ML20087N338
| ML20087N338 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 12/31/1983 |
| From: | Deigl H, Head J, Petesch J TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| ORO-4207-16, NUDOCS 8404030352 | |
| Download: ML20087N338 (98) | |
Text
__
TWENTIETH PR0GRESS R E P Q R T.
of the T-E X A S A&M UNIVERSITY NUCLEAR SCIENCE CENTER January 1, 1983 - December 31, 1983 Prepared By l
H. J. Deigl J. G. Head J. E. Petesch R. D. Ro6ers B. W. Willits and the Nuclear Science Center Staff Submitted to l
U.S. Nuclear Regulatory Commission and U.S. Department of Energy and The Texas A&M University System By D. E. Feltz, Director Nuclear Science Center Texas Engineering Experiment Station College Station, Texas March, 1984
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Table of Contents P.aFa I.
Introduction 1
II.
Reactor Utilization 3
A.
Utilization Summary 3
B.
Utilization by the Texas A&M University System 3
C.
Utilization by Other Educational Institutions 8
D.
Utilization by Non-University Institutions 11 III.
Facility Operations 13 A.
Facility Safety and Operational Improvements 13 Demineralizer Room Upgrade 13 Facility Paging System Improvements 13 B.
Improvements to Reactor Systems and Experimental Facilities 13 Facility Air Monitor System Improvements 13 Laboratory #4 Pneumatic Controller 15 Dry Air System Modification 15 Control Room Sample Timer 15 South Pneumatic Station Modification 18 Beam Port #4 Modifications 18 C.
Operational Problems 18 Failure of Demineralizer Room Sump Pumps 18 Waste Storage Tank Leakage 18 Failure of Two Additional Fuel Elements to Pass Fuel Inspection Criteria 18
~
Secondary Cooling System Pump Failure 20 Centrol Rod Drive Units 20 USNRC Enforcement Conference 20 1
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Reportable Occurrences 20 Bowing.0bserved in Fuel Elements
- 7463 and #7386 20 Failure of Fuel Thermocouple During Reactor Startup 21 Possible Operation in Excess of Licensed Power Level 21 D.
Reactor Operations Related Items 22 Reinitiation of Pulsing Operation 22 Facility License Renewal 22 Fuel Shipment 22 Revision of NSC Normal Schedule of Operation 22 Measurement of Withdrawal Times for Transient Rod During Pulsing Operation 23 E.
Changes in Operating Procedures 23 F.
Unscheduled Shutdowns 23 G.
Reactor Maintenance and Surveillance 25 IV.
Facility' Administration 29 A.
Organization 29 3.
Personnel 29 C.
Reactor Safety Boara 32 Appendix'I C
Description of Projects Utilizing the NSCR Appendix 1II' Publications, Theses, and Papers Which Involved Use of NSC Facilit'es From 1976.to Date
' 11 -
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1 Appendix III Environmental Survey Program and Effluent
~
Release Summary and Personnel Exposure Summary Appendix IV Universities, Colleges, Indsstrial Organi-zations, Government and State Agencies Served by the NSC During Twenty-One Years of Operation Appendix V Texas A&M University Departments Served by the NSC During Twenty-One Years of Operation 111 e
List of Tables and Figures Page Table 1 9eactor Utilization Summary 5
Table II Total Research Dollars to TAMU Resulting 6
From Utilization of the NSCR Table III Academic Use of the Reactor 9
Figure 1
Yearly Reactor Operation 4
2 Demineralizer Room Floor Plan 14 3
Facility Air Monitors Air Flow 16 i
Manifold 4
Facility Dry Air System 17 l
5 South Pneumatic Station 19 6
Transient Rod Timing Device 24 7
Nuclear Science Center Reactor 30 Operations Organizational Chart iV
4 1
I.
INTRODUCTION The Nuclear Science Center is operated by the Texas-Engineering Experiment Station as a service to the Texas A&M University System and the State of Texas.
The facility is available to the University, other educational institutions, governmental agencies, and private organizations'and individuals.
The facility operating license was ranewed in March, 1983 and extends through March,.2003 This report has_been prepared by the staff of the Nuclear Science Csnter of the Texas Engineering Experiment Station to satisfy the reporting' requirements of USDOE Contract Number DE-AC05-75ER04207 (formerly EY-76-C-05-4207) and of 10CFR50 59 The report covers
.the period from' January 1, 1983 through December 31, 1983 Reactor. utilization improved slightly from 1982 with increases seen in total number of irradiations, number of. samples irradiated, and total experiment hours.
Reactor operation of 94.6 Mw-days for
^1983 represents approximately a 1.4% increase over the previous year.
.It should be noted, however, that effective 1 September 1983 the operating 1 schedule for the NSCR-has been reduced to include only two fourteen hour shifts and three~eight hour shifts per week unless
.opacial requests are made.
It is not expected that this change will result in any significant. decrease in reactor utilization.
An NSC.
"Uners Group" has been created and meets periodically to discuss experimenter'needs and ways in which the NSC can be of better service.
This increased communication between users and NSC management will hopefully improve _ utilization even more.
Core VIII, established in December 1982, was used throughout 1983 Pulse operations were reinitiated in February 1983 for the first time since.1976, and a total of 75 pulses ($116.36 total pulse reactivity).were executed.
A detailed pulse test program to monitor
.psak core, temperatures and to periodically inspect certain fuel ele-mtnts was completed satisfactorily.
Several major facility projects, modifications, and improvements ware' completed during the past year. "A total of 10 FLIP fuel elements Tand 41 Standard. fuel. elements were shipped in August 1983 to Argonne National Laboratory in Idaho Falls,' Idaho.
A new dual dryer system was installed in the facility dry air system, and the facility air
- monitor' manifold was modified for more efficient operation. A new room,was built outside the main confinenent building to house the facility airimonitor electronic equipment which is also to be upgraded
-in the nearJfuture.
Improvements were also made to the south pneu-
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inttic station and the pneumatic system controller for laboratory
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and new digital sample timers were added in the reactor control Droom.
An upgrade of the demineralizer room. started in 1982 was com-
- pleted and involved repainting and floor resurfacing for better drain-
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l Several operational problems occurred in 1983 but did not result in a significant loss in reactor operating time.
During a scheduled core inspection prior to reinitiating pulsing operations two addi-tional fuel elements failed to pass the inspection requirements and ware, therefore, removed from the core and declared non-usuable for rOcotor operation".
A leak i.n waste storage tank #2 was corrected by cleaning and patching.
Both demineralizer room sump pumps failed during the year and-had to be replaced.
The secondary cooling pump c1co failed but was able to be mechanically corrected.
A reportable occurrenca from December 1982 concerning an overpower incident re-sulted in an NRC enforcement conference in March 1983 This con-forence was held with NSC administrative personnel to emphasize the nood for proper operator training and administrative controls to avoid similar problems in the future.
Administratively during 1983 Donald E. Feltz was officially named Director following a short period of serving as Acting Director.
Dale Rogers was named Assistant Director.
Management and supervisory positions have been filled and these individuals have gained valuable experience during the past year.
Personnel turnover has been sta-bilized at the present time.
n i -
3 II.
REACTOR UTILIZATION A.
Utilization Summary Utilization of the NSCR during the reporting period is shown in Figure 1 and Table I.
Figure 1 presents reactor operation from January 1969 through December 1983 During the present reporting period the NSCR was used by approximately 1750 students (includes 1724 involved in tours or lab work and 28 student researchers) and 39 faculty and staff members representing 16 departments at Texas A&M University.
In addi-tion, more than 300 faculty and students from 11 other educa-tional institutions used the facilities, and 5008 visitors were registered during 1983, including several public and private school groups.
A total of 15 non-university organi-
.zations had programs that were dependent upon the NSCR.
During twenty one years of operation, the NSC has pro-vided services to 40 departments at Texas A&M University, 103 other colleges and universities, 78 industrial organizations, and 20 federal and state agencies.
(See Appendix IV and V for listings).
B.
Utilization by the Texas A&M University System A NSC " Users Group" was formed in September 1983 This group is comprised of 12 researchers representing 7 university departments and one outside state-supported organization.
Dr. Gerald Schlapper of the Nuclear _ Engineering Department was elected Chairman of this group.
Members were asked by the WSC staff to aid in the collection of research information to obtain a more detailed accounting of realized research funding to the TAMU System as a result of utilization of the NSC.
This survey was conducted based on the following questions directed toward each experimenter contacted:
1.
Did the research performed depend upon the reactor for an integral part of the results obtained?
2.
What TAMU departments and/or other universities were in-volved in the research?
What students, Masters or Ph.D.,
were involved?
3 What was the total dollar amount of the funding received?
4.
Are there any proposals pending that rely upon the NSCR7 If so, what are the dollar amounts?
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TABLE I f
REACTOR UTILIZATION
SUMMARY
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1983 Annual Total cNumber of Days Reactor Operated 229
. Reactor Operation (MW-Days) 94.60 Number of Hours at Steady State 2376.9 Average Number of Operating Hours Per Week 47.5 Total Number of Pulses 75 Total Pulse Reactivity Insertion
$116.3d Number of Irradiations 865 Number of Samples Irradiated 16046 Sample-Irradiation Hours 134218.8 Average Number of Irradiations per Operating Day 3 78 Irradiation Experiment-Hours 14931.9 Beam Port Experiment-Hours 40.4
' Irradiation Cell Experiment Hours 0
Total Experiment-Hours 14972.2 Fraction of Utilization Attributable to Commercial Work 39
. Number..of Visitors 5008 cNote:
50 Weeks of Operation Available
6 The results of this survey show that the highest percentage of research dollars was generated by the College of. Science.
This is due mainly to the neutron activation analysis program (NAA) conducted by the Center for Trace Characterization.
The College of Geosciences leads the way in pending research dollars.
It is interesting to note that 70% of these research dollars were the result of the use of the NAA programs offered by the NSC and CTC.
It is our conclusion that these figures justify more interest and support for the NSC from the university.
At this time-information is being gathered on the research dollar amounts realized by non-university users as a result of utilizing the NSC.
Results of the survey of the TAMU users are presented in Table II.
Table II Total Research Dollars to TAMU Resulting From Utilization of the NSCR Research Research dollars Percent of Dollars (81-83)
Total (81-83)
(Pending)
College of Veterinary
$250,000 11.6
$30,000 Msdicine College of Engineering 370,142 17.2 244,855 College of Agriculture 80,000 37 325,000
. College of Geosciences 272,500 12.7 550,000 College of Science 1,174,228 54.8 205,000
$2,146,870 100
$1,354,855
F 7
I During 1983 the following personnel from various depart-i ments at Texas A&M University used the NSCR for research.
I
. Appendix I' describes some of the projects completed.
Chemistry Department Faculty and Staff:
Dr. M. W. Rowe, Associate Professor Dr. Y. N. Tang, Professor Dr. A. Clearfield, Professor Dr. R. Zingaro, Professor Dr. M. S. Mohan, Visiting Professor Students:
M. Tobey B. Menta W.
Ilger L. Garza B. Roberts D. Ilger Civil Engineering Faculty and Staff:- Dr. A. McFarland B. Harbert, Lecturer Students:
B. Diot Biology Faculty and Staff:
Dr. K. Aufterheide, Assistant Professor Students:
V. Simmons J. Terrio Center for Trace Characterization Staff:
Dr. D. James, Research Chemist Dr. M. Akanni V. Ogugbuaja, Technician T. Woods, Technician Nuclear Engineering Department Faculty:
Dr. C. A. Erdman, Professor and Head Dr. F.
R'.
Best, Assistant Professor Dr. R. R. Hart, Professor Dr. J. D. Randall, Professor Dr. T. A. Parish, Associate Professor Dr. G.
A. Schlapper, Assistant Professor Students:
J. O'Donnell K. Welch M. Schuller G. Sjoden H. Giap M. Whiteacre S. Vrana J.
Pina T. Powell D. Goodman S.
Lee E.
Parma
8 Nuclear Science Centep Staff:
R. D. Rogers, Assistant Director Y. Contreras, Health Physicist R. Land, Research Assistant J. Head, Manager of Technical Services K. Head, Research Associate Animal Science Department Faculty and Staff:
Dr. W. C. Ellis, Professor V. Latimer, Technician Students:
D. Delaney B. Uarrington L.
Roth Radiological Safety Office Staff:
Dr.
R. D. Neff, Radiological Safety Officer J. Simek, Assistant Radiological Safety Officer P. Sandel Students:
R. Yupari J. O'Donnell Veterinary Physiology and Pharmacology Faculty:
Dr. D.
Hightower, Professor Students:
D. Followill B. Copeutt In addition to the research performed by the above per-sonnel, the.NSCR was used as an educational aid in numerous academic courses offered by the University.
Table III indi-cates the academic courses and the number of students using the facility.
-C.
Utilization by Other Educational Institutions In addition =to Texas A&M University, services were pro-vided to the following educational institutions through the Department of Energy Reactor Sharing Program.
A description of some of the projects utilizina, the react or is presented in Appendix I.
9 TABLE III ACADEMIC USE OF THE REACTOR No. Stuckents Department Course No.
Instructor and Purpose Architecture 633 Trost 13 - Tour Building Construction 336 Woods 31 - Tour Chemistry 116 Kolar 140 - Tour Ch;sistry 116 Kolar 135 - Tour Chcmistry 116 Kolar 128 - Tour Ch:mistry 116 Kolar 92 - Tour
.Chtmistry 116 Kolar 130 - Tour Ch;mistry 116 Kolar 18 - Tour
.Ch:mistry 116 Kolar 149 - Tour Chtr' ry 116 Kolar 138 - Tour Cha.a
.y 116 Kolar 90 - Tour Chosistry 116 Kolar 133 - Tour Ch:mistry 116 Kolar 132 - Tour Engineering Design Graphics Vinson 12 - Tour E.D.I.C.
354 Janke 25 - Tour E.D.I.C.
354 Janke 15 - Tour
.E.D.I.C.
354 Janke 22 - Tour E.D.I.C.
354 Janke 10 - Tour E.D.I.C.
354 Janke 38 - Tour E.D.I.C.
406 Horn 26 - Tour Industrial Education 144 Marshall 16 - Tour Gastrock 4 - Tour Naval Science Navcl Science Gastrock 10 - Tour Nuclear Engineering 101 Brady 74 - Tour Nuclear Engineering 405 Randall 9 - Lab Nuclear Engineering 405 Randall 15 - Lab / Class Nuclear Engineering 405 Randall 12 - Lab / Class Nuclear Engineering 405 Randall 12 - La'o/ Class Nuclear Engineering 408 Land 16 - Lab Nuclear Engineering 479 Schlapper 14 - Class Nuclear Engineering 479 Schlapper 15 - Lab Nuclear Engineering 606 Randall 9 - Lab R: creation and Parks 375 Kaiser 18 - Tour R; creation and Parks 375 Kaiser 23 - Tour Total 1724
10 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 Sam Houston State University -- Huntsville, Texas Faculty:
Dr. Charles Manka -- Physics Department Dr.
B. Covington Dr. C. Fitzpatrick Dr. Grun Students:
Physics Classes J. Minton Baylor University -- Waco, Texas Faculty:
Dr. Robert McLaurin Dr. Wong Students:
Physica Classes Texas State Technical Institute -- Waco, Texas Faculty:
Mr. Carl Kee -- Chairman Nuclear Technology Students:
Nuclear Technology Classes Texas State Tecnnical Institute -- Harlingen, Texas Faculty:
Mr. Pedro Jimenez -- Chairman Nuclear Technology Students:
Nuclear Technology Classes Louisiana State University -- Baton Rouge, Louisiana Faculty:
Dr. R. Knaus Sul Ross University -- Alpine, Texas Faculty:
Dr. D. Nelson Dr. G. D. Mattison Dr. D. Rohs Texas Tech University -- Lubbock, Texas Faculty:
Dr. C. R.
Richardson -- Animal Science Student:
Mike Conner, Ph.D. Dissertation J
11 Public and Private School Tours No. of Students Beaumont Charleton High School -- Beaumont, 30 Texas Cyprus Community School -- Houston, Texas
, 45 Montgomery High School -- Montgomery, Texas 19 Carlisle High School -- Henderson, Texas 25 Henderson High School -- Henderson, Texas 24 Harden Jefferson High School -- Sour Lake, 15 Texas Brookshire High School -- Brookshire, Texas 14 Tomball High School -- Tomball, Texas 24 Madisonville High School -- Madisonville, 52 Texas Fayetteville Jr. High School -- Fayetteville, 33 Texas St. Joseph School -- Bryan, Texas 36 Navasota High School -- Navasota, Texas 15 Others (Career Day) --
164 D.
Utilization by Non-University Institutions National Aeronautics ar# Space Administration -- Houston, Texas Experimenters:
M. Strait Dr. D. Blanchard Nuclear Sourqes and Services -- Houston, Texas Experimenters:
R. C. Gallagher E. Johnson Shell Development Company -- Houston, Texas Experimenters:
L. H. Griffin J. Papajohn E. L. Woody Texas Instruments -- Dallas, Texas Experimenters:
S. Halfacre B. Gnade Gulf Nuclear -- Houston, Texas Experimenters:
A.
Payne G.
Pettyjohn l
12 M.
D.
Anderson Hospital (University of Texas Medical Center)
Experimenters:
Dr.
R. Tilbury Dr. C.
Reading Dr.
C. H. Poynton J. Cundiff Hughes Research Labs -- Malibu, California Experimenters:
Mr. E. Wesel Dr. R. Hart E. Parma Hughes Aircraft -- Carlsbad, California Experimenter:
Mr. D. Bell General Electric Company -- Mount Vernon, Indiana Experimenter:
G.
R.
Ashley Tracerco -- Houston, Texas Experimenters:
W.
Ramage Dr. Ferguson J. Landry Tech-Sil -- Houston, Texas Experimenter:
M. Welch White Sands (U.S. Army) -- White Sands Missile Range, New Mexico Experimenter:
Capt. J. Bliss Gulf Science and Technology -- Cheswick, Pennsylvania Experimenter:
E. Miller Jim Beck, Consultant -- Lake Charles, Louisiana Experimenter:
Dr. J.
Beck Universal Technology Corporation -- Dayton, Ohio Experimenter:
Dr. R. Hart
13-
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III.
FACILITY OPERATIONS A.
Facility Safety and Operational-Improvements Demineralizer Room Upgrade The degradation of the demineralizer room floor and the chemical contamination problems that result during demineralizer regeneration have seriously deteriorated the floor and sump.
In addition, the chtmical contamination.was a serious hazard to personnel working in the demineralizer room.
A project was undertaken and brought to completion that included the following major areas of improve-ment:
1)
Provide an acid and caustic drain line directly from the caustic tar.k and the acid pump to the demineralizer room sump.
2)
Minimize tne amount of area of the floor that is exposed to chemical leakage and spillage by cutting a trench drain below the demineralizer piping and regeneration components that con-tribute to this contamination.
3)
Provide an overall improvement in the demineralizer room drainage.
4)
Recondition and coat the demineralizer room sump to minimize further chemical damage.
Figure 2 shows the demineralizer room floor plan in its present condition.
Facility Paging System Improvements
. The NSC paging-system was a source of continuous problems due to decreased performance of the, outdated amplifier system and wiring
' problems that resulted in improper impedance matching of the paging eptakers.- A reliable' paging and facility-wide communication system
-10 vital to safe and efficient facility operation.
The system wiring problems were investigated and systematically corrected, and indi-vidual. phone units were repaired as necessary.
A new amplifier
-was installed whichLresulted in a significant-improvement in overall
-system quality and reliability.
Further improvements are planned in the-replacement of.many of the outdated phene units as new units are purchased or made available.
B.
' Improvements to Reactor Systems and Experimental-Facilities Facility Air Monitor System Improvements
- Several improvements to the facility air monitor system have
.cither been made or are currently in progress.
These improvements
. include: the following:
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The sampling lines to the Facility Air Monitor (FAM) units and the vacuum suction lines were either modified or replaced.
The major area of improvement was in the suction line manifold, which controls air flow through the detectors, and in the flow meter layout.
The lines to each unit, the valves, and the flow-meters were arranged in a more orderly manner than the previous system.
Additionally, a flow diagram was provided beneath the
-suction lines on the manifold support structure.
The modified system is as shown in Figure 3, and the design provides a means.of cross connecting detectors such that required monitors can be backed up by those not required.
In addition calibration and air flow standardization has been greatly simplified by use of convenient connections on the new manifold.
2)
The FAM detector and electronic systems are currently in the process of being upgraded to a more state-of-the-art system.
A separate room has been constructed within the mechanical equip-ment room to house the FAM electronic counting equipment in an air. conditioned environment.
The purpose of this change is to consolidate the electronics to control the operating environ-ment, and to provide a centralized location in which to conduct a radiation hazard analysis during an emergency.
Laboratory #4 Pneumatic Controller The pneumatic system controller for Laboratory #4 was modified into a more compact digital unit with a less complex set of control buttona.
The. modification is a convenience measure to the experi-manter operating the pneumatic' system.
A " permit switch" in the rGactor control room transfers control to the experimenter who selects the desired irradiation time.
Dry Air System Modification In May 1983, the dry air supply system for the transient rod was modified-by installing two new self regenerative dessicant dryers,
- n new air chiller, and associated oil and particle filters.
The system, shown in Figure 4, has an increased air drying capacity and improved moisture removal capabilities.
Control Room Sample Timer A new digital sample activation. timer unit was designed and installed in tne reactor control room.
The timer is capable of
. timing the-irradiation of six samples simultaneously.
The modified timer improves the timing of irradiations by incorporating a warning
.fonture.that alarms-two minutes prior to completion of the irradiation and again when.the sample irradiation has been completed.
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18 South Pneumatic Station Modification The pneumatic control solenoids and associated CO2 gas lines were modified, and the system, including the gas supply. valves, was mounted on a wall bracket.
The system line-up efficiency is increased significantly since the piping and valves are arranged in a symmetric configuration which enables the operator to visualilze and accomplish the desired system line-up.
The south pneumatic station is presently as shown in Figure 5 Beam Port #4 Modifications Modifications have been proposed by the NSC staff to upgrade Beam Port #4 with the installation and calibration of a beam shaper, an improved beam port reflector, and a new water shutter.
The beam shaper and filter is installed and the calibration and adjustments are being made at the present time.
The plans for the reflector and water shutter are being completed, and the project should be completed in 1984.
C.
Operational Problems t
Failure of Demineralizer Room Sump Pumps Through twenty-three years of service, regeneration chemicals slowly destroyed the carbon steel casings on the demineralizer sump pumps and both were rendered out of service.
The pumps were removed and a temporary casing patch was used to return one of the pumps to service.
Two new pumps with stainless steel casings and internal components were received and installed in July 1983, and the system was returned to service.
Waste Storage Tank Leakage A leak in waste storage tank #2 was corrected by cleaning and patching.
In addition a new water stirrer was installed, and the tank was returned to service in June 1983 Failure of Two Additional Fuel Elements to Pass Fuel Inspection Criteria In January 1983 during a partial ccre inspection of selected high temperature elements it was discovered that one element failed to pass the "go/no go" criteria which indicated that either excessive bowing or swelling had occurred.
Since this inspection was being made prior to reinitiation of pulsing operations it was decided to inspect and measure all fuel elements in the reactor core.
Con-siderable effort was involved in this, and the inspection was com-pleted in a relatively short period of time.
It should be noted that one additional element failed the inspection criteria.
These two elements were included in the fuel snipment to ANL-West (Idaho Falls, Idaho) in August 1983
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20 Sncondary Cooling System Pump Failure In SeptemberL1983 an excessive vibration in the secondary cooling pump was-observed, and an investigation showed the most. probable craa of component failure to be the upper and/or lower bearings of the-motor.
Replacement bearings were obtained and installed while secondary cooling flow was maintained utilizing a fire depart-
'msnt pumper truck, such that no reactor operating time was sacrificed.
The pump was tested satisfactorily and returned to service, but it was noted that further maintenance may be necessary in the future dus to overall wear of the pump shaft and bushings.
Additionally, it is suspected that some-settling of the pump and cooling tower foundations may have occurred and could be contributing to pump
.minalignment problems.
Further investigation of this situation is planned as the maintenance schedule permits.
Control Rod Drive Units Several incidents of dropped shim safety control rods during the year have been attributed to either deterioration of the scram magnet coil or deterioration of the coiled extension wiring through which the scram. magnet current is supplied.
A suitable replacement wiring was developed, and all shim safety rod drives (including the spare rod drive) were upgraded by replacing the original equipment with an equivalent coiled wiring.
No further rod drops have since occurred that are directly attributable to deterioration of the coiled extension wiring.
Additional shim safety rod drive unit problems that have been experienced are due to the critical upper and. lower limit switch adjustments that must be made as a drive unittis installed and tested for operability.
A design change of the limit-switch adjustable mounting bracket is expected to be ad-dressed-by~the.NSC staff.
The maintenance problems experienced with the rod drive units, as described above, have resulted in losses of scheduled-hours of operation.
USNRC~ Enforcement Conference A reportable occurrence from December 1982 concerning an overpower
' incident resulted in an NRC enforcement conference held in March 1983 Representatives from USNRC Region IV met with NSC adminis-trative personnel to emphasize the need for proper administrative controls and improved operator training to avoid similar occurrences in-the future.
In addition a two year program has been implemented to upgrade existing standard operating procedures.
Reportable Occurrences
' Bowing Observed in-Fuel Elements #7463 and #7386
~-During a fuel element in.epection being performed on 5 January 1983:it was discovered that element #7463 failed the go/no go test.
________--_____m-___
21 A slight bowing was observed and the element appeared to be somewhat puffy about midheight.
There was not, however, any cladding rupture or apparent scratches.
A complete core unloading and fuel inspection wna performed and one additional element, #7486, failed the 60/no go test due to bowing.
Again, there was no cladding rupture or covere scratches present.
In reviewing the history of these two elements it was found th t both elements were in the core since 1973 and had not been inapected since that time.
In addition both rods were in approxi-m2tely the same position relative to the transient rod during past pulsing operations.
These elements were not inspected at the time fuel damage was first discovered in 1976 since other elements in aimilar core locations were found to have no visible deformation.
It should also be noted that the elements inspected at the time of discovery of fuel damage were reinspected during this past shutdown and showed no signs of abnormal wear.
Based on this information it is felt that elements #7463 and #7486 were bowed during pulsing operations prior to September, 1976 and have operated at steady state in that condition since that time.
These two elements have barn removed from the reactor core, and steady state reactor operation hao continued.
Failure of Fuel Thermocouple During Reactor Startup On January 10, 1983 during a reactor startup to 400 kilowatts 4
it was noticed by the reactor operator that the fuel temperature I
indication was not tracking.
This startup was the initial startup following a core loading during which the instrumented fuel element wns hzadled.
The thermocouple was verified operational prior to startup and indicated approximately ambient pool temperature.
It was not until the reactor was above the point of adding neat that the operator noted no increase in fuel temperature.
At that point
- the startup was discontinued, and the reactor was shutdown for in-vestigation.
Shorted thermocouples wires were discovered in a terminal box causing the indication to read approximately ambient temperature at all times.
The problem was corrected, but during subsequent operation at 400 kilowatts, it was noted that the fuel temperature indication was somewhat lower than that indicated on a second thermo-couple (TC #2) in the same element.
Therefore, the reactor was shutdown again, and the fuel temperature instrument was connected to the more conservative (highest) indication (TC #2 in IF #8795).
The reactor has operated since that time with no further problems.
Possible Operation in Excess of Licensed Power Level
.Due to an unexplained disagreement between the linear and safety channel' indications the reactor was operated approximately 5% above its licensed power for nine hours on October 3, 1983 The incident
22 was initiated during reactor operation following movement of the reactor away from an experimental device known to have a' negative rcactivity worth.
The startup performed following movement of the
-rcactor resulted in slightly higher fuel temperature and safety channel indications.
These differences were noted by the operators involved but were not pursued.
During this time both safety am-plifiers indicated 106% while the linear channel, considered to bs the " prime standard" power indicator, indicated a power level of 1 Mw.
The differences in core parameters were not questioned since minor shifts in safety amplifier readings had been observed on prior occasions due to xenon and experimental conditions in the core.
Calorimetrics were performed to determine reactor power, and operation has been limited to 95% power until a thorough study can ba completed to determine actual core power as compared to linear channel indication.
In addition an immediate upgrade program was initiated for reactor operations personnel.
D.
Reactor Operations Related Items R9 initiation of Pulsing Operation Due to the need to pursue research and experimental studies utilizing the NSCR pulsing capabilities, a study was conducted to regain this capability.
An extensive pulse test program was de-voloped and presented for review by the Reactor Safety Board.
The program was approved and initiated in February 1983 and phase I of this program was successfully completed and reported to the USNRC.
i Facility License Renewal A facility license R-83 was renewed by the USNRC in March 1983 and is valid for twenty years from date of issue.
Compliance with license requirements and associated technical specification was immediately established.
Funl Shipment In August 1983 the NSC and ANL/ West (Idaho) conducted the transfer of 41 Standard and 10 FLIP irradiated TRIGA fuel elements in a DOE / DOE shipment to the ANL/ West facility.
The shipment was performed following considerable advance preparation on the part of both facilities.
Revision of NSC Normal Schedule of Operation In September 1983 the normal operation schedule of the NSCR was adjusted to include a second shift (14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> of operation) on Monday and Tuesday only.
A standard day of operation from 8: 00 A.M.
to 5: 00'P.M. was established for Wednesday through Friday, clthough special arrangements can be made in advance for reactor opsration at times other than those normally scheduled.
23 Messurement of Withdrawal Times For Transient Rod During Pulsing Operation A timing device developed for the transient rod allows monitoring
~of rod withdrawal times during puling operation.
This device (see Figure 6) consists primarily of a light source /phototransistor as-s:mbly mounted on the guide tube and a graduated photographic negative attached to the rod extension.
A square wave signal of varying pulse width and repetition rate is generated dependent upon rod spred.
The signal is captured on an oscilloscope with storage c:pability and can be compared to a neutron flux signal which is triggered by the first pulse generated by the timing device.
E.
Changes in Operating Procedures The following changes to SOP's were reviewed and approved by the RSB during the reporting period:
SOP Number Subject II-B Operationa Records II-C Reactor Startup II-D Steady State Operation II-E
~ Pulsing Operation II-F Reactor Shutdown II-J Power Calibration II-K Control Rod Calibration II-L Pulse Calibration III-C Linear Power Measuring Channel Maintenance and Surveillance III-G Reactor Pulse Power Surveillance III-P Millivolt Potentiometer Maintenance and Surveillance IV-A Experiment Approval VI-A General VII-A Health Physics Administration VII-B Health Physics Maintenance and Surveillance F.
Unscheduled Shutdowns A total of nineteen unscheduled shutdowns occurred during 1983 As can be seen several were electronic in nature due to equipment ago.
The unscheduled shutdowns can be arranged in the following categories:
i
TRANSIENT ROD EXTENSION
~
PHOTOTRANSISTOR CASSETTE muu L
?
TAPE uma PHOTOTRANSISTOR RECORDER E
BIAS / PULSE e
SHAPING CIRCulT d-
'I di g
DC M
PUL5E POWER o
c SUPPLY INTEGRATOR DUAL TRACE OSCILLOSCOPE PULSE DETECTOR -.-
Figure 6.
Transient Rod Timing Device 1
25 Cause of Shutdowns Number of Shutdowns Building power loss 6
Operator error 6
Electronics 7
G.
Reactor Maintenance and Surveillance 1.
A calibration of the fuel temperature measuring channel was completed on 1-10-83 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 and comparing the fuel element temperature and the pool water temperature prior to reactor startup.
3 Control rod calibrations for 1983 were as follows:
Core VIII (12-3-83)
Control Rod Rod Worth SS #1
$2.64 SS #2 1.64 SS #3 2.21 SS #4 4.23 RR
.85 TR 2 74
' Shutdown Margin 4.71 In addition to the above measurements several calibrations were performed on the transient rod to determine if there was a significant difference in total worth under various xenon and experiment load conditions.
The following re-sults were obtained in February:
Control Rod Rod Worth TR (2/4/83)
$2.89 (with xenon, reactor against beam port reflector).
TR (2/7/83) 2.72 (xenon free, against re-flector).
TR (2/11/83) 2.69 (with xenon, away from reflector).
TR (2/14/83) 2.65 (xenon free, away from reflector).
J
26 4.
The reactivity worth of all experiments was either estimated
~
or measured, as appropriate before reactor operation with the experiment.
The most reactive experiment irradiated had a worth of $ 0.16.
5.
Pulse operations of the NSCR were reinitiated in February 1983 At that time a detailed test progran was implemented to determine the pulse reactivity limit corresponding to the technical specification limit of 830aC maximum core temperature.
In addition visual and measurement inspections were required on potential high temperature elements through-out the program.
Pulsing continued throughout the year with no indication of abnormal fuel wear or damage.
6.
The scram times of the control rods were measured with the following results:
Date Control Rod Time in seconds 1-8-03 ss #1 956 TR 1.16 1-9-83 ss #2 596 ss #3 709 ss #4
.732 1-12-83 ss #2
.648 1-18-83 ss #4
.692 2-25-83 ss #4
.628 ss #4
.676 4-1-83 ss #1
.684 ss #3
.676 4-18-83 TR 1.174 4-20-83 TR
.86 5-5-83 ss #4-
.67 5-13-83 ss #1 744 6-30-83 TR
.84 7-5-83 TR
.868 7-11-83 ss #2
.654 7-14-83 ss #1
.626 7-21-83 ss #2
.60 8-10-83 ss #3
.684 9-7-83 ss #1
.604 9-8-83 ss #1
.604 9-30-83 ss #1
.566 I
27 Date Control Rod Time in seconds 10-14-83 ss #2
.594 10-21-83 ss #4
.679 ss #2
.628 11-11-83 TR
.828 11-23-83 ss #2
.624 ss #1
.608 7
A Channel test of each of the reactor safety system channels for the intended mode of operation was performed prior to each day's operation.
The pool level alarm was tested weekly.
8.
Channel calibrations were made of the power level monitoring channels by the calorimetric method as follows:
Indicated Actual Core Date Power (Kw)
Power (Kw)
% Error Loading 1-10-83 400 448
- +22.0 VIII 1-11-83 400 343
- -14.2 VIII 1-17-83 400 375
- 6.2 VIII 10-5-83 400 370
- 7.5 VIII 10-10-83 400 417
+ 4.0 VIII I
- It should be noted that the large error was a result of detector repositioning during annual maintenance and was corrected prior to operating the reactor at licensed power.
9 The ventilation system was verified to be operable by con-ducting a test of the system each week throughout the year.
- 10. Emergency evacuation drills were conducted on 3-25-83 and 7-15-83
- 11. Weekly checks were performed throughout the year to verify that the NsC security alarm system was operable.
- 12. Calibration dates for facility air monitors and area radiation monitors were as follows:
Monitoring system Date of Calibration Ch #1 - stack Particulate 7-28-83 Ch #2 - Fission Product 6-4-83 Ch #3 - stack Gas 7-28-83 Ch #4 - Building Particulate 7-22-83 Ch #6 - Building Gas 7-28-83 Area Radiation Monitors 10-7-83
28 i
- 13. A review of the NSC security plan was conducted by the NSC staff and the Reactor Safety Board on January 28, 1983
1 29 IV.
FACILITY ADMINISTRATION A.
Organization The organization chart for reactor operations at the Nuclear Science Center is presented in Figure 7.
During this reporting year Donald E. Feltz was named Director, and R. Dale Rogers was promoted to Assistant Director.
Gary Waldrep re-signed as Manager of Technical Services and was temporarily
. replaced by Dr. R. T. Perry.
Jerald Head has since assumed the duties as Manager of Technical Services upon the transfer of Dr.
R. T. Perry to the Nuclear Engineering Department at Texas A&M University.
Barry Willits was assigned as Manager of Reactor Operations, and Terry Rolon was promoted to Reactor Supervisor following the resignation of Dan Rodgers.
Barry Willits and Jerald Head received senice reactor operator licenses and Scott Thomas received his reactor operator license in 1983 A reduction in the reactor operating schedule effec-tive in September resulted in a small cutback in personnel,
-and John Theis has terminated as Reactor Supervisor.
The NSC does, however, employ students on a part-time basis when full-l time help is not available.
B.
Personnel The following is a list of personnel at the Nuclear Science Center for the period of January 1, 1983 - December 31, 1983 Facility Administration and Reactor Operations Staff
+Feltz, D. E.
- Director
+Petesch, J. E.
- Reactor Supervisor
+Rodgers, D.
J.
- Reactor Supervisor (Terminated)
+ Rogers, R. D.
- Assistant Director 4
l
+Rolon, T.
R.
- Reactor Supervisor i
l l
4
-e-
DIRECTOR l
l ASSISTANT l
DIRECTOR SUPPORT MANAGER OF GROUP REACTOR OPERATIONS l
1 i
L_____________
REACTOR SUPERVISOR (S) 1 1
1 I
L______________li SENIOR REACTOR OPERATORS REACTOR OPERATORS l
Figure
.7.,
Nuclear Science Center Reactor Operations Organization Chart
'l
31 Facility Administration and Reactor Operations Staff (Cont'd)
+Sims, W. W.
- Reactor Operator
+Theis, J. W.
- Reactor Supervisor (Terminated)
" Thomas, S. R.
- Reactor Operator
+Willits, B. L.
- Manager, Reactor Operations Technical Service and Maintenance Deigl, C.
- Draftsman (Terminated)
Fisher, T.
- Scientific Instrument Maker II Goodman, D.
- Student Technician
+ Head, J. G.
- Manager, Technical Services
- Head, K. M.
- Engineering Research Associate Horn, C. R.
- Mechanical Equipment Foreman Johnson, G.
- Student Worker I
- Khalil, N.
- Co-op Research Aide
" Land, R.
- Engineering Research Associate (Terminated)
Mattern, J.
- Co-op Research Aide Perry, R. T.
- Manager, Technical Services (Terminated)
Restivo, A._L.
- Engineering Research Associate Schneider, L.
- Student Worker I
- Thompson, J.
- Reactor Maintenance Technician Thompson, L.
- Reactor Maintenance Supervisor (Terminated)
+Waldrep, G. W.
- Manager, Technical Services (Terminated)
Whitworth, D. W.
- Draftsman Yupari, R.
- Student Technician (Terminated)
[
- Licensed Reactor Operator
+ Licensed Senior Reactor Operator Clerical Huss, K.
- Receptionist (Terminated)
Mitchell, Y.
- Secretary Ribardo, J.
- Bookkeeper i
32 Health Physics Staff Contreras, Y.
- Health Physicist Deigl, H.
J.
- Senior Health Physicist Rodriguez, L.
- Health Physicist Stehle, W.,
- Health Physicist (Terminated)
Texas Engineering Extension Service (Nuclear Training Staff)
- Bradley, D.
- Secretary (Terminated)
Buchanan, R. J.
- Training Specialist Dunn, R. F.
- Instructor (Terminated)
Holste, C.
- Instructor (Terminated)
- White, R.
- Instructor (Terminated)
C.
Reactor Safety Board Committee Composition Chairman F. Jennings, Director, Office of University Research (January 1, 1983 - December 31, 1983)
Voting Members Dr. F. Sicilio, Professor of Chemistry l
(January 1, 1983 - December 31, 1983)
Dr. R. L. Watson, Professor of Chemistry and Associate Dean of Science
'(January 1, 1983 - August 31, 1983) (Term completed)
Dr. R.
R.. Hart, Professor of Nuclear Engineering (January 1, 1983 - December 31, 1983)
Dr.'E. A. Schweikert, Professor of Chemistry (January 1, 1983 - December 31, 1983)
Dr. K.
L. Wolf, Professor of Chemistry (September-1, 1983 - December 31, 1983) (Initial appointment) l R. Green, Assistant Professor, Small Animal Clinic
- (January 1, 1983 - December 31, 1983)
L Dr. R. A. Kenefick, Professor of Physics j
(January 1, 1983 - December 31, 1983) k
l 33 Ex-Officio Members Dr. C. A. Erdman, Professor and Head of Naclear Engineering (January 1, 1983 - December 31, 1983)
D. E.
Feltz, Director of Nuclear Science Center (January 1, 1983 - December 31, 1983)
Dr. R. D. Neff, Professor and University Radiological Safety Officer (January 1, 1983 - December 31, 1983)
Meeting Frecuency The Reactor Safety Board (RSB) met on the following dates during the calendar year 1983:
1/18/83, 4/13/83, 7/5/83 (Sub-committee), 7/25/83, 10/28/83 RSB Audits During the reporting period RSB audits of NSC activities were conducted on the following dates:
1/14/83, 4/12/83, 7/11/83, 11/7/83 l
I t
~
APPENDIX I Description of Projects Utilizing the NSCR f
1
I-1 DESCRIPTION OF PROJECTS UTILIZING THE NSCR A.
Texas A&M University Nuclear Engineering NEUTRON DOSIMETRY OF A U-Zr HYDRIDE FUELED REACTOR l
Personnel Dr.' Gerald A. Schlapper -- Professor John O'Donnell -- Graduate Assistant Neutron spectral measurements were made in_various locations in the reactor core.
These measurements were made using threshold foils during both steady-state and pulse operations.
Information obtained will be used in other pending research involving the NSCR.
SELF-ANNEALING EFFECTS ON NEUTRON TRANSMUTATION DOPED SILICON Personnel Dr. Ron R. Hart -- Professor A' study was performed for Universal Technology Corporation to determine the effect of self-annealing on energy levels in neutron transmutation doped (NTD) silicon.
This project was a joint effort involving the University of Missouri Research Reactor (MURR) and the NSCR.
Silicon' samples doped at the NSC were compared to those doped at MURR where self-annealing due to gamma heating is signifi-cant.
These results were then used by the Air Force Wright Aero-j nautical Laboratory (AFWAL) to characterize NTD silicon for detectors.
NEUTRON FLUX PROFILE MEASUREMENTS IN THE NSCR Personnel Dr. Gerald A. Schlapper -- Professor Glenn Sjoden -- Student Reactor _ flux profile studies were performed using bare and cadmium i
i covered cobalt wires.
Information gained is part of an increasing effort to better characterize the NSCR.
KINETICS AND CONTROL OF A SPACE REACTOR DESIGN Parsonnel Dr. Gerald A. Schlapper -- Professor Steve Vrana -- Graduate Assistant
I-2 Comparisons of measured and calculated response of the NSCR during pulsing were made to test a computer based kinetics model.
This model is being developed for research pending with the U.S.
Air Force.
FLUENCE MONITOR CALIBRATION OF-MRID FOR NTD OF SILICON Personnel Dr. Ron R. Hart -- Professor Kenneth L. Welch -- Graduate Assistant Jerald G. Head -- Technical Services Tom Fisher -- Electronics Technician A current integrating device, designed and constructed by NSC staff, was calibrated for use with a self-powered neutron detector to monitor MRID during irradiations of Silicon ingots.
This system should provide more accurate predictions of Phosphorus concentrations achieved.
ANALYSIS OF SORBER PERFORMANCE ON THE RECOVERY OF URANIUM FROM SEAWATER Personnel Dr. Frederick R.
Best -- Assistant Professor Huan Giap -- Undergraduate Jose Pina -- Graduate Assistant The uranium concentration profile for hydrous titanium oxide
(
pollets and acrylic amidoxime resins POG503 and 501 were determined j
using track-etch techniques.
Measurements showed that all three l
sorbers have an inert core region that contained no uranium so that the uranium concentration in the enriched rind is much higher than the bulk uranium concentrations measured by other techniques.
FUSION REACTOR BLANKET RESEARCH Personnel Dr. T.
A. Parish -- Professor Mike Schuller -- Graduate Assistant l
l Further studies in fusion reactor blanket research were performed.
In these experiments, tritium was produced by irradiating lithium fluoride wafers.
Measurements of tritium content were then made and compared to calculated values.
The goal of this project is to determine the feasibility of a LiF and water slurry as a fusion ramotor blanket.
SORBER PERFORMANCE DATA ON THE RECOVERY OF STRATEGIC ELEMENTS FROM SEAWATER Personnel Dr. Frederick R. Best -- Assistant Professor r
Matthew'M. Whiteacre -- Graduate Assistant
I-3 NAA was used to determine the total elemental analysis of 17 different sorbers exposed to natural seawater for periods of 3 to 7 days.
Potentially interesting quantities of aluminum, vanadium, chromium, cobalt, and molybdenum were found.
DEVELOPMENT OF AN AUTOMATIC FLUX WIRE COUNTER Parsonnel Dr. G. A. Schlapper -- Professor David Goodman -- Student Interest in reactor flux profiles led to the development of an automatic flux wire counting device to eliminate the tedious procedures used in the past.
The device consists of a stepping motor, a beta scintillator detector and a multichannel scaler.
Bata particle emitting wires can then be counted continuously to yield a flux profile for the core without having to cut the wire into smaller pieces.
Chemistry COMPLEXES AND CATIONS SUPPORTED ON THE SURFACE AND.BETWEEN LAYERS OF ZIRCONIUM PHOSPHATE I.
COPPER (II) AND ITS AMMONIA COMPLEXES Personnel Dr.
A.
Clearfield -- Professor Bharati Menta -- Post Doctorate Neutron activation analysis was used to determine cation content of complexes placed on the surface of Zirconium Phosphate and to o
determine the ion exchange of alkali metal cations.
This information may be valuable in the development of fuel cells based on Zirconium Phosphate conductors.
STABILITY OF HZr2(P0s)3 AT HIGH TEMPERATURES Psrsonnel Dr. A. Clearfield -- Professor Brian Roberts -- Graduate Assistant The compound NaZr2(POS): is the end membe'r of a solid solution
. series of general composition Nai+xZr2Si P _x012 These compounds x3 cra of interest because the solids for which x = 1.8-2.3 are fast ion conductors.
The question arises as to whether the protonic forms of these compounds would also be fast proton conductors.
There is at present a great deal of interest in obtaining heat stable proton conductors for use in a variety of fuel cells.
Our interest stcms from curiosity as to the mechanism of proton conduction in colids as well as the practical use of these materials.
Thus, the problem to be solved is the preparation of HZr2(PO*)s, the determi-nation of its stability to high temperature and eventually to measure ths conductivity.
I-4 A STUDY OF URANIUM IN SOUTH TEXAS LIGNITE Personnel Dr. Ralph Zingaro -- Professor Wayne A.
Ilger -- Graduate Assistant The delayed neutron counting system was used to determine the octual uranium content in South Texas Lignites.
This was part of a project funded by the Welch Foundation and TENRAC to determine tho. quantity and oxidation state of uranium in lignite.
TRACE ELEMENT CHARACTERIZATION OF DEEP BASIN LIGNITES OF TEXAS Personnel Dr. Mysore S. Mohan -- Professor Dr. Ralph A. Zingaro -- Professor Wayne Ilger -- Graduate Assistant Drew Ilger -- Graduate Assistant NAA was used for trace element and uranium analysis of lignite samples from South Texas.
This work was performed to determine analytical concentration and chemical form of the elements in order to predict technological and environmental impact of the use of those lignites as fuel.
ANALYSIS OF CHERT SAMPLES IN RELATION TO-ANCIENT CULTURES Personnel Dr. M. Howe -- Professor Mark Tobey -- Student 1
This investigation was performed as a joint effort between the
. Archaeology and Chemistry Departments.
Chert samples were analyzed using neutron activation analysis in conjunction with the NSCR and the Canberra Scorpio analyzing system.
Trace metals and rare earth elements in-tool samples were identified so that matches between environments and cultures could be made.
This work resulted in l
a trip for the experimenter to gather further data and extend the l
range of the findings.
Studies will continue into 1984.
Center for Trace Characterization ANALYSIS OF NIGERIAN DOMESTIC SOAPS Personnel I
Dr.
M. Akanni -- Visiting Professor Dr. W.
D. James -- Professor Neutron activation analysis was used to determine trace element concentrations'in soaps from Nigeria.
This study was an application of a new technique to determine composition of soaps made from ashes.
I-5
~
BIOAVAILABILITY OF As., ETC. FROM FLY ASH Personnel
~
Dr. W. D.
James -- Professor
~
Victor Ogugbuaja -- Graduate Assistant Neutron activation analysis was used to determine trace element L.
concentrations in rats due to ingestion of fly ash.
This study, funded by EPRI, was performed in conjunction with Battelle Columbus Laboratories.
5 NAA 0F VIOLIN WOODS Personnel Dr. Dennis James -- Professor Dr. J. Nagyvary -- Professor, Biochemistry / Biophysics Samples of wood from violins were analyzed in an attempt to discover the wood treatment processes used during construction.
Analyses seem to indicate that the wood was treated with seawater.
Rasults may lead to a rediscovery of ancient violin construction techniques. Articles on these results were published in Science Digest, Discover, and Science '84.
MEASUREMENTS OF BA, CR, AND V IN MARINE SEDIMENTS Psrsonnel Dr. Dennis James -- Professor Dr. B.
Presley -- Oceanography l
i-Further studies were conducted of trace element concentrations in marine. sediments.
In particular, Ba, Cr, and V released from offshore drilling sites was traced into the environment in marine stdiments.
This is a new approach for sediment tracking.
FATE OF TRACE ELEMENTS IN MHD COAL COMBUSTION Parsonnel Dr. W. D. James -- Professor Dr. M. Akanni -- Visiting Professor Neutron activation analysis was used to determine the trace clement distribution patterns in effluents from magneto hydrodynamic' coal combustion and the results compared to those from conventional coal burning facilities.
I-6 PRELIMINARY FIRE ANT DIET MARKER STUDIES Parsonnel Dr. W.
D.
James -- Professor Dr. S.
B. Vinson -- Professor, Entomology Stable isotope tracer techniques are gaining widespread use in animal science applications.
A similar study may also be possible to gain information on the feeding habits of the fire ant.
Some preliminary measurements of rare earth content of fire ants was performed using NAA Civil Engineering (Air Quality Control)
CHARACTERIZATION OF TEXAS LIGNITES Personnel Dr. Andrew McFarland -- Professor Dr. Dennis James -- CTC Bob Diot -- Graduate Assistant Neutron activation analysis was performed by CTC to characterize and determine the environmental control implications of Texas lignite.
Preliminary studies of asbestos were also performed by NAA and by analysis of thermoluminescent glow curves.
Further work with asbestos is pending in fiscal year 1984.
Radiological Safety Office l
URANIUM CONTENT IN LIGNITE SAMPLES Personnel Dr. R. D. Neff -- Professor John O'Donnell -- Graduate Student The NSC delayed neutron counting system was used to determine the uranium content in lignite samples.
This work was a continuation of studies to determine the biological hazards _of coal combustion.
Biology RADIATION INDUCED MUTATIONS IN PROT 0ZOA Parsonnel Dr. Karl Aufterheide -- Professor Venetia Simmons -- Student James Terrio -- Student
I-7 Attempts were made to induce mutations in cultures of common protozoa using radiation.
Research had already been performed using x-ray and ultraviolet radiation exposures.
Further studies were made at the NSC using thermal neutrons and gamma radiation as the mutagen.
Animal Science l
FLOW OF INGESTED FORAGE PARTICLES THROUGH THE G.I. TRACT OF CATTLE Personnel Dr. W. C.
Ellis -- Professor Vivian Latimer -- Lab Technician Larry Roth -- Graduate Assistant Dave Delaney -- Graduate Assistant Bobby Warrington -- Graduate Assistant Further studies of cattle G.I.
tracts were made using rare earth tracers.
Ingested forage particles were activated and quantities of rare earth tracers added to the feed were measured at various points along the G.I. tract.
Veterinary Physiology and Pharmacology DETERMINATION OF EXCHANGEABLE POTASSIUM IN THE CANINE BY MEANS OF WHOLE BODY COUNTING Personnel' Dr. Dan Hightower -- Professor l
Brian Copoutt -- Graduate Assistant David Followill -- Graduate Assistant l
Comparisons were made of the amounts of exchangeable potassium msasured by the urinary method and those measured by whole body counting to determine the accuracy of whole body counting of canines.
Ssveral dogs were injected with a potassium-42 chloride solution and measurements made of the *2K concentration in urine samples.
until the isotope had equilibrated.
The known amount of **K injected minus that excreted through the urine was compared to the data obtained from a whole body count.
B.
Other Universities Sam Houston State University NEUTRON TRANSMUTATION DOPING AND ACTIVATION ANALYS'IS OF LASER PRODUCED PLASMA DEPOSITS Personnel Dr. B. Covington -- Assistant Professor, Physics Dr. C. K. Manka -- Assistant Pro; 2ssor, Physics
I-8 Continued tests of neutron transmutation doped (NTD) semiconductor materials were peformed to determine more practical applications of'this technique.
Studies were also performed using NAA to determine aluminum released from a laser produced plasmas.
Further research is to be performed using dysprosium as the activant.
Texas State Technical Institute (Harlingen, Texas)
Personnel Mr. Pedro Jimenez -- Chairman, Nuclear Technology During June of 1983, eight students and two staff members from the Nuclear Technology Department spent three days at the NSC for hands-on training in the following topics:
Activation Analysis and Ge(Li) Spectrometry Reactor Pool Water Analysis Shipment of Radioactive Materials Decontamination Exercise Survey Instrument Calibration Gas-Proportional Counting Air Sampling Texas State Technical Institute (Waco, Texas)
Personnel Mr. Carl Kee -- Chairman, Nuclear Technology During 1983, the TSTI Nuclear Technology enrollment was 68 stu-l dents.
During their tenure each student spent approximately 16A clock hours at the NSC.
Therefore, TSTI students spent-approxi-mately 11,152 student hours at the NSC undergoing training in health physics.
Louisiana State University USE OF RARE EARTHS AS STABLE TRACERS Personnel Dr. R. Knaus -- Assistant Professor Studies were made of the slow, natural leaching of Indium, Dyspro-sium, and Samarium stable tracers into a small stream from the car-casses of five 10-15 pound rainbow trout.
Samples were gathered from above (background) and below the point where the trout were allowed to decay naturally.
NAA was then used to analyze these samples.
i l
I-9 Sul Ross State University GEOLOGIC STUDIES
~
Personnel
~
Dr. Dennis 0. Nelson -- Associate Professor Dr. G. David Mattison -- Associate Professor Dr. David Rohs -- Assistant Professor A number of geologic studies were performed using neutron activa-tion analysis.
These studies include:
1.
Geochemistry of the Igneous Rocks of the Davis Mountains, West Texas.
2.
Geochemistry of the Igneous Rocks of Clarion Island, Mexico.
3 Geochemistry of the Igneous Rocks of the Big Bend Park, West Texas.
4.
Geochemistry of the Igneous Rocks of Black Gap, Texas.
5.
Geochemical Characterization of Deep-Water Carbonates.
6.
Composition of Benthic Organisms in a Fresh Water Stream.
7.
Geochemistry of Tertiary Volcanic Rocks, Mexico.
C.
Non-University Institutions Texas Instruments QUALITY ASSURANCE TESTS OF SEMICONDUCTOR MATERIALS USING NAA Personnel Sandra Halfacre -- Texas Instruments Bruce Gnade -- Texas Instruments Silicon samples, activated at the NSC and shipped back to TI in Dallas, were analyzed for trace element impurities.
Elements of interest include Au, Cr, W, Sb, Pt, La, Ga, Co, and K.
Results wsre used to improve production techniques and increase the quality of semiconductors being produced.
White Sands Missile Range USE OF 2'Na AS A MISSILE PROJECT'ILE TRACER Porsonnel Captain John Bliss -- White Sands Missile Rande
I-10
,4 device containing Na 2Co a was activated to produce 1 Curie of Na, This device was then flown to White Sands Missile Range and attached gg a missile which was fired and then aborted in mid-flight.
The Na gammas then provided a means of locating the war-hoed of the missile even though it had buried in the sand.
The test was performed to benchmark trajectory models used to determine the location of missile warheads after being aborted.
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'l APPENDIX II Publications, Theses, and Papers Which Involved Use of 1
NSC Facilities From 1976 to Date l
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11-1 Publications, Theses, and Papers Which Involved Use of NSC Facilities From 1976 to Date 1.
O. F. Zeck, G. P. Genarro, Y. Y. Su and Y. -N.
Tang, "Effect 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 D ifluoride", J.C.S. Chem. Ccmm., 6 (1977).
3 M. D. Devous, Sr., "A Radiation-Induced Model of Chronic Con-gestive 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 and Department of Cardiology, November 1977 5.
D. E. Feltz, J. D.
Randall, and R. F. Schumacher, " Report on Damaged FLIP TRIGA Fuel", Fifth Triga Owner's Conference, Tucson, Arizona, March 1977 6.
J. D. Randall, " Forensic Activation Analysis", NSCR Technical Report No. 36, November 1977
- A 7
Skinner, N.
G.,
" Nuclear Engineering Aspects of Neutron Trans-mutation Doping of Silicon", Master's Project in Nuclear Engi-neering, Texas A&M University, 1977 8.
'R.'R. Hart, L. D. Albert, " Measurement of P-31 Concentrations Produced by Neutron Transmutation Doping of Silicon", Presented at International Conference on Neutron Transmutation Doping, University of Mo., April 1978.
9 D. Wootan, " Measurement of Neutron Flux in Thermal Rotisserie",
Master's Thesis in Nuclear Engineering, November 1978.
10.
Huang, W.,
J. Chatham, " Uranium in Lignite:
I Geological Occurrence in Texas", Tenth International Congress on Sedimen--
tology, Volume 1, A-L, pp. 317, 1978.
- 11. ' Huang, W.,
S. Parks, " Uranium Resources in Some Tertiary Sedi-ments 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.
12.
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 1978.
I
II-2
- 13. Presley, R.J., R. Pflaum, J. Tre' fry, " Fallout and Natural Radionuclides in Mississippi Delta Sediments", Environ-mental Oceanograohic Science, Vol. 59, No. 4, April 1978 (abstract).
- 14. - 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.
- 15. Prasse, E.M.,
" Uranium and Its Relationship to Host Rock Minerology in an Unoxidized Roll Front in the Jackson Group, South Texas", Masters'.Thesic in Geology,_ December 1978.
~
- 16. Lescano, C., W.C. Ellis, "An Evaluation of Lanthanides as Particulate Matter Markers", American Society of Animal Science (abstract), Tucson, Arizona, 1979
- 17. Bachinski, S.W. and Scott, R.B.,
1979, " Rare-Earth and Other Trace Elements Contents and the Origin or Mineetes:
Grochim.
Cosmochim. Acta", Vol. 43, 93.
~
- 18. Scott, R.B.,
- Temple, D.G.,
and Peron, P.,
1979, " Nature'of Hydrothermal Exchange Between Oceanic Crust and Seawater at 260N. Lat., Mid-Atlantic Ridge In Benthic Boundary Layer' Processes", an IOGC_ Symposium on the Benthic Boundary Layer.
- 19. Tiezzi, L.J.,
and Scott, R.B., 1979, "Crystag Fractionation in a_ Cumulate Gabbro, Mid-Atlantic Ridge, 26 N, Lat.:
Jour.
Geophys. Research".
- 20. 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.
Cosmochim. Acta".
l
- 21. 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.
- 22. Scott,-. R.B., ~1979, " Petrology and Geochemistry of Ocean Plateaus",.A TAMU Symposium on Ocean Plateaus.
'23. Clearfield, A.,
and L..Kullberg, "On the Mechanism of Ion-Exchange in_ Zirconium Phosphates:
An _ Equilibrium Study of
' Sodium-Potassium-Hydrogen Exchange on Crystalline Zirconium Phosphates", Jour, of Inorganic and Nuclear Chem., 1979
- 24. 0.F.
Seck, 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).
II-3 25
- Chatham, J.R.,
"A Study of Uranium Distribution in an Upper Jackson Lignite - Sandstone Ore Body, South Texas", Masters' Thesis in Geology, May 1979
- 26. Parks, S.L., " Distribution and Possible Mechanism'of Uranium Accumulation in the Catahoula Tuff, Live Oak County, Texas",
Masters' Thesis in Geology, May 1979.
27
- Miller, M.E.,
" Uranium Roll Front Study in the Upper Jackson Group Alascosa County, Texas", Masters' Thesis in Geology, December 1979.
- 28. Ellis, W.C.,
J.H. Matis, and Carlos Lascano, "A Method for Determining In-Vivo Rates of Particle Size Degradation, Genesis, and Passage from the Rumen", Proc. of 15th Conference on Rumen Function, 1979.
29
- Ellis, W.C., J.H. Matis, and Carlos Lascano, " Sites Contributing to Compartmental Flow for Forage Residues", Ann. Res. Vet, 1979
- 30. Lescano, Carlos, " Determination of Grazed Forage Voluntary Intake", Ph.D. Dissertation in Animal Nutrition, December 1979
- 31. Pond, Kevin, "Effect of Monensin on Intake Digestibility, Gastrointestinal Fill and Flow in Cattle Grazing Coastal Bermuda Pasture", Masters' Thesis in Animal Nutrition, August 1979.
- 32. Losa, Hector, "Effect of Protein Defficiency on Forage Intake and Digestibility", Masters' Thesis in Animal Nutrition, May 1979.
33 Tenhet, Vicki L.,
" Penetration Mechanism and Distribution Gradients of Sodium-Tripoly-Phosphate in Peeled and Deveined Shrimp", Masters' Thesis in Animal Science, December 1979 34.
E.E. Siefert, K-L. Loh, R.A. Ferrieri, and Y.-N.
- Tang,
" Formation of 1-S11acyclopenta '2,4-diene through Recoil Silicon Atom Reactions", J. Am. Chem. Soc., 102, 2285 (1980).
35
- Rowe, M.W.,
E.W. F11 berth, and H.J.
Shaeffer, " Uranium in Huero and Guadalupe Mountain Indian Ceramics", Archaeometry Great Britain, 1980, 36.
- Ledger, E.B.,
T.T. Tieh, and M.W.
Rowe, " Delayed Neutron Activation Determination of Uranium in Thirteen French Rock Reference Samples", Geostandards Newsletters, 1980 37
- Tieh, T.T.,
E.B.
Ledger, M.W.
Rowe, " Release of Uranium from Granitic Rocks During In Situ Weathering and Initial Erosion (Central Texas)", Chemical Geology, 1980.
II-4
- 38. " Core Modification of the Texas A&M Nuclear Science Center Reactor for Improved Commercial Utilization", J.P. Taft with-John D.-Randall and K. Walker, (March 1980).
- 39. '" Organization and Management of Health Physics Support for a Research Reactor", E.F. Bates with R.D. Neff and J.D.
Randall, (March 1980).
i
- 40. " Analysis of Uranium in Ore Samples by Delayed Neutron Activation Analysis", Radiochemical and Radioanalytical Letters, by K.L. Walker, October 1980.
- 41. " Formation of 1-S11acyclopenta-2,4 diene Through Recoil Silicon Atom Reactions", E.E. Siefert, K.-L.
Loh, R.A.
Ferrieri, and Y.-N.
Tang, J. Am. Chem. Soc., 102, 2285, (1980).
- 42. " Fluoride Atom Shift in 1,2-Difluoroethyl Radicals",
J.C.S. Chem. Comm., 814 (1980).
- 43. E.B. Ledger,-T.T. Tieh, and M.W. Howe, " Delayed Neutron Activation Determination of Uranium in Twelve Rock Reference Standards", Geostandard Newsletter, 4, 153-155, (1980).
- 44. Dr. Dan Hightower, "Whole Body Counting", Southwest Chapter of Society of Nuclear Medicine, 1981.
-45. Jeff Watson and Billy Covington, " Neutron Transmutation Doped Silicon", American Association of-Physics Teachers, 1981.
- 46. Lennart Kullberg and Abraham Clearfield, " Mechanism of Ion l
Exchange in Zirconium Phosphates - 31.
Thermodynamics of Alkali Metal Ion Exchange on Amorphous ZrP", J. Phys. Chem.,
1981.
- 47. Lennart Kullberg and Abraham Clearfield, " Mechanism of Ion Exchange in Zirconium Phosphates - 32.
Thermodynamics of Alkali Metal lon Exchange on Crystalline a-ZrP", J. Phys.
Chem., 1981.
- 48. Dennis Nelson, -William McDonough, and David Mattison, " Trace Element Geochemistry of the Sawtooth Mountain Syenites, i
Transpecos Magmatic Belt of West Texas", Trans Pecos Volcanism Symposium, 1981.
- 49. " Reactions of Monomeric Difluorosilylene with Ethylene",
E.E. Siefert, S.D..Witt, and Y.-N.
Tang, J.
Chem. Soc.,
i Chem. Comm., 217-218 (1981).
50.#" Unusual Compounds Synthesized via Nuclear Recoil Methods,"
Y.-N.
Tang, Advances in Chemistry Series, No. 197, "Short-l Lived Radionuclides in Chemistry and Biology", K.A. Krohn and J. W.
Root (eds.), American Chemical Society, pp. 53-66 (1961).
II-5 51.
- Parma, E.
J.,
" Gamma Abundance of Silicon-31", Master's Thesis in Nuclear Engineering, Texas A&M University, 1981.
52.
Theriot, L.
R.,
- Daley, L.,
" Matrix Effect in Atomic Absorption Determination of Copper in Fraction I Protein:
Possible Role of Copper in Light Sensitive Control of Ribulose Biphosphate Carboxyglase Activity", Texas Journal of Science, December, 1981.
53
" Characterization of Uranium-Rich Organic Material Obtained from a South Texas Lignite", M. S. Mohan, R.
A.
Zingaro, R.
D. Macfarlane and K. J. Irgolic, 1982, and Pittsburgh Energy Technology Center, May 18, 1982 by R. A. Zingaro.
54.
" Biological Attributes of the West Hackberry Beine Disposal Site, Oceans 82", 4, 285 (1982) with D.
Casserly, M. Vecchiono, R. Maples, R.
Ilg, Gaston, D. Weston and L. Dervoen.
55
" Quick Separation of Manganese from Brine Solutions Radiochem Radioanal Letters 51, 65 (1982) with G. L. Grout and C. L.
Webre.
56.
" Annealing Studi6s of Transmutation Doped Silicon", paper pre-sented at Texas Academy of Science Meeting in San Angelo in March, 1982 by Jeff Watson and Billy Covington.
57
" Annealing Study of NTD Silicon:
Boron", paper presented at Fourth International NTD Conference in Washington, D.C.,
in June 1982 by Jeff Watson and Billy Covington, 58.
" Annealing Study of NTD Silicon:
Boron", to be published in the proceedings of the Fourth International NTD Conference in 1982 by Jeff Watson and Billy Covington.
59
" Implications of Fission Track Ages from the Kaplan Geothermal-Geopressure Zone, Vermilion Parish, Louisiana", R. K.
- Dokka, Transactions of Gulf Coast Association of Geological Societies, Vol. 32, pages 465-468 (1982).
60.
William F. McDonough, Dennis O. Nelson, and G. David Mattison,
" Major and Trace Element Variation in a Dynamically Evolving Silicon Magma Chamber", Trans-Pecos Volcanism, March 1982.
61.
John H.'Schieffer, G.
David Mattison and Dennis 0. Nelson, "The Mineralogy and Geochemistry of the Igneous Rocks of the Terlingua District, Brewster County, Texas", Trans-Pecos Volcanism, March 1982.
62.
John H. Schieffer and G.
David Mattison, " Nature and Origin of Alkalic and Calcic Veinlets in Xenoliths from the Terlingua District, West Texas.
Geological Society of America, October, 1982.
N W
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II-6 63 C. Conrad, " Uranium in the Oatman Creek Granite and Its Economic Impact", Masters Thesis in Geology, 1982.
64.
W. Schaf tenaar, " Uranium in Igneous Rock of the Central Davis Mountains of West Texas", Masters Thesis in Geology, 1982.
65.
H. Deigl and D.
E. Feltz, " Antiquity, Man and Machine".
Paper presented at Eighth TRIGA User's Conference, Idaho Falls, Idaho, March 1982.
66.
D. Rogers and J. D.
Randall, "In-Pool Neutron Radiography of Damaged FLIP Fuel".
Paper presented at Eighth TRIGA User's Conference, Idaho Falls, Idaho, March 1982.
67 Beasley, C. W., " Perfusion Measurement with Rubidium 81 to Krypton 81m Ratio", Ph.D., Dissertion in Veterinary Physiology and Pharmacology, Texas A&M University, 1982.
68.
Brady, M.
C.,
" Radiation Field Measurements in the TAMU Nuclear Science Center Irradiation Cell", Master's Thesis in Nuclear Engineering, Texas A&M University, 1982.
69 Parma, E. J. and Hart, R.
R.,
" Measurements of the Gamma Abun-dance of 3*Si",
Proceedings of the Fourth International Confe-rence on Neutron Transmutation Doping of Semiconductors, Gaithers-burg, Maryland, June 1982.
70.
Young, M. H. and Hart, R.
R.,
" Neutron Transmutation Doping of p-Type Czochralski-Grown GaAs", Proceedings of the Fourth l
International Conference on Neutron Transmutation Doping of l
Semiconductors, Gaithersburg, Maryland, June 1982.
71.
Welch, K.
L.,
" Fluence Monitor Calibration of the Multiple Rotisserie Irradiation Device for Neutron Transmutation Doping",
Master's Project in Nuclear Engineering, Texas A&M University, 1983 72.
Pgzoniski, L.,
Hanna, A.
N.,
- Suschny, 0.,
" Report on Intercom-parisons S-14, S-15, S-16 of the Determination of Uranium and Thorium in Thorium Ores", IAEA Report IAEA/RL/101, 1983 l
73 Schieffer, J.
H.,
Nelson, D.
O.,
" Petrology and Geochemistry of Megacrysts, Xenoliths, and their Host Basalts from the Ter-lingua Mercury District of West Texas", Geological Society of America, Abstracts with Program, V.
13, 1983 74.
Nelson, D. O.,_Ott, K. L. and Tolley, R.
D.,
" Geochemistry of Cibolo Creek I:
Evaluation of Element Distribution in Stream Sediments", Earth Sciences, 1983 75.
Rudnick, R.
L.,
" Geochemistry and Tectonic Affinities of a Pro-terozoic Bimodal Igenous Suite, West Texas", Geology, 1983 l
II-7 i
76.
McDonough, W.
G.,
"The Geochemistry and Petrology of a Trachyte Comendite Suite from the Oligocene Paisano Volcano, West Texas".
Master's Thesis in Geology, Sul Ross State University, 1983 77.
Kennicutt II, M.
C.,
Keeney-Kennicutt, W.
L., Presley,' B.
J.,
and Fenner, F.,
"The Use of Pyrolysis and Barium Distributions to Assess the Areal Extent of Drilling Fluids in Surficial Marine Sediments", Environ. Geol. 4, pp. 239-249 (1983).
78.
Presley, B.
J.,
Sheu, D.
D.,
"Orea Basin:
Recent Deep-Sea Black Mud", Annual Meeting of the Geological Society of America, Indianapolis, Indiana (1983).
79 Whiteacre, M.,
"Sorber Performance Data on the Recovery of Strategic Elements from Seawater", Master's Project in Nuclear Engineering, Texas A&M University, 1983 80.
Best, F. R. and Whiteacre, M.,
"Sorber Performance Data on the Recovery of Strategic Elements from Seawater", International 3
Conference on Recovery of Uranium from Seawater, Japan, 1983 81.
James, W.
D.,
" Multiple Stable Isotope Markers Used in Nutrition Research", Annual American Nuclear Society Meeting, Detroit, Michigan, 1983 82.
Akanni, M.
S.,
Ogugbuaja, V.
O., James, W.
D.,
" Trace Element Content of Magnetohydrodynamic Coal Combustion Effluents",
Journal of Radioanalytical Chemistry, V.
79, No.
2, pp. 197-205, 1983 l
l 83 Rudnick, R.
L.,
" Petrology and Geochemistry of the Carrizo Mountain Group", Geology, Spring 1983 84.
Simpkins, T.
H.,
"The Geology and Geochemistry of the Aguachili Mountain Fluorspar-Beryllium District".
Presented at the Geology Society of America Meeting, Fall, 1983 85 Schlapper, G.
A.,
Neff, R.
D.,
Davis, D.
R.,
and Sandel, P.
S.,
" Measurement of Routinely Encountered Neutron Doses in Research Facilities", Radiation Protection Management, October 1983 86.
- Khalil, N.,
"A Test of the Efficiency of the Raw Water Stirring System Installed in Liquid Waste Holdup Tank 1",
Technical Report l
Number 44, (1983).
87 Goodman, D.
G.,
" Motor Driven Flux Wire Counter", Technical Report Number 45, 1983 88.
O'Donnell, J., " Determination of the Neutron Flux in the TAMU Nuclear Science Center Reactor During Pulce and Steady State l
Operation", Master's Thesis in Nuclear Engineering, Texas A&M j
University, 1983 l
II-8 89 Followill, D.
S., " Determination of Exchangeable Potassium in the Canine by Means of Whole-Body Counting", Master's Project in Nuclear Engineering, Texas A&M University, 1983 90.
Mohan, M.
S.,
and Zingaro, R.
A., " Trace Element Characterization of Deep Basin Lignites of Texas", Final Report to Texas Energy and Natural Resources Advisory Council, 1983 i
91.
Ilger, W.
A., "A Study of Uranium in South Texas Lignite",
Master's Thesis in Chemistry, Texas A&M University, 1983 92.
Daley, L.
S.,
"ESR of Transition Metal 'Chromophores' in RuBP Case Supporting Neutron Activation and Optical Data Concepts of UV Light Activation Through Transition Metal Chromophores".in Blue Light Syndrome, 2 Horst Senger, ed.,
Springer-Verlay, 1984.
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APPENDIX III Summaries of Health Physics Support Effluent Releases Environmental Survey Program Radiation and Contamination Control Program and Personnel Exposures i
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III-1 Summary of Health Physics Support for the Operation of the Nuclear Science Center Reactor 1983 Provided health physics monitoring support for processing 1198 irradiations containing over 19,655 samples and approximately 2236 curies of radioactivity.
Certified 624 shipments of radiaoctive materials to off-site industry.
Certified 117 shipments of radioactive materials to other campus laboratories.
Provided monitoring support for processing and handling over 11,466 experimental samples retained at the Nuclear Science Center laboratories.
Conducted environmental survey program in cooperation with the Texas State Department of Health.
This program consists of in-situ TLD monitors and the collection, analyses and evaluation of 55 soil, water, vegetation, and milk samples.
Provided personnel monitoring support for ~ 35 persons on a daily basis and 5008 visitors as required.
Performed radionuclide analyses and packaged approximately 29.2 Ft* of dry solid radioactive waste for disposal.
Performed radioisotope identification and determined radio-activity concentrations for 43 releases of radioactive liquid effluents totaling 2,600,000 gallons including fresh water diluent.
Performed surveys of the Nuclear Science Center facilities for radiation levels and radioactive contamination including the collection, analyses, and evaluation of approximately 300 smear samples on a monthly basis.
Conducted radiation safety training for 64 NSC employees and experimental personnel using NSC facilities.
____.______J
III-2 EFFLUENT RELEASE
SUMMARY
Introduction Summaries of radioactive effluents released from the Nuclear Science Center for 1983 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 6.86 E-12 uC1/cc.
Total radioactivity released for the year was 3 98 E-04 curies.
There were 4 radioisotopes with
> 8 day half-lives identified from isotopic analyses of the filter papers in addition to the < 8 day half-lives of the decay daughters of Radon-Thorium.
These data are presented in Table 1.
Gaccous Releases Argon-41 is the major gaseous effluent produced and released at the Nuclear Science Center.
This effluent is measured by counting the Argon-41 photopeak in the gaseous discharges of the central exhaust stack.
Total Argon-41 released during 1983 was 1.77 curies.
This results in an annual average release rate of 2.46 E-08 uC1/cc as measured 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 116-119, June 1980) 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 2.
Liquid Waste Releases Radioactive liquid effluents are collected in liquid waste holdup tanks prior to release from the confines of the Nuclear Science Conter.
Sample analyses for radioisotope identification and radio-activity concentrations were determined for each release.
There were 43 liquid waste releases totaling 2.84 E 06 gallons including diluents from the Nuclear Science Center during 1983 The total radioactivity released for 1983 was 5.54 E-03 Ci with an average concentration of 5 34 E-07 pCi/ml.
Summaries of the radioisotope data are presented in Table 3 through 15 Radioactivity concen-trations for each isetcpe were below the limits specified in 10CFR20 Appendix B.
III-3 TABLE 1 PARTICULATE EFFLUENT RELEASES -
ANNUAL
SUMMARY
1983 Exhaust Concentration Total Radioactivity
~ Month Volume (cc)
(uCi/cc)
(uC1)
(C1) 4 4
January 6 31 E 12 6.85 E-12 43 22 4 32 E-05
- February 5.91 E 12 2.05 E-12 13.89 1 39 E-05
- March, 6.31 E 12 5.03 E-12 31.74 3 17 E-05 April 6.12 E 12 1.07 E-12 6.55 6.55 E-06 May 6.31 E 12 1.07 E-12 6.75 6.75 E-06 June 6.12 E 12 1.18 E-12 7.22 7.22 E-06 July 6.31 E 12 4.8 E-12
-30.29 3.03 E-05
' August 6.31 E 12 3 75 E-12 23.66 2 37 E-05 September 6.12 E 12 2 39 E-11 146.27 1.46 E-04 October 6.31 E 12 6.82 E-12 43 03 4 30 E-05 1
November 6.12 E 12 1.70 E-12 10.40 1.04 E-05 December 6'.31 E 12 2 38 E-11 15.02 1.50 E-05 4
- Total Volume:
7.45 E-13 cc l
Annual Average-Release:
'6.86.E-12 pCi/cc l
Total Radioactivity Released:
3 78 E-04 i
L
III-4 TABLE 2 GASEOUS EFFLUENT RELEASES ARGON-41 ANNUAL
SUMMARY
1983 Total Radio-Exhaust Concentration
- Concentration **
Ratio activity Month Volume (cc)
(pCi/cc)
(pCi/cc)
MPC**
(C1)*
January 6.31 E 12 1.02 E-08 5.10 E-11 1.28 E-03 6.44 E-02 February 5.91 E 12 8.31 E-09 4.16 E-11 1.04 E-03 4.91 E-02 March 6.31 E 12 4.59 E-09 2.29 E-11 5.73 E-04 2.90 E-02 April 6.12 E 12 1.11 E-08 5.55 E-11 1 39 E-03 6.79 E-02 May 6.31 E 12 2.04 E-08
.1.02 E-10 2.55 E-03 1.28 E-01 June 6.12 E 12 5.99 E-08 3 00 E-10 7.50 E-03 3.67 E-01 I
July 6 31 E 12 3.45 E-08 1 73 E-10 4 33 E-03 2.18 E-01 August 6.31 E 12 2.23 E-08 1.12 E-10 2.80 E-03 1.41 E-01 September-6.12 E 12 2 92 E-08 1.46 E-10 3 65'E-03 1.79 E-01 0ctober 6.31 E 12 2.17 E-08 1.09 E-10 2.73 E-03 1.37 E-01 i
November 6.12'E 12 1.89 E-08 9.45 E-11 2.36 E-03 1.16 E-01 l December 6.31 E 12 5.40 E-08 2.70 E-10 6.75 E-03 3 41 E-01 Total Volume:
7.45 E 13 cc I Annual Average Release *:
2.46 E-08 uCi/cc Total. Radioactivity Released *:
1.77 'Ci
-0As measured in the central exhaust stack.
L.
" 00As determined at 100 meters, approximate boundary of exclusion area, with 200/1' dilution factor (SAR, pp. 117-119, June 1979).
i
III-5 TABLE 3 RADI0 ACTIVE LIQUID EFFLUENT RELEASES
SUMMARY
1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL p C1/cc pCi/cc Percent Curies Co-141 1
1.26E+08 4.73016E-08 9E-05
3.41E+08 1.96188E-09 2E-05 9.80939E-03 6.69E-07 Cd-115 2
2.51E+08 3 20717E-07 3E-05 1.06906 8.05E-05 4
Co-57 3
6.46E+08 3 97833E-08 4E-04 9.94582E-03 2 57E-05 Co-58 16 2 988E+09 1.98527E-07 9E-05
.220586 5 932E-04 Co-60 39 5 971E+09 5.22174E-07 3E-05 1 74058 3 1179E-03 Au-198 1
1.52E+08 1.16447E-08 SE-05
.0232895 1.77E-06
-Ir-192 3
6.41E+08 6.69392E-08 4E-05
.167348 4.2908E-05 l Mn-54 23 3 799E+09 2.66146E-07
,E-04
.266146 1.01109E-0}
1
( Na-22 2
4.5E+08 1.45778E-08 3E-05
.0485926 6.56E-06 Na-24 3
4.29E+08 1.67483E-07 3E-05 558275 7.185E-05 Tb-160 1
9.85E+07 4 31472E-07 4E-05 1.07868 4.25E-05 r
l.Zn-65' 25 4.001E+09 1.05439E-06 1E-04 1.05439 4.2186E-03 I
Total Number of Releases:
43
< Total Volume Including Dilution:
1.038E+10 mL Total Activity:
5.544E-03 Curies Average Concentration Including Dilution:
5 34104E-07 uCi/cc l.
1
III-6 TABLE 4 NUCLEAR SCIENCE CENTER RADI0 ACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
January 1983 i
No. of Volume Conc.
MPC MPC Activity Isotope Releases mL pCi/cc pCi/cc Percent Curies Cd-115 1
1.42E+08 2.07746E-07 3E-05
.692488 2.95E-05 Co-58 3
3 516E+08 8.04608E-08 9E-05
.0894008 2.829E-05 Co-60 7
8.646E+08 1.86398E-07 3E-05
.621328 1.6116E-04
.Mn-54 6
7 106E+08 1.02927E-07 1E-04
.102927 7 314E-05
{Na-24 1
1.42E+08 1.23239E-08 3E-05
.0410798 1 75E-06 Zn-65 6
7.106E+08 2 37405E-07 1E-04
.237405 1.687E-04 l
Total Number of Releases:
7 Total Number Released (with dilution):
8.646E+08 mL Average Concentration (with dilution):
5 34779E-07 pCi/cc i
Total hadioactivity:
4.6237E-04 Curies r.
I
III-7 TABLE 5 NUCLEAR SCIENCE CENTER RADI0 ACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
February 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL pCi/cc pCi/cc Percent Curies Co-58 2
3 29E+08 1.27964E-07 9E-05
.142182 4.21E-05 Co-60 5
6.30339E+08 3 23509E-07 3E-05 1.07836 2.0392E-04 Au-198 1
1.52E+08 1.16447E-08 SE-05
.0232895 1.77E-06 Ir-192 1
1.67E+08_
1.18563E-07 4E-05
.296407 1.98E-05 Mn-54 3
4.68E+08 1.18547E-07 1E-04
.118547 5.'548E-05 Tb-160 1
9.85E+07 4.31472E-07 4E-05 1.07868 4.25E-05 Zn-65 2
3 29E+08 4.05471E-07 1E-04
.405471 1 334E-04 Total Number of Releases:
6 Total Volume Released (with dilution):
7.28839E+08 mL Average Concentration (with dilution):
6.4707E-07 pCi/cc Total Radioactivity:-
4.7161E-04 Curies
III-8 1
TABLE 6 NUCLEAR SCIENCE CENTER RADIOACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
March 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL pCi/cc pCi/cc Percent Curies Cd-115 1
1.1E+08 4.63636E-07 3E-05 1.54545 5.1E-05 Co-58 1
1.1E+08 4.77273E-07 9E-05 530303 5.25E-05 Co-60 3
3 7E+08 4E-07 3E-05 1 33333 1.48E-04 Mn-54 3
3 7E+08 2.22757E-07 1E-04
.222737 8.242E-05 Na-22 1
1.1E+08 5.6E-08 3E-05
.186667 6.16E-06 Na-24 1
1.1E+08 2.89091E-07 3E-05 963636 3 18E-05 Zn-65 1
1.1E+08 1 70909E-06 1E-04 1.70909 1.88E-04 Total Number of Releases:
3 Total Volume Released (with dilution):
3 7E+08 mL Average Concentration (with dilution):
1.57162E-06 pCi/cc Total Radioactivity:
5.815E-04 Curies
III-9 TABLE 7 NUCLEAR SCIENCE CENTER RADIOACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
April 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL UC1/cc PCi/cc Percent Curies Co-58 3
4.93E+08 1.86004E-07 9E-05
.206671 9.17E-05
. Co-60 4
6.6E+08 4.25909E-07 3E-05 1.4197 2.811E,04 Mn-54 3
4.93E+08 3 09939E-07 1E-04 309939 1.528E-04
- Zn-65 3
4.93E+08 6.69777E-07 1E-04
.669777 3 302E- 04
' Total Number of Releases:
5
. Total Vol'ume Released (with dilution):
7.7E+0E mL Average Concentration (with dilution):
1.11078E-06 pCi/cc Total Radioactivity:
8.553E-04 Curies mmme n i a
III-10 TABLE 8 NUCLEAR SCIENCE CENTER RADIOACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
May 1983 No. of Volume Conc.
MPC M?C Activity Isotope Releases mL uCi/cc uCi/cc Percent Curies Zn-65 1
1.75E+08 7.54286E-08 1E-04
.0754286 1 32E-05 Total Number of Releases:
1
- Total Volume Released (with dilution):
3.439E+08 mL
. Average Concentration (with dilution):
3.83833E-08 pCi/cc Total Radioactivity:
1 32E-05 Curies O
ha mm ii
III-11 i-1 l
TABLE 9 NUCLEAR SCIENCE CENTER RADIOACTIVE. LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
June 1983 No. of Volume Conc.
MPC MFC Activity Isotope Releases mL UC1/cc 4Ci/cc Percent Curies Co-58 1
1 32E+08 3.69697E-07 9E-05
.410774 4.88E-05 Co-60 5
6.59E+08 8.44917E-07 3E-05 2.81639
' 5.568E-04 Ir-192~
1
_1 33E+08 1.7218E-07 4E-05
.430451 2.29E-05 Zn-65 2
2.46E+08 1.09431E-06 1E-04 1.09431 2.69E-04 l
l Total-Number of Releases:
5 Total Volume Released (with dilution):
6.59E+08 mL
, Average. Concentration-(with dilution):
1.46115E-06 pCi/cc
' Total Radioactivity:
9.629E-04 Curies t
i-i l
III-12 TABLE 10 NU'JLEAR SCIENCE CENTER RADI0ACT'.VE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
July 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL pCi/cc pCi/cc Percent Curies Co-60 2
3.85E+08 7.61039E-07 3E-05 2.5368 2.93E-04 Total Number of Releases:
2 Total Volume Released (with dilution):
3 85E+08 mL Average Concentration (with dilution):
7.61039E-07 pC1/cc Total Radioactivity:
2.93E-04 Curies
III-13 TABLE 11 NUCLEAR SCIENCE CENTER RADIOACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
August 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL uCi/cc pCi/cc Percent Curies Ce-141 1
1.26E+08 4.73016E-08 9E-05
.0525573 5.96E-06 Co-60 2
2.48E+08 6.0LO65E-07 3E-05 2.02688 1.508E-04 Zn-65 1
1.22E+08 2 34426E-07 1E-04
.234426 2.86E-05 Total Number of Releases:
3 Total Volume Released (with dilution):
7.41E+08 mL Average Concentration (with dilution):
2.49258E-07 uCi/cc Total Radioactivity:
1.847E-04 Curies O
~ __
III-14 I
TABLE 12 NUCLEAR SCIENCE CENTER RADI0 ACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
September 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL Ci/cc pCi/cc Percent Curies 4
Co-57 1
1.53E+08 1 50327E-08 4E-04 3 75817E-03 2 3E-06 Co-58 1
1.78E+08 7 30337E-07 9E-05
4.5E+08 1.00289E-06 3E-05 3 34296 4.513E-04
- Mn-54 1
1 78E+08 9.83146E-07 1E-04 983146 1.75E-04 l
Na-24 1'
-1.78E+08 2.15169E-07 3E-05 717228 3.83E-05 l
Zn-65 2
3 31E+08 3 28731E-06 1E-04 3.28731 1.0881E-03 i
Total Number of Releases:
3 l Total Volume Released (with dilution) 4.5E+08 mL i Average Concentration (with dilution):
4.19511E-06 pCi/cc.
' Total Radioactivity:
1.8878E-03 Curies i
y wv
,,,g--
s-w
-v
- ~'w"vm
--~vwww'
- v
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-~--*e-~
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9,--
t-~--4,o
- ve
III-15 k
TABLE ~13 NUCLEAR SCIENCE CENTER RADIOACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
October 1983 No. of Volume Conc.
MPC MPC Activity Isotope Releases mL pCi/cc uCi/cc Percent Curies Co-60 2
3 45E+08 1.71594E-07 3E-05 571981 5.92E-05 Mn-54 1
h.2E+08 4.11818E-08 1E-04
.0411818 9.06E-06 Zn-65 1
1.25E+08 2.976E-07
-1E-04
.2976 3 72E-05 Total Number of Releases:
2 Total Volume Released (with dilution):
3.45E+08 mL Average Concentration (with dilution):
3 05507E-07 pCi/cc Total Radioactivity:
1.054E-04 Curies
III-16 TABLE 14 NUCLEAR SCIENCE CENTER RADIOACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
November 1983 No. of Volume Conc.
MFC MPC Activity Isotope Releases mL pCi/cc uCi/cc Percent Curies Co-57 2
4.93E+08 4.74645E-08 4E-04
.0118661 2 34E-05 Co-58
9 1E+08 7 95495E-07 3E-05 2.65165 7.239E-04 Mn-54 4
9.1E+08 5.03088E-07 1E-04 503088 4.5781E-04 Zn-65 4
9 1E+08 2.0967E-06 1E-04 2.0967 1.908E-03 Total Number of Releases:
4 Total Volume Released (with dilution):
9 1E+08 mL Average Concentration (with dilution):
3.64099E-06 pC1/cc Total Radioactivity:
3 133E-03 Curies
III-17 TABLE 15 NUCLEAR SCIENCE CENTER RADI0 ACTIVE LIQUID EFFLUENT RELEASES MONTHLY
SUMMARY
December 1983 l
1 No. of Volume Conc.
MPC MPC Activity Isotope P.eleases mL p Ci/cc pCi/cc Percent Curies Co-60 1
1.09E+08 2.90826E-07 3E-05 969419 3 17E-05 Mn-54 1
1.09E+08 3.69725E-08 1E-04
.0369725 4.03E-06 i
Zn-65 1
1.09E+08 2.34862E-07 1E-04
.234862 2.56E-05 Total-Number of Releases:
1 l
Total Volume Released (with dilution):
1.09E+08 mL
-Average Concentration (with dilution):
5.62385E-07 pCi/cc
,. Total Radioactivity:
6.13E-05 Curies l
t i
l l
i
7 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 stmples were analyzed for gross gamma and beta activities and isotope identification.
Data from these samples remained basically unchanged from 1983 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 unrestricted 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 Depart-msnt of Health, Division of Occupational Health and Radiation Control.
Ambient background for these measurements is determined from a control dosimeter located southeast of Easterwood Airport approximately 800 l
motors 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 16 lists the average exposure rate above ambient back-ground for a number of locations at the site boundary.
The highest expocure points at the north and west location of the site boundary.
Additionally, a dosimeter is located adjacent to the radiaoctive waste storage building and the instrument calibration range.
Ex-posure data from this dosimeter is not considered as a result of reactor operations but does reflect the maximum site boundary exposure of 337 mR per year.
This site boundary location is further protected from free 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 1983 are pre-scnted in Tables 16-20 for gross beta activity.
l l
LLL-19 TABLE 16 ENVIRONMENTAL RADIATION MONITORING PROGRAM ~
INTEGRATED RADIATION EXPOSURE 29 July 1982 to 28 October 1983 Average Exposure Exposure Rate Station Number Location (mR/ Year)
(mR/ Day) 1 NW corner - Firemans Training School 59 0.16 2
Fence corner west of TLD Station #4 84 0.22 3
Back fence south of TLD Station #2 92 0.25 4
West corner NSC &
calibration fence 95 0.26 5
Fence NSC front gate 69 0.18 6
East corner NSC &
~
calibration fence 337 0.92 7
Easterwood-Airport fence north of stock tank 65 0.17 8
Evergreen tree in open field west of calibration fence 53 0.14 9
Fence by trailers next to, NSC 61 0.16 10 Fence 50' from TLD Station
- 9 69 0.19
.11 Fence by aluminum gate by Easterwood Airport 62
,0.17
III-20
~
TABLE 17 ENVIRONMENTAL SURVEY PROGRAM FIRST QUARTER
SUMMARY
1983 VEGETATION Number Location Samples (pCi/gm)
NSC Creek 2
47 NSC Outside 1
15 NSC Inside 1
22 TAMU Landfill 1
63 MILK (pCi/L)
[
TAMU Dairy 1
159 WATER (pCi/mL)
NSC Creek 1
0.010 Uhite Creek 2
0.014 l
Upper Brazos 1
0.005 Sanitary Outflow 1
0.060 Airport Fish Pond 1
0.160 Lower Brazos 2
0.010
III-21 TABLE 18 ENVIRONMENTAL SURVEY PROGRAM SECOND QUARTER
SUMMARY
1983 VEGETATION Number Location Samples (pCi/gm)
Uhite Creek 3
35.5 NSC Creek 2
47.0 NSC Inside 3
25 3 TAMU Landfill 2
45.0 Highway 6 and Rock Prairie 2
28.8 Neinast Site 1
47.0 A&M Dairy 1
15.0 WATER Radioactivity (pC1/ml)
(pCi/mL)
Sanitary Outflow 1
0.140 Easterwood Airport 1
0.090 White Creek 3
0.175 NSC Creek 2
0.070 Lower Brazos River 1
0.060 Upper Brazos River 1
0.050 l
MILK Radioactivity (pCi/mL)
(pC1/mL)
TAMU Dairy 1
0.141
III-22 TABLE 19 ENVIRONMENTAL SURVEY Ph0 GRAM THIRD QUARTER
SUMMARY
1983 VEGETATION Number Location Samples (pCi/gm)
White Creek 3
25.2 NSC Creek 2
7.7 NSC Site 3
25.4 NSC Offsite 1
9.5 MILK (pC1/mL)
TAMU Dairy 1
0.021 WATER (pCi/mL)
NSC Creek 3
0.030 White Creek 3
0.058 i
TAMU Sanitary Outflow 1
0.021 1
Easterwood Fish Pond 1
0.026 Lower Brazos 1
0.032 Upper Brazos 1
0.031 b
III-23 PERSONNEL EXPOSURES Radiation exposures to personnel at the Nuclear Science Center for 1983 were within the limits of 10CFR20.
The maximum exposure re-ceived by an individual for the year was 610 mrem.
A total of approximately 4.45 MANREM was received for 1983 More important, the exposures reflect an extended effort by sll personnel to minimize and eliminate radiation exposures whenever practicable.
These ex-posure data becomes more significant when one considers that in addition to routine reactor operations, over 19,000 samples containing approximately 22.00 curies of radioactivity were produced and pro-cessed at the Nuclear Science Center in 1983 The whole-body exposure data for NSC employees and experimental parsonnel 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 effective in preventing exposure to radiation.
There were 5,008 visitors to the Nuclear Science Center during 1983 The maximum exposure to any visitor as determined by film badges 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.
I e
l
,y III-24 I
~
TABLE 20
SUMMARY
OF WHOLE BODY EXPOSURES 1983 Whole Body Exposure Range Number of Persons (Rem)
In Range No Measurable Exposure 17 Less than 0.10d 13 0.100 - 0.249 9
0.250 - 0.499 6
0.500 - 0.749 1
0.750 - 0.999 0
1.000 - 1.999 0
2.000 - 2.999 0
L
'3 000 - 3 999 -
0 0
4.000 4.999 0
5.000 Greater than 5.000 0
I.
Total Number of Individuals Repo'ted:
46
~
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l l
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y
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9,
--m w-w-
r 9,
+p
-+,y-
-,---p&e-,
III-25 SOLID RADIOACTIVE WASTE 8
There was a total of 29.2 ft of dry solid waste material packaged in plastic bags for disposal during 1983 These materials ware transferred to the Radiological Safety Office, Texas License 6-448, for disposal.
This material consisted of laboratory glass-ware, irradiation containers, decontamination materials, and ex-psndable protective clothing and equipment, e.g.,
paper, shoe covers,
_ plastic bags and gloves.
This material contained Co-60, Ir-192, Cs-137, Zn-65, Ce-141, Mn-54, Cr-51, Br-82, Cd-109 and mixed fission products with the total radioactivity being 3 1 E-2 C1.
These data are in Table 21.
III-26 TABLE 21 SOLID RADIOACTIVE WASTE DISPOSAL ANNUAL
SUMMARY
1983 Radioactivity Radioisotope (pC1)
Co-60 28784 Ir-192 928 Cs-137 92 Zn-65 495 Ce-141 60 Mn-54 71 Cr-51 30 i'
Cd-109 50 Mixed Fission Products 578 3
Total Volume:
29.2 Ft contained in plastic bags.
Total Radioactivity:
3 1 E-2,Ci i
III-27 RADIATION AND CONTAMINATION CONTROL PROGRAM Introduction The detection and elimination of radiation hazards is an integral part of the Radiation-Safety Program at the Nuclear Science Center.
The radiation.and smear survey programs contribute to the control and elimination of these health hazards.
This program is effective in preventing the spread of radioactive contamination, improper storage of radioactive materials, and unwarranted exposures to radiation.
Radiation Survey The Nuclear Science Center uses an area radiation monitoring system consisting of nine (9) detector enannels. located throughout
'the Reactor and Laboratory Buildings.
This system is equipped with alarm settings and remote readouts in the control and recep-tion 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 Nuclear Science Center Facilities and site boundaries are
. surveyed monthly with beta-gamma sensitive instruments.
.These measurements are taken to determine proper storage and identifi-cation of radioactive materials and that visitor and routine work areas are free of radiation hazards.
Additionally, radiation monitoring support is provided for the reactor operations and experimenter groups to insure the safe handling of radioactive materials and control of personnel exposures.
There were no un-expected radiation levels or improper exposures of radiaoctive materials-detected during 1983 These surveys revealed only back-
' ground radiations at the site perimeter fence.
. Contamination Survey The Nuclear Science. Center is routinely surveyed for radio-ac,tive contamination every month.
This program inclu, des the collection, analysis and evalu'ation of approximately 250 smear samples and the decontamination of areas and stored materials with removabIe beta-gamma radioactivities of greater than 200 2
dpm/100 cm,
l
l APPENDIX IV Universities, Colleges, Industrial Organizations,
~
Government and State Agencies Served by the NSC During Twenty One Years of Operation l
IV-1 Other Universities and Colleges Baylor University Sam 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 Angeles Bluefield College Lamar State College of Technology Potomac St., College New Mexico State University Thames Valley St. Tech. College Rice University Victoria College Austin College Tennessee Tech. University Southern Methodist University Wharton County Jr. College California State Poly. College Grayson County College Washington University West Virginia Inst. of Tech.
Hastings College Galveston College Winona State 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 Texas Southmost College University of Southern Louisiana Stephen F.
Austin College University of Oklahoma Louisiana State University Somerset Community College Xavier University Grove City College Temple University Penn.
Louisiana Tech.
Bemidgi State College Abraham Baldwin College Chadran State College Kent St. University
~--
IV-2 Other Universities and Colleges (Cont'd)
~
State University of Ohio Pan American College
. Alfred St. College Tarleton St. College Community College of the Finger Columbus College i
Lakes Texas Tech University 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 l
Fort Valley State College North Shore-Community College
.Denison University University of Wisconsin i
State UniversityfCollege, N.Y.
Hill Jr. College Auburn University McLennan Community College
~ Clarion. State College Southeast Missouri St'.
College University of Alaska Southwestern State College I
University of' Arkansas Mary Hardin Baylor University-of Houston Texas State Technical Inst.
. Southwest Texas State' College North Texas State University e
Iowa State University University of Arizona Blinn ' College McNeese State University l
State College-of Arkansas
- Texas Eastern University
('
The Defiance College Henderson County Jr. College San Antonio College Massachusetts Institute of Technology Laredo'Jr. College University of Texas at Dallas
-University of Corpus Christi Moody College.
South Dakota State Sul Ross University l~
Arapahoe Jr.. College East Texas State University California St.-College University of Nebraska University of. Texas-Tyler
7 IV-3 Industrial Organizations States Marine Lines Comfaco Southwest Research Institute Rivera Foods Humble Oil and Refining Co.
North American Aviation Institute of Research and Gulf Research Instrumentation Estrada Incorporated Xomox
-Shell Chemical Co.
Texas Nuclear
' Mobil Oil Co.
Bio Assay Lab-Bio Nuclear 2~
Texas' Instruments Inc.
NAPKO Corp.
Todd Shipyards Corp.
D.W. Mueller, Consultant Shell' Development Co.
General Nuclear Corp.
4 Tennessee Gas Transmission-Co.
Nuclear Environmental Eng. Corp.
)
Lane Well Co.
Shell Development, Oakland Calif.
l-Petro-Tex Chemical Corp.
Nuclear Sources and Services ll' Babcock and Wilcox Co.
Exxon Medical Arts Atomic Energy Industrial Texaco, Inc.
Hughes Research Lab Monsanto Co.
TRAC 0 Inc.
Hastings Radiochemical Works
. Lloyd Barber and-Assoc 1ates E.I..DuPont DeNemours and Co.
Temple Industries l
Mission-Engineering Chemtrol-Inc.
ESSO Research and Engineering Jet Research Diamond Alkali Co.
Resource Engineering-Dow Chemical-Co.
Ranger Engineering L
.Celanese Co..
Turbine Lab l.
Gulf Nuclear
' Independent. Exploration Co.
l
IV-4 Industrial Organizations (Cont'd)
' Westinghouse Electric Gulf Science and Technology I
Tech-Sil l
Avery Oil. Company l
Bell Helicopter Universal Technology Corporation Spectronics LGL, LTD.
E-Systems
-Monsanto, Inc.
Radian ~ Corp.
Nuclear Laboratory Services
-Core Laboratories Pacific Gas and Electric-
. Houston Lighting and Power Broz Labs-Balcones Research i
i General Electric Company
. Gulf States Utilities Kansas Gas and Electric i
I Teledyne Bendix l
Research Concepts l
l LAmerican Hoechst
. Engineers / Designers, Inc.
i-1Tracerco TRIAD l
IV-5 l
. Government and State Agencies M. D. Anderson Hospital Houston _ Police Department Houston, District Attorney Brooks Medical Center National Aeronautics and Space Administration
. North East Radiological Health-Lab Department of the Army I
Wichita Falls,_ District Attorney Corpus Christi, District Attorney
[
Dallas County, District Attorney Denton County, District Attorney Jefferson County, District Attorney Oklahoma Medical Examiner
'U.S.
Air Force i
j Osage. County Oklahoma, District Attorney Bureau of Economic Geology t
Amarillo District Attorney Orange: Police Department t
Fort Worth Police Department Austin -Police -Department-t I '
i APPENDIX V Texas A&M University Departments Served by the NSC During Twenty One Years of Operation i
\\
I f
i-
V-1 TAMU Department and Agencies Department of Biochemistry and Biophysics Department of Nuclear Engineering Department of 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 College of Medicine
V-2 TAMU Departments (Cont'd)
Department of Health 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 Department of Entomology Department of Recreation and Parks Department of Engineering Design Graphics College of Architecture and Environmental Design Center for Energy and Mineral Resources
i s
e TEXAS ENGINEERING EXPERIMENT STATION THE TEXAS A&M UNIVERSITY SYSTEM COLLEGE STATION. TEXAS 77843-3575 f'
I i
27 March 1984 NUCLEAR SCIENCE CENTER 409,'845-7551 Mr. Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
Docket 50-128
Dear Mr. Thomas:
In accordance with the reporting requirements of Technical Specifications 6.6.1 for the Texas A&M University Nuclear Science Center Reactor we hereby submit 3 copies of our annual report for the period of January 1, 1983 -
December 31, 1983.
Sincerely, 4 1/
i gN Donald E. Feltz Director DEF/ym
. Enclosures PP,)
1 i
RESEARCH AND DEVELOPMENT FOR MANKIND
^
I' v
L Porm AEC-427 U.S. ATOM:C ENERGY COMMISSIO.
UNIVERSITY-TYPE CONTRACTOR'S RECOMMENDATION FOR AECM 3201 DISPOSITION OF SCIENTIFIC AND TECHNICAL DOCUMENT f See instructions on Reverse $1de) 1.' AEC REPORT NO.
- 2. TITLE
" Twentieth Progress Report Of the Texas A&M OR0-4207-16 University Nuclear Science Center"
- 3. rYPE OF DOCUMENT (Check one):
O s. Scientific and technica report Contract NO. DE-AC05-76ER04207 C b. Conference paper not to be published in a journal:
(fOrmerly EY-76-C-05-4207)
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[g] c. Other (Specify) Facilit_y Progress Report 4.
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6.
SUBMITTED BY: NAME AND POSITION (Please print or type)
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p.,,
AAA Y uh Ye5L7YB9-FOR AEC USE ONI.Y
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O O a. AEC patent clearance has been granted by responsible AEC patent group.
r O b. Report has been sent to responsible AFC patent group for clearance.
O c. Pateat eie.rence not required.
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INSTRUCTIONS Who uses this Form: AEC contract administrators will using the operations office code shall complete designate the AEC contractors who are to use this Form.
the report number by adding the identifying Generally speaking, it will be used by educational institu-portion of the contract number and a sequential tions and other "not for profit" institutions. AEC National number, e.g., NYO-2200-1, NYO-2200-2, etc.
Laboratories and other major contractors will generally use Subcontractor reports shall be identified with the longer Form AEC-426.
the code used by the prime contractor.
When to use this Form: AEC contractors are required item 2. Give title exactly as on the document itself.
under their contracts to transmit specified types of docu-ments to the AEC. Some, but not all, of these are item 3. If box c is checked, indicate type ofitem being transmitted by AEC centract administrators to AEC's sent, e.g., thesis, translation, etc.
Division of Technical Information Extension (DTIE) and may be incorporated into AEC's technical information item 4. The " normal announcement and distribution documentation system. Types of documents which will be procedures" for unclassified documents may transmitted to DTIE are identified in instructions which the include abstracting in " Nuclear Science Ab-contractor receives from his contract administrator. Each stracts" (NSA); and distribution to appropriate such document is to be accompanied by one copy of this T D-4500.(" Standard Distribution for Unclas-transmittal Form recommending to DTIE appropriate an-sified Scientific and Technical Reports") ad-nouncement and distribution of the document. Documents dressees, to libraries which through purchase of which the contractor may be required to submit to the microfiche maintain collections of AEC reports, AEC.under his contract but which are not of the type to be and to the Clearinghouse for Federal Scientific transmitted to DTIE, e.g., contract proposals, should not be and TechnicalInformation for sale to the public.
accompanied by a copy of this transmittal Form.
Check 4b or 4c if there is need for limiting announcement and distribution procedures de-Where to send this Form: Send the document and the scribed above. The normal expectation is that attached Form AEC-427 to the AEC contract administrate:
there should seldom be a necessity to check 4c.
for transmittal to DTIE unless the AEC contract admini-strator specifies otherwise.
Item 5. If 4b or 4c is checked, give reason for recommending announcement or distribution Item instructions:
restrictions, e.g., " preliminary information",
" prepared primarily for internal use", etc.
Item 1. The first element in the number shall be an AEC-approved code. This may be a code which item 6. Enter name of person to whom inquiries is unique to the contractor, e.g., MIT, or it may concerning the recommendations on this Form be the code of the AEC operations office,i.e.,
may be addressed.
NYO, COO, ORO, IDO, SRO, SAN, ALO, RLO, NVO. The contract administrator will specify item 7. AEC contract administrators may use this space the code which is to be used.
to show concurrence or nonconcurrence with the recommendation in item 4 and to make The code shall be followed by a sequential other recommendations.
number, or by a contract number plus a sequential number, as follows: (a) Contractors Item 8. AEC contract administrator or patent group with unique codes may complete the report representative should check a, b, or c, and number by adding a sequential number to the forward this Form and the document to:
code, e.g., MIT 101, MIT-102, etc.; or they may add the identifying portion of the contract USAEC - DTIE number and a sequential number, e.g.,
P. O. Box 62 ABC-2105-1, ABC-2105 2, etc.; (b) Contractors Oak Ridge, TN 37830 0v G P O 8 9 4.80 5 i
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