ML20080L180
| ML20080L180 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 07/31/1983 |
| From: | Beck G, Hopke P, Miley G ILLINOIS, UNIV. OF, URBANA, IL |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8309300170 | |
| Download: ML20080L180 (3) | |
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ANNUAL REPORT August 1, 1982 - July 31, 1983 ILLIN0IS LOPRA REACTOR Facility License R-ll7 I.
SUMMARY
OF_ OPERATING EXPERIENCE The LOPRA was scheduled for operation a total of 85 hours9.837963e-4 days <br />0.0236 hours <br />1.405423e-4 weeks <br />3.23425e-5 months <br /> and was in actual operation a total of 49.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Usage almost doubled the amount for the previous year because of a special Nuclear Engineering course that involved operator training. The present use includes an ' Approach to Critical' experiment in which the Advanced TRIiiA is used as the source of neutrons, a control rod reactivity worth measurement experiment using 1/M relationships, and a power calibration in which the loss of reactivity is related to the power level. The ' Approach to Critical' experinent is conducted as part of a one-week training program for nuclear power plant operators. The types and percent-ages of usage for the above period was:
Operator Training (power plant personnel) 19%
Student Experiments 74%
Surveillance Requirements 7%
II. TABULATION OF OPERATION Hours Critical
- and Energy 49.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 0.0026 MW-hrs
- This includes time for loading fuel elements during the approach to critical experiments. The actual critical time was 8.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or 17% of the above time.
III. EMERGENCY SHUTDOWNS and INADVERTENT SCRAMS There was one inadvertent scram during this period. During an experiment, a student bumped the console manual scram button in the process of moving the poison control rod that controls the power level.
IV. MAINTENANCE During a check out on September 23, 1983 the pul hy supports, which allow for the movement of the LOPRA platform, were pulled loose. As a result, movement of the platform toward or away from the thermal column could not be done in the normal manner. A check was made on criticality, and the system was found to be slightly subcritical with the poison control rod completely removed.
The platform was moved to a point where the boral curtain could be slipped between the platform and the thermal column. With the curtain removed, four graphite dummy elements were then positioned in the outer row. With this 8309300170 g3o733 DR ADOCK 05000356 AO PDR
Page 2 arrangement the LOPRA could be operated as a critical assembly. The excess reactivity above criticality was 7-8 cents. Following any experiment using the LOPRA, the boral curtain is placed between the assembly and the thermal column.
! The power level is still calibrated by comparing the reactivi ty loss to the power level. However, with only 7-8 cents excess, the maximum power level is 4-5 kilowatts. Previously the reactivity loss up to 9.0 kilo-watts had been determined for the calibration.
The Nuclear Reactor Committee has recommended that the system for moving
- the platform should be repaired. The largest problem would be the removal and possible storage of the 6,000 gallons of demineralized water in the bulk l shielding facility.
V. CONDITIONS UNDER SECTION 50.59 of 10 CFR 50 l There were no changes to procedures or experiments during this period.
A change to the system was made as indicated in the previous section.
VI., VII., VIII. RADI0 ACTIVITY
, Because of the low power and infrequent use of the LOPRA, its operation does not contribute to the release of effluents. Personnel records for the laboratory are given in the Annual Report for the Advanced TRIGA Reactor, 4
License no. R-115, dated February 26, 1982 (Docket No. 50-151).
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'U in versity of Illinois at Urbana-Champaign Nuclear Engineering Program a ";;,':";!:frf"in!:'" '"' 9-23-83 Urbana, filinois 61801
- 217) 333 2295 Director Division of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Sir:
SUBJECT:
Annual Report, LOPRA Reactor License No. R-ll7 Docket No. 50-356 The following is written to comply with the requirements of Section 6.7.f. of the Technical Specifications and the conditions of I
50.59 of 10 CFR 50. The outline follows the numbered sequence of Section 6.7.f. of the Technical Specifications.
Yours truly, N
v idY /
Gerald P. Beck, Reactor Supervisor a 2 049 Philip K. Mopke', 'Chafnnan Nuclear Reactor Committee
/ b Tf NL Geptge H. Myey, Chairperson N6 clear Engineering Program l
Attachment Copy: Region III, USNRC 9
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