05000366/LER-1980-158-03, /03L-0:on 801126,drywell Pneumatic Return Isolation Valve 2P70-F020 Found Leaking at 6589 Accm.Caused by Scratches on Seat of Valve Probably Due to Valve Closing on Debris.Scratches Removed.Retest Successful

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/03L-0:on 801126,drywell Pneumatic Return Isolation Valve 2P70-F020 Found Leaking at 6589 Accm.Caused by Scratches on Seat of Valve Probably Due to Valve Closing on Debris.Scratches Removed.Retest Successful
ML19340D178
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 12/19/1980
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19340D175 List:
References
LER-80-158-03L, LER-80-158-3L, NUDOCS 8012290253
Download: ML19340D178 (2)


LER-1980-158, /03L-0:on 801126,drywell Pneumatic Return Isolation Valve 2P70-F020 Found Leaking at 6589 Accm.Caused by Scratches on Seat of Valve Probably Due to Valve Closing on Debris.Scratches Removed.Retest Successful
Event date:
Report date:
3661980158R03 - NRC Website

text

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EVENT DESCRIPTION AND PROBA8LE CONSEoUENCES h 1

l o l 2 I L0n 11-25-80. with Unit 2 in refueling an LLRT by orocedure HNP-2-3952 I

lolAlIwas performed on the drywell pneumatic return isolation valve 2P70-F020.l o 4 10n 11-26-80. the LLRT coordinator reviewed the data in which the valve i

o s lwas founri to be leaking at 6589 accm.

This leakage could cause the.60 l 10161 ILa overall allowable leakage limit of Tech Specs 3.6.1.2.B.1 to be ex-1 1

10171 Lceeded.

This is a repetitive occurrence - see LER 50-366/1980-151.

I loisi IThere were no effects on public health or safety due to this event.

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ITITlIThe leakage was due to scratches on the seat of the valve which were I

li li i lorobably due to the valve closina on debris.

The valve seat was col-I lished to remove the scratches; then a successful retest was performed I

7 8 lby LLRT procedure HNP-2-3952.

The retest leakage of the drywell pneum-l latic return isolation valve 2P70-F020 was 0 accm.

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NAME OF PREPARER C-l_ COggin. SUDt. Plt. Eng_ Serv. PHONE:

LER #:

50-366/1980-158 Licensee:

Georgia Power Company Facility Name:

Edwin I.

Hatch Docket f:

50-366

Narrative

Report for LER 50-366/1980-158 On 11-25-80, with Unit 2 in the refueling mode, a local leak rate test was performed per procedure HNP-2-3952,

" Primary Containment Periodic Type B and Type C Leakage Tests", on: the drywell pneumatic return isolation valve 2P70-F020.

On 11-26-80, the LLRT coordinator reviewed the data in which the valve leakage was foun~d' to be 6589 'accm.

Good engineering practice dictates that the valve be repaired to prevent the

.60 La overall allowable leakage limit of Tech

' Specs 3.b.1.2.B.1 from being exceeded.

This is a

repetitive occurrence - see LER 50-366/1980-151.

There were no effects on public health or safety due to this event.

The leakage of the drywell pneumatic return isolation valve 2P70-F020 was due to scratches on the seat of the valve which were probably the result of the valve closing on debris.

The valve seat was polished to remove the scratches, _and the valve-was successfully retested by LLRT procedure HNP-2-3952.

The retest valve leakage was 0 accm.

--w s