ML19345E154

Annual Progress Rept of Univ of Fl Training Reactor:Sept 1979 - Aug 1980.

ML19345E154
Person / Time
Site:	05000083
Issue date:	11/30/1980
From:	Diaz N FLORIDA, UNIV. OF, GAINESVILLE, FL
To:
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ML19345E151	List: ML19345E150 ML19345E154
References
ORO-4014-10, NUDOCS 8012230348
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Text

Contract # EY-76-S-05-4014 I Q Report # OR0-4014-10 I

ANNUAL PROGRESS REPORT OF THE g

UNIVERSITY OF FLORIDA TRAINING REACTOR l SEPTEMBER 1, 1979 - AUGUST 31, 1980 I

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Submitted to the Department of Energy Nuclear Regulatory Commission and l

University of Florida l

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'I 8, i Nils J. Diaz Professor and Director of Nuclear Facilities II.

Department of Nuclear Engineering Sciences I College of Engineering University of Florida Gair.esville, Florida l November,1980 I.

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l TABLE OF CONTENTS Pace Number I. INTRODUCTION 1 II. UNIVERSITY OF FLORIDA PERSONNEL ASSOCIATED WITH THE REACTOR I

3 III. FACILITY OPERATION 5 I IV. MODIFICATIONS TO THE OPERATING CHARACTERISTICS OR CAPABILITIES OF THE UFTR 12 I V. SIGNIFICANT MAINTENANCE AND TESTS OF REACTOR SYSTEMS 13 VI. CHANGES TO TECHNICAL SPECIFICATIONS AND STANDARD OPERATING PROCEDURES 15 l

VII. RADI0 ACTIVE RELEASES AND ENVIRONMENTAL SURVEILLANCE 16 VIII. EDUCATION, RESEARCH AND TRAINING UTILIZATION 18 I IX. THESES, PUBLICATIONS, REPORTS AND ORAL PRESENTATIONS OF WORK RELATED TO THE USE AND OPERATION OF THE UFTR 21 I

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1 I. INTRODUCTION I The University of Florida Training Reactor's overall utilization was in-creased from the previous year during this reporting period (September 1, 1979 - August 31,1980). It remains, however, significantly below histori-cal levels. The areas of teaching and training are just below average util-ization but research activities have almost stopped.

Several factors have contributed to the relatively poor utilization.

1. The reactor has not increased its power level to satisfy the needs of experimenters. This has resulted in the transfer of experiments to the Georgia Tech reactor and restrictions in starting other research programs.

2. The reactor staff and administration has dedicated a large portion of its time to satisfying regulatory requirements, including re-licensing of the Facility, preparation of a Safety Analysis Report, new Safeguards and Physical l

Security Plan and associated modifications, emergency planning and others.

No time has been available to develop research, educational or training pro-grams which could not be handled with the present staff.

3. The lack of a full-time Reactor Manager at the Facility, totally de-dicated to its administration and conduct of operations, hampers effective and consistent administration of the facility.

The facility has undergone modifications to increase its Physical Security and Safeguards according to Federal Regulations, as well as implemert an Emergency Plan to deal with radiological events.

The new Safety Analysis Report for the UFTR is being printed, with sub-l mittal to the Nuclear Regulatory Commission expected by December 31, 1980.

New courses utilizing the UFTR are designed and training programs for the nuclear utilities are contracted for the upcoming year. These will sign-ificantly increase utilization, but a concerted effort must be made to increase I

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i research utilization.

The increase in research utilization should be accomplished by a com-

bined effort at College and Departmental level; it requires a commitment to provide analytical services to experimenters as well as " free" utiliza-l tion or reduced-cost reactor time to initiate or develop research programs.

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I 3 II. UNIVERSITY OF Fl.0RIDA PERSONNEL ASSOCIATED WITH THE REACTOR I A. Personnel Emp'loyed by the UFTR

'I N.J. Diaz - Professor and Director of Nuclear Facilities, Reactor Supervisor

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H. Gogun - Senior Reactor Operator (full-time)

G. Fogle - Reactor Operator (full-time) l M. Constable * - Student Reactor Operator (1/2 time)

, S. Jaffe* - Student Reactor Operator (1/3 time)

B. Other Licensed Operators G.R. Dalton - Professor and Senior Reactor Operator, Nuclear I Engineering Sciences Department C. Radiation Control Office ~

T.J. Bauer - Radiation Control Officer H.G. Norton - Radiation Control Technician G.R. Renshaw - Radiation Control Technician G. McCrane - Radiation Control Technician W. Caughlin - Nuclear Technician (1/2 time)

A. Williams - Nuclear Technician (1/4 time)

Z. Berry - Nuclear Technician (1/4 time) l l M. Grote - Nuclear Technician (1/4 time)

B. McCully - Nuclear Technician (1/4 time)

D. Reactor Safety Review Subconinittee I G.R. Dalton - Chairman l N.J. Diaz A.M. Jacobs**

- Member

- Member l M.J. Ohanian - Member I

• NRC license to be granted by December 31st, 1980

• • Appointed in November,1980

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I 4 I D. Reactor Safety Review Subcomittee (continued)

T.J. Bauer - Member W.E. Bolch - Member E. Line Responsibility for the UFTR Administration R.Q. Marston, President, University of Florida W.H. Chen, Dean, College of Engineering l, A.M. Jacobs, Chairman, Department of Nuclear Engineering Sciences N.J. Diaz, Director of Nuclear Facilities and Reactor Supervisor F. Line Responsibility for the Radiation Control Office R.Q. Marston, President, University of Florida W.E. Elmore, Vice-President, Administrative Affairs l B.G. Dunavant, Director, Environmental Health and Safety T.J. Bauer, Radiation Control Officer i

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III. FACILITY OPERATION I The UFTR maintained the low level of energy generation and overall util-ization experienced the last two years. Although the educational and com-ercial utilization (training) increased, the reduction in research activities offset the gains from the other areas of use. The UFTR lacked the manpower to actively search for and support research projects.

I Changes in regulations and standards affecting the UFTR continue to decrease the availability of the reactor as the staff continues to concentrate on making the necessary modifications, plans, reports, etc. It 1s expected that this level of regulatory activity will decrease to a more acceptable condition the coming year, especially after the new operating license is I granted.

Shown in Table I is a sumary of the reactor utilization for this report-ing period. The list categorizes the twenty-three different research projects, teaching and training activities. The total reactor run-time was about 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> and the experiments used over 550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> of facility time.

I Table II sumarizes the different categories of reactor utilization:

g teaching and research operator's training, commercial utilization (utility training program), testing and surveillance, and demonstrations. The research utilization was reduced to two projects using less than 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of reactor run-time.

B Detailed in Table III are the monthly and total energy generation, as well as the hours at full-power per month and total this year. The UFTR generated g

9.8 Mw-brs during this period.

Described in Table IV are the reasons and dates for unscheduled shutdowns and reportable incidents for the reporting period; however, an incident in-volving the PuBe startup source was reported to the NRC due to its radiological I

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6 significance. No radiation was released or significant radiation dose received by anyone due to this or any other reactor operation.

I It is expected that, with the addition of a Reactor Manager, two part-time operators and support from the Analytical Facility of the Depart-ment, the research utilization can be significantly increased during the upcoming year.

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SUMMARY

OF FACILITY UTILIZATION

. (September 1979 - August 1980)

_ls NOTE: The projects marked with a t indicate irradiations or neutron activations.

The projects marked with an

• indicate training use. The projects marked with a tt indicate demonstrations of reactor operations. " Utilization I Time" is total time that the facility dedicates to a particular use, it includes "Run Time".

to shutdown.

"Run Time" is inclusive time from reactor startup I

PROJECT AND USER TYPE OF ACTIVITY UTILIZATION TIME RUN TIME (hours) (hours) t ENU 4505L, Dr. W. Ellis' NAA hair, insects and 3.67 2.68 standards t ENU 4505L, Dr. W. Ellis Neutron relaxation length by 2.83 1.05 NAA of gold foil I ttENU 4505L, H. Gogun aT of moderator 3.42 2.48 g ttENU 4505L, Dr. G. Dalton Sub-critical multiplication 1.12 0.83 MENU 4505L, Dr. G. Dalton 1/M and p determination by 6.10 5.25 blade drop method t'ENU 4505L, H. Gogun p worth of control blade by 2.33 1.78 positive period method ttENU 4505L, H. Gogun High power and " cold slug" 1.83 1.52 g t'ENU 4505L, H. Gogun Calometric heat balance 3.48 2.60 ttENU 4505L, H. Gogun Low power,sub-critical opera- 2.78 2.35 tion t ENU 4304L, Dr. W. Ellis NAA copper foil and discs for 3.83 2.02 class demonstration I ttENU 5005, Dr. H. Campbell High power operation 0.92 0.17

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• ENU 5176, H. Gogun, G. Fogle Reactor Operator Training Course 70.37 30.90 I

• ENV 6932, Dr.B. Dunavant, Radiation survey at power H. Norton 2.25 1.87

• ENV 6932, H. Norton Area monitor calibration exer- 0.73 0.44 I. cise

• ENV 6932, H. Norton Anti-C clothing exercise 1.00 0.00

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UTILIZATION TIME RUN TIME TYPE OF ACTIVITY (hours) j PROJECT AND USER thours) 3.48 2.78

• ENU 6517, Dr. W. Ellis Time delay coincidence spec-j trometry by NAA of copper foils g 3.72 3.23 ttNES 600, Dr. E. Carroll Danger coefficient and statis-tical weight 0.83 0.48 Absolute B counting and $ de-i t NES 600, Dr.W, Vernetson termination by NAA of gold foil 0.33

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Effective resonance integral by 1.00 t ENU 6515L, Dr. W.

Vernetson NAA of metal foils I

• Central Fla. Community College HP Lab, Radiation surveys at power 1.53 0.98 H. Norton g 55.70 51.10 t Dr. G.S. Roessler and NAA of trace elements in can-J. Swanson cer metastasis 5.58 4.18 Feasibility study of GCR $

t Dr. E.E. Carroll and determination M. McCoy I t Summer Science Training Program, Dr.W.Vernetson, c determination by NAA of gold foil 2.00 0.87 J. Houck 166.05 123.93

• Louisiana Power & Light Operator training H. Gogun, G. Fogle 39.90 10.85

• Reactor Operator Train- Training operators for NRC ing, H. Gogun, G. Fogle license 46.08 8.49 tt Reactor tours and demon- Orientation, lectures and strations, H. Gogun, operation demonstrations G. Fogle 7.68 3.30

• Reactor Operator Requal- Compliance with NRC requali-ification Training, H. fication training requirements I Gogun 4I Counting activity of stack 8.00 6.20 t Determination of Ar effluent sample Concentration, G.Fogle, l J, Swanson 34.83 28.77

• UFTR Testing and Instrument calibrations and I Calibration Runs, H. Gogun verifications TOTALS 483.04 301.43 I

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TABLE II UFTR UTILIZATION

SUMMARY

Utilization Time Run Time (hours) (hours; UF Courses and Laboratories 119.22 64.61 l

Research Activities 61.28 55.28 UFTR Operator Training and 47.58 14.15 l Requalification I UFTR Testing and Surveillance

• 42.83 34.97 Conmercial Utilization 166.05 123.93 I (Louisiana Power & Light Reactor f Operator Training)'

Reactor Tours and Demonstration Runs ** 46.08 8.49 l

l TOTALS 483.04 301.43 1

• Console checkouts are excluded I ** Note: 33 tours were conducted for 313 persons. These include high school, junior college and UF students, emergency response team units and interested members of the general public.

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MONTHLY REACTOR ENERGY GENERATION Monthly Totals Kw-Hrs Hours at Full Porter

l September 1979 1.33 0.0 October 1979 141.43 1.4

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November 1979 0.1 0.0

December 1979 17.1 0.17 January 1980 725.95 7.25 l February 1980 682.72 6.73 March 1980 1,163.61 8.67 April 1980 1,855.0 18.5 June 1980 222.16 1.60 July 1980 1,554.03 13.03 l

l August 1980 _140.51 1.35 I TOTALS 9,800.14 __90.97

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I TABLE IV l

J l UNSCHEDULED SCRAMS Date Occurrence I May 6, 1980 Electrical Failure I

July 14, 1980 Electrical Transient July 24, 1980 Manual Scram

• July 25,1980 Electrical Failure I

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• Senior Operator initiated manual scram on realizing PuBe source was still in reactor at 10 kw power level. Full port submitted to NRC on incident on August 5,1980.

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I 12 il IV. MODIFICATIONS TO THE OPERATING CHARACTERISTICS OR CAPABILITIES OF THE UFTR II l No significant modifications to the operating characteristics of the l

l UFTR were done during the period September 1,1979 through August 31, 1980.

A series of significant improvements in the area of Physical Protection

• and Emergency Response have been implemented.

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• Withheld from public disclosure pursuant to 10 CFR 2.790 r

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V. SIGNIFICANT MAINTENANCE AND TEST OF REACTOR SYSTEMS I Date Description I 6 September,1979 Replaced Dry Cells Security System Control Unit 18 September,1979 Replaced Motor Drive Safety Blade #2 28 September,1979 S-1 Control Blade Drop Times Completed l 16 October, 1979 25 October,1979 Q-1 Completed Quarterly SCRAM Checks S-2 Completed Blade Worth Measurements 5 November,1979 Repaired Recorder Air Particulate Detector 4 December,1979 Q-2 Calibration Check of Area Monitors 7 December,1979 Q-3 Conducted Radiological Emergency Drill l 11 December,1979 20 December,1979 Repaired 2 Pen Recorder Repaired 2 Pen Recorder 15 January, 1980 Q-1 Completed Quarterly Scram Checks 15 January,1980 Replaced the 2 Pen Recorder Amplifier 16 January, 1980 Repaired Digital Blade Position Indicator l 4 February, 1980 11 February,1980 Leak Checked Antimony-Beryllium Source Reactivity Worth Measurements Safety #1 12 February, 1980 Reactivity Worth Measurements Safety #1

13 February,1980 Reactivity Worth Measurements Safety #1 15 February, 1980 Repaired Leak Shield Tank Purification Loop

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l 18 February,1980 Repaired North Area Monitor Recorder

. 27 February, 1980 Q-3 Radiological Emergency Drill With Disaster Team and Hospital 5 March, 1980

I Q-2 Completed Calibration Checks Area Monitor I

14 l Date Description 12 March 1980 Repaired Stack Monitor Preamplifier 13 March 1980 Completed Power Installation for Relocating Partial Monitor 31 March,1980 Repaired Solo Bridge Conductivity Probe 1 April, 1980 S-1 Blade Drop Timing Checks I 10 April, 1980 Repaired Connection to Security System 10 April, 1980 Repaired Batteries in Security System 16 April,1980 A-2 Annual Calibration Test of Nuclear Instruments 22 April,1980 Replaced Rupture Disc in Coolant System l 2 May, 1980 Q-1 Quarterly Check Scram Functions 20 May, 1980 Q-2 Calibration Check of Area Monitors 27 May, 1980 S-2 Reactivity Check of Blade Worth 2 June, 1980 Changed Secondary Cooling to City Water 3 June, 1980 Changed Secondary Cooling to City Water l 24 June, 1980 3 July, 1980 Q-3 Completed Radiological Emergency Drill Q-1 Quarterly Check Scram Functions 24 July, 1980 Changed Secondary Cooling to City Water 24 July, 1980 Changed Secondary Cooling to Well Water 7 August, 1980 Cleaned and Decontaminated East West Thru Port l

I 15 August, 1980 Oiled Diluting Fan Bearing 26 August, 1980 Q-1 Quarterly Check Scram Functions 27 August, 1980 Replaced Overhead Crane Support Cable 29 August, 1980 Q-3 Completed Radiological Emergency Drill

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VI. CHANGES TO TECHNICAL SPECIFICATIONS AND STANDARD OPERATING PROCEDURES I

A. There were no changed to the Technical Specifications during this reporting period.

.l B. Revisions to Standard Operating Procedures

1. UFTR-SOP-A.1 - Pre-operational Checks

. a. PART II Rev.10, 5/80

2. UFTR-SOP-A.2 - Startup

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Paga 4 Page 5 Rev. 6,10/80 Rev. 6,10/80

c. Page 6 Rev. 6, 10/80

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3. UFTR-SOP-A.3 - Operation at Power

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a. Page 1 Rev. 6, 10/80

4. UFTR-SOP-D.2 - Radiation Work Pennit

a. Page 1 Rev. 7, 8/80

5. UFTR-SOP-E.4A - Reactor Shielding and Graphite

a. Coversheet Orig.,1/80

b. Page 1 Orig. , 1/80

c. Page 2 Orig. ,1/80

6. UFTR-50P-E.4B - Auxiliary Systems Maintenance Shield Tank & Shield Tank Recirculating System

a. Coversheet Ori g. , 1/80

b. Page 1 Ori g. , 1/80 I c.

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VII. RADI0 ACTIVE RELEASES AND ENVIRONMENTAL SURVEILLANCE A. Gaseous (Argon-41) ,

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i Month pCi Released pCi/ml*

September 1979 5.93 x 10 3 2.06 x 10-12

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October 1979 6.3 x 10 5 2.19 x 10-10 November 1979 4.01 x 10 2 1.39 x 10-13 December 1979 7.62 x 10 4 2.65 x 10-II g January 1980 3.24 x 10 6 1.12 x 10-9 February 1980 3.04 x 10 6 1.05 x 10-9 March 1980 5.19 x 10 6 1.8 x 10-9 April 1980 8.27 x 10 0 2.01 x 10-May 1980 1.4 x 10 7 3.5 x 10-9 June 1980 9.9 x 10 5 2.41 x 10-10 July 1980 6.9 x 10 6 1.7 x 10-9 August 1980 6.2 x 10 5 1.52 x 10-10

.g TOTAL ARGON-41 RELEASED = 42.39 Ci

3 B. Liquid Waste From The UFTR/ Nuclear Sciences Complex *

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There were 618,000 liters discharged to the campus sanitary sewage system during this reporting period.

Month pCf/ml8 September 1979 2 x 10-9 lI November 1979 NDA December 1979 NDA

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T I 17 I Month pCi/ml8 January 1980 1.7 x 10-8 February 1980 NDA April 1980 NDA July 1980 NDA August 1980 NDA I

• The effluent discharged into the holding tanks comes from twenty laboratories within the Nuclear Sciences Center as well as the UFTR complex.

NDA - No Detectable Activity, minimum detectable activity = 2.4 x 10-9 pCi/ml The UFTR normally released to the holding tanks approximately 1.5 liters of pri-mary coolant per week due to waste from primary sampling. The average activity for this coolant was y.34 x 10-7pCi/ml for the reporting period.

I On April 22, 1980, approximately 176 liters of water were released to the hold-ing tanks at 1.08 x 10-7 pCi/ml. This represents the total primary coolant re-I lease for this reporting period. There was no detectable alpha activity released.

Allowing for the decay in the holding tanks and using a characteristic half-life of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, the activity was reduced to less than 5.4 x 10-8 pCi/ml. This ac-tivity was diluted to a level of NDA before tanks were released to the environ-I ment.

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I The UFTR maintains film badge monitoring in areas adjacent to the UFTR complex.

The seven monthly monitored film badges usually read less than 10 millroentgens.

I The following is the total for this reporting period September 1979 through August 1980:

A-1 50 millirens l A-2 A-3 40 millirens 20 millirens A-4 20 millirens g A-5 50 millirens

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A-6 30 millirens A-7 20 millirens No personnel associated with the UFTR received more than 10 mr/ month.

Dosimeter exposure measurements for visitors to the UFTR were all less than 5 I milliroentgen for this reporting period.

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VIII. EDUCATION, RESEARCH, AND TRAINING UTILIZATION Note: The participating students are indicated with an *. Other partici-pants are faculty or staff members of the University of Florida, un-less specifically designated otherwise. A ** indicates those stu-I dents working on theses or dissertations.

1. Nuclear Engineering Laboratory II (ENU 6516) - Dr. E.E. Carroll, Dr.

l W.H. Ellis, Dr. W.G. Vernetson (Nuclear Engineering Sciences)

This Nuclear Engineering Laboratory for graduate students used the UFTR for a series of experiments, including irradiation of materials and reactor measurements.

2. Principles of Nuclear Reactor Operations (ENU 5176) - Dr. N.J. Diaz, UFTR Staff (Nuclear Engineering Sciences)

For this course, participating students are assigned in pairs to spend two hours weekly in the UFTR cell perfonning reactor startups, shutdowns, operations at power, as well as tests and calibrations of reactor systems and nuclear instruments normally doni as routine checkouts. This course is recommended for senior undergraduates and graduate students in Nuclear Engi-I neering. All student activities in the UFTR are performed under the direction of a licensed Reactor Operator or Senior Reactor Operator.

3. Principles of Nuclear Reactors (ENU 4101) - Dr. H.D. Campbell (Nuclear Engi-neering Sciences)

Fundamental aspects of reactor operations are demonstrated to engineering students majoring in areas other than nuclear engineering.

4. Fundamentals of Reactor Engineering (ENU 5005) - Dr. H.D. Campbell (Nu-clear Engineering Sciences)

Fundamental aspects of reactor operations are demonstrated to engineering students majoring in areas other than nuclear engineering.

5. Nuclear Engineering Laboratory 1 (ENU 4505L) - Dr. W.H. Ellis (Nuclear l Engineering Sciences)

This Nuclear Engineering Laboratory for undergraduate students used the UFTR for a series of experiments and exercises that included: radiation field I

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surveys and radiation protection, measurement of the diffusion length of neutrons in graphite, low and high power reactor operations,1/m approach to critical by control blade, temperature coefficient measurements, and blade reactivity measurements by blade drop and positive period techniques.

6. Application of Nuclear Radiation and Energy 1 (ENU 4304) - Dr. W.H. Ellis (Nuclear Engineering Sciences)

The use of radioisotopes in nuclear analysis, engineering and special re-search problems are demonstrated by the activation of materials in the UFTR and the corresponding studies.

7. Special Problems in Environmental Engineering (ENV-6932) - Dr. B.G. Dunavant, H. Norton, (Environmental Engineering Sciences)

The reactor is used for demonstration of resctor operations, for reactor-related health physics activities and radiation protection exercises and for isotope technique laboratories.

8. LPL Reactor Operations Training Program - N.J. Diaz, G.W. Fogle, H. Gogun, l W.G. Vernetson (Nuclear Engineering Sciences)

The cold-license candidates for the Waterford 3 SES nuclear power plant of the Louisiana Power and Light Co. spent three weeks performing hands-on oper-ations at the UFTR. This is a federal requirement established for candidates for Reactor Operator licenses.

l 9. UFTR Operator Training and Requalification - N.J. Diaz, G.W. Fogle, H. Gogun and Reactor Staff (Nuclear Engineering Sciences)

The training or requalification programs establish a required number of startups, weekly checks, daily check, drills and lectures for each operator to participate in in order to develop or maintain proficiency.

10. NAA Research - Trace Elements and Cancer - Dr. G.S. Roessler, John Swanson**,

l M. Soucie* (Nuclear Engineering Sciences)

This research project studied the relationship between trace elements in tissue, cancer and cancer metastasis. Activation analysis of murine melanoma tissue is used to compare elemental composition of mouse normal tissue, primary tumor and metastasis. The research also used various biological standards to I

t 20 establish base composition levels.

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E.E. Carroll, N.J. Diaz, M. McCoy** (Nuclear Engineering Sciences)

Foils are activated in the UFTR to calibrate foils strings and test the computational system that will be used in the Gaseous Core Reactor Experiments at Los Alamos Scientific Laboratory.

12. UFTR Calibration and Test Runs - H. Gogun, G.W. Fogle (Nuclear Engineer-ing Sciences)

I The required testing and surveillance of reactor protection, control and radiation monitoring systems is conducted according to the established re-quirements of the Technical Specifications.

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1. " Trace Elements and Cancer," Ph.D. dissertation, John Swanson, August 4, 1980.

2. " Generation, Measurement and Utilization of Xenon Excimer Radiation Pro-duced by Nuclear Reactor Products," R.A. Walters, et al., ANS Transactions, Volume 34, June, 1980.

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