ML20215E256
| ML20215E256 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 08/02/1976 |
| From: | Prussin S CALIFORNIA, UNIV. OF, BERKELEY, CA |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215E220 | List:
|
| References | |
| FOIA-86-811 8246, NUDOCS 8612190043 | |
| Download: ML20215E256 (3) | |
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~JNIVERSITY OF CALIFORNIA, BERKELEY BERKELEY
- DAVIS
- IRVINE
- LOS ANGELES
- RIVERSIDE
- SAN DIECO
- SAN FRANCISCO SANTA BARBARA
- SANTA CRUZ COLLECE OF ENGINEERINC BEREELEY, CALIFORNIA 94720
~~ DEPARTMENT OF NUCLEAR ENGINEERLNC yJ:
August 2, 1976 9 Q,
Docket No. 50-224 e
/
Director D
Division of Operating Reactors 6'g
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Office of Nuclear Reactor Regulations
_.i U.S. Nuclear Regulatory Commission i[
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h Washington D.C. 20555 s
Dear Sir:
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On July 9th, 1976, a letter was sent to your office
/
reporti an unusual occurrence on the Berkeley Research O'
6,Y Reactor Linear power channel during a routine power calibra-tion.
It was reported then, that non-linearity occurred in the linear power channel output with respect to rise in pool temperature during the early part of measurements, especially near the 1 MW region.
It was also reported that because of this nonlinear occurrence, we might have operated exceeding our license of 1 MW thermal limit.
Since then, extensive measurements and testing have been made.
Results show that nonlinearity during power calibration occurred during the first 30 minutes of the measurements only.
The cause was determined to be a thermal transient rather than an electronic or ion chamber malfunc-tion.
It was also established that after the first 30 minutes of measurements a steady-state condition was reached and that the linear channel responded quite linearly with respect to rise in temperature up to pool temperature of 30*C.
Attached is a graph of one of the measurements per-formed on the 15th of July at a power level of 900 kW as calibration setting was m.aintained at 6.44 x 10-gorder current indicated on the linear recorder.
The linear re Amp /kW indicated on the recorder.
As one can see from the graph, during the first 20 minutes of operation, a thermal transient occurred and the average rise in temperature was approximately 9'C/ hour -
900 kW indicated on the linear recorder.
Extrapolation of this number gave a power coefficient of 10'C/ hour - 1 MW indica:ed.
After the first 30 minutes, a steady state was reached and an average power coefficient of 6.6*C/ hour -
900 kW or 7.37'C/ hour - 1 MW indicated was recorded.
8612190043 861216 501(5
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i August 2, 1976 On the reported reactor operation on July 6,,
a similar calibration pattern was obtained.
It was reported that during the first 20 minutes of operation a temperature rise of 3.4*C was noticed; this corres-ponded to 10.2*C/ hour.
The reactor was then scrammed after 26 minutes of operation.
This number is approxi-mately.2% higher than the one obtained during the test on July 15.
Analysis and comparison of transient and steady state data collected during the 3 weeks of testing concluded that, within 5% accuracy specified by Genenal Atomic, during the 26 minute reactor operations on July 6, 1976, we did not exceed our licensed 1 MW thermal limit.
In order to stay on the conservative side of safety, the linear power channel calibration current is now set to 6.35 x 10-7 Amp /kW indicated.
This setting will correspond to thermal power output of 986 kW as per 1 MW indicated'on the linear recorder.
Very truly yours,
.% G.Pwk Stanley G. Prussin Reactor Administrator SGPsirs Enc.
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