ML040920398

Purdue University Reactor - 1 Report on Reactor Operations

ML040920398
Person / Time
Site:	Purdue University
Issue date:	03/31/2004
From:	Merritt E Purdue University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML040920398 (6)

Text

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REPORT ON REACTOR OPERATIONS For the Period January 1, 2003 to December 31, 2003 PURDUE UNIVERSITY REACTOR-1 (PUR-1)

Facility Docket No. 50-182 PURDUE UNIVERSITY West Lafayette, Indiana 47907 March 2004 Prepared by E. C. Merritt Reactor Supervisor

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, 2003 to December 31, 2003.

During the reporting period of 2003 a total of 632 people visited the reactor facility. Those people included 141 different groups, of which 75 groups were for the purpose of maintenance or surveillance testing, 21 groups were for class purposes, 31 groups were tours, and 14 groups were participants in our reactor sharing program.

2. PLANT DESIGN AND OPERATIONAL CHANGES 2.1 Facility Design Changes There were no design changes to the facility in 2003.

2.2 Performance Characteristics The operation of the PUR-1 facility continued satisfactorily during the reporting period. During the visual inspection 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 performance of the fuel continued during the year.

2.3 Changes in Operating Procedures Concerning Safety of Facility Operations The oversight committee approved a new emergency procedure in March.

2.4 Results of Surveillance Tests and Inspections 2.4.1 Reactivity Limits The reactivity worths of the control rods were determined to be as follows:

Shim-safety #1 - 4.52%

Shim-safety #2 - 2.51 %

Regulating Rod - 0.26%

These values are consistent with previous reported values. The worth curves of the control rods were checked after the inspection and the excess was determined to be 0.44%. The shutdown margin was determined to be 2.07%

based on these values.

The inspection of the control rods was completed on August 19, 2003 with no evidence of change or deterioration observed.

No experiment was placed in the reactor pool during the year that would require the determination of its reactivity during the initial criticality following its installation.

2.4.2 Reactor Safety Systems Each pre-startup check included a channel test for each safety system, provided the shutdown exceeded 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during operation.

On January 7, 2004, the required 2003 electronic calibration of all safety channels was completed.

The required 2003 irradiation of gold foils for a power calibration was done on January 27, 2004. The calibration indicated that the actual power was below (i.e., conservative) the indicated power level (i.e. the actual power being 576 watts when the indicated power level was at 750 watts). These last two did not exceed the 'annual not to exceed 15 months' allowed in the Technical Specifications.

During the pre-startup, which precedes each run, the radiation area monitors and the continuous air monitor were checked for normal operation. During 2003, the calibration of the radiation area monitors was completed on April 9 and September 26 and the continuous air monitor was completed on January 27 and September 20.

Following the control rod inspections, the rod drop times were measured on August 19, 2003. The rod drop times fell between 525 and 633 milliseconds.

These values are consistent with past measurements and are well within the specification limit of one second.

2.4.3 Primarv Coolant System The weekly measurements of the pH of the primary coolant consistently gave readings between 4.9 and 5.6 during 2003. These values are within the specification limits of 5.5 4 1.0. During the weekly checks and the pre-startup check, which precedes each run, the conductivity of the primary coolant was measured and the values never exceeded 2.1 micromhos-cm. This represents a resistivity of more than 476,000 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 pre-startup checklist that was completed prior to each reactor run.

Monthly samples of the primary coolant were collected and analyzed by personnel from Radiological and Environmental Management for gross alpha and beta activity. No activity was identified in the samples, which would indicate failure of the fuel plates.

2.4.4 Containment Readings between 0.07 and 0.19 inches of water were recorded weekly for the negative pressure in the reactor room.

The semi-annual checks made in 2003 for the proper operation of the inlet and outlet dampers and the air conditioner were completed on June 12, and December 22. All worked satisfactorily.

Selected fuel plates were visually inspected on August 19, 2003. 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, 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.

No samples of unknown composition or that required double encapsulation were submitted for irradiation.

2.5 Changes. Tests and Experiments Requiring Commission Authorization During 2003 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 The laboratory director Dr. Robert Bean left the University during 2003. Dr. Sean McDeavitt is now the laboratory director. Otherwise, there were no changes in the Facility Staff during the year. There is currently only one licensed operator, the reactor supervisor, at the facility.

3. POWER GENERATION

Operation of the PUR-1 during 2003 consisted of 42 runs, which generated 178,104 watt-minutes of energy and covered an integrated running time of 93.2 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 2003. It occurred on May 1, 2003. The root cause was operator error (i.e. range change on Channel 3).

5. MAINTENANCE There were five instances of non-routine maintenance during the reporting period. One had to do with water leaking in the process system piping. The others were either cleaning (a connector was creating noise from dust across high voltage surfaces) or standard parts replacement. All could be expected with our instrumentation.

6. CHANGES. 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 effluent was released to the environs beyond our effective control, as measured at or prior to the point of such release.

8. OCCUPATIONAL PERSONNEL RADIATION EXPOSURE No radiation exposures greater than 25% of the appropriate limits of 10 CFR 20 were received during the reporting period.