.3 5.2+/-1.0 3.1+/-0.9 4.5+/-0.9
- 1. 9+/-0. 7 1.7+/-0.8 1.4+/-1.0
- 1. 8+/-0. 8
- 2. 4+/-1. 0 1.5+/-0.7
- 1. 5+/-0. 6
- 1. 4+/-0. 7 1.1+/-0.9 2.6+/-0.9 3.2+/-1.0 2.7+/-0.8
- 1. 9+/-0. 8
- 1. 7+/-0. 7
- 1. 3+/-0. 9 2.6+/-0.8 2.3+/-0.9 2.1+/-0.7 2.5+/-0.7 L 7+/-0. 8
<1.0 1.3+/-0.7
- 1. 6+/-0. 9 2.0+/-0.8 1.1+/-0. 7 2.0+/-0.8
<2.0 2.8+/-0.9 2.1+/-0.9 1.8+/-0.7 3.2+/-0.8 2.0+/-0.7
- 2. 8+/-1. 2
- 1. 6+/-0. 7 2.3+/-0.8 2.3+/-0.7 2.2+/-0.7 2.8+/-0.9
<1.0 2.3+/-0.8
- 2. 4+/-1.0 2.8+/-0.9 2.7+/-0.9 2.8+/-1.1 2.1+/-1. 5 2.4+/-0.9 2.0+/-0.9 2.6+/-0.9 2.0+/-0.7 2.2+/-0.8
- 2. 0+/-1.1 2.5+/-0.9
- 2. 5+/-1.0 2.3+/-0.8 2.8+/-0.8 1.1+/-0. 6
<0.9
- 1. ~~6. 8 1.2+/-0.7 0.8+/-0.6
- 1. 0+/-0. 6
- 1. 6+/-0. 7 2.5+/-1.2 2.5+/-0.9
- 1. 9+/-0. 7 2.1+/-0. 7 2.2+/-0.8
<2.0 2.2+/-0.8
- 1. 7+/-0.8 2.0+/-0.7 1.8+/-0.7 1.3+/-0.7 1.2+/-0.9
- 1. 4+/-0. 7 2.3+/-0.8 1.9+/-0.7 1.4+/-0.7 2.7+/-0.9 3.4+/-1.6 1.7+/-0.8
- 1. 8+/-0. 9 2.4+/-0.8 2.8+/-0.9
<0.9
<2.0
<1.1
<1.3
<1.0 1.4+/-0. 7
<1.1 1.9+/-1.2
<1.3
<1.4 1.7+/-0.9
<1.1 2.5+/-0.7 2.7+/-1.2 3.2+/-0.9 3.0+/-0.8 3.6+/-0.8 3.2+/-0.8 2.3+/-1.8 1.8+/-1. 7 2.3+/-2.0 2.2+/-1.5 2.2+/-1.9 2.1+/-1. 7 GRAND AVERAGE
- Sampling dates can be found in Table C-5.
Results until the week ending 5/26/92 were regorted by Controls for Environmental Pollution, Results reported thereafter were by the new Q lab, Teledlne Isotopes Inc.
a~
This sample was lost b¥ Teledyne Isotopes, therefore no A pha/Beta analysis was performed.
Sample loss from torn ilter.
AVERAGE
- 2. 5+/-1.3
- 2. 2+/-1. 3 2.1+/-1. 3 1.6+/-0.8
- 1. 7+/-0. 9 2.2+/-2.0 1.2+/-0.4 2.1+/-1. 4 3.4+/-2.4
- 1. 7+/-0. 7 2.2+/-1.6 2.1+/-1.0 1.5+/-0.8
- 2. 3+/-1.1 2.2+/-0.8 2.3+/-1.4 2.3+/-0.7 2.4+/-0.6 1.0+/-0.4 2.1+/-0.7 2.0+/-0.4
- 1. 6+/-0. 9
- 2. 5+/-1. 3
- 1. 3+/-0. 8 1.4+/-0. 7 3.0+/-0.8 2.2+/-1.8 Inc.
l TABLE C-2 1992 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in units of 10*3 pCi/m3 +/- 2 sigma
<--------------------------------- STATION ID --------------------------------->
MONTH SA-APT-5Sl SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)
JANUARY 19+/-2 13+/-2 20+/-2 19+/-2 17+/-2 14+/-2 17+/-6 27+/-2 24+/-2 27+/-3 28+/-3 24+/-2 18+/-2 25+/-7 20+/-2 19+/-3 22+/-2 28+/-3 25+/-2 22+/-2 23+/-7 27+/-2 24+/-2 24+/-2 28+/-2 27+/-2 21+/-2 25+/-5 28+/-3 29+/-3 29+/-2 29+/-3 28+/-3 28+/-2 29+/-1 FEBRUARY 17+/-2 16+/-2 19+/-2 18+/-2 19+/-2 20+/-2 18+/-3 15+/-2 19+/-2 17+/-2 18+/-2
- 18+/-2 21+/-2 18+/-4 19+/-2 16+/-2 I
21+/-2 19+/-3 20+/-3 18+/-2 19+/-3 19+/-2 19+/-2 20+/-2 20+/-2 21+/-2 19+/-2 20+/-2 00 MARCH 17+/-2 14+/-2 15+/-2 11+/-2 16+/-2 17+/-2 15+/-5 26+/-3 22+/-2 24+/-2 25+/-2 27+/-2 20+/-2 24+/-5 0
23+/-3 15+/-1 20+/-2 18+/-2 22+/-2 21+/-2 20+/-6 18+/-2 16+/-2 21+/-2 22+/-2 22+/-2 17+/-2 19+/-5 APRIL 25+/-3 17+/-2 16+/-2 20+/-3 22+/-3 21+/-2 20+/-7 26+/-3 20+/-2 28+/-2 28+/-3 26+/-2 42+/-4 28+/-15 13+/-2 15+/-2 13+/-2 15+/-2 18+/-2 13+/-2 15+/-4 12+/-2 11+/-1 13+/-2 14+/-2' 14+/-2 16+/-3 13+/-4 MAY 22+/-3 20+/-1 24+/-2 21+/-2 25+/-2 21+/-2 22+/-4 9.1+/-2.1 7+/-2 10+/-2 9.6+/-2.0 10+/-2
- 9. 8+/-1. 9 9+/-2 13+/-2 13+/-2 15+/-2 16+/-2 16+/-2 12+/-2 14+/-3 22+/-2 19+/-2 22+/-2 22+/-2 24+/-2 20+/-2 22+/-4 15+/-3 15+/-3 18+/-2 20+/-3 17+/-2 14+/-2 17+/-5 JUNE 7.* 5+/-2. 3 14+/-2 8.7+/-2.0 7.5+/-2.2 10+/-2 9.0+/-2.1 9+/-5 16+/-2 20+/-3 19+/-2 16+/-2 21+/-2 21+/-2 19+/-5 16+/-2 15+/-2 17+/-2 18+/-2 16+/-2 18+/-2 17+/-2 27+/-3
( 1) 24+/-2 24+/-2 24+/-2 21+/-2 24+/-4
TABLE C-2 (Cont'd) 1992 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma
<-----------~--------------------- STATION ID --------------------------------->
MONTH SA-APT-5Sl SA-APT-501 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)
JULY 22+/-3 20+/-2 20+/-2 20+/-2 24+/-3 22+/-2 21+/-3 27+/-3 27+/-3 30+/-3 28+/-3 27+/-2 20+/-2 27+/-7 24+/-3 22+/-3 24+/-2 23+/-3 23+/-2 20+/-2 23+/-3 19+/-2 21+/-3 16+/-2 15+/-2 20+/-2 18+/-2 18+/-5 28+/-3 22+/-3 27+/-3 23+/-2 24+/-2 20+/-2 24+/-6 AUGUST 26+/-3 22+/-3 24+/-3 24+/-3 30+/-3 23+/-2 25+/-6 19+/-2 18+/-2 18+/-2 19+/-2 18+/-2 19+/-2 19+/-1 22+/-3 25+/-3 25+/-3 22+/-3 22+/-2 22+/-2 23+/-3 26+/-2
- 25+/-3 33+/-3 27+/-3 33+/-3 28+/-3 29+/-7 SEPTEMBER 25+/-3 25+/-3 22+/-3 29+/-3 27+/-2 20+/-2 25+/-7 CX>
18+/-2 21+/-3 22+/-3 17+/-3 18+/-2 15+/-2 19+/-5 t-*
20+/-2 20+/-2 25+/-3 21+/-3 25+/-2 32+/-3 24+/-9 15+/-2 13+/-2 11+/-2 9.5+/-2.4 10+/-2 9.9+/-2.0 11+/-4 OCTOBER 30+/-3 31+/-3 29+/-3 30+/-3 28+/-3 31+/-3 30+/-2 22+/-2 21+/-2 22+/-2 23+/-2 22+/-2 19+/-2 22+/-3 32+/-3 29+/-3 31+/-3 37+/-3 35+/-3 35+/-3 33+/-6 28+/-3 28+/-3 27+/-3 28+/-3 26+/-3 24+/-2 27+/-3 29+/-3 28+/-3 29+/-3 30+/-3 29+/-3 26+/-2 29+/-3 NOVEMBER 12+/-2 14+/-2 2H1 12+/-2 12+/-2 12+/-2 11+/-8 26+/-3 21+/-2 26+/-3 23+/-2 21+/-2 23+/-5 25+/-3 25+/-3 24+/-2 23+/-3 27+/-2 25+/-2 25+/-3 18+/-2 16+/-2 17+/-2 17+/-2
- 11+/-2 12+/-2 16+/-4 DECEMBER 26+/-3 28+/-3 23+/-2 27+/-3 27+/-2 33+/-3 27+/-7 15+/-2 15+/-2 14+/-2 13+/-3 13+/-2 15+/-2 14+/-2 22+/-2 22+/-3 19+/-2 22+/-3 23+/-2 18+/-2 21+/-4 30+/-2 31+/-3 37+/-3 37+/-3 34+/-2 38+/-3 35+/-7 AVERAGE 21+/-12 20+/-11 21+/-13 21+/-13 22+/-12 21+/-14 GRAND AVERAGE 21+/-12
- Sampling dates can be found in Table C-5.
Environmental Pollution,
- Results until the week endin~ 5/26/92 were reported bl Controls for Inc. Results u~
re~orted thereafter were br he new QC lab, Teledyne sotopes Inc.
This sample was lost bt Te edyne Isotopes, therefore no alpha/beta analysis was performed.
Sample loss from torn ilter.
TABLE C-3 1992 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* AND GAMMA EMITTERS**
IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-* pCi/m' :!: 2 sigma
<-- STRONTIUM -->
<-- GAMMA EMITTERS -->
STATION ID SAMPLING PERIOD Sr-89 Sr-90 Be-7 SA-APT-5S1 12-30-91 to 03-31-92
<0.3
<0.2 63+/-5 SA-APT-5D1 (1) 12-30-91 to 03-31-92 (3)
(3)
(3)
SA-APT-16E1 12-30-90 to 03-31~92 0.4:!:0.1
<0.2 56:!:5 SA-APT-1F1 12~30-91 to 03-31-92
<0.3
<0.2 61+/-5 SA-APT-2F2 12-30-91 to 03-31-92
<0.3
<0.2 59+/-4 SA-APT-3H3 (C) 12-30-91 to 03-30-92 0.3:!:0.1
<0.2 55:1:5 SA-APT-5S1 03-31-92 to 06-29-92 87:1:7 SA-APT-501 (2) 03-31-92 to 06-29-92 81+/-10 SA-APT-16E1 03-31-92 to 06-29-92 80+/-5
. SA-APT-1 F1 03-31-92 to 06-29-92 73+/-6 SA-APT-2F2 03-31-92 to 06-29-92 95:1:6 SA-APT-3H3 (C) 03-30-92 to 06-29-92 81:!:4 SA-APT-5S1 06-29-92 to 09-29-92 78+/-5 SA-APT-5D1 (2) 06-29-92 to 09-29-92 70:1:7 SA-APT-16E1 06-'29-92 to 09-29-92 81+/-6 SA-APT-1F1 06-29-92 to 09-29-92 62+/-4 SA-APT~2F2 06-29-92 to 09-29-92 73+/-5 SA-APT-3H3 (C) 06-29-92 to 09-28-92 72+/-4 SA-APT-5S1 09-29-92 to 12-29-92 60+/-4 SA-APT-5D1 (2) 09-29-92 to 12-29-92 54+/-5 SA-APT-16E1 09-29-92 to 12-28-92 69:!:5 SA-APT-1F1 09-29-92 to 12-29-92 62+/-6 SA-APT-2F2 09-29-92 to 12-29 62+/-5 SA-APT-3H3 (C) 09-28-92 to 12-28-92 63+/-5 AVERAGE 69+/-22
- 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-28.
- Management audit analyses, not required by Technical Specifications or by specific conmitments to Local officials.
CC) Control Station (1) Results by Controls for Environmental Pollution, Inc.
(2) Results from 2nd Qtr to year's end 1992,. by Teledyne Isotopes, Inc.
(3) Controls for Environmental Pollution, Inc. never performed a gamma or strontium analysis on the first quarter air filter sample.
82 IC-40
<6.2 (3)
<4.2
<4.9
<3.6
<4.8 18+/-4
<20
<4.4 11+/-4
<4.5 10:1:4
<12
<20
<12
<4.1
<4.0
<3.8
<4.5
<10 11+/-4 11 +/-1
<4.2 12+/-3
QC)
(,,.)
MONTH JANUARY FEBRUARY MARCH APRIL MAY JUNE TABLE C-4 1992 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3
<-------------------------------------- STATION ID -------------------------------------->
SA-AI0-5Sl SA-AI0-5Dl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3
(
(Control)
<2.5
<13
<3.9
<4.3
<10
<10
<7.8
<13
<8.5
<10
<3.3
<6.7
<4.6
<13
<3.5
<8.5
<3.3
<1.9
<7.9
<13
<11
<3.7
<3.4'
<3.8
<4.0
<13
<4.2
<3.0
<4.7
<11
<4.4
<13
<7.1
<3.0'
<8.8
<3.2
<7.8
<13
<4.7
<11
<4.0
<6.7
<4.9
<13
<7.0
<8.8
<5.2
<7.4
<4.9
<13
<2.9
<5.1
<7.6
<7.8
<6.1
<13
<9.1
<5.3
<5.5
<7.8
<6.4
<13
<4.9
<5.8
<6.5
<3.5
<9.3
<13
<5.8
<3.4
<5.2
<7.7
<11
<13
<5.2
<6.4
<9.7
<10
<9.6
<13
<5.9
<11
<4.5
<8.1
<6.7
<13
<7.1
' <5. 6
<6.3'
<15
<12
<13
<6.3
<3.5
<13
<9.4
<10
<13
<8.1
<5.0
<13
<13
<6.7
<13
<4.6
<5.7
<9.3
<2.3
<4.6
<13
<5.6
<15
<3.6
<6.8
<5.7
<13
<6.9
<6.9
<3.8
<8.2
<5.1
<13
<5.4
<8.0
<6.2
<3.0
<7.5
<13
<1.8
<5.7
<13
<8.5
<6.6
<9.0
<3.3
<8.5.
<4.0
<3.4
<9.6
<10
<6.1
<12
<7.3
<12
<6.8
<10
<3.5
<8.6
<4.5
<2.4
<16 '
<9.0
<4.3
<4.0
<9.3
<9.8
00
-'="
TABLE C-4 (Cont'd) 1992 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3
<-------------------------------------- STATION ID -------------------~------------------>
MONTH SA-AI0-5Sl SA-AI0-5Dl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control)
JULY
<4.8
<10
<8.6
<8.2
<3.6
<10
<7.1
<10
<3.4
<4.6
<13
<7.5
<5.8
<20
<4.0
<5.0
<4.9
<2.1
<14
<20
<7.9
<7.7
<4.6
<10
<9.6
<10
<4.2
<3.7
<5.6
<2.2 AUGUST
<6.7
<20
<8.9
<11
<7.6
<10
<6.4
<10
<5.5
<1.6
<::10
<3.3
<12
<20
<4.9
<9.4
<4.3
<2.4
<9.1
<10
<5.8
<3.5
<3.4
<5.9 SEPTEMBER
<5.9
<20
<7.3
<5.2
<7.1
<3.6
<6.4
<20
<8.8
<13
<10
<6.9
<6.1
<10
<14
<5.4
<3.9
<5.5
<7.9
<40
<8.2
<17
<9.6
<6.7 OCTOBER
<3.6
<20
<5.7
<18
<5.2
<4.8
<4.7
<20
<4.7
<3.1
<8.8
<4.6
<4.1
<20
<9.0
<5.7
<12
<8.1
<8.5
<20
<5.4
<6.0
<13
<4.3
<12
<20
<3.9
<12
<3.7
<6.6 NOVEMBER
<6.2
<9.0
<5.5
<8.6
<6.9
<5.1
<5.9
~~~o
<3.5
<8.8
<8.2
<4.5
<7.8
<4.8
<9.1
<5.9
<4.8
<6.6
<8.0
<4.1
<7.1
<6.8
<3.1 DECEMBER
<9.2
<8.0
<6.8
<6.0*
<2.4
<3.6
<6.3
<10
<6.9
<5.2
<10
<4.7
<11
<20
<6.2
<9.3
<4.3
<5.0
<6.4
<9.0
<7.8
<8.5
<4.8
<3.7
- I-131 results are corrected for decay to sample stop date.
- Sampling dates can be found in Table C-5.
- Results until the week ending 6/01/92 were reported by Controls for Environmental Pollution, Inc. Results reported thereafter were by the new QC lab, Teledyne Isotopes Inc.
(l) There was no sample collected at this location for the weeR of 11/9-16/92. Air Iodine cartrige was never installed into the filter assembly.
O:>
VI MONTH JANUARY FEBRUARY TABLE C-5 1992 SAMPLING DATES FOR AIR SAMPLES
<--------~--------------------------- STATION CODE ------------------------------------>
5Sl 501 16El iFl 2F2 3Hj 12-30-91 to 01-06-92 01~06-92 to 01-13-92 01-13-92 to 01-20-92 01-20-92 to 01-27-92 01-27-92 to 02-03-92 02-03-92 to 02-10-92 02-10-92 to 02-18-92 02-18-92 to 02-24-92 02-24-92 to 03-02-92 12-30-91 to 01-06-92 01-06-92 to 01-13-92 01-13-92 to 01-20-92 01-20-92 to 01-27-92 01-27-92 to 02-03-92 02-03-92 to 02-10-92 02-10-92 to 02-18-92 02-18-92 to 02-24-92 02-24-92 to 03-02-92 12-30-91 to 01-06-92 01-06-92 to 01-13-92 01-13-92 to 01-20-92 01-20-92 to 01-27-92 01-27-92 to 02-03-92 02-03-92 to 02-10-92 02-10-92 to 02-18-92 02-18-92 to 02-24-92 02-24-92 to 03-02-92 12-30-91 to 01-06-92 01-06-92 to 01-13-92 01-13-92 to 01-20-92 01-20-92 to 01-27-92 01-27-92 to 02-03-92 02-03-92 to 02-10-92 02-10-92 to 02-18-92 02-18-92 to 02-24-92 02-24-92 to 03-02-92 12-30-91 to 01-06-92 01-06-92 to 01-13-92 01-13-92 to 01-20-92 01-20-92 to 01-27-92 01-27-92 to 02-03-92 02-03-92 to 02-10-92 02-10-92 to 02-18-92 02-18-92 to 02-24-92 02-24-92 to 03-02-92 (Control) 12-30-91 to 01-06-92 01-06-92 to 01-13-92 01-13-92 to 01-20-92 01-20-92 to 01-27-92 01-27-92 to 02-03-92 02-03-92 to o~-10-92 02-10-92 to 02-18-92 02-18-92 to 02-24-92 02-24-92 to 03-03-92
TABLE C-5 (Cont'd) 1992 SAMPLING DATES FOR AIR SAMPLES
<------------------------------------ STATION CODE ------------------------------------>
MONTH 5Sl 5Dl 16El lFl 2F2 3H3 (Control)
MARCH 03-02-92 03-02-92 03-02"'.'92 03-02-92 03-02-92 03-02-92 to to to to to to 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 03-09-92 to to to to to to 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 03-16-92 to to to to to to 03-23-92 03-23-92 03-23-92 03-23-92 03-23-92 03-23-92 00 03-23-92 03-23-92 03-23-92 03-23-92 03-23-92 03-23-92 CJ'\\
to to to to to to 03-31-92 03-31-92 03-31-92 03-31-92 03-31-92 03-30-92 APRIL 03-31-92 03-31-92 03-31-92 03-31-92 03-31-92 03-30-92 to to to to to to 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 04-06-92 to to to to to to 04-13-92 04-13-92 04-13-92 04-13-92 04-13-92 04-13-92 04-13-92 04-13-92 04-13-92 04....:13-92 04-13-92 04-13-92 to to to to to to 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 04-20-92 to to to to to to 04-27-92 04-27-92 04-27-92 04-27-92 04-27-92 04-27-92 MAY 04-27-92 04-27-92 04-27-92 04-27-92 04-27-92 04-27-92 to to to to to to 05-04-92 05-04-92 05-04-92.
05-04-92 05-04-92 05-04-92
TABLE C-5 (Cont'd) 1992 SAMPLING DATES FOR AIR SAMPLES
<------------------------------------ STATION CODE ------------------------------------>
MONTH 5Sl 501 16El lFl 2F2.
3H3 (Control)
MAY 05-04-92 05-04-92 05-04-92 05-04~92 05-04-92 05-04-92 to to to to to to 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 05-11-92 to to to to to to 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 05-18-92 to to to to to to 05-26-92 05-26-92*
05:-26-92 05-26-92 05-26-92 05-26-92 00 05-26-92 05-26-92
..... J 05-26-92 05-26-92 05-26-92 05-26-92 to to to to to to 06-01-92 06-01-92 06-01-92 06-01-92 06-01-92 06-01-92 JUNE 06-01-92 06.!0l-92 06-01-92 06-01-92 06-01-92 06-01-92 to to to to to to 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06-08-92 06*-00-92 to to to to to to 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 06-15-92 to to to to to to 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 06-22-92 to to to to to to 06-29-92 06-29-92 06.-29-92 06-29-92 06-29-92 06-29-92 JULY 06-29-92 06-29-92 06-29-92 06-29-92 06-29-92 06-29-92 to to to to to to 07-06-92 07-06-92 07-06-92 07-06-92 07-06-92 07-06-92
TA~LE C-5 (Cont'd) 1992 SAMPLING DATES FOR AIR SAMPLES
<------------------------------------ STATION CODE ------------------------------------>.
MONTH 5Sl 5Dl 16El lFl 2F2 3H3.
(Control)
JULY 07-06-92 07-06-92 07-06-92 07-06-92 07-06-92 07-06-92 to to to to to to 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 07-13-92 to to to to to to 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 07-20-92 to**
to to to to to 07-27-92 07-27-92 07-27-92 07-27-92 07-27-92 07-27-92 00 00 07-27-92 07-27-92 07-27-92 07-27-92 07-27-92 07-27-92 to to to to to to 08-03-92 08-03-92 08-03-92 08-03-92 08-03-92 08-03-92 AUGUST 08-03-92 08-03-92 08-03-92 08-03-92 08-03-92 08-03-92 to to to to to to 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 08-10-92 to to to to to to 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 08-17-92 to to to to to to 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 08-24-92 to to to to to to 09-01-92 09-01-92 09'-01-92 09-01-92 09-01-92 08-31-92
TABLE c-5 (Cont'd) 1992 SAMPLING DATES FOR AIR SAMPLES
<-----------------------------,------- STATION CODE -----------------~---------------~-->
MONTH 5Sl 501 16El lFl 2F2 3H3 (Controi)
SEPTEMBER 09-01-92 09-01-92 09-01-92 09-01-92 09-01-92 08-31-92 to to to to to to 09-08-92 09-08-92 09-08,-92 09-08-92 09-08-92 09-08-92 09-08-92 09-08-92 09-08-92 09-08-92.
09-08-92 09-08-92 to to to to to to 09-15-92 09-15-92 09-15-92 09-15-92 09-15-92 09-14-92 09-15-92 09-15-92 09-15-92 09-15-92 0'9-15-92 09-14-92 to to to to to to 09-22-92 09-22-92 09-22-92 09-22-92 09-22-92 09-21-92 00
'09-22-92 09-22-92 09-22-92 09-22-92 09-22-92 09-21-92 l.C to to to to to to 09-29-92 09-29-92 09-29-92 09-29-92 09-29-92 09-28-92 OCTOBER 09-29-92 09-29-92 09-29-92 09-29-92 09-29-92 09-28-92 to to to to to to 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92 10-05-92
.10-05-92 to to to to to to 10-13-92 10-13-92 10-13-92*
10-13-92 10-13-92 10-13-92 10-13-92 10-13-92 10-13-92 10-13-92 10-13-92 10-13-92 to to to to to to 10-20-92 10-20-92 10-20-92 10-20-92 10-20-92 10-19-92 10-20-92 10-20-92 10-20-92 10-20-92 10-20-92 10-19-92 to to to to to to 10-25-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 10-26-92 to to to to to to 11-02-92 11-02-92 11-02-92 11-02-92 11-02-92 11-02-92
TABLE C-5 (Cont'd) 1992 SAMPLING DATES FOR AIR SAMPLES
<------------------------------------ STATION CODE ------------------------------------>
MONTH 5Sl 5Dl 16El lFl 2F2 3H3.
(Control)
NOVEMBER 11-02-92 11-02-92 11-02-92 11-02-92 11-02-92 11-02-92 to to to to to to 11-09-92 11-09-92 11-09-92 11-09-92 11-09-92 11-09-92 11-09-92 11-09-92(l) 11-09-.92 11-09-92 11-09-92 11-09-92 to to to to to to 11-16-92 11-16-92 11-16-92 11-16-92 11-16-92 11-16-92 11-16-92 11-16-92 11-16-92 11-16-92 ll'.""16-92 11-16-92 to to to to to to 11-23-92 11-23-92 11-23-92 11-23-92 11-23-92 11-23-92
\\0 11-23-92 11-23-92 11-23-92 11-23-92 11-23-92 11-23-92 0
.to to to to to to 12-01-92 12-01-92 12-01-92 12-01-92 12-01-92 11-30-92 DECEMBER 12-01-92 12-01-92 12-01-92 12-01-92 12-01-92 11-30-92 to to to to to to 12-08-92 12-08-92 12-08-92 12-08-92 12-08-92 12-07-92 12-08-92 12-08-92 12-08-92 12-08-92 12-08-92 12-07-92 to to to to to to 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 12-14-92 to to to to to to 12-21-92 12-21-92 12-21-92 12-21-92 12-21-92 12-21-92 12:..21-92 12-21-92 12-21-92 12-21-92 12-21-92 12-21-92 to to to to to to 12-29-92 12-29-92 12-28-92 12-29-92 12-29-92 12-28-92 (1)
No air iodine cartridge was loaded into the assembly for the week of 11/9-16/92; however, an air particulate filter was collected.
TABLE C-6 1992 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, TRITIUM AND GAMMA EMITTERS* IN PRECIPITATION Results in Units of pCi/L +/- 2 sigma STATION ID:
SA-RWA-2F2
<--GAMMA EMITTERS-->
SAMPLING PERIOD GROSS ALPHA GROSS BETA TRITIUM Be-7 K-40 12-30-91 to 01-2.7-92
<1.4 2.0+/-0.8
<160 120+/-40 140+/-55 01-27.-92 to 03-02-92
<1.0 1.1+/-0. 7 220+/-110 46+/-16
<49 03-02-92 to 03-31-92
<1.0 2.3+/-0.7
<170 92+/-20
<50 03-31-92 to 04-27-92 1.4+/-1.1 15+/-2 810+/-100 160+/-47
<64 04-27-92 to 06-01-92
<1.3 2.4+/-0.7 220+/-90 58+/-12
<13 06-01-92 to 06-29-92
<1.2 6.4+/-1.0 240+/-90 140+/-23
<19 06-29-92 to 07-27-92 1.4+/-1.0 6.5+/-1.0
<150 89+/-29
<23 07-27-92 to 09-01-92
<1.4
- 7. 0+/-1.1
<150 78+/-16
<16 09-01-92 to 09-29-92
<3.7 3.3+/-0.7 160+/-90 45+/-13 60+/-25 09-29-92 to H-02-92
<1.3 5.2+/-0.9
<150 81+/-12
<17 11-02-92 to 12-01-92
<1.2 1.1+/-0. 7
<140 43+/-14 56+/-14 12-01-92 to 12-29-92
<0.8 2.6+/-0.8
<130 58+/-19
<18 AVERAGE 4.6+/-7.8 84+/-77
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28
- 91
TABLE C-7 1992 DIRECT RADIATION MEASUREMENTS -
QUARTERLY TLD RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)
JANUARY.
APRIL JULY OCTOBER STATION ID to to to to MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 6.0+/-0.3 5.4+/-0.2 5.6+/-0.6 4.8+/-0.4 SA-IDM-5Sl 5.6+/-0.3 4.2+/-0.9 5.0+/-0.3 4.4+/-0.2 SA-IDM-6S2 6.0+/-0.3 5.3+/-0.2 5.5+/-0.3 4.6+/-1.3 SA-IDM-7Sl 7.7+/-0.6 6.7+/-0.4 8.6+/-2.1 6.3+/-0.6 SA-IDM-lOSl 6.7+/-0.5 5.8+/-0.5 5.9+/-0.4 6.4+/-1.0 SA-IDM-llSl 5.6+/-0.3 5.1+/-0.3 5.4+/-0.3 9.5+/-3.0 SA-IDM-402 6.5+/-0.7 5.8+/-0.4 5.9+/-0.4 5.6+/-0.5 SA-IDM-501 5.0+/-0.4 5.4+/-0.3 5.4+/-0.4 5.1+/-0. 4 SA-IDM-1001 6.6+/-0.6 5.7+/-0.4 6.0+/-0.4 5.7+/-0.4 SA-IDM-1401 6.2+/-0.4 5.4+/-0.2 5.7+/-0.3 5.0+/-0.3 SA-IDM-2Ei
- 5. 5+/-1.1 5.5+/-0.6 5.6+/-0.5 4.9+/-0.4 SA-IDM-3El 5.7+/-0.4 5.0+/-0.4 5.3+/-0.3 4.8+/-0.4 SA-IDM-9El 6.2+/-0.8 6.2+/-0.4 6.6+/-0.5 5.9+/-0.5 SA-IDM-11E2 6.8+/-0.7 6.2+/-0.3 6.4+/-0.4 5.7+/-0.5 SA-IDM-12El 6.6+/-0.5 5.7+/-0.3 5.2+/-0.4 5.8+/-0.4 SA-IDM-13El 5.9+/-0.4 5.1+/-0~1 5.5+/-0.4 4.9+/-0.2 SA-IDM-16El 6.2+/-0.5 5.9+/-0.3 5.9+/-0.4 5.2+/-0.3 SA-IDM-lFl 6.5+/-1.2 5.6+/-0.3 5.9+/-0.3 5.1+/-0.2 SA-IDM-2F2 5.4+/-0.4 4.6+/-0.4 4.7+/-0.2 4.1+/-0.2 SA-IDM-2F5 6.1+/-0.6*
5.8+/-0.3 5.7+/-0.5 5.0+/-0.2 SA-IDM-2F6 6.0+/-0.2 4.9+/-0.2 5.6+/-0.4 4.9+/-0.2 SA-IDM-3F2 5.7+/-0.4 5.2+/-0.9 5.3+/-0.3 4.6+/-0.2 SA-IDM-3F3 6.2+/-0.5 5.0+/-0.3 5.1+/-0.2 4.4+/-0.2 SA-IDM-5Fl 6.0+/-0.5 5.3+/-0.3 5.5+/-0.2 4.8+/-0.2 SA-IDM-6Fl 5.4+/-0.2 4.4+/-0.1
- 4.7+/-0.1 4.2+/-0.1 SA-IDM-7F2 4.8+/-0.8 4.4+/-0.1 4.4+/-0.2 4.0+/-0.3 SA-IDM-10F2 6.3+/-0.6 6.1+/-0.4 6.2+/-0.4 5.6+/-0.5 SA-IDM-llFl 6.6+/-0.6 5.4+/-0.3 5.4+/-0.4 5.5+/-0.4 SA-IDM-12Fl 5.5+/-0.4 5.7+/-0.6 5.9+/-0.3 4.7+/-0.6 SA-IDM-13F2 6.3+/-0.9 5.6+/-0.3 5.8+/-0.2 5.3+/-0.3 SA-IDM-13F3 6.4+/-0.6 5.6+/-0.5 5.0+/-0.7 5.3+/-0.4 SA-IDM-13F4 6.0+/-0.4 5.7+/-0.4 5.8+/-0.3 5.2+/-0.3 SA-IDM-14F2 7.1+/-0.6 6.5+/-0.5 6.7+/-0.4 6.2+/-0.4 SA-IDM-15F3 6.8+/-0.6 6.0+/-0.5 6.2+/-0.4 5.6+/-0.5 SA-IDM-16F2
- 5.-9+/-0. 3 5.4+/-0.2 5.4+/-0.3 5.1+/-0.3 SA-IDM-1G3 (C) 7.0+/-0.5 6.2+/-0.2.
6.5+/-0.5 6.0+/-0.3 SA-IDM-3Gl (C) 6.4+/-0.5 5.6+/-0.4 5.7+/-0.6 5.2+/-0.3 SA-IDM-lOGl (C) 6.4+/-0.6 5.7+/-0.5 5.4+/-0.5 5.4+/-0.5 SA-IDM-16Gl (C) 6.5+/-0.4 5.7+/-0.3 5.5+/-0.4 5.7+/-0.4 SA-IDM-3Hl (C).6.0+/-0.3 5.3+/-0.2 5.6+/-0.2 4.8+/-0.2 SA-IDM-3H3 (C) 6.5+/-0.6 5.8+/-0.4 5.9+/-0.3 5.0+/-0.4 AVERAGE 6.2+/-1.1 5.5+/-1.1
- 5. 7+/-1.4 5.3+/-1.8 GRAND AVERAGE
- The standard month = 30.4 days.
(C) Control station 92 AVERAGE
- 5. 5+/-1. 0 4.8+/-1.3 5.4+/-1.2 7.3+/-2.1 6.2+/-0.8 6.4+/-4.2 6.0+/-0.8 5.2+/-0.4 6.0+/-0.8
- 5. 6+/-1. 0 5.4+/-0.6 5.2+/-0.8 6.2+/-0.6 6.3+/-0.9 5.8+/-1.2 5.4+/-0.9 5.8+/-0.8 5.8+/-1.2
- 4. 7+/-1.1 5.7+/-0.9 5.4+/-1.1
. 5.2+/-0.9 5.'2+/-1.5
- 5. 4+/-1. 0
- 4. 7+/-1.1 4.4+/-0.7 6.1+/-0.6
- 5. 7+/-1.2
- 5. 5+/-1.1 5.8+/-0.8 5.6+/-1.2 5.7+/-0.7 6.6+/-0.8 6.2+/-1.0 5.5+/-0.7 6.4+/-0.9
. 5. 7+/-1.0 5.7+/-0.9 5.9+/-0.9
- 5. 4+/-1.0
- 5. 8+/-1.2
- 5. 7+/-1. 5
TABLE C-8 1992 DIRECT RADIATION MEASUREMENTS -
MONTHLY TLO RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)
STATION ID JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2
.8. 4+/-0. 7 6.9+/-0.4 7.3+/-0.6 8.2+/-0.9 5.3+/-0.1
- 8. 6+/-1. 3 SA-IDM-5Sl 7.5+/-0.5 6.4+/-0.6 7.2+/-1.1 7.4+/-0.4 5.6+/-0.1 8.3+/-0.3 SA-IDM-6S2 8.3+/-0.6 7.0+/-0.7 7.4+/-0.5 7.5+/-2.4 6.2+/-0.3 8.9+/-0.3 SA-IDM-7Sl 10+/-1 8.3+/-0.5 8.8+/-0.8 9.0+/-0.5
- 7. 6+/-0*. 7 10+/-1 SA-IDM-lOSl 9.2+/-0.9 8.0+/-0.3
- 8. 6+/-1. 6 8.5+/-0.4 6.8+/-0.3 9.4+/-0.7 SA-IDM-llSl 8.2+/-0.6 I 7.7+/-1.6 7.6+/-1.7 7.3+/-0.4 6.2+/-0.5 8.5+/-0.6 SA-IDM-501 8.1+/-0.6 7.0+/-0.3 7.5+/-0.5 7.8+/-0.6 5.9+/-0.5 8.8+/-0.5 SA-IDM-1001 8.6+/-0.5 7.5+/-0.4 8.1+/-0. 7 8.2+/-0.4 6.6+/-0.5 9.4+/-0.6 SA-IDM-1401 8.2+/-1.2 7.5+/-0.8 7.6+/-0.5 7.9+/-0.4 6.2+/-0.6 9.1+/-0. 5 SA-IDM-2El 8.1+/-0.8 6.9+/-0.5 7.8+/-0.7 7.8+/-0.4 6.0+/-0.3 8*.7+/-0.5
\\Cl SA-IDM-3El 8.0+/-0.4 6.5+/-0.3 7.0+/-0.5 7.7+/-0.5 5.7+/-0.4 8.5+/-0.5 U.:*
SA-IDM-13El 8.0+/-0.5 7.0+/-0.8 7.4+/-0.5 7.8+/-0.4 5.9+/-0.5 9.1+/-0. 7 SA-IDM-16El 8.6+/-0.5 7.4+/-0.7 7.1+/-0. 5 8.2+/-0.6 6.1+/-0. 3 9.0+/-0.4 SA-IDM-lFl 8.2+/-0.6 7.5+/-0.4 7.7+/-0.4 8.2+/-0.4 6.2+/-0.4 9.1+/-0.4 SA-IDM-2F2 7.6+/-0.3 6.6+/-0.2 6.6+/-0.5 7.3+/-0.3 5.4+/-0.4 8.1+/-0.2 SA-IOM-2F6 8.4+/-0.5 7.1+/-0.3 7.4+/-0.5 8.0+/-0.2 6.0+/-0.2 8.7+/-0.4 SA-IDM-5Fl 7.9+/-0.7 6.9+/-0.6 7.3+/-0.6 7.8+/-0.4 5.9+/-0.3 8.8+/-0.3 SA-IDM-6Fl 6.9+/-0.5 6.3+/-0.2 6.4+/-0.8 7.2+/-0.4 5.3+/-0.5 8.3+/-0.3 SA-IDM-7F2 7.0+/-0.4 5.9+/-0.3 6.4+/-0.3 6.9+/-0.8 5.0+/-0.3 7.5+/-0.4 SA-IDM-llFl 8.4+/-0.5 8.1+/-1. 0 8.3+/-0.5 8.1+/-0.6 6.8+/-0.3 10+/-1 SA-IDM-13F4 8.1+/-1.1 7.3+/-0.5 8.0+/-0.6 8.1+/-0.4 6.3+/-0.1 9.7+/-0.5 SA-IDM-3Gl ( c) 8.5+/-0.7 7.1+/-0.4 7.9+/-0.3 8.0+/-0.5
- 6.4+/-0.5 9.9+/-0.5 SA-IDM-3Hl ( c) 8.3+/-0.4 6.8+/-0.3 7.4+/-0.4
- 7. 7+/-0. 8 6.3+/-0.4 9.7+/-0.3.
SA-IDM-3H3 ( c) 8.8+/-0.7 7.8+/-0.4 8.1+/-0. 4 7.4+/-0.9 6.9+/-0.4 9.9+/-0.6 AVERAGE 8.2+/-1.3 7.1+/-1.2
- 7. 5+/-1. 2 7.8+/-0.9 6.1+/-1.2 9.0+/-1.3
TABLE C-8 (Cont'd) 1992 DIRECT RADIATION MEASUREMENTS -
MONTHLY TLC RESULTS Results in mrad/standard month* +/- 2 sigma (Results by Teledyne Isotopes)
STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 7.9+/-0.7 6.7+/-0.4 6.7+/-0.5 5.7+/-0.6 4.8+/-0.6 7.~+/-0.5 7.0+/-2.4 5A-IDM-5Sl 7.3+/-0.5
.6.2+/-0.3 6.4+/-0.3 5.6+/-0.5 4.4+/-0.4 6.9+/-0.4 6.6+/-2.1 SA-IDM-652 8.1+/-0.4 6.6+/-0.5 7.0+/-0.3 6.2+/-0.3 4.9+/-0.4 8.0+/-1.4 7.2+/-2.2 5A-IDM-751 9.2+/-0.5 7.9+/-0.5 8.3+/-0.8 7.4+/-0.9 6.4+/-1.2 8.7+/-0.8 8.5+/-2.1 SA-IDM-1051 7.4+/-0.7 6.3+/-1.7 7.7+/-0.6 6.9+/-0.9 6.6+/-1.3 8.9+/-1.3 7.9+/-2.1 SA-IDM-llSl 7.6+/-0.9 7.1+/-0.7 7.3+/-0.7 7.9+/-1.5 11+/-4 13+/-4 8.3+/-3.8
.SA-IDM-5Dl 7.9+/-0.5 6.6+/-0.6 6.7+/-0.6 6.2+/-0.5 4.6+/-0.6 7.1+/-0. 5 7.0+/-2.3 SA-IDM-1001 8~7+/-0.6 7.4+/-0.5 7.3+/-0.5 7.2+/-0.7 5.2+/-0.7 8.0+/-0.5 7.7+/-2.2 SA-IDM-1401 8.0+/-0.4 6.0+/-1.3 6.2+/-0.7 6.4+/-0.5 4.8+/-0.6 7.6+/-0.6 7.1+/-2.4 5A-IDM-2El 8.1+/-0.6 6.7+/-0.4 6.7+/-0.2 6.3+/-0.8 4.7+/-0.3 7.3+/-0.7 7.1+/-2. 2
\\0 SA-IDM-3El 7.8+/-0.4.
6.5+/-0.5 6.5+/-0.2 6.0+/-0.8 4.6+/-0.4 7.1+/-0. 5 6.8+/-2.2
~
SA-IDM-13El 7.8+/-0.5 6.5+/-0.2 6.6+/-0.4 6.2+/-0.5 5.0+/-0.7 7.7+/-0.7 7.1+/-2. 2 SA-IDM-16El 8.3+/-0.5 6.9+/-0.5 6.9+/-0.4 6.4+/-0.7 5.0+/-0.7 7.6+/-0.7 7.3+/-2.3 SA-IDM-lFl 8.3+/-0.7 6.7+/-0.8 7.2+/-0.3 6.4+/-0.9 5.2+/-0.8 7.4+/-0.5 7.3+/-2.2
- SA-IDM-2F2 7.2+/-0.2 5.8+/-0.4 6.1+/-0.2 5.5+/-0.4 4.2+/-0.4 6.6+/-0.2 6.4+/-2.2 5A-IDM-2F6 7.9+/-0.4 6.5+/-0.6 6.9+/-0.2 6.1+/-0.5 4.5+/-0.5 7.2+/-1.1 7.1+/-2. 3.
SA-IDM-5Fl 8.1+/-0.4 6.5+/-0.5 6.9+/-0.5 6.0+/-0.7 5.0+/-0.9 7.1+/-0. 7 7.0+/-2.1 SA-IDM-6Fl 7.2+/-0.6 5.5+/-0.5 6.3+/-0.2 5.5+/-0.4 4.2+/-0.9 6.5+/-0.5 6.3+/-2.2 5A-IDM-7F2 6.9+/-0.2 5.4+/-0.2 5.8+/-0.2 5.0+/-0.5 3.9+/-0.1 6.1+/-0.4 6.0+/-2.1 SA-IDM-llFl 8.6+/-0.4 7.6+/-0.5 7.3+/-0.5 7.0+/-0.8 5.6+/-0.8.
8.5+/-0.8 7.9+/-2.2 SA-IDM-13F4 8.4+/-0.5 7.0+/-0.4 7.1+/-0.3 6.7+/-0.9 5.5+/-0.6 8.3+/-0.6 7.5+/-2.2 SA-IDM-3Gl ( c) 8.4+/-0.7 7.1+/-0.5 7.4+/-0.4 6.4+/-1.2
- 5.4+/-0.4 7,;6+/-0.5 7.5+/-2.3 SA-IDM-3Hl (C) 8.0+/-0.2 6.9+/-0.6 7.2+/-0.7 6.3+/-0.7 5.1+/-0.2 7.3+/-0.5 7.3+/-2.3 5A-IDM-3H3 ( c) 8.8+/-0.5
- 7. 5+/-1. 0 8.0+/-0.5 7.8+/-0.8 5.6+/-0.6 8.4+/-0.7 7.9+/-2.1 AVERAGE
- 8. 0+/-1.1 6.7+/-1.2 6.9+/-1.2 6.4+/-1.4 5.3+/-2.8 7.8+/-2.6 GRAND AVERAGE 7.2+/-2.5
- The standard month = 30.4 days (C) Control Station
TABLE C-9 1992 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING
<----- GAMMA EMITTERS ----->
STATION ID PERIOD I-131 K-40 Ra-226 SA-MLK-2F7 01/6-7/92
<0.2 1400+/-100
<5.9 SA-MLK-11F3 01/6-7/92
<0.1 1300+/-69
<3.8 SA-MLK-14F4 01/6-7/92
<0.2 1300+/-84
<4.4 SA-MLK-3Gl (C) 01/5-6/92
<0.2 1400+/-79 24+/-4 SA-MLK-2F7 02/2-3/92
<0.2 1200+/-75
<3.0 SA-MLK-11F3 02/2-3/92
<0.3 1300+/-82
<3.6 SA-MLK-14F4 02/2-3/92
<0.1 1400+/-67
<4.0 SA-MLK-3Gl (C) 02/2-3/92
<0.2.
1300+/-80
<3.8 SA-MLK-2F7 03/8-9/92
<0.3 1400+/-88
<4.4 SA-MLK-11F3 03/9-10/92
<0.2 1400+/-86
<3.7 SA-MLK-14F4 03/9-10/92
<0.3 1400+/-72
<3.1 SA-MLK-3Gl (C) 03/8-9/92
<0.2 1300+/-77
<1.4 SA-MLK-2F7 04/5-6/92
<0.3 1400+/-97
<5.3 SA-MLK-11F3 04/6-:7/92
<0.3 1400+/-82
<3.8 SA-MLK-14F4 04/5-6/92
<0.3 1400+/-68
<4.1 SA-MLK-3Gl (C) 04/5-6/92
<0.1 1400+/-83
<4.6 SA-MLK-2F7 04/19-20/92
<0.3 1400+/-96
<4.5 SA-MLK-11F3 04/20-21/92
<0.2 1400+/-86
<4.1 SA-MLK-14F4 04/19-20/92
<0.2 1400+/-69
<i2 SA-MLK-3Gl (C) 04/19-20/92
<0.2 1400+/-80
<3.6 SA-MLK-2F7 05/3-4/92
<0.2 1500+/-91
<3.7 SA-MLK-11F3 05/4-5/92
<0.1 1400+/-77
<4.0 SA-MLK-14F4 05/3-4/92
<0.3 1400+/-82
<3.7 SA-MLK-3Gl (C) 05/3-4/92
<0.2 1300+/-68
<3.2 SA-MLK-2F7 05/17-18/92
<0.4 1200+/-94
<4.4 SA-MLK-11F3 05/18-19/92
<0.3 1400+/-84
<3.3 SA-MLK-14F4 05/17-18/92
<0.1 1400+/-69
<3.0 SA-MLK-3Gl (C) 05/17-18/92
<0.2 1400+/-78
<6.8 SA-MLK-2F7 06/8-9/92
<0.3 1500+/-92
<3.7 SA-MLK-11F3 06/7-8/92
<0.2 1400+/-84
<3.7 SA-MLK-14F4 06/8-9/92
<0.3 1400+/-110
<4.8 SA-MLK-3Gl (C) 06/8-9/92
<0.2 1300+/-73
<5.0 SA-MLK-2F7 06/22-23/92
<0.3 1400+/-84
<4.6 SA-MLK-11F3 06/22-23/92
<0.3 1300+/-70
<3.3 SA-MLK-14F4 06/22-23/92
<0.3 1400+/-82
<4.4 SA-MLK-3Gl (C) 06/22-23/92
<0.3 1300+/-86
<3.0 SA-MLK-2F7 07/6-7/92
<0.2 1400+/-93
<3.2 SA-MLK-11F3 07/6-7/92
<0.4 1400+/-84
<4.3 SA-MLK-14F4 07/6-7/92
<0.3 1400+/-79
<7.8 SA-MLK-3Gl (C) 07/5-6/92
<0.2 1300+/-69
<3.9 SA-MLK-2F7 07/20-21/92
<0.3 1600+/-88
<3.4 SA-MLK-11F3 07/20-21/92
<0.2 1400+/-77
<3.9 SA-MLK-14F4 07/20-21/92
<0.2 1400+/-68
<2.4 SA-MLK-3Gl (C) 07/19-20/92
<0.3 1300+/-98
<5.9 95
TABLE C-9 (Cont'd) 1992 CONCENTRATIONS C>,F IODINE-131* AND GAMMA EMITTERS** IN MILK Results in Units of pCi/L +/- 2 sigma SAMPLING
<----- GAMMA EMITTERS ----->
STATION ID PERIOD I-131 K-40 Ra-226 SA-MLK-2F7 08/3-4/92
<0.3 1500+/-86
<3~3 SA-MLK-11F3 08/3-4/92
<0.3
. 1400+/-70
<3.1 SA-MLK-14F4 08/3-:4/92
<0.2 1400+/-100
<5.0 SA-MLK-3Gl (C) 08/2-3/92
<0.3 1400+/-86
<4.7 SA-MLK-2F7 08/17-18/92
<0.2 1300+/-82
<3.6 SA-MLK-11F3 08/17-18/92
<0.3.
1400+/-82
<3.4 SA-MLK-14F4 08/17-18/92
<0.1 1400+/-90
<4.5 SA-MLK-3Gl (C) 08/16-17/92
<0.1 1400+/-69
<2.6 SA-MLK-2F7 09/8-9/92
.<0.2 1400+/-89
<2.7 SA-MLK-11F3 09/8-9/92
<0.2 1400+/-80
<3.0 SA-MLK-14F4 09/8-9/92
<0.2 1200+/-79
<3.6 SA-MLK-3Gl (C) 09/8-9/92
<0.3 1400+/-67
<2.9 SA-MLK-2F7 09/22-23/92
<0.3 1400+/-86
<6.3 SA-MLK-11F3 09/22-23/92
<0.1 1400+/-83
<4.9 SA-MLK-14F4 09/22-23/92
<0.4 1400+/-70
<2.9 SA-MLK-3Gl (C) 09/22-23/92
<0.2 1100+/-62
<2.4 SA-MLK-2F7 10/4-5/92
<0.2 1400+/-78
<4.7 SA-MLK-11F3 10/5-6/92
<0.2 1500+/-75
<4.4 SA-MLK-14F4 10/5-6/92
<0.3 1500+/-86
<7.0 SA-MLK-3Gl (C) 10/4-5/92
<0.2 1400+/-87
<3.2 SA-MLK-2F7 10/20-21/92
<0.3 1400+/-75
<3.8 SA-MLK-11F3 10/20-21/92
<0.3 1400+/-79
<4.8 SA-MLK-14F4 10/20-21/92
<0.2 1300+/-90
<4.5 SA-MLK-3Gl (C) 10/19-20/92
<0.3 1300+/-82
<7.2 SA-MLK-2F7 11/9-10/92
<0.3 1300+/-75
<4.0 SA-MLK-11F3 11/9-10/92
<0.3 1100+/-94
<3.5 SA-MLK-14F4 11/8-9/92
<0.4 1400+/-86
<4.8 SA-MLK-3Gl (C) 11/9-10/92
<0.4 1400+/-83
<4.2 SA-MLK-2F7 11/23-24/92
<0.2 1500+/-90
<9.9 SA-MLK-11F3 11/23-24/92
<0.2 1500+/-71
<2.4 SA-MLK-14F4 11/23-24/92
<0.3 1400+/-85
<8.9 SA-MLK-3Gl (C) 11/22-23/92
<0.4 1300+/-66
<3.4 SA-MLK-2F7 12/7-8/92
<0.3 1400+/-78
<3.8 SA-MLK-11F3 12/8-9/92
<0.4 1500+/-73
<2.5 SA-MLK-14F4 12/8-9/92
<0.7 1400+/-82
<6.5 SA-MLK-3Gl (C) 12/7-8/92
<0.2 1200+/-120
<2.2 AVERAGE 1375+/-170
- Iodine-131 results are corrected for decay to midpoint of collection period.
Iodine-131 analyzed to a sensitivity of 1.0 pCi/liter.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
- Monthly a.ample collected during Jan., Feb., March and Dec., when animals are not on pasture.
(C) Control Station 96
TABLE C-10 1992 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* IN MILK**
Results in Units of pCi/L +/- 2 sigma STATION ID SAMPLING PERIOD
<--- STRONTIUM --->
Sr-89 Sr-90 SA-MLK-2F7 SA-MLK-11F3 SA-MLK-14F4 SA-MLK-3Gl (Control)
AVERAGE 7/06-07/92 7/06-07/92 7/06-07/92 7/05-06/92
<1.2 3.4+/-0.5
<1. 0 1.1+/-0.4
<1.0 1.8+/-0.4
<1.2 2.4+/-0.5 2.2+/-1.9
- 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.
97
TABLE C-11 1992 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 SA-WWA-2S3 01-27-92
<1.4
- 4. 9+/-1. Q 5.3+/-0.5 SA-WWA-3El (C) 01-27-92
<1.4 10+/-1 9.4+/-0.9 SA-WWA-2S3 02-24-92
<0.9 2.8+/-0.8 2.0+/-0.2 SA-WWA-3El (C) 02-24-92
<1.0 11+/-1 5.6+/-0.6 SA-WWA-2S3 03-31-92
<1.3 2.2+/-0.7 3.2+/-0.3 SA-WWA-3El (C) 03-31-92
<1.2 11+/-1 9.9+/-1. 0 SA-WWA-2S3 04-28-92
<1.3 6.5+/-1.0 6.4+/-0.6 SA-WWA-3El (C) 04-27-92
<1.3 10+/-1 9.6+/-1.0 SA-WWA-2S3 05-26-92
<1.3
- 7. 8+/-1.* 1 7.5+/-0.7 SA-WWA-3El (C) 05-26-92
<1.4 10+/-1 9.8+/-1.0 SA-WWA-2S3 06-29-92 2.4+/-1.4 5.5+/-1.0 4.6+/-0.5 SA-WWA-3El (C) 06-29-92
<1.2 8.7+/-1.1 8.3+/-0.8 SA-WWA-2S3 07-27-92
<1.2 4.7+/-0.9 4.3+/-0.4 SA-WWA-3El (C) 07-27-92
<1.0 10+/-1 9.3+/-0.9 SA-WWA-2S3 08-24-92
<1.4 2.8+/-0.8 3.0+/-0.3 SA-WWA-3El (C) 08-24-92
<1.5 10+/-1 9.5+/-1.0 SA-WWA-2S3 09-29-92
<3.3 3.7+/-0.8 2.9+/-0.3 SA-WWA-3El (C) 09-29-92
<3.5 10+/-1 9.4+/-0.9 SA-WWA-2S3 10-26-92
<1.2 2.7+/-0.8 3.2+/-0.3 SA-WWA-3El (C) 10-26-92
<1.4 10+/-1 12+/-1 SA-WWA-2S3 11-23-92
<1.2 3.3+/-0.9 10+/-1 SA-WWA-3El (C) 11-23-92
<1.5
- 8. 8+/-1. 2 16+/-2 SA-WWA-2SJ 12-29-92
<0.8 2.7+/-0.8 3.2+/-0.3 SA-WWA-3El (C) 12-29-92
<0.8 10+/-1 21+/-2 AvERAGE SA-WWA-2S3 4.1+/-3.5 4.6+/-4.7 SA-WWA-3El (C) 10+/-1.4 10.8+/-8.0 GRAND AVERAGE 7.0+/-6.5 7.7+/-9.0 (C) Control Station 98 TRITIUM
<150
<150
<150
<160
<190
<180
<170
<170
<150
<150
'<140
- 210+/-90
<160
<170
<160
<160
<130
<130
<140
<140
<140
<140
<130
<130
TABLE C-12 1992 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS** IN WELL WATER Results in Units of pCi/L +/- 2 sigma SAMPLING
<---- GAMMA EMITTERS ---->
STATION ID DATE I-131*
K-40 Ra-226 SA-WWA-2S3 01-27-92
<0.2
<18 32+/-5 SA-WWA-3El (C) 01-27-92
<0.2
<16 180+/-6 SA-WWA-2S3 02-24-92
<0.3
<20
<2.9 SA-WWA-3El (C) 02-24-92
<0.1
<19
<2.4.
SA-WWA-2S3 03-31-92
<0.3 58+/-16 18+/-3 SA-WWA-3El (C) 03-31-92
<0.2
<15 98+/-5 SA-WWA-2S3 04-28-92
<0.2
<19 45+/-4 SA-WWA-3El (C) 04-27-92
<0.3
<28 160+/-7 SA-WWA-2S3 05~26-92
<0.3
<21 24+/-37 SA-WWA-3El (C) 05-26-92
<0.3
<27 69+/-6 SA-WWA-2S3 06-29-92
<0.1
<22 13+/-2 SA-WWA-3El (C) 06-29-92
<0.2 75+/-25 120+/-5 SA-WWA-2S3 07-27-92
<0.8
<4.5 2.2+/-0.5 SA-WWA-3El (C) 07-27-92
<0.2 55+/-18 40+/-4 SA-WWA-2S3 08-24-92
<0.2 48+/-16
<2.2
- sA-WWA-3El (C) 08-24-92
<0.2 69+/-23 93+/-6 sA~wwA-2S3 09-29-92
<0.5
<15 13+/-2 SA-WWA-3El (C) 09-29-92
<0.2
<75 11+/-7 SA-WWA-2S3 10-26-92
<0.2
<36 12+/-3 SA-WWA-3El (C) 10-26-92
<0.4
<18 160+/-6 SA-WWA-2S3 11-23-92
<0.4 52+/-21 9.9+/-2.8 SA-WWA-3El (C) 11-23-92
<0.1
<19 160+/-7 SA-WWA-2S3 12-29-92
<0.3
<15 8.7+/-2.0 SA-WWA-3El (C) 12-29-92
<0.4
<16 70+/-4 AVERAGE SA-WWA-2S3 15+/-26 SA-WWA-3El (C) 97+/-121 GRAND AVERAGE 56+/-120
- Iodine-131 analyzed to a sensitivity of 1.0 pCi/liter.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
(C) Control Station 99
TABLE C-13 1992-CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90*
IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L
<-- STRONTIUM -"'."">
STATION ID SAMPLING PERIOD Sr-89 Sr-90 SA-WWA-283 01/27/92 to 03/31/92
<0.6
<0.5 SA-WWA-3El (C) 01/27/92 to 03/31/92
<0.5
<0.4 SA-WWA-283 04/28/92 to 06/29/92
<0.6
<0.5 SA-WWA-3El (C) 04/28/92 to 06/29/92
<0.5
<0.4 SA-WWA-283 07/27/92 to 09/29/92
<0.5
<0.4 SA-WWA-3El (C) 07/27/92 to 09/29/92
<0.5
<0.5 SA-WWA-283 10/26/92 to 12/29/92
<0.6
. <0~ 4 SA-WWA-3El (C) 10/26/92 to 12/29/92.
<0.6
<0.4
- Strontium results are corrected for decay to stop date of collection period.
(C) Control station 100
TABLE C-14 1992 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3 SAMPLING GROSS GROSS TYPE PERIOD ALPHA BETA K-40 TRITIUM Raw 01/01-31/92
<1.5 3 *. 7+/-0.9 2.3+/-0.2 180+/-90 Treated 01/01-31/92
<1.3 3.5+/-0.8 2.1+/-0.2
<150 Raw 02/01-29/92 1.4+/-0.9 3.4+/-0.8 1.2+/-0.1
<190 Treated 02/01-29/92
<1.0 2.7+/-0.8
- 1. 0+/-0.1
- <190 Raw 03/01-31/92
<1.0 3.2+/-0.8
- 1. 8+/-0.2
<180 Treated 03/01-31/92
<1.0 3.0+/-0.8
- 1. 8+/-0.2
<180 Raw 04/01-30/92
<1.4 2.9+/-0.8
- 1. 8+/-0.2
<150 Treated 04/01-30/92.
<1.3 2.2+/-0.7
- 1. 8+/-0.2
<150 Raw 05/01-31/92
<1.3 4.0+/-0.8
- 1. 9+/-0. 2 320+/-90 Treated 05/01-31/92
<1.4 2.4+/-0.7
- 1. 9+/-0. 2
<130 Raw 06/01-30/92
<1.1 2.2+/-0.7 1.8+/-0.2
<170 Treated 06/01-30/92
<1.0 1.7+/-0~7 1.7+/-0.2
<160 Raw 07/01-31/92 1.1+/-0. 9 2.5+/-0.7 1.3+/-0.1
<160 Treated 07/01-31/92 1.9+/-1.1 2.3+/-0.7 1.4+/-0.1
<160 Raw 08/01-31/92
<1.4 2.6+/-0.8 1.4+/-0.1 270+/-100 Treated 08/01-31/92
<1.4 1.9+/-0. 7
- 1. 5+/-0. 2 230+/-90 Raw 09/01-30/92
<3.6 4.0+/-0.8
- 1. 6+/-0. 2
<130 Treated 09/01-30/92
<3.3 2.8+/-0.7
- 1. 6+/-0.2
<150 Raw 10/01-31/92
<1.3 3.1+/-0.8 1.6+/-0.2 220+/-90 Treated 10/01-31/92
<1.2 2.3+/-0.8 1.8+/-0.2
<150 Raw 11/01-30/92
<L2 3.5+/-0.9 2.9+/-0.3
<140 Treated 11/01-30/92
<1.1 2.6+/-0.8 2.8+/-0.3
<140 Raw 12/01-31/92
<0.8 4.9+/-0.9 3.3+/-0.3
<120 Treated 12/01-31/92
<0.8 3.8+/-0.8 3.2+/-0.3
<120 AVERAGE Raw 3.3+/-1.5 1.9+/-1.3 Treated
- 2. 6+/-1.2 1.9+/-1.2 GRAND AVERAGE 3.0+/-1.5 1.9+/-1.2 101
. TABLE C-15 1992 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**
IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3 SAMPLING
<------ GAMMA EMITTERS ----->
TYPE PERIOD I-131 K-40 Ra-226 Raw 01/1-31/92
<0.4
<22
<3.1 Treated 01/1-31/92
<0.3
<20
<2.4 Raw 02/1-29/92
<0.5
<40
<1.8 Treated 02/1-29/92
<0.7
<18
<8.8 Raw 03/1-31/92
<0.2
<19
<3.6 Treated 03/1-31/92
<0.2 58+/-24
<3.3 Raw 04/1-30/92
<0.3
<55
<3.9 Treated 04/1-30/92
<0.4
<60
<4.6 Raw 05/1-31/92
<0.3 65+/-18
<9.4 Treated 05/1-31/92
<0.2
<52
<4.7 Raw 06/1-30/92
<0.2
<7.8
<2.3 Treated 06/1-30/92
<0.2 57+/-14
<1.9 Raw 07/1.:...31/92
<0.4
<15
<2.9 Treated 07/1-31/92
<0.4 57+/-15
<4.8 Raw 08/1-31/92
<0.2 50+/-18.
<7.2 Treated 08/1-31/92
<0.2
<14
<2.0 Raw 09/1-30/92
<0.3
<43
<2.6 Treated 09/1-30/92
<0.3
<38
<2.6 Raw 10/1-31/92
<0.4
<42 7.9+/-2.6 Treated 10/1-31/92
<0.4
<39
<3.1 Raw 11/1-30/92
<0.3 58+/-17
<2.8 Treated 11/1-30/92
<0.2
<15
<1.6 Raw 12/1-31/92
<0.3
<21
<6.5 Treated 12/1-31/92
<0.6 39+/-14
<2.0
- Iodine-131 analyzed to a sensitivity of 1.0 pCi/liter.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
102
TABLE C-16 1992 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90* IN QUARTERLY COMPOSITES OF RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma STATION ID: SA-PWR/T-2F3
<-- STRONTIUM -->
TYPE SAMPLING PERIOD Sr-89 Sr-90 Raw 01-:01-92 to 03-31-92
<0.6
<0.5 Treated 01-01-92 to 03-31-92
<0.6
<0.5 Raw 04-01-92 to 06-30-92
<1.1
<0.9 Treated 04-01-92 to 06-30-92
<0.7
<0.6 Raw 07-01-92 to 09-30-92
<0.5
<0.5 Treated 07-01-92 to 09-30-92
<0.5
<0.,5 Raw 10-01-92 to 12-31-92
<0.8
<0.6 Treated 10-01-92 to 12-31-92
<0.7
<0.6
- Strontium results are corrected for decay to stop date of collection period
- 103
TABLE C-17.
1992 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING
<-- GAMMA STATION ID DATE SAMPLE TYPE K-40 SA-FPV-3E3 OS-04-92 Asparagus 2S00+/-2SO SA-FPV-2G2 (C)
OS-11-92 Asparagus 2200+/-260 AVERAGE 23S0+/-420 SA-FPL-2F4 07-28-92 Cabbage 3900+/-310 SA-FPL-3H5 (C) 07-27-92 Cabbage 3100+/-260 SA-FPL-5F3 07-27-92 Cabbage 5600+/-460 SA-FPL-14F3 08-10-92 Cabbage 2600+/-230 AVERAGE 3800+/-2630 SA-FPV-2F4 07-28-92 Corn 2500+/-210 SA-FPV-14F3 07-27-92 corn 2100+/-160 SA-FPV-lGl (C) 08-04-92 Corn 2400+/-210 SA-FPV-3H5 (C) 07-27-92 Corn 2900+/-230 SA-FPY-3El 08-04-92 Corn 2800+/-220 AVERAGE 2S40+/-640 SA-FPV-3E3 08-10-92 Peppers 1500+/-160 SA-FPV-14F3 08-04-92 Peppers 1700+/-210 SA-FPV-3H5 (C) 07-27-92 Peppers 3700+/-480 SA-FPV-2F4 07-28-92 Peppers 1800+/-220 AVERAGE 2175+/-20SO SA-FPV-2F4 07-28-92 Tomatoes 2700+/-200 SA-FPV-14F3 07-27-92 Tomatoes 4600+/-380 SA-FPV-lGl (C) 08-04-92 Tomatoes 1700+/-130 SA-FPV-3H5 (C) 07-27-92 Tomatoes 2000+/-150 AVERAGE 2750+/-2600 GRAND AVERAGE 2750+/-2120
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
104 EMITTERS -->
Be-7
<34
<SS 360+/-94
<73
<340
<33
<32
<13
<36
<43
<14
<41
<22
<100
<24
<46
<39
<17
<34
TABLE C-18 1992 CONCENTRATIONS OF GAMMA EMITTERS* IN BEEF** AND GAME Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING
<-- GAMMA EMITTERS -->
STATION ID DATE SAMPLE TYPE K-40 Ra-226 SA-GAM-11D1 02-20-92 Muskrat 2200+/-200
<22 (Control)
SA-GAM-3El 02-20-92 Muskrat 2400+/-170
<16 AVERAGE Muskrat 2300+/-283
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
- Although not required by Technical Specifications, beef
- samples are normally collected twice each year.
However, due to uncertain availability of the sample, no beef samples were obtained in 1992
- 105
TABLE C-19 1992 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma SAMPLING STATION ID DATE SA-VGT-2F7 09-02-92 SA-VGT-14F4 09-15-92 SA-VGT-3Gl (C) 09-15-92 SA-VGT-2F7 10-05-92 AVERAGE SA-VGT-11F3 11-09-92 SA-VGT-3El 10-26-92 SA-VGT-2F7 11-21-92 SA-VGT-3Gl (C) 11-21-92 SA-VGT-14F4 10-20-92 AVERAGE SAMPLE TYPE Corn Silage Corn Silage Corn Silage Silage Soybeans Soybeans Soybeans Soybeans Soybeans
<---- GAMMA EMITTERS ---->
Be-7 K-40 680+/-160 640+/-150 520+/-160 700+/-190 635+/-161
<68
<120
<70
<46
<52 4600+/-410 3400+/-360 4100+/-400 4800+/-480 4225+/-1248 14000+/-530 13000+/-510 14000+/-570 12000+/-380 15000+/-420 13600+/-2280
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
(C) Control Station 106
TABLE C-20 1992 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SOIL Results in Units of pci/kg (dry) +/- 2 sigma SAMPLING
<------------ GAMMA EMITTERS ------------>
STATION ID DATE Sr-90 K-40 Cs-137 Ra-226 Th-232 SA-SOL-681 07-15-92
<17 10000+/-330 110+/-14 480+/-35 660+/-60 SA-SOL-lODl 07-14-92 66+/-12 8800+/-280 470+/-18 920+/-37 890+/-58
(
SA-SOL-16El 07-14-92 46+/-11 13000+/-410 200+/-22 1100+/-43 1200+/-85 SA-SOL-lFl 07-15-92 92+/-11 4600+/-180 1400+/-24 430+/-25 410+/-37 SA-SOL-2F4 07-15-92 38+/-9 7100+/-240 330+/-15 740+/-31 660+/-50 I-'
SA-SOL-2F7 07-15-92 55+/-10 9300+/-380 270+/-20 1000+/-42 940+/-82 0
-....J SA-SOL-5Fl 07-15-92 190+/-19 7600+/-280 870+/-30 780+/-32 760+/-53 SA-SOL-11F3 07-14-92 53+/-12 12000+/-390 170+/-17 1200+/-47 1200+/-92 SA-SOL-14F4 07-14-92 54+/-12 14000+/-440 360+/-21 1200+/-48 1200+/-78 SA-SOL-3Gl (C) 07-14-92 26+/-9 9000+/-360 200+/-19 980+/-64 840+/-68 AVERAGE 64+/-98 9540+/-5702 438+/-803 883+/-546 876+/-535-
- All other gamma emitters searched for were <LLD; typical LLDs are given in '!'able C-28.
( C) Control station
TABLE C-21 1992 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma
<----------------------------------- STATION ID -------------------------->
SAMPLING SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-12-92
<2.3
<2.1
<2.3
<2.0
<2.3 02-11-92
<1.9
<1.8
<1.9
<1.9
<1.8 03-14-92
<1.4 2.2+/-1.3
<1.4
<1. 5
- 1. 5+/-1. 2 04-09-92
<1. 6
<1.5
<1. 6
<1.6
<1.4 05-11-92
<2.0
<2.0
<2.0
<1.9
<2.0 1--'
0 06-15-92
<1.3
<1.2
- 1. 4+/-1. l
<1.2
<1.2 00 07-14-92
<1.3
<1.3
<1.3
<1.2
<1.2 08-06-92
<2.8
<2.2
<2.5
<2.7
<2.0 09-12-92 1.3+/-1. l
- 1. 3+/-1.0
- 1. 8+/-1. 5
<1.1
- 1. 6+/-1. l
- 1. 4+/-0. 6 10-08-92
<3.4
<3.8
<3.3
<2.6
<2.7 11-15-92
- 1. 6+/-1.2
- 1. 5+/-1. l
<1.3
<1.2
<1.3 12-15-92
<1.3
<1.6
<1.4
<2.0
<1.4
TABLE C-22 1992 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma
<----------------------------------- STATION ID -------------------------->
SAMPLING SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE DATE (Control) 01-12-92 79+/-9 76+/-8 100+/-11 69+/-8 43+/-6 73+/-41 02-11-92 84+/-10 77+/-9 88+/-10 40+/-6 42+/-6 66+/-47 03-14-92 38+/-5 45+/-6 75+/-9 31+/-5 32+/-5 44+/-36 04-09-92 62+/-7 42+/-6 100+/-10 20+/-4 33+/-5 51+/-62 05-11-92 43+/-6 28+/-5 62+/-8 13+/-3 18+/-4 33+/-40 t-*
0 06-15-92 41+/-6 27+/-4 53+/-6 15+/-3 14+/-3 30+/-34
\\Cl 07-14-92 76+/-8 59+/-7 58+/-7 45+/-6 36+/-5 55+/-30 08-06-92 69+/-8 53+/-7 89+/-9 37+/-5 32+/-5 56+/-47 09-12-92 64+/-8 51+/-7 95+/-10 36+/-6 52+/-7 60+/-44 10-08-92 110+/-11 97+/-10 140+/-14 62+/-7 76+/-8 97+/-61 11-15-92 37+/-5 41+/-6 66+/-8 21+/-4 26+/-4 38+/-35 12-15-92 69+/-7 58+/-7 96+/-10 22+/-4 52+/-6 59+/-54 AVERAGE 64+/-44 55+/-41 85+/-48 34+/-36 38+/-34 GRAND AVERAGE 55+/-54
TABLE C-23 1992 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**
IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma SAMPLING
<---- GAMMA EMITTERS ---->
STATION ID DATE I-131 K-40 Ra-226 Th-232 SA-SWA-llAl 01/12/92
<0.2 120+/-21
<7.3
<10 SA-SWA-12Cl (C) 01/12/92
<0.3 120+/-33
<3.8
<9.6 SA-SWA-7El 01/12/92
<0.3 100+/-25
<3.0
<4.8 SA-SWA-1F2 01/12/92
<0.7 73+/-17
<2.2
<7.5 SA-SWA-16Fl 01/12/92
.<0.1 49+/-9
<9.3
<4.3 SA-SWA-llAl 02/11/92
- <o.4 140+/-36
<3.2
<12 SA-SWA-12Cl (C) 02/11/92
<0.3
<25
<2A
<4.9 SA-SWA-7El 02/11/92
<0.3 94+/-20
<1. 7
<2.9 SA-SWA-1F2 02/11/92
<0.6 46+/-8
<2.0
<2.8 SA-SWA-16Fl 02/11/92
<0.2 78+/-19
<2.0
<2.9 SA-SWA-llAl 03/14/92
<0.3 92+/-26
<3.0
<3.1 SA-SWA-12Cl (C) 03/14/92
<0.3 120+/-29
<2.9
<5.0 SA-SWA-7El 03/14/92
<0.2 140+/-29
<5.5
<5.6 SA-SWA-1F2 03/14/92
<0.4 46+/-11 69+/-4
<10 SA-SWA-16Fl 03/14/92
<0.3 87+/-24
<2.8
<3.9 SA-SWA-llAl 04/09/92
<0.3 48+/-10
<1. 7
<3.4 SA-SWA-12Cl (C) 04/09/92
<0.4 92+/-24
<6.0
<5.8 SA-SWA-7El 04/09/92
<0.2 86+/-27
<2.4
<4.3 SA-SWA-1F2 04/09/92
<0.5 56+/-24
<2.6
<9.6 SA-SWA-16Fl 04/09/92
<0.3
<33
<2.7
<8.2 SA-SWA-llAl 05/11/92
<0.4 89+/-23
<5.2
<2.6 SA-SWA-12Cl (C) 05/11/92
<0.1 83+/-27 25+/-3
<12 SA-SWA-7El 05/11/92
<0.3 50+/-9
<1.9
<7.0 SA-SWA-1F2 05/11/92
<0.5 59+/-19
<2.1
<4.4 SA-SWA-16Fl 05/11/92
<0.2 47+/-19 6.8+/-2.2
<9.4 SA-SWA-llAl 06/15/92
<0.2 86+/-14
<1.9
<3.8 SA-SWA-12Cl (C) 06/15/92
<0.4
<22
<2.6
<8.0 SA-SWA-7El 06/15/92
<0.4 110+/-1.9
<2.3
<3.9 SA-SWA-1F2 06/15/92
<0.6 62+/-15
<0.8
<5.4 SA-SWA-16Fl 06/15/?2
<0.5
<19
<5.2
<5.2 SA-SWA-llAl 07/14/92
<0.3 130+/-24 7.3+/-2.4 7.5+/-3.7 SA-SWA-12Cl (C) 07/14/92
<0.3 30+/-8
<3.9
<4.8 SA-SWA-7El 07/14/92
<0.3 150+/-24
<4.9
<2.3 SA-SWA-1F2 07/14/92
<0.3 110+/-19
<6.6
<10 SA-SWA-16Fl 07/14/92
<0.3 66+/-14
<1.7
<5.9 110
SAMPLING STATION ID SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl SA-SWA-11Al SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl SA-SWA-11Al SA;...SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl SA-SWA-11Al SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl SA-SWA-11Al SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE TABLE C-23 (Cont'd) 1992 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS**
IN SURFACE WATER Results in Units-of pCi/L +/- 2 sigma
<---- GAMMA EMITTERS --~->
DATE I-131 K-40 Ra-226 Th-232 08/06/9'2
<0.3 110+/-19
<5.1
<7.2 (C) 08/06/92
<0.5 87+/-17
<1. 7
<3.5 08/06/92
<0.2 98+/-22
<2.8
<8.8 08/06/92
<0.4 80+/-19
<2.3
<3.7 08/06/92
<0.2 57+/-2_3
<4.8
<7.8 09/12/92
-( 1) 350+/-37
<2.8
<11 (C) 09/12/92
( 1) 88+/-16
<L4
<7.2 09/12/92 (1) 130+/-20
<2.0
<4.2 09/12/92
( 1) -
190+/-32
<2.8
<9.8 09/12/92 (1)
<23
<6.3
<4.0 10/08/92 (1)
<19
<2.0
<3.4 (C) 10/08/92 (1) 130+/-22
<5.8
<9.0 10/08/92 (1) 140+/-41
<3.1
<5.7 10/08/92 (1) 68+/-25
<2.8
<5.7 10/08/92 (1) 120+/ <2.5
<2.2 11/15/92 (1) 83+/-26
<2.2
<11 (C) 11/15/92 (1)
<16
<2.2
<6.9 11/15/92 (1)
<25 12+/-3
<8.1 11/15/92 (1) 62+/-19 23+/-3
<6.0 11/15/92 (1)
<38
<4.2
<8.6 12/15/92 (1) 68+/-27
<4.9
<5.9 (C) 12/15/92 (1) 100+/-22
<4.4
<11 12/15/92 (1) 140+/-23
<2.0
<9.8 12/15/92 (1) 86+/-20
<2.2
<8.6 12/15/92 (1)
<38
<1.8
<7.7 85+/-105
- Iodine-131 results are corrected for decay to endpoint of collection period.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
(C) Control Station (1) Implementation of Tech. Spec. change; Amendment #133 for Salem Unit #1 and Amendment #112 for Salem Unit #2.
No high sensitivity analysis for I 131 required
- 111
Table C-24 1992 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L +/- 2 sigma
<----------------------------------- STATION ID -------------------------->
SAMPLING SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl AVERAGE PERIOD (Control) 01-12-92 to
<190 210+/-110
<180
<180
<190 03-14-92.
04-09-92 to
<150 200+/-90
<130
<130
<160 06-15-92 07-14-92 I-'
to
<150
<150
<150 240+/-90
<140 I-'
09-12-92 10-08-92 to
<130
<130
<140 180+/-80
<130 12-15-92 AVERAGE
1-*
1-*
(.,'
TABLE C-25 1992 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90*, TRITIUM AND GAMMA EMITTERS** IN EDIBLE FISH STATION ID SA-ESF-llAl SA-ESF-12Cl (C)
SA-ESF-7El AVERAGE SA-ESF-llAl SA-ESF-12Cl ( c)
SA-ESF-7El AVERAGE GRAND AVERAGE Results in Units of pCi/kg (wet) +/- 2 sigma (Except for strontium in bone analyses which are reported in pCi/kg (dry))
SAMPLING PERIOD 05/19-27/92 05/19-27/92 05/19-27/92 10/07-08/92 10/07-08/92 10/07-10/92 STRONTIUM
<--- BONES --->
<~--- FLESH--->
<51 210+/-18
<22
<15
<70 420+/-26
<21
<15
<49 260+/-18
<25
<16 297+/-219
<25
<16
<57
<33
<35
<24
<44
<25
<57
<34
<38
<22 297+/-219 TRITIUM (FLESH)
<-GAMMA EMITTERS (FLESH)->
AQUEOUS FRACTION K-40
<300 3100+/-250
<280 2900+/-200
<300 3300+/-220 3100+/-400
<80 3700+/-260
<60 3600+/-240
<90 3300+/-180 3533+/-416 3317+/-599
- 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-28.
- Tritium results until 6/01/92 are by Controls for Environmental Pollution, Inc. After that date, results are reported by Teledyne Isotopes, Inc.
(C) Control Station
I-'
I-'
.p-.
TABLE C-26 1992 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90*, TRITIUM AND GAMMA EMITTERS** IN BLUE CRABS Results in Units of pCi/kg (wet) +/- 2 sigma (Except for strontium in shell analyses which are repor~ed in pci/kg (dry))
<----------- STRONTIUM ---------->
SAMPLING
<--- FLESH --->
<--- SHELL --->
TRITIUM (FLESH)
STATION ID DATE Sr-89 sr-90 Sr-89 Sr-90 AQUEOUS FRACTION SA-ECH-llAl 07/27/92
<25
<18
<23 88+/-9
<300 SA-ECH-12Cl (C) 07/27/92
<19
<14
<24 93+/-10
<300 AVERAGE 91+/-5 SA-ECH-llAl
- 10/08/92
<36
<20
<37 110+/-13
<100 SA-ECH-12Cl (C) 10/08/92
<32
<18
<82
<51
<100 AVERAGE GRAND AVERAGE 97+/-23
- 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-28.
- Tritium results by Teledyne Isotopes, Inc.
(C) Control Station GAMMA EMITTER K-40 3100+/-200 3200+/-230 3150+/-100 3200+/-240 2900+/-190 3050+/-300 3100+/-283 (FLESH)
TABLE C-27 1992 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SEDIMENT Results in Units of pCi/kg (dry) +/- 2 sigma SAMPLING
<----------------------------- GAMMA EMITTERS ----------------------------->
STATION ID DATE Sr-90 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 SA-ESS-llAl 6/15/92
<26 9700+/-400
<20 57+/-20 88+/-38
<15 100+/-24 580+/-41 700+/-80 SA-ESS-15Al 6/15/92
<22 6900+/-220 21+/-8 120+/-12
<9.1 30+/-10
<10 440+/-26 470+/-41 SA-ESS-16Al 6/15/92 44+/-12 6800+/-380 48+/-17 120+/-26 92+/-34 80+/-23
<13 1800+/-56 1600+/-99 SA-ESS-12Cl (C) 6/15/92
<24 16000+/-460
<36
<13
<14 54+/-15
<17 620+/-40' 850+/-71 SA-ESS-7El 6/15/92
<20 13000+/-410
<8.4
<9.7
<57 51+/-i8 39+/-14 760+/-41 760+/-76 SA-ESS-16Fl 6/15/92
<28 17000+/-510
<23
<16
<42
<7.3
<12 630+/-42 933+/-86 AVERAGE 11567+/-8909 40+/-54 805+/-996 886+/-768 SA-ESS-llAl 11/18/92
<22 2700+/-170
<17 58+/-11 36+/-12
<6.7
<4.2 150+/-17 180+/-33 t-' SA-ESS-15Al 11/18/92
<21 3800+/-220
<5.8 38+/-10 32+/-12 36+/-14
<4.1 420+/-28 520+/-44 t-' SA-ESS-16Al 11/18/92
<24 3700+/-250 28+/-12 43+/-17
<15 37+/-15
<10 380+/-28 620+/-56 V1 SA-ESS-12Cl (C) 11/18/92
<24 14000+/-34
<16
<8.2
<9.2 61+/-14
<11 680+/-30 830+/-58 SA-ESS-7El 11/15/92
<22 11000+/-320
<19
<6.2
<11
<12
<27 700+/-43 690+/-58 SA-ESS-16Fl 11/15/92
<26 18000+/-520
<7.0
<14
<16 67+/-25
<10 600+/-49 980+/-90 AVERAGE 8867+/-12797 37+/-49 488+/-424 637+/-552 GRAND AVERAGE 10217+/-10884 38+/-50 647+/-801 761+/-688
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-28.
(C) Control Station
SAMPLE TYPE:
ACTIVITY:
GEOMETRY:
COUNT TIME:
DELAY TO COUNT:
NUCLIDES BE-7 NA-22 K-40 CR-51 MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 ZRNB-95 M0-99 RU-103 RU-106 AG*100m SB-125 TE-129m 1-131 TE-132 BA-133 CS-134 CS-136 CS-137 BA-140 LA-140 BALA-140 CE-141 CE-144 RA-226 TH-232 TABLE C-28 1992 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY
<------------AIR------------>
<-------WATER------->
IOOINE PARTICULATES GAMMA SCAN IODINE 10-3 pCi/m 3
10-3 pCi/m3 pCi.(L pCi/L 100 ML 13 FILTERS 3.5 LITER 100 ML 120 MINS 1000 MINS 100 MINS 1000 MINS 2 DAYS 5 DAYS 7 DAYS 3 DAYS 6.8 15 0.45 11 7.1 35 2.9 16 0.32 1.7 0.33 1.6 0.79 3.7 0.36 2.1 0.69 3.9 0.49 0.44 3
550 200 0.33 1.6 2.9 14 0.55 2.0 0.77' 4.0 120 62 13.0 0.98 3.8 0.60 41 13 3.7 0.39 1.8 0.56 2.9 0.28 1.6 2.2 15 0.31 2.3 1.1 9.2 0.87 7.4 1.2 7.1 116
<-------MILK-------->
GAMMA SCAN IODINE pCi/L pCi/L 3.5 LITER 100 ML 500 MINS 1000 MINS 2 DAYS 2 DAYS 22 4.5 120 22 3.4 2.9 7.2 4.0 8.6 3.1 5.7 41 2.5 28 3.4 8.2 99 3.2 0.42 3.9 3.0 3.3 3.2 15 3.9 17 6.6 12
TABLE C-28 (cont't) 1992 PSE&G RESEARCH & TESTING LABORATORY LLDs FOR GAMMA SPECTROMETRY 117
APPENDIX D SYNOPSES OF ANALYTICAL PROCEDURES 11 a
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by the PSE&G Research and Testing Laboratory and contract laboratories for analyzing the 1992 Artificial Island Radiological Environmental Monitoring Program samples.
LAB*
PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G CEP TI PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G PSE&G
.PSE&G TABLE OF CONTENTS PROCEDURE DESCRIPTION PAGE GROSS ALPHA Analysis of Air Particulates......*.*.*...*..**..*.
123 Analysis of Water...................................
12 5 GROSS BETA Analysis of Air Particulates..*...........*...*....
126
_ Analysis of Water..................................
128 POTASSIUM-40 Analysis of Water..................................
129 TRITIUM Analysis of Water...................................
13 o Analysis of Aqueous Fraction of Fish and Crab.*****
131 Analysis of Aqueous Fraction of Biological Material 132 IODINE-131 Analysis of Filtered Air *******..*******.****.*****
133 Analysis of Raw Milk.. ~............................
13 4 Analysis of Water..................................
135 STRONTIUM-89 AND STRONTIUM-90 Analysis of Air Particulates.****.*.....*.*.**.**.*
136 Analysis of Raw Milk...............................
139 Analysis of Water..................................
142 Analysis of Vegetation, Meat and Aquatic Samples *.*
145 Analysis of Bone and Shell....*******..****.*.**.**
148 Analysis of Soil and Sediment *.**.*..*.**.****.**.*
151 Analysis of Samples for Stable Strontium.*.**.*****
154 121
LAB*
PSE&G PSE&G PSE&G PSE&G SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd)
TABLE OF CONTENTS PROCEDURE DESCRIPTION PAGE GAMMA SPECTROMETRY
.Analysis of Air Particulates.......................
156 Analysis of Raw Milk...............................
157 Analysis of Water..................................
158 Analysis of Solids (combined procedures)........*..
159 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters.....**....
160
- PSE&G - PSE&G Research and Testing Laboratory CEP
- Controls for Environmental Pollution, Inc.
TI
- Teledyne Isotopes 122
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low back-ground gas proportional counter.
Along with a set of air particulate samples, a clean air filter is included as a blank with an Am-241 air filter geometry alpha counting standard.
The specific alpha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.
Calculation of Gross Alpha Activity:
Air flow is corrected first by using the following equations:
p = (B-V)/29.92 p = Pressure correction factor B = Time-averaged barometric pressure during sampling period, "Hg v = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°F, "Hg v = F*P*0.946*0.0283 E
F = Uncorrected air flow, ft3 0.946 = Temperature correction factor from 609F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %
efficiency/100) v = Corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows:
Result (pCi/m3) =
(G-B)/T (2.22)*(E)*(V)
G = Sample gross counts B = Background counts (from blank filter)
T = Count time of sample and blank, mins.
E = Fractional Am-241 counting efficiency V = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 123
2-sigma error (pCi/m3) = (1.96*(G+B)1/2)*A (G-B)
Calculation of lower limit of detection:
A = Gross aipha activity, pCi/m+3 G =Sample-gross counts B = Background counts (from blank filter)
A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.
LLD(pCi/m3) =
4.66 * (B)1/2 (2.22)*(E)*(V)*(T) 124 B =
E =
v =
T =
Background counts (from blank filter)
Fractional Am-241 counting efficiency Corrected air flow of sample, m3 Count time of blank, mins.
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS ALPHA ANALYSia OF WATER SAMPLES Water samples require pretreatment of all suspended material for the purpose of keeping the final sample thickness to a minimum.
This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample filtrate.
The combined sample is then neutralized with dilute ammonium hydroxide.
From this point, both sample and blank are acidified with dilute sulfuric acid.
Barium carrier is added and the sample is heated to S0°c in order to help precipitate barium sulfate.
Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced.
After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroxide to.precipitate ferric hydroxide.
The mixed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted on a stainless steel planchet.
The sample is then alpha-counted for the appropriate time on a low background gas proportional counter, along with a U-238 source of the same.
geometry.
The blank is treated in the same manner as the sample.
Calculation of Gross Alpha Activity:
Result (pCi/L) =
(G-B)/T (2.22)*(E)*(V)*(S)
G B
T E
v s
=
=
=
=
=
=
Sample gross counts Background counts (from blank sample)
Count time of sample and blank Fractional counting efficiency from U-238 source Sample volume, liters Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm p~r pCi 2-sigma error (pCi/L) = (l.96*(G+B)1/2)*A (G-B) 125 A = Gross alpha activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low back-ground gas proportional counter.
Along with a set of air particulate samples, a clean air filter is included as a blank with an Sr-90 air filter geometry beta counting standard.
The gross beta activity is computed on the basis of total corrected air flow sampled during the collection period.
This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.
Calculation of Gross Beta Activity:
Air flow is corrected first by using the following equations:
P = (B-V)/29.92 V = F*P*0.946*0.0283 E
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 F = Uncorrected air flow, ft3 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %
efficiency/100)
V = Corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows:
Result (pCi/m3) =
(G-B)/T (2.22)*(E)*(V)
G = Sample gross counts B = Background counts (from blank filter)
T = Count time of sample and blank, mine.
E = Fractional Sr-90 counting efficiency V = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 126
2-sigma error (pCi/m3) = (1.96*(G+B)1/2)*A (G-B)
Calculation of lower limit of detection:
A = Gross beta activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter)
A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.
LLD(pCi/m3) =
4.66 * (B)1/2 (2.22)*(E)*(V)*(T) 127 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.
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly.
Then, a 1.0 liter* portion is removed from the potable, rain or well water container and 250ml taken from each surface water.
A deionized water blank is prepared for each different volume of sample (e.g.
1.0 liter blank for 1.0 liter samples and 250ml for 250ml samples).
All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml.
At that point, the samples and blanks are transferred to tared stainless steel ribbed planchets and evaporated to dryness under an infrared heat lamp.
They are subsequently cooled in a desiccator, weighed and counted on a low background gas proportional counter along with an Sr-90 source of the same geometry*.
Calculation of Gross Beta Activity:
Result (pCi/L) =
(G-B)/T (2.22)*(E)*V)*(S)
G B
T E
v s
=
=
=
=
=
=
Sample gross counts Background counts (from blank sample)
Count time of sample and blank Fractional counting efficiency from Sr-90 source Sample volume, liters Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = (l.96*(G+B)1/2)*A (G-B) 128 A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR POTASSIUM 40 A 60 ml aliquot of water is acidified to pH <2 with concentrated nitric acid and then analyzed for potassium by the following Atomic Absorption Spectrophotometry method: potassium standards of known concentrations (similar to that of the samples) are first prepared.
An aliquot of each sample and standard is pipetted into stoppered erlenmeyer flasks.
In addition, a duplicate sample, water blank and a quality control sample are likewise pipetted into their respective flasks.
A solution consisting of 1%
sodium is added to all flasks to achieve a minimum of 2,000mg/L of sodium in the final sample volume.
The spectrophotometer generates the calibration curve based upon standard absorbance and' sample absorbance is c.onverted 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 const*ant for converting ppm to pCi/L c = Potassium concentration, ppm 129
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum.
Eight ml of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting.
An internal standard is prepared by mixing Sml of sample, lOml of Instagel, and O.lml~0.2ml of a standard with known activity.
The efficiency is determined from this.
Also prepared is a blank consisting of Bml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination.
This is done for each pair of samples to be counted.
Activity is computed as follows:
A (pCi/L) =
(G-B)*(lOOO) 2.22*(E)*(V)*(T)
Efficiency (E) is computed as follows:
E = (N)*(D)
A' N is determined as follows:
N = C-(G/T)
A = Activity B = Background count of sample G = Gross count of sample E
Counting Efficiency v = Aliquot volume (ml)
T = count time (min) 2.22 = DPM/pCi 1000 = Number of ml per L N = Net CPM of spiked sample D = Decay factor of spike A' = DPM of spike c = CPM of spiked sample G = Gross counts of sample T = Count time (min)
The associated error is expressed at 95% confidence limit, as follows:
1.96*(G/T2+B/T2)1/2*(1000) 2.22*(V)*(E)
Samples are designated LLD if the activity is less than the following value:
LLD (pCi/L) =. (4.66)*(B)1/2*(1000) 2.22*(V)*(E)*(T) 130
SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL POLLUTION, INC., PROCEDURE T~ITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliquot of fish or crab flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation.
Three milliliters of the extracted water i~ then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear Corporat 1ion).
The resultant mixture is comprised of 19 percent sample in a clear gel-type aquasol and provides a triti~ counting efficiency of approximately 30 percent, when counted on a Beckman LS-100 Liquid Scintillation Spectrometer.
The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted.
The counting efficiency is-determined from these standards which are equal in activity but vary in the amount of quenching.
All samples are counted for 500 minutes each
- 131
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE TRITIPM*ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS A weighed aliquot of fish or crab flesh is placed in a suitable flask or container having a connection to a vacuum system.
Water is. removed from the sample by vacuum distillation.
Three or ten milliliters (depending on the total yolume of water distilled) are added to a scintillating cocktail to a total of 20 milliliters.
The resultant mixture is counted in a Packard automatic sample changing liquid scintillator for at least 100 minutes.
The efficiency of the counting system is determined.with a tritium standard traceable to NIST. *A quench correction to the counting efficiency is automatically applied to the results.
The calculation of the tritium activity is related to the original, equivalent weight of the sample in units of pCi/g (wet).
132
\\
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-irnpregnated 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-sigrna error and LLD:
Result (pCi/m3) =
N*D
= R (2.22)*(E)*(A)*(T)*(V)
N = Net counts under photopeak D = Decay correction factor tl t2 A
E A
T v
2.22 2-sigrna error (pCi/m3) = 1.96*(GC+Bc)1/2*R N
=
=
=
=
=
=
Atl*EXP(At2) 1-EXP(-Atl)
Acquisition live time Elapsed time from sample collection to start of acquisition 0.693/nuclide half life Detector efficiency Gamma abundance factor (no. of photons per disintegration)
Acquisition live time, mins.
Sample volume, m3 No. of dpm per pCi GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/m3) =
4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 133
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF RAW MILK FOR IODINE-131 Stable iodine carrier is equilibrated in a 4-liter volume of raw milk before two separate Sdml batches of anion exchange resin are introduced to extract iodine.
After each batch has been stirred in the milk for an appropriate time, both are then transferred to an aluminum sample can where the resins
- are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick.
The can is hermetically sealed and then counted on a gamma detector.
Calculation of I-131 Activity:
Result (pCi/L) =
N*D
= R (2.22)*(E)*(A)*(T)*(V) 2-sigma error (pCi/L)
N = Net counts under photopeak D =-Decay correction factor
>..tl*EXP(>..t2) 1-EXP(->..tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition
>.. = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no.
photons per disintegration)
T = Acquisition live time, mins.
V = Sample volume, L 2.22 = No. of dpm per pCi 1.96*(GC+BC)1/2*R N
GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/L) =
4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 134 of
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF WATER FOR IODINE-131 Stable iodine carrier is equilibrated with Sodium Bisulf ite in a 4-liter volume of water, and then filtered, before two separate SOml batches of anion exchange resin are introduced to extract iodine. After each batch has been stirred in the water for an appropriate time, both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick.
The can is hermetically sealed and then counted on a gamma
- detector.
Calculation of I-131 Activity:
Result (pCi/L)
N*D
= R (2.22)*(E)*(A)*(T)*(V)
N = Net counts under photopeak D
tl t2
).
E A
T v
2.22 2-sigma error (pCi/L) = 1.96*(GC+BC)1/2*R N
=
=
=
=
=
=
=
=
=
Decay correction factor
).tl*EXP().t2) 1-EXP(-).tl)
Acquisition live time Elapsed time from sample collection to start of acquisition 0.693/nuclide half life Detector efficiency Gamma abundance factor (no.
photons per.disintegration)
Acquisition live time, mins.
Sample volume, L No. of dpm per pCi GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/L) =
4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 135 of
SYNOPSIS OF PSE&G RESEARCH.AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF AIR FILTERS The air filters are placed in a small beaker and just enough *fuming nitric acid is added to cover the filters.
A blank, composed of the same number of clean air filters, is prepared in the same way.
Stable strontium carrier is then introduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media.
Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out.
Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip.
The strontium is precipitated as a carbonate, which is dried and weighed.
The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later.
The basis for this two count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous *equations to solve for them.
Calculation of Sr-90 Activity:
Sr-90 Results (pCi/m3) =
N4/R where S6 (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
= W2 A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas. proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' =Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to-Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = Sr-90 counting standard efficiency V =Sample quantity (m3) u = Chemical yield N4 = (N2 -
Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) ~ (1 + Rl*Il)*Fl)
I1 = 1 -
EXP ((-0.693/2.667.)*tl)
I2 1 -
EXP ((-0.693/2.667)*t2) tl Elapsed time from Y-90 strip to first count 136
t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff;y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
N2 = X -
Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/m3) =
[
2* (X+Y) +
w12 (Xl+Yl)*Fl~ 1 /2 w12 J (Wl*W2)
(N2-Fl*Nl)
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/m3) =
'4.66* (X+Y) + (Xl+Yl)*Fl2 1/2
[
W12 w12 Calculation of Sr-89 Activity:
Sr-89 Results (pCi/m3) =
N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 = Nl -
N7*(1,+ Rl*Ir)
N7 = (N2 -
Fl*Nl)/Wl (This represents counts due to Sr-90) 137
E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to 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 *
(S82+s92)~
~~
(Xl+Yl)*Fl~, 1 1 2 w12
_j S9 = (Xl+Yl) 11 2 (Nl - N7*(l+Rl*Il))
All other variables are as previously defined.
Keeping the same variable definitions, the LLD for Sr-89 (pCi/m3) =
4.66*(S82+s92)1/2 138
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF RAW MILK Stable strontium carrier is first introduced into a milk sample and into a distilled water sample of equal volume to be used as a blank.
The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations.
These cations are then eluted off with a TRIS-buffered 4N sodium chloride solution into a beaker and precipitated as carbonates.
The carbonates are converted to nitrates with 6N nitric acid and, by acidifying further to an overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium.
Barium chromate precipitation is then performed to remove any traces of radium and radiobarium.
Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precip-itation.
Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip.
The strontium is precipitated as its carbonate, filtered, dried and weighed to determine strontium recovery.
The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later.
The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of Sr-90 Activity:
Sr-90 Results (pCi/L) =
N4/R (2.22)*(E)*(E(lS)fE')*(S6)*(V)*(U)
= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particuiar gas proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = Sr-90 counting standard efficiency V = Sample quantity (liters)
U = Chemical yield N4 = (N2 -.Fl*Nl)/Wl =net counts* due to Sr-90 only Wl = ((1 + Rl*I2) ~ (1 + Rl*Il)*Fl)
Il = 1 -
EXP ((-0.693/2.667)*tl) 139
I2 1 -
EXP ((-0.693/2.667)*t2) tl =Elapsed time from Y-90 strip to first.count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
N2 = X -
Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
R = Count time of sample and blank Using the same variable definitions as above,
'the 2-sigma error for Sr-90 (pCi/L) =
~* (X+Y) + (Xl+Yl)*Fl~l1/2 * (Wl*W2)
~ w12 w12
~
(N2-Fl*Nl)
Again, keeping the same variable definitions, the"LLD for Sr-90 (pCi/L) =
r;..66* (X+Y) + (Xl+Yl)*Fa 1/2 L w12 w12 J 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) 140
E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is.run with each group of environmental strontium samples)
F9 EXP ((-0.693/50.S)*t) t Elapsed time from midpoint of collection period to time of recount for milk samples only.
For all other samples, this represents the elapsed time from sample stop date to time of recount.
50.5 = Half-life of Sr-89, days All other quantities are as previously defined.
The 2-sigma error for Sr-89 (pCi/L) = 2* (S82+s92)1/2
- W3 (Nl - N7*(l+Rl*Il))
SS =liX+Y) + (Xl+Yl)*Fl2 /2
~w12 w12 59 = (Xl+Yl) 1/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for Sr-89 (pCi/L) =
4.66*(582+592)1/2 141
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank.
The sample(s) and blank are then made alkaline and heated to near boiling before precipitating the carbonates.
The carbonates are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium.
Radioactive interferences are stripped out by coprecipita-tion on ferric hydroxide (yttrium strip) followed by a barium chromate strip.
The strontium is precipitated as a carbonate before being dried and weighed.
The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later.
The basis for this two count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
Since surface waters, as well.as some drinking water samples, have been found to contain significant amounts of_ stable strontium, a separate aliquot from each sample is analyzed for stable strontium.
These results are used in correcting the chemical recovery of strontium to its true value.
Calculation of *sr-90 Activity:
Sr-90 Results (pCi/L) =
N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
= W2 where 56 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter,_ where A, Band Care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2
. E(lS)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = Sr-90 counting standard efficiency V = Sample quantity (liters) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) -
(1 + Rl*Il)*Fl)
Il = i EXP ((-0.693/2.667)*tl) 142
I2 = 1 -
EXP ((-0.693/2.667)*t2) tl =. Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
N2 = X -
Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 No. of dpm per pCi Fl= EXP ((-0.693/2.667)**t2)
R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/L)
~* (X+Y) + (Xl+Yl)*Fl~1/2
- L w12 w12 J (Wl*W2)
(N2-Fl*Nl)
Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) =
r;:.66* (X+Y) + (Xl+Yl)*Fl~1/2
-L w12 w12 I
Calculation of Sr-89 Activity:
sr-89 Results (pCi/L) =
N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 87 = 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) 143
E(l5)/E' = Ratio of Sr-89 efficiency at thickness value of 15mg/cm~+2~- to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
F9 =EXP ((-0.693/50.5)*t) t Elapsed time from midpoint of collection period to time of recount for milk samples only.
For all other samples, this represents the elapsed time from sample stop date to time of recount.
50.5 = Half-life of Sr-89, days All other quantities are as previously defined.
The 2-sigma error for Sr-89 (pCi/L) = 2* (582+592) 1 /2 *. W3 (Nl - N7*(l+Rl*Il))
SB =l~x+Y) + (Xl+Yl) *Fa 1 /2.
Lw12 w12 J S9 = (Xl+Y1)1/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for Sr-89 (pCi/L) =
4.66*(S82+s92)1/2 144
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT, CRAB SHELL AND AQUATIC SAMPLES The samples are weighed (recorded as."wet" weight) as received, before being placed in an oven to dry at 100°C.
At the completion of the drying period, samples are again weighed (recorded as "dry" weight) and then pulverize_d.
A measured amount (quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed in a muffle furnace.
The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 900°C for 1/2 hour.
After removal from the furnace, the melt is cooled, pulverized and added to SOOml distilled water and heated to near boiling for 30 minutes, with stirring.
The ~ample is filtered (filtrate discarded) and the carbonates on the filter dissolved with 1:1 nitric acid (HNo3).
The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming HNo3.
After calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroxide followed by coprecipitation on barium chromate.
The strontium is precipitated as its carbonate, which is dried and weighed.
The samples are then counted on a low background gas proportional counter and, again, at least 14 days later.
The basis *for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of Sr-90 Activity:
Sr-90 Results (pCi/kg wet) =
N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = Sr-90 counting standard efficiency V = Sample quantity (kg wet) u = Chemical yield N4 = (N2 Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) -
(1 + Rl*Il)*Fl) 145
I1 = 1 -
EXP ((-0.693/2.667)*tl)
I2 = 1 -
EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff 'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
N2 = X -
Y, where X and Y are recount gross counts and background counts, respectiyely Nl = Xl -
Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.6?7)*t2)
R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/kg wet) =
~* (X+Y) + (Xl+Yl)*Fl~1/2 * (Wl*W2)
\\~ w12 w12
~
(N2-Fl*Nl)
Again, keeping the same variable definitions, the LLD for sr-90 (pCi/kg wet) =
r.;..66* (X+Y) + (Xl+Yl)*Fa ~/2 L w12 w12 J Calculation of Sr-89 Activity:
Sr-89 Results (pCi/kg wet) =
NG/R (2.22)*(E)*(E(l5)fE')*(S7)*(V)*(U)*(F9)
= W3 S7 G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
NG = Nl -
N7*(1 + Rl*Il) 146
N7 = (N2 - Fl*Nl)/Wl (Thi~ represents counts due to Sr-90)
E(15)/E' Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
F9 =EXP ((-0.693/50.5)*t) t Elapsed time from midpoint of collection period to time of recount for milk samples only.
For all other samples, this represents the elapsed time from sample stop date to time of recount.
50.5 = Half-life of Sr-89, days All other quantities are as previously defined.
The 2-sigma error for Sr-89 (pCi/kg wet) = 2* (S82+s92) 1/2
- W3 (Nl -
N7*(l+Rl*Il))
SS =~X+Y) + (Xl+Yl) *Fa 1 /2 Lw12 w12 J 59 = (Xl+Yl)1/2 All other variables are as previously def1ned.
Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg wet) =
4.66*(S82+s92)1/2 147
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE The bone or shell is first physically separated from the rest of the sample before being broken. up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample.
After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized.
An aliquot of the sample is removed, weighed and ashed in a muffle furnace.
Then, in the presence of strontium carrier and cesium holdback carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered.
The sample is then treated with concentrated (70%) nitric acid and boiled until strontium nitrate crystallizes out.
The strontium nitrate is freed of calcium by repeated fuming nitric acid recrystallizations.
From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide followed by coprecipitation with barium chromate.
The strontium is precipitated as strontium carbonate, which is dried, weighed, then beta-counted on a.low background gas proportional counter.
A second ~aunt is performed at least 14 days later.
The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of sr-90 Activity:
Sr-90 Results (pCi/kg dry) =
N4/R (2.22)*(E)*(E(lS)fE')*(S6)*(V)*(U)
= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of Sr-90 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = Sr-90 counting standard efficiency V = Sample quantity (kg dry)
U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only 148
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 t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
N2 = X -
Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl -.Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pci Fl= EXP ((-0.693/2.667)*t2)
R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/kg dry) =
1~ (X+Y) + (Xl+Yl) *F~ 112 *
(Wl*W2)
[
w12 w12 -,
(N2-Fl*Nl)
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kg dry) =
r;66* (X+Y) + (Xl+Yl)*Fl~ 1/2 L w12 w12
_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 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.)
149
N6 = Nl - N7*(1 + Rl*Il)
N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90)
E(l5)/E' = Ratio of sr-89 efficiency at thickness value of 15mg/cm~+2~- to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of envi~onmental 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)
SS =~X+Y) + (Xl+Yl)*Fl~1/2
[w12 w12 -,.
S9 ~ (Xl+Yl) 112
- 2* css2+s92)112
- w3 (Nl - N7*(l+Rl*Il))
All other variables are as previously defined.
Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg dry) =
4.66*(S82+s92)1/2 150
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 con-taining only 1/3 - liter concentrated HCl and Sml strontium carrier is run in parallel with the sample.
.The samples are stirred vigorously for at least 30 minutes and then filtered.
The filtrate is then diluted to a known volume and aliquots removed for stable strontium.
The remaining sample is alkalinized with ammonium hydroxide to precipitate all the transitional elements.
After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontium and calcium carbonate.
These carbonates are first filtered and then digested with 6N HNo3.
Two fuming (90%) HNo3 recrystallizations are then performed. to remove calcium.
Subsequently, radioactive impurities are removed by two precipitation steps, using ferric hydroxide and barium chromate as carriers.
The strontium is precipitated as strontium carbonate before being dried and weighed.
The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.).
There is a second count at least 14 days later.
The basis for this two-count method is that Sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them
- Calculation of Sr-90 Activity:
Sr-90 Results (pCi/kg dry) =
N4/R (2.22)*(E)*{E(l5)/E')*(S6)*(V)*(U)
= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band Care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E' = 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 count.a due to Sr-90 only Wl = ((1 + Rl*I2) -
(1 + Rl*Il) *Fl) 151
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 c.ount t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
N2 = X -
Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (pCi/kg dry) =
G* cx+Y> + cx1+Yl)*F~ 112 *
(Wl*W2)
~ w12 w12
~
(N2-Fl*Nl)
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kg dry) = *
~.66* (X+Y) + (Xl+Yl)*F~\\112
\\-
w12 w12 J Calculation of Sr-89 Activity:
sr-89 Results (pCi/kg dry) =
N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized Sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
NG = Nl - N7*(1 + Rl*Il) 152
N7 = (N2 -
Fl*Nl)/Wl (This represents counts due to Sr-90)
E(l5)/E' Ratio of Sr-89 efficiency at thickness value of 15mg/cm2 to Sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
F9 =EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only.
For all other samples, this represents the elapsed time from sample stop date to time of recount.
50.5 = Half-life of Sr-89, days All other quantities are as previously defined.
The 2-sigma error for Sr-89 (pCi/kg dry) = 2* (582+592)1/2
- W3 (Nl - N7*(l+Rl*Il))
58 ~~X+Y) + (Xl+Yl)*F~1/2
~w12 w12
~
S9 = (Xl+Y1)1/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for Sr-89 (pCi/kg dry) =
4.66*(S82+s92)1/2 153
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Chemical/Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes.
In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element of interest.
The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask.
Bone and shell are prepared by ashing 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask.
All the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium.
The sample, spiked samples and blank absorbance are determined by Atomic Absorption Spectroscopy (AAS) and are plotted graphically.
The true sample concentrations are then extrapolated from this graph.
Chemical and ionization interferences are controlled by the addition of 0."1% or more of lanthanum to all samples.
For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH
<2 with hydrochloric or Nitric acid and analyzed by AAS or AES as follows: A series of strontium standards (of similar concentration to the unknowns) is prepared.
Then, to 9 ml of each prepared sample, blank and standard, is added 1 ml of lanthanum to achieve a minimum of 0.1% lanthanum in' all solutions.
All results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.
Sample Calculation of Corrected Chemical Recovery of Strontium in Soil and Sediment:
Reported concentration of stable strontium (mg/L):l19 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 0.025 154
Net weight of srco3 precipitate (mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (125mg) x (.5935) = 74.2 Corrected chemical recovery of strontium =
74.2 = 0.623 119.0 The calculations follow the same sequence for bone and shell samples.
Sample Calculation of Corrected Chemical Recovery of Strontium in Water:
Reported concentrations of stable strontium (mg/L): 1.65 Volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample (l.65mg/L) x (2.0L) 3.30mg Quantity of strontium carrier added to sample (mg): 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of Srco3 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935) = 17.2mg Corrected chemical recovery of stro~tium = 17.2mg =.738 23.3mg 155
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 actfvi'ty, 2-sigma error and LLD:
Result (pCi/m3)
N*D
= R (2.22)*(E)*(A)*(T)*(V)
N =Net counts.under photopeak D = Decay correction factor
>.tl*EXP(At2.)
1-EXP(->.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition
>. = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = Acquisition live time, mins.
V = Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3) = 1.96*(GC+BC)1/2*R N
GC = Gross counts BC = Background count.s All other variables are as defined earlier.
The LLD (pCi/m3) =
4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 156
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF RAW MILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker.
The sample is brought to ambient temperature and then counted on a gamma detector.
Calculation of Gamma Activity:
The following are the calculations performed for the gamma activity, 2-sigma error and LLD=*
Result (pCi/L) =
N*D
= R (2.22)*(E)*(A)*(T)*(V)
N = Net counts* under photopeak D = Decay correction factor tl t2
).
E A
T v
2.22 2-sigma error (pCi/L) = 1.96*(GC+BC)1/2*R N
=
=
=
=
=
=
=
=
). tl*EXP(>.t2) 1-EXP(->.tl)
Acquisition live time Elapsed time from sample collec-tion to start of acquisition 0.693/nuclide half life Detector efficiency Gamma abundance factor (no. of photons per disintegration)
Acquisition live time, mins.
Sample volume, liters.
No. of dpm per pCi GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/L) =
4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 157
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated Marinelli beaker and then counted on a gamma detector.
Calculation of Gamma Activity:
The following are the calculations performed for the gamma activity, 2-sigma error and LLD:
Result (pCi/L)
N*D
= R (2.22)*(E)*(A)*(T)*(V)
N = Net counts under photopeak D = Decay correction factor tl t2 A
E A
T v
2.22 2-sigma error (pCi/L) = 1.96*(GC+BC)1/2*R N
=
=
=
=
=
=
=
Atl*EXP(At2) 1-:-EXP (-Atl)
Acquisition live time Elapsed time from sample collec-tion to start of acquisition 0~693/nuclide half life Detector efficiency Gamma abundance factor (no. of photons per disintegration)
Acquisition live time, mins.
Sample volume, liters No. of dpm per pci GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/L) =
4.66*(BC)1/2*D (2.22)*(E)*(A)*(T)*(V) 158
SYNOPSIS OF PSE&G RESEARCH AND TESTING LABORATORY PROCEDURE GAMMA ANALYSIS OF SOLIDS Several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required.
For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight.
A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm3), when possible, in a tared aluminum can.
The can is weighed, hermetically sealed and counted.
In most cases, a wet sample is prepared (when a lower sensitivity is acceptable) by either grinding/chopping the wet sample or by using a food processor to puree it. The sample is poured into a calibrated, tared clear plastic container, aluminum can, or marinelli beaker until a standard volume is reached for that container.
The sample is weighed, sealed, and counted.
Soil and sediment samples are first oven dried until a constant weight is achieved and then pulverized.
The sample is added to a tared aluminum can, compacted to a standard volume and weighed. It is hermetically sealed, cured for 30 days to allow for ingrowth, and counted.
Calculation of Gamma Activity:
The following are the calculations performed for the gamma activity, 2-sigma error and LLD:
Result (pCi/kg) =
N*D
= R (2.22)*(E)*(A)*(T)*(V)
N = Net counts under photopeak D = Decay correction factor Atl*EXP (.At2) l..;.EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = Acquisition live time, mins.
V = Sample volume, kilograms 2.22 = No. of dpm per pCi 2-sigma error (pCi/kg) = 1.96*(GC+BC)1/2*R N
GC Gross counts BC Background counts All other variables are as defined earlier.
The LLD (pCi/kg) =
4.66*(BC)1/2*D (2.22}*(E)*(A)*(T)*(V) 159
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE
~ALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso4 :Dy phosphor.
They are first annealed in a 2S0°c oven prior to exposure in the field.
Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader.
The dosimeter is then re-irradiated by a standardized Cs-137 source and the four areas are read again.
Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter.
The readings of control dosimeters are subtracted to allow for transit dose and system back-ground.
The results are computed as follows:
For any given area of the dosimeter, the dose in mR is calculated by the following formula:
DOSE = R * (REDOSE/RR)-AVC R = Initial reading of the area RR Second reading of the area (after re-irradiation)
REDOSE = Re-irradiation dose, mR AVC = Average of control values, mR where AVC 4N
~CDOSE/4N i=l N = Total number of control dosi-meters CDOSE = CR*(CREDOSE/CRR)
CDOSE = Control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation)
CREDOSE = Re-irradiation dose of the control dosimeter, mR 160
APPENDIX E
SUMMARY
OF USEPA
. ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 161
APPENDIX E
SUMMARY
OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a.summary of the analytical results for the 1992 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program.
TABLE NO.
E-1 TABLE OF CONTENTS TABLE DESCRIPTION Gross Alpha and Gross Beta Emitters in Water and Air Particulates.................................
PAGE 164 E-2 Gamma Emitters in Milk, Water, Air Particulates E-3 E-4 E-5 and Food Products........ *....... *................
16 5 Tritium in Water.................................
Iodine in Water.................................
Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products *.*..............*..
163 166 167 168
TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM DATE MM-YY 01-92 03..:..92 04-92 08-92 09-92 10-92 Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter)
PSE&G ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d.
EPA-WAT-AB339 Water Alpha 29+/-0.8 Beta 31+/-1.2 EPA-APT-GABS343 APT Beta 40+/-0.9 EPA-WAT-P344 Water Beta 126+/-2.1 EPA-APT-GABS351 APT Alpha 60+/-1.4 Beta 67+/-0.5 EPA-WAT-AB353 Water Alpha 36+/-2.1 Beta 42+/-1.6 EPA-WAT-P357 water Alpha 30+/-2.0 Beta 49+/-1.2 EPA Known 30+/-8 30+/-5 41+/-5 140+/-21 30+/-8 69+/-10 45+/-11 50+/-5 29+/-7.0 53+/-10
- s.d. -
one standard deviation of three* individual analytical results
- known value plus or minus one sigma as reported by EPA 164
TABLE E-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM DATE MM-YY 02-92 03-92 04-92 04-92 06-92 08-92 09-92 10-92 10-92 Gamma Analysis of Milk, Water (pCi/L) and Air Particulate (pCi/filter)
ENV SAMPLE CODE MEDIUM EPA-WAT-G340 Water EPA-APT-GABS343 APT EPA-WAT-P344 Water EPA-MLK-GS345 Milk EPA-WAT-G348 Water EPA-APT-GABS351 APT EPA-MLK-GS354 MLK EPA-WAT-G355 Water EPA-WAT-P357 Water ANALYSIS Ba-133 Co-60 Zn-65 Ru-106 Cs-134 cs-137 Cs-137 Cs-134 Cs-137 Co-60 Cs-137 K(l)
I-131 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 Cs-137.
Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 Co-60 cs-134 Cs-137 PSE&G Mean +/- s.d.
88+/-2.8 41+/-2.0 146+/-2.5 213+/-9.1 30+/-0.7 50+/-0.4 13+/-0.5
. 26+/-1. 6 24+/-0.5 56+/-0.5 39+/-0.9 1563+/-25 76+/-2.8 21+/-0.8 105+/-1.2 140+/-0.9 97+/-2.6 16+/-0.9 17+/-0.5 21+/-0.5 108+/-2.4 18+/-0.0 1780+/-8.2 13+/-0.0 155+/-0.5*
170+/-1.9 10+/-0.0 10+/-0.9 73+/-1.9 15+/-0.3 6.3+/-0.3 8.7+/-0.4 (1) Reported as mg/l of Potassium EPA Known 76+/-8 40+/-5 148+/-15 203+/-20 31+/-5 49+/-5 10+/-5 24+/-5 22+/-5 56+/-5 39+/-5 1710+/-86 78+/-8 20+/-5 99+/-10 141+/-14 15+/-5 15+/-5 98+/-10 18+/-5 100+/-10 15+/-5 1750+/-88 10+/-5 148+/-15 175+/-18 8.0+/-5.0 8.0+/-5.0 74+/-7 15+/-5.0 5+/-5.0 8+/-5.0
- s.d. -
one standard deviation of three individual analytical results
- known value plus or minus one sigma as reported by EPA 165
TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM DATE MM-YY 02-92 06-92 10-92 Tritium Analysis of Water (pCi/L)
ENV SAMPLE CODE MEDIUM ANALYSIS EPA-WAT-H344 Water H-3 EPA-WAT-H349 Water H-3 EPA-WAT-H356 Water H-3 PSE&G Mean +/- s.d.
8127+/-52 2043+/-17 5887+/-20
- EPA Known 7904+/-790 2125+/-347 5962+/-596
- s.d. -
one standard deviation of three individual analytical results
- known value plus or minus one sigma as reported by EPA 166
TABLE E-4 USEPA ENVIRONMENTAL.RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM DATE MM-YY 02-92 08-92 Iodine Analysis of Water (pCi/L)
ENV SAMPLE CODE MEDIUM ANALYSIS EPA-WAT-I341 Water I-131 EPA-WAT-I350 Water I-131 PSE&G Mean +/- s.d.
60+/-1.2 49+/-5.1 EPA Known 59+/-6.0 45+/-6.0.
- s.d. -
one standard deviation of three individual analytical results
- known valu~ plus or minus one sigma as reported by EPA 167
TABLE E-5 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter),
Milk (pCi/L) and Water (pCi/L)
DATE PSE&G EPA MM-YY ENV SAMPLE CODE MEDIUM ANALYSIS Mean +/- s.d.
Known 01-92 EPA-WAT-S338 Water Sr-89 56+/-2.4 51+/-5.0 Sr-90 20+/-0.9 20+/-5.0 03-92 EPA-APT-GABS343 APT Sr-9Q 14+/-0.5 15+/-5.0 04-92 EPA-WAT-P344 Water sr-89 16+/-0.5 15+/-5.0 Sr-90.
16+/-0.5 17+/-5.0 04-92 EPA-MLK-GS345 Milk Sr-89.
38+/-4.2 38+/-5.0 Sr-90 24+/-1.2 29+/-5.0 05-92 EPA-WAT-S346 water Sr-89 31+/-0.9 29+/-5.0 Sr-90
~.7+/-0.5 8.0+/-5.0 08-92 EPA-WAT-GABS351 APT Sr-90 22+/-1.4 25+/-5 09-92 EPA-WAT-S352 water Sr-89 21+/-1.2 20+/-5.0 Sr-90 14+/-0.8 15+/-5.0 09-92 EPA-MLK-GS354 Milk Sr-89 14+/-1. 6 15+/-5.0 Sr-90 14+/-1.2 15+/-5.0 10-92 EPA-WAT-P357 water Sr-89 15+/-0.5 8+/-5.0 sz.:-90 19+/-0.9 10+/-5.0
- s.d. - one standard deviation of three individual analytical results
- known value plus or minus one sigma as reported by EPA 168
APPENDIX F.
SYNOPSIS OF LAND USE CENSUS 169
APPENDIX F SYNOPSIS OF 1992 LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal~ the nearest residence, and the nearest garden of greater than 50m (500ft2) producing broad leaf vegetation, in each of the 16 meteorological sectors.
Tabulated below are the results of these surveys:
Milk Nearest Vegetable Animal Residence Garden Meteorological Sept.,. 1992 Sept., 1992 Sept., 1992 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 171