ML20205C023

Segregation of Uncontaminated Dry Active Waste, Final Rept

ML20205C023
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Site:	Sequoyah
Issue date:	11/30/1983
From:	Kornblith L NATIONAL NUCLEAR CORP., LTD.
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ML20205B991	List: ML20205B984 ML20205C012 ML20205C023 ML20205C048 ML20205C086
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EPRI-NP-3299, NUDOCS 8608120231
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i t ow lovel radioacative wastes EPRI NP 3299 Elec,tric Power Radiation monitoring Project 1557 9

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NP-3299 Research Project 1557-9 Final Report, November 1983 Prepared by NATIONAL NUCLEAR CORPORATION 1904 Colony Street Mountain View, California 94043 Principal Investigator L. Kornblith, Jr.

Prepared for Electric Power Research Institute 3412 Hillview Avenue Palo Alto, California 94304 EPRI Project Manager M. D. Naughton Chemistry, Radiation, and Monitoring Program Nuclear Power Division

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ORDERING INFORMATION Recuests for copies of this report should be directed to Research Reports Center 3

(RRC), Box 50490 Palo Alto, CA 94303 (415) 965-4081. There is no charge for reports requested by EPRI member utilities and affiliates. U.S. utility associations, U.S. government

't agencies (federal, state, and local), media, and foreign organizations with which EPRI has an information excnange agreement. On request, RRC will send a catalog of EPRI reports.

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Ccovr9nt 1993 E ecteic Power Researen institute. Inc Ad ngnes reservea i

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inis repers was prepared tv ine osaanitatonist named De'ow as an account of wore sponsored cy the E'ectric Pewes H^e.itcn Inst. tate Inc itPRio Pdestrier (PHI mencers of E PRI the orqJnilatCnts) MJmed tetoa not any s

peewn si tirq on tAusof any of t'vm ias makes any warranty encress of irnolied. wien resDect to the use of any etortnaton apparatus metnod ce process discrosed e Inis recort or that sucn use enaf not intringe pe vate-c

., owned regnts os ri assur*vs any hat

• ties witn respect to the u>e of os for camages resuiting from sne use e

of any mtorrnaten apparatus metnod o# peocess disclosed in in.s report Prepared Dy 1

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EPRI PERSPECTIVE PROJECT DESCRIPTION The costs of shipping and disposal of radioactive waste from nuclear power plants have escalated rapidly since 1975. Dry active waste (DAW) accounts for a large part of the volume, but much of it is contaminated only slightly. Segregating nuclear wastes which have activity levels so low that they pose no public hazard could save on costly disposal procedures.

RP1557-9 used a large-volume monitor to characterize the activity distribution of DAWs from TVA's Sequoyah Nuclear Station. Six-hundred consecutive bags of waste generated over a period of about six weeks had their radiation dose rates indivi-dually measured and recorded. Since the monitor is a gross counting system, cali-bration procedures were developed that used reactor coolant activity as the cali-bration standard. This approach provided the necessary nuclide distribution in the correct geometry and made it possible to calculate the activity distribution for the entire sample of 600 bags.

PROJECT OBJECTIVES The objectives of this project were (1) to assess the use of large-volume monitors for DAW and (2) to characterize the activity distribution in the OAW from an operating nuclear plant.

PROJECT RESULTS The large-volume monitor performed reliably, providing accurate measurement of radi-ation dose rates from the 600 bags of waste. Activity levels ranged from 0 to 10,000 nanocuries per kilogram. While 10% of the bags concentrated 40% of the total activity, about half the bags registered less than 100 nanocuries per kilogram, showing very low levels-of contamination. Plant estimates of the activity of waste drums filled with these bags appear to be quite conservative, overestimating the activity of most drums.

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From this work it is apparent that nuclear plants generata a large volume of DAWs that are only very slightly contaminated. Presently this material is disposed of as-radioactive waste, a costly process in view of such low contamination levels.

EPRI intends to support the reexamination of this practice to determine whether it is necessary in order to protect public health and safety. In addition, EPRI is conducting ongoing waste disposal research focusing on advanced volume reduction systems, disposal economics, and waste minimization techniques.

This report should be of interest to generation operators and engineers.

Michael D. Naughton, Project Manager Nuclear Power Division i

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[ i' ABSTRACT A program has been carried out to characterize the Dry Active Waste (DAW) stream from a typical PWR power plant in order to determine the usefulness of large.-volume DAW monitors for segregating such waste in order to dispose of it in appropriate facilities.

A waste monitor using plastic scintillation counters was used for measuring the The monitor had a volume of about 300 liters and an overall efficiency waste.

of about 12% for a typical radwaste radionuclide mixture. It provides automatic compensation for background radioactivity and could measure a bag of waste in less than a ninute, including background measurements.

Six hundred consecutively generated bags of DAW were measured. These had a total activity of about one millicurie and an average specific activity of about 540 nanocuries per kilogram. About half of the bags contained less than 1000 nanocuries and had specific activities of less than 100 nanocuries per kilogram.

Based on simplified preliminary calculations, it appears that an evaluation of the risks of disposal of bags such as these in a landfill other than a low-level waste disposal facility could be carried out that would demonstrate that such disposal of half or more of these bags would not result in any substantial hazard, either short or long-term.

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ACKfi0WLEDGMENTS We wish to express our appreciation for the assistance to the program rendered by Mr. Roy R$nsey of the Tennessee Valley Authority. He has been the engineer in charge of the activities at Sequoyah and his aid has been invaluable. He has enjoyed the support of the Plant Superintendent, Mr. C. C. Mason, as well as that of other Sequoyah personnel. Mr. Lenin Riales, of the Waste Management Group in the Chattanooga general offices, has been strongly supportive of the program, both during the attempt to install it at Browns Ferry and later at Sequoyah.

We also thank Mr. Kitts, then Health Physics Supervisor at Sequoyah, for his suggestion that we use bags of rags saturated with the radioactive samples as calibration sources. This method provides a substantially improved simulation of bags of DAW.

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e C0f1 TENTS Section Page 1

INTRODUCTION 1-1 2

BACKGROUtiD AND CHRONOLOGY 2-1 i

3 EQUIPMEtiT DESCRIPTION 3-1 4

CALIBRATION 4-1 Background Measurements 4-1 Calibration Sample Preparation 4-4 Calibration Setting Selection 4-10 5

DATA AND ANALYSIS 5-1 6

CORRELATION Ci MEASUREMENTS WITH SHIPPIl4G MEASUREMENTS 6-1 7

CONCLUSIONS AND RECOMMEN0ATIONS 7-1 i

APPEllDIX A BAG M0ti!TORIllG PROGRAM GENERAL INSTRUCT 10fiS A-1 APPENDIX B DATA OBTAINED ON INDIVIDUAL BAGS RANKED BY TOTAL B-1 ACTIVITY CONTENT APPENDIX C DATA OBTAINED ON INDIVIDUAL BAGS RANKED BY SPECIFIC C-1 ACTIVITY O

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t ILLUSTRATi0fiS Figure Page 1-1 WCM-10 Waste Curie lionitor 1-3 5-1

% of Bags less than N Nanocuries or Nanocuries/Kg 5-4 5-2

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'Page 4-1 Initial Samples 4-5

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4-6 4-3 Comr:rison of WCM-10 and Laboratory Measurements 4-7 4-4 Total Activity and Isotopic Distribution of February Samples 4-8 4-5 Comparison of WCM and Laboratory Measurements 4-8 4-6 Dispersed Sample Measurements 4-9 5

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SUMMARY

The purpose of this project is to evaluate a method of reducing costs of low-level waste disposal. The method proposed is to reduce the waste volume by segregating the portion of the Dry Active Waste (DAW) stream that presents no health hazard so that it need not be shipped to a connercial radioactive low-level waste facility.

Disposal of Dry Active Waste (DAW) is becoming increasingly burdensome to nuclear power plant operators. The number of active conmercial burial sites has been reduced to two. Additionally, both shipping costs and disposal costs are increasing at an unprecedented rate. This is compounded by increasing restriction on shipping aad disposal, both by the state and the NRC. These factors all impose additional costs and workloads that are substantial because of the larqe volume of the DAW stream.

In addition, it has long been recognized that available space at disposal sites is limited and that the space available should be used for material requiring the restrictions currently imposed and not for material that could be disposed of more simply. The NRC reinforced this point in October,1981, in its policy statement on low-level waste volume reduction.

In early 1982, National Nuclear Corporation (NNC) proposed to the Electric Power Research Institute (EPRI) a program to evaluate the use of its Waste Cu-ie Monitor, Model WCM-10, in an operating commercial nuclear plant environment to achieve the following objectives:

To characterize the distribution of the measured activity (nCi/kg) in e

DAW from an operating plant; To establish the reliability of large-volume monitoring compared to e

hand methods; To demonstrate calibration techniques for large volume OAW monitors; e

and To quantify the effectiveness of segregation procedures to reduce the e

volume of DAW.

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s It was !#1C's belief that the prcposed study, together with a subsequent safety analysis based on the data obtained, could be used to prepare a license amendment request to the NRC to justify disposal of a large.,ction of this relatively innocuous waste stream either in a utility owned land-fill within the site boundary or in a local public land-fill.

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The contract between EPRI and NHC was executed in June, 1982. The Tennessee Valley Authority (TVA)'was contacted by NNC and agreed to support the program.

The support provided by TVA included the use of TVA facilities and on-site manpower at the Sequoyah Nuclear Plant.

The monitor used in the program was a National Nucica Corporation Model WCM-10 Waste Curie Monitor. This is a large-volume, high-sensitivity monitor with a counting volume measuring about 24"x27"x29".

It uses six large plastic scintillators as detectors, with very high geometric efficiency. The scintillations are detected by photomultipliers, amplified, and counted. The resultant count appears on a digital readout which, by appropriate calibration, is direct-reading in nanocuries. The counting time used was 10 seconds.

The monitor is quite sensitive and has an overall efficiency of about 12% for a typical fission product mixture. It is very simple to operate and is provided with an adjustable alarm, calibrated in nanocuries, that operates a red or green light to give positive indication to an unskilled operator.

The monitor is well shielded so that it can be used in areas having background levels found in typical plants. It also contains a scale for weighing the samples.

A novel method of preparing calibration samples was developed, using bags of rags, geometrically similar to bags of 1%h', saturated with liquid samples from the waste streams containing the appupr ate isotopes. Representative waste analyses showed the streams to co-in sut 34". Cobalt-60, 43% Cobalt-58, 12".

Manganese-54 and the balance pri art i, Q<iium-134 and 137 and Iodine-131.

Six hundred consecutive bags of DAW, generated over a period of five or six weeks, were measured. The total activity in these bags ranged from zero to about 30 microcuries. The activity concentrations ranged fron zero to 10,000 nanocuries per kilogram.

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.-i In the analyses of the data, bags were ranked both by total activity and by concentration.

Twenty-five percent of the bags contained less than 100 nanocuries,-

57% contained less than 1000, and 79% contained less than 5000. With respect to concentration, 50% contained less than 100 nanocuries per kilogram, 74%

contained less than 500 and 81% contained less than 1000 nanocuries per kilogram. The 50% containing less than 100 nCi/kg contained only about 2.4% of the to'tal activity. The data obtained are presente'd in a form that permits easy determination of the fraction meeting any defined total activity or concentration criterion or any combination of the two.

Dose rates measured by hand-held meters in contact with the bags were also recorded. It was apparent from the data that hand-held meters could not be used to reliably determine whether bags met a given release criterion.

Records were also kept to determine how the cumulative measured activity of a group of bags put into a given drum for shipment compared with the activity measured by the method used in the past. No correlation was possible because of the excessive conservatism in the methods currently used.

The objectives set forth above have been achieved:

Characterization of the waste at Sequoyah has been accomplished.

o The reliability of large-volume monitoring has been established.

e A suitable calibration technique has been developed and demonstrated.

e The data are in hand to quantify the effectiveness of segregation e

procedures once an appropriate set of criteria has been selected.

A set of criteria must be developed, based on health effects and legal requirements, for this work to become of practical value. Such a set of criteria would have to be acceptable to the Nuclear Regulatory Commission and, in some cases, apprcpriate State and local authorities. Given such criteria, this program establishes that substantial cost reduction can be achieved.

Developnent of such criteria seems to be a logical next step.

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Section 1 INTRODUCTION This project is directed at evaluating Dry Active Waste (DAW) monitoririg techniques for effective segregation of uncontaminated wastes or wastes that are only slightly contaminated. Four objectives were defined for the project:

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To characterize the distribution of the measured activity (nCi/kg) in DAW from an operating comercial nuclear plant; 2.

To establish the reliability of large volume monitoring compared to hand methods; 3.

To demonstrate calibration techniques for large volume DAW monitors; and 4.

To quantify the effectiveness of segregation procedures to reduce the volume of DAW at an operating nuclear power plant.

The first objective has been achieved as it relates to a particular plant during normal power operation. The reliability of large volume monitoring has been established, although it is not possible at this time to establish a suitable index for comparing its reliability to that of hand methods. A calibration technique has been developed and demonstrated. The final objective has been achieved to the extent that all of the necessary data are in hand to quantify the effectiveness of segregation procedures once an appropriate set of segregation criteria has been selected. A set of criteria must be developed as a separate project, based on calculated health effects and legal requirements.

To become of practical use, such a set of criteria would have to be acceptable to and accepted by the fluclear Regulatory Comission and, in some cases, appropriate State or local authorities. Given such criteria and the data

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developed in this project, the effects of segregation can easily be quantified.

Trie instrunent used for large volume monitoring was the WCH-10 Waste Curie Monitor (Fig 1-1) manufactured by fiational fluclear Corporation. It was set up in the Auxiliary Building of the Sequoyah fluclear Plant of the Tennessee Valley Authority. A group of bags of contaminated Dry Active Waste (DAW) Collected during April and the first half of May,1983 constituted the sample tested.

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Each bag was measured with a hand-held detector in accordance with the normal procedure and then measured in the WCM-10. Most b,ags were then opened on a frisking table and the contents hand-frisked. If individual items having high activity were identified, these were removed and the bags remeasured. This was effective in only a few cases, because of the relatively uniform contamination of the material in most bags.

The results from the 600 sample bags were analyzed in three sequential groups of 200 bags e'ach to give a measure of consistency. A record was kept of which bags went into each of about a dozen

" test drums" and the total measured activity put into each drum compared to the estimated activity measured in the manner normally used for shipment to the waste disposal site.

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Section 2 BACKGROUf4D AllD CHR0:10 LOGY Disposal of low-level radioactive waste is becoming increasingly burdensome to nuclear power plant operators. The number of active commercial burial sites has been reduced to two. Additionally, both shipping costs and disposal costs are increasing at an unprecedented rate. This is compounded by increasing restriction on shipping and disposal, both by the state and the liRC.

These factors all impose additional costs and workloads on the power plant operators.

In addition to the burdens identified above, it has long been re' cognized that available space at disposal sites is limited and that the space should be used for material requiring application of the conditions currently imposed on disposal of radioactive waste and not for material that could be disposed of more simply. The fiRC reinforced this point in October,1981, in its policy statement on low-level waste volume reduction.

The UAW stream in a nuclear power plant is a stream containing large volumes of low-level waste. The majority of this material is extremely low level but is frequently mixed with material of somewhat greater activity.

Some plants attempt to provide a system for the separate collection of nonContaminated material from controlled areas, but this has seldom been very successful and the material usually ends up conningled with the contaminated material, in addition, where the segregation has been carried out, there is often reluctance, for public relations reasons, to release this material locally.

Even if this is not a problem, licensees properly will not release the material without a check to assure that it is in fact uncontaminated. This in turn leads ir.to questions of at what level does one consider waste to be non-contaminated and how does one measure it.

In view of the above considerations, in early 1932 flational fluclear Corporation (fiflC) proposed to the Elactric Power Research Institute (EPRI) a program to test its lJaste Curie Monitor,liodel WCit-10, in a realistic plant environment to achieve the objectives defined in the Introduction. It was fif4C's belief that the proposed study, together with a subsequent safety analysis based on the 2-1

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data obtained, could be used to prepare a license 3mendment request to the NRC to justify disposal of a large fraction of this,relatively innocuous waste stream either in a utility owned land-fill within the site boundary or in a

local public land-fill.

In June,1982, EPRI contracted with NNC for its execution.

The Tennessee Valley Authority (TVA) was contacted by NNC and 6 greed to support the program, initially at its Browns Ferry site. The support to be provided included use of the TVA facilities and the provision of the necessary man-power to carry out the on-site activities.

In the fall of 1982 Browns Ferry authorities deter:nined that their current work load did not permit them to support the activity adequately and in early October the program, with the WCP 10, was transferred from Browns Ferry to the Sequoyah Nuclear Plant.

A preliminary calibration of the machine was made in late November, but it was decided that a different calibration method would be more suitable. Because of plant problems not related to the project, recalibration could not be done Defore the Christmas vacation period, but it was anticipated that it would be Carried out in January.

Again plant operating contingencies precluded the necessary support for the recalibration. It was finally carried out on March 22 and 23. Health physics support was provided starting April 1 and the actual measurenents started a few days later. They continued until May 13. During a 6 week period a total of 607 yellow bags were measured.

To keep the data dnalysis simple, the last seven bags were ignored and the analysis was based on three batches of 200 Dags each. A few (6) " green" bags, used for noncontaminated material, were also measured. Two of the six appeared to be more contaminated than the least-contaminated 25% of the yellow bags.

During the last two weeks of the measurements, a record was kept of the bags that sent into 13 drums for shipment to the waste disposal site. This was done so that the total amount of activity put into each of these drums could be conpared to the amount determined to be present using the normal assay measurements carried out before shipment. This consists of making dose rate measurements with a hand-held instrument at fixed distances fran the drum and dpplying an empirically derived formula to convert these to radioactive 1

content. The measurenents are discussed in Section 6. The project measurement program was completed in late May and early June 1933.

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Section 3 EQUIPMENT DESCRIPTION The monitor used for measuring the radioactive material content of the bags is the flational fluclear Corporation Model WCli-10 Waste Curie Monitor. Figure 3-1 is a photograph of the monitor. This is a large-volume high sensitivity monitor with a counting volume measuring about 24" wide by 27" high by 29" deep. It uses six zS"x19"x1-1/2" plastic scintillators (including one in the door) as detectors.

The scintillations are detected by photomultipliers, amplified, and counted. The number of counts accumulated during the counting interval (normally 10 seconds with an option of 100 seconds) 1s divided by the setting of a calibration control and each count out of the divider gives a

single count on the digital read-out. Proper selection of the calibration control setting results in the digital read-out being direct-reading in nanocuries.

To operate the unit, a control toggle switch on the front of the monitor is first set to the background counting mode with the machine empty.

The background ganna rays penetrating the 1-1/2" lead shielding are counted for a

10 second background counting period.

During this time, the circuitry is drranged so that the read-out st6rts at its full reading of 100,000 a!)d counts down, in a normal background the number of counts during the 10 second period will De 100 to 200 (giving a read-out indication of 99800 to 99900) but the count-rate will be higher if the background is elevated. At the end of the counting period, the reading is retained. The sample is then inserted and tne switch set to the sample counting mode. The machine then counts the number of background plus sample counts detected during the sample counting period.

If the background has not changed, the final reading will be the activity of the sample alone. (The background counts detected in the two counting intervals will have cancelled each other.)

The method of operation outlined above permits the monitor to be used in background areas typical of those likely to be encountered in DAW measurement activities, provided Care is taken to avoid inaking measurements while high-activity material is being moved in the vicinity of the monitor.

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This is discussed in subsequent sections.

The monitor is quite sensitive and has an overall efficiency of about 12% for a typical fission product mixture. It is not, however, energy sensitive and cannot be used for isotopic discrimination. The unit used in this project began to lose counts at a sample activity of abo'ut 10 microcuries and saturated at about 25 microcuries, although the reading does not decrease at higher levels. The significance of this saturation is discussed in a later section.

Later models of the monitors avoid this problem by modifications to the electronics.

In addition to the controls discussed above, the monitor is equipped with a

dial for setting an alarm point. A red or green light is turned on at the end of the sample counting period to show whether the sample is above or below the a larm point.

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Section 4 CALIBRATION In general " Calibration" may be subdivided into three parts. The first is the measurement of the background, the variation in it, and the analysis of the probable errors it causes. The second is the preparation of the calibration samples and their measurement in the WCM-10. The final area is the selection of an appropriate calibration setting for the machine. Each of these parts will be discussed.

BACKGROUND HEASUREMENTS The method of operation of the monitor in measuring background and samples was discussed in Section 3.

Two effects can inject errors into the process we have described.

The first is statistical counting errors and the second is changes in background between the time the background is counted and the time the sample is counted. We will look at each of these and to provide numerical examples we will make the following assumptions: 1) we have three samples containing 15,150 and 1500 nanocuries; 2) we have determined that 50 is the correct calibration factor; 3) a ten-second counting time is used unless otherwise specified; and 4) the background is 150 nanocuries-equivalent. This latter is a term for the background gamma-rays penetratir.g the monitor's shielding which gives the same reading as a 150 nanocurie source in the monitor in a zero background field.

We first look at the statistical errors. The statistical uncertainty is the square root of the total number of gammas counted.

From the earlier discussion, it is seen that the total number of gammas counted is the sum of the background count and the background-plus-sample count multipliad by the calibration factor. To convert the uncertainty in counts to the uncertainty in nanocuries, the former must be divided by the calibration factor. Thus Uncertainty (nCi)

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o N = the calibration factor. For the assumptions above, the first sample would have an uncertainty of 2.5 nanocuries, or 17%. Fo.r the second sample, it would be 3 nanocuries, or 27., and for the large sample it would be 6 nanocuries, or 0.4%. This latter is insignificant. The 2% uncertainty for the 150 nCi sample, in most contexts, is also insignificant, but for the small sample the uncertainty is significant. It can be reduced by about a factor of 3 by counting for 100 seconds, or can be reduced by talling multiple counts. Four counts will reduce it by a factor of two, and may, in some rare instances, be worthwhile.

The statistical error effect generally is less significant than the effect of changing background. For example, take the effect of 10% increase in background between the time background is counted and the time the sample is counted. With our 15 nCi sample, the readout will count down 150 counts and then count back up 180 counts. The sample will appear to have an activity of 30nci, twice its actual value. Higher background levels or larger changes will make this effect worse and vice versa. A 10% decrease will make the sample appear to have no activity. For the 150 nCi sample the effect will be 10% and for the strong sample it will be only 1%. Fortunately, changes this large in a sho-t time are not likely, although they could be caused by such things as movement of strong sources near the monitor. In addition, the WCM-10 has been designed to keep the background up-to-date. The machine, once started on counting background, continues to put out a new background count every 10 (or 100) seconds until the door is opened to put in the sample, so delay in measuring the sample does not result in using outdated background data.

A series of measurements was carried out to provide information on the background at the monitor location in the Sequoyah Auxiliary Building. The measurements were directed toward answering two questions: first, did the background change over the time periods of interest; and second, how large was it?

Two sets of measurements were made. On March 22 a series of 14100-second background counts was logged. The measurements were scattered over a period of several hours. The results ranged from 112 to 121 nanocuries-equivalent. The individual readings in this series, in chronological order, were 117, 121, 119, 121, 118, 118, 121, 119, 121, 121, 121, 120, 116 and 112. On a statistical basis, one would expect an uncertainty of about 0.5.

The uncertainty calculated fro.n the measured values is about 2.5, five times the random error.

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Even ignoring the last two values, which are clearly lower than the rest, would leave an uncertainty three times as larg'e as expected. Thus, we can conclude that over periods of a few minutes or a few tens of minutes, the background can vary by several nanocuries-equivalent and that it can vary much more over longer time periods. Actually, during later measurements, changes of several hundreds of nanocuries-equivalent were noted when hot waste druns were moved near the monitor during measurements.

Since we were planning to normally use ten-second counting times, ten-second background measurements were more relevant to our needs. A number of such measurements were made on March 23. The first series consisted of thirty measurements taken early in the day during a.ive-minute period. The measured values were 113 twice,114 twice,115 four times,116 twelve times,117 seven times, 118 twice, and 119 once. There was no discernible time-trend. The mean value of these is 116.0 and the probable deviation of any one value is 11.6 nCi. Since the monitor only reads integral values and rounds down, one sigma would cover the readings of 114, 115, 116, and 117. These include 25 of the 30 readings. The standard deviation calculated from the 30 readings is about 1.3 nCi. It seems clear that during this five-minute period there was no significant background variation and the distribution of the counting rate measurements was within a normal statistical distribution.

A few hours later another series was run. This time 20 measurements were taken consecutively. Again there was no discernible time-trend, although the average value was noticeably lower than it had been a few hours earlier. This time the values were 108 three times,109 three times,110 five times,111 three times, 112 twice, 113 three times, and 114 once. The mean value of these is 110.55 and the probable deviation is 11.6. Sixteen of the twenty are within this range, again indicating a normal distribution. The measured standard deviation was 11.8 nC1.

A few hours later, a third set was taken, this time of ten readings. These

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measured values were 107, 104, 106, 106, 101, 104, 108, 105, 103, and 102. The mean value is 104.6 and the pecbable deviation is 11.5. One sigma includes six f

of the ten measurements. The measured standard deviation is 12.1. This is somewhat larger than woulo be expected, but not exceptional.

It is clear from these data that the background was dropping during the period covered by these measurements and even the highest value, in the morning, was 4-3 l

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4 8 less than the value measured the day before. The reason for the slow change was not investigated, but, since nonnal work was going on in the adjacent waste-handling areas, it is reasonable to assume that this was the cause. The general background drift in a downward direction was confinned by 13 additional readings taken at various times between the last two series of measurements.

These varied from 107 to 111 and averaged 109.5, fitting neatly into the trend.

it appears that for a ten-second counting time, the statistical variations can account for most of the variations. This would be of the order of 2 or 3 nano-curies for an extremely small sample, increasing to about twice that at a microcurie and then increasing as the square root of the sample size. The percentage error from this source starts high (about 15% for a 15 nanocurie sample) and drops rapidly, being less than 0.5% at a microcurie. It would appear that the way to improve matters for small samples would be to count for a longer time, but this is not so (under the circtmstances of these measurements) because then background changes between background-counting time and sample-counting time begin to make themselves feit. More improvement can be made by repeating the 10-second measurement, but the accuracy only increases as the square root of the number of repetitions. Happily, precise knowledge of the amount of activity is not important for such low values in the case of our present needs. For conservativeness, we consider +4 nanocuries to be a i

reasonable limit on the accuracy of the instrument at low readings as a result of the Sequoyah background conditions and statistical variations. One would expect that in higher background areas with proportionate background variations, the error would go as the square root of the background.

CALIBRATION SAMPLE PREPARATION In order to obtain accurate measurements, the NCM-10 should be calibrated with samples having isotopic distributions similar to the material to be measured after calibration. Although the instrument is not very energy-dependent, there is a slight dependence because at very low energies (e.g., under 100 kev) gamna rays are attenuated by the 1/16th-inch stainless steel liner and at relatively high energies fewer of the gamas lose their energy in the plastic detectors.

Since most of the isotopes of interest have gannas between about 0.2 and 1.5 mev, these variations are not very significant. More important is the fact that some isotopes have two gannas per disintegration. The only one of these of interest is Cobalt-60, but this is a very important isotope as far as the isotopic make up of DAW is concerned.

4-4 1

s-

't a,4, At Sequoyah it is known that the isotopic distribution of the DAW stream (and most of the other contaminated material) is very similar to that of the water entering the clean-up system. This is basically reactor primary system water that has decayed a few weeks. This was selected as a suitable source of materials for preparing samples, i

The first samples were two one-liter samples taken before and after the

~

clean up demineralizers. A sanple designated sample "H" was prepared fran the before-demineralizer sample by diluting 20 ml to one liter. This had an activity after dilution of 527 nC1/1 One-fiftn of the other sanple was diluted four-to-one to make sample "L" and the remainder was diluted five-to-four to make sample "M".

These had activities of 33.6 and 120.3 nCi/1, respectively. The total activities and isotopic distributions were measured in the Sequoyah radio-chemistry laboratory. Table 4-1 shows the isotope distributions of these samples. In each case, the Xenon-133 contribution was ignored, %cause this is not seen due to self-shielding and absorption in the WCM-10 liner.

{

Table 4-1 INITIAL SAMPLES L

M H

Units Total Activity 33.6 120.3 526 nCi/l Mn-54 1.9 1.8 1.8 Co-58 78.0 77.7 90.4 Co-60 12.0 11.3 3.9 Fe-59 7.6 6.8 Nb-95 1.3 l-131 1.1 3.4 Cs-137 0.5 The analyses for the two lower samples are essentially the same, although some isotopes in sample H do not show up in sample L because they are below the detection limit. Sanple H is slightly, but not much, different, reflecting the selective clean-up capability of the demineralizers. These samples were then put into the WCM-10, at about the center of the measuring volume, and found to 4-5

t measure 54, 231, and 927 nanocuries. These values were measured with a calibration setting of 27, which was arbitrarily selected.

It was next decided to prepare a set of samples covering a wider range. Five one-liter samples were prepared and designatd A through E.

A, B, and C were prepared from the af ter-demineralizer samples and had activities measured in the laboratory as 14.4, 33.6 and 121 nanocuries. (B was the old sample L. A was 10". of the sample M, and C was 90% of the sample M.) Samples 0 and E were before-demineralizer samples, O being the old sample H and E another sample from the original liter. Table 4-2 shows the laboratory analyses for these.

For sample A, everything except the cobalt-60 was below the detection threshold. These simples were then lounted in the WCM-10. After a preliminary measurement, a new calibration setting of 44 was selected and each sample counted for 100 seconds. The results and the statistical counting errors are shown in Table 4-3.

The agreement between laboratory and WCM-10 is quite good, the largest deviation being about 8% for sample D.

Table 4-2 SEC0tl0 SET OF SAMPLES A

B C

D E

Units Total Activity 14.4 33.6 121 526 1109 nCill lin-54 1.9 2.1 1.8 1.8 Co-58 100.0 78.0 77.5 90.4 87.5 Co-60 12.4 12.1 3.9 6.7 Fe-59 7.6 6.9 fib-95 0.5 I-131 1.4 3.4 3.0 Cs-137 0.5 0.5 Af ter the above work was done, it was suggested that a inore acceptable Calibration standard might be made by pouring our one-liter sample over a bundle of rags in a typical plastic bag. This is a very attractive scheme because the calibration sa:nple is then more geometrically like the real samples. In addition, by this time it was realized that the measurements in 4-6

O,,

the WCM-10 were being af fected by the self-shielding of the sample, whereas the s.

laboratory measurements were not since they included calculated correction for this.

l Table 4-3 COMPARISON OF WCM-10 AND LABORATORY MEASUREMENTS i

i Sample WCM Measurement Lab Measurement Units A

14 + 4 14.4 nCi B

32 + 1 33.6 nCi C

125 + 1 121 nCi O

567 + 2 526 nCi E

1077 + 2 1109 nCi A nes before-denineralizer sample was taken in February and a new set of calibration standards prepared. A preliminary set of measurements was.aade in I

the laboratJry and in the WCM-10. For some undetennined reason, the WCM-10 4

read low by about 20"..

In March the samples were remeasured in the laboratory, i

this time using 800 ml of the original samples and putting then in Marinelli beakers. This geometry, because of the lesser water thickness, reduces, but does not eliminate, the self-shielding. The algorithm used to calculate the activity for the laboratory measurements corrects for the remaining self-shielding. There is no correction for it, of course, in the WCM-10 measure.nent. Table 4-4 shows the total activity measurements for these samples, as well as the isotopic distributions.

4 i

The samples in the Marinelli beakers were then measured in the WCM-10. Table 4-5 shows the comparison of these sets of measurements, including the ratio by l

which the calibration would have to be changed to make the WCM-10 readings I

agree with the laboratcry results. As can be seen, a 207, increase in the

}

calibration control setting (from 44 to 53) would reduce the readings by about i

175 and make the three hatter samples read 191, 529, and 1102 nanocuries.

1 These are all within 24 of the laboratory measure;nents. The number 2 sample

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would be about 20% low, but the statistics are poor for such a low activity j

l level. The f act that the WCll-10 readings were 177. higher, relative to the

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4-7 i

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laboratory measurements, for the samples in Marinelli beakers than in one-liter bottles, supports the reasoning th&t there is a se,1f-shielding effect. This is reinforced in the next experiment, where dispersing the sample will increase the measured value by a substantial amount.

~

Table 4-4 TOTAL ACTIVITY AND IS0 TOPIC OISTRIBUTION OF FEBRUARY SAMPLES (Marinelli Beaker Geometry)

1. 1 82 83

1. 4

1. 5 Units Total Activity 4.4 11.1 192 540 1088 nCi/l Mn-54 4.7 2.1 11.9 12.3 11.0 Co-57 0.2 0.2 0.2 Co-58 44.9 61.4 43.6 42.6 44.1 Co-60 34.0 23.6 34.0 33.4 35.7 Zn-65 6.4 l-131 4.4 2.6 3.5 2.8 Xe-133 6.5 Cs-134 5.6 2.8 2.7 2.1 Cs-137 6.4 4.9 5.3 4.1 Table 4-5 Cut 1 PARIS 0N OF WCH AND LABORATORY MEASUREMENTS Samole

• WCf1 Measurement Lab Measurement Ratio 1

5 12 4.4 1.44 2

10 + 3 11.1

.90 3

230 1 4 192 1.20 4

637 1 8 540 1.18 5

1328 1 0 1088 1.22 1

4-8 l

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The next operation was to pour each sample into a bag of rags (about 10-15 pounds). After the first bag was completed (sample #4), it was found that most of the liquid stayed near the top of the rag bundl'e and little soaked down to the bottom. A consequence of this was that the reading obtained in the WCM-10 was somewhat sensitive to the orientation and location of the sample. A number of measurements were made in what seemed to be the extremes of position. They ranged from 751 to 907, or roughly 8251 10"..

In general, the readings were highest wnen the hottest portion of the sample was nearest to a wall of the monitor.

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L The remaining samples were loaded into the bags with more care to achieve reasonably uniform distribution.

This was quite successful, reducing the variation to 17% for sample #5 and 15% for sample #3. The variations for the two lowest-activity samples were greater, but basically what one would expect from background and statistical variations.

The interesting thing to note is that tne readings for the dispersed samples were significantly higher than the readings taken with the same material in the Marinelli beaker configuration. This, of course, is what was expected and I

reflects the reduction in self-shielding. Table 4-6 shows the three sets of measurements--WCM-10 measurements in Marinelli beakers, WCM-10 measurements in dispersed form, and lab measurements in Marinelli beakers. It also shows the ratio of the dispersed form measurement to the laboratory measurement. This is an index for resetting the calibration control and indicates that a setting of 66 (one and a half times the setting of 44 that was used for the measurements) is the "most realistic value".

Table 4-6 01SPERSED SAMPLE tiEASUREliENTS WCM Measurement WCM Measurement Sample #

Marinelli Beaker Dispersed Lab Measurement Ratio 1

5 12 5.7 1 2.7 4.4 1.30 2

10 1 3 1813 11.1 1.62 3

23014 284 1 14 192 1.48 4

637 18 828 1 80 540 1.53 5

1328 +10 1660 +115 1088 1.53 4-9

^ CALIBRATION SETTING SELECTION It was decided in the interest of conservatism to increase the sensitivity (deci' ease the calibration setting) of the WCM-10 to provide for two of the effects discussed earlie. A 10% factor was decided upon to make allowance for the geometrical effects discussed.

This, alone, would have led to a setting of 60, rather than the "best value" setting of 66.

In addition to this correction, it was felt desirable to provide for possible changes in isotopic composition.

As discussed earlier, the most significant effect of such changes is the varying number of gamas per disintegration resulting from varying fractions of Cobalt-60.

If we make the reasonable assumption (based on the analyses discussed earlier) that Cobalt-60 constitutes one-third of the total, activity, the average number of gammas per disintegra-tion is 1.33.

If the Cobalt-60 abundance dropped to 20%, this number would drop to 1.20, a 10% ddop.

If it increased to 45 or 50%, the number would

, increase about 10%.

Thus a ten percent allowance in the setting for such changes would provide for Cobalt-60 fractions from 20% to 50%.

Even if there were no Cobalt-60 (a most unlikely event) the result would only be 15 or 20%

lower.

Increases in Cobalt-60 fraction are in the conservative direction.

Actually, the changes resulting from Cobalt-60 changes are not quite as large as stated because the detector is slightly less sensitive to Cobalt-60 gamas than to the lower energy gamas that predoninate the other common isotopes.

As a consequence of these considerations and the desire to provide some margin for statistical effects, it was decided to apply an additional 10% sensitivity

' increase. The final calibration factor selected was 54.

This sort of application of conservatism factors does not lend itself to a simple expression of probable error.

We conclude, however, that the measured value is unlikely to be low by more than 3 nano-curies, even for samples of low radioactivity, and unlikely to be high by more than 20%.

If the "best value" setting had been used, all of the activity data discussed in Section 5 would be reduced by 22%.

~

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4-10

~~i

Section 5 DATA AND ANALYSIS Plant personnel started taking data in early April. The Waste Curie Monitor was set up in the waste handling area and the operations were carried out in accordance with procedures based on criteria developed jointly by TVA and NNC.

A copy of the procedure is provided in Appendix A.

The data taken on each bag included bag number, the maximum external dose rate, the WCit-10 reading and the weight. If the dose rate was low enough (less than 2 mr/hr), the bag was opened on the frisking table and a general description of the contents recorded. If the contents were such that it seemed likely that much of the radioactivity was concentrated on few items, these were removed and the bag remeasured. This was done with a very small number of bags. In most cases the contamination in the bags was widely distributed and in many cases the contents were wet.

The data were handled in batches of two hundred bags each. The concentration of activity, or specific activity (in terms of nanocuries per kilogram) was calculated and the two hundred bags in each batch were ranked by both total activity and specific activity. For each of the rankings, the fraction of the total activity in the batch in the bags lower in the list than the bag under consideration was calculated. For example, in the first batch the bag ranked 117th in total activity contained 485 nanocuries and all 83 of the bags having less activity than that contained, in total, only 1.237. of the activity in the batch. This allows us to select any cut-off point and readily determine the fraction of the bags and of the total activity falling above or below that cut-off.

Before dealing further with the numbers, one shortcoming of the data should be pointed out. As mentioned earlier, the monitor begins to saturate at about 10 microcuries and is essentially completely saturated at about 25 microcuries.

This means that for the bags shown as containing over 10 microcuries, and particularly for those listed as being near 25 microcuries, the actual content is probably sonewhat greater than listed. On the other hand, close examination 5-1

of the data indicates that there probably are not many bags substantially higher than the measured activity. Consequently, when we say that the total measured content of the first batch was 0.99 millicuries, it was really greater than that, but probably not much greater than that. For the same reason, when

^

we say that the least-contaminated half of the first batch contained 2.28% of the measured activity in the batch, it means that they contained 2.28% of the measured activity of 0.99 millicuries, but certainly less than 2.28% of the actual content. Since we are interested only in the lower activity bags when we are contemplating disposal at other than a contaminated waste disposal site, this shortcoming does not affect the usefulness of the results.

The first batch had a measured content of 0.990 millicuries and weighed 1442.6 k ilograms. The average specific activity was 687 nanocuries per kilogram (or 687 picocuries per gram).

The second batch contained 0.615 millicuries, weighed 1446.2 kilograms and averaged 425 nanocuries per kilogra.n. The third batch contained 0.743 millicuries, weighed 1477.5 kilograms and averaged 503 nanocuries per kilogram.

In all cases, these numbers are subject to the qualifications discussed above.

For the entire lot of 600 bags, the total content was 2.35 millicuries, the weight was 4366 kilograms, and the average concentration was 538 nanocuries per kilogram.

Appendix B contains the data obtained on individual bags, ranked by total activity content. Appendix C is the same data but ranked by specific activity.

The following paragraphs give sane examples of how the data can be used to determine the amount of waste that meets the criteria that might be selected in the safety analysis.

Depending on the method of analysis selected, either total activity or specific activity may be the parameter of interest in calculating radiation exposure.

In the first category, for example, one might select 100, 1000, and 5000 nano-curies as cut-off points. Our data in Table B-1 show that 100 nanocuries would include 39 (19-1/2%) of the bags in the first batch, 1000 nanocuries would include 106 bags (53%) and 5000 nanocuries would include 147 bags, or about three-fourths of the bags. The equivalent figures for the entire 600-bag lot are not shown in a single table, but the percentages are 25t, 57% and 79%.

The concentration, or specific activity, data can be handled in the sane way..

5-2 1

., ~

f If de selected as cut-off points, for example, 100, 500, and 1000 nanocuries per kilogram, we find, using the information in the. tables of Appendix C, that for the entire lot the lowest cut-off point would include about 50% of the bags, the next would include about 74%, and the highest cut-off would include about 81% of all the bags. Further, the 50% of the bags below 100 nanocuries per kilogram contain less than 2.43% of the total activity.

Witn very little more effort, one can determine how many t.ags meet a combined set of criteria. For example, one might select the criteria of 1000 nanocuries total activity and 100 nanocuries per kilogram.

Two hundred ninety seven (49-1/2%) of the 600 bags meet both criteria and an additional 50 bags meet one but not both.

The curves plotted in Figure 5-1 show the percentage of bags having less than a given activity per bag and the percentage having less than a given specific l

activity. In both cases the curve represents the entire 600-bag lot. Attempts j

to plot each batch separately did not provide any additional useful information. Figure 5-2 is a curve of the fraction of total activity as a

function of the number of bags with the bags ranked by total content. It is almost logarithmic. The first 40% of the bags contain about 1% of the activity, and the next 30% contain 9% more. The highest 10% of the bags contain almost

]

60% of the total radioactivity.

There is no way to make a simple graphic presentation of the relationship between dose rate measurements and radioactivity content. It is obvious, of course, that there is a general correlation of dose rates to activity. Higher dose rates do not necessarily mean higher activity, however. For example, in the first batch there were 22 bags measuring over 20 microcuries.

The individual dose-rate readings for these bags ranged from less than 0.5 mr/hr to 4

a

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40 mr/hr. Six of the 22 measured 10 mr/hr or higher, but these were the 5th, l

8th, 9th,10th,15th, and 16th bags, rather than the first six. Fourteen of 4

4 the bags measured over 10 but, under 20 mr/hr. One of these measured 3 mr/hr, j

two were listed as greater than 2 mr/hr and two measured less than 0.5 mr/hr.

i At the other end of the scale, the readings were pretty much a function of the background at the monent and of the care taken by the technician (unfortunately it was impossible to have a single technician assigned to the proj ect continuously). Many readings were simply recorded as less than some amount, j

rather than a specific reading. Af ter the first batch, somediat more care was given to recording the actual reading and a "less than" value usually means 5-3

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% of Bags l

5-5

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i "less than but close to".

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4

+

Four bags in the third batch measured 7 nanocuries each of total activity.

i The dose rate for one of these was.03 mr/hr, one was.1, one was.2, and one was 1.5.

One might be suspicious of self-shielding effects.

If this were the cause, one would expect the one measuring the highest to be the lightest and vice versa. The data show the exact opposite. Although these observations contribute little to this project, they make quite clear that, at the low i

levels we are concerned with, dose rates cannot be used as a criterion for determining a disposal mode.

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k J Section 6 CORRELATION OF MEASUREMENTS WITH SHIPPING MEASUREMENTS One hundred and thirty five of the bags were packed into 13 identified drums.

Fro:n six to eighteen bags went into each. The total activity in these drums was then determined by the method normally used at Sequoyah in preparing shipping infonnation.

The data produced for shipment yielded results several orders of magnitude higher than the number produced by adding the values measured in the WCM-10 for the individual bags.

For exanple, Drun 83-343, by WCM-10 measurements, contained 10.6 microcuries. By the shipping papers, it contained 2.0 milli-curies, about 200 times more. Inquiry showed that the 2.0 millicuries was obtained by the formula used to calculate the 2.0 millicurie content applied to drums weighing less than 250 pounds (this one weighed 225).

It states that the content in millicuries equals twenty times the dose rate in mrem /hr measured at three feet from the hottest point on the drum surface. The reading in this case was "less than 0.1 mrem /hr", presumably the bottom of the scale on the instrument used.

0.1 mrem /hr was therefore used in the calculation. This, of course, gives the result of 2.0 millicuries. Using this same formula, an empty drum would be shipped as containing about 0.25 millicuries, just from natural background (if the instrument could read that low). If a drum was filled with 600 pounds of clean sand, it would be shipped as containing at least 4 millicuries because the fannula for drums over 500 pounds uses a constant of 300 instead of 20.

The equations used at Sequoyah are very conservative. This conservatism may be, and probably is, appropriate for the purpose for which it was intended, but it makes them useless for confirming the measurements made in this program.

6-1

- s

\\,

. Section 7 CONCLUSIONS AND, RECOMMENDATIONS u

(

Q

(

q s

4 1

-k' The data show that for the conditions ex;isting at Secucyah during the measure-

~

\\

r ments, most bags of waste had very low lev 01s of;rajicactivity. Nen percent of them contained about 60% of the total activity and the top 30% contained 90". cf l

Fortypercentofthebikscontainednegligibleamounts, totaling the total.

about 1% of the entire activity. '

)

(

d i

l The distributions found, however, could +not. hav,e been foundpy making dose rate measurenents with a hand-held instrutilnt. [ Ant instrunent measuring total activity with a good geOnetrical ef ficiency' was necessary.

Calibration techniques were demonstrated Sthat show good agreement with' laboratory measurement of samples.

??

if reasonable criteria are developed, a large fraction of the DAW stream can be disposed of without transporting it to a licensed low-level waste disposal site without undue risk to the health and safety of the public, the utility j

employees or the dump site employees.

It is recommended that additional measurements be taken on a limited scale to provide assurance the the Sequoyah measurements typify the situation at other pressurized water reactors and to detennine if the situation differs at boiling water reactors, g

I Concurrently, support should be given to several utilities in presenting this and similar information to the regulatory authorities -- federal, state,,and local -- in order to secure approval for disposal of the more irnocuous of,this i

material either in local public landfiils or in an on-site lanofill.

The information and experience obtained in these efforts should be t. sed as the basis for preparing a guide for use by.nember utilities in obtaining disposal authorizations.

i 5

a 7-1

4 Appendix A BAG MONITORING PROGRAM GENERAL INSTRUCTIONS PURPOSE To establish a procedure for control of DAW (Dry Active Waste) processing, monitoring, segregation, and data collection program. Program duration is four weeks.

CONDITIONS FOR OPERATION 1.

HP representative must be present for surveying of material that is counted in monitor.

2.

All bags of trash, both yellow and green will be counted in monitor.

3.

All bags with (2 mr/hr dose rate will be opened on frisking table and each item checked for contamination.

4.

During the test period, there will be an accountability of bags which are placed in 10 druns to allow comparison of values on drum contents between bag monitor, drum counter (test equipment to be brought in) and conventional method of content calculation.

l 5.

Monitor must be power up from 110V wall outlet.

6.

Area background must be sufficiently low to allow frisking.

7.

Data collected will be recorded on data sheets as attacheo.

8.

Care will be taken to prevent contamination of monitor lines and area.

9.

The monitor liner will be wiped down or washed as necessary to maintain contamination levels down and background in monitor low. One per shift will be sufficient usually.

10. During processing, watch for sudden increases in background which indicates the liner is contaninated.

11. Monitoring will be suspended during periods when background in area is changing rapidly, such as when trash is brougnt in or when barrels or boxes are moved out to storage.

PRECAUTIONS 1.

Health physics measures will be adhered to as HP rep, prescribes to prevent personnel and equipment contamination.

A-1

2.

Nothing will be declared clean relying on the monitor only. Frisking is at present the only approved method of detenmining that an item may be released to a clean area.

~

3.

Any non-canplying items as specified by SQA-133, Attachment

'A', will be removed from bags prior to compacting.

4 No bags with greater than 2 mr/hr dose rate will ba opened outside a C-zone.

5.

If problems or questionable readings occur, contact the Radwaste Coordinator before proceeding or recording data.

INSTRUCTIONS 1.

Monitor and frisk bags that accumulate in storage area each 7-3 Monday-Friday, 2.

Number each bag prior to placing in monitor.

3.

Maintain all the information requested on the data sheets.

4.

Clean monitor liner at beginning of each shift.

5.

Verify less than 200 nano-ci background on monitor before and during counting procedure through shif t.

a 6.

Verify that scales in monitor are working correctly during monitoring 4

process, between bags the indicator should return to zero. If scales cannot be initially zerced, remove line.' and check scale clips, all four, in place.

7.

Use care in renoving or reinstalling liner as rough treatment will cause scale clips to be Jarred out of place.

4 A-2

-w,,--.

t Appendix B DATA OBTAltiED ON INDIVIDUAL BAGS RANKED BY TOTtL ACTIVITY CONTENT O

e

n e.

e e

e nig Table B-1 Part 1 t

RANK BY TOTAL ACTIVITY - IST 200

,s.,

,s..

meneMW... u.

c.

me...

. m..

. =,..

n,,.

.a.

..e a.

heJai'WjyXhe.MWs&dM' i,.. o S.w4., dO' d4Mi#eONWiedeldl&MM/NAeR$LA.Lilit?Miet e

4.'43Lsk-W4kMkald"""^

%eM@2 2

.= a e

=.

Ai

.1 e.

&.3 * * =.

13

-=-

-* * * =.

3 4

4me e

^

LeFt a

• 4W w.. V. -

.d42.3

f. 4 L e.4 3.a

=.v 3

k

.h.

& > & =.t

=.=t.-

1 C.W*es m

e 3

s 3

.s e.dwr

c. s.a (e.

be.=04 g'

.s. : =.4 =. =

.e.=.=

c 3

s 334:

-ss sc be.4'c4 e.

a s.

m.

?

w -

Swb

$.4 m

g33=

=s w

we.VV1 we

==

=.

. = =

• 2 a=.=.=<=

3 Yeb.3 g.9 =.

.4== g 7 "t w y ab=

(.*

a 2?

• a*

4=...=.

.1*

3 3=

C*$,1 e s y-4

• F 9 R.

L e b. =. =.

E"

. =. b..z

.b.

,.e.

V, e,3 e y <2 44

1. E. N. 4

=.. *. = - ae?

etM*-

e m. m.2

=. e.

.a s..e 2 ;--

...=

• C y

A.

• .4

.r...

3., V143O.

e**

s-

< q e 0, b r

• 2.,=.

3?

• s=

s..

e 3 3 =. =.

e_

=

4.

cr.

.i==.

(e.

e L.s,=.,

=.,<

.=

e r

..9 r w s

.1 3' (3

--a*

a.= b b 6=3%

e <=b&

.e

=. =.

34,

c. a r-4e.e n=--

as

+

g.h.. 6 a

. =. F.

s.

13 ebbar

< b-

&*=r.

9w *.a.

3 Ce a=.=.

Q 4 a.3 14e

b. O wA..z

-.a (ew

z. s -

a. e. -

e i

eCe3 %- *

,s r a*

w e r.e s., C

.r.

- W r

r

=.4--Fr

• 6 e $ =a =. C.s a -=

s 4a

.S.i e..

• m =.

(e.

e b

b

~3 A

3-

• .=g-

& = =..s e.

b

• L a -=

we<1*-

4 c.

.,0=,.=

a 3 =.

,, e we 1 * ** i 4

@ e $. s 'W.3 C*

4*

.w.aw e.

3=

=4

.W w

v

. A, a =. w3 2 e

A..k w 1

w

=

4.04 cg

• e e

5 b

44

-, A, s s A. p s e.

609b..t h

s s. =

as 4

e

,a a g e -

we a.*a.

43 bb=

=.*.=.6

• . =.*

b' le.

A s.,

<.

3 s.

,4 ng.e 9

- c ebw

<w aV e. 7.,.2

.i e 4==.=

2

../

• O C.Y a*=

(ewq e C. a. s.

m.

=3 m

e.

fa Z*.*

abar 4 'b-3 Ve=4e.A 4e

• . **=

• 3**

.3.

a m

=. =.

a.S e *F

=

E.3

,9 A.

a-=

a b C 3 =.

e 4.

- a s==

.e 34 3

3 e.s=

4=.

4.*.,

a. n w.

. a. *s g

. e5 ew-b.

. =,

s.

r a.ar.

46

. e.

b e.

b.

g

-.3-4 e s

'1 3p eb.a

< a.

sb

- s.3 s

2=3 g

a e 4-4 b

.c

.e = b3

.we.C.&.

x'

a. n.,4

• i e

s aczy

.e 1.9 r..

zi3=

C*

s3 aw-Oe.=e -

4 4 =. g e

4 rc 4

h 3

24 saw.

.' 6 (e.

M C C. e-

• 2 a=

w

. = =..-

= :s

-e

-.a.,

.s a e.

eb- -

e -

Ves.r-4C ez 4 e. a-t-*

u e w =. J. ~.2 *:

a 4.

s3, -

ser se.

-w

=

z.ea.h s=.=..-

4 C3e=W..

a b-

=.

e r

3 b.

. =. <=

cb.-s 3=--=

s o.

ob wL

- a ar z3 w.

..t r. s.*a=.

1. =..t

< e.q a

• .-e.1 04 g

-3 4wr e,.t

. w

• r =.

.z 1

b. =

T-a e.-

w s,.C =. s

..z==.

4 q

e *..i.=

or er

.r 4.. r 6 =..

=r 3s

.b

=b. a =.

e b

a.a=.

,= s

.z.-:.:..e q

.s..

e.

eb*

., = =.

.1*=.

,.e

.34t*

-.7

. 4 e.

-a1

. = = =.-. =. =s s.

..z...e be*wa..

1

=

b

-w

&.-~.4 34a f

=

(3 e

• S. u. s.** & e.

.c 3

b e.

• .e.

3 3*

W.

2&*

.b--

r e

e b' *em.t =

z.

3 =.. =. = * *

.-*.2=.

s1 s e-Ve*fFs J

?.12 4

2*

4 4.Ff Me

.2 32 M

e V **.9 W

=.

.==*

s a.

a =..t.

.e=

we4-

• e a

b-S 3 e.

E =-

49.-9 4 = t *

.h A.

• .i :

z=

.i. =.....

1%

s.

eb*

b-sa bes*b*

a.E.= =.

r

• M 9 4 4.=.4 4 *= q *

.A b

3 q

a43*

3 **

4*

.<bs

=. h

<=e.

abww&

b<

g.

. 1 =. =. =.

..a 2

T o =-

a 1T**

m2 4

4.

4:==

-M-bow.

4 ab 4.*

.&r abT s.

e b w w.'

b=.=

me==

C e s J 2'

.3i

. s =. w s s.3..

9-

• *.2 1

s:

CW 9

4 = 4. s-4-*

b.

2 m1C aC ab s

(e.

s

.. m.a

-=*

- e 26

.*w.

Ie.

ewws w.

3 9t 4 U e w.1.-

on 4

4 4cas 3

4 '* &

311e

^^

ww w w b:

=

e.

ebwws TV

.= 1

.. =. 1 :-

= =. * =.

4

=-

G e.?

• 4 4 9

]w a 4 =.

.*C63a

f. e =-

1 4 4 me-

.s

?.t c

ewwn

..=7 v

.a i

a 33.-

a-b esb F wa

4..:

.e&.

s.=.

e4 ekea-

=

4

-4

-4 s

• .3 1.

s s

=b8 T4 e

.' A c.3

.-=

gm.

f e

S

==g e==.e g4

4. *.3 4s C. A s e. e

,s 3*

e b

sw eCA *

.3 3

=-

=.

34 -F e.

=.=.s-zw as C-e E

a. a 4G&a se.

eb&b&

f *.

s

=

e n-o a <.T.=

1e 4=

-=

4 6

V*

.a.= &

.3=*

=

b a * *.

4..1.=.

.4 9

a

• w-Agr gWa

• 1 f

e

.w

.=4 3

e l a* *.* &

M =.

Eb s e-me.. e. =

'.2 =. 1 e

2

% e E =. =. =

w =.

.=

2.=*

, e-1

a

• • =

c e-a*

1 e br a =. w

?,=

.==.1

.=63:

• 9

==

9 em..

C e =-

Uese<=.

• =

47 2*

U.

aw e.:. 2 2. "**

1, "

i

= *. *

?.T T.

7.*.7

(

e

• 3*s 2**

e b.:-. w24 O

W

.-2

==,m

a e<

w bC 17*

. 2 3

em r

/.

9*. *

• C s

b o...s.=.=

a.-:

3

-= e 4

=

.==.=..t

.a. =..*

ebs**

=

1 rw Vw=

-.=.3

\\.a n-e-

e k n.9 =.

TF

.=..m

. = =. =.,.

4

=

w e E.T,3 4

. *3 y (3; =.

Oa' 4 :..T Ie-

-==

• • b e

3*ME

4. a g e=

..t.1

=

a -

.w.

.=

eb4as bb ab -

4c..,.

f. e w eLEA 134 4 e E 4. =.

• .=

3 =.

==

. s ;.

e 3--

1

=.**3

.* * =.

A.

• * =.

bea.*.9 W

a - g e 4

• 4 e. ;-

• • e.1 2:

==q===.

.3-e.

%0 Ab es

• w 4qC m,3 -

5 s,4 a4

• 4 3 *.

• C A

b-e b' G e n eba g

e a

• at==

, 1

. A,.,

e 3*9=

w

=.".&,

b e.--.

• D D.=.

e.-..*,=*7.

y~ e eNAb-4 a.1 b y j

en g - -

=

• - c b :*

. e-m e.FF.

gy 3

=

o b.1 =.,=

,,A.

-n 3. 3-

• • • TF

. =.

g

.Tb 6

4,. 4 b' O 424*

9 4;b

==

en W

.4=

3 4 - -.

.=

.je bn**

"I.I

- = =.

3

=

sq 3 =.

e.

O b

.E.

.b i

• 22=

= = =.

..T

.=.i 9

.e==*

• m gg.

• -.=

s ew w-

/

T a b.43*

• * =..

S

=. s.

s b=

3

.t.,

m

.y.

=.b.*=-

2..*.*

=

e b a I Fa w. m.*

.E.'

..1 e b.4* !.

a 34 * = =

Y.

ee ek.-

g **

9 e.9 * i.9

• . =

.3

=.?

.s -

a a

b

.2 b

b -

m e

• r.. =

.=.=a b

o.1=w -

• 2

=T=.

s e.

ob'.=.=.

• 4 a

g

..*.e*

.*=.7 b,

=.

F

.=.9

=.h g.

9

= * *.

=

a

=.

r ee=.=..

..

s si.

eb

.=.,.t-

..b 4.

= *...

b

= =..

.. =.

s.*=.*.

e.:

,,2 m*

=

c.

eb 9 e. =. w r

=. &

=.=. *

• -F e w.4 - = -..

..a

= -

b c

.1..

.=

e.

~ e.. =., ~

=.. -

2,

e. :..

..n1 e-

=

..4

. ~,. -.

=.

e b a.-n~

. z..

=.

, A.2

., a =-.

e.

ob

~....

=

s b

• me 1:

. r.

- r. = ;

- : - s

~

m

=

• b*=-

=. =.

. =.

c =.

...=..

. =.

e.4... =.. =.

y

. r...

...b.

z e-

..m.e. :..=.

=. =.

..s:

3

- 3 s -.

...t w

e.-

er

.r

. =.

s

-=. -

=.

=-

=

=

==

=. =.

=

eb..S 3* -

b, e -a.s

..

. e a-

• b e.

2=:

~.

%e.

ob...

b e

.r:

• -.=

=..

ww.

. ;~.

b e

.4 :

• C.t e:

a**-

e b. b.:...:

ba

=. =.

e.9

• ..9 ah eb.

• .3

..z :

e=

s*S

=

I.

D. - 3

-v.,-n.

n-,

y-

.m--

7 wn

,,---,w-,

n.-,

---

,----m

4',

Table B.1 Part 2 RANK SY TOTAL ACTIVITY - IST 200 s.

..t

.a.

.,...4 u.

w.- - w.

.- - -.~,m m u m.,mm.mm m..

-.. =.

-r..

mnnwn

.,=.

. =.

.c, e u, 3.,

==

. =.

e.,

w.

=

.4 m,.

.,,,.,..=:

e m, b, o,.,

24

=.

. tu - =.

e.

< e,.

.t

. a.

er

_w

=J

- e.R

• LL 4

4 4=. a*

9 3*

a.s

+..

4 1

. s, a **

1.*=.

a.s 2

<e.

e L. 3. s3.4.2 3

C 3

13.

y

. 1 esss 4--

.2

w..

.1 999

..m.

e

.a 9 s b s.4 2 =.

.s 5.i.

t4 e.

. =-

_

sg S.e ess34 932 33 c.

1.

1

=

.a f. e.

b wa

.3 s o-w s.

e66:qS.4.

9&a g

4,

s

,M 3 -.

s s

.M.i f

g a".2 -

1

%9 13

. e-b' 4.E.3 e b b *<.3 4&.3 39*

4 **

S.

.t=

g

=

1 s'

a-r s.?

s a.

• = *

• s

. E.

. L L. =.

E

.c=

.s E

7 4.3*.

.e s -.

&g2 2.

i

.4

. i3 ). s a 119 3=

I. e.

w v

w y

4

,,. e.

k

=./

=

.M 4.

.m g

• .T *&

&c9 3

e.=

..i q '

4.

• 4

.a f.c g3 4e ss m

=*

o s

s a

..i-3.

=. ?

- e-A

.e g 43

$ e =a w

E

=

0 %, =s '

7

=.

1-9

.e r -?L 19

.g a

m 5

6 a.9 -?

.1

. =.

aWW.=.

. S..S-C s

( e =.

s'n e

s

. e.

. L U,3.:.

. 3 e_

3..

Ie-q t3 4.* t

• =.

s. =.

_.i -

• w

.Fw

• L.m 4. 9 9,.4

. b3r s

=..s a _3 --

..i..

.=

s

.e-3 J.

e O

4

1. =_

a. 4 a.t s

.a.a r

4 eOL :.

.S a.

3

( e s-e 4

s e.

a

. =.

33g a.

a s

v

• F

&a.

1 s

-=2

. T.

r.

els.2

3. r.

3.

v

,3 Ie=

,3 4

-=

.. =

a

.E -

=

w

.19 e s L =..*.' s.3 22 S

as=

s

=

.T

(.4 O

4.* 3

=-

s

.=_

c M3

. C s =. t-g.

.g 3

+*

A a. a e.

.=

=

s

%.3 k,

4FT

=J ast r, w.

. =.

. Cs q.... 3

_=_a_

-S

.2

. v.

42, a

0

(.=.

- ss w.e w

.AT A.a.-

.F

.w)=.

.11

.-;1

• 3

. =

a,

. s, s,. =.,4.c,

. e-

. t s,.,

e

=.

. r.-

. =.

e u, s,..

=,,. r,.....r.

4% =~.,.

.. -..l,, c.. -

=

. =.

. _ =. -=

.s

. e._

.sm.....i T /

,1

. a t,. :

s

,=

r4.

.. =

.s e s s,.,..

c +,-

t. i... s,.. =.=

h.

s....

..=

. =.

3 e s, u,. =.

h.

.a

... =..... =...

. -,,.,,,=

s.

..- u. t. - -.

2..:.

. - a.

. =.

r1 w

...s.un~4

.e,4..,.,.m,.:.. a.

s,,.

a.

.

.sw

.m 1

. =.

4-s r.

=

u;s

=.

. =. 3=

. t a c,, t.. m,..,

a.t.y iM,!1 tMEM w : =- --,:-.

..=

=.. -

.n

.. =.

.n,-us

.J. :.. w m s-v=-

-s

., =

.i.n

. =.

. g,s : -

.=.

.=.4.

g.

8t.....

..r4m...-r, m c,..

L, F..

.w.

..,,r =, e.

-. 4 e s, t,. _a. =

,.n.

. =. =.

=. -

.=

. =. a

.F. C..e..

r

..,c.

_ = _ _ -

.m

=

,.H.4 u

= m ' -t

.Y

. 00H

.]

.,., =..=..*e..:

.=e_...J

~eM.. L.n,.. y h1,.

. n Ly.

1, =5 E

.R. t.i.,. =

4.

s

. f. f.

14

f. f..

6 m.

O F ".

CF 5iK. E A

• C Of 4 H

E.m ; Aries

.,=

=. :....

. L, s, s.,.., =. =

. w.3 -

...m.

=. =.

.i s

=

s

=.

s ea 2

,. =.

93 es s.t; 9=..=

. C L.i,.

.e.

- 3

.s --

.. =.

33

.33 4:_-e

%...=

T w-. m,

..,g

., If J

.,.1.e, s.-

s

.e i

. w sa....

r es E n-

3.,.. s..w r,-..a. g 4m. ric s-. p E.=

4s

.sw

=.

..s ogw.=

.i s.,.

%...=.

s s.

g.s

=...

, e 3,

y.e...w.

.F. -. H. " 5 H'e'".5 e.

1. s.s e m

. w.

4

. L' L.e.

.i.3 s e.-

w w

m

.sc 3.=

.a.,.=

..r 6s e-M,=

..-m

4. -

..z

. a.

e s L, e.

q3

= :.

s.:

. =.

.5 3

ws

-s

.i.=s=.

w;

.=-

2.

, ; s *. ~- = =~.=. = =

-e... g..

2*

I 33.

r. =..,=

1 e;

esw.

T h'..,..=;..

e:

e s.a e==

.a s

.. -:- *. = -.. _d ; r g,., r. e.q.

==

=.

w'Jend m

m =.

..

=.

$7:

.e,: -

ess.

=..s

=.

. s' L s.*3-

. =..z 3

=

. C s s.2

.= =. r 33 sr r

e.

, s-

.e.n

. =.

a

.mmn=

-s 6ss

. s. = ss.

S

~,

s

. =.

.2 a.:

~.,

. s.o s :

n s,6 -

..s

_.s

=.

.s =

.s.s.

. s.-.

4.:..

e s3, 6s =..-=

m s9%.

. sms

. =.

r e U s s, -. :.

=

3

..z

=.

~~s.,

.~-

o6*6 6

• *=

.%.s..t m. =

3% 3

..-?

.s

.?

s

. =

. %' 6 % S. :

.w

=.

s7s-S

.ssss

..S s

B-4

6 y,.*

o e

o S e

t 199La g-Z deJ4 I WNA' 9A 101V7 V31IA11A - ZNG 200

' mns_N O_I_ N O I /,,M D GO dd*d4* dNM 9d0 9d0 NOI NJ GM dd a ~.w;==;;:=mmu' I / M S snmmmmm' d4

• dNM

~wmmamrazammuar mmEm ESC 346CC T670 t*

O*6STS T

C09 Tt55 ST?

>*S

• 099S 9T 33T 3S949 3C59 3

O*6TES E

CST Tt55 TSL

>*S

'099T 9E ECO ESECC ECC9 S

94TT C

CTC Tt59 T59

>*S

'09CL 9C:

O'9CT 559 3?999 3690 TO O'4009

.T ' 0 t

346 TtTS T44 S

'09TT 91 ESS 379Ct TC59 TO O'

S.

COT TC54 500 T'

'046E 9S' C55 87C09 CSLS S

O*4STT 9

C9C TCL?

CTS F*S

'0495 99 3ST BtB9S 9C5T 9

O*4TT9 4

COL TCtT T?C

>*S

'04tL 94 303 Bt3SS T039

>*S O'9433 9

Ct6 TB97 394 O*T

'0434 99 009 ?tTTS

?909 T'S O'90C A

ELC TEL?

FFA

)*S

• 0409 95' 394 37049 3409 T'S O'9509 TO

'C93 TES?

CT?

)'S

• 0999 40 399 509TC ELLY O'9 O*SSST TT S?9 T809 TTt

>*S

• 0999 LT CTT 5CE9C TtSS 70 O*ST45 TE 350 TTST C9T

>*S

'09tL 43 T

0*745S TC' C05 TT??

TC9

>*S

• 0935 4C 25C 5CB09 CtTC T'S 35T T999?

9TC 0 t?99 TT CCS TITE T06

)'S

'09T 47 545 T9593 3599 T

O 7 T 6 T TS CLS T094 TLO

>*3

• 0S6C 4S.

L 544 TSt0S 3LST 4

O'CS?T T9 C99 T09E T??

>*S

• 0S4S 49

'354 T?9TS T9S9 )0*S O'C955 TL C9T T090 T55

>*B

• 0599 *44 355 TCTTT TE9$

O*S O'C?9T TS 39E TOCC 391

>*S

'OS?T 42 SOT TCISC TBTT

>*S O'C394 TS 355 TOST TOE

>*S

'022S 45 C99 TT959 TL45

)'S O*C044 50 33C TOTB TSS

>*S

• 0909 90 C90 TOLOS T??i

)'S O*350C ET Bt5 64T T91

>*S

'OTSE 9T COT 995C T39C

>'S O*3490 53 S?3 609 T95 S

'0748 93

>'S C?S 4T99 9ST S

O*3974 3C 340 9??

TCT O'S

>'S

• 079C EC 590 9407 TETL 0*35C4 37 ET5 997 TCC

'O??5 97

)'S COT 74SC TC59

)'

O*379 3S C09 9?S 92

>'S

• 0tC9 99 l

095 7429 409

>*S O'EC9C 39 CCT 9tI 99

>*3

• 075?

99 33S tSLS 994

>*S 0*EC06 Bd C50 93T 40

>*S

'O?05 94 306 tC56 tCT

>*S O*25C4 89 390 901 T45

)'S

• 0059 99 SOS 7877 65C

>*S 0*ST99 35 C91 LCT SS

>*S

'OC??

95 555 7099 S??

>'S 0*ET05 CO CSC LTi T09 S

• 0925 50

>'S C?3 C6SE EBE

>*S 0*3009 CT C39 99C TOS

)'

'009T 5T 3tL C605 5??C

>*S 0*T54T CE CSS 99C TTC

)'4

'OCST 63

'35B C455 059

>*S O*TSTC CC ETT 9T4 T93

>'S

'OC?

6C:

-396 CLTL C97

>'S O*T9SE CT ESE 9?4 T30 S

• OCC 67

>'S COC Ct53 796

)*S 0*T459 CS 834 9TT 90

• OCTS 69-

>'S BTB Ct99 T4CT

>*S O*T4CS C9 C93 901 TT5

)'

'OC05 59

'C9C Ct06 tT9

)'3 0*T997 C4 349 99!

TS

>'S

• OC 64 CSC CE50 T94

>*S O*T9C CG C5T 949 SS

>*T

'056T 68 C??

C049 t59

>*S O*TSO CS CST 944 49 O's S

'039T 65

'C00 COSE E41

>*S O*TECT 70 355 SSC TEO

• 034E T00

>'S 347 593T TTT

>*S O*T?9S tT 399 S?9 9T

'039C TOT 394 3t55 CCL

)'S O*T???

tS CTO S?0 99

)'S

'035S T03 30C 5707 59T

>*S O'T?0S

?C C4S S35 57

>*3

• 0Et9 TOC' -

E9T 3355

?97

>*S O*TC95 77 3TL SE9 59

>'S

• 0E92-T0?

CCC 3T5T T56

>*S O*TCCC tS C53 ST?

TTT S

'0E?5 TOS

)'S CTT ETtT BSS O'S 0*T369 79 ELE STL T35

• 032T T09'

)'S C?9 305C C90 O*S O'T39S ta 309 SOS 44

• 05TE TOL

>'S CTO T6TS 599

>*S O'!3CT 79 ECS

?49 9T

'030S TC9

>'S 589 T999 T?9

>'S O*TSOC tS E55 74T 8S

'OT54 TOS C09 TLLI T9T

)'S O'TT4T SO COS

?4T T09

>*S

• 0T95 TTO T

O*TT?9 ST CTt t9L 99 tcO TLTS CSO

>'S S

• 0T93 TTT

)'S O'TTT9 SE 3CT

??9 TOT 330 TLC 5 359

)'S

>'3

'OTLS TTE O*T05 SC C9E

??0 55

)'

'OT94 TTC C?9 T994 55T C59 T949 T30

)'3 O'T09C ST 397 TTC OT

>*S

'OT9T TTT

'C87 T995 SC9

)'3 O* TOC 9 SS 954 C5T tL

>'T

'OTST TTS TOT 99 BtC C99 79

>'S

• 0T?9 TT9

?9E T939 T3T

>*S O'05ET SOS TSSS 999

>*S SL C3T C9?

SC

>*S

'OTtS TT4 309 TS?6 T43

>*S

• 0595 99 CSO C92 SC O*S

• 0TC9 TTS E?9 TSCS C95

>*S

'05CT SS C59 C t S_

19

>*T

'OTC TTS C

C3S TST?

35T

>*S 0505 90 ic

=?

>'S

'OTES TSO r

.a 1

Table B-2 Part P.

RANK BY TOTAL ACTIVITY - 2ND 200

.B.,A., G,.,,N,, C I.<,.m. /.n.G.,

DR F R...,R,._T._R,N K

,B A.G _N_C I _NC,I_/ K G.,,D R _FR._PT._A_N K.

NCI K 20a 313 40

<.5

.012 121 357 17 5

<.2

.0001 181 245 305 53

<.5

.0115 122 Oss 14 3

<.5

.0001 182 210 295 25

<.5

.011 123 235 13 9

<.5

.0001 183 36a 283 57

<.5

. 0105 124 241 13 6

<.5

.0001 184 372 283 37

<.5

.0101 125 212 12 1

<.5 0

185 339 257 29

<.5

.0097 126 373 12 4

<.5 0

186 237 246 95

<*5

.0093 127 211 8

3

<.5 0

187 Ra6 236 Sa

(.5

.0089 128 250 5

2

<.5 0

159 233 234 73

<,5

.0035 129 337 a

i

<.5 0

189:

315 222 41

<;5

.00S1 130 316 3

1

<.5 0

190 330 207 51

<.2

.0075 131 398 3

0

<.1 0

191 251 203 31

<.5

.0075 132 265 2

0

<.5 0

192 250 201 42

<.5

.0071 133 265 2

0

<.5 0

193 312 200 30

(.5

.0068 134 313 2

1

<.5 0

194 265 193 7a

(.5

.0065 135 355 2

0

<.2 0

195 271 169 25

<.5

.0062 135 370 2

1

<.5 0

196 302 152 46

<.5

.0059 137 215 1

0

<.5 0

197

• 221 16a 27

<.5

.0056 138 234 1

0

<.5 0

198-39a 161 55

<.1

.0054 139 320 1

0

<.5 0

199 300 157 25

<.5

.0051 140 327 1

1

<.5 0

200 227 155 45

<.5

.0015 141 -

254 152 22

<.5

.0046 142 343 142 22

<.5

.0044 143 CODE:

29a 130 59

<.5

.0042 144 BAG = ORIGINAL SAG NUM5ER 272 126 25

<.5

.004 145 NCI = TOTAL RADI0 ACTIVITY IN 393 120 17

<.2

.0038 146 BAG IN NANOCURIE5 32a 117 33

<.5

.0036 147 NCI/KG = SFECIFIC ACTIVITY OF 309 116 15

<.5

.0034 148 BAG IN NANCCURIE5 PER.r.ILOGRAM 329 110 7

<.5

.0032 149 DR = MEA 3URED MAXIMUM DO5E RATE 371 108 34

<.2

.003 150 IN CONTACT WITH BAG IN MREM RER 232 105 23

<.5

.0029 151 HOUR 385 101 13

<.5

.0027 152 FR.RT. = FRACTIONAL PFOT OF 376 99 16

<.2

.0025 153 TOTAL ACTIVITY OF BATCH THAT I5 207 94 67

<.5

.0024 15a IN THE BAGS SELOW THAT LISTING 269 94 10

<.5

.0022 155 RNK = ORDER RANK OF SAG 545ED ON.

2G3 86 la

<.5

.0021 156 TOTAL ACTIVITY 213 86 7

<.5

.0019 157

'225 86 24

<.5

.0018 158 240 Sa 7

<.5

.0017 159 THE TOTAL RADIGACTIVITY IN THE 37-Sa 10

<.5

.0015 160 EATCH IS 615079 NANOCURIES 3 9 2~

79 7

<.1

.0011 161 THE TOTAL WEIGHT OF THE BATCH 2 5 '.

72 13

<.5

.0013 162 I5 1446.2 KILOGRAM 5 371 71 la

<.5

.0012 163 3

.s 317 63 3

<.5

.0011 16?

THE AVERAGE 5FICIFIC ACTIDT;T 252 62 16

<.5

.001 165 OF THE SATCH IS 425 NANOCURIES 367 57 11

<.2

.0009 166 NANOCURIE5 FER KILOGRAM 365 52 5

<.5

.0006 167 255 50 12

<.5

.0007 165 222 47 13

<.5

.0006 169 375 37 5

<.2

.0006 170 241 31 4

<.5

.0005 171 359 31 12

<.2

.0005 172 325 30 a

<.5

.0004 173 295 25 5

<.5

.0004 171 352 25 a

<.5

.0003 175 347 27 6

<.5

.0003 176 359 21 4

<.5

.0002 177 343 22 5

<.1

.0002 178 319 21 2

<.5

.0002 179 296 la 5

<.5

.0001 150:

[

B-6

.m._.

t..

i a

Table B-3 Part 1 RANK BY TOTAL ACTIVITY - 3RD 200

-..;. =~

r-2--....-v

_, :. n..,,

.c

,. h _s _

.l,.

r C+

N._T.

- N K.

=n r

d e.d.c**wmma<w.Ge6.Me@d#w2uwamosaissen

e. t r

s. e. s= ~

-s, s.e 1

3--

4

.3

- 4

..s

. s.<. < 1_

2. 4

. =. - -

w.,.e.,4w m ww....-

. g...

e e.-~-

p*.*-.

= y.

=. s% :

s _3.

.4

.c

.w.

s a

=

3 e-"M -

"W " mnus s=<

e s,.=

. O.

.4 3

=_ s s sa<.

s__.

C J, r

r. a. :.

sas.

e_ a 93 3

. L g = =.

=_.

.L.

w

=. = a s =. = s.s

.4 s 99 s3

-a e r., =. 1

.e

c. e..

sws=s sr4 (4

. w =. =. =, os

-a t

34 4

w rs -

.s w

w

.3 s =. r g.

_7...

e_

0.,r.s w r.

e_ g s a0 4 w==

se u

3-.

.e

. c3 -

w.

ee es J

.. = _

=. - - s

=.s=.

13--

c

. s

-a=s Un. s= c =s 4

.s

=q-

.a c. e..:

4:

-..a q6

. s e w.3 p,

a=. =

ws:

s. =. m n.

g. s=;

=.. e

~. -.

.=.

m=

g=

s z. w..-m s. s.

y 6

.s

<r

_w 4

=., ;

3

-3 4

3

.e-se 0.C_

4 3

e m

sa

. a. c. =

4.=.=

.4

.0.==.=.

2

..

g

.s..

. s s,.

s

.s s

se W

b.a L3.. ;, s.

p

c. r 44.

4a-s,. 4

. n =_ J, 3

• <w

. s.,

s

..4 2 4 =a r

.wa

,C s

.-. =.

a am..s

- w

..=.=s q.s-

0.. =, =_ D. ;.

e....,-

. u s.

a

.=

=.

. n e...s

,4 v

s s

4.

-.s s. w==. =_ s.=-s

.. _ =

-3 Jr sr

.4

. V, r.,

C me s,

m

=

s. s.4 =.

.s.=.

,=

0., s s-.

3 a.t

.3.s a.

4 s_-

5.4

.0 w

~,.1

=. s h3%

a s.=.4

=

s s

.=

3.=_

3.

w 4

w w. g e *.=.

.e q

. s.

3 3.t r =s

.b.

3r

. L e. = =

3 s

-=.

q C.D

=~.

.e.e

=.4=.

4 s

Jsw s.

.0 s.s

= c.

=. s% _:

.er

4. 1

c. a...t 3 -

e s

na c

4 -

(. s=

s..

c..= s-r**-

4 -..

=. =r :. =..s.

s =..

4 a. :. s s. e.

.e.s

=.s_

4 mg s. =.

. s =.

.s

. w

• s.3 3.m e.

w f s

..t.?

_1

.t 0. c..-. ;

.e.4 r..*=

• . c =

3. s r.

q.e.

a. e. 9 e.

4.

..?-

_-: = *:

41 s

4 3

. L

s. g w

.c s _-

s 3*

4.a

(. e.

.wJOg

.e.s.

a===

-=

6 w

w s

e w

3 F

.w.

s

--sv

=. * = _..=s.=_

.*s_

Q. =. =. 1 T_

. C.

=..?

.. 4.S =.

.= w 9

M 9=

. a.S,.

<s g

7 *

=. ~. s%

.14 r*.

. <.? i s-..

s e..i =. 1

.e 4,=

eag.

..sr

(.9

. O 's = e*

0 t_

s

.w..

=. =. =.s.

1--

e. =. 4 9 9. s*

q.c1=.=

9%=

=_

a. C. s.1.:

1.=

9.

4.

c. = c=

_4m..

.t a.

. s-9-

. m.5 g

_=.4 w

4 w--

s w.

• .a

.. s 2

4 %:

.. z. s.

p.

s.

(. c.

. a.t.s.=

.=s

. s s. =....n.=

-.=

s.*.=

s c

=.....

s

.ss.

s a.

=.

0 =<

. a.s -=

s.3

-sm

. 3 3.,.t

=

s

.fs.

6.-

_m s..

3 e.1

.m. *. =. 3

c. a.

. = =. =.

s,. =.

w

=. _ w

. s =. 3 as w

r q

., 3 3

=

e s o s.=

s s.

w..

s

.=.

-=s

=.

3

+

%--=

=a

=. s.$

e. -.-

_.=.r.4 se 2.4 r s.e

e..= =.

at:

4-=

re.=rs=.

w.

w.

s s,.-

.< s e.

. s a. r e-s_

m 3

==

=

. s, a s, OS

s. w r

s..=.

. n._

.sc.=;

a s

s

• .=.,

= s

. 4.--

.s.*..=

3 c.

3 a...

C. s.

4_O

. w, :

. w n.., ;

= s. =.

w.*ss s-w

-=

=.

=..:s

. : r.

=.

3 7-

-=.T-

. =. s.. U r =_

s. =.

e_ s- -

c

.0

. s.s t :

O c.

.- =,.=

r =e s s 1

• 9-3-

3--

=r

. =

-. = -

s. 3.=

a

.w;

. L s..

s.0 r.

r

.e

. =.

s.1Y..

==

,s-4 3

3

=. =.. -

. =. _ -

s.O a.S_r Y

<w.

se; es;

.Us.

5 e

..a

-...=

4 c. -

(. =.

. s c.s.

3-

.4 s,

s_. =-

e. r s,

<s

.. = =.r..s. -...=a.-

3=

=

.s r

p =.,.

. a.

.q 3w a s. =.

r. s_

w.

.w.

w.,4

.s.

3=

ora r.rs wr

.w.

w..se.

s.4 tcw

.a

. O s., e_

r. J s v, r

. --a.

.= s.=

.s. 5 -swr

.1 g.34,

3U

=..=s g =_

s 4-.

3

.L-

. L s(3 d

3-s s

=.. = -

s-Y s* s*

..=

7

. C. e. a.v.s=s s

s

..=

s 1-t s- ;

y

_rm

(..,_

.g.4 _rw 5

. - =.

s s.

0.3

.,=.

.,. s,

=_

...s

. = -

s 3 e.

C O.,

s

.s

. 013.,

3:

3

. s.?

s,3. s.1 :-

1.,.1

- =.

_= =. c. a.

9 1 _=

c. w=.:

(. e.

.i _= 3 ws

. 0, l e,s r_ =,

.==.=r.

s..a3=.

3 s.

a.

r

(..,

s rs.

ew.

=. =.

• z e..

=.

.C p.

sw

. =.

..=.1.=

. =.

s._.=

=

7=

.r -

s.c,,.=

a, s s

. a =.

. s.4 : =

a

_.s.=

9=

s_

. =.. -

. =.

s.:

c. r

=..s

. Lw.

.s314.4

.v a,c w

s

_s r

m -*

.s.

ws

=.. = =.

a m. s,

.

4.S 3

a

.s=.

. s.4 =.

, a 4._

.w_s wes_=.

3 s=

s=

m..

., s,

2. =.

.=.s4.-

s a=

a e

. L,.4 3

=

s.

es.

tes s

4 3

s,_-

s,

..

.4 w

.ws

.= 5::

..s.

e w =_

m 3

s

= :

.L1

_4 3 3

.=.1

.=_ :

.a s

,s

- :. =

_ = * :

. s:a e s =.

3 3

=_

. = =.

.-s.

s..:..s.s

.w c=

. L.3. e.

3 a

g s

. s =. q --.,

a

., a sess 4

=_1

.3..-

a..

a.

:.3 J

i.O

.w;

. C.,;

.s;-

3 3

..sr 4 t

..

4.

=_ :

= e.,

,.. -0,.

. 0.4s 4 m e.

s, c,

.= s.,..,.

w.:,._

w

-s

. L _:

= _ = _ -

- =. =. :

3:

..s w..s

, =.

=.,r.,

4

.0 4.., -

_4 s.

ss w,

_m..

.u_ _

=.

. a.4 4 4a=

_s...

-s v. 1..= s,s =_

w ws

=.s.,=-

= s.

4

=.

r.-

2,_=

=..

,.w,=.

..0.,.0.-

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Table C-2 Part 2 RANK BY CONCENTRATION - 2ND 200

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4.

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