ML19330A807

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Sixteenth Progress Rept of Tx A&M Univ,Nuclear Science Ctr, 1979
ML19330A807
Person / Time
Site: 05000128
Issue date: 06/30/1980
From: Bates E, Feltz D, Taft J
TEXAS A&M UNIV., COLLEGE STATION, TX
To:
Shared Package
ML19330A803 List:
References
ORO-4207-13, NUDOCS 8007290475
Download: ML19330A807 (80)


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900729o475 l SIXTEENTH PROGRESS REPORT L 0F THE TEXAS A&M UNIVERSITY NUCLEAR SCIENCE CENTER E

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SIXTEENTH PR00RESS REPORT of the TEXAS A&M UNIVERSITY NUCLEAR SCIENCE CENTER January 1, 1979 - December 31, 1979 Prepared by E. F. Bates D. E. Feltz J. P. Taft

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1. L. Walker I and the Nuclear Science Center Staff Submitted to U. S. Department of Energy I Texas A&M University and by John D. Randall, Director Nuclear Science Center Texas Engineering Experiment Station College Station, Texas June 1980 80072904f

Table of Contents Page I I. Introduction 1 II. Reactor Utilization A. Utilization Summary 2 B. Utilization by the Texas A&M University I System 2 C. Other Educational Institutions 6 I D. Non-University Institutions 10 III. Facility Operations A. Facility Safety and Operational Improvements 13 NSC Employees Complete Fire Training Course Improved Radio Communications to Handle Emergencies B. Improvements to Reactor Systems and Experimental Facilities 13 Console Changes and Improvements New Core Loading Reactor Bridge Yoke Wheel Lock Overflow Pipe for Liquid Waste Holdup Tank Lab No. 3 Pneumatic System C. Operational Problems and Solutions 16 Demineralizer Resin Problems Reportable Occurrence - Failure of an Experiment Scram Circuit D. Changes in Operating Procedures 17 E. Unscheduled Shutdowns 18 I F. Reactor Maintenance and Surveillance 18 i

Page IV. Facility Administration A. Organization 22 B. Personnel 22 C. Reactor Safety Board 25 Appendix I Description of Projects Utilizing the NSCR Appendix II Publications, Theses, and Papers Presented at I Technical Meetings Which Involved Use of NSC Facilities From 1976 to Date Appendix III Environmental Survey Program and Effluent Release Summary and Personnel Exposure I Summary Appendix IV Universities, Colleges, Industrial Organizations, Government and State Agencies I Served by the NSC During Sixteen Years of Operation Appendix V Texas A&M University Departments Served by the NSC During Sixteen Years of Operation I ,

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LIST OF TABLES AND FIGURES Page Table I Reactor Utilization Summary 4 Table II Academic Use of the Reactor 8 Figure 1 Yearly Reactor Operation 3 2 NSCR Core VI, 87 FLIP Elements 15 3 The Nuclear Science Center Organizational Chart

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E b I. INTHODUCTION The Nuclear Science Center is operated by the Texas Engineering Experiment Station as a service to Texas A&M University and the State of Texas. The facility is

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available to the University, other educational institutions,

- governmental agencie.,, and private organizations and individuals.

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This report has been prepared by the staff of the Nuclear Science Center of the Texas Engineering Experiment Station to satisfy the reporting requirements of USDOE

[ Contract Number DE-AC05-76ER04207 (formerly EY-76-C-05-4207) and of 10 CFR 50 59 The reports covers the period from January 1, 1979 through December 31, 1979 I Reactor utilization continued to grow during 1979 with an increase in the total number of irradiations, sample irradiation hours, number of samples irradiated, and total experiment hours. Reactor operation of 85.71 Mw-days for 1979 was essentially the same as the previous year. The I reactor was not pulsed during the reporting period due to a restriction on pulsing until the fuel damage study is completed.

The installation of an operational full FLIP core was achieved during the reporting period. The full FLIP core provides increased core life and improved irradiation capabilities for experiments .

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2 II. REACTOR UTILIZATION A. Utilization Summary l

[ Utilization of the NSCR during the reporting period is l

shown in Figure 1 and Table I. Figure 1 presents reactor i operation from January 1962 through December 1979 During 1

[ the present reporting period the NSCR was used by more than 940 students and 33 raculty and staff members representing 19 departments at Texas A&M University. In addition, more l

{ than 230 faculty and students from 9 other educational institutions used the facilities, and 4,029 visitors were I

l registered during 1979, including 21 high school groups. '

r A total of 20 non-university organizations had programs that were dependent upon the NSCR.

During sixteen years of operation, the NSC has provided services to 35 departments at Texas A&M University, 99 other colleges and universities, 61 industrial organizations and 16 feceral and state agencies (See Appendix IV and V for listings).

B. Utilization by the Texas A&M University System During 1978'the following personnel from various depart-ments at Texas A&M University used the NSCR for research.

Appendix I describes the projects.

Chemistry Department Faculty and Staff: Dr. M. W. Howe, Assistant Professor 1 Dr. E. Sie fert , Post Doctorate Dr. Y. N. Tang, Associate Professor Dr. A. Clearfield, Assistant. Professor i Dr. T. Vickery, Professor i I Dr. R. Zingaro, Professor Dr. M. S. Mohan, Research Associate Dr. L. Kullberg, Research Associate Students: G. Harrison S. Johnson E. Ledger (Geology)

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TABLE I a REACTOR UTILIZATION

SUMMARY

1979 Annual Total

  • Number of Days Reactor Operated 239 Reactor Operation (MW-Days) 85 71 Number of Hours at Steady State 2187.19 Average Number of Operating llours per week 43 74 Total Number of Pulses 0 Total Pulse Reactivity Insertion 0 I Number of Irradiations 960 Number of Samples Irradiated 11,618 Sample Irradiation Hours 51,787.7 I Average Number of Irradiations per Operating Day 4.02 1 Irradiation Experiment-Hours 16,378.66 Beam Port Experiment-Hours 46.41 Irradiation Cell Experiment-lfoura 0 Total Experiment-Iours 16,425.07 Fraction of Utilization Attributable to Commercial Work 0.41 Number of Visltors 4,029 I
  • Note: 50 Weeks of operation Available I

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5 Oceanography Faculty: Dr. W. M. Sackett, Professor i Dr.

Dr.

B. J. Presley, Associate Professor D. Schink, Professor I Staff: Dr.

Dr.

P. Booth, Research Associate J. Trefry, Research Associate Students: R. Pflaum I F. Weber B. Taylor J. Pecon Center for Trace Characterizatlon Staff: Dr. D. Moore, Assistant Research Chemist Students: S. Johnson P. Andurer M. Yulo Geology Department Faculty: Dr. R. B. Scott, Associate Professor Dr. T. T. Tieh, Associate Professor Dr. W. Huang, Associate Professor Students: L. Tiezzi B. Bomber B. Toelle M. Miller E. Ledger S. Gowan D. Slater C. Conrad P. Whiting l Nuclear Engineering Department Faculty: Dr. R. D. Neff, Professor Dr. R. R. Hart, Associate Professor Dr. J. D. Randall, Professor Students: J. Harvill D. Davis S. Rottler S. Lee Nuclear Science Center I Staff: Dr. J. D. Handall, Director Mr. D. E. Feltz, Associate Director Mr. E. F. Bates, Health Physicist Mr. K. L. Walker, Reactor Coordinator I Mr. J. P. Taft, Reactor Supervisor Ms. M. G. Urbantke, Research Associate Mr. G. W. Waldrep, Research Associate Mr. J. W. Theis, Reactor Supervisor '

Mr. G. S. Staany, Assistant Reactor Supervisor I

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Animal Science Department Faculty: Dr. W. C. Ellis, Professor Dr. G. Finne, Assistant Professor Staff: Mr. John Snell, Research Associate

{ Students: Carlos Lascano V. Tenhet Industrial Education F

L Faculty: Dr. G. D. Gutcher, Professor Student: Ken Usiak

[ Radiological Safety Office r~ Staff: Dr. R. D. Neff, Radiological Safety Officer Students: J. Harvill D. Mayfield D. Davis Veterinary Physiology and Pharmacology Faculty: Dr. D. Hightower, Professor i

Staff: Dr. R. Badertscher, Clinical Associate l

1 Students: D. Hobson T. Lowery In addition to the research performed by the above personnel, the NSCR was used as an educational aid in numerous academic courses offered by the University. Table I Il indicates the academic courses and the number of students using the facility.

C. Other Educational Institutions I In addition to Texas A&M University, services were pro-vided to the following educational institutions. A descrip-tion of some of the projects utilizing the reactor is pre-sented in Appendix 1.

McNeese State University -- Lake Charles, Louisiana Experimenter: Dr. Jim Beck -- Physics Department McLennan Community College -- Waco, Texas Faculty: Mr. Don Tatum -- Physics Department Students: Physics Classes I

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Sam Houston State University -- Huntsville, Texas Faculty: Dr. Charles K. Manka -- Physics Department Students: Physics Classes

{ Moody College -- Galveston, Texas Faculty: Mr. J. Philips -- Marine Engineering Department Students: Marine Nuclear Engineering Class

_Blinn College - 'e nham , Texas Students: Science Club F Baylor University -- Waco, Texas Faculty: Dr. Ken-Hsi Wang -- Physics Department Students: Physics Class l Texas State Technical Institute -- Waco, Texas '

Faculty: Mr. Carl Kee -- Chairman, Nuclear System

, Technology Students: Nuclear Technology Classes Texas State Technical Institute -- Harlingen, Texas Faculty: Mr. Pedro Jimenez -- Chairman, Nuclear Technology Students: Nuclear Technology Classes University of Texas at Austin Experimenter: Ms. Solveig Turpin Ms. helinda Urbantke

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r 8 TABLE II y ACADEMIC USE OF THE REACTOR i

" UNDERGRADUATE COURSES I Student Student L Credit Number Credit Reactor Reactor Department and Course Hours Students Hours Hours Hours r

CHEMISTRY 106 Chemical Perspectives 4 417 1668 1 417 NUCLEAR ENGINEERING 101 Engineering Analysis 2 26 52 1 26 r 405 Nuclear Engineering Experiments 44 132 3 132 L 408 Principles of Radlaslon

, 3 Protection 3 18 54 3 54 E 402 Nuclear Detection and Isotope Technology 3 39 117 1 39 485 Problems 3 1 3 14 14 j PHYSICS I

j 220 Modern Physics 351 Experimental Physics for Non-Scientists 4

1 90 22 360 22 1

1 90 22 350 Cultural Approach to I Physics CIVIL ENGINEERING 3 20 60 1 20 i

l 479 Power Plant Construet3on MARINE ENGINEERING 3 37 111 1 37 i

(Moody College) 305 Nuclear Marine j Engineering 3 l '> 45 1 15 MECHANICAL ENGINEERING 417 Power Engineerinc 3 14 42 1 14

, AEROSPACE ENGINEERING i

312 Materials Science 3 37 111 1 37 ENGINEERING TECHNOLOGY 308 A Study of Modern i Industry 3 79 237 1 79 i

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L_ GRADUATE COURSES E Student Student L_ edit Number Credit Reactor Reactor Department and Course .aurs_ Students Hours Hours Hours _

[ NUCLEAR ENGINEERING 606 Reactor Experimentation 3 10 30 66 660 y 691 Research 12 2 24 11 22 i

ARCHITECTURE 633 Environmental Controls Systems 3 38 114 1 38 INDUSTRIAL EDUCATION j 691 Research 23 1 23 29 29 VET. PHYSIOLOGY 691 Research 6 1 6 29 29 i PLANT SCIENCES t

l 609 Quantitative Plant Physiology 4 5 20 1 5 INDUSTRIAL ENGINEERING

, 689 Industrial Construction 3 10 30 1 10 Totals h 247 138 793 4

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High School Tours No. Students Somerville High School -- Somerville, Texas 14 North Lamar High School -- Conally, Texas l Falfurias High School -- Falfurias, Texas 6

14 Richfield High School -- Waco, Texas 8 Ula High School -- Abilene, Texas 18 I Beaumont High School -- Beaumont, Te. xa s Elkhart High School -- Elkhart, Texas 58 18 New Waverly High School -- New Waverly, Texas 31 Hardin-Jef ferson High School -- Sour Lake , Texas 13 Allen Academy -- Bryan, Texas 38 Brazos Valley Science Fair -- College Station, Texas 20 Gatesville High School -- Gatesville, Texas I Huntsville High School -- Huntsville, Texas 9

24 East Bernard High School -- East Bernard, Texas 38 Grapeland High School -- Grapeland, Texas 12 i Normangee High School -- Normangee, Texas A&M Consolidated High School -- College Station, Te xas 8

14 Career Day -- Texas A&M 118 I Bryan High School -- Bryan, Texas Sharpstown High School -- Houston, Texas 7

34 Snook High School -- Snook, Texas 34 D. Non-University Institutions National Aeronautis , and Space Administration -- Houston, Texas Experimenters: Dr. D. P. Blanchard D. E. Robbins D. Teasley Nuclear Sources and Services -- Houston, Texas Experimenter. R. D. Gallagher Shell Development Company -- Houston, Texas I Experimenters: J.

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Whlte Skrivanek J. Keenan Gulf Nuclear -- Houston, Texas Experimenter: E. Acree M. D. Anderson Hospital (University of Texas Medical Center)

Experimenter: J. Cundiff I

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L Experimenter: J. D. Fandall Oklahoma Medical Examiner Experimenter: J. D. Handall I

' U. S. Air Force m Experimenters: R. Shaprey J. Taft G. Waldrep Core Laboratories Experimenters: J. Jackson K. Walker G. Waldrep Todd Research E

l r- Experimenter: E. Bates 7- LGL, Ltd.

L Experimenters: D. Plitt K. Walker Spectronics Experimenters: M. Morrow .K. Walker M. Urbantke E-Systems Experimenters: E. Paschetag M. Urbantke K. Walker Exxon Corporation Experimenters: J. Randall M. Urbantke Bureau of Economic GeologE Experimenter: 1; . Walker Pacific Gas and Electric Experimenters: D. Serpa R. D. Neff M. Urbantke j Monsanto f

Experimenters: J. J. Shteh M. Urbantke K. Walker Nuclear Laboratory Services Experimenter: J. D. Randall l

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I 12 i Radian Corporation Experimenters: B. F. Jones K. Williams M. Urbantke K. Walker Balcones Research Center Experimenters: S. Turpin M. Urbantke K. Walker I

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r III. FACILITY OPERATIONS A. Facility Safety and Operational Improrements NSC Employees Complete Fire Training Course f Several individuals from the NSC reactor operations group and l I

maintenance group completed a fire training course for nuclear reactor operators. This course was developed by the staffs of the NSC and the Brayton Fireman Training Field and was offered l

g through the Texas Engineering Extension Service. The one week g courses involved partici. pants from various nuclear power utilities across the nation. Thes. courses will be offered again in 1980.

The NSC now has employees trained in basic fire fighting to provide the necessary initial response to fires in those areas critical to reactor and plant operationo. i l

Improved Radio Communications to Handle Emergencies Radio communications between the NSC and the University j Communications Hoom has been upgraded by the installation on campus I of a radio frequency repeater system. The system utilizes coded transmissions that eccentially eliminate inverference from other I

radio networks in the area. Additional versatility was obtained by I the addition of a battery powered portable radio at the NSC. This replaces a base station unit previously in use. Telephone and radio remain the primary means of communications during the handling of emergencies at the NSC.

B. Improvements to Reactor Systems and Experimental Facilities Console Changes and Improvements

a. New shim safety rod drive control units were installed in j the reactor console. The units provife an improved display
5 of the carriage movement and control r ~ positions and j utilize an improved switch design. The rod position

!g indication was converted from a 0-40 cm scale to a digital j display of 0-100%. The control rods can be repositioned i to within an indicated 0.1%. The rod drive switch function

) was modified to provide separate switches for rod up and rod down movement. The rod down switch was changed to a i momentary contact type and does not latch as in the i previous units.

b. A new reset panel was installed to improve the display
and the reliability of switches. This unit provides ig separate switches for acknowledgement of alarms on either j

the " Main Panalarm" or the " Auxiliary Panalarm".

function was added for the temperature scram and the a reset j magnet power reset switch was relocated to provide easier access to tne operator.

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c. Individual shim safety rod drop switches were added to

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- the console to improve procedures for calibration of control rods by the rod drop method. These switches p are located on the left side of the console on the L voltage supply panel. This panel is behind a door whio" helps prevent accidental activation af the switches.

d. The air cooling and filter system for the reactor console was modified to reduce dust collection on instruments.in the console. The new system draws cool air from the building air conditioning duct, filters the air and then delivers it to the incide of the console. This creates o positive pressure in the console cabinets and air exits the lower portion of the rear doors. This is a considerable improvement over the old system which created a negative pressure inside the console cabinets resulting in un-filtered air being drawn across instruments through cracks and open panels on the console. The dust problem was eliminated by the new system.

New Core Loading I The first NSC TRIGA reactor loading containing all FLIP fuel was performed in November 1979 The loading was designated Core V and contained 83 elements with a total excess reactivity of

$2.90. This was not sufficient excess reactivity to maintain an I operational core and meet utilization requirements. The loading was modified by the addition of 4 FLIP elements. This loading was designated Core VI and contains 87 elements with a total I excess reactivjty of $5.73 Figure 2.

The Core VI loading is shown in Inct eased utilization was achieved by providing irradiation positions (flux traps) on the periphery of the core.

I These positions are vacant fuel bundle locations approximately 3" x 3" in cross sectional area. There have be>n no operational problems with the new core loading.

Reactor Bridge Yoke Wheel Lock A locking device has been installed on the crank wheel which 1 I operates the movable yoke on the reactor bridge. The crank wheel is used to raise and lower the reactor frame structure for re-positioning of the reactor. Following relocation of the bridge I

the yoke is lowered until the reactor frar.. rest firmly on the

floor of the pool. The bridge yoxe lock is keyed the same as i the bridge rail movement lock.

Overflow Pipe for Liquid Waste Holdup Tanks f A four inch PVC pipe was installed connecting the tops of

! liquid holdup tanks #1 and #2. These 5,000 gallon tanks are

! placed in alternate service by manual valve control. When the ,

! tank on line to the sump pump reaches approximately 90% full it is 1 iE v Aved ff and the second tank in placed in service. Accidental ig k j

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FIG. 2 NSCR CORE VI, 87 FLIP ELEMENTS ji

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overflow of a tank in service is handled by the interconnection of the two tanks. The probability of both tanks being full at the same time is very small as the tanks are under a daily surveillance program checking for tank levels and draining requirements.

Lab No. 3 Pneumatic System The pneumatic system for lab No. 3 uranium analysis was up-s graded to an automated sample irradiation and sample counting system. In the near future an automatic sample loader and a system to automatically transfer the sample to storage after

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counting will be added. The new system uses polyethylene tubing i of 1" 0.D. and 7/8" I.D. for the sample line. A new irradiator L was fabricated for positioning in the reactor core. The system was designed to utilize the existing pneumatic system programmer

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located in the reactor console. A sample diverter was developed

_ for routing to the shielded detector system for counting. Air I cyclinders are used to position the diverter using a sequence of

~ signals supplied by the pneumatic system programmer. Similar signals will be used for operation of the automatic sample loader and the sample storage systems.

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C. Operational Problems and Solutions

  • l Demineralizer Resin Problems l The cation and anion resins of the mixed bed demineralizer

] have reached a very poor performance level and their replacement g) is planned for early 1980. To improve the performance until replacement it was necessary to treat the resins with a saltwater solution. This treatment resulted in improved separation of the resins for only one or two regenerations. At present the only way

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to achieve a separation for regeneration is to backwash the resins

% for extended periods of time. The resins have been in service ~

for approximately five years and have operated at a capacity much r lower than expected. The replacement resins will be selected on the basis of their ability to provide easier separation and deliver higher capacity while maintaining high purity water.

Reportable Occurrence - Failure of an Experiment Scram Circuit On 15 June 1979 during surveillance testing of scram circuits, an experiment scram circuit failed to function properly. The s circuit is associated with the Beam Port No. 4 neutron radiography cave entry dool. This circuit provides a reactor scram upon entry if the reactor is positioned within 18 inches of the beam port target. The reactor was not operating at the time. The failure of the scram circuit was due to a malfunction of the " Experiment Scran Reset" switch on the reactor console. The switch failed to mechanically switch contacts. Dust was observed on the moving parts of the switch. The switch was cleaned and immediately functioned properly. Other switches on the reset panel were also I

17 ( cleaned to prevent possible malfunctions. The switch was tested daily for the next 5 days of reactor operation without a failure. This problem is not expected to recur due to a recent change { in the reactor console air cooling system as discussed in Section B of this report. D. Changes in Operating Procedures Amendment No. 7 to Facility License R-83 was approved pro-viding a change to the Technical Specifications which authorizes ( the irradiation of explosive materials in the neutron radiography facility. The subject of fire and subsequent damage related to the handling of explosive materials in the neutron radiography [ facility received considerable attention by the NRC. In the interest of industrial safety and the protection of equipment the NSC will implement a smoke detectar system. The system will provide a means of detecting smoke in the reactor cable tray area and the _ central exhaust system. 1980. This system will be in operation in early [ , The following changes to SOP's were reviewed and approved by the RSB during the reporting period: SOP Number { Subject I-A Definitions and Abbreviations ( Figure I-C-1 NSC Administrative Organizational Chart I-G Distribution and Binding [ II-A General Organization and Responsibilities Figure II-A-1 { Reactor Operations Administration II-C Reactor Startup [ Figure II-C-1(a) and (b) Pre-Startup Checklist Figure II-F-1(a) and (b) Daily Shutdown Checklist [ II-G Movement of Reactor Bridge II-I Reactor Core Manipulation II-M Response to Alarms [ Figure III-I-2 Semiannual Scram Circuit Test III-L Control Rod Drive Maintenance F L IV-E Irradiation Cell Experiments Figure IV-E-3 r L Checklist for NSCR Irradiation Cell F l v.

a 18 [ E. Unscheduled Shutdowns A total of ten unscheduled shutdowns occurred during 1979 The unscheduled shutdowns can be arranged in the following categories: Cause of Shutdowns Number of Shutdowns { Building power loss 3 Instrument malfunction 3 Operator error 2 Control Rod Drive Magnet Failure 1 [ Technician Inadvertently Initiated 1 F. Reactor Maintenance and Surveillance

1. A calibration of the fuel temperature measuring channel was performed on 1-12-79 The LSSS was set at 525 C

[ (975 F).

2. A channel check of the fuel element temperature measuring

(. channel was made daily by recording the fuel element temperature and the pool water temperature prior to reactor startup. 3 The control rods were cal.ibrated as follows: Core IV-B (2/19/79) Control Rod Rod Worth ( SS #1 $2.84 SS #2 2 30 {- SS #3 3 31 SS_#4 4.43 RR 0 59 Shutdown Margin $1.03 m E [

F 19 L r-L Core IV-B (4/2/79) c Control Rod Rod Worth L SS #1 $2.72 SS #2 2.42 SS #3 3.25 SS #4 4.49 L RR 59 Shutdown Margin $1.13 I L Core V (11/1/79) , r- Control Rod Rod Worth I SS #1 SS #2

                                                               $2 33 1.95 SS #3                         2 72 3                                  SS #4                         3.45 RR                            0.61 Shutdown Margin                $4.11 Core VI (11/12/79)

Control Rod Rod Worth SS #1 $2.04 SS #2 1.69 SS #3 3 26 I SS #4 4.57 RR 0.46 Shutdown Margin $1.18 l

4. The reactivity worth of all experiments was either l estimated or measured, as appropriate, before reactor operation with the experiment. The most reactive experiment irradiated had a worth of -344 5 Pulse tests were not performed during the reporting period due to the non-pulsing restriction initiated on 1 October 1976. This restriction has been enforced since the discovery of damaged PLIP fuel elements ad-Jacent to the transient rod.

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6. The scram times of the control rods were measured with the l p following results: i Date Control Rod Time In Seconds I l-24-79 SS #4 0.69 L

2-15-79 SS #3 0.68 p SS #4 0.62 3-7-79 SS #4 0.59 l 3-23-79 SS #1 0.59 I [ SS #2 SS #3 SS #4 0.66 0.66 0 70 l 1 6-5-79 SS #2 0.68 6-15-79 SS #2 0.68 5 9-14-79 SS #1 0.65 f SS #2 0.66 SS #3 0.71 SS #4 0.66 l I 10-15-79 SS #2 0.68 7 A channel test of each of the reactor safety system h channels for the intended mode of operation was performed 1 I prior to each day's operation. tested weekly. s The pool level alarm was 'g 8. Channel calibrations were made of the power level monitoring g channels by the calorimetric method as follows: 1 4 CHANNEL CALIBRATIONS Indicated Actual l Date Power Power  % Error Core Loading 1-5-79 400 379.0 -5 3 IV-B I l-2-79 405 385.5 -5.0 V (new core) 11-9-79 400 319.5 -25.0 VI (new core) i j 9 The ventilation system was verified to be operable by I conducting a test of the system each week throughout the year.

10. Emergency evacuation drills were cenducted on 8-2-79 and

'I 12-12-79 ! 11. Checks were performed to verify that the NSC security alarm system was operable each week throughout the year. i I

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12. Calibration dates for facility air monitors and area radiation monitors were as follows:

Monitoring S;* stem Date of Calibration ( Ch #1 - Stack Particulate 6-19-79 Ch #2 - Fission Product 3-29-79 { Ch #3 - Stack Gas 8-31-79 Ch #4 - Building Particulate 2-2-79 Ch #5 - Building Alpha 2-2-79 [ Ch #6 - Building Gas 8-31-79 Area Radiation Monitors 4-5-79 [ 13 Three intrusion drills were conducted during the reporting period. The drill conducted on January 30, 1979, re sulted in a good response time by the University Police. How- [ ever, the radio operator requested that procedures be reissued in a new format to prevent misinterpretations. This was done and the drills conducted on March 26, 1979, ( and December 5,1979, were very satisfactory. The intrusion drill conducted on March 26 was audited by a member of the Reactor Safety Board. [ 14. A review of the NSC security plan was conducted by the NSC staff and the Reactor Safety Board in January 1980. During the reporting period new procedures were implemented [ to improve security. It was noted that NSC and University personnel conformed to the new procedures very quickly. New equipment to further improve securit _s planned to ( be operational in early 1980. The RSB was informed that the NSC is considering the use of video tapes to improve _ the training of University Police and NSC employees involved in security o f the NSC. It is hoped this system will be available by the end of 1980. [ [ [ E-E E r I

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22 IV. FACLLITY ADMINISTRATION A. Organization The organizational chart of the Nuclear Science Center is presented in Figure 3 During the reporting year Greg Stasny received his senior reactor operator license and was promoted to Assistant Reactor Supervisor. Dan Rodgers received his reactor operator license and was assigned to the second shift. Ken Walker, Dale Rogers, and Gary Waldrop received their senior reactor operator license during the reporting period. Gary Waldrep and Melinda Urbantke received their Nuclear Engineering degree and have been assigned as Research Engineers. Russell Schroeder joined the reactor operation's staff as a half time reactor operator in training for licensing. Randy Woelfel resigned from his position as health physicist and I was replaced by Gary Wiechering. The student worker turnover rate'was high as expectid, however, the NSC will continue to employ students part time when student co-op research aides are not available. B. Personnel The following la a list of personnel of the Nuclear Science Center for the period January 1, 1979 - December 31, 1979 Facility Administration and Reactor Operations Staff

        +Feltz, D. E.
                                    - Associate Director and Manager of Reactor Operations
        + Harris, C. E.
                                    - Reactor Operator (terminated)
        +Randall, J. D.
                                    - Director Rodgers, D. J.            - Reactor Operator I        + Rogers, R. D.

Schroeder, R.

                                    - Reactor Operator
                                    - Reactor Operator (trainee)
        +Staany, G. S.
                                   - Assistant Reactor Supervisor
        +Taft, J. P.
                                   - Reactor Supervisor

_ +Thels, J. W.

                                   - Reactor Supervisor
        +Waldrep, G. W.

- - Research Engineer M

[ [ [ [ . _ . DIRECTOR [ ASSOCIATE DIRECTOR SUPPORT MANAGER OF REACTOR GROUP RE A CTOR OPER ATIONS COORDINATOR [ l L_______ RFACTOR [ l SUPERV I SOR (S) I [ I L ._ __ __ _ _ _ SENIOR REACTOR OPER ATORS REACTOR { OPER ATORS E [ [ F FIG. 3 THE NUCLEAR SCIENCE CENTER L ORGANIZATIONAL CHART I L w g

24 Facility Administration an' Reactor Operations Staf f (Cont 'd)

                  + Walker, K. L.                                     - Reactor Coordinator
                                                 *L ensed Reactrv Operator
                                                 + Licensed Senior Reactor Operator Technical Service and Maintenance Allen, D. R.                                              - Electronics Technician Ball, J. R.                                               - Co-op Research Aide (terminated)                         '

l Bowers, W. W., Jr. - Mechanical Maintenance Technician l Clapp, D. J. - Student Worker II (terminated) Day, A. W. - Dra f tsman (terminated) Driver, G. D. - Dra f t sman (terminated) Echols, R. M. - Draftsman (terminated) Fickey, J. B. - Maintenance Worker II (terminated) Foster, C. E. - Student Worker II Greene, H. K. - Co-op Research Alde (terminated) Rorn, C. R. - Mechanical Equipment Foreman ~ l Jamieson, M. - Student Worker IV (terminated) Kearns, J. P. - Student Worker (terminated) Lavat, K. A. - Draftsman Neal, M. L. - Student Technician (terminated) Neeley, D. R. - Student Technician (terminated) Pedersen, P. V. - Student Worker II Price, J. E. - Co-op Research Aide Restivo, A. L. - Facility Maintenance Foreman Shores, S. P. - Student Technician (terminated) Stowers, S. T. - Student Worker II Talarico, M. A. - Student Worker II (terminated) Urbantke, M. G. - Hesearch Ene;1neer l Clerical i Mitchell, Y. - Secretary Westbrook, B. M. - Bookkeeper l l l

L 25 {- Health Physics Staff Bates. E. F. - Senior Health Physicint Holbrook, K. - Student Technician { Huereque, E. L. - Co-op Research Aide (terminated) Wiechering, G. - Health Physicist Woelfel, R. E. - Health Physicist (terminated)

       'C. Reactor Safety Board Committee Composition

{ Dr. R. R. Berg, Chairman, Professor and Director, of fice of University Research (January 1, 1979 - December 31, 1979) [ Dr. D. Hightower, Professor of Veterinary Physiology and Pharmacology (January 1, 1979 - Lecember 31, 1979) Dr. L. C. Northcliffe, Professor of Physics ( (January 1, 1979 - December 31, 1979) _ Dr. F. Sicilio, Professor of Chemistry _ (January 1,1979 - Decetaber 31, 1979) Dr. T. T. Tieh, Associate Professor of Geology (January 1, 1979 --December 31, 1979)

 -         Dr. R. R. Hart, Associate Professor of Nuclear Engineering (January 1, 1979 - December 31, 1979)

Dr. R. L'. Watson, Professor of Chemistry (September 1, 1979 - December 31, 1979) Dr. J. K. Gladden, Professor _of Chemistry (January 1, 1979 - August 31, 1979) Dr. H. R. Thornton, Professor of Mechanical Engineering (January _1, 1979 --August 31, 1979) {. Dr. R. G. Cochran, -(Ex-Officio), Professor and Head of Nuclear Engineering (January 1, 1979 - December 31, 1979) M .

[ [ 26 Dr. R. D. Neff, (Ex-Officio), Profeucor and University Radiological Safety Officer [ (January 1, 1979 - December 31, 1979) Dr. J. D. Randall, (Ex-Officio), Professor of Nuclear Engi-( neering and Director of Nuclear Science Center (January 1, 1979 - December 31, 1979) [ Meeting Frequency [ The Reactor Safety Board (RSB) met on the following dates during the calendar year 1979: 2/7/79, 6/15/79, 9/28/79 { RSB Audits _ During the reporting period RSB audits of NSC activities

 - were conducted on the following dates: 1/8/79, 3/26/79, 6/18/79, 9/19/79, 12/19/79 W

[ 2 7 [ W M F L E

~ u E L E L r L r APPENDIX I Description of Projects Utilizing the NSCR I~ I I ,I 4

I-l DESCRIPTION OF PROJECTS UTILIZING THE NSCR A. Texas A&M University Veterinary Physiology 1 F TRACE ELEMENT CHARACTERIZATION OF ANIMAL DISEASES Personnel l Dr. Dan Hightower -- Professor i l David Hobson -- Graduate Assistant I Biological tissue samples were irradiated in an attempt to determine any relationship between trace element levels and various animal diseases. Elements of interest in the study included Na, Cl, K, Br, I, Cr, As, Cu, Mn, and Zn. DETERMINAL ON OF IODINE IN VARIOUS BIOLOGICAL MATRICES Personnel 4 Dr. Dan Hightower -- Professor David Hobson -- Graduate Assistant The purpose of this experiment is to determine whether or not i protein bound and total iodine levels in various biological matrices (urine, blood, feces, saliva, etc.) can be measured accurately and rapidly using NAA procedures. The work is part of a federal study 1 on the possible detrimental effects of certain food colorings. Pigs are used as the experimental animal. I Veterinary Medicine DEVELOPMENT OF PROSTATIC IMAGING AGENT i i Personnel i 1 j Robert R. Badertscher, II -- Clinical Research Associate  !

Dr. Dan Hightower -- Professor l Dr. David M. Hood -- Professor l

The main objective of this project was to develop a prostatic

imaging agent with the Cog as a model. Our hypothesis was that Paloseln, a copper containing superoxide dismutase enzyme, could j be used as a labeled scanning agent which is selectively taken up

! by the prostate gland and externally imaged in neoplastic conditions. ! To accomplish this, we attempted to exchange activated 6'*Cu for the two copper atoms in the Palosein molecule, by adjusting the pH l l

I-2 C of the 0.1 molar sodium acetate solution down to 3.7 for 30 minutes, and then neutralizing the pH back to 7 0 with sodium [ hydroxide. The supernate was passed through a G-25 Sephadex column and 1.0 ml fractions were collected for approximately one hour. [ Radiological Safety Office - Nuclear Engineering Department [ DETERMINATION OF NATURALLY OCCURRING RADIONUCLIDES IN COAL AND COAL RESIDUES Personnel [ Dr. R. D. Neff -- Radiological Safety Officer and Professor _ Joe P. Harvill -- Graduate Assistant Due to the increased utilization of coal as a heat source for the production of electrical energy, an assessment of the naturally occurring radionuclide concentrations in ash products is necessitated. [ From this assessment, the possibility and degree of radiation hazard from either stack emissions, or perhaps directly from the waste disposal areas, may be evaluated. In pursuit of this goal, the { delayed neutron counting facility at the Nuclear Science Center was used to determine the uranium fraction of the sample. Also,

~

analysis for various daughter products in the uranium and thorium chains was accomplished by use of the counting systems in con-junction with the Scorpio computing system. DETERMINATION OF NEUTRON ENERGY SPECTRUM Personnel

~

Dr. R. D. Neff -- Radiological Safety Officer and Professor Don Davis -- Graduate Assistant Currently, personnel monitoring for neutrons requires detailed [ knowledge about the energy spectrum of the neutron field in question. As part of a project to . determine the best method for neutron monitoring at the NSC, a measurement of the energy spectrum near

~

the NSC neutron radiography facility was done. This employed a Bonner's Sphere system and a specialized computer program for data unfolding. The results of this project will allow determination of the energy range which contributes most to l neutron dose. Subsequently, other projects will lead to the mos, appropriate neutron monitor based on response to the measured spectrum. l I l

i I-3 Chemistry TRACE ANALYSIS OF CEMENTS Personnel . Dr. Thomas Vickery -- Assistant Professor Gabrielle Harrison -- Graduate AssLtant The trace elements analyzed will be used in the establishment of a procedure for the " fingerprinting" of cements . NAA is used here to acquire (1) a profile of the elements present in the I samples, (2) a quantitative determination of the concentration of the trace elements of interest. This information would complement any further data obtained from other methods. EQUILIBRIUM STUDY OF SODIUM-POTASSIUM-HYDROGEN EXCHANGE ON CRYSTALLINE ZIRCONIUM PHOSPHATES Personnel Dr. A. Clearfield -- Profc sor I Dr. L. Kullberg -- Research Associate Using the NSC for activation analysis, isotherms for the ion-exchange of sodium-potassium-hydrogen in crystalline zirconium l phosphates have been determined. The phases formed during the exchange were also identified. 5 TRITIUM AND SILICON-31 PRODUCTION PROJECT l Personnel Dr. Yi-Noo Tang -- Professor Dr. E-Chung Wu -- Professor Dr. E. E. Siefert -- Post Doctorate Recoil tritium atoms, generates from 3He(nep)3H process I with thermal neutrons from the reactor, reacted with organic compounds such as C H 5F, C 2H5 C1 and C-CgHe to yield products either from abstraction or substitution. The substituted products thus formed carried a large amount of residue energy. I The pressure dependence of the unimolecular decompositions of these substitutional products has been investigated under a very wide range of pressure including the use of large aluminum containers for low pressure studies. The results indicated that (1) essentially all excited molecules will decompose under a very low pressure condition, and (2) the fraction decomposed (or I stabilized) varied as a linear function of log P effective pressure, P The was calculated by takibh. into con-sideration the relatih,c,ollisional ocefficient of the component molecules in each system. Further studies on pressure effect i and the. analysis of energetics of these and other similar systems I are in progress. I m

i I-4 1 The reactions of recoil 31 S1 atoms formed by the nuclear transformation, 31 P(n,p)31Si, have been studied. I In such systems, it has been shown that recoil 31 Si atoms will abstract either H from PH 3 or F from PF 3 to give the corresponding silylenes, 31SiH 2 or 31SiF 2 The reactions of the silylenes I thus formed wi',h various conjugated dienes are the major concern of this program. It has been shown that these silylenes formed in the nuclear recoil system consist of about 20% singlet and I 80% triplet. The additipn of silylenes in all of these forms will add to conjugated dienes to give the corresponding silacy-clopent-3-enes. The relative reactivities of the butadiene, various pentadienes, and hexadienes are being studied and the I nature of a large steric effect observed in some of the addition reactions is under serious consideration. NEUTRON ACTIVATION FOR POTASSIUM IN METEORITES FOR 39Ar/40Ar DATING Personnel Dr. M. W. Rowe -- Professor Dave Aylmer -- Graduate Assistant By irradiating meteorite samples and standards, it is possible to determine the K, Ca, and K-Ar age of the samples. The analysis I 13 done with noble gas mass spectrometry. The 39K is activated and decays to 39 Ar which allows an accurate estimation of the K content. An estination of the 40 Ar level which decays from I 40 K, can also be made. Thus, the ratio of $9Ar/40Ar leads to an accurate calculation of the K-Ar age of the sample. Ca is included to correct for any interference with the K determination. Ages on the order of 4.5 x 109 years are expected. Center for Energy and Mineral Resources - Chemistry Department TRACE ELEMENTS IN LIGNITES Personnel Dr. Ralph Zingaro -- Professor Dr. Mysore Mohan -- Research Associate The present energy situation is a painful reminder of the urgent necessity of utilizing energy resources other than oil. It can be anticipated with resonable certainty, that increasing demands will be placed on coal and nuclear energy resources of the country. Texas lignite deposits occupy a unique place in this scheme since, apart from b71ng an obvious source of combustible fuel, they are rich in uranium. \ I \ I

i I-5 The primary goal of the project is to gain an understanding of the chemical nature of uranium in these deposits. The first steps will involve the preparation of enriched and unmodified I samples. Size-fractionation, density-gradient fractionation and flotation will be some of the methods used in the enrichment procedure. Facilities at the Nuclear Science Center will be used I to determine uranium content in these fractions by neutron activation analysis. The uranium-rich fractions will be examined by ultraviolet, infrared, Raman and mass spectroscopy to obtain specific information about the chemical nature of uranium in lignite. Geology MINE AND FORMATION DESCRIPTION PROJECTS Personnel Dr. Thomas Tieh -- Associate Professor Dr. Wen H. Huang -- Associate Professor Students working under the above faculty members performed various studies of the uranium concentration and distribution in I several different regions of Texas. Some of these were in areas where exploration and/or production of uranium is underway, others address regions where the potential for exploration is of interest. I The following did work of this nature using both the delayed neutron method for concentration assay and the fission-track technique for distribution analyses: E. Ledger (Ph.D) -

                                " Uranium in Volcan1 clastic Sediments of the Catahoula Formation of Texas" B. Bomber (M.S.)

I C. Conrad

                                " Uranium Mineralization Along a Fault Plane in Tertiary Sedimentary Rocks"
                       " Uranium in Igneous Rocks in Central Texas" S. Parks (M.S.)       " Distribution and Possible Mechanism of I               Urania 1 Accumulation in the Catahoula Tuff, Live Oak County, Texas" M. Miller (M.S.)       " Uranium Roll Front Study in the Upper Jackson Group, Alascona County, Texas" URANIUM LEACHING PROJECT Personnel Dr. Wen H. Huang -- Associate Professor I         Kendall Pickett -- Graduate Assistant B. Toelle -- Graduate Aesistant S. Gowan -- Graduate Assista. ,

,I D. Slater -- Graduate Assistant P. Whiting -- Student

                                                                              --_a

I-6 - This work addressed the feasibility of a particular method of leaching uranium from sandstones and lignites. The objective was to use neutron activation analysis to measure levels of uranium as well as other trace elements such as Mo, As, Fe, Ca, Te, Se, V, and Si in the product and wash. The work would ultimately help determine the selectivity of various leaching processes. TRACE ELEMENT ANALYSIS OF "t710US GEOLOGICAL REGIONS Personnel Dr. Robert Scott - u essor I Larry Tiezzi -- Graduate Assistant Jim Garrison -- Graduate Student, University of Texas Nel Tyner -- Graduate Student, University of Texas A series of studies of several areas of the world have been done to determine rare earth and trace metal levels throughout various types of rocks. These include mid-ocean ridge basalts, I hydrothermally altered basalts, igneous rocks from the Llano region of Texas, Arizona basalts, and rocks from the Deep Sea Drilling Project in the Pacific Back-Arc Basin. Data obtained are being used to study existing geological models and develop additional models and descriptive techniques. Oceanography DETERMINATION OF TRACE METAL CONCENTRATIONS IN SURFICIAL SEDIMENTS, MACRONEKTON AND SPINY OYSTERS FROM THE SOUTH TEXAS TOPOGRAPHIC FEATURES STUDY Fersonnel Dr. B. J. Presley -- Professor Dr. P. N. Booth -- Research Ase)ciate Dr. S. Schofield -- Research Associate I Robert Taylor -- Graduate Assistant Der Duen Sheu -- Graduate Assistant The NSC facilities were used to determine the levels of vanadium (V), barium (Ba) and other trace elements (when possible) in various sample types by neutron activation analysis. These samples included spiny oyster tissue (Spondylus Americanus) and both leaches and total digests of marine sediments. These samples were collected as part of the Bureau of Land Management's Gulf of Mexico Topographic Features Study. Most came from the I vicinity of the East Flower Gardens Bank. The primary purpose of these analyses is to determine baseline levels of trace metals in the biota and sediments from these biologically important These data will I fishing banks on the outer continental shelf. be used to evaluate the impact which present and future oil and gas exploration and production may have on these potentially

s I-7 sensitive reef communities. .The expected level of V in ( Spondylus samples is about 10 ppm. The levels of Ba and V in the sediment: samples should be 1300 ppm and 1100 ppm respectively. { URANIUM IN ANOXIC SEDIMENTS ON THE GUD COAST Personnel ( Dr. William Sackett -- Professor Frederick Webber--- Graduate Assistant {- A worldwide increase in nuclear power dependency and a continual depletion of high grade reanium ores are resulting in the utilization of lower and lower grade uranium deposits. For example, sandstones in the South Texas Coastal Plain with from [ 0.1 to 0.2% uranium are presently being mined. In the future, high uranium-bearing materials in the sea may become important economic sources of this valuable element. [ One potential source of uranium in the ocean is anoxic environments. Several studies have shown that there is more than { an order of magnitude uranium enrichment in anoxic sediments (up.to 0.01%). Anoxic sediments along the Gulf Coast such as found in the newly discovered Orca basin and in various estuarine and near shore environments may show similar or greater enrich-E- ments than those found elsewhere. Thus, the goal of this work is to determine uranium concentrations in sediments in various anoxic environments along the Gulf Coast in order to provide the [ data base'for the evaluation of anoxic Gulf Coast marine sediments as future uranium sources.

 ~

CESIUM. UPTAKE IN CORAL Personnel _ Dr. David Schink -- Professor Jill Pecon -- Graduate Assistant [ This experiment utilized Cs-134 produced at the NSC as a tracer in coral. During a cruise aboard the Research Vessel GYRE, corals were placed in plexiglass aquaria to which the cesium tracer had-been added. Every eight days, one aquarium was [- opened and the coral removed-for analysis. This involved digestion,- filtering, and counting. In this manner data was obtained concerning the incorporation of cesium from ambient hf waters into the tissues of coral.

                   ' SEDIMENT DEPOSITION MEASUREMENTS IN THE GULF OF MEXICO USING

{ Cs-137 Personnel- _ Dr. B.-J. Presley -- Professor-Ron Pflaum -- Graduate Assistant I g

- I-8 e

       .Using fallout Cs-137 as a tracer, sediment deposition was examined in the Gulf of Mexico. Samples were counted on equipment located at the NSC and data were obtained on the areas and rates

{ of sediment deposition. Nuclear Engineering Personnel Dr. Ron Hart -- Assistant Professor Steve Rattler -- Student Assistant ~ MEASUREMENTS OF 31P CONCENTRATIONS PRODUCED BY NEUTRON TRANSMUTATION DOPING OF SILICON

      *This work is a continuation of studies designed to measure the production of 31 P by irradiations of float-zoned silicon at

~ the NSC. The process is known as neutron transmutation doping. Measurements were made to calibrate the NSC facility so that ~ correlations between neutron fluence (irradiation time) and calculated dopant concentrations could be made. Work was also done on gallium-arsenide crystals. Animal Science I FLOW OF INGESTED FORAGE PARTICLES THROUGH THE G.I. TRACT OF CATTLE Personnel Dr. W. C. Ellis -- Professor John Snell -- Research Associate Carlos Lascano -- Graduate Assistant An experiment was conducted utilizing several different rare I earth radionuclides as flow markers of ingested forage particles through the gastrointestinal tract of grazing cattle. Isotopes used include 141 Ce, 169Yb, 147Nd. Ingested forage was collected from several surgically modified heifers grazing within university owned land. This material was then labelled with one radionuclide and introduced into each I animal's stomach. Collection of ingesta and feces was done, and these were prepared and analyzed or. a NaI(Tl) detector. From assay, information concerning particle flow was collected. PENETRATION MECHANISM AND DISTRIBUTION GRADIENTS OF SODIUM TRIPOLYPHOSPHATE (STP) 'N PEELED AND DEVEINED SHRIMP Personnel Dr. Gunnar Finne -- Assistant Professor Vick! Tenhet -- Graduate Assistant

I-9 ~ In a project sponsored by the National Shrimp Breaders Association, peeled and deveined shrimp were labelled with 32P to determine the distribution of the preservative STP af ter treat-ment. Shrimp were treated with .5% and 1% STP solution, frozen, ^ and sliced. Each section was counted on a scintillation detector to determine the distribution of STP from outside to inside. ~ Results showed that the STP tended to accumulate on the surface of the tissue preventing further uptake. At higher concentrations (5%-10%), prolonged treatment overcame the apparant barrier resulting in uniform distributions throughout the muscle. B. Other Universities Reactor Demonstrations The following groups visited the NSC in 1979 for a detailed  ; facility tour and demonstration of activation analysis capabilities. This included explanation Of techniques.and, in some cases, I activation of samples for observation or specialized applications such as forensic analysis. Institution No. Students McLennan Community College 93 l Sam Houston State University 40 l Moody College 15 I Blinn College Baylor University 27 8 Texas State Technical Institute (Waco, Texas) Fersonnel Mr. Carl Kee -- Chairman, Nuclear Systems Technology During the year, approximacely 25 students from the first and g second years of the Nuclear Technology Program came to the NSC for F. laboratory classes in a number of areas pertaining to radiation safety. Tne following laboratories were performed during 1979:

1. Neutron Activation Analysis
2. Neutron Flux Determination 3 Reactor Operating Experience and Instrumentation Study
4. Pool Water Chemistry Analysis 5 Radioactive Waste Analysis
6. Contamination Control I

l I-10 7 Personnel Dosimetry

8. Instrument Calibration and Survey 9 Air Monitoring System Study
10. Fixed Area Monitoring System Study Uniyorsity of Texas Personnel Ms. Solveig Turpin -- Research Associate, Balcones Research Laboratory With the assistance of the NSC staff, neutron activation analysis was used to measure trace elements in ceramic and clay samples from the south coast of Peru. It is hoped that this data can be used to determine associations that might indicate origins of these possibly preh.storic ceramic pottery samples. This might lead to further information on migratory habits of ancient tribes.

McNeese State University Personnel 1 Dr. Jim Beck -- Professor Using the NSC for irradiation services, neutron activation analysis projects were performed on geothermal brines. Saltwater I from deep gas wells in Louisiana which has a potential use as a thermal energy source were analyzed for trace metal content to determine possible harmful constituents. Another project was done for metal levels in home air conditioning filters to determine I normal exposures to pollutants. Texas State Technical Institute (Harlingen, Texas) Personnel Mr. Pedro R. Jimenez -- Chairman, Nuclear Technology Twelve second year nuclear technology students performed a one-day lab class covering neutron activation analysis, pool I water chemistry, and area radiation survey. C. Industrial Training Programs In addition to the activities described above, the NSC

n through the Texas Engineering Extension Service has embarked g on a program to develop a number of training courses for industrial organizations. These are primarily oriented toward
                                                                                 . . _ -   ~

E I-ll nuclear power plant and medical research personnel. A description of the courses in presented below. FIREFIGHTING FOR NUCLEAR POWER PLANT PERSONNEL Instructors Mr. Paul Hanneman, TEEX Mr. Gene Bates, NSC I Mr. Ken Walker, NSC This course uses the extensive facilities at the Brayton Fire-man Training Field for practical, hands-on training in the types of fire situations which might be faced by nuclear power plant fire brigades. Usually the brigade members have had little or no such experience. This is combined with the expertise and use of the NSC to present the particular problems of firefighting with radiation or radioactive contamination present. A combined fire / radioactive contamination exercise is conducted as a final exam. Three courses I were held in 1979 with representatives from more than 15 nuclear utilities in the U.S. and Canada. RADIATION SAFETY TRAINING Instructors Mr. Gene Bates, NSC Dr. R. D. Neff, RSO Mr. J. Simek, RSO Mr. G. Wiechering, NSC These courses are taught in conjunction with the Radiological I Safety Of fice (RS0). Depending on the program, instruction is conducted both at the NSC and other campus facilities. Courses taught in 1979 are: Applied Health Physics Training for Supervisory Personnel This four week on-the-job training course prepares supervisory personnel to establish and direct radiological safety programs. Four individuals from two nuclear utilities participated in 1979 Advanced Health Physics Technicians Training This course is designed for technicians who perform daily health physics tasks under professional supervision. Fifteen individuals from the U.S. Army participated in 1979

[ [ [ [ [ [ [ [ APPENDIX II [ Publications, Theses, and Papers Presented at Technical Meetings Which Involved Use of NSC Facilities From 1976 to Date [ [ [ m W [ [ E- . E

s o II-l Publications, Theses, and Papers Presented at Technical Meetings Which Involved Use of NSC Facilities From 1976 to Date

1. 0.F. Zeck, G.P. Genarro, Y.Y. Su and Y. -N Tang, "E f fe c t of Additives on the Reaction of Monomeric Silicon Difluoride with 1, 3-Butadiene," J. Amer. Chem. Soc., 98, 3474 (1976).
2. R.A. Ferrieri, E.E. Siefert, M.J. Griffin, O.F. Zeck and Y. -N. Tang, " Relative Reactivities of Conjugated Dienes towards Silicon Difluoride," J.C.S. Chem. Comm., 6 (1977).

I 3 M.D. Devous, Sr., "A Raniation-Induced Model of Chronic Congestive Heart Failure", Scott and White Hospital, Department of Radiology and Nuclear Medicine, May, 1977

4. M.D. Devous, Sr., "A Canine Model of Congestive Heart Failure", University of Florida, Department of Radiology I and Department of Cardiology, November 1977 5 D.E. Feltz, J.D. Randall, and R.F. Schumacher, " Report on I Damaged FLIP TRIGA Fuel", Fifth Triga Owner's Conference, Tucson, Arizona, March 1977
6. Randall, " Forensic Activation Analysis", NSCR Tech-I J.D.

nical Report No. 36, November 1977 7 R.R. Hart, L.D. Albert, " Measurement of P 31 Concentrations Produced by Neutron Transmutation Doping of Silicon", Presented at International Conference on Neutron Trans-mutation Doping, University of Mo., April 1978.

8. D. Wootan, " Measurement of Neutron Flux in Thermal Rotisserie", Master's Thesis in Nuclear Engineering, November 1978.

9 Huang, W., J. Chatham, " Uranium in Lignite: I Geological Occurrence in Texas", Tenth International Congress on Sedimentology, Volume 1, A-L, pp. 317, 1978.

10. Huang, W., S. Parks, " Uranium Resources in Some Tertiary Sediments of Texas Gulf Coastal Plain: I Geologic Occurrences in the Lower Miocene Sediments", Tenth International Congress on Sedimentology, Vol. 1, A-L, pp. 318, 1978.
11. Huang, W., K. Pickett, " Factors Controlling In-Situ Leaching of Uranium from Sandstone and Lignite Deposits in South Texas", Proceedings of Uranium Mining Technology, Update 78, Reno, Nevada, November 1973.

L_

12. Presley, R.J., R. Pflaum, J. Trefry, " Fallout and Natural

~ Radionuclides in Mississippi Delta Sediments", Environ-mental Oceanographic Science, Vol. 59, No. 4, April 1978 (abstract).

II-2 13 Fishman, P.H., "Minerological Analysis and Uranium Distribution of the Sediments from the Upper Jackson Formation Karnes County, Texas", Masters' Thesis in Geology, December 1978.

14. Prasse, E.M., " Uranium and Its Relationship to Host Rock Minerology in an Unoxidized Roll Front in the Jackson Group, South Texas", Masters' Thesis in Geology, December 1978.

15 Lescano, C., W.C. Ellis, "An Evaluation of Lanthanides as Particulate Matter Markers", American Society of Animal Science (abstract), Tucson, Arizona, 1979

16. Bachinski, S.W. and Scott, R.B., 1979, " Rare-Earth and Other Trace Elements Contents and the Origin of Mineetes:

Grochim. Cosmochim. Acta", Vol. 43, 93 17 Scott, R.B., Temple, D.G., and Peron, P., 1979, " Nature of Hydrothermal Exchange Between Oceanic Crust and Seawater at 26 N. Lat., Mid-Atlantic Ridge: In Benthic Boundary Layer Processes", an IOGC Symposium on the Benthic Boundary Layer.

18. Tiezzi, L.J., and Scott, R.B., 1979, " Crystal Fractionation in a Cumulate Gabbro, Mid-Atlantic Ridge, 26 N. Lat.: Jour.

Geophys. Research". 19 McGoldrick, P.J., Keays, R.R. and Scott, R.B., 1979,

   " Thallium: A Sensitive Indicator of Rock / Seawater Inter-action of Sulfur Saturation of Silicate Melts: Geochim.         l Cosmochim. Acta".                                               j
20. Zakoriadze, G., Scott R.B., and Lilly, D.H., 1979,
   " Petrology and Geochemistry of the Palao-Kyushu Remnant Arc, Site 448, DSDP Leg 59: Trans American Geophys.

Union", v. 50, 94.

21. Scott, R.B., 1979, " Petrology and Geochemistry of Ocean l Plateaus", A TAMU Symposium on Ocean Plateaus. )

l

22. Clearfield, A., and L. Kullberg, "On the Mechanism of Ion- l Exchange in Zirconium Phosphates: An Equilibrium Study of Sodium-Potassium-Hydrogen Exchange on Crystalline Zirconium Phosphates", Jour. of Inorganic and Nuclear Chem., 1979 23 0.F. Zeck, R.A. Ferrieri, C.A. Copp, G.P. Gennaro and Y. -N.

Tang, " Gas Phase Recoil Phosphorus Reactions IV-Effect of Moderators on Abstraction Reactions," J. Inorg. Nucl. Chem.,  ! 41, 785 (1979).

24. Cnatnam, J.R., "A Study of Uranium Distribution in an Upper l Jackson Lignite - Sandstone Ore Body, South Texas", Masters' Thesis in Geology, May 1979 25 Parks, S.L., " Distribution and Possible Mechanism of Uranium Accumulation in the Catahoula Tuff, Live Oak County, Texas",

Masters' Thesis in Geology, May 1979

I y II-3 l L

26. - Miller, M.E., " Uranium Roll Front Study in the Upper Jackson

[ Group Alaseosa County, Texas", Masters' Thesis in Geology, December 1979 l r 27 .Ellis, W.C., J.H. Matis, and Carlos Lascano, "A Method for l L Determining In-Vivo Rates of Particle Size Degradation,

             . Genesis, and Passage from the Ruman".s Proc. of 15th Conference on Ruman Function, 1979

" 28. Ellis,_W.C., J.H. Matis, and Carlos Lascano, " Sites Contributing to Compartmental Flow for Forage Residues", Ann. Res. Vet, p 1979 " l 29 Lescano, Carlos, " Determination of Grazed Forage Voluntary - Intake," Ph.d. Dissertation in Animal Nutrition, December L 1979

30. Pond, Kevin, "Effect of Monensin on Intake Digestibility, Gastrointestinal Fill and Flow in Cattle Grazing Coastal Bermuda Pasture", Masters Thesis in Animal Nutrition, i August 1979 L 31. Loza, Hector, "Effect of Protein Defficiency on Forage Intake and Digestibility", Masters Thesis in Animal Nutrition, j May 1979 1 l \
32. Tenhet, Vicki L., " Penetration Mechanism and Distribution 1 Gradients of Sodium-Tripoly-Phosphate in Peeled and Deveined I Shrimp", Masters Thesis in Animal Science, December 1979 L

33 E.E. Siefert, K.-L. Loh, R.A. Ferrieri, and Y.-N. Tang, J- " Formation of 1-S11acyclopenta-2,4-eiene through Recoil L Silicon Atom Reactions", J. Am. Chem. Soc., 102, 2285 (1980). E 34. .Rowe, M.W., E.W. Filberth, and H.J. Shaeffer, " Uranium in Huero and Guadalupe Mountain Indian Ceramics", Archaeometry Great Britain, 1980. F i 35 Ledger, E.B., .T. Tieh, and M.W. Rowe, " Delayed Neutron Activation Determination of Uranium in Thirteen French Rock y Reference Samples", Geostandards Newsletters, 1980.

36. Tieh, T.T., E.B. Ledger, M.W. Rowe, " Release of Uranium from Granitic Rocks During In Situ Weathering and Initial Erosion

{L . (Central Texas)", Chemical Geology, 1980. t P W F

  - . -                 .. , = ,                 -v-,,   ,,   -
                                                                 ,,      ~, ,      ,,    ,---,-re,   r

I I I I I Appendix III I Summaries of Health Physics Support Effluent Releases Environmental Survey Program Radiation and Contamination Control Program and Personnel Exposures I I I I l W

[ III-l Summary of Health Physics [ Support for the Operation of the Nuclear Science Center Reactor 1979 Provided health physics monitoring support for processing 920 irradiations containing over 11,000 samples and 1050 [ curies of radioactivity. [ Certified 603 shipments of radioactive materials to off-site industry. Certified 254 shipments of radioactive materials to other campus laboratories.

  -  Provided monitoring support for processing and handling over 5500 experimental samples retained at the Nuclear Science Center laboratories.

Conducted environmental survey program in cooperation with h the Texas State Department of Health. This program consists of in-situ TLD monitors and the collection, analyses and evaluation of over 100 soil, water, vegetation, and milk { samples. Provided personnel monitoring support for 40-50 persons on a daily basis and over 4,000 visitors as required. Performed radionuclide analyses and packaged approximately _ 300 Ft 3 of dry solid radioactive waste for disposal. Performed radioisotope identification and determined radio-activity concentrations for 44 releases of radioactive liquid effluents totaling 910,000 gallons including fresh water diluent. Volume of fresh water diluent was 690,000 rallons required to maintain effluent releases to approxi-aately 1% of MPC values specified in 10CFR20. E Performed surveys of the Nuclear Science Center facilities for

  -  radiation levels and radioactive contamination including the collection, analyses, and evaluation of approximately 250 smear    samples on a weekly basis.

Conducted radiation safety training for 50 NSC employees and experimental personnel using NSC facilities.

 ~   Conducted radiation safety training for off-site support agencies required for the implementation of emergency planning and preparedness procedures. These personnel in-cluded 15 members of St. Joseph's Hospital, 38 members of College Station Fire Department and ambulanary services,

[ and 40 members of the University Police Department. E L n l

L III-2 EFFLUENT RELEASE

SUMMARY

[ Introduction b ' Summaries of radioactive effluents released from the Nuclear t Science Center for 1979 are included in this Appendix. These data are presented in tabular form and include atmospheric, liquid and ( solid. waste releases. Particulate Releases [ Radioactive particulates are monitored at the base of the central exhaust stack and summarized on a monthly basis. The [- annual average release rate was 1.39 E-11 uC1/cc. Total radio-activity released for the year was 1.03 E-03 curies. There were no radioisotopes with > 8 day half-lives identified frem isotopic analyses of the filter papers. These analyses revealed only the (- decay daughters of Radon-Thoron. These data are presented in Table I. ( Gaseous Releases Argon-41 is the major gaseous effluent produced and released [ at the Nuclear Science Center. This effluent is measured by photo-peak counting the gaseous discharges in the central exhaust stack. Total Argon-41 radioactivities released during 1979 was 2.41 C1. This results in an annual average release rate of 3 23 E-08 uCi/cc [ as mes',ured in the central exhaust stack with no dilution factors applied. Applying the dilution factor of 5.0 E-03 allowed at the site boundary (as determined, SAR, pages 117-119, June 1979) {' results in radioactivity concentrations of < 1% of the limits specified in 10CFR20, Appendix B, Table II, Column 1. These data are summarized on a monthly basis and presented in Table II. [ Liquid Waste Releases Radioactive liquid effluents re collected in liquid waste holdup tanks prior to release from ;he confines of the Nuclear Science Center. Sample analyses for radioisotope identification and radioactivity concentrations were determined for each release. ( There were 44 liquid waste releases totaling 910 E 05 gallons in-cluding diluents from the Nuclear Science Center during 1979 The total radioactivity released for 1979 was 2 35 E-02 C1 with an [ average concentration of-6.83 E-06 uCi/ml. Radioisotopes were

         -identified as Ir-192, Co-60, Mn-54, Co-58, Na-24, Zn-65, Cr-51, Cd-ll5, Ce-141, Br-82, Cd-109, Co-57, Cs-137, I-133, and Sb-122.

Radioactivity concentrations for each radioisotope were below the [. limits specified in 10CFR20. Summaries of these data are presented in Tables 3-13 r L r L

                                        . ?.m w III-3 Solid Radioactive Waste

( There was 29.41 Ft 3 of dry solid waste materials packaged in 4 each 55 gallons steel drums for disposal during 1979 These materials were transferred to the Radiological Safety Cffice, Texas License 6-448, for disposal. This material consisted of [ Eu-152 contaminated soil and 5 each 14 inch sections of 3 inch carbon steel pipe doped with Co-60. These materials contained 2.43 E-01 ci of co-60 and 1.02 E-03 ci of Eu-152. These data are ( summarized in Table 14. Also, an additional volume of approximately 250 Ft 3 of dry solid waste materials was assayed for radioactivity concentration and radioisotope identification. These materials [ were packaged in 55 gallon steel drums and stored for future disposal. [ [ [ [ [ . [ [ [ [ [ E E r L. ~

III-4 I TABLE 1 I PARTICULATE EFFLUENT RELEASES ANNUAL

SUMMARY

1979 I Exhaust Volume Concentration Total Radioactivity Month cc pC1/cc C1 Ci January 6.31 E 12 4.42 E-11 278.90 2.79 E-04 February 5.71 E 12 2.64 E-11 150 74 1.51 E-Oh March 6.31 E 12 1.63 E-11 102.85 1.03 E-04 April 6.12 E 12 1.02 E-11 62.42 6.24 E-05 May 6.31 E 12 9.07 E-12 57 23 5.72 E-05 June 6.12 E 12 6.53 E-12 39 96 3.40 E-05 July 6.31 E 12 1 92 E-ll 121.15 1.21 E-04 August 6.31 E 12 4.67 E-12 29.46 2 95 E-05 September 6.12 E 12 6.53 E-12 39 96 4.00 E-05 October 6.31 E 12 1.10 E-11 69.41 6.94 E-05 November 6 12 E 12 8.71 E-12 53 30 5.33 E-05 December 6.31 E 12 4.72 E-12 29.76 2.98 E-05 I Total Volume: 7.44 E 13 cc Annual Average Release: 1 39 E-ll uCi/cc T otal Radioactivity Released: 1.03 E-03 Ci I I c i

III-5 [ TEE 2 GASEOUS EFFLLETI RELEASES APSON-41 { ANNUAL SU44ARY 1979 Exhaust Volume Concentration

  • Concentration ** Percent ** Radioactivity *

[_ Month cc pC1/cc-uC1/cc MPC Total (C1) January 6 31 E 12 2 35 E-08 1.17 E-10 03 1.48 E-01 Februar"/ 5 71 E 12 3 35 E-08 1.67 E-10 0.4 1 91 E-01 { March 6. 1 E 12 3 35 E-08 1.67 E-10 0.4 2.11 E-01 April 6.12 E 12 3.10 E-08 1.55 E-10 0.4 1.89 E-01 May 6.31 E 12 2 35 E-08 1.17 E-10 03 1.48 E-01 June 6.12 E 12 2.60 E-08 1 30 E-10 03 1.59 E-01 [ ~ July 6 31 E 12 1 37 E-08 6.85 E-ll 0.2 8.69 E-02 August 6 31 E 12 { 2 36 E-08 1.18 E-10 03 1.48 E-01 Septe:rber 6.12 E 12 2.85 E-08 1.42 E-10 0.4 1 74 E-01 [ October 6 31 E 12 2.60 E-08 1 30 E-10 03 1.64 E-01 November 6.12 E 12 4.45 E-08 2.25 E-10 0.6 2.72 E-01 b December 6.31 E 12 8.19 E-08 4.09 E-10 1.0 5 16 E-01

    . Total Volurre: 7.44 E 13 cc-

{ Annual Average Belease*: 3 23 E-08 uC1/cc Total Radioactivity Released *: 2.41 C1 _ #As masured in the Central Exhaust Stack

     ##As Determined at 100 meters, approximate boundary of exclusion area,

{ trith 200/1 Dilution Factor; SAR, Pages 117-119, June 1979 E 9 E

L III-6 RADI0 ACTIVE LIQUID EFFILEIT RELEASES [ SUDIARY 1979 [ Number Volume

  • Concentration
  • Isotope MPC-W MPC Radioactivity Releases Gallons uC1/cc pC1/cc  % C1 Ir-192 39 7.96 E 05 4.45 E-06 4.0 E-05 11.1 1 34 E-02 Co-60 42 8 77 E 05 1.12 E-06 3 0 E-05 37 3 72 E-03
  ~

Mn-54 38 8.08 E 05 7.45 E-07 1.0 E-04 07 2.28 E-03 Co-58 { 35 7 76 E 05 3 35 E-07 9 0 E-05 0.4 9.85 E-04 Na-24 10 1 90 E-05 1.23 E-c6 4.1 3 0 E-05 8.86 E-04 [  ::n-65 21 7 15 E 05 2 99 E-07 1.0 E-04 03 8.11 E-04 _ Cr-51 3 6.20 E 04 2.17 E-06 2.0 E-03 0.1 5.10 E-04 Cd-115 1 2.85 E 04 4.02 E-06 3.0 E-05 13 4 4.34 E-04 Ce-141 11 2.64 E 05 3 47 E-07 9 0 E-05 0.4 3.44,E-04 B'-82 4 7.60 E 04 3 21 E-07 4.0 E-05 0.8 9.49 E-05 Cd-109 1 1 70 E 04 5 53 E-07 2.0 E-04 03 _ 3 56 E-05 Co-57 5 1 55 E 05 6.00 E-08 4.0 E-04 <.1 _ 3 52 E-05 Cs-137 2 34 E 04 5 04 E-03 2.0 E-05 03 6.50 E-06 I-133 1 1 70 E 04 4.18 E-08 1.0 E-06 4.2 2.69 E-06 So-122 1 17 E 04 2.50 E-08 <.1 3 0 E-05 1.61 E-06 Total Releases: 44 _

  • Total Volume: Gallons: 9 10 E 05 CC: 3 45 E 09
  • Average Concentration: 6.83 E-06 uC1/cc Total Radioactivity: 2 35 E-02 Ci

{

  • Includes fh sh water diluent E

r U

III-7 TEE 4 RADI0ACTI'E LIQUID EFFLUFllT Fri:ASES FDhTd2 SUFRY I January 1979 Nu:ter of Volume

  • Concentration
  • MPC-W MPC Radiractivity Isotope Releases Gallons pC1/cc uC1/cc  % C1 Co-60 2 3.40 E 04 1.25 E-06 5 0 E-05 25 1.61 E-04 Zn-65 2 3.40 E 04 1.02 E-06 1.0 E-04 1.0 1 32 E-04 bh-54 1 1 70 E 04 1.14 E-06 1.0 E-04 1.1 7 35 E-05 Cr-51 1 1 70 E 04 7.83 E-07 2.0 E-03 <1 5 05 E-05 Co-58 1 1.70 E 04 6.63 E-07 9 0 E-05 07 4.27 E-05 Ce-141 1 1 70 E 04 2.25 E-07 9.0 E-05 0.2 1.45 E-05 I

Total Palease: 2 Total Volume: Gallens 3 40 E 04 cc 1.29 E 08 Average Concentration: 3.68 E-06 uCi/cc . Total Fadioactivity: 4 75 E-04 Ci

  • Includes fresh water diluent I

I E I n L

[ III-8 TABIE 5 RADICACflVE LIQUID EFFILEE IEIEASES IC EHLY SUFNARY b Bhrch 1979 Ntrber of Volume

  • Concentration
  • MPC 'd MPC Radiocctivity Isotope Releases Gallons pCi/cc pC1/cc 5 C1 Co-60 2 3 A0 E 04 9 07 E-07 5.0 E-05 1.8 1.17 E-04 q

Zn-65 2 3 40 E 04 1.0 E-04 5 33 E-07 05 6.88 E-05 [ C0-58 2 3.40 E 04 1.53 E-07 1.0 E-04 0.2 1 98 E-05 Ir-192 2 3.40 E 04 6.23 E-08 4.0 E-05 0.2 8.04 E-06 _ Sb-122 1 170 E 04 2.50 E-08 3 0 E-05 <0.1 1.61 E-c6 Total Release: 2 { Total Volume: Gallons 3.40 E 04 cc 1.29 E 08 Average Concentration: 1.67 E-06 pC1/cc i ( Total Padioactivity: 2.15 E-04 Ci 0 Includes fresh water diluent [ m mes W [ [ E u s

III-9 TABLE 6 FADICACTIVE LIQUID EFFLUE!72 FI. LEASES IO7fHLY SUGIAPX April 1979 I Nu:nber of Volu:r.e

  • Concentration
  • MPC-W MPC P,adioactivity Isotope Paleases Gallons uCi/cc pC1/cc  % C1 Co-60 3 5 10 E 04 1 94 E-06 3 0 E-05 6.5 3 76 E-04 Zn-65 3 5 10 E 04 1.08 E-06 1.0 E-04 1.1 2.10 E-04 Mn-54 2 34 E 04 1.96 E-06 1.0 E-04 2.0 1.26 E-04 Co-58 3 5 10 E 04 2 76 E-07 9 0 E-05 03 5 34 E-05 Cd-109 1 1 70 E 04 5.52 E-07 2.0 E-04 03 3 56 E-05 Ce-141 2 34 E 04 4.13 E-07 9 0 E-05 0.5 2.66 E-05 Ir-192 2 3.4 E 04 3 98 E-07 4.0 E-05 1.0 2 56 E-05 Co-57 1 1 70 E 04 4.48 E-08 4.0 E-04 <0.1 2.89 E-06 I-133 1 1 70 E 04 4.17 E-08 1. 0 E- 4.2 2.69 E-06 I Total Feleases: 3
                                                                                                     ~

Total Volu:m: Gallons 5.10 E 04 cc 193 E 08 Average Concentration: 4.44 E-06 uCi/cc Total F.adioactivity: 8.58 E-08 Ci DIncludes fresh water diluent I I I u

III-10 TABE 7 RADI0 ACTIVE LIQUID EFFLElE REEASES MormiLY SIINARY May 1979 Ntaber of Volu:m* Concentration

  • MPC-W MPC Padioactivity l Isotooe Releases Gallons pC1/cc pC1/cc  % Ci i l

Na-24 2 3 25 E 04 2.46 E-06 3 0 E-05 8.2 3 03 E-04 Co-60 3 4.95 E 04 7 29 E-07 3 0 E-05 2.4 1 37 E-04 Br-82 3 4.95 E 04 4.83 E-07 4.0 E-US 1.2 9 08 E-05 Ir-192 3 4.95 E 04 2 33 E-07 4.0 E-05 0.6 4 39 E-u l Mn-54 2 3 25 E 04 2.20 E-07 1.0 E-04 1.0 E-04 0.2 0.2 2 71 E-05 Zn-65 2 3 25 5 04 2.06 E-07 2 54 E-05 Co-58 2 3 25 E 04 6.20 E-08 9 0 E-05 <0.1 7.63 E-06 Ce-141 1 1.55 E 04 2.40 E-08 9.0 E-05 <0.1 1.41 E-06 I Total Releases: 3 Total Volume: Gallons 4.95 E 04 cc 1.88 E 08 Average Concentration: 3 38 E-06 pC1/cc

           ' Total Radioactivity: 6.36 E-04 Ci 0 Includes 6 sh water diluent i

I l I

III-ll TAB E 8 I RADICACTIVE LIQUID EFFLUE'E EEEASES MONDILY

SUMMARY

June 1979 Ntr.ber of Volume

  • Concentration MFC-W IGC Radioactivity Isotope Releases Gallons pC1/cc pC1/cc  % C1 Co-60 5 1.20 E 05 1.62 E-06 3 0 E-05 5.4 7.42 E-04 Mn-54 5 1.20 E 05 8.69 E-07 1.0 E-04 0.9 3 96 E-04 Zn-65 4 9 15 E 04 8.31 E-07 1.0 E-04 0.8 2.88 E-04 Co-58 5 1.20 E 05 2.14 E-07 9,0 E-05 0.2 9.78 E-05 Ir-192 5 1.20 E 05 1 95 E-07 4.0 E-05 0.5 8.91 E-Op I Ce-141 2 4.57 E 04 5 18 E-08 9 0 E-05 <0.1 8.99 E-06 i

l Br-82 1 2.85 E 04 3.87 E-08 4.0 E-05 <0.1 4.19 E-06 Total Releases: 5 Total Volume: Gallons 1.20 E 05 cc 4.56 E 08 Average Concentration: 3 56 E-06 uCi/cc Total Radioactivity: 1.63 E-03 Ci 0 Includes fresh water diluent

III-12 [ TABLE 9 RADI0 ACTIVE LIQUID EFFLUDir RELEASES BDIELY SIM4ARY July 1979 Number of Volume

  • Concentration
  • BFC-W MFC Padioactivity l Isotope
~

Releases Gallcns pCi/cc pC1/cc  % C1 Cd-ll5 2 2.85 E 04 4.02 E-06 4.0 E-05 10.0 4.34 E-04 [ Cr-51 2 2.85 E 04 3 76 E-06 2.0 E-03 0.2 4.07 E-04 Co-60 4 7.87 E 04 1.05 E-06 3 0 E-05 35 3 14 E-04 Mn-54 4 7.87 E 04 9 93 E-07 1.0 E-04 1.0 2.96 E-04 .- Na-24 2 2.85 E 04 2.66 E-06 3 0 E-05 8.9 2.87 E-04

~

Zn-65 3 6.23 E 04 8.48 E-07 1.0 E-04 0.8 2.00 E-04 Co-58 { 3 6.23 E 04 4.39 E-07 9.0 E-05 05 1.04 E-04 Ir-192 4 7.87 E 04 3.41 E-07 4.0 E-05 09 1.02 E-04 h Co-57 1 170 E 04 4.48 E-08 4.0 E-04 0.1 2.89 E-06 Total Releases: 4 Total Volume: Gallons 7.87 E 04 cc 2 98 E 08 Average Concentration: 7.72 E-06 uCi/cc { Total Radioactivity: 2.15 E-03 Ci

  • Includes fresh water diluent

[ E E n L

IIId 3 {.- TABLE 10

                                ~ RADI0 ACTIVE LIQUID EFFILEff RELEASES MONIHLY SGNARY

{. , Atgust 1979. [_ Number of Voltm

  • Concentration
  • MPC-W MFC Padioactivity' Isotope Releases. Gallons uC1/cc uC1/cc  % Ci

[~ Co-60 5 1.13 E 05 9.80 E-07 3 0 E-05 33 4.18 E-04 Mn-54 6 1.29 E 05 6.63 Er07 1.0 E-04 07 3.24 E-04 Na-24 2 6.23 E 04 6.12 E-07 2.0 3 0 E-05 1.44 E-04 Zn-65 4 9 58 E 04 3.84 E-07 1.0 E-04 0.4 [ Co-58 6 1.29 E 05 1.39 E-04 2.19 E-07 9 0 E-05 0.2 1.08 E-04 Cr-51 { 1 1.65 E 04 8.47 E-07 2.0 E-03 0.4 5 30 E-05 Ir-192 4 C.55 E 04 1 78 E 4.0 E-05 0.4 4.42 E-05 [ Co-57 1 1 53 E 04 2 70 E-08 4.0 E-04 <0.1 1 56 E-06 [

    'Ibtal Releases:    6
    'Ibtal Volurra: ,allons' 1.29 E 05 cc 4.89 E 08 s

{ '. Average Concentration: 2.52 E-06 uC1/cc Total Radioactivity: 1.23 E-03 Ci

    # Includes fresh water diluent

[ [ E E D:

[ III-14 [ { TABLE 11 RADIOACTIVE LIQrJID EFTLUENT RELEASES { MONIELY SUGARY September 1979 Number of Volume" Concentration

  • IEC-W MPC Radicactivity Isotope Releases Gallons pCi/cc pC1/cc  % C1

( Ir-192 8 1 58 E 05 2.03 E-06 4.0 E-05 5.1 1.21 E-03 Co-60 7 1.41 E 05 9.69 E-07 3 0 E-05 32 5.16 E-04 Mn-54 7 1.41 E 05 6.37 E-07 1.0 E-04 0.6 3 39 E-04 Zn-65 6 1.24 E 05 4 78 E-07 1.0 E-04 0.5 2.25 E-04 Co-58 6 1.24 E 05 3 44 E-07 9 0 E-05 0.4 1.62 E-04 { Na-24 4 6.65 E 04 6.01 E-07 3 0 E-05 2.0 1 51 E-04 Ce-141 2 2.85 E 04 1 59 E-07 0.2 9 0 E-05 1 72 E-05 b Co-57 2 2 90 E 04 1.S2 E-08 4.0 E-04 <0.1 2.0 E-06 [ Total Releases: 8 Total Volume: Gallons 1 58 E 05 cc 5.97 E 08 Average Concentration: 4.40 E-06 pCi/cc { Total Radioactivity: 2.63 E-03 Ci

  • Includes fresh water diluent

[ [ [ r m u F

III-15 [ TABLE 12 RADICACFIVE LIQUID EFFLUDTT RELEASES bnVfHLY SLM4ARY October 1979 [ Number of Volume # Concentration

  • MFC-W MPC Radioactivity Isotope Releases Gallons pC1/cc pC1/cc  % C1
  ~

Ir-192 .7 1.89 E 05 1 58 E-05 4.0 E-05 39.5 1.13 E-02 Co-60 .7 1.89 E 05 1.16 E-06 3 0 E-05 3.8 8.33 E-04 {. Mn-54. 7 -1.89 E 05 9 35 E-07 1.0 E-05 93 6.69 E-04 h Co-58 5 156 E 05 5 94 E-07 9 0 E-05 0.6 3 49 E-04 Ce-141 4 1.22 E 05 6.02 E-07 9 0 E-05 15 2.79 E-04 Cn-65 4 1.40 E 05 4.71 E-07 1.0 E-05 4.7 2.51 E-04 Co-57 1 7 70 E 04 8.87 E-08 4.0 E-05 0.2 2.59 E-03 Cs-137 2 3.40 E 04 5.04 E-08 4.0 E-05 0.1 6.50 E-06

      ~
          'Ibtal Releases: 7 Total Volume: Gallons .1.89 E 04 cc 7 16 E 08 Average Concentration: 1 92 E-05 uCVcc Total'Eadioactivity: 1 38 E-02 Ci
 ~
  • Includes fresh water diluent

[L [- [- E m

III-16 TABLE 13 RADICACTIVE LIQUID EFFIlEV. f REEASES i FDNTHLY SGNARY November 1979 Nw.ber of Volu:r.e* Concentration

  • FTC-W h?C Fadioactivity Isotope Releases Gallons pCi/cc pC1/cc . Ci l Ir-192 4 6.70 E 04 2.12 E-06 4.0 E-05 5.3 5 38 E-04 Co-60 4 6.70 E 04 4.20 E-37 3 0 E-05 1.4 1.07 E-04 Zn-65 3 5.00 E 04 2.23 E-07 1.0 E-05 2.2 4.24 E-05 Mn-54 4 6.70 E 04 1.14 E-07 1.0 E-05 1.1 2 90 E-05 l Co-58 3 5 00 E 04 7.82 E-08 9 0 E-05 <1 1.49 E-05 l

l Total Releases: 4 'Ibtal Volume: Gallons 6.70 E 04 cc 2 54 E 08 Average Concentration: 2.88 E-06 uC1/cc Total Radioactivity: 7 32 E-04 Ci " Includes fresh water diluent

III-17 TA3LE 14 SOLID RADICACTIVE WASTE DISPOSAL ANNUAL SGNARY 1979 Radioisotope Padioactivity (C1) Co-60 2.43 E-01 Eu-152 1.02 E-03

              'Ibtal Volu:m: 29.41 Ft3 contained in 4 ea. 55 gallen steel drrs Total Radioactivity:  2.44 E-01 Ci I

I I I I I I I I 1 I

III-18 ENVIRONMENTAL SURVEY PROGRAM [ Introduction

            'The environmental survey samples were collected in accordance

[ with the schedules of the cooperative surveillance program between the Texas State Department of Health and Texas A&M University. These samples were analyzed for gross gamma and beta activities and isotope identification. Data from these samples remained [~ basically unchanged from 1978 and reflect the continued use of retention facilities and sample analysis for laboratory effluents prior to their release. Sample analyses indicate that the { -activities are remaining at normal background levels in the un-

                                            ~

restricted environment. The environmental survey program was expanded in 1977 to in- [ clude the in-situ measurement of integrated radiation exposures at the site boundaries. These measurements are made for a period of approximately 90 days using commercially available thermoluminescent {' dosimeters (TLD's) of lithium fluoride chips in glass encapsulated bulbs. These dosimeters are provided and processed by Texas Department of Health, Division of Occupational Health and Radiation Control. Ambient background for these measurements is determined [ from a control dosimeter lccated southeast of Easterwood Airport approximately 800 meters east of the Nuclear Science Center site. This location is at a right angle to the prevailing southeasterly (' Winds which occur a large majority of the time on an annual basis. Table 19 lists the average exposure rate above ambient back- [- ground for. a number of locations at the site boundary. The highest exposure points at the nortn and west location of the site boundary. Additionally, a dosimeter is located adjacent to the radioactive waste storage building and the instrument calibration range.

 ~

Exposure data from this dosimeter.is not considered as a result of. reactor operations but does reflect the maximum site boundary exposure of 51 3 micro R/hr. This site boundary location is [ further protected from ?ree access to the general public for an additional 100 meters of fenced Texas A&M University property. A dosimeter at this location reveals only background radiations. Summaries of the environmental survey program for 1979 are presented in Tables 15-19 E E E n

III-19 TABLE 15 ENVIRONMENTAL SURVEY PROGRAM E FIRFT QUARTER

SUMMARY

1979 WATER Radioactivity (Pci/L) Number Location Samples Average Maximum Minimum TAMU Sanitary Outflow 12.0 50 14.1 5.0 3 92 4.5 NSC Creek 1 340.0 20.0 White Creek 1 13 0 2 50 VEGETATION Radioactivity (Pci/gm, ASHED) Number Locatiori Samples Average Maximum Minimum I NSC Site (Outside Fence) 1 28 : 27 NSC Site (Inside I Fence) 1 33 : 2.2 NSC Creek 1 19 2.1 Cyclotron 1 45 30 White Creek I 1 14 30 MILK Radioactivity (Pci/L) I Location Number Samples Isotope Average Maximum Minimum TAMU Dairy 3 K-40 1190 53 1330 2 53 1100 1 55 H-3 <500 <500 <500 I m

III-20 TABLE 16 i ENVIRONMENTAL SURVEY PROGRAM SECOND QUARTER

SUMMARY

1979 WATER Radioactivity (Pci/L) Number Location Samples Average Maximum Minimum NSC Creek 4 13 1 51 25 1.4 7 White Creek 3 9.9 5.4 21 2.4 Sanitary Outflow 7.5 1.6 Upper Brazos 3 12 7.6 32 1.4 1 5.8 13 7.2 : 1.0 4.4 1.0 Lower Brazos 2 15 5 37 26 : 6.5 5.0 1.0 VEGETATION Radioactivity (Pci/gm, Dry, wt.) I Location Number Samples Average Maximum Minimum NSC Site (Inside Fence) 37.6 50.0 I NSC Site (Outside Fence) White Creek 3 3 4 37.1 33.7 29 2.6 7 58.0 2 39 3.6 50.0 2 4.9 24.0 16.0 17 1.1 24.0 z 2.2 NSC Creek 31.6 2 23 3 43 0 32 20.0 17 MILK Radioactivity (Pci/L) Number I Location Samples Isotope Average Maximum Minimum TAMU Dairy 3 Cs-137 72 4.5 8.9 5.5 5.6 2 3.6 I H-3 K-40 1216

                                                 <500 71   1220
                                                                <500 85   1210
                                                                             <500 61 I

I L, F~

III-21 [ TABLE 17 ['- ENVIRONMENTAL SURVEY PROGRAM THIRD QUARTER

SUMMARY

1979 WATER Radioactivity (Pci/L) Number _ Location Samples Average Maximum Minimum NSC Creek - 3 46.9 z 8 88.0 12 6.8 4

       -White Creek                       2           13 0       14.0    5.3
       -Upper Brazos_ River                                   5                      12    4.7 1            7.6    4

[- Louer Brazos River 1 13 0 7 Sanitary _0utflow 9.6 14.0 3 5 55 6.6 4 [: VEGETATION { Radioactivity (Pci/gm, Dr wt.) Number

              . Location               Samples       Average      Maximum         Minimum NSC_ Site (Inside Fence)          3         20.0    15   23.0    1.8     15.0    1.2 NSC Site-(Outside Fence)          4         17.4    13   20.0    1.4     15.0    1.2

{ -White Creek

       -NSC. Creek 1         24.0    1.2 3         26 3    2.8    35    27        17 z 2.8 MILK Radioac t.'.vity (Pc1/L)

Number Location Samples Isotope Average Maximum Minimum ~ TAMU Dairy 3 K-40 1353 76 1430 86 1200 72 H-3 <500 <500 <500 [ [ E E 9 1

[.; III-22 TABLE 18 ( ENVIRONMENTAL SURVEY PROGRAM FOURTH QUARTER

SUMMARY

{ 1979 WATER _ Radioactivity (Pci/L) Number- {- ' Location Samples Average Maximum Minimu:a White Creek 1 5.3 4.5 Sanitary Outflow 2 3.7 [-. NSC Creek 2 109 -11 5 124 12 94 11 Lower Brazos 2 5.2 2.4 8.4 4.8 2.0 - Upper Brazos 2 10 3 6.5 14.0 8.7 4.6 6.7 VEGETATION [ Radioactivity (Pci/gm, Dry. wt.) [L Number

          -Location              Samples      Average         Maximum              Minimum E
    -NSC Site (Inside Fence)        1       14.0     1.9 NSC-Site (Outside Fence)       1       17.0     1.2 NSC Creek                       1       18.0     2.5 MILK h;                               Radioactivity (Pci/L)

Number Location Samples Isotope {. Average ' Maximum Minimum TAMU Dairy 2 K-40 1180 104 1240 74 1120 134 I-192 54 13 5 [- H <500 <500 <500 [ c: [ g

III-22 TABLE 19 ENVIRONMENTAL RADIATION MONITORING PROGRAM INTEGRATED RADIATION EXPOSURE December 27, 1978 - January 17, 1980 I Station Exposure Exposure Exposure Rate Number Location (Gross MR) (Net MR) (Micro R/hr) 1 Background 59 59 - 2 NSC Fence Northwest 88 29 31 3 NSC Fence West 103 44 4.7 4 NSC Fence North 107 48 51 5 NSC Fence East 86 27 2.9 6 Radioactive Waste Storage Building 535 476 51 3 7 100 Meters East of NSC Boundary 63 4 0.4 I *8 NSC Fence South in Line With Hyperbaric Lab 38 7 1.4

  *9          NSC Fence South in Line With Living I

Quarters 35 4 0.8

  • Measurements begun on July 5, 1979 with the establishment of I temporary living quarters for the hyperbaric lab night watchman located fence.

approximately 25 meters south of the NSC south boundary I I I I h

L-III-23 r L RADIATION AND CONTAMINATION CONTROL PROGRAM. Introduction The detection and elimination of radiation hazards is an I integral part of the Radiation Safety Program at the Nuclear k Science Center. The radiation and smear survey programs con-tribute to the control and elimination of these health hazards. r- This program is effective in preventing the spread of radio-E active contamination, improper storage of radioactive materials, and unwarranted exposures to radiation. Radiation Survey r' The Nuclear Science Center uses an area radiation monitoring , system, consisting of nine (9) detector channels located throughout the Reactor and Laboratory Buildings. This system is equipped with alarm settings and remote readouts in the control and reception l rooms. Radiation levels and operational checks are recorded on a daily basis. This system functions as a radiation safety monitor , for the early detection of impending radiation hazards. The i p Nuclear Science Center Facilities and site boundaries are surveyed l L monthly with beta-gamma sensitive instruments. These measurements , are taken to determine proper storage and identification of radio- l y active materials and that visitor and routine work areas are free l of radiatien hazards. Additionally, radiation monitoring support is provided for the reactor operations and experimenter groups i to insure the safe handling of radioactive materials and control l I of personnel exposures. There were no unexpected radiation levels L or improper storage of radioactive materials detected during 1979 These surveys revealed-only background radiations at the site 7 perimeter fence. L Contamination Survey "~ L The Nuclear Science Center is routinely surveyed for radio-active contamination every week. This program includes the ~ collection, enalysis and evaluation of approximately 250 smear Le samples and the decontamination of areas and stored materials with removable beta-gamma radioactivities of greater than 300 dpm/100 cm 2. This program was effective in the elimination of [ contaminated areas and ascertaining that visitor and personnel 1 traffic patterns were free of radioactive contamination. l i u i m L,. l l - I - l 6 NM .

L { III-24 [ PERSONNEL EXPOSURES [ Radiation exposures to personnel at the Nuclear Science Center for 1979 were within the limits of 10CFR20. The maximum exposure received by an individual for the year was 1060 mrem. A total of 5.610 MANREM was received for 1979 More important, the exposures reflect-an extended effort by all personnel to minimize and eliminate radiation exposures whenever practicable. These exposure data becomes more significant when one considers that in addition to routine reactor operations, over 11,000 samples containing 1050 cuties of radioactivity were produced and processed at the { Nuclear Science Center in 1979 The whole-body exposure data for NSC employees and experimental personnel are presented in Table 20. [ These data are presented in graded divisions as required under 10CFR20.202(a). The access control procedures for visiting personnel were effec-tive in preventing exposure to radiation. There were 4,029 [- visitors to the Nuclear Science Center during 1979 The maximum exposure to any visitor was less than the minimum measurable quantities. These values are 10 millirems for X or gamma, 40 _ millirems for hard Beta, 20 millirems for fast neutrons and 10 millirems for thermal neutron radiations. E O w W W m W w m~ E

III-25 TABLE cc PERSONNEL WHOLE-BODY EXPOSURES 1979 Annual Whole-Body Number of Individuals Dose " Ranges (Rems) in Each Range No Measurable Exposure 9 Less than 0.100 30 0.100 - 0.250 4 0.250 - 0 500 2 0.500 - 0 750 4 0.750 - 1.000 0 1.000 - 2.000 1 Oreater than 2.000 0 I Total Number of Individuals Reported: 50 I

  • Individual values equal to the values separating exposure ranges are ranges are reported in the higher range.

I I I b i

1 i . I I APPENDIX IV Universities, Colleges, Industrial Organizations, I Government and State Agencies Served by the NSC During Sixteen Years of Operation I I I 3 I L

s. IV-1 h:

                                          ~

Other Universities and Colleges Baylor! University- LSam Houston State {. Baylor, College of Medicine University of New Hampshire University'of Texas Catholic College for Women Texas Women's University Taft College [ . University: California, Los Angles Blue Field College Lamar State CollegeLof Technology Potomac St. College New Mexico State University Thames Valley St. Tech. Collega Rice University Victoria College [. Austin College Tennessee Tech. University {J Southern Methodist University Wharton County Jr. College California State Poly. College Grayson County College-Washington University West Vir61nia Inst. of Tech. Hastings College [ Winona State--College Galveston College Arkansas Poly College { Wisconsin State University Eastern Kentucky University Milwaukee Institute of Technology Sue Bennett College [: ' Arkansas State College' Cheyney St. College Ball State Teachers College University of Genova h.

         .I Texas ~Southmost College                University of Southern Louisiana Stephen F. Austin Col ege.              University of Oklahoma Louisiana State University.             Somerset Community College

[ Xavier University. . Grave City College Temple University.Penn. Louisiana Tech. [ Bemidgi State College Abraham'Baldwin College Chadran State. College' Kent St. University {- O r l .

IV-2 Other Universities and Colleges (Con't) State University of Ohio Pan American College Alfred St. College Tarleton St. College Community College of the Finger Columbus College Lakes Nebraska Weslyan University Howard Payne College Lock Haven St. College Prairie View A&M College San Bernadino Valley College Longwood College North Park College and Theolo- S.D. School of Mines gical Seminary College p Fort Valley State College tierth Shore Community College Denison University University of Wisconsin State University College, N.Y. Hill Jr. College Auburn University McLennan Community College Clarion State College Southeast Missouri St. College University of Alaska Southwestern State College University of Arkansas Mary Hardin Baylor University of Houston Texas State Technical Inst. Southwest Texas State College North Texas State University  ; Iowa State Univeralty University of Arizona Blinn College McNeese State University State College of Arkansas Texas Eastern University The Defiance College Henderson County Jr. College I San Antonio College Laredo Jr. College Massachusetts Institute of Technology University of Texas at Dallas I University of Corpus Christi Moody College South Dakota State 7 Arapahoe Jr. College L_, California St. College m

                            +

3 IV-3 Industrial Organizations

    -States' Marine. Lines'                    Comfaco Southwest Research-Institute              Rivera Foods Humble' Oil'end Refining Co.

North American' Aviation Institute of Research and Gulf Research Instrumentation 1- Estrada Incorporated -Xomox Shell' Chemical Co. Texas-Nuclear Mobil Oil Co. Bio Assay Lab-Bio Nuclear Texas Instruments Inc. NAPKO Corp. Todd Shipyards Corp. D.W. Mueller, Consultant Shell Development Co. General Nuclear Corp. Tennessee Gas Transmission Co. Nuclear Environmental Eng. Corp. Lane Well Co. Shell Development, Oakland Calif. Petro-Tex Chemical Corp. Nuclear Sources and Services

     ' Babcock and Wilcox Co.                  Exxon Medical Arts                              Atomic Energy Industrial f

Texaco Inc. Hughes Research Lab Monsanto'co. TRACO Inc. Hastings Radiochem'ical Works Lloyd Barber and Associates E.I. DuPont DeNemours and Co. Temple Industries Mission Engineering Chemtro l . Inc . ESSO.Research and' Engineering Jet Research Diamond - Alkali . Co '. Resource Engineering

  ~

Dow Chemical.Co. Ranger Engineering Celanese Co'. Turbine Lab Independent-Exploration Co. Gulf Nuclear

IV-4 Industrial Organizations (Cont'd) Westingnouse Electric Avery Oil Company Bell Helicopter Spectronics LGL, LTD. E-Systems Monsanto, Inc. Radian Corp. Nuclear Laboratory Services Core Laboratories Pacific Gas and Electric l 1 l l

l 3 i I IV-5 i j Government and State Agencies M.D. Anderson Hospital Houston Police Department l Houston, District Attorney Brooks Medical Center National Aeronautics and Space Administration 4 North East Radiological Health Lab i Department of the Army l Wichita Falls, District Attorney Corpus Christi, District Attorney 1 ( Dallas County, District Attorney Denton County, District Attorney 1 Jefferson County, District Attorney j Oklahoma Medical Examiner i l U.S. Air Force I j Osage County Oklahoma, District Attorney Bureau of Economic Geology i I l, l

l l l l APPENDIX V  ! l Texaa-A&M University Departments Served by 1 ( The NSC During Sixteen Years of Operation I 1 1

                                            ]

l i

w V-1 (- TAMU Department ~and Agencies Department of Biochemistry ~and Biophysics [. Department.of Nuclear Engineering _ DepartmentLof Oceanography

              -Activation _ Analysis Research Laboratory

{.- - Department of' Physics Department of' Petroleum Engineering Department of-Animal-Science Department of Range Science {- Department of Mechanical Engineering { .. Department of Wildlife and Fisheries Sciences Department of-Chemistry Department of Large Animal Veterinary Medicine and Surgery ' Radiological Safety Office [. Cyclotron Institute Department of' Plant Sciences {- Nuclear Science Center Department of-Veterinary Physiology and Pharmacology Department of Radiation Biology [ Center for Trace. Characterization { Bioengineering Program,' College of Engineering Texas ~ Engineering Extension Service, Electronic Training ( Department-of. Geology

Department of Forest Science
           - Department ~ of Soil and Crop Sciences F              Collegefor' Medicine L                                                 -

b, _ _ V-2 [ TAMU Departments (Con't) Department of Ilealth and Physical Education [ Department of Architecture { ' Department of Building Construction Department of Industrial Engineering [ Department of Industrial Education Department of Aerospace Engineering [ Department of Engineering Technology {. Department of Civil Engineering Fireman's Training School ( Department of Archaeology [ [ [- m [ [ [ [ [ g W}}