ML20043B633
| ML20043B633 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1989 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005310029 | |
| Download: ML20043B633 (202) | |
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.W , 4 OPU Nuclear Corporation- -j Nuc'le' ar m.on:r388 Forked River, New Jersey 08731 0388 -
609 971 4000 ' Writer's Direct Dit) Number:
,a May 11, 1990 ,
i; U.S. . Nuclear Regulatory Commission-
;Attnt- . Document Control Desk L ~ Washington, DC 20555
Dear Sir:
A .n h- ' Subjects Oyster Creek Nuclear Generating Station l Docket No. 50-219 . Radiological. Environmental Monitoring Program ~ (REMP) Report. I 1 Enclosed is a copy of_the Oyster Creek REMP report for 1989.. This submittal is made j in accordance with Technical Specification 6.9.1.e. J If there are any questions regarding this matter, please call Mr. Michael Heller, . Licensing.Engineerj-at (609) 971-4680. y gruly yours,/ A 1 C' I E. :. 'itzpatrick ' l: e resident and' Director i Oyster Creek
, ?EEF/MHzje Enclosure r cc Chief Bureau of Nuclear Engineering
'NJ Department;of Environmental Protection CN 411 y Trenton, NJ 08625 l Regional Administrator i
_ Region 1 L' l ;. U . S ~. Nuclear-Regulatory Commission l .. 475 Allendale Road , ! . King of Prussia, PA 10406 i NRC Resident Inspector Oyster Creek - 9005310029 891231 p PDR ADOCI. 05000219 R PDC GPU Nuclear Corporation is a subsidiary of General Public Utihties Corporation , s .
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p < e 0 ' ' OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey The 650 MWplant is a single unit, five-loop General
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Electric Boiling Water Reactor (BWR). The site, about 800 acres, is in Lacey and Ocean Townships of Ocean County. Located approximately nine miles south of Toms River, it is about 50 miles east of Philadelphia, and 60 miles south of Newark. Construction began in December 1963. The station began commercialcperation on December 23,1969, and at that time was the largest nuclear facility in the United States solely financed by a private company. The Reactor Building, Turbine Building and Ventilation Stack are the most prominent structures at the site. The Reactor Building stands approxi-mately 150 feet high with 42 feet extending below grade. The Reactor Building serves as a secondary containment and houses the primary containment (drywell), the reactor vessel E and its auxiliary systems which comprise the Nuclear Steam Supply System. The drywell, E: which houses the reactor vessel, is constructed of high density reinforced concrete with an inner steelliner measuring 120 feet high and 70 feelin diameter. gi The reactor vesselis 63 feet high and iB feet in diameter. E The 652 ton reactor contains 560 fuelassemblies, each with 62 fuel rods that are 12 feet long, and 137 control rods. The reactor operates at a nominalpressure of 1,020 pounds per square inch and an average temperature of 540 degrees Fahrenheit. The Turbine Building houses the turbine generator, control l! m room, main condensers, power conversion equipment and auxiliary systems. The turbine-generator consists of one high pressure turbine, three low pressure turbines, a generator ; and an exciter. The turbines and generator tum at 1,800 revolutions per minute to generate three-phase, 60-cycle electricity at 24,000 volts. The electricity generated is provided to the grid by two transformers which boost the voltage to 230,000 volts. Steam is supplied to the high pressure turbine from the {} reactor. After being used to drive the turbines and generator, the steam is condensed in the J main condensers and returned to the reactor vesselin the form of water through the con- l densate and feedwaterpumps. i The main condensers consist of three horizontal, single i pass, divided water boxes containing 44,000 tubes having a totallength of about 1,875,000 i feet. Cooling 'wateris provided from Bamegat Bay, through the South Branch of the Forked .\ River and passes through the condensers and discharges into Oyster Creek for return to Bamegat Bay. The wateris pumped by four 1,000-horsepowerpumps, each of which } moves about 115,000 gallons per minute through the 6 foot diameter pipes that feed the : condensers. .} L The ventilation stack is 368 feet high with 26 feet extend- ! / . ing below grade. The stack provides ventilation for the Reactor Building, Turbine Building > b ,and Radwaste Facilities. Oyster Creek is owned by Jersey Central Power & Light (JCP&L) Company and oper- g atedby GPU Nuclear (GPUN) E< Corporation. JCP&L and 1 GPUN are units of the GPU l, System. n0 ll a
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, -j 1989 (t Radiological Environmental Monitoring Report Prepared By Oyster Creek Environmental Controls
.I,: GPU Nuclear Corporation l
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n y .- i 3 TABLE OF CONTENTS m PAGE 1
-TABLE OF CONTENTS l 1 LIST OF TABLES 111' --
LIST OF FIGURES iv
SUMMARY
AND CONCLUSIONS 1 4 INTRODUCTION 4 ~, 1 Characteristics of Radiatior. 4' Sources of Radiation- 5 i Nuclear Reactor Operations 8' [ Sources: of Liquid and Airborne Ef fluents 12 DESCRIPTION OF THE OYSTER CREEK SITE 14-14
! General Information Climatological. Summary - 1989 .14 l l -EFFLUENTS 18' Y
Historical Background 18-c
~ Effluent Release Limits 19
! Effluent Control Program 22 Effluent Data 23
'4 i 3i RADIOLOGICAL ENVIRONMENTAL MONITORING 27 Environmental Exposure Pathways to Humans from Airborne and Liquid Effluents 27
- I:- Sampling 28 29 i l Analysis Quality Assurance Program. 33 DIRECT RADIATION MONITORING 117 Sample Collection.and Analysis 117 ;
I' Results 118 : 1 ATMOSPHERIC MONITORING 122 L- Sample collection and Analysis 122 Results 123 AQUATIC MONITORING 127 Sample Collection and Analysis 127 , Results 128 I .
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t l TABLE OF CONTENTS .
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ll TERRESTRIAL MONITORING 134 [g- Sample Collection and Analysis 134 I igL Results 135' ] GROUNDWATER' MONITORING '137 ? 3
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- 7 Sample Collection and Analysis 137 l
" -138 Results
- v. 1.
RADIOLOGICAL IMPACT OF OCNGS OPERATIONS '139 Determination of Radiation Doses to the Public 139 1 Results of Dose Calculations 142. . REFERENCES 146
?
APPENDIX A: 1989 REMP Sampling Locations and Description, 149
. Synopsis of REMP, and Sampling and Analysis Exceptions
.I APPENDIX B .1989 Lower Limits of Detection -(LLD) Exceptions 162 ..
APPENDIX C: Changes Effected in the 1989 REMP 164-
' APPENDIX D: 1989 Quality Assurance Results 166 .
f APPENDIX E: '1989 EPA Cross-Check Results 170 l APPENDIX F: L 1989 Annual Dairy Census 173
-I APPENDIX G: ' Dose Calculation Methodology. 175 APPENDIX Hs 1989 Groundwater Monitoring Results 180 APPENDIX It .1989. REMP Sample Collection and Analysis Methods 183 APPENDIX J 1989 TLD Quarterly Data 189 b
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LIST OF TABLES TITLE
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TABLE P89.In ! s
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1~ Sourcee and Doses of Radiation 6'. ~I
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( '2 Radionuclide Composition of OCNGS Effluents for 1989
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. g'. Radiological Environmental Monitoring Program Summary 35 ;
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Oyster: Creek Nuclear Generating Station , j January, 1989 through December, 1989 l 4 Species of Fish Caught as 129
' lW- Part-of.the OCNGS REMP in 1939 ;
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. 3-- 5L Calculated Maximum Hypothatical Domes to- 144 1
,- g an Individual from Liquid and Airborne Effluent Releases from Oyster Creek
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' for 1989
[ 6 Calculated Maximum Total Radiation Doses 145 to the Population from Liquid and Airborne . Effluent from Oyster Creek for 1989 l \ . . . s l
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Is LIST OF FIGURES FIGURE TITLE JAGl1 b I 1 Oyster Creek
- Nuclear Generating Station Simplified Schematic 10 i
17 2 Monthly Precipitation at the Oyster Creek p - Nuclear Generating Station'During 1989 l
.g Cosipared with Historical (1946-1981) Atlantic.
~g City National Weather Service Precipitation Data.
3 -Location of Kadiological Environmental Monitoring 30 Program (REMP) Stations Within.1 Mile of the Site o ; .] 4 Location of Radiological Environmental Monitoring .31 Program-(REMP) Stations Greater than-1 Mile and Within 2 Miles of the Site 15 5 Location of Radiological Environmental Monitoring 32
,l.- Program (REMP) Stations Greater than 2 Miles
- W: From the Site'
!i 6 Mean Teledyne TLD Gamma Dose 1984-1989 119 j I;'~ oyster Creek Radiological Environmental R
l Monitcring. Program - Dose in Millirem per Standard Month
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- W .- 7 Mean Teledyne Isotope TLD Gamma Dose for 1989 120 !
Based on Distance from Reactor. Oyster Creek
- . Radiological Environmental Monitoring Program -
? - Dose;in Millirem per Standard Month L 8 Mean Panasonic TLD Gamma Dose for 1989 Based on 121 1
; h. Distance from Reactor. Oyster Creek Radiological ,
pW Environmental Monitoring Program - Dose in ;j l_ Millirem per Standard Month < 9 Weekly Mean Air Particulate Gross Beta 124 Concentrations. Oyster Creek Radiological ,. . Environmental Monitoring Program - Results in ? Picoeuries per Cubic Meter 10 Air Particulate Gross Beta Concentrations 125 1984-1989, oyster Creek Radiological ;
~
L Environmental Monitoring Program - Results in Picocuries per Cubic Meter 7 11 Cobalt-60 Concentrations.in Clams 1984-1989. 130 1 oyster Creek Radiological Envir'onmental i Monitoring Program - Results in pCi per kg (wet) 5 iv
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LIST OF FIGURES-(Continued)
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d FIGURE TITLE PAfg3 ;
'l 12' ' Cobalt-60 concentration in Aquatic Sediment 131 1 1984-1989. Oyster Creek Radiological j Environmental Monitoring Program - Results.in j
;li- Picoeuries per. Kilogram (Dry).-
13 Cobalt-60 Concentration in Blue Crab 1984-1989. 132
$ Oyster Creek Radiological Environmental Monitoring Program - Results in Picocuries i per Kilogram (Wet)
- I 1
~14 Monthly Mean Cesium-137 Activity in Coll'ards.
Oyster Creek Radiological Environmental 136 1 Monitoring Program Results in Picoeuries- 'l per Kilogram (Wet) 15 Exposure Pathways for. Routinely Released 141
.7 Radionuclides from'the OCNGS .{
-H-1 Locations of On-Site Welle 182 ,
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SUMMARY
AND CONCLUSIONS -l
.The-radiological env ronmental i monitoring performed during 1989 by the GPU Nuclear' Environmental Controls Department at the Oyster Creek Nuclear (
Generating Station (OCNGS) is discussed in this report. The operation of a nuclear power. plant results in the release of small amounts of i l l radioactive materials to the environment. A radiological environmental ' 3L monitoring program (REMP) has been established to monitor radiation and
, m radioactive materials in the environment around the OCNGS.' The program evaluates the relationship between amounts of' radioactive material !I released in effluents to the environment and resultant radiation doses to individuals. Summaries and interpretations of the data were published ,
semiannually from 1969-1985 and annually since 1986 (References 1, 2, and-3). . Additional information concerning releases of radioactive materials
' I:. to the environment is contained in the Semi-Annual Effluent Reports- 3 submitted to the United States Nuclear Regulatory Commission (USNRC). ,
t During 1989, as in previous years, the radioactive liquid and airborne effluents associated with the OCNGS were a small fraction of the applicable federal regulatory limits and did not-have significant or measurable effects on the quality of the environment. Estimated radiation
-W doses to the public attributable to 1989 operations at the OCNGS ranged from less than one percent to a maximum of only 16 percent of the applicable regulatory limits. Furthermore, they were significantly less than doses received from common sources of radiation.
Radioactive materials considered in this report are normally present in the environment, either naturally or as a result of non-OCNGS activities such as prior atmospheric nuclear weapons testing and medical-industry , activities. Consequently, measuremente made in the vicinity of the site (indicator) were compared to background maaeurements to determine any L impact of OCNGS operatiens. Samples of air, precipitation, well water, surface water, clams, sediment, fish, crabs, vegetables, and soil were l collected. External penetrating radiation dose measurements also were
-l made using thermoluminescent dosimeters (TLD's) in the vicinity of the OCNGS. Samples were analyzed for radioactivity including tritium (H-3),
gross beta and gamma-emitting radionuclides. t
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Tne results of_ environmental measurements were.used to assess the environmentai' impact of CCNGS operations, to demonstrate compliance with the Technical Specifications (reference 4') and applicable federal regulations, and to verify the adequacy of containment and radioactive effluent control systems.. The data collected by the REMP provided a ' historical record'of the levels of radionuclides and radiation s f - attributable to natural causes, worldwide fallout from prior nuclear l W weapons tests, and'the OCNGS operations.
.. Radiological impacts in terms of radiation dose as a result of OCNGS 4
operations were calculated and also are discussed. The results provided -
; in this report are summarized in the following highlights.
- o During 1989, over 1,775 samples were taken from the aquatic, e atmospheric, and terrestrial environments around OCNGS. More than 2,500 analyses were performed on these samples. Four a hundred-ninety-one (491) direct radiation dose measurements using thermoluminescent dosimeters (TLDs) also were made. Over ,
eighty-two (82) groundwater samples, including local domestic water supplies, were collected and more than two hundred i forty-five (245) analyses were performed on these samples. )
.'I- .
o In addition to natural radioactivity, trace levels of cesium-137 ; (Cs-137) were detected in various media and were attributed to f fallout from prior nuclear weapon testing and Chernobyl. g-3 o cobalt-60 (Co-60) was detected in nediment samples as a result of OCNGS operations. Although cobalt-60 had been' detected.in clams from the Barnegat Bay system in prior study years, this nuclide. did not appear in clam samples collected during 198S. o The predominant radionuclides released in station effluents were xenon-135 in gases and tritium in liquids. Estimated radiation doses to the public, attributable to these effluents, ranged from
; less than one percent to a maximum of only 16 percent of 4
applicable regulatory limits. u
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d o.. !During 198', 9 the maximum whole body dose potentially received by an individual from liquid and airborne effluents combined was i
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conservatively, calculated to be about 0.522 millirems total.. The q -l whole body dose to the, surrounding population from liquid and airborne effluents was calculated to be"22.30 person-rem.--This is-approximately 45,000. times lower than the dose that the total-i population-in the ocNGS area receives from natural background ' W. sources. t- -h 1 I-I , 1 I . i u e ll; 1 l:: 1, l, l
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INTRODUCTION
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.i; characteristics of Radiation Instability within the nucleus of a radioactive atom results in the
, release of energy in the form of radiation. Radiation is classified ;
according to its nature - particulate and electromagnetic. Particulate i t radiation consists of energetic subatomic particles such as electrons (beta particles), protons, neutrons, and alpha particles. Because af its ! limited ability to penetrate the human body, particulate radiation in the
;- environment contributes primarily to internal radiation exposure resulting >
from inhalation and ingestion of radioactivity. Electromagnetic radiations in the form of x-rays and gamma rays have characteristics similar to visible light but are more energetic and, hence, more penetrating. Although x-rays and gamma rays are penetrating i and can pass through varying thicknesses of materials, once they are absorbed they produce energetic electrons which release their energy in a manner that is identical to beta particles. The principal concern for '
, gamma. radiation from radionuclides in the environment is.their 3 contribution to external radiation exposure. q The rate at which atoms undergo disintegration (radioactive decay) varies
-among radioactive elements, but is uniquely constant for each specific radionuclide. The term " half-life" defines the time it takes for half of ,
'any amount of an element to decay and can vary from a fraction of a second -(
for some radionuclides to millions of years for others. In fact, the
$I natural background radiation to which all mankind has been exposed is largely'due to the radionuclides of uranium, thorium, and. potassium.
These radioactive elements were formed with the creation of the universe and, owing to their long half-lives, will continue to be present for millions of years to come. For example, potassium-40 has a half-life of L, 1.3 billion years and existe naturally within our bodies. As a result approximately 4000 atoms of potassium emit radiation interns 11y within L- each of us every second of our life. .I 1 3 lt
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4sa i 3 s ( q .; In assessing the impact r)f radioactivity on the environment, it is
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important to know the quantity of radiodctivity released and the resultant i radiation doses. The common unit'of radioactivity is the curie. It
= represents the radioactivity-in one gram of natural radium which is also i - J equal to a decay rate of 37 billion radiation emissions every second. -
7 Because of the extremely small amounts of radioactive material'in the r environment, it is more convenient to use fractions of a curie.- Subunits like picoeurie (one trillionth of a curlo) are frequently used to express the radioactivity present in environmental and biological samples.
- I The biological effects of a specific dose of radiation are the same l
I whether the radiation source is external or internal to the body. The
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important factor is how much radiation energy or dose was deposited. The-l_ unit of radiation dose is the rem, which also incorporates the variable
- 'effactiveness of difforent-forms of radiation to produce biological change. For environmental radiation exposures, it is convenient to use
; - the smaller unit of millirem to express dose (1000 millirema equals j' - 1 rem). When radiation exposure occurs over periods of time, it is appropriate to refer to the dose rate. Dose rates,'therefore, define the
= ; total dose for a fixed interval of time and for environmental exposures P. .
are usually measured with reference to one year of time'(millirems per
- year).
L , l--- j Sources-of Radiation )
. Life on earth has evolved amid the constant exposure to natural 1 : radiation; In fact, natural radiation is the single major source to which the general population is exposed. Although everyone on the planet is 3- exposed to natural radiation, some people receive more than others. 5
-1 l Radiation exposure from natural background has three components (i.e., .
cosmic, terrestrial, and internal) and varies with altitude and geographic E location, as well as with living habits.
; l For example, cosmic radiation originating from deep interstellar space and l
-g the sun increases with altitude, since there is less air which acts as a
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shield..--similarly, terrestrial radiation resulting from the presence of. ; naturally occurring radionuclides in the soil varies and_may be significantly higher in some areas of the country than in others.~; Even
-the use of particular. building materials for houses, cooking with gas,.and.
.home insulation affect exposure to natural radiation.
The presence of radioactivity in the human body results from the
-inhalation and ingestion of air, food, and water containing naturally occurring radionuclides. For example, drinking water contains trace
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[ amounts of uranium and radium and milk contains radioactive potassium.
',' Table 1 summarizes-the common sources of radiation and their average I annual doses. '
TABLE 1- ,; (Ref. 5) , Sources and Doses of Radiation
- Natural (82%) Man-made (18%) .j ur Radiation Dose Radiation Dose 7 Source fmillirems/vear) Source (millirems /vear)-
Radon- 200 (55%) cosmic rays 27 (8%) Medical X-rays 39 (11%)' t l Terrestrial 28 (8%) Nuclear Medicine 14 (4%)
' Internal 40 (11%) consumer products 101(3%)
Ll i'. Other <1 (<1%) , (Releases from nat. gas,
-g; phosphate mining, burning 'l 3 of coal, weapons fallout,
& nuclear fuel cycle)
- 1. APPROXIMATE APPROXIMATE f TOTAL 300 TOTAL 63 L- -
- Percentage contribution of the total dose is shown in parentheses. t l The average person in.the United States receives about 300 millireme (0.3 L
m rem) per year from natural background radiation sources. This estimate { was revised from about 100 to 300'millireme because of the inclusion of radon gas which has always been present but has not previously figured in the. calculations. In'some regions of the country, the amount of natural 4 radiation is significantly higher. Residents of colorado, for example, I '
f 56 receive an additional 60 millireme per year due to the increase in, cosmic .
.and terrestrial radiation levels. In fact, for every 100 feet above sea {
1evel, a person will receive an additional 1 millirem per year f rom' cosmic radiation. In several regions of the world, high concentrations of J uranium'and radium deposits result in' doses of several thousand millirems l 5I; each year to their residents (Ref. 6). , i
- Recently, public attention has focused on radon, a naturally occurring 1
radioactive gas produced from uranium and radium decay. These elements l are widely distributed in trace amounts in the earth's crust. Unusually high concentrations have been found in certain parts of eastern .I I Pennsylvania and northern New Jersey. Radon levels in some homes in these-areas are hundreds of times greater than: levels found elsewhere in the United States. However, additional surveys are needed to determine the q E -
; l full extent of the problem nationwide. Radon is the largest component of ,
natural background radiation and may be responsible for a substantial number of' lung cancer deaths annually. The National Council on Radiation
- U Protection and Measurements (NCRP) estimates that the' average individual in the United States receives an. annual dose of about 2,400 millireme to 7
the lung from natural radon gas (Ref.-5). This lung dose is considered to o ; be equivalent to a whole body dose of 200 millirems. The NCRP has J B .. recommended actions to control indoor radon sources and reduce: exposures. When radioactive substances are inheled or swallowed, they are distributed within the body in a nonuniform fashion. For example, radioactive iodine ) selectively concentrates-in the thyroid gland, radioactive cesium-is distributed throughout the body-water and muscles, and radioactive' strontium concentrates in the bones. The total dose to organs by a given P: W! radionuclide is also influenced by the quantity and the duration of time that the radionuclide remains in the body, including its physical, L-l biological and chemical characteristics. Depending on their rate of radioactive decay and biological elimination from the body, some radionuclides stay in the body for very short times while others remain
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- 'In' addition to natural radiation, we are exposed to radiation from a' I number of man-made sources. The single largest of t' hose sources comes !
from diagnostic medical x-rays, and nuclear medicine procedures. -Some 180 l , t million Americans receive medical x-rays each year. The annual-dose to an-individual from such radiation averages about 53 millirems. Much smaller doses come from nuclear weapons fallout and consumer products such as ,
. televisions, smoke detectors, and fertilizers. Production of commercial
- E nuclear power and its associated fuel cycle contributes less than l' ,
millirem to the annual dose of about 300 millireme for the average individual living in the United States. Fallout conunonly refers to the radioactive debris that settles to the 'i surface of the earth following the detonation of nuclear weapons. . It is 5, dispersed throughout the onvironment either by dry deposition or washed W: down to the earth's surface by rain or snow. There are approximately 200. radionuclides produced in the nuclear weapon detonation process; a number $
; of these are detected in fallout. The radionuclides found in fallout -f which produce most of the f allout radiation e:sposures to humans are iddine-131 (I-131), strontium-89 (Sr-89), cesium-137-(Co-137), and ;
strontium-90 (Sr-90). There has been no atmospheric nuclear weapon testing since 1980 and many of the radionuclides have decayed i
'=L significantly, consequently, doses to the public.from fallout have been-l decreasing. -l As a result of.the nuclear accident at chernobyl, USSR, on April 26, 1986, fallout was dispersed throughout the environment and detected in various-media such as air, milk, and soil.
l ((g,q, lear Reactor Ooerations ! Common to the commercial production of electricity is'the consumption of fuel which produces heat to make steam which turns the turbine-generator l which generates electricity. Unlike the burning of coal, oil, or gas in fossil-fuel powered plants to generate heat, the fuel of most nuclears I
; reactors is comprised of the element uranium in the form of uranium 1
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; 1 oxide. Tho' fuel produces power by the process called' fission. In fission the uranium atom absorbs a neutron (an atomic particle found'in nature and also produced by the fissioning of uranium in the reactor) and splits to ,
. produce. smaller atoms termed fission products, along with heat, radiation
?
j and free neutrons. The free neutrons travel through the reactor and are p- -l 1
-j >- . similarly absorbed by the uranium, permitting the fission process to continue. As this process continues, more fission products, radiation, f g heat and neutrons are produced and a sustained reaction occurs. The heat :
produced is transferred - via reactor coolant water - from the fuel to produce steam which drives a turbine-generator to produce electricity. The fission products are mostly radioactive: . thr* is to say they are unstable atoms which emit radiation as they change to stable atoms. Neutrons which are not absorbed by the uranium fuel may be absorbed.by i L stable atoms in the materials which make up the components and structures, of the reactor. In such cases, stable atoms often become radioactive.~
- This process is called activation and the radioactive atoms which result :
3, are called activation products. l The OCNGS reactor is a Boiling Water Reactor (BWR). The nuclear fuel is designed to be contained within sealed fuel rods arranged in arrays called h bundles which are located within a massive steel reactor-vessel. As
.m depicted in Figure 1, cooling water boils within the reactor vessel .
producing steam for use in the turbine. 'After the energy is extracted
> from'the steam in the turbine, it is cooled and condensed back int 6 water in the main condensers. 'This condensate is-then pumped back into the reactor vessel. . Several hundred radionuclides of some 40 different elements are created i W during the process of generating electricity. Because of reactor-L1 engineering designs, the short half-lives of many radionuclides, and their chemical and physical properties, nearly all radioactivity is contained.
L The OCNGS reactor has six independent barriers that confine radioactive o materials produced by the fission reaction as it heats the w "+ . Under > { normal operating conditions, essentially all radioactivity is contained L; z within the first two barriers. I . [
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- 1. Reactor Vessel 8. Steam line .
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- 2. Steam Separators & Dryers 9. Reactor Fua._" .- Panps '
- 3. Fuel Core
~; 10. FeedwaterHeaters(3) l i j. 4. Recirculation Pumps (5) 11. Feedwater Supply -
'5. Nitrogen Atmosphere 12.~ Cor.i...xr Water Discharge
- 6. Drywell Containment Structure 13. Cc,.Awr
_ _. 7. 'Ibrus 14. Turbine-C;.w. kr . E B '
- 15. Condenser Water Inlet i r -
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The ceramic uranium fuel pellets provide the first barrier. Most of the. fission products are either trapped or chemically bound in the fuel where they remain. However, a few . fission products which are volatile or ! n gaseous at normal operating temperatures may not be contained in the fuel. s . LI- The second barrier consists of zirconium alloy tubes that resist corrosion. ,
': and degradation due to high temperatures; The fuel pellets'are contained ,
._i -- ;}
;' within these tubes. There is a small gap between the fuel and the ;
cladding, in which the noble gases and other volatile radionuclides
- collect. ,
s The primary coolant water is the third barrier. Many of the fission q' products, including radioactive iodine , strontium and cesium are. soluble 3 I i
- and are retained in water in an ionic (electrically charged) form. These materials can be removed in the reactor coolant purification system.
l
.. - However, krypton and xenon do not readily dissolve in.the coolant, ; 'i particularly at high temperatures. Krypton and xenon collect as a gas above the condensate when the steam is condensed.
- I: The fourth barrier consists of the reactor pressure vessel,. turbine, condenser, and associated piping of the coolant system. -The reactor i -
pressure vessel.is a 63-foot high tank with steel walls about nine inches thick. It encases the reactor core. The remainder of the coolant system includes 1.he turbine and condenser and associated piping. This system' ; provides containment for radioactivity in the primary coolant. The drywell provides the fifth barrier. It is a steel-lined vessel surrounded by concrete walls approximately 4 1/2 to 7 1/4 feet thick that enclose the reactor pressure vessel and recirculating pumps and loops. W The reactor building provides the sixth barrier. It is a reinforced concrete and steel superstructure which is always maintained at e negative pressure. I l I i 1 %e ,n eg e v. g w we-- w - v- _ m _. --_m- _ _ - - - - - = *--
l . 1 sources of Liould and Airborne Effluents Although the previously described barriers contain radioactivity with high
- efficiency, small amounts of radioactive fission products are nevertheless able to diffuse or migrate through minor flaws in the fuel cladding and IL '
into the reactor coolant. Trace quantities of reactor system component f.. E . and structural materials which.have been. activated, also get into the
; reactor coolant water. Many of the soluble fission and activation products such as iodines, strontiums, cobalts, and cesiums are removed by I
domineralizers in the purification system of the reactor coolant. The physical'and chemical properties of noble gas fission products in tho'
- primary coolant prevent their removal by the domineralizers.
Because the reactor system has many valves and fittings, an absolute seal = I. L cannot be achieved. . Minute drainage of radioactive liquids from valves, piping, and/or equipment associated with the coolant system may occur in- [ the Reactor, and/or Turbine 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 pumped to and: processed in l V the Radwaste_ Building. p 5 Reactor off-gas, consisting primarily of hydrogen and radioactive non-condensable gases, is withdrawn from the reactor primary system by steam jet air ejectors. These: air ejectors drive the process stream through a 60 minute holdup pipe at approximately 110: cubic feet per minute and then into the Augmented Off-Gas (AOG) System. . The. holdup pipe allows
. radionuclides with short half-lives to decay. The Augmented Off-Gas
= System is a gaseous processing system which provides hydrogen conversion
. 1 to water via a catalytic recombiner, removes the water (vapor) from the i process stream, holds up the process stream to allow further decay of I short-lived nuclides, and filters the off-gas using charcoal beds and High Efficiency Particulate (HEPA) filters prior to discharge to the base of the stack. Once the process stream enters the stack, it is diluted by building ventilation, which averages 200,000 cubic feet per minute, is
. monitored and sampled, and then is discharged out the top of the 368-foot
' = stack.
I.
g - 1 The liquid waste processing system receives water contaminated with radioactivity and processes'it by' filtration, domineralization, and distillation. -Purified radwaste water is recycled to the plant. ; occasionally, it' is necessary to discharge this purified water to the .j environment. Contaminants removed during the purification process are; !
-disposed of via the solido disposal systems.. When purified water'is-discharged to the environment, it is first' sampled, analyzed,, assigned a l t
release rate, and then released'to the discharge canal which has-a flow '! rate of 460,000 to 960,000 gallons per minute. ! I< .
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e, DESCRIPTION OF THE OCNGS SITE
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- ' L General Information
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l 4 The Oyster Creek' Nuclear Generating Station is located in Lacey Township r of Ocean County, New Jersey, about 60 miles South of Newark, 9~ miles south. l L of Toms River and 35 miles north of Atlantic City. It lies approximately < t . j f 2 miles inland from Barnegat Bay. The site,. covering 1416 acres,=is situated partly. in Lacey Township 'and, to a lesser extent, in Ocean 4 I - Township. The Garden State Parkway bounds the site on the west. . Overland access is provided by U. S. Route 9, passing through the-site and separating a 661-acre eastern portion from the balance of the property west of the highway.. The station is about 1/4 mile west of the highway and 1-1/4' miles east of the parkway. Tho'aite property extends about ., ( 2
. I.~ 3-1/2 miles. inland from the bayp-the maximum width in the north-south direction is almost 1 mile. The site location is part of the New Jersey shore area with its relatively flat topography and extensive freshwater and saltwater marshlande. The south branch of Forked River runs across
;the northern side of.the site, and Oyster Creek partly borders the southern aide.
t It'is estimated that approximately 3.3 million people reside within a 50 mile radius of the station (Reference "r) . Tha aearest population center is ocean Township (population 3731) which lies less than two miles south-southeast of the site. Two miles to the north,,14,161 people reside.
) i in Lacey Township. Dover Township, situated 9.5 miles to the north, is the nearest major population center with a population of 61,287. The region adjacent to Barnegat Bay is one of the State's mosc rapidly developing areas. In addition to the resident population, a sizeable seasonal influx of people occurs during the summer. This influx occurs 3- almost exclusively along the waterfront.
Climatoloolcal Summarv The reporting period of 1989 provided some interecting meteorological situations. A record cold month was present along with overall higher amounts of precipitation.
-m n- n.
~ For the first half of the period, the predominant wind directions were g from the west-northwest and the south-southwest. The normal northwest f
' wind directions are expected during the winter months as the polar jet stream normally pushes: southward and allows Canadian air masses to dominate the region. A small maxima of east-northeast direction was present. This was due to the influence of extratropical low pressure
; systems (northeastern storms) which are common to.the region, especially'-
;a -- during the winter months,.and the airflow around large high pressure !
systems. Periods with this onshore direction have characteristic low 1 j clouds, drizzle and fog l(stable atmospheres). From April through June, the wind directions took on a summer-like pattern as wind directions from
- the southwest became commonplace. This is referred to as the transition time when the jet stream begins its retreat northward. The summer monthe j were an anomaly. .The predominant wind direction during the early'second !
~'
+ half of the period was.from the west-southwest. Normal summer months have maxima from the south and the west, the latter direction due to modified . q
. continental polar air masses that follow cold frontal passages. The
~
former' maximum-is due mainly to the end result of,the sea breeze j l phenomenon.- At the height of this mesoscale effect (approximately 2:00 to-4:00 in the afternoon)' the wind will parallel the coast - the result' created from uneven heating between' land and' sea coupled with the natural se rotation of the earth. The lack of any appreciable sea breeze (southerly wind component) was mainly duo'to the northward drift of the subtropical-high pressure center, a phenomenon common to the southeast coast. The. northward movement caused increased southwest wind which acted to hinder .1 the development of the sea breeze. The period from October through December was fairly normal as the predominant wind direction was from the 1 l northwest, reflecting the southerly return of the polar jet stream. The average monthly temperature for the site remained near normal for most ) of the year. The most notable exception occurred during December, when - the average temperature was 24 degrees F. This is over 10 degrees F lower than the Atlantic City average (35 degrees F) and represents a record for the area. During January, the average temperature was 4 degrees F higher than the Atlantic City average. The remaining ten months were very close l 1 I l 1
- y I'
to normal. There was very little occurrence.of the thermally-induced sea i breeze'at the' site. This was due to the noticeably high percentage of ~. i offshore winds during the peak summer months when the sea breeze is most i prevalent. These offshore winds act to inhibit the inland penetration of s this phenomenon. The highest mean r.ionthly temperature occurred in July
., , (72.5 degre9s F) while December took credit for the lowest (24.4 degrees).
The aforementioned record for cold in December of 1989 lead to-a sharp-decrease in precipitation for that month (0.80 inches). This was due in
; part to the largo dome of high pressure associated with the abnormally-cold air masses that swept through the eastern half of the country. The standard extratropical cyclones that form off the North Carolina coast were forced southward thus missing the northeast but providing the
. mid-Atlantic states with larger-than-normal snow amounts. The lack of
'. precipitation during December did not help to keep the annual
; precipitation total below the normal annual total for the area. A total
~of~47.74 inches of precipitation fell during 1989. This amounts to approximately 5.56 inches of precipitation above the normal'(41.29 inches at Atlantic City). Highlights-for the year included small amounts (under -
~
l.00' inch) during the normally dry months of June and July and-a monthly maximum of 7.08 inches during August. Precipitation during.the summer I Ii ' months were primarily due to small-scale convective showers and f 1 thunderstorms. These eventa are characterized by short duration but strong intensity. With this type of precipitation event, there will be increased particulate fallout (washout) from the atmosphere, which has implications for radionuclide deposition. During the summer, marine air, i which is stable, will generally suppress these convective storms and decrease precipitation at most coastal locations. The sea breeze can f
.I-produce the same result. The remainder of the period's contribution to rainfall was due to extratropical storms of light to moderate intensity
- Ii and long duration, especially during the first quarter (January-March) and September through November.
For a more complete meteorological summary refer to the Semiannual Effluent Release Reports for 1989. L.
~
MONTHLY PRECIPITATION AT THE 0YSTER CREEK NUCLEAR GENERATING STATION' , DURING 1989 COMPARED WITH HISTORICAL'(1946.- 1981) ATLANTIC CITY NATIONAL WEATHER SERVICE PRECIPITATION DATA . 20-NOTE: LIMITED DATA IN JULY DUE TO TOWER MAINTENANCE 18-16-ro Era i i g5' m 14- c l' o R
$ 12- ATLANTIC CITY M-Z
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10- OYSTER CREEK
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y 6- .l 4- m g 2-0- 1 I I I I I I I I I 1 1 JAN FEB MAR -APR MAY JUN JUL AUG SEP OCT NOV .DEC MONTH
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I o I EFFLUENTS
?
e Historical Backaround Almost from the outset of the discovery of x-rays in 1895 by Wilhelm I T Roentgen the potential hazard of ionizing ~ radiation was recognized and efforts were made to establish radiation protection standards.. The. International Commission on Radiological Protection (ICRP) and the .; National Council on Radiation Protection and Measurements (NCRP) were .[ established in 1926 and 1929, respectively, and have the longest { continuous experience in the review of radiation health effects and with l t recommendations on guidelines for radiological protection and radiation 1 I exposure limits. In 1955, the United Nations created a Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) to summarize l 4 reports received on radiation levels and the effects on man and his environment. The National Academy of Sciences (NAS) formed a committee in 1956 to review the biological effects of atomic radiation (BEAR). A 1. series of reports have been issued by this and succeeding NAS committees 1 on the biological effects.of ionizing radiation (BEIR); the most,recent lL g' W being 1987-(known as BEIR IV). The Federal Radiation Council (FRC) was
- - formed in 1959 to provide a federal policy on human radiation exposures.
These federal policies are approved by the President of the United States. These committees and connissions of nationally and internationally j recognized scientific experts have been dedicated to the understanding of { the health effects of radiation by investigating all sources of relevant knowledge and scientific data and by providing guidance for radiological
' protection. Their members are selected from universities, scientific E research centers and other national and international research organizations. The committee reports contain scientific data obtained j from physical, biological, and epidemiological studies on radiation health effects and serve as scientific references for information presented in this report. Since its inception, the USNRC has depended upon the recommendations of the ICRP, the NCRP, and the FRC (incorporated in the I
United States Environmental Protection Agency in 1970) for basic radiation protection standards and guidance in establishing regulations for the l nuclear industry (Ref. 8 through 11).
~
I .
1 I' Effluent Release Limits As part of routine plant operations, limited quantities of radioactivity are released to the environment in liquid and airborne effluenta. An effluent control program is implemented to ensure radioactivity released j I to the snvironment is minimal and does not exceed release limits. Radioactive effluent releases at Oyster Creek are under the regulatory jurisdiction of the USNRC. Regulations through the years have changed and reflect operating experience and advances in nuclear technology. Federal l regulations as defined by Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20) establish limits on the concentrations of radioactivw 1 l effluents released to the environment. Federal effluent limits are set at I l low levels to protect the health and safety of the public. GPU Nuclear conducts operations in a manner that holds radioactive (sf fluents to small percentages of the federal limits. A recommendation of the ICRP, NCRP, and FRC is that radiation exposures should be maintained at levels which are "as low as reasonably achievable" l' I (ALARA) and comuensurate with the societal benefit derived from the activities resulting in such exposures. For this reason, dose limit guidelines were established by the USNRC for releases of radioactive t affluents from nuclear power plants. These guidelines are presented in the Oyster Creek Technical specifications. Maintaining releases within . these operation guidelines demonstrates that radioactive effluents are 4 being maintained "as low as reasonably achievable". I WB The oyster Creek Technical Specification dose limit guidelines are as follows: l I o Technical Specification 3.6.K.1 t
- I The dose equivalent rate outside of the EXCLUSION AREA due to radioactive noble gas in gaseous effluent shall not exceed 500 mrem / year to the total body or 3000 mrem / year to the skin.
I
b , B I, o Technical Specification 3.6.L.1 1 The air dose outside of the EXCLUSION AREA due to noble gas released in gaseous effluent shall not exceed ; 5 mrad / calendar quarter due to gamma radiation, ) I 10 mrad / calendar quarter due to beta radiation, 10 mrad / calendar year due to gamma radiation, or J 20 mrad / calendar year due to beta radiation. o Technical specification 3.6.N.1 The annual dose to a MEMBER OF THE PUBLIC due to radiation and I radioactive material in effluents from the OCNGS outside of the EXCLUSION AREA shall not exceed 75 mRom to his thyroid or 25 f I mrem to his total body or to any other organ. o Technical specification 3.6.K.2 I The dose equivalent rate outside of the EXCLUSION AREA due to 88 H-3, I-131, 2-133, and to radioactive material in particulate ! form having half-lives of 8 days or more in gaseous effluents ; I shall not exceed 1500 mrem / year to any body organ when the dose rato due to H-3, Sr-89, Sr-90, and alpha-omitting radionuclides i is averaged over no more than 3 months and the dose rate due to other radionuclides is averaged over no more than 31 days. t o Technical Specification 3.6.H.1 l The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, and from radionuclides in particulate form having half-lives of , 8 days or more in gaseous effluents, outside of the EXCLUSION AREA shall not exceed 7.5 mrem to any body organ per calendar ;
$ quarter or 15 mrem to any body organ per calendar year.
I g . I ,
1 i o Technical specification 3.6.I.1 The concentration of radioactive material, other than noble gases, in liquid eM1uent in the discharge canal at the Route 9 I bridge shall not exceed the concentrations specified in 10 CTR I Part 20, Appendix B, Table II, column 2. l { o Technical specification 3.6.I.2 The concentration of noble gases dissolved or entrained in liquid offluent in the disch&rge canal at the Route 9 bridge shall not 1 exceed 2 x 10~4 microcuries/ milliliter. o Technical specification 3.6.J.1 1 The dose to a MEMBER OF THE PUBLIC due to radioactive material in liquid effluents beyond the outside of the EXCLUSION AREA shall not rxce.d, I 1.5 mrem to the total body during any calendar quarter, 6 mrem to any body organ during any calendar quarter, 3 mRom to the total body during any calendar year, or 10 mRom to any body organ during any calendar year. I I I I 4 I
'I
- j. :
Effluent control Proaram i Effluent control includes plar.t components such as the ventilation system and i11ters, off gas holdup components, domineraliters and an evaporator j system. In addition to minimizing the release of radioactivity, the j I effluent control program includes all aspects of effluent and environmental monitoring. This includes the operation and data analysis nosociated with a complex radiation monitoring system, environmental F sampling and monitoring, and a comprehensive quality assurance program. over the years, the program has evolved in response to changing regulatory requirements and plant conditions, yor example, additional i 1 instruments and samplers have been installed to provide that measurements I 1 of offluents remain onseale in the event of any accidental release of radioactivity. j I Iffluent Instrumentation: . Liquid and airborne effluent measuring instrumentation is designed to detect the presence and the amount of I radioactivity in effluents. Many of these instruments provide continuous ,g. uu - surveillance of radioactivity releases. Calibrations of effluent instruments are performed using reference standards certified by the United States National Institute of Standards and Technology. Where continuous surveillance is not practicable or possible, contingencies are spelled out in the Technical specifications. If pre ~ designated setpoints are reached, releases are immediately terminated. Effluent samelino and Analysis: In addition to continuous radiation W monitoring instruments, samples of offluents are taken and subjected to laboratory analysis to identify tho' specific radionuclide quantities being released. A sample must be representative of the effluent from which it is taken. Sampling and analysis provide a sensitive and precise snethod of determining effluent composition. Samples are analyzed using the highest quality laboratory counting equipment. Radiation instrument readings and sample results are compared to ensure correct correlation.
- I I ~22-1
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- j, Iffluent Data As part of routine plant operations, limited quantities of radioactivity are released to the environment in liquid and airborne effluents. Amounts of radioactivity released varies and is dependent upon operating i conditions, power levels, fuel conditions, effici<incy of liquid and gas f
.g processing systems, and proper functioning of plant equipment. The ;
5 1argest variations occur in the airborne affluents of fission and { activation gases which are proportional to the augmented off gas system l operation in the gas processing system and to the integrity of the fuel cladding. In general effluents have been decreasing with time due to improved fuel integrity and increased efficiency of processing. systems. l With respect to activity released during 1989, the predominant !g ' W radionuclides were Xe-135 in gases and H-3 in liquids. The amount of
. radioactivity released is summarized and reported semiannually to the !
USNRC. Estimated radiation doses to the public, attributable to these offluents, ranged from less than one percent to a maximum of only 16-percent of the applicable regulatory limits. A summary of the OCNGS liquid and airborne offluents for 1989 is provided in Table 2. t I Radioactive constituents of these effluents are discussed in the following sections. Noble cases: The predominant radionuclides released in airborne offluents are the noble gases xenon (Xe) and krypton (Kr). Small amounts are also released in liquid effluents. The total amounts of xenon and krypton released into the atmosphere in 1989 was 164 curies and 160 curies respectively. These noble gases were readily dispersed into the atmosphere when released and because of their short half-lives, quickly , decayed into stable forms. I Iodines and Particulates: The discharge of iodines and particulates to i the environment is minimized by factors such as their high chemical reactivity and solubility in water combined with the high efficiency y removal of airborne and liquid processing systems. k I - l TABLE 2 I RADIONUCLIDE COMPOSITION OF OCNGS EFFLUENTS FOR 1989 Licaid Effluents (C1) Caseous Effluents fci) Radienuelide Half-Life OCNGS OCNGS H-3 12.3 vaars 3.96 1.03 El Cr 51 27.7 dave ND 6.77 E-3 9.41 E-4 Mn-54 312 days 9.22 E-5 r Fe-55 2.7 vaars 3.33 E-4 ND Co-60 5.3 vaars 5.55 E-3 ND I. Kr-85m 4.B hours ND 2.89 El Kr-87 76 minutes ND 6.31 El Kr-88 2.8 hours ND 6.80 El , Sr-89 50.5 dave ND 2.67 E-3 l Sr-90 28.8 voars ND 1.71 E-5 _ [ Te-99m 6.0 hours ND 4.06 E-2 1-131 8.0 days 1.92 E-3 4.03 E-2 _ 1 I-132 2.3 hours ND 8.82 E-2 ; I-133 20.9 hours 5.94 E-4 8.33 E-2 Xe-133 5.2 days 6.42 E-4 ND Cs-134 2.1 years 1.41 E-2 ND' , I-135 6.7 hours ND 3.87 E-2 > Xe-135 9.1 hours 1.57 E-3 1.50 E2 Xe-135m 15.6 minutes ND 1.39 El
= Cs-137 30.2 years 5.75 E-2 ND l Gross Aloha 1.81 E-5 4.33 E-5 Notei All effluents expressed in scientific notation.
.ND = No Activity Detected I.
I. I
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k i I of the gaseous radioiodines, iodine-131 is of particular concern because of its relatively long half-life of 8 days. Particulates of relative 1 1 concern are the radiocesiums (Co-134 and Cs-137), radiostrontiums-(Sr-89 and Sr-90), technetium-99m (Tc-99m) and activation products chromium-51 (Cr-51), manganese-54 (Mn-54), and cobalt-60 (Co-60). The total amount of ( iodines and particulates released from the station in 1989 was 0.30 curies in airborne effluents and 0.080 curies in liquid effluents. l Tritium: Tritium is the predominant radionuclide released in liquid effluents and also is released in airborne effluents. Tritium is a radioactive isotope of hydrogen. It is produced in the reactor coolant as a result of neutron interaction with the naturally-occurring deuterium (also a hydrogen isotope) present in water. The total amount of H-3 I released in liquid and airborne affluents was 14.3 curies. To place this number in perspective, the world inventory of natural cosmic ray produced tritium is 70 million curies, which corresponds to a production rate of 4 million curies per year (Ref. 12). Tritium contributions to the environment from nuclear power production are sufficiently small that they i have no measurable effect on the existing environmental concentrations. I ' Transurantes: Transuranics are produced by neutron capture in the fuel, and typically emit alpha and beta particles as they decay. Important transuranic isotopes produced in reactors are uranium-239 (U-239), I plutonium-238 (Pu-238), plutonium-239 (Pu-239), plutonium-240 (Pu-240), plutonium-241 (Pu-241), americium-241 (Am-241), plutonium-243 (Pu-243), ! plus other isotopes of americium and curium. They have half-lives ranging from tens to millions of years. Transuranics are mostly retained within , the nuclear fuel. Because they are so insoluble and non-volatile they are not readily transported through plant pathways _to the environment. Gas and liquid processing systems remove greater than 90% of any transuranics outside the reactor coolant. Since greater than 99% of all transuranics are retained within the fuel and transuranic removal processes are extremely efficient, releases in airbcrne and liquid effluents are not monitored. I I l
- - _ . _ -- -. ~- . - . . - . - . . .-
t l I t carbon-14: Production of carbon-14 (C-14) in reactors is small. It is produced in the reactor coolant as a result of neutron interactions with , oxygen and nitrogen. Estimates for all nuclear power production j worldwide, show that 235,000 curies will be released from 1970 through j 1990 (Ref. 13). I Cart.on-14 also is produced naturally by the interactions of cosmic l i radiation with oxygen and nitrogen in the upper atmosphere. The worldwide inventory of natural C-14 is estimated at 241 million curies (Ref. 13). , since the inventory of natural carbon-14 is so large, releases from l nuclear power plants do not result in a measurable change in the f background concentration of carbon-14. Consequently, carbon-14 is not I I~ routinely monitored in plant offluents. I I I: i l: I : I I ! Lt. 12 I I . I .
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-I RADIOLOGICAL ENVIRONMENTAL MONITORING l t
GPUN conducts a comprehensive radiological environmental monitoring program (REMP) at Oyster Creek to monitor radiation and radioactive
~
materials in the environment. This program provides information on radioactivity in the environment from OCNGS releases and information on , the potential principal pathways of exposure to humans. , The USNRC has established regulatory guides which contain acceptable : monitoring practices (Rwf. 14). The OCNGS REMP was designed on the basis of these regulatory guides along with the USNRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Ref. 15). All of f thou guidelines have been met and in most cases the OCNGS program greatly exceeds them. The important objectives of the REMP are
a o to assess impacts to the public from OCNGS operations .
o to verify in-plant controls for the containment of radioactive , materials o to determine buildup of long-lived radionuclides in the environment and changes in background radiation levels IL o to provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the environment. a Environmental Exoosure Pathways to Humans from Airborne and Liould Effluents Br Environmental transport pathways is the term for movement of radionuclides through the environment and transport to humans. The airborne pathways have basically five routes of importance: (1) direct radiation, (2) deposition on vegetation, (3) deposition on soil, (4) consumption by 'l animals and (5) inhalation by humans. Liquid pathways have three basic routes of importance: (1) ingestion of drinking water, (2) fish and I
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e I i1 j shellfish consumption and (3) exposure from shoreline sediments. Each of ) these possible routes that can lead to radiation exposure to humans is f 1 termed an exposure pathway. As can be seen, these routes are both numerous and varied. While some pathways are relatively simple, such as i inhalation of airborne radioactive materials, others may be complex. For
'I example,' radioactive airborne particulates may deposit onto forage which when eaten by cows may be secreted into milk, which is subsequently ;
i consumed by man. This is known as the air-grass-cow-milk pathway, Although radionuclides can reach humans by a number of pathways, some are I more important than others. The critical pathway for a given radionuclide, is the one that produces the greatest dose to a population, or to a specific segment of the population. This segment of the ; population is known as the critical group, and may be defined by age, ,I dietary, or other cultural factors. The dose may be delivered to the , whole body or confined to a specific organ; the organ receiving the greatest fraction of the dose is known as the critical organ. This information was used to develop the oyster creek program. ; i
-I Samoline I
The OCNGS radiological environmental monitoring program consists of two , phases -- the preoperational and the operational. The preoperati'onal phase provided data which is used as a basis for evaluating increases in . radiation levels and radioactivity in the vicinity of the plant after the plant becomes operational. The operheional phase began in 1969 when the OCNGS began power generation.
- The program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With emphasis on the critical pathways to.
humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include air, precipitation, well water, surface water, clams, sediment, fish, crabs, vegetables, and
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i I - to measure gamma radiation levels. The Technical Specifications and recommendations from the scientific staff of GPUN specify the sample types l to be collected and analyses to be performed.
~
Sampling locations were established by considering metecrology, population , distribution, hydrology, and land use characteristics of the local area. The sampling locations are divided into two classes, indicator and I background. Indicator locations are those which are expected to show effects from OC'NGS operations, if any exist. These locations were - primarily selected on the basis of where the highest predicted environmental concentrations would occur. While the indicator locations are typically within a few miles of the plant, the background stations are generally at distances greater than 10 miles from the oCNGS. Therefore, background samples are collected at locations which are expected to be , I unaffected by station operations. They provide a basis on which to ' evaluate fluctuations at indicator locations relative to natural background radiation and natural radioactivity and fallout from prior , nuclear weapon tests. Figures 3, 4, and 5 show the current sampling i locations around the OCNGS. Table A-1 in Appendix A describes the sampling locations by distance and azimuth. I' Analysis - In addition to specifying the minimum media to be collected and the minimum number of sampling locations, the Technical Specifications also ,
- l. specify the frequency of sample collection and the types of analyses to be performed. Additionally, analytical sensitivities (detection limits) and j reporting levels also are specified. Table A-2 in Appendix A provides a
.- synopsis of the sample types, number of sampling locations, collection !
frequencies, number of samples collected, types of analyses and frequencies, and number of samples analyzed. Table h-3 in Appendix A i presents problems encountered in cample collection and analysis. Sample l analyses which did not meet the required analytical sensitivities are l1 presented in Appendix B. Changes in sample collection and analysis are described in Appendix C. u LI - i -29 - I
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J. d W ',aN %.WJ' - " . m .#t, , r..;.'!' . .t " E. ... Oyster Crwek Nuclear Generating Station (OCNGS) location of Radiological Emstrunental Monitanng 1%gmm (REMP) E Stataans gmater than 2 miles fran the site I l3 = l \ - ,- - - , l ; I The analytical results are routinely reviewed by GPUN scientists to assure that sensitivities have been achieved and that the proper analysea have I been performed. All analytical results are subjected to an automated ! review process which ensures that Technical Specification-required lower limits of detection are met and that reporting levels are not exceeded. i Investigations are conducted when anomalous values are discovered. I I Table 3 provides a summary of radionuclide concentrations in environmental j samples from the OCHGS in 1989. The data are summarized in the format i suggested in the USNRC Branch Technical Position (Ref. 15). 4 Measurement of low radionuclido concentrations in environmental media requires special analysis techniques.. Analytical laboratories use , state-of-the-art laboratory equipment designed to detect beta and gamma i radiation. This equipment must meet the required analytical I sensitivities. Examples of the specialized laboratory equipment used are germanium detectors with multichannel analyzers for determining specific , gamma emitting radionuclides, liquid scintillation detectors for tritium, . low level alpha and beta counters, and coincidence counters for low level I-131 detection. Computer hardware and software used in conjunction with the counting equipment perform calculations and provide data management. - Analysis methods are discussed in more detail in references 16, 17, and 18 I and are also described in Appendix 1. ouality Assurance Prooram A quality assurance program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological i Monitoring Programs" (Ref. 19) and as required by the Technical i Specifications. It is documented by GPUN written policies, procedures, = and records. This program is designed to identify possible deficiencies so that immediate corrective action can be taken. It also provides a I measure of confidence in the results of the monitoring program in order to assure the regulatory agencies and the public that the results are valid. ; The quality assurance program for the measurement of radioactivity in environmental media is implemented by: . I,- yy --ws t- ,-- e--.o, w a w_ a-- - at---- - - - , t i o auditing analytical laboratories , o requiring analytical laboratories to participate in the USEPA cross-check Program f o requiring analytical contractor laboratories to split samples for , separate analysis (recounts are performed when samples are not ! I o able to be split) splitting samples, having the samples analyaed by independent l laboratories, and then compe. ring the results for agreement t o requiring analytical laborretories to provide quality assurance reports showing laboratory instrument calibration and maintenance tests and results of blind, split, and duplicate analyses r The quality assurance program and the results of the USEPA cross-Check j Program are outlined * /7pendices D and E, respectively. I : y Procedures were written and approved by Environmental Controls, Quality l Assurance, and analytical laboratories to cover all aspects of the radiological environmental monitoring program. These procedures cover ! I such areas as sample collection, sampling equipment calibration and maintenance, laboratory analysis, and data review. 1 5 I : I I I I I t-I -l E O E .E E E E E E E E E E E E E- E E O TABLE 3 RADIGIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 "IHROUGH DECEMBER,1989 THE FOLLOWING PAGES ARE A
SUMMARY
OF REMP DATA FOR THE SCHEDUIID COLLECTION PERIOD JANUARY,1989 THRU DECEMBER,1989. DATA ARE SUMMARIZED ON AN ANNUAL BASIS, WHERE: 1.) XXX-MEAN(N/ TOTAL); MEAN AND RANCE BASED ON RANCE DETECTABLE ACTIVITIES OF ALL XXX STATIONS 2.) XXX-BACKGROUND OR INDICATOR STATIONS 3.) (N/ TOTAL)-FRACTION CF DETECTABLE ACTIVITIES / TOTAL NUMBER OF ANALYSES PERFORMED 4.) STATION-STATION WITH HIGHEST ANNUAL MEAN 5.) BACKGROUND STATIONS USED ARE: STATION A,C,H,14 31,94 18/36 SAMPLE TYPE AIR PARTICULATE SEDIMENT WELL WATER / AIR IODINE CLAMS VEGETABLES PRECIPITATION SURFACE WATER SOIL FISH (**) BLUE CRAB (**) 6.) *-NO DATA SAMPLED ; **-STATION 94 ONLY l
. ~
e e e e e e e e e e e e e m .m e e m- e TABLE 3 RADI0IDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER Ilh INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/IUTAL) ~ STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION - STATION-MEAN(N/ TOTAL) - RANGE AIR PARTICUIATE GROSS BETA 676 2.87E-03 1.57E-02 (468 /468 ) 1.63E-02(208 /208 ) 1 20 3 4 5 (PCI/M3) ( 5.14E 3.69E-02) ( 4.94E 3.78E-02) 66 71 72 73 1 1.65E-02(52 /52 ) ( 5.I4E 3.50E-02) , AIR PARTICULATE GAMMA CE-144 169 9.20E-03 < LIE (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 i 73 < LID (0 /13 ) AIR PARTICUIATE GAMMA AG-110M 169 2.75E-03 < LLD (0 /117 ) < LID (O /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICUIATE GAMMA TE-129M 169 3.59E+03 < LID (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA CS-134 169 3.53E-03 < LID (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICUIATE GAMMA CO-58 169 3.37E-03 < LID (0 /117 ) < 1.LD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /I3 )
.., a - -
, ,,- ,. . . , - - , , - --~w .- , e . - - , .
TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SLEMARY OYSTER CREEK NUCLEAR GENERATING STATION JANUARY 1989 THROUGH DECEMBER,1989 ANNUAL SLMMARY SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LIE INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE AIR PARTICUIATE GAMMA MN-54 169 3.14E-03 < LIE (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72. 73 73 < LID (0 /13 ) AIR PARTICUIATE CAMMA FE-59 169 7.92E-03 < LLD (0 /117 ) < LIE (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICUIATE GAMMA CS-136 169 6.03E-03 < LID (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICULATE GAMMA TE-132 169 4.65E-02 < LLD (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 <. LLD (0 /13 ) AIR PARTICUIATE GAMMA ZN-65 169 9.48E-03 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA CO-60 169 4.11E-03 < LID (0 /117 ) < LIE (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 )
- l l
E E E E E_E E E E O E E E E E E E E O TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE AIR PARTICUIATE GAMMA K-40 169 4.29E-02 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICULATE GAMMA BE-7 169 3.10E-02 9.07E-02 (117 /117 ) 8.88E-02(52 /52 ) 1 20 3 4'5 (PCI/M3) ( 4.68E 1.50E-01) ( 6.09E 1.20E-01) 66 71 72 73 72 9.78E-02(13 /13 ) ( 7.26E 1.25E-01) AIR PAitTICUIATE CAMMA ZR-95 169 5.81E-03 < LID (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA NB-95 169 3.33E-03 < LLD (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 )' . AIR PARTICUIATE GAMMA SB-125 169 6.24E < LID (0 /117 ) < LID (0 /52 ) ~1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA CE-141 169 2.87E-03 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) i _. r . _ _ _ _ _
--_m
mmW W W memM W W W W WW W W mW TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH LECDIBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES PERNRMED STATION STATION-MEAN(N/TCrfAL) RANGE AIR PARTICULATE GAMMA RU-103 169 2.95E-03 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICULATE GAMMA CR-51 160 2.33E-02 < LID (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) , , AIR PARTICUIATE CAMMA BA-140 169 1.77E-02 < LID (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (POI /M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA 1A-140 169 9.NE-03 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5
- (PCI/M3) 66 71 72 73 73 < LIE (0 /13 )
i AIR PARTICUIATE GAMMA AC-228 169 -1.16E-02 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4-5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA RA-224 169 7.67E-01 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71' 72 73 73 < LIE (0 /13 )
. - - . , , . - ._ . _ .,_m _ _.. . . . , , , _ _ . . _ . ._ _ ._ _,_ -....._ _ . - _ _ . _ ~ , . _ - , . . . . - .
m m m m ,g M emM M M M M MW M: MW TABLE 3 RADIOlhGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1939 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANCE FDR INDICATOR ANALYSES MEAN PEREVRMED STATION STATION-MEAN(N/ TOTAL) RANGE AIR PARTICUIATE GAMMA RA-226 169 3.90E-02 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < L1D (0 /13 ) AIR PARTICUIATE GAMMA I-131 169 7.15E-03 < LID (0 /117 ) < LT.D (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICULATE GAMMA NA-22 169 4.02E-03 < LLD (0 /117 ) < LLD (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 , 73 < LID (0 /13 ) AIR FARTICUIATE GAMMA RU-106 169 2.56E-02 < LLD (0 /117 ) < LIE (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) AIR PARTICULATE CAMMA CO-57 169 1.17E-03 < LIE (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LLD (0 /13 ) AIR PARTICUIATE GAMMA I-133 169 9.24E+05 < LID (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 '72 73 73 < LIE (0 /13 )
sj j., . - >-- c -
.u$ ua g g am3mM M M MM M W M M M 6 M~W TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED-0F PANGE RANGE FUR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE AIR PARTICUIATE GAM".A CS-137 169 2.96E-03 < LLD (0 /117 ) < LID (0 /52 ) 1 20 3 4 5 (PCI/M3) 66 71 72 73 73 < LID (0 /13 ) PRECIPITATION GAMMA CE-144 24 2.22E401 < LID (0 /12 ) < LLD (0 /12 ) 66 72 73 (PCI/L) 73 < LLD (0 /4 ) PRECIPITATION GAMMA AG-110M 24 3.87E+00 < LLD (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 ) PRECIPITATION GAMMA TE-129M 24 1.71E+07 < LID (0 /12 ) < LIE (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 ) PRECIPITATION GAMMA CS-134 24 5.58E+00 < LID (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LLD (0 /4 ) PRECIPITATION GAMMA CO-58 24 4.53E+00 < LID (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 )
g W W M WM M M M M M SS E E M E M
, . TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM SUl91ARY OYSTER CREEK NUCLEAR GENERATING STATION JANUART,1989 THROUGH DECEMBER,1989 ANNUAL SLMMARY SAMPLE TYPE ANALYSIS ISOTOPE NUMBER L1D INDICATOR-MEAN(N/ TOTAL) STATIONS USED BACKGROUND-MEAN(N/ TOTAL)
OF RANGE RANGE FUR INDICATOR ANALYSES MEAN PERFURMED STATION STAT'ON-MEAN(N/ TOTAL) RANGE PRECIPITATION GAMMA MN-54 24 4.36E+00 < LLD (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 ) PRECIPITATION CAMMA FE-59 24 9.64E400 (0 /12 ) (PCI/L)
< LID < LID (0 /12 ) 66 72 73 73 < LIE (0 /4 )
PRECIPITATION GAMMA CS-136 24 6.11E+00 (0 /12 )
< LID < LIE (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 )
PRECIPITATION GAMMA TE-132 24 9.65E+01 (0 /12 )
< LID < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 )
PRECIPITATION GAMMA ZN-65 24 1.35E+01 (0 /12 ) (PCI/L)
< LID < LLD (0 /12 ) 66 72 73 73 < LLD (0 /4 )
PRECIPITATION CAR *fA CO-60 24 5.24E+00 < LLD (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LID (0 /4 )
8 M MM Q QM M MW M M 'M M 8 MM M & 1 TABLE 3 RADIO 1DGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE PRECIPITATION GAMMA K-40 24 5.80E+01 < LIE (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LLD (0 /4 ) PRECIPITATION GAMMA BE-7 24 3.82E+01 < LID (0 /12 ) < LIE (0 /12 ) 66 72 73 (PCI/L) 73 < LLD (0 /4 ) PRECIPITATION GAMMA ZR-95 24 7.43E+00 < LID (0 /12 ) < LLD (0 /12 ) 66 72 73 (PCI/L)
, 73 < LID (0 /4 )
PRECIPITATION GAMMA NB-95 24 4.51E+00 < LID (0 /I2 ) < LIE (0 /12 ) 66 72 73 (PCI/L) 73 < LIE (0 /4 )
- PRECIPITATION GAMMA SB-125 24 1.02E401 < LIB (0 /12 ) < LID (0 /12 ) 66 72 73 (PCI/L) 73 < LLD (0 /4 )
PRECIPITATION GAMMA CE-141 24 5.59E400 < LLD (0 /12 ) < LID (0 /12 ) 66 72 73 (PC1/L) 73 < LIE (0 /4 ) _ - _ - _ _ _ _ _ _ _ _ _ . . _ _ _ - . . . - . _ . _ -. . _ . . - - . __. __ _ - _ , - . = _ . -
. +[:g :
- .: - - - - - af
~
!MJ S M M 'W . S W W ~E : M 4 M QM E. M E M : W[ W TABLE 3' RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL)' STAfl0NS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(*' ~ n'4L) RANGE PRECIPITATION GAMMA RU-103 24 4.41E+00 < LLD (0 /12 ) < LLD (0 /12 ) 60 72 73 (PCI/L) 73 < LLD (0 /4 ) PRECIPITATION GAMMA CR-51 24 3.29E+01 < LLD (0 /12 ) < LLD (0 /12 ) 66~ 72 -73.: (PCI/L)
'73 < LLD (0 /4 )
PRECIPITATION BA-140 < LLD GAMMA' 24- 1.94E+01 (0 /12 ) < LLD .(0 /12-) 66 .72 73 (PCI/L) 73- < LLD (0 /4 ) PRECIPITATION GAMMA IA-140 24 '9.15E+00 < LLD (0 /12 ) < LLD (0 /12 ) 66 72 73 (PCI/L) 73 <'LLD (0 /4 ) PRECIPITATION GAMMA AC-228 24 1.60E401 < LIE (0 /12 ) < LLD (0 /12 ) 66' 72 73 (PCI/L)
~
73 < LLD (0 /4 ) PRECIPITATION GAMMA RA-224 24- 1.54E+03 < LLD' (0 /12 ) < LLD (0 /12 ) 66 72 7 3 .. (PCI/L) 73 < LLD (0 /4-)
.- . . ~
. . _ . _ _ _ . .. - _- - - - . ~ .
,- , :n , .,. g, y E' S WIEj13'S S O WW W 4 W M~E :E M WI 4 TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION-JANUARY,1989'THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMEER. LLD INDICATOR-MEAN(N/ TOTAL) STATIONS USED BACKGROUND-MEAN(N/ TOTAL) OF RANGE RANGE ;FOR INDICATOR-ANAPC- - MEAN PEh 44MD'- STATION STATION-MEAN(N/ TOTAL)
-RANGE PRECIPITATION GAMMA RA-226 24 at (0 /12 ) 72' 73.
>.. .< LLD < LID. (0 /12 ) 66' (PCI/L) 73 < LIE (0 /4 )
PRECIPITATION GAMMA I-131 24 1.47E+02 < LID (0 /12 ). < LLD (0 /12 ) 66 72 73-(PCI/L) 73 < LLD (0 /4-) PRECIPITATION GAMMA NA-22 24 5.24E+00 (0 /12 )-
< LID < LIE (0 /12 ) 66 72 73-(PCI/L) 73 < LLD (0 /4 ).
PRECIPITATION GAMMA 'RU-106 24 3.75E+01 (0 /12 )
< LLD < LIB (0 /12 ) 66 72 73 (PCI/L) '
73 < LLD (0 /4 )- PRECIPITATION GAMMA CO-57 24 2.93E+00 (0 /12 )
< LLD < LLD (0 /12 ) 66 72 73 +
(PCI/L) 73 < LLD'(0 /4 ) PRECIPITATION GAMMA I-133 24 4.29E+09 (0 /12 )
< LLD -< LLD (0 /12 ) 66: 72' 73 l (PCI/L) l 73 < LLD-(0 /4 )
,_ _ . . _ . . ,.. ; _. . ._ _ _, . _ _ . ,g.__ , .s , _- m __ _ . . --- , m .__u., _. _
- .,c ,
w s .
._ :ML 6 E-E E6 E E EOM E E 'E E E E-E E u
TABLE 3 RADIGIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
' OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED
' ~ '
OF RANGE RANCE WR INDICATOR ANALYSES MEAN PERNRMED STATION STATION-MEAN(N/TUTA1). RANGE PRECIPITATION GAMMA CS-137 24 4.40E+00 < LLD (0 /12 ) < LLD (0 /19 ) 66 72. 73 (PCI/L) 73 < LLD (0 /4 ) PRECIPITATION TRITIUM 24 1.50E+02 2.34E+02 (1 /12 ): < LLD (0 /12 ) 66 72' 73 (PCI/L) ( 2.34E402 - 2.34E+02) 72 2.34E+02(1 /4 ) ( 2.34E+02 - 2 34E+02) AIR IODINE 10 DINE-131 676 2.84E-02 < LLD .(0 /468 ) < LID (0 /208~) 1 20 3 4 5 (PCI/M3) 66 71 -72 73. 73 < LLD (O./5? ) CABBAGE GAMMA CE-144 11 8'.01E+01 . < LLD (0 /8-) < LLD (0 /3 ) 35 66 (PCI/KG(WET))
. 66 < LLD (0 /4 )
CABBAGE GAMMA AG-110M 11 2.00E+01 < LLD (0 /8-) . < LLD (0 /3 ) 35 66 (PCI/KG(WET)) ' 66 < LLD (0 /4 ) CABBAGE CAMMA TE-129M 11 1.28E+04 < LLD (0 /8 ) < LLD (0 /3 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4 )
-i
.m. . _ . . ,. . -. u. .._.2 ,_-, . , . , _:..s ; . w , _. , ._-..__a,..._.__, , ._,
, -:xr; O~ _ _
TABLE 3 ~ RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION- ,
' JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) ' STATIONS USED' BACRGROUND-MEAN(N/ TOTAL)~ 0F
~
RANGE- RANGE FOR INDICATOR ANALYSES MEAN~ PERFORMED- STATION STATION-MEAN(N/ TOTAL) RANGE-CABBAGE- GAMMA CS-134 11 2.13E401~ < LLD (0 /8 ) < LLD (O'/3 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) CABBAGE . GAMMA CO-58 '11 1.88E+01 < LLD (0 /8:) < LLD (0 /3 ) 35' 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) CABBAGE GAMMA MN-54 11 1.94E+01 < LLD (0 /8 ) < LLD (0 /3') 35 66
-(PCI/KG(UET))
66 < LLD (0 /4-) CABBAGE GAMMA FE-59 11 4.96E+01 < LLD (0 /8 ) < LID (0 /3 )- 35 66 (PCI/KG(WET)) '- 66 < LLD.(0 /4 ). CABBAGE GAMMA CS-136 11 2.39E+01 < LIB (0 /8 ). < LLD -(0 /3 ) 35 66 (PCI/KG(UET)) 66 < LLD (0 /4 ) CABBAGE GAMMA TE-132 11 :4.1IE+01 < LLD (0 /8.) < LLD .(0 /3.) 35 66 (PCI/KG(WET)) 66- < LLD-(O /4 )
, _ 1 _ . _ _ - . . . _ - - . - _ , . . . . __a., --._,...-_._..__=-_z._ _ . . . . . . , _ . u..-,....,. - _,- 2_ a . . . - . _ _ . _ . . . .u
TABLE 3' RADIO 1DGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION
' JANUARY,1989 THROUGH DECEMBER,'1989 ANNUAL
SUMMARY
l SAMPLE TYPE ANALYSIS ISOTOPE NUMBER -LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) . STATIONS USED : OF RANGE RANGE FOR Ib1DICATOR ~ l ANALYSES . MEAN -- PERFORMED STATION -STATION-MEAN(N/ TOTAL) RANGE i CABBAGE GAMMA ZN-65 11 5.95E+01 L< LLD (0 /8 ) < LLD (0 /3 ) 35 66 (PCI/KG(UET)) 66 < LLD (0 /4 ) CABBAGE GAMMA CO-60 '11 2.51E+01 < LLD (0 /8 ) < LLD -(0 /3-) 35' 66 (PCI/KG(WET)) i 66 < LLD (0 /4 ) CABBAGE GAMMA K-40 11 1.80E+02- 4.00E+03 (8 /8 ) 2.09E+03(3 /3 ) 35 66 (PCI/KG(UET)) ( 2.19E403 -'5.58E403) ( 1.42E+03 - 3.11E+03) ! 35 4.90E+03(4 /4 )
-( 2.99E403 - 5.58E+03)
CABBAGE GAMMA BE-7 11 1.37E+02 2.95E+02 (2 /8 ) < LLD .(0 /3 ) 35 66 (PCI/KG(UET)) ( 2.75E+02 - 3.16E402) 66 3.16E+02(1 /4 ) ( 3.16E+02 - 3.16E402) CABBAGE GAMMA ZR-95 11 3.29E401 < LLD (0 /8 ) < LLD -(0 /3 ) 35 66 (PCI/KG(UET)) 66 < LLD (0 /4 ) CABBAGE GAMMA NB-95 11 1.83E+01 < LLD_ .(0 /8 ) < LLD (0 /3 ) 35 66 (PCI/KG(UET)) 66 -< LLD (0 /4 )
'C_al*.'- - _ _ _ - . _ _ _ _ _ . -'*i I'1 # '
E '
LM M ;Wi :M : W- M W' W 'W . W " W .. W W W W W
.. TABLE 3-RADIO 1DGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION
-JANUARY,1989 THROUGH DECEMBER,1989 .
~'
ANNUAL
SUMMARY
SAMPLE TYPE. ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL): 2 STATIONS USED OF RANGE RANGE- FOR INDICATOR? ANALYSES .MEAN PERFORMED STATION. STATION-MEAN(N/ TOTAL) r RANGE CABBAGE GAMMA SB-125 11 3.95E+01 < LLD (0 /8 ) < LLD (0 /3 ) 35 66 (PCI/KG(UET)) 66 < LLD (0 /4 ) CRIBBAGE GAMMA CE-141 11 1.97E401 < LLD (0 /8 ) < LLD (0 /3 ) 35 66 (PCI/KG(WET)) 66 ~ < LID (0 /4 ) CABBAGE GAMMA ItU-103 *11 1.58E+01 < LLD (0 /8 ) < LLD (0 /3 )' 35 66 (PCI/KG(UET)) 66 < LLD (0 /4 ) CABBAGE GAMMA CR-51 11 1.22E+02 < LLD (0 /8 ) < LLD (0 /3') 35 66 si (PCI/KG(UET)) ^ 66 <lLLD (0 /4 ) CABBAGE GAMMA BA-140 11 7.60E+01 < LLD (0 /8 ) < LIE -(0 /3 ) 35: 66 (PCI/KG(WET)) 66 < LLD (0 /4 )
~
CABBAGE GAMMA 1A-140 -11 3.16E+01 < LLD (0 /8 ) ' < L1h (0 /3 ) 35 66 (PCI/KG(UET)) 66 .< LLD (0 /4 ) . 5 _, _ , - _ m_. _ ...w.. _ _ _ , . . . _ . , ,_.
y._ . _ . ,
: .~
f- ;
^
1ll . TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
- SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL)'~ BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANCE FOR INDICATOR ANALYSES' MEAN PERFORMED STATION- STATION-MEAN(N/ TOTAL) l RANGE
' CABBAGE - GAMMA AC-228 11- 7.46E+01- '< LLD (0 /8 ) - < LID (0 /3_.) 35' 66 (PCI/KG(WET))
66 ' < LID (0 /4 ) CABBAGE GAMMA RA-224 11 9.41E+02 < LLD (0 /8 ) < LLD (O./3 ) 351 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) CABBAGE GAMMA RA-226 11 2.84E+02 < LLD (O /8 ) < LLD- (0 /3 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4~)- CABBAGE GAMMA I-131 11 2.18E+ 01- < LLD (0 /8 ) < LLD . (0 /3 ) 35 66-(PCI/KG(WET)) 66 < LLD (O./4..). CAB 3 AGE GAMMA NA-22 11 2.73E+01 < LLD .(0 /8 ) < LLD.. (0 /3-) 35 66 (PCI/KG(WET)) 66 < LID (0 /4 ) CABBAGE GAMMA RU-106 11 1.57E+02 < LLD (0 /8 ) <7 LID (0 /3 ). :35 66 (PCI/KG(WET)) 66 < LLD-(0 /4').
~ . . - . _ . .. . - , - - . .- ,_ ..= . ..- - - - .=- _ . . - - - - .- _ . . -
, . ~ _ . .mv v; :- =gy
.@: E',
,h' ;M .- -
~
+t.4 TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION-JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) . STATIONS USED OF ~ RANGE RANGE ~ FOR INDICATOR-ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE CABBAGE - GAMMA CO-57. 1.01E+01 11 < LLD (0./8 ) < LLD (0 /3 ) 35 '66 (PCI/KG(WET)) 66 < LLD (0 /4 )- CABBAGE GAMMA 11 3.10E+03 I-133 < LLD (O /8 ) < LLD (0 /3 ) 35 66 (PCI/KG(WET)) 66 < LIE (0 /4 ) CABBAGE GAMMA CS-137 11 1.84E+01 < LLD (0 /8 ) < LIE -(O'/3 ) 35 66. (PCI/KG(WET))
'66 < LLD (0 /4 )
SURFACE WATER CAMMA -CE-144 104 2.22E+01 < LLD (0 /78 ) <.LLD .(0 /26 ) 23 24. 25 32 (PCI/L) - 93 93 '< LLD (0 /13 ) SURFACE WATER GAMMA AG-110M 104 3.79E+00 < LLD (0 /78') < LIB (0 /26 ) 23 24. 25 32' (PCI/L) 93 93 < LLD (0 /13 ) SURFACE WATER GAMMA TE-129M 104 1.58E+03 < LLD (0 /78 ) < LLD (0 /26 ) 23 24- 25. 32 (PCI/L) . . 93 93 < LLD (0 /13.) 8
. _ . , - . _ . , . _ , + --, - - - , - . , . , . ..-~--w - ., . , . . , rv.-_.,.-s - s . , . . .
- 1.m r m . . . . . .
TABLE.3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM EUMMARY OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989
~ ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LIB INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANCE FOR. INDICATOR ANALYSES . MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SURFACE WATER GAMMA CS-134 104 5.58E+00 < LLD' -(0 /78 ) < LLD (0 /26 ) 23 24f 75 32' (PCI/L) 93 93- < LLD (0 /13 ) SURFACE WATER GAMMA CO-58 104 4.35E+00 < LLD (0 /78 ) < LLD (0 /26') 23 24 25 32 (PCI/L) 93 93 < LLD (0 /13 ) SURFACE WATER GAMMA MN-54 < LLD (0 /78 ) 104 4.28E+00 < LLD (0 /26 ) 23 :24 -25 32 (PCI/L) 93 93 .< LLD (0 /13.) SURFACE WATER GAMMA FE-59 104 9.52E+00 -< LLD (0 /78 ) < LLD. (0 /26 ) 23 24 25 32 (PCI/L) .. ~
-93 93 < LLD (0 /13 )
l SURFACE WATER GAMMA CS-136 104 5.00Et00 < LLD (0 /78 ) < LIB (0 /26 ) 23 .241 5 32 l (PCI/L) 93 93 '< LLD (0 /13 ) SURFACE WATER GAMMA TE-132 104 8.37E+00 < LLD (0-/78 ) < LIE (0 /26.) 23 24 25' 32 (PCI/L) 93 93 < LLD (0 /13 )
M.' M t M : W :. W : W : W [ M W W W ~_ W ."; W : E W-M M . M -L , W '
-. - u.; ,
TABLE l3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAFPLE TYPE ANALYSIS ISOTOPE NUMBER LLD . INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED
~~
OF RANGE RANGE FOR INDICATOR ANALYSES MEAN ' PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE
- i SURFACE
- WATER GAMMA ZN-65 104 1.31E+01- < LLD (0 /78.) < LIE (0 /26.) 23 24 25 .32 -
93 < LG (0 /13 ) SURFACE WATER GAMMA CO-60 104 5.27E+00 < LLD (0 /78 ) < LLD .(0 /26 ) 23 24 25 '32 L (PCI/L) 93 93 < LLD.(0 /13-) SURFACE WATER GAMMA K-40 104 3.87E+01 1.99E+02 (76 /78 ) 2.49E+02(26 /26 ) 23 24- 25 32' (PCI/L) ( 4.19E+01 - 3.32E+02) ( 1.73E+02 - 3.41E+02). 93 25 2.32E+02(13 /13 ) ( 1.74E+02 - 3.32E+02) SURFACE WATER GAMMA BE-7 104 3.14E+01 < LLD (0 /78 ) < LLD (0 /26 ) 23 24 25- 32 (PCI/L) 93 93 < LLD (0 /13 ) SURFACE WATER GAMMA ZR-95 104 7.34E+00 < LLD (0 /78 ) < LLD (0 /26 ) 23 24 25. 32-(PCI/L) 93 93 < LIE (0 /13 ) SURFACE WATER GAMMA NB-95 104 4.28E400 < LLD- (O /78 ) .< LLD (0 /26.) 23. 24~ 25 32 (PCI/L) 93 93 .< LLD (0 /13 ) 7
- 5 3 - .. -
. - - . , , , . . ,, . - . . - - , . - . . -n . .- ; .. - -. . . .; z,.- - ~ a , ;. n ;a .
-. -~ .. . . _
y f W ~WL M 5 3 W !L M 'W_W, W ..( W ,' W i) W W - W M [.[W W WL M' E
' TABLE 3 RADIO 1DGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989.- ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL). BACKGROUND-MEAN(N/ TOTAL) STATIONS USED' 0F RANGE RANGE FOR INDICATOR-ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SURFACE WATER GAMMA SB-125 104 9.93E+00 < LLD -(0 /78 ) < LIE (0 /26 )- 23 '24'~[25 32-(PCI/L) 93 93 < LLD (0 /13 ) SURFACE WATER GAMMA CE-141 104 5.43E400 < LLD (0 /78 ) < LLD (0 /26 ) 23 24~ 25':32 (PCI/L) 93 93 < LLD (0 /13 )- SURFACE MATER GAMMA RU-103 104 4.0SE+00 - < LLD (0 /78 ) '< LID (0 /26 ) 23. 24 25 '32 (PCI/L) . . 93 93 < LID (0 /13 ) SURFACE WATER GAMMA CR-51 104 3.12E401 ~< LLD- (0 /78 ) < LID (O /26 ) 23 24 25 32-(PCI/L) 93 93 < LLD (0 /13 ) SURFACE WATER GAMMA BA-140 104 1.63E+01 < LLD: (0 /78 ) < LLD (0 /26 ) 23 24 25 32-(PCI/L) 93 93 < LLD (0 /13 ) SURFACE WATER GAMMA 1A-140 104 7.63E+00 < LLD (0 /78-) < LLD (0 /26 ) 23 24 25 32 (PCI/L) 93 93 < LLD.(0 /13 ) E _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____________:_: :-= . a ~ ,-;. a .. - - ,, - . .:
+ _ g-l
.. c -
o c
-TABLE.3 RADIOLOGICAL' ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER. CREEK NUCLEAR GENERATING STATION-JANUARY,1989 THROUGH DECEMBER,1989
- ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER 'LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) . . STATIONS USED -
~
OF RANGE' RANGE FOR' INDICATOR ANALYSES MEAN PERFORMED STATION .- STATION-MEAN(N/ TOTAL) RANCE SURFt.CE.UATER GAMMA AC-228 104 1.63E+01 < LLD (0 /78 ) < LLD '(0 /26 ) 23 24 25 32: (PCI/L) 93 , 93 < LLD (0 /13 ) SURFACE WATER GAMMA RA-224 .(O /78 ) 104 1.96E+02 < LLD < LLD (0 /26 ) 23 24 25 32-(PCI/L) 93-93 < LLD (0 /13 ) SURFACE WATER GAMMA RA-226 104 8.21E+01 < LLD (0./78 ) < L1D (0 /26 ) 23 24 25 32 (PCI/L) 93 93 < LLD-(0 /13 ) SURFACE WATER GAMMA I-131 104 9.54E+01 '< LLD (0'/78 ) < LLD (0 /26 ) 23 24 ^25 32' (PCI/L) 93 i
-93 < LLD (0 /13 )'
SURFACE WATER GAMMA NA-22 104 5.26E+00 < LLD (0 /78 ) < LLD (0 /26 ) 23 24 25 32 (PCI/L) 93 93 < LLD'(0 /13 ) SURFACE WATER GAMMA -RU-106 104 3.56E+01 < LLD (0 /78 ) < LLD' (0 /26 ) 23 24 25: 32 (PCI/L) 93 'i
'h
... ___ _ . ..- - - ~. - :. .--;,_ . ,, .-- .
,__ ~
. J - . -
z.. - - T TABLE 3 RADIOIJ0GICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
~
OYSTER' CREEK NUCLEAR GENERATING STATION : JANUARY,1989 THROUGH DECEMBER,1989' ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL)- STATIONS USED.. OF RANGE RANGE FOR INDICATOR-ANALYSES MEAN PI'RFORMED STATION' STATION-MEAN(N/ TOTAL) -A RANGE' SURFACE WATER GAMMA CO-57 104 2.94E+00 < LLD (0 /78 ) 23 24 J25' 32!
< LLD (0 /26-)
(PCI/L) 93 93 .< LLD (0 /13 ) e SURFACE WATER GAMMA I-133 104 3.38E+02 < LLD (0 /78 ) .< LLD (0 /26 ) 23 24 25 32
.(PCI/L) _
93 93 < LLD (0 /13 ) SURFACE WATER GAMMA CS-137 104 4.22E+00 '< LIE (O /78 ) < LLD (0 /26 ) 23 24 25 .32 (PCI/L) 93 93 < LIE (0 -/13 ) SURFACE WATER TRITIUM 104 1.50E+02 1.64E+02 (5 /78 ) (PCI/L)
< LLD (0 /26 ) 23. 24 25 32L
( 1.50Et02 - 1.75E402) . 93 33 1.75E+02(1 /13 ) ( 1.75E+02 - 1.75E402) COLLARD GAMMA CE-144 14 7.23E+01 < LLD (0 /9-) _ < LLD- (0 /5.) 35 66 (PCI/KG(UET)) 66 < LLD (0 /4 ) COLLARD GAMMA -AG-110M 14 1.95E401 < LLD. (0 /9 ) < LLD (O /5 ). 35 66 (PCI/KG(WET)) 66 < LLD.(0 /4 )-
..- . . _ . . . . ___ _ _ _ ._ , . . cu .- ,. _ . . . . . . :_ _ n .. . - _ . _ . .- ,
_ _. . . n .-
+
w-TABLE.3-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER' CREEK NUCLEAR GENERATING STATION
-JANUARY,1989.THROUGH DECEMEER,1989
' ANNUAL
SUMMARY
. SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE- . FOR ' INDICATOR ...
ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE COLLARD GAMMA TE-129M 14 1.62E+04- < LLD (0 /9 ) < LLD.' (0 /5 ) 35 66 (PCI/KG(WET)) 66 < LIE (0 /4 ) COLMRD GAMMA CS-134 -14 2.19E+01 < LLD (0 /9 ) .:< LLD (0 /5 ) 35 66 (PCI/KG(WET)) 66 < LIA (0 /4 ) COLLARD GAMMA CO-58 14 2.01E+01 < LLD (0~/9-) '< LLD (0 /5 ) 35 66 l (PCI/KG(WET)) l 66 < LLD (0 /4 ) COLuRD GAMMA MN-54 14 2.03E+01 < LLD (0./9 ) < LLD (0 /5 ) 35 66-t (PCI/KG(WET)) l 66- < LLD (0 /4 ) l COLLARD GAMMA FE-59 14 5.46E+01 < LLD (0 /9 ) < LLD (0 /5 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4.) i l i COLLARD GAMMA CS-136 14 2.54E+01 < LLD (0 /9 ) < LLD (0 /5 ) '35' 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) i ! __ _ _ _ _ _ - _ _ _ _ __ _ _ __ _____. ~ _- -- -
- . -- -- - . - . .- - --- , -, - - ~.-
y 2
.. cx .. -
~;
}.
n,- TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH-DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) . BACKGROUND-MEAN(N/ TOTAL) STATIONS USED-0F RANGE RANGE- FOR INDICATOR ANALYSES MEAN-PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE COLIARD GAMMA TE-132 14 4.39E+01 < LLD (0 /9 ) < LLD. (0 /5 ). ~35 66' (PCI/KG(WET)) 66 '< LLD (0 /4,) COLLARD GAMMA ZN-65 14' - 6.97E+01 < LLD (0 /9 ) < LLD (0 /5 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) COLIARD GAMMA CO-60 14 2.62E+01 < LIB (0 /9 ) < LLD (0 /5 ). 35 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) COLLARD GAMMA K-40 14 1.80E+02 4.55E+03 (9 /9 ) ~4'.38E+03(5 /5 ) 35 66 - (PCI/KG(WET)) ( 3.46E+03 - 6.32E+03) ( 3.60E+03 - 4.92E+03) t 35 5.07E403(5 /5 ) ( 4.11E+03 - 6.32E+03) COLIARD GAMMA BE-7 14 1.26E+02 5.31E+02 (2 /9 ) < LLD (0 /5 ) 35 66 (PCI/KG(WET)) ( 4.22E+02 - 6.41E402) 66 6.41E402(1 /4 ) ( 6.41E+02 - 6.41E+02) COLLARD GAMMA ZR-95 14 3.63E+01 < LLD (0 /9 ) < LID (0 /5 ) ' 35' 66 (PCI/KG(WET)) *
. - .. . . . -- . - . - -. . ,. - - , , . _ . ~-- . . . ,
E E' E E E E l W i~ E E , EE.E'E:W _. E E EE TABLE 3- " RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989:THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR-INDICATOR ANALYSFS MEAN TERFORMED- STATION- STATION-MEAN(N/ TOTAL) RANGE COLIARD GAMMA NB-95 14 2.00E+01 < LLD (0 /9 ) < LLD (0-/5 ) 35 66 (PCI/KG(WET))
< LLD (0 /4 )
66 COLLARD GAMMA SB-125 14 3.95E+01 (0 /9 )
< LLD < LLD (0 /5 ) 35 66 (PCI/KG(UET))
66 < LLD (0 /4 ) I COLIARD GAMMA CE-141 14 1.88E+01 < LLD (0 /9 ) < LLD 35 66 (0 /5 ) (PCI/KG(WET)) 66 < LLD (0 /4 ) COLIARD GAMMA -RU-103 14 1.69E+01 (0 /9 ) (PCI/KG(WET))
< LLD < LLD (0 /5-) 35 66-66 < LLD (0 /4 )
COLIARD GAMMA CR-51 14 1.23E402 <.LLD -(0~/9 ) < LLD (0 /5 ) 35 66 (PCI/KG(UET)) 66 < LLD (0 /4.) COLLARD GAMMA BA-140 14 7.17E+01 < LLD (0 /9 ) < LLD - (0 /5 )- 35 66 (PCI/KG(WET)) 66 < LLD (0 /4-)
- 2
~ . . , w.. .--.(-,~-. ..w. n .r-.~e, r- -- ~ ~-~r-,,# ~-us< m - - ~ * - ~ ~ ~ ~ ~ ' - -e-="" v"'~-
r- ~~'s * ' - " " " ~ ' ' " * * ' * ' * * ' ' '* ~" *
. ,_. ---x---------- -- . - - - - - - - - - - - - - -
..-g
. I '
L Aj TABLE 3 RADI0IEGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989~THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL)' BACKGROUND-MEAN(N/ TOTAL) STATIONS USED. OF . RANGE . RANGE FOR-INDICATOR' ANALYSES .
..MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE COLIARD - GAMMA LA-140 14 3.11E+01 < LLD (0 /9-) < LLD (0 /5 ) 35 66' (PCI/KG(UET)) 66' < LLD (0 /4 ) COLIARD GAMMA AC-228 14 8.02E+01 < LLD < LLD (0 /9 ) (0 /5 )' 35 66 (PCI/KG(WET)) 66 < LIE (0 ' /4 ) COLIARD GAMMA RA-224 9.51E+02 14 < LLD (0 /9 ) < IID (0 /5 )' 35 66: (PCI/KG(UET)) 66 <:LLD (0 /4 ) COLLARD
~
GAMMA RA-226 14 2.72E402 '<-LLD (0 /9 ) < LID '(0 /5') 35 '66 (PCI/KG(UET)) ' 66 < LLD (0 /4 ) COLLARD GAMMA 2.34E401 I-131 14 < LLD (0 /9 ) < LID (0 /5 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) COLLARD GAMMA NA-22 14 2. 98E401 < LLD (0 /9.)- '< LLD (0 /5 ) .35 66 (PCI/KG(UET)) 66 < LIE (0 /4 )
. : , .. . . _- . , , . . ;- - - - = . . ,. : _ . - . , _ . . . =-a
- ,q
_ W' m M LW W W-W.~W W M EW L W , m' :W W W W WJ W ' TABLE.3-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
~
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989.THPOUGH DECEMBER,1989
. ANNUAL'
SUMMARY
-SAMPLE TYPE- ANALYSIS ISOTOPE NUMBER LLD- INDICATOR-MEAN(N/ TOTAL)_'
BACKGROUND-MEAN(N/ TOTAL) . STATIONS USED-OF
~
RANGE RANGE FOR INDICATOR.
- ANALYSES - MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE COLIARD - GAMMA RU-106 1.58E+02 14 < LLD' (0 /9 ) < LLD (0 /5 ) 35 66 (PCI/KG(WET)) 66 < LLD (0 /4 ) COLIARD GAMMA CO-57 9.48E+00 14 < LLD (0 /9 ) < LIE (0 /5 ) 35. 66-(PCI/KG(UET)) 66 < LLD (0 /4 ) COLLARD GAMMA I-133 14- 4.66E+03 < LLD < LLD (0 /9 ) (0 /5 ) 35 66 i (PCI/KG(UET)) 66 < LLD (0 /4 ) l l COLLARD' GAMMA CS-137 14 1 84E+01. 2.81E401 (2 /9 ) < LID (0 /5 )- 35 66 (PCI/KG(UET)) ( 1.95E+01 - 3.68E401) ( 1.95E401 - 3.68E+01)- WELL VATER GAMMA CE-144 2.23E+01 72 < LLD (0 /59 ) < LLD (0 /13 ) l' 19 20 21 (PCI/L) l 22 < LLD (0 /12 ) l WELL WATER f:AMMA AG-110M 72 3.79E+00 < LLD (0 /59 ) < LID (0 /13 )_ 1 19 20 21' l (PCI/L) 22 < LLD (0 /12 )' 5 L-,.%- ._.:-me ...-m.%s.,w.w . _...e_.y_d. --- _t-E- -wrn. -
-m..
. , - g g ;.g-
~
W TABLE.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION ~ JANUARY,1989 THROUGH DECEMBER,1989-
' ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) STATIONS USED BACKGROUND-MEAN(N/ TOTAL)- OF RANGE RANGE FOR INDICATOR ANALYSES MFAN l PERFORMED STATION - STATION-HEAN(N/ TOTAL) RANGE WELL WATER GAMMA TE-129M 72 1.57E+03 < LLD (0 /59-) < LLD (0 /13 ) 1 19 -20 21 l (PCI/L) 22 < LLD (0 /12 ) WELL WATER GAMMA CS-134 72 6.23E+00 (0 /59 ) ,. < LLD < LLD- (0 /13 ) 1 19 20 21 l (PCI/L) [ 22 < LLD (0 /12 ) WELL MATER GAMMA CO-58 72 4.42E+00 (0 /59 ) < LLD
< LLD (0 /13 ) 1 19' 20 21 (PCI/L) 22 < LID (0 /12 )
WELL MATER GAMMA MN-54 72- 4.30E+00 < LLD (0 /59 ) < LLD .(0 /13-) 1 19 .20 21 (PCI/L) 22 < LID (0 /12 ) WELL UATER GAMMA FE-59 72 9.19E+00' (0'/59 )
< LLD < LID (0 /13 ) 1 19 20 21-(PCI/L) 22 < LLD (0 /12 )
UELL MATER CAMMA CS-136 72 5.02E+00 < LLD (0 /59 ) < LID (0 /13 ); 1 19 20 21 r (PCI/L) 22 < LLD (0 /I2 )
- 4. , ,- w__ _[ ~ . _ _ . _ _ _ - _ -, _ .-. .,_, _ _ -.- _ ,s -_'
. ,; ,- .n g
^
. y .-
e ~
. ; .l
' TABLE 3
' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989.THROUGH DECEMBER,1989
' ANNUAL
SUMMARY
. SAMPLE TYPE ANALYSIS ISOTOPE NUMBER- LLD INDICATOR-MEAN(N/ TOTAL)~ STATIONS ~USED ~
BACKGROUND-MEAN(N/ TOTAL)- OF RANGE '
' RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE WELL WATER GAMMA TE-132 72 8.22E+00 < LLD (0 /59 ) < LLD. (0 /13 ) 1 19 20' 21 (PCI/L) 22 < LLD (0 /12 ) UELL WATER GAMMA ZN-65 72 1.37E401 (0 /59.)
< LLD . < LLD (0 /13 ) 1 19 20. 21 (PCI/L) 22 < LLD (0 /12 )
WELL WATER GAMMA CO-60 72 5.27E400- (0 /59 )
< LLD < LLD (0 /13 ) l' 19 20 21 (PCI/L) 22 < LLD (0 /12 )
WELL WATER GAMMA K-40 72 5.69E+01 < LLD (0 /59 ) < LID (O /13 ) 1 19 20 21 (PCI/L) 22 < LLD (0 /12 ) l l UELL WATER GAMMA OE-7 72 3.17E401 < LLD (0 /59 ) < LLD (0 /13 ) 1 19 20 21
- (PCI/L) 22- - < LLD (0 /12 )
WELL WATER GAMMA ZR-95 72 7.32E+00 < LID (O./59 ) <~LLD- :(C /13 ) 1 19 20 21 (PCI/L) 22 < LIE (0 /12.) _ -. , ._ - _ . . _ s _ ._.w... _-. . _ . _ _ , . , , . _ . - , , , __a . . . . ~ . _ . . . . _ . . _ . ~ _ . . _ __ . _ , _ -
u .. :- . - . , z. - - ~ W? W M LE E ;W- [W . E W E E M ~E E'E E E E: E
?.
. TABLE 3 RADIGIDGICAL' ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989.- ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER. LLD. INDICATOR-MEAN(N/ TOTAL) STATIONS USED-BACKGROUND-MEAN(N/ TOTAL) OF . RANGE' RANGE FOR INDICATOR ^ ANALYSES' MEAN PERFORMED STATION- STATION-MEAN(N/ TOTAL) RANGE
'NB-95 WELL UATER GAMMA 72 4.33E+00 (0 /59 )
<-LLD < LLD (0 /13 ) 1 '19 .20'.21
*(PCI/L) 22 < LID (0 /12 )
WELL VATER GAMMA SB-125 72 9.94E+00 (0 /59 )
< LLD < LIE (0 /13 ) 1 19 20 21t (PCI/L) 22 < LID (0 /12 )
UELL WATER GAMMA CE-141 72 5.51E+00 (0 /59 )
< LLD . < LLD (0 /13 ) 1 19 20 21 -
(PCI/L) 22 < LLD (0 /12 ) WELL UATER GAMMA RU-103 72 4.14E+00 < LLD (0 /59 ) < LLD (0 /13 ) 1 19 20 21-(PCI/L) ' 22 < LLD (0 /12 ) UELL WATER GAMMA CR-51 72 3'13E+01 (0 /59 ) (PCI/L)
< LLD < LLD (0'/13 ) 1 19 20 21 22 .< LLD (0 /12 )
WELL UATER GAMMA BA-140 72 1.64E+01 (0 /59 ) (PCI/L)
< LLD < LLD (0 /13 ) 1 19 20 21 22 <'LLD (0 /12 )
_ _ . - . _ _ . _ _ , _ , . , ,w , , _ _,, a _ - . _ ~ . . . ._.,_; w . , , - . . . . . _ _ _ . _ . . _ _ . _
u ,. _M M M M M M 'M M M M M' & M M -~ M ^ W M M S' TABLE.3
' RADIOIDGICAL' ENVIRONMENTAL' MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION
~ JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD- INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL)- STATIONS USED'.
'OF RANGE- RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION-. STATION-MEAN(N/ TOTAL)
RANGE UELL WATER GAMMA IA-140- 72 7.64E+00 ' < LIE ' (PCI/L)
.(0'/59 ) < LID (0 /13 ) 1 19' -20 21' 22 < LLD (0 /12 )
WELL WATER GAMMA AC-228 72 1.61E+01 < LLD '(0 /59 ). < LLD (0 /13 ) 1 19 20 21 (PCI/L) 22 < LLD (0 /12 ) WELL UATER GAMMA RA-224 72 1.93E+02 < LLD (0 /59 ) < LIE (0 /13 ) 1 19 20 21 (PCI/L) 22 < LLD (0 /12 ) UELL UATER CAMMA RA-226 72 8.20E+01 < LLD (0 /59 ) < LLD (0 /13-) 1 19 20 21 (PCI/L) 22 < LLD (0 /12 ) UELL UATER GAMMA I-131 72 9.18E+01 < LLD (PCI/L) (0-/59 ) < LID (0 /13 ) 1 19 20 21 22 < LLD (0 /12 ) WELL WATER GAMMA NA-22 72 5.13E+00 < LLD (0 /59 ) < LLD (0 /13.) 1 19 20 21-(PCI/L) 22 < LLD (0 /12 ) l _ __ a __
TABLE 3 RADIOIAGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER' CREEK NUCLEAR GENERATING STATION JANUARY,1989.THROUGH DECEMBER,1989 . ANNUAL
SUMMARY
' SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD , INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED. -
0F RANGE RANGE FOR INDICATORi ANALYSES MEAN-PERFORMED STATION . STATION-MEAN(N/ TOTAL) RANGE 3.56E+01 < LLD (0 /59 ) < LLD (0 /13-) 1 19 .20 21-WELL UATER GAMMA RU-106 ' 72 (PCI/L) 22 < LIE (0 /12 ) WELL WATER GAMMA CO-57 72 2.94E+00 < LLD (0 /59 ) < LLD (0 /13 ) 1 l9 20 21 . (PCI/L) 22 < LLD (O'/12-) UELL VATER GAMMA I-133 72 3.12E402 < LLD (0 /59 ) < LLD (0 /13 ) 1 19 20 '21-(PCI/L) 22 < LLD (0 /12 )- WELL WATER GAMMA CS-137 72 4.38E+00 < LLD (0 /59 ) < LID (0 /13 ) 1 19 20 21 (PCI/L) 22 < LIE (0 /12 ) WELL WATER TRITIUM ^72 1.50E+02 2.04E+02 (2 /59 ) 1.45E+02(1 /13 ) 1. 19 20 21 (PCI/L) ( 1.78E+02 - 2.30E+02) ( 1.45E+02 - 1.45E+02). 20 2.30E+02(1 /10 ) ( 2.30E+02 - 2.30E+02) BLUE CRAB GAMMA CE-144 13 8.38E+01 < LLD (0 /9 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET))
'93 < LLD (0./4 ).
l
_ fmg lE EE S E E E. E E. ' O; E U W ~ W TE' E O Ej E.! TABLE ~3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR. GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS -ISOTOPE NUMBER LLD . INDICATOR-MEAN(N/ TOTAL) STATIONS USED. BACKGROUND-MEAN(N/ TOTAL) OF RANGE RANGE FOR INDICATOR ANALYSES MEAN. PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE BLUE CRAB GAMMA AG-110M 13 1.96E+01 -< LLD (0 /9 ) < LID 33 93 (0 /4 ) (PCI/KG(WET)) 93 < LLD-(0 /4-) BLUE CRAB GAMMA TE-129M' 13 1.90E+04 < LLD (O /9 ) < LLD 33 93~ (0 /4 ) (PCI/KG(WET)) 93 < LLD (0 /4 ) BLUE CRAB GAMMA CS-134 13 2.95E+01 < LLD (0 /9 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) .. 93 < IJD (0 /4 ' ) BLUE CRAB GAMMA CO-58 13 2.25E+01 < LLD (0 /9 ) < LLD -(0 /4 ) 33 93; (PCI/KG(WET)) 93 < LLD (0 /4 ) BLUE CRAB GAMMA MN-54 13 2.13E+01 (0 /9 )
< LLD < LID - (0 /4 ) 33 93 (PCI/KG(WET))
93 ..< LID (0 /4 ) BLUE CRAB GAMMA FE-59 13 5.51E+01 < LLD '(0 /9 ) < LLD (0 /4 )- 33 93 (PCI/KG(WET)) 93- < LLD (O./4 ) t W. _ . _ . . _ . _ . . _ . , .,..u., , __ , _ ., .;~.~.,, __1..,_,._., ,.,:.-,_.'
...,.A . , , _ . . _ . _ _ . . .. . A ,m . . . _ ,
.- .; - _, -p W W W: W' W: W. . E L W E ~MI M S -
W W M' W M M W_ s i l TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,~1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL)'- STATIONS USED BACKGROUND-MEAN(N/ TOTAL) OF ' RANGE RANGE. FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE BLUE CRAB GAMMA CS-136 -13 2.96E+01 < LLD (0 /9.-) < LID (0 /4 ) 33 93 (PCI/KG(WET)) l 93 < LLD (0 /4 )
- BLUE CRAB CAMMA TE-132 13 5.18E+01 (0./9 )
< LLD < LLD (0 /4 ) 33: 93 (PCI/KG(WET))
~
93 < LLD (0 /4 ) BLUE CRAB GAMMA ZN-65 13 7.92E401 < LLD. (0 /9 ) < LLD (0 /4 )' 33 93 (PCI/KG(WET)) 93 < LLD (0 /4 ) BLUE CRAB GAMMA CO-60 13 2.83E+01 < LLD ^ (0 /9 ) < LLD (0 /4 ) 33 93. (PCI/KG(WET)) - 93 < LIE (0 /4 ) BLUE CRAB GAMMA K-40 13 1.80E+02 2.67E+03 (9 /9 ) 2.73E+03(4 /4 ) 33 93 (PCI/KG(WET)) ( 2.39E+03 - 3.13E403) ( 1.99E+03 - 3.13E+03) 93 2.77E+03(4 /4 ) ( 2.39E+03 - 3.13E+03) BLUE CRAB GAMMA BE-7 13 1.51E+02 (0 /9 ) (PCI/KG(WET))
< LLD < LID '(0 /4-) 33 93 93 < LLD (0 /4 )'
e
'-68. -.-%.. . _ . - m -
- g. ,._q g-v ,
, . , , _ _ _ _ _. _ _ - _ _ _ - , _ _ . ______;___._____ _ _ .f.. , . . _ _ _ _ _ _ _ . , , . _ , ,_,_,.)
- ame aus. sus sus aus ans en- ami sus: ame ass -ass aus e sus asp ' ass: sus aus TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED: OF RANGE RANGE FOR INDICATOR-ANALYSES : MEAN PERFORMED . STATION _ STATION-MEAN(N/ TOTAL)
-RANGE BLUE CRAB GAMMA ZR-95 13 3.70E+01- < LLD~ (0 /9 ) < LLD ~ (O /4 ) 33 '93 (PCI/KG(UET))
93 < LLD (0 /4 ) BLUE CRAB GAMMA NB-95 13 2.31E+01 < LID (0 /9 ) < LLD (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LIE (0 /4 ) BLUE CRAB GAMMA .SB-125 13 4.70E+01 < LLD (0 /9 ) < LLD (0 /4^) 33 93 (PCI/KG(UET)) .. 93 < LLD (0 /4 ) SLUE CRAB GAMMA CE-141 13 2.19E+01 < LLD (0 /9 ) < LLD (0 /4 ) 33 93 (PCI/KG(UET)) ~ 93 < LIE (0 /4')
~
BLUE CRAB GAMMA RU-103 13 1.87E+01 < LLD (0 /9 ) '< LLD (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LLD (0 /4 ) BLUE CRAB GAMMA CR-51 13 1.45E+02 < LLD (0 /9 ) -< LLD (0./4 ) 33' 93 (PCI/KG(UET)) 93 .< LLD (0 /4 )
. 69-
' ' ~ ~ ~ ~ ' ~ ~
. -- . - . - ---,- - ~~-
- - - -~ ~ ~ --
m -, E E E 'E..E E :E M E O [$ 6 W E S E E O l l I l TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION
- l. JANUARY,1989'THROUGH DECEMBER,1969
! 1 ANNUAL
SUMMARY
l SAMPLE TYPE ANALYSIS - ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED. i 0F- RANGE RANGE L FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE l l BLUE CRAB GAMMA BA-140 13 8.55E+01 (0 /9 )
~
-< LLD < LLD '(O /4 ) 33 93 (PCI/KG(UET))
93 < LLD (0 /4 ) BLUE CRAB GAMMA LA-140 3.92E+01 < LLD - (0 /9 ) 13_ < LLD (0 /4 ) 33 93 { (PCI/KG(WET)) 03 -< LLD (0 /4 ) BLUE CRAB GAMMA AC-228 13 8.81E+01 < LLD (0 /9-) < LLD (0 /4 ) 33 - 93 (PCI/KG(WET)) 93 < LLD (0 /4 ) -i BLUE CRAB GAMMA RA-224 13 1.20E+03 (PCI/KG(WET))
< LLD (0 /9 ) < LLD (0 /4 ) 33 93. -
' 93 . < LIE (0 /4 )
BLUE CRAB GAMMA RA-226 13 3.26E+02 (PCI/KG(WET))
< LLD -(0 /9 ) < LIE (0 /4 ) 33 93 -
93 < LLD (0 /4-) BLUE CRAB GAMMA 13 2.74E401 (PCI/KG(UET)) I-131 < LLD (0 /9 ) < LLD (0 /4 ) 33 93 ; 93 < LIE (0 /4 ) i i t
' 70-3 -
~-,m u~ - , - - q ~me,-J n p w e --w -v- g y .ym-w paw- , ,,.7-_ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
y , - ,,a _ , , _ _ _ _ _ _ _
w -.
~ ;.7 . w ~ ~ Lfgy ,,f y 3 E E E E E. E E~E E E~M N E E E O M O'-
TABLE'3 RADIOIDGICAL ENVIRONMENTAL-MONITORING PROGRAM
SUMMARY
OYSTER CREEK' NUCLEAR GENERATING STATION-JANUARY,1989 THROUGH DECEMBER 1989
' ANNUAL
SUMMARY
SAMPLE TYPE ANALYSI:> ISOTOPE NUMBER LLD - INDICATOR-MEAN(N/ TOTAL) . STATIONS USED BACKGROUND-MEAN(N/ TOTAL) OF- RANGE RANGE FOR INDICATOR ANALYSES . . MEAN- -t PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE BLUE CRAB GAMMA NA-22 13 3.01E+01 < LLD (0 /9 ) < LID (0 /4 ) . 33 93 (PCI/KG(WET)) 93 < LLD (0 /4 ) BIDE CRAB GAMMA RU-106 13 1.76E+02 . < LLD (0 /9 ) < LLD 33 93" (0 /4 ) (PCI/KG(WET)) 93 < LLD (0 /4 ) BLUE CRAB GAMMA CO-57 13 1.07E+01 < LLD (0 /9 ) < LLD (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /4 ) BLUE CRAB GAMMA I-133 13 5.26E+03 (0 /9 ) (PCI/KG(WET))
< LID < LLD. (0 /4 ) 33 95 93 < LLD-(O /4 )
BLUE CRAB GAMMA CS-137 2.I4E+01 13 < LLD. (0 /9 ) < LID (0 /4 ) 33 93 (PCI/KG(WET))
- 93 < LLD (0 /4 )
BLUEFISH GAMMA CE-144 9 9.70E+01 '(0 /6 )
< LLD' < LID (0 /3 ) 33 93 (PCI/KG(WET))
93 < LID (0 /3 ) 4 w , .v .,w > - . _ .s .. p, u < ~,-. --,._.aw,
, yy . . _ ,+ ~, m. ,- _.m , .m'
~ , --ee., , . , .y m- w.n,, ee -
.., y-a.,- w ~, ,,n.< , ,y-, .,,n v .e, 4 ,
M M M WW W W M' W D M *W W W M' W M TABIE 3 RADIOLOGICAL EP"flR9tMENTAL MONITOR 1FG PROGRAll SUf9tARY OYSTER CREEK NUCLEAR GENERATII3G STATION JANUARY,1979 TIENi DECEMBER,1989 ANNUAL SUMM?RY SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-: FEAR (N/WTAL) STATIONS USED-BACFGROUND-MEAN(N/ TOTAL) 0F RANGE RANGE FDR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-FIAN(N/ TOTAL) RANGE CLUEFISH GAMMA AG-110M 9 2.30E+01 < 11D (O /6 ) < LID (0 /3 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /3 ) BIDEFISH GAMMA TE-129M 9 3.23E+04 < I; 0 (0 /6 ) < LLD 33 93 (0 /3 ) (PCI/KG(WET)) 93 < LID (0 /3 ) BLUEFISH GAMMA CS-134 9 2.94E+01 <. LTh {S /6 ) < LID (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /3 ) BLUEFISil GAMMA CO-58 9 2.42E+01 < I LO (PCI/KG(WET)) (0 /6 ) < LID (0 /3 ) 33 93 93 < LIE (0 /3 ) BLUEFISli GAMMA MN-54 9 2.27E+01 < LIJs (0 /6 ) (PCI/KG(WET))
< LID (0 /3 ) -
33 93 93 < LID (0 /3 ) BLUEFIS!I GAMMA FE-59 9 5.88E401 < Ub (0 /6 ) < LLD 33 93 (0 /3 ) (PCI/KG(WET)) - 93 < LLD (0 /3 )
mW mW W W M eM W W W W W M W W W W TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUl9lARY OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANCE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE BLITEFISH GAMMA CS-136 9 3.36E+01 < LLO (PCI/KG(UET)) (0 /6 ) < LIR (0 /3 ) 33 93 93 < LLD (0 /3 ) BLUEFISH GAMMA TE-132 7.54E+01 9 < LIE (0 /6 ) < LIE (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /3 ) BLUEFISH GAMMA ZN-65 9 7.20EiC1 < LIE < LIR (0 /6 ) (0 /3 ) 33 93 (PCI/KG(UET)) 93 < LLD (0 /3 ) BLUEFISH GAMMA CO-60 9 2.84E+01 < LLE (0 /6 ) < LID (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LIE (0 /3 ) BLUEFISH GAMMA K-40 9 1.80E+02 4.DSh.4C3 (6 /6 ) 3.67E+03(3 /3.) 33 93 (PCI/KG(UET)) ( 3.56F403 5.17E+03) ( 3.31E+03 - 3.85E+03) 33- 4.26E+03(3 /3 ) ( 3.56E+03 - 3.17E+03) BLUEFISH GAMMA BE-7 9 1.77E+02 < LIS (D /6 ) < LID (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /3 )
E E E E EE E M E U O E E E E W E E E TABLE 3 RADIOIDGICAL ENVIRONNENTAL MONITORING FROGRAM SUfflARY OYSTER CREEK NUCI. EAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER 1989 ANNUAL SUTtARY-SAMPLE TYPE ANALYSIS ISOTOPE NUMBER IID INDIChiDR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF R/SGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) i RANGE BLUEFISH GAMMA ZR-95 9 3.93E+01 < LLD de /6 ) < LLD (0 /3 ) 33 93 (PCI/KG(UET)) 93 < Lab (0 /3 ) BLUEFISH GAMMA NB-95 9 2.29E+01 < LLD (O /6 ) < LLD (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /3 ) BLUEFISH GAMMA SB-125 9 5.34E+01 (PCI/KG(WET))
< LID (0 /6 ) < LLD (0 /3 ) 33 93 93 < LID (0 /3 )
BLUEFISH GAMMA CE-141 9 2.66E+01 < IJE < LID (0 /6 ) (0 /3 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /3 ) BLUEFISH GAMMA RU-103 9 2.18E+01 < LLD < LLD (PCI/KG(WET)) (0 /6 ) (0 /3 )- 33 93 93 < LID (0 /3 ) BLUEFISH GAMMA CR-51 9 1.DE+02 < l.LD < LTE (0 /6 ) (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /3 )
.- ~ . . . - - -
.m .__
W M M N WM Y O M N O & M M M & M M 8 ". TABLK 3 RADIOIDGICAL ENVIRCipfE!@L M011IORING PROGRAM SIMMRY OYSTER CREEK NCCLEAR GENERATING STATION JANUARY,.198f THROrGI DECEMBER 1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INPICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANCE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE BILEFISH GAMMA BA-140 9 1.05E+02 < LLD < LID (0 /6 ) (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /3 ) BLUEFISH GAMMA LA-140 9 4.06E+01 < LLD (PCI/KG(WET)) (0 /6 ) < LID (0 /3 ) 33 93 93 < LIE (0 /3 ) ' BLUEFISil GAMMA AC-228 9 9.08E+0L
< LLO (0 /6 ) < LLD (0 /3 ) 33 93
- (PCI/KG(WET))
93 < Il3 (0 /3 ) BLUEFISil GAMMA RA-224 9 1.72E+03 (0 /6 )
< LID < LID (0 /3 ) 33 93 (PCI/KG(UET))
93 < LLD (0 /3 ) BLUEFISil GAMMA RA-226 9 3.94E+02 < LLD (PCI/KG(WET)) (0 /6 ) < LID (0 /3 ) 33 93 93 < LLD (0 /3 ) BLUEFISil GAMMA I-131 9 3.69E+01 < LLD (PCI/KG(WET)) (0 /6 ) < LID (0 /3 ) 33 93 93 < LLD (0 /3 )
,y e , + .c g %i + .w- .c,. ,.m . - .- --
r e, - ,e 3 w eo , < - S ,,.,.4.e., - , -.. c- -, ,-,-.,-.--...w --
WW W
.E -
E E E % U M EE O E E E O E E E TABLE 3 RADIGIJDCICAL ENVIRONMENTAL MONITORING PROGRAM SUf9LARY OYSTER CREEK NUCLEAR GENERATING STATIO!v JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) - BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANCE EVR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE BLUEFISH NA-22 < LLD (0 /6 ) GAMMA 9 3.04E+01 < LID (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /3 ) BLUEFISH GAMMA RU-106 9 1.98E+02 (0 /6 )
< LIE < LID (0 /3 ) 33 93 (PCI/KG(WET))
93 < LID (0 /3 ) BLUEFISH GAMMA CO-57 9 1.30E+0I < LLD (0 /6 ) < LID (0 /3 ) 33 93 (PCI/KG(WET)) 1-93 < LID (0 /3 ) BLUEFISH GAMMA 9 1.24E+04 < LLD (0 /6 ) I-133 < LID (0 /3 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /3 ) BLUEFISH GAMMA CS-137 9 2 46E+01 1.55E+01 (1 /6 )
< LID (0 /3 ) 33 93 (PCI/KG(WET)) ( 1.65E+01 - 1.65E+01) 93 1.65E+01(1 /3 )
( 1.65E401 - 1.65E+01) i SUMMER FLOUNDER GAMMA CE-144 2 8.87E+01 < LLD (0 /1 ) < LID (0 /1 ) 93 (PCI/KG(UET)) 93 < LLD (0 /1 )
-, .- -- , . .. . . ~ - - , . ~ . . . -_ . - - . -
@ MM M M M E U M E E O E E E N E -
TAELE 3 . _.. RADIO 1DGICAL ENVTRONMENTAL MONITORING PROGRAM SU!9fARY OYSTER sREEK NUCLEAR GENERATING STATION JANIJARY,1989 THROUGH DECEMEER,1989 ANFRTAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER IlD INDICATOR-MEAN(N/ TOTAL) STATIONS USED BACKGROUND-MEAN(N/ TOTAL) OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SUMMER FLOUNDER GAMMA AG-110M 2 2.37E+01 < LLD < LLD (0 /1 ) (0 /1 ) 93 (PCI/KG(WET)) 93 < LIE (0 /1 ) SUMMER FIBUNDER
- GA.DiA TE-129M 2 - 7.67E+04 < LIR (0/1) < LLD (0/1) 93 (PCI/KG(WET))
93 < LLD (0 /1 ) SUMMER FLOUNDER GAMMA CS-134 2 2.69E+01 < LIE (0 /1 ) < LID (0 /1 ) 93 (PCI/KG(UET)) 93 < LIE (0 /1 ) SUMMER FLOUNDER GAMMA CO-58 2 2.86E+01 < LLD (0 /1 ) < LLD 93 (0 /1 ) (PCI/KG(WET)) 93 < LID (0 /1 ) SUMMER FLOUNDER GAMMA MN-54 2 2.56E4 01 < LLD (0 /1 ) (PCI/KG(UET))
< LID (0 /1 ) 93 i
93 < LLD (0 /1 ) SUMMER FIDUNDER CAMMA FE-59 2 7.58E+01 < LLD (0 /1 ) < LLD (0 /1 ) 93 (PCI/KG(WET)) 93 < LLD (0 /1 ) pim e p a
-g-. msg *- mg p-**W-mewg g- e ,M1 v e gi e w- 4- . *w quW rwey -
- w wa-e =-v-, -i-wp- -+ gy.v g e,gh taiv ,
M MM MM M M M~ M - N U N W .E E E E E' E TABLE 3 RADIOLDGICAL EWIRO*GMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
EAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INDICATOR-MEAN(N/ TOTAL) BACKGROUNC-MEAN(N/ TOTAL) STATIONS USED i 0F RANCE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SUMMER FIDUNDER GAMMA CS-136 2 3.81E+01 < LID (0 /1 ) < LID 93 (0 /1 ~ ) (PCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER FIDUNDER GAMMA TE-132 2 1.012+02 < LLD (0 /1 ) < LLD (0 /1 ) 93 (PCI/KG(WET)) 93 < IJD (0 /1 ) SUMMER FIDUNDER GAMMA ZN-65 2 7.84E+01 < LID (0/1) < LIE (0 /1 ) 93 (PCI/KG(WET)) 93 < LIE (0 /1 ) SUMMER FIDUNDER CAMMA CO-60 2 3.43E+01 (0 /1 ) < LLD (PCI/KG(WET))
< LLD (0 /1 ) 93 93 < LIE (0 /1 )
SUMMER FIDUNDER CAMMA K-40 2 1.80E+02 4.72E+03 (1 /1 ) 4.12E+03(1 /1 ) 93 (PCI/KG(WET)) ( 4.72E403 - 4.72E+03) ( 4.12E+03 - 4.12E+03) 93 4.72E+03(1 /1 ) ( 4.72E+03 - 4.72E+03) SUMMER FLOUNDER GAMMA BE-7 2 1.79E+02 < LLD (0 /1 ) < LID 93 (0 /1 ) ) (PCI/KG(WET)) l 93 < LLD (0 /1 ) . l l l _ _ . . ~ s. - . _ . ,_ , _ - _ _ . . . . - _ , , . . . . - _ _ . - . , _ , . . _ . . _ _ . _ _ _
p q M M M M M . M Q M & MM YM O M, I TABLE 3 RADIOLDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LIE INDICATOR-MEAN(N/ TOTAL) STATIONS USED' BACKGROUND-MEAN(N/ TOTAL) . OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SUMMER FIDUNDER GAMMA ZR-95 2 4.57E+01 < LIE (0 /1 ) < LIE (O /1 ) 93~ (PCI/KG(WET)) 93 < LID (0 /1 ) SUMMER FLOUNDER CAMMA NB-95 2 2.66E+01 < LIE (0 /1 ) < LLD (0 /1 ) 93 (PCI/KG(UET)) 93 < LID (0 /1 ) SUMMER FIDUNDER GAMMA SB-125 2 5.25E+01 < LLD (0/1) < LID (0 /1 ) 93 (FCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER F1DUNDER GAMMA CE-141 2 2.46E+01 < LLD (0/1) < LID (0/1) 93 (PCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER FLOUNDER GAMMA RU-103 2 2.2SE+01 < LLD (0 /1 ) < LID (0 /1 ) 93 (PCI/KG(WET)) 93 < LID (0 /1 ) SUMMER FLOUNDER CAMMA CR-51 2 1.73E402 < LLD (0 /1 ) < LLD (0 /1 ) 93 (PCI/KG(WET)) 93 < LLD (0 /1 )
. . - . . . - , . . -,a.. - . . . . - , . - .. . - - , . ~ . -.. .. -. . .. . . . . . -
&M M M M M M M M &M Y M M~M M M M- M TABLE 3 RADIGIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/TUTAL) STATIONS USED OF RANGE RANGE ET)R INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
. RANGE SUMMER FIDUNDER GAMMA BA-140 2 1.15E+02 < I.LD (0 /1 ) < LIE (0 /1 ) 93
-(PCI/KG(WET))
93 < LIE (0 /1 ) SUMMER FIDUNDER CAMMA LA-140 2 6.14E+01 < LIE (0 /1 ) < LLD (0/1) 93' (PCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER FIDUNDER GAMMA AC-228 2 9.53E+01 < LID (0 /1 ) < LLD (0 /1 ) 93 (PCI/KG(WET)) 93 < LIE (0 /1 ) SUMMER FIDUNDER CAMMA RA-224 2 2. 37E4 03 < LID (0 /1 ) < LLD (0/1) 93 (PCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER FIDUNDER CAMMA RA-226 2 3.88E402 < LLD (0/1) < LIE (0 /1 ) 93 (PCI/KG(WET)) 93 < LLD (0 /1 ) , SUMMER FIEUNDER GAMMA I-131 2 4.32E+01 < LLD (0 /1 ) < LLD (0 /1 ) 93 (PCI/KG(WET)) 93 < LIE (0 /1 ) , i l i _ _ _ _ _ _ - _ _ - . - - ,- .._c . - - - ~ , , - - ,. - --. - x ,. . . - - - . - - . . - - - . -,1. -
W MM M MM M M M MW M W W M M MM M l TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
ANAINSIS ISOTOPE NUMBER LIE INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED SAMPLE TYPE OF RANGE RANGE FOR INDICATUR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SUMMER FLOUNDER GAMMA NA-22 2 3.80E+01 < LLD (0 /1 ) < LIE (O /1 ) 93 (PCI/KG(WET)) I 93 < LID (0 /1 ) SUMMER FIDUNDER GAMMA RU-106 2 2.05E+02 < LLD (0/1) < LLD (0 /1 ) 93 !
-(PCI/KG(WET))
93 < LID (0 /1 ) SUMMER F1DUNDER GAMMA CO-57 2 1.13E+01 < LID (0 /1 ) < LLD (0/1) 93 (PCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER FIDUNDER GAMMA I-133 2 4.41Et04 < LLD (0 /I ) < LLD (0/1) 93 (PCI/KG(WET)) 93 < LLD (0 /1 ) SUMMER F1DUNDER GAMMA CS-137 2 2.61E+01 < LLD (O /1 ) < LID (O /1 ) 93 ; (PCI/KG(WET)) 93 < LLD (0 /1 ) CIAMS GAMMA CE-144 65 6.38E+01 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (FC:/KG(WET)) 25 < LTD (0 /13 ) M M M M M M M M M M W. W - <W WM M M M M-TABLE ~3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECDfBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE P]R INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE CLPMS GAMMA AG-110M 65 1.40E+01 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(UET)) 25 < LIE (0 /13 ) , CIAM3 GAMMA TE-129M 65 1.64E+04 (0 /39 )
< LID < LID (0 /26 ) 23 24 25' (PCI/KG(UET)) .
25 < LLD (0 /13 ) CIAMS GAMMA CS-134 65 2.41E+01 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA CO-58 65 1.65E+01 (0 /39 ) 4 < LLD < LLD (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA MN-34 65 1.60E+01 (0 /39 ) < LLD
< LID (0 /26 ) 23 24 25 (PCI/KG(WET))
25 < LLD (0 /13 ) CIAMS GAMMA FE-59 65 3.83E+01 (0 /39 )
< LLD < LLD (0 /26 ) 23 24 25 (PCI/KG(WET)) .
25 < LLD (0 /13 )
W M M M M M E U MM E-"M W W W E E E E TABLE 3 RADIGIDGICAL ENVIRONMENTAL MONITORING PROGRAM SLHMARY OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER 'LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANCE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE CIAMS GAMMA CS-136 65 2.05E+01 < LID (0 /39 ) < LLD (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LIE (0 /13 ) CIAMS GAMMA TE-132 65 3.96E+01 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA ZN-65 ~65 5.65E+01 < LLD (0 /39 ) < LLD (O /26 ) 23 24 25 (PCI/KG(WET)) 25 < LIE (0 /13 ) CLAMS GAMMA CO-60 65 2.06E+01 < LLD (0 /39 ) < LIE (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA K-40 65 1.80E+02 9.77E+02 (39 /39 ) 1.04E+03(26 /26 ) 23 24 25 (PCI/KG(WET)) ( 7.28E+02 - 1.31E+03) ( 4.54E+02 - 1.57E+03) 23 1.01E+03(13 /13 ) ( 8.50E+02 - 1.30E+03) CIAMS GAMMA BE-7 65 1.15E+02 < LLD (0 /39 ) < LLD (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 .< LLD (0 /13 )
, _ _ .- _ -. ..._ .. _ - . = . .
- -~ -
M MM M- M 'M M W WW M WM & M M M M' M TABLE 3 RADIOIMICAL ENVIRONMENTAL MONITORING ' PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBiJt LTE INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FDR INDICATOR' ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANCE i CIAMS GAMMA ZR-95 65 2.81E+01 (PCI/KG(WET))
< LIE (0 /39 ) < LLD (0 /26 ) 23 24 25 25 < LID (0 /13 )
CLAMS GAMMA NB-95 65 1.68E+01 (PCI/KG(WET))
< LLD (0 /39 ) < LIE - (0 /26 ) 23 24 25 25 < LIE (0 /13 )
CIAMS GAMMA SB-125 65 5.41E+01 < LLD (0 /39 ) < LLD (0 /26 ) 23 24 25 (PCI/KG(UET)) 25 < LIE (0 /13 ) CIAMS GAMMA CE-141 65 1.67E+01 (PCI/KG(WET))
< LID (0 /39 ) < LLD (0 /26 ) 23 24 25 25 < LIE (0 /13 )
l CIAMS GAMMA RU-103 65 1.43E+01 < LLD (PCI/KG(UET)) (0 /39 ) < LIB (0 /26 ) 23 24 25 l 25 < LLD (0 /13 ) CIAMS GAMMA CR-51 65 < LLD (PCI/KG(WET))
- 1. 07Ev.12 (0 /39 ) < LIE (0 /26 ) 23 24 25 25 < LID (0 /13 )
y - - ., , - , - . .,,% , , . ..w.- cy.., . , . . . _ _ -
..y 3 - , -m... .y. , , , .m , . , .
E; M6 6 'E E E E E M S6 E E E EE
-TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
, OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 -
ANNUAL
SUMMARY
EAMPLE TYPE ANALYSIS ISOTOPE NUMBER IID INDICATOR-MEAN(N/ TOTAL) BACKGROUNI)-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN-PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE CIAMS GAMMA BA-140 65 6.49E+01 < LLD (0 /39 ) < LLD '(0 /26 ) 23 24 25 (PCI/KG(UET)) 25 < LID (0 /13 ) CIAMS GAMMA IA-140 65 3.09E+01 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA AC-228 65 6.21E+01 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(UET)) 25 < LLD (0 /13 ) CIAMS GAMMA RA-224 65 9.16E402 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA RA-226 65 2.43E+02 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LID (0 /13 ) l CIAMS GAMMA I-131 65 2.04EtO) < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(UET)) 25 < LID (0 /13 ) l I l
, - -.. ._ .~ . . - . . . . . .- - - - -.- .- _ _ _ . . . - .
-mmem W W W M- MM M W W .M M M 'M MW TABLL 3 RADIOIJDGICAL ENVIRONNENTAL MONITORING PROGRAM
SUMMARY
OYSTER GREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEF.BER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANCE RANCE EDR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE CIAMS
- GAMMA NA-22 65 2.08E+01 < LID (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET))
25 < LLD (0 /13 ) CIAMS GAMMA RU-106 ti5 1.27E+02 < LID (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA CO-57 65 8.24E+00 < LLD (0 /39 ) < LID (0 /26 ) 23 24 25 . (PCI/KG(WET)) 25 < LID (0 /13 ) CifES GAMMA I-133 65 7. 04 E+03 < LID (0 /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD (0 /13 ) CIAMS GAMMA CS-137 -65 1.SSE401 < LLD (O /39 ) < LID (0 /26 ) 23 24 25 (PCI/KG(WET)) 25 < LLD.(0 /13 ) TAUTOG GAMMA CE-144 11 1.63E+02 < LLD (0 /7 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /6 )
-m ~ m W -m ;W W W W M M -W W W W m W W W W TABLE 3 RAOIOIDCICAL EfMIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAP. GENERATING STATION JANU7RY,1989 THROUGH DECEMBER.1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER 113 INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FDR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)- RANGE TAUTOG ^ CAMMA AG-110M 11 3.71E+01 < LID (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /6 ) TAUTOG GAMMA TE-129M 11 1. 30D95 < LLD (0 /7 ) < LLD (0 ft. ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTOG GAMMA CS-134 11 5.15Et01 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /6 ) TAUTOG GAMMA CO-58 11 4.26E&Oi < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTGG GAMMA MN-54 11 3.76E+01 < LLD (0 /7 ) < LLD (d/4) 33 93 (PCI/KG(WET)) 93 < LID (0 /6 ) . TAUTOG GAMMA FE-59 11 ??.10E+01 < LID (0 /7 ) < LIE (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /6 )
M" M M M M M , M M M M M M M M M M TABLE 3 RADIOLOGICAL Eh71P.ONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLFAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANFUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE TAUTOG ^ GAMMA CS-136 11 5.77E+01 < LID (0 /7 ) < LID (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /6 ) TALTTOG GAMMA TE-132 11 1.74E+02 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PGI/KG(UET)) 93 < LID (0 /6 ) TAUTOG GAMMA ZN-65 11 1.15E+ 02 < L1D (O /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) 4 TAUTOG GAMMA CO-60 11 4.79E+01 < LLD (0 /7 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTOG GAMMA K-40 11 1.806402 4.52E+03 (7 /7 ) 4.91E+03(4 /4 ) 33 93 (PCI/KG(WET)) ( 3.39E+03 - 5.85E+03) ( 3.54E+03 - 7.13E+03) 33 4.63E+03(1 /1-) (. 4.63E+03 - 4.63E403) TAUTOG GAMMA BE-7 11 2.9/E'02 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /6 )
-d8-i
- WW .
W E. . E' .E E . EE E E E E E TABLE 3 RADIO 1DGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTEP. CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF Rtat,E RANGE FUR INDICATOR - ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE l TAUTOG ^ GAMMA ZR-95 11 6.90E401 < LTD (0 /7 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LID (0 /6 ) TAUTOG GAMMA NB-95 . 11 3.97Z+01 < 11D (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LIE (0 /6 ) TAUTGd; SB-125 GAMMA 11 9.04C+01 < LIB (O /7 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTOG GAMMA CE-141 11 4.57E+Gt < LLD 'O /7 ) . < LID (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) l TAUTGG GAMMA RU-103 11 3.90E+0! < LLD (0 /7 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) , 93 < LIE (0 /6 ) i TAUTOG GAMMA CR-51 11 3.01E+02 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 l (PCI/KG(WET)) l 93 < LLD (0 /6 ) l I ____________________-__-_____a '* '-_ _ _ .
-'CV-*-%" -#' 5'I T w 'Me'd - . *A *W W V % i * ' '
- t* '*T#f" 8N'#' 'av #'eC- ed "Y 1*'MP
***T' W *"'"t- %m
. , y -.
1W W We 'W' _M. .
.: W z W ; W W 'W,W'W .
W W W W W TABLE 3 7
. RADIOIDGICAL ENVIRONitfl.TAL MGi4ITORING PROGRAM
SUMMARY
OYSTER CREEK NUGli2R GENERATING STATION JANUARY,1984 ThPSUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDTCATO'l -MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RAtIGE RANGE FOR INDICATOR ANALY3ES- MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE TAUTOG GAMMA BA-140 11 1.88E+02 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUYOG GAMMA IA-140 11 '/ . 57E +0i < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTOG GAMMA -AC-228 11 1.47E+C' < ilB (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTOG GAMMA RA-224 11 3.99L+03 < LIB (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /6 ) TAUTOG GAMMA RA-226 11 7.12E+C2 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(UET)) 93 < LID (0 /6 ) TAUTOG GAMMA I-131 11 6.60Ea01 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) _0
-. .. .- - .. . - - - . . = .____- . _ . ~-_ ---
6-TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CRFEK faXI. EAR CRIERATING STATION JANUARY.19CF THEO'.iGH DECEMBER,1989 A;mdAL
SUMMARY
- SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LID.. IN41GA10F-tfEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS U$ED OF RA W'S RANGE- FOR INDICATOR l ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE-TAUTOG GAMMA NA-22 11 4.94E+01 < LLD (0 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) , 93 < LLD (0 /6 ) TAUTOG GAMMA RU-106 11 3.30E+02 < LIA (0 /7 ) < LID (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LIE (0 /6 ) TAUTOG GAMMA CO-57 11 2.08E+01 < LED (0 /7 ) < LIE (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LIE (0 /6 ) TAUTOG GAMMA I-133 11 1.19E*b5 < LID 10 /7 ) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) TAUTOG GAMMA CS-137 11 4.03E+01 < LID (0 f7) < LLD (0 /4 ) 33 93 (PCI/KG(WET)) 93 < LLD (0 /6 ) SOIL GAMMA CE-144 6 1.24E+02 < LLD (O /4 ) < LLD (0 /2 ) 35 66
~ (PCI/KG(DRY))
66 < LID (0 /2 )
~
91
. _ _ , - , _ , . .,,_m _. u.. . . . . . -. . ~ __; - - - . - -.. ,
TABLE 3 RADIOIJDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTE2 CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUCH DECEMBER,1989 ANNUAL SIMMARY EAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANCE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) I RANCE SOIL GAMMA AG-110M 6 4.00E401 < IJD (G /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LIE (0 /2 ) , SOIL GAMMA TE-129M 6 5.03E+94 < LIE (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 ) SOIL GAMMA CS-134 6 4.37E+01 < LLD (0 /4 ) < LLD (0 /2 ) 35 66
- (PCI/KG(DRY))
66 < LLD (0 /2 ) SOIL CAMMA CO-58 6 2. 30E401 <ID (0 /4 ) < LID (0 /2 ) 35 66
' (PCI/KG(DRY))
. 66 < LIE (0 /2 )
SOIL GAMMA MN-54 6 2.15E401 < LII, (G /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LIE (0 /2 ) SOIL GAMMA FE-59 6 4.90E401 <113 (C /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LLD (0 /2 )
^2-
_ . _ _ . - . _ . _ _ , . . , _ . . . - _ .- ._ .~,_.._,u. _ _- _ .-_ ,_. . __ _ _ . _s_,-_.,_-,_
< ;-- - - _ y _ _ ._ _ .y _ . . , _ . ._ _ _ _ _ . _ M M- M M' M 'M M - M' J M M M _ M -- M ~' M MM-M M M TABII 3 RADIOIDGICAL t:NVIRONMENTAL l10NITO"ING FROGRAM
SUMMARY
OYSTER CREEf tMJCLFAk GENEi(ATING STATION JANUARY,198? THEUUGH DECEMBER,1989 ANNUAI.
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LTD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF R*NCE RANGE IVR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE SOIL GAMMA CS-136 6 2.88E+01 + ' UE (3 /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 )
.EOIL GAMMA TE-132 6 1.02E+02 < LLD to /4 ) < LLD (0 /2 )
35 66 (FCI/KG(DRY)) 65 < LID (0 /2 ) SOIL b!MMA ZN-65 6 9.05E401 < LID (0 /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)'s 66 < L1D (0 /2 ) SOIL GAMMA CO-60 6 2.49E+01 <*'D (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 ) SOIL GAMMA K-40 6 2.60E401 1.342+03 (A /4 ) 6.42E+03(2 /2 ) 35 66 (PCI/KG(DRY)) ( 1.02E+03 - 2.01E+03) ( 6.16E+03 - 6.68E+03) 66 1.61E+03(2 /2 ) ( 1.71E403 - 2.01E403) SOIL GAMMA BE-7 6 1.14C402 ' US (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 ) .
-93<
E E E E E'E E E 'E E E E E E E E E E E [ TABI E 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING ETATION JANUARY,1989 THROUGH DECEhBER,1989 ANN"AL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAW(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE FOR INDICATOR-ANALYSES MEW PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE
^
SOIL GAMA ZR 6 3.96E+01 < LID (0 /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LIB (0 /2 ) SOIL GAMMA NB-95 6 2.37E+01 .< LLD (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LLD (0 /2 ) SOIL GAMMA SB-125 6 5.15E401 < LLD (0 /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) , 66 < LID (0 /2 ) SOIL GAMMA CE-141 6 3.19E401 < LLD (0 /4 ) < LIE (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LLD (0 /2 ) 4 SOIL GAMMA RU-103 6 2.01E+01 < LIE (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LIE (0 /2 ) SOIL GAMMA CR-51 6 1.71E+02 < LID (0 /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LIE (0 /2 ) O d e
, , -. , , -m
. . o,. , . .C~r .%+- ,, . -,
E E E E. E E E E EE E E E,E E E E E TABLE 3 RADIOIAGICAL ENVIRONI! ENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NCCIEAR GENERATING STATION JANUARY,1989 THROUGH CECEMBER,1989 ANNUAI,SUliMARY ! SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LIE INDICATO2-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED l OF RANGE RANGE FOR INDICATOR ANALYSES
-MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE SOIL GAMMA BA-140 6 1.04E+02. < LID (0 /4 ) < LIE (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 ) SOIL GAMMA IA- 140 6 4.63E+01 < 1.2 (O /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 ) SOIL GAMMA AC-228 6 2.60E+01 3. lfrE+02 (4 /4 ) 8.71E+02(2 /2 ) 35 66 (PCI/KG(DRY)) ( 2.30d+02 - 4;SLE+02) ( 8.52E+02 - 8.90E+02) 66 3.99E+02(2 /2 ) ( 3.13E+02 - 4.86E+02) SOIL GAMMA RA-224 6 2.58E+03 < LIE (0 /4 ) < LLD (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LLD (0 /2 ) SOIL GAMMA RA-226 6 2.60E+01 n.29E+02 (4 /4 ) 2.38E+03(2 /2 ) 35 66 (PC1/KG(DRY)) ( 4.82EA2 1.G9E+03) ( 2.33E+03 - 2.42E+03) 66 1.07E403(2 /2 ) ( 1.05E+03 - 1.09E+03) SOIL GAMMA I-131 6 3.58Et01 < Lih (0 /6 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LLD (0 /2 )
-. _. . _ _ . -, ._. .. .- -.~ .. _ ,. . . _ . . ~ . - - . _ . . . , _ . , . _ , _
-_ v - ._ - - - .. __
m W- M M lm m W W W! W ~m M M e mm mM M TABLE 3 RADIOIDGICAL EINIRGI0tENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1969 THROUGH DECEMBrR,1989 ANNUA 1.
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INLICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RAH;E RANGE FVR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE
~
SOIL GAMMA NA-22 6 2.43E+01 < LLD (0 /4 ) < LLD (C /2 ) 35 66 (PCI/KG(DRY)) 66 < LLD (0 /2 ) SOIL GAMMA RU-106 6 1.69E+02 < LLD (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LID (0 /2 ) SOIL . GAMMA CO-57 6 1.55E+01 < LLD !O /4 ) < LIE (0 /2 ) 35 66 (PCI/KC(DRY)) 66 < LLD (0 /2 ) . SOIL GAMMA I-133 6 3.51E+04 < LID (0 /4 ) < LID (0 /2 ) 35 66 (PCI/KG(DRY)) 66 < LIE (0 /2 ) SOIL GAMMA CS-137 6 2.60E+01 1 28Et02 (4 /6 ) 1.33E+02(2 /2 ) 35 66 (PCI/KG(DRY)) ( 7.14E+01 - 2.01E402) ( 1.20E+02 - 1.47E+02) 65 1.68E402(2 /2 ) ( 1.35E+02 - 2.01E+02) WAKFISil GAMMA CE-144 2 1.47E402 < LLO (9 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) . 93 < LIE (0 /2 ) oc.-
.- - .. - - - _ _ . . , - ,, _ , _ _ _ - . _ . - .- ~___- _ _ , _- - _ . _ _ _ _ . ._ -. ... - . _ _ - - _
W' . W W W W -E W W M -' W - W 'W . W W W W 'W E TAB!E 3 RADIOIDGICAL ENVIRONMENTAL MONITORIW FF09AM
SUMMARY
OYSTER CREEK NUCLEA't vMTI.'F; htT40;! JANUARY,1989 'ntROUCil DECFMBER. % 9 - ANNUAL SbMMARY SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(F/T9TAL; BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RAMGE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE WEAKFISil GAMMA AG-110M 2 3.68E+01 < LTD (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) { * - * ) 93 < LID (0 /2 ) WEAKFISil GAMMA TE-129M 2 7.86E+04 < LID (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /2 ) WEAKFISil GAMMA CS-134 2 4.33E+01 < LLD (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) { * - * )
~ 93 < Ilb (0 /2 )
WEAKFISil GAMMA CO-58 2 3.65E401 < LLD (0 /2 ) * (* /* ) 93 (PCI/KG(UET)) ( * - * -) 93 < LIE (0 /2 ) l UEAKFISH GAMMA -MN-54 2 3 91E+01 < LIE (0 /2 ) * (* /* ) 93 l (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /2 )' - a UEAKFISH GAMMA FE-59 2 9.10E+01 < L1.3 (0 /2 ) * (* /* ) 93 (PCI/KG(UET)) ( * - * ) 93 < LIE (0 /2 )
~
I
- M M M M 8 8 8 8 8- O M M M M 'M M M M TABLE 3 RADIOIEGICAL ENVIRONMENTAL MONIT*> RING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGli DECEMF,ER.1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE RANGE IVR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE WEAKFISil GAMMA CS-136 2 5.09E+01 < LIE (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * * ) 93 < LIE (0 /2 ) UEAKFISil CAMMA TE-132 2 1.23E402 < LIE (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * * . ) 93 < LLD (0 /2 ) . WEAKFISH GAMMA ZN-65 2 1.04E+02 < LLD (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * ) 93 < LIE (0 /2 ) WEAKFISil GAMMA CO-60 2 4.70E+01 < LLD (0 /2 ) * (* /* ) 93 , (PCI/KG(WET)) { *
* )
93 < LIE (0 /2 ) WEAKFISH GAMMA K-40 2 2.60E+01 4.80E+03 (2 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( 3.24E+03 - 6.37E*03) ( * * ) 93 4.80E+03(2 /2 ) ( 3.24E+03 - 6.37E+03) i UEAKFISH GAMMA BE-7 2 2.78E+02 < LIS (G /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < US (0 /2 ) 92-
E E. E. E E E E E E EE E E E E E E E i' TABLE RADIOLDGICAL ENVIRONMENTAL MCNITORING PROCP.ful SUMMAR1 OYSTER CREEK NUCLEAR CGERA'i1NG STATION JANUARY,1989 THROUGII fsEOEMBER,1%9 ANNUAL
SUMMARY
' SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LIE INDICATOR-MEAN(N/ TOTAL) BTE'tGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANCE RANGE FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE
- WEAKFISH GAMMA ZR-95 2 5.93E+01 < LLD 'O f/ ) * (* /* ) 93 (PCI/KG(WET)) ( * - * )
93 < UrJ (0 /2 ) WEAKFISH GAMMA NB-95 2 3.54E+01 < LIE (O /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) , 93 < LIE (0 /2 ) VEAKFISH GAMMA SB-125 2 7.12E401 < LIE (O /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < LID (0 /2 ) . 1 UEAKFISH GAMMA CE-141 2 3.87E+01 < LLD tie /2 ) * (* /* ) 93 (PCI/KG(WET)) { * - * ) 93 LLD (0 /2 ) WEAKFISH GAMMA RU-103 2 3.27E+01 < LIE (O /2 ) * (* /* ) 93 (PCI/KG(VET)) ( * - * ) 93 < UE (0 /2 ) LTEAKFISH GAMMA CR-51 2 2.39E+02 < LLD f3 /2 ) * (* /* ) 93 (PCI/KG(WET)) { * - * ) 93 < LLD (0 /2 )
- l - - 99 e----- , ,-' -
- s y - g-F +w--V ar w-- g t -
3 g- g -e g y+ -
-y,y, y e J _-W g .-e _mee-e w-_hrm.- _,,.sL.m m
,,__-es____1e r___.2
.r- .- -
, .;p_ , - --.
.- mg.
E[ E ' E - E E E E El E E ~E E E E E E E E ,E 3_ _ ;f, 3-=. s . n TABLE'3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION-JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL'
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL} STATIONS USED~ OF . RANGE - RANGE FUR INDICATOR-- ANALYSES .
.MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)-
RANGE WEAKFISH GAMMA BA-140 2 1.60E+02 < LLD (0 /2 ) * (* /*-)-' 93 (PCI/KG(UET)) .( * - * ) 93 < LID (0 /2 ) UEAKFISH GAMMA LA-140 2 7.15E401 < LIE (0 /2 ) * (* /* ) 93 (PCI/KG(UET)) ( * - * ) 93 < LID (0 /2 ) UEAKFISH GAMMA AC-228 2 1.29E+02 < LLD (0 /2 ) * (* /* ) 93 (PCI/KG(UET)) ( * - * ) 93 < 11D (0 /2 ) UEAKFISH GAMMA RA-224 2 2.89E+03 < t11 (0 /2 ) * (* /* ) 93 (PCI/KG(UET)) ( * - *. ) 93 < LID (0 /2 ) UEAKFISH GAMMA - RA-226 2 5.83E402 . < LLD (0 /2 ) * (* /* ). 93 (PCI/KG(UET)) ( * - * .) 93 < LLD (0 /2 ) UEAKFISH GAMMA I-131 2 5.33E401 < LLD (0 /2 ) * (* /* )' 93 (PCI/KG(UET)) (* - * ) 93 < LLD (0 /2 )
-100-
.g
#- .f .-u_-- w,sm -
A,c e s. .-.am,..,-m w-ae.m+.w-,em._. m s at d.-w. . gs-_,.v.rmve.t_ .___,m-- me --.--._.m .gmi%,. ,...%,m..-
--.,mwyewm-..
g _g , , . . ,
?E LE' E E LE 'E' E .E .
E LE ' E: E E E E E E E E 2 l TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION i- JANUARY,1989 THROUGH DECEMBER.1989' l ANNUAL
SUMMARY
l ' SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) '~ STATIONS USED l .. OF RANGE RANGE- FDR INDICATOR l ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE
- 1 WEAKFISH GAMMA NA-22 2 4.37E+01 < LLD -(0 /2 ) .
* -(* /* ) 93 (PCI/KG(WET)) { * - * )
93 < LLD_(0 /2.) UEAKFISH RU-106 2.89E+02 < LLD (0 /2 )
- GAMMA 2 (* /* ) 93 (PCI/KG(UET)) ( * .
- * )..
93 < LLD (0 /2 ) UEAKFISH GAMMA CO-57 2 1.91E+01 < LLD (0 /2 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ). 93 < LLD (0 /2 ) WEAKFISH GAMMA I-133 2 3.09E+04 < LLD (0 /2 )- *- (* /* ) 93 (PCI/KG(WET)) ( * . -.* ) 93 < LLD (0 /2'), WEAKFISH GAMMA CS-137 2- 3.12E+01 < LLD (0 /2 ) *- '(*
/* ) 93' (PCI/KG(WET)) ( * - * .
. )
93 < LLD (0 /2 ) WINTER FIDUNDER GAMMA CE-144 1 3.50E+02' < LLD (0 /1 ) *- (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < LLD (O./1 )
--- 101 -
. ~~ - , . . - .; . :_, , . :- . . . - . . - . . .w -- - .-- - , . . ~ . , ,
M' , . [ :. ..
' ~
i
~
TABLE 3-RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989-ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF. RANGE RANGE FOR INDICATOR ANALYSES MEAN' PERFORMED- STATION STATION-MEAN(N/ TOTAL) RANGE WINTER FIAUNDER GAMMA AG-110M 1 6.68E+01 < LLD (0 /1 ) * (* /* ) . :93 (PCI/KG(WET)) '( *- - * ) 93 < LLD (0 /1-) WINTER FIDUNDER GAMMA TE-129M 1 2.54E+06 < LIE (0 /1 ) * (* /* ) 93 (PCI/KG(WET)) { * - * ) 93 < LID (0 /1 ) WINTER FLOUNDER GAMMA CS-134 1- 1.18E+02 < LLD (O/1) * (* /* ) 93 (PCI/KG(UET)) ( * - * ) 93 < LIE (0 /1 ) WINTER FIDUNDER GAMMA CO-58 1 6.36E+01 < LLD (0 /1 ) -* (* /* ) 93 (PCI/KG(WET)) . ( * - * ) 93 < LLD (0 /1 ) WINTER FLOUNDER GAMMA MN-54 1 6.42E+01 < LLD (0 /1 ) * (* /* ) 93 (PCI/KG(WET)) ( * .- * .)
< LLD (0 /1 )
93 WINTER FLOUNDER GAMMA FE-59 1 1.56E+02 < LLD (0 /1 ) * (* /*.) 93 (PCI/KG(WET)) (* - * -) 93 < LIE (0 /1 ).
-102-
. _ . , . . . . _ .. _ - . , ...;. .,_ , _.a_
; __ . _ ~ _ ._._o_-_______ _ _ _ _ _ _ _ _ _ _ _ _ . . _ .
^
+> . . -
l - W W ' W M' W'M W- M M3 W. :W W W 'Wi W W W=W v-TABLE 3 ~ RADIOIDGICAL ENVIRONMENTAL MONIT0 RING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION
- JANUARY,1989.THROUGH DECEMBFJt 1989 ANNUAL
SUMMARY
. BACKGROUND-MEAN(N/ TOTAL) STATIONS USED SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD ' INDICATOR-MEAN(N/ TOTAL)
RANGE RANGE -FOR1 INDICATOR OF ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE CS-136 1 1.33E+02 < LLD (0 /1 ). * (* /* ) . -93 WINTER, FLOUNDER GAMMA - * ( * ) (PCI/KG(WET)) 93 < LLD (0 /1')' 1.13E+03 < LLD (0 /1 ) * (* /* ) 93 WINTER FIDUNDER GAMMA TE-132 1 ( * ) (PCI/KG(WET)) 93 < LIB (0 '/1 ) 2.23E+02 < LLD (0/1) * (*/*) ~93-WINTER FLOUNDER GAMMA ZN-65 1 . ( * ) - (PCI/KG(WET)) 93 < LLD (0 /1 ) 6.95E+01 < LLD (0 /1 ) * (* /* ) 93 WINTER FLOUNDER GAMMA CO-60 1 (- * ) (PCI/KG(WET)) 93 < LLD (0 /1 ) 2.60E+01 5.43E+03 (1 /1 ) * (* /* ) 93 WINTER FLOUNDER GAMMA K-40 1 (PCI/KG(WET)) ~( 5.43E+03 - 5.43E+03) ( *. - * ) 93 5.43E+03(1 /1 ) ( 5.43E+03 - 5.43E+03). 5.83E+02 < LLD * (* /* ) 93 WINTER FLOUNDER GAMMA BE-7 1 (0 /1 ) (PCI/KG(WET)) (* .. * ) l 93 < LLD (0 fl )
-103-
c W W W W W W l
-M iW
@.W.M-WW .
S W 18A D$7 ~ W l-.. M '
. TABLE 3-RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCIA^R GENERATING STATION JANUARY,1989'THROUGH DECEMBER,1989 ANNUAL
SUMMARY
LIE . INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED SAMPLE TYPE ANALYSIS ISOTOPE NUMBER RANGE RANGE FOR INDICATOR. OF MEAN' ANALYSES PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE 1.34E+02 < LLD (0 /1 ) * (* /* ) 93 WINTER FIDUNDER CAMMA ZR-95 1 (.* ) (PCI/KG(WET)) 93 < LLD (0 /1 ) 7.69E+01 < LLD (0 /1 ) * (* /* ) 93 WINTER FLDUNDER GAMMA NB-95 1
-(PCI/KG(UET))
(. * - *- ) 93 < LLD (0 /1 ) 1.77E+02 < LLD (0 /1 ) * (* /* ) 93 WINTER FIDUNDER GAMMA SB-125 1 { * ) (PCI/KG(WET)) 93 < LLD (0 /1 ) 1.01E+02 < LLD (0 /1 ) * (* /* ) 93 WINTER FLOUNDER CAMMA CE-141 1 (PCI/KG(UET)) (*. .
- * )
93 < LLD (0 /1 ) 7.47E+01 < LLD (0 /1 ) * (* /* ) 93 WINTER FIDUNDER CAMMA -RU-103 1 ( * ) (PCI/KG(WET)) 93 < LLD (0 /1 ) UINTER F1DUNDER GAMMA CR 1 6.65E+02 .< LLD (0 /1 ) * -(* /* ) 93 ( *- - * ) (PCI/KG(UET)) 93 < LLD (0 /1 )
-104-
E: W E. ;E (E.; E W W W W W W W W W W W W b _ k TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED.. OF RANGE RANGE. MR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE WINTER FLOUNDER GAMMA BA-140 1 4.41E+02 < LIE (0 /1 ) *- (* /* ) 93 (PCI/KG(WET)) ('* ) 93 < LLD (0 /1 ) WIMTER FIDUNDER . GAMMA IA-140 1 1.83E+02 < LLD (0 /1 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /1 ) WINTER FIDUNDER GAMMA AC-228 1 2.74E+02 < LLD (0 /1' ) '* (* /* ) 93 * (PCI/KG(UET)) ( *- - * ) 93 < LLD (0 /1 ) WINTER FLOUNDER GAMMA RA-224 1 1.93E+04 < LLD (O./1.) * (* /* ) 93 (PCI/KG(WET)) ( * ) 93 < LLD'(0 /1 ) WINTER FIDUNDER GAMMA RA-226 1 1.32E403 < LLD ~(0 /1 ) * (* /* ) . 93 (PCI/KG(WET)) -( * * ) 93 . < LLD (0 /1 ) (0 /1 )
~
WINTER FIDUNDER GAMMA I-131 1 2.04E+02 < LLD * (* /* )' 93 (PCI/KG(WET)) ( * - * ) 93~ < LLD (0 /1 ).
-105 - .- , . - , .. - ,. . ,- ,. , , - .. . ..-z,. ,r ., . . l _ .= -
- .: ,( _
3 /, =r- -gm
- ~ '
l TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION .
-JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED-OF RANGE RANGE FDR INDICATOR' ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
. RANGE-i VINTER FIDUNDER GAMMA NA-22 1 6.80E+01 < LLD (0 /1 -) * (* /* ) . 93 (PCI/KG(UET)) (. * - * )
93 < LLD (0 /1 ) WINTER FIDUNDER GAMMA RU-106 1 6.21E+02 <.LLD (0 /1 ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /1 ) WINTER FIDUNDER GAMMA CO-57 1 4.20E+01 < LLD (0/1) .
* (* /* ) 93 (PCI/KG(WET)) ( * - * )
93 < LLD (0 /1 ) WINTER FLOUNDER GAMMA I-133 1 7.08E+06 < LLD (0 /1' ) * (* /* ) 93 (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /1-). WINTER FIBUNDER GAMMA CS-137 1 7.21E401 < LLD -(0 /1 ) * (* /* ) 93 (PCI/KG(WET)) ( * .
- * )
93 s LLD (0 /1 ) AMERICAN EEL GAMMA CE-144 2 6.31E+01- < LLD (0 /2 ) * (*'/* ) !33 93 (PCI/KG(WET)) .. .( * .- *
. )
93 < LLD (0 /1 )
-106-
_ _ . _ , . - _ , _ u . . _ _ ...:,. _-- _ . ; .. _ _
~ ~ -
- 4 O ' E E E E E E E EE E E E-. E E E E: E .
TABLE.3 - RADIGIDGICAL' ENVIRONMENTAL ~ MONITORING - PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH. DECEMBER,1989 ANNUAL
SUMMARY
. SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD ' INDICATOR-MEAN(N/ TOTAL). BACKGROUND-MEAN(N/ TOTAL) STATIONS USED-0F ' RANGE RANCE FOR INDICATOR-ANALYSES - MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANCE AMERICAN EEL GAMMA AG-110M 2 l'.52E+01 < LLD (0 /2 ) * (* /* ) 33 93 (PCI/KG(UET)) ( :* ' - * ) 93 < LLD-(0 /1 ) AMERICAN EEL GAMMA TE-129M 2 2.17E404 < LLD. (0 /2 ) * (* /* ) 33. 93'- (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /1 ) AMERICAN EEL GAMMA CS-134 2 1.69E+01' < LLD (0 /2 ) * (* /* ) 33 93 (PCI/KG(WET)) ( * - * ) 93 .< LLD (0 /1 ) . AMERICAN EEL GAMMA CO-58 2 1.81E+01 . < LLD (0 /2 ) * ~ (* /* ) . 33 93 (PCI/KG(WET)) (* - * ) 93 < LLD (0 /1') AMERICAN EEL GAMMA MN-54 2 1.67E+01 < LLD (0 /2 ) *. (* /* ). 33 93 (PCI/KG(WET)) . ( * - * ) 93 < LLD (0 /1 ) , AMERICAN EEL GAMMA FE-59 2 3.92E+01 < LLD (0 /2 ) *. (* /* )- 33 93 [ (PCI/KG(WET)) ( * - * ) , 93 '< LLD (0 /1 )
.-107-i P ' -Y m + gi- ., .y.v.. 4...swM'W'.+=.egy'1- . , _ + - .N- .+p+,.' p g--sM.m> - -m,;.- aw _ _ . _ _ =g y .- . 4, _ _
-__,t_ ______j.___,g__ __ __ ., n
_ ?O 'EL E E E E-E W. E E E E 'E' E E E ' ' E ~ E[ O TABLE 3
- RADIO 1DGICAL' ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED OF RANGE- RANCE FOR INDICATOR-ANALYSES .
.MEAN.
PERFORMED . STATION STATION-MEAN(N/ TOTAL) RANGE AMERICAN' EEL GAMMA CS-136 2 2.20E+01 < LLD (0 /2 ) * (* /* ) 33 93. (PCT /C(UET)) ( * - * ) 93 < LLD (0 /1 ) AMEPICAN EEL GAMMA TE-132 2 4.18E+01 < LLD (0 /2 ) * (* /* ) 33 93 (1. * ! /KG(Wr t)) ( * - * ) 93 < LLD (0 /1 ) AMERI::AN EEL GAMMA 2N-65 2 4.87E+01 < LLD (0 /2 ) * (* /* ) 33 93 (PC1/KG(WET)) ( * - * -) 93 .< LLD (0 /1-) ! AMERICAN EEL GAMMA CO-60 2 1.94E+01 < LLD (0 /2 ) * (* /* ) 33 93 (PCI/KG(WET)) ( * - * ) 93 < LIE (0 /1 ) AMERICAN EFL GAMMA K-40 2 2.60E+01 2.16E+03 (2 /2 ) * -(*'/* ). 33 93 (PCI/KG(WET)) ( 2.12E+03 - 2.20E+03) ( * - * )
. 33 2.20E+03(1 /1 )
( 2.20E+03 - 2.20E+03) l AMERICAN EEL GAMMA BE-7 2 1.18 E+ 02 . ~ < LLD (0 /2 ) * (* /* )' 33 93 (PCI/KG(WET)) ( * -* ) 93 < LLD (0 /1 )
-108-
- 1. . - - , _ -
x .. , - , - - ~ . ; ,- , ._-+..-..a----- . . - . . -_; .. -. . _ _ _ _ _ , _ =
=. :; +
M E'- E ~ E. E E W M W E E S E: W ~E W_ W W W
? TABLE 3 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989-
. ANNUAL'
SUMMARY
LLD 3ACKGROUND-MEAN(N/ TOTAL) STATIONS USED-- SAMPLE TYPE ANALYSIS ISOTOPE NUMBER' INDICATOR-MEAN(N/ TOTAL) RANGE RANGE FOR INDICATOR-OF MEANi ANALYSES PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE
*~ 33 '93 AMERICA?T EEL GAMMA ZR-95 2 2.76E+01 < LLD (0 /2 ) - *
(* /* ). ( * ) (PCI/KG(WET)) 93 < LLD (0 /1 ) 2 1 61E+01 < LLD (0 /2 ) * (* /* ) 33 93 AMERICAN EEL GAMMA NB-95 . ( * ) (PCI/KG(WET)) 93 < LID (0 /1 ) 3.67E+01 < LLD (0 /2 ) * (* /* ) 33 93 AMERICAN EEL GAMMA SB-125 2 (PCI/KG(WET)) (- * - * ) 93 < LLD (0 /1 ) CE-141 2 1.70E+01 < LLD (0 /2 ) * (* /* ) 33- 93 AMERICAN EEL GAMMA . { * -
)
(PCI/KG(WET)) 93 < LID -(0 /1 ) RU-103 2 1.49E+01 < LLD (0 /2 ) * (* /* ) 33 93 AMERICAN EEL GAMMA - * (-* ) (PCI/KG(WET)) 93 < LLD (0 /1 ) 2 1.16E402 < LLD *~ (* /* ) 33 93 AMERICAN EEL GAMMA CR-51 (0 /2')- . (PCI/KG(WET)) ( . *' - -* ) 93 < LLD (O'/1-)
-109- ~ _
- O . E E;: E" E M E' M- E O M W'.M .
E E E : M) El E TABLE 3' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER .LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED. 5 0F RANGE RANGE- FOR INDICATOR ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL) RANGE' -AMERICAN EEL GAMMA BA-140 2 7.15E401 < LLD (0 /2 ) * (* /* ) 33- 93
-). '(PCI/KG(WET)) (
- 93 < LIA (0 /1 )
I AMERICAN EEL GAMMA IA-140 2 2.92E+01 '< LLD (0 /2 ) * , (* /* ) ~ 33 93 (PCI/KG(WET)) ( * - * ) 93 < LLD (0 /1 ) l AMERICAN EEL GAMMA AC-228 2 5.97E+01 < LLD (0 /2 ) * -(* /* ) 33 93 (PCI/KG(WET)) ( *- - * ) 7 93 .< LLD (0 /1 ) AMERICAN EEL GAMMA RA-224 2 9.91E+02 < LLD (0 /2 ) (* f* ) . 33 93. l (PCI/KG(WET)) -( ) ! 93 < LLD (0 /1 ) AMERICAN EEL GAMMA RA-226 2 2.67E+02 < LLD (0 /2 ) * (* /* ) 33 93 (PCI/KG(WET)) ( * ) 93 < LLD (0 /1 ) AMERICAN EEL GAMMA I-131 2 2.07E401 < LLD (0 /2 ) * (* /* ) 33 93 i (PCI/KG(WET)) ( * - * ) 93 < LLD (O'/1 )
-110- ~
_. ~ . _ , . . _ . , _ _,.e. ,
, .a c. _. ._ - ,.,..; __ . , - . _ . . _ . . _ . . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . . . _ _ . _ _ _ _ . ,
.W W EI E E LE. E M[ W O E S ~ W. E - E E S E O~
y .- TABLE 3 , RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK' NUCLEAR GENERATING STATION ' JANUARY,1989 THROUGH DECEMBER,1989 . ANNUAL
SUMMARY
SAMPLE TYPE ALLYSIS ISOTOPE NUMBER LLD : INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL). STATIONS USED OF RANGE' RANGE 'FOR INDICATOR-ANALYSES . MEAN
, PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE AMERICAN EEL GAMMA NA-22 2 .2.18E+01 < LLD (0 /2 ) * (* /* ) 33 93-(PCI/KG(WET)) ( *- - * ) 93 < LLD (0 /1 ) AMERICAN EEL GAMMA RU-106 2 1.51E+02 < LLD (0 /2 ) * (* /* ) .33 93: (PCI/KG(WET)) ( * ) 93 < LLD (0 /1 ) AMERICAN EEL GAMMA CO-57 2 8.64E+00 < LIE (O /2 ) * (* /* ) '33 93J (PCI/KG(WET)) (' * - * ) 93 < LLD (0 /,1 ) AMERICnN EEL GAMMA I-133 2 7.88E+03 < LLD' (0 /2-) w (* /* ) 33 93 (PCI/KG(WET)) (~* - * ) 93 < LLD (0 /1 ) l AMERICAN EEL GAMMA CS-137 2 1.68E+01' < LLD '(0 /2 )' * (* /*-) . 33 93 l (PCI/KG(WET)) ' ( ... * ) ,, 93 < LLD (0 /1-) AQUATIC SEDIMENT GAMMA CE-144 88 1.09E+02 < LLD (0 /66 ) < LLD~ .(0 /22 ). 23 -_24 25. 32' (PCI/KG(DRY)) 93 93 < LLD (0_/11 ) _ l l
-111-i i_-.___ _ _ - - , _ -_,__i=4~..
. ,W- ;_--.,_ _
...,_...a,=.__ _ _._c_ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ , _ , _ _ _ _ .
p 7-
-7 O M M1 & lM 'M- M M M M &' M ' Ml M M M M M M'
_ e w TABLE 3
- RADIOlhGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
-OYSTER'CRELK NUCLEAR CENERATING-STATION JANUARY,1989 THROUGH DECEMBER,1989~
- ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD: INDICATOR-MEAN(N/ TOTAL) " BACKGROUND-MEAN(N/ TOTAL). ~ STATIONS USED' 0F RANGE RANGE FOR INDICATOR. ANALYSES - MEAN. ..
-PERFORMED STATION STATION-MEAN(N/ TOTAL)
RANGE
. 3 AQUATIC' SEDIMENT GAMMA AG-110M 88 2.74E+01 < LLD '(O /66 ) ' < LID ' (0 /22 )
- 23. 24 '251.'32.-
(PCI/KG(DRY)) 93 93 < LLD (0 /11 ) AQUNIIC SEDIMENT GAMMA TE-129M 88 8.05E+04 < LLD (0 /66 ) < LID (0 /22 ) ' 23 24. 25. 32
- (PCI/KG(DRY)) 33 93 < LLD (0 /11 ).
AQUATIC SEDIMENT CAMMA CS-134 88 3.36E+01 < LLD (0 /66 ). < LLD - (0 /22 ) 23- 24 25 32 (PCI/KG(DRY)) 93 93 < LLD (0 /11 ) AQUATIC SEDIMENT GAMMA CO-58 88 2.15E+01 < LLD (0 /66 ) < LLD ( /22 ) 23 24 25 32 , (PCI/KG(DRY)) - 93 93' < LLD (0 /11 )- AQUATIC SEDIMENT GAMMA MN-54 88 2.13E401 < LLD (0 /66 ) < LID . '(o /22 ) 23 24 25 32.' (PCI/KC(DRY)) 93 93- < LLD (0 /11') AQUATIC SEDIMENT GAMMA FE-59 88 5.36E+01 < LLD (0 /66 ) < LLD (0 /22 )' 23 24 25 32. (PCI/KG(DRY)) 93 93 < LLD (0 /11 )'
-112-
*e+ - - - -
m- p-g. s4 w 'e- -w -,-P . ras
-. p -= g ey+ 7 g.- s
--wi..w_._4 -.. p,a r--?*__v y- __g9e yag- m.s,p*,-
e t$ M M IM W: LEI M E E S E W 'ML M E' W E E W
. . m TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM _
SUMMARY
' OYSTER' CREEK NUCLEAR GENERATING STATION JANUARY,1989 THROUGH DECEMBER,1989 l ANNUAL
SUMMARY
l- SAMPLE TYPE ANALYSIS ISOTOPE NUMBER LLD' INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) STATIONS USED: l OF RANGE RANGE, FOR INDICATOR l ANALYSES MEAN PERFORMED STATION STATION-MEAN(N/ TOTAL). RANGE AQUATIC' SEDIMENT GAMMA CS'-136 88 2.81E+01 .. < LLD (0 /66 ) < LIE (0 /22 ) 23. 24 25 :32i (PCI/KG(DRY)) 93 .; 93 < LLD (0 /11 ) AQUATIC SEDIMENT GAMMA TE-132 88 7.96E+01 < LLD (0 /66 ) < LLD (0 /22 ) 23 24- 2532( (PCI/KG(DRY)) 93-93 < LLD (0 /11 ) AQUATIC SEDIMENT GAMMA ZN-65 88 8.38E+01 < LLD (0 /66 ) < LLD (0 /22 ).' 23 24- 25L 32 (PCI/KG(DRY)) 93-93 < LIE (0 /11' ) ' AQUATIC SEDIMENT GAMMA CO-60 88 2.11E401 9.80E+01 (20 /66 ) . < LLD (0 /22 ) 23 24 ' 25 32 (PCI/KG(DRY)) ( 2.61E+01 - 1.77E+02) . 93 33 1.29E+02(11 /11 ) ( 1.05E+02 - 1.77E+02) AQUATIC SEDIMENT GAMMA K 88 1.60E402 7.03E+03 (66 /66 ) 1.33E+04(22 /22 ) 23 24 '25 32. (PCI/KG(DRY)) ( 5.33E+02 - 1.60E404) ( 6.11E+03 - 1.91E+04) 93 4 33 1.15E+04(11 /11 ) ( 5.59E+03 - 1.60E+04)
~
AQUATIC SEDIMENT GAMMA BE-7 88 1.31E+02 3.33E+02-(19./66 ) 2.56E+02(3 /22 ) 23 24 25' ;32 (PCI/KG(DRY)) ( 1.17E+02.- 1.76E+03) ( 1.31E402 - 3.54E+02). 9 3 -- 24 6.39E+02(4./11 ) ( 2.03E+02, - 1.76E+03) ,
-113-m.a-m % r pg *.e,w.i--A.
. r.wa em-s s y e- .,,.9 *taf r- ,an*bw-pia g y. -.e.--yMg' yep
-+'., @ .a.*w'+ewvr-wg 9 mar ,, .pe+q -.
.ys- .wa yy w- -
yy
, , ^ ! , . , &- DR EO ST 2
3 2 3 2 3 2 3 2 3 2 3
^
UA 5 5 5 5 5 5 C 2 2 2 2 2 2 SI ND M ON '4 4 4 4 4 4 II 2 2 2 2 2 2
. T N ARA ~
TOE 33 33 33 33 33 33 SFM 29 29 29 29 29 29
& )~
L
. A' T' ) ) ) ) ) ) '
O M T~
/
.),
L 2 2 2 2 2 2 2 2 2 2 2' 2 - N (' A / / / / / / - ._ T _ N O 0 0 0 0' 0 0 _ AE T ( ( ( ( ( ( _ EG / ) ) ) ) .) ) , M MN . N( DR
- A N
1 1 1 1 1 1 1 1 1 1 1 1 N A . D / D / D / D / D / BI ' / _
~ U EE L L L L' L _
O MG L 0 L O L 0 L 0 L _0 L~ 0 Y R N ( ( ( ( ( ( M R A G K NA
. OR D
D
< D
< D '< D D -
M C' I L L L L L L M A T L L L L L L _ U B A S T < < < < .< <
& M AN S
RO9 GI8 OT9 ) N O 3 9 3 9 3 9 3 9 3 9 3 9 RA1, L I - PT A' T M G SR E T O A T
) ) ) ) ) ) .
NGB T' S 6 6 6 6 6 6 INM / 6 6 6 6 6 6 RIE N' / / / / / / OTC ( - - TAE N M IRD NE YE A 0 ( 0 ( 0 ( 0 ( 0 ( 0 ( 4 1 1 ONHRM - MEGA - GUMR
.. 3L OMOE D D D D D D -
O ARRUTG
. ETAHSAN' LNET CA L
L L L L L L L L L L L BEL LIR '< < < < < < . AMC9AD TNU8UN ON9NI M- .R IK 1, N VEY A 1 0 1 0 1 0 1 0 1 0 2 0 NER D + 4 + + 4 + ERA L E E E E E E CU L 0 5 5 5 4 2
.L N
$ ARA CEJ IT SE D
7 3 2 2 5 4 7 2 8 1 5 1 GS EM . OY R SR LO E YO 8 8 8 8 8 8 O B LF 8 8 8 8 8 8 - M I D A M UFNE NOAP AR R , E 5 1 3 P 5 5 2 4 0 1 O 9 9 1 1 1 5 M T O R B B E U R S Z N S C R C I M. S M. I S Y L A N A M M A A M M A A M M A A M M A A M M A A M M A A G G G G G G . T O T N) E) T N) E) T N) E) N) E) T N) E) T N) E) MY MY MY MY MY MY - I R IR I R I R I R I R E DD DD DD DD DD DD P E( E( E( E( E( E( M Y T SG C/ K SG C/ K SG C/ K SG C/ K SG C/ K SG C/ K - E II II II II II II L TC TC TC TC TC TC P AP AP AP AP AP AP - M U( U( U( U( U( U( A Q Q Q Q Q Q S A A A A A A -
.! t
; d',
{ : 2 2 2 2 2 2
~
eMg , DR EO ST 3 3 3 ~3 3 3 _ UA 5 5 5 5 5 5' C 2~ 2 2 2 2 2 SI ND _M_ ON II' T N 4~ 2 4 2 4 2 4 2 4 2 4' 2 . ARA - TOE 33 33 33 33 33 33 SFM 29 29 29 29 29 29 . BM ) L
')
A ) T ) ) ) ) )' ) ) ) O 22 2 23 3 M T
/
)
L 2 2 2 2 20
/+
0
+
2 2 20~
/+
0
+
2' 2 N (' A /' / E E / E E / _ T 23 7 23' 1 N O 0 0 26.)0 0' 25.)6 0 AE T ( ( ( ( - ( ( EG / ) - ) 2717 ) 3 l' 11 ) M MN A N ( 1 1 0
+ - / -
1 1 0
+ - / -
1 1 DR N 1 1 E 1 E 1 N A D' / D / 4212 D / 5212 E ,/ U EE L L 6010 L 1010 I O MG L 0 L 0 + ( + L 0 +( + L . 0 Y R N M R A G K NA OR ( D ( D 5E2E 608
+4
( D 1E3E 704
+1
( E M C I L L 4. E L 7. E I M A T' L L 382 L 509 L U B A 0. ( S T S
< < (
.5' <. ( 3. (
. 1 S M AN RO9 GI8 N 3 3 5 3 3 3 OT9 ) O 9 9 2 9 .
3' 9 RA1, LA I ) )
~M PT G
SR E T O T A T
) )
)2 6+
0 )
)3 6+
0 ) NGB T S 6 6 6E 6 6E 6 INM / 6 6 /0 6 /1 6
~ RIE N / / 2 / 6 /
OTC ( 6 5 - O TAE IRD NE N~
-A YE 0
( 0 ( 68 ( 0 ( 61 ( 0 ( 5 1 1 NHRM 2 2 - MEGA - 01 02 GUMR~ +0 40 3L OMOE D D E4 D E+ D N ARRUTG ETAHSAN LNET CA L L L L 9E 18 8 L L 2E
- 7. 7.
0 L L BEL LIR < < 4 < 9 < AMC9AD 9 2 TNU8UN ON9NI ( ( M R IK 1, N VEY A 1 0 1 0 1 0 3 0 0 2 1 0 NER D + + + + + + ERA L E E E E E E CU L 1 1 0 9 9 4 L- N 0 9 0 3 4 0
& ARA CEJ IT' SE D 9 3 5 2 2 3 GS^ EM OY R SR LO E YO 8 8 8 8 8 8 O B LF 8 8 M I D
M UFNE AR 8 8 8 8 A NOAP R E 0 0 8 4 6 P 4 4 2 2 2 1 O 1 M T O 1 A A 2 C 2 A 2 A 3 1 S B L A R R I I M S I
.M S Y
L A M A M A M A M A M A M A M M M M M M N A A A A A A A G G G G G G T N) E) T N) E) T N) E) T N) E) T N) E) T N)~ E )' MY MY MY MY MY MY IR IR IR I R I R IR E DD DD DD DD DD DD P E( E{ E( E( E( E( M Y T SG C/ K SG C/ K SG C/ K SG C/ K SG C/ K SG K E II II I I II I I C/ II L TC TC TC TC TC TC P AP AP AP AP AP AP i& y M A S U( Q A U( Q A U( Q A U( Q A U( Q A U( Q A
mM M M M M M mM M e m -
^
mmeW - b' TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OYSTER CREEK NUCLEAR GENERATING STATION' JANUARY,1989 THROUGH DECEMBER,1989 ANNUAL
SUMMARY
SAMPLE TYPE ANALYSIS ISOTOPE NUMBER .LLD INDICATOR-MEAN(N/ TOTAL) BACKGROUND-MEAN(N/ TOTAL) '
. STATIONS USED OF RANGE RANGE FOR INDICATOR
~
ANALYSES MEAN PERFORMED' STATION STATION-MEAN(N/ TOTAL) RANGE AQUATIC' SEDIMENT GAMMA NA-22 88 2.81E+01 < LLD (0 /66 ) < LLD (0 /22 ). 23 24 '25-.32 , (PCI/KG(DRY)) 93 93 < LLD_(0 /11 ) AQUATIC SEDIMENT GAMMA RU-106 88 1.66E+02 < LLD (0 /66 ) < LLD (0 /22-) 23 24 25 32-93 (PCI/KG(DRY)) 93 < LLD (0 /11 ) AQUATIC SEDIMENT GAMMA CO-57 88 1.36E+01 < LLD (0 /66.) < LLD (0 /22 ) 23 24 25'- 32. (PCI/KG(DRY)) 93 93 < LLD (0 /11 ) AQUATIC SEDIMENT GAMMA I-133 88 5.30E+05 < LLD (0 /66 ) < LLD (0 /22 ) 23 24 25 32 (PCI/KG(DRY)) 93. 93 < LLD (0./11-) AQUATIC SEDIMENT GAMMA CS-137 88 1. 44 E+ 01 7.99E+01 (45 /66 ) 7.61E401(21 /22')' 23 24 25 .'32. (PCI/KG(DRY)) ( 1.22E+01 - 2.48E+02) . ( 1.52E+01 - 2.12E+02)' 93 33 1.84E+02(11 /11 ) ( 1.19E402 2.48E+02) 1
-116-
_--_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ - ~
= - - - ~ :. - -- -- - - - . ~ = - , - - = = . - ~ ,.- , :---. . u~ ~ ~ = - -
.' 'E t
DIRECT RADIATION MONITORING b
' Dose rates from external radiation' sources were measured at a number of locations in the vicinity of the OCNGS using thermoluminescent dosimeters :
(TLDs). . Naturally occurring sources, including radiations of cosmic origin and natural radioactive materials in the air and ground, as well as fallout
- from prior nuclear weapon testing, resulted in a certain. amount of ,
penetrating radiation.being recorded at all monitoring locations. Indicator TLD's'were placed systematically with at least one station in each of'16 '! cardinal l compass sectors (in a ring) at the site at a maximum distance of 1.5 miles. TLD's were also placed within a five mile radius of the OCNGS,.in j locations where,the potential for deposition of radioactivity is known to be high, in areas of public interest, population centers, and in background-locations which are typically greater than ten miles distant from the OCNGS. I samole collection and Analysis 1 i I A state-of-the-art thermoluminescent dosimeter is used. Thermoluminescence ,
. is a process in which ionizing radiation, upon interacting with the sensitive; material of the TLD (the phosphor or ' element') causes some of the energy j deposited in the phosphor to be stored.in stable ' traps'-in the TLD. i I, material. These TLD traps are so stable that they do not decay appreciably' !
over the course of months or even years. This provides an excellent method of integrating the exposure received over a period of time. The energy stored in the TLD's as a result of interactions with radiation is removed and measured by a controlled heating process in a calibrated reading system. Att the TLD is heated, the phosphor releases the stored energy as-light. The ; I 1 amount of light given off is directly proportional to the radiation dose-the TLD received. The reading process ' zeros' the TLD and prepares it for reuse. The TLD's in use for environmental monitoring at the OCNGS are-capable of accurately measuring exposures between 1 mrem (well below normal environmental levels for the quarterly menitoring periods) and 1000 REM. iE During 1989, TLD's were collected every twelve weeks from locations ranging from less than 0.2 miles to 35.1 miles from the OCNGS. Four GPUN Panasonic TLD's and one vendor supplied (Teledyne Isotopes) TLD are exposed at each of 63 monitoring locations. GPUN TLD's provide sixteen independent detectors
-117-
t " p , 4 . at each station. ' Vendor ~ supplied TLD's provide an additional four independent measurements. This provides 19 redundant detectors at each I station. In addition, two of the 63 monitoring locations are quality-control (QC) stations at which 4 additional GPUN TLD's and one vendor supplied TLD are exposed for quality control purposes. . Forty independent measurements are l I made at these locations. Results All TLD dose rate data presented in this report have been normalized; GPUN TLD results to a standard quarter (91.3 days) and vendor supplied data to a
; 1 standard month (30.4 days). The data are normalized to eliminate differences N' caused by slightly differing exposure periods. TLD dose rate data are.
presented in Tables J-1 and J-2 in Appendix J. I In'1989, the dose rate measured at indicator stations using vendor supplied (Teledyne Isotope) TLDs Sveraged 3.9 mrem / standard month and ranged from 3.0 > to 5.7 mrem / standard month. The dose at background TLD stations, located U I greater than 30 miles from the OCNGS, averaged 3.9' mrem / standard month and ranged from 3.3 to 4.7 mrem / standard month. The mean dose rates from indicator and background stations were the.same suggesting that OCNGS~ operation contributed little if any to off-site exposure., These results;are consistent with the results of measurements from previous years (Fig. 6). The standard deviation of dose rates ranged from 0.1 to 0.9 mrem / standard I month. Considering this range of standard deviation, no relationship.between 1 ~ j> dose rate and distance from the OCNGS was observed over the four quarterly , n t. l; sampling periods (Fig. 7). m y -. f .Regarding GPUN TLD data, the mean dose rate from indicator stations was 10.28 mrem per standard quarter with a range from 7.71 to 14.",0 mR per standard quarter. The background mean dose rate, from stations greater than 30 miles from the OCNGS, was 10.93 mrem per standard quarter with dose rates ranging
- from 9.48-to 12.70 mrem per standard quarter. Background dose rates were higher than indicator dose rates again suggesting that OCNGS operation had
- little if any affect on off-site exposures. The standard deviation of dose M re.es ranged from 0.11 to 11.54 mrem per standard quarter. Considering these data, no relationship between dose rate and distance from the OCNGS was observed over the four, quarterly sampling periods (Fig. 8).
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, - mir aus asIsup: amm emp aus sum. aus as as ama enn muni es em e en b
~
MEAN TELEDYNE TLD: GAMMA DOSE 1984L-- 1989f OYSTER. CREEK RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM DOSE IN MILLIREM PER STANDARD MONTH - 10-4 9-8- - BACKGROUND MEAN 7- . INDICATOR MEAN " 6-V h. i e -c. n 5- y 3 4- \( a \ ; L 3-2- 1-0- 1 I I I I I I i l- 1 I I i i i I -l I i i i 1 1 1 I 8 8 8 88 8 8 .8 -8 8 8 8 888 8 - 8. 8 8: 8 8 -8 8 8-- 19 4 4 '4 4 5. 5-.5 5:6'6 6 6 .7 7. 7
.7 8 8- 8l 8 9. 9 9. 9 0-1 2 3-4 1 2' 3 4 1 2::3- 4 1 23 4 'l 2 3 - 4' -1 2' 3: 4: 1
' YEAR / QUARTER
.. . .. - ,. . - = - = - -
s _ - . . M. M 'M iML M M M m' M MM M M MM M M M M_
.MEAN TELEDYNE ISOTOPE:TLD GAMMA DOSE FOR'1989 BASED'ON-DISTANCE.FROM REACTOR - ~
OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DOSE IN. MILLIREM PER STANDARD MONTH l 10- j 9- I
~'
OVER 5 MILES 8-2 TO 5 MILES 7-I 'O TO 2 MILES 1 .! 8 6- 8 ^ i g 5" 4-c e 3-2J 1-a 0-I I -1 1 I 89-1 89-2 89 89 90-1' YEAR / QUARTER
. = , - - .=, . = . x .= . - - - - .a . . - . . .. - . . .
g-- .- : - . -- - m - e sus Jag alle eum a ens e er m sum, ens .eus a m m ;mm;; e
.g
-MEAN PANASONIC TLD-GAMMA DOSE FOR 1989 BASED ON1 DISTANCE FROM. REACTOR':
OYSTER CREEK RADIOLOGICAL' ENVIRONMENTAL MONITORING PROGRAM '
- DOSE IN MILLIREM PER STANDARD MONTHi 10-9-
OVER 5 MILES 8-2 TO 5 MILES 7-1 0 TO 2 MILES 3 S 6- E s g 5-4- A 1" 2 3-1- 0-1 I 'l i 1 89-1 89-2 89-3 89 90-1
-YEAR / QUARTER:
'.,.,-.~,,,4',, . 4 '. c .
.. m . ,.,S . . , . . _ . =
_ _ _ _ _1.._ ___ _ _ _ . .,____m_.____m ,__.m_ _ _ , _ _
) i 4 ATMOSPHERIC MONITORING I A primary' exposure pathway to man is the inhalation and ingestion of radionuclides _ released to the atmosphere. Radioactivity in ambient air-was sampled by.a-network of thirteen continuous *y operating air samplers. Precipitation samples-were also collected at these thirteen locations.. ! I, Indicator air sampling and precipitation stations are located in-prevailing, downwind directions, local population areas, and areas of ; public and special interest. All indicator stations are located within-6.5 miles of-the OCNGS. Background air sampling and precipitation-
- stations are. located greater than 17 miles from the site in Lakewood, Allenhurst, Cookstown, and Hammonton, NJ.
I samole collection and Analysis Mechanical air samplers are used to continuously draw a recorded volume of air through a glass fiber (particulate) filter and then through a charcoal cartridge. A dry gas meter, which is temperature compensated, is-used-inside the air sampler to record air volumes.- Internal vacuums are also I measured in order to pressure correct the indicated volume. ..All air samplers are maintained 'and calibrated by GPU Nuclear iristrument and control technicians. The particulate filters were collected weekly and analyzed for gross beta j radioactivity. The filters were then combined monthly by individual ,
-station locations and analyzed for gamma-emitting radionuclides.
I Charcoal cartridges, used to collect gaseous radioiodines, contain' a activated charcoal.- Charcoal cartridges were collected weekly and I analyzed for iodine-131 (I-131) activity. Precipitation samples were collected monthly using an eight-inch diameter
' funnel that drains into a collection container. Each sample was analyzed for tritium and gamma-emitting radionuclides.
I -122-
- } ' ,
3: 'l Results I During 1989, 676, gross beta analyses were performed on air._particulateL filters (Table'3). The background mean gross beta activity (0.0163 pCi/m3 )~ was slightly higher than the indicator mean (0.0157' pC1/m3) . I and all gross beta analysis results were within two standard deviations of-
=the historical-mean.
'i Figure 9 presents the'1989 weekly mean gross beta concentrations for indicator and background stations. Note that the indicator station means-are virtually identical to the background-station means. These results are consistent with the results of gross beta analyses of air samples from I -
previous years-(Figure 10). The air particulate gross beta' analysis-results-clearly show that offluent containing gross beta radioactivity j from OCNGS operation did not have any measurable impact on the local. environment. .l t Air charcoal cartridges (676 samples) were analyzed for iodine-131 (I-131) and~no'radioiodine was detected in any of the samples (Table 3). One.
- 8. .
. iodine-131 result could not meet the required sensitivity. This was caused when the air sampling apparatus at a background station in I Lakewood, NJ failed after drawing a relatively low volume (140.9 cubic meters) of air (an average volume of approximately 600 cubic meters is j
normally collected during the sampling period). Gamma isotopic analyses were performed on 169 air particulate filter composites (Table 3). The only radionuclide identified was naturally occurring beryllium-7 (Be-7) which cannot be attributed to effluents from I the OCNGS. With regard to precipitation sampling, 24 gamma isotopic and 24 tritium analyses were performed during 1989 (Table 3). Tritium activity was , detected in one indicator sample. This tritium activity (234 pC1/ liter) was only 12 percent of the lower limit of detection specified by Oyster Creek Technical Specifications, cnd 1.2 percent of the EPA's drinking
-123-
num uma es um!s: man e e:s e e eum aus sua e am ums 31 g - muu ens - l -WEEKLY MEAN AIR' PARTICULATE GROSS: BETA CONCENTRATIONS. L OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM q
-RESULTS IN PIC0. CURIES PER CUBIC METER.
1 ! 0.40-t 0.35-0.30-1 T 0.25- -3 s c. n p 0.20-BACKGROUND MEAN- .: 0.15- ] INDICATOR.MEAN 1 0.10-0.05- j g,gg _ N ==::
; I l i I I I 1 i i l' I .-l I JAN FEB MAR .APR MAY- JUN .JUL - AUG -- SEP 0CT .NOV - DEC i
~
2 ->___.____ --._ -*-' '~e-
' *-- ' + 's_ - _ _ -< "
-_-___t__--_:-' ';'- ' "-~Nwa=__-'-- v ~ ' '" t __=s -~ F 'r
insa . aus sus um sum ens sus eum up aua sum: .suus. e m :i m i ens mus: sus num aus AIR PARTICULATE GROSS BETA. CONCENTRATIONS 1984 - 1989' -
' OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL' MONITORING PROGRAM RESULTS IN'PIC0 CURIES PER. CUBIC-METER- ,
l .. 0.5 - 0.4 - BACKGROUND MEAN i 0.3 - , c 5-T 8 E
" CHERNOBYL Y 0.2 - :
!) .
t i f INDICATOR MEAN ' O.1 - k -> 0.0 - i i i I i I I I I I 1 I I I I I i i 1. i I i :l l- 1 8 8 8 8 .8 8 8 8 8 8 8 8 8 8 8 8 8 8- 8 8 88 ' 8 8 9 ' 4 4 4 4 5 5 5 5 6 6 6 6 7 7 7 7- 8 81 8 9 99 9 ~0. i l 1 2 3 4 1 2 3 4;1.2.3 4 l' 2 3 4 1 2- 3 :4 1 .2 4 1_ ,. YEAR / QUARTER'
-- - . -.-- - - - - _ . -- ..-- - - - -. - - _ _ - - _ - - _ - _ - _ = - - _ . .-
# a ,
a d + , l G
- water. limit. ~considering the'large: environmental' inventory.of tritium due
' to cosmic? ray interactions and. nuclear weapons testing, it is' highly- l unlikely that the relatively minuto amount of tritium in OCNGS's. effluents.
could have a measurable effect on existing' environmental. concentrations,
'h No' detectable levels of gamma radioactivity were observed in precipitation --
- samples (Table 3)..
u- . a I I 1 I ,
-1 k
,T 9
I .! i
^
I I-
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-126-
r [ l AOUATIC MONITORING
' Brackish water,from Barnegat Bay is drawn in through the south branch of Forked River, pumped into the OCNGC cooling systems, and then discharged g to Barnegat Bay'via Oyster Creek. Fish, clams, and crabs are harvested' ,)
=
from the bay on a recreational and, to a limited extent, commercial 1 basis. . The ingestion pathway is addressed because of fish,: clam, and' crab.
'g.j W _ consumption.
On occasion,7 a radioactive liquid release is discharged under the limit.s : established in the OCNGS Technical Specifications and 10CFR20. Highly i purified water, containing traces of radioactivity, is discharged into Oyster Creek which has a minimum flow rate of slightly under one-half ' I million gallons per minute. There were 42 liquid releases made from the OCNGS during 1989. Samples of surface water, sediment, fish, blue crab, 'l and hard clams were routinely collected from the OCNGS intake and discharge canals, Barnegat' Bay, Manahawkin Bay, and Great Bay.in order to monitor any environmental impact that may be associated with these releases. samole collection and Analysis surface water, sediment, and clam. samples were collected every four l weeks.1 Grab samples of-surface-water and sediment were collected.from six ? j 1
-indicator stations and two background stations. . Grab samples of clams j were collected from three indicator and two background stations.- Three l indicator stations for surface water and sediment are located in the OCNGS discharge canal - Oyster Creek. No clams are available to be collected at these stations. Three indicator stations are located in Barnegat Bay in close proximity to the mouth of Oyster Creek. One background station is I ..
located in Manahawkin Bay, approximately 11 miles south of the OCNGS. A second background station is located approximately 22 miles south of the OCNGS in Great Bay. LI I ""~ I .
I J Blue crab and fish samples were collected every our weeks (when available) from two indicator stations and one background station. Both i indicator stations are located in the OCNGS discharge canal and the background station is located in Great Bay. Crab pots were used to catch blue crab. The hook and line technique was used to catch fish. A11' samples were analysed f or ganna-omitting nuclideep weter samples were also subjected to tritium analyses. i Kasults surface water was sampled 104 times at eight different locations during , 1989. One gamma emitting nuclide, potassium-40, (K-40) was detected (Table 3). Also detected was tritium (H-3) activity which was found in $ I samples (Table 3). Both of these radionuclides are naturally occurring and found in great abundance in salt water. Based upon these data, operation of the OCNGS had no detectable affect upon the local surface water. r I Sixty-five clam samples were collected from five different locations f I during 1989. Gamma isotopic analyses indicated that the only gamma-emitting nuclide present was potassium-40 (K-40) which is naturally occurring and commonly found in st.it water (Table h;
- _ Six gamma-emitting nuclides were detected in the 88 sediment samples ,
collected during 1989 (Table 3). Four of these radionuclides, , bery111um-7, potassium-40, radium-226, and actinium-228 are naturally occurring and were seen frequently at both background and indicator _g a stations. cesium-137, which is a fission fallout product and also , occurred in OCNGS affluents during 1989, was also seen at both background and indicator si ut.lons. Cesium-137 has been detected in considerable , abundance after weapons tests and the Chernobyl accident. The presence of this radionuclide in similar concentrations in 96 percent of the backgro.tnd samples and only 68 percent of the indicator samples (Table 3)
~
I suggests that most of the r esivm-137 in Barnagat Bay sediments originated from the latter two source.s. t
+
1
-128-I
l I i i Cobalt-60 was detected in thirty percent of the indicator station samples and none of the background station samples (Table 3). The presence of this radionuclide in Barnegat Bay sediments is of interest because it can be attributed to OCNGS liquid effluents. As documented in previous I reports, OCNGS relat3d cobalt-60 has been found in sediment and clams from Barnegat Bay since at least the mid-1970's. The volume of liquid effluents has been significantly reduced since that time and this decrease in the rate of input of cobalt-60 to the environment, combined with the radioactive decay of the existing inventory, has resulted in a gradual r decline in the cobalt-60 concentration in sediment and clame (Figs. 11 and 12). The last detectable concentration of this radionuclide in clams was . during the third quarter of 1987 (Fig. 11). Thirteen blue crab sumples were collected from three locations during I 1989. A gamma isotopic analysis was performed on each sample of crab meat and naturally occurring potassium-40 (K-40) was the only radionuclide ( identified (Table 3). The close association of this epocios with Barnegat o Bay sediments could make it susceptible to cobalt-60 uptake. However no detectable cobalt-60 activity has been observed in blue crab samples , collected since 1985 (Fig. 13). l Twenty-seven fish samples, yielding six species, were collected from 3 sampling locations during 1989. The species and number of samples collected are listed below: l-TABLE 4 , SPECIES OF FISH CAUGHT AS PART OF THE OCNGS REMP IN 1989 E13]} Number of Sarroles Tautog 11 1'Wl Bluefish American Eel 9 2 l Summer Flounder 2 I Weaktish Winter Flounder 2 1 I lI .
-129-I .
mmme ee e e e ee eeeeee L COBALT-60. CONCENTRATION IN CLAMS 1984 - 1989 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *
- RESULTS IN PCI PER KG (WET)
I l l 50 J : l MISSING DATA DUE TO ICE COVER /IACK OF MEDIA CAUGHT 40-i i 30- , , f 6 C E
- y m i i- = !
l 20- '
- BACKGROUND MEAN INDICATOR MEAN l
10-
/
I 0- F - - - - - :---- k -- I i I I I ! 1 I I I I I I I ! I I I I I I I I I I 8 8 8 8 8 8 8 88 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 9 i j 4 4 4 4 5 5 5 5 6 6 6 6 7 7 7 7 8 8 8 8 9 9 9 9 0 4 l 1 2 3 4 1 2 3 4. 1 2 3 4 1 2 3 4 1 2 3~ 4' 1 2 3 4 1 j YEAR / QUARTER
ma sus sa sua e muu aus en aus aus an em age sus aus em aus aus as-COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT 1984 - 1989 OYSTER CREEK RADIOLOGICAL ENVIRONMEh"rAL MONITORING PROGRAM RESULTS IN PICOCURIES PER KILOGRAM (DRY)- 5004 450- INDICATOR MEAN 400~ BACKGROUND MEAN 3501 1 J 300
,b250} f h ' h 200 J w 1501 f
100-50- - 4 #--* 0, - ----= - >(^- I I I I I I I I I I I I I I I I I I I ! m i I I I I 8 8 8 8 8 8 8 8 8 8 8 8 8 8 6 8 8 8 8 8 8 9 8 8 8 5 6 6 6 6 7 7 7 7 8 8 8 8 9 9 9 9 0 4 4 4 4 5 5 5 1 2 3 41 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 YEAR / QUARTER
mW W W im W W m' . m ~m W m m m m m m g-COBALT-60 CONCENTRATION IN BLUE CRAB 1984 - 1989 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 RESULTS IN PIC0 CURIES PER KILOGRAM (WET) 50-i i 40- NOTE: MISSING DATA DUE TO LACK OF MEDIA CAUGHT l
; 30- 3 i g t M A !
BACKGROUND READING - l i 20-
" l '
i ' INDICATOR MEAN
- 10- :
l 0- - i I i l i I I I i l I i i i i l I I I I i i I i i I 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 9 i i 4 4 4 4 5 5 5 5 6 6 6 6 7 7 7 7 8 8 8 8 9 9 9 9 0 ; i I _ _ _ _ _ ____________________ l 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 l ! ! YEAR / QUARTER
. . . . . . . . . -. . . _ _ .. . . . , . . _ . _ . _ , - , . . . . _ . . . _ , _ _ ...~_.__....-.s.__ _________m_.._._ _. _..___ . _ ___ _ _ _ _ _ _
l t Naturally occurring potassium-40 (K-40) was detected in each of the 27 gamma isotopic analyses (Table 3). One bluefish sample, collected from indicator station 93, had a detectable quantity of costum-137 (Cs-137) radioactivity. As discussed above, cesium-137 is a ubiquitous fission , fallout product and has been detected in considerable abundance after weapons tests and the Chernobyl nuclear accident. It was also discharged ] in very small quantities (Table 2) from the OCNGS during 1989. The level I .of co-137 activity in this fien (16.5 pci/kg (wet)) was only 11 percent of_ the lower limit of detection and 0.8 percent of the reporting level l specified by the OCNGS Technical specifications. Similar low levels of this radionuclide are found in fish throughout the world as a result of , fh11out (Ref.20). I l I ! I I , I~ I I L I LI I . 9
I I TERRESTRIAL. MONITORING . i Radionuclides released to the atmosphere may be deposited on soil and vegetation and may be incorporated into milk, vegetables, and/or other food products.- To assess the impact of dose to humans from the ingestion 'I pathway, food product samples such as green leafy vegetables were. [ collected and analyzed during 1989. Surface soil samples were also I collected and analysed for the purpose of monitoring the potential buildup of atmospherically deposited radionuclides. I The contribution of radionuclides from the OCNGS operation was assessed by comparing the results of samples collected in prevalent downwind [ locations, primarily to the southeast of the site, with background samples collected from distant and generally upwind directions. A datry census was conducted to determine the locations of conenercial
- dairy operations and milk producing animals in each of the 16 meteorological sectors out to a distance of five miles from the OCNGS.
The census showed that there were no dairy animals within a.5 mile radius of the plant (Appendia F). t GPUN Oyster Creek Environmental Controls established and maintained two-t gardens near the site boundary in the two sectors with the highest I potential for radioactive deposition in lieu of performing an annual garden census. Both gardens are greater than 50 square meters in size and ,
; produce green leafy vegetables. A commercial farm located cpproximately i 24 miles northwest of the site was used as a background station.
I Samole Collection and Analysis
?
7-l Broadleaf vegetables, specifically cabbage and collards, were collected on a monthly basis beginning in June and ending in October 1989. A gamma isotopic analysis was performed on each sample. ; surface soil samples from the gardens were collected during June and
' September. Each soil sample was subjected to a gamma isotopic analysis.
LI
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cy ,
-i Results Naturally occurring potassium-40 activity and beryllium-7 activity was detected in cabbage and collard samples (Table 3). Potassium-40 was I
I
-detected in 100% of the samples collected from both indicator and background stations. Bery111um-7 was detected in 4 of 17 samples j collected, but seen at indicator stations only. ' Cesium-137 activity was detected in 2 of 17 samples collected, but observed only in collard indicator samples (rigure 14). In regard to the cesium-137 activity detected, the maximum concentration was 36.8 pci/kg (wet) which is only 46 ,
percent of the lower limit of detection (80 pci/kg (wet)) and 1.8 percent I of the reporting level (2000 pCi/kg (wet)) specified by the OCNGS Technical Specifications. Cesium-137 was detected in soil samples coils,cted from the gardens in which the vegetables were grown (Table 3).
, closer analysis reveals that the background mean was slightly higher than
.the indicator mean concentration. It is well established that root uptake of Cs-137 from soil is minimal and that foliar absorption is the main-
. pathway of Cs-137 to the food chain (Ref. 20). These results suggest that I the cesium-137 detected in vegetables collected at the indicator stations
.was atmospherically deposited rather than taken up from the soil. As no ,
cesium-137 activity was detected in OCNGS gaseous effluents during 1989, it is likely that the trace amounts of this nuclide found in collards originated from previous weapons testing and the Chernobyl nuclear i accident. In addition to the cesium-137 activity, naturally occurring potassium-40, actinium-228, and radium-228 activity was observed in all soil samples collected from indicator and background stations (Table 3). l
.I.
I LI l
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]
I !
. . - . . .-- . . - . _ - ._______-______-l
me WB em e e as aus e an e en m e as e e em ;Eas e MONTHLY MEAN CESIUM-137 AUTivrrf IN COLLARDS ; OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM: _ RESULTS IN PIC0 CURIES PER KILOGRAM (WET) 200 J i I INDICATOR MEAN 150-3 1 O g; BACKGROUND READING g ; y 100- m 1 I i [' l 1 50-i
"' ~ "' ' ~
0-l I i 1 1 I I I I I I I JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC t YEAR -1989 j
'1 NOTE: DATA ONIX AVAIIABLE DURING MEDIA GROWING SEASON-
I GROUNDWATER MONITORING r The oyster Creek Nuclear Generating Station is located on the Atlantic Coastal Plain Physiographic Province. This Province extends southeastward from the l Fall tone, a topographic break that marks the boundary between the Atlantic Coastal Plain and the more rugged topography of the Piedmont Province. The ; I Fall tone is also where the crystalline and sedimentary rocks of the Piedmont l and the unconsolidated coastal plain sediments meet. At~1 east five distinct bodies of fresh groundwater or aquifers exist in the vicinity of the OCNGS. From the surface downward,-they ares ; I 1. Unconfined, Recent and Upper Cape N6y Formation a I 2. 3. 4. Confined, Lower Cape May Formation Confined, Cohansey sand Confined, Upper Zone in the Kirkwood Formation '
- 5. Confined, Lower tone in the Kirkwood Formation The unconfined Recent and Cape May Formations are replenished directly by local precipitation. The recharge to the confined aquifers occurs .
f I primarily from direct rainfall penetration on the outcrop areas, which are generally to the west of the site at higher elevations. I Samole Collection and Analysis As part of the routine REMP, six wells were sampled on a monthly basis. Grab samples were obtained from five local residences and one OCNGS well. The depths of the residential wel.ls are unknown but most local domestic wells draw upon the Cohancey aquifer; the OCNGS well is approximately 380 feet deep, in the Kirkwood formation. Each sample was subjected to a I tritium and gamma isotopic analysis. In addition, a well network (17 wells) was installed around the OCNGS in 1983 to serve as an early detection and monitoring system for spills, I I '
-137-
E , D . L
- l. g ' i
!g ; I separate from routine REMP sampling. During 1989, fifteen of these wells located in the Cape May, Cohansey and Kirkwood aquifers, were sampled I semiannually using grab sample methodology. The samples were analyzed for tritium and gamma emitting nuclides. 1 I* Results -) i seventy-two routine REMP well water samples were collected during 1989 (Table 3). No gamma-omitting nuclides were detected in any sample. ! Tritium activity was detected in two indicator samples and one background sample. These results were not considered significant because the level . of tritium was only one percent of the EPA drinking water limit and less than 12 percent of the lower limit of detection required by the OCNGS ,
)
I' Technical Specifications. l The results of the analyses of 28 samples from the OCNGS spill monitoring j well network were similar (Appendix H). No gamma-omitting nuclides were " detected and tritium activity was detected in only two samplas. The . maximum tritium level (2100 pCi/ liter) was less than eleven percent of the EPA drinking water limit. Censidering the very large environmental I inventory of tritium due to cosmic ray interactions and nuclear weapons testing, it is highly unlikely that the relatxvely minute amounts of i tritium in the OCNGC's effluents could have a measurable effect on existing environmental concentrations. 3 I I I I I
-138-
m . . . .
~,
h i l
.E ;
RADIOLOGICAL IMPACT OF OCNGS OPERATIONS ; I An assessment of potential radiological impact indicated that radiation doses to the public from 1989 operations at OCNGS were well below all ! applicable regulatory. limits and were significantly less than doses j received from common sectces of radiation. The 1989 whole body dose [ t potentially received by an assumed maximum exposed individual from OCNGS i liquid and airborne effluents was conservatively calculated to be about I 0.522 millirem total or only 2.09 percent of the OCNGS Technical Specification limit. The 1989 whole body dose to the surrounding population from OCNGS liquid and airborne effluents was calculated to be 22 person-rem and'O.30 person-rem respectively. This is approximately l 45,000 times lower than the doses to the total population within a 50-mile k radius of the OCNGS resulting from natural background sources. P Determination of Radiation Domes to the Public To the extent possible, doses to the public are based on direct
. measurement of dose rates from external sources and measurements of radionuclide concentrations in the environment which may contribute to an ,
! internal dose of rediation. Thermoluminescent dosimeters (TLDs) , L positioned in the environment around Oyster Creek provide measurements to t j determine external radiation doses to humans. Samples of air, water, food L products, etc. are used to determine internal doses, l' I I L During normal plant operations the quantities of radionuclide releases are bg typically too small to be measured once distributed in the offsite environment. As a result, the potential offsite doses are calculated using a computerized model that predicts concentrations of radioactive ; materials in the environment and subsequent radiation doses on the basis of radionuclides released to the environment. GPUN calculates doses using an advanced dispersion model called MIDAS (Meteorological Information and Dose Assessment System). This model incorporates the guidelines and methodology set forth by the USNRC in Regulatory Guideline 1.109. Due to the censervative assumptions that are used in the model, the calculated
-139-
l I l j, doses are considerably higher than the actual doses to people. Generally, ! when levels of radioactivity in environmental samples were compared to ; levels predicted by the model, the resultant doses predicted by the model were higher than the actual environmental samples. l ' i
~
The type and amount of radioactivity released from the OCNGS is calculated
. using measurements from effluent radiation monitoring instruments and ,
g5
-5 effluent sample analysis. once released, the dispersion of radionuclides f in the environment is readily determined by computer modelling. Airborne releases are diluted and carried away from the site by atmospheric diffusion which continuously acts to disperse radioactivity. Variables '
which affect atmospheric dispersion include wind speed and direction, temperature at different elevations, and terrain. A meteorological I monitoring station northwest of the reactor site is linked to a computer terminal which permanently records all necessary meteorological data. Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Barnegat Bay estuary and 7 Atlantic C,cean. . I The pathways to human exposure also are included in the model. These I pathways are depicted in yigure 15. The exposure pathways considered for the discharge of the station's liquid affluent are fish and shellfish consutoption and shoreline exposure. The exposure pathways considered fer I airborne effluents include plume exposure, inhalation, vegetable consumption (during growing season) and land deposition. MIDAS employs f numerous data files which describe the area around the OCNGS in terms of demography and foodstuffs production. Data files include such information as the distance from the plant stack to the site boundary in each compass sector (sixteen in all), the population groupings, g.Od2ns of more than 500 square feet, meat animals, and crop yields. When determining the dose to humans, it is necessary to consider all pathways and all exposed tissues, summing the dose from each to provide the total dose for each organ as well as the whole body from a given . radionuclide in the environment. Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for iI
~
g
,.yn.e,. p-
i t' t FIGURE 15 l pI EXPOSURE PATHWAYS FOR ROUTINELY-RELEASED RADIONUCLIDES FROM THE OCNGS j- Gasseus Etnuents 45 r 9 I ; Oyster Creek Station Liquid Etnuents - l s** i h immersion i /
)
l .t 1 (80eting, SemmIng) I { l V I 1%, -
** ",%i%,,
ee I W Seefood Consumption ~ ! x%* I l ~ l
% 92 o.
y Dp= =J - g l v .q ? N l PREDOMINANT RADIONUCLIDES , g- NOBLE CASES (Xe, Kr) ACTIVATION PRODUCTS (Co-60 Mn-54) .. _g Plume Exposure Shoreline Exposure and Consumption RADIOIODINES (I-131, 1-133) f Seafood - I Inhalation and Consumption of Vegetables RADIOCESIUMS (Cs-134, Cs-137) Shoreline Exposure and Consumption of Seafood and Vegetables
^ TRITIUM (H-3)
=I Inhalation and Consumption of Vegetables
-141-
. - . . . . - . . .-. -. -. .. .-l
~
i( < l i / radionuelides taken into the body, the metabolism of the radionuclide in l the body must be known along with the physical characteristics of.the ! nuclide such as energies, types of radiations emitted and half-life. MIDAS also contains dose ccnversion factors for 75 radionuclides for each of four age groups (adults, teenagers, children and infants) and eight f organs (total body, thyroid, liver, skin, kidney, lung, bone and gastro-intestinal tract). ; i Doses are calculated for what is termed the
- maximum hypothetical l individual." This individual is assumed to be affected by the combined I
maximum environmental concentrations wherever they occur. For liquid releases,' the maximum hypothetical individual would be one who stands at the U.S. Route 9 discharge canal shoreline for 67 hours per year while ; eating 43 pounds of fish and shellfish. For airborne releases, the 5 maximum hypothetical individual would live at the location of highest radionuclide concentration for inhalation and direct plume exposure while { eating 1,389 pounds of vegetables per year. This location is 966 meters f to the southeast and 966 meters to the north-northeast based on the meteorological conditions at the time of releases. The conservative usage factors and other assumptions used in the model result in a conservative overestimation of dose. Doses to the population within 50 miles of the OCNGS for airborne effluents and the entire population using the Barnegat estuary and Atlantic ocean are calculated.- Appendix 0 contains a more I detailed discussion of the dose calculation methodology. Results of Dose Calculations Doses from natural background radiation provide a baseline for assessing , the potential public health significance of radioactive affluents. The I average person in the United States receives about 300 n.1111 rem (mR) per f year from natural backgrtund radiation sources. Natural background ; radiation from cosmic, terrestrial and natural radionuclides in the human body (not including radon), averages about 100 mR/yr. The natural background radiation from cosmic and terrestrial sources varies with I I
-142-
i I l 1 geographic location, ranging from a low of about 65 mR/yr on the Atlantic and Gulf coastal plains to as much as 350 mR/yr on the Colorado plateau j (Ref. 6). The Nation 1L1 Council of Radiation Protection and Measurements (NCRp) now estimated that the average individual in the United States receives an annual dose of about 2,400 millireme to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole body dose of 200 millireme (Ref. 5). Effluent releases from the OCNG8.and , I other nuclear power plants contribute but a very small percentage to the natural radioactivity which has always been present in the air, water, soil and even in our bodies. In general, the annual population doses from I natural background radiation (excluding radon) are 1,000 to 1,000,000 1 times larger than the doses to the same population resulting from nuclear power plant operations (Ref. 20). i l 5 Results of the dose calculations are summarized in Tables 5 and 6. Table l
-5 compares the calculated maximum dose to an individual of the public to i the OCNGS Technical Specifications dose limits. Table 6 presents the maximum total body radiation doses to the population within 50 miles of the plant from airborne releases and to the entire population using Barnegat Bay and Atlantic ocean biota for liquid releases.
If These conservative calculations of the doses to members of the public from , the OCNGS ranged from less than one percent to a maximum of only 16 percent of the applicable regulatory limits. They are also considerably lower than the doses from natural background and fallout from prior I nuclear weapon tests. [ I I I . I I
-143-I .. . .. _
e ,, I . TABLE 5 i CALCULATED MAXIMUM MYPOTHETICAL DOSES TO AN INDIVIDUAL FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM.THE OCNOS i FOR_1989 Maximum Hvoothetical Dome To An Individual I Oyster Creek NGS Tech. Spec. Limit Calculated Value Percent of millirem / year Toch. Spec. 'I 1 millirem /vear __ OCNGS Limit i Trom Radionuclides 3 total body, or .481 '16 In Liquid Releases 10 any organ .700 7
)
I From Radionuclides 5 total body, or .041 0.82 l In Airborne Releases 15 skin .044 0.29 , (Noble Gas) From Radionuclides 15 any organ .081 0.54 '! In Airborne Releases
'I. (Iodine and Particulates)
Calculated Value Percent of l 40 CFR 190 millirem / year Tech, spec. > l millirem /vaar OCNGS Limit Total From Site 25 whole body .522 2.09-75 thyroid . 081 0.11 25 other organs .744 2.98 I
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TABLE 6 CALCULATED MAXIMUM TOTAL kADIATION DOSES TO THE POPULATION FROM LIOUID AND AIRBORNE EFFLUENT FROH THE OCNGS ] FOR 1989 Calculated Population i Total Body Dose l Person-Rom / Year
,I OCNGS From Radionuclides in Liquid Releases 22.0 t (Barnegat Bay and Atlantic Ocean Users) i I From Radionuclides in Airborne Releases (Within 50-M11e Radius of OCNGS) 0.30 1
.I l DOSE DUE TO NATURAL BACKGROUND RADIATION I Approximately 990,000 Person-Rom Per Year
- t. .
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y . , , , . ,,. _ _ , _ _ _ , . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ , . _ _ _ _ _ , _ .
ji LI REFERENCES (1) GPU Nuclear Corporation. "1986 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1987. I (2) GPU Nuclear Corporation. "1987 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1988.
-(3) GPU Nuclear Corporation. "1988 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1989.
(4) Jersey Central Power and Light Company. " oyster Creek Nuclear Generating Station Operatit.g License and Technical Specifications," Appendix A, DPR-16, April 1969. I (5) National Council on Radiation Protection and Measurements, Report No. 93, " Ionizing Radiation Exposure of the Population of the United States," 1987. (6) . CRC Handbook, "Radioecology: Nuclear Energy and the Environment," F. Ward Whicker and Vincent Schults, Volume I, 1982. I (7) CPU Nuclear Corporation. "0yster Creek Nuclear Generating Station Emergency Plan," Document Number 2000-PLN-1300.1, Revision 8, January 1983. (8) National Council on Radiation Protection and Measurements, Report No. 22, " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, Iesued June 1959, superseding Handbook S2). l B g . al46-I :
E .v 1 L l l (9) International Commission on Radiological Protection, Publication 2, .
" Report of Committee II on Permissible Dose for Internal Radiation ]
i I (1959)," with 1962 Supplement Issued in ICRP Publication 6; Publication 9, " Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of ,] lI Publication 9 concerning environmental monitoring; and ICRP Publication 26 (1977). I i. (10) Federal Radiation Council Report No. 1, " Background Material for the ! , Development of Radiation Protection standards," May 13, 1960. i 'g (11) National Council on Radiation Protection and Measurements, Report 3 No. 39, " Basic Radiation Protection Criteria," January 1971. ,j (12) National Council on Radiation Protection and Measurements, Report No. 62, " Tritium in the Environment," March 1979. ; (13) National Council on Radiation Protection and Measurements, Report No. 81, " Carbon-14 in the Environment," May 1985.
;I (14) United states Nuclear Regulatory Commission. Regulatory Guide 4.1,
" Programs for Monitoring Radioactivity in The Environs of Nuclear Power Plants," Revision 1, April 1975.
I (15) United States Nuclear Regulatory Commission Branch Technical J Position, "An Acceptable Radiological Environmental Monitoring Program,* Revision 1, November 1979. (16) Teledyne Isotopes. " Procedures and Quality Assurance Handbook." IWL-00320365, 1975. . I (17) Radiation Management Corporation. " Analytical and Quality Control Program." RMC-TM-75-3, 1975.
+
I I .
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.. - . . . . -- . . - . ~ . - - . - _ - . . . _
I ! (18) Telodyne Isotopes. " Environmental Radiation Analysis Quality control Manual.' IWL-00320361, 1975. 4 (19) . United States Nuclear Regulatory Commission. Regulatory Guide 4.15, {
" Quality Assurance for Radiological Monitoring Programs (Normal
- g ;
5 Operations) = Effluent Streams and the Environment," Revision 1, [ February 1979. I (20) NUREG/CR-4068 *Sununary of Historical Experience with Releases of Radioactive Materials from Commercial Nuclear' Power Plants in the United States", 1985. ; (21) Eisenbud, Merril, 1987. " Environmental Radioactivity." Academic . I : I : I 3 il I I .I '
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I' APPENDIX A 1j I 1989 REMP Sampling Locations and Descriptions, I Syncpsis of REMP, and Sampling and Analysis Exceptions LI I i l I . I t
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N N O E E E E E E E 'E E E O E E E E i TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS t l j Sample Station Medium Code Distance Azimuth Description APT, Af.0, RWA, 1 0.2 miles 228' SW of site, at Oyster Creek Fire Pond TLD Forked River, NJ' WWA 1 0.1 227 On site, at Oyster Creek Pretreatment Building Lab, Forked River, NJ f APT, AIO, RWA, 3 6.1 94 E of site, near Coast Guard Station TLD Island Beach State Park , APT, AIO, RWA, 4 4.7 215 SW of site, where Route 554 and the Garden i i TLD State Parkway meet, Barnegat, NJ i APT, AIO, RWA, 5 5.2 355 N of site, Garden State Parkway Service Area, TLD Forked River, NJ ' TLD 6 2.2 14 NNE of site, Lane Place, behind St. Pius j Church, Forked River, NJ i l TLD 7 1.8 111 ESE of site, Bay Parkway, Sands Point [ Harbor, Waretown, NJ 4 TLD 8 2.3 180 S of site, Route 9 at the waretown : Substation, waretown, NJ ! TLD 9 2.0 230 SW of site, where Route 532 and the Garden State Parkway meet, waretowfi, NJ , APT, AIO, RWA, A 31.1 25 NNE of site, JCP&L office parking lot, next-TLD to substation, A11enhurst, NJ [ APT, AIO, RWA, C 35.1 309 NW of site, JCP&L of fice rear parking lot, . TLD Cookstown, NJ 4 . _ _ . . . . _ . . . . ,,. . ,,,-.,m - . . _ _ . .,_m . . _ _ _ _ _ _ _ _ ___ _ _ _ . _ _ _ . . _ _._,__m . . _ _ . . _ _ _. _ . _ _ _ . . . _ _ . _ . _ _ _ . _ _ _ _ _ _
TABLE A-1 (continued) . RADIOLOGICAL ENVIRONMENT 3L MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance Azimuth Description , APT, AIO, RWA, H 35 miles 248' WSW of site, Atlantic Electric office TLD storage yard, Hammeonton, NJ TLD 10 10.2 21 NNE of site, Route 37 and Gilford Avenue, Toms River, NJ TLD 11 8.3 156 SSE of site, 80th and Anchor Streets at Water Tower, Harvey Cedars, NJ TLD 12 9.4 192 SSW of site, Atlantic Electric substation access road, Cedar Run, NJ TLD 13 8.3 345 NNW of site, Dover Road, next to last pole e traveling west, South Toms River, NJ APT, AIO, RWA, 14 18 1 N of site, Larrabee Substation on TLD Randolph Road, Lakewood, NJ TLD 15 19 309 NW of site, Route 539, last pole on south side across from Bomarc Site, New Egypt, NJ , TLD 16 18 271 W of site, two poles south of the intersection of Routes 563 and 72. TLD 17 19 ~ 214 SW of site, Route 563, 2 miles north at high voltage line, New Fretna, NJ WWA 18 1.7 42 NE of site, Townsend's Marina, Lacey Road, Forked River, NJ WWA 19 1.6 73 ENE of site, 1015 Inland Road, Forked River Beach, Forked River, NJ j.
17 M. .M M M M M M M m'#M M Me meeeM E TABLE A-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING IOCATIONS Sample Station Medium Code Distance Azimuth Description APT, AIO, RWA, 20 0.7 miles 93* E of site, on Funninger Farm on south side TLD of access road, Pole BT17, Forked River, NJ wwA 20 1.0 80 E of site, on Finninger Farm ett Environmental Laboratory, Forked River, NJ
- WWA 21 1.0 115 ESE of site, at 215 Dock Avenue, Waretown, NJ TLD, WWA 22 1.6 146 SE of site, at 27 Long John Silver Way, i Skipper's Core, Pole #BT152 ON, Waretown, NJ SWA, CLAM, AQS 23 4.0 63 ENE of site, Barnegat Bay off Stouts Creek e 400 yards SE of FL*1" i
SWA, CLAM, AQS 24 2.0 304 ESE of site, Barnegat Bay, 250 yards ) SE of FL"3" SWA, CLAM, AQS 25 1.8 127 SE of site, Barnegat Bay off Holiday Harbor, 200 yards SE of lagoon mouth 2 , SWA, CLAM, AQS 31 10.5 183 S of site, Manahawkin Bay 25 yards SE of C "23* and N "24" SWA, AQS 32 1.9 98 E of site, mouth of Oyster Creek discharge canal SWA, AQS, 33 0.7 104 ESE of site, 1200 yards east of Route 9 FISH, CRAB Bridge in Oyster Creek Discharge Canal l VEG, SOIL 35 0.4 110 ESE of site, east of Route 9 and North of the Discharge Canal, Forked River, NJ
~ ,, _ . . _ ._ . . - . , _ - . _ .,_ . - . . . . . . , . _. . . _ _ . . . . . . . . _ . ,
- E' E E .M M M M M M 'M M M e W e M e W W J
TABLE A-1 (continued) i RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS i Sample Station Medium Code Distance Azisanth Description VGTN, SOIL 36 24 miles 315' NW of site, at DeWolf's U-Pick Farm, New Egypt, NJ TLD 51 0.4 358 N of site, On the access road to Forked River site, Forked River, NJ TLD 52 0.4 340 NNW of site, on the access road to Forked River site, Forked River, NJ TLD 53 0.3 310 MW of site, at the JCP&L Visitor's Center, Forked River, NJ d e TLD 54 0.3 294 WNW of site, on the access road to Forked e River site, Forked River, NJ TLD 55 1.5 273 W of site, next to Basin #1 on the Forked l River site, Forked River, NJ TLD 56 1.1 258 WSW of site, on the siren pole of the ] Building 12 parking lot, Forked River site, Forked River, NJ TLD 57 0.2 203 SSW of site, on Southern Area Stores access road, Pole BT 375, L,' Forked River, NJ l TLD 58 0.4 180 S of site, on Southern Area Stores access road, Pole JC-7-L, Forked River,' NJ TLD 59 0.3 163 SSE of site, on Southern Area Stores access road, on gray post, Waretown, NJ TLD 60 0.4 136 SE of site, on Southern Area Stores access road entrance, Waretown, NJ i e ~r a s - -- . - _ _ . = . .- -__-__=__=_______-.-n =_.~-._-~.__._c
= ,
mmmmM M M m m' m m M* m memeem TABLE A-1 (continued) RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Distance -Azimuth Description Medium Code 61 0.3 miles 116' ESE of site, on Route 9 south of Oyster Creek TLD Main Entrance, Pole BT1458, Forked River, NJ. 62 0.2 99 E of site, on Route 9 at access road to TLD Main Gate, Pole BT-61, Forked River, NJ 63 0.2 70 ENE of site, on Route 9 at North Gate access TLD road, Pole BT 14D63, Forked River, NJ 64 0.3 48 NE of site, on Route 9 north of North Gate TLD access road on Pole JC407X, Forked River, NJ 0.4 22 NNE of site, on Route 9 at.. Intake Canal TLD 65 e Bridge on Pole JC406L, Forked River, NJ 66 0.5 127 SE of site, east of Route 9 and south of the APT, AIO, RWA, TLD, VEG, SOIL Discharge Canal, inside fence, Waretown, NJ 67 1.0 161 SSE of site, on Route 9 at waretown Plaza, TLD Waretown, NJ 69 1.3 70 ENE of site, at the intersection of TLD Chesapeake Drive and Buena Vista Road on Pole JCl347L, Forked River, NJ 70 1.6 183 S of site, on Route 532, 3/4 mile seest of TLD Route 9, in front of Martin residence, Waretown, NJ 71 1.7 165 SSE of site, on Route 532 at the Waretown APT, AIO, RWA, Municipal Building, Waretown, NJ TLD 72 1.9 27' NNE of site, at Community Hall, APT, AIO, RWA Forked River, NJ
MY M M M M M M MI 'O M MM MM M M' M M TABLE A-1 (continued)' RADIOIEGICAL ENVIRONMENTAL MONI70 RING PROGRAM SAMPLING IDCATIONS Sample Station 4 Medium Code Distance Azimuth Description APT, AIO rwa, 73 1.8 miles lil' ESE of site, on Bay Parkway, Sands Point TLD Harbor, waretown, NJ TLD 74 2.0 90 E of site, Orlando Drive and Penguin Court, Pole JC6472L, Forked River, NJ TLD 75 2.0 69 ENE of site, 1225 Beach Blvd. and Naul Drive, Forked River, NJ TLD 76 1.7 51 NE of site, on Lacey Road across frors Captain's-Inn Restaurant, Forked River, NJ TLD 77 1.5 26 NNE of site, NJ State Narina parking lot, Y Yorked River, NJ TLD 78 1.8 2 N of site, 1514 Arient Road, Forked River, NJ TLD 79 2.9 161 SSE of site, on Bonita Drive at Barnegat Bay, Pole JC133 ON TLD 80 3.1 38 NE of site, Riviera Drive and Dewey Drive, j Pole BT787, Lanoka Harbor, NJ TLD 81 4.6 192 SSW of site, east of Route 9 at Brook and i School Streets, Pole JC257BGT, Barnegat, NJ TLD 82 4.4 38 NE of site, Bay Way and Clairmen Avenue, Pole JC1273L, Lanoka Harbor, NJ . ! TLD 83 5.8 29 NME of site, Route 9 and Harbor Inn Road, ! Pole BT666B, Berkeley, NJ l i l
- l. . - .. ._._..._m.- ~. . . , . . . - - . . ~ , . . _ _ . . . . _ . _ . . . . ~ _ _ _ _ . . _ . _ , . . . . _ _ _ . . . -
D .M..- l
, , - y' E ~ M " M 'M M M 6 -M M M _ M ;M!. M
- W MM M M M TABLE A-1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING IDCATIONS'
' Sample Station Descrigtion Medium Code Distance Azimuth _
84 4.8 miles 339' NNW of site, w I 2cey Road, ' 1.3 miles 'tsest of TLD the Garden Stata karkway on JCPGL siren pole, Forked River, NJ 85 3.8 254 WSW of site, on Route 532 West, just prior: TLD to landfill, Pole BT354,_Waretown, NJ 4.8 226 SW of sito c7 Route 554, 1 mile west of the TLD 86 Garden l&27f, Parkway, Barnegat, NJ 87 7:2 143 SE of site, north of Seaview Drive on siren TLD pole, Loveladies, NJ 4 E 6.6 127 SE of site, eastern end of 3rd Street, a TLD 08 Barnegat Light, NJ 89 6.2 110 ESE of site, Job Francis residence, 1aland TLD Beach State Park 90 6.6 '74 ENE of site, parking lot A-5, Pole JC181, TLD Island Beach State Park 9.5 4 N of site, on Robins Parkwar, near Lobster TLD 91 Shanty Restaurant, Toms River, NJ 92 9.2 48 NE of site, at Guard Shack / Toll Booth, TLD Island Beach State Park 93 0.25 150 SSE of site, Oyster Creek Discharge Canal, SWA, AQS west of the confluence of freshwater Oyster Creek
... hw
_7 saa ses mme - i nas amm .aus use uma man man -- em nas amm . , amm amm TABLE A-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING IDCATIONS Sample Station Distance Azimuth Description Medium Code 93 0.1 to 0.3 miles 128' to 257 SE to WSW of site, Oyster Creek Discharge FISH, CRAB Canal between pump discharge and Route 9 94 21.8 201 SSW of site, in Great Bay, south of Jimmies SWA, AQS, CLAM, FISH Creek west of channel marker 1 94 21.8 201 SSW of site, in Great Bay, adjacent to docks CRAB of. Cape Horn Marina 95 2.5 243 WSW of site, at Ocean County voTech School TLD on JCP&L siren pole, Waretown, NJ 1.1 15 NNE of site, at sewage pumping station across TLD 96 a from Oyster Bay Restaurant, Forked River, NJ 97 1.3 43 NE of site, at Twin Rivers newage pumping TLD station, Forked River, NJ T1 0.2 228 SW of site,'at Oyster Creek Fire Pond,
. TLD
-Forked River,.NJ
=
IDENTIFICATION KEY SWA ,= Surface Water SOIL = Soil APT = Air Particulate AIO = Air Iodine' AQS = Aquatic Sediment' FISH = Fish RWA = Precipitation CLAM = Class CRAB = Crab WWA = Well Water VEG = Vegetables TLD = TLD
I TABLE A 2 y m_t SYNOPSit OF THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONDUCTED BY GPUN ENVIRONMENTAL CONTROLS FOR
- OYSTER CREEK NUCLEAR GENERAflWC ST Afl0N-1969 (1)
NUMBER OF NUMBER OF NUMBER OF l SAMPLE- SAMPLING COLLECTION SAMPLES TYPE OF- ANALYSit SAMPLES
}
TYPE LOCAfl0NS FkEQUENCY COLLECTED ANALYSIS FREQUENCY ANALYZED (2)
- Air Particulate 13 m kly. 676 GR bets weekly 676 Gansna 4 week 169
-- composite Air lodine 13 weekly 676 l 131 weekly 676 Precipitation 13 4 week. 52 Genom 12 week- 24 (3) combined for composite
TABLE A-3 (continued) SAMPLING AND ANALYSIS EXCEPTIONS 1989
- 34. October 25,'1989 surface water samples from stations 93 and'94 I were preserved prior to a raw aliquot being drawn off. No iodine analysis could be performed on these two samples.
- 35. November 1, 1989 The ait particulate filter from station 71 was-damaged during removal. Moisture caused the filter to adhere.-
- 36. November. 14, 1989 Well water from station 20 - electrical power previously cut to station. No sample collected.
It 37. November 29, 1989 Station 79 quarterly TLD lost.
- 38. December 11, 1989 Air sampler at station 14 failed after 28.2 I hours of operation.
13, 1989. It was repaired on December I 39. Decembe'r 12, 1989 Well water from station 20 - electrical power-previously cut to station. No sample collected.-
- 40. December 13, 1989 Winter flounder sample from station 93 - only 140 grams of sample collected. Sample'rasulta qualitative only due to small aliquot.-
I. 41. ' December. 14, 1989 Surface water, clam, and sediment samples from station 31 and 94.. Each. collected approximately 1 mile from the usual location due to icing I conditions. I - I g I. I I g; .
I I' .d i I' I I l .. .' 5 APPENDIX B 1989 Lower Limits of Detection (LLD) Exceptions I I
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-TABLE B-1
. TECHNICAL SPECIFICATIONS ANALYTICAL RESULTS WHICH' FAIT *n TO MEET THE REOUIRED T.T.n DURING 1989 No. of Samples Out ~
' Samnie Medla Analysis Reauired TT.h of Como11ance comments FISH. En-65 260 pC1/kg (wet) 1 Small Sample Size (Tautog) Cs-134 130 pCi/kg (wet) 1 Small Sample size' Air Iodine I-131- 0.07 pCi/m 3 1 Low Sample Volume NOTE: ~More than the minimum number of samples and analyses required by-the-Technical Specifications were collected and performed so that none of
.the missed LLD values listed above resulted in any. violations of the Technical Specifications.
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I I-I - 1 I .. I APPENDIX C. I- Changes Effected in the 1989 REMP I
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1 - f f / s APPENDlX C chances Effected in the 1989 REMP
- Modification of sample analysis schedule for precipitation.-
~
' January, 1989 Previous to this modification, precipitation samples collected from stations 1, 3, 4, 5, A,.C, H, 14, 20, 66 71, 72, and 73
__ were analyzed on a monthly basis.- This moditication' changed - the analysis schedule. With this modification, samples.- continue to be collected on a monthly basis from.the above mentioned 13 stations,.but samples from stations A, C, H, 66,
- 72, and 73 are composited quarterly and then analyzed. Samples from stations 1, 3, 4, 5, 14, 20, and 71 are held until the results from the analyzed six samples are interpreted.- The
; remaining' samples are than either analyzed or disposed of.
October, 1989 _ Modification of sample analysis schedule for aquatic sediment.' Previous to this modification,. aquatic sediment: samples from l stations 23, 24, 25,,31, 32, 33, 93, and 94 were collected and J analyzed on a monthly basis. This modification changed the analysis schedule. Samples continue to be collected on a , monthly basis, but the station san.ples g then composited-
--. quarterly and analyzed.
November, 1989 Well Water Station #20 was abandoned. This was not a Tech. Spec. required station. A J 1 1 1
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I I-1 I' . I! it L I f APPENDIX D 1989 Quality Assurance Results It I I: I I: I; . I g .
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~
w-IE The oyster Creek Environmental' Controls Quality Assurance (QA) Program - consists of three phases. . Phase I consists of splitting samples collectAd l i
, at designated stations and having them analyzed by separate (independent).
~ laboratories._ Analysis-results from the quality control (QC) laboratory are compared to those from the primary laboratory as set forth in OC.
. Environmental Controls procedure 9410-ADM-4500.07. Agreement-criteria are
; established in this procedure. If non-agreement of the data occurs,'an ig' -
investigation begins which may include recounting or reanalyzing the ! samples in question. l
~
Phase II requires that-laboratories analyzing environmental samples for oyster Creek participate in the USEPA Cross-Check Program. This serves as independent verification of their ability to correctly analyze l t environmental samples. Results of this interlaboratory comparison program _ j I;- are presented in Appendix E. ! Phase III requires that contractor / company laboratories perform duplicate analyses on every twentieth sample. Table D-1 outlines the duplicate ! analyses portion of the QA program. Results of the two analyses were reviewed per'proceduro 9410-ADM-4500.07.-- one non-agreement occurred , a I during 1989 - this in a clam sample gamma isotopic recount. This non-agreement was-attributed to the non-homogeneous distribution'of 9 { radioactivity in the aliquot. ; Table D-2' outlines the split sample portion (Phase I) of the QA program for the media collected during 1989. 'Six non-agreements occurred during 1989 for which explanations have yet to be completed despite ongoing q
-investigations. Final resolution of these six non-agreements will be
{
'45 reported in the 1990 Radiological Environmental Monitoring Report. [
- II j IL I:
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-ps TABLE D-1
_-_= 1989 QA SAMPLE PROGRAM NUMBER OF DUPLICATE ANALYSIS PERFORMED ANALYSES SAMPLE' GROSS -GAMMA MEDIUM h 11 ,2 M ISOTOPIC AIR PARTICULATE 29 10 40 AIR IODINE-
~
RAIN WATER 2 3
--- - WELL WATER 4 8 5 10-SURFACE WATER- = -
AQUATIC SEDIMENT 2 CLAMS 9 VEGETABLES 2
-3
_] SOIL 1 FISH .1 CRAB- 2 J > 1 1 1 J 1
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I TABLE D-2
-l l '
1989 OA SAMPL*:. PROGRAM ! SPLIT SAMPLEp :) l I .l l . NUMBER OF NUMBER OF OA SAMPLE l 1 -
. SAMPLE REGULAR COLLECTION Q& COLLECTION
'. MEDIUM STATIONS FREQUENCY , STATIONS FREQUENCY l .. . . . 'l J - Precipitation 13 MONTHLY 1 QUARTERLY WHEN AVAILABLE- 'l
, -)
Surface Water 8 MONTHLY 1 QUARTERLY. J iW Well Water- '6 MONTHLY 1 QUARTERLY j
! C1ams 5 MONTHLY 1 QUARTERLY.. '
- Soil- 3 QUARTERLY WHEN 1 QUARTERLY WHEN
- - , VEGETABLES AVAILABLE VEGETABLES AVAILABLE j
- Sediment 8 MONTHLY 1 QUARTERLY Vegetables 3 MONTHLY WHEN 1- QUARTERLY WHEN g AVAILABLE AVAILABLE >
-1
. TLD 63 QUARTERLY 2 QUARTERLY
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-169-
m--.--.-..,__c_,--, - - _ _ . . _ - - - . - - _ _ . , _ , . _ _ _ , _ . - - -_
.f . .' '
':);
e iv.?. s 5 I. I . g i 8 I APPENDIX E 1989'US EPA Cross-Check Results l 4
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i . _A.xmm-mm_-_.:mm__m. h_ _ _ _ - - _ _ _ _ _ __ m ________.. __
a I'
' TABLE E-1 OYSTER CREEK NUCLEAR GENERATING STATION
.US EPA CROSS-CHECK PROGRAM 1989
= EPA RESULTS GPUN-ERL* TI** DATE__ MEDIA- _.__ NUCLIDE fA) RESULTS (B)- RESULTS fC&D). .I$ Jan 1989- " WATER = Gross Alpha 8.0 1 8.7 8.7 6.0 1 2.0 7.3 1 1.2 1.2 Gross Beta 4.0 1 5.7 1 0.6 5.3 1 Feb 1989 WATER Co-60 10.0 1 8.7 9.3 1 0.6-- 10.0 1 2.0 Cr-51 235.0 i 41.6- 253.3 1 5.8 245 - 1: 46-Cs-134 10.0 1 8.7 9.3 1 2.1 9.7'i. 3.0 11.7 1 2.3 -1.2
~
/ Cs-137 10.0 1 8.7 11.7 1 LI2 Ru-106. 178.0 1 31.2 173.3 1 15.3 181 1 7.6 2n-65 159.0 1 27.7- 156.7 1 5.8 170 1 10
'g I-131 106.0 1. 19.1 110.0-1 0.0 109.0 1 4.0-H-3 2754.0 1 616.6 2866.7 1115.5 2820 1 20
..g.
Mar 1989 AIR FILTER Cs-137 20.0 1 8.7 20.7 1 1.2 21.3 1 1.2 1.2 (I . Gross Alpha Gross Beta 21.0 1 62.0 1 8.7 8.7 25.3 1. 0.6 60.7 1 3.1 21.7 1 68.3 1 4.2 Apr 1989 WATER Cs-134 20.0 1 8.7 _19.0 1 1.0 -21.0 1 5.2 R Co-137 . 20.0 1 8.7 19.3 1 1.2 23.0 1 2.0
-Gross Alpha 29.0 1 12.1 21.0 1 2.7 22.7 1 2.3 Gross Beta 57.0 1 8.7 45.0 1 5.3 52.3 1 6.1 I- ; 48.7 1 0. 6 ' 54.0 i '6.9~
-Apr 1989 MILK Cs-137 50.0 1 8.7 K-40 1600.0 1 138.6 1566.7 1 57.7 1521 1 208 May 1989 WATER Gross Alpha 30.0 1 13.9 22.0 1- 1.0 24.0 1 2.0=
Gross Beta 50.0 1 8.7 48.0 1 1.0 49.3 1- 15.6 Sr-89 6.0 1 5.0 E 6.3 1 0.6
- l- Jun 1989 WATER Sr-90 6.0 1 1.5 E 6.3 1 0.6 Ba-133 49.0 1 8.7 50.7'i 0.6 33.0 1 3.6 Co-60 31.0 1- 8.7 29.7 1 3.2. 30.0 1 2.7-8 Cs-134 Co-137 39.0 1 20.0 1 8.7 8.7 38.0 1 1.0 21.3 1 '1.2 34.0-1 22.0 1 2.7 3.6 Ru-106 128.0 1 22.5 123.3 1 5.8 113.7-1 17.5 Zn-65 165.0 1 29.4 '163.3.1 5.8 165.3 1 0.6 t
8 H-3 4503.0 1 779.4 4700.0 1100.0 4466.7't 152.8 j- Jul 1989 WATER Uranium 41.0 1 6.0 NO DATA 36.0 1 1.0
.g2 Ra-226 17.7 1 2.7 NO DATA 16.0 1 0.0 Ra-228 18.3 1 2.7 NO DATA 20.7 1 2.1 Aug 1989 WATER Pu-239 2.8 1 0.3 NO DATA 2.4 1 0.2 I-131 83.0 13.9 85.7 1 0.6 84.7 1 5.8 Aug 1989 AIR FILTER Cs-137 10.0 1 8.7 10.3 1 0.6 12.0 1 1.0 I. Gross Alpha 6.0 1 8.7 7.3 1 0.6 8.3 1.0 Sep 1989 WATER Gross Alpha 4.0 1 8.7 3.0 1 0.0 5.0 1 0.0 4
~
Gross Beta 6.0 1 8.7 6.3 1 0.6 8.0 1 0.0
-171- 1 c
18 TABLE E-1. CYSTER CREEK NUCLEAR GENERATING STATION US EPA CROSS-CHECK PROGRAM 1989
""- EPA RESULTS GPUN-ERL* - T!**
DATE MEDIA NUCLIDE (A) RESULTS (B) RESULTS (C&D)- Oct 1989 WATER Ba-133 59.0 1 10.4 63.0 1 1.0 51 0 1. 4.4 Co-60 30.0 1 8.7 28.3 1 1.2 30.7'ig 2.1 f Co-134 29.0 1 8.7 27.3 1 0.6 23.7 1 1.2 Co-137 59.0 1 8.7 63.7 1 1.5 61.7 1- 1.5 Ru-106 '161.0 1 27.7 166.7 1. 5.8 '139.0 1. 15.7 En-65 '129.0 1 22.5 123.3'1 5.8 128.3 1 2.9 Co-134 5.0 1 8.7. 4.7 1 0.6 5.0 1 0. 0 ' , I_ y
- Cs-137_ 5.0 1 8 .' 7 5.3 1 0.6 7.0 1 0.0
- H-3 3496.0 1 630.5 3633.3 1 115'.5- 3407 1 150 l l Gross Alpha 49.0 1 20.8 43.0 1 1.7 41.7 1 9.4
- Gross Peta 32.0 1 8.7 30.0 1 0.0 31.7 1 2.3
- GPUN-ERL - The Environmental Radioactivity Laboratory located in Middletown, PA
** Telodyne Isotopes Midwest Laboratory located in North Brook, IL -
Is 'Results Through Apsil 1989 Telodyne Isotopes Westwood Laboratory located in Westwood, NJ - Results (Primarily) After April 1989 A.0 EPA results are prese$ted as the known values and the expected laboratory I . precision (one sigma, one determination) and control limits as defined by the EPA. Units are pCi/L for water and milk except K-40 is in mg/L. Units are total poi for air particulate filters. Units for food are pCi/kg except K-40 which is mg/kg. - B. GPUN-ERL results - average i one sigma. Units are pCi/L.for. water and milk I except K is in mg/L. Units are total pCi for air particulate filters. Units for food are pCi/kg. C. Teledyne Westwood renults - average 1 one sigma. Units are pci/L for water and I milk except K is in mg/L. Units are total pCi for air particulate filters. Units for food are pC1/kg. g- D. Teledyne Midwest results are given as the average of 1 two sigma for three 13 determinations. Units are pC1/L for water.and milk except K-40 is in mg/L. Units are total pCi for air particulate filters. Units for food are oct/>g except K-40 which is mg/kg. E. Results for Sr-89, Sr-90, and low level I-131 were not provided to the EPA. A procedure for the analysis of Strontium has not been developed and equipment problems prevented the analysis of low level I-131 by the EPA recommended method. 1 -172-1 ,
1
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APPENDIX F
' . -i 1989 Annual Dairy census I '!
1 I l,
;}
4 I. ' k I:
.- 1, I
3
-173-I 1
V
I' , ,
. v
-Annual-Dairy census - 1989-l Ocean; county' Agricultural Agent, Ms._Debra Smith-Flola, was contacted regarding the occurrence of dairy animals within a.five mile radius of the-
' OCNGS. According to her records, there are no commercial' dairy-operations f or dairy animals lwithin-a five mile radius of the OCNGS.--
>i :- 8 I! I I 18 I I B i I
- t
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5 l> ;e . I I I' .
.' l.
8 - o
- j, APPENDIX G Dose calculation Methodology s; I ,
[ . I 2 i I ! r u .
'I
, -175-f .
.i.
To the extent-possible, radiological impacts were evaluated based on the direct measurement of dose rates or of radionuclide concentrations in the f environment.,.However, the quantities of radionuclide releases associated with 1989 OCNGS operations were often too small to be measured once dispersed in the offsite environment.- As a result, the potential offsite doses could only=be estimated by using computerized models that predict concentrations of radioactive materials in the environment and subsequent a radi.ation doses on the basis of radionuclides released to the environment. GPUN calculates doses using an advanced class "A" dispersion model called MIDAS (Heteorological Information and Dose Assessment System).- This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109. MIDAS uses hourly meteorological information matched to the time of releases to assess the dispersion of effluents in the discharge canal / estuary system.and the atmosphere. I- Combining this assessment of dispersion.and dilution with effluent data, postulated maximum hypothetical doses to the public from the OCNGS effluents are calculated. The maximum individual dose is calculated as well as the dose to the total population within 50 miles of-OCNGS for gaseous effluents and the entire population downstream of the OCNGS around Barnegat Bay and the Atlantic Ocean for liquid effluents. Values of I environmental parameters and radionuclide concentration factors have been chosen to provide conservative results. As a recult, the doses calculated using this model are conservative estimates (i.e., overestimated) of the actual exposures.
'The 'ose d summary table, Table G-1, presents the maximum hypothetical doses to an individual resulting from effluents from OCNGS during the 1989 reporting period. Population doses are presented in Table G-1.
Lieuid (Individuali I As recommended in USNRC Regulatory Guide 1.109, dose calculations are performed on four age groups and eight organs (Table G-1). The pathways considered are consumption of fish, consumption of shellfish and shoreline I I -176-
vcs > 4
' exposure ~. All pathways are considered to be primary recreational n-activities associated with the~Barnegat Bay and Atlantic Ocean in-the
, vicinity'of,the OCNGS. The " receptor" would be that individual who eats fish and shellfish that reside in the station discharge, and stands on the shoreline influenced by the station discharge. Table-G-1 presents the maximum total. body doso and critical organ dose for the age group most effected.
4
-For the 1989 reporting period, the calculated maximum hypothetical total body dose received by anyone from liquid effluents would have been 0.481 mrom to an adult. This' represents 16 percent of the OCNGS Technical Specification annual dose limits. Similarly, the maximum hypothetical organ dose from liquid affluents would have been 0.700 mrom to the liver.
I of an adult. This represents 7 percent of the OCNGS Technical
. specification annual dose limits.
. caseous tIndividual)
-There are seven major pathways considered-in the dose calculation for
~
gaseous effluents. These ares (1) plume exposure, (2) inhalation, (3)
" consumption of cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7)
\gEB standing on contaminated ground.
~
The maximum plume exposure reported in lines 3 and 4 of Table G-1 generally occurs at, or near, the site boundary. The notation of " air dose" is, interpreted to mean that these doses are not.to an individual but are considered to be the maximum dose at a location. The location is not necessarily a receptor. It should be noted that real-time meteorology was.- s I- used in all dose calculations for gaseous effluents. With respect to the releases for the 1989 reporting period, the maximum plume exposure (air dose) would have been 0.151 and 0.007 mrad for OCNGS gamma and beta dose, respectively. These doses are equal to 1.51 percent and 0.04 percent of the OCNGS Technical Specification annual dose limits, respectively. g
-177-
.iI I ?
1 r., .
-t The calculated doses to the closest receptor (individual) in the maximally.
affected sector (s) are presented in lines 5 and 6 of Table 0-1. Plume exposures-to an individual, regardless of age, from gaseous offluents during the 1989 reporting period were 0.041 mrom and 0.044 mrem for total ?! I body and skin exposure, respectively.- These doses are equivalent to 0.82 percent.and 0.29 percent of the OCNGS Technical; Specification annual dose {
- limits, respectively.
- 5 The dose to the maximum exposed organ due to radioactive iodine and' f particulates is presented in line 7 ef Table G-1. This'does not include the whole body plume' exposure which was separated out on line 5. The dose' i presented'in this'section again reflects the maximum exposed organ for the appropriate age group. During=1989, gaseous iodines and particulates from-OCNGS would have resulted in a maximum dose of 0.081 mrom to the thyroid I of an infant. This dose is only 0.54 percent of the OCNGS Technical Specification annual dose limits.
I - Poculation Doses (Llauid and Gaseousi i; The population doses resulting from liquid and gaseous effluents are summed over all pathways and the affected population (Table G-1, lines Lus 8-11). Liquid population dose is based upon the population-located within the region from the OCNGS outfall extending out to the Atlantic Ocean. The population' dose due to gaseous effluents is based upon the 1980 population projections of the Final Safety Analysis Report'(FSAR) and ' considers the population out to a distance.of 50 miles around the OCNGS as I well as the much larger total population which can be fed by food stuffs grown in the 50. mile radius. Population doses are summed over all
~
. w -- distances and sectors to give an aggregate done.
- Total OCNGS, liquid and gaseous effluents resulted in a population dose of 22.3 person-rem total body for the 1989 reporting period. This is approximately 45,000 times lower than the doses to the same population resulting from natural background sources.
^
-178-
, , y E /1 E E 'W E S W W" E . E W W W TM ,g g g igi ~g
. TABLE G-1.
SUMMARY
OF MAXIMUM' INDIVIDUAL AND POPULATION DOSES FROM~OCNGS EFFLUENTS FOR 1989 Individual Doses Estimated- . Location Percent of Tech. Spec. Dose / year . Age Dist Dir. Tech. Spec.. Limit' Effluent Oroan ierem) Group im) fToward1- Limit' imrem/vr). 1 Liquid Total Body 0.481 Teen ~ Receptor 1 16 3 2 Liould Liver O.700 Adult Receptor'1 7 10 3 Noble Gas Air Dose 0.151 --- 405 E 1.51 10-
' (Ganuna-mrad )
4 Noble Gas Air Dose 0.007 -- 640 N O.04 20 ~ (Beta mrad)
, 5 Noble Gas Total Body 0.041 ALL 966 NNE O.82 5' l
U .. y 6 Noble Gas Skin 0.044 ALL 966 NNE O.29 15 7 Iodine and Thyroid 0.081- INFANT 966 NNE O.54 15 - Particulate PopuIation Doses Estimated Applicable Population Dose. Effluent Oroan (Person-rem) 8 Liquid Total Body 22 9 Liquid Thyroid 17 10 Gaseous Total. Body 0.30 11 Gaseous Thyroid 0.83 _ - _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ , - - _ _ _ _ _ _ _ _ _ _ _ _ _ - ~- - - - - .- - ~ ~. . . - , - , - . , , . .. .
y >-( f
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g,t. e I I APPENDIX H-1989 Groundwater Monitoring Results
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TABLE H OCNGS - GROUNDWATER RESULTS' CONCENTRATION IN pci/ liter +/- 2 Standard Deviation e
. March 1989 october 1989 Station M G===* Imotoolc H-), ; G====-Isotonic-ocaW-1 <160 pci/ liter <LLD ' <180 pci/ liter <LLD
.oc-W-2 -
- -<180 pci/ liter <LLD
-oc-W-3 <150 pci/ liter <LLD 2501130 pci/ liter <LLD
.oc-W-4 <140 pci/ liter <LLD <180 pci/ liter <LLD oc-W <150 pci/ liter <LLD. <180 pci/ liter <LLD oc-W-6-l <140 pci/ liter <LLD <180 pci/ liter <LLD
'- oc-W-7 <140 pci/ liter <LLD <190 pci/litar <LLD oc-W-9' <150 pcl/ liter <LLD <180 pci/ liter <LLD OC-W-10 <140 pci/ liter <LLD <180,pci/ liter <LLD
- Oc-W - - <180 pci/ liter <LLD
.g
<LLD ' '
W- .OC-W-13 - <140 pct / liter. <LLD <180 pci/ liter p
~oc-W-14: '<140 pci/ liter <LLD 21001200 pci/ liter <LLD oc-W <150 pci/ liter <LLD <180 pci/ liter <LLD oc-W-16 <140 pci/ liter <LLD <180 pci/ liter <LLD oc-W-17 <140 pci/ liter <LLD <180 pci/ liter- .<LLD DUPLICATES NOT INCLUDED ,
I I I 8' Jg
-181-
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i I s FIGURE H-1 LOCATIONS OF-ON-SITE WELL8 i. E SU BSTATION I - g . 1 I . L u j
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i j INMME CANAL
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DISCH ARG E - CANAL l 3 W-3 W-4
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APPENDIX I ' ' , .'1989 REMP Sample Collection and Analysis Methods
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-183-
E E E E O E N ~ E -' E E E E'M W. E O E E Sq c: e ! I., :- TABLE I-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF SAMPLE COLLECTION AND ANALYSIS METHODS 1989 Approximate cample Sample Size Procedure Procedure j Analysis - m, Samolino Method Colle ged Number Abstract Gr-Beta APT Continuous weekly or more 1 filter TMI-EC Low backgrouns gas frequent air sampling (approximately 600 9420-IMP-4592.05 flow proportional through filter paper cubic meters weekly) counting Gamma APT Monthly composite of each 4 filters TMI-EC Gawana isotopic, spectro- station (approximately 2400 9420-IMP-4592.05 analysis scopy cubic meters) Gamma AIO Continuous weekly or more 1 cartridge TMI-EC Gamme isotopic Spectro- frequent air sampling (approximately 600 9420-OPS-4591.04 analysis
& scopy through charcoal cartridges cubic meters weekly)
# c b t Gamma SWA Monthly grab 7.5 liters TMI-EC Gamma isotopic spectro- 9420-IMP-4592.06 analpis scopy TI-Midwest Gamma is4 topic GS-01 analysis
. Ti-Westwood Gamma Isotopic PRO-042-3 analysis Gamma RWA Monthly composite Minimum of 0.5 liters TMI-EC Gamma isotopic :
Spectro- 9420-IMP-4592.06 analysis l scopy l T1-MMwest Gamune isotopic GS-01 analysis TI-Weetrood Gamune 190 topic P140-042-5 analysis I
.- - . -- -. - , - - :. . u - _ . _ .. . . _- -. . - _ ..-. .-
O E E O O E OO E E M M M E E M M M - M --
= _ -
s/ TABLE I-1 (Continued) RADIOLOGICAL ENVIROIEMENTAL MOttITORING PROGRAM
SUMMARY
OF SAMPLE COLLECTIOtt AND ANALYSIS METHODS 1989 l Approximate Sample Sample Size Procedure Procedure i Analysis Medium Samolino Method Collected Number Abstract i Gamma WWA Monthly grab 7.5 liters TMI-EC Gamma isotcpic Spectro- 9420-IMP-4592.06 enalysis scopy TI-Midwest Genuma isotopic { GS-01 analysis l TI-Westwood Gamma Isotopic PRO-042-5 analysis Gamma CLAM Grab sample monthly I kg TMI-EC Gansne isotopic . 4 Spectro- FISH Grab sample semiannually (if possible) 942C-IMP-4592.03 analysis
$ scopy CRAB Gamma isoto;;>1c 8 TI-Midwest ;
GS-01 analysis TI-Westwood Ganuma Isotopic PRO-042-5 analysis Gamma AQS Grab sample monthly 3.8 liters TMI-EC Gamuna isotopic Spectro- SOIL Grab sample quarterly (if possible) 9420-IMP-4592.04 analysis scopy (when vegetables are available) TI-Midwest Gesuna isotopic ! GS-01 analysis TI-Westwood Gasuna Isotopic PRO-042-5 analysis 4
.w.- --. * ,. 1., . .,# . --w w.<-e ..r. -- , n -, ,. ,....,=y -w. e...w w,
7. M M S O ' & 'M S M MM M M M M .M,M M M M TABLE I-1 (Continued)
., RADIOIDGICAL ENVIROteENTAL MONITORING PROGRAM
SUMMARY
OF SAMPLE COLLECTION AND ANALYSIS METHODS 1989 Approximate Sample Sample Size Procedure Procedure Analysis Medium Samplino Method Collected N=Wr Abstract Gamma VEG Grab sample when available 1 kg or more TMI-EC G - isotopic Spectro- (if possible) 9420-IMP-4592.03 analysis scopy TI-Midwest Gasuna isotopic
; . GS-01 analysis
- TI-westwood Gassna Isotopic I PRO-042-5 analysis i
Tritium SWA Monthly Grab 7.5 liters TMI-EC Sample mixed with 9420-IMP-4592.02 scintillation fluid
$ for scintillation y
8 counting TI-Aldwest Sample distilled, T-02 mixed with scintillation fluid i for scintillation I counting TI-westwood Sample vaporized I PRO-052-2 and water vapor , counted. 1
- - - . . _ __.mm. _ . . _ . . _ . . _ , , , ,
E E O O EE @ E E E E E E E E E E E E TABLE I-1 (Continued) RADIOIDGICAL ENVIRORGENTAL MONITURIleG PftOGRAM SUIGIARY OF SAMPLE COLLECTION AND ANALYSIS METHODS 1999 Approximate Sample Sample Size Procedure Procedure Analysis Medium Samolina Method Collected "*r Abstract Tritium RWA Monthly composite Minimum of TM1-EC Sample sized with O.5 liters 9420- As 492.02 ociatillation fluid for scintillation counting TI-Mid% - Sample distilled, , T-02 mined with
~
scintillation fluid for scintillation counting d
- $ TI-Weetwood sample vaporized
' 8 PRO-OS2-2 and water vapor - counted. Tritium WWA Monthly grab 7.5 liters TMI-EC Sample mixed with ! 9420-IMP-4592.02 scintillation fluid for scintillation counting TI-Midwest Sample distilaed, T-02 mixed with scintillation fluid for scintillation counting TI-Westwood sample vaporized PRO-052-2 and water vapor counted.
. - . . - _ . , . _ m . ,m.,__ _ . - _ . . . _ . . ._ . . _ _ _ _ , . _ - . . _ _ _ _ _ _ _ _ . _
__ _ _ . ___...__..___.m... _ . _ _ _ . . _ _ _ _ _ _ _ _ . _ . . _ . . _ _ _ _ . ..
S O O- S.'M OM M M & & M 'M M M M M M
+
TABLE I-1 (Continued) RADIOI4GICAL ENVIROOGENTAL MONITORING Pft0 GRAM , SUfetARY OF SAMPLE COT " MION AIED ANALYSIS naAnuus 11El Approximate Sample Sample Size Procedure Procedure Analysis Medium Samplino Method Collected War Abstract TLD Immersion Dosimeters exchanged TLD TMI-2 Thermoluminiscent Dose quarter]; 9200-0PS-4250.01 dosimetry TLD Immersion Dosimeters exchanged TLD TI-18eetwood Thermoluminiecent l
- Dose quarterly Pro-342-17 dosimetry e
e I i t .i l l t t 9 .- -- , . . , y , ,. y# -- u ..w-n, - . , ,...%- ...--3,y--,..,,..m-- -m__ -_u __=__mm___-+.__m.-m - _ _ _ -. m____--.______.mm_.___-m.-__m. _ - - - -
, . . . - . - - . . - ~ - - - - - - - - - ~ - - - - - - ~ - - - - - - - ~ ~ - - ~ ~ ~ ^ ^ - - ' ' - ' ~ ~ ~ - ' " ~ ~ ~ " ' ~ ~ ~ " ^ ^ ' ^ ~ ~ ~ ^ ^ ^ ^ ^ ~
~
I l e I "I . i 'I 1 I APPRNDIX J
- g .
1989 TLD Quarterly Data l 5 1 4 l I . I l. I ' I > I -189-I
g - - m m m m-m m 6 m mea e aee m- m TABLE J-1 Oyster Creek Nuclear Generating Station - Environssental Controls 1989 Quarterly Environmental TLD Report - Teledyne Isotopes Running Table - M1111 Rem Per Staredard Month and 2-Standard Deviations STATION FIRST QUARTER SECDND QUARTER THIRD QUARTER FOURTH QUARTER 1 3.6 +/- 0.2 4.1 +/- 0.4 4.0 +/- 0.2 5.6 +/- 0.7 3 3.4 +/- 0.1 4.6 +/- 0.3 3.4 +/- 0.4 3.7 +/- 0.3 4 3.2 +/- O.1 4.1 +/- 0.2 3.1 +/- 0.4 3.4 +/- 0.2 5 4.2 +/- 0.5 3.6 +/- 0.3 3.3 +/- O.3 3.6 +/- 0.3 6 4.2 +/- 0 2 4.4 +/- 0.1 3.2 +/- 0.2 3.5 +/- 0.4 7 3.1 +/- 0.1 3.4 +/- O.3 3.1 +/- 0.2 4.3 +/- O.3 8 3.4 +/- O.3 3.7 +/- O.3 3.3 +/- 0.4 3.6 +/- 0.3 9 3.4 +/- 0.2 3c7 +/- 0.2 3.4 +/- 0.2 3.7 +/- 0.3 10 4.5 +/- 0.2 3.5 +/- 0.1 3.3 +/- 0.2 4.5 +/- 0.4 11 3.9 +/- O.3 4.2 +/- 0.2 4.0 +/- 0.5 3.3 +/- 0.1 12 4.5 +/- 0.3 3.8 +/- 0.3 3.4 +/- 0.4 3.3 +/- O.3 13 3.1 +/- 0.1 3.4 +/- 0.1 3.1 +/- 0.2 4.3 +/- 0.2 s 14 4.7 +/- 0.4 5.2 +/- 0.4 4.1 +/- 0.4 4.3 +/- 0.4 5 15 3.5 +/- O.2 3.8 +/- 0.1 3.3 +/- O.3 3.7 +/- 0.3
? 16 4.0 +/- O.1 3.4 +/- 0.2 3.0 +/- O.2 3.4 +/- O.1 17 4.2 +/- 0.1 3.5 +/- 0.2 3.3 +/- 0.4 3.5 +/- 0.2 ! 20 3.0 +/- 0.6 3.6 +/- 0.2 4.0 +/- 0.3 3.4 +/- 0.2 I
22 3.3 +/- 0.2 3.6 4/- O.1 4.1 +/- 0.2 4.5 +/- 0.4 51 5.4 +/- 0.4 5.7 +/- 0.5 4.3 +/- 0.4 4.5 +/- 0.4 52 5.6 +/- O.3 5.0 +/- O.3 4.3 +/- 0.3 5.1 +/- 0.4 53 4.9 +/- 0.1 4.3 +/- 0.4 3.7 +/- 0.3 5.7 +/- 0.4 54 3.8 +/- 0.4 4.8 +/- 0.2 3.5 +/- 0.1 3.9 +/- 0.2 55 3.4 +/- 0.3 3.8 +/- 0.3 3.4 +/- 0.3 3.5 +/- O.2 56 5.2 +/- 0.4 5.3 +/- 0.6 3.7 +/- O.3 4.4 +/- 0.6 57 4.8 +/- 0.4 4.8 +/- 0.5 4.9 +/- 0.5 5.6 +/- 0.6 [ 58 3.3 +/- 0.3 4.1 +/- 0.5 4.4 +/- 0.5 4.2 +/- 0.4 59 3.9 +/- O.3 5.3 +/- 0.4 4.9 +/- 0.4 4.4 +/- 0.4 l 60 3.3 +/- 0.2 3.9 +/- 0.2 3.2 +/- 0.3 4.6 +/- 0.5 , 61 3.4 +/- O.3 3.8 +/- 0.2 3.8 +/- 0.8 3.8 +/- 0.2 ! 62 3.5 +/- 0.2 4.3 +/- 0.8 4.2 +/- 0.3 3.7 +/- 0.4 63 3.5 +/- 0.2 3.9 +/- 0.3 1.4 +/- 0.3 3.6 +/- 0.3 64 3.3 +/- 0.2 3.6 +/- 0.2 4.3 +/- 0.5 3.4 +/- 0.2 __ . _ _ m - _ _ ~ , , ~ . . - . . - , _ . . . ~ . . . . .
E EE E E E E E O E @ E E E E E E~ TABLE J-1 (Continued) Oyster Creek Nuclear Generating Station - Environamental Controls 1989 Quarterly Environmental TLD Esport - Teledyne Isotopes Running Table - M1111 Rem Per Standard Month and 2-Standard Deviations STATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER 65 3.3 +/- 0.2 3.6 +/- 0.3 * +/-
- 4.5 +/- 0.1 66 3.5 +/- 0.1 3.5 +/- 0.2 3.4 +/- 0.4 3.6 +/-'O.1 67 3.4 +/- 0.2 3.8 +/- 0.2 4.3 +/- 0.2 3.6 +/- 0.1 69 3.4 +/- 0.1 3.6 +/- 0.2 4.1 + /- 0. 3 3.5 +/- 0.1 70 4.1 +/- 0.1 3.4 +/- 0.2 4.0 +/- 0.4 4.3 +/- 0.1 71 3.3 +/- O.2 4.4 +/- 0.2 3.8 +/- 0.4 3.6 +/- 0.1 73 3.3 +/- 0.2 4.3 +/- Q.1 3.2 +/- 0.2 1.4 +/- 0.2 74 3.4 +/- 0.1 4.7 +/- 0.4 3.8 +/- 0.4 4.4 +/- 0.7 ,
75 3.8 +/- 0.1 4.1 +/- 0.2 4.5 +/- 0.5 3.9 +/- 0.1 76 3.3 +/- O.2 3.7 +/- 0.2 3.2 +/- 0.4 3.4 +/- 0.1 77 3.3 +/- 0.3 3.7 +/- 0.1 3.4 +/- 0.1 4.4 +/- 0.3 78 4.3 +/- 0.1 3.8 +/- 0.1 3.2 +/- 0.2 3.5 +/- 0.1 e 79 3.0 +/- 0.1 4.3 +/- 0.4 3.0 +/- 0.1 * +/-
- 5 80 3.2 +/- 0.0 3.8 +/- 0.2 3.3 +/- 0.3 3.8 +/- 0.1
$' 81 3.7 +/- 0.3 4.1 +/- 0.3 3.7 +/- 0.1 4.6 +/- 0.1 82 3.8 +/- 0.2 3.9 +/- O.2 3.8 +/- O.2 3.9 +/- 0.3~
83 3.4 +/- 0.2 4.7 +/- 0.4 3.8 +/- 0.2 4.8 +/- 0.2 84 * +/-
- 3.8 +/- 0.3 3.9 +/- 0.3 4.9 +/- 0.4 85 3.5 +/- 0.1 4.7 +/- 0.2 3.7 +/- 0.2 3.9 +/- 0.2 86 3.5 +/- 0.3 3.6 +/- 0.2 3.7 +/- 0.2 4.8 +/- 0.4 87 3.7 +/- 0.2 4.8 +/- O.2 4.2 +/- 0.3 5.0 +/- 0.5 88 3.2 +/- 0.1 4.3 +/- 0.2 4.6 +/- 0.1 4.4 +/- 0.3 89 3.2.+/- 0.2 4.6 +/- 0.6 3.3 +/- 0.1 3.6 +/- 0.1 90 3.0 +/- 0.1 3.3 +/- 0.2 3.4 +/- 0.2 3.3 +/- 0.1 91 3.4 +/- 0.1 3.7 +/- 0.4 3.8 +/- 0.3 3.8 +/- 0.2 92 4.2 +/- 0.3 4.4 +/- 0.3 4.4 +/- 0.4 4.7 +/- 0.3 95 3.2 +/- 0.2 3.5 +/- 0.4 3.5 +/- 0.2 3.5 +/- 0.2 96 3.8 +/- 0.2 4.3 +/- 0.9 3.9 +/- 0.2 4.1 +/- 0.3 97 3.4 +/- O.1 3.7 +/- 0.2 4,3 +/- 0.2 4.7 +/- 0.,4 A 3.8 +/- 0.2 4.2 +/- 0.4 3.9 +/- 0.3 4.0 +/- 0.3 C 3.4 +/- 0.2 4.7 +/- 0.2 3.5 +/- 0.2 4.7 +/- 0.1 H 3.3 +/- 0.2 3.5 +/- 0.1 3.3 +/- 0.2 4.4 +/- O.2 T1 4.8 +/- 0.2 5.0 +/- 0.3 4.2 +/- 0.3 4.4 +/- 0.2
*IDST TLD
r m MM M mm m m M em m .
~
mm m mm TABLE J-2 Oyster Creek Nuclear Generating Station - Environmental Controls 1989 Quarterly Environmental TLD Report - Panasonic Running Table - M1111 Rem Per Standard Quarter and 2-Standard Deviations SECOND QUARTER THIRD QUARTER FOURTH QOARTER STATION FIRST QUARTER 10.20 +/- 0.97 10.10 +/- 0.66 11.50 +/- 0.73 1 9.18 +/- 1.75 10.60 +/- 1.56 10.10 +/- 0.84 9.77 +/- 0.36 10.20 +/- 0.99 3 9.19 +/- 0.93 9.08 +/- 0.71 9.33 +/- 1.10 4 8.97 +/- 1.42 10.40 +/- 1.25 10.60 +/- 0.65 11.00 +/- 0.56 5 10.30 +/- 0.40 9.31 +/- 0.37 9.08 +/- 0.47 10.10 +/- 0.58 6 8.98 +/- 1.52 8.68 +/- 0.89 8.58 +/- 0.63 10.00 +/- C.30 7 9.72 +/- 1.07 9.52 +/- 1.05 11.30 +/- 1.29 11.20 +/- 0.85 8 10.40 +/- 0.94 11.10 +/- 0.91 10.80 +/- 0.56 11.90 +/- 0.85 9 10.90 +/- 1.16 9.87 +/- 1.01 9.42 +/- 0.51 11.60 +/- 0.99 , 10 9.21 +/- 1.17 9.27 +/- 0.87 9.20 +/- 0.89 10.50 +/- 2 37__, i 11 9.02 +/- 1.17 l 11.10 +/- 0.75 9.87 +/- 0.53 11.10 +/- 11.54 12 10.60 +/- 0.67 ! 9.25 +/- 0.95 8.48 +/- 0.69 10.30 +/- 0.98 13 9.64 +/- 0.77 12.70 +/- 0.73 11.90 +/- 0.58 13.10 +/- 0.80
- 14 12.60 +/- 0.61 10.20 +/- 0.61 11.40 +/- 0.76 5 15 9 30 +/- 1.79 10.20 +/- 1.12 9.26 +/- 1.02 9.73 +/- 0.95 Y 16 9. T",' + /- 0. 4 3 9.66 +/- 0.88 9.06 +/- 1.13 10.10 +/- 0.78 10.40 +/- 0.43 17 9.64 +/- 1.51 9.59 +/- 1.21 9.60 +/- 0.94 '9.74 +/- 0.94 20 9.86 +/- 1.36 9.47 +/- 0.98 9.05 +/- 0.49 10.40 +/- 0.70 22 9.62 +/- 1.03 12.50 +/- 0.54 12.70 +/- 0.84 13.50 +/- 0.52 51 12.70 +/- 1.40 13.70 +/- 1.09 12.60 +/- 0.63 14.50 +/- 0.58 52 13.40 +/- 1.19 11.80 +/- 1.10 11.30 +/- 1.00 12.30 +/- 0.52 53 11.40 +/- 1.44
* +/-
- 9.50 +/- 1.15 9.28 +/- 0.23 11.00 +/- 0.35 54 10.60 +/- 1.03 10.10 +/- 0.80 10.70 +/- 0.66 55 9.68 +/- 1.12 11.70 +/- 0.40 10.50 +/- 0.83 12.30 +/- 0.20 56 11.90 +/- 0.79 12.60 +/- 1.50 12.70 +/- 0.75 14.50 +/- 2.34 57 11.70 +/- 0.53 11.00 +/- 0.89 10.80 +/- 0.51 12.60 +/- 0.80 58 9.01 +/- 1.79 11.20 +/- 0.92 13.20 +/- 0. 72 ____
59 10.80 +/- 2.32 11.90 +/- 1.39 9.99 +/- 0.86 10.30 +/- 1.39 30.70 +/- 0.54 60 10.20 +/- 0.33 10.60 +/- 0.60 9.87 +/- 0.65 10.30 +/- 0.70 61 9.04 +/- 1.14 10.70 +/- 0.68 10.70 +/- 0.60 11.50 +/- 0.92 62 9.51 +/- 1.70 11.60 +/- 1.12 11.20 +/- 0.43 11.50 +/- 1.01 63 11.20 +/- 1.32 10.80 +/- 0.25 ' 64 10.60 +/- 0.98 10.00 +/- 0.80 9.50 +/- 0.97
- LOST TLD
(. M~M M M M M M M M M M IM M M' ' M M M TABLE J-2 (Continued) Oyster Creek Nuclear Generating Station - Environmental Controls 1989 Quarterly Environmental TLD Report - Panasonic Running Table - M1111 Rem Per Standard Quarter and 2-Standard Deviations STATION FIRST OUARTER SECOND OUARTER THIRD OUARTER FVURTH OUARTER 65 9.02 +/- 0.62 10.20 +/- 1.13 * +/-
- 11.00 +/- 0.66 66 8.46 +/- 1.14 9.83 +/- 0.96 9.64 +/- 0.92 10.20 +/- 0.42 67 10.60 +/- 1.13 10.90 +/- 0.94 9.51 +/- 0.81 11.40 +/- 0.66 69 9.87 +/- 0.96 9.65 +/- 0.46 8.81 +/- 0.85 10.30 +/- 0.43 70 7.71 +/- 3.49 9.74 +/- 0.49 8.65 +/- 0.19 10.00 +/- 0.54 71 9.30 +/- 1.15 9.82 +/- 0.48 9.19 +/- 0.77 10.90 +/- 0.72 73 9.94 +/- 0.94 -
9.24 +/- 0.58 8.75 +/- 0.17 9.67 +/- 0.53 74 10.40 +/- 1.26 9.89 +/- 0.97 10.00 +/- 0.61 10.80 +/- 0.71 75 11.80 +/- 1.23 11.00 +/- 1.18 10.40 +/- 0.76 11.20 +/- 0.98 76 8.56 +/- 0.89 8.94 +/- 0.89 9.02 +/- 0.67 10.10 +/- 0.90 77 10.00 +/- 0.63 9.85 +/- 0.83 9.08 */- 0.66 10.20 +/- 0.49 78 8.73 +/- 0.98 10.10 +/- 0.82 9.28 +/- 0.41 10.30 +/- 0.33 s 79 9.12 +/- 1.38 8.49 +/- 0.69 8.20 +/- 0.56 9.38 +/- 0.52 U
~
80 8.91 +/- 1.52 9.41 +/- 0.67 9.36 +/- 0.69 9.84 +/- 0.56 Y 81 11.00 +/- 1.62 10.60 +/- 0.40 10.30 +/- 0.50 11.00 +/- 0.58 82 10.80 +/- 1.62 10.90 +/- 1.01 10.60 +/- 0.56 11.00 +/- 0.94 83 10.60 +/- 1.76 10.60 +/- 1.42 9.78 +/- 0.65 10.70 +/- 0.76 84 10.80 +/- 0.73 11.80 +/- 1.22 10.50 +/- 0.61 10.40 +/- 0.92 85 10.50 +/- 1.44 10.00 +/- 1.10 9.65 +/- 0.57 10.70 +/- 0.51 86 10.20 +/- 1.40 10.20 +/- 1.43 9.66 +/- 0.52 9.92 +/- 0.80 87 10.90 +/- 1.10 11.30 +/- 1.23 10.90 + /- 0. 30 12.00 +/- 0.43 88 8.04 +/- 1.29 9.34 +/- 0.45 8.65 +/- 0.50 9.40 +/- 0.59 89 9.51 +/- 1.75 8.38 +/- 1.08 7.97 +/- 0.82 9.59 +/- 0.80 90 8.97 +/- 1.16 8.97 +/- 0.59 9.58 +/- 0.67 9.28 +/- 0.79 91 10.00 +/- 0.90 10.40 +/- 0.77 10.60 +/- 0.90 10.40 +/- 1.07 92 11.70 +/- 1.16 11.90 +/- 1.37 11.40 +/- 0.38 11.50 +/- 1.07 95 10.10 +/- 0.49 9.48 +/- 0.57 9.58 +/- 0.83 9.76 +/- 0.89 f 96 10.40 +/- 1.16 9.66 +/- 0.11 10.80 +/- 1.01 10.90 +/- 0.42 97 10.10 +/- 1.42 9.88 +/- 1.26 10.40 +/- 0.29 10.30 +/- 0.58 A 12.10 +/- 1.70 11.70 +/- 1.11 '11.00 +/- 1.14 12.70 +/- 1.17 C 9.86 +/- 1.46 10.20 +/- 1.24 10.60 +/- 0.86 12.20 +/- 0.96 H 10.90 +/- 1.45 9.48 +/- 0.69 9.94 +/- 0.99 10.50 +/- O.95 T1 9.09 +/- 1.13 9.76 +/- 1.24 10.10 +/- O.66 11.90 +/- 0.99
*IDST TLD
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. . _ ._~ . , ~ - , , _ . - , .. .-- - , , _ _ , . _ . _ _ - .. _ . . , _ ~ _ , . -}}