ML20206G379
| ML20206G379 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/31/1998 |
| From: | Kuehn G GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1920-99-20233, NUDOCS 9905070186 | |
| Download: ML20206G379 (100) | |
Text
.
c l
{ GPU Nuclear. Inc.
( Route 441 South NUCLEAR Post Office Box 480 Middletown. PA 17057-0430 Tel 717-944 7621 I
April 29,1999 1920-99-20233 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Saxton Nuclear Experimental Corporation (SNEC)
Operating License No. DPR-4 Docket Nos. 50-146 1998 Radiological Environmental Monitoring Report In accordance with SNEC Technical Specification Section 3.8.2.3 and the SNEC Off-Site Dose Calculation Manual Part 3, Section 1.0 the 1998 SNEC Radiological Environmental Monitoring Report is enclosed.
Please contact Dennis P. Kelly of Licensing at 609-971-4246 if you have any questions regarding this submittal.
Sincerely, ,
h- N G. A. Kuehn Vice President SNEC AFP Enclosure cc: NRC Project Manager NR.R ' "'
NRC Project Scientist, Region I
, , } t}
, f hO 9905070186 981231 #
a 1 Radiological Environmental Monitoring Report for 1998 Saxton Nuclear Experimental Corporation e' 's '
'a
- p ,# i;gllYf w
":ll["^ J g,%gj$f&$q[1lG{ay
- 4 *4L --JE i<'
w.-%
" W e Sli;W WE @ MlT gg,lQl,NQj?;,dl$h_s
- 'g Mh %a;# *$g ?p;g , , y y;44
" ~ '
J.
>g
- n. - &lifW,ii;;
.o -~ . " ra i i?"
"' 3:g%wll%
dl T W
'N; , '/ b ' -fU j .g'.
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT l
TABLE OF CONTENTS l l
l Page Title i TABLE OF CONTENTS iii LIST OF TABLES iv LIST OF FIGURES v LIST OF ABBREVIATIONS, SYMBOLS AND 1 ACRONYMS 1
SUMMARY
AND CONCLUSIONS 4 INTRODUCTION 4 Characteristics of Radiation 5 Sources of Radiation 9 DESCRIPTION OF Tile SNEC SITE j 9 Location of the Plant Site 9 Description of Plant Site 10 SNEC Decommissioning Operations 10 Facility Description 10 Containment Vessel 11 Demography - Iluman Activities in the Environs 11 Geology 14 RADIOLOGICAL ENVIRONMENTAL MONITORING 15 Sampling 16 Analysis i 16 Data Review !
17 Quality Assurance Program 21 DIRECT RADIATION MONITORING 22 Sample Collection and Analysis 22 Results 25 ATMOSPHERIC MONITORING 26 Sample Collection and Analysis 26 Air Results 31 GROUNDWATER MONITORING 32 Groundwater Results 36 BROAD LEAF VEGETATION MONITORING 37 SURFACE WATER MONITORING Pagei
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT 1
Page Title 38 AQUATIC SEDIMENT MONITORING 40 REFERENCES I APPENDIX A: 1998 REMP Sampling Locations and 1
Descriptions, Synopsis of REMP, and Exceptions in Sampling and Analysis APPENDIX B: 1998 Lower Limit of Detection (LLD)
Exceptions APPENDIX C: 1998 REMP Changes APPENDIX D: 1998 Action Levels APPENDIX E: 1998 Quality Control Program APPENDIX F: 1998 Cross-Check Program Results APPENDIX G: 1998 Data Reporting and Analysis APPENDIX H: 1998 REMP Sample Collection and j Analysis Methods APPENDIX 1: 1998 TLD Quarterly Data l
1 I
Pageii I
l j
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l LIST OF TABLES I
Page Title ,
I l
6 Table 1 Sources and Doses of Radiation 24 Table 2 SNEC TLD Summary for 1998 24 Table 3 Highest Site Boundary Exposure Comparison 28 Table 4 1998 Average Gross Beta Concentrations in Air Particulates 28 Table 5 1998 Average Gross Alpha Concentrations in Air l Particulates 1 34 Table 6 Tritium Concentrations in GEO-5 35 Table 7 1998 Tritium Results in Groundwater Monitoring l Wells i 39 Table 8 1998 Concentrations in Aquatic Sediment I
Page lii
1 1 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REfY)RT
\
l LIST OF FIGURES ,
1 Page Title 13 Figure 1 SNEC Facility Site Layout 19 Figure 2 Locations of REMP TLD and Aquatic Sediment Stations 20 Figure 3 Locations of REMP Groundwater Wells 29 Figure 4 1998 Gross Beta Concentrations in Air !
Particulates 30 Figure 5 1998 Gross Alpha Concentrations in Air Particulates i
l 1
i i
Page iv I
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT LIST OF ABBREVIATIONS, i
SYMBOLS AND ACRONYMS ABBREVIATIONS south-southwest . . . .. . ... .. . . . . . . SSW cubic feet per second .. .. . . . . . . . cfs standard deviation.. . .. .... .. std dev cubic meter (s).. . ... . . ...... ... .. .m 3 standard month., . .... . . . std month curic(s)... .... . .......... . ... . . .... . . . Ci west . . ..... .. ... . . .. .........W curie (s) per year . . . . . . . . . . . . . . . . . . . . . Ci/yr west-northwest . . .. .. .... . . . . . . . WNW cast . . . . . .. ............. ... .............E west-southwest .. ... .... .. . . .. ...WSW cast-northeast . ... . . .. . . . . . . . . . EN E year (s) . .... . . ................yr east-southeast .. .. . .. .. .. . . ... .. . . . ESE E.LEMENT SYMBOLS gram (s) . . . . . . . . . . . . . .... .. . . .. . ... ...g actinium . . . . . . . . . . . .. . .. ... .Ac hour (s) . . . . . . .... . . . ........ ....h antimony . . . . .. . . . . . Sb liter (s) . . . . . . . .. .. . . . .........L argon . . . .. . .. . . . . . . Ar meter (s) . . . . . . . . . . . . . . . . . . . . . . . . . .. .m bariu m . . . . . . . . . . . . . . . . . .. . . . .. .Ba microroentgen per hour . . .... . ... . uR/h beryllium . . .. .. . . ... . .. . . . . . . Be mile per hour .. . . . . . ... ... . .. . . mph carbon . . . . . . . . . . . . ................C millirem . . . . . . . . . . . . . . . . . . .. . . mrem cesium. . ... .....................Cs millirem per hour . .. . ..... . .... . . mrem /h chromium .. . . .... . ... . . . . . Cr millirem per standard cobalt . . .. . . . . . . . . . . . . Co month . , . .. .. . . . mrem /std month curium . . . . . . . . . . .... .. . . . . Cm millitem per year . . . . . . . . . . . . . . . . . . mremlyr hydrogen (tritium) .... . . . . . H -3 milliroentgen. .. .. . .... . . .mR iodine. .. .. ... . .. . .. ......I milliroentgen per hour.. . . . . . . . . . m R/h iron . . .. .. .. ... .. . .. ...... .Fe milliroentgen per standard krypton . . . . . .. .. .. . ... ...Kr month . . . . . . . . . ...... . . ......mR/std month lanthanum .. ... .. . . .. .. .... . . . La north . . . . . . . . . . . . . . . . . . . . . ..... .. .. .N manganese . .. . .. . .. ..... .. . . . .. M n northeast . . . . . . . . ........ .. . .. .... .....NE niobium .... . .. .. . . . . . . . . . . . . . Nb northwest . .. . .. . .. ..... .. .... . . NW nitrogen .. . . .. ... .. . . ... .....N nonh-northeast.. . ... . .. . .. . . NNE oxygen.... .. . . .... . . ..........O north-northwest . . . . . . . . . . . . . . . . . . . . . . . . . . ..NNW plutonium . .. . . .. .. .. .Pu percent. .. ..........................% potassium .. . . . . . .. . .. . . ...K picocurie (s). . . . . . . . . . . . . . . . . . . . . . . . . . . pCi radium . . . . . . . . . . ... .. ... . . .Ra picocurie (s) per cubic meter . . . ...... . . pCi/m 2 radon . . .. .... . ....... . . . . . . . . . . . . Rn picocurie (s) per gram . . . . . . . . . . . . . . . . . . pCi/g ru thenium . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ru picocurie (s) per liter . ... ... . . . ... .. . . . pCi/L silver. . . . . . . ...... ... . .. . . . . . . . . Ag re ference(s) . . . . . . . . . . . . . . . . . . . . . .. Ref. (Refs.) strontium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Sr rem per year .... .. .. . . . . . . . . . . . . . rem /yr thorium . , . . . . . . . . . . . . . . . . . . . . Th Roentgen . . . . . . . . ...... . .. .. .... . ......R tritiated water vapor . ... . .... .. ...HTO Roentgen equivalent man. . . . . . . . . . . . . . . . . . . . . . . rem uranium . .. ................................U s outh . . . . . . . . . . . . . . . . . . . . . . . . . . . ............S xenon . . . . . . . . . ... .... . . ... .. . . . . . . . Xe southea st . . . . . . . . . . . . . . . . . . . . . . . . . . . . .....SE zinc .. ..... . ... . . . .... .. . .Zn southwest . , . . . . . . . . . . . . . . . . . . . . . . . . . .... .. S W zirconium . . . . . . . . . . . . . .. . . . . . . . Zr Pagev
1 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ACRONYMS American National Standards National Voluntary Laboratory Ins ti'ut e . . . . . . . . . . . . . . . . . . . . . . . . . .. ANSI Accreditation Program....... . ....NVLAP
{
as low as reasonably Offsite Dose Calculation Manual .... ....ODCM achievable. . .. . . . .. .ALARA Pennsylvania State Bureau biological effects of atomic of Radiation Protection . .. . ..... . PaBRP radiation . . . . . . . . . . . . . . . . . . . . . . . .... .... B E A R pressurized water reactor.. ....... .. ... .. PWR i biological effects of ionizing l radiation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B EIR quality assurance...... . .. .. . . . . .QA l l
Department of Energy... .. ... .... DOE quality control . .. ... . . .... . . .QC j 1
l Derived Air Concentration.. . .DAC radiological environmental monitoring program.. ...... ... .... . R E M P Federal Radiation Council... . . . .. .. ...FRC Saxton Nuclear Experimental 3 Final Safety Analysis Report . . . . .FSAR Corporation.... . . .. . ... . . . . . . . ..SNEC General Public Utilities thermoluminescent dosimeter. ... ...TLD Nuclear Corporation... . . . .. ..GPU Nuclear Title 10 of the Code of high efficiency particulate air. . . .11 EPA Federal Regulations. Part 20. .. ...10 CFR 20 International Committee on Title 10 of the Code of Radiation Protection.. . .lCRP Federal Regulations, Part 50, Appendix I ... . .. . .10 CFR 50 App. I lower limit of detection.. . . . . . . . . . . . . . LL D Title 40 of the Code of mean sea level .. . . . . . . .. ... . . ... . . msl Federal Regulations, Part 190.. . . . .. .. . .... . 40 CFR 190 minimum detectable concentration.. ..MDC United Nations Scientific National Academy of Sciences . ... ..... . NAS Committee on the Effects of National Council on Radiation Atomic Radiation . .. . .. UNSCEAR Protection and Measurements. . . .. ..... NCRP United States Environmental Protection Agency . . ... ... . ....USEPA National Institute of Standards and Technology .... ... . .. .NIST United States Nuclear Regulatory Commission.... .. ... .. .. .USNRC Page vi
t 1998 RADIOLOGICAL ENVIRONMENT 4L MONITORING REPORT l
l
SUMMARY
AND CONCLUSIONS l l
l This report reviews the radiological environmental monitoring performed in 1998 by GPU Nuclear for the Saxton Nuclear Experimental Corporation i (SNEC) Facility. The environmental sample ;
results indicated that SNEC operations in 1998 had no adverse effect on either the environment or the health and safety of the public.
Many of the radioactive materials discussed in this report are normally present in the environment, either from natural processes or as a result of non-SNEC activities such as prior atmospheric nuclear weapon tests and medical industry activities. To determine the impact of SNEC operations on the environment and the public, results from samples collected close to SNEC (indicator stations) were compared to results from samples obtained at distant sites (control or background stations).
Page 1
i I998 RADIOLOGICAL ENVIRONMENTAL MONlwRING REPORT 1
The results of environmental measurements were used to assess the impact of SNEC decommissioning operations and to demonstrate compliance with the SNEC Offsite Dose
]
Calculation Manual (Ref.1) and applicable Federal and State regulations. l 1
During 1998, samples of air, surface water, sediment, soil, vegetation, and groundwater were collected. Direct radiation exposures were also measured in the vicinity of SNEC. Samples were analyzed for gross alpha and gross beta radioactivity, tritium (H-3), strontium-90 (Sr-90), and/or gamma emitting radionuclides. The results are discussed in the various sections of this report and are summarized in the following highlights: j u Approximately 300 samples were collected in 1998 from the aquatic, atmospheric and terrestrial environments around the SNEC facility. There were nearly 600 analyses i performed on these samples. In addition,112 direct radiation exposure measurements were I taken using thermoluminescent dosimeters (TLDs). The monitoring performed in 1998 met ;
or exceeded the sample collection and analysis requirements of the SNEC Offsite Dose j Calculation Manual (ODCM). ;
E The raw surface water collected downstream of the SNEC liquid discharge outfall resulted in less then detectable activities for radionuclides attributed to SNEC, including tritium (H-3).
E River sediments collected just downstream of the SNEC liquid discharge outfall and at the control station upstream of the site detected low concentrations of Cesium-137 (Cs-137).
These concentrations were attributed to fallout from prior nuclear weapon tests. Cs-137 was also detected in aquatic sediments collected from storm drains that are located on site.
Cesium is readily adsorbed by suspended particles in sediment. i E Eight groundwater samples collected from the onsite monitoring and supply wells contained I H-3 above ambient concentrations. The activities of these samples ranged from 120 to 150 l picocuries per liter (pCi/L). Although humans do not consume this water, it was well l below the United States Environmental Protection Agency's (USEPA's) Primary Drinking l Water Standard (Ref. 2) of 20,000 pCi/L.
E Gamma radiation exposure rates recorded at the offsite indicator TLD stations averaged 65 milliroentgens per year (mR/yr). These exposure rates were consistent with those I' presented by the National Council on Radiation Protection and Measurements (Ref. 3). No increase in ambient gamma radiation levels was detected.
Page 2
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT In conclusion, radioactive materials related to SNEC operations were detected in certain on-site environmental samples, but the measured concentrations were very low. During 1998, no liquid effluents were released and no SNEC related radioactivity was detected in the gaseous effluent releases that occurred from SNEC. Hence, no dose to the public should be attributed to SNEC activities. The environmental sample results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.
Therefore, based on the results of the radiological environmental monitoring program (REMP)
SNEC operations in 1998 did not have any adverse effects on the health and safety of the public or on the environment.
l 4
I l
f I
i l
Page 3 l 1
l
I i998 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT INTRODUCTION Characteristics of Radiation Instability within the nucleus of radioactive atoms results in the release of energy in the form of radiation. Radiation is classified according to its nature -- particulate and electromagnetic.
Particulate radiation consists of energetic l subatomic particles such as electrons (beta particles), protons, neutrons, and alpha particles. i Because of its limited ability to penetrate the human body, particulate radiation in the environment contributes primarily to internal radiation exposure resulting from inhalation and l ingestion of radioactivity. '
Electromagnetic radiation in the form of x-rays l and gamma rays has characteristics similar to !
visible light but is more energetic and, hence, j more penetrating. Although x-rays and gamma l rays are penetrating and can pass through varying thicknesses of materials, once they are j 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 contribution to external radiation exposure.
Page 4
(
1998 RADIOLOGICAL ENVIRONMENTAL MONlwR1NG REPORT The rate with 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 natural background radiation to which all mankind has been exposed is largely due to the radionuclides of uranium (U), thorium (Th), and potassium (K). 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 (K-40) has a half-life of 1.3 billion years and exists naturally within our bodies. As a result, approximately 4000 atoms of potassium emit radiation within each of us every second of our lives.
In assessing the impact of radioactivity on the environment, it is important to know the quantity of radioactivity released and the resultant radiation doses. The common unit of radioactivity is the curie (Ci). The curie represents the radioactivity in one gram (g) of natural radium (Ra), which is equivalent to a decay rate of 37 billion radiation emissions every second. Because of the extremely small amounts of radioactive material in the environment, it is more convenient to use fractions of a curie. Subunits like picocurie, pCi, (one trillionth of a curie) are frequently used to express the radioactivity present in environmental and biological samples.
The biological effect4 of a whole body equivalent dose of radiation are the same whether the radiation source is external or internal to the body. The important factor is how much radiation energy or dose was deposited. The unit of radiation dose is the Roentgen equivalent man (rem), which also incorporates the variable effectiveness of different forms of radiation to produce biological change. For environmental radiation exposures, it is convenient to use the smaller unit of millirem (mrem) to express dose (1000 mrem equals 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 environmental exposures are usually expressed with reference to one year (mrem /yr).
Sources of Radiation Life on earth has evolved amid the constant exposure to natural radiation. In fact, the single major source of radiation to which the general population is exposed comes from natural sources. Although everyone on the planet is exposed to natural radiation, some people receive more than others do. Radiation exposure from natural background has three components (i.e., cosmic, terrestrial, and internal) and varies with altitude and geographic location, as well as with living habits. For example, cosmic radiation originating from deep interstellar space and the sun increases with altitude, since there is Page 5
i 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT less air which acts as a shield. Similarly, terrestrial radiation resulting from the presence ;
of naturally-occurring radionuclides in the soil and rocks varies and may be significantly I higher in some areas of the country than in others. Even the use of particular building materials for houses, cooking with natural 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 amounts of uranium and j radium while milk contains radioactive potassium. Table 1 summarizes the common j sources of radiation and their average annual doses.
The average person in the United States receives about 300 mrem /yr (0.3 rem /yr) from natural background radiation sources (Ref. 4). This estimate was revised from about 100 to 300 mrem because of the inclusion of radon gas which has always been present but j l was not previously included in the calculations. In some regions of the country, the j amount of natural radiation is significantly higher. Residents of Colorado, for example, receive an additional 60 mrem /yr due to the increase in cosmic and terrestrial radiation levels. In fact, for every 100 feet above sea level, a person will receive an additional 1 mrem /yr from cosmic radiation. In several regions of the world, naturally high j concentrations of uranium and radium deposits result in doses of several thousand j mrem /yr to their residents (Ref.5). !
TABLEI Sources and Doses of Radiation
- Natural (82%) Manmade (18%)
Radiation Dose Radiation Dose Source (mrem /vr) Source (mrem /vr)
Radon 200 (55 %) Medical X-rays 39 (11 % )
Cosmic rays 27 (8%) Nuclear Medicine 14 (4 %)
Terrestrial 28 (8%) Consumer products 10 (3%)
Internal 40 (l1 %) Other <1(<1%)
(Releases from nat. gas, phosphate mining, burning of coal, weapons fallout, & nuclear fuel cycle)
APPROXIMATE APPROXIMATE TOTAL 300 TOTAL 60
- Percentage contribution of the total dose is shown in parentheses. Source: Ref. 4 Page 6
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Recently, public attention has focused on radon (Rn), a naturally-occurring radioactive gas produced from uranium and radium decay. These elements are widely distributed in trace amounts in the earth's crust. Unusually high concentrations have been found in certain parts of eastern 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. Additional surveys, however, are needed to detennine the 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 Protection and Measurements (NCRP) estimates that the average individual in the United States receives an annual dose of about 2,400 mrem to the lung from natural radon gas (Ref. 4). This lung dose is considered to be equivalent to a whole body dose of 200 mrem. The NCRP has recommended actions to control indoor radon sources and reduce exposures.
When radioactive substances are inhaled or swallowed, they are not uniformly distributed within the body. 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 radionuclide is influenced by the quantity and the duration of time that the radionuclide remains in the body, including its physical, 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 for years.
In addition to natural radiation, we are exposed to radiation from a number of manmade sources. The single largest of these sources comes from diagnostic medical x-rays and nuclear medicine procedures. Some 180 million Americans receive medical x-rays and nuclear medicine treatment each year. The annual dose to an individual from such radiation averages about 53 mrem. Much smaller doses come from nuclear weapon fallout and consumer products such as televisions, smoke detectors, and fertilizers. !
Production of commercial nuclear power and its associated fuel cycle contributes less than 1 mrem to the annual dose of about 360 mrem for the average individual living in !
the United States.
Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of a nuclear weapon. It is dispersed throughout the environment either by dry deposition or washed down to the earth's surface by precipitation. 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, which produce most of the fallout radiation exposures to j humans are 1-131, Cs-137, Sr-89, and Sr-90.
There has been no atmospheric nuclear weapon testing since 1980 and many of the 1
Page 7
l i
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT radionuclides, still present in our environment, have decayed significantly.
Consequently, doses to the public from fallout have been decreasing. As a result of the nuclear accident at Chernobyl, Ukraine, on April 26,1986, radioactive materials were dispersed throughout the environment and detected in various media such as air, milk, and soil. Cesium-134 Cs-137,1-131 and other radionuclides were detected in the weeks following the Chernobyl accident.
l l
1 Page 8
4 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT DESCRIPTION OF THE SNEC SITE Location of the Plant Site The site is located about 100 miles east of Pittsburgh and 90 miles west of Harrisburg, Pennsylvania in the Allegheny Mountains, three-fourths of a mile north of the Borough of Saxten in Liberty Township, Bedford County, Pennsylvania. The site is on the north side of Pennsylvania Route 913,17 miles south of U.S. Route 22, and about 15 miles north of the Enezewood Interchange of the Pennsylvania Turnpike.
Description of Plant Site Saxton was built adjacent to the Saxton Steam Electric Generating Station of Pennsylvania Electric Company (Penelec), a subsidiary of GPU. This coal fired station operated from 1923 to 1974 and was demolished between 1975 and 1977. The Saxton site consists of 1.148 fenced acres of the approximate 150 acres owned by Penelec. An additional 9.6 acre fenced area contains an electrical switchyard and buildings under Penelec control. A general property layout is shown in Figure 1. The Sax *on site, as well as a portion of the Penelec area and the surrounding Page 9
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT uncontrolled lands, is in the 100-year floodplain of the Raystown Branch of the Juniata River which borders the north and west ponion of the property. A small stream known as Shoup's Run crosses the central portion of the property and joins the Juniata River. Normal elevation of the River near Saxton is approximately 794 feet above mean sea level (msl). The site and adjacent property lie about 17 feet above river level. Much of the property consists of gently sloping open grassland, a result of the restoration activities following the demolition of the Saxton Steam Electric Generating Station.
SNEC Decommissionine Operations The Saxton Nuclear Experimental Facility was a pioneer in the development of the nuclear energy program for the United States. It operated for ten years, from 1962 to 1972, and provided valuable information on operations and training. The fuel was removed from the Containment Vessel (CV) in 1972 and shipped to the Atomic Energy Commission (AEC) facility at Savannah River, South Carolina. Following fuel removal, equipment, tanks, and piping located outside the CV were removed. Final decontamination and dismantlement of reactor support structures and buildings were completed in 1992.
On April 20,1998, the U.S. Nuclear Regulatory Commission (NRC) gave its approval for the final stage of decommissioning. The first task was to verify that the ventilation system for SNEC's decommissioning support building (DSB) was operating correctly. Next, a 10-foot by 15-foot opening was cut in the DSB to allow movement of materials and equipment in and out of the building. Five of seven 20-ton large concrete shield blocks used to shield the reactor j vessel during plant operation have already been amoved through this opening. In October !
1998, the large component structures, pressurizer, steam generator and reactor vessel, were removed and shipped to Chem-Nuclear's low-level waste facility in Barnwell, S.C. Additional information can be obtained from the 1998 SNEC Annual Operations Report (Ref. 6). 1 Epcility Description The only remaining Saxton stmetures include the Containment Vessel (CV), the two remaining l concrete shield walls and tunnel sections that are immediately adjacent to the outer circumference of the CV. Concrete barrier walls have been installed to isolate the open ends l of the tunnel that were connected to the Control & Auxiliary Buildings, the Radioactive Waste Disposal Facility and the Steam Plant. Portions of the Steam Plant Tunnel still exist beyond the point where the tunnel was blocked-off. j l
Containment Vessel The Saxton Containment Vessel is a circular steel structure approximately 100 ft. tall by 50 ft. )
in diameter with approximately 50 percent of the structure below grade. The CV is subdivided Page 10
1 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT into a reactor compartment / storage well, primary compartment, auxiliary compartment and an operating floor. Concrete walls, floors and ceilings separate these areas from each other. The below grade portion of the CV is lined with concrete, as well.
Demagtaphy - Human Activities in the Environs i
The area surrounding the Saxton site is generally mral forested and mountainous terrain. The population density of the area is low with small concentrations in the valleys and along main I highways. The site lies about three-fourths of a mile north of the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania. The population and population trends for the Borough of Saxton, Bedford County and the adjacent counties of Blair and Huntingdon have decreased by approximately 3% between 1980 and 1990 (Ref. 7). At the time the SNEC facility was constructed, the estimated population of the Borough of Saxton was 975 as recorded during the 1960 census. Thirty years later, the population as recorded during the 1990 census was 838, a decline of 16.3%.
The nearest population center (as defined by 10 CFR 100) of 25,000 or more is the city of Altoona which lies approximately 20 miles north-northwest of the Saxton site. The 1990 population of Altoona was 51,881. The closest incorporated towns other than the Borough of Saxton are Coalmont Borough about 2.5 miles to the east, Dudley Borough about 3.4 miles to the east and Broad Top about 5.3 miles also to the east.
Current uses of adjoining properties include undeveloped wooded and residential areas. A cemetery lies along the eastern property boundary while undeveloped wooded and residential areas border the northern, southern and western property boundaries.
The Raystown Branch of the Juniata River in the vicinity of the site is primarily used for recreational boating and fishing by local residences. The vast majority of recreational activities along the river, however, are located downstream of the site on Raystown Lake.
Approximately 34 miles downstream of the site, the Raystown Branch of the Juniata River is dammed, impounding the river to form Raystown Lake. The dam built by the US Army Core of Engineers (COE) for flood control, recreation and water quality purposes was constmeted from 1%8 to 1973. At normal pool level, the lake is 27 miles long and has an area of 8,300 acres. Raystown Lake provides one of the better recreational areas in this part of Pennsylvania. The Federal Government developed the lake extensively for recreational activities including boating, fishing, camping, hunting, and picnicking.
Geolony The Saxton site lies in the Appalachian highlands in the Ridge and Valley physiographic province. This province comprises alternate successions of narrow ridges and broad or narrow Page 11
i
- 1 1998 RADIOLOGICAL ENVIRONMENTAL MONIH) RING REli)RT valleys trending generally northeast. This region contains alternating hard and soft sedimentary rocks that have been severely folded by lateral compression into a series of anticlines and synclines. The ridge consists of Tuscarora quartzite and a small amount of Pleistocene gravel. Most of the area is underlain by strata of Upper Devonian age. Although coal was mined in the general area of the site, no coal has been reported to lie beneath the site, nor has the site been undermined. The ridges immediately to the northwest of the site rise to 1300 feet and to the southeast rise to 1500 feet with site elevation being approximately 811 feet above msl.
)
1 l
1 1
Page 12 l
l l
a
(
l l
l Figure 1 1 I
i SNEC FACILITY SITE BOUNDARIES (No Scale)
N '
. Trauer compsex
/-'
, bd l
,e ,
son-sies n 'N ,% l
/ Weste storage
, g. SNEC cv
\')l
/ Aree Park ng ree _
4' #
'N l d DSF )
I
, 'O ,
l 4~,w - .a.
! Acease need outer Fence Page 13
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT i
RADIOLOGICAL !
t ENVIRONMENTAL MONITORING GPU Nuclear conducts a comprehensive radiological environmental monitoring program (REMP) at SNEC to measure levels of radiation and radioactive materialc in the environment.
The information obtained from the REMP is then used to determine the effect of SNEC operations, if any, on the environment and the public.
The USNRC has established regulatory guides i that contain acceptable monitoring practices. The SNEC REMP was designed on the basis of these l regulatory guides along with the guidance provided by the USNRC Radiological Assessment Branch Technical Position for an acceptable radiological environmental monitoring program (Ref. 8). The SNEC REMP meets or exceeds the monitoring requirements set forth by the USNRC.
Page 14
\
I 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT The important objectives of the REMP are:
u To assess dose impacts to the public from the SNEC Facility, a To verify decommissioning controls for the containment of radioactive materials.
e To determine buildup of long-lived radionuclides in the environment and changes in background radiation levels.
I E 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.
m To fulfill the requirements of the SNEC Technical Specifications.
Sampline The program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and then interpreting the results. These samples include, but are not limited to, air, water, sediment, soil, vegetation and groundwater.
Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels.
The Offsite Dose Calculation Manual (ODCM), (Ref.1) defines the sample types to be collected and the analyses to be performed. As appropriate, changes to the REMP are initiated by recommendations from the scientific staff at the GPU Nuclear Environmental Radioactivity ;
Laboratory. However, the minimum sampling and analysis requirements specified in the ODCM are maintained or exceeded.
Sampling locations were established by considering topography, meteorology, population distribution, hydrology, and areas of public interest. The sampling locations are divided into two classes, indicator and control. Indicator locations are those which are expected to show I effects from SNEC activities, if any exist. These locations were selected primarily on the basis of where the highest predicted environmental concentrations would occur. The indicator locations are typically within the site boundary, along the perimeter fence or a few miles from the SNEC facility.
Control stations are located generally at distances greater than 10 miles from SNEC. The samples collected at these sites are expected to be unaffected by SNEC operations. Data from control locations provide a basis for evaluating indicator data relative to natural background radioactivity and fallout from prior nuclear weapon tests. Figures 2 and 3 show the current I sampling locations around the facility. Table A-1 in Appendix A describes the sampling l locations by distance along with the type (s) of samples collected at each sampling location.
Page 15 l
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REfY)RT Analysis In addition to specifying the media to be collected and the number of sampling locations, the ODCM also specifies the frequency of sample collection and the types and frequency of analyses to be performed. Also specified are analytical sensitivities (detection limits) and reporting levels. Table A-2 in Appendix A provides a synopsis of the sample types, number of sampling locations, collection frequencies, number of samples collected, types and frequencies of analyses, and number of samples analyzed. Table A-3 in Appendix A lists samples which were not collected or analyzed as per the requirements of the ODCM. Changes in sample collection and analysis are described in Appendix C. All samples analyzed meet the required analytical sensitivities.
Measurement of low radionuclide concentrations in environmental media requires special analysis techniques. Analytical laboratories use state-of-the-ar. @ oratory equipment designed to detect all three types of radiation emitted (alpha, beta, and gamma). This equipment must meet the analytical sensitivities required by the ODCM. Examples of the specialized laboratory equipment used are germanium detectors with multichannel analyzers for determining specific gamma-emitting radionuclides, liquid scintillation counters for detecting H-3, low level proportional counters for detecting gross alpha and beta radioactivity and alpha spectroscopy for determining specific transuranic isotopes.
Calibrations of the counting equipment are performed by using standards traceable to the National Institute of Standards and Technology (NIST). Computer hardware and software used in conjunction with the counting equipment perform calculations and provide data management. Analysis methods are described in Appendix H.
Data Review The analytical results are routinely reviewed by GPU Nuclear scientists to assure that sensitivities have been achieved and that the proper analyses have been performed.
Imestigations are conducted when action levels or USNRC reporting levels are reached or when anomalous values are discovered. This review process is discussed in more detail in Appendix D.
Tables 4 and 5 depict gross beta and gross alpha results, respectively. Table 6 lists the tritium concentrations from station GEO-5 and Table 7 lists tritium results from all 1998 monitoring wells. Table 8 provides a summary of radionuclide concentrations detected in the aquatic sediment samples for 1998. Statistical methods used to derive these tables along with other statistical conclusions are detailed in Appendix G. Quality control (QC) sample results were used mainly to verify the primary sample result or the first result in the case of a duplicate analysis. Therefore, the QC results were excluded from these tables and the main text of this report to avoid biasing the results.
f l Page 16
1 l
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REl%)RT Ouality Assurance Program A quality assurance (QA) program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs" (Ref 9) and as required by the Technical Specifications. GPU Nuclear maintains written policies, procedures, and records, that encompass all aspects of the REMP including sample collection, equipment calibration, laboratory analysis and data review.
The QA program is designed to identify possible deficiencies so that immediate corrective )
action can be taken. The program also provides assurance to the regulatory agencies and the public that the results are valid. The QA program for the measurement of radioactivity in environmental samples is implemented by:
1 m Auditing all REMP-related activities including analytical laboratories.
5 Requiring analytical laboratories to participate in a cross-check program (s).
I E Requiring analytical laboratories to split samples for separate analysis (recounts are I performed when samples cannot be split).
E Splitting samples, having the samples analyzed by independent laboratories, and then comparing the results for agreement.
m Reviewing QC results of the analytical laboratories including spike and blank sample results and duplicate analysis results.
The QA program and the results of the cross-check programs are outlined in Appendix E and I F, respectively.
The TLD readers are calibrated monthly against standard TLDs to within five percent of the standard TLD values. Also, each group of TLDs processed by a reader contains control TLDs that are used to correct for minor variations in the reader. The accuracy and variability of the results for the control TLDs are examined for each group of TLDs to assure the reader is '
functioning properly. In addition, each element (TLD) has an individual correction factor based on its response to a known exposure.
Other cross-checks, calibrations, and certifications used to assure the accuracy of the TLD program include:
a Semiannually, randomly selected TLDs are sent to an independent laboratory where they are irradiated to set doses unknown to GPU Nuclear. TLDs which meet the criteria specified by the National Voluntary Laboratory Accreditation Program (NVLAP) are used Page 17
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT for this test. The GPU Nuclear dosimetry laboratory processes the TLDs and the results are ermpared against established limits.
5 Every two years, each TLD is checked to ensure an appropriate correction factor is assigned to each element of the TLD.
5 Every two years, GPU Nuclear's dosimetry program is examined and NVLAP recertified by the NIST.
The environmental dosimeters were tested and qualified to the American National Standard Institutes (ANSI) publication N545-1975 and the USNRC Regulatory Guide 4.13 (Refs.10 and11).
Page 18
Figure 2 l b ,
9 5 LEGEND
'98 , '90 8Frun
, m , ,
0 20 40 totK15ts i
. o--- u trar==
RAYSTOWN BRANCH e--- . mars == swr 31.r==
l
'\ JUNIATA RIVER e---me vrcim== =cn.o amac ir ==
N. N _. _ -..-- =
\
, s u -.
l s R A s
\
Q l
p / B i 4
4ri-i W . "&'M
-s
- i
.W, i-i GM-4 ,
I '
,4 -. mm. -
C N i - iu a
p---.-, 'gi-.'
I i s g-*
1 I s l ' -e i c. .
7 I .
w- i0io D
?ici-. M N o-m i
i
', leaA i i L _._. ._. . _ . _ . _ - . _ . g_,
i E L l F'-i .F1-2 g f I I I
I I
K y = H .G l F
, If' ns-s o n-i L- u-oe-------------4---- - - - - -o- - - - - - - - 4
/ SNEC FAQUTY S1E ONRONMEM1Al, esOIETOIWIS STA11 TBS
/ assuw suump empus armet m Pass 19
Figure 3 SNEC Monitoring Wells Map me
+
~
'N
'N. ,
a
~~"
~
eeus stam
' _ LEGEND '
l suus a sumuses smessues ,
Ns i, .
ampuur um i c ==
+ m m wease , ,
s, N
+ sumust sat umaans 'sur
'" s aus-te IWGASI A .
D7 + es. . .
suunnt 4 t" we -
N 1 T 8 -
anweeamt
_ +~_. ~+
1,
~ ~ '~"
l_ , ._
M i
+ .
'l
'"'88' aus-t m .
senON NUCUWt M1fff I.mprr 10steen. MargIB couMM. m MONITOR WELL LOCATION PLAN
6 SCALE IN FET Pace 20
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REl%)RT DIRECT RADIATION MONITORING Radiation is a normal component of the environment resulting primarily from natural sources, such as cosmic radiation and naturally-occurring radionuclides, and to a lesser extent from manmade sources, such as fallout from prior nuclear weapon tests. The cessation of atmospheric nuclear weapon tests and the decay of fallout products have resulted in a gradual decrease in environmental radiation levels. Direct radiation monitoring measures ionizing radiation primarily from cosmic and terrestrial sources.
Gamma radiation exposure rates near SNEC were measured using thermoluminescent dosimeters (TLDs). There are 28 TLDs that surround the SNEC facility. Sixteen Indicator Stations, one per compass sector, are located on the SNEC outer perimeter fence. One station is located in the Penelec Line Department garage. There are nine Offsite Indicator Stations in various sectors within two miles of the site. There are also two Control Stations, each about 10 miles from the site. The indicator stations are used to detect any potential effect of SNEC Facility activities on environmental radiation levels.
Page 21
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING Reft)RT No relationship between the SNEC facility activities and offsite exposure rates were detected at any station. The 1998 quarterly exposure rates for the individual TLD stations are contained in Appendix 1.
Samole Collection and Analysis A thermoluminescent dosimeter (TLD) is composed of a crystal (phosphor) which absorbs and stores energy in traps when exposed to ionizing radiation. These traps are so stable that they do not decay appreciably over time. When heated, the crystal emits light proportional to the amount of radiation received, and the light is measured to determine the integrated exposure. This process is referred to as thermoluminescence. The reading process 'rezeros' (anneals) the TLD and prepares it for reuse. The TLDs in use for environmental monitoring at the SNEC facility are capable of accurately measuring exposures from a minimum of 1 mR (well below normal environmental exposures for the quarterly monitoring periods) to a maximum of 200,000 mR. I Each TLD station consists of 2 TLD badges, each of which has 4 phosphors or elements.
Since each TLD responds to radiation independently, this provides 8 independent detectors at each station. Of the 4 elements in GPU Nuclear's TLDs,3 are composed of calcium sulfate and I is composed of lithium borate. The calcium sulfate elements are shielded with a thin layer of lead making the response to different energies of gamma radiation more linear. The lead also shields the elements from beta radiation, making them sensitive to gamma radiation only. The lithium borate element is shielded differently to permit the detection of beta radiation as well as gamma. The combination of different phosphor materials, shielding, and multiple phosphors per badge permit quantification of both gamma and beta radiation. Only the calcium sulfate phosphors are used for environmental monitoring; however, the lithium borate elements can be used to j evaluate beta exposures or as a backup to the calcium sulfate elements should more data I I
be required.
Data from the TLDs were evaluated by obtaining the average of the usable element results at each station. All TLD exposure rate data presented in this repon were normalized to a standard month (std month) to adjust for variable field exposure periods.
A std month is 30.4 days. Several badges were used to quantify transit exposure during storage and handling of TLDs. Transit exposures were subtracted from gross field exposures to produce net field exposures.
Results In 1998, the average annual exposure rate for offsite indicator stations was 5.4 i 0.5 I mR/std month. Quarterly exposure rates ranged from 4.0 to 8.3 mR/std month. Offsite indicator station E2-1, located 0.25 mile from the CV, displayed the highest elevated j Page 22 l
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT exposures. An investigation revealed that the elevated results were due to residual waste from the coal-fired station formerly located adjacent to SNEC. The soil at station E2-1 consists of a mixture of coal slag and cinders, which emit a slightly elevated gamma from naturally occurring Th-232 and Ra-226, and thus adding to the TLD results.
The average annual exposure rate for the two control stations, those stations farther than 10 miles from SNEC, was 5.1 i 0.5 mR/std month. Quarterly exposure rates at the control stations ranged from 4.4 to 5.8 mR/std month. Table 2 depicts the average offsite indicator results with the average control results.
As expected, slightly elevated exposure rates were observed during the fourth quarter of 1998. The TLDs along the perimeter fence from sectors A through E showed increases from 23% to 49% from the previous quarter due to the large component removal project that occurred in October. Also, the storage of radioactive materials proximal to the subject TLD stations contributed to this increase.
No elevated exposure rates attributed to the SNEC facility activities were observed at any offsite station. The fourth quarter offsite and control stations showed a slight increase (14% and 10% respectively) on average from the previous quarter. The cause for this increase was probably related to a handling or processing problem. TLDs are sensitive and accurate mechanisms for measuring the low exposure rates characteristic of environmental levels. Effects of normal SNEC facility activities, however, are too small to be discernible outside the normal range of background radiation levels. Table 3 compares the highest site boundary exposure result to the allowable maximum exposure rate based on 40 CFR 190 (Ref.12).
The annual average gamma radiation exposure rate recorded from all offsite indicator TLD stations was 5.42 mR/std month. This equates to an annual exposure rate of 65 mR/yr. Exposure of this magnitude is consistent with the annual average dose a person receives from cosmic and terrestrial sources (Table 1, " Sources and Doses of Radiation").
Page 23
e I
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REFY)RT l
l I
TABLE 2 1998 SNEC TLD Summary Field Cycle: January 8,1998 to January 19,1999 l
mR/std month MEAN M1NIMUM MAX 1 MUM l Average Offsite Indicator Stations 5.42 3.96 @ El-17 8.34 @ E2-1 Average .
Control Stations 5.08 4.35 @ H10-1 5.84 @ G10-1 l l
1 TABLE 3 Highest Site Boundary Exposure Comparison Compared to an allowable maximum exposure m std 8.70 rate of 0.37 mR/hr. This equivalent to the 25 mR m ntti At Station annual limit specified by 40 CFR 190 adjusted by D1-4 the 67-hour recreational factor specified in Reg.
Guide 1.109 (shoreline exposure for maximum 0.0119 mR/Hr exposed teenager) (Ref.12).
l Page 24 ,
l
J998 RADIOLOGICAL ENVIRONMENTAL MONED) RING RELY)RT ATMOSPHERIC MONITORING A potential exposure pathway to humans is the inhalation of airborne radioactive materials. To monitor this exposure pathway, ambient air was sampled by a network of continuously operating samplers and then analyzed for radioactivity content. Based on the analytical results, no contribution to the general levels of airborne radioactivity was attributed to the SNEC facility during 1998.
The indicator air sampling stations are located in the three predominant wind sectors around the Containment Vessel (CV), the north sector (Al-2), the east sector (Dl-1), and the south sector (J1-3). The control air sampling station (G10-1),
which is 10 miles from the site, provided background airborne radioactivity data for comparison.
Page 25
I
- \
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l Samnie Collection and Analysis Mechanical air samplers were used to continuously draw air through glass fiber filters.
l To maintain a constant flow rate throughout the collection period, each sampler was equipped with a mass flow probe. This electronic device maintains a constant airflow across the filter paper. All air samplers were calibrated semiannually and maintained by instmmentation technicians.
The glass fiber filters were used to collect airborne particulate matter. The filters were collected weekly (biweekly during the 1" quarter) and analyzed for gross alpha and gross beta radioactivity. The filters were then combined quarterly by individual station ,
locations and analyzed for gamma-emitting radionuclides. l Air Results During 1998,177 air particulate samples (filters) were collected and analyzed for gross alpha and gross beta radioactivity. The particulate matter (dust particles) collected either weekly or biweekly on all indicator and control filters contained gross beta radioactivity above the minimum detectable concentration (MDC). The gross beta !
concentrations measured on the filters collected from indicator sites ranged from I 0.0060 i 0.0023 pCi/m' to 0.041 i 0.005 pCi/m' and averaged 0.0204 0.014 pCi/m'. The air particulate samples collected from the control location had gross beta concentrations, which ranged from 0.0048 t 0.0022'pCi/m' to 0.045 i 0.004 pCi/m' and averaged 0.0204 i 0.017 pCi/m'. The average results are listed in Table 4. !
As depicted in Figure 4, average weekly gross beta concentrations at indicator and control air monitoring locations were analogous and trended similarly throughout the monitoring period. The weekly gross beta concentrations and trends at individual air sampling sites also were similar. The 1998 data indicated that gross beta radioactivity l levels did not change as a result of SNEC operations. Additionally, the gross beta {
radioactivity associated with airborne particulates was due to naturally-occurrmg '
radionuclides.
i Air particulate gross alpha concentrations (detected above the MDC) at indicator stations ranged from 0.0008 i 0.0006 pCi/m' to 0.0064 0.0010 pCi/m' and j averaged 0.0023 0.0003 pCi/m'. Control samples averaged 0.0020 i 0.0019 !
pCi/m' and ranged from 0.0008 i 0.0005 pCi/m' to 0.0061 i 0.0010 pCi/m'. l l'
Average weekly gross alpha concentrations are depicted in Figure 5. Due to a I naturally-occurring alpha ingrowth that occurs in air particulate samples, variations in ,
concentrations were observed. As the time between sample collection and sample j analysis increased, so did the ingrowth of alpha resulting in higher sample activity. l Page 26
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT Inconsistent or late sample deliveries to the analytical laboratory promoted these variations of concentrations. Actual concentrations (whether the count rates were above, below, or equal to the blank count rates) were used to calculate weekly averages because approximately 13% (23 of 177) of the weekly results were below the MDC.
Using actual concentrations eliminates biases in the data and missing data points on graphs. As depicted in Figure 5, average weekly gross alpha concentrations at indicator and control stations remained relatively constant throughout the monitoring period. Generally, the trends of average gross alpha concentrations at indicator and control sites were similar. The average results are listed in Table 5.
The data obtained in 1998 indicated that gross alpha radioactivity levels did not change as a result of the SNEC facility. In addition, the gross alpha radioactivity measured on the particulate filters was caused by naturally-occurring radionuclides.
Gamma-emitting radionuclides related to the SNEC facility were not detected on any of the quarterly composites that were analyzed in 1998. As expected, all of the quarterly composite samples contained naturally-occurring beryllium-7 (Be-7). Concentrations detected on indicator samples were similar to those detected on control filters.
Page 27
. 1 1998 RAl)l0 LOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 4 1998 Average Gross Beta Concentrations in Airborne Particulates (pCi/m') <
Station Description Average + 2 std dev*
l A1-2 (1) North Sector 0.0203 0.012 D l-1 (I) East Sector 0.0203 0.014 J1-3 (1) South Sector 0.0206 i 0.014 G10-1 (C) New Granada 0.0204 0.018
- Averages and standard deviations are based on concentrations > . .
(1) = Indicator Station (C) = Control Station TABLE 5 j
, 1998 Average Gross Alpha Concentrations in Airborne Particulates (pCi/m') l Station Description _ Averare + 2 std Acy*
Al-2 (I) North Sector 0.0024 i 0.0022 Dl-1 (I) East Sector 0.0022 0.0018 J1-3 (I) South Sector 0.0022 0.0018 G10-1 (C) New Granada 0.0020 i 0.0020
- Averages and standard deviations are based on concentrations > MDC (I) = Indicator Station (C) = Control Station Page 28
1, 1I 1'
~
' " i s
e r\ O $
t l
a u
sA uI I f
9 Uo c tV' 8 Sc I
i t
r hT \ , i I a A P
i r
nr
\
I 5
A l i I n
Y I
i s I i
t n
o k[ I a
r 5
d 4 t e n I =
MT r
u e i
F g
c n
o h[
N 5 m %
C t
a i y 5 e ' 8 B R b ' 8 G
s s
o r
U k k
8 I 9
9 W0 1
8 s
5 4 5 5 4
0 0
0 0
3 0
0
_ _ 0 0
O 0 O
,<Ef l
- 71/21 M - 3/21 O
,w - 91/11 W % @
a o
b b g
es - 5/11 fE 0 i
- 22/01
'4 "
- 8/01 m - 42/9 j-- - - 01/9
,3_" m d - 72/8 M
3ll - 31/8
- 03/7 7 I
= 61/7
% -2/7 l O w g g - 81/6 s a g 2
- -- 1 12/S E
T:: -7'8
{ >
- 32/4 M
g > - 9/4 Q \ i - 62/3 Q - 21/3 g . --
- 21/2 l - 92/1 f :':
51/1
< o o A A A 9 P A reteM cibuC rep seirucociP
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REIY)RT GROUNDWATER MONITORING Groundwater monitoring is conducted to check for water leakage, if any, from the SNEC Containment Vessel. An investigation was performed to define the depth of the bedrock surface and the orientation of the bedrock groundwater flow pathways (Ref.14). The site is immediately underlain by a fill-layer composed of flyash, cinders and/or silt and sand-size sediment. This fill-layer is underlain by a layer of boulders in a silty clay matrix. The surface of the bedrock lies beneath this boulder layer at a depth between approximately 7.5 to 18 feet.
The results of this investigation indicate that the overburden groundwater occurs at a depth ranging from approximately 4 to 16 feet. Groundwater elevation contour maps of this data indicate that the groundwater within the overburden soil flows west toward the Raystown Branch of the Juniata River.
Groundwater movement within the bedrock beneath the site is predominately controlled by fractures in the bedrock.
There are two major fracture patterns; one trends northeast-southwest, and dips moderately toward the northwest. The second fracture pattern trends northwest-southeast, and dips steeply toward the southwest (Ref.14). Groundwater also Page 31
. l l
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT moves within the spaces (bedding planes) between the individual layers of the siltstone bedrock at Saxton. l In 1994, eight overburden groundwater wells were restored. Four of the wells are hydraulically downgradient of the containment vessel (GEO-3, GEO-6, GEO-7, GEO-8).
The other four wells (GEO-1, GEO-2, GEO-4, GEO-5) serve as background monitoring l points, since these wells are located hydraulically upgradient of the containment vessel.
Two bedrock wells (MW-1 and MW-2) were also monitored. As part of the analysis performed by the contracted hydrogeologic consultants (GEO Engineering), it was determined that bedrock monitoring wells should be installed at an angle in order to maximize the interception of fractures and bedding planes. The boreholes were drilled into I bedrock at an angle of approximately 25 degrees from vertical to accomplish this. Filling the annular space with a sand filter pack, a bentonite pellet seal and cement grout allows these wells to monitor only the significant fractures and bedding planes of the bedrock l ground water.
In May of 1998, three additional monitoring wells were drilled. Two bedrock wells (MW-3 and MW-4) were installed to determine if there was contamination in the vicinity of the former Radwaste Facility Building. This area was monitored by GEO-5, which in the past was the only well to show positive tritium levels. An additional overburden well (GEO-
- 10) was installed to supplement the existing monitoring wells to monitor for the possible migration of trace amounts of tritium or other contaminates.
In addition, two off-site (potable water) samples were collected. One site monitored the well water from the Pennelec Line Department garage located adjacent to the site. The other sample collected was from a resident in the borough of Saxton. The resident water sample was initially believed to be a well water, but it was later ascertained that this water was actually from the township water supply. All Saxton township residents get their water from one of two sources. Putts Hollow reservoir is the primary source, but during low water levels, the township switches to the Seton Plant water suppiv. which draws from !
the Juniata River upstream of the SNEC facility Neither of these s .:A detected any I radioactive contaminates. l Groundwater Results !
l Locations of the onsite groundwater stations sampled in 1998 are shown in Figure 3. The results from the analyses performed on these samples indicated no radioactive contamination from plant-related radionuclides, other then tritium. Of the 53 groundwater samples collected in 1998, eight samples contained H-3 ranging from 120 to 180 pCi/L, Page 32 l 1
l
. l l
l
l l
!998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
which is considered slightly above ambient concentrations. These are well below the USEPA's Primary Drinking Water Standard of 20,000 pCi/L. Tritium analysis requires a I minimum sensitivity of 200 pCi/L. Required sensitivities for Co-60, Cs-134, and Cs-137 (gamma emitting radionuclides) are 15 pCi/L.
As stated earlier, GEO-5 originally was the only well to show positive tritium levels. The Grst sample obtained from GEO-5 was collected and analyzed July of 1994. A "Less ,
Than" result for tritium was reported. Gamma analysis performed on this sample yielded l "Less Than" activities. The October 1994 sample reported 560 pCi/L tritium. A special collection was performed two weeks later to conGrm the positive tritium and a result of 310 pCi/L was obtained. Gamma analysis continued to show no reportable activity.
The following quarterly and special collections yielded some positive and some "Less Than" tritium activities. The highest activity of tritium (760 pCi/L) was observed October 1995. Since that time, no concentrations above 200 pCi/L were observed. Table 6 is a list of all tritium results that have been performed since the start of GEO-5 monitoring.
Upon review of these results, it appears that the activity in the GEO-5 area can be attributed to pockets of tritiated water trapped in fractures leading to the overburden groundwater. In order to assess the possibility of other contaminates in this area, GPU Nuclear contracted Haley & Aldrich, Inc. (formally GEO Engineering) to add sur .a nti monitoring wells in this location (Ref.15). These new wells showed int. ,ae- 'ritium activity slightly above the MDC. The new monitoring wells, like the former s mils, yielded "Less Then" activities for gamma analysis. Table 7 is a list of tritium results from all the monitoring wells sampled in 1998. The results indicate that no other contaminates are present in the groundwater.
Page 33
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 6 SX-GW-GEO-5 TRITIUM RESULTS l Activity 20 pCi/L DATE RESULTS 7/13/94 < 170 10/06/94 560 130 10/27/94 310 120 1/12/95 < 190 4/05/95 < 180 5/30/95 270 120 6/13/95 370 130 7/13/95 370 110 8/17/95 390 130 )
9/15/95 410 130 10/18/95 760 140 11/17/95 < 200 1/25/96 < 190 4/03/96 < 150 7/10/96 < 140 I
10/03/96 < 140 1/08/97 < 140 4/16/97 < 150 7/09/97 < 150 10/01/97 180 100 1/08/98 < 150 4/15/98 140 80 7/09/98 < 120 10/08/98 < 130 Page 34
!998 RAlbl0 LOGICAL. ENVIRONMENTAL MONITORING REl%)RT TABLE 7 1998 Tritium Results of Ground Water Analysis Activity i 2 o pCi/l Monitoring First Qtr Second Qtr Third Qtr Fourth Qtr Will 01/08/98 04/15/98 07/09/98 10/08/98 GEO1 < 150 120 i 80 < 120 150 i 80 GEO-2 < 150 < 120 < 120 < 120 GEO-3 < 150 < 120 < 120
- GEO-4 < 150 < 120 < 120
- GEO-5 < 150 140 t 80 < 120 < 130 GEO-6 < 150 < 120 < 120 < 120 GEO-7 < 150 < 120 < 120 < 120 GEO-8 < 150 < 120 < 120
- GEO 10 *
< 120** < 120 140 80 SX-GW-MW1 < 150 < 140 180 i 80
- SX-GW-MW2 < 150 < 140 < 120 < 120 SX-GW-MW3
- 150 80** < 120 150 i 80 SX-GW-MW4
- 140 80** < 120 < 120 SX-GW-El-1 < 150 < 120 < 120 < 120 SX-GW-G i-1 < 150 < 120 < 120 < 120 No sample collected
- Sampled on 05/28/98 Page 35
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REfY)RT BROAD LEAF VEGETATION MONITORING Radionuclides released into the atmosphere may deposit on vegetation. To assess the deposition, broad leaf vegetation were collected and analyzed for gamma-emitting isotopes.
Collection occurred during the growing season from two different sectors on site where the prevailing wind direction has been determined. Naturally-occurring Be-7 and K-40 were measured in all samples. No radionuclides attributable to SNEC operations were detected above the MDC.
Page 36
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT SURFACE WATER MONITORING The Juniata River surface water was monitored for radionuclides of potential SNEC origin. Two grab samples, one control and one indicator, were collected on a quarterly basis and analyzed for gamma emitting radionuclides and tritium. The indicator sample was collected at the discharge !
bulkhead leading into the river, while the control sample was collected upstream of the discharge.
No tritium or radionuclides attributed to SNEC operations were detected above the MDC.
i i
I l
i l
Page 37 L
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REEDRT AQU/JOIC SEDIMENT MONITORING Sediment samples were collected from on-site storm drains on a quarterly basis (Stations Al-1 and Cl-6). In addition, a sediment sample taken directly from the Juniata River at the discharge bulkhead (Al-4) as well as a control sediment sample (Q1-2) taken up river from the discharge, were also collected. The sediment is dried and then analyzed for gamma emitting radioisotopes.
Low concentrations of cesium-137 (Cs-137) were detected in both river sediments. These concentrations were attributed to fallout from prior nuclear weapon tests.
SNEC-related cesium-137 (Cs-137) was detected in all the sediments collected on site. The average activity was 1.4 pCi/g dried. Cs-137 is readily adsorbed by suspended particles and is concentrated in the storm drains.
Sediment results are listed in Table 8.
Page 38
s l
l 1
I 1998 RADIOLOGICAL ENVIRONMENTAL MONIK) RING REl%)RT TABLE 8 Quarterly Results of Sediment Analysis Activity i 2 o pCi/g dried Fint Qtr Second Qtr Third Qtr Fourth Qtr 01/08/98 04/I5/98 07/09/98 10/08/98 Cs-137 A1-1(1) 1.5 0.2 1.810.2 0.96 i 0.10 1.5 i 0.1 Cl-6(I) 2.0 0.2 1.5 i 0.1 0.58 i 0.06 1.110.1 A1-4(1) 0.047 i 0.013 0.081 i 0.015 0.13 0.2 0.1710.02 Ql-2(C) 0.17 t 0.04 0.027 i 0.010 0.051 1 0.027 0.036 1 0.015 Cs-134 Al-1(1) < 0.02 < 0.02 < 0.020 < 0.04 Cl-6(I) < 0.06 < 0.05 < 0.04 < 0.03 Al-4(1) < 0.011 < 0.012 < 0.015 < 0.016 Ql-2(C) < 0.04 < 0.009 < 0.03 < 0.016 Co-60 A1-1(1) < 0.03 < 0.03 < 0.02 < 0.05 Cl-6(1) < 0.07 < 0.07 < 0.05 < 0.03 Al-4(1) < 0.012 < 0.012 < 0.018 < 0.017 Ql-2(C) < 0.04 < 0.011 < 0.04 < 0.018 (1) = Indicator Station (C) = Control Station Page 39
1998 RADIOLOGICAL ENVIRONMENTAL MON 110 RING REPORT REFERENCES (1) Saxton Nuclear Experimental Corporation Facility, Offsite Dose Calculation Manual, 6575-PLN-4542.08.
(2) United States Environmental Protection Agency, Primary Drinking Water Standard, 40-CFR-141.
(3) 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, Issued June 1959, superseding Handbook 52).
(4) National Council on Radiation Protection and Measurements. Report No.
- 93. "lonizing Radiation Exposure of the Population of the United States."
1987.
(5) CRC Handbook. "Radioecology: Nuclear Energy and the Environment."
F. Ward Whicker and Vincent Schultz, Volume 1,1982.
(6) Saxton Nuclear Experimental Corporation, " Annual Operations Report" May 1999.
(7) 1990 Census Information provided by The Pennsylvania State Data Center.
(8) United States Nuclear Regulatory Commission Branch Technical Position.
"An Acceptable Radiological Environmental Monitoring Program."
Revision 1, November 1979.
(9) United States Nuclear Regulatory Commission. Regulatory Guide 4.15.
" Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment." Revision 1, February 1979.
Page 40
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT (10) American National Standards Institute, Inc, " Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry." ANSI N545-1975.
1' (11) United States Nuclear Regulatory Commission. Regulatory Guide 4.13.
" Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications." Revision 1, July 1977.
(12) United States Nuclear Regulatory Commission 40 CFR 190 Regulatory Guide 1.109.
(13) GEO Engineering " Phase I Report of Findings - Groundwater Investigation."
November 18, 1992. '
l (14) GEO Engineering " Summary of Field Work." June 7,1994.
(15) Haley and Aldrich " Summary of Field Work." July 24,1998.
l l
l t
I i
i Page 41
_a
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX A 1998 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Exceptiora in Sampling and Analysis Page Al l
1998 RADICLOGICAL ENVIRONMENTAL MONITORING REl%)RT I
TABLE A-1 Saxton Nuclear Experimental Corporation Facility Radiological Environmental Monitoring Program Description Station Sample Code Medium Descrintion N_ ole Al-1 Sediment Drain outfall outside Water rarely present perimeter fence Al-2 Air Particulate Westinghouse Yard Area Al-2 Water Containment Vessel Sump (Radiological) l Al-4 Surface Water Juniata River at the Sediment Westinghouse Weir bulkhead Al-5 TLD N sector, perimeter fence B1-4 Surface Water Drop weir in the Westinghouse Sediment Yard Area B1-6 TLD NNE sector, perimeter fence Cl-6 Sediment Drain outfall, NE corner of Water rarely present perimeter fence Cl-9 TLD NE sector, perimeter fence C2-1 TLD Weaver Ridge,0.8 mile from CV i
D1-1 Air Particulate Open Field ENE sector D1-4 TLD ENE sector, perimeter fence D2-1 TLD Weaver Bridge 1.3 miles from CV Page A2 1
I
e 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REl%)RT TABLE A-1 (Cont'd)
SNEC Radialagien! Environmental Monitoring Program Description Station Sample Code Medign Description N_o2 j El-1 Potable Penelec Line Shack Water El-7 TLD E sector, perimeter fence El-17 TLD Penelec Line Shack E2-1 TLD E sector,0.25 mile from CV i i
E3-1 TLD 3 miles East of CV in State j Gameland #67 )
l F1-2 TLD ESE sector, perimeter fence "
G1-1 TLD SE sector, private residence Potable in Saxton (Putts Hollow Reservoir Water or Seton Water Supply Plant)
G1-2 TLD SE sector, perimeter fence G1-6 Water Containment Vessel Pipe Tunnel (Radiological)
G2-1 TLD SE sector, closest private residence G10-1 Air Paniculate Reichley Microwave Tower Offsite Control Station G10-2 TLD New Granada Offsite Control Station H1-5 TLD SSE sector, perimeter fence H2-1 TLD Tussey Mt. High School Page A3
4 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1
TABLE A-1 (Cont'd)
SNEC Radiological Environmental Monitoring Program Description Station Sample Code Medium Description Note H10-1 TLD Wells Tannery Offsite Control Station J1-1 TLD Penelec Fence 100 feet from SE corner of West garage J1-3 Air Particulate Penelec Area S sector K1-5 TLD Saxton Borough Hall Ki-8 TLD SSW sector, perimeter fence L1-1 TLD SW sector, perimeter fence L2-1 TLD SW sector, Stonerstown,1 mile From CV j i
M1-6 TLD WSW sector, perimeter fence i
N1-4 TLD W sector, perimeter fence l P1-1 TLD WNW sector, perimeter fence Q1-2 Surface Water Old Station Discharge Upstream, control Sediment ,
Q1-3 TLD NW sector, perimeter fence l l
R1-1 TLD NNW sector, perimeter fence Page A4
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-1 (Cont'd)
SNEC Radiological Environmental Monitoring Program Description Station Sample Code Medium Descriptiom N_ote Geo1 Groundwater Monitoring well South of CV fenced area Geo 2 Groundwater Monitoring well West of CV fenced area l
Geo 3 Groundwater Monitoring well West of CV fenced area Geo 4 Groundwater Monitoring well East of CV fenced area Geo 5 Groundwater Monitoring well East of CV fenced area i
1 Geo 6 Groundwater Monitoring well North of CV i fenced area j
Geo 7 Groundwater Monitoring well East of CV l fenced area l Geo 8 Groundwater Monitoring well North of CV l fenced area Geo 9 Groundwater Piezometer inside of CV Fenced ;
Area l Geo 10 Groundwater Monitoring well Northeast of CV fenced area 1 MW1 Groundwater Northeast to Northwest diag anal well MW2 Groundwater Northwest to Southwest diagonal well MW3 Groundwater Monitoring well East of CV fenced area MW4 Groundwater Monitoring well East of CV fenced area Page A5
/
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
l r
TABLE A-2 i Synopsis of the Radiological Environmental Monitoring Program Conducted by GPUN Environmental Radioactivity Laboratory for Saxton Nuclear Experimental Corporation Facility Number of Numbee of Number of Sample Sampling Collection (s) Samples Type of Analysis Samples Tm_ Locations Freauency Couected Analysis Freauency Analyzed
- i Air Partx:ulate 4 Weekly 177 Gr-Beta Weekly / Biweekly 177 Biweekly Gr Alpha Weekly / Biweekly 177 Gamrna Quarterly 16 Aquatic Sediment 4 Quanerly 16 Gamma Quanerly 16 ;
i Broad Leaf 2 Annually 2 Gamrna Annually 2 Vegetation Groundwater 13 Quarterly $2 11 3 Quanerly $3 Gamma Quanerly $3 Sr 90 Quarterly 7 i
Potable Water 2 Quanerly 8 H3 Quarterly 8 Gamina Quarterly 8 Gr-Beta Quantly 8 D* Weters 28 Quarterly 8% Immersion Quarterly 8M*
(TLD) " Dose Surface hater 2 Quarterly 8 Gamma Quanerly 8 11 3 Quanerly 8 NOTES:
(1) This table represents results from the primary (I tsc) program. It does not include quality control (QC) results.
(2) The total number of analyses does not include duplicate analyses, recounts, or reanalyses. i (3) For the purposes of this table a dosimeter is considered to be a phosphor (clement). l (4) The sotal number of samples or elements (TLDs) used for data analysis. ,
($) Biweekly means once every two weeks. j l
Page A6 !
i
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
)
TABLE A-3 Sampling and Analysis Exceptions 1998* '
Period of Deviation Description of Deviation and Corrective Action December 31,1997 to Air Sample Station SX-AP-DI-1 had a mechanical malfunction in the i Febmary 12,1998 pump. No sample was obtained.
October 8,1998 No sample from SX-GW-MW-1, inaccessible due to the crane used for the large component removal project.
October 8,1998 No sample from SX-GW-GEO4, inaccessible due to the crane used for the large component removal project.
October 8,1998 No sample from SX-GW-GEO-3 due to dry weather conditions.
October 8,1998 No sample from SX-GW-GEO-8 due to dry weather corxiitions.
I 1
- The exceptions described in this table are those that are considered deviations from radiological environmental monitoring as required by the ODCM. Other sampling arx! I analysis deviations occurred during the year. They were not included in this table because the minimum number of samples were collected and analyzed. Reports describing all sampling and analysis exceptions are on file at GPUN Environmental Radioactivity ;
laboratory. .
Page A7
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
l APPENDIX B l
1998 Lower Limit of Detection (LLD)
Exceptions Page B1
- ll ! l S
a m
p l
e M
e d
i a
T A A h e
n a
l l
r y i
s t
e s i
s o w f e r
1 9
t h e R 9
8 e n e R A
o a t d u e h D e La n i
r A I O
t e o a e d Sn Na L c O t
i wl ey L Ey l G
o r t L Ctc i I
C n i c D Ra A l L l La E E
i m
i mre l
MR e N oWoN t
i i Ps u V I
t s
t s Rt l T R P
a o u Mh.
e c o i e s q A O i l B N g
e s f t Dt s e t h S f uW i
r h L M B f o t Fa e c E E ham i
2 u e h e d N i
B e a h T t l n Lep L A La F t l d c t f L de s L i
oia D Di el M n n e i
l Dd O N
a T ( d ut r o I
1 Lt i 0
bl Lo gnMe R I
e N Dme 1 e 9t G D -
)
e 9
7 R E
1 t l t Y
( h R)
P e T g
a r e q e
D u C 4
i r o
) e m d m e
n t
s
1998 RADIOLOGICAL ENVIRONMENTAL MONIR) RING RELY)RT APPENDIX C 1998 REMP Changes i
Page C1
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE C 1998 REMP Changes May,1998 Additions to the groundwater monitoring program have been made in 1998. I Due to the positive tritium levels in GEO-5 and investigation was made to determine if higher levels might be present deeper in the bedrock. Haley and Aldrich Engineering was contracted to add supplemental monitoring wells in this vicinity. Two bedrock wells were drilled in the vicinity of GEO-5. And j an overburden well was drilled northeast of the CV to monitor for the possible l migration of any contaminates. These wells are sampled on a quarterly basis for gamma and tritium analysis along with the other monitoring wells.
l These enhancements improve environmental assessment during the Decommissioning project.
1 Page C2
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT APPENDIX D 1998 Action Levels Page DI
1998 RAD 101.0GICAL ENVIRONMENTAL MONITORING REl%)RT Analytical results of environmental samples were routinely reviewed and evaluated by the GPU Nuclear Environmental Radioactivity Laboratory staff. The results were checked for LLD violations, anomalous values, USNRC reporting levels, main sample and quality control (QC) sample agreement (Appendix E), and action levels.
Established by GPU Nuclear, the action level is defined as that level of reactor-related radioactivity which when detected in environmental samples initiates an investigation and subsequent actions, as necessary. An action level is reached if either of the following two criteria is met:
E The radioactivity concentration at an indicator station reaches or exceeds those concentrations listed in Table D-1.
5 The radioactivity concentration at the indicator station reaches or exceeds 10 times the mean concentration for the control locations. (This criteria applies only to those media and analyses which are not listed in Table D-1.)
Action levels for gamma exposure rates measured by TLDs have also been established. For TLDs, an action level is reached if any of the following three criteria is met:
E The exposure rate at an indicator station not on the owner controlled area fence exceeds three times the mean of the control stations.
5 The exposure rate at an indicator station on the owner controlled area fence l exceeds 0.185mR/Hr (50% of the 40 CFR 190 limit of 25 mR/yr adjusted by a 1
67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> recreational factor).
5 The exposure rate at an indicator station not on the owner controlled area fence exceeds either two times the previous quarterly result or two times the historical average for the station.
If an action level is reached, an investigation is initiated which consists of some or all of the following actions:
E Examine the collection sheets for an indication of any equipment malfunctions, collection or delivery errors.
5 Examine the running tables (prior data) for trends.
E Review control station data.
Page D2
,,,,,q 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT E Review QC or duplicate sample data (if available).
m Recount and/or reanalyze the sample.
E Collect and analyze an additional sample.
The results of the investigation are then documented. As appropriate, site personnel are apprised of plant-related radioactivity that exceeds the GPU Nuclear action level. If it is concluded that the detected activity is related to SNEC operations and also exceeds the USNRC reporting limits as defined in the ODCM, a detailed report will be issued to the USNRC.
During 1998, there were no sample results that equaled or exceeded action level violations.
Page D3
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT TABLE D-1 SNEC REMP Analytical Required Sensitivities (LLD) and Reporting Levels Exposure / Pathways and/or Samo!c 1]Lqils Analysts Reauired LLD Reportine Level Air Paniculate pCi/m3 Gr Alpha 1.5 E-3 1.0E-1 (AP) Gr Beta 1.0E-2 1.0E0 Cs-134 5.0E-2 1.0El Cs-137 6.0E 2 2.0El Sr-90 1.0E-2 1.0E-1 Sediment / Soil pCi/g (dry) Cs 134 1.5 E-1 1.0E0 (SD/S) Cs-137 1.8E-1 5.0E0 Sr-90 5.0E-2 5.0E-1 Water pCi/L Gr Alpha 5.0E0 1.0E2 (SW/GW) Gr Beta 4.0E0 5.0El Tritium 2.0E3 2.0E4 Co-60 1.5El 3.0E2 Cs-134 1.5El 3.0El Cs-137 1.8El 5.0El g Sr-90 2.0E0 8.0E0 Vegetation pCi/g (wet) Cs-134 2.0E-2 1.0E0 (BR) Cs-137 2.0E-2 2.0E0 St-90 1.0E-1 1.0E 1 l
Page D4
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX E 1998 Quality Control Program Page El
. I 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT A quality assurance (QA) program is an essential part of any radiological environmental monitoring program (REMP). It provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of quality assurance must be evident in all phases of the monitoring program. These include, but are not limited to, sample collection, preservation and shipment, receipt of samples by the analysis laboratory, preparation and analysis of samples and data review and reporting. An effective QA program will allow for the identification of deficiencies in all monitoring processes so that appropriate investigative and corrective actions can be implemented.
The USNRC published Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment",
which defines an acceptable QA program (Ref. 9). The guidance contained in Regulatory Guide 4.15 has been adopted by GPU Nuclear. To meet the objectives of this position document, procedures and plans have been written and implemented.
In the laboratory, samples are typically analyzed one time. Therefore, laboratory personnel must be reasonably confident with the analytical results which are generated.
One means of achieving confidence in the results is through the analysis of quality control (QC) samples.
Three types of QC samples are routinely analyzed by the laboratories as part of the GPU Nuclear Three Mile Island Environmental Affairs REMP QA Program. They include intralaboratory split samples, cross-check program samples, and interlaboratory split samples. A discussion of each QC sample type is provided below.
Intralaboratory Solit SamDles Each laboratory is required to split at a minimum every twentieth sample and perform an analysis (or analyses) on each portion. The samples which can not be split (e.g., air particulate filters) are counted twice. The results of the two analyses are then checked by staff scientists for agreement using the criteria defined in procedure 6510-SUR-4523.03.
Agreement is considered acceptable if the coefficient of variation for the two values is eighty-five percent or less. Nonagreement of the sample concentrations may result in recounting or reanalyzing the sample (s) in question.
During 1996, all of the paired intralaboratory split sample results were found to agree.
Cross-check Program Samples Each laboratory analyzing environmental samples for GPU Nuclear participates in at least two separate cross-check programs. USDOE, USEPA, and Analytics supply either Page E2
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT water, air particulates, vegetation and soil samples. All samples are sent to the laboratories as unknowns. Participation in these programs provides an independent check on the ability of each laboratory to perform analyses on various kinds of samples containing detectable concentrations of radioactivity. The results submitted by the laboratories are compared to:
- 1) limits established by the USEPA, or 2) agreement criteria used by the NRC in their Configuratory Measurement Inspection Program. If the results are outside the established limits or agreement criteria, the laboratories are requested to perform an investigation and take corrective action as necessary.
The 1998 cross-check program results from each laboratory are listed in Appendix F.
Explanations are provided for those results which were not submitted and/or which were not within the established limits.
Interlaboratory Solit Samples The third type of QC sample is the interlaboratory split sample. These samples are the ones wWh are collected routinely for the REMP. After or during the collection process, the samp is thoroughly mixed (as necessary) to ensure that, as much as possible, the distributia of radioactivity in the sample is homogeneous. The sample is then split into two portions. One portion is sent to the primary (main) lab and the other portion is sent to the QC laboratory.
Analysis results from the QC laboratory are then compared to those from the primary laboratory. The agreement criteria is the same as that used for the intralaboratory split samples. Corrective action for disagreements may include recounting or reanalyzing the sample (s). There were no interlaboratory nonagreements during the entire year.
Page E3
1998 RAD 101.0GICAL ENVIRONMENT 4L MONITORING REPORT APPENDIX F 1998 Cross-Check Program Results Page F1 l
s,
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE F-1 1998 USEPA Cross Check Program Results EPA Control GPUN-ERL TBE Collection Linuts Results Results Date Media Nuclide (A) (B) (B)
Water Sr49 8.0
- 8.7 8.33
- 0.58 5.00
- 1.73 01/16/98 St 90 32 0 8.7 34.33
- 1.15 31 67
- 0.58 01/30/98 Water Alpha 30 5 2 13.2 21.00
- 2.65 33.00
- 2.56 Beta 3.9
- 8.7 7.23
- 0.32 5 60
- 0.90 Water 1131 104 9 18.2 103 33
- 5.77 110 00
- 0.00 02/06/98 (C) 104.9 18.2 106.67
- 5.77 (D) 03/13/98 Water H-3 2155 0
- 603.8 2166.67 57.74 1833.33 57.74 Water Alpha 54 4
- 23.6 46.67
- 2.08 50 00
- 1.73 i 04/21/98 Beta 94.7
- 17.3 87.33
- 11.02 102.00
- 6.56 l Co 60 50 0
- 8.7 50.00
- 1.00 52.33
- 1.53 l Sr49 60 8.7 4.67 0.58 4 67
- 1.15 Sr-90 18 0 2 8.7 17.33 2 2.31 21.67
- 1.15 Cs-134 22.0
- 8.7 20.00 1.00 21.00
- 1.00 Cs 137 10 0 8.7 11.00
- 1.00 11.67
- 0.58 0605/98 Water Co-60 12.0
- 8.7 13.00
- 0.00 13.00
- 1.00 Zn-65 104 0
- 17.3 105.67
- 7.51 111.67
- 2.52 Ba 133 40 0
- 8.7 40.00
- 2.00 35 00
- 2.65 Cs-134 31 0 2 8.7 29.00
- 1.73 32.33
- 0.58 Cs 137 35 0 2 8.7 34.33
- 1.15 37 6~ z 2.08 Water Sr49 210
- 8.7 21.67
- 2.31 21.00
- 1.00 07/17/98 Sr 90 ?.0 8.7 6.67 0.58 6.33
- 0.58 Alpha 72
- 8.7 6.43
- 0.12 5.43
- 0.64 07/24/98 Water Beta 12.8 = 8.7 14.00
- 0.00 14.67
- 2.08 08/07/98 Water H-3 17996
- 3122.9 19000.00 0.00 16000 00
- 0.00 Water 1 131 6.1 3.5 7.00
- 0.53 5 93
- 0.55 09/11/98 (C) 6.I
- 3.5 6.60
- 0.26 (D)
Water Alpha 49.9 2 21.7 49.33
- 0.58 45.67
- 1.15 10/21/97 Beta 143.4
- 37.3 140.00
- 0 00 136 67
- 5.77 Co-60 10 0 -
8.7 12.00
- 2.65 10 67
- 0.58 Sr49 36 0 8.7 42.33
- 2.52 36 00
- 1.00 Sr-90 22.0
- 8.7 24.33
- 2.31 21.67
- 2.08 Cs-134 41.0
- 8.7 40.67
- 0.58 41.33 0.58 Cs-137 34 0
- 8.7 36.33 0.58 36 00
- 1.00 Water Alpha 14.7 z 8.7 14.33 3.21 19.67 : 1.53 10/31/97 Beta 48.9
- 8.7 47.67
- 7.23 50 67 2 3.51 Page F2
1998 RADIOLOGICAL ENVIRONAfENTAL of0NITORING REPORT TABLE F-1 1998 USEPA Cross Check Program Results EPA Control GPUN-ERL TBE Collection Limits Results Results Date Media Nuclide (A) (B) (B)
I1/6/98 Water Co-60 38.0 8.7 38.00 1.00 39.67
- 2.52 Zn45 131.0
- 22.6 146.67 5.77 140.67
- 10.97 Ba-133 56.0
- 10.4 59.67
- 1.53 46.33
- 2.52 Cs-134 105.0
- 8.7 103.00
- 6.08 103.00
- 2.00 Cs-137 111.0
- 10.4 116.67
- 5.77 115.33
- 1.53 A. The EPA Control Limit is the known concentration
- 3 sigma for three determinations. The units are pCi/L.
B. The GPUN-ERL and TBE results are the average of three determinations
- one standard deviation. The units are pCi/L.
C. The analysis was performed by first concentrating I-131 on a resin. The resin was then counted by gamma spectroscopy.
D. The analysis was performed by gamma spectroscopy. The 1-131 in the sample was not concentrated prior to counting.
Criteria are listed in EPA 600/4-81-(X)4.
Page F3
j ifl l1 lll l ! i 1 i l' T
N F G E e M e S
E ESE S E ES S OaSE S E ES ESE S E ES ESE SE S S OteE E EEE E E ES EE S S S S S S S S SES TE S S E
Y YYYY N Ne YYY YYYYYYY NN F 3S E e YY YYYYY E Y YYYiYYY R e e G S S A
x
. O I 2 0 4 0 3 3 6 7 9 2 1 1 5 2 5 5 6 2 4 7 7 0 9 7 0 5 6 9 5 2 a T 1 3332 3 5 7 3 3 4 4 9 02 25 3 3 2 35 6 8 333 1 1 MAR 2 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 2 1 1 1 2 7 6 4 3 3 96 7 3 1 1 1 1 1 1 O
0 5 5 4 3 aT I 1 7 6 6 7 7 7 9 1 6 2 2 4 7 7 7 7 6 6 8 8 8 1 5 0 0 0 7 5
o6 9 6 6 3 9 t 7 6 5 4 4 2 1 6 5 0 6 4 9 3 7 4 6 8 7 35 4 MAR 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T
R O 6 8 0 0 2 7 O I 0 3 9 0 9 9 4 3 0 2 2 51 933 086 0 4 8 3 2 1 9 1 3 6 6 6 0 4 0 2 0 6 T 91 72 2 6 7 6 0 2 6 9 3 0 5 1 1 8 6 4 7 P A 1 9 9 1 9 9 9 8 0 8 2 0 1 1 2 9 2 9 0 9 0 9 0 0 1
1 5 6 3 5 9 8 E t s R 1 0 0 1 0 2 0 0 0 0 1 0 1 1 1 1 4 1 1 0 1 0 1 0 1 0 1 1 1 I 0 0 R l G u N s Y I e T N
R O
R I A ) 3 6 6 2 0 7 0 9 4 3 8 5 0 0 5 3 2 1 2 3 1 4 2 0 0 3 9 2 2 8 1 6 6 1 7 5 4 1 T E( 0 0 8 0 0 5 4 01 0 0 6 5 8 T m R 0 7 8 7 39 1 3 4 0 0 0 0 0 0 1
2 2 1 5 7 0 5 5 2 2 8 5 8 5 6 0 4 0 0 2 1 9 03 5 2 1 0 I E 0 0 0 0 1 0 0 0 0 0 0 1 0 0 0 0 0 9 0 0 0 0 2 2 0 0 0 7 42 N a r L C 1 0 0 6 0
f g EMN A U L
o E r O A P D T
N E k UD
)
9 0 0 0 04 60 0 0 0 0 2 0 68 0 3 8 0 0 0 0 5 3 0 0 5 0 0 5 E 5 3 03 91 0 3 0 9 60 1
5 4 2 ce L A 6
0 2 11 1
1 9
0 7 8 0 6 4 7 6 4 9 4 0 0 1 5 3 3 6 7 0 0 0 7
6 1 0 1 7 5 7 5 0 5 0 6 01 7 00 4 F
M F-h A C V ( 0 8 I 9 9 1 1 1
1 1 5 0 0 2 1 0 0 0 2 9 3 2 1 5 3 31 31 6 4 1
1 2 0 8 07 0 1
1 7 95 e
N 1 1 1 1
3 3 1 7 3 g O
R E
L C a P
I V B ss Y N A o T E T r N L C IA T
) 8 0 0 0 0 0 B 0 0 0 0 0 0 0 0 0 0 6 6 0 0 4 4 02 06 0 0 0 0 0 0 0
0 0 0 0 0 0 00 0
0 00 0 00 0 0
0 00 00 00 0 0 08 00 0 0 A L R ( 0 9 0 0 0 0 1 0 0 1 3 0 0 0 1 0 0 35 0 00 00 00 3 0 C
I E 0 0 1 1 2 3 0 0 0 0 0 1 0 0 0 5 0 0 4 4 1 7 4 4 0 0 2 2 8 0 03 C
G O
M N L E U P U
O I E G D O A D E )
U D 76 00 00 00 00 00 0 0 0 0 0 0 0 6 6 0 0 00 3 23 63 6 0 0 R L & 0 7 0 00 08 70 0 0 0 0 3 0 0 0 0 0 0 0 0 00 0 00 00 0 70 7 0 0 00 0 0 0 0 0 0 0 8 8 A 1 3 9 3 0 0 00 2 0 0 0 0 0 0 1 2 1 0 505 0 8 0 1 7 0 0
9 9 9 VA (
0 7 I 1 1 2 1 1 5 0 0 1 2 0 0 0 1 1 7 8 5 3 3 7 9 2 1 2 3 6 1
1 2 1 1 9 8 0 1 7 1 0 3
1 9 1
e 1 4
id 24 41 7 0 4 7 a 4 8 9 5 t 1
7 3 04 32 9 09 4 1 4 7 8 9 3- 8 4 t 4 4 0 l 5- 41 3 3 - hp eta -52 3 3 2 0 4 8 a 2 32 Na 2- 6 3 40 232 39 0 u2 u - 9r- 32- N 1
c -
r- 2 1 1 o o -s s - 1 n - P- >S S UUU u o -
s K Pu -P uS r e- l - -
N m
AC CC CC A D MP t A C s K uS m
P U U U- AC mmc C r n ia l te i o
i l t d F i a
e o t e
M A r i S g e
V n 8 i
o 9 8 8 t
te 9 9 9 c a 9 9 le D l1/
l 1
/
1
/
o 3 e l
/
1
/
C 3 3 llll
jl l 1 llj 4 i jI T
N H I 3 K K K L E e e e e e e e M S E OoEY OoS t
N eeNY ES SESESESESE SE S ES t
t S S E SE ESE SE ESE S S S NE OoS OoOoOto SE S E Oo t t t E
E Y NN e YYEYYYYYYY E EY7YY YY YY N Y NNNNNN e e e e Y Y NN e R e e e e e e G S S S S S S S A
. O xa T I 2 0 5 2 5
2 5 1 1 0 0 4 5 6 6 2 9 8 8 2 7 5 7 2 0 4 3 3 2 l 5 2 3 6 3 6 81 2 2 35 4 2 4 5 33 15 6 41 4 4 4 9 9 6 3 35 6 MAR I 1 1 1 1 1 1 I 1 1 1 1 1 2 1 1 1 1 I 1 I 1 2 3 1 1 3
. O 2 0 0 2 2 3 9 0 6 0 5 0 0 7 ni T I 3 5 3 0 2 6 4 6 1 1 3 4 0 3 8 0 7 8 8 2 5 $. 6 8 7 8 7 8 8 4 . 7 7 5 7 7 7 7 6 6 8 8 8 8 7 6 M A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 R
T R O 2 0 2 9 6 0 9 5 0 0 6 1 1 3 0 51 9 0 6 6 3 8 1 2 3 9 8 2 8 5 9 O I T 4 5 5 2 5 0 9 0 9 3 1 6 6 7 8 7 3 2 4 4 6 9 6 0 7 4 1 7 P A 1 2 1 5 0 0 0 1 9 0 2 1 1 1 9 0 9 0 9 0 0 0 4 8 7 8 7 0 1 4 E s R 1 1 1 I 1 1 1 1 0 1 1 1 1 1 0 1 0 1 0 1 1 1 1 0 0 0 0 1 1 0 R l t
G u s Y N
I e T R N O R I A ) 0 0 5 0 0 1 0 2 0 0 0 0 5 0 0 0 0 0 0 6 6 1 2 7 7 7 9 2 3 6 8 0 0 0 0 0 5 6 0 0 8 3 6 7 10 0 0 5 0 01 0 0 0 0 0 0 3 2
0 0 00 5 1 T T E( 0 2 7 9 0 0 5 9 0 0 1 0 0 0 0 5 0 0 4 0 0 5 0 0 0 0 I m R 0 1 1 2 0 01 6 1 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 8 3 0
E 3 1 N a L C 1
O r MN M g E U L o r
E O
A D T P E 0 0 N k UD
)
6 0 0 0 0 0 0 0 0 0 6 0 7 6 6 1 0 0 6 70 05 602 60 2 09 0 0 0 0 0 0 0 0 00 0 5 E2 ce L A 22 063 A C 0
0 8 6 2 0 1
2 0 0 3 00 52 5 65 934 933 0 8 7 0
8 5 1
1 4 6 1 9 4 4 8 2 6 1 2 6
2 3
5 0 4 4 0 6 3 F
M N
F- h V (
1 1
4 2 0 4 2 1 2 1
2 5 2 1 0 0 0 0 9 22 1 2 4 0 0 8 1 0 0 0 5 9 3 1 9 3 e g
a OE RL C I
P V B s s Y NAo T N
ETr I 0 0 0 L
A C A T B(
) 0 0 0 0 1 0 0
0 0 00 0
0 0 0
0 0 0 00 00 0 0 0 0 032 0 0 0 0 0 0 6 6 9 0 0 0 0 0 0 0 0 0 0 0 5 0 0 0 0 0 5 4 0 0 6 0 2 2 9 0 0 0 0 0 0 2 3 0 0
3 0
0 0 0 0 0 0 0 0
R 0 0 C
I L E C
0 2 5 3 0 0 1 2 3 6 0 0 0 0 0 0 1 3 0 0 0 0 0 2 0 0 0 0 03 1
7 G M N O
L E U P G
U O
I E D O ) 0 0 0 A E UD 0 0 0 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 0 R D L & 4 07 0
0 00 0
0 0 0
0 0 00 06 52 175 3 0 0 0 0 0 0 0 0 0 6 6 4 449 0 0 0 0 0 0 8 4 0 5 3 20 7 0 0 4 4 0 0 0 0 0 0 2 0
1 2
0 2
4 00 0 0 0
8 8 A A 1 3 1 0 0 4 3 0 0 0 0 9 1 2 5 0 0 3 1 0 0 0 0 05 9 9 V (
1 5 3 5 2 2 2 2 1 0 3 1
9 1
9 1 1 9
1 e 1 7 4 8 9 1 7
d 4 0 3 5 s hp ae 0 4 8 t a 4 0 37 ha a 5 43 839 25 0 4 8 t a 0 0 lcu 24 i
1 5 t -3 5-n32 32 -9 r-3-23-2 N. 2 1 p e t n - 2 2 1 9- 32 3
2- N.
3 1
4 9-o -
N A C mo C F s e lA DH MNPuS UUU AmC C- s J A D MNbbS r -
S U U U C s KS r r
r e ai e l t
l d t a
i F
e c
e S
M W i r
A n 8 8 8 o 9 9 9 it te 9 9 9 c a e 1 1 1 I
D 1
/ /
1
/
1 Io 3
/
9
/ 7 C 9 l lIlf ilIt l llliI lfl l ll ll l ll il l llll
=
e b le f l
l b i s
i af . t i n 3l w
s t
poi eld e uth s
t lp e c cMg a - rBf72 o e qr s
T N M m
a toer E nny00 a e c is49 E
M S S S S S S S S e s
y nh ysi na1 1 s s t t
l E E E E E E E E S S S S S E E E E E E F E E OtoES SS S S S S E E iv i )i t
hi ent a*a E g e E
R Y YYYY YYY Y YYYY YYYY NN YYYe ica 1we t
qo goe re5 r0 w e
e 6 u G S h Bt a A ig 5 r iahmohrre D. t d n v d1a l h
- e aL r s rofuts
. O .f o I h af I
e2M x I 0 2 6 0 2 4 9 3 9 0 6 3 2 4 5 5 9 0 0 6 2 ed (de nt d en oq u4 0. E a T 7 6 4 4 4 9 3 3 4 2 2 5 3 5 2 2 3 5 4 2 4 d e r e1 e M AR 2 1 1 1 1 7 1 1 1 1 i s lcu u as e r h 1 1 1 1 1 1 1 1 1 1 1 us latvl eht as t 1
- t s
nr e d s e us ow0 u s teel h es hc ka r r pci6 O
t u T I 8 4 9 0 9 6 8 0 6 4 6 8 7 6 6 5 5 0 0 4 7 8 8 4 6 5 8 7 8 7 1 5 0 8 0 5 0 0 7 8 8 6 ae eB r
gla mas n sh a ey 1 es l
v M AR 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o . i. igl i t an e r ue f n s o ei r iowawl e a T ni t h Te oS ee r s h v R O ioseg t . hl . rAu g d s et 2 2 0 1 0 9 4 7 0 2 0 7 519 0 4 2 2 4 a y e r d ot sio a ).
1 O I 1 L )rd eop u tr i hs 'q T 0 5 5 5 3 3 I 5 2 3 4 5 0 4 0 6 2 6 2 nid P A 2 8 0 0 1 8 9 9 1 0 0 1 9 9 0 0 0 71 9 9 9 img t s a E s R 1 0 1 1 1 0 0 0 1 1 1 1 0 0 1 1 1 0 0 0 0 r n teir u
sBd0 er R t l e u ede ht m e r0 s2 uf n9 G u dd l d a
n isbis1 l r o o ut e s Y i s nid y* n- an N
I e T d a o )g a an0 o enl R N ivin i
O R I A ) 0 6 7 0 00 00 00 70 70 00 0 0 0 0 0 0 0 0 0 0 0 0 0 dm i
l s1d u qe a 6. (n m zh3 wea T E( 0 00 0 2 0 8 0 02 07 00 000000 04 4 8 3 5 8 c nBnt 1 rD 1
T R 0 0 0 0 0 I. 0 0 0 inan t o(
I m E 0 0 1 0 2 2 0 0 04 0 1 1 2 6 6 1 0 0 0 0 0 0 hte co i 6 eb r v euang.
el N a L C n f o1 lusl O r MN f oe e )
- pu v aigin M g E U tyb 8 9 2. d, acLri rn 5 e e o a L o E O
r D inw
. a 9(iBMew 1
nl u d t
r A
T P s r rhe e ct s t a J
usi n
- e aah r t eda e
.ht r r t N E )
0 0 0 0 0 0 0 0 h u n u I e n a ght uw ei k UD 6 0 0 0 0 0 0 0 00 00 0 0 0 0 0 00 04 01 f i 0 0 0 6 E 2 c L A 3 00 0 0 2 0 5 0 00 0 2 5 r a m fot h f4i la e 1 1 1 3 7 0 0 3 7 6 2 4 0 9 8 202 4 1 1 5 5 0 ia gpml e ed o4 wvl b F M e A C 2 0 9 6 0 3 0 9 0 t ns0 a md 2La e N Fh V (
1 2 3 4 6 1
4 5 3 1 0 4 3 1 1 1 1 2 0 0 1 r
foim s d a
Mp t
e g
a O
R EC L Bw qo sa t e d(
ed ut ge r a s
e0 a n 49 rh e=E e c
c a
P I
V B ss Y ladD t e Lq20 u0 ah e ye rlei e gt e t n
N Ao T N
tot d psoi r .s Mr Es le eb wb e E Tr I ne y hte wata wtat s pn a v
C A 0 0 0 00 JO 0 0 00 0 0 0 0 00 0 00 0 0 0 0 0 . a rl mie eh L T
)
B 0 0 0 0 M5 06 0 30 000 0 000 00 00 0 00 0 0 1 2 d e
ne na si oixycelmd s c A R ( 8 6 0 0 0 0 1
0 0 1 2 6 1 1 i 1 ioh t a t s ol C
I L E C
0 0 3 4 5 5 0 5 5 2 0 0 3 0 0 0 1 1 0 0 u n
6 t fl ta o a n
dlyr e a pnngo a a reu e si t npai awh G M N h c
ge eri g t imef aa 1
4 i le5 t
E U U O a var uo b r o 2 wb 9 L P e r oqe uAs - t a1 r s t O G f sh I E f o
s
) et te hh be 08 . s isMotp1 n As ef n
c o D O 0 io n wf t t owi t o1 o ri c cfoLantioa A E UD 0
)
0 00 00 00 0 0 0 0 0 0 00 00 00
(
e4 D 0 00 00 000 0 gmes tai edMi t
0 0 0 R L & 0 0 0 0 0 26 40 00 0 4 0 0 02 0 0 00 0 7 0 7 a .
in nsnqs 1 ue l sl pees ht ar 8 A A 2 8 5 0 0 0 0 1 5 5 4 5 9 r oimue o i 9
9 8
9 V (
1 1
2 1
4 2 0 3 8 5 5 1
1 5 5 6 8 1 9 0 4 3 3 1
1 1 1 0 0 0 ma r e e mi oBea h g
totar s s
a sh e t wde st t tal t lt eLzoir o 1 9 e e sniof u . a it h c p 1
dhi e ft m r osdwDMs r o o rs ate) t e
.Eleeh d i re e pi t
a oef 8 s ic r e) t m m w,a w lprod yeym1 r
o r si9 rl i n 19- )g D sa u8) 6 e
e r
r e4d aau =nn n q .e)0L o (g qs ae - Ju 2i B ngD 'qL If qB s 1 4 1 d 4 46 0 73 0 3 8 39 0 4 0 7 5 a 5
4 8 9 h ae 5- 3 4 8 t a fd 2 23 9 0 oraI i
2- 2 2 3 3 3 t l - 1 4 2 9 1 t 2 2 -N 1 t r i c81 an r . Bo 5i a mmc C- K- PuP uS AmC o s- e lp c o -
n - - r-u s r B - - nd f q e ef N AC CFA MPu Pu S UUU an e a t n 2 s m0io5b mts gri eo B.hsDd ee ra te tyd r ded*he o O r2 Wg ar6 0.a t 2.
9 hh t 8 t a1 t t e s s v awis a r n te co6 s p ar 7 iw0* s (s 00 a e a
s e
n ie iyno eie2le ud r(b 6o 0. 7 1 h). lac ut a ia d
e t
t o
i a t r
e a
ut naf vatr ie 'q ws we lai st- r nr.ulhp ut 2(
qd( e s a e at 1 t
q vi d M ge e W Le Mcl aeM wer uBLadn1evcml cos2 Be La r e8 t icf u
e h n si h
V n s s r EuVaEir s a n4Mie0 z 2. fo h EUUtsE l yc2Edi41 s - ns n w n OPPiOan n . At
- Me h a eO*e a,de o 8 9
8 9 DGGuDa .
. 2 pC 77 ml l
i it c t e 9 9 e ee e e er .
eh4 me4 e c D D D D D A gDi9 t
a e w1 asD1 ( thn u 1 1 l
l D 1
/ /
1 o 9
/
9
/
C . . . . . . .
ABCDEF G 1 1
s f f
e - _
ht . s s h t
- n _
shh ut s ; i Ur outg eya a in- s e e c. d w e ioh ht t d mye w r es v
s aeh tn csen r e rs wo d , -
nI ; s.
e n
r t
nt c hi t t r i l aM .t l
- e, e r n c g c edt ht e u s aa ah r e s s lmEn s e .
ts i e5 ee Lo Kih s et r t d th yno re r p
o iwf l 5 r 5 ba h nh -
e feWi h - i l2, db nl e t t ehteth eT a t d d t s at r aE sF d r ea t pl enr t t
ora.o ne .e l 3 t
ow ut i
mttei 0i t i s
h ics t t
a s
e fo t
r to uc m i d 'q i u de ferdhl eTC h ql u
s 2bmsa r t t
im os olat aeB s t r mt r i ae r r u ve es i .
ph e su icsi r
t5 a ps rpee ei odT et s l
l o
et oh Ts0 s gs r
se r e h cd . a1f pk r et a ae eit ah n t r e labe l@t
- a o; r
e pr
_ r t
n o
iLr o e s od o t n pb mh a ah a wTp c oR Kuie t ayoit gt cf e ot . o e _
taE r een ra ush u i gt lcs r t ne v r l u e ht ipre8)ea s v bh o e hto li eb d ee sr ee2n3epr wp 6
e is ui e Demeie f o
d hc laT d amolug wd e . urh t r 2 . l ph gU s a e a isl s oleca t...
y w o e..amlah o ra hh e
ei d kt a I mo r t y
lvb ao k
s lnl Oeb myugms
. r eAv fiyo t
f r4 a n
gl ps e .
t fo r r e ed lal n
a me apt r e l,e u eya ma m~ n r e3 n u pr e s cd c r v s s o e di mi^ x a ub2i - sr e a n h e a o e T h ig r
lbam pL )
nr apm a
id . tpmUf n o u n (s eb e r rle wid s e f tr th n o o es t
ui n d
ht e -_
R d e et ae5d s e h2 e s a,e dip n a is s tye ua mi h t _
cq eh h lyu y d _
O e cB t t e su1- ueh n P
ht A 8 lpf a o nh a t eb s c ch e e c a e nb inDsl e n a a .
E d e to2 nht a
e t rSi a h a r
u ut c nd a al l ei t
is1 t l
.h a ta8 a 9 R s N02 .s a? s - te d tcfir t r orh c os o nde rw n1 e de an d 9 u
1 a e( a n e hw md i a At s 7. d io c -
G c e
een ue apm3 r
wlue ryb d
ur s url a3d l eCe 9 o
u hf e0l ieit ir1 o 9 N v at r gge )i n
ahi 3 i 7iq f t oyd d ts9 I a 4 vgr aa s ainh st d nCr t T l
- 4. la ood a i h1 R d s i h b t dt an a or O y d nLnie nwuguiur rt f nbTef tani0 o r a s re nr isr s aMui l yi sg a nia(h s x e a d f ht ae T m gEih tpuozt en e al t h el a o a 3l r e gs ed r e f y in e I nTpse c lycd gugCnil oe oco. eaer benr a rr ms n:
s wie n s s ov c u ei at a N d e
nh r t a olotnreiTe s uar a, nht o
O i l
c at yihhd e chc uw
- r esi r uhl legrb i oe ir t o Whi u a f a r ecle u h t h1 p af _
M n h t
t t t lore mcl t s tne upc . ty- r o odt e xuTo s e f s t qsl au d u a
aBwo t
L e i e el wlai da tebd m g5 f a fed sh fro )g.L A
T s
e r a n2 r t
d eciet e rowd e q E I
M s8 ) hs a 1 lvh e
D lec b d topot s
et mi1 tsb- ieAl e v i y pd sBo f w.lmt e 0 o h ek N . and ce cye nh S i t
m, o yeea ui2 5 u Tn t 7 e r to r sh3 g E tpsi r a arecr (iq s 5
e a e s ecs rc0 n la1 l
)d
.i F _
r rh c fod e iutr l t
M 5
- c una wop u0 0. si v1 ea me 2 e
AcDt E n b nl e 9 at he o yk ao s d2 g N e sl uz u
F o c r s epn*cr e 9 a mhh et K Pa _
ki o is 1 d O e ul
- e e l
r o e 1 nhh e ahc ron a pe ee3 or ipe vt - f rL t t mrb6 p a 2 o R f e ei qb mtoWt ebefi ih l t oa s
e a l
u*hw 8 s -
I V
L R wBl l e e ah l pe c s we9 f
c3 r ht v 9 le E 7,2ihd et le4 ht l tehdn isLn( u L"l e 1
(
i t
N 2 swtn a e s n t
i et oaHMssla t t e m io ;c nis w uf u sMaa n ec E s ont )
i t u r c ht n
b(ie t
a as h ac t
- c. de e i d *. .E s eh voF a r aE c lai d inp o r e e e ul L p9 4 sdtseeawiel u s i cc aci rattad d 40k e
ae h nt L e.
pmgeMl bDinil i
e1 t f t u A d e c c r pr pa1 i
s sw l
m C z c1 AsAs Pl ge g npas eh bi r c g e n(- o aE b lt . at irt s ro I
G ly a aa eel r ygyrf erhetp a u1 s q gu l if d d a
n ewQwh r nh w A pie re reiwt l
a e rBies r ns tae ehe cc e ci t O a wioLd s o re . eb voend le6 u e a p L
O s
e 7 aMad lu e cb gf c t
rE Lns n at t h let h e t
r eh e nia m Aws t
b0 a ish d o icel lp pisTy r v I
m 8. a n n
iMd a rse caKt mo ama pr yhh igo r
wt rleb ndi .
od e D a s
4 e PM55Eee eal e mcDt e ulei g etrioa a e 5. l c1 ad c ne t
is e A y Ae t
h lu pW roc a .n h met tp4 asa az ey h re R n lyah lue8 e f v sde esi s es 8
a e
QhEth t a a m.f s i. al es t oos c9 c il v wrl a et Ana ow sl i ins et e .. mh a0 9 k e Luuwyuls lul r i t
t uly r t ht, e tnt f h u c s g, y ieVL ves n;o n oiuta no oe i
9 l a a lt n
l ou n l
lq t a eri nl 1 u s
ME v F ;. ci lau t evn s e r adebdnis ps to e st si a eX c - -
B d . ..r reoh ct eed rP m rop i ael t ic A e i)gla d gem i
x htee t rl e . c fa nl a u v e r aci eA p
s e
9%896 1
32223 963 i r ob a ge n ea s dn D. i 3d n
ne s e. pk r n l
iav pb e o r e m Q toptpaih s t I waet t
r m
a m
e t cl e a r : d )rlul qw dl u aCir a n abo n f a rl s e el oo frf ts r e it r cn ah e vi7 k ishr lyTf o tw i dt s e
v e lsu W" ao tc i e ouTd w gM i n t ffht voteou ane*e f
a ei ta e* h m d en nmr i
f w r eb t
a s e wd er e s wwhot 1 h 9 t nai
- s. ne o u isi d s 5 r a os or i n ny(h sk iq l l e
z .i 5 ab ne sh a ceeci wknsleos kitfrli t mlyal t a bl o a
c ck n Lorkr ap u he upe uw rh - r ws ana*
l ly E e iuanbe e ts t latn F"Avey vL so e no eJf n l
a t n a imi t
n a
'm i id d* hla ecnhM Mpa a uad e Esda e ot ori ta oe ot o s a c n C u
s e en t e4 r 1 s vdbuCE h e e ade ilsor a e
s trh ny s t rd ln w e e
e 65 at a ri phed Le a o
e ary "yh tewhhAmd e ry t T P igeLa s r ol o t p H rf iuRDh b fof u e .
46M00 ts no o g, 0 et c
- - tsE G t bl .Es rd c n c4 .
s -
ha re EEEEEluc 98991 s s s
ieOP e c. . od t
Liibk(1 aMh t nl wf ao ael e 0 a
)
te se si t rr n6 o5 r . Ath r t _
e a a,e 8 iaN r pp n s wiE. % a w u e o uu c - .
00000 e e rd e r _
lpt s oeQy c. g c i I t
mie0 o 1
u Leiqc r L.c o imM t
- ** *
- ei al e ah r9 B ml u ht lc r a s u lu s M.ac nae d .fMt H 1 s a si M0444f 6 Mwlae l E _
a s u t
o r5 -
s e r -
EEEEEo n bov oo)ht aLi vvasl i u goEa n o rk c wmS
- weEl, r e r mgm lo a i
s e l e l8Me eciat e pt e 2 e sd e 9 r p vr ehv i irHh t
h TD 6 O 8 0. 8. l 88789AD I E gPdT el is t a t 3h 2 cwaT( a nh 3 r rh0 r o eT3l f ar n
oi cE eO l
J K
L M DD
T N
E S S S S M E E E O )ES SE SES ES SE E C
S S EE E S S S S S S E EEEEE O) S S S S S S S EE S ES EE S S 3 YYYYYY N(YYiDEE E EE E E E
E Y Y Y N(YYYYYY YY Y YY Y YYYYYY R
G A
xI
.O 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 3 6 3 3 3 6 3 3 a T 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 36 3336 33 MAR 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t
s t I O
5 l iTr 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 6 7 7 7 6 75 57 5 5 5 u MAR 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 u0 0 0 0 0 0 0 0 0 0 0 9 0 0 0 0 0 s
e T R O 8 5 2 4 7 6 R
I T 8 8 0 3 9 0 1
1 %71 05 1 0 8 8 0 2
9 7 6 0 9 0 9 0 0 4 1 6 4 0 7 8 0 9 2
1 4 5 0 8 9
9 6 01 9 9 3 2 9 9 0 0 0 O m A R
0 0 1 1 0 1 1 0 1 1 1 0 1 1 0 1 0 1 1 1 1 0 1 1 0 0 0 1 0 1 1 1 P a r
E g R N G o r O I
N I P T U 0 0 0 9 5 0 0 0 1 0 0 5 0 0 4 6 0 5 6 5 0 3 0 8 0 0 4 30 8 2 0 4 R L 1 0 9 8 6 3 3 4 2 7 3 3 0 7 9 6 7 2 3 7 t 1 7 7 0 7 3 5 5 3 2 9 2 D k O 3 6 5 5 5 6 6 5 6 5 6 7 6 6 5 5 5 5 6 6 6 6 6 5 6 1 1 2 2 2 1 2 3 1 c S E
1 e R N h O C M s
)
A L s M 0 7 8 4 5 4 6 5 6 6 A o G 7 3 0 30 0 30 7 7 0 0 7 371 3 7 7 0 3 0 30 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T 3 r YI S 0 3 2 2 2 1 2 1 2 3 2 0 1 1 1 2 1 1 0 2 2 1 1 1 0 0 0 0 0 0 0 0 N T E FC NI (
I A
8 F
M E a l
T e N Lt R E
g a
O B n S C) A P R e C N I A TU I
M 5 2 6 2 9 6 9 V
N Tmn Y L
G I
S 2 0 1 6 8 6 4 6 3 7 9 8 2 3 3 5 7 5 4 5 2 6 7 3 4 3 2 4 0 0 0 1
0 0 0 0 0 0 0 0 1 1 0 0 1
0 081 1
0 E o A 3(
r N L A A i v
C I
G n
O E E 2 8 5 L
O S U)
LA 4 0 0
8 7 5
3 4 6 2 4 5 4 7 1 8 6 9 0 7 9 2 3 5 9 0 7 60 4 5 2 3 2 4 7 7 0 4 8 3 1 5 6 7 0 1 5 4 5 C
1 1 3 8 5 4 6 6 9 6 7 6 1 1 1 0 1 0 1 2 I A( 2 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 D I V A
R T 8 Y 9
9 L
1 A Uf) E 1 N PGA(l D 0 3
0 7
1 0
2 1 2 0
1 0
1 9 8
0 4 2 5
0 0 7 8 0
7 3 4
2 7
3 6 04 7 9 6 4 8 7 0
1 3
6 0 0 3 4 5 7
0 1 8 5 4
T1 . 3 1 5 0 L0 0 0 00 01 02 1 1 1 7 8 1 A V 1 1 1 1 1 1 1 1 1 8
9 9
1 e d
i l
c 1 4 7 4 1 4 7 4 1 4 7 4 u a 4 1 3 3 5 9 5 0 9 0 4 1 3 3 5 9 5 0 9 0 4 1 3 3 5- 95 56 04 N h a 1 5 1 1 -6 4 8 1 1 1 5 1 1 - 5 44 1 8- -9 1 5 1 1 CCMFNZENO CCCCMFN ZCENO 3 3 - 3 lp te ER A B CC S S C RR S S 1
I 1
1 C C C C E R S S - N E
- A F NO ZCl 1
RR S S ER S S r r r e a e e e g i hi h hi d i t
k k l d
e F i
F F n l i d d i o
M s r i r
tr a M M M S A A A C n
o 8 8 8 8 8 8 8 8 it et 9 9 9 9 9 9 9 9 c 1 1 1 1 1 1 1 1 le D a 1 6
1 6
1 6
1 6
1 6
1 6
1 6
1 6
lo 0 0 0 0 0 0 0 0 C
j1l
E s n o
y.
e i
ae. ht t
k n le ut s l t
h ba l
i i
npc w
.d et e r4 e0 e1 wmiseep t rt c5 "g o we gr h6 naR- oaly r n knss a9 c d op t o n i ot a pC t n5l c a i
r tr e it r r e e ohA i Ee n u o H341 act c ex eF b u t t l t
af o Co dteot rh os s in
- n f et h
i e o d o h.S he e r t r M
. ntaa i
r igC t h t ost pe ed oTeu ot. iges sl g
n l a
e gear hd ni nf ri t nr i i t s
i l r d n dt i se i
l a aht n f caeer ou mnk n o
e trF v wyi e ewk o aiehhnk e ec e p m r
arog i 8kl a l l
s n it a m m rgigc e o Cf di is t
r5 e r r e r r i o4 t wb a mn ah ss o w a pH nC c1 et elr li sg9lb e
a i et ao r sc c
e E r
rl eai.
t e aa w vr -5 a e ht d i o C l
t t D14 hcn igheE pi k i ci l r n a
p ihio o Fe n fo t
s Ft dl a
m1 o - t i
mem t n
T R
r fo ao nt t
fC rEwc a e 7 e Heh . H )t nf acn if 9 i
i i le b
a l e
u O i l Ci) oa u y1 v L 79 h e5 -
t f
f la b1 g E i t P pSm t
/ s9i i
e e E vdetoe c n R
l a oi r g hd r Cm1p (
rll whdtE t F i w
d n
t of s t r n 6 r )i t a ee x lo a, G t )3 uu 9 o C a mereews y s aune t N d y( r fb oo0 lo f
ne I nd8 a( es m e. ght ac e is t s ht e R a w8 m O
l ioi /g 7* ht aolrb wf a 3
( el h c d 8 t ht t a
e T 5 y t z .iYn i
n I SC1 r p h yege ep 2 ly )e h e i T
r N fo k, a wk nc i a gw dk n n e 0
1 i w s n0 r a ac 5 n a a8 n .at na i o w o
t s
3
)l yMe u w2 o3 t 4 s r 0 e t
u h a nt a h s r
L d a s ae 06 b lo s W A ( rl kn1 ats7w awc1 l s s e
/g oa nsOi l w e i t
v T
N f v u5 u0 e el uppw eaaCw t r
e .m i nn t i Ls C/c s l hiol i c 9 E Ra1 l ame a va ci oo gt io i
pii c t t e o . F f ,Cty t Cvs a n rh a s e
. e n I
h k pl a 5. s aa r t
c i s na iae t datie g N ien2 l
eh ww c s n i t h n a O MaA1 r ut oe i t
yHik i
hl mev bt o
i h Rn P a daev nu a R " ia a5 .i wm mi l
r s e o t i
nt i I t t v nkl l n uc t
oi aw 0 r t V f oiH80 n t
t 5 e N
E LU
/
i i nt wnt o eoi hc s A 2.l e1 e9 c o l
ins ere r t yb s n ol l a
7 c 4 n 8 u nmt ty of L C pnpo s. C m k e sl Hto (w 5 enC
- iat t e r ge 9 FEdis . r e o erie noa r
A eia ol f ce eut i ur dla C aatog e r t ht gtaA L. 08.0 6 nu cl a nar e I ar / 1 i l uve ch t G s nt n t i pnd e h i
Cmo9 9 oa v ashct oi O i nm32 ar l ai at r eh pot r1 1
e n c, h mif Pr ws L Ue1r s er o 4 f gt o n
O o: 3 e 9. h iog on y
t
. e*ist t ve et l ih l o
I o w pio g0Tt is a e D nd o e10 al r u st nti a i n a r e en u i t i A i s en ar 3 6 r ole am.bh nAa o g v l
ct a e
pt r R aor2 ai er t
r r l u ao uss e r s osfb r il an t deihn e s n 8 t n msat e e vci hi t aidtaci t n
t n 3 5 8 nec wiH l I 9
9 e r c o s c r e8 t f . wtaepg g n e ta dt nf e 63 21 Cno e r r ne s ar geni m 5.0 6.1 i
1 nece . r nci t m co i 1 1 Rc h tooi 221 l
f b cia crl e opt n e - - -
oei ct s s s s crh yn e t c atytet i
r r a De uus e e - - - Ny 1
e e r 505 nt wf npt latam i i
t ed5 st e - pl r etrRearhb t
i au
.h y t
r r
g a ar s o e rm A
g 4567 8 8 000000 Si Ui v t
cnct o oAer kne go c o c u f
DoCcAesger e ep ee a ce i pe k
ag l b
e it c e yeg r inca t
at af Hh t - h nonuh ut al as y e n i
s s
bh ta e n d r e o hterd ed st t f e . n e)7sdt e s o u yi is eDz e r i ~r i epva o t vt l b s n sar o y edi9t l t e r c nwki 9 h r a v e i
l e u i
e a n ep4 .l a hocu1 t t e sc9 luoc paoc0 wh9 t
o sl u nt oco s
u s r3 n i e n(r ee t
a t n cae laie1 aC ht r r enh1 i
y e i
vme 0 h c t a cea ads meakt yec suDk e wec t
Veuf a s p l m
y laUru n
o 1
65 2 0
oo e .h2 h ne t t ul e 81 sl a owla mt h e04. ot 3 < < r t
e nPs it at s cave t ht e d as ga cr t
ni c r g AGa e u < < - - l n
iV1 ty uleo i i 1 oi f lo - - 0 i l
aU 5 apl t wlcrLs5 s9 1 s sdf a e hh cc m s e 4 481 5 2 61 0 mv sas nPR vm541 0 eue . r o - f ioaee n aa ecUP R<222 22 i
n a6658 e r nh a a wta a er u l
AGC w s* *
- s gnoicEot t e r Fer euuce r r
l i
m ee ddG ad j eeeoi4543 ae et ee v lu dl l e r
e aa sHHDkH21 1 2 lasTcfriHaaaah n i 1 975l ehi l t
vh vct t
e ivve i r r DDD i i e d eo t
o . . . t ni o i r
NABC D T 1 . 23.. Cm
1
- I I998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT l
l l
i APPENDIX G 1998 Data Reporting and Analysis l
l l
1 i
(
Page G1 !
t i
5
4 l
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1
Environmental samples frequently contain very little, if any, radioactivity. Even when very sensitive, state-of-the-art counting equipment is used, many of the sample count rates can not be differentiated from the background count rate or the count rate of the blank sample. When this occurs, the sample is said to have a radioactivity level or concentration at or below the sensitivity of the analysis method. In this case, the analysis result is reported as less than a numerical value, which corresponds to the sensitivity of the analysis method. Sensitivities are influenced by parameters such as sample volume, background or blank sample count rate and efficiency of the counting device.
The terms used to describe the sensitivity are the lower limit of detection (LLD) and minimum detectable concentration (MDC). For this report, these two terms are considered to be synonymous. They are defined as:
- V
- 2.22
- Y
- exp " I l
I where: j Sb = the standard deviation of the background counting rate or the counting -
rate of a blank sample, as counts per minute, E = the counting efficiency of the equipment, as counts per disintegration, V = the volume or mass of the sample, such as L, g or m2 ,
2.22 = the number of disintegrations per minute per picoeurie, Y = the chemical yield, if applicable, A = the radioactive decay constant for the particular radionuclide and At = the elapsed time between sample collection (or end of sample collection period) and counting.
The applicable LLD or MDC for each radionuclide and analysis is listed in Table D-1. A large percentage of the 1998 sample results were reported as less than the LLD or MDC.
Results which were reported as less than the LLD or MDC were not included in the calculations of averages, standard deviations and ranges (by station or group) in the text and tables of this report.
The data from samples which contained concentrations above the LLD or MDC were used in the calculations (averages, standard deviations and ranges) contained in this report. The individual results were generally reported to two significant figures. Each result also included a two-sigma counting uncertainty (95% confidence interval) to the same decimal place. At a minimum, a counting uncertainty equal to 10 percent of the measured concentration was reported. The counting uncertainties were not used in any statistical calculations in this report.
Page G2
t i998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT The data used in a few tables and all annual graphs were actual sample concentrations. For historical graphs, actual sample concentrations were used for 1998 data points only. The actual concentration is calculated by subtracting the background count rate or the count rate of a blank sample from the count rate of the sample. The net count rate is the converted to a net sample concentration which is either positive, negative or zero.
There are several advantages of using actual sample concentrations. Biases in the data (averages, ranges, etc.), such as those caused oy averaging only sample concentrations above the MDC, are eliminated. Missing data points on graphs also are eliminated. It should be noted that negative sample concentrations are important to the overall averages and trends in the data, but they have no physical significance. A negative sample concentration simply means that the background or blank sample count rate is greater than the sample.
Quality control results (interlaboratory and intralaboratory) were not statistically analyzed with other data. Including quality control data would introduce a bias at selected stations while providing little additional interpretive information.
Page G3
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX H 1998 REMP Sample Collection and Analysis Methods Page H1
O psG a G G A e
r r
- n a
cm B A y l
, m e l j4 s
, a t a i
, E a
s p
y H A G A A S G
R P P P IKa e
W W dm ip ul me' f
a aQ A w 9" hCo t
hC t
ug u c a a m e
e a
- mn non e
t s rt de n
u kn yl e uti g n goim l ' hu hu irl s
p y g oy d II f o n r
a r
c iu tl s I u t
! s ag l
8 c r b bo '
e rw c
r w e a s iwm mb a ep e o D
p e a e p e a e S -
e s m
- p kl pe kl a n a pi ylks ey y m sm c . e n
P" r r p
gpl I o o l me o
- r r i f
b b g n S 1 mw oh f
i i
w i
w uS 9 9
ni c l
t e e e
e e
Me nN 8 -
s h y a r
kl k yl t
h uE n R A
y s
e e t
r p a ai o
d aC r D mco i
r r r c s s y R I _
oll r e f t c
o l
el a
m a
m o f a d O
L _
r e od ct e
pi pl i
So i
O _
m w d g m gn al o G a it h mg I C
A p ci l L -
I 3 1 C6 5 ( i 5
( i Mf e al h (i 5 f .
g k ut bo 0
0 0f 0l i R i l p A
CE E ei r
pl i u i 1 c m - et I etr I
p r on N -
nc Mf 5
L 1 r 0 tX o l V it bs el e i 0 0 X x l v e i T I R
P
) et e r r tl C
I C Ami na c t or A O s s u u B a
) (6 b bi ylate oin N g
e 9 i
c M
c M
zS e a nme L E M E
dm a nt n
(
H N e e 2
)
t e
t e
r p
l e H N 9 r s s da T
,3 ) ) S l A A
i z L 0
0 e nM ao M T 66E 66E 6E 6E (
3 E yli n O PB 55 R ld(56E R 55 R 5 R 1
5 R 5 R s io t N mE 4 - 100 L 1
o0L 1
100L
~ -
1 0 L 10L 80L I P s r 1
1 I
M M M r e Min D 2e 5t s SP SP SP P P P c e eg R E
4 dA 44 44 44 4 4 t w
o o
5 5 5 5 55 99 5
9 5
9 5
9 un hP N d
99 1 2 99 1 2 1 2 2 2 2 r e aly o r G 00 (
M3 0 00 .0 0 0 Ns i do sg R 4 6 45 1 5 5 as n r E b 1 a P e
r 9m 9
8 O
R T
8' Sa c f S cL
- I S da cS a a en oa nev fo E o o a oo ""
m e
c al um a y nt p n
ag r i yl eg s
t b
d l
e "p
" n r u r m nl t opl u
n t
i b w
mle
- 8l iwe n gna s.i lbn t
a e sisg ea a g c 8" s
a b
)
d.
p oPcoce d
s npo n ip "al be a v c a g k
8 I
a in c r "
o ta nt an i
P"'ed kp o
v e
ri ro base msion g o r r u
- Pr t
E i oat n
- I o k el emd f op l n ue d c ai s r a a n r pi a u
ic c e "c nd d
g a
8 e
d nmfod ap s s ad II5 nou ga no s ' u r
l l r h wn i a n s s f
l 0 e y eg q a l 5 t 5m o "
s isa a ui dy c s g fl ai t
w
- A s
r md mp e io i
d s. u c on wle p P' b
s t
e n o r o r ao p t n p ss p I" a mirt is ri n ngOi n t a r os o "" c t
e x oi so t yl c n i
p et n don e oe i o
o
(
nc pip l a
he or ru r f
o nlp iol n
a I'
o t
c e
toai n r na a n l
d e l c r h i e n r
o e
g imb u l
" y a m a ic t
n r o " linm e tph t
u .
oi s cs y f
r wnb aoo og g hr e ' l n
d iad isfo nl a n "
t t t
a c di n e a ia tn
" eml is n l
t u u e t
r c c o
- 8 e i s o yb r u s ai c
- " hDf t t b p e e lpo g t r mM A
i
- " w g. a t
e i co pi s m s.
t i i
sP r ns '* det ms e od u ma uly oa i
n nt d n d iun n a t
e a s m c n
- ou s c
e de ma m a m. c p el c
s a P
r v g d c, i
'E
- d nm e e ts e ie r e reoi if v
o inyt r n v
o s fo c
" tet a i mc em d
n er lpa% ""5" '
- I dl de d
t .
b a
s l u
o f
o e b
a s
a n det ia l
e a pm lepciroe nmt n a e
mgr n u a
e r n i o mm a a WI "
s m r frs e a oe r m
a r
e i h e a a t
s e m a
Dc S g
- 0" 3 Sf pp S Th m S T
R 8 9
O P m9 a1 b r
e E r gs s u m
R od isN y
S 4 D0 64
- 0. 0 2 58 000 258 0.0 0 1
0 G r o lar e 21 99 21 99 21 1 999 d
o 21 9991 doo y3 r 4 d
o N Ph t nu Ad e 55 55 5 55 o 5 555 w5 te2 o w7 I
R ge c 44 PS 44 PS 444 PSS w2 t 3 - 444 PSS t s -
3 iS m4 t s -
1 O iMn o MP MP M PP s - 2 e25 5 MPP e25 s oP e24 I r oi s P
r I 0 t
-0 I
- O0
- W4-4 EOO L 00O EO t
- 0OW4 - D0 W3 -
I L001 L00 L0001 I- 10 EO N t iy s R 55 E66 1
R 55 E66 1 1 R5 5 5 E666 1 1 BRR R555 BR TPP E666 TP 1 1 t M6 T6 BR TP O nl M oa L
A MnA l
e iz S
T ad e N H tn n lp 3 E E e a md s t s H M
N L mn nio ae S zy n e
m t
n e e g
O B ot t
el an a
d le m e P a
R A r c i e mA )
le n E l E
I V T vl l i
x o
b i r
s 0 1
8
/
s 4 N
no r p
s s te W r d n D
/
D.
E EC A p
k gp o l 5
i 0 i n
0 1
L T
1 1
L l
al e I fi
( 3 2 r
7 2 I A c p C
i gm I
G l o oS a
O i df L
O I
ao R-y D
A R
Cw d o I E -
ht e
8 N M 9
9 S =. g s 3'
I S l i
n g s e e e lp '
p lp lp 8 m m m "
m a a a a s s s S '
b b b
- a r
a r
a r
- g g g '
y y ly
- t lr lr
- c e e "
ar a
na t
r a
u u u Q Q Q
'e na l
ph ad a
SM s e D S
W S
- U
- S D I
y p
)
s n
i a t i o
s m mct ly a
n m, u i
t n
mid aDa ei a r
A g T G( R
9 e
I d
e n
si t
k SSI GBA a WD D WRP sk m
====== K e
SAiGBA u q mr r i y
or rf a umoun ad aP c at i e r ci csi dLni DSoWe a e n a a u f c
mdiDt k
mo e Val e e t
.r gine s g net e
W(TL.
a a
r k
i
)D.. .n t
e r
1 9
9 _
8 .
R _
A _
D I
O _
L O
G I
C A
L E
.4
.44I i A N l I Tl k I il i :
p p
V I
e kLe i
t t g r g sDrs aei nr o r R P
s s
e/( n(
x O g
a m8f i
ua a mi a N e i Ea a l v yl l 5 7 e t
M 1
1 ne n - - ai l 0 S E 4 u a -
a b C m u
a N
l yl = )e l
l T q m pi c A uq a u M Si L
r a r et r t
e et e M yl yl r
er r s G O
)
p el i
l N
1 e
r ts 1 e
w d D e p e e R I
k r o
r S N
w at t
t G
w h R e m e E E
k yl D R
T
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX I 1998 TLD Quarterly Data Page 11
' l i
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLEI ,
1998 TLD Quarterly Data l mR Per Std Month 2o I l
Station 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter l
A1-5 5.4 0.8 5. 0* 0. 5 5.5* 0.5 6.8* 0.6 B1-6 5.4* 0.7 5.3* 0.4 6.5* 0.6 8.9 0.4 C1-9 5.0* 0.7 4.8 0.4 6. 5* 0. 5 9.0* 0.5 i C21 5. 6* 0. 7 5. 3* 0. 2 5. 5* 0.4 6.2* 0.7 1 D14 6.3* 0.5 5.6* 0.5 8.4* 0,8 12.5* 1.0 D2-1 5.7A 0.3 5.5* 1.0 5.6* 0.5 6.3t 0.5 E1-7 5.4* 0.3 5.2A 0.4 5.2 0.8 6.5* 0.4 El 17 4. 2* 0. 5 4.0 0.4 4.3* 0.5 5.60.6 E2-1 7.6* 0.9 7. l* 0.4 7.8t 0.4 8.3t 0 9 E3-1 5.5 0.6 5.5* 0.3 5.2* 0.5 5.9* 0.4 F 1-2 6.3* 0.6 6.4* 0.5 6.7* 0.5 8.1* 0. 8 G11 4.9* 0.5 4.7* 0.3 4.9* 0.3 5.8* 0.4 GI-2 5. 7* 0. 5 5.5* 0.6 5.8 0.9 6. "'* 0. 5 i G21 4.8* 0.4 4.5* 0.4 4.4* 0.2 4. 9* 0. 3 l
G10-2 5.6* 0.3 5. 4* 0. 3 5. 4
- 0. 5 5.8* 0.6 !
H 1-5 5.6* 0.8 5.5* 0.4 5.6 0.7 6.4* 0.5 i H2-1 5. 8* 0. 3 5.5i 0.6 5.5 0.4 6.3 0.4 H 10-1 4.5* 1.0 4. 6* 0. 3 4.4* 0.6 5.0t 0.4 Jl 1 4.8* 0.4 4.9* 0.4 5.1* 0.6 5.9* 0.5 {
Ki 5 4.2A 0.5 4.1 0.2 4.2* 0. 3 4.6* 0.5 l K18 4.9* 0.5 5.0* 0.4 5.2i 0.4 5.9i 0.5 I Ll-1 5.li 0 8 5.1* 0.2 5.2* 0.4 5.9* 0.3 I L21 5.0* 0.6 4.9 0.5 5.1* 0.1 5. 8* 0. 9 Ml-6 5.2* 0.7 5.1* 0.8 5. 3
- 0. 4 6.0 0.7 N1-4 5. 3
- 0. 7 4.9i 0.2 5.3* 0.5 5.80.5 P1-1 5.6* 0.6 5.6* 0.6 5.4* 0.4 5. 9* 0. 5 Q1-3 4.6* 0.5 4.5 0.3 4.60.3 5.3* 0.7 Rl-1 5.4* 0.7 5.5 0.3 5.6* 0.7 6.5* 0.5 I
i Page 12