05000321/LER-1981-024-03, /03L-0:on 810401,data Sheets from 810325 & 28 Local Leakage Rate Tests Showed Valves Leak Rate Could Exceed Tech Spec Limit.Cause of Leaking Unknown. Investigation Underway

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/03L-0:on 810401,data Sheets from 810325 & 28 Local Leakage Rate Tests Showed Valves Leak Rate Could Exceed Tech Spec Limit.Cause of Leaking Unknown. Investigation Underway
ML20003G218
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 04/21/1981
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20003G217 List:
References
LER-81-024-03L-01, LER-81-24-3L-1, NUDOCS 8104280483
Download: ML20003G218 (2)


LER-1981-024, /03L-0:on 810401,data Sheets from 810325 & 28 Local Leakage Rate Tests Showed Valves Leak Rate Could Exceed Tech Spec Limit.Cause of Leaking Unknown. Investigation Underway
Event date:
Report date:
3211981024R03 - NRC Website

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LICENSEE EVENT REPORT

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8 Gu 61 DOCKET fJU'?eEf t L3 03 EVLNT DATE 74 75 HEPOftTDATE so EVENT DESCnlPTION AND PROSABLE CONSEoUENCES h 1012110n 3-25-81 and 3-28-81. with Unit 1 shuidown for a refuelino/ torus mod-1 lification outaqe LLRTs of the nitrocen inert and ource sucoly valves T484 o a 10141 IF10 3. F307, F308, F309, F324 &the feedwater check valves B21-F010A and I

o s IF011A were performed.

On 4-1-81, a eview of the data sheets by the I

lo lc l [LLRT coordinator determined that the valves were leakino such that thev I [ol71Icould cause the.60 La limit of Tech Specs 4.7.A.2.G to be exceeded.

I 10181 Rhis is a repetitive occurrence - see LER 50-321/1981-023.

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44 47 CAUSE oESCRIPTION AND CORRECTIVE ACTIONS h 111011 The cause of the valves leaking is unknown at the oresent time; an in-I lililIvestication is underway.

The valves will be repaired and successfullv i lii2l [ retested prior to startup followino the outage.

An update recort will I

I islai Lbe submitted.

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O LER f:- 50-321/1981-024 Licensee:- Georgia Power Company Facility Name:

Edwin I. Hatch 2

Docket #:

50-521

Narrative

Report for LER 50-321/1981-024.

i On 3-25-81, with Unit i shutdown for a refueling / torus modif-

- ication outage local leakage rate tests of the nitrogen. inert and purge supply valves T48-F103, F307, F308, F309 and F324 j

were performed per HNP-1-3952 (Primary Containment Periodic Type B and Type C Leakage Tests).

On. 3-28 -81, LLRTs of the j

fcedwater check valve B21-F010A and the. manual isolation valve B21-F011A were performed per IINP-1-3952.

On 4-1-81, the LLRT coordinator reviewed the data sheets, and it was determined that the valves were leaking excess.ively. (as found:

would not pressurize) such that they would cause the

. 60 i.a overall allowable leakage limit of Tech Specs 4.7. A.2.G to be exceed-

. O ca.

This is a repetitive occurrence recer to tua s0-521/

l 1981-023.

There were no effects on public health o*r safety.

I The cause of the valves leaking is unknown at the present time; an investigation is underway.

The valves will be -

repaired and successfully retested prior to startup' following

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the outage.

An update report will be submitted.

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