ML19207C443

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Annual Operating Rept for Aug 1978-Jul 1979
ML19207C443
Person / Time
Site: 05000356
Issue date: 08/01/1979
From:
ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML19207C440 List:
References
NUDOCS 7909110630
Download: ML19207C443 (2)


Text

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ANNUAL REPORT August 1,1978 - Aug Jst 1,1979 ILLINOIS LOPRA REACTOR Facility License R-ll7 I.

SUMMARY

E OPERATING EXPERIENCE A. Usage The LOPRA was scheduled for operation a total of 63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br /> and was in actual operation a total of 29.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Scheduled operations averaged 5.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> / month and actual operation 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> / month. The LOPRA was used for training during this period. The types and percentages of usage for the scheduled time were:

Approach to Critical Experiments 51%

Operator Training 13%

Measurements 36%

B. Performance Characteristics - None C. Changes - None D. New Experiments - None II. TABULATION OF OPERATION Hours Critical

  • and Eneray Steady St..te Operation 29.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> .0043 MW-hrs
  • This includes time for loading fuel elements during the approach to critical experiment. Actual critical time would be about 30% of this value.

III. D4ERGENCY SHUTDOWNS - Ncne IV. MAINTENANCE The Poisian Control Rod and both safety rods were inspected in July.

No unusual wear or corrosion was noted. The fuel elements were also inspected .

in July and showed no excessive signs of corrosion. There were no leaking 4 elements detected. 2 V. CONDITIONS UNDER SECTION 50.59 of 10 CFR 50 There were no changes to the system or procedures durirg this period.

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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, License No. R-115, dated February 19, 1979. (Docket No. 50-151) 1 7 II ) *

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