ML19347B026
| ML19347B026 | |
| Person / Time | |
|---|---|
| Site: | 05000072 |
| Issue date: | 09/23/1980 |
| From: | Jenson C, Turley R UTAH, UNIV. OF, SALT LAKE CITY, UT |
| To: | |
| Shared Package | |
| ML19347A874 | List: |
| References | |
| NUDOCS 8010010265 | |
| Download: ML19347B026 (3) | |
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- University of Utah TRIGA Reactor Amended Annual Operating Report July 1, 1979 to June 30, 1980 A. NARRATIVE
- 1. Operating Experience The reactor was critical for 52.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and produced 2405.6 KWH of power. The TRIGA was used in laboratory teaching, systens test, power measurements and sample irradiation. Two reactor operators were licensed to operatre the reactor.
- 2. Changes in Facility Design, etc. ;
Additional stainless steel clad fuel, received during April 1979, '
has been incorporated into the reactor core. Aluminum clad fuel still remained in the c-ring as of June 30, 1980, and the reactor safety limi+
setting was maintained at 430'C, consistent and more conservative than technical specification 2.2.b.
- 3. Surveillance Tests ,
- a. Control Rod Worth Core Configuration 6 .
Safety $2.28 Shim $2.24 Reg. $0,52
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Excess React 1vity $0,80 Shtt Down Margin with Safety Removed $1.96 l
Core Configuration 7 Safety $2.23 Shim $2.57 Reg. $0.47 Excess Reactivity $1.57 Shut Down Margin with Shim Removed $1.13 Core Configuration 8 l l
Safety $0.96 l Shim $1.31 Reg. $0.17 go/OS Excess Reactivity $0.40 Shut Down Margin with Shim Removed $0.73
U of U TRIGA Feactor Amended Annual Opert'.ing Report, 7/1/79 to 6/30/80
- b. Control Rod Inspection The biennial control rod checks were performed A 18, 1980.
The rods showed no visible deterioration or damage. prilDroptimes were all less than 0.5 seconds measured 7/31/79, 2/8/80, 4/17/80, 5/7/80.
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- c. Reactor Power Level j Power calibration with gold foil 3/11/80 at 10 KW (subsequent to NRC inspection),
- d. Fuel Inspection and Temperature Calibration All fuel in the TRIGA tank was inspected February 4,1980, with the exception of the instrumenta+. ion fuel rod which was inspected on July 2,1980. No signs of deterioration or damage was visible.
Fuel temperature circuit calibrated to less than 5*C error over the range from 0*C to 450*C, 3/11/80.
B. ENERGY OUTPUT -
The reactor was critical for 52.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and produced 2405.6 KWH of power. The total, power produced since initial criticality is 14724.03 KWH.
C. INADVERTANT SCRAMS ,
There were 8 inadvertant scrams Number Tyge Cause 6 Hi-log Signal spikes from various extraneous sources )
including calibration switch. '
Action: Restart after scram.
2 Linear Operator not switching linear range switch Recorder correctly.
Action: Instructed operator in good switching practice.
D. MAJOR MAINTENANCE A new log recorder has been installed out the period meter pot was not a ttached.
E. CHANGES PURSUANT TO 50-59 The period instrunentation was driven by a pot mechanically connected to l the log recorder. The loads placed on the recorder drive motors by the pot l caused frequent and prolonged time intervals when the recorder could not be l made to function. Although the period circuit was included as instrumentation l l
i g .- l l'
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' U of U TRIGA Reactor Amended Annual Operating Report, 7/1/79 to 6/30/80 l in the SAR, it serves no function other than as a possible source of informa- I tion to the operator. The period meter performs no scram function and no limitations upon the period are given in the technical specifications. Further, the fuel is capable of large transients without damage; i.e., pulsing, but this reactor is incapable of pulsing and the fastest period of a few seconds is governed by the ability of the operator to switch linear ranges before a ,
scram occurs at full scale on any range. The maximum power range operable is J 100 KW. In the worst case, scrams would occur at 100 KW,115% power and 150 KW !
for the linear, percent, and log power system.
F. RADI0 ACTIVE EFFLUENTS
- 1. Liquid Waste - The water demineralizer was recharged 3/31/80. Measure-ments and calculations give the release as 6,6x10-4 pC1/ml of Co60 which is less than lx10-3 pCi/ml from Table I, column 2 per 10CFR20.303. This was further dil 60 gallons of water to a concentration of 5x10 gted* by before discharge to the sewer system. This Co 60 "is present from the original fuel being transported in a dirty cask; it is not due to damaged fuel.
- 2. Gaseous Waste - Negligible The TRIGA has run for 2405,6 KWH at powers to 90 KW. At this level AR4I production is negggible. Our stack monitor will detect 33% of 10CFR20 Table I for AR and we have seen nothing in the monitor.
- 3. Solid Waste - None i G. RADIATION EXPOSURES One staff member received 321 crem radiation exposure, 234 mrem of which occurred during fuel transfer from the storage pits to the reactor tank. No other staff member received over 100 mrem /yr and no visitor recieved a measurable does. Monthly surveys have identified no contamination.
H. ENVIRONMENTAL SURVEY Environmental surveys have been taken continuously since construction of the reactor and the latest reports in June and August of 1979 and June 1980 have identified no measurable increase in radiation.
prepared by J g,* Approved by~
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