05000348/LER-1980-020-03, /03L-0:on 800303,inaccurate Pressure Signal Noted from PT-494,1C S/G Pressure Transmitter.Caused by Frozen Sensing Line Due to Abnormally Cold Weather & Insufficient Protection.Sensing Line Thawed & Channel Check Performed

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/03L-0:on 800303,inaccurate Pressure Signal Noted from PT-494,1C S/G Pressure Transmitter.Caused by Frozen Sensing Line Due to Abnormally Cold Weather & Insufficient Protection.Sensing Line Thawed & Channel Check Performed
ML19309C399
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 04/02/1980
From: Hairston W
ALABAMA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19309C388 List:
References
LER-80-020-03L, LER-80-20-3L, NUDOCS 8004080554
Download: ML19309C399 (1)


LER-1980-020, /03L-0:on 800303,inaccurate Pressure Signal Noted from PT-494,1C S/G Pressure Transmitter.Caused by Frozen Sensing Line Due to Abnormally Cold Weather & Insufficient Protection.Sensing Line Thawed & Channel Check Performed
Event date:
Report date:
3481980020R03 - NRC Website

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. NIC FORM 366 U.S. NUCLEAR REGULATORY COMMl1SION (7 77).

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60 61 DOCKET NuC's 68 69 EVENT oATE 14 iS REPORT DATE 80 EVENT DESCRIPTION AND PROBADLE CONSEQUENCES h lAt 0630 on 3/3/80 an inaccurate pressure signal was noted from PT-494, 1C S/G l

o 2 Iolal_! pressure transmitter. As a result PT-494 was declared inoperabic. T/S 3.3.2 l

l o I 4 l l requires, in part, that the pressure channels for the steam generator be operable.

l I o I s l IT/S 3. 3.2 action statements were met.

The health and safety of the public were not o o laffected.

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The frozen sensing line was thawnd out and a channel check performed to I

linsure operability. Temporary heating measurt.1 were placed in the Main Steam and l

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1ii1I IValve Room.

The 1C S/G pressure channel was retu aed to service at 0905 on 3/3/80.

l lt la i IThe sensing line froze due to abnormally cold weather and insufficient freeze protec-l 2

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LER 80-020/03L-0 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (Continued) on a portion of the line in the Main Steam and Valve Room. A design review of this occurrence has been requested, included in this review will be a re-evaluation of our response to IEB 79-24.

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