ML20237L089
| ML20237L089 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 08/21/1987 |
| From: | Roush M MARYLAND, UNIV. OF, COLLEGE PARK, MD |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709080209 | |
| Download: ML20237L089 (15) | |
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THEUNIVERSIT(OF MARYLAND J
COLLEGE PARK CAMPUS j Department of chemical and Nuclear Engineering August 21, 1987 Section 50.4 Distribution Document Control Desk U.S. Nuclear Regulatory Commission h-hUhbbb '
Washington, D.C. 20555
Dear Sir / Madam:
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This annual report is submitted in accordance with requirements set forth in our Technical Specifications for j the Maryland University Training Reactor (MUTR). _This report l
covers the time period from June 30, 1986 to June 30, 1987. l A. Summary of Operation Experience During the period of June 30, 1986 to June 30, 1987 the reactor was operated 201 times, an increase of 12% over l 1985-6, producing a total of 14.5 megawatt-hours of energy. i This is equivalent to approximately .74 grams burnup of U-235.
Several minor problems were encountered with the reactor during this reporting period. Corrections and minor adjustments were made to the reactor during this time.
The general reactor operations can be broken down into the following categories:
- a. Operator Training and Nuclear Engineering Courses (54%)
- b. Activation Analysis (27%)
- c. C~alibration and Maintenance (9%)
- d. Tours and Demonstrations (10%)
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Cohege Park. Maryland 20742 (301) 454-2430/6
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We continued to provide reactor service to the Nuclear Engineering courses; primarily, ENNU 320 - Nuclear Reactor ;
l Operations. This service utilized the reactor for five j (5) two hour sessions per week. Continued reactor training l
time was provided to the Armed Forces Radiobiological Research
'*' l Institute operators and staff to continue their operating l proficiency, while their reactor was under reconstruction.
Three AFRRI Senior Operators successfully passed their operations exam at our facility through special permission granted 4 i
by the Nuclear Reulatory Commission. In addition, two University l personnel obtained their operator's licenses.
The DOE " Reactor Sharing Program" was renewed at the same level of effort for this reporting period. This enabled us to use four (4) students on a part-time basis to support reactor operations.
An extensive effort has been devoted during this time period to the characterization of the neutron and gamma fluxes using ASTM standard techniques. This was undertaken in order to provide a standardization irradiation facility l i
for outside contract support. Two undergraduate students from the University won awards for presentations based on this characterization work at the recent Eastern Regional ANS student conference.
Activation Analysis was done in support of a Chesapeake Bay Oyster-Radioisotopic analysis program directed by Dr. ,
l Maria Gavrilas for the Baltimore Gas and Electric Company.
The objective of the project is to relate the operation of the Calvert Cliffs Power Plant to the uptake of silver by oysters in the surrounding Chesapeake Bay. Over 60 more samples of oysters have been analyzed for cilver by neutron activation analysis.
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" 'In related work, one student used the MUTR in her master's thesis to determine the buildup silver in coolant water by determining the concentration of Ag10Sm by neutron activation analysis.
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August 21, 1987 Several electronic componbnts and systems have been irradiated for Westinghouse Corp. under contract. They have been interested in the neutron exposure level which leads to failure.
Some activation analysis work has been performed for the Wye River Institute to determine the extent of migration of fertilizer from fields near the Chesapsake Bay.
Samples of ceramic material have been activated in the MUTR as part of a study being carried out at University of Maryland Baltimore Campus, concerning high. temperature superconducting properties.
s Ten (10) millicuries of Nd-147 was produced under contract for the Catholic University of America by the irradiation of Nd (natural) metal.
B. Maintenance Items 9/4/86 Problem: Bulk water temperature indicator Solution: Removed RTD from electrical connector and cleaned out, sprayed with tuner cleaner and placed back in position about 1 in. further in the water than before.
9/4/86 Problem: Inlet water indicator Solution: ,
Cleaned up electrical connection and sprayed with tuner cleaner.
9/10/86 Problem: Pressure drop in secondary water check valves Solution: The pressure drop in the secondary water check valves was checked by Kilamaya Plumbing Co. and was measured ,
to be only 3 psi. Therefore, the flow does not appear to be limited by the check valves.
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August 21,_1987 ;
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.i 9/17/86 Problem: Diffuser pump. motor is blowing fuses j Solution: Physical Plant electricians rewired the diffuser pump from 12 amps to the specified 6 amps. This will minimize the circuit breaker trip frequency.
9/30/86 Problem: Failure of fuel temperature read j
-, out Solution: Replaced the-battery in fuel thermocouple device.
2/5/87 Problem: Sensitivity of glove box monitor i'
Solution: Moved glove box radiation monitor instrument electronic circuitry from consolc r00m to the Hot Room.
Doing this reduced capacitance in the cable to the detector circuitry.
Sensitivity has been improved and the monitor tracks with a portable- j survey meter up'to approximately l 5 mR but is nonlinear after that ;
point. This nonlinearity problem l is being investigated. In the meantime, radiation levels at-the surface of the rabbit are being recorded j in isotope log book.
2/87 Problem: KW-Hr meter reading low
'? to 4
6/9/87 Solution: After a series of continuing problems with KW-Hr meter reading low, the CIC power supply and CIC itself were replaced, and the new system adjusted to indicate the correct KW-Hr produced, f
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August 21, 1987 4/8/87 Problem: Diffuser pump occasionally will not start.
Solution: Found loose connecting bar on overload in controller. Tightened bar, operational check was satisfactory.
5/6/87 Problem: Exhaust external scram did not work during start-up check.
Solution: Adjusted cabling and tightened connector.
Scram functions properly.
5/13/87 Problem: Exhaust external scram not working Solution: Replaced circuit board #1 on exhaust j monitor, due to faulty Scram drivo '
transitor. Scram now functicns properly, i l
6/29/87 Problem: Hot Room cave lead bricks fell on l worker !
i Solution: Proceeded according to personnel i emergency plan. Rebuild brick wall.
Plans made for making wall more secure.
C. Equipment Surveillance and Tests I
Area Radiation Monitors Area radiation monitors for the bridge and exhaust were calibrated in accordance with the Technical Specification surveillance schedule.
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, f, Pool Water Analysis i
Pool water was sampled and activation analysis made on a monthly basis in accordance with the Technical Specification
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surveillance schedule. No radioisotope concentration above MPC was measured.
Control Rod Inspection l A control rod inspecti'on was performed December 16, 1986. The appearance of the rods has not changed since the last inspection of January 7, 1985.
Control Rod Calibration i Control rod worth calibrations were performed during the time period September 8 - 13, 1986. The measured integral and differential worth is within experimental error of previous calibrations. Shutdown margins and excess reactivities were calculated and found to be within the Technical Specification requirements.
Control Rod Drop Time ,
I Control rod drop times were measured on December 16, 1986. All drop times were less than .8 seconds which are less than the 1 second required by the Technical Specifications.
Power Calibration A power calibration war 7erformed on October 11, 1986.
The measured thermal power output was 200 kW and the indicated power on. Safety Channel I and II were 200 kW and 202.5 kW respectively. Since the measured and indicated power levels were very close, no adjustments of either Safety Channel were made.
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August 21, 1987 l D. Radioactive Effluent Discharged to the Environment and Radioactive Waste Shipped Of f-site f or Di sposal No waste water with radioisotopic concentrations greater than MPC were discharged to the sewer system. Monthly air ;
samples taken in the reactor building contained no activity greater than background. A small amount of low level radioactive j waste in liquid and solid form has been shipped for off-site i disposal through the University Radiation Safety Office.
E. Unplanned Shut-Downs, Scrams and Reportable Occurrences i
Two unplanned shut-downs associated with Reportable i occurrences have taken place during this reporting period.
Both Reportable Occurrences were reported promptly to NRC Region I followed within two weeks by a written report.
The first one occurred on September 30, 1986 with a ;
low battery voltage causing a malfunction in the fuel temperature i thermocouple circuit. The second one occurred on March 26, 1987 when the Safety Channel II IC was moved by mistake during shutdown conditions and discovered during a subsequent reactor run.
' F. Radiation Exposures l See the attached ALARA audits for this time period.
(1985 - 1986 and 1986 - 1987)
G. Changes to Facility Personnel, Procedures, and Experiments Dr. David D. Ebert became the Reactor Director on April 6, 1987 and Dr. Ralph L. Belcher became the Associate Reactor Director on the same day.
The Office of Provost of Mathematics, Physical Science and Engineering has been eliminated and replaced in the organizational table by the Dean of Engineering starting July 1, 1966.
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August 21, 1987 4 Changes to Procedures have been reviewed and approved by the Reactor Safety Committee. Change to the following
< Procedures have been made:
- 1. OP101-Reactor Startup Checkout
- 2. OP102-Reactor Shutdown checkout
- 3. OP105-Installation of Experiments l
Two special experiments which consist of modifications inside the by approved East theand West Safety Reactor Beam Ports have been reviewed and Committee.
Sincerely, MLR:ga k,u.ek f voYu Marvin L. Roush Chairman / Professor k Chemical & Nuclear Engineering j i
Department I cc: Dr. David D. Ebert Dr. Frank J. Munno Mr. Lowell E. Tripp Mr. David F. Limroth Mr. Thomas Foley Enclosure i
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THE UNIVERSITYOF MARYLAND COLLEGE PARK CAMPUS Department of Chemical and Nuclear Engineering August 21, 1987 MEMORANDUM TO: Dr. Gary Pertmer C//- 6,Y 8[2 7/87 Chairman
' Reactor Safety Committee FROM: h -
Dr. David Ebert Reactor Director
Subject:
ALARA Audit for 8/15/86 to 6/15/87 Item 1 Radiation Area Monitor Calibration All portable radiation monitors have been calibrated s emi-annually . This service is performed by Radiation Safety with the exception of the RAMS and the Glove Box Monitor.
The Glove Box Monitor was recalibrates on 1/6/87.
The RAMS were calibrated on 4/27/87.
. Item 2 Control Rod Inspection The control rods are inspected bi-annually. Inspection was performed 12/16/86. No significant changes had occurred since last inspection.
Item 3 Fuel Rod Inspection This inspection is not required according to the MUTR Tech. Spec. (8/7/84). This inspection has been replaced by Pool Water Gamma Ray Analysis.
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Page Memo - Dr. G. Pertmer August 21, 1987 I
Item 4. I q Power Calibration A power calibration was performed on 10/11/86.
The results were as follows:
1 1 Indicated power level on:
Safety Channel I = 200 kW Safety Channel II = 202.5 kW Measured thermal power output = 200 kW Since the measured and the indicated power levels were very close, no adjustments of safety channel I or II were made.
Item 5 )
l Pool Water Gamma Activity Analysis Gamma activity analysic has been performed on a monthly basis of reactor poo) Water. No radioisotope attributed to fission products were found. All radioisotopes' concen-tration were no grerter than the
. maximum permissible concen-tration.
Item 6 Film Badge Exposure Records
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. ':+d, All but 7 personnel film badges showed exposures less than 10 mrem. 7 persons received exposures greater than 10 mrem as follows:
3 persons received approximately 30 mR 1 person received approximately 40 mR 2 persons received approximately 70 mR' 1 person received approximately 80 mR
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Memo - Dr. G. Pertmer I August 21, 1987 j 1
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The following is a list of the 3 0 area mor.itors film badges. 1
,, Monitor # Location Exposure (mrem) 1 Control Room 10 2 Bridge 750 j 3 Hot Room 50 l 4 W. Balcony 50 '
5 S. Wall upper level approx. 10 6 S. Wall lower level approx. 10 7 E. Wall lower level approx. 50 8 Water Room 880
- 9 N. Wall lower level 110 10 W. Wall lower level 10
- = Pu Be sources stored in water roon Item 7 Contamination Survey Report l
l No area of contamination was found.
Item 8 Self-Reading Pocket Dosimeters (a) Calibration l
The calibrations are performed every 6 months by Radiation Safety.
(b) Visitors Log-Personnel Exposure l No significant dose was recorded in the pocket dosimeter for any visitors during this audit period.
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THE UNIVERSITY OF MARYLAND COLLEGE PARK CAMPUS Department of Chemical and Nuclear Engineering June 23, 1987 MEMORANDUM TO: , Gary Pert Vt N unau wa n ,
Reactor Safety Committee FROM: b b- /
Dr. David Ebert Reactor Director
Subject:
ALARA Audit for 8/11/83 to 8/14/86 Item 1 Radiation Area Monitor Calibration All portable radiation monitors have been calibrated semi-annually. This service is performed by Radiation Safety with the exception of the RAMS and the Glove Box Monitor.
The Glove Box Monitor was replaced and recalibrates on 9/11/85.
The RAMS were calibrated on 5/19/86.
Item 2 Control Rod Inspection The control rods are inspected biannually. Inspection was not required during this reporting period.
Item 3 '
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Fuel Rod Inspection l I
This inspection is not required according to the MUTR Tech. Spec.
(8/7/84). This inspection has been replaced by Pool Water Gamma Ray Analysis. !
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l Memo to Dr. G. Pertmer June 23, 1987 l
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Power Calibration l No power calibration was performed during this audit period. How- l l ever, one was done on 10/11/86. I i
The results were as follows:
l Indicated power level en:
Safety Channel I = 200 kW Safety Channel II = 202.5 kW Measured thermal power output = 200 kW Since the measured and the indicated power levels were very close, no adjustments of safety channel I or II were made.
Item 5
, Pool Water Gamma Activity Analysis, Gamma activity analysis has been performed on a monthly basis of reactor pool water. No radioisotope attributed to fission products were found. All radioisotopes' concentration were no greater than the maximum permissible concen". ration.
Item 6 Film Badge Exposure Records All personnel film badges showed no over exposures. However, 23 l persons did receive reportable doses of exposure.
l l 7 persons received approximately 10 mR l 14 persons received approximately 20 mR 1 person received approximately 40 mR (shallow) 1 persn received approximately 60 mR (deep) and 130 mR (shallow) 1 a - __ _ - _ _ _ _ _ _ _ _ _ - - _
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Memo to Dr. G. Pertmer l June 23, 1987 )
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The following is a list of the 10 area monitors film badges. !
Monitor # Location Exposure 1 Control Room M (minimal <10) 2 Bridge 360 3 Hot Room 80
- 4 W. Balcony 80 5 S. Wall upper level M 6 S. Wall lower level M 7 E. Wall lower level 110 8 Water Room 840 9 N. Wall lower level 70 10 W. Wall lower level 20 Monitor 8 was the only monitor deviating from last year's value.
A total of 160 mR of the 840 mR reported were due to fast neutrons.
Item 7 Contamination Survey Report I
No area of contamination was found. j Item 8 Self-Reading Pocket Dosimeters (a) Calibration The calibrations are performed every 6 months by Radiation Safety.
(b) Visitors Log-Personnel Exposure No significant dose was recorded in the pocket dosimeter for any visitors during this audit period.
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