ML19344E575: Difference between revisions

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ATTACHMENT LER 80-27/3L-0 Millstone Unit 2 Docket No. 50-336 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During steady state power operation, a leak was evident within the containment due to the frequency of pumping the contaiment sump and a slow decrease in Safety Injection Tank (SIT) Number 1 level. A containment entry disclosed a failed socket weld on a fitting in a 1 inch recirculation line. The leak was isolated and the weld was ground out and rewelded.
ATTACHMENT LER 80-27/3L-0 Millstone Unit 2 Docket No. 50-336 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During steady state power operation, a leak was evident within the containment due to the frequency of pumping the contaiment sump and a slow decrease in Safety Injection Tank (SIT) Number 1 level. A containment entry disclosed a failed socket weld on a fitting in a 1 inch recirculation line. The leak was isolated and the weld was ground out and rewelded.
Similar events:          77-10 dated 3/21/77; 77-37 dated 9/16/77 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The cause of the leak was a crack caused by long term fatigue s
Similar events:          77-10 dated 3/21/77; 77-37 dated 9/16/77 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The cause of the leak was a crack caused by long term fatigue s
    '
attributed to vibration. The leak path was via SIT Number 1 through a leaking drain valve 2-SI-618 caused by a controller malfunction.
attributed to vibration. The leak path was via SIT Number 1 through a leaking drain valve 2-SI-618 caused by a controller malfunction.
The fuses to 2-SI-618 were pulled to fail the valve closed. The valve is a Fisher Type 667-DBQ 1 inch diaphragm control valve rated 1500 PSI. The valve controller will be repaired during the refueling outage.
The fuses to 2-SI-618 were pulled to fail the valve closed. The valve is a Fisher Type 667-DBQ 1 inch diaphragm control valve rated 1500 PSI. The valve controller will be repaired during the refueling outage.
The long tenn corrective action for the recirculation line cracking will be a stress evaluation of this line and hanger rework (if required) during the refueling outage. The piping is Schedule 40S, Type 304 Stainless Steel,' ASME Class 2.
The long tenn corrective action for the recirculation line cracking will be a stress evaluation of this line and hanger rework (if required) during the refueling outage. The piping is Schedule 40S, Type 304 Stainless Steel,' ASME Class 2.
                          . . _ _          ..
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Latest revision as of 06:28, 31 January 2020

LER 80-027/03L-0:on 800729,during Steady State Power Operation,Leak from Failed Socket Weld Found on Fitting in 1-inch Safety Injection Tank Recirculation Line.Caused by Crack Due to long-term Fatigue Attributed to Vibration
ML19344E575
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/25/1980
From: Harris J
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19344E574 List:
References
LER-80-027-03L, LER-80-27-3L, NUDOCS 8009020285
Download: ML19344E575 (2)


Text

l U. S. NUCLE AR ret.,ULATORY COMMISSION l NHC>QRf.1366%

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LICENSEE EVENT REPORT

( ,) CONTROL BLOCK: l l l l l l l 6

(PLE ASE PRINT OR TYPE ALL REQUIREO IN*ORMATIONI 1

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SF CAT 58 lg i 8 9 LICENSEE CCDE 14 15 LICENSE NuYSER CCN'T olil T,y l L @l 0 l 5 l 0 l 0 l0 l3 l3 16 }@l 0 l 7 l C l 9 l 8 l 074 l@l75 018l

, 2l 5 l 8 l 080l@

REpoR f QATE F 8 60 61 DOCKET NUM9ER tia 69 Evt1T DATE EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o l 21 l During steady state power operation, a leak was evident within the containment. A l "

lo t a l I containment entry disclosed a failed socket weld on a fitting in a 1 inch safety i I o !41 l injection tank recirculation line. The leak was isolated and the weld was ground out l l o 13 l l and rewelded. Similar events: 77-10 (3/21/77); 77-37 (9/17/77) [

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9 10 11 12 i3 18 19 20 SEQU ENTI AL OCCURRENCE REPORT REvlSION EVENTvEAR rdPCRT NO. CODE TYPE N C.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1i i o l l The cause of the leak was a crack caused by long term fatigue attributed to vibration. l ii iii i The long term corrective action for this recirculation line will be a stress I i,i2i l evaluation and hanger rework (if reauired) during the refueling outage. I I

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ATTACHMENT LER 80-27/3L-0 Millstone Unit 2 Docket No. 50-336 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During steady state power operation, a leak was evident within the containment due to the frequency of pumping the contaiment sump and a slow decrease in Safety Injection Tank (SIT) Number 1 level. A containment entry disclosed a failed socket weld on a fitting in a 1 inch recirculation line. The leak was isolated and the weld was ground out and rewelded.

Similar events: 77-10 dated 3/21/77; 77-37 dated 9/16/77 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The cause of the leak was a crack caused by long term fatigue s

attributed to vibration. The leak path was via SIT Number 1 through a leaking drain valve 2-SI-618 caused by a controller malfunction.

The fuses to 2-SI-618 were pulled to fail the valve closed. The valve is a Fisher Type 667-DBQ 1 inch diaphragm control valve rated 1500 PSI. The valve controller will be repaired during the refueling outage.

The long tenn corrective action for the recirculation line cracking will be a stress evaluation of this line and hanger rework (if required) during the refueling outage. The piping is Schedule 40S, Type 304 Stainless Steel,' ASME Class 2.

_.