05000366/LER-1980-075-03, /03L-0:on 800428 Core Max Fraction of Limiting Power Density in Excess of Tech Specs.Corrective Action Failed to Lower Power Density.Caused by Lower than Equilibrium Xenon Distribution During Startup

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/03L-0:on 800428 Core Max Fraction of Limiting Power Density in Excess of Tech Specs.Corrective Action Failed to Lower Power Density.Caused by Lower than Equilibrium Xenon Distribution During Startup
ML19323F175
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/15/1980
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19323F170 List:
References
LER-80-075-03L, LER-80-75-3L, NUDOCS 8005280616
Download: ML19323F175 (2)


LER-1980-075, /03L-0:on 800428 Core Max Fraction of Limiting Power Density in Excess of Tech Specs.Corrective Action Failed to Lower Power Density.Caused by Lower than Equilibrium Xenon Distribution During Startup
Event date:
Report date:
3661980075R03 - NRC Website

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NRC FORM 364 U. S. NUCLEAR REGULAT ORY COMMISSION 87 77)

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60 61 DOCKET NUMSER 6d 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRin TION AND PROB ADLE CONSEQUENCES h IAt approximately 62% of rated core thermal power during reactor startup.I o 2 g o i3 lthe CMFLPD was calculated to be 70.3%.

Corrective action was taken but I g o i. ldid not lower the CMFLPD to allow adjustment of APRMs per Tech Specs l

i o i s j [ 3. 2. 2.

Preparations were made to reduce reactor power to less than or i

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lequal to 25% within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but the problem was corrected bef-l l.o.11] I ore a ny significant' reduction.

There were no effects on public health l

see LER 50-366/1980-010.

t ioisi l and sa fety. This is a repetitive event

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3J J4 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h liioi IThe high CMFLPD was due to lower than equilibrium xenon distribution l

lduring startup.

The initial corrective action failed because of inef-l i i lfective control rod adjustments.

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Licensee:

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Narrative

Report for LER 50-366/1980-075 At approximately 2300 CST on 4-27-80, the shift nuclear engineer completed an LPRM-Process Computer calibration (00-1) and requested a "P-1" calculation.

The PI indicated that the core maximu'n fraction of limiting power density (C'4FLPD) was 70.3% relative to the fraction of. rated core thermal power (FRCTP) of 62%.

The engineer began taking corrective action within the prescribed 15 minutes to allev.iate the c'tFLoD problen, but after control rod pattern adjustments at the end of the 2-hour limit the CMFL30 sa s still too high to a 1 1. o w adjustment of the APRwc as required by Tech Specs sect ion 3.2.2.

preparations were made to have the reactor below 25%

of core rated thermal power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

During this 4-hour period, the CMFLPD was lowered by another control rod pattern adjustment and APRMs adjusted, and normal reactor startup was centinued.

To avoid these type occurrences in the future personnel involved have been informed of more effective c o r r e c ':i v e actions to take in similar situat ions.

This type event has occurred before and was reparted under LER 50-366/1980-010.

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