ML20132H122
| ML20132H122 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 12/31/1992 |
| From: | Clikeman F PURDUE UNIV., WEST LAFAYETTE, IN |
| To: | |
| Shared Package | |
| ML20132H016 | List: |
| References | |
| NUDOCS 9612270143 | |
| Download: ML20132H122 (6) | |
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4 SCHOOL OF NUCLEAR ENGINEERING d
Purdue University West Lafayette, Indiana 47907 o = %.
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i l REPORT ON REACTOR OPERATIONS l
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For the Period January 1,1992 to December 31,1992 l
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PURDUE UNIVERSITY REACTOR-1 l PURDUE UNIVERSITY !
West Lafayette, Indiana 47907 i June,1993 2
Prepared by F. M. Clikeman Laboratory Director and Reactor Supervisor i
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- 1. INTRODUCTION This mport is submitted to meet the requimments set forth in 10 CFR 50.59 and the technical specifications of the Purdue University Reactor (PUR-1) for the period January -
1,1992 to December 31,1992.
During the reporting period of 1992 a total of 434 people visited the reactor facility.
Those people included 111 different groups, of which 77 groups wem for the purpose of maintenance or surveillance testing,10 groups were for class purposes, 19 groups wem -
pre-scheduled tours,4 groups were participants in our reactor sharing program and I was classified as a miscellaneous group.
- 2. PLANT DESIGN AND OPERATIONAL CHANGES 2.1 Facility Design Changes Them were no design changes to the facility in 1992.
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 No changes in the operating procedures of the facility.
2.4 Results of Surveillance Tests and Inspections 2.4.1 Reactivity Limits The mactivity worths of the control rods were determined to be as follows:
Shim-safety #1 - 5.00%
Shim-safety #2 - 2.65%
Regulating Rod - 0.27%
, The worth curves of the control rods wem checked after the inspecdon and the excess was determined to be 0.44%. The shutdown margin was determined to be 7.92% based on these values.
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,, The inspection of the control rods was completed on July 29,1992 with no l
, evidence of change or deterioration observed. :
, 1 No experiment was placed in the reactor pool during the year that would - l j_ require the determination ofits reactivity during the initial criticality !
I ' following its installation.
2.4.2 Reactor Safety Systems 1
i Each prestartup check included a channel test for each safety system, - j l 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-E 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.
On July 31,1992 the electronic calibration of all safety channels was
- compl:ted.
i fa The irradiation of gold foils for a power calibration was done on August 20 j and 27. The first calibration on August 20 indicated that the actual power was
- , 16% below the indicated power level at 100 watts and that the system was 1- nonlinear in a conservative direction. Therefore, it was decided to reposition j_ the channel 2 detector to give a more accurate power indication. This was accomplished on August 27 and second power calibration was made.
On October 15, channel 2 had to be recalibrated and another power calibration was performed to verify the absolute power calibration of the reactor. The actual power level was 14% below the indicated power. This is in the safe direction.
During the prestartup which precedes each ron, the radiation area monitors and the continuous air monitor were checked for normal operation. During 1992 the calibration of the radiation area monitors and the continuous air ;
monitor was completed on March 17 and September 15.
Following the control rod inspections, the rod drop times were measured on July 30,' 1992. The rod drop times fell between 607 and 653 milliseconds.
These values are consistent with past measurements and are well within the ;
. specification limits of I second.
' 3 2.4.3 Primary Coolant System The weekly measumments of the pH of the primary coolant fell between 5.2 an'd 5.5 during 1992. These value'are within the specification limits of 5.5 +
1.0.
During the weekly checks and the prestanup check which proceeds each run, the conductivity of the primary coolant was measured and the values never exceeded 1.47 micromhos-cm. This represents a resistivity of more than 680.000 ohm /cm which exceeds the lower limit of 330,000 ohm /cm as given in the specifications.
The specification of 13 feet of water was always either met or exceeded, according to the prestarted check list that was completed prior to each reactor run.
Monthly samples of the primary coolant was collected and analyzed by per'sonnel from Radiological and Environmental Management for gross alpha and beta activity. No activity was identified in the samples which would indicate failum of the fuel plates.
. 2.4.4 Containment Reading . tween 0.06 and 0.16 inches of water were recorded weekly for the negar;ve pn:ssure in the reactor room.
The semi-annual checks made in 1992 for the proper operation of the inlet and outlet dampers and the air condidoner were completed on March, September, and December 1992. All worked satisfactorily.
Selected fuel plates were visually inspected on July 29,1992. The surface condition of fuel plate #4-3-73 indicated no change from the last inspection, and the cladding of the other inspected plates identified no changes.
2.4.5 Experiments The mass of the singly encapsulated samples and the flux of the reactor are such that the complete release of all gaseous, paniculate, 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.
4 No samples of unknown composition or that mquired double encapsulation were submitted for irradiation.
2.5 Changes, Tests and Experiments Requiring Commission Authorization During 1992 no changes, or experiments which required authorization from the Commission pursuant to 10 CFR 50.59 (a) were performed.
2.6 Changes in Facility Staff There were no changes in the Facility Staff during the year.
- 3. POWER GENERATION Operation of the PUR-1 during 1992 consisted of 15 runs which generated 72,574 watt-minutes of energy and covemd an integrated running time of 46.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 4. UNSCHEDULED SHUTDOWNS One unscheduled shutdown occurred during 1992. This shutdown was associated with noise on the input of the log N channel generating false period indications in CSA-2. ]
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. .
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- 5. MAINTENANCE l 1
Only routine nidintenance was required during the mporting period.
- 6. CIIANGES, TESTS AND EXPERIMENTS No changes, tests or experiments were 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 efnuents were released to the environs beyond our l effective control, as measured at or prior to the point of such release. !
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