ML19207B300

LER 79-043/01T-1 on 790628:radwaste Sump Discharge Piping Between Drywell Penetrations & Second Containment Isolation Valves Was Not Supported Per Seismic Class I Requirements. Caused by Design Error.Supports Redesigned & Installed

ML19207B300
Person / Time
Site:	Hatch
Issue date:	08/17/1979
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19207B296	List: ML19207B295 ML19207B300
References
LER-79-043-01T, NUDOCS 7908240362
Download: ML19207B300 (3)

Text

Update Report, Frevious kepcYt Date

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EVE'#T OE3:3 PT:ON A 0PACCA 40 E':C E S ot: I While reviewino oice suoport desicn for concrete anchor bolt surveillance purcoses, itl o i a i 1 was detemined that the rtdwaste sumo discharce pipino between the drywell penetra- I _

o Ia i i tions (X-18, X-19) and the second containment isolation '/alves (G11-F004, F020) was l' fo s I not supported per seismic Class I requirements. Thiswascontrarytothecriteriaof-l o is 1 FSAR Section 1.6.7.1. The reactor was in the refuelino mode when this deficiency was 1 -

oIi i discovered. This was not a repetitive occurrence. l Ol4 l l S Y S T ! '.' CAUSE CAu;! CO? . VALVE CO2E C002 SU?C ci CO'.tPC'J t J T C O D E SUSCODE GUBCOOE o i ?i LM I ^ !8 I B l@ I A l@ l sIJ i VI P I 01 R I T l@ l B l@ l Z l @

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Iii i The cause nf this event was desian error The Unit 1 oinina specification did not I

!i t .1 i specify this pipe as seismic Class I. After evaluatina th3 oicing sucoorts as then I i i, I presently installed, it was determined that this pioing was not adeauately supported  ;

i i: I for the postulated seismic event. The piping supports were redesigned and installed l lii: I to meet seismic Class I recuirements. (continued)  !

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• Georgia Power Company Plant E. I. Hatch Baxley, Georgia 31513 - .

Cause Description and Corrective Actions (continued) -

This design' deficiency was resolved durir: the current refueling outage, under the enncrete expansion anchor surve llance and testing program.

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flARRATIVE

SUMMARY

- (LER #50-321/1979-043)

While perforcing concrete expansion anchor surveillance evaluation for Unit 1, it wa- determined that the drywell radwaste sump discharge piping between the drywell penetrations and the second isolation valves was not supported per '

seismic Class I requiremer.ts. This was contrary to the criteria of FSAR sec-tion 1.6.7.1, and was reported under Technical Specifications 6.9.1.8.i. The reactor was in the refueling mode when this deficiency was discovered.

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The cause of this event was design error. The Unit 1 piping specification did not specify the subject pipe as seismic Class I. It was determined that the then existing piping was not adequately supported for the postulated seis-mic event. '

This piping was analyzed and supported seismically. Implementation was accom-plished during the current refueling outage ynder the concrete expansion anch-or surveillance and testing program. ,

The similar Unit 2 piping is installed as seismic Class I.

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