05000366/LER-1981-016-03, /03L-0:on 810305,steam Flow Indicator for Main Steamline a Did Not Show Flow in Line While Increasing Reactor Power.Caused by Valve Stem Separated from Inner Disc of Valve.Valve Stem,Inner & Main Discs & Cylinder Replaced

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/03L-0:on 810305,steam Flow Indicator for Main Steamline a Did Not Show Flow in Line While Increasing Reactor Power.Caused by Valve Stem Separated from Inner Disc of Valve.Valve Stem,Inner & Main Discs & Cylinder Replaced
ML20003E428
Person / Time
Site: Hatch 
Issue date: 03/27/1981
From: Nix R
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20003E426 List:
References
LER-81-016-03L-01, LER-81-16-3L-1, NUDOCS 8104030448
Download: ML20003E428 (2)


LER-1981-016, /03L-0:on 810305,steam Flow Indicator for Main Steamline a Did Not Show Flow in Line While Increasing Reactor Power.Caused by Valve Stem Separated from Inner Disc of Valve.Valve Stem,Inner & Main Discs & Cylinder Replaced
Event date:
Report date:
3661981016R03 - NRC Website

text

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tvtNT DATE 14 15 P[FJt T DAT E BJ EVENT DESCRIPTION AND PROBABLE CONSECUENCES h I o 12 ] l On llarch 5,1931, while increasinq reactor power, the Steam Flow Incica+w I

[o i3 i l for the "A' flain Steamline was not indicating a flow in the line. When j

10141 I an attempt was made to' close the Inboard Isolation Valve on the "A"

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disc cylinder and main disc were replaced and the valve reassembled.

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The Main Steam Isolation Valve Trip Test was then performed and the l

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s-LER No.: 50-366/1981-016 Licensee: Georgia Power Company Facility: Edwin I. Hatch Docket No.: 50-366

Narrative

Report for LER 50-366/1981-016.

On thrch 5, 1981, with the reactor in the run mode at 55% Mut, there was no flow in the "A" Main Steamline as evidenced by the Steam flow Indicator. When an attempt was made to slow close the Inboard Main Steam Isolation Valve on the "A" Steamline, to check for an increase in the other steamline flows, the valve did

...t give a full closed indication.

As the Inboard Isolation Valve was incapable of meeting the requirements of Tech Specs Table 3.6.3-1, the Outboard Isolation Valve was closed per Tech Specs 3.6.3 Action A.2.

This was not a repetitive event.

~When the valve.as disassembled, after the reactor was shutdown for other activi tie, it was discovered that the valve stem had separated from the inner disc of the valve.

Although the valve did not receive a closed indication it was closed, as the valve disc closes in the direction of the flow.

The valve stem then hit against the top of the disc preventing the stem from traveling enough to actuate the limit switches for a full closed indication.

The. valve stem, inner disc, disc cylinder and main disc were replaced and the valve reassembled.

A leak rate -test was then performed and no leakage was found. The Main Steam ~ Line Isolation Valve Trip Test was performed satisfactorily and the valve returned to service on March 14, 1981.

The Steam Flow Indicators were checked on'.the other three steam lines to insure that this was a singular incident.

Isolation Valves for Unit I and Unit II are manufactured by different companies. Unit II valves are manufactured by -Rockwell and Unit I valves are manufactured by Atwood and Morrill...

Neither public health' and safety nor safe plant, 6

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