ML20132H106
| ML20132H106 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 12/31/1989 |
| From: | Stansberry E PURDUE UNIV., WEST LAFAYETTE, IN |
| To: | |
| Shared Package | |
| ML20132H016 | List: |
| References | |
| NUDOCS 9612270139 | |
| Download: ML20132H106 (6) | |
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SC~HOOL OF NUCLEAR ENGINEERING !
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Purdue University West Lafayette, Indiana 47907 o
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9612270139 961212 DR ADOCK 0500 2
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l O REPORT ON REACTOR OPERATIONS For the Period ,
1 January 1,1989 to December 31,1989 PURDUE UNIVERSITY REACTOR-1 PURDUE UNIVERSITY O West Lafayette, Indiana 47907 March,1990 Prepared by Eldon R. Stansberry Reactor Supervisor O
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- 1. INTRODUCTION This report is submitted to meet the requirements set forth in 10 CFR 50.59 and the technical specifications of the Purdue University Reactor (PUR-1) for the period January 1,1989 to December 31,1989.
During the reporting period of 1989 a total of 643 persons visited the teactor facility.
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Those persons included 170 different groups, of which 104 groups were for the purpose of maintenance or surveillance testing,14 groups were for class purposes, 29 groups were pre-scheduled tours,6 groups were participants in our reactor sharing program and 17 were miscellaneous groups.
- 2. PLANT DESIGN AND OPERATIONAL CIIANGES 2.1 Facility Design Changes There were no design changes to the facility in 1989.
2.2 Performance Characteristics The operation of the PUR-1 facility continued satisfactorily during the reporting period. During the visualinspection of the surfaces of two representative fuel plates no changes were identified. This inspection included any defects that might compromise the integrity of the cladding including any evidence of corrosion.
Satisfactory preformance of the fuel continued during the year.
2.3 Changes in Operating Procedures Concerning Safety of Facility Operations O
No changes in the operating procedures of the facility were made during 1989.
2.4 Results of Surveillance Tests and Inspections 2.4.1 Reactivity Limits 1
The reactivity worths of the control rods were determined to be as follows:
Shim-safety #1 - 5.01%
D Shim-safety #2 - 2.66% l Regulating Rod - 0.25%
The worth curves of the control rods were checked after the inspection and the excess was calculated to be 0.45%. The shutdown margin was determined to be 7.47% based on these values.
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'). 2 The control rod inspection was done on July 6,1989 with no evidence of .
change or deterioration observed. 1 i
No experiment was placed in the reactor pool during the year that would require the determination ofits reactivity during the initial criticality j following its installation. I J' 2.4.2 ' Reactor Safety Systems Each prestartup check included a channel test for each safety system, provided the shutdown exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or if the system was repaired or de-energized.
Each reactor safety system had a channel check performed at time intervals of less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during operation.
3' On August 29,1989 the electronic calibration of all safety channels was ;
completed.
- The irradiation of gold foils for a power calibration was done on September _ ;
11,1989. No significant change was identified from this irradiation.
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! During the prestanup which precedes each run, the radiation ama monitors I
- . and the continuous air monitor were checked for normal operation. During j j 1989 the calibration of the radiation ama monitors was completed on March
{3 27 and September 18 and the calibration of the continuous air monitor was completed on March 30 and September 29.
Following the control rod inspections, the rod drop times wem measured on j July 10,1989. The rod drop times fell between 412 and 562 milliseconds.
These values are consistent with past measurements and are well within the specification limits of I second.
2.4.3 Primary Coolant System O The weekly measurements of the pH of the primary coolant fell between 5.0 and 6.4 during 1989. These value are within the specification limits of 5.5 +_
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During the prestartup check, which proceeds each run, the conductivity of the
. primary coolant was measumd and the values never exceeded 1.35 O
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9 micromhos-cm. This represents a resistivity of more than 740,000 ohnVem 1 which exceeds the lower limit of 330,000 ohnvem as given in the speciScations. i The specification of 13 feet of water was always either met or exceeded,- i according to the prestarted check list that was completed prior to each reactor -
y run.
Monthly samples of the primary coolant was collected and analyzed by personnel from Radiological and Environmental Management for'gmss alpha ~
j and beta activity. No activity was identified in the samples which would indicate failure of the fuel plates. 2 2.4.4 Containment.
Readings between 0.055 and 0.135 inches of water were recorded weekly 'for l0 the negative pressure in the reactor room and exceeded the minimum of 0.05 inches required by the specifications. !
F F The semi-annual checks made in 1989 for the proper operation of the inlet l and outlet dampers and the air conditioner were completed on April 17 and l October 18,1989. All worked satisfactorily.
l Selected fuel plates were visually inspected on July 6,1989. nc surface
[ condition of fuel plate #4-3-73 indicated no change fmm the last inspection, g and the cladding of the other inspected plates identified no changes.
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' 2.4.5 Experiments I
The mass of the singly encapsulated samples and the flux of the reactor are such that the complete release of all gaseous, particulate, and volatile components of the samples would not result in doses in excess of 10% of the equivalent annual doses as stated in 10 CFR 20.
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No samples of unknown composition or that required double encapsulation 1 0;
were submitted forirradiation. i 2.5 Changes, Tests and Experiments Requiring Commission Authorization l
During 1989 no changes, or e.xperiments which required authorization from the Commission pursuant to 10 CFR 50.59 (a) were performed.-
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t I (3 4 2.6 Changes in Facility Staff l
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i l No changes in the facility staff occurred in 1989. l
- 3. POWER GENERATION 1 l l Operation of the PUR-1 during 1989 consisted of 47 runs which generated 321,636 watt-O minutes of energy and covered an integrated running time of 124.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 4. UNSCHEDULED SHUTDOWNS l
Ten unscheduled shutdowns occurnd during 1989. All shutdowns were associated with l the log in channel. Three shutdowns were caused by rod drops. Operating closer to the instruments bop current than the instrument was designed to operate often causes a drop if an irregularity develops in the magnet current. The mmaining shutdowns were related to false period indications. Voltage checks and routine maintenance corrected these
. problems.
All of these unscheduled shutdowns were on the conservative side of safety and no unsafe condition existed at the time of shutdown.
- 5. MAINTENANCE Only routine maintenance was requimd during the reporting period.
- 6. CHANGES, TESTS AND EXPERIMENTS
- g No changes, tests or experiments wem carried out without prior Commission approval pursuant to the requirements of 10 CFR 50.59 (b).
- 7. RADIOACTIVE EFFLUENT RELEASES No measurable amount of radioactive effluents were micased to the environs beyond our effective control, as measured at or prior to the point of such release.
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